Text

05000321/366-2009-301 Draft Simulator Scenarios
	ML091730171
Person / Time
Site:	Hatch
Issue date:	06/22/2009
From:	; Division of Nuclear Materials Safety II
To:	; Southern Nuclear Operating Co
References
	50-321/09-301, 50-366/09-301
	Download: ML091730171 (132)
	v • d • e

Page lof34 Scenario Summary DRAF'T Facility: E. I Hatch Scenario No.: 4-01 Op-Test No.: 2009-301 Initiating Conditions: I Unit 2 is at 60% perfonning a reactor start-up. All equipment is operable.

Turnover I Continue increasing reactor power using the reactivity plan.

Summary:

Evept 1: ComponentJTS; As the team prepares to raise reactor power, the "2A" Reactor Recirculation pump seals will develop a failure that results in reactor coolant leaking into the DryweU (DW). The team will trip and isolate the "2A" Reactor Recirc pump. The Shift Supervisor (SS) will address TS for coolant leakage and single Recirc loop operation.

Event 2: ComponentJTS; The Recirc pump seal leak (Event 1) causes DW pressure to increase.

The team will receive a P603 alarm that will direct DW venting to be placed in service. The BOP operator will attempt to start Standby Gas Treatment (SBGT). The SBGT suction dampers will not open for the first SBGT system the operator attempts to start. The opposite SBGT train will then be started and DW venting will be aligned. The SS will address TS for an inoperable train of SBGT.

Event 3: Reactivity; The tripped Recirc pump (Event 1) will result in operation inside the Region of Potential Instabilities of the Power-To-Flow map. The team will insert control rods to exit the region.

Event 4: Nonnal; The power reduction (Event 1) will result in Feedwater flow decreasing to the point that their minimum flow valves cycle open. The team will remove one RFPT from service.

Event 5: ComponentJTS; SRV "2G" will inadvertently open. The team will attempt to close the SRV IAW the abnonnal procedure for a stuck open SRV. The SRV will go closed after the team directs the fuses to be pulled (Critical task). If Torus temperature exceeds 95°F, the team will place RHR in Suppression Pool Cooling. The SS will address TS for the failed SRV.

Event 6: Major/Component; The "2C" Station Service Air Compressor (SSAC) will trip. The "2B" SSAC will not auto start, and an operator will start the "2A" SSAC.

Event 7A: Major/Component; The running RFPT will trip, resulting in Reactor Water Level (RWL) decreasing below +3 inches. The reactor will scrarnlbe scrammed. An ATWS condition-,

will exist, requiring manual control rod insertion (Critical task). RCIC will start, but RPV level will decrease since makeup requirements exceed RCIC capacity. HPCI will NOT auto start.

Event 7B: Component; RCIC will trip. If the team has not started a RFPT (Event 7 A) to control reactor water level, the trip of RCIC will leave the Feedwater system as the only high pressure source of injection. The team will start and use a RFPT that was previously shutdown (Event 4) to control RWL above -185 inches (Critical Task).

Page 2 of34 Critical Tasks and ES 304-4 Attributes

) DRAFT

. Facility: E. I Hatch Scenario No.: 4-01 Op-Test No.: 2009-301 Critical Tasks

Remove fuse to close SRV "G" prior to entering the unsafe area of the Boron Injection Initiation Temperature curve (Event 5).

Commence insertion of control rods before entering the unsafe region of the Heat Capacity Temperature Limit graph (Event 7A).

Maintain RWL above -185 inches. This is the lowest level that corresponds to adequate core cooling with injection (Event 7B).

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 6 1. Recirc Pump Seal failure

2. SBGT suction dampers

3. SRV fails open

4. Failure of SSAC I

I 5. Control Rods fail to insert

6. HPCI Fails to start

7. RCIC trip

2. Malfunctions After 1-2 2 1. HPCI Fails to start EOP Entry 2. RCIC Trip

3. Abnormal Events 2-4 3 1. SRV Fails Open

2. Recirc Pump Trip

3. Loss of Air

4. Major Transients 1-2 1 1. Reactor scram!ATWS

5. EOPs entered, 1-2 2 1. RCA EOP Flow Chart requiring substantive 2. RC EOP Flow Chart actions

6. EOPs contingencies 0-2 1 1. CP-3 ATWS Level Control Flow Chart requiring substantive actions

7. Critical Tasks 2-3 3 1. Pull fuses for SRV

2. Insert Rods during ATWS

3. Maintain RWL >-185 inches

Page 3 of34

) AppendixD Scenario Outline Form ES-D-1 DRAFT Facility: E.IHatch Scenario No.: 4-01 Op-Test No.: 2009-301 Examiners: Operators: SRO RO BOP Initial Conditions.: Plant is at 60% power.

Turnover: A plant startup is in progress. Increase reactor power lAW the reactivity plan.

Event Malf. No. iEvent Event No. Type* Description 1 mfB3L39A C (ATC) Recirc Pump "A" seal leakage causes DW leakage.

mfB3L45A TS (SRO) Pump is secured and isolated.

aoB31-603A 2 fET-T46-01 C (BOP) Vent the DrywelL Suction valves for the first SBGT started will fail fET-T46-02 TS (SRO) to open, examinee must use opposite train to vent the Drywell 3 R (ATC) Decrease reactor power by inserting control rods to return to the

) acceptable region of the power to flow map.

~ N (BOP) Remove one RFPT from service 5 mfB2L130G rfB2L306 C (ATC) Stuck open SRV, 2B21-F013G, only a tracking RAS.

6 mfP5L222C mfP5L222A C (BOP) Loss of "2C" SSAC. "2B" SSAC does not start.

Manually start "2A" SSAC.

7A mfN21_87A mfN21_87B M (ALL) The running RFPT trip, the reactor scrams/is scrammed and all rods m:fE4L107 C (BOP) do not insert (ATWS). HPCI fails to start (2E41-FOOI failed closed).

mfCIL211 RCIC starts but RWL decreases since makeup requirements exceed RCIC capacity. RPV level will go below -185" if a RFPT is not used to control RPV level.

~B mf2E5LllO C (BOP) After RWL band has been lowered to below -60" AND the MSIVs have been over-ridden, RCIC will trip. RPV level will go below

-185" if a RFPT is not used to control RPV leveL

(N)ormal, (R)eacti vity, (I)nstrument, (C)omponent, (M)ajor

AQQendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 1 Page 4 of34 Event

Description:

Recirc Pump "A" seal leakage causes DW leakage.

Pump is secured and isolated II Ti~~ J Position . . 1 Applicant's Actions or Behavior 1 Simulator Operator With Chief Examiners Permission:

Call control room BOP operator and request the following (this action will ensure the ATC operator responds to the Recirc Seal leak):

As the Chemistry Lab, request a reading from the Pre-Treatment Radiation Monitor, 2D 11-K60 1.

Simulator Operator When the candidate pulls 34GO-OPS-005 AND before power is increased; press (RB-l) to activate:

mfB3L39A (30/30)

mfB3 L 45A (90/50)

aoB31-603A (50/1 0)

ATC

Receives Annunciator "Outer Seal A Leak Detection Flow High",

34AR-602-116-2

Observes and compares 2B31-R603A, Seal A No.1 pressure indicator, AND 2B31-R602A, Seal A No.2 pressure indicator, to determine the outer seal has failed.

Notifies SS that the Outer Seal on Recirc A has failed

Has an Extra Operator perform 34SV-SUV-019-2, Surveillance Checks, to determine magnitude of leak.

Monitors 2Dll-R630, Fission Products Monitor recorder, to detennine IF primary system coolant is leaking from seals.

Monitors Drywell pressure

657 Panel Alarm - Multipoint Temperature RCDR 247-R626 Temperature High 657 -025 -----_. __ ._ ... _._---_ .... __ ._---

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A!2£endix 0 Required Operator Actions Form ES-O-2

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Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 1 Page 5 of34 Event

Description:

Recirc Pump "A" seal leakage causes DW leakage.

Pump is secured and isolated Time Position Applicant's Actions or Behavior SS

Receives Primary Containment Press High alarm (603-115)

Directs Operator to Check DW Leakage

Directs the operator to vent the DW with SBGT, when DW pressure approaches 0.65 psig. (SEE EVENT 3 FOR SBGT START)

Simulator Operator As the operator checking DW leakage, report:

DW Equipment drain leakage is stable at 1.7 gpm

Floor drain leakage has increased from 0.8 gpm to 12.1 gpm.

SS

Directs operator to shutdown and isolate Recirc pump A

Enters Tech Specs 3.4.4 for Rx Coolant Leakage (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to reduce leakage to within limits.

After Recirc pump A is tripped, enters Tech Spec 3.4.1 for Single Loop Recirc operation. (Notifies STA that new limits apply for APLHGR, MCPR, LHGR, and APRMs Simulated Thermal power -New Setpoints are required within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .)

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AQQ.endix 0 Required Operator Actions Form ES-O-2 I

Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 1 Page 6 of34 Event

Description:

Recirc Pump "A" seal leakage causes DW leakage.

Pump is secured and isolated Time Position Applicant's Actions or Behavior ATC

Per 34AR-602-116-2 and 34S0-B31-001-2, Recirc System, Performs one of the following to secure the Reactor Recirc Pump:

Either (actions for Immediate Shutdown) 0 Place the ASD "A" control switch in Pull to Lock (P602) 0 Depress the ASD "A" Shutdown pushbutton (P602)

OR (Actions for Shutdown in a Timely Manner) 0 Depress the ASD "A" Shutdown pushbutton (P602) 0 Confirm ASD A speed ramps to -370 RPM (2B31-R660) or 22% (2B31-R661) 0 Confirm Recirc Pump A goes to 0 RPM (2B31-R660) or 22%

(2B31-R661) and drive coasts to 0 gpm (2B31-R614 or R617) 0 Confirm ASD A Start pushbutton illuminates i 0 Place ASD "A" control switch 2B31-S002A to Pull-To-Lock (P602)

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AQQendix 0 Required Operator Actions Form ES-O-2

).. Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 1 Page 7 of34 Event

Description:

Recirc Pump "A" seal leakage causes DW leakage.

Pump is secured and isolated Time Position Applicant's Actions or Behavior ATC

Receives and Acknowledges the following Annunciators:

o Recirc loop A Out of Service 602-127, o Speed Control A signal failure 602-132 o Fluid Drive A Scoop Tube Lock 602-126 o RBM Downscale 603-211 o Rod Out Block 603-238 o Heater Trouble Alarm 650-135 (may come in and clear)

Closes 2B31-F031A, Reactor Recirc A Pump Disch Vlv o Receive annunciator: Recirc Flow Limit 603-134

Closes 2B31-F023A, Reactor Recirc A Pump Suction Vlv

Dispatches SO to close Seal Injection To Pump A Header Isolation Valve,2B31-F008A.

Enters 34AB-B31-001-2 "Reactor Recirculation Pump(s) TRIP,

) Recirc Loops Flow mismatch, Or ASD Cell Bypass."

o Notify Plant Management and Load Dispatcher Simulator Operator When requested to close 2B31-F008, press (RB-2) to activate:

rfB3L29, Recirc mini purge B31-FOI6A closure (simulates B31-F008A being closed)

AND THEN

MODIFY aoB31-603A to 10 @ 40 Simulator Operator If another DW leakage check is requested, report:

Drywell floor drain leakage has decreased to 1.8 gpm.

AQ.Qendix 0 Required Operator Actions Form ES-O-2

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Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 1 Page 80f34 Event

Description:

Recirc Pump "A" seal leakage causes DW leakage.

Pump is secured and isolated l Time Position Applicant's Actions or Behavior Simulator Operator Proceed to the next IIC failure at the Chief Examiner's direction.

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AImendix 0 Required Operator Actions Form ES-O-2

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Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 2 Page 9 of34 Event

Description:

Drywell venting, failed SBGT.

Time Position Applicant's Actions or Behavior Note; This event will begin when an operator is given direction to begin venting the Drywell due to the Recirc Pump seal leak in Event 1 SS

When venting is required; Directs Operator to vent the drywell.

BOP

Enters 34S0-T48-002-2, "Containment Atmosphere Dilution System" or uses placard to vent the Drywell.

Enters 34S0-T46-001-2, "Standby Gas Treatment System" procedure or uses placard at the 2Hll-P657 panel to start SBGT 2A or 2B.

Determines that 2T46-FOOl (A or B) and 2T46-F003 (A or B) for the selected train will not open

Informs SS that SBGT (A or B) cannot be started due to suction

) valve failure.

Note: Event triggers will insert overrides to keep the first valves that are operated from opening and thert remove the event trigger from the opposite SBCT train. The examinee will not be successful with the first SBCT train; however, the second SBCT trail'! used will be successful.

I SS

Enters Tech Specs 3.6.4.3 for the SBGT with the failed suction dampers (7 day RAS to operable status) i

Direct that maintenance be contacted to determine problem with failed SBGT suction dampers.

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A~endixD Required Operator Actions Form ES-D-2

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Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 2 Page 10 of34 Event

Description:

Drywell venting, failed SBGT.

Time Position Applicant's Actions or Behavior BOP

Vents with the opposite train of SBGT per 34S0-T46-00 1-2 SBGT System procedure or uses placard.

0 Opens 2T46-F001 (A or B) or 2T46-F003(A or B) for the subsequent train.

0 Places SBGT Fan (A or B) control switch to "RUN."

0 Receives alarm 2B (or 2A) SBGT Switch Not In Auto 654-076 (or 657-091) 0 Confirms 2T46-F002 (A or B) OPENS 0 Confirms SBGT Heater red light illuminates.

) 0 Opens 2T48-F334A or 2T48-F334B (both valves may be opened) 0 Receives alarm DW Vent Exh Bypass Vlv Open 654-002 (or 657-008) 0 Receives alarm DRWUTorus N2 MlU 2 Inch Isol Valves Open 654-035 (or 657-042) 0 Opens 2T48-F335A or 2T48-F335B(both valves may be opened) 0 Opens 2T48-F336A or 2T48-F336B. (both valves may be opened) 0 Monitors DW pressure

AQQendix D Required Operator Actions Form ES-D-2 lOP-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 3 Page 11 of 34 Event

Description:

Insert control rods to return to safe area of Power to flow map Time I PositloiIl Applicant's Actions or Behavior I SS

IAW 34GO-OPS-005-2 Power Changes,

Within 15 minutes of entering the Immediate Exit Region of the Power to Flow map, directs operator to exit the region by inserting control rods.

Has a control rod movement brief per 34GO-OPS-065-0 Simulator Operator

If the Team calls for the STA or Reactor Engineering for rod movement recommendations, then recommend:

0 "Insert rods in reverse order, starting with the current rod group."

)

SS

Directs the operator to insert the rods to the insert limit after consulting with the STA ATC

Inserts control rods per 34GO-OPS-065-0, starting with control rod GROUP 51.

During rod insertion, rod steps will be performed in reverse sequential order, starting at the highest numbered step. (** rod steps are not required to be performed sequentially, but must be positioned to their RWM insert limit prior to inserting lower numbered groups).

Selects Rod

Places Control Rod movement switch to the IN position

Verifies Rod moves using Rod display information and Rx and Generator power decreasing.

A~endixO Required Operator Actions Form ES-O-2 I

Op* Test No.: 2009*301 Scenario No.: 4*01 Event No.: 3 Page 12 of34 Event

Description:

Insert control rods to return to safe area of Power to flow map Time Position Applicant's Actions or Behavior ATe

Adjust 2ell-F003 as required to maintain 220 - 280 psid drive water dp for control rod movement.

It is allowable to flag the RBM downscale and Rod Block alarms, if desired.

ATe Note: RBM Downscale 603-211 will alarm during this movement due to the significant rod worth of these rods.

Releases Rod movement switch so that the control rod stops 1 position before the insert limit unless the insert limit is 00.

Initials Rod movement Sheet.

Verifier, if available, Initials Rod movement sheet.

Notifies the SS when they are out of the region of potential instabilities.

Note: If Power is decreased enough, the LPRM Downscale Alarm 603-246 will annunciate.

AQQendix D Required Operator Actions Form ES-D-2

)) Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.:

Page 13 of34 Event

Description:

Insert control rods to return to safe area of Power to flow map Time Position Applicant's Actions or Behavior Simulator Operator:

When directed by the Chief Examiner; If the team does not address shutting down a RFPT in a timely manner, then as Shift Manager, call the Control Room and direct the SS:

0 "Respond to the RFPT low flow annunciator(s)."

The intent of this communication is prompt the team to begin the normal evolution of shutting down one of the RFPTs.

I I

AQ.Qendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 4 Page 14 of34 Event

Description:

Remove one RFPT from service Time Position Applicant's Actions or Behavior

Reactor Feed Pump Shutdown 0 Confirm Feedwater Flow is less than 7 Mlbmlhr.

0 Confirm RFPT's are in Automatic control on 2C32-R600, Master Controller.

0 Place 2C32-R601A (B), RFP A (B) MIA Station, in ManuaL 0 Decrease RFPT 2A (2B) speed with RFP A (B) M I A Station until the other RFP is controlling reactor vessel leveL 0 Place the RFPT, 2A (2B) TMR Mode Switch to SS. Confirm Speed Setter (yellow) light illuminates.

0 Take 2N21-C005A (B), RFPT 2A (2B) Speed Setter, to lower, until turbine speed stops decreasing, paneI2Hll-P650.

0 Dispatch SO to confirm open RFPT drain valves 0 Confirm HP Stop Valves (2Nll-F012A or B) and LP Stop

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I Valve (2N38-F009A or B) close (P650)

NOTE: The team can elect to trip the RPFT, if so; 0 Receives alarm; RFPT 2A OR B Tripped 650-325 (A RFPT) 650-326 (B RFPT) 0 When RFPT 2A (2B) speed is zero (the RFPT may windmill if the suction valve and min flow are open and will not go on TG),

confirm 2N39-C002A (B), RFPT 2A (2B) Turning Gear motor, STARTS and Turning Gear engages (subsection 7.1.7 has instructions for placing a RFPT on TG).

L -___________

A~endixO Required Operator Actions Form ES-O-2

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Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 5 Page 15 of34 Event

Description:

Stuck open SRV, 2B21-F013G.

Time Position Applicant's Actions or Behavior With Chief Examiners Permission:

Simulator Operator enters mfB21 130G, SRV G fails open. (RB-3)

All

Receives "Safety Blowdown Pressure High," 34AR-602-311-2 and "Safety Blowdown Valves Leaking," 34AR-603-122-2 alarms SS

Directs operator to enter 34AB-B21-003-2, Failure of SafetylRelief valves, and dispatch an operator to pull the fuses for SRV "G."

I ATC

Enters 34AB-B21-003-2, Failure of SafetylRelief valves ATC

Determines that SRV "G" is open

Manually cycles SRV "G"

Attempts to reset ADS as follows:

0 Depresses the ADS Logic A Timer Reset pushbutton 0 Depresses the ADS Logic B Timer Reset pushbutton

Attempts to reset LLS as follows:

0 Depresses the LLS Channel AlC Reset pushbutton.

0 Depresses the LLS Channel BID Reset pushbutton.

Informs SS that the "G" SRV is open and the fuses will have to be pulled for the valve

Notifies SSS to pull the Fuses for SRV "G."

(Critical Task - Remove fhse to close SRV "G" prior to entering the unsafe area of the Boron Injection Initiation Temperature curve)

Simulator Operator, 2 Minutes after the request was made to pull fuses for the SRV "G", enters rfB2L306 to simulate pulling the fuses for SRV "G." Then, Notify the crew that the fuses have been pulled for SRV "G." Intent is for Torus Temperature to remain below 95°F. (RB-4)

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AW2endix 0 Required Operator Actions Form ES-O-2

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Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 5 Page 16 of34 Event

Description:

Stuck open SRV, 2B21-F013G.

Time Position Applicant's Actions or Behavior SS

Initiates a Tracking RAS for TS LCO 3.6.1.6

Directs operators to verify that the "G" SRV is closed, after the fuses are pulled.

ATC

Confinns that SRV "G" is closed by monitoring:

0 SRV tailpipe temperature decrease 0 Torus level stabilizing 0 Torus Temp stabilizing 0 Rx and Generator power returns to the pre-event level I

ATC

Resets the SRV leak detection by placing the Leak Detection Logic A Reset key lock switch to Reset position and back to Nonnal position and confinn that the Amber SRV indicating lights have Extinguished.

Infonns the SS that SRV "G" is closed.

SS

Infonns the crew that operability of the suppression chamber-drywell vacuum breakers must be perfonned within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per 34SV-T48-002-2, Suppression Chamber To Drywell Vacuum Breaker System Operability.

Notifies Chemistry and initiates a CR to initiate increased monitoring of vessel moisture content carryover per 64CH-SAM-025-0.

A~endixD Required Operator Actions Form ES-D-2

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Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 5 Page 17 of 34 Event

Description:

Stuck open SRV, 2821-F013G.

Time Position Applicant's Actions or Behavior NOTE: If the request to pull the fuses is not given for 2 or more minutes torus temperature will exceed 95°F. The remainder of this Event is NOT required if Torus temps remain below 95°F.

ALL

The team recognizes torus temperature is above 95°P.

ATC

Enters 34AB-T23-003-2, Torus Temperature Above 95°P

Confirms the high temperature by OBSERVING the Suppression Pool bulk average temperature on the SPDS primary display

Places RHR in Suppression Pool cooling per 34S0-Ell-OlO-2, Residual Heat Removal I

NOTE: The operator may place torus cooling in service by using the Placard that's available or using the appropriate section of the procedure. These steps assume the Placard is used.

The A or B loop of RHR may be used. The following steps are written assuming "B" loop and "B" pump is used. If "A" loop is used, substitute "A" for "B" for valves and if "B" pump is not used substitute "A", "C", or "D" for "B" pump.

BOP

Enters 34S0-Ell-OlO-2, Residual Heat Removal 0 Places RHRSW in service 0 Prelubes RHRSW pump 0 Overrides 2EI1-P068B Low Discharge Pressure Interlock

AQ.Qendix 0 Required Operator Actions Form ES-O-2

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Op-Test No.: 2009-301 Scenario No.: ~~

4-01 Event No.: ~~

5 Page 18 of34 Event

Description:

Stuck open SRV, 2B21-F013G.

Time Position Applicant's Actions or Behavior 0 SEC System Auto Initiation Signal Present (650-234 remains alarmed) 0 Auto Blow Down CS or RHR Press Permissive (602-312 remains alarmed) 0 RHR Flow Low <<601-215 is received and clears)

BOP 0 Positions 2Ell-F068B to 45% OPEN 0 Starts RHRSW pump B

- RHR HX B DiffPress Low (601-215) alarms i 0 Places 2Ell-F068B Low Discharge Pressure Interlock switch to normal position.

0 Positions 2Ell-F068B to obtain < 4400 GPM AND < 450 PSIG

- RHR HX B Din'Press Low (601-215) alarm clears

AQQendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 5 Page 19 of34 Event

Description:

Stuck open SRV, 2B21-F013G.

Time Position Applicant's Actions or Behavior BOP

Place RHR loop B in Suppression Pool Cooling o Does NOT position the 2/3 Core Height Permissive switch.

(RWL will NOT be lowered to below 2/3 core height) o Does NOT place the Containment Spray valve Control switch in the manual position. (LOCA signal is not present) o Confirm open 2Ell-F048B, HX Bypass Vlv.

o Close CLOSE 2Ell-F047B, Hx Inlet Vlv.

0 Start "2B RHR pump

- SEC System Auto Initiation Signal Present (650-234) alarms

- Auto Blow Down CS or RHR Press Permissive (602-312) alarms

- RHR Flow Low (601-215) alarms o Open 2E11-F028B, Torus Spray or Test Vlv.

o Throttle open 2E11-F024B, Full Flow Test Line Vlv. and establish

) RHR flow of less than or equal to 7700 gpm (R603B)

- RHR Flow Low (601-215) alarm clears o Open 2Ell-F047A(B), Hx Inlet Vlv.

o CLOSE 2Ell-F048A(B), Hx Bypass Vlv.

o Reports to SS that RHR has been placed in Suppression Pool Cooling mode

- - - - c~ __ ~ ......

AQ.Qendix 0 Required Operator Actions Form ES-O-2

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Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 6 Page 20 of34 Event

Description:

Loss of "2C" SSAC, "2B" SSAC does not start, manually start "2A" SSAC Time Position Applicant's Actions or Behavior Simulator Operator, as directed by the Chief Examiner, Insert mfP51_222C, Air Compressor trip. (RB-5)

BOP

Responds to "PANEL 2Hll-P700 SYSTEM TROUBLE" annunciator on 2Hll-P650 panel.

Responds to annunciator "AIR CMPSR 2C Tripped/ Shutdown."34AR-700-233-2 i

Addresses the abnormal procedure 34AB-P51-001-2, "Loss Of Instrument and Service Air System or Water Intrusion Into The Service Air System."

0 Places the control switch for "B" compressor to start at 2Hll-P650.

0 Recognizes "B" air compressor will not start.

0 Places the switch for "A" air compressor to start, the air compressor does start.

0 Places the control switch 2P51-S3, on Pane12Hll-P650 for Air

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Comp 2P51-COOIC to OffPull-To-Lock 0 Contacts Health Physics.

0 Has the SSS to locally check Air Compressor 2P51-COOIC Microprocessor for cause of Trip.

0 Investigate cause of 2P51-COOIB fail to run.

0 Notifies the SS of the status of the air system.

i i

SS Notifies maintenance to begin investigating the trip condition on C Air Compressor and failure on the "B" SSAC.

Simulator onerator:

If called as Unit One SS or ATe: with request to cross-tie air systems report the Unit One is operating on only the "A" compressor and it will not supply both units, therefore; cannot cross-tie.

A~endixO Required Operator Actions Form ES-O-2

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)11 Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 7A Page 21 of34 Event

Description:

RFPT Trip / ATWS actions / HPCI Failure to Start Time T Position-, Applicant's Actions or Behavior Simulator Operator:

When directed by the Chief Examiner; Only activate ONE of the follO'lNing malfunctions:

If the "A" RFPT is in service, Insert mfN2L87 A (RB-6)

If the "B" RFPT is in service, Insert mfN21_87B (RB-7)

All

Diagnose trip of Feedwater pump / Loss of all High Pressure Feedwater Injection

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SS

Direct NPO to scram the reactor 0 Enters RC or RC-A EOP Flowchart.

0 Directs CBO to perform RC-1 placard.

0 Directs BOP to perform RC-2 and RC-3 placards.

SS Enters RC-A Flowchart (ATWS) and CP3 (ATWS Level Control).

Directs ATC to:

0 Confirm the reactor Mode Switch in Shutdown.

0 Confirm ARI Initiation.

0 Confirm Recirc runback to minimum.

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AQQendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 7A Page 22 of34 Event

Description:

RFPT Trip I ATWS actions I HPCI Failure to Start Time Position Applicant's Actions or Behavior ATC

Manually SCRAMs the Reactor using the SCRAM pushbuttons.

Places Rx Mode Switch in SID.

Initiates Alternate Rod Insertion (ARI) by rotating the button collars and depressing both ARI push buttons at the same time.

Uses the Full Core Display and Rod Worth Minimizer to determine that all control rods are not inserted past position 02.

Informs the SS that all rods are NOT fully inserted (ATWS).

Inserts IRMs and SRMs.

Places SDV Isol Vlv Switch to "ISOL" and verifies closed.

If not tripped, places Recirc to minimum speed.

)

ATC

Reports to the SS that:

0 The Reactor Mode Switch is in the Shutdown position.

0 ARI has been initiated (CBO may initiate ARI at this time).

0 Recirc is at minimum speed.

)

Aooendix 0 Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 7A Page 23 of34 Event

Description:

RFPT Trip I ATWS actions I HPCI Failure to Start Time Position Applicant's Actions or Behavior BOP Performs actions of RC-2 and RC-3 after Reactor SCRAM.

BOP

Confirms proper Level Control response:

Checks ECCS Injection Systems.

0 Observes HPCI failure to start and informs SS.

0 Either starts RCIC or verifies it auto starts when level goes below

-35 inches.

BOP

When feed flow is less than the capacity of the S/U level control valve

(::::; 1.5 mlbm/hr), then:

Opens 2N21-FI25.

Places 2C32-R619, FW S/U level control valve controller, in Auto, set at approximately 9 inches.

Closes 2N21-FllO.

)

i BOP

Attempts to manually start HPCI:

0 Open 2E41-F059, Lube Oil Cooling Wtr Valve.

0 Start 2E41-C002-2, Barom Cndsr Vacuum Pump.

0 Attempt to open 2E41-FOOI, Turb Steam Supply Vlv.

0 Informs SS of 2E41-FOOI failure to open

~ ..

AQ.Qendix 0 Required Operator Actions Form ES-O-2

-- -~---------- ---~--------.----

)

Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 7A Page 24 of34 Event

Description:

RFPT Trip I ATWS actions I HPCI Failure to Start I Time Position Applicant's Actions or Behavior SS

Directs BOP operator or SSS to contact maintenance and have HPCI failure investigated.

BOP

Manually starts a Reactor Feedwater Pump (P650):

0 Confirm the Condensate system is available.

0 Take the A or B RFPT Reset-Trip control switch to reset.

0 Confirm the RFPT HP stop valve red light illuminates.

0 Confirm the RFPT LP stop valve red light illuminates.

0 Confirm the RFPT trip annunciator clears 650-325 (or 326).

0 Raise RFPT speed using the Speed Setter switch until speed is at 2100 RPM +/- 100 RPM and confirm MIA Station Permissive white

) light illuminates.

0 Place the RFPT TMR Mode Switch to MIA and confirm the MIA station green light illuminates.

0 Raise RFPT speed with the MIA station until RFP discharge pressure (R635A/B) > reactor pressure (R605A).

I

AQQendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 7A Page 25 of34 Event

Description:

RFPT Trip I ATWS actions I HPCI Failure to Start Time Position Applicant's Actions or Behavior I

I I

BOP

Inject to the RPV and control reactor water level in the band assigned by the SS by performing one of the following:

0 Throttling 2N21-FllO (Bypass Valve) as necessary to raise or lower injection flow rate.

OR 0 Confirm open or open 2N21-F125 (SULCV isolation valve) and then throttling 2N21-Flll (2C32-R629 S/U LvI Control Valve) as necessary to raise or lower injection flow rate.

Note: Until the SS assigns a reactor water level band, the level band is I lAW 34AB-C71-001-2, RC-2 placard.

)I I I

i i

I I

BOP

Monitors RPV pressure.

Confirms proper operation of pressure control system LLS.

If necessary, allows RPV pressure to exceed 1074 psig then cycles any SRV to initiate Low Low Set.

Maintains RPV pressure between 1074 and 800 psig.

As time permits notifies SS of pressure control system operation.

)

Al2I2endix D Required Operator Actions Form ES-D-2

\

Op*Test No.: 2009*301 Scenario No.: 4*01 Event No.: 7A Page 26 of34 Event

Description:

RFPT Trip / ATWS actions / HPCI Failure to Start Time Position Applicant's Actions or Behavior SS

Directs CBO or STA to report reactor power or observes reactor power on SPDS.

ATC/STA

Reports power level to the SS.

)

Note: the SS may proceed down the "power" or "level path first.

SS

Directs CBO to trip the Recirc Pumps if power is >5%.

Directs CBO to reset ARI and insert control rods per 31EO-EOP-I03-2.

)

ATC

Trips Recirc pumps, if not already tripped

A,W2endix 0 Required Operator Actions Form ES-O-2

)

Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 7A Page 27 of34 Event

Description:

RFPT Trip I ATWS actions I HPCI Failure to Start Time Position Applicant's Actions or Behavior

Enters 31EO-EOP-I03-2, "EOP Control Rod fusertion Methods."

Directs the SSS to send a SO to place the ARI test switches in test on 2CII-POOI (local panel) per the 103 procedure.

Places the SDV high level trip bypass switch in the "Open" position.

Direct the SSS to override all automatic scram signals per 31EO-EOP-103-2.

Places the Disch Vol Isol Test Switch to NORM (this action may not be done until the SSS reports back that the automatic scrams have been overridden).

)

I i

I I

i i

If asked for a rod insertion order, the STA will recommend to the ATC to start i in the center of the core and spiral out in a "black and white" pattern. i i

I I

I i

I

~ -~

ATC

Prepares to manually insert control rods lAW 31EO-EOP-I03:

Aooendix 0 Form ES-O-2

~

)

Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 7A Page 28 of34 Event

Description:

RFPT Trip / ATWS actions / HPCI Failure to Start Time Position Applicant's Actions or Behavior (Critical Task - Commence insertion of control rods before entering the unsafe region of the Heat Capacity Temperature Limit graph).

Places the Reactor Mode Switch in "Refuel."

Places the RWM Bypass Switch in "Bypass."

Ask STA which rods have the highest worth or inserts rod in a black and white pattern.

Establishes adequate drive water pressure by adjusting 2Cll-F003, Drive Pressure Control Valve.

May start a second CRD pump to establish adequate drive water pressure.

Selects a rod.

Drives selected rod to at least the 02 position using the Emergency In Notch Override switch or Rod Movement Switch.

) i I

I i

I SS

Orders BOP to inhibit ADS.

Directs BOP or SSS to have MSIV closure on low RPV level overridden.

Directs BOP to override 2P41-F316 isolation.

SBLC injection is an option for the SS to consider, but is not required for low power ATWS conditions.

f

)

A~endixO Required Operator Actions Form ES-O-2

)

Op-Test No.: 2009-301 Scenario No.: 4*01 Event No.: 7A Page 29 of34 Event

Description:

RFPT Trip / ATWS actions / HPCI Failure to Start Time Position Applicant's Actions or Behavior BOP

Inhibits ADS by placing both Keylock inhibit switches to "Inhibit."

If directed to do so by the SS, calls the SSS to have MSN closure override performed.

Places override switches for 2P41-F316 in the override switches to "Overide."

SS

As a conservative action, the SS may direct injection of boron using SBLC.

)

ATC

If directed by the SS to inject SBLC:

0 Places the SBLC switch to either position "A" or "B".

Confirm the following 0 Squib Vlv Ready indicating lights extinguish.

0 SBLC Loss of Continuity to Squib Valve annunciator alarms 0 Selected SBLC pump has started 0 2G31-F004, Rx Water Cleanup Vlv is closed 0 SBLC tank level is decreasing 0 SBLC discharge pressure> reactor pressure 0 Reactor power is decreasing I

AQQendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 7A Page 30 of34 Event

Description:

RFPT Trip I ATWS actions I HPCI Failure to Start Time Position Applicant's Actions or Behavior SS

If water level is above -60" and power above 5% when the SS addresses CP-3, he will Direct the BOP to lower water level to below -

60" using 31EO-EOP-113-2.

BOP

Reduces injection to lower RWL to < -60 inches using

\

31EO-EOP-100-2:

I

Recognizes HPCI failure to start, and informs SS .

i

Lowers Feedwater flow as necessary to achieve a lowering RWL trend.

SS

When RPV level is below -60 inches, Directs the BOP operator to control RPV level within a level band. Any band between -60 inches and -185 inches is acceptable.

(Typically -60" to -100" to maintain RPV level above -101")

If RWL is subsequently allowed to increase to >-60 inches and Rx power is >5%, the override will be re-addressed to once again, lower level to < -60.

I

AQQendix 0 Required Operator Actions Form ES-O-2

',h Ii Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 7B Page 31 of 34 Event

Description:

RCIC Trip Time I Position I Applicant's Actions or Behavior Simulator operator:

AFTER the MSIV low level closure HAS BEEN BYPASSED:

THEN

Insert mf2E5L110, "RC~IC Turbine Trip" (RB-8)

BOP

Use Feedwater system to control RPV water level in the assigned band (Critical Task - Maintain RWL above -185 inches)

Verify/Place RFPT controllers in Manual

Raise RFPT speed to increase pressure to above RPV pressure

Do one of the following to provide injection to the RPV:

0 Verify/Place the Startup Level Control Valve in Manual 0 Open/Verify open 2N21-F125 0 Throttle open 2N21-Fll1 (SULCV)

OR 0 Throttle open 2N21-FllO I

I i

SS IF the following conditions exist: !

Reactor power >5%. i

RWL above TAF. I

Torus temperature is in the safe region of the BUT curve.

SRVs are open. I I

Then Addresses the override located at coordinate C2 on EOP Flowchart CP-3 to Terminate and Prevent injection to the RPV.

AQQendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 7B Page 32 of34 Event

Description:

RCIC Trip Time Position Applicant's Actions or Behavior SS

Determines that RPV level can be maintained above -185 inches.

Arrives at "Wait Until" (CP-3 at F-7) for Hot Shutdown Boron Weight.

\

i BOP

As time allows, and when generator load goes below 80 MWe, the crew performs TC-l to trip the Main Turbine.

Manually Trip the Turbine.

Confirm TSV's, TCV's, and CIV's have properly closed.

Confirm the generator PCBs and exciter field breaker tripped.

Confirm the 4160 VAC station service busses have transferred to their alternate supply.

Confirm/Place TOM in auto.

0 Start TO Oil Pump 0 Motor Suction Pump 0 Lift Pumps

Close the RSSV's (2NII-F004A and F004B).

~~ ,~. ~~ ~

AQQendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 7B Page 33 of34 Event

Description:

RCIC Trip II Time ***1 Position J Applicant's Actions or Behavior AFTER the following conditions EXIST:

Control Rods are Inserting.

RWL is being maintained in the established level band.

The SCRAM has beerLTeset.

The SDV Vent & Drains are open.

THEN, with Chief Examiner's permission:

Delete MF2Cll-211 and

Enter mf60313289, Scram ][)ischarge Volume High Level Trip alarm OFF, and mf60313307, Scram DIscharge Volume Not Drained Alarm OFF (RB-9)

ATC

SCRAMS Reactor

All rods insert

Notifies SS that all rods are full in .

SS

Transitions to RC - Point B

Orders Operator to slowly increase RWL to 3 to 50 inches.

l............-_______

AQQendix D Required Operator Actions Form ES-D-2

\

Op-Test No.: 2009-301 Scenario No.: 4-01 Event No.: 7B Page 34 of34 Event

Description:

RCIC Trip Time Position Applicant's Actions or Behavior Simulator Operator:

With Chief Examiner's permission Scenario will stop here.

)

Page 1 of32 Scenario Summary DRAIlT

)Facility: E. I Hatch Scenario No.: 4-02 Op-Test No.: 2009-301 Initiating Conditions: Unit 2 is at 60% performing a reactor start-up. "2A" Core Spray pump is tagged out.

Turnover The HPCI surveillance is to be performed in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

RHR "2B" is in Torus Cooling in preparation for the HPCI surveillance.

Lower Torus level to 147.5 inches for HPCI Surveillance.

Summary:

Event 1: Normal; The BOP operator will lower Torus level.

Event 2: Instrument; The cooling water controller for the "2B" RFPT will fail. This results in high temperatures on the RFPT oil system and RFPT bearings. The BOP operator will place the controller in manual and adjust cooling water flow to reduce the temperatures. If manual control is not taken within 3 minutes, RFPT vibrations will occur and continue to increase until either the temperature is reduced or 6 mils is reached. RFPT trip is required at 6 mils.

Event 3: ComponentlTS; The "2B" RHRSW pump trips. The team is directed by an ARP, to place the "2D" RHRSW in service lAW the RHR System procedure.

Event 4: Reactivity/Component; A Recirculation Pump ASD Cell will auto bypass on the "2A" Recirc pump. Tbis will result in a flow and power reduction. The ASD Cell Bypass and Recirc flow mismatch will be addressed by annunciator response procedures and an abnormal

) procedure. The SS will address TS for Recirc flow mismatch.

Event 5: Reactivity; The plant will be operating in the Immediate Exit Region of the Power-to-Flow map (Event 4). The team will exit the region of the P/F map by either inserting control rods or increasing Recirc Pump speed.

Event 6: ComponentlTS; The RCIC turbine receives a inadvertent trip while in standby due to accidental bumping of the trip lever. The SS addresses TS for RCIC being inoperable. RCIC will be returned to standby by the BOP operator.

Event 7: Component; 600VAC Bus 2A is inadvertently tripped. A report will inform the team that the cause of the trip is known and the bus may be re-energized. The BOP operator will restore the bus lAW abnormal and system operating procedures.

Event SA: Major; A loss of all high pressure injection/reactor scram occurs as a result of the following:

"2D" 4l60VAC bus trips, "2C" Condensate Booster pump trips, HPCI cannot be started, "B" Feedwater line breaks inside the Drywell (LOCA and a loss of an injection line for RCIC) and both CRD pumps trip.

Event SB: Component; ECCS LOCA logic fails so operators are required to manually start ECCS equipment (RHR, CS, EDGs) (Critical Task). Operators will align RHR to spray the Suppression Chamber. Containment sprays will be secured prior to reaching TAF.

Event SC: Major/Component; Reactor water level will decrease to TAF, requiring the team to Emergency Depressurize the RPV (Critical Taslk). Only 3 ADS valves will open. The team will manually open 4 additional SRVs. Operators must manually open the RHR and CS discharge valves after reactor pressure decreases below the 500 psig permissive signal (Critical Task).

) Reactor pressure will decrease to below the shut-off head of the low pressure ECCS pumps and RWL will be restored to above TAF using all available injection systems. After RWL is determined to be above TAF, injection valves will be throttled to control injection and raise RWL to the normal EOP band.

Page 20f32 AppendixD Critical Task List Form ES-D-1 DRAFT Facility: E. I Hatch Scenario No.: 4-02 Op-Test No.: 2009-301 Critical Tasks

Start ECCS pumps prior to opening ADS valves (Event 8B)

Open ADS valves before RWL reaches -185 inches (Event 8C)

Begin opening ECCS discharge valves after reactor pressure decreases below the 500 psig permissive and before reactor pressure decreases to below ECCS pump shutoff head. (Event 8C)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 8 1. RFPT Temperature Controller failure.

2. RHRSW pump trip.

3. Recirc ASD Cell Bypass.

4. RCIC trip.

5. Loss of "2A" 600 VAC bus.

6. LOCA Logic failure.

7. Failure of ADS valves to open.

2. Malfunctions After 1-2 2 1. LOCA Logic failure.

EOPEntry 2. Failure of ADS valves to open.

3. Abnormal Events 2-4 2 1. Recirc ASD Cell Bypass.

2. Loss of "2A" 600 V AC bus.

4. Major Transients 1-2 2 1. Scram, Loss of high pressure injection.

2. Emergency Depressurize at TAF.

5. EOPs entered, 1-2 1 1. RC requiring substantive actions

6. EOPs contingencies 0-2 2 1. CP-l Alternate RPV Level Control requiring substantive 2. CP-l Emergency Depressurization actions

7. Critical Tasks 2-3 3 1. Start ECCS Pumps

2. Open SRVs to Emergency Depressurize.

3. Open ECCS Discharge Valves

Page 3 of32 AppendixD Scenario Outline Form ES-D-l DRA~FT Facility: E. I Hatch Scenario No.: 4-02 Op-Test No.: 2009-301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at 100% power. Core Spray pump "2A" is tagged out for maintenance due to the supply breaker tripping during a Surveillance test.

Turnover: The HPCI surveillance is to be performed in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . RHR "2B" is in Torus Cooling in preparation for the HPCI surveillance. Lower Torus level to 147.5 inches for HPCI Surveillance Event Malf. No. Event Event No. Type* Description 1 N (BOP) Lower Torus level to 147.5 inches using RHR Loop "2B."

2 mtN2L88B I (ATC) Feedwater pump 2B cooling water controller failure.

TC repair and return to auto.

)1 3 I

mtEIL120B Irs (SRO) "2B" RHRSW pump trips, team places the other RHRSW pump in C (BOP) service.

4 mfB3L135A R (ATC) A Reactor Recirc ASD cell is auto bypassed.

r (ATC) "2A" Recirc speed decreases resulting in a flow mismatch.

5 R (ATC) Inseli control rods or raise Reactor Recirc pump speed to return to safe area of Power to flow map.

6 mtE5L61 Irs (SRO) RCIC Trip & Throttle valve tripped locally, must be reset and re-r (BOP) latched.

7 mfR23_174 r (BOP) Loss of 600 V AC Bus 2A. Main Transformer temperatures increase.

Restoration of power to the bus.

8A mtR22_181 M (All) 4160 VAC "D" trips causing a loss of 2 Condensate and Condensate mfB2L229B booster pumps, then Feedwater line B breaks, causing a LOCA, HPCI mtE4LI04 trips on start and will not be returned to service.

diCIIB-S4A diCIIB-S4B mfCIIA_30A mfCllB 30B 8B mtEIL202B C (BOP) ECCS fails to start on LOCA signal.

mtE21 202A 8C mfB2L129A M (ALL) Emergency depressurization is required due to low RWL

) mfB2L129C C (ATC) During emergency depress ADS valves A, C, E, and H don't operate.

mfB2L129E mfB21 129H

(N)ormal, (R )eacti vi ty, (I)nstrument, (C)omponent, (M)ajor

A~endixO Required Operator Actions Form ES-O-2

)

Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 1 Page 4 of32 Event

Description:

Lower Torus level to 147.5 inches using RHR Loop "2B."

Time Position Applicant's Actions or Behavior SS

Directs the operator to lower torus water level to 147.5" using "B" loop ofRHR.

BOP

Enters 34S0-E11-01O-2, Section 7.4.5, Residual Heat Removal System.

Confirms Radwaste is capable of receiving the water to be transferred.

Confirms the RHR discharge water temperature is < 200°F, 2T47-I R627, point 3.

Opens 2Ell-F049, RHR to Radwaste Valve.

Monitors torus level on 2T48-R607A (B), 2Hll-P602 (2Hll-P654).

Throttles OPEN, 2Ell-F040, RHR to Radwaste Valve.

BOP

Monitors torus water level and once level has been lowered to approximately 147.5" secures the flow path.

Closes 2Ell-F040, RHR to Radwaste Valve.

Closes 2Ell-F049, RHR to Radwaste Valve.

Reports to the SS that torus water level has been lowered to 147.5"

A~endixD Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 2 Page 50f32 Event

Description:

Feedwater pump 2B cooling water controller failure.

Time Position Applicant's Actions or Behavior Simulator Operator At Chief Examiner's direction:

While the BOP operator is lowering torus water level, press (RR-I) to activate:

0 mfN21_88B, Feedwater Pump Lube Oil Cooling System Failure ALL The following alarms will annunciate:

34AR-650-315-2, "RFPT 2B Brg Oil Temp High"

34AR-650-112-2, "RFP/COND BRG Metal Temp High"

34AR-650-333-2, "RFPT 2B BRG Temp High"

)

ATC Note: the operator may immediately place the controller in manual in accordance with 31GO-OPS-021-0, Manipulation and Control of Equipment, responding to a failed controller.

Addresses the high temp annunciator, pulling the ARP

At panel2HII-P655, check all temperature indicators on 2N32-R616 to determine actual oil temperatures.

Confirm that RFPT 2B Oil Temp controller, 2P41-R606, on panel 2HI1-P650 is adjusted for 110 to 130°F ATC

Recognizes the automatic function of the controller has failed, closing the cooling water valve.

I

Places the controller in manual, depresses the open/increase pushbutton, opening the valve. Oil temperatures begin decreasing and the alarm extinguishes.

Al2I2endix D Required Operator Actions Form ES-D-2

\

Op*TestNo.: 2009-301 Scenario No.: 4*02 Event No.: 2 Page 6 of32 Event

Description:

Feedwater pump 2B cooling water controller failure.

Time Position Applicant's Actions or Behavior All

If this condition exists for over 3 minutes alarm 34AR-650-332-2, "RFPT 2B EXCESSIVE VIBRATION," will illuminate.

BOP

Confirm excessive vibration by observing 2N32-R600, Turbine Vibration and Eccentricity Recorder, points 13 and 14, on panel2Hll-P650 (DEPENDENT) OR 2H21-P536, TMR Workstation Mark V Control PaneL

IF the RFPT vibration INCREASES to 6 mils, TRIP 2B RFPT.

~

SS

Notifies maintenance of the RFPT temperature controller problem.

Simulator Operator After the team has taken manual control of the temperature controller AND has notified Maintenance of the problem:

THEN Delete malfunction mfN2L88B AND

Call the control room and report the following:

0 "Time compression is being used; the problem with 2P41-R606 was a wiring harness on the temperature sensor. The automatic function of the temperature controller has been repaired anell may be returned to service."

AQQendix 0 Required Operator Actions Form ES-O-2

- --- ---------.- .. -.-----~--------------- ------ -----------------------------_ .. _ - - - - - - - - - _ .. _--------------------- - --- - ---

" Op-Test No.: 2009-301 Scenario No.: - 4-02 Event No.:

2 Page 7 of32 Event

Description:

Feedwater pump 2B cooling water controller failure.

Time Position Applicant's Actions or Behavior SS

Directs the ATC to return 2P41-R606 to automatic operation.

ATC

Depresses the automatic pushbutton on controller 2P41-R606.

Verifies the controller responds correctly in automatic.

Notifies the SS the Lube Oil Temperature Controller has been returned I to automatic. !

)

A~endixO Required Operator Actions Form ES-O-2

\

I Op*Test No.: 2009-301 Scenario No.: 4*02 Event No.: 3 Page 8 of32 Event

Description:

"2B" RHRSW pump trips, "2D" RHRSW pump started Time Position Applicant's Actions or Behavior Simulator Operator At Chief Examiner's direction, press (RB*2) to activate:

mfEll_115B, Trip of "2B" RHRSW pump C (ALL) Diagnose loss of "2B" RHRSW SS (TS)

Direct BOP operator to respond to annunciators.

LCOIRAS for RHRSW pump (TS 3.7.l.A: 30 days to restore).

LCOIRAS for RHR Suppression Pool Cooling (TS3.6.2.3: 7 days to restore).

LCO/RAS for RHR Suppression Pool Sprays (TS 3.6.2.4: 7 days to

) restore).

BOP

Respond to the following annunciators:

0 RHRSW Pump B Trip, 601-226.

0 RHR HX B DiffPress Low, 601-215 (comes in and clears).

I

Al4.!2endix 0 Required Operator Actions Form ES-O-2

)) Op*Test No.: 2009-301 Scenario No.: 4*02 Event No.: 3 Page 9 of32 Event

Description:

"2B" RHRSW pump trips, "2D" RHRSW pump started I Time Position Applicant's Actions or Behavior C (BOP)

Respond to ARP:

0 RHR SRV WTR Pump B Trip

Start "2D" RHRSW pump 0 Depress the RHRSW Lube Valve pushbutton, allow pump prelubing to occur for 1 minute.

0 Place the RHRSW pressure interlock switch for 2Ell-F068B in the "Override" position.

0 Throttle 2Ell-F068B to 45% open.

0 Confirm 2E11-F068B red light is illuminated 0 Confirm RHR HX Diff Press Low annunciator illuminates 0 Start the "2B" RHRSW pump 0 Place the RHRSW pressure interlock switch for 2Ell-F068B in I

the "NORMAL" position.

0 Throttle 2E11-F068A open (max flow 4,400 gpm, maintaining RHRSW pressure <450 psig

A.tmendix D Required Operator Actions Form ES-D-2

)11 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 4 Page 10 of32 Event

Description:

Recirc ASD cell is auto-bypassed, reduced Recirc pump speed.

Time Position I Applicant's Actions or Behavior Simulator Operator At Chief Examiner's direction, press (RB-3) to activate:

mfB31_135A, Recirc ASD A Cell Bypass SSTS

Direct ATC to respond to Recirc Loop Out Of Service Annunciator

Direct maintenance be contacted to determine cause of Recirc speed decrease

TS LCO/RAS Recirculating Loops Operating (TS 3.4.1 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to satisfy the LCO).

)

C (ATC)

Respond to Recirc Loop Out Of Service Annunciator R (ATC)

Diagnose Recirc pump speed mismatch

Enter 34AB-B31-001-2, "Reactor Recirculation Pump(s) Trip, Recirc Loops Mismatch, OR ASD Cell Bypass 0 Confirm the "SPD HLD RESET' pushbutton is illuminated Note: If the SS directs rods to be inserted to exit the Immediate Exit Region, go to Event 5, otherwise continue here:

0 Enter section III of 34AB-B31-00 1-2

If Recirc speed mismatch >35%, inform SS of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limit to balance Recirc Pump flows 0 When directed by SS with STA guidance:

Depress the respective SPD HLD RESET pushbutton indicating lamp

Increase speed of the "2A" Recirc Pump per 34S0-B31-001-2, Reactor Recirc System"

Aru4endix 0 Required Operator Actions Form ES-O-2

) Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 4 Page 11 of32 Event

Description:

Recirc ASD cell is auto-bypassed, reduced Recirc pump speed.

Time Position Applicant's Actions or Behavior STA

Recommend increasing core flow to exit the immediate exit region and match Recirc Pump flow.

)

Simulator Operator At Chief Examiner's direction:

Call the Control Room as I&C with the following message:

0 The "2A" Recirculation Pump ASD has automatically bypassed a cell, conditions at the ASD are normal for this condition.

AQQendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 5 Page 12 of32 Event

Description:

Insert control rods to return to safe area of Power to flow map.

II Time 1 Position I Applicant's Actions or Behavior SS

Within 15 minutes of entering the Immediate Exit Region of the Power to Flow map, directs operator to exit the region by inserting control rods.

Has a control rod movement brief per 34GO-OPS-065-0 Simulator Operator If the Team calls for the STA or Reactor Engineering, for rod movement recommendati ons:

Respond as follows:

0 "I am 10 minutes away and to use the Reactivity Manipulations

) Turnover."

ATC

Inserts control rods per 34GO-OPS-065-0, starting with control rod GROUP 54.

During rod insertion, rod steps will be performed in reverse sequential order, starting at the highest numbered step. (** rod steps are not required to be performed sequentially, but must be positioned to their RWM insert limit prior to inserting lower numbered groups).

Selects Rod

Places Control Rod movement switch to the IN position

Verifies Rod moves using Rod display information and Rx and Generator power decreasing.

ATC

If required, adjust 2Cll-F003 to get 220 - 280psid drive water dp.

AQQendix 0 Required Operator Actions Form ES-O-2

)

Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 5 Page 13 of32 Event

Description:

Insert control rods to return to safe area of Power to flow map.

Time Position Applicant's Actions or Behavior ATe Note: RBM Downscale alarm may alarm during this movement due to the significant rod worth of these rods. It is allowed to flag the RBM Downscale and Rod Block alarm.

Releases Rod movement switch so that the control rod stops 1 position before the insert limit unless the insert limit is 00.

Initials Rod movement Sheet.

Verifier, if available, Initials Rod movement sheet.

Notifies the SS when they are out of the region of potential instabilities.

Note: Advise the STA to recommend inserting the current rod group to its insert limit.

)I SS

Directs the operator to insert the rods to the insert limit after consulting with the STA.

A~endix D Required Operator Actions Form ES-D-2

)

/11 Op*Test No.: 2009-301 Scenario No.: 4*02 Event No.: 6 Page 14 of32 Event

Description:

RCIC Turbine Trip and Throttle Valve tripped locally Time Position I Applicant's Actions or Behavior 1 Simulator Operator

At Chief Examiner's direction, press (RB-4) to activate:

0 mfE51_61, RCTe Overspeed Trip ALL

Annunciator 34AR-602-301-2, "RCIC TURBINE TRIP" is received.

BOP

Confirms RCIC Turbine has tripped per the following indications:-

2E51-F524, Trip & Throttle Valve, indicates closed.

2E51-F013, Pump Discharge Valve, indicates closed.

2E51-F019, Min Flow Valve, indicates closed.

SS

Notifies the SSS to have the RCIC trip investigated.

AQRendix 0 Required Operator Actions Form ES-O-2

- - - - - - - - - - - - - - - - - - - - - -.. -------------------~--- --------- ------ ---

)

Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 6 Page 15 of32

~-

Event

Description:

RCIC Turbine Trip and Throttle Valve tripped locally Time Position Applicant's Actions or Behavior SS

Addresses tech specs 3.5.3.A for RCIC being inop.

Determines a one hour RAS exist to verify by administrative means that HPCI is operable.

Determines a 14 day RAS exist to restore RCIC to operable status .

Simulator Operator After TSs have been addressedl:

As a SO in training, caD the Control Room and report:

0 "While I was in the RCIC room I accidentally bumped a lever on the RCIC pedestal. It changed position along with a long rod attached to the lever."

I SS

Notifies the SSS to have the RCIC mechanical overspeed reset.

Directs the operator to return RCIC to standby. May use generic guidance of 31GO-OPS-021-0 to open the trip and throttle valve.

)

A~endix 0 Required Operator Actions Form ES-O-2 I Op*TestNo.: 2009-301 Scenario No.: 4*02 Event No.: 6 Page 16 of32 Event

Description:

RCIC Turbine Trip and Throttle Valve tripped locally Time Position Applicant's Actions or Behavior Simulator Operator AFTER the operator has identified the problem as a trip AND RCIC is directed to be reset locally:

Delete malfunction mfE5L61 THEN

Call the control room and report:

0 "The RCIC mechanical over-speed mechanism has been reset."

I BOP

Enters 34S0-E51-001-2, Reactor Core Isolation Cooling (RCIC)

System section for resetting the mechanical overspeed.

At pane12Hll-P602, takes 2E51-F524, Turbine Trip & Throttle Valve control switch to close and holds until valve operator is fully closed.

At pane12H11-P602, takes 2E51-F524, Turbine Trip & Throttle Valve (T&T), control switch to open and holds until the valve is operator is fully open, verifying the valve indication reflects the valve is opening along with the valve operator.

Verifies "RCIC Turbine Trip" annunciator clears i

A~endix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 6 Page 17 of32 Event

Description:

RCIC Turbine Trip and Throttle Valve tripped locally Time Position Applicant's Actions or Behavior BOP

Notifies the SS that RCIC's Trip & Throttle valve is open And RCIC has been returned to the standby condition.

May confirm the remainder of the standby lineup but the only required manipulation is to re-Iatch and open the T&T valve.

I SS

Determines the RASs associated with RCIC no longer exist

AQQendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 7 Page 18 of 32 Event

Description:

Loss and Restoration of Power to 600VAC Bus 2A II Time I Position I Applicant's Actions or Behavior Simulator Operator At Chief Examiner's direction., press (RB-5) to activate::

Activate mtR23_174, 600 V AC Bus 2A Fault.

Simulator Operator After the 600 V AC bus supply breaker trips:

)

Delete malfunction mfR23_174, 600 VAC Bus 2A Fault.

All

Diagnose loss of "2A" 600VAC bus SS

Direct BOP operator to respond to alarms associated with the loss of 600V Bus 2A:

0 600V Bus 2A Undervoltage alann (P651) 0 Air Cmpsr 2C Tripped/SD (P700) 0 Standby EHC Pump Running (P650) 0 Offgas Panel alanns (P600) 0 Main Transformer Misc Alarm 0 STA SVC Supply Breaker Trip

Direct BOP operator to enter 34AB-R23-002-2, "Loss of 600V Bus 2A, 2AA, 2BB, or 2B"

Direct that maintenance investigate problem with 600VAC Bus 2A

~----- .... -.--- ------ _.. -------- -----------

A~endixD Required Operator Actions Form ES-D-2

\

Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 7 Page 19 of32 Event

Description:

Loss and Restoration of Power to 600VAC Bus 2A Time Position Applicant1s Actions or Behavior BOP

Respond to the following annunciators:

0 600V Bus 2A Undervoltage alarm (P651) 0 Air Cmpsr 2C TrippediSD (P700) 0 Standby EHC Pump Running (P650) 0 Offgas Panel alarms (P600) 0 Main Transformer Misc Alarm (P651) 0 STA SVC Supply Breaker Trip (P651)

Enter 34AB-R23-002-2, "Loss of 600V Bus 2A, 2AA, 2BB, or 2B."

~

0 Call Switchyard maintenance to monitor Main Transformer temperatures.

0 Address Main Transformer load limitations in 34AR-651-113-2, Main Xfmr Winding Temp High (70% load limit with half the fans de-energized) 0 Enter 34AB-R24-002-2, Loss of Non-Essential AC Distribution 0 Check position of Normal and Alternate supply breakers to "2A" 600VAC Bus and determine the Normal Supply breaker has tripped (Green light and Amber light illuminated)

A~endix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 7 Page 20 of32 Event

Description:

Loss and Restoration of Power to 600VAC Bus 2A Time Position Applicant's Actions or Behavior Simulator Operator At Chief Examiner's direction:

After the team has called for Maintenance support;

Call the control room as. Electrical Maintenance and report:

0 "The nonnal supply breaker to 2R23-S00 1 was tripped accidentally, and there is no problem with the bus. No lockout relays have tripped.'"

SS

Direct the BOP operator to energize "2A" 600 VAC Bus

)I C (BOP)

Perform Enter 34AB-R23-002-2, "Loss of 600V Bus 2A, 2AA, 2BB, or 2B" actions to prepare for energizing the bus.

Strip all loads from "2A" 600VAC Bus 0 Supply to 2R24-S035 Turb Bldg MCC 2D-B 0 Supply to 2R24-S036 WGTB MCC 0 FDR to Bldg Xfmr

Place pump switches to "PTL" or "OFF" 0 "2A" Stator Cooling Water pump 0 "2A" EHC Pump

AImendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 7 Page 21 of32 Event

Description:

Loss and Restoration of Power to 600VAC Bus 2A Time Position Applicant's Actions or Behavior C (BOP)

Re-Energize "2A" 600 VAC Bus IAW with 34S0-R23-001-2, "600V / 480V AC System 0 Confirm that power is available from 4160V Bus 2C as indicated by the potential lights.

0 Confirm that 4160V Bus 2C voltage is normal.

0 On paneI2Hll-P676, confirm that 87S2AX (87S2BX), Sta Serv Transf 2A (2B) Diff Aux Relay is reset.

0 TAKE ACB 135632, Alt Supply To 2R23-S00 1, AND ACB 135634, Norm Supply to 2R23-S001, control switches to TRIP AND confirm that the green flags are visible.

0 CLOSE ACB 135436, Feeder To SST 2A.

0 Strip all loads off 600V AC Bus 2A by tripping all feeder

~ breakers.

0 CLOSE ACB 135634, Norm Supply To 2R23-S001 (2R23-S002),

to energize the bus AND confirm that 600V AC Bus 2A voltage is normal.

Restore all "2A" 600 VAC Bus feeder breakers 0 Supply to 2R24-S035 Turb Bldg MCC 2D-B 0 Supply to 2R24-S036 WGTB MCC 0 FDR to Bldg Xfmr NOTE: All parts of this section are not required to be completed before Event 8A is initiated (Chief Examiners discretion). The intent of this event is I for the BOP operator to demonstrate to properly strip and energize the bus.

A~endixD Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: SA Page 22 of32 Event

Description:

Loss of Condensate System and Feedwater line Break:.

Time Position Applicant's Actions or Behavior Simulator Operator With Chief Examiners Permission, press (RB-6) to activate:

mfR22_181, 4KV Bus 2D Fault

mfN21_80C, Condensate Booster Pump C Trip

mfB21_229B, FW LINE "B" BREAK INSIDE CONTAINMENT

mfE4L104, HPCI Turbine Trip

mfC1 L30A, CRD A Pump Trip

mfC1L30B, CRD B Pump Trip ALL

Recognizes a loss of "D" 4160 VAC station service electrical bus and a trip of 2C Condensate Booster Pump has occurred resulting in a loss of Condensate and Condensate Booster pumps A, B, and C.

)

An automatic scram due to decreasing reactor water level or high drywell pressure will occur.

Identifies drywell pressure is rapidly increasing.

SS

Assigns the ATC to perform RC-l.

Assigns the BOP operator to perform RC-2 and RC-3.

Enters the RC EOP flow chart 31EO-EOP-01O-2

As time allows,

Enters 31EO-EOP-012-2, PC-l flow chart.

As time allows:

o Directs an operator to perform TC-1 o Notifies maintenance to repair 4160 VAC D and CBP 2C.

o Dispatches personnel to the EDGs to check for proper operation.

o Directs 2P41-F316A-D to be opened

AQQendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: SA Page 23 of32 Event

Description:

Loss of Condensate System and Feedwater line Break.

Time Position Applicant's Actions or Behavior ATC

Performs RC-1 consisting of:

0 Inserts a manual scram.

0 Places the mode switch to shutdown.

0 Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

0 Notifies SS of rod position check.

0 Places SDV isolation valve switch to "isolate" & confirms closed.

0 If not tripped, places the Recirc pumps at minimum speed.

0 Inserts SRMs and IRMs.

0 Shifts recorders to read IRMS, when required.

0 Ranges IRMS to bring reading on scale.

0 Notifies the SS when the above actions are complete.

I

AQQendix 0 Required Operator Actions Form ES-O-2

\

Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: SA Page 24 of32 Event

Description:

Loss of Condensate System and Feedwater line Break.

Time Position Applicant's Actions or Behavior BOP

Performs RC-2 actions consisting of:

Confirms proper Level Control response:

0 Checks ECCS Injection Systems and secure as necessary.

0 Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.

0 IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.

)

BOP

When feed flow is less than the capacity of the SID level control valve

(::::: 1.5 mlbm/hr), then:

0 Opens 2N21-FI25.

0 Places 2C32-R619, FW SID level control valve controller, in Auto, set at approximately 9 inches.

0 Closes2N21-Fll O.

0 Secures one RFPT if necessary.

0 Recognizes "B" Feedwater line break 0 Places 2N21-F006B, Feedwater line isolation valve to close.

0 Notifies SS of Feedwater line break.

I I

i I

AQ.Qendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: SA Page 25 of32 Event

Description:

Loss of Condensate System and Feedwater line Break.

I Time Position Applicant's Actions or Behavior BOP

Performs RC-3 consisting of:

0 Monitor RPV pressure.

0 Confirm proper operation of pressure control system (TBV, LLS, etc.).

0 If necessary, allow RPV pressure to exceed 1074 psig then cycle any SRV to initiate LLS.

0 Maintain RPV pressure between 1074 and 800 psig.

0 Notify SS of pressure control system operation.

)

A~endixD Required Operator Actions Form ES-D-2 JI Op*Test No.: 2009*301 Scenario No.: 4-02 Event No.: 8B Page 26 of32 I Event

Description:

ECCS fails to start on LOCA signal.

II Time - IPosition--1 Applicant's Actions or Behavior BOP

Identifies the ECCS pumps have not started when RPV water level decreased below -101" or with DIW pressure >1.85psig.

Places the control switch for RHR "A" to start.

Places the control switch for RHR "C" to start.

(Critical task - start ECCS pumps prior to opening ADS valves).

BOP

Places the control switch for RHR "B" to start.

Places the control switch for RHR "D" to start.

Places the control switch for Core Spray "B" to start NOTE: If DIW conditions are present for a long enough period of time (dependent on closure of2N2l-F006B) Torus and DIW sprays will be initiated.

,~

SS

Orders initiation of Suppression Pool Sprays

Al2J2endix 0 Required Operator Actions Form ES-O-2 Op*Test No.: 2009-301 Scenario No.: 4*02 Event No.: 8B Page 27 of32 Event

Description:

ECCS fails to start on LOCA signal.

Time Position Applicant's Actions or Behavior ATC

Initiates Suppression Pool Sprays by:

Places Containment Spray Valve Control switch on 2Hll-P601 in the Manual position.(required due to the LOCA signal)

Verifies the RHR pumps 2A(B) and 2C(D) are operating.

Opens 2Ell-F028A(B).

Throttles open 2Ell-F027A(B).

Monitors Suppression chamber pressure.

I I

I

~ i SS Note: When 2N21-F006B is closed containment parameters will change quickly and the parameters to spray the drywell may only exist for a short period of time.

When suppression chamber pressure exceeds 11 psig and If it remains above 11 psig for sufficient time to respond to condition:

Evaluates the drywell spray initiation limit graph, determining whether plant parameters are currently in the safe region.

Directs the Recirc pumps be secured.

Directs the drywell cooling fans be secured.

Once these conditions are checked and actions completed, the SS directs the ATC operator to Spray the drywell.

-~- ---- ----.-~-------------

A~endixD Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4*02 Event No.: 8B Page 28 of32 Event

Description:

ECCS fails to start on LOCA signal.

Time Position Applicant's Actions or Behavior ATC

Initiates drywell sprays in the "A" or "B" loop of RHR by:

Opens 2Ell-F021A(B) on 2Hll-P601 paneL

Throttles open 2E II-FO 16A(B) to establish at least 5000 gpm to the drywelL I

SS

Directs that drywell and suppression pool sprays be secured before the respective area decreases below 0 psi of if reactor water level decreases to TAP.

ATC

Secure DIW sprays prior to DIW pressure <Opsig or if RWL decreases to TAF.

Secure Torus sprays prior to <Opsig.

Secure Torus cooling and Torus sprays ifRWL decreases to TAP.

A~endixO Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 8C Page 29 of32 Event

Description:

Failure of ADS valves to operate.

Time Position Applicant's Actions or Behavior BOP

Monitors RPV water level as it trends down.

Informs the SS of water level reaching -155."

SS

PerCP-l o Orders emergency depressurization once water level decreases below

-155" and prior to -185."

o Orders all available table 8 systems injecting until water level raises above -155."

~

ATC

Opens 7 ADS valves, (Critical Task- Open ADS valves before RWL reaches -185 inches)

ATC

Places switches for the ADS valves to OPEN.

Recognizes valves A, C, E, and H, do not receive an amber light.

Notifies the SS

,-- SS

DIRECTs the ATC to open 4 LLS valves.

AQQendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 8C Page 30 of32 Event

Description:

Failure of ADS valves to operate.

Time Position Applicant's Actions or Behavior ATC

Opens 2B21-F013B, D, F, and G.

BOP

Verifies I Opens RHR and Core Spray injection valves open once the Reactor Pressure Low 500 psig alarm illuminates. (Critical Task-Begin opening ECCS discharge valves after reactor pressure decreases below the 500 psig perrnissive and before reactor pressure decreases to

) below ECCS pump shutoff head.)

Verifies injection from Core Spray and RHR pumps begins as soon as reactor pressure decreases below the shut off head of the pumps.

When water level is restored above Top OF Active Fuel throttles flow for CIS and RHR per the SS directions.

Note: When drywell sprays are secured, drywell temperatures will increase.

Depending on how long DW sprays have been secured and the temperature inside the drywell when emergency depressurization occurs, reactor water level instruments may experience flashing.

~--.--- -- -------------_ .. _------------

A~endixO Required Operator Actions Form ES-O-2

\

I Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 8C Page 31 of32 Event

Description:

Failure of ADS valves to operate.

Time Position Applicant's Actions or Behavior BOP

Observes fuel zone water level instruments and the normal 0" to 60" water level instruments for flashing.

If flashing occurs notifies the SS.

Note the following steps are contingent on whether the water level instruments experience flashing.

~ SS

If flashing occurs then transitions to CP-2, 31EO-EOP-016-2 point "I" flooding for non-ATWS.

Directs the operator to close:

MSIVs

RPV head vents

MSLdrains

RCIC isolation valves

HPCI isolation valves.

Directs the operator to raise injection to obtain 50 psid reactor pressure above torus pressure.

-~~ . ----.-.-.-.--.-.--.-.~-

Al2I2endix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-02 Event No.: 8C Page 32 of32 Event

Description:

Failure of ADS valves to operate.

Time Position Applicant's Actions or Behavior ATC

Verifies the following are closed:

MSIVs

RPV head vents

MSLdrains

RCIC isolation valves

HPCI isolation valves.

SS

Sets a pressure band for the operator to achieve, must be greater than 50 psid above torus pressure.

)I SS Starts the flooding interval time limit.

With Chief Examiners Permission:

The scenario should be terminated when the crew has Emergency depressurized the reactor AND:

0 Re-established adequate core cooling with water level above T AF OR 0 Reactor pressure more than 50 psid above torus pressure.

/.~

Page lof32 Scenario Summary DRAFT

) Facility: E. I Hatch Scenario No.: 4-03 Op-Test No.: 2009-301 Initiating Conditions: Unit 2 is at 1% power, performinKa reactor stat1:-11P.

Turnover Raise pressure set to 420 psig. Withdraw Control Rods to until one Main Turbine Bypass Valve 80% open in preparation for the start of "2A" RFPT.

Summary:

Event 1: Normal evolution; RPV pressure will be raised to 420 psig using the DEHC system.

Event 2: Reactivity control; Following the pressure increase, control rods will be withdrawn to open the #1 Main Turbine Bypass Valve to 80% open.

Event 3: Component; While withdrawing control rods to open the #1 Bypass Valve, control rod 26-23 sticks. It will not move at normal CRD drive water pressure. CRD drive water pressure will be raised lAW the Inability to Move a Control Rod abnormal procedure. When drive water pressure (dp) is >350 psig, the rod will move. Rod withdrawal will then continue normally.

Event 4: Component; The Control Room will receive a report that the "2C" Condensate Booster Pump (CBP) has an oil leak. The message will be worded such that there is time to start another pump and secure the running CBP. It will be recommended that the pump be shut down. The team will start a standby CBP ("2A" or "2B") and secure the "2C" CBP.

0)

Event 5: InstrumentlTS; After the standby CBP has been placed in service, 2E41-F002 (HPCI Inboard Steam Isolation Valve) will close as the result of an instrument failure (High Steam Flow dp). Time compression will be used to repair the condition and the team will restore HPCI to standby. SS addresses Tech Specs for HPCI operability and HPCI instrumentation.

Event 6: Component; "2A" CRD pump will trip. "2B" CRD pump will be started IAW the Loss of CRD abnormal procedure. The pump trip will be investigated. The "2B" CRD pump will trip, resulting in a condition requiring a manual reactor scram. When the scram is inserted, several control rods will not fully insert due to the combination of low RPV pressure and both CRD pumps being off. Power is <5%, so control rod insertion will be addressed using the abnormal procedure for control rods insertion. The SS will enter the RC-A EOP flow chart if RWL decreases < 3 inches. The "2A" CRD pump will be repaired and started, causing the remaining control rods to fully insert as charging water pressure increases, with the scram inserted. SS addresses TS requirement for loss of CRD.

Event 7A; Major/Component; Torus water level will begin increasing at 3 inches/minute due to an outage valving error. The team will attempt to isolate the flow path; however, the Core Spray AOV and MOV suction valves will fail to work. The SS enters the PCC EOP flowchart.

Event 7B: The SS uses EOP Contingency Procedure I (CP-l) and directs an operator to Emergency Depressurize the RPV. An operator opens 7 ADS valves prior to Torus water level exceeding 193 inches. (Critical Task)

Event 8: Component; The Startup Level Control Valve (SULCV) fails closed requiring operators to control RWL with the SULCV Bypass Valve, or by using Core Spray, or Residual Heat Removal systems. (Critical Task)

Page 20f32 Critical Task List Facility: E. I Hatch Scenario No.: 4-03 Op-Test No.: 2009-301

')

Critical Tasks

Fully insert all control rods by restarting a CRD pump. (Event 6)

Open 7 SRV s prior to Torus Water Level exceeding 193 Inches. (Event 7 A) o NOTE: The critical task is met when 5 SRVs have been opened. This is the minimum number of SRVs required by the EOPs to Emergency Depressurize the RPV.

Align available systems for vessel injection to maintain RWL greater than -185 inches. (Event 8)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 5 1. Stuck control rod.

2. HPCI isolation.

3. CRD Pump Trip.

4. Torus water level increases.

5. SULCV fails closed.

2. Malfunctions After 1-2 1 1. 2 Main Turbine Bypass Valves fail closed.

EOP Entry 2. SULCV fails closed.

3. Abnormal Events 2-4 3 1. Inability to move a control rod.

2. Loss ofCRD.

3. Control rod insertion.

4. Major Transients 1-2 1 1. Torus water level increasing.

5. EOPs entered, 1-2 1 1. PCC EOP Flowchart.

requiring substantive actions

6. EOPs contingencies 0-2 1 1. CP-l Emergency Depress.

requiring substantive actions

7. Critical Tasks 2-3 2 1. Open SRVs to Emergency Depressurize

2. Insert control rods

3. Maintain RWL >-185 inches

~----

L.... __

Page 3 of32 AppendixD Scenario Outline Form ES-D-l DRAFT

)

Facility: E. I Hatch Scenario No.: 4-3 Op-Test No.: 2009-301 Examiners: Operators: SRO RO BOP Initial Conditions. The unit is starting up Rx Pressure at 380 psig. Power is to be increased to the point of starting the first feed pump.

Turnover: Increase pressure set to 420 psig reactor pressure and continue power increase using control rods until approximately one bypass valve is open 80%. At that time place the first reactor feed pump in service. Heat up data is being taken by a third operator.

Event Malf. No. Event Event No. Type* Description 1 N/A N (BOP) Increase Reactor Pressure to 420 psig prior to preparation for RFPT

'2A' Startup.

2 N/A R (ATC) Pull rods and to achieve one bypass valve 80% open in preparation for RFPT Startup.

mfCIL280

)3 mfC12_22 26-23 C (ATC) Control rod 26-23 at "00" is stuck, must increase drive water dip and double clutch to get rod to move from position "00".

none ft t (BOP) System Operator reports Condensate Booster Pump (CBP) "C" has an oil leak, "A" or "B" CBP must be started, "A" shutdown.

S mffi41_108 ~ (BOP) HPCI Instrument malfunction results in an isolation of 2E41-F002, ITS (SRO) compressed repair realign.

6 mfCIL30A CATC CRD A Trip / Start CRD B/ several minutes later CRD B trips/

mfCll_30B IrS (SRO) Manual SCRAM

~A svoT48140 Torus level begins to increase due to Core Spray CST and Torus

~ (ALL) svoN37226 suction valves being open at the same time. Valve failures will svoN37227 prevent closing the CS suction valves. Torus level continues to aoPll-R601 increase, challenging EOP limits (Heat Capacity Temperature Limit, diE21-F019A Pressure Suppression Pressure and SRV Tail Pipe Level Limit graphs).

I7B Emergency depress due to high Torus water level 8 mtN2L99 r (BOP) SULCV fails closed. RPV level will be controlled either by throttling open 2N21-FllO, or by using a low pressure ECCS pump system.

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

AQQendix 0 Required Operator Actions Form ES-O-2

)

Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 1 Page 40f32 Event

Description:

Increase Reactor Pressure to 420 psig using pressure set Time Position Applicant's Actions or Behavior SRO

Orders operator to increase reactor pressure to 420 psig BOP

Using pressure set increases reactor pressure to 420 psig

On EHC HMI selects control,

Selects psi-load

Selects Ramp Rate verifies desired ramp rate

Selects Pressure and enters 420

Selects OK pushbutton

Monitors and verifies that reactor pressure increases to desired pressure.

Notifies SS that reactor pressure is at 420 psig.

)

A~endixO Required Operator Actions Form ES-O-2

)

Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 2 Page 5 of32 Event

Description:

Pull rods 80% on Bypass Valve #1.

Time Position Applicant's Actions or Behavior SS

Orders control rods withdrawn per the pull sequence .

ATC

Withdraws control rods to continue the power increase by:

Selects the first control rod in the currently latched or next group per the pull sheet and RWM.

First rod moved is 50-31 step 10.

Continuously withdraws the rod to the withdraw limit, releasing the switch one notch before the withdraw limit, unless the withdraw limit is 48.

Continues withdrawing rods per the pull sheet.

Monitors bypass valve position and ensures expected plant response from control withdrawal.

)

Note: May get "RMCS/RWM ROD BLOCK or SYS TROUBLE" annunciator.

This is not abnormal when selecting rods in a different group.

)

AImendix 0 Required Operator Actions Form ES-O-2 I

Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 3 Page 60f32 Event

Description:

Control rod at "00" is stuck, must increase drive water dp and double clutch to get rod to move from position "00."

Time Position Applicant's Actions or Behavior Simulator Operator

After rod 26-23 is moved to position 02 or beyond, THEN 0 DELETE mfC 1 L280 AND 0 DELETE mfC12_2226-23.

ATC Attempts to withdraw control rod 26-23, rod fails to withdraw.

Notifies the SS of the inability to move 10-07.

Addresses 34AB-Cll-003-2, "Inability to Move a Control Rod."

Proceeds through the flow chart within 34AB-CII-003-2,

Is the rod at position "OO?,' ans. Yes,

)

Verifies indications are normaL

Raises drive water dp in 50 psid increments and attempts to move the rod per the "double clutch" method at each increment.

Once above 330 psid, the rod moves.

NOTE: the control rod has potential to double notch when it moves.

)

ARI2endix 0 Required Operator Actions Form ES-O-2

}II Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 4 Page 7 of32 Event

Description:

System Operator reports Condensate Booster pump "A" has an oil leak, "B" must be started, "A" shutdown.

Time Position I Applicant's Actions or Behavior 1 Simulator Operator When directed by the chief examiner:

Call the Control Room as a System Operator (SO), and REPORT:

o I am performing rounds. The "2C" Condensate Booster pump has an oil leak.

When questioned about the size of the oil leak, REPORT:

o The CBP is low on oil and a slow steady stream of oil is leaking, I recommend shutting it down as soon as possible.

IF asked if there is enough oil to allow the pump to run without damage to the pump, THEN REPORT:

o I recommend that it be shut down as soon as possible.

SS

Directs Operator to place 2A or 2B Condensate Booster pump (CBP) in service and shutdown the 2C Condensate Booster pump.

BOP

Enters 34S0-N21-007-2 and performs the following actions:

Directs an SO to:

Verify that 2A or 2B CBP Oil Reservoir and motor bearing oil levels are WITHIN normal level marks.

Throttle 2P41-F364A or B, outlet valve as necessary to maintain the oil temperature between 50°F and 115°F.

Confirm / Place CBP 2A or 2B Oil Pump control switch in Auto and Confirm pump is running.

Confirm Closed/Close 2N21-F020A or B, Standby CBP Discharge Valve.

AQQendix 0 Required Operator Actions Form ES-O-2

----------------------~-.----.-- -- - - -

I Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 4 Page 8 of32 Event

Description:

System Operator reports Condensate Booster pump "A" has an oil leak, "B" must be started, "A" shutdown.

Time Position Applicant's Actions or Behavior Simulator Operator

Call the Control Room as a SO and REPORT:

\

0 The oil level for CBP 2A (or 2B) oil levels is normal.

) 0 Oil temperature is at 95°F.

0 The oil pump is running in Auto.

0 2N21-F020A or B is closed.

Note: You do NOT have to enter the remote function for closing the discharge valve for the CBP. The procedure requires it to be throttled prior to pump start; however, we do not have throttle capability.

BOP

Directs SO to:

Throttle Open 2N21-F020A or B, CBP Discharge Valve, for 15 seconds

Observe for indication of a stuck open / leaking discharge check valve as evidenced by increasing pressure on the pump side of the discharge check valve.

Simulator Operator

)

VERIFY that rfN21_60A (or 60B) is in Open.

Call the Control Room as a SO and REPORT:

~-~

AQQendix 0 Required Operator Actions Form ES-O-2

)

Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 4 Page 90f32 Event

Description:

System Operator reports Condensate Booster pump "A" has an oil leak, "B" must be started, "A" shutdown.

Time Position Applicant's Actions or Behavior 0 2N21-F020A (or F020B) has been opened 15 seconds 0 The discharge check valve does NOT indicate leakage.

BOP

Starts Condensate Booster Pump 2A or 2B, by placing the control switch to Start.

Has SO throttle open the Discharge valve and maintain oil temp by throttling PSW to the oil cooler.

\

)

Simulator Operator

Call the Control Room as a SO and REPORT:

0 "The discharge valve is full open for CBP 2A (or 2B)."

0 "Oil temp is being maintained at 95°F."

BOP

When condensate and Feedwater flows and pressures have stabilized, directs the SO to close 2N21-F020C Simulator Operator

)

ENTER rfN2L62 (CBP "C" Disch valve close)

THEN

AQ.Qendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 4 Page 10 of32 Event

Description:

System Operator reports Condensate Booster pump "A" has an oil leak, "B" must be started, "A" shutdown.

Time Position Applicant's Actions or Behavior

Call the Control Room as a SO and REPORT:

0 "The 2C CBP discharge valve has started closing."

BOP

Places CBP 2C control switch to stop within 90 secs of being told the discharge valve has started closing.

Reports to SS that 2A or 2B CBP is operating and that the 2C CBP has been secured. May ask SS if it is desired to place the 2C CBP in standby. If so the CBP 2C control switch will be placed in Auto.

)

i SS

May direct the operator to place CBP 2C in PTL Off or Standby and i leave oil pump in off. i I

i Simulator Operator *

IF requested to re-open the discharge valve:

0 ENTER rfN2L62 (CBP "c" Disch valve Open)

)

Call the Control Room as a SO and report:

0 "The "2C" CBP discharge valve is Open." ----_ ......... _ -

AQ.Qendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 4 Page 11 of 32 Event

Description:

System Operator reports Condensate Booster pump "A" has an oil leak, "B" must be started, "A" shutdown.

Time Position Applicant's Actions or Behavior

)

AQQendix 0 Required Operator Actions Form ES-O-2 JI II Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 4 Page 12 of32 Event

Description:

System Operator reports Condensate Booster pump "A" has an oil leak, "B" must be started, "A" shutdown.

Time I Position I Applicant's Actions or Behavior 1

AQ.Q.endix D Required Operator Actions Form ES-D-2

~

Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 5 Page 13 of32 Event

Description:

HPCI instrument malfunction, causing an isolation of 2E41-FOO2 Time Position Applicant's Actions or Behavior Simulator Operator

At Chief Examiner's direction PRESS (RB-l) to activate:

0 mfE4L108, HPCI instrument malfunction (2E41-F002 isolates)

BOP Addresses annunciators:

HPCI Steam Line DiffPress High, 601-104-2

HPCI Turbine Trip Solenoid Energized, 601-109-2

HPCI Isolation Trip Logic A Initiated, 601-115-2 BOP Addresses annunciator "HPCI Isolation Trip Logic "A" Initiated.

)

Confirms 2E41-F002 is closed.

Closes 2E41-F003

Checks for validity of the alarm, monitoring related alarms.

SS Notifies maintenance to investigate

The HPCI Steam Line Diff Press High signal.

~---.---

Al2I2endix D Required Operator Actions Form ES-D-2

~

Op* Test No.: 2009*301 Scenario No.: 4*3 Event No.: 5 Page 14 of32 Event

Description:

HPCI instrument malfunction, causing an isolation of 2E41-FOO2 Time Position Applicant's Actions or Behavior Simulator Operator

As an I&C Technician, call the Control Room and REPORT:

0 "The cause of the isolation is 2E41-N 657 A.

0 "It has failed upscale."

0 "We are repairing the problem at this time."

SS

Addresses Tech Specs 3.3.6.1 and determines a RAS requires the channel to be placed in trip in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND

')

Tech Specs 3.5.1 on BPCI operability, that BPCI is inop with a 14 day RAS

,//

Simulator Operator

DELETE mfE4L108, HPCI instrument malfunction.

As an I&C Tech, call the Control Room and REPORT:

0 "I am using Time Compression and it has been 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months since we talked. BPCI instrument 2E41-N657 A has been repaired."

SS Directs the ATC operator to realign BPCI to standby status.

AQ.Qendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 5 Page 15 of 32 Event

Description:

HPCI instrument malfunction, causing an isolation of 2E41-FOO2 I Time Position Applicant's Actions or Behavior BOP Using 34S0-E41-001-2, HPCI System Procedure, the operator should

Reset the "B" isolation, observing the white light on panel 2H11-P60 1 extinguishes.

Pressurize HPCI with the 2E41-F003 lAW 7.1.40.2

Opens 2E41-F003

Opens 2E41-F054

Slowly Opens 2E41-F002

Monitors HPCI Steam line pressure

When HPCI Steam line pressure is within 50 psig of Reactor pressure, fully opens 2E41-F002.

Closes 2E41-F054, when HPCI Turbine Inlet Drain Pot Level High (601-110) Clears

Notifies SS HPCI is returned to Standby

)

I i

I I

i i

I I

i I

I

AQQ.endix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 6 Page 16 of32 Event

Description:

CRD A Trip I Start CRD BI CRD B tripsl Manual SCRAM II Time I Position I Applicant's Actions or Behavior Simulator Operator

At Chief Examiner's direction, PRESS (RB-2) to activate:

o mfC 1 L30A; 2A CRD Pump Trip All * "CRD Pump A Breaker" annunciator will alarm.

ATC

Determines that CRD pump "2A" has tripped.

Reports the trip of "2A" CRD pump to the SS.

SS

Directs the ATC to address the ARP for the tripped CRD pump annunciator (34AR -603-128-2).

Directs the ATC to enter 34AB-Cll-001-2, "Loss of CRD System." I I

Almendix 0 Required Operator Actions Form ES-O-2 I

Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 6 Page 17 of32 Event

Description:

CRD A Trip / Start CRD B/ CRD B trips/ Manual SCRAM Time Position Applicant's Actions or Behavior ATC

Addresses 34AR-603-128-2, "CRD Pump A Breaker Trip."

Enters 34AB-Cll-001-2, "Loss ofCRD System."

Places the CRD Flow Controller in manual.

Lowers the controller output to "0".

Any attempt to re-start the 2A CRD pump will faiL

Starts "2B" CRD pump.

Raises CRD flow to 50 gpm.

If required, send a SO locally to close 2C11-F034, "Charging Water Header Isolation Valve" to establish adequate drive water pressure.

I SS

As time permits, orders SO and Maintenance to investigate the loss of "2A" CRD Pump.

AQQ.endix 0 Required Operator Actions Form ES-O-2

- - -----_ .. _---------- ~

\

Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 6 Page 18 of 32 Event

Description:

CRD A Trip / Start CRD B/ CRD B trips/ Manual SCRAM I Time Position Applicant's Actions or Behavior Simulator Operator

When the "B" CRD is placed in service and stable, THEN at Chief Examiner's Direction, PRESS (RB-3) to activate:

o mfCIL30B; 2B C1RD Pump Trip All * "CRD Pump B Breaker" annunciator will alarm.

I ATC

Determines that CRD pump "2B" has tripped.

Reports the trip of "2B" CRD pump to the SS.

SS

Directs the ATC to address the ARP for the tripped CRD pump annunciator (34AR-603-129-2).

Directs the ATC to enter 34AB-Cll-00l-2, "Loss of CRD System."

AQ.Qendix 0 Required Operator Actions Form ES-O-2

\

Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 6 Page 19 of 32 Event

Description:

CRD A Trip / Start CRD B/ CRD B trips/ Manual SCRAM Time Position Applicant's Actions or Behavior ATC

Addresses 34AR-603-129-2, "CRD Pump B Breaker Trip."

Enters 34AB-Cll-001-2, "Loss of CRD System."

Places the CRD Flow Controller in manual.

Lowers the controller output to "0."

Attempt to re-start the 2B CRD pump, but it will not start

Notifies the SS that the 2B CRD Pump will NOT restart.

)

ATC

Receives CRD Accumulator Press Low or Level High alarm (603-148-2)

Notifies SS

- --------------------_._----_ .... - _... _ - - ---.-----.--~-------------.--- - - - - - _ .. _--_ .. _ - - - - - - - - - - - - - - - -

AQ.Qendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 6 Page 20 of32 Event

Description:

CRD A Trip! Start CRD B! CRD B trips! Manual SCRAM Time Position Applicant's Actions or Behavior SS

Directs ATC monitor for more accumulator lights on the full core display and to dispatch personnel the CRD RCUs to check pressure.

Simulator Operator

3 minutes AFTER being directed to check HCU pressures, THEN REPORT:

o Pressure indication on several HCUs indicate between 850 psig and 900 psig.

ATC

Determines multiple accumulator lights are illuminating

Notifies SS Simulator Operator

LOOK AHEAD at the next Simulator Operator task (time sensitive) .

A~endixO Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 6 Page 21 of32 Event

Description:

CRD A Trip / Start CRD B/ CRD B trips/ Manual SCRAM Time Position Applicant's Actions or Behavior NOTE: The SS may not have time to determine Tech Spec actions prior to scram.

If this happens, have the SS determine the Tech Spec actions after the scenario is terminated.

SS

Determines that a Tech Spec required shutdown exist lAW with Tech Spec 3.1.S.C, 3.1.S.D and 34AB-Cll-001-2, Loss ofCRD Procedure due to reactor pressure less than 900 psig and multiple inoperable accumulators.

Orders the ATC operator to perform RC-l placard and manually Scram the Reactor.

Orders the BOP operator to perform RC-2 and RC-3 placards ATC NOTE: The number of control rods not full in will depend on how long of time it is from the loss of CRD to the Scram (could vary froml0 to 70 rods).

Inserts a manual scram and places the Rx Mode switch in Shutdown.

Notifies the SS that all control rods did not insert.

L-_____ --

AQQendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 6 Page 22 of32 Event

Description:

CRD A Trip / Start CRD B/ CRD B trips/ Manual SCRAM Time Position Applicant's Actions or Behavior SS

Orders the ATC operator to insert control rods lAW 34AB-C 11-005-2, Control Insertion Methods.

IfRWL decreases to less than 3 inches, will enter the RC EOP flowchart; however, RWL is not expected to go below 3 inches.

ATC

Enters 34AB-Cll-005-2

Bypasses the Scram Discharge Volume high level trip

Resets the Scram

)

Places the Scram Discharge Volume Isolation Test switch to NORMAL Simulator Operator

2 minutes after the scram has been inserted:

0 DELETE mfCIl_30A

Call the ATC that a Tin)le Compression is being used and it is 10 minutes later, and REPORT:

0 "2A CRD pump has. been repaired."

"---~ ... - -

AQ.Qendix D Required Operator Actions Form ES-D-2

.~

Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 6 Page 23 of32 Event

Description:

CRD A Trip I Start CRD BI CRD B tripsl Manual SCRAM I Time Position Applicant's Actions or Behavior ATC

Starts 2A CRD Pump and establishes drive water DP.

Places the Reactor Mode Switch to REFUEL.

Places the RWM Bypass switch to BYPASS.

Obtain recommendations from the STA as to which rods have the highest worth (Black and white spiral pattern.)

Inserts control rods."

Critical Task: Take actions to fully insert all control rods by restarting a CRDpump.

)

BOP Performs actions of RC-2 and RC-3 after Reactor SCRAM.

Confirms proper Level Control response:

Checks ECCS Injection Systems and secures as necessary.

Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.

IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.

BOP

With feed flow is less than the capacity of the S/U level control valve

(;:::; 1.5 mlbm/hr), verifies:

2N21-F125 is open.

I

Places 2C32-R619, FW SIU level control valve controller, in Auto, set at approximately 9 inches.

Ensures 2N21-FllO is closed.

- - - - - - - - - - - _ .. ------_ .. _--_._-------------_ .. _--------------- ------- ---- ...... -.... ---.- .. -...... --.-.------.-~--~--~

A~endixO Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 6 Page 24 of32 Event

Description:

CRD A Trip I Start CRD BI CRD B tripsl Manual SCRAM Time Position Applicant's Actions or Behavior

Determines that the SULCV is failed closed.

Opens 2N2l-FIlO (almost impossible to control RWL with this valve at this power leveL)

OR

Starts RCIC for RWL control

)

AQQendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 7A Page 25 of32 Event

Description:

Core Spray Suction Valves Opened Result In Increasing Torus Water Level II Time I Position I Applicant's Actions or Behavior I Simulator Operator

When directed by the Chief Examiner, PRESS (RB-4) to activate:

0 svoT48140; Suppression Pool Water Level 0 aoPll-R601; Condensate Storage Tank Level

Note: The following overrides were entered at the beginning of the scenario:

0 diE21-FOOIA; Core Spray Suction Valve 0 diE21-F019A; Core Spray Torus Suction Valve 0 svoN37226; Turbine Bypass Valve #2 Position 0 svoN37227; Turbine Bypass Valve #3 Position 0 Event trigger E21-0J; 2E21-FOOIA lights go out and valve fails

) open when the green light illuminates.

All

Recognize Torus water level is increasing.

SS

Direct operators to look for the source of water entering the Suppression Chamber.

May dispatch SO's to the Reactor Building Diagonals to check for val ve lineup issues.

Enters Primary Containment Control (PCC) EOP flowchart when Suppression Pool level exceeds 150 inches.

AQ.Qendix 0 Required Operator Actions Form ES-O-2 J

Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 7A Page 26 of32 Event

Description:

Core Spray Suction Valves Opened Result In Increasing Torus Water Level Time Position Applicant's Actions or Behavior BOP

Monitor panels looking for sources of in-leakage to the Suppression chamber.

Determines Condensate Storage Tank level is decreasing.

Enters the following ARP's.

0 Torus Level High, 601-127 0 Torus Level (RC1C) High, 602-230 Simulator O,Qerator

)

When torus level reaches 160 inches, call the control room as the Operations Control Center (OCC) supervisor and REPORT:

0 "I sent a team to align the Unit 1 Core Spray suction to the CST in preparation for Reactor Cavity Flood up."

0 "They went to Unit 2 and began to open 2E21-F002A before they noticed they were on the incorrect unit."

0 "When they attempted to close the valve, the valve hand wheel would not tum and we could not get the valve to close.

Maintenance is on their way to the valve."

SS

Direct the BOP operator to close the "2A" Core Spray suction valves.

)

AQQ.endix 0 Required Operator Actions Form ES-O-2

.----.------~--.----------

Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 7A Page 27 of32 Event

Description:

Core Spray Suction Valves Opened Result In Increasing Torus Water Level Time Position Applicant's Actions or Behavior BOP

Place the 2E21-FOOIA valve switch in the close position 0 Recognizes that the lights for 2E21-FOOIA de-energize.

0 Reports to the SS that the lights for 2E21-FOOIA de-energized.

Place the 2E21-F019A valve switch in the close position.

0 Recognizes that 2E21-F019A did not close.

0 Reports to the SS that 2E21-F019A did not close.

Checks Torus level and determines that Torus level is still increasing.

I Simulator Operator

If directed to close 2PI1-F029, WAIT for 5 minutes and THEN REPORT:

0 "The valve hand wheel for 2PII-F029 broke off of the valve stem and we are sending someone to get us a wrench."

SS

Direct operators to maintain Torus Water Level below 193 inches to remain in the safe region of the Heat Capacity Temperature Limit (HCTL) EOP graph and the SRV Tailpipe Level Limit graph using 34S0-El1-0I0-2 or 34GO-OPS-087-2.

Directs that maintenance investigate the failure of the "2A" Core Spray suction valves to close.

AQ.Qendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 7A Page 28 of32 Event

Description:

Core Spray Suction Valves Opened Result In Increasing Torus Water Level Time Position Applicant's Actions or Behavior BOP

If time allows, use 34S0-EII-OIO-2 "RHR System" to align RHR for draining the Torus to Radwaste:

0 Confirm Radwaste is capable of receiving water 0 Open 2Ell-F049 0 Close 2Ell-FOO3B 0 Close 2EII-F047B 0 Confirm Open 2EII-F048B 0 Start a "B" loop RHR pump 0 Confirm discharge water is less than 200F (2T47-R627 pt. 3) 0 Throttle Open 2Ell-F040

)

SS

Directs operators to terminate any external sources of water except for sources necessary to ensure adequate core cooling, boron injection, or CRD.

If the need to Emergency Depressurize is recognized in time, then Anticipates Emergency Depressurization.

0 Assign an operator to fully open all Main Turbine Bypass Valves.

AQQendix 0 Required Operator Actions Form ES-O-2

'i Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 7A Page 29 of32 Event

Description:

Core Spray Suction Valves Opened Result In Increasing Torus Water Level Time Position Applicant's Actions or Behavior ATC/BOP

On the DEHC panel 0 Select the Control> Bypass Valve screen.

0 Insert a ramp rate of 100, then press OK.

0 Insert a bypass valve position of 100, then press OK.

0 Checks that the Bypass Valve Jack status is active.

0 Recognizes that only 1 Bypass Valve opens.

0 Reports to the SS that only 1 Bypass Valve opens.

I

)

I I

AQQendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 7B Page 30 of32 Event

Description:

Emergency Depressurization of the RPV Time Position Applicant's Actions or Behavior SS

Prior to exceeding 193 inches in the Torus.

0 Orders 7 ADS valves open for Emergency Depress.

(Critical Task - Open 7 SRVs prior to Torus Water Level exceeding 193 Inches. Critical task is met when 5 SRVs have been opened.)

i Simulator Operator i

)

When torus level reaches 205 inches, call the control room as the Operations Control Center (OCC) supervisor and REPORT:

0 "Maintenance has closed 2E21-F002A." I i

I I

I BOP

Places the switches for 7 ADS valves in the open position.

0 If Anticipate Emergency Depressurization was performed, the amber lights for the SRVs will not illuminate if pressure has been reduced to below approximately 300 psig. In this case the operator must use 2H11-P614 recorder indication to monitor tail pipe temperatures for the SRVs to verify the valves actually opened (Recorder 2B21-R614).

0 Depending on Reactor Water Level prior to opening ADS valves, RWL may swell to above 60 inches, requiring the operator to enter 34AB-C32-00 1-2, Reactor Water Level Above 60 inches.

Operator secures all injection other than CRD

AQQendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 8 Page 3101'32 Event

Description:

SULC Fails Closed, Will Use 2N21-F110 or Low Pressure ECCS System(s) to Maintain RWL.

Time Position Applicant's Actions or Behavior Note: If the operator controlling RPV level has difficulty determining why injection with the Condensate System is not occurring (failed Startup Level Control Valve failed closed), the candidate may then elect or be directed to use low pressure ECCS maintain RWL.

Simulator Operator

AFTER the ADS valves have been opened, PRESS (RB-S) to activate:

o mtN2L99, SULCV fails closed (See Event 8A)

BOP

The BOP recognizes the SULCV has failed closed.

)

Performs one or more of the following to inject water into the reactor.

o Throttles open 2N21-FllO, and inject water into the reactor.

OR o Starts a CS Pump.

o Confirm discharge pressure >265 psig.

o Confirm 2E21-F031A(B) closes when flow >950 gpm.

o Confirm a CS and RHR room cooler automatically starts.

o When RPV pressure is <425 psig, throttles open 2E21-F005A(B).

OR o Starts a RHR pump.

o When RPV pressure is <425 psig, throttles open 2Ell-F015A(B).

Reports SULCV problem to the SS.

Critical Task - Align available systems for vessel injection to maintain RWL greater than -185 inches.

NOTE: The critical task is met when 5 SRVs have been opened (EOP minimum number of SRVs required to Emergency Depressurize the RPV).

A~endixD Required Operator Actions Form ES-D-2

/ Op-Test No.: 2009-301 Scenario No.: 4-3 Event No.: 8 Page 32 of32 Event

Description:

SULC Fails Closed, Will Use 2N21-FIlO or Low Pressure ECCS System(s) to Maintain RWL.

Time Position Applicant's Actions or Behavior

)

Simulator Operator

With Chief Examiners permission AND

When reactor water is being controlled following the emergency depressurization, with reactor pressure below 50 psig, THEN 0 Terminate the scenario.

!.,~:.:"" ~:;

Page 10f34 Scenario Summary

.. ) Facility: E. I Hatch Scenario No.: 4*04 OR-Test No.: 2009-301 DRAFT Initiating Conditions: I Unit 2 is at 90%. RCIC - RCIC is isolated following repair of the outboard isolation valve breaker. System restoration to standby per 34S0-E51-001-2, RCIC System, is in progress at step 7.1.1.33. The functional test for the Valve has been performed.

Turnover I Continue 34S0-E51-001-2, RCIC System, to return RCIC to Standby, at step 7.1.1.33.

Summary:

Event 1: Normal; The BOP operator will un-isolate RCIC.

Event 2: ComponentITS; Mter RCIC has been un-isolated, a half scram will occur due to a PRNM 2 out of 4 logic trip. A control rod will scram due to a blown fuse. The control rod will be withdrawn after having the fuse replaced lAW abnormal procedure guidance. The SS will address Tech Specs for inoperable PRNM 2 out of 4 logic module.

Event 3/4: ComponentlReactivity; Mter the control rod has been fully withdrawn, the "2A" Recirc Pump will begin to vibrate. A high vibration alarm will be received. Recirc pump speed will be reduced and the vibration alarm will clear. Any attempt to raise Recirc speed will cause the alarm to be received again.

Event 5: ComponentITS; A RWCU line will break outside of Primary Containment. The outboard isolation valve is failed open and cannot be closed. The inboard valve fails to automatically close on an automatic isolation signal and must be manually closed (Critical Task). The SS addresses Tech Specs for inoperable Primary Containment Isolation Valves.

Event 6: ComponentITS; "2B" Instrument Bus will be lost due blown fuse. The bus will be restored after the fuse is replaced. Impacted systems will be restored back to their normal alignment as time permits. The SS will address TS for loss of the Instrument Bus.

Event 7A: (Major) A loss of all Startup Transformer "2D" will occur. The reactor will scram and MSlVs will close. All control rods fully insert. The only Unit 2 4160V bus that will be energized without operator action is "2P". There is a hard phase-to'-phase short on "2E" 4160VAC bus which causes the alternate breaker to trip after it closes in. The "2A" EDG output breaker will not close. "2G" 4160 VAC bus fails to auto transfer and the associated EDG cannot be started. RCIC trips when it attempts to start. HPCI fails to auto start but can be manually started. Drywell pressure will increase to above 1.85 psig. The SS will direct the EOP actions lAW with the RC and PCC EOP flowcharts.

Event 7B: Component; "2G" 4160 VAC bus will be energized from SAT "2C.

Event 7C: Component; Start HPCI and inject to maintain RWL above top of active fueL (Critical Task)

Page 2 of34 Critical Task List

) Facility: E. I Hatch Scenario No.: 4-04 Op-Test No.: 2009-301 Critical Tasks

Manually isolate RWCU before exceeding maximum safe Secondary Containment Control EOP parameters (Temperatures, Radiation levels or SC water levels) (Event 5).

Maintain RWL above -185 inches. This is the lowest level that corresponds to adequate core cooling with injection (Event 7C).

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 6 1. Control Rod fully inserts.

2. Recirc Pump Vibration.

3. RWCU Pipe Break.

4. Instrument Bus Loss.

5. Loss of SAT "2D"

6. HPCI fails to auto start.

2. Malfunctions After 1-2 2 1. "2C" EDG cannot be started.

EOP Entry 2. HPCI fails to auto start.

I

3. Abnormal Events 2-4 3 1. RWCU pipe break inside the Reactor Bldg.

2. Instrument Bus Loss.

3. Mispositioned Control Rod

4. Major Transients 1-2 1 1. Loss of SAT "2D"

5. EOPs entered, 1-2 2 1. RC EOP Flowchart requiring substantive 2. PCC EOP Flowchart actions

6. EOPs contingencies 0-2 0 requiring substantive actions

7. Critical Tasks 2-3 2 1. Isolate RWCU line break.

2. Maintain RWL above -185 inches using HPCI.

~_L_

Page 3 of34

.') Appendix D Scenario Outline Form ES*D*1 DRAFT Facility: E. I Hatch Scenario No.: 4*04 Op*Test No.: 2009*301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is at 90% RTP following Turbine Control Valve testing.

RCIC is isolated following repair of the outboard isolation valve breaker.

System restoration to standby per 34S0-E51-001-2, RCIC System, is in progress at step 7.1.1.33.

The functional test for the Valve has been performed.

Turnover: Continue 34S0-E51-001-2, RCIC System, to return RCIC to Standby, at step 7.1.1.33.

Event Malf. No. Event Event No. Type* Description 1 [N (BOP) Un-isolate RCIC and return to standby.

diC51-K617A-S2 ~ (ATC) PRNM 2 out of 4 logic module trips causing a half scram and a 2 diC51-K617A-S1 Irs (SRO) control rod to scram in due to a blown fuse.

mfC12_26 14-39

) 3 mtB3L41A ~ (ATC) Recirc Pump "A" high vibration, power increase will be stopped and

~ (ATC) decrease started. Decreasing to about 62% power will correct

~ condition.

5 mfG31_207A 12 (BOP) RWCU line break outside of Secondary Containment. Must be svoG31071, IrS (SRO) manually isolated (Critical Task), with failure of outboard isolation mfG31 52 valve to close.

~ ImtR25_186 r (BOP) Loss of "2B" Instrument Bus. Restoration of "2B" Instrument Bus.

rfT41-299 Irs (SRO) 7A mfSll_227B ~ (ALL) Loss of all Startup Transformer "2D".

mfP64_193B "B" DW Chiller fault mtR22-182 Fault on "2E" 4160VAC bus.

mtR43_168A "2A" EDG output breaker will not close.

diR22_135584C "2G" 4160 VAC bus fails to auto transfer.

mfC1L30B "B" CRD pump trips mtR43_167C "2C" EDG cannot be started.

mfN30_122 Main turbine trip mfE5LllO RCIC trips after auto starting.

mfE41_235A HPCI fails to auto start.

mfE41_235B 7B C (ATC) Energize "2G" 4160 VAC bus from SAT "2C.

7C C (BOP) Start HPCI to control RWL (Critical Task).

I

(N)ormal, (R)eacti vity, (I)nstrument, (C)omponent, (M)ajor

A~endixO Required Operator Actions Form ES-O-2 Op*Test No.: 2009*301 Scenario No.: 4*04 Event No.: 1 Page 4 of34 Event

Description:

Un-isolate RCIC and return to standby.

Time Position Applicant's Actions or Behavior SS

Directs the operator to continue with RCIC "Return to Standby" per the Initial Condition sheet.

BOP

Un-isolates RCIC per 34S0-E51-001-2, RCIC System, starting at step

? .1.1.36 to return RCIC to standby.

Warms and Pressurizes the RCIC Steam Line by performing the following steps:

0 Confirms Closed 2E51-F008, Steam Supply Line Isol Vlv.

0 Confirms Closed 2E51-FOO?, Steam Supply Isol Vlv.

0 Confirms Open/Opens 2E51-F054, Steam Line Drain Vlv.

I BOP

Opens 2E51-F008, Steam Supply Line Isol Vlv.

Slowly Throttles Open 2E51-FOO?, Steam Supply Isol Vlv. I

When turbine steam inlet pressure is WITHIN 50 PSIG of reactor pressure as monitored on 2B21-R623A(B), Rx Water LevellRx Press, on paneI2Hll-P601, fully open 2E51-FOO?, Steam Supply Isol Vlv, is FULLY OPEN.

When RCIC Turbine Inlet Drain Pot Level High (602-308), clears, confirm Closed/Close 2E51-F054, Steam Line Drain Vlv.

(Alarm may not come in.)

Has other operator perform independent verification for RCIC Standby lineup.

Notifies SS when RCIC is returned to Standby.

SS

Declares RCIC Operable

A~endix D Required Operator Actions Form ES-D-2

-~'~h aI

/11 Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 2 Page 5 of 34 Event

Description:

PRNM 2 out of 4 logic module trips causing a half scram and a control rod to scram in due to a blown fuse.

Time -rpOSiliODI Applicant's Actions or Behavior Simulator operator

As directed by the Chief Examiner, press the following:

(THESE 10's ARE SEQUENCE SENSITIVE):

0 First, press (RB-1) to activate diC51-K617A-S2 THEN 0 Press (RB-2) to activate diC51-K617A-S1 and mfC12_26 14-39 ALL

Address the following alarms:

0 Recognizes a half scram occurs on RPS "A" 0 Reactor Neutron Monitoring Sys Trip, 34AR-603-109-2 0 Reactor Auto Scram System "A" trip, 34AR-603-126-2 0 Rod Drift, 34AR-603-247-2 0 Identifies control rod 14-39 has scrammed full in.

NOTE: The team may immediately address the abnormal procedure 34AB-C11-004-2, Mis-positioned Control Rods, since the control rod is mis-positioned.

CBO

Addresses annunciator "Rod Drift," 34AR-603-247-2 0 At panel2H11-P603, confirms that one or more Rod Drift lights are illuminated on the full core display.

0 Selects the drifting rod and confirms that RPIS indicates the rod is not at an even reed switch position.

0 Notifies the Shift Supervisor and the STA 0 Refers to 34AB-Cll-004-2, "Mis-positioned Control Rods," for recovery of drifting OR mis-positioned control rod.

0 When directed by the Shift Supervisor, resets the rod drift using the Rod Drift Alarm reset switch on Pane12H11-P603.

A~endix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 2 Page 6 of34 Event

Description:

PRNM 2 out of 4 logic module trips causing a half scram and a control rod to scram in due to a blown fuse.

I Time Position Applicant's Actions or Behavior Note: Either of the following alarms may be addressed first.

CBO

Addresses annunciator Reactor Neutron Monitoring Sys Trip, 34AR-603-109-2.

0 Confirms validity of the alarm by checking the neutron monitoring indicators on pane12H11-P603, 2H11-P606, and 2H11-P60S.

0 Identifies Two Out Of Four Logic Module 2C51-K617 A has tripped. Observes the HIGH/INOP Trip X red LEDs are illuminated.

0 Identifies none of the APRMlOPRMs are tripped.

I 0 Reports the information to the SS.

CBO

Addresses annunciator "Reactor Auto Scram System A Trip," 34AR-603-117-2.

0 Confirm scram group A lights for Trip System A on panel 2H11-P603 are extinguished.

0 Determine the cause of the trip.

0 Attempt to correct or bypass the cause of the trip.

0 Using the Process Computer, run an OD-7 and determine whether control rod movement has occurred.

A~endix 0 Required Operator Actions Form ES-O-2

\

1 Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 2 Page 7 of 34 Event

Description:

PRNM 2 out of 4 logic module trips causing a half scram and a control rod to scram in due to a blown fuse.

Time Position Applicant's Actions or Behavior SS

Notifies maintenance to begin repairs on the "Two Out Of Four Logic" module A.

Notifies maintenance to investigate the cause of the control rod scramming in (possible blown fuse).

Addresses tech specs for the logic module 3.3.1.1-1 2.e 0 Determines a RAS exist per 3.3.1.1-1 A requiring the channel or triP system be placed in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

)

Simulator Operator AFTER being directed to investigate the problem with control rod 14-39, then:

Delete malfunction: mfC12_26 14-39

Call the control room, as electrical maintenance. Inform the team that Time Compression Is Being Used, and REPORT:

0 "The fuse for control rod 14-39 (RPS B side) was blown and it has been replaced."

AImendix 0 Required Operator Actions Form ES-O-2

- ------ .... -- .. ---~~

Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 2 Page 8 of34 Event

Description:

PRNM 2 out of 4 logic module trips causing a half scram and a control rod to scram in due to a blown fuse.

Time Position Applicant's Actions or Behavior Simulator Operator After being called to investigate the problem with the 2 out of 4 voter module:

DELETE override: diC51-K617 A-S2

DELETE override: diC51-K617 A-Sl

Call the control room, as I&C. Inform the team that Time Compression Is Being Used, and REPORT:

0 "The 2 out of 4 voters module was a shorted contact on a switch.

The problem has been corrected."

)

CBO

Resets the half Scram 0 Rotates the Reactor Scram Reset Switch in both directions 0 Scram Group A lights illuminate SS

Direct the STA to confirm compliance Power Distribution Limits per with TS 3.2.

A!mendix 0 Required Operator Actions Form ES-O-2

\

/

Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 2 Page 9 of34 Event

Description:

PRNM 2 out of 4 logic module trips causing a half scram and a control rod to scram in due to a blown fuse.

Time Position Applicant's Actions or Behavior SS,CBO Performs a Control Rod Movement Brief, using Attachment 2 of 34GO-OPS-065-0. Control Rod Movement.

, CBO (R)

Refers to Attachment 2 of 34AB-CII-004-2, "Mis-positioned Control Rods," to recover the control rod.

Withdraws the control rod using both the rod Movement switch and the Rod Out Notch Override switch.

Simulator Operator

After the CBO has referred to attachment 2 of 34AB-C 11-004-2, "Mis-positioned Control Rods 0 "Provide marked up copy of attachment 2 (2 pages) of 34AB-CII-004-2.

CBO

Respond to the following annunciators when received during control rod withdrawal (will be received several times):

0 RBM Upscale or Inop 603-202 0 Rod Out Block 602-238

De-Select and Re-Select control rod 14-39 to clear the alarm.

AQQendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 2 Page 10 of34 Event

Description:

PRNM 2 out of 4 logic module trips causing a half scram and a control rod to scram in due to a blown fuse.

I Time Position Applicant's Actions or Behavior CBO Performs a Coupling Check of control rod 14-39.

SS

Addresses Tech Specs section 3.1.6, "Rod Pattern Control," for compliance with BPWS and determines that LCO 3.1.6 does not apply I

since reactor power is above 10%.

~.

A~endixO Required Operator Actions Form ES-O-2 "JI Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 3&4 Page 11 of34 II Event

Description:

Recirc Pump "A" high vibration, power increase will be stopped and decrease started. Decreasing by 5% power will correct condition.

Time r** Position I Applicant's Actions or Behavior 1 Simulator Operator

At Chief Examiner's direction press (RB-3) to activate:

0 mfB3L41A, "A" Recirc Pump high vibration All

Receives Recirc Pump A High Vibration alarm (602-104)

SS

Directs operator to enter 34AR-602-104-2.

CBO

Enters 34AR-602-104-2 0 Depresses the Hi vibration reset pushbutton and determines that the alarm does not clear.

0 Notifies the SS that the vibration alarm did not clear.

0 Notifies the SS that the ARP requires reducing Recirc flow and attempting to reset the alarm again.

SS

Directs the operator to reduce Rx power with Recirc per 34GO-OPS-005 and 34S0-B31-001-2, exceeding 10 MWE/minute if necessary.

Reminds the operator that entry into the immediate exit region of the Power to Flow map is allowed.

Notifies Plant Management, Load Dispatcher, and Engineering that the power increase has been halted pending investigation of Recire Pump "2A" high vibration condition.

A~endixO Required Operator Actions Form ES-O-2

/

Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 3&4 Page 12 of34 Event

Description:

Recirc Pump "A" high vibration, power increase will be stopped and decrease started. Decreasing by 5% power will correct condition.

Time Position Applicant's Actions or Behavior CBO

Enters the following procedures 0 34GO-OPS-005-2S, "Power Changes" 0 34S0-B31-001-2S, "Recirculation System" 0 Decreases reactor power with Recirc flow decrease per 34S0-B31-00l-2S by pressing the Master Recirc Flow Control Decrease push-buttons (may use any of the 3 decrease pushbuttons ).

) 0 Monitors power decrease by observing APRM and generator output indications.

0 RBM Downscale (603-211) alarm will be received unless an edge rod is selected CBO

Stops power reduction periodically and depresses the high vibration reset pushbutton.

0 The alarm will not clear until after power is reduced by at least 5%.

Simulator Operator

After power has been reduced by 5%

)

0 Delete mfB3L41A, "A" Recire Pump high vibration."

AQQendix 0 Required Operator Actions Form ES-O-2

- - - --------------------_ .. _----------------- - - - - - ---- -- - - - -.----.--.--------~-~-- ----- - --- - ---- - -- -

Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 3&4 Page 13 of34 Event

Description:

Recirc Pump "A" high vibration, power increase will be stopped and decrease started. Decreasing by 5% power will correct condition.

Time Position Applicant's Actions or Behavior CBO

Depresses the Hi vibration reset pushbutton and determines that the alarm DOES clear.

Notifies the SS that the vibration alarm is clear after reducing Recirc pump speed.

Simulator Operator

)

If Recirc Pump speed is increased to raise power:

0 Enter mfB3 L 4IA,"A" Recirc Pump high vibration

THEN, if Recirc pump speed is subsequently reduced:

0 Delete mfB3L41A, "A" Recirc Pump high vibration SS

Direct the operator to determine whether the plant is in the safe region of the Power to Flow map.

CBO

Determines that the plant is in the safe area of the Power to Flow map.

Simulator Operator Enter the next event now or at the Chief Examiner's direction.

I

AQQendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 5 Page 14 of34 Event

Description:

RWCU line break outside containment. Must be manually isolated, with failure of outboard isolation valve to close.

Time Position Applicant's Actions or Behavior Simulator Operator

At Chief Examiner's direction, press (RB-4) to activate:

0 mfG3L207A, G31-FOOI Fails to isolate on Group 5 0 mfG3L52, RWCU System Leak Note: svoG31071, G31-F004 Valve position was activated at ST=O All * "RWCU System Leak" Alarm, (602-421), is received.

SS

Request SSS to send a RO to Control Room back panel to determine leakage.

I Simulator Operator

If asked to determine leakage, then report:

0 2G31-N615 RWClJ differential t10w indicates 78 gpm.

BOP

Enters 34AR-602-421-2, "RWCU Sys Leak"

Enters 34AB-G31-001-2, "RWCU Isolation" 0 Determines that RWCU should have tripped and isolated.

0 Trips RWCU Pump "2B" 0 Places the control switches for 2G31-FOOI and 2G31-F004 to the CLOSE position.

0 Determines that the RWCU System 2G31-FOOI DID close.

(Critical Task) 0 Determines that the RWCU System 2G31-F004 DID NOT close.

0 Notifies SS that 2G31- F004 will not close.

AQQendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 5 Page 15 of34 Event

Description:

RWCU line break outside containment. Must be manually isolated, with failure of outboard isolation valve to close.

Time Position Applicant's Actions or Behavior BOP .. Enters 34AB-T22-001-1, Primary Coolant System Pipe Break Reactor Building.

.. Contact Chemistry to isolate the autoclave and the Mitigation Monitoring system. (Note the SS may contact Chemistry.)

BOP .. Enters 34AB-T22-001-2, "Primary Coolant System Pipe Break Reactor BUilding."

I 0 Monitor Reactor Water Level.

0 Monitor Reactor power.

0 Confirm all Automatic Actions have occurred.

0 Investigate the extent of damage to the RWCU System.

0 Monitor Reactor Chemistry and continue operations, as allowed by TS.

A~endixO Required Operator Actions Form ES-O-2

)

Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 5 Page 16 of34 Event

Description:

Rweu line break outside containment. Must be manually isolated, with failure of outboard isolation valve to close.

II Time Position Applicant's Actions or Behavior SS

Dispatches SO to determine RWeU leak location.

Dispatches SO/Maintenance to determine why 2G31-F004 did not close.

Directs maintenance to investigate why the RWeU leak detection isolation signal did not close either RWeU isolation valve.

Enters TS for 2G31-FOO4.

Determines that LeO 3.6.1.3.A applies and that the RWeU Line must be isolated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Simulator Operator I

As the SO sent to investigate the RWeU leak, REPORT:

0 "Viewing with the camera, there appears to have been a leak on the non-regenerative heat exchanger as there is water on the floor, but there is no leakage at this time" -----.-.-.------~---

Af22endix 0 Required Operator Actions Form ES-O-2 il Op-Test No_: 2009-301 Scenario No.: 4-04 Event No.: 6 Page 17 of34 II Event

Description:

Loss of Instrument Bus "B" followed by Restoration of Instrument Bus "B" Time I Position I Applicant's Actions or Behavior Simulator Operator

At chief examiners direction press (RB-5) to activate:

0 mfR25_186, 120/208 VAC Inst Bus 2B Fault.

C (ALL)

Diagnose loss of Instrument Bus "B" 0 Loss of top green lights on each DrywelllTorus Vacuum Breaker (P602) 0 Loss of "D" steam flow indication (P603)

RLW decreases to below 32" and then recovers to normaL

) 0 0

RWLC automatically transfers to single element Loss of ASD RPM indication 2B31-R660A and B 0 Loss of2B Recirc Speed indicator (2B31-R661A-l) 0 Loss of 2B Recirc Speed Demand indicator (R661A-2)

The following annunciators will be received:

0 Torus Vacuum Relief Valve F311 Open, 603-251 0 Feedwater Control System Trouble, 603-132 0 Additional annunciators listed in attachment 3 of 34AB-R25-002-2.

SS (TS)

Direct BOP operator to pull and enter 34AB-R25-002-2, Loss of Instrument Buses.

Direct that a System Operator and Maintenance investigate the loss of 2B Instrument Bus.

Determines TS 3.8.7.C applies with a requirement of 8 hrs to restore.

AQ.Q.endix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 6 Page 18 of 34 Event

Description:

Loss of Instrument Bus "B" followed by Restoration of Instrument Bus "B" Time Position Applicant's Actions or Behavior BOP

Pull and enter 34AB-R25-002-2, Loss of Instrument Buses .

0 Call SSS to send an SO and maintenance to investigate the bus loss.

0 Check supply breaker #28 closed on R25-S037.

0 Direct the electrician to check fuses in 2R20N-P002.

Simulator Operator

)

As electrical maintenance, call the control room and report:

0 The fuses in 2R20N*-P002 are blown BOP

Direct the electrician to replace the blown fuses in 2R20N-P002 Simulator Operator

AFTER an electrician is. directed to replace the blown fuses in 2R20N-P002, then:

0 Delete mfR25_186, 1201208 VAC Inst Bus 2B Fault.

THEN

Call the control room as electrical maintenance and REPORT:

! 0 "The fuses have been replaced in 2R20N-P002.

L_ -- ---- - -------- ------- -----_ .. - ._-_ ...... _-_._------_ ...... _----_ ....... _-_ .. _----_ .. ---------------_ .. _--_._ .... _----_ ... _ - - - - - - - - -

AQQendix 0 Required Operator Actions Form ES-O-2

)

Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 6 Page 19 of34 Event

Description:

Loss of Instrument Bus "B" followed by Restoration of Instrument Bus "B" Time Position Applicant's Actions or Behavior Completing all of the tasks listed in 34AB-R25-002-2 will require a large amount time.

It is not expected that all of these tasks will be completed during this scenario, and at the chief examiners direction, proceed to the next event.

Note: the next event is the major event (LOSP).

SS

Direct the BOP operator to restore loads IAW 34AB-R25-002-2.

BOP (C)

Restore loads and plant alignment following power restoration to "2B"

)I Instrument bus.

/IL11 0 Reset group isolation signals using Group Isolation Reset switches 0 Open Fission Product Monitoring isolation valves (P700) 1\[1:)

2Dll-F052

2Dll-F053

2Dll-F072

{\{iJ 0 Reset and return RB ventilation to normal.

0 Reset and return RF ventilation to normal.

1 /,~(i) Confirm Recirc System has returned to normal.

'(~/ 0 Secure SBGT and place it in standby.

0 Restore DW Equipment and Floor Drain sumps.

0 Return the Steam Packing Exhauster to service.

0 Restore Control Building ventilation to normal alignment.

0 Return RWLC to 3 element control.

~---

AQQendix 0 Required Operator Actions Form ES-O-2

~-

- ~---------

)

Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 6 Page 20 of34 Event

Description:

Loss of Instrument Bus "Boo followed by Restoration of Instrument Bus "Boo Time Position Applicant's Actions or Behavior Simulator Operator

If the team calls Unit 1 to have the Unit 1 actions performed to reset Secondary Containment Isolation, then press (RB-6) to activate:

0 rfT41-299, Unit IRefuel Floor Vent Logic Reset

AQQendix 0 Required Operator Actions Form ES-O-2

)

,.. Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 7A Page 21 of34 Event

Description:

Loss of Startup Transformer "2D".

Time I Position I Applicant's Actions or Behavior Simulator Operator

At Chief Examiner's Direction press (RB-7) to activate:

0 mfCl L30B; Control Rod Drive Pump B Trip 0 mfP64_193B; Drywell Chiller Compressor B FAIL 0 mtR22-182; 4KV Bus 2E Fault 0 mfSlL227B; SAT 2D Failure 0 diR22-135574C; Contr SW ACB 135574 (4KV 2F Norm Brkr) 0 mfR43_168A; Diesel Gen Tie Brk Fails Auto Close 2A Note: mtR43_167C, Diesel Gen Fail to Start 2C was active since the beginning of the scenario.

SS Enters the RC flowchart due to low reactor water level (RWL) and assigns the following tasks Note: the SS may assign one operator to perform Scram procedure placards RC-l, RC-2 and RC-3.

Assigns the CBO to perform RC-l.

Assigns the BOP operator to perform RC-2 and RC-3.

If time allows assigns TC-l to be performed.

CBO

Performs RC-l consisting of:

AQQendix D Required Operator Actions Form ES-D-2

)

Op- Test No.: 2009-301 Scenario No.: 4-04 Event No.: 7A Page 22 of34 Event

Description:

Loss of Startup Transformer "2D".

Time Position Applicant's Actions or Behavior 0 Inserts a manual scram.

0 Places the mode switch to shutdown.

0 Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

0 Notifies the SS of rod position check.

0 Places SDV isolation valve switch to "isolate" & confirms closed.

0 Inserts SRMs and IRMs.

0 Shifts recorders to read IRMS, when required.

0 Ranges IRMS to bring reading on scale.

0 Notifies the SS when the above actions are complete.

)

BOP Note: the operator will delay performing some RC-2 actions due to lack of power to the Feedwater system.

Performs RC-2 actions consisting of:

0 Confirms proper Level Control response:

0 Checks ECCS Injection Systems and secure as necessary.

0 Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.

0 IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.

AQQendix 0 Required Operator Actions Form ES-O-2

-~--.~ ~----

-~---.~----.-.--------- -- --- - ------------_ ... _------

'\

Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 7A Page 23 of34 Event

Description:

Loss of Startup Transformer "2D".

Time Position Applicant's Actions or Behavior BOP

When feed flow is less than the capacity of the SID level control valve

(;::: 1.5 mlbmfhr), then:

0 Opens 2N21-F125. No power.

0 Places 2C32-R619, FW SID level control valve controller, in Auto, set at approximately 9 inches.

0 Closes 2N21-FllO. No power.

0 Identifies that no Condensate or Condensate Booster pumps are operating. No power.

0 If time allows, places switches for all the Condensate and Condensate Booster pumps may in the Trip or Pull-to-Lock position.

)

\

)

AQ.Qendix D Reguired Operator Actions Form ES-D-2 j

Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 7A Page 24 of34 Event

Description:

Loss of Startup Transformer "2D".

Time Position Applicant's Actions or Behavior BOP

Recognizes the MSIVs have closed.

Recognizes RCIC trip.

Recognizes that HPCI did not START.

See event 7C BOP

Performs RC-3 consisting of:

0 Monitor RPV pressure.

0 Confirm proper operation of pressure control system (TBV, LLS, etc.). No power 0 If necessary, allows RPV pressure to exceed 1074 psig then cycles any SRV to initiate LLS.

) 0 Maintain RPV pressure between 1074 and 800 psig.

0 Notify SS of pressure control system operation.

SS

Directs the CBO to address the plant electrical systems and enter:

0 34AB-R22-003-2, "Station Blackout" 0 34AB-R43-001-2, "Diesel Generator Recovery"

Calls for maintenance support in restoring emergency 4160 V AC buses.

.--.---- .. -------~-

AQQendix 0 Required Operator Actions Form ES-O-2

)

Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 7A Page 25 of34 Event

Description:

Loss of Startup Transformer "2D".

Time Position Applicant's Actions or Behavior I

CBO

Confirms Diesel Generator response:

0 "2A" EDG is running, but not tied to "2E" 4160VAC Bus.

0 "lB" EDG is running, but not tied to "2F' 4160VAC Bus.

Standby Service Water Pump is running .

0 "2C" EDG is not running.

i i

) CBO

Evaluates the emergency buses:

0 "2E" is de-energized.

0 "2F" is energized from SAT 2C.

0 "2G" is de-energized.

A~endixD Required Operator Actions Form ES-D-2

~*~h Ii

/11 Op-Test No.: 2009*301 Scenario No.: 4*04 Event No.: 7B Page 26 of34 Event

Description:

4160 VAC 2G Manually Energized from Startup Transformer "2C".

Time I Position I Applicant's Actions or Behavior CBO

Enters 34AB-R22-003-2, "Station Blackout."

Enters 34AB-R43-001-2, "Diesel Generator Recovery."

CBO May attempt to close the "2A" EDG output breaker using 34AB-R43-001-2, Diesel Generator Recovery, Attachment 2 (or placard).

Ask is the diesel running unloaded? Yes

Confirms the normal and alternate supply breakers are open.

Lowers EDG frequency to 57 hz, then raise to 60 Hz.

Recognizes the EDG breaker closed and tripped open.

Did the Emergency Bus energize? NO

Refers to 34AB-R43-001-2.

Calls for Maintenance assistance. Time:

Simulator Operator

After 10 minutes has elapsed from the time of the call for assistance with the "2E" 4160 V AC Bus, call the control room as Electrical Maintenance in the EDG bldg and REPORT:

0 "The "2E" bus appears to have a hard short between two main bus bars. Length of time necessary to resolve the problem is unknown at this time."

AQ.Qendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 7B Page 27 of34 Event

Description:

4160 VAC 2G Manually Energized from Startup Transformer "2C".

Time Position Applicant's Actions or Behavior Simulator Operator

AFTER the 86 lockout has tripped for the "2G" 4160 V AC bus, THEN:

0 DELETE diR22-135584C; Contr SW ACB 135574 CBO In addressing "G" 4160 VAC bus the operator may use Attachment 2 (or placard) of 34AB-R43-001-2, Diesel Generator Recovery which directs the operator to determine and perform the following steps:

Is the diesel running unloaded? NO

Is the Auto Start System operative light lit: NO

,

Confirms the normal and alternate supply breakers are open.

I I

Depresses the EDG Shutdown Relay logic push-button (normally auto start occurs in 110 seconds, in this case the EDG will not start)

Did the EDG start? NO

Is the Auto Start System Operative light lit? NO

Direct operator at the EDG building to locally start the "2C" EDG Time:

Simulator Operator

After 4 minutes has elapsed from the call concerning the "2C" EDG, call the control room as the SO in the EDG bldg and REPORT:

0 "The "2C" EDG will cannot be started locally."

)

AJ2J2endix D Required Operator Actions Form ES-D-2

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/

Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 7B Page 28 of34 Event

Description:

4160 VAC 2G Manually Energized from Startup Transformer "2C".

Time Position Applicant's Actions or Behavior SS May confirm with electrical maintenance that 4160 VAC bus is ready to be re-energized. (see the next Simulator Operator direction)

Directs the CBO to reset the LOSP relay for "2G" 4160 VAC bus.

)

Simulator Operator

If electrical maintenance is called to determine if there is a fault on the "2G" 4160 VAC bus, then REPORT:

0 "No faults are apparent. No relays are tripped to indicate an electrical ground or over-current condition."

If asked whether the bus may be energized, then 0 "From an electrical safety and equipment damage point of view, the bus is ready to be energized."

~--- ,-- ----- .. _- -------------------_ .. - --- --------------------------------------_._------_ .. _ - - - - - - - - - - - - - - - - - - -

Af412endix D Required Operator Actions Form ES-D-2

)! Op* Test No.: 2009*301 Scenario No.: 4*04 Event No.:

7B Page 29 of34 Event

Description:

4160 VAC 20 Manually Energized from Startup Transformer "2C".

Time Position Applicant's Actions or Behavior CBO

Addresses 34AB-R22-002-2, Loss of Emergency Bus 0 Direction is provided to energize "20" 4160 bus from SAT "2C" using 34S0-R22-001-2, "4160 VAC System."

Addresses 34S0-R22-001-2, "4160 VAC System" for Restoration of power to 4160 VAC Emergency Bus (2E, 2F, 20) from Alternate power Supply (2C).

0 Confirms power available to SAT 2C.

0 Confirms requirements are met to reset SAT 2C lockout relay.

(see the next Simulator Operator direction) 0 Direct reset of SAT 2C lockout relay at Bus 2R22-S00S.

0 Confirms requirements are met to reset LOSP lockout relay.

) 0 Requests permission from the SS to reset the LOSP relay for "20" 4160 V AC bus 0 Hold 4160 VAC Bus 20 LOSP lockout relay in RESET.

0 Confirm the 4160 VAC bus 20 Alternate Supply breaker closes.

0 Place the Alternate Supply breaker to the close position.

Simulator Operator

If directed to reset the lock out relay for SAT 2C, REPORT:

0 "The lockout relay for SAT 2C is NOT tripped"

AQQendix D Required Operator Actions Form ES-D-2

/

Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 7B Page 30 of34 Event

Description:

4160 VAC 20 Manually Energized from Startup Transformer "2C".

Time Position Applicant's Actions or Behavior CBO

Confirms "2B" PSW Pump starts

Confirms 2P41-F316 Band D automatically close i

I CBO

Addresses 34AB-R23-001-2, Loss Of 600 Volt Emergency Bus, for I "c" and "D" 600VAC buses. I

Resets the non-essential load lock-outs on 2Hll-P652

Directs the SSS close breakers fed from 600 VAC systems such as:

I 0 1251250 VDC battery chargers.

0 Reactor Protection System power supply.

0 Station Service Air Compressors.

0 Reactor Building Closed Cooling Water pump.

I Simulator Operator

When requested to perform remote actions to send operators out to help in restoration of 600 VAC bus loads, THEN perform the remote functions to restore (Ol"JL Y perform the actions for those systems specifically requested):

) 0 Station Service Battery Chargers 0 Vital AC Battery Charger 0 RPS power restoration 0 Station Service Air Compressor

AQQendix 0 Required Operator Actions Form ES-O-2

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Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 7B Page 31 of34 Event

Description:

4160 VAC 20 Manually Energized from Startup Transformer "2C".

Time Position Applicant's Actions or Behavior I

SS

Enters the PC EOP Flowchart due to high Drywell pressure (1.85 psig)

An assigns the following actions:

Directs the operator to restore drywell chillers and coolers per 31EO-

) EOP-I00-2, Miscellaneous Emergency Overrides.

Simulator Operator

AFTER being directed to restore DW chillers AND AFTER DW pressure has exceeded 1.85 psig:

I 0 DELETE mfP64_193B, "Drywell Chiller Compressor B FAIL" i

CBO

Restores drywell chillers per 31EO-EOP-100-2 section 3.7 by:

0 Verifies drywell temperature is below 250 Fusing SPDS and/or 0

recognizes there is not a leak in primary containment.

0 Place 2P64-S3, LOCA Override Switch, to BYPASS on panel 2Hll-P700 0 Has the SSS open links:

Upper TB 1-11, 2R22-S007 Fr. 7 ,2P64-B006B 0 Directs the SSS reset 86 lockout relays on drywell chiller breaker

A.l2.Rendix D Required Operator Actions Form ES-D-2

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Op*Test No.: 2009*301 Scenario No.: 4*04 Event No.: 7B Page 32 of34 Event

Description:

4160 VAC 2G Manually Energized from Startup Transformer "2C".

Time Position Applicant's Actions or Behavior on 4160V bus and "G" (2R22-S007 Fr. 11) 0 May have the SSS to reset the POR relay for each chiller.

0 Monitors for chiller start by observing the red light on 2HII-P700 or input from the SSS.

~

Restores the drywell coolers per 31EO-EOP-I00-2 section 3.6 by:

0 Verifies drywell temperature is below 250 OF on SPDS and/or recognizes there is not a leak in primary containment.

0 Place drywell cooling fans system B key-lock LOCA override switch to BYPASS on 2Hll-P654.

0 Observes the drywell cooler fans start by observing their red lights illuminating on 2HII-P654.

_._------ ~ L ..

AQQendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-301 Scenario No.: 4-04 Event No.: 7C Page 33 of34 Event

Description:

BPCI must be manually started.

Time Position Applicant's Actions or Behavior NOTE:

The following 2 malfunctions were entered at ST-O:

0 mfE4L235A (BPCI Fails To Auto Start On Low Level) 0 mfE41-_235B (BPeI Fails To Auto Start On Bi DryweIl Press)

BOP

Recognizes that BPCI failed to Auto Start and Starts BPCI (CRTICAL TASK) HPCI is the only high pressure injection system, perform this action prior to emergency depressurization being required due to lowing level.

BOP

Recognizes BPCI fails to auto start at -35" or 1.85 psig DW pressure and manually starts per 34S0-E41-001-2, prior to emergency depressurization.

0 Opens 2E41-F059, Lube Oil Cooling Wtr Vlv.

0 Starts 2E41-C002-2, Barometric Condenser Vacuum Pump.

0 Opens 2E41-FOOl, Turbine Steam Supply Vlv 0 Takes 2E41-C002-3, Aux Oil Pump, control switch to the START position.

0 Opens 2E41-F006, Pump Discharge Valve.

BOP

Confirm the following valves OPENED:

0 Turbine Control Vlv 0 Turbine Stop Vlv

Recognizes that the flow controller has failed low

Places flow controller in manual and adjust as required to achieve the following

Confirm the turbine comes up to speed

Confirms 2E41-F012, Min Flow Vlv, closed.

Adjust flow with 2E41-R612, Flow Control to maintain water level.

AQQendix 0 Required Operator Actions Form ES-O-2 Op- Test No.: 2009-301 Scenario No.: 4-04 Event No.: 7C Page 34 of34 Event

Description:

BPCI must be manually started.

Time Position Applicant's Actions or Behavior BOP

When LLS is initiated to control Rx pressure, RWL may go above 52",

if so, the BPCI high water level trip will have to be reset to inject with BPCI prior to -35".

BOP

Continues manual control of BPCI to maintain RWL.

With Chief Examiners pennissilon:

I

The Scenario will be stopped when:

0 "20" 4160 V AC Emergency Bus is energized AND one of the following:

0 HPCI is being used for RWL control OR 0 The Plant has been emergency depressed and Low pressure ECCS is being used for RWL control

ML091730171

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