ML13084A096

CG-2013-02-DRAFT Exam Outlines

ML13084A096
Person / Time
Site:	Columbia
Issue date:	02/08/2013
From:	Garchow S Operations Branch IV
To:
laura hurley
References
50-397/13-002
Download: ML13084A096 (118)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Columbia Date of Examination: February 2013 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

Determine if APRM indication is greater than reactor power as calculated from Main Turbine Bypass Valve position and Reactor Feedwater temperature (2.1.25 RO 3.9). Given the positions of the four Main Turbine Bypass Valves, Reactor Feedwater Conduct of Operations M, R temperature and house loads, calculate current reactor power by plotting the values on the Core Thermal Power Versus Bypass Valve Position graph in PPM 3.1.2 and summing the values. Compare the results to the APRM reading to determine if APRM indications are greater than reactor power.

Use procedures to assign operators to the positions required to meet minimum crew compliment (2.1.5 RO 2.9). Provided a list of the On-Coming crew Conduct of Operations N, R operators and the PQD Viewer duty areas, assign operators to positions to meet the requirements for the minimum crew compliment.

Use electrical prints to determine why RHR-P-2C did not start following a manual initiation (2.2.41 RO Equipment Control M, R 3.5). Given a set of initial conditions, explain which contacts prevent starting RHR-P-2C using the ARM

& DEPRESS pushbutton.

Use radiological survey maps to determine the minimum and maximum stay times until radiation Radiation Control D, R, P exposure limits are reached (2.3.4 RO 3.2). Given year-to-date exposure and work instructions, refer to radiological survey maps to determine work area radiation levels and calculate the time at which a

radiation exposure limit will be reached.

Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Columbia Date of Examination: February 2013 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

Determine if a MODE change is allowed during a plant startup (2.1.23 SRO 4.4). With a plant startup in progress, the SRO candidate is provided a list of Conduct of Operations D, R plant conditions and required to determine if a MODE change is allowed. The candidate must recognize that HPCS is inoperable and LCO 3.0.4 is not applicable.

Use procedures to project On-Coming Crews watch manning, and verify qualifications meet the minimum requirements (2.1.5 SRO 3.9). Provided the list of Conduct of Operations N, R operators scheduled for the new crew starting a series of nightshifts and PQD Viewer areas, the SRO candidate must determine that the minimum qualifications are not satisfied.

Maintain control of equipment status by issuing a Fire Protection System Impairment (2.2.14 SRO 4.3).

During the performance of a surveillance, two Main Equipment Control M, R Control Room Halon Tanks have been reported to have UNSAT pressures. The SRO candidate must determine that a Fire Protection System Impairment is required to track the equipment status, and complete the Impairment.

The SRO Candidate is tasked with reviewing a request to initiate blowdown from the Circulating Water and Plant Service Water systems (2.3.6 SRO Radiation Control D, P, R 3.8). Given parameters associated with CW and TSW blowdown, the SRO candidate must determine that the minimum instrumentation required to initiate blowdown is not available, and should not be

allowed.

The SRO Candidate is given that a UE was previously declared due to a credible threat security Emergency event. The situation then escalates and the SRO has D, R Procedures/Plan to determine that an Emergency Plan upgrade is required, the applicable EAL and then fill out the required Classification Notification Form.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Columbia Date of Examination: February 2013 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. Reactor Manual Control System / Conduct a Refueling Interlocks A, L, N, S 1 Functional Test of the Refuel Position One-Rod-Out Interlock (201002 A3.01). With the MODE Switch in SHUTDOWN, place the plant in MODE 5 and perform OSP-NSSE-W402 (Refuel Position One-Rod-Out Interlock CFT). The designated control rod is in a quadrant that does not have an operable SRM.

b. Component Cooling Water System / Restore adequate Component A, M, S 8 Cooling Water (RCC) flow to containment loads (400000 A1.01). While transferring SM-7 to the Backup Transformer, a lockout on SL-71 occurs.

This results in the loss of one RCC pumps and requires manual action to start the standby RCC pump to restore normal system flow.

c. Reactor Core Isolation Cooling System / Manually initiate RCIC and A, D, L, S 2 establish normal RPV water level (217000 A4.04). Initiate RCIC for level control following a scram. The controller is failed and manual control is required to establish flow and restore RPV water level.

d. Main and Reheat Steam / Open the inboard MSIVs to establish the Main D, L, S 4 Condenser as a heat sink (239001 A4.01). Following a loss and restoration of Containment Instrument Air, open the inboard MSIVs to restore the Main Condenser heat sink.

e. Reactor/Turbine Pressure Regulating System / Lower RPV pressure with A, D, L, S 3 Main Turbine Bypass Valves (241000 A2.03). Three Main Turbine Bypass Valves fail open while manually reducing RPV pressure. Entry into ABN-PRESSURE and actions to close the MSIVs are required prior to RPV Pressure reaching 500 psig.

f. Traversing In-Core Probe System / Manually Initiate Containment A, D, P, S 7 Isolations (223002 A2.03; A3.01; A3.02). TIP-V-5 is found to be opened when -50 Isolations are verified. Action is then taken to manually isolate the containment penetration by firing the associated squib

valve.

g. Fuel Pool Cooling and Clean-up / Align Standby Service Water to the L, N, S 9 Fuel Pool Cooling HX following a complete loss of RCC (233000 A2.08).

Following a reactor scram due to a complete loss of RCC and with Fuel Pool Temperatures rising, align Service Water A and B to the Fuel Pool Cooling HXs.

h. Secondary Containment / Restore Secondary Containment differential M, S 5 pressure (290001 A4.01). Operate the Reactor Building HVAC System to restore Reactor Building differential pressure. Start ROA-FN-1A and REA-FN-1A.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Emergency Generators / Shutdown DG-2 from the local control panel A, D, EN, R 6 (264000 K4.07). DG-2 fails to stop when the stop pushbutton is depressed requiring a manual trip using the mechanical overspeed device.

j. Reactor Core Isolation Cooling System / Prevent a RCIC High Exhaust D, E, EN, L, 2 Pressure Trip (217000 A2.02). During a Station Blackout, performs the P, R actions of PPM 5.6.1 required to prevent a high exhaust pressure trip of the RCIC turbine.

k. Primary Containment System and Auxiliaries / Perform Emergency C, D, E, 5 Drywell Venting during a LOCA using SGT-B (223001 A2.07). With a LOCA EN, L, R signal present, emergency vent the Drywell using SGT.

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9 / <8 / <4 (E)mergency or abnormal in-plant >1 / >1 / >1 (EN)gineered safety feature - / - / > 1 (control room system)

(L)ow-Power / Shutdown >1 / >1 / >1 (N)ew or (M)odified from bank including >2 / >2 / >1 1(A)

<3/ < 3 / < 2 (randomly selected)

(P)revious 2 exams

>1 / >1 / >1 (R)CA (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Columbia Date of Examination: February 2013 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Type Safety System / JPM Title Code* Function

a. Reactor Manual Control System / Conduct a Refueling Interlocks Functional A, L, N, S 1 Test of the Refuel Position One-Rod-Out Interlock (201002 A3.01). With the MODE Switch in SHUTDOWN, place the plant in MODE 5 and perform OSP-NSSE-W402 (Refuel Position One-Rod-Out Interlock CFT). The designated control rod is in a quadrant that does not have an operable SRM.

b. Component Cooling Water System / Restore adequate Component Cooling A, M, S 8 Water (RCC) flow to containment loads (400000 A1.01). While transferring SM-7 to the Backup Transformer, a lockout on SL-71 occurs. This results in the loss of one RCC pumps and requires manual action to start the standby RCC pump to restore normal system flow.

c.

d. Main and Reheat Steam / Open the inboard MSIVs to establish the Main D, L, S 4 Condenser as a heat sink (239001 A4.01). Following a loss and restoration of Containment Instrument Air, open the inboard MSIVs to restore the Main Condenser heat sink.

e. Reactor/Turbine Pressure Regulating System / Lower RPV pressure with Main A, D, L, S 3 Turbine Bypass Valves (241000 A2.03). Three Main Turbine Bypass Valves fail open while manually reducing RPV pressure. Entry into ABN-PRESSURE and actions to close the MSIVs are required prior to RPV Pressure reaching 500 psig.

f. Traversing In-Core Probe System / Manually Initiate Containment Isolations A, D, P, S 7 (223002 A2.03; A3.01; A3.02). TIP-V-5 is found to be opened when -50 Isolations are verified. Action is then taken to manually isolate the containment penetration by firing the associated squib valve.

g. Fuel Pool Cooling and Clean-up / Align Standby Service Water to the Fuel Pool L, N, S 9 Cooling HX following a complete loss of RCC (233000 A2.08). Following a reactor scram due to a complete loss of RCC and with Fuel Pool Temperatures rising, align Service Water A and B to the Fuel Pool Cooling HXs.

h. Secondary Containment / Restore Secondary Containment differential pressure M, S 5 (290001 A4.01). Operate the Reactor Building HVAC System to restore Reactor Building differential pressure. Start ROA-FN-1A and REA-FN-1A.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Emergency Generators / Shutdown DG-2 from the local control panel A, D, EN, R 6 (264000 K4.07). DG-2 fails to stop when the stop pushbutton is depressed requiring a manual trip using the mechanical overspeed device.

j. Reactor Core Isolation Cooling System / Prevent a RCIC High Exhaust D, E, EN, L, 2 Pressure Trip (217000 A2.02). During a Station Blackout, performs the P, R actions of PPM 5.6.1 required to prevent a high exhaust pressure trip of the RCIC turbine.

k. Primary Containment System and Auxiliaries / Perform Emergency Drywell C, D, E, 5 Venting during a LOCA using SGT-B (223001 A2.07). With a LOCA signal EN, L, R present, emergency vent the Drywell using SGT.

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room

<9 / <8 / <4 (D)irect from bank

>1 / >1 / >1 (E)mergency or abnormal in-plant

- / - / > 1 (control room system)

(EN)gineered safety feature

>1 / >1 / >1 (L)ow-Power / Shutdown

>2 / >2 / >1 (N)ew or (M)odified from bank including 1(A)

<3/ < 3 / < 2 (randomly selected)

(P)revious 2 exams

>1 / >1 / >1 (R)CA (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Columbia Date of Examination: February 2013 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. Reactor Manual Control System / Conduct a Refueling Interlocks A, L, N, S 1 Functional Test of the Refuel Position One-Rod-Out Interlock (201002 A3.01). With the MODE Switch in SHUTDOWN, place the plant in MODE 5 and perform OSP-NSSE-W402 (Refuel Position One-Rod-Out Interlock CFT). The designated control rod is in a quadrant that does not have an operable SRM.

b. Component Cooling Water System / Restore adequate Component A, M, S 8 Cooling Water (RCC) flow to containment loads (400000 A1.01). While transferring SM-7 to the Backup Transformer, a lockout on SL-71 occurs.

This results in the loss of one RCC pumps and requires manual action to start the standby RCC pump to restore normal system flow.

c.

d.

e.

f.

g.

h.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Emergency Generators / Shutdown DG-2 from the local control panel A, D, EN, R 6 (264000 K4.07). DG-2 fails to stop when the stop pushbutton is depressed requiring a manual trip using the mechanical overspeed device.

j. Reactor Core Isolation Cooling System / Prevent a RCIC High Exhaust D, E, EN, L, 2 Pressure Trip (217000 A2.02). During a Station Blackout, performs the P, R actions of PPM 5.6.1 required to prevent a high exhaust pressure trip of the RCIC turbine.

k. Primary Containment System and Auxiliaries / Perform Emergency C, D, E, 5 Drywell Venting during a LOCA using SGT-B (223001 A2.07). With a LOCA EN, L, R signal present, emergency vent the Drywell using SGT.

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room

<9 / <8 / <4 (D)irect from bank

>1 / >1 / >1 (E)mergency or abnormal in-plant

- / - / > 1 (control room system)

(EN)gineered safety feature

>1 / >1 / >1 (L)ow-Power / Shutdown

>2 / >2 / >1 (N)ew or (M)odified from bank including 1(A)

<3/ < 3 / < 2 (randomly selected)

(P)revious 2 exams

>1 / >1 / >1 (R)CA (S)imulator ES-301, Page 23 of 27

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION Reduce Power with Flow; BPV Surveillance - One BPV is Failed Closed; NR Instrument Fails LESSON TITLE Downscale; Fire in TB - CAS Leak - A/Cs Fail to Auto Start - CAS A/B Trip; Scram on Loss of CAS Pressure; Steam Leak in Containment; RHR-P-2A Overcurrent Causes an SM-7 Lockout; RHR-P-2B Fail Auto Start Then a Shaft Shear; RRC-P-1A Stop P/B Failed off; Spray with SW-B per PPM 5.5.2; Secure Drywell Sprays LENGTH OF LESSON 1.5 Hours INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code LO001750 Rev. No. 0 JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 12/09/12 REVISED BY DATE VALIDATED BY DATE TECHNICAL REVIEW DATE INSTRUCTIONAL REVIEW DATE SAT Coordinator APPROVED DATE Operations Training Manager

NRC EXAM SCENARIO #1 Initial conditions: The plant is operating at 100% power. TSW-P-1A is tagged out for motor replacement. The reactivity brief and task preview for the shifts scheduled activities have been completed.

Shift Directions: Per the Reactivity Control Plan, reduce reactor power with flow to 90%. Concurrent with the power reduction, perform OSP-MS-M701, Bypass Valves Test.

Event Timeline Event Type* Event Description No.

1 T=0 R (ATC) Power reduction to 90% by lowering RRC flow.

R (CRS) 2 T=0 C (BOP) Perform OSP-MS-M701, Main Turbine Bypass Valves Test. BV3 fails to open, requiring BPVs to be declared inoperable (Tech Spec).

3 T = 20 I (ATC) RFW-LI-606A (the selected NR instrument) fails downscale (Tech Spec).

I (CRS) 4 T = 35 I (BOP) Fire in the Turbine Building resulting in degrading Control Air header pressure. Both standby CAS compressors fail to auto start on low header pressure, and must be manually started to restore header pressure.

5 T = 45 M (All) Loss of CAS-C-1A and CAS-C-1B.

A manual rector scram is required prior to MSIV closure.

6 T = 55 M (All) A Steam LOCA develops inside containment when the MSIVs close.

7 T = 60 C (BOP) When Drywell pressure reaches 1.68 psig, RHR-P-2A will automatically start with an overcurrent condition. The output breaker will fail to trip and cause C (CRS) a lockout on SM-7. DG-1 must be emergency tripped.

8 T = 65 C (BOP) RHR-P-2B fails to auto start. RHR-P-2B has a sheared shaft when manually started. Initiate Drywell sprays with SW-B through RHR-B using PPM 5.5.2 C (CRS) after Drywell temperature reaches 285°F, but before Drywell temperature reaches 330°F (Critical Task).

Secure Drywell sprays when Drywell pressure drops to LT 12 psig and before it drops to -0.5 psig (Critical Task).

LO001750 Rev. 0 Page 1 of 29

NRC EXAM SCENARIO #1 9 T = 65 C (ATC) The stop pushbutton fails to stop RRC-P-1A.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor LO001750 Rev. 0 Page 2 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 The scenario starts with Columbia at 100% power. TSW-P-1A is tagged out for motor replacement.

After the crew takes the shift, power is to be lowered to 90% for economic dispatch request from BPA. The crew will lower power with RRC flow.

At the same time, the BOP operator will perform BPV surveillance test, OSP-MS-M701. When the third bypass valve is tested, it will not open. The CRS will refer to Tech Specs and enter TS 3.7.6.

After Tech Specs are referenced, RFW-LI-606A will fail downscale. The crew will swap FWLC channels from Channel A to Channel B. Tech Spec again will be referenced.

The next event is a fire in the Aux Boiler Room, Turbine Building 441 elevation East side. The fire will cause a rupture in the Control Air System. CAS pressure will slowly drop. ABN-FIRE and ABN-CAS will be entered. The Standby CAS compressors will not auto start but may be started manually. When started, CAS pressure will start to recover.

Due to a failed fire hose that occurs during firefighting efforts, CAS-C-1A and CAS-C-1B become wetted and will trip.

With only one CAS compressor running, CAS pressure will again begin to drop. Firefighting efforts will put the fire out.

When it is determined that a complete loss of air is apparent, the crew will insert a manual scram (should be prior to MSIVs going closed which would cause an automatic scram).

When the MSIVs close, a Steam LOCA inside containment will occur causing a High Drywell Pressure signal at 1.68 psig.

When RHR-P-2A starts on high Drywell pressure, it will have an overcurrent fault. The breaker on SM-7 will not open, and a lockout on SM-7 will occur. The crew will emergency trip DG-1 which will be running with no Service Water.

Additionally, RHR-P-2B will not auto start on high Drywell pressure but may be manually started. When it is started the shaft will shear and the pump will develop no discharge pressure.

The crew will realize that both RRC pumps are running without RCC flow (RRC pumps tripped off on the high drywell pressure signal). When the stop pushbutton for RRC-P-1A is depressed it will not stop the pump. The crew will open one of the supply breakers to stop RRC-P-1A.

Wetwell pressure will rise to 2 psig and the crew will want to spray the Wetwell but will realize both RHR spray systems are not operational.

Drywell/Wetwell pressure and Drywell temperature will continue to rise. The crew will perform PPM 5.5.2, RHR/SW Crosstie Lineup.

Wetwell sprays will be initiated (GT 2 psig Wetwell pressure). Drywell Sprays will be initiated when Drywell temperature reaches 285°F or Wetwell pressure reaches 12 psig. (Note: After MSIVs close it takes 5 minutes and 15 seconds to get to 285°F DW/T, 6 minutes and 15 seconds to get to 12 psig WW/P, and 12 minutes to get to 330°F DW/T) (Critical Task).

LO001750 Rev. 0 Page 3 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Drywell Sprays will be secured when Drywell Pressure drops to LT 12 psig and before Drywell Pressure drops to LT -

0.5 psig (Critical Task).

The scenario will be terminated when drywell sprays have been secured.

LO001750 Rev. 0 Page 4 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Event No. 1

==

Description:==

Reduce Reactor Power with flow.

This event is initiated by the turnover information.

Time Position Applicants Actions or Behavior T=0 CRS Directs the ATC to reduce reactor power at the rate of 1 Hz per minute or 10 MWe/minute and stop the power decrease when Reactor Power is approximately 90%.

ATC Reduces reactor power with RRC flow as directed at the rate directed.

Verifies both RRC pump individual pump controllers are in AUTO and depresses the Master Controller LOWER pushbutton to lower RRC Pump flow.

COMMENTS:

LO001750 Rev. 0 Page 5 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Event No. 2

==

Description:==

Perform Bypass Valve Test Surveillance OSP-MS-M701 (Tech Spec).

This event is initiated by turnover information. Failure of BPV #3 to open is active from the beginning of the scenario.

Time Position Applicants Actions or Behavior T=0 CRS Directs BOP operator to perform OSP-MS-M701.

BOP Flags expected annunciators per P&L 3.4.

Step 7.1 Reduce Reactor Power to LE 3411 Mwt (75 Mwt below 100% power) per PPM 3.2.1 or 3.2.6.

Step 7.2 Verify proper margin to Pre-Conditioned Status (PCS) exists per PPM 9.3.18.

NOTE: Due to low extraction steam pressures, therefore slower heater level control, low pressure heaters 1 and 2 are removed from service when Reactor Power is LT 76% and testing Turbine Bypass Valves.

Step 7.3 If reactor power is LT 76%, then verify COND-HX-1A, B, and C and COND-HX-2A, B, and C are removed from service per SOP-FWH-SHUTDOWN..

NOTE: The following condensate flow requirement is to allow sufficient margin for Desuperheat Sprays and Hotwell dump flow, while providing sufficient flow to the Reactor. NOTE: Each Condensate Booster Pump is rated for 11,000 gpm.

Step 7.4 If condensate flow is not 3000 gpm LT the rated flow for the present condensate pump configuration (as indicated on COND-FR-11), then reduce reactor power until condensate flow is 3000 gpm LT the rated flow for the present pump configuration.

Step 7.5 Establish desuperheat spray at approximately 150 psig (COND-PI-40), by one or more of the following methods. N/A method(s) not used.

• Place COND-PCV-40 to OPEN (Desuper Spray Press Control)

• Throttle OPEN COND-V-178 (Desuper Spray Bypass)

• Place COND-PIC-40 in MANUAL (TB 441, IR-9) to establish desuperheat spray at ~100 LO001750 Rev. 0 Page 6 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 psig Step 7.6 Select BV on the SELECT VALVE panel (Menu, Valve Testing).

Selects Menu. Selects Valve Testing. Selects BV.

Step 7.7 Verify OK TO TEST BV VALVES is green.

(The light will turn green at ~91% power)

NOTE: Use indication on DEH Monitor panel for MWe.

Step 7.8 Perform the following to test BV1:

Step 7.8.1 Record MWe.

Step 7.8.2 Select TEST BV1.

NOTE: When in the Valve Testing Mode, BPVs will move only while the OPEN BV or CLOSE BV button is being touched. Valve motion will stop if finger is lifted from the touch screen, and will resume when the button is touched and held again.

Step 7.8.3 Select TEST.

Step 7.8.4 Touch and hold OPEN BV1 button.

Step 7.8.5 When BPV1 is fully open, then release OPEN BV1 button.

Step 7.8.6 Verify BPV1 is OPEN.

Step 7.8.7 Record MWe.

Step 7.8.8 Touch and hold CLOSE BV1 button.

Step 7.8.9 When BPV1 is fully closed, then release CLOSE BV1 button.

LO001750 Rev. 0 Page 7 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Step 7.8.10 Verify BPV1 is CLOSED.

Step 7.8.11 Record MWe.

Step 7.8.12 Select TEST BV1.

Step 7.8.13 Select EXIT TEST.

CRS Step 7.8.14 Verify Plant conditions have stabilized before continuing to the next step.

BOP Step 7.9 Perform the following to test BV2:

Step 7.9.1 Record MWe.

Step 7.9.2 Select TEST BV2.

NOTE: When in the Valve Testing Mode, BPVs will move only while the OPEN BV or CLOSE BV button is being touched. Valve motion will stop if finger is lifted from the touch screen, and will resume when the button is touched and held again.

Step 7.9.3 Select TEST.

Step 7.9.4 Touch and hold OPEN BV2 button.

Step 7.9.5 When BPV2 is fully open, then release OPEN BV2 button.

Step 7.9.6 Verify BPV2 is OPEN.

Step 7.9.7 Record MWe.

Step 7.9.8 Touch and hold CLOSE BV2 button.

Step 7.9.9 When BPV2 is fully closed, then release CLOSE BV2 button.

LO001750 Rev. 0 Page 8 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Step 7.9.10 Verify BPV2 is CLOSED.

Step 7.9.11 Record MWe.

Step 7.9.12 Select TEST BV2.

Step 7.9.13 Select EXIT TEST.

CRS Step 7.9.14 Verify Plant conditions have stabilized before continuing to the next step.

BOP Step 7.10 Perform the following to test BV3:

Step 7.10.1 Record MWe.

Step 7.10.2 Select TEST BV3.

NOTE: When in the Valve Testing Mode, BPVs will move only while the OPEN BV or CLOSE BV button is being touched.

Valve motion will stop if finger is lifted from the touch screen, and will resume when the button is touched and held again.

Step 7.10.3 Select TEST.

Step 7.10.4 Touch and Hold Open BV3 button.

Step 7.10.5 When BPV3 is fully open, then release OPEN BV3 button.

BOP Recognizes that Bypass valve #3 does not open and informs CRS. (Note: if the OPEN button is held long enough the DEH Trouble alarm will annunciate due to SPC A Control vs. feedback deviation).

CRS Refers to Technical Specifications and refers to LCO 3.7.6 Main Turbine Bypass System.

LO001750 Rev. 0 Page 9 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Contacts Work Control and requests assistance with inoperable bypass valve.

May contact System Engineer.

Conducts Brief - informs crew that LCO 3.7.6 Condition A is applicable and required action is to satisfy the requirements of the LCO within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce thermal power to LT 25% RTP within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

May direct desuperheat spray be secured.

BOP If directed secures desuperheat spray by taking the control switch for COND-PCV-40 to Close.

COMMENT:

LO001750 Rev. 0 Page 10 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Event No. 3

==

Description:==

RFW-LI-606A Fails Downscale.

This event is initiated by activating TRIGGER 1 after Tech Specs for the Bypass Valve has been referenced.

Time Position Applicants Actions or Behavior T = 20 ATC Acknowledges RFW CONTR SYSTEM TROUBLE alarm.

Monitors RPV level and reports level is 36 and steady.

Recognizes RFW-LI-606A indicates downscale and informs CRS.

Refers to ARP.

CRS Enters ABN-INSTRUMENTATION and updates crew on entry.

Determines RFW-LI-606A detector is RFW-DPT-4A.

BOP Per ARP, checks FWLC Video Display on back panel H13-P612 and notes that it indicated A Narrow Range has an invalid signal (reading 0.0 in) and Channel B is controlling.

May direct OPS2 to investigate RFW-DPT-4A on RB 522 on H22-P004.

ROLEPLAY: In two minutes and call X2171 and report there is nothing obviously wrong with RFW-DPT-4A.

BOP May check EFCV-X107 open.

CRS Directs transfer of Reactor Vessel Level Control Channel selector switch from CH A to CH B.

ATC Places the Reactor Vessel Level Control Channels from Channel A to Channel B.

CRS Refers to Tech Specs and identifies TS 3.3.2.2, Feedwater and Main Turbine High Water Trip Instrumentation, Condition A (Place channel in trip within 7 days).

Contacts Work Control about Channel A failure and requirement to put in a tripped condition within 7 days.

Conducts brief.

COMMENTS:

LO001750 Rev. 0 Page 11 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Event No. 4

==

Description:==

Fire in the Turbine Building with degrading CAS pressure on a 2 minute time delay. CAS-C-1A and CAS-C-1C fail to Auto Start.

This event is initiated by activating TRIGGER 2 and is initiated after Tech Specs for RFW-LI-606A failure have been referenced. The failure of compressors to auto start is active from the beginning of the scenario.

Time Position Applicants Actions or Behavior T = 35 BOP Responds to fire alarms and reports alarms indicate a fire in the Turbine Building 441 Boiler Room and the East End Equipment Area.

Reports start of FP-P-2A.

ROLEPLAY: After FP-P-2A starts, call as OPS 3 (on radio) and report heavy smoke coming from the Aux Boiler Room.

CRS Enters ABN-FIRE and updates crew on entry.

BOP Performs ABN-FIRE immediate actions:

• Sounds Alerting Tone

• Announces fire Turbine Building 441 Aux Boiler Room

• Dispatches the Fire Brigade

• Repeats the three steps

• Depresses the Hanford Fire Department pushbutton on FCP-1 ROLEPLAY: After the announcement: As the Fire Brigade Leader request the fire brigade muster at the 441 turnout locker.

BOP Makes announcement for the fire brigade to muster at the 441 turnout locker.

CRS Directs evacuation of non-emergency personnel per PPM 13.5.1 (Blue form).

BOP Announces evacuation of the Turbine Building.

ROLEPLAY: Three minutes later, as the Fire Brigade Leader, report the fire is limited to the Aux Boiler Room.

LO001750 Rev. 0 Page 12 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 BOP Responds to Air Dryer Trouble, the Air AFT-FLTR A dP High, Standby Air Compressor On, and Low CAS Header Pressure alarms as they annunciate.

Informs CRS and refers to ARP.

Informs CRS of lowering CAS pressure and trend (down slow).

CRS Enters ABN-CAS and updates crew on entry.

ROLEPLAY: If asked for local investigation of CAS pressure loss - you will try and investigate but priority is on fighting the fire for now.

BOP When the Standby Compressor On annunciator alarms, verifies starting of standby air compressors.

Recognizes that CAS-C-1A and CAS-C-1C should have auto started but did not. May inform CRS prior to attempting start.

Places the control switches for CAS-C-1A and CAS-C-1C in the START position and reports start of both compressors to the CRS.

Checks CAS pressure and reports CAS pressure trend is up slow (Note: it takes about a minute until CAS pressures downward trend stops and the header starts to re-pressurize).

CRS Directs announcement to suspend all unnecessary use of Control and Service Air be made.

BOP Makes announcement as directed.

COMMENT:

LO001750 Rev. 0 Page 13 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Event No. 5

==

Description:==

Loss of CAS-C-1A and CAS-C-1B.

This event is triggered by activating TRIGGER 3 after it has been reported that CAS pressure trend is up and the Control Air Header Pressure Low annunciator has cleared.

Time Position Applicants Actions or Behavior T=45 BOP Acknowledges and reports Bus 73 ground alarm.

Acknowledges and reports CAS-C-1A motor trip alarm.

Acknowledges and reports Bus 83 ground alarm.

Acknowledges and reports CAS-C-1B motor trip alarm.

Reports CAS-C-1A and CAS-C-1B are not running.

CRS May direct Fire Brigade be contacted and asked about the compressor trips.

ROLEPLAY: If asked, report that the compressors tripped when a fire hose failed and wetted the air compressor motors. Fire water has been isolated to that hose and efforts are underway to replace the hose. The fire is being attacked with another hose and the fire is under control.

Also - if asked about CAS pressure loss report there is no way to investigate that at this time.

BOP Reports CAS pressure again trending down.

CRS Sets CAS pressure as a key parameter.

When it is determined that a complete loss of air is apparent directs RFW-V-118 be verified closed.

Directs RFW-LIC-620 to manual and full open Startup flow control valves.

ATC Verifies RFW-V-118 is closed and fully opens both Startup Flow Control valves (RFW-FCV-10A/10B) using the controllers turn knob until 100 is indicated on the controller. May also observe panel indication for both valves indicates that both are full open (10A fully opens before the 10B starts to open).

CRS May set key parameter of CAS air pressure.

BOP Monitors lowering CAS pressure and reports when key parameter met.

CRS When it is determined that a complete loss of air is apparent directs a manual scram be inserted.

LO001750 Rev. 0 Page 14 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 ATC Announces Listen up for the scram report.

Inserts a manual scram by rotating the Mode switch to Shutdown; Monitors and reports APRM downscale lights illuminated, reports RPV Pressure and trend, and reports RPV Level and trend.

Announces EOP entry due to low RPV level.

Reports All Rods In.

Inserts IRM/SRMs by depressing the Power On and the Drive In pushbuttons.

CRS Enters EOP 5.1.1 (RPV Control) and updates crew on entry.

Right after the CRS announces entry into EOP 5.1.1 (RPV Control): ROLEPLAY: Control Room - this is the Fire Brigade Leader - the fire is out and a re-flash watch has been stationed.

Also - if asked about CAS pressure loss report that you will attempt to look into it (no further feedback during the remainder of the scenario will be given).

CRS Directs RPV level be maintained +13 to +54 with the feed and condensate system.

RPV/L band may be widened to -50 to +54 as the scenario progresses due to MSIV closure and changing feed sources.

Directs PPM 3.3.1 subsequent actions.

Directs pressure control with DEH in automatic (while MSIVs are still open).

Direct +13 actuations be verified.

BOP Verifies the following: Reactor scram; RRC Pumps running at 15 Hz; Group 5 and 6 valves isolated on GDS screen (no yellow bordered NSSS groups on GDS).

Reports +13 actuations verified.

ATC Maintains RPV level in given band with the Feed and Condensate System using RFW-V-118.

Uses Quick Card initially to use RFW pumps to maintain level (while MSIVs are still open should use RFW pumps):

Step 2.1.1 If Reactor Feed Pump(s) (RFP) are operating, then perform the following:

a. Verify RFP(s) have ramped down in speed.

b. If preferred to operate RFW-FCV-2A(B) in auto, then verify RFW-FCV-2A(B) is operating properly in Automatic (Minimum Flow Valve) (H13-P840).

LO001750 Rev. 0 Page 15 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1

c. If desired to operate RFW-FCV-2A(B) in manual to prevent complications in controlling Reactor Level or valve cycling, then place RFW-FCV-2A(B) in Manual, and slowly Open to approximately 80%. (Should leave in Auto)

d. Place RFW-P-1B in MDEM mode using either RFT-COMP-1 or RFT-COMP-2 (Pump Control Screen) as follows (H13-P840):

1) Select MDEM.

2) Select YES.

e. Place RFW-P-1A in MDEM mode using either RFT-COMP-1 or RFT-COMP-2 (Pump Control Screen) as follows (H13-P840):

1) Select MDEM.

2) Select YES.

f. Control Turbine speed as required.

Step 2.1.2 If Feedwater Temperature Reduction was in progress, then verify RFW-V-109 is closed (H13-P840).

Step 2.1.3 Start closing RFW-V-112A and RFW-V-112B (H13-P840).

Step 2.1.4 Start opening RFW-V-118 (Throttle valve) (H13-P840) (Uses RFW-V-118 to control feed rate to vessel to maintain RPV Level as directed)

Step 2.1.5 Verify the following open (H13-P840):

• RFW-V-117A

• RFW-V-117B Step 2.1.6 Verify RFW-LIC-620 is in manual (V selected for Valve position demand) with 0 output LO001750 Rev. 0 Page 16 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 (Startup RPV Level Control) (H13-P603). (Valves are fully open due to loss of CAS)

Step 2.1.7 Verify RFW-V-112A and RFW-V-112B are fully closed.

Step 2.1.8 Verify RFW-V-118 is FULLY OPEN. (Uses RFW-V-118 to control RPV level as directed)

Step 2.1.9 If Reactor Feed Pump(s) (RFP) are operating, then adjust the running RFP speed to establish ~ 200 psid across RFW-FCV-10A & 10B using either Feedwater touch screen (H13-P840). (Will adjust RFW pump speed to be GT RPV pressure)

Note: When MSIVs close, RPV pressure band should be lowered to facilitate feeding with the Condensate Booster pumps.

Maintains RPV level in band directed.

COMMENTS:

LO001750 Rev. 0 Page 17 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Event No. 7

==

Description:==

Steam LOCA inside Primary Containment.

This event is automatically activated when the MSIVs close on low CAS pressure by the event file and uses Trigger 4.

Time Position Applicants Actions or Behavior T=555 BOP Recognizes and reports MSIV closure (due to low CAS pressure).

Places MSIV control switches for all MSIVs in the close position.

Takes manual control of RPV pressure with SRVs at a pressure band of 800 to 1000 psig.

Updates crew.

CRS Directs pressure control with SRVs at 800 - 1000 psig.

May direct a lower pressure band of 500 to 600 psig to facilitate feeding with the Condensate Booster Pumps.

BOP Acknowledges Suppression Pool Level high/low and Drywell/Suppression Pool Temp high annunciators as they annunciate.

Recognizes increasing Drywell pressure and informs CRS.

Reports EOP entry on High Drywell pressure at 1.68 psig (and Wetwell level (+2) and Drywell temperature (135°F) when they occur).

CRS Enters PPM 5.2.1 (Primary Containment Control) and re-enters PPM 5.1.1 (RPV Control) and updates crew.

Directs actuations be verified for 1.68 psig Drywell pressure.

Verifies the following:

HPCS DG, HPCS-P-1 and HPCS-P-2 start DG-1 and DG-2 start RHR-P-2A (Refer to Event 8), RHR-P-2B (refer to Event 9), RHR-P-2C and LPCS-P-1 start CW-P-1B and CW-P-1C trip (continued on next page)

LO001750 Rev. 0 Page 18 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 SW-P-2A and SW-P-2B start RCC-P-1A, RCC-P-1B and RCC-P-1C trip Observes GDS and verifies no yellow bordered NSSS groups (which would indicate a containment isolation valve out of position)

Comments:

LO001750 Rev. 0 Page 19 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Event No. 8

==

Description:==

SM-7 Lockout caused by overcurrent condition on RHR-P-2A and failure of the pumps breaker to open.

This event is active from the start of the scenario and is realized when RHR-P-2A starts. When the pump starts the event file will initiate trigger 5 which causes pump breaker to fail as is and SM-7 lockout on a 30 second time delay.

Time Position Applicants Actions or Behavior T=605T BOP May recognize overcurrent condition on RHR-P-2A when it auto starts by observing pump amp meter on P601.

May recognize that a loss of power to LPCS-P-1 and RHR-P-2A has occurred.

Responds to electrical panel to investigate loss of power.

Notes that SM-7 is not powered.

Investigates annunciators and panel indications and recognizes that a lockout on SM-7 exists (the Lockout Circuit Avail white light for CB-7/1 is not lit) and informs CRS.

Reports that due to the lockout, DG-1 is running without service water.

May refer CRS to ABN-SW and ABN-ELEC-SM1/SM7.

CRS Enters ABN-SW and ABN-ELEC-SM1/SM7 and updates crew.

Directs DG-1 be tripped per subsequent actions of either ABN-SW or ABN-ELEC-SM1/SM7.

BOP Depresses the DG-1 emergency trip pushbutton and reports DG-1 tripped.

Comments:

LO001750 Rev. 0 Page 20 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Event No. 9

==

Description:==

RHR-P-2B Fails to Auto Start and when it is started it has a sheared shaft.

This event is active from the start of the scenario and is realized when 1.69 psig actuations are being verified.

Time Position Applicants Actions or Behavior T=65 BOP While verification of 1.68 psig actuations is being performed, recognizes that RHR-P-2B should have auto started but did not.

Takes the control switch for RHR-P-2B to start and observes breaker closure/pump start.

Verifies proper pump operation and recognizes the pump has not developed any discharge pressure and low running amps are indicated.

Informs CRS.

CRS May direct local investigation of RHR-P-2B.

ROLEPLAY: Wait one minute: RHR-P-2B shaft is sheared and the motor is free spinning from the pump.

CRS Directs RHR-P-2B be secured and may direct control fuses be pulled BOP Secures RHR-P-2B by placing C/S to Stop and directs OPS 2 to pull the control power fuses.

BOOTH OPERATOR: Wait two minutes and ACTIVATE TRIGGER 10 to pull the control power fuses/rackout the breaker and report completion to the control room.

Comments:

LO001750 Rev. 0 Page 21 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Event No. 10

==

Description:==

RRC-P-1A Stop pushbutton Failed.

This event is active from the start of the scenario and is realized when the pushbutton is depressed.

Time Position Applicants Actions or Behavior T=65 ATC Recognizes that RRC pumps are running without RCC cooling (RCC pumps trip off at 1.68 psig Drywell pressure).

Informs CRS and requests permission to stop the RRC pumps.

CRS Directs both RRC pumps be stopped.

ATC Depresses the stop pushbuttons for RRC-P-1A and RRC-P-1B.

Verifies pumps stopped (red ASD lights out and green lights illuminate).

Recognizes RRC-P-1A did not stop.

Informs the CRS of the failure of RRC-P-1A to stop when the Stop pushbutton was depressed.

CRS Directs opening CB-RRA, CB-RPT-3A or CB-RPT-4A to stop RRC-P-1A.

ATC Opens breaker as directed.

Reports RRC-P-1A stopped.

Comments:

LO001750 Rev. 0 Page 22 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 Event No. 11

==

Description:==

Perform PPM 5.5.2 to spray containment with Service Water B.

The Critical Task is to initiate Drywell sprays with SW-B through RHR-B using PPM 5.5.2 after Drywell temperature reaches 285°F, but before Drywell temperature reaches 330°F .

The Critical Task is to terminate Drywell sprays after Drywell pressure reaches 1.68 psig but before drywell pressure drops to LT -0/5 psig.

Time Position Applicants Actions or Behavior T=70 BOP Reports Wetwell pressure at 2 psig and trending up.

CRS Referring to PPM 5.2.1 (Primary Containment Control, determines that Wetwell sprays are required to be initiated (before 12 psig Wetwell pressure).

Recognizes that both loops of RHR are unavailable to spray containment.

Using flow chart icon, directs PPM 5.5.2 (RHR/SW CROSSTIE LINEUP) be performed.

BOP Obtains PPM 5.5.2 and required equipment in plastic bag from EOP drawer.

Step 4.1.1 Verify RHR-P-2B Stopped.

Takes C/S for RHR-P-2B to stop if not previously accomplished.

FLOOR OPERATOR: Be behind H13-P601 and when candidates comes back to perform step 4.1.2 ask what actions he is performing. When step 4.1.2 is stated inform him that he is in the process of performing the step.

Keep him there for one total minute and then inform him that the step has been completed.

NOTE: The following step overrides RHR-V-68B (Heat Exchanger SW Discharge) automatic open logic. E-CP-H13/P680 Bay F is located behind H13-P601.

See Attachment 6.1.

Step 4.1.2 Lift and tape the black wire at TM-7, Terminal 15 (Cable 2M8BB-24) to override RHR-V-68B automatic open logic (E-CP-H13-P680 Bay F) (This panel is not modeled in the simulator but is located behind H13-P601 in the control room.

Step 4.1.3 Verify the following valves are closed:

• RHR-V-24B (Suppression Pool Cooling/Test Return)(H13-P601)

LO001750 Rev. 0 Page 23 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1

• RHR-V-27B (Suppression Pool Spray) (H13-P601)

• RHR-V-16B (Drywell Spray Outboard Isolation) (H13-P601)

• RHR-V-17B (Drywell Spray Inboard Isolation) (H13-P601)

NOTE: If SW-P-1B is operating, then performing the following step may result in injecting service water into the RPV.

Step 4.1.4 Open the following valves:

• RHR-V-115 (SW B to RHR B Cross Connect) (H13-P601)

• RHR-V-116 (SW B to RHR B Cross Connect) (H13-P601)

Step 4.1.5 Start SW-P-1B (if not operating).

Step 4.1.6 Perform one of the following sections. N/A the section not performed.

• Section 4.2 for RPV injection

• Section 4.3 for Containment Sprays Informs the CRS that PPM 5.5.2 is completed up to initiating containment sprays.

CRS Directs spraying the Wetwell.

BOP Step 4.3.1 Verify RHR-V-42B Closed.

Step 4.3.2 If desire to spray the Wetwell, then open RHR-V-27B.

Verifies flow through RHR-B (may not be visible due to only about 500 gpm flowrate from Wetwell sprays).

Informs the CRS that Wetwell sprays have been initiated with SW-B.

CRS Sets key parameter of 285°F DW/T or 12 psig Wetwell pressure.

BOP Informs the CRS when Drywell Temperature reaches 285°F or when Wetwell pressure reaches 12 psig.

CRS Verifies RRC pumps are secured. (It may be at this point in the scenario that the crew attempts to stop RRC-P-1A and not on the loss of RCC cooling flow at 1.68 psig)

Directs Drywell Cooling fans be secured.

LO001750 Rev. 0 Page 24 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 BOP/ATC Goes to back panel and secures the five Drywell Cooling Fans (CRA-FC-2A, 1A, 2B, 1B, 1C

- Fan controls that are not in brown area on panel - Note: CRA-FC-2A and 1A are already off due to loss of power to SM-7).

Informs CRS that Drywell Cooling fans are secured.

CRS Directs Drywell Sprays be initiated with PPM 5.5.2.

BOP Step 4.3.3 If desire to spray the Drywell, then open the following valves:

• RHR-V-17B

• RHR-V-16B Step 4.3.4 Close RHR-V-68B.

Informs CRS Drywell sprays with SW-B have commenced.

Reports Drywell pressure and downward trend.

CRS Directs that Drywell sprays be terminated when Drywell pressure drops to LT 1.68 psig and that Wetwell Sprays be stopped if Wetwell pressure drops to LT 1.68 psig.

BOOTH OPERTOR: When Drywell Sprays have been initiated, reduce MAL-RRS009A to 1500 (and adjust as necessary) to allow Drywell pressure to drop and allow securing of Drywell Sprays.

BOP After Drywell pressure reaches 1.68 psig and before it drops to LT -0.5 pisg, stops Drywell sprays be closing RHR-V-16B and/or RHR-V-17B.

Informs the CRS that Drywell sprays have been stopped.

Comments:

TERMINATION CRITERIA: The scenario will be terminated when Drywell sprays have been stopped.

LO001750 Rev. 0 Page 25 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 TURNOVER INFORMATION Initial Conditions Columbia is operating at 100% power. TSW-P-1A is tagged out for motor replacement. TSW-P-1B is protected and selected as the emergency standby TSW pump.

Shift Directions Reactor Power is to be lowered for economic dispatch due to a request from the BPA. Stop the power decrease when the OK TO TEST BV VALVES green light illuminates at approximately 90% reactor power.

A Reactivity brief for the power reduction has been held and power is to be lowered immediately following shift turnover.

Additionally, commence performance of OSP-MS-M701. The pre job brief has been conducted.

Proper margin to Pre-Conditioned Status (PCS) exists per PPM 9.3.18. The Dittmer Dispatcher has been notified of the upcoming Bypass Valve Testing.

The power reduction and BPV surveillance are to be performed concurrently.

Page 26 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 SIMULATOR SETUP INSTRUCTIONS Reset to IC #171.

Blue Tag TSW-P-1A C/S.

Blue tag the Emergency Standby Selector Switch in the B Pump position.

Flag annunciator.

Have a signed in copy of OSP-MT-M701 available for each crew.

LO001750 Rev. 0 Page 27 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1 SCHEDULE FILE

<SCHEDULE>

<ITEM row = 1>

0

<ACTION>Insert malfunction BKR-RHR002 to FAI_AUT_CLOS</ACTION>

<DESCRIPTION>RHR-P-2B BREAKER</DESCRIPTION>

</ITEM>

<ITEM row = 2>

0

<ACTION>Insert malfunction PMP-RHR002B</ACTION>

<DESCRIPTION>RHR-P-2B SHAFT BREAK</DESCRIPTION>

</ITEM>

<ITEM row = 3>

0

<ACTION>Insert malfunction MOT-RHR001G</ACTION>

<DESCRIPTION>RHR-P-2A MOTOR WINDING OVERCURRENT</DESCRIPTION>

</ITEM>

<ITEM row = 4>

0

<ACTION>Insert malfunction BKR-RHR001 to FA_AUT_TRIP</ACTION>

<DESCRIPTION>RHR-P-2A MOTOR SUPPLY BREAKER</DESCRIPTION>

</ITEM>

<ITEM row = 5>

0

<ACTION>Insert malfunction MAL-CAS005A</ACTION>

<DESCRIPTION>CAS-C-1A FAIL AUTO START</DESCRIPTION>

</ITEM>

<ITEM row = 6>

0

<ACTION>Insert malfunction MAL-CAS005C</ACTION>

<DESCRIPTION>CAS-C-1C FAIL AUTO START</DESCRIPTION>

</ITEM>

<ITEM row = 7>

0

<ACTION>Insert malfunction MAL-DEH013C to 0</ACTION>

<DESCRIPTION> BPV #3 FAILED CLOSED</DESCRIPTION>

</ITEM>

<ITEM row = 8>

0

<ACTION>Insert override OVR-RFC032 to OFF</ACTION>

<DESCRIPTION>RRC-P-1A STOP P/B FAILED UNDEPRESSED</DESCRIPTION>

</ITEM>

<ITEM row = 9>

0

LO001750 Rev. 0 Page 28 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1

<ACTION>Insert remote LOA-EPS388 to RACKED-OUT</ACTION>

<DESCRIPTION>TSW-1A BREAKER RACKED OUT</DESCRIPTION>

</ITEM>

<ITEM row = 10>

0

<EVENT>1</EVENT>

<ACTION>Insert malfunction XMT-RRS106A to 0 on event 1</ACTION>

<DESCRIPTION>RFW-LI-606A FAILED DOWNSCALE</DESCRIPTION>

</ITEM>

<ITEM row = 11>

0

<EVENT>2</EVENT>

<ACTION>insert malfunction MAL-FPS001 after 30 to 100 on event 2</ACTION>

<DESCRIPTION>>FIRE at CAS DRYER AND LOSS OF CAS PRESSURE</DESCRIPTION>

</ITEM>

<ITEM row = 12>

0

<EVENT>2</EVENT>

<ACTION>insert malfunction MAL-CAS004 after 120 to 65 in 300 on event 2</ACTION>

<DESCRIPTION>>FIRE at CAS DRYER AND LOSS OF CAS PRESSURE</DESCRIPTION>

</ITEM>

<ITEM row = 13>

0

<EVENT>2</EVENT>

<ACTION>insert malfunction ANN-840A5I04 to ON after 145 on event 2</ACTION>

<DESCRIPTION>>FIRE at CAS DRYER AND LOSS OF CAS PRESSURE</DESCRIPTION>

</ITEM>

<ITEM row = 14>

0

<EVENT>2</EVENT>

<ACTION>insert malfunction ANN-840A5J05 to ON after 135 on event 2</ACTION>

<DESCRIPTION>>FIRE at CAS DRYER AND LOSS OF CAS PRESSURE</DESCRIPTION>

</ITEM>

<ITEM row = 15>

0

<EVENT>2</EVENT>

<ACTION>insert malfunction ANN-FCP2A04A to ON on event 2</ACTION>

<DESCRIPTION>>FIRE at CAS DRYER AND LOSS OF CAS PRESSURE</DESCRIPTION>

</ITEM>

<ITEM row = 16>

0

<EVENT>2</EVENT>

<ACTION>insert malfunction ANN-FCP2A04C to ON on event 2</ACTION>

<DESCRIPTION>>FIRE at CAS DRYER AND LOSS OF CAS PRESSURE</DESCRIPTION>

</ITEM>

LO001750 Rev. 0 Page 29 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1

<ITEM row = 17>

0

<EVENT>2</EVENT>

<ACTION>Insert malfunction ANN-FCP1A01A after 10 to ON on event 2</ACTION>

<DESCRIPTION>FIRE at CAS DRYER AND LOSS OF CAS PRESSURE</DESCRIPTION>

</ITEM>

<ITEM row = 18>

0

<EVENT>2</EVENT>

<ACTION>Insert malfunction ANN-FCP1A01C after 10 to ON on event 2</ACTION>

<DESCRIPTION>FIRE at CAS DRYER AND LOSS OF CAS PRESSURE</DESCRIPTION>

</ITEM>

<ITEM row = 19>

0

<EVENT>3</EVENT>

<ACTION>Insert malfunction MOT-CAS001G to 100 on event 3</ACTION>

<DESCRIPTION>CAS-C-1A MOTOR WINDING OVERCURRENT</DESCRIPTION>

</ITEM>

<ITEM row = 20>

0

<EVENT>3</EVENT>

<ACTION>Insert malfunction MOT-CAS002G to 100 after 30 on event 3</ACTION>

<DESCRIPTION>CAS-C-1B MOTOR WINDING OVERCURR</DESCRIPTION>

</ITEM>

<ITEM row = 21>

0

<EVENT>4</EVENT>

<ACTION>Insert malfunction MAL-RRS009A to 1500000 in 1800 on event 4</ACTION>

<DESCRIPTION>MN STM LN A BRK AFT FLOW RSTRCTR</DESCRIPTION>

</ITEM>

<ITEM row = 22>

0

<EVENT>5</EVENT>

<ACTION>Insert malfunction BKR-RHR001 to FA_AS_IS on event 5</ACTION>

<DESCRIPTION>RHR-P-2A BREAKER WHEN PUMP STARTS</DESCRIPTION>

</ITEM>

<ITEM row = 23>

0

<EVENT>5</EVENT>

<ACTION>Insert malfunction MAL-EPS001G after 30 on event 5</ACTION>

<DESCRIPTION>4160 VAC BUS OVRCUR/GND SM7</DESCRIPTION>

</ITEM>

<ITEM row = 24>

0

LO001750 Rev. 0 Page 30 of 29

Appendix D NRC EXAM SCENARIO #1 FORM ES-D-1

<EVENT>6</EVENT>

<ACTION>Insert malfunction MOV-SSW002F to FAIL_AUTO_OPEN on event 6</ACTION>

<DESCRIPTION>RHR-V-68B TO KEEP CLOSED FOR PPM 5.5.2</DESCRIPTION>

</ITEM>

<ITEM row = 25>

0

<EVENT>10</EVENT>

<ACTION>Insert remote LOA-EPS397 to RACKED-OUT on event 10</ACTION>

<DESCRIPTION>SM-8 BKR RHR-2B RACKOUT</DESCRIPTION>

</ITEM>

<ITEM row = 26>

0

<ACTION>Event Events/LO001750.evt</ACTION>

<DESCRIPTION>Activate Trigger 4 on MSIV Closure and Trigger 5 on RHR-A Start and Trigger 6 on RHR-V-68B Green light on</DESCRIPTION>

</ITEM>

<ITEM row = 27>

0

<ACTION>Schedule local.sch</ACTION>

<DESCRIPTION>Load Local Operator Actions</DESCRIPTION>

</ITEM>

</SCHEDULE>

EVENT FILE

<EVENT>

<TRIGGER id="4" description="MSIV CLOSURE KICKS TRG 4 TO START STEAM LOCA">X01O196G &gt 0</TRIGGER>

<TRIGGER id="5" description="RHR-P-2A START KICKS TRG 5 FOR SM-7 O/C LOCKOUT">X01O299R &gt 0</TRIGGER>

<TRIGGER id="6" description="RHR-V-68B GREEN ON KICKS TRG 6 TO KEEP VALVE CLOSED">X01O321G &gt 0</TRIGGER>

</EVENT>

LO001750 Rev. 0 Page 31 of 29

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION Pull Control Rods for a Control Rod Set; Rod Drifts Out; Isolate Rod; SGT Strip Heater Fails LESSON TITLE On; Another Failure; OBE - Trip of RFW-P-1A; RRC Pumps Fail to Run Back; RFW-P-1B Trips; Startup Fail to Close in on SM-1, SM-2 and SM Manually Re-Energized; RHR-A Suction Line Rupture ED on Low Suppression Pool Water Level LENGTH OF LESSON 1.5 Hours INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code LO001751 Rev. No. 0 JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/11/12 REVISED BY DATE VALIDATED BY DATE TECHNICAL REVIEW DATE INSTRUCTIONAL REVIEW DATE SAT Coordinator APPROVED DATE Operations Training Manager

NRC EXAM SCENARIO #2 Facility: Columbia Scenario No.: 2 Op-Test No.: 2013 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Reactor power has been lowered to support a Control Rod Set. HPCS-P-1 is tagged out for shaft replacement. The #1 and #2 RFW Heaters have been removed from service per the Reactivity Control Plan. The reactivity brief and the task preview for the shifts scheduled activities have been completed. An SNE is stationed in the Control Room to monitor core conditions.

Turnover: Continue with the Reactivity Control Plan (RCP) and adjust control rods to the target pattern and then return the plant to 100% power.

Event Timeline Event Type* Event Description No.

1 T=0 R (ATC) Pull Control Rods per the Reactivity Control Plan to achieve the target rod R (CRS) pattern.

2 T = 10 C (ATC) While moving control rods, a previously adjusted rod (38-23) begins to drift out.

C (CRS) Once inserted, releasing the continuous insert pushbutton causes the control rod to drift out again, requiring the control rod to be isolated (Tech Spec).

3 T = 20 I (BOP) SGT-A high temperature due to strip heaters failing to de-energize (Tech Spec).

I (CRS) 4 T = 35 C (BOP) Bus Duct Cooling Fan 1A Fails, Standby does not auto start but can be manually started.

5 T = 40 I (ATC) Operating Basis Earthquake.

I (CRS) RFW-P-1A Trip.

RRC pumps fail to automatically run back to 30Hz.

6 T = 50 M (All) A trip of RFW-P-1B results in a loss of Feedwater and a reactor scram.

LO001751 Rev. 0 Page 1 of 24

NRC EXAM SCENARIO #2 7 T = 51 C (All) When the Main Turbine trips, Startup Power will not close in on SM-1, SM-2 or SM-3.

8 T = 60 M (All) Aftershock results in a rupture in the RHR-A suction line.

Emergency Depressurize the RPV before Suppression Pool level reaches 19 feet 2 inches (Critical Task).

9 T = 70 C (BOP) The cross-connect valve between the RHR-A and RCIC pump rooms (FDR-V-607) fails to automatically close due to a failed level switch, and must be manually C (CRS) closed to maintain RCIC operation. Close FDR-V-607 prior to reaching the Maximum Safe Operating Value water level in the RCIC pump room (Critical Task).

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor LO001751 Rev. 0 Page 2 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 The scenario starts with Columbia at approximately 75% power. HPCS-P-1 is OOS due to shaft replacement.

After shift turnover reactor power will be lowered with core flow to 70% to support a control rod set.

During the control rod set, one of the previously moved control rods will begin to drift out of the core. The ATC operator will recognize this and take actions to insert the control rod, which will insert. When the insert pushbutton is released, the control rod will again begin to drift out of the core. The ATC operator will again insert the control rod and the crew will take action to isolate that rod. Tech Spec will be referenced.

After Tech Specs have been referenced a SGT-B high temperature alarm will occur due to a strip heater failing to de-energize. The BOP operator will respond and start SGT-B per and then start SGT-A which will cause temperature to drop. Tech Specs will be referenced.

The next event is a failure of IBD-FN-1A. The BOP operator will respond to annunciators and report the failure of IBD-FN-1A and refer to ARPs. He will note that IBD-FN-1B should have auto started but did not and start IBD-FN-1B.

The next event is an Operating Basis Earthquake which results in a trip of one of the two operating Reactor Feedwater Pumps, RFW-P-1A. During verification of automatic actions the ATC operator will find that the automatic runback of the Reactor Recirculation Pumps did not occur. Manual actions to lower RRC pumps to 30 Hz will be successful.

After the plant stabilizes, the Turbine Building watch will contact the Control Room and inform them that the reason RFW-P-1A tripped was a rupture of the control oil system and that there is a leak in the control oil system on RFW-P-1B. Ten seconds later RFW-P-1B will trip. The crew should attempt to insert a manual scram prior to the automatic scram at +13 inches.

When the Main Turbine trips and the electrical plant transfers to the Startup Transformer, the startup breakers associated with SM-1, SM-2 and SM-3 will not auto close. This results in a loss of all operating Condensate Pumps, closure of the MSIVs, a loss of CRD and a trip of the Control Air Systems Air Compressors. The crew will take action to establish RPV level control with the RCIC system, and restart CRD pumps (HPCS-P-1 is OOS at the beginning of the scenario). Pressure control will be on SRVs at 800 - 1000 psig.

An aftershock will result in a rupture of the RHR-A suction line from the suppression pool causing flooding in the A-RHR room. The crew will take action per EOP PPM 5.3.1 (Secondary Containment Control). During verification of automatic actions the crew will recognize that the cross connect valve between RHR-A room and the RCIC pump room, FDR-V-607, failed to automatically close (due to a failed R1 sump level switch). Prior to reaching Maximum Safe Operating Value in the RCIC pump room, the crew will manually close FDR-V-607 with the control switch which is located on back panel H13-P632.

Makeup to the Suppression Pool cannot be performed due to HPCS being OOS.

The crew should initiate an Emergency Depressurization per PPM 5.1.3, RPV Depressurization, before Suppression Pool water level drops to 19 feet 2 inches.

The scenario will be terminated when an Emergency Depressurization has been performed and RPV level is being returned to +13 to +54 level band.

LO001751 Rev. 0 Page 3 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 Event No. 1

==

Description:==

Reduce Reactor Power to approximately 70% with flow. Withdraws control rods 38-23, 38-39 and 22-23 per reactivity plan from position 06 to position 10.

This event is initiated by the turnover information.

Time Position Applicants Actions or Behavior T=0 CRS Directs control rod withdrawal per reactivity plan.

ATC Selects control rod 38-23 (then 38-39, then 22-23).

Performs the following to withdraw each control rod one notch each time:

• Verifies control rod position and no rod blocks exist

• Depresses the Withdraw pushbutton

• Observes CRD Drive Header and Cooling Header Flow

• Observes Insert then the Withdraw and then the Settle lights illuminate

• Verifies control rod position when settle function complete COMMENTS:

LO001751 Rev. 0 Page 4 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 Event No. 2

==

Description:==

Control Rod 38-23 Drifts Out of the Core This event is initiated by activating TRIGGER 1 when Control Rod 22-39 (the last control rod to be withdrawn per the Reactivity Plan) is selected to be withdrawn (Note: Drift is on 38-23 NOT 22-39).

Time Position Applicants Actions or Behavior T = 10 ATC Acknowledges the Rod Drift annunciator.

Scans the full core display and observes the red drift light is lit for control rod 38-23 or observes the Rod Worth Minimizer Operator Console display and observes the d associated with rod 38-12.

Per ABN-ROD immediate actions - selects Control Rod 38-23.

Observes the rod position.

Notes that the rod is drifting out of the core.

Per ABN-ROD immediate actions:

Depresses the CONTINUOUS INSERT pushbutton.

Drives Control Rod 38-23 full in.

Releases the Continuous Insert pushbutton.

Observes that Control Rod 38-23 continues to drift out of the core and informs the CRS.

Per ABN-ROD Immediate Actions:

Depresses and Holds the CONTINUOUS INSERT pushbutton.

CRS Per ABN-ROD immediate actions:

Directs Control Rod 38-23 be isolated.

BOP Directs OPS2 to isolate control rod 38-23 by closing CRD-V-103 and CRD-V-105 associated with control rod 38-23.

BOOTH OPERATOR: Wait two minutes and then REMOVE MAL-RMC-004 for rod 38-23.

ROLEPLAY: After malfunction is removed inform the control room that the rod has been isolated.

CRS Directs the ATC operator release the CONTINUOUS INSERT pushbutton for 38-23.

ATC Releases the CONTINUOUS INSERT pushbutton and observes control rod remains fully inserted and informs the CRS.

LO001751 Rev. 0 Page 5 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 CRS Refers to Tech Spec 3.1.3 Control Rod operability and notes condition C applies (Fully insert inoperable control rod within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> AND Disarm the associated CRD within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />).

Conducts Brief.

COMMENT:

LO001751 Rev. 0 Page 6 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 Event No. 3

==

Description:==

SGT-B Strip Heater Fails Resulting in a High Temperature Condition.

This event is initiated by activating TRIGGER 2 after Tech Specs for the Control Rod has been referenced.

Time Position Applicants Actions or Behavior T = 20 BOP Acknowledge the SGT Div B Board K2 Trouble alarm on Board S.

Investigates back panel.

Acknowledges the Charcoal Filter B-1 Outlet Temperature High alarm and refers to ARP.

Observes SGT-TI-6B and notes reading (~265°F).

Refers CRS to ABN-SGT-TEMP/RAD.

CRS/BOP May send OPS2 to SGT-B to investigate locally.

ROLEPLAY: If sent, wait two minutes and report that SGT-B train smells hot and the unit is hot to the touch.

The local temperature indications are higher than normal at 200°F and 230°F. There is no smoke and no indications of a fire.

CRS Per ABN-SGT-TEMP/RAD directs SGT-A be started per SOP-SGT-START.

CRS/BOP Directs SGT-DISC-8B2BL (SGT-ESH-1B) disconnect be opened per ARP.

BOOTH OPERATOR: When SGT-FN-1B12 is started per ABN Trigger 3 will automatically initiate and lower SGT Temperature to 100°F on a 15 minute ramp.

ROLEPLAY: When Trigger 3 initiates, report SGT-DISC-8B2BL has been opened.

BOP Starts SGT-A per SOP-SGT-START section 5.2.2:

If manually initiating SGT Train A with the lead fan at the subsystem level, then perform the following (H13-P827, Bd K1):

a. Verify SGT-V-2A is OPEN (Inlet from Reactor Building).

b. Momentarily turn SGT-FN-1A1 fan control switch from AUTO to PTL SYS. START.

c. Verify the following:

• Main Heaters ENERGIZE as indicated by Main Heater ON light and A1 amp meter.

• SGT-V-5A1 OPENS (Exhaust to Stack).

LO001751 Rev. 0 Page 7 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1

• SGT-FN-1A1 STARTS (within 10 seconds).

d. If required to operate in manual flow control, then perform the following: (MANUAL CONTROL SHOULD NOT BE REQUIRED).

CRS Directs subsequent actions of ABN-SGT-TEMP/RAD be performed to start SGT-B.

BOP Start and recirculate the SGT train that has the charcoal high temperature or high radiation as follows:

Step 4.2.1 Verify SGT-V-1A(1B) is CLOSED (Inlet From Containment).

Step 4.2.2 Verify SGT-V-5A1(5B2) and SGT-V-5A2(5B1) are CLOSED (Exhaust to Stack).

Step 4.2.3 Verify SGT-V-2A(2B) is OPEN (Inlet from Reactor Building).

Step 4.2.4 Verify SGT-V-3A2 (3B1) is OPEN (Fan Inlet).

Step 4.2.5 If possible, then station an HP technician near SGT to monitor for airborne contamination/smoke.

Step 4.2.6 Open SGT-V-4A1(4B2) (Exhaust to Reactor Building).

Step 4.2.7 Place SGT-EHC-1A1(1B2) control switch to ON (Main Heater).

Step 4.2.8 Verify SGT-FN-1A1(1B2) starts within 10 seconds after the Main Heaters energize.

Step 4.2.9 If the SGT system is required to be operable, then declare the SGT train inoperable in the Plant Logging System.

Step 4.2.10 Place SGT-DPIC-1A1(1B2) in MANUAL, and adjust the flow rate to approximately 4000 CFM as indicated by SGT-FR-2A1(2B2).

Step 4.2.11 When the charcoal temperature/radiation has returned to normal, then place SGT in LO001751 Rev. 0 Page 8 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 standby per SOP-SGT-STBY.

Reports SGT-B started per ABN-SGT-TEMP/RAD and temperature decreasing.

CRS Refers to Tech Specs 3.6.4.3 (SGT is inoperable when manual control of SGT-B is taken.

TS 3.6.4.3 Condition A is applicable - Restore SGT subsystem to operable status within 7 days.

COMMENTS:

LO001751 Rev. 0 Page 9 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 Event No. 4

==

Description:==

IBD-FN-1A Motor Fails due to ground. IBD-FN-1B does not Auto start.

This event is initiated by activating TRIGGER 9 after Tech Specs for Standby Gas have been referenced.

Time Position Applicants Actions or Behavior Responds to electrical panel alarms as they annunciate:

T = 20 BOP

• Bus 31 ground

• Gen Bus Duct Clr Flow low

• Gen Bus Duct Air Flow Loss Observes Bus Duct Cooling Fans 1A control switch in run but Green light is on and Red light is off. Observes Bus Duct Cooling Fan 1B is also not running.

Informs the CRS and refers to ARPs.

Informs the CRS that the ARP for Air Flow Loss directs to start the standby fan per SOP-IBD-OPS.

Refers the CRS to ABN-GENERATOR.

CRS May direct the standby fan be started per PPM 1.3.1, Conduct of Operations as an auto action that should have occurred and didn't or may direct starting the standby fan per SOP-IBD-OPS.

BOP Starts IBD-FN-1B as directed. Places IBD-FN-1A C/S to Off and notes that IBD-FN-1B does not auto start.

Places IBD-FN-1B C/S to Run and after dampers reposition, notes it does start.

Observes annunciators clear as bus duct temperatures/parameters return to normal.

Reports system status to CRS.

COMMENTS:

LO001751 Rev. 0 Page 10 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 Event No. 5

==

Description:==

Operating Basis Earthquake. Trip of RFW-P-1A (on a 20 second Time Delay). Failure of RRC Pumps to Automatically runback to 30 Hz.

This event is initiated by activating TRIGGER 4 and is initiated after Tech Specs for SGT has been referenced.

Time Position Applicants Actions or Behavior BOOTH OPERATOR: Start EQ at lowest volume and work to highest volume in 15 seconds then turn off the earthquake machine. Activate TRIGGER 4 five seconds into earthquake simulation.

T = 40 BOP Responds to Board S and announces Operating Basis Earthquake Exceeded alarm.

Refers to ARP and directs the CRS to ABN-EARTHQUAKE.

ATC Recognizes and announces the trip of RFW-P-1A.

Observes RPV level dropping.

Observes RFW-P-1B speed ramping up and reports B Feed Pump responding.

Reports RPV level as it drops to about +20 inches and then begins to return to +36.

CRS Directs runback of the RRC pumps be verified.

ATC Observes P602 indications and recognizes:

• both RRC pumps remain at GT 30 Hz

• both RRC Pump controllers remain in Automatic

• the FW Pump trip amber lights are not lit on either controller

• the Feedwater pump Trip Limit annunciator is not in alarm Reports observations to the CRS.

CRS Directs both RRC pump speeds be lowered to 30 Hz.

ATC May leave master controller in Auto and depress the lower pushbutton to reduce RRC-P-1A and RRC-P-1Bs speed to 30 Hz.

May take manual control of the both RRC pump controllers and depresses the lower pushbutton to reduce RRC-P-1A and RRC-P-1Bs speed to 30 Hz or may depress the master controller to lower speeds to 30 Hz.

Reports both RRC pumps at 30 Hz.

Reports Power/Pressure/Level at end of power reduction.

BOP After referring CRS to ABN-EARTHQUAKE, checks back panel and reports all Amber and all Red lights illuminated.

LO001751 Rev. 0 Page 11 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 CRS Updates crew on ABN-EARTHQUAKE entry.

Per subsequent actions - initiates a controlled Reactor Shutdown per PPM 3.2.1.

Directs ABN-EARTHQUAKE announcement be made.

BOP Makes ABN-EARTHQUAKE announcement.

ROLEPLAY: Booth Operator to Role Play SAS officer.

BOP Goes to Simulator Booth and directs SAS to repeat above announcement on the Alternate Security/Area Wide and Security radio channels.

Directs OPS2 inspection of the Spent Fuel Pool for damage.

COMMENT:

LO001751 Rev. 0 Page 12 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 Event No. 6

==

Description:==

Trip of the B Reactor Feedwater Pump.

This event is initiated by activating TRIGGER 5 and is initiated after the below role play which should be made after actions to reduce RRC flow due to the failure of the pumps to runback and actions for the OBE have taken place.

Time Position Applicants Actions or Behavior T = 50 ROLEPLAY: Call X2171 and as OPS3 report oil on floor in front of the Reactor Feed Pump cabinets which appears to be coming from the control oil system and you are investigating further. Call back one minute later and report that you just opened the cabinet door of the B Reactor Feed Pump and it appears there is a leak in the control oil piping on the B Reactor Feed Pump which is getting larger even as you speak. After the Roleplay THEN activate TRIGGER 5.

ATC Acknowledges annunciator and reports trip of the B Reactor Feedwater pump and may also announce that he is initiating a manual reactor scram.

CRS Directs a manual scram if not already being performed.

ATC Turns Mode switch to SHUTDOWN and announces:

Listen up for the scram report:

Mode switch is in Shutdown, APRMs are downscale, RPV Pressure is xxx, RPV Level is xxx and down fast. Reports EOP entry due to low RPV level.

CRS Repeats back the scram report.

Updates crew on EOP 5.1.1 (RPV Control) EOP entry.

ATC Reports RPV level as it drops below -50.

Verifies RCIC initiation and injection to the RPV at 600 gpm (may increase injection flow to 700 gpm).

CRS Directs +13 and -50 actuations be verified.

ATC/BOP Verifies Containment isolation valves closed by GDS indication (no yellow bordered groups). Verifies RCIC initiated. Verifies HPCS DG start.

ATC Updates crew on MSIV closure (Due to loss of RPS power when buses fail to auto transfer to startup power) and that pressure control is on SRVs at 800 to 1000 psig.

CRS Directs pressure control with SRVs at 800 - 1000 psig pressure band.

COMMENTS:

LO001751 Rev. 0 Page 13 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 Event No. 7

==

Description:==

Failure of the Startup Transformer to Auto Close in on SM-1, SM-2 and SM-3 causing a loss of the Condensate system.

This event is active from the beginning of the scenario and is realized when the Main Turbine trips.

Time Position Applicants Actions or Behavior The Critical Task for this event is to re-power SL-21 which supplies power to Control Room back panel H13-P632 which will allow the closure of FDR-V-607 (refer to EVENT 7).

T=50 BOP Responds to the electrical panels and observes that the Startup breakers have not closed in on SM-1, SM-2 and SM-3 but did close in on SH-5 and SH-6.

Observes and reports that Backup Transformer has closed in and is powering SM-7 and SM-8.

Observes DG-1 and DG-2 have auto started.

BOP May report electrical board status to CRS prior to taking the following actions to re-power SM-1, SM-2 and SM-3:

Places the CB-S1 SYNC Selector switch to MAN position.

Places the CB-S1 Control Switch to CLOSE and observes red light on and green light off.

Places the CB-S1 SYNC Selector switch to OFF position.

Places the CB-S2 SYNC Selector switch to MAN position.

Places the CB-S2 Control Switch to CLOSE and observes red light on and green light off.

Places the CB-S2 SYNC Selector switch to OFF position.

Places the CB-S3 SYNC Selector switch to MAN position Places the CB-S3 Control Switch to CLOSE and observes red light on and green light off.

Places the CB-S3 SYNC Selector switch to OFF position.

BOP Re-powers SL-11, SL-21 and SL-31 using quick card:

2.1 Energizing SL-11 from SM-1 (Dead Bus) 2.1.1 Verify SM-1 is energized.

2.1.2 Verify CB-11/1 green light illuminated and green flag displayed.

LO001751 Rev. 0 Page 14 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 2.1.3 If CB-1/11 is OPEN, then perform the following:

a. Verify CB-1/11 white LOCKOUT CIRCUIT AVAIL light illuminated.

b. Verify CB-1/11 green light illuminated and green flag displayed.

c. Close CB-1/11.

2.1.4 Close CB-11/1.

2.1.5 Verify SL-11 voltage is approximately 480 (432-528) volts.

2.2 Energizing SL-21 from SM-2 (Dead Bus) 2.2.1 Verify SM-2 is energized.

2.2.2 Verify CB-21/2 green light illuminated and green flag displayed.

2.2.3 If CB-2/21 is OPEN, then perform the following:

a. Verify CB-2/21 white LOCKOUT CIRCUIT AVAIL light illuminated.

b. Verify CB-2/21 green light illuminated and green flag displayed.

c. Close CB-2/21.

2.2.4 Close CB-21/2.

2.2.5 Verify SL-21 voltage is approximately 480 (432-528) volts.

2.3 Energizing SL-31 from SM-3 (Dead Bus) 2.3.1 Verify SM-3 is energized.

2.3.2 Verify CB-31/3 green light illuminated and green flag displayed.

2.3.3 If CB-3/21 is OPEN, then perform the following:

a. Verify CB-3/31 white LOCKOUT CIRCUIT AVAIL light illuminated.

b. Verify CB-3/31 green light illuminated and green flag displayed.

c. Close CB-3/31.

2.3.4 Close CB-31/3.

2.3.5 Verify SL-31 voltage is approximately 480 (432-528) volts.

CRS Directs both CRD pumps be started for RPV injection.

LO001751 Rev. 0 Page 15 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 ATC/BOP Places CRD controller to manual and takes control switches for CRD-P-1A and CRD-P-1B to START.

May direct OPS2 perform ABN-CRD-MAXFLOW.

BOOTH OPERATOR: If directed to perform ABN-CRD-MAXFLOW, wait three minutes and then ACTIVATE TRIGGER 26 and report completion when valves have completed repositioning.

BOP Reports High Drywell Pressure EOP entry into PPM 5.2.1 (Primary Containment Control) at 1.68 psig with no indication of a leak in the drywell (due to heat up).

CRS Directs 1.68 psig actuations be verified.

LO001751 Rev. 0 Page 16 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 BOP Verifies 1.68 psig actuations:

RHR-P-2A, RHR-P-2B, RHR-P-2C, LPCS-P-1 running on min flow.

DG-1 and DG-2 are running.

SW-P-1A and SW-P-1B are running.

GDS indicates all containment isolation valves closed except for RCIC-V-8 and RCIC-V-63 (no yellow bordered NSSSS groups).

ATC Reports RPV level slowly recovering.

BOP Reports Main Steam Tunnel high temp alarm and eventual EOP entry into PPM 5.3.1 (Secondary Containment Control), due to Main Steam Tunnel Temp Hi Hi.

Reports EOP 5.2.1 (Primary Containment Control), entry on Drywell Temperature and Wetwell level as they occur.

ATC/BOP Recognizes CAS air compressors do not restart on loss of power.

Directs OPS3 to reset CAS air compressors.

ROLEPLAY: A minute after the request to reset CAS, ACTIVATE TRIGGER 23 and when compressors have restarted, report completion to the Control Room.

CRS May decide to expand RPV level band to -50 to +54.

May direct SLC initiation and injection into RPV as an Alternate Injection System (Table 3 of EOP 5.1.1 RPV Control).

ATC If directed, injects with both SLC Systems using SOP-SLC-INJECTION-QC:

2.1 Remove the SLC keylock switch blanks, and insert both keys into the SLC System control switches.

2.2 Initiate SLC injection by performing the following (H13-P603):

• PLACE SLC System A control switch to the OPER position.

• PLACE SLC System B control switch to the OPER position.

2.3 Report the following to the CRS:

• SLC flow rate (-82 gpm)

• Initial tank level (4800 gal)

• RWCU-V-4 status (should be closed)

COMMENTS:

LO001751 Rev. 0 Page 17 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 LO001751 Rev. 0 Page 18 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 Event No. 8

==

Description:==

Earthquake tremor causes a rupture in the RHR-A suction piping resulting in flooding of the RHR-A pump room and Suppression Pool Water Level to drop. Emergency Depressurize the RPV when it is determined that Suppression Pool water level cannot be maintained GT 19 2.

The event is initiated by activating TRIGGER 6 and is initiated after plant has been stabilized, the electrical buses have been re-energized and RPV level is GT -50.

Time Position Applicants Actions or Behavior The Critical Task for this event is to initiate an Emergency Depressurization prior to Suppression Pool Water Level reaching 192.

BOOTH OPERATOR: Start EQ and work back to highest volume in 10 seconds then turn off the earthquake machine. Activate TRIGGER 6 five seconds into earthquake simulation.

T=60 BOP Acknowledges the Suppression Pool Level Hi/Low alarm (P601-A11 2-3 and P601-A12 2-3).

Reports Suppression Pool level dropping giving actual level and trend.

Reports EOP entry into PPM 5.2.1 (Primary Containment Control) on Low Suppression Pool level when level drops to LT -2.

CRS Directs field investigation by OPS2.

Updates crew on PPM 5.2.1 (Primary Containment Control) EOP entry.

ROLE-PLAY - Two minutes after being directed to investigate, report that there is a crack in the piping between the Suppression Pool and the RHR Pumps suction valve, RHR-V-4A. Room water level is rising and you are leaving the room. If asked, the break cannot be isolated.

NOTE: It takes about five minutes after trigger actuation to get the RHR-A Pump Room High Level EOP entry alarm and BISI. The R1 sump high level alarm does not annunciate due to failed level switch which also causes FDR-V-607 not to auto close.

BOP Acknowledges RHR A PUMP ROOM WATER LEVEL HIGH annunciator and BISI and reports EOP entry into PPM 5.3.1 (Secondary Containment Control).

Refers to ARP:

May contact the RWCR Operator to verify sump pumps FDR-P-1A and FDR-P-1B operating.

Refers CRS to ABN-FLOODING.

LO001751 Rev. 0 Page 19 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 Verifies FDR-V-607 closed on P632 and observes valve is actually opened.

Takes FDR-V-607 control switch to close and observes green light on and red light off.

Informs CRS.

CRS Updates crew on PPM 5.3.1 (Secondary Containment Control) EOP entry.

Refers ABN-FLOODING and directs actions:

• Directs evacuation of affected Area (RHR-A Pump Room).

• Directs RHR-P-2A be stopped (Note: Pump will eventually trip on overload if not secured).

• Directs the control power fuses be removed for RHR-P-2A.

• Locate and isolate the source of the flooding per Section 7.2.

• Monitor adjacent ECCS Pump rooms for flooding.

ROLE-PLAY - Two minutes after request to pull RHR-P-2A fuses, ACTIVATE TRIGGER 7 and report control power fuses for RHR-P-2A have been pulled.

BOP Makes evacuation announcement as directed per ABN-FLOODING:

• Sounds Alerting tone for 5-10 seconds

• Alert station personnel to flooding in the RHR-A Pump Room

• Evacuates all non-emergency personnel from the affected area

• Refers to PPM 13.5.1 for localized evacuation.

COMMENTS:

LO001751 Rev. 0 Page 20 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 Event No. 9

==

Description:==

FDR-V-607 (the RHR-A / RCIC Room cross-connect valve) Fails to Auto Close.

This event is initiated by the CRS when it has been determined that Suppression Pool Water Level cannot be maintained GT +192.

The Critical Task is to close FDR-V-607 prior to exceeding Max Safe Operating Level in the RCIC Pump Room.

Time Position Applicants Actions or Behavior T = 75 CRS Recognizes HPCS-P-1 is not available and Suppression Pool Water Level cannot be maintained GT +192.

CRS Updates crew on requirement to initiate an Emergency Depressurization.

Updates crew on PPM 5.1.3 (RPV Depressurization) EOP entry.

Exits the Pressure leg of PPM 5.1.1 (RPV Control), and enters PPM 5.1.3 (Emergency RPV Depressurization).

Determines if RPV injection with LPCS and RHR is required based on RPV Level and trend (It is anticipated that one ECCS pump will be used to return RPV water level back to +13 to +54 level band with RCIC eventually isolating on low RPV pressure).

Determines Wetwell level is above 17.

Directs 7 SRVs (ADS preferred) be opened.

BOP Opens SRVs as directed starting with the first ADS SRV and working to the last.

As each SRV is opened, observes Primary Containment pressure response.

Comments:

LO001751 Rev. 0 Page 21 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 TURNOVER INFORMATION Initial Conditions HPCS-P-1 is undergoing schedule maintenance as the pump shaft has been removed.

The following have been protected per PPM 1.3.83 - RCIC-P-1, LPCS-P-1, DG-1, DG-2, ADS-A, ADS-B SW-A, SW-B, TR-S, TR-B.

Reactor power has been lowered to support a Control Rod Set.

The #1 and #2 RFW Heaters have been removed from service per the Reactivity Control Plan.

The reactivity brief and the task preview for the shifts scheduled activities have been completed.

An SNE is stationed in the Control Room to monitor core conditions.

Shift Directions Continue with the Reactivity Control Plan (RCP) to adjust control rods to the target pattern and then return the plant to 100% power.

Page 22 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 SIMULATOR SETUP INSTRUCTIONS Reset to Saved IC#172 (75% Power, FW Heaters #1 and #2s Removed From Service)

Hang Blue Tags on HPCS-P-1 and HPCS-V-4.

Depress the Manual Out Of Service BISI for the HPCS System.

Make it a Div 3 Work Week.

Flag locked in annunciators.

Protect the following per PPM 1.3.83 - RCIC-P-1, LPCS-P-1, DG-1, DG-2, ADS-A, ADS-B, SW-A, SW-B, TR-S and TR-B.

Set up the Earthquake Machine on lowest volume.

LO001751 Rev. 0 Page 23 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1 SCHEDULE FILE

<SCHEDULE>

<ITEM row = 1>

0

<ACTION>Insert remote LOA-EPS140 to RACKED-OUT</ACTION>

<DESCRIPTION>HPCS-V-4 Breaker Racked out</DESCRIPTION>

</ITEM>

<ITEM row = 2>

0

<ACTION>Insert remote LOA-EPS374 to RACKED-OUT</ACTION>

<DESCRIPTION>HPCS-P-1 Breaker Racked out</DESCRIPTION>

</ITEM>

<ITEM row = 3>

0

<ACTION>Insert malfunction MAL-RFC019</ACTION>

<DESCRIPTION>FAILURE OF ALL FWC INPUTS To RRC ASD</DESCRIPTION>

LO001751 Rev. 0 Page 24 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1

</ITEM>

<ITEM row = 4>

0

<ACTION>Insert malfunction MAL-PCN002R to 850000</ACTION>

<DESCRIPTION>RUPT MS-RV-4D TAILPIP ABOVE SUPP POOL LVL</DESCRIPTION>

</ITEM>

<ITEM row = 5>

0

<ACTION>Insert malfunction BST-SCN020F to FAIL_TO_TRIP</ACTION>

<DESCRIPTION>LEVEL SWITCH for FDR-V-607</DESCRIPTION>

</ITEM>

<ITEM row = 6>

0

<ACTION>Insert malfunction BKR-EPS049 to FAI_AUT_CLOS</ACTION>

<DESCRIPTION>SM-1 STARTUP</DESCRIPTION>

</ITEM>

LO001751 Rev. 0 Page 25 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1

<ITEM row = 7>

0

<ACTION>Insert malfunction BKR-EPS050 to FAI_AUT_CLOS</ACTION>

<DESCRIPTION>SM-2 STARTUP</DESCRIPTION>

</ITEM>

<ITEM row = 8>

0

<ACTION>Insert malfunction BKR-EPS051 to FAI_AUT_CLOS</ACTION>

<DESCRIPTION>SM-3 STARTUP</DESCRIPTION>

</ITEM>

<ITEM row = 9>

0

<EVENT>1</EVENT>

<ACTION>Insert malfunction MAL-RMC004-3823 to OUT on event 1</ACTION>

<DESCRIPTION>ROD 38-23 DRIFTS OUT</DESCRIPTION>

</ITEM>

<ITEM row = 10>

LO001751 Rev. 0 Page 26 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1

0

<EVENT>2</EVENT>

<ACTION>Insert malfunction XMT-SCN111A to 275 on event 2</ACTION>

<DESCRIPTION>SGT-TE-6B FOR SGT-1B1 OUTLET TEMP</DESCRIPTION>

</ITEM>

<ITEM row = 11>

0

<EVENT>2</EVENT>

<ACTION>Insert malfunction XMT-RMS034A to 2 on event 2</ACTION>

<DESCRIPTION>ARM-RE-8 SGT FILTER AREA</DESCRIPTION>

</ITEM>

<ITEM row = 12>

0

<EVENT>3</EVENT>

<ACTION>Insert malfunction XMT-SCN111A from 275.0 to 100.0 in 900 on event 3</ACTION>

<DESCRIPTION>SGT-TE-6B FIXED OUTPUT SGT-CF-1B1 OUTLET TEMP</DESCRIPTION>

</ITEM>

LO001751 Rev. 0 Page 27 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1

<ITEM row = 13>

0

<EVENT>4</EVENT>

<ACTION>Insert malfunction MAL-RWB001 to 0.222 on event 4 delete in 10</ACTION>

<DESCRIPTION>OBE EARTHQUAKE</DESCRIPTION>

</ITEM>

<ITEM row = 14>

0

<EVENT>4</EVENT>

<ACTION>Insert malfunction XMT-FPT020A after 10 to 10 in 20 on event 4</ACTION>

<DESCRIPTION>RFT-1A CONTROL OIL PRESS METER</DESCRIPTION>

</ITEM>

<ITEM row = 15>

0

<EVENT>4</EVENT>

<ACTION>Insert malfunction RLY-FPT007F after 20 to TRIP on event 4</ACTION>

<DESCRIPTION>RFT-1A CONTROL OIL PRESSURE LOW</DESCRIPTION>

</ITEM>

LO001751 Rev. 0 Page 28 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1

<ITEM row = 16>

0

<EVENT>4</EVENT>

<ACTION>Insert override OVR-FPT002B after 20 to ON on event 4</ACTION>

<DESCRIPTION>TURBINE 1A EMERG TRIP TO TRIP</DESCRIPTION>

</ITEM>

<ITEM row = 17>

0

<EVENT>5</EVENT>

<ACTION>Insert malfunction XMT-FPT021A to 10 in 20 on event 5</ACTION>

<DESCRIPTION>RFT-1B CONTROL OIL PRESS METER</DESCRIPTION>

</ITEM>

<ITEM row = 18>

0

<EVENT>5</EVENT>

<ACTION>Insert malfunction RLY-FPT008F after 15 to TRIP on event 5</ACTION>

<DESCRIPTION>RFT-1B CONTROL OIL PRESSURE LOW</DESCRIPTION>

LO001751 Rev. 0 Page 29 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1

</ITEM>

<ITEM row = 19>

0

<EVENT>5</EVENT>

<ACTION>Insert override OVR-FPT007B after 20 to ON on event 5</ACTION>

<DESCRIPTION>TURBINE 1B EMERG TRIP TO TRIP</DESCRIPTION>

</ITEM>

<ITEM row = 20>

0

<EVENT>6</EVENT>

<ACTION>Insert malfunction MAL-RWB001 to 0.222 on event 6 delete in 10</ACTION>

<DESCRIPTION>EARTHQUAKE</DESCRIPTION>

</ITEM>

<ITEM row = 21>

0

<EVENT>6</EVENT>

<ACTION>Insert malfunction MAL-RHR001 to 8400 in 600 on event 6</ACTION>

LO001751 Rev. 0 Page 30 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1

<DESCRIPTION>RHR-A Suction Line rupture</DESCRIPTION>

</ITEM>

<ITEM row = 22>

0

<EVENT>6</EVENT>

<ACTION>Insert remote PLP-PCN003 to 18 in 900 on event 6</ACTION>

<DESCRIPTION>Suppression Pool Water Level</DESCRIPTION>

</ITEM>

<ITEM row = 23>

0

<EVENT>7</EVENT>

<ACTION>Insert remote LOA-EPS384 to RACKED-OUT on event 7</ACTION>

<DESCRIPTION>RHR-P-2A Breaker Racked out</DESCRIPTION>

</ITEM>

<ITEM row = 24>

0

<EVENT>8</EVENT>

LO001751 Rev. 0 Page 31 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1

<ACTION>Insert malfunction MOV-RHR029F to FAIL_AS_IS on event 8</ACTION>

<DESCRIPTION>RHR-V-4A</DESCRIPTION>

</ITEM>

<ITEM row = 25>

0

<EVENT>8</EVENT>

<ACTION>Insert override OVR-RHR054B after 150 to OFF on event 8</ACTION>

<DESCRIPTION>RHR-V-4A RED LAMP</DESCRIPTION>

</ITEM>

<ITEM row = 26>

0

<ACTION>Event Events/LO001751.evt</ACTION>

<DESCRIPTION>Activate Triggers 3 for SGT and 8 for RHR-A</DESCRIPTION>

</ITEM>

<ITEM row = 27>

0

<ACTION>Schedule local.sch</ACTION>

LO001751 Rev. 0 Page 32 of 24

Appendix D NRC EXAM SCENARIO #2 FORM ES-D-1

<DESCRIPTION>Load Local Operator Actions</DESCRIPTION>

</ITEM>

</SCHEDULE>

EVENT FILE

<EVENT>

<TRIGGER id="3" description="SGT-FN-1B2 START KICKS TRG 3 TO LOWER TEMPERATURE">XKRO033R &gt 0</TRIGGER>

<TRIGGER id="8" description="RHR-V-4A GREEN KICKS TRG 8 TO GIVE INDICATIONS VALVE CLOSES">X01O343G &gt 0</TRIGGER>

</EVENT>

LO001751 Rev. 0 Page 33 of 24

NRC EXAM SCENARIO #3 INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION Raise Power with Flow to 100%; Perform OSP-HPCS/IST-Q701; HPCS Min Flow Fuses Clear; CRD-P-1B Trips; Grid Disturbance, ASD Channel 1B1 Trips; Grid Disturbance, Lockout on LESSON TITLE SH-5 and SH-6, Manual Scram; Hydraulic ATWS; Inject SLC, RWCU-V-4 Fails to Auto Close; Lower Level, S/R/S Inserts Control Rods LENGTH OF LESSON 1.5 Hours INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code LO001752 Rev. No. 0 JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 12/09/12 REVISED BY DATE VALIDATED BY DATE TECHNICAL REVIEW DATE INSTRUCTIONAL REVIEW DATE SAT Coordinator APPROVED DATE Operations Training Manager

NRC EXAM SCENARIO #3 Facility: Columbia Scenario No.: 3 Op-Test No.: 2013 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: The plant is operating at 95% power. RCC-P-1B is tagged out due to excessive vibrations and imminent failure. OSP-HPCS/IST-Q701, HPCS System Operability Test, is in-progress.

Turnover: Return Columbia to 100% power. Continue with the performance of OSP-HPCS/IST-Q701, starting at Step 7.3. The two year VPI and channel calibration are NOT due. The pre-job brief has been completed, and Equipment Operators are on station to support completion of the surveillance. The power increase and surveillance are to be performed concurrently.

Event Timeline Event Type* Event Description No.

1 T=0 R (ATC) Increase Reactor Power from 95% to 100% with RRC Flow.

R (CRS) 2 T=0 N (BOP) Perform the HPCS System Operability Test, OSP-HPCS/IST-Q701.

N (CRS) 3 T = 15 I (BOP) The HPCS min flow, HPCS-V-12, fuses clear while closing. (Tech Spec).

I (CRS) 4 T = 25 C (ATC) CRD-P-1B trips on low suction pressure.

C (CRS) 5 T = 45 C (CRS) A grid disturbance causes a trip of ASD Channel 1B1. (Tech Spec)

R (ATC) Power reduction by lowering RRC-P-1A speed to match loop flows.

LO001752 Rev. 0 Page 1 of 22

NRC EXAM SCENARIO #3 6 T = 60 C (ATC) Another grid disturbance results in a lockout of SH-5 and SH-6, and a complete loss of RRC flow requiring a manual reactor scram.

C (CRS) 7 T = 60 M (All) Hydraulic ATWS.

Inhibit ADS prior to automatic initiation to prevent an uncontrolled depressurization and significant power excursion (Critical Task).

Terminate and prevent injection into the RPV with the exception of SLC, RCIC, and CRD, to establish an LL (Critical Task).

Perform PPM 5.5.11 to insert control rods. Rods insert. Return RPV level to normal band (Critical Task).

8 T = 65 C (ATC) Inject Standby Liquid Control (boron) prior to exceeding 110°F Suppression Pool temperature (Critical Task).

RWCU-V-4 fails to automatically close when SLC is initiated.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor LO001752 Rev. 0 Page 2 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 Columbia is at 95% power due to economic dispatch. BPA has just requested Columbia return to 100%. Additionally, OSP-HPCS/IST-Q701 is in progress and will be continued after shift turnover.

The ATC will raise reactor power with RRC flow to achieve 100% power.

The BOP operator will perform the HPCS surveillance. As full flow test conditions are established, the Min Flow valve for HPCS-P-1 fuses will clear. The crew should back out of the surveillance and secure HPCS-P-1. Tech Specs will be referenced and HPCS will be declared inoperable.

The next event is a trip of CRD-P-1B on low suction pressure. ABN-CRD will be entered and both suction filters will be placed into service. CRD-P-1A will be started.

The next event is a grid disturbance that results in multiple annunciators and ASD Channel 1B1 tripping causing RRC-P-1B to run back to 51 Hz. The crew will lower RRC-P-1A speed to match loop flows.

Another grid disturbance will result in a lockout on SH-5 and then SH-6 which results in a loss of both RRC pumps. Per immediate actions of ABN-RRC-LOSS a manual reactor scram will be inserted.

The crew will recognize a hydraulic ATWS condition exists. The crew will take manual control of HPCS and will inhibit ADS. RCIC-V-1 will be closed to prevent RCIC initiation at -50 (which would cause the Main Turbine to trip).

Standby Liquid Control will be initiated and when initiated, SLC flow will be only 18 gpm due to relief valves lifting.

PPM 5.5.6 will be performed to prevent the MSIVs from closing when RPV level is lowered.

PPM 5.5.1 will be performed to make all ECCS injection valves throttleable.

The crew will stop and prevent injection into the RPV and establish an Lowered Level of -65 with RPV level being maintained between -80 and -140.

PPM 5.5.11 will be performed to insert control rods.

Control rods will go in after RPV level has been lowered and is being controlled -80 to -140.

When all control rods are inserted the crew will stop SLC injection and return RPV level back to +13 to +54 level band.

The scenario will be terminated when RPV level has been returned to normal.

Page 3 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 Event No. 1

==

Description:==

Raise power with Flow from 95% to 100%.

This event is initiated by the turnover information.

Time Position Applicants Actions or Behavior T=0 CRS Directs ATC to raise power with flow to achieve 100% reactor power at a rate not to exceed 10MWE/min or 1Hz per minute.

ATC Notes Reactor Power and RRC pump flow and Hz indications.

Verifies both RRC pumps individual controllers are in AUTO and depresses Master Controller Raise P/B to increase flow/power as directed.

Informs the CRS when power is 100%.

COMMENTS:

Page 4 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 Event No. 2

==

Description:==

Perform the HPCS System Operability Test, OSP-HPCS/IST-Q701.

This event is initiated by turnover information.

Time Position Applicants Actions or Behavior T=0 7.3.3 If not already operating, then start HPCS-P-2 (Service Water Pump) (H13-P601).

Takes HPCS-P-2 control switch to start and observes red light on, green light off.

7.3.4 If not already open, then verify SW-V-29 auto opens. (Service Water Pump Discharge) (H13-P601).

Observes SW-V-29 red light on green light off and rising discharge pressure on SW-PI-40.

7.3.5 Verify HPCS-P-1 Motor upper and lower lubricant levels are normal. Record SAT in the Driver Lubrication Measured Value space on Attachment 9.2.

Contacts OPS2 and directs step performance.

ROLEPLAY: VERIFY HPCS-P-1 Motor upper and lower lubricant levels are normal.

7.3.6 Verify H13-P601.A1-6.7, HPCS WATER LEG PUMP DISCH PRESS LOW is clear.

Verify HPCS System pressure GE 50 psig per HPCS-PIS-13 (H22-P024) (RB 471).

Contacts OPS2 and requests gage reading.

ROLEPLAY: HPCS-PIS-13 is reading 90 psig.

7.3.8 If HPCS is required to be operable, then enter HPCS as inoperable, but available, in the Plant Logging System.

Informs the CRS to perform this step.

7.3.9 Open HPCS-V-10 (Inboard Test Valve).

Takes control switch for HPCS-V-10 to open and observes valve position indication on HPCS-P01-606 on P601 vertical board.

Page 5 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 7.3.10 If non-intrusive testing is scheduled for HPCS-V-2 and/or HPCS-V-24, then notify Electricians that HPCS-V-2 and HPCS-V-24 are about to open.

7.3.11 Start HPCS-P-1 (H13-P601).

Makes plant announcement of the intent to start HPCS-P-1.

Takes control switch for HPCS-P-1 to start and observes red light on, green light off and amps rising and discharge pressure rise.

7.3.12 Verify HPCS-V-12 (Minimum Flow Valve) auto opens.

Observes HPCS-V-12 red light on and Green light off.

ROLEPLAY: A minute after HPCS-P-1 starts, As OPS2, inform the Control Room that the pump start looks good. ALso call as OPS4 that HPCS-P-2 start looks good.

7.3.13 Throttle open HPCS-V-11 (Outboard Test Valve) to adjust system flow at HPCS-FI-603 to 6560 gpm (GE 6500 gpm but LE 6690 gpm).

Takes control switch for HPCS-V-11 to open and observes valve position indication on HPCS-P01-604 on P601 vertical board.

Observes HPCS flow rising on HPCS-FI-603 as HPCS-V-11 is opened.

7.3.14 Verify HPCS-V-12 (Minimum Flow Valve) auto closes above approximately 1300 gpm.

Observes HPCS-V-12 start to close (green light comes on) as flow is raised GT 1300 gpm.

SEE NEXT EVENT COMMENT:

Page 6 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 Event No. 3

==

Description:==

HPCS-V-12, HPCS Minimum Flow Valve fuses clear.

This event is initiated by EVENT TRIGGER 1 which automatically activates when HPCS flow rises to 3000 gpm.

Time Position Applicants Actions or Behavior T = 10 BOP Observes both the green alight and the red light for HPCS-V-12 go out.

Acknowledges the HPCS OUT OF SERVICE alarm and the MOV Network Pwr loss/OL BISI.

Informs the CRS of indication and alarm/BISI.

CRS May direct HPCS-V-11 be closed and HPCS-P-1 be secured or may direct BOP operator to back out of the surveillance procedure.

BOP Performs actions to secure HPCS as directed by the CRS.

CRS Contacts Work Control / Production about HPCS-V-12.

Refers to Tech Specs and notes LCO 3.5.1 Condition B applies (Verify RCIC operable by administrative means immediately; AND restore HPCS to operable status within14 days). PAM 3.3.3.1 (30 days). Also is reportable to NRC due to single train failure within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

CRS Directs Control Power fuses for HPCS-P-1 be pulled.

BOP ROLEPLAY: Wait three minutes and then ACTIVATE TRIGGER 2 and report completion.

CRS Conducts Brief.

COMMENTS:

Page 7 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 Event No. 4

==

Description:==

CRD-P-1B Trips on Low Suction Pressure.

This event is initiated by activating TRIGGER 3 and is initiated after Tech Specs for HPCS have been referenced and brief has been completed.

Time Position Applicants Actions or Behavior T = 25 ATC Acknowledges CRD PUMP B SUCTION PRESS LOW alarm and refers to ARP.

Acknowledges CRD PUMP ABNORMAL OPERATION alarm and refers to ARP.

Observes CRD-P-1B not running and informs the CRS.

Refers CRS to ABN-CRD.

When Accumulator alarms come in, refers the CRS to Tech Spec 3.1.5.

CRS Updates crew on ABN-CRD entry.

Refers to ABN-CRD and directs placing both CRD suction filters in service per ABN-CRD-MAXFLOW (due to the CRD PUMP B SUCTION PRESS LOW alarm that was in and cleared).

ROLEPLAY: Wait two minutes and then ACTIVATE TRIGGER 26 and report completion.

CRS Notes time the second accumulator alarm comes in and starts the 20 minute clock (see ABN-CRD step 4.1.1).

CRS May hand off ABN completion to ATC or direct individual steps.

Directs placing CRD-FC-600, CRD Flow Controller, in MANUAL at zero output.

ATC Places the CRD Flow Controller in MANUAL by moving black knob to the left over the M.

Depresses the Close pushbutton until the red arrow lowers and is over the 0.

CRS Directs the standby CRD pump, CRD-P-1A be started (May direct the tripped CRD pump be re-started if he determines the cause for the trip is known and has been corrected -Low suction trip corrected by placing both suction filters in service) (CRD-P-1B will trip immediately if restarted)..

ATC Starts CRD pump as directed by taking control switch to start.

Observes amps, pressure indications for CRD pump start.

CRS Directs CRD-FC-600 be nulled and transferred to Auto.

ATC Depresses the Open pushbutton until the red arrow is in the green band.

Moves black lever to the right until over the A.

Observes CRD accumulator alarms clearing.

Page 8 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 Informs the CRS when all accumulator alarms have cleared.

COMMENTS:

Page 9 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 Event No. 5

==

Description:==

Grid Disturbance, ASD Channel 1B1 Fault Trip This event is initiated by activating TRIGGER 4 and is initiated after a CRD pump has been re-started and all CRD accumulators have cleared.

Time Position Applicants Actions or Behavior T=45 ATC Acknowledges various annunciators associated with the grid disturbance.

Acknowledges ASD 1B/1 Alarm and ASD 1B/1 Fault annunciators.

Observes the following indication:

Loop B ASD Channel Failure Limit light illuminated.

RRC-P-1B speed is 51Hz.

Green light on (Red light off) for ASD Channel 1B1.

B RRC Pump controller has transferred to Manual.

Informs CRS that ASD Channel 1B1 has tripped off.

Reports current Reactor Power, Pressure and Level.

Acknowledges A or B Hi Flow Delta annunciator.

Observes Loop B flow at 36,000 gpm and Loop A flow at 44,000 gpm.

CRS Updates crew on ABN-POWER entry.

Refers to Tech Spec 3.4.1, flow mismatch, which is applicable until flows are matched.

Contacts Production/Work Control concerning ASD Channel fault.

Directs RO to match RRC loop flows by lowering RRC Loop A flow.

ATC Reduces RRC-P-1A speed as directed to match flows and clear High Flow Delta alarm (may reduce RRC-A speed with controllers in Auto or may take manual control of RRC-M/A-R676A).

ATC Reports Reactor Power, Pressure and Level after the flow reduction.

Page 10 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 COMMENTS:

Page 11 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 Event No. 6

==

Description:==

Another Grid Disturbance and Lockout on SH-5 and SH-6 causing a loss of both RRC Pumps and a manual scram insertion.

The event is initiated by activating TRIGGER 5 and is initiated after plant has been stabilized and RPV level is STEADY at

+36.

Time Position Applicants Actions or Behavior T=60 ATC Acknowledges various annunciators associated with the grid disturbance.

BOP Responds to electrical plant and recognizes and reports lockout on SH-5 and SH-6.

May not initially report lockouts due to loss of RRC Pumps and insertion of manual scram.

ATC Acknowledges alarms associated with loss of both RRC Pumps.

Recognizes the loss of both RRC pumps and announces intent to initiate a manual reactor scram per immediate actions of ABN-RRC-LOSS.

Inserts a manual reactor scram by turning Mode switch to SHUTDOWN and announces:

Listen up for the scram report:

Mode switch is in Shutdown, APRMs are NOT downscale, current RPV Pressure and trend, and current RPV Level and trend. Reports EOP entry due to failure to scram.

COMMENTS:

Page 12 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 Event No. 7

==

Description:==

Hydraulic ATWS.

This event is active at the beginning of the scenario and is realized when a manual reactor scram is inserted.

Time Position Applicants Actions or Behavior Critical Task is to inhibit ADS prior to an automatic initiation to prevent an uncontrolled depressurization and significant power excursion.

Critical Task is to terminate and prevent injection into the RPV with the exception of SLC, RCIC, and CRD, to establish an Lowered Level.

Critical Task is to Insert Control Rods.

T = 60 ATC Continues with immediate scram actions after recognizing all control rods did not insert:

• Depress the manual scram pushbuttons

• Initiate ARI and verifies valves opened

• Insert SRMs and IRMs Reports reactor power at approximately 45%.

CRS Updates crew on EOP entry into PPM 5.1.1 (RPV Control), and directs/verifies that the Mode Switch has been placed in SHUTDOWN.

Updates crew and exits PPM 5.1.1 (RPV Control) and transitions to PPM 5.1.2 (RPV Control -

ATWS).

Directs BOP to:

• Inhibit ADS and take manual control of HPCS.

• Verify actuations for +13 and -50 as they occur.

• Verify pressure is being maintained by the bypass valves in Auto.

BOP Takes both ADS control switches to the INHIBIT position and acknowledges associated alarms and BISIs.

Arms and Depresses the HPCS system initiation P/B while holding the control switch for HPCS-P-1 to STOP.

Closes HPCS-V-4 when it get fully opened.

Reports ADS inhibited and manual control of HPCS taken to CRS.

CRS Directs bypassing the MSIV isolation interlocks on high tunnel temperature and low RPV level per PPM 5.5.6.

CRS Goes to EOP drawer and gets PPM 5.5.6 procedure and equipment bag containing two keys.

Page 13 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 Performs PPM 5.5.6:

• At H13-P609 places MS-RMS-S84 to BYPASS

• At H13-P611 places MS-RMS-S85 to BYPASS Updates Crew on the completion of PPM 5.5.6.

T = 65 CRS Directs RCIC-V-1 be closed to keep Main Turbine on line when RPV level is lowered.

BOP Closes RCIC-V-1, verifies RCIC trip annunciator and reports completion to CRS.

CRS Directs performance of PPM 5.5.1, Overriding ECCS valve logic to allow throttling RPV injection.

BOP Goes to EOP drawer and pulls PPM 5.5.1 procedure and equipment bag containing 5 keys.

Performs PPM 5.5.1:

• HPCS - Override HPCS-V-4 (HPCS RPV injection valve) automatic logic by placing HPCS-RMS-S25 in the OVERRIDE position (H13-P625).

• LPCS - Override LPCS-V-5 (LPCS RPV injection valve) automatic logic by placing LPCS-RMS-S21 in the OVERRIDE position (H13-P629).

• RHR Loop A - Override RHR-V-42A (RHR RPV injection valve) automatic logic by placing RHR-RMS-S105 in the OVERRIDE position (H13-P629).

• RHR Loop B - Override RHR-V-42B (RHR RPV injection valve) automatic logic by placing RHR-RMS-S106 in the OVERRIDE position (H13-P618).

• RHR Loop C - Override RHR-V-42C (RHR RPV injection valve) automatic logic by placing RHR-RMS-S107 in the OVERRIDE position (H13-P618).

Updates crew to completion of PPM 5.5.1, and that the ECCS injection valves are closed and throttleable.

Page 14 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 CRS Direct the ATC to:

• Stop and prevent condensate and feedwater.

• Lower level to a band less than -65 but greater than -183 (preferred band is -80 to -

140).

• Commence RPV injection at -65.

ATC Uses Quick Cards to stop and prevent Condensate and Feedwater and lines up on the startup flow control valves as directed:

Step 2.1.1 If Reactor Feed Pump(s) (RFP) are operating, then perform the following:

a. Verify RFP(s) have ramped down in speed.

b. Verify RFW-FCV-2A(B) is operating properly in Automatic (Minimum Flow Valve)

(H13-P840).

c. If RFW-FCV-2A(B) is not operating properly and is cycling, complicating Reactor Level Control, then place RFW-FCV-2A(B) in Manual, and slowly open to approximately 80%.

d. Place RFW-P-1B in MDEM mode using either RFT-COMP-1 or RFT-COMP-2 (Pump Control Screen) as follows (H13-P840):

1) Select MDEM.

2) Select YES.

e. Place RFW-P-1A in MDEM mode using either RFT-COMP-1 or RFT-COMP-2 (Pump Control Screen) as follows (H13-P840):

1) Select MDEM.

2) Select YES.

Page 15 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1

f. Control Turbine speed as required.

Step 2.1.2 If Feedwater Temperature Reduction was in progress, then verify RFW-V- 109 is Closed (H13-P840).

Step 2.1.3 Start closing RFW-V-112A and RFW-V-112B (H13-P840). (2H)

Step 2.1.4 Start opening RFW-V-118 (Throttle valve) (H13-P840).

Step 2.1.5 Verify the following Open (H13-P840): (2H)

• RFW-V-117A

• RFW-V-117B Step 2.1.6 Verify RFW-LIC-620 is in MANUAL (V selected for Valve position demand) with 0 output (Startup RPV Level Control) (H13-P603).

Step 2.1.7 Verify RFW-V-112A and RFW-V-112B are Fully Closed.

Step 2.1.8 Verify RFW-V-118 is Fully Open.

Page 16 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 Reports EOP entry on low RPV water level at +13.

Reports Reactor Power as it drops due to lowering level.

When Reactor Power is LT 5%, marks RPV level to establish an LL.

Step 2.1.9 If Reactor Feed Pump(s) (RFP) are operating, then adjust the running RFP speed to establish ~ 200 psid across RFW-FCV-10A & 10B using either Feedwater touch screen (H13-P840).

Step 2.1.10 Adjust RFW-LIC-620 manual output to control RPV level.

Maintains RPV level between LL and -183 as directed (-80 to -140).

T = 70 CRS Directs PPM 5.5.11 be performed to insert control rods.

BOOTH OPERATOR: Be standing next to Board S to get direction from BOP operator to perform .1.

BOP Goes to EOP drawer and pulls procedure for PPM 5.5.11 and equipment bag.

Performs PPM 5.5.11:

Determines that no RPS scram lights are lit Removes one TB1 ARI fuse (P650 F01, F02, F03 or F04)

Removes one TB2 ARI fuse (P650 F01, F02, F03 or F04).

Determines that some or all blue scram valve lights are lit.

Determines Tab B should be performed:

TAB B:

Places the SDV HIGH LEVEL TRIP control switch to BYPASS.

Determines the scram cannot be reset.

Overrides RPS trip signals per Attachment 6.1.

BOP ATTACHEMNT 6.1 Goes to Board S and directs booth operator to perform back panel operations associated with Attachment 6.1 (may also direct Attachment 6.2 at this point).

Page 17 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 BACK PANEL OPERATOR: Take direction from the BOP operator. If Attachment 6.1 is directed, wait three minutes and then Activate TRIGGER 28 to install RPS jumpers.

When completed, circle slash the procedure steps and inform the BOP operator that they have been completed by standing next to Board S and giving the crew an update:

UPDATE READY - Attachment 6.1 of PPM 5.5.11 has been completed, END OF UPDATE.

BOP Continues with Tab B actions:

Reset the scram (by depressing reset pushbuttons).

Ensures both CRD pumps are running (the tripped CRD pump may or may not be re-started per this step but if restarted it will immediately trip).

BACK PANEL OPERATOR: Be standing next to Board S to get direction from BOP operator to perform .2.

BOP Directs Back Panel Operator to perform Attachment 6.2 to bypass all RSCS rod blocks.

BACK PANEL OPERATOR: Take direction from the BOP operator to perform back panel steps of .2. Wait two minutes and then Activate TRIGGER 30 to install jumpers.

When completed, circle slash the two steps at the bottom of the page and inform the BOP operator that they have been completed by standing next to Board S and giving the crew an update:

UPDATE READY - Attachment 6.2 of PPM 5.5.11 has been completed, END OF UPDATE.

BOOTH OPERATOR: When RPV Level has been lowered and is being maintained: TO CLEAR ATWS:

When both scram discharge volume vents and drains are fully open, set the four ATWS malfunctions to a severity of sixty (order does not matter).

BOP Manually starts to drive control rods by starting at 10-43 and inserting every other rod in every other row.

Reports success in driving control rods to CRS.

When the Scram Discharge Volume has been drained for more than 2 minutes initiates a manual scram by depressing the four red manual scram pushbuttons.

If rods do not insert continues scram/reset/scram Tab B and raises SDV drain time by 2 minutes.

Determines All Rods are in and informs the CRS.

Installs the following fuses removed in TAB A:

TB1 ARI fuse Page 18 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 TB2 ARI fuse CRS Directs SLC be stopped.

ATC Takes control switches out of OPER and observes both SLC pumps stop.

BOP CRS Exits PPM 5.1.2 (RPV Control ATWS) and enters PPM 5.1.1 (RPV Control).

Directs RPV level be raised to -50 to +54 band with available systems.

ATC Raises RPV level into band as directed.

TERMINATION POINT - The scenario will be terminated when RPV level is being returned to the directed band.

Comments:

Page 19 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 Event No. 8

==

Description:==

Initiate SLC - RWCU-V-4 fails to auto close.

This event is active from the start of the scenario and is realized when SLC is initiated.

Time Position Applicants Actions or Behavior Critical Task is to inject Standby Liquid Control (boron) prior to exceeding 110°F Suppression Pool temperature.

T = 65 CRS Directs SLC initiation prior to Suppression Pool temperature reaching 110°F.

ATC Initiates SLC per the quick card:

Remove the SLC keylock switch blanks and insert both keys into the SLC System control switches.

Initiate SLC injection by performing the following (H13-P603):

• Place SLC System A control switch to the OPER position

• Place SLC System B control switch to the OPER position Report the following to the CRS:

• SLC flow rate (~82gpm)

• Initial tank level

• RWCU-V-4 status (should be closed)

Reports SLC flow rate indicating low at about 18 gpm.

Reports initial tank level.

Verifies RWCU-V-4 closed and notes valve is actually open.

Takes the control switch for RWCU-V-4 to the close position and observes green light on and red light goes out.

Reports RWCU-V-4 failed to auto close but was manually closed with the control switch.

Directs investigation by OPS2 of reduced SLC flow.

ROLEPLAY - Three minutes after request inform the Control Room that the SLC relief valves are lifting and that maintenance has been contacted and is on their way. You will inform them in any change in SLC status.

Comments:

Page 20 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 TURNOVER INFORMATION Initial Conditions Columbia is at 95% power due to an economic dispatch request from BPA.

RCC-P-1B is tagged Out of Service for pump seal replacement.

BPA has just requested Columbia return to 100%.

LCS 1.3.7.2 has been entered per OSP-HPCS/IST-Q701 step 7.3.2.

Shift Directions Raise power with flow to 100% reactor power.

Continue with OSP-HPCS/IST-Q701.

The two evolutions are to be performed concurrently.

Page 21 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 SIMULATOR SETUP INSTRUCTIONS Have a copy of OSP-HPCS/IST-Q701 with it signed in and prerequisites signed off.

Reset to saved IC #173.

Hang blue tag on RCC-P-1B.

Ensure CRD-P-1B Running and the red dot is over CRD-P-1B.

Booth Operator needs to go on the floor to perform PPM 5.5.11 Attachment 6.1 and 6.2 during the scenario. Have a marker to mark up the EOP procedure available.

You may want to give the HPCS surveillance to the crew ahead of time for them to review.

LO001752 Rev. 0 Page 22 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1 SCHEDULE FILE

<SCHEDULE>

<ITEM row = 1>

0

<ACTION>Insert malfunction MAL-CRD007A2 to 100</ACTION>

<DESCRIPTION>HYDRAULIC ATWS EAST SDV</DESCRIPTION>

</ITEM>

<ITEM row = 2>

0

<ACTION>Insert malfunction MAL-CRD007B2 to 100</ACTION>

<DESCRIPTION>HYDRAULIC ATWS WEST SDV</DESCRIPTION>

</ITEM>

<ITEM row = 3>

0

<ACTION>Insert malfunction MAL-CRD007A1 to 100</ACTION>

<DESCRIPTION>HYDRAULIC ATWS EAST SDV BLOCKAGE</DESCRIPTION>

</ITEM>

<ITEM row = 4>

0

<ACTION>Insert malfunction MAL-CRD007B1 to 100</ACTION>

<DESCRIPTION>HYDRAULIC ATWS WEST SDV BLOCKAGE</DESCRIPTION>

</ITEM>

<ITEM row = 5>

0

<ACTION>Insert malfunction MOV-RWU010F to FAIL_AUTO_CLOSE</ACTION>

<DESCRIPTION>RWCU-V-4</DESCRIPTION>

</ITEM>

<ITEM row = 6>

0

<ACTION>Insert malfunction BKR-RCC002 to FA_CTRL_FUS</ACTION>

<DESCRIPTION>Rackout RCC-P-1B</DESCRIPTION>

</ITEM>

<ITEM row = 7>

0

<ACTION>Insert malfunction PMP-SLC002F to 50</ACTION>

<DESCRIPTION>SLC PUMP 1B REDUCED FLOW</DESCRIPTION>

</ITEM>

<ITEM row = 8>

LO001752 Rev. 0 Page 23 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1

0

<ACTION>Insert malfunction PMP-SLC001F to 100</ACTION>

<DESCRIPTION>SLC PUMP 1A REDUCED FLOW</DESCRIPTION>

</ITEM>

<ITEM row = 9>

0

<EVENT>1</EVENT>

<ACTION>Insert malfunction MOV-CSS004F to FAIL_CNTRL_PWR on event 1</ACTION>

<DESCRIPTION>HPCS-V-12 MINIMUM FLOW</DESCRIPTION>

</ITEM>

<ITEM row = 10>

0

<EVENT>2</EVENT>

<ACTION>Insert malfunction BKR-CSS001 to FA_CTRL_FUS on event 2</ACTION>

<DESCRIPTION>HPCS-P-1 Pull Control Power Fuses</DESCRIPTION>

</ITEM>

<ITEM row = 11>

0

<EVENT>3</EVENT>

<ACTION>Insert malfunction ANN-603A7B06 to ON on event 3 delete in 10</ACTION>

<DESCRIPTION>CRD PUMP B SUCTION PRESS LOW</DESCRIPTION>

</ITEM>

<ITEM row = 12>

0

<EVENT>3</EVENT>

<ACTION>Insert malfunction BKR-CRD002 to TRIP after 5 on event 3</ACTION>

<DESCRIPTION>CRD-P-1B MOTOR SUPPLY BREAKER</DESCRIPTION>

</ITEM>

<ITEM row = 13>

0

<EVENT>4</EVENT>

<ACTION>Insert malfunction MAL-OED004 to 20 in 20 on event 4 delete in 25</ACTION>

<DESCRIPTION>500KV GRID VOLTAGE OSCILLATION</DESCRIPTION>

</ITEM>

<ITEM row = 14>

0

<EVENT>4</EVENT>

<ACTION>Insert malfunction MAL-RFC007R after 25 on event 4</ACTION>

LO001752 Rev. 0 Page 24 of 22

Appendix D NRC EXAM SCENARIO #3 FORM ES-D-1

<DESCRIPTION>ASD CH B1 GROUND FAULT</DESCRIPTION>

</ITEM>

<ITEM row = 15>

0

<EVENT>5</EVENT>

<ACTION>Insert malfunction MAL-OED004 to 20 in 10 on event 5 delete in 20</ACTION>

<DESCRIPTION>500KV GRID VOLTAGE OSCILLATION</DESCRIPTION>

</ITEM>

<ITEM row = 16>

0

<EVENT>5</EVENT>

<ACTION>Insert malfunction MAL-EPS005A after 10 on event 5</ACTION>

<DESCRIPTION>LOCKOUT ON SH-5</DESCRIPTION>

</ITEM>

<ITEM row = 17>

0

<EVENT>5</EVENT>

<ACTION>Insert malfunction MAL-EPS005B after 15 on event 5</ACTION>

<DESCRIPTION>LOCKOUT ON SH-6</DESCRIPTION>

</ITEM>

<ITEM row = 18>

0

<ACTION>Event Events/LO001752.evt</ACTION>

<DESCRIPTION>Activate Trigger 1 for HPCS</DESCRIPTION>

</ITEM>

<ITEM row = 19>

0

<ACTION>Schedule local.sch</ACTION>

<DESCRIPTION>Load Local Operator Actions</DESCRIPTION>

</ITEM>

</SCHEDULE>

EVENT FILE

<EVENT>

<TRIGGER id="1" description="HPCS FLOW GT KICKS TRG 1 TO CLEAR MIN FLOW FUSES">X01D033M &gt 3000</TRIGGER>

</EVENT>

LO001752 Rev. 0 Page 25 of 22

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 3 2.1.37 Overlap with Audit Exam test item SRO-20.

3 2.1.17 Unable to write SRO-only question to this K/A 2/2 271000 2.2.39 No one hour or less Tech Spec action statements associated with Offgas.

ES-401, Page 27 of 33