Text

2011 Kewaunee Power Station Initial License Examination Administered Dynamic Simulator Scenarios
	ML110460653
Person / Time
Site:	Kewaunee
Issue date:	02/15/2011
From:	Walton R; Operations Branch III
To:	;
References
	ROI/SOI-06-SE-SC1, Rev. B
	Download: ML110460653 (206)
	v • d • e

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SITE: Kewaunee Power Station PROGRAM: RO/SRO License Training PROGRAM No. ROI/SRO-TP COURSE: 2011 NRC License Exam Course #:

ROI-06-SE-SC1 SOI-06-SE-SC1 Total Time 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Prepared by: Andrew Fahrenkrug /s 01/24/2011 Printed Name Instructors Signature Date Reviewed by: Jeffrey A. Hinze /s 01/24/2011 (Optional) Printed Name Simulator Date Development Checklist Instructor Signature Reviewed by: Andrew Fahrenkrug /s 01/18/2011 (Optional) Printed Name Simulator Validation Date Checklist Signature Approved by: Randy Hasting /s 01/24/2011 Printed Name Training Supervisor Date Approved by: Mark Goolsbey /s 01/24/2011 Printed Name Facility Date Representative KPS-SEG1-L-RO/SRO-A-01242011-112

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Appendix D Scenario Outline Form ES-D-1 Facility: Kewaunee Power Station Scenario No.: 1 Op-Test No.: 1 Examiners: Operators: SRO: .

ATC: .

BOP: .

Initial Conditions: 100% power EOL Equilibrium Xenon. RCS boron concentration is 77 ppm. RCS Tave is 572ºF. Generator load is 602 MWe gross, AS-31/AS-35 R-11 & R-12 Sample Return Aligned to Containment, PR-1A PRZR PORV Block Valve is closed with power maintained due to PR-2A seat leakage, TD AFW pump is OOS for corrective maintenance on its Aux Lube Oil Pump, 2 inch containment vent is in progress per NOP-RBV-002 section 5.6 Turnover: Notified by DEMI that MISO has escalated a previous Minimum Generation Alert to a Minimum Generation Warning with an actual event, KPS has agreed to Lower Power to 95%.

TS 3.7.5 (AFW system) Condition B with one AFW Train inoperable. Required Action B.1 is to restore train(s) to OPERABLE status with a Completion Time of 72 Hours.

Start Time 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months before scenario start time.

TS 3.4.11 (Reactor Coolant System Pressurizer Power Operated Relief Valves)

Condition A One or more PORVs inoperable and capable of being manually cycled.

Required Action A.1 is to close and maintain power to the associated PORV with a completion time of one hour (Completed).

Event No. Malf. Event Event No. Type* Description PR-2A CAUTION tagged CLOSED due to seat leakage. PR-1A Pre-Load closed TS LCO3.4.11, ACTION A.1.

DO-46113-G OFF T/D AFW Pump OOS. MS-102 in PULLOUT.

Pre-Load N/A DO-46114-G OFF MS-100A/B in CLOSE and lights OFF Pre-Load FW16A BOP - C AFW Pump A fails to auto start. Manual start remains available.

ATC - R 1 N/A Power reduction required due to Minimum Generation Warning.

BOP - N After approximately 5% load decrease, controlling PRZR 2 RX203 -

ATC - I pressure blue channel (III), PT-431 fails high.

2500 0:30 Heaters de-energize and sprays open to lower PRZR pressure.

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FW-7B controller output signal fluctuates resulting in unstable RX02B 3 75 15:00 BOP - C operation of FW-7B, SG B Feed Reg Valve. Value for fluctuation increases to 75% over 15 minutes.

NI05A -

4 1.2 ATC - I NI Red Channel, N41, fails low.

SG01B - ATC, SGTR occurs in SG B ramping to maximum value over a 5-5 5.6 ramp BOP - M minute period. Crew responds to radiation alarms and rising SG over 5 level. When the reactor trips, the SGTR goes to its maximum minutes value, AFW Pump A fails to auto start on low SG level or SI signal.

6 FW16A BOP - C BOP establishes flow to SG A.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO 1-1 OVERVIEW EVENT DESCRIPTION Power reduction. Crew is directed during turnover to perform a power reduction to reduce thermal power to 1673 MW (~ 95% RTP) due to the Minimum Generation Warning with an actual event. Crew should review Standard Reactivity Plan and set up for 5% power reduction 1 at 1/2 %/min.

KW-GOP-307, Hold-At Power Greater Than 35%, will be used to direct the power reduction.

The ATC operator will borate in accordance with the Reactivity Plan using NOP-CVC-001, and the BOP operator will reduce turbine load using NOP-TB-001.

After the power decrease the controlling PRZR Pressure blue channel, PT-431, fails high to 2500 psig. This will result in PRZR heater output going to zero, and PRZR Spray valves opening. Actual PRZR pressure will lower. The crew will perform actions of AOP-GEN-001, Immediate Operator Actions, Attachment H for Pressurizer Spray Valves Open and/or the ARP(s) associated with High Pressure alarms. The failed instrument will be addressed using AOP-MISC-001, Response to Instrument Failure, Attachment G Pressurizer Pressure.

Technical Specifications:

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.1-1 for the channel(s) or train(s) with a completion time of immediately.

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition E one channel inoperable with Required Action E.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.1-1 Item 6. Overtemperature T (Loop B Chan 3 OTT) & item 8.b 2

Pressurizer Pressure High.

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition K one channel inoperable with Required Action K.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.1-1 Item 8.a Pressurizer Pressure Low

TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.2-1 for the channel(s) or train(s) with a completion time of immediately.

TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation Condition D one channel inoperable with Required Action D.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.2-1 Item 1.d Pressurizer Pressure - Low Note: The option in TS for shutting down the plant is not expected to be exercised for this failure The Unit supervisor will direct tripping of bistables. It is expected to trip bistables for the failed channel(s) during the scenario.

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Following the addressing of the failed PRZR pressure channel, FW-7B, SG B Feed Reg Valve, will experience oscillation of the output signal from its controller in AUTO. This will result in fluctuation in SG B level, and feed flow. The BOP operator is expected to respond to the changes in SG B level and/or associated alarms. The crew will respond in accordance with AOP-GEN-001, Immediate Operator Actions, Attachment B, Abnormal Steam Generator Level, 3 or the ARPs for SG level or steam/feed flow. The operator will transfer FW-7B controller to MAN and establish normal level in SG B (33% to 50%). The crew will also enter AOP-FW-001, Abnormal Feedwater System Operation, which also contains direction for maintaining SG level with the FW-7B controller in manual.

If the operator fails to control SG level and a reactor rip signal is generated, then Event 5, SGTR, will be initiated at its final value.

When FW-7B failure has been addressed, Power Range Nuclear Channel N41 (Red) will fail low. This will result in a rapid change in NI power rate and result in control rods in AUTO stepping OUT. The ATC operator will identify rod movement and determine rod movement is NOT required by the plant condition (stable). Actions of AOP-GEN-001, Immediate Operator Actions, Attachment C Uncontrolled Rod Motion will be performed. Once it is determined that a turbine runback or rapid power reduction is NOT in progress, the ATC operator will place the Rod Bank Selector to MAN and verify rod motion stops. The crew will check for instrument failures and determine N41 channel has failed low. The failed instrument will be addressed using AOP-MISC-001, Response to Instrument Failure, Attachment J Nuclear Power Range.

The crew will remove N41 from service. Tave-Tref should be restored to within +/- 1ºF using rod control in manual.

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.1-1 for the channel(s) or train(s) with a completion time of immediately.

Either of the following for Table 3.3.1-1 Item 2.a Neutron Flux High

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition D one channel 4

inoperable with Required Action D.1.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND Required Action D.1.2 reduce Thermal Power to < 75% RTP with a completion time of 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months . Table 3.3.1-1 Item 2.a PR Neutron Flux High OR

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition D one channel inoperable with Required Action D.2.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND Required Action D.2.2 perform SR 3.2.4.2 with a completion time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Table 3.3.1-1 Item 2.a PR Neutron Flux High OR

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition D one channel inoperable with Required Action D.3 to be in MODE 3 with a completion time of 78 Table 3.3.1-1 Item 2.a PR Neutron Flux High KPS-SEG1-L-RO/SRO- A-01242011-112

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Either of the following for Table 3.3.1-1 Item 2.a Neutron Flux High

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition E one channel inoperable with Required Action E.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.1-1 Item 2.b PR Neutron Flux Low & Item 6. Overtemperature T.

OR

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition E one channel inoperable with Required Action E.2 to be in MODE 3 with a completion time of 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months . Table 3.3.1-1 Item 2.b PR Neutron Flux Low & Item 6. Overtemperature T.

The crew should note that tripping of the Loop B Chan 1 OTT will result in TWO channels of OTT being tripped and result in a reactor trip signal being generated. [Tripping of OTT Loop B Chan 1 should NOT be directed.] Management should be contacted to resolve problem and prioritize work.

If the crew elects to trip bistables the unit will trip and will move to the next event SGTR.

After the failed NI channel has been addressed, a tube rupture will occur in SG B. The rupture will build in to a value of approximately over 5 minutes. The crew should recognize secondary system radiation indications for monitors R-43, R-15 and R-19 (SG B steam line N-14, Condenser Air Ejector and SG blowdown), and respond to the lowering RCS pressure, lowering PRZR level and increased charging. When letdown is isolated and maximum charging flow is established with two Charging Pumps, AND PRZR level is still decreasing, the Unit Supervisor (US) will direct a reactor trip as directed by AOP-RC-004 (or AOP-RC-001).

When the reactor is tripped the SGTR will increase to its maximum input value (the ramp is stopped).

5 The crew will perform immediate actions of E-0:

1. CHECK reactor trip and reactor subcritical

2. ENSURE turbine trip

3. CHECK Bus 5 OR Bus 6 (ESF Bus) energized

4. CHECK SI actuated.

It is expected that SI will be manually actuated, or will be required, by this time as PRZR level continues to lower.

The US will provide and brief. The US should address the FOLD OUT Page Criteria 3 for isolating feed flow to a ruptured SG when narrow range level goes above 5%. The ATC operator will perform Attachment A steps while the US directs the BOP operator performing E-0 actions.

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The BOP operator is expected to report the failure of AFW Pump A to start. [It should have started on low-low SG level and/or SI signal.] The BOP operator will manually start AFW Pump A, after closing AFW-2A, (and SI sequencer complete) by taking its control switch to STOP and then START positions. [THIS IS A CRITICAL TASK and must be accomplished by the initiation of the RCS cooldown directed in E-3, step 11]

The crew will continue the actions of E-0 to ensure Safeguards equipment is operating as required. Diagnosis will be made of a SGTR and transition will be made to E-3.

The crew will identify SG B as ruptured and isolate steam flow from SG B by closing the MSIV.

6 [THIS IS A CRITICAL TASK and must be accomplished by the isolation of major flow paths from the SG by completion of E-3, step 4]. Feed flow to SG B will also be stopped. A RCS target temperature based on SG B pressure will be determined and a cooldown initiated using the condenser [MS-1A open] or SD-3A [MS-1A closed]. The cooldown will be stopped and stabilized after the target temperature is reached. The RCS will then be depressurized using PRZR Sprays or a PRZR PORV. Conditions will be checked for SI termination and SI flow stopped. [THIS IS A CRITICAL TASK and must be accomplished before SG B level is at 100% narrow range AND SG B pressure rises above 1050 psig, indicative of SG overfill]

Conditions will be established to allow balance between RCS pressure and SG B pressure.

The scenario may be terminated at the point SI flow is stopped in E-3.

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REQUIREMENTS Goal of Training: Evaluate crew response and performance for the following events:

Power reduction for a minimum generation warning from 100% to 95%

per OP-KW-GOP-307

Controlling Przr pressure blue channel (III), PT-431 fails high

FW-7B controller output signal fluctuates resulting in unstable operation of FW-7B, SG B Feed Reg Valve

NI Red Channel, N41, fails low with outward rod motion

SGTR occurs in SG B

AFW Pump A fails to auto start on low SG level or SI signal with manual start available

SRO/US analysis of plant conditions for Technical Specification application Learning Objectives: While responding as the RO/BOP satisfactorily MEET the performance requirements in TR-AA-400 for the following competencies

a. Understand and Interpret Annunciator and Alarm Signals

b. Diagnose Events and Conditions based on Signals and Reading

c. Understand Plant and System Response

d. Comply with and Use Procedures and Technical Specifications

e. Operate the Control Board

f. Communicate and Interact with Other Crew Members (RO4-06-SED01.002) ROI-06-SE-SC01.001 / SOI-06-SE-SC01.001 While responding as the US satisfactorily MEET the performance requirements in TR-AA-400 for the following competencies

a. Understand and Interpret Annunciator and Alarm Signals

b. Diagnose Events and Conditions based on Signals and Reading

c. Understand Plant and System Response

d. Comply with and Use Procedures and Technical Specifications

e. Operate the Control Board

f. Communicate and Interact with Other Crew Members

g. Direct Shift Operations

h. Comply with and Use Technical Specifications (RO4-06-SED01.003) SOI-06-SE-SC01.002 As the US DETERMINE the appropriate event classification in accordance with EPIP-AD-02,Emegency Classification Determination. (This objective will be completed at the end of the scenario and may be waived at the lead evaluators discretion.) SOI-06-SE-SC01.003 KPS-SEG1-L-RO/SRO-A-01242011-112

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Prerequisites: Enrolled in current ILT class and recommended by station management to take an NRC license exam.

Training Resources: Simulator KPS Exam Team Member NRC Examiners KPS-SEG1-L-RO/SRO- A-01242011-112

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References:

KPS Technical Specifications (ITS)

KPS Technical Requirements Manual (TRM)

EOL Standard Reactivity Plan (100% to 94% @ 0.5%/min)

OP-AA-100 Conduct of Operations OP-AP-300 Reactivity Management OP-AP-104 Emergency and Abnormal Operating Procedures ARP 47011-B, RADIATION INDICATION HIGH ARP 47012-B, RADIATION INDICATION ALERT ARP 47032-J, POWER RANGE NEGATIVE RATE CHANNEL ALERT ARP 47033-K, POWER RANGE CHANNEL DEVIATION ARP 47041-C PRESSURIZER PRESSURE 2385 ARP 47043-C PRESSURIZER CONTROL PRESS ABNORMAL ARP 47043-D PRESSURIZER PRESSURE LOW ARP 47043-E, PRESSURIZER LEVEL DEVIATION ARP-47043-J CHARGING PUMP IN AUTO HIGH/LOW ARP-47044-F ICCMS PANEL TROUBLE ARP 47033-25, TLA-10 STEAM GENERATOR TILTS ARP 47033-35, TLA-15 RMS ABOVE NORMAL ARP 47061-E, S/G B SF > FF ARP 47061-F, S/G B FEEDFLOW EXCESSIVE ARP 47062-D, S/G B PROGRAM LEVEL DEVIATION ARP 47062-E, S/G B BYPASS CV LEVEL DEVIATION AOP-GEN-001, Operator Immediate Actions AOP-MISC-001, Response to Instrument Failure AOP-II-001, Abnormal Inadequate Core Cooling Monitoring (ICCM) System AOP-FW-001, Abnormal Feedwater System Operation AOP-RC-004, Steam Generator Tube Leak AOP-RC-001, Reactor Coolant Leak E-0, Reactor Trip Or Safety Injection E-3, Steam Generator Tube Rupture GOP-307, Hold at Power Greater Than 35%

NOP-CVC-001, Boron Concentration Control NOP-CVC-002, Charging And Volume Control NOP-TB-001, Turbine and Generator Operation NOP-HD-001 Heater and Moisture Separator Drain and Bleeder Steam System SP-32-113 Gaseous Radioactive Effluents Reports for Continuous Releases NOP-RBV-002 Reactor Building Vent System Cold Operations and Making Releases KPS-SEG1-L-RO/SRO- A-01242011-112

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Commitments: Per Outline submitted to NRC for 2011 Operating exam Evaluation Method: Dynamic Simulator Historical Record: Initial Issue Rev B

1. Added NRC Form ES-D-1

2. Page 24 of 70, under 4 TURNOVER Crew Direction added procedure information:

Commence Management directed down power using GOP-307.

3. Page 29 of 70, added flush to Students action WHEN Alt Dilution flush complete:

4. Page 35 of 70, added values and COLR reference to Floor Instructor for RCS pressure, temperature and flow DNB limits

5. Page 36 of 70, added to Students action Potential for TS 3.4.1 RCS DNB limits information.

6. Page 36-37 of 70, changed NOTE concerning bistable tripping not being performed: The remaining action of AOP-MISC-001 address I&C tripping of the bistables for the failed channel, this action will NOT be performed in this Scenario. Kept steps listed as SM direction for contacting I&C/WWC. Deleted NOTE from Booth Instructor column and changed RESPONSE to reflect timing for providing personnel for bistable tripping. Deleted identified bistables.

7. Page 36 of 70, added note to Floor Instructor, When Technical Specifications have been addressed, then continue with next event.

8. Page 45 of 70, corrected typo in Students, Check VST level > 5% to Check VCT level > 5%

9. Page 49 of 70, Added in Students the specific valves closed for isolating feed flow to ruptured SG - AFW-2B and AFW-10B with noun names.

10. Page 52 of 70, added the radiation monitor identifier in parentheses behind name for R-15, R-19, R-33 and R-43.

11. Page 56 -70, added in Students isolating feed flow to the ruptured SG B including the specific valves closed for isolating feed flow to ruptured SG - AFW-2B and AFW-10B with noun names.

12. Page 56 -70, added in Students the specific valves closed and checked closed for ruptured SG - MS-1B and MS-2B. Included in parenthesis behind MS-1A the method for closing (Depresses Main Steam Isolation Initiate Train B pushbutton).

13. Page 66 of 70, corrected Final Value for DI-46331-OPEN and DI-46332-OPEN (CC-610A and CC-610B) from trip to norm.

14. Page 66 of 70, corrected values provided for SG01B under Blind Trigger - Event #30: In Command: changed 9- to 10 and in description changed 5.6 to 10.

Operating Experience: Not required for evaluations Related PRA Initiating Event with Core Damage Frequency:

Information: Total CDF/LERF (3.6E-5/yr)/(1.6E-06/yr)

Steam Generator Tube Rupture - 3% CDF / 61.2%% LERF Important Components:

System CDF Importance Rank LERF Importance Rank AFW 4th 6th Important Operator Actions CDF - None LERF - Isolate ruptured SG an initiate cooldown and depressurization KPS-SEG1-L-RO/SRO- A-01242011-112

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OVERVIEW INITIAL CONDITIONS:

1. Standard IC-13 (100% End of Life equilibrium Xe)

2. Containment vent using the Train B Post-LOCA path is in progress to reduce Containment pressure

3. The following equipment is OOS:

PR-2A PORV has seat leakage and PR-1A, PORV Block Valve, is closed and energized satisfying LCO 3.4.11, Condition A.

Turbine Driven AFW Pump due to corrective maintenance on its Aux Lube Oil Pump, tagout has just been hung

4. R-11/12 Sample Return is aligned to containment SEQUENCE OF EVENTS:

Event 1: Power reduction to 95% power as directed by Plant Management due to minimum generation warning

Station Management has directed back down initiated at 1/2% per minute using Standard Reactivity Plan. Target power level is 570 MWe (~95% NI power; less than 1673 MWt).

The ATC Operator will be responsible for necessary boration(s), and monitoring rod motion, I, and rod position (limits).

The BOP Operator will control the turbine load reduction, adjust Heater Drain Pump B speed and monitor power and SG levels.

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Event 2: Controlling PRZ pressure blue channel (III), PT-431 fails high.

After the power decrease the controlling PRZR Pressure blue channel, PT-431, fails high to 2500 psig. This will result in PRZR heater output going to zero, and PRZR Spray valves opening. Actual PRZR pressure will lower. The crew will perform actions of AOP-GEN-001, Immediate Operator Actions, Attachment H for Pressurizer Spray Valves Open and/or the ARP(s) associated with High Pressure alarms. The failed instrument will be addressed using AOP-MISC-001, Response to Instrument Failure, Attachment G Pressurizer Pressure.

Technical Specifications:

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.1-1 for the channel(s) or train(s) with a completion time of immediately.

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition E one channel inoperable with Required Action E.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.1-1 Item 6. Overtemperature T (Loop B Chan 3 OTT) & item 8.b Pressurizer Pressure High.

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition K one channel inoperable with Required Action K.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.1-1 Item 8.a Pressurizer Pressure Low

TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.2-1 for the channel(s) or train(s) with a completion time of immediately.

TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation Condition D one channel inoperable with Required Action D.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.2-1 Item 1.d Pressurizer Pressure - Low Note: The option in TS for shutting down the plant is not expected to be exercised for this failure The Unit supervisor will direct tripping of bistables. It is expected to trip bistables for the failed channel(s) during the scenario.

Event 3: FW-7B, Main Feedwater Regulating Valve to SG B experiences cycling.

After addressing the failed PRZR pressure channel, FW-7B, SG B Feed Reg Valve, will experience oscillation of the output signal from its controller in AUTO. This will result in fluctuation in SG B level, and feed flow. The BOP operator is expected to respond to the changes in SG B level and/or associated alarms. The crew will respond in accordance with AOP-GEN-001, Immediate Operator Actions, Attachment B, Abnormal Steam Generator Level, or the ARPs for SG level or steam/feed flow. The operator will transfer FW-7B controller to MAN and establish normal level in SG B (30% to 46%). The crew will also enter AOP-FW-001, Abnormal Feedwater System Operation, which also contains direction for maintaining SG level with the FW-7B controller in manual.

If the operator fails to control SG level and a reactor trip signal is generated, then Event 5, SGTR, will be initiated at its final value.

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Event 4: NIS red channel N41 fails low.

When FW-7B failure has been addressed, Power Range Nuclear Channel N41 (Red) will fail low. This will result in a rapid change in NI power rate and result in control rods in AUTO stepping OUT. The ATC operator will identify rod movement and determine rod movement is NOT required by the plant condition (stable). Actions of AOP-GEN-001, Immediate Operator Actions, Attachment C, Uncontrolled Rod Motion will be performed. Once it is determined that a turbine runback or rapid power reduction is NOT in progress, the ATC operator will place the Rod Bank Selector to MAN and verify rod motion stops. The crew will check for instrument failures and determine N41 channel has failed low. The failed instrument will be addressed using AOP-MISC-001, Response to Instrument Failure, Attachment J Nuclear Power Range.

The crew will remove N41 from service. Tave-Tref should be restored to within +/- 1ºF using rod control in manual.

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.1-1 for the channel(s) or train(s) with a completion time of immediately.

Either of the following for Table 3.3.1-1 Item 2.a Neutron Flux High

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition D one channel inoperable with Required Action D.1.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND Required Action D.1.2 reduce Thermal Power to < 75% RTP with a completion time of 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months .

Table 3.3.1-1 Item 2.a PR Neutron Flux High OR

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition D one channel inoperable with Required Action D.2.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND Required Action D.2.2 perform SR 3.2.4.2 with a completion time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Table 3.3.1-1 Item 2.a PR Neutron Flux High OR

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition D one channel inoperable with Required Action D.3 to be in MODE 3 with a completion time of 78 Table 3.3.1-1 Item 2.a PR Neutron Flux High Either of the following for Table 3.3.1-1 Item 6 OTT

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition E one channel inoperable with Required Action E.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.1-1 Item 6. Overtemperature T.

OR

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition E one channel inoperable with Required Action E.2 to be in MODE 3 with a completion time of 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months . Table 3.3.1-1 Item 6.

Overtemperature T.

The crew should note that tripping of the Loop B Chan 1 OTT will result in TWO channels of OTT being tripped and result in a reactor trip signal being generated. [Tripping of OTT Loop B Chan 1 should NOT be directed.] Management should be contacted to resolve problem and prioritize work.

TS LCO 3.0.3 will be entered for this situation.

If the crew elects to trip bistables the unit will trip and will move to the next event SGTR.

KPS-SEG1-L-RO/SRO- A-01242011-112

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Event 5: SGTR After the failed NI channel has been addressed, a tube rupture will occur in SG B. The rupture will build in over 5 minutes. The crew should recognize secondary system radiation indications for monitors R-43, R-15 and R-19 (SG B steam line N-14, Condenser Air Ejector and SG blowdown), and respond to the lowering RCS pressure, lowering PRZR level and increased charging. When letdown is isolated and maximum charging flow is established with two Charging Pumps, AND PRZR level is still decreasing, the Unit Supervisor (US) will direct a reactor trip as directed by AOP-RC-004 (or AOP-RC-001). When the reactor is tripped the SGTR will increase to its maximum input value (the ramp is stopped).

The crew will perform immediate actions of E-0:

5. CHECK reactor trip and reactor subcritical

6. ENSURE turbine trip

7. CHECK Bus 5 OR Bus 6 (ESF Bus) energized

8. CHECK SI actuated.

It is expected that SI will be manually actuated, or will be required, by this time as PRZR level continues to lower.

The US will hold a brief. The US should address the FOLD OUT Page Criteria 3 for isolating feed flow to a ruptured SG when narrow range level goes above 5%. The ATC operator will perform Attachment A steps while the US directs the BOP operator performing E-0 actions.

Event 6: AFW Pump A fails to auto start The BOP operator is expected to report the failure of AFW Pump A to start. [It should have started on low-low SG level and/or SI signal.] The BOP operator will manually start AFW Pump A, after closing AFW-2A, (and SI sequencer complete) by taking its control switch to STOP and then START positions. [THIS IS A CRITICAL TASK and must be accomplished by the initiation of the RCS cooldown directed in E-3, step 11]

The crew will continue the actions of E-0 to ensure Safeguards equipment is operating as required.

Diagnosis will be made of a SGTR and transition will be made to E-3.

The crew will identify SG B as ruptured and isolate feed flow into and steam flow from SG B [THIS IS A CRITICAL TASK and must be accomplished to prevent transition to ECA-3.1]. A RCS target temperature based on SG B pressure will be determined and a cooldown initiated using the condenser

[MS-1A open] or SD-3A [MS-1A closed].[THIS IS A CRITICAL TASK] The cooldown will be stopped and stabilized after the target temperature is reached. The RCS will then be depressurized using PRZR Sprays or a PRZR PORV. Conditions will be checked for SI termination and SI flow stopped. [THIS IS A CRITICAL TASK and must be accomplished before SG B level is at 100% narrow range AND SG B pressure rises above 1050 psig, indicative of SG overfill]

Conditions will be established to allow balance between RCS pressure and SG B pressure.

The scenario may be terminated at the point SI flow is stopped in E-3.

KPS-SEG1-L-RO/SRO- A-01242011-112

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Malfunctions:

Before EOP Entry:

1. PT-431 Pressurizer Pressure Instrument failure

2. FW-7B Controller failure with oscillations

3. Power Range NI Channel N41 fails low After EOP Entry:

1. Steam Generator B tube leakage / rupture

2. AFW Pump A fails to auto start Abnormal Events:

1. PT-431 Pressurizer Pressure Instrument failure

2. FW-7B Controller failure with oscillations

3. Power Range NI Channel N41 fails low

4. AFW Pump A failure to auto start Major Transients:

1. Steam Generator B tube leakage / rupture KPS-SEG1-L-RO/SRO- A-01242011-112

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Critical Tasks CRITICAL TASK: Isolate Feed Flow into and Steam Flow from the Ruptured SG before a transition to ECA-3.1 occurs a) SAFETY SIGNIFICANCE:

i) Failure to isolate the rupture SG causes a loss of differential pressure between the ruptured SG and the intact SG. Upon a loss of differential pressure, the crew must transition to a contingency procedure that constitutes an incorrect performance that necessitates the crew taking compensating action which complicates the event mitigation strategy b) CUE:

i) Increasing SG water Level, Abnormal Radiation indication in the ruptured SG c) MEASURABLE PERFORMANCE INDICATOR:

i) Auxiliary feed flow isolated to SG B as indicated by 0 gpm on the B AFW header ii) 0 gpm main feed flow iii) MS-100B Closed iv) MS-1B and MS-2B Closed d) PERFORMANCE FEEDBACK:

i) Indication of stable or increasing pressure in ruptured SG B ii) Indication of 0 feedwater flow to ruptured SG B WOG Critical Task E-3 -- A CRITICAL TASK Establish AFW flow to A SG to support cooldown and depressurization of the RCS to stop break flow a) SAFETY SIGNIFICANCE:

i) Failure to establish AFW flow to A SG with AFW pump A will prevent having sufficient inventory in SG A to support cooldown and depressurization of the RCS. Cooldown and depressurization of the RCS is part of the mitigation strategy for a ruptured steam generator and result in transition to a contingency procedure.

b) CUE:

i) AFW pump A not running when required. SG water levels less than 17%

c) MEASURABLE PERFORMANCE INDICATOR:

i) Feed flow to SG A as indicated by greater than 0 gpm on flow meter for A AFW Header d) PERFORMANCE FEEDBACK:

i) Flow indication on A AFW header Scenario based Critical Task KPS-SEG1-L-RO/SRO- A-01242011-112

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CRITICAL TASK Establish and maintain an RCS temperature so that transition from E-3 does not occur because the RCS Temperature is in either of the following conditions:

Too high to maintain minimum required subcooling OR

Below the RCS temperature that causes a red path or orange path challenge to the sub criticality and/or integrity CSF status trees a) SAFETY SIGNIFICANCE:

i) Failure to establish and maintain the correct RCS temperature during a SGTR leads to a transition from E-3 to a contingency procedure which constitutes an incorrect performance that necessitates the crew taking compensating actions which complicates the event mitigation strategy b) CUE:

i) SGTR and Ruptured SG level rising c) MEASURABLE PERFORMANCE INDICATOR:

i) Select the correct CET temperature to permit stopping of SI pumps and maintaining the CET temperature to prevent reinitiating of SI and Transition to ECA-3.1 per the foldout page of E-3 d) PERFORMANCE FEEDBACK:

i) Sufficient Subcooling to Stop SI pumps and maintain the SI pumps stopped WOG Critical Task E-3--B CRITICAL TASK Stop Break Flow before SG overfill a) SAFETY SIGNIFICANCE:

i) Failure to stop break flow before SG overfill could result in unnecessary release of radioactivity to the public and thus endangering the health and safety of the public b) CUE:

i) SGTR and Ruptured SG level rising c) MEASURABLE PERFORMANCE INDICATOR:

i) Both SI pumps stopped prior to SG overfill as indicated by a rapid rise in SG pressure d) PERFORMANCE FEEDBACK:

i) SI pumps and in AUTO with subcooling > 15ºF WOG Critical Task E-3C,D KPS-SEG1-L-RO/SRO- A-01242011-112

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TASKS Task Number Task Title SRO Tasks:

1190190302 Apply Technical Specifications During Plant Operations 1190070502 Coordinate the Implementation of the IPEOPs Demonstrate an understanding of the responsibility and requirements for the Control 1190330302 Room Supervisor RO Tasks:

0540060101 Change Turbine and Generator Load 0350240101 Control RCS Boron Concentration by the use of Boration 0360420401 Respond to a Pressurizer Control Press Abnormal Annunciator 0500020401 Respond to ICCMS Panel Trouble Annunciator 05A0100401 Respond to a S/G A(B) Feed Flow Excessive Annunciator 05A0140401 Respond to TLA-10, Steam Generator Tilts 05A0030401 Transfer Feedwater Control from Automatic to Manual Control during Abnormal Feedwater System Operation 0480130401 Respond to a Power Range Negative Rate Channel Alert annunciator 0480030401 Respond to a failure of Power Range Instrumentation 1190250301 Respond to a Steam Generator Tube Leak E000010501 Respond to a Reactor Trip Condition with Safety Injection E030010501 Respond to a Steam Generator Tube Rupture 05B0030401 Respond to Abnormal AFW System Operation STA Tasks: N/A KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

1. INITIAL CONDITIONS:

Standard IC-13

Mode: 1

Exposure: 17000

Power: 99.3%

Boron: (CB): 85 ppm

Temperature: 572ºF

Pressure: 2235 psig

Xenon: Equilibrium

Rods: ARO

Generator 602 Mwe

Thermal Power 1770.1 Mwth KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

2. SIMULATOR SETUP:

RESET to IC# 13 and go to run

ENSURE R-21 is aligned to sample The following forms are needed during the containment - New for ITS Remote scenario and are to be placed in the booth. RM101

ENSURE R-23 PROTECTED TRAIN No Additional Material Need For Booth placard is in place below the R-23 drawer Shift Manager Status board information

Remove T/D AFW Pump from SERVICE, ALIGN the following Equipment OOS equipment and PLACE tags on the equipment PR-2A excessive seat leakage

MS-102 - PULLOUT TD AFW Pump

MS100A - CLOSE

MS100B - CLOSE Note: Alignment is per MA-KW-MCM-AFW-TS 3.7.5 (AFW system) Condition B with 002, Repair of Turbine-Driven Auxiliary one AFW Train inoperable. Required Feedwater Turbine, for appropriate sections Action B.1 is to restore train(s) to OPERABLE status with a Completion Time

POSITION AS-31/AS-35, R-11 and R-of 72 Hours. Start Time 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months before 12 Sample return to return to the scenario start time. containment.

ALIGN Containment Vent 2 path:

PLACE Containment Dome Fan B to TS 3.4.11 (Reactor Coolant System START Pressurizer Power Operated Relief Valves)

Condition A One or more PORVs

STOP Containment Dome Fan A inoperable and capable of being manually and PLACE in AUTO cycled. Required Action A.1 is to close

OPEN LOCA-2B, POST-LOCA and maintain power to the associated HYDROGEN CNTMT VENT ISOL B PORV Block Valve with a completion time

OPEN LOCA-100B, POST-LOCA of one hour (Completed). HYDROGEN TO RECOMBINER B

PLACE PR-1A to CLOSE, and PLACE clearance status tag

OPEN and Run CAEP file. ROI-06-SE-KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Remarks SC1-preload.cae. After file has run for Protected train = A one minute close CAE file.

Risk CDF/LERF= Green

Verify the Instructor Station Summary IAW instructions at the beginning of the SPER / WRs input summary in this SEG None

Second verification of the Instructor IAW instructions at the beginning of the input summary in this SEG GENERAL

Start SmartTest using the Consecutive days of operation ___490____ SmartTemplate for NRC Exam.xlt file.

G-1 Closed (indicate date last month) JD

ENSURE Job Aid 04-009, Simulator xxx Exam/EP Drill Setup and Cleanup Burn up 17,000 MWD/MTU adequate to support exam by COMPLETING ATTACHMENT 1, Sirens Lost Coverage % __0__ Simulator Setup Exams/EP Drill, or Sirens OOS __0__ ATTACHMENT 2, Reset Exam/EP Drill, as appropriate RCS and Pressurizer boron = 85 ppm All other entries are standard KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

3. PRE-SCENARIO:

a) IF this is the first simulator scenario of the week, THEN review the Simulator Differences List with the crew.

b) Provide crew with:

Turnover sheets and plant information

Copies of GOP-307, NOP-TB-001 (IMP IN is to be used during load reduction), NOP-HD-001, NOP-CVC-001 and Standard Reactivity Plan to support down power directed by Management

For containment vent, Provide copy of Data Sheet C, Containment Vent Log, from SP-32-113, Gaseous Radioactive Effluents Reports For Continuous Releases, with Month and Year filled-in, and Date, Start Time, RP Notified (Y) & Remarks (2 Vent) filled-in.

c) Cover Simulator Scenario Briefing Sheet in Job Aid 04-01 with the crew

Inform the crew that the Designated Exam Team Member will take response for the Shift Manager. They will acknowledge communications, but their acknowledgment does KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS not mean agreement or disagreement.

d) ENSURE the crew has been briefed IAW NUREG 1021 Appendix E (Simulator Test Guidelines) e) If allowed by the NRC Chief Examiner, Lead Exam Team Member will perform a Pre-Job brief per Job Aid 04-03.

4. TURNOVER: PROVIDE Shift Turnover (All) Walk down control boards~ 5 minutes Information.

After ~5 minute walk down of boards by the crew. Give the crew the shift.

Shift Direction:

Commence Management directed down power using GOP-307.

5. SCENARIO: During the scenario if the US asks for an EAL evaluation the response is under evaluation KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 1: POWER REDUCTION TO LESS THAN 95% POWER ATC - Reactivity; BOP - Normal Human Performance Tools: Pre-Job Brief, Procedure Compliance, Clear Communications, Peer Checking Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely Controlling Plant Evolutions, Teamwork OP-KW-GOP-307, Hold at Power greater than 35%

The crew has reviewed the back down US Direct power reduction per GOP-307, information prior to entering the Simulator section 5.2.

and decided upon a plan. Direction has

Perform Reactivity Estimate (Crew) been to initiate a back down following turnover to 95% reactor power at 1/2 % per

Reduce load per NOP-TB-001 (BOP) minute.

Perform Reactivity adjustments per NOP-CVC-001 & NOP-CRD-001 (RO)

Note: NOP-CRD-001 is not expected to be

Adjust Heater Drain Pump Speed per used with control rods in automatic NOP-HD-001 (BOP)

Operator Fundamentals: Team work, CREW PERFORM reactivity estimate Precisely Controlling Plant Evolutions

Start time Human Performance: Peer Checking

Expected reactivity change due to load change The crew should use a standard reactivity

Rate of load change plan.

Expected reactivity changes due to xenon A crew brief should be performed for the

Delta-I control limits back down and reactivity plan. All reactivity

Gallons of boration or dilution and rate calculations and manipulations must be of addition peer checked IAW standards.

Control rod steps expected KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS NOP-TB-001, Turbine and Generator Operation If asked, the turbine should be operated in BOP REDUCE load per NOP-TB-001 IMP IN during load reduction section 5.7

Loading rate has been determined and Attachment J does not have to be referenced

VPL should be maintained as close as reasonably possible to actual turbine load

Set Turbine Controls to IMP In

Adjust setter until value is approximately 5 to 9 % below Reference value

Loading Rate set to 1/2 %/min ROLE: DEMI US Directs DEMI be informed or contacts REQUEST: Inform of back down DEMI to inform them of rate and amount of load reduction ( ~ 5% at 1/2 %/min)

RESPONSE: Acknowledge back down DELAY: None ROLE: ATC US inform ATC of load reduction REQUEST: Inform of back down RESPONSE: Acknowledge back down DELAY: None Human Performance: Focus Brief on going BOP Press the GO button and maintain to GO on the turbine, Self Checking reactive load limits within the limits of Operator Fundamental: Teamwork. Attachment E.

KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamental: Closely Monitoring BOP Monitor plant parameters for correct parameters system response and then place the Turbine in HOLD when required load reduction is complete.

Human Performance: Peer Checking BOP press VVE POS Limit UP/DOWN Pushbutton until VPL is within 2% to 3% of current load The procedure states if required to place to BOP place the turbine on the VPL the Turbine on the VPL.

Human Performance: Peer Checking ROLE: ATC US When load reduction is complete then REQUEST: Inform of completion of back inform ATC down RESPONSE: Acknowledge back down complete DELAY: None NOP-CVC-001, Boron Concentration Control Human Performance Tools: Peer Checking US/RO DETERMINE rate and magnitude of boration including 20 gallon flush Boration should be conducted per Standard Reactivity Plan Operator Fundamentals: Knowledge of US/RO ESTIMATE expected change in Plant Design and Theory Rod Position, Boron Concentration, and Reactor Thermal Power Human Performance: Peer Checking RO SET Boric acid Totalizer

ENTER desired value on thumbwheel

While depressing black pushbutton, CLOSE shutter on Boric Acid Totalizer KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance: Peer Checking RO POSITION Reactor Makeup Mode Selector to BORATE CREW should wait until boron affects Tave RO POSITION Reactor Makeup Control prior to starting the back down. switch to START Human Performance: Peer Checking RO ADJUST CVC-403 for BA flow rate ROLE: AO RO when the boration is complete then REQUEST: Ensure CVC-712A & 712B

Ensure CVC-712A & 712B closed closed

Check correct quantity boric acid RESPONSE: Acknowledge direction and added report valves closed after delay

Reset Boric Acid Totalizer DELAY: 5 minutes Human Performance: Peer Checking RO PERFORM 20 gpm flush

SET Rx Makeup Totalizer to 20

POSITION Reactor Makeup Mode Selector switch to ALT DIL

POSITION CVC-406/CV-31094, BA Blender to VCT Control switch to CLOSE

POSITION Reactor Makeup Control switch to START KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS The setpoint value is determined using RO WHEN Alt Dilution flush complete:

current Boron Concentration and RD 2.1.1 OR Operator Aid 96-3

ENSURE MU-1022 set to 60 gpm

DETERMINE setpoint for CVC-403 that Human Performance: Peer Checking will provide blended flow at current RCS Human Performance: Self Checking Boron Concentration

SET CVC-403 hand controller to recorded setpoint

POSITION CVC-406 Control switch to AUTO

POSITION Reactor Makeup Mode Selector switch to AUTO

POSITION Reactor Makeup Control switch to START

At Rx Makeup Totalizer, CHECK correct quantity

Reset Reactor MU Totalizer NOP-HD-001, Heater Moisture Separator Drain and Bleeder Steam System BOP ADJUST heater drain pump speed to maintain equal loading KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 2: Controlling Channel Pressurizer Pressure PT-431, Blue Channel, Fails High Human Performance Tools: Procedure Compliance, Clear Communications, Verification Practices Operator Fundamentals: Closely Monitoring Plant Conditions, Knowledge of Plant Design and Theory Instrument RO Technical Specification SRO The controlling channel will cause the When directed by the Lead Evaluator insert Annunciators:

PRZR pressure control system to respond TRIGGER 1 47041-C Pressurizer Pressure 2385 to a high Przr pressure condition: Verify that RX203, PT-431 PRZ Press 47043-C Pressurizer Control Pressure inserts Abnormal

PRZR heaters will deenergize

PRZR Spray Valves will open 47043-D Pressurizer Pressure Low

PORVs remain closed since only one 47043-J Charging Pump in Auto High/Low channel is affected Speed

Actual PRZR pressure will lower 47044-F ICCMS Panel Trouble

Alarms 47041-C, 47043-C are associated with the failed PRZR Indications pressure channel PI-431 above 2235 psig and rising toward

47043-D is associated with the 2500 psig OPERABLE PRZR pressure channels PRZR pressure PI-429, PI-430 & PI-449

47043-J is related to the below 2235 psig and lowering depressurization resulting in rise in PRZR heaters in AUTO green lights lit PRZR level PRZR Spray Valve PS-1A & PS-1B red

47044-F is related to reduced lights light and valve demand position subcooling (< 20ºF) due to trending to 100% (Open) depressurization KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamentals: Closely CREW Respond to and diagnose Blue Monitoring Plant Conditions, Knowledge of channel Pressurizer pressure failing high.

Plant Design and Theory Human Performance Tools: Clear US DIRECT/ENSURE action of ARPs Communications and/or AOP-GEN-001 performed ARP 47043-C or ARP-47041-C are likely the first ARPs addressed. AOP-GEN-001 actions may be taken by RO based upon opening of PRZR Spray valves ARP-47043-C, Pressurizer Control Pressure Abnormal RO Check Pressurizer Pressure - Normal At 2235 psig RNO If the controlling Pressurizer pressure instrument has failed then perform the following:

Position PRZR Pressure Control Channel Selector Switch to remove the failed instrument

GO TO OP-KW-AOP-MISC-001 ARP-47041-C, Pressurizer Pressure 2385 RO Check Reactor NOT Tripped RO Check Pressurizer Spray Valves Both Open RO Check All Pressurizer Heaters Off KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO Check Alarm - NOT Caused by Instrument Failure RNO

Position PRZR Pressure Control Channel Selector Switch to remove the failed instrument (2-1 position)

GO TO OP-KW-AOP-MISC-001 AOP-GEN-001, Operator Immediate Actions, Attachment H Human Performance Tools: Procedure RO Check Pressurizer Spray Valves -

Compliance Both Closed RNO IF PRZR Pressure less than 2260

Manually Close PS-1A & PS-1B Human Performance: Clear RO Check Initiating Event - Instrument Communications Failure - Identify PT-431 failed A short crew brief may be held during the US Transition to AOP-MISC-001 transition US may direct the BOP Operator to verify BOP CHECK other ARPs for actions and that the remaining ARPs are addressed report remaining ARPs have actions addressed by AOPs

ARP 47044-F directs additional actions:

o CHECK indicated subcooling normal ICCM Error Code E45 - Low saturation SMM display > 20ºF margin alarm (RCS subcooling less than or Error Code E45 displayed equal to 20°F)

KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS o CHECK Pressurizer Pressure -

stable at or trending to 2235 psig Restore pressure CHECK requirements of TS 3.4.1 satisfied o CHECK RCS Tavg - stable at or trending to program o CHECK Required Accident Monitoring Instrumentation OPERABLE - TS Table 3.3.3-1 o CHECK ICCMS PANEL TROUBLE Alarm 47044-F - CLEAR AOP-MISC-001, Response to Instrument Failure Human Performance Tools: Procedure RO VERIFY Immediate Actions for Compliance Pressurizer Spray Valve Open per AOP-GEN-001 have been completed Human Performance Tools. Verification RO POSITION PRZR Pressure Control Practices(Peer Checking) Channel Selector switch to a position that does NOT use PT-431 The 2(White)/1(Red) position will be selected Human Performance Tools. Peer Checking US/RO POSITION PRZR Pressure Channel 1 (red) is the preferred channel but Recorder Input Selector switch to an Channel 2 or 4 may be selected operable Channel. (Channel 1, 2, or 4)

KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS NOTE: The control channel may initially RO RESTORE RCS Pressure 2220-2250 raise PRZR pressure above the normal psig (2235 psig) due to controller windup.

Human Performance Tools. Peer Checking RO RETURN Pressurizer Spray Valves to AUTO ROLE: SM US inform SM of PT-431 failure RESPONSE: Acknowledge failure of PT-431 ROLE: SM ROLE: I&C US DIRECT I&C to perform corrective REQUEST: Ask I&C to perform corrective REQUEST: Perform Corrective maintenance on PT-431 - may directly maintenance on failed channel Maintenance on failed channel inform I&C or ask SM to inform I&C RESPONSE: Acknowledge direction inform RESPONSE: Acknowledge direction and will inform I&C state that will write CR, generate work order DELAY: None and begin getting people together DELAY: None During this time it is expected that the US US Address Technical Specifications has a crew brief.

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation)

Other than the failed PRZR pressure Condition A One or more Functions channel, the following conditions will be with one or more required channels addressed in Technical Specifications: or trains inoperable. Required Action A.1 enter the condition

RCS pressure, temperature and flow referenced in Table 3.3.1-1 for the DNB limits (LCO 3.4.1) depending on channel(s) or train(s) with a crew response time may have completion time of immediately.

entered and exit (COLR 2.11 - based upon PRZR pressure 2217 psig for KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS control board indication or 2219 psig

TS 3.3.1 (Reactor Protection for computer indication) System (RPS) Instrumentation)

PAM Instrumentation (LCO 3.3.3) - met Condition E one channel inoperable These may be addressed later, after AOP- with Required Action E.1 to place MISC-001 actions channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.1-1 Item

6. Overtemperature T (Loop B Chan 3 OTT) & item 8.b Pressurizer Pressure High.

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation)

Condition K one channel inoperable with Required Action K.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.1-1 Item 8.a Pressurizer Pressure Low

TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.2-1 for the channel(s) or train(s) with a completion time of immediately.

TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation Condition D one channel inoperable with Required Action D.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Table 3.3.2-1 Item 1.d Pressurizer Pressure - Low KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

Potential for TS 3.4.1 RCS DNB Limits, a. Pressurizer pressure is greater than or equal to the limit specified in the COLR (2.11)

Condition A with one or more parameters not within limits with Required Action A.1 to restore RCS DNB parameter(s) to within limits with a completion time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

The remaining action of AOP-MISC-001 RO CHECK the existing bistable status to address I&C tripping of the bistables for ensure a Reactor trip will NOT occur when the failed channel, this action will NOT the failed channel is placed in tripped be performed in this Scenario. condition

No adverse condition noted ROLE: SM ROLE: I&C US request SM or directly contact I&C to REQUEST: Contact I&C to perform SP- REQUEST: perform SP-47-316G for the perform SP-47-316G for the failed channel 47-316G failed channel RESPONSE: wait delay then report that RESPONSE: Acknowledge direction to I&C reports SP-47-316G does not need to perform SP-47-316G. I&C states procedure be performed at this time is not required at this time.

DELAY: 1 minute DELAY: None ROLE: SM ROLE: WWC and/or I&C US request SM or directly contact I&C to REQUEST: Send and I&C tech to the REQUEST: Send and I&C tech to the come to the control room for tripping of control room for the tripping of bistables control room for the tripping of bistables bistables RESPONSE: Acknowledge the request and RESPONSE: Acknowledge the request and inform the Control Room that an I&C tech inform the Control Room that an I&C tech will be in the control room in about 45 will be in the control room in about 45 minutes minutes Delay: 1 minute Delay: None KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS When Technical Specifications have been addressed, then continue with next event EVENT 3: FW-7B, Main Feedwater Flow Control Valve, Controller Oscillations Human Performance Tools: Procedure Compliance, STAR, Clear Communications Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely Controlling Plant Evolutions Component BOP FW-7B, SG B Feed Flow Control Valve will When directed by the Lead Evaluator insert Annunciators:

begin divergent oscillation. SG B level will TRIGGER 15 47061-F S/G B Feedflow Excessive fluctuate with the control valve movement. If Verify that RX02B, Steam Generator Level no action is taken a reactor trip will result on 47062-D S/G B Program Level Deviation Controller Unstable (FW-7B) inserts Low SG level (25% NR) with low FW flow. 47062-E S/G B Bypass CV Level Deviation 47061-E S/G B SF > FF TLA-10 Steam Generator Tilts Indications FW-7B cycling Operator Fundamentals: Closely CREW Respond to and diagnose unstable Monitoring Plant Conditions, Bias for response of FW-7B Controller with changes Conservative Decisions in SG B level and feed flow.

Human Performance Tools: Clear Communications US DIRECT/ENSURE action of ARPs and/or AOP-GEN-001 performed SG A level will also be affected by oscillations of FW-7B but to a much lesser extent. The Operator may decide to take manual control of both FW Control Valves to stabilize plant. Alarms are NOT expected for SG A KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS AOP-GEN-001, Immediate Operator Actions Operator Fundamentals: Closely BOP CHECK Steam Generator Narrow Monitoring Plant Conditions Range Level stable at program level and Human Performance Tools: STAR, Clear with level changing in an uncontrolled Communications manner:

SHIFT FW-7B Controller to MAN Depending on the time it takes the crew to

THROTTLE FW-7B to maintain SG B identify the cycling of FW-7B TLA-11 may narrow range level stable between 30%

alarm. and 46%

BOP CHECK for Instrument Failure:

SG Narrow Range Level

SG Feedwater Flow

SG Steam Flow

SG Pressure US Transition to AOP-FW-001 AOP-FW-001, Abnormal Feedwater System Operation US DIRECT action of AOP-FW-001 CHECK entry condition due to feedwater flow NOT normal KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS The BOP Operator will be required to BOP CHECK SG levels normal maintain SG B level with FW-7B in MAN

ENSURE FW-7B in MAN Operator Fundamentals: Closely Monitoring Plant Conditions

THROTTLE FW-7B as necessary to establish 44% NR level Human Performance Tools: STAR, Clear Communications ROLE: SM US Inform SM of FW-7B and MAN control RESPONSE: Acknowledge failure of FW- of SG B level 7B EVENT 4: Power Range Nuclear Instrument Channel N41 Fails Low Human Performance Tools: Procedure Compliance, Clear Communications, Verification Practices Operator Fundamentals: Closely Monitoring Plant Conditions, Bias for Conservative Decisions, Teamwork, Knowledge of Plant Design and Theory Instrument ATC Failure of the NI instrument low will result in When directed by the Lead Evaluator insert Annunciators:

OUTWARD control rod motion in AUTO due TRIGGER 17 47061-F, S/G B Feedflow Excessive to turbine-NI power mismatch. Verify that NI05A, Improper Power Range 47032-J, Power Range Negative Rate Response (N41) inserts Channel Alert 47033-K, Power Range Channel Deviation TLA-6 Power Range Radial Flux Tilt Board Indications NI-41 power indication 0%

Outward Rod Motion KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamental: Closely Monitoring CREW Identifies rod motion and takes Plant Parameters actions per AOP-GEN-001 AOP-GEN-001, Immediate Operator Actions Operator Fundamental: Teamwork RO Check Rod Motion Stopped - NO Human Performance: Clear BOP Identify that there is NOT a Turbine Communication Runback or rapid power reduction in progress Human Performance: Self Checking RO Position the Control Rod Bank Selector Switch to MAN Human Performance: Clear CREW Identify NI failure Communication The US may hold a brief at this point when US Transition to AOP-MISC-001 plant conditions are stable AOP-MISC-001, Response to Instrument Failure, Attachment J RO Ensure the immediate actions for uncontrolled rod motion performed per AOP-GEN-001 Human Performance: Self Checking, RO Perform the following to defeat failed Verification Practices (Peer Checking) PR Channel Verify Control Rod Bank Selector Switch in MAN Position the following switches to the failed PR Channel

Upper section on Detector Current Comparator

Lower Section switch on Detector Current Comparator

Rod Stop Bypass switch on KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Miscellaneous Control and Indication Panel

Power Mismatch Bypass switch on Miscellaneous Control and Indication Panel

Comparator Channel Defeat Switch on Comparator and Rate Drawer Operator Fundamental: Knowledge of Plant CREW Ensure interlocks in required state Design and Theory for existing unit conditions If greater than 10% Power Ensure the following:

44905-0501 P-7 Permissive OFF

44905-0502 Permissive P-8 OFF

44905-0201 Permissive P-10 ON US If two or more Power Range Channels inoperable - N/A US/RO Restore Tave-Tref error to within 1ºF US read the caution with P-7 and P-10 if additional NI channel fails high ROLE: SM ROLE: I&C US DIRECT I&C to perform corrective REQUEST: Ask I&C to perform corrective REQUEST: Perform Corrective maintenance on NI may directly inform maintenance on failed channel Maintenance on failed channel I&C or ask SM to inform I&C RESPONSE: Acknowledge direction inform RESPONSE: Acknowledge direction and will inform I&C state that will write CR, generate work order DELAY: None and begin getting people together DELAY: None KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS The US may hold a crew brief at this time if US refer to TS 3.3.1 plant conditions are stable

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation)

Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.1-1 for the channel(s) or train(s) with a completion time of immediately.

Either of the following for Table 3.3.1-1 Item 2.a Neutron Flux High

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation)

Condition D one channel inoperable with Required Action D.1.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND Required Action D.1.2 reduce Thermal Power to < 75% RTP with a completion time of 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months . Table 3.3.1-1 Item 2.a PR Neutron Flux High OR

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation)

Condition D one channel inoperable with Required Action D.2.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND Required Action D.2.2 perform SR 3.2.4.2 with a completion time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Table 3.3.1-1 Item 2.a PR Neutron Flux High KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS OR

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation)

Condition D one channel inoperable with Required Action D.3 to be in MODE 3 with a completion time of 78 Table 3.3.1-1 Item 2.a PR Neutron Flux High Either of the following for Table 3.3.1-1 Item 6 OTT

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation)

Condition E one channel inoperable with Required Action E.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.1-1 Item

6. Overtemperature T.

OR

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation)

Condition E one channel inoperable with Required Action E.2 to be in MODE 3 with a completion time of 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months . Table 3.3.1-1 Item 6.

Overtemperature T.

LCO 3.03 because of being unable to trip failed channel KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: SM ROLE: I&C US request SM or directly contact I&C to REQUEST: perform SP-47-316E for the REQUEST: perform SP-47-316E for the perform SP-47-316E for the failed channel failed channel failed channel RESPONSE: Acknowledge direction to RESPONSE: Acknowledge direction to perform SP-47-316E. I&C states procedure perform SP-47-316E. I&C states procedure is not required at this time. is not required at this time.

DELAY: 2 minutes DELAY: None Knowledge of Plant Design and Theory US/RO Check the existing bistable condition to ensure a reactor trip will NOT occur when the failed channel is placed in Note: The crew should note that tripping of tripped condition - Crew determines that the Loop B Chan 1 OTT will result in TWO tripping bistables will result in a reactor trip channels of OTT being tripped and result in a reactor trip signal being generated.

[Tripping of OTT Loop B Chan 1 should NOT be directed.] Management should be contacted to resolve problem and prioritize work.

KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 5/6: Tube Rupture on B SG - Failure of AFW pump A to Auto Start Human Performance Tools: Procedure Compliance, Clear Communications, Peer Checking Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely Controlling Plant Evolutions, Understanding Plant Design and Theory Major - ALL Component BOP The inserted fault will initial be a tube leak At the lead evaluators direction insert Annunciators:

and rapidly build to a SG tube rupture. The TRIGGER 23 to insert SG B Tube Rupture TLA-15, RMS Above Normal crew will not have time to perform a power

Ensure SG01B inserts and is ramping to Board Indications:

reduction before a Reactor Trip is required a value of 9 over 5 minutes R-15 count rate rising When a reactor trip occurs, malfunction

When a reactor trip occurs, ENSURE SG01B will change to a value of 10 R-19 count rate rising SG01B value changes to 10 R-43, N-16 radiation indication rising US Direct reference to TLA-15, RMS Above Normal US Transition to AOP-RC-004, Steam Generator Tube Leak AOP-RC-004 The tube leak rate will rapidly progress to a (CAS)US/RO Check reactor trip not rupture. Crew may return to this CAS for required direction to trip.

Check PRZR level > 3%

Check Reactor Critical

Check VCT level > 5%

KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS The tube leak rate will rapidly progress to a (CAS)US/RO Check PRZR level stable at rupture. Crew may return to this CAS for or trending to program level direction to trip. RNO

Increase charging speed to establish maximum charging flow

Position PRZR heaters ON to maintain RCS pressure

If PRZR level continues to decrease, Then close all LD isolation valves

If PRZR level continues to decrease, then:

o Manually trip reactor o Go To E-0

Control Charging flow as necessary to maintain PRZR Level US/RO Check Automatic Makeup controls Ensure Makeup is set at proper boric acid concentration Ensure Reactor Makeup Mode Control Switch - In AUTO Check Reactor Makeup Control switch -

Red Light ON Check VCT Level - Between 17% and 28%

It is not expected that AOP-RC-004 will be US/RO Determine SG leak rate exercised past this step KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS E-0, Reactor Trip or Safety Injection US based on plant conditions and reports from the board operator about maintaining PRZR level the US should hold a focus brief and direct tripping of the rector RO Manually Trip the Reactor RO Ensure Reactor Trip

Check Reactor Trip and Bypass Breakers OPEN

Check Reactor Subcritical BOP Ensure Turbine Trip

Check HP Turbine Impulse Pressure Trending Toward Zero

Check both Turbine Stop Valves Closed BOP Check 4160V Emergency AC Buses at Both energized. Bus 5 and Bus 6 SI should have actuated, or will be required RO Check SI actuated manually, on lowering PRZR level and RCS Check permissive status 44905-1201 SI pressure. Signal Activated LIT KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RNO Determine appropriate recovery action Check if SI is required

PRZR pressure < 1815 psig

PRZR Level < 3%

RCS subcooling < 15ºF

SG pressure < 500 psig

Containment pressure > 4 psig If SI is required then manually actuate both trains of SI US Hold crew brief

Announce Crew Brief

EAL o Under review

Recap Major Events o Steam Generator Tube Rupture in B SG

Ongoing Recovery Actions o Continue in E-0

Comments

End Crew Brief Crew Monitors Foldout Page See separate section below. RO - Performs Attachment A by direction from the SRO.

KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS This action is one part of the critical BOP Identifies Ruptured B SG Task.

If any SG is ruptured (Level rising in an CRITICAL TASK: Isolate Feed Flow into uncontrolled manner or abnormal and Steam Flow from the Ruptured SG radiation) and affected SG narrow before a transition to ECA-3.1 occurs range level is greater than 5%[13%]

then isolate feed flow to the ruptured SAFETY SIGNIFICANCE: Failure to SGs isolate the rupture SG causes a loss of differential pressure between the ruptured o CLOSE AFW-2B, AFW Pump B SG and the intact SG. Upon a loss of Flow Control Vlv differential pressure, the crew must o CLOSE AFW-10B, AFW Train B transition to a contingency procedure that Crossover Valve constitutes an incorrect performance that necessitates the crew taking compensating action which complicates the event mitigation strategy CUE: Increasing SG water Level, Abnormal Radiation indication in the ruptured SG MEASURABLE PERFORMANCE INDICATOR:

Auxiliary Feed flow isolated to SG B as indicated by 0 gpm on the B AFW header

0 gpm main feed flow

MS-100B Closed

MS-1B and MS-2B Closed PERFORMANCE FEEDBACK:

Indication of stable or increasing pressure in ruptured SG B

Indication of 0 feedwater flow to ruptured SG B WOG Critical Task E-3 -- A KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS CRITICAL TASK Establish AFW flow to A (CAS) US/BOP Check AFW Pumps SG to support cooldown and Running depressurization of the RCS to stop break Check AFW Pump A Running flow SAFETY SIGNIFICANCE: Failure to RNO establish AFW flow to A SG with AFW

Close AFW-2A pump A will prevent having sufficient inventory in SG A to support cooldown and

When SI Sequencer Complete Start depressurization of the RCS. Cooldown AFW Pump A and depressurization of the RCS is part of Check AFW Pump B Running the mitigation strategy for a ruptured steam generator and result in transition to a Check MD AFW Pumps Both Running contingency procedure. Throttle MD Flow as necessary to maintain CUE: AFW pump A not running when discharge pressures greater than 1000 psig required. SG water levels less than 17% prior to and immediately prior to stopping MEASURABLE PERFORMANCE TD AFW pump. - N/A INDICATOR: Feed flow to SG A as Stop TD AFW pump and place in Pullout -

indicated by greater than 0 gpm on flow N/A meter for A AFW Header PERFORMANCE FEEDBACK: Flow indication on A AFW header (CAS) US/BOP AFW discharge pressure >

1000 psig US/BOP Check Secondary Heat Sink Ensure total AFW flow > 210 gpm OR SG narrow range level > 5% [13%]

US/CREW Check RXCP Seal Cooling Normal KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS (CAS) US/CREW Check RCS Temperature Control

RCS Cold Leg temperatures

<5470F and Stable RNO

Main Steam Dump Mode Selector Switch to RESET then STM PRESS

Stop Dumping Steam

If SG pressure less than 1005 psig Then VERIFY SG PORV CLOSED

Reduce Total Feed Flow to between 210 - 250 gpm

CLOSE MS-1A, MS-2A, MS-1B, MS-2B if RCS temperature continues to lower US/RO Check PRZR PORVs - Both Closed US/RO Check PRZR Spray Valves Closed US/ RO Check if RXCPS should remain running OP-AP-104 states that in the absence of CREW Monitor CSF Status Trees the STA the crew will monitor CSF status trees KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS CREW Check If any SG is Faulted The US should hold a crew brief on the CREW Check if SG tubes are intact transition to E-3

Air Ejector Exhaust Monitor Normal (R-15)

SG Blowdown Liquid Monitor Normal (R-19)

Main Steam Line Radiation Normal (R-33)

N-16 before the trip normal (R-43)

Steam Flow/Feed Flow and AG narrow range response normal before the trip RNO DO NOT Continue until Attachment A is Complete Transition to E-3 KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS E-0 Attachment A RO Notify Plant Personnel using Gai-Tronics RO Check Feedwater Isolation

FW-7A/B Closed

FW-10A/B Closed

FW-12A/B Closed

FW Pumps A & B OFF RO Check SI Pumps - BOTH RUNNING RO Check RHR Pumps - BOTH RUNNING RO Check CC Pumps - BOTH RUNNING RO Check Containment and Containment Ventilation Isolation Check CI Active Status Panel light - ALL LIT Place control switches for LD-4A/B/C to Close RO Close LD-4A RO Check if MSIVs can remain OPEN

Check if any MSIV or bypass open

Check Containment Pressure has remained < 17 psig

Check MS Header HI-HI Steam Flow bistable lights - OFF

Check MS Header HI Steam Flow bistable lights - OFF KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS (CAS) RO Check Containment Spray NOT required

Containment Pressure has remained <

23 psig RO Check SW Alignment

All SW Pumps Running

Check SW Header pressures - both >

82.5 psig RO Check Containment Cooling

Check CFCUs - All Running

Ensure CFCU SW return Isolation Valves - ALL OPEN

Check Shroud Cooling Coil Bypass vavles - ALL OPEN

Check Containment Pressure has remained below 4 psig RO Verify Aux Building Special Ventilation

Check Annunciator Zone SV BNDRY Damper not Closed - Clear (47052-G)

Check Zone SV Fans - ALL RUNNING RO Check Si Active Status Panel Lights -

ALL LIT NOTE: Depending upon crew action and RO Check SI Flow speed RCS pressure may be lower than Check RCS Pressure < 2000 psig 2000 psig. This will not affect the flow of RNO the scenario.

Return to Procedure and Step in Effect KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS E-3, Steam Generator Tube Rupture (CAS) US/RO Check If RXCPs should remain running

RXCPs - Any Running

Subcooling > 15ºF [37ºF]

ROLE: SM ROLE: Radiation Protection CREW Identify Ruptured Steam Generator REQUEST: Contact Chemistry and RP for REQUEST: Support surveys as requested

Steam Generator B samples and Surveys RESPONSE: Acknowledge request.

RESPONSE: Acknowledge request. DELAY: None DELAY: None ROLE: Chemistry REQUEST: Sample SGs as requested RESPONSE: Acknowledge request DELAY: None KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS If feed flow was not isolated earlier it will be (CAS) US/BOP - Check if Feed Flow to isolated at this time - First part of Critical Ruptured Steam Generator should be Task. stopped CRITICAL TASK: Isolate Feed Flow into

Place B AFW pump to Pullout and Steam Flow from the Ruptured SG before a transition to ECA-3.1 occurs

Isolate Feed Flow to SG B (if not SAFETY SIGNIFICANCE: Failure to done previously) isolate the rupture SG causes a loss of o CLOSE AFW-2B, AFW Pump B differential pressure between the ruptured Flow Control Vlv SG and the intact SG. Upon a loss of differential pressure, the crew must o CLOSE AFW-10B, AFW Train B transition to a contingency procedure that Crossover Valve constitutes an incorrect performance that necessitates the crew taking compensating action which complicates the event mitigation strategy CUE: Increasing SG water Level, Abnormal Radiation indication in the ruptured SG MEASURABLE PERFORMANCE INDICATOR:

Auxiliary Feed flow isolated to SG B as indicated by 0 gpm on the B AFW header

0 gpm main feed flow

MS-100B Closed

MS-1B and MS-2B Closed PERFORMANCE FEEDBACK:

Indication of stable or increasing pressure in ruptured SG B

Indication of 0 feedwater flow to ruptured SG B WOG Critical Task E-3 -- A KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Isolate Steam Flow from the ruptured SG. US/BOP CLOSE Ruptured SG MSIV and MS-100B is already closed for maintenance Bypass Valves

- Completes the critical task

MS-1B, S/G B Main Steam Isolation CRITICAL TASK: Isolate Feed Flow into Valve (Depresses Main Steam and Steam Flow from the Ruptured SG Isolation Initiate Train B pushbutton) before a transition to ECA-3.1 occurs SAFETY SIGNIFICANCE: Failure to

MS-2B, isolate the rupture SG causes a loss of differential pressure between the ruptured SG and the intact SG. Upon a loss of differential pressure, the crew must transition to a contingency procedure that constitutes an incorrect performance that necessitates the crew taking compensating action which complicates the event mitigation strategy CUE: Increasing SG water Level, Abnormal Radiation indication in the ruptured SG MEASURABLE PERFORMANCE INDICATOR:

Auxiliary Feed flow isolated to SG B as indicated by 0 gpm on the B AFW header

0 gpm main feed flow

MS-100B Closed

MS-1B and MS-2B Closed PERFORMANCE FEEDBACK:

Indication of stable or increasing pressure in ruptured SG B

Indication of 0 feedwater flow to ruptured SG B WOG Critical Task E-3 -- A KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS These items be done and require no US/BOP Minimize steam dump from manipulation ruptured SG

SD-3B set to 1050 psig

Check SD-3B closed

Close supply to TDAFW, MS-100B ROLE: AO/EO US/BOP Isolate ruptured SG REQUEST: Close TD-1-9, TD 9

BT-2B/3B RESPONSE: Wait delay that report valves

TD-1-9 / TD-3-9 are closed DELAY: 7 minutes If the crew has failed to isolate feed flow US/BOP Check ruptured SG >400 psig into and steam flow from the ruptured SG by this time and the crew transitions to ECA-3.1 then the crew has failed to meet the critical task KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO Reset SI Selection of the correct CET is part of this US Determine Target Core Exit critical Task Thermocouple Temperature CRITICAL TASK Establish and maintain an RCS temperature so that transition from E-3 Ruptured SG Required CET does not occur because the RCS Pressure (PSIG) Temperature ºF Temperature is in either of the following Greater than 1200 534[515]

conditions: 1199 to 1150 539[509]

Too high to maintain minimum required 1149 to 1100 534[504]

subcooling OR 1099 to 1050 528[498]

Below the RCS temperature that causes 1049 to 1000 522[491]

a red path or orange path challenge to the sub criticality and/or integrity CSF 999 to 950 516[485]

status trees 949 to 900 509[478]

SAFETY SIGNIFICANCE: Failure to 899 to 850 503[471]

establish and maintain the correct RCS temperature during a SGTR leads to a 849 to 800 496[464]

transition from E-3 to a contingency 799 to 750 488[456]

procedure which constitutes an incorrect 749 to 700 481[448]

performance that necessitates the crew 699 to 650 472[439]

taking compensating actions which complicates the event mitigation strategy 649 to 600 464[430]

CUE: SGTR and Ruptured SG level rising 599 to 550 454[420]

MEASURABLE PERFORMANCE 549 to 500 444[409]

INDICATOR: Select the correct CET temperature to permit stopping of SI pumps 499 to 450 434[397]

and maintaining the CET temperature to 449 to 400 422[385]

prevent reinitiating of SI and Transition to ECA-3.1 per the foldout page of E-3 PERFORMANCE FEEDBACK: Sufficient Subcooling to Stop SI pumps and maintain the SI pumps stopped WOG Critical Task E-3--B KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS The critical task to start AFW Pump A must US/BOP Maintain All Running AFW pump be accomplished by this time to support the Discharge pressures greater than 1000 psig cooldown and depressurization of the RCS

Throttle AFW-2A US/BOP Cooldown the RCS to Target CET Temperature Dump Steam from SG A If MS-1A OPEN

Position Main Steam Dump Mode Selector to Reset Then Stem pressure

Dump Steam using HC-484 at Max Rate

At 540ºF Place both Main Steam Dump Interlock Selector switches to BYPASS INTLK If MS-1A CLOSED

Dump Steam at Max Rate using SD-3A Check CET < Target Temperature RNO Continue Cooldown until CETs < target Temperature while continuing with procedure (CAS) US/BOP Maintain Intact SG Level

Check intact SG narrow range level

>5% [13%]

Control Feed Flow to maintain intact SG narrow range level 22% to 50%

KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS (CAS) US/RO Check Pressurizer PORVs and Block Valves Available

Power Available to PRZR Block Valves

PRZR PORVs Both Closed

Check at least one PRZR Block Valve OPEN US/RO Reset SI US/RO Reset Containment Isolation US/BOP/RO Check Instrument Air Established to containment

IA-101 OPEN

Check reactor building header pressure

> 60 psig (CAS) US/RO Check if RHR pumps should be stopped

Check if RCS pressure > 270 psig[300 psig]

Check RHR pumps not supplying containment Sump Recirculation

Stop both RHR pumps and place in AUTO KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/RO Establish charging pumps -At Least One Running Check charging pumps - At Least One Running RNO Perform the following

CC Flow maintained to thermal barrier

Ensure Charging Pump Load within the capacity of power source

Start at least one charging pump Align Charging pump suction to the RWST

OPEN CVC-301

CLOSE CVC-1 Increase charging pump speed and start second charging pump as necessary to establish maximum charging flow Maintain CET Temperature < Target CREW check if RCS Cooldown should be Temperature is part of the critical task to stopped prevent unnecessary reinitiating of SI and

Check CET < Target Temperature transition to ECA-3.1

Stop RCS Cooldown

Maintain CET < Target Temperature US/BOP Check Ruptured SG pressure Stable or increasing If the crew has not maintained target CET CREW Check RCS subcooling based on temperature this will not be met and a CETs greater than 35ºF [80ºF]

transition to ECA-3.1 will be required KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/RO Depressurize RCS Using Normal Spray:

Check normal Spray available Spray PRZR with Max Spray to achieve desired rate of depressurization until any of the following conditions are satisfied

PRZR LEVEL >77% [73%]

RCS Subcooling < 15ºF [60ºF]

RCS pressure less than ruptured SG pressure AND PRZR Level >3% [15%]

Close Normal Spray Valves CRITICAL TASK Stop Break Flow before CREW Check if SI flow can be terminated:

SG overfill

Check RCS subcooling based on CETs SAFETY SIGNIFICANCE: Failure to stop > 15ºF [60ºF]

break flow before SG overfill could result in

Check RCS pressure stable or unnecessary release of radioactivity to the increasing public and thus endangering the health and

Check PRZR Level > 3% [15%]

safety of the public

Check Secondary Heat Sink CUE: SGTR and Ruptured SG level rising

Total feed flow > 210 gpm available OR Narrow range level in intact SG > 5%

MEASURABLE PERFORMANCE

[13%]

INDICATOR: Both SI pumps stopped and placed in AUTO while maintain CET

Stop SI pumps and place in AUTO temperatures to prevent reinitiating SI and Transition to ECA-3.1 PERFORMANCE FEEDBACK: SI pumps and in AUTO with subcooling > 15ºF WOG Critical Task E-3C,D KPS-SEG1-L-RO/SRO- A-01242011-112

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

6. SCENARIO END: a. FREEZE simulator at direction of floor instructor.

b. STOP Data Capture via SmartTest (optional)

7. POST-SCENARIO:

a. ENSURE simulator problems encountered during the scenario are documented IAW site specific process.

b. ENSURE training attendance is documented on, Training Attendance Report.

c. SOLICIT/COLLECT trainee feedback KPS-SEG1-L-RO/SRO- A-01242011-112

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INPUT

SUMMARY

Delay Ramp Event Severity Final Relative Description Time Time Trigger Or Value Value Order MALFUNCTIONS FW16A Failure to Auto Start AFW Pump 1A 00:00:00 00:00:00 None TRUE TRUE Preload RX201C PT-431 PRZ PRESS 00:00:00 00:00:30 1 0 2500 1 RX02B Steam Generator Level Controller Unstable (FW-7B) 00:00:00 00:15:00 15 0 75 8 NI05A Improper Power Range Channel Response (N41) 00:00:00 00:00:00 17 0 1.2 9 SG01B Steam Generator Tube Leak Inlet Tubesheet Hi-Vol 00:00:00 00:05:00 23 0 9 10 REMOTE FUNCTIONS RM101 R-21 Alignment 00:00:00 00:00:00 None Cntmt Cntmt setup RP141 407C-OverTemperature Trip 00:00:00 00:00:00 3 norm trip 2 RP142 407D-Rod Stop Norm 00:00:00 00:00:00 5 norm trip 3 RP164 431A-High Pressure Trip 00:00:00 00:00:00 7 norm trip 4 RP167 431J-Low Pressure Trip 00:00:00 00:00:00 9 norm trip 5 RP166 431I-Unblock SI Norm 00:00:00 00:00:00 11 norm trip 6 RP165 431G-SI Norm 00:00:00 00:00:00 13 norm trip 7 RP133 405C-Over Temperature Trip 00:00:00 00:00:00 19 norm trip cond RP134 405D-Rod Stop Norm 00:00:00 00:00:00 21 norm trip cond OVERRIDES KPS-SEG1-L-RO/SRO- A-01242011-112

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INPUT

SUMMARY

Delay Ramp Event Severity Final Relative Description Time Time Trigger Or Value Value Order MCC DI-46331-OPEN CC-610A 00:00:00 00:00:00 28 norm norm cond MCC DI-46332-OPEN CC-610B 00:00:00 00:00:00 28 norm norm cond MCA DO-46113-G MS-100A 00:00:00 00:00:00 None OFF OFF Preload MCA DO-46114-G MS-100B 00:00:00 00:00:00 None OFF OFF Preload Blind Triggers Event #25 Event Action: hwzfww1084==1.0 Command: dor di-46331-open Deletes override when FW-7A closed Event #27 Event Action: hwzfww1084==1.0 Command: dor di-46332-open Deletes override when FW-7A closed Event #28 Event Action: an:47021a==1.0 Command:

Activate trigger 28 when SI Train A activates Event #30 Event Action: hwzrpg5622==1.0 Command: imf SG01B 10 Inserts SG01B at 10 when the reactor trips KPS-SEG1-L-RO/SRO- A-01242011-112

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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 an explanation after the item.

Yes No

1. The scenario contains objectives for the desired tasks and relevant Human Performance Tools.

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

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

4. Turnover information includes a Daily At Power Risk Assessment provided by the PRA Group. (PRA Validated with crew during validation)

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

6. The Scenario Guide includes responses for all communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices.

7. The scenario includes related industry experience. (Not Required for Evaluations)

8. 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.

9. Any identified Critical Tasks possesses the following elements (NUREG-1021):

Essential to safety with adverse consequences or significant degradation,

Cue(s) prompt the Operator to respond.

Defined and measurable performance indicators.

Performance feedback.

The use of N/A is allowed for item 9 only if this is NOT an evaluated scenario.

10. Technical Specifications including Limiting Conditions for Operation, reactivity briefings, and Emergency-Plan entries are addressed as appropriate.

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

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SIMULATOR EXERCISE 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.

Yes No

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

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

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

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

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

6. Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence?

7. 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.

8. Any identified Critical Tasks possesses the following elements (NUREG-1021):

Essential to safety with adverse consequences or significant degradation,

Cue(s) prompt the Operator to respond.

Defined and measurable performance indicators.

Performance feedback.

The use of N/A is allowed for item 8 only if this is NOT an evaluated scenario.

Discrepancies noted (Check none or list items in comments field) None Comments: None Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

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Applied & Implemented All Information Passed on to All Any Knowledge or Performance Corrective Actions if TS/TRM (PP-1) Identified All Applicable Correctly Crew Members (i.e., briefs) Deficiencies Required As Time Allowed 3.3.1 Yes No Yes No Yes No 3.3.2 Yes No Yes No Yes No LCO 3.03 Yes No Yes No Yes No EALs All Information Passed on to All Any Knowledge or Performance Corrective Actions if Identified All Applicable Classified & Notified Timely (EP Group) Crew Members (i.e., briefs) Deficiencies Required Alert Yes No Yes No Yes No Any Knowledge or Performance Corrective Actions if Procedure Compliance (PP-3) Applied & Implemented Correctly As Time Allowed Deficiencies Required GOP-307 Yes No NOP-TB-001 Yes No NOP-CVC-001 Yes No AOP-GEN-001 Yes No AOP-MISC-001 Yes No AOP-RC-004 Yes No E-0 Yes No E-3 Yes No KPS-SEG1-L-RO/SRO- A-01242011-112

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Any Knowledge or Performance Corrective Actions if Human Performance Errors (PP-2) Identify All HU Errors or Potential HU Errors Deficiencies Required Questioning Attitude Stop When Unsure Self Checking Procedure Use and Adherence Clear Communications Place Keeping Verification Practices Identify All Operator Fundamental Errors Or Potential Operator Fundamental Any Knowledge or Performance Corrective Actions if Operator Fundamentals Errors Deficiencies Required Teamwork Effectiveness (T)

High Standards for Controlling Plant Evolutions (H)

Indications and Plant Parameters Monitored Closely (I)

Natural Bias for Conservative Approach to Plant Operations (N)

Knowledge of Plant Design and Theory (K)

KPS-SEG1-L-RO/SRO- A-01242011-112

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SITE: Kewaunee Power Station PROGRAM: RO/SRO License Training PROGRAM No. ROl/SRO TP COURSE: 2011 NRC License Exam Course #: ROI-06-SE-SC2 SOI-06-SE-SC2 Total Time 2 Hours Prepared by: Andrew Fahrenkrug /s 01/24/2011 Printed Name Instructors Signature Date Reviewed by: Jeffrey A. Hinze /s 01/24/2011 (Optional) Printed Name Simulator Development Checklist Date Instructor Signature Reviewed by: Andrew Fahrenkrug /s 01/19/2011 (Optional) Printed Name Simulator Validation Checklist Date Signature Approved by: Randy Hastings /s 01/24/2011 Printed Name Training Supervisor Date Approved by: Mark Goolsbey /s 01/25/2011 Printed Name Facility Representative Date KPS-SEG2-L-RO/SRO-A-01242011-113

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Appendix D Scenario Outline Form ES-D-1 Facility: Kewaunee Power Station Scenario No.: 2 Op-Test No.: 1 Examiners: Operators: SRO: .

ATC: .

BOP: .

Initial Conditions: IC-17: 51% power EOL Equilibrium Xenon. RCS boron concentration is 256 ppm. RCS Tave is 558ºF. Generator load is 282 MWe gross. AS-31/AS-35 R-11 & R-12 Sample Return Aligned to Containment, PR-1A PRZR PORV Block Valve is closed with power maintained due to PR-2A seat leakage, 2 inch containment vent is in progress per NOP-RBV-002 section 5.6, N41 is OOS (failed low previous shift) Power increase is to be initiated to 56% power. Main Feedwater Pump A start is in progress.

Turnover: Power initially lowered due to problems associated with Main Feed Pump 1A.

Problems have been corrected and the pump is ready for retest. Plant Management has directed starting Main Feed Pump 1A and raising power to 56%

at 1/2% per minute. Then hold at 56% for testing of Main Feed Pump 1A.

OP-KW-GOP-106 has been completed up-to and including 5.1.12.

NOP-FW-001 has been completed up-to and including step 5.1.5

Reactor Engineering has provided a reactivity plan and the plan has been reviewed and approved.

TS 3.4.11 (Reactor Coolant System Pressurizer Power Operated Relief Valves)

Condition A One or more PORVs inoperable and capable of being manually cycled.

Required Action A.1 is to close and maintain power to the associated PORV with a completion time of one hour (Completed).

TS 3.3.1(Reactor Protection System (RPS) Instrumentation) Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.1-1 for the channel(s) or train(s) with a completion time of immediately.

TS 3.3.1 Reactor Protection System (RPS) Instrumentation) Condition D one channel inoperable with Required Action D.2.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND Required Action D.2.2 perform SR 3.2.4.2 with a completion time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Table 3.3.1-1 Item 2.a PR Neutron Flux High - Channel in Trip and SR 3.2.4.2 performed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months before start of the scenario TS 3.3.1 Reactor Protection System (RPS) Instrumentation) Condition E one channel inoperable with Required Action E.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . - Channel in Trip KPS-SEG2-L-RO/SRO-A-01242011-113

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Event Malf. Event Event No. No. Type* Description Pre- PR-2A CAUTION tagged CLOSED due to seat leakage. PR-Load 1A closed TS LCO3.4.11, ACTION A.1.

NI05A -

1.2 RF:

Pre- N41 Power Range NI Red Channel is OOS failed low. OTT RP133 - N/A Load Trip Trip bistable and Rod Stop bistable are tripped.

RP134 -

Trip DI-46355-CLOSE ON DI-46355-Pre- OPEN OFF Containment Sump B Supply to RHR Pumps, SI-350A and ATC - C Load DI-46356-CLOSE ON SI-350B, fail to open DI-46356-OPEN OFF Turbine load is increased and Main Feedwater Pump B is ATC - R 1 N/A started prior to exceeding 285 psig impulse pressure (56%

BOP - N turbine power)

SG A red pressure channel (PT-468) fails high to 1400 psig RX213 - over 30 seconds resulting in increase in indicated steam flow 2 BOP - C 1400 0:30 to SG A, increase in feed flow to SG A and opening of SG A PORV, SD-3A RC08 - An unisolable RCS leak to containment atmosphere of 3 ATC - C 1.4 5:00 approximately 20 gpm develops over a 5-minute period.

ATC, RC03A - BOP -

4 10%, 0:30 M RCS leak propagates into a large-break LOCA.

DI-46355-CLOSE ON DI-46355-SI-350A and SI-350B, CNTMT Sump B Supply To RHR OPEN OFF Pump A/B, fail to open in ES-1.3, Transfer To Containment 5 ATC - C DI-46356-CLOSE ON Sump Recirculation, requiring transition to ECA-1.1, Loss of DI-46356- Emergency Coolant Recirculation OPEN OFF

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO 1-2 OVERVIEW EVENT DESCRIPTION Feedwater Pump A start and Power increase.

Crew is directed during turnover to start MFP 1A and perform a power increase to approximately 56% RTP at 1/2 %/min. The crew should start MFP 1A per NOP-FW-001.

1 After starting MFP 1A the crew should commence the power increase using OP-KW-GOP-106.

The ATC operator will dilute in accordance with the Reactivity Plan using NOP-CVC-001, and the BOP operator will raise turbine load using NOP-TB-001.

After the power increase, SG A red channel pressure, PT-468, fails high to 1400 psig over 30 seconds. This will result in indicated SG A steam flow reading higher than actual flow, and cause FW-7 A to throttle open to increase feed flow in response to the increased steam flow. Additionally, SD-3A, SG A PORV will open in response to the overpressure condition sensed by its controller.

The BOP operator will respond according to AOP-GEN-001, Immediate Operator Actions, Attachment D for a SG PORV Failure, and/or the appropriate Alarm Response Procedures. Once SD-3A is noted to be open with SG A pressure less than 1005 psig, the BOP operator will manually close SD-3A by taking its controller to the MANUAL position and ensuring the control potentiometer is rotated fully clockwise to 0% demand.

The operator should also take action to place FW-7A, Feed Reg Valve, in MAN, to control SG level at 44% (AOP-GEN-001, Attachment A).

The failed pressure instrument will be identified and removed from service using AOP-MISC-001, Response to Instrument Failure, Attachment D Steam Generator Pressure.

The alternate steam flow channel (FT-465 White) will be selected. When SG A level is stabilized FW-7A controller will be restored to Automatic.

Technical Specifications:

2

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition A One or more Functions with one or more required channels or trains inoperable.

Required Action A.1 enter the condition referenced in Table 3.3.1-1 for the channel(s) or train(s) with a completion time of immediately.

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition E one channel inoperable with Required Action E.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.1-1 Item 15. SG Water Level - Low coincident with Steam Flow/Feedwater Flow Mismatch.

TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.2-1 for the channel(s) or train(s) with a completion time of immediately.

TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation Condition D one channel inoperable with Required Action D.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.2-1 Item 1.e Safety Injection -

Steam Line Pressure - Low

TS 3.3.3 Post Accident Monitoring Instrumentation all functions are met The Unit supervisor will direct tripping of bistables. It is NOT expected to trip bistables for the failed channel(s) during the scenario KPS-SEG2-L-RO/SRO-A-01242011-113

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After the failed SG pressure channel is addressed, a small non-isolable leak will develop in containment. The leak will reach a maximum value of approximately 20 gpm over a 2-minute period. Containment radiation monitors will indicate a marked increase in radiation levels inside containment, containment pressure and humidity level will rise, Fireworks RXCP vault detection will alarm with rising temperatures in containment.

Charging Pump A in auto will increase speed to attempt to maintain PRZR level on program The crew will respond by entering AOP-RC-001, Reactor Coolant Leak. With PRZR level lowering the crew is expected to isolate letdown and establish charging flow to maintain PRZR level on program. The crew will then attempt to diagnose and isolate the leak. The 3

crew should determine the leak is in containment based on containment conditions. The Unit Supervisor should inform the Shift Manager (or crew member) to contact RP and set up for a containment entry to determine leak location. The Unit Supervisor will direct determining the leak rate, and based upon the value, determine that if the condition continues a unit shutdown would be required.

Technical Specifications:

TS 3.4.13 RCS Operational Leakage Condition A RCS operational LEAKAGE not within limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE with Required Action A.1 to reduce leakage to within limits with a completion time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

After Technical Specifications for the RCS leak have been addressed the RCS leak will develop into a large break LOCA. RCS pressure and PRZR level will rapidly decrease.

The crew is expected to recognize the need for a reactor trip and initiate Safety Injection on PRZR pressure and/or PRZR level (cannot be maintain > 3%). The reactor will trip and Safety Injection will actuate.

The crew will perform immediate actions of E-0:

1. Verify reactor trip

2. Verify turbine rip

3. Verify Bus 5 OR Bus 6 (ESF Bus) energized

4. Check SI actuated.

It is expected that SI will have been actuated, or will be required, by this time.

The US will provide and brief. The US should address the FOLD OUT Page Criteria 4 stopping RXCPs. The ATC operator will perform Attachment A steps while the US directs the BOP operator performing E-0 actions.

The crew will continue the actions of E-0 to ensure Safeguards equipment is operating as required. Diagnosis will be made of a LOCA and transition will be made to E-1, Loss of Reactor Or Secondary Coolant. A RED Path is expected to exist in the Integrity CSF Status Tree. If so, entry is made into FR-P.1. When performing step 1, RCS pressure is less than 300 psig and RHR injection flow (FI-626 or FI-928) is above 700 gpm, so transition will then be made to E-1.

The crew will continue action of E-1 and monitor RWST level. When RWST level is <

37%, as indicated by annunciator 47023-B, RWST LEVEL LOW, the crew will transition to ES-1.3, Transfer To Containment Sump Recirculation.

KPS-SEG2-L-RO/SRO-A- 01242011-113

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The crew will identify Train A ECCS flow, and stop Train B and unnecessary equipment.

The crew will attempt to open both Containment Sump B to RHR Pump Suction valves SI-350A and SI-350B at step 7 of ES-1.3. Neither valve will operate resulting in transition to ECA-1.1, Loss of Emergency Coolant Recirculation.

In ECA-1.1, the BOP operator will check Containment Cooling with four Fan Coil Units in operation. The crew will determine the required number of Containment Spray Pumps required operating, stop the ICS Pumps to conserve RWST inventory. The ATC operator 5 will be directed to initiate refill of the RWST using NOP-CVC-001. The BOP operator will continue with actions of ECA-1.1 by maintaining SG levels, initiating cooldown, if necessary, and monitoring EECS Pump operation.

Actions will continue until it is determined that SI flow CANNOT be terminated (Step 17),

the minimum required injection flow is determined, RHR Pumps stopped, and direction provided to adjust SI-7B locally to achieve the determined minimum flow. [THIS IS A CRITICAL TASK]

The scenario may be terminated minimum injection flow has been determined.

KPS-SEG2-L-RO/SRO-A- 01242011-113

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REQUIREMENTS Goal of Training: Evaluate the crews response to the following events:

Turbine Load increase

Start a Main Feed Pump

Reactivity manipulations

Failure of SG A pressure channel (PT-468 Red Channel) High

Unisolable RCS Leak in containment to atmosphere

Large Break LOCA

Contingency on failure to establish containment sump recirculation Learning Objectives: While responding as the RO/BOP satisfactorily MEET the performance requirements in TR-AA-400 for the following competencies

a. Understand and Interpret Annunciator and Alarm Signals

b. Diagnose Events and Conditions based on Signals and Reading

c. Understand Plant and System Response

d. Comply with and Use Procedures and Technical Specifications

e. Operate the Control Board

f. Communicate and Interact with Other Crew Members (RO4-06-SED01.002) ROI-06-SE-SC02.001 / SOI-06-SE-SC02.001 While responding as the US satisfactorily MEET the performance requirements in TR-AA-400 for the following competencies

a. Understand and Interpret Annunciator and Alarm Signals

b. Diagnose Events and Conditions based on Signals and Reading

c. Understand Plant and System Response

d. Comply with and Use Procedures and Technical Specifications

e. Operate the Control Board

f. Communicate and Interact with Other Crew Members

g. Direct Shift Operations

h. Comply with and Use Technical Specifications (RO4-06-SED01.003) SOI-06-SE-SC02.002 As the US DETERMINE the appropriate event classification in accordance with EPIP-AD-02,Emegency Classification Determination. (This objective will be completed at the end of the scenario and may be waived at the lead evaluators discretion.) SOI-06-SE-SC02.003 Prerequisites: Enrolled in current ILT class and recommended by station management to take an NRC license exam.

KPS-SEG2-L-RO/SRO-A-01242011-113

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Training Resources: Simulator KPS Exam Team Member NRC Examiners KPS-SEG2-L-RO/SRO-A- 01242011-113

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References:

KPS Technical Specifications (ITS)

KPS Technical Requirements Manual (TRM)

OP-AA-100 Conduct of Operations OP-AP-104 Emergency and Abnormal Operating Procedures OP-AP-300 Reactivity Management OP-KW-GOP-106 Startup From 35% Power to Full Power NOP-RBV-002 Reactor Building Vent System Cold Operations and Making Releases NOP-TB-001 Turbine and Generator Operation NOP-FW-001 Normal Feedwater System Operation NOP-CD-001 Condensate System NOP-RCS-001 Reactor Coolant Pump Operation NOP-RCS-003 Pressurizer Pressure Control NOP-HD-001 Heater and Moisture Separator Drain and Bleeder Steam System NOP-CVC-001, Boron Concentration Control SP-32-113 Gaseous Radioactive Effluents Reports for Continuous Releases OSP-RCS-001 Reactor Coolant System Leak Rate Check AOP-GEN-001 Immediate Operator Actions AOP-MISC-001 Response to Instrument Failure AOP-MDS-002 Post Accident Leakage Control System AOP-GEN-001 Immediate Operator Actions AOP-MISC-001 Response to Instrument Failure AOP-RM-001 Abnormal Radiation Monitoring AOP-RC-001 Reactor Coolant Leak ARP 47011-B Radiation Indication High ARP-47012-B Radiation Indication Alert ARP-47023-A RWST Level Low-Low ARP-47023-B RWST Level Low ARP-47031-P Containment Sump A Level Hi-Hi ARP-47031-Q Containment Sump A Level High ARP-47032-Q RHR Pump Pit A/B Level High ARP-47033-R Aux BLDG Flood Level High ARP-47033-35 TLA-15 RMS Above Normal ARP-47043-C Pressurizer Control Press Abnormal ARP-47043-D PRZR Pressure Low ARP-47043-E Pressurizer Level Deviation ARP-47043-F PRZR Level Low ARP-47061-A Feedwater Pump A Trip ARP-47061-C S/G A Feed Flow Excessive ARP-47061-G FWP A/B Suction Press Low ARP-47063-C Feedwater Pump A Abnormal ARP-47064-C Feedwater Pump A Vibration ARP-47065-C FWP Sea; Water DP High E-0 Reactor Trip or Safety Injection E-1 Loss of Reactor or Secondary Coolant ES-1.3 Transfer to Containment Sump Recirculation ECA-1.1 Loss of Emergency Coolant Recirculation KPS-SEG2-L-RO/SRO-A- 01242011-113

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Commitments: Per Outline submitted to NRC for 2011 Operating exam Evaluation Method: Dynamic Simulator Historical Record: Initial Issue Rev B Update Critical Task 3 Operating Experience: Not required for evaluations Related PRA Initiating Event with Core Damage Frequency:

Information: Total CDF/LERF (3.6E-5/yr)/(1.6E-06/yr)

Transient with MFW Available CDF/LERF 10%/2.8%

Important Components:

System CDF Importance Rank LERF Importance Rank SI 8th 3rd Important Operator Actions CDF - Limit SI and refill RWST if sump recirculation unavailable LERF - Limit SI and refill RWST if sump recirculation unavailable KPS-SEG2-L-RO/SRO-A- 01242011-113

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OVERVIEW INITIAL CONDITIONS:

1. Standard IC-17 51% power EOL.

2. 2 inch containment Vent is in progress per NOP-RBV-002 section 5.6.

3. The following equipment is OOS:

a. PR-2A seat leakage. PR-1A is closed with power maintained.

b. N41 has failed low. Corrective Maintenance is in progress. All actions have been completed per AOP-Gen-001 and AOP-Misc-001.

4. R-11/12 Sample Return is aligned to the containment.

SEQUENCE OF EVENTS:

Event 1: Raise Power to 56% and start MFP A Crew is directed during turnover to start MFP 1A and perform a power increase to approximately 56% RTP at 1/2 %/min. The crew should start MFP 1A per NOP-FW-001. After starting MFP 1A the crew should commence the power increase using OP-KW-GOP-106.

The ATC operator will dilute in accordance with the Reactivity Plan using NOP-CVC-001, and the BOP operator will raise turbine load using NOP-TB-001.

Event 2: After the power increase, SG A red channel pressure, PT-468, fails high to 1400 psig over 30 seconds This will result in indicated SG A steam flow reading higher than actual flow, and cause FW-7 A to throttle open to increase feed flow in response to the increased steam flow. Additionally, SD-3A, SG A PORV will open in response to the overpressure condition sensed by its controller.

The BOP operator will respond according to AOP-GEN-001, Immediate Operator Actions, Attachment D for a SG PORV Failure, and/or the appropriate Alarm Response Procedures. Once SD-3A is noted to be open with SG A pressure less than 1005 psig, the BOP operator will manually close SD-3A by taking its controller to the MANUAL position and ensuring the control potentiometer is rotated fully clockwise to 0%

demand.

The operator should also take action to place FW-7A, Feed Reg Valve, in MAN, to control SG level at 30%

to 46% (AOP-GEN-001, Attachment B).

The failed pressure instrument will be identified and removed from service using AOP-MISC-001, Response to Instrument Failure, Attachment D Steam Generator Pressure. The alternate steam flow channel (FT-465 White) will be selected. When SG A level is stabilized FW-7A controller will be restored to Automatic.

Technical Specifications:

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.1-1 for the channel(s) or train(s) with a completion time of immediately.

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation) Condition E one channel inoperable KPS-SEG2-L-RO/SRO-A- 01242011-113

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with Required Action E.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.1-1 Item 15. SG Water Level - Low coincident with Steam Flow/Feedwater Flow Mismatch.

TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.2-1 for the channel(s) or train(s) with a completion time of immediately.

TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation Condition D one channel inoperable with Required Action D.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.2-1 Item 1.e Safety Injection - Steam Line Pressure - Low

TS 3.3.3 Post Accident Monitoring Instrumentation all functions are met The Unit supervisor will direct tripping of bistables. It is expected to trip bistables for the failed channel(s) during the scenario Event 3: After the failed SG pressure channel is addressed, a small non-isolable RCS leak will develop in containment.

The leak will reach a maximum value of approximately 20 gpm over a 2-minute period. Containment radiation monitors will indicate a marked increase in radiation levels inside containment, containment pressure and humidity level will rise, Fireworks RXCP vault detection will alarm with rising temperatures in containment. Charging Pump A in auto will increase speed to attempt to maintain PRZR level on program The crew will respond by entering AOP-RC-001, Reactor Coolant Leak. With PRZR level lowering the crew is expected to isolate letdown and establish charging flow to maintain PRZR level on program. The crew will then attempt to diagnose and isolate the leak. The crew should determine the leak is in containment based on containment conditions. The Unit Supervisor should inform the Shift Manager (or crew member) to contact RP and set up for a containment entry to determine leak location. The Unit Supervisor will direct determining the leak rate, and based upon the value, determine that if the condition continues a unit shutdown would be required.

Technical Specifications:

TS 3.4.13 RCS Operational Leakage Condition A RCS operational LEAKAGE not within limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE with Required Action A.1 to reduce leakage to within limits with a completion time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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Event 4 After Technical Specifications for the RCS leak have been addressed the RCS leak will develop into a large break LOCA.

RCS pressure and PRZR level will rapidly decrease. The crew is expected to recognize the need for a reactor trip and initiate Safety Injection on PRZR pressure and/or PRZR level (cannot be maintain > 3%).

The reactor will trip and Safety Injection will actuate. The Containment Fan Coils Units will trip on overcurrent during the SI sequence. There is no operator action that will correct this. Tripping of Containment Fan Coil Units is done in the scenario to maintain containment pressure elevated to maintain ICS flow.

The crew will perform immediate actions of E-0:

5. Verify reactor trip

6. Verify turbine trip

7. Verify Bus 5 OR Bus 6 (ESF Bus) energized

8. Check SI actuated.

It is expected that SI will have been actuated, or will be required, by this time.

The US will hold a brief. The US should address the FOLD OUT Page Criteria stopping RXCPs. The ATC operator will perform Attachment A steps while the US directs the BOP operator performing E-0 actions.

The crew will continue the actions of E-0 to ensure Safeguards equipment is operating as required.

Diagnosis will be made of a LOCA and transition will be made to E-1, Loss of Reactor Or Secondary Coolant. A RED Path is expected to exist in the Integrity CSF Status Tree. If so, entry is made into FR-P.1.

When performing step 1, RCS pressure is less than 300 psig and RHR injection flow (FI-626 or FI-928) is above 700 gpm, so transition will then be made to E-1.

The crew will continue action of E-1 and monitor RWST level. When RWST level is < 37%, as indicated by annunciator 47023-B, RWST LEVEL LOW, the crew will transition to ES-1.3, Transfer To Containment Sump Recirculation.

Event 5 Failure of CVC-211 and CVC-212 to CLOSE During the performance of E-0 Attachment A by the ATC, while ensuring containment isolation will identify that CVC-211 and CVC-212 did not close. All attempted actions to close CVC-211 will fail. CVC-212 will be able to be closed from the Control Room using CVC-212 control switch on MCB.

Per Attachment A the ATC operator will manually actuate containment isolation, action will fail to close CVC-211 and CVC-212. After the failure of manual initiation of containment isolation the ATC operator will then refer to Attachment B to determine how to isolate the flow path. Options for the ATC operator are: (1)

Ensure associated in isolation closed, CVC-211 is the in line isolation for CVC-212 and CVC-212 is the inline isolation for CVC-211, (2) Manually or locally close valves, CVC-211 is inside of containment and cannot be readily accessed and if the ATC operator directs the NAO to locally close CVC-212, CVC-211 inside of containment, the NAO will report the radiation levels are too high and RP will not let them enter the area. Expected the operator to close CVC-212 using the control switch on MCB. Control switch on MCB for CVC-211 will fail to work, (3) Locally close manual inline isolation, see explanation for (1) and (2).

Isolation of Containment is a Critical Task Event 6 Failure of SI-350A and SI-350B to OPEN The crew will identify Train A ECCS flow, and stop Train B and unnecessary equipment.

The crew will attempt to open both Containment Sump B to RHR Pump Suction valves SI-350A and SI-350B at step 7 of ES-1.3. Neither valve will operate resulting in transition to ECA-1.1, Loss of Emergency Coolant Recirculation.

In ECA-1.1, the BOP operator will check Containment Cooling with four Fan Coil Units in operation. The crew will determine the required number of Containment Spray Pumps required operating, stop the ICS Pumps to conserve RWST inventory. The ATC operator will be directed to initiate refill of the RWST using KPS-SEG2-L-RO/SRO-A- 01242011-113

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NOP-CVC-001. The BOP operator will continue with actions of ECA-1.1 by maintaining SG levels, initiating cooldown, if necessary, and monitoring EECS Pump operation.

Actions will continue until it is determined that SI flow CANNOT be terminated (Step 17), the minimum required injection flow is determined, RHR Pumps stopped, and direction provided to adjust SI-7B locally to achieve the determined minimum flow. [THIS IS A CRITICAL TASK]

The scenario may be terminated minimum injection flow has been determined.

Malfunctions:

Before EOP Entry:

1. PT-468 SG A pressure Transmitter Fails High

2. Unisolable RCS Leak After EOP Entry:

1. SI-350A and SI-350B fail to OPEN

2. CVC-211 & CVC-212 fail to CLOSE Abnormal Events:

1. SG Pressure Transmitter Fails High

2. RCS Leak Major Transients:

1. Large Break LOCA Critical Tasks CRITICAL TASK: STOP RXCPs a) SAFETY SIGNIFICANCE:

i) The purpose of tripping the RXCPs during LB LOCA accident conditions is to prevent pump damage and ensure RXCPs are available if needed for future recovery actions.

b) CUE:

i) RXCPs running during LB LOCA and Subcooling less than 15°F [37°F] with at least one SI pump running and capable of delivering flow, and no operator controlled cooldown in progress.

c) MEASURABLE PERFORMANCE INDICATOR:

i) Crew Stops RXCPs before transitioning from E-0 per foldout page of E-0 or AOP-RC-005.

d) PERFORMANCE FEEDBACK:

i) RXCPs stopped.

CRITICAL TASK: Isolate Containment by closing CVC-212 a) SAFETY SIGNIFICANCE:

i) Failure of automatic containment isolation resulting in the rise in radiation levels and exposure of personnel to radiation unnecessarily.

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ii) Failure of the operator to realize the failure of containment isolation and take appropriate actions demonstrates the inability of the operator to safely and effectively operate the plant during emergency situations.

b) CUE:

i) Valid Containment Isolation signal and containment isolation valves CVC-211 and CVC-212 open c) MEASURABLE PERFORMANCE INDICATOR:

i) Close CVC-212 prior to the transition from E-0 d) PERFORMANCE FEEDBACK:

i) CVC-212 green light Lit indicates valve close and Containment Isolation Status panel indicates CVC-212 closed CRITICAL TASK: Maintaining RWST >4% during the scenario a) SAFETY SIGNIFICANCE:

i) Throttling of SI-7A minimizes flow from the RWST and prolongs core cooling. The scenario is designed so that by reducing outflow from the RWST by stopping ICS pumps or one train of SI, and making up to the RWST will prevent the RWST level from lowering to < 4% prior to throttling SI-7A and prolong core cooling and minimizing core damage. The acts of minimizing outflow from the RWST and establishing makeup to the RWST are part of a critical task to maximize length of time the RWST volume is available for core cooling.

b) CUE:

i) Loss of containment sump recirculation as indicated by SI-350A and SI-350B not opening.

c) MEASURABLE PERFORMANCE INDICATOR:

i) RWST maintained > 4% during the scenario with the scenario end point being throttling SI-7A d) PERFORMANCE FEEDBACK:

i) Response from NAO that to acknowledge throttling SI-7A.

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TASKS Task Number Task Title SRO Tasks:

1190190302 Apply Technical Specifications During Plant Operations 1190070502 Coordinate the Implementation of the IPEOPs Demonstrate an understanding of the responsibility and requirements for the Control 1190330302 Room Supervisor RO Tasks:

0540060101 Change Turbine and Generator Load 0350240101 Control RCS Boron Concentration by the use of Boration 0060000001 Operate the Steam Generator and Steam Generator Water Level Control System and its components during any mode of operation 03600030401 Respond to an unidentified RCS leak E010050501 Respond to a loss of Emergency Coolant Recirculation STA Tasks: N/A KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

1. INITIAL CONDITIONS:

Special Standard IC17

Mode: 1

Exposure: 17000

Power: 51%

Boron: (CB): 222 ppm

Temperature: 558

Pressure: 2235

Xenon: equil

Rods: D 125

Generator: 283 Mwe

Thermal Output 907.4

2. SIMULATOR SETUP:

RESET to IC# 17 and go to run The following forms are needed during the

ENSURE R-21 is aligned to sample scenario and are to be placed in the booth. containment - New for ITS

ENSURE R-23 PROTECTED TRAIN placard is in place below the R-23 KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS No Additional Material Need For Booth drawer

POSITION AS-31/AS-35, R-11 and R-12 Sample return to return to the Shift Manager Status board information containment.

Equipment OOS

ENSURE two sets of PRZR backup heaters are ON (A & B)

PR-2A excessive seat leakage

At BOP 1 PPCS Monitor set monitor to N41 Display FW Pumps temperatures from the Feedwater Pumps graphical display TS 3.4.11 (Reactor Coolant System

ALIGN Containment Vent 2 path:

Pressurizer Power Operated Relief Valves)

PLACE Containment Dome Fan B to Condition A One or more PORVs START inoperable and capable of being manually cycled. Required Action A.1 is to close and

STOP Containment Dome Fan A maintain power to the associated PORV and PLACE in AUTO Block Valve with a completion time of one

OPEN LOCA-2B, POST-LOCA hour (Completed). HYDROGEN CNTMT VENT ISOL B

OPEN LOCA-100B, POST-LOCA TS 3.3.1(Reactor Protection System (RPS) HYDROGEN TO RECOMBINER B Instrumentation) Condition A One or more

PLACE PR-1A to CLOSE, and PLACE Functions with one or more required clearance status tag channels or trains inoperable. Required Action A.1 enter the condition referenced in

Remove the N41 from service as follows Table 3.3.1-1 for the channel(s) or train(s)

Pace Rod Control Selector Switch with a completion time of immediately. in MAN TS 3.3.1 Reactor Protection System (RPS)

Position the following switches to Instrumentation) Condition D one channel the failed PR Channel N41 inoperable with Required Action D.2.1 to

Upper section on Detector place channel in trip with a completion time Current Comparator of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND Required Action D.2.2

Lower Section switch on Detector perform SR 3.2.4.2 with a completion time Current Comparator of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Table 3.3.1-1 Item

Rod Stop Bypass switch on 2.a PR Neutron Flux High - Channel in Trip Miscellaneous Control and and SR 3.2.4.2 performed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months before KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS start of the scenario Indication Panel TS 3.3.1 Reactor Protection System (RPS)

Power Mismatch Bypass switch Instrumentation) Condition E one channel on Miscellaneous Control and inoperable with Required Action E.1 to Indication Panel place channel in trip with a completion time

Comparator Channel Defeat of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . - Channel in Trip Switch on Comparator and Rate Drawer

On N41A drawer place control power breaker to OFF NOTE: Leave the Control Rod Selector Switch in MAN Until after the CAEP file has been run

OPEN and Run CAEP file. ROI-06-SE-SC2-preload.cae. After file has run for one minute close CAE file.

Place the Control Rod Selector Switch to AUTO

Ensure PPCS boron reads 222 ppm. In Remarks PPCS Functions, Operator Entry, Boron Concentration, Enter New Protected train = A Boron Concentration and then press Risk CDF/LERF= Green APPLY.

SPER / WRs

Verify the Instructor Station Summary None IAW instructions at the beginning of the input summary in this SEG GENERAL

Second verification of the Instructor IAW Consecutive days of operation ___490____ instructions at the beginning of the input G-1 Closed (indicate date last month) JD summary in this SEG xxx

Start SmartTest using the SmartTemplate for NRC Exam.xlt file.

Burn up 17,000 MWD/MTU

ENSURE Job Aid 04-009, Simulator Sirens Lost Coverage % __0__ Exam/EP Drill Setup and Cleanup KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Sirens OOS __0__ adequate to support exam by RCS and Pressurizer boron = 222 ppm COMPLETING ATTACHMENT 1, Simulator Setup Exams/EP Drill, or All other entries are standard ATTACHMENT 2, Reset Exam/EP Drill, as appropriate

3. PRE-SCENARIO:

a) IF this is the first simulator scenario of the week, THEN review the Simulator Differences List with the crew.

b) Provide crew with:

Turnover sheets and plant information

Plant Brief for GOP-106 - To be given if asked for

Brief for startup of second main Feed Pump - to be given if asked for

Copies of the following procedures:

GOP-106 completed up to and including section 5.1.14,

NOP-FW-001 completed up to and including step 5.1.6.k

NOP-TB-001 completed for all 5.1 and up to and including step 5.2.1.c (Turbine is NOT on VPL)

NOP-HD-001,

NOP-CVC-001

Reactivity Plan to support power change KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

For containment vent, Provide copy of Data Sheet C, Containment Vent Log, from SP-32-113, Gaseous Radioactive Effluents Reports For Continuous Releases, with Month and Year filled-in, and Date, Start Time, RP Notified (Y)

& Remarks (2 Vent) filled-in.

c) Cover Simulator Scenario Briefing Sheet in Job Aid 04-01 with the crew

Inform the crew that the Designated Exam Team Member will take response for the Shift Manager. They will acknowledge communications, but their acknowledgment does not mean agreement or disagreement.

d) ENSURE the crew has been briefed IAW NUREG 1021 Appendix E (Simulator Test Guidelines) e) If allowed by the NRC Chief Examiner, Lead Exam Team Member will perform a Pre-Job brief per Job Aid 04-03.

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

4. TURNOVER: After ~5 minute walk The crew has been given direction to raise down of boards by the crew. Give the crew power to 56% and start A MFP. Power was the shift. reduced 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago for FWP 1A Shift Direction: corrective maintenance Commence Management directed starting of Main Feed pump A and power escalation (All) Walk down control boards~ 5 minutes

9. SCENARIO:

During the scenario if the US asks for an EAL evaluation the response is under evaluation EVENT 1: POWER ESCALATION AND START OF MAIN FEED PUMP A Human Performance Tools: Pre-Job Brief, Procedure Compliance, Clear Communications, Verification Practices, Self Checking Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely Controlling Plant Evolutions, Teamwork Reactivity - ATC Normal - BOP A second Main Feed Pump must be started US go over the plan established prior to prior to exceeding 285 psig impulse entering the simulator.

pressure approximately 56% Turbine Load).

Use GOP-106 as governing procedure As long as the crew completes starting of to raise power Main Pump A prior to this the task is completed satisfactorily

Use NOP-TB-001 to raise turbine load

Use NOP-CVC-001 for boron control Pre-Job Brief will have been performed

Rod Control expected to remain in prior to entry into the simulator. The crew AUTO if go to manual then use NOP-may elect to clarify or re-iterate some items CRD-001 for control rod operation.

in a short brief.

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS OP-KW-GOP-106 Startup From 35% Power to Full Power US When the conditions of step 5.1.14 are met, then perform the following

Direct to raise power per NOP-TB-001 US Prior to exceeding 285 psig impulse pressure (approximately 56% Turbine Load) Ensure two feedwater pumps are running per NOP-FW-001 NOP-FW-001 Normal Feedwater System Operation This section has NOP-FW-001 completed If required: BOP Start FW Pump 1A as Follows through step 5.1.6.k and reflects the starting ROLE: EO

Position FW-2A/MV-32025, Feedwater of the FW Pump at step 5.1.6.l Pump 1A and Discharge Valve, control REQUEST: Step 5.1.6.k local actions Human Performance: Self Checking, switch to START RESPONSE: FW-201A is now CLOSED Verification Practices, Clear Communication The operator should hold a focus brief and announce on the GAI-Tronics starting of FWP 1A prior to performance of the step BOP

Ensure FW Pump Group Parameters stabilize BOP

If steam Generator A(B) Level is rising due to excessive leakage past FW-7A(B) or FW-10A(B), then perform the following - N/A KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: EO BOP direct the EO to perform locally steps REQUEST: Perform steps 5.16.p & 5.16.q 5.16.p & 5.16.q of NOP-FW-001 RESPONSE: Acknowledge direction and report steps completed after delay DELAY: 21 minutes NOP-TB-001 Turbine and Generator Operation, section 5.2 NOP-TB-001 has been completed for BOP raise load as follows section 5.1 (all) and 5.2 up to and including

Set Setter to required load using 5.2.c (Turbine is NOT on VPL) reference Control UP/DOWN pushbuttons

Set loading rate % per minute as The desired Loading Rate is 1/2 % min determined by US which will be set into the Load Rate

Ensure loading rate % per minute less thumbwheel than the following:

Maximum allowed by fuel performance and Turbine Operating Limits ROLE: SM ROLE: DEMI US inform DEMI of load increase REQUEST: Inform DEMI of Load increase REQUEST: Inform of Load increase

Rate of load increase RESPONSE: Acknowledge direction to RESPONSE: Acknowledge load increase

Amount of load increase inform DEMI of load increase wait delay DELAY: None then inform US DEMI has been informed of load increase DELAY: 2 minutes BOP Adjust Valve Pos Limit to between 2%

and 3% above next stopping point to ensure load limits are not exceeded KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS NOTE: Placing the turbine to GO may not This request may occur after turbine loading BOP Press GO pushbutton occur until AFTER the CVCS boron dilution has been initiated has been started. ROLE: EO REQUEST: Monitor the following turbine Human Performance: Clear components:

Communications. Self Checking,

Generator Exciter Verification Practices

Lube Oil parameters

Generator parameters Operator Fundamentals: Teamwork RESPONSE: Acknowledge direction The operator should have a focus brief to ensure the crew is aware that the load increase is being commenced Operator Fundamental: Closely monitoring BOP Check Control valve Position as load parameters and indications is raised per Attachment G NOP-CVC-001 Boron Concentration Control, Dilution Section 5.4 There are three notes referring to reactivity RO check at least one of the following control prior to performance of a dilution: pumps operating

Positive reactivity additions shall be

RXCP A performed using one method at a

RXCP B time unless performed using an approved reactivity plan

RHR Pump A

PPCS reactivity function is the most

RHR Pump B accurate method to determine differential boron worth

For large dilution refer to precaution and limitation Section 4.18 - The dilution per the reactivity plan is less than 1000 gallons KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance: Pre-Job Brief RO Determine rate and magnitude of dilution required This should be covered in the brief before the crew enters the simulator and determined by the reactivity plan Human Performance: Pre-Job Brief RO Estimate change in rod position, Boron Concentration, Tave and Reactor Thermal Power These items should have been covered in the pre-job brief.

Human Performance: Self Checking RO Adjust MU-1022/CV-31095, Blender Control Rx MU Flow, hand controller to required flow rate Human Performance: Verification Practices RO Set Rx Makeup Totalizer to required

- Peer Checking quantity RO Close red shutter on Rx Makeup Totalizer Human Performance: Verification Practices RO Position Reactor Makeup Mode

- Peer Checking Selector switch to the required mode It is expected that the crew will use Alt

Dilute Dilute

Alt Dilute Human Performance: Verification Practices RO If performing alternate dilute AND VCT

- Peer Checking dilution not required then position control switch for CVC-406/CV-31094, BA Blender to VCT to CLOSE Human Performance: Verification Practices RO Position Reactor Makeup Control

- Peer Checking switch to START KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamental: Closely Monitoring RO If any of the following occur, then Plant Conditions position Reactor Makeup Control switch to STOP

Changes in parameters indicating negative reactivity addition

Subcritical count rate doubles

Actual RCS Boron Concentration less than or equal to required concentration Human Performance: Pre-Job Brief The following steps are permitted if This option should be covered in the pre required to place Reactor Makeup job-brief when discussing what could go Control System in AUTO - Not expected wrong to be performed but allowed RO If required to immediately place Reactor Makeup Control System in Auto

Position Reactor Makeup Control switch to STOP

Ensure MU-1022 hand controller set at 60 gpm

Ensure CVC-406 Control switch positioned to Auto

Position Reactor Makeup Selector to AUTO

Position Reactor Makeup Control switch to START

At 44560/YIC-11, Rx Makeup Totalizer, Record number if gallons added

Record reactivity manipulation in Control Room Narrative log KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance: Self Checking, RO When the dilution is complete then Verification Practices - Peer Checking restore system as follows:

Set CVC-403/CV-31092, Boric Acid to Blender for auto makeup as follows

Using RD2.1.1 or operator Sid 96-3 Determine setpoint for CVC-403 that will provide blended flow at current RCS Boron Concentration

Record setpoint for CVC-403

Set CVC-403 hand controller to recorded setpoint Ensure MU-1022 hand controller set at 60 gpm Ensure CV-406 Control switch positioned to AUTO Position Reactor Makeup Mode Selector switch to START At 44560/YIC-111, Rx Makeup Totalizer, Check correct quantity added At 44560/YIC-111, press black pushbutton and Ensure Totalizer output window resets to all zeros Record reactivity manipulation in Control Room Narrative log RO If RCS Boron concentration has been changed by greater than 50 gpm then operate PRZR heaters as necessary to equalize RCS and PRZR boron per NOP-RCS-003 KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS NOP-RCS-003 Pressurizer Pressure Control Note in NOP-RCS-003 prior to section 5.2 RO When required for plant conditions then for operation of Pressurizer Backup Heaters position any combination or single Backup

Pressurizer Backup Heaters should be Przr Heater Group(s) to ON energized for any of the following

Pressurizer Heater Group A reasons:

Pressurizer Heater Group B

Equalize RCS to pressurizer boric acid

Pressurizer Heater Group D difference of more than 50 ppm

Pressurizer Heater Group E

To reduce excessive cycling of Pressurizer backup heaters during RCS temperature changes

To minimize pressure transients during plant evolutions RO When NO longer required for plant conditions then position any or all of the Backup Przr Heater Group(s) to AUTO or OFF

Pressurizer Heater Group A

Pressurizer Heater Group B

Pressurizer Heater Group D

Pressurizer Heater Group E NOP-CVC-001 Boron Concentration Control, Dilution Section 5.4 RO Record completion time NOP-CVC-001 Boron Concentration Control, Verification of Automatic Makeup section 5.2 During the scenario when Automatic occurs RO Observe VCT Level on LI-112 or the US should direct the RO to perform this LI141B to ensure proper automatic control section of NOP-CVC-001 for verification of operation Automatic Makeup KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO Using the following check for proper boron concentration during automatic makeup

CVCS BA & MU flow Recorder

Rx Makeup and Boric Acid Flow Totalizers

Boric Acid Tank level change to Boric Acid Totalizer Change

Source Range Count Rate

Change in Tave

Control rod motion RO If adjustment to BA concentration of makeup flow is required during auto makeup then adjust CVC-403 as required to raise or lower concentration There is note for during CVCs blended flow An alarm may occur on the Waste Panel RO If low flow to single BA transfer pump is makeup with low BA flow one BA transfer due to high gas pressure in Waste Gas suspected during parallel pump operation pump may provide most of the flow and Header if the crew vents the VCT because then perform the following:

cause a low flow condition in the other of rising pressure. Throttle Open the following as necessary to pump - Not Expected ROLE: AO in increase system flow REQUEST: Waste Gas Header High

CVC-712A/CV-311106, Bat A Recric Pressure alarm at Waste Gas Panel is due Control to Control Room activities.

CVC-712B/CV-311107, Bat B Recric RESPONSE: Acknowledge report Control Monitor BAST A Levels using the following instruments

LI-106

LI-172

LI-190 KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

LI-196 Monitor BAST B Levels using the following instruments:

LI-102

LI-171

LI-189

LI-197 Adjust the following as required to maintain BAST Levels approximately equal

CVC-712A

CVC-712B When Makeup is complete then close the following

CVC-712A

CVC-712B RO When automatic makeup is stopped then perform the following

Record Boric Acid Totalizer Output

Record Rx Makeup Totalizer output

At 44559/YIC-110 Boric Acid Totalizer press the black reset pushbutton and ensure totalizer output window resets to all zeros

At 44560/YIC-111 Rx Makeup Totalizer press the black reset pushbutton and ensure totalizer output window resets to all zeros KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

Record reactivity manipulation in Control Room Narrative log

Record Completion Time EVENT 2: SG A RED CHANNEL PRESSURE, PT-468. FAILS HIGH TO 1400 PSIG OVER 30 SECONDS Human Performance Tools: Procedure Compliance, Clear Communications, Peer Checking, Self Checking Operator Fundamentals: Precisely Controlling Plant Parameters, Knowledge of Plant design and Theory, Teamwork, Closing Monitoring Plant Conditions BOP - Component SRO - Technical Specification When the lead evaluator determines that At the lead Evaluators Direction insert Annunciators:

crew has completed the requirements of the TRIGGER 1 and Ensure RX213 is active 47061-C, S/G A FEED FLOW EXCESSIVE normal power increase and starting FWP and ramping to 1400 psig over 30 seconds (Depending on when the crew recognizes 1A then can continue to event 2 the problem and takes action)

TLA-10, SG TILTS Board Indications A SG level increasing above program Reactor Thermal Increasing SD-3A ,SG PORV red light LIT SG A Pressure Pt-468 rising Operator Fundamental: Closely Monitoring BOP Identifies the following Plant Conditions SD-3A OPEN SG A pressure on PT-468 rising SG A narrow range level not maintaining on program.

KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS AOP-GEN-001, Immediate Operator Actions, Attachment D Steam Generator PORV Failure BOP Performs immediate actions of AOP-GEN-001 to Shut SD-3A

Check Steam Generator PORVs BOTH CLOSED (NO SD-3A OPEN)

RNO

If SG pressure < 1005 psig than STOP SG PORV Flow

Manually CLOSE SD-3A BOP Check Initiating Event Instrument Failure -PT-468 US Transition to AOP-MISC-001 AOP-GEN-001, Immediate Operator Actions, Attachment B Abnormal Steam Generator Level Human performance: Self Checking, Clear BOP Performs immediate actions of AOP-Communications, Procedure Compliance, GEN-001 to place FW-7A in MAN Peer Checking

If SG level is changing in an uncontrolled manner then PERFORM Operator Fundamental: Precisely the following Controlling Plant Parameters, Teamwork o SHIFT affected SG Feedwater Flow Controller to Manual - FW-7A o THROTTLE affected SG Feedwater control valve to maintain SG narrow range level stable between 30% and 46% - FW-7A BOP Check Initiating Event - Instrument Failure SG Pressure PT-468 KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US Transition to AOP-MISC-001 US Hold Brief to for entry to AOP-MISC-001 Actions for AOP-MISC-001, Response to Instrument Failure, Attachment D US/BOP If failed steam pressure channel is an input to a SG PORV

VERIFY Immediate Actions of AOP-GEN-001 are complete

Place affected SG PORV to Manual (SD-3A)

Adjust SG PORV as necessary to control SG Pressure at desired value BOP If the failed steam pressure channel is selected (via the associated Steam Flow Selector switch) as the input to SG level control then perform the following

Ensure immediate actions for Steam Generator level control failure performed per AOP-GEN-001

Restore SG Level program value to program value of 44%

Defeat the failed channel input by selecting the alternate steam flow channel on the associated Steam Flow Channel Selector switch

When SG Level is restored to normal and feed/steam flow are matched then place the affected SG feed regulating valve in AUTO KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: SM ROLE: WWC and/or I&C US Contact SM/WWC/IC to perform REQUEST: Contact WWC and/or I&C to REQUEST: Inform of failed instrument and corrective action on failed instrument inform of failed instrument and perform perform corrective maintenance on failed corrective maintenance for the failed instrument.

instrument RESPONSE: Support as requested, will get RESPONSE: Will contact, after Delay work order together and start on other report that WWC and /or I&C has been paper work for corrective maintenance contacted Delay: None DELAY: 1 minute The US may have brief at this time for the US Refer to TS failed instrument. TS 3.3.1 for table 3.3.1-1 Function 15

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation)

Condition A One or more Functions with one or more required channels The US may also refer to TS 3.7.4 SG or trains inoperable. Required PORVs. TWO SG PORVs remain Action A.1 enter the condition OPERABLE per Tech Specs since SD-3A referenced in Table 3.3.1-1 for the remains capable of being operated in channel(s) or train(s) with a MANUAL completion time of immediately.

TS 3.3.1 (Reactor Protection System (RPS) Instrumentation)

Condition E one channel inoperable with Required Action E.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Table 3.3.1-1 Item

15. SG Water Level - Low coincident with Steam Flow/Feedwater Flow Mismatch.

KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS TS 3.3.2 for table 3.3.2-1 Function 1,e

TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation Condition A One or more Functions with one or more required channels or trains inoperable. Required Action A.1 enter the condition referenced in Table 3.3.2-1 for the channel(s) or train(s) with a completion time of immediately.

TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation Condition D one channel inoperable with Required Action D.1 to place channel in trip with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Table 3.3.2-1 Item 1.e Safety Injection - Steam Line Pressure -

Low The remaining action of AOP-MISC-001 US Contact I&C for performance of SP address I&C tripping of the bistables for 316E the failed channel, this action will NOT ROLE: WWC and/or I&C be performed in this Scenario.

REQUEST: Perform SP-47-316E ROLE: SM RESPONSE: SP-47-316E will take REQUEST: Contact I&C to perform SP- approximately 45 minutes to complete 47-316E Delay: None RESPONSE: wait delay then report that I&C reports SP-47-316E will take approximately 45 minutes to complete DELAY: 1 minute KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS If bistable tripping has been omitted by ROLE: SM ROLE: WWC and/or I&C the lead evaluator then this statement is REQUEST: Send and I&C tech to the REQUEST: Send and I&C tech to the N/A control room for the tripping of bistables control room for the tripping of bistables CREW Check the existing bistable status to RESPONSE: Acknowledge the request and RESPONSE: Acknowledge the request and ensure a reactor trip will not occur when the inform the Control Room that an I&C tech inform the Control Room that an I&C tech failed instrument is placed in tripped will be in the control room in about 45 will be in the control room in about 45 condition minutes minutes Delay: 1 minute Delay: None EVENT 3: Small Non-Isolable RCS leak inside of containment Human Performance Tools: Procedure Compliance, Questioning Attitude Operator Fundamentals: Teamwork, Closely Monitoring Plant Conditions ATC-Component After Technical Specifications have been At the lead evaluators direction insert Annunciators:

covered by the US Bistable Tripping may be Trigger 11 and ensure that malfunction 47033-35, TLA-15 RMS Above Normal omitted at the lead evaluators discretion) RC08 inserts and ramps to a value of 1.4 47012-B, Radiation Indication Alert then event 3 is expected to be directed to over 5minutes begin. 47011-B, Radiation Indication High Human Performance: Questioning Attitude Parameters Identified by Crew Operator Fundamental: Closely monitoring

Humidity rising plant conditions

Charging speed increasing

PRZR level lowering slowly

Containment pressure rising

Rad Monitors increasing

R-11, R-12, R-21, & R-7 rising KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS The US may direct the BOP to perform the US Direct Performance of ARPs for actions of the ARPS while they and the RO radiation levels - May choose to directly perform the actions of AOP-RC-001 enter AOP-RC-001 based on plant indication 47033-35 TLA-15 RMS Above Normal, 47012-B Radiation Indication Alert OR 47011-B Radiation Indication High ROLE: SM ROLE: RP BOP/RO Check alarm due to any of the REQUEST: Inform RP of Rad Monitor REQUEST: Inform of Rad Monitor Alarms following Alarms and to survey the affected areas. and to survey the affected areas.

R-15 RESPONSE: Acknowledge request to RESPONSE: Acknowledge the Rad Monitor

R-19 contact RP and after delay report that RP Alarms & Surveys. And any other request has been informed made by the crew.

R-42 DELAY: One Minute DELAY: None

R-43 Operator should note that alarm is due to R-11, R-12 & R-21 Note: R-7 may alarm depending on the crew reaction time RNO

Direct RP to Survey the affected area and to assist in identifying and isolating source The US may elect to have the BOP perform US Transition to AOP-RM-001 the actions AOP-RM-001 vice directing the procedure. The BOP will have keep the US informed of equipment manipulations or problems encountered during performance of the procedure KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS AOP-RM-001 Abnormal Radiation Monitoring System Depending on the speed of the crew to get (CAS) BOP Check if Personnel should be to this point R-7 may be in alarm or alarm evacuated during the performance of the procedure. If R-2 through R-10 in Alarm - NO in alarm the operator will determine that no personnel are in containment and only action is to announce the event BOP Radiation Monitors - None Failed downscale Depending on the speed of the crew to get BOP Check operation of Each Affected to this point R-7 may be in alarm or alarm Radiation Monitor Using Table 1 during the performance of the procedure Verify all applicable steps from table 1 below completed - Determine R-11, R-12 &

R-21 are the affected Radiation Monitors.

Table 1 Affected GO TO Radiation Page STEP Monitor R-7 9 8 R-11 12 10 R-12 13 11 R-21 22 20 KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS AOP-RM-001 for R-7, R-11, R-12 and/or R-21 Alarming BOP Check radiation monitor operating Properly - Yes

[R-7]

(None)

[R-11/R-12]

NOTE: The first three bullets are performed

Position Tape Drive Control to Fast for only for R-11 in alarm. at least 15 seconds

Position Tape Drive Control To OPERATE

Check R-11 Indication Decreasing

If High Radiation Alarm has occurred then check specific automatic actions of Attachment A have occurred:

a. Following Dampers Close

TAV-12

RBV-2

RBV-5

RBV-3

b. Following valves closed

SA-7003B

LOCA-2B

[R-21]

If High Radiation Alarm has occurred then check specific automatic actions of Attachment A have occurred:

a. The following Dampers Close

TAV-12

RBV-1

RBV-4 KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

RBV-5

b. The Following Valves Close

LOCA-100B

LOCA-201B The US should be performing AOP-RC-001 BOP Check Radiation Levels Normal at this time with the RO RNO

[R-7]

Perform AOP-RC-001 while continuing with this procedure ROLE: SM [R-11/R-12]

REQUEST: Review EAL for classification.

Inform the SM to review Emergency Action Level Matrix for Event RESPONSE: Acknowledge direction to Classifications review the EAL matrix for classification

Perform AOP-RC-001 while continuing DELAY: None with this procedure Aligned per initial conditions in the scenario

Ensure R-11/12 return aligned to containment

[R-21]

Inform the SM to review Emergency Action Level Matrix for Event Classifications

Perform AOP-RC-001 while continuing with this procedure The US may be performing AOP-RC-001 at US Transition to AOP-RC-001 this time with the RO KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS AOP-RC-001 Reactor Coolant Leak US/RO Check RHR System NOT in service for RCS Cooldown (CAS) US/RO Check Reactor Trip not Required

Check PRXR Level >3%

Check Reactor Critical

Check VCT Level >5%

(CAS) US/RO Check PRZR level Stable at or trending to program level RNO

If PRZR level decreasing the perform the following

Close all letdown isolation valves o LD-2 o LD-3 o LD-4A o LD-4B o LD-4C o LD-300

If PRZR level continues to decrease then increase charging pump speed as necessary to establish maximum charging flow The rest of the actions for the RNO should be entered with the small leak rate until the large break LOCA develops KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/RO Check for leakage in Auxiliary Building ROLE: AO

Check Auxiliary Building radiation REQUEST: Check Aux Bldg Sumps Monitors Normal normal: o R-4 o R-13

Sump Tank o R-14

Sludge Intercept Tank

Check Auxiliary Building Sumps RESPONSE: Acknowledge Request. Normal Report tank conditions normal o Sump Tank DELAY: 5 Minutes o Sludge Intercept Tank NOTE: The diagnostic steps may be US/RO Determine if Leak is on Letdown performed in any order. When the leak is Line isolated, the remaining diagnostic steps are

Close all LD isolation valves not required to be performed.

Check leak isolated o RNO - Go To next step US/RO Determine if leak is on Charging Line

Close all LD isolation valves

Close Charging Line flow control valve CVC-7 and establish one charging pump running at minimum speed

Check RXCP seal injection intact

Close charging line isolation CVC-11

Check leak isolated o RNO - Re-establish CHG and Go To next step KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/RO Determine if leak is on RXCP Seal Injection Lines o Seal Injection flow between 6 gpm and 13 gpm o Labyrinth seal P normal ROLE: AO US/RO Check Charging Pump Leakage REQUEST: Check Charging Pumps for Normal leakage and Perform Local Actions if required RESPONSE: Acknowledge Request to check charging pumps for leakage. Report there is no local indication of leakage from the charging pumps DELAY: 5 Minutes ROLE: SM ROLE: RP US/RO Check RCS Intact inside of REQUEST: Contact RP to Prepare for REQUEST: Prepare for Containment Entry Containment Containment Entry to determine leak to determine leak location

R-11/12/21/7/2 not normal and not location RESPONSE: Acknowledge the direction for stable RESPONSE: Acknowledge the request for Containment Entry. It will take

Cntmt Humidity not normal and not RP and after delay report that RP has approximately to 60 minutes to get ready to stable stated it will take approximately to 60 enter containment.

Check Containment Sump A run minutes to get ready to enter containment. DELAY: None history Normal DELAY: One minute Consult RP and Perform ROLE: OMOC Containment Entry to identify REQUEST: Management approval for source of leakage containment entry When Leak identified Then RESPONSE: Acknowledge request for Isolate Leak management approval for containment entry and will get back to you shortly.

DELAY: None KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS At this point in the procedure the crew is US/RO Determine RCS Leakage directed to move past the diagnostic steps Perform any of the following in the procedure to determine RCS leak

OP-KW-OSP-RCS-001, Reactor rate and if a plant shutdown is required. Coolant System Leak Rate Check OR If not already done at this time the crew

Charging Letdown Mass Balance should determine that the RCS leak rate is OR approximately 20 gpm

VCT Level Trend The US should hold a brief at this time to US Determine if Plant Shutdown Required assess the situation

RCS Operational leakage does not comply with TS3.4.13 RCS Operational ROLE: SM leakage REQUEST: EAL Classification and contact OR management for direction on plant

Plant Management directs plant shutdown shutdown RESPONSE: EAL Under Evaluation and Technical Specification will Contact Plant Management TS 3.4.13 RCS Operational Leakage Condition A RCS operational LEAKAGE not DELAY: None within limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE with Required Action A.1 to reduce leakage to within limits with a completion time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 4/5: LARGE BREAK LOCA -Failure of CVC 211 & CVC-212 to Close Human Performance Tools: Clear Communications, Self Checking, Procedure Use and Adherence, Peer Checking Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely Controlling Plant Evolutions, Teamwork Major ALL Component: ATC After the US has addressed TS for the RCS At the lead evaluators direction insert Annunciators for RCS Leak leak then at the lead evaluators direction TRIGGER 13 and ENSURE that the LARGE break LOCA can be inserted malfunction RC03A at and ramps to 5 over 47031-P, Containment Sump A Level Hi-Hi 3 minutes 47031-Q, Containment Sump A Level High Containment Sump Level Alarms may When TRIGGER 13 is inserted ENSURE 47043-C, Pressurizer Control Press already be in at this time malfunction RC08 is deleted Abnormal During the performance of E-0/E-1/ECA- After the crew takes the RXCP to pullout 47043-D, PRZR Pressure Low 1.1 a red path on integrity may exists. then ENSURE that TRIGGER 2 is active The crew should enter FR-P.1 and exit at and malfunction RC03A is ramping to 100% 47043-E, Pressurizer Level Deviation step 1 due to a LOCA in progress over 2 minutes 47043-F, PRZR Level Low TLA-15 RMS Above Normal During the performance of E-1 when 47011-B, Radiation Indication High RWST level lowers to 37% the crew 47012-B, Radiation Indication Alert should transition to ES-1.3.

Board Indications Radiation Monitors rising The lead evaluator may direct the insertion of trigger 2 and ramping the malfunction to PRZR level lowering 100% if the crew does trip RXCPs by the PRZR pressure lowering time they are directed to monitor CSF Containment humidity and pressure rising status trees. This is not expected to be required, but if it does occur there will be a Orange path on Core Cooling KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamentals: Closely RO reports that PRZR level and pressure is Monitoring Plant Conditions, Precisely decreasing Controlling Plant Evolutions Human Performance Tools: Clear Communications US/RO Refer to the CAS step in AOP-RC-001 either Check Reactor Trip not Required

Check PRXR Level >3%

Check Reactor Critical

Check VCT Level >5%

OR Check PRZR level Stable at or trending to program level RNO

If PRZR level decreasing the perform the following

Close all letdown isolation valves o LD-2 o LD-3 o LD-4A o LD-4B o LD-4C o LD-300

If PRZR level continues to decrease then increase charging pump speed as necessary to establish maximum charging flow

If PRZR Level continues to decrease the perform the following o Manual Trip the Reactor o GO TO E-0 KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance Tools: Clear US DIRECT Manual tripping of the reactor Communications and implementation of E-0 AOP-GEN-001, operator immediate actions also directs tripping the reactor if PRZR level cannot be maintained greater than 3%

E-0 Reactor Trip or Safety Injection RO Manually Trip the Reactor RO Ensure Reactor Trip

Check Reactor Trip and Bypass Breakers OPEN

Check Reactor Subcritical BOP Ensure Turbine Trip

Check HP Turbine Impulse Pressure Trending Toward zero

Check both Turbine Stop Valves Closed BOP Check 4160V Emergency AC Buses Both energized. Bus 5 AND Bus 6 KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 49 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS SI should have actuated, or will be required RO Check SI actuated manually, on lowering PRZR level and RCS Check permissive status 44905-1201 SI pressure. Signal Activated LIT RNO Determine appropriate recovery action Check if SI is required

PRZR pressure < 1815 psig

PRZR Level < 3%

RCS subcooling < 15ºF

SG pressure < 500 psig

Containment pressure > 4 psig If SI is required then manually actuate both trains of SI US Hold crew brief

Announce Crew Brief

EAL o Under review

Recap Major Events o Large Break LOCA

Ongoing Recovery Actions o Continue in E-0

Comments

End Crew Brief CREW Monitors Foldout Page KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamentals: Precisely After the crew takes the RXCP to pullout US/RO IDENTIFY RXCP Trip Criteria per Controlling Plant Evolutions then ENSURE that TRIGGER 2 is active Foldout Page Human Performance Tools:, Procedure and malfunction RC03A is ramping to 100%

IDENTIFY at least one SI pump use and Adherence over 2 minutes Running and capable of delivering flow Critical Task: STOP RXCPs

IDENTIFY RCS subcooling based on Safety Significance: The purpose of CETs <15ºF [37°F]

tripping the RXCPs during LBLOCA

IDENTIFY Operator controlled accident conditions is to prevent pump cooldown NOT in progress damage and ensure RXCPs are available if needed for future recovery actions

RO STOP and PLACE BOTH RXCPs in PULLOUT Cue: RXCPs running during large break LOCA and Subcooling less than 15°F

[37°F] with at least one SI pump running and capable of delivering flow, and no operator controlled cooldown in progress.

Measurable Performance Indicator:

Crew Stops RXCPs before transitioning from E-0 per foldout page of E-0 or AOP-RC-005 Performance Feedback: RXCPs stopped See separate section below. RO Performs Attachment A by direction from the SRO.

Following this step if AFW Pumps are (CAS) US/BOP Check AFW Pumps tripped due to the Low Discharge Pressure Running - All Expected to be running Trip, the crew may restart the AFW pumps using the Foldout Page Guidance 4: Check AFW Pump A Running

Close the AFW Pump discharge Check AFW Pump B running valve(s) (AFW-2A or AFW-2B) Check MD AFW Pumps Both Running

Reset and start AFW Pump(s)

KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

Throttle AFW Pump discharge Throttle MD Flow as necessary to maintain valves as necessary to establish discharge pressures greater than 1000 psig desired flow while maintaining prior to and immediately prior to stopping discharge pressure > 1000 psig TD AFW pump. - N/A Stop TD AFW pump and place in Pullout (CAS) US/BOP AFW discharge pressure >

1000 psig US/BOP Check Secondary Heat Sink Ensure total AFW flow > 210 gpm OR SG narrow range level > 5% [13%]

US/CREW Check RXCP Seal Cooling Normal (CAS) US/CREW Check RCS Temperature Control

RCS Cold Leg temperatures <5470F and Stable RNO

Main Steam Dump Mode Selector Switch to RESET then STM PRESS

Stop Dumping Steam

If SG pressure less than 1005 psig Then VERIFY SG PORV CLOSED

Reduce Total Feed Flow to between 210 - 250 gpm

CLOSE MS-1A, MS-2A, MS-1B, MS-2B if RCS temperature continues to lower KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/RO Check PRZR PORVs - Both Closed US/RO Check PRZR Spray Valves Closed US/ RO Check if RXCPS should remain running OP-AP-104 states that in the absence of IF REQUIRED AND DIRECTED BY THE CREW Monitor CSF Status Trees the STA the crew will monitor CSF status LEAD EVALUATOR THEN INSERT trees. TRIGGER 2 AND ENSURE RC03A IS Depending on the crew speed in performing RAMPING TO 100%

E-0 and tripping RXCPs there may be a RED path on Integrity. If a red path on Integrity exists then the crew will transition to FR-P.1 Check RCS pressure > 270 psig

[300 psig] - RNO - Check RHR flow > 700 gpm then return to procedure and Step in effect.

If the crew has not tripped RXCPs by this time then the lead evaluator direct the booth operator to insert TRIGGER 2 If the crew has not tripped RXCPs by this time they will be required to transition to FR-C.1 for an ORANGE path on Core Cooling Actions for FR-C.1 are scripted after E-0 actions and before E-1 Actions KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS CREW Check If any SG is Faulted The US should hold a crew brief on the CREW Check if SG tubes are intact transition to E-1

Air Ejector Exhaust Monitor Normal

SG Blowdown Liquid Monitor Normal

Main Steam Line Radiation Normal

N-16 before the trip normal

Steam Flow/Feed Flow and SG narrow range response normal before the trip CREW Check If RCS Intact Inside of Containment Check Containment Pressure Normal AND Check Containment Radiation Normal

R-2

R-7 RNO Perform the following Do NOT Continue until Attachment A complete GO TO E-1 US Conduct Crew Brief

Announce Crew Brief

EAL o Under review

Recap Major Events o Large Break LOCA KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

Ongoing Recovery Actions o Continue in E-1

Comments

End Crew Brief E-0 Attachment A RO Notify Plant Personnel using Gai-Tronics RO Check Feedwater Isolation

FW-7A/B Closed

FW-10A/B Closed

FW-12A/B Closed

FW Pumps A & B OFF RO Check SI Pumps - BOTH RUNNING RO Check RHR Pumps - BOTH RUNNING RO Check CC Pumps - BOTH RUNNING CRITICAL TASK: Isolate Containment by ROLE: AO RO Check Containment and Containment closing CVC-212 REQUEST: Locally Close CVC-212 Ventilation Isolation SAFETY SIGNIFICANCE: RESPONSE: Acknowledge the direction to

Check CI Active Status Panel light -

i) Failure of automatic containment locally close CVC-212. After Delay report ALL LIT isolation resulting the rise in because of Aux building radiation levels radiation levels and exposure of access HP is not allowing entry at this time KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 55 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS personnel to radiation DELAY: 2 minutes RNO unnecessarily Isolate flow paths ii) Failure of the operator to realize ENSURE when the operator takes CVC-212

Manually Actuate CI the failure of containment to CLOSE that TRIGGER 30 is active and isolation and take appropriate

If flow path not isolated then isolate Override DI-46214-OPEN is deleted flow path using attachment B actions demonstrates the inability of the operator to safely Containment isolation Verification as and effectively operate the plant follows:

during emergency situations. o Ensure associated In-CUE: Line Isolation CLOSED i) Valid Containment Isolation OR signal and containment isolation o Manually or Locally valves CVC-211 and CVC-212 CLOSE valve or damper open OR MEASURABLE PERFORMANCE o Locally CLOSE Manual INDICATOR: In-Line Isolation i) Close CVC-212 prior to

Place control switches for LD-4A/B/C to transition from E-0 Close PERFORMANCE FEEDBACK:

i) CVC-212 green light Lit indicates valve close and Containment Isolation Status panel indicates CVC-212 closed KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO Check if MSIVs can remain OPEN

Check if any MSIV or bypass open

Check Containment Pressure has remained < 17 psig

Check MS Header HI-HI Steam Flow bistable lights - OFF

Check MS Header HI Steam Flow bistable lights - OFF Operator Fundamental: Closely Monitoring (CAS) RO Check Containment Spray NOT Plant Conditions required Human Performance: Procedure Use and

Containment Pressure has remained <

Adherence\ 23 psig RNO All actions will occur but the operator is Establish containment spray required to ensure that all actions for ICS

Check Containment spray actuated have occurred.

o 47021-F LIT

If containment spray has NOT actuated

- N/A

Ensure all Containment Spray Pump Discharge Valves open o ICS-5A o ICS-6A o ICS-5B o ICS-6B KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

When SI sequencer is complete then ensure ICS pumps running

Ensure both Caustic Additive to Containment Spray Valves Open o CI-1001A o CI-1001B RO Check SW Alignment

All SW Pumps Running

Check SW Header pressures - both >

82.5 psig The fan coil units will not be able to be RO Check Containment Cooling started. Per the rules of usage for AOPs

Check CFCUs - All Running and EOPs in OP-AP-104 the operator RNO- When SI Sequencer complete THEN should move on to the next step and report manually START fan coil units failure to the US. Still have two ICS pumps

Ensure CFCU SW return Isolation running Valves - ALL OPEN

Check Shroud Cooling Coil Bypass valves - ALL OPEN

(CAS) Check Containment Pressure has remained below 4 psig RNO

Ensure all CFCU Emergency Discharge Dampers OPEN o RBV-150A o RBV-150B o RBV-150C o RBV-150D KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO Verify Aux Building Special Ventilation

Check Annunciator Zone SV BNDRY Damper not Closed - Clear (47052-G)

Check Zone SV Fans - ALL RUNNING RO Check Si Active Status Panel Lights -

ALL LIT RO Check SI Flow

Check RCS Pressure < 2000 psig

Check SI pumps flow indicated on FI-925

Check RCS pressure < 270 psig [300 psig]

Check RHR pump Flow indicated on FI-626 for pump A and FI-928 for pump B

RO Return procedure and step in effect FR-C.1 Inadequate Core Cooling RO Ensure proper SI valve Alignment (Table in Procedure)

RO Check SI Flow in Both Trains

Check SI pumps flow indicated

Check RHR pumps flow indicated RO/BOP Check RXCP Support Conditions available per OP-KW-NOP-RCS-001 RO Check SI Accumulator Isolation Valves Both Open KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO Check CET < 1200ºF US Return to procedure and step in effect E-1 RXCPs should have been tripped per Fold US/RO Check If RXCPs Should Be Tripped out Page US/BOP Check If Steam Generators Are Faulted (CAS) US/BOP MAINTAIN Intact Steam Generator Levels

Check intact SG narrow range level >

5% [13%]

RNO

Maintain total feed flow greater than 210 gpm until narrow range level > 5%

[13%] in at least one intact SG

Control feed flow to maintain intact narrow range level between 5% [13%]

and 50%

US/CREW Check Main Steam Radiation Channels R-31 And R-33 On SPDS -

NORMAL KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/RO (CAS) Check PRZR PORVs And Block Valves Available

Check Power available to PRZR PORV block valves o PR-1A o PR-2A

Check PRZR PORVS both CLOSED o PR-2A o PR-2B

Check PRZR PORVS block valves at least one OPEN o PR-1A o PR-1B Human Performance: Peer Checking US/RO Reset SI Human Performance: Peer Checking US/RO Reset Containment Isolation US/RO Check If RHR Pumps Should Be Stopped

Check RCS pressure >270 psig

[300psig]

RNO

Ensure both RHR pumps running KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 61 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/BOP CHECK Instrument Air To Containment Established

IA-101 Open

Reactor Building header pressure > 60 psig The crew will meet conditions to transition US/BOP Check Power Supply to charging to ES-1.3, Containment Sump Recirculation pumps - Off-Site power available when RWST level has lowered to 37% or lower as indicated by alarm 47023-B RWST LEVEL LOW lit US/RO Check Charging Flow Established

Start two charging pumps and establish charging flow to maintain PRZR level > 3% [15%]

RO/BOP checks each sub-step and US/RO Check If SI Should Be Terminated determines step requirement is NOT met. CHECK RCS subcooling based on core exit thermocouples - > 15°F [60°F]

CHECK RCS pressure:

Greater than 2000 psig AND

Stable or Increasing RO reports conditions not satisfied KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 62 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Do not expect that ICS can be stopped at US/RO (CAS) check if ICS can be stopped this time. It is a CAS and should be

Check ICS Pumps any running performed when the conditions are met.

Check Containment pressure < 4 psig

RESET ICS The background for the step states that stopping ICS pumps when containment

Stop ICS pumps and place in Auto pressure <4 psig prevents RWST depletion

Close and if containment pressure again rises o ICS-5A than FR-Z.1 will procedurally guide the operator to restart ICS. o ICS-5B o ICS-6A WOG ERG based critical tasks lists makeup o ICS-6B to the RWST and minimize RWST outflow o CI-1001A as a critical task o CI-1001B

Check RHR pump supply to ICS pumps CLOSED o RHR-400A o RHR-400B US/RO/BOP Check RCS and SG pressures:

Pressure in both Steam Generators Stable or Decreasing AND

RCS pressure Stable or Decreasing US/BOP Check if Diesel Generators should remain running

Stop B EDG KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/RO Check at least one ECCS train capable of Sump Recirculation

RHR pumps Available o RHR pump A o RHR pump B

Check RWST supply to RHR pumps available o SI-300A o SI-300B

Check Containment Sump B supply to RHR pumps available o SI-350A o SI-351A o SI-350B o SI-351B

Check SI Recirculation to RWST available o SI-208 o SI-209

Check RHR heat exchanger flow control valves available o RHR-8A o RHR-8B Human Performance: Clear ROLE: AO US direct board operator to contact NAO to Communications REQUEST: Place to following breakers to place the following breakers to on:

on:

SI-9A, MCC 52B(C3)

SI-9A, MCC 52B(C3)

SI-20A, MCC 52B(C4)

SI-20A, MCC 52B(C4)

SI-11A, MCC 52B(D1)

SI-11A, MCC 52B(D1)

SI-20B, MCC 62B(A3)

SI-20B, MCC 62B(A3)

KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

SI-11B, MCC 62B ext(1CF)

SI-11B, MCC 62B ext(1CF)

RESPONSE: Acknowledge direction. Wait delay time then insert TRIGGER 15 then report to the control that the action was completed.

DELAY: 8 minutes US/RO Check if RCS is intact outside containment

Aux building radiation levels

47032-Q clear

47033-R clear ROLE: SM ROLE: Emergency Director US inform the SM to consult with the REQUEST: Request Emergency Director REQUEST: Determine if OP-KW-AOP- Emergency director to determine if OP-KW-Determine if OP-KW-AOP-MDS-002, Post MDS-002, Post Accident Leakage Control AOP-MDS-002, Post Accident Leakage Accident Leakage Control System, should System, should be implemented. Control System, should be implemented.

be implemented. RESPONSE: Will evaluate and inform SM RESPONSE: Will evaluate and inform of of decision decision DELAY: None DELAY: None ROLE: SM ROLE: Chemistry US inform SM to direct chemistry to perform REQUEST: Request Chemistry to Perform REQUEST: Perform the following per the following per EPIP-RET-03C, Post the following per EPIP-RET-03C, Post EPIP-RET-03C, Post Accident operation of Accident operation of the High Radiation Accident operation of the High Radiation the High Radiation Sample Room Sample Room Sample Room

Start Up the Containment Hydrogen

Start Up the Containment Hydrogen

Start Up the Containment Hydrogen Monitoring System Monitoring System Monitoring System

Sample Both Steam Generators for

Sample Both Steam Generators for

Sample Both Steam Generators for Activity Activity KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Activity

Sample RCS for Boron and Activity

Sample RCS for Boron and Activity

Sample RCS for Boron and Activity RESPONSE: Acknowledge direction, RESPONSE: Acknowledge direction, and DELAY: None inform the US after delay that chemistry has acknowledge the direction DELAY: One Minute Do not expect any additional equipment to US evaluate the plant to start additional be started at this time equipment as necessary US/RO check if RCS cooldown and depressurization required

Check RCS pressure > 270 psig

[300 psig]

RNO

If RHR loop flow greater than 700 gpm Then GO TO Step 23 (Next Step)

US/RO check if transfer to containment sump recirculation is required

RWST level < 37%

KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamental: Team work to keep US crew brief the team informed of direction and

Announce Crew Brief problems

EAL o Under evaluation Human Performance: Clear Communications

Recap Major Events ROLE: SM o LOCA REQUEST: EAL Determination

On going Recovery Actions RESPONSE: Under evaluation o Transition to ES-1.3 for containment recirculation DELAY: None

Technical Specifications o Evaluate later time

Comments

End Crew Brief CREW determine RWST level < 37%,

47023-B US transition to ES-1.3 ES-1.3 Note: Critical task to stop any pumps US/RO check containment Wide range taking a suction from the RWST when the level > 2 feet RWST Low Low Level Alarm 47023-A is received.

Depending upon the speed of the crew this may occur prior to failure of SI-350A and SI-350B to open. The critical task is scripted in ECA-1.1 portion of the SEG KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 67 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO reset SI RO reset ICS WOG ERG based critical tasks lists makeup US/RO establish one train of injection to the RWST and minimize RWST outflow

Check train A injection flow:

as a critical task o SI pump A running and pump amps indicate flow OR o RHR pump A running and flow indicated FI-626

Stop SI pump B

Stop RHR pump B US/RO (CAS) check RCS pressure < 2000 psig Human Performance: Self Checking and RO close both SI recirculation to RWST Peer Checking valves

SI-208

SI-209 KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 68 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 6: LOSS OF EMERGENCY COOLANT RECIRCULATION ECA-1.1 - SI-350A & SI-350B Fail to OPEN Human Performance: Clear Communications, Self Checking, Peer Checking, Operator Fundamental: Team Work, Closely Monitoring Plant Parameters, Knowledge of Plant Design and Theory Component ATC Neither SI-350A or SI-350B will open RO open both CNTMT Sump B supply to RHR pump valves

SI-350A

SI-350B RNO - GOTO ECA-1.1 Loss of emergency Coolant Recirculation ROLE: SM ROLE: WWC US crew brief REQUEST: WWC Respond to SI-350A REQUEST: Respond to SI-350A and SI-

Announce Crew Brief and SI-350B not working 350B not working

EAL RESPONSE: Will get people working on RESPONSE: Will get people working on o Under Evaluation the problem and inform the control room of the problem and inform the control room of

Recap Major Events any intended actions. any intended actions. o LOCA DELAY: One Minute DELAY: None

On going Recovery Actions o Transition to ECA-1.1

Technical Specifications o Evaluate later time

Comments

End Crew Brief US Transition to ECA-1.1 KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ECA-1.1 Loss of Emergency Coolant Recirculation US/RO (CAS) check RHR pumps not cavitating ROLE: SM . . . ROLE: WWC/TSC/ED/NAO . . . US inform the SM to dispatch personnel as REQUEST: Dispatch personnel as REQUEST: Dispatch personnel as necessary to restore Emergency Coolant necessary to restore Emergency Coolant necessary to restore Emergency Coolant Restoration equipment Restoration equipment Restoration equipment RESPONSE: Personnel are dispatched. RESPONSE: Personnel are dispatched.

DELAY: None Note: No action will be successful prior to Note: No action will be successful prior to the completion of the scenario.

the completion of the scenario. DELAY: None US/RO check if RHR system should be de-ROLE: AO pressurized:

REQUEST: Check status of MCC breakers

Check Containment Sump Supply to for SI-350A and SI-350B: RHR any closed

SI-350A - MCC-52F Ext(1CF) o SI-350A

SI-350B - MCC-62B(B4) o SI-351A o SI-350B RESPONSE: Acknowledge request.

o SI-351B After DELAY, report that breakers are

Check RHR Pump Discharge tripped.

pressure > 450 psig DELAY: 7 minutes RNO GO TO next step (Step 4)

KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/RO check idle RWST/SI train aligned for sump recirculation:

Verify idle train containment sump B supply to RHR pump OPEN o SI-350A o SI-351A o SI-350B o SI-351B RNO - GO TO Step 6 US/RO Check containment cooling

Ensure CFCU All Running

Ensure CFCU SW return isolation valves all open o SW-903A o SW-903B o SW-903C o SW-903D

Check Shroud cooling bypass valves all open o SW-901A-1 o SW-901B-1 o SW-901C-1 o SW-901D-1

(CAS) Check containment pressure Has remained below 4 psig RNO

Ensure all CFCU Emergency Discharge Dampers open o RBV-150A o RBV-150B o RBV-150C o RBV-150D KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS This step directs the operator to another US/RO (CAS) Check RWST level > 4%

step in the procedure and is different from RNO the fold out page criteria. The step of the IF RWST level < 4%, Go To Step which procedure directs the team to stop all directs stopping of all pumps taking a pumps taking suction from the RWST.

suction from the RWST (Step 30)

Note: The CAS step in E-1 for stopping US/RO Determine Containment Spray ICS pumps has been applicable to this requirements point. IF containment pressure is less than

Check ICS pump suction aligned to 4 psig the ICS pumps should have stopped. RWST

Determine number of ICS pumps WOG ERG based critical tasks lists makeup required from the table to the RWST and minimize RWST outflow as a critical task. For this scenario the time RWST CNTMT Fan ICS line does not extend long enough to meet level Press Coil pumps all the requirements for a critical task, but Units required this task is significant. > 46 psig -------- 2 0 or 1 2 For this scenario makeup flow established Greater 23 - 46 to RWST prior to RWST level reaching 4% Than 2 or 3 1 psig and tripping pumps is critical. This means 37%

4 0 two parts to the critical task that are inter connected - Stopping/Reducing number of < 23 psig -------- 0 ICS pumps and establishing makeup to the RWST. > 46 psig -------- 2 Between 0 or 1 1 23 - 46 4% and psig >2 0 37%

< 23 psig -------- 0

< 4% ------------- --------- 0 KPS-SEG2-L-RO/SRO-A- 01242011-113

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SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

Check running ICS pumps equal to greater to number required WOG ERG based critical tasks lists makeup US direct RO to refill the RWST per NOP-to the RWST and minimize RWST outflow CVC-001- US continue with this procedure as a critical task BOP (CAS) Maintain intact SG levels

Maintain SG levels 5% [13%] - 50%

BOP initiate RCS cooldown to cold shutdown

Cooldown rate < 100ºF/hr

Dump Steam RO check ECCS Pump Status

SI pumps any running OR

RHR pumps any running in SI injection mode RO reset SI RO establish one train of SI flow

Check SI pumps - only one running

Check RCS pressure less than 270 psig [300 psig]

Check RHR pumps - only one running KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 73 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO verify NO backflow from RWST to Containment sump Subcooling at this should not meet RO check if one RXCP should be started requirements for starting a RXCP

Both RXCPs stopped

Check RCS subcooling based on core CETs o > 15ºF [60ºF]

o Critical Task: Maintaining RWST >4% US/RO (CAS) check if SI can be terminated during the scenario

Check RCS subcooling based on Safety Significance: Throttling of SI-7A CETs > 65ºF [110ºF]

minimizes flow from the RWST and RNO prolongs core cooling. The scenario is designed so that by reducing outflow from

Establish minimum injection flow the RWST by stopping ICS pumps or one o Determine minimum required train of SI, and making up to the RWST will injection flow from prevent the RWST level from lowering to < Attachment A 4% prior to throttling SI-7A and prolong core o Stop any RHR pump running cooling and minimizing core damage. The in SI injection mode acts of minimizing outflow from the RWST o Open SI-208 and SI 209 and establishing makeup to the RWST are part of a critical task to maximize length of o Throttle SI-7A to establish time the RWST volume is available for core required SI injection flow cooling. (Critical Task)

Cue: Loss of containment sump recirculation as indicated by SI-350A and SI-350B not opening.

Measurable Performance Indicator:

RWST maintained > 4% during the scenario with the scenario end point being throttling KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 74 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS SI-7A Performance Feedback: Response from NAO that to acknowledge throttling SI-7A.

The Scenario may be stopped after direction is given to throttle SI-7A at the direction of the lead evaluator Transition step from earlier when asked if RO Stop all Pumps taking a suction from RWST level > 4% the RWST and PLACE in PULLOUT

SI pumps

RHR pumps

ICS pumps

Charging pumps KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 75 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

6. SCENARIO END: a. FREEZE simulator at direction of floor instructor.

b. STOP Data Capture via SmartTest (optional)

7. POST-SCENARIO:

a. ENSURE simulator problems encountered during the scenario are documented IAW site specific process.

b. ENSURE training attendance is documented on, Training Attendance Report.

KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 76 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

INPUT

SUMMARY

Delay Ramp Event Severity Final Relative Description Time Time Trigger Or Value Value Order MALFUNCTIONS RX213 PT-468 S/G A Pressure (A PORV and SWGLC Dens) 00:00:00 00:00:30 1 0 1400 1 RC08 Reactor Coolant System Leaks 00:00:00 00:05:00 11 0 1.4 2 CH04A Instantaneous Overcurrent CFCU A 00:01:20 00:00:00 13 FALSE TRUE 3 CH04B Instantaneous Overcurrent CFCU B 00:01:30 00:00:00 13 FALSE TRUE 3 RC03A Loss of Coolant Accident - Hot Leg (1A) 00:00:00 00:03:00 13 0 5 3 NI05A Improper Power Range Channel Response (N41) 00:00:00 00:00:00 None 1.2 1.2 preload CH04C Instantaneous Overcurrent CFCU C 00:01:34 00:00:00 13 FALSE TRUE 3 CH04D Instantaneous Overcurrent CFCU D 00:01:38 00:00:00 13 FALSE TRUE 3 REMOTE FUNCTIONS RM101 R-21 Alignment 00:00:00 00:00:00 None Cntmt Cntmt setup RP181 466B FWF>SF NORM 00:00:00 00:00:00 3 norm trip request RP182 466C FWF<SF NORM 00:00:00 00:00:00 5 norm trip request RP186 468B Low Pressure 00:00:00 00:00:00 7 norm trip request RP185 468A LO/LO SAL NORM 00:00:00 00:00:00 9 norm trip request SI119 SI-9A Breaker 00:00:00 00:00:00 15 off on request SI117 SI-20A Breaker 00:00:00 00:00:00 15 off on request SI-115 SI-11A Breaker 00:00:00 00:00:00 15 off on request KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 77 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

INPUT

SUMMARY

Delay Ramp Event Severity Final Relative Description Time Time Trigger Or Value Value Order SI118 SI-20B Breaker 00:00:00 00:00:00 15 off on request SI116 SI-11B Breaker 00:00:00 00:00:00 15 off on request RP133 405C - Over Temperature Trip 00:00:00 00:00:00 None trip trip preload RP134 405D - Rod Stop 00:00:00 00:00:00 None trip trip preload OVERRIDES MCB DI-46211-CLOSE CVC-211 CLOSE 00:00:00 00:00:00 None NORM NORM preload MCB DI-46211-OPEN CVC-211 OPEN 00:00:00 00:00:00 None TRIP NORM preload MCB DI-46214-OPEN CVC-212 OPEN 00:00:00 00:00:00 None TRIP NORM preload MCC DI-46355-CLOSE SI-350A 00:00:00 00:00:00 None TRIP NORM preload MCC DI-46355-OPEN SI-350A 00:00:00 00:00:00 None NORM NORM preload MCC DI-46356-CLOSE SI-350B 00:00:00 00:00:00 None TRIP NORM preload MCC DI-46356-OPEN SI-350B 00:00:00 00:00:00 None NORM NORM preload MCC DI-46331-OPEN CC-610A 00:00:00 00:00:00 28 ON ON cond MCC DI-46332-OPEN CC-610B 00:00:00 00:00:00 28 ON ON cond KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 78 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

Blind Triggers Event #2 Event Action: hwzrcrrcpb==0.0 Command: imf rc03a 100 00:02:00 5 Raises LOCA size when RXCPs are Tripped Event #25 Event Action: hwzfww1084==1.0 Command: dor di-46331-open Deletes override when FW-7A closed Event #27 Event Action: hwzfww1084==1.0 Command: dor di-46332-open Deletes override when FW-7A closed Event #28 Event Action: an:47021a==1.0 Command:

Activate trigger 28 when SI Train A activates Event #30 Event Action: hwzcvg214==1.0 Command: dor di-46214-open Deletes override of cvc-212 open when cvc-212 is taken to close KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 79 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B SIMULATOR SCENARIO DEVELOPMENT CHECKLIST Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

Yes No

1. The scenario contains objectives for the desired tasks and relevant Human Performance Tools.

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

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

4. Turnover information includes a Daily At Power Risk Assessment provided by the PRA Group. - Done by the Crew during validation

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

6. The Scenario Guide includes responses for all communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices.

7. The scenario includes related industry experience. Not Required for Evaluations

8. 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.

9. Any identified Critical Tasks possesses the following elements (NUREG-1021):

Essential to safety with adverse consequences or significant degradation,

Cue(s) prompt the Operator to respond.

Defined and measurable performance indicators.

Performance feedback.

The use of N/A is allowed for item 9 only if this is NOT an evaluated scenario.

10. Technical Specifications including Limiting Conditions for Operation, reactivity briefings, and Emergency-Plan entries are addressed as appropriate.

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

KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 80 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B SIMULATOR EXERCISE 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.

Yes No

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

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

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

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

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

6. Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence?

7. 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.

8. Any identified Critical Tasks possesses the following elements (NUREG-1021):

Essential to safety with adverse consequences or significant degradation,

Cue(s) prompt the Operator to respond.

Defined and measurable performance indicators.

Performance feedback.

The use of N/A is allowed for item 8 only if this is NOT an evaluated scenario.

Discrepancies noted (Check none or list items in comments field) None Comments: None Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 81 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B_

Applied & Implemented All Information Passed on to All Any Knowledge or Performance Corrective Actions if TS/TRM (PP-1) Identified All Applicable Correctly Crew Members (i.e., briefs) Deficiencies Required As Time Allowed TS 3.3.1 for table 3.3.1-1 Function Yes No Yes No Yes No 15 TS 3.3.2 for table 3.3.2-1 Function Yes No Yes No Yes No 1,e TS 3.4.13 Yes No Yes No Yes No EALs All Information Passed on to All Any Knowledge or Performance Corrective Actions if Identified All Applicable Classified & Notified Timely (EP Group) Crew Members (i.e., briefs) Deficiencies Required FA1 Yes No Yes No Yes No Any Knowledge or Performance Corrective Actions if Procedure Compliance (PP-3) Applied & Implemented Correctly As Time Allowed Deficiencies Required NOP-TB-001 Yes No NOP-FW-001 Yes No AOP-GEN-001 Yes No AOP-MISC-001 Yes No AOP-RM-001 Yes No NOP-CVC-001 Yes No AOP-RC-001 Yes No E-0 Yes No E-1 Yes No ES-1.3 Yes No ECA-1.1 Yes No

Simulator Exercise Guide Job Aid Page 82 of 82 SEG#_ROI/SRO-06-SE-SC2_ Rev ; _B Any Knowledge or Performance Corrective Actions if Human Performance Errors (PP-2) Identify All HU Errors or Potential HU Errors Deficiencies Required Questioning Attitude Stop When Unsure Self Checking Procedure Use and Adherence Clear Communications Place Keeping Verification Practices Identify All Operator Fundamental Errors Or Potential Operator Fundamental Any Knowledge or Performance Corrective Actions if Operator Fundamentals Errors Deficiencies Required Teamwork Effectiveness (T)

High Standards for Controlling Plant Evolutions (H)

Indications and Plant Parameters Monitored Closely (I)

Natural Bias for Conservative Approach to Plant Operations (N)

Knowledge of Plant Design and Theory (K)

KPS-SEG2-L-RO/SRO-A- 01242011-113

Simulator Exercise Guide Job Aid Page 1 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SITE: Kewaunee Power Station PROGRAM: RO/SRO License Training PROGRAM No. ROI/SRO-TP COURSE: 2011 NRC License Exam Course #: ROI-06-SE-SC3 SOI-06-SE-SC3 Total Time 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Prepared by: Andrew Fahrenkrug /s 01/24/2011 Printed Name Instructors Signature Date Reviewed by: Jeffrey A. Hinze /s 01/24/2011 (Optional) Printed Name Simulator Development Checklist Date Instructor Signature Reviewed by: Andrew Fahrenkrug /s 01/19/2011 (Optional) Printed Name Simulator Validation Checklist Date Signature Approved by: Randy Hasting /s 01/24/2011 Printed Name Training Supervisor Date Approved by: Mark Gooslbey /s 01/25/2011 Printed Name Facility Representative Date KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 2 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B Appendix D Scenario Outline Form ES-D-1 Facility: Kewaunee Power Station Scenario No.: 3 Op-Test No.: 1 Examiners: Operators: SRO: .

ATC: .

BOP: .

Initial Conditions: 75% power EOL Equilibrium Xenon. RCS boron concentration is 162 ppm. RCS Tave is 557ºF. Generator load is 423 MWe gross. AS-31/AS-35 R-11 & R-12 Sample Return Aligned to Containment, PR-1A PRZR PORV Block Valve is closed with power maintained due to PR-2A seat leakage, 2 inch containment vent is in progress per NOP-RBV-002 section 5.6, Turnover: Maintain 75% Power, TS 3.4.11 (Reactor Coolant System Pressurizer Power Operated Relief Valves) Condition A One or more PORVs inoperable and capable of being manually cycled. Required Action A.1 is to close and maintain power to the associated PORV Block Valve with a completion time of one hour (Completed).

Event Malf. Event Event No. No. Type* Description Pre- PR-2A CAUTION tagged CLOSED due to seat leakage. PR-Load 1A closed TS LCO3.4.11, ACTION A.1.

DI-46230-CLOSE Pre- ON CVC-440, Emergency Boration to Charging Pumps, fails ATC - C Load DI-46230- closed OPEN OFF Pre- SI05B &

SI05A ATC - C Failure of SI pumps to Auto Start Load RC10B Pressurizer PORV PR-2B fails partially open resulting in 1 ATC - C 10% PRZR pressure decreasing.

SG tube leak of approximately 15 gpm in SG B entered over SG03B ATC - R 2 5 minutes 30 5:00 BOP - N Crew initiates a power reduction to 45% power DI-46230-CLOSE ON CVC-440, Emergency Boration to Charging Pumps, fails 3 DI-46230- ATC - C closed OPEN OFF KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 3 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B MS03B 1.0 B steam line leak outside Containment. EO calls in. - ATC ATC, 4 BOP - M the Controls Trip the Reactor and BOP Initiate Main Steam 3:00 Isolation Steam Generator B Safety Opens when the crew closes the 5 MS04B BOP-C MS-1B - Operator Isolate Feed Flow to Steam Generator B SI05A, 6 SI05B ATC-C Failure of Safety Injection Pumps to Auto Start

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 4 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO 1-3 OVERVIEW EVENT DESCRIPTION PR-2B, PRZR PORV, will fail partially open resulting in a decrease in PRZR pressure as steam is released to the PRT. Annunciator 47042-A, PRESSURIZER PORV OPEN will alarm and dual red/green indication will show for PR-2B. The ATC Operator will perform the actions of AOP-GEN-001, Immediate Operator Actions, Attachment A Pressurizer PORV Open. With PRZR pressure less than 2315 psig, the operator will check the PORVs closed and take control switch for PR-1B, PRZR PORV Block Valve, to CLOSE, checking the valve does close. The operator will also take PR-2B control switch to CLOSE - PR-2B will NOT close if the operator takes the switch to CLOSE.

Technical Specification: Closing PR-1B before failure to close PR-1B causes a transition E-1 is a critical Task

3.4.11 Pressurizer Power Operated Relief Valves (PORVs) Condition B One 1 PORV inoperable and not capable of being manually cycled Required Action B.1 Close associated block valve with a completion time of one hour and Required Action B.2 Remove power from associated block valve with a completion time of one hour and Required Action B.3 Restore PORV to OPERABLE status with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months If RCS pressures lowers to less than 2217 psig control board or 2219 psig computer indication

3.4.1 RCS Pressure Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Condition A One or more RCS DNB parameters not within limits Required Action A.1 Restore RCS DNB parameter(s) to within limit with a completion time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

3.4.13 RCS Operational Leakage Not Met while PORV open-Enter and Exit Condition A A SG tube leak of approximately 15 gpm occurs in SG B ramped in over 5 minutes. SG B recorder will show an increase in N16 count rate as leak develops, and a PPCS alarm actuating TLA-15, RMS ABOVE NORMAL.

The crew will respond by entering AOP-RC-004, Steam Generator Tube Leak, check that the leakage is within charging system capability to maintain PRZR level > 3%.

Charging flow will be adjusted to maintain PRZR level on program value. The crew will compare R-15 reading to the Chemistry estimated 100 GPD from CY-KW-059-003. With leakage greater than 100 GPD as indicated by R-15 count rate, the crew will check R19 (SG Blow Down monitor) has increased > 5% from background, and then initiate 2 ACTION LEVEL 3 actions. A load decrease of 3%/min to

< 45% power to ensure the unit is less than 50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of leak initiation.

The leaking SG will be identified and SG blow down isolated. The crew will direct actions to minimize secondary system contamination. At 45% power, the (un)loading rate may be adjusted to 1%/min provided that MODE 3 can be achieved within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months of leak initiation.

Technical Specification:

TS 3.4.13 RCS Operational LEAKAGE Condition B Primary to secondary LEAKAGE not within limit Required Action B.1be in MODE 3 with a completion time of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and Required Action B.2 be in MODE 5 with a required completion time in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 5 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B During the load back down while performing actions of AOP-GEN-002, Rapid Power Reduction, the ATC operator will initiate a boration of 50 gallons of boric acid using the emergency boration flow path (Attachment A). When the operator attempts to open CVC-440, Emergency Boration to Charging Pumps, the valve fails to open. The operator will then initiate a boration path using the normal boration flow path (Step E5) by setting 3

the Boration Totalizer to 50.0, setting CVC-403 controller to the desired flow rate, placing the Reactor Makeup Mode Selector to BORATE, and then placing the Reactor Makeup Control switch to START. When the 50 gallons have been added, the ATC operator will restore the respective Makeup control switches to AUTO and START.

Subsequent borations will be accomplished using Attachment F.

When power has been reduced by at least 5% and not greater than 10%, a steam line leak outside containment will occur on the B steam line header. The leak is NOT expected to actuate any protective or safeguards function. The crew should recognize 4

condition and determine a reactor trip is required as directed by AOP-GEN-001, followed by closing the MSIVs.

The crew will perform immediate actions of E-0:

The BOP will initiate a main steam isolation and the crew will complete the immediate actions of E-0, Reactor Trip or Safety Injection. When MS-1B, Main Steam Isolation 5

closes, Steam Generator B safety will fail open. The BOP will then isolate feed flow to Steam Generator B per the foldout page criteria.

Safety Injection will automatically initiate. The safety injection pumps will fail to automatically start. The ATC operator will start both safety injection pumps per Attachment A of E-0, Reactor Trip or Safety Injection.

6 The crew will continue in E-0 and then transition to E-2, Faulted Steam Generator Isolation the scenario will end after the crew has completed the steps in E-2 to isolate all steam flow from the faulted Steam Generator KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 6 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B REQUIREMENTS Goal of Training: Evaluate crew response and performance for the following events:

Failed Open PRZR PORV

SG Tube Leak occurs in SG B

Rapid Power reduction required by the SG Tube Leak

During the power reduction, Emergency Boration path will function properly, the normal path will be used.

A steam line leak from the B steam header outside of containment.

Failed open SG safety

Safety Injection Pumps Fail to Auto Start Learning Objectives: While responding as the RO/BOP satisfactorily MEET the performance requirements in TR-AA-400 for the following competencies

a. Understand and Interpret Annunciator and Alarm Signals

b. Diagnose Events and Conditions based on Signals and Reading

c. Understand Plant and System Response

d. Comply with and Use Procedures and Technical Specifications

e. Operate the Control Board

f. Communicate and Interact with Other Crew Members (RO4-06-SED01.002) ROI-06-SE-SC03.001 / SOI-06-SE-SC03.001 While responding as the US satisfactorily MEET the performance requirements in TR-AA-400 for the following competencies

a. Understand and Interpret Annunciator and Alarm Signals

b. Diagnose Events and Conditions based on Signals and Reading

c. Understand Plant and System Response

d. Comply with and Use Procedures and Technical Specifications

e. Operate the Control Board

f. Communicate and Interact with Other Crew Members

g. Direct Shift Operations

h. Comply with and Use Technical Specifications (RO4-06-SED01.003) SOI-06-SE-SC03.002 As the US DETERMINE the appropriate event classification in accordance with EPIP-AD-02,Emegency Classification Determination. (This objective will be completed at the end of the scenario and may be waived at the lead evaluators discretion.) SOI-06-SE-SC03.003 Prerequisites: Enrolled in current ILT class and recommended by station management to take an NRC license exam.

KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 7 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B Training Resources: Simulator KPS Exam Team Member NRC Examiners

References:

KPS Technical Specifications (ITS)

KPS Technical Requirements Manual (TRM)

OP-AA-100 Conduct of Operations OP-AP-300 Reactivity Management OP-AP-104 Emergency and Abnormal Operating Procedures NOP-EHV-001, 4160V AC Supply and Distribution System Operation NOP-CVC-001, Boron Concentration Control NOP-CVC-002, Charging And Volume Control AOP-GEN-002, Rapid Power Reduction NOP-RBV-002, Reactor Building Vent System Cold Operation and Making Releases NOP-HD-001 Heater and Moisture Separator Drain and Bleeder Steam System SP-32-113 Gaseous Radioactive Effluents Reports for Continuous Releases CY-KW-059-003, Primary to Secondary Leak Rate Date ARP 47011-B, RADIATION INDICATION HIGH ARP 47012-B, RADIATION INDICATION ALERT ARP-47033-35, TLA-15 RMS ABOVE NORMAL ARP-47041-B, Pressurizer Safety Disch Temp high ARP-47042-A, Pressurizer PORV OPEN ARP-47042-B, Pressurizer PORV Discharge Temp High ARP-47043-B, Pressurizer Relief Tank Abnormal ARP-47043-C, Pressurizer Control Press Abnormal ARP-47043-D, Pressurizer Pressure Low AOP-RC-004, Steam Generator Tube Leak AOP-GEN-001, Operator Immediate Actions AOP-RM-001 Abnormal Radiation Monitoring E-0, Reactor Trip Or Safety Injection E-2 Faulted Steam Generator Isolation KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 8 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B Commitments: Per Outline submitted to NRC for 2011 Operating exam Evaluation Method: Dynamic Simulator Historical Record: Initial Issue Rev B Added failure of PRZR PORV open Added reference to SG safety in Goal of training Updated PRA information Operating Experience: Not required for evaluations Related PRA Initiating Event with Core Damage Frequency:

Information: Total CDF/LERF (3.6E-5/yr)/(1.6E-06/yr)

Transient with MFW Available CDF/LERF 10%/2.8%

High Energy Line Break CDF/LERF 6%/2.2%

Stuck Open PORV CDF/LERF 3%/

Important Components:

System CDF Importance Rank LERF Importance Rank SI 8th 3rd Important Operator Actions CDF

Close PRZR PORV block valve to isolate Stuck Open PORV LERF - None KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 9 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: A OVERVIEW INITIAL CONDITIONS:

1. Standard IC-16 (73% End of Life equilibrium Xe)

2. Containment vent using the Train B Post-LOCA path is in progress to reduce Containment pressure

3. The following equipment is OOS:

PR-2A PORV has seat leakage and PR-1A, PORV Block Valve, is closed and energized satisfying LCO 3.4.11, Condition A.

4. R-11/12 Sample Return is aligned to the containment.

SEQUENCE OF EVENTS:

Event 1: PR-2B fails partially open PR-2B, PRZR PORV, will fail partially open resulting in a decrease in PRZR pressure as steam is released to the PRT. Annunciator 47042-A, PRESSURIZER PORV OPEN will alarm and dual red/green indication will show for PR-2B. The ATC Operator will perform the actions of AOP-GEN-001, Immediate Operator Actions, Attachment A Pressurizer PORV Open. With PRZR pressure less than 2315 psig, the operator will check the PORVs closed and take control switch for PR-1B, PRZR PORV Block Valve, to CLOSE, checking the valve does close. The operator will also take PR-2B control switch to CLOSE - PR-2B will NOT close if the operator takes the switch to CLOSE.

Technical Specification: Closing PR-1B before failure to close PR-1B causes a transition E-1 is a critical Task

3.4.11 Pressurizer Power Operated Relief Valves (PORVs) Condition B One PORV inoperable and not capable of being manually cycled Required Action B.1 Close associated block valve with a completion time of one hour and Required Action B.2 Remove power from associated block valve with a completion time of one hour and Required Action B.3 Restore PORV to OPERABLE status with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months If RCS pressures lowers to less than 2217 psig control board or 2219 psig computer indication 3.4.1 RCS Pressure Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Condition A One or more RCS DNB parameters not within limits Required Action A.1 Restore RCS DNB parameter(s) to within limit with a completion time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.4.13 RCS Operational Leakage Not Met while PORV open-Enter and Exit Condition A KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 10 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: A Event 2: 15 gpm Tube Leak in the B Steam Generator.

A SG tube leak of approximately 15 gpm occurs in SG B ramped in over 5 minutes. SG B recorder will show an increase in N16 count rate as leak develops, and a PPCS alarm actuating TLA-15, RMS ABOVE NORMAL.

The crew will respond by entering AOP-RC-004, Steam Generator Tube Leak, check that the leakage is within charging system capability to maintain PRZR level > 3%. Charging flow will be adjusted to maintain PRZR level on program value. The crew will compare R-15 reading to the Chemistry estimated 100 GPD from CY-KW-059-003. With leakage greater than 100 GPD as indicated by R-15 count rate, the crew will check R19 (SG Blow Down monitor) has increased > 5% from background, and then initiate ACTION LEVEL 3 actions. A load decrease of 3%/min to < 45% power to ensure the unit is less than 50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of leak initiation.

The leaking SG will be identified and SG blow down isolated. The crew will direct actions to minimize secondary system contamination. At 45% power, the (un)loading rate may be adjusted to 1%/min provided that MODE 3 can be achieved within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months of leak initiation.

Technical Specification:

TS 3.4.13 RCS Operational LEAKAGE Condition B Primary to secondary LEAKAGE not within limit Required Action B.1be in MODE 3 with a completion time of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and Required Action B.2 be in MODE 5 with a required completion time in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Event 3: CVC-440, Emergency Boration to the Charging Pumps fails to open.

During the load back down while performing actions of AOP-GEN-002, Rapid Power Reduction, the ATC operator will initiate a boration of 50 gallons of boric acid using the emergency boration flow path (Attachment A). When the operator attempts to open CVC-440, Emergency Boration to Charging Pumps, the valve fails to open. The operator will then initiate a boration path using the normal boration flow path (Step E5) by setting the Boration Totalizer to 50.0, setting CVC-403 controller to the desired flow rate, placing the Reactor Makeup Mode Selector to BORATE, and then placing the Reactor Makeup Control switch to START. When the 50 gallons have been added, the ATC operator will restore the respective Makeup control switches to AUTO and START. Subsequent borations will be accomplished using Attachment F.

Event 4: Steam Leak from steam header B When power has been reduced by at least 5% and not greater than 10%, a steam line leak outside containment will occur on the B steam line header. The leak is NOT expected to actuate any protective or safeguards function. The crew should recognize condition and determine a reactor trip is required as directed by AOP-GEN-001, followed by closing the MSIVs.

The crew will perform immediate actions of E-0 Event 5: SG B Safety Fails Open when MSIVs Closed The BOP will initiate a main steam isolation and the crew will complete the immediate actions of E-0, Reactor Trip or Safety Injection. When MS-1B, Main Steam Isolation closes, Steam Generator B safety will fail open. The BOP will then isolate feed flow to Steam Generator B per the foldout page criteria.

Event 6: Failure of Safety Injection pumps to automatically start Safety Injection will automatically initiate. The safety injection pumps will fail to automatically start. The ATC operator will start both safety injection pumps per Attachment A of E-0, Reactor Trip or Safety Injection.

The crew will continue in E-0 and then transition to E-2, Faulted Steam Generator Isolation the scenario will end after the crew has completed the steps in E-2 to isolate all steam flow from the faulted Steam Generator KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 11 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: A Malfunctions:

Before EOP Entry:

1. PR-2B fails partially open

2. Steam Generator Tube Leak

3. CVC-440 Emergency Boration to the Charging Pumps fails closed

4. Steam Line Leak, B Steam Header After EOP Entry:

1. SG B Safety Fails Open

2. SI Pumps fail to auto start Abnormal Events:

1. PR-2B Open

2. Steam Generator Tube Leak

3. Steam Leak Out side Containment Major Transients:

1. SG B Safety fails open during main steam isolation resulting in Safety Injection Critical Tasks Critical Task: Closing PR-1B before failure to close PR-1B causes a transition E-1 for loss of RCS inventory through the PORV a) SAFETY SIGNIFICANCE:

i) Failure to close the PRZR PORV Block valve under the scenario conditions constitutes mis-operation or incorrect crew performance which leads to degradation of RCS barrier to fission product release. In this case the RCS fission product barrier can be restored to full integrity by closing PR-1B. Failure of the crew to close PR-1B represents a Demonstrated inability by the crew to take an action or combination of actions that would prevent a challenge to plant safety.

b) CUE:

i) PR-2B valve position indicator, Annunciator PORV OPEN, Decreasing PRZR Pressure, PRT Level and Pressure increasing c) MEASURABLE PERFORMANCE INDICATOR:

i) Closing PR-1B before failure to close PR-1B causes a transition E-1 due to loss of RCS inventory through PR-1B d) FEEDBACK:

i) PR-1B indicates Closed, PRZR Pressure stabilizes and then increases.

WOG Critical Task ECA-0.0 - - A/ E - M CRITICAL TASK: Isolate feed flow to faulted Steam Generator B by the completion of the Step in E-2 requiring isolation of feed flow a) SAFETY SIGNIFICANCE:

i) Failure to isolate feed flow to the faulted steam generator that can be isolated causes a challenge KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 12 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: A to CSFs beyond those irreparably introduced by the scenario conditions b) CUE:

i) Steam Flow indicated on B Steam Header with MS-1B closed, Steam Generator B pressure lowering in an uncontrolled manner.

c) MEASURABLE PERFORMANCE INDICATOR:

i) AFW-2B closed and AFW-10B or AFW-10A closed by completion of Step 4 of E-2 d) PERFORMANCE FEEDBACK:

i) No feed water flow indicated on AFW Header B KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 13 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: A TASKS Task Number Task Title SRO Tasks:

1190190302 Apply Technical Specifications During Plant Operations 1190070502 Coordinate the Implementation of the IPEOPs Demonstrate an understanding of the responsibility and requirements for the Control 1190330302 Room Supervisor A030010402 Perform a Rapid Power Reduction RO Tasks:

0540060101 Change Turbine and Generator Load 0360240401 Respond to a Pressurizer PORV Open Annunciator 0350240101 Control RCS Boron Concentration by the use of Boration 1190250301 Respond to a Steam Generator Tube Leak E000010501 Respond to a Reactor Trip Condition with Safety Injection A030010402 Perform a Rapid Power Reduction STA Tasks: N/A KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 14 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

1. INITIAL CONDITIONS:

Standard IC 16

Mode: 1

Exposure: 17000

Power: 75.3%

Boron: (CB): 162 ppm

Temperature: 564.8ºF

Pressure: 2235 psig

Xenon: Equil

Rods: D170

Generator: 452 Mwe

Thermal Power 1347.5 MWth KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 15 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

2. SIMULATOR SETUP:

RESET to IC# 16 and go to run

Align R-21 to containment using remote The following forms are needed during the RM101.

scenario and are to be placed in the booth.

ENSURE R-23 PROTECTED TRAIN placard is in place below the R-23 drawer.

No Additional Material Need For Booth

POSITION AS-31/AS-35, R-11 and R-12 Sample return to return to the containment.

Operator

ALIGN Containment Vent 2 path:

PLACE Containment Dome Fan B to Shift Manager Status board information START Equipment OOS

STOP Containment Dome Fan A and PLACE in AUTO PR-2A excessive seat leakage

OPEN LOCA-2B, Post-LOCA Hydrogen Cntmt Vent Isol B TS 3.4.11 (Reactor Coolant System

OPEN LOCA-100B, Post-LOCA Hydrogen To Recombiner B Pressurizer Power Operated Relief Valves)

Condition A One or more PORVs

PLACE PR-1A to CLOSE, and PLACE clearance status tag inoperable and capable of being manually cycled. Required Action A.1 is to close

OPEN and Run CAEP file. ROI-06-SE-SC3-and maintain power to the associated preload.cae. After file has run for one minute close CAE file.

PORV Block Valve with a completion time of one hour (Completed).

Verify the Instructor Station Summary IAW instructions at the beginning of the input summary in this SEG

Second verification of the Instructor IAW instructions at the beginning of the input summary in this SEG

Start SmartTest using the SmartTemplate for NRC Exam.xlt file.

ENSURE Job Aid 04-009, Simulator Exam/EP Drill Setup and Cleanup adequate to support exam by COMPLETING ATTACHMENT 1, Simulator Setup Exams/EP Drill, or ATTACHMENT 2, Reset KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 16 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Exam/EP Drill, as appropriate Remarks Protected train = A Risk CDF/LERF= Green SPER / WRs None GENERAL Consecutive days of operation ___490____

G-1 Closed (indicate date last month) JD xxx Burn up 17,000 MWD/MTU Sirens Lost Coverage % __0__

Sirens OOS __0__

RCS and Pressurizer boron = 162 ppm All other entries are standard KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 17 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

3. PRE-SCENARIO:

a. IF this is the first simulator scenario of the week, THEN review the Simulator Differences List with the crew.

a) IF this is the first simulator scenario of the week, THEN review the Simulator Differences List with the crew.

b) Provide crew with:

Turnover sheets and plant information

For containment vent, Provide copy of Data Sheet C, Containment Vent Log, from SP-32-113, Gaseous Radioactive Effluents Reports For Continuous Releases, with Month and Year filled-in, and Date, Start Time, RP Notified (Y) & Remarks (2 Vent) filled-in.

c) Cover Simulator Scenario Briefing Sheet in Job Aid 04-01 with the crew

Inform the crew that the Designated Exam Team Member will take response for the Shift Manager. They will acknowledge communications, but their acknowledgment does not mean agreement or disagreement.

KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 18 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS d) ENSURE the crew has been briefed IAW NUREG 1021 Appendix E (Simulator Test Guidelines) e) If allowed by the NRC Chief Examiner, Lead Exam Team Member will perform a Pre-Job brief per Job Aid 04-03.

4. TURNOVER: PROVIDE Shift Turnover (All) Walk down control boards~ 5 minutes Information.

After ~5 minute walk down of boards by the crew. Give the crew the shift.

Shift Direction:

Maintain current power until direction given by management to raise power

5. SCENARIO:

During the Scenario if asked as SM for EAL report that it is under evaluation KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 19 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 1: PR-2B PRZR PORV Fails Open Human Performance Tools: Procedure Compliance, Clear Communications Operator Fundamentals: Closely Monitoring Plant Conditions ATC-Component (Event May be Omitted if not required for At the direction of the lead evaluator Annunciators:

the evaluation) INSERT TRIGGER 1 and ENSURE that 47042-A, Pressurizer PORV OPEN malfunction RC10B is active with a value of 47042-B, Pressurizer PORV Discharge 10% Temp High Event may begin after the crew isolates the 47043-C, Pressurizer Control Press SW leak and TS has been addressed or at Abnormal the lead evaluators discretion. 47041-B, Pressurizer Safety Disch Temp high If the crew fails to close the PRZR Block 47043-B, Pressurizer Relief Tank Abnormal valve and the reactor trips and the crew 47043-D, Pressurizer Pressure Low performs the actions of E-O and SI is Board indications:

initiated then continue in Event 5. Initiating PRZR Pressure lowering Event 5 prior to taking the TD AFW pump to PR-2B indicates OPEN (Red Light LIT pullout Operator Fundamental: Closely Monitoring CREW diagnose PR-2B and take actions of Plant Conditions OP-KW-GEN-001 Attachment A Other ARP actions should be reviewed by the crew, actions are covered by AOP-GEN-001 KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 20 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS OP-KW-AOP-GEN-001, Immediate Operator Actions, Attachment A Human Performance: Clear RO Check PRZR Pressure > 2315 psig Communications, Procedure Compliance.

Critical Task: Closing PR-1B before RO Check Both PORVs -CLOSED failure to close PR-1B causes a transition E-1 RNO SAFETY SIGNIFICANCE:

STOP PORV Flow a) Failure to close the PRZR PORV

PLACE block valve control switch Block valve under the scenario for PR-1B to close (Critical Task) conditions constitutes mis-operation or incorrect crew performance which

PLACE Control switch for open leads to degradation of RCS barrier PORV PR-2B to CLOSE to fission product release. In this case the RCS fission product barrier can be restored to full integrity by closing PR-1B. Failure of the crew to close PR-1B represents a Demonstrated inability by the crew to take an action or combination of actions that would prevent a challenge to plant safety.

CUE:

a) PR-2B valve position indicator, Annunciator PORV OPEN, Decreasing PRZR Pressure, PRT Level and Pressure increasing MEASURABLE PERFORMANCE INDICATOR:

a) Closing PR-1B before failure to close PR-1B causes a transition E-1 b) FEEDBACK:

i) PR-1B indicates Closed, PRZR KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 21 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Pressure stabilizes and then increases.

WOG Critical Task ECA-0.0 - - A/ E - M ROLE: SM ROLE: WWC US Hold crew brief REQUEST: WWC to remove power from REQUEST: Remove power from PR-1B

Announce Crew Brief PR-1B RESPONSE: Acknowledge direction. After

EAL RESPONSE: Acknowledge direction to Delay insert TRIGGER 15 and report Power o Under Evaluation contact WWC. After Delay report that the Removed.

Recap Major Events WWC has been informed of request. Then DELAY: 13 minutes o PR-2B failed open contact booth and have complete action for removing power per direction in booth When insert Trigger 15 ENSURE lights for

Ongoing Recovery Actions block. PR-1B are NOT LIT o Remove Power from PR-1B

- 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months DELAY: 1 minutes

Technical Specifications o 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) Condition B One PORV inoperable and capable of being manually cycled Required Action B.1 Close associated block valve with a completion time of one hour and Required Action B.2 Remove power from associated block valve with a completion time of one hour and Required Action B.3 Restore PORV to OPERABLE status with a completion time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 22 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS o 3.4.1 RCS Pressure TS LCO 3.4.1 will apply if RCS pressure Temperature, and Flow lowers to less than 2217 psig control board Departure from Nucleate or 2219 psig computer indication. This is Boiling (DNB) Limits the COLR for DNB pressure limit identified Condition A One or more in TRM 2.11.2 RCS DNB parameters not within limits Required Action A.1 Restore RCS DNB parameter(s) to within limit with a completion time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Comments o LCO 3.4.13 RCS Leakage Condition A

End Crew Brief EVENT 2: 15 gpm Tube Leak in the B Steam Generator Human Performance Tools: Procedure Compliance, STAR, Clear Communications Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely Controlling Plant Evolutions Reactivity ATC Normal BOP The US may split the crew to perform both At the direction of the lead examiner insert Annunciators:

AO-RM-001, ARPs and AOP-RC-004 in a TRIGGER 3 and ensure that malfunction 47033-35 TLA-15 RMS Above Normal efficient manner SG03B is active and ramping to 30 over 5 minutes ARP 47011-B, RADIATION INDICATION Actions for Radiation Monitors are listed HIGH - Will Alarm as malfunction severity first then the actions of AOP-RC-004 rises ARP 47012-B, RADIATION INDICATION ALERT - Will Alarm as malfunction severity rises KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 23 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Indications PPCS Alarm for R-43 SG B N16 count rate goes up 1000 cps R-15 and R-19 count rates rising US Direct either RO or BOP to address ARP for TLA-15 (ARP-47012-B or 47011-B as applicable) 47033-35 TLA-15 RMS Above Normal, 47012-B Radiation Indication Alert OR 47011-B Radiation Indication High BOP/RO

[R-43]

ROLE: SM ROLE: RP Check alarm due to any of the following REQUEST: Inform RP of Rad Monitor REQUEST: Inform of Rad Monitor Alarms

R-15 Alarms and to survey the affected areas. and to survey the affected areas.

RESPONSE: Acknowledge request to RESPONSE: Acknowledge the Rad Monitor

R-19 contact RP and after delay report that RP Alarms & Surveys. And any other request

R-42 has been informed made by the crew.

R-43 DELAY: One Minute DELAY: None Operator should note that alarm is due to R-43 RNO AOP-RC-004 actions follow the actions of

Direct RP to survey the affected area AOP-RM-001 (next)

GO To AOP-RC-004

[R-15; R-19]

Check if the alarm is due to planned evolution KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 24 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: RP RNO ROLE: SM REQUEST: Inform of Rad Monitor Alarms

Perform the following:

REQUEST: Inform RP of Rad Monitor and to survey the affected areas.

o Determine affected channel(s)

Alarms and to survey the affected areas. RESPONSE: Acknowledge the Rad Monitor o Notify RP to assist in identifying and RESPONSE: Acknowledge request to Alarms & Surveys. And any other request isolating source contact RP and after delay report that RP made by the crew.

has been informed o GO TO AOP-RM-001 DELAY: None DELAY: One Minute AOP-RM-001 Abnormal Radiation Monitoring System The crew may already be performing AOP- (CAS) BOP Check if Personnel should be RC-004 actions when directed to perform evacuated AOP-RM-001 R-2 through R-10 in Alarm - NO BOP Radiation Monitors - None Failed downscale At this time R-15 and R-19 may not be Alert BOP Check operation of Each Affected or High. The operator should perform the Radiation Monitor Using Table 1 actions of AOP-RM-001 as time permits in Verify all applicable steps from table 1 conjunction with AOP-RC-004 and when below completed - Determine the affected alarms activate - Direction should be given Radiation Monitors.

by the US with evaluation of plant conditions Table 1 Affected GO TO Radiation Page STEP Monitor R-15 16 14 R-19 20 18 R-43 32 27 KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 25 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS BOP/RO Check radiation monitor operating Properly - Yes Expected that the US will be continuing with ROLE: EO BOP/RO Check Radiation Levels Normal AOP-RC-004 with the operator not REQUEST: Inform of Alarm and direct to RNO performing AOP-RM-001 or wait until back close HS-17 Perform the following:

down is started until addressing all the RESPONSE: Acknowledge the information actions in AOP-RM-001 given and direction to close HS-17. After [R-43]

Delay report that HS-17 closed

Consult with Chemistry and DELAY: 4 minutes Radiation Protection to determine sampling and surveying requirements

PERFORM AOP-RC-004 while continuing in this procedure

[R-15 / R-19]

If High Radiation alarm has occurred then perform the following:

Check the specific automatic actions of Attachment A have occurred o AR-6 Positioned to Duct o BT-2A Closed o BT-2B Closed o BT-3A Closed o BT-3B Closed o BT-31A Closed o BT-31B Closed o BT-32A Closed o BT-32B Closed o HS-17-1Closed

CLOSE Stm Supply to AHU-1 Humidifier, HS-17 KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 26 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

If radiation indication in Alert or High alarm range then perform AOP-RC-004 while continuing with this procedure AOP-RC-004 Steam Generator Tube Leak RO CHECK Reactor Trip NOT required

Pressurizer level > 3%

Reactor Critical

VCT Level > 5%

(CAS) RO CHECK Pressurizer Level Stable at or trending to program

INCREASE Charging pump speed and start second charging pump as necessary to establish maximum charging flow

POSITION Pressurizer heaters to ON

IF Pressurizer level continues to decrease Close all letdown isolation valves o LD-2 o LD-3 o LD-4A o LD-4B o LD-4C o LD-300

If PRZR Level continues to lower then perform the following o Manually Trip the Reactor o GO TO E-0 KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 27 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

CONTROL Charging flow as necessary to maintain Pressurizer level at program value RO Check Automatic Makeup Control

Ensure Makeup set at proper boric acid concentration

Ensure Reactor Makeup Mode Control Switch in AUTO

Check Reactor Makeup Control switch Red Light On

Check VCT Level Between 17% and 28%

ROLE: SM ROLE: Chemistry US DETERMINE SG Leak Rate REQUEST: Request that Chemistry create REQUEST: Request that Primary to

CHECK R-15 Primary to Secondary primary to secondary leak rate conversion secondary leak rate conversion graph be Leak rate conversion graph from graph be created and determine 100 gpd R- created and determine 100 gpd R-19 count CY-KW-059-003 19 count rate rate

CHECK leakage > 100 gpd RESPONSE: Acknowledge direction and RESPONSE: Acknowledge direction and report after delay 1 report that chemistry report after delay that the R-19 count rate informed and After Delay 2 report that for 100 gpd leak rate is 3192 CPM chemistry has determined that the R-19 DELAY: 4 minutes count rate for 100 gpd leak rate is 3192 CPM DELAY 1: 1 minutes DELAY 2: 4 minutes US/RO/BOP CHECK if entry into ACTION LEVEL 3 required

CHECK R-19 increase 5%

GOTO step 11(Action Level 3)

KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 28 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Actions for AOP-GEN-002 are scripted after ROLE: NAO (CAS) US/RO PERFORM ACTION LEVEL AOP-RC-004 REQUEST: Verify Priming Ejector Control 3 Actions Switch closed and in PULLOUT

DIRECT NAO to ensure Priming RESPONSE: acknowledge communication. Ejector Control Switch closed and Report back to the control room that place in PULLOUT Priming Ejector Control Switch closed and

PERFORM Task Brief using in PULLOUT Attachment A DELAY: 3 minutes

DISTRIBUTE field copies of procedures AOP-RC-004 and AOP-GEN-002 ROLE: NAOs - May request additional

MONITOR R-15 and R-19 at least personnel every 15 minutes REQUEST: Come to the Control For Brief

INITIATE Turbine and Generator RESPONSE: Report to the Control Room load decrease to Hot Shutdown After Delay o REDUCE load at 3%/min per DELAY: 2 minutes AOP-GEN-002 while continuing with AOP-RC-004 ROLE: SM ROLE: Chemistry US (CAS) IDENTIFY leaking Steam REQUEST: Chemistry Sample SGs and REQUEST: Sample SGs and perform an Generator perform an accelerated count rate accelerated count rate

DIRECT Chemistry to sample and RESPONSE: Acknowledge the direction RESPONSE: Acknowledge the direction perform accelerated count (The unit will trip prior to report for sample (The unit will trip prior to report for sample

SURVEY SG Blowdown CIC Ion results) and inform after delay that results) Exchange Resin Column for chemistry has been given the direction to DELAY: N/A indications sample SGs and perform and accelerated count DELAY: One Minute KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 29 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: RP ROLE: SM REQUEST: Survey SG Blowdown CIC Ion REQUEST: RP survey SG Blowdown CIC Exchanger Resin Column for indications Ion Exchanger Resin Column for indications above background using held radiation above background using held radiation monitor monitor RESPONSE: Acknowledge the direction RESPONSE: After Delay 1 report that RP is and after delay report that SG B Blowdown informed to perform the requested survey CIC Ion Exchanger column if greater than and after delay 2 report survey has been background and elevated and SG B Blowdown CIC Ion Exchanger DELAY: 5 minutes column if greater than background and elevated DELAY 1: 1 minutes DELAY 2: 5 minutes ROLE: SM ROLE: Chemistry BOP CHECK Steam Generator Blowdown REQUEST: Inform Chemistry Blowdown REQUEST: Blowdown Isolated isolated Isolated RESPONSE: Acknowledge blowdown

ENSUE SG Blowdown isolation RESPONSE: Acknowledge direction to isolated valves CLOSED inform chemistry that blowdown is isolated o BT-2A DELAY: N/A o BT-3A and then after delay report that chemistry has been informed that blowdown is o BT-2B isolated o BT-3B

NOTIFY Chemistry that Blowdown DELAY: One Minute is isolated The board operator may request the NAO to (CAS)US/BOP MINIMIZE Condenser perform local actions in one communication. Hotwell level If this occurs then acknowledge the

DIRECT NAO to close MU-2A direction and report the actions complete

POSITION MU-3B to FLUSH per the delay scripted for the actions

CHECK Hotwell level 25%

KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 30 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: NAO

DIRECT NAO to bypass makeup REQUEST: Close MU-2A water plant heater per NOP-MUP-RESPONSE: Acknowledge 001 communication. Report back to the control room after Delay INSERT TRIGGER 5 and report that MU-2A is CLOSED DELAY: 4 minutes ROLE: NAO REQUEST: Bypass makeup water plant heaters RESPONSE: Acknowledge communication.

Report back to the control room after delay minutes that the makeup water plant heater is bypassed DELAY: 6 minutes ROLE: NAO (CAS) US/BOP MINIMIZE Secondary REQUEST: Perform Step 15 of AOP-RC- System Contamination 004

DIRECT NAO to perform step 15 RESPONSE: Acknowledge direction and report after delay the action of Step 15 are complete DELAY: 9 minutes There are no triggers or simulator actions to perform for step 15 - Not Modeled in Sim KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 31 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS This should be the last step performed for ROLE: NAO (CAS) US/BOP ALIGN Heating Steam AOP-RC-004. If the Operator attempts to REQUEST: Perform Step 16of AOP-RC- System Drains to the Condenser Re-align the Bus for shutdown then delay 004

DIRECT NAO to perform step 16 the report of area clear until after the RESPONSE: Acknowledge direction and reactor trip. report after delay the action of Step 16 are complete DELAY: 3 minutes There are no triggers or simulator actions to perform for step 16 - Not Modeled in Sim US CHECK Back down Rate

Check Turbine power at 45%

o DO NOT CONTINUE until turbine power is less than 45%

AOP-GEN-002 Rapid Power Reduction US CHECK VPL Power Reduction required

Go to step 3 US DETERMINE recommended minimum power reduction rate

Load Reduction of 3%/min is directed from AOP-RC-004 (CAS) US/RO Check Control Rods in AUTO KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 32 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 3: Failure of CVC-440 to Operate Human Performance Tools: Procedure Compliance, STAR, Clear Communications, Verification Practices Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely Controlling Plant Evolutions Component - ATC Human Performance: Peer Checking- All (CAS) RO Perform boration reactivity calculations shall be peer

Check load reduction >5%

checked.

Perform rapid boration per Attachment.

E (Detailed Actions of Attachment E Scripted below) o Report CVC-440 failed to open o Initiate boration of 50 gallons using the Reactor Makeup System BORATE selection o Restore AUTO Makeup when boration complete AOP-GEN-002 Attachment E Actions for Rapid Boration Operator Should select 50 gallons based on RO Determine Amount Of boric Acid from initial conditions of EOL Using Table Below Burnup Boric Acid Gallons BOL (1500MWD/MTU) 30 MOL (10000MWD/MTU) 40 EOL (18250MWD/MTU) 50 KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 33 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamentals: Monitor plant RO Initiate Rapid Boration parameters

If Emergency Boration Flow Human Performance: Clear Totalizer is not available or Rapid Communications, Self Checking (STAR) Boration can be established then GO TO Step E5

OPEN CVC-440 - Identify will not open and report to US and then goto to Step 5 RO If rapid boration cannot be established then initiate boration as follows:

Set Boric Acid Totalizer to desired value

Close Boric Acid Totalizer Shutter

Set CVC-403 hand controller to desired setpoint

Position Reactor Makeup Mode Selector to BORATE

Position Reactor Makeup Control Switch to Start

(CAS) Adjust CVC-403 setpoint as necessary to establish desired flow rate KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 34 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

When Boration Complete then return to Auto Makeup o Position Reactor Makeup Mode Selector switch to Auto o Position Reactor Makeup Control switch to Start

If adding additional Boron then GO TO Attachment F Human Performance: Peer Checking- All (CAS) CREW Perform boration reactivity calculations shall be peer

Check Standard Reactivity Plan (SRP) checked. available

Borate per the applicable SRP minus any boron from Rapid Boration using Attachment F AOP-GEN-002 Attachment F Actions for Normal Boration The amount of the boration will be RO Starting a normal boration determined from the standard reactivity plan

Set the boric acid totalizer to the for taking the unit off line. This amount desired quantity should be peer checked

Close the boric acid totalizer shutter Further action in Attachment F is not

Set CVC-403 Hand Controller to the expected prior to reactor trip desired value Rate of Power Boric Acid Injection Reduction Rate 1% 5 GPM 3% 10 GPM KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 35 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

Position Reactor Makeup Mode Selector switch to Borate

Position Reactor Makeup Control Switch to Start

(CAS) Adjust CVC-403 setpoint as necessary to establish desired flow

(CAS) Start and Stop Reactor Makeup Control System as necessary to establish desired RCS Boron Concentration AOP-GEN-002 Actions After direction for Boration RO Place all PRZR heaters ON Setter position will be determined by the (CAS) US/RO Perform turbine load US. reduction

Check load Reduction Desired

Check Turbine Mode OPER AUTO

Check Turbine Selected to IMP IN RNO

Perform the following o Press IMP in Pushbutton o Check the following indications IMP IN pushbutton LIT IMP OUT pushbutton DIM KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 36 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

Set setter to desired turbine load

Check VPL POS LIMIT light OFF

Set Loading rate % per min to value determined in step 3 - 3%

Press GO pushbutton (CAS) BOP Maintain MVAR Out Loading 0-150 MVAR (CAS) US/CREW Control Boration flow and power reduction to maintain plant parameters

I

Rod Insertion Limits

Tave/Tref Deviation CREW Plant announcement (CAS) RO Control charging and letdown to maintain RCS inventory per NOP-CVC-002 ROLE: SM ROLE: DEMI/ATC US Inform DEMI and ATC of power REQUEST: Inform of DEMI and ATC of REQUEST: Inform of Power Reduction reduction Power Reduction RESPONSE: Acknowledge power RESPONSE: Acknowledge direction to Reduction inform DEMI and ATC then after delay DELAY: None report that DEMI and ATC has been informed of the power reduction DELAY: One Minute KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 37 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS If a Brief is held here, it should be short US Check if task briefing should be covering performed Load decrease to 45%

CVC-440 failure Declaration of UNUSUAL EVENT due to leak rate- Escalation is if actuation of SI is required due to worsening of leak to SG (CAS) RO Check Rod Position If either Control Bank LOW limit or Control Bank LOW-LOW Limits annunciators are lit then continue boration US/RO If Control Bank LOW-LOW Limits annunciator actuates, address Technical Specifications - Determine if rods actually below RILs LCO 3.1.6 Condition A

Required Action A.1.1 Verify SDM within limits within one hour OR

Required Actions; o A.1.2 Initiate boration to restore SDM within limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND o A.2 Restore control bank to within limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 38 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS (CAS) CREW Control Tavg/Tref Deviation

Check Control Rods move as necessary to restore Tave/Trev deviation

Check status light load loss 10 PCT Rate LIT

Check Tavg > 540ºF CREW Perform a review of SER Points as time permits (CAS) Check Control Systems Operating in Automatic

SG Level

PRZR Press Control

PRZR Level Control KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 39 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 4: Steam Leak Down Stream MSIVs Human Performance Tools: Procedure Compliance, STAR, Clear Communications, Verification Practices Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely Controlling Plant Evolutions Component - ATC Major - BOP & ATC If the operators do not perform the actions When direct by the lead evaluator then CREW Perform the IMMEDIATE actions of of AOP-GEN-001 when the report is insert TRIGGER 7 and ensure malfunction AOP-GEN-001 Attachment G received from the EO then the US should MS03B is active and ramping to a value of 1 direct the actions. over 3 minutes After the malfunction has been active for 3 minutes then call the Control Room as the EO and report the following in a panicked voice:

There is a LOT of Steam coming from Main Steam Piping around the Battery Room and I am leaving the area for FEAR of LIFE.

AOP-GEN-001 Immediate Operator Actions Attachment G Main Steam Line Break Downstream of MSIVs CREW Check if MSIVs should be closed

Check Steam leak outside of containment threatens life or equipment o Increased steam flow and elevated steam exclusion temperatures OR o Personnel report from outside the Control Room KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 40 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO Manually Trip the Reactor EVENT 5: SG B Safety Fails Open when MSIVs Close Human Performance Tools: Procedure Compliance, STAR, Clear Communications, Verification Practices Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely Controlling Plant Evolutions Component - BOP Major - BOP & ATC The failure of SG B safety open will cause This event happens automatically when the BOP CLOSE both MSIVs conditions for safety injection. The crew BOP closes the MSIVs

MS-1A for SG A may manually initiate a safety injection depending on plant conditions at the time of

MS-1B for SG B ENSURE malfunction MS04B is active the step in E-0 when MS-1B goes closed Trigger 9 should activate US Direct the crew to perform the immediate actions of E-0 E-0 Reactor Trip or Safety Injection RO Ensure Reactor Trip

Check Reactor Trip and Bypass Breakers OPEN

Check Reactor Subcritical BOP Ensure Turbine Trip

Check HP Turbine Impulse Pressure Trending Toward zero

Check both Turbine Stop Valves Closed KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 41 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS BOP Check 4160V Emergency AC Buses Both energized. Bus 5 and Bus 6 SI should have actuated, or will be required RO Check SI actuated manually, on lowering PRZR level and RCS Check permissive status 44905-1201 SI pressure. Signal Activated LIT RNO Determine appropriate recovery action Check if SI is required

PRZR pressure < 1815 psig

PRZR Level < 3%

RCS subcooling < 15ºF

SG pressure < 500 psig

Containment pressure > 4 psig If SI is required then manually actuate both trains of SI US Hold crew brief

Announce Crew Brief

EAL o Under review

Recap Major Events o Tube Leak and Faulted SG

Ongoing Recovery Actions o Continue in E-0

Comments

End Crew Brief KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 42 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS The foldout page criterion for faulted SG CREW Monitors Foldout Page isolation is met. It is a critical task to isolate feed flow to the faulted SG The operator may choose to take B AFW BOP Perform actions to isolate feed flow to pump to Stop and Pullout at this time but it faulted SG B is not required

Close AFW-2B It is expected that the critical task is met at

Close AFW-10B this time but the crew has until Step 4 of E-2 to complete the task CRITICAL TASK: Isolate feed flow to faulted Steam Generator B by the completion of the Step in E-2 requiring isolation of feed flow SAFETY SIGNIFICANCE: Failure to isolate feed flow to the faulted steam generator that can be isolated causes a challenge to CSFs beyond those irreparably introduced by the scenario conditions CUE: Steam Flow indicated on B Steam Header with MS-1B closed MEASURABLE PERFORMANCE INDICATOR: AFW-2B closed and AFW-10B or AFW-10A closed by completion of Step 4 of E-2 PERFORMANCE FEEDBACK: No feed water flow indicated on AFW Header B KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 43 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 6: Safety Injection Pumps fail to Auto Start on Safety Injection Signal Human Performance Tools: Procedure Compliance, STAR, Clear Communications, Verification Practices Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely Controlling Plant Evolutions Component - ATC See separate section below. RO Performs Attachment A by direction The US and RO may pull the step forward from the SRO.

to start the SI pumps.

Depending on the speed of the crew the (CAS) US/BOP Check AFW Pumps AFW pumps may be tripped. Running

Check AFW Pump A Running o CLOSE AFW-2A o When SI Sequencer Complete then Reset and Start AFW Pump A

Check AFW Pump B running o CLOSE AFW-2B o When SI Sequencer Complete then Reset and Start AFW Pump B

Check MD AFW Pumps Both Running

Throttle MD Flow as necessary to maintain discharge pressures greater than 1000 psig prior to and immediately prior to stopping TD AFW pump. - N/A

Stop TD AFW pump and place in Pullout KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 44 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS (CAS) US/BOP AFW discharge pressure >

1000 psig US/BOP Check Secondary Heat Sink Ensure total AFW flow > 210 gpm OR SG narrow range level > 5% [13%]

US/CREW Check RXCP Seal Cooling Normal (CAS) US/CREW Check RCS Temperature Control

RCS Cold Leg temperatures <5470F and Stable RNO

Main Steam Dump Mode Selector Switch to RESET then STM PRESS

Stop Dumping Steam

If SG pressure less than 1005 psig Then VERIFY SG PORV CLOSED

Reduce Total Feed Flow to between 210 - 250 gpm

CLOSE MS-1A, MS-2A, MS-1B, MS-2B if RCS temperature continues to lower US/RO Check PRZR PORVs - Both Closed US/RO Check PRZR Spray Valves Closed KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 45 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/ RO Check if RXCPS should remain running OP-AP-104 states that in the absence of CREW Monitor CSF Status Trees the STA the crew will monitor CSF status trees CREW Check If any SG is Faulted Check Both SGs

Any SG pressure Decreasing in uncontrolled manner or completely depressurized

Do not Continue until Attachment A is complete

GO TO E-2 E-0 Attachment A RO Notify Plant Personnel using Gai-Tronics RO Check Feedwater Isolation

FW-7A/B Closed

FW-10A/B Closed

FW-12A/B Closed

FW Pumps A & B OFF RO Check SI Pumps - Neither running RNO When SI Sequencer complete then manually start both pumps RO Check RHR Pumps - BOTH RUNNING KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 46 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO Check CC Pumps - BOTH RUNNING RO Check Containment and Containment Ventilation Isolation

Check CI Active Status Panel light -

ALL LIT

Place control switches for LD-4A/B/C to Close RO Check if MSIVs can remain OPEN

Check if any MSIV or bypass open -

NO (CAS) RO Check Containment Spray NOT required

Containment Pressure has remained <

23 psig RO Check SW Alignment

All SW Pumps Running

Check SW Header pressures - both >

82.5 psig RO Check Containment Cooling

Check CFCUs - All Running

Ensure CFCU SW return Isolation Valves - ALL OPEN

Check Shroud Cooling Coil Bypass valves - ALL OPEN

(CAS) Check Containment Pressure has remained below 4 psig KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 47 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RNO

Ensure all CFCU Emergency Discharge Dampers OPEN o RBV-150A o RBV-150B o RBV-150C o RBV-150D RO Verify Aux Building Special Ventilation

Check Annunciator Zone SV BNDRY Damper not Closed - Clear (47052-G)

Check Zone SV Fans - ALL RUNNING RO Check Si Active Status Panel Lights -

ALL LIT RO Check SI Flow

Check RCS Pressure < 2000 psig RO Return procedure and step in effect US Hold Crew brief and transition to E-2 E-2 Faulted Steam Generator Isolation Once the crew has transitioned to E-2 and US/BOP Ensure MSIV and Bypass for Feed flow has been isolated to the faulted faulted SG B are Closed steam generator then the scenario may stop at the lead evaluator discretion. The scenario has been validated until the transition to E-3 KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 48 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/BOP Check pressure in both SG any stable or increasing - Identify A SG intact US/BOP Identify faulted Steam Generator Any SG pressure decreasing in an uncontrolled manner or completely depressurize -Identify SG B US/BOP Isolate feed Flow to faulted SG

Ensure the following valves closed o FW-12B o FW-7B o FW-10B o AFW-10B o AFW-2B

Place AFW Pump B in PULLOUT US/BOP Isolate Steam Flow from Faulted Steam Generator

Ensure Following valves are closed o BT-2B o BT-3B o BT-31B o BT-32B o SD-3B o MS-100B US/BOP Check CST Level > 20%

KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 49 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/CREW Check Secondary Radiation Normal RNO Transition to E-3

6. SCENARIO END: Ends on transition to E-3 a. FREEZE simulator at direction of floor instructor.

b. STOP Data Capture via SmartTest (optional)

7. POST-SCENARIO:

a. ENSURE simulator problems encountered during the scenario are documented IAW site specific process.

b. ENSURE training attendance is documented on, Training Attendance Report.

c. SOLICIT/COLLECT trainee feedback KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 50 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B INPUT

SUMMARY

Delay Ramp Event Severity Final Relative Description Time Time Trigger Or Value Value Order MALFUNCTIONS SI05B Failure Auto Start SI Pump B 00:00:00 00:00:00 None TRUE TRUE preload SI05A Failure Auto Start SI Pump A 00:00:00 00:00:00 None TRUE TRUE preload RC10B Pressurizer PORV PR-2B Fails Open (PCV-430) 00:00:00 00:00:00 1 0 10 1 SG03B Steam Generator Tube Leak Top of Tubes Lo-Volume 00:00:00 00:05:00 3 0 30 2 MS03B Main Steam Line Rupture Outside of Containment (1B) 00:00:00 00:03:00 7 0 1 3 MS04B Main Steam Safety Valve Fails Open (1B) 00:00:00 00:00:00 9 FALSE TRUE 4 REMOTE FUNCTIONS RM101 R-21 Alignment 00:00:00 00:00:00 None Cntmt Cntmt setup FW185 MU-2A Condenser Makeup from CST 00:00:00 00:00:00 5 100 0 request OVERRIDES MCB DI-46230-CLOSE CVC-440 00:00:00 00:00:00 None ON ON preload MCB DI-46230-OPEN CVC-440 00:00:00 00:00:00 None OFF OFF preload MCC DO-46413-G PR-1B 00:00:00 00:00:00 15 OFF OFF 1.1 Blind Triggers Event #9 Event Action: hwzmsg6136(2)==1.0 Command: imf MS04B Activates Trigger 9 when MS-1B is closed KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 51 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SIMULATOR SCENARIO DEVELOPMENT CHECKLIST Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

Yes No

1. The scenario contains objectives for the desired tasks and relevant Human Performance Tools.

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

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

4. Turnover information includes a Daily At Power Risk Assessment provided by the PRA Group. Done by the crew during validation

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

6. The Scenario Guide includes responses for all communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices.

7. The scenario includes related industry experience. Not Required for evaluations

8. 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.

9. Any identified Critical Tasks possesses the following elements (NUREG-1021):

Essential to safety with adverse consequences or significant degradation,

Cue(s) prompt the Operator to respond.

Defined and measurable performance indicators.

Performance feedback.

The use of N/A is allowed for item 9 only if this is NOT an evaluated scenario.

10. Technical Specifications including Limiting Conditions for Operation, reactivity briefings, and Emergency-Plan entries are addressed as appropriate.

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

KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 52 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B SIMULATOR EXERCISE 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.

Yes No

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

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

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

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

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

6. Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence?

7. 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.

8. Any identified Critical Tasks possesses the following elements (NUREG-1021):

Essential to safety with adverse consequences or significant degradation,

Cue(s) prompt the Operator to respond.

Defined and measurable performance indicators.

Performance feedback.

The use of N/A is allowed for item 8 only if this is NOT an evaluated scenario.

Discrepancies noted (Check none or list items in comments field) None Comments: None Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 53 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B Applied & Implemented All Information Passed on to All Any Knowledge or Performance Corrective Actions if TS/TRM (PP-1) Identified All Applicable Correctly Crew Members (i.e., briefs) Deficiencies Required As Time Allowed LCO 3.1.6 Yes No Yes No Yes No LCO 3.4.11 Yes No Yes No Yes No LCO 3.4.1 Yes No Yes No Yes No LCO 3.4.13 Yes No Yes No Yes No Yes No Yes No Yes No Yes No Yes No Yes No EALs All Information Passed on to All Any Knowledge or Performance Corrective Actions if Identified All Applicable Classified & Notified Timely (EP Group) Crew Members (i.e., briefs) Deficiencies Required UE Yes No Yes No Yes No Any Knowledge or Performance Corrective Actions if Procedure Compliance (PP-3) Applied & Implemented Correctly As Time Allowed Deficiencies Required AOP-RC-004 Yes No AOP-GEN-002 Yes No AOP-RM-001 Yes No AOP-GEN-001 Yes No E-0 Yes No E-2 Yes No KPS-SEG3-L-RO/SRO-A-01242011-114

Simulator Exercise Guide Job Aid Page 54 of 54 SEG# ROI/SOI-06-SE-SC3 Rev: B Any Knowledge or Performance Corrective Actions if Human Performance Errors (PP-2) Identify All HU Errors or Potential HU Errors Deficiencies Required Questioning Attitude Stop When Unsure Self Checking Procedure Use and Adherence Clear Communications Place Keeping Verification Practices Identify All Operator Fundamental Errors Or Potential Operator Fundamental Any Knowledge or Performance Corrective Actions if Operator Fundamentals Errors Deficiencies Required Teamwork Effectiveness (T)

High Standards for Controlling Plant Evolutions (H)

Indications and Plant Parameters Monitored Closely (I)

Natural Bias for Conservative Approach to Plant Operations (N)

Knowledge of Plant Design and Theory (K)

KPS-SEG3-L-RO/SRO-A-01242011-114

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