ML20217P064

Forwards Exam Matls Being Submitted by Braidwood Generating Station for Review,Comment & Approval for Initial License Re-Examination Scheduled for Wk of 980413.Submittal Includes SRO Job Performance Measures & Associated Questions

ML20217P064
Person / Time
Site:	Braidwood
Issue date:	03/10/1998
From:	Trusheim M COMMONWEALTH EDISON CO.
To:	Mcneil D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20217P016	List: ML20217P013 ML20217P064
References
NUDOCS 9805060052
Download: ML20217P064 (159)

Text

.)

March 10,1998 Mr. Dell McNeil U. S. Nuclear Regulatory Commission Region III 801 Warrenville Road Lisle, IL 60532-4351

Dear Mr. McNeil:

Enclosed are the examination materials that Braidwood Generating Station is submitting for review, comment, and approval for the Initial License Re-Examination scheduled for the week of April 13,1998 at Braidwood Generating Station.

This submittal includes the Senior Reactor Operator Job Performance Measures and associated questions.

These examination materials have been developed in accordance with Interim Revision 8 of NUREG-1021 (" Operator Licensing Examiner Standards"). Please note that reference I

materials are attached to each individual examination question or item per your reque s Please ensure that these materials are withheld from public disclosure until after the examinations are complete.

If you have any questions or concerns regarding this submittal, please contact Paul Hippely at (815) 458-3411 extension 2353 or 2235.

List of

Enclosures:

Job Performance Measures and questions with references attached Completed Checklists:

ES-301-2 ES-301-3 Examination Security Agreement (ES-201-3)

Sincerely, YWf Mark Trusheim 0;mrating Engineer Braidwood Nuclear Generating Station

'; &J 9905060052 900429 PDR ADOCK 05000456 V

PM

ES-301 Individual Walk-Through Test Outline Form-ES-301-2 Facility: Braidwood Date of Examination:

4/14/98-4/15/98 Excmination Level: SRO Operating Test Number:

1 System / JPM Title / Type Codes

• Safety Planned Follow-up Questions:

Function K/A/G -Importance - Description 1.

Establish Excess Letdown 2

a.

SYS004K104 3.4/3.8 Seal Injection flow control with a loss of DC power.

with ICC9511 out of position closed.

N A

S b.

SYS004K132 2.8/3.1 Restoration of seal return with low pressure in the i

VCT.

l 2.

Respond to a WS System 4

a.

SYS076A201 3.5/3.7 Required operator actions with a loss of Non-essential Malfunction (N-54) service water < P-8.

b.

SYS076K302 2.5/2.8 Determine plant restrictions on a loss of cooling to a D

S stator water cooler.

1 3.

Respond to a PZR Pressure 7

a.

SYS016K302 3.4/3.5 Determine actions that will occur, with no operator Channel Malfunction with action, to a leak in the controlling PZR level channel failure of B/S to Trip reference leg.

b.

SYS016K308 3.5/3.7 Determine actions required with a failed PZR pressure N

A S

detector and failure of PORV and Spray valve to close.

4.

Manually initiate 5

a.

SYS026A401 4.5/4.3 Determine required operator actions to close ICS019 Containment Spray. (N-46) valves on a steam break.

b.

SYS026K406 2.8/3.2 Determine CS system status with auto start signal M

S L

present and ICS010A inadvertently closed.

5.

Perform an Emergency I

a.

SYS004K201 2.9/3.1 Knowledge of Emergency boration paths available Boration with failure of a coincident with a turbine trip and loss of offsite power.

1 CV pump. (N-27) l b.

SYS004A404 3.2/3.6 Determine required amount of emergency boration for M

S L

stuck rods and low RCS temperature.

6.

Crosstic of ESF and Non-6 a.

SYS064A205 3.1/3.2 Detennine allowable DG loading while crosstied to ESF Bus during BwEP-1, Non-ESF bus.

j l

Loss of RCS. (N-94) b.

SYS062K403 2.8/3.1 Determine electric plant lineup following loss of Non-l D

S L

ESF 4KV bus with no operator actions.

l 7.

Respond to a Safety 3

a.

SYS006K409 3.8/4.2 Determine valve position following operation during

)

l Injection with Loss of an S1 with a loss of an instrument bus.

Instrument Bus 114.

b.

SYS013K401 3.9/4.3 Determine how to reset S1 with a reactor trip breaker N

A S

failed closed.

8.

Respond to a Loose Parts 4

a.

SYS016-2.2.22 3.8/4.2 Identify failure to comply with technical Monitor Alarm. (N-48) specifications on loss of 2 RCS flow instruments.

b.

SYS003K614 2.6/2.9 Determine RCP shutdown is required when abnormal D

P conditions exist after pump start 9.

Perform a Local Reset of 2

a.

SYS013K403 3.9/4.4 Identify what protection is available when Si signals Phase A Isolation. (N-92) are blocked at P-11.

b.

SYS013K502 2.9/3.3 Determine what Automatic protection is available D

P when placing SSPS into a " Shutdown Condition"

10. Align the Fire Hazards 7

a.

APE 068AK206 2.4*/2.7 Explain the reason for pulling control power fuses Panel. (N-34) when taking local control.

D P

R b.

APE 068AK310 3.9/4.2 Explain w hy letdown is reduced prior to evacuation of the control room.

Type Codes: (D) Direct from bank,(M)odified from bank,(N)ew,(A)lternate Path,(C)ontrol Room,(S)imulator,(P)lant, (L)ow Power / Shutdown. (R)CA NUREG-1021 Interim Rev. 8 January 1997 i

j

nk, JOB PERFORMANCE MEASURE TASK TITLE: Excess Letdown Operation with.1CC9511 out of position closed JPM No.:

NRC-1 REV:

0 TPO No.:

IV.C.CV-07 K&A No.:

SYS004A4.05 TASK No.:

P1-CV-TK-007 K&A IMP:

3.6/3.1 TRAINEE:

Kurt Heinrich DATE:

4/15/98 EVALUATOR:

Dell McNeil Th3 Trainee PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS:

(*) - 4, 5, 6 JPM TIME:

CRITICAL TIME: NA APPRCX. COMPLETION TIME 10 MINUTES EVALUATION METHOD:

LOCATFON:

X PERFORM IN PLANT SIMULATE X

SIMULATOR GENERAL

REFERENCES:

I 1.

BwOP CV-15, Rev. 8 MATERIALS: None TASK STANDARDS:

1.

Establish excess letdown.

2.

Identify loss of cooling to excess letdown heat exchangers TASK CONDITIONS:

1.

You are the Unit NSO.

2.

Unit is at Power, Steady State.

3.

All plant systems and controls are normal.

INITIATING CUES:

1.

Last shift identified increasing AP across the RC filter.

2.

The US directs you to establish excess letdown from all RCS loops to the VCT through both Excess Letdown heat exchangers and secure normal letdown to facilitate investigation of the RC filter.

I 1

NRC-1 1

3/9/98 7:19 AM I

1 1

n.

SIMULATOR SETUP:

IC-16, 50% power.

1.

Close ICC9411 A&B by modifying remote function MRF CC35 0% and MRF CC36 0% on'sim diagram CC5.

. f'.

)

l 4

l l

l NRC-1 2

3/9/98 7:19 AM l

l

a PERFORMANCE CHECKLIST STANDARDS UN EAI EAI EZA RECORD START TIME 1.

Refer to BwOP CV-15.

Locate and Open O-0 0

BwCP CV-15.

(May be performed at any time.)

2.

Verify Rx Power limit.

Verify Rx Power is at O

O O

least 0.1% below the applicable power limit.

3.

Verify seal water return Verity ICV 8100 and O

O O

valve lineup.

1CV8112 open.

• 4.

Establish excess letdown Open:

D D

O flow.

• 1CC9437A

• 1CC9437B l

0 Verify /Close l

1HCV-CV123 r

(CUE: The SM does not want Seal Return directed o Place 1CV8143 to VCT l

to Spray Nossles.)

position I

• 5.

Establish Flow-Open Loop Drains:

U C

C l

e Loop drain valves (IRC8037A/B/C/D)

• ICV 8153A/B e Slowly OPEN 1HCV-CV123 to obtain flow.

• 6.

Identify loss of cooling to Identify Excess O

O O

i Letdown outlet Excess letdown heat exchangers and close 1HCV-temperature on ITI-CV123.

122A >16 5'F.

Identify loss of i

cooling to heat exchanger and close 1HCV-CV123 NRC-1 3

3/9/98 7:19 AM

I l

PERFORMANCE CHEQ,KLIST STANDARDS UN SAT SAT Ela 7

Notify Unit Supervisor and Notify US of failure O

O O

e recommend investigation.

• Recommend investigating failure (CUE: This completes this JPM,)-

RECORD STOP TIME COMMENTS:

• /

NRC-1 4

3/9/98 7:19 AM l

i JPM Questions Question No: _1_

Reference Use: YES/NO

)

}

Unit 1 is at 100% power with the following CVCS lineup:

j i

1 A Regen _ and letdown Heat Exchangers on line o

ICV 8149A and ICV 8149C are open o

ICV-182 is set at 70% open o

o ICV-121 controller at 65%

o PZR 12 vel stable at 60%

I The following indications were then observed:

Annunciator 1-21-E10,125VDC DIST. PN's 111/113 VOLT LOW, alarms c

o DC Bus 111 volts indicates low on IPM01J The Unit Supervisor directs you to maintain 8 gpm seal injection to each RCP. With ICV-182 remaining at 70% open, what is the total flow indicated on IFI-121 after adjusting to 8 gpm per pump?

i l

Expected Answer:

32 gpm total charging flow. (Regen Hx charging and letdown isolation valves ICV 8389A and ICV 8324A fail closed) i l

Actual Answer:

l i

Candidate's response matched expected answer.

t Sat Unsat K/A: SYS004K104 3.4/3.8 LP Objective: Chap 15A; K.O.14 i

Reference (s):

20E-1-4030CV24, CV27 P&lD M-64, sheet 5 BwAR 1-21-E10

[

NRC-1 5

3/9/98 7:19 AM

i Question No: 1 Reference Use: YES/NO An inadvertent Phase A occurs on Train B with Unit 1 at full power. The following conditions exist:-

PZR Pressure is 2315 psig and decreasing slowly o

PZR Level is 64% and increasing o

VCT level is 38% and increasing o

VCT pressure is 12 psig and increasing o

Auto Makeup is occurring o

Phase A has just been reset o

What operator actions are required to restore seal return to normal?

)

Expected Answer:

y Raise VCT pressure to > 15 psig, then open 1CV8112. (1CV8100 does not close on Train B OA) 1 Actual Answer:

Candidate's response matched expected answer.

Sat Unsat K/A: SYS004K132 2.8/3.1 LP Objective: RCP-1; K.O. 3 R;ference(s):

IBwOA PRI-13, Step 9, page 5 of 11 20E-1-4030CV12, EF60 NRC-1 6

3/9/98 7:19 AM

4 OPERATOR OUESTION SHEET Question No:

1 Reference Use: YES/NO Unit 1 is at 100% power with the following CVCS lineup:

I A Regen and Letdown Heat Exchangers on line o

ICV 8149A and ICV 8149C are open o

ICV-182 is set at 70% open o

o ICV-121 controller at 65%

o PZR Level stable at 60%

The following indications were then observed:

o.' nnunciator 1-21-E10,125VDC DIST. PNL 111/113 VOLT LOW, alarms o DC Bus 111 volts indicates low on IPM01J The Unit Supervisor directs you to maintain 8 gpm seal injection to each RCP. With ICV-182 remaining at 70% open, what is the total flow indicated on IFI-121 after adjusting to 8 gpm per pump?

I l

l NRC-1 7

3/9/98 7:19 AM

i OPERATOR OUESTION SHEET Question No: _1 Reference Use: YES/NG An inadvertent Phase A occurs on Train B with Unit 1 at full power. The following conditions exist:

PZR Pressure is 2315 psig and decreasing slowly o

PZR Level is 64% and increasing o

VCT level is 38% and increasing o

VCT pressure is 12 psig and increasing o

Auto Makeup is occurring o

Phase A has just been reset o

What operator actions are required to restore seal return to normal?

f<

l L

NRC-1 8

3/9/98 7:19 AM

TASK CONDITIONS:

1.

You are the Unit NSO.

2.

Unit is at Power, Steady State.

3.

All plant systems and controls are normal.

' INITIATING CUES:

1.

Last shift identified increasing AP across the RC filter.

2.

The US directs you to establish excess letdown from all RCS loops to the VCT through both Excess Letdown heat exchangers and secure normal letdown to facilitate investigation of the RC filter.

i NRC-1 9

3/9/98 7:19 AM

s,

" f JO3 PERFO3JfANCE MEASURE TASK TITLE: ' Rocp:nd to a t's System Malfunction l

l

.JPM No.

NRC-2 REV:

8 i

TPO No.:

IV.D.OA-33 K&A No.:

SYS076A2.01 TASK No.:.'

P1-OA-TK-091-K&A IMP:

3.5/3.7 TRAINEE:

Kurt Heinrich DATE:

4/15/98 EVALUATOR:

Dell McNeil Tha Trainee: PASSED' this JPM.

TIME STARTED:

i-FAILED TIME FINISHED:

1 CRITICAL ELEMENTS:

(*) 4, 5 JPM TIME:

1 CRITICAL TIME: NA APPROX. COMPLETION TIME 6 MINUTES EVALUATION METHOD:

LOCATION:

-PERFORM IN PLANT SIMULATE SIMULATOR l.

i GENERAL

REFERENCES:

1.

OBwOA SEC-5, Rev. 54 2.

BwOP WS-1, Rev. 6 and BwoP WS-3, Rev. 5 3.

BwAR 0-38-B10, WS HDR PRESS LOW, Rev 5 MATERIALS: None-l TASK STANDARDS:

l 1.

Respond to a WS System Malfunction.

l

' TASK CONDITIONS:

1.

You are the Unit 1 Admin NSO.

2, WS pumps OB & OC are running.

i It INITIATING CUES:

l-1.

The Equipment Attendant repor?;s that the Oil Level in the upper trotor bearing of OC WS pump is out of sight low.

2.

Bearing temperatures are rising steadily and are now at 180*F.

3.

Annunciator BwAR 0-38-B10, WS HDR PRESS LOW has just alarmed.

s NRC-2 1

3/10/98 7:23 AM

SIMULATOR SETUP:

IC-16, 50% power.

1. Start WS pump OB and secure WS pump OA.

3 Modify remote function MRF SW38 open on sim diagram SW9 to prevent 0A pump auto start.

3. Modify remote function MRF SW26 10% on sim diagram SW9 to cause low amps on the 1C pump.

4 N

l l

J i

NRC-2 2

3/10/98 7:23 AM i

.)

PERFORMANCE CHECKLIST STANDARDS UN SAT SAT N/A R~ CORD START TIME 1.

Refer to OBwOA SEC-5 Locate and Open OBwOA O

O O

SEC-5

.(May be done at any time.)

2.

Initiate BwOA SEC-5 for both Notify both units to O

O O

units.

initiate BwOA SEC-5.

3.

Check WS System Status Check:

O O

O l

WS Header Pressure

>80 psig i

I Dispatch an Operator O

O O

• 4.

Start the OA WS Pump e

to Verify WS Pump is (CUE: Operator reports properly lined up for CA WS Pump is starting per BwOP ready for starting.

WS.1 (Step 3) e Place Control Switch (CUE: Operator reports that for OA WS Pump in OA WS Pump is normal START.

l following start.)

• 5.

Stop the OC WS Pump Place Control Switch for O O

O OC WS Pump in TRIP / PULL-OUT Position.

6.

Check the.0C WS Pump Dispatch an Operator to check the OC WS Pump l

(CUE: Operator reports OC WS properly shutdown, pumpp has stopped and all conditions are Dispatch operator to e

normal after the verify tripped WS shutdown

• pump not rotating.

NRC-2 3

3/10/98 7:23 AM L

l-t

PERFORMANCE CHECKLIST STANDARDS UN SAT SAT N/A 7.

Check the Status of the Check -

O U

O Station Air Systems

• Station Air Compressor run (CUE: Station Air compressor lights.

temperatures are normal.)

Dispatch Operators to e

check running SAC temps 8.

Check WS Header Pressure Verify WS Pressure > 80 0

0 0

<80 psig.

psig.

9.

Evaluate plant status.

Dispatch operators to O

,d O

check (CUE: System intact equipment temps are WS system piping normal.)

intact Running equipment not overheated.

(CUE: This completes this JPM.)

)

RECORD STOP TIME COMMEIITS:

l

'NRC-2 4

3/10/98 7:23 AM i

JPM Ouestions Question No:

1 Reference Use: YES@O Unit 1 is coming out of a forced shutdown. The following conditions exist:

Unit 1 is currently holding at 28% reactor power for Chemistry.

o Unit 2 is in a refueling outage.

o The running WS pump trips.

e The standby pump auto started, o

The third pump is OOS for maintenance.

o The discharge check valve for the tripped pump failed to close.

o What actions are required for the current plant conditions?

Expected Answer:

Manually close discharge valve for tripped pump.

Trip the Main Turbine if the TGTMS GEN TEMP TRIP STPT EXCEEDED annunciator is lit and perform IBwOA TG-8, Turbine Trip Below P-8, while continuing with IBwOA SEC-5.

Actual Answer:

i l

Candidate's response matched expected answer.

l Sat Unsat K/A: SYS076A201 3.5/3.7 LP Objective: 1/0BwOA SEC-5: K.O. 3 l

Reference (s):

OBwOA SEC-5, Step 2.b. RNO, page 2 of 1I IBwOA SEC-5, Step 2.a. RNO, page 3 of 4 NRC-2 5

3/10/98 7:23 AM L.

Question Nr: J_

Reference Use: YES/NO The following plant conditions exist:

Unit 1 is at 100% power o

A Non-essential service water break has occurred at the inlet to the 1 A stator water cooler o

o 'Non-essential service water pressure is decreasing and the standby pump auto starts o WS Hdr Press annunciator 0-38-B10 is in Stator Cooling Water Disch Temp High annunciator 1-18-B14 is in o

The local operator reports isolating leak by shutting 1WS033A and 1WS034A. What further actions are required to stabilize the unit?

Expected Answer:

With one stator water cooler isolated, main generator load should be reduced to 75% of rated load.

(approx. 880 Mw)

Actual Answer:

l 1

i f Candidate's response matched expected answer.

Sat,_ Unsat __.

K/A: SYS076K302 2.5/2.8 LP Objective: Chap 21; K.O. 8a.

Reference (s):

BwOP GC-13 C.3., D.I.,E.3.

i NRC-2 6

3/10/98 7:23 AM

QPERATOR OUESTION SHEET Question No:

1 Reference Use: YES/NG Unit 1 is coming out of a forced shutdown. The following conditions exist:

Unit 1 is currently holding at 28% reactor power for Chemistry.

o Unit 2 is in a refueling outage.

o The running WS pump trips.

o The standby pump auto started.

o The third pump is OOS for maintenance.

o The discharge check valve for the tripped pump failed to close.

e What actions are required for the current plant conditions?

l 1

l I

NRC-2 7

3/10/98 7:23 AM

OPERATOR OUESTION SHEET Question No: 1 Reference Use: YFSNO The following plant conditions exist:

Unit 1 is at 100% power o

o A Non-essential service water break has occurred at the inlet to the 1 A stator water cooler Non-essential service water pressure is decreasing and the standby pump auto starts o

o WS Hdr Press annunciator 0-38-B10 is in Stator Cooling Water Disch Temp IIigh annunciator 1-18-B14 is in o

l The local operator reports isolating leak by shutting IWS033A and IWS034A. What further actions are required to stabilize the unit?

r l

l NRC-2 0

3/10/98 7:23 AM i

TASK CONDITIONS:

1.

You are the Unit 1 Admin NSO.

2.

WS pumps OB & OC are running.

INITIATING CUES:

1.

The Equipment Attendant reports that the Oil Level in the upper motor bearing of OC WS pump is out of sight low.

2.

Bearing temperatures are rising steadily and are now at 180 F.

3.

Annunciator BwAR 0-38-B10, WS IIDR PRESS LOW has just alarmed.

NRC-2 9

3/10/98 7:23 AM t

j4' l

JOB PERFORMANCE MEASURE TASK TITLE:

Respond to a PER Pressure Channel Nalfunction with Failure of Bistable to Trip.

l l

lJPM No.:

NRC-3 REV:

0 TPO No.:

IV.D.OA-11 K&A No.:

SYS016A2.01 f

TASK No.:

P1B-KF-TK-007 K&A IMP:

3.0/3.1 P1-OA-TK-007 TRAINEE:

Kurt Heinrich DATE:

4/15/98 EVALUATOR:

Dell McNeil

~

Tha Trainee:

PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

4 CRITICAL ELEMENTS:

(*) 3, 6, 7, 10 JPM TIME:

CRITICAL TIME: NA APPROX COMPLETION TIME 1,8 MINUTES EVALUATION METHOD:

LOCATION:

X PERFORM IN PLANT SIMULATE X

SIMULATOR GENERAL

REFERENCES:

1.

1BwOA INST-2 (Attachment B), Rev. 57 2.

Technical Specifications 3.3.1, 3.3.2, 3.3.3.5,

3.2.5 MATERIALS

None TASK STANDARDS:

1.

Perform actions required to respond to a PZR Pressure channel failure.

2.

Identify all associated Tech Spec LCO's.

3.

Identify the proper action statements for all associated LCO's.

4.

Identify failure of bistable to trip.

TASK CONDITIONS:

1.

You are the Unit 1 NSO.

l 2.

Unit is at power.

l INITIATING CUES:

1.

Respond to changing plant conditions.

NRC-3 1

3/10/98 7:31 AM

0

,9 himuletor Satup:

IC-16, 50% power.

t i

NRC-3 2

3/10/98 7:31 M

PERFORMANCE CHECKLIST STANDARDS UN SAT SAT ELA RECORD START TIME 1.

Enter 1BwOA INST-2 Locate and Open IBwOA O

O O

INST-2 to Attachment B.

(May be done any time.)

2.

Check PZR Pressure.

Observe all PZR pressure O

O O

channels 455-458.

Identify Pressure channel 455 Failed High

• 3.

Return Pressurizer Pressure Place Master PZR O

O O

to normal.

pressure controller in MANUAL.

Control PZR pressure

/

Select an operable a

channel.

4.

Check PZR PORVs, Spray check:

O O

O valves and Heaters.

PZR PORV's - CLOSED PZR Spray Valves -

e NORMAL PZR Heaters - Normal 5.

Select operable PZR pressure Recorder Channel O

O O

channel on recorder.

Selector switch positioned to any channel but 455.

• 6.

Trip associated bistables.

o Ensure no other O

O O

channels are in test or tripped.

• Dispatch an NSO to 1PA01J and Trip the following bistables.

]

• PB455A(C1-153, BS-1)

• PB455C(Cl-153, BS-4)

• PB455D(C1-153, BS-3)

• PB455B(C1-153, BS-2)

• TB411C(C1-124, BS-3)

(Does not trip)

• TB411D(C1-124, BS-4) l o

NRC-3 3

3/10/98 7:31 AM

PERFORMANCE CHEQKLIST STANDAR2.S UN SAT SEE Elb

• 7.

Identify failure of Bistable Identify failure of O

O O

TB411C to trip.

Bistable TB411C to trip (glg US has been notified and directs you to o Notify US of failure continue with the of bistable to trip procedure and evaluate Tech specs upon completion) 8.

Check P-11 Interlock.

Check:

O O

O e P-11 window dark.

9.

Check PZR Pressure Control Check:

O O

O in Auto.

• PORV's in Auto PZR Sprays in Auto e

e PZR Master Pressure Controller in Auto

• 10.

Determine LCOs and action Locate and open O

O O

statements.

Technical Specifications, determine required actions:

(g!g: The SM requests all

• LCO 3.3.1 Applicable Action o

F.U.

7, 9,

10 statements.)

o 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to trip bistables Identify need to trip bistable TB411C within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

• LCO 3.3.2 o

F.U. 1.d, 9.a o 6 Hour to trip bistables o 1 Hour to ensure P-11 is de-energized.

• LCO 3.3.3.5 o

F.U. 4 o ' Restore in 7 days

-or-HSB in 6 hrs and HSD in 6 hrs o LCO 3.2.5 o Restore in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

-or-Reduce Thermal Power to < 5%

within the next 4 hrs NRC-3 4

3/10/98 7:31 AM

4 PERPORMANCE CHECKLIST STANDARDS UN EAT SAT

((/A (CUE: This completes this JPM.)

RECORD STOP TIME COMMENTS:

/

9 l

NRC-3 5

3/10/98 7:31 AM

JPM Ouestions l

Question No:

1 Reference Use: YES/NO A leak of 5 gpm occurs on the reference leg of controlling pressurizer level channel 459 with the unit at full power.

With no operator actions, what is the sequence of events that will occur with no operator actions to l

this failure?

l Expected Answer:

1. Indicated level will be high l

2. Charging flow will decrease to minimum

3. Letdown will isolate at 17% on ILT-460

4. Heaters will turn off at 17%

5. Level will increase due to letdown isolation

6. B/U heaters will turn on at > 17%

7. High level alann will be received at 70%

8. Reactor trip will occur at 92% on ILT-460 and 461.

Actual Answer:

I Candidate's response matched expected answer.

Sat Unsat K/A: SYS016K302 3.4/3.5 LP Objective: Chap 14; K.O.19 Reference (s):

UFSAR Fig 7.2-1 NRC-3 6

3/10/98 7:31 AM i

l I

L

4 Question No:

2 Reference Use: YES/NO Unit 1 is at 25% power with the Pressure Control Channel Select switch is in the CH-455/CI(-456 position. Pressure channel 455 fails high and the following plant conditions are observed:

The pressurizer spray valves and PORV-455A opens Pressure has decreased below 2200 psig The pressurizer PORV-455A and spray valve RY455B will not close manually What actions are required for this situation?

Expected Answer:

Close the PORV-455A block valve,1RY8000A; trip the Reactor; trip the ID RCP Actual Answer:

Candidate's response matched expected answer.

Sat Unsat K/A: SYS016K308 3.5/3.7 LP Objective: INST-2; K.O. 4 Reference (s):

OA INST-2 NRC-3 7

3/10/98 7:31 AM

OPERATOR OUESTION SHEET Question No:

1 Reference Use: YES/NO A leak of 5 gpm occurs on the reference leg of controlling pressurizer level channel 459 with the unit at full power.

With no operator actions, what is the sequence of events that will occur with no operator actions to this failure?

I i

i NRC-3 8

3/10/98 7:31 AM

OPERATOR OUESTION SHEET Question No:

2 Reference Use: YES/NO Unit 1 is at 25% power with the Pressure Control Channel Select switch is in the CH-455/CH-456 position. Pressure channel 455 fails high and the following plant conditions are observed:

The pressurizer spray valves and PORV-455A opens Pressure has decreased below 2200 psig The pressurizer PORV-455A and spray valve RY455B will not close manually What actions are required for this situation?

,/

l l

NRC-3 9

3/10/98 7:31 AM

TASK CONDITIONS:

1.

You are the Unit 1 NSO.

2.

Unit is at power.

I INITIATING CUES:

1.

Respond tr changing plant conditions.

I l

i l

j l

l i

NRC-3 10 3/10/98 7:31 AM

4.

JOB PERFORMANCE MEASURE TASK TITLE: Nanually Initiate Containment spray JPM No.:

NRC-4 REV: 6 TPO No.:

IV.D.CS-01 K&A No.:

SYS026A401 TASK No.:

P1-CS-TK-001 K&A IMP:

4.5/4.3 TRAINEE:

Kurt Heinrich DATE:

4/15/98 EVALUATOR:

Dell McNeil Th2 Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS:

(*)

5, 7, 8

JPM TIME:

CRITICAL TIME: NA APPROX COMPLETION TIME 11 MINUTES i

EVALUATION METHOD:

LOCATION:

L X PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL

REFERENCES:

1.

18wFR-Z.1, Rev.

1, WOG-1B MATERIALS: None TASK STANDARDS:

1.

Perform the actions required to manually initiate Containment Spray operation.

TASK CONDITIONS:

1.

You are the Unit NSO.

2.

A Large Break LOCA has occurred, IBwEP-1 is in Progress.

3.

The ECCS is in the injection mode, RCS pressure - 250 psig.

}

4.

RCP's have been stopped.

I INITIATING CUES:

l

1. The CNMT PRESS HI-3 annunciator (1-3-B4) has just alarmed and the STA has informed you that an Orange Path exists on Containment.

(No other Orange or Red paths exist.)

J

2. The US directs you to perform the actions of IBwFR-Z.1, " Response to High Containment Pressure",

NRC-4 1

3/10/98 7:54 AM t

Simulator Setup:

IC-16, 50%' power.

1..

On simulator diagram RP15 modify remote function MRF-RP63 OUT to prevent valve operation on B Train CS.

2.

On simulator diagram RP14 modify remote functions MRF RP36 OUT and MRP RP37 OUT to prevent operation of A Train CS.

3.

Insert a Large Break LOCA'on loop A, IMF TH06A MAX Value.

4.

Freeze simulator when'Hi-3 in containment occurs and gpvto run when examiner is ready.

'5.

When candidate manually actuates CS, modify remote functions RP36 and RP37 to normal.

NRC-4 2

3/10/98 7:54 AM

PERFORMANCE CHECKLIST STANDARDS UN EAl EAI E/3 RECORD START TIME 1.

Enter _BwFR-Z.1 Locate and Open O

O O

DwFR-Z.1 2.

Verify Containment Isolation Check Containment O

O O

Isolation Phase A Group 3 Monitor Lights 3.

Verify Containment Check Containment Vent.

O O

O Ventilation Isolated Isolation Group 6 Monitor Lights 4.

Check if containment Spray Check if Containment O

O O

is Required.

pressure has increased

>20 psig.

• 5.

Verify Valve Alignment -

Identify 1CS007A&B D

D D

Manually Actuate Containment closed.

Spray Manually actuate CS and Phase B 1 sol.

6.

Identify failure of B train 1A CS Pump Run Light O

O O

i CS to Actuate LIT IB CS Pump Run Light NOT LIT

• 7.

Manually open 1CS007B Place ICS007B Control O

O O

Switch to Open e

Place PP 1B Test O

O O

• 8.

Manually open 1CS019B Switch in Test Place 1CS019B Control Switch to Open i

o Place PP 1B Test i

Switch in Test 9.

Verify open 1CS010A&B open Verify iCS010B open O

O O

NRC-4 3

3/10/90 7:54 AM

4 PERFORMANCE CHECKLIST STANMRDS UN SAT SAI Ela 10.

Verify CS Pumps Running Check:

O O

O 1A CS Pump Run Light e

LIT IB CS Pump Run Light LIT 11.

Verify Phase B Valves closed.

Verify Cnmt Isolation O

O O

Phase B Group 6 Monitor Lights LIT 12.

Verify all RCP's secured Verify all RCP's secured O

O O

r (53[E This complette this JPM.)

RECORD STOP TIME

~

COMMENTS:

1 I

i I

-NRC-4 4

3/10/98 7:54 AM

l l

JPM Ouestions l

Question No:

1 Reference Use: YES/NO The following plant conditions exist on Unit 1 following a steamline break inside containment:

RCS Pressure is 1650 psig and rising o

o PZR Level is 0%

RCS Temp is 420 F and decreasing slowly.

o Containment pressure is 24 psig and decreasing slowly.

o o CS Add Tank 12 vel is 62%

Transition to EP-2 has just been performed o

The US directs you to secure NaOH addition due to high containment pressure caused by secondary break.

What actions are required to perform this action?

Expected Answer:

4 Reset CS Actuation signal and close ICS019A and B.

Actual Answer:

l Candidate's response matched expected answer.

Sat Unsat K/A: SYS026A401 4.5/4.3 LP Objective: EP-1 Series; K.O.1.d Ref:renn(s):

20E-1-4030CS06 1BwEP-1, Step 8, Page 8 of 24 l;.

l i

NRC-4 5

3/10/98 7:54 AM

.Questi:n N : _2_

Refercnce Use: YES/NO During a control board valve lineup, normally open ICS010A was inadvertently closed. A large break LOCA has just occurred while the plant was in Mode 3.

What is the status of the Containment Spray system after containment pressure reaches 20 psig with no operator actions?

Expected Answer:

Both containment spray pumps will be running supplying blended flow to containment.

Actual Answer:

l l

l l

l Candidate's response matched expected answer.

Sat Unsat K/A: SYS026K406 2.8/3.2 LP Objective: Chap 59; K.O. 8 R:ference(s):

20E-1-4030CS01, 02, 07 i

t NRC-4 6

3/10/98 7:54 AM

OPERATOR OUESTION SHEET Question No:

1 Reference Use: - YES/NG j

The following plant conditions exist on Unit 1 following a steamline break inside containment:

RCS Pressure is 1650 psig and rising o

o PZR Level is 0%

RCS Temp is 420 F and decreasing slowly.

o Containment pressure is 24 psig and decreasing slowly.

o o CS Add Tank level is 62%

Transition to EP-2 has just been performed o

The US directs you to secure HaOH addition due to high containment pressure caused by secondary break.

What actions are required to perform this action?

l l

I NRC-4 7

3/10/98 7:54 AM 1

7 OPERATOR OUESTION SHEET Question No:

2 Reference Use: YES/NO During a control board valve lineup, normally open ICS010A was inadvertently closed. A large break l

LOCA has just occurred while the plant was in Mode 3.

What is the status of the Containment Spray system after containment pressure reaches 20 psig with no t

operator act,ons?

i l

t i

NRC-4 8

3/10/98 7:54 AM

1 9

TASK. CONDITIONS:

1.

-You are the Unit-NSO.

2.

'A Large Break LOCA has occurred, 1BwEP-1 is in Progress'.

.3.

The ECCS is.in the injection mode, RCS pressure ~ 250 psig.

4.

RCP's have been stopped.

. INITIATING CUES:

1.

The CNMT PRESS HI-3 annunciator (1-3-B4) has just alarmed and the STA has informed you that an Orange Path exists on Containment.

(;No other Orange or Red paths exist.)

2.

The US directs you to perform the actions of 1BwFR-Z.1, i

" Response to High Containment Pressure".

l

(

NRC-4 9

3/10/98 7:54 AM

5g JOB PERFORMANCE MEASURE LTASK TITLE: Perform an Einergency Boration JPM No.:

NRC-5 REV:

0 TPO No.:

IV.D.OA-08 K&A No.:

SYS004A2.14 TASK No.:

P1-OA-TK-033 K&A IMP:

3.8/3.9 TRAINEE:

Kurt Heinrich DATE:

4/15/98 EVALUATOR:

Dell McNeil Tha Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS:

(*) 2, 3 JPM TIME:

CRITICAL TIME: NA APPROX COMPLr.; TION TIME 10 MINITIES EVALUATION METHOD:

LOCATION:

f X PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL

REFERENCES:

1.

IBwOA PRI-2, Rev. 56 2.

1BwAR 1-9-A3, Rev SE1 i

MATERIALS: None TASK STANDARDS:

1.

Initiate Emergency Boration of the RCS.

TASK CONDITIONS:

j 1.

You are the unit NSO.

2.

A Reactor Trip has occurred and 1BwEP ES-0.1 is in progress at Step 5.

INITIATING CUES:

1.

Control Bank D, Group 1, Rod Bottom Lights are NOT LIT and the Group 1 Rods indicate 198 steps.

2.

The US directs you to commence Emergency Boration in accordance with 1BwOA PRI-2.

NRC-5 1

3/10/98 8:05 AM

~E Eimulator Setup:

IC-16, 50% power

1. Insert malfunctions FW43 and FW44 to trip AF pumps to prevent excessive cooldown.

2. Insert malfunctions RD05D4 200 steps and RD05M12 200 steps to stick 2 control rods out.

3. Trip 1A CV pump and the Main Turbine.

4. Af ter the reactor trips, freeze the simulator until the examiner is ready to proceed.

l NRC-5 2

3/10/98 8:05 AM

T PERFORMANCE CHECKLIST STANDARDS UN EAT SAI E/.h RECORD START TIME l

l 1.

Refer to 1BwOA PRI-2.

Locate and Open O

O O

l' 1BwOA PRI-2.

(NOTE: May be done at anytime.)

• 2.

Verify Cent. Chg. Pump Identify trip of 1A CV O

O O

]

running pump and start 1B CV

, pump as follows:

o verify suction source

- ICV 112B & C open Start 1B CV pump

• 3.

Align boration flowpath

~

Place 1CV8104 Control O

O O

3 Switch to Open.

-f j

Start. Boric Acid Transfer Pump e Check boration flow >

30 gpm.

O Increase Charging flow as necessary 4.

Energize Pzr backup heaters.

Manually turn on the O

O O

Backup Heaters.

l (EEE: This completes this JPM.)

RECORD STOP TIME l

i I

COMMENTS:

l NRC-5 3

3/10/98 8:05 AM

I i

l l

JPM Questiona l

Question No:

1 Reference Use:

YES/NO l

i l

Due to faults on Bus 143 and in the switchyard, both units have lost offsite power. The fault caused a reactor

{

l trip on both units. If plant conditions require an emergency boration for Unit 1, what method (s) is(are) l available to borate the RCS? (Assume normal plant lineup prior to the reactor trip) l 1

I l-Expected Answer:

)

l l

r The only emergency boration flowpath available is from the RWST via the CV pump suction.

Actual Answer:

1 l

l l

r l

l Candidate's response matched expected answer.

i l

Sat Unsat K/A: SYS004K201 2.9/3.1 LP Objective: Chap ISB; K.O.11 Reference (s):

BwOA PRI-2 20E-1-4030AB01 l

NRC-5 4

3/10/98 8:05 AM i

I L

le Qucation No:

2 Reference Use:

YES/NG i

l j

Unit 1 is operating at 100% of full power when a Main Turbine trip occurs. The following plant coriditions exist upon entry into ES-0.1, " Reactor Trip Response":

SD Bank E control rods at 231 steps o

PZR Level is 18% and rising o

PZR Press is 2045 psig and rising o

RCS Tavg 540 F and stable, o

Steam Dumps are closed o

l

. How much boric acid is required to be added from the BAST?

Expected Answer:

4975 gallons (545*F-540*F=5'F 5x35 gal =175 gallonsfor temp deviation 4 rods in SD Bank E 4x1200 gal =4800 gallonsfor rods Totalgallons = 175 gal + 4800 gal = 4975 gallons)

Actual Answer:

I Candidate's response matched expected answer.

Sat Unsat K/A:

SYS004A404 3.2/3.6 LP Objective: EP-0 Series; K.O. 6 l

ROf erence (s) : ES-0.1, step 3e RNO, 5b RNO I

l NRC-5 5

3/10/98 8:05 AM l.

m ET l

Qu3ction No:

1 Reference Use:

YES/NO Due to faults on Bus 143 and in the switchyard, both units have lost offsite power. The fault caused a reactor trip on both units. If plant conditions require an emergency boration for Unit 1, what method (s) is(are) available to borate the RCS? (Assume normal plant lineup prior to the reactor trip)

\\

j NRC-5 6

3/10/98 8:05 AM l

OPERATOR QUESTION SHEET l

Qucation No:

2 Reference Use:

YES440 Unit 1 is operating at 100% of full power when a Main Turbine trip occurs. The following plant conditions exist upon entry into ES-0.1, " Reactor Trip Response":

SD Bank E control rods at 231 steps o

l PZR Ixvel is 18% and rising o

PZR Press is 2045 psig and rising o

l RCS Tavg 540 F and stable.

o l

Steam Dumps are closed o

l How much boric acid is required to be added from the BAST?

.- f i

i l

l NRC-5 7

3/10/98 8:05 AM

TASK CONDITIONS:

1.

You are the unit NSO.

2.

A Reactor Trip has occurred and IBwEP ES-0.1 is in progress at Step 5.

INITIATING CUES:

1.

Control Bank D, Group 1, Rod Bottom Lights are NOT LIT and the Group 1 Rods indicate 198 steps.

2.

The US directs you to commence Emergency Boration in accordance with 1BwOA PRI-2.

)

i i

i NRC-5 8

3/10/98 8:05 AM I

\\*

r.

JOI PERFORMANCE MEASURE

.~*

TASK TITLE: Cross Tie of ESF and Non-ESF Bus JPM No.

NRC-6 REV:

2 TPO No.: IV.D.OA-60/61 KEA No.:

SYS062A2.12 TASK No.: P1-OA-TK-024 K&A IMP:

3.2/3.6 TRAINEE:

Kurt Heinrich DATE:

4/15/98 EVALUATOR:

Dell McNeil

.Tha Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS:

(*)

5, 7 JPM TIME:

CRITICAL TIME: NA APPROX. COMPLETION TIME 6 MINUTES i

EVALUATION METHOD:

LOCATION-J X

PERFORM IN PLANT j

SIMULATE X

SIMULATOR MATERIALS:

1.

Copy of BwEP-1, Step 11.b.

(RNO), Rev 1A, WOG-1B GENERAL

REFERENCES:

1.

BwEP-1,' Step 11.b.

(RNO), Rev 1A, WOG-1B TASK STANDARDS:

J 1.

Correctly perform the required actions per BwEP-1, Step 11.b.

Cross connecting a non-ESF bus to a ESF bus.

TASK CONDITIONS:

)

1.

You are the extra NSO.

2.

The Unit has experienced a loss of coolant accident.

I 3.

The NSO has completed the actions of BwEP-0 and transitioned to BwEP-1.

4.

Unit Common Station Air Compressor is unavailable due to maintenance activities.

5.

The ' SAC 1 RCVR PRESS LOW" annunciator (37-C2) on OPM01J is lit, and Service Air Header Pressure is 92 psig and decreasing slowly.

INITIATING CUES:

The US directs you to perform BwEP-1, Step 11.b.

I NRC-6 1

3/10/98 8:17 AM

Simulator Satup:

IC16, 50% power

1. Insert malfunction ED18D to prevent ABT of 1442 breaker.

2. Override 1442 Breaker handswitch in PTL to prevent operation of breaker.

3. Insert LOCA to trip and SI the unit.

4. Perform actions up to step 11 of EP-1.

Ensure SI is reset.

r I

1 I

i

. NRC-6 2

3/10/98 8:17 AM t

1

PERFORMANCE CHECKLIST-STANDARDS UN B.hT M

E1h i

R" CORD START TIME i

1.

Check 4KV NON-ESF busses -

Check the following O

O O

ENERGIZED BY OFFSITE POWER:

indications:

• SAT 142-1 Bus Alive light - LIT

• ACB 1432 - CLOSED

• SAT 142-2 Bus Alive light - LIT

• ACB 1442 - OPEN 2.

Attempt to restore offsite

• Attempt to close ACB D

D D

power to Bus 144.

1442.

-OR-(CUE: EO reports ACB appears

• Dispatch an EO to to be damaged) locally check ACB 1442.

3.

Locally verify all breakers

• Dispatch an EO to O

O O

on Bus 144 are OPEN.

locally verify all breakers on Bus 144 (CUE: EO reports all are open.

BRKRS open bus 144) 4.

Place all non-running WS Place the control switch O

O O

pumps in the PULL OUT for WS Pump OB to the position for Bus 144.

PULL OUT position.

• 5.

Reset SI Recirc Sump Depress the SI RECIRC O

O O

Isolation Valve.

SUMP ISOL VLV reset push-button for TRAIN B.

(1SI8811B) 6.

'Open all 480V transformer Open the following for O

O O

LOW side breakers for Bus Bus 144:

144.

1) XFMR 034RA (BUS 034R)

2) XFMR 034 (BUS 034P)

3) XFMR 134X (BUS 134X)

4) XFMR 134Y (BUS 134Y)

5) XFMR 134Z (BUS 134Z)

6) XFMR 034WA (BUS 034W)

7) XFMR 134V (BUS 134V)

8) B/U HTR GP "B"

9) CONTROL HTR GP "C" NRC-6 3

3/10/98 8:17 AM

PERFORMANCE CHECKLIST STANDARDS UN EAI EAT E/3

• 7 Energize Bus 144 from ESP Close breaker 1421.

O O*

O crosstie breaker.

(CUE This completes chis JPM)

RECORD STOP TIME COMMENTS:

/

1 i

i l

1 NRC-6 4

3/10/98 8:17 AM

\\

l JPM Ouestions Question No:

1 Reference Use: YES/NO Given the following plant conditions on Unit 1:

Mode 3 following a Loss of Offsite Power e

Bus 141 is powered from 1 A Diesel Generator o

o Bus 143 has been crosstied to Bus 141 Current bus 141 loading is 1350 KW o

Current bus 143 loading is 2137 KW o

If the 1 A SX pump is started, how much load is still available following the pump start on the 1 A Diesel Generator for continuous operation under the current plant conditions?

Expected Answer:

1000KW remaining. [5500KW - 1350 (141 loads) - 2137 (143 loads) - 1013 (I A SX pump load)]

Actual Answer:

Candidate's response matched expected answer.

Sat Unsat K/A: SYS064A205 3.1/3.2 LP Objective: ELEC-3; K.O. 4 R ference(s):

BwOA ELEC-3 page 7, BwOA ELEC-4 page 11 NRC-6 5

3/10/98 8:17 AM i

Question N:: _2_

Refer:nce Use: YES/NO Unit 1 is at 100% power with all systems lineup for normal operation. While performing an offsite power availability surveillance, the operator notices breaker 1441 trip. It appears to have tripped due to gro'und overcurrent.

If all equipment operates as designed, what would you expect the plant conditions and 4KV bus status to be in 5 minutes?

l l

Expected Answer:

Unit 1 tripped with all buses, except bus 144, energized from SAT 142-1 and 142-2.

- (WHPS Actuates closing FW valves resulting in a reactor trip, all other buses will ABT)

Actual Answer:

Candidate's response matched expected answer.

Sat Unsat, _.

K/A: SYS062v.403 2.8/3.1 LP Objective: Chap 4; K.O.16 Reference (s):

20E-1-4008BQ 20E-1-4030LV08 i

20E-1-4030FW20, 61 NRC-6 6

3/10/98 8:17 AM i

OPERATOR OUESTION SHEET Question No:

1 Reference Use: YES/NO Given the following plant conditions on Unit 1:

Mode 3 following a Loss of Offsite Power o

Bus 141 is powered from 1 A Diesel Generator o

o Bus 143 has been crosstied to Bus 141 Current bus 141 loading is 1350 KW o

Current bus 143 loading is 2137 KW o

If the 1 A SX pump is started, how much load is still available following the pump start on the 1 A Diesel Generator for continuous operation under the current plant conditions?

I l

NRC-6 7

3/10/98 8:17 AM

OPERATOR OUESTION SHEET 1

I Question No: _2_

Reference Use: YES/NO Unit 1 is at 100% power with all systems lineup for norma! operation. While performing an offsite power availability surveillance, the operator notices breaker 1441 trip. It appears to have tripped due to ground overcurrent.

If all equipment operates as designed, what would you expect the plant conditions and 4KV bus status to be in 5 minutes?

I 4

NRC-6 8

3/10/98 8:17 AM

4 Q

TASK CONDITIONS:

1.

You are the extra NSO.

2.

The Unit has experienced a loss of coolant accident.

3.

The NSO has completed the actions of BwEP-0 and transitioned to BwEP-1.

4.

Unit Common Station Air Compressor is unavailable due to maintenance activities.

5.

The " SAC 1 RCVR PRESS LOW" annunciator (37-C2) on OPM01J is lit, and Service Air Header Pressure is 92 psig and decreasing slowly.

INITIATING CUES:

The US directs you to perform BwEP-1, Step 11.b.

l.

NRC-6 9

3/10/98 8:17 AM

e

=

JOB PERFORMANCE MEASURE TASK TITLE: Respond to a Safety Injection with a Loss of Instrument Bus 114 JPM No..

NRC-7 REV:

0 TPO No.-

IV.D.EP-19 K&A No.-

SYS013A4.01 TASK No.:

P1-EP-TK-037 K&A IMP:

4.5/4.8 TRAINEE:

Kurt Heinrich DATE:

4/15/98 EVALUATOR:

Dell McNeil Tha Trainee:

PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS:

(*)

1, 2,

3, 4,

6, 10, JPM TIME:

11, 12, 16 CRITICAL TIME: NA APPROX COMPLETION TIME 9 MINUTES EVALUATION METHOD:

LOCATION:

X PERFORM IN PLANT SIMULATE X

SIMULATOR GENERAL

REFERENCES:

1.

1BwEP-0, Rev. lA, WOG 1B MATERIALS: None l

TASK STANDARDS:

l l

1.

Perform the Immediate Action steps for a Reactor trip from memory.

2.

Perform the next twelve steps for a Safety Injection.

l TASK CONDITIONS:

1.

You are the unit NSO.

2.

Reactor is steady state, all conditions are NORMAL.

l 3.

All systems are in AUTO.

INITIATING CUES:

1.

Respond to changing plant conditions.

NRC-7 1

3/10/98 8:48 AM

Simulator Setup:

IC-16, 50% power

'1. Insert malfunction ED11D to de-energize Instrument Bus 114 then override switch to manually actuate SI.

/

1 l

l l

l

\\

NRC-7 2

3/10/98 8:48 AM i

L

'4 PERFORMANCE CHECKLIST STANDARDS UN 1AI SAI:

Ela RECORD START TIME

• 1. Verify Reactor Trip.

Verify:

O O

O Rod Bottom Lights LIT.

RTB's open.

• Neutron flux decreasing.

• 2.

Verify Turbine trip.

Verify:

• All Throttle Stop O

O O

Valves - CLOSED.

• All Governor Valves -

CLOSED.

• 3.

Verify Power to 4KV ESF ESF busses BOTH D

D D

Buses.

ENERGIZED:

• Bus 141

• Bus 142 l

• 4.

Check if SI Actuated.

Check:

O O

O Any SI First Out l

Annunciator L'.T.

• SI Actuated Permissive Light LIT.

Manually actuate SI

)

5.

Verify FW Isolation.

Verify:

O O

O

a. FW pumps - TRIPPED:

FW PUMPS TRIP alarms - LIT.

b. FW isolation monitor lights - LIT.

c. FW pumps discharge valves - CLOSED:

• 1FWOO2A

• 1FWOO2B

• 1FWOO2C NRC-7 3

3/10/98 8:48 AM i

PERFORMANCE CHECKLIST STANDARDS UN EhT Bh.T Elb

• 6.

Verify ECCS Pumps Running.

Verify CV Pumps Run O

O O

Lights LIT.

Manually start IB CV pump Verify RH Pumps Run Lights LIT.

Manually start 1B RH pump Verify SI Pumps Run Lights LIT.

Manually start 1B SI Pump 7.

Verify Containment Isolation Verify Group 3 CNMT Isol O

Or O

Phase A.

Monitor Lights - LIT.

Manually align following valves:

• RF027 *PR001B *WOOO6B

• WOO 20B

• WOOS 6A *FP010

• PS229A *PS229B aRE9157

• RE9160B *RE9170 *CV8112

• RY8028 *RY8033 8.

Verify Containment Verify Group 6 CNMT Vent O

O.

O Ventilation Isolation.

Isol Monitor Lights -

LIT.

l Verify AF Pump Run O

O O

9.

Verify AF Pumps Running.

Lights LIT.

l Verify AF013's open Verify AF005's throttled - B Train Closed

• 10.

Verify RCFC's running in Low Verify RCFC Low Speed O

O O

Speed.

Run Lights - LIT.

i

• Stop 1B and 1D RCFC High Speed Fans.

f

• After 20 seconds, start 1B and ID RCFCs in Low Speed j

NRC-7 4

3/10/98 8:48 AM

I l

i.

l PERFORMANCE CHECKLIST STANDARDS UN EAT SAI Ela

)

• 11.

Verify CC Pumps Running.

Verify CC Pumps Run O

O O

Lights LIT.

Manually start 1B CC pump

• 12.

Verify SX Pumps Running.

Verify SX Pumps Run O

O O

Lights LIT.

Manually start 1B SX pump 13.

Check if Main Steamlines Verify steamline O

O O

should be isolated.

isolation NOT required by checking for one or

+

more of the following:

)

• Any Steamline Pressure 5 40 psig 6

-OR-

• Containment Pressure 2 2 psig 8

14.

Verify Containment Spray not Verify Containment Spray O

O O

Required.

NOT required by checking:

• Containment Pressure has remained <20 psig.

15.

Verify total AF Flow.

Verify total AF flow:

O O

O AF Flow > 500 gpm e

available Check SG Narrow Range Level >11%

• Control feed flow to maintain 11 to 50%

Verify no SG level increasing in an uncontrolled manner t

NRC-7 5

3/10/98 8:48 AM

PERFORMANCE CHECKLIST STANDARDS UN SAT SAT E/.A

• 16.

Verify Diesel Generators

' verify:

O O-O Running.

DGs both running -

Manually start 1B DG o ISX169A&B Open o Dispatch Operator to locally check Diesel Generators.

'(CUES.This completes this JPM.)

l RECORD STOP TIME I

i COMMENTS:

+/

r l'

o l

i 1

NRC-7 6

3/10/98 8:48 AM

6 I

JPM Ouestions I

Question No:

1 Reference Use:

YES/NO Given the following plant conditions on Unit 1:

o less ofInstrument Bus 114 o Small break LOCA on C loop Currently at step 20 of EP-0 o

All operator actions in accordance with EP-0 have been completed o

The operator inadvertently takes both control switches for ISI8801 A and ISI8801B to the close position.

What are the valve positions for ISI880) A and ISI8801B after the control switch manipulations?

4 Expected Answer:

IS18801 A would close and then re-open. ISI8801B would close and remain closed.

1 Actual Answers i

Candidate's response matched expected answer.

Sat Unsat K/A: SYS006K409 3.8/4.2 LP Objective: Chap 61; K.O. 8 Reference (s):

IBwOA ELEC-2, Table D, Page 19 of 21 20E-1-4030SIM UFSAR figure 7.2-1 i

NRC-7 7

3/10/98 8:48 AM

Qucation N3:

2 Reference Use:

YES/NO l

Given the following plant conditions on Unit 1:

l Small Break LOCA has occurred from 100% power o

RCS Press is 1100 psig o

o PZR Level is 0%

l o

SG Press is 600 psig Containment Press is 3 psig o

A Reactor Trip has been actuated from IPM05J and IPM06J o

l

.o "A" Reactor Trip Breaker is closed Currently at step 10 of EP-1 o

What actions are required to accomplish a reset of SI on Train A?

t

'/

Expected Answer:

Locally open or rack out the "A" Reactor Trip Breaker and depress the "A" Train SI reset pushbutton.

Actual Answer Candidate's response matched expected answer.

Sat Unsat I

K/A: SYS013K401 3.9/4.3 LP Objective: Chap 61; K.O. 6 l

R0f erence (s) : UFSAR Figure 7.2-1 Sheets 2 and 8 I

NRC-7~

8 3/10/98 8:48 AM

OPERATOR OUESTION SHEET Question No 1

Reference Use:

YESANO l

Given the following plant conditions on Unit 1:

o Loss of Instrument Bus 114 Small break LOCA on C loop o

Currently at step 20 of EP-0 i

e l

All operator actions in accordance with EP4 have been completed o

The operator inadvertently takes both control switches for ISI8801 A and ISI8801B to the close position.

What are the valve positions for ISI8801 A and ISI8801B after the control switch manipulations?

l l

I i

NRC-7 9

3/10/98 8:48 AM

i

]

OPERATOR OUESTION SHEET

^

Question No 2

Reference Use:

YES/NO Given the following plant conditions on Unit 1:

Small Break LOCA has occurred from 100% power o

RCS Press 'is 1100 psig o

o PZR Level is 0%

SG Press is 600 psig o

Containment Press is 3 psig o

A Reactor Trip has been actuated from IPM05J and IPM06J o

"A" Reactor Trip Breaker is closed o

Currently at step 10 of EP-1 o

What actions are required to accomplish a reset of SI on Train A?

l I

l l

NRC-7 10 3/10/98 8:4B AM

TASK CONDITIONS:

1.

You are the unit NSO.

2.

Reactor is steady state, all conditions are NORMAL.

3.

All systems are in AUTO.

INITIATING CUES:

1.

Respond to changing plant conditions.

i i

i l

NRC-7 11 3/10/98 8:48 AM

r 4'

JOB PERFORMANCE MEASURE TASK TITLE: Respond to a Loose Parts Nonitor Alarm JPM No.:

NRC-8 REV; 6 TPO No.:

IV.D.LM-03 K&A No.:

SYS002A3.02 TASK No.:

P1-LM-TK-005 K&A IMP:

2.6/2.8 TRAINEE:

Kurt Heinrich DATE:

4/14/98 EVALUATOR:

Dell McNeil Tha Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS:

(*)

2, 4 JPM TIME:

CRITICAL TIME: NA APPROX COMPLETION TIME 13 MINUTES EVALUATION METHOD:

LOCATION:

PERFORM X IN PLANT X

SIMULATE SIMULATOR GENERAL

REFERENCES:

1.

BwAR 2-13-E9, Rev. 51 2.

BwCP LM-6, Rev. 5 3.

BwCP LM-ST1, Rev. 51 MATERIALS:

1.

Copy of BwOP LM-6 2.

Copy of BwOP LM-ST1 TASK STANDARDS:

1.

Respond to Loose Parts Monitor Alarm.

TASK CONDITIONS:

1.

Unit 2 is at Power. All systems normal with no evolutions in progress.

2.

You are the extra'NSO.

3.

Loose Parts Monitor System Trouble is in Alarm (2-13-E9).

4.

SER point 1760 " Loose Parts Monitor System Impact Noise Level Alarm" is printed.

1 INITIATING CUES:

You are directed by the Unit Supervisor to take the appropriate actions per BwAR 2-13-E9.

j i

i l

I NRC-8 1

3/10/98 9:05 AM

PERFORMANCE CHECKLIST STANDARDS UN SAAI SAT RECORD START TIME 1.

Refer to BwAR 2-13-E9.

Open BwAR 2-13-E9.

O O

O

• 2.

Determine if alarm is HIGH

• Locate Loose Parts O

O O

or LOW.

Monitor Cabinet in AEER.

Check:

(C23: Channel 2VY-LM003 High

• Alarming Module Hi l

Alarm Light is LIT.)

Alarm and Lo Alarm l

Lights.

l (CUE: FIRST OUT LED 3 is l

LIT.)

• First Out Indicator.

3.

Perform subsequent operator

• Record time, plant O

O O

l actions of BwAR 2-13-E9.

status and First Out Alarm number.

(EEE: No Plant Transients have occurred. FIRST

• Refer to BwOP LM-6.

OUT LED 3 is LIT.)

a

• 4.

Perform BwOP LM-6.

O O

O (CEE: REM P/B's are pressed.

Verify / Press Rem P/B on Tape Recorder 1 and 2.

j 2VY-LM003 Hi Alarm and

• Note Channel in Alarm First Out LED 3 are and First Out.

LIT.

• Determine sensor location - Hot Side S/G A Channel Head.

Alarms clear, 2VY-

• Press the Reset on LM003 Hi Alarm Master Alarm.

relights, FIRST OUT LED 3 is LIT.

Speaker Selector

• Align speaker 6 to Switches are aligned First Out Channel.

to 2VY-LM003.

j There are metallic

• Listen for metallic impact sounds, impact sounds.

SM is contacted to e

Contact Shift Manager inform Sys. Eng.

to inform System and/or Station Nuclear Engineering and/or Engineer.)

Station Nuclear Engineer (qHE: This completes this JPM.)

RECORD STOP TIME COMMENTS:

NRC-8 2

3/10/98 9:05 AM

JPM Ouestions Question No:

1 __

Reference Use:

YES/NO Unit 2 is at 100% power. RCS loop flow channel 2FT-415 fails low at 10:30 a.m. Ten (10) minutes later, a Unit I reactor trip occurs due to a card failure on DEHC 5 % hours after the reactor trip, RCS loop flow

{

channel,2FT-436 fails high. No Actions per the BwOA have taken place.

What Unit 2 action (s) is(are) required?

{

l Expected Answer:

Need to trip bistables for both failed loop flow transmitters. 20 minutes remain to trip bistable for 2FT-415 and six hours to trip bistable for 2FT-436.

Actual Answer:

I l

I

(

l Candidate's response matched expected answer.

Sat Unsat K/A: sysol6-2.2.22 3.8/4.2 LP Objective: INST 2; K.O. 5 R:ference(s):

2BwOA INST-2, Attachment K Tech Specs 3.3.1 I

NRC-8 1

3/10/98 9:05 AM

Quostien No:

2 Reference Use:

YES/NO l

Unit 2 has 2C and 2D RCPs running with RCS Temp of 175 F and RCS Press of 300 psig. After starting the 2A RCP, the following stable plant conditions exists:

RCS Temp - 170'F o

RCS Press - 330 psig o

VCT Pressure - 16 psig o

RCP parameters as follows:

2A 2B 2G 2D o

Motor Bearing Temps 165*F 137*F 157 F 157'F e

Lower Radial Bearing Temps 175 F 137 F 164 F 163 F e

e RCP Seal AP 300 psid 260 psid 295 psid 305 psid SealInjection flows 8 gpm 10 gpm 8.5 gpm 8 gpm e

. RCP Vibrations 6 mils 1 mil 2.5 mils 2 mils What actions, if any, are required following the start of the 2A RCP and prior to startin[the 2B RCP?

Expected Answer:

Trip the 1A RCP (due to excessive vibrations) and raise 2B RCP Seal AP to > 275 psid (by increasing RCS pressure).

Actual Answer:

Candidate's response matched expected answer.

Sat Unsat K/A: SYS003K614 2.6/2.9 LP Objective: Chap 13; K.O. 8 R0ference(s): BwOP RC-1 l

j NRC-8 2

3/10/98 9:05 AM l

[

_QERRATOR OUESTION' SHEET l

Question No:

1 Reference Use:

YES/NO Unit 2 is at 100% power, RCS loop flow channel 2FT-415 fails low at 10:30 a.m. Ten (10) minutes later, a l

Unit I reactor trip occurs due to a card failure on DEHC. 5 % hours after the reactor trip, RCS loop flow l

channel,2FT-436 fails high, No Actions per the BwOA have taken place.

What Unit 2 action (s) is(are) required?

l 1

I i

i l

I NRC-8 3

3/10/98 9:05 AM

OPERATOR OUESTION SHEET Question No:

2 Reference Use:

YES/NO l

Unit 2 has 2C and 2D RCPs running with RCS Temp of 175 F and RCS Press of 300 psig. After starting the 2A RCP, the following stable plant conditions exists:

RCS Temp - 170 F o

RCS Press - 330 psig o

VCT Pressure - 16 psig o

RCP parameters as follows:

2A 2B 2C 2D o

Motor Bearing Temps 165'F 137'F 157 F 157 F e

Lower Radial Bearing Temps 175'F 137*F 164*F 163 F e

RCP Seal AP 300 psid 260 psid 295 psid 305 psid e

Seal Injection flows 8 gpm 10 gpm 8.5 gpm 8 gpm e

RCP Vibrations 6 mils 1 mit 2.5 mils 2 m ils What actions, if any, are required following the start of the 2A RCP and prior to starting the 2B RCP?

i NRC-8 4

3/10/98 9:05 AM t

TASK CONDITIONS:

1..

Unit 2 is at Power.

All systems normal with no evolutions in progress.

I 2.

You are the extra NSO.

I 3.

Loose Parts Monitor System Trouble is in Alarm (2-13 -E9).

4.

SER point 1760 " Loose Parts Monitor System Impact Noise Level Alarm" is printed.

i INITIATING CUES:

You are directed by the Unit Supervisor to take the appropriate actions per 2BwAR 2-13-E9.

l l

NRC-8 5

3/10/98 9:05 AM

e l*

i l

JOB PERFORMANCE MEASURE TASK TITLE: Local Roset of Phase A Isolation

~

JPM No.:

NRC-9 REV:

2 TPO No.*

IV.D.RP-01 K&A No.:

SYS013K4.02 TASK No.:

P1-RP-TK-002 K&A IMP:

3.9/4.2 TRAINEE:

Kurt Heinrich DATE:

4/14/98 EVALUATOR:

Dell McNeil Tha Trainee PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS:

(*)

2, 5, 6 JPM TIME:

CRITICAL TIME: NA APPROX COMPLETION TIME 13 MINUTES j

EVALUATION METHOD:

LOCATION:

PERFORM X IN PLANT X SIMULATE SIMULATOR GENERAL

REFERENCES:

l-1.

2BwOA PRI-5 Attachment E, Rev. 57 MATERIM.S l

1.

Cabinet Key for 2PA09J l

2.

' Attachment

'E" of 2BwCA PRI-5 TASK STANDARDS:

i 1.

Correctly reset containment isolation phase A, IAW 2BwCA PRI-5, Attachment E.

I TASK CONDITIONS:

1.

The crew is responding to a spurious Train A safety injection on Unit 2.

2.

2BwEP ES-1.1 (SI Termination) is in progress at step #2.

3.

The Phase A reset pushbutton for Train A in the Control Room will not work.

INITIATING CUES:

l The Unit Supervisor has directed you to reset Phase A containment isolation on Train l

A per 2BwCA PRI-5 Attachment E.

No safety concerns exists for entry into the AEER.

j i

1 l

NRC-9 1

3/10/98 9:16 AM

]

' PERFORMANCE CHECKLIST STANDAFDS UN EAT E8.I E/h f

[

RECORD START TIME t

NOTE Hand Candidate the enclosed copy of 2BwCA PRI-5

• Attachment E (Control. Room Inaccessibility Unit 2, ESF

(

Remote Block or Reset). Only the portions of the procedure needed to reset Train A of' Containment Phase A l

Isolation need to be completed.

i l

1 Obtain keys to EF cabinet.

Proceed to the Shift O

O O

Office and obtain the key fors 2PA09J ggyg

.f<

Have Examinee locate the jumpers, but do not allow *them to be removed from the cabinet.

NOTE Due to time or radiological concerns, Step 2 can be explained by the Candidate at the evaluator's

• discretion.

• 2.

Obtain 2 Jumpers At the Center Desk or at O

O' O

the Remote Shutdown Panel locate the 2 onap clip jumpers required.

3.

Proceed to the Aux. Electric Proceed to the Aux.

O O

O Equipment Room.

Electric Equipment Room for Unit 2.

4.

Proceed to cabinet 2PA09J.

Unlock and open the rear O

O O

of 2PA09J.

i NOTE Inform Examinee that all required actions in 2PA09J are to be simulated and make every effort not to touch any of the components in 2PA09J.

• 5.

Reset Train A Cnmt. Phase A In the rear of the Logic O

O O

Isolation.

Cab. locate terminal board TB504 and jumper (ggg: Jumper installed points 7 and 8.

across points 7 and 8.)

NRC-9 2

3/10/98 9:16 AM

1 PERFORMANCE CHECKLIST STANDARDS UN SAT SAT H/A

• 6.

Unlatch Train A Phase A In the rear of outout O

O O

Slave Relays.

Cabinet locate terminal board TB644 and jumper (ggE: Jumper installed points 3 and 4.

across points 3 and 4.)

7 Check K605 relays 2PA09J Check K605 relay in O

O O

deenergized.

2PA09J deenergized (relay not sucked in.)

(ggg: K605 is doenergized.)

8.

Remove jumpers.

Remove jumpers.

O O

O (EEE: Jumpers removed.)

(EEE: This completes this JPM.)

RECORD STOP TIME 1

i l

COMMENTS:

l l

t

)

l I

NRC-9 3

3/10/98 9:16 AM j

l

\\

t

4 JPM Ouestions e

i Question No:

1 Reference Use: VES/NO Unit 1 is shutdown with a cooldown in progress. RCS pressure has just been reduced to less than 1930 psig and the steamline low pressure SI signal has been blocked.

What protection is now provided if a steamline break accident occurs?

Expected Answer:

Rapid steamline depressurization protection is still provided by the High Steamline Pressure Rate signal.

Actual Answer:

Candidate's response matched expected answer.

Sat Unsat K/A: SYS013K403 3.9/4.4 LP Objective: Chap 61; K.O. 7 Reference (s):

BwAR 1-BP-4.2 Technical Specification Basis - B3/4.3.2 i

l l

l NRC-9 4

3/10/98 9:16 AM

Question N::

2 Reference Use: YES/NO The following plant conditions exist on Unit 2:

Shutdown for refueling outage RH cooldown in progress on 'A' Train Rif RCS Temperature is 210'F e

RCS Pressure is 335 psig e

What operator actions are required to allow placing SSPS 'n a " Shutdown Condition" and what SSPS automatic actuation capabilities are NOT disabled when in, the " Shutdown Condition"?

Expected Answer:

Unit must be placed in Mode 5 (<200 F). BDPS and VQ are not disabled.

Actual Answer:

Candidate's response matched expected answer.

Sat Unsat K/A: SYS013K502 2.9/3.3 LP Objective: Chap 60a; K.O. 9 Reference (s):

BwOP RP-7 NRC-9 5

3/10/98 9:16 AM

OPERATOR OUESTION SHEET Question No:

1 Reference Use: VES/NO Unit 1 is shutdown with a cooldown in progress. RCS pressure hasjust been reduced to less than 1930 psig and the steamline low pressure SI signal has been blocked.

What protection is now provided if a steamline break accident occurs?

/

1 J

l NRC-9 6

3/10/98 9:16 AM

1 OPERATOR OUESTION SHEET Question No: _L Reference Use: YES/NO The following plant conditions exist on Unit 2:

Shutdown for refueling outage l

RH cooldown in progress on 'A' Train RH RCS Temperature is 210 F e

RCS Pressure is 335 psig l

What operator actions are required to allow placing SSPS in a " Shutdown Condition" and what SSPS automatic actuation capabilities are NOT disabled when in the " Shutdown Condition"?

l l

l l

l l

1 l

l NRC-9 7

3/10/98 9:16 AM

TASK CONDITIONS:

I.

The crew is responding to a spurious Train A safety injection on Unit 2.

2.

2BwEP ES-1.1 (ST. Termination) is in progress at step #2.

3.

The Phase A reset pushbutton for Train A in the Control Room will not work.

INITIATING CUES:

The Unit Supervisor has directed you to reset Phase A containment isolation on Train A per 2BwOA PRI-5 Attachment E. No safety concerns exists for entry into the AEER.

NRC-9 8

3/10/98 9:16 AM

l 5 t

JO3 PERFORMANCE MEASURE TASK TITLE: Align the Fire Masards Panel JPM No.:

NRC-10 REV:

6 TPO No.:

IV.D.OA-27 K&A No.:

SYS016K4.01 TASK No.:

P1-OA-TK-001 K&A IMP:

4.4/4.4 TRAINEE:

Kurt Heinrich DATE:

4/14/98 EVALUATOR:

Dell McNeil Tha Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

l CRITICAL ELEMENTS:

(*)

2, 3 JPM TIME:

l l

CRITICAL TIME: NA APPROX. COMPLETION TIME 8 MINUTES EVALUATION METHOD:

LOCATION:

.f PERFORM X IN PLANT r

X SIMULATE SIMULATOR i

l GENERAL

REFERENCES:

l l

1.

2BwCA PRI-5, Rev. 57B l

MATERIALS:

1.

2BwOA PRI-5 l

TASK STANDARDS:

1.

Activate the Fire Hazards Panel.

TASK CONDITIONS:

1.

You are an Extra NSO.

2.

A fire is ongoing in the Main Control Room and the U-1 Aux. Elect Room.

3.

The Remote Shutdown panels have been manned.

4.

1BwCA PRI-5 and 2BwOA PRI-5 are in Progress.

5.

Division 22 power to the fire hazards panel is de-energized.

INITIATING CUES:

You have been directed to ALIGN the Fire Hazards Panel to monitor Unit 2 S/G Levels, S/G Pressures, PZR Level and PZR Pressure using 2BwOA PRI-5, Step 7.

l

\\

l NRC-10 1

3/10/98 9:32 AM i

i

F-PERFORMANCE CHECKLIST STANDARDS UN EAT EAT E/.h R" CORD START TIME 1.

Proceed to 2PL10J, Fire Locate the Fire Hazards O

O O

Hazards Panel.

Panel.

(426' El Curved Wall Area S-24 on Unit 2) i t

• 2.

Verify Power is supplied to Verify / place:

O O

O l

the RCS WR Hot and Cold Leg l

Temperature indications.

• Power Switch 2HS-LV001 l

to #1 position (qq3: Power Switch 2HS-LV001 (Division 21 power) is in the #3 position when arriving at cabinet) l l

(gggi Power Switch 2HS-LV001 l

is in the #1 position) l

• 3.

Activate the Fire Hazards Place the Panel Switches O

O O

Panel, to the FIRE position.

(EEE: 2HS-RYO33 is in FIRE 2HS-RYO33 - PZR PRESS.

position, 2HS-RYO34 is in FIRE 2HS-RYO34 - PZR LEVEL.

l

position, 2HS-MS193 is in FIRE 2HS-MS193 - SG 2A

position, PRESS.

2HS-MS194 is in FIRE 2HS-MS194 - SG 2B

position, PRESS.

2HS-FW309 is in FIRE 2HS-FW309 - SG 2A WR

position, LEVEL.

2HS-FW310 is in FIRE 2HS-FW310 - SG 2B WR position.)

LEVEL.

(EEE: This costpletes this JPM.)

l RECORD STOP TIME COMMENTS:

i j

NRC-10 2

3/10/98 9:32 AM l

1 JPM Ouestions l

l t

l l

Qucation No:

1 Reference Use:

VBG-/NO j

Why are the control power fuses pulled when taking local emergency control of safe shutdown equipment?

l I

l Expected Answer:

i j

To disable all automatic trips and allow start of vital equipment.

l l

Actual Answers l

i l

l candidate's response matched expected answer.

Sat Unsat l

K/A: APE 068AK2% 2.4*/2.7 LP Objective: ELEC-5; K.O. 3 l

Reference (s):

2BwOA Elec-5, page 4 1

l l

NRC-10 1

3/10/98 9:32 AM

Qucatien Nor 2

Rafcrcnco Uco YES/NO During evacuation of the control room, letdown flowrate is established at 45 gpm as a preparation for Remote Shutdown Panel operation.

What is'the basis for establishing a minimum letdown Dowrate?

Expected Answer:

This minimizes the possibility of letdown isolation. (Letdown operations from the remote shutdown panel are hampered due to the lack of control for the letdown line pressure control valve ICV 131) l Actual Answer:

I l

f Candidate's response matched expected answer.

Sat Unsat K/A APE 068AK310 3.9/4.2 LP Objective: PRI-5; K.O. 3 Roference(s): 2BwOA Pri-5, step 5b, page 5 of 77 i

l l

l l

NRC-10 2

3/10/98 9:32 AM l

f OPERATOR QUESTION SHEET Question No:

1 Reference Use:

VE6/NO l

Why are the control power fuses pulled when taking local emergency control of safe shutdown equipment?

i 1

i f

l o

l l

i i

l l

l l

l l

NRC-10 3

3/10/98 9:32 AM

}

~

OPERATOR OUESTION SHEET Question No:

2 Reference Use:

VES/NO During evacuation of the control room, letdown flowrate is established at 45 gpm as a preparation for Remote Shutdown Panel operation.

What is the basis for establishing a minimum letdown flowrate?

l l

i l

l NRC-10 4

3/10/98 9:32 AM

TASK CONDITIONS:

1.

You are an Extra NSO.

2.

A fire is ongoing in the' Main Control Room and the U-1 Aux. Elect Room.

3.

The Remote Shutdown panels have been manned.

4.

1BwOA PRI-5 and 2BwOA PRI-5 are in Progress.

5.

Division 22 power to the fire hazards panel is de-energized.

v INITIATING CUES:

You have been directed to ALIGN the Fire Hazards Panel to monitor Unit 2 S/G Levels, S/G Pressures, PZR Level and PZR Pressure using 2BwOA PRI-5, Step 7.-

l i

i i

1 NRC-10 5

3/10/98 9:32 AM

-6

1. L PERATING TEST ppMS CNLY)

E BRAIDWOOD INITIAL R AKE EXAMINATlON-WEEK op 4/13/98 l

0 0

i W

ES-301 Individuil W. Ik-Through Ts:st Outline Form ES-301-2 Facility: Braidwood Nuclear Station Date of Examination: 04/14-15$Q,,,

l Exam Level: SRO(l)

Operating Test No.:

98304 System / JPM Title / Type Codes

• Safety Planned Follow-up Questions:

Function K/A/G -Importance - Description l

1. Establish Excess Letdown 2

a. SYS004K104 3.4/3.8 Seal Injection flow control w/ loss of (N.A,S)

DC power

b. SYS004D132 2.8/3.1 Restoration of seal retum w/ low press in the VCT

2. Respond to a WS Sys Malfunction 4

a. SYS076A2013.5/3.7 Required operator actions w/ loss of (DS) non-essential service water

b. SYS076K302 2.5/2.8 Determine plant restrictions on loss of cooling to a stator water cooler

3. Respond to a PZR press channel 7

a. SYS0162.1.12 2.9/4.0 Determine T.S. requirements for a Malfunction (NAS) failed pressurizer channel.

b. SYS016K308 3.5/3.7 Determine actions w/ failed PZR l

pressure detector w/ failure of PORV & Spray valves.

4. Manually Initiate Containment 5

a. SYS026A4014.5/4.3 Determine required operator actions to Spray (MSL) close 1CS019 valves or! steam break.

b. SYS026K406 2.8/3.2 Determine CS sys status w/ auto start signal present and 1CS010A shut.

5. Perform an Emergency Boration 1

a. SYS004K2012.9/3.1 Knowledge of Emergency boration (MSL) paths available w/ loss of electrical power.

b. SYS004A404 3.2/3.6 Determine required amount of emergency boration for stuck rods and low RCS temp.

6. Crosstie ESF and Non-ESF Bus 6

a. SYS064A205 3.1/3.2 Determine allowable DG loading while (DSL) crosstied to Non-ESF bus.

b. SYS062K403 2.8/3.1 Determine electric plant lineup following loss of Non-ESF 4KV bus w/no operator action.

7. Respond to SI w/ Loss of 3

a. SYS006K409 3.8/4.2 Determine valve position following Instrument Bus 114 (NAS) operation during an Sl w/ loss ofinst bus.

b. SYS013K4013.9/4.3 Determine how to reset SI w/ Reactor Trip Breaker failed closed.

8. Respond to a Loose Parts Monitor 4

a. SYS0162.2.22 3.8/4.2 Identify failure to comply w/ T.S. on Alarm (DP) loss of 2 RCS flow instruments.

b. SYS003K614 2.6/2.9 Determine RCP shutdown is required

9. Perform Local Reset of Phase A 2

a. SYS013K403 3.9/4.4 identify protection available when SI Isolation (DP) signals are block,ed at P-11.

b. SYS013K502 2.9/3.3 Determine protection available when placing SSPS into shutdown condition.

10. Align the Fire Hazards Panel 7

a. APE 068AK206 2.4/2.7 Explain the reason for pulling control l

(DPR) power fuses when taking local control of components.

b. APE 068AK310 3.9/4.2 Explain why letdown is reduced prior to evacuation of the coritrol room.

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA

S..

JOB PERFORMANCE MEASURE TASK TITLE: Excess Letdown Operation with 1CC9511 out of position closed JPM No.: NRC-1 REV: 0 TPO No.: IV.C.CV-07 K & A N o.: SYS004A4.05 TASK No.:

P1-CV-TK-007 K&A IMP: 3.6/3.1 TRAINEE:

DATE: 4/15/98 EVALUATOR:

The Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

I CRITICAL ELEMENTS: (*) 4, 5, 6, 8, 9 JPM TIME:

CRITICAL TIME: NA APPROX. COMPLETION TIME 10 MINUTES EVALUATION METHOD:

LOCATION:

X PERFORM

_ IN PLANT

_ SIMULATE X SIMULATOR GENERAL

REFERENCES:

1.

BwOP CV-15, Rev. 8 MATERIALS: None TASK STANDARDS:

1.

Establish excess letdown.

i 2.

Identify loss of cooling to excess letdown heat exchangers TASK CONDITIONS:

I 1.

You are the Unit NSO.

2.

Unit is at Power, Steady State.

3.

All plant systems and controls are normal.

INITIATING CUES:

1.

Last shift identified increasing AP across the RC filter.

2.

The US directs you to establish excess letdown from all RCS loops to the VCT through both Excess Letdown heat exchangers and secure normal letdown to facilitate investigation of the RC filter.

NRC-1 1

April 14,1998 w

SIMULATOR SETUP:

l IC-16, 50% power.

Close 1CC9411 A&B by modifying remote function MRF CC35 0% and MRF CC36 0% on sim diagram CC5.

t l

l l

l l

l NRC-1 2

April 14,1998

PERFORMANCE CHECKLIST STANDARDS UN fiel siaI N/A RECORD START TIME 1.

Refer to BwOP CV-15.

Locate and Open BwOP CV-o o

a 15.

(May be performed at any time.)

2.

Verify Rx Power limit.

Verify Rx Power is at least a

o o

0.1% below the applicable power limit.

3.

Verify seal water return Verify 1CV8100 and 1CV8112 o

o a

valve lineup.

open.

• 4.

Establish excess Open:

o o

a letdown flow.

1CC9437A 1CC94378 (CUE: The SM does not want Verify /Close Se-1 Return directed to Spray 1HCV-CV123 Nozzles.)

Place 1CV8143 to VCT position

• 5.

Establish Flow Open Loop Drains:

a o

a

. Loop drain valves (1RC8037A/B/C/D)

+ 1CV8153A/B

. Slowly OPEN 1HCV-CV123 to obtain flow.

• 6.

Identify loss of cooling identify Excess Letdown outlet a

o o

to Excess letdown heat temperature on 1TI-122A exchangers and close

>165'F.

1HCV-CV123.

Identify loss of cooling to heat exchanger and close 1HCV-CV123 NRC-1 3

April 14,1998

PERFORMANCE CHECKLIST STANDARDS UN SAI S6I N/A 7.

Notify Unit Supervisor Notify US of failure o

a o

and recommend investigation.

Recommend investigating failure

• 8.

Establish Excess Letdown Flow.

.c'owly open 1HCV-CV123 to a

o a

obtain flow

• 9.

Secure Normal CV Letdown per BwOP Close the following valves:

a o

a CV17 1CV8149A 1CV8149B 1CV8149C 1CV460 1CV459 1CV8152 1CV8160 (CUE: This completes this JPM.)

~~

~

~

~

~

Instructor Note:

After cause is identified, report local valve (ICC9511) has been repositioned open and continue with excess letdown operations.

L RECORD STOP TIME NRC-1 4

April 14,1998

i JPM Questions l

Question No: 1 Reference Use: YES/NO Unit 1 is at 100% power with the following CVCS lineup:

1A Regen and Letdown Heat Exchangers on line 1CV8149A and 1CV8149C are open 1CV-182 is set at 70% open i

1CV-121 controller at 65%

PZR Level stable at 60%

The following indications were then observed:

Annunciator 1-21-E10,125VDC DIST. PNL 111/113 VOLT LOW, alarms DC Bus 111 volts indicates low on 1PM01J The Unit Supervisor ditocts you to maintain 8 gpm seal injection to each RCP. With 1CV-182 remaining at 70% open, what is the total flow indicated on 1F1-121 after adjusting to 8 gpm per pump?

Expected Answer:

32 gpm total charging flow. (Regen Hx charging and letdown isolation valves 1CV8389A and 1CV8324A fait closed)

Actual Answer:

l l Candidate's response matched expected answer.

Sat ___ Unsat __.

KIA: SYS004K104 3.4/3.8 LP Objective: Chap 15A; K.O.14 R ference(s):

20E-1-4030CV24, CV27 P&lD M-64, sheet 5 BwAR 1-21-E10 l

l f

I NRC-1 5

April 14,1998 I

Cuestion No: _2_

Reference Use: YES/NO An inadvertent Phase A occurs on Train B with Unit 1 at full power. The following conditions exist:

PZR Pressure is 2315 psig and decreasing slowly PZR Levelis 64% and increasing VCT levelis 38% and increasing e.

VCT pressure is 12 psig and increasing a

Auto Makeup is occurring Phase A has just been reset What operator actions are required to restore seal retum to normal?

Expe::ted Answer:

Riise VCT pressure to > 15 psig, then open 1CV8112. (1CV8100 does not close on Train B eA)

Actual Answer:

3 1

l l Candidate's response matched expected answer.

Sat __ Unsat __.

K/A: SYS004K132 2.8/3.1 LP Objective: RCP-1; K.O. 3 R;ference(s):

18wOA PRI-13, Step 9, page 5 of 11 20E-1-4030CV12, EF60 i

t l

i l

NRC-1 6

April 14,1998 j

JO3 PERFOR:2ANCE MEASURE TASK TITLE: Align the Fire Hazards Panel JPM No.: NRC-10 REV: 6

- TPO.No.: IV.D.OA-27 K&A No.: SYS016K4.01 TASK No.: P1-OA-TK-001 K&A IMP: 4.4/4.4 TRAINEE:

DATE: 4/14/98 EVALUATOR:

The Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS: (*)2,3 JPM TIME:

CRITICAL TIME: NA APPROX. COMPLETION TIME 8 MINUTES EVALUATION METHOD:

LOCATION:

__ PERFORM X IN PLANT X SIMULATE

___ SIMULATOR GENERAL

REFERENCES:

1.

2BwOA PRI-5, Rev. 57A MATERIALS.

2BwOA PRI-5 TASK STANDARDS:

1.

Activate the Fire Hazards Panel.

TASK CONDITIONS:

1.

You are an Extra NSO.

2.

A fire is ongoing in the Main Control Room and the U-1 Aux. Elect Room.

3.

The Remote Shutdown panels have been manned.

4.

1BwOA PRI-5 and 2BwOA PRI-5 are in Progress.

5.-

Division 21 power to the fire hazards panel is de-energized.

INITIATING CUES:

You have been directed to ALIGN the Fire Hazards Panel to monitor Unit 2 S/G Levels, S/G Pressures, PZR j

L v;l and PZR Pressure using 2BwOA PRI-5, Step 7.

l-l NRC-10 1

April 15,1998

)

PERFORMANCE CHECKLIST STANDARDS UN SAI

.SAI Nla RECORD START TIME 1.

Proceed to 2PL10J, Fire Locate the Fire Hazards Panel.

_a_ _a

_a Hazards Panel.

(426' El Curved Wall Area S-24 on Unit 2)

• 2.

Verify Power is supplied Verify / place:

_a_ _a

_a to the RCS WR Hot and Cold Leg Temperature

. Power Switch 2HS-LV001 to indications.

1. 3 position (Division 22 power)

(M: Power Switch 2HS-LV001 is in the #1 position when arriving at cabinet)

(M: Power Switch 2HS-LV001 is in the #1 position)

• 3.

Activate the Fire Place the Panel Switches to the

_a_ _a

_a Hazards Panel.

FIRE position.

(M: 2HS-RY033 is in 2HS-RY033 - PZR PRESS.

FIRE position, 2HS-RYO34 is in FIRE

?HS-RYO34 - PZR LEVEL.

position, 2HS-MS193 is in FIRE

• 2HS-MS193 - SG 2A

position, PRESS.

2HS-MS194 is in FIRE 2HS-MS194 - SG 2B

position, PRESS.

2HS-FW309 is in FIRE 2HS-FW309 - SG 2A WR

position, LEVEL.

2HS-FW310 is in FIRE 2HS-FW310 - SG 2B WR position.)

LEVEL.

(M This completes this JPM.)

RECORD STOP TIME NRC-10 2

April 15,1998

JPM Questions Question No: 1 Reference Use: VEGNO Why are the control power fuses pulled when taking local emergency control of safe shutdown equipment?

Expected Answer:

To disable all automatic trips and allow start of vital equipment.

Actual Answer:

l l Candidate's response matched expected answer.

Sat _ Unsat _.

KIA: APE 068AK206 2.4*/2.7 LP Objective: ELEC-5; K.O. 3 Reference (s):

2BwOA Elec-5, page 4 i

t l

NRC-10 3

' April 15,1998

Question N::: _2_

Reference Use: VEGINO During evacuation of the control room, letdown flowrate is established at 45 gpm as a preparation for Remote Shutdown Panel operation.

What is the basis for establishing a minimum letdown flowrate?

Expected Answer:

This minimizes the possibility of letdown isolation. (Letdown operations from the remote shutdown panel are h:mpered due to the lack of control for the letdown line pressure control valve 1CV131)

Actual Answer:

l l Candidate's response matched expected answer.

Sat _ Unsat _.

KIA: APE 068AK310 3.9/4.2 LP Objective: PRl-5; K.O. 3 R:ference(s):

2BwOA Pri-5, step Sb, page 5 of 77 I

i NRC-10 4

April 15,1998 a

f JOB PERFORMANCE MEASURE TASK TITLE: Respond to a WS System Malfunction JPM No.: NRC-2 REV: 8 TPO No.: IV.D.OA-33 K&A No.: SYS076A2.01 TASK No.:

P1-OA-TK-091 K&A IMP: 3.5/3.7 TRAINEE:

DATE: 4/15/98 EVALUATOR:

The Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS: (*)4,5 JPM TIME:

CRITICAL TIME: NA APPROX. COMPLETION TIME 6 MINUTES EVALUATION METHOD:

LOCATION:

l

_ PERFORM

__. lN PLANT l

_ SIMULATE

__ SIMULATOR GENERAL

REFERENCES:

1.

OBwOA SEC-5, Rev. 54 2.

BwOP WS-1, Rev. 6 and BwOP WS-3, Rev. 5 3.

BwAR 0-38-B10, WS HDR PRESS LOW, Rev 5 l

MATERIALS: None TASK STANDARDS:

l 1.

Respond to a WS System Malfunction.

TASK CONDITIONS:

1.

You are the Unit 1 Admin NSO.

l 2.

WS pumps OB & OC are running.

INITIATING CUES:

1.

The Equipment Attendant reports that the Oil Level in the upper motor bearing of OC WS pump 4

is out of sight low.

2.

Bearing temperatures are rising steadily and are now at 180*F.

3.

Respond to WS HDR PRESS LOW Annunciator.

NRC-2 1

April 15,1998

SIMULATOR SETUP:

IC-16,50% power.

Start WS pump OB and secure WS pump OA.

Modify remote function MRF SW38 open on sim diagram SW9 to prevent 0A pump auto start.

Modify remote function MRF SW2610% on sim diagram SW9 to cause low amps on the 1C pump.

9 NRC-2 2

April 15,1998

PERFORMANCE CHECKLIST STANDARDS UN SAI SAI Nla RECORD START TIME 1.

Refer to OBwOA SEC-5 Locate and Open OBwoA o

o o

l SEC-5 (May be done at any time.)

2.

Initiate BwOA SEC-5 for Notify both units to initiate o

a o

both units.

BwOA SEC-5.

3.

Check WS System Check:

a o

a Status WS Header Pressure >80 psig l

• 4.

Start the OA WS Pump Dispatch an Operator to Verify a

o a

WS Pump is properly lined up (CUE: Operator for starting per BwOP WS-1 reports OA WS Pump (Step 3) is ready for starting.

Place Control Switch for 0A WS Pump in START.

(CUE: Operator reports that OA WS Pump is normal following start.)

1

• 5.

Stop the OC WS Pump Place Control Switch ror OC WS o

o o

Pump in TRIP / PULL-OUT Position.

i 6.-

Check the OC WS Pump Dispatch an Operator to o

o a

l check the OC WS Pump (CUE: Operator properly shutdown.

reports OC WS pump has stopped and all Dispatch operator to verify conditions are normal tripped WS pump not rotating.

after the shutdown.

l l

NRC-2 3

April 15,1998 l

I

PERFORMANCE CHECKLIST STANDARDS UN S6I.SAI N/A 7.

Check the Status of Check -

a a

a the Station Air Systems Station Air Compressor run lights.

(CUE: Station Air Dispatch Operators to check compressor temperatures running SAC temps are normal.)

8.

Check WS Header Verify WS Pressure > 80 psig.

o a

a Pressure <80 psig.

j l

9.

Evaluate plant Dispatch operators to check a

a a

status.

WS system piping intact l

(CUE: System intact equipment temps are Running equipment not normal.)

overheated.

(CUE: This completes this JPM.)

l RECORD STOP TIME l

COMMENTS:

l NRC-2 4

April 15,1998

JPM Questions I

Question No: 1 Reference Use: YES/NG Unit 1 is coming out of a forced shutdown. The following conditions exist:

Unit 1 is currently holding at 28% reactor power for Chemistry.

Unit 2 is in a refueling outage.

The running WS pump trips.

j The standby pump auto started.

The third pump is OOS for maintenance.

The discharge check valve for the tripped pump failed to close.

What actions are required for the current plant conditions?

Expected Answer:

M:nually close discharge valve for tripped pump.

Trip the Main Turbine if the TGTMS GEN TEMP TRIP STPT EXCEEDED annunciator is lit and perform 1BwOA TG-8, Turbine Trip Below P-8, while continuing with 1BwOA SEC-5.

Actual Answer:

l l Candidate's response matched expected answer.

Sat.__ Unsat __.

KlA: SYS076A201 3.5/3.7 LP Objective: 1/0BwOA SEC-5; K.O.3 Reference (s):

OBwOA SEC-5, Step 2.b, RNO, page 2 of 11 18wOA Sec 5, Step 2.a. RNO, page 3 of 41 NRC-2 5

April 15,1998

I Question N2: _2_

Referenc3 Use: YES#de The following plant conditions exist:

Unit 1 is at 100% power e

A Non-essential service water break has occurred at the inlet to the 1A stator water cooler e

Non-essential service water pressure is decreasing and the standby pump auto starts e

WS Hdr Press annunciator 0-38-B10 is in Stator Cooling Water Disch Temp High annunciator 1-18-B14 is in e

The local operator reports isolating leak by shuttir.g 1WS033A and 1WS034A. What further actions are required to stabilize the unit?

Expected Answer:

With one stator water cooler isolated, main generator load should be reduced to 75% of rated load.

(cpprox. 880 Mw)

Actual Answer:

l l Candidate's response matched expected answer.

Sat ___ Unsat ___.

KIA: SYS076K302 2.5/2.8 LP Objective: Chap 21; K.O. 8a.

Reference (s):

BwOP GC-13, C.3., D.1.,E.3.

NRC-2 6

April 15,1998

JOB PERFORMANCE MEASURE TASK TITLE: Manually initiate Containment Spray JPM No.: NRC-4 REV:6 TPO No.: IV.D.CS-01 K&A No.: SYS026A401 T A S K N o.:

P1-CS-TK-001 K&A IMP: 4 5/4.3 TRAINEE:

DATE: 4/15/98 EVALUATOR:

The Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS: (*) 5, 7, 8 JPM TIME:

CRITICAL TIME: NA APPROX COMPLETION TIME 11 MINUTES EVALUATION METHOD:

LOCATION:

X PERFORM

._ IN PLANT

__ SIMULATE X SIMULATOR GENERAL

REFERENCES:

1.

18wFR-Z.1, Rev.1, WOG-1B MATERIALS: None TASK STANDARDS:

1.

Perform the actions required to manually initiate Containment Spray operation.

TASK CONDITIONS:

1.

You are the Unit NSO.

2.

A Large Break LOCA has occurred,18wEP-1 is in Progress.

3.

The ECCS is in the injection mode, RCS pressure - 250 psig.

4 RCP's have been stopped.

INITIATING CUES:

The CNMT PRESS Hi-3 annunciator (1-3-B4) has just alarmed and the STA has informed you that an Orange Path exists on Containment. (No other Orange or Red paths exist.)

l The US directs you to perform the actions of 18wFR-Z.1, " Response to High Containment Pressure".

NRC-4 1

April 15,1998 L

F Simulator Setup:

IC-16,50% power.

On simulator diagram RP15 modify remote function MRF RP63 OUT to prevent valve operation on B Train CS.

On simulator diagram RP14 modify remote functions MRF RP36 OUT and MRF RP37 OUT to prevent operation of A Train CS.

l Insert a Large Break LOCA on loop A, IMF TH06A MAX Value.

Trip RCP's and Freeze simulator when Hi-3 in containment occurs and go to run when examiner is ready.

When candidate manually actuates CS, modify remote functions RP36 and RP37 to normal.

i i

l 1

l l

NRC-4 2

April 15,1998 i

i

PERFORMANCE CHECKLIST STANDARDS UN SAI SAI N/.6 RECORD START TIME 1.

Enter.BwFf:-Z.1 Locate and Open a

a o

BwFR-Z.1 2.

Verify Containment Check Containment isolation a

o o

isolation Phase A Group 3 Monitor Lights 3.

Verify Containment Check Containment Vent, a

o a

Ventilation isolated Isolation Group 6 Monitor Lights 3a.

Verify Proper Verify Open:

o a

o Emergency Alignment 1CS001A 1CS001B 4.

Check if Containment Check if Containment pressure o

o a

Spray is Required.

has increased >20 psig.

'5.

Verify Valve Alignment -

Identify 1CS007A&B closed.

o a

o Manually Actuate Containment Spray Manually actuate CS and Phase B isol.

6.

Identify failure of B train 1A CS Pump Run Light LIT u

a o

CS to Actuate 18 CS Pump Run Light NOT LlT

• 7.

Manually open Place 1CS0078 Control Switch a

o a

1CS0078 to Open

'8.

Manually open Verify 1CS019A open a

o a

1CS019B Place PP 1B Test Switch in Test Place 1CS019B Control Switch to Open Place PP 1B Test Switch in Normal 9.

Verify open Verify 1CS010A&B open a

o a

1CS010A&B open NRC-4 3

April 15,1998

~

ib.

VGrify CS Pumps Check:

o a

o Running 1A CS Pump Run Light LIT i

1B CS Pump Run Light LIT 11.

Verify Phase B Valves Verify Cnmt isolation Phase B o

a o

Closed Group 6 Monitor Lights LIT l

I 12.

Verify all RCP's Verify all RCP's secured o

a o

secured l

13.

Check CS Flow Check the following flow a

o a

Indications on Scale meters:

CS Pump Discharge Flow CS Eductor Suction Flow CS Eductor Additive Flow 14.

Reset Containment Depress Containment Spray a

o a

Spray Signal Signal Reset Pushbuttons CSRA CSRB i

(CME-This completes this JPM.)

i i

RECORD STOP TIME COMMENTS:

NRC-4 4

April 15,1998 i

I-l

(

JPM Questions 1

Question No: 1 Reference Use: YESING l

The following plant conditions exist on Unit 1 following a steamline break inside containment:

I RCS Pressure is 1650 psig and rising e

PZR Levelis 0%

RCS Temp is 420*F and decreasing slowly.

e Containment pressure is 24 psig and decreasing slowly.

CS Add Tank Levelis 62%

Transition to EP-2 has just been performed e

The US directs you to secure NaOH addition due to high containment pressure caused by secondary break.

What actions are required to perform this action?

l l

Expected Answer:

R: set CS Actuation signal and close 1CS019A and B.

Actual Answer:

l l

l Candidate's response matched expected answer, Sat _ Unsat _.

KIA: SYS026A401 4.5/4.3 LP Objective: EP-1 Series; K.O.1.d Reference (s):

20E-1-4030CS06 l

18wEP-1, Step 8, Page 8 of 24 NRC-4 5

Apnl 15,1998 l

1 l

e Cuestion No: _2_

Reference Use: YES/NO During a control board valve lineup, normally open 1CS010A was inadvertently closed. A large break LOCA has just occurred while the plant was in Mode 3.

i Wh:_t is the status of the Containment Spray system after containment pressure reaches 20 psig with no

)

operator actions?

l Expected Answer:

Both containment spray pumps will be running supplying blended flow to containment.

l Actual Answer:

l l

l Candidate's response matched expected answer.

Sat __ Unsat __.

K/A: SYS026K406 2.8/3.2 LP Objective: Chap 59; K.O. 8 l

Reference (s):

20E-1-4030CS01, 02, 07 NRC-4 6

April 15,1998 i

JOB PERFORMANCE MEASURE TASK TITLE:

Respond to a PZR Pressure Channel Malfunction with Failure of Bistable to Trip.

JPM No.: NRC-3 REV: 0 TPO No.: IV.D.OA-11 K & A N o.: SYS016A2.01 TASK No.:

P18-KF-TK-007 K&A IMP: 3.0/3.1 P1-OA-TK-007 TRAINEE:

DATE: 4/15/98 3

i EVALUATOR:

The Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

1 CRITICAL ELEMENTS: (*) 3, 6, 7,10 JPM TIME:

CRITICAL TIME: NA APPROX COMPLETION TIME 18 MINUTES EVALUATION METHOD:

LOCATION:

_X_ PERFORM

_ IN PLANT

_ SIMULATE

_X_ SIMULATOR GENERAL

REFERENCES:

1.

1BwOA INST-2 (Attachment B), Rev. 57 2.

Technical Specifications 3.3.1, 3.3.2, 3.3.3.5, 3.2.5 MATERIALS: None TASK STANDARDS:

1 1.

Perforrn actions required to respond to a PZR Pressure channel failure.

2.

Identify all associated Tech Spec LCO's.

3.

Identify the proper action statements for all associated LCO's.

4.

Identify failure of bistable to trip.

I l

TASK CONDITIONS:

1.

You are the Unit 1 NSO.

2.

Unit is at power.

INITIATING CUES:

1.

Respond to PZR PRESS HIGH RX TRIP STPT ALERT Annunciator.

NRC-3 1

April 15,1998 a

Simulator Setup:

i l

lC-16,50% power.

Do not trip bistable TB411C(C1-124, BS-3) when requested by operator. Inform him the switch has been l

placed in the test position.

I l

2. Trip bistables as requested on simulator diagrams RX10 and RX4, I

l i

l i

l l

l I

1 NRC-3 2

April 15,1998 i

s PERFORMANCE CHECKLISI STANDARDS UN S6I SAI Nia RECORD START TIME 1.

Enter 18wOA INST-2 Locate and Open 1BwOA o

o o

INST-2 to Attachment B.

(May be done any time.)

2.

Check PZR Pressure.

Observe all PZR pressure o

o o

channels 455-458.

Identify Pressure channel 455 Failed High

• 3.

Return Pressurizer Place Master PZR pressure Pressure to normal.

controllerin MANUAL.

O o

o Control PZR pressure Select an operable channel.

4.

Check PZR PORVs, Check:

o o

o

]

Spray Valves and Heaters.

PZR PORV's - CLOSED PZR Spray Valves - NORMAL PZR Heaters - Normal 5.

Select operable PZR Recorder Channel Selector a

o o

pressure channel on switch positioned to any recorder.

channel but 455.

• 6.

Trip associated Ensure no other channels are o

a o

bistables.

in test or tripped.

. Dispatch an NSO to 1PA01J and Trip the following bistables.

. PB455A(C1-153, BS-1)

. PB455C(C1-153, BS-4)

. PB455D(C1-153, BS-3)

. PB455B(C1-153, BS-2)

. TB411C(C1-124, BS-3)

(Does not trip)

. TB411D(C1-124, BS-4) l NRC-3 3

April 15,1998

i 1

• 7.

Identify failure of identify fcilure of a

a a

Bistable TB411C to Bistable TB411C to i

trip.

trip (C.UE: US has been Notify US of failure of notified and directs bistable to trip you to continue with the procedure and evaluate Tech Specs upon completion) 8.

Check P-11 Interlock.

Check:

a a

a

. P-11 window dark.

9.

Check PZR Pressure Check:

a a

a Controlin Auto.

. PORV's in Auto PZR Sprays in Auto

. PZR Master Pressure Controllerin Auto (CUE: This completes this JPM.)

RECORD STOP TIME COMMENTS:

i l

l l

NRC-3 4

April 15,1998

JPM Questions Question No: 1 Reference Use: YES/NO Determine LCOs and action statements for the Pressurizer Pressure Channel failure.

Expected Answer:

LCO 3.3.1 F.U. 7, 9,10 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to trip bistables identify need to trip bistable TB411C within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> LCO 3.3.2 F.U.1.d, 9.a 6 Hour to trip bistables 1 Hour to ensure P-11 is de-energized.

LCO 3.3.3.5 F.U. 4 Restore in 7 days

-or-HSB in 6 hrs and HSD in 6 hrs LCO 3.2.5 Restore in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

-or-Reduce Thermal Power to < 5% within the next 4 hrs Actual Answer:

I l

l Candidate's response matched expected answer.

j Sat __._ Unsat __.

KIA: SYS0162.1.12 2.9/4.0 LP Objective: Chap 14; K.O. 26 Reference (s):

Technical Specifications l

NRC-3 5

April 15,1998

Question No:

2_.

Reference Use: YESMO Unit 1 is at 25% power with the Pressure Control Channel Select switch is in the CH-455/CH-456 position. Pressure channel 455 fails high and the following plant conditions are observed:

The pressurizer spray valves and PORV-455A opens.

Pressure has decreased below 2200 psig The pressurizer PORV-455A and spray valve RY455B will not close manually What actions are required for this situation?

Expected Answer:

Close the PORV-455A block valve,1RY8000A; trip the Reactor; trip the 1D RCP i

Actual Answer:

1 l

l Candidate's response matched expected answer.

Sat _ Unsat _.

K/A: SYS016K308 3.5/3.7 LP Objective: INST-2; K.O. 4 Reference (s):

OA INST-2 NRC-3 6

April 15,1998 1

t.

JOB PERFORMANCE MEASURE TASK TITLE: Manually initiate Containment Spray JPM No.: NRC-4 REV: 6 TPO No.: IV.D.CS-01 K & A N o.: SYS026A401 TASK No.:

P1-CS-TK-001 K&A IMP: 4.5/4.3 TRAINEE:

DATE: 4/15/98 EVALUATOR:

The Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS: (*)5,7,8 JPM TIME:

CRITICAL TIME: NA APPROX COMPLETION TIME 11 MINUTES EVALUATION METHOD:

LOCATION:

X PERFORM

.__ IN PLANT

____ SIMULATE

._X. SIMULATOR GENERAL

REFERENCES:

1.

18wFR-Z.1, Rev.1, WOG-1B MATERIALS: None TASK STANDARDS:

1.

Perform the actions required to manually initiate Containment Spray operation.

TASK CONDITIONS:

i 1.

You are the Unit NSO.

2.

A Large Break LOCA has occurred,1BwEP-1 is in Progress.

3.

The ECCS is in the injection mode, RCS pressure - 250 psig.

l 4.

RCP's have been stopped.

INITIATING CUES:

The CNMT PRESS Hi-3 annunciator (1-3-84) has just alarmed and the STA has informed you that an Orange Path exists on Containment. (No other Orange or Red paths exist.)

The US directs you to perform the actions of 1BwFR-Z.1, " Response to High Containment Pressure".

NRC-4 1

April 15,1998

(

i

Simulator Setup:

IC-16,50% power.

On simulator diagram RP15 modify remote function MRF RP63 OUT to prevent valve operation on B Train CS.

On simulator diagram RP14 modify remote functions MRF RP36 OUT and MRF RP37 OUT to prevent operation of A Train CS.

Insert a Large Break LOCA on loop A, IMF TH06A MAX Value.

Trip RCP's and Freeze simulator when Hi-3 in containment occurs and go to run when examiner is ready.

When candidate manually actuates CS, modify remote functions RP36 and RP37 to normal.

i 4

NRC-4 2

April 15,1998

I PERFORMANCE CHECKLIST STANDARDS UN S6I SAI Hla RECORD START TIME l

1.

Enter _BwFR-Z.1 Locate and Open a

a a

BwFR-Z.1 2.

Verify Containment Check Containment isolation a

a a

l lsolation Phase A Group 3 l-Monitor Lights l

3.

Verify Containment Check Containment Vent.

o a

o l

Ventilation isolated Isolation Group 6 Monitor Lights j

i l

32.

Verify Proper Verify Open:

o a

a J

Emergency Alignment 1CS001A 1CS001B l

\\

)

4.

Check if Containment Check if Containment pressure a

a a

l Spray is Required.

has increased >20 psig.

l

'5.

Verify Valve Alignment -

Identify 1CS007A&B closed.

o a

o Manually Actuate Containment Spray Manually actuate CS and Phase B isol.

6. '

identify failure of B train 1A CS Pump Run Light LIT a

a a

CS to Actuate 1B CS Pump Run Light NOT LIT

• 7.

Manually open Place 1CS007B Control Switch a

a a

1CS007B to Open

• 8.

Manually open Verify 1CS019A open a

a a

i 1CS019B Place PP 18 Test Switch in Test Place 1CS019B Control Switch to Open Place PP 1B Test Switch in i

[-

Normal 1

9.

Verify open Verify 1CS010A&B open a

a a

1CS010A&B open l

l NRC-4 3

April 15,1998

10.

V;rify CS Pumps Check:

a a

a Running 1A CS Pump Run Light LIT 18 CS Pump Run Light LIT 11.

Verify Phase B Valves Verify Cnmt Isolation Phase B a

a a

Closed Group 6 Monitor Lights LIT 12.

Verify all RCP's Verify all RCP's secured a

a a

secured 13.

Check CS Flow Check the following flow a

a a

indications on Scale meters:

CS Pump Discharge Flow CS Eductor Suction Flow CS Eductor Additive Flow 14.

Reset Containment Depress Containment Spray a

a a

Spray Signal Signal Reset Pushbuttons CSRA CSRB (C11E:

This completes this JPM.)

RECORD STOP TIME COMMENTS:

I NRC-4 4

April 15,1998

l JPM Questions Question No: 1 Reference Use: YES/NO The following plant conditions exist on Unit 1 following a steamline break inside containment:

RCS Pressure is 1650 psig and rising PZR Levelis 0%

RCS Temp is 420*F and decreasing slowly.

Containment pressure is 24 psig and decreasing slowly.

CS Add Tank Levelis 62%

Transition to EP-2 has just been performed

=

The US directs you to secure NaOH addition due to high containment pressure caused by secondary break.

What actions are required to perform this action?

Expected Answer:

Reset CS Actuation signal and close 1CS019A and B.

Attual Answer:

i l

l Candidate's response matched expected answer.

Sat _ Unsat _.

K/A: SYS026A401 4.5/4.3 LP Objective: EP-1 Series; K.O.1.d Reference (s):

20E-1-4030CS06 1BwEP-1, Step 8, Page 8 of 24 l

NRC-4 5

April 15,1998

@uestion No: _2_

Reference Use: YES/NO During a control board valve lineup, normally open 1CS010A was inadvertently closed. A large break LOCA has just occurred while the plant was in Mode 3.

What is the status of the Containment Spray system after containment pressure reaches 20 psig with no operator actions?

Expected Answer:

Both containment spray pumps will be running supplying blended flow to containment.

Actual Answer:

i l

l Candidate's response matched expected answer.

l-Sat _ _ Unsat __.

K/A: SYS026K406 2.8/3.2 LP Objective: Chap 59; K.O. 8 Reference (s):

20E-1-4030CS01, 02, 07 NRC-4 6

April 15,1998 1

l.

I i

!0 o

l l

JOB PERFORMANCE MEASURE TASK TITLE: Perform an Emergency Boration JPM No.: NRC-6 REV: 0 i

TPO No.: IV.D.OA-08.

K & A N o.: SYS004A2.14 T A S K N o.: P1-OA-TK-033 K&A IMP: 3.8/3.9

. TRAINEE:

DATE: 4/15/98 l

EVALUATOR:

l ThaTrainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS: (*)2,3 JPM TIME:

l CRITICAL TIME: NA APPROX COMPLETION TIME 10 MINUTES EVALUATION METHOD:

LOCATION:

X PERFORM

__ IN PLANT I

___. SIMULATE

._X_ SIMULATOR GENERAL

REFERENCES:

1.

18wOA PRI-2, Rev. 56 2.

1BwAR 1-9-A3, Rev SE1 MATERIALS: None TASK STANDARDS:

1.

Initiate Emergency Boration of the RCS.

I TASK CONDITIONS:

1.

You are the unit NSO.

2.

A Reactor Trip has occurred and 1BwEP ES-0.1 is in progress at Step 5.

INITIATING CUES:

1.

Shutdown Bank E Rod Bottom Lights are NOT LIT.

2.

The US directs you to commence Emergency Boration in accordance with 1BwOA PRI-2.

l l

NRC-5 1

April 15,1998

1l 6 t

Simulator Setup:

IC-16,50% power

\\

insert malfunctions FW43 and FW44 to trip AF pumps to prevent excessive cooldown.

i insert malfunctions RD05H04, D08, H12, and M08 at 231 steps to stick 4 control rods out.

Insert malfunctions to fail Tave at 540*F.

Trip 1 A CV pump and the Main Turbine.

After the reactor trips, freeze the simulator until the examiner is ready to proceed.

l l

NRC-5 2

April 15,1998

4 PERFORMANCE CHECKLIST STANDARDS UN sAI SAT Hla l

RECORD START TIME 1.

Refer to 1BwOA PRI-2.

Locate and Open a

o a

1BwOA PRI-2.

(NOTE: May be done at cnytime.)

l

• 2.

Verify Cent. Chg. Pump identify trip of 1 A CV pump and a

o o

running start 1B CV pump as follows:

i Verify. suction source

- 1CV112B & C open Start 1B CV pump

• 3.

Align boration flowpath Place 1CV8104 Control a

o o

l l

Switch to Open.

Start Boric Acid Transfer Pump Check boration flow > 30 gpm.

t increase Charging flow as necessary l

l 4.

Energize Pzr backup Manually turn on the Backup a

o o

heaters.

Heaters.

I i

I (GUE: This completes this JPM.)

l RECORD STOP TIME l

l COMMENTS:

NRC-5 3

April 15,1998

1 p-l.

I JPM Questions Question No: 1 Reference Use: YES/NO l

l l

Due to faults on Bus 143 and in the switchyard, both units have lost offsite power. The fault caused a reactor trip on both units. If plant conditions require an emergency boration for Unit 1, what method (s) is(are) available to borate the RCS? (Assume normal plant lineup prior to the reactor trip) l Expected Answer:

i The only emergency boration flowpath available is from the RWST via the CV pump suction.

l Actual Answer:

l l

l Candidate's response matched expected answer.

Sat _, Unsat _.

KIA: SYS004K201 2.9/3.1 LP Objective: Chap 15B; K.O.11 Reference (s):

BwOA PRI-2 20E-1-4030AB01 l

i t

i NRC-5 4

April 15,1998

' Question No:._2_

Reference Use: YES/NO Unit 1 is operating at 100% of full power when a M::in Turbirie tri conditions exist upon entry into ES-0.1, " Reactor Trip Response,p occurs. The following plant SD Bank E control rods at 231 steps PZR Levelis 18% and rising PZR Press is 2045 psig and rising RCS Tavg 540*F and stable.

Steam Dumps are closed How much' boric acid is required to be added from the BAST?

Expected Answer:

4975 gallons l

(545 *F-540 'F=5 'F 5x35 gal =175 gallons for temp deviation 4 rods in SD Bank E 4x1200 gal =4800 gallons for rods Total gallons = 175 gal + 4800 gal = 4975 gallons)

Actual Answer:

l l Candidate's response matched expected answer.

i Sat.___ Unsat ____.

KIA: SYS004A404 3.2/3.6 LP Objective: EP-0 Series; K.O. 6 Reference (s):

ES-0.1, step 3e RNO, Sb RNO NRC-5 5

April 15,1998

1 1

JOB PERFORMANCE MEASURE l

TASK TITLE: Cross Tie of ESF and Non-ESF Bus l

l JPM No.: NRC-6 REV: 2 TPO No.: IV.D.OA-60/61 K & A N o.: SYS062A2.12 TASK No.: P1-OA-TK-024 K&AiMP: 3.2/3.6 l

TRAINEE:

DATE: 4/15/98 EVALUATOR:

The Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

l CRITICAL ELEMENTS: (*) 5, 7 JPM TIME:

l l

CRITICAL TIME: NA APPROX. COMPLETION TIME 6 MINUTES 1

EVALUATION METHOD:

LOCATION:

_.X_ PERFORM

._ IN PLANT

__ SIMULATE

__X_ SIMULATOR MATERIALS:

1 Copy of BwEP-1, Step 11.b. (RNO), Rev 1 A, WOG-1B l

l GENERAL

REFERENCES:

l BwEP-1, Step 11.b. (RNO), Rev 1 A, WOG-1B TASK STANDARDS:

1.

Correctly perform the required actions per BwEP-1, Step 11.b. Cross connecting a non-ESF bus to a ESF bus.

TASK CONDITIONS:

1.

You are the extra NSO.

l 2.

The Unit has experienced a loss of coolant accident.

3.

The NSO has completed the actions of BwEP-0 and transitioned to BwEP-1.

4.

Unit Common Station Air Compressor is unavailable due to maintenance activities.

5.

The " SAC 1 RCVR PRESS LOW' annunciator (37-C2) on OPM01J is lit, and Service Air Header Pressure is 92 psig and decreasing slowly.

INITIATING CUES:

The US directs you to perform BwEP-1, Step 11.b.

NRC-6 1

April 14,1998

Simulator Setup:

1^

l lC16,50% power l

l Insert malfunction ED18D to prevent ABT of 1442 breaker.

l l

Override 1442 Breaker handswitch in PTL to prevent operation of breaker.

i insert LOCA to trip and Si the unit.

Perform actions up to step 11 of EP-1. Ensure Sl is reset.

I i

l l

l l

l l

NRC-6 2

April 14,1998 1

j PERFORMANCE CHECKLIST STANDARDS UN

(

l SAI SAI N/A I

RECORD START TIME 1.

Check 4KV NON-ESF Check the following indications:

a o

a busses -ENERGlZED BY OFFSITE POWER:

. SAT 142-1 Bus Alive light -

l LIT

. ACB 1432 - CLOSED l

. SAT 142-2 Bus Alive light -

l LIT

. ACB 1442 - OPEN l

2.

Attempt to restore

. Attempt to close ACB 1442.

o a

o offsite power to Bus

-O R-144.

. Dispatch an EO to locally check ACB 1442.

l (CUE: EO repods ACB cppears to be damaged) i l

3.

Locally verify all Dispatch an EO to locally a

o a

breakers on Bus 144 verify all breakers on Bus 144 are OPEN.

are open.

(CUE: EO reports all BRKRS open on bus 144) l l

t 4.

Place all non-running Place the contro! switch for WS o

o o

l WS pumps in the PULL Pump OB to the PULL OUT OUT position for Bus position.

144.

l l

• 5.

Reset Si Recire Sump Depress the SI RECIRC SUMP o

o a

l isolation Valve.

ISOL VLV reset push-button for TRAIN B. (1Sl8811B) 6, Open all 480V Open the following for Bus 144:

a o

o transformer LOW side

1) XFMR 034RA (BUS 034R) l breakers for Bus 144.

2) XFMR 034 (BUS 034P) l

3) XFMR 134X (BUS 134X) l

4) XFMR 134Y (BUS 134Y)

5) XFMR 134Z (BUS 134Z)

6) XFMR 034WA (BUS 034W)

7) XFMR 134V (BUS 134V)

8) B/U HTR GP "B"

9) CONTROL HTR GP "C" NRC-6 3

April 14,1998 t

i PERFORMANCE CHECKLIST STANDARDS UN SAI SAI N/A

• 7 Energize Bus 144 Close breaker 1421.

o o

a from ESF crosstie breaker.

(CUE: This completes this JPM)

RECORD STOP TIME COMMENTS:

j l

l l

l t

I i

I l

l l

NRC-6 4

April 14,1998

JPM Quegtions Question No: 1 Reference Use: YES/NO Given the following plant conditions on Unit 1:

Mode 3 following a Loss of Offsite Power Bus 141 is powered from 1 A Diesel Generator e

Bus 143 has been crosstied to Bus 141 e

Current bus 141 loading is 1350 KW Current bus 143 loading is 2137 KW e

If the 1 A SX pump is started, how much load is still avaRable following the pump start on the 1 A Diesel Generator for continuous operation under the current plant conditions?

Expected Answer:

1000KW remaining. [5500KW - 1350 (141 loads) - 2137 (143 loads) - 1013 (1 A SX pump load)]

Actual Answer:

l l Candidate's response matched expected answer.

Sat _ Unsat _.

KIA: SYS064A205 3.1/3.2 LP Objective: ELEC-3; K.O. 4 Reference (s):

BwOA ELEC-3 page 7 BwOA ELEC-4 page 11 NRC-6 5

April 14,1998

Qusction No: _2 Rafsrence Uso: YES/NO Unit 1 is at 100% power with all systems lineup for normal operation. While performing an offsite power availability surveillance, the operator notices breaker 1441 trip. It appears to have tripped due to ground overcurrent.

If all equipment operates as designed, what would you expect the plant conditions and 4KV bus status to be in 5 minutes?

Expected Answer:

Unit 1 tripped with all buses, except bus 144, energized from SAT 142-1 and 142-2.

(WHPS Actuates closing FW valves resulting in a reactor trip, all other buses will ABT)

Actual Answer:

l l Candidate's response matched expected answer.

Sat ___ Unsat __.

K/A: SYS062K403 2.8/3.1 LP Objective: Chap 4; K.O.16 Rsference(s):

20E-1-400880 20E-1-4030LV08 20E-1-4030FW20, 61 NRC-6 6

April 14,1998 l

JOB PERFORMANCE MEASURE TASK TITLE: Respond to a Safety injection with a Loss of Instrument Bus 114 JPM No.: NRC-7 REV: 0 TPO No.: IV.D.EP-19 K & A N o.: SYS013A4.01 T A S K N o.: P1-EP-TK-037 K&A IMP: 4.5/4.8 TRAINEE:

DATE: 4/15/98 EVALUATOR:

The Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS: (*) 1, 2, 3, 4, 6,10, JPM TIME:

11,12,16 CRITICAL TIME: NA APPROX COMPLETION TIME 9 MINUTES EVALUATION METHOD:

LOCATION:

_X_ PERFORM

_ IN PLANT

_ SIMULATE X SIMULATOR GENERAL

REFERENCES:

1.

18wEP-0, Rev.1 A, WOG 1B MATERIALS: None TASK STANDARDS:

1.

Perform the immediate Action steps for a Reactor trip from memory.

2.

Perform the next twelve steps for a Safety injection.

1 TASK CONDITIONS:

1.

You are the unit NSO.

2.

A Reactor Trip and Manual Si has just occurred.

3.

All systems are in AUTO.

INITIATING CUES:

1.

Take appropriate actions in accordance with BwEP-0.

NRC-7 1

April 15,1998

Simulator Setup:

. IC-16,50% power Insert malfunction ED11D to de-energize Instrument Bus 114 then override switch to manually actuate Sl.

i i

l NRC-7 2

April 15,1998

j PERFORMANCE CHECKLIST STANDARDS UN l

SAI SAI LE6 RECORD START TIME

• 1.

Verify Reactor Trip.

Verify:

o a

o Rod Bottom Lights LIT.

RTB's open.

Neutron flux decreasing.

• 2.

Verify Turbine trip.

Verify:

a o

o All Throttle Stop Valves -

CLOSED.

1 All Governor Valves -

CLOSED.

• 3.

Verify Power to 4KV ESF busses BOTH a

o o

ESF Buses.

ENERGlZED:

l

. Bus 141

. Bus 142

• 4.

Checkif St Actuated.

Check:

a o

a Any SI First Out Annunciator LIT.

SI Actuated Permissive Light j

LIT.

i i

Manually actuate SI l

5.

Verify FW lsolation.

Verify:

o o

o

a. FW pumps - TRIPPED:

i l

FW PUMPS TRIP alarms - LIT.

b. FW isolation monitor lights -

l l

LIT.

1 i

c. FW pumps discharge valves - CLOSED:

1FWOO2A 1FWOO2B 1FWOO2C NRC-7 3

April 15,1998

PERFORMANCE CHECKLIST STANDARDS UN SAI SAI N/A

• 6.

Verify ECCS Pumps Verify CV Pumps Mun Lights a

a o

Running.

LIT.

Manually start 1B CV pump Verify RH Pumps Run Lights l

LIT.

i Manually start 1B RH pump Verify St Pumps Run Lights LIT.

Manually start 1B SI pump D

D D

j 7.

Verify Containment Verify Group 3 CNMT isol Isolation Phase A.

Monitor Lights - LIT.

j Manually Actuate Phase A Manually align following valves:

.RF027.PR001B.WOOO6B

. WOO 20B. WOOS 6A.FP010

.PS229A.PS229B.RE9157

.RE9160B.RE9170.CV8112

.RY8028.RY8033 O

O O

8.

Verify Containment Verify Group 6 CNMT Vent isol Ventilation isolation.

Monitor Lights - LIT.

O O

O 9.

Verify AF_ Pumps Verify AF Pump Run Lights LIT.

Running.

Verify AF013's open Verify AF005's throttled - B Train Closed O

O O

• 10.

Verify RCFC's running Verify RCFC Low Speed Run in Low Speed.

Lights - LIT.

. Stop 1B and 1D RCFC High Speed Fans.

After 20 seconds, start 18 and 1D RCFCs in Low Speed I

NRC-7 4

April 15,1998

PERFORMANCE CHECKLIST STANDARDS UN SaI SAI Bla

• 11.

Verify CC Pumps Verify CC Pumps Run Lights a

o a

Running.

LIT.

l Manually start 1R CC pump

• 12.

Verify SX Pumps Verify SX Pumps Run Lights o

a o

Running.

LIT.

Manually start 18 SX pump 13.

Check if Main Verify steamline isolation NOI o

a a

Steamlines should be required by checking for one or

isolated, more of the following:

. Any Steamline Pressure

<640 psig

-OR-

. Containment Pressure

>8.2 psig 14.

Verify Containment Verify Containment Spray NOT a

a o

Spray not Required.

required by checking:

. Containment Pressure has remained <20 psig.

15.

Verify total AF Flow.

Verify total AF flow; o

a o

AF Flow > 500 gpm available Check SG Narrow Range Level

>11%

Control feed flow to maintain 11 to 50%

Verify no SG levelincreasing in an uncontrolled manner NRC-7 5

April 15,1998

PERFORMANCE CHECKLIST STANDARDS UN S6I SAI MB i

• 16.

Verify Diesel Verify:

a o

a Generators Running.

DGs both running - Manually start 1B DG 1SX169A&B Open Dispatch Operator to locally check Diesel Generator <a.

(CUE:

This completes this JPM.)

RECORD STOP TIME COMMENTS:

'l NRC-7 6

April 15,1998

(

JPM Questions i

Question No: 1 Reference Use: YES/NO 1

Given the following plant conditions on Unit 1:

Loss of instrument Bus 114 Small break LOCA on C loop Currently at step 20 of EP-0

+

All operator actions in accordance with EP-0 have been completed e

The operator inadvertently takes both control switches for 1Sl8801 A and 1Sl8801B to the close position.

What are the valve positions for 1Sl8801 A and 1S18801B after the control switch manipulations?

Expected Answer:

1Sl8801 A would close and then re-open.1Sl8801B would close and remain closed.

A tual Answer:

l l Candidate's response matched expected answer.

Sat _ Unsat _.

K/A: SYS006K409 3.8/4.2 LP Objective: Chap 61; K.O. 8 Reference (s):

18wOA ELEC-2, Table D, Page 19 of 21 20E-1-4030S106 UFSAR figure 7.2-1 1

i I

l NRC-7 7

April 15,1998 4

l l

Question No: _2_

Reference Use: YES/NO Given the following plant conditions on Unit 1:

Small Break LOCA has occurred from 100% power RCS Press is 1100 psig e-PZR Levelis 0%

SG Press is 600 psig e

Containment Press is 3 psig A Reactor Trip has been actuated from 1PM05J and 1PM06J "A" Reactor Trip Breaker is closed e

Currently at step 10 of EP-1 e

Wh:t actions are required to accomplish a reset of Sl on Train A?

Expected Answer:

Locally open or rack out the "A" Reactor Trip Breaker and depress the "A" Train Si reset pushbutton.

Actual Answer:

l l Candidate's response matched expected answer.

Sat _ Unsat _.

K/A: SYS013K401 3.9/4.3 LP Objective: Chap 61: K.O. 6 Reference (s):

UFSAR Figure 7.2-1 Sheets 2 and 8 i

j NRC-7 8

April 15,1998

JOB PERFORMANCE MEASURE TASK TITLE: Respond to a Loose Patts Monitor Alarm JPM No.: NRC-8 REV: 6 TPO No.: IV.D.LM-03 K & A N o.: SYS002A3.02 T A S K N o.:

P1-LM-TK-005 K&A IMP: 2.6/2.8 TRAINEE:

DATE: 4/14/98 EVALUATOR:

The Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS: (*)2,4 JPM TIME:

CRITICAL TIME: NA APPROX COMPLETION TIME 13 MINUTES EVALUATION METHOD:

LOCATION:

___ PERFORM X IN PLANT j

X SIMULATE

__ SIMULATOR GENERAL

REFERENCES:

1.

BwAR 2-13-E9, Rev. 51 2.

BwOP LM-6, Rev. 5 3.

BwOP LM-ST1, Rev. 51 MATERIALS:

1.

Copy of BwOP LM-6 2.

Copy of BwOP LM-ST1 TASK STANDARDS:

1.

Respond to Loose Parts Monitor Alarm.

TASK CONDITIONS:

1.

Unit 2 is at Power. All systems normal with no evolutions in progress.

2.

You are the extra NSO.

3.

Loose Parts Moni or System Trouble is in Alarm (2-13-E9).

4.

SER point 1760 " Lose Parts Monitor System impact Noise Level Alarm"is printed.

NRC-8 1

April 14,1998

INITIATING CUES:

You are directed by the Unit Supervisor to take the appropriate actions per BwAR 2-13-E9.

)

l l

i i

C-8 2

April 14,1998

i PERFORMANCE CHECKLIST STANDARDS UN M M N/A l

RECORD START TIME 1.

Refer to BwAR 2-13-E9.

Open BwAR 2-13-E9.

O o

a

• 2.

Determine if alarm is

. Locate Loose Parts a

o a

HIGH or LOW.

Monitor Cabinet in AEER.

I Check:

(GUf.: Channel 2W-LM003 Alarming Module Hi High Alarm Light is LIT.)

Alarm and Lo Alarm Lights.

(CUE: FIRST OUT LED 3 is LIT.)

. First Out Indicator.

l I

3.

Perform subsequent

. Record time, plant a

o o

operator actions of status and First Out BwAR 2-13-E9.

Alarm number.

(GUE: No Plant Transients

. Refer to BwOP LM-6.

have occurred. FIRST OUT LED 3 is LIT.)

I

• 4.

Perform BwOP LM-6.

. Verify / Press Rem P/B on a

o o

Tape Recorder 1 and 2.

(C.UE REM P/B's are pressed.

. Note Channelin Alarm and First Out.

2W-LM003 Hi Alarm and First

. Determine sensor location -

Out LED 3 are LIT.

Hot Side S/G A Channel Head.

Al:rms clear,2W-LM003 Hi

. Press the Reset on Afirm relights, FIRST OUT Mester Alarm.

LED 3 is LIT.

Speaker Selector Switches are

. Align speakers to First Out cligned to 2W-LM003.

Channel.

There are metallic impact

. Listen for metallic impact s:unds.

sounds.

SM is contacted to inform Sys.

. Contact Shift Manager to Eng and/or Station Nuclear inform System Engineering Engineer.)

and/or Station Nuclear Engineer 4

NRC-8 3

April 14,1998 i

L

D (GME: Thi3 completes this JP!2.)

l l

RECORD STOP TIME COMMENTS:

I l.-

NRC 4 April 14,1998 l

l l

JPM Questions Question No: 1 Reference Use: YES/NO 1

l l

Unit 2 is at 100% power. RCS loop flow channel 2FT-415 fails low at 10:30 a.m. Ten (10) minutes later, a Unit i reactor trip occurs due to a card failure on DEHC. 5 % hours after the reactor trip, RCS loop flow chinnel,2FT-436 fails high. No Actions per the BwOA have taken place.

What Unit 2 action (s) is(are) required?

Expected Answer:

Need to trip bistables for both failed loop flow transmitters. 20 minutes remain to trip bistable for 2FT-415 and six hours to trip bistable for 2FT-436.

Actual Answer:

l l Candidate's response matched expected answer.

Sat.__ Unsat __.

KIA: SYS016-2.2.22 3.8/4.2 LP Objective: INST 2; K.O. 5 i

Reference (s):

2BwOA INST-2, Attachment K Tech Specs 3.3.1 i

i NRC-8 5

April 14,1998

Question Nr: _2_

R:ference Use: YES/NO Unit 2 has 2C and 2D RCPs running with RCS Temp of 175*F and RCS Press of 300 psig. After starting the 2A RCP, the following stable plant conditions exists:

RCS Temp - 170*F RCS Press - 330 psig VCT Pressure - 16 psig RCP parameters as follows:

26 2B 2C 20 Motor Bearing Temps 165'F 137'F 157'F 157'F Lower Radial Bearing Temps 175'F 137'F 164*F 163*F RCP Seal AP 300 psid 260 psid 295 psid 305 psid Sealinjection flows 8 gpm 10 gpm 8.5 gpm 8 gpm RCP Vibrations 6 mits 1 mit 2.5 mils 2 mils What actions, if any, are required following the start of the 2A RCP and prior to starting the 2B RCP?

Expected Answer:

Trip the 1 A RCP (due to excessive vibrations) and raise 2B RCP Seal AP to > 275 psid (by increasing RCS pressure).

Actual Answer:

l l Candidate's response matched expected answer.

Sat _ Unsat _.

K/A: SYS003K614 2.6/2.9 LP Objective: Chap 13; K.O. 8 Reference (s):

BwOP RC-1 NRC-8 6

April 14,1998 i

JOB PERFORMANCE MEASURE TASK TITLE: Local Roset of Phase A isolation JPM No.: NRC-9 REV: 2 TPO No.: IV.D.RP-01 K&A No.: SYS013K4.02 TASK No.:

P1-RP-TK-002 K&A IMP: 3.9/4.2 TRAINEE:

DATE: 4/14/98 EVALUATOR:

The Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS: (*)2,5,6 JPM TIME:

CRITICAL TIME: NA APPROX COMPLETION TIME 13 MINUTES EVALUATION METHOD:

LOCATlON:

_ PERFORM X IN PLANT K. SIMULATE

.__ SIMULATOR GENERAL

REFERENCES:

1.

2BwOA PRI-5 Attachment E, Rev. 57A MATERIALS:

Cabinet Key for 2PA09J Attachment "E" of 2BwOA PRI-5 TASK STANDARDS:

)

1.

Correctly reset containment isolation phase A, IAW 2BwOA PRI-5, Attachment E.

TASK CONDITIONS:

The crew is responding to a spurious Train A safety injection on Unit 2.

2BwEP ES-1.1 (Si Termination) is in progress at step #2.

The Phase A reset pushbutton for Train A in the Control Room will not work.

INITIATING CUES:

The Unit Supervisor has directed you to reset Phase A containment isolation on Train A per 2BwOA PRI 5 Attachment E. No safety concerns exists for entry into the AEER.

NRC-9 1

April 15,1998

r 1

PERFORMANCE CHECKLIST STANDARDS UN SAI S6I N/A RECORD START TIME

.................c............................................

NOTE Hand Candidate the enclosed copy of 2BwOA PRI-5 Attachment E (Control Room Inaccessibility Unit 2, ESF Remote Block or Reset).

Only the portions of the procedure needed to reset Train A of Containment Phase A isolation need to be completed.

1.

Obtain keys to EF Proceed to the Shift Office and a

o a

cabinet.

obtain the key for 2PA09J NOTE Have Examinee locate the jumpers, but do not allow them to be removed from the cabinet.

~*

NOTE 1

Due to time or radiological concems, Step 2 can be explained by the Candidate at the evaluator's discretion.

• 2.

Obtain 2 Jumpers At the Center Desk or at the o

a o

Remote Shutdown Panellocate the 2 snap clip jumpers required.

3.

Proceed to the Aux.

Electric Equipment Proceed to the Aux. Electric a

o a

Room.

Equipment Room for Unit 2.

4.

Proceed to cabinet a

o a

2PA09).

Unlock and open the rear of 2PA09).

i NRC-9 2

April 15,1998

PERFORMANCE CHECKLIST STANDARDS UN SAI SAI N/A NOTE Inform Examinee that all required actions in 2PA09J are to be

• simulated and make every effort not to touch any of the components

• in 2PA09J.

• 5.

Reset Train A Cnmt.

In the rear of the Logic Cab.

o a

a Phase A Isolation.

locate terminal board TB504 and jumper points 7 and 8.

(M: Jumper installed across points 7 and 8.)

• 6.

Unlatch Train A In the rear of Output Cabinet a

o a

Phase A Slave locate terminal board TB644 Relays.

and jumper points 3 and 4.

(M: Jumper installed across points 3 and 4.)

7 Check K605 relays Check K605 relay in 2PA09J a

a a

2PA09J deenergized (relay not deenergized.

sucked in.)

(M: K605is doenergized.)

8.

Remove jumpers.

Remove jumpers.

a a

a (M: Jumpers removed.)

(M: This completes this JPM.)

RECORD STOP TIME COMMENTS:

i NRC-9 3

April 15,1998

JPM Questions l

Question No: 1 Refer 6nce Use: VE6/NO l

Unit 1 is shutdown with a cooldown in progress. RCS pressure has just been reduced to less than l.

1930 psig and the steamline low pressure Si signal has been blocked.

l What protection is now provided if a steamline break accident occurs?

Expected Answer:

Rapid steamline depressurization protection is still provided by the High Steamline Pressure Rate signal.

Actual Answer:

l l Candidate's response matched expected answer.

Sat __ Unsat.__.

K/A: SYS013K403 3.9/4.4 LP Objective: Chap 61; K.O. 7 Reference (s):

BwAR 1-BP-4.2 Technical Specification Basis - B3/4.3.2 NRC-9 4

April 15,1998

l

+-

Question N : _2_

Reference Use: YES/NO The following plant conditions exist on Unit 2:

Shutdown for refueling outage RH cooldown in progress on 'A' Train RH RCS Temperature is 210'F RCS Pressure is 335 psig What operator actions are required to allow placing SSPS in a " Shutdown Condition" and what SSPS automatic actuation capabilities are NOT disabled when in the " Shutdown Condition"?

Expected Answer:

Unit must be placed in Mode 5 (<200*F). BDPS and VQ are not disabled.

Actual Answer:

l l Candidate's response matched expected answer.

Sat __ Unsat KIA: SYS013K502 2.9/3.3 LP Objective: Chap 60a; K.O. 9 Reference (s):

BwOP RP-7 NRC-9 5

April 15,1998

l JOB PERFORZANCE MEASURE TASK TITLE: Align the Fire Hazards Panel JPM No.: NRC-10 REV;6 TPO No.: IV.D.OA-27 KSA No.: SYS016K4.01 TASK No.: P1-OA-TK-001 K&A IMP: 4.4/4.4 TRAINEE:

DATE: 4/14/98 EVALUATOR:

The Trainee: PASSED this JPM.

TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS: (*)2,3 JPM TIME:

CRITICAL TIME: NA APPROX. COMPLETION TIME 8 MINUTES EVALUATION METHOD:

LOCATION:

__ PERFORM X IN PLANT

__X. SIMULATE

___ SIMULATOR GENERAL

REFERENCES:

1.

2BwOA PRI-5, Rev. 57A MATERIALS:

2BwOA PRI-5 l

TASK STANDARDS:

1.

Activate the Fire Mazards Panel.

TASK CONDITIONS:

1.

You are an Extra NSO.

2.

A fire is ongoing in the Main Control Room and the U-1 Aux. Elect Room.

3.

The Remote Shutdown panels have been manned.

4.

18wOA PRI-5 and 2BwOA PRI-5 are in Progress.

5.

Division 21 power to the fire hazards panel is de-energized.

INITIATING CUES:

Ycu have been directed to ALIGN the Fire Hazards Panel to monitor Unit 2 S/G Levels, S/G Pressures, PZR Lcvel and PZR Pressure using 2BwOA PRI-5, Step 7.

h. l "

1 April 15,1998

O PERFORMANCE CHECKLlSI STANDARDS UN SaI SAI N!B RECORD START TIME 1.

Proceed to 2PL10J, Fire Locate the Fire Hazards Panel.

_a_ _a

_a Hazards Panel.

(426' El Curved Wall Area S-24 on Unit 2)

• 2.

Verify Power is supplied Verify / place:

_a_ _a

_a to the RCS WR Hot and Cold Leg Temperature

. Power Switch 2HS-LV001 to indications.

1. 3 position (Division 22 power)

(CME: Power Switch 2HS-LV001 is in the #1 position when arriving at cabinet)

(CRE: Power Switch 2HS-LV001 is in the #1 position)

• 3.

Activate the Fire Place the Panel Switches to the

_a_ _a

,_o Hazards Panel.

FIRE position.

(CME: 2HS-RY033 is in 2HS-RYO33 - PZR PRESS.

FIRE position, 2HS-RY034 is in FIRE 2HS-RY034 - PZR LEVEL.

position, 2HS-MS193 is in FIRE 2HS-MS193 - SG 2A

position, PRESS.

2HS-MS194 is in FIRE 2HS-MS194 - SG 2B

position, PRESS.

2HS-FW309 is in FIRE 2HS-FW309 - SG 2A WR

position, LEVEL.

2HS-FW310 is in FIRE 2HS-FW310 - SG 2B WR position.)

LEVEL.

(CME' This completes this JPM.)

RECORD STOP TIME NRC-10 2

April 15,1998

t JPM Questions Question No: 1 Reference Use: VE6/NO Why are the control power fuses pulled when taking local emergency control of safe shutdown equipment?

Expected Answer:

To disable all automatic trips and allow start of vital equipment.

Actual Answer:

l l Candidate's response matched expected answer.

Sat _ Unsat._.

K/A: APE 068AK206 2.4*/2.7 LP Objective: ELEC-5; K.O. 3 Reference (s):

2BwOA Elec-5, page 4 NRC-10 3

April 15,1998

Que: tion N:: _2_

Referenco Use: VEGINO During evacuation of the control room, letdown flowrate is established at 45 gpm as a preparation for Remote Shutdown Panel operation.

What is the basis for establishing a minimum letdown flowrate?

Expected Answer:

This minimizes the possibility of letdown isolation. (Letdown operations from the remote shutdown panel are h:mpered due to the lack of control for the letdown line pressure control valve 1CV131)

Actual Answer:

l l Candidate's response matched expected answer.

Sat __ Unsat ___.

K/A: APE 068AK310 3.9/4.2 LP Objective: PRI-5; K.O. 3 R;ference(e):

28wOA Pri-5, step Sb, page 5 of 77 f

NRC-10 4

April 15,1998

_ _ _ _ _ - _ _ _ _ _.