Text

2011 Davis-Besse Nuclear Power Station Initial Examination Proposed Simulator Scenarios
	ML12020A267
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Site:	Davis Besse
Issue date:	12/27/2011
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Appendix D Scenario Outline Form ES-D-1 Facility: DAVIS-BESSE Scenario No.: 1 Op Test No.: NRC 2011 Examiners: Candidates: SRO ATC BOP Initial Conditions:

The unit is at 2% power

MFPT 2 is in service

Boric Acid Pump 1 is OOS.

Turnover: Raise power to 4% IAW DB-OP-06901, PLANT STARTUP, Step 3.30, and then continue with the procedure. Prestart checklist for Main Condensate Pump 2 and MFPT 1 are complete.

Event Malf. Event No. No. Type* Event Description 1 N - SRO Raise power to 4%

R - ATC 2 C - BOP, Running Condensate Pump trips SRO 3 TS - SRO BA Pump 2 trips 4 TS - SRO Hi Activity in RCS 5 I - ATC, RCS Pressure channel selected for NNI fails hi SRO TS - SRO 6 M - ALL Circ Water System rupture in the Circ Pump house 7 C - ATC, Two stuck rods SRO 8 C - ALL Both AFPTs trip on overspeed (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Page 1 of 16 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Scenario Event Summary DAVIS-BESSE 2011 NRC SCENARIO 1 The crew will assume the watch at Step 3.30 of DB-OP-06901, PLANT STARTUP. MFP 2 is in service and power is stable at 2%. Step 3.30 raises power to 4% for turbine warmup. One Boric Acid Pump is OOS.

The crew will raise power to 4%. When power is stable and the crew is preparing to continue in DB-OP-06901, the Lead Evaluate can cue the Condensate Pump Trip.

The crew will start a Condensate Pump.

On cue from the Lead Evaluator, an Equipment Operator reports the breaker on the only available Boric Acid Pump is tripped. The SRO should enter the TRM.

On cue from Lead Evaluator, Letdown radiation event will be inserted. The crew will enter the abnormal procedure for RCS high activity. Chemistry will report high RCS activity and the SRO will enter the TS.

After the Letdown Activity TS has been entered, the Lead Evaluator can cue the RCS pressure channel failure. The crew should respond in accordance with DB-OP-02513, PRESSURIZER SYSTEM ABNORMAL OPERATION. The operator should perform the immediate actions for the failed input and then the crew should re-establish normal conditions. The SRO will enter the T.S.

On cue from the Lead Evaluator, a major circulating water rupture occurs in the Circ Pump house. The crew will respond to alarms and enter DB-OP-02517, CIRCULATING WATER PUMP TRIP/CIRCULATING WATER SYSTEM RUPTURES.

The SRO should direct a trip of all Circulating Water Pumps and a reactor trip. When the reactor trips, two or more rods will be stuck fully withdrawn and both AFW Pumps overspeed trip.

The crew will work through DB-OP-02000, establishing feedwater flow from the MDFP and boration flow to compensate for the stuck control rods.

NUREG-1021, Revision 9 Supplement 1 2Page of 16 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op-Test No.: 2011 NRC Scenario No.: 1 Event No.: 1 Page 3 of 16 Event

Description:

Power increase Time Position Applicants Action or Behavior SRO Direct power increase in accordance with DB-OP-06901 ATC Raise power using the Rod Control Panel ATC Adjust Pzr level to match RCS temperature rise BOP Monitor Turbine Bypass Valves At Lead Evaluators discretion, proceed to Event 2 NUREG-1021, Revision 9 Supplement 1 3Page of 16 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op-Test No.: 2011 NRC Scenario No.: 1 Event No.: 2 Page 4 of 16 Event

Description:

Running Condensate Pump trips Indication Available:

Alarm 13-2-B CNDS PMP DISCH HDR PRESS Condensate Pump 1 lights are off Condensate Pump 1 amps indicate zero Time Position Applicants Action or Behavior Crew GO TO DB-OP-02013, Condensate FW Alarm Panel 13 Crew Determine no Condensate Pumps are running SRO REFER TO DB-OP-06221, Condensate System, Section 5.0, and 3.6 or 3.7, starting of a Condensate Pump BOP Start Condensate Pump I/F Role 1. When sent to Condensate Pump 1 breaker, identify a Play 50/51 relay has tripped

2. Role-play as Maintenance/Work Week Manager/Field Supervisor as necessary to investigate

3. Respond to CTRM inquires for starting Condensate Pump, ie. prestartup checks are complete, CD577 open for PI, CD 14 close for vents, vibrations are normal, proper leakoff

4. If asked, after 30 minutes report seal water pressure is 25 psig.

At Lead Evaluators discretion, proceed to Event 3 NUREG-1021, Revision 9 Supplement 1 4Page of 16 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op-Test No.: 2011 NRC Scenario No.: 1 Event No.: 3 Page 5 of 16 Event

Description:

BAAT Pump 2 Breaker trips open Indications Available:

BAAT Pump 2 indicating lights are OFF Time Position Applicants Action or Behavior Role Role play as an Equipment Operator to report BAAT Pump Play 2 breaker, BF1169 on F11D is tripped Role Role-play as Maintenance/Work Week Manager/Field Play Supervisor as necessary to investigate the breaker trip.

After ~5 minutes report the need to tag out and troubleshoot.

Determines that TRM 8.1.1.A, Boric Acid Injection Flowpath, is SRO applicable for loss of both Boric Acid Addition Tank Pumps. 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Action At Lead Evaluators discretion, proceed to Event 4 NUREG-1021, Revision 9 Supplement 1 5Page of 16 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op-Test No.: 2011 NRC Scenario No.: 1 Event No.: 4 Page 6 of 16 Event

Description:

High RCS Activity Indication:

2-1-A, LETDOWN RAD HI RE 1998 radiation level rising RE 1998 Alert/High alarm lights on Time Position Applicants Action or Behavior Crew GO TO DB-OP-02002, Letdown/Makeup Alarm Panel 2 SRO Refer To DB-OP-02535, High Activity in the RCS SRO Notify Radiation Protection of potential radiation changes SRO Notify Chemistry to confirm the alarm by sampling RCS SRO Refer To TS 3.4.1 NOTE SRO At end of scenario have SRO declare EAL At Lead Evaluators discretion, proceed to Event 5 NUREG-1021, Revision 9 Supplement 1 6Page of 16 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op-Test No.: 2011 NRC Scenario No.: 1 Event No.: 5 Page 7 of 16 Event

Description:

RCS Pressure Transmitter (PT RC2B2) Fails High Indications Available:

Annunciator 4-4-B, HOT LEG PRESS HI 4-1-D, PZR RLF VLV OPEN Time Position Applicants Action or Behavior Crew Refer to annunciator response, DB-OP-02004 Direct entry to DB-OP-02513, Pressurizer System Abnormal SRO Operations CRITICAL TASK Determine PORV is open ATC Immediate

Close RC-11, PORV Block Action CRITICAL TASK Determine Spray Valve RC-2 is open ATC Immediate

Close Spray Valve Action Manually control Pressurizer heaters and spray to control RCS ATC pressure NUREG-1021, Revision 9 Supplement 1 7Page of 16 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op-Test No.: 2011 NRC Scenario No.: 1 Event No.: 5 Page 8 of 16 Event

Description:

RCS Pressure Transmitter Fails High (cont.)

Time Position Applicants Action or Behavior Exchange RCS Pressure input to heaters and spray IAW DB-OP-06403, RPS and NI Operating Procedure IF exchanging the RCS PRESSURE NNI input, THEN perform the following:

1. Place the following Pressurizer Heaters in OFF OR as ATC directed by the Control Room SRO.

HIS RC2-2, Bank 2

HIS RC2-3, Bank 3

HIS RC2-4, Bank 4

HIS RC2A, Essen Bank 1

2. Remove the cap on the selection panel for the alternate RC PRESSURE NNI receptacle in RPS Channel 2.

3. Disconnect the amphenol connector from the RC BOP PRESSURE NNI subassembly and reconnect the amphenol connector to the alternate RC PRESSURE NNI Receptacle.

4. Cap the open RC PRESSURE NNI receptacle.

ATC Return heaters and Spray to automatic ATC Reopen RC-11, PORV Block Determines that TS 3.3.1 is applicable for RCS pressure input SRO to RPS Channel 1 is failed BOP May decide to place RPS Channel 1 in Manual Bypass At Lead Evaluators discretion, proceed to Event 6, 7, 8 NUREG-1021, Revision 9 Supplement 1 8Page of 16 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op-Test No.: 2011 NRC Scenario No.: 1 Event No.: 6,7,8 Page 9 of 16 Event

Description:

(6) Circ Water System Rupture in Circ Water Pump House, CW pump discharge valve fails to automatically close, (7) 2 Stuck Rods, (8) AFPT failures Indications Available:

Annunciator 11-1-E, CLNG TWR BASIN LVL LO L070, CIRC WTR PMP HOUSE SUMP LVL Annunciator 11-3-E, CIRC WATER PUMP TEMP HI Time Position Applicants Action or Behavior I/F Role If EO is called to check Circ Water, after 2 minutes report Play that there is a pipe rupture upstream of CWP discharge valve and water level is rising in the Circ Water Pump House Go to DB-OP-02517, Circulating Water Pump Trip/Circulating SRO Water System Rupture Close Circulating Water Pump Discharge Valves BOP

Press CLOSE twice for each valve BOP Verify Circulating Water Pumps trip SRO Direct Reactor Trip and SFRCS Manual initiation Trip Reactor ATC

Perform Immediate Actions BOP Manually Initiate SFRCS SRO Direct implementation of any necessary Specific Rules NUREG-1021, Revision 9 Supplement 1 Page 9 of 16 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op-Test No.: 2011 NRC Scenario No.: 1 Event No.: 6,7,8 Page 10 of 16 Event

Description:

Cont.

Time Position Applicants Action or Behavior

Implement Specific Rule 1

Lock MU Pump suctions to the BWST ATC

Adjust Makeup and Letdown to maintain a boron injection flowpath from the BWST

Control MU Tank level using Attachment 13 Implement Specific Rule 4

- Refer to Attachment 5, section A Direct Equipment Operator to open FW 6396 Verify SUFW valves are in HAND with demands at zero CRITICAL BOP Verify Feedwater Block valves are closed TASK Block and open Feedwater Stop valves Block and Reset SUFW valves Start the MDFP Establish feedwater flow to at least one SG at < 1000 gpm BOP Verify proper SG level control using Specific Rule 4 SRO Implement DB-OP-02000 Supplementary Actions At Lead Evaluators discretion, terminate the scenario EAL SRO Determine if any EAL were applicable during the scenario:

Action see attached KEY. SU 9-1 applies

Note - It is acceptable to take these actions after routing back to supplementary action step 4.2.

- Note - Depending on the timeliness of these actions, SFRCS may re-actuate on Steam to Feed P after the Manual actuation requiring some of the steps in Attachment 5 to be repeat NUREG-1021, Revision 9 Supplement 1 Page 10 of 16 FENOC Facsimile Rev. 1

2011 NRC EXAM DAVIS BESSE SCENARIO 1 INSTRUCTOR FACILITY CUE SHEET Note: Role-play as Maintenance/Work Week Manager/Duty Team as necessary to investigate and make duty phone calls

1. Event 2, Condensate Pump Trip (a) When sent to Condensate Pump 1 breaker, identify a 50/51 relay tripped (b) Role-play as Maintenance/Work Week Manager/Field Supervisor as necessary to investigate (c) Respond to CTRM inquires for starting Condensate Pump, ie. prestartup checks are complete, CD577 open for PI, CD 14 close for vents, vibrations are normal, proper leakoff (d) If asked, after 30 minutes report seal water pressure is 25 psig.

2. Event 3, Boric Acid Pump Breaker Trip (a) Role play as an Equipment Operator to report BAAT Pump 2 breaker, BF1169 on F11D is tripped (b) Role-play as Maintenance/Work Week Manager/Field Supervisor as necessary to investigate the breaker trip. After ~5 minutes report the need to tag out and troubleshoot.

3. Event 6, Circ Water System Rupture (a) If EO is called to check Circ Water System/House, after 2 minutes report that there is a pipe rupture upstream of CWP discharge valve and water level is rising in the Circ Water Pump House (b) No flooding observed in Condensate Pit

4. Event 8, AFPT Problems (a) Report FW 6396 is open (b) AFPT 1 linkage is bent and can not be fixed by EO NUREG-1021, Revision 9 Supplement 1 Page 11 of 16 FENOC Facsimile Rev. 1

2011 NRC EXAM DAVIS BESSE SCENARIO 1 SIMULATOR SETUP

2% power IC

MFPT 2 running

MFPT 1 in Standby

Protected Train 2

BAAT Pump 1 tagged out

Monitor reactor power to maintain ~2% power until the crew takes control

Hang License Requirement Sheet on status board

Chart recorders clears

Applicable procedures wiped clean

Used Alarm Typer paper remover

Computer alarms cleared/acknowledged Setup BAAT Pump 1 ( P38-1) OOS

Remote B623C to Racked Out Two stuck Rods

L141M Control Rod 42

L142M Control Rod 41 EVENT 1 EVENT 5 Raise power to 4% RCS Pressure channel selected for NNI fails hi, PT-RC2B2 L4P2E from 0.58 in 60 seconds EVENT 2 EVENT 6 Trip running Condensate Pump Circ Water System rupture in the Circ Pump house FAK41 KK10 to 0.01 EVENT 3 EVENT 7 Trip BA Pump 2 Breaker Two stuck rods Remote B619C to Rack Out bkr Malfunctions L141M and L142M EVENT 4 EVENT 8 High RCS Activity >2E6 Both AFPTs trip on overspeed CM03 set at 0.21 AFPT 1: SFEIC to open, TTV1 OS Linkage AFPT 2: Remote SFEQA to trip, TTV2 manual trip NUREG-1021, Revision 9 Supplement 1 Page 12 of 16 FENOC Facsimile Rev. 1

2011 NRC EXAM DAVIS BESSE SCENARIO 1 Facility: Davis-Besse Task No: 334-01-05-0300 Task

Title:

Scenario 1 EAL Classification and Initial Notification Form K/A

Reference:

2.4.41 Job Performance Measure No: NEW Examinee:

NRC Examiner: Date:

Method of testing:

Simulated Performance ___ Actual Performance _X_

Classroom __X_ Simulator __ Plant ___

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

The plant conditions are specified in the Initial Conditions and Initiating Cues.

Task Standard:

Classify an event and complete the Initial Notification Form Required Materials:

RA-EP-01500, Emergency Notification General

References:

Initiating Cue:

The plant conditions are specified in the Initial Conditions and Initiating Cues.

Time Critical Task: No Validation Time: 30 minutes NUREG-1021, Revision 9 Supplement 1 Page 13 of 16 FENOC Facsimile Rev. 1

2011 NRC EXAM DAVIS BESSE SCENARIO 1 EAL DETERMINATION EXAMINER COPY INITIAL CONDITIONS The following events occurred during the scenario:

The running Condensate Pump tripped

Boric Acid Pump 2 breaker tripped

Letdown Activity rose

NNI selected RCS Pressure failed high

Circ Water Pump ruptured occurred

2 Control Rods did not insert on reactor trip

Both AFPTs tripped Wind Direction is 90° Wind Speed is 2 mph INITIATION CUE Determine the highest EALs classification, if any, apply and complete the Initial Notification Form if applicable.

(Hand Candidate a copy of DB-EP-01500, Emergency Classification)

See Initial Notification Form (INF) for KEY Critical items on INF form

1. Line 2: This is a DRILL

2. Line 3: a. EAL number (SU 9), Note: Date and Time not critical

3. Line 4: General description of event, example provided

4. *Line 5: a. Airborne release in progress

5. Line 6: c. No PAR recommended

Release in progress because the AFPT were running during event.

NOTE:

Because the AFPT will not be running when the RCS activity first initiated the EAL, it may be necessary to ask a follow-up question to anyone who checks the block for no release in progress. The follow-up question is Why did you select no release in progress? As long as the student explains that the AFPT was not running when the RCS activity first initiated, this will be considered SAT.

NUREG-1021, Revision 9 Supplement 1 Page 14 of 16 FENOC Facsimile Rev. 1

2011 NRC EXAM DAVIS BESSE SCENARIO 1 CANDIDATE COPY INITIAL CONDITIONS The following events occurred during the scenario:

The running Condensate Pump tripped

Boric Acid Pump 2 breaker tripped

Letdown Activity rose

NNI selected RCS Pressure failed high

Circ Water Pump ruptured occurred

2 Control Rods did not insert on reactor trip

Both AFPTs tripped Wind Direction is 90° Wind Speed is 2 mph INITIATION CUE Determine the highest EALs classification, if any, apply and complete the Initial Notification Form if applicable.

NUREG-1021, Revision 9 Supplement 1 Page 15 of 16 FENOC Facsimile Rev. 1

2011 NRC EXAM DAVIS BESSE SCENARIO 1 Verification of Completion Job Performance Measure No. Scenario 1 EAL JPM Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:_____________________________________________________________

Response:_____________________________________________________________

Result: Satisfactory/Unsatisfactory Examiners signature and date: _______________________________________

NUREG-1021, Revision 9 Supplement 1 Page 16 of 16 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Facility: Davis-Besse Scenario No.: 2 Op Test No.: NRC 2011 Examiners: Operators: SRO ATC BOP Initial Conditions:

70% power, MOL

AFPT #1 tagged OOS Turnover: The plant is at 70% power. MFPT #1 has a leak on the inboard bearing supply line.

The previous shift initiated a power reduction to take MFPT #1 out of service for repairs. Continue the power reduction at 5 %/minute and remove MFPT #1 from service. AFWPT 1 is OOS for Governor work Protected Train 2 Event Malf. Event Event No. No. Type* Description 1 N-SRO Controlled power reduction R-ATC 2 C-BOP, Increasing vibration on MFPT #1 requiring manual trip SRO 3 C-ATC, ICS AUTO Runback fails SRO 4 I- ATC, Selected Pressurizer temperature element fails low SRO 5 TS-SRO 120VAC Inverter alarm actuates in the control room 6 C- ATC, OTSG Tube Leak BOP, TS-SRO 7 M-ALL MFPT #2 trips 8 M-ALL OTSG tube leak rises to rupture following the reactor trip 9 C-ATC, PZR Spray Valve fails CLOSED during depressurization SRO

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Page 1 of 20 FENOC Facsimile Rev. 1

Scenario Event Summary 2011 NRC Scenario 2 DAVIS-BESSE 2011 NRC SCENARIO 2 The crew will take the watch with power holding at approximately 70%. The previous shift initiated a power reduction to take MFPT #1 out of service for repairs using DB-OP-06902, Power Operation. Directions will be to continue the power reduction and remove MFPT #1 from service for repair of an oil leak.

Any time after the power reduction is initiated the Lead Evaluator can cue initiation of rising vibration levels on MFPT #1. The crew should respond to alarm 10-3-A in accordance with DB-OP-02010, FEEDWATER ALARM PANEL 10 ANNUNCIATORS. The Auxiliary Operator (AO) will report a vibration level exceeding the threshold for tripping the pump. The crew should trip MFPT #1, recognize that an AUTO runback did not initiate and then manually runback power to within the capacity of one MFWP.

After power has stabilized, the Lead Evaluator can cue the selected Pressurizer temperature element failing low.. Pressurizer level will indicate low. The RCS make-up valve, MU32, will open. Crew will take MU32 to hand to maintain Pressurizer level where it is at. The crew will determine the failure and select a different Pressurizer temperature element.

After the crew has selected a different Pressurizer temperature element, the Lead Evaluator can cue actuation of alarm 1-6-A, INV YV1-YV-3 TRBL. The crew should respond in accordance with DB-OP-02001, ELECTRICAL DISTRIBUTION ALARM PANEL 1 ANNUNCIATORS, and dispatch an AO to investigate. The AO will report that one of the inverters has shifted to the alternate source. The SRO should request maintenance assistance and/or enter the correct TS.

If necessary, the maintenance supervisor will report an electrical problem that indicates the normal supply cannot be restored until corrective actions are completed.

Any time after the SRO has entered the TS for the 120VAC problem, the Lead Evaluator can cue initiation of the OTSG tube leak. The crew should respond to alarm 9-4-A, Vac Sys Disch Rad Hi, in accordance with DB-OP-02009, PLANT SERVICES ALARM PANEL 9 ANNUNCIATORS, which will direct them to DB-OP-02531, STEAM GENERATOR TUBE LEAK, for actions. The simulator operator will maintain leak rate greater than the TS limit but less than DB-OP-02000 entry. After the crew has recognized the tube leak and/or the SRO is evaluating the tube leak TS, the Lead Evaluator can cue the MFPT #2 trip. This results in a reactor trip and entry into DB-OP-02000. After the crew has entered DB-OP-02000, the OTSG tube leak will ramp to a size below SFAS actuation. Among other actions, the crew will perform the following high level activities: establish HPI piggyback operation, depressurize the RCS using Pressurizer PORV when the Spray Valve fails closed.

The Lead Evaluator can terminate the scenario when all high level activities have been completed and the evaluators agree the crew can be properly evaluated.

NUREG-1021, Revision 9 Supplement 1 Page 2 of 20 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 Scenario # 2 Event # 1 Page 3 of 20 Event

Description:

Controlled Power Reduction Time Position Applicants Actions or Behavior Direct Load Reduction to ~450 MWe at 5 %/minute IAW SRO DB-OP-06902, Section 6 ATC Set ULD to 450 MWe and ENTER ATC Set ULD for 5 %/min and ENTER CREW Monitor plant parameters On Lead Evaluators discretion, insert Event 2 NUREG-1021, Revision 9 Supplement 1 Page 3 of 20 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 Scenario # 2 Event # 2 Page 4 of 20 Event

Description:

ICS AUTO Runback Fails Time Position Applicants Actions or Behavior Event 2: Increasing Vibrations on MFPT 1 requiring manual trip Indications Available:

10-3-A, MFP 1 or BFP 1 BEARING VIB HI Excessive vibration of MFP 1 Bearings Excessive vibration of MFPT 1 Bearings Excessive vibration of MFPT 1 Gear Reducer Bearings CREW Refer to Annunciator Response DB-OP-02010 Send EO to locally monitor the MAIN FD PUMPS 1 AND 2 BOP VIBRATION PANEL for Gear Reducer, Booster Pump, and Feed Pump vibration.

Obtain vibration reading from ZJR 2538, MAIN TURBINE &

BOP MFP TURBINES - BEARING VIBRATION & ECCENTRICITY, points 11 and 12 for MFPT 1.

IF vibration amplitude increases and remains above the second setpoint AND Maintenance personnel are NOT immediately SRO/BOP available to take vibration readings, THEN trip MFPT 1 using HS 797, TURBINE TRIP.

I/F Role 1. Report that Maintenance personnel are NOT available.

Play

2. If asked, EO reports vibration from MFP vibration panel (use value on I/F screen)

BOP TRIP MFPT #1 NUREG-1021, Revision 9 Supplement 1 Page 4 of 20 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 Scenario # 2 Event # 3 Page 5 of 20 Event

Description:

ICS AUTO Runback Fails Time Position Applicants Actions or Behavior Event 3: Auto ICS MFP Runback fails Indications Available:

8-4-A, MFPT 1 TRIP 4-3-E, PZR LEVEL HI 14-3-D, ICS MFP LOSS OR LOW DEAR RUNBACK 14-4-C, ICS RX PWR LIMITED BY FEEDWATER IF an ICS Runback occurs THEN REFER to DB-OP-06401, Integrated Control System Operating Procedure. Runback should occur but does NOT.

Places SG/RX DEMAND H/A Station in HAND and initiates ATC runback at 20% power per minute (See Event next page)

Crew may refer to OP-06401 for runback.

IF the runback was caused by a feed pump trip, THEN perform ATC/BOP the following:

IF ICS was NOT in TRACK, THEN verify ICS is or has runback at 20%/minute to 55% power. OTHERWISE place HIC ICS13, ATC SG/RX DEMAND station in HAND AND perform the runback at 20%/minute to 55% power. (ULD DEMAND as read on DAAS=514 Mwe)

IF the pressurizer spray valve was operated, THEN verify RC2, ATC PRESSURIZER SPRAY VALVE is in AUTO AND closed.

ATC/BOP Perform a NIP/HBP comparison for the current power level.

REFER to DB-OP-06902, Power Operations, for guidance to SRO operate plant equipment for the current power level.

On Lead Evaluators discretion, proceed to Event 4 NUREG-1021, Revision 9 Supplement 1 Page 5 of 20 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 Scenario # 2 Event # 4 Page 6 of 20 Event

Description:

Time Position Applicants Actions or Behavior Event 4: Selected Pzr temperature element (TE), RC15-1, fails low Indications Available:

2-4-C, MU FLOW HI TRN 2 4-2-E, PZR LVL LO CREW Go To DB-OP-02004, RC Alarm Panel 4 Annunciators CREW Refer to DB-OP-02513, Section 4.6.

ATC Place MU32, RCS Makeup valve, in HAND ATC Adjust MU32 to obtain desired Makeup flow or Pzr level ATC Compare Pzr Instrument, identify selected TE has failed ATC Select a good TE ATC Place MU32 in AUTO On Lead Evaluators discretion, proceed to Event 5 NUREG-1021, Revision 9 Supplement 1 Page 6 of 20 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 Scenario # 2 Event # 5 Page 7 of 20 Event

Description:

120VAC Inverter Alarm Actuates in the Control Room Time Position Applicants Actions or Behavior Event 5: 120 VAC Inverter actions in the CTRM Indications Available:

Annunciator Alarm (1-6-A) INV YVI-YV3 TRBL CREW Refer to Annunciator Response DB-OP-02001 Dispatch EO to inspect Essential Inverters YV1 or YV3 to SRO determine which channel(s) caused the alarm.

I/F Role EO reports that the YRF1 input breaker CB1 is open Play REFER to DB-OP-06319, Instrument AC System Procedure, SRO Emergency Operations Section.

SRO Refer to Technical Specification: 3.8.7 On Lead Evaluators discretion, proceed to Event 6 NUREG-1021, Revision 9 Supplement 1 Page 7 of 20 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 Scenario # 2 Event # 6 Page 8 of 20 Event

Description:

OTSG Tube Leak Time Position Applicants Actions or Behavior Event 6: SG Tube Leak Indications Available:

9-4-A, VAC SYS DISCH RAD HI 12-1-B, MN STM LINE 2 RAD HI Makeup flow rising PZR level lowering CREW Refer to Annunciator Response DB-OP-02009 and/or 02012 BOP Confirms reading on RE600 on CTRM RIM panel GO to DB-OP-02531, Steam Generator Tube Leak, for SRO guidance.

CREW Determine which SG is leaking (SG-2)

Calculate a leak rate using Attachment 1, Steam Generator CREW Tube Leak Rate Calculation. ( ~35 gpm)

Crew Determines SGTL is <50 gpm Determine Emergency Classification. REFER to RA-EP-SRO 01500, emergency Classification.

NOTE At end of scenario have SRO declare EAL SRO Refer to TS 3.4.13, RCS Operational Leakage, Condition B Determine a shutdown rate to achieve at a minimum less than SRO 50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SRO Refer To DB-OP-02504, Rapid Shutdown NUREG-1021, Revision 9 Supplement 1 Page 8 of 20 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 Scenario # 2 Event # 6 Page 9 of 20 Event

Description:

OTSG Tube Leak Time Position Applicants Actions or Behavior Notify Chemistry personnel to perform Attachment 2, Chemistry SRO Personnel Responsibilities.

Notify Radiation Protection personnel to perform Attachment 3, SRO Radiation Protection Personnel Responsibilities.

Perform Attachment 4, Control of Secondary Contamination SRO and Offsite Releases.

IF the leak rate calculation exceeds T.S. 3.4.13 limits with 4 SRO RCPs running, Notify the System Control Center (SCC) of the unit load SRO reduction.

As determined by the SRO, reduce unit load IAW DB-OP-SRO 02504 by any of the following methods:

ATC

At the LOAD CONTROL panel:

1. Set the RATE OF CHANGE to a rate specified by the ATC SRO and press ENTER

2. Set the Target Load specified by the SRO and press ATC ENTER CREW .Monitor plant parameters On Lead Evaluators discretion, proceed to Event 7, 8, 9 NUREG-1021, Revision 9 Supplement 1 Page 9 of 20 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 Scenario # 2 Event # 7, 8, 9 Page 10 of 20 Event

Description:

Time Position Applicants Actions or Behavior Event 7, Manual trip of MFPT 2 8, SGTL increase to a SG Tube Rupture 9, Pzr Spray Valve fais closed during depressurization Indications Available:

8-4-b, MFPT 2 Trip 8-1-A, CRD TRIP CONFIRM Manually Trip the Reactor

Reactor Trip Pushbutton has been depressed AND ATC

Power is decreasing on the Intermediate Range Nuclear Instrumentation Manually trip the Turbine.

ATC

Turbine Trip Pushbutton has been depressed AND

Turbine Stop Valves 1, 2, 3 AND 4 are closed SRO Implement any necessary Specific Rules SG LEVEL SETPOINTS - May apply. MDFP must be started to feed SG 1 IAW Attachment 5

Enable BOTH MDFP Discharge Valves, HIS 6460 and 6459 BOP

Close Both MDFP Discharge Valves, LIC 6460 and 6459

Start MDFP

Establish FW flow to SG 1 at less than 1000 gpm NUREG-1021, Revision 9 Supplement 1 Page 10 of 20 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 Scenario # 2 Event # 7, 8, 9 Page 11 of 20 Event

Description:

Time Position Applicants Actions or Behavior Implement any necessary Symptom Mitigation Sections SRO

Section 8.0 STEAM GENERATOR TUBE RUPTURE -

does apply. SRO will route to Section 8.0, Step 8.19 CRITICAL IF HPI piggyback operation is NOT in service, THEN line up TASK and start HPI piggyback operation as follows per Att 8:

*Start the standby CCW Pump.

*Start BOTH HPI Pumps

*Open HPI Injection Valves, HP2A, 2B, 2C, and 2D ATC

*Start BOTH LPI pumps are running

*Open DH64 and DH63

*Transfer MU Pump suctions to the BWST

Set Pzr Level Controller to 100

*Verify Standby Makeup Pump is running IF BOTH MU Pumps are running, THEN open MU 6421, CTMT ATC ISOLATION FOR ALTERNATE INJECTION LINE.

ATC Control MU flow using MU 6419 and MU 32 per Speciic Rule 3 Verify SG levels are controlled at OR increasing the proper BOP level using Specific Rule 4.

ATC Depressurize the RCS as follows:

Turn off all PZR heaters.

CAUTION: With the SFAS Low RCS Pressure Trip blocked, the operator is responsible for initiating SFAS should the leak rate increase such that Pressurizer level OR RCS pressure can NOT be controlled.

NUREG-1021, Revision 9 Supplement 1 Page 11 of 20 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 Scenario # 2 Event # 7, 8, 9 Page 12 of 20 Event

Description:

Time Position Applicants Actions or Behavior IF SFAS has NOT actuated on Low RCS Pressure, AND RCS pressure decrease is being manually controlled, THEN block CREW the SFAS Low RCS Pressure trip when the BLOCK PERMIT comes on.

Use Pressurizer Spray to reduce RCS pressure to maintain ATC minimum adequate subcooling margin.

ATC Verify RC 10, PZR SPRAY BLOCK Valve.

ATC Open RC 2, PZR SPRAY Valve (valve does NOT open).

IF Pressurizer Spray is NOT available OR is NOT sufficient to SRO reduce RCS pressure THEN REFER to Step 8.25 for guidance on Depressurizing the RCS without PZR Spray.

Depressurize the RCS as follows:

Turn off all PZR Heaters ATC

Start the QT Circ Pump if available

Close DR 2012A and DR 2012B, CTMT Normal Sump CTMT Isolation valves Reduce RCS pressure to close to the minimum adequate SCM ATC curve (Fig. 1) using one of the following methods:

PZR Vent Line Method

Open RC 200, PZR VENT TO QT ISOLATION ATC

Open RC239A, PZR STEAM SPACE SAMPLE

Manually Cycle RC239A and Pzr heaters to maintain RCS pressure close to minimum adequate SCM OR NUREG-1021, Revision 9 Supplement 1 Page 12 of 20 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 Scenario # 2 Event # 7, 8, 9 Page 13 of 20 Event

Description:

Time Position Applicants Actions or Behavior PORV method

Open RC 11, PORV Block Valve ATC

Open RC 2A, PORV

Manually cycle the PORV AND control PZR heaters to maintain RCS pressure close to the minimum adequate SCM CAUTION: With the SFAS Low RCS Pressure trips blocked, the operator is responsible for initiating SFAS if the leak rate rises such that PZR level OR RCS pressure can NOT be controlled.

IF SFAS has NOT actuated on Low RCS Pressure, AND if the RCS pressure decrease is being manually controlled with CREW adequate SCM THEN block the SFAS Low RCS Pressure trips when the BLOCK PERMITs come in.

Allow HPI and MU to recover PZR level AND maintain PZR ATC level from 80 to 120 inches by controlling HPI and MU.

SRO Check for entry into PTS criteria. REFER to Specific Rule 5.

CREW Establish a 50°F/hr cooldown rate.

IF SFRCS has tripped the AVVs, THEN block the trip and take control as follows:

Place BOTH AVV H/A Stations in HAND

Reduce BOTH demands to zero.

BOP

Press the AVV BLOCK pushbuttons (HIS-ICS-11D or HIS-ICS-11C).

Press AUTO on HIS-ICS-11B or HIS-ICS-11A

Control SG pressure using the H/A Station NUREG-1021, Revision 9 Supplement 1 Page 13 of 20 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 Scenario # 2 Event # 7, 8, 9 Page 14 of 20 Event

Description:

Time Position Applicants Actions or Behavior CRITICAL Depressurize the RCS down to AND maintain close to the TASK CREW minimum adequate subcooling margin limit during RCS cooldown.

Scenario may be terminated when RCS depressurization is in progress EAL SRO Determine if any EAL were applicable during the scenario.

Action See attached INF KEY. FA1 for SGTR NUREG-1021, Revision 9 Supplement 1 Page 14 of 20 FENOC Facsimile Rev. 1

INSTRUCTOR FACILITY CUE SHEET\

NOTE: Role-play as Maintenance/Work Week Manager/Duty Team as necessary

1. Event 2

a. Report that Maintenance personnel are NOT available.

b. If asked, EO reports vibration from MFP vibration panel (use value on I/F screen)

2. Event 5

a. EO reports that the YRF1 input breaker CB1 is open NUREG-1021, Revision 9 Supplement 1 Page 15 of 20 FENOC Facsimile Rev. 1

SIMULATOR SETUP

~70% power

AFPT 1 OOS for Governor work

MFPT 1 has an oil leak

Protected Train 2 SETUP ICS - L3M1A, MFP runback failure Tagout AFP 1: SFE8B, closes MS1106 RemoteSFE8A, opens MS106 breaker SFEAB, closes MS106A Remote SFEAA opens MS106A breaker Remote SFE1A, trips AFPT 1 trip throttle valve Event 1 Event 6 SG 2 Tube Leak Lower power to remove MFP 1 from service HH51 from 0.0 to 0.0095 in 300, (~35 gpm)

Event 2, Increasing MFPT 1 vibrations Event 7 Spurious trip of MFP 2 SFFB from 0.01 to 0.85 in 900 on Event 2 SFR6C SFFA from 0.01 to 0.9 in 600 on Event 2 Event 3 Event 8 SG2 Tube Rupture, Spray Valve FC L3M1A, MFP runback failure HH51 to 0.093 increases SG 2 Tube Leak (~300 gpm)

HV00C, RC2 Motor fails close Event 4, Pzr TE fails low H1C1H, TT15-1 RTD short Event 15, After MFPT 1 is tripped, change vibration SFFB from 0.85 to 0 in 900 Event 5 120v inverter failure SFFA from 0.9 to 0 om 900 Remote E601, open breaker to YRF1 NUREG-1021, Revision 9 Supplement 1 Page 16 of 20 FENOC Facsimile Rev. 1

Facility: 2011 NRC Davis-Besse Task No: 334-01-05-0300 Task

Title:

Scenario 2 EAL Classification and Initial Notification Form K/A

Reference:

2.4.41 Job Performance Measure No: NEW Examinee:

NRC Examiner: Date:

Method of testing:

Simulated Performance ___ Actual Performance _X_

Classroom ___ Simulator __ X Plant ___

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

The plant conditions are specified in the Initial Conditions and Initiating Cues.

Task Standard:

Classify an event and complete the Initial Notification Form Required Materials:

RA-EP-01500, Emergency Notification General

References:

Initiating Cue:

The plant conditions are specified in the Initial Conditions and Initiating Cues.

Time Critical Task: No Validation Time: 30 minutes NUREG-1021, Revision 9 Supplement 1 Page 17 of 20 FENOC Facsimile Rev. 1

2011 NRC Exam Scenario 2 EAL DETERMINATION EXAMINER COPY INITIAL CONDITIONS The following events occurred during the scenario:

Controlled power reduction

MFPT 1 vibration and trips

ICS Feedpump Runback trip

Pressurizer temperature element fails low

YRF1 failure

SG Tube Leak increases to SG Tube Rupture

Pressurizer Spray Valve fails closed Wind Direction is 90° Wind Speed is 2 mph INITIATION CUE Determine the highest EALs classification, if any, apply and complete the Initial Notification Form if applicable.

(Hand Candidate a copy of DB-EP-01500, Emergency Classification)

See Initial Notification Form (INF) for KEY Critical items on INF form

1. Line 2: This is a DRILL

2. Line 3: a. EAL number (SU 1), Note: Date and Time not critical

3. Line 4: General description of event, example provided

4. *Line 5: c. Release in progress

5. Line 6: c. No PAR recommended

Release in progress because the AFPT were running and AVV are used during event.

NUREG-1021, Revision 9 Supplement 1 Page 18 of 20 FENOC Facsimile Rev. 1

2011 NRC Exam Scenario 2 CANDIDATE COPY INITIAL CONDITIONS The following events occurred during the scenario:

Controlled power reduction

MFPT 1 vibration and trips

ICS Feedpump Runback trip

Pressurizer temperature element fails low

YRF1 failure

SG Tube Leak increases to SG Tube Rupture

Pressurizer Spray Valve fails closed Wind Direction is 90° Wind Speed is 2 mph INITIATION CUE Determine the highest EALs classification, if any, apply and complete the Initial Notification Form if applicable.

NUREG-1021, Revision 9 Supplement 1 Page 19 of 20 FENOC Facsimile Rev. 1

Verification of Completion Job Performance Measure No. Scenario 2 EAL JPM Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:_____________________________________________________________

Response:_____________________________________________________________

Result: Satisfactory/Unsatisfactory Examiners signature and date: _______________________________________

Determine if any EALs apply and complete applicable paperwork NUREG-1021, Revision 9 Supplement 1 Page 20 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Facility: DAVIS-BESSE Scenario No.: 3 Op Test No.: NRC 2011 Examiners: Operators: SRO ATC BOP Initial Conditions: ~60% power, 3 Reactor Coolant Pumps (RCP) running RCP 1-1 is not running Low Pressure Injection Pump 1 is out of service Turnover: The crew will assume the watch with the plant at ~60% power. Three RCPs are running. RCP 1-1 was stopped due to low oil level in the lower bearing reservoir. Senior Management is currently deciding when to begin a plant shutdown to repair RCP 1-1. Following turnover the Crew will take action to transfer Gland Steam from Main Steam to Auxiliary Steam in order allow I&C to calibrate the Main Steam Reducer controller Event Malf. Event Event No. No. Type* Description N - BPO, 1 Transfer Gland Steam from Main Steam to Auxiliary Steam SRO The crew will be notified that Auxiliary Feedwater Pump 1 2 TS - SRO has no Governor oil C - ATC, Pressurizer level control valve (MU 32) fails to operate in 3

SRO auto R - ATC 4 N - SRO Control Rod drop TS - SRO 5 I - All Loss of NNI X DC, manual Rx trip required 6 M - All Loss of Offsite AC C - ATC, 7 Emergency Diesel Generator 1 fails to auto start SRO C - BOP, 8 AFW Pump 2 governor valve closes SRO

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Page 1 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 DAVIS-BESSE 2011 NRC SIMULATOR SCENARIO 3 The crew will assume control with power at ~60% power and 3 Reactor Coolant Pumps in operation.

After turnover is complete the Lead Evaluator will direct the crew to transfer Gland Steam from Main Steam to Auxiliary Steam.

The Lead Evaluator will cue the Auxiliary Feedwater Pump 1 governor oil problem. The crew should review TS and declare AFW 1 inoperable.

The Lead Evaluator will cue the dropped rod. The RCS temperature will lower and the Pressurizer level will drop due to the dropped control rod. If Pressurizer level drops to 200 inches alarm 4-2-E, PZR LVL LO will alarm. The MU 32 failure to operate in automatic will be inserted when the rod drops. The crew should identify that MU 32 is not responding. The crew should take MU 32 to HAND and control Pressurizer level by adjusting MU 32 position manually.

For the dropped rod, the crew should enter DB-OP-02516, CRD Malfunctions. The SRO should enter TS. The TS Limit with a dropped rod and 3 RCPs running is 45%

power (320 MWE). The crew should reduce power in accordance with DB-OP-02504, Rapid Shutdown.

The Lead Evaluator will cue the Loss of NNI X DC power during control rod recovery.

Annunciator 14-1-D, NNI-X 24 VDC BUS TRIP, on MSR/ICS Alarm Panel 14 Annunciators will alarm. The crew should enter DB-OP-2532, Loss of NNI/ICS Power.

The crew should recognize a minor transient is in progress due to the mid-scale failure of Turbine Throttle Pressure by transferring the Turbine to MANUAL and transferring the SG/Rx Demand Station to HAND, and lowering the Turbine load.

The Lead Evaluator will cue the Loss of Offsite AC power. The crew will enter DB-OP-02000, RPS, SFAS, SFRCS Trip, or SG Tube Rupture, when the reactor trips.

Emergency Diesel Generator (EDG) 1 will fail to auto start. EDG 1 should be started manually.

The AFPT 2 governor valve will fail closed when AFW Pump 2 receives a start signal.

The crew should respond by entering DB-OP-02000, Section 6, Lack Of Heat Transfer.

The crew should energize non-essential electrical bus D2 from the Station Blackout Diesel Generator or one of the EDGs and align the Motor Driven Feedwater Pump to feed at least one of the Steam Generators.

The Lead Evaluator can terminate the scenario when all high level activities have been completed and the evaluators agree the crew can be properly evaluated.

NUREG-1021, Revision 9 Supplement 1 Page 2 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: 2011 NRC Scenario No.: 2 Event No.: 1 Page 3 of 20 Event

Description:

Following turnover the Crew will transfer Gland steam from the Main Steam system to the Auxiliary Steam System in accordance with DB-OP-06205 Section 3.6.

Time Position Applicants Actions or Behavior BOP Verify the 235 psig Aux Steam Header is in service Direct an Equipment Operator to open AS1934, Aux Steam Supply BOP to 5# Condensate Tank 1-1 Control Valve, for 1 minute and then close AS 1934 I/F Inform the CTRM that As1934 has been opened for 1 minute Role and then closed Play Throttle open GS 2385, Steam Seal Feed Bypass, to control Gland BOP Steam pressure at 4.5 psig using HIS 2385 BOP Close GS 2384, Seal Steam Supply Valve using HIS 2384 Open GS 2380, Aux Steam Supply Steam Seal Valve, using HIS BOP 2380 BOP Close GS 2385 using HIS 2385 BOP Verify Steam Seal Header pressure is between 2.5 to 4.5 psig At Lead Controllers discretion, proceed to Event 2 NUREG-1021, Revision 9 Supplement 1 Page 3 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: 2011 NRC Scenario No.: 3 Event No.: 2 Page 4 of 20 Event

Description:

An Equipment Operator will report that AFPT 1 Governor oil sightglass is broken and the oil has leaked out. The SRO should declare AFPT 1 inoperable and entered the AFW Tech Spec Time Position Applicants Actions or Behavior I/F Call CTRM and report that AFPT 1 Governor oil sight glass is Role broken and the oil has leaked out.

Play SRO Determine AFW Pump 1 is inoperable SRO Refer to Tech Spec 3.7.5, Emergency Feedwater, Condition B Notify Operations Management of the unplanned entry into Tech SRO Specs At Lead Controllers discretion, proceed to Event 3 and 4 NUREG-1021, Revision 9 Supplement 1 Page 4 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: 2011 NRC Scenario No.: 3 Event No.: 3&4 Page 5 of 20 Event

Description:

(3)Regulating Control Rod 5-8 drops, and (4) MU32 does not operate in manual Time Position Applicants Actions or Behavior Recognize a dropped control rod

Annunciator 5-1-E, CRD LCO CREW

Annunciator 5-2-E, CRD ASYMETRIC ROD

Control Rod 5-8 Rod Bottom light ON SRO Implement DB-OP-02516, CRD Malfunctions Reduce Reactor power to 50%

ATC

Reduce ULD MAX LOAD LIMIT to 320 MWE

Set ULD to 3%/MIN SRO Refer to DB-OP-02504, Rapid Shutdown SRO Notify the Load Dispatcher of plant shutdown Contact Chemistry to monitor Condensate Polishers and sample SRO the RCS ATC Maintain Makeup tank level Remove a Main Feed Pump from service

Place the ICS controller in HAND and lower speed to 3900 RPM

Null the transfer volts using the MDT 20 output BOP

Place the MDT 20 control in MANUAL

Lower the MDT 20 to the LOW SPEED STOP

Trip the MFPT

Verify the Discharge NRV is closed NUREG-1021, Revision 9 Supplement 1 Page 5 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: 2011 NRC Scenario No.: 3 Event No.: 3&4 Page 6 of 20 Event

Description:

(3)Regulating Control Rod 5-8 drops, and (4) MU32 does not operate in manual (cont.)

Time Position Applicants Actions or Behavior Reduce Pressurizer set point to 180 inches if necessary ATC

Recognize MU 32 is not responding in Automatic control Place MU 32 in HAND in accordance with DB-OP-02512, Makeup ATC and Purification Malfunctions, and manually control Pressurizer level as directed Stabilize power at < 45%

ATC

Adjust the ULD MAX LOAD LIMIT as directed

Adjust the ULD RATE OF CHANGE as directed SRO Refer to NG-DB-00230, Reactivity Management SRO Contact Reactor Engineering ATC Contact Work Week Manager/I&C to investigate Refer to DB-OP-02516 Attachment 3 to determine Tech Spec SRO applicability

Tech Spec. 3.1.4 for the dropped rod At Lead Controllers discretion, proceed to Event 5 NUREG-1021, Revision 9 Supplement 1 Page 6 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: 2011 NRC Scenario No.: 3 Event No.: 5 Page 7 of 20 Event

Description:

A loss of NNI-X DC power causes a midscale failure of HAND/AUTO stations for MU 32 for Pressurizer level control and MU 19 for Seal Injection flow control.

Turbine Throttle Pressure fails midscale. Most indicators and controls powered by NNI-X DC will automatically transfer to NNI-Y DC powered indicators and control. Manual control of Pressurizer heaters, Pressurizer Spray and Pressurizer level will be required Time Position Applicants Actions or Behavior Recognize a loss of NNI-X DC Power

14-1-D NNI-X 24 VDC BUS TRIP CREW

Loss of X-DC NNI Power Indicating Light on Control Room Panel C5722 SRO Implement DB-OP-02532, Loss of NNI/ICS Power CREW Monitor for a plant transient If a significant transient occurs, then (1) Trip the Reactor ATC (2) Initiate and Isolate SFRCS using Manual Actuation Switches (3) Go To DB-OP-02000, EOP I/F If the Reactor is tripped, insert malfunctions 6,7,8 If a minor transient occurs due to a midscale failure of Turbine CREW Throttle Pressure occurs BPO Place the EHC Control Panel in MANUAL ATC Place the SG/Rx Demand Station in HAND Lower Turbine load using the DECREASE pushbutton to restore BOP Turbine Header pressure to 870 to 880 psig ATC Monitor Pressurizer level using uncompensated level indicators NUREG-1021, Revision 9 Supplement 1 Page 7 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: 2011 NRC Scenario No.: 3 Event No.: 5 Page 8 of 20 Event

Description:

Loss of NNI-X DC power (cont.)

Time Position Applicants Actions or Behavior Maintain RCS pressure by manually controlling Pressurizer Heaters ATC and Pressurizer Spray as necessary Place the Makeup System alternate injection line in service

Close MU 6422, Makeup Train 2 To RCS Isolation

Open MU 6421, Makeup Train 1 To RCS Isolation ATC

Throttle open MU 6419, Makeup Train 1 Injection, to maintain desired Pressurizer level

Direct an Equipment Operator to open MU 6423B, Makeup Train 1 Flow Controller Bypass Monitor Makeup Tank level using NNI-Y powered indication ATC Manually transfer Makeup Pump suction valves as required ATC/BOP Transfer all NNI selector switches to NNI-Y I/F Role Role play as I&C for investigating loss of NNI-X DC At Lead Controllers discretion, proceed to Event 6, 7, 8 NUREG-1021, Revision 9 Supplement 1 Page 8 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: 2011 NRC Scenario No.: 3 Event No.: 6,7,8 Page 9 of 20 Event

Description:

A loss of offsite electrical power causes a Reactor trip and a loss of all RCPs. The loss of the RCPs causes a SFRCS actuation. AFPT 1 will start and overspeed trip due to the loss of governor oil. AFPT 2 fails to start requiring the use of the MDFP. D2 Bus will have to be reenergized to provide power to the MDFP. EDG 1 fails to automatically start but can be started manually from the Control Room Time Position Applicants Actions or Behavior CREW Recognize a loss of offsite power and Reactor trip Perform DB-OP-02000 Immediate Actions

Manually trip the reactor ATC

Verify power decreasing in the intermediate range

Manually trip the turbine SRO Route to DB-OP-02000, Section 3 SRO Verify immediate actions CREW Implement Specific Rules

Use Attachment 6 of DB-OP-02000 to re-power D2 Bus

- From the SBODG

Verify AD213 close

Open ABDD2

Verify AD 110 is open

Start the SBODG by pressing START at the SBODG ATC/BOP Control Panel C5740

Check SBODG speed approximately 900 RPM

Verify AD213 is closed

Close AD 301 to energize Bus D2

Verify Bus D2 energized

Verify AD2DF7 is closed

Verify BDF7 is closed

Critical Task NUREG-1021, Revision 9 Supplement 1 Page 9 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: 2011 NRC Scenario No.: 3 Event No.: 6,7,8 Page 10 of 20 Event

Description:

Continued Time Position Applicants Actions or Behavior

Use Attachment 6 of DB-OP-02000 to re-power D2 Bus

- From EDG 2

Verify AD301, SBODG BKR is open

Verify AD205, XFMR BDF6 is open

Verify AD206, CLNG WTR PMP 2 is open

Verify AD201, STA AIR CMPSR 2 is open or lock out

Verify AD202, CLNG TWR MU PMP 2 is open

Verify AD204, HTR DRN PMP 2 is open

Verify AD207, CNDS PMP 2 is open

Verify AD210, MOTOR DRIVEN FEED PUMP is open

Open ABDD2, HIS 6228, ABDD2

Place D1 SYNC SELECT to BKR to D2

Close AD110, HIS 6233, AD110

Verify D2 is energized

Place D1 SYNC SELECT in the OFF

Close AD2DF7

Verify BDF7 is closed

- From EDG 1 ATC/BOP

Verify AD301, SBODG BKR is open

Verify ABDD2, BUS TIE XFMR BD is open

Verify AD205, XFMR BDF6 is open

Verify AD206, CLNG WTR PMP 2 is open

Verify AD201, STA AIR CMPSR 2 is open or lock out

Verify AD202, CLNG TWR MU PMP 2 is open

Verify AD204, HTR DRN PMP 2 is open

Verify AD207, CNDS PMP 2 is open

Verify AD210, MOTOR DRIVEN FEED PUMP is open

Verify AD110 is open, HIS 6233, AD110

Verify HBBD is open, HIS 6214, HBBD

Verify AC110 is open, HIS 6223, AC110

Place the C1 SYNC SELECT Switch to BKR TO XBD

Close ABDC1, HIS 6220, ABDC1

Place the C1 SYNC SELECT Switch to OFF

Close ABDD2, HIS 6228, ABDD2

Verify D2 is energized

Close AD2DF7

Verify BDF7 is closed

Critical Task NUREG-1021, Revision 9 Supplement 1 Page 10 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: 2011 NRC Scenario No.: 3 Event No.: 6,7,8 Page 11 of 20 Event

Description:

Continued Time Position Applicants Actions or Behavior

Use Attachment 5 of DB-OP-02000 to start the MDFP

- Enable BOTH MDFP Discharge Valves

HIS 6460

HIS 6459

- Close BOTH MDFP Discharge Valves BOP

LIC 6460

LIC 6459

- Start the MDFP

- Establish feedwater flow to aSteam Generators at less than 1000 gpm indicated flow on the MDFP Flow Indicator FI 5876 Verify proper SG level control using Specific Rule 4, Steam BOP Generator Control Direct an Equipment Operator to locally shift MDFP recirculation to BOP the CST Implement Specific Rule 6

Verify MU Pump 1 breaker is open

Manually start EDG 1 ATC

Verify C1 Bus is energized

Verify CCW Pump 1 is running

Verify Service Water Pump 1 is running CREW Recognize lowering Instrument Air pressure BOP Start the EIAC

Critical Task NUREG-1021, Revision 9 Supplement 1 Page 11 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: 2011 NRC Scenario No.: 3 Event No.: 6,7,8 Page 12 of 20 Event

Description:

Continued Time Position Applicants Actions or Behavior CREW Check for symptom direction ATC Check for all Group 1-7 Control Rods fully inserted Perform Attachment 1, Primary Inventory Control Actions

Transfer MU Pump suctions to the BWST ATC

Manually control MU 6419 to control Pressurizer level at 80 to 120 inches

Brief the SRO on Primary Plant status Perform Attachment 2, Steam Generator Inventory and Pressure Control Actions

- Verify Steam Generator Levels are being controlled at 49 inches with the MDFP

- Place the Atmospheric Vent Valves in manual using Attachment 3

Place the AVV Hand/Auto Stations in HAND BPO

Reduce the AVV) demands to zero

Press the AVV BLOCK pushbuttons

Press AUTO on the AVV Hand Indicating Switches

Control Steam Generator Pressure as required from the Hand/Auto stations to maintain RCS Tave constant or slightly lowering

- Establish one Condensate Pump operation I/F Role play as an Equipment Operator to investigate the loss of Role both AFW Pumps. Report AFPT 1 tripped on overspeed due Play to no Governor control and AFPT 2 governor valve is stuck closed NUREG-1021, Revision 9 Supplement 1 Page 12 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: 2011 NRC Scenario No.: 3 Event No.: 6,7,8 Page 13 of 20 Event

Description:

Continued Time Position Applicants Actions or Behavior Check for NNI Power available

- With NNI X DC power lost, then perform the following:

Operate PZR Heaters and Spray manually to maintain RCS pressure ATC

If uncompensated PZR Level is less than 60 inches then turn off all PZR Heaters

Alternate Injection Line may be used to maintain PZR Level per Specific Rule 3 BOP Check for ICS Power available BOP Check for Instrument Air available ATC Check SFAS has not actuated Verify proper SFRCS actuation for the trip parameters present BOP using Table 1 Check for:

Adequate subcooling margin CREW

Proper primary to secondary heat transfer

SG Tube Rupture Termination criteria

MDFP supplying AFW to both SGs

Pressurizer level at proper level using the Alternate Injection Line EAL Determine if any EALs were applicable during the scenario: see SRO Action attached KEY. SU 1.1 applies NUREG-1021, Revision 9 Supplement 1 Page 13 of 20 FENOC Facsimile Rev. 1

CUE SHEET NOTE: Role Play as Maintenance/Work Week Manager/Operations as needed.

Event 1 - Transfer Gland Steam from Main Steam to Aux Steam Role play as an Equipment Operator to open AS1934, Aux Steam Supply to 5# Condensate Tank 1-1 Control Valve, for 1 minute and then close AS 1934 Event 2 and 3 - Loss of oil in AFPT 1 governor Role play as an Equipment Operator to call the Control Room to report the oil sight glass on the AFPT 1 governor is broken and the oil has leaked out of the governor Event 4 - Dropped Control Rod Role play as Operations Management for Reactivity Management notifications Role play as I&C for investigating the dropped rod Role play as the System Dispatcher to acknowledge the power reduction Event 5 - Loss of NNI-X DC Role play as I&C for investigating loss of NNI-X DC Event 6, 7 and 8 - Loss of offsite power, Reactor trip, failure of EDG 1 to automatically start and loss of both AFW Pumps Role play as an Equipment Operator to investigate the loss of both AFW Pumps. Report AFPT 1 tripped on overspeed due to no Governor control and AFPT 2 governor valve is stuck closed NUREG-1021, Revision 9 Supplement 1 Page 14 of 20 FENOC Facsimile Rev. 1

2011 NRC Exam, Scenario 3 Simulator Setup Instructions

1. Verify the following:

a. Previous data on Yokogawa recorders is cleared

c. Applicable procedures are wiped cleaned

d. Used Alarm Typer paper is removed

e. Computer alarms are cleared/acknowledged

2. Initialize at 50 to 60% power

3. Equipment Status:

a. Hang License Requirement Sheet on the status board for LPI Train 1 and RCP 1-1

b. Tag out LPI Pump 1

c. Turn on the LPI blue status

d. Hang Protected Train 2 signs

4. Set Up Batch File

a. Initial Setup

- Rackout the breaker for LPI Pump 1 IRFBDP1A to Ractout IRF BDPIE to TRUE

- EDG 1 fails to automatically start IMF G529B to DEFEAT

- Stop RCP 1-1

b. Triggers

- AFPT 2 Gov Valve closes when AFPT 2 steam admission valve opens TRGSET 8 SXA5889B>0.2 NUREG-1021, Revision 9 Supplement 1 Page 15 of 20 FENOC Facsimile Rev. 1

c. Events Event 1 - Transfer GS from Main Steam to Auxiliary Steam Event 2 - Loss of oil from AFPT 1 governor IMF SFEJA (2)

Event 3 - Rod 5-8 drops, location M-5 IMF LI53B (3)

Event 4 - Blown fuse causes MU32 to fail to control in automatic IMF H170 to 4.00000 (4)

Event 5 - Loss of NNI X DC IMF NP19B Event 6 - Loss of offsite power IMF PLZZ (6)

Event 7 - EDG 1 fails to automatically start Part of the setup Event 8 - AFPT 2 Gov Valve closes when the AFP starts IMF SFERE after 300(8) TRUE NUREG-1021, Revision 9 Supplement 1 Page 16 of 20 FENOC Facsimile Rev. 1

Facility: 2011 NRC Davis-Besse Task No: 334-01-05-0300 Task

Title:

Scenario 3 EAL Classification and Initial Notification Form K/A

Reference:

2.4.41 Job Performance Measure No: NEW Examinee:

NRC Examiner: Date:

Method of testing:

Simulated Performance ___ Actual Performance _X_

Classroom ___ Simulator __ X Plant ___

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

The plant conditions are specified in the Initial Conditions and Initiating Cues.

Task Standard:

Classify an event and complete the Initial Notification Form Required Materials:

RA-EP-01500, Emergency Notification General

References:

Initiating Cue:

The plant conditions are specified in the Initial Conditions and Initiating Cues.

Time Critical Task: No Validation Time: 30 minutes NUREG-1021, Revision 9 Supplement 1 Page 17 of 20 FENOC Facsimile Rev. 1

2011 NRC Exam Scenario 3 EAL DETERMINATION EXAMINER COPY INITIAL CONDITIONS The following events occurred during the scenario:

Transfer Gland Steam from Main Steam to Auxiliary Steam

Loss if Governor oil to AFPT 1

MU32 failed to operate in AUTO

Control Rod 5-8 drops into core

Loss of NNI-DC

Loss of Offsite Power

Emergency Diesel Generator 1 fails to auto start

AFWP 2 Governor valve closes Wind Direction is 90° Wind Speed is 2 mph INITIATION CUE Determine the highest EALs classification, if any, apply and complete the Initial Notification Form if applicable.

(Hand Candidate a copy of DB-EP-01500, Emergency Classification)

See Initial Notification Form (INF) for KEY Critical items on INF form

1. Line 2: This is a DRILL

2. Line 3: a. EAL number (SU 1), Note: Date and Time not critical

3. Line 4: General description of event, example provided

4. *Line 5: c. Release in progress

5. Line 6: c. No PAR recommended

Release in progress because the AFPT were running and AVV are used during event.

NUREG-1021, Revision 9 Supplement 1 Page 18 of 20 FENOC Facsimile Rev. 1

2011 NRC Exam Scenario 3 CANDIDATE COPY INITIAL CONDITIONS The following events occurred during the scenario:

Transfer Gland Steam from Main Steam to Auxiliary Steam

Loss if Governor oil to AFPT 1

MU32 failed to operate in AUTO

Control Rod 5-8 drops into core

Loss of NNI-DC

Loss of Offsite Power

Emergency Diesel Generator 1 fails to auto start

AFWP 2 Governor valve closes Wind Direction is 90° Wind Speed is 2 mph INITIATION CUE Determine the highest EALs classification, if any, apply and complete the Initial Notification Form if applicable.

NUREG-1021, Revision 9 Supplement 1 Page 19 of 20 FENOC Facsimile Rev. 1

Verification of Completion Job Performance Measure No. Scenario 3 EAL JPM Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:_____________________________________________________________

Response:_____________________________________________________________

Result: Satisfactory/Unsatisfactory Examiners signature and date: _______________________________________

NUREG-1021, Revision 9 Supplement 1 Page 20 of 20 FENOC Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Facility: Davis-Besse Scenario No.: 4 Op Test No.: NRC 2011 Examiners: Operators: SRO ATC BOP Initial Conditions:

80% power, MOL

AFPT #1 tagged OOS Turnover: Hold at 80% power while the Reactor Engineer reviews the calorimetric calculation completed at the end of the last shift.

Event Malf. Event Event No. No. Type* Description 1 TS-SRO AO reports oil leak on Train 1 Containment Spray Pump.

st 2 C-All RCP 1 Stage Seal failure on RCP 1-1.

3 R-ATC Power reduction prior to stopping RCP 1-1.

N-SRO TS-SRO 4 I-ATC, RCS Hot Leg RTD slowly drifts HI.

BOP, SRO 5 M-ALL RCP 1-2 Breaker trips. Reactor Trip required.

AUTO and MANUAL Reactor trip fails.

6 M-ALL PZR Safety Valve fails OPEN, initiating SFAS.

7 C-ATC, HPIP 1 trips.

SRO HPIP 2 fails to automatically start.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Page 1 of 22 FENOC Facsimile Rev. 1

Scenario Event Description 2011 NRC Scenario 4 DAVIS-BESSE 2011 NRC SCENARIO 4 The crew will take the watch with power holding at 80% power while the Reactor Engineer reviews the calorimetric calculation completed at the end of the last shift.

On cue from the Lead Evaluator, an AO will call the control room to report an oil leak on Containment Spray (CS) Pump #1. The SRO should request assistance from maintenance and/or enter the applicable TS. If necessary, a maintenance supervisor will report that the pump must be tagged OOS in order to make the repairs.

After the SRO has declared the TS for the CS Pump, the Lead Evaluator will cue the RCP 1-1 seal failure. The crew should respond to alarm 6-3-A in accordance with DB-OP-02006, REACTOR COOLANT PUMP ALARM PANEL 6 ANNUNCIATORS, and then enter DB-OP-02515, REACTOR COOLANT PUMP AND MOTOR ABNORMAL OPERATION.

DB-OP-02515 will require the crew to reduce power to 72% in accordance with DB-OP-02504, RAPID SHUTDOWN, and stop the affected RCP. The SRO should enter the proper TS after the RCP is stopped.

On cue from the Lead Evaluator, the RCS Thot selected on HIS3A and for Tave or UNIT will begin to drift HI. The crew should respond to alarm 4-2-B or indications in accordance with DB-OP-02004, REACTOR COOLANT ALARM PANEL 4 ANNUNCIATORS. The affected controls should be shifted to an alternate channel and the channel should be removed from service. The channel does not have to be removed from service to proceed with the scenario.

The Lead Evaluator can cue RCP 1-2 breaker trip when evaluation on the Thot failure is complete. The crew should recognize that an AUTO reactor trip should have occurred and attempt to initiate a MANUAL reactor trip. This will fail and the ATC should initiate a reactor trip by momentarily de-energizing Busses E2 and F2. Coincident with the reactor trip a PZR Safety Valve will fail sufficiently open to cause an SFAS actuation. HPIP #1 will trip and HPIP #2 will fail to automatically start. The crew should enter DB-OP-02000 - RPS, SFAS, SFRCS TRIP, OR S/G TUBE RUPTURE, and, among other actions, perform the following high level activities:

verify the reactor is tripped, start HPIP #2, complete the actions for lack of adequate subcooling margin.

The Lead Evaluator can terminate the scenario when all high level activities have been completed and the evaluators agree the crew can be properly evaluated.

NUREG-1021, Revision 9 Supplement 1 Page 2 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 1 Page 3 of 22 Event

Description:

AO Reports Oil Leak On Train 1 Containment Spray Pump Time Position Applicants Actions or Behavior I/F Role When directed by Lead Evaluator, Call the control room to Play report an oil leak on Containment Spray Pump 1.

Role play as Maintenance/Work Week Manager/Operations as necessary.

SRO Refers to Tech Spec LCO 3.6.6 ATC/BOP Manually energize CS pump 1 blue light.

SRO May Call Work Week Manager.

SRO May refer to Risk Matrix (Yellow).

At Lead Evaluators discretion, proceed to Event 2 NUREG-1021, Revision 9 Supplement 1 Page 3 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 2&3 Page 4 of 22 st Event

Description:

RCP 1 Stage Seal Failure on RCP 1-1; Power Reduction Prior to Stopping RCP 1-1 Time Position Applicants Actions or Behavior Indications Available:

(6-3-A) 1-1 SEAL RET FLOW HI.

High controlled bleedoff flow of RCP 1-1 seal water.

Respond to Annunciator Alarm (6-3-A) 1-1 SEAL RET FLOW Crew HI.

ATC Observe High controlled bleedoff flow of RCP 1-1.

Refer to DB-OP-02515, Reactor Coolant Pump and Motor SRO Abnormal Operation.

Determine IF any of the following RCP conditions exist:

Seal Return Temp 200°F CREW Total seal leakage for the affected RCP 2.0 gpm.

Seal stage pressure drop greater than 1440 PSIG CREW Determines total seal leakage is > 2.0 gpm.

IF a Reactor Shutdown to take the Unit off line is NOT desired, CREW THEN, perform those steps necessary to reduce reactor power to the desired power level, AND REFER TO Attachment 1, Reduce reactor power to 72 percent using DB-OP-02504, Rapid Shutdown At the Load Control Center Panel:

Set the rate of change and Enter ATC

Select the reactor power to the target load and Enter

IF the APSRs are available, THEN attempt to maintain Axial Power Imbalance between 0 and negative 20 percent.

NUREG-1021, Revision 9 Supplement 1 Page 4 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 2&3 Page 5 of 22 st Event

Description:

RCP 1 Stage Seal Failure on RCP 1-1; Power Reduction Prior to Stopping RCP 1-1 Time Position Applicants Actions or Behavior ATC/BOP Stop the affected RCP.

BOP Verify proper Feedwater flow ratios of 2.4 to 1.

ATC/BOP Verify Tave control transferred to the RC loop with two RCPs.

CREW Verify RCS flow is greater than the flow required by T.S. 3.4.1.

Within four hours verify the Ø/Ø/Flow AND High Flux Trips SRO setpoints have been reduced in accordance with TS 3.4.4.

Notify the Steam Control Center (SCC). Load dispatcher of the SRO unit load reduction.

Request Chemistry to perform the following:

SRO

Monitor Condensate Polisher operation

Sample the RCS for an isotopic analysis of Iodine.

Boric Acid/water may be added to RCS to adjust rod position.

To Batch, at the Batch Controller:

NOTE: (# is the keypad number

1. Press BATCH SET

2. Press number keys for size of batch ATC 3. Press ENTER

4. Press DISPLAY (lower) to exist BATCH SET

5. Press BATCH (4) to display batch size

6. Press DISPLAY (lower)

7. Press TOTAL (7)

8. Press TOTAL RESET(6)

NUREG-1021, Revision 9 Supplement 1 Page 5 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 2&3 Page 6 of 22 st Event

Description:

RCP 1 Stage Seal Failure on RCP 1-1; Power Reduction Prior to Stopping RCP 1-1 Time Position Applicants Actions or Behavior

9. Press DISPLAY (upper)

10. Press RATE (*8)

11. Press RUN

12. Open MU40 using HISMU40

13. Start a Boric Acid Pump using HIS MU50A/B

14. Adjust MU flow, if necessary, with MU23 using HC MU23

15. Open WC 3526 using HIS 3526

16. When batch is complete, verify MU40 is closed

17. Close WC 3526 using HIS 3526 At Lead Evaluators discretion, proceed to Event 4 NUREG-1021, Revision 9 Supplement 1 Page 6 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 4 Page 7 of 22 Event

Description:

RCS Hot Leg RTD Slowly Drifts HI Time Position Applicants Actions or Behavior Booth Operator Instructions:

When directed, insert command for Event 4 Indications Available:

4-2-B, HOT LEG TEMP HIGH 14-4-D, ICS FW LIMITED BY RX POWER 14-4-E, ICS INPUT MISMATCH 14-6-D, ICS IN TRACK 4-2-E, PZR LVL LO Loop 2 Thot indication rising ATC Check the alarm by observing Loop 1 and Loop 2 Hot Leg Tis.

ATC Verify the ICS is reducing Rx power to lower Tave to 582°F Compare Hot Leg Temperature Indicators TI RC3A1 and ATC T1 RC3B1 on RC Panel C5718.

IF the selected Hot Leg Temperature Transmitter failed, THEN ATC verify SASS has transferred to unfaulted instrument.

Respond to Annunciator Alarm (4-2-E) PZR LVL LO IAW with Crew DB-OP-02004, Reactor Coolant Alarm Panel 4 Annunciators ATC Observes Low Pressurizer level as indicated on LRS RC14 IF Pressurizer Level is due to a Tave transient, THEN perform the following:

Reduce MU-32 Setpoint to ~ 180 ATC

WHEN Tave is restored to ~ 582°F, AND Pressurizer Level is stable, THEN restore MU-32 to 220 inches as directed by the CTRM SRO.

NUREG-1021, Revision 9 Supplement 1 Page 7 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 4 Page 8 of 22 Event

Description:

RCS Hot Leg RTD Slowly Drifts HI Time Position Applicants Actions or Behavior CREW Determine which instrument pair has caused the alarm. (Thot)

Refer to DB-OP-06404 NNI System and Operating procedure, SRO and/or DB-OP-02526, Primary to Secondary Heat Transfer Upset ATC Place Rod Control Panel in Manual and adjust power.

BOP Place BOTH FEEDWATER DEMAND H/A Stations in HAND.

Maintain Feedwater flow matched with Plant power using SP6A BOP and SP7A AND LOOP 1 FEEDWATER DEMAND H\A Station.

ATC/BOP Check for ICS module, component, or instrument failures.

At Lead Evaluators discretion, proceed to Event 5 NUREG-1021, Revision 9 Supplement 1 Page 8 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 5, 6, & 7 Page 9 of 22 Event

Description:

RCP 1-2 Breaker Trips; Reactor Trip Required; AUTO and MANUAL Reactor Trip Fails; PZR Safety Valve Fails OPEN, Initiating SFAS; HPIP 1 Trips; HPIP 2 Fails to Automatically Start Time Position Applicants Actions or Behavior Booth Operator Instructions:

When directed, insert command for Event 5 Indications Available:

5-3-H, RPS POWER - PUMPS TRIPPED 5-1-G, H, I, J, RPS CH 1, 2, 3, 4 TRIPPED ZL4265A and ZL 4265A red lights lit - Safety Valve Open indication ATC Manually Trip the Reactor.

Reactor Trip Pushbutton has been depressed; AND Power is decreasing on the Intermediate Range Nuclear Instrumentation (NO).

IF the reactor is NOT shutdown, THEN perform the following actions until the reactor is shutdown.

Manually deenergize the CRDs in the order listed below:

CRITICAL 1. Momentarily deenergize 480-Volt Unit Substations TASK ATC E2 AND F2 simultaneously.

Maintain balanced primary to secondary heat transfer:

1. IF MFW is less than Reactor power, THEN manually control MFW flow to match Reactor power.

NUREG-1021, Revision 9 Supplement 1 Page 9 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 5, 6, & 7 Page 10 of 22 Event

Description:

RCP 1-2 Breaker Trips; Reactor Trip Required; AUTO and MANUAL Reactor Trip Fails; PZR Safety Valve Fails OPEN, Initiating SFAS; HPIP 1 Trips; HPIP 2 Fails to Automatically Start Time Position Applicants Actions or Behavior ATC Manually trip the Turbine.

Turbine Trip Pushbutton has been depressed.

AND Turbine Stop Valves 1, 2, 3 AND 4 are closed.

OR Turbine Control Valves 1, 2, 3, AND 4 are closed.

SRO CHECK FOR SPECIFIC RULE OR SYMPTOM DIRECTION Implement any necessary Specific Rules.

ACTIONS FOR LOSS OF SUBCOOLING MARGIN Applies Specific Rule 2 MU\HPI\LPI FLOW INITIATION, THROTTLING, AND TERMINATION Applies Specific Rule 3 SRO Implement any necessary Symptom Mitigation Sections LACK OF ADEQUATE SUBCOOLING MARGIN applies NUREG-1021, Revision 9 Supplement 1 Page 10 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 5, 6, & 7 Page 11 of 22 Event

Description:

RCP 1-2 Breaker Trips; Reactor Trip Required; AUTO and MANUAL Reactor Trip Fails; PZR Safety Valve Fails OPEN, Initiating SFAS; HPIP 1 Trips; HPIP 2 Fails to Automatically Start Time Position Applicants Actions or Behavior Directs tripping remaining RCPs IAW specific Rule 2 when SRO subcooling is lost.

CRITICAL TASK ATC Trips all remaining RCPs MU\HPI Initiation ATC Start the standby CCW Pump.

CRITICAL Start BOTH HPI Pumps.

TASK ATC

HPI Pump 1 (Tripped)

HPI Pump 2 Open HPI Injection Valves.

HP 2A ATC

HP 2B

HP 2C

HP 2D IF only one HPI train is available, THEN REFER TO ATC/SRO Attachment 11, HPI Flow Balancing.

Stop Makeup flow through HPI Train 2 by closing MU 6422, MU ATC CTMT ISOLATION.

Verify HPI Train 2 Injection Valves are fully open.

HP2A, HIGH PRESSURE INJECTION LINE 2-1 ATC ISOLATION

HP2B, HIGH PRESSURE INJECTION LINE 2-2 ISOLATION NUREG-1021, Revision 9 Supplement 1 Page 11 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 5, 6, & 7 Page 12 of 22 Event

Description:

RCP 1-2 Breaker Trips; Reactor Trip Required; AUTO and MANUAL Reactor Trip Fails; PZR Safety Valve Fails OPEN, Initiating SFAS; HPIP 1 Trips; HPIP 2 Fails to Automatically Start Time Position Applicants Actions or Behavior Determine which injection line has the lower flow and REFER TO Figure 3, HPI Balancing.

ATC

FYI HP3A

FYI HP3B IF only the lower flow is NOT in the acceptable region, THEN ATC throttle the higher flow line until:

The lower flow line is in the acceptable region OR

The high flow line reaches the lower limit of the acceptable region IF MU 6422 was closed in Step 2.a above, THEN open MU ATC 6422, MU CTMT ISOLATION.

ATC Monitor RCS Pressure.

Routes to DB-OP-02000, section for LACK OF ADEQUATE SRO SUBCOOLING MARGIN ATC Trip all RCPs. (Already performed.)

NUREG-1021, Revision 9 Supplement 1 Page 12 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 5, 6, & 7 Page 13 of 22 Event

Description:

RCP 1-2 Breaker Trips; Reactor Trip Required; AUTO and MANUAL Reactor Trip Fails; PZR Safety Valve Fails OPEN, Initiating SFAS; HPIP 1 Trips; HPIP 2 Fails to Automatically Start Time Position Applicants Actions or Behavior Verify BOTH HPI Trains are in service as follows:

Verify BOTH CCW Trains are in service to supply essential cooling:

ATC

CCW Train 1

CCW Train 2 Verify BOTH HPI Pumps are running.

ATC

HPI Pump 1 - tripped

HPI Pump 2 Verify HPI Injection Valves fully open.

HP 2A ATC

HP2B

HP2C

HP2D Lineup Makeup System as follows:

Lock MU Pump Suctions in the BWST position.

ATC

MU 3971

MU6405 ATC Start the second MU Pump.

Start BOTH LPI Pumps ATC

LPI Pump 1

LPI Pump 2 NUREG-1021, Revision 9 Supplement 1 Page 13 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 5, 6, & 7 Page 14 of 22 Event

Description:

RCP 1-2 Breaker Trips; Reactor Trip Required; AUTO and MANUAL Reactor Trip Fails; PZR Safety Valve Fails OPEN, Initiating SFAS; HPIP 1 Trips; HPIP 2 Fails to Automatically Start Time Position Applicants Actions or Behavior ATC Open MU 6420, MU 32 BYPASS.

ATC Verify MU 6422, MU CTMT ISOLATION is open.

IF LPI Flow into the RCS does not exist, THEN perform the following:

a. Open BOTH piggyback valves ATC

DH63

DH64

b. IF two MU Pumps are running, THEN perform the following:

ATC

Open MU 6421, CTMT ISOLATION FOR ALTERNATE MU INJECTION LINE

Open MU 6419, ALTERNATE MU INJECTION LINE.

CREW Verify proper SFAS response.

Verify proper SFRCS actuation for the trip parameters present BOP using Table 1.

BOP Verify proper SG level control by AFW using Specific Rule 4.

Isolate Possible RCS Leaks as follows:

IF MU/HPI PORV Cooling is NOT in progress, THEN perform the following:

ATC

Verify RC 2A, PORV, control switch in AUTO.

Close RC 11, PORV BLOCK Valve.

NUREG-1021, Revision 9 Supplement 1 Page 14 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 5, 6, & 7 Page 15 of 22 Event

Description:

RCP 1-2 Breaker Trips; Reactor Trip Required; AUTO and MANUAL Reactor Trip Fails; PZR Safety Valve Fails OPEN, Initiating SFAS; HPIP 1 Trips; HPIP 2 Fails to Automatically Start Time Position Applicants Actions or Behavior ATC Verify MU 2B, LETDOWN ISO is closed.

ATC Verify RC 2, PZR SPRAY Valve is closed.

ATC Close RC 10, PZR SPRAY BLOCK Valve.

Close Pressurizer Sample Isolations ATC

RC 239A

RC 239B Verify Loop 1 High Point Vents are closed:

ATC

RC 4608A

RC 4608B Verify Loop 2 High Point Vents are closed.

ATC

RC 4610A

RC 4610B Verify CFT Isolation Valves are open.

ATC

CF1A

CF1B SRO If adequate subcooling margin exists, THEN GO TO Step 5.18.

ADEQUATE SUBCOOLING MARGIN (20°F) HAS BEEN ESTABLISHED NUREG-1021, Revision 9 Supplement 1 Page 15 of 22 FENOC Facsimile Rev. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 2011 NRC Scenario # 4 Event # 5, 6, & 7 Page 16 of 22 Event

Description:

RCP 1-2 Breaker Trips; Reactor Trip Required; AUTO and MANUAL Reactor Trip Fails; PZR Safety Valve Fails OPEN, Initiating SFAS; HPIP 1 Trips; HPIP 2 Fails to Automatically Start Time Position Applicants Actions or Behavior Throttle MU and HPI as necessary to maintain adequate CREW subcooling margin. REFER TO Specific Rule 5, PTS Requirements.

Scenario may be terminated when crew reaches Step 5.18.

EAL SRO Determine if any EALs were applicable during the Action scenario: see attached KEY. FA1 or SA3 FA1 due to Pzr Safety Stuck Open SA3 due to ATWS NUREG-1021, Revision 9 Supplement 1 Page 16 of 22 FENOC Facsimile Rev. 1

SIMULATOR INSTRUCTIONS

1. Verify the following

a. Previous data o Yokogawa recorders is cleared

b. Applicable procedures are wiped clean

c. Used Alarm Typer paper is removed

d. Computer alarms are cleared/acknowledged

2. Initialize at 80% power

3. Equipment Status

a. Hand License Requirement Sheet on the Status Board

b. Tag out AFPT 1 speed changer

c. Turn on the AFW blue light

d. Hang Protected Train 2 sign

4. Set Up Batch Files

a. Initial Setup (1) Remove AFPT 1 from service (a) Trip the Trip Throttle Valve: IRF SFE1A to CLOSE (b) Close MS106A IMF SFEAB (c) Open MS106A breaker, BE1271 IRF SFEAA to OPEN, delete in 10 (d) Close MS106 IMF SFE8B (e) Open MS106 breaker IRF SFE8A to OPEN, delete in 10 (2) Fail the Reactor to automatically Trip:

(a) RPS trip override IMF L4 (b) ARTS trip override IMF L8 (c) DSS Ch 1 Opto-Isol failure IMF L5D1 (d) DSS Ch 2 Opto-Isol failure IMF L5D2 (3) Fails HPI 2 to AUTO START IMF BFP2E

b. Events (1) CSP 1 breaker, BE111RACK OUT IRF BDP3A to TRUE (2) RCP 1-1 first stage seal failure IMF HN09 in 300 (3) Power Reduction (4) RCS Loop 2 Th RTD slowly drifts high IMFL1T6H from 0.81 in 120 (5) RCP 1-2 breaker fails open IMF H102J (6) RO must trip E2 and F2 (7) Pzr Safety fails open IMF HV40C (8) HPIP 1 trips IMF BFP1C NUREG-1021, Revision 9 Supplement 1 Page 17 of 22 FENOC Facsimile Rev. 1

SIMULATOR INSTRUCTIONS

5. Instructor Station Cues NOTE: Role Play as Maintenance/Work Week Managers/Operations as applicable

a. Event 1 - CTMT Spray Pump 1 Oil Leak (1) Role Play as a Plant Operator to report the oil sight glass for the outboard bearing on CSP 1 is broken and oil from the bearing has leaked onto the floor.

(2) Role Play to remove close power fuses of racked out breaker for CSP 1

c. Event 2 - RCP 1-1 Seal Failure and power reduction to stop RCP -1 (1) Role Play as the System Dispatcher, if contacted (2) Role Play as Equipment Operator, if contacted

d. Event 3 - Selected Thot RTD transmitter (TT RC3A1) fails high

e. Event 4 - RCP 1-2 breaker trip

f. Event 5 - ATWS

g. Event 6 - Pressurizer Safety fails open

h. Event 7 - HPI Pump 1 trips, HPI Pump 2 fails to auto start NUREG-1021, Revision 9 Supplement 1 Page 18 of 22 FENOC Facsimile Rev. 1

Facility: Davis-Besse Task No: 334-01-05-0300 Task

Title:

Scenario 4 EAL Classification and Initial Notification Form K/A

Reference:

2.4.41 Job Performance Measure No: NEW Examinee:

NRC Examiner: Date:

Method of testing:

Simulated Performance ___ Actual Performance _X_

Classroom ___ Simulator _X_ Plant ___

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

The plant conditions are specified in the Initial Conditions and Initiating Cues.

Task Standard:

Classify an event and complete the Initial Notification Form Required Materials:

RA-EP-01500, Emergency Notification General

References:

Initiating Cue:

The plant conditions are specified in the Initial Conditions and Initiating Cues.

Time Critical Task: No Validation Time: 30 minutes NUREG-1021, Revision 9 Supplement 1 Page 19 of 22 FENOC Facsimile Rev. 1

EAL DETERMINATION EXAMINER COPY INITIAL CONDITIONS

The following events occurred during the scenario:

CTMT Spray Pump 1 becomes inoperable

RCP 1-1 seal failure with >2 gpm seal return

RCS Hot Leg RTD fails high

ATWS

Pzr Safety Valve fails open, initiating SFAS

High Pressure Injection Pump 1 trips

High Pressure Injection Pump 2 fails to automatic start Wind Direction is 90° Wind Speed is 2 mph INITIATION CUE Determine the highest EALs classification, if any, apply and complete the Initial Notification Form if applicable.

(Hand Candidate a copy of DB-EP-01500, Emergency Classification)

See Initial Notification Form (INF) for KEY Critical items on INF form

1. Line 2: This is a DRILL

2. Line 3: a. EAL number (FA1 OR SA3), Note: Date and Time not critical

3. Line 4: General description of event, exampleS provided

4. *Line 5: a. Airborne release in progress

5. Line 6: c. No PAR recommended

Release in progress because the AFPT were running during event and AVV are being used to cooldown RCS.

NUREG-1021, Revision 9 Supplement 1 Page 20 of 22 FENOC Facsimile Rev. 1

CANDIDATE COPY INITIAL CONDITIONS The following events occurred during the scenario:

The following events occurred during the scenario:

CTMT Spray Pump 1 becomes inoperable

RCP 1-1 seal failure with >2 gpm seal return

RCS Hot Leg RTD fails high

ATWS

Pzr Safety Valve fails open, initiating SFAS

High Pressure Injection Pump 1 trips

High Pressure Injection Pump 2 fails to automatic start Wind Direction is 90° Wind Speed is 2 mph INITIATION CUE Determine the highest EALs classification, if any, apply and complete the Initial Notification Form if applicable.

NUREG-1021, Revision 9 Supplement 1 Page 21 of 22 FENOC Facsimile Rev. 1

Verification of Completion Job Performance Measure No. Scenario 4 EAL JPM Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:_____________________________________________________________

Response:_____________________________________________________________

Result: Satisfactory/Unsatisfactory Examiners signature and date: _______________________________________

NUREG-1021, Revision 9 Supplement 1 Page 22 of 22 FENOC Facsimile Rev. 1

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