ML081370451

Final - Section C Operating Exam (Folder 3),

ML081370451
Person / Time
Site:	FitzPatrick
Issue date:	03/25/2008
From:	Todd Fish Operations Branch I
To:	Peter Dietrich Entergy Nuclear Northeast
Hansell S
Shared Package
ML072850856	List: IR 05000333/2008301 ML072960631 ML080850880 ML081020600 ML081370203 ML081370232 ML081370261 ML081370267 ML081370299 ML081370315 ML081370319 ML081370387 ML081370417 ML081370442 ML081370451 ML081400330 ML081480142 ML081480167 ML082170282
References
LOI-08-01
Download: ML081370451 (46)

Text

i 3

JAMES A. FITZPATRICK NUCLEAR POWER PLANT 2008 NRC INITIAL LICENSE EXAMINATION SCENARIO 7 TITLE: LOl-08-0 7 NRC EXAMINATION SCENARIO 7, Swap CRD pumps, HPCI aux oil pump breaker failure, power reduction, RFP trip and failure to runback, Loss of all CRD pumps, ATWS, RCIC controller failure, Emergency Depressurization SCENARIO NUMBER: NEW PA TH: LO1 EXAM STANDALONE COMPUTER:

LO1 08-01 NRC LO1 Examination Scenario 1 page 1 of 14 i

I

PRIVATE }RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DA TE CHANGE CHANGE INITIA TOR RE VIEWED LO1 08-01 NRC LO1 Examination Scenario 1 Page 2 of 14

A. TITLE: LOI-08-01 NRC LO1 EXALIINATION SCENARIO 1, ATWYEmergency Depressurization

5. SCENARIO SETUP:

1. Initial Protected IC 227

2. Special Instructions:

a. Plant operating normally a t 8 7 % CTP

3. Preset Conditions:

4. Consumable Forms and Procedures:

LOL 08-01 NRC LO1 Examination Scenario 1 Page 3 of 14

C. SCENARIO

SUMMARY

Operating normally a t 87%, after assuming shift will continue to 65% in preparation for cleaning condenser water boxes; Perform a swap of CRD pumps to allow maintenance t o record vibration data on the 'B' CRD pump.

Critical TaskdStandards PRIVATE J Critical Task #I: Directs insertion of scram when All CRD is lost and HCU alarms are in Critical Task #2: EP-3 Insert control rods by alternate means. Diagnose that success path is to de-energize scram solenoids Critical Task #3: Emergency depressurize by opening 7 ADS valves LO1 08-01 NRC LO1 Examination Scenario 1 Page 4 of 14

1. Swap in service CRD pumps. (Normal evolution)

2. HPCI Aux Oil Pump breaker failure. (Component Failure)

3. 5% power reduction. (Reactivity Manipulation)

4. A RFP trip and failure of Recirc runback. (Component Failure)

5. I Loss of all CRD pumps (Technical Specification) I I 6. 1 ATWS due to RPS failure. (Major Transient)

I 7. I Main turbine trip, loss of Auxiliary busses (Component Failure)

I 8. I RCIC controller failure. (Component Failure)

9. Emergency Depressurization (Major Transient)

LO1 08-01 NRC LO1 Examination Scenario 1 Page 5 of 14

PRIVATE ]INSTRUCTOR POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ACTIVITY Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete

~~

Provide Turnover (Attach. Maintenance and performance monitoring is on station for

1) CRD pump vibration monitoring; need to swap CRD first thing.

~~ ~

After the shift turnover, All Walkdown the control panels and assume the watch. SAT / UNSAT / NA allow no more than five minutes for panel walkdown I 1 CRS Provide crew brief. SAT / UNSAT / NA

1. Swap in service CRD OP-25 G.10 Changing In-service CRD Pumps SAT / UNSAT / NA pumps. (Normal evolution)

[Cue CRS if needed]

• Start CRD pump (CRD PMP 03P-16A ). SAT / UNSAT / NA

.Stop other CRD pump (CRD PMP 03P-16B). SAT / UNSAT / NA

• Adjust CRD FLOW CNTRL 03FIC-301 to establish 59 to 61 SAT / UNSAT / NA gpm on 03FI-310 or 03FIC-301.

• Verify normal operating values on the following indicators at SAT / UNSAT / NA panel 09-5:

+ CHG WTR PRESS 03Pl-302: BETWEEN 1390 and 1580 psig, not to exceed 1670 psig LO1 08-01 NRC LO1 Examination Scenario 1 OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

+ DRV WTR DlFF PRESS 03DPI-303: 260 to 270 psid

+ CLG WTR DlFF PRESS 03DPI-304: approximately 10 to 26 psid

+ DRV WTR FLOW 03Fl-305: zero when no CRD is being driven

+ CLG WTR FLOW 03Fl-306: 59 to 61 gpm

2. Trip of HPCl Aux Oil Pump breaker.

(Component Failure)

[Cue booth]

ARP 9-3-3-38 SN0-2 Recognize/reportannunciator alarm for HPCl component SAT / UNSAT / NA LCO 3.5. I Condition C loss of power SN0-2 Recognize/report Loss of power indication for 23P-150 SAT / UNSAT / NA ATC/ Dispatches NPO to HPCl to investigate SAT / UNSAT / NA SNO-2 Locally:

Role play: Verify green light at pump control switch.

After several minutes, NPO Stop AUX OIL PMP 23P-150.

Reset the thermal overloads on t h e pump circuit reports no obvious problem breaker.

at 23P-150. Start AUX OIL PMP 23P-150.

IF motor trips again, Acrid odor at breaker THEN perform the following:

, determine ampere loading of motor LO1 08-01 NRC LO1 Examination Scenario 1 COMMENTS/EVALUATION observe pump f o r damage.

CRS Reviews Technical Specifications SAT / UNSAT / NA TS LCO 3.5.1, Condition C. 14 day action statement

3. Power reduction to 65% CRS Directs ATC to reduce reactor power using recirc. Do not go SAT / UNSAT / NA CTP for water box below 55% core flow.

cleaning.

(Reactivity Manipulation)

Guidance given in RAP 7.3.16 for adjusting reactor power, including maximum rate of power change.

-Maintain core flow LESS THAN OR EQUAL TO 77 Mlb/hr.

Control mismatch between recirculation loop jet pump flow as follows:

• Adjust speed in 1 to 3% increments.

ATC OP-27 Adjust RWR MG Set A/B speed to desired speed. SAT / UNSAT / NA Verify core flow and reactor power steady out following speed adjustment.

4. A RFP trip and failure of Recirc runback.

(Component Failure)

[Initiate from 83% CTP]

[Cue booth]

LO1 08-01 NRC LO1 Examination Scenario 1

POSl EV A 0 P-42 Feedwa ter A0P - F A utomatic Act ions malfunction Loss of one reactor feed pump Reactor feed pump trip annunciator alarms RWR pumps do not RPV water level lowers runback due to component If RPV water level lowers to 196.5 inches, both RWR failure MG sets run back to 44% speed Operating reactor feed pump should restore level ~ ~~

ATC .Reduce core flow to 55% OP-27 Attachment 4 SAT I UNSAT 1.NA

.Then reduce reactor power per RAP-7.3.16 by inserting CRAM groups

5. Loss of all CRD pumps (Technical Specification)

[Cue booth]

Insert triggers 5 and 6 AOP-69 IF charging water header pressure is not restored to GREATER THAN OR EQUAL TO 940 psis WITHIN 20 minutes of a second accumulator light, THEN insert a manual scram. ~ ~ ~

SN02 AOP-69: Monitor ACCUM alarm lights on full core display at SAT / UNSAT / NA panel 09-5, and execute ARP-09-5-1-43 as appropriate.

ARP 09-5-1-43 actions:

LO1 08-01 NRC LO1 Examination Scenario 1 OPERATOR ACTIONS/S.TANDARD

1. Initiate corrective action for HCU accumulator trouble per Section G of OP-25.

2. Monitor Full Core Display for additional HCU accumulator lights.

3. IF accumulator pressure is LESS THAN 940 psig or water can not be drained, then declare accumulator inoperable and refer to Technical Specifications SN02 AOP-69:*Ensure CRD FLOW CNTRL 03FIC-301 is in MAN. SAT / UNSAT / NA

=Rotatemanual control knob on CRD FLOW CNTRL 03FIC-301 fully counterclockwise.

• Verify in-service CRD flow control valve (03FCV-19A or 6) is closed.

Attempt to start A CRD pump (CRD PMP 03P-16A).

If the first pump fails to start, attempt to start the other.

Role play:

Report as NPO that CRD is not recoverable. Mechanical failure of CRD pump. Oil is all over the floor.

Insert manual scram when CRS Direct insertion of manual scram CRITICAL TASK evident CRD is not recoverable and SAT / UNSAT / NA accumulator alarms are in ATC Depress manual scram pushbuttons SAT / UNSAT / NA EvaluatorlBooth Operator Note: Spurious trip of 6 RFP should automatically occur when P/Bs are depressed.

Place reactor mode switch in shutdown Fully insert IRMs and SRMs SAT / UNSAT / NA Verify power decreasing APRM / IRM / SRM SAT / UNSAT / NA LO1 08-01 NRC LO1 Examination Scenario 1 IPRIVATE )INSTRUCTOR ACTIVITY OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION

6. ATWS due to RPS SN02 At 09-5 and 09-4, Recognize ATWS conditions, trend level SAT / UNSAT / NA failure. (Major Transient) performance and manipulate GEMAC Master/lndividual controllers, RFP discharge valves and RFP trip as necessary to control level.

ATC *Insert manual scram SAT / UNSAT / NA ATC *Mode switch to shutdown SAT / UNSAT / NA

• Identify failure to scram ATC *Initiate ARI SAT / UNSAT / NA CRS *Enter EOP-3 SNO *Reduce recirc flow to minimum SAT / UNSAT / NA SNO *Trip both recirc pumps SAT i UNSAT 1 NA SNO *Override ADS SAT / UNSAT / NA SNO *Inject with SLC SAT / UNSAT / NA ATC *EP-3 Insert control rods by alternate means SAT / UNSAT / NA

• Diagnose that success path is to de-energize scram solenoids.

CRITICAL TASK EvaluatorlBooth Operator: Pull fuses approx. 30 seconds after Crew requests it.

ALL *EP-5 Terminate and Prevent Injection SAT / UNSAT / NA High pressure injection systems first

• Trip HPCl by depressing trip push buttons

• Manual control of FW CRS Enter EOP-2 LO1 08-01 NRC LO1 Examination Scenario 1 - 1 1-

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ALL 1 *Lower level maintain level 80 - 100 I SAT / UNSAT / NA

7. Main turbine trip, loss Evaluator/Booth Operator: When scram fuses are pulled of Auxiliary busses (see above), power will rapidly drop as rods insert, and the (Component Failure) MT will either auto trip on reverse power or due to ATC action. Aux busses will fail to auto transfer, leading to loss of condensate, and forcing level control over to RCIC.

Loss of Condensate and condensate booster pumps I MSVsshut

8. RClC controller failure. SN02 Inject with RCIC maintain level 80 - 100 SAT / UNSAT / NA (Component Failure) EvaluatorlBooth Operator: RCIC will trip 3 minutes after applicant shifts controller to Manual.

[After manual control is established, RClC will auto trip]

RClC starts, runs to low speed stop SN02 1 Take manual control of RClC 1 SAT / UNSAT / NA

9. Emergency ALL All rods in (after RPS fuses are pulled in EP-3) SAT / UNSAT / NA Depressurization (Major Exit EOP-3, enter EOP-2 Transient)

CRS 1 Directs SNO to open 7 ADS valves CRITICAL STEP SAT / UNSAT / NA SNO Opens seven, ,A nC \ml\rnc vaiv=a 1 CRITICAL STEP SAT / UNSAT / NA CRS Directs the SNO to maintain level 0 to 222.5 with LPCl SAT / UNSAT / NA LO1 08-01 NRC LO1 Examination Scenario 1 -1 2-

.I-TERMINATE THE SCENARIO LO1 08-01 NRC LO1 Examination Scenario 1 -1 3-

ATTACHMENT 1 Operating normally at about 87%. After assuming shift, perform a swap of CRD pumps to allow maintenance to record vibration data on the B CRD pump. Reduce reactor power to 65% in preparation for cleaning condenser water boxes.;

LO1 08-01 NRC LO1 Examination Scenario 1 -1 4-

JAMES A. FITZPATRICK NUCLEAR POWER PLANT 2008 NRC INITIAL LICENSE EXAMINA TION SCENARIO 3 TITLE: LO/-08-01 NRC EXAMINA TION SCENARIO 3. APRM instrument failure. Restoration of busses 10200 and 10400 to T4, Failure of LPCI inverter, Inadvertent HPCI initiation, Loss of Instrument Air, SBLOCA, Both loop of RHR Containment spray fail, Spray Torus/Drywell with RHR S W SCENARIO NUMBER: NEW PATH: LO1 EXAM STANDALONE COMPUTER:

LO1 08-01 NRC LO1 Examination Scenario 3 Page 1 of 13

P R I V A T E }RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DA TE CHANGE CHANGE INITIA TOR RE VIEWED LO1 08-01 NRC LO1 Examination Scenario 3 Page 2 of 13

TITLE: LO/-08-01 NRC EXAMINA TION SCENARIO 3. APRM instrument failure. Restoration of busses 10200 and 10400 to T4, Failure of LPCI inverter, Inadvertent HPCI initiation, Loss of Instrument Air, SBLOCA, Both loop of RHR Containment spray fail, Spray Torus/Drywell with RHR SW A.

B. SCENARIO SETUP:

1. Initial Protected IC 228

2. Special Instructions:

a. Plant operating normally a t 50%) CTP

3. Preset Conditions:

Trigger I N M I 5:B A P R M Channel B inoperative - True Trigger 4 ED04:B Inverter 7 1 -1NV-3B Failure - True Trigger 5 HP05 HPCI Inadvertent initiation - True Trigger 6 I A 0 2 Loss of Instrument Air - 1 0 0 % Ramp 7:OO minutes Trigger 7 - /*scram push b u t t o n * / ( z d 5 a s 3 a = 1 ) II (zd5as3b= 1) II manual scram Trigger 8 - */zlol O a s l 3 a ( 2 ) = 1 II 1Omov38a Trigger ) 1 II 1 0 m o v 3 8 b red light is o n 9 - * / ~ 1 0 1 0 a s I 3 b ( 2=

4. Consumable Forms and Procedures:

LO1 08-01 NRC LO1 Examination Scenario 3 Page 3 of 13

C. SCENARIO

SUMMARY

The plant at 50% power. Power ascension was suspended to allow Electrical Maintenanceto perform an inspection of T4 following a report of a cooling fan problem. Busses 10200 and 10400 are currently fed from Reserve. Electrical Maintenance has successfully completed the inspection of T4. The shift will restore the electric plant lineup to normal by transferring busses 10200 and 10400 from Reserve to Normal.

Raise reactor power with control rods. Start at Step 46 with rod 30-19. Pull from notch 12 to 24.

Continue power ascension per OP-65.

Critical Task #1: Manual scram on loss of instrument air Critical Task #2: Sprays containment Critical Task #3:

Critical Task #4:

LO1 08-01 NRC LO1 Examination Scenario 3 Page 4 of 13

1. APRM instrument failure. (Instrument failure) RO

2. Restoration of busses 10200 and 10400 to T4. (Normal Evolution) All

3. Raises power with control rods (Reactivity manipulation) RO

4. Failure of LPCI inverter (Component failure) BOP

5. Inadvertent HPCI initiation (Component failure) BOP/SRO

6. I Unisolable leak on Instrument Air header (Component failure) All

7. I SBLOCA on recirc line, containment spray required (Major transient) All

8. I Spray torus, both loop of RHR fail (Component failure) All

9. Spray Torus/Drywell with RHR S W (Major transient) AI1 D. TERMINA TION CUES:

LO1 08-01 NRC LO1 Examination Scenario 3 Page 5 of 13

(PRIVATE ]INSTRUCTOR POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ACTIVITY Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, All 1 Walkdown the control panels and assume the watch. I SAT / UNSAT / NA allow no more than five minutes for panel walkdown

~

CRS Provide crew brief. SAT / UNSAT / NA

1. APRM instrument failure. ALL *Identify '/2 scram SAT / UNSAT / NA (Instrument failure) *Identifies 'B' APRM inop ATC 1 *Bypass 'B' APRM

[Cue Booth1 *Reset % Scram (note: procedure use is not required for bypassing APRM and resetting '/2 scram)

LO1 08-01 NRC LO1 Examination Scenario 3 OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION One to adjust bus voltage at LTC CONTROL One to operate breaker control switches

.Place BUS 10400 FDR SYNCH SW switch in NORM.

.Match voltages on NON-EMERG BKRS INCOMING and RUNNING volt meters using LTC CONTROL switch.

• WHEN incoming and running voltages are matched, AND synchroscope is a t approximately 1 2 o'clock, perform the following bus transfer using the same hand, without unnecessary delay, t o perform each breaker operation:

C l o s e NSS TO BUS 10400 BKR 10402.

.Open RSS TO BUS 10400 BKR 10412.

.Place BUS 10400 FDR SYNCH SW switch in OFF and remove handle.

.Verify all white lights for RPS A and RPS B power source selectors are on a t panel 09-1 6.

Possible EPIC alarm on low volts, volts are in acceptable range

[546 - 6 151 no action required until after bus shift comptete

3. Raises power with ATC Step 4 6 of pull sheet, Rod 30- 9 from notch 1 2 t o 24 control rods (Reactivity Rod 22- 9 from notch 12 to 2 4 manipulationl

[Cue CRSI

4. Failure of LPCI inverter ALL 09-8-5-11 LPCI MOV I P S B 7 1 I N V - 3 B MINOR ALARM TROUBLE LO1 08-01 NRC LO1 Examination Scenario 3 P COMMENTS /EV ALU AT10 N (Component failure) 09-8-5:6,7,9, IO,1 1 (Various power supply trouble alarms)

[Cue Booth]

NPO reports: LPCl inverter SN02 + Transfer LPCl MOV bus to alternate feed by ARP input breaker is tripped on i. Investigate cause of alarm.

MCC-162 IF cause of alarm is not readily apparent, THEN place LPCI MOV Bus B on alternate feed as follows:

CRS a. Verify L-16 is energized at panel 0 9 - 8 .

b. Place LPCI MOV B PWR SUPP switch in ALT PULL TO Lock at panel 09-8.

c. WHEN the cause of the alarm is known and corrected, LPCI MOV Bus B may be restored to normal per Section G of OP-43C.

Refer to Technical Specifications.

+ Transfer t o alt power causes annunciators 09-8-5-5, 6 &9 Result is 'B' LPCl is inoperable but available TS 3.8.4 Condition 'D' and LCO 3.5.1 Condition 'A' (7day)

5. inadvertent HPCl initiation SAT I UNSAT / NA (Component failure)

[Cue Boothl I HPCI initiates All Recognizes/report HPCl is starting SAT / UNSAT / NA CRS Directs crew t o verify the validity of the HPCl auto start using SAT / UNSAT / NA multiple indications Acting as an NPO report: SNO Observer indications for Drywell pressure and reactor level, SAT / UNSAT / NA 23 AK-3 relay has evidence determines HPCl start is not valid of charring but there is no fire in the Relay Room.

CRS Directs SNO/NCO to triphecure HPCl SAT / UNSAT / NA LO1 08-01 NRC LO1 Examination Scenario 3 c PRIVATE )INSTRUCTOR ACT1V ITY I---

If HPCI injects SNO CRS CRS OPERATOR ACTIONS/STANDARD Secure the HPCl turbine Enters AOP-32, Unexplained /Unanticipated Reactivity Addition (if HPCI injected and power changes)

TS 3.5.1 D and C, 14 day LCO, verify RClC operable

~

COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA 7 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to restore HPCl or LPCl SN02 SBGT started on HPCl start, secure SBGT or lineup flow path by opening suction valve

6. Unisolable leak on ALL Air compressors start, air pressure trends down Instrument Air Header AOP-12

[Cue Booth to start while HPCI recovery is in progress)

CRS Directs manual scram Role play: ATC 9-6-2-39 SERV AIR HDR ISOL VLV CLOSED (95 psig) SAT / UNSAT / NA As NPO report massive air 9-6-2-3 1 SERV AIR HDR PRESS LO (95 psi@

leak on common discharge 9-7-3-43 SPE Vac Lo piping of air compressors.

Leak is not isolable EOP-5 entry on RB pressure CRITICAL TASK upon rod INSERT Manual Scram drift alarm or recognize not recoverable AOP-12 LO1 08-01 NRC LO1 Examination Scenario 3 - 1 0-

OPERATOR ACTIONWSTANDARD Depending on the severity of the CRS OUTBD MSlVs will eventually shut on loss of air loss of air or the source of the problem, the following could occur:

EOP-2 on low RPV level after scram Control rods drift inward.

Level control 177-222.5 inches Air operated valves fail as-is or in fail safe position.

Directs 1OOF/hr cooldown Valves drift from expected position due to vibration or system pressure.

Outboard MSIVs drift closed (accumulators could delay closure for up to 30 minutes).

01-107AOV-100 (off gas disch to stack) fails open.

7. SBLOCA on recirc line, CRS AOP-39 containment spray required Drywell pressure increasing (Major transient)

EOP-2 and EOP-4 on High DW pressure All EDGs start

[Auto initiation upon insertion of scram] Prevent injection from LPCl and CS (EP-5)

8. Spray Torus failure CRS Directs initiation of Torus Sprays when torus pressure is SAT I UNSAT I NA greater than 2.7 psi.

Directs S N O to place loop of RHR in torus spray.

[Auto initiation]

SN02 Places loop of RHR in torus spray I SAT / UNSAT / NA Use other loop of RHR for SN02 Pumps tripped when starting torus spray SAT I UNSAT / NA success Shift to other RHR loop, both RHR pumps trip LO1 08-01 NRC LO1 Examination Scenario 3 -1 1-

PRIVATE )INSTRUCTOR POSIT10N OPERATOR ACTIONWSTANDARD COMMENTS/EVALUATION .

ACTIVITY I I ALL I Crew uses RHR Service Water for torus and/or drywell spray I SAT / UNSAT / NA I per EP-14 (5.1 'A' loop or 5.2 'B' loop)

CRITICAL TASK I 9. Spray Torus/Drywell I SN02 I Maintain RPV pressure with SRVs after MSlVs shut I SAT / UNSAT / NA I I 1 SN02 1 Spray D W when pressure reaches 15 psig. 1 SAT / UNSAT / NA I TERMlNATE THE SCENARIO LO1 08-01 NRC LO1 Examination Scenario 3 - 1 2-

m JAMES A. FITZPATRICK NUCLEAR POWER PLANT 2008 NRC INITIAL LICENSE EXAMINA TION SCENARIO 4 TITLE: LOI-08-07 NRC EXAMINATION SCENARIO 4, Trip of Service water pump/ Stuck control rod/ Swap TBCLC pumps / Loss of FW heater level control / Feed pump trip, loss of condensate pumps, / RCIC pump tri@/ HPCI fail to auto start/ RWR loop break inside drywell

/ Containment sprays required SCENARIO NUMBER: NEW PA TH: LO1 EXAM STANDALONE COMPUTER:

LO1 08-01 NRC LO1 Examination Scenario 4 Page 1 of 10

PRIVATE }RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DA TE CHANGE CHANGE INITIA TOR REVIE WED L

LO1 08-01 NRC LO1 Examination Scenario 4 Page 2 of 10

TITLE: LOl-08-0 1 NRC LO1 EXAMINATION SCENARIO 4, Trip of Service water pump/ Stuck control rod/ Swap TBCLC pumps / Loss of FW heater level control / Feed pump trip, loss of condensate pumps, / RCIC pump trip / HPCI fail to auto start/ RWR loop break inside drywell

/ Containment sprays required B. SCENARIO SETUP:

1. Initial Protected IC 229

2. Special Instructions:

a. Plant operating normally a t 9 2 % CTP

3. Preset Conditions:

Event 7 /

• s c r a m push buttons*/(zd5aas3a = 1 ) II (zd5as3b = 1) II m a n scram Event 10 /

• 3 8 A o p e n * / z l o l O a s l 3 a ( 2 ) = 1 Event 1 1 /

• 3 8 B o p e n * / z l o l O a s l 3 b ( 2 ) = 1

4. Consumable Forms and Procedures.

C. SCENARIO

SUMMARY

PRIVATE 1 92% CTP, pulling rods to 103% rod line and 96% CTP, then hold for one hour prior to proceeding to 100% CTP using recirc flow.

Rod pull sheet step 65. Next rod will be rod 18-15. rod pull from 12 - 16 Crew will swap TBCLC pumps in preparation for maintenance.

Critical Task #1: Insert Reactor Scram on trip of both feed pumps Critical Task #2: Spray torus/drywell on high pressure LO1 08-01 NRC LO1 Examination Scenario 4 Page 3 of 10

I '

1. Trip of 'B' Service Water pump. Manual start of 'A

• S W pump. (Component Failure)

2. Raise power by withdrawing control rods (Reactivity manipulation)

3. Stuck control rod (Component Failure)(Tech Spec)

I 4. 1 Swap TBCLC pumps. (Normal evolution)

I 5. 1 Loss of level control 6A FW heater. (Component failure)

I 6. I Both Feed pumps trip. (Component Failure)

I 7. 1 Condensate pumps trip. (Component Failure) starts then trips after two minutes.

HPCI fail to auto start. (Component Failure)

I 9. Recirc loop break in drywell. Containment sprays required. (Major transient)

D. TERMINA TION CUES:

1 . All Rods in.

2. DW sprays in service LO1 08-01 NRC LO1 Examination Scenario 4 Page 4 of 10

POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach.

P 111 After the shift turnover, All Walkdown the control panels and assume the watch. SAT / UNSAT / NA allow no more than five minutes for anel walkdown CRS Provide crew brief. I SAT / UNSAT I NA

1. Trip of B Service Water pump.

Manual start of A SW pump.

(Component Failure) 88,

[Cue booth]

InsertTri e r l ALL SN02 I ARP 9-6-2-13 SERV WTR PMP 4 6 P - I B OVERLOAD OR T R I P ARP 9-6-2-34 Service wafer header pressure low Operator starts standby pump.

I I SAT / UNSAT / NA I 1 Reports failure of standby pump to start automatically.

LO1 08-01 NRC LO1 Examination Scenario 4 PRIVATE )INSTRUCTOR OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ACTIVITY At this power level, the CRS Acknowledges reports from SN02 crew recognizes that two S W pumps are required and the SN02 must SN02 Places B SWP in PTL manually start the A S W pump. A circuit failure will prevent the auto start, so if the crew waits, a low pressure condition will result

2. Raise power by OP-25 withdrawing control rods (Reactivity manipuIation)

The crew will raise power by withdrawing control rods Step 65 Rod 18-15 Rod 18-39 Rod 34-39 Rod 34-15

3. Stuck control rod Pull Sheet Step 65 from 12 to 16 (Component Failure)(Tech 0P-25 Spec) OP-26 The A TC will recognize a n d Reports rod 18-39 will not withdraw with normal drive report control rod 18-39 ATC pressure fails to move CRS Acknowledge and concur with raising drive pressure After first increase in drive ATC IAW OP-25 E. Incrementally raises drive water pressure to LO1 08-01 NRC LO1 Examination Scenario 4 POSITION OPERATOR ACTIONS/STANDARD COMMENTSlEVALUATlON attempt rod withdrawal When drive dP raised Is time delete RDIO stuck rod Rod may double notch at raised drive pressure Recognizes and reports rod is withdrawing, restores CRD ATC parameters to normal range

4. Swap TBCLC pumps. CRS Directs TBCLC pump swap (Normal evolution)

In support of maintenance, SN02 OP-41 G . l Steps 1 - 5 the crew swaps TBCLC starts the C pump, secures the Bpump.

[Cue CRS]

5. Loss of level control 6A AOP-32, Unexplained power change (if crew does not FW heater string. recognize level control failure but notes a rise in CTP)

(Component faiIure) AOP-62, Loss of Feedwater Heating

[Cue Booth]

Insert Trigger 5: ALL 09-6-3-36 HI FDWTR HTR 6 A LVL HI 09-6-3-26 Hi-HI FDWTR HTR 6 A LVL HI-HI 09-7-3-11, I 2 IST STAGE RHTR DRN TK 3 A LvL HI 2ND STAGE RHTR DRN TK 4A LVL HI NPO reports both valves All Normal and dump valve are not responding are closed. No response when operated locally All AOP-62 Loss of Feedwater Heating ATC Monitor for thermal hydraulic instability CRS Upon a noted rise in thermal power, Directs to rapidly lower recirc flow until power < 72%, do not go -65% core flow ATC Lowers reactor power with recirc LO1 08-01 NRC LO1 Examination Scenario 4 PRIVATE )INSTRUCTOR POS IT10N OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ACTIVITY

6. Both Feed pumps trip.

{Cornponent FaiI ure)

Insert Trigger 6: when recirc ALL Recognize/report trip of both Feed Pumps SAT / UNSAT / NA is beina lowered in Event 5 1 SAT / UNSAT / NA I

CRS Directs insertion of manual scram.

Critical Task SN02 Inserts manual scram. SAT / UNSAT / NA Takes mode switch to SHUTDOWN Makes post scram reports Critical Task

7. Condensate pumps trip CRS EOP-2 on low RPV level SAT / UNSAT / NA on reactor scram AOP-1 for reactor scram (Component failure)

I SAT / m S A T I NA

~~

Loss of all feed SN02 Maintain level 177 - 222.5 inches

8. RClC starts and trips SN02 Operator identifies RClC trip SAT / UNSAT / NA after two minutes, 10 Operator identifies HPCl failure to auto start, manually aligns seconds and injects with HPCl (opens 23 MOV-14)

HPCl fails to AUTO start, HPCl in pressure control mode but is available to start manually. (Component CRS TS entries on HPCl and RClC fai Iure)

9. RWR loop break in EOP-2 SAT / UNSAT / NA drywell. Containment EOP-4 High DW pressure, High Torus level sprays required. (Major 9-5-1 -34 High Drywell pressure transient)

JCue Booth]

I SAT / UNSAT / NA I

Terminate and prevent Core Spray and RHR per EP-5 LO1 08-01 NRC LO1 Examination Scenario 4 TERMINATE THE SCENARIO EALs Unusual Event 2.1.1 Unidentified DW leakage > 10 gpm Alert 3.1.1 Primary Containment pressure > 2.7 LO! 08-01 NRC LO1 Examination Scenario 4 7

I-Z w

t I

0 7

u l I-I-

C 9

co 0

JAMES A. FITZPATRICK NUCLEAR POWER PLANT 2008 NRC INITIAL LICENSE EXAMINA TION SCENARIO 5 TITLE: LOI-08-01 NRC EXAMINATION SCENARIO 5, SBGT trip / Shutdown condensate pump /

Failure of NR level control / Fuel clad failure/ A TWS / R WCU failure to isolate / Steam leak in Reactor Building / Emergency Depressurization SCENARIO NUMBER: NEW PATH: LO1 EXAM STANDALONE COMPUTER:

LO1 08-01 NRC LO1 Examination Scenario 5 Page 1 of 12

PRIVATE }RECORD OF CHANGES SOURCE OF BRIEF DESCRIPTION OF DA TE CHANGE CHANGE INITIA TOR REVIE WED LO1 08-01 NRC LO1 Examination Scenario 5 Page 2 of 12

TITLE: LO/-08-01 NRC LO1 EXAMINATION SCENARIO 5, SBGT trip / Shutdown condensate pump /

Failure of NR level control / Fuel clad failure/ A TWS / R WCU failure to isolate / Steam leak in Reactor Building / Emergency Depressurization B. SCENARIO SETUP:

1. Initial Protected IC 230

2. Special Instructions:

a. Plant operating normally at 50% CTP

3. Preset Conditions:

4. Consumable Forms and Procedures:

LO1 08-01 NRC LO1 Examination Scenario 5 Page 3 of 1 2

C. SCENARIO

SUMMARY

Drywell is being purged IAW OP-37 D.6.11. SBGT'A' is running to vent torus

'C'Condensate pump is running in preparation for securing 'B' condensate pump for maintenance Control rods are a t Step 47 Critical Task #2: Directs declaration of SAE due t o failure of RWCU t o isolate Critical Task #3: Open 7 ADS valves LO1 08-01 NRC LO1 Examination Scenario 5 Page 4 of 12

I I. 1 #A Standby Gas Treatment fan trip. (Coniponent Failure) (Technical Specification)

I 2. I Normal shutdown of 'B' condensate pump. (Normal evolution)

I 3. 1 Failure of 'B' NR level instrument upscale,.level transient. (Instrument failure)

4. Fuel clad failure (Component Failure) (Technical Specification)

5. ATWS due to RPS 'A' failure. Startup level control valve fail closed (Instrument failure)

(component failure)

6. F W startup level control valve failure (Component Failure)

7. R WCU failure to isolate (Component Failure)

I 8. I Steam leak in Reactor Building resulting in rad release. (Major Transient)

I 9. I Reactor depressurization. (Major Transient)

D. TERMINATlON CUES:

1. All rods in.

2. 7 ADS valves open.

LO1 08-01 NRC LO1 Examination Scenario 5 Page 5 of 12

IPRIVATE )INSTRUCTOR ACTIVITY Note: possible R WR runback POSITION SNO OPERATOR ACTIONS/STANDARD Shift level column to A, per OP-2A G.30 COMMENTS/EVALUATION if level column is shifted Place Rx WTR LVL COLUMN SEL 06-SI switch in A-LEVEL.

with level too low.

Ensure RPV water level stabilizes.

IF reactor water level control was placed in manual control, THEN restore reactor water level control to automatic when directed by the Shift Manager.

Restore RFP control to Auto per OP-2A G.41 Balance RX WTR LVL CNTRL 06LC-83 controller by adjusting SP ADJUST knob.

Place RX WTR LVL CNTRL 06LC-83 controller in BAL.

CRS Refer to Tech Specs, table 3.3.2.2 A, 7 day AOT I SAT / UNSAT / NA Cue Event 4 when RFP control is returned to AUTO

4. Turbine Building Radiation Alarms indicate fuel clad failure (Component failure)

SJAE Rad Off-gas HI AOP-3, High Activity in Reactor Coolant or Off-gas I ARP 09-3-2-27 Directs entry into AOP-3. SAT / UNSAT / NA CRS Directs local evacuations of areas with ARMS in alarm.

Directs reduction in power to reduce rad levels 09-3-2-10 Off-Gas timer initiates SAT / UNSAT / NA All Announce evacuate TB Crew performs a controlled Inserts control rods t o get below 70% rod line per RAP-power reduction to stabilize 7.3.1 6.

SNO rad levels Reduce power to < 40% CTP LO1 08-01 NRC LO1 Examination Scenario 5 OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Identifies EOP-5 entry on high rad level approaching max safe. SAT / UNSAT / NA I All Identifies 15 min timer timed out.

1 CRS Directs UE notification and applicable announcements [should activate TSC and OSCI.

SAT / UNSAT / NA 1 CRS Directs a manual scram prior to reaching a max safe and execution of AOP-I .

SAT / UNSAT / NA SNO Announces and inserts a manual scram. SAT / UNSAT / NA

5. A TWS due to RPS 'A ATC Recognizes and announces failure of manual scram. SAT / UNSAT / NA failure. (Instrument failure)

SNO-2 Places Mode Switch t o Shutdown Recognizes and announces failure of mode switch t o scram the reactor CRS Enters EOP-3 EAL Alert for failure to scram Rods fail to insert, ARI is ATC Announce ATWS and depress ARI pushbutton CRITICAL STEP successful Announces success of ARI and carries out AOP-1. SAT / UNSAT / NA CRS Exits EOP-3 Directs entry into EOP-2 SAT / UNSAT / NA CRS 0 Directs level band of 177" t o 222.5" 0 Directs pressure stabilized 900 t o 1000# with BPVs HPCl / RClC starts HPCI may be tripped by operator if flow is not needed

6. Startup level control valve fail closed (component failure)

LO1 08-01 NRC LO1 Examination Scenario 5 POSIT10N OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ACTIVITY RPV level control will be SN02 Control RPV level using HPCI/RCIC/ feed via 34 MOV 100A or SAT / UNSAT 1 NA coarse with only discharge 1 OOB valves for control.

7. R WCU fails to isolate (after scram RPV level shrink) (Component Failure)

SNO Identifies failure of the RWCU 12MOV-15 t o isolate.

Identify entry conditions for AOP-39 (Loss of Coolant)

Directs entry into AOP-39.

II SAT I UNSAT I NA SAT I UNSAT / NA CRS Directs declaration of SAE due t o failure of RWCU t o isolate. CRITICAL STEP CRS EAL 3.4.1 SAT I UNSAT I NA

8. Steam leak in Reactor Building resulting in rad release. (Major Transient)

I Steam leak in RWCU area CRS May preemptively depressurize via the main condenser Determines temperatures are approaching SAE level. SAT I UNSAT I NA CRS EAL 4.1 .l CRS Executes Emergency depressurization leg of EOP-2 due t o SAT I UNSAT / NA reaching 2 MAX SAFES LO1 08-01 NRC LO1 Examination Scenario 5 -1 0-

PRIVATE )INSTRUCTOR ACTIVITY

9. Emergency Depressurization (Major Transient)

CRS Directs 7 ADS valves opened. CRITICAL STEP Directs level control maintained with feed and condensate a t 177" t o 222.5". SAT / UNSAT / NA SNO As directed opens and verifies open 7 ADS valves CRITICAL STEP I SAT / UNSAT / NA TERMINATE THE SCENARIO LO1 08-01 NRC LO1 Examination Scenario 5 -1 1-

c m

t u

a,

.-c E

v-6 v) 2 Q e

3 0 ua, u

u m c v) a, c

> U a, I hl u

0 c F 0, 8 I

.-I= m c

c cn 2 .-c

.-v)

L 3

u a  %

I-6 vl u-c

.-0 u

l-l 4 e m

F Q a E!

Q I\

3 .-c a cn 0 .-I=

c c s3 c .-0

.w 2 m c

.-v)

E" 3

Q U

0 m

v)

(z a,

U c

uo ai 0

Q