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2009 Clinton Power Station Initial License Examination Administered Scenarios
	ML100710757
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Site:	Clinton
Issue date:	08/24/2009
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Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-01 Exam Scenario 1 REVISION 00

DEVELOPER:

Tom Pickley

REVIEWED BY:

Simulator Instructor

APPROVED BY:

/ Operations Date Overview Makeup/Reject:

All CP's except H and J are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS ar e Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: 1WF Evap is in operating. A and B RT F/D are in service.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 1 Total Core Flow: __70.7___ mlb/hr FCV Position: A: __52.8_____% B: __53.1____%

Reactor Power __65__% (<=100%) _2282__ MWt (<=3473) _737__ Mwe Xenon: Stable RPV Level _33_ in Narrow Range RPV Pressure _963__ psi (< 1045) In service SDC loop None MODE 1 Containment Suppression Pool Temperature: _75.5_ F

(<=93.1 F) Suppression Pool Level _19.2_ ft (19 ft 0 to 19 ft 5 in) Drywell Pressure _0.8 _ psi (0 to 1 psig) Drywell to Containment dp: _0.8 _ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _104_ F

(<=146.53 F) Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _28_ in Hg CPI (goal < 1.1):

1.00 Off - Gas Flow: _38.5_scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature:

_94_ F Reactor Chlorides:

0.51 ppb Generator Reactive Load: _228_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip

None Comments: See Turnover Sheet

From "Excellence in Human Performance" Leaders reinforce desired jobsite behaviors (Handbook page 17) Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During traini ng activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mist akes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

OP-AB-300-1003 Revision 5 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 4 Station:

Clinton Valid Date(s): xx/xx/xxxx Reactivity Maneuver Plan #: C11-Simu.1

Multiple Activations Allowed? No (If yes, CRS may make additional copies) Prepared by:

Joe Top / xx/xx/xx Reviewed by: Roger Bottom /xx/xx/xx Reactor Engineer / Date Qualified Nuclear Engineer / Date Approved by: Michelle Strange / xx/xx/xx Authorized by: / xx/xx/xx RE Manager / Date Senior Reactor Operator / Date NF Review by Michael Charm / xx/xx/xx NF Reciewer / Date ReMA Activated:

/ xx/xx/xx ReMA Terminated:

/ xx/xx/xx Unit Supervisor / Date Unit Supervisor / Date Title of Evolution: Power Reduction to Removal of A TDRFP Purpose/Overview of Evolution:

This ReMA is provided for a non emergent load reduction to support removal of the A TDRFP.

This ReMA is NOT intended to take the place of emergency load reductions per the guidance of CPS 3005.01, Unit Power Changes. Emergency load reductions shall be implemented per the guidance of CPS 3005.01, Unit Power Changes. Reactivity Maneuver Steps Extended General Issues: Select desired amount of power reduction 1. Reduce reactor power to 60% with flow 2. Maintain reactor power using rods and flow

3. 4. General Issues: The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003. Main Steam Line Radiation Monitors may initially show elevated response from crud burst in core (due to rod movements) and from "hydrogen pockets" being swept into the core (due to flow perturbations in the condensate / feedwater piping). Response should diminish as the feedwater system comes to equilibrium.

OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP 1 of 2 Reactivity Maneuver Plan # C11-Simu.1 Description of Step :

Reduce reactor power to

~ 60% with flow.

Rod notching may also be used if necessary to control FCL. The Reactor Engineer will provide

guidance on the control rods to be moved to achieve the FCL necessa ry to support operating at 60%.

It is acceptable to stop at intermediate power levels as necessary to support plant conditions.

_________________________________________________________________________________ Note: Additional monitoring is required per C PS 3005.01, in addition to what is specified below. QNE presence required in the Control Room? Yes No X* *RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %)

N/A N/A MFLCPR < 0.900 Core Flow (Mlb/hr or %)

N/A N/AMFLPD < 0.900 FCL (%) < 90.0 % MAPRAT N/A N/ACritical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)

High Low FCL Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display after completion of power reduction. Contingency: Insert control rods in reverse order sequence to reduce FCL.

90.0 % N/A Step Complete: ___________________

/_______ Verified by: _________________

/_______ Reactor Operator / Date Unit Supervisor / Date

OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP 2 of 2 Reactivity Maneuver Plan # C11-Simu.1 Description of Step :

Maintain target power level using available flow. Rod notching ma y also be used, as needed, to maintain power level. The Reactor Engineer will provide guidance on when to notch control rods.

QNE presence required in the Control Room? Yes _

_ No X*

RE Coverage will be provided consistent with OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %) ~60% (~2084 MWt)

MFLCPR N/A N/ACore Flow (Mlb/hr or %)

N/A N/AMFLPD N/A N/AFCL (%) N/A N/AMAPRAT N/A N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)

High Low Step Complete: ___________________

/_______ Verified by: _________________

/_______ Reactor Operator / Date Unit Supervisor / Date

FIGURE 1: CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP 03476951042138917372084 2431 2778312634730.08.516.925.433.842.350.759.267.676.184.593.0CORE FLOW - mlbm/hr(use core plate dP when Single Loop)

THERMAL POWER - MWTh 0

10 20 30 40 50 60 70 80 901000102030405060708090100110PERCENT CORE FLOW PERCENT THERMAL POWE RRestricted ZoneCONTROLLED ENTRY REGIONCAVITATION PROTECTION LINES (HIGH SPEED, 2 PUMP OPERATION)SINGLE LOOPENVELOPE 60% 40%90.4 50%OPRM ENABLED REGION[> 25% CTP AND < 60% FLOW]90% FCL (Typ.) 80%25868MELLLA Limit [100.7% FCL]OPRM OPERABLE [21.6 % CTP, 750 MWth]

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.:

One Operating Test No.:

08-01 Examiners: ____________________________ Operators: ____________________ ____________________________

____________________

____________________________ ____________________

Initial Conditions:

65% power, Drywell pressure is high.

Thunderstorm storms are expected in the area within the next hour.

Turnover:

1. Run 'B' mixer to reduce DW pressure - First Priority

2. Power needs lowered to 60% power to remove the 'A' RFPT from service for a scheduled outage due to problems.

Event No. Malf. No.

Event Type* Event Description 1 HVAC_SP ARE_L3 1 N-BOP TS-CRS Reduce DW pressure, 'B' mixer trips, entry into ITS.

2 NA R-ATC Power reduction to support removal of 'A' TDRFP 3 Override C-ATC 'A' TDRFP trouble alarm 4 Override C-ATC 'B' RWCU pump seal plate temperature high 5 YP_XMFTB_4912 1 TS-CRS 'A' APRM fails downscale.

6 YFFWPPS S_13 1 C-BOP 'B' MC pump coupling fails 7 YPXMALS E_1 C-BOP Fuel failure 8 YP_XMFTB_4068, 69, 70, 71 M-ALL Debris in the Condenser causes all CD pumps to trip 9 RR03 M-ALL A small RR leak occurs in the Drywell 10 YFRIPPSS M-ALL The RCIC shaft breaks 11 YP_XMFTB_4103 M-ALL HPCS Injects and then trips *(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2 Appendix D Scenario Outline Form ES-D-1 Page 2 of 2 Scenario No.:

One Operating Test No.:

08-01 Narrative Summary

Event # Description

1. Drywell pressure is high requiring the BOP to run 'B' mixing compressor to reduce Drywell pressure. Operational Requirement Manual action 3.5.2 for the test Prep switch entered. The mixing compressor trips and the CRS enters ITS

3.6.3.3. 2. Power is reduced with recirculation flow to allow removal of the RFPT.

3. 'A' TDRFP experiences a trouble alarm on a thrust bearing wear condition requiring tripping of the 'A' TDRFP. This will require verification that the running 'B' TDRFP is adequately maintaining level. A RR FCV runback will require entry to CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core

Stability Control to verify no core instabilities along with entry into CPS 4002.01, Abnormal RPV Level/Loss of Feedwater At Power

4. RWCU pump B develops a seal leak requiring its removal from service.

5. 'A' APRM fails down scale entry into ITS 3.3.1.1 and OPRM ITS 3.3.1.3.

6. 'B' MC pump coupling fails results in the loss of makeup condensate. This requires the startup of the standby pump.

7. Fuel clad failure will require entry to the CPS 4010.01. Subsequent activities will

require the BOP to shut valves RE021&22, RF021&22, along with other

activities.

8, 9, 10 & 11. Debris breaks loose in the condenser causing a loss of suction and trip of all CD pumps. A small RR loop leak occurs and the RCIC shaft breaks and HPCS injects and then trips. A Blowdown is performed at TAF and level is

recovered with Low Pressure ECCS.

EOPS 1,3,6 Critical tasks: Emergency Depressurize when less than TAF. Recover level to above TAF.

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 1 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour. (Plant power level) 65% Power/70% FCL CPS 3005.01 thru step 8.2.9 2312 MWt A-2, step 36 is complete 747 MWe 70.7 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Reactor Power has been reduced to 65% and is scheduled to continue to 60% with RR FCVs to allow for RFPT 1A removal from service for maintenance to work on some problems. Existing LCOs, date of next surveillance None Surviellances or major maintenance CPS 9014.01 RPC Sys W/D Limitation Test was completed SAT last month. Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Comments, evolutions, problems, etc.

Online Safety is Green First Priority - Run 'B' mixer to reduce DW pressure (lowest run time).

Per Cumulative Date 9094.01D001for this month: 'A' Mixer run time is 4 hrs 52 minutes

'B' Mixer run time is 5 minutes Cumulative data will be taken care of by the WCS Containment pressure is 0.3 psig Lower power to 60% with flow within the next hour to support removal of A TDRFP.

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 2 Operator Actions Event No.(s):

1 Page 1 of 1

Description:

Reduce Drywell pressure Initiation: Following shift turnover Cues: Directed by SRO Time Position Applicant's Actions or Behavior BOP Per CPS 3316.01, Containment Combustible Gas Control, step 8.3: Places MOV Test Prep Switch for CGCS Div 2 to Test and notes time.

1. Start CGCS Hydrogen Cmpr 1B, 1HG02CB. Record start time IAW CPS 9094.01D001 2. Verify 1HG009B, CGCS Cmpr 1B Suct Vlv opens.

At DW pressure of .6 psig the B Mixer will trip off.

SECURING DRYWELL VENTING

1. Stop CGCS Hydrogen Cmpr 1B, 1HG02CB. Record stop time IAW CPS 9094.01D001 2. Verify 1HG009A(B), CGCS Cmpr1B Suct Vlv shuts. (If the control switch is not taken to stop the suction valve will remain open)

Places MOV Test Prep Switch for CGCS Div 2 into NORMAL and notes time.

RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Applies ORM ACTION 3.5.2 for MOV Test Prep Switch for CGCS Div 2 Enters ITS 3.6.3.3 A.1 for B Mixer.

Terminus: D/W Venting is completed and ITS call completed NOTES:

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 3 Operator Actions Event No.(s):

2 Page 1 of 1

Description:

Power reduction to support removal of the A RFPT turbine Initiation: Following D/W Venting and ITS call.

Cues: Directed by SRO Time Position Applicant's Actions or Behavior RO Per CPS 3005.01, Unit Power Changes, step 8.2.8.

Reduce power with Flow to ~60%.

BOP Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.

Terminus: Clearly observable plant response from change in power level.

NOTES:

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 4 Operator Actions Event No.(s):

3 Page 1 of 1

Description:

'A' TDRFP trouble alarm Initiation: Following the power reduction, on the signal of lead examiner Cues: Annunciator 5002-1B alarms , report from field operator Time Position Applicant's Actions or Behavior RO Per CPS 5002-1B, RFP 1A trouble: Trips the

'A' TDRFP due to high thrust bearing wear Observes Low Level Alarm and RR FCV runback Per CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core Stability Control, monitor for: Entry to the restricted zone Core Instabilities power operating Map CPS 4002.01, Abnormal RPV Level/Loss of Feedwater At Power As necessary, Start/stop Condensate, Condensate Booster or Reactor Feedwater pumps in support of level control.

Maintain adequate NPSH to the Feed Pumps (> 320 psig)

BOP Dispatches a field operator Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO Enters CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core Stability Control, Directs actions listed above. Enters CPS 4002.01, Abnormal RPV Level/Lo ss of Feedwater At Power, Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.

o Contacts Shift Manager and recommends notifications.

Terminus: 'A' TDRFP tripped and RPV level stabilized NOTES: TO EVALUATORS: If computer points FW-BC902 and or FW-BC903 are called up on DCS, inform the operators they both indicate High. (This is a limitation of the simulator.)

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 5 Operator Actions Event No.(s):

4 Page 1 of 1

Description:

RWCU Pump seal plate temperature high Initiation: Upon resolution of the FW transient on the signal of the lead evaluator Cues: Annunciator CPS 5000-2E alarms Time Position Applicant's Actions or Behavior RO Per CPS 3303.01, RWCU step 8.1.4 and 8.1.3: Direct field Operator to remove all Filter demins from service Open the F/D bypass valve Shutdown RWCU pump 'B' Place one F/D in service BOP Dispatches a field operator to support RWCU operation Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO Enters CPS 3303.01 Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.

o Contacts Shift Manager and recommends notifications.

Terminus: RWCU pump has been shutdown IAW CPS 3303.01 NOTES:

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 6 Operator Actions Event No.(s):

5 Page 1 of 1

Description:

Failure of 'A 'APRM Initiation: RWCU pump has been shutdown IAW CPS 3303.01, on the signal of lead examiner Cues: Annunciator 5060-8E Time Position Applicant's Actions or Behavior BOP Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

RO Acknowledges and announces 'A' AP RM annunciator and reading Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any additional unusual or unexpected conditions.

SRO Directs actions listed above. Declares 'A' APRM Inop per ITS 3.3.1.1 A.1 and 'A' OPRM Inop per ITS 3.3.1.3.A.1 or A.2 or A.3.

Complies with action statement(s) for T.S. Section o May direct going to Sensor Bypass for Div 1. Enforces OPS expectations and standards Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

o Contacts Shift Manager and recommends notifications.

Terminus: SRO has addressed ITS requirements.

NOTES:

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 7 Operator Actions Event No.(s):

6 Page 1 of 1

Description:

MC pump "B" coupling fails Initiation: SRO has addressed I.T.S. requirements, on the signal of lead examiner Cues: Annunciator CPS 5014-2C alarming Time Position Applicant's Actions or Behavior BOP Per CPS 3208.01 MC/CY, STEP 8.1.1.1 (or 8.2.2): Direct shutting the discharge valve and reopen upon pump start (if section 8.1.1.1 is used). Start up the standby pump Shutdown the failed pump RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO Directs actions listed above. Enforces OPS expectations and standards.

o Contacts Shift Manager.

Terminus: Standby Pump started and shutdown of the failed pump

NOTES:

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 8 Operator Actions Event No.(s):

7 Page 1 of 1

Description:

Fuel failure Initiation: After crew has started an other MC pump, on the signal of lead examiner Cues: OG pretreat alarming, MSL rad monitors trending up Time Position Applicant's Actions or Behavior BOP Per CPS 4010.01, Reactor Coolant Hi Activity, Sub. Action: Sound the CNMT evacuation alarm. Shut: 1RE021, EQ Drain Sump Disch CNMT Inbd Vlv. 1RE022, EQ Drain Sump Disch CNMT Outbd Vlv. 1RF021, Flr Drain Sump Disch CNMT Inbd Vlv. 1RF022, Flr Drain Sump Disch CNMT Outbd Vlv.

CPS 3408.01 VR/VQ, Step 8.1.1.2:

o Shift CNMT Building HVAC System to Continuous CNMT Purge Filtered mode RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO Enters CPS 4010.01, Reactor Coolant Hi Activity, and directs actions listed above. Directs Chemistry to sample the Reactor Coolant Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards.

o Contacts Shift Manager and recommends notifications.

Terminus: Valves shut, SRO has entered CPS 4010.01 and directed actions accordingly.

NOTES:

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Operator Actions Event No.(s): 8, 9,10,11 Page 1 of 2

Description:

Debris breaks loose in the condenser causing a loss of suction and trip of all CD pumps and small RR leak. Initiation:

After Fuel Failure has been addressed, on the signal of lead examiner Cues: All Condensate and Feedwater pumps trip Time Position Applicant's Actions or Behavior RO Inserts a manual scram CPS 4100.01, Reactor Scram: Place mode switch in Shutdown Check and report power 1% and trending down Check rods, reports shutdown criteria is met Report level and pressure are following expected trends Verify turbine and generator are tripped Stabilize pressure <1065 psig Performs EOP/ON actions as directed by SRO Coordinates with BOP operator to monitor and control RPV press BOP Makes plant announcement for reactor scram and evacuate the containment Coordinates with RO to monitor and control RPV press Evacuate the Containment Performs EOP/ON actions as directed by SRO Reports HPCS Injection and trip Reports RCIC will not inject Maximize CRD Inject with SLC Initiates ADS verifies 7 ADS valves are open Maximizes injection and restores level above TAF Critical Task NOTES: Critical Task 9

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 Event No.(s): 8, 9,10 Unisolable main steam line Page 2 of 2 Time Position Applicant's Actions or Behavior SRO Directs entry into EOP-1, EOP-6 for high drywell pressure a nd EOP-3 (Blowdown) actions as entry conditions are met. Directs Stabilize pressure below 1065 psig Hold level above TAF Maximize CRD Inject with SLC When RPV water level is less than TAF, directs entry into EOP-3 and EOP actions: Initiation of ADS verify 7 ADS valves are open Terminus:

Reactor scrammed ADS has been initiated Level restored above TAF Upon approval of lead examiner Critical Task NOTES: 10 D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 11 Simulator Operator Instructions

Initial Setup

1. Verify daily lamp test completed

2. Reset to IC-41 (Verify/Adjust Power to 65% with rods and/or flow to match turnover). Make sure DW pressure is up to ~1.0 psig built into the initial conditions or the Lesson plan Ensure B MC pump is running B RT pump is running. A TDRFP is running.

3. Load the lesson plan for this scenario.

4. Place simulator in RUN

5. Verify Rod Drive pressure at 250 #.

6. Turn on and advance recorders

7. Verify the AR/PR server is running and stabilize AR/PR

8. Identify T/S issues associated with OOS and turnover

9. Ensure PR001 is on service and PR002 is in Standby. (Main Stack monitors).

1 0. Ensure PR012 is operating / in-service. (If asked at any time during the evaluation why PR012 is running, inform crew it is to support Chemistry. This is a limitation discovered during ITR/Validation of scenario, PR012 won't auto start and can't be started from the instructor station so it is started at the beginning of the scenario so it will be running if it is needed or referenced.)

1 1. Verify simulator conditions match the turnover 1 2. Provide a copy of CPS 3005.01, signing for step 8.2.9.

1 3. Fill out plant status and have Turnover Sheet ready for the crew.

1 4. Provide pull sheets, REMA, Re instructions and Cram Instructions.

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 12 Event Triggers and Role Play If asked at any time during the evaluation why PR012 is running, inform crew it is to support Chemistry. (This is a limitation discovered during ITR/Validation of scenario, PR012 won't auto start and can't be started from the instructor station so it is started at the beginning of the scenario so it will be running if it is needed or referenced.)

Event # 1. Lower DW pressure.

a. No trigger. Activates when D/W pressure is less than .6 psig.

b. Role play - To support this evolution. If sent to B Mixer it appears fine. If sent to B Mixer breaker it is tripped and has a bad smell. NO FIRE.

c. Role play - If asked then Cumulative data will be taken care of by the WCS.

2. Power reduction to support removal of a RFPT turbine

a. No triggers

3. 'A' TDRFP trouble alarm

a. Remote trigger 1

b. Role Play- field Operator that 43 psig on Thrust Bearing Wear Pressure at 1PL76JA and starting to hear unusual sounds from 'A' TDRFP.

c. TO EVALUATORS / Booth Operators: If computer points FW-BC902 and or FW-BC903 are called up on PPC, inform the operators they both indicate High. (This is a limitation of the simulator.)

d. Role Play for Chemistry, RP and RE.

4. 'B' RT pump seal plate temperature high

a. Remote trigger 2 on request from lead evaluator

b. Role play field operator that 'B' RT pump seal temperature is 285 degrees and rising slowly. The CCW is lined up to this pump and the other 'A' RT pump is at 175 degrees and stable. No steam in the room.

c. Remote trigger 7 to remove RT F/D 'A', Remote trigger 8 to remove RT F/D 'B'.

d. Remote trigger 9 to place on service RT F/D 'A', Remote trigger 10 to place on service RT F/D 'B'

5. 'A' APRM fails down scale

a. Remote trigger 3 on request from lead evaluator

b. Role play as C/I if requested, investigating. Will come up with troubleshooting plan.

6. 'B' MC pump coupling fails. a. Remote trigger 4 on request from lead evaluator

b. Role Play - 'B' MC coupling is failed and support the startup of the 'A' MC pump.

7. Fuel failure

a. Remote trigger 5 on request from lead evaluator

b. Role Play - 'If requested Primary to secondary Ctnt d/p is .0125 psid.

c. Role Play - As Chemistry and RP is called.

d. If back panels are checked, inform operators all MSL Rads are tracking together.

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 08-24-09 08-01 13 8. Loss of all Condensate Pumps

a. Remote trigger 6 on request from lead evaluator.

b. After 2 minutes from scram announcement go to MCR as IMD.

Procedures Used During Simulator Scenario # 1 (List of Annunciators on back of page)

1. EOP-1 2. EOP-3 3. EOP-9 4. 3316.01 CCGS

5. ITS/ORM/ODCM

6. 3005.01 Unit Power Changes

7. 4008.01 O/N

8. 4100.02 O/N

9. 4002.01 O/N

10. 3303.01 RT

11. 3208.01 MC/CY

12. 4010.01 O/N

13. 3408.01 VR/VQ

14. 4100.01 O/N

15. 4001.02 O/N

16. 4979.01 O/N

17. 4411.03 18. 4411.09

19. Annuciators:

5002-1B, 1C, 2Q, 4G 5000-2E, 2C 5060-8E 5014-2C 5041-7H,1C 5041-1c, 7H 5031-1G 5003-1D/E 5006-3D 5015-1A-M, 4C-M 5016-1G 5000-2C/E/F 5043-2A, 1G 5042-5H 5043-1G 5067-3E/F, 2L 5013-3A, 4E 5064-3C/D, 4C/D 5130-1G, 2G 5004-1L 5006-3D, 2H 5062-8E All alarms after the Scram

Clinton Power Station Licensed Operator Training Simulator Exercise Guide EXAM ILT 08-1 Exam Scenario 2 REVISION 00

DEVELOPER:

Tom Pickley

REVIEWED BY:

Simulator Instructor

APPROVED BY:

/ Operations Date Overview Makeup/Reject:

CP's B,C,D,E and F are in service. RO tr ain #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS ar e Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: 1WF Evap is in Hot Standby. A and B RT F/D are in service.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 1 Total Core Flow: _32.4_ mlb/hr FCV Position: A: __90___% B: __90__%

Reactor Power _27_% (<=100%) _919_ MWt (<=3473) _244_ Mwe Xenon: Stable RPV Level _29_ in Narrow Range RPV Pressure _929_ psi (< 1045) In service SDC loop None MODE 1 Containment Suppression Pool Temperature: _75.5_ F

(<=93.1 F) Suppression Pool Level _19.2_ ft (19 ft 0 to 19 ft 5 in) Drywell Pressure _0.5_ psi (0 to 1 psig) Drywell to Containment dp: _0.5_ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _103_ F

(<=146.53 F) Secondary Containment: _0.74_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _28.7_ in Hg CPI (goal < 1.1):

1.00 Off - Gas Flow: _34.4_ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature:

_84_ F Reactor Chlorides:

0.51 ppb Generator Reactive Load: _85.4_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip

None Comments: See Turnover Sheet

From "Excellence in Human Performance" Leaders reinforce desired jobsite behaviors (Handbook page 17) Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During traini ng activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mist akes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

OP-AB-300-1003 Revision 5 ATTACHMENT 1 Reactivity Maneuver Approval Cover Page Page 1 of 4 Station:

Clinton Valid Date(s):

xx/xx/xxxx Reactivity Maneuver Plan #: C11-Simu.3 Multiple Activations Allowed? No (If yes, CRS may make additional copies) Prepared by: Roger Bottom / xx/xx/xx Reviewed by: Joe QNE / xx/xx/xx Reactor Engineer / Date Qualified Nuclear Engineer / Date Approved by: Michelle QNE Boss/ xx/xx/xx Authorized by: / xx/xx/xx RE Manager / Date Senior Reactor Operator / Date NF Review Carlos Quark / xx/xx/xx NF Reviewer / Date ReMA Activated:

/ xx/xx/xx ReMA Terminated:

/ xx/xx/xx Unit Supervisor / Date Unit Supervisor / Date Title of Evolution: RR Pump Upshift Purpose/Overview of Evolution:

This ReMA provides the steps for raising reac tor power to support upshift of the RR Pumps. Reactivity Maneuver Steps Extended General Issues: Select desired amount of power increase 1. Withdraw control rods to achieve conditions to support RR Upshift 2. Shift RR Pumps to fast speed and increase flow to 65% (~54.9 Mlbm/hr)

3. 4. General Issues: The critical parameters are provided as a guide to focus the monitoring of the evolution. Changes to these parameters may be necessary to accommodate the actual startup load profile and predictor uncertainties. Changes to the critical parameters are to be done in accordance with the ReMA Training and Reference Material guidelines per OP-AB-300-1003. The plan is to pull control rods in order to achieve sufficient conditions to perform and RR pump upshift. Flow will then be increased to ~65%.

OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP 1 of 2 Reactivity Maneuver Plan # C11-Simu.3 Description of Step :

Increase reactor power with control rods to ~30% (~1050 MWt) to support RR pump shift to fast speed. Perform control rod pulls in accordance with approved sequence.

Ensure Feedwater heating is in service and that feedwater temperature is within 50°F of nominal prior to exceeding 21.6% (750 MWt). Reference Appendix A of CPS 3102.01. QNE presence required in the Control Room? Yes X No * *RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %)

N/A N/A MFLCPR N/A N/ACore Flow (Mlb/hr or %)

N/A N/AMFLPD N/A N/AFCL (%) N/A N/AMAPRAT N/A N/ACritical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)

High Low FCL Monitor Frequency: Demand 3D Case or verify with power and flow from P680 display. FCL should be monitored constantly after crossing 21.6% power and just prior to pump upshift. Contingency: Insert control rods in reverse order sequence to reduce FCL.

57.3 % N/A Step Complete: ___________________

/_______ Verified by: _________________

/_______ Reactor Operator / Date Unit Supervisor / Date

OP-AB-300-1003 Revision 5 ATTACHMENT 2 Reactivity Maneuver Guidance Sheet STEP 2 of 2 Reactivity Maneuver Plan # C11-Simu.3 Description of Step :

Shift RR Pumps to fast speed and increase core flow to ~65% (~54.9 Mlbm/hr). Increasing flow may be performed in increments to support throttling FCVs and as necessary to place other plant systems in service.

Reactor power will be 40-45% (1389 - 1563 MWt) at the completion of this step.

Note: It is possible that performing a pump upshift will cause the plan t to enter into the CONTROLLED ENTRY REGION of the power / flow operating ma

p. Per EC 358831, entry into this region in support of RR pump shifting activities has been evaluated and is acceptable. QNE presence required in the Control Room? Yes X* No * *RE Coverage shall be provided consistent with the guidelines of OP-AB-300-1003 and NF-AB-701. Initial Conditions (may be ranges) to be verified at the START of the Step Parameter Value or Range Init. Parameter Value or Range Init.Core Power (MWth or %)

N/A N/A MFLCPR < 0.900 Core Flow (Mlb/hr or %)

N/A N/AMFLPD < 0.900 FCL (%) < 57.3% MAPRAT N/A N/A Critical Parameters to be Verified During the Step Description; including frequency, method of monitoring, and contingency actions (if needed)

High Low Step Complete: ___________________

/_______ Verified by: _________________

/_______ Reactor Operator / Date Unit Supervisor / Date

FIGURE 1: CPS STABILITY CONTROL & POWER/FLOW OPERATING MAP 03476951042138917372084 2431 2778312634730.08.516.925.433.842.350.759.267.676.184.593.0CORE FLOW - mlbm/hr(use core plate dP when Single Loop)

THERMAL POWER - MWTh 0

10 20 30 40 50 60 70 80 901000102030405060708090100110PERCENT CORE FLOW PERCENT THERMAL POWE RRestricted ZoneCONTROLLED ENTRY REGIONCAVITATION PROTECTION LINES (HIGH SPEED, 2 PUMP OPERATION)SINGLE LOOPENVELOPE 60% 40%90.4 50%OPRM ENABLED REGION[> 25% CTP AND < 60% FLOW]90% FCL (Typ.) 80%25868MELLLA Limit [100.7% FCL]OPRM OPERABLE [21.6 % CTP, 750 MWth]

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.:

Two Operating Test No.:

08-01 Examiners: ____________________________ Operators: ____________________ ____________________________

____________________

____________________________ ____________________

Initial Conditions:

27% power RR Pumps on LFMG, Pulling rods to 30% power for Recirculation pump upshift.

Thunderstorms are expected in the area within the next hour.

Turnover:

1. Shift Main EHC pump to support maintenance - First Priority.

2. Pull rods to raise power to 30% and await instructions to shift Reactor Recirc pumps to Fast Speed.

Malf. No.

Event Type* Event Description 1 NA N-BOP Main EHC pump swap.

2 NA R-ATC Pull rods to raise power.

3 4025I_Acti on3ROD16 49I_ACTIO N3 1 C-ATC TS-CRS Rod drifts outward.

4 HP01HP_1E22C003_

MTFSHEA R 1 C-BOP TS-CRS HPCS WLP Shaft shears.

5 YAFWPPLB_5 30.000 C-ATC "A" CB pump clogged oil filter/bearing oil deficiency.

6 YP_XMFT B_3918 1 C-BOP Trip of 'B' CCW pump.

7 YAMSAVF P_15 0.0 I-BOP SSE level control failure.

8 YP_XMFT B_5082 1 M-ALL RPV Instrument line failure in the secondary containment.

9 YP_XMFT B_4963 1 M-ALL Auto and Manual scram failure.

10 YP_XMFT B_5107 _1 M-ALL One SLC Pump fails to start *(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2 Appendix D Scenario Outline Form ES-D-1 Scenario No.:

Two Operating Test No.:

08-01 Narrative Summary

Event # Description

1. Swap the running Main EHC pumps, the 'A' Main EHC pump will be started and the 'B' Main EHC pump shutdown.

2. Allow rod withdrawal to raise power.

3. During rod withdrawal a rod continues to move outward, Off-Normal CPS 4007.02 requires operator action to stop its outward movement. Once the rod is scrammed the

rod will no longer withdraw. LCO 3.1.3 action C.1&2 is entered.

4. HPCS WLP shaft shear. Stop the WLP, pull C/P fuses and CRS enters ITS 3.5.1 B.1

and B.2. 5. "A" CB pump will experience a Clogged oil filter with a bearing oil deficiency requiring the startup of the standby pump and shutdown of the "A" pump.

6. Trip of 'B' CCW pump. Start up 'A' CCW pump.

7. SSE level control fails causing level to go low requiring the manual level control to

restore level on the SSE.

8. The RPV instrument line will break resulting in a partial lost of RPV instrumentation, a steam leak in the secondary containment and EOP-8 entry. Two areas in secondary containment will exceed Maximum Safe temperature requiring blowdown.

9. When scrammed, rods will not move resulting in reactor remaining at power and entry to EOP-1A. This will require insertion of rods and the initiation of SLC to

shutdown the reactor.

10. When SLC is started the B SLC pump fails to start.

EOPS 8,1A,3 Critical tasks: Insert control rods and/or start SLC to shutdown the reactor Terminate and Prevent Injection prior to emergency depressurization Initiate emergency depressurization once two Max Safe temperatures are exceeded. Commence RPV feed to Restore level to the prescribed band when RPV pressure is below figure J.

Page of 2 2

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 1 Shift Turnover Information Day of week and shift Today Day Shift Weather conditions Thunderstorms are expected in the area within the next hour. (Plant power level) 27% Power A-2, step 27 is complete, 16-33 at 26 944 MWt 252 MWe 32.4 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions Raise power by pulling rods to 30% then await instructions to shift RR pumps to fast speed. RE is present and available. Rx startup in progress. Gang is permissible, but continuous drive is NOT authorized Existing LCOs, date of next surveillance Surveillances or major maintenance FWLC selected to channel B for calibration of channel A later this shift. . Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment Comments, evolutions, problems, etc. Online Safety is Green Shift Main EHC pump to support maintenance - First Priority. In 3004.01 complete thru step 8.3.10 Carrying electrical load in accordance with the Power Team.

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 2 Operator Actions Event No.(s):

1 Page 1 of 1

Description:

Main EHC running pump swap.

Initiation: Following turnover Cues: Directed by SRO Time Position Applicant's Actions or Behavior BOP Per CPS 3105.02, EHC, STEP 8.1.2.1: Startup the standby pump (A) Wait for at least thirty seconds Shutdown the running pump (B) 5017-3A may or may not alarm. Test the standby pump (B)

The standby pump is started by a local operation and then stopped in the control room. RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.

Terminus: Main EHC pumps shifted

NOTES:

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 3 Operator Actions Event No.(s):

2 Page 1 of 1

Description:

Pull rods to raise power Initiation: Following Main EHC pump shift.

Cues: Directed by SRO Time Position Applicant's Actions or Behavior RO Per Turbine Startup and Generator Synchronization, CPS3004.01, step 8.3.11 and NF-CL-721 series: Withdraw rods to raise power to 30% Rods are withdrawn by depressing the withdraw pushbutton or the continuous and withdraw pushbuttons together.

BOP Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Clearly observable plant response from change in power level.

NOTES:

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 4 Operator Actions Event No.(s):

3 Page 1 of 1

Description:

Rod 16-49 drifts outward Initiation: Once the reactivity manipulation is complete, on the signal of lead examiner Cues: Rod Drift, 5006-4G alarms Time Position Applicant's Actions or Behavior RO Per Inadvertent Rod Movement, CPS 4007.02: Immediate actions Select and fully insert the moving rod with the In Timer Skip button Subsequent actions; Once fully inserted release the In Timer Skip button Observe rod withdrawal Reinsert rod with the In Timer Skip button Per CPS 5006-3D, OPRM Enabled: Monitor for core instabilities BOP Dispatch a field operator to the HCU for the rod Directs field operator to Individually scram rod Evaluates thermal limits Evaluate MSL rad monitor values Evaluates OG Rad levels SRO Enters and direct actions per Inadvertent Rod Movement, CPS 4007.02 Control Rod Operability, Tech. Spec. LCO 3.1.3 action C.1&2 Contacts Shift Manager and recommends notifications.

Terminus: Once rod is fully inserted, individually scrammed and Tech Specs referenced.

NOTES:

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 5 Operator Actions Event No.(s):

4 Page 1 of 1

Description:

HPCS WLP Shaft shears Initiation: Following completion of rod failure, on the signal of lead examiner Cues: HPCS System, 5062-7D alarms Time Position Applicant's Actions or Behavior BOP Per ARP Procedure CPS 5062-7D:

Dispatches NLO to investigate.

o If ATM is checked for pressure it reads 0 psig When directed: Shutdown the HPCS WLP Pump. Per HPCS CPS 3309.01 precaution 4.3:

Dispatches NLO to remove HPCS control power fuses. 5062-7B will alarm.

RO Monitors reactor to ensure operati ons remain within established bands. Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO Directs actions listed above. Evaluates and enters Technical Specification LCO 3.5.1 B.1 and B.2. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Contacts Shift Manager and recommends notifications.

Terminus: HPCS control power fuses removed and Technical Specifications evaluated.

NOTES: If the crew does not pull the control power fuses the coupling on the HPCS pump will be broken to prevent HPCS from injecting.

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 6 Operator Actions Event No.(s):

5 Page 1 of 1

Description:

CB pump "A" clogged oil filter/bearing oil deficiency Initiation: After crew has addressed HPCS problem and on the signal of lead examiner.

Cues: Annunciator CPS 5001-1H alarming, Time Position Applicant's Actions or Behavior RO CPS 5001-1H, Clogged Oil Filter CB 1A: Directs field operator to turn Cuno filter CPS 3104.01, CD/CB step 8.2.2: Startup standby CB pump Shutdown 'A' CB pump BOP Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO Directs actions listed above. Enforces OPS expectations and standards Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Standby CB pump started and shutdown the 'A' CB pump.

NOTES:

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 7 Operator Actions Event No.(s):

6 Page 1 of 1

Description:

Trip of 'B' CCW pump Initiation:

After shifting of CB pumps, on the signal of lead examiner Cues: Annunciator CPS 5040-1B alarming, Time Position Applicant's Actions or Behavior RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions. Responds to annunciator 5003-3D and 3E, RR Low Cooling Water Flow.

BOP Respond to annunciator 5040-1B,Informs CRS B CCW pump tripped. Starts standby pump per ARP (O/A 2.a). Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO Directs actions listed above. Directs starting of 'A' CCW pump. Directs RO to monitor RR and RT Temps. Enforces OPS expectations and standards Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Terminus: Standby CCW pump started.

NOTES:

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 8 Operator Actions Event No.(s):

7 Page 1 of 1

Description:

SSE level control failure Initiation: After crew has addressed CCW pump trip and on the signal of lead examiner Cues: Annunciator CPS 5019-3A alarming Time Position Applicant's Actions or Behavior BOP Per CPS 5019-3A, Hi/Lo SSE Shell, OA 2: Determines level to be low. Direct field operator to investigate. Throttle open 1GS-S10, SSE Feed Water Bypass Vlv to restore level to the -2 1/2 -+ 2 1/2. Note: When the operator feeds with the Bypass valve the additional cold water will initially cause SSE pressure to drop further before it recovers.

RO Monitors reactor to ensure operati ons remain within established bands Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

SRO Directs actions listed above. Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.

Terminus: SSE level restored and alarm clear NOTES: May take up to (2) minutes for alarm to come in. (This is normal.)

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 9 Operator Actions Event No.(s): 8,9,10 Page 1 of 5

Description:

RPV Instrument line failure in the secondary containment, Failure to scram Initiation: on the signal of lead examiner Cues: Multiple secondary containment area temperature and area radiation alarms, Rods fail to insert upon Scramming Time Position Applicant's Actions or Behavior RO Reports EOP-8 entry on Hi temperature Performs EOP actions as directed by SRO Initiate a manual reactor scram before first max safe temperature is exceeded Per CPS 4100.01, Reactor Scram: Place mode switch in Shutdown Check and report power unchanged Operate FW to control level 3 to 8 Check rods, reports shutdown criteria is not met Report level and pressure are following expected trends Stabilize pressure <1065 psig Coordinates with BOP operator to monitor and control RPV level and press BOP Reports secondary containment high temperature and rad alarms to SRO Makes plant announcement for reactor scram Should make plant announcement to evacuate Fuel/Aux buildings. Performs EOP actions as directed by SRO Verifies operation of area coolers Verifies operation of VF, Fuel Bldg Vent. Evacuates affected areas of Secondary Containment Monitors area temperatures, le vels and radiation levels Reports a secondary containment Max Sa fe temperature being approached to SRO Reports two secondary containment Max Safe temperatures are being exceeded to SRO Coordinates with RO to monitor and control RPV level and press Critical Task

NOTES:

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 10 Event No.(s): 8,9,10 Page 2 of 5 Time Position Applicant's Actions or Behavior SRO Directs entry into EOP-8 and EOP actions as entry conditions are met:

1. Operate VF

2. Operate area coolers

3. Hold floor drain sump levels below max. normal

4. Isolate all discharges into the affected area except systems needed for: EOP Actions Fire Fighting

5. Per EOP-8/CPS 4001.01, Reactor Coolant Leakage: Directs BOP to isolate the source of leakage 6. Direct a scram prior to exceeding Maximum safe temperature 7. Enters EOP-1 Directs additional actions:

1. Notification of Radiation Protection (RP) Department

2. Evacuate affected areas of Secondary Containment Directs and verifies performance of appropriate actions per EOP-1:

1. Mode Switch to SHUTDOWN Per EOP-1 enters EOP-1A Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas Critical Task NOTES:

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 11 Event No.(s): 8,9,10 Page 3 of 5 Time Position Applicant's Actions or Behavior RO Performs EOP actions as directed by SRO:

Arms and depresses MANUAL SCRAM push-buttons.

Initiates ARI.

CPS No. 4411.08, Alternate Control Rod Insertion Inserts control rods until RPC lockup Directs defeating RPC for further rod insertion Verifies RR downshifts at Level 3, and trips at Level 2.

Terminates and prevents injection CB/FW systems CPS 4411.02

When RPV level reaches -60", control RPV water level between TAF and -60" using only the listed Preferred ATWS Systems BOP Performs EOP-1A actions as directed by SRO: I nhibits ADS. Verifies needed auto actions. I solations D G Start Dispatches area operator to monitor DGs Starts and verifies injection of SLC trains 'A' and 'B'. Reports SLC B failure to start.

Terminates and prevents injection systems CPS 4411.02

1. HPCS 2. RCIC 3. LPCS - LPCS-5 valve may cycle open due to Instrument failure. 'B' RO may have to give LPCS-5 valve a close signal to complete the T/P.

4. LPCI Stabilizes RPV pressure below 1065 psig Critical Task Critical Task Critical Task Critical Task NOTES:

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 12 Event No.(s): 8,9,10 Page 4 of 5 Time Position Applicant's Actions or Behavior SRO Directs entry into EOP-1A and EOP actions as entry conditions are met: 1. Inhibit ADS 2. Arm and depress MANUAL SCRAM push-buttons

3. Initiate ARI

5. Determines Power to be greater than 5% and Directs injection of SLC 6. Insert control rods manually per CPS No. 4411.08, Alternate Control Rod Insertion 7. Verifies needed auto actions. Isolations DG Start 8. Terminate and prevent injection of Detail F1 CPS 4411.02

9. When RPV level reaches -60", control RPV water level between TAF and -60" using only the listed Preferred ATWS Systems 10. Enters EOP-6 for High Drywell Temperature 11. Directs crew to stabilize RPV pressure below 1065 psig Monitor status and hold condition of identif ied parameters below (within) specified values. On transient, positions himself as command authority on the unit. Acknowledges immediate operator actions and directs subsequent actions. Enforces OPS expectations and standards. Contacts Shift Manager and recommends notifications.

Critical Task NOTES: Critical Task Critical Task D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 13 Event No.(s): 8,9,10 Page 5 of 5 Time Position Applicant's Actions or Behavior RO Performs EOP-3 actions as directed by SRO Termination and prevention of injection of all F1 systems

1. CB/FW At less then 138 psig:

Re-feed to level band OF -60 to TAF BOP Performs EOP-3 actions as directed by SRO termination and prevention of injection of all F1 systems

1. LPCS 2. LPCI initiation of ADS and verify 7 ADS valves open SRO Enters EOP-3 and direct Blowdown once exceeding Maximum safe temperature in two areas Directs termination and prevention of injection of all F1 systems Directs initiation of ADS and verify 7 ADS valves open Directs Re-feed at 138 psig Directs level band at -60 to -TAF Terminus: E OP-8 actions initiated S LC started Rod Insert commenced R PV level lowered ADS initiated Level restored and stabilized Upon approval of lead examiner Critical Task Critical Task Critical Task Critical Task 4 Critical Tasks NOTES:

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 14 Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed

2. Reset to IC-42 (Verify/Adjust Power to 27% with rods and to match turnover If needed).

3. Load the lesson plan for this scenario.

4. Place simulator in RUN.

5. Select the FWLC level instrument B.

6. Turn on and advance recorders.

7. Verify Load set is at 600 MWe.

8. Verify the AR/PR server is running and stabilize AR/PR.

9. Verify Rod Drive pressure at 250#.

1 0. Identify T/S issues associated with OOS and turnover.

1 1. Verify simulator conditions match the turnover.

1 2. Rema and Rod Pull sheets marked up thru step 27 with 16-33 at 26 1 3. Provide marked up CPS 3004.01 complete to step 8.3.10.

1 4. Fill out plant status sheet and have Turnover sheet ready for crew.

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 15 Event Triggers and Role Play Event # 1. Main EHC pump swap

a. No trigger - to start b. Role play - Field operator to swap the running Main EHC pumps. Local EHC pressure reading of 1625 psig for pump and 1625 psig header. All other EHC parameters are normal

c. Remote trigger 10

- When requested to test auto start feature

d. The Pump will shutoff when stopped with the control room switch.

2. Pull rods to raise power

a. No triggers

b. RE -Xenon is at equilibrium. Gang is permissible, but continuos drive is NOT authorized

3. Rod drifts outward.

a. Remote trigger 1 - on request from lead evaluator.

b. No problem lights at the RGDC or RACCs

c. Role Play - Field operator reports no indications of problem at the HCU.

d. RE - 3D ran thermal limits have not been approached or exceeded. If scram times are asked for? Then no rods are slow.

e. Remote trigger 8 - When directed to scram the rod and report it completed. When asked accumulator N2 pressure is 1200 psig after rod is scrammed

4. HPCS WLP shaft shears

a. Remote trigger 2 - on request from lead evaluator

b. Role play - Field Operator if asked HPCS WLP the motor is turning but the pump is not.

c. If ATM is checked it is reading 0 psig.

d. Remote trigger 7 - When directed remove HPCS motor breaker Trip and C/P fuses and report it completed.

e. If called - Respond as maintenance to investigate.

f. If requested by CRS, RCIC is operable by administrative means.

NOTE: If the control power fuses are not pulled then insert the HPCS Shaft Break from the Lesson Plan.

5. CB pump "A" clogged oil filter/bearing oil deficiency

a. Remote trigger 3 - on request from lead evaluator

b. Role play - Field Operator to turn the Cuno filter for the CB A pump and report it done, leave this alarm in. Support startup of the standby CB pump. (Lube oil is >8 psi and >75 F) More Event Triggers and Role Play on the next page

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 16 6. 'B' CCW pump Trip

a. Remote trigger 4 on request from lead evaluator

b. When sent to A CCW pump it is okay. When sent to the breaker it is warm to the touch and has an overcurrent trip in. No fire.

c. Role play as maintenance personnel in the field if requested.

7. SSE level control failure

a. Remote trigger 5 - on request from lead evaluator

b. Role play as field operator no indications locally that would explain failure.

c. Controller is set at 0 inches, but level control valve is shut.

d. May take up to (2) minutes for alarm to come in. (This is normal.)

8. RPV Instrument line failure in the secondary containment

a. Remote trigger 6 on request from lead evaluator

b. When the XL3 printout is requested provide attachment 1

c. Role play as personnel in the field

(1) When an operator is dispatched to the 781 East Gas Control Boundary report that the area appears to have a steam leak. You are unable to enter.

9. Auto and Manual scram failure

a. Triggers - already active

b. Perform Pending actions when requested

c. Show up in the MCR 2 minutes after the scram announcement as IMD. (10 min if no announcement)

10. RT-1 and RT-4 fail to shut on SLC initiation

a. Triggers - already active D-2, Dynamic Simulator Scenario 2 EXAM DATE: 08-24-09 08-01 I 17 TEAR THIS PIECE OFF AND GIVE TO OPERATOR CHECKING FP ALARM Attachment 1

=============

========

=========

61-17 AB-781 East Col 121-124 AC ALARM 61-18 AB-781 East Col 121-124 AC ALARM

61-19 AB-781 East Col 121-124 AC ALARM

61-20 AB-781 East Col 121-124 AC ALARM

Procedures Used During Simulator Scenario # 3 (List of Annunciators on back of page)

1. EOP-1 2. EOP-1A 3. EOP-8 4. EOP-3 5. EOP-6 6. 3105.02 EHC

7. ITS/ORM/ODCM

8. 3004.01 TG S/U and Sync

9. 4007.02 O/N

10. 3309.01 HPCS

11. 3104.01 CD/CB

12. 4100.01 O/N

13. 4001.01 O/N

14. 4411.08 ARI

15. 4411.02 T/P

16. SLC hard card

17. T/P hard card (2)

18. 3203.01 CCW

19. 3107.01 GS

20. 3304.02 RCIS

21. 4411.104410.00 C012

22. 4411.09 23. 4410.00 C003

24. 4410.00 C004

25. 4411.03 26. 4411.04 27. 4411.11 28. 4411.02 29. 3101.01 30. HU-AA-1211

31. OP-AB-300-1001

32. Annuciators:

5006-4G, 5D, 3H, 1H, 3D 5062-7D, 8E, 7B 5019-3A 5001-1H 5040-1B, 8D 5003-3D, 3E, 2F, 2J, 2M, 4B, 4H 5017-3A 5130-1G ,2G 5003-3D, 3K 5002-2P, 1Q 5004-3A, 3F 5009-5B 5063-7H 5065-6F 5140 AR/PR All alarms after the Scram