ML081370299

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Draft - Section C Operating Exam (Folder 2),
ML081370299
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 02/28/2008
From: Todd Fish
Operations Branch I
To: Peter Dietrich
Entergy Nuclear Northeast
Hansell S
Shared Package
ML072850856 List:
References
LOI-08-01
Download: ML081370299 (49)
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I TITLE: LOl-08-01 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 PATH: LO1 EXAM STANDALONE COMPUTER:

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

PRIVATE }RECORD OF CHANGES

-"CHANGE .

LO1 08-01 NRC LO1 Examination Scenario 1 Page 2 of 14

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

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

C. SCENARIO

SUMMARY

PRIVATE ]

Shift Turnover PRIVATE ]

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 t o allow maintenance to record vibration data on the 'B' CRD pump.

Critical Jasks/Standards PRIVATE 1 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

PRIV EVENT SEQUENCE ATE

)EVEN T NO.

1. Swap in service CRD pumps. (Normal evolution)
2. HPCI Aux Oil Pump breaker failure. (Component Failure)
3. 1 5% power reduction. (Reactivity Manipulation)
4. 1 *A' RFP trip and failure of Recirc runback. (Component Failure)
5. 1 Loss o f all CRD pumps (Technical Specification)
6. ATWS due to RPS failure. (Major Transient)
7. Main turbine trip, loss of Auxiliary busses (Component Failure)
8. RCIC controller failure. (Component Failure)
9. Emergency Depressurization (Major Transient)

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

POSITION OPERATOR ACTIONWTANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete I Provide Turnover (Attach. Maintenance and performance monitoring is on station for I I)

After the shift turnover, All CRD pump vibration monitoring; need to swap CRD first thing.

Walkdown the control panels and assume the watch. SAT / UNSAT / NA allow no more than five minutes for panel walkdown 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]

=StartCRD pump (CRD PMP 03P-16A ). SAT / UNSAT / NA

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

=Verifynormal operating values on the following indicators at SAT / UNSAT / NA panel 09-5:

+ CHG WTR PRESS 03Pl-302: BETWEEN 1390 and J to exceed 1670 psig 1580 psig, y LO1 08-01 NRC LO1 Examination Scenario 1 OPERATOR ACTIONS/STANDARD

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

+ CLG WTR DIFF 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 S N0-2 Recognize/report annunciator alarm for HPCl component SAT / UNSAT 1NA loss of power LCO 3.5. I Condition C SNO-2 ?ecognize/report Loss of power indication for 23P-150 SAT / UNSAT / NA ATCI %patches NPO to HPCI to investigate SAT / UNSAT / NA SNO-2

,ocally:

Role play: Ierify green light at pump control switch.

top AUX OIL PMP 23P-150.

After several minutes, NPO teset the thermal overloads on the pump circuit reports no obvious problem ireaker .

at 23P-150. ;tart 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 OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION observe pump for damaqe.

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 7.3.16for 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 9s follows:

.Adjust speed in I to 3% increments.

ATC 3P-27 Adjust RWR MG Set A/B speed to desired speed. SAT / UNSAT / NA derify core flow and reactor power steady out following speed adjustment.

of Recirc runback.

(Cornponent Failure)

[Initiate from 83% CTP]

LO1 08-01 NRC LO1 Examination Scenario 1 IPRIVATE )INSTRUCTOR ACTIVITY AOP-42 Feedwater OPERATOR ACTIONWSTANDARD AOP-42 Automatic Actions CO MMENTS/EVALU AT10 N 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 /. 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 N R C LO1 Examination Scenario 1 PRIVATE )INSTRUCTOR OPERATOR ACTIONS/STANDARD ACTIVITY

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
  • Rotate manual control knob on CRD FLOW CNTRL 03FIC-301 fully counterclockwise.

-Verify in-service CRD flow control valve (03FCV-19A or B) 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 0 Depress manual scram pushbuttons SAT / UNSAT / NA Evaluator/Booth Operator Note: Spurious trip of B RFP should automatically occur when P/Bs are depressed.

Place reactor mode switch in shutdown 1 SAT / UNSAT / NA

~

Fully insert IRMs and SRMs Verify power decreasing APRM / IRM / SRM 1 SAT / UNSAT / NA LO1 08-01 NRC LO1 Examination Scenario 1 POSIT1ON 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.

[AUTO]

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

=Diagnosethat 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

=Manualcontrol of FW CRS Enter EOP-2 LO1 08-01 NRC LO1 Examination Scenario 1 -1 1-

PRIVATE ]INSTRUCTOR POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ACTIVITY

.Lower level maintain level 80 - 100 SAT / UNSAT / NA

7. Main turbine trip, loss EvaluatorlBooth 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 MSlVs shut condensate booster pumps

8. RClC controller failure. SN02 Inject with RClC 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, RCIC will auto trip]

RCIC starts, runs to low speed stop I SN02 Take manual control of RClC SAT I 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)

I I CRS Directs SNO to open 7 ADS valves CRITICAL STEP SAT / UNSAT / NA I I SNO Opens seven ADS valves CRITICAL STEP SAT / UNSAT / NA 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-

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ATTACHMENT 1 Shift Turnover PRIVATE 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-

-*Ml ndWO3 3NO 7 WONWlS MI WX3 IO 7 **HlWd

PRIVATE )RECORD OF CHANGES LO1 08-01 NRC LO1 Examination Scenario 3 Page 2 of 13

TITLE: LOl-08-0 1 NRC EXAMINA TION SCENARIO 3. APRM instrument failure. Restoration of busses 10200 and 10400 to T4, Failure of LPCJ inverter, inadvertent HPCi initiation, Loss of Instrument Air, SRLOCA, Both loop of RHR Containment spray fail, Spray Torus/Drywell with RHR SW A.

6. SCENARIO SETUP:
1. Initial Protected IC 228
2. Special Instructions:
a. Plant operating normally a t 5 0 % CTP
3. Preset Conditions:

Trigger 1 N M 1 5 : B APRM Channel B inoperative - True Trigger 4 ED04:B Inverter 7 1-INV-36 Failure - True Trigger 5 H P 0 5 HPCl Inadvertent initiation - True Trigger 6 IA02 Loss of Instrument Air - 1 0 0 % Ramp 7 : O O minutes Trigger 7 - /*scram push button*/(zd5as3a= 1) II (zd5as3b= 1) II manual scram Trigger 8 - * / z l o l O a s l 3 a ( 2 ) = 1 I1 1Omov38a Trigger 9 - */zlolOas13b(2) = 1 II 1 0 m o v 3 8 b red light is o n

4. Consumable Forms and Procedures:

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

C. ' SCENARIO

SUMMARY

PRIVATE 1 Shift Turn0ver PRIVATE ]

The plant a t 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 Tasks/Standards PRIVATE ]

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

PRlV EVENT SEQUENCE ATE

)EVEN T NO.

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 L PCI inverter (Component failure) BOP
5. Inadvertent HPCI initiation (Component failure) BOP/SRO I 6- Unisolable leak on Instrument Air header (Component failure) All

~

SBLOCA on recirc line, containment spray required (Major transient) All I 8. I Spray torus, both loop of RHR fail (Component failure) All ~ ~~~

Spray Torus/Drywell with RHR S W (Major transient) All D. TERMINATION CUES:

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

(PRIVATE ]INSTRUCTOR POSIT1ON OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete I I Provide Turnover (Attach. 1 )

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 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

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

LO1 08-01 NRC LO1 Examination Scenario 3 OPERATOR ACTIONS/STANDARD CO MMENTS/EVALUAT10 N i

h o p trip of APRM CRS TS for failed APRM SAT / UNSAT / NA

  • No impact TRM for rod block
2. Restoration of busses ALL 3P-46A SAT / UNSAT / NA 10200 and 10400 from D.21 for 10200 (shift prior to 10400 bus by procedure note) reserve to normal. (Normal Evolution) *Station operators as follows:

One to adjust bus voltage at LTC CONTROL

[Cue CRSJ One to operate breaker control switches

  • Place BUS 10200 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, to perform each breaker operation:
  • Close NSS TO BUS 10200 BKR 10202.
  • Open RSS TO BUS 10200 BKR 10212.
  • Place BUS 1 0 2 0 0 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.

D.23 for 10400

.Station operators as follows:

LO1 08-01 NRC LO1 Examination Scenario 3

. I PRIVATE )INSTRUCTOR rd o PERATO R ACTIO NS/STAN DARD CO MMENTWEVALUAT ION ACTIVITY 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 at approximately 12 o'clock, perform the following bus transfer using the same hand, without unnecessary delay, to perform each breaker operation:
  • Close 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 6 power source selectors are on at panel 09-1 6.

Possible EPIC alarm on low volts, volts are in acceptable range 1546 - 6 151 no action required until after bus shift complete

3. Raises power with ATC Step 4 6 of pull sheet, Rod 30-19 from notch 12 to 24 control rods (Reactivity Rod 22-1 9 from notch 1 2 t o 2 4 manipulation)

[Cue CRSJ

4. Failure of LPCI inverter ALL 09-8-5-11 LPCI MOV I P S B 71INV-3B MINOR ALARM TROUBLE LO1 08-01 NRC LO1 Examination Scenario 3

. I<

OPERATOR ACTIONWSTANDARD COMMENTS/EVALUATION (Component failure} 09-8-5:6,7,9,10,1 1 (Various power supply trouble alarms)

[Cue Boothl NPO reports: LPCI inverter SN02 + Transfer LPCl MOV bus t o alternate feed b y 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 09-8.

b. Place LPCI MOV B PWR SUPP switch in ALT PULL TO Lock at panel 0 9 - 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 to 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' (7 day)

5. Inadvertent HPCI initiation SAT / UNSAT / NA (Component failure}

[Cue Booth]

HPCI initiates All Recognizes/report HPCl is starting I 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 va6d of charring but there is no fire in the Relay Room.

I CRS Directs SNO/NCO t o triphecure HPCl I SAT / UNSAT / NA LO1 08-01 NRC LO1 Examination Scenario 3 PRIVATE )INSTRUCTOR OPERATOR ACTIONS/STANDARD COMMENTS/EV ALUAT1ON ACTIVITY SNO Secure the HPCl turbine SAT / UNSAT / NA If HPCI injects CRS Enters AOP-32, Unexplained /Unanticipated Reactivity SAT / UNSAT / N A Addition (if HPCI injected and power changes)

CRS TS 3.5.1 D and C, 1 4 day LCO, verify RClC operable 7 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> t o restore HPCl or LPCl SN02 SBGT started on HPCl start, secure SBGT or lineup flow path by opening suction valve

-~~ ~ ~

6. Unisoiabie 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 9-6-2-31 SERVAIR HDR PRESS LO (95 psig) 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 OPERATOR ACTIONS/STANDARD COMMENTSIEVALUATION I 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 Directs 1OOF/hr cooldown fail safe position.

Valves drift from expected position due to vibration or system pressure.

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

07-707AOV-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 o f scram1 Prevent injection from LPCl and CS (EP-5)

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

Directs SNO to place loop of RHR in torus spray.

[Auto initiation]

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

PRIVATE ]INST'RUCTOR POSITION OPERATOR ACTlONSlSTANDARD ACTIVITY I

Crew uses RHR Service Water for torus and/or drywell spray SAT / UNSAT / NA per EP-14 (5.1 'A' loop or 5.2 '6' loop)

ALL

9. Spray Torus/Drywell SN02 Maintain RPV pressure with SRVs after MSlVs shut SN02 Spray DW when pressure reaches 15 psig. SAT / UNSAT / NA LO1 08-01 NRC LO1 Examination Scenario 3 -1 2-

ATTACHMENT 1 The plant at 50% power. Power ascension was suspended to allow Electrical Maintenance to 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 inspectionof 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.

LO1 08-01 NRC LO1 Examination Scenario 3 - 1 3-

TITLE: L 01-08-0I NRC EXAMINA TION 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 SCENARIO NUMBER: NEW PATH: 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 RE VIEWED LO1 08-01 NRC LO1 Examination Scenario 4 Page 2 of 10

TITLE: LOI-08-01 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/ R WR loop break inside drywell

/ Containment sprays required

8. SCENARIO SETUP:
1. Initial Protected IC 229
2. Special Instructions:
a. Plant operating normally a t 92% CTP
3. Preset Conditions:

Event 7 /*scram push buttons*/(zd5aas3a = 1) II (zd5as3b = 1) II m a n scram Event 1 0 /

  • 3 8 A o p e n * / z l o l O a s l 3 a ( 2 ) = 1 Event 1 1 /*386 o p e n * / z l o I O a s l 3 b ( 2 ) = 1
4. Consumable Forms and Procedures:

C. SCENARIO

SUMMARY

PRIVATE 1 Shift Turn0ver PRIVATE 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.

Criiical Tasks/Standards PRIVATE 1 1 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

PRlV EVENT SEQUENCE ATE

)EVEN T NO.

1. I Trip of 'B' Service Water pump. Manual start of 'A' SW pump. (Component Failure)
2. I Raise power by withdrawing control rods (Reactivity manipulation) 3.

~

I Stuck control rod (Component FailurellTech Spec)

4. Swap TBCLC pumps. (Normal evolution)
5. Loss of level control 6A FW heater. (Component failure)
6. Both Feed pumps trip. (Component Failure)
7. Condensate pumps trip. (Component Failure)
8. RCIC starts then trips after two minutes.

HPCI fail to auto start. (Component Failure)

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

D. TERMINATION CUES:

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

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

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 CRS

1. Trip of B Service Water pump .

Manual start of A SW pump.

(Component Failure)

[Cue booth]

Insert Trigger 1 ARP 9-6-2-13 SERV WTR PMP 4 6 P - I B OVERLOAD OR T R I P I ALL SN02 ARP 9-6-2-34 Service water header pressure low Operator starts standby pump. SAT / UNSAT / NA Reports failure of standby pump to start automatically.

LO1 08-01 NRC LO1 Examination Scenario 4

~RIVATE 1INSTRUCTOR OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ACTIVITY At this power level, the Acknowledges reports from SN02 crew recognizes that two S W pumps are required and the SN02 must SN02 Places BSWP 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 (Reactivitv manieulation)

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 FaiI ure)(Tech OP-25 Spec) OP-26 The ATC will recognize and 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 I

IAW OP-25 E. Incrementally raises drive water pressure to After first increase in drive ATC I LO1 08-01 NRC LO1 Examination Scenario 4

  • .I

~RIVATE~INSTRUCTOR P 6 SITION OPERATOR ACTIONSISTANDARD COMMENTWEVALUATION ACTIVITY water pressure, rod moves attempt rod withdrawal When drive dP raised 1 time delete RDIO stuck rod Rod may double notch at raised drive pressure ATC Recognizes and reports rod is withdrawing, restores CRD I I 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 %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 failure) AOP-62, Loss of Feedwater Heating 09-6-3-36 FDWTR HTR 6 A LVL HI 09-6-3-26 Hi-HI FDWTR HTR 6 A LVL HI-HI 09-7-3-1 1,12 IST STAGE RIITR DRN TK 3 A L a 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 ot3erated locallv All AOP-62 Loss of Feedwater Heating ATC Monitor for thermal hydraulic instability II I

CRS ATC Upon a noted rise in thermal power, Directs to rapidly lower recirc flow until power < 72%, do not go -65% core flow Lowers reactor power with recirc

~-

LO1 08-01 NRC LO1 Examination Scenario 4 PRIVATE )INSTRUCTOR 0 POSITI N OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ACTIVITY

6. Both Feed pumps trip.

(Component Failure)

Insert Trigger 6: when recirc ALL Recognize/report trip of both Feed Pumps SAT / UNSAT / NA is beina lowered in Event 5 CRS Directs insertion of manual scram. SAT / UNSAT / NA Critical Task SN02 Inserts manual scram. SAT / UNSAT / NA Takes mode switch to SHUTDOWN Makes Dost scram reDorts 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)

Loss of all feed SN02 Maintain level 177 - 222.5 inches SAT / UNSAT / NA I

8. RCIC starts and trips SN02 Operator identifies RClC trip SAT / UNSAT / hJA 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 / N h drywell. Containment EOP-4 High DW pressure, High Torus level sprays required. (Major 9-5-1-34 High Drywell pressure transient)

[Cue Booth1 Terminate and prevent Core Spray and RHR per EP-5 SAT / UNSAT / N k LO1 08-01 NRC LO1 Examination Scenario 4 E

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ATTACHMENT 1 Shift Turnover {PRIVATE }

92% CTP, pulling rods to 103% rod line and 96% U P , 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 from 12 - 16.

Crew will swap TBCLC pumps in preparation for maintenance. Start 'C', secure 'B'.

LO1 08-01 NRC LO1 Examination Scenario 4 - 1 0-

TITLE: LO/-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 RE VIEWED LO1 08-01 NRC LO1 Examination Scenario 5 Page 2 of 12

TITLE: LOl-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 a t 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

PRIVATE 1 Shift Turnover PRIVATE 1 Drywell is being purged IAW OP-37 0.6.11. SBGTA is running to vent torus CCondensate pump is running in preparation for securing B condensate pump for maintenance Control rods are at Step 47 Critical Tasks/Standards PRIVATE 1 Critical Task #1: Announce ATWS and depress ARI pushbutton Critical Task #2: Directs declaration of SAE due to failure of RWCU t o isolate Critical Task #3: Open 7 ADS valves 6

LO1 08-01 NRC LO1 Examination Scenario 5 Page 4 of 12

PRIV EVENT SEQUENCE ATE

}EVEN T NO.

1. 'A Standby Gas Treatment fan trip. (Component Failure) (Technical Specification)
2. Normal shutdown of 'B' condensate pump. (Normal evolution)
3. Failure of 'B' NR level instrument upscale, level transient. (Instrument failure)
4. Fuel clad failure (Component Failure) (Technical Specification)
5. A TWS due to RPS 'A' failure. Startup level control valve fail closed (Instrument failure)

(component failure)

6. FW 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. (Maior Transient)

I 9. 1 Reactor depressurization. (Major Transient)

D. TERMNA TION CUES:

1. All rods in.
2. 7 ADS valves open.

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

OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1) 'C' condensate pump is running in preparation for securing 'B' condensate pump SBGT 'A' is running to purge drywell IAW OP-37 D.6.11 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 CRS Provide crew brief. SAT / UNSAT / NA

1. 'A' Standby Gas CRS Annunciator 09-75 2 4 SAT / UNSAT / NA Treatment fan trip. Swap vent lineup using OP-20 (Component Failure)

(Technical Specification)

[Cue Booth]

SN02 Swap vent lineup using OP-20 Swap trains of SGT by opening SAT / UNSAT / NA NPO reports breaker for SGT 01-1 25MOV-12, 01-1 25MOV-l00B, AUTO start of 'B' fan

'A' is tripped, smell hot and there is NO fire CRS Determine TS action statement SAT / UNSAT / NA 3.6.4.3 Condition 'A', 7 day AOT

2. Norma1 shutdown of '8' OP-3 F . l Shutdown of ONE condensate pump condensate pump. (Normal LO1 08-01 NRC LO1 Examination Scenario 5

~RIVATE ACTIVITY evolution)

]INSTRUCTOR Ensure 'C' condensate pump is running prior to securing

'B' condensate pump.

PO SITION SNO-2 OPERATOR ACTIONS/STANDARD Place and hold pump control switch for the condensate pump to be shutdown in STOP.

WHEN condensate discharge header pressure stabilizes, allow pump control switch t o return to normal.

vCOMMENTS/EVALUATION SAT / UNSAT / NA

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

Cue Booth All Recognizeheport RV level high alarm 9 1 -28 Recognizesheport RPV level is lowering (annunciator 9 1 -

28)

Recognizeheport failure of 'B' NR level indication CRS Enters AOP-42, Feedwater Malfunction (Lowering Feedwater SAT / UNSAT / NA Flow)

NPO reports backfill system SNO Takes manual control of feedwater, returns water level t o the SAT / UNSAT / NA is normal. Nothing unusual green band.

a t instrument rack SNO If annunciator 09-5-1-28, RX WTR LVL ALARM HI OR LO SAT / UNSAT / NA alarms, refers to ARP CRS Assigns an SNO to feedwater control with no other duties. SAT / UNSAT / NA LO1 08-01 NRC LO1 Examination Scenario 5 OPERATOR ACTIONWSTANDARD COMMENTS/EVALUATION Note: possible RWR runback SNO Shift level column to A, per OP-2A G.30 if level column is shifted Place RX WTR LVL COLUMN SEL 06-SI switch in A-LEVEL.

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.

I I

CRS Refer to Tech Spec's, 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 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 to get below 70% rod line per RAP-PO wer reduction to stabilize 7.3.16.

SNO rad levels Reduce power to < 40% CTP LO1 08-01 NRC LO1 Examination Scenario 5

'1 1 _1

~RIVATE)INSTRUCTOR POSiTiON OPERA TO^ ACTIONSISTANDARD COMMENTS/EVALUATION ACTIVITY identifies EOP-5 entry on high rad level approaching rnax safe. SAT / UNSAT / NA All Identifies 15 min timer timed out.

Directs UE notification and applicable announcements [should SAT / UNSAT / NA CRS activate TSC and OSCI.

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

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

5. ATWS due to RPS 'A# ATC Recognizes and announces failure of manual scram. SAT / UNSAT / NA failure. (Instrument failure) Places Mode Switch t o Shutdown SNO-2 Recognizes and announces failure of mode switch to scram the reactor CRS Enters EOP-3 EAL Alert for failure t o 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 Directs level band of 177" to 222.5" Directs pressure stabilized 900 to 1000# with BPVs HPCl / RClC starts HPCl 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 lmklvarEjlNsrnucron ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION RPV level control will be SN02 Control RPV level using HPCI/RCIC/ feed via 34 MOV 100A or SAT / UNSAT / NA coarse with only discharge 1OOB valves for control.

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

Identifies failure of the RWCU 12MOV-15 t o isolate. SAT / UNSAT / NA SNO Identify entry conditions for AOP-39 (Loss of Coolant)

Directs entry into AOP-39. SAT / UNSAT / NA Directs execution of AOP-39 Attachment 2 by SNO.

CRS Attempt to isolate the leak by shutting 12MOV-15 EOP-5 on High Temps (RWCU and 300 RB)

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

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

~

Steam leak in RWCU area CRS May preemptively depressurize via the main condenser 3etermines temperatures are approaching SAE level. SAT / UNSAT / NA CRS i A L 4.1.1 CRS Ixecutes Emergency depressurization leg of EOP-2 due t o SAT / UNSAT / NA

.caching 2 MAX SAFES LO1 08-01 NRC LO1 Examination Scenario 5 PRIVATE 1 INSTRUCTOR POSITIO N OPERATOR ACTIONS/STANDARD CO MM ENTS/EVALUATIO N 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 As directed opens and verifies open 7 ADS valves CRITICAL STEP SAT / UNSAT I NA TERMINATE THE SCENARIO LO1 08-01 NRC LO1 Examination Scenario 5 -1 1-

ATTACHMENT 1 Shift Turnover PRIVATE Drywell is being purged IAW OP-37 0.6.11. SBGTA is running to vent torus C Condensate pump is running in preparation for securing B condensate pump for maintenance Control rods are at Step 47 LO1 08-01 NRC LO1 Examination Scenario 5 -1 2-

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