Text

2009 Monticello Initial License Examination Administered Dynamic Simulator Scenarios
	ML100910519
Person / Time
Site:	Monticello
Issue date:	02/23/2009
From:	Bielby M; NRC/RGN-III/DRS/OLB
To:	;
References
	Download: ML100910519 (128)
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Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No.: ILT-SS-04E (NRC 1) Op-Test No.: MNGP 09 Examiners: ____________________________ Operators:

Initial Conditions:

Normal plant startup in progress at approximately 38% power. No Limiting conditions for Operation in effect.

Turnover:

Ready to place the B Feedwater Regulating valve in service.

Continue raising reactor power with Recirc.

Event No.

Malf. No.

Event Type*

Event Description 1

None N

(BOP)

Place the B Feedwater Regulating valve in service.

2 None R

(ATC/SRO)

Raise reactor power with Recirc from 38% to 50%.

3 RR09C I

(ATC/SRO)

Recirc Speed Controller failure.

Operator will lock the scoop tube. The CRS will address Tech Specs for Recirc speed mismatch.

4 RC02 I

(BOP/SRO)

RCIC Auto Initiation (Inadvertent).

The BOP will secure RCIC. The CRS will determine Tech Specs for inoperable RCIC. (ABNORMAL) 5 EG02A&B C

(BOP/SRO)

Complete loss of Stator Water cooling flow.

BOP actions to start a SWC pump will be unsuccessful.

The crew will manually scram the reactor. (ABNORMAL) 6 CH16 CH19 TC02 TC06A&B EG03 M

(Crew)

Scram with Hydraulic ATWS The crew will perform C.5-1100 for RPV control.

The crew will perform C.5-2007 for a failure to scram.

The Power/Level Control contingency will be necessary.

The scenario ends when Hot Shutdown Boron weight has been injected and the crew begins restoring RPV level.

7 SL01A&B C

(ATC)

The 1st SBLC Pump fails to start.

The OATC will successfully start the 2nd SBLC Pump (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 & 5 Quantitative attributes:

Total Malfunctions: 5 Malfunctions Malfunction(s) after EOP: E7 Abnormal Events: E3, E4 & E5 EOPs: 1100 EOP Contingencies: Power/Level Control (2007)

Critical Tasks: Inhibit ADS, Initiate SBLC, Power/Level Control Tech Spec: E3 & E4 SRO-I ATC I/C: E3 & E7 Note: CRS does not get shared credit for (N)ormal event

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SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG #

ILT-SS-04E SEG TITLE:

2009 ILT NRC 1 - ATWS 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 (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

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Guide Requirements Goal of Training:

ILT NRC EXAM Learning Objectives:

1. Demonstrate the ability to predict and/or monitor changes in parameters associated with operating system controls for the 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.

Prerequisites:

Completion of MT-ILT Training program Training Resources:

Simulator

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References:

1.

FP-T-SAT-72

2.

FP-T-SAT-75

3.

NUREG 1021, Rev.9, Supplement 1 Commitments:

None Evaluation Method:

ILT NRC EXAM Operating Experience:

None Related PRA Information:

Initiating Event with Core Damage Frequency:

ATWS Important Components:

SBLC, CRD Important Operator Actions with Task Number:

SS304.201 - Implement the response for Failure to Scram.

CR314.104 - Perform actions associated with Failure To Scram.

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TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

Shift Manager Tasks:

None SRO Tasks:

SS200.133 Direct Reactor Startup to Full Power IAW C.1 5, 6, 7 SS299.352 Apply administrative requirements for Tech Spec Section 3.4 and Bases to Reactor Coolant System (RCS) 5, 6 SS299.353 Apply administrative requirements for Tech Spec Section 3.5 and Bases to ECCS and RCIC 5, 6 SS304.193 Implement RPV control.

5, 6, 7 SS304.194 Implement primary containment control.

5, 6, 7 SS304.201 Implement the response for a failure to scram 5, 6, 7 SS314.101 Supervise alternate rod insertion 5, 6, 7 SS314.108 Supervise terminate and prevent 5, 6, 7 SS315.126 Supervise response to a stator cooling water failure.

5, 6, 7 SS315.160 Supervise response to inadvertent ECCS initiation.

5, 6, 7 RO Tasks:

CR200.127 Perform a power ascension after the reactor is on line >15% power.

1, 2, 3, 4 CR200.171 Perform the procedure for a stator cooling water failure.

1, 2, 3, 4 CR200.204 Perform the procedure for inadvertent ECCS initiation.

1, 2, 3, 4 CR202.114 Respond to unstable speed control on one pump. 1, 2, 3, 4 CR299.354 Apply Tech Spec 3.4 and Bases to the Reactor Coolant System (RCS) 2, 5 CR299.355 Apply Tech Spec 3.5 and Bases to ECCS and RCIC 2, 5 CR304.102 Perform actions associated with RPV Control.

1, 2, 3, 4

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RO Tasks:

CR304.103 Perform actions associated with Primary Containment Control.

1, 2, 3, 4 CR314.104 Perform actions associated with Failure To Scram 1, 2, 3, 4 CR314.105 Perform actions associated with Alternate Rod Insertion 1, 2, 3, 4 CR314.112 Perform actions to Terminate and Prevent injection 1, 2, 3, 4 STA Tasks:

None

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QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)

Malfunctions:

Before EOP Entry:

1. #11 Recirc Pump speed control failure

2. Inadvertent initiation of RCIC

3. Loss of Stator Water cooling flow After EOP Entry:

1. Failure of a SBLC pump to start Abnormal Events:

1. Inadvertent initiation of RCIC

2. Loss of Stator Water cooling flow Major Transients:

1. ATWS Critical Tasks:

1. {Perform the actions to inhibit ADS during an ATWS situation.}

2. {During failure to scram conditions with reactor power above 3%, terminate and prevent injection from all sources except SBLC, RCIC, and CRD until level lowers to at least -33.}

3. {During failure to scram conditions with a critical reactor, insert control rods using one or more methods contained within C.5-3101 to achieve reactor shutdown under all conditions}

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SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from:

Adjust an IC to 40% power with 11 RFP running and the A Main Feedwater Regulating Valve in service (IC-281).

2. The initial plant conditions are:

Normal Plant Startup in progress Initial power Level - 38%

Electrical lineup - 2R Supplying Xcel Condition - Green CDF - Yellow Master Level control is in Auto with the A M/A station in AUTO Plant staffing - Normal Week day with the normal plant staffing on site for a startup.

3. The following equipment is OOS:

12 Service Water Pump out for replacement of pump and motor.

4. The following evolutions are planned for the shift:

Place the B Main FWRV in service.

Continue C.1 (STARTUP). Power Ascension - VIII.A. at Step 11.

Raise power to 48% using Recirc Pumps.

Nuclear Engineer recommendations for power ascension to 48% are provided Nuclear Engineering is recalculating data for power rise from 48% to 100%

power.

Deleted: Ex Deleted: <#>Continue C.1 (STARTUP). Power Ascension -

VIII.A. at Step 11.¶ Place the B Main FWRV in service.

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SEQUENCE OF EVENTS:

Event 1: Perform power escalation as directed by the Nuclear Engineer

The crew will take the duty with the plant at 38% reactor power. Power is being raised for a Normal plant startup. After taking the duty the CRS will direct the performance of C.1 (Startup) VIII.A Step 11 (page 78). This will have the BOP place the B Main Feedwater Regulating Valve in service and then the OATC will place level control in 3 Element and continue raising reactor power using recirc.

Event 2: Raise Reactor Power with Recirc

After the B Main Feedwater Regulating Valve is in service the OATC will begin to raise reactor power to 48% by raising Recirc pump speed.

Event 3: 11 Recirc Speed Control Signal Failure

While raising power with Recirc pumps, a failure will occur causing a slow, steady rise in No. 11 Recirc pump speed. The OATC should diagnose this failure of speed control and by procedure lock the scoop tube. The crew should suspend any further power escalation until the speed control problem has been addressed. The CRS should address Tech Specs for recirc pump speed mismatch.

Event 4: RCIC Auto Initiation

After the Speed control problem with No. 11 Recirc Pump has been addressed, an inadvertent initiation of RCIC will occur. The crew should work together to diagnose this event by watching reactor water level and RCIC controls and indications. The crew should enter the C.4 to secure RCIC and determine Tech Spec requirements. The RCIC Trip pushbutton will fail to work requiring the BOP to secure RCIC using MO-2075 or MO-2080.

Event 5: Complete loss of Stator Water cooling flow

Once actions are complete for the inadvertent RCIC initiation, #11 Stator Water Cooling (SWC) pump will trip with a failure of #12 SWC pump to auto start. The BOP will take manual action to start #12 SWC pump and will be successful.

After a 5 minute delay, the #12 SWC pump will also trip requiring the insertion of a manual scram.

Event 6: Reactor Scram/ATWS with SBLC failure

When the Reactor scrams an ATWS situation develops and the Reactor remains at power. The crew will enter 2007 for guidance. Following guidance in C.5-3101, the rods will fully insert. The CRS will then transfer back to C.5-1100 once rods are fully inserted and restore RPV water level to the normal band.

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Event 7 SBLC Failure The first SBLC pump that is attempted to be started will fail to start. When a start of the second pump is attempted, it will start.

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NOTE: Table may be modified as needed to include all scenario time-line items SCENARIO TIME-LINE:

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

1. INITIAL CONDITIONS (IC):

a. 40 % power IC-281

b. Mode: 1

c. Exposure: MOC

d. Present Power: 38%

e. XCEL Condition: Green

f.

CDF: Yellow

g. Generator: ~200 MWe

2. SIMULATOR SET UP

a. Set the plant initial conditions per the Initial conditions under the Scenario Overview.

b. Enter the malfunctions, remotes, overrides and event triggers per the Simulator Set-up Checklist.

3. SHIFT BRIEF:

CRS Conducts Shift Brief:

Verify crew performs walk down of control boards and reviews turnover checklists.

When asked for out plant status provide the following:

Plant is at 38% power, XCEL System condition is Green, and CDF is Yellow. A normal plant startup is in progress and the second Main FWRV is ready to be placed in service IAW C.1 (Startup) VIII (Power Ascension) Step 11, (Page 78)

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS/INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Turbine Building Status:

4 Condensate Demineralizers are in service with the E vessel available to be placed in service. B vessel is the highest at 5.9 psid.

The following support is available:

12 Service Water Pump is tagged out and removed, ready for the new pump & motor.

Operations:

Normal staffing for the startup.

Reactor Building Status:

Maintenance:

Support available for normal plant startup.

Processing water later in the shift Engineering:

Support available for normal plant startup.

All systems are normal for continuing plant startup Management:

Support available for normal plant startup.

At the completion of the shift brief inform the CRS that their crew has the duty.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS/INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 1

4. PLACE B MAIN FWRV IN SERVICE PLACE B MAIN FWRV IN SERVICE CRS Directs the BOP to place the B Main FWRV in service IAW B.05.07-05.D.4 (Place Remaining B Main FW Reg Valve CV-6-12B in Service).

BOP Performs the required actions from B.05.07-05.D.4 (Place Remaining B MAIN FW REG VAVE CV-6-12B in Service).

a. CRS directs the continuance of C.1 (STARTUP) VIII.A Step 11.a (page 78) which directs performance of B.05.07-05.D.4 (Place Remaining B MAIN FW REG VAVE CV-6-12B in Service).

Verifies MO-1134, Hp Fw Line B Block valve is OPEN

Verifies CV-6-12B Feedwater Control M/A Station (6-84B) bias (vertical scale is set at ZERO, Or slightly negative.

Monitors RPV level during this operation.

Slowly OPEN CV-6-12B controller (6-84B) and observe output signal increasing (horizontal scale).

Monitor Vessel Level and Feedwater Loop Flows as CV-6-12B opens

WHEN CV-6-12B controller (6-84B) output (horizontal scale) matches the demand signal (vertical scale),

THEN place CV-6-12B controller (6-84B) in AUTO position.

CRS directs the performance of VIII.A.11.b & c BOP/

OATC

Places Reactor Level Control in 3 Element Control

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS/INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES If called for the status of the RBM jumpers, inform the CRS that the jumpers are removed.

CRS Verifies any jumper hung to bypass the Rod Block Monitor per Operations Manual B.05.01.02-05.H has been removed.

Event 2

5. Raise Reactor Power with Recirc Raise Reactor Power with Recirc

a. CRS directs the OATC to raise Recirc speed to 48% reactor power using the following:

1) 2300 (Reactivity Adjustment)

CRS CRS directs the OATC to raise Recirc speed to 48%

2) Nuclear Engineer Reactivity Maneuvering Steps OATC Raises Recirc speed to raise power.

b. BOP is required to Peer check Maintains loop flow parameters approximately equal Event 3

6. RECIRC PUMP RUNAWAY:

RECIRC PUMP RUNAWAY Key Parameter Response: Pump speed rising.

Key Expected Alarms: 4-C-5 (Fluid Drive A Scoop Tube Lock) once the OATC locks the scoop tube.

a. When directed by the Lead Instructor, at approximately 42% power, insert MANUAL TRIGGER 1 (RR09C). This should be inserted when the OATC raises 11 Recirc speed. The failure will engage and speed will continue rising until the OATC takes action.

Auto Actions:

Reactor power rising, loop flow rising, pump speed rising OATC Identifies that 11 Recirc speed continues to rise after releasing the control switch, verifies via recorder indication, locks the scoop tube and informs the CRS.

b. If called, respond appropriately as the Ops Manager, Plant Manager, Engineering or maintenance concerning notification of the event.

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

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS/INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES B.01.04-05.H.1 actions:

c. If called as an in-plant operator to investigate the #11 Recirc MG, there is no apparent problem.

OATC Lock the scoop tube drive Crew Notify:

Ops Manager Engineering Plant and Systems Manager

d. For this scenario it is NOT expected that the crew will need to make recirc adjustments following the speed control issue. The CRS may direct a second operator to prepare for local manual adjustments Instrument Engineer

e. Depending on how soon the OATC recognized the runaway recirc pump and locked the scoop tube, the mismatch may NOT be >10%. However, the CRS should still evaluate for entry into this condition.

CRS Evaluate Tech Specs and enter TS 3.4.1 Condition B for mismatched Recirc flows (>10% when operating at < 70%

rated core flow)

CRS Notifies an extra licensed operator to make preparations for manually adjusting #11 Recirc scoop tube CRS Suspends further power escalation until the problem with the Recirc speed control has been resolved.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS/INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 4

2. RCIC INADVERTANT AUTO INITIATION RCIC INADVERTANT AUTO INITIATION Key Parameter Response:

Pump speed rising.

Key Expected Alarms:

4-A-14 (RCIC Low Flow)

Auto Actions:

RCIC starts and injects, Feed flow may reduce to compensate.

a. When directed by the Lead Examiner, insert MANUAL TRIGGER 3 (RC02) to cause an auto initiation of RCIC with a failure of the turbine trip pushbutton.

Crew Recognizes the RCIC start and informs CRS Crew Makes a plant announcement about RCIC in operation and about evacuation of the RCIC Room CRS Directs BOP to use C.4-G and secure RCIC NOTE: The CRS may direct RCIC shutdown IAW the Hard Card, but should also direct the use of the C.4-G procedure.

Performs the required actions per C.4-G (Inadvertent ECCS Initiation Signal).

BOP Notify CRS BOP Determines was caused by a spurious signal.

NOTE: 4AWI-04.01.01 allows the CRS to secure a system.

BOP Depresses the RCIC Turbine Trip pushbutton.

BOP Determines that HO-7, Turbine Stop Valve, remains open.

b. With a failure of the RCIC Trip Pushbutton, two additional methods may be used to shutdown RCIC.

BOP Notifies CRS CRS Directs the BOP to secure RCIC by:

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SCENARIO TIME-LINE:

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

1. Closing MO-2080:

Places the handswitch for MO-2080 to close.

CRS may reference C.4-B.04.01.E (PCIS Group 5) for alternate methods to shutdown RCIC Observes HO-7 closing Verifies that RCIC speed lowers when the valve has closed and reports to the CRS that RCIC has been shutdown.

BOP

2. For closing the Steam line isolation valves:

Closes MO-2075

c. MO-2076 and MO-2078 will reopen if closed due to receiving an open signal from the initiation signal.

Verifies one of the steam line isolations remain closed

d. MO-2075 will remain closed.

Verifies RCIC speed lowers when the steam line isolates Notifies CRS that RCIC has been shutdown Crew Notifies Management, RP and Single Point of Contact.

e. If called, respond appropriately as the Ops Manager, Plant Manager, Engineering, RP or maintenance concerning notification.

CRS References TS 3.5.3 to assess RCIC operability CRS Determines RCIC is INOP (but available in an emergency) and Condition A applies Required Action A.1 - HPCI is administratively operable Required Action A.2 - Restore in 14 days

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS/INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 5

3. TRIP OF #11 Stator Water Cooling Pump TRIP OF #11 Stator Water Cooling Pump Key Parameter Response: Loss of running pump indication.

Key Expected Alarms: 8-A-17 (No. 1 Generator Cooling Wtr Failure)

Auto Actions: Standby pump fails to auto start

a. When directed by the Lead Examiner, insert MANUAL TRIGGER 5 (EG02A & EG02B with 5 min delay). This will trip the running SWC Pump and prevent the Standby pump from starting automatically.

BOP Performs the required actions of C.4-B.06.02.04.A: (Stator Cooling Water Failure)

b. Additionally with Manual Trigger 5, verify CH16 and CH19 activate which will cause the ATWS when the crew inserts a Scram Verify a Stator Cooling water pump is running.

The BOP should start the standby pump and 8-A-17 should clear.

After a 5 min delay, 12 SWC Pump will trip.

The BOP should recognize that a loss of SWC has occurred and communicate to the CRS that a reactor scram is required.

If a total loss of Stator Cooling has occurred, And cooling can NOT be immediately restored, Then initiate a Reactor Scram.

CRS Directs OATC to insert a manual reactor scram. May direct reducing Recirc Flow to minimum first.

OATC If directed, reduces Recirc Flow to minimum

c. When the reactor is scrammed and the Mode Switch is taken to SHUTDOWN verify Inserts a manual reactor scram.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS/INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES MANUAL TRIGGER 6 activates. This will cause the turbine to trip simulating a problem with the runback circuitry from the loss of stator water cooling. This will complicate the ATWS forcing the crew to inject SBLC.

Takes the Mode Switch to SHUTDOWN Event 6

4. EOP ACTIONS (ATWS)

EOP ACTIONS (ATWS)

OATC Provides a Scram Report Mode Switch is in Shutdown All rods are NOT in Reactor power is >3%

EOP Entry CRS Enters EOP 1100 RPV Control, transitions to EOP 2007, Failure to Scram, and directs:

Inhibit ADS Defeat MSIV Low-Low Level Isolation (C.5-3301)

Prevent Core Spray injection (C.5-3205)

Perform ATWS hard card actions BOP Inhibits ADS

{Perform the actions to inhibit ADS during an ATWS situation.}

BOP Defeat MSIV low-low level isolation

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS/INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES BOP Terminates and Prevents Core Spray OATC Power Leg Actions:

{During failure to scram conditions with reactor power above 3%, terminate and prevent injection from all sources except SBLC, RCIC, and CRD until level lowers to at least -33.}

Performs the Power Leg hard card.

Enters 3101 to insert the control rods Event 6 ATWS Actions (Contd)

{During failure to scram conditions with a critical reactor, insert control rods using one or more methods contained within C.5-3101 to achieve reactor shutdown under all conditions}

OATC 3101 Actions:

a. Part C will be successful with elevated drive pressure and driving rods.

Performs Part C to insert rods

b. DELETE CH19 when directed by the lead instructor to allow rods to drift in and be driven in.

Closes CRD-168, CRD-79-1 & CRD-79-2

c. Insert MANUAL TRIGGER 11 (CH 34) to close CRD-168 when requested.

Closes CRD-14 to raise drive pressure

d. Insert MANUAL TRIGGER 13 (CH 22) to close CRD-14 when requested.

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS/INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Event 7

5. SBLC Failure

a. Event Triggers 7 or 9 will auto activate to clear the trip on the second SBLC pump that is started.

OATC Initiates SBLC before Torus temp reaches 110ºF

b. If #11 SBLC is attempted to be started first, verify SL01B deletes so #12 SBLC pump will start.

Whichever SBLC pump is attempted to be started will fail to start.

c. If #12 SBLC is attempted to be started first, verify SL01A deletes so #11 SBLC pump will start.

When the opposite pump is attempted to be started it will start.

Event 6

6. Level Leg Actions:

Level Leg Actions:

Verify needed auto actions With power >3% & level above -33

a. Meets the override conditions and therefore enters the forced level reduction leg.

BOP Prevents injection from Condensate & Feedwater, HPCI, and LPCI CRS Lets level drop until Power is <3% or

b. For level control, the CRS should direct condensate and feedwater injection be All SRVs stay closed and DW < 2 psig or

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS/INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES Level reaches -126 inches Records final level and sets level band re-established and used to maintain level in the desired band.

Uses Condensate & Feedwater as necessary to maintain established level band.

Event 6

7. Pressure leg actions:

CRS/

BOP Stabilize RPV pressure below 1056 psig using SRVs

a. When directed by the Lead Examiner, Delete CH16 to allow the control rods to insert.

OATC Recognizes and reports all rods are fully inserted.

Event 6 BOP Monitor Primary Containment Parameters

8. EOP ACTIONS (PRIMARY CONTAINMENT CONTROL)

(Note: Malfunctions for the Generator Lockout and stuck closed Turbine Bypass valves are included to ensure heat addition to the Primary Containment and necessitate SBLC operation.)

If Torus Water Temperature exceeds 90°F, notify the CRS of the EOP C.5-1200 entry condition.

CRS Enters EOP C.5-1200 Primary (Containment Control)

a. EOP C.5-1200 steps become applicable only if Torus Water Temperature exceeds 90°F Directs start of all available Torus Cooling BOP Starts all available Torus Cooling A (B)

NOTE: THIS SHOULD BE DIRECTED USING THE TORUS COOLING HARD CARD.

Verify CV-1728 (1729), RHR HX SW Outlet, controller set at 20%.

Formatted: Font: Not Bold, No underline

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SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS/INSTRUCTOR NOTES CREW POS EXPECTED STUDENT RESPONSES START No 11(12) and or No 13(14) RHRSW pumps as needed.

Adjust flow for ~3500 gpm per pump using CV-1728 (CV-1729).

BOP Verify No 11(12) and /or No 13 (14) RHR pumps running.

Partially OPEN MO-2008 (2009), Torus Cooling Inj/Test Inboard, by holding handswitch in OPEN position for 8 seconds.

Give MO-2006 (2007) an OPEN signal by momentarily placing RHR Div 1 Disch to Torus Otbd handswitch 10A-S14A (B) to OPEN.

THROTTLE OPEN MO-2008 (2009) to provide ~4000 gpm per pump.

CLOSE MO-2002 (2003), HX Bypass.

Verify V-AC-5 (4), A (B) RHR RM COOLER UNIT, in operation.

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SCENARIO TIME-LINE:

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

9. SCENARIO TERMINATION SCENARIO TERMINATION CRS Exits C.5-2007 and enters C.5-1100.

OATC Restores water level to +9 to +48 inches using condensate and feedwater.

Crew:

Remain in simulator for potential questions from evaluator.

a. When conditions are stabilized as follows or at discretion of lead instructor/evaluator end the scenario by placing the simulator in FREEZE.

1) All rods inserted and the crew has restored RPV water level to the normal band. OR

2) Hot Shutdown Boron Injected and the crew has restored RPV water level to the normal band.

No discussion of scenario or erasing of procedure marking is allowed.

Deleted: the Deleted:.

Deleted: entered C.5-1100 and/or Deleted: with Hot Shutdown Boron Injected.

Deleted: End the scenario by placing the simulator in FREEZE.

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SIMULATOR INPUT

SUMMARY

Manual Trigger Type Code Description Delay Ramp Final Severity Or Value Event Trigger 1

Malfunction RR09C 11 Recirc Pump runaway 00:00:00 00:00:00 10 None 3

Malfunction RC02 RCIC Auto-Initiation 00:00:00 00:00:00 True None 5

Malfunction EG02A 11 Stator Cooling Pump Trip 00:00:00 00:00:00 True None 5

Malfunction EG02B 12 Stator Cooling Pump Trip 00:05:00 00:00:00 True None 7

Malfunction SL01A SBLC PUMP #11 TRIP 00:00:00 00:00:00 True ZD_SLSS2 9

Malfunction SL01B SBLC PUMP #12 TRIP 00:00:00 00:00:00 True ZD_SLSS1 5

Malfunction CH16 Failure to Scram 00:00:00 00:00:00 True None 5

Malfunction CH19 Multiple Control Rods Stuck 00:00:00 00:00:00 True None 6

Malfunction TC02 Turbine Master Trip 00:02:00 00:00:00 True ZD_S1SHD 5

Malfunction TC06A

1 BPV Stuck Closed 00:00:00 00:00:00 True 5

Malfunction TC06B

2 BPV Stuck Closed 00:00:00 00:00:00 True 6

Malfunction EG03 Generator Lockout 00:02:00 00:00:00 True ZD_S1SHD 11 Remote CH34 CRD-168 00:00:00 00:00:00 Closed None 13 Remote CH22 CRD-14 00:00:00 00:00:00 0

None

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SIMULATOR INPUT

SUMMARY

Manual Trigger Type Code Description Delay Ramp Final Severity Or Value Event Trigger 4

Override 05-S088-02 12 SWC Pump Handswitch - STOP 00:00:00 00:00:00 TRUE ZD_SSCWP(2)

Initial Condition Override 02-S17-04 A520P31 RCIC Turbine Trip 00:00:00 00:00:00 Off None Initial Condition Override 04-A1DS108-02 A530P32 12 SWP green light 00:00:00 00:00:00 Off None

Initial Condition Remote TC01 Exhaust Hood Spray Control Valve 00:00:00 00:00:00 Normal None

= Built into IC-281 and NOT shown on Input summary Manual Settings & Instructions:

1. Reset to IC 281.

2. Verify the remote for Exhaust Hood Spray is set to Normal.

3. Insert the override for the RCIC Turbine Trip. This will prevent the RCIC Turbine Trip pushbutton from working during the inadvertent initiation.

4. To isolated #12 Service Water Pump:

a. Place #12 Service Water pump handswitch to STOP to clear the Stby Setup light.

b. Hang a SECURE/CAUTION tag.

c. Install the override to turn off the green light indication.

5. Activate Manual trigger 4 at the beginning of the scenario. The event trigger for this removes the handswitch to stop override allowing it to start manually.

6. Activate Manual Triggers 7 and 9 at the beginning of the scenario. The event triggers for these remove the trip in one second from the SBLC pump that is NOT initially started. This will allow the second SBLC Pump to start.

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7. Verify 4 Condensate Demineralizers are in service.

8. Event Trigger 6 will activate the Turbine Master trip when the Mode Switch is taken to SHUTDOWN on the scram. The Turbine ETV will NOT trip but the turbine master trip will force SRVs to lift ensuring the crew takes action to inject SBLC.

9. Verify availability of Nuclear Engineer Recommendations for power ascension to 48%.

(This table may be modified based on site simulator)

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Attach the following site-specific information as necessary:

Simulator Set-up Checklist (before and after training)

Pre-evaluation Brief Guide (for evaluations only)

Post-evaluation Critique (for evaluations only)

Turnover Log Historical Record:

New Create

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SIMULATOR SETUP CHECKLIST (IC *)

Before Training or Evaluation:

Simulator in Training Load Alarm Sound ON on simulator console Simulator reset to correct IC (malfunctions, remotes, overrides entered per guide)

MTF-7100-051 (Attendance Record) available Chart recorders operating and forwarded Tags hung per simulator guide (Caution, Danger, Info)

Pens, paper, markers, available Turnover Sheet, LCO log, PRA sheet as applicable SPDS terminals operating Verify that SPDS is the EOF has MPIRT in the lower right corner of display.

Verify SPIRT does NOT appear in the lower right corner. (If it does, contact John Shriver)

Check for outside air temperature approximately the same as real air temperature on the SPDS (another indication that the SPDS is indicating Live data or Simulator data).

Process Computer alarm screen up and clear Numac alarms reset and displays off RWCU filter demin flows set to desired flow (approx. 80 gpm)

RWCU temperature set between 115° and 118°F Generator MVAR loading 50 MVAR delivered Turbine lube oil temperature between 111° and 113°F Reactor water level control is in 3 element and Median selected (unless IC specifies a different configuration)

Status board updated Verify all Hi / Hi-Hi alarms are reset on C-37 for neutron monitors.

Continued on Back

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SIMULATOR SETUP CHECKLIST (IC *)

(Continued)

Before Evaluation Only:

Videotape in VCR and setup to record (Taped evaluations only)

Exam signs posted on all simulator doors Evaluation team briefed SEC contacted if participating Determine individual responsible for SEC duties if SEC NOT participating Phone volume at Instructor Console in the Simulator Control Room turned down After Training for the Day Simulator reset to IC-15 Tags removed from control panels Exam/Training signs turned around Procedures cleaned and put away Headsets turned off and put away Recorders stopped Phone volume at Instructor Console in the Simulator Control Room returned to normal

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Simulator Scenario Development Checklist Mark with an X Yes or No for any of the following. If the answer is No, include justification for the no answer or the corrective action needed to correct the discrepancy after the item.

Yes No

1. The scenario contains objectives for the desired tasks and relevant human performance tools.

Yes No

2. The scenario identifies key parameter response, expected alarms, and automatic actions associated with the induced perturbations.

Yes No

3. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.

Yes No

4. Plant PRA initiating events, important equipment, and important tasks are identified.

Yes No

5. Turnover information includes a Daily At Power or Shutdown Safety Risk Assessment.

Yes No

6. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.

Yes No

7. The scenario guide includes responses for all anticipated communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices. Include estimated completion times and/or notes for use of time compression.

Yes No

8. The scenario includes related industry experience. SOER, SER and similar OE recommendations are clearly identified and fully addressed.*

Yes No

9. The scenario guide incorporates verification of Operator Fundamental application.*

Yes No

10. Training elements and specific human performance elements are addressed in the scenario critique guide to be used by the critique facilitator. The critique guide includes standards for expected performance.*

Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

For evaluations these items may be marked NO without justification.

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Simulator Scenario Validation Checklist Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

1. The desired initial condition(s) could be achieved.

Yes No

2. All malfunctions and other instructor interface items were functional and responded to support the simulator scenario.

Yes No

3. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.

Yes No

4. All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.

Yes No

5. During the simulator scenario, observed changes corresponded to expected plant response.

Yes No

6. Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence? If learning objective(s) could NOT be satisfied, identify the objectives in the Simulator Action Request Yes No

7. Evaluation: The simulator is capable of being used to satisfy learning or examination objectives without exceptions, significant performance discrepancies, or deviation from the approved scenario sequence.

Yes No Discrepancies noted (Check none or list items found)

None SMAR = Simulator Action Request SMAR:

SMAR:

Comments:

Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No.: ILT-SS-05E (NRC 2) Op-Test No.: MNGP 09 Examiners: ____________________________ Operators:

Initial Conditions:

Normal plant startup in progress at approximately 54% power. No Limiting conditions for Operation in effect.

Turnover:

Waiting for Nuclear Engineers to double check rod sequence calculations; then continue raising reactor power with Rods. While waiting, perform Core Spray Quarterly Event No.

Malf. No.

Event Type*

Event Description 1

CS01A N

(BOP/SRO)

Perform Core Spray Quarterly.

Pump motor breaker trips on Lockout.

2 RW01 C-05-A35 I

(ATC/SRO)

The RWM fails inoperable. The CRS refers to Tech Spec 3.3.B.3(b) and determines that the RWM can be bypassed.

3 C-06-A02 C

(BOP/SRO)

Reactor Feed Pump high vibration. The BOP will address this problem and eventually trip the RFP. (ABNORMAL) 4 None R

(ATC/SRO)

Lower reactor power with Rods from 54% to 50%

with control rods in preparation for securing the RFP.

5 CH07B C

(ATC)

CRD Flow Control valve fails closed.

ATC will swap to alternate Flow Control Valve.

6 AP07 I

(BOP/SRO)

Inadvertent ADS Initiation The BOP will address this problem. The CRS will address Tech Specs for 3.3.5. (ABNORMAL) 7 ED05A RR01B M

(Crew)

Bus 11 Lockout, reactor scram, LOCA. All rods fully insert and the Primary containment responds as designed, but HPCI fails and RCIC cannot keep up with the inventory loss. Alternate Level Control contingency is performed.

Emergency Depressurization is finally necessary to allow low pressure systems to inject. EOPs C.5 1100 and 1200 are performed.

8 HP04B HP03 C

(BOP or ATC)

HPCI Fails to inject. The BOP/ATC will take manual control but HPCI Turbine eventually trips.

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

Total Malfunctions: 7 Malfunctions Malfunction(s) after EOP: E8 Abnormal Events: E3 & E6 EOPs: 1100 & 1200 EOP Contingencies: ALC & ED Critical Tasks: ED, Restore RPV Level Tech Specs:E2 & E6 SRO-I ATC I/C: E2 & E5

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SIMULATOR EXERCISE GUIDE (SEG)

SITE: MONTICELLO SEG #

ILT-SS-05E SEG TITLE:

2009 ILT NRC 2, LOCA & ALC 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 (Simulator Scenario Development Checklist.)

Date Validated by:

Validation Lead Instructor (Simulator Scenario Validation Checklist.)

Date Approved by:

Training Supervision Date

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