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Dua 2017 Ile - Proposed Exam Scenarios 1-2-3-Alt
	ML17214A036
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Site:	Duane Arnold
Issue date:	06/14/2017
From:	Bielby M; Operations Branch III
To:	; NextEra Energy Duane Arnold
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NEXTETA EYW- SIMULATOR EXERCISE GUIDE SEG REf SITE: DAEC Revision #: 0 LMS ID: PDA OPS ESG I LMS Rev. Date: N/A SEG TITLE: NRC lNlTlAL LICENSE EXAM, SCENARIO #l SEG TYPE: ! Training X Evaluation PRocRAM: !LOCT XLOIT !Other:

DURATION: -90 minutes Developed by:

lnstructor/Developer Date Reviewed by:

lnstructor (l nstructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date Filename: l_esg TR-AA-230-1 003-F06 Revision 0 Page 1 of 24

NEXTETA-EYrc- NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev.0 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective This Evaluation Scenario Guide evaluates the Operators' ability to:

"Given the malfunctions presented in this ESG, the students will protect the public, protect plant personnel, and protect plant equipment, in accordance with plant procedures."

Enabling Objectives: Evaluation Guide, no tasks are trained Prerequisites: None Training Resources: A. Simulator B. Evaluation team C. Operations Management Representative D, Simulator Driver E. Phone Talker F. Exam Proctor for custody of the crew between scenarios G. Simulator Video recording equipment References A, ARP 1C054 Rev. 82 B. ARP 1C088 Rev.113 C. AOP 410 Rev. 29 D. ARP 1C084 Rev, 90 E. ARP 1C23' Rev. 19 F. ARP 1C238 Rev.23 G. Ol 734 Rev. 59 H. AOP 644, Rev. 17 L AOP 255.1, Rev.46 J. AOP 255.2, Rev, 43 K. EOP2 Rev. 18 L. EOP 1 Rev.20 M. ED Rev. 11 N. OP-AA-102-1003 Rev. 18 O. lPOl 3 Rev. 152 P. Ol 856.1, Rev.48 Q. Ol 304.1, Rev.84 R. O1304.2, Rev. 96 S. Ol304.2QRC 1, Rev.0 Protected Gontent: None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance Operating None Experience Risk Significant Operator Actions Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page2 of 24

NEXIETA-EYrc- NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev.0 SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title Reactor Operator 14.16 Remove the Startuo Transformer (1X3) from service 15.10 Transfer Essential Bus from Startup to Standbv Transformer 45.21 Reset A/B or Startup Feed Regulating Valve Lockup 93.22 Perform the lmmediate Operator Responses to a Reactor Scram 94.1 5 Respond to Loss of River Water Supply 95.21 Perform Defeat 11 95.25 Perform Defeat 15 95.44 Perform actions of RC/L of EOP 1 95.45 Perform initial EOP 1 actions (RC) 95.46 Perform actions of RC/P of EOP 1 95.63 Perform DW leq of EOP 2 95.64 Perform PC/P leo of EOP 2 95.74 Perform ALC leq of EOP 1 when lniection Systems are lined up and available 95.76 Perform ALC with 1 Core Sorav and 1 other ECCS pump available 95.80 Perform an Emeroencv Depressurization Using SRVs Sen ior Reactor Operator 1.02 Determine operabilitv for TS required components 4.21 Direct Crew Actions to Perform the lmmediate Operator Responses to a Reactor Scram 5.04 Direct Crew Responses to Loss of 143 5.08 Direct Crew Response to Loss of 4160V Nonessential Power Condition 5.15 Direct Crew Response to Loss of River Water Supply 6.21 Direct Crew Response to Perform EOP Defeat 11 6.25 Direct Crew Response for performance of Defeat 15 6.44 Direct Crew Response for performance of the RC/L leg of EOP 1 6.45 Direct Crew Response for performance of initial EOP 1 actions (RC) 6.46 Direct Crew Response for performance of RC/P leg of EOP 1 6.63 Direct Crew Response for performance of the DW/T les of EOP 2 6.64 Direct Crew Response for performance of the PC/P leg of EOP 2 6.74 Direct Crew Response to Perform ALC leg of EOP 1 when lnjection Systems are lined up 6.76 Direct Crew Response to Perform ALC with 1 core spray and 1 other ECCS pump available 6.78 Direct Crew Response for performance of Emergency Depressurization UPDATE LOG: lndicate in the following table any minor changes or major revisions (as defined in TR-M-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE Rev. 0 lnitial development lor 2017 I nitial development for N/A See Cover NRC LOIT Examination 2017 NRC LOIT See Cover Examination Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 3 of 24

NEXTETA'

,YS*ø NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev.0 SEG RIET OVERVIEW / SEQUENCE OF EVENTS Event # Description When the crew assumes the shift reactor power is approximately 80% following 'A'feed pump vibration analysis. On the last shift, repairs were made to the 'B' FRV due to internal fault that caused the 'B' FRV to lock. .Once the crew takes the shift they will be required to reset the 'B' FRV lockup using ARP 1C05A (F-1) section 4. Following 'A' feed pump vibration analysis, RE will request the crew to raise Reactor Power by 5o/o and hold prior to continuing raising power to 100%.

1 Once the crew has reset the 'B' FRV lockup and raised power to approximately 85%, the crew will respond to 'B' FRV failing downscale. The crew will enter AOP 644 and AOP 255.2 due to the feedwater transient and subsequent power fluctuation.

2 The crew will then respond to control rod 02-19 drifting in. The crew will be able to stop the rod from drifting using controls on 1C05. AOP 255.1 will be entered to address the drifting rod. The crew will enter LCO 3.1.3 Gondition C.

3 Startup Transformer Trouble annunciator will be received and the crew will respond via ARP 1C084 (A-7), "Startup XFMR 1X3 Trouble". ln-plant personnelwill be dispatched to the S/U Transformer to investigate and upon investigation; it will reveal a Sudden lnternal Pressure Trip. The crew will take 1X3 out of service per Ol 304.2. The crew then responds to and determines the appropriate Technical Specification actions (see page 171for Startup Transformer OOS.

4 After the crew removes 1X3 from service, a small steam leak will occur in the Drywell. The crew will implement the actions of and enter EOP 2, Primary Containment Control. The crew will enter AOP 573 to address rising Drywell pressure. The crew will eventually enter EOP 1, Reactor Control and insert a manual scram prior to exceeding 2# in the Drywell.

5 After the scram is inserted and after Drywell pressure exceeds 2#, HPCI will fail to start due to the HPCI aux oil pump tripping. At the same time a lockout of 143 will occur causing the loss of "A" Core Spray pump and "4" and "C" RHR pumps. The leak in the drywell will require the crew to initiate sprays to prevent drywell air temperature from exceeding 280"F. (CRITICAL) 6 After the reactor scram and due to the turbine trip and 1X3 removed from service, Non-Essential Busses will be deenergized causing the crew to control level and pressure via RCIC (HPCI will trip and cannot be restarted) and Steam Line Drains with SRV's.

7 As RPV water level continues to lower, the crew will enter EOP 1 ALC leg. The crew will ensure the appropriate injection subsystems and systems are available and lined up as RPV level lowers. The crew will enter ED after RPV level reaches 15" and prior to -25" in the RPV. (CRITICAL) The crew will recognize that the LPCI inject valve MO-1905 will not automatically open with a 450 psig signal. Operator action at 1C03 will open MO-1905 and RHR will be used to restore and maintain RPV level in the directed control band.

(cRrTrcAL)

I When RPV level is being restored 170-211" the scenario will be terminated Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 4 of 24

NEXTETA-

l

=YSrg RIET NRC lNlTlAL LICENSE EXAM, SCENARIO Rev.0 SEG SIMULATOR SET UP INSTRUCTIONS 1 . Set NRC Exam Security for the Simulator per QF-1071-08

2. Perform simulator set up per TDAP 1839 Attachment 2, Simulator Setup Checklist.

3, Load the saved lC (in folder with this ESG) to a SNAPSHOT

a. Reset to that SNAPSHOT.

b. Place the Simulator in RUN OR

4. Reset to lC 23, place the simulator in RUN and perform the following:

a. Raise power to approximately 80%

b. lnsert fw16b and remove to lockup FRV'B'

c. lnsert event triggers, malfunctions, overrides and remotes per the tables below.

5. RUN Schedule File "ESG_1.sch" and LEAVE lT RUNNING

6. Verify Malfunctions

7. Verify Remotes (Note that environmental remotes will already be timing)

L Verifv Overrides

9. Ensure MOL pull sheet is in the 1C058 hanging file.

10. Ensure EOOS has the same system status lineup as the start of the simulator scenario.

11. Setup control panel including equipment clearance tags, information tags, caution tags or other site-specific devices used as an aid to the operator.

12. After going to run, to insert the 'B' FRV lockup perform the following:

a. lnsert fw16b to lockup FRV'B'

b. Remove fwl6b in order to allow for the crew to reset

13. Provide appropriate shift turnover documentation.

a. Markup ARP 1C054 (F-1) as follows:

(1) Circle/slash the following sections/steps:

a) Section 1.0 - SteP 1.4 b) Section 2.0 - SteP 2,1 c) Section 3.0 - Steps 3.1,3.2 (a), Note, 3.7, 3,8, 3.10 (2) ONLY circle the following sections/steps:

a) Section 3.0 - 3.3 (3) N/A the following sections/steps:

a) Section 3.0 - 3.4, 3.5, 3,6, 3.8, 3.9 Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 5 of 24

NEXTETA-EYrc- NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev.0 SEG EVENT TRIGGER DEFINITIONS Trigger No Trigger Loqic Statement Trigger Word Description 1,7,9,13 Manually Activated Manually Activated 5 ZLOHPHS2256(2) == 1 HS-2256(2) AUX OrL PUMP 1P-218 LlTES (RED) TO ON 11 ZLOCSHS2103(4) == 1 Pump 1P-2114 (Red) to Red 15 ZLOPCHS43l0(2) == 1 CV-4310 open 17 ZDIRDCIlAS3(1) == 1 C11AS3 NOTCH OVRRD EMER IN TO EMER-ROD MALFUNCTIONS:

Time Malf. No. Malfunction Title ET Delav Ramp lnitialValue FinalValue 1C08A (A-07) STARTUP XFMR 1X3 Setup AN1C08A(7) 1 1:00 CRYWOLF ON TROUBLE RECIRC LOOP RUPT _ DESIGN BASES Setup RR15A LOCA AT 1OO% - LOOP A I 30:00 0 0.05 Setup EDOSC 4.16 KV/480V BUS FAULT - BUS 1A3 11 2 SEC INACTIVE ACTIVE LPCI A INJECT VALVE FAILS TO AUTO Setup STRHOl ACTIVE ACTIVE oPEN - MO-2003 LPCI B INJECT VALVE FAILS TO AUTO Setup STRH02 ACTIVE ACTIVE oPEN - MO-1905 Setup HP12 HPClAux Oil Pump 1P218Trip 5 INACTIVE ACTIVE FW REG VALVE CONTROLLER FAILURE Setup FW128 7 7:00 AS IS 0 (AUTO)- FWRV B Setup RD060219 CONTROL ROD DRIVES IN- ROD O2-19 13 INACTIVE ACTIVE REMOTES Time Malf. No. Malfunction Title ET Delav Ramo lnitialValue FinalValue HS-2256(1) AUX OrL PUMP 1P-218 LIrES Setup DO-HP-032 5 INACTIVE ACTIVE (GREEN)

HS-2256(2) AUX OIL PUMP 1P-218 LITES ACTIVE Setup DO-HP-033 5 INACTIVE (RED)

SCHEDULE FILES ESG 1

@Time Event Action Description 15 Modify rr15a to 1.5 in 900 RECIRC LOOP RUPT - DESIGN Setup BASES LOCA AT 100o/o - LOOP A 17 Delete malfunction rd06021 9 CONTROL ROD DRIVES IN- ROD Setup 02-19 Conduct simulator crew pre-scenario brief using TR AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.

lf surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 6 of 24

NEXTETA-EYrc- NRC lNlTlAL LICENSE EXAM, SCENARIO #l Rev.0 SEG SHIFT TURNOVER INFORMATION a Monday, Day Shift a Warm summer day,77 degrees F, Severe Weather possibility later today a Approx o Protected train- "4" a Technical Specification Action statements in effect.

o DAEC is in compliance with all LCO's o Plant PRA/PSA Status including CDF/LERF & color o CDF 2.95 E-6, 1 year to Yellow ICDP o LERF 1.70 E-6, I year to yellow ILERP a Evolutions in progress or planned for upcoming shift:

o Repairs to an internal fault of the 'B' FRV controller are complete. Reset of lockup on 'B' FRV is expected upon conclusion of turnover.

o Power was lowered to perform 'A' feed pump vibration analysis. 'A' feed pump vibration analysis was completed on the last shift. The crew has been instructed to raise power.

o RE's have requested the crew to raise Reactor Power by 5o/o and hold prior to continuing raising power to 100%.

a Comments, problems, operator workarounds, etc.

o One extra NSPEO available in Work Control o Radwaste Operator is NSPEO qualified Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 PageT of24

NflETA"

=Y6 NRC lNlTlAL LCENSE EXAM, SCENARIO #1 Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE After the crew Booth Communicator Crew has assumed Respond as plant personnel and a Reset the 'B' FRV lockup the shift: respond as necessary CRS a Direct crew to reset the 'B' FRV IAW the ARP RO o Resets the'B' FRV using ARP 1C054 (F-1) section 4 as follows:

o When the cause of the lockout has been conected, perform the following:

. Verify that the controller LED displays for the locked Feed Reg Valve are lit.

. Verify the Feedwater Lockout Relay amber light above the associated Lockout Relay is dim.

o Reset a locked Feed Reg Valve as follows:

. At HC-16218 FEED REG VALVE MANUAUAUTO TRANSFER for the locked Feed Reg Valve, perform the following:

. Verify or place in MANUAL ('M' is selected on the A/M pushbutton).

o Select'Y' on the display.

. Adjust the'Y' bias setting to zero.

. Obtain the cunent Feed Reg Valve position using Zl-16211or the locked Feed Reg Valve.

. Using Attachment 1, determine the appropriate M/A station controller output signal 'V'.

. At HC-1621, perform the following:

. Select'V' on the display to indicate controller output.

Filename: l_esg TR-AA-230-1 003-F06 Revision 0 Page 8 of 24

NflETA' NRC lNlTAL LICENSE EXAM, SCENARO #l Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTVITY EXPECTED STUDENT RESPONSE Cont RO

. Adjust 'V' to the value obtained from Attachment 1.

. Reset the lockout using HSS-1621.

. Verify the Feedwater Lockout Relay amber light is no longer lit.

o Transfer CV-1621 to AUTO as follows:

. Verify the B FEED REG VALVE CONTROLLER HC-1621 is in MANUAL.

. Select'V on the display for B FEED REG VALVE CONTROLLER, HC-1621.

. Select'V on the display for MASTER FEED REG VALVE CONTROLLER, LC-4577.

. Match the Feedwater Reg Valve controller top meter display with the MASTER FEED REG VALVE CONTROLLER top meter display by adjusting the potentiometer on HC-1 621.

. Verify proper response of the Feedwater Regulating valve by monitoring Zl-1621.

. SelectAUTO on HC-1621.

. Select'S' on the display for B FEED REG VALVE CONTROLLER, HC1621.

' Select'S' on the display for MASTER FEED REG VALVE CONTROLLER, LC-4577.

Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 9 of 24

NEXTETA' NRC lNlTlAL LICENSE EXAM, SCENARIO #l Rev.0 SEG n.8 Raise power CREW a Raise reactor power by 5%

lf contacted as Booth Communicator RO organization for Respond as plant personneland a Raises reactor power by 5o/o IAW lPOl 3 and Ol 856.1 as follows:

assistance. respond as necessary o Monitor neutron monitoring instrumentation during control rod movements.

o Verifies the following indications:

. White backlight on the Rod Select pushbutton tums ON

. On the Full Core Display, the white'XX-XX" select light corresponding to the rod selected turns ON

. On the Four Rod Group Display, the white SELECT light turns ON denoting the position display for the selected rod.

o Momentarily places the ROD MOVEMENT CONTROL in the OUT-NOTCH position and verifies:

. The green ROD lN light turns ON momentarily and then turns OFF o The red ROD OUT light turns ON after the green ROD lN light turns OFF.

o The red ROD OUT light turns OFF

. The amber ROD SETTLE light turns ON and then turns OFF o The rod has been withdrawn as indicated on the Four Rod Group Display CRS a Direct and observe reactivity manipulations to achieve a 5o/o raise in reactor power Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 10 of 24

NEXTETA-

=Yst' E.E1 NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev. O SEG After the crew Simulator Operator Crew has reduced Activate ET 7. a Respond to 'B' FRV failure downscale power, reset This will activate FW128 for failure of 'B' RO the'B'FRV, and at the FRV o Assuming manual control of a malfunctioning system direction of the . Take manual control of the'B'Feedwater controller HC-1621 to Floor lnstructor: restore reactor water level o Place one APRM recorder in each trip system to fast speed to lf contacted as Booth Gommunicator monitor for APRM undamped oscillations greater than normal.

organization for Respond as plant personnel and . Verify proper operation/indication of other systems and/or indications assistance: respond as necessary . Verify control rod positions are cotrect for the established sequence, by using Rod Position Log.

lf contacted as Booth Gommunicator . Verify thermal limits on the Official 3D Case.

operators to inspect the 'B' Acknowledge communication o When power is stabilized, plot location on the Stability Power / Flow FRV locally: Map.

CRS Two minutes Booth Gommunicator . Establish critical parameter monitoring of RPV Water Level after being sent lnform control room that nothing o Direct entering AOP 644 to investigate

.B'FRV:

abnormal is seen at the FRV . May direct entering AOP 255.2 Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page11o124

NEXIETA" NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev.0

=YX#- SEG After the crew Simulator Operator Crew has Reactor Activate ET 13. a Respond to control rod 02-19 drifting in IAWARP 1C05A (D-O).

water level This will activate RD060219 with will cause RO restored and at control rod 02-19 to drift in. a Place the C11A-S3 EMERG IN/NOTCH OVERRIDE SELECT switch the direction of the floor on 1C05 in the EMERG ROD lN position momentarily to abort the rod instructor: sequence timer.

a Run an OFFCIAL 3D CASE for abnormal reactor power/control rod lf contacted as Booth Gommunicator distributions.

organization for Respond as plant personnel and a Verify control rod positions are correct for the established sequence, assistance: by using Rod Position Log.

respond as necessary a When power is stabilized, plot location on the Stability Power / Flow Map.

lf contacted as Booth Gommunicator a When Rod motion has been stopped and/or position indication has RE in regards Acknowledge commu nication been restored clear the alarm by momentarily taking C11A-S7 Rod to drifting rod:

Drift Alarm ReseUTest switch to RESET.

Booth Gommunicator CRS Two minutes o lnform control room that further Direct entering AOP 255.1 after contacted as RE: analysis is required and inform shortly . May direct re-entering AOP 255.2

. Notify the Reactor Engineer of the abnormal rod pattern.

lf sent to HCU Booth Gommunicator . Comply with the Technical Specification requirements for Control to investigate: Acknowledge communication Rod Operability LCO 3.1.3 Condition C Two minutes Booth Communicator after sent to lnform control room that nothing HCU: abnormal is seen at the HCU When Emergency Simulator Operator ln/Notch Override Select VERIFY RDO6O2I9 IS DELETED is taken to This will stop rod 02-19 from drifting in EMER ROD IN:

Filename: l_esg TR-AA-230-1 003-F06 Revision 0 Page 12 of 24

NEXlcra' eNEBgr@r NRC lNlTlAL LICENSE EXAM, SCENARIO #l Rev.0 SEG ffi Loss of 1X3 Crew

. lmplement actions of ARP 1C084 (A-7) Startup XFMR 1X3 Trouble.

After RO investigation of Simulator Operator . Send an Operator locally to 1X3 Alarm Cubicle to determine the cause of trip of 1.412 the alarm.

lnsert ETI and tech spec call and at the This inserts AN1C08A(7), S/U Xfmr trouble o With the aid of Table 1, take the appropriate Corrective Action.

direction of the alarm after 1:00 minute time delay. . Take 1X3 out of service per Ol 304.1 and O1304.2, (or Ol 304.2 ORC) floor instructor: CRS r Contact the Electrical Maintenance Supervisor to perform a portable Gas 1 min. after ET Simulator Operator Analysis of the combustible gas.

1 goes active: Verify lC08A [A-71 annunciates. o Direct taking out 1X3 out of service per Ol 304.2 (or Ol 304.2 ORC)

When Booth Gommunicator contacted to investigate 1X3 Acknowledge request.

alarm:

2 min. after told to investigate Booth Gommunicator 1X3 alarm: lnform Control Room there is a Sudden lnternal Pressure Trip Alarm in.

Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 13 of24

NEXTETA" NRC lNlTAL LICENSE EXAM, SCENARO #1 Rev.0 SEG

=YSxø_ ffi After crew Crew receives report o Take 1X3 out of service IAW Ol 304.2 and Ol 304.2 QRCI that 1X3 has hi-RO combustible gas and rising: . Using Ol304.2QRC1:

. Transfer 143 to the Standby Transformer by performing the following:

lflwhen r Place BUS 143 TRANSFER switch in MANUAL.

contacted to Booth Communicator o lnsert the handle in the SYNCHRONIZE switch for 4l(/ BREAKER verify Acknowledge request. 14301 STANDBY TRANSFORMER TO BUS 143, and place in the switchgear ON position.

rooms clear:

. Verify that the synchroscope indicates near 12 o'clock and not Booth Gommunicator moving with both white (differential phase voltage) indicating lights lfAlt/hen OFF.

Ac knowled ge i nformation/req uests contacted as organization:

. Place the control switch 4KV BREAKER 14301 STNDBY TRANSFORMER TO BUS 143 momentarily to the CLOSE position.

. Verify BUS 143 STANDBY AMPERES greater than zero amps.

r Place the control switch 4KV BREAKER 14302 STARTUP TRANSFORMER TO BUS 143 momentarily in the TRlP position.

. Place the SYNCHRONIZE switch for4KV BREAKER 14301 STANDBY TRANSFORMER TO BUS 143 in the OFF position.

o Place BUS 143 TRANSFER switch in AUTO.

Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 14 of 24

N=XTera" NRC lNlTlAL LICENSE EXAM, SCENARIO #l Rev.0

=YSre_ F.,ET SEG RO

. Using Ol304.2QRC1:

o Transfer 1A4 to the Standby Transformer by performing the following.

o Place BUS 144 TRANSFER switch in MANUAL.

. Insert the handle in the SYNCHRONIZE switch for 4KV BREAKER 1A401STANDBY TRANSFORMER TO BUS 144, and ptace in the ON position.

. Verify that the synchroscope indicates near 12 o'clock and not moving with both white (differential phase voltage) indicating lights OFF.

o Place the control switch 41(/ BREAKER 14401 STNDBY TRANSFORMER TO BUS 144 momentarily to the CLOSE position

. Verify BUS 144 STANDBY AMPERES greater than zero amps.

. Place the control switch 4KV BREAKER 14402 STARTUP TRANSFORMER TO BUS 1A4 momentarity in the TRtp position.

. Place the SYNCHRONIZE switch for 4l(/ BREAKER 1A401 STANDBY TRANSFORMER TO BUS 144 in the OFF position.

. Place BUS 1A4 TRANSFER switch in AUTO.

RO a Using O1304.2 QRCI:

o Remove startup Transformer 1X3 from service by performing the following:

o lf required, transfer Bus 141 to the Aux Transformer per Ol 304.1.

. lf required, transfer Bus 142 to the Aux Transformer per Ol 304.1.

. Place the STARTUP TRANSFORMER J BREAKER (OCB SS50) control switch momentarily in the TRIP position.

o Place the STARTUP TRANSFORMER K BREAKER (OCB 5560) control switch momentarily in the TRIP position.

Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 15 of 24

NEXttfa" ENE@ xEEa NRC INITIAL LICENSE EXAM, SCENARIO #l Rev.0 SEG

-/- nEr Floor lnstructor CRS Gheck that CRS is using Ol 304.2 . Using O1304.2 section "TRANSFERRING ESSENTIAL BUS 143[4]

secton "TFIANS FERRI NG FROM STARTUP TO STANDBY TRANSFORMER:

ESSENTTAL BUS 1A3[4] FROM . lf in Mode 1,2, ot 3, verify the following Tech Spec conditions are STARTUP TO STANDBY entered:

TRANSFORMER" for Tech Spec call. o T.S. 3.8.1 Condition A for Standby XFMR Offsite Circuit

. T.S. 3.8.1 Condition B for associated SBDG lf the Startup XFMR Offsite Circuit is currently inoperable, then enter the following additional Tech Spec conditions:

o T.S. 3.8.1 Condition C for both Offsite Circuits inoperable

. T.S. 3.8.1 Condition F (three AC sources inoperable)

. T.S. 3.0.3 (per 3.8.1F)

Filename:'l_esg TR-AA-230-1 003-F06 Revision 0 Page 16 of 24

SEG When Booth Communicator CREW contacted as Acknowledge notification. o Using Ol 304.1 section "REMOVING THE STARTUP TRANSFORMER ITC Midwest: (1X3) FROM SERVlCE":

. Verify Essential Busses 143 and 1A4 are transferred to the Standby lf contacted as Transformer or SBDG per Ol 304.2.

Booth Gommunicator the Acknowledge request.

. Verify Non-essential Busses 141 and 1A2 are transfened to the organization for Auxiliary Transformer per Ol 304.1.

assistance: . Notify ITC Midwest that the Startup Transformer (1X3) will/has be/been removed from service.

. Record the time ITC Midwest was notified that the Startup Transformer was removed from service in the Operating Log.

After 1X3 is Simulator Operator Crew taken out of lnsert ET 9 a Respond to a coolant leak in containment.

service and This will start a drywell leak. RO Tech Spec has been discussed Monitor outside barometric pressure utilizing Computer Point M000 to and at the determine if weather conditions are causing a change in indicated direction of the drywell pressure.

floor instructor: . Verify RIM-91844 and RIM-91848, NW and South Drywell Area Hi Range Rad Monitors, are reading less than 20R/hr.

Start one train of the Standby Gas Treatment System.

After the crew Simulator Operator

. Depress the DIV 1 Reset and DIV 2 Reset pushbuttons to clear the takes HS-4310 isolation signals.

Verify ET 15 goes AGTIVE to Auto Open:

This will increase the size of the leak r Position switches at 1C03 as follows:

leading to the crew to scram. o HS-4303 Outbd DrywellVent lsol CV-4303 Auto Open o HS-4310 lnbd DW Vent Bypass lsol CV-4310 Auto Open o HS-4302 lnbd DrywellVent lsol CV-4302 Auto Open CRS a Directs enterAOP 573 Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 17 of24

NC ETA" NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev.0 SEG Crew

. lmplements EOP 1, RPV Control mitigation strategies.

RO o Prior to exceeding 2# Drywell Pressure, insert and perform lmmediate Operator Responses to a Reactor Scram

. Scrams the reactor and performs lPOl 5, Scram.

o Restores and maintains RPV level 170-211" using directed control system.

. lnstalls Defeat 11.

o Monitors and controls RC/P 800-1055 psig using directed control system (SRVs and MSL drains).

Commences cool down of the RPV to directed RC/P control band with the directed control system.

CRS o Direct crew response to Off Normal Events/ Accidents o Direct Grew Response to manually lnsert a Scram Before Any Parameter Reaches Maximum Safe Operating Limits Directs scramming the reactor and performing lpOl S, Scram.

o Directs RC/L band of 170-211" using the directed control system, RCtC.

. Directs installation of Defeat 11.

o Directs Rc/P of 800-1055 psig using directed control system (sRVs and MSL drains).

Direct Grew Response to Establish a cooldown of the Rpv at a Rate of

<100F/hr Directs cooling down the RPV with Alternate pressure Control Systems (Table 7).

Filename: l_esg TR-AA-230-1 003-F06 Revision 0 Page 18 o 24

NflETA" NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev.0

=Yzaxç SEG After Drywell Simulator Operator Crew Pressure Verify ET 5 AND ll goes active . lmplements the mitigation strategies of EOP 2, Primary Containment exceeds 2 psig Control This will insert HP12 to trip the HPCIAux Oil Pump and ED08C to Lockout Bus 143 RO

. lnforms the CRS of containment parameters including parameter name, lf contacted to Booth Gommunicator value and trend.

investigate 1P-218 breaker:

Acknowledge request. o lnstalls Defeat 4.

. Utilizes Ol 149 QRC to spray the torus.

Two minutes Booth Communicator o Utilizes Ol 149 QRC to spray the drywell.

after 1P-218 lnform control room that breaker for 1P- o Utilizes OI 149 QRC to establish torus cooling.

investigation: 218 is tripped on ground fault. CRS

. Performs a crew update of entry into EOP 2 due to Drywell Pressure.

. Obtains containment parameters.

o Directs installation of Defeat 4.

o Directs spraying the torus after confirmation that torus pressure is greater than 2 psig.

o Directs spraying the drywell before drywell temperature reaches 2A0F.

(cRrTrcAL)

. Verifies torus water level less than 13.5 ft.

o Verifies plot of drywell temperature and drywell pressure on the DWSIL curye allows drywell sprays.

. Verifies recirculation pumps are secured.

o Directs maximizing torus cooling.

. Placekeeps in EoP 2 to the applicable wAtr UNTlL steps in T/L (T/L-3 and T/L 10), T/T (T/T-6), DWT (DWT-6) and PC/P (PC/p-7) tegs Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 19 of 24

NflETA'

l Rev.0 ryYk NRC NlTlAL LICENSE EXAM, SCENARO SEG ALC Crew

. lmplements that mitigation strategies of the ALC contingency of EOP 1 RO o Lockouts ADS.

Attempts to restore and maintain RPV level above +15" o Maximizes injection with CRD in accordance with AIP 407.

o lnjects with SBLC in accordance with AIP 406.

o Verifies injection subsystems can be lined up for injection

. Verifies at least one injection subsystem lined up with a pump running.

CRS o Directs ADS lockout.

o Directs RPV level bands as RPV level lowers o Directs maximizing injection with CRD in accordance with AIP 407.

o Directs injection with SBLC in accordance with AIP 406.

Ensures injections subsystems can be lined up for injection.

o Waits for RPV levelto drop to +15"

. Ensures at least one injection subsystem lined up with a pump running

. Before RPV level reaches -25" performs an E mergency Depressurization Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page2} of24

NEXTETA" ENqllq.a nffi NRC lNTIAL LCENSE EXAM, SCENARIO #l Rev.0 SEG

_/-

F.EI Emergency Crew Depress.: . After RPV level reaches +15" enters and implements the mitigation strategies of EOP ED. (CRITICAL)

. Places handswitch of the first SRV to OPEN prior to RPV level reaching

-25" RO

. Perform Actions of EOP 1 ALC and ED.

o lnstalls Defeat 11.

. Perform an Emergency Depressurization Using SRVs.

. Open4ADS SRVs

. Recognizes MO-1905 does not automatically open at 450 psig and takes action at 1C03 to open MO-1905. (cRlTlCAL)

CRS o Direct Crew Response for performance of EOP 1 ALC and ED o Directs installation of Defeat 11.

o Verifies all control rods inserted to at least position 00.

o Verifies torus water level above 4.5 feet o Direct Crew Response to Perform an Emergency Depressurization Using SRVs a Directs open ing 4 ADS SRVs Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page21 of24

NC ETA'

=YINK NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev.0 SEG EOP 1 Crew lmplementation . lmplements mitigation strategies of EOP 1 after EOP ED to restore after EOP ED: adequate core cooling RO o Verifies low pressure ECCS system (B & D RHR Pumps) start and align to inject into the RPV

. Reports 1 Core Spray pumps are injecting and 1 other ECCS pump is injecting.

o Throttles RHR injection to restore and maintain RPV 170-211" CRS o Verifies 1 Core Spray pumps and 1 other ECCS pump available for injection o Direct Grew Response to Maximize lnjection with Table 2 Systems o Direct to maximize injection with all available Preferred lnjection Systems (Table 1A) and Alternate lnjection Systems (Table 2A).

. Determines RPV level can be restored and maintained above +1S" and returns to the normal RPV level control leg of EOP 1 o Directs restoring and maintaining RPV level 170-211" using low pressure ECCS systems Directs throttling RHR injection to maintain RPV level 170-211' When RPV Simulator Operator level is being Place the simulator in FREEZE.

restored, the crew is progressing to Floor lnstructor SDC, and at Announce the scenario is complete; the direction of please stand by your stations and do the Floor not discuss the scenario with your lnstructor: crew.

- - END OF SCENARIO ***

Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page22 of 24

NEXTETA-EYT6: NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev.0 SEG QUANTITATIVE ATTRI BUTES Malfunctions:

Before EOP Entry:

1. 'B' FRV fail downscale

2. Control Rod Drift

3. S/U Xfmr Hi Combustible Gas After EOP Entry:

1. HPCI Trip Upon Startup

2. Loss of 1A3

3. Drywell Steam Leak Abnormal Events:

1. AOP 644

2. AOP 255.2

3. AOP 255.1 Maior Transients:

1. LOCA in DW

2. ALC

3. ED Critical Tasks:

1. #22: BEFORE drywell temperature reaches 280"F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays. {BWROG: N/A}

2. #1 : lF the reactor is shutdown under all conditions and RPV level drops to +15", THEN perform Emergency RPV Depressurization before RPV level reaches -25".

{BWROG: RPV 1.1}

3. #2: lF the reactor is shutdown under all conditions, THEN crew actions must be taken to restore and maintain RPV level for adequate core cooling. {BWROG: RPV 1.2}

Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page23 o 24

EW NEXTETA" nf NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev. 0 SEG CREW GRADING ATTACHMENT ESG 1 Rev. 0 Date Operator Name Position Evaluator OSM CRS STA 1C05 1C03 B.O.P Management Representative/Lead Evaluator Crew Critical Tasks Task Statement SAT UNSAT

1. BEFORE drywell temperature reaches 280'F and WHILE in the safe region of the DWSIL, THEN initiate drywell sprays.

2. lF the reactor is shutdown under all conditions and RPV level drops to

+15", THEN perform Emergency RPV Depressurization before RPV level reaches -25".

3. lF the reactor is shutdown under all conditions, THEN crew actions must be taken to restore and maintain RPV level for adequate core cooling.

Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page24 of 24

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CNTER TITLE: OFFSITE POWER SOURCES Page Rev.

1of11 5

Usage Level CONTINUOUS Record the following: Date / Time: lnitials NoTE: User shall perform and document a Temp lssue / Rev. Check to ensure revision is current, in accordance with procedure use and adherence requirements.

Prepared By: I Date Print Signature cRoss-DrscrPLrNE REVTEW (As REQUTRED)

Reviewed By: I Date:

Print Signature Reviewed By: I Date:

Print Signature Reviewed By: Date Print Signature PROCEDURE APPROVAL Approved By I Date Print Signature

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CNTER TITLE: OFFSITE POWER SOURCES Page Rev.

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1.0 PURPOSE 1.1 This STP verifies correct breaker alignment and indicated power availability for each offsite circuit capable of supplying the onsite Class 1E AC Electrical Distribution System.

1.2 This STP is routinely performed with both offsite circuits available, or in response to the condition of one offsite circuit or one diesel generator inoperable.

2.0 BRIEFING NFORMATION 2.1 PERFORMANCE I NFORMATION 2.1.1 Section 7.0 of this STP contains two (2) sections that cover the anticipated conditions under which this STP will be performed. The STP is organized as follows Sect. Conditions 7.1 Both Offsite Circuits Available 7.2 One Offsite Circuit Available Only one of these sections should need to be performed to satisfy the performance requirements associated with this STP. All steps within a particular section are to be performed in sequence and the STP steps carried through to completion, unless stated othenruise.

2.1.2 Personnel recommended to perform this procedure 1 Operations 2.1.3 Special Test Equipment required :

1 Marking Pen (Do not use light colored hi-lighters or markers, Use only dark colored pens or markers. See General Caution 2.2.1).

2.2 GENERAL CAUTIONS 2.2.1 lf utilizing a paper copy of this surveillance, do not use light colored hi-lighters or markers to record data, outline configurations on drawings or to initial steps.

Light-colored hi-lighters are not dark enough to reproduce adequately as the QA record. Not applicable when using electronic copies.

2.3 SPECIAL PRECAUTIONS 2.3.1 None

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

3 of 5

11

3.0 REFERENCES

3,1 Applicable drawings:

3.1.1 BECH-E001<1>

3.1.2 BECH-E005 3.1.3 BECH-E023 3.2 Supporting documents:

3.2.1 NG-97-2146 4.0 GENERAL INSTRUCTIONS 4.1 Steps marked with a "TS" immediately to the right of the step sign-off line are required by Technical Specifications. lf these steps do not meet their acceptance criteria or cannot be performed, a NRC reportable condition may exist and shall be reported to the Control Room Supervisor (CRS) immediately.

4.2 lf any equipment or components are observed to be in a state of disrepair during the performance of this STP, appropriate corrective maintenance shall be initiated.

4.3 An Action Request (AR) should be completed for any problems encountered with "TS" marked steps during the performance of this test.

4.4 The CRS shall be notified immediately and the appropriate Limiting Conditions for Operation section of Technical Specifications referred to whenever problems are encountered during the performance of this STP, 5.0 APPENDICES None

SURVEILLANCE TEST PROCEDURE STP 3.8,1-01 DAEC DUANE ARNOLO ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

4of11 5

Prerequisites Performance Date: INITIALS 6.0 PREREQUISITES 6.1 Verify Offsite power is supplying essential buses lA3 and 144 via either the startup transformer (normal source) or the standby transformer (alternate source).

6.2 Evaluate electrical system status and select the STP section which is to be performed:

t I Section 7.1 - Both Offsite Circuits Available t I Section 7.2 - One Offsite Circuit Available

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

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Performance Date: INITIALS 7.0 PROCEDURE 7.1 BOTH OFFSITE CIRCUITS AVAILABLE NOTE lnformation from the Load Dispatcher may be needed to complete the following step.

7 .1.1 Using the guidance below and Attachment 1, identify two separate circuits available to transmit power from the offsite power sources to the essential buses.

a. Based on equipmenUsystem lineup and operational status, use a dark marking pen to trace an available circuit from an offsite power source to the Startup Transformer supply breakers, 14302 and 14402.

b. Based on equipmenUsystem lineup and operational status, use a dark marking pen to trace a second circuit from another offsite power source to the Standby Transformer supply breakers, 14301 and 1A401 such that it does not share any lines, buses, or transformers in common with the circuit to the Startup Transformer supply breakers.

c. Based on equipmenUsystem lineup and operational status, complete the electrical lineup by using a dark marking pen to trace the connections from each Essential Bus (143 and 144) to the Startup or Standby Transformer supply breaker currently feeding the bus.

7.1.2 Confirm two (2) independent offsite circuits are available by initialing one of the two sets of statements below and N/A'ing the other:

a. A circuit exists from an offsite power source, through the TS Startup Transformer and its supply breakers to both 143 and 144 essential buses; AND A second independent circuit exists from a ditferent offsite source, through the Standby Transformer to its supply breakers.

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

6 of 11 5

Performance Date: INITIALS

b. A circuit exists from an offsite power source, through the TS Startup Transformer and one of its supply breakers to either the 1A3 or 1A4 essentialbus; AND A second independent circuit exists from a different otfsite source, through the Standby Transformer and one of its supply breakers to the other essential bus.

(PRTNT / SrGN)

I I

I Performed by: Date: Time: lnit.

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAE,C DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

7of11 5

Performance Date INITIALS 7.2 ONE OFFSITE CIRCUIT AVAILABLE NOTE lnformation from the Load Dispatcher may be needed to complete the following step.

7.2.1 Using the guidance below and Attachment 1, identify a circuit available to transmit power from an offsite power source to the essential buses.

a. Based on equipmenUsystem lineup and operational status, use a dark marking pen to trace an available circuit from an offsite power source to the Startup Transformer supply breakers, 14302 and 1A402 or Standby Transformer supply breakers, 14301 and 14401.

b. Based on equipmenVsystem lineup and operationalstatus, complete the electrical lineup by using a dark marking pen to trace the connections from the required Essential Bus(es)

(143 and/or 1A4) to the Startup or Standby Transformer supply breakers.

7.2.2 If in Mode 1,2 or 3, mark Step 7.2.4 "N/A" and proceed with the performance of Step 7.2.3.

OR lf in Mode 4 or 5, or during movement of irradiated fuel assemblies in the Secondary Containment, mark Step 7.2.3'N/4" and proceed with the performance of Step 7.2.4.

7.2.3 Confirm an offsite circuit exists from an offsite power source, S through either the Startup or Standby Transformer and its associated supply breakers to both 143 and 144 essential buses.

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLO ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

I of 11 5

Performance Date: INITIALS 7.2.4 Confirm an offsite circuit exists from an offsite power source by initialing one of the two statements below and "N/A'ing" the other:

a. An offsite circuit exists from an offsite power source, through TS either the Startup or Standby Transformer and its associated supply breakers to both 1A3 and 144 essential buses.

b. An offsite circuit exists from an offsite power source, through TS either the Startup or Standby Transformer and one of its associated supply breakers to the required 143 or 144 essential bus.

(PRTNT / SrGN)

I I

I Performed by Date Time: lnit.

ir

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

9 of 5

11 Performance Date: INITIALS 8.0 ACCEPTANCE CRITERIA 8.1 lndicate the reason for performing the STP:

t I Routine with both offsite circuits available t 1 Routine with one offsite circuit available while in Mode 4 or 5 or during movement of irradiated fuel assemblies in the secondary containment t 1 Action in response to one offsite circuit inoperable t I Action in response to one diesel generator inoperable t I Other, explain below:

8.2 All Technical Specification required items, as indicated by "TS", have been performed satisfactorily:

8.2.1 Section 7.1 ( ) YES ( ) NO = CRS notified 8.2.2 Section 7.2 ( ) YES ( ) NO + CRS notified 8.3 All other items checked in this test have been performed satisfactorily:

8.3.1 Section 7.1 ( ) YES ( ) NO + CRS notified 8.3.2 Section 7.2 ( ) YES ( ) NO + CRS notified

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

10 of 5

11 Performance Date INITIALS 8.4 lndicate any relevant test comments below, othenryise mark this step "N/4" (PRTNT / SrGN)

I Operations Date 9.0 ATTACHMENTS 9.1 Attachment 1 - DAEC Offsite Power Circuits Feeding Essential Buses

SURVEILLANCE TEST PROCEDURE sTP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page 11 of Rev. 5 11 Attachment't DAEC OFFSITE POWER CIRCUITS FEEDING ESSENTIAL BUSES Sheet I of 1 7510 "c'

Dysart Sub Power Source Breaker Transformer Bus 5950 5560

.AB' "tc Downtown lndustrial Line Unacceptable path for the of this STP 4290 161KV West IA Bus 301 302 345KV West Bus 2820 6780 Hills 1A3 Sub 31 10 0220 0710 E490

'B' Hazelton Sub LA4 4730 2690 East Bus 9180 161KV East 1A ,IA Bus 40'l 402 Hawatha Sub L2 8090 5550 Farfax 5ub

NEXTETA-SIMULATOR EXERCISE GUIDE SEG

=Yrc SITE: DAEC Revision #: 0 LMS ID: PDA OPS ESG 2 LMS Rev. Date: N/A SEG TITLE: NRG lNlTlAL LICENSE EXAM, SCENARIO #2 SEG TYPE: ! Training X Evaluation PRocRAM: nLOCT XLOIT nOther:

DURATION: -90 minutes Developed by:

lnstructor/Developer Date Reviewed by:

lnstructor (lnstructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date Filename:2-esg Page 1 of 25 TR-AA-230-1 003-F06 Revision 0

,Y*x6 NEXTETA' NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG SIMULATOR EXERCISE GUIDE REQUREMENTS Terminal Objective This Evaluation Scenario Guide evaluates the Operators' ability to:

"Given the malfunctions presented in this ESG, the students will protect the public, protect plant personnel, and protect plant equipment, in accordance with plant procedures."

Enabling Evaluation Guide, no tasks are trained. Evaluated tasks are listed on page 4 Objectives:

Prerequisites: None Training A. Simulator Resources: B. Evaluation team C. Operations Management Representative D. Simulator Driver E. Phone Talker F. Exam Proctor for custody of the crew between scenarios G, Simulator Video recording equipment

References:

A. O1644, Rev. 172 B. lPOl 2, Rev. 154

c. O1264, Rev. 138 D. Ol 856.1, Rev. 48 E. Ol 856.2, Rev.9 F. Ol 878,8, Rev.27 G. AOP 255.1, Rev. 46 H. ARP 1C034, Rev, 58

t. ARP 1C048, Rev. 81 J. ARP 1C084, Rev.92 K. EOP 3, Rev.22 L. EOP Defeat 15, Rev. 7 M. ARP 1C058, Rev, 105 N. EOP 1, Rev. 20

o. ATWS, Rev.23 P. O1644 QRC 2, Rev 0 Q. Ol 149 QRC 4, Rev. 0 R. Ol 734 QRC 1, Rev. 0 S. Ol 153 QRC 1, Rev. 4 ProtectedContent: None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance Operating None Experience:

Risk Significant Operator Actions:

Filename:2-esg TR-AA-230-1 003-F06 Revision 0 Page 2 ot 25

NEXTETA

ÉY4- NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG TAS KS ASSOCIATED wl TH SIM ULATO R EXERCI SE G U IDE Task # Task Title Reactor Operator 8.11 Manual De or lnte ADS Auto lnitiation 93.21 Perform a Fast Power Reduction 94.50 nd to Condenser H h re 95.21 Perform EOP Defeat 11 95.42 ln into the RPV with SBLC from the Boron Tank 95.45 Perform lnitial EOP 1 Actions 95.50 Perfo rm /L to Control RPV Level d an ATWS 95.51 Perform Power/Level Control 95.55 Perform lnitial ATWS Actions 95.56 Perform /P to Control RPV Pressure Durin an ATWS 95.57 Perform /Q to Reduced Reactor Power or SCRAM the Reactor Senior Reactor O rator 1.02 Determine OperabilitY for Techn ical Specification Required Components 5.50 Direct Crew to Condenser Hi h ure 6.21 Direct Crew to Perform EOP Defeat 11 6.42 Direct Crew tol into the RPV with SBLC from the Boron Tank 6.45 Direct Crew se for of initial EOP 1 actions RC 6.50 Direct Crew SE to Perform /L to Control Level an ATWS 6.51 Direct Crew se to Perform Power/Level Control 6.55 Direct Crew SE to Perform lnitialATWS Actions 6.56 Direct Crew Res SE to /Q to reduce r/scram the reactor duri ATWS 6.57 Direct Crew Res SE to /P to control RPV re durin an ATWS UPDATE LOG: lndicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial Or use form TR-AA-230-1 003-F16.

DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER I nitial development for See Cover lnitial development for 2017 2017 NRC LOIT N/A Rev. 0 See Cover NRC LOIT Examination Examination Filename:2_esg TR-AA-230-1003-F06 Revision 0 Page 3 of 25

NFX] ETA ENERGY_Ø NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG OVERVIEW / SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE Event # Description The crew will assume the shift at approximately at 8% Reactor power with applicable portions of lPOl 2 completed. 'A' CRD pump is OOS due to gearbox inspection. The crew will be briefed as to the need to withdraw rods through step 17 (approximately 10% reactor power), transfer from the Startup FRV to the 'A' FRV, and then continue with the power ascension' 1

After initial power rise and transfer of the FRVs, the crew will attempt to continue the power rise when a loss of notch indication and an entry into AOP 255.1 . The crew will confer with RE and will substitute the rod position IAW Ol 878.8 Section 8.2 2 Following the AOP entry, Annunciator RE-41168 OFFGAS VENT PIPE B DNSC/INOP due to an Electrical Fault. The crew will determine LGO 3.3.6.1 for Function 2c - Offgas Vent Stack - High Radiation - Channel B does not need be entered since not in the mode of applicability.

3 A grid voltage transient causes 'A' SB DG to spuriously start, and the Voltage Regulator fails to maintain voltage. The crew wi ll place the 'A' SBDG handswitch to PTL, declare the

'A'SBDG inoperable, and enter LGO 3.8.1, Gondition B and LCO 3.7.3 Condition A.

4 A steam leak in the Steam Tunnel causing an entry into EOP 3. The crew will attempt to insert a manual scram and discover an ElectricalATWS. The'B'CRD pump will trip shortly after due to high vibrations. Temperatures will continue to rise during the ATWS and cause Group 1 isolation.

5 The crew will enter EOP 1, determine that an Electrical ATWS is occurring, then transition to ATWS, lock out ADS (CRITICAL), perform the Electrical ATWS RlPs, and attempt to inject with SBLC only to discover that the inject valve is stuck and SBLC injection is not available.

6 The crew will transition to power level control and Terminate and Prevent injection.

(CRITICAL) and establish a level band until all rods are inserted. (CRITICAL) The crew will notice that RCIC failed to start and start RCIC manually.

7 performance of Electrical RlPs (RPS Fuses) will insert rods to shutdown the Reactor (cRrTrcAL)

B After all rods are verified to be fully inserted, the crew will transition from EOP ATWS back to EOP 1 and establish an RPV level band of 170 -211" the scenario will be over.

name:2_esg TR-AA-230-1 003-F06 Revision 0 Page 4 of 25

NEXTETA NRC lNlTlAL LCENSE EXAM, SCENARIO #2, Rev.0 SEG

=Y,ffi SIMULATOR SET UP INSTRUCTIONS

1. Set NRC Exam Security for the Simulator per QF-1071-08

2. Perform simulator set up per TDAP 1839 Attachment 2, Simulator Setup Checklist.

3. Load the saved lC (in folder with this ESG) to a SNAPSHOT reset to that SNAPSHOT and place the Simulator in RUN, OR 4 Reset to lC 184, place the simulator in RUN and perform the following:

a. lnsert Event Triggers, Malfunctions, Overrides, and Remotes per the tables below

b. Using MOL pull sheets insert control rods to achieve approximately 8% reactor power

c. Using lnSight bring up ypfastxen and set to -1.0000 three times to burn out Xenon

d. Pull rods as necessary to achieve approximately 8% reactor power after the Xenon burn.

e. Substitute final feedwater temperatures (computer points 8030, 8031, 8032, 8033)

f. Place Mode Selector switch to the RUN position'

5. RUN Schedule File "Actions.sch" and LEAVE lT RUNNING.

. Verify Malfunctions.

7. Verify Remotes (Note that environmental remotes will already be timing)

8. Verify Overrides.

9. Ensure MOL pull sheet is in the 1C058 hanging file' 10 Establish EOOS conditions for OOS components and plant conditions 11 Setup control panel including equipment clearance tags, information tags, caution tags or other site-specific devices used as an aid to the operator.

a. Substitute final feedwater temperatures (computer points 8030, 8031, 8032,8033)

b. Place Guarded system tags on'A'CRD pump 12 Plant procedures being worked at time of scenario initiation including what steps are completed.

a. Remove CRAM group sheets from 1C05

b. Place O1264 on desk open to Appendix 2

c. Ol 856.1 Section 4.1.5 (1) Place keep the following steps as complete:

a) All Notes and StePs 1-7 (2) Place keep the following steps as in progress:

a) StePs 8-9

d. Place Ol 856.2 on desk open to Section 4.1

e. lPOl 2 section 4.3 (1) Place keep the following steps as complete:

a) All Notes, CRSs, and Cautions up to step 20 b) StePs 1-11a, 12'17, 19-20 Filename:2_esg TR-AA-230-1 003-F06 Revision 0 Page 5 of 25

NEXTETA" NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG (2) Place keep the following steps as in progress:

a) Steps 1 1b & c

f. Rod sequence sheets (1) Place keep rods as out up to and including Step 15'

g. Mark Power/Flow Map as necessary Filename:2_esg TR-AA-230-1 003-F06 Revision 0 Page 6 of 25

NEXTETA-NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG

=Yr6 EVENT TRIGGER DEFINITIONS Trigger No. Trigger Logic Statement Trigger Word Description 1,3,5,17 MANUALLY ACTIVATED MANUALLY ACTIVATED 7 ZDIDGDGI(1) == I 'A' SBDG control HS in PTL o ZDlHVHS6514 == 1 HS-6514 RX BLDG SUPPLY FAN 1V-SF-10C to START 11 RPDISIRUN(1) l= 1 Reactor Mode Switch out of RUN MALFUNCTIONS lnitial Final Time Malf. No Malfunction Title ET Delay Ramp Value Value Setup MS18A VALVE CV1158A/B FAILURE - CV1158A 100 100 100 100 MS18B LVE CV1158A/B FAI - cv1 1588 RPS SCRAM CIRCUIT FAILURE (ATWS)- AUTO ACTIVE ACTIVE Setup RPOSA SCRAM FAILURE RPS SCRAM CIRCUIT FAILURE (ATWS)- MANUAL ACTIVE ACTIVE Setup RPOSB FAILURE SC RPS SCRAM CIRCUIT FAILURE (ATWS)- ARI FAILURE ACTIVE ACTIVE Setup RPOSC Setuo STRCOl TRIP OVRD- RCIC FAILS TO AUTO START ACTIVE ACTIVE Setup RMO3RE41 168 RE-41168 OFFGAS VENT PIPE B 1 3 SEC INACTIVE ACTIVE 1C034 (B-04) OFFGAS VENT PIPE RM-4116 A/B HI 3 SEC CRWVOLF CRWVOLF Setup AN1C03A(13) 1 Setuo DGO3A 1G31 'A'D GENERATOR TRIP- A 3 06:00 INACTIVE ACTIVE 1G31 'A'DIESEL GENERATOR V/R OSCILLATES IN 30 DGOSA 3 5 SEC 0 100 Setup AUTO- SEC 1G31 'A' DIESEL GENERATOR SPURIOUS START- DG 3 INACTIVE ACTIVE Setup DGOTA A POWER GRID FREQUENCY DISTURBANCE 3 0 45 Setup EDO2 (DELETE in 1 SEC)

POWER GRID VOLTAGE TRANSIENT 3 50 45 Setup EDO3 (DELETE in 1 SEC)

CR RPIS REED SW FAILURE OPEN- ROD 18-27 ACTIVE ACTIVE Setup RD0441827 STEAM IN STEAM TUNNE A 5 6:00 0 0.35 MSOSA ALL INDIVIDUAL ROD SC RAM SWITCHES FAIL ACTIVE ACTIVE S RPOsE CRD HYD MP TRIP - PUMP ACTIVE ACTIVE Setup RD11A CRD PUMP'B' HIGH VI BRATION 11 1:00 INACTIVE ACTIVE RD26B RD HYDRAU MP TRIP - PUMP 11 1:30 INACTIVE ACTIVE Setup RD11B SBLC INJECT VALVE V-26-9 STUCK 0 0 Setuo SLO4 REMOTES:

lnitial Final Time Remote No. Remote Title ET Delay Ramp Value Value MN co N D 1 E- 7 A VAC U U M BR EAKE R V 73 17 02:00 CLOSED OPEN Setup MC01 MC02 M N co N D I E-7 B VAC U U M BR EAKE R V 67 17 02:30 CLOSED OPEN Setup HS-1807A(1)CRD PUMP 1 807 BREAKER ACTIVE ACTIVE Setup DO-RD-615 TRIPPED GR HS-1807A(2) CRD PU MP 1807 BREAKER ACTIVE ACTIVE Setup DO-RD-616 TRIPPED HS-18074(3) CRD PUMP 1807 BREAKER ACTIVE ACTIVE Setup DO-RD-617 TRIPPED (RED)

Filename: 2_esg TR-AA-230-1003-F06 Revision 0 PageT of25

NEXTETA-NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG

=Y"&

SCHEDULE FILES Actions.sch

@ Time Event Action Descri Setup 7 Delete malfunction dg03a 1G31 'A' DIESEL GENERATOR TRIP- DG A I Modifv malfunction msO8a to 0.6 in 300 Conduct simulator crew pre-scenario brief using TR-AA--230-1007-F06, Simulator lnstructor Pre-Exercise Checklist.

lf surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename:2-esg TR-AA-230-1 003-F06 Revision 0 Page I of 25

NEXTETA' EYx6:t NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG SHIFT TURNOVER INFORMATION o Today, Day Shift o Warm summer afternoon temperatures in the mid 70's

. Plant power - -8o/o with the corresponding MWe, MWth, and core flow o Protected Train - "4" o Procedures or major maintenance in progress:

o lPOl 2 startup in Progress o 'A'CRD Pump OOS, gearbox open for inspection

' Approximate time for restoration is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

. Technical Specification Action statements in effect:

o DAEC is in compliance with all LCO's a Plant PRA Status o CDF: 1.29 x 10-6, GREEN, I year to Yellow ICDP o LERF 3.05 x 10-7, GREEN, 1 year to Yellow ILERP O Evolutions in progress or planned for upcoming shift:

o Continue to raise power IAW with lPOl 2 to approximately 10% this will coincide with the completion of steP 17 o Transfer feed control from the Startup FRV to the 'A' FRV IAW Ol 644 Section 3.6 o Continue to raise power IAW with lPOl 2 a Comments, problems, operator workarounds, etc' o One extra NSPEO available in Work Control o Radwaste Operator is NSPEO qualified Filename:2_esg TR-AA-230-1 003-F06 Revision 0 Page 9 of 25

NE)CETA' NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG

=Yrç SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE rPot 2 CREW a Withdraw control rods IAW lPOl 2 and Ol 856.1 to complete step 17 RO a When reactor power reaches approximately 10% power on APRMs or as desired by the CRS/OSM o Continue to raise power with control rod withdrawal until one bypass valve is open and the second bypass valve is approximately 25o/o open.

o Monitor neutron monitoring instrumentation during control rod movements.

o Verifies the following indications:

o White backlight on the Rod Select pushbutton turns ON

. .XX-XX' select light On the Full Core Display, the white corresponding to the rod selected turns ON

. On the Four Rod Group Display, the white SELECT light turns ON denoting the position display for the selected rod.

Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page 10 of25

NEXTETA NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG

=ysre_

SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Raise Power RO Cont. Momentarily places the ROD MOVEMENT CONTROL in the OUT-NOTCH position and verifies:

. The green ROD lN light turns ON momentarily and then turns OFF

. The red ROD OUT light turns ON after the green ROD lN light turns OFF.

The red ROD OUT light turns OFF

. The amber ROD SETTLE light turns ON and then turns OFF

. The rod has been withdrawn as indicated on the Four Rod Group Display CRS a Direct and observe reactivity manipulations to achieve step 17 complete Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page 11 ot25

NCIETA' NRC lNlTAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Shift FRVfrom Booth Communicator CREW S/U to'A' Acknowledge coordi nation a Shift FRV from the S/U FRV to the 'A' FRV o1644 RO o Shift feed flow control from the STARTUP FEED REG VALVE to A FEED REG VALVE as follows:

o Verify the MASTER FEED REG VALVE CONTROLLER, LC-4577, is in AUTO and select 'V'with the D pushbutton on the display.

o Verify the STARTUP FEED REG VALVE CONTROLLER, HC-1622, is in AUTO.

o Verify the A FEED REG VALVE CONTROLLER HC-1579 is in MANUAL.

o Select'V' on the display for the A FEED REG VALVE CONTROLLER, HC-1579.

o Slowly open A FEED REG VALVE CV-1579 using the potentiometer on HG-1 579.

o Monitor reactor water level closely and confirm auto operation of FEEDWATER STARTUP FEED REG VALVECV-1622.

o When the display on CV-1579 is matching the display on LC-4577, select AUTO on HC-1579.

o Select MANUAL on STARTUP FEED REG VALVE CONTROLLER HC-1622.

o Slowly close STARTUP FEED REG VALVECV-1622 using the potentiometer on HC-1622.

o Monitor reactor water level closely and verify auto operation of A FEED REG VALVE CV-1579.

o Close MO-1631, Startup Feedline Block.

CRS a Coordinate shifting feed flow controlfrom the STARTUP FEED REG VALVE to A FEED REG VALVE.

Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page 12 of 25

NEXI ETA-NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUGTOR ACTIVITY EXPECTED STUDENT RESPONSE Control Rod CREW Position Lost a Perform the Follow Up Actions of AOP 255.1 for Abnormal Rod AOP 255.1 Control and Position lndications RO a For rod position indication lost at one notch:

o Attempt to move the affected rod, as allowed by rod lF called as any Booth Gommunicator sequence, to an adjacent notch to check for reed switch DAEC support Acknowledge coordination failure personnel: o Consult with CRS/OSM and Reactor Engineer to modify rod pattern if necessary to avoid leaving the control rod at the notch with no position indication lf contacted as Booth Gommunicator CRS RE for Acknowledge commu nication a Direct the performance of AOP 255.1 forAbnormal Rod Control and substituting Position lndications position for rod a Consult with Reactor Engineer to enter Substitute Rod Position into 18-27: 3D Monicore per REDPT Section 3.7, Substituting Rod Positions ln 3D Monicore.

Two minutes Booth Gommunicator after contacted Report to the control room that you as RE: concur with substituting rod position for rod 18-27 and to continue with startup.

Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page 13 of 25

NEXTETA'

=Ytsg NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONS Position CREW Substitution a Substitute notch position IAW Ol 878.8 Section 8.2 878.8 RO

. At 1C28, verify the Rod Worth Minimizer (RWM-CC) keylock MODE switch in the OPER position.

. At 1C05, verify the Rod Worth Minimizer (RWM-OD) keylock mode switch is in the OPERATE position.

. At 1C05 (RWM-OD), press the ETC soft-key untilthe SUBSTITUTE OPTIONS menu choice becomes available.

o Press the appropriate soft-key.

o Press the INCREMENT POSTION soft-key to select the desired position.

. lndependently verify desired position on RWM Display Press the ENTER SUBSTITUTE soft-key.

. Verify screen display.

o Press the EXIT soft-key

. lnsert rod 18-27 to position 06 CRS a Direct substituting notch position for rod 18-27 a Direct rod 18-27 insertion to n06 Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page 14 of 25

NEXTETA" NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG

=Y4 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSÉ Offgas Vent CREW Pipe RM a Respond to annunciators per ARP 1C034 (C-4)

Downscale RO After crew has a At 1C10, monitor OFFGAS STACK VENT PIPE B RAD MONITOR inserted rod 18- Simulator Operator: RM-41168 to determine if DOWNSCALE or INOPERATIVE.\

27 to position a Send an Operator to the following panels to verify the breakers ACTIVATE ET 1 06 and/or when closed/reset:

directed by the This causes RE-41168 OFFGAS VENT o RM41168 - 1D60 Breaker 03 Floor lnstructor: PIPE B to fail.

CRS lf contacted to Booth Communicator: . Determine affected Tech Spec investigate . LCO 3.3.6.1 1 D60: After 2 minutes, inform control room o Function 2c Offgas Vent Stack - High Radiation - Channel B that Breaker 03 for 1D60 is closed in o Determine not in mode of applicability with no noticeable problems.

lF called as any Booth Gommunicator:

DAEC support personnel: Acknowledge Request Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page 15 of25

NEX refa' NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When directed Simulator Operator: CREW by the Floor a Respond to annunciators perARP 1C084 (A-10)

ACTIVATE ET 3 lnstructor: RO This causes a momentary grid . Verify that EMERG SERV WATER PUMP 1P-994 is running.

disturbance. 'A' SBDG will spuriously start o Verify 1V-SF-20 Diesel Generator Supply Fan is running.

and its voltage regulator fail. . lf "4" SBDG 1G-31 was not started for testing and is no longer required for operation, shut down '4" SBDG 1G-31 per O1324 (Standby Diesel Generator System).

lF called as any Booth Gommunicator: CRS DAEC support personnel: Acknowledge Request a f SBDG 1G-31 is determined to be inoperative, comply with the Technical Specification requirements for AC Sources-Operating and AC Sources-Shutdown.

lf contacted to Booth Gommunicator:

investigate'A' SBDG:

Acknowledge Request Three minutes Booth Gommunicator:

after requested to investigate Inform control room that'A'SBDG

.A'SBDG: appears to be normal and all alarms at 1C93 are as expected.

lf contacted to Booth Gommunicator:

verify operation of 'A' ESW:

Acknowledge Request Two minutes Booth Gommunicator:

after requested to verify lnform control room that'A' ESW is operation'A' operating SAT.

ESW:

Filename:2_esg TR-AA-230-1 003-F06 Revision 0 Page 16 of25

NEXTETA' NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG

=ysre_

SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the crew Simulator Operator: CREW places the 'A' a Determine that'A' SBDG is not operating correctly and secure it by VERIFY ET 7 ACTIVATES SBDG in PTL: placing the handswitch HS-32314 in PTL.

This deletes malfunction dg03a.

RO Simulator Operator: a Place'A'SBDG handswitch HS-32314 in PTL lf the crew does not take the 'A' SBDG CRS to PTL prior to the auto trip: a Determine that the 'A' SBDG is INOPERABLE and enter appropriate Tech Specs Pause "Delete malfunction dg03a" in Actions.sch a LCO 3.8.1, Condition B

. 8.1, Perform SR 3.8.1.1 for Operable offsite circuits within 1 AND hour AND once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

. 8.2 Declare required features, supported by the inoperable DG INSERT ET 7 inoperable when the redundant required features are inoperable within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition B concurrent with Evaluator Note: inoperability of redundant required feature(s).

lf the crew does not place 'A' SBDG in PTL in 6 minutes, it will trip on generator o 8.3 Determine OPERABLE DG is not inoperable due to common lockout. cause failure within 24 hrs.

lf the crew requests a copy o 8.4 Perform SR 3.8.1.2 for OPERABLE DG once per 72hrs.

of . 8.5 Restore DG to OPERABLE Status within 7 days.

sTP 3.8.1-01 Floor Evaluator:

and/or STP Give the crew the requested copy of 3.8.1-02: STP 3.8.1-01 and/or STP 3.8.1-02 Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page17 of25

NEX rCfa' NRC lNlTlAL LCENSE EXAM, SCENARIO #2, Rev.0 SEG YPYK SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EOP 3 CREW Steam Leak in a Respond to annunciators perARP 1C048 (B-4), STEAM LEAK DET Steam Tunnel AMBIENT HITEMP/EOP 3.

After SBDG has Simulator Operator: RO TS has been a Send an Operator to 1C21to determine which area has the high declared and at ACTIVATE ET 5 temperature condition.

the direction of This will insert MS08A to start the Steam a Start 1V-EF-1,1V-EF-Z and 1V-EF-3 MAIN PLANT EXHAUST the Floor Tunnelsteam leak. FANS by positioning the following handswitches to START and verify lnstructor:

their respective dampers indicate OPEN:

(NOTE: Bring up EOPSLD and monitor Steam Tunnel Temperature) o Fan Handswitch Panel Damper o 1V-EF-1 HS-7613 1C234 1V-AD-16U o 1V-EF-2 HS-7614 1C238 1V-AD-16V o 1V-EF-3 HS-7615 1C23C 1V-AD-16W o Start the Reactor Building Exhaust Fans by positioning the following handswitches to START:

o Fan Handswitch Panel o 1V-EF-114 HS-76114 1C23A.

o 1V-EF-118 HS-76118 1C238 o Start the Reactor Building Supply Fans by positioning the following handswitches to START:

o Fan Handswitch Panel o 1V-SF-104 HS-6512 1C23.

o 1V-SF-108 HS-6513 1C238 o 1V-SF-10C HS-6514 1C23C a lnsert manual reactor scram Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page 18 of 25

N(Tera-NRC INITIAL LIGENSE EXAM, SGENARIO #2, Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPEGTED STUDENT RESPONSE EOP 3 Cont. CRS a Direct Crew Response for performance of EOP 3 for high area temperatures level including EOP 1 o Direct Main Plant Supply and Exhaust Fans in a 3-2-3 lineup o Determines RPV pressure reduction will lessen the leakage rate.

o Before steam tunnel temperature reaches the Group I setpoint enter EOP 1 and direct inserting manual reactor scram.

EOP 1 CREW Transition to a lmplements the mitigation strategies of EOP 1 and EOP ATWS ATWS RO o lnserts a manual reactor scram.

. Reports the'B' CRD pump high vibes and trip o Recognizes an electricalATWS has occurred and reports the type of ATWS and reactor power.

. Places the master Feedwater level controller to 158.5" in AUTO.

CRS o Enters EOP 1, RPV Control based on reactor power is above 5o/o or unknown after a scram signal is received.

. Determines that a reactor scram has been initiated

. Validates isolations, initiations and SBDG initiations that should have occurred but did not.

o Recognizes and implements the CRS "IF any rod is withdrawn past position AND it has NOT been determined that the reactor will remain shutdown under all conditions without boron THEN exit this procedure and enter ATWS".

Filename:2_esg TR-AA-230-1 003-F06 Revision 0 Page 19 of25

NEXTETA' NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG SMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE ATWS Crew a lmplements the mitigation strategies of EOP 1 and EOP ATWS RO

. Locks out ADS (CRITICAL) lf directed to Booth Gommunicator:

. Performs the ATWS QRC.

vent the scram . Reports completion of the ATWS QRC. Determines that ARI was Acknowledge the request. unsuccessful. Reports RPV level and reactor power.

air header:

. Announces failure to scram.

. Reports SBLC inject pressure high and no flow.

o lnstalls Defeat 11.

Three (3) c RS minutes after Booth Gommunicator: Directs locking out ADS.

being directed lnform the control room that you o Verifies at least one set of inboard and outboard MSIVs are not open.

to vent the cannot vent the scram air header due to . Directs performance of the ATWS QRC.

scram air the valve being bound. o Directs initiation of SBLC.

header: o Directs electricalATWS rod insertion procedures

. Exits the ATWS "Q" leg flowpath and enters "L" leg actions Filename:2_esg TR-AA-230-l 003-F06 Revision 0 Page 20 of 25

NEXTETA NRC lNlTAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG

=Yrç SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE ATWS Crew o lmplements AOP ATWS power level control actions RO a Verifies or trip/lockout HPCI.

a Terminates injection:

o Condensate and Feed:

. Close Feedwater Regulating Valves CV-1579, CV-1621' "JJ:rli jllij;,,."r or Master Fed Reg Valve Auto/Man Control LC4577 and dialthe Evaluator Note: controller down until all Feedwater Regulating Ensure that while level is lowering that the Valves indicate closed as indicated on:

RO acknowledges RCIC failure to auto . HC-1579, A Feed Reg Valve Manual/Auto Transfer start and recommends starting RCIC. . HC-1621, B Feed Reg Valve Manual/Auto Transfer

. HC-1622, Startup Feed Reg Valve Manual/Auto Transfer a RHR:

o Place MO-2004 and/or MO-1904 LPC OPEN INTLK OVERRIDE HS-2004C and/or HS-1904C to OVERRIDE o When 1C038 (B-5) RHR RX LO PRESSURE PERMISSIVE AT 450 PSIG is activated, close MO-2004[MO-190a] by taking HS-2004[HS-1 904] to CLOSE o Recognizes that RCIC did not start automatically a Starts RCIC manually.

a Reports reactor power when RPV level reaches 87" and lowering.

CRS

. Directs terminating and preventing injection from CS, RHR and Condensate and Feedwater. (CRITICAL)

. Directs starting RCIC manually

. Directs reporting reactor power at 87" and lowering.

. Directs continuing to lower RPV level until conditions allow for reinjection.

Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page21 of25

NEX refa' eNTljYø_ nnr R NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG RET SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE ATWS Crew a When all rods are in, transition from ATWS to EOP 1 RO a Reports rod insertion working by drifting rods, and/or removing RPS Fuses. (CRITICAL) a Controls level 170"-211" using Condensate and Feedwater (cRrTrcAL) c RS

. Directs transition back to EOP 1

. Directs RPV level 170"-211" using Condensate and Feedwater When all rods are full in:

Simulator Operator:

lF directed to break Main Acknowledge the direction, then Condenser ACTIVATE ET 17 Vacuum:

This inserts remote functions mc01 and mc02.

Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page22 of 25

NEXTETA" ENERGYØ NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG ffi SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the crew Booth Instructor has inserted all Place the simulator in FREEZE.

control rods and is restoring RPV Water Floor lnstructor Levelto >170" Perform a crew update and announce and.at the to the crew the simulator is in freeze direction of the and the scenario is complete.

Floor lnstructor:

- " END OF SCENARIO ***

Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page 23 of 25

eW NEXIETA" NRC lNTIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG QUANTITATIVE ATTRI BUTES Malfunctions:

Before EOP Entry:

1. Loss of notch indication

2. RE-41168 Offgas Vent Pipe "8" Failed Downscale

3. .A" SBDG 1G-2l Spurious Start and failure to maintain Voltage Regulation After EOP Entry:

1. RCIC Fails to Auto Start Abnormal Events:

1. AOP 255.1

2. ARP 1CO8A

.l Maior Transients:

1. EOP 3 Steam Tunnel Leak

2. ElectricalATWS Critical Task

1. li4: lF a scram is required and reactor power is above 5%, THEN reduce power below 5%

using one or more of the following methods: {BWROG RPV 4' 1, 5'1, 6'1}

lnserting control rods using RlPs

2. #6: lF a reactor scram is required and the reactor is not shutdown under all conditions, THEN lockout ADS before automatic actuation. {BWROG RPV 4.2,5.2,6.21

3. #10: lF a reactor scram is required, and reactor power is >5%, and Power/Level Control is required, THEN terminate and prevent injection until conditions allow reinjection.

{BWROG RPV 6.3}

4. #7: lF performing ATWS Power/Level Control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems. {BWROG RPV 5.5}

Filename:2_esg TR-AA-230-1 003-F06 Revision 0 Page 24 of 25

NEXTETA"

,Y,& NRC lNlTAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG CREW GRADING ATTACHMENT ESG 2 Rev. __ !_ Date Operator Name Position Evaluator OSM CRS STA 1C05 1C03 B.O.P Management Representative/Lead Evaluator I Crew Critical Tasks Task Statement SAT UNSAT

1. lF a scram is required and reactor power is above 5%, THEN reduce power below 5% using one or more of the following methods:

. lnserting control rods using RlPs

2. lF a reactor scram is required and the reactor is not shutdown under all conditions, THEN lockout ADS before automatic actuation. (Potential)

3. lF a reactor scram is required, and reactor power is >5%, and Power/Level Control is required, THEN terminate and prevent injection until conditions allow reinjection.

4. lF performing ATWS Power/Level Control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems.

Fílename:2_esg TR-AA-230-1 003-F06 Revision 0 Page 25 ol 25

SURVEILLANCE TEST PROCEDURE STP 3.8.1-0 1 DAE,C DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

1of 5

1 1 Usage Level CONTINUOUS Record the following: Date / Time: l _lnitials NOTE: IJser shatt perform and document a Temp lssue / Rev. Check to ensure revision is current, in accordance with procedure use and adherence requirements.

Prepared By: Date Print Signature cRoss-DlsclPLlNE REVIEW (AS REQUIRED)

Reviewed By: Date Print Signature Reviewed By: Date Print Signature Reviewed By: Date Print Signature PROCEDURE APPROVAL Approved By I Date Print Signature

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

2of11 5

1.0 PURPOSE 1.1 This STP verifies correct breaker alignment and indicated power availability for each offsite circuit capable of supplying the onsite Class 1E AC Electrical Distribution System.

1.2 This STP is routinely performed with both offsite circuits available, or in response to the condition of one offsite circuit or one diesel generator inoperable.

2.0 BRIEFING INFORMATION 2.1 PERFORMANCE I NFORMATION 2.1.1 Section 7.0 of this STP contains two (2) sections that cover the anticipated conditions under which this STP will be performed. The STP is organized as follows:

Sect. Conditions 7.1 Both Offsite Circuits Available 7.2 One Offsite Circuit Available Only one of these sections should need to be performed to satisfy the performance requirements associated with this STP. All steps within a particular section are to be performed in sequence and the STP steps carried through to completion, unless stated othenruise.

2.1.2 Personnel recommended to perform this procedure:

1 Operations 2.1.3 Special Test Equipment required:

1 Marking Pen (Do not use light colored hi-lighters or markers. Use only dark colored pens or markers. See General Caution 2,2.1).

2.2 GENERAL CAUTIONS 2.2.1 lf utilizing a paper copy of this surveillance, do not use light colored hi-lighters or markers to record data, outline configurations on drawings or to initial steps.

Light-colored hi-lighters are not dark enough to reproduce adequately as the QA record. Not applicable when using electronic copies.

2.3 SPECIAL PRECAUTIONS 2.3.1 None

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

3 of 5

11

3.0 REFERENCES

3.1 Applicable drawings:

3.1.1 BECH-E001<1>

3.1.2 BECH-E005 3.1.3 BECH-E023 3.2 Supporting documents:

3.2.1 NG-97-2146 4.0 GENERAL INSTRUCTIONS 4.1 Steps marked with a "TS" immediately to the right of the step sign-off line are required by Technical Specifications. lf these steps do not meet their acceptance criteria or cannot be performed, a NRC reportable condition may exist and shall be reported to the Control Room Supervisor (CRS) immediately.

4.2 lf any equipment or components are observed to be in a state of disrepair during the performance of this STP, appropriate corrective maintenance shall be initiated.

4.3 An Action Request (AR) should be completed for any problems encountered with "TS" marked steps during the performance of this test.

4.4 The CRS shall be notified immediately and the appropriate Limiting Conditions for Operation section of Technical Specifications referred to whenever problems are encountered during the performance of this STP.

5.0 APPENDICES None

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

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Prerequisites Performance Date: INITIALS 6.0 PREREQUISITES 6.1 Verify Offsite power is supplying essential buses 143 and 1A4 via either the startup transformer (normal source) or the standby transformer (alternate source).

6.2 Evaluate electrical system status and select the STP section which is to be performed:

t I Section 7.1 - Both Offsite Circuits Available t 1 Section 7.2 - One Offsite Circuit Available

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

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11 Performance Date INITIALS 7.0 PROCEDURE 7.1 BOTH OFFSITE CIRCUITS AVAILABLE NOTE lnformation from the Load Dispatcher may be needed to complete the following step.

7.1.1 Using the guidance below and Attachment 1, identify two separate circuits available to transmit power from the offsite power sources to the essential buses.

a. Based on equipmenVsystem lineup and operational status, use a dark marking pen to trace an available circuit from an offsite power source to the Startup Transformer supply breakers, 1A302 and 14402.

b. Based on equipmenVsystem lineup and operational status, use a dark marking pen to trace a second circuit from another offsite power source to the Standby Transformer supply breakers, 1A301 and 14401 such that it does not share any lines, buses, or transformers in common with the circuit to the Startup Transformer supply breakers.

c. Based on equipmenVsystem lineup and operational status, complete the electrical lineup by using a dark marking pen to trace the connections from each Essential Bus (143 and 'tA4) to the Startup or Standby Transformer supply breaker currently feeding the bus.

7.1.2 Confirm two (2) independent offsite circuits are available by initialing one of the two sets of statements below and N/A'ing the other:

a. A circuit exists from an offsite power source, through the TS Startup Transformer and its supply breakers to both 143 and 1A4 essential buses; AND A second independent circuit exists from a different offsite source, through the Standby Transformer to its supply breakers.

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

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Performance Date INITIALS

b. A circuit exists from an offsite power source, through the TS Startup Transformer and one of its supply breakers to either the 1A3 or 1A4 essential bus; AND A second independent circuit exists from a different offsite source, through the Standby Transformer and one of its supply breakers to the other essential bus.

(PRTNT / SrGN)

I I

I Performed by: Date: Time: lnit

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAE,C DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

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Performance Date INITIALS 7.2 ONE OFFSITE CIRCUIT AVAILABLE NOTE lnformation from the Load Dispatcher may be needed to complete the following step.

7.2.1 Using the guidance below and Attachment 1, identify a circuit available to transmit power from an offsite power source to the essential buses.

a. Based on equipmenVsystem lineup and operational status, use a dark marking pen to trace an available circuit from an offsite power source to the Startup Transformer supply breakers, 14302 and 1A402 or Standby Transformer supply breakers, 14301 and 14401.

b. Based on equipmenUsystem lineup and operationalstatus, complete the electrical lineup by using a dark marking pen to trace the connections from the required Essential Bus(es)

(143 and/or 1A4) to the Startup or Standby Transformer supply breakers.

7.2.2 lf in Mode 1,2 or 3, mark Step 7.2.4 "N/A" and proceed with the performance of Step 7.2.3.

OR lf in Mode 4 or 5, or during movement of irradiated fuel assemblies in the Secondary Containment, mark Step 7.2.3 "N/4" and proceed with the performance of Step 7.2.4.

7.2.3 Confirm an offsite circuit exists from an offsite power source, TS through either the Startup or Standby Transformer and its associated supply breakers to both 1A3 and 144 essential buses.

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAE,C DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

I 5

of 11 Performance Date: INITIALS 7.2.4 Confirm an offsite circuit exists from an offsite power source by initialing one of the two statements below and "N/A'ing" the other:

a. An offsite circuit exists from an offsite power source, through TS either the Startup or Standby Transformer and its associated supply breakers to both 1A3 and 144 essential buses.

b. An offsite circuit exists from an offsite power source, through TS either the Startup or Standby Transformer and one of its associated supply breakers to the required lA3 or 144 essential bus.

(PRTNT / SrGN)

I I

I Performed by: Date Time: lnit.

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

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Performance Date: INITIALS 8.0 ACCEPTANCE CRTERIA 8.1 lndicate the reason for performing the STP:

t I Routine with both offsite circuits available t I Routine with one offsite circuit available while in Mode 4 or 5 or during movement of irradiated fuel assemblies in the secondary containment t I Action in response to one offsite circuit inoperable t I Action in response to one diesel generator inoperable t I Other, explain below:

8.2 All Technical Specification required items, as indicated by "TS", have been performed satisfactorily:

8.2.1 Section 7.1 ( ) YES ( ) NO + CRS notified 8.2.2 Section 7.2 ( ) YES ( ) NO + CRS notified 8.3 All other items checked in this test have been performed satisfactorily:

8.3.1 Section 7.1 ( ) YES ( ) NO = CRS notified 8.3.2 Section 7.2 ( ) YES ( ) NO + CRS notified

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAE,C OUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.

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11 Performance Date INITIALS 8.4 lndicate any relevant test comments below, othenruise mark this step "N/4" (PRTNT / SrGN)

I Operations Date 9.0 ATTACHMENTS 9,1 Attachment I - DAEC Offsite Power Circuits Feeding Essential Buses

SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page '11 o 11 Rev. 5 Attachment 1 DAEC OFFSITE POWER CRCUITS FEEDING ESSENTIAL BUSES Sheet 1 of 1 7510 Dysart Sub Power Source Breaker Transformer Bus 5950 5560

AB" "K' Downtown lndustriâl Line Unacceptable path for the of this STP 16lKV West 1A 1A Bus 301 302 345KV West Bus 67E0 "s"

Hills 1A3 Sub 31 10 0220 8490 T,I "8"

Hzelton 144 Sub 2690 "D"

East Bus 9180 161KV East 1A Bus 401 402 Hawatha Sub 8090 5550 Ferfex Sub

SURVEILLANCE TEST PROCEDURE STP 3.8.1-02 DAE,C DUANE ARNOLD ENERGY CENTER TITLE ONE STANDBY DIESEL GENERATOR INOPERABLE Page Rev.

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Usage Level CONTINUOUS Approved fo, i!lg[1@] printing lF NO Temporarv Chanqes are in effect for this procedure.

Record the following: Date / Time I lnitials:

NOTE: A check to ensure current revision and no temporary changes shall be performed and documented every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months if active document use exceeds a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period as determined from the date and time recorded above.

Prepared By: I Date:

Print Signature cRoss-DtsctPlrNE REVTEW (AS REQUIRED)

Reviewed By: I Date Print Signature Reviewed By I Date:

Print Signature Reviewed By I Date:

Print Signature PROCEDURE APPROVAL BY QUALIFIED REVIEWER Approved By I Date:

Print Signature

SURVEILLANCE TEST PROCEDURE STP 3.8.1-02 DAE,C DUANE ARNOLD ENERGY CENTER TITLE ONE STANDBY DIESEL GENERATOR INOPERABLE Page Rev.

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7 1.0 PURPOSE 1.1 The purpose of this test is to implement the REQUIRED ACTIONS of LCO 3.8.1 when one Diesel Generator is inoperable.

1.2 This procedure also provides instructions for scheduling and performance of SR 3.8.1 .1 and SR 3.8.1.2 in accordance with LCO 3.8.1 Action 8.1 and Action 8.4, respectively.

2.0 BRIEFING INFORMATION 2.1 PERFORMANCE INFORMATION 2.1.1 Testing is organized as follows:

STP Sections Evolution 7.1 Required Actions For LCO 3.8.1, Condition B 7.2 Other Actions For One SBDG lnoperable 2.1.2 Personnel recommended to perform this STP:

1 Operations 2.1.3 Special Test Equipment required:

None 2.2 GENERAL CAUTIONS 2.2.1 None 2.3 SPECIAL PRECAUTIONS 2.3,1 None

3.0 REFERENCES

3.1 Associated STPs:

3.1.1 STP 3.8.1-01 3.1.2 STP 3.8.1-03 3.2 ODI-8, LCO Surveillance Log and Flag 4.0 GENERAL INSTRUCTIONS 4.1 The Control Room Supervisor (CRS) shall be notified immediately and the appropriate Limiting Conditions for Operations section of Technical Specifications referred to whenever problems are encountered during the performance of this STP.

SURVEILLANCE TEST PROCEDURE STP 3.8.1-02 o DAEC DUANE ARNOLD ENERGY CENTER TITLE ONE STANDBY DIESEL GENERATOR INOPERABLE Page Rev.

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5.0 APPENDICES 5.1 None

SURVEILLANCE TEST PROCEDURE STP 3.8,1-02 DAEC DUANE ARNOLD ENERCY CENTER TITLE ONE STANDBY DESEL GENERATOR INOPERABLE Page Rev.

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Prerequisites Performance Date INITIALS 6.0 PREREQUISITES 6.1 None

SURVEILLANCE TEST PROCEDURE STP 3.8.1-02 DAEC DUANE ARNOLD ENERGY CENTER TITLE ONE STANDBY DIESEL GENERATOR INOPERABLE Page Rev.

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Performance Date INITIALS 7.0 PROCEDURE 7.1 REQUIRED ACTIONS FOR LCO 3.8.1, CONDITION B 7.1.1 Enter the appropriate component designator in space provided below (N/A any non-applicable condition):

Diesel Generator is INOPERABLE AND/OR ESW Subsystem is INOPERABLE NOTE Step 7.1.2 must be performed within one (1) hour of determining that one diesel generator has become inoperable.

7.1.2 Perform STP 3.8.1-01 7.1.3 Schedule performance of STP 3.8.1-01 within 1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of the completion of Step 7 .1 .2 in accordance with ODI-8.

NOTE ln reference to the following step, initial diesel generator operability testing must be performed within seventy-two (72) hours of declaring a diesel generator inoperable and once every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months thereafter. Not required to be performed when the cause of the inoperable DG is preplanned, preventive maintenance and testing.

7 .1.4 Prepare and place LCO Surveillance Due Flags (Green Cards),

requiring the performance of STP 3.8.1-03 on the operable diesel generator. Mark this step N/A if the cause of the inoperable DG is preplan ned, preventive mai ntenance and testing.

NOTE Step 7.1.5 must be performed within four (4) hours of discovery that one diesel generator is inoperable concurrent with inoperability of redundant required feature(s).

7.1.5 Declare required feature(s), supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable

SURVEILLANCE TEST PROCEDURE STP 3.8.1-02 DAE,C DUANE ARNOLD ENERGY CENTER TITLE ONE STANDBY DIESEL GENERATOR INOPERABLE Page Rev.

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Performance Date: INITIALS NOTE Step 7.1.6 must be performed within twenty-four (24) hours of determining that one diesel generator has become inoperable. Step 7.1.6 performs an evaluation to demonstrate that the remaining diesel is not susceptible to the same condition(s) that rendered the first diesel inoperable.

7.1.6 Perform an evaluation on the remaining diesel, verifying that the remaining diesel is not susceptible to the same condition(s) that rendered the first diesel inoperable. List and describe any analysis and/or inspection(s) performed to prove continued operability of the remaining diesel in the spaces provided below (attach additional sheets if necessary):

(Attach copy[ies] of supporting documents to the back of this STP)

Performed by: Date: Time 7.2 OTHER ACTIONS FOR ONE SBDG INOPERABLE 7.2.'l lF the associated SBDG or ESW support subsystem are/will be unavailable, THEN verin7 the 1K-1 Backup lnstrument Air Compressor is aligned to be powered from the operable SBDG per Ol 518.1 .

Performed by: Date Time

SURVEILLANCE TEST PROCEDURT STP 3.8.1-02 DAEC DUANE ARNOLD ENERGY CENTER TITLE ONE STANDBY DIESEL GENERATOR INOPERABLE Page Rev.

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Performance Date: INITIALS 8.0 ACCEPTANCE CRITERIA 8.1 lf this STP is performed for any reason other than for satisfying the PURPOSE as stated in Section 1.0, indicate below (othenruise mark this step "N/4"):

8.2 All steps of this STP have been performed satisfactorily:

( )YES ( )NO +CRSnotified 8.3 lndicate any relevant test comments below, othenruise mark this step "N/4":

Operations Date Surveillance Coordinator Date 9.0 ATTACHMENTS 9.1 None

NEXTETA'

,Y1. SIMULATOR EXERCISE GUIDE SEG SITE: DAEC Revision #: 0 LMS ID: PDA OPS ESG 3 LMS Rev. Date: N/A SEG TITLE: NRG lNlTlAL LICENSE EXAM, SCENARIO #3 SEG TYPE: n Training X Evaluation PRocRAM: nLOCT XLOIT nOther:

DURATION: -90 minutes Developed by:

lnstructor/Developer Date Reviewed by:

I nstructor (l nstructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date Filename:3_esg TR AA-230-1003-F06 Revision 0 Page 1 of 32

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=Y6 NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective This Evaluation Scenario Guide evaluates the Operators' ability to:

"Given the malfunctions presented in this ESG, the students will protect the public, protect plant personnel, and protect plant equipment, in accordance with plant procedures."

Enabling Evaluation Guide, no tasks are trained. Evaluated tasks are listed on page 4 Objectives:

Prerequisites: None Training A. Simulator Resources: B, Evaluation team

c. Operations Management Representative D. Simulator Driver E. Phone Talker F. Exam Proctor for custody of the crew between scenarios G Simulator Video recording equipment

References:

A. AOP 255.1, Rev. 46 J, ARP 1C064, rev 70 B. AOP 672.2, rev.37 K. ARP 1C078, rev 89 C. AOP 901, Rev. 29 L. ED, Rev.10 D. ARP 1C034, Rev.54 M, EOP 1, Rev. 19 E. ARP 1C038, rev 41 N. EOP 3 EOP 4, Rev. 21 F. ARP 1C03C, rev43 O. Ol 255, Rev. 89 G. ARP 1C048, Rev. 80 P. O1414. Rev.40 H. ARP 1C05A, Rev. 81

l. ARP 1C058, Rev. 104 ProtectedContent: None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance Operating N/A Experience:

Risk Significant Operator Actions:

Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page2 of 32

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,YSx6 NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TASKS ASSOCIATE WITH SIMULATOR EXERCISE GUIDE Task # Task Title Reactor Operator 95.71 Perform Actions of EOP 4 95.72 Reduce Offsite Radioactivity Release Rate with a Primary System Discharging Outside of Containment 95.45 Perform initial EOP 1 actions (RC) 95.44 Perform actions of RC/L of EOP 1 95.46 Perform actions of RC/P of EOP 1 95.20 Perform Defeat 11 95.80 Perform an Emeroencv Depressurization Usinq SRVs 95.68 Perform Actions of EOP3 for High Area Temp, Rad, Water Level lncluding EOP 1 and ED 95.69 Manually lnsert A Scram Before Any Area Parameter Reaches Maximum Safe Operatinq Limits 95.70 Perform actions of EOP 3 for hi area temp, rad, and water level including commencement of plant S/D.

93.21 Perform a Fast Power Reduction 94.22 Respond to Earthquake Condition 94.02 Respond to Abnormal Control rod Movement/lndication Senior Reactor Operator 6.72 Direct Crew Response for Performance of EOP 4 6.21 Direct Crew Response for performance of Defeat 11 6.45 Direct Crew Response for performance of initial EOP 1 actions (RC) 6.44 Direct Crew Response for performance of the RC/L leg of EOP 1 6.46 Direct Crew Response for performance of RC/P leg of EOP 1 6.78 Direct Crew Response for performance of Emergency Depressurization 6.68 Direct Crew Response for performance of EOP 3 for high area temperatures/radiation /water level including commencement of a plant shutdown 6.67 Direct Crew Response for performance of EOP3 for high area temperature/radiation/water level including EOP 1 and ED 5.22 Direct Crew Response to Earthquake Condition 5.02 Direct Crew Response to Abnormal Control rod Movement/lndication 4.07 Recommend Mitigation Strategies for Accidents Ps) 4.08 Verifv EAL determination 4.09 Perform internal and external notifications UPDATE LOG: lndicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update lna form TR-M-230-1 003-F1 6.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE See Cover lnitial development for lnitial development for 2017 NRC N/A Rev.0 2017 NRC LOIT LOIT Examination See Cover Examination Filename:3_esg TR-AA-230-1003-F06 Revision 0 Page 3 of 32

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=Y6 NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG OVERVIEW / SEQUENCE OF EVENTS SEQUENCE OF EVENTS Event # Description Eastern lowa has the potential for severe weather. Several strong storms are forming in the Dakota's and Western Minnesota. "4" Core Spray is out of service for replacement of the breaker overcurrent relay. Work expected to finish tomorrow morning with operability run on days tomorrow. LCO 3.5.1 Condition B, day 2 of 7. The crew will be briefed as to the need to switch running RBCCW pumps and lower 5o/o to assist in PPC Maintenance and HPCI testing.

1 After alternating RBCCW pumps and power reduction an OBE Earthquake occurs and the crew enters AOP 901.

2 Due to the OBE, PS4549, RPS ChannelA HiVessel Pressure Scram and LLS Arming switch fails resulting in a half scram. The Crew will recognize that C71A-K5A Relay is not energized due to a failure of PS-4549, High Reactor Pressure, relay causing an 'A' RPS AUTO SCRAM signal. The crew will enter Tech Spec LCO 3.3.1.1 RPS lnstrumentation Condition A - Function 3.

3 A single Control Rod scrams in during the half scram. The crew will enter AOP 255.1 and 255.2 to respond to the control rod abnormal. The crew will enter Tech Spec LGO 3.1.3 Control Rod OPERABILITY Gondition C.

4 The crew will respond to a steam leak from RCIC, Enter EOP 3, and attempt to isolate the leak. The lnboard RCIC Steam Line lsolation MO-2400 will develop a thermal overload and RCIC Outboard Steam Line lsolation MO-2401 will not close; this will cause RCIC room temperature will exceed max normal and will approach max safe. The crew will insert a manual reactor scram prior to temperatures exceeding max safe. (CRITICAL) After the scram, the thermal overload for MO-2400 will reset.

5 The Crew will recognize a fuel leak and enter AOP 672.2.

6.

A steam leak develops in the RWCU room. Group 5 automatic actions failto occur, however, the leak can be isolated by closing the valves from the control room. (CRITICAL) 7 A steam leak will be reported from the Turbine Building. The crew will attempt to shut the MSIVs but will discover that 'A' MSIVs fail to close. This results in the crew to take action IAW EOP 4 and perform an ED prior to reaching a GE Release Rate. (CRITICAL) 8.

After the ED, when the crew has depressurized the RPV and is recovering RPV Water level to the directed band, the scenario is complete.

Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page 4 of 32

NEXTETA" NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG

=Yr6 SIMULATOR SET UP INSTRUCTIONS

1. Set NRC Exam Security for the Simulator per QF-1071-08

2. Perform simulator set up per TDAP 1839 Attachment 2, Simulator Setup Checklist,

3. Load the saved lC (in folder with this ESG) to a SNAPSHOT reset to that SNAPSHOT and place the Simulator in RUN, OR

4. Reset to lC 20, place the simulator in RUN and perform the following:

a. lnsert Event Triggers, Malfunctions, Overrides, and Remotes per the tables below

5. COPY the Schedule Files listed below from the folder with this ESG to the S \TRex-D u a ne\Li g htn ng\S ched u le d rectory.

i i

6. RUN Schedule File "lLT3Actions,sch" and LEAVE lT RUNNING.

7. VerifyMalfunctions.

8. Verify Remotes (Note that environmental remotes will already be timing)

9. Verify Overrides.

10. Startup Thundersound in Earthquake mode

a. At the right side instructor station computer in the booth, select THUNDERSOUND from the Toolbar.

b. Select EARTHQUAKE from the popup window.

c, Toggle the red stop square to the green arrow.

d. Verify the computer volume is turned up to at least 35.

11 . Ensure MOL pull sheet is in the 1C058 hanging file.

12. Establish EOOS conditions for OOS components and plant conditions

13. Place clearance tags on 1C03 "A' Core Spray system mimic as follows:

a. Place MIP tag on HS2103, CORE SPRAY PUMP 1P211A handswitch

b. Place a maintenance/testing border on 1C034 (A-9)

c. Make'A'Core Spray Loop UNAVAILABLE in EOOS.

d. Hang Guarded EquiPment tags on:

(1) RHR Pumps'B'&'D' (2) Core SPraY LooP'B' (3) 'B',ESW (4) 'B',SBDG (5) 1p.4 (6) 1B,4 (7) 1844 (8) 1V-AC-11 Flename:3_esg TR-AA-230-1 003-F06 Revision 0 Page 5 of 32

NEXTETA' NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG

=Yjçt,&

EVENT TRIGGER DEFI NITIONS:

Trigger No. Trigger Logic Statement Trigger Word Description 1,3,5,7,9, MANUALLY ACTIVATED MANUALLY ACTIVATED 12,14,16 18 yp_mms24c == 1 RX BLDG SUPPLY FNA 1V-SF-1OC 20 msvpcv4413 <= .95 21040 OUTBOARD MSIV STM LINE A 22 RPDISIRUN(1) != 1 Reactor Mode Switch out of RUN 24 RRPRV < 880 RPV Pressure < 880 26 YCASL5S >= 30 RWCU HX Room Temperature > 130F 28 cuvpmo2700 <= .05 I cuvpmo2701 <= .05 RWCU ISOLATION 30 ZAORMRl4448A >= .490000 A STEAM LINE RAD MONITOR Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page 6 of 32

NEXTCTA'

=Ysr6 NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG I MALFUNCTIONS:

Final Time Malf. No. Malfunction Title ET Delay Ramp lnitialValue Value CORE SPRAY PUMP TRIP- CORE SPRAY PUMP A ACTIVE ACTIVE Setup CSOlA TRIP Setup CSO5A CORE SPRAY PUMP A - FAILURE TO AUTO-INITIATE ACTIVE ACTIVE 1C03A (A-09) 'A' CORE SPRAY PUMP 1P-2114 TRIP ON Setup AN1C03A(e) ON OR MOTOR OVERLOAD Setup MSOSA MSIV DISC FAILURE- INBD MSIV A 100 100 MS28A cRoup 5 tsoLATroN vALVE(s) FAIL(S) TO CLOSE-ACTIVE ACTIVE Setup M02700 GROUP 5 TSOLATTON VALVE(S) FAIL(S) TO CLOSE- ACTIVE ACTIVE Setup M528B MO2701 GROUP 5 TSOLATTON VALVE(S) FAIL(S) TO CLOSE- ACTIVE ACTIVE Setup M528C MO2740 GROUP 6 TSOLATTON VALVE(S) FAIL(S) TO CLOSE- ACTIVE ACTIVE Setup MS31B M02401 Setup RClOA MO24OO THERMAL OVERLOAD BREAKER TRIP ACTIVE ACTIVE RCIC ROOM COOLER ESW FLOW BLOCKAGE- 1V- 3 5 SEC 0 100 Setup SWl4A AC-154 RCIC ROOM COOLER ESW FLOW BLOCKAGE. 1V- 3 5 SEC 0 100 Setup SW148 AC-158 etup RC06 RClC STEAM SUPPLY LINE BREAK (RCIC ROOM) 3 1O SEC 07:00 0 25 RCIC STEAM SUPPLY LINE BREAK (RCIC ROOM) 18 10 SEC 07:00 0 75 Setup RC06 NEW Setup D228 BREAKER TRIP 1D1401 FOR MO24O1 14 INACTIVE ACTIVE COOLANT LEAKAGE OUTSIDE THE PRIMARY 0 1.5 Setup cu10 CONTAIMENT 22 2:00 07:00 MSL RUPTURE OUTSIDE PRIMARY CONTAINMENT. 28 04:00 02:00 0 0.5 Setup MSO4A STM LINE A Setup RXOl FUEL CLADDING FAILURE 30 05:30 20:00 0 0.01 Setup TC06A TURBINE BYPASS VALVE FAILURE- BV-1 24 0 0 Setup TC06B TURBINE BYPASS VALVE FAILURE- BV-2 24 0 0 Setup MSO5B MSIV DISC FAILURE- OTBD MSIV A 100 100 RM5945 KAMAN 2 TB NORM MONITOR 28 4:00 30 AS IS 0.005 Setup RM09RM5945 SEC FAILURE RM5945 KAMAN 2 TB NORM MONITOR 28 4:30 2:30 AS IS 0.031 Setup RMO9RM5945 FATLURE (NEW)

RM5945 KAMAN 2 TB NORM MONITOR 28 7:OO 5:00 AS IS 0.061 Setup RMO9RM5945 FAILURE (NEW)

RM5945 KAMAN 2 TB NORM MONITOR 28 12:00 10:00 AS IS 0.62 Setup RMO9RM5945 FAILURE (NEW) 1C058 (E-08) PCIS GROUP'5' ISOLATION 26 CRYWOLF ON Setup AN1C05B(40) INITIATED Filename: 3_esg TR-AA-230-1003-F06 Revision 0 PageT of32

NEXTETA" ENERGYø2 NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG tugt REMOTES lnitial Final Time Remote No. Remote Title ET Delay Ramp Value Value TURBINE BUILDING EXHAUST FAN 1V-EF-214 - HS- MAN Setup HVO9 1 MAN 5945 Setup FPOS RCIC DELUGE MAN ISOLATION VALVE V-33-84 1 OPEN CLOSE OVERRIDES:

lnitial Final Time Override No Override Title ET Delay Ramp Value Value E21R700A CORE SPRAY PUMP 1P-2114 (0-150 0 0 Setup AO-CS-002 AMPS)

Setup Dt-cs-008 HS-2103 PUMP 1P-2114 STOP STOP Setup DO-CS-003 HS-2103(1) PUMP 1P-2114 (WHlrE) OFF OFF Setup DO-CS-004 HS-2103(2) PUMP 1P-2114 (GREEN) OFF OFF Setup DO-CS-006 HS-2103(4) PUMP 1P-2114 (RED) OFF OFF Setup DO-CS-005 HS-2103(3) PUMP 1P-2114 (AMBER) OFF OFF Setup Dt-HV-006 HS-5928 TURB BLDG ROOF EXH FANS 1V-REF-20127 AUTO AUTO HS-5948 TB EXH FAN LEAD SEL (A&B-FAN,B&C- AB AB Setup Dt-HV-007 FAN,C&A-FAN)

Setup Dt-HV-033 HS-6516 TURB BLD SPLY FAN 1V-SF-224 START START Setup Dt-HV-034 HS-6517 TURB BLD SPLY FAN 1V-SF-228 START START Setup Dt-RC-008 HS-2401 OUTBD STM LINE ISOL. VLV AUTO AUTO Setup AO-FW-o15 FI-4408 STEAM FLOW A - FI-4408 20 02:00 As-ls 8 PCIS-LAIRWCU PCIS GROUP 5 A LOGIC ISOLATION 26 OFF ON Setup DO-MS-192 SIGNAL RWCU PCIS-LBIRWCU PCIS GROUP 5 B LOGIC ISOLATION 26 OFF ON Setup DO-MS-212 SIGNAL RWCU Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page 8 of 32

NEXTETA" NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev.0 SEG

=Yr6 SCHEDULE FILES:

lLT3Actions.sch

@ Time Event Action Description Setup 1 lnsert malfunction zz01 delete in 20 0.01 G Recorders Operating lnsert malfunction zz01 delete in 30 after 0.01 G Recorders Operating Setup 1 30 lnsert malfunction zz02 delete in 50 after Setup 1 Operating Basis Earthquake Event 30 Setup 1 lnsert malfunction RR38A after 40 RPV PRESS SWITCH PS4549 FAILURE Setup 1 lnsert malfunction rd081807 after 40 CONTROL ROD SCRAMS- ROD 18-07 I nsert malfu nction rm02 re4448a to Setup 28 RE-44484 MAIN STEAM LINE A 49.00000 in 120 after 180 I nsert malfunction rm02re4448c to Setup 28 RE-4448C MAIN STEAM LINE C 45.00000 in 120 after 180 lnsert malfunction rm02re444ib to Setup 28 RE-44488 MAIN STEAM LINE B 44.00000 in 120 after 180 lnsert malfunction rm02re4448d to Setup 28 RE-4448D MAIN STEAM LINE D 45.00000 in 120 after 180 lnsert malfunction rmO1re9158 to 55.00000 Setup 28 RE-9158 CONDENSATE PUMP AREA in 00 after 180 lnsert malfunction rmO1re9159 to 59.00000 RE-9159 REACTOR FEED PUMP AREA Setup 28 in 600 after 180 lnsert malfunction rmO1re9160 to 61.00000 Setup 28 RE-9160 TURBINE LUBE OIL AREA in 600 after 180 lnsert malfunction rmO1re9179 to 57.00000 RE-9179 TURBINE FRONT STANDARD Setup 28 in 600 after 180 Setup 22 Delete malfunction RC1 0A MO24OO THERMAL OVERLOAD BREAKER TRIP Modify malfunction rm02re4448a to 55 in RE.4448A MAIN STEAM LINE A 30 300 Conduct simulator crew pre-scenario brief using TR AA-230-1007-F06, Simulator lnstructor Pre-Exercise Checklist lf surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page 9 of 32

NEXTETA

NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG

=Y*txg SHIFT TURNOVER INFORMATION

. Today, Night Shift o Temperatures in the 80's. Eastern lowa has the potential for severe weather. Several strong storms are forming in the Dakota's and Western Minnesota, o Plant power -100o/o, with corresponding MWe, MWth, and core flow o Protected Train - "8"

. Procedures or major maintenance in progress:

o "4" Core Spray is out of service for replacement of the breaker overcurrent relay. Work 0

"T;" ff : i,ii"i i:i tii: :ff i:l i":i ii:, ll i; ",,

. Technical Specification Action statements in effect:

^

o DAEC is in compliance with all LCO's o A" Core Spray is out of service for replacement of the breaker overcurrent relay. Work expected to finish tomorrow morning with operability run on days tomorrow. LCO 3.5.1 Condition B, daY 2 of 7 .

o Plant PRA Status o CDF: 1.34 x 10-6, GREEN, I year to Yellow ICDP o LERF 3.27 x l0-7, GREEN, 1 year to Yellow ILERP o Evolutions in progress or planned for upcoming shift:

o Alternate running RBCCW pumps from 'B' & 'C' running to 'A' & 'C' running for motor inspections on 'B' RBCCW pump IAW Ol 414 SectionT .1.

o Lower power by 5o/o IAW lPOl 3, Power Operations (35o/o-100% Rated Power) to assist in PPC Maintenance and HPCI testing

. RE recommends only lowering Rx Recirc by l Mlbm/hr due to load line concerns a Comments, problems, operator workarounds, etc.

o One extra NSPEO available in Work Control o Radwaste Operator is NSPEO qualified Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page 10 of 32

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=Yry NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSÉ Switch running CREW RBCCW pumps . Switch running RBCCW pumps IAW Ol 414 section 7.1 RO When Booth Gommunicator: . Place the Standby RBCCW pump handswitch on 1C06 in the START contacted as position Acknowledge the request.

any dept. in organization:

. Verify that the Standby RBCCW pump starts

. Place the handswitch for the RBCCW pump that is to be secured in the STOP position

. Verify that RBCCW Pump Disch Header LO Pressure (1C068, D-3) is reset o Place the handswitch for the secured RBCCW Pump in AUTO CRS o The CRS will direct switchinq runninq RBCCW Pumps lPot 3 CREW

. Lower reactor power by 5o/o to assist in PPC Maintenance and HPCI testing RO

. Lower reactor power by 5o/o IAW lPOl 3 as follows:

o At 1C04, reduce RECIRC MG SET A and B SPEED CONTROL in small equal increments to lower core flow by approximately lMlb/hr, maintaining balanced Recirc lop flow, while closely monitoring the Power to Flow Map, so as not to exceed MELLLA, as directed by the CRS/OSM.

. lnsert control rods per the cunent Control Rod Withdrawal Sequence Sheets to lower power by approximately 40 MWth or as directed by the CRS/OSM.

CRS o Direct and observe reactivity manipulations to achieve a 5Yo reduction in reactor power Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page11ot32

NEXIera"

=Yry NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Earthquake CREW

. Enter and carry out the actions of AOP 901, Earthquake.

After the crew reduces power Simulator Operator CRS by -5o/o and at the direction of AGTIVATE ET 1 o Direct Crew Response to an Earthquake Condition.

the floor This will cause the 0.01G recorder alarm to . lF the amber DESIGN BASIS EARTHQUAKE, or amber OPERATING instructor: run; and then, 30 seconds later, an OBE BASIS EARTHQUAKE lights are ON, and not a malfunction, THEN with additional malfunctions. commence shutting down the reactor to be in cold shutdown within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The following scripts are on Booth Gommunicator: o Enter EOP 2 T/L on High/Low Torus Water Level (may be administratively exited).

the following HPCI Suction Swap/Torus LevelAlarms -

pages: Pg. 15 o Direct Health Physics to perform radiation surveys of the normally PS-4549/Half Scram Pg. 16 accessible areas inside DAEC Buildings, and the site grounds including HCU 18 Pg. 17118 the lndependent Spent Fuel Storage lnstallation.

. Direct chemist to review KAMAN data and perform sensor checks.

o Direct control room operators monitor the control room panels for changes in some of the following critical plant parameters When contacted as any dept. in Booth Communicator:

organization:

Acknowledge the request.

Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page 12 o1 32

NEXTETA' F:NEFGY ¿Z NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG

--- n

-m TIME/NOTES INSTRUCTOR ACTVITY EXPECTED STUDENT RESPONSE lf contacted as Booth Communicator: CREW Duty Station Acknowledge the request.

. Enter and carry out the actions of AOP 901, Earthquake Manager:

RO o Respond to an Earthquake Condition.

. Monitor reactor power, pressure, and level on 1C05.

lf contacted as Booth Gommunicator: o Monitor for any Control Rod out of position.

HP or Acknowledge the request.

o At 1C06, verify River Water Supply system integrity by:

Chemistry: . Verify all available RWS pumps will start and deliver >6000 gpm flow.

. Using HS 4918, RIVER WATER SUPPLY LOOP SELECT switch, Booth Gommunicator: select A CV4915 and B CV4914, one at a time, to verify RWS lf contacted as an in-plant Acknowledge the request to perfrom makeup flow can be established with each loop ensuring RWS operator: inside and outside plant walkdowns. piping is intact.

Keep track of which operator has been o Monitor Process and Area Radiation Monitoring System channels on sent to what location in the plant. Panels 1C10 and 1C11.

. Send operators, with portable radiation monitors, to perform a quick walk through of the plant to determine the general condition of the plant structure and system's integrity, and immediately report back any damage to the Control Room.

Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page 13 of 32

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,Yra,¿k NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Earthquake CREW a Respond to the HPCI Suction Transfer annunciator 1C03C D-4 HPCI Suction RO Swap

. Confirm the Torus high level condition at 1C03 on Ll-43974 / B WR TORUS LEVEL indicators, or at 1C09 on LR-43964 / B TORUS LEVEL.

o Verify the AUTOMATIC ACTIONS have occurred.

. lf Hl TORUS LEVEL is confirmed, then enter EOP-2 (Primary Containment Control). /

CRS a Enter EOP 2 on T/L (may be administratively exited)

Earthquake CREW a Respond to the Torus Level annunciator 1C038 (D-9)

Torus Level RO Alarms a Monitor the Torus level on URS 4384 (Channel 3) and UR 4385 (Channel 2) at 1C29 or LR4396A/B at 1C09.

a Verify the AUTOMATIC ACTIONS have occurred.

CRS a Enter EOP 2 on T/L (may be administratively exited)

Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page 14 of 32

NEXTETA*

=Ysg NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TME/NOTES INSTRUCTOR ACTVITY EXPECTED STUDENT RESPONSE Segment 1 Evaluator Note: CREW Earthquake lF the crew checks the condition of C71A- a Respond to the REACTOR VESSEL HIGH PRESSURE TRIP PS-4549 K5A inform the operator that the relay annunciator 1C058 C-4 fingers are toward the cover. (De-energized a Respond to the "A' RPS AUTO SCRAM annunciator 1C054 A-2 position, but do not directly say it is de-RO energized) All other relays are as seen.

a At 1C05, confirm Reactor pressure high on PR-4563/4564, REACTOR PRESSU RE/REACTOR WATER LEVEL.

o Verify Scram Group A12 3 4 indicating lights are off.

Evaluator Note:

a ldentify the cause of the A RPS Auto Scram.

The crew will determine that PS4549 has failed. The crew will not be able to correct CRS the cause of the half scram, or reset it. a Enter the applicable Tech Specs:

. LGO 3.3.1.1 RPS lnstrumentation Function 3 is not OPERABLE - Gondition A; required action 4.1 Place channel in trip in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or A.2 Place associated trip system in trip in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page 15 of32

NFXTETA-NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TIME/NOTES INSTRUCTOR ACTIVTY EXPECTED STUDENT RESPONSE Earthquake CREW a Respond to the ROD DRIFT annunciator 1C054 D-6 lf sent to Booth Gommunicator: RO investigate Acknowledge Request a At 1C05, select affected Control Rod, monitor 4 rod display to HCU 18-07 determine if a control rod is drifting, and if so in what direction.

Booth Gommunicator: a lf any control rod has scrammed, perform the following:

Two minutes after sent to lnform the control room HCU l8-07 . Run an OFFICIAL 3D CASE for abnormal reactor appears to be scrammed; both scram power/control rod distributions.

investigate HCU 18-07:

solenoid pilot valves are de-energized . Notify the Reactor Engineer of the abnormal rod pattern.

and are venting air.

a When Rod motion has been stopped and/or position indication has been restored clear the alarm by momentarily taking C11A-S7 Rod Drift Alarm ReseUTest switch to RESET.

Booth Communicator: CRS lf sent to The fuses for Rod 18-07 appear to have a Enter the applicable Tech Specs:

investigate blown. o fuses for Rod LCO 3.1.5 Control Rod Scram Accumulators OPERABILITY 18-07 wait one for rod 18-07 Condition A; Required Actions 4.2 Declare the minute and associated control rod inoperable in I hours.

report: . LGO 3.1.3 Gontrol Rod OPERABILITY for rod 18-07 Condition C; Required Actions C.1 Fully insert inoperable control rod (met) and C.2 Disarm the associated CRD in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page 16 of 32

NEXlera' NRc lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG

=Yjç,&

TIME/NOTES INSTRUCTOR AGTIVITY EXPECTED STUDENT RESPONSE Earthquake CREW a Perform actions of AOP 255.1 in the mispositioned control rod section AOP 255.1 RO

. Once power has stabilized, manually initiate an Official 3D Case lf contacted as Booth Communicator: . Verify thermal limits on the official 3D Case.

Reactor Acknowledge Request CRS Engineer:

o Direct actions or AOP 255.1 Two minutes

. Contact RE and Ops Manager Booth Gommunicator:

after contacted as RE: Report that there is no current issue with leaving 18-07 inserted.

Earthquake CREW a Perform actions of AOP 255.2 for the unplanned power change AOP 255.2 RO a Place one APRM recorder in each trip system to fast speed to monitor for APRM undamped oscillations greater than normal.

CRS a Direct actions of AOP 255.2 Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page17 o32

N(TETA'

=Yry NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TME/NOTES NSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE RCIC Leak CREW a Respond to the Steam Leak detection alarm, 1C048 B-4 When the TS Simulator Operator: a Determine that the RCIC room temperature is above Max Normal Declaration is ACTIVATE ET 3 RO made and at This starts the unisolable RCIC steam line a Send an Operator to 1C21to determine which area has the high the direction of leak. temperature condition.

the Floor lnstructor: a Verify the AUTOMATIC ACTIONS have occurred. lf the specified automatic response has failed to occur, manually initiate the Simulator Operator: appropriate actions.

When ventilation is VERIFY ET 18 ACTIVATES CRS taken to a 3-2-3 This will increase the leak rate to ensure a Enter EOP 3 (Secondary Containment Control).

lineup: Max Safe will be reached.

lF sent to the Booth Gommunicator:

RCIC room: Acknowledge Request Four minutes Booth Gommunicator:

after sent to RCIC room: lnform the control room that you are at the RGIC room door and can hear a loud roar from inside the room, but there is no evidence of steam outside the room.

After sent to reset the Booth Gommunicator:

thermal overload for Communications for this event are located MO2400: on page 20.

Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page 18 of 32

NEXTETA F]NF:PíGYØ NRC lNlTlAL LICENSE EXAM, SGENARIO #3 Rev. 0 SEG

,-- ffi E

TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE RCIC Leak Crew o lmplement the actions of EOP 3, Secondary Containment Control.

lF sent to open Simulator Operator: RO breaker for MO- Acknowledge the direction and brief, o Starts ESW for RCIC Room Coolers 24Q1: wait 2 minutes then o Operates available main plant supply and exhaust fans.

AGTIVATE ET 14 . Start 1V-EF-1 ,1V-EF-2, and 1V-EF-3 MAIN PLANT EXHAUST FANS by THEN positioning the following handswitches to START and verify their Booth Gommunicator respective dampers indicate OPEN:

Gontact the Gontrol Room and report . Fan Handswitch Panel Damper the breaker for MO-2401 is open. . 1V-EF-1 HS-7613 1C23A. 1V-AD-16U

. 1V-EF-2 HS-7614 1C238 1V-AD-16V lf sent to close Booth Communicator . 1V-EF-3 HS-7615 MO-2401 1C23C 1V-AD-16W Acknowledge Request manually: Start the Reactor Building Exhaust Fans by positioning the following handswitches to START:

After sent to

. Fan Handswitch Panel Booth Gommunicator o 1V-EF-114 HS-76114 1C23A close MO-2401 and at the Report to the Gontrol Room that you o 1V-EF-118 HS-76118 1C238 direction of the cannot get MO-2401 to move.

Floor lnstructor:

o Start the Reactor Building Supply Fans by positioning the following handswitches to START:

. Fan Handswitch Panel o 1V-SF-104 HS-6512 1C234

. 1V-SF-108 HS-6513 1C238 1V-SF-10C HS-6514 1C23C

. lnserts a manual reactor scram Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page 19 of32

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=Yry NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TIME/NOTES NSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EOP 3 cont. CRS

. Directs starting ESW for RCIC Room Coolers

. Directs operating available main plant supply and exhaust fans.

. Properly placekeeps in EOP 3, Secondary Containment Control.

. lsolates all systems discharging into the area except systems required to be operated by EOPS OR required to suppress a fire.

. Determines that RPV pressure reduction will decrease leakage into secondary containment.

. Before any parameter reaches is Max Safe Operating Limit:

o Enter EOP 1. (CRITICAL)

EOP 1 CREW Simulator Operator: . lmplements the actions of EOP 1, RPV Control.

When the VERIFY ET 22 ACITVATES RO MODE switch is When the RO takes the Mode Switch out of o lnserts a manual reactor scram.

placed in RUN. This begins the RWGU leak (isolable) o SHUTDOWN: Places the MODE switch in SHUTDOWN.

starts, and isolates the RCIC steam leak.

CRS

. Directs inserting a manual reactor scram.

o Directs a RPV level band of 170-211" using condensate and feedwater.

After the scram Booth Communicator o Directs a RPV pressure band of 800-1055 psig using turbine bypass and when valves.

Gontact the Control Room and report RC10A has that the thermal overload for MO-2400 o Directs commencing a cooldown to lessen the driving head on the leak in been deleted: the RCIC Room.

has reset.

Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page29 of 32

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=Y:ry NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONS RWCU Leak CREW When RWCU Simulator Operator: a Respond to the Steam Leak detection alarm, 1C048 B-4 HX room temp VERIFY ET 26 ACTIVATES a Determine that the RWCU room temperature is above Max Normal.

is > 130F:

This will activate the Group 5 Annunciator - RO 1C058 (E-08) a Send an Operator to 1C21to determine which area has the high tem perature condition.

When MO-2700 Simulator Operator: a Verify the AUTOMATIC ACTIONS have occurred. lf the specified or MO-2701 are VERIFY ET 28 ACTIVATES automatic response has failed to occur, manually initiate the closed:

This will start the 'A' steam line TB leak appropriate actions. (CRITCAL)

Pg. 2q and associated leak rad monitor CRS indications on delays. a Enter EOP 3 (Secondary Containment Control).

Evaluator Note:

The crew will re-enter EOP 3 on High Area Temperature; the steam leak can be isolated by the crew.

lf sent to the RWCU HX Booth Gommunicator:

room: Wait 2 minutes and inform the control room that you can hear a loud whistle from inside the room but there is no evidence of steam outside the room.

Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page21 o 32

NEXIefa"

=--%- NRC lNlTlAL LICENSE EXAM, SGENARIO #3 Rev. 0 SEG TME/NOTES INSTRUCTOR ACTVITY EXPECTED STUDENT RESPONSE Segment 3 CREW RWCU Leak . Respond to the steam leak in RWCU per ARP 1C058 E-8 RO

. Check the amber lights on the PCIS status board on 1C04 to determine if a half or a full Group 5 lsolation has occurred.

o Verify completion of the Group 5 lsolation by one of the following means:

. Verify that the individual valves from Section 2.0 AUTOMATIC ACTIONS are closed, OR

. On the PCIS status board, verify that the green ALL VALVES CLOSED lights are on to coincide with the amber ISOLATION SIGNAL lights that are on, allowing time for the valves to close, OR o Check the CIMS Printer PRT-1 which will print out Group 5 valves which failto close on an isolation signal.

Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page22 of 32

NEXTETA" ENERGYøZ NRG lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG

-/- rÃ'er m

TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Fuel Failure / CREW Release . Determine that a steam leak exists in the Turbine Building and attempt to close the MSlVs.

4 minutes after Simulator Operator: . lf delay closing the MSlVs, a Group 1 lsolation will occur.

the reactor is VERIFY the following: Recognize both "4" MSIVs failto close.

scrammed:

ms04a and rm09rm5945 have inserted and are ramping AND Booth Gommunicator:

Gontact the control room as HP personnel and report that there is loud noise and rapidly getting humid and hot in the turbine building north end. You have left the area.

Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page 23 of 32

NEXIera' ENERGYøZ NRC NlTlAL LICENSE EXAM, SCENARIO #3 Rev.0 SEG

-/- unrln ffi TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Fuel Failure / CREW Release . Respond to the REACTOR BLDG ARM Hl RAD alarm, 1C048 A-6

. ln addition to EOP 3, the crew will determine that the cause for the Reactor radiation rise in the Reactor Building rooms is potentially due to a fuel Building ARM failure and enter AOP 672.2 alarm RO

. Perform the following:

. At 1C11, monitor ARM lndicator and Trip Units to determine the affected Area within the Reactor Building.

o Check Computer Point 8571, REACTOR BLDG RAD HIGH.

. At 1C02, confirm the Area High Radiation conditions on RR-9150 AREA RADIATION MON ITORING recorder.

. lf an actual high radiation condition exists in the affected area enter EOP 3 (Secondary Containment Control).

CRS o Enter EOP 3 on High Radiation o Direct the actions of AOP 672.2 Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page24 of 32

NEXTETA" NRC lNlTlAL LICENSE EXAM, SGENARIO #3 Rev. 0 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Fuel Failure / Evaluator Note: Crew Release EOP 3 and AOP 672.2 (below) should be . lmplements the mitigation strategies of EOP 3, Secondary Gontainment EOP 3 performed concurrently. Control RO When Simulator Operator: . Informs the CRS of Reactor Building ARM readings.

rm92re4448ais Verify ET 30 ACTIVATES . Announces evacuation of the Reactor Building at 49.0000:

This will cause rm02re4448a to ramp to 55; CRS this will cause a MSL Hi-Hi Rad annunciator. Also, this will insert x01 on a

. Appropriately place keeps in EOP 3, Secondary Containment Control.

delay. . Answers SC-4'Will RPV pressure reduction decrease leakage into secondary containment?' NO Places a line above SC-8 WAIT UNTIL the same parameter exceeds its Max Safe Operating Limit in Two or More Areas

. After the same parameter exceeds Max Safe Operating Limit in Two or More Areas places a checkmark in SC-9 "Begin reactor shutdown per lPOl 3,4, or 5 as appropriate since the plant is already shutdown Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page2 of 32

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=Yry NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TME/NOTES INSTRUCTOR ACTIVTY EXPECTED STUDENT RESPONSÉ Crew

. lmplements the mitigation strategies of AOP 672.2, Offgas Radiation/

Reactor Coolant High Activity RO

. Respond to Off Gas Radiation /Reactor Coolant High Activity Condition

. Notify Health Physics of increasing activity levels.

. Bypass the Main Condenser High Backpressure trip on 1C15 and 1C17 .

o Establish MSIV leakage treatment system flowpath.

CRS

. Direct Crew Response to Off-Gas Radiation/Reactor Coolant High Activity Condition

. Establish critical parameter monitoring of in-plant radiation levels and offsite release rates, as priorities allow.

. Request chemistry department perform a reactor coolant isotopic analysis and Offgas Pretreat analysis.

o lF a valid Main Steam Line Hi Rad (1C058, D-2) is received and the reactor is shutdown THEN cooldown and depressurize the reactor using lf contacted as Booth Gommunicator: the suppression pool as a heat sink as follows:

HP: Acknowledge the i nformation. o Establish reactor pressure control with SRVs prior to closing the MSlVs.

. Cooldown the reactor with the main condenser unavailable per lPOl 4.

. Notify HP that rad levels in the torus room and areas of the reactor building may significantly rise.

Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page26 of 32

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=Yr*& NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TIME/NOTES INSTRUCTOR AGTIVITY EXPECTED STU DENT RESPONSE After the TB Crew KAMAN . lmplements the mitigation strategies of EOP 4, Radioactivity Release exceeds the Control ALERT EAL RO level:

. Perform actions of EOP 4 lflwhen directed Booth Gommunicator:

o lF Group 3 isolation exists AND Reactor Building Kaman Monitors have a to stop fans: Wait 3 minutes and report that the Hl-HlAlarm THEN 1V-EF-21"A" and "8" Fans were . Stop main plant exhaust fans.

running and that you secured the"B" . Stop turbine building supply fans.

Fan. The "A" Fan's hand-switch, HS-5945, broke off.

. Verify at least one turbine building exhaust fan operating in high speed.

. Verify Group 3 isolation complete.

o Reduce Offsite Radioactivity Release Rate with a Primary System lF the crew Discharging Outside of Containment Simulator Operator:

lowers RPV VERIFY ET 24 ACTIVATES o Attempts to isolate all primary systems discharging radioactivity outside pressure prior the primary and secondary containments except for those systems to ED: This will close the bypass valves. required to be operated by EOPs

. Attempts to close at least one of the "4" steam line MSIV's using the handswitch and the test switch. (May have already been attempted) o Emergency Depressurization is required.

Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page27 of 32

NEXTCTA' ENE@ NRC lNlTAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG ffi TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE After the TB CRS KAMAN Direct crew response for Performance of EOP 4 exceeds the ALERT EAL Directs isolating all primary systems discharging radioactivity outside the primary and secondary containments except for those systems required to level:

be operated by EOPs.

. WAIT UNTIL any primary system is discharging radioactivity into areas outside the primary and secondary containments

. Begins reactor shutdown per lPOl 3, 4, or 5 as appropriate (already completed) o BEFORE offsite radioactivity release rate reaches a General Emergency Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page29 ol 32

NEXIETA

=Yr*& NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the TB Crew KAMAN . lmplements the mitigation strategies of Emergency Depressurization.

exceeds the RO SITE EMERGENCY . lnstall Defeat 11 (if not done previously).

EAL level and . Maintains RPV level170-211" using directed control system.

is approaching . Reports torus water level.

the GENERAL EMERGENCY o Opens 4 ADS SRVs.

level, the crew . Commences to initiate actions to place shutdown cooling in service.

Emergency CRS Depressurizes Directs Defeat 11 installation (if not done previously).

o Directs RPV level be maintained 17Q-211" using directed controlsystem As RPV Simulator Operator:

pressure is . Verifies torus level greater than 4.5'.

VERIFY ET 24 ACTIVATES lowered past . Directs opening 4 ADS SRVs.

This will close the bypass valves 880#: . Continues RPV depressurization using SRVs.

WAIT UNTIL shutdown cooling interlock clears and further cooldown is required.

Directs continuing to cold shutdown conditions with shutdown cooling using only RHR pumps NOT required to maintain RPV level above 170" Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page29 of32

NEXTETA EYJ6, NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When RPV Simulator Operator pressure is Place the simulator in FREEZE.

lowering to establish depressurized Floor lnstructor conditions, Perform a crew update and announce to RPV water the crew the simulator is in freeze and level is being the scenario is complete.

controlled, and at the direction of the floor instructor:

- - END OF SCENARIO **

Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page 30 of 32

NEXTETA'

=Ysr6 NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG QUANTITATIVE ATTRI BUTES Malfunctions:

Before EOP Entry:

1. Operational Basis Earthquake

2. RPV Pressure Switch Failure, PS4549 fails high

3. Single rod scrams in

4. RCIC Steam Leak After EOP Entry:

1. RWCU leak (isolable)

2. Fuel Failure

3. Steam Tunnel Steam Leak

4. Turbine Bypass Valve Failure Abnormal Events:

1. AOP 901

2. AOP 255.1

3. AOP 255.2 Maior Transients:

1. Earthquake

2. Offsite Release

3. ED Critical Tasks:

1. #28: JF a primary System is discharging into Secondary Containment and any parameter is above the Max Normal Operating Limit, THEN crew actions are taken to isolate all systems discharging into the area except those required by EOPs or to suppress a fire.

{BWROG N/A}

2. #2g: lF the reactor is at power AND a primary system is discharging into secondary containment, THEN insert a manual scram before any parameter reaches the Max. Safe Operating Limit. {BWROG SC 1.1}

3. #i2: lF a primary system is discharging outside secondary containment, THEN perform Emergency RPV Depressurization before offsite release rates reach General Emergency levels. {BWROG RP 1.1}

Filename:3_esg TR-AA-230-1 003-F06 Revision 0

NEXTETA" EYrc- NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG CREW GRADING ATTACHMENT ESG 3 Rev Date Operator Name Position Evaluator OSM CRS STA 1C05 1C03 B.O.P Management Representative/Lead Evaluator Crew Critical Tasks Task Statement SAT UNSAT

1. lF a primary System is discharging into Secondary Containment and any parameter is above the Max Normal Operating Limit, THEN crew actions are taken to isolate all systems discharging into the area except those required by EOPs or to suppress a fire.

2. lF the reactor is at power AND a primary system is discharging into secondary containment, THEN insert a manual scram before any parameter reaches the Max. Safe Operating Limit.

3. lF a primary system is discharging outside secondary containment, THEN perform Emergency RPV Depressurization before offsite release rates reach General Emergency levels.

Flename:3_esg TR-AA-230-1 003-F06 Revision 0

EW-NEXTETA-F.tt SIMULATOR EXERCISE GUIDE SEG SITE: DAEC Revision #: 0 LMS ID: ESG AIt LMS Rev. Date: N/A SEG TITLE: NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT SEG TYPE: [J Training X Evaluation PRocRAM: nLOCT XLOIT nOther:

DURATION: -90 minutes lDeveloped byl:

lnstructor/Developer Date Reviewed by:

lnstructor (lnstructional Review) Date Validated by:

SME (Technical Review) Date Approved by:

Training Supervision Date Approved by:

Training Program Owner (Line) Date alt TR-AA-230-1 003-F06 Revision 0 Page 1 of 23

NEXIETA E\src- NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective This Evaluation Scenario Guide evaluates the Operators' ability to:

"Given the malfunctions presented in this ESG, the students will protect the public, protect plant personnel, and protect plant equipment, in accordance with plant procedures."

Enabling Evaluation Guide, no tasks are trained.

Objectives Prerequisites: Enrolled in Licensed Operator Continuing Training, License Operator lnitial Training, Senior Reactor Operator- Certification Training Training A. Simulator Resources: B. Evaluation team C. Operations Management Representative D. Simulator Driver E. Phone Talker F. Exam Proctor for custody of the crew between scenarios G. Simulator Video recording equipment

References:

A. Ol 693.2, Rev. 51 B. AOP 646 Rev. 23 C. AOP 255.2 Rev.43 D. AOP 264Rev.14 E. AOP 573 Rev.6 F. EOP2 Rev. 18 G, EOP 1 Rev.20 H. ATWS Rev.23

l. ED Rev. 11 J. ATWS Rev. 23 K. lPOl 4 Rev. 133 L. lPOl 3 Rev. 152 M. ARP 1C048 Rev. 81 N. ARP 1C044 Rev. 62 O. ARP 1C054 Rev. 82 P. OP-AA-102-1003 Rev, 11 Q. Ol 644 QRC 2, Rev. 0 R. Ol 149 QRC 4, Rev. 0 S. Ol 153 QRC 1, Rev.4 Protected Gontent:, None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance Operating None Experience:

Risk Significant Operator Actions:

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page2 of 23

EYW NEXTETA" ruf NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Task # Task Title Reactor Operator 1.04 Respond to Annunciators 10.03 Alternate CRD Pumps 72.02 lnsert Control Rods using Single Notch 93.22 Perform the lmmediate Operator Responses to a Reactor Scram 94.03 Respond to Power/Reactivity Abnormal Change Condition 94.1 9 Respond to Loss of Feedwater Heating Condition 94.53 Respond to Primary Containment Control Abnormal Situation 94.58 Respond to Loss of Reactor Recirculation Pump(s) 95.00 Respond to Emergency Situations 95.21 Perform EOP Defeat 11 95.25 Perform Defeat 15 95.44 Perform actions of RC/L of EOP 1 95.45 Perform initial EOP 1 actions (RC) 95.46 Perform actions of RC/P of EOP 1 95.50 Perform /L to Control RPV Level during an ATWS 95.52 Control RPV lniections prior to, during, and subsequent to ED during ATWS.

95.55 Perform initialATWS actions (/)

95.56 Perform /P to Con trol RPV Pressure During an ATWS.

95.57 Perform /Q to Reduce Reactor Power or Scram the Reactor 95.63 Perform DW/T leg of EOP 2 95.64 Perform PC/P leg of EOP 2 Senior Reactor Operator 1.02 Determine operability for TS required components 4.21 Direct Crew Actions to Perform the lmmediate Operator Responses to a Reactor Scram 5.03 Direct Crew Responses to Power/Reactivity Abnormal Chanqe Condition 5.19 Direct Crew Response to Loss of Feedwater Heating Condition 5.53 Direct Crew response to a Primary Containment ControlAbnormal Situation 5.58 Direct Crew response to Loss of Reactor Recirculation Pump(s) 6.21 Direct Crew Response to Perform EOP Defeat 11 6.25 Direct Crew Response for performance of Defeat 15 6.44 Direct Crew Response for performance of the RC/L leg of EOP 1 6.45 Direct Crew Response for performance of initial EOP 1 actions (RC) 6.46 Direct Crew Response for performance of RC/P leg of EOP 1 6.50 Direct Crew Response to Perform /L to Control Level Durinq an ATWS 6.52 Direct Crew Response to Control RPV lnjection prior to, during and subsequent to Emergency Depressurization during ATWS 6.55 Direct Crew Response to Perform lnitialATWS Actions (/)

6.56 Direct Crew Response to perform /Q to reduce power/scram the reactor durinq ATWS 6.57 Direct Crew Response to perform /P to control RPV pressure during an ATWS 6.63 Direct Crew Response for performance of the DWT leg of EOP 2 6.64 Direct Crew Response for performance of the PC/P leg of EOP 2 Filename: ESG alt TR AA-230-1003-F06 Revision 0 Page 3 of 23

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=Yøarg NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG UPDATE LOG: lndicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

PREPARER DATE

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

REVIEWER DATE Rev.0 lnitial development for 2017 lnitial development for N/A See Cover NRC LOIT Examination 2017 NRC LOlT See Cover Examination Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 4 of 23

NEXI ETA ENENGYø2 NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG FLEgT OVERVIEW / SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE Event # Description When the crew assumes the shift reactor power is approximately 100%. The'B' RHR Pump is inoperable due to breaker refurbishment; return time is approximately three days. After crew turnover, maintenance has requested immediately swapping running EHC pumps.

1 The crew will swap running EHC pumps IAW Ol 693.2 Section 6.2 2 Once the EHC pump swap is completed, the 'B' Recirc Pump will experience a 20o/o runback, the scoop tube will not be able to be locked until after the 'B' Recirc Pump speed is less than 75o/o, and the crew will enter LCO 3.4.1 Condition C. The 'B' Recirc Pump will experience erratic parameters and will trip. The crew will lower power IAW lPOl 3.

3 Then the 'A' CRD pump will trip on overcurrent and three CRD accumulators alarm on low pressure. Permission is given to stad standby pump IAW Ol 255. After the 'B' CRD Pump is returned to service the CRD Accumulators remain in alarm on low pressure. The crew will enter LCO 3.1.5 Gondition B.

4 A small leak in the drywell and rising drywell pressure. As temperature rises in the Drywell, the crew will insert a manual scram prior to Drywell temperature reaching 280F (cRrTrcAL).

5 As Primary Containment pressures and temperatures rise the 'A' side enable containment switch will not function and MO-2000 will not open causing Drywell temperature to rise past 280F. MO-2000 will be able to be opened through manual operations if an individual is sent to open the valve.

6 The crew will determine that there is a hydraulic AiWS and transition to EOP ATWS. The crew will lockout ADS (CRITICAL), perform the ATWS QRC, inject SBLC, Terminate and Prevent injection (CRITICAL) and establish a level band until all rods are inserted (CRITICAL), and insert the control rods with the RIPS. (CRITICAL) Rods will be able to be inserted via Scram-Reset-Scram.

7 The scenario may be terminated after all rods are in and RPV level is being restored Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 5 of 23

NEXTETA-EYtsrc- NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG SIMULATOR SET UP INSTRUCTIONS 1 . Set NRC Exam Security for the Simulator per QF-1071-08

2. Perform simulator set up per TDAP 1839 Attachment 2, Simulator Setup Checklist.

3. Load the saved lC (in folder with this ESG) to a SNAPSHOT

a. Reset to that SNAPSHOT.

b. Place the Simulator in RUN OR

4. Reset to lC 20, place the simulator in RUN and perform the following:

a. lnsert event triggers, malfunctions, overrides and remotes per the tables below.

5. Have a second instructor verify that the auto triggers are setup as indicated below and evaluate to "FALSE" _

6. Verify Malfunctions _

7. Verify Remotes (Note that environmental remotes will already be timing)

8. Verify Overrides

9. Ensure MOL pull sheet is in the 1C058 hanging file.

10 Ensure EOOS has the same system status lineup as the start of the simulator scenario.

11 Setup control panel including equipment clearance tags, information tags, caution tags or other site-specific devices used as an aid to the operator.

a. Place a Testing and Maintenance border on 1C038 (A-8) "B' RHR Pump 1P-2298 Trip or Motor Overload b, Hang caution tags on the following:

(1) HS-1915, B RHR PUMP 1P-2288

c. Hang Guarded System tags on the following:

(1) "B',ESW (2) "B',RHRSW (3) "B',DG (4) 1p.4 (5) 1B,4 (6) 1B,44 11 Provide appropriate sh ift turnover documentation.

a. Have STP 3.4.2-01 Jet Pump Operability iest available upon request.

12 RUN Schedule File

.ESG alt.sch" and LEAVE lT RUNNING.

Fi lename: ESG alt TR-AA-230-1003-F06 Revision 0 Page 6 of 23

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,Ynar6 NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG EVENT TRIGGER DEFINITIONS Trigger No. Trigger Losic Statement Trigger Word Description 1 ,3,5,7,9,13,15, Manually Activated Manually Activated 21,23 11 ZDlRDHS18078(4) == 1 Deletes RD073819 17 rrl <= 523 RPV water level less than or equal to 170"

'19 zaorrr6211b <= 0.75 'B' Recirc Pump speed less than 75%

MALFUNCTIONS:

Time Malf. No. Malfunction Title ET Delav Ramp lnitialValue Final Value Setup RRO6B RECIRC M-G DRIVE MOTOR BREAKER 3 2:O0 INACTIVE ACTIVE TRIP - M-G B RD070615 Control Rod Accumulator Trouble - Rod 5 1 min lnactive Active Setup 06-1 5 RD073435 Control Rod Accumulator Trouble - Rod 5 1 min lnactive Active Setup 34-35 10 sec Setup RD11A CRD Hvdraulic Pumo Trio - Pumo A 5 lnactive Active RD073819 Control Rod Accumulator Trouble - Rod 5 1 min lnactive Active Setup 38-1 I 30 sec rr15b RECIRC LOOP RUPT - DESIGN BASES 13 15 min 0 1.5 Setup LOCA AT 100o/o - LOOP B AN1C03B(8) 1C038 (A-08)'B' RHR Pump 1P-2298 Trip ON ON Setup Or Motor Overload rr05b RECIRC PUMP SHAFT SEIZURE- PMP B 3 5:00 0 100 Setu ms32 SPURIOUS GROUP 7 ISOLATION 17 lnactive Active Setup rp05g HYDRAULIC LOCK SCRAM DISCHARGE 75 75 VOLUME IVARIABLE)

Setup r136b Spurious 20% Recirc Runback B Train 1 INACTIVE ACTIVE Setup rr06 'B'RECIRC SCOOP TUBE LOCK UP (LOCK,UNLOCK) UNLOCK UNLOCK OVERRIDES Time Malf. No. Malfunction Title ET Delay Ramp lnitial Value Final Value Setup Dt-RH-014 HS.19O3C CONT SPRAY VLV CTRL OFF OFF Setup Dt-RH-076 HS-2OOO CONTAINMENT SPRAY MOV- AUTO CLOSE 2000 Setup DO-RH-063 HS-1915(2) RHR PUMP 1P-2298 LliES - On off (wHrTE)

Setup DO-RH-064 HS-1915(3) RHR PUMP 1P-2298 LTTES - On off (RED)

Setup DO-RH-065 HS-1915(4) RHR PUMP '.lP-2298 LIrES - On off (AMBER)

Setup DO-RH-062 HS-1915(1) RHR PUMP 1P-2298 LlTES - On off (GREEN)

Setup Dt-PC-038 HS-43218 GRP 7 CHAN B DW CLG AND Normal Normal FAN OVR DO-RH-132 HS-2000(1 ) CONTATNMENT SPRAY 21 1:00 ON OFF Setup MOV-2OOO (GREEN)

DO-RH-133 H5-2000(2) CONTATNMENT SPRAY 21 1:00 ON OFF Setup MOV-2000 (RED)

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 PageT of23

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,YSxø NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG fime Malf. No. Malfunction Title ET Delav Ramp lnitialValue FinalValue Setup Dt-RH-076 HS-2OOO CONTAINMENT SPRAY MOV- 27 CLOSE OPEN (NEW) 2000 REMOTES:

Time Malf. No. Malfunction Title ET Delav Ramo lnitialValue Final Value Setup RDO4 CRD PUMP 1P-2098 DISCHARGE 7 l MIN 100 50 VALVE V-17 -10 ISOLATION Setup RD04 (NEW) CRD PUMP 1P-2098 DISCHARGE 15 l MIN 50 100 VALVE V 10 ISOLATION Setup RHlO MAN OPER OF 'B' RHR PUMP (1P2298 Norm Open BREAKER)

ATWS TEST SWlTCH (AKA DEFEAT 12)

Setup rp02 23 2:30 RUN TEST HS-1863A rp03 ATWS TEST SWlTCH (AKA DEFEAT 12) 23 2:00 Setup RUN TEST HS-1864A (RUN.TEST)

SCHEDULE FILES:

ESG_alt

@Time Event Action Description o Modify rd04 to 100 in 60 after 60 CRD PUMP 1P-2O98 DISCHARGE Setup VALVE V-17 -10 ISOLATION Setup 11 Delete malfunction rd073819 after 5 CONTROL ROD ACCUMULATOR TROUBLE- ROD 38-19 Setup 19 Delete malfunction 1106 'B'RECIRC SCOOPE TUBE LOCK uP (LOCK,UNLOCK)

Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator lnstructor Pre-Exercise Checklist.

lf surrogate operators are to be used, brief them using TR-AA-230-1007-F11, Surrogate Brief Checklist Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page I of 23

NEXTETA-EYr6- NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG SHIFT TURNOVER INFORMATION

. Today, Dayshift o Warm, summer day, temperatures in the high 70's. No inclement weather expected.

o Plant power - -100o/o Rx Pwr with corresponding MWe, MWth and core flow.

. Protected train - "4" o Procedures or major maintenance in progress:

o 'B' RHR Pump is inoperable because of a fault in the motor winding. Maintenance expects repairs to be completed in 3 days.

o Technical Specification Action statements in effect o TS 3.5.1 Condition A, Day 1 of 30 day LCO, due to "B' RHR Pump inoperative o TS 3.6.2.3, Condition A, Residual Heat Removal (RHR) Suppression Pool Cooling, Day 1 of 30 day LCO, due to "8" RHR Pump inoperative o Plant PRA/PSA Status including CDF/LERF & color o CDF : GREEN 1.35 E-6, I YR TO YELLOW LCDP o LERF: GREEN 3.328-7,lYR TO YELLOW ILERP a Evolutions in progress or planned for upcoming shift o Maintenance has requested swapping running EHC pumps to allow for checks on the running pump.

o Comments, problems, operator workarounds, etc.

o One extra NSPEO available in Work Control o Radwaste Operator is NSPEO qualified Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 9 of 23

NEXiera' NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTONS TME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE After the crew Crew has taken the o Switch running EHC pumps shift:

RO When contacted

. At 1C07 , start standby EHC pump 1P-978 by momentarily placing Booth Gommunicator handswitch HS-36658 in the START position.

as organization personnel: Acknowledge Request . Verify annunciator EHC PUMPS 1P97NB BOTH RUNNING (1C07A, C-

4) is activated

. Verify both EHC pump 1P-97N8 amps have stabilized

. Stop EHC Pump 1P-974 by momentarily placing handswitch HS-36654 in the STOP position

. Verify annunciators EHC PUMPS 1P-97N8 BOTH RUNNTNG and ECH PUMP 1P-97N8 HS NOT lN AUTO are reset CRS o Direct switching running EHC pumps Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 10 of23

NEXTETA' rEly-a NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG

,.- nnErn RF SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Recirc Runback Crew After EHC Simulator Operator a Respond to a'B' Recirc Pump 20% Runback pumps are lnsert ET 1 RO swapped and at the direction of This will cause 'B' Recirc Pump 20% . Attempt to lock'B' Recirc Pump Scoop Tube. (Will lock once pump the floor runback and failure of 'B' Recirc Pump speed is lower than 75%)

instructor: Scoop Tube lock until speed is lower than 75%. o Stabilize Reactor water level.

o When power is stabilized, plot location on the Stability Power / Flow Map

. Determine Recirc Pump speed mismatch is outside of acceptable When contacted limits as organization Booth Gommunicator CRS personnel: Acknowledge Request

. Comply with Tech Specs and Ol 264, Appendix 1 When contacted Booth Gommunicator o Enter LCO 3.4.1 Condition C as plant Wait 2 minutes and inform Control personnelto Room that there is nothing abnormal investigate'B' about the 'B' Recirc Pump, but will Recirc Pump: continue to investigate.

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Pagello'f23

NEXIera*

NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O ryyLa_ ffi SEG s IMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE AOP 264 Crew After power has Simulator Operator a Respond to 'B' Recirc Pump trip been reduced Insert ET 3 RO below MELLLA and at the floor This will insert "B" Recirc Pump shaft o Verify the AUTOMATIC ACTIONS have occurred:

instructors seizure and, after a2.OO delay, trip the direction: drive motor breaker for the 'B' Recirc o B RECIRC MG SET MOTOR BREAKER 1204 is OpEN.

pump. o B GENERATOR FIELD BREAKER is OPEN.

When sent to . send an operator to lc1138 in the MG set Room to monitor relays.

Booth Gommunicator either 1C149 or o Momentarily place B RECIRC MG SET MOTOR BREAKER 1Fü:O4 1C1138: Acknowledge Request handswitch in the STOP position to achieve GREEN FLAG status.

. Stabilize reactor water level between 186" and 195".

. Verify open B RECIRC PUMP DISCH BYP vatve MO4630.

Two minutes after sent to Booth Gommunicator . Close B RECIRC PUMP DISCHARGE vatve MO-4628.

lnform Control Room that the 'B' Recirc 1C1138: MG Drive Motor breaker is tripped with . Re-perform appropriate steps in AOP 255.2 concurrenily.

indication of a ground fault Relay 831- . After 5 minutes, reopen B RECIRC PUMP DISCHARGE valve MO-K3B active. No smoke, smell, or fire. 4628.

Two minutes Booth Communicator o lnsert control rods per the control Rod withdrawal sequence sheets after sent to Inform Control Room that 1V-SF-12 to maintain power less than or equalto (s) 60.0%.

1C149: handswitch is in AUTO . Reduce core flow to less than or equal to (<) 53% if necessary.

. send operatorto 1c149 and verifythat Recirculation pump MG set Room supply fan 1v-sF-12 has its respective handswitch HS-6534A in AUTO or START.

Flename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 12 o 23

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=Y"K NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE AOP 264 Cont.: CRS o Directs entering AOP 264 and reentering AOP 255.2.

When contacted Booth Communicator

. Directs and supervises reactivity manipulation to lower power below as support 60/o.

personnel: Acknowledge Request

. Comply with the Technical Specification requirements for Recirculation Loops Operating (3.4.1 Condition C)

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 13 of23

NEXlera"

=yøø_ R.E NRG lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CRD pump Crew trip/accumulator TS a Respond to'A' CRD pump trip and corresponding accumulator lights After Load Line Simulator Operator RO is below 1O0Vo, a Send operator to check 1P-2094 breaker and to the pump for fault power has been lnsert ET 5 indications.

reduced -5olo, This will cause the'A' CRD pump to trip the TS has been and accumulator lights to illuminate after a a Start CRD Pump 1P-2098 per Ol 255 or Ol 255 QRC1.

time delay entered and at o Verify adequate oil level in CRD Pump 1P-2098 motor and the direction of speed changer.

the floor instructor: o Close 1P-2098 Pump Discharge lsolation V-17-10 to approximately 112 turn open.

When contacted Booth Gommunicator to investigate o Adjust CRD SYSTEM FLOW CONTROL FC-1814 to 0 gpm Acknowledge Request in MANUAL.

CRD pump and breaker: o Verify MO-1833, INLET TO CRD RETURN LINE, is fuily Booth Gommunicator open.

Two minutes lnform Gontrol Room that GRD pump is after request for warn to the touch/ GRD breaker has o Start CRD PUMP 1P-2098 CRD pump and breaker status: tripped on time delay overcurrent o Slowly open Discharge lsolation V-17-10 to pressurize downstream piping and to prevent CRD pump from tripping When contacted on low suction pressure.

to investigate Booth Gommunicator the Acknowledge Request o Vent both CRD Discharge Filters 1F-201{and B, using the accumulators: following Vent Valves:

Two minutes Booth Gommunicator o 1F-201A after request for lnform the control room 06-15, 34-35, . V-17-15 CRD Pump Disch Filter 1F-2014 Vent accumulator pressures:

38-l 9 accumulator pressures: . V-17-17 1F-201A Combined VenV Drain Line lsolation 06 915 psig, 34 890 psig, 38 935 psig Filename: ESG alt TR AA 230-1003-F06 Revision 0 Page 14 of23

NEXTETA" ryprk NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG CRD pump Crew trip/accumulator TS Cont.:

a Respond to'A' CRD pump trip and corresponding accumulator lights Booth Communicator When contacted RO Acknowledge Request to close V-17-10 a Start CRD Pump 1P-2098 per Ol 255 or Ol 255 QRC1. (Cont.)

Simulator Operator Trturn closed:

Wait I min and INSERT ET 7 o 1F-2018 This will insert RD04 to Tz openV-17-10 . Y-17-18 CRD Pump Disch Filter 1F-2018 Vent

. Y-17-201F-2018 Combined VenV Drain Line lsolation Booth Communicator o Verify charging header pressurized > 1200 psig on pl-18164 When contacted CHARGING WATER PRESSURE.

to open Acknowledge Request v-17-1Q. Simulator Operator o Slowly adjust CRD SYSTEM FLOW CONTROL FC-1814 to obtain approximately 40 gpm on Fl-1814 CRD SYSTEM Wait I min and INSERT ET 9 FLOW.

This will delete RD04 to fully open V-17-10 o When FC-1814 is properly controlling flow, then shift to When contacted AUTO.

Booth Gommunicator to investigate o Slowly adjust DRIVE WATER nP CONTROL MO-1830 to the Acknowledge Request obtain approximately 260 psid on PDt-1B2SA DRTVE WATER accumulators after CRD pump ^P.

is started: CRS Booth Gommunicator o One minute Directs starting the'B' CRD Pump lnform the control room 06-15, 34-35, after request for 38-1 9 accumulator pressures: . Comply with the Technical Specification requirements for Control accumulator Rod Scram Accumulators (3.1.5 Condition B) pressures: 06 925 psig, 34 900 psig, 38 1100 psig lf contacted as Booth Gommunicator RE to verify slow rods: lnform control room that there are currently no slow rods.

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 15 of 23

NEXTETA

%3 NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG Coolant Rupture After'B'CRD is running and the Simulator Operator TS has been NSERT ET 13 entered and at This inserts a leak from the 'B' Recirc the direction of Loop.

the floor instructor:

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 16 of23

NEXTETA" E:NryY2<- NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG

,.- tfla ffi EOP 2 Crew After Drywell . lmplements the mitigation strategies of EOP 2, Primary Containment Pressure Control exceeds 2 psig: RO lf contacted as Booth Communicator . lnforms the CRS of containment parameters including parameter name, plant personnel Acknowledge Request value and trend.

to deenergize Simulator Operator o lnstalls Defeat 4.

MO-2000:

ACTIVATE ET 21 o Utilizes Ol 149 QRC to spray the torus using 'A'side Torus Sprays.

This willturn off the lights on 1C03 for MO- o Realizes that MO-2000 INBD DRYWELL SPRAY valve will not open and 2000 after a one minute delay. HS-1903C ENABLE CONTAINMENT SPRAY VALVES will not function.

o lnserts a manual reactor scram (CRITIGAL)

Booth Gommunicator One minute after ET 21 is Contact the Control Room and inform CRS activated: them that the breaker for MO-2000 is o Enters into EOP 2 due to Drywell Pressure.

open.

o Obtains containment parameters.

lf contacted to o Directs installation of Defeat 4.

Booth Communicator open locally o Directs spraying the torus after confirmation that torus pressure is greater Acknowledge Request than 2 psig.

open MO-2000 o Directs spraying the drywell before drywelltemperature reaches 280F.

Four minutes o Directs inserting a manual reactor scram Simulator Operator after contacted r Placekeeps in EOP 2 to the applicable WAIT UNTTL steps in the pC/p ACTIVATE ET 27 (PC/P-7) leg to locally open M0-2000: Booth Gommunicator Gontact the Gontrol Room and inform them that MO-2000 is open.

Filename: ESG alt iR-AA-230-1 003-F06 Revision 0 Page17 of23

NEXIETA"

=Y4 NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG EOP 1 Crew Transition to . lmplements the mitigation strategies of EOP 1, RPV Control.

ATWS RO o Recognizes a hydraulic ATWS has occurred and reports the type of ATWS and reactor power.

r Places the master feedwater level controller to 158.S" in AUTO.

CRS o Enters EOP 1, RPV Control based on reactor power is above So/o or unknown after a scram signal is received.

. Recommends refer to EPIP 1.1 for EAL assessment.

o Determines that a reactor scram has been initiated o Validates isolations, initiations and sBDG initiations that should have occurred but did not.

. Recognizes and implements the CRS "lF any rod is withdrawn past position AND it has Nor been determined that the reactor will remain shutdown under all conditions without boron THEN exit this procedure and enter ATWS'.

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 18 of23

NEXTETA' NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG ATWS Cont. Simulator Operator Crew

. lmplements the actions of ATWS.

When directed AGTIVATE ET 23 RO to install Defeat This will place Remote Functions RP02 in . Locks out ADS. (CRlTlcAL) 12:

TEST after a time delay; to install Defeat . Gompletes the ATWS QRC. Reports completion and includes SBLC

12. availability, ARI success, reactor power and RPV level.

When RP02 is inserted, callthe control

. lnstalls Defeat 11.

room and inform them that Defeat 12 is

. lnjects SBLC. Reports completion and includes reactor power and RPV complete. level.

. Coordinates performance of the Hydraulic ATWS RlPs. (CRITICAL)

. lnstalls Defeat 4 o Verifies ortrip/lockout HPCI.

. Terminates injection:

. Condensate and Feed:

. Close Feedwater Regulating Valves CV-1579, CV-1621, CV-1622 as follows:

. Take MANUAL control of Master Fed Reg Valve Auto/Man Control LC-4577 and dialthe controller down until all Feedwater Regulating Valves indicate closed as indicated on:

o HC-1579, A Feed Reg Valve Manual/Auto Transfer

. HC-1621, B Feed Reg Valve Manual/Auto Transfer o HC-1622, Startup Feed Reg Valve Manual/Auto Transfer

. RHR:

. Place MO-2004 and/or MO-1904 LPCI OPEN INTLK OVERRIDE HS-2004C and/or HS-1904C to OVERRIDE When 1C038 (B-5) RHR RX LO PRESSURE PERMISSIVE AT 450 PSIG is activated, close MO-2004[MO-1904] by taking HS-2004[HS-1904]to CLOSE Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 19 of23

NEXTETA NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG ATWS Cont. CRS o Directs locking out ADS.

o Directs the ATWS QRC be completed.

o Directs Defeat 11 installation.

o Directs injection of SBLC.

. Directs performance of Hydraulic RIPS including installation of Defeat 12.

o Directs power level control mitigation strategies.

o Directs inserting Defeat 4.

. Directs Terminate/prevent injection from HPCI, Condensate/Feedwater, Core Spray and RHR. (cRlTlCAL)

ATWS Crew

. lmplements the actions of ATWS.

RO

. Reports reactor power at87" and lowering.

. Reports RPV level when reactor power is less than 5% or when 15" is reached.

. Secures RCIC when RPV level is under control.

. 1C05 operator assumes the front panel RlPs after RPV level is under control.

CRS o Directs reporting reactor power at87" and lowering.

. Directs RPV level continue to be lowered until reactor power is less than 5o/o or RPV level reaches 15".

o Directs RPV level control band of -25" to either 15" or the RPV level when reactor power was 5% with condensate and feedwater.

(cRrTrcAL)

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page2O of 23

NEXTETA"

=Yry NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG ATWS Crew Transition to . When all rods are in, transition from ATWS to EOP 1 EOP 1 RO Floor lnstructor . Reports that all rods in after performing Scram-Reset-Scram After all rods Monitor and ensure that crew monitors . Secures SBLC have inserted. pressure during re-flood of the RPV. o Controls level 170"-211" using Condensate and Feedwater Grew should limit injection to ensure cooldown limits are not violated. CRS

. Confers with the SM on the transition to ATWS.

. Directs securing SBLC injection o Directs RPV level 170"-211" using Condensate and Feedwater When RPV level Simulator Operator is being Place the simulator in FREEZE.

restored, the crew is progressing to Floor lnstructor SDC, and at the direction of the Announce the scenario is complete; Floor lnstructor: please stand by your stations and do not discuss the scenario with your crew.

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page21 of23

NEXTETA" EYrc- NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG QUANTITATIVE ATTRI BUTES Malfunctions:

Before EOP Entry:

1. 'B' Recirc Pump 20o/o runback

2. Recirculation pump trip

3. CRD pump trip

4. Accumulator fails to recharge After EOP Entry:

1. 'A' side containment enable switch fails to operate

2. 'B' side lnboard Drywell Spray valve (MO-2000) fails to open Abnormal Events:

1. AOP 255.2

2. AOP 264 Maior Transients:

1. LOCA

2. ATWS Gritical Tasks:

21 lF the reactor is operating at power and Drywell temperature is rising, THEN insert a manual scram before drywell temperature reaches 280'F. {BWROG PC 4.1}

4: lF a scram is required and Reactor power is above 5%, THEN reduce power below 5%

using one or more of the following methods: {BWROG RPV 4.1, 5.1, 6.1}

lnserting control rods using RlPs lnjection of Boron

6: lF a reactor scram is required and the reactor is not shutdown under all conditions, THEN lockout ADS before automatic actuation. {BWROG RPV 4.2,5.2,6.21

10: lF a reactor scram is required, and reactor power is >5%, and Power/level control is required, THEN terminate and prevent injection until conditions allow reinjection. {BWROG RPV 6.3)

11 lF performing ATWS Power/level control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems. {BWROG RPV 6.4}

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 22 of 23

NEXTETA-

,Yr6. NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG CREW GRADING ATTACHMENT ESG ALT Rev. 0 Date Operator Name Position Evaluator OSM CRS STA 1C05 1C03 B.O.P Management Representative/Lead Evaluator I Crew Critical Tasks Task Statement SAT UNSAT

1. lF the reactor is operating at power and Drywell temperature is rising, THEN insert a manual scram before drywelltemperature reaches 280.F.

2. lF a scram is required and Reactor power is above 5%, THEN reduce power below 5% using one or more of the following methods:

lnjection of Boron lnserting control rods using RlPs

3. lF a reactor scram is required and the reactor is not shutdown under all conditions, THEN lockout ADS before automatic actuation,

4. lF a reactor scram is required, and reactor power is >5%, and Power/level control is required, THEN terminate and prevent injection until conditions allow reinjection.

5. lF performing ATWS Power/level control and Conditions are met to allow reinjection, THEN crew actions are taken to maintain RPV level above -25" by injecting using Table 1B systems.

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 23 of 23

SURVEILLANCE TEST PROCEDURE STP 3.4,2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILIW TEST Page Rev.

1of22 36 Usage Level:

CONTINUOUS Record the following: Date / Time I lnitials:

NOTE: lJser shatt peform and document a Temp lssue / Rev. Check to ensure revision is current, in accordance with procedure use and adherence requirements.

Prepared By: I Date:

Print Signature cRoss-DrscrPLlNE REVIEW (AS REQUIRED)

Reviewed By: I Date:

Print Signature Reviewed By: I Date:

Print Signature PROCEDURE APPROVAL Approved By I Date Print Signature

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TTTLE: DAILY JET PUMP OPERABILIW TEST Page Rev.

2of22 36 r.0 PURPOSE 1.1 The purpose of this STP is to log Recirc Pump speeds daily to ensure Recirc Pumps are not operating at a significant speed mismatch and to verify Jet Pump operability. Verification of Jet Pump operability shall be made daily, following startup of a Recirculation Pump, and after any unexplained changes in core flow, Jet Pump Loop flow, Recirc Loop flow, or core plate differential pressure.

1.2 When this procedure is performed in its entirety it FULLY SATISFIES Recirculation Loop Operations Recirc Pump speed mismatch surveillance requirements.

1.3 When this procedure is performed in its entirety it FULLY SATISFIES Jet Pumps surveillance requirements.

2.0 BRIEFING INFORMATION 2.1 PERFORMANCE I NFORMATION 2.1.1 This STP is organized as follows:

STP Sections Evolution 7.1 Recirc Pump Speed Mismatch Check 7.2 Jet Pumps 9-16 Operability Check 7.3 Jet Pumps 1-8 Operability Check 7.4 Jet Pump Trending Data All steps within a section are to be performed in sequence and the STP steps carried through to completion, unless otherwise indicated. The sections may be performed concurrently for ease of recording data.

Sections 7 .2 and 7 .3 are not required to be performed when reactor power is less than or equal to (<) 21.7% RTP. lf this procedure is being performed when reactor power is less than or equal to (<) 21.7% RTP, Prerequisite 6.2 and Sections 7.2 and 7 .3 are to be marked "N/4".

2.1.2 Personnel recommended to perform this procedure 1 Operations 2.1.3 Special Test Equipment required:

None 2.1.4 lf Recirculation Pump speed is less than 60% of rated, an Engineering evaluation may be performed to determine Jet Pump OPERABILITY.

2.1.5 Collect Jet Pump DP values using the "2 MIN AVE" screen on FR-4501 and FR-4502 in Sections 7.2,7.3, andT.4. Any display screen can be used at other times.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAE,C DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

3of22 36 2.2 GENERAL CAUTIONS 2.2.1 None 2.3 SPECIAL PRECAUTIONS 2.3.1 None

3.0 REFERENCES

3.1 None 4.0 GENERAL INSTRUCTIONS 4.1 Steps marked with a "TS" immediately to the right of the step sign-off line are required by Technical Specifications. lf these steps do not meet their acceptance criteria or cannot be performed, a NRC reportable condition may exist and shall be reported to the Control Room Supervisor (CRS) immediately.

4.2 The CRS shall be immediately notified and the appropriate Limiting Condition for Operations section of Technical Specifications referred to whenever problems are encountered during the performance of this STP.

4.3 An Action Request (AR) should be completed for any problems encountered with "TS" marked steps during the performance of this test.

5.0 APPENDICES 5.1 Appendix A - JETS Program lnstructions

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAE,C DUANE ARNOLD ENERGY CENfER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

4of22 36 Appendix A JETS PROGRAM INSTRUCTIONS Sheet 1 o'f 1

1. lf at a workstation desktop with access to PPC, log in to PPC as follows:

a. Click the Windows icon in the lower left corner of the screen.

b. Click Computer: OSDisk (C:): Program Files (x86): Reflection: User: PPC.

c. At Username Prompt, type SSE <Enter>.

d. At Password Prompt, enter the appropriate password and press <Entep. Note that the program will not display any characters, nor will the cursor move, while entering the password.

e, At the $ prompt, type JETS and press <Enter>.

The Jet Pump Program main menu should come up on the screen.

2. lf at a VAX/PPC terminal, log onto SSE as follows:

a. Log onto the SSE account.

b. At the PPCI-SSE prompt, type JETS and press <Enter>. The Jet Pump program main menu should come up on the screen.

3. Type I to access combined Loop A and Loop B Jet Pump tables. Type 2 to access only the Loop A Jet Pump table (Jet Pumps 9-16). Type 3 to access only the Loop B Jet Pump table (Jet Pumps l-8).

NOTE All ÂPs must be a positive value between 0 and 30, but not including 0 (0<lP<30). The program will automatically tab forward as each Jet Pump's AP is entered. The <Tab> key may be used to move forward to the next Jet Pump, if desired. The <Control> and <H> keys pressed simultaneously may be used to move backward to the previous Jet Pump, if desired. lf desired to change a ÂP, use the <Backspace> key to erase all numerals to the left of the decimal point before entering the new numbers.

4. Type in each Jet Pump's AP NOTE lf all fields are not filled with a positive number between 0 and 30, but not including 0 (0<AP<30) when Step 5.0 is performed, the program will not calculate the % deviations and will return to the Jet Pump main menu.

5. Press the <Enter> key to calculate the % deviations. The printout will automatically print on laser printer LTA14 and the program will automatically terminate.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILIW TEST Page Rev.

5of22 36 Prerequisites Performance Date: INITIALS 6.0 PREREQUISITES 6.1 The reactor is in two-loop operation. (lf the reactor is in single loop operation, perform STP 3.4,2-03 instead.) (oPS) 6.2 For sectionsT.2 and 7.3, reactor power is greater than (>) 21'7%RTP (See Performance lnformation Step 2.1.1.) (oPS)

SURVEILLANCE TEST PROCEDURb STP 3.4.2-01 DAE,C DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

6of22 36 Performance Date: INITIALS 7.0 PROCEDURE 7.1 RECIRC PUMP SPEED MISMATCH CHECK 7.1,1 At 1C04, on SIC-92454, A MG SET SPEED CONTROL, perform the following:

a. Use the "D" button to select "X" - PERCENT SPEED and TS record the value:

A MG SET PERCENT SPEED (SlC-92454'X)

b. Use the "D" button to select "S" - SETPOINT.

7.1.2 At 1C04, on SIC-92458, B MG SET SPEED CONTROL, perform the following: -%o

a. Use the "D" button to select "X" - PERCENT SPEED and TS record the value:

B MG SET PERCENT SPEED (SlC-92458.X)

b. Use the "D" button to select "S" - SETPOINT.

7 .1.3 On Figure 1, plot the intersection of the Recirc Pump speed values using the data recorded in Steps 7.1.1.a and -Yo7 .1'2'a.

7.1.4 Confirm that the point plotted on Figure 1 is within the appropriate TS limit for the current core power. lf the point is outside the limit, immediately notify the CRS, (PRTNT / SrGN)

I I

I Performed by: Date: Time: lnit

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAE,C OUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

7of22 36 SPEED OF PUMP 4" Figure 1 Sheet 1 of 1 vs. SPEED OF PUMP "B" LIMIT LIMIT ABOVE OR BELOW UAL TO 69.4o/o 69.4o/o POWER POWER 110 100 N \\ N 90

\

N \

\y

/

OUTSIDE Y

\\

v s Y

s 80 LIMIT o CONDITIONS xS tJ 70 IJJ //

lt, 60

)

f

=

50 K NN \

f 40 30 Y OUTSIDE LIMIT CONDITIONS 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 "8" PUMP SPEED (%)

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILIW TEST Page Rev.

8of22 36 Performance Date: INITIALS 7.2 JET PUMPS 9-16 OPERABILITY CHECK 7.2.1 At 1C04, record the following data for the "4" Recirc Pump:

A MG SET PERCENT SPEED (SlC-92454.X from Step 7.1.1.a)

DTSCHARGE FLOW (Fl-4634A) KGPM LOOP A FLOW (FR-4503, Ch 1) Mlbm/hr 7.2.2 Using the data recorded in Step 7.2.1, plot "A" Recirc MG Set TS speed vs, "4" Recirc Pump discharge flow on Figure 2.

7.2.3 Using the data recorded in Step 7.2.1, plot "4" Recirc MG Set TS speed vs. Loop "A" Jet Pump flow on Figure 3.

NOTE lf Step 7.2.4.a is answered NO, Acceptance Criteria Step 8.2.2 should be answered YES !f either Step 7.2.8.a or Step 7 .2.8.e is answered YES.

7.2.4 Perform the following evaluation

a. Are all of the points that were plotted on Figure 2 and Figure 3 TS between or on the sloped lines?

(YES/NO)

b. lf the answer to Step 7.2.4.a was YES, Jet Pumps 9-16 are OPERABLE. "N/A" the remainder of Section T.2 and Figure 4.

c. lf the answer to Step 7.2.4.a was NO, immediately notify the CRS.

7.2.5 lf the JETS program is available, obtain a printout of "4" Recirc Loop AP's using the instructions provided in Appendix "A".

a. Attach the printout to the STP.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTR TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

9of22 36 Performance Date: INITIALS 7.2.6 lf the JETS program is NOT available, perform the following

a. At 1C38 recorder FR-4501 Jet Pump Flow - Loop A, using the "2 MIN AVE" screen record the indicated RECIRC LOOP A Jet Pump differential pressure value for each Jet Pump in column "4" of Table A (contained in Step 7,2.6.d).

b. Calculate the sum of the individual Jet Pump ÂPs and the average Jet Pump AP and record those values in the appropriate spaces at the bottom of Table A.

c. Calculate the difference between each individual Jet Pump aP and the average AP and record the results in column "8" of Table A.

d. Using the following equation, calculate the percent deviation of each individual Jet Pump aP from the average and record the result in column "C" of Table A. ^P, lnd, AP - Avg. lP

% Deviation = 100 x Avg. lP TABLE A A B c JET PUMP (^P) (lnd.AP - Avg.nP) (% Deviation)

JP-9 JP-I O JP-11 JP.12 JP-13 JP-14 JP.15 JP-16 I

(Sum of APs) (Avs. aP) 7.2.7 Plot each individual Recirc Loop "4" Jet Pump % deviation value (from column "C" of Table A or JETS program calculation) on Figure 4.

SURVEILLANCE TEST PROCEDURb STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

10 of 22 36 Performance Date: INITIALS NOTE lf Step 7.2.8.a is answered NO, Acceptance Criteria Step 8.2.2 shall be answered NO also, unless Recirc Pump speed is less than 60% of rated and an Engineering evaluation determines that the Jet Pumps are OPERABLE.

7.2.8 Perform the following evaluation

a. Are all of the points plotted on Figure 4 on or between the TS lines of the allowable band?

(YES/NO)

b. lf the answer to Step 7.2.8.a is YES, Jet Pumps 9-16 are OPERABLE. "N/A" Steps 7.2.8.c, 7.2.8.d, and T.2.8.e.

c. lf the answer to Step 7.2.8.a is NO and Recirc Pump speed is greater than or equalto (>) 60% of rated, immediately notify the CRS. Then, "N/4" Steps 7.2.8.b,7.2.8.d, andT.2.8.e.

d. lf the answer to Step 7.2.8.a is NO and Recirc Pump speed is less than (<) 60% of rated, immediately inform the CRS and then contact Engineering to perform an evaluation of Jet Pump operability. Then, "N/4" Steps 7.2.8.b andT.2.8.c.

e. lf an Engineering evaluation was performed, are Jet TS Pumps 9-16 OPERABLE? ("N/A" if an Engineering evaluation Engineering is not required to be performed.)

(YES/NO)

(PRTNT / SlGN)

I I

I Performed by: Date Time: lnit.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAE,C DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILIW TEST Page Rev.

11 of 36 22

A MG SET SPEED Figure 2 Sheet 1 of 1 vs. "4" RECIRC PUMP DISCHARGE FLOW TWo Loop Operation

",4," Recirc Pump Flow Curve 35.0 I

i I

I i

30.0 I

I I

2s.0 I i

I I

I f

4 v 20.0

/

1 i

o .1.

i tJr c) b0 I

r L

(g x l o l

(^ I 5 .0 i (

n l I i I

a. I I

E l l

I 't'I 1 0 .0

/ I I

j i

i 5.0 0 0 rO \O rO \O \O 1O 1O \

o\

\O \O 1O 1O 1O \ \O 1O \O 6\ o\ O\ O\ O\ O\ O\ o\ O\ O\ O\ O\ O\ O\ O\ O\ O\

Alr)Otr)Ot.)O .+

lr) lr) a

\o

\o c)ra)c)lr)C)\notno It*tt*OOoOO\O\OO c-l C.l cQ cf) t tr)

MG Set Speed (%)

Last updated from data acquired on November 1-4,2016

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAE,C DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILIW TEST Page Rev.

12 of 22 36

A MG SET SPEED Figure 3 Sheet 1 of 1 vs. LOOP "4" JET PUMP FLOW Ttvo Loop Operation Jet Pump Loop "4" Flow 30.0 25.0 I

1 20.0 ti PTr I

¿ 15.0 o

tr a

o J

I 0.0 5.0 0 .0

\o .O rO : rO \O \O rO \O \o 1O \o \O \O 1 1O 1O \O \O o\ o\ o\ o\ 6\ o\ 6\ \ O\ o\ o\ \ O\ O\ O\ O\ O\ O\ O\

Olr)Olr)Otr)AO (r)

\o lr) AtnO\r)Olr)O oooo\ooo Nc.c.)cos+tr)t\o t-r t--

MC Set Speed (%)

Last updated from data acquired on November 1-4, 2016

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILIW TEST Page Rev.

13 o 22 36 LOOP A JET PUMP % DEVIATION Sheet 1 of Figure 4 vS. JET PUMP NUMBER 1

TWo Loop Operation Loop ttA" Jet Pump Dp o/o Deviation 30.0%

\

./ \

./ \ ./

20.0%

\ ./ \ ,/

\ ,/ -

\ \ /

10.0%

cd

()

â 0.0%

a.

â a.

(,)

1 0 .0o/o

-20.0%

\ ./

\

\ a

-30.0%

9 10 ll t2 13 14 15 16 Jet Pump Number Last updated from data acquired on November 1-4, 2016.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABLIW TEST Page Rev.

14 of 22 36 Performance Date: INITIALS 7.3 JET PUMPS 1-8 OPERABILITY CHECK 7 .3.1 At 1C04, record the following data for the "8" Recirc Pump:

B MG SET PERCENT SPEED (SlC-92458.X from Step 7.1.2.a) o/o DTSCHARG E FLOW (Fl-46348) KGPM LOOP B FLOW (FR-4504, Ch 1) Mlbm/hr 7.3.2 Using the data recorded in Step 7.3.1, plot "8" Recirc MG Set TS speed vs. "8" Recirc Pump discharge flow on Figure 5.

7.3.3 Using the data recorded in Step 7.3.1, plot "8" Recirc MG Set TS speed vs. Loop "B" Jet Pump flow on Figure 6.

NOTE lf Step 7.3.4.a is answered NO, Acceptance Criteria Step 8,2.3 should be answered YES jI either Step 7.3.8.a or Step 7.3.8.e is answered YES.

7.3.4 Perform the following evaluation

a. Are all of the points that were plotted on Figure 5 and Figure 6 TS between or on the sloped lines?

(YES/NO)

b. lf the answer to Step 7.3.4.a was YES, Jet Pumps 1-8 are OPERABLE. "N/4" the remainder of Section 7.3 and Figure 7

c. lf the answer to Step 7.3.4.a was NO, immediately notify the CRS.

7.3.5 lf the JETS program is available, obtain a printout of "8" Recirc Loop AP's using the instructions provided in Appendix "A".

a. Attach the printout to the STP.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAE,C DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

15 of 22 36 Performance Date INITIALS 7.3.6 lf the JETS program is NOT available, perform the following

a. At I C38 recorder FR-4502 Jet Pump Flow - Loop B, using the "2 MIN AVE" screen record the indicated RECIRC LOOP B Jet Pump differential pressure value for each Jet Pump in column "4" of Table B (contained in Step 7.3.6.d).

b. Calculate the sum of the individual Jet Pump APs and the average Jet Pump and record the results in the appropriate spaces^P at the bottom of Table B.

c. Calculate the difference between each individual Jet Pump AP and the average AP and record the result in column "8" of Table B.

d. Using the following equation, calculate the percent deviation of each individual Jet Pump ÂP from the average P and then record the result in column "C" of Table B.

lnd. AP - Avg.

% Deviation = 100 x ^P Avg. lP TABLE B A B c JET PUMP (^P) (lnd.ÂP - Avg.AP) (% Deviation)

JP-1 JP-2 JP-3 JP-4 JP-5 JP-6 JP-7 JP-8 I

(Sum of ÂPs) (Avs. ÂP) 7.3.7 Plot each individual Recirc Loop "8" Jet Pump % deviation value (from column "C" of Table B or JETS program calculation) on Figure 7.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLO ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

16 of 22 36 Performance Date: INITIALS NOTE lf Step 7.3.8.a is answered NO, Acceptance Criteria Step 8.2,3 shall be answered NO also, unless Recirc Pump speed is less than 60% of rated and an Engineering evaluation determines that Jet Pumps are OPERABLE.

7.3.8 Perform the following evaluation

a. Are allof the points plotted on Figure 7 on or between the TS lines of the allowable band?

(YES/NO)

b. lf the answer to Step 7.3.8.a is YES, Jet Pumps 1-8 are OPERABLE. "N/4" Steps 7.3.8.c, 7.3.8.d, and 7.3.8,e.

c. lf the answer to Step 7.3.8.a is NO and Recirc Pump speed is greater than or equal to (>) 60% of rated, immediately notify the CRS. Then, "N/4" Steps 7.3.8.b, 7.3.8.d, and 7.3.8.e.

d. lf the answer to Step 7.3.8.a is NO and Recirc Pump speed is less than (<) 60% of rated, immediately inform the CRS and then contact Engineering to perform an evaluation of Jet Pump operability. Then, "N/4" Steps 7.3.8.b and 7.3.8.c.

e. lf an Engineering evaluation was performed, are Jet Pumps TS 1-8 OPERABLE? ("N/4" if an Engineering evaluation is not Engineering required to be performed.)

(YES/NO)

(PRTNT / SrGN)

I I

I Performed by: Date: Time lnit.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLO ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

17 of 22 36

B MG SET SPEED Figure 5 Sheet 1 of 1 vs. "8" RECIRC PUMP DISCHARGE FLOW Tivo Loop Operation "8" Recirc Pump Flow Curve 35.0 30.0 I

I.

i 25.0 I i

i

-i i

)/

I Yzo 0 llr o

bo L

c ts ls .0 4 t-l

9. T E I i 4 L l

10.0 5.0 0.0 1O \O 1O 1O \o \O \O 1O 1O 1O 1O 1O 1O 1O 1O \O \O 1O o\ o\ o\ o\ e\ o\ o\ o\

lr)

O(Otr)O(.)O Otr)OIr)Otr)Olr)OInO c.tc catsl.) lr) \O\OFtr-oOoOO\O\OO MG Set Speed (%)

Last updated from data acquired on November 1-4, 2016

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILIry TEST Page Rev.

18 of 22 36

B MG SET SPEED Figure 6 Sheet 1 of 1 vs. LOOP "8" JET PUMP FLOW TWo Loop Operation Jet Pump Loop "8" Flow 30.0 I !!

I L

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tl I il it i

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\o lr) olr)olr)o\n<>

ooooO.O'OO c.c.lc +$(r)tr) t-* t*r MG Set Speed (%)

Last updated from data acquired on November 1-4, 2016

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAE,C DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILIW TEST Page Rev.

19 of 22 36 LOOP 8" JET PUMP % DEVIATION Figure 7 Sheet 1 of 1 vs. JET PUMP NUMBER T\vo Loop Operation Loop t'8" Jet Pump Dp o/o Deviation 30.0%

\

\ /

20.0%

\ ./ \ /

\ ./ /

\ / 7 10.0%

(B c) 0 .0%

a t-l a

(.)

I 0 0%

\

-20.0%

\ ./

\ .a

\ ./

-30.0%

1 2 J 45 6 7 8 Jet Pump Number Last updated from data acquired on November 1-4, 2016.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

20 of 22 36 Performance Date INITIALS 7.4 JET PUMPS TRENDING DATA 7 .4.1 At 1C38, record the following Jet Pump DIP (2 Min Ave) from FR-4501 Jet Pump Flow - Loop A. lf data was recorded previously in this STP, 'N/A'this step:

Channel 51, JP-g Channel 52, JP-10 Channel 53, JP-1 1 Channel 54, JP-12 Channel 55, JP-13 Channel 56, JP-14 Channel 57, JP-15 Channel 58, JP-16 7.4.2 At 1C38, record thefollowing Jet Pump DIP (2 Min Ave) from FR-4502 Jet Pump Flow - Loop B. lf data was recorded previously in this STP, 'N/4" this step:

Channel 51, JP-1 Channel 52, JP-2 Channel 53, JP-3 Channel 54, JP-4 Channel 55, JP-5 Channel 56, JP-6 Channel 57, JP-7 Channel 58, JP-8 7.4.3 At 1C38, record jet pump total developed head as read on FR-4502:

Channel I, PDT-4567 psid (PRTNT / SlGN)

I I

Performed by: Date Time: lnit.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAE,C DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABIUry TEST Page Rev.

21 of 36 22 Performance Date INITIALS 8.0 ACCEPTANCE CRITERIA 8.1 Check below the reason for performing this STP. lf this STP is performed for any reason other than for satisfying the PURPOSE as stated in Section 1.0, indicate below (otherwise mark this step "N/4"):

Daily Requirement Pump Start Unexplained changes Other 8.2 All Technical-Specification-required items, as indicated by "TS", have been performed satisfactorily.

8.2.1 Section 7.1 ( ) YES ( ) NO + CRS notified 8.2.2 Section 7.2 ( ) YES ( ) NO + CRS notified 8.2.3 Section 7.3 ( ) YES ( ) NO =+ CRS notified 8.3 All other items checked in this test have been performed satisfactorily.

8.3.1 Section 7.1 ( )YES ( ) NO = CRS notified 8.3.2 Section 7.2 ( ) YES ( ) NO + CRS notified 8.3.3 Section 7.3 ( ) YES ( ) NO + CRS notified 8.3.4 Section 7.4 ( ) YES ( ) NO + CRS notified

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC TITLE: DAILY JET PUMP OPERABILIW TEST Page Rev.

22 of 22 36 f--\' DUANE ARNOLD ENERCY CENTER Performance Date: INITIALS 8.4 lndicate any relevant test comments below, otherwise mark this step "N/4":

/ srGN)

I Operations Date 9,0 ATTACHMENTS 9.1 None

ML17214A036

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ML17214A036

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