ML17172A711
| ML17172A711 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/21/2017 |
| From: | Virginia Electric & Power Co (VEPCO) |
| To: | NRC/RGN-II |
| References | |
| Download: ML17172A711 (185) | |
Text
Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Both emergency busses are de-energized Attempts to re-energize either emergency bus have failed Another operator was assigned to perform the Turbine Building attachment of 2-ECA-0.0 INITIATING CUE You have been requested to perform the "Turbine Building Operations" attachment of 2-ECA-0.0.
2016 NRC EXAM IN PLANT I Page: 2 of 9 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM N1578 TASK Perform local actions in the turbine building in response to a loss of all AC power (2-ECA-0.0, SOER-99-1).
TASK STANDARDS Hydrogen was vented from the main generator, the condenser vacuum breaker was opened, nitrogen was isolated to the LP turbines, and the hotwell makeup valves were isolated K/A
REFERENCE:
05EA1.04 (3.5/3.9)
ALTERNATE PATH:
N/A TASK COMPLETION TIMES Validation Time =
10 minutes Start Time = _______
Actual Time = _______ minutes Stop Time = _______
PERFORMANCE EVALUATION Rating
[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date EVALUATOR'S COMMENTS
2016 NRC EXAM IN PLANT I Page: 3 of 9
2016 NRC EXAM IN PLANT I Page: 4 of 9 Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)
OPERATOR PROGRAM N1578 READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
PREREQUISITES Before being evaluated on the task, the trainee must have completed the reactor operator's course checkout during which the objectives listed below would have been addressed.
INITIAL CONDITIONS Both emergency busses are de-energized Attempts to re-energize either emergency bus have failed Another operator was assigned to perform the Turbine Building attachment of 1-ECA-0.0 INITIATING CUE
2016 NRC EXAM IN PLANT I Page: 5 of 9 You have been requested to perform the "Turbine Building Operations" attachment of 2-ECA-0.0.
EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))
Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))
TOOLS AND EQUIPMENT None PERFORMANCE STEPS START TIME 1
Open 2-GM-8 to vent hydrogen from the main generator.
Procedure Step 1 CRITICAL STEP SAT [ ] UNSAT [ ]
Standard 2-GM-8 is simulated to be turned in the counter-clockwise direction until it is full open Simulation Cue(s) The valve handwheel has stopped turning Notes/Comments
2016 NRC EXAM IN PLANT I Page: 6 of 9 2
Open 2-AS-MOV-200 to break vacuum on the condenser.
Procedure Step 2 CRITICAL STEP SAT [ ] UNSAT [ ]
Standard 2-AS-MOV-200 is simulated to be turned in the counter-clockwise direction until it is full open Simulation Cue(s) The MOV handwheel has stopped turning and the stem is showing full open Notes/Comments 3
Close 2-GN-203 to isolate nitrogen injection to the low-pressure turbine exhaust.
Procedure Step 3 SAT [ ] UNSAT [ ]
Standard 2-GN-203 is verified closed by simulating turning in the clockwise direction and checking stem position is down Simulation Cue(s) You are unable to turn the handwheel in the clockwise direction and the stem position is as you see it.
Notes/Comments
2016 NRC EXAM IN PLANT I Page: 7 of 9 4
Isolate Hotwell Makeup valves by closing the following:
- 2-CN-151, Inlet to Makeup Valve 2-CN-LCV-209-1 Isol Valve
- 2-CN-148, Inlet to 2-CN-LCV-209-2 Isol Valve
- 2-CN-150, 2-CN-LCV-209-2 Bypass Valve
- 2-CN-143, 2-CN-LCV-208 Bypass Valve Procedure Step 4 & 5 SAT [ ] UNSAT [ ]
Standard Each valve is closed or verified closed by simulating turning the handwheel in the clockwise direction and checking that the stem is fully in the down position.
Simulation Cue(s) 2-CN-151 - The valve handwheel has stopped turning and the stem is fully in the down position.
2-CN-148 - The valve handwheel has stopped turning and the stem is fully in the down position.
2-CN-150 - You are unable to turn the handwheel in the clockwise direction and the stem position is as you see it.
2-CN-143 - You are unable to turn the handwheel in the clockwise direction and the stem position is as you see it.
Notes/Comments 5
Close 2-CN-141, Inlet To Hotwell High Level Divert Isol Valve Procedure Step 6 SAT [ ] UNSAT [ ]
Standard 2-CN-141 is verified closed by simulating turning in the clockwise direction and checking stem position is down Simulation Cue(s) You are unable to turn the handwheel in the clockwise direction and the stem position is as you see it.
Notes/Comments
2016 NRC EXAM IN PLANT I Page: 8 of 9 6
Initiate purge of the main generator using CO2 Procedure Step 7 SAT [ ] UNSAT [ ]
Simulation Cue(s) Assume that another operator has initiated purging the generator Notes/Comments 7
Inform the control room operator that all local turbine building operations are complete.
Procedure Step _____
SAT [ ] UNSAT [ ]
Simulation Cue(s) The control has been notified Notes/Comments
>>>>> END OF EVALUATION <<<<<
STOP TIME
2016 NRC EXAM IN PLANT I Page: 9 of 9 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)
1 of 1 NUMBER 2-ECA-0.0 ATTACHMENT TITLE TURBINE BUILDING OPERATIONS ATTACHMENT 3
REVISION 28 PAGE CAUTION: Venting Hydrogen and breaking Condenser vacuum MUST be completed expeditiously to ensure successful completion of DC Bus Load Shed.
NOTE: If ECA-0.0 is in effect on BOTH Units and only one operator is available to perform the Turbine Building Operations Attachments on both units, then Steps 1 and 2 are the priority steps and should be performed on each Unit before performance of remaining Steps.
- 1. ___ Open 2-GM-8, Main Generator Hydrogen Vent Valve (located on the Turbine Building Mezzanine at the west end of the Condenser), to vent hydrogen from the Generator.
- 2. ___ Open 2-AS-MOV-200, 1B Condenser Vacuum Breaker (located on the Turbine Building Mezzanine at the west end of the Condenser), to break vacuum on the Condenser.
- 3. ___ Close 2-GN-203, Nitrogen Injection To LP Turbine Exhaust Isol Vv, (located in Unit 2 Turbine doghouse, southwest corner).
4.
Isolate Hotwell Makeup valves by closing the following (located in the east end of the Turbine Building basement):
2-CN-151, Inlet to Makeup Valve 2-CN-LCV-209-1 Isol Valve 2-CN-148, Inlet to 2-CN-LCV-209-2 Isol Valve 2-CN-150, 2-CN-LCV-209-2 Bypass Valve
- 5. ___ Close 2-CN-143, 2-CN-LCV-208 Bypass Valve (Located In The Turbine Building Basement at the Southwest Corner Of The Condenser).
- 6. ___ Close 2-CN-141, Inlet To Hotwell High Level Divert Isol Valve (located in the Turbine Building basement at the southwest corner of the Condenser).
- 7. ___ Initiate 2-OP-43.1, Operation of the Generator Gas Systems, section for purging hydrogen from the Generator using CO2, while continuing with this procedure.
- 8. ___ Notify the Control Room that ATTACHMENT 3 is complete.
Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit startup is in progress Components are being returned to service following maintenance INITIATING CUE You are requested to place the initial rod drive MG set in service and parallel the second MG with the running MG set in accordance with 1-OP-58.1.
2016 NRC EXAM IN PLANT J Page: 2 of 16 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Place both rod control motor generator set in operation with both rod control motor generator sets shut down (1-OP-58.1).
TASK STANDARDS Task was performed as directed by the procedure referenced in the task statement within parentheses (one of the underlined procedures if several are cited)
K/A
REFERENCE:
001A4.08 (3.7/3.4)
ALTERNATE PATH:
N/A TASK COMPLETION TIMES Validation Time =
20 minutes Start Time = _______
Actual Time = _______ minutes Stop Time = _______
PERFORMANCE EVALUATION Rating
[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date EVALUATOR'S COMMENTS
2016 NRC EXAM IN PLANT J Page: 3 of 16
2016 NRC EXAM IN PLANT J Page: 4 of 16 Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)
OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
PREREQUISITES Before being evaluated on the task, the trainee must have completed the reactor operator's course checkout during which the objectives listed below would have been addressed.
INITIAL CONDITIONS Unit startup is in progress Components are being returned to service following maintenance
2016 NRC EXAM IN PLANT J Page: 5 of 16 INITIATING CUE You are requested to place the initial rod drive MG set in service and parallel the second MG with the running MG set in accordance with 1-OP-58.1.
EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))
Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))
TOOLS AND EQUIPMENT None PERFORMANCE STEPS START TIME 1
Check initial conditions and review precautions and limitations Procedure Step 5.1.1 & 5.1.2 SAT [ ] UNSAT [ ]
Standards Initial conditions are checked and precautions and limitations are reviewed Notes/Comments
2016 NRC EXAM IN PLANT J Page: 6 of 16 2
Ensure all reactor trip breakers and reactor trip bypass breakers are open.
Procedure Step 5.1.3 SAT [ ] UNSAT [ ]
Standards The position is checked on all four breakers Simulation Cue(s) A green OPEN flag is indicating an all of the breakers Notes/Comments 3
Check that both motor generator set output breakers are racked to CONNECT.
Procedure Step 5.1.4 SAT [ ] UNSAT [ ]
Standards Output breakers are verified in the connect position Simulation Cue(s) 1-ED-BKR-01A1 and 01B1 are racked to CONNECT Notes/Comments
2016 NRC EXAM IN PLANT J Page: 7 of 16 4
Align all switches and devices on the applicable motor generator set control panel.
Procedure Step 5.1.5 SAT [ ] UNSAT [ ]
Simulation Cue(s) Inform the trainee that each switch or device is in the position specified by the procedure as he checks them:
The Generator No. 1 Voltage Adjust potentiometer is set to the mid range position.
The Generator No. 2 Voltage Adjust potentiometer is set to the mid range position.
The Generator No. 1 Synchronize switch, is OFF.
The Generator No. 2 Synchronize switch, is OFF.
The Generator No. 1 Ammeter switch is in position A.
The Generator No. 2 Ammeter switch is in position A.
The Generator No. 1 Voltmeter switch is in position A-B.
The Generator No. 2 Voltmeter switch is in position A-B.
The 1KS grounding switch is in the OPEN position.(This switch is inside the cabinet, DO NOT allow the cabinet to be opened)
Notes/Comments: The 1KS grounding switch is inside the cabinet. DO NOT allow the operator to open the cabinet.
5 Check that each MG set output and supply breaker lights and control switch indications are green.
Procedure Step 5.1.6.a - d SAT [ ] UNSAT [ ]
Standards Output and supply breaker lights and control switch indications are checked to be GREEN Simulation Cue(s) All breaker lights and control switch indications are green Notes/Comments
2016 NRC EXAM IN PLANT J Page: 8 of 16 6
Check the applicable relays for red flags.
Procedure Step 5.1.6.e SAT [ ] UNSAT [ ]
Standards Relay flags are checked Simulation Cue(s) None of the relays listed in the procedure show red flags (No RED flags should be showing)
Notes/Comments 7
Close the motor input circuit breaker for the motor generator set to be started.
Procedure Step 5.1.7 SAT [ ] UNSAT [ ]
Standards MG set supply breaker is closed Simulation Cue(s) There is audible indication that the MG set is accelerating Notes/Comments
2016 NRC EXAM IN PLANT J Page: 9 of 16 8
Flash the field for the generator, and adjust the generator's voltage, as required.
Procedure Step 5.1.8 SAT [ ] UNSAT [ ]
Standards GEN FIELD FLASH button is depressed and voltage is adjusted to normal Simulation Cue(s) Voltage increased and stabilized at approximately 235 volts Simulation Cue(s) After adjustment, inform the trainee that voltage now reads 260 volts Notes/Comments 9
Close the generator output circuit breaker for the motor generator being placed in service.
Procedure Step 5.1.9 Critical Step SAT [ ] UNSAT [ ]
Standards 1-ED-MG-1A or 1B is closed Simulation Cue(s) The output breaker RED light is lit Notes/Comments
2016 NRC EXAM IN PLANT J Page: 10 of 16 10 If MG set voltage is not at 260 volts, then adjust the voltage adjust potentiometer to 260 volts.
Procedure Step 5.1.10 SAT [ ] UNSAT [ ]
Standards Voltage is adjusted to approximately 260 volts Simulation Cue(s) Voltage is approximately 260 volts Notes/Comments: The following steps are for paralleling the second MG set IAW section 5.2 of the procedure.
11 Check initial conditions and review precautions and limitations Procedure Step 5.2.1 & 5.2.2 SAT [ ] UNSAT [ ]
Standards Initial conditions are checked and precautions and limitations are reviewed (Previously reviewed in section 5.1 of the procedure)
Notes/Comments:
2016 NRC EXAM IN PLANT J Page: 11 of 16 12 Ensure that the voltage potentiometer is in mid-position and the synchronize switch is OFF.
Procedure Step 5.2.3.a & b SAT [ ] UNSAT [ ]
Standards Voltage potentiometer is verified in mid-position and the synchronize switch is verified OFF Simulation Cue(s) Switches are in the desired position Notes/Comments 13 Reset relay flags or motor generator set breakers, if required.
Procedure Step 5.2.3.c SAT [ ] UNSAT [ ]
Standards Relay flags are checked Simulation Cue(s) No relays have RED flags Notes/Comments
2016 NRC EXAM IN PLANT J Page: 12 of 16 14 Close the motor input circuit breaker for the motor generator set to be started.
Procedure Step 5.2.4 SAT [ ] UNSAT [ ]
Standards MG set supply breaker is closed Simulation Cue(s) There is audible indication that the MG set is accelerating Notes/Comments 15 Flash the field for the generator, and adjust the generator's voltage, as required.
Procedure Step 5.2.5 SAT [ ] UNSAT [ ]
Standards GEN FIELD FLASH button is depressed and voltage is adjusted to normal Simulation Cue(s) Voltage increased and stabilized at approximately 235 volts Notes/Comments
2016 NRC EXAM IN PLANT J Page: 13 of 16 16 Adjust the voltage potentiometer as required, to match the running voltage.
Procedure Step 5.2.5.e SAT [ ] UNSAT [ ]
Standards Voltage is adjusted to approximately +/- 5 volts of running voltage Simulation Cue(s) After adjustment, inform the trainee that voltage now reads +/- 5 volts of running voltage Notes/Comments 17 Turn the synchronize switch to the ON position, and verify that the applicable motor generator set's generator output breaker closes.
Procedure Step 5.2.5.f Critical Step SAT [ ] UNSAT [ ]
Standards Synchronize switch is placed in ON Simulation Cue(s) Inform the trainee that the MG set output breaker has closed Notes/Comments
2016 NRC EXAM IN PLANT J Page: 14 of 16 18 Turn the synchronize switch to the OFF position.
Procedure Step5.2.5.h SAT [ ] UNSAT [ ]
Standards Synchronize switch is placed in OFF Notes/Comments 19 Verify voltage indicates approximately the same on each MG set. If not, then notify system engineering.
Procedure Step 5.2.5.i SAT [ ] UNSAT [ ]
Standards Voltage is checked the same on both MG sets Simulation Cue(s) Voltage indicates approximately the same on each MG set Notes/Comments 20 Red-flag the motor generator set's generator output circuit breaker. Procedure Step 5.2.5.j SAT [ ] UNSAT [ ]
Standards MG set output breaker control switch is placed in CLOSE Notes/Comments
>>>>> END OF EVALUATION <<<<<
2016 NRC EXAM IN PLANT J Page: 15 of 16 STOP TIME
2016 NRC EXAM IN PLANT J Page: 16 of 16 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)
DOMINION 1-OP-58.1 North Anna Power Station Revision 25 Page 4 of 24 2.4 Commitment Documents 2.4.1 CTS 02-92-2260-113, Surveillance Review for (old) TS 4.3.1.1.1, Table 4.3-1 2.4.2 CA213828; CR444735: NANN - U-1 Rod Drive MG B Output Breaker Tripped Open on Attempt to Close per 1-OP-58.1 Init Verif 3.0 INITIAL CONDITIONS 3.1 AMSAC has been reset.
3.2 The following MG Set Power Supply Breakers for the MG Set to be started, are in CONNECT:
- 1-EP-BKR-14B1-4, 1-ED-MG-1A Rod Drive M-G Set Motor Supply Breaker
- 1-EP-BKR-14C2-12, 1-ED-MG-1B Rod Drive M-G Set Motor Supply Breaker 3.3 IF paralleling a Shutdown MG Set to an Operating MG Set, THEN the Reactor Trip Breakers are closed.
3.4 A Synchronizing Switch key is available if starting a MG Set, located in the light bulb cabinet in the MCR.
4.0 PRECAUTIONS AND LIMITATIONS 4.1 IF the MG Sets are unloaded, such as after a Reactor Trip or Shutdown, THEN DO NOT run the sets paralleled for an extended period.
4.2 The Rod Control MG Sets supply power to the Control Rods. Disruption of this power while the Unit is operating will result in a Reactor Trip.
DOMINION 1-OP-58.1 North Anna Power Station Revision 25 Page 5 of 24 4.3 The following Reactor Trip System Instrumentation listed in Tech Spec 3.3.1, Table 3.3.1-1 MUST be operable before the Control Rods are capable of withdrawal: (Reference 2.4.1)
- Source Range
- Intermediate Range
- Reactor Trip Breakers
- Bypass Trip Breakers
- Automatic Trip Logic 4.4 WHEN placing the first MG Set in operation, THEN the MG Set Output breaker can NOT be closed unless the Output Breakers for BOTH MG Sets are racked to CONNECT.
4.5 When placing the first MG Set in operation, then the preferred MG-Set is B, because all synchronizing circuitry for both MG sets is located in the A Cabinet.
If a problem exists synchronizing MG sets and A is already In-Service, then when the A Cabinet is open to work on the B Circuitry A MG Set could be tripped.
4.6 If an overcurrent trip occurs, then before closing the MG Set Motor Breaker, the breakers are reset by putting the breaker control switch in the PULL-OUT position.
MG Set Output Breakers may require more effort to place in the full PULL-OUT position than the MG Set Supply Breakers. The PULL-OUT position for the MG Set Output Breakers will be the same as the position for MG Set Supply Breakers (approximately one inch out) (Reference 2.4.2)
DOMINION 1-OP-58.1 North Anna Power Station Revision 25 Page 6 of 24 4.7 When relays and breakers are in a reset condition with breakers open, the green indicating lights for MG Set Output Breakers should be lit, even with the control switch in PULL-OUT position. The MG Set Supply Breaker lights are off with the control switch in PULL-OUT position. (Reference 2.4.2)
DOMINION 1-OP-58.1 North Anna Power Station Revision 25 Page 7 of 24 5.0 INSTRUCTIONS 5.1 Starting an MG Set with Both Sets Shut Down 5.1.1 Check Initial Conditions are satisfied.
5.1.2 Review Precautions and Limitations.
5.1.3 Ensure the following breakers are open:
- 1-EP-BKR-RTA, Reactor Trip Breaker A
- 1-EP-BKR-RTB, Reactor Trip Breaker B
- 1-EP-BKR-BYA, Reactor Trip Bypass Breaker A
- 1-EP-BKR-BYB, Reactor Trip Bypass Breaker B NOTE: An MG Set Output breaker can NOT be closed unless the Output Breakers for BOTH MG Sets are racked to CONNECT.
5.1.4 Check that BOTH of the following MG Set Output Breakers are racked to the CONNECT position:
- 1-ED-MG-01A Output Breaker, 1-ED-BKR-01A1, Generator No. 1
- 1-ED-MG-01B Output Breaker, 1-ED-BKR-01B1, Generator No. 2 5.1.5 Do the following switch lineup:
- a. Place the Generator No. 1 Voltage Adjust potentiometer to the mid range position.
DOMINION 1-OP-58.1 North Anna Power Station Revision 25 Page 8 of 24 b.
Place the Generator No. 2 Voltage Adjust potentiometer to the mid range position.
- c. Ensure Generator No. 1 Synchronize switch, is OFF.
d.
Ensure Generator No. 2 Synchronize switch, is OFF.
e.
Ensure Generator No. 1 Ammeter switch is in position A.
f.
Ensure Generator No. 2 Ammeter switch is in position A.
g.
Ensure Generator No. 1 Voltmeter switch is in position A-B.
h.
Ensure Generator No. 2 Voltmeter switch is in position A-B.
i.
Ensure 1KS, the three-pole grounding switch on the inside of the control cabinet, is in the OPEN position.
DOMINION 1-OP-58.1 North Anna Power Station Revision 25 Page 9 of 24 NOTE: If an overcurrent trip occurs, then before closing the MG Set Motor Breaker, the breakers are reset by putting the breaker control switch in the PULL-OUT position. MG Set Output Breakers may require more effort to place in the full PULL-OUT position than the MG Set Supply Breakers. The PULL-OUT position for the MG Set Output Breakers will be the same as the position for MG Set Supply Breakers (approximately one inch out)
(Reference 2.4.2)
NOTE: When relays and breakers are in a reset condition with breakers open, the green indicating lights for MG Set Output Breakers should be lit, even with the control switch in PULL-OUT position. The MG Set Supply Breaker lights are off with the control switch in PULL-OUT position.
(Reference 2.4.2) 5.1.6 Do the following: (Reference 2.4.2)
- a. Check 1-ED-MG-1A, Rod Drive MG Set Generator Output Breaker light and control switch indications are green. IF light is NOT green, THEN place the switch in TRIP after PULL-OUT.
b.
Check 1-ED-MG-1B, Rod Drive MG Set Generator Output Breaker light and control switch indications are green. IF light is NOT green, THEN place the switch in TRIP after PULL-OUT.
c.
Check 1-ED-MG-1A, Rod Drive MG Set Motor Supply Breaker light and control switch indications are green. IF light is NOT green, THEN place the switch in TRIP after PULL-OUT.
DOMINION 1-OP-58.1 North Anna Power Station Revision 25 Page 10 of 24 d.
Check 1-ED-MG-1B, Rod Drive MG Set Motor Supply Breaker light and control switch indications are green. IF light is NOT green, THEN place the switch in TRIP after PULL-OUT.
e.
IF any MG Set breaker was reset (placed in TRIP after PULL-OUT) to obtain a green light OR any of the following relays show a red flag, THEN perform Substeps 5.1.6.e.1, 5.1.6.e.2, and 5.1.6.e.3 below:
- Generator No. 1 Ground Protective Relay
- Generator No. 1 Directional Overcurrent A and C Relays
- Generator No. 2 Directional Overcurrent A and C Relays
- 1. Depress the RELAY FLAG RESET pushbutton.
- 2. Reset the flag on the following relays which show a red flag. Mark relays not reset N/A.
- Generator No. 1 Ground Protective Relay
- Generator No. 1 Directional Overcurrent A and C Relays
- Generator No. 2 Directional Overcurrent A and C Relays
- 3. Repeat Step 5.1.6.
NOTE: Preferred MG is B based on P & L Step 4.5 5.1.7 Close ONE of the following Rod Drive MG Set Motor Supply Breakers for the MG Set to be started. Mark MG Set not started N/A:
- 1-ED-MG-1A, Rod Drive MG Set Motor Supply Breaker
- 1-ED-MG-1B, Rod Drive MG Set Motor Supply Breaker
DOMINION 1-OP-58.1 North Anna Power Station Revision 25 Page 11 of 24 5.1.8 Do the following for the Rod Drive MG Set started:
a.
Check MG Set is accelerating.
b.
Depress and hold GEN. FIELD FLASH button.
- c. Check voltage increases to at least 230 to 240 volts.
d.
WHEN voltage stabilizes, THEN release GEN. FIELD FLASH button.
e.
Adjust the Voltage Adjust potentiometer until the voltmeter indicates 260 VAC.
5.1.9 Close ONE of the following Rod Drive MG Set Generator Output Breaker for the running MG Set. Mark breaker not closed N/A:
- 1-ED-MG-1A, Rod Drive MG Set Generator Output Breaker
- 1-ED-MG-1B, Rod Drive MG Set Generator Output Breaker 5.1.10 IF MG Set voltage NOT at 260 VAC, THEN adjust the Voltage Adjust potentiometer to 260 VAC.
Completed by: ___________________________________________ Date: _________
DOMINION 1-OP-58.1 North Anna Power Station Revision 25 Page 12 of 24 5.2 Paralleling a Shutdown MG Set to an Operating MG Set 5.2.1 Check Initial Conditions are satisfied.
5.2.2 Review Precautions and Limitations.
5.2.3 Do the following for the shutdown MG Set:
a.
Ensure the Voltage Adjust potentiometer is in the mid-position.
b.
Ensure the Synchronize switch, is OFF.
c.
IF any of the following relays show a red flag, THEN perform Substeps 5.2.3.c.1, 5.2.3.c.2, and 5.2.3.c.3 below:
- Generator No. 1 Ground Protective Relay
- Generator No. 1 Directional Overcurrent A and C Relays
- Generator No. 2 Directional Overcurrent A and C Relays
- 1. Depress the RELAY FLAG RESET pushbutton.
- 2. Reset the flag on the following relays which show a red flag. Mark relays NOT reset N/A.
- Generator No. 1 Ground Protective Relay
- Generator No. 1 Directional Overcurrent A and C Relays
- Generator No. 2 Directional Overcurrent A and C Relays
- 3. IF an overcurrent trip occurs, THEN, before closing the MG Set Motor Breaker, reset the breaker by placing the switch in TRIP after PULL-OUT.
DOMINION 1-OP-58.1 North Anna Power Station Revision 25 Page 13 of 24 5.2.4 Close ONE of the following Rod Drive MG Set Motor Supply Breakers for the MG Set to be started. Mark MG Set not started N/A:
- 1-ED-MG-1A, Rod Drive MG Set Motor Supply Breaker
- 1-ED-MG-1B, Rod Drive MG Set Motor Supply Breaker 5.2.5 Do the following for the MG Set that was started:
- a. Check MG set is accelerating.
b.
Depress and hold GEN. FIELD FLASH button.
- c. Check voltage increases to at least 230 to 240 volts.
d.
WHEN voltage is stabilized, THEN release GEN. FIELD FLASH button.
NOTE: A mismatch of less than + 5 volts is preferred, however the automatic synchronizer will operate properly with a maximum mismatch of + 12 volts.
e.
Adjust the Voltage Adjust potentiometer until the voltmeter matches running voltage as close as possible to 260 VAC.
DOMINION 1-OP-58.1 North Anna Power Station Revision 25 Page 14 of 24 NOTE: The Rod Drive MG Set Generator Output Breaker must be out of the Pull-To-Lock position by pushing the control switch lever in. This will allow the synchronizing circuit to automatically close the output breaker.
NOTE: The synchronizing relay can take up to 60 seconds to activate. Greater than 60 seconds is indication of a synchronizing circuit problem.
f.
Place the Synchronize switch in ON AND wait no more than 60 seconds, THEN do Substep 5.2.5.g.
g.
Check the Rod Drive MG Set Generator Output Breaker that is being paralleled closes. Mark MG Set Output Breaker not being paralleled N/A:
- 1-ED-MG-1A, Rod Drive MG Set Generator Output Breaker
- 1-ED-MG-1B, Rod Drive MG Set Generator Output Breaker h.
Place the Synchronize switch in OFF.
NOTE: When MG Sets are operated in parallel the output voltage should be approximately the same on each set.
i.
Check voltage indicates approximately the same on each MG Set. IF NOT, THEN notify System Engineering.
j.
RED FLAG the Rod Drive MG Set Generator Output Breaker by placing the control switch to the CLOSE position.
Completed by: ___________________________________________ Date: _________
Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Equipment rotation is in progress 1-GW-F-1B is running Equipment status has been reviewed to verify station configuration will support performance of this procedure INITIATING CUE You are requested to shift process vent blowers in accordance with 0-OP-23.3.
2016 NRC EXAM IN PLANT K Page: 2 of 10 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Shift Process Vent System blowers (0-OP-23.3).
TASK STANDARDS Task was performed as directed by the procedure referenced in the task statement within parentheses (one of the underlined procedures if several are cited)
Work was performed in compliance with the Radiation Work Permit; exposure to surface and airborne contamination was minimized; and ALARA principles were applied K/A
REFERENCE:
071A1.06 (2.5/2.8)
ALTERNATE PATH:
N/A TASK COMPLETION TIMES Validation Time =
10 minutes Start Time = _______
Actual Time = _______ minutes Stop Time = _______
PERFORMANCE EVALUATION Rating
[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date EVALUATOR'S COMMENTS
2016 NRC EXAM IN PLANT K Page: 3 of 10
2016 NRC EXAM IN PLANT K Page: 4 of 10 Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)
OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
PREREQUISITES Before being evaluated on the task, the trainee must have completed the reactor operator's course checkout during which the objectives listed below would have been addressed.
INITIAL CONDITIONS Equipment rotation is in progress 1-GW-F-1B is running Equipment status has been reviewed to verify station configuration will support performance of this procedure
2016 NRC EXAM IN PLANT K Page: 5 of 10 INITIATING CUE You are requested to shift process vent blowers IAW 0-OP-23.3.
EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))
Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))
TOOLS AND EQUIPMENT Administrative key PERFORMANCE STEPS START TIME 1
Check initial conditions and review precautions and limitations.
Procedure Step 5.3.1 & 5.3.2 SAT [ ] UNSAT [ ]
Standards Initial condition is checked and precautions and limitations are reviewed Notes/Comments
2016 NRC EXAM IN PLANT K Page: 6 of 10 2
Open the following valves for 1-GW-F-1A:
- l-GW-l35, 1A Waste Gas Process Vent Blower Suct Isol Valve
- l-GW-l38, 1A Waste Gas Process Vent Blower Disch Isol Valve Procedure Step 5.3.3 Critical Step SAT [ ] UNSAT [ ]
Standards The valves are simulated to be turned in the counter-clockwise direction until the handwheel stops turning Simulation Cue(s) The handwheel has stopped turning and the position indicating stem is full out.
If asked: 1-GW-135 has been independently verified.
Notes/Comments 3
Turn ON 1-EP-BKR-1A2-1 G3, 1A Waste Gas Process Vent Blower Circuit Breaker 1-GW-F-1A.
Procedure Step 5.3.4 Critical Step SAT [ ] UNSAT [ ]
Standards The breaker is simulated to be turned to the ON position Simulation Cue(s) The breaker indicates in the ON position Notes/Comments
2016 NRC EXAM IN PLANT K Page: 7 of 10 4
Start l-GW-F-1A, PROCESS VENT BLOWER, at Waste Disposal Panel in Control Room.
Procedure Step 5.3.5 SAT [ ] UNSAT [ ]
Standards The operator simulates calling the control room to start 1-GW-F-1A Simulation Cue(s) 1-GW-F-1A is running Notes/Comments 5
Stop l-GW-F-1B, PROCESS VENT BLOWER, at Waste Disposal Panel in Control Room.
Procedure Step 5.3.6 SAT [ ] UNSAT [ ]
Standards The operator simulates calling the control room to stop 1-GW-F-1B Simulation Cue(s) 1-GW-F-1B has been stopped Notes/Comments
2016 NRC EXAM IN PLANT K Page: 8 of 10 6
Verify 1-GW-FI-108, PROCESS VENT FLOW, at Waste Disposal Panel in Control Room, is reading 270-330 scfm.
Procedure Step 5.3.7 SAT [ ] UNSAT [ ]
Standards The operator simulates calling the control room to verify flow Simulation Cue(s) Backboards operator reports flow is 350 scfm Notes/Comments 7
IF flow is >330 scfm, THEN throttle closed l-GW-l38, 1A Waste Gas Process Vent Blower Disch Isol Valve, as required to obtain 270-330 scfm.
Procedure Step 5.3.7.b SAT [ ] UNSAT [ ]
Standards 1-GW-138 is simulated to be turned in the clockwise direction Simulation Cue(s) Once the trainee throttles closed on the discharge valve, state that flow is now 300 scfm Notes/Comments
2016 NRC EXAM IN PLANT K Page: 9 of 10 8
Turn OFF breaker 1-EP-BKR-1C2-1 D3, 1B Waste Gas Process Vent Blower Circuit Breaker 1-GW-F-1B.
Procedure Step 5.3.8 SAT [ ] UNSAT [ ]
Standards The breaker is simulated to be turned to the OFF position Simulation Cue(s) The breaker indicates in the OFF position Notes/Comments 9
Close the following valves for 1-GW-F-1B, 1B Waste Gas Process Vent Blower:
- l-GW-l39, 1B Waste Gas Process Vent Blower Suct Isol Valve
- l-GW-l42, 1B Waste Gas Process Vent Blower Disch Isol Valve Procedure Step 5.3.9 SAT [ ] UNSAT [ ]
Standards The valves are simulated to be turned in the clockwise direction until the handwheel stops turning Simulation Cue(s) The handwheel has stopped turning and the position indicating stem is full in.
Another operator will be assigned to independently verify the procedure.
Notes/Comments
>>>>> END OF EVALUATION <<<<<
STOP TIME
2016 NRC EXAM IN PLANT K Page: 10 of 10 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)
DOMINION 0-OP-23.3 North Anna Power Station Revision 7 Page 5 of 21 Init Verif 3.0 INITIAL CONDITIONS 3.1 Review the equipment status to verify station configuration will support performance of this procedure.
4.0 PRECAUTIONS AND LIMITATIONS 4.1 Comply with the following guidelines when marking steps N/A:
- IF the conditional requirements of a step do not require the action to be performed, THEN mark the step N/A.
- IF any other step is marked N/A, THEN have the SRO (or designee) approve the N/A and justify the N/A on the Procedure Cover Sheet.
4.2 Flow must be maintained between 270 and 330 scfm flowrate when operating Process Vent Blowers. Flow should be maintained at least 285 scfm.
4.3 Due to possible Charcoal Filter degradation, the Process Vent Filter System should NOT be placed in service during or following painting, fire, or chemical release in any ventilation zone communicating with the inlet to the Process Vent System.
IF the Process Vent System MUST remain in service under these conditions, THEN the surveillance requirements of TRM 3.6.3 must be satisfied.
(References 2.3.10 and 2.4.3) 4.4 The radioactive gaseous effluent monitoring instrumentation channels shall be operable in accordance with the Radioactive Gaseous Effluent Monitoring Instrumentation Attachment of VPAP-2103N, Offsite Dose Calculation Manual (North Anna). (Reference 2.2.2) 4.5 Flowrate is based on normal temperatures in the Auxiliary Building and Process Vent System. Flowrate should not be adjusted when abnormal temperatures exist.
Temperature could be abnormally low in Winter when the rolling steel door near the Process Vent Filter is open.
DOMINION 0-OP-23.3 North Anna Power Station Revision 7 Page 14 of 21 5.3 Shifting from 1-GW-F-1B, 1B Waste Gas Process Vent Blower, to 1-GW-F-1A, 1A Waste Gas Process Vent Blower 5.3.1 Check Initial Condition is satisfied.
5.3.2 Review Precautions and Limitations.
5.3.3 Open the following valves for 1-GW-F-1A, Process Vent Blower:
IV
- l-GW-l35, 1A Waste Gas Process Vent Blower Suct Isol Valve
- l-GW-l38, 1A Waste Gas Process Vent Blower Disch Isol Valve 5.3.4 Turn ON 1-EP-BKR-1A2-1 G3, 1A Waste Gas Process Vent Blower Circuit Breaker 1-GW-F-1A.
5.3.5 Start l-GW-F-1A, PROCESS VENT BLOWER, at Waste Disposal Panel in Control Room.
5.3.6 Stop l-GW-F-1B, PROCESS VENT BLOWER, at Waste Disposal Panel in Control Room.
NOTE: Although 270 scfm meets TRM criteria, flow should be maintained at least 285 scfm.
5.3.7 Verify 1-GW-FI-108, PROCESS VENT FLOW, at Waste Disposal Panel in Control Room, is reading 270-330 scfm. IF flow is outside these limits, THEN do Substep 5.3.7.a OR 5.3.7.b as appropriate:
a.
IF flow is <270 scfm, THEN do the following:
- 1. Stop l-GW-F-1A, PROCESS VENT BLOWER
- 2. Start l-GW-F-1B, PROCESS VENT BLOWER
DOMINION 0-OP-23.3 North Anna Power Station Revision 7 Page 15 of 21
- 3. Turn OFF 1-EP-BKR-1A2-1 G3, 1A Waste Gas Process Vent Blower Circuit Breaker 1-GW-F-1A.
- 4. Close following valves for 1-GW-F-1A:
IV
- l-GW-l35, 1A Waste Gas Process Vent Blower Suct Isol Valve IV
- l-GW-l38, 1A Waste Gas Process Vent Blower Disch Isol Valve
- 5. Mark the remainder of this section N/A.
b.
IF flow is >330 scfm, THEN throttle closed l-GW-l38, 1A Waste Gas Process Vent Blower Disch Isol Valve, as required to obtain 270-330 scfm.
5.3.8 Turn OFF breaker 1-EP-BKR-1C2-1 D3, 1B Waste Gas Process Vent Blower Circuit Breaker 1-GW-F-1B.
5.3.9 Close the following valves for 1-GW-F-1B, 1B Waste Gas Process Vent Blower:
IV
- l-GW-l39, 1B Waste Gas Process Vent Blower Suct Isol Valve IV
- l-GW-l42, 1B Waste Gas Process Vent Blower Disch Isol Valve Completed by: ___________________________________________ Date: _________
Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS A LOCA has occurred No High-Head Safety Injection flow is indicated INITIATING CUE You are requested to perform attachment 6 of 1-E-0, "Manual Verification of SI Flowpath."
NAPS 2016 NRC EXAM SIM JPM A Page: 2 of 8 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM R730 TASK Verify safety injection flow (1-E-0).
TASK STANDARDS Charging suction was aligned to RWST, and flow was established through BIT K/A
REFERENCE:
011EA1.13 (4.1/4.2)
ALTERNATE PATH:
Boron Injection Tank MOVs fail to open requiring alternate flow path to be used TASK COMPLETION TIMES Validation Time =
8 minutes Start Time = _______
Actual Time = _______ minutes Stop Time = _______
PERFORMANCE EVALUATION Rating
[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date EVALUATOR'S COMMENTS
NAPS 2016 NRC EXAM SIM JPM A Page: 3 of 8 Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)
OPERATOR PROGRAM R730 READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
PREREQUISITES The trainee has completed the applicable course knowledge training at the Reactor Operator level.
INITIAL CONDITIONS A LOCA has occurred No High-Head Safety Injection flow is indicated INITIATING CUE You are requested to perform attachment 6 of 1-E-0, "Manual Verification of SI Flowpath."
NAPS 2016 NRC EXAM SIM JPM A Page: 4 of 8 EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))
Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))
TOOLS AND EQUIPMENT A copy of attachment 6 from 1-E-0 is available PERFORMANCE STEPS START TIME 1
Manually align charging pump suction from the refueling water storage tank.
Procedure Step 1 & 2 Standards 1-CH-MOV-1115B and/or 1115D is opened 1-CH-MOV-1115C and/or 1115E is closed Notes/Comments
NAPS 2016 NRC EXAM SIM JPM A Page: 5 of 8 2
Close at least one normal charging isolation valve.
Procedure Step _3__
SAT [ ] UNSAT [ ]
Standards Either 1-CH-MOV-1289A or 1-CH-MOV-1289B is closed Simulation Cue(s) 1-CH-MOV-1289A or 1-CH-MOV-1289B have green lights lit and red lights not lit Notes/Comments 3
Close BIT RECIRC valves.
Procedure Step __4__
SAT [ ] UNSAT [ ]
Standards 1-SI-TV-1884A, 1884B, and 1884C are closed Notes/Comments 4
OPEN AT LEAST ONE BIT OUTLET VALVE - NO.
(alt path)
Procedure Step __5__
Standards OPEN push-buttons for 1-SI-MOV-1867C and/or 1867D are depressed Notes/Comments - BIT Outlet MOVs will not OPEN. RNO action taken (1-SI-MOV-1836 will not open) Operator will obtain key #21 and open EITHER 1-SI-MOV-1869A OR 1-SI-MOV-1869B and proceed to Step 7.
NAPS 2016 NRC EXAM SIM JPM A Page: 6 of 8 5
Turn on control power and open 1-SI-MOV-1836 -NO.
(alt path)
Procedure Step
_5 RNO Standards OPEN push-button for 1-SI-MOV-1836 is depressed Notes/Comments SI-MOV-1836 will not open 6
Turn on control power and open 1-SI-MOV-1869A or 1869B.
Procedure Step
_5 RNO CRITICAL STEP SAT [ ] UNSAT [ ]
Standards EITHER 1-SI-MOV-1869A OR 1-SI-MOV-1869B is opened.
Cue(s)
IF the operator requests that the key be delivered from the WCC then state: You have permission to use the key from the Appendix R/Vital area key box.
Notes/Comments - Operator will obtain key #21 and open EITHER 1-SI-MOV-1869A OR 1-SI-MOV-1869B and proceed to Step 7.
7 Verify the charging pumps are running.
Procedure Step __7__
SAT [ ] UNSAT [ ]
Standards Operator ensures two pumps are running, if available.
Notes/Comments
NAPS 2016 NRC EXAM SIM JPM A Page: 7 of 8 5
Verify that high-head safety injection flow to the cold-legs is indicated.
Procedure Step _____
SAT [ ] UNSAT [ ]
Standards Adequate cold-leg safety injection flow is indicated Simulation Cue(s) Assume that another operator will complete the procedure Notes/Comments
>>>>> END OF EVALUATION <<<<<
STOP TIME
NAPS 2016 NRC EXAM SIM JPM A Page: 8 of 8 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)
SIMULATOR SETUP JOB PERFORMANCE MEASURE R730 TASK Verify safety injection flow (1-E-0).
CHECKLIST
_______ Recall IC #1 (100% power)
_______ Enter malfunctions SI 108, 0701, 0702 and RC 04 100% degradation
_______ Enter malfunctions for 1-SI-MOV-1836, 1-SI-MOV-1867C, and 1-SI-MOV-1867D
_______ Go to Run
_______ Perform 1st 4 steps of 1-E-0
_______ Place the simulator in FREEZE
STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 of 5 NUMBER 1-E-0 ATTACHMENT TITLE MANUAL VERIFICATION OF SI FLOWPATH ATTACHMENT 6
REVISION 49 PAGE
- 1. ___ OPEN CHARGING PUMP SUCTION FROM RWST ISOLATION VALVES:
Locally open at least one valve.
- 1-CH-MOV-1115B
- 1-CH-MOV-1115D
WHEN at least one valve is open, THEN GO TO Step 2.
- 2. ___ CLOSE CHARGING PUMP SUCTION FROM VCT ISOLATION VALVES:
Locally close at least one valve before continuing with Step 3.
- 1-CH-MOV-1115C
- 1-CH-MOV-1115E
- 3. ___ CLOSE AT LEAST ONE NORMAL CHARGING ISOLATION VALVE:
Place 1-CH-FCV-1122 in MANUAL and close.
- 1-CH-MOV-1289A
- 1-CH-MOV-1289B
NUMBER 1-E-0 ATTACHMENT TITLE MANUAL VERIFICATION OF SI FLOWPATH ATTACHMENT 6
REVISION 49 PAGE 2 of 5 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. ___ CLOSE BIT RECIRC VALVES:
- 1-SI-TV-1884A
- 1-SI-TV-1884B
- 1-SI-TV-1884C IF both of the following valves will NOT close, THEN do the following:
- 1-SI-TV-1884A
- 1-SI-TV-1884B
a) Turn on control power to AND open 1-SI-MOV-1836, SI COLD LEG INJECTION ALTERNATE HDR ISOLATION.
IF 1-SI-MOV-1836 will NOT open, THEN turn on control power to AND open one of the following valves (Key Required):
b) Continue with Step 7.
NUMBER 1-E-0 ATTACHMENT TITLE MANUAL VERIFICATION OF SI FLOWPATH ATTACHMENT 6
REVISION 49 PAGE 3 of 5 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. ___ OPEN AT LEAST ONE BIT OUTLET VALVE:
- 1-SI-MOV-1867C
- 1-SI-MOV-1867D
Turn on control power to AND open 1-SI-MOV-1836, SI COLD LEG INJECTION ALTERNATE HDR ISOLATION.
IF 1-SI-MOV-1836 will NOT open, THEN turn on control power to AND open one of the following valves (Key Required):
GO TO Step 7.
- 6. ___ OPEN AT LEAST ONE BIT INLET VALVE:
- 1-SI-MOV-1867A
- 1-SI-MOV-1867B
Turn on control power to AND open 1-SI-MOV-1836, SI COLD LEG INJECTION ALTERNATE HDR ISOLATION.
IF 1-SI-MOV-1836 will NOT open, THEN turn on control power to AND open one of the following valves (Key Required):
GO TO Step 7.
NUMBER 1-E-0 ATTACHMENT TITLE MANUAL VERIFICATION OF SI FLOWPATH ATTACHMENT 6
REVISION 49 PAGE 4 of 5 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. ___ VERIFY CHARGING PUMPS - RUNNING
Manually start pumps.
- 8. ___ VERIFY SI FLOW - INDICATED:
- 1-SI-FI-1943
- 1-SI-FI-1943-1 OR
- 1-SI-FI-1940
- 1-SI-FI-1940-1
NUMBER 1-E-0 ATTACHMENT TITLE MANUAL VERIFICATION OF SI FLOWPATH ATTACHMENT 6
REVISION 49 PAGE 5 of 5 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. ___ VERIFY SI FLOW ALIGNED THROUGH BIT Align flow through BIT:
a) IF both of the following valves are open, THEN locally close 1-SI-71, BIT Outlet Hdr To Boric Acid Tank Isol Valve:
- 1-SI-TV-1884A
- 1-SI-TV-1884B b) Locally open at least one BIT outlet valve:
- 1-SI-MOV-1867C
- 1-SI-MOV-1867D c) Locally open at least one BIT inlet valve:
- 1-SI-MOV-1867A
- 1-SI-MOV-1867B d) WHEN SI flow through the BIT is established, THEN ensure the following valves are closed AND turn off control power:
- 1-SI-MOV-1836
- 1-SI-MOV-1869B
- 1-SI-MOV-1869A
- 10. ___ RETURN TO PROCEDURE AND STEP IN EFFECT
- END -
Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit 1 has been tripped, and steady-state conditions of 2,235 psig and approximately 548°F exist Both motor-driven auxiliary feedwater pumps are unavailable Turbine-driven auxiliary feedwater pump is running All main feedwater pumps, heater drain pumps, and condensate pumps have been stopped due to a feed-line break in the turbine building An operator is standing by in the AFPH with a copy of 1-AP-22.4 INITIATING CUE You are requested to respond to a Loss of Both Motor-Driven AFW pumps in accordance with 1-AP-22.4.
NAPS 2016 NRC EXAM SIM JPM B Page: 2 of 14 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM R524 TASK Supply feedwater to all three steam generators using the HCV header (1-AP-22.4).
TASK STANDARDS The HCV header has been aligned to feed all SGs from the Terry Turbine K/A
REFERENCE:
061-A2.04 (3.4/3.8)
ALTERNATE PATH:
N/A TASK COMPLETION TIMES Validation Time =
15 minutes Start Time = _______
Actual Time = _______ minutes Stop Time = _______
PERFORMANCE EVALUATION Rating
[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date EVALUATOR'S COMMENTS
NAPS 2016 NRC EXAM SIM JPM B Page: 3 of 14 Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)
OPERATOR PROGRAM R524 READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
PREREQUISITES The trainee has completed the applicable course knowledge training at the Reactor Operator level.
INITIAL CONDITIONS Unit 1 has been tripped, and steady-state conditions of 2,235 psig and approximately 548°F exist Both motor-driven auxiliary feedwater pumps are unavailable Turbine-driven auxiliary feedwater pump is running All main feedwater pumps, heater drain pumps, and condensate pumps have been stopped due to a feed-line break in the turbine building
NAPS 2016 NRC EXAM SIM JPM B Page: 4 of 14 An operator is standing by in the AFPH with a copy of 1-AP-22.4 INITIATING CUE You are requested to respond to a Loss of Both Motor-Driven AFW pumps in accordance with 1-AP-22.4.
EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))
Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))
TOOLS AND EQUIPMENT None PERFORMANCE STEPS START TIME 1
Determine if the Main Feedwater System is in service.
Procedure Step __1__
SAT [ ] UNSAT [ ]
Standards Main feed pumps are verified stopped, or initial conditions are reviewed Simulation Cue(s) Main feedwater pumps have been stopped Notes/Comments
NAPS 2016 NRC EXAM SIM JPM B Page: 5 of 14 2
Stop all but one reactor coolant pump.
Procedure Step RNO 1.a Critical Step SAT [ ] UNSAT [ ]
Standards Exactly two reactor coolant pump control switches are placed in AUTO-AFTER-STOP Notes/Comments 3
Place spray valve(s) for any idle RCP(s) in manual and close.
Procedure Step RNO 1.a SAT [ ] UNSAT [ ]
Standards Spray valve(s) for idle RCP(s) are placed in manual and verified closed Simulation Cue(s) After placed in manual:
1-RC-PCV-1455A(B) has red light lit for MANUAL and demand is zero Notes/Comments
NAPS 2016 NRC EXAM SIM JPM B Page: 6 of 14 4
Initiate attempts to restore main feedwater.
Procedure Step RNO 1.b SAT [ ] UNSAT [ ]
Standards Operator states that he would inform unit supervisor of need to restore main feedwater Performance Cue(s)
Assume that another operator will perform this step Simulation Cue(s) Assume that another operator will perform this step Notes/Comments 5
Verify that the turbine-driven auxiliary feedwater pump is running.
Procedure Step 2 SAT [ ] UNSAT [ ]
Standards Verifies that 1-FW-P-2 is running Simulation Cue(s) Turbine-driven auxiliary feedwater pump trip valves have red lights LIT and green light NOT lit. Flow is indicated.
Notes/Comments
NAPS 2016 NRC EXAM SIM JPM B Page: 7 of 14 6
Verify that emergency condensate storage tank level is greater than 40%.
Procedure Step 3 SAT [ ] UNSAT [ ]
Standards Operator checks ECST indicators are > 40%
Simulation Cue(s) Emergency condensate storage tank level is 90%
Notes/Comments 7
Perform attachment 5 to align HCV header for feeding all SGs.
Procedure Step 4 SAT [ ] UNSAT [ ]
Standards Operator checks with SRO for header to align Performance Cue(s)
The SRO directs that the HCV header be used Notes/Comments
NAPS 2016 NRC EXAM SIM JPM B Page: 8 of 14 8
Open the auxiliary feedwater HCV header to "A" steam generator 1-FW-HCV-100A.
Procedure Step Att. 5 step 1 Critical Step SAT [ ] UNSAT [ ]
NOTE TO THE EVALUATOR OPERATOR MAY NOT NEED TO OPEN 1-FW-HCV-100A DUE TO HAVING SUFFICIENT LEVEL IN THE "A" SG. MAY ALSO OPEN AND THEN RECLOSE THE VALVE.
Standards Potentiometer for 1-FW-HCV-100A is turned in the clockwise direction Notes/Comments 9
Open the auxiliary feedwater HCV header to "B" steam generator 1-FW-HCV-100B.
Procedure Step Att. 5 step 1 Critical Step SAT [ ] UNSAT [ ]
Standards Potentiometer for 1-FW-HCV-100B is turned in the clockwise direction Notes/Comments
NAPS 2016 NRC EXAM SIM JPM B Page: 9 of 14 10 Open the auxiliary feedwater HCV header to "C" steam generator 1-FW-HCV-100C.
Procedure Step Att. 5 step 1 SAT [ ] UNSAT [ ]
Standards Potentiometer for 1-FW-HCV-100C verified at 100%
Notes/Comments 11 Close the auxiliary feedwater MOV header to "B" steam generator 1-FW-MOV-100B.
Procedure Step Att. 5 step 2 Standards Control switch for 1-FW-MOV-100B is placed in CLOSE and held there until valve indicates closed Simulation Cue(s) 1-FW-MOV-100B has red light LIT and green light NOT lit After switch has been held in CLOSE for some period of time: 1-FW-MOV-100B has green light LIT and red light NOT lit Notes/Comments
NAPS 2016 NRC EXAM SIM JPM B Page: 10 of 14 12 Request the safeguards operator to unlock and close the discharge valve for 1-FW-P-3A to the HCV header, 1-FW-172.
Procedure Step Att. 5 step 3.a SAT [ ] UNSAT [ ]
Standards Operator in AFW pump house is contacted to perform step Simulation Cue(s) 1-FW-172 is closed Notes/Comments:
Candidate may instruct Safeguards operator to perform all of step 3.
NAPS 2016 NRC EXAM SIM JPM B Page: 11 of 14 13 Request the safeguards operator to unlock and open the following valves.
Turbine-driven auxiliary feedwater pump to the steam generator HCV header outlet isolation valve 1-FW-155 Auxiliary feedwater "A" HCV 1-FW-HCV-100A outlet isolation valve 1-FW-64 Auxiliary feedwater "B" HCV 1-FW-HCV-100B outlet isolation valve 1-FW-96 Procedure Step Att. 5 step 3.b Critical Step SAT [ ] UNSAT [ ]
Standards Safeguards operator is requested to unlock and open 1-FW-155, 64, and 96 Simulation Cue(s) 1-FW-155, 1-FW-64, and 1-FW-96 are open Notes/Comments There will be a 2 minute delay until manual valves are repositioned. Safeguards operator will call to inform candidate that step 3 is complete.
NAPS 2016 NRC EXAM SIM JPM B Page: 12 of 14 14 Slowly close the turbine-driven auxiliary feedwater pump to "A" steam generator valve 1-FW-MOV-100D.
Procedure Step Att. 5 step 4 Critical Step SAT [ ] UNSAT [ ]
NOTE TO THE EVALUATOR OPERATOR MAY HAVE CLOSED THIS VALVE EARLIER TO CONTROL STEAM GENERATOR LEVEL Standards Control switch for 1-FW-MOV-100D is placed in CLOSE Simulation Cue(s) 1-FW-MOV-100D has red light LIT and green light NOT lit After switch has been held in CLOSE for some period of time: 1-FW-MOV-100D has green light LIT and red light NOT lit Notes/Comments 15 Notify control room that Attachment 5 is complete and return to 1-AP-22.4, step in effect.
Procedure Step Att. 5 step 5 SAT [ ] UNSAT [ ]
Standards Operator returns to step 5 of procedure Performance Cue(s)
Assume another operator will continue with 1-AP-22.4 Simulation Cue(s) Assume another operator will continue with 1-AP-22.4 Notes/Comments
>>>>> END OF EVALUATION <<<<<
NAPS 2016 NRC EXAM SIM JPM B Page: 13 of 14 STOP TIME
NAPS 2016 NRC EXAM SIM JPM B Page: 14 of 14 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)
SIMULATOR SETUP JOB PERFORMANCE MEASURE R524 TASK Supply feedwater to all three steam generators using the HCV header (1-AP-22.4).
CHECKLIST
_____ Recall IC #332
_____ Place 1-FW-P-3A in PTL, rack out the breaker, and place sticker on switch
_____ Close 1-FW-172 using ExtremeView
_____ Enter malfunction FW2302; Delay time = 60, Trigger = 1
_____ Enter malfunction FW1301, Delay time = 0, Severity = 50, Trigger = 1
_____ Place the following on triggers:
FW_155, Delay time = 10, Ramp = 20, Trigger 2 FW_64, Delay time = 30, Ramp = 20, Trigger 2 FW_96, Delay time = 50, Ramp = 20, Trigger 2
_____ Go to RUN, insert Trigger 1, manually trip reactor and turbine, and close the reheater FCVs
_____ Place the following pumps in PULL-TO-LOCK: condensate pumps and main feedwater pumps
_____ Establish RCS pressure and temperature per initial conditions and place the simulator in freeze
_____ When called to do local lineup, insert Trigger 2 (Can report that 1-FW-172 is closed and tagged, if necessary)
_____ Once the triggers time out, report that attachment 5 step 3 lineup is complete
NUMBER 1-AP-22.4 PROCEDURE TITLE LOSS OF BOTH MOTOR-DRIVEN AFW PUMPS REVISION 9
PAGE 2 of 8 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION:
- When ECST level decreases to 40%, then 1-AP-22.5, LOSS OF EMERGENCY CONDENSATE STORAGE TANK 1-CN-TK-1, should be initiated to provide an alternate water source to the AFW Pumps.
- The AFW Pumps should not be run on recirc for extended periods of time, to prevent heating of the ECST above the following maximum temperatures:
- 100 °F 1-FW-P-2
- 120 °F 1-FW-P-3A
- 120 °F 1-FW-P-3B
- To prevent possible degradation to the AFW Pump, the amount of time spent on minimum recirc flow should be minimized.
- To prevent lifting relief valve 1-FW-RV-100 when reducing feed flow, any MOV or HCV supplied by the Turbine-Driven AFW Pump should be slowly throttled.
- To prevent lifting relief valve 1-FW-RV-100, a discharge flowpath must be available to feed an SG from the Turbine-Driven AFW Pump.
NOTE:
- Normal PRZR spray should be isolated from any RCP that is stopped.
- If AFW Pumps are lost due to loss of control from the Control Room, then evaluate using 1-AP-20, OPERATION FROM THE AUXILIARY SHUTDOWN PANEL, to start the affected AFW Pumps from the Auxiliary Shutdown Panel.
- 1. ___ CHECK MAIN FEEDWATER -
IN SERVICE Do the following:
a) Stop all but one RCP.
IF A RCP is stopped, THEN place 1-RC-PCV-1455A in manual and close.
IF C RCP is stopped, THEN place 1-RC-PCV-1455B in manual and close.
b) Initiate attempts to restore Main Feedwater.
NUMBER 1-AP-22.4 PROCEDURE TITLE LOSS OF BOTH MOTOR-DRIVEN AFW PUMPS REVISION 9
PAGE 3 of 8 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
a) Open 1-FW-MOV-100D, TURBINE DRIVEN AFW PUMP TO A SG.
b) Put Steam Supply Valves for Turbine Driven AFW Pump in OPEN:
- 1-MS-TV-111A
- 1-MS-TV-111B
- 3. ___ CHECK ECST LEVEL - GREATER THAN 40%
Initiate 1-AP-22.5, LOSS OF EMERGENCY CONDENSATE STORAGE TANK 1-CN-TK-1.
NOTE:
- The AFW lineup drawings of ATTACHMENT 4 and ATTACHMENT 5 should be retained in the Control Room to provide Control Room personnel with a graphical representation of the AFW lineup.
Perform ATTACHMENT 4 to align MOV Header for feeding all SGs.
WHEN ATTACHMENT 4 is complete, THEN GO TO Step 7.
- 1-FW-HCV-100A for A SG
- 1-FW-HCV-100B for B SG
- 1-FW-HCV-100C for C SG
IF SG level cannot be maintained due to AFW Pressure Control Valve limiting flow, THEN perform ATTACHMENT 3, FAILING OPEN AFW PRESSURE CONTROL VALVES, Step 1.
- 6. ___ GO TO STEP 8
1 of 2 NUMBER 1-AP-22.4 ATTACHMENT TITLE ALIGNING TURBINE-DRIVEN AFW PUMP TO HCV HEADER ATTACHMENT 5
REVISION 9
PAGE NOTE: Some AFW System valves have admin locks.
1.
Have the CRO open the following AFW Valves:
___
___
___
3.
Locally perform the following valve lineup (located in the Motor-Driven AFW Pumphouse):
___ a) Unlock and close 1-FW-172, Discharge Valve for 1-FW-P-3A to HCV Header.
b) Unlock and open the following valves:
- 5. ___ Notify the Control Room that ATTACHMENT 5 is complete and to return to 1-AP-22.4, step in effect.
NUMBER 1-AP-22.4 ATTACHMENT TITLE ALIGNING TURBINE-DRIVEN AFW PUMP TO HCV HEADER ATTACHMENT 5
REVISION 9
PAGE 2 of 2 AUXILIARY FEEDWATER SYSTEM 1-FW-P-2 ALIGNED TO THE HCV HEADER Graphics No: BP712H Emergency Condensate Storage Tank Service Water Fire Main F
F F
Main Feed Main Feed Main Feed S/G 1A S/G 1C S/G 1B OSC ISC 1-FW-142 Condensate Makeup LC 1-FW-545 1-FW-143 1-FW-160 1-FW-173 1-FW-227 1-FW-145 1-FW-229 1-FW-162 1-FW-230 1-FW-180 1-FW-175 1-FW-P-3B 1-FW-P-3A 1-FW-P-2 1-FW-543 1-FW-548 1-FW-172 1-FW-166 1-FW-546 1-FW-190 1-FW-184 1-FW-MOV-100D 1-FW-278 1-FW-149 1-FW-155 1-FW-PCV-159B 1-FW-HCV-100A 1-FW-64 1-FW-HCV-100C 1-FW-HCV-100B 1-FW-128 1-FW-96 1-FW-PCV-159A 1-FW-MOV-100A 1-FW-62 1-FW-MOV-100B 1-FW-MOV-100C 1-FW-94 1-FW-126 1-FW-228 Drain 1-FW-176 Drain
Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit is stable at 100% power.
Reactor coolant pump 1C has just lost seal cooling.
INITIATING CUE You are requested to respond to the loss of seal cooling in accordance with 1-AP-33.2, "Loss of Reactor Coolant Pump Seal Cooling".
NAPS 2016 NRC EXAM SIM JPM C Page: 2 of 12 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM R724 TASK Respond to a loss of reactor coolant pump seal cooling (1-AP-33.2).
TASK STANDARDS Reactor manually tripped, "C" RCP stopped, seal return isolated, and "C" thermal barrier TV verified closed.
K/A
REFERENCE:
015-AA1.07 (3.5/3.4)
ALTERNATE PATH:
1-CH-MOV-1381 fails to close requiring use of alternate MOV to isolate TASK COMPLETION TIMES Validation Time =
10 minutes Start Time = _______
Actual Time = _______ minutes Stop Time = _______
PERFORMANCE EVALUATION Rating
[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date EVALUATOR'S COMMENTS
NAPS 2016 NRC EXAM SIM JPM C Page: 3 of 12 Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)
OPERATOR PROGRAM R724 READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
PREREQUISITES The trainee has completed the applicable course knowledge training at the reactor operator level.
INITIAL CONDITIONS Unit is stable at 100% power.
Reactor coolant pump 1C has just lost seal cooling.
NAPS 2016 NRC EXAM SIM JPM C Page: 4 of 12 INITIATING CUE You are requested to respond to the loss of seal cooling in accordance with 1-AP-33.2, "Loss of Reactor Coolant Pump Seal Cooling."
EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s)).
Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s)).
TOOLS AND EQUIPMENT None
NAPS 2016 NRC EXAM SIM JPM C Page: 5 of 12 PERFORMANCE STEPS START TIME 1
Verify that the affected reactor coolant pump(s) stopped.
Procedure Step 1 of 1-AP-33.2 SAT [ ] UNSAT [ ]
Standards Operator verifies that all RCPs are running and applies RNO step to trip the reactor.
Simulation Cue(s) All reactor coolant pumps are currently running.
Notes/Comments 2
Go to 1-E-0 while continuing with this procedure.
Procedure Step 1 RNO a of 1-AP-33.2 RNO Critical Step SAT [ ] UNSAT [ ]
Standards Reactor trip switches on benchboard 1-1 and/or 1-2 momentarily placed in the TRIP position Simulation Cue(s) Reactor trip breakers have green lights LIT and red lights NOT lit.
Notes/Comments
NAPS 2016 NRC EXAM SIM JPM C Page: 6 of 12 3
Verify reactor tripped.
Procedure Step 1 of 1-E-0 SAT [ ] UNSAT [ ]
Standards Operator verifies reactor is tripped (RTBs open, rod bottom lights on, flux decreasing).
Notes/Comments 4
Verify turbine trip Procedure Step 2 of 1-E-0 Standards Operator verifies turbine stop valves closed, resets Reheater FCVs, and verifies G-12 open (30 sec TD).
Notes/Comments 5
Verify both ac emergency busses energized - yes.
Procedure Step 3 of 1-E-0 SAT [ ] UNSAT [ ]
Standards Verifies 1H and 1J busses both energized by observing volt meters on 1H and 1J EDG control panels.
Notes/Comments
NAPS 2016 NRC EXAM SIM JPM C Page: 7 of 12 6
Check if SI is actuated Procedure Step 4 of 1-E-0 SAT [ ] UNSAT [ ]
Standards Checks low head pumps running-NO.
Any first out annunciator lit - NO.
Performance Cue(s)
Additional crew members will continue with 1-E-0. The Unit Supervisor directs you to continue performance of 1-AP-33.2.
Simulation Cue(s) Additional crew members will continue with 1-E-0. The Unit Supervisor directs you to continue performance of 1-AP-33.2.
Notes/Comments 7
Stop the affected reactor coolant pump(s).
Procedure Step 1.RNO b of 1-AP-33.2 Critical Step SAT [ ] UNSAT [ ]
Standards Control switch for reactor coolant pump 1C is placed in AUTO-AFTER-STOP or PULL-TO-LOCK.
Simulation Cue(s) Reactor coolant pump 1C indicates stopped.
Notes/Comments
NAPS 2016 NRC EXAM SIM JPM C Page: 8 of 12 8
Close the affected reactor coolant pump's spray valve.
Procedure Step 1.RNO c of 1-AP-33.2 Critical Step SAT [ ] UNSAT [ ]
Standards Controller for 1-RC-PCV-1455B is placed in MANUAL and the lower push-button is momentarily depressed until the controller output indicates zero.
Notes/Comments 9
Check A or B RCP affected - NO Procedure Step 2 of 1-AP-33.2 Standards Operator proceeds to step 3.
Notes/Comments 10 Verify RCP seal cooling isolated - Check C RCP affected Procedure Step 3.a of 1-AP-33.2 Standards Operator checks C RCP affected Notes/Comments
NAPS 2016 NRC EXAM SIM JPM C Page: 9 of 12 11 Close 1-CH-MOV-1381 - NO. (alternate path step - valve open and cannot be closed)
Procedure Step 3.b of 1-AP-33.2 SAT [ ] UNSAT [ ]
Standards Operator recognizes that 1-CH-MOV-1381 is still open (after momentarily depressing close pushbutton) and applies RNO to close 1-CH-MOV-1380.
Simulation Cue(s) Reactor coolant pump seal water return valve, 1-CH-MOV-1381, is open.
Notes/Comments Valve is open and will not close requiring operator to take action and close alternative valve 1-CH-MOV-1380.
12 Close reactor coolant pump seal water return valve 1-CH-MOV-1380. (alternate path step)
Procedure Step 3.b RNO of 1-AP-33.2 Critical Step SAT [ ] UNSAT [ ]
Standards Close push-button for reactor coolant pump seal water return valve, 1-CH-MOV-1380, is momentarily depressed.
Simulation Cue(s) Reactor coolant pump seal water return valve, 1-CH-MOV-1380, is closed.
Notes/Comments
NAPS 2016 NRC EXAM SIM JPM C Page: 10 of 12 13 Request an auxiliary building qualified operator to close the affected reactor coolant pump's seal injection isolation valve, 1-CH-310.
Procedure Step 3.c of 1-AP-33.2 SAT [ ] UNSAT [ ]
Standards Operator requests an auxiliary operator to close 1-CH-310.
Simulation Cue(s) 1C reactor coolant pump's seal injection isolation valve, 1-CH-310, is closed.
Notes/Comments 14 Close the affected reactor coolant pump's thermal barrier trip valves.
Procedure Step 3.d of 1-AP-33.2 SAT [ ] UNSAT [ ]
Standards Operator verifies that 1-CC-TV-116C, 1C RCP thermal barrier CC return valve, is closed.
Simulation Cue(s) 1C RCP thermal barrier CC return valve, 1-CC-TV-116C, is closed.
Notes/Comments
NAPS 2016 NRC EXAM SIM JPM C Page: 11 of 12 15 Verify that the Component Cooling Water System is in service.
Procedure Step 4 of 1-AP-33.2 SAT [ ] UNSAT [ ]
Standards Operator verifies that Component Cooling Water is in service.
Simulation Cue(s) The Component Cooling Water System is in service.
Notes/Comments 16 Determine if natural circulation cooldown is required.
Procedure Step 5 of 1-AP-33.2 SAT [ ] UNSAT [ ]
Standards Operator determines that natural circulation is NOT required since RCPs are running. Applies RNO step a go to 1-OP-3.2.
Performance Cue(s)
As Unit Supervisor acknowledge procedure transition requirement and completion of 1-AP-33.2, inform operator that this completes the JPM.
Simulation Cue(s) Two reactor coolant pumps are in operation.
Simulation Cue(s) As Unit Supervisor acknowledge procedure transition requirement and completion of 1-AP-33.2, inform operator that this completes the JPM.
Notes/Comments END OF EVALUATION STOP TIME
NAPS 2016 NRC EXAM SIM JPM C Page: 12 of 12 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)
SIMULATOR SETUP JOB PERFORMANCE MEASURE R724 TASK Respond to a loss of reactor coolant pump seal cooling (1-AP-33.2).
CHECKLIST
_____ Recall IC #333
_____ Do Simspray and check recorders Respond as Auxiliary Building operator to close affected RCP Seal injection Isolation valve (1-CH-310) when directed by operator.
NUMBER 1-AP-33.2 PROCEDURE TITLE LOSS OF RCP SEAL COOLING REVISION 11 PAGE 2 of 4 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: Affected RCP seal cooling must be isolated and remain isolated until the RCS is cooled down to less than 200°F.
- 1. ___ VERIFY AFFECTED RCPS -
STOPPED Do the following:
a) GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION, while continuing with this procedure.
b) Stop affected RCPs.
c) Close affected RCPs spray valve:
- 1-RC-PCV-1455A for 1-RC-P-1A
- 1-RC-PCV-1455B for 1-RC-P-1C NOTE: When the Seal Return valve is closed, then the Shaft Seal Hi Pressure Annunciator and PCS alarms are expected, as seal cavity pressures equalize to RCS pressure.
GO TO Step 3.
a) Verify loop flow for affected pump indicates RCP is stopped
a) WHEN the RCP indicates stopped, THEN proceed with Step 2.b.
b) Close affected RCP Seal Leakoff valve:
- 1-CH-HCV-1303A for 1-RC-P-1A
- 1-CH-HCV-1303B for 1-RC-P-1B b)
NUMBER 1-AP-33.2 PROCEDURE TITLE LOSS OF RCP SEAL COOLING REVISION 11 PAGE 3 of 4 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. ___ VERIFY RCP SEAL COOLING -
ISOLATED:
a) Check C RCP - AFFECTED
a) GO TO Step 3.c.
b) Close 1-CH-MOV-1381, SEAL WATER RETURN OUTSIDE MOV
b) IF 1-CH-MOV-1381 cannot be closed, THEN close 1-CH-MOV-1380.
IF neither 1-CH-MOV-1381 or 1-CH-MOV-1380 can be closed electrically, THEN locally close 1-CH-MOV-1381.
c) Affected RCP Seal Injection Isolation Valves - CLOSED:
c) Locally close valves.
- 1-CH-310, 1C RCP Seal Injection Header Inlet Isol Valve d) Affected RCP Thermal Barrier CC Return Valve(s) - CLOSED:
d) Close valves.
- 1-CC-TV-116A
- 1-CC-TV-116B
- 1-CC-TV-116C
- 4. ___ VERIFY CC SYSTEM - IN SERVICE
Initiate 1-AP-15, LOSS OF COMPONENT COOLING.
NUMBER 1-AP-33.2 PROCEDURE TITLE LOSS OF RCP SEAL COOLING REVISION 11 PAGE 4 of 4 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:
- Affected RCP(s) should not be run before seal package inspection is completed.
- Affected RCP seals must be disassembled and inspected upon safe plant shutdown and cooldown.
- 5. ___ DETERMINE IF NATURAL CIRCULATION COOLDOWN IS REQUIRED:
a) No RCPs - AVAILABLE a) GO TO appropriate procedure:
- 1-OP-3.2, UNIT SHUTDOWN FROM MODE 3 TO MODE 4 OR
- 1-OP-3.3, UNIT SHUTDOWN FROM MODE 4 TO MODE 5
b) GO TO 1-ES-0.2A, NATURAL CIRCULATION COOLDOWN WITH CRDM FANS
- 6. ___ RETURN TO PROCEDURE AND STEP IN EFFECT
- END -
NUMBER 1-E-0 PROCEDURE TITLE REACTOR TRIP OR SAFETY INJECTION REVISION 49 PAGE 2 of 21 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
[ 1 ] ___ VERIFY REACTOR TRIP:
a) Manually Trip Reactor
IF Reactor will NOT trip, THEN GO TO 1-FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, STEP 1.
b) Check the following:
- Reactor Trip and Bypass Breakers -
OPEN
- Rod Bottom Lights - LIT
- Neutron flux - LOWERING
[ 2 ] ___ VERIFY TURBINE TRIP:
a) Manually Trip Turbine a)
b) Verify all Turbine Stop Valves - CLOSED
IF Turbine is still NOT tripped, THEN manually run back Turbine.
IF Turbine cannot be run back, THEN close Main Steamline Valves:
- ALL MSTVs
- ALL MSTV Bypass Valves
c) Reset Reheaters c)
d) Reduce Reheater Control Manual valve positioner to Zero.
e) Verify Generator Output Breaker - OPEN
e) IF Generator Output Breaker does NOT open after 30 seconds, THEN manually open G-12 AND Exciter Field Breaker.
NUMBER 1-E-0 PROCEDURE TITLE REACTOR TRIP OR SAFETY INJECTION REVISION 49 PAGE 3 of 21 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
[ 3 ] ___ VERIFY BOTH AC EMERGENCY BUSSES - ENERGIZED Do the following:
a) IF no AC Emergency Bus is energized, THEN immediately restore power to at least one AC Emergency Bus.
IF power cannot be restored, THEN GO TO 1-ECA-0.0, LOSS OF ALL AC POWER, STEP 1.
b) Try to restore power to de-energized AC Emergency Bus using 0-AP-10, LOSS OF ELECTRICAL POWER, as time permits.
Continue with Step 4.
NUMBER 1-E-0 PROCEDURE TITLE REACTOR TRIP OR SAFETY INJECTION REVISION 49 PAGE 4 of 21 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
[ 4 ] ___ CHECK SI STATUS:
a) Check if SI is actuated:
- Any SI First-Out Annunciator - LIT a) Check if SI is required or imminent as indicated by any of the following:
- Low PRZR pressure
- High Containment pressure
- Steamline differential pressure
- High steamflow with either:
- Lo-Lo Tave OR
- Low steam pressure
IF SI required, THEN GO TO Step 4b.
IF SI is NOT required, THEN GO TO 1-ES-0.1, REACTOR TRIP RESPONSE, STEP 1.
b) Manually actuate SI
- 5. ___ INITIATE ATTACHMENT 4, EQUIPMENT VERIFICATION, WHILE CONTINUING WITH THIS PROCEDURE
Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit is stable at 100% power Annunciator window 1-AR-9 (1J-D8) ACCUM 1A-1B-1C HI-LO PRESS is illuminated Pressure in safety injection accumulator 1-SI-TK-1C is < 600 psig The nitrogen system is not aligned to supply the PORV N2 accumulators Equipment status has been reviewed and supports the performance of this procedure The outsides operator has verified an adequate source of nitrogen is available and has started the nitrogen system pump INITIATING CUE You are requested to increase pressure in safety injection accumulator 1-SI-TK-1C to between 630 and 640 psig in accordance with 1-OP-7.3, "Filling, Draining, Pressurizing, and Venting SI Accumulators."
2016 NRC EXAM SIM JPM D Page: 2 of 10 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM R589 TASK Pressurize a safety injection accumulator (1-OP-7.3).
TASK STANDARDS Specified accumulator was pressurized with nitrogen Task was performed as directed by the procedure referenced in the task statement within parentheses (one of the underlined procedures if several are cited)
K/A
REFERENCE:
006A4.07 (4.4/4.4)
ALTERNATE PATH:
N/A TASK COMPLETION TIMES Validation Time =
15 Start Time = _______
Actual Time = _______ minutes Stop Time = _______
PERFORMANCE EVALUATION Rating
[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date EVALUATOR'S COMMENTS
2016 NRC EXAM SIM JPM D Page: 3 of 10
2016 NRC EXAM SIM JPM D Page: 4 of 10 Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)
OPERATOR PROGRAM R589 READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
PREREQUISITES The trainee has completed the applicable course knowledge training at the Reactor Operator level.
INITIAL CONDITIONS Unit is stable at 100% power Annunciator window 1-AR-9 (1J-D8) ACCUM 1A-1B-1C HI-LO PRESS is illuminated Pressure in safety injection accumulator 1-SI-TK-1C is < 600 psig The nitrogen system is not aligned to supply the PORV N2 accumulators Equipment status has been reviewed and supports the performance of this procedure
2016 NRC EXAM SIM JPM D Page: 5 of 10 The outsides operator has verified an adequate source of nitrogen is available and has started the nitrogen system pump INITIATING CUE You are requested to increase pressure in safety injection accumulator 1-SI-TK-1C to between 630 and 640 psig in accordance with 1-OP-7.3, "Filling, Draining, Pressurizing, and Venting SI Accumulators."
EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))
Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))
TOOLS AND EQUIPMENT None PERFORMANCE STEPS START TIME
2016 NRC EXAM SIM JPM D Page: 6 of 10 1
Verify that initial conditions are satisfied.
Procedure Step 5.4.1 SAT [ ] UNSAT [ ]
Standards Initial conditions are verified to be satisfied Performance Cue(s)
If asked: RWST boron concentration is 2700 ppm Simulation Cue(s) If asked: RWST boron concentration is 2700 ppm Notes/Comments 2
Review precautions and limitations.
Procedure Step 5.4.2 SAT [ ] UNSAT [ ]
Standards Precautions and limitations have been reviewed Notes/Comments 3
Place 1-SI-HIC-100 at zero percent output.
Procedure Step 5.4.3 SAT [ ] UNSAT [ ]
Standards 1-SI-HIC-100 output is decreased to zero Notes/Comments
2016 NRC EXAM SIM JPM D Page: 7 of 10 4
Open 1-SI-TV-100.
Procedure Step 5.4.4 Critical Step SAT [ ] UNSAT [ ]
NOTE TO THE EVALUATOR Must press open buttons on both panels simultaneously for 1-SI-TV-100 to open Standards 1-SI-TV-100 is opened Performance Cue(s)
If asked: The outsides operator reports the nitrogen system pump is running.
Simulation Cue(s) If asked: The outsides operator reports the nitrogen system pump is running.
Must press open buttons on both panels for 1-SI-TV-100 Notes/Comments
2016 NRC EXAM SIM JPM D Page: 8 of 10 5
Slowly increase the output of 1-SI-HIC-100 to pressurize the accumulator supply header Procedure Step 5.4.5 Critical Step SAT [ ] UNSAT [ ]
Standards Output on 1-SI-HIC-100 is raised above 0%
Performance Cue(s)
If asked: The outsides operator reports the nitrogen system pump is running.
If asked: US desires 100% output on 1-SI-HIC-100 Simulation Cue(s) If asked: The outsides operator reports the nitrogen system pump is running.
If asked: US desires 100% output on 1-SI-HIC-100 Notes/Comments 6
Open N2 valve for the desired accumulator SI-HCV-1853C.
Procedure Step 5.4.6 Critical Step SAT [ ] UNSAT [ ]
Standards 1-SI-HCV-1853C is opened and pressure in 1-SI-TK-1C is increasing Simulation Cue(s)
Notes/Comments
2016 NRC EXAM SIM JPM D Page: 9 of 10 7
When the desired pressure has been reached, then do the following:
Close 1-SI-HCV-1853C, the nitrogen supply valve to accumulator 1-SI-TK-1C.
Close nitrogen supply trip valve 1-SI-TV-100.
Increase the output of 1-SI-HIC-100 to 100%.
Procedure Step 5.4.7 Critical Step SAT [ ] UNSAT [ ]
Standards 1-SI-HCV-1853C is closed Standards Pressure in 1-SI-TK-1C has stopped increasing Performance Cue(s)
After accumulator pressure has been verified to be increasing:
Use pen to indicate that pressure is between 630 and 640 psig on both "C" accumulator pressure indicators.
(If asked: PCS indication is 635 psig)
If needed: US requires you to return the accumulator nitrogen lineup to normal Notes/Comments
>>>>> END OF EVALUATION <<<<<
STOP TIME
2016 NRC EXAM SIM JPM D Page: 10 of 10 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)
SIMULATOR SETUP JOB PERFORMANCE MEASURE R589 TASK Pressurize a safety injection accumulator (1-OP-7.3).
CHECKLIST Recall 100% power IC #334 Slowly reduce pressure in "C" accumulator using tanksnstuff until J-D8 is illuminated
(~1178 LM)
Place simulator in freeze
DOMINION 1-OP-7.3 North Anna Power Station Revision 52 Page 28 of 64 5.4 Pressurizing Safety Injection Accumulators 5.4.1 Verify Initial Conditions are satisfied.
5.4.2 Review Precautions and Limitations.
5.4.3 Place 1-SI-HIC-100, CONTAINMENT NITROGEN SUPPLY HEADER, at zero percent output.
NOTE: Liquid Nitrogen system pump should be started prior to initiating Nitrogen flow.
NOTE: To open 1-SI-TV-100, the pushbuttons on both the H Safeguards Panel (1-SI-TV-100A) AND the J Safeguards Panel (1-SI-TV-100B) must be used.
5.4.4 Open 1-SI-TV-100, NITROGEN SUPPLY TO CONTAINMENT.
5.4.5 Slowly increase the output of 1-SI-HIC-100 to pressurize the accumulator supply header.
DOMINION 1-OP-7.3 North Anna Power Station Revision 52 Page 29 of 64 NOTE: WHEN a significant increase in pressure is made to the SI Accumulators, THEN a noticeable decrease in level indication may be expected. This is a result of the new design and placement of Accumulator level transmitters by DCP 94-016, SI Accumulator Level Transmitter Replacement.
5.4.6 Open N2 valve for desired Accumulator (only 1 valve is allowed open at a time):
- IF 1-SI-TK-1A is to be pressurized, THEN open 1-SI-HCV-1853A, A SI ACCUMULATOR N2 SUPPLY VALVE.
- IF 1-SI-TK-1B is to be pressurized, THEN open 1-SI-HCV-1853B, B SI ACCUMULATOR N2 SUPPLY VALVE.
- IF 1-SI-TK-1C is to be pressurized, THEN open 1-SI-HCV-1853C, C SI ACCUMULATOR N2 SUPPLY VALVE.
NOTE: Maximum accumulator pressure is 667 psig.
5.4.7 WHEN the desired pressure has been reached, THEN do the following:
a.
IF the N2 System is aligned to supply the PORV N2 accumulators, THEN place 1-SI-HIC-100 at zero percent output.
CAUTION Do not cross-connect the accumulator gas spaces in Mode 3 or above. During a large break LOCA, nitrogen pressure in the cross-connected SI accumulator could bleed off through the faulted loop accumulator. As a result, the nitrogen pressure in the cross-connected accumulator may be less than that assumed in the Accident Analysis. (References 2.4.3 and 2.4.4)
DOMINION 1-OP-7.3 North Anna Power Station Revision 52 Page 30 of 64 b.
Do the following for the Accumulator just pressurized:
IV
- IF 1-SI-TK-1A was just pressurized, THEN close 1-SI-HCV-1853A, A SI ACCUMULATOR N2 SUPPLY VALVE.
IV
- IF 1-SI-TK-1B was just pressurized, THEN close 1-SI-HCV-1853B, B SI ACCUMULATOR N2 SUPPLY VALVE.
IV
- IF 1-SI-TK-1C was just pressurized, THEN close 1-SI-HCV-1853C, C SI ACCUMULATOR N2 SUPPLY VALVE.
c.
IF desired to pressurize another accumulator, THEN return to Step 5.4.5.
NOTE: To close 1-SI-TV-100, the pushbutton on either the H Safeguards Panel (1-SI-TV-100A) or the J Safeguards Panel (1-SI-TV-100B) may be used. If desired, both pushbuttons may be used.
d.
IF the Nitrogen System is NOT aligned to supply the PORV N2 accumulators, THEN close 1-SI-TV-100, NITROGEN SUPPLY TO CONTAINMENT.
e.
IF the N2 System is NOT aligned to supply the PORV N2 accumulators, THEN increase the output of 1-SI-HIC-100 to 100 percent.
Completed by: ___________________________________________ Date: _________
Dominion North Anna Power Station LICENSED OPERATOR REQUALIFICATION PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS The unit is at 100% power INITIATING CUE You are requested to respond to plant conditions and perform any applicable immediate operator actions
2016 NRC EXAM SIM JPM E Page: 2 of 6 Dominion North Anna Power Station LICENSED OPERATOR REQUALIFICATION PROGRAM JOB PERFORMANCE MEASURE R675 / 13341 TASK Respond to a failure of main generator voltage regulator high (1-AP-26).
TASK STANDARDS Voltage regulator was turned off and reactor was manually tripped K/A
REFERENCE:
077AA1.03 (3.8/3.7)
ALTERNATE-PATH TOPIC BASE ADJUST switch fails to operate requiring unit trip TASK COMPLETION TIMES Validation Time =
4 minutes Start Time = _______
Actual Time = _______ minutes Stop Time = _______
PERFORMANCE EVALUATION Rating
[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date EVALUATOR'S COMMENTS
2016 NRC EXAM SIM JPM E Page: 3 of 6 Dominion North Anna Power Station LICENSED OPERATOR REQUALIFICATION PROGRAM JOB PERFORMANCE MEASURE R675 / 13341 READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS The unit is at 100% power INITIATING CUE You are requested to respond to plant conditions and perform any applicable immediate operator actions EVALUATION METHOD Perform if conducted in the simulator or in the electrical laboratory (use Performance Cue(s))
Simulate if conducted in the station (use Simulation Cue(s))
TOOLS AND EQUIPMENT None PERFORMANCE STEPS START TIME
2016 NRC EXAM SIM JPM E Page: 4 of 6 1
Check the status of the main generator.
Procedure Step 1 SAT [ ] UNSAT [ ]
Standards Main generator output voltage and MVARs are verified increasing, and generator MW is verified stable Simulation Cue(s) Main generator voltage is slowly going up Simulation Cue(s) Megawatts are stable Simulation Cue(s) MVARs are slowing going to the outside Notes/Comments 2
Turn the voltage regulator switch to OFF.
Procedure Step 2 SAT [ ] UNSAT [ ]
Standards Voltage regulator control switch is placed in OFF Simulation Cue(s) Main generator output voltage is stable at 22.5 KV, reactive load is 230 MVARSs IN (or use pen to show)
Notes/Comments Will cause damage to main generator components if no action taken.
2016 NRC EXAM SIM JPM E Page: 5 of 6 3
Adjust the main generator's output voltage into the normal range using the base adjust switch.
Procedure Step 3 SAT [ ] UNSAT [ ]
Standards Base adjust switch is placed in the RAISE position and reactive load is verified to remain greater than 200 MVARs IN (alt path - MVARS cannot be raised above 200 MVARS IN)
Simulation Cue(s) Before adjustment: Reactive load is 230 MVARS IN After adjustment: Reactive load has remained 230 MVARS IN Notes/Comments 4
Go to 1-E-0.
Procedure Step 3 RNO a CRITICAL STEP SAT [ ] UNSAT [ ]
Standards Reactor trip switches on benchboard 1-1 and/or 1-2 are in the TRIP position Performance Cue(s)
Assume that another operator is continuing with E-0 Simulation Cue(s) Assume that another operator is continuing with E-0 Notes/Comments Will cause damage to main generator components if no action taken.
>>>>> END OF EVALUATION <<<<<
STOP TIME
2016 NRC EXAM SIM JPM E Page: 6 of 6 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)
SIMULATOR SETUP JOB PERFORMANCE MEASURE R675 / 13341 NORMAL TASK Respond to a failure of main generator voltage regulator high (1-AP-26).
ALTERNATE-PATH TOPIC BASE ADJUST switch fails to operate CHECKLIST
_____ Recall IC (100% power) (IC 335)
_____ Place simulator in RUN
_____ Do the following to ensure reactive load decreases to greater than 200 MVARs IN when voltage regulator is placed in OFF (ensures step 3 is critical):
Lower voltage using voltage regulator until reactive load is 150 MVARS IN Meter override (GM): Generator MVAR = 0.3, Ramp = 5, Trigger = 2 Set up Trigger 2 on trigger screen as VOLT_REG_OFF==1
_____ Switch override: V REG_BAS1_OFF = ON, V_REG_BAS1_RAISE = OFF, V_REG_BAS@_LOWER = OFF
_____ Enter malfunction EL09, trigger = 1, delay time = 0, ramp = 70, severity = 35 NOTE: Tested to be sure reactor would not trip if operator did not do actions. Will cause damage to main generator components if no action taken.
NUMBER 1-AP-26 PROCEDURE TITLE FAILURE OF MAIN GENERATOR VOLTAGE REGULATOR HIGH REVISION 12 PAGE 2 of 3 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: IF unsure of conditions, THEN leave the Voltage Regulator in Auto.
[ 1 ] ___ CHECK GENERATOR STATUS:
Do the following:
- Sustained Generator output voltage increase with MVAR increase AND
- Contact System Operator
- Return to procedure and step in effect
- MW stable
[ 2 ] ___ TURN VOLTAGE REGULATOR CONTROL SWITCH TO OFF
[ 3 ] ___ ADJUST GENERATOR VOLTAGE USING THE VOLTAGE REGULATOR BASE ADJUST SWITCH:
- GENERATOR OUTPUT VOLTAGE - NORMAL RANGE
a) IF Reactor power is greater than or equal to 30%, THEN GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION.
b) IF Reactor power is less than 30%, THEN Trip Turbine and GO TO 1-AP-2.1, TURBINE TRIP WITHOUT REACTOR TRIP REQUIRED.
NUMBER 1-E-0 PROCEDURE TITLE REACTOR TRIP OR SAFETY INJECTION REVISION 49 PAGE 2 of 21 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
[ 1 ] ___ VERIFY REACTOR TRIP:
a) Manually Trip Reactor
IF Reactor will NOT trip, THEN GO TO 1-FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, STEP 1.
b) Check the following:
- Reactor Trip and Bypass Breakers -
OPEN
- Rod Bottom Lights - LIT
- Neutron flux - LOWERING
[ 2 ] ___ VERIFY TURBINE TRIP:
a) Manually Trip Turbine a)
b) Verify all Turbine Stop Valves - CLOSED
IF Turbine is still NOT tripped, THEN manually run back Turbine.
IF Turbine cannot be run back, THEN close Main Steamline Valves:
- ALL MSTVs
- ALL MSTV Bypass Valves
c) Reset Reheaters c)
d) Reduce Reheater Control Manual valve positioner to Zero.
e) Verify Generator Output Breaker - OPEN
e) IF Generator Output Breaker does NOT open after 30 seconds, THEN manually open G-12 AND Exciter Field Breaker.
Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Rated thermal power is stable at 100%
Daily feedwater flow calorimetric heat balance is required to be performed Unit-1 PCS is operable All Nuclear Instruments (NIs) are operable 1-PT-24.1, CALORIMETRIC HEAT BALANCE (COMPUTER CALCULATION), has been completed up to the point of adjusting power range NIs INITIATING CUE You are requested to adjust the power-range NIs in accordance with 1-PT-24.1.
2016 NRC EXAM SIM JPM F Page: 2 of 11 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM R710 TASK Adjust the power-range NIs (1-PT-24.1).
TASK STANDARDS Task was performed as directed by the procedure referenced in the task statement within parentheses (one of the underlined procedures if several are cited)
K/A
REFERENCE:
015A1.01 (3.5/3.8)
ALTERNATE PATH:
Control rods step uncontrollably when placed in auto requiring operator action TASK COMPLETION TIMES Validation Time =
20 minutes Start Time = _______
Actual Time = _______ minutes Stop Time = _______
PERFORMANCE EVALUATION Rating
[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date EVALUATOR'S COMMENTS
2016 NRC EXAM SIM JPM F Page: 3 of 11
2016 NRC EXAM SIM JPM F Page: 4 of 11 Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)
OPERATOR PROGRAM R710 READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
PREREQUISITES The trainee has completed the applicable course knowledge training at the Reactor Operator level.
INITIAL CONDITIONS Rated thermal power is stable at 100%
Daily feedwater flow calorimetric heat balance is required to be performed Unit-1 PCS is operable All Nuclear Instruments (NIs) are operable 1-PT-24.1, CALORIMETRIC HEAT BALANCE (COMPUTER CALCULATION), has been completed up to the point of adjusting power range NIs
2016 NRC EXAM SIM JPM F Page: 5 of 11 INITIATING CUE You are requested to adjust the power-range NIs in accordance with 1-PT-24.1.
EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))
Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))
TOOLS AND EQUIPMENT None PERFORMANCE STEPS START TIME 1
IF the Power Range NI channels are within 2 percent of the Power, Calorimetric (U0980) AND the SRO has directed that adjustments be made, THEN adjust the channels as directed using Attachment
- 3.
Procedure Step 6.2.3 SAT [ ] UNSAT [ ]
Performance Cue(s)
N-44 adjustment is desired Notes/Comments
2016 NRC EXAM SIM JPM F Page: 6 of 11 2
Review steps 1-9 of attachment 3 Procedure Step Att 3: 1 - 9 SAT [ ] UNSAT [ ]
Standards Steps 1 through 9 are reviewed Notes/Comments Steps 1-6 of Attachment 3 are instructions on how to perform the attachment. Steps 7-9 will be marked N/A due to the conditions of the JPM 3
Verify that no trip signals are present on the NI power-range channels.
Procedure Step Att 3: 10 SAT [ ] UNSAT [ ]
Standards NIs and/or status lights are checked to verify no trip signals Notes/Comments Step 11 will be N/A as noted in initial JPM conditions
2016 NRC EXAM SIM JPM F Page: 7 of 11 4
IF adjusting Channel N44, THEN place the following equipment in MANUAL control:
- Bypass Feedwater Regulating Valves
- Rod Control System Procedure Step Att 3: 12 SAT [ ] UNSAT [ ]
Standards Bypass feedwater regulating valves are verified in manual and the Rod Control System is placed in MANUAL Notes/Comments 5
Check present NI readings have not changed significantly (Approximately 0.5 %) from the As Found NI readings on.
Procedure Step Att 3: 13.1 & 13.2 SAT [ ] UNSAT [ ]
Standards NIs are verified within 0.5% of the as-found indications Notes/Comments Step 13.2 is N/A
2016 NRC EXAM SIM JPM F Page: 8 of 11 6
IF sufficient adjustments can be made, THEN individually adjust the gain potentiometer on the front panel of each Power Range NI channel to within 2 percent of the Power, Calorimetric (U0980).
Procedure Step Att 3: 13.3 SAT [ ] UNSAT [ ]
Standards Gain potentiometer for N-44 is increased to match the calorimetric Notes/Comments Step 13.4 and step 14 are N/A 7
IF Channel N44 was adjusted, THEN wait at least 1 minute before returning the equipment listed in Step 12 to AUTO control.
Procedure Step Att 3: 15 SAT [ ] UNSAT [ ]
Standards Rod Control System is placed in AUTO Performance Cue(s)
If asked: It is desired to place rod control in AUTO Notes/Comments Alt path - Rods will insert when rod control switch is placed in AUTO requiring entry into 1-AP-1.1
2016 NRC EXAM SIM JPM F Page: 9 of 11 8
Put Control Rod Bank Selector switch to MANUAL Procedure Step AP-1.1: 1 SAT [ ] UNSAT [ ]
Standards Rod Control System is placed in MANUAL Notes/Comments 9
Verify Rod motion - STOPPED - NO Procedure Step AP-1.1: 2 SAT [ ] UNSAT [ ]
Standards Rods motion is noted to not be stopped and the operator transitions to 1-E-0 Notes/Comments
2016 NRC EXAM SIM JPM F Page: 10 of 11 10 Perform Immediate Actions of 1-E-0 Procedure Step 1-E-0 CRITICAL STEP SAT [ ] UNSAT [ ]
Standards Reactor trip switches on benchboard 1-1 and/or 1-2 are momentarily placed in the TRIP position Performance Cue(s)
Assume that another operator is continuing with E-0 Notes/Comments
>>>>> END OF EVALUATION <<<<<
STOP TIME
2016 NRC EXAM SIM JPM F Page: 11 of 11 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)
DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 6 of 25 Init Verif 3.0 INITIAL CONDITIONS 3.1 Check the Unit 1 PCS Calorimetric Program is operable. IF the computer calorimetric program is NOT operable, THEN perform 1-PT-24, Calorimetric Heat Balance (Hand Calculation).
3.2 IF the Unit 1 PCS Calorimetric Program is NOT operable, THEN immediately refer to TRM TR 3.3.10 Condition C.
3.3 IF power exceeds 2893 MWt (98.4 %), THEN one of the following conditions exists:
- Feedwater Ultrasonic Flow Meter Calorimetric is the calorimetric of record.
- The Action Statement of TRM 3.3.10, Condition A has been entered.
3.4 IF power is less than or equal to 2893 MWt (98.4 %), THEN one of the following conditions exists:
- Feedwater Ultrasonic Flow Meter Calorimetric is the calorimetric of record.
- An Info Action Statement of TRM 3.3.10 has been entered to prevent raising power above 2893 MWt (98.4 %) until TSR 3.3.10.1 is met.
NOTE: Performance of this procedure is not required until Thermal Power has been greater than or equal to 15 % RTP for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3.5 Check Unit 1 is stable at greater than or equal to 15 percent Rated Thermal Power.
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DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 7 of 25 4.0 PRECAUTIONS AND LIMITATIONS 4.1 Comply with the following guidelines when marking steps N/A:
- IF the conditional requirements of a step do not require the action to be performed, THEN mark the step N/A.
- IF this test is being performed as a Post-Maintenance Test, THEN mark inappropriate steps N/A.
- IF any other step is marked N/A, THEN have the SRO (or designee) approve the N/A and submit a Procedure Action Request (PAR).
4.2 The average power level over any 12-hour shift MUST NOT exceed 2940 MW (100 percent of Rated Thermal Power) based on a Feedwater Ultrasonic Flow Meter Calorimetric.
4.3 Perform this procedure for surveillance purposes between [0300 and 0900] at least once each day, or additionally as required.
4.4 Ensure at least 15 minutes has elapsed since the last reboot of the Unit 1 PCS.
4.5 Error messages for the Unit 1 PCS do NOT appear on the Calorimetric Report. Error messages can be viewed by clicking on the yellow message button. This will bring up all error messages pertaining to Unit 1 PCS applications.
4.6 IF plant conditions change enough to affect the NI indications after the computer calorimetric calculation is performed, THEN adjusting the NIs to the calorimetric power can result in incorrect NI indications. (Reference 2.3.15) 4.7 IF the PCS point for one power range NIS (N0049A, N0050A, N0051A, or N0052A) is suspect (Blue), THEN it may be Deleted From Processing to remove it as an input to the AFD Monitor Alarm. The AFD Monitor Alarm is operable with three operable NIS points inputting into the program. (References 2.4.3 and 2.4.4)
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DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 8 of 25 5.0 SPECIAL TOOLS AND EQUIPMENT None
DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 9 of 25 6.0 INSTRUCTIONS 6.1 Perform Attachment 1, Unit 1 PCS Feed Flow Calorimetric.
6.2 IF Power Range NI channels will be adjusted using a valid Calorimetric Report, THEN do the following:
6.2.1 IF the Feed Flow Calorimetric (Power, Calorimetric U0980) determined on exceeds the Power Range NI channels by more than 2 percent, THEN adjust the affected Power Range NI channels accordingly using, Power Range NI Channel Adjustment.
6.2.2 IF the Power Range NI channels exceed the Feed Flow Calorimetric (Power, Calorimetric U0980) determined on Attachment 1 AND the SRO has directed that adjustments be made, THEN adjust the channels as directed using Attachment 3.
6.2.3 IF the Power Range NI channels are within 2 percent of the Power, Calorimetric (U0980) AND the SRO has directed that adjustments be made, THEN adjust the channels as directed using Attachment 3.
6.3 Record the AS LEFT NI INDICATED REACTOR POWER and the AS LEFT GAIN POTENTIOMETER SETTING for each channel on Attachment 2, Power Range Channel Indication.
6.4 Attach the Calorimetric Report(s) to this procedure.
6.5 IF the Feedwater Ultrasonic Flow Meter Calorimetric is the calorimetric of record, THEN ensure that the Normalized Feedwater Venturi calorimetric normalization factors are being updated or appropriate compensatory actions are being taken:
(Reference 2.4.7) 6.5.1 On Unit 1 PCS, display all points in CALAUTO group by typing SHOW CALAUTO in the upper yellow bar and press ENTER.
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DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 10 of 25 6.5.2 IF any Unit 1 PCS Point Group CALAUTO Calorimetric AUTO/MAN switches are in MAN, THEN do the following:
a.
Declare the Normalized Feedwater Venturi calorimetric non-functional until the AUTO/MAN switches are returned to AUTO status.
b.
Notify Reactor Engineering or the STA to refer to 1-OP-31.24, Changing the Calorimetric of Record, to place the AUTO/MAN switches to AUTO.
6.6 IF the Feedwater Venturi Calorimetric or the Normalized Feedwater Venturi Calorimetric is the calorimetric of record, THEN do the following:
(Reference 2.4.7) 6.6.1 On Unit 1 PCS, display all points in CALAUTO group by typing SHOW CALAUTO in the upper yellow bar and press ENTER.
6.6.2 IF any Unit 1 PCS Point Group CALAUTO Calorimetric AUTO/MAN switches are NOT in MAN, THEN notify Reactor Engineering to evaluate the configuration of the AUTO/MAN switches and refer to 1-OP-31.24, Changing the Calorimetric of Record, to place the AUTO/MAN switches in the desired configuration.
6.7 Discard attachments not used.
7.0 FOLLOW-ON 7.1 Acceptance Criteria All operable Power Range NI channels were within or adjusted to within the allowed tolerances specified in Step 6.2.
DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 11 of 25 7.2 Follow-On Tasks 7.2.1 IF Step 7.1 CANNOT be satisfied, THEN refer to the Action Statement of Tech Spec 3.3.1 and TRM TR 3.3.10, Feedwater Ultrasonic Flow Meter Calorimetric.
7.2.2 IF Unit 1 PCS is displaying messages concerning the use of the Default Value for Charging/Seal Water/Letdown, THEN ensure a Condition Report or other appropriate action has been initiated.
7.3 Completion Notification Notify the SRO that this test is complete.
Completed by: ___________________________________________ Date: _________
ATTACHMENTS
DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 12 of 25 (Page 1 of 3)
Unit 1 PCS Feed Flow Calorimetric 1.
Check that the desired calorimetric is selected as follows:
1.1 From the CALORIMETRIC MENU screen, check the desired calorimetric is selected.
1.2 IF the desired calorimetric is NOT selected, THEN GO TO 1-OP-31.24, Changing the Calorimetric of Record.
2.
Check the current SG blowdown flows are correct as follows:
2.1 From the CALORIMETRIC MENU screen, select BLOWDOWN FLOW UPDATE.
2.2 Ensure the high capacity blowdown flows are correct.
2.3 Ensure the low capacity blowdown flows are correct.
IV 2.4 IF blowdown flows were changed, THEN have a second qualified operator review the BLOWDOWN FLOW UPDATE screen and check the SG blowdown flows are correct.
3.
On the CALORIMETRIC MENU screen, select PRINT CURRENT DATA and print Calorimetric Report.
4.
Check the Calorimetric Report for any data associated with the Calorimetric of Record that is indicated as NCAL. IF any data on the Calorimetric Report is indicated as NCAL, THEN evaluate and correct using Attachment 5, Unit 1 PCS Calorimetric NCAL And Error Messages.
5.
Click on the message button to see if there are any messages pertaining to the calorimetric. IF there are any messages, THEN take the appropriate action as indicated by the messages and Attachment 5.
6.
IF a valid calorimetric report CANNOT be obtained, THEN, mark the remainder of this attachment N/A and perform 1-PT-24, Calorimetric Heat Balance (Hand Calculation).
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DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 13 of 25 (Page 2 of 3)
Unit 1 PCS Feed Flow Calorimetric 7.
IF a valid Unit 1 PCS Calorimetric Report was obtained, THEN do the following:
IV 7.1 Obtain and record the expected loop power, using the following equation:
0.976735 (U0980) + 2.72 =_____________% (Reference 2.4.1) 7.2 Obtain and record the indicated loop power: _____________% (U0956) 7.3 Record the difference between the expected and the indicated loop power:
_____________% (Reference 2.4.1) 7.4 IF the expected loop power differs from the indicated loop power by more than 3 percent, THEN contact the STA OR Reactor Engineer for resolution before adjusting the Power Range NI Channels. (Reference 2.4.1)
NOTE: Due to the noise level in the feedwater flow signal, the FF/SF ratio may momentarily spike above the nominal indication. The actions in the step below are applicable only when the ratio is actually above 1.06. When the ratio returns to below 1.06, channel operation is satisfactory.
7.5 IF power is above 80 % AND the ratio of feedwater flow to steam flow in any loop exceeds 1.06, THEN perform the following: (Reference 2.3.13) a.
Notify the Reactor Engineer.
b.
Notify the STA.
c.
Enter a Condition Report.
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DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 14 of 25 (Page 3 of 3)
Unit 1 PCS Feed Flow Calorimetric NOTE: IF the PCS point for one power range NIS (N0049A, N0050A, N0051A, or N0052A) is suspect (Blue), THEN it may be Deleted From Processing to remove it as an input to the AFD Monitor Alarm. The AFD Monitor Alarm is operable with 3 operable NIS points inputting into the program.
(References 2.4.3 and 2.4.4) 7.6 Complete Attachment 2, Power Range Channel Indication, except for as left NI Indicated Reactor Power AND as left Gain Potentiometer setting.
7.7 RETURN TO Step 6.2.
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DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 16 of 25 (Page 1 of 5)
Power Range NI Channel Adjustment NOTE: IF Power Range NI Channels were adjusted upward and then must be subsequently adjusted downward, THEN no trip setpoint change is required as long as the adjustment does NOT go below the previous 100 % power gain setting.
1.
Adjust the Power Range NI channels using the following guidelines:
- Adjust one at a time based on the vertical board meter readings.
- A licensed Reactor Operator MUST make the adjustments under the supervision of a licensed Senior Reactor Operator.
- A Qualified Instrument Technician MUST make the coarse adjustments under the supervision of a licensed Senior Reactor Operator.
2.
Because of the sensitivity of the coarse level adjust potentiometer the possibility exists to actuate protection bistables associated with the affected channel. Make coarse adjustments in small increments.
3.
IF Calorimetric Calculation is NOT recent, OR RCS Temperature is NOT on program, THEN consult SRO prior to adjusting NIs.
4.
Uncertainties in the calculated calorimetric power level increase as the reactor power level is reduced below 100 % RTP. This increased uncertainty can be introduced into the Power Range NI channels when they are normalized to the calorimetric power at these power levels. This can potentially cause the NI overpower trip setpoint to be non-conservative if the NI Channels are adjusted downward at these lower power levels. To prevent this from happening, the NI overpower trip and rod stop setpoint may need to be reduced if the NIs are adjusted downward at calculated calorimetric power levels less than 85 % RTP. (References 2.3.6 and 2.4.2) 5.
Previous 100 % power gain setting is defined as the Power Range NI Channel gain setting from the last 100 % power calorimetric.
6.
Reduced power levels is defined as less than 85 % calorimetric power.
DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 17 of 25 (Page 2 of 5)
Power Range NI Channel Adjustment 7.
IF the Unit has operated for less than 7 days at reduced power levels, THEN the previous 100 % power gain setting is the base line for determining if the new Power Range NI Channel gain setting will be considered a downward adjustment.
8.
IF the Unit has operated for greater than 7 days at reduced power levels, THEN contact the Reactor Engineer to determine NI High Flux Trip Setpoints and NI Rod Stop Setpoints.
9.
IF Reactor Power is less than 85 % AND any Power Range NI Channel requires downward adjustment below the previous 100 % power gain setting, THEN adjust the overpower trip and rod stop setpoints for all Power Range NI channels as follows before adjusting any NI downward: (References 2.3.6 and 2.4.2) 9.1 From Attachment 4, Overpower Trip and Rod Stop Downward Adjustment Setpoints, record the appropriate values in the Power Range Section of the Reactor Data Book.
9.2 Notify I & C to install the new setpoints before adjusting NIs downward.
9.3 Make an Abnormal Status Log entry for downward adjustment of overpower trip and rod stop setpoints.
CAUTION IF Power Range NI Channel Overpower Trip and Rod Stop setpoints were previously adjusted at a lower power, THEN a new setpoint should be installed in the following step based on the current calorimetric power level.
DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 18 of 25 (Page 3 of 5)
Power Range NI Channel Adjustment
- 10. Check no trip signals are present for the following Power Range NI channels:
- N41
- N42
- N43
- N44
- 11. IF any Power Range NI channel is inoperable, THEN do the following:
11.1 IF N44 is inoperable, THEN place the following in MANUAL control:
- Bypass Feedwater Regulating Valves
- Rod Control System 11.2 Reinsert the Control Power Fuses for the inoperable channel.
11.3 Place the Selector Switch in the A and B position. (The Selector Switch may be left in the A and B position until the channel is returned to operable status.)
11.4 Adjust the A and B test signal potentiometers to match the other channels.
11.5 Reset the rate alarm.
11.6 Check no trip signal on inoperable channel.
DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 19 of 25 (Page 4 of 5)
Power Range NI Channel Adjustment
- 12. IF adjusting Channel N44, THEN place the following equipment in MANUAL control:
- Bypass Feedwater Regulating Valves
- Rod Control System
- 13. Individually adjust the gain potentiometer of each Power Range NI channel as follows:
13.1 Check present NI readings have not changed significantly (Approximately 0.5 %) from the As Found NI readings on Attachment 2.
13.2 IF readings in Step 13.1 have changed significantly, THEN DO NOT adjust NIs AND recheck stable plant conditions.
13.3 IF sufficient adjustments can be made, THEN individually adjust the gain potentiometer on the front panel of each Power Range NI channel to within 2 percent of the Power, Calorimetric (U0980).
CAUTION
- Rapid adjustment of the gain potentiometer can generate a rate trip signal.
- Because of the sensitivity of the coarse level adjust potentiometer the possibility exists to actuate protection bistables associated with the affected channel. Coarse adjustments should be made in small increments.
DOMINION 1-PT-24.1 North Anna Power Station Revision 34 Page 20 of 25 (Page 5 of 5)
Power Range NI Channel Adjustment 13.4 IF sufficient adjustments cannot be made using the potentiometer on the front panel OR spiking occurs when adjustment is attempted, THEN do the following to adjust the Power Range NI channel using the coarse level adjust potentiometer:
a.
Obtain concurrence for using the coarse level adjust potentiometer as follows:
1.
IF adjustment is necessary due to an inadequate amount of fine gain potentiometer available, THEN obtain concurrence from the Unit 1 SRO.
2.
IF adjustment is necessary due to spiking occurring when gain potentiometer adjustment was attempted, THEN obtain concurrence from the Unit 1 SRO.
b.
Have a qualified Instrument Technician adjust the coarse level adjust potentiometer, R312, and the potentiometer on the front panel until the front panel potentiometer is near mid-range and the Power Range NI channels are within 2 percent of the % RTP.
c.
IF any Power Range NI channel was adjusted using the coarse level adjust potentiometer, THEN note this action on the cover page.
d.
IF the coarse level adjustment was used due to spiking when the gain potentiometer was used, THEN enter a Condition Report for spiking.
e.
Ensure Reactor Engineering is notified that a coarse adjustment has been made to the Unit 1 Power Range Nuclear Instruments. Voice mail or e-mail are acceptable methods of notification.
- 14. IF a Power Range NI channel was inoperable, THEN remove the Control Power Fuses installed in Step 11.2.
- 15. IF Channel N44 was adjusted, THEN wait at least 1 minute before returning the equipment listed in Step 12 to AUTO control.
Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit 1 is at 100%.
Flooding has occurred in the turbine building.
TURB BLD FLOOD ALARM TROUBLE annunciator (1D-G7) has just alarmed.
Circulating Water System rupture has been reported on Unit 1.
Liquid waste discharge is aligned to the Unit 1 discharge tunnel.
INITIATING CUE You are requested to respond to circulating water flooding in the turbine building in accordance with 0-AP-39.1, Turbine Building Flooding.
NAPS 2016 NRC EXAM SIM JPM G Page: 2 of 12 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM 13355 TASK Respond to turbine building flooding with Circulating water pump fails to trip (0-AP-39.1).
TASK STANDARDS All waterbox inlets were closed, 15G10 was defeated, 15G1 was opened, all waterbox outlets were closed, and 1-LW-PCV-115 was placed in HAND.
K/A
REFERENCE:
075A2.03 (2.5/2.7)
ALTERNATE PATH:
Waterbox inlet MOVs fail to close requiring additional actions in response to failure TASK COMPLETION TIMES Validation Time =
13 minutes Start Time = _______
Actual Time = _______ minutes Stop Time = _______
PERFORMANCE EVALUATION Rating
[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date EVALUATOR'S COMMENTS
NAPS 2016 NRC EXAM SIM JPM G Page: 3 of 12 Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)
OPERATOR PROGRAM 13355 READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
PREREQUISITES The trainee has completed the applicable course knowledge training at the reactor operator level INITIAL CONDITIONS Unit 1 is at 100%.
Flooding has occurred in the turbine building.
TURB BLD FLOOD ALARM TROUBLE annunciator (1D-G7) has just alarmed.
Circulating Water System rupture has been reported on Unit 1.
Liquid waste discharge is aligned to the Unit 1 discharge tunnel.
NAPS 2016 NRC EXAM SIM JPM G Page: 4 of 12 INITIATING CUE You are requested to respond to circulating water flooding in the turbine building in accordance with 0-AP-39.1, Turbine Building Flooding.
EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))
Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))
TOOLS AND EQUIPMENT None PERFORMANCE STEPS START TIME Note: Operator will read the following procedure caution and note:
CAUTION: Auxiliary Building flooding could carry over into the Turbine Building through the Service Water Tunnel into the Turbine Building Valve Pit.
NOTE: If a Reactor trip occurs, then, in order to recover the plant from the flooding, this procedure should be performed in conjunction with Emergency Operating Procedures.
1 Identify source of the flooding Procedure Step 1 of 0-AP-39.1 SAT [ ] UNSAT [ ]
Standards Operator initials step and continues with Step 2.
(source, Unit 1 Circ Water, was provided by initial conditions)
Notes/Comments
NAPS 2016 NRC EXAM SIM JPM G Page: 5 of 12 2
Determine if reactor should be tripped - YES.
(based on initial conditions provided - circ water system rupture)
Procedure Step 2.a,b, &c of 0-AP-39.1 SAT [ ] UNSAT [ ]
Standards Reactor trip switch on benchboard 1-1 and or 1-2 momentarily placed in TRIP.
Reheater Reset pushbutton momentarily depressed.
Performance Cue(s)
After immediate operator actions are done: The remaining crew members will perform 1-E-0, you are directed to continue performance of 0-AP-39.1 Notes/Comments 3
Check if Bearing Cooling System status is abnormal - NO.
Procedure Step 3 of 0-AP-39.1 SAT [ ] UNSAT [ ]
Standards Operator goes to RNO column and continues with Step 4.
Notes/Comments This step is intended to initiate additional actions IF the leak were in the bearing cooling (BC) system, based on the initial conditions of the JPM the leak is in the Circ Water System. The candidate may elect to check items such as BC system annunciators, basin level, makeup valve postion, etc. to satisfy themselves, but these actions are not required based on the initial conditions provided.
Note: Operator will read the following procedure note:
NOTE:
- If a G-Bus is de-energized because of a CW system rupture, then a reduced Bearing Lube flow condition could result on the opposite unit. The de-energized bus should be re-energized as soon as possible.
- When the waterbox inlet box valves start to close, then the CW pumps for the affected unit should trip.
NAPS 2016 NRC EXAM SIM JPM G Page: 6 of 12 4
Check CW system abnormal - YES.
Procedure Step 4a of 0-AP-39.1 SAT [ ] UNSAT [ ]
Standards Operator continues to substep 4b based on initial conditions provided.
Notes/Comments 5
Place all Unit 1 circulating water motor-operated valve interlock defeat switches in NORMAL.
Procedure Step 4.b.1 of 0-AP-39.1 SAT [ ] UNSAT [ ]
Standards Circulating water motor-operated valve switches are verified to be in NORMAL Notes/Comments
NAPS 2016 NRC EXAM SIM JPM G Page: 7 of 12 6
Close the following water box inlet motor-operated valves.
1-CW-MOV-101A 1-CW-MOV-101B 1-CW-MOV-101C 1-CW-MOV-101D Procedure Step 4.b.2 of 0-AP-39.1 NOTE TO THE EVALUATOR 1-CW-MOV-101C and 1-CW-MOV101D cannot be closed but will close once the pumps have tripped.
(1-CW MOV-102C and 1-CW MOV-102D will also not close if attempted but will close on subsequent steps)
There is no RNO for this step.
Standards CLOSE push-button is depressed for the following motor-operated valves 1-CW-MOV-101A 1-CW-MOV-101B 1-CW-MOV-101C 1-CW-MOV-101D Notes/Comments
NAPS 2016 NRC EXAM SIM JPM G Page: 8 of 12 7
Verify that the Unit1 Circulating Water pumps are tripped - NO.
(Alternate path step)
Procedure Step 4.b.3 of 0-AP-39.1 SAT [ ] UNSAT [ ]
Standards Operator determines that Unit 1 CW pumps are NOT tripped (by observing breaker indication on Circ Water panel) and implements step 4.b.3) RNO Notes/Comments 8
De-energize the unit-1 "G" bus.
Procedure Step 4.b.3 RNO a,b,&c of 0-AP-39.1 Critical Step SAT [ ] UNSAT [ ]
Standards
- 1) 15G10 transfer switch is placed in DEFEAT.
- 2) 15G10 status checked as open.
- 3) 15G1 is opened.
ONLY elements 1&3 are critical since 15G10 is already open (normal alignment)
Notes/Comments:
1-CW-MOV-101C & D will start to close when 15G1 is opened.
NAPS 2016 NRC EXAM SIM JPM G Page: 9 of 12 9
Place the unit-1 circulating water pumps in PULL-TO-LOCK.
Procedure Step 4.b.3. RNO d of 0-AP-39.1 SAT [ ] UNSAT [ ]
Standards Operator places all four (4) CW pump switches in PTL Notes/Comments 10 Verify that all circulating water pump breakers are open.
Procedure Step 4.b.3 RNO e of 0-AP-39.1 SAT [ ] UNSAT [ ]
Standards Operator verifies CW pump breakers open prior to placing switches in pull-to-lock, or locally, or using PCS.
Notes/Comments Control room breaker light indication was available when the previous step was performed (placing pump breakers in pull-to-lock).
11 Re-energize the unit-1 "G" bus..
Procedure Step 4.b.3. RNO f of 0-AP-39.1 SAT [ ] UNSAT [ ]
Standards Operator acknowledges that another operator will re-energize the bus.
Performance Cue(s)
Another operator will re-energize the bus Notes/Comments
NAPS 2016 NRC EXAM SIM JPM G Page: 10 of 12 12 Close the following water box outlet motor-operated valves.
1-CW-MOV-102A 1-CW-MOV-102B 1-CW-MOV-102C 1-CW-MOV-102D Procedure Step 4.b.4 of 0-AP-39.1 Critical Step SAT [ ] UNSAT [ ]
Standards CLOSE push-button is momenetarily depressed for the following motor-operated valves 1-CW-MOV-102A 1-CW-MOV-102B 1-CW-MOV-102C 1-CW-MOV-102D Notes/Comments Operator will most likely be waiting on inlet valves to stroke fully closed 13 Request the turbine building operator to secure the unit-1 High-capacity Steam Generator Blowdown System.
Procedure Step 4.b.5 of 0-AP-39.1 SAT [ ] UNSAT [ ]
Standards Operator calls Turbine bldg. operator to secure HCBD per the OP Notes/Comments When requested, Booth operator will acknowledge operators direction and call back and report action is complete
NAPS 2016 NRC EXAM SIM JPM G Page: 11 of 12 14 Check if liquid waste releases can be continued -NO.
Procedure Step 4.b.6 RNO of 0-AP-39.1 SAT [ ] UNSAT [ ]
Standards Operator determines that LW releases cannot be continued and places 1-LW-PCV-115 in HAND and verifies it is closed (status of LW aligned to Unit 1 tunnel provided by initial conditions).
Performance Cue(s)
Another operator will complete 0-AP-39.1.
This completes JPM.
Notes/Comments If operator calls HP booth operator will respond that the release permit requires 3 CW pumps to be running on the tunnel that LW is discharging to.
END OF EVALUATION STOP TIME
NAPS 2016 NRC EXAM SIM JPM G Page: 12 of 12 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)
SIMULATOR SETUP JOB PERFORMANCE MEASURE 13355 TASK Respond to turbine building flooding with Circulating water pump fails to trip (0-AP-39.1).
CHECKLIST
_____ Recall IC # 337 (100% power)
_____ Do simspray and check recorders Step 4.b.5) when called acknowledge as turbine operator to secure high capacity blowdown in accordance with 1-OP-32.3 If called as outsides operator report that all 4 Unit 1 CW pump breakers are verified open locally If called as HP report that the release permit requires 3 CW pumps running.
NUMBER 1-E-0 PROCEDURE TITLE REACTOR TRIP OR SAFETY INJECTION REVISION 49 PAGE 2 of 21 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
[ 1 ] ___ VERIFY REACTOR TRIP:
a) Manually Trip Reactor
IF Reactor will NOT trip, THEN GO TO 1-FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, STEP 1.
b) Check the following:
- Reactor Trip and Bypass Breakers -
OPEN
- Rod Bottom Lights - LIT
- Neutron flux - LOWERING
[ 2 ] ___ VERIFY TURBINE TRIP:
a) Manually Trip Turbine a)
b) Verify all Turbine Stop Valves - CLOSED
IF Turbine is still NOT tripped, THEN manually run back Turbine.
IF Turbine cannot be run back, THEN close Main Steamline Valves:
- ALL MSTVs
- ALL MSTV Bypass Valves
c) Reset Reheaters c)
d) Reduce Reheater Control Manual valve positioner to Zero.
e) Verify Generator Output Breaker - OPEN
e) IF Generator Output Breaker does NOT open after 30 seconds, THEN manually open G-12 AND Exciter Field Breaker.
NUMBER 0-AP-39.1 PROCEDURE TITLE TURBINE BUILDING FLOODING REVISION 9
PAGE 2 of 14 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: Auxiliary Building flooding could carry over into the Turbine Building through the Service Water Tunnel into the Turbine Building Valve Pit.
NOTE: If a Reactor trip occurs, then, in order to recover the plant from the flooding, this procedure should be performed in conjunction with Emergency Operating Procedures.
- 1. ___ IDENTIFY SOURCE OF FLOODING
- 2. ___ DETERMINE IF REACTOR SHOULD BE TRIPPED:
a) Check if any of the following conditions exists:
- Circulating Water System rupture
- Condensate System rupture
- Feedwater System rupture
- Bearing Cooling System rupture
- Annunciator D Panel G-7, TURB BLD FLOOD ALARM TROUBLE, is LIT with Turbine Building basement flooded to greater than 1 foot
a) GO TO Step 3.
b) Trip Reactor
NUMBER 0-AP-39.1 PROCEDURE TITLE TURBINE BUILDING FLOODING REVISION 9
PAGE 3 of 14 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED c) Initiate appropriate procedure while continuing with this procedure:
- 1-E-0, REACTOR TRIP OR SAFETY INJECTION
- 2-E-0, REACTOR TRIP OR SAFETY INJECTION
- 3. ___ CHECK BEARING COOLING SYSTEM STATUS:
a) Bearing Cooling System - ABNORMAL
a) GO TO Step 4.
b) Do the following:
- 1) Place both Bearing Cooling Pumps to PTL.
- 2) Initiate the following for affected unit:
- 1-AP-19, LOSS OF BEARING COOLING WATER
- 2-AP-19, LOSS OF BEARING COOLING WATER
NUMBER 0-AP-39.1 PROCEDURE TITLE TURBINE BUILDING FLOODING REVISION 9
PAGE 4 of 14 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:
- If a G-Bus is de-energized because of a CW system rupture, then a reduced Bearing Lube flow condition could result on the opposite unit. The de-energized bus should be re-energized as soon as possible.
- When the waterbox inlet box valves start to close, then the CW pumps for the affected unit should trip.
- 4. ___ CHECK CIRCULATING WATER SYSTEM STATUS:
a) CW System - ABNORMAL.
a) GO TO Step 5.
b) Do the following:
b)
- 1) Place all affected unit CW MOV Interlock Defeat switches in NORMAL (located at bottom of CW Panel) 1)
(STEP 4 CONTINUED ON NEXT PAGE)
NUMBER 0-AP-39.1 PROCEDURE TITLE TURBINE BUILDING FLOODING REVISION 9
PAGE 5 of 14 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.
CHECK CIRCULATING WATER SYSTEM STATUS: (Continued)
- 2) Close the affected unit waterbox inlet MOVs:
- Unit 1:
- 1-CW-MOV-101A
- 1-CW-MOV-101B
- 1-CW-MOV-101C
- 1-CW-MOV-101D 2)
- Unit 2:
- 2-CW-MOV-201A
- 2-CW-MOV-201B
- 2-CW-MOV-201C
- 2-CW-MOV-201D (STEP 4 CONTINUED ON NEXT PAGE)
NUMBER 0-AP-39.1 PROCEDURE TITLE TURBINE BUILDING FLOODING REVISION 9
PAGE 6 of 14 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.
CHECK CIRCULATING WATER SYSTEM STATUS: (Continued)
- 3) Verify the affected unit CW Pumps trip
- 3) Do the following:
- a. Place 15G10 Transfer switch to DEFEAT.
- b. Open 15G10.
- c. De-energize the affected unit G Bus:
- Open 15G1 for Unit 1.
- Open 25G1 for Unit 2.
- d. Place all Circulating Water Pumps on the affected unit to PTL.
- e. Verify all CW Pump breakers open.
f.
Re-energize the affected unit G Bus using applicable MOP:
- 1-MOP-26.80, 1G 4160-VOLT BUS
- 2-MOP-26.80, 2G 4160-VOLT BUS (STEP 4 CONTINUED ON NEXT PAGE)
NUMBER 0-AP-39.1 PROCEDURE TITLE TURBINE BUILDING FLOODING REVISION 9
PAGE 7 of 14 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.
CHECK CIRCULATING WATER SYSTEM STATUS: (Continued)
4)
- Unit 1:
- 1-CW-MOV-102A
- 1-CW-MOV-102B
- 1-CW-MOV-102C
- 1-CW-MOV-102D OR
- Unit 2:
- 2-CW-MOV-202A
- 2-CW-MOV-202B
- 2-CW-MOV-202C
- 2-CW-MOV-202D (STEP 4 CONTINUED ON NEXT PAGE)
NUMBER 0-AP-39.1 PROCEDURE TITLE TURBINE BUILDING FLOODING REVISION 9
PAGE 8 of 14 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.
CHECK CIRCULATING WATER SYSTEM STATUS: (Continued)
- 5) Secure High Capacity Blowdown System on affected Unit (if in service):
- 1-OP-32.3, HIGH CAPACITY STEAM GENERATOR BLOWDOWN SYSTEM OPERATION
- 2-OP-32.3, HIGH CAPACITY STEAM GENERATOR BLOWDOWN SYSTEM OPERATION 5)
- 6) Check if Liquid Waste releases can be continued:
- Adequate number of CW pumps running - YES
- Liquid Waste - NOT DISCHARGING TO A SECURED CW TUNNEL
- 6) Secure Liquid Waste releases:
- Place 1-LW-PCV-115 control switch to HAND and push Close button
- Isolate U-1 Low Capacity SG blowdown
- Isolate U-2 Low Capacity SG blowdown
- 5. ___ CHECK FEEDWATER/CONDENSATE SYSTEM STATUS:
a) Either system - ABNORMAL:
- Condensate System
a) GO TO Step 6.
(STEP 5 CONTINUED ON NEXT PAGE)
Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS The "A" waste gas decay tank (WGDT) is on holdup and is ready for release The "A" WGDT has been sampled and a release permit has been issued by Health Physics The tagout has been cleared on "A" WGDT Purging or venting either units reactor head, pressurizer, or PRT is not in progress The Nitrogen Gas System is operable.
INITIATING CUE You are requested to place waste gas decay tank 1-GW-TK-1A on bleed from the backboards using 0-OP-23.2.
NAPS 2016 NRC EXAM SIM JPM H Page: 2 of 10 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM R717 TASK Place a waste gas decay tank on bleed from the backboards (0-OP-23.2).
TASK STANDARDS "A" Waste Gas Decay Tank is discharging per 0-OP-23.2 K/A
REFERENCE:
071A4.27 (3.0/2.7)
ALTERNATE PATH:
N/A TASK COMPLETION TIMES Validation Time =
25 minutes Start Time = _______
Actual Time = _______ minutes Stop Time = _______
PERFORMANCE EVALUATION Rating
[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)
Evaluator (Print)
Evaluator's Signature /
Date EVALUATOR'S COMMENTS
NAPS 2016 NRC EXAM SIM JPM H Page: 3 of 10 Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)
OPERATOR PROGRAM R717 READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
PREREQUISITES The trainee has completed the applicable course knowledge training at the Reactor Operator level.
INITIAL CONDITIONS The "A" waste gas decay tank (WGDT) is on holdup and is ready for release The "A" WGDT has been sampled and a release permit has been issued by Health Physics The tagout has been cleared on "A" WGDT Purging or venting either units reactor head, pressurizer, or PRT is not in progress The Nitrogen Gas System is operable.
NAPS 2016 NRC EXAM SIM JPM H Page: 4 of 10 INITIATING CUE You are requested to place waste gas decay tank 1-GW-TK-1A on bleed from the backboards using 0-OP-23.2.
EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))
Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))
TOOLS AND EQUIPMENT None PERFORMANCE STEPS START TIME 1
Record the waste gas decay tank release permit number.
Procedure Step 5.3.10.a SAT [ ] UNSAT [ ]
Standards Operator records correct Waste Gas Decay Tank release permit number in the appropriate space (Printed on permit)
Notes/Comments Operator may review initial conditions and precautions & limitations before starting.
NAPS 2016 NRC EXAM SIM JPM H Page: 5 of 10 2
Ensure recorders are in operation.
Procedure Step 5.3.10.b SAT [ ] UNSAT [ ]
Standards Operator ensures the following recorders are in operation:
1-GW-FR-101 1-MM-SR-102 Notes/Comments Steps 5.3.10.c & d are N/A due to paperless recorders installed.
3 If Yokogawa recorders are installed, then electronically mark the recorder with "1-GW-TK-1A "START" and enter the waste gas release permit number on the required recorders.
Procedure Step 5.3.10.e SAT [ ] UNSAT [ ]
Standards Operator electronically marks the following recorders.
1-GW-FR-101 1-MM-SR-102 1-MM-ZR-102 Performance Cue(s)
If desired, after the operator performs actions to mark first recorder, the following cue may be read: Assume that the other chart recorders for this step have been marked as required.
Notes/Comments:
NAPS 2016 NRC EXAM SIM JPM H Page: 6 of 10 4
Enter release information on 1-RM-RR-178 Process Vent Radiation Monitor Activity and Release Rate Recorder.
Procedure Step 5.3.10.f SAT [ ] UNSAT [ ]
Standards Operator sets up 1-RM-RR-178 for bleed of 1-GW-TK-1A Performance Cue(s)
Step 5.3.11.f.5 - Concur with CV required by the procedure for MESSAGE 1 Simulation Cue(s) "1-GW-TK-1A START" is displayed with the present time and date Notes/Comments 5
Document start of the release in the narrative log.
Procedure Step 5.3.10.g SAT [ ] UNSAT [ ]
Standards Operator simulates making a narrative log entry for starting the release of 1-GW-TK-1A Performance Cue(s)
Assume another operator will make the required narrative log entry Notes/Comments
NAPS 2016 NRC EXAM SIM JPM H Page: 7 of 10 6
Notify Health Physics that the decay tank release is starting.
Procedure Step 5.3.11.a SAT [ ] UNSAT [ ]
Standards Operator notifies the Health Physics Department Notes/Comments 7
Ensure 1-GW-FCV-101 controller is at 0% demand.
Procedure Step 5.3.11.b SAT [ ] UNSAT [ ]
Standards Operator ensures the demand output of the flow controller associated with 1-GW-FCV-101 is 0%
Notes/Comments
NAPS 2016 NRC EXAM SIM JPM H Page: 8 of 10 8
Open decay tank outlet valve 1-GW-FCV-101, and adjust the controller to obtain the desired flow.
Procedure Step 5.3.11.c & d Critical Step SAT [ ] UNSAT [ ]
Standards MODULATE push-button for 1-GW-FCV-101 is depressed Standards Controller for 1-GW-FCV-101 is adjusted to establish a flow rate that does not exceed the maximum flow rate indicated on the release form Performance Cue(s)
Concur with PEER CHECKS required by procedure Simulation Cue(s) Your maximum flow rate is 3 scfm Notes/Comments 9
Place 1-GW-FCV-101 in AUTO, and check proper operation.
Procedure Step 5.3.11.e Critical Step SAT [ ] UNSAT [ ]
Standards Operator places the controller associated with 1-GW-FCV-101 in AUTO and checks for proper operation Performance Cue(s)
Concur with PEER CHECKS required by procedure Performance Cue(s)
(After AUTO flow control has been established) Assume another operator will continue with the procedure Notes/Comments
>>>>> END OF EVALUATION <<<<<
NAPS 2016 NRC EXAM SIM JPM H Page: 9 of 10 STOP TIME
NAPS 2016 NRC EXAM SIM JPM H Page: 10 of 10 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)
SIMULATOR SETUP JOB PERFORMANCE MEASURE R717 TASK Place a waste gas decay tank on bleed from the backboards (0-OP-23.2).
CHECKLIST Set up "A" WGDT level so that it requires discharge
DOMINION HP-3010.030 North Anna Power Station Revision 11 Page 27 of 30 (Page 1 of 1)
Waste Gas Decay Tank Release Permit PART 1.1 - OPERATIONS DEPARTMENT RELEASE REQUEST Prior to release, complete Part 1.1. Forward Release Permit to Health Physics for release authorization.
WGDT to be released:
1-GW-TK-1A 1-GW-TK-1B Operations By (Printed Name)
Operations By (Signature)
Date PART 1.2 - OPERATIONS DEPARTMENT RELEASE REQUEST At each start and stop of release, record data indicated below. After release, return Permit to Health Physics.
Release Status Date and Time Release Rate CFM PSIG Operations By Remarks (Printed Name)
(Initials)
Start Stop Start Stop Vol. Released, mL = 8.9E+5 x (PSIG Start - PSIG Stop) = _________________mL.
PART 2 - RELEASE AUTHORIZATION AND REQUIREMENTS (as indicated and marked. A valid Process Vent RMS alarm voids this permit.
PERMIT NO.
1-GW-TK-1A 1-GW-TK-1B Maximum Authorized Release Rate: _____ CFM. Authorized Release Rate is: ________% Tech Spec.
Required controls or conditions _________________________________________________________________________________________________________
HP Authorization By (Printed Name)
HP Authorization By (Signature)
Date PART 3 - ANALYSES AND RELEASE DATA Release Data By (Printed Name)
(Initials)
Date Complete Prior to Release mL Released Sample Release Rate Nuclide
µCi/mL Factor, RRF
µCi/mL x RRF
µCi Released Remarks Kr-85m 1.32E-3*
Kr-85 2.57E-4**
Kr-87 6.70E-3*
Kr-88 1.66E-2*
Xe-131m 1.22E-4**
Xe-133m 2.84E-4*
Xe-133 3.33E-4*
Xe-135m 3.53E-3*
Xe-135 2.05E-3*
Xe-138 1.00E-2*
Ar-41 1.00E-2*
NG µCi/mL x RRF H-3***
4.25E-4
- Based on total body dose factor.
- Based on skin dose factors.
- If required by Supv R.A.
________CFM Max. % Tech Spec
= ________
= _________CFM
% Tech Spec Allocated for WGDT = _______
Transfer release data to release records?
Date Release Records By (Printed Name)
Release Records By (Signature)
Date
µ
x
µ
2.5 2.1E-5 16-WGDT-03 Joe HP Tech Joseph Tech Today 3
DOMINION 0-OP-23.2 North Anna Power Station Revision 24-P1 Page 8 of 75 Init Verif 3.0 INITIAL CONDITIONS 3.1 Nitrogen Gas System is operable.
3.2 Radiation Monitoring System is operable.
4.0 PRECAUTIONS AND LIMITATIONS 4.1 TRM 3.3.5: One Oxygen Monitor instrumentation channel of the Waste Gas Holdup System Explosive Gas Monitoring System shall be OPERABLE.
4.2 Limit oxygen concentration in the Waste Gas Decay Tanks to 2 % by volume whenever Hydrogen concentration could exceed 4 % by volume. This will ensure the requirements of TRM 3.10.2 are maintained.
4.3 TRM 3.10.3: The quantity of radioactivity contained in each Gas Storage tank shall be limited to less than or equal to 25,000 curies noble gases (considered as Xe-133).
4.4 A numbered radioactive waste discharge record must be initiated by Health Physics Department or Operations Department before any waste is discharged. ALL numbered forms must be accounted for, even those that may have to be voided.
4.5 During normal conditions of plant operations, radioactive gases should be provided with a minimum hold up of sixty days except for low radioactive gaseous wastes resulting from purge and fill operations associated with Refueling and Reactor startup.
4.6 Minimize recirculating concentrated high activity gases which could be released through leaks in the recirculating path.
4.7 Gaseous waste, gas and particulate activity shall be continuously monitored and recorded during release of radioactive gaseous wastes via the effluent line.
DOMINION 0-OP-23.2 North Anna Power Station Revision 24-P1 Page 9 of 75 4.8 A Licensed Senior Reactor Operator shall be made aware of any release being made.
4.9 ALL releases shall be made by a licensed operator or an individual in training for an operator's license under the direction of a licensed operator or licensed senior operator.
4.10 IF any adjustments must be made to the analyzer, THEN contact the Instrument Department.
4.11 VPAP-2103N, Offsite Dose Calculation Manual (North Anna): Radioactive gaseous effluent monitoring instrumentation channels shown in the Radioactive Gaseous Effluent Monitoring Instrumentation Attachment shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits specified for noble gases in 6.3.1.a are not exceeded. (Reference 2.4.1) 4.12 Any significant increase in oxygen concentration of the inservice WGDT shall be investigated and actions taken to correct deficiencies.
4.13 It is preferred to operate 1-GW-FCV-101 in AUTO control to maintain flow
< 3 SCFM. IF Manual control is required, THEN it is to only be done with SRO permission. (Reference 2.4.3) 4.14 IF purging or venting of a units reactor vessel head, pressurizer, or PRT is in progress, THEN consideration should be given to delaying the release of A or B WGDT. Performing these evolutions simultaneously in the past has caused the auto functions associated with 1-GW-RI-178, Process Vents Rad Mon, to actuate on numerous occasions. (Reference 2.4.4) 4.15 Performance of Section 5.21 will deadhead each GW compressor against its associated discharge diaphragm valve.
4.16 During performance of Section 5.21, constant communication between the Fuel Building and MCR should be established.
DOMINION 0-OP-23.2 North Anna Power Station Revision 24-P1 Page 10 of 75 4.17 In the event of a diaphragm rupture of 1-GW-69 or 1-GW-72, the WGDT(s) can be isolated from input by closing 1-GW-73 and 1-GW-74.
4.18 IF any instrumentation is NOT functional, THEN have the Unit SRO review TRM TR 3.3.9 for applicability.
RO RO
DOMINION 0-OP-23.2 North Anna Power Station Revision 24-P1 Page 15 of 75 5.3 Placing 1-GW-TK-1A Waste Gas Decay Tank on Bleed 5.3.1 Check Initial Conditions are satisfied.
5.3.2 Review Precautions and Limitations.
NOTE: A numbered radioactive waste discharge record must be initiated by Health Physics Department or Operations Department before any waste is discharged. ALL numbered forms must be accounted for, even those that may have to be voided.
NOTE: Tank should be held as long as possible to allow for radioactive decay.
5.3.3 Initiate a HP form Waste Gas Decay Tank Release Record and forward to Health Physics.
5.3.4 Check the Process Vent System is in operation.
5.3.5 Check that Process Vent MGP Radiation Monitors operable:
a.
1-GW-RI-178-1, Process Vent RM Noble Gas Normal:
- operate light - LIT
- test light - NOT LIT
- alert, high and H/H lights - NOT LIT
- Display operable CAUTION If purging or venting of a units reactor vessel head, pressurizer, or PRT is in progress, consideration should be given to delaying the release of A or B WGDT. Performing these evolutions simultaneously in the past has caused the auto functions associated with 1-GW-RI-178, Process Vents Rad Mon, to actuate on numerous occasions.
DOMINION 0-OP-23.2 North Anna Power Station Revision 24-P1 Page 16 of 75 b.
1-GW-RI-178-2, Process Vent RM Noble Gas Accident:
- operate light - LIT
- test light - LIT
- alert and high lights - NOT LIT
- Display operable c.
Unit 2 Annunciator Panel 2B-C5, PROCESS VENT VNT STACK A&B RAD MONITORS FAILURE - NOT LIT 5.3.6 Check 1-GW-FCV-101, CHAR FILT IN FM DECAY TKS CONT, is closed.
5.3.7 Check closed 1-GW-TK-1B outlet valves:
- 1-GW-28, 1B Waste Gas Decay Tk To Prcs Vent/Surge Drum Isol
- 1-GW-29, 1B Waste Gas Decay Tk To Process Vent Isol Valve NOTE: Minimize recirculating concentrated high activity gases which could be released through leaks in the recirculating path.
5.3.8 Check closed 1-GW-17, 1A Waste Gas Decay Tank Recirc To Surge Drum Isol.
NOTE: SRO authorizes clearance of tagout issued in Section 5.5 of this procedure.
5.3.9 Open 1-GW-TK-1A outlet valves to Process Vent System:
PC
- a. 1-GW-15, 1A Waste Gas Decay Tk To Prcs Vent/Surge Drum Isol PC
DOMINION 0-OP-23.2 North Anna Power Station Revision 24-P1 Page 17 of 75 NOTE: Gaseous waste activity shall be continuously monitored and recorded while releasing WGDT.
5.3.10 Do the following:
a.
Record the Waste Gas Decay Tank Release Permit Number: _________
b.
Ensure the following recorders are in operation:
- 1-GW-FR-101, Char Fltr Inlet Flow FM Decay Tks Recorder
- 1-MM-SR-102, Wind Speed Recorder c.
IF any paper recorder is installed, THEN mark the following applicable recorders with date, time, tank 1-GW-TK-1A, and the Waste Gas Decay Tank Release Permit Number. Mark any Yokogawa recorder installed by DCP 09-00146 N/A:
- 1-GW-FR-101, Char Fltr Inlet Flow FM Decay Tks Recorder
- 1-MM-SR-102, Wind Speed Recorder d.
Ensure Wind Direction is monitored and recorded as follows:
- 1. IF paper recorder 1-MM-ZR-102, Wind Direction Recorder, is installed AND operable, THEN mark 1-MM-ZR-102 with date, time, tank 1-GW-TK-1A, and the Waste Gas Decay Tank Release Permit Number. Mark Step N/A, if Yokogawa recorder is installed by DCP 09-00146.
DOMINION 0-OP-23.2 North Anna Power Station Revision 24-P1 Page 18 of 75
- 2. IF 1-MM-ZR-102, Wind Direction Recorder, is NOT functional, THEN check that ALL of the following PCS points are operable.
IF NOT THEN, have the Unit SRO enter TRM TR 3.3.3 and 3.3.9:
- M3MM003A, LOWER WIND DIRECTION
- M3MM004A, UPPER WIND DIRECTION
- M3MM005A, BACKUP WIND DIRECTION e.
IF any of the following Yokogawa recorders are installed by DCP 09-00146, THEN perform Steps 5.3.10.e.1 through 5.3.10.e.3 for each of the applicable recorders:
- 1-GW-FR-101, Char Fltr Inlet Flow FM Decay Tks Recorder
- 1-MM-SR-102, Wind Speed Recorder
- 1-MM-ZR-102, Wind Direction Recorder, if operable
- 1. Enter Waste Gas Decay Tank Release Permit Number for each applicable Yokogawa recorder, as follows:
(a) Open Soft Key access door.
(b) Press FUNC.
(c) Press Free message soft key.
(d) Press Next soft key (right key).
(e) Press message 5 soft key.
DOMINION 0-OP-23.2 North Anna Power Station Revision 24-P1 Page 19 of 75 NOTE: Using the arrow soft keys position the cursor and the DISPLAY/ENTER button & Arrow Keys to enter the permit number. The permit number will display on recorder screen, when the MESSAGE is entered.
(f) Enter or edit the current Waste Gas Decay Tank Release Permit Number.
(g) Select ENT.
(h) Press DISP/ENTER.
- 2. Enter START message for each applicable Yokogawa recorder, as follows:
(a) Press FUNC.
(b) Press Message soft key.
(c) Press 1-10 soft key.
(d) Press the Message 1 soft key one time to mark the recorder with 1-GW-TK-1A START, date and time.
- 3. Repeat Steps 5.3.10.e.1 and 5.3.10.e.2, as required for each of the applicable recorders.
f.
Do the following for 1-RM-RR-178, Process Vent RM Activity and Release Rate Recorder:
- 1. Ensure 1-RM-RR-178, Radiation Recorder is in operation.
- 2. Open Soft Key access door (left pull slot).
- 3. Press the FUNC key to display blue functions on the screen.
- 4. Press the key under the MESSAGE blue function displayed on the screen.
DOMINION 0-OP-23.2 North Anna Power Station Revision 24-P1 Page 20 of 75 NOTE: Using the DISPLAY/ENTER button and Arrow Keys to display trends on the recorder will display the message on recorder screen, when MESSAGE is entered.
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- 5. Press the key one time under the MESSAGE 1 blue function displayed on the screen to mark the recorder with 1-GW-TK-1A START, date and time.
g.
Make a narrative log entry addressing start of 1-GW-TK-1A release with the Waste Gas Decay Tank Release Permit Number.
5.3.11 Release WGDT as follows:
- a. Notify H.P. Dept. that WGDT Release is starting.
b.
Ensure 1-GW-FCV-101 controller, CHAR FILT IN FM DECAY TKS CONT, demand is 0 %.
PC
- c. Push MODULATE button for 1-GW-FCV-101, WGDT TO PROCESS VENT.
NOTE: It is preferred to operate 1-GW-FCV-101 in AUTO control to maintain flow
< 3 SCFM. IF Manual control is required, THEN it is to only be done with SRO permission. (Reference 2.4.3)
PC
- d. Adjust 1-GW-FCV-101 Controller to obtain desired flow, BUT NOT to exceed maximum flow on HP Release form.
PC
- e. Place 1-GW-FCV-101 in AUTO, and check proper operation.
(Reference 2.4.3) 5.3.12 WHEN pressure in the tank reaches approximately 10 psig as indicated on 1-GW-PI-109A or when directed by the SRO, THEN do the following:
IV a.
Close 1-GW-16, 1A Waste Gas Decay Tank To Process Vent Isol Vv.
IV b.
Close 1-GW-15, 1A Waste Gas Decay Tk To Prcs Vent/Surge Drum Isol.