ML14163A388

Provides peer check for con trol rod movements

Verifies the following during switch movement 0 Amber OVERRIDE light is illuminated 0 Green INSERT light is ill uminated following switch movement and remains 1:m for approximately 1 second 0 Rod position readout mo mentarily displays the next lower odd-numbered digit as tt1e drive unlatches Terminus: Control rods are withdrawn to the discretion of the Lead Evaluator.

Notes/Comments ILT13-1 NRCScenario1 Page 5 of 27

ILT 13-1 NRC Scenario 1 (New)

Op-Test No.: 13-1 NRC Scenario No.: _NRC Sim 1 Event No.: 2 Event

Description:

A control rod will be stuck at (20sition 12 (26-23}

Initiation: When the ATC attempts to withdraw Control Rod 26-23.

Cues: Control Rod 26-23 will not move when withdrawal signal is applied.

Time Position Applicant's Actions or Behavior ATC

Recognizes/reports a stuck control rod 26-23

Enters and executes ABN-6 OR 302.2 P&L 6.2. 7 0 Verifies that no Control Rod Blocks are in effect.

0 If CRD DR WTR PRESS indicates< 250 psid, adjusts to 250 psid.

0 If using ABN-6 and the US requests, consult with the System Manager and Reactor Engineering to determine if Procedure 235 should be performed concurrently with ABN-6. [ROLE PLAY 1]

ROLE PLAY 1: If requested, report as the System Manager and Reactor Engineering to complete actions of ABN-6, then perform actions of Procedure 235 if still necessary.

0 If the Control Rod will not move, apply RAISE drive water pressure to 300 psid and then attempt to withdraw the rod. [ROLE PLAY 2]

ROLE PLAY 2: When the ATC raises drive water pressure the first time, DELETE MAL-CRD007 2623.

May directs entry into ABN-Ei or use 302.2 P&L 6.2.7 to free stuck rod

May notify SMIWWM/Reactor Engineering BOP

May announce entry into ABN-6 (may be performed by ATC)

Terminus: Control rod 26-23 has been un-stuck and is withdrawn to position 48.

ILT 13-1 NRC Scenario 1 Page 6 of 27

ILT 13-1 NRC Scenario 1 (!New)

Notes/Comments ILT 13-1 NRC Scenario 1 Page 7 of 27

ILT 13-1 NRC Scenario 1 (New)

Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 1 Event No.: 3 Event

Description:

Leak in Isolation Condenser Shell Bl!rigger 1]

Initiation: Control rod 26-23 has been un-stuck and is withdrawn to position 48., or as directed by the Lead Examiner.

Cues: Annunciator C6b, SHELL B LVL HI/LO; ISOL CONDENSER B LEVEL indicates lower than normal Time Position Applicant's Actions or Behavior BOP

Responds to annunciator Cf3b, SHELL B LVL HI/LO .

0 Reports Isolation Condenser shell level and trend.

0 May restore shell water level lAW procedure 307, Isolation Condenser System, section 7.4.1, using Demineralized Water.

Records initial shell water level on Attachment 307-15

Opens V-11<34 on Panel 5F/6F .

Verifies annunciator K6d is received .

Commences filling isolation condenser until shell level indicates between 7.3 and 7.7 feet.

0 After shell level makeup has been initiated, reports Isolation Condenser Shell level is not rising.

0 May direct the EO to investigate Isolation Condenser B. [ROLE PLAY]

ROLE PLAY: When asked as the EO to investigate, report IC-B shell level is "CURRENT VALUE" ft. and lowering. There is water on the floor under the ICs. The water is contained, directed to the floor drain, and no equipment is affected. If asked to verify 1-7 sump is not overflowing, report it is not overflowing and is not isolated.

0 If directed to isolate Isolation Condenser B, places the following switchHs in CLOSE:

AC V-14-3:2 (steam)

DC V-14-33 (steam)

DC V-14-35 (condensate return)

AC V-14-37 (condensate return} --

Lead Evaluator: At the discretion of the Lead Evaluator, call the Control Room as the Shift Manager and direct the crew to Manually Isolate Isolation Condenser B.

Declares Isolation Condenser B inoperable and applies Tech Spec 3.8.B, C.

0 The shell side of each condenser shall contain a minimum water volume of 22,730 gallons. If the minimum volume cannot be maintained or if a source of makeup water is not available to the ILT 13-1 NRC Scenario 1 Page 8 of 27

ILT 13-1 NRC Scenario 1 (New) condenser, the condenser shall be considered inoperable.

0 If one isolation co ndenser becomes inoperable during the run mo de the reactor may remain in operation for a pe~ riod not to exceed 7 days provided the motor operated isolation and condensate makE.*up valves in the operable isolation condens er are verified daily to be operable.

May direct arming IC-B thermal overloads lAW 307 step 11.7.1

Notifies SMIWWM about Is olation Condenser B .

May direct the BOP to isolate Isolation Condenser B .

Terminus: Isolation Condenser B is declared inoperabll e and the SRO has applied Tech Specs.

Notes/Comments ILT 13-1 NRC Scenario 1 Page 9 of 27

ILT 13-1 NRC Scenario 1 (New)

Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 1 Event No.: 1 Event

Description:

Respond to trip of VMCC 1B2 rTriaaer 31 Initiation: Isolation Condenser B is declared inoperable and the SRO has applied Tech Specs.or as directed by the Lead Examiner Cues: Annunciators G3c, RPS MG SET 2 TRIP; G1c, SCRAM CONTACTOR OPEN; 9XF4a, PROT SYS PNL 2 PWR LOST; 9XF5c, CIP-3 INV AC INP LOST Time Position Applicant's Actions or Behavior

==-======================~!

Responds to annunciators

Recognizes and reports loss of VMCC 1B2

Performs ABN-51 o Confirms CIP-3 INV AC INP LOST (9XF-5-c) alarm received o Verifies the Trans Output green Off light is lit on Panel 7R o Restores power to PSP-2 by placing the Power Select switch in the TRANS position o Resets the following:

o Half Scram signal (4F) o Main Steam Isolation signal (4F) o APRM lights (5R) o APRM flow converters (3R, 5R) o Main Steam Line Rad Monitor drawers o Annunciators o NOTE: The following are simulated photographs. The candidate can simulate and assume indications are as expected.

Resets the INOP status LED on APRM FCTR cards

Verifies status LED on FCTR card is GREEN

Verifies Curve Select Display is "0" o Resets/verifies reset annunciator 9XF-4-a, PROT SYS PNL PWR LOST o Informs the US the following valves inoperable (1 F/2F) lAW Tech Spec 3.7 and 3.5.A.3 (only if 'B' Battery is unavailable- it will begin discharging but will be available for several hours)

V-14-31, DC Steam Inlet Valve to 'A' Condenser

V-14-34, DC Condensate Return Valve from 'A' Condenser

V-16-2, Inlet Isolation Valve to Cleanup Auxiliary Pump

V-16-14, Clean-Up Inlet Isolation Valve o Informs the US the B Battery is INOPERABLE as soon

"--------'----------L----a_s_it_b_e_,~Q'-in_s'---'-di-=-s-=-ch'---a'---r--'>L__:_gin___g_ _ _____

ILT 13-1 NRC Scenario 1 Page 10 of 27

ILT 13-1 NRC Scenario 1 (New) 0 Monitors 125 VDC 8 Bus Voltage 0 Reduces loads as directed by the US utilizing the 8 Battery Load List 0 Monitors 125 VDC A Bus Voltage 0 Verifies the following alarms are received:

0 MCC-1AB2 PWR XFER (9XF-2-c) 0 VACP-1 PWR XFER (9XF-3-c) 0 IP-4 PWR XFER (9XF-7-c) 0 Confirms one Fire Diesel Pump is operating in MANUAL mode and the other Fire Diesel Pump in AUTO mode 0 Directs the EO to investigate the loss of VMCC 182

[ROLE PLAY]

ROLE PLAY: As the EO sent to investigate the trip ofVMCC 182, report the feeder breaker to VMCC 1 82 tripped on overload 0 Informs US of Tech Specs section 3.7, Auxiliary Power 0 Notifies the Director of Operations and the WWM 0 Informs US to refer to EP-AA-1010 0 Reports ABN-51 is COQ:!f>lete SRO

Directs entry into ABN-51

Notifies SMIWWM about the loss of VMCC 182

Declares VMCC 1 82 inoperable

Declares B Battery inoperable as soon as it begins to discharge

Reviews/applies Tech Spec 3.7'.8 0 The reactor shall be PLACED IN the COLD SHUTDOWN CONDITION if the availability of power falls below that requin~d by Specification A above

Declares the following valves inoperable (1 F/2F) lAW Tech Spec 3.5.A.3 (only if 'B' BattHry is fully discharged) 0 V-14-31, DC Steam Inlet Valve to 'A' Condenser 0 V-14-34, DC Condensate Return Valve from 'A' Condenser 0 V-16-2, Inlet Isolation Valve to Cleanup Auxiliary Pump 0 V-16-14, Clean-Up Inlet Isolation Valve ATC

Makes plant announcement of ~~mtry into ABN-51

Reports % scram on RPS 2

Following restoration of RPS-2, resets the following:

0 Half Scram signal 0 Main Steam Isolation ~nal ILT 13-1 NRC Scenario 1 Page 11 of 27

ILT 13-1 NRC Scenario 1 (New)

Terminus: ABN-51 actions are complete and the SRO has reviewed/applied Tech Specs 3.7.8 and 3.5.A.3 Notes/Comments ILT 13-1 NRC Scenario 1 Page 12 of 27

ILT 13-1 NRC Scenario 1 (New)

Op-Test No.: 13-1 NRC Scenario No . : NRC Sim 1 Event No.: § I Event

Description:

The in-service RBCCW j;2Umj;2 tri12s I"Trigger 5]

Initiation: ABN-51 actions are complete and the SRO has reviewed/applied Tech Specs 3.7.B and 3.5.A.3, or as directed by the Lead Examiner Cues: Annunciators C3c, RBCCW PUMP 1-1 TRIP; Eld, E7f, F7b, CCW FLOW LO for all Recirculation Pumps; RBCCW PUMP 1-1 indicates tripped Time Position Applicant's Actions or Behavior BOP

Responds to annunciators C3c, RBCCW PUMP 1-1 TRIP; E7d, E7f, F7b, CCW FLOW ILO for all Recirculation Pumps

Checks RBCCW HX OUTLET PRESS and RBCCW PUMP 1-1 indications and recognizes RBCCW Pump 1-1 has tripped

Enters and performs immediate actions of ABN-19 .

Starts RBCCW Pump 1-2 by placing its control switch to START (must be started within 1 minute)

Reports RBCCW Pump 1-1 tripped and RBCCW Pump 1-2 was started and indications are normal

Directs EO to determine if RBCCW Pump 1-1 tripped on overload and to perform running checks on RBCCW Pump 1-2 [ROLE PLAY]

ROLE PLAY: When directed as the EO to check RBCCW Pump 1-1 for overload and to perform running checks on RBCCW Pump 1-2, report that RBCCW Pump 1-1 tripped on overload and report that running checks on RBCCW Pump 1-2 are SAT.

Directs entry into ABN-19

May enter Primary Containment Control EOP on high DW Temp (if required)

Notifies SMIWWM about the failed RBCCW Pump 1-1 ATC

Makes plant announcement about ABN-19 entry (may be performed by BOP)

Terminus: RBCCW Pump 1-2 has been manually started ILT 13-1 NRC Scenario 1 Page 13 of 27

ILT 13-1 NRC Scenario 1 (New)

Notes/Comments ILT 13-1 NRC Scenario 1 Page 14 of 27

ILT 13-1 NRC Scenario 1 (New)

Op-Test No.: 13-1 NRC Scenario No. : NRC Sim 1 Event No.: 6 Event

Description:

The standby (second} RBCCW PurQQ. trips resulting in a loss of all RBCCW flow [Trigger 7]

Initiation: RBCCW Pump 1-2 has been manually starte d, or as directed by the Lead Examiner Cues: Annunciators C4c, RBCCW PUMP 1-2 TRIP; E7' d, E7f, F7b, F7d, F7f, CCW FLOW LO for all Recirculation Pumps; Time Position Applicant's Act ions or Behavior SRO

Recognizes a loss of all RBC CW flow has occurred and enters ABN-19

Directs a manual scram lAW ABN-1

May direct tripping all Recirc ulation Pumps

Directs entry into RPV Control *- With A TWS 0 Directs ATC to perforrn SP-21 (Control rod insertions) 0 Directs ADS Bypasse1::i 0 Directs SP-16 (MSIV I_0-LO Bypass) 0 Directs RPV water lev el138" -175" lAW SP-19 (Feedwater)

When all control rods are ins erted, exits RPV Control- With A TWS EOP and enters RPV Control - No ATWS EOP ATC

Trips all operating Recirculati on Pumps lAW ABN-19

Manually scrams the reactor IA'WABN-1

Depresses both MANUALS CRAM pushbuttons

Places the REACTOR MOD E SELECTOR switch in SHUTDOWN

Reports eight control rods fai led to insert; power < 2%

Initiates ARI

Places ROPS in BYPASS

Places recirculation flow to rn inimum

Reports Immediate Failure to Scram Actions are Complete

Inserts SRMs

Inserts IRMs ILT 13-1 NRC Scenario 1 Page 15 of 27

ILT 13-1 NRC Scenario 1 (New)

Performs SP-21

Starts the standby CRD Pum p with its control switch to START

Resets the scram by pressin1g tlhe SCRAM SYSTEM RESET pushbutton, or directs the EC>to close the CRD Charging Header Isolation Valve V 52 [ROLE PLAY]

ROLE PLAY: To close the CRD Charging Header Isola tion Valve V-15-52, INSERT Trigger 9. Report when complete.

Places the REACTOR MODl::SELECTOR switch in REFUEL

Places the ROD WORTH Ml NIMIZER keylock in BYPASS

Places the CRD DRIVE WATER PRESSURE CONTROL NC18 switch to CLOSE

Places ROD POWER to ON

Selects a control rod by pres sing the associated pushbutton on the ROD DISPLAY MAT~ux CRITICAL TASK 1

Places the ROD CONTROL *switch to ROD IN

Reports successful in insertir1g control rods BOP/

Places ADS TIMER switche sin BYPASS when directed Crew

Performs SP-16 to bypass tl1e LO-LO MSIV isolation

Obtains 4 EOP plugs

In the EOP BYPASS PLUG:3 Panels in the rear of 6R & 7R:

Places plugs into BP1 & BP:2

Places the ISOL SIGNAL BYPASS V-6-395 switch to BYPASS

Notifies SRO

Performs SP-19 (Feedwater)

Controls RPV water level in the desired band using:

0 Feedwater Regulating Valves 0 Feedwater Regulating Valves Block valves 0 Feedwater Low Flow'Jalves 0 Heater Bank Outlet ls1:::>lation Valves 0 Feedwater & Conden,sate Pumps

When directed by the SRO, controls RPV water level as directed following entry into RPV Control - no A TWS

Reports entry into RPV Con trol - No A TWS on low RPV water level ILT 13-1 NRC Scenario 1 Page 16 of 27

ILT 13-1 NRC Scenario 1 (New)

When RPV level begins to rise following the scram, then performs the following:

Trips 2 Feed Pumps with their control switches

Places all MFRVs in MANUAL

Closes all MFRVs

Enters SP-2 (Cond/FW) when directed

Controls RPV water level usin!J the following as necessary:

Feedwater Regulating valves

Main Feed Regulating ValvH (IIIIFRV) Block valves

Feedwater Low Flow valves

Heater Bank Outlet Isolation valves

Feedwater and Condensate pumps

Maintains RPV pressure (approximately) 800 - 1000 psig using the Turbine Bypass Valves (may be performed by BOP)

If an RPV isolation occurred (due to reaching RPV Lo-Lo Level post scram), directs the Crew to maintain RPV pressure (approximately) 800- 1000 psig using the Isolation Condensers (SP-11) and/or EMRVs (SP-12) (may be performed by BOP)

Terminus: The reactor is scrammed, all Recirculation Pumps are tripped, and RPV water level and pressure are under control Notes/Comments

,--------------------------~~-----------~

ILT 13-1 NRC Scenario 1 Page 17 of 27

ILT 13-1 NRC Scenario 1 (New)

Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 1 Event No.: 7 Event

Description:

Large steam leak in the Drvwell [Trigger 11] with eight control rods failing to insert Initiation: The reactor is scrammed, all Recirculation Pumps are tripped, and RPV water level and pressure are under control, or as directed by the Lead Examiner Cues: Drywell pressure and temperature rising; Annunciators C3f, DW PRESS HI/LO; C1f, C2f, DW PRESS HI-HI Time Position

~~~~~~~~~9=~~~~~~~~~~=-

Applicant's Actions or Behavior J

Crew

Reports DW pressure rising

Responds to Annunciators C3f, DW PRESS HIILO; C1f, C2f, (BOP DW PRESS HI-HI

&

Reports EOP entry on high Drywell pressure and temperature ATC)

Performs SP-1 (Verifications)

Lines up Drywell Sprays IAV\1 SP-29 o Confirms all Recirculation Pumps are tripped o Trips all Drywell Recirculation Fans by placing their control switches to OFF

Initiates Drywell Sprays lAW SP-29 o For DW Spray System 1(2)

Places the SYSTEM MODE SELECT switch to the CRITICAL TASK 2 DW SPRAY positiion

Verifies TORUS CLG DISCHARGE valve closes

Verifies DW SPRAY DISCHARGE valve opens

Confirms the SYSTEM MODE SELECT switch is in the DW SPRAY position

Verifies TORUS CLG DISCHARGE valve is closed

Verifies DW SPRAY DISCHARGE valve is open

Starts and ESW PUMP by placing its control switch in START

Places and holds the SYSTEM 1(2) PUMPS START PERMISSIVE keylock to the pump to be started

Starts the CONTAINMENT SPRAY PUMP by placing its control switch to START

Maintains DW Pressure between 4-12 psig

~~~~~~~~~~~~----------------

ILT 13-1 NRC Scenario 1 Page 18 of 27

ILT 13-1 NRC Scenario 1 (New)

Maintains RPV water level in the desired band 138" - 175" lAW SP-2 (FW/Cond) and/or SP-3 (CRD)

Maintains RPV Pressure in t he band directed by the SRO SRO

May reduce the RPV pressu re band to approximately 500-700 psig due to the leak

If RPV pressure falls < 500 ~>Si!~. informs the crew the Yarways are no longer avail<:ible for RPV level indication

May secure Core Spray lAW SP-10

Directs entry into Primary C ontainment Control EOP and re-entry into RPV Control - no ,A.TWS (high OW Pressure)

Directs entry into ABN-36 wt1en the LOOP occurs

Before bulk Drywell tempera ture reaches 281°F:

0 Verifies Drywell tempera ture/pressure within the CSIL Curve 0 Verifies Torus water Ieve~I< 348" 0 Directs lineup of Drywell Sprays lAW SP-29

When it is determined Drywell temperature cannot be maintained below 281°F, directs initiation of Drywell Sprays CRITICAL TASK 2

()R

When Dryweii/Torus pressure reaches 12 psig, directs initiation of Drywell Sprays IAVV SP-29

May Anticipate ED (using Tu rbine Bypass Valves and/or Isolation Condensers)

FLOOR: Raise the steam leak at the Lead Examiners Discresion Terminus: Drywell Sprays have been initiated and Drywell pressure is lowering Notes/Comments ILT13-1 NRCScenario1 Page 19 of 27

ILT 13-1 NRC Scenario 1 (Ne1w)

Op-Test No.: 13-1 NRC Scenario No .: NRC Sim 1 Event No.: l! I Event

Description:

CRD Flow Control Valve fails closed ffiigger 13]

Initiation: When the SECOND Control Rod that faile d to manually insert post scram, or as directed by the Lead Examiner, insert Trigger 13 Cues: Annunciator H5c, CRD HIGH TEMP; DRIVE WA.TER FLOW, COOLING WATER FLOW, CLG WTR/REACTOR LlP, & DRIVE WTR/REA. CTOR LlP go downscale Time Position Applicant's Actions or Behavior I I I Crew

Responds to annunciator H 5c, CRD HIGH TEMP, and abnormal CRD indications.

Reports abnormal CRD indi cations .

Reports the CRD FCV (NC~WA) indicates closed .

May direct the EO to investi gate the failed CRD FCV [ROLE PLAY 1].

Enters ABN-6, Control Rod Malfunctions, section 13, Flow Control Valve NC-30A!B Fa ils Closed.

Places CRD FCV NC30B in service lAW procedure 302.1, section 6.3.3.

0 Places the CRD FLOW CONTROLLER in MAN.

0 Directs the EO to open t he standby FCV inlet/outlet valves

[ROLE PLAY 2].

0 Directs the EO to place the 4-Way Valve in position to supply both controllers [IROLE PLAY 3].

0 Places the CRD FLOW CONTROL VALVES switch to the B position.

0 Directs the EO to place the 4-Way Valve in position to supply the in-service cor1troller [ROLE PLAY 4].

0 Verifies normal CRD ind ications.

0 Places the CRD FLOW CONTROLLER in AUTO.

0 Directs the EO to close 1: he failed FCV inlet/outlet valves

[ROLE PLAY 5].

Reports the standby CRD F<~Vis in service and indications are normal.

May continue in EMG-SP21 and attempt to reset the scram and re-scram. This is unsuccessful.

May continue in EMG-SP21 and attempt to scram each rod by their individual scram test switches. This is a success path.

CRITICAL TASK 1

Manually drives all rods that failed to scram to less than ILT 13-1 NRC Scenario 1 Page 20 of 27

ILT 13-1 NRC Scenario 1 (New) position 04 Crew

Announces entry into ABN- 6, c.Jontrol Rod Malfunctions, due to CRD FCV NC30A failing 'clo sed.

May check CRD Temperatu res on Panel 8R and report there are several control rods with high temperatures.

Directs entry into ABN-6, Ccmt rol Rod Malfunctions, due to CRD FCV NC30A failing clo se d.

May directs swapping CRD FC Vs lAW procedure 302.1, section 6.3.3.

Notifies the SMMIWM abou tU1e failed CRD FCV.

CRITICAL TASK 1

Directs inserting all rods tha t fa iled to scram to less than position 04 ROLE 1. When/if asked as the EO to investigate t he in-service CRD FCV (NC30A),

PLAY report that it is closed, was leaking air badly. , and that you have isolated the air supply to the valve.

2. (Step 6.3.3.1.1.2.b) When/if asked as th eE:o to open the standby CRD FCV inlet/outlet valves, insert Trigger 15a nd report the valves OPEN (V-15-1 8' v-1 5-19).

3. (Step 6.3.3.1.1.3) When/if asked as the EO to place the 4-Way Valve in position to supply both controllers, state it is in the position to supply both controller (NO booth actions are require d).

4. (Step 6.3.3.1.1.5) When/if asked as the EO to place the 4-Way Valve in position to supply the in-service controlle rs tate it is in the position to supply NC30B (NO booth actions are rec~ui red).

5. (Step 6.3.3.1.1.8.a) When/if asked as th eE:o to close the failed FCV inlet/outlet valves, state the valves are cl OS ed insert Trigger 17 (closes V-15-16, V-15-17).

ROLE The ONLY success paths lAW SP-21 (Hy draulic A TWS) are to manually PLAY drive all rods in after the Crew swaps CRD Flow Control Valves or scram each rod with their individual scr*am test switches on Panel SR.

If the Crew requests an EO to Vent the CRI) ( )ver-Piston volume inform NOTE them V-15-24 and V-15-25 are mechanical! ys.*eized and cannot be operated.

Terminus: CRD FCV NC30B is in service and CRD pa1*am eters indicate normal and the Crew insert all control rods to less than posi tio n 04.

ILT 13-1 NRC Scenario 1 Page 21 of 27

ILT 13-1 NRC Scenario 1 (New)

Procedures Used Event Procedure 1

302.2

Control Rod pull sheets 2

ABN-6 3

RAP-6C8

307, section 7 and Attachment 307-15

TS 3.8 4

ABN-51

RAP-G3c

RAP-G3c

RAP-G1c

RAP-C9XF4a

RAP-9XF5c

TS 3.7 5

ABN-19

RAP-C3c 6

ABN-19

ABN-1

RPV Control-no A TWS

SP-1

SP-2

SP-3

SP-11

SP-12 7

RPV Control-no ATWS

Primary Containment Control ILT13-1 NRCScenario1 Page 22 of 27

ILT 13-1 NRC Scenario 1 (New)

SP-29

ABN-36 8

RAP-H5c

ABN-6

302.1 ILT 13-1 NRC Scenario 1 Page 23 of 27

ILT 13-1 NRC Scenario 1 (New)

Simulator Setup

1. Reset to IC-151. Password: 2014iltnrc

2. Verify B & C MFRVs are in MAN and closed

3. Have a copy of 302.2, 201, & 402.2 for the applicants

4. Place Air Compressor #3 in PTL and hang tag

5. Have a copy of Scenario 1 pull-sheets (SequencH Step Numbers 9-11 completed through step 10 and rod 34-15 of step 10) in yellow. Place in binder in simulator in front of Step 8 (or hand to students as part of their pre-scenario brief).

6. Verify the RWM is in BYPASS and tagged OOS

7. Verify Nls are on IRMs Event Trigger Malfunction 1 NA NA

-~------------1 2 Preset- MAL-CRD007-*26-23

This will stic: k Control Rod 26-23.

NOTE: DE LETE this malfunction when the Applicar1t raises CRD drive pressure th1~ 1st time to rod 26-23 lAW ABN-6. (See Booth actions for Event 2).

3 T1-

IMF-ANN-C -6B

ICH-ICSOO~~ A from 7.2' to 0' over a 3-minute ram1J This will cause IC B shell water level indication to lower to 0' over a 3-minute period. Note th at this malfunction set to lower to 0' will !Jive an indication on Panel 1F/2F of 0'.

4 T3- MAL-EDS004B

Loss ofVM cc 182 5 TS- MAL -RBCOO 1A ILT 13-1 NRC Scenario 1 Page 24 of 27

ILT 13-1 NRC Scenario 1 (New)

Trips RBCC W Pump 1-1 6 T7~ MAL-RBC001 B

Trips RBCC,W Pump 1-2 T9~ LOA-CRD024 t oO

This closes CRD Supply Water Valve to Charging \Arat13r Header valve V-15-52 7 Preset~ MAL-CRD022- ~223, 0231,2251,3051, 5031, 5023, 30 03,2203

This will res ult in eight control rods failing to sc1ram Preset~ hwx03i271 s.eq .1

This will act ivate Trigger 11 when the Mode Switc h is taken to SHUTDOWN SWI-CASO 11 t(:>OFF Preset~

This fails th e ARI Normal/Bypass switch in thE~ NORMAL position so the only succes s path to drive rods is swapping th e failed CRD flow control valve in Evemt #8 or opening individual scram test~;witches for the rods that failed to scrarn MAL-NSS017B to 10% over 20 minutes Conditional with a 2-minute time delay T11 ~

This will ca use a steam leak in the Drywell 8 T13 ~ MAL-CRD001 A to 0

This closes CRD FCV NC30A ILT 13-1 NRC Scenario 1 Page 25 of 27

ILT 13-1 NRC Scenario 1 (New)

T13--+ MAL-ANN-H-5C to ON on a 30 sec time delay LOA-CRD012 to *1 T15--+

LOA-CRD0111:o *1

This opens the alternate FCV NC30B inlet/outlet valves.

LOA-CRD009 to 0 T17--+

LOA-CRD01 0 to 0

This closes the failed FCV NC30A inlet/outlet valves ILT 13-1 NRC Scenario 1 Page 26 of 27

ILT 13-1 NRC Scenario 1 (New)

Shift Turnover Current plant conditions:

2% power with mode switch in STARTUP

Control rod withdrawal is in progress

Air Compressor #3 is tagged OOS

RWM is tagged OOS

lnerting the Primary Containment is on hold for a nitrogen delivery. The reactor Mode switch is in STARTUP.

Steam chest warming is in progress Shift Activities

Continue with rod withdrawal. Complete step 10 Group 3-1 starting at rod 34-39.

When rod pulls are complete wait for further direction from Reactor Engineering.

Timing of rod position 00-02 is not required and Continuous Rod Withdrawal is allowed per Reactor Engineering.

Procedure 201, Plant Startup is currently at Step 6.5"7 to withdraw control rods to achieve 1-2 Turbine Bypass valves open ILT 13-1 NRC Scenario 1 Page 27 of 27

ILT 13-1 NRC Scenario 2 (New)

Scenario Outline Facility: Oyster Creek Scenario No.:~ Op Test No.: 13-1 NRC Examiners: Operators:

Initial Conditions:

97% power

Main Generator voltage control is in Manual Turnover:

Place the AVR in automatic service lAW 336.1, section 8, starting at Step 8.2 Event No. Malf. No. Event Type* Event I I I I Description I

1 N/A N BOP Return the AVR to service lAW 336.1.

MAL-2 MSS005A c BOP Trip of Steam Pc:1cking Exhauster 1.

MAL-NIS020F I ATC APRM 6 fails upscale with a failure of Y2 scram on 3 RLY-RPS003B, TS SRO RPS 2.

0048 4

MAL- c BOP Trip of USS 1A3.

EDS003C TS SRO 5

ICH- c Turbine high vibration requiring a manual scram.

TSI15A, ATC TSI014A R MAL-CFW012B Feedwater line break with failure of Feedwater check SRV-6 CFW002B M Crew valves and loss of all Feedwater and Condensate SRV- Pumps.

CFW003B VLV-7 CSS004, 006, 011' c Crew Failure of Core Spray Isolation Valves to auto open.

012 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Transient, {TS) Tech Specs ILT 13-1 NRC Scenario 2 Page 1 of 25

ILT 13-1 NRC Scenario 2 (New)

Simulator Summary Event Event Summary 1 The BOP will return the AVR to automatic service lAW 336.1. The BOP will place the AVR MODE Switch to the AUTO position and confirm indications voltage regulation is in automatic. (BOP: Normal Evolution) 2 The BOP will respond to the failure of the in-service steam packing exhauster. The BOP will start the standby Exhauster and throttle open its discharge valve to maintain the correct vacuum. (BOP:

Component Malfunction) 3 APRM 6 will fail high with no expected % scram on RPS 2. The SRO will direct entry into ABN-39, RPS Failures. The ATC will insert a manual %scram on RPS 2. The SRO will apply Tech Spec 3.1.1.

(ATC: Instrument Malfunction; SRO: Tech Spec) 4 The BOP will respond to a loss of USS 11\3 and execute ABN-46, Loss of USS 1A3. The BOP will start Service Water Pump 1-2, restore power to ER-42, and confirm HP Screen Wash Pump 1-2 and LP Screen Wash Pump 1-4 are runnin~~- The SRO will review and apply Tech Spec 3.7. (BOP: Component Malfunction; SRO: Tech Specs) 5 The crew will respond to turbine VIBRATION HI annunciator and recognize rising bearing vibrations to the level that requires a power reduction and manual scram. The ATC will manually scram the reactor and BOP will confirm trip of the turbine. ABN-1, Reactor Scram, and ABN-10, Turbine Trip, procedures will be entered. The crew will be required to open the Main Condenser Vacuum Breaker to mitigate the turbine high vibration.(ATG: Component Malfunction; ATC: Reactivity Manipulation) 6 The crew will respond to a large Feedwater line break compounded with the failure of the Feedwater isolation check valves. The crew will enter the RPV Control- no ATWS EOP. During the event, all condensate and feedwater pumps will trip. The crew will Emergency Depressurize (ED) if RPV water level reaches 0" OR lower RPV pressure to allow low pressure systems to inject. (Crew: Major Evolution) (PRA)

ILT 13-1 NRC Scenario 2 Page 2 of 25

ILT 13-1 NRC Scenario 2 (New) 7 The crew will respond to the failure of the Core Spray Parallel Isolation valves to automatically open. The valves will open manually from their control switches on panel1 F/2F. (Crew: Component Malfunction After EOP) (PRA)

Critical The crew must manually scram the reactor on Turbine High Vibration.

Task 1 An automatic scram may not occur ancl turbine damage may result in entry into Emergency Action Levels for a loss of the primary decay heat removal mechanism.

Critical The SRO will direct Emergency Depressurization when RPV water Task 2 level reaches 0" TAF provided at least one injection source is lined up and running OR with low pressure injection systems running that have the capacity to restore and maintain RPV water level the SRO will direct lowering RPV pressure as necessary to allow low pressure systems to inject.

Critical The crew recognizes that the Core Spray Parallel Isolation Valves Task 3 failed to automatically open at- 300# reactor pressure and manually opens at least one valve in each Core Spray system to allow Core Spray to inject into the RPV to restore RPV water level above T AF.

ES-301-4 Target Quantitative Actual Event Attributes Attributes Number(s)

1. Total malfunctions (5-8) 6 2-7

2. Malfunctions after EOP entry (1-2) 1 7

3. Abnormal events (2-4) 3 3-5

4. Major transients (1-2) 1 6

5. EOPs entered/requiring substantive 2 6 actions (1-2)

6. EOP contingencies requiring substantive 1 6 actions (0-2)

7. Critical tasks (2-3) 3 5-7 ILT 13-1 NRC Scenario 2 Page 3 of 25

ILT 13-1 NRC Scenario 2 (New)

Op-Test No.: 13-1 NRC Scenario No.: NRCSi m 2 Event No.: 1 Event

Description:

Return the AVR to service lAW 3:~6.1.

Initiation: Following shift turnover Cues: As directed by the SRO following shift turnover Time Position Applicant's Actions or Be havior SRO

Directs the BOP to shift 1from manual to automatic voltage regulation lAW 336.1, section 8, startin gat Step 8.2 BOP

Shifts from manual to automatic voltag e regulation lAW 336.1, section 8, step 8.2.

0 Verifies the EX2100e TRANSFER VOLTMETER (8F/9F) is reading Zero (+/- 1°/c>)

0 Places the AVR MODE Switch (AV R\97CS Panel 8F/9F) to the AUTO position and allow swit ch to return to center.

(Panel 8F/9F) 0 Confirms the AUTO light illuminate d above AVR MODE Switch. (AVR\97CS Panel 8F/9F) 0 Confirms the PSS Status is Enable d locally at the HMI ROLE PLAY: As the EO at the HMI, report that the PSS is active (336.1 step 8.5) 0 Removes VOLTAGE CONTROL IN MANUAL operator aids installed per Section 7.0.

0 May verify Terminal Voltage or Exci tation are within the requirements of 336.1, section 5.0, on the PJM website.

[FLOOR ROLE PLAY]

FLOOR ROLE PLAY: If the applicant requests (or attempts to ver ify on the PJM website) that Terminal Voltage or MG Excitation (VARS) are within the limits of section 5.0, inform them that the requirements of section 5.0 are satisfacto ry.

0 May notify the Power team when in auto Terminus: The AVR is in automatic voltage control ILT 13-1 NRC Scenario 2 Page 4 of 25

ILT 13-1 NRC Scenario 2 (New)

Notes/Comments ILT 13-1 NRC Scenario 2 Page 5 of 25

ILT 13-1 NRC Scenario 2 (New)

Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 2 Event No.:~ I Event

Description:

Trir;2 of Steam Packing Exhauster 1 [Trigger 1]

Initiation: The AVR is in automatic voltage control, or as directed by the Lead Examiner Cues: Annunciator Q8c, EXHAUSTER TRIP Time Position Applicant's Actions or Behavior BOP

Responds to annunciator Q8c, EXHAUSTER TRIP 0 Reports Exhauster Bllower 1 has tripped 0 Verifies gland steam prBssure 0 Closes Exhauster Blower 1 Valve V-7-38 0 Starts Exhauster Blower 2 and verifies the red light on 0 Throttles open Exhauster Valve 2 V-7-39 0 Adjusts Exhauster Valve 2 V-7-39 to maintain GLAND STM HEADER VACUUM at 15- 17.5 inches of water 0 Reports Exhauster B!lower 2 is in service

Directs EO to investigate the trip of Exhauster Blower 1 [Role Play]

As the EO sent to investigate the trip of Exhauster Blower 1, report there are indications of an overload on the breaker.

ROLE PLAY

May send an EO to the Turbine Building operating floor to investigate; report as the EO you are on the TB operating floor.

May have RP check radiation levels on the Turbine Building operating floor; acknowledge the report.

Notifies SMNVWM for repair

May direct condenser vacuum as key parameter

May evacuate the TB operating floor Terminus: Exhauster Blower 2 has been started and proper gland steam header vacuum is established ILT 13-1 NRC Scenario 2 Page 6 of 25

ILT 13-1 NRC Scenario 2 (New)

Notes/Comments ILT 13-1 NRC Scenario 2 Page 7 of 25

ILT 13-1 NRC Scenario 2: (New)

Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 2 Event No.:~

Event

Description:

APRM 6 UQscale Failure with no RPS 2% Scram [Trigger 3]

Initiation: Exhauster Blower 2 has been started and proper gland steam header vacuum is established, or as directed by the Lead Examiner Cues: Annunciators G2f, APRM HIHIIINOP II; G3f, APRM HI; APRM 6 indicates 150 with the HI-HI and HI lights on Time Position Applicant's Actions or Behavior I

-~

Responds to annunciators G2f, APRM HIHI/INOP II and G3f, APRM HI 0 Reports APRM 6 indicates 150 and that an RPS 2 %

scram should have occurred 0 Checks the following:

0 recirculation flow 0 feedwater flow and temperature 0 reactor pressure 0 reactor water level

Performs ABN-39 0 Inserts a% scram on RPS 2 by pressing the MANUAL SCRAM RPS 2 push button 0 Refers SRO to Tech Spec 3.1

May Bypass APRM 6 lAW 403 if directed SRO

Directs entry into ABN-39, RPS Failures and directs the ATC to insert a %scram on R.PS 2 (may direct inserting a %scram prior to referencing ABN-39)

Reviews Tech Spec 3.1 and verifies RPS 2 and APRM 6 are in the tripped condition and meeting their design function

Notifies SMNVWM for the APRM and RPS failures

Notifies the Director of Ope~ rations I SM I RE

Determines no other action is currently required

May direct bypassing APRM 6 BOP

Makes plant page for entry into ABN-39, RPS Failures ILT 13-1 NRC Scenario 2 Page 8 of 25

ILT 13-1 NRC Scenario 2 (New)

May verify APRM 6 indic ation on Panel 5R Terminus: RPS 2 is tripped and the SRO has revie wed/applied the Tech Specs Notes/Comments ILT 13-1 NRC Scenario 2 Page 9 of 25

ILT 13-1 NRC Scenario 2 (New)

Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 2 Event No.: 4 Event

Description:

Loss of 480 VAG Bus USS 1A3 [Trigger 5].

Initiation: RPS 2 is tripped and the SRO has reviewed/applied the Tech Specs, or as directed by the Lead Examiner.

Cues: Annunciators S8f, FOR TO 460V 1A3 TRIP, and U5a, 1A3 MN BRKR TRIP Time Position Applicant's Actions or Behavior BOP Per RAPs S-8-f, FOR TO 460V 1A3 TRIP, and U-5-a, 1A3 MN BRKR TRIP (NOTE: Applicant may directly enter and execute ABN-46 instead of RAP).

Checks Breaker position and Bus amps

Has EO check at the local breaker cubicle for relay targets

Verifies trip of 4160V Breaker 1A3P

Refers to ABN-46

Checks Bus loads have shed

Determines cause of Breaker trip [BOOTH]

BOOTH: When requested to investigate cause of USS 1A3 trip, report that the 1A3P breaker tripped on overload Per ABN-46, LOSS OF USS 1A3:

IMMEDIATE OPERATOR ACTIONS

Starts 1-2 Service Water pump SUBSEQUENT OPERA TOR ACTIONS

Has an EO restore power to Panel ER-42 [BOOTH]

BOOTH: When requested, insert LOA-CWS0049 to B31 (Trigger 7) to restore power to B31. Report to Control Room when complete. (ABN-46 step 4.2.1)

ILT 13-1 NRC Scenario 2 Page 10 of 25

ILT 13-1 NRC Scenario 2 (New)

Has an EO confirm HP Screen Wash Pump 1-2 and LP Screen Wash Pump 1-4 are running [BOOTH]

BOOTH: NOTE: Screen Wash Control Panel and Low Pressure Screen Wash pumps are not modeled. When requested to confirm HP Screen Wash Pump 1-2 and LP Screen Wash Pump 1-4 are running, report they are both running. May request EO to check intake dp.

Monitors North intake DP, Circ Water pump amps and main condenser vacuum

Notifies Security of the loss of security lighting at the intake

Requests Work Week Manager to mobilize Electrical Maintenance for troubleshooting and repair ATC

May assist in communications associated with execution of RAPs and ABN-46 SRO

Directs entry into ABN-46, Loss of USS 1A3

Determines that USS 1A3 is inoperable per Tech Spec 3.7 and determines that the plant must be placed in the cold shutdown condition Terminus: ABN-46 has been performed and the SHO has addressed Tech Specs.

Notes/Comments ILT 13-1 NRC Scenario 2 Page 11 of 25

ILT 13-1 NRC Scenario 2 (New)

Op-Test No.: 13-1 NRC Scenario Nc).: NRC Sim 2 Event No.: .§.

Event

Description:

Turbine VIBRATION HI annunci'ato r reguiring a manual scram

[Trigger 9] (See Lead Evaluator Cue below}

Initiation: ABN-46 has been performed and the SRC) h as addressed Tech Specs., or as directed by the Lead Examiner Cues: Annunciator Q3b, VIBRATION HI; Turbine be ari ngs 6 and 7 vibrations rising Time Position Applicant's Ac~tions or Behavior BOP

Responds to annunciate rQ 3b, VIBRATION HI 0 Reports turbine beari ng vibration levels 0 Reports Bearing 6 at 10 mils and rising and bearing 7 at 10 mils and rising. Rep arts that the RAP requires a manual turbine trip at: ar1y level > 12 mils LEAD EVALUATOR: IF the simulator fails to provid1ei ndications of Turbine mils rising, THEN inform the crew that Bearing 6 & 7 are at 10 rnil sand steady. After the ATC lowers power, inform the crew that BearinQ 6 & 7 are 13 mils and risinQ.

Controls RPV water leve Ia s directed following the scram 0 Reports entry into R PV Control - No A TWS on low RPV water level 0 When RPV level begi ns to rise following the scram, then performs the followin!g:

0 Trips 2 Feed Pum ps with their control switches 0 Places all MFRVs in MANUAL 0 Closes all MFRVs 0 Directs the EO to clo se CRD Supply Water Valve to Charging Water He a der valve V-15-52 [ROLE PLAY]

ROLE PLAY: As the EO directed to close CRD Sup ply Water Valve to Charging Water Header valve V-15-52, insert Trigger 30. Report wh en complete.

0 Enters SP-2 (Cond/Fw) when directed 0 Controls RPV wat:er level using the following as necessary:

0 Feedwater Re gu lating valves 0 Main Feed Re gu lating Valve (MFRV) Block valves 0 Feedwater LmNF~low valves ILT 13-1 NRC Scenario 2 Page 12 of 25

ILT 13-1 NRC Scenario 2 (New) o Heater Bank Outlet Isolation valves o Feedwater and Condensate pumps

Performs SP-1 as directed

Makes plant announcement for reactor scram SRO

Directs the ATC to reduce reactor power with Recirc Flow

[Lead Evaluator I Booth - Raise turbine vibration lAW the NOTE on page 22]

CRITICAL TASK 1

Directs the ATC to manually scram the reactor lAW ABN-1

Directs entry into RPV Control - No A TWS o Directs the Crew to maintain RPV water level 138" - 160" using SP2 (Cond/FW) and/or SP3 (CRD) o Directs the Crew to maintain RPV pressure (approximately) 800 -- 1000 psig using the Isolation Condensers (SP-11) and/or EMRVs (SP-12) o May direct pressure control on TBV before Vacuum Breaker is opened lAW ABN-10 and if an RPV isolation has not occurred

Directs entry into ABN-1 0, Turbine Trip o Directs main condenser Vacuum Breaker, V--2-44 opened NOTE: When V-2-44 is opened, The Main Turbine vibration (high mils) malfunction will automatically be deleted (return to normal) AND Event #7 will initiate.

Directs SP-1 (Confirmation of Automatic Initiations and Isolations) 1f------t-----+-----------*-*-----------*-----

Reduces power with Rec:irc Flow prior to reaching 12 mils on bearing 6 or 7 [BOOTH]

CRITICAL TASK 1

Scrams the reactor lAW ABN-1 o Depresses both Manual Scram Pushbuttons o Places the Reactor IVIode Selector switch in SHUTDOWN o Verifies all control rods fully inserted o Reports immediate scram actions complete

Performs ABN-1 0, Turbine Trip o Verifies turbine valves closed o Verifies 230 KV breakers open o Verifies GENERATOR FIELD BREAKER open o Verifies plant loads supplied by Startup Transformers

~---~---~------------

ILT 13-1 NRC Scenario 2 Page 13 of 25

ILT 13-1 NRC Scenario 2 (New) 0 Confirms CLOSED HWC H2 Inlet Isolation Valve, V-567-005 0 Requests SRO confirmation to open main condenser Vacuum Breaker, V-2 -44 0 Opens main cond enser Vacuum Breaker, V-2-44 with its control switch 0 Starts the Auxiliary 0 il Pumps 0 Starts the Turbine Be aring Oil Lift Pump

Performs SP-11 (ICs) an d/or SP-12 (EMRVs) to maintain RPV pressure as directe d 0 SP-11 (ICs) 0 Trips Recirculatio n Pump A for use with IC-A (or Recirculation Purr1p E for use with IC-B) 0 Verifies RPV water level < 160" 0 Cycles Condensa te Return Valve V-14-34 as necessary to mair1tain RPV Pressure with IC-A (or V-14-35 for IC-B) 0 SP-12 (EMRVs) 0 Verifies Torus water level is > 90" 0 Places one or mo re EMRV control switch in the MAN position, then bac k to AUTO Terminus: The reactor is scrammed, the main coneJenser vacuum breaker is open, and RPV water level and pressure are unde1*control Notes/Comments

,.--------'--'---------'------'-------------------------~---

ILT 13-1 NRC Scenario 2 Page 14 of 25

ILT 13-1 NRC Scenario 2 (New)

Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 2 Event No.: 617 Event

Description:

Feedwater line break in the Turbine Building with the failure of Feedwater Check Valves and the loss of all Condensate/Feedwater Pumgs

[Automatically initiates when V-2-44 is opened in Event #6]. Core Spray Parallel Isolation Valves fail to automatically open.

Initiation: The reactor is scrammed, the main condenser vacuum breaker is open, and RPV water level and pressure are under control, or as directed by the Lead Examiner Cues: Feedwater Flow rises greater than Steam Flow; Annunciators P2f, CONDENSER BAY 1-2 LEVEL HI; J8c, FCS/RFRC TROUBLE; P3f, PUMP ROOM 1-3 LEVEL HI; Feedwater flow rising; Annunciator J8a, TRUNNION ROOM TEMP HI; Turbine Building 6P goes positive; Annunciatots K1 b, K2b, K3b, PUMP A, B, C TRIP Time Position Applicant's Actions or Behavior Crew

Responds to Annunciators P2f, CONDENSER BAY 1-2 LEVEL HI 0 Directs an EO to perform the following:

Verify level locally

Verify pumps are in AUTO

VERIFY pump discharge valves are open [ROLE PLAY]

ROLE PLAY: As the EO directed to investigate the Condenser Bay hi level, report the following: all pumps are in AUTO and operating, pump discharge valves are open, and level is 36" water column and rising. Also report there is water raining down from the ceiling in the Feed Pump Room (this is also stated on Page 15 but should be promptly reported to the Control Room).

Responds to annunciator JBc, FCS/RFRC TROUBLE 0 Checks for feed pump runout condition and feed/steam flow 0 Reports feedwater flow is rising and A/C MFRVs are opening further

Responds to annunciator J8a, TRUNNION ROOM TEMP HI 0 Reads individual readouts of tunnel temperature on Panel 1OR and reports 0 Monitors Trunnion Room temperatures ROLE PLAY: When directed as the EO to perform in-plant SP-3 actions, insert Trigger

13. Report when complete.

ILT 13-1 NRC Scenario 2 Page 15 of 25

ILT 13-1 NRC Scenario 2 (New)

Responds to annunciators K1 b, K2b, K3b, PUMP A, B, C TRIP o Reports all Condensate and Feedwater Pumps tripped o Dispatches EO to investigate [ROLE PLAY]

ROLE PLAY: When directed as the EO investigate the loss of Condensate/Feeedwater Pumps, report that water is raining down from the ceiling in the Feedwater Pump Room.

Reports RPV water level lowering

Reports RPV water level low-low (90")

Performs SP-1

Bypasses ADS by placing ADS TIMER keylock switches to BYPASS

Performs SP-7 o Starts a SLC Pump by placing key into the STANDBY LIQUID CONTROL keylock and rotating to FIRE SYS 1 or FIRE SYS 2 o Verifies proper indications o Reports SLC injecting lAW SP-7

Bypasses ADS Timers

Initiates Isolation Condensers for Level Restoration (cycles IC DC Condensate Return Valves open then closes them)

Performs SP-9 (Core Spray) o Verifies Core Spray suction valves open o Confirms closed Core Spray Test Flow Return valves o Confirms one Core Spray Main pump operating in each Core Spray System o Confirms one Core Spray Booster pump operating in each Core Spray System o Confirms open Core Spray Discharge valves o When RPV pressure is< 305 psig, recognizes/reports Core Spray Parallel Isolation Valves did not open as expected CRITICAL TASK 3 o Manually opens all Core Spray Parallel Isolation Valves by placing their control 8witches to OPEN (Critical Task)

Reports Core Spray injecting ILT 13-1 NRC Scenario 2 Page 16 of 25

ILT 13-1 NRC Scenario 2 (New)

Reports RPV water level rising

Lowers RPV pressure by opening some EMRVs by placing CRITICAL TASK 2 AUTO DEPRESS VALVI::switches to MAN (or all available EMRVS to ED) or with Isolation Condensers

Bypasses ROPS by plac in£1 ROPS in BYPASS, if directed

Performs SP-4 0 Presses the OVERRI DE switches that are lit 0 Presses all ACTUATI::D switches 0 Cycles the Parallel Is alation valves as required to maintain RPV water I,eve I

Reports Torus Water ten1perature > 95 oF- EOP entry (due to using EMRVs for pres sure control)

Performs SP-25 (Torus Cooling) 0 Confirms the SYSTEIVI MODE SELECT switch in TORUS COOLING position 0 Starts the selected E:S'I'J Pump by placing its control switch to START 0 Places and holds the SYSTEM PUMPS START PERMISSIVE keylocl<switch in the selected pump position 0 Starts the selected C ontainment Spray Pump by placing its control switch to START 0 Reports Torus Coolin g is in service SRO

Directs RPV pressure co ntroiiAW SP-11 (Isolation Condensers) and/or SP- 12 (EMRVs)

May direct a reactor power reduction with recirculation flow or control rods when the ris ing feedwater flow is reported

If required, may direct th e following:

0 When Trunnion Room temperature is anticipated to exceed 176° F, directs the ATC to manually scram the reactor lAW ABN-*1 OR enters RPV Control EOP based on conserving RP\I inventory 0 Directs SP-2 (Fee dwater) and SP-3 (CRD) to maintain RPV water level 1:38"- 160" 0 Directs SP-1 (Autc~ Initiation Verification) 0 Directs SP-7 (SLC )

0 With RPV water le ve~ below 61 ":

Directs AD~) bypassed

Directs lsolc:ition Condensers initiated, then ILT 13-1 NRC Scenario 2 Page 17 of 25

ILT 13-1 NRC Scenario 2 (New) removed

Directs linin g up Core Spray lAW SP-9 (Core Spray)

Directs lowe~ring RPV pressure as required to allow low pr*essure systems to inject (Critical Task)

If RPV wate~r level reaches 0", directs entry into CRITICAL TASK 2 Emergency Depressurization - No A TWS (Critical Ta sk)

1. Direc:ts ROPS bypassed

2. Verif ies Torus water level > 90"

3. Direc:ts all EMRVs open CRITICAL TASK 3 0 Directs RPV water level 100" - 175" with Core Spray lAW SP-4 (Critica I Task)

If Torus Temperature ex1:eE3ds 95F, may enter and direct Primary Containment Cc1ntrol EOP on high Torus water temperature 0 Directs Torus Coolin~l initiated lAW SP-25 Terminus: RPV pressure has lowered to allow Core Spray injecting into the RPV and RPV water level is rising.

Notes/Comments ILT 13-1 NRC Scenario 2 Page 18 of 25

ILT 13-1 NRC Scenario 2 (New)

Procedures Used Event Procedure 1

Copy of 336.1 handed out 2

Copy of REMA handed out 3

RAP-Q8c 4

ABN-29

RAP-G2f

RAP-G3f

TS 3.1

403

403-2 in 403 book 5

ABN-46

RAP-SSt

RAP-U5a 6

RAP-Q3b

ABN-10

ABN-1

RPV Control - No ATWS EOP

SP-2

SP-3

SP-11

SP-12 7

RAP-J3e

317

317.1

317.4

317.5 ILT 13-1 NRC Scenario 2 Page 19 of 25

ILT 13-1 NRC Scenario 2 (New)

ABN-17

202.1 8

RAP K1b

RAP-K1c

RAP-K1d

RAP P2f

RAP-P3f

RAP-J8a

RAP-J8c

RPV Control - No ATWS EOP

Primary Containment Control EOP

ED- No ATWS EOP

Secondary Containment Control EOP

SP25

SP2

SP3

SP4

SP7

SP9 ILT 13-1 NRC Scenario 2 Page 20 of 25

ILT 13-1 NRC Scenario 2 (New)

Simulator Setup

1. Reset to IC-115

2. Lower reactor power to 97% with recirc flow

3. Place the AVR in manual voltage control lAW 336.1, section 7

4. Have copy of 336.1 (complete procedure) for applicants; mark step 8.1.1 and 8.1.2 complete

5. Have a blank copy of Attachment 403-2 in the 403 binder

6. Ensure Service Water Pump 1-1 is running and Service Water Pump 1-2 is secured NOTE: If snapping this scenario to 0 (zero), when resetting, the AVR may return to AUTO on reset. The AVR must then be returned to manual.

Event Trigger Malfunction 1 N/A N/A 2 Trigger 1 ~ MAL-MSSO 05A

Trips St~3am Packing Blower 1 3 Trigger 3 ~ MAL-NIS02 OF to 150

This cau ses APRM 6 to fail upscale Presets RLY-RPSOCl38 RLY-RPSO 048

This cau se,s a failure of RPS 2 to %

scram fr om the upscale APRM 6 4 Trigger 5 ~ MAL-EDSO 03C

This will insert a loss of USS 1A3 Trigger 7 ~ LOA-CWSO49 to 831

This will restore power to ER-42 ILT 13-1 NRC Scenario 2 Page 21 of 25

ILT 13-1 NRC Scenario 2 (New) 5 Trigger 9----+ ICH-TSI015A to 10 mils ICH-TSI014A to 10 mils

This creates a high vibration to turbine bearing *7 (10 mils) and bearing 6 (10 mils)

NOTE: Booth change final value of Bearing 6 & 7 to 13 mils on a 3 minute ramp, at the direction of the LEAD EXAMINER, after the ATC reduces recirc flow to lower power.

Trigger 30- LOA-CRD024 to 0

This closes CRD Supply Water Valve to Chargin!~ Water Header valve V-15-52 NOTE: The following Presets will delete the high Turbine Vibration when the crew opens V-2-44, Main Condenser Vacuum Breaker AND initiate Event #7 Insert the following Event Trigger (1) and PRESET----+ Command (2) on Trigger 15:

1) hwx05o094r

2) DMF ICH-TSI015A Insert the following Event Trigger (1) and PRESET----+ Command (2) on Trigger 17:

1) hwx05o094r

2) DMF ICH-TSI014A ILT 13-1 NRC Scenario 2 Page 22 of 25

ILT 13-1 NRC Scenario 2 (New)

ILT 13-1 NRC Scenario 2 Page 23 of 25

ILT 13-1 NRC Scenario 2 (New) 7 Preset~ VLV-CSS0111to FAIL AUTO OPEN (for V-20-40)

VLV-CSS004 to FAIL AUTO OPEN (for V-20-15)

VLV-CSS012 to FAIL AUTO OPEN (forV-20-41)

VLV-CSS006 to FAIL AUTO OPEN (for V-20-21)

This prevents the auto opening of all Core Spray Parallel Isolation valves, but does allow manual manipulation ILT 13-1 NRC Scenario 2 Page 24 of 25

ILT 13-1 NRC Scenario 2 (New)

Shift Turnover Current plant conditions:

97% power

Main Generator voltage control is in Manual Shift Activities:

Place the AVR in automatic service lAW 336.1, section 8, starting on step 8.2 ILT 13-1 NRC Scenario 2 Page 25 of 25

ILT 13-1 NRC Scenario 3 (Modified)

Scenario Outline Facility: Oyster Creek Scenario No.: ~ Op Test No.: ~3-1 NRC Examiners: Operators:

Initial Conditions:

95% power

EDG-2 is OOS for maintenance

Surveillance 636.4.003, Diesel Generator Load Test, is in progress on EDG-1

An operator is stationed at EDG-1 for the surveillance

All EDG-1 diesel alarms are in their normal state Turnover:

Complete surveillance 636.4.003, Diesel Generator Load Test, starting at step 6.7, due to a question of operability (oil sight glass was low on the last shift)

Event No. Malf. No. Event Type* Event I I I I Description I

1 MAL- c BOP Trip of EDG-1 during performance of surveillance DGN004A 636.4.003.

TS SRO MAL- I ATC 2 NIS019_0 BOP LPRM 28-25A upscale failure (input to APRM 4).

18A TS SRO MAL- c ATC 3 CRD005_ BOP Outward drifting control rod (rod 18-11).

18-11 TS SRO 4

MAL-R Fuel failure requiring power reduction with recirc RXS001 ATC flow 5 MAL-M Fuel failure willl increase requiring a reactor scram RXS001 Crew and reactor isolation MAL-ICS002B Isolation Condenser B tube leak with steam valves M

6 VLV- Crew failing to close ~eads to RPV Emergency ICS007, c Depressurization 008

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs ILT 13-1 NRC Scenario 3 Page 1 of 20

ILT 13-1 NRC Scenario 3 (Modified)

Simulator Summary Event Event Summary 1 The BOP will continue with 636.4.003, Diesel Generator #1 Load Test at step 6.7. One minute after the diesel starts it will trip and the BOP will momentarily place the EDG-1 NOHMAL START switch in the STOP position. Investigation will reveal EDG-1 tripped on an overspeed condition. The SRO will determines a COLD SHUTDOWN CONDITION LCO applies lAW TS 3.7.C.3 due to neither diesel being available. (BOP: Component Malfunction; SRO: Tech Specs) 2 The BOP will respond to an LPRM upscale failure, affecting APRM 4.

The ATC will bypass APRM 4 and reset the Y:z scram and the BOP will bypass the LPRM from the APRM and the alarm circuit lAW procedure 403. Following successful LPRM bypass, the ATC will un-bypass APRM 4. The SRO will verify APRM 4 operability with Tech Spec 3.1. (ATC: Instrument Malfunction; BOP: Instrument Malfunction; SRO: Tech Specs)

The ATC will respond to an outward drifting control rod (rod 18-11 ).

3 The ATC will enter ABN-6 and attempt to drive the rod to its original position. The rod will continue to move out at which time the ATC will drive the rod to position 00. The BOP will manually scram the rod from panel 6XR. The Reactor Building Operator will Isolate the HCU for rod 18-11. The SRO will evaluate TS 3.2.B.4, Reactivity Control, for applicability and determine that it does not apply since there are not more than six control rods inoperable. (ATC: Component Malfunction; BOP: Component Malfunction; SRO Tech Spec) 4 The crew will respond to rising Off-Gas activity and enter ABN-26, High Main Steam/Off-Gas/Stack Effluent .Activity. When the Off-Gas HI HI alarm is received, the ATC will reduce power with Recirculation Flow to attempt to lower Off-Gas activity. (ATC: Reactivity Manipulation) (PRA) 5 The fuel failure will increase and activity will continue to rise and the crew will scram the reactor and shut MSIVs lAW ABN-26, High Main Steam/Off-Gas/Stack Effluent Activity. (Crew: Major)

ILT 13-1 NRC Scenario 3 Page 2 of 20

ILT 13-1 NRC Scenario 3 (Modified) 6 A tube leak will occur in Isolation Condenser B and the steam line will not be able to be isolated. Entry into Radioactivity Release Control EOP. The Shift Dose Assessor will call the control room and report that offsite dose has exceeded that required for a General Emergency. This will require the SRO to direct an Emergency Depressurization from the Radioactivity Release EOP. This will render the EMRVs as the only method available for RPV pressure control. (Crew: Major; Crew: Component Malfunction After EOP)

(PRA)

Critical When Main Steam Line Radiation Monitors are > 800 mr/hr and Off-Task 1 Gas activity is rising OR if the Off-Gas HI HI alarm is received and does not clear within 15 minutes, THEN scram the reactor and manually isolate the reactor if it doesn't isolate automatically.

Critical When a GE from offsite dose has been dl3Ciared, then Emergency Task 2 Depressurize the RPV.

ES-301-4 Target Quantitative Actual Event Attributes Attributes Number(s)

1. Total malfunctions (5-8) 6 1-6

2. Malfunctions after EOP entry (1-2) 1 6

3. Abnormal events (2-4) 2 3-4

4. Major transients (1-2) 2 5-6

5. EOPs entered/requiring substantive 1 5 actions (1-2)

6. EOP contingencies requiring substantive 1 6 actions (0-2)

7. Critical tasks (2-3) 2 5-6 ILT 13-1 NRC Scenario 3 Page 3 of 20

ILT 13-1 NRC Scenario 3 (Modified)

Op-Test No.: 13-1 NRC Scenario No .: NRC Sim 3 Event No.: 1 Event

Description:

Tri12 of EDG-1 during 12erformance<)f surveillance 636.4.003.

Initiation: Following shift turnover Cues: Annunciator T4b, EDG 1 DISABLED; T1b, U ((>UT RELAY TRIP; EDG-1 UNIT START light extinguishes Time Position Applicant's A ctions or Behavior BOP

Continues with surveillan ce 636.4.003 at starting at step 6.7.

0 Verifies the following fo r EDG-1:

UNIT START and uNIT IDLE lights are extinguished

EDG-1 diesel alar ms are in their normal state

EDG-1 MODE SE LE_CTOR switch is in the PEAKING position 0 Verifies an operator isstationed at EDG-1 [part of initial conditions]

0 Positions the NORM AL START switch for EDG 1 to the START position NOTE: 45 seconds after starting EDG-1 it will trip.

Responds to annunciator T-4-b 0 Positions the NORM AL START switch for EDG 1 to the STOP position (per s te~> 6.10 of surveillance) 0 Directs EO at EDG-1 to investigate cause of the trip.

[ROLE PLAY]

ROLE PLAY: Report that EDG-1 tripped on oven*,pe~ed.

NOTE/CUE: If asked to verify proper operation of th e creepy crank, acknowledge the report and inform them the creepy crank is operati ng properly.

Provides oversight for ED G --1 surveillance .

May direct RAP-T4b be performed [may designate T4b as an expected alarm]

Declares EDG-1 INOPEF~A BLE.

Applies Tech Spec 3.7.C. 3 0 If both diesel generat ors become inoperable during power operation, the reacto rs hall be placed in the COLD SHUTDOWN CONDI Tl ON.

ILT 13-1 NRC Scenario 3 Page 4 of 20

ILT 13-1 NRC Scenario 3 (Modified)

Notifies SMNVWM about EDG status Terminus: EDG-1 has been declared INOPERABLE and the SRO has reviewed/applied Tech Specs.

Notes/Comments ILT 13-1 NRC Scenario 3 Page 5 of 20

ILT 13-1 NRC Scenario 3 (Modified)

Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 3 Event No.: g Event

Description:

LPRM 28-25A upscale failure (input to APRM 4)

[Trigger 3]

Initiation: EDG-1 has been declared INOPERABLE and the SRO has reviewed/applied Tech Specs., or as directed by the Lead Examiner Cues: Annunciators G1c, SCRAM CONTACTOR OPEN; G1d, CHANNEL I; G1f, APRM HI-HI/INOP I; G3f, APRM HI; G6f, LPRM HI; APRM 4 indicates high;LPRM 28-25A indicates high; Annunciator H?a, ROD BLOCK Time Position Applicant's Actions or Behavior BOP

Responds to annunciators G1c, SCRAM CONTACTOR OPEN; G1d, CHANNEL I; G1f, APRM HI-HI/INOP I; G3f, APRM HI; G6f, LPRM HI o Monitors recirculation flow, feedwater flow and temperature, reactor pressure, and RPV water level o Checks APRM 4 drawer for LPRM failures o ReportsLPRM 28-25A indicates high

BypassesLPRM 28-25A lAW 403 o Obtain permission from the US to bypass an LPRM associated with an APRM o Directs the ATC to bypass APRM 4 o Perform the following for an LPRM detector in an APRM channel:

Rotate red input bypass switch in the counterclockwise direction

Position alarm bypass toggle switch to BYPASS

Verify white BYPASS light Lit

Verify amber light Lit adjacent to bypassed detector

Verify white INPUT BYP light for the APRM channel Lit

Adjusts APRM 4 gain if not within 1%

Directs SRO to update Attachment 403-2

Notify Reactor Engineer

~------~------~---------------------------------------------

ILT 13-1 NRC Scenario 3 Page 6 of 20

ILT 13-1 NRC Scenario 3 (Modified)

Reports % scram RPS 1

Reports APRM 4 indicate s high with HI and HI-HI lights lit

Reports all other APRMs indicate normal

Monitors reactor power

Bypasses APRM 4 by pia cing the APRM BYPASS to CH 4 prior to bypassing the LF)RM; may reset the% scram at this point

Monitors APRM 4 output to insure proper response with the LPRM detector bypasse d when the LPRM is bypassed

Un-bypasses APRM 4 after the LPRM is bypassed

Resets the % scram SRO

Directs BOP to bypass A PHM 4 and LPRM 28-25A lAW 403

Directs ATC to un-bypas.sAPRM 4

Directs ATC to reset the *1Y2 scram (when APRM 4 is bypassed or after APRM 4 is returr1ed to normal)

Notifies Reactor Enginee r, SMIWWM of the event

Reviews Tech Specs 3.1. B.1 0 Determines that an o perable APRM Channel only requires 4 operable inputs an<j that APRM 4 is still operable 0 Failure of four chamb ers assigned to any one APRM shall make the APRM inop erable Terminus: LPRM 28-25A is bypassed and the SRC) has reviewed Tech Specs 3.1.B.1

~~

Notes/Comments ILT 13-1 NRC Scenario 3 Page 7 of 20

ILT 13-1 NRC Scenario 3 (IVIodified)

Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 3 Event No.:~

Event

Description:

Respond to an outward driftinq control rod (rod 18-11) rTRIGGER 51 Initiation: LPRM 28-25A is bypassed and the SRO has reviewed Tech Specs 3.1.B.1, or as directed by the Lead Examiner Cues: Annunciator H6a, ROD DRIFT; Control rod position indication for control rod 18-11 is rising Time Position Applicant's Actions or Behavior ATC

Responds to Annunciator H6a, ROD DRIFT 0 Reports control rocl 18-11 is drifting outward of the core 0 Reports entry into ABN-6

Places ROD POWER Switch to ON

Selects control rod 18-11

Applies an insert signal to the control rod

When the control rod is returned to its programmed position, then removes the insert signal

Reports that the control rod continues to drift outward

Applies a continuous INSERT signal to the control rod using the ROD CONTROL switch

Following the rod scram, removes the insert signal

Reports that control rod 18-11 remains at position 00

Directs the EO to isolate the associated HCU lAW with Procedure 302.1, Control Rod Hydraulic System [ROLE PLAY]

Places ROD POWER switch to OFF

Notifies Chemistry to sample Reactor Coolant for activity

Monitors Off-gas activity, Reactor coolant activity, and Main steam line radiation

Notifies Reactor Engineering

Informs US to consult Tech Spec, Section 3.2 .

ROLE As the EO directed to isolate HCU 18-11, report that HCU 18-11 is isolated PLAY (no booth actions required)

Scrams the affected control rod from Panel 6XR lAW procedure 235 0 May direct the EO to verify the following valves open at HCU 18-11: 101, 102, &108 [ROLE PLAY]

ROLE PLAY: When directed as the EO to verify the 101, 102, and 108 valves open at HCU 18-11, report that the valves are open OR directs the EO to isolate HCU 18-11 with cooling water.

ILT 13-1 NRC Scenario 3 Page 8 of 20

ILT 13-1 NRC Scenario 3 (Modified) 0 Obtain Key #129 from the key locker located in the Shift Managers office for Panel 6XR 0 Unlocks Pane16XR 0 Selects the control! rod 18-11 and places the toggle switch to the open (scram) position (up position) 0 Verifies that the scram display illuminates for 18-11 rod position indicator (Panel 4F) [BOOTH]

BOOTH: When control rod 18-11 indicates in a scrammed condition, then DELETE MAL-CRDOOS 1811.

0 When rod movement stops, removes the scram signal by placing the 18-'11 toggle switch to the closed position (down position) 0 Verifies the scram si~lnal is removed 0 Locks Panel 6XR 0 Returns the key to the kel" locker in SM office SRO

Directs entry into ABN-6

Notifies SMIWWM and Reactor Engineering about the drifting control rod

Declares control rod 18-11 inoperable

Reviews/applies Tech Spec 3.2.8.4 Terminu Control rod 18-11 is valved out at position 00, and the SRO has s: reviewed/applied the Tech Specs Notes/Comments ILT 13-1 NRC Scenario 3 Page 9 of 20

ILT 13-1 NRC Scenario 3 (Modified)

Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 3 Event No.: 1 Event

Description:

Fuel Failures Leads to a Reactor Power Reduction [Trigger 9]

Initiation: Control rod 18-11 is valved out at position 00, and the SRO has reviewed/applied the Tech Specs, or as directed by the Lead Examiner Cues: Annunciators 10F1k, AREA MON HI; 10F2c, OFFGAS HI; Offgas radiation monitors rising Time Position Applicant's Actions or Behavior BOP

Reports Main Steam and Off-Gas radiation rising (rna y be reported by ATC)

Responds to annunciator 1OF1 k, AREA MON HI 0 Reports the SJAE AREA ARM is above the highs etpoint

Responds to Annunciator 1OF2c, OFF GAS HI

Reports offgas radiation monitors rising

Performs ABN-26, High Main Steam I Off-Gas I Stack Effluent Activity 0 Directs Chemistry to sample the following for offga sand reactor coolant activity 0 Informs the Unit Supervisor of Technical Specificat ions 3.6.E & 4.6.E 0 Informs Reactor Engineering of the rise in Off gas effluent activity 0 When the OFFGAS HI (10F1c) annunciator is rece ived, notifies Chemistry of the changes

Makes plant announcement of entry into ABN-26 (may be performed by ATC)

Directs entry into ABN-26, High Main Steam I Off-Gas I Stack Effluent Activity ATC

Reports Main Steam and Off-Gas radiation rising (rna y be reported by BOP)

Performs ABN-26, High Main Steam I Off-Gas I Stack Effluent Activity 0 When the OFF GAS HI (1 OF1 c) annunciator is rece ived, reduces reactor power taking the MASTER RECIR c ILT13-1 NRCScenario3 Page 10 of 20

ILT 13-1 NRC Scenario 3 (Modified)

SPEED CONTROLLE:R knob in the CCW direction 0 May insert Cram rods*

May direct performance of ABN-1 Attachment 4 Terminus: The ATC reduced reactor power when tl1e OFFGAS HI (10F1c) annunciator was received Notes/Comments ILT 13-1 NRC Scenario 3 Page 11 of 20

ILT 13-1 NRC Scenario 3 (Modified)

Op-Test No.: 13-1 NRC Scenario No .: NRC Sim 3 Event No.:§ Event

Description:

Fuel Failure Will Rise Resulting In .A Reactor Scram and Reactor Isolation Initiation: The ATC reduced reactor power when the 0 FFGAS HI (1 OF1 c) annunciator was received, or as directed by the Lead Examiner Cues: Annunciator 10F1c, OFFGAS HI-HI; Offgas r*adi ation monitors rising Time Position Applicant's ;tions or Behavior FLOOR At the Lead Evaluator's discretion, wherItt1e OFF GAS HI-HI (1 OF2c)

Evaluator annunciator is received and reactor power is reduced again to clear the alarm, a 15-minute waiting period begin*s t<) see if the alarm will clear. The alarm is designed to NOT clear. Thereto re , announce to the SRO that time compression is being used here and tha t 15 minutes have elapsed and Offgas has isolated [BOOTH]

BOOTH When the Floor Evaluator has announced time compression above, insert Trigger 13 to isolate the AOG system.

~------------*--------- -----

Performs ABN-26, High I\tla in Steam I Off-Gas I Stack Effluent Activity 0 When the OFFGAS HI-H I (1 OF2c) annunciator is received, reduces re'act or power taking the MASTER RECIRC SPEED CO NT ROLLER knob in the CCW direction CRITICAL TASK 1

Scrams the reactor lAW AB N-1 (may also scram due to offsite dose rate) 0 Depresses both MamJa I Scram Pushbuttons 0 Places the Reactor Mod e Selector switch in SHUTDOWN 0 Verifies all control rocIs fully inserted 0 Reports immediate sc;ra m actions complete

Performs ABN-26 0 Confirm V-7-31, Off Gas* Exhaust Isolation Valve closed 0 Confirms AOV-0001 N-C)001 B, AOG Inlet Valves closed 0 Places Drain Valves 'v--/-291SOV-016 control switch in the CLOSE position 0 Closes the following ' ral ves (the following valves will be ILT13-1 NRCScenario3 Page 12 of 20

ILT 13-1 NRC Scenario 3 (Modified) closed if RPV Lo-Lo Iev el was reached post scram):

0 MSIVs 0 Isolation CondeSE! rt ube side vent valves 0 V-24-29, Reactor water sample valve 0 w V-24-29, Reactor ater sample valve 0 V-6-395, Drywell J\ir Supply valve 0 May evacuate the Re actor Building and Turbine Building 0 Refers SRO to EP-N\-1 010 SRO

When the time compress io n has been announced, directs the A TC to scram the reacto ra nd perform ABN-1 [the SRO may CRITICAL TASK 1 direct a reactor scram pri or to time compression being announced if they believet he rise in main steam activity cannot be turned]

Following the scram, dire~cts closure of the MSIVs and sample valves lAW ABN -26 (the valves will be closed if RPV Lo-Lo level was reached pc>st scram):

Directs entry into RPV C on trol- No ATWS EOP 0 Directs the Crew to mai ntain RPV water level 138" - 160" using SP2 (Cond/FW ) a nd/or SP3 (CRD) 0 Directs the Crew to mai ntain RPV pressure (approximately) 800-- 1000 psig using the Isolation Condensers (SP-11) or EMRVs (SP-12)