ML092810439
| ML092810439 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 10/08/2009 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-390/09-301, 50-391/09-301 | |
| Download: ML092810439 (66) | |
Text
Appendix D Scenario Outline Form ES-D-1 Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Facility:
Watts Bar Scenario No.: 1 Op Test No.:
1 Examiners:
Operators:
Initial Conditions:
15% RTP, MOL. RCP Boards have not been transferred. After this transfer, power is to be raised to full power Turnover:
15% RTP was achieved 45 minutes ago, leaving 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> and 15 minutes for the initial performance of 1-SI-92-1,NIS Daily Comparison. IA MFP has been placed in service. 1B-B Thermal Barrier Booster Pump is out-of service due to a seized pump shaft. Expected return to service is to be determined. OR 14.10 has been entered for the 1B-B Thermal Barrier Booster Pump. RCP #1, #2 and #3 have been transferred. RCP #4 is on its alternate power supply, and after relay testing, is now ready to transfer to its normal power supply.
Event No.
Malf. No.
Event Type*
Event Description 1
N/A N-SRO/RO Transfer RCP #4 Board to normal supply.
2 N/A R-SRO/RO N-BOP Raise reactor power using GO-3.
3 RX07A I-SRO/RO TS-SRO 1-PT-68-340 fails high, requiring manual control of PZR pressure.
4 RW18A C-SRO/BOP TS-SRO ERCW Pump A-A Shaft Shears. Operator manually starts a redundant ERCW pump.
5 CV09 I-SRO/RO VCT Level Transmitter 1-LT-62-130A fails to 100%.
6 RM90106 C-BOP TS-SRO Lower Compartment Radiation Monitor 1-RM-90-106 fails.
7 166-E 166-D M-ALL Seismic Event.
8 MS02B MS04A/B/C/D M-ALL MSLB on SG #2 outside Containment. Reactor auto trips and crew enters E-0.
9 RP55A/B/C C-BOP C-SRO ALL AFW Pumps fail to auto start. BOP manually starts AFW pumps.
10 MS04A/B/C/D C-ALL All MSIVs fail to auto close, and cannot be closed manually. (FR-P.1)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
1 Page 2 of 66 Event
Description:
Transfer RCP Boards to normal supply.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Scenario 1 - Summary Initial Condition The Unit is at 15% RTP, MOL. IA MFP has been placed in service.
Turnover:
15% RTP, was achieved 45 minutes ago, leaving 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> and 15 minutes for the initial performance of 1-SI-92-1,NIS Daily Comparison. IA MFP has been placed in service. 1B-B Thermal Barrier Booster Pump is out-of service due to a seized pump shaft. Expected return to service is to be determined. OR 14.10 has been entered for the 1B-B Thermal Barrier Booster Pump. RCP #1, #2 and #3 have been transferred. RCP #4 is on its alternate power supply, and after relay testing, is now ready to transfer to its normal power supply.
Event 1 Crew transfers power supply to RCP #4 from startup to USST.
Event 2 Crew begins raising reactor power per GO-3, Unit Startup.
Event 3 1-PT-68-340 (PZR pressure control) fails high, causing PZR sprays to fully open and heaters to deenergize.
RO takes manual control of the master pressure controller to control PZR pressure. SRO implements AOI-18, Malfunction of PZR Pressure Control, and evaluates Technical Specifications.
Event 4 ERCW Pump A-A shaft shears. CCW Hx outlet temperatures will begin rising. There is no standby start feature for these pumps. The SRO will implement AOI-13, Loss of Essential Raw Cooling Water, which will direct manual starting of a redundant ERCW pump. SRO evaluates Technical Specifications.
Event 5 A VCT level transmitter fails to 100%, resulting in letdown diverting to the radwaste system (HUT). VCT level lowers, and auto makeup is disabled by this failure. The operator manually controls an LCV to prevent a low level in the VCT and to prevent charging pump suction swapping to the RWST.
Event 6 Lower Compartment Radiation Monitor 1-RM-90-106 fails. Requires various actions per the Alarm Response Instruction, including performing a source check. SRO evaluates Technical Specifications.
Event 7 A seismic event occurs, which generates 166-E SEISMIC RECORDING INITIATED AND 166-D OBE SPECTRA EXCEEDED annunciators. Requires implementation of AOI-9, Earthquake. This earthquake does not result in any significant and immediately noticeable damage to the plant, but IS designed to be a precursor for Event 8.
Event 8 A Main Steam Line Break occurs outside of containment. The crew ensures the reactor trips and enters E-0, with eventual transition to ECA-2.1 for uncontrolled depressurization of all SGs (see Event 10).
Event 9 AFW pumps will not auto start, requiring operator action to manually start ALL AFW pumps.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
1 Page 3 of 66 Event
Description:
Transfer RCP Boards to normal supply.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Event 10 All MSIVs fail to auto close. Crew attempts to close MSIVs at Aux. Control Room, but NO MSIVs will close.
This requires implementation of FR-P.1, Pressurized Thermal Shock. Recommended to terminate scenario when the Cold Overpressure Protection System (COPS) is armed.
Critical Task 1 Critical Task 2 FR-P.1 -- A:
Terminate ECCS flow so that if the challenge to the integrity CSF is
- Severe, an extreme challenge is prevented
- Extreme, RCS pressure and temperature are controlled before the end of the scenario FR-P.1 -- B:
Control the AFW flow rate in order to minimize the RCS cooldown rate before an extreme (red-path) challenge develops to the integrity CSF
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
1 Page 4 of 66 Event
Description:
Transfer RCP Boards to normal supply.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 The following actions are taken from SOI-202.04, 6.9KV Reactor Coolant Pump Board 1D, Section 8.0, Infrequent Operations.
[1] OBTAIN SRO approval.
[2] ENSURE MSB has verified Time Delay Relay (TDR) 1-62-068-0074 contact points 1and 5 closed (located on left side panel in compartment 1D3 of RCP BD 1D).
NOTE IF Unit is out of service, Bd may be energized by backfeeding from USSTs.
[3] CHECK voltage 6560 to 7260V to Normal ACB 2124 on 1-EI 58, USST 1B \\VOLTS [1-M-1].
[4] ENSURE 1-HS-68-31AA, RCP 2 NORMAL BKR & LIFT PMP [1-M-5], PUSHED IN to place handswitch in control of ACB 2114..
[5] ENSURE 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR [1-M-5], PUSHED IN to place ACB 2624 auto transfer in MANUAL.
[6] MONITOR 1-EI-68-73A, RCP 4 AMPS [1-M-5] during transfer to ensure RCP Amp load transfers to Normal supply.
CAUTION Release handswitches SLOWLY after transfer is complete to prevent inadvertent breaker actuation.
Start of Critical Step(s)
[7] PLACE AND HOLD 1-HS-68-73AA, RCP 4 NORMAL BKR &
LIFT PMP, in START, AND PLACE 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR, in STOP.
End of Critical Step(s)
[8] ENSURE Normal ACB 2124 CLOSED, and Alt ACB 2624 OPEN.
[9] IF desired to place Board Transfer in AUTO, THEN PULL 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR, out to PULL AUTO.
SRO This action completes GO-3 Section 5.4. The SRO continues with GO-3, Section 5.5, Raise Power to Between 20 and 24%.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
2 Page 5 of 66 Event
Description:
Raise reactor power using GO-3 using GO-3Unit Startup from less than 4% to Reactor Power to 30% Reactor Power, Section 5.5 Raise Reactor Power to Between 20 and 24 %.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 The following actions are taken from GO-3Unit Startup from less than 4% to Reactor Power to 30% Reactor Power, Section 5.5, Raise Reactor Power to Between 20 and 24%.
NOTES
- 1) To enter this section Turbine load should be between 15 and 20%.
- 2) The main emphasis of this section is to raise Reactor Power to between 20 and 24%
- 3) Pre-conditioned power levels and maximum allowable rates of power changes are specified by TI-45, Determination of Preconditioned Reactor Power.
- 4) Declared fuel defects, as determined by the Fuel Reliability Assessment Team (FRAT) or the Shift Manager, have limitations on rate of power changes as specified in TI-45.
- 5)
Power escalations should be per SOI-47.02 Turbine loading recommendations.
- 6) If possible, dilution should be in 50 to 75 gallon batches every 12 to 15 minutes for a steady rise in TAVG. Dilution and rod movement rates may be adjusted depending on SG level stability.
- 7) If a feedwater flow/pressure transient occurs during turbine rollup or subsequent loading, the operator may place the TDMFWP recirc controller in MANUAL to prevent feedback into the system due to valve modulations.
The following actions are taken from SOI-62.02, Boron Concentration Control, Section 6.6, Minor Dilution.
NOTES
- 1) Section 6.6, Minor Dilution, may be reproduced, laminated, displayed, reused, etc. as desired.
- 2) Minor Dilution is defined as the addition of Primary Water done several times each shift to compensate for fuel burn-up, and maintain Tavg on program.
[1] ENSURE 1-HS-68-341H, BACKUP HEATER C, is ON, to equalize Pzr-RCS CB.
[2] ADJUST 1-FQ-62-142, PW BATCH COUNTER, for required quantity.
[3] PLACE 1-HS-62-140B, VCT MAKEUP MODE in DIL.
[4] TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to START.
[4.1] CHECK Red light is LIT.
[5] MONITOR the following parameters:
1-PI-62-122 1-M-6 VCT PRESS 1-LI-62-129A 1-M-6 VCT LEVEL 1-FI-62-142 1-M-6 PW TO BLENDER FLOW 1-FQ-62-142 1-M-6 PW BATCH COUNTER
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
2 Page 6 of 66 Event
Description:
Raise reactor power using GO-3 using GO-3Unit Startup from less than 4% to Reactor Power to 30% Reactor Power, Section 5.5 Raise Reactor Power to Between 20 and 24 %.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 1-FQ-62-139 1-M-6 PW BATCH COUNTER RO
[6] WHEN dilution is COMPLETE, AND 1-FCV-62-128 is closed, THEN PLACE 1-HS-62-140B, VCT MAKEUP MODE, in AUTO.
[7] TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to START.
[7.1] CHECK Red light is LIT.
The following actions are taken from GO-3Unit Startup from less than 4% to Reactor Power to 30% Reactor Power, Section 5.5 Raise Reactor Power to Between 20 and 24 %.
[1] INITIATE a rise in Reactor power to between 20 and 24% by performing the following:
[1.1] DETERMINE appropriate LOAD RATE per SOI-47.02.
[1.2] SET the LOAD RATE at predetermined value.
[1.3] PUSH REFERENCE CONTROL (raise) button to set desired load in SETTER display.
[1.4] PUSH the GO button.
NOTES
- 1) TAVG is programmed from 557°F at no load to 586.2°F at 100%, at a rate of 0.29 °F/%
power.
- 2) Pzr level is programmed from 25 to 60% as a function of TAVG.
[2] MONITOR the following as load rises:
A. TAVG following TREF program.
B. RCP seal flow between 8 and 13 gpm per pump.
C. Pzr level on program.
RO D. Correct power distribution, quadrant power tilts, rod insertion, rod misalignment, inoperable RPIs, and inoperable rods by monitoring:
All RPIs Step Counters Loop T NIS RO
[3] COMPARE TAVG, T, and NIS to check indications are consistent with expected values.
[4] WHEN Turbine load is greater than 15%, THEN
[4.1] CHECK Permissive 66-A, C-5 LO TURB IMPULSE PRESS ROD BLOCK, is NOT LIT.
[4.2] IF auto rod control is desired, THEN PLACE rod control in
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
2 Page 7 of 66 Event
Description:
Raise reactor power using GO-3 using GO-3Unit Startup from less than 4% to Reactor Power to 30% Reactor Power, Section 5.5 Raise Reactor Power to Between 20 and 24 %.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 AUTO per SOI-85.01.
CAUTION If the Steam Dumps cycle, the MFP and Bypass Regs may swing, and control rods may respond if in Auto.
[5] WHEN steam dump demand (1-XI-1-33) reduces to zero, THEN TRANSFER Steam Dumps to TAVG mode by performing the following:
[5.1] PLACE 1-HS-1-103A, STEAM DUMP FSV A, to OFF
[5.2] PLACE 1-HS-1-103B, STEAM DUMP FSV B, to OFF.
[5.3] PLACE 1-HS-1-103D, STEAM DUMP MODE, to T AVG.
[5.4] IF Permissive 66-E, C-7 LOSS OF LOAD STM DUMP INTERLOCK, is LIT, THEN
[5.4.1] MOMENTARILY PLACE 1-HS-1-103D to RESET.
[5.4.2] CHECK Permissive 66-E is NOT LIT.
[5.5] ADJUST 1-PIC-1-33, STEAM DUMP PRESS CONTROL, to 84% and place in AUTO.
NOTE If TAVG is greater than TREF, a demand will be indicated in TAVG mode, however, the dumps will NOT operate until armed by a load rejection or a Reactor trip signal.
[5.6] PLACE 1-HS-1-103A, STEAM DUMP FSV A, to ON.
[5.7] PLACE 1-HS-1-103B, STEAM DUMP FSV B, to ON.
NOTE Step 5.5[6] is performed to prevent water hammer in the #2 Feedwater Heater hi-level bypass lines at higher power levels. Isolating air fail the valves closed (EDC 52270).
[6] PRIOR to exceeding 20% turbine load:
[6.1] VERIFY the #2 Feedwater Heater normal level control valves (1-LCV-6-21, -43, -66) are maintaining the #2 heaters at normal levels
[6.2] ISOLATE air to the # 2 Feedwater Heater Hi-level bypass to condenser LCVs by closing the following valves:
Lead Examiner may cue the next event.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
3 Page 8 of 66 Event
Description:
1-PT-68-340, Pressurizer Pressure Control, fails high.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Expected Alarms:
90-A PZR PRESS HI 123-C OVERTEMP T TRIP ALERT 123-D OVERTEMP T TURB RUNBACK & C-3 ROD BLOCK RO Diagnoses and announces failure.
RO May place master pressure controller in MANUAL to regain control of RCS pressure after the failure.
SRO Enter and direct actions of AOI-18, Malfunction Of Pressurizer Pressure Control System, and directs crew actions.
NOTE 120 AC VITAL PWR BD 1-IV [breaker 2] supplies the plugmold power strip associated with both PZR spray valves and several other instruments required to respond to this event.
- 1. CHECK pressurizer pressure stable or trending to desired pressure:
1-PI-68-340A, 1-PI-68-334, 1-PI-68-323, 1-PI-68-322.
- 1. RESPONSE NOT OBTAINED PLACE pzr master controller 1-PIC-68-340A in MANUAL and RESTORE press to normal.
- 2. CHECK 1-XS-68-340D selected to a failed controlling or backup channel.
- 3. RESTORE press control to normal:
- a. SELECT operable channels for control and backup with 1-XS-68-340D.
- b. ENSURE operable channel selected for recording with 1-XS-68-340B.
- c. WHEN Pressurizer pressure on program, THEN RETURN Pzr master controller 1-PIC-68-340A to AUTO.
- 4. NOTIFY Work Control to remove failed channel from service.
- 5. ** GO TO Step 17.
- 17. REFER TO the following Tech Specs:
3.3.1-1, 6. Overtemperature T Condition W.
8.a. Pressurizer Pressure Low Condition X 8.b. Pressurizer Pressure High Condition W 3.3.2-1, 1.d Pressurizer Pressure Low Condition D 8.b Pressurizer Pressure P-11 Condition L SRO
- 18. INITIATE repairs to failed equipment.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
3 Page 9 of 66 Event
Description:
1-PT-68-340, Pressurizer Pressure Control, fails high.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 SRO
- 19. RETURN TO Instruction in effect.
CREW Crew Brief would be conducted for this event as time allows prior to the next event.
CREW Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.
Operations Management - Shift Manager.
Maintenance Personnel -Maintenance Shift Supervisor (MSS).
(Note: Maintenance notification may be delegated to the Shift Manager).
Lead Examiner may cue the next event.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
4 Page 10 of 66 Event
Description:
ERCW Pump A-A Shaft Shears.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Expected Alarms:
223-A ERCW HDR A SUP PRESS LO 223-B ERCW PMP A-A DISCH PRESS LO BOP Diagnoses and announces failure BOP May enter Alarm Response Instructions 223-A and 223-B.
SRO Enter and direct actions of AOI-13, Loss of Essential Raw Cooling Water, and directs crew actions, using Section 3.2, Loss of ERCW Pump.
- 1. START redundant trained ERCW Pump.
- 2. ENSURE header pressures and flows return to expected values for existing plant conditions.
- 3. ENSURE pump amps NORMAL.
- 4. PLACE failed pump HS in PULL TO LOCK.
- 5. DISPATCH personnel to determine reason for pump failure.
- 6. Locally CLOSE discharge valve on failed pump.
- 7. ENSURE applicable emergency power selector switch selected away from failed pump.
- 8. INITIATE repair.
- 9. REFER TO Tech Spec 3.7.8, Essential Raw Cooling Water System (ERCW).
3.7.8 Condition A. and 3.8.1.c until the auto start switch has been repositioned
- 10. RETURN TO Instruction in effect.
CREW Crew Brief would typically be conducted for this event as time allows prior to the next event.
CREW Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.
Operations Management - Shift Manager.
Maintenance Personnel -Maintenance Shift Supervisor (MSS).
(Note: Maintenance notification may be delegated to the Shift Manager).
Lead Examiner may cue the next event.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
5 Page 11 of 66 Event
Description:
VCT Level Transmitter 1-LT-62-130A fails to 100%.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Expected Alarms:
109-A, VCT LEVEL HI/LO RO Diagnoses and announces failure RO Enters Alarm Response Instructions 109-A.
SRO Enter and direct actions of ARI 109-A, VCT LEVEL HI/LO.
[1] IF high level, THEN
[a] ENSURE 1-LCV-62-118 diverted to HUT and OPEN.
[b] ENSURE NO VCT makeup in progress.
Step is N/A due to failure mode.
[2] IF low level, THEN ENSURE 1-LCV-62-118 aligned to VCT.
INITIATE makeup in accordance with SOI-62.02, BORON CONCENTRATION CONTROL.
ENSURE suction to the Centrifugal Charging Pump swaps over to the RWST at 7% VCT level.
Step is N/A due to failure mode.
[3] VERIFY letdown and charging in service and that Reactor Coolant Filter is not clogged.
[4] IF 1-LCV-62-118 diverted to HUT due to instrument failure, THEN
[a] PLACE 1-HS-62-118 in VCT position until repairs completed.
[b] PLACE 1-HS-62-118 in P-AUTO position when repairs completed.
[5] IF RCS leakage is suspected, THEN GO TO AOI-6, SMALL REACTOR COOLANT SYSTEM LEAK.
Step is N/A due to failure mode.
CREW Crew Brief would be conducted for this event as time allows prior to the next event.
CREW Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.
Operations Management - Shift Manager.
Maintenance Personnel -Maintenance Shift Supervisor (MSS).
(Note: Maintenance notification may be delegated to the Shift Manager).
Lead Examiner may cue the next event when Tech Spec Evaluation Complete and SRO has addressed the need for a Crew Brief.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
6 Page 12 of 66 Event
Description:
Lower Compartment Radiation Monitor 1-RM-90-106 fails.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Expected Alarms:
173-E, LWR CNTMT AIR 1-RM-90-106 INSTR MALF BOP Diagnoses and announces failure BOP Enters Alarm Response Instructions 173-E.
SRO Enter and direct actions of ARI 173-E, LWR CNTMT AIR 1-RM 106 INSTR MALF.
NOTES
- 1) 1-RE-90-106 has NO AUTO flow control.
- 2) Computer points R1012A and R1013A correspond to the listed source channels.
BOP 1] CHECK 1-RM-90-106A or B Operate light lit, IF NOT, THEN PERFORM source check on affected channel and reset the monitor.
[2] ENSURE correct valve and switch alignment on panel 0-M-12 per SOI-90.02, Gaseous Process Radiation Monitors.
[3] DISPATCH Operator with Radiological Protection coverage to investigate alarm and initiate corrective action.
[4] NOTIFY Chemistry Countroom to initiate sampling IAW 1-SI 25 if required.
[5] NOTIFY MIG to investigate alarm.
[6] ALIGN 1-RM-90-112 to lower containment IAW SOI-90.02 if 1-RM-90-106 is inoperable.
[7] REFER TO Tech Specs (LCO 3.4.15).
3.4.15.B RCS Leakage Detection Instrumentation CREW Crew Brief would typically be conducted for this event as time allows prior to the next event.
CREW Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.
Operations Management - Shift Manager.
Maintenance Personnel -Maintenance Shift Supervisor (MSS).
(Note: Maintenance notification may be delegated to the Shift Manager).
Lead Examiner may cue the next event.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
7, 8, 9 and 10 Page 13 of 66 Event
Description:
Seismic Event, MSLB on SG #2 outside Containment., failure of AFW pumps to AUTO start, and all MSIVs fail to auto close (cannot be closed manually).
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Expected Alarms:
166-D OBE SPECTRA EXCEEDED 166-E SEISMIC RECORDING INITIATED NOTE TO EVALUATOR: It is not expected that the crew would enter the AOI-9 Earthquake, since the steam line break will occur shortly after receipt of 166-D and 166-E.
BOP Diagnoses and announces failure BOP Enters Alarm Response Instructions 166-E, SEISMIC RECORDING INITIATED, and 166-D, OBE SPECTRA EXCEEDED.
SRO Due to the rapid nature of the steam line failure, the SRO will NOT enter and direct actions of AOI-9, EARTHQUAKE, but will address the EOP entry.
NOTE TO EVALUATOR: After Seismic Event, the #2 Main steam line ruptures outside containment, and ALL MSIVs fail to close.
BOP Diagnoses and announces reactor trip and safety injection actuations RO Performs E-0 Immediate Operator Actions.
BOP Performs E-0 Immediate Operator Actions.
SRO Enter and direct actions of E-0, REACTOR TRIP OR SAFETY INJECTION.
- 1. ENSURE reactor trip:
Reactor trip and bypass breakers OPEN.
RPIs at bottom of scale.
Neutron flux DROPPING.
- 2. ENSURE Turbine Trip:
All turbine stop valves CLOSED.
- 3. CHECK 6.9 kV shutdown boards:
- a. At least one board energized from:
CSST (offsite),
OR D/G (blackout).
- 4. CHECK SI actuated:
- a. Any SI annunciator LIT.
- b. Both trains SI ACTUATED.
- 1-XX-55-6C
- 1-XX-55-6D
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
7, 8, 9 and 10 Page 14 of 66 Event
Description:
Seismic Event, MSLB on SG #2 outside Containment., failure of AFW pumps to AUTO start, and all MSIVs fail to auto close (cannot be closed manually).
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 BOP
- 5. EVALUATE support systems:
REFER TO Appendixes A and B (E-0), Equipment Verification pages 15-28.
- 6. ANNOUNCE reactor trip and safety injection over PA system.
Event 9 BOP Recognizes the failure of the AFW pumps to start and MANUALLY starts pumps.
- 7. ENSURE secondary heat sink available with either:
- At least one S/G NR level greater than 29% [39% ADV].
- 8. MONITOR RCS temp stable at or trending to 557°F:
Event 10 RO Recognizes failure of AUTO closure and attempts to MANUALLY close MSIVs from the MCR handswitches. MSIVs will remain OPEN after action is taken.
- 8. RESPONSE NOT OBTAINED IF temp less than 557°F, THEN ENSURE steam dumps and S/G PORVs CLOSED.
IF cooldown continues, THEN:
- PLACE steam dump controls OFF.
- CONTROL total AFW flow to maintain greater than 410 gpm UNTIL NR level in at least one S/G greater than 29% [39% ADV].
IF cooldown continues after AFW flow is controlled, THEN
- CLOSE MSIVs.
- ENSURE MSIV bypasses CLOSED.
IF RCS temp greater than 564°F, THEN ENSURE either steam dumps or S/G PORVs OPEN.
- 9. ENSURE excess letdown valves CLOSED:
- 1-FCV-62-54
- 1-FCV-62-55
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
7, 8, 9 and 10 Page 15 of 66 Event
Description:
Seismic Event, MSLB on SG #2 outside Containment., failure of AFW pumps to AUTO start, and all MSIVs fail to auto close (cannot be closed manually).
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 RO
- 10. CHECK pzr PORVs and block valves:
- a. Pzr PORVs CLOSED.
- b. At least one block valve OPEN.
- 11. CHECK pzr safety valves CLOSED:
- EVALUATE tailpipe temperatures and acoustic monitors.
- 12. CHECK pzr sprays CLOSED.
- 13. CHECK if RCPs should remain in service:
- a. Phase B signals DARK [MISSP].
- b. RCS pressure greater than 1500 psig.
- 13. RESPONSE NOT OBTAINED
- a. STOP all RCPs. ** GO TO Step 14.
WHEN injection flow established, THEN STOP all RCPs.
- 14. CHECK S/G pressures:
- All S/G pressures controlled or rising.
- All S/G pressures greater than 120 psig.
- 14. RESPONSE NOT OBTAINED IF S/G pressure low OR dropping uncontrolled, THEN ** GO TO E-2, Faulted Steam Generator Isolation.
NOTE TO EVALUATOR: The following steps are taken from E-2.
CAUTION If a faulted S/G is NOT needed for RCS cooldown, it should remain isolated during subsequent recovery actions.
- 1. RESPONSE NOT OBTAINED Manually CLOSE valves.
IF valves can NOT be closed, THEN Locally REMOVE power to valves:
DISPATCH NAUO to perform Attachment 1 (E-2).
NOTE If it is known that a steam leak exists in the Turbine building, the following step should not be performed until the affected steam header is depressurized.
- 2. PLACE steam dump controls OFF:
- 1-HS-1-103A, STEAM DUMP FSV A.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
7, 8, 9 and 10 Page 16 of 66 Event
Description:
Seismic Event, MSLB on SG #2 outside Containment., failure of AFW pumps to AUTO start, and all MSIVs fail to auto close (cannot be closed manually).
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9
- 1-HS-1-103B, STEAM DUMP FSV B.
- 3. CHECK for at least one Intact S/G:
- Any S/G pressure controlled or rising, OR
- Any S/G pressure greater than P-sat for RCS incore temperature.
- 3. RESPONSE NOT OBTAINED IF pressure in all four S/Gs dropping uncontrolled, THEN
- GO TO ECA-2.1, Uncontrolled Depressurization of All Steam Generators.
NOTE TO EVALUATOR: The following steps are taken from ECA-2.1, Uncontrolled Depressurization of All Steam Generators.
CAUTION If, at any time, except during SI termination steps 14 through 24, any Intact S/G can be isolated from the break and re-pressurized, then recovery actions should continue with E-2, Faulted Steam Generator Isolation.
- 1. REFER TO EPIP-1, Emergency Plan Classification Flowchart.
CAUTION If the TD AFW pump is the only available source of feed flow to ANY S/G, the steam supply must be maintained available.
- 2. ENSURE secondary pressure boundary isolated:
- PLACE steam dump controls OFF.
- ENSURE MFW reg and bypass reg valves CLOSED.
- ENSURE MFW isolation and bypass isolation valves CLOSED.
- ENSURE S/G PORVs CLOSED.
- ENSURE S/G blowdown ISOLATED.
- 2. RESPONSE NOT OBTAINED Manually CLOSE valves to restore pressure boundary on at least one S/G.
IF valves CANNOT be closed, THEN DISPATCH personnel to close valves locally, one loop at a time:
- CLOSE MSIV and bypass valve as necessary USING (ECA-2.1).
- ISOLATE S/G atmospheric relief valve as necessary.
- ISOLATE blowdown locally as necessary.
CAUTION If total feed flow CAPABILITY of 410 gpm is available, FR-H.1, Loss of Secondary Heat Sink, should NOT be implemented.
NOTE Minimum detectable flow is assured by observing flow indicator response to valve movement.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
7, 8, 9 and 10 Page 17 of 66 Event
Description:
Seismic Event, MSLB on SG #2 outside Containment., failure of AFW pumps to AUTO start, and all MSIVs fail to auto close (cannot be closed manually).
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 RO
- 3. CONTROL feed flow to minimize RCS cooldown and prevent S/G dryout:
- a. CHECK T-cold cooldown rate less than 100ºF in the last one hour.
- b. CONTROL feed flow to maintain S/G NR levels less than 50%.
- c. IF any S/G NR level drops to 29% [39% ADV], THEN MAINTAIN at least minimum detectable flow to each S/G with low level.
- 4. MONITOR shutdown margin during RCS cooldown:
- REFER TO 1-SI-0-10, Shutdown Margin OR REACTINW Computer Program.
- 5. MONITOR T-hot stable or dropping.
CAUTION The 1500 psig RCP trip criteria is NOT applicable if the pressure drop is caused by S/G depressurization as indicated by RCS temperature at T-sat for S/G pressure.
NOTE Seal injection flow should be maintained to all RCPs.
- 6. MONITOR if RCPs should remain in service:
- a. Phase B DARK [MISSP].
- b. RCS pressure greater than 1500 psig.
- 7. MONITOR pzr PORVs and block valves:
- a. Pzr PORVs CLOSED.
- b. At least one block valve OPEN.
- 8. CHECK secondary side activity levels:
- S/G discharge rad monitors NORMAL.
- Condenser vacuum exhaust rad monitors NORMAL.
- S/G blowdown rad monitor recorders NORMAL trend prior to isolation,
- S/G sample results by Chemistry NORMAL.
CAUTION If offsite power is lost after SI reset, manual action will be required to restart the SI pumps and RHR pumps due to loss of SI start signal.
NOTE TO EVALUATOR: The transient in progress will cause an ORANGE PATH condition, which will require entry into FR-P.1 PRESSURIZED THERMAL SHOCK. The following steps are taken from FR-P.1.
- 1. CHECK RCS pressure greater than 150 psig.
- 2. CHECK T-cold stable or rising.
- 2. RESPONSE NOT OBTAINED IF T-cold dropping uncontrolled, THEN:
- ENSURE steam dump valves CLOSED.
- ENSURE S/G PORVs CLOSED.
IF RHR System in Shutdown Cooling mode, THEN STOP any cooldown from RHR.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
7, 8, 9 and 10 Page 18 of 66 Event
Description:
Seismic Event, MSLB on SG #2 outside Containment., failure of AFW pumps to AUTO start, and all MSIVs fail to auto close (cannot be closed manually).
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 IF uncontrolled cooldown continues, THEN:
- CLOSE MSIVs,
- ENSURE MSIV bypasses CLOSED.
- PLACE steam dump controls OFF.
CAUTION
- If the turbine-driven AFW pump is the only available source of feed flow, steam supply to the turbine-driven AFW Pump must be maintained from at least one S/G.
- If a faulted S/G is necessary for RCS temperature control feed flow to that generator should be maintained.
NOTE
- A Faulted S/G is any S/G that is depressurizing in an uncontrolled manner or is completely depressurized.
- Minimum detectable flow is assured by observing flow indicator response to valve movement.
- 3. CHECK S/G pressures:
- All S/G pressures controlled or rising.
- All S/G pressures greater than 120 psig.
- 3. RESPONSE NOT OBTAINED IF S/G with low or dropping press has NOT been isolated, THEN REFER TO E-2, Faulted Steam Generator Isolation, while continuing with this instruction.
ENSURE TD AFW pump being supplied from intact S/G.
IF all S/Gs Faulted, THEN CONTROL feed flow at minimum detectable flow to each S/G.
IF Faulted S/G necessary for RCS temp control, THEN CONTROL feed flow to minimum detectable flow to that S/G.
IF Faulted S/G NOT necessary for RCS temp control, THEN ISOLATE all feedwater to Faulted S/G.
- 4. MONITOR CST volume greater than 200,000 gal.
CRITICAL TASK SRO
- 5. MINIMIZE RCS cooldown:
- a. CHECK at least one intact S/G NR level greater than 29%
[39% ADV].
- b. CONTROL feed flow to intact S/G(s) as necessary.
- c. CONTROL S/G pressures as necessary.
- 6. MONITOR pzr PORVs and block valves:
- a. CHECK at least one block valve OPEN.
- b. CHECK RCS temperature less than 350 F.
- c. ARM COPS with 1-HS-68-334D and 1-HS-68-340AD.
- d. CHECK RCS pressure less than cold overpressure limit:
- REFER TO Figure 1, Cold Overpressure Limit Curve.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
1 Event #
7, 8, 9 and 10 Page 19 of 66 Event
Description:
Seismic Event, MSLB on SG #2 outside Containment., failure of AFW pumps to AUTO start, and all MSIVs fail to auto close (cannot be closed manually).
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 RO 6.d. RESPONSE NOT OBTAINED ENSURE at least one pzr PORV OPEN. WHEN press less than cold overpress limit, THEN PERFORM Substep 6g. GO TO Step 7.
- 7. CHECK ECCS in service:
- Flow thru BIT.
NOTE Either Loop 1 or 2 pzr spray valve is effective for Loop 2 RCP in service or for Loops 1, 3,
& 4 RCPs in service.
- 8. CHECK SI termination criteria:
- RCS subcooling greater than 115°F [135°F ADV].
CAUTION If offsite power is lost after SI reset, then manual action will be required to restart the SI pumps and RHR pumps.
- 9. RESET SI, and CHECK the following:
- SI ACTUATED permissive DARK.
- AUTO SI BLOCKED permissive LIT.
- 10. RESET Phase A and Phase B, and INITIATE Appendix A, (FR-P.1), CLA Breaker Operation.
- 11. ENSURE cntmt air in service:
- a. Aux air press greater than 75 psig [M-15].
- b. Cntmt air supply valves OPEN [M-15]:
- 1-FCV-32-80.
- 1-FCV-32-102.
- 1-FCV-32-110.
CRITICAL TASK
- 12. STOP ECCS pumps, and PLACE in A-AUTO:
- RHR pumps.
- SI pumps.
- All BUT one charging pump.
END OF SCENARIO
Simulator Console Operators Instructions NRC Scenario 1 SIMULATOR SETUP INFORMATION Page 20 of 66
Simulator Console Operators Instructions NRC Scenario 1 SIMULATOR SETUP INFORMATION Page 21 of 66
- 1.
ENSURE NRC EXAMINATION SECURITY has been established.
- 2.
RESET the Simulator to IC-331. (Must have correct password in order to RESET).
- 3.
ENSURE the following information appears on the Director Summary Display:
Key Description Event Final ms04a msiv fails to close 1-4 active ms04b msiv fails to close 1-11 active ms04c msiv fails to close 1-22 active ms04d msiv fails to close 1-29 active rp55a failure of auto start on motor driven aux feedpump a active rp55b failure of auto start on motor driven aux feedpump b active rp55c failure of auto start on motor driven aux feedpump c active rc07a pzr pressure transmitter fails to position chnl 1 68-340 1
100 rw18a ercw pump a-a sheared shaft 2
active cv09 vct level transmitter fails to position; 130-a 3
100 rm90106a failure of rm-90-106a cntmt bdlg lwr compt mon - particulate 4
0 mux_05c080 166-e seismic recording initiated 5
On mux_05c072 166-d obe spectra exceeded 5
On ms02b main steam line break outside containment sg #2 5
50
- 4.
Place the simulator in RUN momentarily. Acknowledge alarms, and then place the simulator in FREEZE.
Appendix D Scenario Outline Form ES-D-1 Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 1
N/A Transfer RCP Board power supplies.
2 N/A Raise reactor power using GO-3 3
1 1-PT-68-340 fails high ROLE PLAY: As work control, when contacted, inform the MCR that it will be an hour or more before the work package to trouble shoot and repair the failed channel is complete.
ROLE PLAY: As work control, when contacted to initiate performance of IMI-160, reply that the instrument shop will be notified and instructed to contact the control room before the IMI is to be performed.
4 2
ERCW pump A-A Shaft Shears ROLE PLAY: As Outside AUO, when contacted, confirm that the shaft for the A-A ERCW pump is sheared.
5 3
VCT Level transmitter 1-LT-62-130A fails to 100%
ROLE PLAY:
6 4
Lower Containment Radiation Monitor 1-RM-90-106 fails.
ROLE PLAY:
7 Seismic Event, 166-D, 166-E annunciators received.
ROLE PLAY: As Outside AUO, report that a violent shaking has been felt on site.
ROLE PLAY: As Nuclear Security and report that a violent shaking of the ground has been reported by multiple Security Officers at a variety of locations on site..
8 Main steam line break on #2 SG OUTSIDE containment.
ROLE PLAY: As Outside AUO, state that there is a large cloud of steam outside the plant.
ROLE PLAY: As Control Building AUO report that the ACR switches for the MSIVs are in the Aux position.
Insert remote function msr26a, msr26b, msr26c and msr26d to AUX. MSIVs WILL REMAIN OPEN.
ROLE PLAY: As Control Building AUO report that the fuses for the MSIVs have been removed per E-2, or ECA-2.1, Attachment 1.
Appendix D Scenario Outline Form ES-D-1 Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 9
ALL AFW pumps fail to start, requiring manual starts of all pumps.
10 NO MSIVs close, and CANNOT be closed manually.
Malfunctions to prevent closure are active and DO NOT require entry.
Appendix D Scenario Outline Form ES-D-1 Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Facility:
Watts Bar Scenario No.: 2 Op Test No.:
1 Examiners:
Operators:
Initial Conditions:
53% RTP, BOL.
Turnover:
The plant is at 53%, BOL. 1A Motor Driven AFW pump is out-of-service, and disassembled to replace a motor bearing. 1B-B Thermal Barrier Booster Pump is out-of service due to a seized pump shaft. 1-SI-0-21, Excore QPTR has been performed SAT. Commence a power escalation to 90%, at the maximum allowed rate Event No.
Malf. No.
Event Type*
Event Description 1
N/A N-SRO/BOP R-RO Commence power escalation to 90%.
2 RX02F I-SRO/RO TS-SRO Loop 2 RCS T-cold instrument fails HIGH. Requires manual control of rods to terminate rod insertion.
3 RX26G I-SRO/BOP TS-SRO SG #4 pressure transmitter fails LOW. Requires manual control of feed flow.
4 TU02I, J, K C-SRO/BOP High vibration on turbine bearings 9, 10 and 11. Requires manual reactor trip when one bearing reaches 14 mils.
5 RP01C I-SRO/RO Reactor trip failure (ATWS). Requires entry into FR-S.1.
6 TH03C M-ALL An RCS leak develops, progressing to a Small Break LOCA.
7 CS02A/B C-BOP/SRO Containment Spray fails to actuate on Hi-Hi Containment pressure actuation.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
2 Event #
1 Page 25 of 66 Event
Description:
Commence power escalation to 90%.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Scenario 2 - Summary Initial Condition - IC-332, 53%, BOL.
Turnover The plant is at 53%, MOL. 1A Motor Driven AFW pump is out-of-service, and disassembled to replace a motor bearing. LCO 3.7.5.b was entered 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> ago. Expected to return to service in approximately 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
1B-B Thermal Barrier Booster Pump is out-of service due to seized pump shaft. OR-14.10 was entered due to the thermal barrier booster pumps. Expected return to service is to be determined. 1-SI-0-21, Excore QPTR, has been performed SAT. Commence a power escalation to 90%. Boron concentration is currently at 1080 ppm.
Event 1 Crew commences a power escalation to 90% per GO-4, Normal Power Operation.
Event 2 A Loop 2 RCS Tcold instrument fails HIGH, causing control rods to continuously insert. Operator takes manual control of rods to stop the insertion. AOI-2, Malfunction of Reactor Control System, is entered. SRO evaluates Technical Specifications.
Event 3 SG #4 pressure transmitter 1-PT-1-27A fails LOW, causing the steam flow signal for SG #4 to lower, resulting in lowering feed flow. Operator takes manual control of feed flow to stabilize level in SG #4. SRO implements AOI-16, Loss of Normal Feedwater. SRO evaluates Technical Specifications for the failed instrument.
Event 4 Main Turbine bearings 9, 10, and 11 begin experiencing high vibration. Ramps in over a 5 minute period.
Requires a manual reactor trip prior to any bearing exceeding 14 mils.
Event 5 ATWS. The RO is unable to trip the reactor from the control room and must manually drive rods; the BOP manually trips the turbine. Crew implements FR-S.1, ATWS.
Event 6 An RCS leak develops and progresses to a Small Break LOCA (ramp to 54% severity over 3 minutes).
Event 7 Containment Spray fails to auto actuate on Hi-Hi containment pressure. Requires manually starting both Containment Spray Pumps.
Critical Task 1 Critical Task 2 FR-S.1 - A: Isolate the main turbine from the SGs within 30 seconds of the discovery of the ATWS condition FR-S.1-C: Insert negative reactivity into the core by at least one of the following methods before completing the immediate-action steps of FR-S.1:
- De-energize the control rod drive MG sets
- Insert RCCAs
- Establish emergency boration flow to the RCS Critical Task 3 FR-S.1 - B: Start AFW pumps within 60 seconds of
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
2 Event #
1 Page 26 of 66 Event
Description:
Commence power escalation to 90%.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 the ATWS condition.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
2 Event #
1 Page 27 of 66 Event
Description:
Commence power escalation to 90%.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Console Operator: No action required for Event 1 None: Crew will continue power increase from 53% using GO-4, Normal Power Operation, Section 5.5 at Step [23]
BOP Increase turbine load as directed.
BOP Start secondary equipment as directed.
RO Withdraw control rods as directed.
RO Perform dilutions as directed.
SRO Direct reactivity manipulations.
The following actions are taken from SOI-62.02, Boron Concentration Control, Section 6.6, Minor Dilution.
NOTES
- 1) Section 6.6, Minor Dilution, may be reproduced, laminated, displayed, reused, etc. as desired.
- 2) Minor Dilution is defined as the addition of Primary Water done several times each shift to compensate for fuel burn-up, and maintain Tavg on program.
[1] ENSURE 1-HS-68-341H, BACKUP HEATER C, is ON, to equalize Pzr-RCS CB.
[2] ADJUST 1-FQ-62-142, PW BATCH COUNTER, for required quantity.
[3] PLACE 1-HS-62-140B, VCT MAKEUP MODE in DIL.
[4] TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to START.
[4.1] CHECK Red light is LIT.
[5] MONITOR the following parameters:
1-PI-62-122 1-M-6 VCT PRESS 1-LI-62-129A 1-M-6 VCT LEVEL 1-FI-62-142 1-M-6 PW TO BLENDER FLOW 1-FQ-62-142 1-M-6 PW BATCH COUNTER 1-FQ-62-139 1-M-6 PW BATCH COUNTER RO
[6] WHEN dilution is COMPLETE, AND 1-FCV-62-128 is closed, THEN PLACE 1-HS-62-140B, VCT MAKEUP MODE, in AUTO.
[7] TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to START.
[7.1] CHECK Red light is LIT The following actions are taken from GO-4 GO-4, Normal Power Operation, Section 5.5 at Step [23]
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
2 Event #
1 Page 28 of 66 Event
Description:
Commence power escalation to 90%.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9
[23] CONTINUE ascension to 90% power (70 to 74% if following refueling) by performing the following:
[23.1] IF during any of the following steps the REFERENCE changes in an undesired manner, THEN ADJUST VPL to stop turbine load rise.
OR PUSH TURBINE MANUAL to place the turbine control mode in manual mode and PROCEED to section 5.6 BOP
[23.2] ADJUST VALVE POSITION LIMIT to 90% or to 5% above the Gov Control Indication.
[23.3] SET LOAD RATE at predetermined value.
[23.4] PUSH REFERENCE CONTROL (raise) button to set desired load in SETTER display.
NOTE RCS should be diluted to raise TAVG, then Turbine load raised along with TAVG. Control rods will be used along with dilution to maintain I and, if needed, for temperature.
[23.5] PUSH GO button.
[23.6] MONITOR Generator Megawatts RISING.
NOTE: Step 23 will be repeated on a repetitive basis until power changes have been made.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
2 Event #
2 Page 29 of 66 Event
Description:
Loop 2 T cold Instrument fails High Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Console Operator: When directed, initiate Event 2 Indications available:
1-M-5A 91-F EAGLE PROC PROT CH II RTD FAILURE 1-M-5A 93-A RCS LOOP T DEVIATION 1-M-5A 94-A TAVG-T REF DEVIATION 1-M-5A 94-B TAVG-T AUCT DEVIATION Loop 2 RCS Tavg 1-TI-68-2A indicates approximately 590°F.
Control Rods insert at 72 steps/minute.
RO Diagnose and announce failure.
RO May place Control Rods in Manual, after confirming that no runback is in progress.
SRO Enter and direct actions of AOI-2, Malfunction Of Reactor Control System, Section 3.2, Continuous Rod Withdrawal/Insertion and directs crew actions.
- 1. PLACE control rods in MAN.
- 2. CHECK control rod movement STOPPED.
- 3. MAINTAIN T-avg on PROGRAM. (Reference Attachment 1)
USE control rods.
OR ADJUST turbine load.
- 4. CHECK loop T-avg channels NORMAL.
RO Determines that Loop 2 T-avg channel is NOT NORMAL, by observing 1-TI-68-25E on Panel 1-M-5.
- 4. Enters Step 4, Response Not Obtained Column for actions.
RO DEFEAT failed loop T and loop T-avg channels by placing 1-XS-68-2D, T CHANNEL DEFEAT, and 1-XS-68-2M, TAVG CHANNEL DEFEAT, in failed channel position (Loop 2) then PULL.
RO ENSURE TR-68-2A placed to operable channel using.1-XS-68-2B, T RCDR TR-68-2A LOOP SELECT [1-M-5]. TR-68-2A is in Loop l position.
SRO NOTIFY Maintenance to implement IMI-160 for failed channel.
RO WHEN at least 3 minutes have elapsed since failed T-avg channel is defeated, THEN a) ENSURE T-avg and T-ref within 1°F.
b) ENSURE zero demand on control rod position indication [1-M-4].
c) PLACE rods in AUTO.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
2 Event #
2 Page 30 of 66 Event
Description:
Loop 2 T cold Instrument fails High Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 RO
- 5. CHECK Auct Tavg NORMAL on 1-TR-68-2B.
- 6. CHECK NIS power range channels NORMAL.
- 7. CHECK the following:
Turbine impulse pressure channel 1-PI-1-73, NORMAL.
Tref and Auct Tavg NORMAL on 1-TR-68-2B (Reference )
- 8. MONITOR core power distribution parameters:
Power range channels.
Flux Indicators.
T-avg.
Loop T.
Incore TCs.
Feed flow/Steam flow.
- 9. INITIATE repairs to failed equipment.
SRO Contacts Work Control to initiate troubleshooting and repairs to Loop 2 T-avg instrument.
- 10. REFER TO Tech Specs:
SRO 3.3.1-1, Function 6. Overtemperature T, Condition W.
Function 7. Overpower T, Condition W.
Function 13. SG Water Level Low-Low Coincident with Vessel T, Condition V 3.3.2-1, Function 6.b Auxiliary Feedwater Start, SG Water Level Low-Low Coincident with Vessel T, Condition N CAUTION Allowing at least 5 minutes between any rod control input (i.e., T-avg, T-ref, or NIS) change and placing rods in AUTO, will help prevent undesired control rod movement.
- 11. NOTIFY Chemistry of any reactor power changes greater than 15% in one hour.
SRO 12 IF loop T and loop Tavg channels were defeated due to Tavg channel failure, and Tavg channel has been repaired, THEN PUSH IN 1-XS-68-2D, T CHANNEL DEFEAT, and 1-XS-68-2M, TAVG CHANNEL DEFEAT, and select away from all T and Tavg channels. (Step is conditional and will be N/Aed)
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
2 Event #
2 Page 31 of 66 Event
Description:
Loop 2 T cold Instrument fails High Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 SRO 13.WHEN conditions allow auto rod control, THEN:
- a. ENSURE T-avg and T-ref within 1°F.
- b. ENSURE zero demand on control rod position indication [1-M-4].
- c. PLACE rods in AUTO.
- 14. WHEN conditions allow auto pzr level control, THEN ENSURE pzr level returned to normal program, AND PLACE 1-FCV-62-93 in AUTO SRO
- 15. RETURN TO Instruction in effect.
CREW Crew Brief would conducted for this event as time allows prior to the next event.
CREW Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.
Operations Management - Shift Manager.
Maintenance Personnel - Maintenance Shift Supervisor (MSS). (Note: Maintenance notification may be delegated to the Shift Manager).
Lead Examiner may cue the next event.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
2 Event #
3 Page 32 of 66 Event
Description:
SG #4 pressure transmitter fails LOW Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Indications available:
1-M-4C 63-F SG LEVEL DEVIATION 1-M-6B 119-A SG 4 PRESS LO 1-M-6B 123-A SG 4 PRESS NEG RATE BOP Diagnose and announce failure BOP May place SG #4 main feedwater regulating valve in Manual in order to minimize the effect of the instrument failure.
SRO Enters AOI-16, Loss Of Normal Feedwater, Section 3.6, MFW reg or bypass reg valve control failure and directs crew actions BOP
- 1. CONTROL failed MFW reg or bypass reg valve in MANUAL.
- 2. EVALUATE placing control rods in MANUAL.
NOTE If the main reg. valve is malfunctioning, the bypass reg. valve for the affected loop may be manually positioned as necessary up to 0.85 x 106 lb/hr flow to dampen oscillations in feedwater flow. A power tilt in the affected core quadrant may occur due to a rise in bypass flow. Flows above 84,500 lbm/hr in the bypass line will invalidate the value of computer point U1118.
- 3. CHECK SG levels on bypass reg valve control.
SRO Enters Response Not Obtained Column and then proceeds to Step 5.
- 5. CHECK S/G levels returning to PROGRAM.
- 6. MONITOR TDMFW Pump speed normal for current power level.
NOTE A LO FW FLOW WTR HAMMER annunciation [59-C] will be received when any main feedwater flow drops to less than 0.75 x 106 lb/hr.
- 7. WHEN any S/G MFW flow drops to less than 0.55 x 106 lb/hr, THEN INITIATE manual anti-water hammer actions: No actions are required.
CAUTION Power range N41 controls S/G 1 and S/G 4 MFW reg valves. N42 controls S/G 2 and S/G 3 MFW reg valves.
NOTE All power range monitors input to auctioneered high anticipatory circuit for bypass FW reg valves.
- 8. CHECK power range N41 through N44 NORMAL.
NOTE Steps 7 & 8 should end up having the same channel (A or B) selected for steam flow and feed flow on each S/G to ensure a loss of voltage to any one channel will have minimal effect on the affected S/G level.
- 9. CHECK controlling steam flow Channels NORMAL. Reports that SG #4 is NOT normal
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
2 Event #
3 Page 33 of 66 Event
Description:
SG #4 pressure transmitter fails LOW Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 SRO
- 9. RESPONSE NOT OBTAINED BOP
- a. SELECT operable channel.
- b. EVALUATE effect of the failed channel on the MFPs Speed Control and ADJUST in MANUAL as necessary while continuing this section.
- 10. CHECK controlling FW flow channels NORMAL.
- 11. CHECK press compensation channel(s) NORMAL.
- 11. RESPONSE NOT OBTAINED REFER to Tech Specs SRO 3.3.2-1, Function 1.e Safety Injection - Steam Line Pressure-Low, Condition D Function 4.d Steam Line Isolation - Steam Line Pressure-Low, Condition D SRO
- 12. IF affected S/G controlling channel and level NORMAL, THEN
- a. RETURN MFW reg valve to AUTO.
- b. RETURN TDMFWP Speed Control to AUTO (if in MANUAL).
- 13. WHEN conditions allow auto rod control, THEN,
- a. ENSURE T-avg and T-ref within 1°F.
- b. ENSURE zero demand on control rod position indication
[1-M-4].
- c. PLACE rods in AUTO.
SRO 13.INITIATE repairs to failed equipment. (Step miss-numbered in actual plant procedure)
- 14. RETURN TO Instruction in effect.
CREW Crew Brief would be conducted for this event as time allows prior to the next event.
CREW Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.
Operations Management - Shift Manager.
Maintenance Personnel -Maintenance Shift Supervisor (MSS). (Note: Maintenance notification may be delegated to the Shift Manager).
Lead Examiner may cue the next event.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
2 Event #
4 Page 34 of 66 Event
Description:
High vibration on turbine bearings 9, 10 and 11 Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Console Operator: When directed, initiate Event 4 Indications available:
1-M-2A 23-A TURB/GEN VIBRATION HI/HI-HI ICS display for Main Turbine indicates rising vibration on multiple bearings.
BOP Diagnose and announce failure BOP Respond to Annunciator 23-A TURB/GEN VIBRATION HI/HI-HI SRO Direct performance of ARI 23-A.
SRO Announces the High Vibration Limit of 14 mils to the crew BOP
[1] IF the cause of this alarm is COUPLING vibration, THEN notify the Sys Eng. No Operator action is required.
[2] MONITOR 1-CRT-47-121 [1-M-2] to determine which bearing has possible vibration problems.
[3] DISPATCH Operator to perform the following:
- CHECK local indications on 1-L-792.
- SOUND Turbine bearings.
- CHECK Turbine lube oil temperature.
- CHECK Seal Oil temperature.
[4] ATTEMPT to stabilize or reduce bearing vibration by varying one or more of the following parameters within normal operation limits:
- Turbine bearing lube oil supply temperature.
- Generator Megawatts and/or VARS.
- Seal Oil temperature.
Note: (1) For 1-XX-47-131 the Hi alarm set point for the #11 exciter bearing, is 10 mils (ref.
TACF 1-08-0003-047)
[5] IF bearing vibration is above 7 mils (10 mils for # 11 bearing),
THEN NOTIFY Engineering AND EVALUATE if load reduction or unit shutdown warranted.
[6] IF bearing vibration continues to rise above evaluated limits, THEN EVALUATE rapid load reduction per AOI-39, or tripping the turbine prior to exceeding 14 mils vibration.
[7] ENSURE Turbine is operated within startup and loading limitations of SOI-47.02, Turbo-generator Startup Operation.
[8] ENSURE lube oil temperature, condenser vacuum, sealing steam pressure, and exhaust hood temperature are normal.
SRO Directs Reactor Trip and Turbine trip prior to the 14 mil setpoint being reached.
Simulator Console Operators Instructions NRC Scenario 2 SIMULATOR SETUP INFORMATION Page 35 of 66 Console Operator: Open Rod Drive MG set input breakers for 480 V Unit Boards and Reactor Trip breakers by inserting Event 6. Time delays will cause breaker repositioning on a staggered basis with the first breaker opening at 90 seconds and the last breaker opening at 135 seconds.
Indications available:
MANUAL Reactor Trip initiated in response to the turbine high vibration condition is UNSUCCESSFUL from both 1-M-4 and 1-M-6 Reactor Trip switches.
RO Performs IMMEDIATE OPERATOR ACTIONS of FR-S.1-Attempts to trip the reactor from both the 1-M-4 and the 1-M-6 Reactor Trip switches.
CRITICAL TASK RO Performs IMMEDIATE OPERATOR ACTION of FR-S.1 - Ensures control rod insertion by either AUTOMATIC or MANUAL means.
While insertion of rods is being accomplished the RO may dispatch an AUO to open the Rod Drive MG set input breakers at the 480 V Unit Boards, and another AUO to open the Reactor Trip breakers locally.
CRITICAL TASK BOP Performs IMMEDIATE OPERATOR ACTION of FR-S.1-Manually trips the turbine upon recognition of the ATWS conditions.
CRITICAL TASK BOP Manually starts the Auxiliary Feedwater Pumps upon recognition of the ATWS conditions.
Note to Evaluators: The small break LOCA event will be entered automatically 1 minute after the reactor trip breakers are manually opened.
SRO Implements FR-S.1, Nuclear Power Generation/ATWS RO
[1] ENSURE Reactor Trip:
Reactor trip and bypass breakers OPEN.
RPIs at bottom of scale.
Neutron flux DROPPING.
[1] RESPONSE NOT OBTAINED Manually TRIP reactor.
IF reactor will NOT trip, THEN INSERT control rods.
(NOTE: since this is an IMMEDIATE OPERATOR ACTION, the RO is already performing these actions.)
[2] ENSURE Turbine Trip: (NOTE: since this is an IMMEDIATE OPERATOR ACTION, the BOP has already performed these actions.)
[3] CHECK AFW pumps operation:
- b. TD AFW pump RUNNING.
Simulator Console Operators Instructions NRC Scenario 2 SIMULATOR SETUP INFORMATION Page 36 of 66
- c. LCVs in AUTO or controlled in MANUAL.
[3] RESPONSE NOT OBTAINED Manually START pumps and open valves as necessary. (NOTE: since this is an IMMEDIATE OPERATOR ACTION, the BOP has already performed these actions.)
[4] INITIATE RCS Boration:
- a. ENSURE at least one centrifugal charging pump RUNNING.
- b. OPEN RWST outlet valves 1-LCV-62-135 and 1-LCV-62-136.
- c. CLOSE VCT outlet valves 1-LCV-62-132 and 1-LCV-62-133.
- d. OPEN BIT outlet valves 1-FCV-63-25 and 1-FCV-63-26
- e. CHECK BIT flow.
- f. PLACE BA pumps in FAST speed.
- g. Throttle OPEN emergency borate valve 1-FCV-62-138 to maintain boric acid flow RO
[5] CHECK pzr pressure less than 2335 psig.
[6] VERIFY Cntmt Vent Isolation:
- Train A GREEN.
- Train B GREEN.
[7] IF AFW flow established, THEN
- a. PLACE 1-HS-3-45 to LONG CYCLE RECIRC.
- b. PLACE MFW Bypass Reg Valves in AUTO.
[8] IF SI actuated OR required, THEN PERFORM Steps 1 through 6 of E-0, Reactor Trip or Safety Injection, as time allows.
Assigns E-0, Steps 1 through 6 to the BOP.
The RO may have dispatched an AUO to open the Rod Drive MG set input breakers at the 480 V Unit Boards, and another AUO to open the Reactor Trip breakers locally while initially inserting the control rods.
[9] ENSURE the following trips:
- a. Reactor Trip.
- a. RESPONSE NOT OBTAINED DISPATCH operator to locally trip reactor:
- OPEN reactor trip breakers and MG set output breakers
[MG set room].
- OPEN reactor trip breakers and MG set output breakers
[MG set room].
Simulator Console Operators Instructions NRC Scenario 2 SIMULATOR SETUP INFORMATION Page 37 of 66
- OPEN breakers to MG sets [480V unit boards A and B].
- b. Turbine Trip.
The BOP tripped the turbine upon recognition of the ATWS conditions.
[10] MAINTAIN rod insertion UNTIL rods fully inserted.
Rods are fully inserted based on local operator actions already performed.
[11] REFER TO EPIP-1, Emergency Plan Classification Flowchart for ATWS event.
[12] MONITOR reactor subcriticality:
- a. CHECK Power range channels less than 5%.
- b. CHECK Intermediate range startup rate NEGATIVE.
- c. GO TO Step 21.
[21] TERMINATE emergency boration:
- a. PLACE BA transfer pumps in SLOW speed.
- b. CLOSE emergency borate valve 1-FCV-62-138.
- c. IF alternate boration opened, THEN Locally CLOSE 1-ISV 929.
CAUTION Evaluation of boration requirements should consider subsequent cooldown actions in addition to current conditions.
[22] DETERMINE shutdown margin requirements:
- a. NOTIFY Chemistry to sample RCS.
- b. REFER TO 1-SI-0-10, Shutdown Margin, OR REACTINW Computer Program.
- c. INITIATE RCS boration as necessary:
- d. INITIATE flushing boric acid piping as necessary:
- REFER TO AOI-34, Immediate Boration.
[23] IF SI actuated, THEN RETURN TO Instruction in effect.
The following actions are taken from E-0, Reactor Trip or Safety Injection SRO Transition is made to E-0.
SRO Directs performance of the high level steps 1-6, since these steps have already been addresses by the BOP during parallel performance with FR-S.1.
[1] ENSURE reactor trip:
[2] ENSURE Turbine Trip:
[3] CHECK 6.9 kV shutdown boards energized:
[4] CHECK SI actuated:
Simulator Console Operators Instructions NRC Scenario 2 SIMULATOR SETUP INFORMATION Page 38 of 66 BOP
[5] EVALUATE support systems:
During performance of this step, the BOP will determine that the Containment Spray system did not automatically start upon the receipt of a hi-hi cntmt pressure signal. The BOP will manually actuate containment spray.
[6] ANNOUNCE reactor trip and safety injection over PA system.
[7] ENSURE secondary heat sink available with either:
- At least one S/G NR level greater than 29% [39% ADV].
[8] MONITOR RCS temp stable at or trending to 557°F:
[9] ENSURE excess letdown valves CLOSED:
- 1-FCV-62-54
- 1-FCV-62-55 RO
[10] CHECK pzr PORVs and block valves:
- a. Pzr PORVs CLOSED.
- b. At least one block valve OPEN.
[11] CHECK pzr safety valves CLOSED:
EVALUATE tailpipe temperatures and acoustic monitors.
[12] CHECK pzr sprays CLOSED.
[13] CHECK if RCPs should remain in service:
- a. Phase B signals DARK [MISSP].
- b. RCS pressure greater than 1500 psig.
[14] CHECK S/G pressures:
- All S/G pressures controlled or rising.
- All S/G pressures greater than 120 psig.
[15] CHECK for RUPTURED S/G
- All S/Gs narrow range levels CONTROLLED or DROPPING.
- Secondary side radiation NORMAL from Appendix A.
[16] CHECK cntmt conditions:
- Cntmt pressure NORMAL.
- Radiation NORMAL from Appendix A.
- Cntmt sump level NORMAL.
- Cntmt temp ann window DARK [104-B].
SRO (Since cntmt parameters are abnormal, the SRO will enter the RNO and make the transition to E-1.)
Simulator Console Operators Instructions NRC Scenario 2 SIMULATOR SETUP INFORMATION Page 39 of 66
- GO TO E-1, Loss of Reactor or Secondary Coolant.
[1] CHECK if RCPs should remain in service:
- a. Phase B signals DARK [MISSP].
- b. RCS pressure greater than 1500 psig.
[2] REFER TO EPIP-1, Emergency Plan Classification Flowchart.
[3] RECORD current time to mark initiation of LOCA and determination of time for hot leg recirc.
[4] CHECK S/G pressures:
- All S/G pressures controlled or rising.
- All S/Gs pressures greater than 120 psig.
[5] MAINTAIN Intact S/G NR levels:
- a. MONITOR levels greater than 29% [39% ADV].
- b. CONTROL intact S/G levels between 29% and 50% [39%
and 50% ADV].
[6] CHECK secondary radiation:
- S/G discharge monitors NORMAL.
- Condenser vacuum exhaust rad monitors NORMAL.
- S/G blowdown rad monitor recorders NORMAL trend prior to isolation.
[7] ENSURE cntmt hydrogen analyzers in service:
- PLACE 1-HS-43-200A in ANALYZE [M-10].
- PLACE 1-HS-43-210A in ANALYZE [M-10].
- CHECK low flow lights not lit [M-10].
- Locally CHECK low analyzer temp lights NOT lit [North wall of Train A 480V SD Bd rm].
[8] MONITOR pzr PORVs and block valves:
- a. Pzr PORVs CLOSED.
- b. At least one block valve OPEN.
[9] DETERMINE if cntmt spray should be stopped:
- a. MONITOR cntmt pressure less than 2.0 psig.
- b. CHECK at least one cntmt spray pump RUNNING.
- c. RESET cntmt spray signal.
- d. STOP cntmt spray pumps, and PLACE in A-AUTO.
- e. CLOSE cntmt spray discharge valves 1-FCV-72-2 and 1-FCV-72-39.
Simulator Console Operators Instructions NRC Scenario 2 SIMULATOR SETUP INFORMATION Page 40 of 66 BOP
[10] ENSURE both pocket sump pumps STOPPED [M-15]:
[11] CHECK SI termination criteria:
- a. CHECK RCS subcooling greater than 65ºF [85ºF ADV].
[11] a. RESPONSE NOT OBTAINED
- a. ** GO TO Caution prior to Step 12.
[12] RESET SI and CHECK the following:
- SI ACTUATED permissive DARK.
- AUTO SI BLOCKED permissive LIT.
[13] DETERMINE if RHR pumps should be stopped:
- a. CHECK RCS pressure greater than 150 psig.
- c. CHECK RCS pressure stable or rising.
- d. STOP RHR pumps and PLACE in A-AUTO.
- e. MONITOR RCS pressure greater than 150 psig.
[14] CHECK pressure in all S/Gs controlled or rising.
[15] CHECK RCS pressure stable or dropping.
[16] MONITOR electrical board status:
- a. CHECK offsite power available
- b. CHECK all shutdown boards ENERGIZED by offsite power.
- c. PLACE any unloaded D/G in standby USING SOI-82 Diesel Generators.
[17] INITIATE BOP realignment:
- REFER TO AOI-17, Turbine Trip.
[18] INITIATE 480V board room breaker alignments USING the following:
- Appendix A (E-1), CLA Breaker Operation.
- Appendix B (E-1), Ice Condenser AHU Breaker Operation.
- Appendix C (E-1), 1-FCV-63-1 Breaker Operation.
- Appendix D (E-1), 1-FCV-63-22 Breaker Operation.
[19] DETERMINE if hydrogen igniters should be energized:
- a. CHECK hydrogen analyzers in service.
- b. CHECK cntmt hydrogen less than 5% [M-10].
Simulator Console Operators Instructions NRC Scenario 2 SIMULATOR SETUP INFORMATION Page 41 of 66
- c. ENERGIZE hydrogen igniters [M-10]:
- 1-HS-268-73 ON.
- 1-HS-268-74 ON.
[20] ENSURE RHR available for cntmt sump recirculation:
[21] EVALUATE plant equipment status:
- REFER TO Appendix E (E-1), Equipment Evaluation.
[22] CHECK Aux Bldg radiation for loss of RCS inventory outside cntmt:
- a. Area monitor recorders 1-RR-90-1 and 0-RR-90-12A Aux Bldg points NORMAL.
- b. Vent monitor recorder 0-RR-90-101 NORMAL trend prior to isolation.
[23] NOTIFY Chemistry of event status and plant conditions.
[24] DETERMINE if RCS cooldown and depressurization is required:
- a. CHECK RCS pressure greater than 150 psig.
The following steps are taken from ES-1.2, Post LOCA Cooldown and Depressurization.
[1] PREPARE for switchover to RHR cntmt sump:
- a. RESTORE power to 1-FCV-63-1, RWST to RHR suction, USING Appendix A, (ES-1.2) 1-FCV-63-1 Breaker Operation.
CAUTION If offsite power is lost after SI reset, manual action will be required to restart the SI pumps and RHR pumps due to loss of SI start signal.
[2] RESET SI, and CHECK the following:
- SI ACTUATED permissive DARK.
- AUTO SI BLOCKED permissive LIT.
[3] RESET Phase A and Phase B.
[4] ENSURE cntmt air in service:
- a. Aux air press greater than 75 psig [M-15].
Simulator Console Operators Instructions NRC Scenario 2 SIMULATOR SETUP INFORMATION Page 42 of 66
- b. Cntmt air supply valves OPEN [M-15]:
- 1-FCV-32-80.
- 1-FCV-32-102.
- 1-FCV-32-110.
[5] MONITOR electrical board status:
- a. CHECK offsite power available.
- b. CHECK all shutdown boards ENERGIZED by offsite power.
- c. CHECK all unit boards ENERGIZED.
- d. PLACE any unloaded D/G in standby USING SOI-82 Diesel Generators.
NOTE Backup heater C bank may need to be placed in AUX at the breaker compt to ensure it is turned OFF.
[6] ENSURE pzr heaters off:
- PLACE Backup heaters A-A OFF.
- PLACE Backup heaters B-B OFF.
- PLACE Backup heaters C OFF.
- PLACE Control heaters D OFF.
[7]. DETERMINE if RHR pumps should be stopped:
- b. CHECK RCS press:
- RCS press greater than 150 psig.
- RCS press stable or rising.
- c. STOP RHR pumps, and PLACE in A-AUTO.
- d. MONITOR RCS press greater than 150 psig.
[8] MONITOR Intact S/G NR levels:
- a. At least one intact S/G NR level greater than 29% [39% ADV].
- b. CONTROL intact S/G levels between 29% and 50% [39%
and 50% ADV].
[9] EVALUATE Motor-Driven AFW Pumps recirc flow per FOP.
NOTE The following boration will result in a CB in the ACTIVE portion of the RCS which will be higher than the calculated cold shutdown CB.
NOTE TO EVALUATOR: The Surrogate STA will provide a value for RCS boron concentration which will satisfy cold shutdown conditions. This value is 1561 ppm.
[10] INITIATE RCS boration to cold shutdown boron concentration:
- a. DETERMINE cold shutdown CB:
- REFER TO 1-SI-0-10, Shutdown Margin, OR REACTINW Computer Program.
- b. INITIATE RCS boration:
Simulator Console Operators Instructions NRC Scenario 2 SIMULATOR SETUP INFORMATION Page 43 of 66
[11] MONITOR shutdown margin during RCS cooldown:
- RCS hot leg.
- CVCS letdown line.
NOTE After the low steamline pressure SI signal is blocked, main steamline isolation will occur if the high steam pressure rate setpoint is exceeded.
INITIATE RCS cooldown to cold shutdown:
- a. WHEN RCS pressure is less than 1962 psig (P-11), THEN
- BLOCK low pzr pressure SI.
- BLOCK low steam pressure SI.
- b. MAINTAIN T-cold cooldown rate less than 100ºF in one hour.
- c. DUMP steam to condenser from Intact S/Gs.
- d. IF RHR in shutdown cooling mode, THEN USE RHR and S/Gs for cooling.
END OF SCENARIO
Simulator Console Operators Instructions NRC Scenario 2 SIMULATOR SETUP INFORMATION Page 44 of 66
- 1.
ENSURE NRC EXAMINATION SECURITY has been established.
- 2.
RESET the Simulator to IC-332. (Must have correct password in order to RESET).
- 3.
ENSURE the following information appears on the Director Summary Display:
Key Description Event Final rp01c manual and automatic reactor trip signal failure (atws) active cs02 failure of cs signal by hi-hi cntmt pressure active rx02f cold leg 2 rtd 2 failure 1
100 rx26g stm gen pres transmitter failure, chnl I pt-1-27a 2
0 tu02k main turbine high vibes exciter brg #11 3
95 tu02j main turbine high vibes exciter brg #10 3
90 tu02i main turbine high vibes gen brg #9 3
100 th03c loca - small leak loop 3 4
50 rd01 rod control mg set #1 bkr 6
open rd02 rod control mg set #2 bkr 6
open rp15a reactor trip breaker rta trip 6
open rp15b reactor trip breaker rtb trip 6
open fw07a electric afw pump a trip active hs-3-118a-1 01160 aux fw pump a-a motor sw (green) active off hs-3-335 intentionally left blank active close hs-3-335-1 hs-3-355 indicating lights active off hs-3-335-2 hs-3-355 indicating lights active off hs-3-118a hs-3-118a auxiliary feedwater pump a-a motor sw active ptlock
- 4.
Place Hold Order Tag on 1A MD AFWP A handswitch, 1-HS-3-118A.
- 5.
Place the simulator in RUN momentarily. Acknowledge alarms and then place the simulator in FREEZE.
Appendix D Scenario Outline Form ES-D-1 Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 1
N/A Commence power escalation to 90%.
2 1
Loop 2 RCS T-cold instrument fails HIGH.
ROLE PLAY: As work control, when contacted, inform the MCR that it will be an hour or more before the work package to trouble shoot and repair the failed channel is complete.
ROLE PLAY: As work control, when contacted to initiate performance of IMI-160, reply that the instrument shop will be notified and instructed to contact the control room before the IMI is to be performed.
3 2
SG #4 pressure transmitter fails LOW.
ROLE PLAY: As work control, when contacted, inform the MCR that it will be an hour or more before the work package to trouble shoot and repair the failed channel is complete.
ROLE PLAY: As work control, when contacted to initiate performance of IMI-160, reply that the instrument shop will be notified and instructed to contact the control room before the IMI is to be performed.
4 3
High vibration on turbine bearings 9, 10 and 11.
ROLE PLAY:
5 N/A (malfunction entered as part of setup)
Reactor trip failure (ATWS).
ROLE PLAY: As Turbine Building AUO, acknowledge direction to open the 480 V breakers to the Rod Drive MG sets.
ROLE PLAY: As Control Building AUO, acknowledge direction to manually open the Reactor Trip breakers and MG set output breakers.
Activate Simulator Event 6, in order to begin the sequence of events to locally open breakers after the AUOs have been dispatched.
6 4
An RCS leak develops, progressing to a Small Break LOCA.
7 N/A (malfunction entered as part of setup)
Containment Spray fails to actuate on Hi-Hi Containment pressure actuation.
Appendix D Scenario Outline Form ES-D-1 Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Facility:
Watts Bar Scenario No.: 3 Op Test No.:
1 Examiners:
Operators:
Initial Conditions:
100% RTP, EOL, RCS boron is 69 ppm.
Turnover:
1-SI-85-2 was temporarily suspended. Control Bank D rods need to be exercised to complete the surveillance; then reduce power to 95% for removing 1C Condensate Booster Pump from service due to an oil leak. 1A Motor Driven Aux Feed Pump was removed from service 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago for motor repairs. LCO 3.7.5.b was entered. The 1A MD AFW Pump is expected to be returned to service in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Event No.
Malf. No.
Event Type*
Event Description 1
N/A N-SRO/RO Perform 1-SI-85-2 Reactivity Control Systems Moveable Assemblies (Mode 1 and 2).
2 N/A R-SRO/RO Power reduction to 95%.
3 NI07B I-RO/SRO I-BOP TS-SRO Power Range N42 Fails High.
4 CV01A C-SRO/RO TS-SRO Charging Pump 1A-A trips on instantaneous overcurrent.
5 FW06 FW05A C-SRO/BOP R-RO Main Feedwater Pump 1A trips due to low bearing oil pressure. Standby Main Feedwater Pump trips on auto start.
6 FW05B M-ALL Main Feedwater Pump 1B trips due to low bearing oil pressure.
7 ED06B C-SRO/BOP Loss of 1B 6.9 KV Shutdown Board on differential.
8 FW22C C-SRO/BOP TDAFDW Pump becomes steam/air bound. (FR-H.1).
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
1 Page 47 of 66 Event
Description:
Perform 1-SI-85-2, Reactivity Control Moveable Assemblies.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Scenario 3 - Summary Initial Condition - IC-333, 100%, EOL.
Turnover 100% RTP, EOL, RCS boron is 69 ppm. Rod Control is in MANUAL. 1-SI-85-2 performance is in progress, complete through Control Bank C. 1A Motor Driven AFW pump is out-of-service, currently disassembled to replace motor bearings. Expected return to service in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Oil is currently drained from the pump.
Repairs are expected to be complete in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. 1B-B Thermal Barrier Booster Pump out-of service due to seized pump shaft. Expected return to service has yet to be determined.
Event 1 Perform 1-SI-85-2 Reactivity Control Systems Moveable Assemblies (Mode 1 and 2), Sections 6.8 Control Bank D and 6.9 Restoration.
Event 2 Perform power reduction to 95% to support removal of 1C Condensate Booster Pump from Service.
Event 3 Power Range N42 Fails High, requires RO to place rod control in MANUAL to terminate the rod insertion transient. Requires entry into AOI-2/AOI-4 to stabilize the plant. Tech Spec evaluation.
Event 4 Charging Pump 1A-A trips on instantaneous overcurrent. Requires RO to isolate charging and letdown MANUALLY to protect Regenerative Heat Exchanger. Requires entry into AOI-20 to recover CVCS alignment to normal. Tech Spec evaluation.
Event 5 Main Feedwater Pump 1A trips due to low bearing oil pressure. Requires entry into AOI-16, Section 3.5 with manual runback to less than 800 MWE due to Standby MFP failing to start.
Event 6 Main Feedwater Pump 1B trips due to low bearing oil pressure causing the plant to trip.
Event 7 1B 6.9 KV Shutdown Board picks up differential lockout relay, de-energizing all of its loads. This event causes loss of remaining charging pump. It also results on a loss of 1B MDAFWP.
Event 8 TDAFDW Pump becomes steam/air bound. Loss of Feedwater conditions exist, requiring entry into FR-H.1.
Critical Task 1 Critical Task 2 Isolates letdown upon loss of charging flow, to protect the charging penetration from thermal shock.
FR-H.1 - F Initiate RCS bleed and feed so that the RCS depressurizes sufficiently for intermediate head injection to occur.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
1 Page 48 of 66 Event
Description:
Perform 1-SI-85-2, Reactivity Control Moveable Assemblies.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 1-SI-85-2, REACTIVITY CONTROL SYSTEMS MOVABLE CONTROL ASSEMBLIES (MODES 1 AND 2) Section 6.8, Control Bank D (CBD) and Section 6.9, Restoration will be performed to accomplish this task.
Section 6.8, Control Bank D (CBD)
NOTE 1 Between rod bank movements, Tavg - Tref deviation may be adjusted using manual rod control or by adjusting turbine load.
NOTE 2 Rod movement is verified by monitoring (RPIs) and Step Counters.
[1] ENSURE Tavg - Tref deviation is adjusted to allow for bank movement of ten steps.
NOTE 1-XA-55-4B-87A, ROD INSERTION LIMIT LO, may actuate during the following test sections.
[2] RECORD the initial position of the following Step Counters:
1-CBDG1, CONTROL BANK D1: ______________ steps.
1-CBDG2, CONTROL BANK D2: ______________ steps.
NOTE The operator has the option of moving Control Bank D five Steps in one direction, then ten Steps in the opposite direction and then return to normal. This method will have less overall effect on Reactor Power.
[3] PLACE 1-RBSS, ROD BANK SELECT, in CBD.
NOTE 1-XA-55-4A-64F, C-11 BANK D AUTO WITHDRAWAL BLOCKED, will actuate if Control Bank D Rods are withdrawn past 220 Steps.
[4] MOVE Control Bank D at least ten Steps in any one direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPIs. (Acc Crit)
[5] VERIFY Control Bank D1 and D2 Step Counters agree within plus or minus 2 steps.
[6] RETURN Control Bank D to its original position as recorded in Step [2] of this section using 1-FLRM, ROD MOTION CONTROL.
[7] IF Rod Insertion Limit Lo Alarm 87-A does not clear, THEN REFER TO Tech Spec LCO 3.1.7.
CONTACT System Engineer to reset 87-A USING ICS.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
1 Page 49 of 66 Event
Description:
Perform 1-SI-85-2, Reactivity Control Moveable Assemblies.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Section 6.9, Restoration CAUTION If rod movement demand exists via any of the following methods, the rod bank select switch should be moved through AUTO rapidly to avoid undesired rod movement:
Tavg is not within 1°F of program, Less than 5 minutes has elapsed since any change in rod control input (i.e, Tavg, Tref, or NIS),
Demand is indicated on the Computer Enhanced Rod Position Indication (CERPI) monitors [1-M-4].
[1] PLACE 1-RBSS, ROD BANK SELECT, in MANUAL.
[2] IF Tavg not on program, THEN RETURN Tavg - Tref within 1.5°F.
[3] RETURN 1-RBSS, ROD BANK SELECT, to the as found position recorded in Section 4.3, Step [2] (page 6 of 17).
[4] IF Acceptance Criteria is not met, THEN NOTIFY the SRO as soon as practical after observation of the noncompliance, for consideration of possible entry into LCO 3.1.5.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
2 Page 50 of 66 Event
Description:
Power Reduction to 95%.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 The following actions are associated with the power reduction from 100% to 95% to remove the 1C Condensate Booster Pump from service.
[1] Operations Superintendent has authorized load reduction.
[2] REVIEW of GO-4, Normal Power Operation, Precautions and Limitations Section 3.0 COMPLETE.
[3] IF reducing power for compliance to LCO 3.7.1, THEN:
[3.1] ENSURE Reactor Engineering revises neutron flux high reactor trip setpoints per Tech Spec 3.7.1.
[3.2] MAINTAIN power less than revised trip setpoint as allowed by Tech Spec 3.7.1.
[4] ENSURE RADIATION PROTECTION is notified of impending load reduction.
[5] ENSURE Chemistry evaluates status and flowrate of the following for the impending load reduction:
- Steam Generator Blowdown.
- Condensate Polishers.
[6] NOTIFY COND DI Operator is notified of load reduction and to remove beds as needed.
[7] NOTIFY Load Coordinator is notified of impending load reduction.
[8] ENSURE letdown flow is maximized.
NOTES
- 1) For a change in the rated thermal power greater than or equal to 15% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Chemistry shall check Reactor Coolant DE I-131 specific activity by initiating 1-SI-68-28 (SR 3.4.16.2).
- 2) QPTR alarms should be expected during significant load reductions, and the required LCO entries should NOT be considered as unplanned.
- 3) For core operating recommendations for situations such as End of Life or unusual power maneuvers, contact Reactor Engineering.
- 4) Turbine load change may be stopped by depressing the HOLD push button, using VPL, or by depressing the MANUAL push button.
- 5) TI-45, Determination of Preconditioned Reactor Power, identifies rate of power decreases when plant conditions and/or operating limitations do not require a faster reduction in power.
- 6) The Conditioned Power Level (CPL) needs to be tracked for ramp rate considerations.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
2 Page 51 of 66 Event
Description:
Power Reduction to 95%.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 SRO
[9] DETERMINE the CPL and ramp rate restrictions from TI-45, Determination of Preconditioned Reactor Power, AND RECORD section reviewed / restrictions in narrative log:
RECORD section reviewed / restrictions in table below:
[10] INITIATE load reduction by PERFORMING the following on the Turbine EHC panel:
[10.1] IF during any of the following steps the REFERENCE changes in an undesired manner, THEN ADJUST VPL to stop turbine load rise.
OR PUSH TURBINE MANUAL to place the turbine control mode in manual mode and proceed to section 5.6.
[10.2] PUSH REFERENCE CONTROL (lower) button to set desired load in SETTER display.
[10.3] SET LOAD RATE as required.
[10.4] PUSH GO button.
[10.5] MONITOR Generator Megawatts DROPPING.
[10.6] CHECK that load change has STOPPED when reference display equals setter OR IF desired to stop the load change, THEN STOP the load change by DEPRESSING the HOLD pushbutton BOP
[10.7] WHEN desired to resume the load change, THEN PRESS the GO push button and continue to monitor load.
[10.8] ADJUST VALVE POSITION LIMIT to 5% above the Gov Control Indication or as needed.
[10.9] REPEAT Steps 5.3[10.2] to 5.3[10.5] to achieve desired load.
CAUTION Do not exceed load rate of 5%/minute, or 10% step change BOP
[11] MONITOR the following during the load reduction:
[11.1] TAVG following TREF program.
[11.2] All RPIs, Step Counters, Loop T, and NIS for correct power distribution, quadrant power tilts, rod insertion, rod misalignment, inoperable RPIs, and inoperable rods.
Lead Examiner may cue the next event when the power reduction has been initiated.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
3 Page 52 of 66 Event
Description:
Power Range N42 Fails High.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Expected Alarms:
1-M-3C 63-F SG LEVEL DEVIATION 1-M-4B 83-A, POWER RANGE OVERPOWER ROD WD STOP 1-M-4B 83-E, POWER RANGE CHANNEL DEVIATION 1-M-6A 115-C, POWER RANGE FLUX HI 1-M-6A 115-E, POWER RANGE FLUX RATE HI RO Diagnoses and announces failure of Power Range Channel N42.
BOP Determines that N42 failure is affecting SG level control associated with SG 2 and 3.
SRO Enter and direct actions of AOI-4, Nuclear Instrumentation Malfunctions, Section 3.4, Power Range Monitor (PRM) Failure and directs crew actions.
- 1. PLACE control rods in MANUAL.
- 2. CHECK rod motion STOPPED.
CAUTION N41 controls S/G 1 and S/G 4 MFW reg valves.
N42 controls S/G 2 and S/G 3 MFW reg valves.
NOTE All four bypass reg valves are controlled by auctioneered high nuclear power as an anticipatory input.
- 3. CHECK N41 and N42 NORMAL.
- 3. RESPONSE NOT OBTAINED ENSURE S/G levels on PROGRAM:
- a. PLACE affected S/G MFW reg valves (main and/or bypass) in MANUAL.
- b. ADJUST FW as required to maintain levels on program.
- c. PLACE affected S/G LEVEL - NIS BIAS controller in MANUAL.
- d. MATCH bias controller to demand output on unaffected SGs.
- e. ENSURE S/G reg valve level demand and level are matched.
- f. PLACE affected S/G reg valves (main or bypass, as required) in AUTO.
NOTE Control rod withdrawal may not be possible if a PRM has failed high due to the 103%
Rod Withdrawl Stop (C-2).
SRO/RO
- 4. MAINTAIN T-avg and T-ref within 3°F.
- 5. ENSURE 1-NR-92-145 recording operable power range channel.
NOTE Inputs to 1-TR-68-2A include power range monitor, pressurizer pressure, T and Tavg.
Selection of an operable channel should consider other failures in addition to the failed power
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
3 Page 53 of 66 Event
Description:
Power Range N42 Fails High.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 range monitor channel.
- 6. ENSURE 1-TR-68-2A placed to operable T/OTT/OPT channel using 1-XS-68-2B, T RCDR TR-68-2A LOOP SELECT [1-M-5].
- 7. DEFEAT affected PRM functions:
REFER TO Attachment 1, PRM Function At NIS Rack.
NOTE TO EVALUATOR: The following steps are taken from AOI-4, Attachment 1, PRM Function at NIS Rack.
NOTE The following annunciators may be affected by defeating a PRM channel:
[66-C, 67-C, 68-C, 69-C] N-(#) OVERPOWER ROD STOP BYPASSED.
[82-E] NIS CHANNEL IN TEST.
[83-A] POWER RANGE OVERPOWER ROD WD STOP.
[83-E] POWER RANGE CHANNEL DEVIATION.
[115-C] POWER RANGE FLUX HI.
[115-E] POWER RANGE FLUX RATE HI.
- 1. PERFORM the following steps for the affected PRM:
- a. PLACE DETECTOR CURRENT COMPARATOR switch for UPPER SECTION to failed channel.
- b. PLACE DETECTOR CURRENT COMPARATOR switch for LOWER SECTION to failed channel.
NOTE On the following step, annunciator window 83-A, POWER RANGE OVERPOWER ROD WD STOP will clear (if channel failure was high) and window 66-C, 67-C, 68-C OR 69-C, N-(#)
OVERPOWER ROD STOP BYPASSED, will come into alarm depending on which channel is bypassed.
- c. PLACE ROD STOP BYPASS switch to failed channel.
- d. PLACE POWER MISMATCH BYPASS switch to failed channel.
NOTE On the following step, annunciator window 83-E, POWER RANGE CHANNEL DEVIATION, will clear and annunciator window 82-E, NIS CHANNEL IN TEST, will come into alarm.
- e. PLACE COMPARATOR CHANNEL DEFEAT switch to failed channel.
NOTE On the following step, annunciator window 115-E, POWER RANGE FLUX RATE HI, will clear if the positive rate trip light is LIT.
- f. IF POSITIVE RATE TRIP is LIT, THEN RESET RATE MODE switch.
NOTE TO EVALUATOR: The crew must return to AOI-4, Section 3.4, Step 8 to complete
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
3 Page 54 of 66 Event
Description:
Power Range N42 Fails High.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 required actions. The following continues with Step 8.
CAUTION Allowing at least 5 minutes between any rod control input (i.e., T-avg, T-ref, or NIS) change and placing rods in AUTO, will help prevent undesired control rod movement.
- 8. WHEN failed PRM defeated AND AUTO rod control desired, THEN:
- a. ENSURE T-avg and T-ref within 1°.
- b. ENSURE zero demand on control rod position indication [1-M-4].
- c. PLACE control rods in AUTO.
- 9. INITIATE repairs on failed channel.
- 10. NOTIFY Work Control to have IM trip failed channel bistables.
CAUTION Power fuses should not be removed during the performance of IMI-160 until affected S/G level controls are in manual at either the SG LEVEL - NIS BIAS controller(s) or the MFW reg valve controllers.
- 11. WHEN notified bistables are tripped, CHECK lights and alarms referenced in Appendix A are LIT.
- 12. REFER TO Tech Specs:
SRO 3.3.1-1, Function 2. Power Range Neutron Flux a. High Condition D Function 2. Power Range Neutron Flux b. Low Condition E Function 3, Power Range Neutron Flux Rate a. High Condition E Function 6, Overtemperature T, Condition W Function 16, Power Range Neutron Flux, P-8, Condition S Function 16, Power Range Neutron Flux, P-9, Condition S Function 16, Power Range Neutron Flux, P-10, Condition S 3.2.4, Quadrant Power Tilt Ratio (QPTR)
SR3.2.4.2 Verify QPTR is within limits using the moveable incore detectors ONCE within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
- 13. NOTIFY Operations Duty Manager and Rx Engineering of failed channel.
- 14. DO NOT CONTINUE with this Instruction UNTIL failed PRM repair is completed.
CREW Crew Brief would typically be conducted for this event as time allows prior to the next event.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
3 Page 55 of 66 Event
Description:
Power Range N42 Fails High.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 CREW Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.
Operations Management - Shift Manager.
Maintenance Personnel -Maintenance Shift Supervisor (MSS).
(Note: Maintenance notification may be delegated to the Shift Manager).
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
4 Page 56 of 66 Event
Description:
Overcurrent Trip of Charging Pump 1A-A.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Expected Alarms:
1-M-1B, 14-E M-1 THRU M-6 MOTOR TRIPOUT 1-M-5D, 108-A CHARGING FLOW HI/LO RO Diagnoses and announces trip of 1A CCP.
BOP Dispatches an AUO to the 1A CCP to determine cause of trip.
Dispatches AUO to 1A 6.9 KV Shutdown Board to check 1A CCP breaker for targets.
RO Refers to Annunciator 108-A, CHARGING FLOW HI/LO, for actions SRO Enter and direct actions of AOI-20, MALFUNCTION OF PRESSURIZER LEVEL CONTROL SYSTEM and directs crew actions.
CAUTION Charging and letdown must be in service together. If letdown isolates or charging is lost, the other must be isolated.
- 1. CHECK pzr level program signal NORMAL:
1-LR-68-339 (green pen).
NOTE 1-XS-68-339E selects one channel to control level to program and one backup channel for control interlocks.
- 2. CHECK if 1-XS-68-339E is selected to FAILED channel (control or backup):
LI-68-339, LI-68-320, LI-68-335.
SRO Step 2 RESPONSE NOT OBTAINED IF pzr level is low OR dropping, THEN
- GO TO Step 12.
- 12. CHECK any charging pump RUNNING.
CRITICAL TASK RO Step 12 RESPONSE NOT OBTAINED PERFORM the following:
- a. ISOLATE letdown:
CLOSE letdown orifice(s).
CLOSE 1-FCV-62-69.
CLOSE 1-FCV-62-70.
- b. RESTORE charging and letdown:
REFER TO Attachment 1.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
4 Page 57 of 66 Event
Description:
Overcurrent Trip of Charging Pump 1A-A.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 SRO
- c. ** GO TO Step 18.
NOTE TO EVALUATOR: The following steps are contained in AOI-20, Attachment 1, ALIGNMENT OF CHARGING AND LETDOWN.
- 1. IF charging NOT established, THEN PERFORM the following:
- a. CLOSE 1-FCV-62-89, CHRG HDR-RCP SEALS FLOW CONTROL.
- b. ENSURE Charging Pump running.
- c. OPEN 1-FCV-62-90 and 1-FCV-62-91, CHARGING LINE ISOL.
- e. ADJUST 1-FCV-62-93 to maintain seal injection flow between 8 and 13 gpm for each RCP.
- 2. ENSURE letdown isol valves OPEN:
1-FCV-62-69, CVCS LETDOWN ISOLATION.
1-FCV-62-70, CVCS LETDOWN ISOLATION.
1-FCV-62-77, CVCS LP LETDOWN ISOLATION.
- 4. PLACE 1-HIC-62-81A, LETDOWN PRESS CONTROL, in MANUAL at 40-50% OPEN if using 75 gpm orifice (20-30%
OPEN if using 45 gpm orifice).
- 5. THROTTLE OPEN 1-FCV-62-89 and ESTABLISH 75 gpm or greater charging flow while maintaining seal injection flow between 8 and 13 gpm for each RCP using 1-FCV-62-93.
- 6. OPEN letdown orifices as needed:
1-FCV-62-72 (45 gpm).
1-FCV-62-73 (75 gpm).
1-FCV-62-74 (75 gpm).
1-FCV-62-76 (5 gpm).
- 7. ADJUST 1-HIC-62-81A, LETDOWN PRESS CONTROL, for desired press, (320 psig at normal letdown temp), and PLACE in AUTO.
- 9. RETURN pzr level to program.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
4 Page 58 of 66 Event
Description:
Overcurrent Trip of Charging Pump 1A-A.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 RO
- 10. RETURN 1-HIC-62-93A, CHARGING FLOW PZR LEVEL CONTROL, in AUTO.
NOTE TO EVALUATOR: The crew must return to AOI-20, Step 18 after performance of.
- 18. NOTIFY Work Control to initiate corrective action, if necessary.
- 19. EVALUATE system alignment/status:
REVIEW actions performed in this Instruction.
REFER TO SOI-62.01, CVCS - Charging and Letdown.
SRO Evaluate Technical Specifications and Technical Requirements based on the loss of the 1A CCP.
Technical Specifications:
3.5.2 ECCS-Operating, Condition A.
Technical Requirements:
3.1.4, Charging Pumps, Operating, Condition A.
CREW Crew Brief would typically be conducted for this event as time allows prior to the next event.
CREW Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.
Operations Management - Shift Manager.
Maintenance Personnel - Maintenance Shift Supervisor (MSS).
(Note: Maintenance notification may be delegated to the Shift Manager).
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
5 Page 59 of 66 Event
Description:
1A Main Feed Pump trips due to low bearing oil pressure.
Standby Main Feed Pump Trips on Auto Start.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Expected Alarms:
1-M-1C 14-E, M-1 THRU M-6 MOTOR TRIPOUT Procedure:
Technical Specifications:
BOP Diagnoses and announces trip of 1A Main Feed Pump, and the trip of the Standby MPF on the start signal.
RO Determines that a Balance of Plant Runback is in progress.
RO Dispatches an AUO to the 1 A MFP to determine the cause of the trip. Dispatches an AUO to 6.9 KV Unit Board 1D to determine the cause of the trip of the Standby Main Feed Pump.
SRO Enter and direct actions of AOI-16, LOSS OF NORMAL FEEDWATER and enters Section 3.5, MFWP TRIP greater than or equal to 800MWe (67% Turbine Load).
- 1. IF loss of S/G level is imminent, THEN TRIP reactor, and ** GO TO E-0, Reactor Trip or Safety Injection.
- 2. CHECK turbine load less than or equal to 1000 MWe (85%).
- 2. RESPONSE NOT OBTAINED ENSURE Standby MFWP running.
REDUCE turbine load to less than 1000 MWe with valve position limiter.
- 3. PLACE tripped MFP recirc valve controller in MANUAL, and CLOSE recirc valve.
- 4. CHECK turbine load less than 800 MWe (67%),
- 4. RESPONSE NOT OBTAINED ENSURE Standby MFWP running.
IF Standby MFWP NOT available THEN REDUCE turbine load to less than 800 MWe with valve position limiter.
- 5. ENSURE MFWP speed rising to control S/G P and levels on program.
CAUTION Continued load reductions below 800 MWe should be done using normal turbine controls at less than or equal to 5% min.
- 6. ENSURE adequate feed flow for existing conditions:
Feed flow greater than or equal to steam flow.
S/G levels returning to program.
- 7. ENSURE T-avg and T-ref within 3°F.
CAUTION Runback may result in exceeding Tech Spec 3.2.3 limits on Axial Flux
Appendix D Required Operator Actions Form ES-D-2 Op Test No.:
NRC Scenario #
3 Event #
5 Page 60 of 66 Event
Description:
1A Main Feed Pump trips due to low bearing oil pressure.
Standby Main Feed Pump Trips on Auto Start.
Time Position Applicants Actions or Behavior Appendix D Watts Bar NRC Exam May 2009 NUREG 1021 Revision 9 Difference (AFD).
- 8. MONITOR AFD within limits of LCO 3.2.3.
- 8. RESPONSE NOT OBTAINED INITIATE boration to return AFD within limits.
- 9. IF feed flow greater than 40%, THEN ENSURE tripped MFWP turbine condenser valves CLOSED:
Pump A, 1-FCV-2-205 and -210, OR Pump B, 1-FCV-2-211 and -216.
- 10. MONITOR reg valves controlling S/G levels on program.
- 11. IF C-7 LOSS OF LOAD STM DUMP INTERLOCK annunciator LIT [66E], THEN
- a. ENSURE steam dump valves have zero demand.
- b. RESET loss-of-load interlock with steam dump mode switch.
- 12. ENSURE Condensate System Pumps in service as necessary:
REFER TO GO-4, Normal Power Operation.
- 13. IF reactor power dropped by greater than or equal to 15% in one hour, THEN NOTIFY Chemistry to initiate power change sampling requirements.
- 14. CHECK VALVE POS LIMIT LIT.
- 15. REDUCE turbine load setpoint using REFERENCE CONTROL (lower) AND GO button until VALVE POS LIMIT LIGHT not LIT, THEN SET valve position limiter to 95%.
- 16. INITIATE repairs on failed pump.
- 17. RETURN TO Instruction in effect.
CREW Crew Brief would typically be conducted for this event as time allows prior to the next event.
CREW Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief.
Operations Management - Shift Manager.
Maintenance Personnel - Maintenance Shift Supervisor (MSS).
(Note: Maintenance notification may be delegated to the Shift Manager).
Simulator Console Operators Instructions NRC Scenario 3 SIMULATOR SETUP INFORMATION Page 61 of 66 BOP Diagnoses and announces trip of 1B Main Feed Pump, and the trip of the Reactor Trip due to loss of both MFPs.
RO Performs E-0 Immediate Operator Actions.
BOP Performs E-0 Immediate Operator Actions.
SRO Enter and direct actions of E-0, REACTOR TRIP OR SAFETY INJECTION.
NOTE 1 Steps 1 thru 4 are IMMEDIATE ACTION STEPS.
NOTE 2 Status Trees / SPDS should be monitored when transitioned to another instruction.
- 1. ENSURE reactor trip:
Reactor trip and bypass breakers OPEN.
RPIs at bottom of scale.
Neutron flux DROPPING.
- 2. ENSURE Turbine Trip:
All turbine stop valves CLOSED.
- 3. CHECK 6.9 kV shutdown boards:
- a. At least one board energized from:
CSST (offsite),
OR D/G (blackout).
- 4. CHECK SI actuated:
- a. Any SI annunciator LIT.
- 4. RESPONSE NOT OBTAINED DETERMINE if SI required:
- a. IF ANY of the following exists:
- S/G press less than 675 psig, OR
- Cntmt press greater than 1.5 psig THEN ACTUATE SI manually.
IF SI NOT required, THEN
- GO TO ES-0.1, Reactor Trip Response.
SRO Transitions to ES-0.1, REACTOR TRIP RESPONSE.
SRO Assigns Status Tree Performance to Surrogate STA.
NOTE TO EVALUATOR: The following steps are taken from ES-0.1, REACTOR TRIP RESPONSE.
CAUTION Plant conditions, AFW pump start signals and flow requirements should be
Simulator Console Operators Instructions NRC Scenario 3 SIMULATOR SETUP INFORMATION Page 62 of 66 evaluated as time allows.
- 1. MONITOR SI actuation criteria:
- IF SI actuation occurs during the performance of this Instruction, THEN ** GO TO E-0, Reactor Trip or Safety Injection.
- 2. CHECK Generator PCBs OPEN.
- 3. MONITOR RCS temperature stable at or trending to 557°F:
- 4. ENSURE AFW operation:
- a. AFW established:
- TD AFW pump RUNNING.
- LCVs in AUTO or controlled in MANUAL.
- b. Heat sink available:
- Total feed flow greater than 410 gpm, OR
- At least one S/G NR level greater than 29%.
- 4. RESPONSE NOT OBTAINED
- b. IF heat sink can NOT be established, THEN ** GO TO FR-H.1, Loss Of Secondary Heat Sink.
SRO Transitions to FR-H.1, LOSS OF SECONDARY HEAT SINK.
CAUTION
- If total feed flow CAPABILITY of 410 gpm is available, this Instruction should NOT be performed.
If an Intact S/G is available, feed flow should NOT be reestablished to any faulted S/G.
- 1. CHECK if secondary heat sink is required:
- a. RCS pressure greater than any Intact S/G pressure.
- b. RCS temperature greater than 375°F [360°F ADV].
- 2. ENSURE at least one charging pump RUNNING.
CRITICAL TASK
- 2. RESPONSE NOT OBTAINED
Simulator Console Operators Instructions NRC Scenario 3 SIMULATOR SETUP INFORMATION Page 63 of 66 IF at least one charging pump NOT RUNNING, THEN STOP all RCPs AND ** GO TO Cautions prior to Step 18 to initiate RCS bleed and feed.
Since the 1B 6.9 KV Shutdown Board has tripped on differential and is damaged, the SRO must go to Step 18 to initiate RCS bleed and feed.
SRO Directs RO to STOP ALL RCPs CAUTION
- Step 18 Through 20 must be performed quickly in order to establish RCS heat removal by RCS bleed and feed.
- Termination of bleed and feed is required prior to transitioning out of FR-H.1 when heat sink is restored.
- 18. ACTUATE SI.
- 19. ENSURE at least one of the following RCS feed paths:
- At least one charging pump injecting thru BIT, OR
- At least one SI Pump running with its injection valves open.
CAUTION
- When the reactor vessel head vent block valve is opened, the throttle valve will cycle open and closed.
- Slowly opening (5 seconds stroke time) the head vent valve will prevent water hammer and pipe damage.
- 20. ENSURE adequate RCS bleed path:
CAUTION WHEN feedwater source is AVAILABLE, THEN feed rate will be controlled by Steps 30 and 31.
NOTE The details of Steps 4 through 15 may be referred to as necessary to establish feed flow in the following step but procedure performance must continue to terminate RCS bleed and feed.
BOP Contacts Auxiliary Building AUO to determine the status of the TD AFW pump. This is consistent with the above NOTE.
BOP May direct the AUO to vent the TDAFW pump after it is shutdown.
BOP May contact Work Control to determine the status of the 1A MD AFW pump repairs.
- 21. RESET SI, and CHECK the following:
- SI ACTUATED permissive DARK.
- AUTO SI BLOCKED permissive LIT.
- 22. RESET Containment Isolation Phase A and Phase B.
- 23. ENSURE cntmt air in service:
- a. Aux air press greater than 75 psig [M-15].
- b. Cntmt air supply valves OPEN [M-15]:
Simulator Console Operators Instructions NRC Scenario 3 SIMULATOR SETUP INFORMATION Page 64 of 66
- 1-FCV-32-80.
- 1-FCV-32-102.
- 1-FCV-32-110.
- 24. PERFORM Steps 1 through 6 of E-0, REACTOR TRIP OR SAFETY INJECTION, while continuing with this Instruction.
- 25. MAINTAIN RCS bleed and feed paths:
- MAINTAIN charging pump injection thru BIT.
- MAINTAIN SI pump flow.
- MAINTAIN both pzr PORVs and block valves OPEN.
END OF SCENARIO
Simulator Console Operators Instructions NRC Scenario 3 SIMULATOR SETUP INFORMATION Page 65 of 66
- 1.
ENSURE NRC EXAMINATION SECURITY has been established.
- 2.
RESET the Simulator to IC-333. (Must have correct password in order to RESET).
- 3.
ENSURE the following information appears on the Director Summary Display:
Key Description Event Final fw22c airbound tdafw pump active fw06 electrical feed pump trip active ni07b pr channel output signal failure pr chnl 2 1
120 cv01a charging pump trip 2
fw05a turbine drive feed pump trip a trip 3
fw05b turbine drive feed pump trip b trip 4
ed06b Loss of 6.9 kv shutdown board bus 1b-b 19 fw07a electric afw pump a trip active hs-3-118a-1 01160 aux fw pump a-a motor sw (green) active off hs-3-335 intentionally left blank active close hs-3-335-1 hs-3-355 indicating lights active off hs-3-335-2 hs-3-355 indicating lights active off hs-3-118a hs-3-118a auxiliary feedwater pump a-a motor sw active ptlock pi-46-12 02120 mfpt a brg oil press 3
0 pi-46-39 02120 mfpt b brg oil press 4
0
- 4.
Place Hold Order Tag on 1A MD AFWP A handswitch, 1-HS-3-118A.
- 5.
Place the simulator in RUN momentarily. Acknowledge alarms, then place the simulator in FREEZE.
Simulator Console Operators Instructions NRC Scenario 3 SIMULATOR SETUP INFORMATION Page 66 of 66 1
N/A Perform 1-SI-85-2 Reactivity Control Systems Moveable Assemblies (Mode 1 and 2).
2 N/A Power Reduction to 95%.
3 Event 1 Fails PR N42 output to 120%.
ROLE PLAY: As work control, when contacted, inform the MCR that it will be an hour or more before the work package to trouble shoot and repair the failed channel is complete.
ROLE PLAY: As work control, when contacted to initiate performance of IMI-160, reply that the instrument shop will be notified and instructed to contact the control room before the IMI is to be performed.
4 Event 2 1A CCP trip.
ROLE PLAY: As Auxiliary Building AUO, report that the pump motor is hot, and there is a burnt odor in the area.
ROLE PLAY: As Control Building AUO, report that the 1A CCP tripped on instantaneous overcurrent.
5 Event 3 MFP 1A trips due to low bearing oil pressure.
ROLE PLAY: As Turbine Building AUO, report that bearing oil pressure indicates 0 psig locally, but there are no apparent leaks.
Standby MFP trips on instantaneous overcurrent.
ROLE PLAY: As Turbine Building AUO, report that the pump motor is hot, and there is a burnt odor in the area.
ROLE PLAY: As Turbine Building AUO, report that the 1A CCP tripped on instantaneous overcurrent.
6 Event 4 MFP 1B trips due to low bearing oil pressure.
ROLE PLAY: As Turbine Building AUO, report that bearing oil pressure indicates 0 psig locally, but there are no apparent leaks.
7 Event 19 (automatically enters on reactor trip)
Loss of 1B 6.9 KV Shutdown Board on differential.
ROLE PLAY: As Control Building AUO, report that the 1B Shutdown board tripped on differential, and that there is substantial damage to the board.
8 Event 19 TDAFDW Pump becomes steam/air bound.
ROLE PLAY: As the Auxiliary Building AUO, report that the TDAFWP is steam bound. Request that the pump be shutdown in order to attempt venting of the pump.