Text

NRC - Proposed Scenarios for the Palisades Initial Examination - May 2005
	ML052270379
Person / Time
Site:	Palisades
Issue date:	05/23/2005
From:	Palagi B; NRC/RGN-III/DRS/OLB
To:	; Nuclear Management Co
References
	50-255/05-301 50-255/05-301
	Download: ML052270379 (57)
	v • d • e

PROPOSED SCENARIOS

Appendix D Scenario Outline Form ES-D-1 Facility: PALISADES Scenario No.: 1 Op-Test No.: 1 Examiners: _____________

Operators: _____________________

Initial Conditions:

60% power. P-7B Service Water Pp. is out of service.

Turnover:

Shift orders are to alternate Component Cooling Water Pumps, and then continue a power ascension.

Event No.

Malf. No.

Event Type*

Event Description 1

N/A SRO (N)

RO (N)

Alternate operating CCW pps.

2 N/A SRO (N)

RO (R)

BOP (N)

Power ascension.

3 RP24 SRO (I)

BOP (I)

Cold Leg #1 RTD fails high.

4 CC02 CC13 SRO (C)

RO (C)

CCW pp. trips; standby fails to start.

5 CC03 SRO (C)

RO (C)

CCW system leak (isolable per ONP-6.2).

6 RC09A SRO (C)

RO (C)

P-50A PCP bearing high temperature. Requires manual reactor trip.

7 TC02 SRO (C)

BOP (C)

Main Turbine Fails to Auto or Manually Trip.

8 MS03A SRO (M)

RO (M)

BOP (M)

Main Steam Line Break Inside Containment (EOP-6.0).

9 CH05 SRO (C)

RO (C)

Containment Spray Fails to Auto Actuate.

10 CH05 SRO (C)

RO (C)

Containment Isolation Fails to Auto or Manual Actuate

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

Scenario 1 - Simulator Operator Instructions Reset to IC-15 (or similar) 60% power MOL IC.

SW Pump P-7B is OOS with a Caution Tag hung on the handswitch.

ENSURE CCW Pump P-52C is in service, with P-52A and P-52B in STANDBY.

INSERT CH05A/B to prevent Containment Spray auto actuation.

INSERT TC02 to prevent Main Turbine auto trip and manual trip.

INSERT CC13B/C to prevent CCW standby pumps auto start.

Event No.

Simulator Operator Instructions 1

Alternate CCW Pps. - No SIM OP actions.

2 Power ascension - No SIM OP actions.

3 REMOTE 1 INSERT RP24A (Cold Leg #1 RTD Fails HIGH) - TE-0112C-A Value = 100.

4 REMOTE 2 INSERT CC02A P-52A trips. STDBY pumps do NOT auto start.

5 REMOTE 3 INSERT CC03/04 CCW system leak. Ramp over 1 minute to 100 gpm (Value = 100), AND CC04 value @ 50.

After 3 minutes, INSERT OVRD for C-105 off normal alarm. EK-1160.

6 REMOTE 4 INSERT RC09A Loss of lube oil to P-50A. (Pump will trip on overcurrent in 15 minutes). Requires manual Reactor trip.

Manual Reactor Trip 7

TC02 (ACTIVE AT SETUP) Main Turbine fails to auto trip and will not trip from C-01.

8 REMOTE 5 INSERT MS03A "A" MSLB. Insert 20 seconds after the Main Turbine is tripped. Value = 20%. Ramp = 2 minutes. Change value to 30% at examiner's direction.

9/10 CH05A/B (ACTIVE AT SETUP) CSS, SIAS fails to auto actuate, CIS fails to auto or manual actuate.

1. (EVENT #1) For alternating CCW pps. if asked, initial CCW Hx dP is E-54A = 6.6 psid, E-54B = 6.8 psid. After starting P-52C, dPs are: E-54A = 14.1 psid, E-54B = 14.2 psid. When P-52A has been secured, dPs are E-54A = 6.8 psid, E-54B

= 6.5 psid.

2. (EVENT #5) When sent to investigate CCW system leakage, promptly report that there is leakage from the valve body flange for CV-0944 on the upstream side.

3. (EVENT #5) DELETE MF CC03 (may use trigger) when NCO closes CV-0944A. If asked, report leak has dramatically reduced. When CV-0977B and CV-0944 are closed locally report, after two minutes report that leak has completely stopped.

4. (EVENT #6) If contacted as System Engineer for loss of lube oil to P-50A, wait 5 minutes and report to the Control Room.

Scenario 1 - Turnover Information Plant is at 60% power, MOL. Boron is 910 ppm. A power ascension was in progress when a Chemistry hold was implemented. The Chemistry hold is no longer required. P-7B Service Water is out of service for a bearing inspection. It is expected to be 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months before bearing inspection is completed.

Shift orders are to alternate running CCW pumps by placing P-52A in service, and P-52C in STANDBY, per SOP-16, 7.3.6. Once this is complete, the power ascension is to resume at 6% per hour. At 86% power, the rate of power ascension will be adjusted to 4% per hour, per GOP-5, Att. 5.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

1 Page 1 of 1 Event

Description:

Alternate CCW Pumps Time Position Applicant's Actions or Behavior SRO RO Enters SOP-16, section 7.3.6.

RO Ensures locked open all available CCW pp. suction/discharge valves.

RO Coordinates with AO to open vent for P-52C.

RO Verifies both CCW Heat Exchangers in operation.

RO Starts P-52A.

RO Stops P-52C.

RO Places P-52C in standby by pressing amber STANDBY button above handswitch.

Verifies amber light is LIT.

RO May request final reading on CCW Heat Exchangers differential pressure, but not required.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

2 Page 1 of 1 Event

Description:

Power Ascension Time Position Applicant's Actions or Behavior SRO Enters/continues and directs the actions of GOP-5.

SRO Reviews GOP-5 Precautions and Limitations with crew.

SRO May discuss ASI control strategy. Determines target ASI = -0.02.

Note: The above actions should already have been done as part of prejob brief.

RO BOP Continue power escalation as directed by CRS.

Note to Examiner: Various techniques may be used for the power ascension (e.g., withdraw control rods, start with a 50 gal. dilution, follow with a 100 gal.

dilution, etc.)

BOP Selects DEH rate at 6% per hour.

Note: Per GOP-5, and turnover information, this rate must be changed to 4% / hr.

when power reaches 86%.

RO BOP Monitor Tave and Tref.

BOP Initiates GO on DEH control for Main Turbine load increase.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

3 Page 1 of 1 Event

Description:

Cold Leg #1 RTD Fails HIGH (TE-0112C-A)

Time Position Applicant's Actions or Behavior SRO BOP RO Diagnoses failure of Cold Leg #1 RTD:

EK-06C TM/Lo pressure channel trip EK-06C TM/Lo pressure channel pretrip EK-07 No PCS Protection Channel A EK-09 Loop 1 Loop 2 Tave deviation EK-09 Loop 1 Tave/Tref Gross deviation EK-06D Nuclear - delta T power deviation/T-inlet off normal/calculator trouble channel A SRO Enters and directs the actions of various ARP-21.

BOP Bypass the Variable High Power Trip (Trip #1) and the TM/LP trip (Trip #9) for A Channel of RPS, per SOP-36.

1.

Insert bypass key above affected RPS Trip Unit.

2.

Turn key 90º clockwise.

3.

Verify lit YELLOW light above bypass keyswitch.

SRO Notify I&C to troubleshoot.

SRO Refers to various Technical Specifications:

LCO 3.1.6 LCO 3.3.1 (Items 1 and 9)

LCO 3.3.8 Item 6)

LCO 3.4.12 (Condition B.1)

ORM 3.17.6 Table 3.17.6, Item 12

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

4 Page 1 of 1 Event

Description:

CCW Pump P-52A trips, Standby pumps fail to start Time Position Applicant's Actions or Behavior SRO RO Diagnose trip of CCW Pump P-52A P-52A breaker indicates OPEN EK-1167, COMPONENT CLG PUMPS P-52A/B/C TRIP alarms EK-1169, COMPONENT CLG PUMPS DISCHARGE LO PRESS alarms.

Standby CCW Pump FAILS to start.

SRO Enters and directs the actions of ARP-7 and ONP-6.2. Makes PA announcement of entering ONP-6.2.

RO Starts available CCW Pump P-52B or P-52C.

SRO RO Auxiliary Operator actions directed, as appropriate. (May dispatch AO to check CCW Hx dP.)

RO Monitors CRDM and PCP parameters, as appropriate.

SRO Refers to Tech Spec 3.7.7. A.1 is required action. Determines one train inoperable and must restore within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Note: Loss of the auto start feature on low header pressure does not render the pump inoperable.

SRO Initiates troubleshooting and repair.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

5 Page 1 of 1 Event

Description:

CCW System Leak (isolable)

Time Position Applicant's Actions or Behavior SRO RO Diagnoses that a CCW System Leak is occurring:

Lowering CCW Surge Tank level EK-1172, CCW Surge Tank Hi-Lo Level EK-1160 RADWASTE PANEL C105 OFF NORMAL SRO Enters and directs the actions of ONP-6.2, Loss of CCW.

RO Ensures P-79A or P-79B, Primary Makeup Pump is running.

Ensures CV-0918, Surge Tank Fill, is operating.

SRO Refers to ONP-6.2, Att. 1 for determining leak location and possible isolation.

SRO RO BOP Leak location may be diagnosed by:

Dispatch AOs to troubleshoot.

Monitoring radwaste system parameters.

SRO RO Isolates leak by:

Closes CV-0944A Directs AO to close air supply to CV-0977B, CV-0944.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

6 Page 1 of 1 Event

Description:

Primary Coolant Pump P-50A Loss of Lube Oil (Hi Bearing Temp)

Time Position Applicant's Actions or Behavior SRO RO Diagnoses loss of lube oil to P-50A:

EK-0925 - Pri coolant pump P-50A oil level hi/lo Rising bearing temperatures on P-50A.

Upper Reservoir Oil Level indication (LIA-0136A) indicates low.

RO BOP Commence monitoring / trending of P-50A bearing temperatures.

SRO Contact System Engineer for assistance.

SRO Directs a manual reactor trip, and securing of P-50A, based on criteria of ONP-6.2, step 4.3. (Hi Bearing Temp > 175º F)

RO Trips the reactor, and then secures P-50A PCP. CRITICAL TASK ALL Enter EOP-1.0, "Standard Post Trip Actions" and carry out Immediate Actions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

7 Page 1 of 1 Event

Description:

Main Turbine Fails to Auto Trip or Manual from Control Rm.

Time Position Applicant's Actions or Behavior SRO BOP Diagnoses that the Main Turbine did not automatically trip when the reactor was tripped:

EK-0101, Turbine Trip is NOT alarming.

Turbine steam valves are still open.

S/G pressures lowering PCS cooldown and depressurization BOP Attempts to manually trip Main Turbine using Unit Emergency Trip lighted pushbutton. Determines turbine does not trip and takes contingency action.

Closes both MSIVs. May operate only ONE handswitch, since either MSIV closing causes BOTH MSIVs to close. CRITICAL TASK Continue with EOP-1.0 Immediate Actions.

RO Determine that Reactivity Control is MET.

BOP Control the Feedwater System:

Places both operating MFPs to manual and ramp one to minimum speed.

As Tave lowers toward 525ºF, ramps second MFP to minimum speed.

Closes ALL MFRVs and Bypass FRVs.

CRITICAL TASK to prevent PCS overcooling (inadvertent SIAS).

BOP Determine that Vital Auxiliaries - Electrical acceptance criteria are MET.

RO Determine that PCS Inventory Control acceptance criteria are MET.

(may not be met, depending on progress of event).

RO Determine that PCS Pressure Control acceptance criteria are NOT met.

If PZR pressure is less than 1605 psia:

Verify SIAS initiated per EK-1342.

Ensure all available HPSI and LPSI pumps operating with loop valves OPEN.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

8 Page 1 of 1 Event

Description:

Main Steam Line Break Inside Containment Time Position Applicant's Actions or Behavior SRO BOP RO Diagnose Main Steam line break inside containment:

Excessive steam flow from A S/G S/G isolation actuation S/G pressures and PCS temperatures and pressures lowering Containment humidity, temperature, and pressure rising PCS subcooling rising RO If PZR pressure is less than 1300 psia, STOP PCPs to have one in each loop operating.

RO Determine that Core Heat Removal acceptance criteria are MET.

RO BOP Determine that PCS Heat Removal acceptance criteria are not MET. May not be met depending on S/G pressures.

(May isolate AFW to most affected S/G.)

RO Determine that Containment Isolation acceptance criteria are NOT met.

(due to Containment pressure > 0.85 psig)

RO Determine that Containment Atmosphere acceptance criteria are NOT met.

(due to Containment pressure > 0.85 psig)

RO Determine that Vital Auxiliaries - Water acceptance criteria are met.

RO Determine that Vital Auxiliaries - Air acceptance criteria are met.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

9/10 Page 1 of 2 Event

Description:

Containment Spray, SIAS, CIS, Fail to Auto Actuate Time Position Applicant's Actions or Behavior Note to Examiner: This malfunction disables not only Cont. Spray auto actuation, but also SIAS and Containment Isolation (CIS). These are Events 9, and 10.

This event is actually part of Event 8 (MSLB).

RO If Containment pressure reaches 4.0 psig, manually initiates SIAS:

Depresses PB-1, INJECTION INITIATE Depresses PB-2, INJECTION INITIATE Verifies EK-1342, SAFETY INJ INITIATED alarming Ensures all available HPSI and LPSI pps. operating with associated loop valves open.

(Note: SIAS will still auto actuate on PZR Low Pressure at 1605 psia.)

RO BOP If Containment pressure reaches 4.0 psig, determines Containment Isolation did NOT occur:

EK-1126, CIS INITIATED, NOT in alarm Valves NOT properly aligned Initiates CHR signal to isolate containment Depresses CHRL-CS, HIGH RADIATION INITIATE, and/or Depresses CHRR-CS, HIGH RADIATION INITIATE and determines CIS still has NOT occurred. Takes manual action to use manual CIS initiation pushbuttons.

BOP Manually closes both MSIVs.

CV-0510 (A S/G)

CV-0501 (B S/G)

Note: This may already have occurred.

BOP Manually closes both Main Feed Reg Valves and Bypass Valves:

CV-0701 ('A' S/G)

CV-0703 ('B' S/G)

CV-0735 ('A' S/G)

CV-0734 ('B' S/G)

Note: These actions may already have occurred.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

9/10 Page 2 of 2 Event

Description:

Containment Spray, SIAS, CIS, Fail to Auto Actuate Time Position Applicant's Actions or Behavior RO If Containment pressure is greater than or equal to 4.0 psig:

Ensures all available CAC 'A' fans operating (V-1A, 2A, 3A, 4A)

Open both Containment Spray Valves, CV-3001, CV-3002.

Start all Containment Spray Pumps (P-54A/B/C).

CRITICAL TASK to establish containment spray flow when conditions are met (>

4.0 psig in containment).

RO Manually closes CCW Isolation Valves:

CV-0910, (KEY: 337)

CV-0911, (KEY: 338)

CV-0940, (KEY: 336)

SRO RO Trips all remaining PCPs within approx. 10 minutes of closing CCW Containment Isolation valves, due to no cooling water flow Event 8 (MSLB) continues on next page.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

8 Page 1 of 3 Event

Description:

Main Steam Line Break Inside Containment Time Position Applicant's Actions or Behavior RO BOP BOP turns panels over to RO and reports to CRS.

SRO BOP Align Control Room HVAC to Emergency Mode within 20 minutes of reactor trip.

SRO BOP Verify at least ONE Condensate Pump and ONE Cooling Tower Pump operating.

SRO BOP Perform EOP Supplement 5 for SIAS Checklist.

SRO BOP Perform EOP Supplement 6 for Containment Isolation Checklist.

CRITICAL TASK to ensure containment is isolated.

SRO BOP Perform Emergency Shutdown Checklist per GOP-10.

BOP or RO Trip both Main Feed Pumps (since MSIVs have been closed).

SRO Refer to EOP-1.0, Attachment 1, "Event Diagnostic Flow Chart" and diagnose the event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

8 Page 2 of 3 Event

Description:

Main Steam Line Break Inside Containment Time Position Applicant's Actions or Behavior SRO Transition to EOP-6.0, Excess Steam Demand Event.

SRO Assign performance of EOP-6.0 Safety Function Status Checks to STA.

RO BOP Commence emergency boration to establish PCS boron concentration greater than or equal to boron needed for Tave >525F as verified by sample or hand calculation per EOP Supplement 35.

RO Verify PCP operating limits are satisfied per EOP Supplement 1.

Note: May have already stopped PCPs due to lack of CCW flow to containment.

ALL Determine the most affected S/G by considering ALL of the following:

High steam flow from S/G Lowering S/G pressure Lowering S/G level Lowering Loop Tc temperature BOP Isolate A S/G per EOP Supplement 17.

RO BOP Stabilize PCS temperature by maintaining B S/G pressure slightly above 'A' S/G pressure.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.: 1 Event No.:

8 Page 3 of 3 Event

Description:

Main Steam Line Break Inside Containment Time Position Applicant's Actions or Behavior RO Verify SI pump throttling criteria are satisfied.

Terminate scenario when A S/G has been isolated, PCS temperature has been stabilized, and SI Pump throttling criteria are satisfied, or at the examiner's discretion.

Appendix D Scenario Outline Form ES-D-1 Facility: PALISADES Scenario No.: 2 Op-Test No.: ___1____

Examiners: _________________

Operators: __________________

Initial Conditions:

86% power. P-8B AFW Pp. is out of service.

Turnover:

Shift orders are to Test Cycle Cont. Spray Valves, per SOP-4.

Event No.

Malf. No.

Event Type*

Event Description 1

N/A SRO (N)

RO (N)

Test Cycle Containment Spray Valves (SOP-4).

2 RX09 SRO (I)

RO (I)

PZR Normal Level Control signal fails low.

3 N/A SRO (T)

Report of Lube Oil Inventory Low 4

OVRD SRO (C)

BOP (C)

Turbine Bypass Valve fails open (ONP-9).

5 OVRD SRO (C)

BOP (C)

RO (R)

Cooling Tower Pp. P-39A trips (ONP-14), and Rapid Downpower (due to degrading vacuum). (ONP-26).

6 FT01A/B SRO (C)

RO (C)

BOTH Main Feedwater Pps. trip, requiring Manual Reactor Trip.

7 OVRD ED12B SRO (C)

BOP (C)

Safety Bus 1D deenergizes, and D/G 1-2 fails to auto start.

8 IA17A/C SRO (C)

RO (C)

Instrument Air Compressors fail to auto start.

9 FW16A/C SRO (M)

BOP (M)

P-8A AFW Pp. trips, P-8C will not start. (EOP-7.0).

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (T)ech Spec

Scenario 2 - Simulator Operator Instructions Reset to IC-16 86% power MOL IC.

AFW Pump P-8B is OOS with a Caution Tag hung on the handswitch.

ENSURE C-2B Instr. Air Compressor is in service, with C-2A and C-2C in AUTO.

INSERT FW03C to prevent P-8C auto start.

INSERT IA17A/C to prevent C-2A/C auto start.

INSERT ED12B to prevent D/G 1-2 auto start.

Event No.

Simulator Operator Instructions 1

Test Cycle Containment Spray Valves per SOP-4.

2 REMOTE 1 INSERT RX09 PZR Normal Level Control signal fails LOW. At examiner direction, remove this malfunction. See note below.

3 Make Phone Call - report as Chemistry that during MS-46 "Verification of Emergency Diesel Generator Stored Lube Oil Inventory" that 1 drum of lube oil was found punctured and empty.

There are 3 55 gallon barrels remaining onsite.

4 Setup for TBV Fail OPEN.

REMOTE 2

1.

CV-0511 Man PB:

PIC-0511-MAN to ON

PIC-0511-M light to OFF

PIC-0511-A Auto lamp to ON

PIC-0511-MNC-2 to ON

PIC-0511-MAN [ZD13P(717)]

2.

Trigger #6 Go to Event _______

type in ZDI3P(717)

Action is dor pic-0511-MNC-2

3.

Trigger #7 4.

Trigger #8

zdi 3p(717)

zdi 3p(717)

dor pic-0511-m

dor pic-0511-a 5

REMOTE 3 INSERT CW01A to trip P-39A Cooling Tower Pp. Crew performs a rapid downpower.

6 REMOTE 4 INSERT FT01A/B (BOTH MFW Pps. trip.)

Manual Reactor Trip 7

REMOTE 5 INSERT OVRD 152-203-1 for opening Bus 1D feeder breaker 152-203 1 minute after the trip.

Note: This override de-energizes Bus 1D without causing a fault (by overriding the handswitch), thereby allowing the BOP to reenergize Bus 1D by starting D/G 1-2.

ED12B (ACTIVE AT SETUP) D/G 1-2 fails to auto start.

8 IA17A/C (ACTIVE AT SETUP) Prevents C-2A/C auto start.

9 REMOTE 6 INSERT FW16A/C Trips P-8A/C if running. Identified concern:

Crew may not meet criteria for Cond. Pp. feed if S/G levels are too low. May elect to brief for

once-thru cooling before initiating a cooldown.

FW03C (ACTIVE AT SETUP) Prevents P-8C auto start.

1.

(EVENT #2) After several minutes call as Shift Manager and explain during I&C activities a wire was mislanded causing PZR level control malfunction. The wire has been relanded properly and both PZR level controllers are fully functional. Recommend that PZR level control be restored to CASCADE.

Scenario 2 - Turnover Information Plant is at 86% power, MOL. Boron is 777 ppm. P-8B Aux. Feedwater Pump is out of service for repairs on the overspeed trip linkage. It is expected to be 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months before reassembly is completed.

Shift orders are to maintain the plant at full power. An additional task is to perform a special test of the Containment Spray Valves to verify that the valves will stroke full open and then closed. This test is to be done in accordance with SOP-4, 7.3.1, "Test Cycle Containment Spray Valves From Control Room".

Documentation of results and completion of this test will be performed by the Shift Manager.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.:

1 Page 1 of 1 Event

Description:

Test Cycle Containment Spray Valves per SOP-4 Time Position Applicant's Actions or Behavior SRO RO Enter SOP-4, 7.3.1 to perform test.

RO Ensures Containment Spray Pumps are not operating:

Indicating lights above handswitches.

Containment Spray header pressure indications.

RO Places handswitches for Containment Spray Valves to TEST on C-03 panel.

CV-3001 CV-3002 RO Verifies open both Containment Spray Isolation Valves by observing indicating lights above control switches.

RO Places handswitches for Containment Spray Valves to CLOSE.

RO Verifies closed both Containment Spray Valves.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.:

2 Page 1 of 1 Event

Description:

PZR Normal Level Control Signal Fails Low Time Position Applicant's Actions or Behavior SRO RO Diagnoses a failure of the normal PZR level control signal:

EK-0734 - chg. pump seal cooling lo pressure alarms due to charging pumps start.

Observes both fixed speed charging pps start.

P-55A variable speed pp rises to maximum speed.

EK-0761, Pressurizer Level Hi-Lo, may alarm.

RO May Takes manual control of P-55A variable speed charging pp.. May also secure both fixed speed pps. (P-55B/C).

RO Manually controls PZR level at program level for current power level (86%).

(Also may swap PZR level controllers.)

SRO Refers to Tech. Spec. 3.4.9 (as directed by the ARP). Determines that maximum allowable PZR level is 62.8%.

NOTE: SRO will receive report from Shift Manager regarding I&C inadvertent open circuit and that PZR level controllers are now functional.

RO Restores one PZR level controller to CASCADE.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.:

3 Page 1 of 1 Event

Description:

Inadequate Lube Oil Inventory On-site Time Position Applicant's Actions or Behavior SRO Receives report from Chemistry that during MS-46 "Verification of Emergency Diesel Generator Stored Lube Oil Inventory" that 1 drum of lube oil was found punctured and empty. There are 3 55 gallon barrels remaining onsite.

SRO Refers to Tech. Spec. 3.8.3, and determines required action is B.1 - restore to limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

NOTE: If asked, NO spill has occurred and no Spill Plan actions are required.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.:

4 Page 1 of 1 Event

Description:

Turbine Bypass Valve Fails Open Time Position Applicant's Actions or Behavior SRO BOP RO Diagnoses Turbine Bypass Valve has failed open:

Various alarms including:

Nuclear Power / delta T, EK-0603, 4, 7, 8 Rack D Notes Tave lowering.

BOP Manually closes the TBV. (Allowed to perform prior to ONP entry, but not required.)

SRO Enters and directs the actions of ONP-9.0, Excessive Load Increase.

SRO BOP Reduce turbine load to restore reactor power to pre-event power level or less.

(Not required if TBV is manually closed.)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.:

5 Page 1 of 1 Event

Description:

P-39A Cooling Tower Pp. Trips Time Position Applicant's Actions or Behavior BOP SRO Diagnoses that P-39A has tripped:

EK-3522, "CLG TWR PUMP P-39A TRIP" Possible lowering trend on Main Condenser vacuum.

SRO Enters and directs the actions of ONP-14, Loss of Condenser Vacuum.

Power Reduction starts here.

SRO BOP RO Initiate a rapid downpower to <55% at a rate of < 300% per hour, as directed by ONP-14 and as controlled by ONP-26, Rapid Downpower.

RO Inserts Group 4 control rods 10" to start power reduction.

BOP Coordinates with RO and commences a turbine derate at rate specified by SRO.

RO BOP Stabilize power at <55% as specified by SRO.

Note: This will take some time to stabilize; i.e., crew will slow rate of power reduction significantly when vacuum starts to stabilize.

BOP Places one Main FW pp. to MANUAL at minimum speed.

Note to Examiner: BOTH Main Feed Pps. will trip here.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.:

6/7 Page 1 of 1 Event

Description:

BOTH Main Feedwater Pumps Trip / Manual Reactor Trip Time Position Applicant's Actions or Behavior BOP SRO Diagnose BOTH MFW pumps have tripped:

EK-0143/44, FW Pump Turbine K7 Trip EK-0961/62, Steam Gen Lo Level EK-0972, Reactor Trip Note to Examiner:

1.

Crew may not have time to manually TRIP THE REACTOR before it trips on Low S/G Level.

2.

Safety Bus 1D deenergizes at time of trip.

ALL Enter EOP-1.0, "Standard Post Trip Actions" and carry out Immediate Actions.

RO Determine that Reactivity Control is MET.

BOP Control the Feedwater System:

Closes ALL MFRVs and Bypass FRVs.

BOP Determine that Vital Auxiliaries - Electrical acceptance criteria are NOT met.

Diagnoses that Bus 1D has deenergized. (This is Event 7.)

Diagnoses that EDG 1-2 has NOT started.

Manually starts EDG 1-2 and ensures loads sequencing on.

(CRITICAL TASK to start EDG 1-2.)

RO Determine that PCS Inventory Control acceptance criteria are MET.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.:

7/8 Page 1 of 2 Event

Description:

Bus 1D De-energizes, Instr. Air Comp. Manual Start Time Position Applicant's Actions or Behavior RO Determine that PCS Pressure Control acceptance criteria are MET.

RO Determine that Core Heat Removal acceptance criteria are MET.

RO BOP Determine that PCS Heat Removal acceptance criteria are not MET.

(May not be met due to low S/G level outside of acceptable range of 5% -

70%.)

RO Determine that Containment Isolation acceptance criteria are MET.

RO Determine that Containment Atmosphere acceptance criteria are MET.

RO Determine that Vital Auxiliaries - Water acceptance criteria are met.

RO Determine that Vital Auxiliaries - Air acceptance criteria are NOT met.

Note:

The air compressor that was running (C-2B) prior to the Rx trip lost power when Bus 1D de-energized. It does NOT sequence back onto the bus. RO must manually start C-2A or C-2C.

(Event 8)

RO Manually starts C-2A or C-2C and/or opens Feedwater Purity Air crosstie CV-1221.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.:

7/8 Page 2 of 2 Event

Description:

Bus 1D De-energizes, Instr. Air Comp. Manual Start Time Position Applicant's Actions or Behavior RO BOP BOP turns panels over to RO and reports to CRS.

SRO BOP Align Control Room HVAC to Emergency Mode within 20 minutes of reactor trip.

SRO BOP Verify at least ONE Condensate Pump and ONE Cooling Tower Pump operating.

SRO BOP Perform Emergency Shutdown Checklist per GOP-10.

SRO Refer to EOP-1.0, Attachment 1, "Event Diagnostic Flow Chart" and diagnose the event.

SRO Transition to EOP-2.0, Reactor Trip Recovery Enter loss of P-78A and P-78C AFW pps. (Event 9)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.:

9 Page 1 of 2 Event

Description:

Loss of All Feedwater (EOP-7.0)

Time Position Applicant's Actions or Behavior RO Diagnoses that NO Auxiliary Feedwater pumps are available:

EK-0139, Aux Feedwater Pump Trip, is alarming No Aux. FW flow indicated.

Indicating lights above control switches.

SRO Re-enters EOP-1.0 Diagnostic Flow Chart and diagnoses a Loss of All Feedwater, EOP-7.0.

(Note: Acceptable if candidate goes directly to EOP-7.0.)

SRO Assigns EOP-7.0 Safety Function Status Checks to STA.

SRO RO Stops all Primary Coolant Pumps.

CRITICAL TASK (to reduce heat input to PCS)

RO Commence emergency boration.

SRO BOP Conserve S/G inventory by closing ALL S/G blowdown valves:

'A' S/G '

B' S/G CV-0767 CV-0768 CV-0771 CV-0770 CV-0739 CV-0738 SRO Evaluates feedwater options and determines that FW using Condensate Pps.

from the Condenser should be used.

NO AFW pps. are available.

NO MFW pps. are available.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.:

9 Page 2 of 2 Event

Description:

Loss of All Feedwater (EOP-7.0)

Time Position Applicant's Actions or Behavior SRO RO Commence a cooldown to establish conditions for feeding S/Gs with a Condensate Pump.

CRITICAL TASK to take actions to attempt establishing conditions for feeding S/G with Condensate Pp.

Note to Examiner: It may not be possible to actually establish the conditions, depending on S/G levels.

In this case, candidate may elect to transition to the Functional Recovery Procedure, EOP-9.0.

Note: After cooldown is established, at the direction of the Lead Examiner, terminate the scenario.

A ppendix D Scenario Outline Form ES-D-1 Facility: Palisades Scenario No.: _ NRC 2005-3 _______

Op-Test No.: _______

Examiners: Operators:

Initial Conditions: IC-16 86% power, MOL, HPSI P-66B tagged out, PIC-0101A is OOS for calibration. Boron 820PPM, Equilibrum Xenon, ASI -0.001, Target ASI +0.012, Reg Rod group 4 at step 113, SGBD flow 20K / SG, Offgas flow 2.0 cfm Turnover: 86% power, MOL. P-66B tagged out for impeller replacement and is scheduled to be returned in 2 days. Shift priority is to increase power to 100% at 4% per hour per GOP-5.

Event No.

Malf.

No.

Event Type*

Event Description 1

N/A RO(R)

SRO(N)

Increase Rx power from 86% power 2

RX06B RO(I)

SRO(I)

PZR Press Controller output Fails Low 3

RX10A BOP(I)

SRO(I)

S/G >A= Level Transmitter LT-701 output Fails Low.

4 SW04B BOP( C)

SRO( C)

Service Water Pump P-7B Trips (P-7C will need to be manually started to increase SW pressure) 5 RC03 RO( C)

SRO( C)

PCS leak (25 gpm) (Tech Spec).

Severity =25 6

OVRDs BOP/RO

( C)

SRO( C)

Initiate Rx Trip per ONP-23.1. Failure of Rx to Trip from either Rx Trip pushbuttons.

7 RC04 RO(M)

BOP(M)

SRO(M)

Small Break LOCA (250gpm)

Value = 25%

8 ED13A

/B SI07A/

B RO ( C)

BOP( C)

SRO (

C)

Failure of SIAS to automatically or manually actuate.

9 SI01A BOP( C)

SRO( C)

P-66A Trips on ground over-current when manually started (no HPSI flow available).

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

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-3 Event No.: 1 Page ___

of ___

Event

Description:

Increase Reactor Power from 86% power Time Position Applicant=s Actions or Behaviors RO Determines amount of reactivity that must compensated for during power increase. Approximate amount of dilution water that needs to be added.

BOP Programs the turbine controls to increase turbine load to 90% power at 4%/Hr.

SRO Directs the BOP to start the power increase.

BOP Starts turbine ramp.

RO Adds primary water to dilute the PCS as necessary to maintain temperature.

RO Monitors core parameters PCS temp., core flux profile, NI strumentation.

in RO Adjust control rods as necessary to control temp and core flux profile.

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-3 Event No.: 2 Page ___

of ___

Event

Description:

PZR Pressure Controller output Fails Low Time Position Applicant=s Actions or Behaviors PZR Pressure Controller PIC-0101B output fails low.

RO RO notices PZR pressure increasing (sprays close and Htr=s energize) or PZR Pressure Off Normal Hi-Lo alarm comes in.

RO Refers to EK-0754, PZR Pressure Off Normal Hi-Lo ARP.

RO Recommend entering ONP-18, Pressurizer Pressure ontrol Malfunctions C

procedure.

SRO Enters ONP-18, Pressurizer Pressure Control Malfunctions procedure and directs RO to take manual control of RO Takes manual control of PIC-0101B and restores PZR pressure to 2060 psia.

SRO Direct the ramp to be placed on hold if necessary while he crew addresses the PZR t

pressure control problem.

RO If directed place ramp on hold.

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-3 Event No.: 3 Page ___ of ___

Event

Description:

S/G >A= Level Transmitter LT-701 output Fails Low Time Position Applicant=s Actions or Behaviors S/G >A= Level Transmitter LT-701 fails low BOP Notices FW Flow increasing, S/G Levels increasing and, PCS Temperature decreasing.

BOP Takes manual control of S/G >A= Level to prevent S/G overfill and restore S/G level to 65%. (60%-70%).

SRO Direct ramp be placed on hold if PCS temperature han c

ges make it necessary.

RO If directed, place the ramp on hold while crew addresses the failed S/G Level Transmitter.

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-3 Event No.: 4 Page ___

of ___

Event

Description:

Service Water Pump P-7B Trips (P-7C will need to be manually started to increase Service Water pressure)

Time Position Applicant=s Actions or Behaviors Service Water Pump P-7B trips.

RO Determines that Service Water Pump P-7B has tripped and standby Service Water Pump did not auto start.

EK-1137 Service Water Pump P-7B Overload / Trip SRO Enters Loss of Service Water procedure ONP-6.1.

SRO Directs BOP to start standby Service Water Pump (P-7C) to restore Service Water System pressure.

SRO Determine that the following Tech. Spec. LCO applies to the failure of the P -7B Service Water Pump.

3.7.8 Cond. A A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-3 Event No.: 5 Page ___

of ___

Event

Description:

PCS leak (25 gpm)

Time Position Applicant=s Actions or Behaviors Initiate PCS leak at 25 gpm.

RO Notices Cnmt Sump level increasing and Cnmt gas monitor level increasing. Will also notice PZR level decreasing and Charging Flow increasing. Informs SRO.

SRO Enter Primary Coolant Leak ONP 23.1.

SRO Direct RO to start additional charging pumps if RO Start additional charging pumps as necessary to maintain PZR level.

SRO RO Determine PCS Leak Rate is in excess of Tech Spec limits, so CV-1064, CV-1065, CV-1910, & CV-1911 must be closed. (Cnmt vent isol. Vlvs) (May trip reactor first and then do this after EOP-1.0).

SRO Evaluate Emergency Plan or direct Shift Manager to evaluate Emergency Plan.

RO SRO Determine PCS leakage rate using charging and tdown and PCP Controlled Bleedoff flow or PZR level le SRO After PCS leakage is determined to be greater than 10 gpm, direct a Rx Trip and enter EOP-1.0.

SRO Direct actions to isolate letdown to conserve PCS inventory per step 4.8 following Rx trip.

RO Isolate letdown to conserve PCS inventory.

(This step and previous step may not occur. Operators will go to EOP-1.0 and not perform these two steps.)

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-3 Event No.: 6 Page ___

of ___

Event

Description:

Initiate Rx Trip per ONP-23.1. Rx Trip doesn=t actuate using either Rx Trip pushbuttons.

Time Position Applicant=s Actions or Behaviors Manual Rx Trip does not actuate from either manual trip location.

RO / BOP Attempts to trip Rx from both Manual Rx Trip SRO Enters EOP-1.0 and directs the de-energizing of control rod using toggle switches in back of control panel OR opening of CRD Clutch Power Feeder Bkrs 42-1RPS and RO / BOP De-energizes control rod using toggle switches in back of control panel OR directs AO to open CRD Clutch Power Feeder Bkrs 42-1RPS and 42-2RPS (Critical Task)

SRO Completes EOP-1.0, and Safety Function Status Check heet.

S Note: After Rx is Tripped enter Event #7

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-3 Event No.: 7-9 Page ___ of ___

Event

Description:

Small Break LOCA (250gpm), Failure of SIAS to actuate, and P-66A trips on ground over-current when manually started.

Time Position Applicant=s Actions or Behaviors RO Determines that leak rate has increased from the initial leak size. Informs the SRO of the increase in leak size or SRO Verify Auto Safety Injection Signal when PZR Pressure reaches 1605 psia RO Attempt to Manually Actuate SIAS, but SIAS doesn=t actuate SRO Direct RO and or BOP to manually start ESF equipment.

RO / BOP Manually start SIAS loads. (Critical Task).

RO / BOP HPSI P-66A starts and trips due to a ground over-current i

SRO Enters EOP-4.0 Loss of Coolant Accident Recovery and then EOP-9.0 Functional Recovery Procedure. Note: A direct entry into EOP-9.0 may be made.

SRO Realize SI flow is less than limits of EOP Supplement 4.

RO Trip two PCPs (A&D normally shutdown to maintain PZR sprays) when PCS pressure decreases below 1300 psia.

BOP Place Hydrogen monitor in service per SOP-38

SRO Determine success paths associated with EOP-9.0 RC-1 RC-3 (with SIS)

DC-1 IC-2 Jeopardized (if above HPSI shutoff head)

PC-3 Jeopardized (if above HPSI shutoff head)

HR-2 Jeopardized (if above HPSI shutoff head)

CI-1 CA-2 RO Trip remaining PCPs to minimize heat input per IC-2

- - - - Need to verify why this is done********************************

SRO RO BOP Initiate Cool Down and Depressurization of PCS to establish ECCS flow.(Critical Task).

Termination Criteria: At discretion of Chief Examiner after PCS Cooldown and Depressurization has been initiated.

A ppendix D Scenario Outline Form ES-D-1 Facility: Palisades Scenario No.: _ NRC 2005-4 ____p-Test No.: ______

Examiners: Operators:

Initial Conditions: IC-17 100% power, MOL, D/G 1-1 tagged out of service.

Turnover: 100% power, MOL. D/G 1-1 tagged out of service for a governor replacement and is scheduled to be returned in 3 days. Boron 770 ppm, ASI

+0.014, S/G blowdown flow 20K per S/G, Offgas flow is 2.0 cfm.

Event No.

Malf.

No.

Event Type*

Event Description 1

RX07B RO (C)

SRO(C)

Pressurizer Level Transmitter LT-0101B fails low.

2 OVRD s

BOP(I)

SRO(I)

LIC-0702 output fails low in automatic. Feed Reg Valve closes and must be re-opened by taking manual control of LIC-0702.

3 CV06 RO(I)

SRO(I)

PT-0202 fails low which causes letdown pressure controller PIC-0202 to close letdown control valve. This causes letdown line relief valve to open. (Tech Spec) 4 SRO Earthquake reported by Outside AO.

5 CH06 A

BOP ( C)

SRO (T,C)

Determines Control Room HVAC unit tripped (Tech Spec).

6 EG04 OVRD s

BOP( C)

SRO( C)

Generator Voltage Regulator failure causes Main Generator voltage to increase.

7 SG01 A

RO( C)

SRO(T,C)

AA@ Steam Generator tube leak starts at 10 gpm.

SRO to determine PCS leakage Tech. Spec. is being exceeded and a Rx Trip is required (Tech Spec).

Severity = 1.0 8

MS06B RO(M)

BOP(M)

SRO(M)

AB@ Steam Generator fault occurs due to a Main Steam Line Code Safety valve failing open.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-4 Event No.: 1 Page ___

of ___

Event

Description:

Pressurizer Level Transmitter LT-0101B fails low.

Time Position Applicant=s Actions or Behaviors Pressurize Pressure Level Transmitter PT-0101A LT-0101B fails low.

RO Determines that PZR spray valves have fully closed and PZR heaters have energized 3 charging pumps are in service, letdown at minimum, and PZR heaters have tripped. Yellow alarm light on >B= controller is lit and EK-0761, Pressurizer level Hi - Lo alarm. Determines that controlling channel LT-0101B has failed low. Informs SRO of observation.

SRO SRO may direct two different action:

1. Attempts to take manual control of the LIC and restore PZR level or,

2. Switch the controlling PZR level control channel to LIC-0101A.

RO Perform actions directed by SRO and restore PZR level to normal operation level (6557% ).

SRO Determines that Tech Spec 3.4.9 (Pzr Lvl > 62.8%) and 3.4.1 (Pzr Press. < 2010 psia) must be entered, if applicable.

SRO Enter ONP-18, Pressurizer Pressure Control Malfunction due to low PZR Press.

BOP Cycle Xfmr PZR Htrs Bkr 152-211-CS to TRIP and then ON.

RO Switch Heater Control Selector Switch to the channel >A=

position

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-4 Event No.: 2 Page ___

of ___

Event

Description:

LIC-0702 output fails low while in automatic.

Time Position Applicant=s Actions or Behaviors BOP Determines the feed reg valve for the AA@ S/G has failed partially closed (45%)

BOP S/G Low level alarm ARP directs manual control be taken to restore S/G level. EK-0962 S/G >A= Lo Level alarm.

SRO Direct BOP to take manual control of LIC-0702 and restore S/G level. ONP-3 Loss of Main Feedwater will be entered.

BOP Takes manual control of LIC-0702 and restores S/G >A=

vel to 65% NR.

le

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-4 Event No.: 3 Page ___

of ___

Event

Description:

Letdown pressure controller PIC-0202 fails low.

Time Position Applicant=s Actions or Behaviors Letdown pressure controller PIC-0202 fails low. Letdown pressure control valve closes as a result.

RO Responds to high letdown line relief valve 2006 discharge temperature high, also responds to red fault light on PIC-0202 controller.

RO Refers to EK-0704 Letdown Hx tube inlet Hi-Lo Press.

Refers to EK-0702, Relief Valve 2006 Discharge Hi Temp SRO Direct RO to take manual control of PIC-0202 and restore letdown line pressure to 460 psig.

RO Take manual control of PIC-0202 and restore and maintain letdown line pressure at 460 psig.

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-4 Event No.: 4 Page ___ of ___

Event

Description:

Earthquake reported by Outside AO.

Time Position Applicant=s Actions or Behaviors Earthquake reported by Outside AO.

SRO Enter ONP-12 Act of Nature procedure.

SRO Contact the National Earthquake Information Center for verification.

SRO Notify I & C to check seismic accelerometers.

SRO Notify Civil / Structural engineering to evaluate affects on plant components.

SRO Maintain current Plant condition until evaluations of equipment is are complete.

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-4 Event No.: 5 Page ___

of ___

Event

Description:

Control Room HVAC Unit Trip.

Time Position Applicant=s Actions or Behaviors Control Room HVAC Unit trip.

BOP EK0249 Control Room Lo Press CPIC-1659/1660 alarms Determines that the CRV air handling unit fan V-95 has tripped and condensing unit VC-11 has tripped. Informs SRO of the problem.

SRO Direct the BOP to align and start the >B= train of CRV.

BOP Starts >B= train of CRV per SOP-24, Ventilation and Air Conditioning procedure per section 7.7.1 or 7.7.2.

1. For the train to be started Ensure fan V-96 CS is in ON.

2. For the train to be started Ensure VC-10 CS is in AUTO.

3. Check for proper indications on the train being started.

Note: Shutdown of >A= train of CRV may be performed at SRO=s direction SRO Determines that Tech Spec 3.7.10 Condition A (7 days) and 3.7.11 Condition A (30 days) must be entered.

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-4 Event No.: 6 Page ___

of ___

Event

Description:

Main Generator Voltage Regulator fails high Time Position Applicant=s Actions or Behaviors Main Generator Voltage Regulator failure high BOP Responds to EK-0317 Generator Hi Voltage / Hz alarm and BOP Check if Generator voltage is normal. Determines that terminal voltage is high, VAR indication offscale out, and the DC Adjuster output is Pegged high at 100%

BOP EK-0317 Generator Hi Voltage / Hz ARP directs BOP to lower DC Adjuster to control Generator terminal voltage between 21 kV and 23 kV.

SRO EK-0310 Generator Voltage Reg Trip ARP Directs BOP to place Voltage Regulator Control Switch to OFF or TEST position. Then directs BOP to lower DC Adjuster to control Generator terminal voltage between 21 kV and 23 kV.

(Note: Candidate may lower voltage using the DC Adjuster prior to going to OFF or TEST on the AC Adjuster.

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-4 Event No.: 7 Page ___

of ___

Event

Description:

AA@ Steam Generator tube leak starts at 10 gpm.

Time Position Applicant=s Actions or Behaviors AA@ Steam Generator tube leak starts at 10 gpm.

RO / BOP Respond to Secondary Radiation alarms, Main Steam Gamma Monitors Condenser Off Gas Monitor & S/G RO Determine Charging Header flow is increasing as PZR level is decreasing SRO Enter ONP-23.2 Steam Generator Tube Leak procedure.

RO / BOP

/ SRO Determine S/G tube leakage rate.

SRO Determine that Tech Spec 3.4.8 for PCS Leakage is being exceeded SRO Direct the Rx to be Tripped and EOP-1.0 to be entered per ONP-23 2 S/G Tube Leak procedure step 4 1 h RO Trip Rx per SRO direction.

SRO Enters EOP-1.0 Standard Post Trip Recovery Procedure.

Enters EOP-5 0 Steam Generator Tube Rupture Recovery

A ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: NRC 2005-4 Event No.: 8 Page ___

of ___

Event

Description:

AB@ Steam Generator becomes Faulted due to a Main Steam Line Code Safety valve failing open.

Time Position Applicant=s Actions or Behaviors AB@ Steam Generator fault occurs due to a Main Steam Line Code Safety valve failing open.

BOP / RO Notices Main Steam Line Pressures decreasing. Informs the SRO of observation.

SRO Using Safety Function Status Check Sheet for EOP-5.0 S/G Tube Rupture determines that the crew should transition to EOP-9.0 Functional Recovery procedure.

BOP Per EOP-9.0 Functional Recovery Procedure place Hydrogen Monitor in service per SOP-38.

RO / BOP Isolate AB@ Steam Generator per EOP Supplement 18.

(Critical Task)

SRO / RO /

BOP SRO determines the following priority of the recovery actions.

SRO Recovery action priorities:

RC-3 MVAE DC-1, AC-2 1 IC-2 PC-3 HR-2 CI-1 CA-2 MVAW-1 MVAA-1 SRO Directs actions of HR-2 (highest jeopardized safety function) and directs a cooldown via steaming of least affected S/G to within 50 psi of most affected S/G and not add to cooldown.. The least affected S/G in this case is the palisades exam Page 56 of 57 2005

Termination Criteria: At the discretion of the Chief Examiner when a PCS Cooldown and Depressurization has been initiated.

palisades exam Page 57 of 57 2005

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