Text

Dua 2017 Ile - Proposed Exam Scenarios 1-2-3-Alt
	ML17214A036
Person / Time
Site:	Duane Arnold
Issue date:	06/14/2017
From:	Bielby M; Operations Branch III
To:	; NextEra Energy Duane Arnold
Shared Package
ML16308A458	List: ML17214A027; ML17214A028; ML17214A034; ML17214A036; ML17214A038; ML17214A050;
References
	Download: ML17214A036 (155)
	v • d • e

SEG SIMULATOR EXERCISE GUIDE NEXTETA EYW-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

SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev.0 NEXTETA-EYrc-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:

Prerequisites:

Training Resources:

Evaluation Guide, no tasks are trained None 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 None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance Operating Experience None Risk Significant Operator Actions Protected Gontent:

Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page2 of 24

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

TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE See Cover N/A I nitial development for 2017 NRC LOIT Examination lnitial development lor 2017 NRC LOIT Examination Rev. 0 See Cover DATE REVIEWER AR/TWR#

REASON FOR CHANGE DESCRIPTION OF CHANGE DATE PREPARER 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.

Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 3 of 24

SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev.0 NEXTETA'

,YS*ø RIET OVERVIEW / SEQUENCE OF EVENTS When RPV level is being restored 170-211" the scenario will be terminated I

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) 7 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.

6 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) 5 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.

4 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.

3 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.

2 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.

1 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%.

Description Event #

Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page 4 of 24

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

=YSrg RIET 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

SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev.0 NEXTETA-EYrc-EVENT TRIGGER DEFINITIONS MALFUNCTIONS:

C11AS3 NOTCH OVRRD EMER IN TO EMER-ROD ZDIRDCIlAS3(1)== 1 17 CV-4310 open ZLOPCHS43l0(2)== 1 15 Pump 1P-2114 (Red) to Red ZLOCSHS2103(4)== 1 11 HS-2256(2) AUX OrL PUMP 1P-218 LlTES (RED) TO ON ZLOHPHS2256(2)== 1 5

Manually Activated Manually Activated 1,7,9,13 Trigger Word Description Trigger Loqic Statement Trigger No ACTIVE INACTIVE 13 CONTROL ROD DRIVES IN-ROD O2-19 RD060219 0

AS IS 7:00 7

FW REG VALVE CONTROLLER FAILURE (AUTO)- FWRV B FW128 ACTIVE INACTIVE 5

HPClAux Oil Pump 1P218Trip HP12 Setup ACTIVE ACTIVE LPCI B INJECT VALVE FAILS TO AUTO oPEN - MO-1905 STRH02 Setup ACTIVE ACTIVE LPCI A INJECT VALVE FAILS TO AUTO oPEN - MO-2003 STRHOl Setup ACTIVE INACTIVE 2 SEC 11 4.16 KV/480V BUS FAULT - BUS 1A3 EDOSC Setup 0.05 0

30:00 I

RECIRC LOOP RUPT _ DESIGN BASES LOCA AT 1OO% - LOOP A RR15A Setup ON CRYWOLF 1:00 1

1C08A (A-07) STARTUP XFMR 1X3 TROUBLE AN1C08A(7)

Setup FinalValue lnitialValue Ramp Delav ET Malfunction Title Malf. No.

Time Setup Setup REMOTES ACTIVE INACTIVE 5

HS-2256(2) AUX OIL PUMP 1P-218 LITES (RED)

DO-HP-033 Setup ACTIVE INACTIVE 5

HS-2256(1) AUX OrL PUMP 1P-218 LIrES (GREEN)

DO-HP-032 Setup FinalValue lnitialValue Ramo Delav ET Malfunction Title Malf. No.

Time SCHEDULE FILES CONTROL ROD DRIVES IN-ROD 02-19 Delete malfunction rd06021 9 17 Setup RECIRC LOOP RUPT - DESIGN BASES LOCA AT 100o/o - LOOP A Modify rr15a to 1.5 in 900 15 Setup Description Action Event

@Time ESG 1 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

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

o DAEC is in compliance with all LCO's 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 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%.

Comments, problems, operator workarounds, etc.

o One extra NSPEO available in Work Control o Radwaste Operator is NSPEO qualified a

a a

o a

a Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 PageT of24

NflETA"

=Y6 NRC lNlTlAL LCENSE EXAM, SCENARIO #1 Rev.0 SEG After the crew has assumed the shift:

TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Booth Communicator Respond as plant personnel and respond as necessary INSTRUCTOR ACTIVITY Crew a

Reset the 'B' FRV lockup 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.

EXPECTED STUDENT RESPONSE 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 Cont TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS INSTRUCTOR ACTVITY RO o

. 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.

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.

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

NEXTETA' n.8 NRC lNlTlAL LICENSE EXAM, SCENARIO #l Rev.0 SEG Raise power lf contacted as organization for assistance.

Booth Communicator Respond as plant personneland respond as necessary Raise reactor power by 5%

Raises reactor power by 5o/o IAW lPOl 3 and Ol 856.1 as follows:

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 Direct and observe reactivity manipulations to achieve a 5o/o raise in reactor power CREW a

RO CRS a

a 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 has reduced power, reset the'B'FRV, and at the direction of the Floor lnstructor:

lf contacted as organization for assistance:

lf contacted as operators to inspect the 'B' FRV locally:

Two minutes after being sent to investigate

.B'FRV:

Simulator Operator Activate ET 7.

This will activate FW128 for failure of 'B' FRV Booth Gommunicator Respond as plant personnel and respond as necessary Booth Gommunicator Acknowledge communication Booth Gommunicator lnform control room that nothing abnormal is seen at the FRV Respond to 'B' FRV failure downscale Crew a

RO o Assuming manual control of a malfunctioning system

. Take manual control of the'B'Feedwater controller HC-1621 to restore reactor water level o Place one APRM recorder in each trip system to fast speed to monitor for APRM undamped oscillations greater than normal.

. Verify proper operation/indication of other systems and/or indications

. Verify control rod positions are cotrect for the established sequence, by using Rod Position Log.

. Verify thermal limits on the Official 3D Case.

o When power is stabilized, plot location on the Stability Power / Flow Map.

. Establish critical parameter monitoring of RPV Water Level o Direct entering AOP 644

. May direct entering AOP 255.2 CRS Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page11o124

NEXIETA"

=YX#-

NRC lNlTlAL LICENSE EXAM, SCENARIO #1 Rev.0 SEG After the crew has Reactor water level restored and at the direction of the floor instructor:

lf contacted as organization for assistance:

lf contacted as RE in regards to drifting rod:

Two minutes after contacted as RE:

lf sent to HCU to investigate:

Two minutes after sent to HCU:

When Emergency ln/Notch Override Select is taken to EMER ROD IN:

Simulator Operator Activate ET 13.

This will activate RD060219 with will cause control rod 02-19 to drift in.

Booth Gommunicator Respond as plant personnel and respond as necessary Booth Gommunicator Acknowledge commu nication Booth Gommunicator lnform control room that further analysis is required and inform shortly Booth Gommunicator Acknowledge communication Booth Communicator lnform control room that nothing abnormal is seen at the HCU Simulator Operator VERIFY RDO6O2I9 IS DELETED This will stop rod 02-19 from drifting in Respond to control rod 02-19 drifting in IAWARP 1C05A (D-O).

Place the C11A-S3 EMERG IN/NOTCH OVERRIDE SELECT switch on 1C05 in the EMERG ROD lN position momentarily to abort the rod sequence timer.

Run an OFFCIAL 3D CASE for abnormal reactor power/control rod distributions.

Verify control rod positions are correct for the established sequence, by using Rod Position Log.

When power is stabilized, plot location on the Stability Power / Flow Map.

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.

o Direct entering AOP 255.1

. May direct re-entering AOP 255.2 Notify the Reactor Engineer of the abnormal rod pattern.

. Comply with the Technical Specification requirements for Control Rod Operability LCO 3.1.3 Condition C Crew a

RO a

a a

CRS 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 After investigation of trip of 1.412 and tech spec call and at the direction of the floor instructor:

1 min. after ET 1 goes active:

When contacted to investigate 1X3 alarm:

2 min. after told to investigate 1X3 alarm:

Simulator Operator lnsert ETI This inserts AN1C08A(7), S/U Xfmr trouble alarm after 1:00 minute time delay.

Simulator Operator Verify lC08A [A-71 annunciates.

Booth Gommunicator Acknowledge request.

Booth Gommunicator lnform Control Room there is a Sudden lnternal Pressure Trip Alarm in.

Crew

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

RO

. Send an Operator locally to 1X3 Alarm Cubicle to determine the cause of the alarm.

o With the aid of Table 1, take the appropriate Corrective Action.

. Take 1X3 out of service per Ol 304.1 and O1304.2, (or Ol 304.2 ORC)

CRS r Contact the Electrical Maintenance Supervisor to perform a portable Gas Analysis of the combustible gas.

o Direct taking out 1X3 out of service per Ol 304.2 (or Ol 304.2 ORC)

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

NEXTETA"

=YSxø_

ffi NRC lNlTAL LICENSE EXAM, SCENARO #1 Rev.0 SEG After crew receives report that 1X3 has hi-combustible gas and rising:

lflwhen contacted to verify switchgear rooms clear:

lfAlt/hen contacted as organization:

Booth Communicator Acknowledge request.

Booth Gommunicator Ac knowled ge i nformation/req uests Crew o Take 1X3 out of service IAW Ol 304.2 and Ol 304.2 QRCI RO

. Using Ol304.2QRC1:

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

r Place BUS 143 TRANSFER switch in MANUAL.

o lnsert the handle in the SYNCHRONIZE switch for 4l(/ BREAKER 14301 STANDBY TRANSFORMER TO BUS 143, and place 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.

. 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

F.,ET N=XTera"

=YSre_

NRC lNlTlAL LICENSE EXAM, SCENARIO #l Rev.0 SEG RO 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.

a 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.

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 Gheck that CRS is using Ol 304.2 secton "TFIANS FERRI NG ESSENTTAL BUS 1A3[4] FROM STARTUP TO STANDBY TRANSFORMER" for Tech Spec call.

CRS

. Using O1304.2 section "TRANSFERRING ESSENTIAL BUS 143[4]

FROM STARTUP TO STANDBY TRANSFORMER:

. lf in Mode 1,2, ot 3, verify the following Tech Spec conditions are entered:

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

After 1X3 is taken out of service and Tech Spec has been discussed and at the direction of the floor instructor:

After the crew takes HS-4310 to Auto Open:

When contacted as ITC Midwest:

lf contacted as the organization for assistance:

Simulator Operator lnsert ET 9 This will start a drywell leak.

Simulator Operator Verify ET 15 goes AGTIVE This will increase the size of the leak leading to the crew to scram.

Booth Communicator Acknowledge notification.

Booth Gommunicator Acknowledge request.

Crew Respond to a coolant leak in containment.

a RO CRS Monitor outside barometric pressure utilizing Computer Point M000 to determine if weather conditions are causing a change in indicated drywell pressure.

. 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.

Depress the DIV 1 Reset and DIV 2 Reset pushbuttons to clear the isolation signals.

r Position switches at 1C03 as follows:

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 a

Directs enterAOP 573 CREW o Using Ol 304.1 section "REMOVING THE STARTUP TRANSFORMER (1X3) FROM SERVlCE":

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

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

. 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.

SEG 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"

=Yzaxç NRC INITIAL LICENSE EXAM, SCENARIO #1 Rev.0 SEG After Drywell Pressure exceeds 2 psig lf contacted to investigate 1P-218 breaker:

Two minutes after 1P-218 investigation:

Simulator Operator Verify ET 5 AND ll goes active This will insert HP12 to trip the HPCIAux Oil Pump and ED08C to Lockout Bus 143 Booth Gommunicator Acknowledge request.

Booth Communicator lnform control room that breaker for 1P-218 is tripped on ground fault.

Crew

. lmplements the mitigation strategies of EOP 2, Primary Containment Control RO

. lnforms the CRS of containment parameters including parameter name, value and trend.

o lnstalls Defeat 4.

. Utilizes Ol 149 QRC to spray the torus.

o Utilizes Ol 149 QRC to spray the drywell.

o Utilizes OI 149 QRC to establish torus cooling.

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' ryYk NRC NlTlAL LICENSE EXAM, SCENARO #l Rev.0 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 Emergency Depressurization Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page2} of24

F.EI NEXTETA" ENqllq.a

_/-

nffi NRC lNTIAL LCENSE EXAM, SCENARIO #l Rev.0 SEG Emergency Depress.:

Crew

. 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 opening 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 Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 When RPV level is being restored, the crew is progressing to SDC, and at the direction of the Floor lnstructor:

EOP 1 lmplementation after EOP ED:

Simulator Operator Place the simulator in FREEZE.

Floor lnstructor Announce the scenario is complete; please stand by your stations and do not discuss the scenario with your crew.

Crew

. lmplements mitigation strategies of EOP 1 after EOP ED to restore 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'

- - END OF SCENARIO ***

Page22 of 24

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

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

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

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.

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".

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

UNSAT SAT Task Statement Filename: 1_esg TR-AA-230-1 003-F06 Revision 0 Page24 of 24

STP Page Rev.

3.8.1-01 1of11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CNTER 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:

Date Print Signature Approved By I

Date Print Signature PROCEDURE APPROVAL I

Reviewed By:

I Date:

Print Signature Reviewed By:

I Date:

Print Signature Reviewed By:

Date Print Signature cRoss-DrscrPLrNE REVTEW (As REQUTRED)

STP Page Rev.

3.8.1-01 2of11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CNTER 1.0 1.1 1.2 PURPOSE 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.

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.

BRIEFING NFORMATION 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 One Offsite Circuit Available 7.2 Both Offsite Circuits Available 7.1 Conditions Sect.

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 2.0 2.1

STP Page Rev.

3.8.1-01 3 of 11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CENTER 3.0 3,1

3.2 REFERENCES

Applicable drawings:

3.1.1 BECH-E001<1>

3.1.2 BECH-E005 3.1.3 BECH-E023 Supporting documents:

3.2.1 NG-97-2146 GENERAL INSTRUCTIONS 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.

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.

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

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, 4.0 4.1 4.2 4.3 4.4 5.0 APPENDICES None

INITIALS Performance Date:

Prerequisites STP Page Rev.

3.8,1-01 4of11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLO ENERGY CENTER 6.0 6.1 PREREQUISITES 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

INITIALS Performance Date:

STP Page Rev.

3.8.1-01 5 of 11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CENTER 7.0 7.1 PROCEDURE 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 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.

TS

INITIALS Performance Date:

STP Page Rev.

3.8.1-01 6 of 11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CENTER

b. A circuit exists from an offsite power source, through the 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 TS I

I Performed by:

Date:

Time:

lnit.

INITIALS Performance Date STP Page Rev.

3.8.1-01 7of11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAE,C DUANE ARNOLD ENERGY CENTER 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, through either the Startup or Standby Transformer and its associated supply breakers to both 143 and 144 essential buses.

S

INITIALS Performance Date:

STP Page Rev.

3.8.1-01 I of 11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLO ENERGY CENTER 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 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 either the Startup or Standby Transformer and one of its associated supply breakers to the required 143 or 144 essential bus.

(PRTNT / SrGN)

TS TS I

I I

Performed by Date Time:

lnit.

ir

INITIALS Performance Date:

STP Page Rev.

3.8.1-01 9 of 11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CENTER 8.0 8.1 8.2 8.3 ACCEPTANCE CRITERIA 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:

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 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

INITIALS Performance Date STP Page Rev.

3.8.1-01 10 of 11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CENTER 8.4 lndicate any relevant test comments below, othenryise mark this step "N/4" (PRTNT / SrGN)

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

Attachment't DAEC DUANE ARNOLD ENERGY CENTER DAEC OFFSITE POWER CIRCUITS FEEDING ESSENTIAL BUSES SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES Sheet I of 1 sTP 3.8.1-01 Page 11 of 11 Rev. 5 Dysart Sub L2 31 10

'B' 0220 Unacceptable path for the of this STP 0710 4730 2820 8090 9180 2690 6780 4290 5950

.AB' 7510 "c'

Hills Sub Sub Hazelton Bus East 345KV West Bus Downtown lndustrial Line Hawatha Sub 5550 E490 5560 "tc 1A 40'l IA 301

,IA 402 302 1A3 LA4 161KV East Bus 161KV West Bus Power Source Transformer Breaker Bus Farfax 5ub

SEG SIMULATOR EXERCISE GUIDE NEXTETA-

=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 TR-AA-230-1 003-F06 Revision 0 Page 1 of 25

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

,Y*x6 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."

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

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:

O1644, Rev. 172 lPOl 2, Rev. 154 O1264, Rev. 138 Ol 856.1, Rev. 48 Ol 856.2, Rev.9 Ol 878,8, Rev.27 AOP 255.1, Rev. 46 ARP 1C034, Rev, 58 ARP 1C048, Rev. 81 ARP 1C084, Rev.92 EOP 3, Rev.22 EOP Defeat 15, Rev. 7 ARP 1C058, Rev, 105 EOP 1, Rev. 20 ATWS, Rev.23 O1644 QRC 2, Rev Q. Ol 149 QRC 4, Rev.

R. Ol 734 QRC 1, Rev.

S. Ol 153 QRC 1, Rev.

ProtectedContent: None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance A.

B.

c.

D.

E.

F.

G.

H.

t.

J.

K.

L.

M.

N.

o.

P.

0 0

0 4

Operating Experience:

Risk Significant Operator Actions:

None Filename:2-esg TR-AA-230-1 003-F06 Revision 0 Page 2 ot 25

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

ÉY4-Direct Crew Res SE to

/Q to reduce r/scram the reactor duri ATWS Direct Crew Res SE to

/P to control RPV re durin an ATWS 6.57 6.56 Direct Crew se to Perform Power/Level Control Direct Crew SE to Perform lnitialATWS Actions 6.55 6.51 Direct Crew se for of initial EOP 1 actions RC Direct Crew SE to Perform /L to Control Level an ATWS 6.50 6.45 Direct Crew tol into the RPV with SBLC from the Boron Tank 6.42 Direct Crew to Perform EOP Defeat 11 6.21 Direct Crew to Condenser Hi h

ure 5.50 Determine OperabilitY for Techn ical Specification Required Components 1.02 Senior Reactor O rator Perform /Q to Reduced Reactor Power or SCRAM the Reactor 95.57 Perform /P to Control RPV Pressure Durin an ATWS 95.56 Perform lnitial ATWS Actions 95.55 Perform Power/Level Control 95.51 Perform lnitial EOP 1 Actions Perfo rm /L to Control RPV Level d an ATWS 95.50 95.45 Perform EOP Defeat 11 ln into the RPV with SBLC from the Boron Tank 95.42 95.21 Perform a Fast Power Reduction nd to Condenser H h

re 94.50 93.21 Manual De or lnte ADS Auto lnitiation 8.11 Reactor Operator Task Title Task #

TASKS ASSOCIATED wlTH SIMULATOR EXERCI SE GUIDE See Cover Rev. 0 lnitial development for 2017 NRC LOIT Examination N/A I nitial development for 2017 NRC LOIT Examination See Cover REVIEWER DESCRIPTION OF CHANGE AR/TWR#

REASON FOR CHANGE DATE 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 form TR-AA-230-1 003-F16.

Or use Filename:2_esg TR-AA-230-1003-F06 Revision 0 Page 3 of 25

SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 NFX] ETA ENERGY_Ø OVERVIEW / SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE 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.

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

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.

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.

3 A grid voltage transient causes 'A' SB fails to maintain voltage. The crew wi

'A'SBDG inoperable, and enter LGO DG to spuriously start, and the Voltage Regulator ll place the 'A' SBDG handswitch to PTL, declare the 3.8.1, Gondition B and LCO 3.7.3 Condition A.

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.

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 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' Event #

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

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

=Y,ffi 1.

2.

3.

SIMULATOR SET UP INSTRUCTIONS Set NRC Exam Security for the Simulator per QF-1071-08 Perform simulator set up per TDAP 1839 Attachment 2, Simulator Setup Checklist.

Load the saved lC (in folder with this ESG) to a SNAPSHOT reset to that SNAPSHOT and place the Simulator in RUN, OR 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' RUN Schedule File "Actions.sch" and LEAVE lT RUNNING.

Verify Malfunctions.

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

Verify Overrides.

Ensure MOL pull sheet is in the 1C058 hanging file' Establish EOOS conditions for OOS components and plant conditions 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 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 4

5.

7.

8.

9.

10 11 12 Filename:2_esg TR-AA-230-1 003-F06 Revision 0 Page 5 of 25

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

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

=Yr6 EVENT TRIGGER DEFINITIONS Reactor Mode Switch out of RUN RPDISIRUN(1) l= 1 11 HS-6514 RX BLDG SUPPLY FAN 1V-SF-10C to START ZDlHVHS6514== 1 o

'A' SBDG control HS in PTL ZDIDGDGI(1)== I 7

MANUALLY ACTIVATED MANUALLY ACTIVATED 1,3,5,17 Trigger Word Description Trigger Logic Statement Trigger No.

MALFUNCTIONS 0

0 SBLC INJECT VALVE V-26-9 STUCK SLO4 Setuo ACTIVE INACTIVE 1:30 11 RD HYDRAU MP TRIP - PUMP RD11B Setup ACTIVE INACTIVE 1:00 11 CRD PUMP'B' HIGH VI BRATION RD26B ACTIVE ACTIVE CRD HYD MP TRIP - PUMP RD11A Setup ACTIVE ACTIVE ALL INDIVIDUAL ROD SC RAM SWITCHES FAIL RPOsE S

0.35 0

6:00 5

STEAM IN STEAM TUNNE A

MSOSA ACTIVE ACTIVE CR RPIS REED SW FAILURE OPEN-ROD 18-27 RD0441827 Setup 45 50 3

POWER GRID VOLTAGE TRANSIENT (DELETE in 1 SEC)

EDO3 Setup 45 0

3 POWER GRID FREQUENCY DISTURBANCE (DELETE in 1 SEC)

EDO2 Setup ACTIVE INACTIVE 3

1G31 'A' DIESEL GENERATOR SPURIOUS START-DG A

DGOTA 100 0

30 SEC 5 SEC 3

1G31 'A'DIESEL GENERATOR V/R OSCILLATES IN AUTO-DGOSA ACTIVE INACTIVE 06:00 3

1G31 'A'D GENERATOR TRIP-A DGO3A Setuo CRWVOLF CRWVOLF 3 SEC 1

1C034 (B-04) OFFGAS VENT PIPE RM-4116 A/B HI AN1C03A(13)

Setup ACTIVE INACTIVE 3 SEC 1

RE-41168 OFFGAS VENT PIPE B RMO3RE41 168 Setup ACTIVE ACTIVE TRIP OVRD-RCIC FAILS TO AUTO START STRCOl Setuo ACTIVE ACTIVE TWS)- ARI FAILURE RPS SCRAM CIRCUIT FAILURE (A RPOSC Setup ACTIVE ACTIVE RPS SCRAM CIRCUIT FAILURE (ATWS)- MANUAL SC FAILURE RPOSB Setup ACTIVE ACTIVE RPS SCRAM CIRCUIT FAILURE (ATWS)- AUTO SCRAM FAILURE RPOSA Setup 100 100 LVE CV1158A/B FAI

- cv1 1588 MS18B 100 100 VALVE CV1158A/B FAILURE - CV1158A MS18A Setup Final Value lnitial Value Ramp Delay ET Malfunction Title Malf. No Time Setup Setup REMOTES:

ACTIVE ACTIVE HS-18074(3) CRD PUMP 1807 TRIPPED (RED)

BREAKER DO-RD-617 ACTIVE ACTIVE HS-1807A(2) CRD PU MP 1807 BREAKER TRIPPED DO-RD-616 Setup ACTIVE ACTIVE HS-1807A(1)CRD PUMP 1 807 BREAKER TRIPPED GR DO-RD-615 Setup OPEN CLOSED 02:30 17 M N co N D I E-7B VAC U U M BREAKER V-03-67 MC02 Setup OPEN CLOSED 02:00 17 MN coN D 1 E-7A VAC U U M BREAKE R V-03-73 MC01 Setup Final Value lnitial Value Ramp Delay ET Remote Title Remote No.

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

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

=Y"&

SCHEDULE FILES Modifv malfunction msO8a to 0.6 in 300 I

1G31 'A' DIESEL GENERATOR TRIP-DG A Delete malfunction dg03a 7

Setup Descri Action Event

@ Time Actions.sch 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

SHIFT TURNOVER INFORMATION SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 NEXTETA' EYx6:t 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 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 Comments, problems, operator workarounds, etc' o One extra NSPEO available in Work Control o Radwaste Operator is NSPEO qualified O

a Filename:2_esg TR-AA-230-1 003-F06 Revision 0 Page 9 of 25

NE)CETA'

=Yrç NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG rPot 2 TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS INSTRUCTOR ACTIVITY 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 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

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

NEXTETA

=ysre_

NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG Raise Power Cont.

TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS INSTRUCTOR ACTIVITY RO 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 EXPECTED STUDENT RESPONSE Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page 11 ot25

NCIETA' NRC lNlTAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG Shift FRVfrom S/U to'A' o1644 TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Booth Communicator Acknowledge coordi nation INSTRUCTOR ACTIVITY CREW RO CRS a

a Shift FRV from the S/U FRV to the 'A' FRV 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.

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

EXPECTED STUDENT RESPONSE 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 Control Rod Position Lost AOP 255.1 lF called as any DAEC support personnel:

lf contacted as RE for substituting position for rod 18-27:

Two minutes after contacted as RE:

TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Booth Gommunicator Acknowledge coordination Booth Gommunicator Acknowledge commu nication Booth Gommunicator Report to the control room that you concur with substituting rod position for rod 18-27 and to continue with startup.

INSTRUGTOR ACTIVITY CREW Perform the Follow Up Actions of AOP 255.1 for Abnormal Rod Control and Position lndications For rod position indication lost at one notch:

o Attempt to move the affected rod, as allowed by rod sequence, to an adjacent notch to check for reed switch failure 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 Direct the performance of AOP 255.1 forAbnormal Rod Control and Position lndications Consult with Reactor Engineer to enter Substitute Rod Position into 3D Monicore per REDPT Section 3.7, Substituting Rod Positions ln 3D Monicore.

a RO a

CRS a

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

=Ytsg NEXTETA' NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG Position Substitution 878.8 TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS INSTRUCTOR ACTIVITY CREW a

Substitute notch position IAW Ol 878.8 Section 8.2 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

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

NEXTETA"

=Y4 NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG Offgas Vent Pipe RM Downscale After crew has inserted rod 18-27 to position 06 and/or when directed by the Floor lnstructor:

lf contacted to investigate 1 D60:

lF called as any DAEC support personnel:

TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Simulator Operator:

ACTIVATE ET 1 This causes RE-41168 OFFGAS VENT PIPE B to fail.

Booth Communicator:

After 2 minutes, inform control room that Breaker 03 for 1D60 is closed in with no noticeable problems.

Booth Gommunicator:

Acknowledge Request INSTRUCTOR ACTIVITY CREW a

Respond to annunciators per ARP 1C034 (C-4)

RO a

At 1C10, monitor OFFGAS STACK VENT PIPE B RAD MONITOR RM-41168 to determine if DOWNSCALE or INOPERATIVE.\\

Send an Operator to the following panels to verify the breakers closed/reset:

o RM41168 - 1D60 Breaker 03 a

CRS.

Determine affected Tech Spec LCO 3.3.6.1 o Function 2c Offgas Vent Stack - High Radiation - Channel B o Determine not in mode of applicability EXPECTED STUDENT RESPONSÉ 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 When directed by the Floor lnstructor:

lF called as any DAEC support personnel:

lf contacted to investigate'A' SBDG:

Three minutes after requested to investigate

.A'SBDG:

lf contacted to verify operation of 'A' ESW:

Two minutes after requested to verify operation'A' ESW:

TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Simulator Operator:

ACTIVATE ET 3 This causes a momentary grid disturbance. 'A' SBDG will spuriously start and its voltage regulator fail.

Booth Gommunicator:

Acknowledge Request Booth Gommunicator:

Inform control room that'A'SBDG appears to be normal and all alarms at 1C93 are as expected.

Booth Gommunicator:

Acknowledge Request Booth Gommunicator:

lnform control room that'A' ESW is operating SAT.

INSTRUCTOR ACTIVITY CREW a

Respond to annunciators perARP 1C084 (A-10)

RO. Verify that EMERG SERV WATER PUMP 1P-994 is running.

o Verify 1V-SF-20 Diesel Generator Supply Fan is running.

. 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).

CRS a

f SBDG 1G-31 is determined to be inoperative, comply with the Technical Specification requirements for AC Sources-Operating and AC Sources-Shutdown.

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

NEXTETA'

=ysre_

NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG When the crew places the 'A' SBDG in PTL:

lf the crew requests a copy of sTP 3.8.1-01 and/or STP 3.8.1-02:

TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Simulator Operator:

VERIFY ET 7 ACTIVATES This deletes malfunction dg03a.

Simulator Operator:

lf the crew does not take the 'A' SBDG to PTL prior to the auto trip:

Pause "Delete malfunction dg03a" in Actions.sch AND INSERT ET 7 Evaluator Note:

lf the crew does not place 'A' SBDG in PTL in 6 minutes, it will trip on generator lockout.

Floor Evaluator:

Give the crew the requested copy of STP 3.8.1-01 and/or STP 3.8.1-02 INSTRUCTOR ACTIVITY Determine that'A' SBDG is not operating correctly and secure it by placing the handswitch HS-32314 in PTL.

a Place'A'SBDG handswitch HS-32314 in PTL Determine that the 'A' SBDG is INOPERABLE and enter appropriate Tech Specs LCO 3.8.1, Condition B

. 8.1, Perform SR 3.8.1.1 for Operable offsite circuits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 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 inoperability of redundant required feature(s).

o 8.3 Determine OPERABLE DG is not inoperable due to common cause failure within 24 hrs.

o 8.4 Perform SR 3.8.1.2 for OPERABLE DG once per 72hrs.

. 8.5 Restore DG to OPERABLE Status within 7 days.

CREW RO CRS a

a a

EXPECTED STUDENT RESPONSE Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page17 of25

NEX rCfa' YPYK NRC lNlTlAL LCENSE EXAM, SCENARIO #2, Rev.0 SEG TIME/NOTES EOP 3 Steam Leak in Steam Tunnel After SBDG has TS has been declared and at the direction of the Floor lnstructor:

INSTRUCTOR ACTIVITY Simulator Operator:

ACTIVATE ET 5 This will insert MS08A to start the Steam Tunnelsteam leak.

(NOTE: Bring up EOPSLD and monitor Steam Tunnel Temperature)

SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS EXPECTED STUDENT RESPONSE CREW Respond to annunciators perARP 1C048 (B-4), STEAM LEAK DET AMBIENT HITEMP/EOP 3.

Send an Operator to 1C21to determine which area has the high temperature condition.

Start 1V-EF-1,1V-EF-Z and 1V-EF-3 MAIN PLANT EXHAUST FANS by positioning the following handswitches to START and verify their respective dampers indicate OPEN:

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 lnsert manual reactor scram RO a

a a

a 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 EOP 1 Transition to ATWS EOP 3 Cont.

TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS INSTRUCTOR ACTIVITY CREW a

lmplements the mitigation strategies of EOP 1 and EOP ATWS ROo 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.

CRSo 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".

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.

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

NEXTETA' NRC INITIAL LICENSE EXAM, SCENARIO #2, Rev. 0 SEG ATWS lf directed to vent the scram air header:

Three (3) minutes after being directed to vent the scram air header:

TIME/NOTES SMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Booth Gommunicator:

Acknowledge the request.

Booth Gommunicator:

lnform the control room that you cannot vent the scram air header due to the valve being bound.

INSTRUCTOR ACTIVITY Crew a

lmplements the mitigation strategies of EOP 1 and EOP ATWS RO.

Locks out ADS (CRITICAL)

. Performs the ATWS QRC.

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

. Announces failure to scram.

. Reports SBLC inject pressure high and no flow.

o lnstalls Defeat 11.

Directs locking out ADS.

o Verifies at least one set of inboard and outboard MSIVs are not open.

. Directs performance of the ATWS QRC.

o Directs initiation of SBLC.

o Directs electricalATWS rod insertion procedures

. Exits the ATWS "Q" leg flowpath and enters "L" leg actions RS c

EXPECTED STUDENT RESPONSE Filename:2_esg TR-AA-230-l 003-F06 Revision 0 Page 20 of 25

NEXTETA

=Yrç NRC lNlTAL LICENSE EXAM, SCENARIO #2, Rev.0 SEG ATWS TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Evaluator Note:

Ensure that while level is lowering that the RO acknowledges RCIC failure to auto start and recommends starting RCIC.

INSTRUCTOR ACTIVITY Crew lmplements AOP ATWS power level control actions RO o

a a

a Verifies or trip/lockout HPCI.

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 controller down until all Feedwater Regulating Valves indicate closed as indicated on:

. HC-1579, A Feed Reg Valve Manual/Auto Transfer

. HC-1621, B Feed Reg Valve Manual/Auto Transfer

. HC-1622, Startup Feed Reg Valve Manual/Auto Transfer 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 Recognizes that RCIC did not start automatically Starts RCIC manually.

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

. 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.

o a

a CRS EXPECTED STUDENT RESPONSE 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 When all rods are full in:

lF directed to break Main Condenser Vacuum:

ATWS TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Simulator Operator:

Acknowledge the direction, then ACTIVATE ET 17 This inserts remote functions mc01 and mc02.

INSTRUCTOR ACTIVITY 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)

Controls level 170"-211" using Condensate and Feedwater (cRrTrcAL) a cRS.

Directs transition back to EOP 1 Directs RPV level 170"-211" using Condensate and Feedwater EXPECTED STUDENT RESPONSE Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page22 of 25

NEXTETA" ENERGYØ ffi NRC lNlTlAL LICENSE EXAM, SCENARIO #2, Rev.0

- " END OF SCENARIO ***

SEG When the crew has inserted all control rods and is restoring RPV Water Levelto >170" and.at the direction of the Floor lnstructor:

TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Booth Instructor Place the simulator in FREEZE.

Floor lnstructor Perform a crew update and announce to the crew the simulator is in freeze and the scenario is complete.

INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Filename: 2_esg TR-AA-230-1 003-F06 Revision 0 Page 23 of 25

.l SEG NRC lNTIAL LICENSE EXAM, SCENARIO #2, Rev. 0 NEXIETA" eW 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 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

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

,Y,&

CREW GRADING ATTACHMENT ESG 2 Rev. __ !_

Date B.O.P 1C03 1C05 STA CRS OSM Evaluator Position Operator Name Management Representative/Lead Evaluator Crew Critical Tasks I

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.

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.

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

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

STP Page Rev.

1of 1

5 3.8.1-0 1 1

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAE,C DUANE ARNOLD ENERGY CENTER 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 Reviewed By:

Date Print Signature cRoss-DlsclPLlNE REVIEW (AS REQUIRED)

Approved By I

Date Print Signature PROCEDURE APPROVAL

STP Page Rev.

3.8.1-01 2of11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CENTER 1.0 1.1 PURPOSE 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.

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.

BRIEFING INFORMATION 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:

One Offsite Circuit Available 7.2 Both Offsite Circuits Available 7.1 Conditions Sect.

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 1.2 2.0 2.1

STP Page Rev.

3.8.1-01 3 of 11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CENTER 3.0 3.1 3.2 4.0 4.1 4.2

4.3 REFERENCES

Applicable drawings:

3.1.1 BECH-E001<1>

3.1.2 BECH-E005 3.1.3 BECH-E023 Supporting documents:

3.2.1 NG-97-2146 GENERAL INSTRUCTIONS 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.

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.

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

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.

4.4 5.0 APPENDICES None

INITIALS Performance Date:

Prerequisites STP Page Rev.

3.8.1-01 4of11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CENTER 6.0 6.1 6.2 PREREQUISITES Verify Offsite power is supplying essential buses 143 and 1A4 via either the startup transformer (normal source) or the standby transformer (alternate source).

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

INITIALS Performance Date STP Page Rev.

3.8.1-01 5 of 11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CENTER 7.0 7.1 PROCEDURE 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 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.

TS

INITIALS Performance Date STP Page Rev.

3.8.1-01 6 of 11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CENTER

b. A circuit exists from an offsite power source, through the 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)

TS I

I I

Performed by:

Date:

Time:

lnit

INITIALS Performance Date STP Page Rev.

3.8.1-01 7of11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAE,C DUANE ARNOLD ENERGY CENTER 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.

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.

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

TS

INITIALS Performance Date:

STP Page Rev.

3.8.1-01 I of 11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAE,C DUANE ARNOLD ENERGY CENTER 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 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 either the Startup or Standby Transformer and one of its associated supply breakers to the required lA3 or 144 essential bus.

(PRTNT / SrGN)

I TS TS I

I Performed by:

Date Time:

lnit.

INITIALS Performance Date:

STP Page Rev.

3.8.1-01 9 of 1l 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAEC DUANE ARNOLD ENERGY CENTER 8.0 8.1 8.2 8.3 ACCEPTANCE CRTERIA 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:

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 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

INITIALS Performance Date STP Page Rev.

3.8.1-01 10 of 11 5

SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES DAE,C OUANE ARNOLD ENERGY CENTER 8.4 lndicate any relevant test comments below, othenruise mark this step "N/4" (PRTNT / SrGN)

I 9.0 9,1 Operations Date ATTACHMENTS Attachment I - DAEC Offsite Power Circuits Feeding Essential Buses DAEC DUANE ARNOLD ENERGY CENTER DAEC OFFSITE POWER CRCUITS FEEDING ESSENTIAL BUSES SURVEILLANCE TEST PROCEDURE TITLE: OFFSITE POWER SOURCES Sheet 1 of 1 STP Page Rev.

3.8.1-01

'11 o 11 5

Dysart Sub 0220 Unacceptable path for the of this STP 7510 67E0 5950

AB" 8090 2690 "D"

Hills Sub Sub Hzelton T,I "s"

Bus Bus East 345KV West Downtown lndustriâl Line Hawatha Sub 31 10 "8"

9180 8490 5550 1A 301 1A 401 1A 302 402 1A3 144 "K'

5560 16lKV West Bus 161KV East Bus Power Source Transformer Breaker Bus Ferfex Sub

STP Page Rev.

3.8.1-02 1of7 6

SURVEILLANCE TEST PROCEDURE TITLE ONE STANDBY DIESEL GENERATOR INOPERABLE DAE,C DUANE ARNOLD ENERGY CENTER Usage Level CONTINUOUS Approved fo, i!lg[1@]

printing lF NO Temporarv Chanqes are in effect for this procedure.

Record the following: Date / Time 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.

I Prepared By:

Date:

Print Signature Approved By I

Date:

Print Signature PROCEDURE APPROVAL BY QUALIFIED REVIEWER I

Reviewed By:

I Date Print Signature Reviewed By I

Date:

Print Signature Reviewed By I

Date:

Print Signature cRoss-DtsctPlrNE REVTEW (AS REQUIRED)

STP Page Rev.

3.8.1-02 2o' 7 6

SURVEILLANCE TEST PROCEDURE TITLE ONE STANDBY DIESEL GENERATOR INOPERABLE DAE,C DUANE ARNOLD ENERGY CENTER 1.0 1.1 1.2 2.0 2.1 2.2 2.3 3.0 3.1 PURPOSE The purpose of this test is to implement the REQUIRED ACTIONS of LCO 3.8.1 when one Diesel Generator is inoperable.

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.

BRIEFING INFORMATION PERFORMANCE INFORMATION 2.1.1 Testing is organized as follows:

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

1 Operations 2.1.3 Special Test Equipment required:

None GENERAL CAUTIONS 2.2.1 None SPECIAL PRECAUTIONS 2.3,1 None REFERENCES Associated STPs:

3.1.1 STP 3.8.1-01 3.1.2 STP 3.8.1-03 ODI-8, LCO Surveillance Log and Flag GENERAL INSTRUCTIONS 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.

3.2 4.0 4.1

STP Page Rev.

3.8.1-02 3of7 6

SURVEILLANCE TEST PROCEDURE TITLE ONE STANDBY DIESEL GENERATOR INOPERABLE DAEC DUANE ARNOLD ENERGY CENTER o

5.0 5.1 APPENDICES None

INITIALS Performance Date Prerequisites STP Page Rev.

3.8,1-02 4of7 o

SURVEILLANCE TEST PROCEDURE TITLE ONE STANDBY DESEL GENERATOR INOPERABLE DAEC DUANE ARNOLD ENERCY CENTER 6.0 6.1 PREREQUISITES None

INITIALS Performance Date STP Page Rev.

3.8.1-02 5of7 6

SURVEILLANCE TEST PROCEDURE TITLE ONE STANDBY DIESEL GENERATOR INOPERABLE DAEC DUANE ARNOLD ENERGY CENTER 7.0 7.1 PROCEDURE 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 7.1.3 Perform STP 3.8.1-01 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).

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

INITIALS Performance Date:

STP Page Rev.

3.8.1-02 6o'f7 6

SURVEILLANCE TEST PROCEDURE TITLE ONE STANDBY DIESEL GENERATOR INOPERABLE DAE,C DUANE ARNOLD ENERGY CENTER 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:

7.2 OTHER ACTIONS FOR ONE SBDG INOPERABLE 7.2.'l Date:

Time 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

INITIALS Performance Date:

STP Page Rev.

3.8.1-02 7 of 7 6

SURVEILLANCE TEST PROCEDURT TITLE ONE STANDBY DIESEL GENERATOR INOPERABLE DAEC DUANE ARNOLD ENERGY CENTER 8.0 8.1 8.2 8.3 9.0 9.1 ACCEPTANCE CRITERIA 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"):

All steps of this STP have been performed satisfactorily:

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

Operations Date Surveillance Coordinator Date ATTACHMENTS None

SEG SIMULATOR EXERCISE GUIDE NEXTETA'

,Y1.

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

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

=Y6 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. Evaluated tasks are listed on page 4 Prerequisites:

None Training Resources:

References:

A.

B, c.

D.

E.

F.

G Simulator Evaluation team Operations Management Representative Simulator Driver Phone Talker Exam Proctor for custody of the crew between scenarios Simulator Video recording equipment A. AOP 255.1, Rev. 46 B. AOP 672.2, rev.37 C. AOP 901, Rev. 29 D. ARP 1C034, Rev.54 E. ARP 1C038, rev 41 F. ARP 1C03C, rev43 G. ARP 1C048, Rev. 80 H. ARP 1C05A, Rev. 81

l. ARP 1C058, Rev. 104 J, ARP 1C064, rev 70 K. ARP 1C078, rev 89 L. ED, Rev.10 M, EOP 1, Rev. 19 N. EOP 3 EOP 4, Rev. 21 O. Ol 255, Rev. 89 P. O1414. Rev.40 ProtectedContent: None Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance Operating Experience:

N/A Risk Significant Operator Actions:

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

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

,YSx6 Perform internal and external notifications 4.09 Verifv EAL determination 4.08 Recommend Mitigation Strategies for Accidents Ps) 4.07 Direct Crew Response to Abnormal Control rod Movement/lndication 5.02 Direct Crew Response to Earthquake Condition 5.22 Direct Crew Response for performance of EOP3 for high area temperature/radiation/water level including EOP 1 and ED 6.67 Direct Crew Response for performance of EOP 3 for high area temperatures/radiation /water level including commencement of a plant shutdown 6.68 Direct Crew Response for performance of Emergency Depressurization 6.78 Direct Crew Response for performance of RC/P leg of EOP 1 6.46 Direct Crew Response for performance of the RC/L leg of EOP 1 6.44 Direct Crew Response for performance of initial EOP 1 actions (RC) 6.45 Direct Crew Response for performance of Defeat 11 6.21 Direct Crew Response for Performance of EOP 4 6.72 Senior Reactor Operator Respond to Abnormal Control rod Movement/lndication 94.02 Respond to Earthquake Condition 94.22 Perform a Fast Power Reduction 93.21 Perform actions of EOP 3 for hi area temp, rad, and water level including commencement of plant S/D.

95.70 Manually lnsert A Scram Before Any Area Parameter Reaches Maximum Safe Operatinq Limits 95.69 Perform Actions of EOP3 for High Area Temp, Rad, Water Level lncluding EOP 1 and ED 95.68 Perform an Emeroencv Depressurization Usinq SRVs 95.80 Perform Defeat 11 95.20 Perform actions of RC/P of EOP 1 95.46 Perform actions of RC/L of EOP 1 95.44 Perform initial EOP 1 actions (RC) 95.45 Reduce Offsite Radioactivity Release Rate with a Primary System Discharging Outside of Containment 95.72 Perform Actions of EOP 4 95.71 Reactor Operator Task Title Task #

TASKS ASSOCIATE WITH SIMULATOR EXERCISE GUIDE See Cover N/A lnitial development for 2017 NRC LOIT Examination lnitial development for 2017 NRC LOIT Examination Rev.0 See Cover DATE REVIEWER AR/TWR#

REASON FOR CHANGE DESCRIPTION OF CHANGE DATE PREPARER 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.

Page 3 of 32 Filename:3_esg TR-AA-230-1003-F06 Revision 0

NEXTETA

=Y6 NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG OVERVIEW / SEQUENCE OF EVENTS After the ED, when the crew has depressurized the RPV and is recovering RPV Water level to the directed band, the scenario is complete.

8.

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) 7 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) 6.

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

5 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.

4 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.

3 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.

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

1 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.

Description Event #

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

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

=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 i ng\\S ched u le d i rectory.

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.

1 1. 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

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

=Yjçt,&

EVENT TRIGGER DEFI NITIONS:

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

Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page 6 of 32

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

=Ysr6 I

MALFUNCTIONS:

etup Setup ON CRYWOLF 26 1C058 (E-08) PCIS GROUP'5' ISOLATION INITIATED AN1C05B(40)

Setup 0.62 AS IS 10:00 12:00 28 RM5945 KAMAN 2 TB NORM MONITOR FAILURE (NEW)

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

RMO9RM5945 Setup 0.031 AS IS 2:30 4:30 28 RM5945 KAMAN 2 TB NORM MONITOR FATLURE (NEW)

RMO9RM5945 Setup 0.005 AS IS 30 SEC 4:00 28 RM5945 KAMAN 2 TB NORM MONITOR FAILURE RM09RM5945 Setup 100 100 MSIV DISC FAILURE-OTBD MSIV A MSO5B Setup 0

0 24 TURBINE BYPASS VALVE FAILURE-BV-2 TC06B Setup 0

0 24 TURBINE BYPASS VALVE FAILURE-BV-1 TC06A Setup 0.01 0

20:00 05:30 30 FUEL CLADDING FAILURE RXOl Setup 0.5 0

02:00 04:00 28 MSL RUPTURE OUTSIDE PRIMARY CONTAINMENT.

STM LINE A MSO4A Setup 1.5 0

07:00 2:00 22 COOLANT LEAKAGE OUTSIDE THE PRIMARY CONTAIMENT cu10 Setup ACTIVE INACTIVE 14 BREAKER TRIP 1D1401 FOR MO24O1 D228 Setup 75 0

07:00 10 SEC 18 RCIC STEAM SUPPLY LINE BREAK (RCIC ROOM)

NEW RC06 25 0

07:00 1O SEC 3

RClC STEAM SUPPLY LINE BREAK (RCIC ROOM)

RC06 100 0

5 SEC 3

RCIC ROOM COOLER ESW FLOW BLOCKAGE. 1V-AC-158 SW148 Setup 100 0

5 SEC 3

RCIC ROOM COOLER ESW FLOW BLOCKAGE-1V-AC-154 SWl4A Setup ACTIVE ACTIVE MO24OO THERMAL OVERLOAD BREAKER TRIP RClOA Setup ACTIVE ACTIVE GROUP 6 TSOLATTON VALVE(S) FAIL(S) TO CLOSE-M02401 MS31B Setup ACTIVE ACTIVE GROUP 5 TSOLATTON VALVE(S) FAIL(S) TO CLOSE-MO2740 M528C Setup ACTIVE ACTIVE GROUP 5 TSOLATTON VALVE(S) FAIL(S) TO CLOSE-MO2701 M528B Setup ACTIVE ACTIVE cRoup 5 tsoLATroN vALVE(s) FAIL(S) TO CLOSE-M02700 MS28A Setup 100 100 MSIV DISC FAILURE-INBD MSIV A MSOSA Setup ON ON 1C03A (A-09) 'A' CORE SPRAY PUMP 1P-2114 TRIP OR MOTOR OVERLOAD AN1C03A(e)

Setup ACTIVE ACTIVE CORE SPRAY PUMP A - FAILURE TO AUTO-INITIATE CSO5A Setup ACTIVE ACTIVE CORE SPRAY PUMP TRIP-CORE SPRAY PUMP A TRIP CSOlA Setup Final Value lnitialValue Ramp Delay ET Malfunction Title Malf. No.

Time PageT of32 Filename: 3_esg TR-AA-230-1003-F06 Revision 0

SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 NEXTETA" ENERGYø2 tugt REMOTES CLOSE OPEN 1

RCIC DELUGE MAN ISOLATION VALVE V-33-84 FPOS Setup MAN MAN 1

TURBINE BUILDING EXHAUST FAN 1V-EF-214 - HS-5945 HVO9 Setup Final Value lnitial Value Ramp Delay ET Remote Title Remote No.

Time OVERRIDES:

ON OFF 26 PCIS-LBIRWCU PCIS GROUP 5 B LOGIC ISOLATION SIGNAL RWCU DO-MS-212 Setup ON OFF 26 PCIS-LAIRWCU PCIS GROUP 5 A LOGIC ISOLATION SIGNAL RWCU DO-MS-192 Setup 8

As-ls 02:00 20 FI-4408 STEAM FLOW A - FI-4408 AO-FW-o15 Setup AUTO AUTO HS-2401 OUTBD STM LINE ISOL. VLV Dt-RC-008 START START HS-6517 TURB BLD SPLY FAN 1V-SF-228 Dt-HV-034 START START HS-6516 TURB BLD SPLY FAN 1V-SF-224 Dt-HV-033 Setup AB AB HS-5948 TB EXH FAN LEAD SEL (A&B-FAN,B&C-FAN,C&A-FAN)

Dt-HV-007 Setup AUTO AUTO HS-5928 TURB BLDG ROOF EXH FANS 1V-REF-20127 Dt-HV-006 Setup OFF OFF HS-2103(3) PUMP 1P-2114 (AMBER)

DO-CS-005 Setup OFF OFF HS-2103(4) PUMP 1P-2114 (RED)

DO-CS-006 Setup OFF OFF HS-2103(2) PUMP 1P-2114 (GREEN)

DO-CS-004 Setup OFF OFF HS-2103(1) PUMP 1P-2114 (WHlrE)

DO-CS-003 Setup STOP STOP HS-2103 PUMP 1P-2114 Dt-cs-008 Setup 0

0 E21R700A CORE SPRAY PUMP 1P-2114 (0-150 AMPS)

AO-CS-002 Setup Final Value lnitial Value Ramp Delay ET Override Title Override No Time Setup Setup Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page 8 of 32

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

=Yr6 SCHEDULE FILES:

RE.4448A MAIN STEAM LINE A Modify malfunction rm02re4448a to 55 in 300 30 MO24OO THERMAL OVERLOAD BREAKER TRIP Delete malfunction RC1 0A 22 Setup RE-9179 TURBINE FRONT STANDARD lnsert malfunction rmO1re9179 to 57.00000 in 600 after 180 28 RE-9160 TURBINE LUBE OIL AREA lnsert malfunction rmO1re9160 to 61.00000 in 600 after 180 28 Setup RE-9159 REACTOR FEED PUMP AREA lnsert malfunction rmO1re9159 to 59.00000 in 600 after 180 28 Setup RE-9158 CONDENSATE PUMP AREA lnsert malfunction rmO1re9158 to 55.00000 in 00 after 180 28 Setup RE-4448D MAIN STEAM LINE D lnsert malfunction rm02re4448d to 45.00000 in 120 after 180 28 Setup RE-44488 MAIN STEAM LINE B lnsert malfunction rm02re444ib to 44.00000 in 120 after 180 28 Setup RE-4448C MAIN STEAM LINE C I nsert malfunction rm02re4448c to 45.00000 in 120 after 180 28 Setup RE-44484 MAIN STEAM LINE A I nsert malfu nction rm02 re4448a to 49.00000 in 120 after 180 28 Setup CONTROL ROD SCRAMS-ROD 18-07 lnsert malfunction rd081807 after 40 1

Setup RPV PRESS SWITCH PS4549 FAILURE lnsert malfunction RR38A after 40 1

Setup Operating Basis Earthquake Event lnsert malfunction zz02 delete in 50 after 30 1

Setup 0.01 G Recorders Operating lnsert malfunction zz01 delete in 30 after 30 1

Setup 0.01 G Recorders Operating lnsert malfunction zz01 delete in 20 1

Setup Description Action Event

@ Time lLT3Actions.sch Setup 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

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

=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 Comments, problems, operator workarounds, etc.

o One extra NSPEO available in Work Control o Radwaste Operator is NSPEO qualified a

Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page 10 of 32

NEXTETA'

=Yry NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG lPot 3 Switch running RBCCW pumps When contacted as any dept. in organization:

TIME/NOTES Booth Gommunicator:

Acknowledge the request.

INSTRUCTOR ACTIVITY 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 CREW

. Switch running RBCCW pumps IAW Ol 414 section 7.1 RO

. Place the Standby RBCCW pump handswitch on 1C06 in the START position

. 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 EXPECTED STUDENT RESPONSÉ Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page11ot32

NEXIera"

=Yry NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG Earthquake After the crew reduces power by -5o/o and at the direction of the floor instructor:

The following scripts are on the following pages:

When contacted as any dept. in organization:

TIME/NOTES Simulator Operator AGTIVATE ET 1 This will cause the 0.01G recorder alarm to run; and then, 30 seconds later, an OBE with additional malfunctions.

Booth Gommunicator:

HPCI Suction Swap/Torus LevelAlarms -

Pg. 15 PS-4549/Half Scram Pg. 16 HCU 18 Pg. 17118 Booth Communicator:

Acknowledge the request.

INSTRUCTOR ACTIVITY CREW

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

CRS o Direct Crew Response to an Earthquake Condition.

. lF the amber DESIGN BASIS EARTHQUAKE, or amber OPERATING BASIS EARTHQUAKE lights are ON, and not a malfunction, THEN 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 .

o Enter EOP 2 T/L on High/Low Torus Water Level (may be administratively exited).

o Direct Health Physics to perform radiation surveys of the normally accessible areas inside DAEC Buildings, and the site grounds including 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 EXPECTED STUDENT RESPONSE Filename:3_esg TR-AA-230-1 003-F06 Revision 0 Page 12 o1 32

NEXTETA' F:NEFGY ¿Z n

-m NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 lf contacted as Duty Station Manager:

lf contacted as HP or Chemistry:

lf contacted as an in-plant operator:

TIME/NOTES Booth Communicator:

Acknowledge the request.

Booth Gommunicator:

Acknowledge the request to perfrom inside and outside plant walkdowns.

Keep track of which operator has been sent to what location in the plant.

Booth Gommunicator:

Acknowledge the request.

INSTRUCTOR ACTVITY CREW Enter and carry out the actions of AOP 901, Earthquake RO o Respond to an Earthquake Condition.

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

o Monitor for any Control Rod out of position.

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

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

Using HS 4918, RIVER WATER SUPPLY LOOP SELECT switch, select A CV4915 and B CV4914, one at a time, to verify RWS makeup flow can be established with each loop ensuring RWS piping is intact.

o Monitor Process and Area Radiation Monitoring System channels on 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.

EXPECTED STUDENT RESPONSE Page 13 of 32

NCtera"

,Yra,¿k NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG Earthquake Torus Level Alarms Earthquake HPCI Suction Swap TIME/NOTES INSTRUCTOR ACTIVITY CREW a

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

RO a

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

Verify the AUTOMATIC ACTIONS have occurred.

a CRS a

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

CREW a

Respond to the HPCI Suction Transfer annunciator 1C03C D-4 RO. 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)

EXPECTED STUDENT RESPONSE 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 Segment 1 Earthquake PS-4549 TME/NOTES Evaluator Note:

lF the crew checks the condition of C71A-K5A inform the operator that the relay fingers are toward the cover. (De-energized position, but do not directly say it is de-energized) All other relays are as seen.

Evaluator Note:

The crew will determine that PS4549 has failed. The crew will not be able to correct the cause of the half scram, or reset it.

INSTRUCTOR ACTVITY Respond to the REACTOR VESSEL HIGH PRESSURE TRIP annunciator 1C058 C-4 Respond to the "A' RPS AUTO SCRAM annunciator 1C054 A-2 At 1C05, confirm Reactor pressure high on PR-4563/4564, REACTOR PRESSU RE/REACTOR WATER LEVEL.

Verify Scram Group A12 3 4 indicating lights are off.

ldentify the cause of the A RPS Auto Scram.

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 .

CREW a

a RO a

o a

CRS a

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

NFXTETA-NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG Earthquake lf sent to investigate HCU 18-07 Two minutes after sent to investigate HCU 18-07:

lf sent to investigate fuses for Rod 18-07 wait one minute and report:

TIME/NOTES Booth Gommunicator:

Acknowledge Request Booth Gommunicator:

lnform the control room HCU l8-07 appears to be scrammed; both scram solenoid pilot valves are de-energized and are venting air.

Booth Communicator:

The fuses for Rod 18-07 appear to have blown.

INSTRUCTOR ACTIVTY CREW a

Respond to the ROD DRIFT annunciator 1C054 D-6 At 1C05, select affected Control Rod, monitor 4 rod display to determine if a control rod is drifting, and if so in what direction.

lf any control rod has scrammed, perform the following:

Run an OFFICIAL 3D CASE for abnormal reactor power/control rod distributions.

Notify the Reactor Engineer of the abnormal rod pattern.

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.

Enter the applicable Tech Specs:

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

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 .

RO a

a CRS a

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

NEXlera'

=Yjç,&

NRc lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG Earthquake AOP 255.2 Earthquake AOP 255.1 lf contacted as Reactor Engineer:

Two minutes after contacted as RE:

TIME/NOTES Booth Communicator:

Acknowledge Request Booth Gommunicator:

Report that there is no current issue with leaving 18-07 inserted.

INSTRUCTOR AGTIVITY CREW a

Perform actions of AOP 255.2 for the unplanned power change 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 CREW a

Perform actions of AOP 255.1 in the mispositioned control rod section RO

. Once power has stabilized, manually initiate an Official 3D Case

. Verify thermal limits on the official 3D Case.

CRS o Direct actions or AOP 255.1

. Contact RE and Ops Manager EXPECTED STUDENT RESPONSE 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 RCIC Leak When the TS Declaration is made and at the direction of the Floor lnstructor:

When ventilation is taken to a 3-2-3 lineup:

lF sent to the RCIC room:

Four minutes after sent to RCIC room:

After sent to reset the thermal overload for MO2400:

TME/NOTES Simulator Operator:

ACTIVATE ET 3 This starts the unisolable RCIC steam line leak.

Simulator Operator:

VERIFY ET 18 ACTIVATES This will increase the leak rate to ensure Max Safe will be reached.

Booth Gommunicator:

Acknowledge Request Booth Gommunicator:

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.

Booth Gommunicator:

Communications for this event are located on page 20.

NSTRUCTOR ACTIVITY CREW a

Respond to the Steam Leak detection alarm, 1C048 B-4 Determine that the RCIC room temperature is above Max Normal a

RO a

Send an Operator to 1C21to determine which area has the high temperature condition.

Verify the AUTOMATIC ACTIONS have occurred. lf the specified automatic response has failed to occur, manually initiate the appropriate actions.

a CRS a

Enter EOP 3 (Secondary Containment Control).

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

NEXTETA F]NF:PíGYØ

ffi E

NRC lNlTlAL LICENSE EXAM, SGENARIO #3 Rev. 0 SEG RCIC Leak lF sent to open breaker for MO-24Q1:

lf sent to close MO-2401 manually:

After sent to close MO-2401 and at the direction of the Floor lnstructor:

TIME/NOTES Simulator Operator:

Acknowledge the direction and brief, wait 2 minutes then AGTIVATE ET 14 THEN Booth Gommunicator Gontact the Gontrol Room and report the breaker for MO-2401 is open.

Booth Communicator Acknowledge Request Booth Gommunicator Report to the Gontrol Room that you cannot get MO-2401 to move.

INSTRUCTOR ACTIVITY Crew o lmplement the actions of EOP 3, Secondary Containment Control.

RO o Starts ESW for RCIC Room Coolers o Operates available main plant supply and exhaust fans.

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

. Fan Handswitch Panel Damper

. 1V-EF-1 HS-7613 1C23A. 1V-AD-16U

. 1V-EF-2 HS-7614 1C238 1V-AD-16V

. 1V-EF-3 HS-7615 1C23C 1V-AD-16W Start the Reactor Building Exhaust Fans by positioning the following handswitches to START:

. 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:

. 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 EXPECTED STUDENT RESPONSE Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page 19 of32

NEXTETA'

=Yry NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG EOP 1 When the MODE switch is placed in SHUTDOWN:

After the scram and when RC10A has been deleted:

EOP 3 cont.

TIME/NOTES Simulator Operator:

VERIFY ET 22 ACITVATES When the RO takes the Mode Switch out of RUN. This begins the RWGU leak (isolable) starts, and isolates the RCIC steam leak.

Booth Communicator Gontact the Control Room and report that the thermal overload for MO-2400 has reset.

NSTRUCTOR ACTIVITY CREW

. lmplements the actions of EOP 1, RPV Control.

RO o lnserts a manual reactor scram.

o Places the MODE switch in SHUTDOWN.

CRS

. Directs inserting a manual reactor scram.

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

o Directs a RPV pressure band of 800-1055 psig using turbine bypass valves.

o Directs commencing a cooldown to lessen the driving head on the leak in the RCIC Room.

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)

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

NEXTETA

=Y:ry NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG RWCU Leak When RWCU HX room temp is > 130F:

When MO-2700 or MO-2701 are closed:

lf sent to the RWCU HX room:

TIME/NOTES Simulator Operator:

VERIFY ET 26 ACTIVATES This will activate the Group 5 Annunciator -

1C058 (E-08)

Simulator Operator:

VERIFY ET 28 ACTIVATES This will start the 'A' steam line TB leak Pg. 2q and associated leak rad monitor indications on delays.

Evaluator Note:

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

Booth Gommunicator:

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.

INSTRUCTOR ACTIVITY CREW a

Respond to the Steam Leak detection alarm, 1C048 B-4 Determine that the RWCU room temperature is above Max Normal.

a RO a

Send an Operator to 1C21to determine which area has the high tem perature condition.

Verify the AUTOMATIC ACTIONS have occurred. lf the specified automatic response has failed to occur, manually initiate the appropriate actions. (CRITCAL) a CRS a

Enter EOP 3 (Secondary Containment Control).

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

NEXIefa"

=--%-

NRC lNlTlAL LICENSE EXAM, SGENARIO #3 Rev. 0 SEG Segment 3 RWCU Leak TME/NOTES INSTRUCTOR ACTVITY CREW

. 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.

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

NEXTETA" ENERGYøZ

-/-

rÃ'er m

NRG lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG Fuel Failure /

Release 4 minutes after the reactor is scrammed:

TIME/NOTES Simulator Operator:

VERIFY the following:

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.

INSTRUCTOR ACTIVITY CREW

. Determine that a steam leak exists in the Turbine Building and attempt to close the MSlVs.

. lf delay closing the MSlVs, a Group 1 lsolation will occur.

Recognize both "4" MSIVs failto close.

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

NEXIera' ENERGYøZ

-/-

unrln ffi NRC NlTlAL LICENSE EXAM, SCENARIO #3 Rev.0 SEG Fuel Failure /

Release Reactor Building ARM alarm TIME/NOTES INSTRUCTOR ACTIVITY CREW

. 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 radiation rise in the Reactor Building rooms is potentially due to a fuel failure and enter AOP 672.2 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 EXPECTED STUDENT RESPONSE Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page24 of 32

NEXTETA" NRC lNlTlAL LICENSE EXAM, SGENARIO #3 Rev. 0 SEG Fuel Failure /

Release EOP 3 When rm92re4448ais at 49.0000:

TIME/NOTES Evaluator Note:

EOP 3 and AOP 672.2 (below) should be performed concurrently.

Simulator Operator:

Verify ET 30 ACTIVATES This will cause rm02re4448a to ramp to 55; this will cause a MSL Hi-Hi Rad annunciator. Also, this will insert x01 on a delay.

INSTRUCTOR ACTIVITY Crew

. lmplements the mitigation strategies of EOP 3, Secondary Gontainment Control RO

. Informs the CRS of Reactor Building ARM readings.

. Announces evacuation of the Reactor Building CRS

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

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

NCtera"

=Yry NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG lf contacted as HP:

TME/NOTES Booth Gommunicator:

Acknowledge the i nformation.

INSTRUCTOR ACTIVTY 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 the suppression pool as a heat sink as follows:

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.

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

NEXIera'

=Yr*&

NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG After the TB KAMAN exceeds the ALERT EAL level:

lflwhen directed to stop fans:

lF the crew lowers RPV pressure prior to ED:

TIME/NOTES Booth Gommunicator:

Wait 3 minutes and report that the 1V-EF-21"A" and "8" Fans were running and that you secured the"B" Fan. The "A" Fan's hand-switch, HS-5945, broke off.

Simulator Operator:

VERIFY ET 24 ACTIVATES This will close the bypass valves.

INSTRUCTOR AGTIVITY Crew

. lmplements the mitigation strategies of EOP 4, Radioactivity Release Control RO

. Perform actions of EOP 4 o lF Group 3 isolation exists AND Reactor Building Kaman Monitors have a Hl-HlAlarm THEN

. Stop main plant exhaust fans.

. Stop turbine building supply fans.

. 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 Discharging Outside of Containment o Attempts to isolate all primary systems discharging radioactivity outside the primary and secondary containments except for those systems 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.

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

NEXTCTA' ENE@

ffi NRC lNlTAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG After the TB KAMAN exceeds the ALERT EAL level:

TIME/NOTES INSTRUCTOR ACTIVITY CRS Direct crew response for Performance of EOP 4 Directs isolating all primary systems discharging radioactivity outside the primary and secondary containments except for those systems required to 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 EXPECTED STUDENT RESPONSE 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 When the TB KAMAN exceeds the SITE EMERGENCY EAL level and is approaching the GENERAL EMERGENCY level, the crew Emergency Depressurizes As RPV pressure is lowered past 880#:

TIME/NOTES Simulator Operator:

VERIFY ET 24 ACTIVATES This will close the bypass valves INSTRUCTOR ACTIVITY Crew

. lmplements the mitigation strategies of Emergency Depressurization.

RO

. lnstall Defeat 11 (if not done previously).

. Maintains RPV level170-211" using directed control system.

. Reports torus water level.

o Opens 4 ADS SRVs.

. Commences to initiate actions to place shutdown cooling in service.

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

o Directs RPV level be maintained 17Q-211" using directed controlsystem

. Verifies torus level greater than 4.5'.

. Directs opening 4 ADS SRVs.

. 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" EXPECTED STUDENT RESPONSE Filename: 3_esg TR-AA-230-1 003-F06 Revision 0 Page29 of32

When RPV pressure is lowering to establish depressurized conditions, RPV water level is being controlled, and at the direction of the floor instructor:

TIME/NOTES Simulator Operator Place the simulator in FREEZE.

Floor lnstructor Perform a crew update and announce to the crew the simulator is in freeze and the scenario is complete.

INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE NEXTETA

EYJ6, NRC lNlTlAL LICENSE EXAM, SCENARIO #3 Rev. 0 SEG

- - END OF SCENARIO **

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

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

=Ysr6 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

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

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

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.

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.

UNSAT SAT Task Statement Flename:3_esg TR-AA-230-1 003-F06 Revision 0

SEG SIMULATOR EXERCISE GUIDE NEXTETA-EW-F.tt 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

SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O NEXIETA E\\src-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:

Enrolled in Licensed Operator Continuing Training, License Operator lnitial Training, Senior Reactor Operator-Certification Training Training Resources:

References:

Protected Gontent:,

Operating Experience:

Risk Significant Operator Actions:

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 None 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 Evaluation Method: Dynamic Scenario graded in accordance with NUREG 1021 guidance None Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page2 of 23

SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O NEXTETA" EYW ruf Direct Crew Response for performance of the PC/P leg of EOP 2 6.64 Direct Crew Response for performance of the DWT leg of EOP 2 6.63 Direct Crew Response to perform /P to control RPV pressure during an ATWS 6.57 Direct Crew Response to perform /Q to reduce power/scram the reactor durinq ATWS 6.56 Direct Crew Response to Perform lnitialATWS Actions (/)

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

95.56 Perform initialATWS actions (/)

95.55 Control RPV lniections prior to, during, and subsequent to ED during ATWS.

95.52 Perform /L to Control RPV Level during an ATWS 95.50 Perform actions of RC/P of EOP 1 95.46 Perform initial EOP 1 actions (RC) 95.45 Perform actions of RC/L of EOP 1 95.44 Perform Defeat 15 95.25 Perform EOP Defeat 11 95.21 Respond to Emergency Situations 95.00 Respond to Loss of Reactor Recirculation Pump(s) 94.58 Respond to Primary Containment Control Abnormal Situation 94.53 Respond to Loss of Feedwater Heating Condition 94.1 9 Respond to Power/Reactivity Abnormal Change Condition 94.03 Perform the lmmediate Operator Responses to a Reactor Scram 93.22 lnsert Control Rods using Single Notch 72.02 Alternate CRD Pumps 10.03 Respond to Annunciators 1.04 Reactor Operator Task Title Task #

TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE Filename: ESG alt TR AA-230-1003-F06 Revision 0 Page 3 of 23

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

=Yøarg See Cover N/A lnitial development for 2017 NRC LOlT Examination lnitial development for 2017 NRC LOIT Examination Rev.0 See Cover DATE REVIEWER AR/TWR#

REASON FOR CHANGE DESCRIPTION OF CHANGE DATE PREPARER 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.

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 4 of 23

SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O NEXI ETA ENENGYø2 FLEgT OVERVIEW / SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE The scenario may be terminated after all rods are in and RPV level is being restored 7

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.

6 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.

5 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).

4 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.

3 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.

2 The crew will swap running EHC pumps IAW Ol 693.2 Section 6.2 1

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.

Description Event #

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 5 of 23

4.

5.

SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O NEXTETA-EYtsrc-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 11 OR 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.

Have a second instructor verify that the auto triggers are setup as indicated below and evaluate to "FALSE" Verify Malfunctions Verify Remotes (Note that environmental remotes will already be timing)

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

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

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 Provide appropriate sh ift turnover documentation.

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

RUN Schedule File.ESG alt.sch" and LEAVE lT RUNNING.

Filename: ESG alt 6.

7.

8.

9.

10 11 12 TR-AA-230-1003-F06 Revision 0 Page 6 of 23

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

,Ynar6 EVENT TRIGGER DEFINITIONS

'B' Recirc Pump speed less than 75%

zaorrr6211b <= 0.75

'19 RPV water level less than or equal to 170" rrl <= 523 17 Deletes RD073819 ZDlRDHS18078(4)== 1 11 Manually Activated Manually Activated 1,3,5,7,9,13,15, 21,23 Trigger Word Description Trigger Losic Statement Trigger No.

MALFUNCTIONS:

UNLOCK UNLOCK

'B'RECIRC SCOOP TUBE LOCK UP (LOCK,UNLOCK) rr06 Setup ACTIVE INACTIVE 1

Spurious 20% Recirc Runback B Train r136b Setup 75 75 HYDRAULIC LOCK SCRAM DISCHARGE VOLUME IVARIABLE) rp05g Setup Active lnactive 17 SPURIOUS GROUP 7 ISOLATION ms32 100 0

5:00 3

RECIRC PUMP SHAFT SEIZURE-PMP B rr05b ON ON 1C038 (A-08)'B' RHR Pump 1P-2298 Trip Or Motor Overload AN1C03B(8)

Setup 1.5 0

15 min 13 RECIRC LOOP RUPT - DESIGN BASES LOCA AT 100o/o - LOOP B rr15b Setup Active lnactive 1 min 30 sec 5

Control Rod Accumulator Trouble - Rod 38-1 I RD073819 Setup Active lnactive 5

CRD Hvdraulic Pumo Trio - Pumo A RD11A Setup Active lnactive 1 min 10 sec 5

Control Rod Accumulator Trouble - Rod 34-35 RD073435 Setup Active lnactive 1 min 5

Control Rod Accumulator Trouble - Rod 06-1 5 RD070615 Setup ACTIVE INACTIVE 2:O0 3

RECIRC M-G DRIVE MOTOR BREAKER TRIP - M-G B RRO6B Setup Final Value lnitialValue Ramp Delav ET Malfunction Title Malf. No.

Time Setu OVERRIDES OFF ON 1:00 21 H5-2000(2) CONTATNMENT SPRAY MOV-2000 (RED)

DO-RH-133 OFF ON 1:00 21 HS-2000(1 ) CONTATNMENT SPRAY MOV-2OOO (GREEN)

DO-RH-132 Normal Normal HS-43218 GRP 7 CHAN B DW CLG AND FAN OVR Dt-PC-038 Setup off On HS-1915(1) RHR PUMP 1P-2298 LlTES -

(GREEN)

DO-RH-062 Setup off On HS-1915(4) RHR PUMP '.lP-2298 LIrES -

(AMBER)

DO-RH-065 Setup off On HS-1915(3) RHR PUMP 1P-2298 LTTES -

(RED)

DO-RH-064 Setup off On HS-1915(2) RHR PUMP 1P-2298 LliES -

(wHrTE)

DO-RH-063 Setup CLOSE AUTO HS-2OOO CONTAINMENT SPRAY MOV-2000 Dt-RH-076 Setup OFF OFF HS.19O3C CONT SPRAY VLV CTRL Dt-RH-014 Setup Final Value lnitial Value Ramp Delay ET Malfunction Title Malf. No.

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

SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O NEXTETA'

,YSxø fime REMOTES:

OPEN CLOSE 27 HS-2OOO CONTAINMENT SPRAY MOV-2000 Dt-RH-076 (NEW)

Setup FinalValue lnitialValue Ramp Delav ET Malfunction Title Malf. No.

TEST RUN 2:00 23 ATWS TEST SWlTCH (AKA DEFEAT 12)

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

HS-1863A rp02 Setup Open Norm MAN OPER OF 'B' RHR PUMP (1P2298 BREAKER)

RHlO Setup 100 50 l MIN 15 CRD PUMP 1P-2098 DISCHARGE VALVE V 10 ISOLATION RD04 (NEW)

Setup 50 100 l MIN 7

CRD PUMP 1P-2098 DISCHARGE VALVE V-17 -10 ISOLATION RDO4 Setup Final Value lnitialValue Ramo Delav ET Malfunction Title Malf. No.

Time SCHEDULE FILES:

'B'RECIRC SCOOPE TUBE LOCK uP (LOCK,UNLOCK)

Delete malfunction 1106 19 Setup CONTROL ROD ACCUMULATOR TROUBLE-ROD 38-19 Delete malfunction rd073819 after 5 11 Setup CRD PUMP 1P-2O98 DISCHARGE VALVE V-17 -10 ISOLATION Modify rd04 to 100 in 60 after 60 o

Description Action Event

@Time ESG_alt Setup 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

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

. 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 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 Evolutions in progress or planned for upcoming shift o Maintenance has requested swapping running EHC pumps to allow for checks on the running pump.

Comments, problems, operator workarounds, etc.

o One extra NSPEO available in Work Control o Radwaste Operator is NSPEO qualified o

a o

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 After the crew has taken the shift:

When contacted as organization personnel:

TME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTONS Booth Gommunicator Acknowledge Request INSTRUCTOR ACTIVITY Crew o Switch running EHC pumps RO

. At 1C07, start standby EHC pump 1P-978 by momentarily placing handswitch HS-36658 in the START position.

. 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 EXPECTED STUDENT RESPONSE Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 10 of23

rEly-a nnErn RF NEXTETA' NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG Recirc Runback After EHC pumps are swapped and at the direction of the floor instructor:

When contacted as organization personnel:

When contacted as plant personnelto investigate'B' Recirc Pump:

TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Simulator Operator lnsert ET 1 This will cause 'B' Recirc Pump 20%

runback and failure of 'B' Recirc Pump Scoop Tube lock until speed is lower than 75%.

Booth Gommunicator Acknowledge Request Booth Gommunicator Wait 2 minutes and inform Control Room that there is nothing abnormal about the 'B' Recirc Pump, but will continue to investigate.

INSTRUCTOR ACTIVITY Crew Respond to a'B' Recirc Pump 20% Runback a

RO CRS

. Attempt to lock'B' Recirc Pump Scoop Tube. (Will lock once pump 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 limits

. Comply with Tech Specs and Ol 264, Appendix 1 o Enter LCO 3.4.1 Condition C EXPECTED STUDENT RESPONSE Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Pagello'f23

NEXIera*

ryyLa_

NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O SEG ffi AOP 264 After power has been reduced below MELLLA and at the floor instructors direction:

When sent to either 1C149 or 1C1138:

Two minutes after sent to 1C1138:

Two minutes after sent to 1C149:

TIME/NOTES sIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Simulator Operator Insert ET 3 This will insert "B" Recirc Pump shaft seizure and, after a2.OO delay, trip the drive motor breaker for the 'B' Recirc pump.

Booth Gommunicator Acknowledge Request Booth Gommunicator lnform Control Room that the 'B' Recirc MG Drive Motor breaker is tripped with indication of a ground fault Relay 831-K3B active. No smoke, smell, or fire.

Booth Communicator Inform Control Room that 1V-SF-12 handswitch is in AUTO INSTRUCTOR ACTIVITY Crew Respond to 'B' Recirc Pump trip a

RO o Verify the AUTOMATIC ACTIONS have occurred:

o B RECIRC MG SET MOTOR BREAKER 1204 is OpEN.

o B GENERATOR FIELD BREAKER is OPEN.

. send an operator to lc1138 in the MG set Room to monitor relays.

o Momentarily place B RECIRC MG SET MOTOR BREAKER 1Fü:O4 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.

. Close B RECIRC PUMP DISCHARGE vatve MO-4628.

Re-perform appropriate steps in AOP 255.2 concurrenily.

. After 5 minutes, reopen B RECIRC PUMP DISCHARGE valve MO-4628.

o lnsert control rods per the control Rod withdrawal sequence sheets to maintain power less than or equalto (s) 60.0%.

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.

EXPECTED STUDENT RESPONSE Flename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 12 o 23

=Y"K NEXTETA' NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG AOP 264 Cont.:

When contacted as support personnel:

TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Booth Communicator Acknowledge Request INSTRUCTOR ACTIVITY CRS o Directs entering AOP 264 and reentering AOP 255.2.

. Directs and supervises reactivity manipulation to lower power below 60/o.

. Comply with the Technical Specification requirements for Recirculation Loops Operating (3.4.1 Condition C)

EXPECTED STUDENT RESPONSE Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 13 of23

NEXlera"

=yøø_

NRG lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG R.E CRD pump trip/accumulator TS After Load Line is below 1O0Vo, power has been reduced -5olo, the TS has been entered and at the direction of the floor instructor:

When contacted to investigate CRD pump and breaker:

Two minutes after request for CRD pump and breaker status:

When contacted to investigate the accumulators:

Two minutes after request for accumulator pressures:

TIME/NOTES SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Simulator Operator lnsert ET 5 This will cause the'A' CRD pump to trip and accumulator lights to illuminate after a time delay Booth Gommunicator Acknowledge Request Booth Gommunicator lnform Gontrol Room that GRD pump is warn to the touch/ GRD breaker has tripped on time delay overcurrent Booth Gommunicator Acknowledge Request Booth Gommunicator lnform the control room 06-15, 34-35, 38-l 9 accumulator pressures:

06 915 psig, 34 890 psig, 38 935 psig INSTRUCTOR ACTIVITY Crew Respond to'A' CRD pump trip and corresponding accumulator lights RO a

a Send operator to check 1P-2094 breaker and to the pump for fault indications.

Start CRD Pump 1P-2098 per Ol 255 or Ol 255 QRC1.

o Verify adequate oil level in CRD Pump 1P-2098 motor and speed changer.

o Close 1P-2098 Pump Discharge lsolation V-17-10 to approximately 112 turn open.

o Adjust CRD SYSTEM FLOW CONTROL FC-1814 to 0 gpm in MANUAL.

o Verify MO-1833, INLET TO CRD RETURN LINE, is fuily open.

o Start CRD PUMP 1P-2098 o Slowly open Discharge lsolation V-17-10 to pressurize downstream piping and to prevent CRD pump from tripping on low suction pressure.

o Vent both CRD Discharge Filters 1F-201{and B, using the following Vent Valves:

o 1F-201A

. V-17-15 CRD Pump Disch Filter 1F-2014 Vent

. V-17-17 1F-201A Combined VenV Drain Line lsolation a

EXPECTED STUDENT RESPONSE 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 trip/accumulator TS Cont.:

When contacted to close V-17-10 Trturn closed:

When contacted to open v-17-1Q.

When contacted to investigate the accumulators after CRD pump is started:

One minute after request for accumulator pressures:

lf contacted as RE to verify slow rods:

Booth Communicator Acknowledge Request Simulator Operator Wait I min and INSERT ET 7 This will insert RD04 to Tz openV-17-10 Booth Communicator Acknowledge Request Simulator Operator Wait I min and INSERT ET 9 This will delete RD04 to fully open V-17-10 Booth Gommunicator Acknowledge Request Booth Gommunicator lnform the control room 06-15, 34-35, 38-1 9 accumulator pressures:

06 925 psig, 34 900 psig, 38 1100 psig Booth Gommunicator lnform control room that there are currently no slow rods.

Respond to'A' CRD pump trip and corresponding accumulator lights Start CRD Pump 1P-2098 per Ol 255 or Ol 255 QRC1. (Cont.)

o 1F-2018

. Y-17-18 CRD Pump Disch Filter 1F-2018 Vent

. Y-17-201F-2018 Combined VenV Drain Line lsolation o Verify charging header pressurized > 1200 psig on pl-18164 CHARGING WATER PRESSURE.

o Slowly adjust CRD SYSTEM FLOW CONTROL FC-1814 to obtain approximately 40 gpm on Fl-1814 CRD SYSTEM FLOW.

o When FC-1814 is properly controlling flow, then shift to AUTO.

o Slowly adjust DRIVE WATER nP CONTROL MO-1830 to obtain approximately 260 psid on PDt-1B2SA DRTVE WATER

^P.

o Directs starting the'B' CRD Pump

. Comply with the Technical Specification requirements for Control Rod Scram Accumulators (3.1.5 Condition B)

Crew a

RO a

CRS 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 TS has been entered and at the direction of the floor instructor:

Simulator Operator NSERT ET 13 This inserts a leak from the 'B' Recirc Loop.

Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 16 of23

NEXTETA" E:NryY2<-

tfla NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.0 SEG ffi EOP 2 After Drywell Pressure exceeds 2 psig:

lf contacted as plant personnel to deenergize MO-2000:

One minute after ET 21 is activated:

lf contacted to open locally open MO-2000 Four minutes after contacted to locally open M0-2000:

Booth Communicator Acknowledge Request Simulator Operator ACTIVATE ET 21 This willturn off the lights on 1C03 for MO-2000 after a one minute delay.

Booth Gommunicator Contact the Control Room and inform them that the breaker for MO-2000 is open.

Booth Communicator Acknowledge Request Simulator Operator ACTIVATE ET 27 Booth Gommunicator Gontact the Gontrol Room and inform them that MO-2000 is open.

Crew

. lmplements the mitigation strategies of EOP 2, Primary Containment Control RO

. lnforms the CRS of containment parameters including parameter name, value and trend.

o lnstalls Defeat 4.

o Utilizes Ol 149 QRC to spray the torus using 'A'side Torus Sprays.

o Realizes that MO-2000 INBD DRYWELL SPRAY valve will not open and HS-1903C ENABLE CONTAINMENT SPRAY VALVES will not function.

o lnserts a manual reactor scram (CRITIGAL)

CRS o Enters into EOP 2 due to Drywell Pressure.

o 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 drywelltemperature reaches 280F.

o Directs inserting a manual reactor scram r Placekeeps in EOP 2 to the applicable WAIT UNTTL steps in the pC/p (PC/P-7) leg 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 Transition to ATWS Crew

. lmplements the mitigation strategies of EOP 1, RPV Control.

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.

When directed to install Defeat 12:

Simulator Operator AGTIVATE ET 23 This will place Remote Functions RP02 in TEST after a time delay; to install Defeat 12.

When RP02 is inserted, callthe control room and inform them that Defeat 12 is complete.

Crew

. lmplements the actions of ATWS.

RO

. Locks out ADS. (CRlTlcAL)

. Gompletes the ATWS QRC. Reports completion and includes SBLC availability, ARI success, reactor power and RPV level.

. lnstalls Defeat 11.

. lnjects SBLC. Reports completion and includes reactor power and RPV 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 ATWS Cont.

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)

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)

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 When RPV level is being restored, the crew is progressing to SDC, and at the direction of the Floor lnstructor:

ATWS Transition to EOP 1 After all rods have inserted.

Simulator Operator Place the simulator in FREEZE.

Floor lnstructor Announce the scenario is complete; please stand by your stations and do not discuss the scenario with your crew.

Floor lnstructor Monitor and ensure that crew monitors pressure during re-flood of the RPV.

Grew should limit injection to ensure cooldown limits are not violated.

Crew

. When all rods are in, transition from ATWS to EOP 1 RO

. Reports that all rods in after performing Scram-Reset-Scram

. Secures SBLC o Controls level 170"-211" using Condensate and Feedwater CRS

. Confers with the SM on the transition to ATWS.

. Directs securing SBLC injection o Directs RPV level 170"-211" using Condensate and Feedwater Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page21 of23

SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O NEXTETA" EYrc-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

SEG NRC lNlTlAL LICENSE EXAM, SCENARIO #ALT Rev.O NEXTETA-

,Yr6.

CREW GRADING ATTACHMENT ESG ALT Rev. 0 Date B.O.P 1C03 1C05 STA CRS OSM Evaluator Position Operator Name Management Representative/Lead Evaluator Crew Critical Tasks I

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.

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.

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

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

1. lF the reactor is operating at power and Drywell temperature is rising, THEN insert a manual scram before drywelltemperature reaches 280.F.

UNSAT SAT Task Statement Filename: ESG alt TR-AA-230-1 003-F06 Revision 0 Page 23 of 23

STP Page Rev.

3.4,2-01 1of22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILIW TEST DAEC DUANE ARNOLD ENERGY CENTER 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:

Date:

Print Signature Approved By I

Date Print Signature PROCEDURE APPROVAL I

Reviewed By:

I Date:

Print Signature Reviewed By:

I Date:

Print Signature cRoss-DrscrPLlNE REVIEW (AS REQUIRED)

STP Page Rev.

3.4.2-01 2of22 36 SURVEILLANCE TEST PROCEDURE TTTLE: DAILY JET PUMP OPERABILIW TEST DAEC DUANE ARNOLD ENERGY CENTER r.0 1.1 1.2 1.3 2.0 2.1 PURPOSE 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.

When this procedure is performed in its entirety it FULLY SATISFIES Recirculation Loop Operations Recirc Pump speed mismatch surveillance requirements.

When this procedure is performed in its entirety it FULLY SATISFIES Jet Pumps surveillance requirements.

BRIEFING INFORMATION PERFORMANCE I NFORMATION 2.1.1 This STP is organized as follows:

Jet Pump Trending Data 7.4 Jet Pumps 1-8 Operability Check 7.3 Jet Pumps 9-16 Operability Check 7.2 Recirc Pump Speed Mismatch Check 7.1 Evolution STP Sections 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 Special Test Equipment required:

None 2.1.3 2.1.4 lf Recirculation Pump speed is less than 60% of rated, an Engineering evaluation may be performed to determine Jet Pump OPERABILITY.

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.

2.1.5

STP Page Rev.

3.4.2-01 3of22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST DAE,C DUANE ARNOLD ENERGY CENTER 2.2 2.3 3.0 3.1 4.0 4.1 4.2 4.3 5.0 5.1 GENERAL CAUTIONS 2.2.1 None SPECIAL PRECAUTIONS 2.3.1 None REFERENCES None GENERAL INSTRUCTIONS 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.

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.

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

APPENDICES Appendix A - JETS Program lnstructions

Sheet 1 o'f 1 JETS PROGRAM INSTRUCTIONS Appendix A STP Page Rev.

3.4.2-01 4of22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST DAE,C DUANE ARNOLD ENERGY CENfER

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.

INITIALS Performance Date:

Prerequisites STP Page Rev.

3.4.2-01 5of22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILIW TEST DAEC DUANE ARNOLD ENERGY CENTER 6.0 6.1 PREREQUISITES The reactor is in two-loop operation. (lf the reactor is in single loop operation, perform STP 3.4,2-03 instead.)

For sectionsT.2 and 7.3, reactor power is greater than (>) 21'7%RTP (See Performance lnformation Step 2.1.1.)

(oPS) 6.2 (oPS)

INITIALS Performance Date:

STP Page Rev.

3.4.2-01 6of22 36 SURVEILLANCE TEST PROCEDURb TITLE: DAILY JET PUMP OPERABILITY TEST DAE,C DUANE ARNOLD ENERGY CENTER 7.0 7.1 PROCEDURE 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 record the value:

A MG SET PERCENT SPEED (SlC-92454'X)

-%o

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:

a. Use the "D" button to select "X" - PERCENT SPEED and record the value:

B MG SET PERCENT SPEED (SlC-92458.X)

-Yo

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 7.1'2'a.

7.1.4 Confirm that the point plotted on Figure 1 is within the appropriate limit for the current core power. lf the point is outside the limit, immediately notify the CRS, (PRTNT / SrGN)

Performed by:

Date:

Time:

lnit TS TS TS I

I I

Sheet 1 of 1 SPEED OF PUMP 4" vs. SPEED OF PUMP "B" Figure 1 STP Page Rev.

3.4.2-01 7of22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST DAE,C OUANE ARNOLD ENERGY CENTER OUTSIDE LIMIT CONDITIONS Y

\\

N N

K

)

S

//

x s v

CONDITIONS OUTSIDE LIMIT

\\y Y

Y

\\\\

\\

N

/N

\\\\

N LIMIT BELOW 69.4o/o POWER LIMIT ABOVE OR UAL TO 69.4o/o POWER s

o tJ IJJ lt,

=f f

110 100 90 80 70 60 50 40 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 "8" PUMP SPEED (%)

INITIALS Performance Date:

STP Page Rev.

3.4.2-01 8of22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILIW TEST DAEC DUANE ARNOLD ENERGY CENTER 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)

LOOP A FLOW (FR-4503, Ch 1)

KGPM Mlbm/hr 7.2.2 Using the data recorded in Step 7.2.1, plot "A" Recirc MG Set speed vs, "4" Recirc Pump discharge flow on Figure 2.

Using the data recorded in Step 7.2.1, plot "4" Recirc MG Set 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 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.

TS 7.2.3 TS TS

INITIALS Performance Date:

STP Page Rev.

3.4.2-01 9of22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST DAEC DUANE ARNOLD ENERGY CENTR 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

^P, and record the result in column "C" of Table A.

% Deviation = 100 x lnd, AP - Avg. lP Avg. lP TABLE A A

(^P)

B (lnd.AP - Avg.nP) c

(% Deviation)

JET PUMP JP-9 JP-I O JP-11 JP.12 JP-13 JP-14 JP.15 JP-16 (Sum of APs)

(Avs. aP)

Plot each individual Recirc Loop "4" Jet Pump % deviation value (from column "C" of Table A or JETS program calculation) on Figure 4.

I 7.2.7

INITIALS Performance Date:

STP Page Rev.

3.4.2-01 10 of 22 36 SURVEILLANCE TEST PROCEDURb TITLE: DAILY JET PUMP OPERABILITY TEST DAEC DUANE ARNOLD ENERGY CENTER 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 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.

TS

e. lf an Engineering evaluation was performed, are Jet Pumps 9-16 OPERABLE? ("N/A" if an Engineering evaluation Engineering is not required to be performed.)

(YES/NO)

(PRTNT / SlGN)

I TS I

I Performed by:

Date Time:

lnit.

Sheet 1 of 1

A MG SET SPEED vs. "4" RECIRC PUMP DISCHARGE FLOW Figure 2 STP Page Rev.

3.4.2-01 11 of 22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILIW TEST DAE,C DUANE ARNOLD ENERGY CENTER TWo Loop Operation

",4," Recirc Pump Flow Curve

\\O

\\O 1O 1O 1O

\\

\\O 1O

\\O O\\

O\\

c)ra)c)lr)C)\\notno It*tt*OOoOO\\O\\OO

MG Set Speed (%)

35.0 30.0 2s.0 20.0

.0

.0 5.0 0

v o

tJr c)b0 L(g o(^

n a.

E I

1 5

0 0

rO

\\O rO

\\O

\\O 1O 1O 6\\

o\\

O\\

Alr)Otr)Ot.)O c-l C.l cQ cf) t

.+

tr) lr) lr) o\\a\\o

\\

o\\\\o j

i i

(

i I

I I

l I't' I

I i

lI lI/

i

.1.

I x

1/

ir l

l I

i II I

f 4

I I

i I

I i

Last updated from data acquired on November 1-4,2016

Sheet 1 of 1

A MG SET SPEED vs. LOOP "4" JET PUMP FLOW Figure 3 STP Page Rev.

3.4.2-01 12 of 22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILIW TEST DAE,C DUANE ARNOLD ENERGY CENTER I

1 Ttvo Loop Operation Jet Pump Loop "4" Flow

\\o

.O rO rO

\\O

\\O rO

\\O o\\

o\\

6\\

o\\

6\\

\\

O\\

Olr)Olr)Otr)AO Nc.c.)cos+tr)t\\o MC Set Speed (%)

30.0 25.0 20.0 15.0 I

ti PTr I

¿ o

tr a

oJ 0.0 5.0 0.0

\\o o\\

(r)\\o 1O o\\

t-r

\\o

\\

lr) t--

\\O

\\O 1

1O 1O

\\O

\\O O\\

O\\

AtnO\\r)Olr)O oooo\\ooo Last updated from data acquired on November 1-4, 2016

Sheet 1 of 1 LOOP A JET PUMP % DEVIATION vS. JET PUMP NUMBER Figure 4 STP Page Rev.

3.4.2-01 13 o 22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILIW TEST DAEC DUANE ARNOLD ENERGY CENTER TWo Loop Operation Loop ttA" Jet Pump Dp o/o Deviation 30.0%

20.0%

10.0%

cd

()â a.â a.

(,)

0.0%

1 0.0o/o

-20.0%

-30.0%

9 10 ll t2 13 Jet Pump Number 14 15 16 a

\\

./

\\

\\ /

\\

,/

\\

,/

\\

./

\\

./

\\

./

\\

./

\\

Last updated from data acquired on November 1-4, 2016.

INITIALS Performance Date:

STP Page Rev.

3.4.2-01 14 of 22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABLIW TEST DAEC DUANE ARNOLD ENERGY CENTER 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 speed vs. "8" Recirc Pump discharge flow on Figure 5.

Using the data recorded in Step 7.3.1, plot "8" Recirc MG Set 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 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.

TS 7.3.3 TS TS

INITIALS Performance Date STP Page Rev.

3.4.2-01 15 of 22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST DAE,C DUANE ARNOLD ENERGY CENTER 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

^P and record the results in the appropriate spaces 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.

% Deviation = 100 x lnd. AP - Avg.

^P Avg. lP TABLE B B

(lnd.ÂP - Avg.AP)

A

(^P) c

(% Deviation)

JET PUMP JP-1 JP-2 JP-3 JP-4 JP-5 JP-6 JP-7 JP-8 (Sum of ÂPs)

(Avs. ÂP)

Plot each individual Recirc Loop "8" Jet Pump % deviation value (from column "C" of Table B or JETS program calculation) on Figure 7.

I 7.3.7

INITIALS Performance Date:

STP Page Rev.

3.4.2-01 16 of 22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST DAEC DUANE ARNOLO ENERGY CENTER 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 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 1-8 OPERABLE? ("N/4" if an Engineering evaluation is not required to be performed.)

(YES/NO)

(PRTNT / SrGN)

I Performed by:

Date:

Time lnit.

TS TS Engineering I

I

Sheet 1 of 1

B MG SET SPEED vs. "8" RECIRC PUMP DISCHARGE FLOW Figure 5 STP Page Rev.

3.4.2-01 17 of 22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST DAEC DUANE ARNOLO ENERGY CENTER Tivo Loop Operation "8" Recirc Pump Flow Curve 1O

\\O 1O 1O

\\o

\\O

\\O o\\

o\\

e\\

o\\

O(Otr)O(.)O c.tc catsl.)

35.0 30.0 25.0

Yzo llr obo L

c ts ls t-l 9.

E

10.0 5.0 0

.0 o\\lr) lr) 1O 1O 1O 1O 1O 1O 1O 1O

\\O

\\O 1O Otr)OIr)Otr)Olr)OInO

\\O\\OFtr-oOoOO\\O\\OO MG Set Speed (%)

4 T

i L

I 4

l I

i i

-i i

)/

I I

I.

i 0.0 Last updated from data acquired on November 1-4, 2016

Sheet 1 of 1

B MG SET SPEED vs. LOOP "8" JET PUMP FLOW Figure 6 STP Page Rev.

3.4.2-01 18 of 22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILIry TEST DAEC DUANE ARNOLD ENERGY CENTER I

I I

I tl t1 t1 I

I l

l I

I I

illl Vtv i

t I

I l

L i

i l

'f

..i.

l i

I I-I i

/

I L

I I

I

)t i

A il I.

-t lili

iili/

Y)

I I

I l

l i

i I

l I

I I

rliii I

i I

l l

br I

l lI l

l L

L li' i

I I

i l

I tliltlitil I

l il l

i I

it y,

L

i ii-ii

I I

I i

l TWo Loop Operation Jet Pump Loop "8" Flow 1O

\\O

\\O 1O

\\O 1O 1O

\\O O\\

O\\

\\

O\\

\\

OTOlr)Olr)O'.r) c.c.lc

+$(r)tr)

MG Set Speed (%)

30.0 2s.0 20.0 15.0 10.0 5.0 r+I

I fJr maoo

\\o 1O^\\

(r)

\\o 6\\

t-*

1O o\\lr) t*r o\\

o\\

olr)olr)o\\n<>

ooooO.O'OO 0.0 Last updated from data acquired on November 1-4, 2016

Sheet 1 of 1 LOOP 8" JET PUMP % DEVIATION vs. JET PUMP NUMBER Figure 7 STP Page Rev.

3.4.2-01 19 of 22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILIW TEST DAE,C DUANE ARNOLD ENERGY CENTER T\\vo Loop Operation Loop t'8" Jet Pump Dp o/o Deviation 30.0%

20.0%

10.0%

(B c) a t-la

(.)

0.0%

I 0 0%

-20.0%

-30.0%

1 2

J 45 Jet Pump Number 6

7 8

./

\\

.a

\\

./

\\\\

7

/

\\

/

./

\\

/

./

\\

/

\\

./

\\

/

\\

/

\\

Last updated from data acquired on November 1-4, 2016.

INITIALS Performance Date STP Page Rev.

3.4.2-01 20 of 22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST DAEC DUANE ARNOLD ENERGY CENTER 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 (PRTNT / SlGN) psid I

I Performed by:

Date Time:

lnit.

INITIALS Performance Date STP Page Rev.

3.4.2-01 21 of 22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABIUry TEST DAE,C DUANE ARNOLD ENERGY CENTER 8.0 8.1 8.2 8.3 ACCEPTANCE CRITERIA 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 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 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

INITIALS Performance Date:

STP Page Rev.

3.4.2-01 22 of 22 36 SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILIW TEST DAEC DUANE ARNOLD ENERCY CENTER f--\\'

8.4 lndicate any relevant test comments below, otherwise mark this step "N/4":

/ srGN)

I Operations ATTACHMENTS None Date 9,0 9.1

ML17214A036

Contents

Text

3.2 REFERENCES

References:

4.3 REFERENCES

References:

References:

Navigation menu

ML17214A036

Text

3.2 REFERENCES

References:

4.3 REFERENCES

References:

References:

Navigation menu

Search