ML12069A067

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2010 Monticello Nuclear Generating Plant Initial License Examination Administered Simulator Scenario 5
ML12069A067
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 12/31/2010
From: Mcneil D
Operations Branch III
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Monticello NRC EXAM Scenario 5 Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No.: NRC Scenario 5 Op-Test No.: MNGP 2010 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 89% Power, for Turbine BPV Testing Division 2 Drywell Spray valve inoperable.

Turnover: Perform the Turbine BPV Test. Part A Event Malf. No. Event Event No. Type* Description 1 None N Perform the Turbine BPV Test (No Faults).

BOP 2 None R Raise power with Recirc.

ATC/SRO 3 02-A11P1-V I After a Recirc Speed adjustment, Recirc pump speed ATC/SRO continues to increase. The ATC must lock the Scoop (Ovrd) Tube to stop the runaway. The Recirc Pump speed mismatch should be verified to be within TS limits.

(ABN) (TS) 4 HP01 C HPCI inadvertent initiation. (TS) (ABN) (CT) In-Plant BOP/SRO personnel report a loud water hammer.

5 C #11 Stator cooling Water Pump Trips. #12 Pump does EG02A not auto start but the BOP can manually start it. (ABN)

BOP/SRO 6 PC05 M An unisolable Torus leak begins. The first indication of Crew a problem is high water level in the RHR Rooms, which requires entry into EOP 1300. The Torus HI/Low level alarm follows, which requires entry into EOP 1200. When Torus water Level cannot be controlled, The Crew manually scrams and performs Emergency Depressurization. (CT) 7 CH02_119 C When the reactor is scrammed, one rod fails to insert.

ATC/SRO This must be identified by the ATC, who can insert the rod with CRD. Failure to insert the rod will alter the Emergency Depressurization strategy.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 5 BOP Normal: E1 Malfunction(s) after EOP (1-2): E7 ATC Reactivity (1 per set): E2 Abnormal Events (2-4): E3, 4, & 5 BOP I/C (4 / set): E4 & 5 Major Transient(s) /E-Plan entry (1-2): E6 ATC I/C (4 / set): E3 & 7

QF-1075-02 Rev. 3 (FP-T-SAT-75)

SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG # ILT-SS-15E SEG TITLE: 2010 ILT NRC 5 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: MT-ILT COURSE: NRC EXAM #: M-8119 TOTAL TIME: 1.5 HOURS Additional site-specific signatures may be added as desired.

Developed by:

Instructor Date Reviewed by:

Instructor Date (Simulator Scenario Development Checklist.)

Validated by:

Validation Lead Instructor Date (Simulator Scenario Validation Checklist.)

Approved by:

Training Supervision Date Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 3 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 Guide Requirements ILT NRC Exam Goal of Training:

1. Demonstrate the ability to predict and/or monitor changes in Learning parameters associated with operating system controls for the Objectives: appropriate tasks.
2. Demonstrate the ability to correctly use procedures to correct, control, or mitigate the consequences of normal and abnormal operations for the appropriate tasks.
3. Demonstrate the ability to monitor automatic operations of the systems to ensure proper operation for the appropriate tasks.
4. Demonstrate the ability to manually operate and/or monitor systems in the control room in accordance with approved procedures for the appropriate tasks.
5. Demonstrate the ability to complete administrative requirements, as necessary, in order to operate the plant for the appropriate tasks.
6. Demonstrate knowledge of and ability to implement shift supervision duties as they relate to crew operations for the appropriate tasks.
7. Given a degrading or improving plant condition or event, demonstrate the ability to: (CRS)
a. Evaluate trends that may result in equipment damage or reduction in plant safety.
b. Ensure proper diagnosis of plant problems by monitoring and interpreting data (information from panel indications).
c. Evaluate and diagnose challenges to Critical Plant Parameters.
d. Evaluate events and accidents.
1. Completion of MT-ILT Training Program Prerequisites:
1. Full Scope Simulator Training 2. 3139 (Control Room Shift Turnover Checklist)

Resources: 3. 3140 (Shift Supervisors Office Shift Turnover Checklist)

4. Stopwatch
5. Simulator Driver Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 4 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0

6. Simulator Phone Talker
7. Operations Representative
8. Evaluators
1. B.01.04-05, REACTOR RECIRCULATION SYSTEM

References:

2. C.2-05 (POWER OPERATION - SYSTEM OPERATION)
3. C.4-A (REACTOR SCRAM)
4. C.4-B.06.02.04-A (STATOR COOLING WATER FAILURE)
5. C.4-G (INADVERTENT ECCS INITIATION)
6. C.4.K (IMMEDIATE REACTOR SHUTDOWN)
7. C.5-1100 (RPV CONTROL)
8. C.5-1200 (PRIMARY CONTAINMENT CONTROL)
9. C.5-1300 (SECONDARY CONTAINMENT CONTROL)
10. C.5-2002 (EMERGENCY RPV DEPRESSURIZATION)
11. C.5-3101 (ALTERNATE ROD INSERTION)
12. C.5-3401, (TORUS WATER LEVEL MAKEUP )
13. C.6-004-C-5 (FLUID DRIVE A SCOOP TUBE LOCK)
14. C.6-005-B-24 (REACTOR WATER LEVEL HI/LO)
15. C.6-006-B-9 (10) (HIGH WTR LEVEL RHR ROOM A (B)
16. C.6-004-B-4, (SUPPRESSION WATER LEVEL HI/LOW)
17. C.6-008-A-17 (NO. 1 GENERATOR COOLING WTR FAILURE)
18. Tech Specs Section 3.4
19. Tech Specs Section 3.5
20. OSP-TRB-0570 PART A (EXERCISE MAIN TURBINE BYPASS VALVES)
1. None Commitments:

ILT NRC Exam Evaluation Method:

Not Applicable / ILT Exam Operating Experience:

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 5 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 Initiating Event with Core Damage Frequency Contribution:

Related PRA Information: Internal Flood (36.8%)

Station Blackout (27.4%)

Loss of High Pressure Injection (13.4%)

ATWS (11.4%)

LOCA (7.7%)

Loss of Low Pressure Injection (2.0%)

LOCA Outside Containment (0.6%)

Loss of Containment Heat Removal (0.4%)

Important Components:

EDGs HPCI RCIC Scram Feed/Cond SRV (When stuck open)

SRVs Instrument AC Fire System (for RPV Injection) 4160 VAC Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 6 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 Important Operator Actions with Task Number:

CR314.101, Emergency Depressurize CR305.108, Recover Offsite Power CR305.105/6, SBO-Recover an EDG CR305.121, Align #13 EDG to Essential MCCs CR314.126, Vent Containment CR259.127, Control Feedwater following a Scram CR314.112, Control Reactor Water Level during an ATWS CR211.106, Inject with SBLC during an ATWS Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 7 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

Shift Manager Tasks:

None SRO Tasks:

SS200.133 Direct Reactor Startup to Full Power 6, 7 SS200.134 Supervise and direct core thermal limits monitoring 6, 7 SS299.352 Apply administrative requirements for Tech Spec 6, 7 Section 3.4 and Bases to Reactor Coolant System SS299.353 Apply administrative requirements for Tech Spec 6, 7 Section 3.5 and Bases to ECCS and RCIC SS304.193 Implement RPV control 6, 7 SS304.194 Implement Primary Containment Control 6, 7 SS304.196 Implement Secondary Containment Control 6, 7 SS304.198 Implement Emergency RPV Depressurization 6, 7 SS314.115 Supervise Torus Water Level Makeup 6, 7 SS315.101 Supervise response to a reactor scram 6, 7 SS315.126 Supervise response to Stator Cooling Water 6, 7 Failure SS315.160 Supervise response to Inadvertent ECCS 6, 7 Initiation SS315.164 Supervise immediate reactor shutdown 6, 7 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 8 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 RO Tasks:

CR200.128 Increase reactor power to 100% 1-5 CR200.129 Perform core thermal limits monitoring 1-5 CR200.146 Perform the procedure for Reactor Scram 1-5 CR200.171 Perform the procedure Stator Cooling Water Failure 1-5 CR200.204 Perform the procedure for an inadvertent ECCS 1-5 initiation CR200.208 Perform the procedure for immediate reactor 1-5 shutdown CR202.114 Respond to unstable speed control on one (Recirc) 1-5 pump CR259.127 Control Feedwater following a Scram 1-5 CR304.102 Perform actions associated with RPV control 1-5 CR304.103 Perform actions associated with Primary 1-5 containment control CR304.105 Perform actions associated with Secondary 1-5 Containment Control CR314.101 Perform actions associated with Emergency 1-5 Depressurization CR314.105 Perform actions associated with Alternate Rod 1-5 Insertion CR314.119 Perform actions associated with Torus Water Level 1-5 Makeup STA Tasks:

None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 9 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. Recirc Flow increase
2. HPCI inadvertent Initiation
3. (Optional) Stator Cooling pump trip After EOP Entry:
1. One rod fails to scram Abnormal Events:
1. Recirc Flow increase
2. HPCI inadvertent Initiation Major Transients:
1. Torus Rupture Critical Tasks:
1. CT-14: (Inadvertent ECCS initiation) Restore reactor power to within the license limit.
2. CT-26: When torus water level cannot be restored and maintained above -3.3, then scram and execute Emergency Depressurization per C.5-2002.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 10 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. IC 285, 89%
2. The initial plant conditions are:
  • 89% Power for Turbine BPV testing
3. The following equipment is OOS
4. The following evolutions are planned for the shift:

Event 1: (Optional) Perform the Turbine BPV Test

Event 2: Raise power with Recirc

  • The crew starts to raise Recirc Flow to return to full power.

Event 3: Unstable Recirc Speed Control (Runaway)

  • After a Recirc Speed adjustment, Recirc pump speed continues to increase. The ATC must lock the Scoop Tube in response to the runaway. The Recirc Pump speed mismatch should be verified to be within TS limits.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 11 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 Event 4: HPCI inadvertent initiation.

  • HPCI inadvertently initiates forcing the crew to take actions per C.4-G (INADVERTENT ECCS INITIATION) to reduce Reactor power to within the license limit and secure HPCI. Crew will evaluate Tech Specs for HPCI to determine applicable conditions and required actions.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 12 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 Event 5: (Optional) Stator Cooling Water Pump Trip

  • The running Stator Cooling Pump trips but the standby pump does not automatically start. Operator action will start the standby pump and stabilize the system.

Event 6: Unisolable Torus leak

  • An unisolable Torus leak begins. The Crew manually scrams and performs EOP 1200 and 1300.
  • Emergency Depressurization can be anticipated and RPV pressure lowered using the Turbine Pressure Regulator Override
  • When Torus water Level cannot be controlled, Emergency Depressurization is performed.

Event 7: Insert all control rods

  • When the reactor is scrammed, one rod fails to insert. This must be identified by the ATC, who can insert the rod with CRD.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 13 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 NOTE: Table may be modified as needed to include all scenario time-line items SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

1. INITIAL CONDITIONS (IC):
a. IC: 285
b. Mode: 1
c. Power: 89%
d. Generator: 535 Mwe
e. Xcel system condition is GREEN
f. Plant CDF is GREEN
g. River temp is 56°F and NO towers are in service
h. Outside temp is 60°F
i. Division 2 Containment Spray is out of service
2. SIMULATOR SET UP
a. Set the plant initial conditions per the Initial conditions under the Scenario Overview, Initial Conditions, and Manual Settings.
b. Enter the malfunctions, remotes, overrides and event triggers per the Simulator Input Summary.
c. Control Room and Shift Supervisor turnover checklists should be provided with the scenario IC.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 14 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

d. Core Damage Frequency (CDF) should be updated on the status board.
e. Tech Spec Required Actions should be updated on the status board.
3. COMPLETE TURNOVER:
a. Review applicable current Unit Status
b. Review relevant At-Power Risk status
c. Review current LCOs not met and Action Tech Spec LCO 3.6.1.8 is not met with condition A and Requirements required action A.1 entered yesterday. MO-2023 is due back later in this shift.
d. Verify crew performs walk down of control boards Tech Spec LCO 3.6.1.3 is not met with condition A and and reviews turnover checklists. required actions A.1 and A.2 entered yesterday. This is due to work on MO-2023. MO-2021 is closed, deactivated and tagged.
e. Plant Staffing The following support is available:

Weekday Night Shift The following support is available:

Operations: Normal crew compliment only based on actual crew staffing.

Maintenance: Staffed to support repair of MO-2023 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 15 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Engineering: Staffed to support repair of MO-2023

f. Shift Activities Management: ERT Activated for repair of MO-2023
1) Perform the Turbine Bypass Valve Test Part A
2) Return to full power
4. SHIFT BRIEF
a. Role Play as necessary. Turbine Building status: CRS Leads the Shift Brief 1). 5 Condensate demins in service. ATC/BOP Participate in Shift Brief 2). C highest @ 5.5 psid.

3). All systems in Turbine building are normal.

b. Role Play as necessary. Rx Building status:

4). MO-2023 is tagged out for motor repair.

5). All other systems in the Rx bldg are normal. CRS Crew assumes the duty.

c. Role Play as necessary. Third Operator:

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 16 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS 6). Nothing to add. CRS Crew assumes the duty.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 17 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1 5. (Optional) Perform the Turbine BPV Test Note: This event is OPTIONAL and has no bearing on CRS Supervises Test OSP-TRB-0570 Part A (Exercise Main Turbine the subsequent events. It may be omitted at the Bypass Valves) discretion of the Lead Examiner when the BOP candidate has had the requisite number Normal BOP Performs Test OSP-TRB-0570 Part A (Exercise Main Turbine Events. Bypass Valves) for BV-1 and BV-2:

  • Record generator gross load
  • Select respective valve with BYPASS VALVE TEST switch
  • Press the BYPASS VALVE TEST pushbutton
  • Time the bypass valve travel to the OPEN position
  • Record the time to open (15-25 seconds)
  • Record generator gross load
  • Release the BYPASS VALVE TEST pushbutton
  • Time the bypass valve travel to the CLOSE position
  • Record the time to close (15-25 seconds)
  • Verify valve cycling complete Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 18 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

  • Return the respective BYPASS VALVE TEST switch to OFF ATC Monitors parameters at C-05 that are affected by the Bypass Valve test Event 2 6. Raise power with Recirc
a. Provide the following: CRS Performs a Reactivity Manipulation Brief
1) 2300 (Reactivity Adjustment) CRS directs the ATC to raise Recirc speed to 98% per Reactivity maneuvering Step 2
2) Nuclear Engineer Reactivity Maneuvering Steps BOP Provide a Peer Check
b. Monitor reactor power. At >93% power, begin next ATC o Raises Recirc speed to raise power.

event. (Event 3) o Maintains Flow parameters approximately equal o Monitors the following parameters:

o Pump Speed o Scoop Tube positions o Reactor Differential pressure o Total Jet Pump Flow Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 19 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS o Reactor Water Level and Feedwater Flow o Reactor Pressure and Steam Flow o APRMs o Core Thermal Limits Event 3 7. Unstable Recirc Speed Control (Runaway)

a. When at least 93% power, after a Recirc Speed Key Parameter Response: A Recirc Pump speed adjustment, and as directed by the Lead Examiner rising, Reactor power rising and insert MANUAL TRIGGER 1
1) Verify OVERRIDE 02-A11P1-V becomes Key Expected Alarms: 4-C-5 (Fluid Drive A Scoop Tube active Lock) once the OATC locks the scoop tube.

Recirc Runaway (Continued) Auto Actions: Reactor power rising, loop flow rising, pump speed rising

b. Due to the speed of this event, the ATC may not ATC Identifies that 11 Recirc speed continues to rise after identify the problem prior to reaching the high releasing the control switch, verifies via recorder speed stop, but the scoop tube must still be indication, locks the scoop tube and informs the CRS.

locked.

CRS Directs the RO to perform B.01.04-05.H.1 (Unstable Speed Control on One Pump).

c. If called, respond appropriately as the Ops B.01.04-05.H.1 actions:

Manager, Plant Manager, Engineering or maintenance concerning notification of the event. Crew Notify:

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 20 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Ops Manager Engineering Plant and Systems Manager

d. If called as an out-plant operator to investigate the Instrument Engineer
  1. 11 Recirc MG, there is no apparent problem.
e. Depending on how soon the ATC recognized the CRS Evaluate Tech Specs and enter TS 3.4.1 Condition A for runaway recirc pump and locked the scoop tube, mismatched Recirc flows (5% when operating at 70% rated the mismatch may not be >10%. However, the CRS should still evaluate for entry into this core flow) condition.
f. For this scenario it is not expected that the crew CRS Notifies an extra licensed operator to make preparations will need to make recirc adjustments following the for manually adjusting #11 Recirc scoop tube speed control issue. The CRS may direct a second operator to prepare for local manual adjustments CRS Suspends further power escalation until the problem with the Recirc speed control has been resolved.

Event 4 8. HPCI inadvertent initiation.

a. When directed by the Lead Examiner, insert Key Parameter Response: Reactor power rises, Reactor level MANUAL TRIGGER 3 rises, Generator output rises
1. Verify Malfunction HP01 goes active. Key Expected Alarms: 5-B-24 (REACTOR WATER LEVEL HI/LO)

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 21 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Auto Actions: None CREW Notifies CRS of HPCI initiation.

OATC Reports power and level.

CREW Evaluates Reactor level and need for HPCI initiation and reports HPCI is NOT needed for Reactor level control.

CRS Directs response to HPCI Inadvertent Initiation CT-14 (Inadvertent ECCS initiation) Restore reactor power to within OATC Reduces power as needed to maintain power <100% using the license limit. recirc.

BOP Carries out the following actions of C.4-G, step 3:

  • Places AOP control switch to RUN.
  • Trips HPCI turbine and ensures turbine has stopped.
  • Places AOP control switch in PTL.

Makes C.4 page announcement.

BOP Notifies System Engineer, Nuclear Engineer and Chemistry.

CRS Declares HPCI INOP.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 22 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS HPCI Inadvertent Initiation (Continued) CRS Consults Tech Spec 3.5.1 and determines Conditions J is applicable. Verify that RCIC remains Operable and restore HPCI to Operable in 14 Days. Other 3.5.1 conditions combine HPCI operability with operability of the LPCI mode of RHR, but not the Containment Spray mode.

Event 5 (Optional) Event 4: Stator Cooling Pump Trip Note: This event is OPTIONAL and has no bearing on Key Parameter Response: Indicating lights for 11 Stator Cooling the subsequent events. It may be omitted at the Pump; Red-OFF, Green-ON discretion of the Lead Examiner when the BOP candidate has had the requisite number of I/C failures.

a. When directed by the Lead Examiner, insert Key Expected Alarms: 8-A-17 (No. 1 Generator Cooling Wtr MANUAL TRIGGER 5 Failure)
1) Verify Malfunction EG02A goes active. Auto Actions: Turbine Runback, Reactor scram BOP
b. When the 12 Stator Cooling Pump is taken to
  • Verify a Stator Cooling water pump is running/ Take the START, verify Event Trigger 28 goes active 12 Stator Cooling Pump switch to START Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 23 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

1) Verify Override 05-S088-02 (HS in STOP) is
2) Verify Override 05-S088-01 (HS in START) CRS
  • Supervise the Loss of the Stator Cooling Pump goes active in 1 second and 12 Stator Cooling pump starts.
3) Verify the 1 minute delay for Malfunction PC05 (Torus drain in the next event) begins to time down Event 6 9. Unisolable Torus leak
a. If the Optional malfunction in Event 5 was not Key Parameter Response: Torus Level on LI-2996 (C-04) or PLR used or when directed by the Lead Examiner, 7251A/B (C-03) lowering manually actuate EVENT TRIGGER 28
1) Verify Malfunction PC05 at 100% severity Key Expected Alarms: C-06B 9&10 High water level in RHR C-goes active. 04B-4, Torus HI-LOW Level, C-04B 19, & 24 Torus Vacuum Breakers Open, C-05A-49, Radwaste Trouble, Room A&B Note: It takes at least 19 minutes to reach -3.3 ft, the Auto Actions: Torus to Drywell Vacuum breakers begin to cycle decision point for a Reactor Scram and Emergency depressurization BOP Respond to C-06-B-9 (10) (HIGH WTR LEVEL RHR ROOM A (B) and notifies the CRS ATC
  • Notify Rad Protection that a harsh environment or increase radiation environment may exist in the RHR rooms and that entry is required Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 24 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 6 10. Unisolable Torus Leak/ EOP 1300 Actions Note: The RHR Room water Level is never reported as BOP ATC

  • Dispatches an operator to investigate having reached Max Safe Level (15 inches) and the timeline of local reports allows the Torus water level to be the critical parameter.
a. Role Play in-plant operator. When dispatched,
  • Receive the report from the plant and relay the WAIT 5 MINUTES then report that the water level information to the CRS.

in is approximately 8 inches in both RHR rooms.

The water level appears to be rising slowly.

  • Reports EOP 1300 Entry Condition of RHR Room water levels above 0 inches.

Unisolable Torus Leak/ EOP 1300 Actions CRS Enters and directs actions from EOP1300 Secondary Containment Control Note: Torus Level can be monitored on Insight File BOP ATC

  • Verify the Reactor Bldg Floor drain Sump Pump is pct112. running
b. Role Play in-plant operator. If asked to report the
  • Attempt to identify and isolate the source of the water source of the leak, WAIT UNTIL Torus Water Level is -1 feet, then report, from the catwalk, that the Leak source is a weld at the ring header in Bay 4
c. Role Play in-plant operator. If asked to report CRS Monitor Area Water Levels approach to Max Safe water level in the RHR Rooms, WAIT UNTIL the source of the leak has been reported and then report that the level is now 13 inches and slowly rising.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 25 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 6 11. Unisolable Torus Leak/ EOP 1200 Actions BOP ATC Respond to C04-B-4, (SUPPRESSION WATER LEVEL HI/LOW)

  • Check LI-2996 on C-04 or PLR-7251A/B on C-03
  • Identifies and reports the lowering trend Note it takes approximately 3 minutes to reach -4
  • Reports EOP 1200 Entry Condition when Torus water inches Torus water level level (Narrow Range) is < -4 inches
  • Monitors and reports Torus water level throughout CRS Enters and directs actions from EOP1200 Primary Containment Control
  • Directs performance of C.5-3401, Torus Water Level Makeup
a. Role Play the out-plant operator if assigned to BOP ATC
  • May direct an in-plant operator to perform C.5-3401 perform C.5-3401: Wait 5 minutes and report that steps for Core Spray and RHR. (May choose not to he must find boots as PPE for the water on the perform due to safety concerns) floor.
  • Verifies the HPCI CST Suction, MO-2063 Open
  • Opens the HPCI Pump Minimum Flow Valve CV-2065
  • Verifies the RCIC CST Suction, MO-2201 Open Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 26 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

  • Opens the RCIC Pump Minimum Flow Valve CV-2104 Event 6 12. Immediate Reactor Shutdown CT-26 When torus water level cannot be restored and maintained CRS When it is determined that Torus Water Level cannot be above -3.3, then scram and execute Emergency maintained above -3.3 ft, Manually Scram and enter EOP 1100.

Depressurization per C.5-2002.

CRS May directs an Immediate Reactor Shutdown per C.4.K (Immediate Reactor Shutdown)

ATC

  • May reduce Recirc Flow to minimum
  • Depresses pushbuttons for REACTOR SCRAM A and B Event 6 13. Reactor Scram response (ATC): CRS Supervises response to a Reactor Scram ATC Actions per C.4-A (Reactor Scram):
  • Place Mode Switch in SHUTDOWN.

The OATC may address the stuck rod before proceeding

  • Verify all Control Rods are inserted to or beyond with the remaining C.4.A actions position 04. 1 Rod remains full out (See Event 7)

Reactor Scram response (ATC) (Continued): ATC

  • Provides scram script to CRS Reports when Reactor level drops to less than 9 EOP entry condition.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 27 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

  • Controls Reactor water level between +9 and +48 inches. When reactor water level starts to increase:

o Place CV-6-13 Manual Loading Station Low Flow Valve in AUTO set between 15 and 20 inches o Close both Main FW Reg Valves o Close MO-1133 and MO-1134 (HP Feedwater Line Block valves o Verify CV-6-13 is closed when RPV level reaches +15 to +20 inches

  • Monitor Reactor Power o Insert SRM and IRM detectors.

o Switch recorders from APRM to IRM.

o Range down on IRMs as necessary.

  • Verify SDV Vent and Drain Valves closed.
  • Verify Recirc Pumps have run back to minimum
  • Ask for permission to reset the scram Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 28 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS CRS

  • Authorize resetting the Reactor Scram ATC
  • Place DISCH VOL ISOL TEST switch in ISOL
  • Place SDV HIGH WATER LEVEL BYPASS in BYPASS
  • Reset the Rod Drift alarms
  • Evacuate personnel from the RB Floor and Equipment Drain Tank Room
  • Verify the SDV Vent and Drain Valves open
  • When Annunciator 5-B-30 (DISCH VOLUME TANK NOT DRAINED) IS RESET, Place SDV HIGH WATER LEVEL BYPASS in NORMAL Event 6 14. Reactor Scram response (BOP): BOP Starts performance of Part B of C.4.A
  • Announce over the plant paging system that a Reactor Scram has occurred.
  • Open Main Generator output breakers 8N4 & 8N5.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 29 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

  • Verify the Generator Field Breaker Open.
  • Start the Turbine Aux Oil Pump.
  • Verify Turbine Exhaust Hood Sprays in service.
  • Start the Turbine Bearing Lift Pumps (P-64A-F)

BOP Reactor Scram Response (Continued) BOP

  • Verify Main Steam Pressure Control or Low-Low Set is controlling Reactor Pressure.
  • At C-25, Place the POST SCRAM switch in ON and verify all available Drywell Recirculation Fans are operating
  • Verify 3300 gpm through each operating Feed Pump
  • Verify Auxiliary Oil Pump running on any non-operating Feed Pump
  • Verify 3000 gpm through each operating Condensate Pump Event 6 15. Emergency Depressurization CRS CRS May anticipate Blowdown per a C.5-1100 Override Statement and direct RPV pressure be lowered using the Turbine Bypass Valves Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 30 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS CT-26 When torus water level cannot be restored and maintained CRS When it is determined that Torus Water Level cannot be above -3.3, then scram and execute Emergency maintained above -3.3 ft, Blowdown and enter EOP 2002 .

Depressurization per C.5-2002.

CRS

  • Recognizes when Torus Water Level cannot be maintained above -3.3 ft
  • Verifies Torus level > -5.9 ft.
  • At C-07, places PRESS REG OVERRIDE in OPEN until both Bypass valves are open BOP Perform Emergency Depressurization
  • Verifies that 3 ADS SRV have opened
  • Monitor RPV Pressure and Level Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 31 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7 16. One Control Rod fails to insert Key Parameter Response: No full in Green light for Control Rod 22-51 Key Expected Alarms: None Auto Actions: None

a. When the ATC places the ROD MOVEMENT ATC
  • Identifies that Rod 22-51 did not fully insert CONTROL switch to ROD IN to insert Rod 22-51, verify EVENT TRIGGER 29 goes active and
  • Informs the CRS MALFUNCTION CH02_119, Stuck Rod 22-51, is DELETED.
b. Role Play the Reactor Bldg Operator as
  • Direct an out-plant operator to manually close CRD-14 necessary and, as requested wait 2 minutes and toggle ON MANUAL TRIGGER 9 to close CRD-14
1) Verify REMOTE FUNCTION CH22 goes
  • Select and insert the full out rod active to close CRD-14
  • Informs the CRS when all Rods are Fully inserted
17. SCENARIO TERMINATION Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 32 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

a. The scenario may be terminated when the conditions are stabilized as follows:
1) Actions taken to insert all control Rods
2) Emergency Depressurization has been performed
b. The scenario may be also terminated at the Crew:
  • Remain in simulator for potential questions from discretion of lead instructor/evaluator evaluator.
c. End the scenario by placing the simulator in Crew:
  • No discussion of scenario or erasing of procedure FREEZE. marking is allowed.

Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 33 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SIMULATOR INPUT

SUMMARY

Event Code Description Trigger Delay Ramp MALFUNCTIONS (Allow Tracking Off)

EG02A Stator Cooling Pump #11 Trip 5 None None HP01 HPCI Auto Initiation 3 None None PC05 Torus Drain (Leak) 28 00:01:00 None CH02_119 Control Rod 22-51 Stuck 30 None None CH02_119 Control Rod 22-51 Stuck 29 None None (Inserts and deletes in 1 second)

REMOTE FUNCTIONS CH22 CRD-14 Accumulator Charging Water Isolation Valve 9 None None Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 34 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 SIMULATOR INPUT

SUMMARY

Event Code Description Trigger Delay Ramp OVERRIDES 01-S044-02 A520P31-26 MO-2023 HS open 30 None None 01-S072-02 A520P32-28 MO-2021 HS open 30 None None 01-DS104-02 A531P30-32 MO-2023 RED LAMP 30 None None 01-DS103-02 A531P30-33 MO-2023 GREEN LAMP 30 None None 01-DS157-02 A531P31-30 MO-2021 RED LAMP 30 None None 01-DS156-02 A531P31-31 MO-2021 GREEN LAMP 30 None None 01-S030-02 A520P30-38 MO-2022 HS open 30 None None 05-S088-02 A521P27-48 12 Stator Liquid Pump P-72B-STOP 30 None None 05-S088-02 A521P27-48 12 Stator Liquid Pump P-72B-STOP (Inserts and 28 None None deletes in 1 second) 02-A11P1-V A520P31-37 11 Recirc Pump Manual- RAISE 1 None None 05-S088-01 A521P27-45 12 Stator Liquid Pump P-72B-START 28 00:00:01 None Event Trigger Definitions:

Code Description Event Trigger ZD_SSCWP(2) #12 Stator cooling Pump taken to Start 28 ZD_CRDIN Rod Movement Control Switch taken to ROD IN 29 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 35 of 35 ILT-SS-15E, 2010 ILT NRC 5, Rev. 0 Manual Settings:

1. Reset to IC 285.
a. If necessary, IC 285 can be recreated as follows:

o Reset to IC13, (89% Power).

o Select an edge rod.

o Establish Event Triggers and Commands per the Simulator Input Summary.

2. Manually activate event Trigger 30 to establish the initial conditions for the scenario.
3. Hang Caution Tags for the Inoperable Division 2 Containment Spray Valves.
4. Verify Event Trigger Definitions:
a. Event Trigger 28 is used to delete the Auto start failure of the #12 Stator Cooling Pump and initiate the Torus leak one minute later.
b. Event Trigger 29 is used to delete the Stuck Rod malfunction when the Rod Movement Control Switch is taken to ROD IN.
5. Verify the Malfunctions match the Simulator Input Summary.
6. Verify the Remote Functions match the Simulator Input Summary.
7. Verify the Overrides match the Simulator Input Summary.
8. Verify the following conditions:
a. <90% Power
b. Edge Rod selected
9. Perform the applicable sections of the SIMULATOR SETUP CHECKLIST.
10. Provide the following for the operating crew :
a. OSP-TRB-0570 (Exercise Main Turbine Bypass Valves)
b. Stopwatch
c. Form for Reactivity manipulation of returning to 100 Power
d. A scenario specific Form 3139, Control Room Shift Turnover Checklist
e. A scenario specific Form 3140, Shift Supervision Turnover Checklist Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in FP-G-RM-01.
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