ML20248L662

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Forwards Facility Submitted Outline & Initial Exam Submittal & as Given Operating Exam for Test Administered on 971215-18 at Facility
ML20248L662
Person / Time
Site: Beaver Valley FirstEnergy icon.png
Issue date: 03/05/1998
From: Curley V
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9803230495
Download: ML20248L662 (577)


Text

1 March 5, 1998 i

NOTE io. NRC Document Control Desk Mail Stop 0-5-0-24 FROM: bor'l on fe n . Li nsing Assistant Opera';ing Licensipranch R

SUBJECT:

OPERATORLICENSINGEXAMINATIONADMINJSTEREDON

~Decenhe e is-ir m1. AT bee bik v C .

DOCKET #50-JJ# #

D On beerndee /f-///fr1 Operator Licensing Examinations were administered at the referenced' facility. Attached, you rdll find the following information for processing through NUDOCS and distribution to the NRC staff, including the NRC POR:

" Item #1 - .a) Facility submitted outline and initial exam submittal.

designated for distribution under RIDS Code A070, b). ~ ' As given operating l examination. designated:for

~

~

distribution under RIDS Code A070.

Item #2 - Examination Report with the as given written examination attached. designated for distribution under RIDS Code IE42.

9 9

e 8

9803230495 980305 PDR A00CK 05000334

)gansg k!!!k li.i . . . .

l RCS cooldown rate and total Dow while on RiiR is controlled by...

A. manually adjusting RiiR How through the heat exchanger and automatically controlling CCR How through the heat exchanger.

B. automatically controlling RiiR How through the heat exchanger and manually adjusting CCR How through the heat exchanger.

C. automatically controlling RiiR Cow through the heat exchanger and manually adjusting total RiiR Cow through the system.

D. manually adjusting RIiR flow through the heat exchanger and automatically controlling total RiiR How through the system.

ANSWER: D K/A:005K4.10 Importance: 3.1/3.1 Cognitive Level: Knowledge Ref.: lOM-10.4. A Iss 4 Rev.10 LP#:1LP-SOS-10.1 0BJ:5 History Source: New JTA: 0050080101 1

,1 D pD 1

BVPS-1 f-NRC Exam: ILOT3, Rev 0 An operating manual precaution in OM 24 states that two (2) Condensate pumps must be running before starting the second feed pump. The reason for this is to...

A. ensure adequate flow capability to prevent a low suction pressua feed pump trip.

B. ensure adequate flow capability to prevent robbing the steam generators when the feed pump l

1 recirculation valves open. l C. ensure adequate flow capability to prevent run-out on the heater drains pumps.

D. ensure adequate flow to prevent water hammer in the first point heaters.

ANSWER: A K/A: 056K l .03 Importance: 2.6/2.6 Cognitive Level: Comprehension Ref.: lOM-24.2.A P&L C.1 iss 4 Rev 3  !

LP#:1 LP-SOS-24.1 OBJ: 7 History Source: New JTA: 0590030101 t

2 l

e ,

i i

BVPS-1 l NRC Exam: ILOT3, Rev 0 l l l Given the following:

. Reactor trip and Si due to a Small Break LOCA. {

. All ESF equipment operated as designed. j I

. Various PAB and Safeguards Area Radiation Monitors are in alarm. '

The procedure that should be entered to combat this accident is:

A. ECA-1.1, " Loss of Emergency Coolant Recirculation."

B. FR-Z.2, " Response to Containment Flooding."

C. ECA-1.2, "LOCA Outside Containment."

D. FR-Z.1," Response to High Containment Pressure."

ANSWER: C K/A: E04-EAl.1 Importance: 4.0/4.0 Cognitive Level: Analysis Ref.: lOM-53A.I.E-11ss IB Rev 4 step 19 LP#:1 LP-SOS-53.3 OBJ: 2,6 History Source: New JTA: 3010020601 3

BVPS-1 NRC Exam: ILOT3, Rev 0 1

Which of the following events would result in a containment area radiation monitor

[RM-lRM-215A(B)] alarm?

A. RCP #1 Seal Failure.

B. PZR Safety Valve Seat Leakage.

C. Steam Generator Tube Rupture.

l D. RCS Leak at the incore Seal Table.

l l

ANSWER: D K/A: 061 AA1.01 Importance: 3.6/3.6 Cognitive Level: Analysis Ref.: lOM-6.4.AM, initial Conditions Iss 4 Rev i LP#: 1 LP-SQS-6.5 OBJ: 7 History Source: NRC Bank JTA: 0720030101 l

4 1

J

BVPS-1 NRC Exam: ILOT3, Rev 0 Givea the following plant conditions:

Unit 1 is in Mode 2.

Reactor power is at 10" amps in the J.R. (P-6 activated). .

Preparing to block the source range detectors per the start-up procedure.

The detector for N31 source range fails low.

Which of the following actions should be taken?

A. Enter E-0, " Reactor Trip or Safety injection,"in response to the automatic reactor trip.

B. Hold power at 10 amps, until repairs are made.

C. Insert control rods until power is less than P-6.

D. Place the N31 level trip switch in the bypass position, and continue with the Reactor start-up.

i ANSWER: D K/A: 032AK2.01 Importance: 2.7/3.1 Cognitive Level: Analysis Ref.: lOM-53C.4.1.2.1 A lss 3 Rev 2 pg. 4 step 3 LP#: I LP-SOS-2.2 0 83:5 j

History i

Source: SOS Bank 00472-Modified JTA: 0150040101 l 5 1

l BVPS-1 NRC Exam: ILOT3, Rev 0 i

l Given the following conditions:

A Reactor trip and Safety Injection have occurred de to a SGTR in the 'C' SG.

E-3, " Steam Generator Tube Rupture,"is in effect with a cooldown started at maximum rate, e

The highest S/G Pressure is 900 psig.

RCS Pressure is 1000 psig and dropping.

High Head Safety injection flow is approximately 300 gpm.

Which of the following describes what should be done with the Reactor Coolant Pumps?

A. RCP's should be tripped because RCP trip criteria is currently met.

B. RCP's should be tripped because RCP trip criteria applies after an operator initiated RCS depressurization is commenced.

C. RCP's should not be tripped because RCP trip criteria does not apply once an operator initiated RCS cooldown is commenced.

D. RCP's should not be tripped because RCP trip criteria does not apply until the operator initiated cooldown is completed.

ANSWER: C K/A: 038EK3.08 Importance: 4.1/4.2 Cognitive Level: Comprehension / Analysis Ref.: lOM-53A.I.E-3 lss IB Rev5 Note prior to Step 15 LP#: 1LP-SOS-53.3 OBJ: 3 History Source: NRC Bank - Modified JTA: 3010040101 6

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 The following conditions exist:

  • The Turbine has failed to trip both automatically and manually.

Which of the following actions is/are required to be performed next?

A. Runback the Turbine using the " Turbine Manual" and " Fast Down" pushbuttons.

B. Close all Reheat Stop and Interceptor Valves.

C. Close the Main Steam Trip and Bypass Trip Valves.

D. Place the running EHC Pump in Pull-to-Lock.

ANSWER: C K/A: 007EA2.02 Importance: 4.3/4.6 Cognitive Level: Knowledge Ref.: lOM-54A.I.E-0 lss IB Rev 5 Step 3 RNO 4 I

LP#: l LP-SQS-53.3 OB): 1 History Source: NRC Bank ,

JTA: 3010010601 l l l

l 7

1 BVPS-1 NRC Exam: lLOT3, Rev 0 Given the following:

. Reactor Power is 90%.

. Tavg is stable at 574 F on all three loops.

  • PZR Level is 52% and stable.
  • RCS Pressure is stable at 2235 psig.

1

. Containment pressure and humidity are rising. j l

e Net Charging flow is 0 gpm. l l

. Steam flow on all three loops is 3.78E6 lbm/hr.

. On the "C" SG:

  • Pressure is stable.

. NR Level is dropping. )

)

. Feed flow is pegged high.

Which of the following events is in progress?

A. "C" S/G Main Feed Reg Valve is failed open.

B. "C" S/G controlling Feed Flow channel is failed high.

C. There is a feed line break inside containment. ,

D. There is a Small Break LOCA inside containment, l

1

I 1

ANSWER: C l Importance: 4.1/4.3 K/A: 054AK1.01 Cognitive Level: Analysis Ref.: lOM-12.4.AAE lss 4 Rev 1 pg.1 LP#: 1 LP-SOS-53.3 OBJ: 6 History: Similar question used in 2 LOT 2 NRC exam (0-2-97-60)

Source: NRC Bank

i. JTA: 3010020601 8

_ .____a

BVPS-1 NRC Exam: I LOT 3, Rev 0 l 1

1 Given the following conditions:

  • The reactor has been shutdown for 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. I
  • RCS temperature is 150 degrees F.
  • RCS pressure is Atmospheric. )
  • PZR level is 22%.

Assume RHR cooling is lost. Using the attached curves, which of the following describes the time available until core boiling occurs?

A. Less than 10 minutes.

B.11 to 20 minutes.

l C. 21 to 30 minutes.

D. 31 to 40 minutes.

1 I

l l

ANSWER: D (furnish AOP 1.10.1 attachments 1,2,3,4 with question)

K/A: 025 AK 1.01 Importance: 3.9/4.3 Cognitive Level: Comprehension / Application Ref.: lOM-53C.4.1.10.1 Iss 3A Rev 5 Attachment 1 LP#. ILP-SOS-10.1 OBJ: 9,10 I History Source: NRC Bank JTA: 0000180401 l

l l

_ _ _ _ _ _ _ _ _ _ ~

I BVPS-1 NRC Exam: ILOT3, Rev 0 The following conditions exist:

  • PZR Spray valves (PCV-1RC-455A & B) are closed.

PZR PORV [PCV-1RC-455C] is closed.  ;

  • PZR PORV [PCV-1 RC-456] is cycling.
  • RCS pressure is approximately 2000 psig.

Which of the following Pressurizer Pressure transmitter failures has occurred?

A. [PT-lRC-445] failed low.

B. [PT-1RC-445) failed high.

C. [PT-1RC-444] failed low.

D. [PT-1RC-444) failed high.

i ANSWER: B K/A: 027AA2.18 Importance: 3.4/3.5 l

Cognitive Level: Analysis I Ref.: lOM-6.4.lF lss 4 Rev 6 Attachment 2; lOM-6.1.D iss 4 Rev 1 pg. 7 LP#: ILP-SQS-6.4 OBJ: 15 History Source: NRC Bank JTA: 0000130401 10

BVPS-1 NRC Exam: ILOT3, Rev 0 Given the fol'owing:

Unit 1 is operating at 100% power with all systems in their normal system arrangement.

. Annunciator A9-98,"125VDC Bus 1 Voltage Low," alarms.

. Number 1 DC Bus voltage is 0 VDC.

. A reactor trip occurs.

The Main Feedwater pumps are secured per the Alarm Response Procedure.

Which of the following Auxiliary Feedwater pumps will start?

A. MDAFW pump 3A and the TDAFW pump.

B. MDAFW pump 3B and the TDAFW pump.

C. TDAFW pump only.

D. MDAFW pump 3B only. -

1 I

l l

l ANSWER: B '

K/A: 058 A A2.03 Importance: 3.5/3.9 Cognitive Level: Comprehension / Application l

Ref.: lOM-39.4.AAI Iss 3 Rev 2 LP#: 1 LP-SQS-39.1 OBJ: 4b 1

liistory Source: NRC Bank - Modified JTA: 0000370401 I1

(__- _ _ _ _ _ _ _ _ _ _ _ _ _

BVPS-1 NRC Exam: lLOT3, Rev 0 f The following plant conditions exist:

  • Unit 1 is operating at 100% power.

Pressurizer spray valve [PCV-1RC-455B] is stuck OPEN.

. All efforts to close the spray valve have failed.

. RCS pressure is dropping rapidly.

Which of the following actions should be taken?

A. Trip the 'A' Reactor Coolant Pumr, then trip the reactor.

B. Trip the 'C' Reactor Coolant Pum;, then trip the reactor.

C. Trip the reactor, then trip the 'A' Beactor Coolant Pump.

D. Trip the reactor, then trip the 'C' Reactor Coolant Pump.

1 ANSWER: D K/A: 027AK3.03 Importance: 3.7/4.1 l

Cognitive Level: Comprehension Ref.: lOM-53 A.l.E-0 iss IB Rev 5 Step 22c RNO LP#: 1LP-SQS-6.4 OBJ: 8 History Source: NRC Bank JTA: 3010010601 1

l l

12

BVPS-1 NRC Exam: lLOT3, Rev 0 Which of the following would indicate that th: PRT rupture disk had blown following a pressurizer PORV failing open

l l

1. Pressurizer level dropping. i
2. PORV tailpipe temperatures dropping.
3. PRT temperature dropping.

l 4. PRT pressure dropping. l

\

A.1,2, and 3.

l h

B.1,2, and 4. j

(

C.1,3, and 4.

)

(

D. 2,3, and 4.

i i

ANSWER: D K/A: 008 AA1.08 Importance: 3.8/3.8 Cognitive Level: Analysis Ref.: Steam Tables LP#: 1 LP-SOS-6.4 OBJ: 7 History l

Source: NRC Bank - Modified JTA: 0100040101 l

13 1

- _ _ _ _ _ _ _ _ _ _ _ _ _ ___ ____ - _ _ l

BVPS-1 NRC Exam: lLOT3, Rev 0 Given the following:

A Turbine generator trip has caused a Reactor trip.

The operators are in ES-0.1, " Reactor Trip Response," at step 4, " Check RCS

{

Temperature Stable at or Trending to 547F."

f RCS pressure is 1810 psig and slowly dropping.

Pressurizer level is 22% and stable.

. Core exit T/Cs are 575 F and slowly rising.

Containment pressure is 19 psia and slowly rising All S/G NR levels are 20% and slowly rising.

Which of the following actions should be taken? .

A. Dump steam to the condenser and proceed to step 5 of ES-0.1.

B. Initiate Si and go to E-0," Reactor Trip or Safety injection," step 1. I C. Transition to FR-H.1," Response to Loss of Secondary Heat Sink."

D. Transition to FR-Z.1," Response to High Containment Pressure." j

)

)

ANSWER: B K/A: 009EK3.28 Importance: 4.5/4.5 l

Cognitive Level: Knowledge Ref.: lOM-53A.I.ES-0.1 iss 1B Rev 4 Step 1 l

LP#: I LP-SOS-1.1 OBJ: 1 1 History Source: NRC Bank JTA: 3010010601 14

l BVPS-1 l

NRC Exam: ILOT3, Rev 0 Given the following:

. The unit is in Mode 1 at 50% power proceeding to full power following a refueling outage.

. All control systems are in automatic.

. All pressurizer heaters are turned on to allow for boron mixing as power is raised.

. A loss of Containment Instrument Air occurs.

Assuming no Operator actions are taken, which of the following will occur?

1. R.eactor will trip on high pressurizer level.
2. Letdown will isolate.
3. Pressurizer pressure will rise.
4. Pressurizer pressure will drop.

A. 1, 2, and 3.

B. 1, 2, and 4.

C. 1. 3, and 4.

D. 2,3, and 4.

ANSWER: A ,-

K/A: 065 A A2.08 Importance: 2.9/3.3 Cognitive Level: Analysis Ref. IOM-53C.4.1.34.21ss 3A Rev 3 LP#: I LP-SOS-53C.1 OBJ: 8 History Source: New I

JTA: 000KKK0401 l i

15

BVPS-1 NRC Exam: ILOT3, Rev 0 The plant is in Mode I with all systems in their normal system arrangement. Containment pressure transmitter [PT-LM-101C] failed low and actions were completed per IOM-1.4.lF.

" Instrument Failure." Subsequently, containment pressure transmitter [PT-LM-1018) fails high.

Which of the following will occur?

1. SIS
2. MSLI
3. CIA 4.CIB A. 1, 2, 3, and 4.

B. 1,2, and 3.

C. I and 3.

D. I and 2.

1 ANSWER: B K/A: 013K6.01 Importance: 2.7/3.1 _

l Cognitive Level: Comprehension I Ref.: lOM-1.4.lF lss 4 Rev 1 LP#: ILP-SOS-12.1 OBJ: 5 History Source: New JTA: 103AAA0101 16

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 f The plant is preparing for a start-up. The shutdown bank rods are fully withdrawn, and all control banks are fully inserted. In preparation for the start-up the Control Room operators are performing an Operations Surveillance Test (OST) on Source Range detector N31. Which of the .

following is correct regarding the performance of this test?

A. The shutdown banks must be inserted and the Reactor trip breakers opened. The OST will generate a Reactor Trip signal.

B. The shutdown banks must be inserted and the Reactor trip breakers opened. This will provide a lower baseline source range count to allow all setpoints to be tested.

C. The shutdown banks can be left withdrawn. No Reactor trip signal is generated during the performance of the OST. -

D. The shutdown banks can be left withdrawn. Placing the Level Trip switch to Bypass will prevent the OST from causing a Reactor trip.

ANSWER: D K/A: 015 A3.03 Importance: 3.9/3.9 Cognitive Level: Comprehension / Application Ref: LOST-2.3 iss2 Rev 6 LP#: 1 LP-SOS-2.2 OBJ: 11 History Source: New JTA: 0150090201 l

t 17

BVPS-1 l NRC Exam: ILOT3, Rev 0 l

f Given the following:

  • A spurious Reactor trip and Safety injection have occurred during a Reactor start-up.

. Tavg is stable at 547 F.

l

  • PZR pressure is stable at 2235 psig.

1

. All steam generator water levels and pressures remained stable at 33% and 1005 psig respectively.

Before resetting SI, which of the following pumps can provide feedwater to the S/Gs?

1. Main Feedwater Pumps
2. Auxiliary Feedwater Pumps
3. Dedicated AFW Pump A. I and 2.

B. 2.

C. 2 and 3.

D. 1, 2, and 3.

ANSWER: B K/A: 059A3.06 Importance: 3.2/3.3 Cognitive Level: Knowledge Ref.: lOM-24.1.0 iss 4 Rev 2: OM Fig. 24-3 LP#: ILP-SQS-24.1 OBJ: 4 History Source: New .,

l JTA: 3010010601 ,

l l  !

18

l l BVPS-1 l NRC Exam: 1 LOT 3, Rev 0 l

l l When determining subcooling requirements while progressing through the EOPs, the value for subcooling that is read on the inadequate Core Cooling Monitor (ICCM) is the difference between the saturation temperature for the...

A. pressurizer pressure and the highest loop hot leg temperature.

B. wide range RCS pressure and the highest loop hot leg temperature.

C. pressurizer pressure and the average of the five hottest core exit thermocouple.

D. wide range RCS pressure and the average of the five hottest core exit thermocouple.

1 ANSWER: D K/A: 017A4.02 Importance: 3.8/4.1 Cognitive Level: Knowledge  !

_Ref.: lOM-6.1.C iss 4 Rev 1 pg. 34 _

LP#: I LP-SOS-6.7 O BJ: 4.5 History Source: New JTA: 0170020101 19

BVPS-1 NRC Exam: lLOT3, Rev 0 The plant has cntered Mode 5 for a refueling outage. Containment vacuum has been broken.

Shortly after placing containment purge and exhaust into service, Containment Purge Exhaust monitor [RM-1 VS-104 A] fails high. This will result in...

1. Containment Purge and Exhaust Dampers closing.
2. Auxiliary Building Exhaust Fans tripping.
3. Main Fister Bank Inlet Dampers opening.
4. Containment Purge and Exhaust Fans tripping.

A.1,2, and 3 B. 1,2, and 4.

C. 1,3, and 4.

D. 2,3, and 4.

ANSWER: C i

K/A: 072K3.01 l Importance: 3.2/3.4 Cognitive Level: Knowledge Ref.: lOM43.5.B.2 iss. 4 Rev 2: 10M-43.4.AEG iss 3 Rev 3 LP#: 1 LP-SOS-43.1 OBJ: 6 History: Similar question used in 1 LOT 2 NRC exam (O 80)

Source: New JTA: 0720030101 20

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 I The plant has entered a mini-outage to repair condenser tube leaks. The reactor is stable in Mode 3. A decision is made to completely isolate the condenser circulatir.g water system and repair all four condenser sections simultaneously. This evolution should NOT be allowed to occur because this will result in a loss of...

A. condenser steam dumps and there will be no way to get the plant to Mode 5 if needed.

B. feedwater and require auxiliary feedwater to maintain steam generator levels which is a violation of technical specifications.

C. the ultimate heat sink requirement for technical specifications.

]

D. safety grade flowpath for the Reactor Plant river water system for Appendix R requirements.

{

ANSWER: D K/A: 075K1.08 Importance: 3.2/3.2 i

l Cognitive Level: Comprehension Ref.: lOM-31.4.C iss 4 Rev 2 LP#: 1 LP-SOS-31.1 OBJ: 4 g,or, Source: New JTA: 0750150101 i

t I

21 l

l t _ _ __ _ __ - _-____

BVPS-1 NRC Exam: ILOT3, Rev 0 To warn perscnnel in areas serviced by an automatic CO2 discharge, which of the following will occur before the actual discharge?

A. a wintergreen deodorizer is discharged prict to the CO2 discharge.

B. the station stand-by alarm is sounded prior to the CO2 discharge.

C. a pre-discharge horn will sound and a time delay will occur prior to the CO2 discharge.

D. a red light will flash in the area and a time delay will occur prior to the CO2 discharge.

ANSWER: C K/A: 086K4.04 Importance: 3.1/3.4 Cognitive Level: Knowledge Ref.: lOM-33.4.AAL, Iss3 Rev 0 .

l LP#: ILP-SOS-33.1 OBJ: 1 i )

History: Similar question used in 2LOTl NRC exam (0-2-97-94)

Source: New l

l JTA: 0860050101 l

l j

l 22

BVPS-1 NRC Exam: ILOT3, Rev 0 Which of the following actions are directed in AOP-1.6.5, " Shutdown LOCA"?

1. Manually Initiate Safety injection (both pushbuttons) to recover pressurizer level. -
2. Align HHSI pumps through the hot leg injection flowpath.
3. Manually depressurize and cooldown the RCS to place RHR into service.
4. Manually stan HHSI pumps to recover pressurizer level.

A. 1, 2, and 3.

B. 1, 2, and 4.

C. 1,3, and 4 I

D. 2,3, and 4. l o

I 4

l ANSWER: D l K/A: 2.4.9 Importance: 3.3/3.9 l Cognitive Level: Knowledge l

Ref.: lOM-53C.4.1.6.5 Iss 3A Rev 5 I LP#: 1LP-SOS-53C.1 OBJ: 5 History Source: New JTA: 0000560401 23

BVPS-1 NRC Exam: ILOT3, Rev 0 1

What is the expected procedure flow path for a small break LOCA that is too small for two l

) HHS1 pumps, but too large for one HHS1 pump, i.e., a " smart break"?

I

1. E-0, " Reactor Trip or Safety injection."
2. E-1, " Loss of Reactor or Secondary Coolant."
3. ES-1.1, "Si Termination."
4. ES-1.2, " Post LOCA Cooldown and Depressurization."

5.1OM-11.4.M, " Recovery from Safety Injection."

6. lOM-10.4.A," Residual Heat Removal System Startup."

A.1,2, then 5.

i B.1,2,3, then 4.

C.1, 2, 3, 2, then 4.

D.1,3, then 6.

{

ANSWER: B K/A: E03 EA2.1 Importance: 3.4/4.2 Cognitive Level: Comprehension Ref.: lOM-53A.I.E-1 iss 1B Rev 4 Steps 8 & 22: ES-1.1, step 15 LP#: 1 LP-SQS-53.3 OBJ: 3 Historv Source: LRT Bank Modified JTA: 3010020601 i

l 24

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 Which of the following actions does ECA-1.1," Loss of Emergency Coolant Recirculation" direct?

1. Provide guidance on aligning the HHSI pump suction directly to the containment sump.
2. Terminate cold leg recirculation and restore charging and letdown.
3. Cooldown and depressurize the RCS to allow RHR to be put into service.
4. Provide methods to make-up to the RWST.

I A. 1, 2, and 3. q l

B. 1, 2, and 4 t

C. 1,3, and 4.

D. 2,3, and 4.

1 ANSWER: D l

K/A: El1-EK2.1 Importance: 3.6/3.9 l ,

1 Cognitive Level: Knowledge l

I Ref.: lOM-53 A.ECA-1.11ss 1B Rev 4 LP#: 1 LP-SOS-53.3 OBJ:2 History Source: New JTA: 3010020601 25

BVPS-1 NRC Exam: ILOT3, Rev 0 Given the following:

. Unit I has experienced a Large Break LOCA.

  • Containment pressure is 20 psig and dropping.

The Crew has reached the step in the procedure where CIB is to be reset. Which of the following apply in this situation?

A. CIB cannot be reset until containment pressure is below the actuation setpoint.

B. CIB cannot be reset until containment pressure is subatmopheric. ,

i C. CIB can be reset, but will re-actuate as soon as the reset switches are released. j 1

D. CIB can be reset regardless of containment pressure, j i

l l

ANSWER: D (furnish UFSAR Logics, sheets 1 & 8)

K/A: 103 A4.04 Importance: 3.5/3.5 l l

Cognitive Level: Analysis / Application Ref.: UFSAR Logics Fig. 7.2-1 sheets 1 & 8 LP#: 1 LP-SOS-13.1 OBJ: 5 History Source: New JTA: 0130010101 l

26

BVPS-1 NRC Exam: ILOT3, Rev 0 Given the following conditions:

. The unit is at 100% power.

  • The Red Light associated with the lockoutjack on Vertical Board 'A'; for the 'A' accumulator isolation valve [MOV-lSI-865 A), is illuminated.

[MOV-1 SI-865 A] has...

A. drifted from it's fully opened position.

B. tripped on Thermal Overload, C. received a Safety injection Signal.

D. continuity through its control circuit (circuit grounded).

I ANSWER: D 1

K/A: 013-2.4.48 Importance: 3.5/3.8 Cognitive Level: Analysis l

l Ref.: lOM-54.3.L5 lss 4 Rev 16 L5-21 LP#. ILP-SOS-11.1 OBJ: 12 History Source: New JTA: 0060150101 27

BVPS-1 NRC Exam: ILOT3, Rev 0 Technical Specifications restrict the quantity of radioactive liquids in [lLW-TK-7B] to less than 10 curies (excluding tritium and dissolved or entrained Noble gases). The basis for this limit is to..

A. prevent over-exposure to personnel who must work near or pass by the tank (Transient Pathway Radiation Levels).

B. prevent exceeding 10CFR20 Appendix B limits at the nearest surface water supply in the event of an accidental release.

C. maintain activity Icw enough so that the tank may be discharged with minimum design dilution flow.

D. prevent exceeding 10CFR100 limits for child thyroid dose at the site boundary in the event of an accidental release.

\

ANSWER: B K/A: 059A K 1.02 Importance: 2.6/3.2 Cognitive Level: Knowledge Ref: TS 3.11.1.4 basis LP#: 1LP-SOS-17.1 OBJ: 5 History Source: NRC Bank Modified JTA: 1190150301 28

,' ?

BVPS-1 NRC Exam: ILOT3, Rev 0 Which of the following does the NSS sign for when discharging a Gaseous Waste Decay Tank?

1. Verification of the proper tank and approval for the discharge.
2. Only one batch discharge is being done at a time.
3. The appropriate Rad Monitor alarms have been adjusted.
4. The opposite units NSS has been informed of the discharge.

A. 1,2, and 3.

B. 1, 2, and 4.

C. 1,3, and 4.

D. 2, 3, and 4.

ANSWER: A K/A: 071-2.3.8 Importance: 2.3/3.2 Cognitive Level: Knowledge Ref.: lOM-19.4.E. Decay Tank Discharge LP#: 1 LP-SOS-19.1 OBJ: 9 History Source: New JTA: 3410120302 29

BVPS-1 NRC Exam: ILOT3, Rev 0 Which of the following must be met in order to terminate safety injection following a Small Break LOCA?

1. Adequate subcooling.

I

2. At least one reactor coolant pump in operation.
3. Adequate secondary heat sink.
4. RCS pressure stable or rising.
5. RCS hot leg temperatures stable or rising.
6. Adequate pressurizer level.
7. Charging and letdown available.

A.1, 2, 4, and 6.

B. 2,3, 5, and 7.

C.1, 3, 5, and 7.

D.1,3,4, and 6.

ANSWER: D K/A: E02-EA2.1 Importance: 3.3/4.2 Cognitive Level: Comprehension Ref.: lOM-53A.I.E-1 iss 1B Rev 4 LP#: ILP-SOS-53.2 OBJ: 2 History Source: New JTA: 3010020601 30

BVPS-1 NRC Exam: ILOT3, Rev 0 Given the following:

A reactor trip from 100% power has occurred.

The 'B' RTB has failed to open.

The condenser steam dump (1) controller will maintain Tavg at (2) .

(1) (2)

A. Load Rejection 549 F 1

B. Load Rejection 552 F C. Reactor Trip 547 F D. Reactor Trip 549 F ANSWER: A K/A: 039A2.04 Importance: 3.4/3.7 Cognitive Level: Analysis Ref.: lOM-21.1.D iss 4 Rev 1 pg. 6 LP#: 1LP-SOS-21.1 OBJ: 5 History: Original version used 1 LOT 3 Exam 9 (5/1/97)

Source: SOS Bank modified JTA: 0410030101 l

31

DVPS-1 NRC Exam: 1 LOT 3, Rev 0 f The plant is in Mode 1 with Reactor Plant River Water Pumps [1WR-P-1 A] and [ LWR-P-1B] in service. In order to replace [1WR-P-l A] with [ LWR-P-lC], which sequence of operations must be performed?

1. Rack on [ LWR-P-lC].
2. Rack off[ LWR-P-1 A].

l l 3. Start [l WR-P-lC]. I 1

4. Stop [1 WR-P-1 A].

A. 2, 3, 4,1.

B. 2,4,3,1.

l C. 4,1, 3, 2.

l D. 4, 2,1, 3.

I ANSWER: D l

K/A: 2.1.32 Importance: 3.4/3.8 l

l Cognitive Level: Comprehension Ref.: OM30 Precautions and limitations #3 & #4 i

LP#: 1 LP-SQS-30.2 OBJ: 4 History Source: New JTA: 0760050101 32

BVPS-1 NRC Exam: l LOT 3, Rev 0 Which of the following conditions will prevent the Emergency Diesel Generator output breaker from closing to re-energize the I AE bus following a transient?

A. l AE Emergency Bus feeder breaker, [ACB-1 A10] trips on overcurrent.

B. l AE Emergency Bus reverse phase PT has a blown fuse.

C. 1 A Normal 4KV Bus feeder breaker, [ACB-41C] trips on overcurrent. I l

D. I A Normal 4KV Bus feeder breaker, [ACB-41C) trips due to the Main Generator tripping on J overcurrent.

ANSWER: A K/A: 062K4.01 Importance: 2.6/3.2 Cognitive Level: Knowledge Ref.: lOM-36.4. ACZ LP#: l LP-SOS-36.2 OBJ: 5 History Source: New JTA: 0640040101 l

33

BVPS-1 NRC Exam: ILOT3, Rev 0 in ECA-0.0," Loss of Emergency AC Power," prior to restoring power to an emergency bus, all ,

major loads are placed into Pull-to-Lock with the exception of the Reactor Plant River Water I

Pump. This pump is left in automatic to...

A. provide a load for the diesel generator to prevent it from tripping on overspeed when started in the emergency mode. f B. provide cooling for the diesel generator to prevent overheating and possible failure of the diesel.

C. provide cooling for the charging pumps oil coolers so that make-up to the RCS can begin immediately to replace the RCS lost through the RCP seals.

D. provide cooling to the Control Room Emergency back-up cooling cools to maintain Control Room habitability.

I ANSWER: B K/A: 2.4.18 Importance: 2.7/3.6  ;

Cognitive Level: Knowledge Ref.: 10M-53B.4.ECA-0.0 lss 1B Rev 4: Basis for step 14 LP#: l LP-SOS-53.3 OBJ: 3 History Source: New JTA: 3010060601 34 l

L__ __ _ _

1 BVPS-1 NRC Exam: 1 LOT 3, Rev 0 i

The unit is at 100% power when the following radiation monitors go into alarm:

[RM-1MS-102A] N-16 SG Leak Monitor.

[RM-1BD-100] SG Blowdown Effluent Monitor.

  • [RM-ISV-100] Condenser Air Ejector Vent.

Within 15 minutes, analysis reveals a 0.12 gpm tube leak on the 'A' SG. Which of the following actions should be taken?

A. Enter TS 3.4.6.2 action for RCS leakage and restore the leak to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> I

or be in Hot Standby within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

B. Enter AOP-1.6.4,"SG Tube Leakage," and commence an emergency shutdown to be in Mode 3 as soon as possible.

C. Enter AOP-1.6.4,"SG Tube Leakage," and place the plant in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

D. Manually trip the reactor and initiate Safety injection and enter E-0," Reactor Trip or Safety injection."

ANSWER: B (furnish table out of AOP 1.6.4 step 1)

K/A: 037-2.4.4 Importance: 4.0/4.3 Cognitive Level: Comprehension / Application Ref.: AOP-1.6.4 LP#: 1 LP-SOS-53C.1 OBJ: 2 History j Source: New JTA: 0000110401 35 I I

BVPS-1 NRC Exam: ILOT3, Rev 0 With the unit at 100% power, a HlGH-HIGH alarm is received on Condenser Air Ejector Vent radiation monitor [RM-lSV-100]. This HIGH-HIGH alarm will result in the condenser air ejector exhaust...

A. being isolated.

B. diverting through the Main Filter Banks C. diverting to containment.

D. diverting to the Gaseous Waste Surge Tank.

ANSWER: C K/A: 055 A3.03 Importance: 2.5/2.7 Cognitive Level: Knowledge Ref.: lOM-43.4.ADZ lss 3 Rev 3 LP#: I LP-SOS-43.1 OBJ: 6 History: Original version used 1/3/97 0. #22 >

Source: Modified SOS Bank O. #0947 JTA: 0730030101 i

l 36 1

_ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . . _ ]

BVPS-1 NRC Exam: lLOT3, Rev 0 There has been a reactor trip caused by a loss of off-site power. E-0," Reactor Trip or Safety injection" has been entered. A transition to ECA-0.0," Loss of Emergency 4KV AC Power" was done at step 6, because both emergency 4KV busses were de-energized. The crew has reached the step where they are to determine which bus should be selected as the cross-tie bus when the

  1. 2 Diesel Generator is started locally and the IDF bus is automatically loaded. Which of the following is the appropriate response?

A. Continue on in ECA-0.0 until both emergency busses are restored.

B. Skip ahead to the step which determines the appropriate recovery procedure.

C. Transition to E-0," Reactor Trip or Safety injection."

D. Concurrently perform E-0 and ECA-0.0 until the cross-tie is completed for Bus l AE.

ANSWER: B

K/A
055EK3.02 Importance: 4.3/4.6 Cognitive Level: Analysis l

Ref. lOM-53A.I.ECA-0.0 iss 1B Rev 4 step 11 LP#: 1 LP-SQS-53.3 OBJ: 3 History Source: NRC Bank JTA: 3010060601 37

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 While responding to inadequate core cooling, the operators are unable to establish high head safety injection. Core exit T/C's are 1450 F and RCS pressure is 165 psig. Which of the following states the reason for starting the RCPs under these conditions?

A. Flush nitrogen from the SG tubes so natural circulation flow can be established in subsequent steps.

B. Provide 2-phase forced flow for temporary core cooling to reduce Core exit T/C temperatures.

C. Assure the core remains shutdown by adding borated water from the loops to the voided core.

D. Provide forced RCS flow for heat transfer during SG depressurization, ANSWER: B K/A: 074EK3.07 Importance: 4.0/4.4 Cognitive Level: Knowledge Ref.: lOM-53B.4.FR-C.l. iss.1B Rev 4 step 23 (pg. 48)

LP#: 1 LP-SOS-53.3 OBJ: 3 History Source: NRC Bank l

JTA: 3110030601 1

38 i

BVPS-1 NRC Exam: ILOT3, Rev 0 Which of the following is the termination criteria for an Emergency Boration initiated in accordance with FR-S.1," Response to Nuclear Power Generation /ATWS"?

A. RCS Boron Concentration satisfies that required for adequate shutdown margin.

B. A green path on the Saberiticality status tree is obtained.

C. All control rods have been inserted to the bottom of the core.

D. Boration flow has been maintained at a maximum flowrate for 30 minutes.

ANSWER: A K/A: 024 A A2.05 Importance: 3.3/3.9 Cognitive Level: Knowledge i

Ref.: FR-S.1 iss. IB. Rev. 4 pg.13 caution LP#: ILP-SOS-53.3 OBJ: 4 History Source: NRC Bank JTA: 3110010601

39 l

BVPS-1 NRC Exam: ILOT3, Rev 0 Which of the following is an indication that natural circulation exists in the RCS?"

RCS RCS indicated S/G RCS Cold CNMT Pressure Subcooling Pressure Leg Temp. Pressure on ICCM A.- 600 psig 40 F 400 psig 400 F 10 psia B. I100 psig 30 F 500 psig 470*F 7 psig 1 C. 1500 psig 35 F 600 psig 490 F 10 psia D. 2000 psig 40 F 700 psig 550 F 7 psig i

i 1

l 1

ANSWER: C (Provide Attachments 2-G & 6-A as reference)

K/A: E09A Al.3 Importance: 3.5/3.8 Cognitive Level: Analysis Ref.: lOM-53A.I.2-G & 6-A Iss. IB Rev. 2 LP#: I LP-SQS-53.2 OBJ: 12 j History Source: NRC Bank Modified JTA: 3010010601 I

40

BVPS-1 NRC Exam: lLOT3, Rev 0 The RCP Thermal Barrier Component Cooling Outlet Trip Valve, [TV-lCC-107B],

fails (I) on the loss ofinstrument air and will auto close on high CCR l

(2)  ? . j (1) (2)

A. closed flow B. closed pressure C. open flow D. open pressure ANSWER: A K/A: 015 AK2.08 Importance: 2.6/2.6 Cognitive Level: Knowledge Ref. lOM-53C.4.1.34.2: lOM-6.4.AAH !ss4 Rev 0 LP#: I LP-SOS-6.3 OBJ: 12 History Source: NRC Bank Modified JTA: 0030020101 4I

i i

BVPS-1 NRC Exam: ILOT3, Rev 0 The location of the 18 inch escape manway associated the the CNMT Personnel Airlock Doors is..

A. on the inner and outer doors with no associated interlocks.

B. only on the inner door with no associated interlocks.

C. on the inner and outer doors, interic,cked to prevent any inner and cuter door from being opened simultaneously.

D. on the inner door, interlocked to prevent any inner door and the outer door from being opened simultaneously.

ANSWER: A K/A: 069AK2.03 Importance: 2.8/2.9 Cognitive Level: Knowledge Ref.: lOM-47.4.C lss 4 Rev i pg. Cl L P#: ILP-SOS-47.1 OBJ: 3c History: Similar question used in ILOT2 NRC exam (O 88)

Source: NRC Bank Modified JTA: 0210010101 (now N.O. task l

l l

I 1

42

BVPS-l NRC Exam: ILOT3, Rev 0 Given the following conditions:

  • Reactor power level is 97% and dropping.

. Tavg is 574 F and dropping.

  • Pressurizer pressure is 2225 psig and dropping.
  • Pressurizer level is 53% and dropping.

. MW Recorder is 820 MW and stable.

Which of the following actions should be taken?

A. Check the in-Hold-Out lever is in the Hold position.

B. Enter AOP-1.51.1," Emergency Shutdown."

C. Place the control rod selector switch in Manual.

D. Reduce turbine load to stabilize primary plant parameters.

ANSWER: C K/A: 001 AA1.01 Importance: 3.5/3.2 Cognitive Level: Analysis / Application Ref.: lOM-53C.4.1.1.3 Iss 3A Rev 2 LP#: 1 LP-SOS-53C. l OBJ: 1 History Source: NRC Bank Modified JTA: 0000050401 l

43 l

L-_.------ )

BVPS-1 NRC Exam: ILOT3, Rev 0 The unit is at 100% power with all systems in their NSA configurations for the current power level. ,

Which of the following will occur if Vital Bus IV is de-energized?

A. An OTAT turbine runback will occur.

B. All condenser steam dumps will open.

C. 'C' SG feed reg valve [FCV-lFW-498] shifts to manual.

D. The controlling PZR level channel fails low.

ANSWER: C ,

K/A: 057AA2.20 Importance: 3.6/3.9 Cognitive Level: Comprehension Ref.: lOM-38.4.AAG iss 4 Rev 1 pg. 2 LP#: l LP-SQS-38.1 OBJ: 6 LOT-V-7 2-4 History Source: NRC Bank Modified JTA: 0000350401 i

44 1 I

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 l

The following events have occurred:

  • The unit is at 100% power with all systems in their NSA configurations for the current power level when a Reactor trip and Safety injection occur. .
  • 1 A SG pressure is dropping rapidly.

. 1 A Steam line indicates 2.5E6 lbm/hr steam flow.

  • Containment pressure is 8.5 psig and rising.
  • All ESF actuations occur as designed.

Assuming no operator actions taken, a possible consequence of this accident is...

A. an acidic containment spray solution since the steam will dilute the spray ring water.

B. insufficient containment sump levels to support recirculation spray pump operation.

C. a postulated flaw in the reactor vessel wall propagating if RCS pressure rises.

D. a loss of the steam driven AFW pump due to all three steam lines depressurizing.

l ANSWER: C t K/A: 040EK1.01 Importance: 4.1/4.4 Cognitive Level: Comprehension Ref. lOM-53B.4.F.0 iss 1B Rev 1 pgs. 6 & 7 LP#: l LP-SOS-53.2 OBJ: 8 i

History: Similar question used in 2LOTl NRC exam (0-2-97-58)

Source: NRC Bank Modified l

JTA: 3010030601 45

BVPS-1 NRC Exam: ILOT3, Rev 0 Given the following:

. The unit is at 100% power with all systems in their NSA configurations for the current power level when a Reactor Trip and Si occur.

The operators transition to FR-H.1, " Response to Loss of Secondary Heat Sink due to low S/G NR levels and low AFW flow.

. RCS pressure is less than S/G pressure and FR-H.1 directs a transition to E-1,

" Loss of Reactor or Secondary Coolant.

Based on this information, select the statement that correctly summarizes plant conditions:

A. Large Break LOCA in progress; secondary heat sink required.

B. Large Break LOCA in progress; secondary heat sink not required.

C. Small Break LOCA in progress; secondary heat sink required.

D. Small Break LOCA in progress; secondary heat sink not required.

ANSWER: B K/A: 01 LEA 2.01 Importance: 4.2/4.7 Cognitive Level: Analysis Ref. lOM-53B.4-FR-H.1 lss 1B Rev 3: Basis Step 1 pg. 49 LP#: ILP-SQS-53.3 OBJ: 6 History Source: NRC Bank JTA: 3010020601 46 i

BVPS-1 NRC Exam: ILOT3, Rev 0 FR-S.1, " Response to Nuclear Power Generation /ATWS", requires that pressure be verified to be less than 2335 psig and if not to reduce pressure to less than 2135 psig. The basis for this action is to reduce RCS pressure to...

A. maximize boration Dow.

B. limit cycling of the PZR PORVs.

C. avoid opening of the PZR safety valves.

D. maintain adequate RCP seal injection flow.

ANSWER: A K/A: 029EK3.12 Importance: 4.4/4.7 Cognitive Level: Knowledge Ref. lOM-53B.4.FR-S.i Iss 1B Rev 4 Basis for step 8. pg. 67 LP#: 1 LP-SOS-53.3 OBJ: 2 History Source: NRC Bank JTA: 3110010601 I

l 47 l

l BVPS-1 NRC Exam: ILOT3, Rev 0 i

l Given the following conditions:

i e The 'A' train of RHR is in service.

e l All systems are in their NSA con 6gurations for the current mode of operation.

e

(

RCS temperature is 180 F.

. RCS Pressure is 200 psig.

Which of the following would indicate a tube leak in the "A" RHR heat exchanger? )

A. CCR suige tank level rising.

I B. VCT level rising.

C. RHR return How to the RCS dropping.

D. RCS Boron concentration dropping.

1 ANSWER: A j K/A: 026AA2.01 Importance: 2.9/3.5 Cognitive Level: Analysis Ref. lOM-15.4.AAC lss 4 Rev 3 pg. 2a LP#: I LP-SOS-10.1 OBJ: la History Source: NRC Bank JTA: 0080120101 I

i l

48

BVPS-1 NRC Exam: ILOT3, Rev 0 Which of the following is indicative of, or the result of, a dropped rod with an initial power level of 100%?

1. Rod insertion limit drops.
2. "NIS Power Range Comparator Deviation" alarm.
3. Tavg drops rapidly.
4. Axial Dux difference becomes more negative.

A.1,2, and 3.

B.1,2, and 4.

C.1,3, and 4.

D. 2,3, and 4

. I I

ANSWER: A K/A: 003 AK1.07 Importance: 3.1/3.9 Cognitive Level: Comprehension Ref. lOM-53C.4.1.1.5 iss 3 A Rev 6 LP#: I LP-SQS-53C.1 OBJ: 2 History Source: NRC Bank Modi 6ed ,

JTA: 0000070401 l

49 l

\ _-__--_---_--_____-L

BVPS-1 NRC Exam: ILOT3, Rev 0 Which of the following is the reason that no action is taken in ES-0.1," Reactor Trip Response,"

for a single rod failing to insert?

A. FR-S.1, " Response to Nuclear Power Generation /ATWS" would have already initiated emergency boration flow for a single stuck rod.

B. The core is designed for adequate shutdown margin with a single rod stuck out of the core.

C. The loss of shutdewn margin is not a concern for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following a reactor trip due to Xenon peaking.

D. The core is being adequately borated by safety injection flow from the RWST.

ANSWER: B K/A: 005 AK3.06 Importance: 3.9/4.2

_ Cognitive Level: Knowledge Ref. lOM-538.4.ES-0.11ss IB Rev 4 LP#: l LP-SOS-53.3 OBJ: 3 History lource: NRC Bank Modified JTA: 3010010601 50

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 f

Given the following conditions-  !

e The unit was at 100% power with all systems in their NSA configurations for the current power level. j i

e A main steam line break has occurred inside containment.

. The crew is in FR-P.1, " Response to Imminent Pressurized Thermal Shock," which .

i directs a " soak of the RCS."

Which of the following evolutions can be performed during this soak? i l

A. Warm up the RHR system and commence a cooldown of the RCS.

B. Raise the faulted SG water level to 50% and secure the TDAFW pump.

1 C. Place PZR auxiliary spray in service.

D. Energize the PZR heaters to raise the saturation temperature of the PZR.

l l

l 1

1 I

ANSWER: C l K/A: E08-EK 1.3 Importance: 3.5/4.0 Cognitive Level: Analysis Ref.: lOM-53A.I.FR-P.1 iss 1B Rev 4 pg. 23 LP#: l LP-SOS-53.3 OBJ: 6 j

l History .

l Source: NRC Bank l

JTA: 3110140601 I 51

l BVPS-1 NRC Exam: 1 LOT 3, Rev 0 Given the following conditions:

. The unit is at 92% power with all systems in their NSA configurations for the current power level.

. The reactor did not trip, and the crew is responding with FR-S.1, " Response to Nuclear Power Generation /ATWS."

+ After completing the immediate manual actions, the reactor trip breakers are opened locally and the reactor is shutdown.

  • No other malfunctions or actuations have occurred.

Based on the above information, the crew should..

A. perform the Hrst 15 steps of E-0 while continuing in FR-S.I.

B. transition to E-0, perform the Hrst 15 steps, and then return to FR-S.I.

C. return to procedure and step in effect, i.e., E-0.

D. continue with procedure and step in effect.

I ANSWER: D K/A: 029-2.4.16 Importance: 3.0/4.0 Cognitive Level: Analysis Ref.: 1/20M-538.21ss 1B Rev 3 pg.10: Rules of usage LP#: I LP-LRT-53.1 OBJ: 1 History Source: NRC Bank Modified JTA: 3110010601 l

l 52

BVPS-1 NRC Exam: ILOT3, Rev 0 The following conditions exist:

  • Unit 1 is in Hot Standby following an unscheduled maintenance outage.
  • The Plant Operator is performing valve stroke OST 1.47.3B. -
  • [TV-ISS-105A2], RCL Hot Leg Samples Outside Cnmt Isol valve's closing time is found to be 3.2 seconds.

The acceptable range listed in the OST is 5; 2.0 seconds, the ASME limiting stroke time is 2.0 seconds, and the Technical Specification limiting time is 21.0 seconds.

Based on this information, the OST should be marked:

A. UNSAT, and penetration declared inoperable.

B. UNSAT, and the valve declared inoperable. i C. SAT, because the average stroke time was less than Technical Specification limit, but I l

frequency of testing must be doubled.

D. SAT, because the second stroke time was within 25% of the ASME limiting stroke time i which is acceptable for valves with stroke times less than 1 minute.

ANSWER: B (furnish applicable pages from OST 1.47.3B)

K/A: 069-2.1.33 Importance: 3.4/4.0 i

Cognitive Level: Analysis / Application l

Ref.: LOST-47.3B lss 4 Rev 16 pg. 4 Note l

LP#: 1LP-SQS-ES OBJ: 8 History Source: NRC Bank Modified JTA: 103AAA0201 53

BVPS-1 NRC Exam: ILOT3, Rev 0 The limit for RCS activity ensures that the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose et the site boundary will not exceed a small fraction of the Part 100 limits in the event that a occurs.

A. Steam line rupture with a 1 GPD tube leak.

B. Steam generator tube rupture.

C. Rod Ejection accident.

D. Locked RCP rotor accident.

ANSWER: B K/A: 076-2.2.25 Importance: 2.5/3.7 Cognitive Level: Knowledge Ref. TS 3.4.8 Basis pg. 3/4 4-4 LP#: 1 LP-SQS-6.1 OBJ: 8 i LP-SOS-TS 4 History Source: NRC Bank JTA: 1190150301 i

54

BVPS-1 NRC Exam: ILOT3, Rev 0 Given the following:

. A Steam Generator Tube Rupture has occurred in the IB S/G.

. The Crew is in E-3, " Steam Generator Tube Rupture," preparing to cooldown the RCS. 4 l

. 1B Narrow range level at 74% and rising.

. PZR pressure is 1900 psig.

. Tavg is 547 F.

. Main Condenser Vacuum is 13" Hg Absolute and stable.

. 1B and IC Cire Water Pumps are running.

)

Which of the following actions is/are necessary to commence cooldown in accordance with E-3?

A. Take the Steam dumps to Steam Pressure mode and manually open the dumps to commence the cooldown. 4 B. Take the Steam dumps to Steam Pressure mode, take both Steam Dump Control Selector Switches momentarily to the Defeat Tavg Interlock position, and then manually open the dumps to commence the cooldown.

C. Commence the cooldown using Steam Generator Atmospheric Dumps (PCV-lMS-101 A, B, & C].

D. Commence the cooldown using Steam Generator Atmospheric Dumps

[PCV-lMS-101 A & C].

ANSWER: D K/A: 051 AK3.01 l Importance: 2.8/3.1 Cognitive Level: Analysis Ref.: lOM-21.2.B iss 4 Rev i setpoints: 10M-53A.l.E-3 Iss 1B Rev 5 LP#: ILP-SOS-21.1 OBJ: 4k History: Similar question used in 2LOTl NRC exam (0-2-97-59)

Source: NRC Bank JTA: 3010040601 l 55 l

BVPS-1 NRC Exam: ILOT3, Rev 0 BVPS-: Steam Generator Atmospheric Steam Dump valves (PVC-lMS-101 A,B,C)

Auto / Manual stations are normally set at 1035 psig. Assuming a malfunction of the Auto / Manual station, at what steam pressure will the Atmospheric Steam Dumps open with no operator action?

A.1050 psig.

B. 1060 psig.

C. 1070 psig.

D. 1080 psig.

ANSWER: B K/A: El3-EK2.1 Importance: 3.0/3.1 Cognitive Level: Knowledge Ref.: IOM-21.1.D LP #: I LP-SOS-21.1 Obi.: 3 Ilistory: New ,

Source: LOT Bank JTA: 0390090101 1

1 56

)

_ -_- )

Given the following conditions:

  • Reactor tripped due to a loss of off-site power.
  • RCS presrure is 700 psig.

l

. Tcold is 370 F.

  • Core exit T/Cs are 506 F.

. Pressurizer level is 68% and rising.

  • Operators are performing ES-0.2, " Natural Circulation Cooldown."

Which of the following describes the cause of the abnormally high pressurizer level?

A. Pressurizer level instruments are inaccurate due to the loss of containment cooling.

B. Letdown has not been placed into service due to the loss of offsite power.

C. RCS pressure has reached the injection point for the accumulators.

D. RCS temperature and pressure are at the point where voiding is occuring in the reactor vessel head.

ANSWER: D K/A: 056AK 1.04 Importance: 3.1/3.2 Cognitive Level: Comprehension Ref.: lOM-53A.I.ES-0.2 Iss IB Rev 4 step 20 LP#: 1 LP-SOS-53.3 OBJ: 3,4 History Source: NRC Bank l JTA: 3110130601 i i

l l

57

_ - _ _ _ _ _ _ _ _ i

The following conditions exist:

The unit is at 92% power with all systems in their NSA configurations for the current power level.

l l .

Pressurizer level control channel selector is in the 461/460 position.

Pressurizer level channels indicate as follows:

Channel 459 is 54%.

Channel 460 is 56%.

Channel 461 is 0%.

Channel 462 is 40%.

Which of the following describes the plant response with no operator intervention?

A. Backup heaters energize.

B. Charging Dow rises to maximum.

C. Reactor trips on High PZR level.

D. Reactar trips on High PZR pressure.

ANSWER: C K/A: 028AA2.02 Importance: 3.4/3.8 Cognitive Level: Analysis Ref. lOM-6.4.lF lss 4 Rev 6 pg. 9 LP#: 1 LP-SOS-6.4 l OBJ:12 History Source: NRC Bank 1 JTA: 0110030101 58

l BVPS-1 NRC Exam: lLOT3, Rev 0 i

l Rods are being withdrawn in manual during a reactor stan-up, with all systems operable. For the Control Banks, which of the following describes the status of the Rod Bottom Lights at the moment A4-126," ROD BOTTOM ROD DROP" annunciator clears?

A. Hanks A, B, C, & D - OFF.

B. Banks A, B, C, & D - ON.

C. Banks A, B, & C - OFF; Bank D - ON.

D. Bank A - OFF; Banks B, C, & D - ON.

ANSWER: D

}UA: 014K4.03 Importance: 3.2/3.4 Cognitive Level: Comprehension Ref.: 1LP-SOS-1.4 & 10M-1.2B Iss 4 Rev 4 LPil: I L P-SOS-1.4 OBJ: 2b.c History: Original version used 1 LOT 3 exam Source: SOS Bank Modified JTA: 0140030101 I

l l

! 59 l

BVPS-1 l NRC Exam: ILOT3, Rev 0 l Administrative controls or interlocks provided with the Charging Pumps are designed to accomplish which of the following:

1. If only two pumps are operable, ensure that they are not powered from the same bus.

l

2. Prevent operation of a charging pump when the primary plant is water solid.
3. Prevent cross-tie of emergency busses through the swing pump breakers.

4 Prevent RCS over pressurization in Modes 5 & 6 due to excessive flow.

A. 1,2, and 3.

B. 1, 2, and 4. ,

C. 1,3, and 4.

D. 2,3, and 4.

ANSWER: C K/A: 004K2.02 Importance: 3.3/3.5 Cognitive Level: Comprehension I Ref. IOM-7.2.A Iss 4 Rev 11 pg. 3 P&Ls # 9 & 10; TS 3.5.3 basis LP#: 1 LP-SOS-7.1 OB3: 5 History Source: NRC Bank Modified JTA: 0040150101 l

l i

60

BVPS-1 NRC Exam: ILOT3, Rev 0 Which of the following variables affect the Containment Spray Systems capacity to depressurize l l

the containment in the event of a Design Basis Accident (DBA)?

1. Containment temperature.

l

2. Containment pressure.
3. RWST temperature.
4. Component Cooling Water temperature.

A. 1, 2, and 3.

B. 1, 2, and 4.

C. 1,3, and 4.

D. 2,3, and 4.

i ANSWER: A K/A: 026A1.01 Importance: 3.9/4.2 )

i Cognitive Level: Comprehension Ref.: TS 3.6.1.4 & 3.6.1.5 Bases LP#: I LP-SOS-13.1 OBJ: 1 History l

Source: NRC Bank Modified JTA: 1190150301 61

BVPS-1 NRC Exam: lLOT3, Rev 0 Which of the following describes the sources ofinfluent into the Primary Drains Transfer Tank

[lDG-TK-1]?

A. RCP seal leak-off, sample system drains, and Si valve stem leak-off.

B. CVCS excecs letdown diven line, RCP seals and VCT drains.

C. Si header drains, PRT, and sample system drains.

D. Valve stem leak-off, CVCS excess letdown divert line, and reactor vessel head 0-ring leak-off.

ANSWER: D K/A: 068K 1.07 Importance: 2.7/2.9 Cognitive Level: Knowledge Ref.: lOM-9.1.C pg.1 Iss 4 Rev 0; IOM-9.5 Fig. 9-1 LP#: l LP-SQS-9.1 OBJ: 2 History Source: NRC Bank JTA: 1540110101 l

62

BVPS-1 NRC Exam: lLOT3, Rev 0 The following plant conditions exist:

  • Unit I has tripped due to a loss of off-site power.

. #1 Diesel Generator has failed to stan.

Which of the following describes the status of the AFW system 60 seconds after the reactor trip?

A. Both motor driven pumps are OFF; the steam driven pump is supplying AFW flow.

B. Both motor driven pumps are supplying AFW flow; the steam driven pump is OFF.

C. The ' A' motor driven and the steam driven pumps are OFF; the 'B' motor driven pump is supplying AFW Gow.

D. The ' A' motor driven pump is OFF; the 'B' motor driven and the steam driven pumps are supplying AFW How.

l i

ANSWER: D K/A: 061K4.02 Importance: 4.5/4.6  !

Cognitive Level: Comprehension Ref.: lOM-24.1.D iss 4 Rev 2 pgs. 2 & 3; IOM-24.5 Fig 24-09 Rev 18 LP#: I LP-SOS-24.1 OBJ: 6b History Source: NRC Bank Modified JTA: 0610030101 i

l l

63 1

I' BVPS-1 NRC Exam: lLOT3, Rev 0 I

Which of the following is true with regard to Axial Flux Difference?

A. Boration will cause the Axial Flux Difference to become more negative.

B. When axial flux difference is negative, more power is being produced in the top of the core.

C. For power levels greater than.50%, axial flux is maintained within +7% of target band.

D. When power distribution is distribt'ed equally through the core, AFD is 1.

ANSWER: C K/A: 001 K5.53 Importance: 2.8/3.4 Cognitive Level: Analysis Ref.: TS 3.2.1 LP#: I LP-SQS-2.2 OBJ: 10 History Source: NRC Bank JTA: 0150050101 1

1 l

1 64 j

BVPS-1 NRC Exam: ILOT3, Rev 0 I Which of the following statements is correct if the power range channels have been adjusted based on a calculated calorimetric?

A. If the blowdown flow is ignored in calculating the calorimetric, then actual reactor power .

would be lower than indicated reactor power.

B. If the blowdown flow is ignored in calculating the calorimetric, then actual reactor power would be higher than indicated reactor power.

C. If the feedwater t:mperature used in calculating the calorimetric had been 10 degrees lower than actual feedwater temperature, then actual reactor power would be higher than indicated reactor power.

D. If the feedwater temperature used in calculating the calorimetric had been 10 degrees higher than actual feedwater temperature, then actual reactor power would be lower than indicated reactor power.

ANSWER: A (furnish calorimetric form)

K/A: 015K5.04 Importance: 3.5/3.8 015 A1.01 2.6/3.1 Cognitive Level: Analysis j

Ref.: lOM-54.4.Cl-3 Iss 4 Rev 3 LP#: LP-TMO-6 OBJ: 14 History Source: NRC Bank l

JTA: 0150070201 l

65 L___ _

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 Given the following conditions:

l

. Make-up to the RCS has increased and ONLY the following i i

alarms are received:

. Reactor Coolant Pump Seal Lea > . ,ff Temp High.

. Reactor Coolant Pump Seal Leak-off Flow High.

. Reactor Coolant Pump 1 A Seal Vent Pot Level High.

. Reactor Coolant Pump No.1 Seal Differential Pressure Low.

Which of the following has occurred to the 1 A RCP?

A. #1 seal has failed.

B. #1 and #2 seals have failed.

C. All the seals have failed.

D. Seal injection has failed.

ANSWER: A K/A: 003 A2.01 Importance: 3.5/3.9 Cognitive Level: Analysis Ref.: lOM-6.4.ABC lss 4 Rev 1; IOM-7.4.ABD lss 3 Rev 1; IOM-7.4.ABE iss 3 Rev 3; IOM-7.4.ABF iss 3 Rev i LP#: I LP-SOS-6.3 OBJ: 4e History: Similar question used in 2 LOT 2 NRC exam (0-2-97-53)

Source: NRC Bank JTA: 0030020101 66

BVPS-1 NRC Exam: lLOT3, Rev 0 i

Given the following:

. A large break LOCA has occcurred.

. Sl, CI A, FWl, MSLI, and CIB are actuated.

{

in this condition, the Containment Air Recirculation Fans..

A. must continue to run to ensure Containment pressure returns to sub-atmospheric within j i

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

B. will continue to run until the Containme:it Sump level reaches the high level trip setpoint.  ;

C. should be tripped due to the CIB.

D. should be tripped due to the SlS.

i I

ANSWER: C K/A: 022K4.03 Importance: 3.6/4.0 l

Cognitive Level: Knowledge l Ref.: lOM-44C.1 l LP#: 1 LP-SOS-44C.1 Obj.#: 5 History: New Source: LOT Bank l

JTA: 022-C0101 l 67

i 1 BVPS-1 NRC Exam: ILOT3, Rev 0 I

Unit i Laundry and Contaminated Shower Drain Tank [lLW TK-6A] is being discharged to the Unit 1 Cooling Tower Blowdown. A Hi-Hi alarm is received in the control room from the l discharge radiation monitor. Identify the automatic actions that occur.

[FCV-lLW-103] Contaminated [TV-lLW-116] Contaminated  ;

l Drains Disnosal Flow Control Drains Discharge header Rad Trin Valve A. Closes Closes. I B. Closes Opens.

C. Opens Closes.

l D. Opens Opens.

1 l

1 1

l l

ANSWER: A K/A: 068 A4.04 Importance: 3.8/3.7 Cognitive Level: Knowledge Ref.: lOM-17.l B i

LP#: I LP-SOS-17.1 OBJ: 2 )

History Source: LOT Bank Modified JTA: 069AAA0101 l

l l

68

BVPS-1 NRC Exam: lLOT3, Rev 0 The unit is at 100% power with all systems in their NSA configurations for the current power level. The RO inadvertently changes the Pressurizer Pressure Master Controller setpoint to 2185 psig. Assume a step change in the setpoint and assume the controller remains in automatic.

Which of the following is the immediate automatic response of the system?

A. Spray valves open; Variable heaters go to minimum outpui.

B. PORV 455C opens; Spray valves open; Variable heater go to maximum output.

C. Spray valves open; Variable heaters go to maximum output.

D. Spray valves close; Variable heaters go to minimum.

1 l

i ANSWER: A K/A: 010A3.02 Importance: 3.6/3.5 Cognitive Level: Comprehension Ref.: 1OM-6.5 Fig. 6-59 lss 2 Rev i1 LP#: I LP-SOS-6.4 OBJ: 11 History j l

Source: NRC Bank JTA: 0000130401 69 L_____________

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 In the event of a gross fuel element failure, which one of the following monitors would be the i

first to alarm?

I A. CVCS letdown radiation monitor. .

1 B. Containment area radiation monitor.

C. Vent stack radiation monitor, i

D. SPING radiation monitor. l l.

t ANSWER: A K/A: 073 A1.01 Importance: 3.2/3.5 Cognitive Level: Comprehension Ref.: lOM-53A.I.ES-1.1 iss IB Rev 4 step 16 LP#: I LP-SQS-43.1 OBJ: 9 History Source: NRC Bank JTA: 0000420401 I

i l

70 t__-___-

BVPS-1 NRC Exam: ILOT3, Rev 0 A plant heat-up is in progress. The following RCS temperatures were recorded at the given times:

TIME TEMP 1000 362F 1030 383F 1100 412F i

1130 440F 1200 459F Which of the following statements is correct?

A. No Administrative or Tech Spec limits were exceeded.

l B. The Administrative limit was exceeded but the Tech Spec limit was not. -

C. Both the Administrative and the Tech Spec limits were exceeded.

D. Not enough data has been gathered to determine if any limits were exceeded.

ANSWER: B K/A: 002K 1.03 Importance: 3.7/3.8 Cognitive Level: Analysis Ref.: lOM-50.2.A P&L #14. Iss 4 Rev 2 LP#: I LP-SOS-50.1 OBJ: 7 History Source: NRC Bank JTA: 002AAA0101 1

71 l

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 The following conditions exist:

  • Loops 1 and 3 Tavg indicates 576 F.
  • Loop 2 Tavg indicates offscale high.
  • Loops 1 and 3 Delta T indicates 100%.
  • Loop 2 Delta T indicates 0%.

Which of the following is the cause of these indications?

A. Loop 2 Tcold failed low.

B. Loop 2 Tcold failed high.

C. Loop 2 That failed low.

D. Loop 2 Thot failed high.

ANSWER: B K/A: 016A2.01 Importance: 3.1/3.1 Cognitive Level: Analysis Ref. lOM-l.4. AAl iss 3 Rev 5 LP#: I LP-SOS-6.5 OBJ: 5 History Source: NRC Bank JTA: 0020090101 1

72 !

i

l BVPS-1 NRC Exam: lLOT3, Rev 0 The following conditions exist:

  • Unit 1 is operating at 100% power.
  • Tavg is 576 F.

i e Pressurizer pressure is 2235 psig.

  • Delta 'l' is +8.

e Delta T is 60 F.

Which of the following plant parameter changes would cause the OTAT setpoint to LOWER?

A. Delta 'l' lowers to -2.

B. Tavg rises to 578 F.

1 C. Delta T drops to 55 F with Tavg remaining constant. j D. Pressurizer pressure rises to 2260 psig.

)

i I

ANSWER: B K/A: 012K6. I 1 Importance: 2.9/2.9 Cognitive Level: Analysis Ref.: TS 2.2.1 LP#: I LP-SOS-1.1 OBJ: 8 History Source: NRC Bank JTA: 0120050101 l

l 73

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 Prior to an outage, the steam generator were producing steam at 780 psia with an RCS Tavg of 575 F. During the outage 12% of the steam generator tubes were plugged.

What will be the new full power steam pressure if the RCS Tavg is to remain constant at the same power level as before the tubes were plugged?

A. 700 psia 10 psia.

B. 725 psia i 10 psia.

C. 780 psia 10 psia.

D. 825 psia i 10 psia.

ANSWER: B Q=UA(DELTA T); Q is constant; 100(575-515) = 88(575-Tsteam2)

Tsteam2 = 507F K/A: 035K3.01 Importance: 4.4/4.6 Cognitive Level: Analysis Ref.: Thermo/ Steam Tables LP#: LP-TMO-3 OBJ: 7 History Source: NRC Bank JTA: 0350060101 l

l 4

74

DVPS-1 NRC Exam: ILOT3, Rev 0 What condition would prevent the reactor cavity upender from being operated?

A. The transfer car is at the fuel pool end ofits travel.

B. The transfer tube valve is closed.

C. The manipulator crane is over the upender with the mast in the full DOWN position.

D. The manipulator crane is over the upender with the mast in the full UP position.

ANSWER: C K/A: 034K4.02 Importance: 2.5/3.3 Cognitive Level: Knowledge Ref.: Refueling lesson plan / procedure LP#: 1 LP-SQS-6.13 OBJ: 9 History: New Source: LOT Bank .

JTA: 0340050101 l

l 75 l

BVPS-1 NRC Exam: ILOT3, Rev 0 i

l Which of the following describes the condition associated with the Starting Air System for the l Diesel Generator that would cause the Control Room Diesel Generator Not Available annunciator?

A. One of the two starting air header pressures less than 200 psig. j B. Both of the starting air header pressures less than 200 psig.

C. One of the two starting air header pressures less than 165 psig. )

D. Both of the starting air header pressures less than 165 psig.

I l

l l

ANSWER: C K/A: 064K 1.05 Importance: 3.4/3.9 I

Cognitive Level: Knowledge Ref.: lOM-36.4.AEC & AEL iss 3 Rev 1 LP#: I LP-SQS-36.2 OBJ: 1.2 History Source: NRC Bank Modified JTA: 0640040101 76

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 Which of the following indications would lead you to suspect a leak in the fuel pool liner?

A. Increased auto-make-up from the i : ender to the pool.

B. Fuel Building sump level high alarm.

C. Fuel pool tell-tale drains receiver level high.

D. Fuel pool cooling heat exchanger outlet temperature high.

ANSWER: C K/A: 033 A2.03 Importance: 3.1/3.5 Cognitive Level: Analysis Ref.: lOM-20.1, lOM-20.4. A AC LP#: 1 LP-SOS-20.1 Obj.: 4 i

History: New Source: LOT Bank JTA: 0330170101 l

l l

i 77 I

\ _ _____ _-____ ___ _. _

BVPS-1 NRC Exam: ILOT3, Rev 0 A problem in the instrument air system caused air pressure to momentarily (30 seconds) drop to 65 psig, then return to 105 psig. What should be the response of the Station Air Header Trip Valve [TV-IS A-105]?

A. It closes, then re-opens.

B. It closes and remains closed.

C. It opens, then re-closes.

D. It remains open.

ANSWER: B K/A: 079K1.01 Importance: 3.0/3.1 Cognitive Level: Knowledge Ref.: lOM-34.1D Iss 4 Rev 0 pg. 5 LP#: LP-SOS-34.1 l OBJ: 5a History: New Source: LOT Bank JTA: 0790030101 78 l

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 Given the following:

  • Unit I was operating at 75% power
  • A small break LOCA has occurred
  • RVLIS indicates that a void exists in the vessel head increasing RCS pressure will (1) the size of the void, and (2)

Pressurizer level.

(1) (2)

A. increase increase B. decrease increase C. increase decrease l

D. decrease decrease ANSWER: D K/A: 011 K 5.15 Importance: 3.6/4.0 Cognitive Level: Comprehension Ref.: lOM-53A.I.ES-0.2 iss IB Rev 4 Step 20 LP#: ILP-SOS-53.2 OBJ: 13 History Source: NRC Bank JTA: 3110130601 79

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 A leak in which of the following components would result in a rising level in the Component Cooling Water Surge Tank?

A. Excess Letdown Heat Exchanger.

B. RCP Upper Bearing Cooling Water Cooler.

C. Regenerative Heat Exchanger.  !

D. Component Cooling Water Heat Exchanger.

i ANSWER: A K/A: 008K1.04 Importance: 3.3/3.3  ;

Cognitive Level: Comprehension Ref.10M-15.4.AAC iss 4 Rev 3 LP#: I LP-SOS-15.1 OBJ: 2 I

History Source: NRC Bank l JTA: 0080120101 4

80

BVPS-1 NRC Exam: ILOT3, Rev 0

( Which of the following represents the condition of the steam entering the PRT from a leaking l

l PORV if pressurizer pressure is 1400 psig and the PRT is 15 psig. Assume an ideal l thermodynamic process.

A. Superheated steam at 265 F.

B. Superheated steam at 280 F.

l C. Saturated steam at 265 F.

D. Saturated steam at 280 F.

I ANSWER: A K/A: 007 A4.10 Importance: 3.6/3.8 Cognitive Level: Comprehension / Application l Ref.: Steam tables _

LP#: LP-TMO-5 OBJ: 7 History ,

Source: NRC Bank ,

JTA: 0070030101 l

i 81

BVPS-1 NRC Enm: 1 LOT 3, Rev 0 '

Given the following: i

. Unit 1 in Mode 3 preparing for a normal plant cooldown.

Condenser Steam Dump System is in the steam pressure mode controlling Tavg at 547F in automatic.

[PT-1MS-464] fails low.

I What manual actions will be required by the operator?

A. Manually close steam dumps by switching to the Tavg mode. Cooldown manually in the i Tavg mode.

B. Manually close steam dumps by placing the controller to manual and reducing demand.

l Cooldown manually in the steam pressure mode, f C. Manually open the steam dumps by placing the controller to manual and raising demand.

Cooldown manually in the steam pressure mode.

D. Steam dump control is inoperable. Cooldown manually with the Atmospheric Steam Dump Valves or the Residual Heat Release Valve. l

)

i ANSWER: B K/A: 041K6.03 Importance: 2.7/2.9 Cognitive Level: Comprehension Ref.: lOM-21.1.E. Iss 4 Rev 1: pgs. 4 & 5 LP#: I LP-SOS-21.1 OBJ: 3 History: Original version used 1/15/97 Source: Modified SQS Bank Q. #0669 JTA: 0410050101 82 l

l l

BVPS-1 NRC Exam: ILOT3, Rev 0

. Given the following:

. Both units are operating at 100% power with all systems in normal system arrangement.

. Operations manning is at minimum shift compliment at each unit. .

. An oil fire breaks out in the Unit i Turbine building basement.

. The NSS determines a plant shutdown is required.

Which of the following is correct?

A. Off-site fire fighting personnel must be called in to combat the fire. Not enough personnel are available on-site to fight the fire and shutdown simultaneously.

B. Off-site fire fighting personnel must be called in to combat the fire. Equipment to fight an oil fire is not available on-site.

C. The opposite units fire brigade will fight the fire and the affected unit will perform the required shutdown duties.

D. Minimum shift compliment provides enough personnel to safely shutdown the plant and perform the required fire fighting duties.

ANSWER: D K/A: 067AK1.02 Importance: 3.1/3.9 Cognitive Level: Comprehension l

Ref.: NPDAP 3.5 Rev 6 Pg. 6 i LP#: 1 LP-SOS- AP OBJ: None - TLO only ,

History:

Source: New .

JTA: 3440320302 83 i

BVPS-1 NRC Exam: ILOT3, Rev 0 l

Given the following:

A Control Room fire caused evacuation to the Shutdown Panel (SDP).

. The reactor was tripped 10 minutes ago.

Plant control established at the SDP with all equipment transferred.

With equipment controlled from the SDP, RCS temperature is controlled using (l) , and RCS pressure is controlled using (2) .

(1) (2)

A. condenser steam dumps PZR heater group C.

B. atrnospheric steam dump valves PZR heater groups A and B.

C. condenser steam dumps auxiliary spray.

D. atmospheric steam dump valves, PZR heater group C.

ANSWER: B K/A: 068AK2.01 Importance: 3.9/4.0 Cognitive Level: Knowledge Ref.: AOP-1.33.1 A lssue 3A, Rev.4 LP#: 1 LP-SOS-53C.1 OBJ: 3 History Source: New JTA: 0000570401 l

84

l l . A reactor trip and safety injection have occurred, along with the loss of all feedwater.

l l . The steam driven AFW pump hasjust been returned to service.

l . The crew goes to step 28 of FR-H.1," Response to Loss of Secondary Heat Sink."

(attached)

. The following conditions are noted:

. RCS hot leg temperatures are all greater than 520F.

. All SG wide range levels are less than 10%.

. Core exit TCs are stable.

The action that should be taken is..

A. establish AFW flow ofless than 100 gpm to one SG until narrow range level is greater than 6%. .

B. establish AFW How ofless than 100 gpm to all SGs until narrow range level is greater than 6%.

C. establish maximum AFW How to one intact SG.

D. establish maximum AFW Oow to all intact SGs.

ANSWER: A K/A: 2.1.20 importance: 4.3/4.2 Cognitive Level: Analysis Ref.: lOM-53A.I.FR-H.1 iss IB Rev 3 step 28 LP#: ILP-SOS-53.3 OBJ: 6 History Source: New JTA: 3110060601 85

_ _ _ - - - - - . - - - - - }

BVPS-1 NRC Exam: ILOT3, Rev 0 i Which of the following designates an immediate Manual Action statement in Emergency Operating Procedures?

A. The high level action statement is underlined.

B. The step number has a triangle around it.

C. The step number has a circle around it.

D. The high level action statement is bold.

ANSWER: C K/A: 2.4.I9 Importance: 2.7/3.7 Cognitive Level: Knowledge Ref.1/20M-53B.2 Iss 1B pg. 7 LP#: I LP-SOS-53.1 OBJ: 1 History pi e: NRC Bank JTA. '0010601 86

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 Which of the following correctly describes the monitoring of the Critical Safety Function Status Trees?

A. If an orange tenuinus is encountered, the STA is expected to monitor the remaining trees. If a red terminus is encountered on a lower tree, the crew will continue the orange terminus with the higher priority.

B. If a red terminus is encountered during the performance of the immediate action steps of E-0,

" Reactor Trip or Safety injection", the crew is expected to immediately perform the I I

Functional Recovery Procedure required by the terminus.

C. A yellow terminus will require continuous monitoring until all conditions are satisified.

D. If only green or yellow terminus exist, monitoring frequency may be relaxed.to once every i

10 to 20 minutes, unless a significant change in plant status occurs.

ANSWER: D K/A: 2.4.21 Importance: 3.7/4.3 Cognitive Level: Knowledge l Ref.: n/20M-53B.2 iss IB pg.11 LP#: ILP-SOS-53.1 OBJ: 1.2 History Source: NRC Bank JTA: 3010070601

/

87 L _ __ __- _.

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 Given the following conditions:

  • Mode 3.
  • RCS Tavg is 547 F.

. RCS Boron is 760 ppm.

  • Burnup is 8000 MWD /MTU.
  • Shutdown banks are withdrawn.

Using the attached plant curves, determine which of the following statements is correct:

1 A. Minimum Shutdown Boron requirement is satisfied for the existing conditions.

B. A cooldown to Cold Shutdown can be accomplished at the present boron concentration.

C. A cooldown to Cold Shutdown can be accomplished at the present boron concentration if the Shutdown Banks are inserted.

D. The current boron concentration is adequate to maintain Hot Standby requirements if the Shutdown Banks are inserted.

ANSWER: D (furnish CB-27A, B, C)

K/A: 2.1.25 Importance: 2.8/3.1 Cognitive Level: Comprehension / Application Ref.: Curve Book - BVPS-1: CB-27A,278,27C: Iss 12 Rev 1 LP#: l LP-SOS-50.1 OBJ: 9 History Source: NRC Bank JTA: 3410180302 88

BVPS-1 NRC Exam: ILOT3, Rev 0 Which of the following methods should be used to Independently Verify the position of a CLOSED valve?

A. The person doing the Independent Verification may accompany the person closing the valve and observe him/her close it.

B. Attempt to move the valve in the closed direction.

C. A visual exam is all that is necessary, a " hands-on" verification is not required.

D. The Independent Verification for a procedure step can be substituted with the exact verification frc.n the system valve line-up.

ANSWER: D K/A: 2.1.29 importance: 3.4/3.3 Cognitive Level: Comprehension Ref.: 1/20M-48.3.D iss 3 Rev 18 pg. 5 LP#: 1/2LP SOS-48.1 OBJ: 10 History: Similar question used in 2LOTI NRC exam (0-2-97-12)

Source: NRC Bank hjodified JTA:

l 89

BVPS-1 NRC Exam: ILOT3, Rev 0 Which of the following color combinations is used to identify drums for separation and disposal of clean and radioactive waste?

Clean Waste Contaminated Waste A. Green Magenta B. Green Yellow C. Yellow Green D. Yellow Magenta l

ANSWER: B K/A: 2.3.2 Importance:

Cognitive Level: Knowledge Ref.: Rad Worker Training Handout - Section 8 LP#: LP-RC-02 OBJ: 8-3 History ,,

Source: NRC Bank JTA:

i l 90 1

l J

BVPS-1 NRC Exam: ILOT3, Rev 0 Per NPDAP 2.3, Attachment 5,(attached) which of the following represents a non-intent change to a procedure?

A. A change in initial conditions.

B. A modification to setpoints.

C. Deleting a QC hold point.

D. Addition of steps to return equipment to NSA.

1 l

1 ANSWER: D (furnish attachment 5)

K/A: 2.2.6 Importance: 2.3/3.3 Cognitive Level: Comprehension / Application l

l Ref.: NPDAP 2.3 Attachment 5 Rev 8 LP#: 1/2LP-SOS-48.1 OBJ: 9 History Source: NRC Bank JTA: 3430200302 f

91

BVPS-1 NRC Exam: ILOT1, Rev 0 Which of the following correctly specifies the maximum time period that a working copy of a procedure made from the Control Room Copy may be used for valve manipulations without checking it against the original?

A. Up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the date on the copy.

B. Up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the date on the copy.

C. Up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the date on the copy.

D. Must be checked each shift.

i I

ANSWER: C K/A: 2.1.21 Importance: 3.1/3.2 Cognitive Level: Knowledge Ref.: 1/20M-48.2.C lss 3 Rev 17 pg. 8 LP#: 1/2LP-SOS-48.1 OBJ: 8 l History l Source: NRC Bank .

1 JTA: 3430260302 <_

l l

l 1

i 92

l BVPS-1 NRC Exam: ILOT3, Rev 0 Which of the following are considered " extremities" when considering radiation dose limits? I A. Hands and feet only. .)

B. Hands, elbows, forearms, ankles and feet.

C. Hands, anns, legs, and feet.

D. Hands, elbows, forearms, knees, leg below knees, and feet. ]

i I

l ANSWER: D l

K/A: 2.3.I importance: 2.6/3.0 Cognitive Level: Knowledge Ref.: Health Physics Manual Units 1&2, Appendix 14: 10CFR20.1003 LP#: LP-RC-02 OBJ: 3-5 History Source: NRC Bank JTA:

l 93

BVPS-1 NRC Exam: ILOT3, Rev 0 Operators havejust stabilized the Unit from an unexplained 15% load rejection from full power when another, also unexplained,15% load rejection occurs. Which of the following actions should be taken? ]

A. Re-stabilize the unit in accordance with the AOP.

B. Reduce load to <P-9 in accordance with the IOM.53C.4.1.51.1," Emergency Shutdown" AOP.

C. Place the Reactor in Hot Standby.

D. Start the second EHC pump, and place the EHC controller in Turbine Manual mode of operation.

1 ANSWER: C K/A: 2.1.1 Importance: 3.7/3.8 j l

Cognitive Level: Knowledge Ref. lOM-53C.4, AOP 1.35.2 LP#: LP-SOS-53C.1 OBJ: 3 )

History:

Source: SOS Bank O. #0273 l

JTA: 0000280401 l

94 l

BVPS-1 NRC Exam: ILOT3, Rev u j During the performance of a Clearance procedure, what job position is responsible for authorizing the ESF checklist if the equipment to be cleared is safety related and required in the current mode of operation?

A. NSS.

B. ANSS.

C. Clearance Coordinator.

D. Reactor Operator.

ANSWER: A K/A: 2.2.13 Importance: 3.6/3.8 Cognitive Level: Knowledge Ref.: NPDAP 3.4 Rev 7 Pg. 2. step lll.F.3 LP#: 1/2LP-SOS-48.1 OBJ: 28 History: Used 1/31/97 Source: SOS Bank O. # 0102 JTA: 3420050302 Q

95

BVPS-1 NRC Exam: ILOT3, Rev 0 Which of the following Emergency Shutdown Panel indications are required by Technical Specifications?

1. Auxiliary Feedwater Flow.
2. RCS Hot Leg Temperature.
3. Source Range Flux.
4. Emergency 4kV Bus Voltage.

A. 1, 2, and 3.

B. 1,2, and 4.

C. 1,3, and 4.

D. 2,3, and 4.

l ANSWER: A e

K/A: 2.2.22 Importance: 3.4/4.1 Cognitive Level: Knowledge Ref.: TS3.3.3.5 Table 3.3-9 LP#: LP-SOS-53C.1 OBJ: 6 l 1

History: Similar question used in 2LOTl NRC exam (0-2-97-88)

Source: SOS Bank Q.#0493 JTA: 1190150301 I

96

(________--__

t BVPS-1 l

'NRC Exam: ILOT3, Rev 0 1

l What is the minimum positive threshold indication of personnel contamination when using a frisker?

l A. 100 cpm. l l

l B. 100 cpm above background.

l C. 300 cpm.

D. 300 cpm above background.

1 ANSWER: B K/A: 2.3.4 Importance: 2.5/3.1 i l

Cognitive Level: Knowledge Ref.: Health Physics Manual Issue 4 Rev. I1, Chapter 1 Part 111 l LP#: LP-RC-02 OBJ: 6-5 History Source: SOS Bank O. #0382 JTA: 1190210304 I l

l l

97

I BVPS-1 '

NRC Exam: ILOT3, Rev 0 l

DC Bus #1 has been de-energized due to a fire in the switchboard cabinet. A reactor trip then  ;

1 occurs. Recovery from this transient is complicated because...

A. control of emergency loads on the 1 AE bus are not possible from the Control Room.

B. the #1 Diesel Generator will start and load, but not be able to be stopped from the Control Room.

C. Charging and Letdown will not be available due to the loss of the Station Air Compressors.

D. temperature control will be on the Residual Heat Release valve because the Condenser and Atmoshperic Steam dumps will not be available.

l ANSWER: A

{

s K/A: 063K2.01 Importance: 2.9/3.1 Cognitive Level: Comprehension Ref.: lOM-39.4.AAI Iss 3 Rev 2 LP#: I LP-SQS-39.1 OBJ: 4 History Source: NRC Bank Modified l JTA:

l l

98

i BVPS-1 l NRC Exam: ILOT3, Rev 0 i l

Given the folloving:

e Total AFW flow is 330 gpm. j e Turbine Driven AFW pump secured.

. 2 Motor Driven AFW pumps running.

  • Tz sg is 529 F and lowermg slowly.

. All narrow range SG levels are 4%.

A partial feedwater isolation has occurred, and all condenser and atmospheric steam dump valves are shut. Assume all trends continue.

The correct operator response to these conditions is to..

A. reduce AFW flow and initiate Main Steamline Isolation.

B. reduce AFW flow and commence emergency boration.

C. initiate Main Steamline Isolation and commence emergency boration.

D. Establish SGFW bypass flow, secure AFW flow, and initiate Main Steamline Isolation.

ANSWER: C K/A: 2.4.6 Importance: 3.1/4.0 Cognitive Level: Analysis Ref.: ES-0.1 Step 4 Issue IB Rev 2 LP#: 1 LP-SOS-53.3 OBJ: 3 .

i l

History Source: SOS Bank i

, JTA:

1 99

BVPS-1 NRC Exam: 1 LOT 3, Rev 0 With the plant operating at 100% power, Intermediate Range detector N35 fails high, followed immediately by N36 failing low. Which of the following is the correct operator response?

A. Initiate a Reactor Trip and enter E-0, " Reactor Trip or Safety injection."

B. Restore at least one Intermediate Range Channel in the next hour or be in Hot Shutdown within the following six hours.

C. Since the r. amber of channel operable is less than the number required by the Minimum Operability Channel requirement, Technical Specification 3.0.3 applies.

D. Power operation may continue since Technic .i Specification for Intermediate Range NI's does not apply during present plant condP. sons.

ANSWER: D K/A: 033-2.2.22 l Importance: 3.4/4.1 Cognitive Level: Comprehension / Application Ref.: lOM-53C.4.1.2.1B Iss 3'A Rev 1 LP#: 1 LP-SQS-2.2 OBJ: 5 History Source: NRC Bank JTA: 0000100401 I

l

[

l 1

f 100 l

I-

_ _ _ - _ - - - _ _ _ _ - = _ _ - -

1 BVPS-1 ]

NRC Exam: ILOT3, Rev 0  !

l Given the following: l

. The plant was in Mode I when a loss of offsite power occurred.

. Both Emergency Diesel Generators and the ERF D/G have started and loaded their respective busses. j Control of air-operated valves outside of Containment,is...

A. not possible until offsite power is restored.

B. not possible until the Diesel air compressor is started.

C. possible; the station air compressors will auto load onto the Emergency Diesel Generators.

D. possible, the station air compressors will auto load onto the ERF Diesel Generator, i l

ANSWER: B K/A: 056 AA1.37 Importance: 3.4/3.5 Cognitive Level: Comprehension l

Ref. lOM-37.5 Table 37-21ss 2 Rev 4: lOM-37.5.B.7 iss 4 Rev 12 LP#: I LP-SOS-53C.1 OBJ: 6 History Source: NRC Bank JTA:

i l  !

l 101

BVPS-1 NRC Exam: ILOT3, Rev 0

. Given the following plant conditions:

  • A reactor trip and safety injection have occurred from 100% power.

l E-0, " Reactor Trip or Safety injection," has been completed through step 13 (Verify i

Feedwater Isolation).

  • AFW pumps cannot be started.

Which of the following actions is required?

A. Immediately transition to FR-H.1," Response to Loss of Secondary Heat Sink."

B. Transition to FR-H.1 as soon as a transition out of E-0 occurs.

C. Go to ES-0.0,"Rediagnosis," which will allow a transition to FR-H.l.

D. Transition to FR-H.1 when directed to by E-0.

ANSWER: D K/A: 2.4.I Importance: 4.3/4.6 Cognitive Level: Comprehension Ref: lOM-53 A.1.E-0 iss IB Rev 5 LP#: 1 LP-SQS-53.1 OBJ: 1 History Source: NRC Bank JTA:

1 i

l l

l 102  ;

l l BVPS-1 i NRC Exam: ILOT3, Rev 0 l

i Given the following:

. The unit is at 100%.

. The following parameters are recorded for the 'A' Accumulator:

Accumulator Level is equivalent to 7600 gallons.

Accumulator Pressure is 650 psig.

Accumulator Boron is 1900 ppm.

[]SI-MOV-865 A) is open.

The accumulator should be declared INOPERABLE based on:

A. Level (volume).

B. Pressure.

C. Boron concentration.

D. Discharge valve position.

Answer: A K/A: 006-2.1.33 Importance: 3.4/4.0 Cognitive Level: Knowledge Ref.: TS 3.5.1 LP#: l LP-SQS-TS OBJ: 1 History: Original used 1 LOT 3 exam 4/1/97 Source: SQS Bank 00896 & 0046 - Modified JTA:

1 I

103

4

._ h

)y. 2

'Ijpendix D Scenario Outline Form ES-dei ~

3 Facility: BVPS - Unit 1 Scenario No.: .1. OP-Test No.:

Examiners: Operators:

Obiectives: To evaluate the applicants' ability to raise reactor power to the point gf adding heat, control the reactor at lower power; to implement the AOPs and ARPs for a NI failure and a Pressurizer Level Instrument failure; and to respond to steam line break (EOP E-2) with concurrent component malfunctions and subsequent Safety injection termination (EOP E-1 and ES 1.1.)

Initial Conditions: Rx S/ U in progress, Rx power is at 1E-8 amps, Xenon free, MOL conditions.

Turnover: Bank D at 100 steps. Ready to continue startup at step C.1 of OM-50.4D. FW-150A&B am failed open and CN '101 is in Manual and closed. The inital conditions for Cold Turbine Startup have been verified in accordance with 52.4.A. Boron is 1190 ppm.

Feed flow is being provided by the 1 A MFP with the feedwater bypass valves operating in Auto. The "B" station instrument air compressor is out of service for maintenance but is expected to be returned to service this shift.

Event Malf. Event Event No. No. Type

  • Description 1 R(RO) Raise power to point of anding heat. Crew then raises power to > 10%.

2 MALF C(SRO) N36 IR instrument power fuses blows. Action taken NIS7B IAW T.S. 3.3.1.1 3 N(ALL) Crew continues to raise power, and continues plant startup.

4 MALF I(RO/SRO) LT-459 fails low msulting in letdown isolation.

l PRS 6A N(RO/SR Altemate channel selected and letdown restored to

! O) service 5 MALF C(ALL) Steam leak inside of containment. Lowering RCS MSSIA temperature and increasing power.

l

! 6 MALF M(ALL) Steam line break inside of containment. Results in l

MSSIA safety injection, CIA and CIB.

7 MALF C(RO/SR CH-P-1 A trips on SI actuation. CH-P-1B must be SISSA O) manually started.

8 INH 51 C(ALL) Failure of Main Steamline Isolation.

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Facility: BVPS - Unit 1 Scenario No.: 2 OP-Test No.:

4 Examiners: Operators:

Obiectives: To evaluate the applicant's ability to implement AOPs and ARPs in response to an instrument failure and RCP seal failure; to initiated a plant shutdown as required by T.S. 3.0.3; and to respond to a Pressurizer vapor space LOCA (EOP E-1 and ES-1.2.)

Initial Conditions: 75% power, Bank D at 206 steps, EOL,161 ppm boron, Xenon increasing @ 200pcm/hr due to power decrease from 100% over the past 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> as requested by system operator.

Turnover: FW-P-3A, MDAFW pump is on clearance for motor replacement. Due to be returned next shift. Rod controlis in manual while 1&C troubleshoots a fault on power mismatch circuit, CBD @ 206 steps, boron = 161 ppm, bumup = 14,000 MWD /MTU.

N42 Power Range channelinoperable and removed from service IAW AOP 1.2.1C. Crew is to maintain cunent power level pending request of System Operator.

Event Malf. Event Event No. No. Type

  • Description 1 MALF C(RO/SR PT-RC-455, RCS pressure protection channel I fails 4 NIS3B, 0) high. With N42 already inoperable TS 3.0.3 should be I PRS 8A entered due to 2/3 OT/DT channels being i inoperable.

2 R(RO) Power reduction of at least 5% due to TS 3.0.3.

I N(PO/SR O) 3 MALF 1(RO) VCr levelcontrol channel failure.

CHS20B 1(SRO) 4 MALF C(RO/SR Excessive #1 sealleak off of 20 gpm on IRC-P-1B, B RCSSB O) loop RCP, requiring a Rx trip 1AW ARP 7.4.ABE.

l 5 MALF M(ALL) ATWS that causes a PZR PORV to open. Local Rx 1 CRF12 trip to occur at t = 2 minutes after requested from A&B crew.

6 MALF C(PO/SR Turbine driven AFP trips on start. FW-P-3B fails to i FWM11 O) auto start, must be started manually.

B&C 7 MALF M(ALL) PCV-RC-455C, PZR PORV, leaks. MOV-RC-535 fails PRS 3A to close resulting in vapor space LOCA.

1 NUREG 1021 41 of 42 Interim Rev. 8, January 1997 avm.% i ---_---_-________j

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Appendix D Scentrio Outline Form ES-D-1 o l l

I Facility: BVPS - Unit 1 Scenario No.: 3 OP-Test No.:

I Examiners: Operators:

l .-

Obiectives: To evaluate the applicants' ability to implement AOPs and ARPs in response l to a N1 failure, dropped control rod, loss of main feedwater pump; to a initiate a l controlled power reduction; and to respond to a reactor trip (EOP E-0, and ES-0.1) with subsequent malfunctions leading to a loss of secondary heat sink (EOP-FR-H.1).

Initial conditions: Reactor plant at 80% returning to full power following a load swing to 75% as requested by the System operator. The power decrease was at 10% /hr. Power was held at 75% for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Crew is to return to 100% from 80% at 10%/hr, using OM-52.4.B-Part B.

Tumover: FW-P-3A, MDAFW pump is on clearance for motor replacement. Due to be retumed next shift. CBD @ 182 steps, boron - 1078 ppm, bumup = 3,000 MWD /MTU.

The "B" station instrument air compressor is out of service for bearing replacement.

! Event M alf. N o. Event Event No. Type

  • Description i

1 MALF I("O/SRO N44 power range change fails low, auto rod control )

NIS3D ) drives out control rods. )

2 MALF C(RO/SR During rod withdrawal, rod H14 drops due to blown CRF4 )

O) fuse.

l l 3 R(RO) Power reduction initiated in response to dropped rod.

i N(PO/SR O)

_ 4 MALF C(PO/SR One main feedwater pump trips.

FWM1B O) l 5 MALF M(All) Second main feedwater pump trips, resulting in a FWM1A reactor trip on low SG level.

l 6 INH C(PO/SR Turbine fails to trip, crew manually trips turbine TURT 0) 7 MALF C(PO/SR Tu-bine Driven AFP fails to start.

MFM11C O) 8 MALF M(ALL) FW-P-3B trips on motor fault, resulting in a loss of MFM11D heat sink.

(N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor NUREG 1021 41 of 42 Interim Rev. 8, January l 1997 ,

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ES-301 Individual Walk-through Test Outline Form ES-301-2 Facility: Beaver Valley. Unit One Date of Examination:

Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.:

System / JPM Title / Type Safety Function Planned Follow-up Questions:

Codes

  • K/A/G // Importance // Description
1. CRDS - RCCA Misalignment a. 00i K4.05 / 3.9 I Amount of rod withdrawal to compensate for boration.

D, S b. 001 K5.08 / 4.4 Rod Insertion Limit determination.

2. CVCS - Secure Excess a. 004 Kl.25 / 3.2 Letdown 11 Effect of Si actuation on excess letdown.

N,S b. 004 K6.10 / 3.1 Loss of CVCS heat tracing.

3. PZR PCS - Depressurize to a. EPE 038 EK1.03 / 4.2 Backfill from Ruptured SG III RCS Dilution from Backfill operation.

N A.S b. EPE 038 EK3.06 / 4.5 Bases for minimum level in ruptured SG.

4. RHR -Establish RHR System a. 005 A1.02 / 3.4 Flow IV Flow control while adjusting cooldoun rate.

D,L,S b. APE 025 AA1.02 / 3.9 Determination of boiloff rate following loss of RHR.

5. CSS - Verify Containment a. 026 K1.01/4.2 Spray y Flow path to HHSI with Recirculation spray.

N.A.S b. 026 K4.08 / 4.3 Effect of failure of MOV-lQS-103 A to close.

6. EPD - Perform a Hot a. 062 K2.01/ 3.4 Bus Transfer VI Causes of reactor trip on loss of Bus IB.

D,S b. 062 A2.05 /3.3 UV Trip defeat when cross tying to BV-Unit 2.

7. NNI- Respond to Feed Flow a. 035 A2.04 /3.8 Instrument Failure yll Plant response if action not taken.

N,S b. 016 A3.02 /2.9 l Instrument response to changing temperature. j

8. SAS -Place Diesel Air a. APE 065 AA2.05 /4.1 Compressor in Service ylli When to shutdown or trip due to loss of air pressure.

N,P b. 078 K3.02 /3.6 Effect of loss of air on Makeup Control System.

9. HRPS Startup the a. 028 Al.013.8 Hydrogen Recombiner. y Correction for Hydrogen Analyzer reading.

D.P.R b. 028 K5.02 /3.9 Recombiner operation with Hydrogen > 4%.

10. EDG - Locally Start the a. 064 K6.08 /3.3 l Emer. Diesel Generator VI Application of Tech Specs for inoperable EDGs.

l D,P b. 062 K3.02 / 4.4 Diesel auto start during engine cooldown cycle. I

  • Type Codes: (D)irect from bank (M)odified from bank, (N)ew,(A)leternate path, L (C)ontrol Room, (S)inadator, (L)ow power, (P)lant,. (R)CA '

NUREG-1021 . 22 of 26 Interim Rev. 8 January 1997 A0 1 D ,

BYFS-aEV.I J

t RTL #A5.640E DUQUESNE LIGHT COMPANY

' Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training l OJT CHECKLIST /JPM TITLE: RCCA Misalignment (High, Situation A)

JPM NO.: 1CR-100 l

COMPUTER CODE: N/A Revision No. Date l Revision No. Date l

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l PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, operations Training, or Designee Revision 9

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Powar Division Training Administrative Manual i

LESSON PLAN AND OJT REVISION APPROVAL SHEET l

l

DOCUMENT TITLE: 1CR-100. RCCA Misalignment (Hich. Situation A)

(

Revision Acoroval No. Brief Description Revised by: Signature Date l

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Revision 9

BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: 1CR-100 Rev: 4 System #: 001 Faulted: O JPM

Title:

RCCA Misalignment (High, situation A)

K/A

Reference:

003 AA1.02 /3.4 Task ID #:0000080401 JPM Designation: O NO O RO E SRO X X JPM Application: NRC Initial Exam O Training Evaluation Method LOCATION TYPE O Perform O Plant Site O Training {

O Simulate x Simulator O Annual Requal. Exam O Classroom O OJT x Initial Operator Exam Administered By: O Other:

O Bv-T O NRC D Other:

Evaluation Results Performer: Name: Employee No:

Results O SAT Time (minutes)

O UNSAT* Allotted: 20 Actual: '

Time Critical: O yes x No

  • Comments (Required for UNSAT Evaluation):

I Evaluation Results O Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 7 0 0 Employee No:

Question #1 5 O O Employee No:

  • Comments (Required for UNSAT Evaluation):

l Evaluator (Print): Organization:

Evaluator Signature Date:

R9 vision 9

RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET j

  • THIS SHEET TO BE GIVEN TO CANDIDATE *

-Read:

Task: lRCCAMisalignment(High,SituationA)

INITIAL 58%. power. Rod F-10 of Bank D has been determined CONDITIONS: to be at'197 steps. Bank D is at 179 steps. Rods are in manual. The reason for the rod misalignment has been corrected. Tavg is equal to Tref. Testing and Plant personnel have been notified. A flux map is not necessary. Rods can i be moved in manual. )

1 INIT. CUE: Your supervisor directs you to respond to the .

misaligned rod per the appropriate procedure.

l At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

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Revision 9

_ _ - _ - _ _ _ _ _ _ _ - _ _ - _ _ ~

RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: 1CR-100 JPM TITLE: RCCA Misalignment (High, Situation A)

RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to perform the task respond to RCCA Misalignment.

INIT. CONDITIONS: 58% power. Rod F-10 of Bank D has been determined to be at 197 steps. Bank D is at 179 steps. Rods are in manual. The reason for the rod misalignment has been corrected. Tavg is equal to Tref. Testing and Plant personnel have been notified. A flux map is not necessary. Rods can be moved in manual.

TASK STAN.: Rod alignment complete with all Bank D rods at 179 steps.

INIT. CUE: Your supervisor directs you to respond to the misaligned rod per the appropriate procedure.

REFERENCES:

10M-1.4.X, Issue 3, Rev 5 TOOLS: NONE HANDOUT: 10M-1.4.X, RCCA or RCCA Group Misalignment Revision 9

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RTL #A5.635J NUMBER TITLE ICR-23 RCCA Misalignment (High, Situation A)

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

l Evaluator Setup: -Initialize Simulator to IC 88.

START TIME:

Candidate locates and reviews IOM-1.4.X EVALUATOR CUE: Provide candidate with prepared copy of IOM-1.4.X.

EVALUATOR CUE: lOM-1.4.X has been completed through step 9. The Unit Operations Manager and React r Engineer have been notified.

The rate of control rod motion shall be limited to 5 step incter:r nts and startup rate shall be limited to 0.25 DPM. Situation A should be used for the re-alignment of the misaligned rod.

1.C Place the rod control selector switch 1.1 Candidate locates rod control in the Bank D position. selector switch.

1.2.C Candidate places rod control selector switch in the Bank D position.

COMMENTS:

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Page I of 7 Revision: I

I NUMBER TITLE ICR 100 RCCA Misalignment (High, Situation A)

STEP STANDARD

("C" denotes critical step) . (Indicate "S" for Sat. or "U" for Unsat.)

2.C Place all disconnect switches for the 2.1 Candidate locates the disconnect aficcted group, except for affected switches for Conuni Bank D.

rod, in the rod disconnect position.

2.2.C Candidate places all Control Bank D disconnect switches (except rod F-10)in the disconnect (UP) positic n.

GRI GR2 H2 F6 B8 K10 HI4 K6 P8 COMME!RS:

3. Record the Bank group positions 3.1 Candidate records Control Bank and misaligned rod position. D Group I and Group 2 position.

Group 1: 179 steps Group 1: 179 steps 3.2 Candidate records rod F-10 position.

FIO: 197 steps Page 2 of 7 Revision: I

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RTL #AS.635J NUMBER TITLE ICR 100 RCCA Misaligmnent (High, Situation A)

I STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

I 1

EVALUATOR NOTE: The values for the rod positions are provided in the initial conditions.

COMMENTS:

4.C Step the step counter for the 4.1 Candidate locates the group step misaligned rod group to the position counter for the Bank D group 2 the rod is deterrnined to be in. rods.

4.2.C Candidate sets the step counter i to 197 steps. l COMMENTS:

EVALUATOR CUE: The PO will adjust turbine load as necessary to maintain Tavg.

EVALUATOR NOTE: Tavg will drop, if necessary tell candidate to assume Tavg is being maintained equal to Tref.

l Page 3 of 7 Revision: 1

RTL #A5.635.J NUMBER TITLE ICR-100 RCCA Misalignment (High, Situation A)

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

5.C Insen the affected rod. 5.1 Candidate locates the rod motion lever.

5.2.C Candidate inserts rod in five step increments by placing the rod motion level to the "IN" position.

5.3 Candidate verifies rod moving in proper direction by observing step and individual rod position indication.

5.4 Candidate acknowledges rod control system annunciators.

COMMENTS:

6.C Continue rod insertion untilits 6.1.C Candidate stops rod insertion associated step counterindicates a when the group step counter position corresponding to the bank indicates 179 steps.

j position.

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COMMENTS:

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Page 4 of 7 Revision: I

RTL #A5.635.J NUMBER TITLE ICR 100 RCCA Misalignment (High, Situation A)

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

i

7. Verify misaligned rod is now at the 7.1 Candidate locates the Control same pocition as the other rods in Bank D IRPI indication.

( the bank by reading indisidual RPI.

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7.2 Candidate vesifies that rod F-10 position matches the otler Control Bank D rod positions:

i EVALUATOR CUE: All Control Bank D Rods indicate 179 steps.

COMhENTS:

I 8.C Replace all disconnect switches to 8.1 Candidate locates the disconnect

! the connect position. switches for the Control Bank D position.

8.2.C Candidate places all Control

, Bank D disconnect switches

( (except rod F-10)in the connect (DOWN) position.

l COMMENTS:

l Page 5 of 7 Revision: I

RTL #AS.635.J .-

NUMBER TITLE 1CR 100 RCCA Misalignment (High, Situation A)

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

I 9.C Clear the Urgent Failure alarm. 9.1 Candidate locates the Urgent Alarm Reset Pushbutton.

9.2.C Candidate depresses the pushbutton, 9.3 Candidate verifies the Rod Control System Urgent Alarm clears.

l COMMENTS:

I l 10. Reset the P/A converter if the 10.1 Candidate determines that a misaligned rod was in a control control bank was affected.

bank.

10.2 Candidate asks supenisor to have the P/A converter reset.

I EVALUATOR CUE: The P/A converter has been reset by another operator.

j COMMENTS:

Page 6 of 7 Revision: I

____________________a

RTL #A5.635.3 i

NUMBER TITLE ICR-100 RCCA Misalignment (High, Situation A)

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

EVALUATOR CUE: Your supervisor directs you to i restore rod control to manual.

I 1. Retune the bank sciector switch to 11.1 Candidate locates the bank mamial. selector switch.

I1.2.C Candidate places the bank  ;

selector switch in the manual l position. I l EVALUATOR CUE: The crew will monitor the l required parameters.

1 COMMENTS:

12. Inform supenisor that the rod has 12.1 Candidate informs supervisor been re-aligned. that the rod has been re-aligned.

I COMMENTS:

STOP TIME Page 7 of 7 Revision: I

l BVPS JOB PERFORMANCE MEASURE JPM QUESTION #1 Assume the plant is operating at 5% power following a reactor stanup at beginning oflife (150 MWD /MTU and Boron = 900 ppm). How much boron would be needed to compensate for withdrawing bank D from 125 steps to 130 steps? (Assume xenon free operation.)

OPEN REFERENCE

. ANSWER: )

Change in integral rod worth (CB-24 A) is approximately 40 pcm.

Differential boron worth (CB-20) is approximately -8.25 pcm/ ppm.

)

Amount of boration is 4.5 - 5.0 ppm

! Time Allotted: 7 minutes l

l KA#; 001 K4.05 / 3.9 l

Objective: 1/2LP-NOMCD-1.1 ,

Reference:

Unit I Curve Book l l

\

I Comments: l l

]

1CR-100 BVPS Rev. 0

! BVPS JOB PERFORMANCE MEASURE 1

1

  • THIS SHEET TO BE GIVEN TO CANDIDATE *

! JPM QUESTION #1 Assume the plant is operating at 5% power following a reactor startup at beginning oflife (150 MWD /MTU and Boron = 900 ppm). How much boron would be needed to compensate for withdrawing bank D from 125 steps to 130 steps? (Assume xenon free operation.)

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ICR 100 BVPS Rev, O L _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ . _ _ _

l BVPS JOB PERFORMANCE MEASURE JPM QUESTION #2 Assume the plant is operating at 63% power. What are the minimum control and shutdown rod positions

' that ensure SHUTDOWN MARGIN is maintained?

I l

OPEN REFERENCE ANSWER:

I Control rods: Bank D at 113 - 120 steps.

I Shutdown rods: 225 steps.

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Time Allotted; 5 minutes l

KA #: 001 K5.08 /4.4 l Objective: LP-SQS-1.3 OBJ 15 '

Reference:

T.S. 4.1.1.1.1, 3.1.3.5, 3.1.3.6, and COLR Figure 1.

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Comments:

1CR-100 1

BVPS Rev. O

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EVPS JOB PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • l JPM QUESTION #2 l

Assume the plant is operating at 63% power. What are the minimum control and shutdown rod positions -

that ensure SHUTDOWN MARGIN is maintained?

I 1

ICR-100 BVPS Rev. 0

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division f Training Administrative Manual I

l OJT CHECKLIST /JPM COVER PAGE l PROGRAM TITLE: Licensed Operator Training )

l SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Secure Excess Letdown JPM NO.: ICR-N01

j. COMPUTER CODE: N/A Revision No. Date Revision No. Date l

PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee Revision 9

l RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division

[ Training Administrative Manual )

l LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: ICR-N01. Secure Excess Letdown l

l I Revision ADoroval l

No. Brief Description Revised by: Signature Date j l

1 I

i Revision 9 >

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BEAVER VALLEY JOB PERFORMANCE MEASURE  !

EVALUATOR COVER SHEET l JPM Number: 1CR-N01 Rev: O System #: 004 Faulted: O JPM

Title:

Secure Excess Letdown l

K/A

Reference:

004 A4.06 /3.1 Task ID #:0040160101 l JPM Designation: O NO O RO x SRO JPM Application: x NRC X Initial Exam Training i

Evaluation Method LOCATION TYPE Perform Plant Site Training Simulate X Simulator Annual Requal. Exam O Classroom OJT X Initial Operator Exam Administered By: Other:

BV-T O NRC 0 Other:

Evaluation Results Performer: Name: Employee No:

Results SAT Time (minutes)

UNSAT* Allotted: 10 Actual:

Time Critical: Yes X No

  • Comments (Required for UNSAT Evaluation):

Evaluation Results O Check here if same as above Observer 1: Name: Employee No: l Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 5 O O Employee No:

Question #1 5 I Employee No:

  • Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9

l RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE uEASURE 1

I CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • Read:

Task: Secure Excess Letdown INITIAL A failure of TV-1CH-204 resulted in a loss of CONDITIONS: normal letdown. Excess letdown was placed in service. TV-1CH-204 has been repaired and normal letdown has been returned to service.

INIT. CUE: Your supervisor directs you to secure excess letdown in accordance with 10M-7.4.AF.

At this time, ask the evaluator any questions'you have on this l

.7PM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task. l Point to any indicator or component you verify or check and '

announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

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l Revision 9

R1L #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET

)

JPM NUMBER: ICR-N01 JPM TIrLE: Secure Excess Letdown RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate (perform) the task Secure Excess Letdown.

INIT. CONDITIONS: A failure of TV-1CH-204 resulted in a loss of normal letdown. Excess letdown was placed in service. TV-1CH-204 has been repaired and normal letdown has been .

returned to service.

TASK STAN.: Excess letdown secured in accordance with

, 10M-7.4.AF.

l INIT. CUE: Your supervisor directs you to secure =

excess letdown in accordance with 10M-7.4.AF.

I

REFERENCES:

10M-7.4.AF Issue 4, Revision 2.

I TOOLS: NONE l

HANDOUT: 10M-7.4.AF, Restoring Charging and Letdown 1

l  :

l Revision 9

RTL #AS.635.J NUMBER TITLE ICR-N01 EECURE EXCESS LETDOWN STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

Evaluator Setup: -Initialize Simulator to IC 75.

I j

START TlhE:

Candidate locates and reviews IOM 7.4. AF, Restoring Charging and Letdown.

EVALUATOR CUE: Provide candidate with prepared copy of IOM-7.4.AF.

l L Monitor No.1 Seal Leakoff Wide 1.1 Candidate monitons [FR-lCH-l Range. 154A].

l COMMENTS:

2.C Slowly set Excessletdown HX 2.1 Candidatelocates controller for Flow Control Valve controller to 0. [FCV lCH 137].

2.2.C Candidate slowly reduces controller setpoint to 0 while maintaining [FR-1CH-154 A]

within alarm limits (0.9 gpm *

.02 and 4.7 gpm * .12)

COMMENTS:

Page 1 of 5 Resision: 1

RTL #A5.635.J NUMBER l TITLE ICR-N01 SECURE EXCESS LETDOWN l STEP STANDARD

("C" denotes critical step) (Indicate *S" for Sat. or "U" for Unsat.)

l 3. Close I A RCL Drain valve. - 3.1 Candidate locates the control l switch for [MOV IRC-557A].

l 3.2 Candidate takes control switch l for {MOV-1RC 557A] to tie l CLOSE position.

l l 3.3 Candidate verifies [MOV-IRC-557A] closed by verifying the red indicating light is off and the green indicating light is on.

! EVALUATOR NOTE: MOV-lRC 557B and C are closed and de-energized.

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COMME!GS:

t 4.C Depressurize the excess letdown 4.1 Candidate observes [PI lCH-line. 138].

4.2.C Candidate slowly increases setting of controller for [FCV.

ICH 137] until(PI-lCH 138] j l stabilizes and then returns  ;

control to 0% I l

COMMENTS:

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Page 2 of 5 Revision: 1

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RTL #A5.635J I

1 NUMBER TITLE ICR-N01 SECURE EXCESS LETDOWN STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

5, Close Excessletdown HX Inlet 5.1 Candidate locates the control isolation Valve. switch for [MOV-ICH-201l.

5.2 Candidate takes control switch for [MOV-ICH-201] to the CLOSE position.

5.3 Candidate verifies [MOV-1CH-l l 201] closed by verifying the red indicating light is off and the green indicating light is on.

l COMMENTS:

6. hlign excess letdown to the VCT. 6.1 Candidate locates the control l switch for [HCV-lCH-3891 6.2 Candidate verifies control switch for [HCV-1CH-389] in the VCT position.

COMMENTS:

Page 3 of 5 Revision: 1

RTL #A5.635.J NUMBER TITLE ICR N01 SECURE EXCESS LETDOWN STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

7. Remove power for Loop Drain Line 7.1 Candidate requests local operator Step Wives. to place 480 VAC power supply switches for [MOV-IRC-557A, 557B, AND 557C] in the OFF position.

EVALUATOR CUE: Local control switches have been placed in the OFF position.

l COMMENTS:

(L Adjust RCP seal flow. 8.1 Candidate locates and observes

[FI-lCH-130,127, and 124].

Page 4 of 5 Revision: 1

> 1 l

RTL #AS.635.J i

NUMBER TITLE 1

l ICR N01 SECURE EXCESS LETDOWN STEP STANDARD s

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

8.2 Candidate locates and adjusts controller for [HCV-ICH-186]

as necessary until 6 - 9 gpm is f

indicated on [FI-lCH-130,127, and 124].

COMMENTS:

9. Inform supenisor that excess 9. Candidate informs supenisor letdown has been secured. that excess letdown has been secured.

COMMENTS:

STOP TIME i

l Page5of5 Revision: 1

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BVPS JOB PERFORMANCE MEASURE JPM QUESTION #1 l

Explain the effect that a Safety injection Actuation would have on excess letdown opration. (Assume excess letdown is aligned to the VCT and all systems are NSA except normal letdown, which is isolated.)

' {

OPEN REFERENCE ANSWER:

[SI would cause a CIA which causes] the RCP seal water return containment isolation valves, MOV-ICH-378 and 381 to close, isolating excess letdown. [which would be directed to the PRT via the seal return line relief valve, RV 1CH-382A.]

Time Allotted: 5 minutes KA#: 004 Kl.25 /3.2 Objective: LP-SQS-7.1 OBJ 5

Reference:

OM Figure 7.4 OM 1, Table 1.4 l

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Conunents:

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ICR-N01 BVPS Rev. 0 ,

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l BVPS JOD PERFORMANCE MEASURE l

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #1 l Explain the effect that a Safety injection Actuation would have on excess letdown operation. (Assume l excess letdown is aligned to the VCT and all systems are NSA except normal letdown, which is isolated.)

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ICR-N01 BVPS Rev. 0 l

EVPS JOB PERFORMANCE MEASURE JPM QUESTION #2 What action would be required if, during MODE 4 operation, heat tracing was lost on the piping on the outlets of the boric acid tanks resulting in piping temperature reading of 62*F7 (Assume both boric acid tanks are affected and auxiliary building ambient air temperature is 59'F.)

OPEN REFERENCE ANSWER:

Restore to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be borated to a shutdown margin equivalent to at least 1%

AK/K within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the flowpath to operable status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Time Allotted: 5 minutes KA#: 004 K6.10 /3.1 l

Objective: LP SQS-7.1 OBJ-12

Reference:

T.S. 3.1.2.2 ,

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J 1CR-NoI BVPS Rev. 0 1

i

BVPS JOB PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #2 What action would be required if, during MODE 4 operation, heat tracing was lost on the piping on the I outlets of the boric acid tanks resulting in piping temperature reading of 62*F7 (Assume both boric acid tanks are affected and auxiliary building ambient air temperature is 59'F.)

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1CR-No1 BVPS Rev. O I

RTL #A5.640E -DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual l

I OJT CHECKLISI/JPM COVER PAGE PROGRAM TITLE: Licen: sed Operator Training SUBDIVISION: On-the -Job Training 1

I OJT CHECKLIST /JPM TITLE: Depressurize RCS to Backfill 1 JPM NO'.: ICR-N02 l

COMPUTER COD.El N/A i

Revision No. Date Revision No. Date

=

?

PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee Revision 9

____ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ . _ .J

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET .

DOCUMENT TITLE:1CR-N02. Deoressurize RCS to Backfill Revision ADoroval No. Brief Description Revised by: Signature Date I

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Revision 9

R BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: ICR-N02 Rev: O System #: 010 Faulted: X JPM

Title:

Depressurize RCS to Backfill K/A

Reference:

010 A4.03 / 3.8 Task ID #:3010040601 JPM Designation: O NO O RO x SRO JPM Application: X NRC X Initial Exam O Training Evaluation Method LOCATION TYPE O Perform O Plant Site O Training O Simulate x Simulator O Annual Requal. Exam O Classroom O OJT l

@ Initial Operator Exam Administered By: O Other: j O Bv-T I O NRC O Other:

Evaluation Results Performer: Name: Employee No:

Results O SAT Time (minutes)

O UNSAT* Allotted: 10 Actual:

Time Critical: 0 Yes x No

  • Comments (Required for UNSAT Evaluation):

r Evaluation Results O Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

i Question #1 5 0 0 l

Employee No:

Question #1 5 O O Employee No:

  • Comments (Required for UNSAT Evaluation) :

Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9

f RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE *

.w Read:

Task: Depressurize RCS to Backfill INITIAL A steam generator tube rupture has occurred on CONDITIONS *, le , resulting in a reactor trip and safety injection, E-3, Steam Generator Tube Rupture, has

-been completed and ES-3.1, Post SGTR Cooldown Using Backfill, is in progress.

INIT. CUE: Your supervisor directs you to depressurize the RCS to backfill from the ruptured SG by performing ES-3.1, step 9.

At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

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Revision 9

RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: 1CR-N02 JPM TITLE: Depressurize RCS to Backfill RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate (perform) the task Depressurize RCS to Backfill.

INIT. CONDITIONS: A steam generator tube rupture has occurred on the 1C SG, resulting in a reactor trip and safety injection, E-3, Steam Generator Tube Rupture, has been completed and ES-3.1, Post SGTR Cooldown Using Backfill, is in progress.

TASK STAN.: Backfill initiated in accordance with ES-3.1, step 9.

INIT. CUE: Your supervisor directs you to depressurize the RCS to backfill from the ruptured SG by performing ES-3.1, step 9.

REFERENCES:

10M-53A.1.ES-3.1, Issue 1B, Rev. 4 TOOLS: NONE HANDOUT: 10M-53A.1.ES-3.1, Post SGTR Cooldown Using Backfill.

I Revision 9

RTL #AS.635.J i

! NUMBER TITLE ICR N02 Depressurize RCS to Backfill I

1 STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" Dr Unsat.)

Evaluator Setup: -Initialize Simulator to IC #73.

Run File JPM2

[OVR PO6049D=1)

[OVR PO6049C=2]

START TIME:

1. Use Pressurizer Spray Valves. 1.1 Candidate determines that RCPs are not running (normal spray valves are not available.).

1 COMMENTS:

2.C Use auxiliary spray. 2.1 Candidate locates control switch for MOV-ICH-311, 2.2 Candidate places control switch for MOV-lCH-311 in the OPEN position.

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RTL CA5.635.J l

l NUMBER TITLE 1 ICR N02 Depressurize RCS to Backfill STEP STANDARD

("C" denotes critical step) - (Indicate "S" for Sat. or "U" for Unsat.)

2.3.C Candidate detennines that MOV-lCH-3 t l failed to open.

COMMENTS:

3.C Use Pressurizer PORV. 3.1 Candidate locates the control switch for [PCV-IRC-455C.

455D, or 456].

3.2.C Candidate takes control switch for [PCV-lRC-455C,455D, or 456] to the OPEN position.

3.3 Candidate venfies [PCV-lRC-455C,455D, or 456) open by verifying the red indicating light is on and the green indicating light is off and RCS pressure decreasing.

COMMENTS:

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4. Turn on Pressurizer Heaters. 4.1 Candidate locates the control switches for Pressurizer Heaters.

1 Page 2 of 4 Revision: 1 i

RTL #AS.635)

NUMBER TITLE ICR N02 Depressurize RCS to Backfill STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

4.2 Candidate takes control switches for Pressurizer Heaters to the ON position.

4.3 Candidate verifies heaters energized by verifying the red indicating lights are on.

COMMENTS:

5.C Maintain RCS subcooling. 5.1 Candidate deterniines the RCS subcooling requirement of Attachment 6A.

EVALUATOR NOTE: Candidate should have performed action prior to opening PORV.

5.2 Candidate monitors ICCM to determine RCS subcooling .

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RTL #AS.635.J NUMBER TITLE ICR-N02 Depressurize RCS to Backfill STEP STANDARD

("C" denotes critical step) (Indicate *S" for Sat. or "U" for Unsat.)

5.3.C Candidate closes [PCV-1RC-455C,455D, or 456] such that I subcooling is inaintained greater than requirement of attachinent l l

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1 COMMENTS:

' EVALU ATOR NOTE: Closing the PORV the first tinue completes the JPM.

STOP TIME I

i Page 4 of 4 Revision: 1

BVPS JOB PERFORMANCE MEASURE JPM QUESTION #1 What additions.1 precaution is required during backfill operation when no RCPs are running?

l OPEN REFERENCE ANSWER:

It is necessary to start a RCP in an unaffected loop prior to starting the RCP in the affected loop.

Time Allotted: 5 minutes KA#: EPE 038 EK1.03 /4.2 Objective: LP-SQS-53.3 OBJ-4

Reference:

OM 53B.4.ES 3.1 l

Comments:

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ICR-N02 BVPS Rev. O

BVPS JOB PERFORMANCE MEASURE

  • Tills SIIEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #1 What additional precaution is required during backfill operation when no RCPs are mnning?

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ICR-Not BVPS Rev. 0 l

1 _ _ _ - _ _ - - - -

l OVPS JOB PERFORMANCE MEASURE i

JPM QUESTION #2 j Explain the adverse affects that could occur if, during backfill operations, the ruptured steam generator level were to be lowered below the minimum allowed value.

OPEN REFERENCE ANSWER: -

Iflevel is lowered to txiow tie tops of the tubes, the cooler RCS water could rapidly collapse the stagnant I steam bubble in tic ruptured SG. This would cause SG pressure to drop and break flow to increase.

Time Allotted: 5 minutes KA#: EPE 038 EK3.06 / 4.5 I Objective: LP-SQS-53.3 OBJ - 3

Reference:

OM 53B.4.ES-3.1 Comments:

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ICR-N02 I BVPS Rev. 0

7_

BVPS JOB PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #2 Explain the adverse affects that could occur if, during backfill operations, the ruptured steam generator level were to be lowered below the minimum allowed value.

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CR. N02 BVPS Rev. 0

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r___________ _ _ _ _ ___ _ _ _ _

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual I

l OJT CHECKLIST /JPM COVER PAGE l PROGRAM TITLE: Licensed Operator Training I

SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Establish RHR System Flow JPM NO.: 1CR-062 COMPUTER CODE: N/A Revision No. Date Revision No. Date 1

PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee i

f Revision 9

l l RTL #A5.640E. DUQUESNE LIGHT COMPANY l Nuclear Power Division l Training Administrative Manual f

l LESSON PLAN AND OJT REVISION APPROVAL SHEET l

DOCUMEET TITLE: 1CR-062. Establish RHR System Flow Revision Acoroval No. Brief Description Revised by: Signature Date f

l Revision 9

BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: ICR-062 Rev: 9 System #: 005 Faulted: O JPM

Title:

Establish RHR System Flow K/A

Reference:

005 A4.01 /3.4 Task ID #:0050030101 JPM Designation: O NO O RO @ SRO

( JPM Application: X NRC X Initial Exam O Training Evaluation Method LOCATION TYPE O Perform O Plant Site O Training O Simulate x Simulator O Annual Requal. Exam O Classroom 0 oJT

@ Initial Operator Exam Administered By: O Other:

O av-T O NRC O Other: l

'M Evaluation Results Performer: Name: Emplo(ee No:

Results O SAT Time (minutes) ,

O Allotted: 20 Actual: 1 uNSAT*

Time Critical: 0 Yes x No j

  • Comments (Required for UNSAT Evaluation):

Evaluation Results O Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 5 0 0 Employee No:

Question #1 5 0 0 Employee No:

  • Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9

l RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • Read:

Establish RHR System Flow Task.

INITIAL Plant pressure is approximately 350 psig; plant CONDITIONS,

  • temperature is approximately 325*F; RHR system startup checks have been completed through step D. of 10M-4.A, Residual Heat Removal System Startup (Plant Cooldown)and operation. 1 i

INIT. CUE: Your supervisor directs that you establish an RCS cooldown using both RHR pumps by completing steps E.1 through E.8 of 10M-4.A.

At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

Point to any indicator or component. you verify or check and announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

Revision 9

1 RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: 1CR-062 JPM TITLE: Establish RHR System Flow RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to perform the task Establish RHR System F. ,vt.

INIT. CONDITIONS: Plant pressure is approximately 350 psig; plant temperature is approximately 325 F; RHR system startup checks have been completed through step D. of 10M-4.A, Residual Heat Removal System Startup (Plant Cooldown)and operation.

TASK STAN.: Both RHR pumps in operation with flow established through the RHR heat exchangers and RCS cooldown established.

INIT. CUE: Your supervisor directs that you establish an RCS cooldown using both RHR pumps by completing steps E.1 through E.8 of 10M-4.A.

REFERENCES:

10M-10.4.A, Issue 4, Revision 10 TOOLS: NONE HANDOUT: 10M-4.A, Residual Heat Removal System l

Startup (Plant Cooldown)and operation  !

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i j RTL CAS 635J NUMBER TITLE l

1CR-062 Establish RHR Flow l

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat or "U" for Unsat.)

l l Evaluator Setup: -Initialize Simulator to IC 76. ,

Remove yellow tags from BB-A and ensure RHR recorder is energized. _

START TIME:

\

Candidate locates and reviews IOM-10.4.A. j EVALUATOR CUE: Provide candidate with prepared copy of IOM 10.4.A.

1.C Open RHS Lcop Stop Valves. 1. Candidate locates control switch for MOV-IRH 720A.

1.2.C Candidate places control switch for MOV lRH-720A in the OPEN position.

1.3 Candidate verifies MOV-IRH-l 720A in the open position by verifying the red light is lit and the green light is dark.

1.4 Candidate locates control switch for MOV-IRH-720B.

1.5.C Candidate places control switch for MOV-lRH-720B in the OPEN position.

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I' PageIof5 Revision: I

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l RTL CAS.635.J l

t NUMBER TITLE ICR-062 Establish RHR Flow STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

1.6 Candidate verifies MOV-lRH-720B in the open position by verifying the r d light is lit and the green light is dark.

COMMENTS:

l EVALUATOR CUE: It is not necessary to perform l IOST-10.1 at tius time. l l

l 2.C Start the I A RHR pump. 2.1 Candidate locates the control I switch for 1RH-P 1 A.

2.2.C Candidate places the control 1 switch for IRH-P-1 A in the l START position.

2.3 Candidate verifies IRH-IP-I A started by observing pump amps and breaker indicating lights.

COMMENTS:

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l Page 2 of 5 Revision 1

l RTL CAS.6353 NUMBER TITLE ICR-062 Establish RHR Flow STEP STANDARD

! ("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

l 1.6 Candidate verifies MOV-1RH-720B in the open position by verifying the red light is lit and the green light is dark.

l l COMMENTS:

EVALUATOR CUE: It is not necessary to perfonn IOST-10.1 at this time.

l 2.C Start the I A RHR pump. 2.1 Candidate locates the control l switch for 1RH-P-1 A.

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2.2.C Candidate places the control switch for 1RH-P-1 A in the START position.

l 2.3 Candidate verifies IRH-P-I A

! started by obsening pump amps and breaker indicating lights.

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t l COMMENTS:

1 Page 2 of 5 Resision: 1

l l' l RTL CA5.635.J l i

l NUMBER TITLE i

ICR-062 Establish RHR Flow l

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

5.C Slowly adjust RHR HX Bypass Flow 5.1 Candidate locates controller for Control Valve. MOV-lRH-605.

5.2.C Candidate slowly adjusts output until 7300-8000 gpm is indicated on F1-IRH-605.

EVALUATOR NOTE: Candidate may adjust flow controller in MANUAL or AUTO at tids time.

COMMENTS:

)

J 6.C Open RHR HX Flow Control Valve 6.1. Candidate locates controller for to initiate cooldown. MOV lRH-758.

G. I .C Candidate slowly opens MOV-1RH458 while obsening temperature change on TR-IRH-604.

l EVALUATOR NOTE: After flow has been i initiated, inform candidate that a 40*F/hr cooldown rate has be:n established.

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Page 4 of 5 Revision: I

I RTL #AS.635.J NUMBER TITLE ICR-062 Establish RHR Flow STEP STANDARD i

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

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j. 7. Inform supenisor that RHR flow 7.1 Candidate informs supervisor i has been established. t!wt RIIR flow has been I established.

l COMMENTS:

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l STOP TIME l

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Page 5 of 5 Revision: 1 L' . - --

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DVPS JOB PERFORMANCE MEASURE I

JPM QUESTION #1 l

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Assume the " Heat Exchanger Bypass Valve", MOV-IRH-605 is operating in manual. Explain how MOV.

1RH-605 would have to be adjusted if the cooldown rate of the RCS was increased using RHR ficw.

I CF OSED REFERENCE ANSWER:

As the operator increase cooldown rate by opening the heat exchanger outlet valve, MOV 1RH-758, MOV-IRH-605 will need to throttled to maintain total system flow constant.

Time Allotted: 5 minutes KA#: 005 A1.02 / 3.4 Objective: LP-SQS-10.1 OBJ 5

Reference:

OM-10.1.C I

l Comments:

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ICR-062 BVPS Rev. O l

E______--_-_-_--.--_--____

GYPS JO3 PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #1 Assume the " Heat Exchanger Bypass Valve", MOV-!RH405 is operating in manual. Explain how MOV.

IRH405 would have to be adjusted if the cooldown rate of the RCS was increased t. sing RHR flow.

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I ICR-062 BVPS Rev. 0

BVPS JOB PERFORMANCE MEASURE l

JPM QUESTION #2 l

A loss of all RHR flow has occurred 12 days following plant shutdown. What is the expected boiloff rate of the RCS due to decay heat?

OPEN REFERENCE ANSWER:

43 - 47 gpm Time Allotted: 5 minutes KA #: APE 025 AA1.02 3.9 Objective: LP-SQS-10.1 OBJ-9

Reference:

AOP 1.10.1 Attachment 3 Comments:

1 1CR-062 BVPS Rev. 9

l EVPS JOB PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #2 A loss of all RHR flow has occurred 12 days following plant shutdown. What is the expected boiloff rate of the RCS due to decay heat?

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t-ICR-062 BVPS Rev. 0

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE l PROGRAM TITLE: Licensed Operator Training t

SUBDIVISION: On-the-Job Training l

OJT CHECKLIST /JPM TITLE: Verify Containment Spray JPM nom: ICR-NO3 COMPUTER CODE: N/A Revision No. Date Revision No. Date l

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PREPARED BY: DATE:

l APPROVED FOR ,

IMPLEMENTATION: DATE ,

Director, Operations Training, l or Designee i Revision 9 L______________

RTL #AS.640E DUQUESNE LIGHT COMPANY

Nuclear Power Division i Training Administrative Manual LESSON PI# AN AND OJT REVISION APPROVAL SIIEET l

DOCUMENT TITLE:1CR-NO3, Verify Containment Sorav Revision Annroval No. Brief Description Revised by: Signature Date 4

Revision 9

BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: ICR-NO3 Rev: O System #: 026 Faulted: X JPM

Title:

Verify Containment Spray K/A

Reference:

026 A4.01 / 4.3 Task ID #:3010010601 JPM Designation: O NO RO x SRO JPM Application: @ NRC X Initial Exam Training i g '

Evaluation Method LOCATION TYPE O Perform Plant Site O Training O Simulate E Simulator Annual Requal. Exam Classroom OJT

@ Initial Operator Exam Administered By: Other:

BV-T .

NRC Other:

I Evaluation Results Performer: Name: Employee No:

Results O SAT Time (minutes)

UNSAT* Allotted: 15 Actual:

Time Critical: Yes E No

  • Comments (Required for UNSAT Evaluation):

1 i

haluation Results O check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

l Observer 4: Name Employee No:

l Time (minutes) Results l Question ID Allotted Actual SAT UNSAT*

Question #1 5 0 Employee No:

Question #1 5 Employee No:

  • Comments (Required for UNSAT Evaluation):

Evaluator (Print): . Organization:

Evaluator Signature Date:

Revision 9

RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • Read:

Task: Verify Containment Spray INITIAL A major transient has occurred resulting in a CONDITIONS: reactor trip and safety injection. EOP E-0, Reactor Trip or Safety In]ection, is in progress at this time. Prior to the transient, the plant was operating at 100% power with all systems in NSA.

INIT. CUE: Your supervisor directs you to perform step 15 of E-0, Reactor Trip or Safety Injection.

At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

Revision 9

RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: ICR-NO3 1

l JPM TITLE: Verify Containment Spray RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate (perform) the task Verify Containment Spray.

INIT. CONDITIONS: A major transient has occurred resulting in a reactor trip and safety injection. EOP E-0, Reactor Trip or Safety Injection, is in progress at this time. Prior to the transient, the plant was operating at 100%

power with all systems in NSA.

TASK STAN.: Containment Isolation Phase B and Containment Spray manually aligned in accordance with E-0.

INIT. CUE: Your supervisor directs you to perform step 15 of E-0, Reactor Trip or Safety Injection.

REFFPENCES: 10M-53A.1.E-0, Issue 1B, Rev. 5 10M-53A.1.1-E, Issue 1B, Rev. 3 TOOLS: NONE HANDOUT: 10M-53A.1.E-0, Reactor Trip or Safety Injection.

l Revision 9

NUMBER TITLE ICR-NO3 VERIFY CONTAINMErff SPRAY l

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STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

l l Evaluator Setup: -Initialize Simulator to IC 82.

Do NOT run SIMIC File NOCIB lOVR]

[P01008A=2]

[P01009A=2l

[Pb101I A=2l

[PO1013 A=2l START TIME:

Candidate locates and reviews E-0, Reactor Trip or Safety Injection.

EVALUATOR CUE: Provide candidate with prepared copy of E-0.

1. Check CIB and Containment Spray 1.1 Candidate locates annunciator Status. A172 " CONTAINMENT ISOLATION PHASE B" and verifies that it is not lit..

1.2 Candidate locates [PR-lLM-100A] and determines that it is indicating > 8 psig.

COMMENTS:

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I RTL #AS.635.J l

t NUMBER TITLE i

ICR NO3 VERIFY CONTAINMEbtr SPRAY 1

l 1

l STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.) ,

2. Verify CIB initiated. 2.1 Candidate locates and evalua:es indicating light.; with BLUE CIB mark and determines that they  ;

are not lit.

I COMMENTS:

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3. Manually initiate CIB. 3.1 Candidate locates CIB pushbuttons.

3.2.C Candidate depresses both CIB pushbuttons for each train.

3.3 Candidate locates and evaluates indicating lights with BLUE CIB mark and determines that they are not lit.

COMMENTS: l l

l EVALUATOR CUE: When candidate begins to re-align equipment inform him: "Your supervisor directs you to use EOP Attachment 1-E when i

perfonning manual aligmnent. Provide candidate with copy of IOM 53 A.I.1-E.

1 Page 2 of 6 Revision I

RTL #AS.635J :

NUMBER TITLE ICR NO3 VERIFY CONTAINMENT SPRAY STEP STANDARD -

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

4. Manually Align Equipment. 4.1.C Candidate locates control switch for TV lCC-103A and takes it to the close position.

4.2 Candidate verifies TV-ICC-103 A is closed by verifying the red indicatinglight is out and the green indicating light is lit.

4.3.C Candidate locates control switch for TV-lCC-105E2 and takes it to the close position.

4.4 Candidate verifies TV-1CC-105E2 is closed by verifying the red indicating light is out and the green indicating light is lit.

4.5.C Candidate locates control switch for TV-lCC-107E2 and takes it to the close position.

4.6 Candidate verifies TV 1CC-107E2 is closed by verifying the red indicatinglight is out and the green indicating light is lit.

4.7.C Candidate locates control switch for TV-lCC-Il0E2 and takes it to the close position.

4.8 Candidate verifies TV-1CC-110E2 is closed by verifying the red indicatinglight is out and the green indicating light is lit.

4.9.C Candidate locates control switch for TV-ICC-!!0F2 and takes it to the close position.

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RTL #A5.6353 1 NUMBER TITLE ICR NO3 VERIFY CONTAINMENT SPRAY l

i STEP STANDARD

("C" denotes critical acp) (Indicate "S" for Sat. or "U" for Unsat.)

4.10 Candidate verifies TV-ICC-110F2 is closed by verifying the red indicating light is out and the green indicating light is lit.

4. l l.C Candidate locates control switch for TV ICC-103B and takes it to the close position. -

4.12 Candidate verifies TV-ICC-103B is closed by verifying the

! red indicating light is out and the green indicating light is lit.

4.13.C Candidate locates control switch for TV-lCC-105D2 and takes it i to the close position.

l 4.14 Candidate verifies TV ICC-105D2 is closed by verifying the red indicating light is out and the green indicating light is lit.

4.15.C Candidate locates control witch for TV-lCC-107D2 and takes it to the close position.

4.16 Candidate verifies TV-ICC-107D2 is closed by verifying the red indicating light is out and the green indicating light is lit.

4.17.C Candidate locates control switch for TV-lCC-Il0F1 and takes it to the close position.

1 4.18 Candidate verifies TV-ICC-110FI is closed by verifyin,g the red indicating light is out and the green indicating light is lit.

l Page 4 of 6 Revision 1

RTL #A5.635J NUMBER TITLE ICR-NO3 VERIFY CONTAINMENT SPRAY l

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

4.19.C Candidate locates control switch for TV-lCC-103C and takes it to the close position.

4.20 Candidate verifies TV ICC-103C is closed by verifying the red indicating light is out and the green indicating light is lit.

4.21.C Candidate locates control switch for TV ICC-Ill Al and takes it to the close position.

4.22 Candidate verifies TV-1CC-1II A1 is closed by verifying the red indicating light is out and the green indicating light is lit.

4.23.C Candidate locates control switch for TV lCC IllD2 and takes it to the close position.

4.24 Candidate verifies TV-ICC-1IID2 is closed by verifying the red indicating light is out and the green indicating light is lit.

4.25.C Candidate locates control switch for TV-ICC-100A and takes it to the close position.

4.26 Candidate verifies TV-1CC-100A is closed by verifying the i red indicating light is out and the green indicating light is lit.

4.27.C Candidate locates control switch for TV-1CC-103 Al and takes it to the close position.

Page 5 of 6 Revision: I

RTL #A5.635.J l

NUMBER TITLE

! ICR-NO3 VERIFY CONTAINMElfr SPRAY 1

1 STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat or "U" for Unsat.)

4.28 Candidate verifies TV-lCC-103 A1 is closed by verifying the red indicating light is out and the green indicating light ic lit.

4.29.C Candidate locates control switch for TV-lCC-105El and takes it to the close position.

4.30 Candidate verifies TV-lCC-105El is closed by verifying the red indicating light is out and the green indicating light is lit.

EVALUATOR CUE: Inform candidate that another operator will be performing the rest of the alignment. This completes the JPM.

COMMENTS:

STOP TIME l

1 Page 6 of 6 Revision: 1 i

DVPS JOB PERFORMANCE MEASURE JPM QUESTION #1 Describe the flow path that would be used to supply the suction of the iIHSI pumps if the LHSI were to fail during the Recirculation phase following a Loss of Coolant Accident

' OPEN REFERENCE ANSWER:

The outside recirc spray pumps would be aligned through RS 157,158,159 & 160 to SI-MOV563A and SI MOV563B to supply the HHS! pump suctions. [ Valve numbers are not required. Candidate may trace flow path on drawing or simply explainj Time Allotted: 5 minutes KA#. 026 K1.01/4.2 Objective: 1.P-SQS-53.3 OBJ-6 Referene:: OM Figure 48-100 or IOM 53A.I.1 J. Issue B, Rev 3.

Comments:

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BVPS JOB PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #1 Describe the flow path tlunt would be used to sapply tim suction of tie HHSI pumps if the LHSI were to fait during the Recirculation phase following a Loss of Coolant Accident l

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BVPS Rev. 0

BVPS JOB PERFORMANCE MEASURE JPM QUESTION #2 Asstane that a large break LOCA has occurred resulting in a reactor trip, St. CI A and CIB. Explain which automatic actions would not occur if upon receipt of the RWST Low-Low level signal, the Cut Back Contro! Valve MOV-lQS-103A failed to close?

OPEN REFERENCE ANSWER:

Chemical Injection Pump IQS-P-4C would not stop as intended on Low-Low RWST level.

lf Jote, the purpose of the question is to force candidate to reference logic diagram or OM.]

Time' Allotted: 5 minutes KA#: 026 K4.08 4.3 Objective: LP-SQS 13.1 OBJ-5

Reference:

Dwg No. 8700-LSK-29-1D or IOM 13.1.D. ISS 4, Rev.1 l

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BVPS JOB PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUES ^lJON #2 Assume that a large break LOCA has occurred resulting in a reactor trip. SI, CIA and CIB. Explain how -

the automatic operation of the quench and recirc spray systems would be affected if, upon receipt of the RWST Low-Low level signal Cut Back Control Valve MOWlQS 103 A failed to close?

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RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual

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OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training l

SUBDIVISION: On-the-Job Trainirg OJT CHECKLIST /JPM TITLE: Perform a Hot Bus Transfer JPM NO.: ICR-023 COMPUTER CODE: N/A ,

I Revision No. Date Revision No. Date PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: D_6TI:

Director, Operations Training, or Designee l

l Revision 9

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual

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l LESSON PlaAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: 1CR-023, Perform a Hot Bus Transfer Revision Acoroval No. Brief Description' Revised by: Signature Date 1

Revision 9 i

i HEAVER VALL.EY_J9a E Bf0E)1ANCE M.EASURE EVALUATOR COVER SHEET 1 l

4 JPM Number: 1CR-023 Rev: 7 System #: 062 Faulted: O l JPM

Title:

Perform a Het Bus Transfer l l

K/A

Reference:

006 A4.01 /3.1 Task ID #:062AAA0101 JPM Designation: NO O RO x SRO I JPM Application: @ NRC E Initial Exam Training

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,,- 3: ! ;; , . . . ',, ;, f  :.y . y j 1

Evaluation Mg,thod LOCATION TYPE j O Perrorm O Plant Site O Training l Simulate @ Simulator O Annual Requal. Exam l 0 Classroom O OJT X Initial Operator Exam j Administered By: Other l

BV-T NRC Other:

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.':; b ', . ;  ;;;.

Evaluation Results Performer: Name: Employee No: .,

Results O SAT Time (minutes) ,

O uNSAT* Allotted: 20 Actual: l Time Critical: O yes @ No

  • Comments (Required for UNSAT Evaluation):

. ., . 4 Eya_luation Results check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Resulta Question ID Allotted Actual SAT UNSAT*

Question #1 p D Employee No:

Question #.1 5 Employee No:

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  • Comments (Required for UNSAT Evaluation):

yo. .,

Evaluator (Print): _

Organization-Evaluator Signature Date:

Revision 9

RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • Read:

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Task: lPerformaHotBusTransfer 1

INITIAL The 4KV Busses are being transferred to the System Station Service Transformers in CONDITIONS:

preparation for plant shutdown. j l

I INIT. CUE: Your supervisor directs you to transfer 4KV Bus 1D to the System Station Service Transformer using 10M-36.4.B, 4KV Station Service System Shutdown.

l At JPM.

this time, ask the evaluator any questions ~you have on this When satisfied that you understand the assigned task, announce ]

"I am now beginning the JPM". 1 Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task has'been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

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RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: 1CR-023 JPM TITLE: Perform a Hot Bus Transfer j RECOMMENDED l STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to perform the task Perform a Hot Bus Transfer.

INIT. CONDITIONS: The 4KV Busses are being transferred to the System Station Service Transformers in preparation for plant shutdown.

TASK STAN.: 4KV Bus 1D transferred to the System Station Service Transformer in accordance with 10M-36.4.B, 4KV Station Service System Shutdown.

INIT. CUE: Your supervisor directs you to transfer 4KV Bus ID to the System Station Service Transformer using 10M-36.4.B, 4KV Station Service System Shutdown.

REFERENCES:

10M-36.4.B, Issue 4, Rev. 2 TOOLS: NONE HANDOUT: 10M-36.4.B, 4KV Station Service System Shutdown Revision 9

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RTL #AS.635J NUMBER TITLE ICR-023 Perform a Hot Bus Transfer STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

Evaluator Setup: -Initialize Simulator to IC #79.

START TIME:

1. Candidate locates procedure and step.

Evaluator Cue: Provide candidate with copy IOM-36.4.B.

1.1 Candidate locates IOM-36.4.B step A.4 l

COMMENTS:

2. Monitor USST ID voltages. 2.1 Candidate locates 4KV Bus ID voltmeter.

2.2 Candidate locates 4KV Bus D Selector Switch.

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RTL #A5.635J NUMBER TITLE ICR423 Perfonn a Hot Bus Transfer STEP STANDARD

("C" denotes critical step) (Indicate 'S" for Sat. or "U" for Unsat.)

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2.3 Candidate turns bus 4KV Bus ID Selector Switch as necessary -

while monitoring USST voltages.

COMMEt(TS:

)

3. Monitor SSST IB voltages. 3.1 Candidate locates 4KV common voltmeter.

3.2 Candidate locates SSST IB Selector Switch.

3.3 Candidate turns bus 4KV Bus ID Selector Switch as necessary while monitoring SSST voltages.

I COMMENTS:

l Evaluator Note: Candidate may opt to adjust voltage using Lower Raise & Auto switch on VB-C.

This not required, but may be performed.

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RTL #A5.635.J NUMBER TITLE ICR 023 Perform a Hot Bus Transfer .

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

4. Check Live Bus Transfer Switch in 4.1 Candidate locates Live Bus ON position. Transfer Switch.

4.2 Candidate verifies Live Bus Transfer Switch in ON position.

i COMMENTS:

5.C Close 4KV ACB 341B. 5.1 Candidate locates control switch for ACB 341B.

5.2.C Candidate places control switch  !

I for ACB 341 in the CLOSE .

position.

COMMENTS:

l 6.C Open ACB 34ID. 6.1 Candidate locates 4KV Bus ID Transformer IB ammeter.

6.2 Candidate verifies ammeter deflects to indicate load is being transferred.

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RTL #AS.635.J NUMBER TITLE ICR-023 Perfonn a Hot Bus Transfer STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

6.3 Candidate locates control swith for ACB 341D.

6.4.C Candidate places control switch for ACB 341D in the TRIP position.

COMMENTS:

Evaluator Cue: No other busses are being transferred.

7.C Place Live Bus Transfer Switch in 7.1 Candidate locates Live Bus the OFF position. Transfer Switch.

7.2.C Candidate places the Live Bus Transfer Switch in the OFF position.

COMMENTS:

8.C Verify Bus ID 4160Vlewer Raise 8.1 Candidatelocates Bus 1D and Auto Switch in Auto Position. 4160V Lower Raise and Auto Switch.

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--_ _____ _ ___ ____ ____________________ _ _ _J

RTL #AS.635.J NUMBER TITLE ICR-023 Perform a Hot Bus Transfer STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

8.2.C Candidate checks or places the Bus ID 4160V Lower Raise and Auto Switchin Auto (pullout)

Position.

COMMENTS:

EVALUATOR NOTE: The canidate may check voltages prior to reporting completion of the JPM.

9. Report that bus transfer is complete. 9.1 Candidate reports to supenisor that Bus ID transfer is complete.

COMMENTS:

1 STOP TIME  ;

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BVPS JOB PERFORMANCE MEASURE I

JPM QUESTION #1 Explain why the loss of each of the 4 KV loads supplied by 4KV Bus IB would or would not lead to a reactor trip, with the plant operating at 100*/. full power. Assume all systems are in the Normal System -

Alignment (NS A) prior to the loss of each load and that no operators actions are taken.

OPEN REFERENCE ANSWER:

less of FW-P-1 A would cause reactor trip due to loss of feed.

Loss of CN P-1 A would cause reactor trip due to loss of feed.

Loss of RC-P-1B would cause reactor trip on low flow.

Loss of CT P 1B could cause turbine trip on low vacuum. This could cause the reactor to trip.

Time Allotted: 5 minutes KA #: 062 K2.01/ 3.4 Objective: LP-SQS-36.1

Reference:

OM Figure 36.6 l

Comments:

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ICR-023 BVPS Rev. O

DVPS JOB PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #I Explain why the loss of each of tic 4 KV loads supplied by 4KV Bus IB would or would not lead to a reactor trip, with the plant operating at 100% full power. Assume all systems are in the Normal System Alignment (NS A) prior to the loss of each load and that no operators actions are taken.

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BVPS JOB PERFORMANCE MEASURE JPM QUESTION #2 Explain how to defeat the Bus I AE undervoltage (UV) trip when performing actions to establish power to Bus ! AE from the BV 2 cross-tic during a station blackout.

OPEN REFERENCE ANSWER:

The undervoltage trip is defeated by removing 125 VDC control power. (Opening breaker in cubicle ES Al.

Time Allotted: 5 minutes KA#: 062 A2.05 / 3.3 Objectise: LP-SQS 36.1 OBJ 3.c

Reference:

lOM 53A.I.2-M-A3, ISS IB, REV 2 Comments:

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BVPS JOB PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • I JPM QUESTION #2 -

Explain how to defeat the Bus 1 AE undervoltage (UV) trip when performing actions to establish power to l Bus l AE from the BV-2 cross-tie during a station blackout.

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RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE '

PROGRAM TITLE: Licensed Operator Training '

SUBDIVISION: On-the-Job Training OJT CHECKLIET/JPM TITLE: Respond to Feed Control Failure JPM NO : ICR-N04 COMPUTER CODE: N/A .

l Revision No. Date Revision No. Date I'

PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, l or Designee Revision 9

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual

. LESSON PLAN AND OJT REVISION APPROVAL SHEET l

l DOCUMENT TITLE:1CR-N04, Respond to Feed Control Failure l

1 Revision .

Acoroval No. Brief Description Revised by: Signature Date l

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BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: ICR-N04 Rev: O system #: 016 Faulted: O JPM

Title:

Respond to Feed Control Failure 1 I

l K/A

Reference:

016 A2.01 / 3.1 Task ID #:Os90070101 JPM Designation: O NO O RO x sRO JPM Application: X NRC E Initial Exam O Training l Evaluation Method LOCATION TYPE D Perform O Plant site O Training O simulate x simulator O Annual Requal. Exam O Classroom O OJT X Initial Operator Exam Administered By: O Other:

O Bv-T O NRC 0 Other:

)

Evaluation Results Performer: Name: Employee No:

Results O SAT Time (minutes)

O uNsAT* Allotted: 15 Actual:

Time Critical: 0 Yes x po

  • Comments (Required for UNSAT Evaluation):

Evaluation Results O Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 s O O Employee No:

Question #1 s O O Employee No: l

  • Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization:

Evaluator signature Date:

Revision 9

RTL /AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GisEN TO CANDIDATE
  • Read:

l Task: lRespondtoFeedControlFailure i

I'NITIAL An event has occurred which has resulted in

! muldple annunciators associated with the feed

.ONDITIONS:

wate?/ control system. Prior to the event, the plart was operating at 100% power with all systems in NSA.

INIT. CUE: Your supervisor directs you to evaluate the ann'anciators and existing plant condition in order to determine and implement the appropriate j coriactive actions.

At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand *.he assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met, announce."I have completed the JPM". Then hand back this sheet to the evaluator.

i Revision 9

RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: ICR-N04 JPM TITLE: Respond to Feed Contiol Failure RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate (perform) the task Respond to Feed Control Failure.

INIT. CONDITIONS: An event has occurred which has resulted in multiple annunciators associated with the feed water control system. Prior to the event, the plant was operating at 100%

power with all systems in NSA.

TASK STAN.: Actions taken for instrument failure in accordance with 10M-24.4.IF.

INIT. CUE: Your supervisor directs you to evaluate the annunciators and existing plant condition in order to determine and implement the appropriate corrective actions.

REFERENCES:

10M-24.4.IF, Issue 4, Revision 2 TOOLS: NONE HANDOUT: 10M-24.4.IF, Instrument Failure Procedure, Attachment 2.

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1 NUMBER TITLE ICR N04 RESPOND TO FEED CONTROL FAILURE STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

l Evaluator Setup: -Initialize Simulator to IC 74.

Inunediately place the simulator in Freeze.

START TIME:

EVALUATOR CUE: Your supervisor directs you to evaluate annunciators and control board indications and to take the appropriate actions. " Inform me j when your are ready to begin taking action.

1. Evaluate plant conditions. 1.1 Candidate observes annunciators, SG level, feed flow, and steam flow indications.

1.2 Candidate diagnoses feedwater flow transmitter failure. I EVALUATOR NOTE: Candidate may review  ;

various annunciator response procedures or proceed I directly to the Instrument Failure procedure.

EVALUATOR NOTE: When candidate indicates that he/she is ready to begin, place the simulator in Run.  ;

! COMMENTS:

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RTL CA16353 NUMBER TITLE ICR N04 RESPOND TO FEED CONTROL FAILURE l

STEP STANDARD

(*C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

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2. Identify failed channel. 2.1 Candidate identifies FT-IFW-l 486 as the failed low (and controlling) channel.

l COMMENTS:

i 3.C Take manual control of feed 3.1 Candidate locates controller for regulating valve and stabilize FCV-lFW-488.

l 3.2.C Candidate transfers controller for FCV-lFW-488 to manuat 3.3.C Candidate adjusts controller for FCV-IFW-488 as necessary to stabilize steam generator.

COMhENTS:

EVALUATOR CUE: Your supervisor directs you to j perform the appropriate section of IOM-24.4.IF, i Instrument Failure. Provide candidate with IOM-24.4.!F.  ;

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RTL #AS.635.J

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NUMBER TITLE ICR N04 RESPOND TO FEED CONTROL FAILURE.

STEP STANDARD

("C* denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.) )

4. Select redundant flow transmitter. 4.1 Candidate locates the IB Feed Flow Signal Sel. Switch.

4.2.C Candidate selects the FM-486 position on the IB Feed Flow Signal Sel. Switch.

COMMENTS:

5.C Restore SG level to normal. 5.1.C Candidate adjusts controller for FC%1FW 488 as necessary to restore level to normal range.

1 COMMENTS:

6. Return feed control to automatic. 6.1 Candidate verifies level restored to normal and transfers FCV-IFW-488 to automatic.

COMMENTS: .

Page 3 of 4 Revision: I

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R~lL CA5.635J NUMBER TITLE ICR-N04 RESPOND TO FEED CONTROL FAILURE STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

7. Trip appropriate bistables. 7.1 Candidate requests that BS-488A and 488D be tripped.

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EVALUATOR CUE: Inform candidate that bistables have been tripped as requested.

COMME!RS:

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8. Report that corrective actions are 8.1 Candidate reports that corrective complete. actions are complete.

COMMENTS:

STOP TIME Page 4 of 4 Revision: I

BVPS JOB PERFOR.58.ANCE MEASURE JPM QUESTION #1 List the automatic actions which would have occurred if operator actions not been initiated in response to the failure which just occurred.

CLOSED REFERENCE ANSWER:

l At 75% levell o Main turbine trip.

o Feedwater Isolation

[o Main feed pumps trip.]

[o Feed Valves closej o [ Reactor Trip [due to turbine trip above P-9))

l Time Allotted: 5 minutes KA#: 035 A2.04 / 3.8 l Objective: LP-SQS-24.1 OBJ-5

Reference:

lOM-24.4.AAX l

l Comments:

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BVPS JOB PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #1 List the automatic actions which would have occurred if operator actions not been initiated in response to the failure w hich just occurred.

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BVPS JOB PERFORMANCE MEASURE t

JPM QUESTION #2 l Assume the i A steam generator narrow range levels are indicating 50%. What is tlie expected wide range level:

l A. At no load Tavg?

i l B. At 150*F?

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OPEN REFERENCE ANSWER:

A. 64 % - 68 %

l B. 84 % - 88 %

l I Time Allotted: 5 minutes l

KA #: 016 A3.02 / 2,9 Objective: 1/2 LP-ATA-5 OBJ-21

Reference:

OM Figure 2418 Conunents:

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l BVPS JOB PERFORMANCE MEASURE l

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  • TIIIS SIIEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #2 l

Assunic tlie l A stcain generator starrow range levels are iadicating 50%. What is the expected wide range lesci:

A. At no load Tavg?

B. At 150'F7 1

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BVPS Rev: 0

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training i

OJT CHECKLIST /JPM TITLE: Place Diesel Air Compressor in Service JPM NO.: IPL-N01 i

COMPUTER CODE: N/A l

Revision No. Date Revision No. Date l

l PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee l

Revision 9 i

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Training Administrative Manual l l

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LESSON PLAN AND OJT REVISION APPROVAL SHEET i

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DOCUMENT TITLE:1PL-N01. Place Diesel Air Comoressor in Service I

Revision Acoroval '

No. Brief Description Revised by: Signature Date l

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EVALUATOR COVER SilEET

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JPM Number: 1PL-N01 Rev: O System #: 079 Faulted: O JPM

Title:

Place Diesel Air Compressor in Service K/A

Reference:

2.1.20 / 4.2 Task ID #:790020101 JPM Designation: O NO O RO x SRO 1

U"M Application: X NRC X Initial Exam Training

.j Evaluation Method LOCATION TYPE Perform x plant Site O Training Simulate O Simulator Annual Requal. Exam O Classroom O OJT l E Initial Operator Exam I j

Administered By: O Other:

BV-T j NRC Other:

j Evaluation Results Performer: Name: Employee No:

Results SAT Time (minutes)

O UNSAT* Allotted: 20 Actual:

Time Critical: Yes X No

  • Comments (Required for UNSAT Evaluation):

Evaluation Results -

Check here if same as above Observer 1: Name: _ Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 5 0

Employee No:

Question /1 5 0

i Employee No:

  • Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9

(

RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET THIS SHEET TO BE GIVEN TO CANDIDATE

  • Read:

Task: _

Place Diesel Air Compressor in Service INITIAL A loss of electrical power has occurred, CONDITIONS: resulting in loss of the motor driven air compressors.

INIT. CUE: Your supervisor directs you to place the diesel driven air compressor in service and align its discharge to the station air receiver by performing 10M-34.4.L through step F3.

At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you underrtand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

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Revision 9 l

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RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: 1PL-N01 JPM TITLE: Place Diesel Air Compressor in Service l

RECOMMENDED STARTING LOCATION: CONTROL ROOM l- DIRECTIONS: You are to simulate (perform) the task Place Diesel Air Compressor in Service.

INIT. CONDITIONS: A loss of electrical power has occurred, resulting in loss of the motor driven air compressors.

TASK STAN.: Diesel driven air compressor placed in service in accordance with 10M-34.4.L.

INIT. CUE: Your supervisor directs you to place the diesel driven air compressor in service and align its discharge to the station air receiver by performing 10M-34.4.L through

! step F3.

REFERENCES:

10M-34.4-L Issue 4, Revision 1 TOOLS: NONE HANDOUT: 10M-34.4-L, Placing Diesel Air Compressor  !

in Service.

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I Revision 9

RTL #A5.635.J NUMBER TITLE 1PL-N01 Place Diesel Air Compressor in Service STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

START TIME EVALUATOR CUE: Provide candidate with IOM-34.4.L.

1. Review procedure and precautions 1.1 Candidate resiews procedureind and limitations. precautions and limitations.

EVALUATOR CUE: The air dryer has already

been removed from service.

l l COMMENTS:

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2. De-energize Diesel Air 2.1 Candidate locates trickle charger Compressor's Battery Trickle control switch.

Charger.

2.2 Candidate simulates placing control switch in OFF.

EVALUATOR CUE: The control switch is in the OFF position.

COMMEffTS: .

Page1of5 Revision: 1

RTL #A5.635.J NUMBER TITLE IPL N01 Place Diese! Air Compressor in Senice j l

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

3.C Place and hold Diesel Air 3.1 Candidate locates Selector Compressor's Selector Switch in the Switch.

Hold Position.

3.2.C Candidate simulates placing and  ;

holding Selector switch in the HOLD position.

EVALUATOR CUE: The selector switch is in the HOLD position.

COMMENTS:

4.C Depress the Diesel Air 4.1 Candidate locates the Start Compressor's Start Pushbutton. Pushbutton.

4.2.C Candidate simulates depressing the Start Pushbutton.

EVALUATOR CUE: The Start Pushbutton has been depressed. The diesel is starting, the diesel is running.

COMMENTS:

l Page 2 of 5 Revision: 1

RTL CAS.635.3 NUMBER TITLE IPL-N01 Place Diesel Air Compressor in Sersice STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

5.C Release the Start Pushbutton and 5.1 Candidate releases the Start Selector switch. Pushbutton.

EVALUATOR CUE: The Start Pushbutton has been released.

5.2 Candidate observes diesel oil pressure.

EVALUATOR CUE: Diesel oil pressure is rising.

Diesel oil pressure is > 15 psig.

5.3.C Candidate simulates releasing Selector switch aAer the oil pressure is greater than 15 psig.

EVALUATOR CUE: The Selector Switch has been released.

COMMENTS:

6.C ' Open the Diesel Air Compressor's 6.1 Candidate locates inlet shutter inlet shutter valve. valve.

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Page 3 of 5 Revision: I

RTL #AS.635.J NUMBER TITLE IPL-N01 Place Diesel Air Compressor in Senice STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

6.2.C Candidate simulates opendng inlet shutter valve.

EVALUATOR CUE: The inlet shutter valve is

, open.

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COMMENTS:

l 7.C Align Diesel Air Compressor to 7.1 Candidate locate' s [ISA-90).

Station Air Receiver.

7.2.C Candidate simulates opening

[ISA-90).

EVALUATOR CUE: [ISA-90] is open.  ;

7.3 Candidate locates [ISA-86).

7.4.C Candidate simulates opening i

[ISA-86].

EVALUATOR CUE: ilSA-86] is open.

7.5 CandidatelocatesDiesel Air Compressor's discharge valve.

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Page 4 of 5 Revision: 1

RTL #A5.635J NUMBER TITLE IPL-N01 Place Diesel Air Compressor in Senice l

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l STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

I 7.6.C Candidate simulates opening

, Diesel Air Compressor's discharge valve.

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EVALUATOR CUE: The Diesel Air Compressor's discharge valve is open.

l COMMENTS:

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EVALUATOR CUE: The remaining procedure l steps have been completed by another operator. j l

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8. Inform supenisor that the Diesel Air 8.1 Candidate infonns supenisor  !

Compressor is in senice. that the Diesel Air compressor is in service.

COMMEIRS:

i STOP TIME f

Page 5 of 5 Revision: I l

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EVPS JO3 PERFORMANCE MEASURE JPM QUESTION #1 Assume that a loss of station instrument air has occurred and that the diesel driven air compressor could not be started.

A. At what point should a emergency shutdown be ir.itiated?

B. At what point should the reactor be tripped?

OPEN REFERENCE ANSWER:

A. [ Station Air less than 100 psig] and unable to start air compressor.

B. Actuation of annunciation Al-56, *STEAMLINE STOP VALVE NOT FULLY OPEN' Time Allotted: 5 minutes KA#: APE 065 AA2.05 /4.1 Objective: LP-SQS-53C.1 OBJ-8 Referee::e: AOP 34.1, Issue 3A, Resision 3 Comments:

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l IPleN01 BVPS Rev: 0 L_________________________----------_--_----------_-----__-----

BVPS JOB PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #1 Assume that a loss of station instrument air has occurred and that the diesel driven air compressor could not be started.

A. At what point should a emergency shutdown be initiated?

B. At what point should the reactor be tripped?

l IPirN01 BVPS Rev: 0 l

BVPS JOB PERFORMANCE MEASURE JPM QUESTION #2 What affect would a loss of station instrument air have on the CVCS makeup control valves [FCV-lCH-Il3A,113B, ll4A, and 114B]?

OPEN REFERENCE ANSWER:

FCV-ICH-113 A, Boric Acid to Blender FCV, would fail open. FCV-lCH 113B,114 A, and ll4B would fail closed.

I Time Allotted: 5 minutes KA#: 078 K3.02 /3.6 Objective: LP-SQS-53C.1 OBJ-8

Reference:

AOP 1.34.1, Attachment 1, Issue 3 A, Revision 3 Comments:

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1 1PirN01 BVPS Rev: 0

BVPS JOB PERFORMANCE MEASURE

  • Tills SIIEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #2 What afTect would a loss of station instrument air have on the CVCS makeup control system?

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i 1PL-N01 BVPS Rev: 0

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual l

OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training i

SUBDIVISION: On-the-Job Training i

OJT CHECKLIST /JPM TITLE: Startup the Hydrogen Recombiners l

l JPM NO.: 1PL-017 COMPUTER CODE: N/A i

l Revision No. Date Revision No. Date PREPARED BY: DATE:

APPROVED FOR

l. IMPLEMENTATION: DATE:

Director, Operations Training, or Designee i

l Revision 9

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE:1PL-017. Startuo the Hydrocen Recombiners Revision Anoroval No. Brief Description Revised by: Signature Date 1

1 Revision 9 L_______________-_______._____________

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BEAVER VALLEY JOB PERFORMANCE MEASURE I EVALUATOR COVER SHEET I JPM Number: 1PL-017 Rev: 1 System #: 028 Faulted: O JPM

Title:

Startup the Hydrogen Recombiners K/A

Reference:

028 A4.01 /4.0 Task ID #:028BBB0104 JPM Designation: O NO O RO E SRO JPM Application: X NRC X Initial Exam O Training Evaluation Method LOCATION TYPE O Perform X Plant Site O Training O Simulate O Simulator O Annual Requal. Exam O Classroom O Oar E Initial Operator Exam Administered By: O Other:

O Bv-T .

O NRC D Other:

Evaluation Results l l

Performer: Name: Employee No:

Results O SAT Time (minutes)

O UNSAT* Allotted: 30 Actual:

Time Critical: O yes x No

  • Comments (Required for UNSAT Evaluation):

Evaluation Results O Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 7 0 0 Employee No:

Question #1 5 0 0 Employee No:

  • Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9

RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • Read:

Task: Startup the Hydrogen Recombiners

}

l INITIAL A reactor trip and safety injection have occurred ONDITIONS. due to a Loss of Coolant Accident. 10M-53.A.ES-1.3, Transfer to Cold Leg Recirculation, has been implemented. Hydrogen concentration in containment was obtained and is the equivalent to 2.4% in dry air, requiring the recombiners to be placed in service. All AC distribution systems are operable.

INIT. CUE: Your supervisor directs you to startup the Hydrogen Recombiners by performing 10M-46.4.A, Hydrogen Recombiner Startup.

At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as c'.irected the required task.

Point to any indicator or componen'. you verify or check and announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

Revision 9 i

RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: 1PL-017 JPM TITLE: Startup the Hydrogen Recombiners l

l RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate the task Startup the Hydrogen Recombiners.

INIT. CONDITIONS: A reactor trip and safety injection have occurred due to a Loss of Coolant Accident.

10M-53.A.ES-1.3, Transfer to Cold Leg Recirculation, has.been implemented.

Hydrogen concentration in containment was obtained and is the equivalent to 2.4% in dry air, requiring the recombiners to be placed in service. All AC distribution systems are operable.

TASK ETAN.: Hydrogen recombiner placed in service in accordance with 10M-46.4.A.

INIT. CUE: Your supervisor directs you to startup the Hydrogen Recombiners by performing 10M-46.4.A, Hydrogen Recombiner Startup.

REFT,RENCES: 10M-46.R.A, Issue 4, Revision 2 TOOLS: NONE HANDOUT: 10M-46.4.A, Hydrogen Recombiner Startup.

1 Revision 9

RTL #A5.635.J NUMBER TIT 8.E IPL-017 Startup the Hydrogen Recombiner STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

START TIME EVALUATOR CUE: Provide candidate with copy of lOM-46.4. A.

1. Contact Radeon. 1.1 Candidate contacts Radeon.

EVALUATOR NOTE: Candidate should be briefed by Radcon prior to entering controlled area.

COMMENTS:

2. Obtains Keys. 2.1 Candidate obtains keys SR/O.C.

and SR/O.D.

EVALUATOR CUE: You have obtained SR/O.C.

and SR/O D. keys.

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COMMENTS:

Page i of 7 Revision: I

RTL #A5.635.J .

NUMBER TITLE IPL-017 Startup the Hydrogen Recombiner l

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STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

3. Unlock and open the hydrogen 3.1 Candidate locates reach rod for recombiner isolation valves. lHY-101.
3.2.C Candidate simulates unlocking l and opening iHY-101.

l EVALUATOR CUE: lHY-101 is open.

l; 3.3 Candidate locates reach rod for i 1HY-103.

1 3.4.C Candidate simulates unlocking and opening IHY-103.

EVALUATOR CUE: lHY-103 is open.

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I 3.5 Candidate locates reach rod for IHY-102.

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3.6.C Candidate simulates unlocking and opening IHY-102.

EVALUATOR CUE: lHY-102 is open.

3.7 Candidate locates reach rod for l IHY-104 I

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l Page 2 of 7 Revision: 1 L

RTL #A5.635.J NUMBER TITLE IPL-017 Startup the Hydrogen Recombiner STEP STANDARD l ("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

l 3.8.C Candidate simulates unlocking and opening IHY-104.

EVALUATOR CUE: lHY 104 is open.

COMMENTS:

4. Verify the Containment Vacuum 4.1 Candidate request status of the Pump trip valves are closed. Containment Vacuum Pump trip valves from the Control Room.

EVALUATOR CUE: The Control Room reports that TV lCV-150A, B, C, and D are closed.

4 COMMENTS:

5.C Unlock and open the Recombiner 5.1 Candidate locates IHY-110.

Return and Outlet isolation valves.

5.2.C Candidate simulates unlocking and opening IHY-110.

EVALUATOR CUE: lHY-110 is open.

Page 3 of 7 Revision: I

I RTL #AS.635J NUMBER TITLE i

IPL-017 Startup the Hydrogen Recombiner l

[ STEP STANDARD

! 3' l' ("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

l 5.3 Candidate locates 1HY-l%.

l 5.4.C Candidate simulates unlocking and opening IHY-196.

l EVALUATOR CUE: lHY-196 is open. -

5.5 Candidate locates IHY-Ill.

5.6.C Candidate simulates unlocking and opening 1HY-111, EVALUATOR CUE: 1HY-111 is open.

5.7 Candidate locates 1HY-197.

5.8.C Candidate simulates unlocking and opening IHY-197, EVALUATOR CUE: lHY-197 is open.

COMMENTS:

l

l. EVALUATOR CUE: The wide range analyurs I have been placed in service.

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Page 4 of 7 Revision: I

RTL #A5.635J NUMBER TITLE IPL-017 Startup the Hydrogen Recombiner STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

EVALUATOR CUE: Hydrogen levels require that the recombiners be started.

\

EVALUATOR CUE: Your supervisor directs you to start only the l A hydrogen recombiner.

{

J 6.C Start the hydrogen recombiner. 6.1 Candidate locates MCCl-E5 Cub BN.

6.2.C Candidate simulates turning on MCCl-E5 Cub BN.

l EVALUATOR CUE: MCCl-ES, Cub BN is on.

6.3 Candidate locates MCCl-E5 Cub AQ.

6.4.C Candidate simulates closing MCCl-E5 Cub AQ.

EVALUATOR CUE: MCCl-E5, Cub AQ is closed.

6.5 Candidate locates indication for MOV-lHY-101 A.

6.6 Candidate verifies MOV-lHY-101 A is closed.

l EVALUATOR CUE: MOV-lHY-101 A indicates closed.

Page 5 of 7 Revision: I

RTL CAS.635.J NUMBEK' TITLE IPL-017 Startup the Hydrogen Recombiner.

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

6.7 Candidate locates indication for MOV lHY-103A.

6.8 Candidate verifies MOV-lHY-103A is closed.

EVALUATOR CUE: MOV-lHY-103 A indicates closed.

6.9 Candidate locates MCCI-E5 Cub AQ.

6.10.C Candidate simulates opening MCCl-E5 Cub AQ.

EVALUATOR CUE: MCCl-ES, Cub AQ is open.

6.11 Candidate locates MCCl E5 Cub AU.

6.12.C Candidate simulates opening MCCl-E5 Cub AU.

EVALUATOR CUE: MCCl-ES, Cub AU is open.

6.13 Candidate locates controls for MOV-lHY 102A.

l 6.14.C Candidate simulates opening

i. MOV-!HY-102A.

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EVALUATOR CUE: MOV-lHY-102 A is open.

Page 6 of 7 Revision: I j l

4

RTL #AS.635.J NUMBER TITLE IPL-017 Startup the Hydrogen Recombiner STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

6.15 Candidate locates START pushbutton.

6.16.C Candidate simulates pressing the START pushbutton and holding ]

for ten seconds.

EVALUATOR CUE: The START pushbutton has )

been held for 10 seconds.

1 COMMENTS:

l EVALUATOR CUE: The remainder of this l procedure has been completed by another operator.

7. Inform supervisor that the hydrogen 7.1 Candidate informs supervisor recombiner has been started.. that the Hydrogen Recombirer has been started.

COMMENTS:

STOP TIME i

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Page 7 of 7 Revision: 1

BVPS JOB PERFORMANCE MEASURE JPM QUESTION #1 Given the following conditions, determine the Containment Hydrogen Concentration:

o H2A 1HY-101 A Reading: 7%

o Cable Vault Temperature: 90*F o Contaimnent Pressure: 20 PSIA OPEN REFERENCE j ANSWER:

[ Correction factor from Figure 1 is approximately 0.35) i

[ Actual = Indicated Reading - Correction factor]

H2 concentration is 6.6 - 6.7 %

1 l

l Time Allotted: 7 minutes l

l KA#: 028 Al.01/ 3.8

)

Objective: LP-SQS-46.1 OBJ 10 l

Reference:

lOM-46.4.G, Figure 1, Issue 4, Revision I i

l Comments:

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I IPle017 BV Rev. O f

\ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _

DVPS JOB PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #1 Given the following conditions, determine the Containment Hydrogen Concentration:

o H2A-lHY-101 A Reading: 7%

l o Cable Vault Temperature: 90'F l o Containment Pressure: 20 PSIA i

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l 1Pir017 BV Rev. 0

DVPS JOB PERFORMANCE MEASURE JPM QUESTION #2 The hydrogen concentration in containment increases to 51/2% What effect could starting the recombiner at this point have on the plant?

OPEN REFERENCE ANSWER:

Hydrogen concentration in excess of 4% is combustible and the recombiners can become an ignition source.

1 Time Allotted: 5 minutes KA #: 028 K5.02 /3.9 Objective: LP-SQS-46.1 OBJ-10 i

Reference:

lOM-53E.4.E-1, Issue 1B, Rev. 4 Comments:

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IPle017 BV Rev. 0 I .

BVPS JO3 PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #2 The hydrogen concentration in containment increases to 51/2%. What effect could starting tle I recombiner at this point have on the plant? I l

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IPL-017 BV Rev,0 1

RTL #A5.640E DUQUESNE LIGHT COMPANY 4 Nuclear Power Division I Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training f SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Locally Start the Diesel Generator I

)

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JPM NO.: 1PL-006 )

COMPUTER CODE: N/A Revision No. Date Revision No. Date l

l l

PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee Revision 9

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division l Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET l DOCUMENT TITLE:1PL-006. Locally Start the Diesel Generator Revision Acoroval No. Brief Description Revised by: Signature Date 1

r Revision 9

BEAVER VALLEY JOB PERFORMANCE MEASURE I EVALUATOR COVER SHEET JPM Humber: 1PL-006 Rev: O System #: 064 Faulted: O JPM

Title:

Locally Start the Diesel Generator K/A

Reference:

064 A4.06 /3.9 Task ID #:30100060601 JPM Designation: O NO O RO x SRO JPM Application: X NRC X Initial Exam O Training Evaluation Method LOCATION TYPE Perform E Plant Site O Training Simulate Simulator O Annual Requal. Exam l

Classroom OJT l X Initial Operator Exam l Administered By: O Other:

1 BV-T NRC Other:

Evaluation Results l

Performer: Name: Employee No:

Results SAT Time (minutes)

UNSAT* Allotted: 20 Actual:

Time Critical: Yes x No

  • Comments (Required for UNSAT Evaluation) :

Evaluation Results Check here if same as above observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No: l Observer 4: Name Employee No: l Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 8 _. O Employee No:

Question #1 5 0 Employee No:

  • Comments (Required for UNSAT Evaluation):

f Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9

RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE l

CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • Read: .

i Task: Locally Cart the Diesel Generator 1

INITIAL A station blackout has occurred. OM 53A, ONDITIONS: Procedure ECA-0.0, Loss of All Emergency 4KV Power, is being implemented at this time.

l INIT. CUE: Your supervisor directs you i tart the number -

l one diesel generator by performing Attachment 2-E of 10M-53A.1.

l I

At this time, ask the evaluator any questions you have on this j JPM. j l

When satisfied that you understand the assigned task, announce l "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and l announce your observations. l After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

i Revision 9

t R1L #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: 1PL-006 JPM TITLE: Locally Start the Diesel Generator RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate the task Locally Start the Diesel Generator.

INIT. CONDITIONS: A station blackout has occurred. OM 53A, Procedure ECA-0.0, Loss of All Emergency 4KV Power, is being implemented at this time.

TASK STAN.: Diesel generator started in accordance with 10M-53A.1.2-E.

INIT. CUE: Your supervisor directs you to start the number one diesel generator by performing Attachment 2-E of 10M-53A.1.

REFERENCES:

10M-53A.1.2-E, Issue 1B, Revision 2 l

l TOOLS: NONE l

HANDOUT: 10M-53A.1.2-E, Local Action to Restore AC Power.

I J

Revision 9

RTL #AS.635.J NUMBER TITLE IPL-006 Locally Sta:t the Diesel Generator STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

START TIME _.,

EVALUATOR CUE: Provide candidate with copy of IOM-53 A. I.2-E.

1. Obtain key for EDG Engine Control 1.1 Candidate obtains key 48.

Panel.

EVALUATOR CUE: You have key 48.

COMMENTS:

1 I

2. Establish communications with 2.1 Candidate simulates establishing Control Room. communicadons with Control Room.

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EVALUATOR CUE: You have established l communications with the Control Room.  !

l COMMENTS: l l

Page 1 of 5 Revision: 1

RTL #A5.635.J NUMBER ,

TITLE IPL-006 Locally Start the Diesel Generator STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

3. Clear all Start Failure alarms. 3.1 Candidate observes Start Failure alarms.

EVALUATOR CUE: All Start Failure Alarms are clear.

COMMENTS:

4C Place Selector Switch to LOCAL 4.1 Candidate locates selector START. switch.

4.2.C Candidate simulates inserting key in selector switch.

EVALUATOR CUE: The key has been inserted.

4.3.C Candidate simulates turning selector switch to the LOCAL START position.

EVALUATOR CUE: The switch is in the LOCAL START position.

l COMMENTS:

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l Page 2 of 5 Revision: 1 >

L__ _ - ___ _

RTL CA5.635J NUMBER TITLE IPL-006 Locally Start the Diesel Generator STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

5.C Prime the Diesel Fuel System. 5.1 Candidate locates the FUEL PRIME pushbutton.

5.1.C Candidate simulates depressing the FUEL PRIME pushbutton.

EVALUATOR CUE: The FUEL PRIME pushbutton has been depressed.

COMMENTS:

)

I 6.C Start the Diesel Engine. 6.1 Candidate locates the ENGINE i

START pushbutton.

1 6.2.C Candidate simulates depressing l the ENGINE START pushbutton.

l EVALUATOR CUE: The ENGINE START pushbutton has been depressed. The diesel engine is turning. The diesel engine is running.

f 6.3.C Candidate simulates releasing the ENGINE START pushbutton.

COMMENTS:

Page 3 of 5 Revision: 1

RTL #A5.635.J NUMBER TITLE IPL-006 Locally Start the Diesel Generator STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

7.C Adjust Diesel Generator Speed. 7.1 Candidate observes Diesel Generator speed indication.

EVALUATOR CUE: Engine speed is 810 RPM.

7.2 Candidate locates governor RAISE-LOWER control switch.

7.3.C Candidate simulates taking the governor control switch to the RAISE position.

COMMENTS:

l EVALUATOR CUE: The Engine speed is increasing. Engine speed is 900 RPM.

8. Verify DG output voltage. 8.1 Candidate observes DG output voltage.

EVALUATOR CUE: Diesel Generator output voltage is normal.

EVALUATOR NOTE: Candidate must simulate use of voltmeter selector switch to read voltage.

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' RTL CA$.635.J NUMBER TITLE IPL 006 Locally Start the Diesel Generator 1

STEP STANDARD .

("C" denotes critical step) (Indicate *S" for Sat. or "U" for Unsat.)

EVALUATOR CUE: The Control Room reports that Emergency Bus 1 AE has been energized.

COMMENTS:

9. Inform supervisor that the Diesel 9.1 . Candidate informs supervisor ~

Generator has been started. that '.he Diesel Generator has been started.  ;

COMMENTS:

STOP TIME l

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Page 5 of 5 Revision: 1 I

EVPS J33 PERFORMANCE MEASURE JPM QUESTION #1 i

A resiew of operating logs reveals that at 0100, with plant operating in MODE ONE, the fuel oil storage tank for the A diesel generator contains 17,300 gallons and the fuel oil storage tank for the B diesel generator contains 17,450 gallons. Based on the these conditions, and assuming that no fuel oil could be added to the storage tanks, at what time would the plant have to placed in MODE THREE7 ,

OPEN REFERENCE

' ANSWER:

0900

[Both dicscis are inoperable, T.S. 3.8.1.1 Action e requires that one diesel be restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or the plant be placed in Mode 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following the time of discovery.)]

Time Allotted: 8 minutes I

KA#: 064 K6.08 / 3.3 Objective: LP-SQS 36.2 OBJ-10

Reference:

T.S. 3.8.1.1 1

Comments:

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IPle006 i BVPS Rev: 0

BVPS JOB PERFORMANCE MEASURE

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #1 A review of operating logs reveals that at 0100, with plant operating in MODE ONE, the fuel oil storage tank for the A diesel generator contains 17,300 gallons and the fuel oil storage tank for the B diesel generator contains 17,450 gallons. Based on the these conditions, and assuming that no fuel oil could be added to the storage tanks, at what time would the plant have to placed in MODE THREE?

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l IPIA06 BVPS Rev: 0

BVPS JOB PERFORMANCE MEASURE JPM QUESTION #2 Assume that following surveillance testing, the #1 diesel generator's stop pushbuttons have been depressed and the diesel is in the middle of the I! 1/2 minutes cooldown cycle at idle speed. What would be the response of the diesel generator if an auto start signal, due to safety injection, is received under these operating conditions.

OPEN REFERENCE ANSWER:

The diesel generator would start. [The speed would increase to 900 RPM and the field would be flashed.]

Time Allotted: 5 minutes KA #: 062 K3.02 /4.4 Objective: LP-SQS-53.3 OBJ-3

Reference:

lOM-53B.4.E-1, page 69 Comments:

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1PL-006 BVPS Rev: 0 I

t _ - _ _ - - - _ _ _ _ _ _ - _ _ _

BVPS JOB PERFORMANCE MEASURE

  • THIS SIIEET TO BE GIVEN TO CANDIDATE
  • JPM QUESTION #2 Assume that following surveillance testing, the #1 diesel generator's stop pushbuttons have been depressed and the diesel is in the middle of the 11 1/2 minutes cooldown cycle at idic speed. What would be the response of the diesel generator if an auto start signal, due to safety injection, is received under these operating conditions.

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BVPS Rev: 0 o____________________ _ i

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ES-301 Administrative Topics Outline Form ES-301-1 )

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Facility: E_gaver Vallev Unit 1 Date of Examination: December 15.1997 Examination Level (circle one): RO / SRO Operating Test Number:

Administrative Describe method of evaluation:

Topic / Subject 1. ONE Administrative JPhi, OR i Description 2. TWO Administrative Questions

)

A.1 Plant Parameter Verification JPhi: Perform ECP Calculation Control of i

Operating Q-1 Use of Temporary Operating Procedures Procedures Q-2 Approval of On the Spot Changes (Oh1CNs)

A.2 Tagging and Clearances Q-1 PRA assessment for clearing equipment l ,

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Q-2 Requirement to clear Diesel Generator l

A.3 Radiation Work Permits JPht: Enter High Radiation Area A.4 Emergericy Event Classification JPht: PAR Determination I

NUREG-1021 21 of 26 Interim Rev. 8, January 1997 DVPS REV.I

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training I

OJT CHECKLIST /JPM TITLE: Perform an ECP Calculation JPM NO.: 1AD-A.1 COMPUTER CODE: N/A Revision No. Date Revision No. Date l

PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, ,

or Designee I i

Revision 9

___________________________a

RTL #A5.640E DUQUESNE LIGHT COMPANY l Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training QJT CHECKLIST /JPM TITLE: Perform an ECP Calculation 37PM NQt: 1AD-A.1 COMPUTER CODE: N/A Revision :1o. Date Revision No. Date PREPARED BY: QAIE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee Revision 9

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE:1AD.A1, Perform an ECP Calculation Revision Anoroval No. Brief Description Revised by: Signature Date Revision 9

l BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: 1AD-A.1 Rev: 0 System #: 001 Faulted: O JPM

Title:

Perform an ECP Calculation K/A

Reference:

001 A4.10 /3.9 Task ID #:0010020101 JPM Designation: O NO O RO x SRO JPM Application: X X NRC Initial Exam O Training Evaluation Method LOCATION TYPE E Perform O Plant Site O Training O Simulate O Simulator O Annual Requal. Exam X Classroom O OJT X Initial Operator Exam Administered By: O Other:

O Bv-T O NRC O Other:

l Evaluation Results Performer: Name: Employee No:

Results O SAT Time (minutes)

O UNSAT* Allotted: 30 Actual:

Time Critical: 0 Yes X No

  • Comments (Required for UNSAT Evaluation):

Evaluation Results O Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

t Time (minutes) Results

! Question ID Allotted Actual SAT UNSAT*

Question #1 O O >

Employee No:

Question #1 O O Employee No:

  • Comments (Required for UNSAT Evaluation):

4 . _ ,

Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9

RTL #A5.635.J BEAVER E LLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET THIS SHEET TO BE GIVEN TO CANDIDATE

  • Read:

Task: lPerformanECPCalculation INITIAL Preparing for a plant startup after a reactor trip which occurred 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> ago. Prior to the CONDITIONS: trip, the plant operated for 100% power for 37 days. Prior to the trip Bank D_was at 227 steps, i RCS boron was 719 PPM and core burnup was 7,993 d MWD /MTU. The plant computer is unavailable for the calculation. Starting up in accordance with 10M-50.4.D. Criticality is estimated to be attained within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

INIT. CUE: Your supervisor directs you to perform an ECP calculation.

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l At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

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Revision 9 e-__________-__ -_

RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE i

EVALUATOR DIRECTION SHEET JPM NUMBER: 1AD-A.1 JPM TITLE: Perform an ECP Calculation l

RECOMMENDED

! STARTING LOCATION: CLASS ROOM DIRECTIONS: You are to simulate (perform) the task perform an ECP Calculation.

l INIT. CONDITIONS: Preparing for a plant startup after a reactor trip which occurred 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> ago.

Prior to the trip, the plant operated for

' 100% power for 37 days. Prior to the trip Bank D was at 227 steps, RCS boron was 719 '

PPM and core burnup was 7,993 MWD /MTU. Th'e plant computer is unavailable for the calculation. Starting up in accordance with i 10M-50.4.D. Criticality is estimated to be attained within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

l TASK STAN.: ECP perforNed in accordance with 10M- I 50.4.F.

INIT. CUE: Your supervisor directs you to perform an ECP calculation for a startup with Bank D  !

rods at 100 steps at the time of criticality.

REFERENCES:

Unit 1 Curve Book.

10M-50.4.F, Issue 3, Revision 13 l l

l TOOLS: Calculator l

HANDOUT: 10M-50.4.F, Data Sheet 1 Revision 9

RTL CAS.635.J

. NUMBER TITLE i

1 AD-A.I Perform ECP Calculation l STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

l I

START TIME:

1. Obtain ECP procedure and Unit i 1. Candidate locates IOM-50.4.F Cerve Book. - and Unit ICurve Book.

EVALUATOR CUE: Provide candidate with copy j of IOM-50.4.F and the Unit 1 Curve Book.

1 EVALUATOR NOTE: The examiner may have to wait until the candidate has competed the data l

sheet before evaluating the JPM. The order in which the steps are performed is not critical.

COMMENTS:

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Page 1 of 6 Revision: 1

l' RTL CAS.635.J NUMBER TITLE I AD-A.! Perfonn ECP Calculation l

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

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2. Record Critical Data prior to 2.1 Candidate records prosided data shutdown. on Data Sheet 1, Section A.

Coulmn (I):

Date / Time Boron - 719 ppm l Power - 100%

! Xenon - 100%

1 Samarium - 100%

Rods - 221 steps ,

l COMMENTS:

1 EVALUATOR NOTE: The data recorded and calculated in the following steps must be detennined using the curve book. A range is given for each value. Data falling outside the given range should be evaluated on a case by case basis.

i Page 2 of 6 Resision: 1

i RTL CA5.635.J NUMBER TITLE I

1 AD-A.1 Perform ECP Calculation STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

3. Record Expected Critical Data. 3.1 Candidate determines and records data on Data Sheet 1, Section A, Column (II). ,

f Data / Time Xenon - 52% - 54%

Samarium - 119% -121%

Bank D at 100 steps.

COMMENTS:

4.C Perform reactivity balance. 4.1 Candidate records Power Defect prior to Shutdown - 2000 - 2050 pcm.

4.2 Candidate records control rod worth prior to shutdown - 0.

4.3 Candidate records control rod worth expected at criticality -

840 - 860 pcm.

4.4 Candidate records xenon worth prior to shutdown - 2751 pcm.

4.5 Candidate records xenon wonh expected at criticality - 1430 - )

1485 pcm.

4.6 Candidate records samarium worth prior to shutdown - 615 pcm.

Page 3 of 6 Revision: 1

RTL #A5.635.J

(. NUMBER TITLE I AD-A.1 Perform ECP Calculation STEP STANDARD l

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

4.7 Candidate records samarium worth expected at criticality -

732 - 744 pcm.

4.8 C Candidate determines difference for each reactivity value:

Power Defect = - 2000 - 2050 Pcm

, Rod Worth = 840 - 860 pcm i

Xenon = -1266 - 1321 pcm Samarium = 117 - 119 pcm l

} 4.9.C Candidate determines reactivity

! change: - 2250 - 2450 pcm.

COMMENTS:

l l 5.C Determine critical boron 5.1 Candidate records reactivity concentration. ' change: - 2250 - 2450 pcm. {

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l 5.2 Candidate records line I boron I worth: - 8.8 - - 8.9 pcm.

5.3 Candidate determines line I boron change: 250 - 280 pom.

5.4 Candidate records boron at shutdown: 719 ppm.

5.5 Candidate determines boron for startup: 969 - 999 ppm.

5.6 Candidate determines line 2 boron worth: -8.5 --8.6 pcm.

Page 4 of 6 Revision: 1

RTL #A5.635.J NUMBER TITLE I AD-A.1 Perfonn ECP Calculation STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

l 5.7 Candidate determine line 2 boron change: 260 - 290 ppm.

5.8 Candidate records boron at shutdown: 719 ppm.

5.9.C Candidate determines boron concentration for startup: 979 -

1,009 ppm.

COMMENTS:

6. Mark Section D as N/A. 6.1 Candidate marks N/A on blocks in Section D.

i COMMENTS:

7.C Determine Rod Limits. 7.1 Candidate record critical rod i defect: -840 --860 pcm.

7.2 Candidate determines + 500 pcm value: - 340 - -360 pcm.

7.3 Candidate determine - 500 pcm value: - 1340 --1360 pcm.

l 7.4.C Candidate detennines maximum

( rod postion: 170 - 178 steps.

l Page 5 of 6 Revision: 1 i

A RTL #A5.635.1

^

NUMBER TITLE I AD-A.1 Perform ECP Calculation STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

7.5.C Candiate determines minimum rod position: 37 - 48 steps.

COMMENTS:

8. Report ECP completion. 8.1 Candidate reports that the ECP is complete.

COMMENTS:

STOP TIME I

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i Page 6 of 6 Revision: 1 I

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A.I.2 Question 1 What are three conditions when a Temporary Operating Procedure (TOP) should be used instead of a

' rnaking an on the sp't change?

ANSWER:

Any three:

e When the changes are temporary.

  • When the changes are extensive.

e When the changes are known in advance.

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! = When the changes could be in use for greater than 90 days.

I KA: 2.2.6 / 3.2 l

Reference:

1/2 OM-48.2.B t

! Cominents:

l

-- ____._____________mm____

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • A. I .2 Question 1 What are three conditions when a Temporary Operating Procedure (TOP) should be used instead of a making an on the spot change?

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[

_.- _ _ _ ________.____----_____J

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i l A.I.2 Question 2 What conditions must be met to make an on the spot change to the operating procedures?

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l l The intent of the original procedure is not altered.

The change is required in less than 30 days or the change will prevent a plant trip, reduction in power or j other Productivity or Safety concern.

[The change is documented. reviewed by the OSC and approved by General Manager, Nuclear Operations within 14 days ofimplementation.l )

[ NOTE: Candidate may also discuss OMCN involving intent changes, but tids is not required for full credit. ]

l KA: 2.2.6 / 3.2

Reference:

1/2OM-48.2.B l Comments:

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  • Tills SIIEET TO BE GIVEN TO CANDIDATE
  • A.I.2 Question 2 What conditions must be met to make an on the spot change to the operating procedures?

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A2.1 Based on the Risk Assessment Guidelines as described in NPDAP 7.12, Non Outage Planning, Scheduling and Risk Assessment, whose approval would be required prior to removal of a motor driven, Auxiliary Feedwater Pump from service when the HHSI/ charging pump has also been removed from service? {

l ANSWER:

General Manager of Maintenance Programs and General Manager of Nuclear Operations.

l

[ CDP increase (from Attachment 7) = 4.12 E-06.]

[Therefore, the sy stem combination is designated with a YELLOW color ( > IE-6, but < 1 E-5), and requires approval of General Manager of Maintenance Programs and General Manager or Nuclear Operations ]

REFERENCE:

NPDAP 7.12, Attachment 12 KA: 2.2.I7 /3.5 Comments:

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  • THIS SHEET TO BE GIVEN TO CANDIDATE a A2.1 Based on the Risk Assessment Guidelines as described in NPDAP 7.12, Non Outage Planning, Scheduling and Risk Assessment, whose approval would be required prior to removal of a motor driven, Auxiliary Feedwater Pump from senice when the HHSI/ charging pump has also been removed from senice?

3

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,. 1 A2.2 What are four conditions that must be verified prior to placing a diesel generator on clearance for routine maintenance? Assume the plant is operating in MODE 1 with all systems in NSA.

ANSWER:

1. Actions required by T.S. 3.8.1.1 are done prior to removal from service.
2. Turbine driven AFP must be verified operable.
3. Weather forecast does not indicate thunderstorms or tornadoes
4. Both diesel generators are verified operable.

Reference:

NPDAP 3.4, Attachment 7 l

KA: 2.2.13 /3.8 Comments:

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  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • A2.2 What are four conditions that must be verified prior to placing a diesel generator on cicarance for routine maintenance? Assume the plant is operating in MODE 1 with all systems in NSA.

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RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power. Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE

~

PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Enter High Radiation Area JPM NO.: 1AD-A.3 COMPUTER CODE: N/A j Revision No. Date Revision No. Date PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee O

Revision 9

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE:1AD.A3, Enter Hiah Radiation Area _

Revision Acoroval No. Brief-Description Revised by: Signature Date l

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BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET l

JPM Number: 1AD-A.3 Rev: 0 System #: 194 Faulted: O JPM

Title:

Enter High Radiation Area K/A

Reference:

2.3.1 / 3.0 Task ID #:119 GGG 034 JPM Designation: O NO O RO x SRO JPM Application: x NRC E Initial Exam O Training I

Evaluation Method LOCATION TYPE x Perform O Plant Site O Training O Simulate O Simulator O Annual Requal. Exam x Classroom O OJT l x Initial Operator Exam I Administered By: O Other:

O Bv-T O NRC

{

O Other:

Evaluation Results Performer: Name: Employee No:

Fesults O SAT Time (minutes) i O UNSAT* Allotted: 20 Actual:

Time Critical: O yes x No

  • Comments (Required for UNSAT Evaluation):

Evaluation Results O Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No: l Observer 3: Name Employee No: I Observer 4: Name Employee No:  !

Time (minutes) Results l l

Question ID Allotted Actual SAT UNSAT*

Question #1 O O i Employee No:

i Question #2 O Employee No:

  • Comments (Required for UNSAT Evaluation):

m..

Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9

r RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE l, CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • L

! Read:

l l Task: lEnterHighRadiationArea INITIAL 2HDH-627 which is located in a High Radiation Area needs to be opened.

CONDITIONS:

INIT. CUE: lYoursupervisordirectsyoutoentertheHigh

" Radiation Area in order to open 2HDH-627.

i At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM'!.

Simulate performance or perform as directed the required task.

Point'to any indicator or component you verify or check and announce your observations.

Af ter determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

1 I

Revision 9

RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE e-EVALUATOR DIRECTION SHEET JPM NUMBER: 1AD-A.1 JPM TITLE: Enter High Radiation Area RECOMMENDED-STARTING LOCATION: CLASS ROOM DIRECTIONS: You are to simulate (perform) the task Enter High Radiation Area.

INIT. CONDITIONS: 2HDH-627.which is located in a High Radiation Area needs to be opened.

TASK STAN.: Entry performed in accordance with plant Radiation Control Standards.

INIT. CUE: Your supervisor directs you to enter the High Radiation Area in order to open 2HDH-627.

REFERENCES:

Health Physics Manual LP-RC-02, Revision 17 f

TOOLS: NONE HANDOUT: NONE I

Revision 9

RTL #AS.635.J NUMBER TITLE l AD-A.3 Enter High Radiation Area STEP STANDARD I

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

START TIME l

Evaluator Cue: Provide candidate with TLD, hard hat and safety glasses.

l 1.C Locate and review Radiation Work 1. Candidate locates Radiation j Pennit. Work Permit. I 1.2.C Candidate reviews Radiation Work Permit.

COMMENTS:

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2. Insen Rados ARD into ARD 1000 2.1 Candidate locates Rados ARD.

reader.

2.2 Candidate inserts Rados into ARD 1000 reader.

COMMENTS:

3.C Enter Data in ARD 1000 reader. 3.1.C Candidate enters ID number into ARD 1000 reader.

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Page i of 5 Revision: 1

1 RTL #A5.635.J NUMBER TITLE I

I AD-A.3 Enter High Radiation Area

{

i STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

3.2. Candidate verifies name on ARD 1000 reader.

EVALUATOR CUE: Assume your name is displayed as it would be in the plant.

3.C Candidate enters RWP number in ARD 1000 reader.

COMMENTS:

4. Observe ARD dose and dose rate 4.1 Candidate observes ARD 1000 setpoint and take ticket. reader display and notes ARD dose setpoint.

4.2 Candidate observes ARD 1000 reader display and notes ARD dose rate setpoint.

4.3 Candidate takes and reads ticket.

EVALUATOR CUE: Assume your name is l displayed as it would be in the plant.

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Page 2 of 5 Revision: 1

RTL #A5.635J L. NUMBER ~ TITLE 1 AD A.3 Enter High Radiation Area

)

STEP STANDARD

]

("C" denotes critical step) (Indicate "S" for Sat, or "U" for Unsat.)

l

}

5.C Remove Rados ARD reader. 5.1.C Candidate removes Rados ARD ]'

from ARD 1000 reader.

5.2.C Candidate places R: dos ARD on upper body near TLD.

COMMENTS:

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!' EVALUATOR CUE: You are to simulate donning

protective clothing.

l l EVALUATOR CUE: As Health Physics Tech, l provide candidate with copy of survey map and i

conduct briefing. (Attachment 1)

I.

6. Enter contaminated area. 6.1 Candidate reads posted signs.

EVALUATOR CUE: Assume all dates on signs and survey maps are today's date.

6.2 Candidate enters contaminated i

area.

i COMMENTS: I i

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7. Enter High Radiation Area. 7.1 Candidate proceeds to High Radiation Barrier.

Page 3 of 5 Revision: 1

RTL CAS.635.J NUMBER TITLE l AD-A.3 Enter High Radiation Area STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

l' 7.2 Candidate reads posted signs.

7.3 Candidate enters High Radiation Area and proceeds to work area.

COMMENTS:

8.C Respond to high dose alarm.  ;

EVALUATOR CUE: After candidate reaches work j.

area, turn on tape player to sound high dose rate alann.

{

1 8.1.C Candidate hears alarm and checks ARD.

l EVALUATOR CUE: The ARD is displaying a dose  !

I rate of 107 mrem /hr. l 1

8.2 C Candidate exits High Radiation Area.

EVALUATOR CUE: After candidate exits work area, turn off tape player to silence high dose alann.

Page 4 of 5 Revision: I

RTL #A5.635.J i

. NUMBER TITLE l AD-A.3 Enter High Radiation Area l

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

8.3 Candidate proceeds to telephone and notifies Health Physics.

EVALUATOR CUE: Simulate talking on phone as Rad Tech, acknowledge condition and instruct candidate to return control point.

EVALUATOR CUE: Inform candidate that this completes the JPM.

COMMENTS:

STOP TIME Fage 5 of 5 Revision: 1

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l

I AD-A.3 ATTACHMENT ONE HRA BRIEFING:

1. Review Local Dose Rates on Survey Map.
2. Review Transient Path Dose Rate on Survey Map.
3. Review Areas to avoid / minimize time; hot spots and high rad on Survey Map.
4. Check that ARD is operating properly.
5. Ask candidate what ARD alarm setpoints are.

(Dose Alarm - 50 mrem & Dose Rate Alarm - 99 mrem /hr)

6. Instruct candidate to:

o Read ARD frequently o Notify HP of any changes in conditions o Stay in transient pathway

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclcar Powar Division l Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training l SUBDIVISIOji: On-the-Job Training OJT CHECKLIST /JPM TITLE: Determine PAR JPM NO.: 1AD-A.4 COMPUTER CODE: N/A l

Revision No. Date Revision No. Date

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PREPARED B_1: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee Revision 9

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual 0

l LESSON PLAN AND OJT REVISION APPROVAL SHEET j

~

l DOCUMENT TITLE:1AD. A4 Det.gngine PAR  !

4 l

Revision Acoroval No. Brief Description Revised by: Signature Date  !

l Revision 9

BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET i

, JPM Number: 1AD-A.4 Rev: O System #: 344 Faulted: O  ;

JPM

Title:

Determine PAR K/h

Reference:

2.4.44 / 4.4 Task ID #:3440240302 JPM Designation: O NO O RO x SRO JPM Application: X NRC X Initial Exam O Training Evaluation Method LOCATION TYPE X Perform O Plant Site O Training O Simulate O Simulator O Annual Requal. Exam X Classroom O OJT x Initial Operator Exam Administered By: O Other:

O av-T O NRC O Other:

s . * .

Evaluation Results Performer: Name: Employee No: _

Results O SAT Time (minutes)

O UNSAT* Allotted: is Actual:

Time Critical: O yes x No

  • Comments (Required for UNSAT Evaluation):

Evaluation Results O Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 O O Employee No:

Question #1 O O l Employee No:

  • Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization:

Evaluator Signature Date: l Revision 9

_________-_-A

RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET THIS SHEET TO BE GIVEN TO CANDIDATE

  • Read:

Task: Determine PAR INITIAL Five minutes ago, a plant event occurred CONDITIONS: resulting in the following conditions:

o Core Exit TCs indicate 748 F.

o Subcooling is -147 F.

o RVLIS indicates 35%.(No RCPs running) o Containment pressure is 47 psig.

o 150' wind direction is from 337*.

o 500' wind direction is from 324 .

o CIA and CIB have b3en successfully actuated.

INIT. CUE: You are to evaluate the above conditions and determine which, if any, Offsite Protective Action Recommendations are necessary.

At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, annbunce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

t

, Revision 9 l

RIL VA5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET 1

l JPM NUMBER: 1AD-A.4 '

JPM TITLE: Determine PAR RECOMMENDED STARTING LOCATION: CONTROL ROOM 1

DIRECTIONS: You ara to simulate (perform) the task Determine PAR.

INIT. CONDITIONS: Five minutes ago, a plant event occurred resulting in the following conditions:

o Core Exit TCs indicate 748'F.

o Subcooling is -147 F.

o RVLIS indicates 35%.

(No RCPs running) o Containment pressure is 47 psig.

o 150' wind direction is from 337*.

o 500' wind direction is from 324*.

o CIA and CIB have been successfully actuated.

TASK STAN.: Protective Action Recommendations determined in accordance with EPP/IP 4.1 INIT. CUE: You are to evaluate the above conditions and determine which, if any, Offsite Protective Action Recommendations are necessary. -

REFERENCES:

EPP/IP 4.1 Rev. 8 I

TOOLS: NONE l

HANDOUT: NONE (EPP and EPP/IPs are to be made I available to candidate.)

1 Revision 9 i

l L_-__________

~

RTL #AS.6353

. NUMBER TITLE I AD A.4 Determine PAR STEP STANDARD

("C" denotes :zitical step) (Indicate "S" for Sat. or "U" for Unsat.)

START TIME EVALUATOR NOTE: The candidate may begin by determining Critical Safety F9nction status or by evaluating event classification prior to referencing EPP/IP 4.I

1. Review EPP/IP 4.1. 1.1 Candidate locates EPP/IP 4.1.

1.2 Candidate determines that Protective Action Recommendations required

{

within 15 minutes if General l Emergency is declared. )

I I

1 COMMENTS:

2. Determineif General Emergency 2.1 Candidate locates EPP/I l A, should be declared. Attachment 1 I

l 1

l 1

I i

Page 1 of 4 Resision: 1 1

. . _ . _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ J

RTL #A5.635.J NUMBER TITLE 1 AD-A.4 Determine PAR STEP STANDARD

("C" denotes critical step) (Indicate "S' for Sat. or "U" for Unsat.)

2.2 Candidate determines that two barriers have been lost and there is a potentialloss of third barrier, resulting in a General Emergency condition.

EVALUATOR NOTE: Core Cooling CSF Red Path results in Loss of Fuel Clad Barrier (1.1.1), RVLIS

< 39% results in loss of RCS Barrier (1.2.2) and .;

Containment CSF Red Path results in potential loss )

of CNMT Barrier (1.3.1). j 1

EVALUATOR NOTE: Candidate may reference l EOPs to determine the CSF Red Path conditions exist.

COMMENTS:

3. Candidate refers to Offsite 3.1 Candidate enters Offsite Protection Action Recommendation Protective Action Flow Chart. Recommendation Flowchart on General Emergency EAL other than 7.1.

COMMENTS:

Page 2 of 4 Revision: I

RTL #AS.635.J l

i l

NUMBER TITLE 1 AD-A.4 Determine PAR STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. cr "U" for Unsat.)

6. Report JPM completion. 6.1 Candidate repons that the JPM is complete.

I COMMENTS:

STOP TIME 1

l l

l l

t

? l l

I I

Page 4 of 4 Revision: 1

RTL #AS.635.J NUMBER TITLE I AD A.4 Determine PAR l

STEP STANDARD

("C" denotes critical step) (Indicate "S" for Sat. or "U" for Unsat.)

4. Reference Attachment 2 and 4.1 Candidate references Table I to Determine Downwind Wedge. determine that the 150' elevation Downwind Sectors are FGHJK.

4.2 Candidate references Table I to detennine that the 500' elevation Downwind Sectors are EFGIU.

COMMENTS:

5.C Determine Offsite Protective Action 5.1.C Candidate detennines the Recommendation. following Prctective Action Recommendation:

Evacuate 360*for two miles.

Evacuate Sectors EFGHJK for five miles.

Shelter remainder of10 mile EPZ.

COMMENTS.

i l

l Page 3 of 4 Resision: I

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l . Appendix D Scenario Outline Form ES-D-1 l

Facifity: BVPS - Unit 1 Scenario No.: _1_ OP-Test No.: i

! (

Examiners: Operators:

l l Obiectives: To evaluate the applicants' ability to raise reactor power to the point gf adding heat, control the reactor at lower power; to implement the AOPs and ARPs for a Nl failure and a Pressurizer LevelInstrument failure; and to respond to steam line break (EOP E-2) with concurrent component malfunctions and subsequent Safety injection termination (EOP E-1 and ES-1.1.)

Initial Conditions: Rx S/U in progress, Rx power is at 1E-8 amps, Xenon free, MOL conditions.

Turnover: Bank D at 100 steps. Ready to continue startup at step C.1 of OM-50.4D. FW-150A&B are failed open and CN 101 is in Manual and closed. The inital conditions for Cold Turbine Startup have been verified in accordance with 52.4.A. Boron is 1190 ppm.

Feed flow is being provided by the 1 A MFP with the feedwater bypass valves operating in Auto. The "B" station instrument air compressor is out of service for maintenance but is expected to be retumed to service this shift.

Event Malf. Event Event No. No. Type

  • Description 1 R(RO) Raise power to point of adding heat. Crew then raises
power to > 10%.

l l 2 MALF C(SRO) N361R instrument power fuses blows. Action taken NIS7B 1AW T.S. 3.3.1.1 l

3 N(ALL) Crew continues to raise power, and continues plant startup.

4 MALF I(RO/SRO) LT-459 fails low resulting in letdown isolation.

PRS 6A N(RO/SR Altemate channel selected and letdown restored to O) service 5 MALF C(ALL) Steam leak inside of containment. Lowering RCS MSSIA temperature and increasing power.

6 MALF M(ALL) Steam line break inside of containment. Results in MSSI A . safety injection, CIA and CIB.

7 MALF C(RO/SR CH-P-1 A trips on Si actuation. CH-P-1B must be SISSA O) manually started.

8 INH 51 C(ALL) Failure of Main Steamline Isolation.

NUREG 1021 41 of 42 Interim Rev. 8, January 1997 BVI% Rev.1

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