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, Emergenc y 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 at 87% 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 to 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 of all CRD pumps (Technical Specification)

6.
7.
8.
9.

Emergency Depressurization (Major Transient)

ATWS due to RPS failure. (Major Transient)

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

RCIC controller failure. (Component Failure)

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

Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete I Provide Turnover (Attach.

I I )

After the shift turnover, allow no more than five minutes for panel walkdown

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

[Cue CRS if needed]

POSITION All CRS OPERATOR ACTIONWTANDARD Maintenance and performance monitoring is on station for CRD pump vibration monitoring; need to swap CRD first thing.

Walkdown the control panels and assume the watch.

Provide crew brief OP-25 G.10 Changing In-service CRD Pumps

=Start CRD pump (CRD PMP 03P-16A ).

=Adjust CRD FLOW CNTRL 03FIC-301 to establish 59 to 61 gpm on 03FI-310 or 03FIC-301.

=Verify normal operating values on the following indicators at panel 09-5:

+ CHG WTR PRESS 03Pl-302: BETWEEN 1390 and 1580 psig, yJ to exceed 1670 psig COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA LO1 08-01 NRC LO1 Examination Scenario 1

2. Trip of HPCl Aux Oil Pump breaker.

(Component Failure)

[Cue booth]

ARP 9-3-3-38 S N 0-2 LCO 3.5. I Condition C SNO-2 ATCI SNO-2 Role play:

After several minutes, NPO reports no obvious problem at 23P-150.

Acrid odor at breaker 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 Recognize/report annunciator alarm for HPCl component loss of power SAT / UNSAT 1 NA

?ecognize/report Loss of power indication for 23P-150

%patches NPO to HPCI to investigate SAT / UNSAT / NA SAT / UNSAT / NA

,ocally:

Ierify green light at pump control switch.

teset the thermal overloads on the pump circuit ireaker.

tart AUX OIL PMP 23P-150.

IF motor trips again, THEN perform the following:

, determine ampere loading of motor

top AUX OIL PMP 23P-150.

LO1 08-01 NRC LO1 Examination Scenario 1

3. Power reduction to 65%

CTP for water box cleaning.

(Reactivity Manipulation) of Recirc runback.

(Corn pone n t Failure)

[Initiate from 83% CTP]

CRS CRS ATC OPERATOR ACTIONS/STANDARD observe pump for damaqe.

Reviews Technical Specifications TS LCO 3.5.1, Condition C. 14 day action statement Directs ATC to reduce reactor power using recirc. Do not go below 55% core flow.

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 9s follows:

.Adjust speed in I to 3% increments.

3P-27 Adjust RWR MG Set A/B speed to desired speed.

derify core flow and reactor power steady out following speed adjustment.

COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA LO1 08-01 NRC LO1 Examination Scenario 1

PRIVATE )INSTRUCTOR I ACTIVITY AOP-69: Monitor ACCUM alarm lights on full core display at panel 09-5, and execute ARP-09-5-1-43 as appropriate.

ARP 09-5-1 -43 actions:

AOP-42 Feedwater malfunction RWR pumps do not runback due to component failure SAT / UNSAT / NA

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.

ATC SN02 OPERATOR ACTIONWSTANDARD CO M ME NTS/EV ALU AT10 N AOP-42 Automatic Actions Loss of one reactor feed pump Reactor feed pump trip annunciator alarms RPV water level lowers If RPV water level lowers to 196.5 inches, both RWR MG sets run back to 44% speed Operating reactor feed pump should restore level

  • 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 LO1 08-01 NRC LO1 Examination Scenario 1

PRIVATE )INSTRUCTOR ACTIVITY 0

Depress manual scram pushbuttons Evaluator/Booth Operator Note: Spurious trip of B RFP should automatically occur when P/Bs are depressed.

Place reactor mode switch in shutdown Insert manual scram when evident CRD is not recoverable and accumulator alarms are in SAT / UNSAT / NA SN02 CRS ATC LO1 08-01 NRC LO1 Examination Scenario 1 OPERATOR ACTIONS/STANDARD

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 AOP-69:-Ensure CRD FLOW CNTRL 03FIC-301 is in MAN.
  • 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.

SAT / UNSAT / NA Direct insertion of manual scram CRITICAL TASK SAT / UNSAT / NA

~

Fully insert IRMs and SRMs 1 SAT / UNSAT / NA Verify power decreasing APRM / IRM / SRM

-1 0-1 SAT / UNSAT / NA

POS IT1 ON OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SN02 At 09-5 and 09-4, Recognize ATWS conditions, trend level performance and manipulate GEMAC Master/lndividual controllers, RFP discharge valves and RFP trip as necessary to control level.

SAT / UNSAT / NA

6. ATWS due to RPS failure. (Major Transient)

[AUTO]

ATC

  • Mode switch to shutdown

=Initiate ARI

  • Reduce recirc flow to minimum SAT / UNSAT / NA SNO SNO

=Trip both recirc pumps

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

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

SAT / UNSAT / NA CRITICAL TASK ALL

  • EP-5 Terminate and Prevent Injection High pressure injection systems first
  • Trip HPCl by depressing trip push buttons

=Manual control of FW SAT / UNSAT / NA Enter EOP-2 CRS LO1 08-01 NRC LO1 Examination Scenario 1

-1 1-

PRIVATE ]INSTRUCTOR POSITION ACTIVITY

9. Emergency Depressurization (Major Transient)
7. Main turbine trip, loss of Auxiliary busses (Component Failure)

Loss of Condensate and condensate booster pumps ALL

8. RClC controller failure.

SN02 (Com ponen t Failure)

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

I SN02 RCIC starts, runs to low speed stop I

I CRS I

I SNO LO1 08-01 NRC LO1 Examination Scenario 1 OPERATOR ACTIONS/STANDARD

.Lower level maintain level 80 - 100 EvaluatorlBooth Operator: When scram fuses are pulled (see above), power will rapidly drop as rods insert, and the 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.

MSlVs shut Inject with RClC maintain level 80 - 100 EvaluatorlBooth Operator: RCIC will trip 3 minutes after applicant shifts controller to Manual.

Take manual control of RClC All rods in (after RPS fuses are pulled in EP-3)

Exit EOP-3, enter EOP-2 Directs SNO to open 7 ADS valves Opens seven ADS valves Directs the SNO to maintain level 0 to 222.5 with LPCl

- 1 2-COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT I UNSAT / NA SAT / UNSAT / NA CRITICAL STEP SAT / UNSAT / NA CRITICAL STEP SAT / UNSAT / NA SAT / UNSAT / NA

I m C

0 CI m

C m

X w

E 9

a3 0

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 WON Wl S MI WX3 IO 7 **Hl Wd

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 at 50% CTP
3. Preset Conditions:

Trigger 1 NM15:B APRM Channel B inoperative - True Trigger 4 ED04:B Inverter 7 1 -INV-36 Failure - True Trigger 5 HP05 HPCl Inadvertent initiation - True Trigger 6 IA02 Loss of Instrument Air - 100% Ramp 7:OO minutes Trigger 7 - /*scram push button*/(zd5as3a= 1) II (zd5as3b= 1) II manual scram Trigger 8 - */zlol Oasl3a(2) = 1 I1 1 Omov38a Trigger 9 - */zlolOas13b(2) = 1 II 10mov38b red light is on

4. Consumable Forms and Procedures:

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

C.

' SCENARIO

SUMMARY

PRIVATE 1 Shift Turn0 ver PRIVATE ]

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 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:

Critical Task #2:

Sprays containment Critical Task #3:

Critical Task #4:

Manual scram on loss of instrument air LO1 08-01 NRC LO1 Examination Scenario 3 Page 4 of 13

PRlV ATE

)EVEN T NO.

1.

EVENT SEQUENCE

2.
3.
4.
5.

APRM instrument failure. (Instrument failure) RO Restoration of busses 10200 and 10400 to T4. (Normal Evolution) All Raises power with control rods (Reactivity manipulation) RO Failure of L PCI inverter (Component failure) BOP 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.

TERMINA TION CUES:

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

(PRIVATE ]INSTRUCTOR Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow no more than five minutes for panel walkdown

1. APRM instrument failure.

(Instrument failure)

[Cue Booth]

POS IT1 ON OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION I

I All Walkdown the control panels and assume the watch.

SAT / UNSAT / NA CRS ALL ATC LO1 08-01 NRC LO1 Examination Scenario 3 Provide crew brief.

  • Identifies 'B' APRM inop
  • Reset '/2 Scram SAT / UNSAT / NA SAT / UNSAT / NA (note: procedure use is not required for bypassing APRM and resetting % scram)

hop trip of APRM i

2. Restoration of busses 10200 and 10400 from reserve to normal. (Normal Evolution)

[Cue CRSJ CRS ALL LO1 08-01 NRC LO1 Examination Scenario 3 OPERATOR ACTIONS/STANDARD TS for failed APRM

  • No impact TRM for rod block 3P-46A D.21 for 10200 (shift prior to 10400 bus by procedure note)
  • Station operators as follows:

One to adjust bus voltage at LTC CONTROL 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 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 10200 BKR 10202.
  • Open RSS TO BUS 10200 BKR 1021 2.
  • Place BUS 10200 FDR SYNCH SW switch in OFF and remove handle.
  • Verify all white lights for RPS A and RPS B power source selectors are on at panel 09-1 6.

D.23 for 10400

.Station operators as follows:

CO M M ENTS/EVALU AT10 N SAT / UNSAT / NA SAT / UNSAT / NA

PRIVATE )INSTRUCTOR rd ACTIVITY

3. Raises power with control rods (Reactivity manipulation)

[Cue CRSJ

4. Failure of LPCI inverter ATC ALL I

o PERATO R ACTIO NS/STAN DARD 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 1041 2.
  • 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 Step 46 of pull sheet, Rod 30-1 9 from notch 12 to 24 Rod 22-1 9 from notch 12 to 24 09-8-5-11 LPCI MOV IPS B 71INV-3B MINOR ALARM TROUBLE LO1 08-01 NRC LO1 Examination Scenario 3 CO M M ENT WEVALU AT ION

(Component failure}

[Cue Boo thl NPO reports: LPCI inverter input breaker is tripped on MCC-162

5. Inadvertent HPCI initiation (Component failure}

[Cue Booth]

HPCI initiates Acting as an NPO report:

23 AK-3 relay has evidence of charring but there is no fire in the Relay Room. I SN02 CRS All CRS SNO CRS LO1 08-01 NRC LO1 Examination Scenario 3 I<

OPERATOR ACTIONWSTANDARD 09-8-5:6,7,9,10,1 1 (Various power supply trouble alarms)

+ Transfer LPCl MOV bus to alternate feed by ARP

i. Investigate cause of alarm.

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

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 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.

+ 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)

Refer to Technical Specifications.

COMMENTS/EVALUATION SAT / UNSAT / NA Recognizes/report HPCl is starting I SAT / UNSAT / NA Directs crew to verify the validity of the HPCl auto start using multiple indications SAT / UNSAT / NA Observer indications for Drywell pressure and reactor level, determines HPCl start is not va6d SAT / UNSAT / NA Directs SNO/NCO to triphecure HPCl I SAT / UNSAT / NA

PRIVATE )INSTRUCTOR ACTIVITY If HPCI injects

-~~

~

~

6. Unisoiabie leak on instrument Air Header

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

Role play:

As NPO report massive air leak on common discharge piping of air compressors.

Leak is not isolable SNO CRS CRS SN02 ALL CRS ATC 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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore HPCl or LPCl SBGT started on HPCl start, secure SBGT or lineup flow path by opening suction valve Air compressors start, air pressure trends down AOP-12 Directs manual scram 9-6-2-39 SERV AIR HDR ISOL VLV CLOSED (95 psig) 9-6-2-31 SERVAIR HDR PRESS LO (95 psig) 9-7-3-43 SPE Vac Lo EOP-5 entry on RB pressure INSERT Manual Scram COM M ENT S/EV ALU AT1 ON SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA CRITICAL TASK upon rod drift alarm or recognize not recoverable AOP-12 LO1 08-01 NRC LO1 Examination Scenario 3

I Depending on the severity of the loss of air or the source of the problem, the following could occur:

Control rods drift inward.

Air operated valves fail as-is or in 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, containment spray required (Major transient)

[Auto initiation upon insertion o f scram1

8. Spray Torus failure

[Auto initiation]

Use other loop of RHR for success CRS CRS CRS SN02 LO1 08-01 NRC LO1 Examination Scenario 3 OPERATOR ACTIONS/STANDARD OUTBD MSlVs will eventually shut on loss of air EOP-2 on low RPV level after scram Level control 177-222.5 inches Directs 1 OOF/hr cooldown COMMENTSIEVALUATION AOP-39 Drywell pressure increasing EOP-2 and EOP-4 on High DW pressure All EDGs start Prevent injection from LPCl and CS (EP-5)

Directs initiation of Torus Sprays when torus pressure is greater than 2.7 psi.

Directs SNO to place loop of RHR in torus spray.

Places loop of RHR in torus spray Pumps tripped when starting torus spray Shift to other RHR loop, both RHR pumps trip SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA

-1 1-

PRIVATE ]INST'RUCTOR ACTIVITY I ALL POSITION OPERATOR ACTlONSlSTANDARD Crew uses RHR Service Water for torus and/or drywell spray per EP-14 (5.1 'A' loop or 5.2 '6' loop)

9. Spray Torus/Drywell SN02 SN02 Maintain RPV pressure with SRVs after MSlVs shut Spray DW when pressure reaches 15 psig.

SAT / UNSAT / NA 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 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.

LO1 08-01 NRC LO1 Examination Scenario 3

- 1 3-

TITLE:

L 01-08-0 I 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/ R WR 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 DA TE SOURCE OF BRIEF DESCRIPTION OF CHANGE CHANGE INITIA TOR RE VIE WED 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 at 92% CTP
3. Preset Conditions:

Event 7 /*scram push buttons*/(zd5aas3a = 1) I I (zd5as3b = 1) I I man scram Event 1 0 /

  • 3 8 A open*/zlol Oasl3a(2) = 1 Event 11 /*386 open*/zloIOasl3b(2) = 1
4. Consumable Forms and Procedures:

C.

SCENARIO

SUMMARY

PRIVATE 1 Shift Turn0 ver 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/Stan dards 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 TBCL C pumps. (Normal evolution)

5.
6.
7.
8.

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

Both Feed pumps trip. (Component Failure)

Condensate pumps trip. (Component Failure)

RCIC starts then trips after two minutes.

HPCI fail to auto start. (Component Failure)

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

9.

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

(PRIVATE

)INSTRUCTOR ACTIVITY ARP 9-6-2-1 3 SERV WTR PMP 46P-IB OVERLOAD OR TRIP ARP 9-6-2-34 Service water header pressure low Operator starts standby pump.

Reports failure of stand by pump to start automatically.

Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach.

SAT / UNSAT / NA After the shift turnover, allow no more than five minutes for panel walkdown

1. Trip of B Service Water pump.

Manual start of A SW pump.

(Component Failure)

[Cue booth]

Insert Trigger 1 I

POSITION All CRS ALL SN02 OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Walkdown the control panels and assume the watch.

SAT / UNSAT / NA LO1 08-01 NRC LO1 Examination Scenario 4

~ R I V A T E 1 INSTRUCTOR ACTIVITY At this power level, the crew recognizes that two S W pumps are required and the SN02 must 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 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 (Com pone n t Fai I ure)(Tec h Spec)

The ATC will recognize and report control rod 18-39 fails to move After first increase in drive SN02 ATC CRS ATC LO1 08-01 NRC LO1 Examination Scenario 4 OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Acknowledges reports from SN02 Places B SWP in PTL OP-25 Pull Sheet Step 65 from 12 to 16 OP-25 OP-26 Reports rod 18-39 will not withdraw with normal drive pressure Acknowledge and concur with raising drive pressure IAW OP-25 E. Incrementally raises drive water pressure to I

I

~RIVATE~INSTRUCTOR ACTIVITY P6S IT IO N NPO reports both valves are closed. No response when ot3erated locallv water pressure, rod moves When drive dP raised 1 time delete RDIO stuck rod All ATC

4. Swap TBCLC pumps.

CRS (Normal evolution)

In support of maintenance, SN02 the crew swaps TBCLC starts the %pump, secures the Bpump.

[Cue CRS]

5. Loss of level control 6A FW heater string.

(Com ponent failure)

All ATC I CRS I I ATC

.I OPERATOR ACTIONSISTANDARD COMMENTWEVALUATION attempt rod withdrawal Rod may double notch at raised drive pressure Recognizes and reports rod is withdrawing, restores CRD I

I parameters to normal range Directs TBCLC pump swap OP-41 G.l Steps 1 - 5 AOP-32, Unexplained power change (if crew does not recognize level control failure but notes a rise in CTP)

AOP-62, Loss of Feedwater Heating 09-6-3-36 FDWTR HTR 6A LVL HI 09-6-3-26 Hi-HI FDWTR HTR 6A 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 Normal and dump valve are not responding AOP-62 Loss of Feedwater Heating Monitor for thermal hydraulic instability 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 ACTIVITY SN02

6. Both Feed pumps trip.

(Component Failure)

Insert Trigger 6: when recirc is beina lowered in Event 5 Maintain level 177 - 222.5 inches

7. Condensate pumps trip on reactor scram (Component failure)

SN02 CRS Loss of all feed I

Operator identifies RClC trip Operator identifies HPCl failure to auto start, manually aligns and injects with HPCl (opens 23 MOV-14)

HPCl in pressure control mode TS entries on HPCl and RClC

8. RCIC starts and trips after two minutes, 10 seconds HPCl fails to AUTO start, but is available to start manually. (Component fai I u re\\
9. RWR loop break in drywell. Containment sprays required. (Major transient)

[Cue Booth1 POS ITI 0 N OPERATOR ACTIONS/STANDARD ALL CRS Recognize/report trip of both Feed Pumps Directs insertion of manual scram.

SN02 Inserts manual scram.

Takes mode switch to SHUTDOWN Makes Dost scram reDorts CRS EOP-2 on low RPV level AOP-1 for reactor scram EOP-2 EOP-4 High DW pressure, High Torus level 9-5-1 -34 High Drywell pressure Terminate and prevent Core Spray and RHR per EP-5 COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA Critical Task SAT / UNSAT / NA Critical Task SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / hJA SAT / UNSAT / N h SAT / UNSAT / Nk LO1 08-01 NRC LO1 Examination Scenario 4

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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

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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 DA TE SOURCE OF BRIEF DESCRIPTION OF CHANGE CHANGE INITIA TOR RE VIE WED 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 at 50% CTP
3. Preset Conditions:
4. Consumable Forms and Procedures:

LO1 08-01 NRC LO1 Examination Scenario 5 Page 3 of 12

C.

SCENARIO

SUMMARY

PRIVATE 1 PRIVATE 1 Shift Turnover 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 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 to isolate Critical Task #3: Open 7 ADS valves 6

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

P R I V ATE

}EVEN T NO.

EVENT SEQUENCE I

8.

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

1.
2.
3.
4.
5.
6.
7.

I

9.

1 Reactor depressurization. (Major Transient)

'A Standby Gas Treatment fan trip. (Component Failure) (Technical Specification)

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

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

Fuel clad failure (Component Failure) (Technical Specification)

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

(component failure)

FW startup level control valve failure (Component Failure)

R WCU failure to isolate (Component Failure)

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

Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Turnover (Attach. 1)

After the shift turnover, allow no more than five minutes for panel walkdown

1. 'A' Standby Gas Treatment fan trip.

(Component Failure)

(Technical Specification)

[Cue Booth]

NPO reports breaker for SGT

'A' is tripped, smell hot and there is NO fire

2. Norma1 shutdown of '8' condensate pump. (Normal All CRS CRS SN02 CRS LO1 08-01 NRC LO1 Examination Scenario 5 OPERATOR ACTIONS/STANDARD

'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 Walkdown the control panels and assume the watch.

Provide crew brief.

Annunciator 09-75-1 -24 Swap vent lineup using OP-20 Swap vent lineup using OP-20 Swap trains of SGT by opening 01-1 25MOV-12, 01-1 25MOV-l00B, AUTO start of 'B' fan Determine TS action statement 3.6.4.3 Condition 'A', 7 day AOT OP-3 F.l Shutdown of ONE condensate pump COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA

~ R I V A T E

]INSTRUCTOR ACTIVITY evolution)

Ensure 'C' condensate pump is running prior to securing

'B' condensate pump.

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

Cue Booth NPO reports backfill system is normal. Nothing unusual a t instrument rack PO SITION SNO-2 All CRS SNO SNO CRS 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 to return to normal.

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

28)

Recognizeheport failure of 'B' NR level indication Enters AOP-42, Feedwater Malfunction (Lowering Feedwater Flow)

Takes manual control of feedwater, returns water level to the green band.

If annunciator 09-5-1-28, RX WTR LVL ALARM HI OR LO alarms, refers to ARP Assigns an SNO to feedwater control with no other duties.

COMMENTS/EVALUATION v SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA LO1 08-01 NRC LO1 Examination Scenario 5

Note: possible R WR runback if level column is shifted AOP-3, High Activity in Reactor Coolant or Off-gas Directs entry into AOP-3.

Directs local evacuations of areas with ARMS in alarm.

Directs reduction in power to reduce rad levels I

SAT / UNSAT / NA I

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 Crew performs a controlled PO wer reduction to stabilize rad levels SNO CRS CRS All SNO LO1 08-01 NRC LO1 Examination Scenario 5 OPERATOR ACTIONWSTANDARD Shift level column to A, per OP-2A G.30 Place RX WTR LVL COLUMN SEL 06-SI switch in A-LEVEL.

Ensure RPV water level stabilizes.

COMMENTS/EVALUATION 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.

Refer to Tech Spec's, table 3.3.2.2 A, 7 day AOT I SAT / UNSAT / NA 09-3-2-1 0 Off-Gas timer initiates Announce evacuate TB SAT / UNSAT / NA Inserts control rods to get below 70% rod line per RAP-7.3.16.

Reduce power to < 40% CTP

~RIVATE)INSTRUCTOR ACTIVITY

5. ATWS due to RPS 'A#

failure. (Instrument failure)

Rods fail to insert, ARI is successful

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

'1 POSiTiON All CRS CRS SNO ATC SNO-2 CRS ATC CRS CRS LO1 08-01 NRC LO1 Examination Scenario 5 OPERA TO^ ACTIONSISTANDARD identifies EOP-5 entry on high rad level approaching rnax safe.

Identifies 15 min timer timed out.

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

Directs a manual scram prior to reaching a max safe and execution of AOP-1.

Announces and inserts a manual scram.

Recognizes and announces failure of manual scram.

Places Mode Switch to Shutdown Recognizes and announces failure of mode switch to scram the reactor Enters EOP-3 EAL Alert for failure to scram Announce ATWS and depress ARI pushbutton Announces success of ARI and carries out AOP-1.

Exits EOP-3 Directs entry into EOP-2 HPCl / RClC starts Directs level band of 177" to 222.5" Directs pressure stabilized 900 to 1000# with BPVs HPCl may be tripped by operator if flow is not needed 1

_1 COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA CRITICAL STEP SAT / UNSAT / NA SAT / UNSAT / NA

lmklvarEjlNsrnucron ACTIVITY RPV level control will be coarse with only discharge valves for control.

7. RWCU fails to isolate (after scram RPV level shrink) (Component Failure)
8. Steam leak in Reactor Building resulting in rad release. (Major Transient)

~

Steam leak in RWCU area POSITION SN02 SNO CRS CRS CRS CRS CRS LO1 08-01 NRC LO1 Examination Scenario 5 OPERATOR ACTIONS/STANDARD Control RPV level using HPCI/RCIC/ feed via 34 MOV 100A or 1 OOB Identifies failure of the RWCU 12MOV-15 to isolate.

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

Directs entry into AOP-39.

Directs execution of AOP-39 Attachment 2 by SNO.

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 to failure of RWCU to isolate.

EAL 3.4.1 May preemptively depressurize via the main condenser 3etermines temperatures are approaching SAE level.

i A L 4.1.1 Ixecutes Emergency depressurization leg of EOP-2 due to

.caching 2 MAX SAFES COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA CRITICAL STEP SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA

PRIVATE 1 INSTRUCTOR POSITIO N

ACTIVITY

9. Emergency Depressurization (Major Transient)

CRS OPERATOR ACTIONS/STANDARD Directs 7 ADS valves opened.

Directs level control maintained with feed and condensate at 177" t o 222.5".

As directed opens and verifies open 7 ADS valves TERMINATE THE SCENARIO CO M M ENTS/EVALUATIO N CRITICAL STEP SAT / UNSAT / NA CRITICAL STEP SAT / UNSAT I NA LO1 08-01 NRC LO1 Examination Scenario 5

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ATTACHMENT 1 PRIVATE Shift Turnover 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

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