ML082530408
| ML082530408 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/12/2008 |
| From: | NRC Region 1 |
| To: | |
| Shared Package | |
| ML081630455 | List: |
| References | |
| Download: ML082530408 (73) | |
Text
OC NRC Re-Take Exam 2008 Scenario Outline SRO BOP SRo SRO SRO SRO RO SRO BOP SRo Ro BOP RO ALL Facility: Oyster Creek Scenario No.: NRC 1 Op Test No.: 2008-1 Performs 602.4.004, Main Steam Isolation Valve 10%
Closure Test.
MSlV NS04B sticks open during Closure Test TS 3.5.3.
Respond to Loss of USS 1A2 480V bus.
APRM 6 hop. Failure causes % scram Control Rod Drift Out ABN-6 Control Rod Malfunctions Respond to trip of Service Water Pump 1-1 ABN-18 Service Water Failure Response Main Condenser Vacuum Leak Power Reduction required ABN-14 Loss of Condenser Vacuum RWCU Leak in the Reactor Building RWCU fails to isolate Secondary Containment Control EOP Emergency Depressurization required TS 3.7.B, ABN-45 LOSS Of USS 1A2 RAP-G2f Examiners:
Operators:
SRO-Steve Johnston 4
6 Initial Conditions:
100% Power 0
RWCU Pump B 00s 0
RWM is bypassed and 00s Turnover:
Perform 602.4.004, Main Steam Isolation Valve 10% Closure Test.
MAL-NIS021 F I
C MAL-CRD005-22-15 MAL-SWS001A C
Event Malf. No.
Event No.
8 I
MAL-RCUO13 VLV-RCU001 M
VLV-RCU004 n
MAL-EDSOOJB WL-CFWO17 R
7 1
1 I C MAL-CNS004C 1
orD (N)ormal, (R)eactivity, Event Description SRo [ A Containment Spray pump trips while in Torus Cooling BOP (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 1 Page 1 of 29
OC NRC Re-Take Exam 2008 NRC 1 Simulator Scenario Summarv I
Event 2
3 4
5 6
7 8
9 NRC 1 Event Summary The plant is at rated power. The BOP will peform 602.4.004, Main Steam Isolation Valve 10% Closure Test, for two MSIVs.
MSlV NS04B will stick open during the closure test requiring a TS 3.5.3 entry (TS-SRO)
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.B. (TS-SRO)
The ATC will respond to an INOP failure of an APRM. The APRM must be bypassed and the 1/2 scram reset. TS will be reviewed by the SRO (no LCO required).
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.B.4.
The BOP will respond to a trip of running service water pump 1-1.
Actions will be taken IAW RAP-Klf and ABN-18, Service Water Failure Response, to start the standby pump.
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The crew will diagnose and respond to a lowering 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 recirculation flow and condenser vacuum will stabilize.
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 TRANS I E NT)
Following entry into in Primary Containment Control EOP due to high torus temperature from EMRV operation, a Containment Spray pump will fail to start while being placed in Torus Cooling, requiring Page 2 of 29
OC NRC Re-Take Exam 2008 I the start of an alternate pump.
Critical 1
Task#l 1
Scram before any area temperature reaches MAX SAFE.
Critical Task#2 1 ED when 2 2 area temperatures exceed MAX SAFE.
NRC 1 Page 3 of 29
OC NRC Re-Take Exam 2008 Op-Test No.: 2008-1 Event
Description:
- 1. Perform 602.4.004, Main Steam Isolation Valve 10% Closure Test.
- 2. MSlV NS04B Fails to close during surveillance test.
Scenario No.: NRC 1 Events No.: 1 & 2 Initiation: As directed by the Lead Examiner.
Cues: Position indication for MSlV NS04B do not change.
Time Position SRO BOP Applicants Actions or Behavior 0
0 Reviews/applies Tech Specs 3.5.3.a.
Directs performance of surveillance 602.4.004. beginning at step 6.3.4 Declares MSlV NS04B inoperable when valve V-1-10 fails to close 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 0
Notifies Work Week ManagerIShift Manager (WWMISM) for investigationhepair 0
Updates the Crew steam line within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Test of NS03B Performs surveillance 602.4.004, starting at step 6.3.4 0 Simultaneously perform the following two steps:
0 Depress and hold TEST button for Valve V-1-0008 NS03B (Panel 11 F).
0 Start the stopwatch.
0 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.
Record stroke time 0 Verify relays 2K17 and 2K18 (Panel 7R) de-energized and all contacts opened.
NRC 1 Page 4 of 29
OC NRC Re-Take Exam 2008 0 Verify Plant Process Computer, PID: SOE47, tripped; MSlV CLOSURE SCRAM (2K17). (SOE computer points currently not functional) 0 Verify Plant Process Computer, PID: SOE48, tripped; MSlV CLOSURE SCRAM (2K18). (SOE computer points currently not functional) 0 Verify that the MSlV returns to the fully open position by the red open light illuminating.
0 Verify SCRAM SOLENOIDS lights (Panel 7R) extinguished.
0 Verify SCRAM CONTACTOR OPEN alarm (G-I -c) is received.
Verify MSlV CLOSED II alarm (J-2-a) annunciated.
Verify MN STM VLVS OFF NORMAL alarm (J-8-b) annunciated.
Verify relays 2K51 A and 2K52A (Panel 7R) are de-energized Reset the half scram.
Confirm Plant Process Computer PlDs returned to normal state. (SOE computer points currently not functional) 0 Confirm Alarms returned to normal state.
Verify all SCRAM SOLENOID lights lit (4F/7R).
Verify SCRAM CONTACTOR OPEN alarm (G-I -c) clear.
Verify MSlV CLOSED II alarm (J-2-a) clear.
Verify MN STM VLVS OFF NORMAL alarm (J-8-b) clear.
Verify relays 2K17 and 2K18 (Panel 7R) energized.
Verify relays 2K51A and 2K52A (Panel 7R) energized.
Verify Plant Process Computer PlDs SOE47 and SOE48 are normal. (SOE computer points currently not functional)
Reports MSlV NS03B tested SAT and continues with the next MSlV Test of V-1-10 NS04B (This valve will NOT stroke)
Depress and hold TEST button for Valve 0 Simultaneously perform the following two steps:
0 V-1-01 NS04B (Panel 1 1 F).
0 Start the stopwatch.
0 Observe the Red open indicating light extinguishes for NS04B.
0 Observes the valve failed to close 0 Reports failure of valve to SRO NRC 1 Page 5 of 29
OC NRC Re-Take Exam 2008 ATC 0
Acts as peer checker during the surveillance 11 Terminus: I MSlV NS04B is declared inoperable and TS have been applied.
N otes/Com men ts E
NRC 1 Page 6 of 29
OC NRC Re-Take Exam 2008
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Op-Test No.: 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; 1/2 Scram Time Position Applicant's Actions or Behavior 0
0 Reviews Tech Specs Directs entry into ABN-45, Loss of USS 1A2 o 3.7.B (AC Electrical Power)
. The reactor shall be PLACED IN the COLD SHUTDOWN CONDITION if the availability of power falls below that required by Specification 3.7.A IAW OP-OC-108-104-1001, Guidance For Limiting And Administrative Conditions For Operations, for those cases where the Reactor shall be placed in the COLD SHUTDOWN CONDITION" (no time interval specified): The Reactor shall be placed in a cold shutdown condition in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
. With one required station battery B or C charger inoperable:
- a. Restore associated station battery terminal voltage to greater than or equal to the minimum established float voltage within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />,
- b. Verify affected station battery float current I 2 amps once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and
- c. Restore station battery charger to OPERABLE status within 7 days.
If one isolation condenser becomes inoperable during the run mode the reactor may remain in operation for a period not to exceed 7 days provided the motor operated isolation and condensate makeup valves in the operable isolation condenser are verified daily to be operable.
o 3.7.D.1 (Batteries) o 3.8.C (Isolation Condensers) o 3.5.A.3 (Containment) (Most Limiting)
. For RBCCW valve V-5-167
. Maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (48 NRC 1 Page 7 of 29
OC NRC Re-Take Exam 2008 BOP hours for the traversing in-core probe system) either; (a) Restore the inoperable valve(s) to OPERABLE status or (b) Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolation position, or (c) Isolate each affected penetration by use of at least one closed manual valve or blind flange.
o Other less limiting TS 0
Notifies WWM/SM for repair/investigation of USS 1A2 0
Makes notifications for TS required shutdown 0
Directs entry into Primary Containment Control EOP when bulk Drywell temperature exceeds 150 OF o May direct Primary Containment venting IAW SP-31, Venting 0
May direct a reactor power reduction with recirculation flow to alleviate the rise in Drywell temperature/pressure the Primary Containment to Maintain Pressure Below 3.0 psig 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 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 and V-28-2 o V-28-3 and V-28-4 o V-28-5 and V-28-6 NRC 1 Page 8 of 29
OC NRC Re-Take Exam 2008 NRC 1 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
. Verifies with EO that truck ventilation hose is not in use
[ROLE PLAY I]
. Places STANDBY GAS SELECT switch in SYS 2 position
. Starts EF 1-9 by placing SGTS System Exhaust Fan contro 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 21 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 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 Page 9 of 29
OC NRC Re-Take Exam 2008 ROLE PLAY ATC
. 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 1 B2 by verifying annunciator 9XF1 c 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 0
Vents the Primary Containment IAW SP-31, if requested o Opens the Torus Vent Exhaust valve V-28-18.
o Cycles the Torus Vent Exhaust Bypass valve, V-28-47 to maintain Drywell pressure below 3.0 psig 0
Starts CRD Pump E3 running by placing its control switch to START Directs EO to investigate USS 1A2 and its feeder breaker 0
Makes announcement of loss of bus and '/2 scram 0
May refer to ABN-19, RBCCW Failure Response Reduces reactor power with recirculation flow, if directed 0
Directs EO to raise Service Water flow through the RBCCW heat exchangers [ROLE PLAY 41
- 1) When asked as the EO to verify that truck ventilation hose is not in use in the RB railroad airlock, report that it is not in use.
- 2) To re-energize Protection System Panel 1 from USS 1B2:
to open disconnect switch SW-733-169 and to close disconnect switch SW-733-170, insert LOA-EDSI 33 to 1 B2 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.
- 3) 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.
- 4) If asked to raise SW flow to the RB, INSERT LOA-SWSOO6 and LOA-SWSWOO7 to 10% ABOVE the current value (opens further SW out of the RBCCW heat exchangers). Call the Control Room when complete.
NRC 1 Page 10 of 29
OC NRC Re-Take Exam 2008 requested to pull the annunciator card for the alarming Hi Drywell annunciator (Ch8), place this annunciator to OFF 1
has been performed and the SRO has addresses Technical Specifications.
N otes/Com me n ts NRC 1 Page 11 of 29
OC NRC Re-Take Exam 2008 Op-Test No.: 2008-1
==
Description:==
APRM 6 INOP [TRIGGER 21 Scenario No.: NRC 1 Event No.: 4 Initiation: As directed by Lead examiner Cue: Annunciators G2f, APRM HI-HIIINOP; G2d: CHANNEL 11; Glc, SCRAM CONTACTOR OPEN Time Terminus:
Position ATC BOP SRO Applicants Actions or Behavior 0
Responds to annunciator G2f, APRM HI-HI/INOP, G2d, Channel II, and Glc, SCRAM CONTACTOR OPEN o Reports 1/2 scram RPS System 2 o Reports APRM 6 DN SCL OR INOP light is ON and other APRMs indicate normally 0
Bypasses APRM 6 by placing APRM BYPASS in CH 6 position (Panel 4F) 0 Resets 1/2 scram by depressing SCRAM SYSTEM RESET pushbutton (Panel 4F) 0 Reports APRM bypassed and 1/2 scram reset 0
Completes Attachment 403-2 0
Makes a plant announcement for the scram 0
Checks APRM 6 on back panel and reports INOP light is ON (Panel 5F) 0 Directs bypassing APRM 6 IAW procedure 403 and resetting 1/2 scram 0
May request Attachment 403-2 updated.
0 May review TS 3.1 (no action required) 0 Notifies WWM/SM for APRM 6 repair APRM 6 is bypassed and 1/2 scram reset.
NRC 1 Page 12 of 29
OC NRC Re-Take Exam 2008 N otes/Com men ts ;
1 NRC 1 Page 13 of 29
OC NRC Re-Take Exam 2008 Op-Test No.: 2008-1 Scenario No.: NRC 1 Event No.: 2 lescription: Control Rod 22-1 5 Drifts OutwarcJ [TRIGGER 31
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Initiation: As directed by Lead Examiner Cue: Annunciator H6a, ROD DRIFT Time 1
Position 1
ATC Applicants Actions or Behavior 0
0 0
0 Reports 1 control rod drifting outward (22-15)
Refers to annunciator response H6a Refers to ABN-6 Control Rod malfunctions 0 Confirms Rod Power Switch is ON 0 Selects 22-1 5 0 Applies an insert signal to 22-15 to position rod back to 1 2, then releases switch Recognizes outward motion continues and reports to SRO 0 Applies continuous insert signal 0 After BOP action to scram the rod, removes insert signal Recognizes rod remains at 00 and directs EO to isolate Turns Rod Power OFF 0 Notifies Chemistry (to sample) and Reactor Engineering Monitors for fuel failures Informs SRO to consult TS 3.2.
HCU 22-15 [ROLE PLAY]
Scrams CR 22-15 IAW procedure 302.2 Control Rod Drive Manual Control System [BOOTH]
Unlocks Panel 6XR Selects control rod 22-15 and places the toggle switch 22-15 to the open (scram) position Verifies that the scram display illuminates on rod 22-1 5 position indicator (Panel 4F) and monitors the movement of the selected rod When rod movement stops or rod is fully inserted, then immediately remove the scram signal by placing the toggle switch to the closed position (down position)
NRC 1
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Page 14 of 29
OC NRC Re-Take Exam 2008 ROLE PLAY BOOTH Terminus:
SRO 0 Verifies the scram signal is removed by observing thl de-energization of the scram display on the CRD position indicator Locks Panel 6XR 0 Returns key to key locker in SM office 0
Directs entry to ABN-6 Refers to TS 3.2.6.4, declares Control Rod 22-15 inoperable; verifies <6 inoperable control rods Notifies WWM/SM/RE about the control rod drift When directed to isolate HCU 22-15, wait one minute and then report t HCU 22-15 is isolated.
IF as SM/RE to scram control rod 22-15, report that it is allowed.
When the control rod indicates a scram condition DELETE the rod drift ma Ifu n ct ion.
Control Rod 22-15 is at 00 and scrammed; TS have been addressed.
N otes/C om me n ts --
NRC 1 Page 15 of 29
OC NRC Re-Take Exam 2008 Op-Test No.: 2008-1 Even
Description:
Service Water Pump 1-1 Trig [TRIGGER 41 Scenario No.: NRC 1 Event No.: 6 Initiation: As directed by Lead Examiner Cue: Annunciator Klf, SVC WATER PUMP TRIP; Breaker open indication for Service Water Pump 1-1 ; Service Water pressure indication downscale Time ROLE PLAY Term in us:
Position BOP SRO Applicants Actions or Behavior 0
Responds to annunciator K l f 0
May suggest entry into ABN-19, RBCCW Failure Response 0
Reports Service Water Pump 1-1 has tripped 0
Performs ABN-18, Service Water Failure Response o Starts Service Water Pump 1-2 by placing SERVICE WATER PUMP 1-2 switch to START o Reports service water flow re-established Dispatches EO to check SW pump 1-1 and 1-2 Reviewsldirects entry into ABN-18, Service Water Failure
Response
Notifies WWM/SM about SW Pump 1-1 Trip Report back as EO, SW pump 1-1 motor is hot to the touch. Report a good start on Service Water Pump 1-2 and no reverse rotation on SW Pump 1-1.
Service water pump 1-2 has been started.
Notes/Comments 1 NRC 1 Page 16 of 29
OC NRC Re-Take Exam 2008 NRC 1 Page 17 of 29
OC NRC Re-Take Exam 2008 Terminus:
Op-Test No.: 2008-1 Scenario No.: NRC 1 Event No.: 7 Even
Description:
Main Condenser Vacuum Leak; Power Reduction required
[TRIGGER 51 Rapid Power Reduction Complete, Condenser Vacuum Stable.
Initiation: As directed by the Lead Examiner
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Cues: Annunciator: Q3c Cond Vac Lo 25 inches, Generator MWe decreases Time Position BOP SRO RO Applicants Actions or Behavior 0
Recognize condition by observing indications or reporting alarms 0
Responds to RAP Q3c: COND VAC LO 25 INCHES 0
Responds to ABN-14 Loss of Condenser Vacuum 0 Monitors vacuum 0 Confirms Circ Water pumps operating 0 Confirms SJAEs operating 0 Confirms Gland seal system operating 0 Confirm vacuum breaker V-2-44 is closed Makes plant announcement for degrading vacuum 0
Directs entry into ABN-14, Loss of Condenser Vacuum.
0 Directs a power reduction as necessary to maintain vacuum greater than 22 inches 0
Makes notifications for power reduction.
_ _ _ _ ~ _ _
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 no time delay when power reduction NRC 1 Page 18 of 29
OC NRC Re-Take Exam 2008 N otes/Com me n ts NRC 1 Page 19 of 29
OC NRC Re-Take Exam 2008
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Op-Test No.: 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 Emergency Depressurization [TRIGGER 61 Initiation: As directed by Lead Examiner Cues: Annunciators L ~ c,
RB AP LO; 10F3k, CU SYS AREA HI; 1OF1 k, AREA MON HI; D8d, CU ROOM TEMP HI; Dld/D2d: RWCU HELB I and It Time NRC 1 Position SRO Applicants Actions or Behavior Directs entry into Secondary Containment Control EOP on RB AP low May direct BOP to Perform SP-50 to start RB HVAC System (Note: this SP is complicated by the loss of USS 1A2)
Directs RO to monitor RB area temperatures and radiation levels Directs re-entry into Secondary Containment Control EOP o Directs RWCU isolation o Directs WWMISMINLOs notified to close the RWCU valves o Before any area temperature reaches MAX SAFE, directs manual scram and entry into RPV Control - No AlWS 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 When 1 area temperature is above MAX SAFE, may declare Emergency Depressurization is anticipated 9
Directs ROPS bypassed
. Directs one or more of the following to rapidly depressurize the RPV:
turbine bypass valves opened Isolation Condensers placed into service (IAW SP-
- 11) if RPV water level allows Directs the Reactor Building evacuated 0
Page 20 of 29
OC NRC Re-Take Exam 2008 BOP 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 0
Responds to annunciator L ~ c,
RB AP LO o Reports RB AP is >O Performs SP-50, Reactor Building Ventilation Restart o Verifies REACTOR BUlLlDNG VENT MANIFOLD NO. 1 and 2 are c 9 mrem/hr (Panel 2R) o In rear of Panel 11 R:
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 1-6 IAW 329, RB Heating, Cooling and Ventilation System 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 Responds to Area Radiation Monitors alarms o Reports RWCU area radiation rising o Announces area of rising radiation over the PA System, if d i rected o Monitors RWCU area temperatures (Panel 10R) o Reports RWCU area temperatures rising Responds to high area temperature alarms 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 11 F and Panel 3F) o Reports RWCU cannot be manually isolated 0
Monitor RB area temperatures and radiation levels as 0
Removes EOP BYPAS PLUG from BP4 Inserts EOP BYPAS PLUG into BPI 0
0 NRC 1 Page 21 of 29
OC NRC Re-Take Exam 2008 ATC directed (Panel IOR) o Reports when 1 area temperature is above MAX NORMAL o Reports when 1 area temperature is above MAX SAFE 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) if 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. (TBV will not open manually)
(Panel 7F)
IF directed to anticipate Emergency Depressurization o Opens turbine bypass valves by placing BYPASS VALVE and continues to monitor and continues to monitor 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 I
F12F) o Opens EMRVs by placing AUTO DEPRESS VALVE o Reports 5 EMRVs open switches to MAN 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 beains to rise. trim 2 feedwater NRC 1 Page 22 of 29
OC NRC Re-Take Exam 2008 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 SIA and SIB are closed Places ROPS switch in BYPASS, when directed (Panel 4F)
If asked to investigate RWCU alarms, WAIT 2 minutes, then report that steam is coming out of the Cleanup Room on elevation 51.
Terminus 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 3-
-1 NRC 1 Page 23 of 29
OC NRC Re-Take Exam 2008 Op-Test No.: 2008-1 Scenario No.: NRC 1 Event No.: 9 Event
Description:
Trip of Containment Sprav Pump while in Torus Cooling Initiation: As directed by the Lead Examiner.
Cues: Selected Containment Spray Pump does not indicate normal running indications.
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Time BOOTH Terminus:
E-PLAN Position SRO BOP Applicants Actions or Behavior 0
0 Enters Primary Containment Control EOP when Torus Temperature reaches 95 degrees F.
Directs initiation of Torus Cooling IAW Support Procedure 25 0
0 Reports Torus water temperature 95 O F Places Torus cooling in service as follows IAW SP-25: [BOOTH]
0 CONFIRMS the SYSTEM MODE SELECT SWITCH for the selected system is in the TORUS COOLING position 0 Starts the selected ESW pump 0 Places and Holds the System Pump Start Permissive Keylock for the selected pump in the appropriate position 0 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.
After the first pump start is attempted, DELETE the trip on the other containment spray pump.
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.
FSI : SAE due to LOSS of primary containment barrier AND POTENTIAL LOSS of reactor coolant system barrier.
NRC 1 Page 24 of 29
OC NRC Re-Take Exam 2008 Notes/Comments 1 NRC 1 Page 25 of 29
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. Have a copy of procedure 602.4.004 (MSIV Surveillance Test) completed up to step 6.3.3
- 4. Have the stopwatch available
- 5. Have a signed Attachment 403-2 (with no inoperable components) and a clean, unsigned 403-2
- a. Place these in the 403 Binder
- 6. Place a tag on the RWM Switch in BYPASS
- 8. Verify Service Water Pump 1-1 in service MALFUNCTIONS 1
EVENT I
1 2
L I
3 1-6 TRIGGER NA PRESET -+
T I -+
T2-T3-9 T4-3 MALFUNCTION VLV-RPSOO4 FAIL AS IS o This sticks MSIV NS04B (V-1-10) in its current open position MAL-EDS003B o This results in the loss of USS 1A2 MAL-NIS021 F o This causes an INOP trip of APRM 6 MAL-CRD005-2215 o This causes control rod 22-15 to drift out MAL-SWS001A o This causes service water pump 1-1 to trip NRC 1 Page 26 of 29
7 8
9 OC NRC Re-Take Exam 2008 T5-4 PRESETS-,
T6-4 PRESETS-,
PRESET--,
MAL-CFWO17 0.5 - 1.OO% over 5 minutes o This inserts condenser air leakage o INSERT this malfunction to 0% with no time delay when the power reduction is started or ordered VLV-RCU001 to MECH SEIZE (V-16-1)
VLV-RCU004 to MECH SEIZE (V-16-14) o This keeps the RWCU isolation valves open 0
MAL-RCUOI 3 0-20% over 20 minutes o This inserts a unisolable RWCU leak into the Reactor Building SWI-TCSOI 1 D to OFF SWI-TCSOI 1 E to OFF o This prevents the Operator from opening the TBV with the opening jack switch MAL-CNS004C (Containment Spray Pump 51 C) 0 MAL-CNS004D (Containment Spray Pump 51 D) o This trips the containment spray pumps o WHEN the first containment spray pump start is attempted and tripped, DELETE the other pump trip malfunction NRC 1 Page 27 of 29
OC NRC Re-Take Exam 2008 Procedures Used Event 1 Event 2 Event 3 Event 4 Event 5 Event 6 Event 7 Event 8 602.4.004 (This was handed out with the initial conditions) 602.4.004 (This was handed out with the initial conditions)
RAP-S7f RAP-9XF3a RAP-GI c RAP-G2c ABN-45 RAP-G2d RAP-Glc 03-2 RAP-H 6a ABN-6 RAP-Klf ABN-18 RAP-Q3c ABN-14 RAP-L6c RAP-I OF3k RAP-I OF1 k RAP-D 8d RAP-Dld, -D2d ABN-1 RPV Control - No ATWS EOP RAP-U3a Primary Containment Control EOP Support Procedure 31 202.1 (power reduction) 403 (APRM bypass) 302.2 (single rod scram) 202.1 (power reduction)
Secondary Containment Control EOP SP-50 SP-1 s P-2 SP-3 ED - NO ATWS EOP SP-25 NRC 1 Page 28 of 29
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 surveillance o The SOE computer points are currently NOT functioning and the associated procedure steps have been N/Ad as appropriate NRC 1 Page 29 of 29
OC NRC Retake Exam 2008 Scenario Outline Event No.
1 2
3 Facility: Oyster Creek Scenario No.: NRC 2 Op Test No.: 2008-1 I
Malf. No.
Event Event TY Pe Description N/A N
SRo generator voltage control to automatic IAW 336.1 N/A R
SRo Increase reactor power with control rods Restore the amplidyne to service and transfer main 24KV Main Gen Electrical System BOP MAL-SRO Uncoupled Control Rod ATC ABN-6 Control Rod Malfunction CRD008-34-11 Examiners:
Operators:
SRO-Steve Johnston 4
C SRO EMRV A Inadvertently Opens TS BOP ABN-40 Stuck Open EMRV; TS 3.4.B SWI-ADS001C ANN-EGD ANN-E2D Respond to Reactor Recirc Pump A Alarms, Pump Discharge Valve fails to close ABN-2 Recirculation System Failures TS 3.3.F.
SRo VLV-NSSOOG TS MAL-CRD005 6
MAL-RPSOOG C
SWI-RPS006 MAL-NSSOI 7A MAL-PCN001 N C
VLV-CNSOOG PMP-CNS008A 9
MAL-RPS007 Multiple control rod drifts, Manual scram required and ABNB Control Rod Malfunction Steam leak in Primary Containment, DW/Torus Containment Spray System failures leads to Failure of RWCU System to automatically isolate on SRo fails, ARI required ALL Vacuum Breaker fails open SRO ALL Emergency Depressurization ALL high DW pressure (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 2 Page 1 of 26
OC NRC Retake Exam 2008 NRC 2 Simulator Scenario Summarv Event 1
2 3
4 7
8 9
Event Summary The BOP will place the main generator voltage control in automatic voltage control IAW 336.1, 24KV Main Generator Electrical System. (NORMAL EV 0 LUT IO N)
The ATC will increase reactor power with control rods per the ReMA.
(REACTIVITY MANIPULATION)
The ATC will respond to an uncoupled control rod IAW ABN-6 Control Rod M a If u n ct i o n. (C 0 M PO N E NT MAL F U N C T I 0 N )
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 OF, the SRO will direct entry into the Primary Containment Control EOP and directs initiation of Torus Cooling.
(COMPONENT MALFUNCTION) (TS)
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)
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)
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)
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. (INSTRUMENT MALFUNCTION after EOP)
~~
~
When Drywell pressure exceeds the scram/isolation setpoint, the RWCU System will fail to automatically isolate requiring a manual isolation during the performance of Support procedure 1.
NRC 2 Page 2 of 26
Critical Task #I Critical Task #2 OC NRC Retake Exam 2008 With the failure of the scram pushbuttons and the reactor mode switch, ARI is manually initiated to insert control rods.
Initiate Emergency Depressurization with EMRVS when it has been determined that Torus pressure cannot be maintained below Primary Suppression Pressure Limit (PSP), or when it has been determined that bulk Drywell temperature cannot be restored and maintained below 281" F.
NRC 2 Page 3 of 26
OC NRC Retake Exam 2008 Op-Test No.: 2008-1 Scenario No.: NRC 2 Event No.: 1 Event
Description:
Shift from manual generator voltage control to automatic generator voltage control IAW procedure 336.1, 24 KV Main Generator Electrical Svstem, Section 6.0
~
Initiation: Following shift turnover Cues: As directed by the SRO Time Position SRO BOP NRC 2 Applicants Actions or Behavior 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.
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 1Al bus ammeter for an amp deflection.
CONFIRM amplidyne motor started as indicated by the amp deflection on 1Al 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 PLACE the AMPLIDYNE CONTROL 43CS switch to ON, which leaves the AMPLIDYNE controlling excitation.
scale.
REMOVE VOLTAGE CONTROL IN MANUAL operator aids Page 4 of 26
OC NRC Retake Exam 2008 Role Play Terminus:
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.
0 0
As the NLO, when directed to verify the amplidyne running, state the amplidyne is running. --
The amplidyne is in automatic control.
NoteslComments 7
1 I
I NRC 2 Page 5 of 26
OC NRC Retake Exam 2008 Op-Test No.: 2008-1 Scenario No.:
NRC 2 Event No.: 2 & 3 Event
Description:
I. Withdraws control rods for a power increase IAW the ReMA (14-1 5, 14-39, 38-15, 38-39, 18-43, 18-1 1, 34-43, 34-1 1 from position 40 to 48)
- 2. Uncoupled Control Rod 34-1 1 Initiation: As directed by Lead Examiner Cues: Annunciator H5a, ROD OVERTRAVEL Time Position SRO BOP ATC Applicant's Actions or Behavior 0
Conducts a pre-job reactivity maneuver brief.
0 Directs the ATC to withdraw control rods IAW the reactivity maneuver approval sheet (ReMA).
Acts as the Reactivity Manager during the evolution.
0 Directs entry into ABN-6, Control Rod Malfunctions, when the control rod becomes uncoupled 0
Notifies the Reactor Engineer about the uncoupled control rod [ROLE PLAY]
~
~
~~~
~_________
~
Provides a peer-check for withdrawing control rods and initials on the reactivity maneuver sheet after each control rod is withdrawn.
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 OVERR I DE o Amber OVERRIDE light is ON Verifies:
NRC 2 Page 6 of 26
OC NRC Retake Exam 2008 NOTE ROLE PLAY BOOTH 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 0
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 OVE RR I DE 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 Signs the ReMA when complete Reports all control rods withdrawn IAW the reactivity maneuver approval form Control rod 34-1 1 will be uncoupled.
u As the Reactor Engineer for the uncoupled rod, acknowledge the report. IF the control rod is inserted to between 24-48 during re-coupling, direct that continuous withdrawal is allowed. Below this, single notch, until position 24, then continuous withdraw is allowed. 3 When the RO is inserting the uncoupled control rod, DELETE the uncoupled control rod malfunction.
NRC 2 Page 7 of 26
OC NRC Retake Exam 2008
~-
The uncoupled control rod has been re-coupled and all control rods have been withdrawn.
1 N otes/Com m en ts I
-1 NRC 2 Page 8 of 26
OC NRC Retake Exam 2008 Op-Test No.: 2008-1 Scenario No.: NRC 2 Event No.: fl Event
Description:
EMRV NR-108A opens spuriouslv [TRIGGER I ]
Initiation: As directed by Lead Examiner Cues: Annunciators B3g, EMRV OPEN; B4g, SV/EMRV NOT CLOSED; EMRV NR-108A indicates in the VALVE OPEN REGION (TRIGGER 1)
Time Position BOP Applicants Actions or Behavior 0
0 Responds to annunciators B3g, EMRV OPEN and B4g, SV/EMRV NOT CLOSED Identifies and reports EMRV NR108A is open Performs actions IAW ABN-40, Stuck Open EMRV o Places the MASTER FEEDWATER CONTROLLER in MAN [Panel o Places EMRV NR108A AUTO DEPRESS VALVE switch in OFF
[Panel 1 F/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 NORMAL/DISABLE 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 o Resets the MASTER ALARM units in Panel 15R to silence the 4 FI NRC 2 Page 9 of 26
ATC SRO OC NRC Retake Exam 2008 acoustic monitor alarm o Plots EMRV downcomer temperature IAW Procedure 602.4.003, Electromatic Relief Valve Operability Test o Refers the SRO to Technical Specifications 4.5.F.5 and 4.5.L for su rvei I la nce requirements following EM RV actuation 0
0 0
0 -
Monitors Torus water temperature while EMRV is open Announces EOP entry on high torus water temperature (if it exceeds 95 O F )
Performs SP-25, Initiation of the Containment Spray System in the Torus Cooling Mode, if directed (Panel 1 F/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 1 (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 0
Directs entry into ABN-40, Stuck Open EMRV 0
Declares EMRV NR108A inoperable and reviews/applies TS 3.4.B.2 o If at any time there are only four operable electromatic relief valves, the reactor may remain in operation for a period not to exceed 3 days provided the motor operated isolation and condensate makeup valves in both isolation condensers are verified daily to be operable Refers to TS 4.5.F.5, and 4.5.L o 4.5.F.5.a 0
o Once every 3 months and following any release of energy which would tend to increase pressure to the suppression chamber, each OPERABLE suppression chamber - drywell vacuum breaker shall be exercised. Operation of position switches, indicators and alarms shall be verified every 3 months by operation of each OPERABLE vacuum breaker.
o Whenever heat from relief valve operation is being added to the suppression pool, the pool temperature shall be continually 0 4.5.L.3 NRC 2 Page 10 of 26
OC NRC Retake Exam 2008 monitored and also observed until the heat addition is terminated 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 O F )
o Directs torus cooling initiated IAW SP-25 EMRV NR-108A is DISABLED, the SRO has reviewed Tech Specs and briefed the Crew. Torus Cooling has been initiated, if required.
Notes/Comments I
NRC 2 Page 11 of 26
OC NRC Retake Exam 2008 Op-Test No.: 2008-1 Scenario No.: NRC 2 Event No.: 2 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 BOP ATC Applicants Actions or Behavior 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 0
Annunciator OIL LEVEL HI/LO, E6d o Reports that immediate pump trip is required IAW the RAP-E6d 0
Manually trips Reactor Recirc. Pump A o Place Recirc Pump A DRIVE MOTOR switch to STOP position Refers to ABN-2, Recirculation System Failures o Confirms open the DISCH BYPASS valve open for Recirculation Pump A (V-37-11) o Closes the Recirculation Pump A DISCHARGE valve (V-37-10) o Recognizes failure of discharge valve to close and reports to the SRO o Closes the Recirculation Pump A SUCTION valve (V-37-9) o Contacts Electrical maintenance to attempt closure of Recirculation Pump A discharge valve o Verifies the plotted point on the Power Operation Curve o Informs SRO to review TS 3.3.F., Recirculation Loop Operability, and 3.1 O.A., Core Limits o Selects an operating recirculation loop temperature point o Monitors for fuel failures: Monitors Offgas activity, Main Steam Line radiation, and reactor coolant activity Changes reactor pressure, if directed, by changing the EPR setpoint (980-1 020) [Panel 7F]
0 Refers to ABN-2, Recirculation System Failures o May verify operation on Power Operations Curve NRC 2 Page 12 of 26
OC NRC Retake Exam 2008 Termin us:
SRO Directs trip of Reactor Recirculation Pump A, IAW RAPS Directs entry into ABN-2, Recirculation System Failures Refers to Tech Spec 3.3.F, 3.10.A o 3.3.F.3 o If Specifications 3.3.F.1 and 3.3.F.2 are not met, an orderly shutdown shall be initiated immediately until all operable control rods are fully inserted and the reactor is in either the REFUEL MODE or SHUTDOWN CONDITION within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> o 3.10.A o During POWER OPERATION the maximum AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) for each fuel type as a function of exposure shall not exceed the limits specified in the CORE OPERATING LIMITS REPORT (COLR).
If at any time during POWER OPERATION it is determined by normal surveillance that the limiting value for APLHGR is being exceeded, action shall be initiated to restore operation to within the prescribed limits. If the APLHGR is not returned to within the prescribed limits within two (2) hours, action shall be initiated to bring the reactor to the COLD SHUTDOWN CONDITION within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. During this period surveillance and corresponding action shall continue until reactor operation is within the prescribed limits at which time POWER OPERATION may be continued.
Notify System OwnerIDispatcher, Chemistry, Reactor Engineering, WWMISM Directs that an immediate orderly plant shutdown be initiated IAW procedure 203, Plant Shutdown Recirc. Pump A has been manually tripped and suction valve closed; Tech Specs reviewed, and maintenance contacted.
NRC 2 Page 13 of 26
OC NRC Retake Exam 2008 N otes/Com men ts r
NRC 2 Page 14 of 26
OC NRC Retake Exam 2008 Op-Test No.: 2008-1 Scenario No.: NRC 2 Event No.: 5 Event
Description:
Multiple rod drifts; Scram Required; Manual Scram Fails: ARI required Control rod drifts: 10-1 1, 10-1 9, 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 ATC SRO Applicants Actions or Behavior Responds to Annunciator H6a-Rod Drift Recog n izesheports multiple control rod drifting Initiates a reactor scram IAW ABN-1, Reactor Scram 0 Presses MANUAL SCRAM RPSI and RPS2 pushbuttons 0 Places REACTOR MODE SELECTOR Switch to SHUTDOWN Recognizes/Reports failure to Scram Initiates ARI by pressing ALT ROD INJECTION INITIATION pushbutton (Critical Task)
Reports all rods inserted Controls RPV level band of 138 - 175 IAW Support Procedure 2 (FeedwaterKondensate) & 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
~-
e Directs Reactor Scram when multiple rod drifts are reported e May enter RPV Control w/ATWS EOP momentarily Enters RPV Control - No ATWS EOP on low RPV water level when informed that all control rods are full-in Directs a RPV level band of 138 - 175 IAW Support Procedure 2 (Feedwaterlcondensate) & Support Procedure 3 (CRD)
NRC 2 Page 15 of 26
OC NRC Retake Exam 2008 0 May direct a pressure band of 800 - 1000 psig with turbine bypass valves I
BOP I
May assist in controlling RPV level & Pressure as directed by SRO and ARI initiated, which results in all control NotedComments I----
~ -1 NRC 2 Page 16 of 26
OC NRC Retake Exam 2008 Op-Test No.: 2008-1 Event
Description:
- 1. Steam leak in the Primary Containment; DWiTorus Vacuum Breaker Fails open (TRIGGER 4)
- 2. Containment Spray System Failures; Failure of RWCU Isolation Valves to isolate Scenario No.: NRC 2 Events No.: 7 & 8 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 HIILO, followed by Hld, H2d, DW PRESS HI-HI I & 11; C4f/C5f, TORUS/DW 1/2 VAC BRKR OPEN Time
~
NRC 2 Position BOPlATC Applicants Actions or Behavior Responds to ann unci a tor C4flC5f o Dispatches an EO to the local panel to determine which vacuur Responds to annunciator C3f, DW PRESS HVLO Reports Drywell pressure and temperature are rising Reports hi Drywell pressure and entry into Primary Containment Control EOP and RPV Control - No ATWS EOP Monitorsheports Primary Containment parameters Confirms automatic actions, IAW Support Procedure 1 (See Event
- 9)
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 11 R) 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-2 1 - 1 3) is closed.
o VERIFY that the system DW Spray Discharge valve, V-21-11 (V-2 1-5) 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 Keylock for the selected pump in the appropriate position.
breaker is open Reports that Containment Spray System 1 discharge valve (V -
Page 17 of 26
OC NRC Retake Exam 2008
- 11) will not open, and continues with Containment Spray System 2 0
Reports that Containment Spray Pump 51 C indicates no flow 0
Reports Containment Spray Pump 51 D starts and is operating normally 0
Reports that PSP is rising and when near violated 0
Reports PSP is violated 0
Performs Emergency Depressurization when directed (Critical Task) o Stops injection with Core Spray not required for adequate core cooling IAW Support Procedure 10 o OVERRIDE the Core Spray initiation logic by performing the following at the Core Spray Control Logic:
o PRESS the OVERRIDE switches for all the sensors that are lit.
o PRESS all ACTUATED switches whether lit or unlit.
o CONFIRM Closed Core Spray System 1 and System 2 Parallel Isolation Valves not required for assuring adequate core cooling.
o 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.
o 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.
o Bypasses ROPS by placing ROPS switch in BYPASS o Verifies Torus water level > 90 o Opens 4 EMRVs by placing all AUTO DEPRESS VALVE switches in the MAN position o Reports 4 EMRVS open Performs alternate RPV depressurization as directed:
o Isolation Condensers IAW SP-11 o IC LoopA o Confirms Recirculation Pump A is tripped o Verifies RPV water level is below 160 o Opens Condensate Return Valve V-14-34 with its control switch o IC Loop B o Confirms Recirculation Pump E is tripped by placing RECIRC PUMP E DRIVE MOTOR switch to STOP o Verifies RPV water level is below 160 NRC 2 Page 18 of 26
OC NRC Retake Exam 2008 SRO o Opens Condensate Return Valve V-14-35 with its control switch o Places the BYPASS VALVE OPENING JACK switch to RAISE o Turbine Bypass Valves 0
Reports Torus water temperature 95 O F
0 Directs entry into Primary Containment Control EOP and re-enters RPV Control - No ATWS EOP on high Drywell pressure o Directs automatic actions confirmed IAW Support Procedure 1 o Before DWiTorus reaches 12 psig, directs lineup of Drywell Sprays IAW Support Procedure 29 o When DWiTorus exceeds 12 psig, or before bulk DW temperature reaches 281 O F, directs initiation of Drywell Sprays IAW Support Procedure 29 o When it has been determined that bulk DW temperature cannot be restoredlmaintained below 281 F or it has been determined that Torus pressure cannot be maintained below Pressure Suppression Pressure, then directs Emergency Depressurization (Critical Task)
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 > 90 o Directs 5 EMRVs open o With 5 EMRVs open, directs alternate bRPV depressurization paths:
o Isolation Condensers IAW SP-11 o Turbine Bypass Valves Re-enters Primary Containment Control EOP on high Torus water temperature Site Area Emergency (FSI): Loss of Reactor Coolant Barrier and loss of Primary Containment Barrier NRC 2 Page 19 of 26
OC NRC Retake Exam 2008 Terminus:
The RPV has been emergency depressurized with EMRVs and RPV water level 4
N otes/Com men ts NRC 2 Page 20 of 26
OC NRC Retake Exam 2008 Op-Test No.: 2008-1 Scenario No.: NRC 2 Event No.: 9 Event
Description:
Reactor Water Cleanup System Fails to Automaticallv Isolate on a high Drywell Pressure Condition Initiation: Following shift turnover Cues: As directed by the SRO Time E-Plan Term i n us :
Position SRO BOP Applicants Actions or Behavior 0
Directs performance of SP-1 Confirmation of Automatic Initiations and Isolations, following a high Drywell pressure condition 0
Performs SP-1 0
Reports RWCU did not isolate 0
Closes RWCU System isolation valves with their control switches V-16-1 V-16-14 V-16-61 Site Area Emergency (FSI): Loss of Reactor Coolant Barrier and Loss of Primary Containment Barrier.
The RWCU System is manually isolated.
Notes/Comments i
1 t
NRC 2 Page 21 of 26
OC NRC Retake Exam 2008 PRESET 3 Simulator Setup MAL-CRD008-3411 o This makes control rod 34-1 1 uncoupled
- 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 14-1 5, 14-39, 38-1 5, 38-39, 18-43, 18-1 1, 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 1
EVENT 1
TRIGGER 1
MALFUNCTION I
3 o DELETE this malfunction when the operator is driving the control rod inward to re-couple 4
1 T I - +
1 SWI-ADS001C to ON o This makes EMRV NR108A open by its control switch.
This does allow the EMRV to close when DISABLED NRC 2 Page 22 of 26
OC NRC Retake Exam 2008 5
6
~~
PRESET --+
T2 -+
T3 -+
T4 -+
PRESETS 3 VLV-NSSOO6 to MECH SEIZE o This keeps Recirculation Pump A discharge valve open o This makes annunciator E6d (Recirc. Pump A OIL LEVEL HVLO) alarm ANN-E6d to ON 0
ANN-E2d with a 60-second time delay o This makes annunciator E2d (Recirc. Pump A VIBRATION HI) alarm after 60 seconds MAL-CRD006~1011 0
MAL-CRD006-1019 with a 5 second time delay 0
MAL-CRD006-0623 with a 5 second time delay 0
MAL-CRD006-0627 with a 5 second time delay o This will drift-in control rod 10-1 1, followed by rods IO-19, 06-23 and 06-27 5 seconds later SWI-RPS006A to OFF o This ensures the MODE switch is not placed in SHUTDOWN position o This fails the RPS scram pushbuttons o Taken together, this represents a failure of the mode switch and scram buttons (manual scram failure)
MAL-RPSOO6 0
MAL-NSSOI 7D 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 MAL-RPS007C o This prevents the RWCU System to auto isolate on high DW pressure (but does allow manual isolation) o This prevents Containment Spray System I DW spray valve V-21-11 from opening (See next page)
VLV-CNS008 to MECH SEIZE NRC 2 Page 23 of 26
9 1
PRESET-,
OC NRC Retake Exam 2008 PMP-CNS008A o This breaks the shaft on Containment Spray Pump 51C MAL-RPS007C o This prevents the RWCU System from automatically isolating on a high Drywell pressure condition, but allows manual isolation NRC 2 Page 24 of 26
OC NRC Retake Exam 2008 I Eventl I Event 2 & 3 Event 4 Event 5 r-Event 6 Event 7 & 8 Procedures Used 336.1 (This was handed out with the initial conditions)
ReMA (This was handed out with the initial conditions) 302.2 RAP-B3g RA P - B4g RAP-E2d RAP-E6d RAP-H6a RPV Control - W/ATWS EOP RPV Control - No ATWS SP-1 s P-2 SP-3 Primary Containment Control EOP SP-29 SP-10 RAP-H5a ABN-6 ABN-40 Primary Containment Control EOP 5p-25 ABN-2 203 ABN-1 ED - NO AWS EOP 5p-11 NRC 2 Page 25 of 26
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 26 of 26
OC NRC Re-Take Exam 2008 Scenario Outline NIA R
Facility: Oyster Creek Scenario No.: NRC 3 Op Test No.: 2008-1 ATC Examiners :
Operators:
RO-Steve Johnston Initial Conditions:
0 92%Power 0
RWM bypassed and 00s 0
TBCCW pump 2 00s Turnover:
0 Raise reactor power IAW the ReMA Event No.
1 5
6 NSSOl7A
/ M I ALL MAL-CRD021A MAL-1 1
CRD021 B MAL-I c 1 ATC CRDOOIA Event Description Raise Reactor Power with Control Rods CRD Pump 1A Shaft Failure Stuck Control Rod Condensate Pump B Motor Bearing Hi Temp Requires Power Reduction with Recirculation Flow to Approximately 65% power Small Steam Leak in Primary Containment with Hydraulic A W S CRD Flow Control Valve Fails Closed Requiring Alternate Control Rod Insertion Methods (N)ormal, (R)eactivity, (I)nstrurnent, (C)ornponent, (M)ajor Transient (TS) Tech Spec NRC 3 Page 1 of 18
OC NRC Re-Take Exam 2008 NRC 3 Simulator Scenario Summary Event 1
2 3
4 5
6 Critical Task # I Critical Task #2 Event Summary The ATC will be directed to increase reactor power with control rods IAW the Reactivity Maneuver Approval Form (ReMA). (REACTIVITY MAN I PU LATl ON)
While increasing power with control rods, the running CRD Pump 1A will develop a shaft shear. After local investigation, the ATC will start the redundant CRD pump IAW RAP-Hlc. The SRO will declare a 7-day LCO IAW TS 3.4.D.2. (COMPONENT MALFUNCTION)
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)
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)
~
~~
A steam leak in containment with a hydraulic ATWS will occur requiring entry to Primary Containment Control EOP and RPV Control w/AlWS EOP. The ATC will insert rods per Support Procedure 21. (MAJOR)
While the ATC is inserting control the CRD flow control valve will fail closed requiring additional actions to continue control rod insertion.
(COMPONENT MALFUNCTION after EOP)
With reactor power > 2%, terminate and prevent injection into the RPV by all systems except CRD and Boron injection systems IAW Support Procedure 17.
Insert Control Rods IAW Support Procedure 21.
NRC 3 Page 2 of 18
OC NRC Re-Take Exam 2008
~
~
~
Op-Test No.: 2008-1 Scenario No.:
NRC 3 Event No.: 1 Event
Description:
Withdraws control rods to raise reactor power IAW the ReMA Initiation: As directed by the SRO Cues: Withdrawn control rods show normal indications L
NRC 3 Position SRO BOP ATC Applicant's Actions or Behavior Conducts a pre-job reactivity maneuver brief Approves the ReMA Directs the ATC to withdraw control rods IAW the reactivity maneuver sheet e
Acts as the Reactivity Manager during the control rod manipulations Provides a peer-check for withdrawing control rods and initials on the reactivity maneuver sheet after each control rod is withdrawn.
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.
Verifies the pushbutton light is lit and no others are lit.
Places the ROD CONTROL switch to ROD OUT NOTCH position for approximately one second Verifies:
o Green INSERT light is illuminated o Green INSERT light remains illuminated approximately 1 second Immediately releases the switch allowing it to return to OFF by spring action Verifies:
o The red WITHDRAW light is illuminated approximately 2 seconds following switch movement and remains on for approximately 1.5 seconds Page 3 Of 18
OC NRC Re-Take Exam 2008
---i---
o The rod latches in the next even-numbered position before the e
Turns ROD POWER off when control rod withdrawals are complete 0
Signs the ReMA when control rod withdrawals are complete Reports all control rods withdrawn IAW the reactivity maneuver form SETTLE light is extinguished Terminus: I Control rod withdrawals have commenced.
Notes/Comments NRC 3 Page 4 of 18
OC NRC Re-Take Exam 2008 Op-Test No.: 2008-1 Scenario No.: NRC 3 Event No.: 2 Event
Description:
Responds to a broken CRD Pump A shaft [TRIGGER I]
Initiation: As directed by the Lead Examiner Cues: Control rod withdrawals are interrupted; CRD HYDRAULIC SYSTEM indicators indicate nl flow/pressure; Annunciator H7c, CHARG WTR PRESS LOW; H5c, CRD TEMP HI alarms Time Position ATC SRO Applicants Actions or Behavior Reports unable to withdraw control rods Responds to annunciators H5c, H7c Reports CRD HYDRAULIC SYSTEM indicators indicate no flowlpressure Dispatches NLO to investigate CRD Pump A [ROLE PLAY]
Starts CRD Pump B by placing CRD PUMP NCOIB switch to START and stops CRD Pump A by placing CRD PUMP NCOIA switch in STOP, OR:
Swaps to CRO Pump 6 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 Stops CRD Pump A by placing CRD PUMP NCOIA to STOP o Adjusts CRD FLOW CONTROLLER to attain required flows o Places CRD FLOW CONTROLLER in AUTO o Verifies normal indications Reports CRD Pump 6 is operating and CRD System indications are normal Directs EO to protect CRD Pump B 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 0
Declares CRD Pump A inoperable 0
Reviews Tech Spec 3.4.D.2 o If one CRD hydraulic pump becomes inoperable when the reactor water temperature is above 212OF, the reactor may remain in operation for a period not to exceed 7 days provided the second -
Page 5 of 18
OC NRC Re-Take Exam 2008 ROLE PLAY CRD hydraulic pump is operating and is checked at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. If this condition cannot be met, the reactor water temperature shall be reduced to less than 212OF.
0 Briefs the Crew Notifies Work Week manager (WMM) or Shift Manager about the inoperable CRD Pump A 0
When directed to investigate CRD Pump A, WAIT 2 minutes, then report that the 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 il is ready for start. If asked to report post-running checks, report running checks SAT.
I I
BOP I
0 Makes plant announcement prior to starting CRD Pump B
_ _ 1 Terminus: CRD Pump B has been started and the SRO has applied Tech Specs.
Notes/Comments
---I NRC 3 Page 6 of 18
OC NRC Re-Take Exam 2008 Op-Test No.: 2008-1 Scenario No.: NRC 3 Event
Description:
Responds to Stuck Control Rod 38-23 Event No.: 3 Initiation: During withdraw of the last control rod of the ReMA Cues: Control rod 38-23 shows abnormal indications when a withdraw signal is applied Position SRO BOP ATC
~ - -
Applicant's Actions or Behavior 0
Acts as the Reactivity Manager during control rod manipulations.
0 May refer to ABN-6, Control rod malfunctions due to stuck rod 0
Directs raising CRD drive pressure IAW 302.2 Provides a peer-check for withdrawing control rods and initials on the reactivity maneuver sheet after each control rod is withdrawn.
Withdraws control rods IAW the reactivity maneuver sheet and Procedure 302.2, Control Rod Drive Manual Control System. [PANEL 4F]
0 0
0 Recognizes & reports Control Rod 38-23 is stuck May refer to ABN-6 Control Rod Malfunctions Refers to 302.2, Control Rod Drive Manual Control System, Precautions and Limitations section o 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) o Restores drive pressure to normal 0
Turns ROD POWER off when control rod withdrawals are complete Signs the ReMA when control rod withdrawals are complete Reports all control rods withdrawn IAW the reactivity maneuver form Delete Stuck Rod malfunction after drive water pressure is increased the first time The stuck control rod has been moved and al control rods have been withdrawn for the power increase.
NRC 3 Page 7 of 18
OC NRC Re-Take Exam 2008 I Notes/Comments NRC 3 Page 8 of 18
OC NRC Re-Take Exam 2008 ROLE 1
PLAY 1
Op-Test No.: 2008-1 Scenario No.: NRC 3 Event No.: 4 Event
Description:
Condensate Pump upper bearing High Temp requires removal from service and power reduction [TRIGGER 21 As the EO, report TBCCW is lined up normally and oil levels are normal to Condensate Pump B. Also report that one of the bearing feels real hot.
As the EO, when directed to start the Feedwater Pump auxiliary oil pump, INSERT -
11 Initiation: As directed by Lead examiner 1 Cues: Annunciator J8f, COND/FD PMP BRG TEMP HI
_ _ _ _ _ ~
Applicants Actions or Behavior 0
Performs a rapid power reduction with recirculation flow by rotating the MASTER RECIRC SPEED CONTROLLER knob CCW to about 65% power, IAW 202.1 Requests Chemistry sample reactor coolant (due to power reduction) 0 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 Removes Feedwater Pump and Condensate Pump B from service o Places a Feedwater Pump controller in MAN o Reduces flow by rotating the control knob CCW o Directs EO to start the auxiliary oil pump [ROLE PLAY]
o Stops the Feedwaer Pump by placing its control switch in STOP o Stops Condensate Pump B by placing its control switch in STOP
[ B 0 OT HI 0
0 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 Notifies WWM/SM about Condensate Pump B.
NRC 3 Page 9 of 18
OC NRC Re-Take Exam 2008 LOA-CFW058 (FW Pump A) or LOA-CFW059 (6) or LOA-CFW060 (C). Report II when complete.
When Condensate Pump B is tripped, ramp the bearing temperature (ICH-CFW069A) down from its present temperature to 150 O F over a 5-minute ramp.
1 Reactor power has been lowered to the capacity of 2 feedwater pumps: 1 feedwater pump and Condensate Pump B have been tripped and RPV water level is stable.
N oteslComments :
-7 NRC 3 Page 10 of 18
OC NRC Re-Take Exam 2008 Op-Test No.: 2008-1 Event
Description:
Scenario No.: NRC 3 Event No.: 5 & 6
- 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, insert the steam leak. After several control rods have been manually inserted, insert the CRD FCV failure Cue: I.
Increasing DW pressure and temperature; Annunciators C3f DW PRESS HVLO, followed by Hld, H2d, DW PRESS HI-HI I & II; 2. Loss of ability to insert control rods: CRD FCV indicates closed Time NRC 3 Position ATC
~~ -
Applicants Actions or Behavior Reports Drywell pressure, temperature and leak rate rising As directed, manually scrams the reactor and carries out ABN-1, Reactor Scram (4F)
Presses MANUAL SCRAM BUS1 and BUS 2 pushbuttons Places REACTOR MODE SELECTOR switch in SHUTDOWN Reports control rods not fully inserted and reports reactor power Initiates Alternate Rod Insertion (ARI) by pressing ALT ROD I N J ECTl 0 N I N IT1 AT1 0 N push b u tto n (4F)
As directed, bypasses ROPS (Reactor Overfill Protection System) by placing ROPS switch in BYPASS (4F)
Runs recirculation flow to minimum by rotating the MASTER RECIRC SPEED CONTROLLER knob CCW Trips all recirculation pumps by placing all recirculation pump DRIVE MOTOR switches to STOP Insert control rods IAW Support Procedure 21 (per section 5.2 and/or 5.3) (Critical Task)
Section 5.2 Manual Control Rod Insertion (4F) 0 Verifies CRD Pump running 0 Directs NLO to close CRD Charging Water Valve V-15-52 0 Places REACTOR MODE SELECTOR Switch in REFUEL Places the ROD WORTH MINIMIZER keylock in BYPASS 11 BOOTH Closes CRD drive water pressure control valve by placing CRD DRIVE WATER PRESSURE CONTROL NC18 switch to CLOSE
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Page 11 of 18
OC NRC Re-Take Exam 2008 I
I 0 Selects and Inserts CRAM array control rods 0
Turns ROD POWER switch to ON 0
Selects the control rod 0
Places the ROD CONTROL switch to ROD IN Reports able to manually insert control rods [BOOTH 21 0 Recognizes failure of CRD Flow Control Valve after beginning to drive in control rods [BOOTH 31 0
Notifies SRO of the loss of ability to manually insert control rods 0
May swap CRD FCVs IAW procedure 302.1 0 Takes manual control of the in-service CRD FCV by placing CRD FLOW CONTROLLER in MAN 0 Directs the EO to open the inlet/outlet valves for CRD FCV NC30B [BOOTH]
0 Directs the EO to place the 4 Way Valve V-6-421 in the correct position to supply air to both controllers Places the CRD FLOW CONTROL VALVES switch to the VALVE NC30B position 0 Directs the EO to place the 4 Way Valve V-6-421 in the correct position to supply air to NC30B controller 0 Verifies CRD pressures/flow are normal Places CRD FLOW CONTROLLER in AUTO Directs the EO to close the inlet/outlet valves for CRD FCV NC30A 0 Continues inserting control rods Section 5.3 Scram Reset - Scram [BOOTH 41 0 Verifies CRD Pump running Places ARI NORMALIBYPASS switch in BYPASS Presses ALT ROD INJECTION RESET Pushbutton Obtains four (4) bypass plugs from the EOP toolbox Opens the EOP BYPASS PLUGS RPS 1 panel in the rear of Panel 6R Opens the EOP BYPASS PLUGS RPS 2 panel in the rear of Panel Inserts a bypass plug in BP5, RPS Scram Logic Inserts a bypass plug in BP6, RPS Scram Logic 7R 0
0 nserts a bypass plug in BP5, RPS Scram Logic nserts a bypass plug in BP6, RPS Scram Logic NRC 3 Page 12 of 18
OC NRC Re-Take Exam 2008 BOP SRO 0 Places SDV HI LVL BYPASS switch in BYPASS 0 Resets the scram by depressing the SCRAM SYSTEM RESET pushbutton Confirms SDV vents and drains open 0 When the SDV HI-HI alarms clear, manually scrams the reactor by pressing MANUAL SCRAM BUS1 and BUS 2 pushbuttons 0
Reports control rods inserting/inserted Vents the Primary Containment if directed IAW 312.1 1, Nitrogen System and Containment Atmosphere Control (Hardcard Attachment Vents the Drywell via the Torus by opening Torus vent valves on panel 1 IF:
Opens V-28-47 Opens V-28-18 312.11-10)
Confirms EOP automatic actions IAW Support Procedure 1 Prevents ADS by placing ADS TIMER switches in Bypass (1 F12F)
Bypass MSlV Low-Low water level isolation IAW Support Procedure 16 Terminate & prevents injection IAW Support Procedure 17 (Critical Task)
Maintains level band of -20 to +30 IAW Support Procedure 19 Maintains RPV water level restored 138 - 175 with Support Procedure 2 (Feedwater) and Support procedure 3 (CRD) when all control rods are inserted 0
May direct Primary Containment venting IAW 31 2.11, Nitrogen System and Containment Atmosphere Control (Hardcard Attachment Directs reactor scram and ABN-1, Reactor Scram, prior to drywell pressure scram setpoint Directs entry into RPV Control -With ATWS 0 Directs ARI initiation 0 Directs ROPS bypassed Directs confirmation of automatic actions IAW Support Procedure 1 0 Directs running Recirc Flow to Minimum 0 Directs tripping of Recirc Pumps 312.11-10) 0 NRC 3 Page 13 of 18
OC NRC Re-Take Exam 2008 I
I BOOTH L n a r i o Terminus:
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 (Critical Task)
Directs entry into RPV Control - No ATWS (following control rod insertions)
Directs RPV water level restored 138 - 175 with Support Procedure 2 (Feedwater) and Support procedure 3 (CRD) 0
- 1. To close CRD Charging water valve V-I 5-52 for Support Procedure 21 (TRIGGER 5: LOA-CRD024 to 0; Trigger 5).
- 2. When the ATC has begun control rod insertions and a few control rods have been inserted, fail CRD FCV NC30A closed (Trigger 4).
- 3. To place CRD FCV NC30B in service: open the CRD FCV inletloutlet valves by inserting LOA-CRDOI 1 and LOA-CRD012 to 1: Trigger 6 (opens V-15-18 and V-15-1 9). NO other Booth operations are required for swapping CRD FCVs (4-way valve, inletloutlet valves for CRD FCV NC30A). Report completed actions as appropriate.
RPV injection Terminated & Prevented, and Control rods are inserted. RPV Control -
N otes/Comments NRC 3 Page 14 of 18
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. Check APRM gains and adjust as necessary
- 5. Place a tag on the RWM Switch in BYPASS
- 6. Place TBCCW Pump 2 in PTL and hang tag
- 7. Have a prepared ReMA with the following 3 steps:
- a. Reduce power to 92% with recirculation flow (step 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 I
j EV:NT 1 TRE(3ER MALFUNCTION PMP-CRD002A o This breaks the shaft on CRD Pump NC08A MAL-C RD007-3823 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 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 O F o WHEN Condensate Pump B is manually tripped, ramp the current temperature down to 150 OF NRC 3 Page 15 of 18
OC NRC Re-Take Exam 2008 5
6 6
6 T3 --+
PRESETS -+
T4 -+
T5 ---f T6 --+
over 5 minutes MAL-NSSO17A to 0.1% over a 5 minute ramp o This causes a small steam leak in the Drywell MAL-CRD021A to 100°/~
MAL-CRD021 B to 90%
o This completely blocks 1 SDV (no rod motion in core quadrants) and allows partial control rod scram in the other 2 core quadrants o DELETE these malfunctions after the scram is reset MAL-CRD001A to 0 o This causes CRD FCV NC30A to fail closed LOA-CRD024 to 0 o This will close CRD charging valve V-15-52 LOA-CRDO11 to 1 0
LOA-CRD012 to 1 o This opens the inlet and outlet valves for CRD FCV NC30B NRC 3 Page 16 of 18
OC NRC Re-Take Exam 2008 Event 1 Event 2 Event 3 Event 4 Event 5 & 6 Procedures Used ReMA (This was handed out \\
the initial conditions)
ABN-6 RAP-H5c RAP-H7c 302.2 (control rod withdrawals and stuck rod)
RAP-J8f 202.1 (power reduction)
RAP-Hid, -H2d 312.1 1-10 Hardcard RAP-C3f ABN-1 302.1 (swapping CRD Pumps) 235 RPV Control - W/ATVVS EOP 5p-1 5p-21 5p-16 5p-17 5p-19 RPV Control - No ATWS 5p-2 5p-3 NRC 3 Page 17 of 18
OC NRC Re-Take Exam 2008 Shift Turnover Initial Conditions The plant is at 92% power The RWM is inoperable and bypassed TBCCW Pump 2 is tagged out of service for repair Shift Activities 0
Continue with the ReMA NRC 3 Page 18 of 18