ML030410163

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Initial Submittal of the Scenarios for the Monticello Initial Examination - Oct. 2002
ML030410163
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 10/14/2002
From: Engen M
Nuclear Management Co
To:
Office of Nuclear Reactor Regulation
References
50-263/02-301, ES-D-1 50-263/02-301
Download: ML030410163 (56)
v • d • e


Text

INITIAL SUBMITTAL OF THE SCENARIOS FOR THE MONTICELLO INITIAL EXAMINATION - OCT 2002

Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No. #2 Op-Test No: 02-01 Examiners: Operators:

Initial Conditions: The plant is at 100% power. RCIC surveillance is being completed for PMT.

The "B" CRD FCV is out of service to repair an air line leak. No. 11 and No 12 RHR pumps and No. 11 and No 12 RHRSW pumps are in service for Torus cooling; and LPCI LCO has been entered. All other systems are normal.

Turnover: Complete RCIC surveillance.

Event Malf. Event Event No. No. Type* Description 01 BOP-N Secure from RCIC Surveillance 02 BOP-C Trip of No. 11 RHR Pump.

03 RO-C CRD Pump Failure 04 BOP-I Hydrogen Cooler Water Controller fails partially closed 05 RO-C Leak into RBCCW from RWCU causing the manual isolation of RWCU.

06 RO-R Loss of No. 11 Condensate Pump with loss of Bus 13 causing loss of No. 11 Circ Water Pump. Essential bus 15 will automatically transfer to the 1AR. No. 11 Feed Pump also trips.

07 M Loss of No. 12 Condensate Pump causes loss of No. 12 Feed Pump with loss of feed and reactor scram with ATWS.

08 C "A" CRD FCV fails closed.

09 RO-C Selected SBLC Pump fails to start, and other SBLC must be started.

t 1-I +

I 1 1-A .. L

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 1 Page 1 of 1 Event

Description:

SECURE FROM RCIC SURVEILLANCE (0255-08-lA-1)

Actions or Behavior

1. Declare RCIC inoperable per Technical specification 3.5.D
2. Direct BOP to continue with RCIC test at step 49.

iort that RCIC Surveillance is complete.

toring parameters and may act as peer checker.

I BOP Refer to 0255-08-IA-1, "RCIC SYSTEM PUMP FLOW AND VALVE TESTS".

1. Record present time - hour & minute.
2. Place RCIC FC-13-91 in AUTO.
3. Reduce flow to approximately 200 GPM. (FC-13-91 manual speed control knob)
4. Depress the RCIC Turbine Trip push button (13A-S 17).
5. Record present time - hour & minute.
6. Adjust RCIC flow controller setpoint to 80%. (FC-13-91 automatic thumbwheel)
7. Direct the RBO to locally verify MO-2080 RCIC Turbine Trip Reset Motor (HO-7) is CLOSED.

BOP Report to SRO that RCIC surveillance is complete.

Notes:

Page 1 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 2 Page 1 of 1 Event

Description:

  1. 11 RHR PUMP TRIP Time Position Actions or Behavior SRO Acknowledge report of annunciator 3-A-42 "RHR PUMP 11 LOCKOUT" SRO 1. Refer to Technical Specification 3.5.A.3.b
2. Declare RHR Pump 11 inoperable.
3. Determine 30 day LCO exists.

SRO Acknowledge actions taken by BOP Operator for trip of No. 11 RHR Pump.

RO Monitors plant parameters.

BOP 1. Acknowledge annunciator 3-A-42 "RHR PUMP 11 LOCKOUT"

2. Consult ARP 3-A-42
3. Notify Shift Supervision & System Engineer BOP 1. Verify No. 11 RHR Pump has tripped.
2. Place the handswitch for 11 RHR Pump in PULL-TO-LOCK
3. Reduce flow to within system requirements BOP Reports actions taken for trip of No. I1 RHR Pump to SRO.

Notes:

Page 2 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 3 Page 1 of 1 Event

Description:

CRD PUMP FAILURE Time Position Actions or Behavior SRO 1. Enter C.4-B.01.03.A "LOSS OF CRD PUMP FLOW"

2. Verify #12 CRD Pump is running
3. Notify Shift Supervision and System Engineer
4. Dispatch TBO to ACB-152-506 to investigate cause of the trip.

SRO Acknowledge report of actions taken by RO.

RO 1. Acknowledge annunciators:

"* 5-B CHARGING WATER LOW PRESSURE

"* 5-B CRD PUMP 3-16A BREAKER TRIPPED

"* 5-B CRD PUMP 3-16A OL

2. Verify # 11 CRD Pump has tripped.

"* #11 CRD Pump Breaker indication on CO5. (Green lamp ON, Red lamp OFF)

"*CRDH system flow and pump discharge pressure has decreased to 0 as indicated on:

a. PI-3-302 Charging Water Header Pressure. (C05)
b. FI-3-306 Cooling Water Header Flow (C05)

RO 1. Start #12 CRD Pump. (HS-3 B-S4B to START)

2. Verify #12 CRD Pump Starts

(#12 CRD Pump breaker indication - Green lamp OFF, Red lamp ON)

(PI-3-302 Charging Water Header Pressure - C05)

(FI-3-306 Cooling Water Header Flow - C05)

3. Monitor and Control system pressures and flows.
4. Verify required action per C.4-B.01.03.A, LOSS OF CRD PUMP FLOW, are complete.

RO Report actions taken for trip of CRD Pump to SRO.

BOP Monitor plant parameters.

Notes:

Page 3 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 4 Page 1 of I Event

Description:

HYDROGEN WATER COOLER CONTROLLER FAILURE (TC-1589)

Time Position Actions or Behavior SRO Acknowledge report of 8-A-22, "NO 1 GEN H2 SYSTEM TROUBLE".

SRO Acknowledge report of actions taken by BOP Operator.

RO Monitor plant parameters.

BOP 1. Acknowledge annunciator 8-A-22 NO 1 GEN H2 SYSTEM TROUBLE

2. Consult ARP 8-A-22
3. Direct TBO to determine alarm window from C83B Note: Simulator Communicator reports back after 2 minutes that alarm 83-B-3, MACHINE GAS TEMP HIGH, is in alarm on the local panel.

BOP 1. Consult ARP 83-B-3, "MACHINE GAS TEMP HIGH".

2. Acknowledge computer alarms GEN116 - 119 "GEN COLD GAS AFTER CLR 1 - 4".
3. Direct the TBO to monitor and report indications on:
  • TIS-7171 MACHINE GAS TEMP
  • TIS-7172 ALTERNATOR AIR TEMP BOP I. Determine TC-1589 GEN H2 COOLING WATER TEMPERATURE CONTROLLER (C08) is malfunctioning.
2. Place TC-1589 in MANUAL and THROTTLE OPEN CV-1589 to maintain temperature < 51 deg C.
3. Direct the TBO to verify system integrity.
4. Direct the TBO to vent all Hydrogen Coolers.

BOP Report actions taken to SRO Notes:

Page 4 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 5 Page 1 of 2 Event

Description:

LEAK INTO RBCCW REQUIRING MANUAL ISOLATION Time Position Actions or Behavior SRO Notify Shift Supervision SRO Acknowledge report of 6-B-27 "RBCCW SURGE TK T-3 HIGH-LOW LEVEL" SRO 1. Enter C.4-B.02.05.B "LEAK INTO RBCCW"

2. Direct RBO to verify closed DM-1 11 "RBCCW Surge Tk Demin Wtr Makeup".
3. Verify Recirculation Pump Seal pressures are unchanged.
4. Notify Plant Chemist to sample RBCCW.

Note: Simulator Communicator reports after 2 minutes that DM-1 11 is CLOSED.

SRO 1. Determine the Recirculation System is NOT the source of the leak.

2. Enter B.02.02-05.F.1 - REACTOR WATER CLEANUP SYSTEM SHUTDOWN.
3. Direct that RWCU be shutdown and depressurized.
4. Review Precautions and Limitations.

SRO Acknowledges report of RWCU isolation.

RO 1. Acknowledge annunciator 6-B-27 RBCCW SURGE TK T-3 HIGH-LOW LEVEL

2. Consult ARP 6-B-27
3. Report annunciator to SRO RO 1. Direct RBO to verify level in the RBCCW Surge Tank.

RBO: After approx. 2 minutes report that RBCCW Surge Tank level is 6'4" and has increased 5" since the last round, which was 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.

RO Direct RBO to remove both RWCU Filter Demineralizers from service.

Notes:

Page 5 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 5 Page 2 of 2 Event

Description:

LEAK INTO RBCCW REQUIRING MANUAL ISOLATION Time Position Actions or Behavior RO NOTE: Steps below are directed from B.02.02-05.F. 1 - RWCU SYSTEM SHUTDOWN.

I. CLOSE MO-2397 RWCU INLET INBOARD ISO (HS-16A-S15) C04

2. CLOSE MO-2399 RWCU RETURN ISO (HS-16A-17) C04
3. Determine MO-2398 is not required to be closed since MO-2397 is full closed.
4. OPEN MO-2400 FILTER DEMINERALIZER BYPASS (HS-12A-S4) C04
5. OPEN MO-2404 RWCU DUMP TO HOTWELL (HS-12A-S2) C04
6. Slowly OPEN CV-2403 DUMP FLOW (FC-12-143) C04 RO NOTE: Steps below are directed from B.02.02-05.F.1 - RWCU SYSTEM SHUTDOWN.
1. Determine RWCU is depressurized (PI-12-131) C04
2. CLOSE CV-2403 DUMP FLOW (FC-12-143) C04
3. CLOSE MO-2404 RWCU DUMP TO HOTWELL (HS-12A-S2) C04
4. CLOSE MO-2400 FILTER DEMINERALIZERB/P (HS-12A-S4) C04 RO NOTE: Steps below are directed from C.4-B.02.05.B "LEAK INTO RBCCW".
1. CLOSE MO-3501 RWCU NRHX RBCCW OUT (HS-3501) C04
2. Direct the RBO to CLOSE RBCC-33 NRHX CLG WTR INL.

Note: Simulator Communicator reports back after 2 minutes that RBCC-33 is CLOSED.

RO Monitors RBCCW to determine if leak has stopped.

Note: Simulator Communicator reports to Control Room that RBCCW surge tank level has stopped increasing.

RO Reports to SRO that RWCU has been isolated and it appears that leak has been stopped.

BOP Monitors plant parameters Notes:

Page 6 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 6 Page 1 of 5 Event

Description:

  1. 11 CONDENSATE PUMP TRIP & 4160V BUS #13 LOCKOUT Time Position Actions or Behavior CREW 1. Numerous annunciators alarm. Annunciators specific to this event:
  • 6-A-8 COND PUMP P-IA TRIP
  • 6-A-33 CONDENSATE PUMP LOW DISCH PRESS
  • 8-B- 11 NO 13 4160V BUS LOCKOUT
2. Consult ARP's 6-A-8, 6-A-33, 8-B-I 1 SRO May Announce now entering "Transient Annunciator Response" SRO 1. Enter C.4.F - RAPID POWER REDUCTION
2. Direct RO to reduce Recirculation flow as necessary to maintain RPV level (or similar command - i.e. reduce RR flow to minimum).

NOTE: #11 Feed Pump will probably trip due to suction pressure <70 psig for 10 seconds unless RR flow is quickly decreased.

SRO 1. Determine if core flow is <26 Mlbm/hr.

2. If core flow is <26 Mlbmihr then enter C.4.B.05.01.02.A - CONTROL OF NEUTRON FLUX OSCILLATIONS concurrently.

SRO C.4-B.06.03.A - DECREASING CONDENSER VACUUM 0 Monitor LP Turbine exhaust pressures per SPDS 656.

NOTE: Further action will not be required as condenser vacuum will quickly recover.

RO I. Determine #11 Condensate Pump has tripped using indications below:

"* (Breaker indication C06 -Green lamp ON, Red lamp OFF).

"* Condensate Pump discharge pressure (PI-1289 - C06).

"* Condensate Header Flow (FI-1095A - C06)

2. Notify Shift Supervision Page 7 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 6 Page 2 of 5 Event

Description:

  1. 11 CONDENSATE PUMP TRIP & 4160V BUS #13 LOCKOUT Time Position Actions or Behavior RO Manually reduce Recirculation flow as directed. (Place HS 2A-S 18A & 2A-S 18B to LOWER - C04)

RO Per ARP 6-A-8 COND PUMP P-lA TRIP

  • Verify Reactor Feed Pump suction pressure is >70 psig.

(PI-1120 & PI- 1121 - C06)

Per ARP 6-A-33 CONDENSATE PUMP LOW DISCH PRESS)

"* Verify adequate Hotwell Level.

(LR-1278 - C06)

"* Monitor Reactor Feed Pump suction pressure and flow.

(PI-I 120 & PI-I 121 RFP suction pressure - C06)

(FI-6-89A & FI-6-89B Feedwater flow A & B - CO5)

"* Verify Condensate discharge pressure is >230 psig.

(PI-1289 Condensate discharge pressure - C06)

RO Per ARP 6-A-6 RCT FEED PUMP P-2A TRIP

"* Verify CV-3489 Recirc valve closes after 50 sec.

(CV-3489 lamp indication - C06)

"* Enter C.4-B.6.5.A - FEEDWATER PUMP TRIP RO Per C.4-B.6.5.A - FEEDWATER PUMP TRIP

"* Verify RPV water level is being controlled +9 to +48 inches.

(Feedwater and Safeguards RPV level meters - CO5)

"* Verify #111 RFP Aux Oil Pump is running.

(#1 1 Aux Oil Pump Bkr ind Red ON, Green OFF - C06)

RO Per C.4-B.09.06,B - LOSS OF BUS 13 OR BUS 14:

  • Monitor and control Reactor water level between +30 and +40 inches.

Notes:

Page 8 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 6 Page 3 of 5 Event

Description:

  1. 11 CONDENSATE PUMP TRIP & 4160V BUS #13 LOCKOUT Time Position Actions or Behavior RO Per C.4-B.01.03.A - LOSS OF CRD PUMP FLOW Verify #12 CRD Pump is operating.

(#12 CRD Pump breaker indication - Green lamp OFF, Red lamp ON)

(PI-3-302 Charging Water Header Pressure - CO5)

(FI-3-306 Cooling Water Header Flow - CO5)

BOP Determine #13 4160V bus lockout has occurred.

BOP 1. Enter the following procedure:

  • C.4-B.09.06.B - LOSS OF BUS 13 OR BUS 14
2. Enter the following procedures (directed by C.4-B.09.06.B - LOSS OF BUS 13 OR BUS 14):

"* C.4-B.01.03.A - LOSS OF CRD PUMP FLOW

"* C.4-B.06.04.A - DECREASED CIRCULATING WATER FLOW

"* C.4-B.06.03.A - DECREASING CONDENSER VACUUM

"* C.4-B.09.06.C - LOSS OF BUS 15 OR BUS 16

"* C.4-B.09.07.A - LOSS OF POWER TO LC-101 OR ITS MCC'S

"* C.4-B.09.07.C - LOSS OF POWER TO LC-103 OR ITS MCC'S

"* C.4-B.09.07.E - LOSS OF POWER TO LC-107 OR MCC-1 14

"* C.4-B.09.07.G - LOSS OF POWER TO LC-109 OR ITS MCC'S Notes:

Page 9 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 6 Page 4 of 5 Event

Description:

  1. 11 CONDENSATE PUMP TRIP & 4160V BUS #13 LOCKOUT Time Position Actions or Behavior BOP Per ARP 8-B- 11 NO 13 4160V BUS LOCKOUT

"* Verify # 15 4160V bus has transferred to 1AR.

(152-511 breaker indication - Red OFF, Green ON - C08)

(#15 bus voltage indication - C08)

"* Verify #11 & #12 Emergency Diesel Generators have started.

(#1I1 & #12 EDG voltage indication - C08)

"* Verify LC-107 transfer to LC-108.

BOP Per C.4-B.09.06.B - LOSS OF BUS 13 OR BUS 14:

"* OPEN ACB 52-901 (52-901/CS - CO8)

"* Place 52-901/SS SYNC 109 CTR SEC ACB to ON - CO8

"* CLOSE ACB 52-908 109/102 LOAD CTR TIE ACB (52-908/CS - C08)

"* Verify MO-1850 "11 Cir Wtr Pump P-100 Discharge Valve" has closed. (Bkr indicating lamps - C06)

NOTE: MO-1850 will begin to automatically close when power is restored to LC-109.

BOP C.4-B.06.04.A - DECREASED CIRCULATING WATER FLOW

  • Place #11 Circulating Water Pump control switch to STOP.

(152-305/CS - C06)

BOP C.4-B.09.06.C - LOSS OF BUS 15 OR BUS 16

"* Determine that Bus 15 is being powered by IAR.

(152-511 breaker indication - Red OFF, Green ON - C08)

(#15 bus voltage indication - C08)

"* Consider shutdown of #11 & #12 Emergency Diesel Generators.

Notes:

Page 10 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 6 Page 5 of 5 Event

Description:

  1. 11 CONDENSATE PUMP TRIP & 4160V BUS #13 LOCKOUT Time Position Actions or Behavior BOP C.4-B.09.07.A - LOSS OF POWER TO LC-101 OR ITS MCC'S
  • No action required - LC-101 re-powered automatically.

BOP C.4-B.09.07.C - LOSS OF POWER TO LC-103 OR ITS MCC'S

BOP C.4-B.09.071E - LOSS OF POWER TO LC-107 OR MCC-1 14

  • Determine crosstie between LC-107 and LC-108 is closed.

(Indicated by control room lighting restored)

BOP C.4-B.09.07.G - LOSS OF POWER TO LC-109 OR ITS MCC'S

  • No action required - LC-109 re-powered when breaker 52-908 was closed.

Notes:

Page 11 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 SOp-Test No. Scenario No. 2 Event No. 7-9 Page 1 of 10 Event

Description:

No. 12 Condensate Pump Trip, No. 12 RFP Trip, Scram, ATWS, Time Position Actions or Behavior SRO Acknowledge report of 6-A-9, "COND PUMP P-lB TRIP" SRO NOTE: C.4.K actions may not be performed if RPV water level is decreasing quickly.

1. Per C.4.K - IMMEDIATE REACTOR SHUTDOWN
  • Direct the Reactor Operator to reduce Recirculation flow to minimum.

SDirect the Reactor Operator to manually scram the reactor SRO Enter: C.5-1 100 RPV CONTROL (Entry Condition - Reactor power above 3% when scram required.

1. Verify Reactor Scram has been initiated.
2. Determine all rods ARE NOT in to at least 04.
3. Determine the reactor WILL NOT stay shutdown under all conditions without boron.
4. Leave C.5-1 100 and Enter C.5-2007 SRO Enter C.5-2007 FAILURE TO SCRAM
1. Direct the BOP operator to inhibit ADS Critical 2. Direct the BOP operator to prevent Core Spray injection per C.5-3205.

Step SRO POWER LEG:

1. Verify Mode switch in SHUTDOWN
2. Determine Main Turbine IS NOT on line
3. Direct RO to actuate ATWS SRO 1. Direct RO to insert control rods per C.5-3101 - ALTERNATE ROD INSERTION.

Page 12 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 7-9 Page 2 of 10 Event

Description:

No. 12 Condensate Pump Trip, No. 12 RFP Trip, Scram, ATWS, Time Position Actions or Behavior SRO 1. Determine Torus Temperature will reach 110 'F.

Critical Step 2. Direct RO to inject SBLC SRO PRESSURE LEG

1. Determine Drywell pressure is < 2 psig.
2. Consider opening MSIVs per C.5-3301 if personnel available.
3. Determine SRVs are not rapidly cycling.
4. Consider LO-LO SET can stabilize RPV pressure.

SRO LEVEL LEG

1. Check Detail 'A' for instrument limits.
2. Determine no instrument limits have been exceeded.
3. Determine:
  • Reactor power above 3%
  • Torus temperature above I 10 'F.
  • RPV water level >- 126 inches
4. Determine MSIVs are CLOSED.

Critical 5. Direct BOP operator to Terminate and Prevent HPCI & LPCI per C.5-3205 Step TERMINATE AND PREVENT.

SRO I. Determine Reactor power is < 3%.

2. Record final RPV level on line 2.
3. Direct that RPV level be maintained between -149 inches and value recorded on line 2 with RCIC & HPCI.
4. Verify instrument limits are satisfactory Notes:

Page 13 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2

. Op-Test No. Scenario No. 2 Event No. 7-9 Page 3 of 10 Event

Description:

No. 12 Condensate Pump Trip, No. 12 RFP Trip, Scram, ATWS, Time Position Actions or Behavior SRO Enter C.5-1200 PRIMARY CONTAINMENT CONTROL (90 'F Torus Temperature)

TORUS TEMPERATURE STEPS I. Determine Torus temperature cannot be maintained < 90 'F.

2. Direct BOP operator to start all available torus cooling.
3. Recognize Torus Temperature will reach 110 'F.
4. Enter C.5-1 100 - RPV CONTROL
5. Verify Reactor scram has occurred.
6. Determine Torus temperature can be maintained below fig M, HEAT CAPACITY LIMIT. (SPDS 78)

SRO DRYWELL TEMPERATURE STEPS

1. Monitor and maintain drywell temperature < 135 'F.

NOTE: No further action should be necessary SRO DRYWELLITORUS PRESSURE STEPS

1. Monitor and maintain drywell and torus pressure < 2 psig.

NOTE: No further action should be necessary SRO TORUS LEVEL STEPS I. Monitor and maintain Torus level - 4.0 inches to +3.0 inches.

NOTE: No further action should be necessary SRO HYDROGEN CONTROL STEPS

1. Direct BOP operator to perform procedure C.5-3501 -H2/02 ANALYZER OPERATION, as time permits.

Page 14 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 7-9 Page 4 of 10 Event

Description:

No. 12 Condensate Pump Trip, No. 12 RFP Trip, Scram, ATWS, Time Position Actions or Behavior RO 1. Acknowledge annunciator 6-A-9 "COND PUMP P-I1B TRIP"

2. Determine #12 Condensate Pump has tripped using indications below:
  • (Breaker indication C06 -Green lamp ON, Red lamp OFF).
  • Condensate Pump discharge pressure (PI-1289 - C06).
  • Condensate Header Flow (Fl-I 095A - C06)
3. Notify Shift Supervision RO 1. Acknowledge annunciator 6-A RCT FEED PUMP P-2B TRIP
2. Determine #12 Reactor Feed Pump has tripped using indications below:
  • (Breaker indication C06 -Green lamp ON, Red lamp OFF).
  • Feed Pump discharge pressure (PI-i1131 - C06).
  • Reactor Feed Flow (FI-6-89A & FI-6-89B - C05)
3. Enter C.4-B.06.05.A - FEEDWATER PUMP TRIP
  • Verify no Condensate Pumps are operating.
  • Verify no Reactor Feed Pump suction pressure.
4. Determine neither Feed Water Pump is available.

RO 1. Depress REACTOR SCRAM A and B pushbuttons.

(5A-S3A and 5A-S3B)

2. Recognize control rods are NOT inserted to or beyond position 04.

(Full Core Display - C05)

(RWM displays - All rods not in)

(Reactor Steam flow - Turbine on line)

3. Place the reactor mode switch in SHUTDOWN.
4. Notify Shift Supervision Notes:

Page 15 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 7-9 Page 5 of 10 Event

Description:

No. 12 Condensate Pump Trip, No. 12 RFP Trip, Scram, ATWS, Time Position Actions or Behavior RO 1. Locate procedure B.05.06 ATWS SYSTEM MANUAL INITIATION (hard card)

2. SET the arming collars of one pair of the following switches to the armed position and depress the pushbuttons

"* ATWS A MAN and ATWS C MAN (PB S-5A & S-5C) (CO5)

OR

"* ATWS B MAN and ATWS D MAN (PB S-5B & S-5D) (CO5)

3. Verify Recirc Pump MG Set generator field breakers have tripped.

(Field breaker indicating lights - C04)

4. Trip the MG set drive motors.
  • Place HS 2A-S 1A to STOP (#11 MG set drive motor breaker)
  • Place HS 2A-S I B to STOP (# 12 MG set drive motor breaker)
5. Determine Control Rods DO NOT insert.

RO 1. Locate procedure C.5-3101 - ALTERNATE ROD INSERTION.

2. Determine Part C is appropriate.
3. Determine prerequisites are met:
  • CRD pump available (Breaker indication CO5)
  • Instrument air available (PI-1476 - C06 or PR- 1176 - C07)
  • Reactor Building accessible.
4. Place the RWM Owner Display Keylock Switch in BYPASS.
5. Verify #12 CRD Pump is operating.
6. Place FC-301 - CRD FLOW CONTROL STATION in MANUAL. (C05)

NOTE: The following step will alert the RO to the CRD Flow Control Valve failure - Event 8 (CRD FCV Failure).

7. ADJUST FC-301 to 100%.
8. Determine "A" CRD FLOW CONTROL VALVE CV-3-19A did not open.

(Indicating lights, Green - ON, Red - OFF - CO5)

(PI-3-302 Charging Water Header Pressure - CO5)

(FI-3-306 Cooling Water Header Flow - CO5)

Page 16 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 7-9 Page 6 of 10 Event

Description:

No. 12 Condensate Pump Trip, No. 12 RFP Trip, Scram, ATWS, Time Position Actions or Behavior RO Locate procedure C.5-3 101 (cont'd)

NOTE: Part C will work until 5% reactor power is reached, then the CRD FCV fails closed.

9. Determine Part C will not work to insert control rods.
10. Notify SS that part C did not work due to CRD Flow Control Valve problem.

RO 1. Determine C.5-3 101 Part D is appropriate.

2. Determine prerequisites are met:

I1 division of RPS power available

  • Instrument Air available (PI-1476 - CO6 or PR-1 176 - C07)
  • RPV pressure >100 psig (PI-6-90A & PI-6-90B - CO5)
3. ANNOUNCE over plant PA to evacuate personnel from the Reactor Building 896 ft. Floor and Equipment Drain Tank Room.
4. Depress the ATWS reset PB for the ATWS division actuated earlier.

"* ATWS A MAN and ATWS C MAN (PB S-4A) (C05)

OR

"* ATWS B MAN and ATWS D MAN (PB S-4B) (C05)

5. Determine ATWS cannot be reset.

(5-A ATWS CHANNEL A TRIP does not clear)

(5-A ATWS CHANNEL B TRIP does not clear)

6. Direct RBO to:
  • OPEN D-21 Circuit 6 (125V div. 2)
  • OPEN D-I 1, Circuit 5 (125V div. 1)
7. Determine scram cannot be reset.
8. BYPASS all automatic scram signals;
  • Simulate hanging jumpers -Notify Sim Operator which bypass needs to be installed.

Page 17 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 7-9 Page 7 of 10 Event

Description:

No. 12 Condensate Pump Trip, No. 12 RFP Trip, Scram, ATWS, Time Position Actions or Behavior RO C.5-3 101 Part D steps (cont'd)

9. RESET the scram using the SCRAM LOGIC RESET switch (5A-$9 - CO5)
10. Direct RBO to verify OPEN CRD-14.

Note: Simulator Communicator reports back after 2 minutes that CRD-14 is CLOSED.

11. Verify OPEN SDV vent & drain valves. (light indication C05)
12. Determine 5-B-21 DISCH VOLUME WATER LEVEL SCRAM TRIP is reset.

NOTE: Steps 13 & 14 may be performed concurrently.

13. CLOSE SDV vent & drain valves. (HS 5A-S I1- CO5)
14. Depress both manual scram pushbuttons (5A-S3A & 5A-S3B C05)
15. Notify SS that Part D was not successful.

RO 1. Place SLC system selector switch to SYS 1. (HS 11 A-S 1 CO5)

2. Determine System 1 SBLC did not actuate.
  • System 1 SBLC Pump breaker indication - (Green ON, Red OFF CO5)
  • SBLC DISCHARGE PRESSURE reads 0. (PI-1 1-65 C05)

RO 3. Place SLC system selector switch to SYS 2. (HS 1 A-S 1 CO5)

Critical Step 4. Verify system 2 SBLC did actuate.

  • System 2 SBLC Pump breaker indication- (Green OFF, Red ON CO5)
  • SBLC DISCHARGE PRESSURE reads slightly higher than reactor vessel pressure. (PI-11-65 C05)
  • SBLC tank level decreasing. (LI-I 1-66)
5. Review procedure B.03.05 MANUAL INITIATION, as time permits.

Notes:

Page 18 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 7-9 Page 8 of 10 Event

Description:

No. 12 Condensate Pump Trip, No. 12 RFP Trip, Scram, ATWS, Time Position Actions or Behavior BOP 1. Place switches 2E-S7A & 2E-S7B on C03 to INHIBIT, Critical Step BOP 1. Locate part A (Core Spray) of C.5-3205 - TERMINATE AND PREVENT.

Critical Step 2. Place MO-1751 CS INJECTION BYPASS handswitch in BYPASS.

(14A-S 16A - C03)

3. CLOSE MO-1751, CS INJECTION OUTBOARD (HS 14A-S2A - C03)
4. Place No 11 CORE SPRAY PUMP handswitch in PULL-TO-LOCK (HS 14A-S5A - C03)
5. Place MO-1752 CS INJECTION BYPASS handswitch in BYPASS.

(14A-S16B - C03)

6. CLOSE MO-1752, CS INJECTION OUTBOARD (HS 14A-S2B - C03)
7. Place No 12 CORE SPRAY PUMP handswitch in PULL-TO-LOCK (HS 14A-S5B - C03)

Notes:

Page 19 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No, Scenario No. 2 Event No. 7-9 Page 9 of 10 Event

Description:

No. 12 Condensate Pump Trip, No. 12 RFP Trip, Scram, ATWS, Time Position Actions or Behavior BOP 1. Locate procedure C.5-3205 TERMINATE AND PREVENT parts B & C.

Critical Step Part B

2. OPEN knife switch I OA-S3 IA (C03)
3. OPEN knife switch IOA-S3IB (C03)
4. CLOSE MO-2012 (HS IOA-SIOA C03)
5. CLOSE MO-2013 (HS I0A-SIOB C03)

Part C

1. Determine HPCI is operating.
2. Depress and hold the TURBINE TRIP pushbutton (PB 23A-S22)
3. Verify HPCI has stopped. (SI-7317 HPCI speed C03)
4. Place AUX OIL PUMP in PULL-TO-LOCK. (HS 23A-S17)
5. Wait approximately 5 seconds after AUX OIL PUMP in placed PULL-TO-LOCK then release the HPCI TURBINE TRIP pushbutton.
6. Verify HO-7 CLOSED. (lamp indication C03)

BOP I. Locate procedure C.5-3205

2. Place HPCI AUX OIL PUMP handswitch to AUTO. (HS 23A-S17)

BOP Place Div. I Torus Cooling in service:

1. Locate B.03.04-05.H.5 (Hardcard)
2. Perform steps 1 thru 9 of B.03.04-05.H.5.

Notes:

Page 20 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Op-Test No. Scenario No. 2 Event No. 7-9 Page 10 of 10 Event

Description:

No. 12 Condensate Pump Trip, No. 12 RFP Trip, Scram, ATWS, Time Position Actions or Behavior BOP Place Div. 2 Torus Cooling in service:

1. Locate B.03.04-05.H.6 (Hardcard)
2. Perform steps 1 thru 9 of B.03.04-05.H.6.

BOP 1. Locate C.5-3501 - H2/02 ANALYZER OPERATION

2. Perform steps I thru 14 of C.5-3501 (see attachment 1 for steps).

Notes:

Page 21 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Termination Point:

"* Reactor power <3%

"* RPV Level stabilized Classification:

Alert - Guideline 4 Page 22 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Attachment 1, C.5-3501 MONTICELLO NUCLEAR GENERA TING PLANT Ops Man C.5-3501 Revision 0 Page 2 of 4 PURPOSE This procedure provides instructions to place the H2/02 analyzers in service. This procedure should only be entered as directed by Emergency Operating Procedures.

EQUIPMENT None PRECAUTIONS None PREREQUISITES

1. Primary Containment temperature less than 280 0 F.

OPERATOR ACTIONS GENERAL NOTES:

1. Procedure written is typical for placing one analyzer in service. Both analyzers should be placed in service simultaneously, one sampling the Torus, the other the Drywell.
2. This procedure should be performed as soon as support personnel (Operation or I&C) are available.

-9 smr Page 23 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Attachment 1, C.5-3501 MONTICELLO NUCLEAR GENERATING PLANT Ops Man C.5-3501 Revision 0 Page 3 of 4

3. When analyzers have stabilized, recorder readings may oscillate approximately 2% peak to peak.
1. IF a Group 2 isolation exists, THEN place INBD H2/02 VALVES CLOSE/ISOL BYPASS switch, AND OTBD H2/02 VALVES CLOSE/ISOL BYPASS switch to ISOL BYPASS.
2. NOTE: The sample return valves OPEN automatically when Drywell or Torus sample valves are opened.

OPEN selected Inboard and Outboard sample valves.

3. Verify one H2/02 analyzer is selected to sample the Torus and the other is selected to sample the Drywell.
4. Place ANALYZER MODE SWITCHs to ANALYZE.
5. Depress REMOTE SELECTOR pushbuttons to take control at Control Room.
6. Place FUNCTION SELECTORs to ZERO.
7. Verify 02 DUAL RANGE SWs on 0-25% range.
8. Verify H2 DUAL RANGE SWs on 0-20% range.
9. Place chart recorders ON.

smr Page 24 of 25

NRC SIMULATOR EXAMINATION SCENARIO NO. 2 Attachment 1, C.5-3501 MONTICELLO NUCLEAR GENERATING PLANT Ops Man C.5-3501 Revision 0 Page 4 of 4

-> 10. WHEN analyzers have stabilized, THEN verify 02 concentrations are between 1/8 in. to the left of 0.0% and 1.0%,

AND verify H2 concentrations are between 1/8 in. to the left of 0.0% and 1.0%.

a. IF the 02 or H2 concentrations are not within their prescribed range for the ZERO modes, THEN notify I&C to calibrate.
11. Place FUNCTION SELECTORs to SPAN.
12. WHEN analyzers have stabilized, THEN verify 02 concentrations are between 19.0% and 21.0%,

AND verify H2 concentrations are between 17.0% and 19.0%.

a. IF the 02 or H2 concentrations are not within their prescribed range for the SPAN modes, THEN notify I&C to calibrate.
13. Place FUNCTION SELECTORs to SAMPLE.
14. Select appropriate ranges for sample conditions.

smr Page 25 of 25

Appendix D Scenario Outline Form ES-D-1 Facility: Monticello Scenario No. #3 Op-Test No: 02-01 Examiners: Operators:

Initial Conditions: The plant is approximately 18% power. The Main Turbine has been placed on-line and the next step is to place the Main Turbine Generator in service. Ops Man C.1 is complete through step VI.C.4. No. 12 Reactor Feedpump is out of service, but should be returned to service in time to support power increase. No. 13 Service Water Pump is out of service to repair coupling.

Turnover: Place Main Turbine Generator in service and continue power increase.

Event Malf. Event Event No. No. Type* Description 01 BOP-N Synchronize Main Generator to the Grid 02 RO-R Increase power by pulling rods 03 BOP-C No. 11 Service Water Pump Trip 04 RO-C Hotwell Low Level 05 BOP-C Steam Packing Exhauster High Temperature 06 RO-I Channel "4" APRM Fails High 07 M Design Basis Earthquake 08 RO-C Loss of No. 13 Bus 09 M Nuclear Boiler reference line breaks, causing loss of all level indication.

Note 1 Event 6: If required to get into Tech Spec more could have a failure of B RPS to trip. Problem is that simulator requires a full scram failure (PP04)and 5-B-5 does not come in. If PP04 is removed, to allow a full scram, then 5-B-5 would come in which could be confusing.

+/- +

i i

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. I Page I of 4 Event

Description:

SYNCHRONIZE MAIN GENERATOR TO THE GRID Time Position Actions or Behavior SRO Direct the BOP Operator to synchronize the Main Generator to the grid.

SRO Acknowledge that Main Generator has been synchronized to the grid.

RO Monitor plant parameters.

BOP I. Place the synchronizing switch for 8N4 or 8N5 in ON and verify the following:

(8N4SS or 8N5SS) (PROCEDURE CA, STEP VI.C.5)

a. Synchronizer pointer is moving.

(Synchronizing meter C08)

b. Synchronizing Voltmeters and sensing lights are activated.

(Running and Incoming voltage meters C08)

(White sensing lights below synchronizing meter C08)

2. Using the Speed Load Changer control switch, ADJUST generator speed until synchronous pointer rotation of one revolution in 30 - 120 seconds is achieved.
3. Verify Generator Voltage is between 20.9 KV and 23.1 KV.

(Main Generator voltage meter C08)

4. Using the Manual Voltage Adjust control switch, ADJUST incoming voltage to match running voltage.

(Running and Incoming voltage meters C08)

5. Verify the synchroscope makes at least two complete revolutions.
6. Load the Main Generator by performing the following:
a. Verify the synchrocope pointer is in the GREEN band.
b. Place either 8N4 or 8N5 control switch to close for approx. 1 sec.

(Closed indication for the output breaker is indicated by RED lamp indication above the breaker and generator load present)

7. If the selected output breaker does not close place the breaker control switch to TRIP and return to step 1 above. (step 5 in C. 1)
8. If the selected output breaker does not close on the second attempt, DO NOT reset the breaker and notify System Engineer.

NOTE: If the breaker does not close the second time allow several more attempts.

Page 1 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. I Page 2 of 4 Event

Description:

SYNCHRONIZE MAIN GENERATOR TO THE GRID Time Position Actions or Behavior BOP 9. Place the SPEED LOAD CHANGER to RAISE and increase load to approximately 30 Mwe. (HS SLCM C08)

10. Verify phase-to-phase voltages are approx. equal. (HS VSI C08)

(Main Generator voltage meter C08)

11. Verify phase-to-phase currents are approx. equal.

(3 Generator Amperage meters C08)

12. Place synchroscope to OFF and remove handle from switch.
13. LOG in the Control Room log.
14. Direct TBO to locally inspect the No. I Generator Transformer area and 345KV disconnects.
15. Place the other output breaker synchronizing switch to ON and verify.
a. Incoming and Running voltmeters are matched.
b. Synchroscope indicated frequency is matched.
16. CLOSE the selected output breaker. (8N4/CS or 8N5/CS)
17. Verify phase-to-phase voltages are approx. equal. (HS VSI C08)

(Main Generator voltage meter C08)

18. Verify phase-to-phase currents are approx. equal.

(3 Generator Amperage meters C08)

19. Place synchroscope to OFF and remove handle from switch.
20. LOG in the Control Room log.

2 1. Notify the Transmission System Operator Page 2 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. I Page 3 of 4 Event

Description:

SYNCHRONIZE MAIN GENERATOR TO THE GRID Time Position Actions or Behavior BOP 22. CLOSE the following valves:

a. MO-1197 (HS 1197 C07)
b. MO-1184 (HS 1184 C07)
c. MO-1185 (HS 1185 C07)
d. MO-1186 (HS 1186 C07)
e. MO-1187 (HS 1187 C07) f, MO-1180 (HS-1180 C07)
g. MO-1181 (HS-1181 C07)
h. MO-1182 (HS-1182 C07)
i. MO-1 183 (HS- 1183 C07)

NOTE: Steps 23 thru 27 place the Voltage Regulator in automatic.

23. ZERO the No, 1 MAIN GENERATOR AMPLIDYNE VOLTAGE using the REGULATOR VOLTAGE ADJUST.

(CS-70 C08)

24. Place the REGULATOR TRANSFER switch to AUTO.

(243/CS C08)

25. Verify the white and red lights above the switch are ON.
26. ADJUST MVAR loading per system dispatch.

(CS-90 C08) (MVAR digital display)

27. ZERO the No. 1 MAIN GENERATOR AMPLIDYNE VOLTAGE using the MANUAL VOLTAGE ADJUST.

(CS-70 C08)

NOTE: Steps 28 thru 31 place the Power System Stabilizer in service.

BOP 28. Verify the Automatic Voltage Regulator is in service.

(white and red lights above the switch are ON)

29. Verify the No. 1 MAIN GENERATOR AMPLIDYNE VOLTAGE meter is at ZERO.
30. PRESS the Power System Stabilizer START button on C08.
31. Verify the RED light below the button is ON.

Page 3 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 1 Page 4 of 4 Event

Description:

SYNCHRONIZE MAIN GENERATOR TO THE GRID Time Position Actions or Behavior BOP 1. Verify Exhaust Hood Temperature is < 125 deg F.

(SPDS 654, Pt. TRB138 or TR-1717 Pts. 16 & 17)

2. RAISE (slowly) the SPEED/LOAD CHANGER to increase generator load.
3. Verify the SPEED/LOAD CHANGER is no longer controlling.
4. RAISE the SPEED/LOAD CHANGER setpoint to the high speed stop (107%)
5. SELECT SPDS Format 701 and monitor Generator Gross Rate of Change.

BOP Report to the SRO that the Main Generator has been synchronized to the grid.

Notes:

Page 4 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No, Scenario No. 3 Event No. 2 Page I of I Event

Description:

INCREASE REACTOR POWER BY PULLING CONTROL RODS Time Position Actions or Behavior SRO C. .VII - Power Ascension Verify outside air temperature is > 32 deg.

Verify Isophase Bus Blower in service.

SRO Direct RBO to reduce RWCU flow to 140 GPM.

SRO Increase reactor power per C.2-05 Power Operation - System Operation.

"* Review an official 3D Monitor.

"* Review the Periodic Log.

"* Direct the RO to commence Control Rod Withdrawal continuing at step 16, Control Rod 34-43.

RO Withdraw Control Rods in accordance with the roller tape starting with 34-43.

BOP Monitor Plant Parameters Notes:

Page 5 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 3 Page I of I Event

Description:

  1. 11 SERVICE WATER PUMP TRIP - FAILURE OF STBY PUMP TO START Time Position Actions or Behavior SRO Acknowledge report of 6-B-22, "SERVICE WATER HDR LOW PRESSURE".

SRO Acknowledge report of action taken for trip of No. II Service Water Pump.

RO Monitor plant parameters.

BOP I. Acknowledge annunciator 6-B-22, "SERVICE WATER HDR LOW PRESSURE".

2. Report 6-B-22 to SRO
3. Monitor Service Water System pressure.

(PI-1535 C06)

4. Determine Service Water System pressure is low, #11 Service Water Pump has tripped and 12 Service Water Pump did not automatically start.

(Indicating lights above HS 52-305CS & HS 52-405CS)

5. Start #12 Service Water Pump.

(HS 52-405CS to START)

6. Verify #12 Service Water Pump starts and system pressure is restored.

(Indicating lights above HS 52-405CS) (PI-1535 C06)

7. Verify actions per C.4-B.8.1.1.A LOSS OF SERVICE WATER.
8. Notify Shift Supervision.
9. Direct TBO to: (ARP 6-B-22)

Notes:

Page 6 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 4 Page I of 2 Event

Description:

HOTWELL LOW LEVEL (Condensate reject valve open due to false hotwell level signal)

Time Position Actions or Behavior SRO Acknowledge report of the following annunciators:

6-A-24, "COND BYPASS VALVE OPEN POSITION" 6-A-35, "COND DMIN SYSTEM TROUBLE" 6-A-3 I, "COND E- B HOTWELL HIGH/LOW LEVEL" SRO Acknowledge report of action taken on Hotwell Low Level.

NOTE: This event takes approx. 10 minutes from actuation to the Hotwell Low Level Alarm occurring.

NOTE: Annunciators 6-A-24, COND BYPASS VALVE OPEN POSITION and 6-A-35, COND DMIN SYSTEM TROUBLE, will alarm prior to 6-A-3 1, COND E- I B HOTWELL HIGH/LOW LEVEL, alarming. These alarms indicate that plant conditions have changed but do not specifically identify the condensate reject valve throttled open. Candidates may ascertain the problem prior to 6-A-31 alarming.

RO I. Acknowledge annunciator 6-A-35, COND DMIN SYSTEM TROUBLE.

2. Consult ARP 6-A-35
3. Contact TBO to ascertain which alarm on C-80 is actuated.

Note: Simulator Communicator reports back after 2 minutes that alarm 80-A-21, POWDEX SYSTEM HIGII D/P, is in alarm.

4. Acknowledge annunciator 6-A-24, COND BYPASS VALVE OPEN POSITION.
5. Consult ARP 6-A-24 Notes:

Page 7 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 4 Page 2 of 2 Event

Description:

HOTWELL LOW LEVEL (Condensate reject valve open due to false hotwell level signal)

Time Position Actions or Behavior RO 1. Acknowledge annunciator 6-A-31, COND E-IB HOTWELL HIGH & LOW LEVEL

2. Consult ARP 6-A-3 1.
3. Verify Hotwell low level exists.

(LR-1278 C06)

4. Determine Reject Valve (CV-1093A & B) controller is calling for 100% open.
5. Place CV-1093A & B in MANUAL.
6. Close CV-1093A & B.
7. Monitor Reactor Feed Pump suction pressure.

(PI-1120 & PI-1121 C06)

8. Notify Shift Supervision.
9. Contact I&C to correct controller problem.

BOP Monitor plant parameters and assist in following up on annunciators.

Notes:

Page 8 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 5 Page 1 of I Event

Description:

STEAM PACKING EXHAUSTER HIGH TEMPERATURE Time Position Actions or Behavior SRO Acknowledge report of 7-A-28, "STM PKG EXH K3A & K3B BLWR MTR HI TEMP".

SRO Acknowledge report of action taken for Steam Packing Exhauster trouble.

RO Monitor plant parameters.

BOP 1. Acknowledge annunciator 7-A-28 STM PKG EXH K3A & K3B BLWR MTR HI TEMP.

2. Consult ARP 7-A-28
3. Determine Steam Packing Exhauster K-3A is in service.
4. START Steam Packing Exhauster K-3B.

(HS 42-2122/CS to RUN C07)

5. ADJUST K-3B outlet valve MO-1049 to establish 10" H20 as indicated on Pl 1220, STEAM PACKING EXH VAC. (HS-1049 C07)
6. STOP Steam Packing Exhauster K-3A.

(HS 3122/CS to OFF C07)

7. CLOSE K-3A outlet valve MO-1048.

(HS-1048 to CLOSE C07)

8. Notify Shift Supervision and Plant Electrician.

Notes:

Page 9 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 6 Page 1 of 2 Event

Description:

CHANNEL 4 APRM FAILS HIGH Time Position Actions or Behavior SRO Acknowledge report of annunciators SRO Acknowledge action taken in response to APRM failure.

SRO Determine APRM has failed due to equipment failure.

SRO Determine minimum number of APRM channels are satisfied per Technical Specification, Section 3.2 - Table 3.2.3, SRO Direct RO to place #4 APRM in BYPASS, (ARP 5-A-30)

SRO Notify System Engineer SRO Direct the RO to reset Channel 'B' RPS scram logic. (ARP 5-B-5)

Notes:

Page 10 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 6 Page 2 of 2 Event

Description:

CHANNEL 4 APRM FAILS HIGH Time Position Actions or Behavior RO 1. Acknowledge annunciators:

  • 5-A-3 ROD WITHDRAW BLOCK
  • 5-A-30 APRM HI HI INOP CH 4, 5, 6
  • 5-B-3 REACTOR NEUTRON MONITOR SCRAM TRIP
  • 5-B-5 REACTOR AUTO SCRAM CHANNEL B
2. Report annunciators to SRO
3. Consult ARPs
4. Determine APRM #4 is indicating UPSCALE.

(NR-7-46B CO5)

5. Determine Reactor Protection System Scram Channel 'B' is tripped.

(RPS BUS B amber lamps on CO5 extinguished)

6. Determine Rod Block is actuated. (Annunciator 5-A-3 is in alarm)
7. Determine 'HI-HI' indicating lamp for APRM 4 on panel C37 is ON.
8. Determine remaining APRM channels are within expected range.

(NR-7-46A -D C05)

9. Notify Shift Supervision and I&C.

RO 1. Place APRM #4 to bypass.

(APRM 4 5 6 bypass joystick CO5)

RO 1. Reset Channel 'B' RPS scram logic.

(HS 5A-S9 SCRAM LOGIC RESET CO5)

Notes:

Page 11 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 7 &8 Page 1 of 4 Event

Description:

DESIGN BASIS EARTHQUAKE & BUS #13 LOCKOUT Time Position Actions or Behavior SRO Acknowledge report of annunciators.

May announce now entering "Transient Annunciator Response".

SRO 1. Determine a Design Basis Earthquake has occurred. (Prairie Island could be called if further clarification is desired).

NOTE: C.4.K Immediate Reactor Shutdown may be entered but is not required.

SRO 1. Direct the RO to manually scram the reactor.

Critical Step SRO 1. Per C.4-B.09.06.B LOSS OF BUS 13 OR BUS 14:

  • Monitor and control Reactor water level between +30 and +40 inches.

RO 1. Depress REACTOR SCRAM 'A' and 'B' pushbuttons.

(5A-S3A and 5A-S3B)

RO Carry out actions of C.4.A "REACTOR SCRAM" Applicable Immediate Operator Actions

"* Determine all control rods are inserted to or beyond position 04.

"* Place the reactor mode switch in SHUTDOWN.

"* Notify Shift Supervision Applicable Subsequent Operator Actions

"* Verify that the Recirc pumps are at minimum speed.

"* Control Reactor water level between +9" and +48" with Cond & Feed.

"* Place CV-6-13 (low flow valve) in AUTO.

"* Place CV-6-13 controller setpoint to 15 to 20 inches.

"* Verify CV-6-13 is closed when RPV level reaches 15 to 20 inches.

"* Insert SRM and IRM detectors.

"* Switch APRM/IRM recorders to IRM.

"* Monitor power by ranging down the IRMs to maintain indication on scale.

"* Verify the Scram Discharge Vent and Drain Valves close.

Page 12 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 7 & 8 Page 2 of 4 Event

Description:

DESIGN BASIS EARTHQUAKE & BUS #13 LOCKOUT Time Position Actions or Behavior RO 1. Per C.4-B.0 1.03.A LOSS OF CRD PUMP FLOW

  • Verify CRD flow is available (PI-3-302 Charging Water Header Pressure - CO5)

(FI-3-306 Cooling Water Header Flow - C05)

BOP 1. Acknowledge annunciators:

2. Consult ARPs 6-C-8 & 6-C-13
3. Verify actuation of the Accelerograph Recording System. (Contacting system engineering is an option)
4. Enter C.4-B.5.14A EARTHQUAKE NOTE: Annunciator 6-C- 18 will occur 45 seconds after initial earthquake annunciators (6-C-8 & 6-C-13).

5, Acknowledge annunciator 6-C-18 DESIGN BASIS EARTHQUAKE BOP Announce over the paging system that a Reactor scram has occurred. (C.4.A)

BOP Carry out actions of C,4.A "REACTOR SCRAM" Applicable Subsequent Operator Actions

"* When Generator power is - 0 Mwe OPEN 8N4 and 8N5. (C08)

"* TRIP the Turbine (Turbine emergency trip switch - C07)

"* Verify that Turbine-Generator field breaker is OPEN. (C08)

"* STOP the amplidyne. (Regulator Transfer Switch to OFF - C08)

"* START the Turbine Auxiliary Oil Pump. (C07)

NOTE: Turbine Aux Oil Pump electrical reset is required for start. (C.4.H)

Page 13 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 7& 8 Page 3 of 4 Event

Description:

DESIGN BASIS EARTHQUAKE & BUS #13 LOCKOUT Time Position Actions or Behavior BOP 1. Enter the following procedure:

  • C.4-B.09.06,B LOSS OF BUS 13 OR BUS 14
2. Enter the following procedures (directed by C.4-B.09.06.B LOSS OF BUS 13 OR BUS 14):
  • C.4-B.01.03,A LOSS OF CRD PUMP FLOW
  • C.4-B.06.04.A DECREASED CIRCULATING WATER FLOW
  • C.4-B.06.03.A DECREASING CONDENSER VACUUM
  • C.4-B.09.06.C LOSS OF BUS 15 OR BUS 16
  • C.4-B.09.07.A LOSS OF POWER TO LC-101 OR ITS MCC'S
  • C.4-B.09.07.C LOSS OF POWER TO LC-103 OR ITS MCC'S
  • C.4-B.09.07.E LOSS OF POWER TO LC-107 OR MCC-1 14
  • C.4-B.09.07.G LOSS OF POWER TO LC-109 OR ITS MCC'S BOP 1. PerARP 8-13-11 NO 13 4160V BUS LOCKOUT

" Verify # 15 4160V bus has transferred to 1AR.

(152-511 breaker indication - Red OFF, Green ON - C08)

(#15 bus voltage indication - C08)

" Verify # 11 & # 12 Emergency Diesel Generators have started.

(#I1 & #12 EDG voltage indication - C08)

"* Verify LC-107 transfer to LC-108.

BOP I. Per C.4-13.09.06.B LOSS OF BUS 13 OR BUS 14:

"* OPEN ACB 52-901 (52-901/CS - C08)

"* Place 52-908/SS SYNC 109 CTR SEC ACB to ON - C08

"* CLOSE ACB 52-908 109/102 LOAD CTR TIE ACB (52-908/CS C08)

"* Verify MO-1850 "11 Cir Wtr Pump P-100 Discharge Valve" has closed, (Bkr indicating lamps - C06)

NOTE: MO-1850 will begin to automatically close when power is restored to LC-109.

Page 14 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 7 & 8 Page 4 of 4 Event

Description:

DESIGN BASIS EARTHQUAKE & BUS #13 LOCKOUT Time Position Actions or Behavior BOP 1. C.4-B.06.04.A DECREASED CIRCULATING WATER FLOW

  • Place #11 Circulating Water Pump control switch to SHUTDOWN.

(152-305/CS - C06)

BOP 1. C.4-B.06.03.A DECREASING CONDENSER VACUUM 0 Monitor LP Turbine exhaust pressures per SPDS 656.

BOP 1. C.4-B.09.06.C LOSS OF BUS 15 OR BUS 16

"* Determine that Bus 15 is being powered by IAR.

(152-511 breaker indication - Red OFF, Green ON - C08)

(# 15 bus voltage indication - C08)

"* Consider shutdown of#I I & #12 Emergency Diesel Generators.

BOP 1. C.4-B.09.07.A LOSS OF POWER TO LC-101 OR ITS MCC'S

  • No action required - LC- 101 re-powered automatically.

BOP 1. C.4-B.09.07.C LOSS OF POWER TO LC-103 OR ITS MCC'S

BOP 1. C.4-B.09.07.E LOSS OF POWER TO LC-107 OR MCC-1 14

  • Determine crosstie between LC-107 and LC-108 is closed.

(Indicated by control room lighting restored)

BOP 1. C.4-B.09.07.G LOSS OF POWER TO LC-109 OR ITS MCC'S

  • No action required - LC-109 re-powered when breaker 52-908 was closed.

Notes:

Page 15 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 9 Page I of 5 Event

Description:

LOSS OF ALL RPV LEVEL INDICATION (RPV LEVEL UNKNOWN)

Time Position Actions or Behavior SRO Acknowledge report of annunciators.

SRO Verify RPV water level is known per:

"* SPDS (Display 051)

"* LI-6-52B and LI-2-3-85A.

NOTE: "B" side level instruments will fail 4 minutes after the "A" side. "B" side instruments will fail as drywell pressure approaches +2 psig requiring entry into C.5-1 100.

SRO Enter C.5-1 100 RPV CONTROL (Entry condition +2 psig drywell pressure)

SRO Verify : 1. Reactor scram

2. All rods in to at least 04 SRO Verify RPV water level instrument limits have not been exceeded.

SRO Determine RPV water level is unknown Critical Leave C.5-1 100 - RPV CONTROL Step Enter C.5-2006 - RPV FLOODING at step 24 SRO Determine Torus level is above -5.9 ft.

SRO Direct BOP operator to open 3 ADS valves.

Critical Step SRO Verify 3 ADS valves are open.

SRO Direct BOP operator to close the:

"* MSIVs

"* Main Steam Line Drains

"* RCIC steam isolation valves Page 16 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 9 Page 2 of 5 Event

Description:

LOSS OF ALL RPV LEVEL INDICATION (RPV LEVEL UNKNOWN)

Time Position Actions or Behavior SRO Direct BOP and RO to inject to the RPV using:

Critical 0 Condensate Step 0 LPCI a Core Spray

  • CRD Inject until 3 SRVs are verified OPEN and RPV pressure at least 50 psi above DW pressure, but low as possible.

SRO Confirm Drywell high pressure as indicated on PR-2994 (C04) and SPDS Enter C.5-1200 PRIMARY CONTAINMENT CONTROL (Entry Condition +2 psig Drywell pressure).

SRO Determine Drywell pressure >2 psig Go to step 17 SRO Verify Torus level <14.1 ft and Torus pressure >2 psig.

Direct BOP operator to start Torus spray per C.5-3502.

NOTE: If it is determined that RHR pumps are needed for core cooling, Torus spray will not be initiated until RPV level is restored.

SRO Direct BOP operator to stop Torus spray if Torus pressure drops below 2 psig.

SRO Direct BOP operator to start all available DW cooling per C.5-3503 SRO Maintain Torus level -4.0 to +3.0 inches SRO Determine that Torus level can be maintained <+4.3 ft and >-3.3 ft. (steps 15 & 19)

SRO Direct BOP operator to perform procedure C.5-3501 as time permits.

Page 17 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 9 Page 3 of 5 Event

Description:

LOSS OF ALL RPV LEVEL INDICATION (RPV LEVEL UNKNOWN)

RO Acknowledge annunciator 5-B-24 "REACTOR WATER LEVEL HI/LO" Consult ARP 5-B-24 "REACTOR WATER LEVEL HI/LO" Report annunciator 5-B-24 to SRO Determine LI-6-52A and LI-2-3-85B have failed upscale. (C05)

Verify LI-6-52B and LI-2-3-85A indicate correctly. (C05)

Determine Reactor Feed Pump trip has occurred on high RPV level and cannot be re started.

RO Verify injection from Condensate and CRD.

Critical Step RO Decrease Condensate injection as directed.

BOP Place hand switches for A, C & D SRVs to OPEN.

Critical Step 2E-SIA 2E-SIC 2E-S1D Determine ADS valves did open. (amber lamps on C03 for "A", "C" & "D" SRVs illuminated)

BOP Place MSIV handswitches to CLOSE. (C-03) (HS 16A-SIA- 16A-S1D)

(HS 16A-S2A- 16A-S2D)

CLOSE MO-2373. (C-03) (Main Steam Line Drain) (HS 16A-S5)

CLOSE MO-2374. (C03) (Main Steam Line Drain) (HS 16A-S6)

BOP CLOSE MO-2075. (C-04) (RCIC Isolation) (HS 13A-S1)

CLOSE MO-2076. (C-04) (RCIC Isolation) (HS 13A-S3)

Page 18 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 9 Page 4 of 5 Event

Description:

LOSS OF ALL RPV LEVEL INDICATION (RPV LEVEL UNKNOWN)

Time Position Actions or Behavior BOP Verify injection from Core Spray A & B and LPCI.

Critical Step BOP Verify 3 SRVs are OPEN after floodup is complete by SRV open AMBER lamps ON and RPV pressure increasing as indicated by Recirculation Pump Seal pressure.

BOP Remove Core Spray & LPCI injection as directed.

BOP If placing Div. 1 Torus Spray in service:

1. Locate C.5-3502 Part A.
2. Perform steps I thru 7 of C.5-3502 Part A (See Attachment 1 for steps).

BOP If placing Div 2 Torus Spray in service:

1. Locate C.5-3502 Part B.
2. Perform steps I thru 7 of C.5-3502 Part B (See Attachment 2 for steps).

Notes:

Page 19 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Op-Test No. Scenario No. 3 Event No. 8 Page 5 of 5 Event

Description:

LOSS OF ALL RPV LEVEL INDICATION (RPV LEVEL UNKNOWN)

Time Position Actions or Behavior BOP Locate procedure C.5-3503

1. Place all DW cooling switches to OFF (42-3312/CS, 42-4312/CS, 42-3313/CS, 42-4313/CS on C25
2. OPEN knife switch KS3 100 (behind panel C25)
3. Verify FAN INLET DAMPER control switches in AUTO (C25)
4. Place DW cooling fan control switch in ON.

(42-3312/CS, 42-4312/CS, 42-3313/CS, 42-4313/CS on C25)

5. OPEN associated discharge dampers for started fans.

FAN DISCHARGE DAMPERS V-RF-I V-D-15 V-D-16 V-RF-2 V-D-17 V-D-18 V-RF-3 V-D-19 V-D-20 V-RF-4 V-D-21 V-D-22 BOP Locate C.5-3501 - H2/02 ANALYZER OPERATION Perform steps I thru 14 ofC.5-3501 (See Attachment 3 for steps).

Notes:

Page 20 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Termination Point:

  • RPV pressure >50 psig above Drywell pressure
  • Upon approval of Chief Examiner Classification:

Site Area Emergency - Guideline 22 Page 21 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Attachment 1, C.5-3502, Part A MONTICELLO NUCLEAR GENERATING PLANT Ops Man C.5-3502 Revision 6 Page 3 of 18 PART A TORUS SPRAY - RHR-A EQUIPMENT

PRECAUTIONS None PREREQUISITES

1. 11 and/or 13 RHR pump operating.

OPERATOR ACTIONS

1. Place CONTAINMENT SPRAY 2/3 CORE HEIGHT BYPASS switch 10A-S18A to MANUAL OVERRIDE, if necessary.
2. Place CONTAINMENT SPRAY/COOLING LPCI INITIATION BYPASS switch 1 0A-S1 7A to BYPASS, if necessary.

NOTE: Steps 3, 4 and 5 may be performed concurrently.

3. OPEN MO-2006, DISCHARGE TO TORUS OUTBOARD.
4. OPEN MO-201 0, TORUS SPRAY - INBOARD.
5. THROTTLE MO-2008, TORUS COOLING INJ/TEST INBOARD, as needed to maintain minimum RHR pump flow requirements.
6. Verify CLOSED the following valves, if necessary, while continuing in this procedure:

"* MO-2012, LPCI INJECTION - OUTBOARD

"* MO-2013, LPCI INJECTION - OUTBOARD

7. IF Containment cooling IS NOT in service, THEN perform the following:
a. Verify CV-1 728, RHR HX SW Outlet, controller is set to 20%.
b. Place MO-2002, HX BYPASS keylock switch in the CLOSE position.

9 c. IF RHRSW pumps have been load shed, THEN place 11 and 13 RHRSW PUMPS LPCI AND ECCS LOAD SHED MANUAL OVERRIDE switch* 10A-S1 9A to MANUAL OVERRIDE.

  • 1 I/pdc PART A Page 22 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Attachment 1, C.5-3502, Part A MONTICELLO NUCLEAR GENERATING PLANT Ops Man C.5-3502 Revision 6 Page 4 of 18

d. IF normal off-site power IS NOT available, THE.N perform the following:
1) Place either 11 or 13 RHR pump in PULL-TO-LOCK.
2) START 11 or 13 RHRSW pump.
e. IF normal off-site power IS available, THEN START RHRSW pumps, as needed.
f. Adjust RHRSW flow to -3500 gpm per pump using CV-1 728.
g. Verify OPEN RHRSW-32, RHRSW LOOP A

& B XTIE, to pressurize both RHRSW loops, if needed.

h. Verify CLOSED MO-2002, HX BYPASS.
8. IF directed by Shift Supervision to stop torus spray, THEN CLOSE MO-201 0, TORUS SPRAY - INBOARD.

I/pdc PART A Page 23 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Attachment 2, C.5-3502, Part B MONTICELLO NUCLEAR GENERATING PLANT Ops Man C.5-3502 Revision 6 Page 5 of 18 PART B TORUS SPRAY - RHR-B EQUIPMENT

PRECAUTIONS None PREREQUISITES

.1. 12 and/or 14 RHR pump operating.

OPERATOR ACTIONS"

1. Place CONTAINMENT SPRAY 2/3 CORE HEIGHT BYPASS switch 1OA-S18B to MANUAL OVERRIDE, if necessary.
2. Place CONTAINMENT SPRAY/COOLING LPCI INITIATION BYPASS switch 10A-S1 7B to BYPASS, if necessary.
  • -" NOTE: Steps 3, 4 and 5 may be performed concurrently.
3. OPEN MO-2007, DISCHARGE TO TORUS OUTBOARD.
4. OPEN MO-2011, TORUS SPRAY - INBOARD.
5. THROTTLE MO-2009, TORUS COOLING/INJ TEST INBOARD, as needed to maintain minimum RHR pump flow requirements.
6. Verify CLOSED the following valves, if necessary, while continuing in this procedure:
  • MO-2012, LPCI Injection Outboard
  • MO-2013, LPCI Injection Outboard
7. IF Containment cooling IS NOT in service, THEN. perform the following:
a. Verify CV-1 729, RHR HX SW Outlet, controller is set to 20%.
b. Place MO-2003, HX BYPASS keylock switch in the CLOSE position.

C. IF RHRSW pumps have been load shed, THE.N place 12 and 14 RHRSW PUMPS LPCI AND MANUAL OVERRIDE switch 10A-S1 9B to MANUAL ECCS LOAD SHED OVERRIDE.

I/pdc PART B Page 24 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Attachment 2, C.5-3502, Part B MONTICELLO NUCLEAR GENERATING PLANT Ops Man C.5-3502 Revision 6 Page 6 of 18

d. IF normal off-site power IS NOT available, THEN perform the following:
1) Place either 12 or 14 RHR pump in PULL-TO-LOCK.
2) START 12 or 14 RHRSW pump.
e. IF normal off-site power IS available, THEN START RHRSW pumps, as needed.
f. Adjust RHRSW flow to -3500 gpm per pump using CV-1 729.
g. Verify OPEN RHRSW-32, RHRSW LOOP A & B XTIE, to pressurize both RHRSW loops, if needed.
h. Verify CLOSED MO-2003 HX BYPASS.
8. IF directed by Shift Supervision to stop torus spray, THEN CLOSE MO-2011, TORUS SPRAY - INBOARD.

I/pdc PARTB Page 25 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Attachment 3, C.5-3501 MONTICELLO NUCLEAR GENERATING PLANT Ops Man C.5-3501 Revision 0 Page 2 of 4 PURPOSE 0 This procedure provides instructions to place the H2102 analyzers in service. This procedure should only be entered as directed by Emergency Operating Procedures.

EQUIPMENT None PRECAUTIONS None PREREQUISITES

1. Primary Containment temperature less than 2800F.

OPERATOR ACTIONS GENERAL NOTES:

1. Procedure written is typical for placing one analyzer in service. Both analyzers should be placed in service simultaneously, one sampling the Torus, the other the Drywell.
2. This procedure should be performed as soon as support personnel (Operation or l&C) are available. 9**..

smr Page 26 of 28

NRC SIMULATOR EXAMINATION SCENARIO NO. 3 Attachment 3, C.5-3501 MONTICELLO NUCLEAR GENERATING PLANT Ops Man C.5-3501 Revision 0 Page 3 of 4

3. When analyzers have stabilized, recorder readings may oscillate approximately 2% peak to peak.
1. IF a Group 2 isolation exists, THEN place INBD H2/O2 VALVES CLOSE/ISOL BYPASS switch, AND OTBD H2/02 VALVES CLOSEISOL BYPASS switch to ISOL BYPASS.
2. NOTE: The sample return valves OPEN automatically when Drywell or Torus sample valves are opened.

OPEN selected Inboard and Outboard sample valves.

3. Verify one H2/O2 analyzer is selected to sample the Torus and the other is selected to sample the Drywell.
4. Place ANALYZER MODE SWITCHs to ANALYZE.
5. Depress REMOTE SELECTOR pushbuttons to take control at Control Room.
6. Place FUNCTION SELECTORs to ZERO.
7. Verify 02 DUAL RANGE SWs on 0-25% range.
8. Verify H2 DUAL RANGE SWs on 0-20% range.
9. Place chart recorders ON.

smr Page 27 of 28

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