ML082530401

Retake Exam Draft - Section C Operating Exam (Folder 2)

ML082530401
Person / Time
Site:	Oyster Creek
Issue date:	06/12/2008
From:	- No Known Affiliation, Operations Branch I
To:	D'Antonio J Operations Branch I
Shared Package
ML081630455	List: IR 05000219/2008302 ML081640460 ML082250262 ML082490762 ML082490766 ML082530401 ML082530408 ML082530420 ML083220038 ML083240604
References
Download: ML082530401 (60)

Text

OC NRC Re-Take Exam 2008 Scenario Outline c

Facility: Oyster Creek Scenario No.: NRC 1 Op Test No.: NRC 2008-1 Examiners: Operators: SRO-Steve Johnston Initial Conditions:

100% Power RWCU Pump B 0 0 s RWM is bypassed and 00s Turnover:

e Perform 602.4.004, Main Steam Isolation Valve 10% Closure Test.

Event Malf. No. Event Event No. TY Pe* Description SRO Performs 602.4.004, Main Steam Isolation Valve 10%

1 NIA BOP Closure Test.

MSlV NS04B sticks open during Closure Test 2 VLV-RPS004 TS SRo TS 3.5.3.

C SRO Respond to Loss of USS 1A2 480V bus.

3 MAL-EDSO036 TS BOP TS 3.7.B, ABN-45 LOSSof USS 1A2 SRO APRM 6 hop. Failure causes 1/2 scram 4 MAL-NIS021F I RO RAP-G2f 5

MAL-CRD005-22-15 I IRO I SRO Control Rod Drift Out ABN-6 Control Rod Malfunctions SRO Respond to trip of Service Water Pump 1-2 6 MAL-SWS001B c BOP ABN-18 Service Water Failure Response I Main Condenser Vacuum Leak i

7 MAL-CFWOI 7 SRO Power Reduction required RO ABN-14 Loss of Condenser Vacuum 1.

RWCU Leak in the Reactor Building MAL-RCUO13 RWCU fails to isolate 8 VLV-RCU001 ALL VLV-RCU004 Secondary Containment Control EOP Emergency Depressurization required MAL-CNS004A SRO 9 or B or C or D A Containment Spray pump trips while in Torus Cooling DAD

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 1 Page 1 of 27

OC NRC Re-Take Exam 2008 NRC 1 Simulator Scenario Summary Event Event Summary 1 The plant is at rated power. The BOP will peform 602.4.004, Main Steam Isolation Valve 10% Closure Test, for two MSIVs.

2 MSlV NS04B will stick open during the closure test requiring a TS 3.5.3 entry (TS-SRO) 3 The crew will respond to loss of the USS 1A2 480V Bus. Actions include starting RBCCW 1-2, CRD pump B and swapping RPS power supplies. The SRO will address TS 3.7.6. (TS-SRO) 4 The ATC will respond to an INOP failure of an APRM. The APRM must be bypassed and the % scram reset. TS will be reviewed by the SRO (no LCO required).

5 The ATC/BOP respond to indications of a single control rod drifting out. ABN-6, Control Rod Malfunctions, Section 5.0, will be entered.

The ATC will insert the control rod, which indicates still drifting out.

The BOP will scram the individual control rod from a back panel.

The control rod will be isolated and the SRO will declare the control rod inoperable, and will verify 6 inoperable control rods IAW TS 3.2.6.4.

6 The BOP will respond to a trip of running service water pump 1-2.

Actions will be taken IAW RAP-Klf and ABN-18 Service Water Failure Response to start the standby pump.

7 The crew will diagnose and respond to a loss of Main Condenser Vacuum IAW ABN-14 Loss of Condenser Vacuum. The SRO will direct a power reduction to maintain vacuum. The RO will reduce reactor power with recirc flow and condenser vacuum will stabilize.

8 The Crew will respond to an unisolable Reactor Water Cleanup System leak in the Reactor Building. Before any area temperature reaches MAX SAFE, the SRO will direct a manual scram, which will be successful. When two areas exceed the MAX SAFE temperature values, the SRO will direct emergency depressurization. (MAJOR TRANSIENT) 9 Following entry into in Primary Containment Control EOP due to high torus temperature from EMRC operation, a Containment Spray pump will fail to start while being placed in Torus Cooling, requiring the start of an alternate pump.

NRC 1 Page 2 of 27

OC NRC Re-Take Exam 2008 I

1 Critical Task#I I Scram before any area temperature reaches MAX SAFE.

1 2:;;; 1 ED when 2 2 area temperatures exceed MAX SAFE. (PRA)

NRC 1 Page 3 of 27

OC NRC Re-Take Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 1 Events No.: 1 & 2 Event

Description:

1. Perform 602.4.004, Main Steam Isolation Valve 10% Closure Test.

2. MSlV NS04B Fails to close during surveillance test.

1 Initiation: As directed by the Lead Examiner.

1 Cues: Position indication for MSlV NS04B do not change.

Position Applicants Actions or Behavior SRO 0 Directs performance of surveillance 602.4.004. beginning at step 6.3.4 0 Declares MSlV NS04B inoperable when valve V-1-10 fails to close 0 Reviews/applies Tech Specs 3.5.3.a.

o LCO- Restore within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to operable status or isolate the steam line within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 0 Notifies Work Week ManagerIShift Manager ( W M / S M ) for investigationhepair Updates the Crew BOP 0 Performs surveillance 602.4.004, starting at step 6.3.4 Test of NS03B Simultaneously perform the following two steps:

Depress and hold TEST button for Valve V-1-0008 NS03B (Panel 11F).

Start the stopwatch.

Observe the Red open indicating light Extinguishes for NS03B.

When half scram signal is received, then simultaneously perform the following two steps:

0 Release the TEST button.

Stop the stopwatch.

0 Record stroke time 0 Verify relays 2K17 and 2K18 (Panel 7R) de-energized and all contacts opened.

0 Verify Plant Process Computer, PID: SOE47, tripped; MSlV NRC 1 Page 4 of 27

OC NRC Re-Take Exam 2008 CLOSURE SCRAM (2K17).

a Verify Plant Process Computer, PID: SOE48, tripped; MSlV CLOSURE SCRAM (2K18).

a Verify that the MSlV returns to the fully open position by the red open light illuminating.

a Verify SCRAM SOLENOIDS lights (Panel 7R) extinguished.

a Verify SCRAM CONTACTOR OPEN alarm (G-I -c) is received.

a Verify MSlV CLOSED II alarm (J-2-a) annunciated.

a Verify MN STM VLVS OFF NORMAL alarm (J-8-b) annunciated.

a Verify relays 2K51 A and 2K52A (Panel 7R) are de-energized.

a Reset the half scram.

a Confirm Plant Process Computer PlDs returned to normal state.

a Confirm Alarms returned to normal state.

a Verify all SCRAM SOLENOID lights lit (4F17R).

a Verify SCRAM CONTACTOR OPEN alarm (G-I -c) clear.

a Verify MSlV CLOSED II alarm (J-2-a) clear.

a Verify MN STM VLVS OFF NORMAL alarm (J-8-b) clear.

a Verify relays 2K17 and 2K18 (Panel 7R) energized.

a Verify relays 2K51A and 2K52A (Panel 7R) energized.

a Verify Plant Process Computer PlDs SOE47 and SOE48 are normal.

Test of V-I -10 NS04B Simultaneously perform the following two steps:

Depress and hold TEST button for Valve V-1-01 NS045 (Panel 1 1 F).

Start the stopwatch.

Observe the Red open indicating light extinguishes for NS04B.

Observes the valve failed to close Reports failure of valve to SRO ATC Acts as peer checker during the surveillance Terminus: MSlV NS04B is declared inoperable and TS have been applied.

NRC 1 Page 5 of 27

OC NRC Re-Take Exam 2008 Notes/Comments I E NRC 1 Page 6 of 27

OC NRC Re-Take Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 1 Event No.: 3 Event

Description:

Loss of 480V Bus USS 1A2 [TRIGGER I]

Initiation: As directed by Lead Examiner Cues: Annunciators U3a, 1A2 MN BRKR TRIP; S7f, FDR TO 460V 1A2 TRIP; M Scram Time Position Applicants Actions or Behavior SRO 0 Directs entry into ABN-45, Loss of USS 1A2 0 Reviews Tech Specs o 3.7.B (AC Electrical Power)

The reactor shall be placed in cold shutdown in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> o

3.7.D.3 (Batteries)

Restore the inoperable battery to operable within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, The reactor shall be placed in cold shutdown in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> o 3.8.D (Isolation Condensers)

The reactor shall be placed in cold shutdown in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> o 3.5.A.3 (Containment)

For RBCCW valve V-5-167 Restore or isolate within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or shutdown in the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0

o 3.4.D (CRD) 7 day LCO, Check operating pump every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Notifies WWM/SM for repair/investigation of USS 1A2 0 Makes notifications for TS required shutdown BOP 0 Responds to Annunciators U3a, 1A2 MN BRKR TRIP; S7f, FDR TO 460V 1A2 TRIP 0 Reports loss of USS 1A2 0 Performs ABN-45 o Starts RBCCW Pump 1-2 running by placing its control switch to START o Starts CRD Pump B running by placing its control switch to START o Confirms DW Cooling Recirculation Fans 1-4, and 1-5 running o Secures Reactor Building Ventilation NRC 1 Page 7 of 27

OC NRC Re-Take Exam 2008 Confirms V-28-42 and V-28-43 CLOSED, RB Ventilation Isolation Inlet to Drywell Confirms RB Ventilation Supply Fan SF-1-14 tripped Confirm RB Exhaust Fan EF-1-6 tripped Position EXH VALVES TO MAIN EXHAUST switch to CLOSE Verify Reactor Building Exhaust Main Isolation Damper, V-28-21 closed Verify Reactor Building Exhaust Main Isolation Damper, V-28-22 closed Verify RB Ventilation Supply isolation Valves o V-28-1 andV-28-2 o V-28-3 and V-28-4 o V-28-5 and V-28-6 o V-28-7 and V-28-8 o V-28-9 and V-28-10 o V-28-11 and V-28-12 o V-28-13 and V-28-14 o V-28-15 and V-28-16 o V-28-38 and V-28-39 o Starts Standby Gas Treatment System 2 Places STANDBY GAS SELECT switch in SYS 2 position Starts EF 1-9 by placing SGTS System Exhaust Fan control

. switch to HAND position Verifies:

o EF 1-9 starts o V-28-27 opens o V-28-28 opens

. o V-28-30 opens After flow is established, verifies:

o V-28-28 closes

. o V-28-24 opens Places SGTS Cross-Tie Valve, V-28-48 switch to CLOSE o Re-energizes Protection System Panel 1 [ROLE PLAY]

Directs the EO to perform the following:

o Confirm disconnect switch SW-733-169 is off and Kirk Key removed o Confirm Kirk Key inserted and disconnect switch SW-733-170 is on NRC 1 Page 8 of 27

OC NRC Re-Take Exam 2008 o Confirm EPA breaker 5 and 6 closed Verifies TRANSFORMER OUTPUT green OFF light is lit above RPSI POWER SELECT switch (Panel 6R)

Places RPSI POWER SELECT switch to TRANS position Verifies TRANSFORMER OUTPUT red ON light is lit above RPSI POWER SELECT switch Resets 1/2 scram by pressing SCRAM SYSTEM RESET pushbutton Resets main steam isolation by pressing MAIN STEAM ISOLATION RESET pushbutton APRM lights APRM flow converters Main Steam Line Radiation Monitors Verifies FCTR card status is green and curve selected to 0 Verifies annunciator 9XF3a is clear Verifies auto restart of DCC-Y computer (NOT modeled)

Confirms VLDP-1 transferred to VMCC 1B2 by verifying annunciator 9XF1c is received Informs the SRO of Tech Specs 3.7 for inoperable valves V-14-33 and V-14-35 (Isolation Cooling B steam inlet and condensate return)

Informs SRO to declare C Battery inoperable Monitors DC Bus C voltage ATC 0 Starts CRD Pump B running by placing its control switch to START 0 Directs EO to investigate USS 1A2 and its feeder breaker 0 Makes announcement of loss of bus, % scram ROLE To re-energizes Protection System Panel 1 from USS 1B2:

PLAY 0 to open disconnect switch SW-733-169, insert LOA-EDSI 33 to OPEN 0 to close disconnect switch SW-733-170, insert LOA-EDSI 33 to 1B2 0 to close EPA 5 and 6 breakers, insert LOA-RPS007 to CLOSE When performed, notify the control room: Transformer PS-1 is lined-up to the Bus USS 1B2.

0 If the SRO orders a reactor shutdown started with the loss of USS 1A2, call him as the SM and tell him to leave the plant at its present power to give electrical maintenance a chance to correct the problem.

NRC 1 Page 9 of 27

OC NRC Re-Take Exam 2008 ABN-45 has been performed and the SRO has addresses Technical Specifications.

Notes/Comments NRC 1 Page 10 of 27

OC NRC Re-Take Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 1 Event No.: 4

==

Description:==

APRM 6 INOP [TRIGGER 21 Initiation: As directed by Lead examiner Cue: Annunciators G2f, APRM HI-HIANOP: G2d: CHANNEL II Time Position Applicants Actions or Behavior ATC Responds to annunciator G2f, APRM HI-HIANOP; G2d, Channel II o Reports 1/2 scram RPS System 2 o Reports APRM 6 is upscale and other APRMs indicate normally Bypasses APRM 6 by placing APRM BYPASS in CH 6 position (Panel 4F)

Resets 1/2 scram by depressing SCRAM SYSTEM RESET pushbutton (Panel 4F)

Reports APRM bypassed and 1/2 scram reset BOP 0 Makes a plant announcement for the 1/2 scram Checks APRM 6 on back panel and reports upscale indication (Panel 5F)

SRO 0 Directs bypassing APRM 6 IAW procedure 403 and resetting 1/2 scram May request Attachment 403-2 updated.

0 May review TS 3.1 (no action required) 0 Notifies WWM/SM for APRM 6 repair ROLE When requested, provide the SRO with the completed Attachments 403-2, PLAY 3, and 4 and the blank 403-2.

Terminus: APRM 6 is bypassed and 1/2 scram reset.

NRC 1 Page 11 of 27

OC NRC Re-Take Exam 2008 Notes/Comments NRC 1 Page 12 of 27

OC NRC Re-Take Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 1 Event No.: 5

==

Description:==

Control Rod 22-15 Drifts Outward [TRIGGER 31 Initiation: As directed by Lead Examiner Cue: Annunciator H6a, ROD DRIFT Time Position Applicants Actions or Behavior ATC 0 Reports 1 control rod drifting outward (22-15) 0 Refers to annunciator response H6a 0 Refers to ABN-6 Control Rod malfunctions 0 Confirms Rod Power Switch is ON Selects 22-15 0 Applies an insert signal to 22-15 to position rod back to 12, then releases switch Recognizes outward motion continues and reports to SRO 0 Applies continuous insert signal 0 After BOP action to scram rod, removes insert signal 0 Recognizes rod remains at 00 and directs EO to isolate the HCU Turns Rod Power OFF 0 Notifies Chemistry (to sample) and Reactor Engineering Monitors for fuel failures 0 Informs SRO to consult TS 3.2.

BOP Scrams CR 22-15 IAW procedure 302.2 Control Rod Drive Manual Control System [BOOTH]

SRO 0 Directs entry to ABN-6 0 Refers to TS 3.2.B.4, declares Control Rod 22-15 inoperable; verifies <6 inoperable control rods 0 Notifies WWM/SM about the control rod drift BOOTH When the control rod indicates a scram condition DELETE the rod drift malfunction.

NRC 1 Page 13 of 27

OC NRC Re-Take Exam 2008 Terminus: Control Rod 22-15 is at 00 and scrammed; TS have been addressed.

Notes/Comments

~ - 1 NRC 1 Page 14 of 27

OC NRC Re-Take Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 1 Event No.: 6 Even

Description:

Service Water Pump 1-2 Trip [TRIGGER 41 Initiation: As directed by Lead Examiner Cue: Annunciator Klf, SVC WATER PUMP TRIP; Breaker open indication for Service Water Pump 1-2; Service Water pressure indication downscale Time Position Applicants Actions or Behavior BOP 0 Responds to annunciator K l f 0 May suggest entry into ABN-19, RBCCW Failure Response Reports Service Water Pump 1-2 has tripped 0 Performs ABN-18, Service Water Failure Response o Starts Service Water Pump 1-1 by placing SERVICE WATER PUMP 1-1 switch to START o Reports service water flow re-established 0 Dispatches EO to check SW pump 1-1 and 1-2 0 May refer to ABN-18, Service Water Failure Response 0 Notifies WWM/SM about SW Pump 1-2 Trip ROLE Report back as EO, SW pump 1-2 motor is hot to the touch. Report a good PLAY start on Service Water Pump 1-1.

Terminus: I Service water pump 1-1 has been started Notes/Comments I 1 NRC 1 Page 15 of 27

OC NRC Re-Take Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 1 Event No.: z Even

Description:

Main Condenser Vacuum Leak; Power Reduction required

[TRIGGER 51 Initiation: As directed by the Lead Examiner Cues: Annunciator: Q3c Cond Vac Lo 25 inches, Generator MWe decreases Time Position Applicants Actions or Behavior BOP 0 Recognize condition by observing indications or reporting alarms 0 Responds to RAP Q3c: COND VAC LO 25 INCHES I 0 Responds to ABN-14 Loss of Condenser Vacuum Monitors vacuum 0 Confirms Circ Water pumps operating Confirms SJAEs operating Confirms Gland seal system operating Confirm vacuum breaker V-2-44 is closed 1 SRO 0 Directs entry into ABN-14, Loss of Condenser Vacuum.

0 Directs a power reduction as necessary to maintain vacuum greater than 22 inches I 0 Makes notifications for power reduction.

Ro I 0 Performs a Rapid Power Reduction as directed in ABN-14 by reducing Recirc Flow to not lower than 8.5 X I O 4 gpm BOOTH 1 Set Condenser Leakage to 0 when power reduction begins.

Terminus: I Rapid Power Reduction Complete, Condenser Vacuum Stable.

NRC 1 Page 16 of 27

OC NRC Re-Take Exam 2008 Notes/Com ments I E NRC 1 Page 17 of 27

OC NRC Re-Take Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 1 Event No.: 8 Event

Description:

Unisolable leak in the Reactor Water Cleanup Svstem leading to a manual scram and Emergencv Depressurization (or anticipated ED and rapidlv depressurizes the RPV), [TRIGGER 61 Initiation: As directed by Lead Examiner Cues: Annunciators L ~ cRB , AP LO; 10F3k, CU SYS AREA HI; 1OF1k, AREA MON HI; D8d, CU ROOM TEMP HI; DldlD2d: RWCU HELB I and II Time Position Applicants Actions or Behavior SRO Directs entry into Secondary Containment Control EOP on RB AP low Directs BOP to Perform SP-50 to start RB HVAC System Directs RO to monitor RB area temperatures and radiation levels Directs re-entry into Secondary Containment Control EOP o Directs RWCU isolation o Directs WWM/SM/NLOs notified to close the RWCU valves o Before any area temperature reaches MAX SAFE, directs manual scram and entry into RPV Control - No ATWS

.EOP and ABN-1 Reactor Scram (CRITICAL TASK)

Following the scram, directs RPV water level 138 -

175 using Support Procedure 2 (Feedwater) and/or

. Support Procedure 3 (CRD)

Directs performance of Support Procedure 1,

. Confirmation of Automatic Initiations and Isolations May direct RPV pressure band 500 - 600 psig with turbine bypass valves to reduce leak driving head o When 1 area temperature is above MAX SAFE, may declare Emergency Depressurization is anticipated Directs ROPS bypassed Directs turbine bypass valves opened and/or directs Isolation Condensers placed into service (IAW SP-11)

Directs the Reactor Building evacuated When second area temperature is reported above MAX SAFE, directs entry into Emergency Depressurization - No ATWS EOP (CRITICAL TASK)

NRC 1 Page 18 of 27

OC NRC Re-Take Exam 2008 o Directs ROPS bypassed o Verifies torus water level > 90" o Directs all EMRVs open o Recogizes < 5 EMRVs are open o IF 5 EMRVs are OPEN, and RPV pressure is 50 psig >

Torus pressure, directs other RPV depressurization methods (if not already in service):

Isolation Condensers IAW SP-11

.. Turbine Bypass Valves RWCU in Recirc Mode IAW SP-13

. RWCU in Letdown Mode IAW SP-14 Isolation Condenser Vents IAW SP-52

' Shutdown Cooling BOP 0 Responds to annunciator L ~ cRB , AP LO o Reports RB HVAC is shutdown and RB AP is >O" 0 Performs SP-50, Reactor Building Ventilation Restart o Verifies REACTOR BUlLlDNG VENT MANIFOLD NO. 1 and 2 are < 9 mrem/hr (Panel 2R) o In rear of Panel 1I R :

Removes EOP BYPAS PLUG from BP4

' Inserts EOP BYPAS PLUG into BPI o Opens EXH VALVES TO MAIN EXHAUST V-28-21 and B 28-22 by placing its control switch to OPEN (Panel 11R) o Resets RB Ventilation System by depressing RX BLDG VENT ISOLATION pushbutton o Starts REACTOR BUILDING EXHAUST FAN 1-5 by placing its control switch to START o Confirms MAIN SUPPLY HEADER VALVES TO DW V-28042 and V-28-43 are closed o Starts SUPPLY FANS 1-12 and 1-14 by placing their control switches to ON 0 Responds to Area Radiation Monitors alarms o Reports RWCU area radiation rising o Announces area of rising radiation over the PA System, if directed o Monitors RWCU area temperatures (Panel IOR) o Reports RWCU area temperatures rising 0 Responds to high area temperature alarms NRC 1 Page 19 of 27

OC NRC Re-Take Exam 2008 o Verifies RWCU isolation o Reports RWCU did not automatically isolate o Attempts to close V-16-1 and V-16-14 by placing their control switches to CLOSE (Panel 11F and Panel 3F) o Reports RWCU cannot be manually isolated Monitor RB area temperatures and radiation levels as directed (Panel 10R) o Reports when 1 area temperature is above MAX NORMAL and continues to monitor o Reports when 1 area temperature is above MAX SAFE and continues to monitor o Reports when 2 areas temperature are above MAX SAFE Performs SP-1, Confirmation of Automatic Initiations and Isolations Lowers RPV pressure 500 - 600 psig with turbine bypass valves (TBV) as directed by placing the BYPASS VALVE OPENING JACK switch to RAISE and monitors RPV pressure; Places switch in LOWER when the pressure band is reached to close the TBV. (Panel 7F)

IF directed to anticipate Emergency Depressurization o Opens turbine bypass valves by placing BYPASS VALVE OPENING JACK to RAISE (Panel 7F)

Reports turbine bypass valves will not open o Performs SP-11, Alternate Pressure Control systems Isolation Condensers, if directed Initiates IC system A (B)

Confirms Recirculation Pump A (E) tripped

. Verifies RPV water level 160 Opens DC Condensate Return Valve V-14-34 (V . 35)

Reports Isolation Condenser in service Reports second area temperature above MAX SAFE (if it occurs)

Performs Emergency Depressurization, if directed (Panel 1F12F) o Opens EMRVs by placing AUTO DEPRESS VALVE switches to MAN o Reports 4 EMRVs open o Performs other RPV depressurization methods as directed NRC 1 Page 20 of 27

OC NRC Re-Take Exam 2008 ATC 0 Performs actions IAW ABN-1, reactor Scram (Panel 4F) o Press MANUAL SCRAM BUS 1 and BUS 2 o Places REACTOR MODE SELECTOR switch in SHUTDOWN [BOOTH]

o When RPV water level begins to rise, trips 2 feedwater pumps by placing their control switches to STOP o Places all MFRV FLOW CONTROLLERS in MAN and closes o Verifies all control rods to/beyond position 04 and power is lowering o Controls RPV water level 138 - 175 with SP-2 and SP-3 as directed o Inserts SRMs and IRMs o Verifies:

Main turbine tripped

.. Breakers GDI and GCI are open Main generator field breaker is open

. Breakers 1A and 1B are open Breakers S I A and S I B are closed Places ROPS switch in BYPAS, when directed (Panel 4F)

ROLE If asked to investigate RWCU alarms, WAIT 2 minutes, then report that steam PLAY is coming out of the Cleanup Room on elevation 51.

5 BOOTH SRO 0 Directs entry into Secondary Containment Control EOP on RB AP low 0 Directs BOP to Perform SP-50 to start RB HVAC System 0 Directs RO to monitor RB area temperatures and radiation levels 0 Directs re-entry into Secondary Containment Control EOP o Directs RWCU isolation o Directs WWM/SM/NLOs notified to close the RWCU valves o Before any area temperature reaches MAX SAFE, directs manual scram and entry into RPV Control - No ATWS and ABN-1, Reactor Scram (CRITICAL TASK)

NRC 1 Page 21 of 27

OC NRC Re-Take Exam 2008

. Following the scram, directs RPV water level 138 -

175 using Support Procedure 2 (Feedwater) and/or Support Procedure 3 (CRD)

Directs performance of Support Procedure 1,

. Confirmation of Automatic Initiations and Isolations May direct RPV pressure band 500 - 600 psig with turbine bypass valves to reduce leak driving head o When 1 area temperature is above MAX SAFE, may declare Emergency Depressurization is anticipated Directs ROPS bypassed Directs turbine bypass valves opened and/or directs Isolation Condensers placed into service (IAW SP-11) e Directs the Reactor Building evacuated e When second area temperature is reported above MAX SAFE, directs entry into Emergency Depressurization - No ATWS EOP (CRITICAL TASK) o Directs ROPS bypassed o Verifies torus water level > 90 o Directs all EMRVs open Term in us: The RPV has been emergency depressurized (due to the second area temperature exceeding the MAX SAFE value) and RPV water level is under control.

Notes/Comments NRC 1 Page 22 of 27

OC NRC Re-Take Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 1 Event No.: 9 Event

Description:

Trip of Containment Spray Pump while in Torus Cooling

~~

Initiation: As directed by the Lead Examiner Cues: Selected Containment Spray Pump does not indicate normal running indications.

Time I Position Applicants Actions or Behavior SRO 0 Enters Primary Containment Control EOP when Torus Temperature reaches 95 degrees F.

0 Directs initiation of Torus Cooling IAW Support Procedure 25 BOP 0 Reports Torus water temperature 95 OF 0 Places Torus cooling in service as follows IAW SP-25: [BOOTH]

CONFIRMS the SYSTEM MODE SELECT SWITCH for the selected system is in the TORUS COOLING position 0 Starts the selected ESW pump Places and Holds the System Pump Start Permissive Keylock for the selected pump in the appropriate position Starts the selected Containment Spray pump.

0 Recognizes trip of Containment Spray pump 0 Informs SRO of pump trip.

0 Places alternate Containment Spray pump in service.

BOOTH After the first pump start is attempted, DELETE the trips on the other containment spray pumps.

Terminus: Torus Cooling in service with alternate Containment Spray Pump SCENARIO MAY BE TERMINATED AFTER THE ED IS ACCOMPLISHED AND TORUS COOLING IS IN SERVICE WITH THE ALTERNATE PUMP.

E-PLAN F S I : SAE due to LOSS of primary containment barrier AND POTENTIAL LOSS of reactor coolant system barrier.

NRC 1 Page 23 of 27

OC NRC Re-Take Exam 2008

~~

8 PRESETS-, VLV-RCU001 to MECH SEIZE (V-16-1)

VLV-RCU004 to MECH SEIZE (V-16-14) o This keeps the RWCU isolation valves open T6-t 0 MAL-RCU013 0-20°/0 over 15 minutes o This inserts a unisolable RWCU leak into the Reactor Building

~~

9 PRESET-, 0 MAL-CNS004A (Containment Spray Pump 51A) 0 MAL-CNS004B (Containment Spray Pump 51B)

MAL-CNSOO4C (Containment Spray Pump 51C) 0 MAL-CNS004D (Containment Spray Pump 51D) o This trips the containment spray pumps o WHEN the first containment spray pump start is attempted and tripped, DELETE the other pump trip malfunctions NRC 1 Page 26 of 27

OC NRC Re-Take Exam 2008 Shift Turnover Initial Conditions 0 The plant is at rated power 0 The RWM is inoperable and bypassed 0 RWCU Pump B is tagged out of service for repair Shift Activities 0 Surveillance test 602.4.004, Main Steam Isolation Valve 10% Closure Test, has been initiated and has been completed up to step 6.3.3 (normal surveillance) o Continue with the surveillance test, starting at step 6.3.4 o Other Operators are appropriately stationed to support this s u Neillance NRC 1 Page 27 of 27

OC NRC Retake Exam 2008 Scenario Outline Facility: Oyster Creek Scenario No.: NRC 2 Op Test No.: NRC 2008-1 Examiners: Operators: SRO- Steve Johnston Initial Conditions:

0 90%Power 0 RWM is bypassed and 00s 0 lsophase Bus Fan A is 00s 0 Main Generator voltage control is in manual Turnover:

0 Restore the amplidyne to service and transfer main generator voltage control to automatic IAW 336.1 2 4 W Main Gen Electrical System Inc 3ase reactor ower to rate f IAW the ReMA

~

Event Malf. No. Event Event No. Description Restore the amplidyne to service and transfer main SRO I N/A generator voltage control to automatic IAW 336.1 ATC 24KV Main Gen Electrical System SRO 2 NIA R Increase reactor power with control rods BOP 3 MAL- SRO Uncoupled Control Rod CRD008-34-1 I ATC ABN-6 Control Rod Malfunction

~

4 SWI-ADSOOIC SRO EMRV A Inadvertently Opens BOP ABN-40 Stuck Open EMRV; TS 3.4.8 ANN-EGD ANN-E2D Respond to Reactor Recirc Pump AAlarms, Pump 5 SRO Discharge Valve fails to close VLV-NSSOOG BOP ABN-2 RecirculationSystem Failures TS 3.3 F MAL-CRDOOS Multiple control rod drifts, Manual scram required and 6 MAL-RPSOOG SRO fails, ARI required SWI-RPS006 ATC ABN-6 Control Rod Malfunction MAL-NSS017B Steam leak in Primary Containment, DWnorus 7 MAL-PCN001N ALL Vacuum Breaker fails open MAL-RPS007C 8 VLV-CNS008 SRO Failure of RWCU to Auto isolate, Containment Spray PMP-CNS008A BOP System failures

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 2 Page 1 of 21

OC NRC Retake Exam 2008 NRC 2 Simulator Scenario Summaw Event Event Summary 1 The BOP will place the main generator voltage control in automatic voltage control IAW 336.1, 24KV Main Generator Electrical System. (NORMAL EVOLUTION) 2 The ATC will increase reactor power with control rods per the ReMA.

(REACTIVITY MANIPULATION)

~

3 The ATC will respond to an uncoupled control rod IAW ABN-6 Control Rod Ma Ifunct ion (C0MPONENT MALFUNCTI0N)

I.

4 The A EMRV will spuriously open and the Crew will enter ABN-40, Stuck Open EMRV. The EMRV will close when the BOP places the back-panel keylock switch in DISABLE. The SRO will review and apply TS 3.4.B.2. If Torus water temperature exceeds 95 O F , the SRO will direct entry into the Primary Containment Control EOP and directs initiation of Torus Cooling.

(COMPONENT MALFUNCTION) (TS) 5 The operators will respond to alarms for Recirculation Pump A. Alarms for low oil and high vibrations (RAP-E2d, RAP-E6d) will require an immediate pump trip by the BOP. The recirculation pump discharge valve will fail to close. The SRO will enter ABN-2 Recirc System Failures and apply TS 3.3.F, Recirc Loop Operability. (COMPONENT MALFUNCTION) (TS) 6 Multiple control rod drifts will occur requiring the RO to scram the reactor. The mode switch and RPS pushbuttons will fail but ARI will be successful.

(COMPONENT MALFUNCTION)

~ ~~~~

7 A steam leak will occur in primary containment resulting in an entry to Primary Containment Control EOP and RPV Control no ATWS EOP. Additionally, one DW/Torus Vacuum Breaker will fail open, resulting in the pressurization of the Torus air space. Emergency Depressurization will be required when it has been determined that Torus pressure cannot be maintained below the PSP. (MAJOR) 8 When attempting to spray the drywell, System 1 Containment Spray Discharge valve will fail closed and one System 2 Containment Spray Pump will have a sheared shaft requiring use of an alternate pump. Additionally, RWCU will fail to isolate on high DW pressure but can be manually isolated. (INSTRUMENT MALFUNCTION after EOP)

CriticaI With the failure of the scram pushbuttons and the reactor mode switch, ARI is Task #I initiated to insert control rods.

NRC 2 Page 2 of 21

OC NRC Retake Exam 2008 Critical Initiate Emergency Depressurization with EMRVS prior to exceeding Primary Task #2 Suppression Pressure Limit (PSP), or when the Primary Containment bulk temperature cannot be maintained below 281" F; or, anticipating ED and performing a rapid RPV depressurization before the limits are exceeded. (PRA)

NRC 2 Page 3 of 21

OC NRC Retake Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 2 Event No.: 1 Event

Description:

Shift from manual generator voltaqe control to automatic generator voltage control IAW procedure 336.1, 24 KV Main Generator Electrical System, Section 6.0 Initiation: Following shift turnover Cues: As directed by the SRO Time Position Applicants Actions or Behavior SRO Directs the BOP to shift from manual generator voltage control to automatic generator voltage control IAW procedure 336.1, 24 KV Main Generator Electrical System, Section 6.0.

BOP Shift from manual generator voltage control to automatic generator voltage control IAW procedure 336.1, 24 KV Main Generator Electrical System, Section 6.0 (8F/9F)

Makes plant announcement prior to starting the amplidyne.

NOTIFY PECO Generation Dispatcher that the Main Generator to be place in Automatic Voltage Control.

NOTIFY the Power Team that the Main Generator is to be placed in Automatic Voltage Control.

Simultaneously PLACE the AMPLIDYNE CONTROL 43CS switch in TEST and OBSERVE 1 A l bus ammeter for an amp deflection.

CONFIRM amplidyne motor started as indicated by the amp deflection on 1 A l bus.

Locally VERIFY the AMPLIDYNE motor is running. [ROLE PLAY]

ZERO the AMPLIDYNE Voltmeter as follows:

o PRESS and HOLD the AMPLIDYNE VOLTS Low Range pushbutton.

o OBSERVE the AMPLIDYNE Voltmeter for a zero or center scale reading.

o IF the needle is deflected, THEN ADJUST the voltage using the AMPLIDYNE ADJUST rheostat to return the regulator output to a zero or center scale reading.

o RELEASE the AMPLIDYNE VOLTS Low Range pushbutton.

o VERIFY the AMPLIDYNE Voltmeter reads zero or center scale.

PLACE the AMPLIDYNE CONTROL 43CS switch to ON, which leaves the AMPLIDYNE controlling excitation.

REMOVE VOLTAGE CONTROL IN MANUAL operator aids NRC 2 Page 4 of 21

OC NRC Retake Exam 2008 installed earlier.

CONTROL terminal voltage or excitation level of the generator by adjusting the AMPLIDYNE ADJUST rheostat as required in the range of 23.3 to 24.7 KV.

MAINTAIN a slight BUCK reading by adjusting EXCITER FIELD RHEOSTAT CONTROL 70M switch as needed, which ensures the Main Field will pick up control should the AMPLIDYNE trip.

Reports the generator voltage control is in automatic.

Role Play 1 As the NLO, when directed to verify the amplidyne running, state the amplidyne is running.

Terminus: I The amplidyne is in automatic control.

Notes/Comments i - 1 NRC 2 Page 5 of 21

OC NRC Retake Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 2 Event No.: 2 & 3 Event

Description:

1. Withdraws control rods for a power increase IAW the ReMA (14-15, 14-39, 38-15, 38-39, 18-43, 18-11, 34-43, 34-1 1 from position 40 to 48)

2. Uncoupled Control Rod 34-11 Initiation: As directed by Lead Examiner Cues: Annunciator H5a, ROD OVERTRAVEL Position Applicant's Actions or Behavior SRO Conducts a pre-job reactivity maneuver brief.

Directs the ATC to withdraw control rods IAW the reactivity maneuver approval sheet (ReMA).

0 Acts as the Reactivity Manager during the evolution.

Directs entry into ABN-6, Control Rod Malfunctions, when the control rod becomes uncoupled Notifies the Reactor Engineer about the uncoupled control rod [ROLE PLAY]

BOP Provides a peer-check for withdrawing control rods and initials on the reactivity maneuver sheet after each control rod is withdrawn.

ATC Withdraws control rods IAW the reactivity maneuver sheet and Procedure 302.2, Control Rod Drive Manual Control System. [PANEL 4F]

0 Verifies the PERMIT light is illuminated.

0 Places the ROD POWER switch to ON.

0 Selects the control rod by depressing the corresponding pushbutton on the CONTROL ROD SELECT matrix.

o Verifies the pushbutton light is lit and no others are lit.

0 Turns the ROD CONTROL switch to ROD OUT NOTCH position and simultaneously turns the NOTCH OVERRIDE switch to NOTCH OVERRIDE 0 Verifies:

o Amber OVERRIDE light is ON NRC 2 Page 6 of 21

OC NRC Retake Exam 2008 o Green insert light is ON following switch movement and remains on for about 1 second o Rod position readout momentarily displays the next odd-numbered digit Verifies the WITHDRAW light remains ON for the duration of the withdrawal and an increasing rod position is displayed and releases at position 48 Performs a coupling check at position 48 o Turns the ROD CONTROL switch to ROD OUT NOTCH position and simultaneously turns the NOTCH OVERRIDE switch to NOTCH OVERRIDE o Verifies rod display indicates a continuous readout of 48 with red backlight Responds to annunciator H5a, ROD OVERTRAVEL Reports control rod 34-1 1 is uncoupled and enters ABN-6, Control Rod Malfunctions o Applies a continuous insert signal by placing the ROD CONTROL switch to ROD IN until a response is observed on the nuclear instrumentation (APRMs, LPRMs) or is fully inserted. [BOOTH]

o Withdraws the control rod and verifies coupling at position 48 o Reports control rod 34-1 1 has re-coupled.

o Notifies Reactor Engineering Turns ROD POWER off when complete when control rod manipulations are complete Reports all control rods withdrawn IAW the reactivity maneuver approval form NOTE Control rod 34-1 1 will be uncoupled.

ROLE As the Reactor Engineer for the uncoupled rod, acknowledge the report. IF the control PLAY rod is inserted to between 24-48 during re-coupling, direct that continuous withdrawal is allowed. Below this, single notch, until position 24.

BOOTH When the RO is inserting the uncoupled control rod, DELETE the uncoupled control rod malfunction.

Terminus The uncoupled control rod has been re-coupled and all control rods have been withdrawn.

OC NRC Retake Exam 2008 Notes/Comm ents 1

NRC 2 Page 8 of 21

OC NRC Retake Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 2 Event No.: 4 Event

Description:

EMRV NR-108A opens spuriouslv [TRIGGER I]

Initiation: As directed by Lead Examiner Cues: Annunciators B3gl EMRV OPEN; B4g, SV/EMRV NOT CLOSED; EMRV NR-108A indicates in the VALVE OPEN REGION (TRIGGER 1)

Time Position Applicants Actions or Behavior BOP 0 Responds to annunciators B3gl EMRV OPEN and B4g, SVIEMRV NOT CLOSED Identifies and reports EMRV NR108A is open 0 Performs actions IAW ABN-40, Stuck Open EMRV o Places the MASTER FEEDWATER CONTROLLER in MAN [Panel 4 FI o Places EMRV NR108A AUTO DEPRESS VALVE switch in OFF

[Panel 1F/2F]

o Determines EMRV NOT closed o Cycles EMRV NR-108A AUTO DEPRESS VALVE switch from OFF to MAN to OFF o Determines EMRV NOT closed o Cycles EMRV NR-108A AUTO DEPRESS VALVE switch from OFF to MAN to OFF 3-5 times o Determines EMRV NOT closed o Places the EMRV NR-108A NORMALIDISABLE switch to DISABLE [rear of Panel 1F/2F]

o Verifies/reports EMRV NR-108A indicates closed o Places the MASTER FEEDWATER CONTROLLER in AUTO

[Panel 4F]

Selects the P Display on the MASTER FEEDWATER

. CONTROLLER Selects the S Display on the MASTER FEEDWATER

.. CONTROLLER Raises/lowers the S to match P Places the MASTER FEEDWATER CONTROLLER in AUTO

. by depressing the AUTOIMAN button Verifies the green AUTO light is lit NRC 2 Page 9 of 21

OC NRC Retake Exam 2008 ATC Monitors Torus water temperature while EMRV is open Announces EOP entry on high torus water temperature (if it exceeds 95 OF)

Performs SP-25, initiation of the Containment Spray System in the Torus Cooling Mode, if directed (Panel 1F/2F) o Makes plant announcement prior to starting pumps o Confirms SYSTEM 1 MODE SELECT (SYSTEM 2) switch in TORUS CLG position o Starts the associated ESW PUMP by placing its control switch to START o Places and holds the SYSTEM I(2) PUMPS START PERMISSIVE to the selected pump o Starts the selected CONTAINMENT SPRAY PUMP by placing its control switch to START Reports Torus Cooling in service SRO 0 Directs entry into ABN-40, Stuck Open EMRV Declares EMRV NR108A inoperable and reviews/applies TS 3.4.8.2 o The reactor may remain in operation not to exceed 3 days provided the IC MO isolation and condensate makeup valves in both ICs are verified daily to be operable Refer to TS 4.5.F.5, 4.5.L 0 Notifies WWM/SM about the failed EMRV 0 Briefs the Crew on the event 0 Enters Primary Containment Control EOP (IF torus water temperature exceeds 95 OF) o Directs torus cooling initiated IAW SP-25 Terminus: EMRV NR-108A is DISABLED, the SRO has reviewed Tech Specs and briefed the Crew. Torus Cooling has been initiated, if required.

Notes/Comments r 1 I f NRC 2 Page 10 of 21

OC NRC Retake Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 2 Event No.: 5 Event

Description:

Reactor Recirculation Pump A abnormal operation requiring pump shutdown (low oil level and high vibration) (TRIGGER 2)

Initiation: As directed by lead examiner Cues: Annunciators E6d, OIL LEVEL HVLO and E2d, VIBRATION HI A Time Position Applicants Actions or Behavior BOP Responds to Annunciators VIBRATION HI A E2d, and OIL LEVEL HVLO E6d, (Panel 3F) 0 Annunciator VIBRATION HI A, E2d o Attempts to reset vibration alarm Annunciator OIL LEVEL HVLO, E6d o Reports that immediate pump trip is required IAW the RAP-E6d Manually trips Reactor Recirc. Pump A o Place Recirc Pump A DRIVE MOTOR switch to STOP position Refers to ABN-2, Recirculation System Failures 0 Confirms the DISCH BYPASS valve open for Recirculation Pump A (V-37-11) 0 Closes the Recirculation Pump A DISCHARGE valve (V-37-10) 0 Recognizes failure of discharge valve to close and reports this to the SRO 0 Closes the Recirculation Pump A SUCTION valve (V-37-9) 0 Contacts Electrical maintenance to attempt closure of Recirculation Pump A discharge valve 0 Verifies the plotted point on the Power Operation Curve 0 Informs SRO to review TS 3.3.F., Recirculation Loop Operability, and 3.10.A., Core Limits 0 Selects an operating recirculation loop temperature point 0 Monitors for fuel failures: Monitors Offgas activity, Main Steam Line radiation, and reactor coolant activity 0 Changes reactor pressure, if directed, by changing the EPR setpoint (980-1020) [Panel 7F]

~~

ATC Refers to ABN-2, Recirculation System Failures o May verify operation on Power Operations Curve NRC 2 Page 11 of 21

OC NRC Retake Exam 2008 SRO 0 Directs trip of Reactor Recirculation Pump A, IAW RAPS 0 Directs entry into ABN-2, Recirculation System Failures 0 Refers to Tech Spec 3.3.F, 3.10.A o Tech Spec 3.0.A.: Be in Cold S/D within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Notify System Owner/Dispatcher, Chemistry, Reactor Engineering, W M / SM Terminus: Recirc. Pump A has been manually tripped and suction valve closed; Tech Specs reviewed, and maintenance contacted.

/.lotes/C omments 1

NRC 2 Page 12 of 21

OC NRC Retake Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 2 Event No.: 6 Event

Description:

Multiple rod drifts; Scram Required; Manual Scram Fails; ARI required Control rod drifts: IO-?1, 10-19, 06-23, and 06-27 (TRIGGER 3)

Initiation: As directed by Lead Examiner Cues: Annunciators H6a- ROD DRIFT; Full Core Display control rod position indications changing Time Position Applicants Actions or Behavior ATC 0 Responds to Annunciator H6a- Rod Drift Recognizes/reports multiple control rod Drifting 0 IAW ABN-1, Reactor Scram, Scrams the Reactor with the RPS Pushbuttons & places the Mode Switch to SHUTDOWN 0 Recognizes/Reports failure to Scram Initiates ARI (Critical Task) 0 Reports all rods inserted Controls RPV level band of 138 - 175 IAW Support Procedure 2 (FeedwaterICondensate) & Support Procedure 3 (CRD) o When RPV water level is rising, THEN SELECT one Feedwater Pump to be the operating pump and trip the Feedwater Pumps not selected o CONTROL RPV water level using the following as necessary:

(Panel 5F/6F) o Feedwater Regulating valves o Main Feed Regulating Valve (MFRV) Block valves o Feedwater Low Flow valves o Heater Bank Outlet Isolation valves o Feedwater and Condensate pumps SRO 0 Directs Reactor Scram when multiple rod drifts are reported May enter RPV Control w/ATWS EOP 0 When informed all rods in, Enters RPV Control - No ATWS EOP Directs a RPV level band of 138 - 175 IAW Support Procedure 2 (Feedwater/Condensate) & Support Procedure 3 (CRD)

May direct a pressure band of 800 - 1000 psig with turbine bypass valves NRC 2 Page 13 of 21

OC NRC Retake Exam 2008 i

I BOP i 0 May assist in controlling RPV level & Pressure as directed by S R O I Terminus: The reactor is manually scrammed and ARI initiated, which results in all control rods inserted.

Notes/Comments -

NRC 2 Page 14 of 21

OC NRC Retake Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 2 Events No.: 7 & 8 Event

Description:

1. Steam leak in the Primaw containment; DW/Torus Vacuum Breaker Fails open (TRIGGER 4)

2. Containment Sprav System Failures; Failure of RWCU Isolation Valves to isolate Initiation: The reactor and turbine have tripped; RPV water level is inhear the normal band OR as directed by the Lead Examiner Cues: Increasing DW pressure and temperature; Annunciators C3f DW PRESS HI/LO, followed by H l d , H2d, DW PRESS HI-HI I & 11; C4f/C5f, TORUS/DW 1/2 VAC BRKR OPEN Time Position Applicants Actions or Behavior BOPlATC Responds to annunciator C4flC5f o Dispatches an EO to the local panel to determine which valve is open 0 Responds to annunciator C3f, DW PRESS HI/LO Reports Drywell pressure and temperature are rising 0 Reports hi Drywell pressure and entry into Primary Containment Control EOP and RPV Control - No ATWS EOP 0 Monitors/reports Primary Containment parameters Confirms automatic actions, IAW Support Procedure 1 o Reports that RWCU System did not auto isolate and closes the valves and trips the RWCU Pump (V-16-1 , V-16-14, and I 16-61)

Lines-up and sprays the DW IAW Support Procedure 29 o CONFIRM all Reactor Recirculation Pumps tripped.

o CONFIRM the Drywell Recirc Fans tripped. (Panel 11R) o CONFIRM the SYSTEM MODE SELECT switch for the selected system in the DW SPRAY position.

o VERIFY that the system Torus CLG Discharge valve, V-21-17 (V-21-13) is closed.

o VERIFY that the system DW Spray Discharge valve, V-21-11 (V-21-5) is open.

o START an ESW Pump using its control switch. (Panel 1F/2F) o START a Containment Spray Pump in the selected system as follows:

1. SELECT a Containment Spray Pump to be started.

2. PLACE and HOLD the System Pump Start Permissive NRC 2 Page 15 of 21

OC NRC Retake Exam 2008

~ ~~

Keylock for the selected pump in the appropriate position.

e Reports that Containment Spray System 1 discharge valve (V 11) will not open, and continues with Containment Spray System 2 a Reports that Containment Spray Pump 51C indicates no flow e Reports Containment Spray Pump 51 D starts and is operating normally e Reports that PSP is rising and when near violated a Reports PSP is violated a Performs Emergency Depressurization when directed (Critical Task) 0 Stops injection with Core Spray not required for adequate core cooling IAW Support Procedure 10 0 OVERRIDE the Core Spray initiation logic by performing the following at the Core Spray Control Logic:

0 PRESS the OVERRIDE switches for all the sensors that are lit.

0 PRESS all ACTUATED switches whether lit or unlit.

0 CONFIRM Closed Core Spray System 1 and System 2 Parallel Isolation Valves not required for assuring adequate core cooling.

0 SECURE Core Spray System 1 and System 2 Booster Pumps not required to assure adequate core cooling by placing their respective control switches in STOP.

0 SECURE Core Spray System 1 and System 2 Main Pumps not required to assure adequate core cooling by placing their respective control switches in STOP.

0 Bypasses ROPS 0 Verifies Torus water level > 90 0 Opens 5 EMRVs by placing all AUTO DEPRESS VALVE switches in the MAN position 0 Reports all EMRVS open a Reports Torus water temperature 95 OF SRO Directs entry into Primary Containment Control EOP and re-enters RPV Control - No ATWS EOP o Directs automatic actions confirmed IAW Support Procedure 1 o Before DWnorus reaches 12 psig, directs lineup of Drywell Sprays IAW Support Procedure 29 o When DW/Torus exceeds 12 psig, or before bulk DW temperature reaches 281 F, directs initiation of Drywell Sprays O

NRC 2 Page 16 of 21

OC NRC Retake Exam 2008 IAW Support Procedure 29 o When it has been determined that bulk DW temperature cannot be restored/maintained below 281' F or it has been determined that Torus pressure cannot be maintained below Pressure Suppression Pressure, then direct Emergency Depressurization (Critical Task) 0 Enters Emergency Depressurization - No ATWS EOP o Direct stopping injection with Core Spray not required for adequate core cooling IAW Support Procedure 10 o Directs ROPS bypass o Directs verification of Torus water level o Directs 5 EMRVs open 0 Re-enters Primary Containment Control EOP on high Torus water temperature Terminus: The RPV has been emergency depressurized with EMRVs and RPV water level has been stabilized.

Notes/Comments I I NRC 2 Page 17 of 21

OC NRC Retake Exam 2008 Simulator Setup

1. Reset the simulator to normal full power IC-65

2. Insert the following control rods from position 48 to position 40

a. 14-15, 14-39, 38-15, 38-39, 18-43, 18-11, 34-43, 34-1 1

b. Then reduce power to 90% with recirculation flow

3. Run SIMPROB

4. Have a blank copy of procedure 336.1 available

5. Remove the amplidyne from service IAW 336.1, section 5.0 (include the panel operator aids)

6. Have a ReMA ready, that has 3 steps:

a. Lower recirc flow to 90% power (already performed and signed off)

b. Withdraw control rods 14-15, 14-39, 38-15, 38-39, 18-43, 18-11, 34-43, and 34-1 1 from 40 to 48; continuous out is allowed

c. Raise power with recirc flow

7. Check APRM gains OK MALFUNCTIONS EVENT TRIGGER MALFUNCTION 1

2 NA I None 3 PRESET -+ 1 MAL-CRD008-3411 o This makes control rod 34-1 1 uncoupled o DELETE this malfunction when the operator is driving the control rod inward to re-couple 4 TI -+ 1 0 SWI-ADS001CtoON o This makes EMRV NR108A open by its control switch This does allow the EMRV to close when DISABLED NRC 2 Page 18 of 21

OC NRC Retake Exam 2008 5 PRESET --$ VLV-NSSOO6 to MECH SEIZE o This keeps Recirculation Pump A discharge valve open T2 -+ ANN-E6d to ON o This makes annunciator E6d (Recirc. Pump A OIL LEVEL HVLO) alarm 0 ANN-E2d with a 60-second time delay o This makes annunciator E2d (Recirc. Pump A VIBRATION HI) alarm after 60 seconds 6 T3 -+ MAL-CRD005~1011 0 MAL-CRD005-1019 with a 5 second time delay 0 MAL-CRD005-0623 with a 5 second time delay 0 MAL-CRD005-0627 with a 5 second time delay o This will drift control rod 10-11, followed by rods 10-19, 06-23 and 06-25 5 seconds later SWI-RPS006A to OFF o This ensures the MODE switch is not placed in SHUTDOWN position MAL-RPSOO6 o This fails the RPS scram pushbuttons o Taken together, this represents a failure of the mode switch and scram buttons (manual scram failure) 7 T4 -+ 0 MAL-NSSOI7D to 10% over a 20 minute ramp o This inserts a steam leak in the primary containment MAL-PCN001N to 100%

o This opens a Drywell-Torus vacuum breaker 8 PRESETS MAL-RPS007C o This prevents the RWCU System to auto isolate on high DW pressure (but does allow manual isolation)

VLV-CNS008 to MECH SEIZE o This prevents Containment Spray System I DW spray valve V-21-11 from opening NRC 2 Page 19 of 21

OC NRC Retake Exam 2008 PMP-CNS008A o This breaks the shaft on Containment Spray Pump 51C NRC 2 Page 20 of 21

OC NRC Retake Exam 2008 Shift Turnover Initial Conditions 0 Reactor power has been reduced to 90% with recirculation flow IAW the ReMA 0 The amplidyne is in manual voltage control 0 The RWM is inoperable and bypassed 0 The isophase bus fan A is out of service for repair Shift Activities

1. Place the amplidyne back in service in automatic voltage control IAW Section 6 of procedure 336.1, 24 KV Main Generator Electrical System

2. Continue with the ReMA to raise reactor power o Withdraw control rods o Reactor Engineering will run a few cases after control rods have been withdrawn o They will notify the Control Room when to raise recirculation flow to achieve 100% power NRC 2 Page 21 of 21

OC NRC Re-Take Exam 2008 Scenario Outline Facility: Oyster Creek Scenario No.: NRC 3 Op Test No.: NRC 2008-1 Examiners: Operators: RO- Steve Johnston Initial Conditions:

0 92%Power 0 RWM bypassed and 00s 0 TBCCW pump 2 00s Turnover:

0 Increase reactor power to 100% IAW ReMA Event Malf. No. Event No. Description Increase Power with Rods & Recirc Flow to 1 NIA R ATC

~~

100% Power -

MAL-2 CR D007-382 3 c ATC Stuck Control Rod

~~

PMP-3 CRD002A c ATC CRD Pump 1A Shaft Failure Condensate Pump B Motor Bearing Hi Temp 4 I CH-CFW069A C ATC requires power reduction with Recirculation Flow to approx. 65% power MAL-NSSOl7D MAL- Small Steam leak in containment with Hydraulic 5 CRD021A M ALL ATWS MAL-CRD021B MAL-6 CRDOOIA c ATC CRD Flow Control Valve fails to 0%

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 3 Page 1 of 14

OC NRC Re-Take Exam 2008 NRC 3 Simulator Scenario Summarv Event Event Summary

~~

1 The ATC will be directed to increase reactor power to 100% IAW the Reactivity maneuver Approval Form (ReMA). (REACTIVITY MANI PULATION) 2 The ATC will respond to a stuck control rod IAW procedure 302.2, Control Rod Drive Manual Control System. Increasing drive water pressure will cause the rod to move. (COMPONENT MALFUNCTION) 3 While increasing power, the running CRD Pump 1A will develop a shaft shear. After local investigation, the ATC will start the redundant CRD pump IAW RAP-HIc, and then complete the control rod manipulations.

The SRO will declare a 7-day LCO IAW TS 3.4.D.2. (COMPONENT MALFUNCTION) 4 A Condensate Pump B Motor Bearing Hi Temp will occur requiring the ATC to perform a power reduction with Recirc Flow to approx. 65%

(COMPONENT MALFUNCTION) 5 A steam leak in containment with a hydraulic ATWS will occur requiring entry to Primary Containment Control EOP and RPV Control w/ATWS EOP. The ATC will insert rods per Support Procedure 21. (MAJOR) 6 While the ATC is inserting control the CRD flow control valve will fail closed requiring additional actions (swap flow control valves) to continue control rod insertion. (COMPONENT MALFUNCTION after EOP)

Critical With reactor power > 2%, terminate and prevent injection into the RPV Task # I by all systems except CRD and Boron injection systems IAW Support Procedure 17. (PRA)

Critical Insert Control Rods IAW Support Procedure 21.

Task #2 NRC 3 Page 2 of 14

OC NRC Re-Take Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 3 Event No.: 1 & 2 Event

Description:

1. Withdraws control rods for a power increase IAW the ReMA

2. Responds to Stuck Control Rod 38-23 Initiation: As directed by Lead Examiner Cues: Control rod 38-23 shows abnormal indications when a withdraw signal is applied Time Position Applicants Actions or Behavior SRO 0 Conducts a pre-job reactivity maneuver brief.

0 Directs the ATC to withdraw control rods IAW the reactivity maneuver sheet 0 Acts as the Reactivity Manager during the evolution.

0 May refer to ABN-6, Control rod malfunctions due to stuck rod BOP Provides a peer-check for withdrawing control rods and initials on the reactivity maneuver sheet after each control rod is withdrawn.

ATC Withdraws control rods IAW the reactivity maneuver sheet and Procedure 302.2, Control Rod Drive Manual Control System. [PANEL 4F]

Verifies the PERMIT light is illuminated.

Places the ROD POWER switch to ON.

Selects the control rod by depressing the corresponding pushbutton on the CONTROL ROD SELECT matrix.

o Verifies the pushbutton light is lit and no others are lit.

Turns the ROD CONTROL switch to ROD OUT NOTCH position and simultaneously turns the NOTCH OVERRIDE switch to NOTCH OVERRlDE 0 Verifies:

o Amber OVERRIDE light is ON o Green insert light is ON following switch movement and remains on lar about 1 second o Rod position readout momentarily displays the next odd-numbered digit

~

NRC 3 Page 3 of 14

OC NRC Re-Take Exam 2008 e Verifies the WITHDRAW light remains ON for the duration of the withdrawal and an increasing rod position is displayed and releases at position 48 e Performs a coupling check at position 48 o Turns the ROD CONTROL switch to ROD OUT NOTCH position and simultaneously turns the NOTCH OVERRIDE switch to NOTCH OVERRIDE o Verifies rod display indicates a continuous readout of 48 with red backlight e Recognizes & Reports Control Rod 38-23 is stuck e May refer to ABN-6 Control Rod Malfunctions e Refers to 302.2 Control Rod Drive Manual Control System, precaution:

and Limitations section Places CRD Drive Water Pressure Control Valve to the closed direction to raise drive water pressure 50 psid, then attempts to move control rod (BOOTH)

Restores drive pressure to normal Turns ROD POWER off when complete Reports all control rods withdrawn IAW the reactivity maneuver form BOOTH Delete Stuck Rod malfunction after drive water pressure is increased the first time Terminus: At the examiners discretion when stuck control rod has been moved and sufficient control rods have been withdrawn for the power increase.

Notes/Comments NRC 3 Page 4 of 14

OC NRC Re-Take Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 3 Event No.: 3 Event

Description:

Responds to a broken CRD Pump A shaft [TRIGGER I]

Initiation: As directed by the Lead Examiner Cues: CRD HYDRAULIC SYSTEM indicators indicate no flow/pressure; Annunciator H7c, CHARG WTR PRESS LOW; H5c, CRD TEMP HI alarms

~

Time Position Applicants Actions or Behavior ATC e Responds to annunciators H5c, H7c e Reports CRD HYDRAULIC SYSTEM indicators indicate no flow/pressure e Dispatches NLO to investigate CRD Pump A [ROLE PLAY]

e Starts CRD Pump B by placing CRD PUMP NCOIB switch to STAR-and stops CRD Pump A by placing CRD PUMP NCOIA switch in STOP, OR:

e Starts CRD Pump B IAW procedure 302.1 (Panel 4F) o May request NLO to inspect CRD Pump B prior to start o Places CRD FLOW CONTROLLER in MAN o Places CRD PUMP NCOIB to START o Verifies normal system indications e Stops CRD Pump A o Places CRD PUMP NCOIA to STOP e Adjusts CRD FLOW CONTROLLER to attain required flows e Places CRD FLOW CONTROLLER in AUTO e Verifies normal indications e Reports CRD Pump B is operating and CRD System indications are normal SRO e Directs starting CRD Pump B IAW procedure 302.1, Control Rod Drive System, Section 6.0 OR directs the ATC to start CRD Pump B without using the procedure and stopping CRD Pump A Declares CRD Pump A inoperable Reviews Tech Spec 3.4.D.2 o States a 7-day LCO is required due to inop CRD Pump A Notifies Work Week manager (WMM) or Shift Manager about the NRC 3 Page 5 of 14

OC NRC Re-Take Exam 2008 inoperable CRD Pump A 0 Briefs the Crew BOP 0 Makes plant announcement prior to starting CRD Pump B ROLE 0 When directed to investigate CRD Pump A, WAIT 2 minutes, then report that the PLAY shaft has broken, and the motor is really vibrating.

0 If directed to inspect CRD Pump B prior to start, WAIT 1 minute and report that it is ready for start.

Terminus: CRD Pump B has been started and the SRO has applied Tech Specs.

Notes/Comments r 7 NRC 3 Page 6 of 14

OC NRC Re-Take Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 3 Event No.: 5 Event

Description:

Condensate Pump upper bearing High Temp requires removal from service and power reduction [TRIGGER 21

~ _ _ _

Initiation: As directed by Lead examiner Cues: Annunciator J8f, COND/FD PMP BRG TEMP HI Time Position Applicants Actions or Behavior ATC Performs a rapid power reduction with recirculation flow by rotating the MASTER RECIRC SPEED CONTROLLER knob CCW to about 65% power, IAW 202.1 BOP 0 Responds to annunciator J8f, COND/FD PMP BRG TEMP HI o Monitors pump bearing temperatures (Panel 12XR) o Reports bearing temperatures & trend o Dispatches EO to verify TBCCW lineup & oil levels for Condensate Pump B [ROLE PLAY]

0 SRO 0 Directs ATC to reduce reactor power with recirculation flow to within the capacity of 2 feedwater pumps (rapid power reduction IAW 202.1)

Directs BOP to remove a Feedwater Pump form service & trip the B Condensate Pump 0 May enteddirect entry into ABN-17, Feedwater System Abnormal Conditions, when the FWP trips Notifies WWM/SM about Condensate Pump 6.

ROLE As the EO report TBCCW is lined up normally and oil levels are normal.

PLAY Terminus:

2 Reactor power has been lowered to the capacity of 2 feedwater pumps, Condensate Pump B tripped and RPV water level is stable.

NRC 3 Page 7 of 14

OC NRC Re-Take Exam 2008 NotedComments NRC 3 Page 8 of 14

OC NRC Re-Take Exam 2008 Op-Test No.: NRC 2008-1 Scenario No.: NRC 3 Event No.: 5 & 6 Event

Description:

1. Small Steam leak in containment (TRIGGER 3) with Hvdraulic ATWS

2. CRD Flow Control Valve failure (TRIGGER 4)

Initiation: As directed by the lead examiner Cue: Increasing DW pressure and temperature; Annunciators C3f DW PRESS HVLO, followed by H l d , H2d, DW PRESS HI-HI I & 11 Time Position Applicants Actions or Behavior RO 0 Reports Drywell pressure and temperature rising 0 As directed, manually scrams the reactor and carries out ABN-1, Reactor Scram 0 Reports control rods not inserted and reports reactor power 0 Initiates Alternate Rod Insertion (ARI) (4F) 0 As directed, bypasses ROPS (Reactor Overfill Protection System)

(4F) 0 Runs recirc flow to minimum 0 Trips all recirc pumps 0 Insert control rods IAW Support Procedure 21 (CT) (per section 5.2 and/or 5.3)

Section 5.2 Manual Control Rod Insertion (4F)

Directs NLO to close CRD Charging Water Valve V-15-52 (BOOTH)

Places Mode Switch in Refuel Close CRD drive water pressure control valve Resets ARI Selects and Inserts CRAM array 0 Recognizes failure of CRD Flow Control Valve after beginning to drive in control rods Swaps flow control valves IAW 302.1 CRD System Continues control rod insertion Section 5.3 Places ARI NormaVBypass switch in Bypass NRC 3 Page 9 of 14

OC NRC Re-Take Exam 2008 0 Press ARI Manual Reset Pushbutton 0 Inserts Bypass plugs BP5, BP6 in RPS Panels 1 & 2 0 Place SDV HI LVL BYPASS switch in BYPASS 0 Reset the scram by depressing the Scram reset pushbuttons 0 Confirms SDV vents and drains open 0 When the SDV HI-HI alarms clear, manually scrams the reactor 0 Repeats above steps until all rods are inserted 0 Reports control rods insertinglinserted BOP 0 Confirms EOP automatic actions IAW Support Procedure 1 0 Prevents ADS by placing ADS Timer switches in Bypass (1F12F) 0 Bypass MSlV Low-Low water level isolation IAW Support Procedure 16 0 Terminate & prevents injection IAW Support Procedure 17 (CT) 0 Maintains level band of -20 to +30 IAW Support Procedure 19 SRO 0 Directs reactor scram and ABN-1, Reactor Scram, prior to drywell pressure scram setpoint 0 Directs entry into RPV Control -With ATWS 0 Directs ARI initiation 0 Directs ROPS bypassed 0 Directs confirmation of automatic actions IAW Support Procedure 1 0 Directs running Recirc Flow to Minimum 0 Directs tripping of Recirc Pumps 0 Directs ADS Timer switches in Bypass 0 Directs bypass MSlV Low-Low water level isolation IAW Support Procedure 16 0 Directs BOP to terminate & prevent injection IAW Support Procedure 17 (Critical Task) 0 Directs level band of -20 to +30 IAW Support Procedure 19 0 Directs ATC to insert control rods IAW Support Procedure 21 0 Directs entry into RPV Control - No ATWS (following control rod insertions)

NRC 3 Page 10 of 14

OC NRC Re-Take Exam 2008 BOOTH Close CRD Charging water valve 15-52 for Support Procedure 21 (LOA-CRD024 to 0).

Insert LOA-CRDOI Ito 1 and LOA-CRD012 to 1 to open the B CRD FCV intetloutlet valves. Call the Control Room when this lineup is complete.

Scenario RPV injection Terminated & Prevented, and Control rods are inserted.

Terminus:

Notes/Comments I- --1 NRC 3 Page 11 of 14

OC NRC Re-Take Exam 2008 Simulator Setup

1. Reset the simulator to the normal full power IC-65

2. Run CAEP file SIMPROB

3. Reduce power to 92% with recirculation flow

4. Place a tag on the RWM Switch in BYPASS

5. Place TBCCW Pump 2 in PTL and hang tag

6. Have a prepared ReMA with the following 3 steps:

a. Reduce power to 92% with recirculation flow (already completed)

b. Withdraw the following control rods from position 12 to position 14:

i. 14-31, 14-23, 22-39, 22-15, 30-39, 30-15, 38-31, 38-23

c. Raise power to 100% with recirculation flow MALFUNCTIONS EVENT MALFUNCTION tR':IER 2 PRESET --, MAL-CRD007-382 3 o This sticks control rod 38-23 at its current position (this is the last rod to be moved on the ReMA) o DELETE this malfunction after CRD drive pressure is raised 3 TI + PMP-CRD002A o This breaks the shaft on CRD Pump NC08A 0 ICH-CFW069A from 195-300 over a 10 minute ramp o This causes condensate pump B upper bearing temperature to rise from 195 (alarm point) to 300 "F

5 T3 -+ MAL-NSS017D to 0.1% over a 5 minute ramp o This causes a small steam leak in the Drywell NRC 3 Page 12 of 14

OC NRC Re-Take Exam 2008 MAL-CRD021A to 100%

PRESETS -+ MAL-CRD021B to 100%

o This fills the SDV and results in an ATWS (no rod motion) o DELETE these malfunctions when the scram is reset 6 T4-4 MAL-CRD001A to 0 o This causes CRD FCV NC30A to fail closed

~- ~

516 MANUAL LOA-CRD024 to 0 INSERT o This will close CRD charging valve V-I 5-52 LOA-CRDO11 to 1 LOA-CRD012 to 1 o These open the standby CRD FCV inletloutlet manual valves NRC 3 Page 13 of 14

OC NRC Re-Take Exam 2008 Shift Turnover Initial Conditions 0 The plant is at 92% power 0 The RWM is inoperable and bypassed 0 TBCCW Pump 2 is tagged out of service for repair Shift Activities 0 Continue with the ReMA NRC 3 Page 14 of 14