Text

Final AS-ADMINISTERED Scenarios for the Duane Arnold Examination - November 2002
	ML030590214
Person / Time
Site:	Duane Arnold
Issue date:	11/18/2002
From:	; Nuclear Management Co
To:	; Office of Nuclear Reactor Regulation
References
	50-331/02-301
	Download: ML030590214 (132)
	v • d • e

FINAL AS-ADMINISTERED SCENARIOS FOR THE DUANE ARNOLD EXAMINATION - NOVEMBER 2002

Appendix D . Scenario Outline -- - -,Form ES-D-1 Equivalent Facility: Scenario No.: 1 Op-Test No.:

DAEC (ILC ESG 2002 ILC EXAM Examiners-__________

Examiners:

Significantly Modified Oeaos 2002 CE Initial Condition: Reactor startup in progress at approximately 9% power. EHC Pressure Set is at 940 psig. IRM F has failed downscale and is bypassed.

1 N (BOP) Place a RWCU bed in service.

2 N (RO) Transfer the MODE switch to RUN.

3 R (RO) Withdraw control rods to approximately 12% power.

4 I/C (RO) Control rod 22-39 will not move with normal drive water pressure.

5 I/C Two "C" main steam line high flow DPIS will fail low, due to SRO) equalizing valve found open.

6 I/C (RO) The in-service CRD pump trips.

7 N (RO) Start of the "A" CRD pump.

8 I/C The HPCI Turbine will receive a spurious initiation signal.

(BOP) 9 M (ALL) Torus Leak on HPCI Suction Line and eventual ED.

10 I/C The first Core Spray fill attempt will not work, broken stem on valve.

(BOP) The second Core Spray fill line will work but will not keep up with the leak.

11 I/C If ED is anticipated #1 BPV will fail to open.

(BOP)

-ri')ormal, (H)eactivlty, (I)nstrument, (C)omponent, (M)ajor S-/

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Attachment 6

QF-1030-19 Rev. 0 (FP-T-SAT-30)

EVALUATION SCENARIO GUIDE (ESG)

COMM~tedto NcerEcf¶ 10§ :ýDAEC P GA -OPERAITONS #:

CUS:ILC #: 50007 TTLTM:2 HOURS Instructor Date SMElInstructor

- '/ uperations Manager Date Training Supervisor-Operations Date Retention: Life of policy = lOyrs.

Retention: Life of policy = 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File 2002_ESG 14_newtemplete-doc Page 1 of 35

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MODE SWITCH TO RUN/ PLACE RWCU BED IN SERVICEIMSL DP CELL FAILURE/ ROD PULL/STUCK ROD/CRD PUMP TRIP/HPCI AUTO INITIATION/TORUS LEAK/EOP 3/CS TO TORUS FILL FAILURE/#1 BPV FAILURE/ED, Rev. 0 Guide Requirements Simulator Training Floor Instructor Resources: Booth Instructor Phone Talker

1. IPOI-2

References:

2. ITS

3.01-878.2

4.01-261

5. ARP 1C05A, D-6

6. 01 878.8

7.01-644

8. ARP 1C05A, A-7

9.01-255

10. ARP 1C07B, B-9 11.01304.1

12. EOP-1

13. IPOI-5

14.01-150

15.01-152

16. ACP 1410.10

17. AOP 255.1

18. EOP 1 Performance Mode Evaluation Method:

2002_ESG 14_newtemplete.doc Page 2 of 35

QF-1 030-19 Rev. 0 (FP-T-SAT-30)

MODE SWITCH TO RUN/ PLACE RWCU BED IN SERVICE/MSL DP CELL FAILURE/ ROD PULL/STUCK ROD/CRD PUMP TRIP/HPCI AUTO INITIATION/TORUS LEAK/EOP 3/CS TO TORUS FILL FAILURE/#1 BPV FAILURE/ED, Rev. 0 SCENARIO

SUMMARY

Current plant operating status.

Reactor startup is in progress at approximately 9% power. EHC Pressure Set is at 940 psig. IRM F has failed downscale and is bypassed.

Scenario segments

"* Event 1 (N) Place a RWCU bed in service. (BOP)

"* Event 2 (N) Transfer the MODE switch to RUN. (RO) (SRO)

"* Event 3 (R) Withdraw control rods to approximately 12% power. (RO) (SRO)

"* Event 4 (I/C) Control rod 22-39 will not move with normal drive water pressure. (RO)

"* Event 5 (I/C) Two "C" main steam line high flow DPIS will fail low, due to equalizing valve found open. (SRO)

"* Event 6 (I/C) The in-service CRD pump trips.(RO)

"* Event 7 (N) Start of the "A" CRD pump. (RO)

"* Event 8 (I/C) Inadvertent Start of the HPCI Turbine.

"* Event 9 (M) Torus leak on HPCI Suction line and eventual ED

"* Event 10 (I/C) The first Core Spray fill attempt will not work, broken stem on valve. The other Core Spray fill line will work but will not keep up with the leak.

"* Event 11 (I/C) If ED is anticipated #1 BPV will fail to open 2002_ESG 14_newtemplete.doc Page 3 of 35

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MODE SWITCH TO RUN/ PLACE RWCU BED IN SERVICE/MSL DP CELL FAILURE/ ROD PULL/STUCK ROD/CRD PUMP TRIP/HPCI AUTO INITIATION/TORUS LEAK/EOP 3/CS TO TORUS FILL FAILURE/#1 BPV FAILURE/ED, Rev. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE:

Crew Evolutions:

None

= RO (NSOE, ANSOE)

Task 11.03 Place a RWCU F/D in service.

Task 10.01 Start a CRD pump under normal conditions.

Task 101.14 Respond to a complete loss of CRD water flow.

Task 5.07 Shutdown under auto or manual turbine trip. HPCI Task 72.07 Withdraw control rods using group notch.

Task 79.01 Operate the IRM system during a plant startup.

Task 93.08 Place the Mode Switch in Run from Startup/Hot Standby when power is between 5-12 %.

Task 93.22 Perform immediate operator responses to a reactor scram.

Task 94.02 Respond to no rod movement.

Task 95.44 Perform actions of RC/L of EOP-1.

Task 95.46 Perform actions of RC/P of EOP-1.

Task 95.48 Rapid depressurization with bypass valves Task 95.59 Perform T/L leg of EOP 2 for a rising torus level.

=> Shift Supervisor (SS)

Task 1.01 Direct routine crew and control room activities.

1.01.02 Coordinate operator activities.

1.01.03 Ensure control room activities conform to ACP 1410.1 Conduct of Operations.

Task 1.03 Determine the reportability of the event.

+ Task 1.06 Conduct Shift Brief.

1.06.01 Announce that the crew brief is starting.

1.06.02 Conduct the shift briefing.

1.06.03 Solicit additional comments from each crewmember.

1.06.04 Announce that the briefing is complete.

Task 1.02 Determine operability of Tech Spec required components.

2002_ESG 14_newtemplete.doc Page 4 of 35

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MODE SWITCH TO RUN/ PLACE RWCU BED IN SERVICE/MSL DP CELL FAILURE/ ROD PULL/STUCK ROD/CRD PUMP TRIP/HPCI AUTO INITIATION/TORUS LEAK/EOP 3/CS TO TORUS FILL FAILURE/#1 BPV FAILURE/ED, Rev. 0

1.02.02 Determine if the instrument, component, or system is operable.

1.02.03 Declare the instrument, component and/or system inoperable, enter the correct Condition. If applicable, determine and direct performance or performance of the required SRs,

+ Task 1.21 Direct crew response to off normal event/accidents.

1.21.01 Evaluate the event, determine the cause, and develop mitigation strategies.

1.21.02 Recognize and prioritize data relevant to the accident.

Task 4.07 Direct crew actions to place the Mode Switch in Run from Startup/Hot Standby when power is between 5-12 %.

4.07.01 Supervise the crew to place the Mode Switch in Run.

Task 4.21 Direct crew actions to perform the immediate operator responses to a reactor scram.

e 4.21.03 Direct operator performance of IPOI-5 immediate actions.

Task 5.02 Direct crew response to no control rod movement.

5.02.01 Direct operators to perform immediate and follow-up actions of AOP 255.1 for no rod movement.

5.02.02 Direct operators to commence normal control rod movement lAW control rod withdrawal sequence.

Task 6.44 Direct crew response for performance of the RC/L leg of EOP-1.

6.44.01 Direct operator actions to maintain RPV level between 170" and 211" using the Table 1 injection systems.

Task 6.46 Direct crew response for performance of the RC/P leg of EOP-1.

6.46.04 Direct operator actions to augment RPV pressure control with other steam loads, SRVs, or RWCU.

6.67.01 Direct entry into EOP 3.

6.67.11 Determine if RPV pressure reduction will decrease leakage into secondary containment.

6.48.01 Direct operator actions to rapidly depressurize the RPV with the turbine bypass.

6.55.03 Direct operator actions to prevent injection from HPCI if not required for adequate core cooling and prevent injection from core spray and RHR pumps not required to assure adequate core cooling.

6.60.01 Direct operator actions to raise torus water level using HPCI and/or core spray if they are not required for adequate core cooling and maintain torus water level above 7.1 feet.

2002_ESG 14_newtemplete.doc Page 5 of 35

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MODE SWITCH TO RUN/ PLACE RWCU BED IN SERVICE/MSL DP CELL FAILURE/ ROD PULL/STUCK ROD/CRD PUMP TRIP/HPCI AUTO INITIATION/TORUS LEAK/EOP 3/CS TO TORUS FILL FAILURE/#1 BPV FAILURE/ED, Rev. 0 Scenario Objective(s):

1. Place a RWCU bed in service..

2. Transfer the MODE switch to RUN

3. Withdraw control rods to approximately 12% power.

4. Enter AOP 255.1 for no rod motion.

5. T.S. call for MSL Flow instruments failure.

6. Start a CRD pump following the loss of the running CRD pump.

7. Secure the HPCI Turbine following and inadvertent initiation.

8. ED based on Torus Level reaching 7.1 ft.

9. Determine First CS system will not fill the Torus switch to the other CS system

10. Determine SEP 307 is not working correctly 2002_ESG 14_new templete.doc Page 6 of 35

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MODE SWITCH TO RUN/ PLACE RWCU BED IN SERVICE/MSL DP CELL FAILURE/ ROD PULL/STUCK ROD/CRD PUMP TRIP/HPCI AUTO INITIATION/TORUS LEAK/EOP 3/CS TO TORUS FILL FAILURE/#1 BPV FAILURE/ED, Rev. 0 SCENARIO OUTLINE:

BOOTH INSTRUCTOR ACTIONS 1 Non-Nuclear Instrumentation System 1.1 SIMULATOR SET UP:

a. Verify the following audits have recently been completed:

(1) Procedure racks - ILC Procedures (2) EOP Key locker and Defeat packages

b. Reset to IC 9. (Mode switch is in Startup at z 5% power).

c. Go to RUN.

d. Place the Recirc and Feedwater (Startup & Master) controllers in auto.

e. At the PPC (1) Substitute final feed water points B030 through B033 to 80 OF.

(2) NOTE THAT THESE SUBSTITUTIONS MUST BE REMOVED AT THE END OF THE SCENARIO.

f. IC05 Control panel setup:

(1) Pull rods to Step 25 position 20 and allow the simulator to set for a while.

(Roll back panel recorders)

(2) After the plant is stable verify APRM readings on 1 C05 are between 5 and 12%

(3) Bypass F IRM.

(4) Shift two IRM recorders to fast speed.

(5) Place the ROD OUT magnet on the Rod Movement switch.

(6) Mark up a pull sheet for the current rod positions.

g. Other Control panel setups:

(1) Raise EHC Pressure Set to 940 psig.

(2) Remove keys from Condenser High Backpressure bypass switches.

(3) Verify RWCU draining has been secured.

(4) Establish chest warming. (4.0 on potentiometer)

(5) Remove the "B" RWCU F/D from service.

(6) Roll Recorders (7) Pump the sumps.

(8) Start Drywell inerting.

h. Tags: (Fill out needed information)

(1) Remove LOR Cycle Tags and Degraded Instruments.

(2) Place warning tag on F IRM.

CONTINUED ON NEXT PAGE 2002_ESG 14_newtemplete.doc Page 7 of 35

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MODE SWITCH TO RUN/ PLACE RWCU BED IN SERVICE/MSL DP CELL FAILURE/ ROD PULL/STUCK ROD/CRD PUMP TRIP/HPCI AUTO INITIATION/TORUS LEAK/EOP 3/CS TO TORUS FILL FAILURE/#1 BPV FAILURE/ED, Rev. 0

i. Provide the following documentation:

(1) A Working Copy of IPOI-2 marked through Step 4.3 (9).

(2) Mark up 01 693.1 to Step 3.4(2)

(3) Mark up 01 573 to Step 3.2(12)

j. Plant Process Computer:

(1) Provide Group display 32 on one terminal (2) Display SPDS on the terminal near 1C14.

k. Insert SETUP Malfunctions.

I. Insert SETUP overrides.

m. Verify RWM in operate.

n. Verify 1C80 condensate demin annunciator is reset.

o. Reset HPCI High Level Trip.

p. Reset Recirc 45% runback.

q. Verify SJAEs are in Automatic.

r. At 1C23, place 1P52B HS to Start.

s. Verify OG system pressure is normal.

t. Verify only one 1V-EF-18 is running.

u. Have INOP package for HPCI available in STP file (STP 3.5.1-08).

v. Place a copy of 01 261 in Booth for reference during RWCU evolution Event 1

w. Verify Shift Turnover form isfilled out for both SRO and RO positions.

2002_ESG 14_newtemplete.doc Page 8 of 35

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MODE SWITCH TO RUN/ PLACE RWCU BED IN SERVICE/MSL DP CELL FAILURE/ ROD PULL/STUCK ROD/CRD PUMP TRIP/HPCI AUTO INITIATION/TORUS LEAK/EOP 3/CS TO TORUS FILL FAILURE/#1 BPV FAILURE/ED, Rev. 0

1.2 MALFUNCTIONS

ILC14 or (craig1)

Time Malfunction No. Malfunction Title ET Delay F. Ramp I.

Sev. Sev.

T=0 nm04f F IRM Failed Downscale 0 T=0 rd03039 Rod 30-39 blade stuck T=O rx020623 Rod worth change 0.22 T=0 rx022239 Rod worth change 0.22 T=0 rx023823 Rod worth change 0.22 T=O rx022207 Rod worth change 0.22 As Dir rdllb B CRD Pump trip I When hp01 HPCI Auto Initiate 3 N/A .2 600 0 called for When pc14 Primary Containment Torus leak N/A N/A N/A N/A N/A HPCI in SB AS tc06a #1 BPV Failure 4 N/A 0 N/A As is required

1.3 OVERRIDES

Time Override No. Override Title ET Delay Value Ramp T=0 AN:IC35B(14) 1K14 NA N/A ON N/A 1.4 REMOTE FUNCTIONS:

Time Remote No. Remote Title ET Delay Value Ramp As Dir cs 01 V-21-1 'A' CS SUCTION NA 0 .1 0 FROM CST VLV As Dir cs 02 V-21-2 'B' CS SUCTION NA 0 .1 0 FROM CST VLV T=0 pc02 N2 purge N/A N/A Open N/A 2002_ESG 14_newtemplete.doc Page 9 of 35

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MODE SWITCH TO RUN/ PLACE RWCU BED IN SERVICE/MSL DP CELL FAILURE/ ROD PULL/STUCK ROD/CRD PUMP TRIP/HPCI AUTO INITIATION/TORUS LEAK/EOP 3/CS TO TORUS FILL FAILURE/#1 BPV FAILURE/ED, Rev. 0 1.5 EVENT TRIGGER DEFINITIONS:

Trigger Trigger File Trigger Logic Statement Trigger Word Description Number Name 4 N/A zditcbpvjincr .ge. 1 BPV opening jack push button depressed others N/A Manually Activated N/A FLOOR INSTRUCTOR ACTIONS 2 Simulator Pre-brief:

2.1 Individual position assignments BOOTH / FLOOR INSTRUCTOR ACTIONS 3 Conduct pre-scenario activities in accordance with the following procedures:

3.1 If this scenario is used in performance mode: OTI 105 2002_ESG 14_newtemplete.doc Page 10 of 35

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MODE SWITCH TO RUN/ PLACE RWCU BED IN SERVICEIMSL DP CELL FAILURE/ ROD PULL/STUCK ROD/CRD PUMP TRIP/HPCI AUTO INITIATION/TORUS LEAK/EOP 3/CS TO TORUS FILL FAILURE/#1 BPV FAILURE/ED, Rev. 0 4 COMPLETE A TURNOVER SHEET AS FOLLOWS:

=> Day of week and shift

+ Weekday, Dayshift

=> Weather conditions

+ Mild spring day

= Plant power levels 9.5 % Pwr

+ MWt 155

+ MWe 0

+ CORE FLOW 12.8 Mlb/Hr

= Thermal Limit Problems/Power Evolutions

+ It's been 5 days since a reactor scram due to a keyed radio in the Reactor Bldg.

+ Mode Switch in STARTUP.

+ Two IRM recorders are in fast speed.

+ Rods are at Step 25, position 20

+ Final FW Temperatures B030, B031, B032 and B033 are substituted at 80 0 F.

LCOs, date of next surveillance SExisting

+ None

=> STPs in progress or major maintenance

+ Heatup/Cooldown Log has been secured.

+ STP 3.5.1-09 for HPCI operability was performed SAT.

+ STP 3.5.3-06 for RCIC operability was performed SAT.

= Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment

+ F IRM became inoperable at 0300; AR and a Priority 1 Work Request card submitted.

evolutions, problems, etc.

+ At IPOI-2, Step 4.3 (10) the reactivity watch is stationed at 1C05.

+ z50% on #1 Bypass Valve.

+ Mechanical Vacuum Pump is secured.

+ Condenser High Backpressure switches have been removed.

+ Pressure Set is at 940 psig.

+ Turbine Chest Warming in progress up to Step 3.4(2) in 01 693.1.

+ MSIVs were not closed during the shutdown.

2002_ESG 14_newtemplete.doc Page 11 of 35

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MODE SWITCH TO RUN/ PLACE RWCU BED IN SERVICE/MSL DP CELL FAILURE/ ROD PULL/STUCK ROD/CRD PUMP TRIP/HPCI AUTO INITIATION/TORUS LEAK/EOP 3/CS TO TORUS FILL FAILURE/#1 BPV FAILURE/ED, Rev. 0

400# Inspection completed satisfactorily. No Problems.

One extra NSPEO is being held over to place the "B" RWCU F/D in service.

+ Drywell Inerting is in progress up to Step 3.2(12) in 01 573.

"* 'B" SBGT is running.

SStartup Orders

At 5 to 12 % power perform the following:

0 Transfer the Mode Switch to RUN

"* "B" RWCU F/D has been pre-coated and is ready to be returned to service after you take the watch.

Withdraw rods to >70% open on #1 Bypass Valve for I&C. A Bypass Valve position card was replaced and Techs will enter the heater bay to verify position.

I & C Techs are gathering information from the Start up Feed Reg. valve. As a result we are to leave the Start up Feed Reg. Valve in service as long as possible.01-644 states that it should be shifted before 1.4 E6 MIb/hr feed flow.

2002_ESG 14_newtemplete.doc Page 12 of 35

Rev. (

( ES ; 14 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE 0:00 Phone Talker:

Get familiar with plant conditions.

Shift Turnover Provide Shift Turnovers to the SRO and ROs.

Place a RWCU BOP will place "RWCU in service. OSS will direct that the "B" RWCU F/D be placed inservice.

bed in service ° SS should stop control rod withdrawal since operation of RWCU with Event 1 (N) Role-play as the inplant Second control rod withdrawal could both add reactivity.

Assistant to place the "B" RWCU bed in BOP will perform the following:

service. Get in touch with the inplant operator.

When asked perform the following:

Hold the RWCU pump HS in the start position.

Tell the control room operator that you

Increase flow to the RWCU system by dialing up the thumb wheel on are ready to take the ISOLATE switch 1C04.

from OPEN to ISOLATE, and back to OPEN. t When flows are balanced, and the Second announces that he has his Now you are ready to dial up the flow(RTak1.3 bed thumb wheel full open, release the pump HS.

control thumb wheel. (RO Task 11.03)

At the instructor station perform the following AFTER you state that you will now start dialing up the thumb wheel:

Call up drawing window CUl then select "B" bed and select INSERVICE.

2002_ESG_14_new-templete.doc 13

Rev. (

( ES( _14 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Mode switch to Crew will determine that the situation is right to place the MODE Switch to RUN RO will place the MODE switch in run. the RUN position.

Event 2 (N) OSS will direct that the MODE Switch be placed in RUN. (SRO 4.07)

Role Play HP: RO will perform the following:

Operators should call to inform you

Verify all APRMs 5 - 12 % power after the Mode Switch is in RUN.

Verify no APRM DS lights are on.

Role Play chemist: R Annunciators 1C05A, C-8 and 1C05B C-7 are clear.

Operators should call to inform you after the Mode Switch is in RUN.

Place one APRM recorder on each RPS bus on APRM

Transfer Mode Switch to RUN: (RO 93.08)

Place all recorders to APRM

With draw the IRMs (RO 79.01)

Return IRM/APRM recorders to slow speed

Secure the reactivity monitor.

Crew should:

"* Inform HP that radiation areas should be upgraded.

"* Inform chemist that Mode Switch is in RUN.

Rod Withdrawal RO will commence Rod Withdrawal. OSS will perform the following:

Briefing Phone Talker: 9 Review the rod group and their insert/withdraw limit.

Event 3 (R)

Role Play Reactor engineer for pre- a Conduct a Pre-Rod-Movement brief. (SRO 1.06) rod movement briefing.

14 2002_ESG_14_newtemplete.doc 2002_ESG 14-new-templete.doc 14

Rev. ( ( ES. 14 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Rod withdrawal RO will identify a stuck control rod and carry out AOP actions. RO will perform the following lAW IPOI 2:

Withdraw control rods. (RO 72.07)

Perform rod overtravel checks at position 48 for each rod.

Event4 ( NOTE: When the 1C05 operator gets to RO will inform the OSS that Rod 30-39 will not move when a drive signal is ROD 30-39, it will STICK. They may given to it.

attempt to drive the rod again with OSS will direct that the Actions of AOP 255.1 for no rod movement be normal drive pressure. The rod will still performed. (SRO 5.02) (SRO 1.21) not move. The RO will perform the following: (RO 94.02)

Verify that there is no rod block IMPORTANT! NOTE:

Verify power to the RMCS The Booth operator must

Verify the rod attempting to be driven is actually selected.

Watch and Wait for the

Demand a Rod Pattern Log and verify control rod positions.

operator to increase drive

Verify the following CRD parameters are approximately at their normal water pressure. values:

When the operator increases drive

CRD pump flow at FC-1814, is 40 gpm water pressure lAW AOP, then:

Charging water header pressure at PI-1816A is 1500 psig

Drive water pressure at PI-1825A is 260 psid Delete malfunction: rd022239 0 Raise drive pressure to 310-350 psid and attempt to move the rod

Note that the rod will move.

Restore CRD drive water pressure to normal 2002_ESG_14_new.templete.doc 15

Rev. (

( ESd " 14 SCENARIO TIME-LINE I

IIMEINOTES INSTRUCTOR ACTIVITY i EXPECTED STUDENT RESPONSF After the Rod OSS and Crew determine that the failure of the main steam flow DPIS will withdrawal not affect RPV level control.

The SRO will make T.S. call on an inop begins.

steam line DPIS. OSS will perform the following:

Review TS and determine that each MS line has 4 inputs, the loss of Event 5 (I/C ROLE PLAY as 2 nd assistant and call these 2 requires 2 entries into an LCO. (3.3.6.1 Condition A bases).

the control room and tell them that "C" This will be a 24-hour LCO to fix the problem. If not fixed in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TS "C"MS line high MS line DPIS 4436 C and D on rack 1C 3.3.6.1.C & D will require the MS line isolated in the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

flow dp switches 126B are still pegged low, and all others are positive DP. It appears that DPIS Direct an operator to fill out a Work Request Card (SRO 1.01) failed low.

4436C manifold equalizing valve M-1 14(B-2) PDIS4436C-V-35 is open, and the line is warm to the touch.

NOTE: If asked to close the valve wait about 1minute and then report the valve is closed and the reading on DPIS 4436 C and D are about 1/2 of what the others are reading.

ROLE PLAY as I & C When contacted, inform the crew that it will take about 30 minutes to correct the lineup and verify operability of the detectors.

I 2002_ESG_14_new_templete.doc 16

Rev. ( ( ESC ; 14 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE After AOP 255.1 The RO will recognize the "B"CRD pump RO will identify that the B CRD pump tripped and report itto the SS (RO is complete and has tripped. 101.14) rod pull is rod pll isOSS will direct the following: (SRO 1.21) recommenced After AOP 255.1 is complete and the rod following some pull has continued:

Determine the cause of the trip.

rod withdrawals or as directed by ET1

Start the idle CRD pump lAW 01 255 the lead rdllb

Monitor computer points W092 and W093 for bearing temperatures examiner: above 180 F (1C05A-A7)

"B"CRD Trips This will trip the B CRD pump. . Consult TS. (SRO 1.02)

Role Play NSPEO at 1A4:

E Determine that the plant is not is an LCO until one Accumulator overcurrent o pressure lowers to < 940 psig. Then:

Role Play NSPEO in Reactor Bldg.: R 3.1.5 Condition A, 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to declare either 'slow' OR 'inop'.

Report that motor end pump bearing ""When 2 or more accumulators inoperable, then:

is very hot.

3.1.5 Condition B, 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to restore charging water pressure to

Isolate the Reference Leg Backfill as ">940 1.02) AND 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to either declare the rod 'slow' OR 'inop' (SRO directed. Verify RPV level control selected to B Level when isolating A GEMAC and to A Level when isolating B GEMAC.

"* Make reports as necessary for the start of the A CRD pump. (No further complications)

Role play as Rx Engineer IF ASKED:

All rod scram times were within limits during the last time test.

2002_ESG_14_new.templete.doc 17

Rev. (

( ES(.; 14 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Start of a CRD When directed, throttle the discharge RO will perform the following to start the idle CRD pump (RO 10.01) pump valve of the idle CRD pump by

Isolate the Reference Leg Backfill System.

performing the following: (NSPEO)

Call up screen RDI, and close the A Event 7 (N) CRD discharge valve

Check oil level. (NSPEO)

Throttle discharge valve to 1/2 turn open. (NSPEO)

ROLE PLAY as the 2nd assistant,and

Adjust flow controller to 0 gpm in MANUAL.

inform the control room that the discharge valve of the A CRD pump is

throttled to !1 turn open.

Slowly open the Discharge valve. (NSPEO)

Vent the Discharge Filters. (NSPEO)

After the start perform the following: (Next segment may begin before remaining steps can be completed.)

Call up screen RD1, and open the A

Throttle open MO-1 830, Drive Water AP.

CRD discharge valve.

Raise CRD flow to 40 gpm with flow controller in Manual, Then shift to AUTO.

After Accumulator have charged, Adjust Drive AP to 260 psig.

0 Verify CRD Return line MO-1833 is full open.

Start up GEMAC Reference Leg Backfill System. (NSPEO) i 2002_ESG_14_new-templete.doc 18

Rev. (

( ESd _ 14 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE 3 min after the Event 7 (I/C). Crew will recognize that HPCI has inadvertently initiated. (CRITICAL)

CRD pump is The crew will respond to an auto recovered or as initiation of the HPCI system. Crew will respond to an auto initiation of HPCI.

directed by the lead examiner:

Booth Instructor: Be ready to delete the SRO will verify by TWO independent sources that RPV level is satisfactory, next malfunction to prevent RPV level then from reaching 211". Direct that HPCI be secured, per ACP 1410.1, "Conduct of Operations."

Event 8 (I/C) ET2 BOP will secure HPCI with the initiation signal present. Carry out QRC for Tripping HPCI.

Activate EVENT TRIGGER # 2: Verify the following become active:

IMF hp01 IMPORTANT!!! After HPCI starts remove the malfunction so RPV level does not go out high.

Delete Malfunction: hp01 I

2002_ESG_14_new-templete.doc 19

Rev. ( ( ES ;' 14 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When HPCI is After HPCI is tripped Crew will respond to the Torus Low level alarm.

tripped or as The crew will respond to a unisolable directed by the leak from the Torus in the HPCI suction Lead Examiner: SRO will enter EOP 2 and direct the crew to:

piping

"* Control Torus water level between 10.1 and 10.4 ft using only those systems not required for adequate core cooling Event 9 (M) ET3

"* Raise Torus water level with:

"* Core Spray 01151 Activate EVENT TRIGGER # 3: Verify the following become active: "* HPCI01152

"* Maintain Torus water level above 7.1 ft pc14 "* When determined Torus level will not remain above 7.1 ft Increase as required for ED.

"* Enter EOP 1 Role-Play - if sent investigate report the "* ED Torus area has water on the floor and it Manually scram the reactor when Torus water level cannot be maintained is rising. above 7.1 ft. (CRITICAL)

Enter ED when Torus water level cannot be maintained above 7 1 ft (CRITICAL)

Role-Play - if sent to locate the leak report the leak is at the HPCI suction SRO will enter EOP 3 on Area water level above Max Normal Operating piping at the Torus and can not be Water Level Limit and direct the following:

isolated "* Operate available sump pumps to restore and maintain water level below the Max Normal Operating Water Level Limit.

"* Isolate ALL systems discharging into the area except system required to be operated by EOPs or required to suppress a fire.

"* BOP will direct the in-plant operator to fill the Torus with Core Spray.

2002_ESG_14_new-templete.doc 20

Rev. ( ( ES( ' 14 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 10 The Core Spray valve to fill the Torus will BOP direct the in-plant operator to Raise Torus Level with the Core Spray (IC not open System.

Role-Play as the in-plant operator sent When the first valve will not open the BOP will probably tell the OSS and the to open the Core Spray to CST suction in-plant operator should be directed to the other Core Spray system.

valve.

When told to line up to fill the Torus from the CST wait about 2 minutes then call back and report the valve stem is broken and the valve will not open.

Role-Play as the in-plant operator if sent to open the second Core Spray valve and report the valve is opened to the directed number of turns and you hear flow noise.

2002_ESG_14_new-templete.doc 21

Rev. ( ( ESk "14 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE 3Event 11 IfED is anticipated # 1 BPV will fail SRO will direct SEP 307 due to ED anticipation.

IC) closed. BOP will perform SEP 307 NOTE:

Verifies not 2 psig signal When the BPV opening jack push button 0 Verifies MSIV is open is depressed verify event trigger 4 goes e Verifies EHC pump is running active.

9 Determines Condenser is available ET4

Depress and hold the opening jack pushbutton until both BPV #! And #2 are full open.

e BOP must recognize BPV #1 is not opening.

1 BPV will not open. 9 BPV # 2 will open

2 BPV will open. o BOP is also allowed to:

"* Depress the BPV test push button

"* Verify the READY TO SELECT light is on

"* Depress and hold the select BPV-2 pushbutton to open #2 BPV.

e Verify RPV pressure is lowering.

When a Place the simulator in FREEZE. None cooldown of the RPV has been initiated or as directed by the lead examiner, END OF SCENARIO

REVIEW SCENARIO OBJECTIVES WITH THE OPERATORS ***

2002_ESG_14_newjtemplete.doc 22

Rev. (

( ESC .14 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Event 1 BOP 01 261 Rev 46 RWCU placed in service Section 6.3 lAW 01 261.

service a Verify that the F/D has been placed in HOLD.

s Verify RWCU flow of 70 to 85 gpm on FI-2747. Step 1 Step 2 Sat Unsat

Place the running RWCU pump handswitch in the START Step 8 position and hold it there. Step 10 (NOTE)

Increase pump speed to maintain 75 to 85 gpm flow Step 13 through the beds.

When flows are stable 65-85 on "B" RWCU Bed, release Step 15 the RWCU pump handswitch.

2002_ESG_14_newjtemplete.doc 23

Rev. ( ( ES- J14 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Event 2 RO Transfer Mode Switch to RUN:

IPOI-2 Rev71, Prerequisites for taking

"* Verify all APRMs 5%-12%. section 4.3 the MODE switch to run Mode Switch to RUN

Verify no APRM downscale lights are on. Step (10) verified and MOD switch taken to RUN.

"* Verify MSL low-pressure annunciators are reset.

(1C05 A, C-8 and 1C05B, C-7)

"* Place one APRM recorder on each RPS channel to Sat APRM. Unsat

"* Take Mode Switch to RUN record date and time.

"* Place remaining Recorders in APRM on at a time.

"* Withdraw IRM Detectors,

"* Power on

" IRMs selected 01-878.2, Rev 20.

"* DRIVE OUT depressed and held. Section

"* Return recorders to slow speed. 4.1 or

"* Secure Second Licensed operator at 1C05. 0 Section

Inform HPs and chemists that the Mode Switch is in RUN 6.2 and Rad areas should be upgraded.

IPOI-2, Step (11,12) 2002_ESG_14_new-templete.doc 24

Rev. ( ( ES& '14 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Event 3 OSS reviews the rod group and their insert/withdraw limit. IP01-2, Rev 71 Pre Rod Brief conducted

RodConduct aithdawalequivalent Pre-Rod-Movement brief. P&L 6 lAW IP01-2procedure P&L #6 or Rod withdrawal 0 Announce that the crew brief is starting. reference.

"* Conduct the shift briefing.

"* Solicit additional comments from each Sat crewmember. Unsat

"* Announce that the briefing is complete.

RO Control Rod Withdrawal

Withdraw control rods to 10 - 15% power, or 25 % on IPOI-2 performed lAW IPOI-2 second BPV. Step 4.3 (14, 16)

Sat

Perform rod overtravel checks at position 48 for each rod. IPOI-2,P&L 10 Unsat 2002_ESG 14_new-templete.doc 25

Rev. ( ( ES( ; 14 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Event 4 RO AOP 255.1 Rev Control Rod Withdrawal

Verify that there is no rod block 23 performed stopped and No Rod movement with

Verify power to the RMCS Step 1 AOP 255.1 actions normal drive pressure

Verify the rod attempting to be driven is actually selected. Step 2 correctly implemented.

Demand a Rod Pattern Log and verify control rod Step 3 Sat positions. Unsat

Verify the following CRD parameters are approximately at their normal values:

Step5

"* CRD pump flow at FC-1814, is 40 gpm

"* Charging water header pressure at PI-1816A is 1500 psig

"* Drive water pressure at PI-1825A is 260 psid

° Raise drive pressure to 310-350 psid and attempt to move the rod Step 7 o Note that the rod will move.

° Restore CRD drive water pressure to normal (250 to 265)

Step 12 Note: top of page 10 Event 5 SRO M-1 14 (B-2) T.S. correctly identified.

During the power increase, a call will come in stating that two TS 3.3.6.1.A (or Failure of the "C" main DPIS for MS C are still downscale, and all others are normal. D) Sat steam line instrument

Determines that feedwater level control will not be TS table 3.3.6.1-1 Unsat As directed by Lead affected. (1 .c)

Evaluator when power 0 Initiate a Work Request Card.

change is adequate.

26 2002_ESG_14_newjemplete.doc 2002_ESG 14 new-templete.doc 26

Rev. ( ( ESI ,14 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Event 6 RO ARP 1C05A, A-7 CRD pump trip correctly Rev 6 identified and applicable CRD Trip

Determine the cause of the B CRD pump trip by: Step 3.1 ARP 1C05A A-7 actions completed.

"* Monitor alarm "B" CRD PUMP 1 P-209B LO SUCT PRESSURE (1C05A B-7) Sat

"* If necessary send an operator to the 1A4 breaker. Unsat

"* Monitor Computer points W092 and W093 for any bearing temp >180

If due to causes 1.1-1.5 start the A CRD pump per 01 255 The Aux man will call the control room and inform them that Step 3.2 there is a Differential Overcurrent flag on the CRD pump breaker.

SRO will make the following TS determination:

"* Initially they are in NO spec. Technical

"* After the first accumulator pressure falls to <940 psig, they Specification enter:

3.1.5 Condition A, 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to declare either 'slow' or

'inop'

"* After the second accumulator pressure falling to <940 psig, they enter:

3.1.5 Condition B, 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to restore charging water header pressure to >940 psig AND declare it either

'slow' or 'inop' within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

27 2002_ESG_14_newtemplete.doc 2002_E S G- 4new-templete. doe 27

Rev. (

( ES( ,14 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Event 7 RO 01-255, Rev 49 "A" CRD pump returned

"* Isolate the Reference Leg Backfill System. Step 3.2 la to service lAW 01-255.

Start of a CRD Pump (NSPEO) GEMAC Reference Leg

"* Check oil level. (NSPEO) "* Backfill system removed Step lb and returned to service

"* Throttle discharge valve to 1/2 turn open. (NSPEO) "* Step ic lAW 01-880 Section J.

"* Adjust flow controller to 0 gpm in MANUAL. "* Step ld

"* Start A CRD pump. "* Step le Sat

"* Slowly open the Discharge valve. (NSPEO) Unsat

"* Step If

"* Vent the Discharge Filters. (NSPEO) "* Step 2 (Next segment may begin before remaining steps can be completed.)

"* Verify >1200 psig charging water pressure. "* Step 3

"* Raise CRD flow to 40 gpm with flow controller in Manual, "* Step 4 Then shift to AUTO.

"* When FC-1814 properly controlling level shift to AUTO. "* Step 5

"* Verify CRD Return line MO-1 833 is full open. "* Step 6

"* Start up GEMAC Reference Leg Backfill System.

(NSPEO)

"* Step 7

"* Place Hand switch on 1C05 as directed 01 880 Rev 9 Section 5.3 Step 1 Step 4

"* Place Hand switch on 1C05 as directed Section 3.4 Step 1 Step 4 2002_ESG_14_new-templetý.doc 28

Rev. ( ES( " 14 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Event 8 Crew will recognize that HPCI has inadvertently initiated. Crew will recoanize th~at HPCI Initiation (CRITICAL) HPCI has inadvertently initiated. (CRITICAL)

Crew will respond to an auto initiation of the HPCI.

SRO will verify that RPV level is satisfactory, then Sat

Direct that HPCI be secured. Unsat BOP will secure HPCI with the initiation signal present.

Response to HPCI auto OI 152 QRC 2 initiation and trip HPCI.

" Depress and Hold REMOTE TURBINE TRIP pushbutton Rev 0 SV-2259. Immediate Action Sat

"* Verify TURBINE STOP VALVE HV-2201 closed Step 1 Unsat

"* When turbine speed reaches 0 rpm, place 1P-218 AUX OIL PUMP handswitch HS-2256 in the PULL-TO-LOCK Step 1a position.

" Verify TURBINE CONTROL VALVE HV-2200 closed. Step 1b

"* Verify annunciator 1C03C (A-6) is activated

"* Release HS-2259 push button.

Step 1 c Step 1d

"* Verify MO-2312 HPCI INJECT VALVE closed. Step 1e

"* Verify MO-2318 MIN FLOW BYPASS VALVE closed.

Follow-up Action Step 1 Step2 J ____________________________________________ I _____________ I __________________

2002_ESG_14_new_templete.doc 29

Rev. ( ( ES( ' 14 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Crew Will respond to the I orus LOW level alarm. EOP 2 Rev 9 Manually scram the T/L-1 reactor when Torus SRO will enter EOP 2 and direct the BOP to:

Torus water level T/L-3 water level cannot be reduction entry into EOP "* Control Torus water level between 10.1 and 10.4 ft using maintained above 7.1 ft.

only those systems not required for adequate core cooling T/L-4 (CRITICAL) 2,3 and 1

"* Raise Torus water level with: T/L-5

"* Core SprayOI 151 Enter EOP 1 Sat Concurrently Unsat

"* HPCIOI152 T/L-6

"* Maintain Torus water level above 7.1 ft

"* When determined Torus level will not remain above 7.1 ft Enter ED when Torus EOP I Rev 9 water level cannot be

"* Enter EOP 1 RC-2 maintained above 7 1 ft

"* ED RC-3 (CRITICAL)

Manually scram the reactor when Torus water level cannot be maintained above 7.1 ft. (CRITICAL) RC/L-1 RC/P-1 Sat Enter ED when Torus water level cannot be maintained abover Unsat 7.1 ft. (CRITICAL)

Anticipate ED per SRO will enter EOP 3 on Area water level above Max Normal CRS after RC/P-1 (SEP 307) Event 10 Operating Water Level Limit and direct the following:

"* Operate available sump pumps to restore and maintain RC/P-2 water level below the Max Normal Operating Water Level Limit. RC/P-4

" Isolate ALL systems discharging into the area except RC/P-5 system required to be operated by EOPs or required to suppress a fire. EOP 3 Rev 15

" BOP will direct the in-plant operator to fill the Torus with SC/L-1 Core Spray. SC-2 SC-3 SC-4 SC-8 I. _______________ _____________________

30 2002_ESO_14 newtemplete.doc 2002_ESG 14-new-templete.doc 30

Rev. ( ( ES( ' 14 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Event 10 BOP direct the in-plant operator to Raise Torus Level with the 01 151 Rev 36 One Core Spray System Core Spray System. Per 01 151. Section 11.0 Lineup to fill the Torus

"* Verify CST level >10 ft. Step 1 from the CSTs.

"* Verify Torus suction valves Open Step 2

" Monitor Torus Level

Monitr Toru Step4 LevelUnsat____ Sat When the first valve will not open the BOP will probably tell the OSS and the in-plant operator should be directed to the other Core Spray system.

Note: Level will still lower in the Torus.

31 2002_ESG_14_new.templete.doc 2002_ESG 14-new-templete.doc 31

Rev. ( ( ESý , 14 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Event 11 BOP will attempt to perform SEP 307. # 1 BPV will not open SEP 307 Rev 1 #2 BPV is open.

but #2 BPV will open.

"* Verify at least one set of MSIVs open Step 2 Sat

"* Verify an EHC pump is running Step 3 Unsat Step 4

"* Verify Main Condenser is available

"* Depress and hold the "BYPASS VALVE OPENING JACK Step 5 SELECTOR "INCREASE" pushbutton until BPV-1 and 2 are open

"* OPTIONAL Step 6 Optional

"* Depress the BYPASS VALVE TEST "TESTNG" pushbutton

"* Verify the REAY TO SELECT light is on

"* Depress and hold the SELECT BPV-2 pushbutton until BYPASS VALVE OPENING JACK indicate 100% open

"* Verify RPV pressure is decreasing When ED is directed the BOP will place the Handswitch for 4 ASD/SRVs to open and verify that 4 ADS/SRV are open.

SRO will: EPIP 1.1 EAL declaration

Declare an Unusual Event- HUI. Sat Unsat 32 2002_ESG_14_newtemplete.doc 2002_ESG 14-new-templete.doc 32

CREW GRADING ATTACHMENT ESG ILC 14 Rev. 0 Operator Name Position Evaluator Shift Manager Shift Supervisor STA Reactor Operator 1st Assistant B.O.P. 1st Assistant Management Representative/Lead Evaluator Crew Critical Tasks Task Statement SAT UNSAT

1. Crew will recognize that HPCI has inadvertently initiated.

2. Manually scram the reactor when Torus water level cannot be maintained above 7.1 ft.

3. Enter ED when Torus water level cannot be maintained above 7.1 ft.

Individual Competency Identifiers

1. Performing Reactor Mode change to Mode 1

2. Restoring RWCU filter to service

3. Stuck control rod

4. CRD pump trip

5. Respond to HPCI auto initiation.

6. Determination of EOP 2 entry on Torus Low water level

7. Determine Torus level will not be able to be maintained >7.1 ft enter EOP 1 and ED

8. Recognize CST to CST isolation valve failure

9. Recognize SEP 307 Failure

10. EAL deceleration Attach to crew grading worksheet, OTI-105, Attachment 12 when complete.

2002_ESG 14_newtemplete.doc Page 33 of 35

Rev. 0 ESG ILC 14 OSG VALIDATION CHECKLIST Scenario # ESG ILC 14 Rev. 0 1 Verify that if not run from a protected IC that setup information is provided to reproduce the stated initial conditions.

2 __ Verify that all stated objectives are identified in the body of the OSG.

3 _ Verify that turn over sheets are completed, and are in agreement with both the narrative summary and shift turnover information sheet. Turn over sheets are not required for initial license scenarios.

4 _ Verify that if the scenario requires documents to be provided to the crew, that they are filled out as appropriate (i.e., if an STP is used, it is filled out).

5 _ If this is the initial validation or the revision affects ramp times, event triggers, malfunctions, overrides, remote functions or procedure changes could affect the scenario, then validate the scenario for proper response using a crew. It is preferable to use a crew unfamiliar with the scenario whenever possible. Verify the following while running the scenario:

"* The scenario runs as written and all tasks are performed.

"* The stated time line agrees with actual times.

Critical task statements clearly define the expected plant and student response.

They should also be written so that they are achievable as written. If any question exists, it is preferable to have operations management participate in the validation.

"* Anticipated instructor role play/cues are identified

"* Management expectations are captured and re-enforced.

"* Verify administrative documentation requirements (i.e., CMARs / ARs) are identified.

"* Verify reportability requirements (i.e., ESF actuations) are identified.

"* Verify Technical Specification items / LCO declarations are correct.

"* If procedure steps may cause confusion or disagreement between higher-level procedures and Ols/ARPs that operations management is consulted.

6 __ Shutdown scenarios include shutdown risk assessment, time to boil calculations, and shutdown status board information.

SM E/Instructor Date SME/Instructor Date SME/Instructor Date 2002_ESG 14_newtemplete.doc Page 34 of 35

Appendix D Scenario Outline Form ES-D-1 Equivalent Facility: Scenario No.: 2 Op-Test No.:

DAEC (ESG ILC 9) 2002 ILC EXAM Examiners: Operators:

Initial Condition: The plant is at 75% power. 1A3 is being powered from the Standby Transformer and is ready to be swapped to the Startup Transformer. 4 LPRMs are bypassed.

Tu rnover.

Event Maif. Event Event Description No. No. Type*

1 N (BOP) Transfer 1A3 from the Standby Transformer to the Startup Transformer.

2 R (RO) The SOC requests a power increase of 60 MWE.

3 I/C (RO) An LPRM fails upscale. This will require the crew to bypass the N (RO) LPRM and make an operability call on the LPRMs APRMs.

4 I/C An accident in the plant damages PDIS 2245, a HPCI Steam Line (BOP) Flow Instrument. This causes an isolation of the HPCI outboard valves, requiring entry into TS 3.3.6.1, Condition A, and they will also declare HPCI inoperable in accordance with TS 3.5.1, Conditions F.

5 I/C (RO) The "A" Recirc MG develops an oil leak, which will trip the Recirc pump. The pump trip will place the plant in the Buffer region and the crew will follow the guidance provided in AOP 255.2 and STP 3.4.1 02, to monitor the RPV for instabilities.

6 M (ALL) A LOCA begins. The stresses placed on the Recirc system from the trip result in a leak inside the Primary Containment.

M (ALL) When the crew will scram the plant, an open circuit transfer results in the loss of condensate and feed. With HPCI unavailable and RCIC unable to maintain RPV level, ALC and ED are performed.

7 I/C (RO) RCIC flow controller fails to operate in automatic mode. RCIC speed can be manually controlled.

8 I/C Two ADS SRVs fail to open during ED.

BOP

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor C \WINDOWSPWlie sbbE'D)s kop ES D-I OAECSceaioZ2 dce 3

Attachment 6

QF-1030-19 Rev. 0 (FP-T-SAT-30)

NMC~ EVALUATION SCENARIO GUIDE (ESG)

Committed to NcerEclec SITE DAEC TRANFOR ER/AIS PO ERWT FALREIALC EDSR FAI;LURE ESG I 9 RV.2 P* OGRAM: OPERATIONS COURSE ILC : 50007 TOTAL TIME: 2 HOURS DeyeIop'ed biy: 7// Y/O a2 Instructor Date SME/Instructor Reviewed by: ;z

/OP-4tions Manager " Date TApproh*gv Spridso-OertonDt Training Supervisor- Operations Date Retention: Life of policy = lOyrs.

Retention: Life of policy = 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File ilc-9_esgnew-templete.doc Page 1 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

TRASFER 1A3 FORM THE S/B TO S/U TRANSFORMER/RAISE POWER WITH RECIRC/LPRM UPSCALE/INADVERTENT HPCI ISOLATION/SLO/RCIC FAILURE/ALC ED/SRV FAILURE, Rev. 2 Guide Requirements Simulator Training Simulator Booth Instructor Resources: Phone Talker Simulator Floor Instructor

1. STP 3.8.1-04

References:

2. IPO1-3

3. ARP 1C05A, C-4

4.01-878.3

5. ARP 1C03C, A-9

6. TS

7. AOP 672.3

8. IPOI-4

9.01-563

10. STP 3.4.1-02

11. ARP 1 C04A, B-3

12. ARP 1C04A, A-4

13. STP 3.4.2-02-SLO

14. IPOI-5

15. ARP 1C05A, D-1

16. EOP-1

17. EOP-2

18. ALC

19. ED

20. 01-1 50 2 1. ACP 114.5

22. ACP 1402.3

23. AOP 639

24. ARP lCO6B, A-i Performance Mode Evaluation Method:

ilc-9_esgnew-templete.doc Page 2 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

TRASFER 1A3 FORM THE S/B TO S/U TRANSFORMER/RAISE POWER WITH RECIRC/LPRM UPSCALE/INADVERTENT HPCI ISOLATION/SLO/RCIC FAILURE/ALC ED/SRV FAILURE, Rev. 2 SCENARIO

SUMMARY

Current plant operating status.

The plant is at 75% power. 1A3 is being powered from the Standby Transformer and is ready to be swapped to the Startup Transformer. 4 LPRMs are bypassed.

Scenario segments

"* (Event 1-N) Transfer 1A3 from the Standby transformer to the Startup Transformer.

(SRO/BOP)

"* (Event 2-R) The SOC requests a power increase of 60 MWE. (RO)

"* (Event 3-1) An LPRM fails upscale. This will require the crew to bypass the LPRM and make an operability call on the LPRMs for the APRMs. (RO)

"* (Event 4-1) An accident in the plant damages PDIS 2245, a HPCI Steam Line Flow Instrument. This causes an isolation of the HPCI outboard valves, requiring entry into TS 3.3.6.1, Condition A, and they will also declare HPCI inoperable in accordance with TS 3.5.1, Conditions F. (SRO)

"* (Event 5-C) The "A" Recirc MG develops an oil leak, which will trip the Recirc pump. The pump trip will place the plant in the Buffer region and the crew will follow the guidance provided in AOP 255.2 and STP 3.4.1-02, to monitor the RPV for instabilities. (SRO/RO)

"* (Event 6-M) A LOCA begins. The stresses placed on the Recirc system from the trip result in a leak inside the Primary Containment. (ALL)

"* (Event 6-M) When the crew scrams the plant, an open circuit transfer results in the loss of condensate and feed. With HPCI unavailable and RCIC unable to maintain RPV level, ALC and ED are performed. (ALL)

"* (Event 7-1) RCIC flow controller fails to operate in automatic mode. RCIC speed can be manually controlled. (RO)

" (Event 8-C) Two ADS SRVs fail to open during ED. (BOP) ilc-9_esgnew-templete.doc Page 3 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

TRASFER 1A3 FORM THE S/B TO S/U TRANSFORMER/RAISE POWER WITH RECIRC/LPRM UPSCALE/INADVERTENT HPCI ISOLATION/SLO/RCIC FAILURE/ALC ED/SRV FAILURE, Rev. 2 TASKS ASSOCIATED WITH SIMULATOR EXERCISE:

=> Crew Evolutions:

None

= RO (NSOE, ANSOE)

4.02 RCIC - Verify auto initiation.

15.10 Transfer essential bus from startup to standby transformer.

80.01 Bypass an LPRM

93.11 Raise reactor power by 10% with Recirc flow when >35% power.

93.21 Perform a fast power reduction

93.22 Perform immediate operator responses to a reactor scram.

95.14 Perform EOP Defeat 4.

95.21 Perform EOP Defeat 11.

95.26 Perform EOP Defeat 16.

95.44 Perform the actions of RC/L of EOP-1.

95.46 Perform the actions of RC/P of EOP-1.

95.61 Perform the T/T leg of EOP-2

95.63 Perform the DWIT leg of EOP-2

95.64 Perform the DW/P leg of EOP-2

95.74 Perform ALC when injection systems are lined up and available.

95.80 Perform Emergency Depressurization using SRVs.

99.11 Respond to "A" RECIRC MG DRIVE MOTOR TRIP OR OVERLOAD.

=> Shift Supervisor (SS) 1.01 Direct routine crew and control room activities.

1.01.02 Coordinate operator activities.

1.01.03 Ensure control room activities conform to ACP 1410.1, Conduct of Operations.

1.02 Determine operability of Tech Spec required components.

1.02.02 Determine if the instrument, component, or system is operable.

1.02.03 Declare the instrument, component, or system is inoperable, enter the correct LCO, and determine and direct performance of the LCO STP.

ilc-9_esgnew-templete.doc Page 4 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

TRASFER 1A3 FORM THE S/B TO S/U TRANSFORMER/RAISE POWER WITH RECIRC/LPRM UPSCALE/INADVERTENT HPCI ISOLATION/SLO/RCIC FAILURE/ALC ED/SRV FAILURE, Rev.

2

+ 4.10 Direct crew actions to Raise reactor power by 10% with Recirc flow when >35% power.

4.10.01 Direct the control room crew to raise reactor power using Recirc flow.

4.10.02 Monitor the power assent.

+ 4.20 Direct crew actions to perform a fast power reduction form 100 to Z35%

power.

e 4.20.01 Direct operator performance of the fast power reduction actions.

4.21 Direct crew actions to perform the immediate operator responses to a reactor scram.

e 4.21.03 Direct operator performance of IPOI-5 immediate actions.

5.03 Direct Crew Responses to Power/Reactivity Abnormal Change condition.

5.03.04 Direct operator actions to control the malfunctioning system or component.

5.03.05 Confirm the rod pattern, thermal limits and reactor power are within the allowed range.

5.03.06 Direct any STPs that are required for the new plant status.

6.14 Direct Crew response to perform EOP Defeat 4.

6.14.01 Direct operator actions to perform EOP Defeat 4.

6.21 Direct Crew response to perform EOP Defeat 11.

6.21.01 Direct operator actions to perform EOP Defeat 11.

6.26 Direct Crew response to perform EOP Defeat 16.

6.26.01 Direct operator actions to override the containment sample valves Group 3 isolation using EOP Defeat 16.

6.44 Direct crew response for performance of the RC/L leg of EOP-1.

6.44.01 Direct operator actions to maintain RPV level between 170" and 211" using the Table 1 injection systems.

6.46 Direct crew response for performance of the RC/P leg of EOP-1.

e 6.46.04 Direct operator actions to augment RPV pressure control with other steam loads, SRVs, or RWCU.

6.62 Direct Crew response for performance of the TIT leg of EOP-2.

6.62.01 Direct operator actions to place RHR in the Torus cooling mode.

6.63 Direct Crew response for performance of the DW/L leg of EOP-2.

6.63.01 Direct operator actions to maintain drywell temp <1500 using drywell cooling systems and bypassing the main intake coils if necessary.

ilc-9_esgnew-templete.doc Page 5 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

TRASFER 1A3 FORM THE S/B TO S/U TRANSFORMER/RAISE POWER WITH RECIRC/LPRM UPSCALE/INADVERTENT HPCI ISOLATION/SLO/RCIC FAILURE/ALC ED/SRV FAILURE, Rev. 2

6.63.03 Direct operator actions to secure the running Recirc pumps, initiate drywell sprays using RHR pumps not required continuously for adequate core cooling and verify drywell cooling fans have tripped.

+ 6.64 Direct Crew response for performance of the DW/P leg of EOP-2.

6.64.02 Direct operator actions to Initiate Torus sprays using RHR pumps not required continuously for adequate core cooling.

+ 6.74 Direct Crew response for performance of ALC when injection systems are lined up and available.

6.74.01 Direct operator actions to lineup and inject with all available injection systems/subsystems.

6.74.04 Direct operator actions to maximize injection with all available injection systems/subsystems and alternate injection systems until RPV level is rising.

+ 6.78 Direct Crew response for performance Emergency Depressurization.

6.78.03 Confirm Torus level is >4.5 ft.

6.78.04 Direct operator actions to emergency depressurize the RPV.

I ilc-9_esgn ew templete.doc Page 6 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

TRASFER 1A3 FORM THE S/B TO S/U TRANSFORMER/RAISE POWER WITH RECIRC/LPRM UPSCALE/INADVERTENT HPCI ISOLATION/SLO/RCIC FAILURE/ALC ED/SRV FAILURE, Rev. 2 Scenario Objective(s):

1. Transfer 1A3 for the S/B to S/U Transformer

2. Raise power with Recirc.

3. Respond to an LPRM upscale.

4. Respond to an inadvertent HPCI isolation.

5. Respond to A Recirc pump trip.

6. Respond to a LOCA.

7. Take manual control of RCIC.

8. Perform ALC/ED.

9. Respond to an SRV failure to open during an ED.

ilc-9_esgnew-templete.doc Page 7 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

TRASFER 1A3 FORM THE S/B TO S/U TRANSFORMER/RAISE POWER WITH RECIRC/LPRM UPSCALE/INADVERTENT HPCI ISOLATION/SLO/RCIC FAILURE/ALC ED/SRV FAILURE, Rev. 2 SCENARIO OUTLINE:

BOOTH INSTRUCTOR ACTIONS 1 Non-Nuclear Instrumentation System 1.1 SIMULATOR SET UP:

a. Verify the following audits have been completed:

(1) Procedure racks.

(2) EOP Key locker and Defeat packages.

b. Reset to IC 23. (75% MOL)

c. Set up Event Trigger.

d. Go to RUN and reduce power 30 MWE.

e. Place the Recirc and Feedwater controllers in auto.

f. Have 2 yellow stickies ready, one for Relay E41A-K33, and the other for E41A K35. On the Sticky, write "RELAY TRIPPED". Give these to the Evaluator that is following the BOP operator, and inform him that he will place these on the relays at 1C39.

g. Control Panels:

(1) Adjust main generator VARs to 100 lagging.

(2) Verify PPC Group Display 15 on one terminal.

(3) Place clean pull sheet on 1C05.

(4) Pump the Drywell sumps.

h. Restore Malfunction File ILC9.

i. Restore Override File ILC9.

j. Transfer 1A3 to the Standby Transformer.

k. LPRMs: Bypass the following LPRMs AND remove the LPRM points from scan on the PPC or 3D Cases will be incorrect.

(1) 4C-08-09 LPRM A (2) 4A-32-25 APRM D (3) 4B-24-09 APRM A (4) 2A-16-33 APRM E I. Adjust APRM GAFs.

m. Use the SAIC terminal to set thermal limits as is.

n. Verify all points returned to scan. The crew will be deleting a point during this scenario.

o. Tags:

(1) Remove LOR Cycle Tags and Degraded Instruments.

p. Provide the following documentation:

(1) A marked-up list of bypassed LPRMs.

ilc-9_esgnew-templete.doc Page 8 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

TRASFER 1A3 FORM THE S/B TO S/U TRANSFORMER/RAISE POWER WITH RECIRC/LPRM UPSCALE/INADVERTENT HPCI ISOLATION/SLO/RCIC FAILURE/ALC ED/SRV FAILURE, Rev. 2

1.2 MALFUNCTIONS

ILC9 Time Malf Description Delay Ramp ET Value Final SETUP rc03 RCIC FLOW AUTO CONTROLLER FAILS 0 0 1 As is 0.20 INAUTOMATIC As Dir. rr15a RECIRC LOOP RUPT- DESIGN BASES 0 15:00 2 As is 0.15 LOCA AT 100%- LOOP A (NRVI)

As Dir. nm072425a LPRM CHANNEL FAILS- LPRM 24-25-A 0 0 4 As is 1.0 As Dir. egOla MAIN GENERATOR TRIP- PRIMARY 0 0 1 N/A N/A LOCKOUT (286/P)

As Dir. fwO9a REACTOR FEEDWATER PUMP TRIP- 0 0 5 N/A N/A PUMP A As Dir. fwO9b REACTOR FEEDWATER PUMP TRIP- 0 0 5 N/A NIA PUMP B As Dir AN IC03C(29) 1C03C (D-02) ANNUNCIATOR BOX 0 0 6 ON (4HX9W)

As Dir AN IC03C(9) 1C03C (A-09) ANNUNCIATOR BOX 0 0 6 ON (4HX9W)

As Dir AN IC03C(17) 1C03C (B-08) ANNUNCIATOR BOX 0 0 6 ON I______

_______(4HX9W) ilc-9_esgn ew-templete.doc Page 9 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

TRASFER 1A3 FORM THE S/B TO S/U TRANSFORMER/RAISE POWER WITH RECIRC/LPRM UPSCALE/INADVERTENT HPCI ISOLATION/SLO/RCIC FAILURE/ALC ED/SRV FAILURE, Rev. 2

1.3 OVERRIDES

ILC9 Time Override Description Delay Ramp ET Value Final SETUP Z DI AD HS-4405 ADS PSV4405,C MSL,1140 PSI 0 0 NIA AUTO AUTO (AUTO,OPEN)

SETUP Z DI AD HS-4400 ADS PSV4400,A MSL,1130 PSI 0 0 NIA AUTO AUTO (AUTO,OPEN)

SETUP Z DI RR HS-4665A MG SET LUB OIL 1P-202A 0 0 7 AUTO STOPIRST SETUP Z DI RR HS-4666A MG SET LUB OIL 1P-202B 0 0 7 AUTO STOP/RST SETUP Z LO RR HS-4666A(1) MG SET LUBE OIL PUMP 1P-202B 0 0 7 AS IS OFF (GREEN)

SETUP Z LO RR HS-4666A(2) MG SET LUBE OIL PUMP 1P-202B 0 0 7 AS IS OFF (AMBER)

SETUP Z LO RR HS-4666A(3) MG SET LUBE OIL PUMP 1P-202B 0 0 7 AS IS ON (RED)

SETUP Z LO RR HS-4667A(1) MG SET LUBE OIL PUMP,1P-202C 0 0 7 AS IS OFF (GREEN)

SETUP Z LO RR HS-4667A(2) MG SET LUBE OIL PUMPP-202C 0 0 7 AS IS OFF (AMBER)

SETUP Z LO RR HS-4667A(3) MG SET LUBE OIL PUMP,1P-202C 0 0 7 AS IS ON (RED)

SETUP Z LO RR HS-4665A(2) MG SET LUBE OIL PUMP 1P-202A 0 0 7 AS IS OFF (AMBER)

SETUP Z DI RR HS-4667A MG SET LUB OIL 1P-202C 0 0 7 AUTO STOP/RST SETUP Z DI HP HS-2239 STEAM LINE ISOL MOV-2239 0 0 6 AUTO CLOSE SETUP Z DI HP HS-2322 PUMP SUCTION MOV-2322 (SP) 0 0 6 AUTO CLOSE SETUP Z DI HP HS-2242 HP HS-2242 MANUAL ISOLATION 0 0 6 TRANSI ON

/OFF SETUP Z LO HP HS-2240 AUTO ISOLATION SIGNAL - (A) 0 0 6 AS IS ON SETUP Z LO MS PCIS-LBIHPCI PCIS GROUP 6 B LOGIC ISOLATION 0 0 6 AS IS ON SIGNAL HPCI SETUP Z LO HP XFV-2246C(1) HPCI STEAM SUPPLY PRESS XFV 0 0 6 AS IS ON LITES (GREEN)

SETUP Z LO HP XFV-2246C(2) HPCI STEAM SUPPLY PRESS XFV 0 0 6 AS IS OFF LITES (RED) ilc-9_esgnew-templete.doc Page 10 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

TRASFER 1A3 FORM THE S/B TO S/U TRANSFORMER/RAISE POWER WITH RECIRC/LPRM UPSCALE/INADVERTENT HPCI ISOLATION/SLO/RCIC FAILURE/ALC ED/SRV FAILURE, Rev. 2 1.4 REMOTE FUNCTIONS:

Time Remote Title Value During the MG rrO5a 'A' RECIRC SCOOPE TUBE LOCK UP(LOCK,UNLOCK) LOCK set oil leak Event 6 1.5 EVENT TRIGGER DEFINITIONS:

Trigger Trigger File Trigger Logic Statement Trigger Word Description Number Name 1 N/A rpdislshutdown(1) .ge. 1 Mode Switch to S/D 2 N/A Manually Activated N/A 4 N/A Manually Activated N/A 5 N/A Manually Activated N/A 6 N/A Manually Activated N/A 7 N/A Manually Activated N/A ilc-9_esgn ew templete.doc Page 11 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

TRASFER 1A3 FORM THE S/B TO S/U TRANSFORMER/RAISE POWER WITH RECIRC/LPRM UPSCALE/INADVERTENT HPCI ISOLATION/SLO/RCIC FAILURE/ALC ED/SRV FAILURE, Rev. 2 FLOOR INSTRUCTOR ACTIONS 2 Simulator Pre-brief:

2.1 Individual position assignments BOOTH / FLOOR INSTRUCTOR ACTIONS 2 Conduct pre-scenario activities in accordance with the following procedures:

3.1 If this scenario is used in performance mode: OTI 105 ilc-9_esg_newtemplete. d oc Page 12 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

TRASFER 1A3 FORM THE S/B TO S/U TRANSFORMER/RAISE POWER WITH RECIRC/LPRM UPSCALE/INADVERTENT HPCI ISOLATION/SLO/RCIC FAILURE/ALC ED/SRV FAILURE, Rev. 2 4 COMPLETE A TURNOVER SHEET AS FOLLOWS:

= Day of week and shift

Weekday, 19-07 shift

= Weather conditions

Mild spring weather S(Plant power levels)

+ 70 % Power

1370 MWT

+ 440 MWE

CORE FLOW 36 Mlb/Hr.

Limit Problems/Power Evolutions

None SExisting LCOs, date of next surveillance

+ T.S. 3.8.1.A. STP 3.8.1-01 is due in 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

in progress or major maintenance

The Standby Transformer is powering 1A3.

Maintain 1X4 and Both SBDGs operable.

Electricians completed repair on 1A302 breaker.

1A302 has been verified operable and the Gap is sat.

The system Engineer requested that we wait until after turn over to transfer 1A3 to the Startup Transformer and is standing by outside 1A3.

to be taken out of or SEquipment returned to service this shift/maintenance on major plant equipment

LPRM 4C-08-09, in LPRM A cabinet was reading low. REs recommended bypassing it until a OD-1 can be run tomorrow. Now a total of 4 LPRMs bypassed.

= Comments, evolutions, problems, etc.

+ No extra personnel on shift.

Helpers working until midnight on plant cleanup.

Have been load following at night lately.

Place 1A3 on the Startup Transformer following Shift turnover.

ilc-9_esgnew-templete.doc Page 13 of 31

Rev. C ( ES(Q 9 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Shift Turnover Provide Shift Turnovers to the SRO and

Get familiar with plant conditions.

ROs. SRO will provide beginning of shift brief to coordinate the tasks that were identified on the shift turnover. (SRO 1.01)

Transfer 1A3 to Role Play System Engineer if needed. You SRO direct the BOP to Transfer 1A3 from the Standby to Startup the Startup are standing by for the Transfer of 1A3 to Transformer per 01 304.2 Transformer. the Startup Transformer. BOP Will Transfer 1A3 from the Standby to Startup Transformer per 01 Event 1 304.2 Rev 43 Section 7.4 (After the SRO will direct that the RO raise reactor power with Recirc at a rate of 3-5 Startup MWE/min, in accordance with IPOI 3.

Transformer is Role Play System Dispatcher: SRO 4.10 supplying 1A3 or as directed ° Raise 60 MWE and maintain KVARS RO will raise reactor power with Recirc by performing the following:

by the Lead steady. There is a need for Grid power,

Raise Power with Recirc.

Examiner. so raise power at a rate of 5 MWE/min.

Event 2 ° Maintain KVAR loading.

Monitor total core power by APRMs, Steam Flow and Feed Flow.

RO 93.11 Load Increase. The SRO will monitor the power increase.

SRO 4.10 14 ilc-9_esgnewjemplete.doc ilc-9_esg_new_templete. doe 14

Rev. C

(

SCENARIO TIME-LINE ES( C9 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When power When 1A3 transfer is complete. RO will respond to ARP 1C05A (C-4), LPRM Upscale, and possibly 1C05A change is (0-2) APRM UPSCALE:

complete or as directed by the ET 4

Determine the location of the failed LPRM.

Lead Examiner. Activate Event Trigger # 4 and verify the

Run an "Official Case" to verify that no thermal limits have been following malfunction becomes active: exceeded.

LPRM Upscale nm072425a 0 Using Appendix 1 of 01 878.3, determine where the LPRM is and if the 100% Severity loss of the LPRM affects APRM operability.

Event 3 0 Ramp

Will determine that with 3A-24-25 inoperable, the "C"APRM is still operable.

Role play as the RE and inform the crew . Will obtain SRO permission to bypass the LPRM.

that they should bypass the LPRM and that Task 80.01 you will check it when you run the OD-1 tomorrow. SRO will direct that LPRM 24-25 be bypassed in accordance with 01 878.3.

RO and BOP will bypass the LPRM by performing the following:

"* Bypass affected APRMs.

"* Bypass the affected LPRM and observe the 'white' bypass light on.

"* Notify the RE of the bypassed LPRM.

"* Delete computer point from scan per 01-831.4.

"* Ifnecessary, adjust the GAFs.

"* Unbypass the affected APRMs.

"* Write a Work Request Card on the bypassed LPRM.

SRO checks TS 3.3.1.1, Tbl. 1, Function 2b, and bases B.3.3.1.1 page B.3.3-9 and determines that the plant is not in violation of TS.

ilc-9_esgnew_templete.doc 15

Rev.(

( S C9 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE After LPRM is BOP will respond to the alarms on the HPCI panel and investigate.

bypassed or as directed ET 6

Verify HPCI isolation.

by the Lead Activate Event Trigger # 6. 0 Determine the cause of the isolation.

Examiner. Role play plant Helper Forman: 0 Determine Primary Containment Isolation Valve Instrumentation is HPCI A new Helper was moving the floor plug inoperable and perform the following:

crane on the Rx Bldg. 1st Floor South

Enter TS 3.3.6.1 Condition A, from table 1 Function 3A, and realize that Event 4 and he swung the hook into the they have 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to place the function in trip, and that it is already instrument rack and damaged a gage, there.

PDIS 2245. There was a small water

Determine that HPCI is inoperable with the steam line closed, and enter leak from the gauge but it has stopped TS 3.5.1 Condition F, a 14 day LCO and verify RCIC operable, by now. administrative means, immediately.

Role Play NSPEO and confirm the damage (SRO 1.02) as necessary.

Role play with RO verifying the relays in the back panel, and cue him that:

E41A K33 and E41A E35 are tripped.

16 ilc-9_esgnew..templete.doc ilc-9_esg_new_templete.doc 16

Rev. ( ES( C 9 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE After T.S. Role Play NSPEO RO will take the call and report to the Crew that there is a leak on the "A" determination A line going to the fluid coupler is Recirc M-G set on a line going to the Fluid Coupler.

or as directed cracked approximately 1/2 of the way by the Lead "* Crew will discuss the need to:

around and leaking badly. The leak can Examiner. not be isolated. "* Rapidly remove the M-G set.

SLO "* Perform "A" Recirc MG Fluid drive oil high temp The crew will do one of two things.

ARP, 1C04A (B-3).

Event 5 "* Remove the A Recirc MG set from service, and leave the B operating "* Crew may perform IPOI 4 fast power reduction to remove the MG where it is, set. Note that this may drive them into the buffer or exclusion zone.

(RO 93.21, SRO 4.20)

OR

" After the trip of the MG set, the crew will:

"* Perform a fast power reduction lAW IPOI 4 to remove the A unit. "* SRO will voice that if any undamped oscillations on the APRM occur, that a manual reactor scram be inserted.

NO MATTER which path the crew elects to take, wait 3 min from the report of an oil " Perform "A" Recirc MG Drive Motor Trip or overload ARP 1 C04A, puddle, then simulate the loss of lube oil by (A-4). (RO 99.11) performing the following: "* Verify MG set motor and field breakers are OPEN.

ET 7 "* Verify open the discharge bypass and close the discharge valve Activate Event Trigger # 7: This will turn off for 5 minutes.

both MG set lube oil pumps. "* Determine the cause of the trip.

"* Immediately perform STP 3.4.1-02, SLO procedure.

"* Check for entry into exclusion or buffer regions of power to flow map.

"* Exit via the STP guidance, (prepare to insert rods to lower the load line to less than 75%).

If they reduced power via IPOI 4, they may be in the Exclusion Zone. IF they are they will insert rods to lower load line to <75%.

& I 17 ilc-9_esgnew.jemplete.doc ilc-9_esg~new_templete.doc 17

Rev. 1%

( ES( C9 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE

-r When the crew Start the LOCA by performing the following: Crew will:

begins SLO STP ET 2

When the Drywell approaches 2 psig they will manually scram the Eventl6 reactor.

Activate Event Trigger # 2: verify that the following malfunction becomes active: SRO will direct and the ROs will perform the following:

LOCA rrl 5a "* IPOI-5 Immediate actions. (RO 93.22) (SRO 4.21)

This will start a leak that will go to "* EOP-1. (RO 95.44 & 46) (SRO 6.44 & 6.46) 15% Severity over a 15:00 Ramp. "* Maintain level 170 to 211," using:

CRD, RCIC, SBLC When the Verify Event Trigger # I becomes active.

reactor is "* Override CV-4371A. (RO 95.21) (SRO 6.21) scrammed, Increase rrl 5a as necessary to force the " Perform EOP-2. (RO 95.63 & 64) (SRO 6.62) crew to ED

Maximize Torus cooling when >95 0F. (RO 95.61) (SRO 6.62)

Install Defeat 4 and bypass the main intake coils.

(RO 95.14) (SRO 6.14 & 6.63)

Spray the Torus. (RO 95.64) (SRO 6.64)

After the Generator lock out, insert the following malfunctions to keep the Feed "* Spray the Drywell. (RO 95.63)(SRO 6.63) water pumps from restarting: "* Install Defeat 16 and restore DW sampling. (RO 95.26)

Activate Event Trigger # 5 and verify that (SRO 6.26) the following malfunctions become active: Crew will determine that there was an OPEN transfer of the non-essential FW09A and B busses. The SRO will direct and the ROs will perform the following:

"* Attempt to restore Condensate and Feed.

When the RO calls and asks you to throttle "* Send an operator to throttle the Condensate pump discharge valve so the Condensate pump discharge valve, do that the stem is 1 to 1 inch open.

not give them the Condensate system "* Start the pump and have the inplant operator throttle open the until after the ED. discharge valve.

"* Attempt to start the Feed water pump.

18 ilc-9_esg..new..templete.doc ilc-9_esg_ýnew_templete.doc 18

Rev. ( ( ES( .C 9 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE RCIC Increase rrl5a as necessary to force the EOP I Actions:

crew to ED In an attempt to restore RPV level the SRO will direct and the RO will Event 7 perform:

Line up and inject RCIC into the RPV for level control.

RO will identify that RCIC is not producing rated flow with the flow controller in AUTO. (RO 4.02) 0 Shift to MANUAL and adjust speed to maximize RCIC flow.

As level lowers:

"* Start both CRD pumps and maximize flow.

"* Start SBLC and inject into the RPV.

Entry into ALC If called as the NSPEO to throttle the SRO will determine that RPV level cannot be maintained, and enter ALC.

Condensate pump discharge valve, WAIT Once in ALC the SRO will direct and the ROs will perform the following:

Event 8 Event

!until after the ED, 8*

then: Lock out ADS.

Use remote functions FWO5 Close for the Bse pumpte aunctond F Close 5 for the forA B pump and FW06 Close Athe pump Line up injection sources per ALC. (RO 95.74) (SRO 6.74)

This will 'close the condensate discharge.

ED after 15", but before -25 inches (Critical). (RO 95.80) (SRO 6.78)

AFTER the ED, call and report that the Open4ADSSRVs valve is closed to 1 and % inch open, and that the pump is ready for a start.

Identify PSV 4405 and PSV 4400 fail to open, and open both LLS SRVs (Critical).

Maximize injection to restore RPV level to greater than 15 inches.

(SRO 6.74) 19 ilc-9_esgjiew.templete.doc ilc-9_esg~new_templete.doc 19

Rev. (

( ES( 39 SCENARIO TIME-LINE TIMEINOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE RPV/F None Crew will monitor for entry into SAT Curve. If entry into the sat curve, then perform the following actions:

"° SRO will:

"* Inform the crew that they are in the sat curve.

"* Tell them that the only level instruments that they are to use are the

'Flood ups' and the 'GEMACs', and to increase the monitoring of those level instruments.

"* Tell them that they must subtract 23 inches from the current level indications on the usable instruments, and that the corrected level is the level that all decisions will be based off of.

END When RPV level and/or pressure are stable, None place simulator in FREEZE.

- - END OF SCENARIO ***

- REVIEW SCENARIO OBJECTIVES WITH THE OPERATORS ***

20 ilc-9_esg..newjemplete.doc ilc-9_esg_new_templete.doc 20

Rev. ( ( ES( ,&9 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE Transfer 1A3 to SRO direct the BOP to Transfer 1A3 from the Standby to Startup T.S. 3.8.1 Condition A Startup Transformer the Startup Transformer per 01 304.2 AND Supplying 1A3 Transformer, T.S. 3.8.2 Condition B

SRO should note T.S. conditions for the Transfer. While Bus 1A3 Transfer Event I breaker mode selector Sat switch is in MANUAL Unsat BOP Will Transfer 1A3 from the Standby to Startup Transformer 01304.2 Rev 43 per 01 304.2 Rev 43 Section 7.4 Section 7.4

Identify there are T.S. considerations for this transfer. Step

Bus Transfer switch to manual 1 Sync scope switch to on for 1A302 2

3

Sync Scope near 12 o'clock and phase lights off 4

Incoming volts within 8 volts of running volts 5

Select phase 1 on both S/U and S/B amp meters 6 7

Close in Breaker 1A302 8

Check for equal amperage 9

Open Breaker 1A301 10 11 12

Sync switch to OFF

Check each phase on Startup Transformer for proper amps

Check each phase voltage about 4160 VAC

Place Bus Transfer breaker mode selector switch to AUTO

Inform SRO transfer is complete.

21 ilc-9_esgnew.templete.doc ilc-9_esg~new-templete. doe 21

Rev. ( ( ES( Z9 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE Raising load RO IPOI-3, Rev. 55 Section Power increased with Prior to raising power, the crew may adjust the APRM GAFs. 4.0, Recirc.

Event 2 (The criteria for adjusting the APRMs is a + or - 2% power) Step (14) Sat___

Applicable from Section Unsat 3.0 0 Maintain KVAR loading. Step (5)

Step (6)

Monitor total core power by APRMs, Steam Flow and Feed Flow.

Monitor local power with the LPRMs on the 4-rod display.

22 ic-9_esgnewjemplete.doc ilc-9_esg-new-templete.doc 22

Rev. 1i ( ES( 39 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE LPRM Upscale RO ARP IC00A, C-4, Rev. 5 LPRM 3A-24-25 Step 3.2 identified as upscale.

Determine which LPRM is upscale. (3A-24-25)

Step 3.2.a Event 3 Sat

Confirm the upscale condition by selecting a nearby control Step 3.2.b Unsat rod.

Monitor 4-Rod display LPRM power. Step 3.2.c

Notify RE and comply with the TRM for LHGR.

Step 3.3

Run an Official 3D Case to verify LPRM is not listed as failed and to verify thermal limits are not being violated.

Step 3.4 & 5

Verify that LPRM can be bypassed without making the C APRM inop. Step 3.7 01-878.3, Rev 21 Step (21)

LPRM Upscale LPRM 3A-24-25 Step (4) Bypassed.

Bypassing an With SRO permission, bypass the LPRM per 01-878.3.

LPRM Step (5)

Bypass C & D APRMs. Step (7) Sat

Take the mode selector on the LPRM card to BY. Step (8) Unsat

Observe 1C37 white bypassed light is on. Step (9)

Notify RE that LPRM is bypassed. Step (10)

If necessary, adjust APRM gains. Step (11)

Unbypass APRMs.

Delete the associated computer point from scan per 01 831.4.

Initiate a work request card.

23 ilc-9_esg..new..templete.doc ilc-9 esg~new-templete .doe 23

Rev. ( ES( - 9 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE HPCI BOP ARP IC03C, A-9, Rev. 6 Tech Spec

"* Verify that MO-2239 is closed. Step 3.1 determination Step 3.3 correct.

Event 4 0 Verify HS-2240 Amber light is on.

"* Determine the cause of the isolation. Step 3.4 Sat

"* A helper will call the control room and inform them that a Unsat lifting device slammed into the PDIS and broke it.

"* They will go to ARP 1C03C B-8 and look at Relay E41A K33, High Steam Line DP, tripped and from ARP 1C03C, Evaluator Note:

A-9, HPCI isolation, look at Relay E41A-K35, tripped. If operators are sent

"* Depending on when the CUE comes from the Driver, the to look at relays Crew may look at the HPCI steam leak detection E41A-K33 and temperatures to see ifthere is a steam leak E41A-K35

Initiate a Work Request Card. after they locate the

Notify SRO and determine TS: Step 4.1 relays tell them the

"* TS section 3.5.1 Condition F, 14 day and verify RCIC Step 4.2 relays are tripped.

operable, by administrative means, immediately. (for the TS Section 3.5.1 HPCI inoperable, the SRO may pull out STP 3.5.1-08, Condition F.

this documents that RCIC is operable)

"* TS section 3.3.6.1 Condition A 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Note that the problem is the broken instrument, the valve did its job, and therefore entry into 3.6.1.3 is not TS Section 3.3.6.1 necessary, only a log entry for HPCI Steam Flow Condition A.

DPIS inoperable and HPCI Steam Line Low Pressure inoperable 1 Initiate an AR.

24 ic.9_esg.newjemplete.doc ilc-9_esg~new-templete.doc 24

Rev. 1( C ES( " 9 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE SLO RO ARP IC04A, C-6, Rev. 3 ARP actions for

"* (Possible, as there are no alarms alarming) Reduce A Recirc Steps 3.8.a, b& c Recirc pump trip pump speed to minimum and manually trip Breaker 1A104, in completed.

Event 5 anticipation of high bearing and or oil temps.

Sat ARP IC04A, A-4, Rev. Unsat

"* Check for entry into exclusion or buffer regions of power to 15 flow map. Consult AOP 255.2 for guidance. - Step 3.2 If the crew plots themselves in the buffer region, their guidance is Step 3.3 to, run a SOL case on the PPC, and monitor for Step 3.4 instabilities. Step 3.5

Verify 1A104 and A MG field breakers are open. Step 3.6

Stabilize RPV water level. Step 3.7

Secure A Recirc pump. Step 3.8

"* Verify Disch Bypass is open. Step 3.9

"* Close pump Disch valve.

"* Re-open pump Disch valve after 5 minutes.

If desired to limit the cooldown of the idle loop, the crew may close CV-1804A, Mini Purge Isolation valve

Determine the cause of the trip.

There is nothing in the procedure that tells the operators to secure the oil pumps, however it is a good operations practice, and should be done.

Verify Supply fan 1V-SF-12 in AUTO or START.

25 ilc-9_esg..jiew..templete.doc ilc-9_esg_ýnew_templete.doc 25

Rev. . ( ES( 39 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE SLO continued BOP Step 3.10 SLO STPs are Start STP 3.4.1-02, SLO procedure. STP 3.4.1-02 Rev.4 directed.

Step 7.1.1 Sat___

Unsat 0 Determine stability on Power to Flow Map. Step 7.1.2

(If fast power reduction performed) Determine that entry into the Exclusion Zone has been made.

Step 7.1.3

Exit the region by inserting control rods

(If no fast power reduction) Monitor the plant for undamped Step 3.11 oscillations.

Start STP 3.4.2-03 Daily jet pump operability for-SLO.

TS Section 3.4

Comply with TS.

Enter 3.4.1, Condition D, requires that Recirc be in compliance with the LCO conditions in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (i.e. STP 3.4.1-02).

LOCA RO IPOI-5, Rev. 34 IPOI 5 immediate Reactor Scram

Initiate a backup manual scram Section 3.2 actions complete.

Place the Mode Switch in Shutdown. Step (1) Sat___

Event 6 0 Verify flux decreasing. Step (2) Unsat

Initiate a level setback by pushing the "Manual level setback Step (3) to 175" on 1C05. Step (4)

Verify Recirc is run back to minimum. Step (5)

Verify all control rods fully inserted. Step (6)

Insert all IRMs and SRMs. Step (7) 26 ilc-9_esg..newjemp1ete.doc ilc-9_esg-new-templete.doc 26

Rev. 1( ( ES( -9 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE LOCA SRO/RO EOP-1, Rev. 9 RPV level >170 EOP 1 Recognize EOP-1 entry on RPV low level. Step RC-3 inches

Verify Group 2, 3, & 4 isolation.

Step RC/P-1 Sat Event 6

Verify CS, LPCI, & SBDG initiations.

Step RC/P-2 (cont.

Override CV-4371A.

Verify LLS stabilizes RPV pressure. Step RC/L-1 Restore RPV level 170-211 inches with Table 1 systems:

"* Both CRD pumps

"* RCIC Step RC/L-1 with Table 2 systems:

Restore RPV level 170-211 inches

SBLC

Transition to ALC/ED. Step RC/L-1 RCIC RO 01-150, Rev. 43 RCIC injecting at Identify that RCIC is not producing rated flow with the flow Section 10.1 rated flow.

Event 7 controller in AUTO. Step 2.a

Place FIC-2509 in BAL. Sat NOTE: due to the situation, the next step may be bypassed, Unsat and the speed of the RCIC turbine will be controlled by step (3) Step 2.b

Use the manual adjust knob to match the red pointer with the controller setpoint. Step 2.c

Shift to MAN. Step 3

Adjust speed to maximize RCIC flow. I 27 ilc-9_esgnew.templete.doc ilc-9_esg~new-templete.doc 27

Rev. 1( ( ES( -9 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE LOCA SRO/BOP EOP-2, Rev. 8 RPV level >170 EOP-2 0 Spray the Torus. PC/P-4 inches

"* Secure B Recirc pump and spray the Drywell when PC/P-6 permitted. Verify Drywell fans shutdown. Sat Unsat____

"* Maximize Drywell cooling by installing Defeat 4 and DW/T-3 bypassing main intake coils.

"* Maintain DW air Temp <280°F with Drywell sprays, if DW/IT-5 necessary.

Maximize Torus cooling when >950 F. T/T-3

Maintain Torus level < 13.5 ft. T/L-1

Install Defeat 16 and monitor DW H2 & 02. PCH-1 28 ilc-9_esgnewjemplete.doc ilc-9_esg-new-templetexdoc 28

Rev. 1( ( ES( -9 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE LOCA SRO/BOP ALC, Rev. 2 ED Directed and one ALC/ED ° Lock out ADS. ALC-1 SRV Hand switch in open level <-25 RPV beforeinches

Line up Table 1A and 2A systems for injection (i.e. CRD, Step ALC-2 Step ALC-5 l )

Event 8 SBLC, Core, RHR, and Condensate pumps). (critical)

Wait until RPV level drops to 15". Step ALC-6 Sat

Before level reaches -25": Step ALC-8 Unsat

Emergency Depressurize. Step ALC-10 Emergency depressurize (critical)

"* Verify Torus level > 4.5 ft. ED, Rev. 2 BOP Step ED-6

"* Open 4 ADS SRVs. Step ED-7and 4400 failed to

" Determine that 1 Core Spray and 1 other ECCS pump are Step ED-8 open, and open both available. LLS SRVs. (critical)

Step ALC-11I Sat___

Unsat "Injectinto the RPV to restore and maintain level greater than Step ALC-1 StepALC_12______

+ 15" and exit ALC.

SRO Caution #1 EOP I Sat Curve entry identified if entered.

" Crew will be aware that they are, or may be, in the SAT curve and increase monitoring of RPV level.

Sat

" The only level instruments that they are to use are the 'Flood Unsat ups' and the 'GEMACs', and they are to monitoring for any oscillations.

" They must subtract 23 inches from the current level indications on the usable instruments, and that the corrected level is the level that all decisions will be based off of.

EAL FA-1 EAL Board 29 ilc-9_esg...newtemplete.doc ilc-9_esg~new_ýtemplete.doc 29

CREW GRADING ATTACHMENT ESG ILC 9 Rev. 1 Operator Name Position Evaluator Shift Manager Shift Supervisor STA Reactor Operator 1st Assistant B.O.P. 1st Assistant Management Representative/Lead Evaluator Crew Critical Tasks Task Statement SAT UNSAT

1. ED Directed and one SRV open before RPV level < -25 inches

2. Identify PSV 4405 and 4400 failed to open, and open both LLS SRVs 3.

4.

5.

6.

Individual Competency Identifiers 1.

2.

3.

Attach to crew grading worksheet, OTI-105, Attachment 12 when complete.

ilc-9_esgnewjtemplete.doc Page 30 of 31

Rev. I ESG ILC 9 OSG VALIDATION CHECKLIST Scenario # ESG ILC 9 Rev. 1 1 Verify that if not run from a protected IC that setup information is provided to reproduce the stated initial conditions.

2 Verify that all stated objectives are identified in the body of the OSG.

3 Verify that turn over sheets are completed, and are in agreement with both the narrative summary and shift turnover information sheet. Turn over sheets are not required for initial license scenarios.

4 Verify that if the scenario requires documents to be provided to the crew, that they are filled out as appropriate (i.e., if an STP is used, it is filled out).

5 If this is the initial validation or the revision affects ramp times, event triggers, malfunctions, overrides, remote functions or procedure changes could affect the scenario, then validate the scenario for proper response using a crew. It is preferable to use a crew unfamiliar with the scenario whenever possible. Verify the following while running the scenario:

"* The scenario runs as written and all tasks are performed.

"* The stated time line agrees with actual times.

" Critical task statements clearly define the expected plant and student response.

They should also be written so that they are achievable as written. If any question exists, it is preferable to have operations management participate in the validation.

Anticipated instructor role play/cues are identified

"* Management expectations are captured and re-enforced.

"* Verify administrative documentation requirements (i.e., CMARs / ARs) are identified.

"* Verify reportability requirements (i.e., ESF actuations) are identified.

"* Verify Technical Specification items / LCO declarations are correct.

"* If procedure steps may cause confusion or disagreement between higher-level procedures and OIsIARPs that operations management is consulted.

6 Shutdown scenarios include shutdown risk assessment, time to boil calculations, and shutdown status board information.

SME/Instructor Date SM Eli nstructor Date SME/Instructor Date I

ilc-9_esgnew-templete.doc Page 31 of 31

-Appendix D -- Scenario Outline Form ES-D-1 Equivalent Facility: Scenario No.: 3 Op-Test No.:

DAEC (ESG ILC 7) 2002 ILC EXAM Examiners: Operators:

Initial Condition: The plant is operating at 1420 MWT in preparation for MSIV testing.

Turnover:

Event Malf. Event Event Description No. No. _Type* -~

1 I/C (RO) Shortly after the crew takes control of the plant, the "C" APRM will slowly fail upscale resulting in a half scram.

2 N (BOP) Operators perform MSIV Trip Closure Time Check, STP 3.6.1.3-03.

3 I/C "A" Outboard MSIV will not indicate full closed. The crew should (BOP) declare CV-4413 inoperable and comply with Tech Spec 3.6.1.3.A, which requires the inboard MSIV to be closed and deactivated in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

4 I/C (RO) While the OSS is researching the MSIV LCO, the B Feed Reg Valve controller begins to fail closed. Operators will take manual control and restore RPV level.

5 I/C Air in-leakage into the Main Condenser results in Main Condenser

( BOP) High Backpressure 6 R (RO) In response to the condenser backpressure, the crew will reduce reactor power in accordance with IPOI 4 fast power reduction.

7 I/C The air in-leakage will increase to the point where a manual reactor (SRO) scram should be performed.

8 M (ALL) Control Rods fail to insert. Operators perform EOP ATWS. Control rods may be manually driven for a short while, but other RIPs are unsuccessful until the scram air header is vented. RPV level is lowered to < +87". If Power/Level control conditions exist, RPV level should continue to be lowered.

EOP-2 is entered on high Torus Water Temperature. Torus Cooling should be maximized. When RPV level is lowered < 64", Torus Cooling capability will be lost.

9 I/C (RO) RWCU fails to isolate when SBLC is initiated. Operators should manually close the isolation valves or bypass the filter demins.

10 I/C ATWS pressure control is a problem because the Turbine Bypass (BOP) valves fail to operate.

"l(N)ormai, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor C:\WINDOWSI*el.b*bPdoP\ES.D-1 DAECS.nao 3.do.

2 Attachment 6

QF-1 030-19 Rev. 0 (FP-T-SAT-30)

NMr .> EVALUATION SCENARIO GUIDE (ESG)

Committed to NucteareiZIj S :DAEC PROGRAM--,- OPERATIONS CILC # 50007 2 HOURS rsr1iIon; tire or poiicy = iuyrs.

rKetention: LITe Of policy = 1uyrs. Disposition: Reviewer and Approver Retain in: Training Program File ilc-7_esgnew-templete.doc Page 1 of 31

QF-1 030-19 Rev. 0 (FP-T-SAT-30)

MSIV TESTINGJAPRM FAILUREIFRV FAILURE/CONDENSER HIGH BACKPRESSURE/ATWS/POWER-LEVEL CONTROLJRWCU ISOLATION FAILURE/TURBINE BPV FAILURE, Rev. 2 Guide Requirements Simulator Training Simulator Booth Operator Resources: Phone Talker Simulator Floor Instructor

1. STP 3.6.1.3-03

References:

2. Technical Specifications

3. ARP lC05A, A-2

4. ARP lC05A, B-2

5. ARP lC05A, D-1

6. ARP IC07B, B-I/C-1

7. IPOI-4

8. EOP-1

9. EOP-2

10. ATWS

11.01-153

12.01-416

13.01-454

14.01-149

15.01-644

16.01-878.4

17. ED

18. ACP 1410.10 Performance Mode Evaluation Method:

ilc-7_esgnew-templete. doc Page 2 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MSIV TESTING/APRM FAILUREIFRV FAILURE/CONDENSER HIGH BACKPRESSURE/ATWS/POWER-LEVEL CONTROL/RWCU ISOLATION FAILURE/TURBINE BPV FAILURE, Rev. 2 SCENARIO

SUMMARY

Current plant operating status.

The plant is operating at 70% power in preparation for MSIV testing.

Scenario segments

"* (Event 1 I) Shortly after the crew takes control of the plant, the "C" APRM will slowly fail upscale resulting in a half scram. (RO/SRO)

"* (Event 2 N) Operators perform MSIV Trip Closure Time Check, STP 3.6.1.3-03.

(SRO/BOP)

"* (Event 3 I) "A" Outboard MSIV will not indicate full closed. The crew should declare CV 4413 inoperable and comply with Tech Spec 3.6.1.3.A, which requires the inboard MSIV to be closed and deactivated in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . (SRO/BOP)

" (Event 4 I) While the SS/SM are researching the MSIV LCO, the B Feed Reg Valve controller begins to fail closed. Operators will take manual control and restore RPV level.

(RO)

"* (Event 5 C) Air in-leakage into the Main Condenser results in Main Condenser High Backpressure. (SRO/BOP)

"* (Event 6 R) In response to the condenser backpressure, the crew will reduce reactor power in accordance with IPOI 4 fast power reduction. (SRO/RO)

"* (Event 7 C) The air in-leakage will increase to the point where a manual reactor scram should be performed. (SRO)

" (Event 8 M) Control Rods fail to insert. Operators perform EOP ATWS. Control rods may be manually driven for a short while, but other RIPs are unsuccessful until the scram air header is vented. RPV level is lowered to < +87". If Power/Level control conditions exist, RPV level should continue to be lowered. (ALL)

" (Event 8 M) EOP-2 is entered on high Torus Water Temperature. Torus Cooling should be maximized. When RPV level is lowered < 64", Torus Cooling capability will be lost. (ALL)

" (Event 9 C) RWCU fails to isolate when SBLC is initiated. Operators should manually close the isolation valves or bypass the filter demins. (RO)

" (Event 10 C) ATWS pressure control is a problem because the Turbine Bypass valves fail to operate. (BOP)

" It is possible to approach the Torus Heat Capacity Temperature Limit, in which case the crew should reduce RPV pressure to maintain below the HCTL.

" The scenario ends when all rods have been inserted, and the plant is stable.

ilc-7_esgnewtemplete.doc Page 3 of 31

QF-1 030-19 Rev. 0 (FP-T-SAT-30)

MSIV TESTING/APRM FAILURE/FRV FAILURE/CONDENSER HIGH BACKPRESSURE/ATWS/POWER-LEVEL CONTROURWCU ISOLATION FAILURE/TURBINE BPV FAILURE, Rev. 2 TASKS ASSOCIATED WITH SIMULATOR EXERCISE:

= Crew Evolutions:

None

= RO (NSOE, ANSOE)

1.07 Perform Surveillance Test Procedures.

+ 1.12 Perform Moore Controller Functions

+ 2.06 Perform normal Torus Cooling.

+ 6.02 Perform manual startup/initiation (SBLC).

8.11 Manually delay or interrupt ADS auto initiation.

81.03 Bypass an APRM

81.04 Return a bypassed APRM to service

93.21 Perform Fast Power Reduction

93.22 Perform the Immediate Operator responses to a reactor scram

95.03 Perform reactor scram using the RPS test switches.

95.07 Perform reactor scram using the individual scram test switches.

95.08 Insert control rods by increasing CRD cooling flow and pressure.

95.09 Insert control rods by manually driving control rods.

95.21 Perform EOP Defeat 11.

+ 95.25 Perform EOP Defeat 15.

95.27 Perform EOP Defeat 17.

95.50 Perform /L to Control RPV Level during an ATWS..

95.51 Perform Power/Level control.

+ 95.56 Perform /P to control RPV pressure during an ATWS.

+ 95.57 Perform /Q to reduce reactor power or scram the reactor.

95.61 Perform the T/T leg of EOP-2.

95.80 Perform an Emergency Depressurization using SRVs.

99.25 Respond to condenser high backpressure.

ilc-7_esgnew-templete.doc Page 4 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MSIV TESTING/APRM FAILURE/FRV FAILURE/CONDENSER HIGH BACKPRESSURE/ATWS/POWER-LEVEL CONTROURWCU ISOLATION FAILURE/TURBINE BPV FAILURE, Rev. 2

=> Shift Supervisor (SS)

1.01 Direct routine crew and Control room activities.

1.02 Determine operability of Tech Spec required components.

1.06 Conduct a Shift Brief

1.17 Coordinate Operations/others Surveillance Test activities.

1.21 Direct crew response to off normal events/accidents

4.20 Direct Crew Actions to Perform a Fast Power Reduction from 100% to Approximately 35% Power.

1.01 Direct routine crew and Control room activities.

1.02 Determine operability of Tech Spec required components.

1.06 Conduct a Shift Brief.

+ 1.17 Coordinate Operations/others Surveillance Test activities.

+ 1.21 Direct crew response to off normal events/accidents

+ 4.20 Direct Crew Actions to Perform a Fast Power Reduction from 100% to Approximately 35% Power.

+ 4.21 Direct crew actions to perform the immediate operator responses to a reactor scram.

6.03 Direct crew response to perform reactor scram using the RPS test switches.

6.05 Direct crew response to perform reactor scram by venting the scram air header.

6.07 Direct crew response to perform reactor scram using the individual scram test switches.

6.08 Direct crew response to insert control rods by increasing CRD cooling flow and pressure.

+ 6.09 Direct crew response to insert control rods by manually driving control rods.

+ 6.21 Direct Crew response to perform EOP Defeat 11.

+ 6.50 Direct Crew Response to Perform /L to Control Level During an ATWS.

6.51 Direct crew response to perform Power/Level control.

6.56 Direct crew response to perform /Q to reduce reactor power or scram the reactor during an ATWS.

6.57 Direct crew response to perform /P to control RPV pressure during an ATWS.

6.62 Direct Crew response for performance of the T/T leg of EOP-2.

6.78 Direct Crew response for performance Emergency Depressurization.

ilc-7_esgnew templete.doc Page 5 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MSIV TESTINGJAPRM FAILURE/FRV FAILURE/CONDENSER HIGH BACKPRESSURE/ATWS/POWER-LEVEL CONTROLJRWCU ISOLATION FAILURE/TURBINE BPV FAILURE, Rev. 2 Scenario Objectives:

1. Perform a surveillance test.

2. Make Tech Spec determinations.

3. Respond to a Feed Reg valve controller failure.

4. Respond to Main Condenser high backpressure.

5. Perform ATWS EOP with component failures.

6. Perform ATWS Power/Level Control.

ilc-7_esgnewtemplete.doc Page 6 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MSIV TESTING/APRM FAILURE/FRV FAILURE/CONDENSER HIGH BACKPRESSURE/ATWS/POWER-LEVEL CONTROL/RWCU ISOLATION FAILURE/TURBINE BPV FAILURE, Rev. 2 SCENARIO OUTLINE:

BOOTH INSTRUCTOR ACTIONS 1 Non-Nuclear Instrumentation System 1.1 SIMULATOR SET UP:

a. Set Event Trigger definitions.

b. Reset to IC 23. (75% MOL)

c. Go to RUN.

d. Verify power is <1460 MWT per STP 3.6.1.3-03.

e. Place the Recirc and Feedwater controllers in auto, verify zero bias on FRVs

f. Restore Malfunction File ILC7.

g. Restore Override File ILC7.

h. LPRMs: Bypass the following LPRMs:

(1) 4C-08-09 LPRM A (2) 4A-32-25 APRM D

i. Control Panels:

(1) Check APRM GAFs.

(2) Place the clean pull sheet on IC05.

(3) Pump the Drywell sumps.

(4) Ensure that alarm typer works.

j. Provide a Working Copy of STP 3.6.1.3-03.

k. Verify "B"and "C" RBCCW pump HS in START I. Restore all points to scan using "RESAP". Crews during the scenarios may delete this point from scan.

I ilc-7_esgnew-templete.doc Page 7 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MSIV TESTING/APRM FAILURE/FRV FAILURE/CONDENSER HIGH BACKPRESSURE/ATWS/POWER-LEVEL CONTROUJRWCU ISOLATION FAILURE/TURBINE BPV FAILURE, Rev. 2

1.2 MALFUNCTIONS

ILC7 Time Malfunction Malfunction Title ET Delay F. Ramp I.

No. Sev. Sev.

Setup rp05a Auto scram failure 6 0 N/A 0 N/A Setup rp05b Manual scram failure N/A 0 N/A 0 N/A Setup rpO5c ARI failure N/A 0 N/A 0 N/A Setup rp05d RPS fuse removal failure N/A 0 N/A 0 N/A Setup rp05e Individual scram test switches N/A 0 N/A 0 N/A failure Setup nm08c APRM Upscale 3 0 1.0 60 N/A Setup ms28b MO-2701 failure to isolate N/A 0 N/A 0 N/A Setup ms28c MO-2740 failure to isolate N/A 0 N/A 0 N/A As dir tc06a Bypass valve #1 failure 1 0 0 0 N/A As dir tc06b Bypass valve #2 failure 1 0 0 0 N/A Setup ms07b MSIV fast/slow time N/A 0 0.30 0 Asis As dir ms05b A MSIV OUTBD disc failure 4 0 0.90 3 Asis As dir rdl3 Scram Air Header leak 5 0 1.0 45 N/A As dir mc04a Main condenser air inleakage 6 0 0.015 600 0.005 As dir fw12b B Feed Reg Valve Failure 7 0 0 600 N/A As dir rdllb B CRD Pump Trip 1 45 N/A 0 N/A As dir rdl la A CRD Pump Trip 8 0 N/A 0 N/A As dir mc04b Main condenser air inleakage 1 0 0.20 20 N/A As dir ms28a MO-2700 failure to isolate N/A 0 N/A 0 N/A

1.3 OVERRIDES

ILC7 Time Override No. Override Title ET Delay Value Ramp Setup LO MS HS-4413A(2) A MSIV Outbd indication 4 0 ON 0 Setup LO MS CV-4413(2) A MSIV Outbd indication, 4 0 ON 0 Mimic As dir. LO MS HS-4413A(1) A MSIV Outbd indication 4 0 ON 0 As dir LO MS CV-4413(1) A MSIV Outbd indication 4 0 ON 0 Mimic As dir DI TC BPVTSTG Bypass valve test N/A 0 OFF 0 ilc-7_esg_new-templete. doc Page 8 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MSIV TESTINGIAPRM FAILURE/FRV FAILURE/CONDENSER HIGH BACKPRESSURE/ATWS/POWER-LEVEL CONTROURWCU ISOLATION FAILURE/TURBINE BPV FAILURE, Rev. 2 1.4 REMOTE FUNCTIONS:

None 1.5 EVENT TRIGGER DEFI NITIONS:

Trigger Trigger File Trigger Logic Statement Trigger Word Description Number Name I N/A rpdislshutdown(1).ge.1 Mode Switch to Shutdown 4 N/A msvpcv4413 .le. 0.9 "A" MSIV outboard to close.

others N/A Manually Activated N/A FLOOR INSTRUCTOR ACTIONS 2 Simulator Pre-brief:

2.1 Individual position assignments BOOTH / FLOOR INSTRUCTOR ACTIONS 2 Conduct pre-scenario activities in accordance with the following procedures:

3.1 If this scenario is used in performance mode: OTI 105 ilc-7_esgnewtemplete.doc Page 9 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

MSIV TESTINGIAPRM FAILURE/FRV FAILURE/CONDENSER HIGH BACKPRESSURE/ATWS/POWER-LEVEL CONTROURWCU ISOLATION FAILURE/TURBINE BPV FAILURE, Rev. 2 4 COMPLETE A TURNOVER SHEET AS FOLLOWS:

SDay of week and shift

Saturday, Evening

=> Weather conditions

Mild spring day.

SPlant power levels

75% Power

1420 MWt

+ 470 MWe

38.4 MIb/Hr CORE FLOW

=> Thermal Limit Problems/Power Evolutions

Power reduction to <1460 MWt for STP3.6.1.3-03.

=> Existing LCOs, date of next surveillance

+ None

=> STPs in progress or major maintenance

MSIV Trip Closure Time Check, STP 3.6.1.3-03

=> Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment

+ None

=> Comments, evolutions, problems, etc.

LPRMs4C-08-09 and 4A-32-25 areinop

No extra personnel.

I ilc-7_esgnew templete.doc Page 10 of 31

Rev. ( ( ES( C7 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE 0:00 Provide Shift Turnovers to the SRO and 9 Get familiar with plant conditions.

Shift Turnover ROs. S SRO will provide beginning of shift brief to coordinate the tasks that were identified on the shift turnover. (SRO 1.01, 1.06) 3:00 NOTE: If the crew immediately Crew will respond to 1C05A (A-2), "A" RPS AUTO SCRAM, as follows:

APRM Failure commences STP 3.6.1.3-03(Event 2) Wait 0 Identify the cause of the 1/2 scram.

until the T.S. call is made for Event 3 then start Event 1.

Correct the cause.

Event I

Reset the half scram When the crew assumes the watch, start Crew INOP, will respond to 1C05A (B-2), APRM A, C, OR E UPSCALE TRIP OR as follows:

the APRM failure as follows:

Monitor indications on 1C05 and 1C37 to determine which APRM is ET 3 upscale or inop Activate Event Trigger 3: Verify that the

Suspend testing in progress on other RPS instrumentation.

following malfunction becomes active: 0 Investigate the cause of the failure, initiate a Work Request Card, and nmO8c comply with TS. 3.3.1.1 (Table 3.3.1.1-1) and TRM Section T.3.3.2 This will ramp the "C" APRM to 100 over (SRO 1.02) the next 60 seconds

In this instance, TS requires that 2 APRMs be operable, therefore the APRM can be bypassed and no further TS is required

With the permission of the OSS, bypass the APRM.

0 Delete from scan the associated computer point (B002)

E Reset the half scram. (RO 81.03 & 81.04)

Ensure the B002 is restored to scan after each scenariol!!!!

11 ilc-7_esgnewjemplete.doc ilc- 7_esg-new-templete. doe 11

Rev. ý

( ES( 37 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE MSIV Testing When the operator takes the handswitch Shift Supervisor/Manager for CV-4413 "MSIV A OUTBOARD" to

Perform a Pre-Job Brief. (SRO 1.06) close, Event2 ET 4 CREW MSIV Failure Activate Event trigger 4: Verify that the

Verify Prerequisites. (RO 1.07) (SRO 1.17) correct malfunction and overrides become ° Take MSIV handswitches to close and time the closures.

active.

Event 3

Record closure times and verify 3-5 seconds.

° Identify that when the hand switch for CV-4413 is taken to Close, This is the CV-4413 will indicate an intermediate position.

second valve ° Identify approximately 500,000-Ibm/hr steam flow in the "A" MSL.

that should be tested per the

Notify SS of problem encountered.

STP. 0 The crew should declare CV-4413 inoperable, based on the dual indication, and steam flow, and comply with Tech Spec 3.6.1.3.A, which requires the inboard MSIV to be closed and deactivated in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

(SRO 1.02)

Initiate Work Request Card and AR. (SRO 1.17) 12 ilc-7_esg..jiewjemplete.doc ilc- 7_esg~new_templete.doc 12

Rev. .

(

SCENARIO TIME-LINE ES( C,7 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE After the SRO ET 7

Identify that RPV level is lowering.

begins research on LCO theorMSIV when The actions for this event are located in the ARP for 1C05A (D-1) RPV HI/LO directed by the Activate Event Trigger 7: verify that the level recorder alarm. Note that the operator may take these actions prior to Lead Examiner, following malfunction becomes active: the alarm alarming.

0 Check Feed Reg. Valves for proper operation.

Feed Reg Valve fwl2b

Identify that B Reg. valve is failing closed and shift controller to manual.

Failure (Depress M/A pushbutton) (RO 1.12)

This will cause the "B" feed reg valve to

Restore RPV level to between 186-195 inches.

slowly fail closed Event 4 '(Note: Itwill take &2.5 minutes to reach the Initiate a Work Request Card and an AR RPV low level alarm setpoint.)

Allow time for the crew to complete their administrative actions on both the MSIV and Feed Reg. Valve before proceeding to the next segment.

13 ilc-7_esgnewtemplete.doc ilc- 7_esg_new_templete,doc 13

Rev. 1' ( ES( ,- 7 SCENARIO TIME-LINE TIMEINOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE After RPV level ET 6 Crew will recognize the rise of condenser backpressure.

is stabilized or as directed by The SRO will direct and the RO will perform the following:

the Lead Activate Event Trigger 6: Verify the Examiner following malfunction becomes active:

Identify increasing Main Condenser backpressure. (RO 99.25)

High

Determine rate of change.

Backpressure mc04a, rp05a - for ATWS

Respond to Offgas panel trouble and identify high system flow.

Dispatch operators to check on plant equipment and listen for air in Event 5 This will start a slow air leak into the main leakage condenser.

SRO will direct that the Operators begin Fast Power Reduction lAW IPOI 4. (SRO 4.20)

(Note: It will take ° The RO will Reduce Recirc Flow to 27Mlb/Hr in accordance with IPOI 4,

=3 minutes for the condensers to equalize while maintaining RPV level 186-211 inches. (RO 93.21)

Event 6 _4 minutes to reach the Offgas alarm

,7 minutes to the Backpressure alarm When the crew reaches 27MIb/Hr flow they will assess the plant conditions.

=7 minutes to turbine trip) The SRO will set limits on when to scram the plant if condenser backpressure continues to rise. (SRO 1.21)

The main condenser air leak will get The crew will determine that the condenser backpressure is still rising.

bigger SRO will direct, and the ROs will perform the following:

Event7 Manually scram reactor and carry out the actions of IPOI 5. (SRO 4.21, RO 93.22) 14 ilc-7_esgnewjemplete.doc ilc-7_esg_new_templete .doc 14

Rev. ý

( ES( C7 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the Role Play in-plant personnel as The crew will determine that the plant did not scram and that an electrical reactor scram necessary. ATWS is in progress.

has been The SRO will direct and the ROs will perform the following:

attempted, Verify ET I becomes active on Mode " For ATWS switch "* Lockout ADS. (RO 8.11) (SRO 6.50)

Event 8

(CRITICAL) With a reactor scram required, reactor not shutdown, and conditions for ADS blowdown are met, inhibit ADS mc04b 0.20, ramp 20 sec.

"* Install Defeat 15. (RO 95.25 &27) (SRO 6.50)

The B CRD pump trips in 45 sec. "* Control RPV level -25"-211". (RO 95.50) (SRO 6.50) rdlb " At the beginning of the transient, the SRO may give a narrower Allow the A CRD to be started and run for level band, for example, 158" in auto Important Ill about 3 min, or when ever rods start to " The RO will have to manipulate RPV level control with one feed drift, which ever is sooner. Then perform reg valve in Manual.

the following:

"* Take Mode Switch to Shutdown. (SRO 6.56)

ET 8 "* Verify Recirc at minimum speed. (RO 95.57)(SRO 6.56)

Activate Event Trigger 8: Verify that the "* Initiate ARI and verify Recirc pumps are tripped.

following malfunction becomes active: (RO 95.57) (SRO 6.56) rdlla

The Recirc pumps will not trip automatically, and the RO will have to manually trip the Recirc MG sets if RPT did not automatically trip them following the turbine trip.

"* Inject with SBLC prior to exceeding BIIT.

(RO 95.57)(SRO 6.56).

"(CRITICAL) With a reactor scram required and the reactor not shutdown, take action to reduce nower bv inieatina boron andlnr inserting control rods 15 ilc-7_esg..new..templete.doc ilc- 7_esg_new_templete.doc 15

Rev. (

C SCENARIO TIME-LINE EK _C 7 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE A I VV, " Attempt to shut the reactor down by performing the following:

continued

"* Attempt to Insert control rods by manually driving rods, until both CRD pumps trip. (RO 95.09) (SRO 6.09)

Event 8 "* De-energize RPS with test switches. (RO 95.03) (SRO 6.03)

Continued "* Scram Test switches. (RO 95.07) (SRO 6.07)

"* Vent scram Air header. (SRO 6.05)

"* Increase CRD cooling flow and pressure. (RO 95.08)

(SRO 6.08)

"* Individual Identify Power>5% with RPV level > +87".

"* (Critical) Durin an ATWS with reactor Dower above 5% or unknown and RPV water level above +87". enter Power/Level Control for Thermal/Hydraulic Instability and terminate and prevent iniection into the RPV from Con densate/Feedwate r, HPCI, RHR. CS. and Alternate Flooding Systems. (Table 2B), until RPV level is below

+87" and conditions are met to re-establish iniection, Terminate/prevent injection until RPV level is < +87".(Cond & Feed, HPCI, RHR, CS) (RO 95.51) (SRO 6.51)

If necessary, continue to lower level until <5% or 15" or all SRVs closed with DW Pressure <2#.) (RO 95.51) (SRO 6.51)

Reestablish injection and maintain >-25" with Table 1B systems.

(RO 95.51) (SRO 6.51)

(Critical) When performing Power/Level Control and conditions are met to re-establish iniection, use available Table I B iniection svstems to maintain RPV water level between the lv#.l es__hi'hl3h in step IL-2 and -25".

16 ilc-7_esg...new..templete.doc ilc- 7_esg__new_ýtemplete.doc 16

Rev. ( ( ES( C7 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE

"* For ATWS pressure control:

"* Override CV-4371A. (RO 95.21) (SRO 6.21)

Event 10

Terminate SRV cycling. (RO 95.56) (SRO 6.57)

"* Identify that EHC/Bypass valves are not controlling.

"* Take action to stabilize RPV pressure.

"* Augment RPV pressure control by opening MSL drains.

ATWS None The SRO will direct and the RO will perform the following:

SBLC/RWCU

Inject SBLC into the RPV by placing the SBLC hand switch in PUMPS A failure & B RUN. (RO 6.02)

Verify system initiation.

Event 9

Identify that RWCU fails to isolate.

Manually close MO-2701 & MO-2740 or bypass RWCU Demins.

(SRO 6.56)

ATWS Role Play in-plant personnel as The SRO will direct and the ROs will perform the following actions of EOP 2:

EOP2 necessary. (Note: that the only Primary Containment parameter that will be of concern will be the Torus water temperature).

"* Identify EOP-2 entry 95°F Torus Water Temperature. (RO 95.61)

"* Maximize Torus Cooling. (RO 2.06) (SRO 6.62)

"* Maintain Torus water temperature < Heat Capacity Limit.

"* If Torus water temperature cannot be maintained below HCTL, maintain RPV pressure below HCTL.

17 ilc-7_esgnew..templete.doc ilc-7_esg~new-templete. doe 17

Rev. (

(

SCENARIO TIME-LINE E( .C 7 TIMEINOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE ATWS EXIT Vent the Scram Air Header when the

Identify all rods inserted.

following conditions exist:

Secure SBLC.

"* RPV Level is Stable.

Enter EOP-1.

"* RPV Pressure is stable

"* SBLC is injecting.

"* There is no threat to exceed the Torus HCTL.

ET 5 Activate Event Trigger 5: Verify that the following malfunction become active:

rd13 END When all rods have been inserted, RPV None Pressure and Level are stable, and notifications completed, place the simulator in FREEZE.

- - END OF SCENARIO REVIEW SCENARIO OBJECTIVES WITH THE OPERATORS ***

18 ilc-7_esgnewjemplete .doc ilc-7_esg~new_templete.doc 18

Rev. ( ( E, .C 7 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE APRM "C" RO ARP IC05A (A-2) NOTE: If the crew immediately upscale half

Check Scram group A and B lights to determine if a Rev. 9 commences STP 3.6.1.3-03(Event scram full scram has occurred. Step 3.1 2) Wait until the T.S. call is made for

Verify Scram Group A 1 2 3 4 indicating lights are off. Step 3.3 Event 3 then start Event 1.

Event I

Ifonly a half scram has occurred verify the following: Step 3.7

"* That conditions will not degrade to the point where Step 3.9 a Full Scram is necessary. Step 3.10

"* That no scram set point has been exceeded with Step 4.1 out a scram signal.

"* Manually scram if one of the above has occurred.

Correct the cause of the RPS Auto Scram.

Reset the half scram.

ilc-7_esg-jnew-templete.doc 19

Rev. ( ( ES( 37 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE Bypassing the RO ARP IC05A (B-2) "C" APRM bypassed and 1/2/ Scram APRM and . Check Scram group A and B lights to determine if a Rev. 6 resetting the half reset.

full scram has occurred. Step 3.1 scram Monitor APRM indications on 1C05 and 1 C37 to Step 3.3 Sat Unsat determine which APRM is downscale. Step 3.5

If it is determined that the APRM is failed: Step 3.7

"* Determine the cause, initiate a Work Request Step 3.8 Card, and comply with TS, TRM. Step 4.1

"* With permission, bypass the affected APRM.

"* Reset the half scram.

01 878.4 Rev 22

Place the APRM Bypass switch for APRM to be Section 6.0 bypassed in the BYPASS position. Step 1

Observe that the bypass light on both 1C37 and 1C05 Step 2 are on for the bypassed APRM. Step 3

The Crew may delete from scan the associated computer point (B002) ilc-7_esg-new__templete.doc 20

Rev. ( ( ES( C7 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE MSIV Testing SRO / BOP STP 3.6.1.3-03 STP performed correctly up to step

Perform a Pre-Job Brief, Rev. 2 7.2.3. Identify MSIV failure.

Event2

Verify Prerequisites: Step 6.2

No other testing. Step 6.3 Sat Unsat

<1460 MWt. Step 6.5

All MSIVs open. Step 6.6 Step 7.1 (1-13)

1C15 &1C17 relays energized. Step 7.2 (1-3)

Verify <1460 MWt. Step 7.2 (1-3)

STP is stopped at

Take MSIV handswitches to close and time the step 7.2.3due to closures, valve failure.

Record closure times and verify 3-5 seconds.

Identify the failure CV-4413 to indicate closed.

Notify SS of problem encountered.

MSIV Failure SRO TS 3.6.1.3.A Tech Spec determination is correct.

Declare CV-4413 inoperable and comply with Tech Event 3 Spec 3.6.1.3.A, which requires the inboard MSIV to STP 3.6.1.3-03 Sat Unsat be closed and deactivated in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Initiate Work Request and AR.

21 ilc-7_esgnewjemplete.doc ilc-7_esg_new_templete.doc 21

Rev. ( ( ESy 37 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE Feed Reg Valve RO Identify that RPV level is lowering. ARP 1C05A D-1 RPV level being controlled in green Rev. 5 band in automatic.

Event 4 0 Check Feed Reg Valves for proper operation and Step 3.1 restore to maintain RPV level 186-195. Step 3.2 Sat Unsat 0 Identify that B Reg valve is failing closed and shift Step 3.4 controller to manual. (Depress M/A pushbutton) Step 3.5

Initiate a Work Request Card. Step 4.1 22 ilc-7_esg....new..templete.doc ilc-7_egsg-new-templete .doc 22

Rev. ( .C7 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE Loss of Vacuum SROIBOP 1C34 B-8 Rev. 6 Respond to Offgas panel trouble and identify high Step 3.1 Event 5 system flow. Step 3.3

"* At panel 1C34 confirm the Offgas high flow Step 3.6 condition for >40 scfm and verify in service recombiner A/B temp normal.

"* At 1C07B check Main condenser vacuum, if lost perform ARP 1C07B, D-9.

"* If a failure of PC 4150 is suspected send an operator to verify PC 4150 is set at 350 psig. ARP IC07B

Identify increasing Main Condenser backpressure. 6-1/D-9/C-1, Rev. Note: These ARP have the same 6 actions.

Determine rate of change.

Step 3.2 Event 6 (R)

AOP 672.1 may be entered due to Offgas indications.

ROStep 3.

Step 3.4 Loss of condenser vacuum Identified

Operators will begin Fast Power Reduction. Step 3.5 Sat Unsat

Reduce Recirc Flow to 27MIb/Hr while maintaining Step 4.2 -6 RPV level 186-211 inches.

Event 7

Insert control rods to lower load line. (Possible) IP014 Rev 57 SRO SReactor Section 6.0 scram. Scram prior to automatic

Once the power reduction is completed the SRO Step 1 determines the condenser backpressure is approaching the scram setpoint and orders a Reactor Sat Unsat Scram.

I ilc-7_esg~new-templete .doc 23

Rev. ( ES( .; 7 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE ATWS SRO/ROIBOP EOP-1 Rev. 9 (CRITICAL ) With a reactor scram required, Identify I t an a Electrical e c ATWS. T CRS CRS Following FoADS reactor not shutdown. and conditions for blowdown are met, inhibit ADS Event 8 RC-3

"* Lockout ADS. ATWS Rev. 10 Sat Unsat

"* Install Defeat 15. /-1

Control RPV level -25"-211". /-2

Note the level band directed will probably be /QI narrower than the above /Q-2 (CRITICAL) With a reactor scram required

"* Take Mode Switch to Shutdown. /Q-3 and the reactor not shutdown, take action to

Verify Recirc at minimum Verfy speed.

" inimm sped.

Rcircat /Q-5 Q-6inserting reduce power by iniecting boron and/or control rods

"* Initiate ARI and verify Recirc pumps are tripped. /Q-6

The crew will have to trip the one Recirc pump Sat_____ Unsat

" Inject with SBLC prior to exceeding BIIT. /Q-8

1C05 operator will determine that RWCU did not /Q-1 0 isolate and manually isolate it. /P-1

" Attempt to Insert control rods: /P-2 (Critical) During an ATWS with reactor

De-energize RPS with test switches. /P-4 power above 5% or unknown and RPV water It/L-1 level above +87". enter Power/Level Control SIndividual Scram Test switches. for Thermal/Hydraulic Instability and Vent scram Air header. /L-2 terminate and prevent injection into the RPV from Condensate/Feedwater. HPCI. RHR.

Increase CRD cooling flow and pressure. CS. and Alternate Flooding Systems,

/L-5 (Table 2B). until RPV level is below +87" and SManually drive rods. conditions are met to re-establish iniection.

Sat Unsat 24 ilc-7_esgnewjemplete.doc ilc- 7_esg-new-templete.doc 24

Rev. ( ( ES* C 7 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE ATWS continued. SROIBOP (Critical) When performing The following is performed in the ATWS RPV level leg. Power/Level Control and conditions During an ATWS, if power is > 5% and RPV level is are met to re-establish injection, use greater than 87", the possibility of reactor instabilities available Table 1 B iniection systems exist, therefore level is lowered to 87", this is 2 feet below to maintain RPV water level between the feed water spargers. This raises the final feed water the level established in step /L-2 and temperature, increases voids, lowers power, and -25" decreases the possibility of core instabilities.

"* Identify Power>5% with RPV level > +87". Sat Unsat

"* Terminate/prevent injection until RPV level is

< +87". (Cond & Feed, HPCI, RHR, CS)

"* If necessary, continue to lower level until <5% or 15" or all SRVs closed with DW Pressure <2#.

"* Maintain >-25" with Table 1 B systems.

"* Override CV-4371A.

"* Terminate SRV cycling.

Event 10 This Should be Identify BPVs not responding.

0BOP Identify that EHC/Bypass valves are not controlling. identified during

Augment RPV pressure control by opening MSL Step /P-4 Sat Unsat drains.

ilc- 7_esg-new-templete.doc 25

Rev. (

( E(.C 7 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE SBLC/RWCU RO 01-153 Rev. 30 RWCU Isolated.

failure

Place SBLC switch in PUMPS A & B to RUN. Section 4.0 Verify system initiation. Step 1 Sat Unsat Event 9 0 Pump red lights on/ green off. Step 2

"* Squib valve lights off. Step 3 (RWCU Failure to Isolate)

"* Discharge pressure >RPV pressure.

"* Combined flow >52.4 gpm. Step 4

Identify that RWCU valves, MO-2701 & MO-2740 Step 5 isolate.

Both MO-2700, MO-2701 and MO-2740 fail to isolate, the crew will manually close them or bypass filter demins.

Verify SBLC tank lowering.

26 ilc-7_esg..jiewjemplete.doc ilc- 7_esg-new-templete.doc 26

Rev. ( ( E . .C 7 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE EOP-2 SRO/IBOP EOP-2 Rev. 9 Torus Cooling Maximized.

Identify EOP-2 entry 95°F Torus Water Temperature. T/T-1 T/T-2 Event 8 T/T-4 Sat Unsat continued Maximize Torus Cooling. T/T-5

"* Start ESW pumps.01-454 QRC I

"* RHRSW pumps started. Rev 1

"* RHRSW flow adjusted to 2000-2600 gpm per Immediate actions pump. Step 1 Step 2

"* Start or verify four RHR pumps.

"* Verify Min Flow valves open when <2000 gpm.01-416 QRC 1

"* Open Outboard Torus Cooling valves. Rev 1 Immediate actions

"* Throttle Torus Cooling/Test valves to 9600 gpm Step 1 on each loop. Step 2

"* Close Heat Exchanger Bypass valves. Step 3 Step 4

Maintain Torus water temperature < HCTL. Step 5

IfTorus water temperature cannot be maintained Step 6 below HCTL, maintain RPV pressure below the Follow-up Actions HCTL Step 1 01-149 QRC 2 Rev 0 Immediate Actions Step 1 Step 2 Step 3 Step 4 Step 5 2

ilc-_esnewjmplte~dc ilc- 7_esg_,new__templete.doc 27

Rev. ( ( ES .C 7 SCENARIO CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS SEGMENT REFERENCE ATWS EXIT

Identify all rods inserted. ATWS

Secure SBLC.

Enter EOP-1.

EAL

SA-2 EAL Board 28 ic-7_esgnew..templete.doc ilc-7_esg-new-templete.doc 28

CREW GRADING ATTACHMENT ESG ILC 7 Rev. 1 Operator Name Position Evaluator Shift Supervisor Reactor Operator #1 Reactor Operator #1 Management Representative/Lead Evaluator Crew Critical Tasks Task Statement SAT UNSAT

1. With a reactor scram required, reactor not shutdown, and conditions for ADS blowdown are met, inhibit ADS

2. With a reactor scram required and the reactor not shutdown, take action to reduce power by injecting boron and/or inserting control rods

3. During an ATWS with reactor power above 5% or unknown and RPV water level above +87", enter Power/Level Control for Thermal/Hydraulic Instability and terminate and prevent injection into the RPV from Condensate/Feedwater, HPCI, RHR, CS, and Alternate Flooding Systems, (Table 2B), until RPV level is below

+87" and conditions are met to re-establish injection.

4. When performing Power/Level Control and conditions are met to re-establish injection, use available Table 1B injection systems to maintain RPV water level between the level established in step /L 2 and -25".

ilc-7_esg_new-templete.doc Page 29 of 31

Rev. 1 ESG ILC 7 Individual Competency Identifiers

1. Identify the failed APRM, refer to TS/TRM and appropriate ARPs and Ols and bypass the failed APRM.

2. Identify the failed MSIV, refer to appropriate TS, and determine that the inboard MSIV must be closed and deactivated in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

3. Identify and control RPV water level with a failed controller input.

4. Diagnose the air inleakage, and perform IPOI 4 rapid power reduction to lower power.

When it is determined that an automatic scram will occur, the crew should attempt to manually scram prior to the automatic scram.

5. Recognize the failure to scram, and EOP I/ATWS entry, and perform appropriate actions to insert rods. (initially one CRD pump will be available to drift/drive rods in)

6. As power is lowering, control RPV level such that a high RPV level turbine trip does not occur ("B" FRV is in manual).

7. The crew should recognize the failure of the bypass valves to control pressure, and manually open drains to assist in pressure control.

8. The crew should inject SBLC, and recognize the failure of RWCU to isolate, and manually isolate RWCU.

9. When the crew has entered Power/level control, level should be stabilized below 87 inches, but above -25 inches.

10. If RPV level goes below 64 inches, LPCI logic will prevent RHR operation in torus cooling without 2 psig DW pressure.

11. If RPV level goes below 64 inches, DW cooling will be lost, due to isolation of the well water to the coolers. This could result in 2 psig DW pressure, and high DW temperature.

Attach to crew grading worksheet, OTI-105, Attachment 12 when complete.

ilc-7_esgnewtemplete.doc Page 30 of 31

Rev. I ESG ILC 7 OSG VALIDATION CHECKLIST Scenario # ESG ILC 7 Rev. 1 1 Verify that if not run from a protected IC that setup information is provided to reproduce the stated initial conditions.

2 _ Verify that all stated objectives are identified in the body of the OSG.

3 Verify that turn over sheets are completed, and are in agreement with both the narrative summary and shift turnover information sheet. Turn over sheets are not required for initial license scenarios.

4 _ Verify that if the scenario requires documents to be provided to the crew, that they are filled out as appropriate (i.e., if an STP is used, it is filled out).

5 _ If this is the initial validation or the revision affects ramp times, event triggers, malfunctions, overrides, remote functions or procedure changes could affect the scenario, then validate the scenario for proper response using a crew. It is preferable to use a crew unfamiliar with the scenario whenever possible. Verify the following while running the scenario:

"* The scenario runs as written and all tasks are performed.

"* The stated time line agrees with actual times.

"* Critical task statements clearly define the expected plant and student response.

They should also be written so that they are achievable as written. If any question exists, it is preferable to have operations management participate in the validation.

"* Anticipated instructor role play/cues are identified

"* Management expectations are captured and re-enforced.

"* Verify administrative documentation requirements (i.e., CMARs / ARs) are identified.

"* Verify reportability requirements (i.e., ESF actuations) are identified.

"* Verify Technical Specification items / LCO declarations are correct.

"* If procedure steps may cause confusion or disagreement between higher-level procedures and Ols/ARPs that operations management is consulted.

6 _ Shutdown scenarios include shutdown risk assessment, time to boil calculations, and shutdown status board information.

SME/Instructor Date SME/Instructor Date SME/Instructor Date ilc-7_esgnew-templete.doc Page 31 of 31

QF-1030-19 Rev. 0 (FP-T-SAT-30)

Nm , EVALUATION SCENARIO GUIDE (ESG)

Committed to N.*cear Excell*CEA ST DAEC POPERATIONS COU ILC 50007 90 MINUTES 2002_ESG 15_newtemplete.doc Page 1 of 33

QF-1 030-19 Rev. 0 (FP-T-SAT-30)

DECREASE REACTOR POWER/ STARTUP OF "A"RHRSW/ESW PUMPS/ ROD DRIFT/RWM ROD POSITION SUBSTITUTION/GROUP 3/LOSS OF ANNUCIATOR 1C05/XFV-4642A INDICATES DUAL POSITION/ /GRID INSTABILITY/LOCA, Rev. 0 Guide Requirements

1.01-416

References:

2.01-454

3. ARP 1C03B[29]

4. Tech Spec

5. ACP 1410.1

6. ACP 1410.7

7. ACP 1402.3

8. ARP 1C05B (C-8)

9. ARP 1C04B (A-I)

10. IPOI 5

11. EOP 1

12. EPIP 1.1 Performance Mode Evaluation Method:

2002_ESG 15_newtemplete.doc Page 2 of 33

QF-1030-19 Rev. 0 (FP-T-SAT-30)

DECREASE REACTOR POWER/ STARTUP OF "A"RHRSW/ESW PUMPS/ ROD DRIFT/RWM ROD POSITION SUBSTITUTION/GROUP 3/LOSS OF ANNUCIATOR 1C05/XFV-4642A INDICATES DUAL POSITION/ /GRID INSTABILITY/LOCA, Rev. 0 SCENARIO

SUMMARY

Current plant operating status.

The plant is operating at 90% power. HPCI is in day 9 of 14, it has been repaired but is awaiting the operability testing. There is no other inoperable equipment.

Scenario segments

"* Event 1 (R) 1C05 operator will lower reactor load by 60 MWe. (RO)

"* Event 2 (N) BOP operator will startup the "A" RHRSW and "A" pumps for vibration data collection. (BOP)

"* Event 3 (I/C) Rod drift occurs due to loss of position indication. (RO)

"* Event 4 (N) Insert a substitute value in the RWM. (RO)

"* Event 5 (I/C) XFV-4642A alarms and indicates dual. The BOP operator will investigate to determine if the XFV is isolated. The SRO will determine that this is a reportable event.

The SRO must also make an operability determination of the valve. (SRO/BOP)

"* Event 6 (I/C) A group 3B isolation occurs due to Fuel pool rad monitor failing. (BOP)

"* Event 7 (I/C) 1C05 losses alarm power and does not alarm the Group 3. (RO)

"* Event 8 (M)A grid disturbance will result in a degraded grid voltage. (ALL)

"* Event 9 (I/C) The "A" EDG will start, but not load on to the bus and the "B" EDG will start, but the "B" ESW pump will not. (BOP)

"* Event 10 (I/C) When directed to install defeat 4, the BOP will determine that it will not work.

(BOP)

"* Event 11 (M) The scram will cause a small LOCA to occur inside the PC requiring Torus and D/W sprays. (ALL) 2002_ESG 15_newtemplete.doc Page 3 of 33

QF-1 030-19 Rev. 0 (FP-T-SAT-30)

DECREASE REACTOR POWER/ STARTUP OF "A"RHRSW/ESW PUMPS/ ROD DRIFT/RWM ROD POSITION SUBSTITUTION/GROUP 3/LOSS OF ANNUCIATOR 1C05/XFV-4642A INDICATES DUAL POSITION/ /GRID INSTABILITY/LOCA, Rev. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE:

=> Crew Evolutions:

+ None

= RO (NSOE, ANSOE, XANSOE)

+ 93.12 Lower Reactor Power with Recirc Flow when Above 35% Power.

+ 30.01 Startup RHRSW System.

+ 1.04 Respond to Annunciators.

+ 93.22 Perform immediate operator responses for reactor scram

+ 2.06 Perform normal torus cooling.

+ 95.44 Perform actions of RC/L of EOP-1.

+ 95.46 Perform actions of RC/P of EOP-1.

+ 95.63 Perform D/VVFT leg of EOP 2.

+ 95.64 Perform DAN/P leg of EOP 2.

+ 8.04 Perform manual operation of ADS. (possible)

= SRO

+ 1.02 Determine Operability for Tech Spec Required Components.

1.02.02 Determine if the instrument, system or component is operable.

1.02.03 Declare the instrument, component or system inoperable, enter them correct LCO, and determine and direct performance of the LCO STP.

+ 1.11 Ensure the conduct of plant operations and maintenance are in compliance with administration procedures.

1.11.03.02 Differentiate between a Routine Report, Non routine Report, Immediate Notification Event, Reportable Event and a Licensee Event Report.

+ 1.21 Direct crew response to off-normal events

1.21.02 Recognize and prioritize data relevant to the accident or event

1.21.04 Conduct periodic crew briefings to include plant status, priorities, and key ongoing activities.

4.21 Direct crew actions to perform the immediate operator responses to a reactor scram.

4.21.01 Direct the operator to insert a manual scram.

4.21.02 Direct the confirmation that the reactor is shutdown.

2002_ESG 15_new.templete.doc Page 4 of 33

QF-1 030-19 Rev. 0 (FP-T-SAT-30)

DECREASE REACTOR POWER/ STARTUP OF "A"RHRSW/ESW PUMPS/ ROD DRIFT/RWM ROD POSITION SUBSTITUTION/GROUP 3/LOSS OF ANNUCIATOR 1C05/XFV-4642A INDICATES DUAL POSITION/ /GRID INSTABILITY/LOCA, Rev. 0 e 4.21.03 Direct the operator performance of the IPOI 5 immediate actions

5.11 Direct crew response to loss of RPS AC power condition.

5.11.02 Check Automatic actions for immediate concerns.

5.11.03 Direct performance of the follow-up actions.

5.38 Direct crew response to a loss of Offsite power.

5.38.01 Check automatic actions and conditional statements for immediate concerns.

5.38.02 Direct operator actions to mitigate the consequences of a loss of offsite power and to stabilize plant parameters.

6.44 Direct crew response for performance of the RC/L leg of EOP-1.

6.44.01 Direct operator actions to maintain RPV level between 170" and 211" using the Table 1 injection systems.

6.46 Direct crew response for performance of the RC/P leg of EOP-1.

6.46.04 Direct operator actions to augment RPV pressure control with other steam loads, SRVs, or RWCU.

6.63 Direct crew response for performance of the DW/T leg of EOP 2.

e 6.63-04 Direct operator actions to secure running recirc pumps, initiate DW sprays using RHR not required for adequate core cooling, and verify fans shutdown.

6.64 Direct crew response for performance of the DW/P leg of EOP 2.

6.64.02 Direct operator actions to initiate Torus sprays using RHR not required for adequate core cooling.

6.21 Direct Crew response to perform EOP Defeat 11.

6.21.01 Direct operator actions to perform EOP Defeat 11.

SShift Manager (SM)

None SSTA None 2002_ESG 15_newtemplete.doc Page 5 of 33

QF-1 030-19 Rev. 0 (FP-T-SAT-30)

DECREASE REACTOR POWER/ STARTUP OF "A"RHRSW/ESW PUMPS/ ROD DRIFT/RWM ROD POSITION SUBSTITUTION/GROUP 3/LOSS OF ANNUCIATOR 1C05/XFV-4642A INDICATES DUAL POSITION/ /GRID INSTABILITY/LOCA, Rev. 0 Goal:

Scenario Objective(s):

1. Reactor power decrease

2. Startup of "A" ESW and "A" RHRSW pumps

3. Group 3 Isolation on Fuel Pool Rad Monitor Failure

4. Loss of 1C05B Annunciator power

5. XFV isolation and LPCI loop select inop

6. Respond to degraded off site power source.

7. Ensure that one stable power source will continue to supply power to an Essential bus.

8. Determine Defeat 4 Failure.

9. Respond to a LOCA 2002_ESG 15_newtemplete.doc Page 6 of 33

QF-1030-19 Rev. 0 (FP-T-SAT-30)

DECREASE REACTOR POWER/ STARTUP OF "A"RHRSW/ESW PUMPS/ ROD DRIFT/RWM ROD POSITION SUBSTITUTION/GROUP 3/LOSS OF ANNUCIATOR 1C05/XFV-4642A INDICATES DUAL POSITION/ /GRID INSTABILITY/LOCA, Rev. 0 SCENARIO OUTLINE:

BOOTH INSTRUCTOR ACTIONS Non-Nuclear Instrumentation System 1.1 SIMULATOR SET UP:

a. Reset to IC 20

b. Restore Malfunction File ESG15.

c. Restore Override File ESGIS.

d. Verify that the Pull sheet is on 1C05 and current rod position identified.

1.2 MALFUNCTIONS

ESG15 Time Malfunction Malfunction Title ET Delay F. Ramp I. Sev.

No. Sev.

0 rm02re4131b RE-4131B REFUEL 1 0 1 0 As is POOL LEVEL B 0 an01tc05b CONTROL ROOM 1 0 N/A N/A N/A ANNUNCIATOR PANEL 1C05B AS req. AN:IC03C[29] XFV System "B"Hi 4 N/A ON N/A N/A Flow As Dir ed03 POWER GRID 2 0.28 180sec .50 VOLTAGE TRANS IENT(NORMAL GRID VOLTAGE=0.5)

T=0 dg02a A EDG fails to auto 2 close on bus 1A3 T=O sw1l2b "B" ESW pump fails to 2 start T=0 rrl5a RECIRC LOOP RUPT- 3 .02 120sec As is DESIGN BASES LOCA AT 100%-LOOP A (NRVI)

As Dir rd04a1835 CR RPIS REED SW 5 0 20 0 As is FAILUREOPEN-ROD 18-35 2002_ESG 15_newtemplete.doc Page 7 of 33

QF-1030-19 Rev. 0 (FP-T-SAT-30)

DECREASE REACTOR POWER/ STARTUP OF "A"RHRSW/ESW PUMPS/ ROD DRIFT/RWM ROD POSITION SUBSTITUTION/GROUP 3/LOSS OF ANNUCIATOR 1C05/XFV-4642A INDICATES DUAL POSITION/ /GRID INSTABILITY/LOCA, Rev. 0

1.3 OVERRIDES

ESG15 Time Override No. Override Title ET Delay Value. Ramp 0 Z LO RR HS4642A[GREEN] XFV 4642A 4 N/A ON N/A SETUP Z DI PC HS4321A[NORMAL] Defeat 4 Key Norm Lock SETUP Z DI PC HS4321B[NORMAL] Defeat 4 Key Norm Lock Z LO RR HS4642A[2] JP3 AND JP4 4 OFF RISER DP XFV 4642A (RED) I I I 1.4 REMOTE FUNCTIONS:

None 1.5 EVENT TRIGGER DEFINITIONS:

As noted on Malfunction Table all manually inserted.

FLOOR INSTRUCTOR ACTIONS 2 Simulator Pre-brief:

2.1 Individual position assignments BOOTH I FLOOR INSTRUCTOR ACTIONS 2 Conduct pre-scenario activities in accordance with the following procedures:

3.1 If this scenario is used in performance mode: OTI 105 2002_ESG 15_newtemplete.doc Page 8 of 33

QF-1 030-19 Rev. 0 (FP-T-SAT-30)

DECREASE REACTOR POWER/ STARTUP OF "A"RHRSW/ESW PUMPS/ ROD DRIFT/RWM ROD POSITION SUBSTITUTION/GROUP 3/LOSS OF ANNUCIATOR 1C05/XFV-4642A INDICATES DUAL POSITION/ /GRID INSTABILITY/LOCA, Rev. 0 COMPLETE A TURNOVER SHEET AS FOLLOWS:

= Day of week and shift

Today

Days S Weather conditions if different from actual conditions

Clear

+ Cool power levels

93 % Power

MWT 1785

MWE 617

+ CORE FLOW 46.2 Ibm/hr SThermal Limit Problems/Power Evolutions

System Operations Center wants a decrease of 60 MWe

=> Existing LCOs, Date Of Next Surveillance

+ HPCI is inop Day 9 of 14

= STPs in progress or major maintenance

+ None

=> Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment

HPCI is inop due to MO 2239 failure to meet ASME testing requirements.

MO 2239 was disassembled and restored. All of the HPCI tags have been removed and the HPCI system has been restored. HPCI is available.

There is a meeting in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to brief the HPCI operability test to be run later this shift.

z: Comments, evolutions, problems, etc.

There are no extra personnel

The System Engineer has requested increased vibration data on the "A" RHRSW pump. After shift turnover the Electricians would like you to start "A" RHRSW pump.

2002_ESG 15_newtemplete.doc Page 9 of 33

Rev. (

(

SCENARIO TIME-LINE ESG( 15 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Provide the students' time to walkdown the The students will walkdown the panels and then participate in a shift panels and then provide the shift turnover. turnover.

SRO will conduct a Shift Brief.

10 2002_ESG_15_newAemplete.doc 2002_ESG 15 new-templete.doc 10

Rev. (

(

SCENARIO TIME-LINE ES* 15 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event I Event 1 is performed to evaluate a SRO Provide the 1C05 operator a pre-evolution brief on lowering reactor significant reactivity manipulation, power.

SRO will direct the RO to lower generator load by 60 MWe using the Note: Ifthis is taking both ROs and the floor Reactor Recirculation System.

instructor wants to continue.

Role play as the Load Dispatcher and call RO will lower generator load by 60 MWe using the Recirc System in the control room. Inform the OSS that he accordance with IPOI 3.

want us to stop the power reduction for the

Reduce Recirc MG Set speed in small increments time being due to another unit tripping.

Maintain Recirc Loop flows balanced Event 2 Event 2 will be used to evaluate a normal SRO will direct the BOP to startup the "A" RHRSW and "A" ESW pumps.

evolution. The BOP operator will start up BOP will startup the "A" ESW pump in accordance with 01-454.

the RHRSW and ESW Systems.

BOP will startup the "A" RHRSW pump in accordance with 01-416.

Ifneeded:

Role-play as electricians and call the Control room and ask when can we expect the "A" RHRSW pump run to start?

Role-play as the Aux operator:

When "A" ESW pump is started report the pump and strainer are sat. The auto vent is closed and strainer dp is 0.4 psid.

And When "A" RHRSW pump is started report the pump and strainer are sat. The auto vent is closed and strainer dp is 0.6 psid.

11 2002_ESGl5newtemplete.doc 2002_ESG_15_new-templete.doc 11

Rev. 0(

(

SCENARIO TIME-LINE ESG( 15 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 Rod 18-35 losses position indication SRO directs the 1C05 operator to carry out the actions of the ARP for Rod resulting in a rod drift. Drift.

1C05 Operator respond to Rod Drift Annunciator.

ET 5

Select the rod

Verify no rod motion

5: Verify the Activate event trigger following becomes active rd04a1835 If contacted as the RE Role-play and acknowledge the abnormal rod pattern and if asked if it is OK to move the rod to check position tell them there is no problem with moving the control rod.

Also if asked where to position the rod tell them the rod can be left at position 18 until we run a predictor case and then we can decide on the rod pattern.

Event 4 Substitute the Rod Position in the RWM SRO after determining the correct rod position direct the 1C05 operator to substitute the rod position in the RWM If contacted as the RE 1C05 operator enters the substituted rod position in the RWM.

Role-play and allow the crew to substitute 1the rod position.

12 2002_ESG_15_newtemplete.doc 2002_ESG 15 new-templete.doc 12

Rev. (

(

SCENARIO TIME-LINE ESG( 15 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the Event 4 will be used to evaluate an BOP control rod Instrument/Component failure. The crew

Report that the valve indicates dual.

position has will respond to a failed excess flow check

Contact NSPEO and HP to determine if a leak exists.

been valve.

substituted or as directed by SRO determine that the XFV is inoperable.

the lead ET 4 Using Technical Specifications, determine that with LPC/ loop select and evaluator HPCI both inoperable,HPCI or LPCI must be restoredto operable status within 72 hrs.

Activate event trigger # 4: Verify the The SRO will determine that an ESF actuation has occurred and a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Event 5 following become active notification will need to be performed.

LO RR HS4642A[GREEN] Exact portions of 10 CFR 50.72 and 10 CFR 50.73 need not be identified AN:1C03B[29] and the report does not need to be made.

Role play as NSPEO and report that there T.S. 3.3.5.1 Table I Function 2.J.

is no indication of a leak on lC121B if T.S. 3.3.5.1 condition C3 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to restore or LPCI subsystem is inop.

directed by the control room to go there. T.S. 3.5.1.H 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore HPCI or LPCI subsystems.

NOTE: PDIS 4642 is reading ZERO if asked.

Role play as I&C: If requested to aid in trouble shooting say that you will go to the valve to look at it.

13 2002_ESG_15_new...templete.doc 2002_ýESG_15_new_templete.doc 13

Rev. ( ES(ý 15 SCENARIO TIME-LINE TIME/NOTES_[ INSTRUCTOR ACTIVITY I EXPECTED STUDENT RESPONSE As directed by Events 6 and 7 will evaluate an SRO Direct the BOP operator to determine the cause of the Group 3 the lead Instrument/Component failure causing a isolation.

examiner, Group 3B isolation and the loss of alarm SRO Direct the 1C05 operator to perform the actions AOP 302.2 "Loss of power to 1C05B Alarm Power" Event 6 BOP Recognize determine the cause of the Group 3 isolation is the failure ET 1 of the Fuel Pool Rad monitor.

RO determine that the loss of alarm power to 1C05B is either a fuse in the panel or a switch out of position.

Activate event trigger # 1:Verify the following malfunctions become active:

SRO determines that the CV-4371A is inoperable and complies with ACP 1410.7 and determines that it must be returned to operable within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months rm02re4131 b or must be de-energized (and isolated). (TS 3.6.1.3.C)

SRO should also determine that the group 3 isolation is a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reportable an011c05b event in accordance with ACP 1402.3.

If I&C is called for assistance Role Play as I&C Technician The Fuel Pool Rad Monitor has a bad card and we should be able to replace it within 30 minuets.

Event 7 Once the crew identifies the fuse to 1C05B is the likely cause for the alarm power failure tell the crew that fuse F2 is blown and fuses are on hand and F2 can be replaced.

Clear the malfunction for the loss of Alarm power to I C05B.

14 2002_ESG_15_new...templete.doc 2002_ESG 15 new-templete.doc 14

Rev.(

(

SCENARIO TIME-LINE ESG 15 TIME/NOTES INSTRUCTOR ACTIVITY I EXPECTED STUDENT RESPONSE Once the Group Begin the grid disturbance The crew will diagnose the LOOP. (SRO 5.38) 3 cause is SRO will direct the following:

identified and 1C05B power is ET2 "* IPOI 5 be completed and that the follow-up actions for natural restored or as circulation be carried out. (SRO 4.21 &4.22) determined by Activate event trigger # 2: Verify the following become active "* AOP 301 for the loss of essential power. (SRO 5.38) the Lead Examiner RO will perform the following:

ed03 Grid dg02a "* Carry out IPOI-5 immediate actions. (RO 93.22)

Disturbance swi 2b "* Carry out the actions of AOP 301

"* Carry out the actions of AOP 304 Event 8 Role Play if called as the SOC and inform "* Ask the SS if he should do AOP 358 when finished.

the crew that 10,000 MWE of generators in Illinois tripped. "* Verify SBDGs carrying essential busses. (RO 19.01)

Determine that the B EDG is running, but there is no B ESW This will cause the grid voltage to drop to 80 pump running

% over 3 min.

Crew should secure the B EDG when the A EDG is restored to bus 1A3.

About 3 min after the grid disturbance,

Determine that the A EDG is running and up to speed, however modify ed03 as follows it did not auto transfer.

Crew will manually load the A EDG to bus 1A3.

Event 9 ed03 Final Severity of 0.45 (Critical)

Ramped in over 60 sec.

With electric power available but not supplying EOP required equipment, take manual actions to restore power to systems required This will raise the grid voltage to about 90 % to perform EOP actions.

ROLE PLAY if called to look at the ESW breaker, inform the control room that the breaker door is blackened and the area smells strongly of burnt wires.

I I 15 2002_ESG_15_new...templete.doc 2002_ESG 15 new-templete.doc 15

Rev. 0*

( ESGQ 15 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 9 Role play as the SOC and inform the Continued control room that there has been a severe grid transient, you currently have the grid voltage back up to about 90% and that's where it's going to stay for about an hour.

As directed by When 1A3 is being supplied by the "A" Crew will determines that the DW pressure and temperature are going up, the Lead SBDG. and at 2 psig enter EOP 2. The SRO will direct and the ROs will perform Examiner. AND the following actions: (RO 95.63, 95.64, SRO 6.63, 6.64)

EOP 2 The crew has tripped the "B" SBDG 0 Restore MCC 1B33 and 1B35 after the load shed OR

DW/T Event 11 Restored Off Site power to 1A4

Attempt to control temp < 150 by bypassing the main plant intake coils.

0 Place Defeat 4 in service.

ET3

RO reports that Defeat 4 did not work to increase the speed of the DW fans.

Activate event trigger # 3: Verify the ° While in the safe region of the drywell spray initiation limit, and Event 10 following become active before drywell temperature reaches 280 OF, initiate drywell sprays.

rr15a .02 120 (Critical).

This will start a leak in the PC.

PC/P Increase as required to ensure Drywell

Before the Torus reaches 11 psig, spray the Torus.

Sprays are initiated.

16 2002_ESG_15_newtemplete.doc 2002_E SG_15_new-templete.doc 16

Rev. &, ( ESG( 15 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE EOP 1 Crew recognize EOP-1 entry on 2 psig DAN.

The SRO will direct and the RO's will perform the following actions of EOP 1

", Verify Group 1 isolation. (RO 95.44)

"* Verify Group 3A isolation. (RO 95.44)

"* Restore RPV level 170-211 inches. (RO 95.44) (SRO 6.44)

"* Override CV-4371A. (RO 95.46) (SRO 6.21.01)

"* Verify LLS stabilizes RPV pressure. (RO 95.46) (SRO 6.46)

AOP 358 Role-play as the Aux who is sent to restore OSS will direct the AOP 358 be performed to reset the scram. (SRO RPS. 5.11).

When sent to the Essential Switchgear, RO will perform the following actions to restore RPS. (RO 94.11) report back the following:

Verify auto actions and manually initiate those that did not occur.

"* The RPS MG sets are running 9 Verify reactor scram and perform IPOI 5 satisfactorily. s Verify group 1 and control RPV pressure using these systems, (RCIC.

"* The EPA breakers were tripped on HPCI, LLS, or ADS) under voltage.

Verify Gr. 3 and place CV4371A in override at 1C35.

When directed to close the EPA s Perform

Direct the Aux to 1A3 & 4 Switchgear room to assist in trouble shooting the following: RPS.

Call up the RPS screen RPI, and reset 0 Suspend all electrical switching evolutions.

EPAs.

Break condenser vacuum

If RPS is de-energized and it's power sources are available, then restore RPS per 01 358, section 6.0.

RO will reset the scram and perform applicable portions of 01 358 Attachment 4 to verify the scram is reset properly 17 2002_ESG_15_new..templete.doc 2002_ESG 15 new-templete.doc 17

Rev. ( ( ES* 15 SCENARIO TIME-LINE TIMEINOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE END Place the simulator in FREEZE when the OSS will determine the proper classification is an FA1 due to DW pressure following are complete: above 2 psig and not caused by a loss of DW cooling. (SRO 1.03)

"* RPS power has been restored

"* RPV pressure and level are stable.

"* DW sprays have been initiated

"* Operators have determined the need for thermal stratification actions.

Have the OSS classify the event.

- - END OF SCENARIO **

REVIEW SCENARIO OBJECTIVES WITH THE OPERATORS ***

18 2002_ESG_15_new...templete.doc 2002_ESG 15-new-templete.doc 18

Rev. 0 C ESG( 15 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Decrease generator load by 60 SRO Provide the 1C05 operator with a pre- IPOI 3 Rev 55 Power reduced with Recirc.

MWe. evolution brief prior to reducing reactor Section 2.0 "Precautions Sat Unsat power. and Limitations.

SRO will direct the RO to reduce generator Step 5 Event I load by 60 MWe using the Reactor Recirculation System. Section 3.0" Power Change Guidelines" Step 1 Step 2 RO will reduce generator load by 60 MWe Step 3 using the Recirc System.

"° Reduce Recirc MG Set speed in small Step 5 increments Step 6 Step 79 Step

"* Maintain balanced Recirc loop flows

"* Monitor APRMs, Main Steam Line flow, Section 5.0 "Lowering and Reactor Feedwater flow Seto Power to 5."

35%."

Step 1 Step 2 Step 3 Step 5 2002_ESG_15_new.templete.doc 19

Rev. OC ( ESGQ 15 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Startup of "A" RHRSW/ESW SRO Directs the BOP operator to startup 01-454 Rev 37 "A" ESW and "A" RHRSW pumps. "A"RHRSW and ESW pumps. Section Step 5.0 pumps are running.

Sat Unsat BOP Startup the ESW System per 01-454. 1(a)

Event_2

Start "A" ESW Pump.

2 N/A 3(a)

"* Verify Red running light on (b) 4

"* Verify amps correct 5(a)

"* Verify flow >300 gpm (b) 6

"* Control ESW/RHRSW pit level.

Verify flow greater than 300 gpm.01-416 Rev 26 DFC 18780 in effect.

BOP Startup the "A"RHRSW pump in Section 4.0 accordance with 01-416. Step

"* Place PDIC-2046(1947), RHRSW TO 1 RHR AP controller in MANUAL and 2 CLOSED. 3(a)

"* Start "A"RHRSW pumps. 4 N/A

"* Adjust flow to attain between 2000 and 5 6(a) 2600 gpm. (b) 7(a)

(b) 8 N/A 9

110 2002_ESG_15_new-templete.doc 20

Rev. 0 ( ESG( 15 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Control Rod 18-35 losses SRO Direct the RO to carry out the ARP ARP 1C05A D-6 Rod correctly identified and position indication resulting in a actions for Rod Drift determined not to be rod drift annunciator, moving.

SRO possibly reviews AOP 255.1 for Step 3.1 Abnormal Rod Control And Position Sat Unsat 3.2 Indications.

Event 3 3.3.a SRO may direct the STP for RWM inop to be 3.3.b used.

3.3.c RO perform action lAW ARP 1C05A D-6 for Rod Drift.

AOP 255.1

"* Select the effected rod

"* Verify rod is not drifting

"* Verify rod position is lost at one notch

"* Consult with OSS to substitute rod position

"* Insert rod to check for position The crew may leave the rod at position 18 or return it to position 20 and again substitute the rod position.

BOP possibly be assigned review of AOP 255.1 for abnormal rod control and position indications.

_________________________________ .1.

21 2002_ESG_15_newtemplete.doc 2002_ESGI 5_-new-templete.doc 21

Rev. 0( ( ESG( 15 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Substitute a Rod Position in RO Substitute the rod position per 01 878.8 01 878.8 Rev 15 Rod position correctly RWM Section 8.2 Step 8.2 "Rod Position substituted in the RWM-OD.

Substitution" Sat Unsat

"* Check Mode switch on RWM-CC in 8.2 Event 4 operate (1)

(2)

"* Verify RWM OD is in operate (3)

"* At RWM-OD press ETC key until (4)

SUBSTITUTE OPTION appears (5)

(6)

"* Verify NEW POSITION TO SUBSTITUTE (7) appears

"* Press INCREMENT POSITION or decrement position to select desired position

"* Press ENTER SUBSTITUTE key

"* Press EXIT.

22 2002_ESG_15_newtemplete.doc 2002_E SG_15_.new--templete.doc 22

Rev. ( ESG( 15 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE XFV isolation and LPCI loop BOP Acknowledges annunciator 1C03C D-2, ARP IC03C D-2 select inop EXCESS FLOW CHECK VALVES SYSTEM Step 3.1 Determination of XFV 4642A "B" HI FLOW and responds as directed.

Step 3.2 and what it supplies.

Event 5 At Panel 1C29, monitor excess flow lights to Step 3.3 determine the effected instrument line.

Step 3.4 Sat Unsat Notify the HP office and send an operator Step 4.2 locally to determine the extent of the leak and isolate if possible.

Refer to EFCV Surveillance to determine the Tech Spec.

effects of a closed XFV. 3.3.5.1 Table 1 Function J 3.3.5.1 Condition C If the System "B" instrument excess flow condition renders a system/component inoperative, notify Shift Supervisor and comply with the requirements of DAEC Tech. Specs. Tech Spec determination.

for the effected instrumentation.

SRO will determine that the XFV is Sat Unsat inoperable.

Using Technical Specifications, determine that with LPCI loop select and HPCI both inoperable, 3.5.1 Condition H is a HPCI or LPCI must be restored to operable status possible T.S. call but not within 72 hrs. This is the most conservative call required for this condition and it is expected the OSS would request further and would not be required 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reportable clarificationfor 3.3.5.1 to allow 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . determination.

calling LPCI Subsystem Inop.

Sat Unsat The SRO will determine that an ESF actuation has occurred and a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months notification will need to be performed.

Exact portions of 10 CFR 50.72 and 10 CFR 50.73 need not be identified and the report does not need to be made.

23 2002_ESG_15_newtemplete.doc 2002_ESG-15_new-templete~doc 23

Rev. O ( ESG( 15 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Gr. 3 isolation BOP Perform actions of ARP 1C05B, C-8 ARP IC05B (C-8)

"* Check amber lights on the PCIS Status Rev 16 Recognition of failure Fuel Steps Event 6 board and determine that only a Group 3B Pool Rad Monitor.

3.1 Isolation has occurred. Sat Unsat 3.2

"* Verify completion of the Group 3B 3.3 Isolation. 3.4.a

"* Reopen CV-4371A b

"* Determine the cause of the isolation. C (Fuel Pool Rad Monitor failure) d 3.5

"* The other Fuel Pool Rad monitor and 3.6 N/A other area rad monitors can be checked 3.7. a to verify the instrument has failed. There b would also be several other alarms c indicating an actual rad condition. d N/A Determine fuses F-1 or F-2 3.8 could be the possible cause.

Determine 1C05B has lost RO Determine that 1C05 B (C-8) did not 4.1 Sat Unsat alarm power alarm.

AOP 302.2 Rev 12 Event 7 Perform an alarm test on 1C05 and Immediate Actions determine 1C05 B has lost alarm power Step

Inform the OSS 1 Follow-up Actions

Determine the cause Step 1

"* Locate the alarm panel diagram in the AOP a b

"* Use the diagram to determine likely c cause d

"* Inspect components is the power path 2

"* Replace fuse F2.

When power restored perform annunciator panel check.

w1 Cnl Inov - oo mn rlrm rlI 2002_ESG_15_new-templete.doc isolation is a 4-hour reportable event in 24 accordance with ACP 1402.3.

Rev. K ( ESG( 15 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Grid disturbance/LOOP SRO/BOP AOP 304, Rev 4 Determine loss of 1A3 and Suspend all evolutions in progress perform actions to restore Event 8(M) AOP 301, Rev 34 1A3 with the "A" SBDG.

associated with electrical Switchgear and Immediate Actions Sat Unsat switching operations.

Step 0 Restores power to 1A3 with the A 1 SBDG (SEE EVENT 9) 2

Verify A SBDGs operations as follows: a 3

"* Maintain SBDG volts adjusted to 4 N/A

-4160. 5

"* Maintain SBDG frequency Follow-up Actions adjusted to 60 hertz. Step

"* Verify ESW pumps are running 1 a N/A 0 Verify B SBDGs operations as follows: b

"* Maintain SBDG volts adjusted to c

-4160. d e

"* Maintain SBDG frequency f adjusted to 60 hertz.

g

"* Verify ESW pumps are running h "B"SBDG is not allowed to

BOP determines that the "B" i N/A trip on loss of ESW cooling ESW pump is not running. water.

k

"* Verify SBDG supply fans are I Sat Unsat running

" The crew may try to restore power Local annunciator 1C94 to 1A4 from off-site at this point (A-5) requires securing and it is available. the SBDG if no cooling 25 2002_ESG_15_new..tenaplete.doc 2002_ESG_15_new-templete.doc 25

Rev. ( ( ES(ý 15 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE Restoration of the A EDG BOP Rlestore power to 1A3 with

"* Determines that the EDG did not the "A" SBDG.

Automatically close on to 1A3, and Sat Unsat Event 9 proceeds to the Restoration section of the AOP. (Critical) AOP 301 Rev 34

"* Determine that there is no lock out relay Step tripped. 1

"* Energize 1A3 as follows. 2

"* Transfer switch to Manual. a 1

No EDG lock out trip. 2

No bus lock out. 3

Verify SBDG is running 4 N/A

Insert 'Sync Switch' for 1A311 and turn it 5 on. 6

Re-energize the bus by closing in breaker 7 HS for 1A3 to close. 8

Adjust speed to 60 Hz. 9

Adjust volts to 4160 volts. 10

Turn the 'Sync Switch' off 11

Verify ESW pump is running 12

Verify supply fan running 13

Complete operating checklist.

When the "A" SBDG is supplying 1A3, the crew should secure the "B"SBDG.

Restore bus 1A3 to normal including MCC 1B33 and 1B35 and RPS 26 2002_ESGj5newAemplete.doc 2002_E SGI 5_new-templete.doc 26

Rev. ( ( ES( :15 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE LOOP RO IPOI-5, Rev. Perform IPOI 5 "SCRAM" (Reactor Scram) Step Immediate Actions.

Insert a backup manual scram. 3.2.1 Sat Unsat Event 8(M)

Place the mode switch in SHUTDOWN. 3.2.2 Verify neutron flux decreasing. 3.2.3 Continued *

Control RPV level 170"- 211" 3.2.4

Verify Recirc runback to minimum. 3.2.5

Verify all rods Full-In. 3.2.6

Insert SRMs and IRMs 3.2.7 27 2002_ESG_15_newjemplete.doc 2002_ESG 15_new_templete.doc 27

Rev. O ( ESG( 15 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE EOP 2 SRO EOP 2 Rev. 7 Determine EOP 2 entry on Event 11 is the LOCA " Attempt to maintain DMW temperature < Step Drywell temperature and 150 EOP 1 and 2 entry on DW/T-1 Drywell pressure

" If the D/W cannot be maintained < 150, DW/T-2, & 3.

Event 11(M) then install Defeat 4.

DW/T-4, & 5 Sat Unsat Event 10 is failure of Defeat 4.

Event 10 Defeat 4 Rev 6 Determine Defeat 4 did not

BOP - Determine defeat 4 failed. Step function properly.

1 2 Sat 3 Unsat 4 Failed Initiate Drywell sprays when

"* Before D/W air temDerature reaches PC/P-3 & 4. it is determined drywell 280 deg. F, secure Recirc pumps, and temperature can not be spray the D/W with RHR pumps not maintained below 280OF required for adequate core cooling. (critical)

(Critical)

Sat Before Torus Pressure reaches 11 psig, initiate Torus Spray with RHR pumps not Unsat required for adequate core cooling.

28 2002_ESG_15_newjemplete.doc 2002_ESG 15 new-templete.doc 28

Rev. ( ES(** 15 SCENARIO SEGMENT CREW PERFORMANCE CRITERIA PERFORMANCE COMMENTS REFERENCE LOOP and LOCA SRO EOP-1, Rev.7

"* Recognize EOP-1 entry on DW pressure. Step RC-3

"* Verify Group 1 isolation. Step RC-3

"* Verify Group 3 isolation. Step RC/L-1

"* Restore RPV level 170-211 inches. Step RC/P-1

"* Override CV-4371A Step RC/P-2

"* Verify LLS stabilizes RPV pressure.

29 2002_ESG_15_newjemplete.doc 2002_ESG- 15 new-templete. doe 29

CREW GRADING ATTACHMENT ESG ILC 15 Rev. 0 Operator Name Position Evaluator Shift Manager Shift Supervisor STA Reactor Operator 1st Assistant B.O.P. 1st Assistant Management Representative/Lead Evaluator Crew Critical Tasks Task Statement SAT UNSAT

1. With electric power available but not supplying EOP required equipment, take manual actions to restore power to systems required to perform EOP actions.

2. While in the safe region of the drywell spray initiation limit, and before drywell temperature reaches 280 OF, initiate drywell sprays.

3.

4.

5.

6.

Individual Competency Identifiers 1.

2.

3.

Attach to crew grading worksheet, OTI-105, Attachment 12 when complete.

2002_ESG 15_newtemplete.doc Page 31 of 33

Rev. 0 ESG ILC 15 OSG VALIDATION CHECKLIST Scenario # ESG ILC 15 Rev. 0 1 Verify that if not run from a protected IC that setup information is provided to reproduce the stated initial conditions.

2 _ Verify that all stated objectives are identified in the body of the OSG.

3 Verify that turn over sheets are completed, and are in agreement with both the narrative summary and shift turnover information sheet. Turn over sheets are not required for initial license scenarios.

4 _ Verify that if the scenario requires documents to be provided to the crew, that they are filled out as appropriate (i.e., if an STP is used, it is filled out).

5 If this is the initial validation or the revision affects ramp times, event triggers, malfunctions, overrides, remote functions or procedure changes could affect the scenario, then validate the scenario for proper response using a crew. It is preferable to use a crew unfamiliar with the scenario whenever possible. Verify the following while running the scenario:

"* The scenario runs as written and all tasks are performed.

"* The stated time line agrees with actual times.

"* Critical task statements clearly define the expected plant and student response.

They should also be written so that they are achievable as written. If any question exists, it is preferable to have operations management participate in the validation.

"* Anticipated instructor role play/cues are identified

Management expectations are captured and re-enforced.

"* Verify administrative documentation requirements (i.e., CMARs /ARs) are identified.

"* Verify reportability requirements (i.e., ESF actuations) are identified.

"* Verify Technical Specification items / LCO declarations are correct.

"* if procedure steps may cause confusion or disagreement between higher-level procedures and Ols/ARPs that operations management is consulted.

6 Shutdown scenarios include shutdown risk assessment, time to boil calculations, and shutdown status board information.

SME/Instructor Date SME/Instructor Date SME/Instructor Date 2002_ESG 15_newtemplete.doc Page 32 of 33

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