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Exam Rept 50-324/OL-90-05 for Both Units on 901015-18 & 1108.Results:three of Three Crews & 9 Out of 11 Operators Performed Satisfactorily During Simulator Evaluations
	ML20058K281
Person / Time
Site:	Brunswick
Issue date:	11/30/1990
From:	Munro J, Peebles T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20058K270	List: ML20058K267; ML20058K281;
References
	50-324-OL-90-05, 50-324-OL-90-5, NUDOCS 9012170107
	Download: ML20058K281 (160)
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AT L ANT A, GEORGI A 30323 I

....*,o Report Nos. 50-324/90-05 and 50-325/90-05 Facility Licensee: Carolina Power and Light Company P. O. Box 1551 Raleigh, NC 27602 Fac.ility Docket Nos.: 50-325 and 50-324 Facility License Nos.: DPR-71 and DPR-62 Facility Name: Brunswick 1 and 2 Inspector:

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// 90 John F! Munro 'Date Signed Team Members: B. Holbrook, Region 11 D. Draper, PNL T. Bettendorf, PNL Approved By: 44(

Thopas A. Peebles, Chief

//[/ chd Date/ Signed Operations Branch Division of Reactor Safety

SUMMARY

Scope:

This was.a special announced inspection of crew e"Auations on the Brunswick simulator in accordance with NUREG-1021, ES-601. Both the facility and NRC evaluators assessed the ability of three crews of licensed operators to safely function and operate prior to allowing their return to licensed duties. ;

Resu'lts: .

The NRC determined that three of three crews evaluated and nine of eleven operators performed satisfactorily dur5g the simulator evaluations. Four o)erators were administered requalification retake examinations, and three of tie four passed. One R0 passed the simulator examination but failed the written examination. Improved performance in senior reactor operator command / control and Emergency Operating Procedures was demonstrated by all crews. The two operators who failed the simulator examinations were evaluated again on November 8, 1990, and performed satisfactorily.

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REPORT DETAlls

1. Persons Contacted

B. Leonard, Brunswick Training Manager

+J. Harness, Brunswick Site Manager

J. Moyer, Assistant to Site Manager L. Martin, Corporate Training Director

R. Poulk, Project Specialist, Operator Training

+J. Simon, Operation Manager - Unit 1

W. Geise, Brunswick Simulator Manager

+S. Callis, Brunswick On-Site Licensing

R. Tart, Operations Manager - Unit 2 Other instructors and technicians

Attended exit meetings on October 18 and November 8, 1990.

+ Attended exit meeting on October 18, 1990.

Attended exit meeting on November 8, 1990.

NRC Repr0sentatives J. Munro, Chief, Operator Licensing Section 1, DRS, Region 11 l B. Holbrook, Examiner, Region !!

D. Draper, Examiner, Region 11 ,

T. Bettendorf, Examiner, PNL R. Prevatte, Senior Resident Inspector NOTE: Acronyms and initialisms used throughout this report are listed in the last section. !

2. October 15 - 18 and November 8, 1990, Site Visits The evaluation team observed simulator performance of three shift crews.

The crews consisted of an SF, SCO, and two R0s. Each crew was administered two simulator scenarios. Scenarios were designed to evaluate previously demonstrated generic weaknesses and were administered ,

1 and evaluated in accordance with the guidance of the Examiner Standards, NUREG-1021.

The following list outlines the crews and the specific scenarios on which they were evaluated. 1 Crew G: Scenario #6 - Fire, loss of UPS, ATWS without SPDS, Emergency Depressurization, Loss of HPCl/RCIC i

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Scenario #18 - Leak in DW, Spray Logic Failure, HPCI failure Crew H: Scenario #6 - See Above. ;

Scenario #18 - See Above.

Crew I: Scenario #7 - Stator Cooling Failure, Bypass Valve Failure, ATWS, Stuck Open Safety Relief Valve Scenario #23 - Turbine Trip, Loss of Bus E-8, Loss of B Loop Drywell Spray, Small Break LOCA, Downcomer Break i Retake Exam: l Scenario #13 - Loss of Condenser Vacuum, Turbine Trip, Recirculation Suction Line Break .

Scenario #5 - NI failures, ATWS, 4KV E Bus Loss, FWLCS Failure, SLC System Failure, Steam Leak in Turbine Building, MSIV Closure

a. Crew G:

(1) Scenario #6 The SCO incorrectly directed the initiation of CS during the level recovery phase of E0P-01-LPC. This is contrary to the guidance of Step RC/L-40 which directs use of Table 1 Systems.

Table 1 Systems do not include CS. CS injection was ordered by the SF. CS loop A injected for approximately 15 seconds with a maximum flow rate of about 4500 gpm. The critical task error was caused by the SCO's failure to properly utilize E0P-01-LPC.

The SF (and crew) corrected the error and prevented a large power excursion with its resulting fuel damage.

The NRC evaluators graded the SCO's performance as unsatisfactory due to the failure to perform ISCT #7 - direct slow initiation of injection flow to restore level to TAF when pressure is below MAFP. The licensee graded the SCO's performance as satisfactory in that the error was corrected prior to a power excursion occurring.

(2) Scenario #18 The performance of the crew and individual operators on the scenario and related ISCTs was satisfactory.

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3 The crew was rated snisfactory by both NRC and licensee evaluators. l The performance of one SR0 (SCO) was rated unsatisfactory on scenario #6 by the NRC.

b. Crew H: :

(1) Scenario #6 The R0 did not correctly shutdown HPCI following failure of the HPCI inverter. The operator locked out the auxiliary oil pump, but did not trip the turbine or otherwise shut down the system.

As a result, HPCI injected for approximately four minutes during the required emergency depressurization. Step RC/P-25 of- E0P-01-LPC requires termination of HPCI injection. The NRC and licensee evaluators graded the RO's performance as. ,

unsatisfactory due to his failure to properly terminate and preventinjection--(ISCT#11).

(2) The performance of the crew and. individual operators on the scenario and related ISCTs was satisfactory.

The crew was rated satisfactory by both NRC and licensee evaluators.

One RO was rated unsatisfactory on Scenario #6 by both NRC and licensee evaluators. .

c. Crew 1:

(1) Scenario #7 The performance of the crew and individual operators on the scenario and related ISCTs was satisfactory.

(2) Scenario #23 The performance of the crew and individual operators on the scenario and related ISCTs was satisfactory.

The crew and all individuals were rated satisfactory by both NRC and licensee evaluators.

d. -Retake Exam:

(1) Scenario #13 The performance of the evaluated operators on the scenario and

- related ISCTs was satisfactory, u

4 (2) Scenario #5 The performance of the evaluated operators on the scenario and related ISCTs was satisfactory.

The two evaluated operators were rated satisfactory by both NRC and licensee evaluators.

The evaluation team also~ administered two requalification retake written examinations - one R0 and one SRO. The examinations were prepared by the ;

licensee and reviewed for adequacy by the NRC, The SR0 passed and the R0 '

failed these examinations.

3. Exit Interview The Team Leader met with licensee management on October 18, 1990, and November 8,1990, after completion of the Operational Evaluations. '

Licensee management was informed of the individual and crew results.

4. Acronyms and initialisms ATWS Anticipated Tr asient Without Scram CS Core Spray DRS Division of Rei.ctor Safety DW Drywell E0P Emergency Operating Procedure FWLCS Feedwater Level Centrol System HPCI High Pressure Coolant injection ISCT Individual Simulator Critical Task KV Kilovolt LOCA Loss of Coolant Accident LPC Level Power Control MAFP Minimum Alternate Flooding Pressure MSIV- Main Steam Isolation Valve NI Nuclear Instrumentation NRC Nuclear Regulatory Commission RCIC Reactor Core Isolation Cooling System RC/L Reactor Control / Level-RC/P Reactor Control / Pressure R0- Reactor Operator SCO Senior Control Operator SF Shift Foreman SLC Standby Liquid Control SPDS Safety Parameter Display System SR0 Senior Reactor Operator VPS Uninterruptable Power Supply

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NAME:

DATE: __,19/17/90 __ ,_

CLASS: LOR EXAM: LOR-10-90 RO PREPARED BY: JERNIGAN GRADED BY: .

ALTERNATE GRADER:

TOTAL POINTS: 30.00 POINTS MISSED:

SCORE: _

1. EXAM TIME LIMIT IS 2.0 HOUR 8 l

2. Do not write on exam. (except on attachments)

3. Do not write on back of pages.

4. A score of 80% is required for passing.

5. Use only black ink on this exam, cross out all errors with a single line and initial and date.

I have neither given nor received help on this exam.

All work is my own.

l Signature l l

Exam Reviewer Approved l

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- " LOR-10-90 ROH EXAMINATION **

QUESTION 1 POINT V ALUE8 1.00 If the radiation level in the main stack reaches the Hi-Hi trip setpoint, which one of the following automatic actions will occur?

(Select the correct answer.)

a. The Off-Gas isolation valve AOG-HCV-102 isolates and drains close.

b. Shutdown of the turbine building HVAC System. j

c. Radwaste HVAC isolation and alarms.

d. Group 6 isolation and initiation of SBGT. !

QUESTION 2 POINT VALUE 1.00 1

While operating at 100% steady state power, a recirculation line breaks creating a Loss of Coolant Accident. In the process of responding to the casualty and maintaining control of the plant, you discover the primary containment water level has risen to +70 feet. Which of the following is the most appropriate response? (Select the correct answer.)

a. Reduce reactor water level to maintain a minimum of +10 inches !

above TAF until the containment water level can be restored below the Maximum Containment Water Level Limit, j b.

Terminate injection into the reactor from sources external to the primary containment until containment water level is below the Maximum Containment Water-Level Limit, irrespective of adequate core cooling,

c. Irrespective of whether adequate core cooling is assured, terminate injection into the reactor from all sources until the containment water level is below the Maximum Containment Water Level Limit.

d. Restore and maintain reactor water level between +170 and +200 inches with one or more of the following systems until containment water level can be maintained below the Maximum Containment Water Level Limit: Condensate /Feedwater, CRD, RCIC, HPCI, Core Spray and/or LPCI.

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QUESTION 3 POINT VALUEt 1.00 ,

If the drywell sprays are initiated when the DW temperature is 380'F and pressure is 33 psig, primary containment integrity would be Jeopardized because: (Select the correct answer)

a. The primary containment pressure would decrease-below 2 psig.

b. The primary containment to reactor building vacuum breakers t could not handle the flow.

c. The suppression chamber to drywell maximum differential pressure would be exceeded.

d. The torus ring header vacuum breakers would fail to open. -

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QUESTION 4 POINT VALUE: 1.00 Plant Conditions:

RPV Pressure 1001 psig Suppression Pool Level -3 feet Suppression Pool Temperature 152.5'F.

Assume that an emergency RPV depressurization was executed under the above conditicns. The result would be: (Select the correct answer.)

a. damage to the ring header.

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b. exceeding the heat capacity temperature limit. j

c. overpressurization of the suppression chamber.

d. SRV tail pipe support and T-quencher failures.

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QUESTION 5 PGIllT VALUE: 1.00 Plant Conditions:

Reactor pressure: 1000 psig Suppression pool water level: -5 teet Drywell pressure: 20 psig Suppression Pool Temperature: 119'F In an emergency situation, under the above listed conditions, the reactor (Select the correct answer.)

a. may be depressurized at a rate that will NOT exceed the 100'F/hr cooldown limit.

b. CANNOT be depressurized because the torus water level is too low.

c. should be emergency depressurized because the pressure suppression function of containment is lost.

d. does not need to be emergency depressurized until the water level decreases an additional 6.0 inches.

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QUESTION 6 POINT VALUE 1.00 Plant Conditions:

ATWS Reactor Power 10% '

Reactor Pressure 1000 psig Reactor Water Level + 1" SLC injecting Torus Water Temperature 165'F Torus Water Level - 2 feet Suppression Chamber Pressure-2 psig Given the plant conditions above, which of the following statements describes the crew responses

a. The Heat Capacity Level Limit is being exceeded. The crew should emergency depressurize the reactor.

b. The Heat capacity Temperature Limit is'being exceeded. The crew should open MSIVs and rapidly depressurize to the ,

Condenser, i

c. The Pressure Suppression Pressure limit is being exceeded. The crew should vent the drywell.

d. The Heat Capacity Temperature limit is being exceeded. The crew should emergency depressurize the reactor.

QUESTION 7 POINT VALUE 1.00 During a reactor building fire emergency, the temperature in.the HPCI equipment room is 169'F. The E & RC Technician calls the control room i from the 20 foot elevation and reports an area radiation level of 90 +

mr/hr, steady indications. Which of the following actions is l appropriate? (Assume the high radiation problem is not caused by the

Primary System leakage.) (Select the correct answer.)

a. Continue with reactor operations.

b. Scram the reactor,

c. Shutdown the reactor

d. Scram and emergency depressurize the RPV.

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QUESTION 8 POINT VALUE: 1.00 Assume that during an ATWS event the core is damaged and an unisolatable break from the reactor is causing a radioactivity release.

. The crew is injecting boron (tank level 50%) and maintaining the RPV level at TAF. Reactor power is 8% and reactor pressure is 920 psig.

When the release rate is approaching the General Emergency Release, the crew should:

a. Anticipate emergency depressurization per the guidance of the ,

Reactor Vessel Control Procedure.

b. Increase RPV water level enough to get good mixing of the boron and shut the reactor down.

c. Decrease injection to the reactor and lower the RPV water level to the Minimum Steam Cooling Water Level.

d. Terminate injection to the reactor and manually open seven ADS Valves.

QUESTION 9 POINT VALUE: 1.00 Plant Conditions:

ATWS SLC jnjecting Suppression pool temperature 130'F l During an emergency evolution with the above conditions present, the primary containment control procedure directs the operating crew to commence a reactor cooldown at a rate less than 100*F/hr. The crew should commence the cooldown when: (Selecc the correct answer.)

a. the SLC tank level is less the.1 20%.

b. the entire contents of the SL2 tank have been injected.

c. all but one control rod is inserted beyond position 02.

d. reactor pressure is less than approximately 500 psig.

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QUESTION 10 POINT VALUE 1.00 Assume that there is a complete loss of injection to the reactor. The Reactor is shutdown and CORRECTED Reactor Water Level is minus 45" when

the HPCI system becomes available. The crew should: (select the correct answer). 4

a. Inject with HPCI to bring the reactor water level back to the normal level controlling band.

b. Commence injecting to the reactor with HPCI then.open four SRVs. l

c. Immediately emergency depressurize the reactor with seven SRVs.

d. Commence injecting with HPCI then decrease RPV pressure to a value just above the isolation setpoint.

QUESTION 11 POINT VALUE 1.00 Plant Conditions Reactor Pressure 950 PSIG Reactor Water Level +180 inches All Rods In HPCI Inop A Group One Isolation has occurred due to Main Steam Line High Radiation. The current plant conditions are listed above. Subsequent plant degradation results in the requirment to Emergency Depressurize the reactor. Upon commencing emergency depressurization the crew places all ADS SRV's to open, then the final 4 SRV's to open, however, no SRV's will open. The crew should: (Select the correct answer.)

a. Terminate injection to the reactor until reactor pressure is below the Minimum Alternate Flooding Pressure.

b. Start RCIC and maintain Reactor Pressure at it's current value until SRVs can be restored to operation.

c. Bypass MSIV interlocks and reopen MSIVs to depressurize the reactor to the Main Condenser.

d. Allow Reactor Pressure to be controlled'by SRV cycling. When SRVs are returned to service, open seven SRVs.

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QUESTION 12 POINT VALUE: 1.00 Given procedure EOP-01-PCFP (Primary Containment Flooding) and the following information, determine required operator actions:

Suppression Chamber Pressure 52 psig Drywell Pressure 23 psig

( (Select the correct answer.)

a. Maintain reactor water level hbove -37.5".

b. Establish alternate reactor flooding pressure with at least 1 SRV open with all available HP, LP and alternate injection systems.

c. Terminate injection into the reactor vessel from sources I external to the primary containment.

d. Ensure adequate core cooling by maintaining core spray in service taking suction from the CST. 4 l

QUESTION 13 POINT VALUE: 1.00 If a LOCA signal (Hi DW Press / Low Rx Press) is present and the i l suppression chamber sprays are operating, which one of the following .

conditions will automatically terminate the spraying operation? (Select !

the correct answer.) )

a. Suppression chamber pressure decreases to 2.7 psig.

b. Drywell pressure decreases to 2.7 psig.

c. Primary containment average pressure decreases below 2.7 psig.

d. The maximum differential pressure limit across the suppression !

chamber exceeds 2.7 psig.

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QUESTION 14 POINT VALUE: 1.00 While executing the EOP, what action is required when a Critical Step activates? Assume the operating crew has previously passed the step.

(Select the correct answer.)

a. Proceed on Flow Chart being executed.

b. Go back to the step if you consider it important. ,

c. Finish what you are doing, then go back to the step.

d. Inimediately return to the activated criticci step !

QUESTION 15 POINT ?.51UE: 1.00 Plant conditions:

Group 1 Isolation Reactor Power 10%

Reactor Water Level +75" Reactor Pressure 1000 PSIG '

Suppression Pool Temperature 125'F Drywell Pressure 2 PSIG An EHC Pressure Regulator failure has occurred resulting in a Group 1 Isolation. The reactor has failed to scram. The crew is currently lowering Reactor Water Level to reduce reactor power. The crew should stop lowering level when. . . . (select the correct answer)

a. All SRVs are closed I

b. Suppression Pool temperature stabilizes

c. Reactor Power is less than 3%

d. Reactor Pressure is less than the Minimum Alternate Flooding Pressure i

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- " LOR-10-90 ROH EXAMINATION ** ;

QUE8 TION 16 POINT VALUE: 1.00 ,

During an ATWS condition when Emergency RPV Depressurization is required and only 4 SRV's can be opened, how does the operating crew assure adequate core cooling during the reactor depressurization: L (Select the correct answer.) .

a. resubmergence of the core when the reactor is depressurized.

b. maintain a differential pressure of 50 psid between the RPV and ,

torus for the minimum core flooding interval.

c. inject to the reactor when the RPV pressure is below the minimum alternate flooding pressure.

d. slowl psig.y commence RPV injection when RPV pressure is below 100 QUESTION 17 POINT VALUE 1.00 Current Plant Conditions Reactor Water Level 0 inches Condenser Vacuum 0 inches Reactor Power 1% l "A" Circ Water Pump Running '

"A" Condencate Pump Running "A" Condensate Booster Pump Running A loss of Circulating Water has caused a Reactor Scram. All rods did not fully insert. The crew has lowered Reactor. Water Level to control Reactor Power and the above plant conditions have been established.

Which of the following will prevent the operator from taking action to open the MSIVs.

a. The operator notices that Load Set has decreased to 0%

b. Only the "A" condensate Pump is available for operation

c. The Steam Line HI Flow Alarms have alarmed but are now clear

d. SJAE "A" first Stage Steam Supply Valve will not open l

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- " LOR-10-9 0 ROH EXAMINATION **

i QUESTION 18 POINT VALUE: 1.00 Plant Conditions Reactor has been shutdown for one hour and twenty minutes Reactor Pressure 53 psig q 7 SRVs open Suppression Chamber Pressure 1 psig i Drywell Temperature 200*F '

Level instrumentation available j Following a loss of all level instrumentation due to High Drpell, Temperature the crew has been injecting into the Reactor with RHR. The above conditions have been established for 30 minutes. The crew should....

a. Commence draining the reactor until level instruments indicate on scale or 5 minute has elapsed. ;

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b. Commence draining the reactor until level instrumentation is available regardless of time required.

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c. Commence draining the reactor until level instrumentation is on scale or 3 minutes and 40 seconds has elapsed.

d. Maintain injection to the reactor as is for 41 more minutes.

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QUESTION 19 POINT VALUE: 1.00 Plant Conditions:

ATWS RPV Water Level cannot be determined SLC operating i 1

Four SRV's open While the operating crew is maintaining the RPV pressure slightly above 185 psig (minimum alternate flooding pressuro), the reactor is shutdown ,

due to boron injection. The operating crew should: (Select the l correct answer.) ,

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a. Close 3 SRV's and allcw reactor level to increase until level instruments are back on scale.

b. Terminate injection and wait the maximum core uncovery time limit for level instruments to come on scale.

c. Continue to maintain RPV pressure at the minimum alternate flooding pressure until reactor water level can be determined.

d. Go to the primary containment flooding procedure and execute it concurrently with the level / power control procedure.

l QUESTION 20 POINT VALUE: 1.00 During a total loss of RPV injection on Unit 2, the operating crew will emergency depressurizo the reactor when the RPV water level decreases i to the Minimum Zero Injection RPV Water Level. If the reactor pressure is 700 psig when the crew executes the-blowdown, what is the indicated water level? (Select the correct answer)

a. -37.5 inches

b. -50.0 inches

c. -57,0 inches

d. -65.0 inches l 1

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- " LOR-10-90 ROH EXAMINATION **

QUESTION 21 POINT VALUE 1.00 The plant has been operating at approximately 70% power for 93 hours0.00108 days 0.0258 hours 1.537698e-4 weeks 3.53865e-5 months when you (Control Operator) are instructed to raise reactor power to 100%. As you began incretsing recirculation flow, the "B" loop recirculation pump speed steadily increased beyond the desired value.

In response to tnis condition you locked the scoop tube on the "B" recirculation pump. You note the speed on recirculation pump "A" is Your next action 72%

shouldand be:the (Select speed on recirculation pump)"B" the correct answer. is 87%.

a. Increase the speed of the "A" recirculation pump to 87% and have I & C investigate the cause of the controller failure.

b. Decrease the speed demand signal to the "B" recirculation pump l and unlock the scoop tube. If the speed of the pump does not decrease, trip the pump.

c. Trip the "B" recirculation pump and follow the guidance for the Recirculation Pump Trip.

d. Send an auxiliary operator to manually run back the scoop tube on the "B" loop recirculation pump. . Monitor off-gas activity, LPRMs and stack gas activity.

QUESTION 22 POINT VALUE 1.00

A feedwater rupture has occurred in the steam tunnel. A rapid decrease in Reactor Pressure Vessel water level takes place. You note that water level has decreased to 125 inches and check the High Pressure Coolant Injection (HPCI) system for operation. The HPCI system is not operating. Reactor pressure has decreased to 905 psig. Uelect the

,i statement below that describes the proper plant and operator response to this condition,

a. HPCI has failed to initiate. Manually initiate HPCI and SGBT.

b. HPCI has failed to initiate. Manually initiate RCIC and SGBT.

c. The HPCI initiation setpoint has not been reached. Manually initiate HPCI if it fails to automatically initiate when RPV water level reaches Low Level 2.

d. The HPCI initiation setpoint has not been reached. Manually I initiate HPCI and RCIC if HPCI fails to automatically start.

when RPV water level reaches Low Level 3.

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l QUESTION 23 POINT VALUE: 1.00 ;

RCIC is being run in the full flow test mode to satisfy surveillance requirements. Upon completion of the test, RCIC is shut down per OP 16 when the manual isolation pushbutton is depressed instead of the turbine trip pushbutton. The RCIC system response is: (Select the correct answer.)

a. ONLY the E51-F008 steam supply outboard isolation valve closes.

b. ONLY the E51-F007 steam supply inboard isolation valve closed.

c. BOTH the F008 and F007 valves' shut.

d. NEITHER the F008 or the F007 valves shut.

QUESTION 24 POINT VALUE 1.00 During normal operation at 100% power one 1 steam flow transmitter fails downscale. Which one of the followin(g) correctly describes the FWLCS response to this failure? (Select the correct answer.)

a. The RFPs will lock in the last stable position. >

b. The SF/FF mismatch will result in an increaning level resulting in a turbine trip.

c. A SF/FF mismatch will be sensed, however tr.e level signal is overriding and level will remain at the socpoint,

d. A SF/FF mismatch will be sensed and will result in a reduced

feed flow to match the steam flow signal.

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QUESTION 25 POINT VALUE 1.00 l

The output of the-on-line EHC pressure regulator fails HIGH causing a bypass valve to open. Which one of the following will cause the bypass t to close?

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a. Decrease the bypass jack, t

L b. Decrease the load limit pot.

c. Decrease the pressure setpoint.

d. Decrease the maximum combined flow pot.

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QUESTION 26 POINT VALUE 1.00 l DG #3 has a " UNIT UNAVAILABLE" red light on the RTGB "CA" module and tue following annunciators:

DG-3 Tripped /Not Avail DG-3 Reverse Power Trip DG-3 Auto Start The correct way to reset the DG lockout is: (Select the correct answer.)

a. Roset the DG lockout on the DG local panel.

b. Reset the 86 DB relay at E-3.

c. Roset the DG lockout on the DG local panel and then reset the 86 DB relay at E-3.

d. Reset the 86 DB relay at E-3 and then reset the DG lockout on the DG local panel.

QUESTION 27 POINT VALUE 1.00 Diesel Generator #2 has been started and.is ready to be synchronized to the E-bus. Which one of the following is correct concerning the voltage adjusting rheostat?

I a. With the DG output breaker closed, any switch manipulation will l

adjust the DG KVAR output. -

b. With the DG output breaker closed, any switch manipulation will adjust the DG Stator Voltage.

c. With the DG output breaker open, any switch manipulation will adjust the DG KVAR and field amps.

d. With the DG output breaker open, any switch manipulation will adjust the DG AC amps.

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QUESTION 28 POINT VALUE 1.00 Which SRM 'A' rod block conditions are automatically bypassed when the )

IRM range switch for IRMs A, C, E, and G are all on range 37

a. downscale, upscale

b. INOP, downscale

c. downscale, retract permit

d. INOP, retract permit QUESTION 29 POINT VALUE: 1.00 The operator is increasing reactor power during a reactor startup. The mode switch is in startup, the core is post checkerboard, and RSCS is in A34. Rod 26-23, the last rod in Step 9, has been withdrawn to position 12. The first rod in Step 10, rod 50-31,-is selected and the operator observes the RWM OD screen:

SELF-TEST: FAULT SEQUENCE: A2 BPWS MODE: OPERATE BLOCKS: INSERT STEP: 10 POWER: BELOW LPSP SR 50 - 31 : 12 IB A2 - 10 HELP DISPLAY OFF ETC The reason for insert block ist

a. Insert blocks will be initiated for any rod positioned at the insert limit except position O.

b. The previous rod 26-23 is not fully withdrawn.

l c. A select error,

d. A critical self-test failure.

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- " LOR-10-90 ROH EXAMINATION **

QUESTION 30 POINT VALUE 1.00 Given the following plant conditions:

-the 2C TBCCW pump is lined up and operating on the unit 1 TBCCW system.

-the 2C TBCCW pump unit 2 selector switch is placed in " operate" and the unit 2 contrc2 switch is placed in " start."

choose the answer that correctly states what will happen to the 2C TBCCW pump and the unit 1 and unit 2 motor operated suction and discharge valves.

a. The pump will continue to cperate, the unit 1 valves will stay open, and the unit 2 valves will open.

b. The pump will immediately trip, the unit 1-valves will stay l open, and the unit 2 valves will stay closed. !

c. The pump will continue to operate, the unit 1-valves will close, and the unit 2 valves will open,

d. The pump will immediately trip, the unit 1 valves will close, and the unit 2 valves will stay closed.

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- " LOR-10-90 ROH ANSWER REY **

QUESTION: 1 RECORD: 159, LLN0091 POINT VALUE: 1.00 LESSON PLAN: 03-2B Objectives: 09 ,

If the radiation level in the main stack reaches the Hi-Hi trip setpoint, which one of the following automatic actions will occur?

(Select the correct answer.)

a. The off-Gas isolation valve AOG-HCV-102 isolates and drains close. :

w. Shutdown of the turbine building HVAC System. !

c. Radwaste HVAC isolation and alarms,

d. Group 6 isolation.and initiation of SBGT.

ANSW1R 1 d.

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-a. Reduce reactor water level to maintain a minimum of +10 inches above TAF until the containment water-level can be restored ;

below the Maximum Containment Water Level Limit.

b. Terminate injection =into the reactor from sources external to the primary containment until containment water level is below the Maximum Containment Water Level Limit, irrespective of .

adequate core cooling. !

c. Irrespective of whether adequate core cooling is assured, terminate injection into the reactor from all sources until the containment Level Limit, water level.is below the Maximum containment Water

d. Restore and maintain reactor-water level between +170'and +200 inches with one or more of the-following systems.until, containment water level can be' maintained below the Maximum.

Containment Water Level Limit: Condensate /Feedwater,1CRD,-

RCIC, HPCI, Core Spray and/or LPCI.

_)

ANSWER: 2 b.

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If the drywell sprays are initiated when the DW temperature is 380*F and pressure is 33 psig, primary containment integrity would be 1 jeopardized because: (Select the correct _ answer)

a. The primary containment pressure would decrease below 2 psig. I

b. The primary containment to' reactor building vacuum breakers could not handle the flow. ,

c. The suppression chamber to drywell maximum differential .

pressure would be exceeded. '

d. The torus ring header vacuum breakers would fail to open.

ANSWER: 3 c.

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QUESTION: 4 RECORD: 28, LLE0028 POINT VALUE: 1.00 LESSON PLAN: 07-2K.01 Objectives: .4.A ,_ 5.A Plant Conditions:

RPV Pressure 1001 psig 3 Suppression Pool Level -3 feet-Suppression Pool Temperature 152.5'F

'ssume that an emergency RPV depressurization was executed under the above conditions. The result would be: (Select the correct answer.)

a. damage to the ring header.

b. exceeding the heat capacity temperature limit.

c. overpressurization of the' suppression chamber.

d. SRV tail pipe support and T-quencher failures.

ANSWER: 4 b.

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QUESTION: 5 RECORD: 24, LLE0024 POINT VALUE: 1.00 LESSON PLAN: 07-2K.01 Objectives: 5.C ,

Plant Conditions:

Reactor pressure: 1000 psig Suppression pool water level: -5 feet Drywell pressure: 20 psig Suppression Pool Temperature: 119'F In an emergency situation, under the above listed conditions, the-reactor: (Select the correct answer.)

a. may be depressurized at a rate that will NOT exceed-the 100'F/hr cooldown limit,

b. CANNOT be depressurized because the torus water level is too low,

c. should be emergency depressurized because the pressure suppression function of containment is lost.

d. does not need to be emergency depressurized until the water level decreases an additional 6.0 inches.

ANSWER: 5 c.

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l QUESTION: 6 RECORD: 207, LLE0061 POINT VALUE: 1.00 ,

LESSON PLAN: 07-2K.01 Objectives:-5A , i Plant Conditions: ~I ATWS ,

Reactor Power 10%

-Reactor Pressure 1000 psig Reactor Water Level + 1" SLC injecting-Torus Water Temperature 165'F j!

Torus Water Level - 2 feet Suppression Chamber. Pressure 2 psig ;]

Given'the plant conditions above, which of the following statements !

describes the crew response: l

a. The Heat Capacity Level Limit is being exceeded. The crew. !

should emergency depressurize the reactor.

b. The Heat Capacity Temperature Limit is being exceeded. The crew should open MSIVs and rapidly depressurize to the Condenser.

c. The Pressure Suppression Pressure limit is being exceeded. The crew should vent the drywell,

d. The Heat Capacity Temperature-limit is being exceeded. The crew should emergency depressurize the' reactor. -

ANSWER: 6 d.

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l QUESTION: 7 RECORD: 17, LLE0017 POINT VALUE: 1.00 LESSON PLAN: 07-2K.02 Objectives: 06 , 08 During a reactor building fire emergency, the-temperature in the HPCI I equipment room is 169'F. The E & RC Technician calls the control room from the 20 foot elevation and reports an area radiation level of 90 i mr/hr, steady indications. Which of the following actions is ;

appropriate? (Assume the high radiation problem is not caused by the !

' Primary System leakage.) (Select the correct answer.)

a. Continue with reactor operations. !

b. Scram the reactor,

c. Shutdown tl.e reactor '

d. Scram and emergency depressurize the RPV.-

ANSWER: 7 a.

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QUESTION: 8 RECORD: 206,: -LLE0060 POINT VALUE: 1.00 LESSON PLAN: 07-2K.03 Objectives: 05 , 07 Assume that during an ATWS event the core is damaged and an unisolatable break from the reactor is causing a radioactivity release. i The crew is injecting boron (tank level 50%) and-maintaining the RPV level at TAF. Reactor power is 8%:and reactor pressure is 920 psig.

When the release rate is approaching the General Emergency Release, the crew should:

a. Anticipate emergency depressurization per the guidance of the Reactor Vessel Control Procedure.

b. Increase RPV water level enough to get good mixing of the boron and shut the reactor down,

c. Decrease injection to the reactor and. lower the RPV water level to the Minimum steam Cooling Water-Level,

d. Terminate injection to the reactor and manually open seven ADS f Valves.

l ANSWER: 8 d.

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QUESTION: 9 RECORD: 5, LLE0005 POINT VALUE: 1.00

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LESSON PLAN: 07-2K.04 Objectives: 11 ,,

Plant Conditions: '

ATWS SLC injecting i Suppression pool temperature 130*F During an emergency evolution with the above conditions.present, the primary containment control procedure directs the operating crew to commence a reactor cooldown at a rate less than.100'F/hr.- The crew should commence the cooldown when: (Select the correct answer.)

a. the SLC tank level is less than 20%.

b, the entire contents of the SLC tank have been injected.

c. all but one control rod is inserted beyond position 02.

d. reactor pressure is less than approximately 500 psig.

ANSWER: 9 b.

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QUESTION: 10 RECORD: 205, LLE0059 ' POINT'VALUE: 1.00 LESSON PLAN: 07-2K.05. Objectives:'05 , 08 Assume that there is a complete-loss.of injection-to the reactor. The Reactor is shutdown and CORRECTED Reactor Water Level is minus 45" when.

the HPCI system becomes available. The crew should: (Select the correcc answer) .

a. Inject with HPCI to bring the reactor water level back'to the normal level controlling band.

b. Commence injecting to the reactor with HPCI then open four SRVs.

Immediately emergency depressurize,the reactor with-seven

~

c.

SRVs.

d. Commence injecting with HPCI then.decreaseLRPV pressure to'a- ,

value just above the isolation setpoint.

A!'SWER : 10 c

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QUESTION: 11 RECORD: 204, LLE0058 POINT VALUE: 1.00 ;

LESSON PLAN: 07-2K.06 Objectives: 05 , 04 '

Plant Conditions Reactor Pressure 950 PSIG Reactor Water Level +180 inches All Rods In HPCI Inop j

A Group One Isolation has occurred due to Main Steam Line High Radiation. The current plant conditions are listed above. Subsequent plant degradation results in the requirment to Emergency Depressurize the reactor. Upon commencing emergency'depressurization the crew places all ADS SRV's to open, then the final.4 SRV's to open, however, no SRV's will open. The crew'should: (Select the correct answer.)

a. Terminate injection to the reactor until reactor pressure is below the Minimum Alternate Flooding Pressure. ;

b. Start RCIC and maintain Reactor Pressure at it's current value until SRVs can be restored to operation.

c. Bypass MSIV interlocks and reopen MSIVs to.depressurize the I reactor'to the Main Condenser.

d. Allow Reactor Pressure to be controlled by SRV cycling. When SRVs are returned to service, open seven SRVs.

ANSWER: 11 c.

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QUESTION: 12 RECORD: 234, LLE0076. POINT VALUE: 1.00 LESSON PLAN: 07-2K.06 Objectives: B5 ,

Given proceuore EOP-01-PCFP (Primary Containment Flooding) and the following information, determine required operator actions:

Suppression Chamber Pressure 52 psig. +

Drywell Pressure 23 psig (Select the correct: answer.) ,

a. . Maintain reactor water level above -37.5".

b. Establish alternate reactor. flooding pressure with at least 1 SRV open with all available HP, LP and alternate injection-systems.

c. Terminate injection into'the reactor. vessel' from sources external to the primary containment,

d. Ensure adequate core cooling by maintaining core spray in

service taking suction from the CST.

ANSWER: 12 c.

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QUESTION: 13 RECORD: 171, LLE0043 POINT VALUE: 1.00 LESSON PLAN: 07-2K.08 Objectives: 08 ,

If a LOCA signal (Hi-DW Presr/ Low Rx Press) is present and the suppression chamber sprays ara operating, which one of the following conditions will automatically terminate the sprayina operation? (Select the correct answer.)

a. Suppression chamber pressure decreases to 2.7 psig.

b. Drywell pressure decreases to 2.7 psig.

c. Primary containment average pressure decreases below 2.7 psig,

d. The maximum differential pressure limit across the suppression chamber exceeds.2.7 psig.

ANSWER: 13 b.

QUESTION: 14 RECORD: 202, LLE0056 POINT VALUE: 1.00

. LESSON PLAN: 07-2K.09 Objectives: 07.,

While executing the EOP, what action is required when a critical Step activatea? Assume the operating crew has previously passed the step.

(Select the correct answer.)

( a. Proceed on Flow Chart being executed,

b. Go back to the step if you consider it important.

l L c. Finish what you are doing, then go backJto the. step.

d.- Immediately return to'the activated critical step s

L ANSWER: 14 d.

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'A QUESTION: 15 RECORD: 199, LLE0053 POINT VALUE: '1.00 LESSON PLAN: 07-2K.10 Objectives: 09 , 19 ;

i Plant conditions: !

Group 1 Isolation

( Reactor Power 10%

Reactor Water Level +75" -

Reactor Pressure 1000 PSIG Suppression Pool Temperature 125'F Drywell Pressure 2 PSIG An EHC Pressure Regulator failure has occurred resultir.g in a Group 1 ,

Isolation. The reactor has failed-to scram.- The crew 13-currently lowering Reactor Water Level.to reduce reactor power. The crew should stop lowering level when....(select the correct answer) a.- All SRVs are closed

b. Suppression Pool temperature stabilizes

c. Reactor Power is less than 3%

d. Reactor Pressure is less than-the Minimum Alternate Flooding _

Pressure ANSWER: 15 C. .

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QUESTION -16 RECORD: 201, LLE0055 POINT'VALUE: 1.00 LESSON PLAN: 07-2K.10 Objectives: 19 ,

During an ATWS condition when Emergency RPV Depressurization is-required and only 4 SRV's can be opened, how does the operating crew assure adequate core cooling during the reactor depressurization:

(Select the-correct answer.) l

a. .resubmergence of the core when the reactor is depressurized.

l l b. maintain a differential pressure of 50 psid between the RPV and torus for-the minimum core flooding interval.

c. inject to the reactor when the RPV pressure is below the minimum alternate flooding pressure,

d. slowl psig.y commence RPV injection when RPV pressure in below 100 ANSWER: 16 c.

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-l QUESTION: 17- RECORD:'200, LLE0054 POINT VALUE: 1.00 '!

LESSON PLAN: 07-2K.10- Objectites: 19 , 05 Current Plant Conditions Reactor Water Level 0 inches?

Condenser Vacuum o inches Reactor Power 1%

"A" Circ Water Pump Running "A" Condensate Pump Running ;

"A" Condensate Booster Pump Running A loss of Circulating Water has caused a' Reactor Scram. All rods did not fully-insert. The crew has lowered Reactor Water Level to control Reactor Power and the above plant conditions have been established, i Which of the following will prevent the operator-from taking action to open the MSIVs.

a. The operator notices that Load Set has decreased to 0%

b. . Only the "A" condensate Pump is.available for operation

c. The Steam Line HI Flow Alarms have alarmed'but are now clear

d. SJAE "A" first Stage Steam Supply Valve will not open ANSWER: 17 <

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I QUESTION: 18 RECORD: 197, LLE0051 POINT VALUE: 1.00 l LESSON PLAN: 07-2K.11 Objectives: 04 , 05 Plant Conditions Reactor has been shutdown for one hour and twenty minutes Reactor Pressure 53 psig j 7 SRVs open Suppression Chamber-Pressure 1 psig Drywell Temperature 200'F Level instrumentation available ;

)

Following a loss of all level instrumentation due to High Drywell_

Temperature the crew has been injecting into the Reactor with RHR. The above conditions have been established for 30 minutes. The crew should....

a. Commence draining the reactor until level instruments indicate on scale or 5 minute has elapsed; j

b. Commence draining the reactor until level instrumentation is available regardless of time required,

c. Commence draining the reactor until level instrumentation is on ;

scale or 3. minutes and 40 seconds has elapsed.

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d. Maintain injection to the reactor as'is for 41 more minutes.

ANSWER: 18 l a.

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QUESTION: 19 RECORD: 198, LLE0052 POINT VALUE: 1.00 LESSON PLAN: 07-2K.11 Objectives: 09 , 10 Plant Conditions:

ATWS RPV Water Level cannot be determined SLC operating Four SRV's open

-While the operating crew is maintaining the RPV pressure-slightly above 185 psig (minimum alternate flooding pressure), the' reactor is shutdown due to boron injection. The operating crew should: (Select the- l correct answer.)

a. Close 3 SRV's and allow reactor level to increase until level instruments are back on scale,

b. Terminate injection and wait the maximum core uncovery time limit for level instruments to come on scale.

( c. Continue to maitatnin RPV pressure at the minimum alternate l flooding prescure until reactor water level can be determined.

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d. Go to the primary containment flooding procedure and oxecute it concurrently with the level / power control ~ procedure.

l l ANSWER: 19 C.

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QUESTION: 20 RECORD: 196, LLE0050 POINT VALUE: 1.00 LESSON PLAN: 07-2K.12 Objectives: 07 ,

During a total loss of RPV injection on Unit 2,_the operating crew will_

emergency depressurize the reactor.when the RPV water level-decreases j to the Minimum Zero Injection RPV Water Level. If the reactor-pressure is 700 psig when the crew executes the blowdown, what is the indicated water level? (Select _ the correct answer)

a. -37.5 inches !

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b. -50.0 inches

c. -57.0 inches

d. -65.0 inches l

ANSWER: 20 d.

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l QUESTION: 21 RECORD: 148, LLN0080 POINT.VALUE: 1.00 LESSON PLAN: 10-2A Objectives: 37.B ,

The plant has been operating at approximately.70% power for 93-hours ,.

are instructed to raise reactor power to When 100%. youAs you(Control began Operator)ing increas recirculation flow, the "B" loop-recirculation pump speed steadily increased beyond the desired value.

In response to this condition you locked the scoop tube on the "B" '

L recirculation pump. You note the speed on recirculation pump'"A" is 72% and the speed on recirculation pump "B" is 87%,- Your.next action should be: (Select the correct answer.)

a. Increase the: speed;of the "A" recirculation pump to 87% and have I & C investigate the cause of the controller failure. i

b. Decrease the speed demand signal to the "B" recirculation pump ,

and unlock the scoop tube. If the speed of the pump does not -

decrease, trip the pump. i

c. Trip the "B" recirculation pump'and follow the guidance for the Recirculation Pump Trip..

I d. Send an auxiliary operator to. manually run back the scoop tube-1 on the "B" loop recirculation pump. Monitor off-gas activity, LPRMs and' stack. gas activity.

ANSWER: 21

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QUESTION: 22 RECORD: 138, LLN0070 POINT VALUE: 1.00 f LESSON PLAN: 14-2B Objectives: 06 , '

i A feedwater rupture has occurred in the steam tunnel.. A rapid decrease ,

in Reactor Pressure Vessel water level' takes place. You note.that water level has decreased to'125 inches and check the'High Pressure' The HPCI system'is.not Coolant Injection (HPCI) system for operation.

operating. Reactor creasure has- decreased to 905 psig. Select the statement below that.de. scribes the proper plant and operator response to this condition.

a. HPCI has failed to initiate. Manually initiate HPCI and SGBT.

b. HPCI has failed to initiate. Manually initiate RCIC andLSGBT.

E c. The HPCI initiation setpoint has not been reached. Manually initiate HPCI if it fails to automatically initiate when RPV water level reaches Low Level 2.

d. The HPCI initiation setpoint'has not been reached. Manually -

initiate HPCI and RCIC,1f HPCI fails to automatically start when RPV water level reaches Low Level 3.

I ANSWER: 22 C.

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QUESTION: 23 RECORD: 210, .LLA0030 POINT VALUE: 1.00 LESSON PLAN: 14-2C Objectives: 10 , 12 RCIC is being run in the full flow test mode to satisfy surveillance requirements. Upon completion of the test, RCIC is shut down per OP 16 ,

t when the manual isolation pushbutton is' depressed instead ofothe turbine trip pushbutton.- The RCIC system response is: (Select the correct answer.)

a. ONLY the E51-F008 steam supply outboard isolation valve closes,

b. ONLY the E51-F007 steam supply inboard isolation valve closed.

c. BOTH the F008 and F007 valves shut.

d. NEITHER the F008 or~the F007 valves shut.-

ANSWER: 23 d.

QUESTION: 24 RECORD: 211, LLA0031 POINT VALUE:~1.00 LESSON PLAN: 17-2B Objectives: 09.A ,

i During normal operation at 100% power one 1 steam flow-transmitter i fails downscale. Which one of the followin(g) correctly describes the FWLCS response to this failure? (Select the correct answer.)

j a. The RFPs will lock in the last stable position. I

b. The SF/FF mismatch will result in'an. increasing level resulting :]

i in a turbine trip. }

l l c. A SF/FF mismatch will be sensed, however Ene level signal is l overriding and level will remain at the setpoint.

d. A SF/FF mismatch will be sensed and will result in a reduced j feed flow to match the steam flow signal.

l ANSWER: 24 l

l d.

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l QUESTION: 25 RECORD: 192, LLA0028 POINT VALUE: 1.00 LESSON PLAN: 19-2B Objectivest 11 ,

The output of the on-line EHC pressure regulator' fails HIGH causingLa I bypass valve to open. Which one of the following will cause the bypass ;

to close?

a. Decrease the bypass jack.

l

b. Decrease the load limit pot,

c. Decrease the pressure setpoint.

d. Decrease the maximum combined flow pot.

ANSWER: 25 d.

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QUESTION: 26 RECORD: 193, LLE0049 POINT VALUE: 1.00 LESSON PLAN: 20-2D Objectives: 11 ,

DG #3 has a " UNIT UNAVAILABLE" red light on the RTGB "CA" module and' ,

the following annunciators:-

DG-3 Tripped /Not Avail DG-3 Reverse Power Trip DG-3 Auto Start The correct way to reset the DG lockout is: (Select the correct answer.)

a. Reset the DG lockout on the DG local. panel.

b. Reset the 86 DB. relay at E-3.

c. Reset the DG lockout on the DG local panel and then reset the 86 DB relay at E-3.

d. Reset the 86 DB relay at E-3 and then reset the DG lockout on the DG local panel.

ANSWER: 26 <

d.

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QUESTION: 27 RECORD: 240, LSE0101 POINT VALUE: 1.00 LESSON PLAN: 20-2D Objectives: 23 ,

Diesel Generator #2 has been started and is ready to be synchronized to the E-bus. Which one of the following is correct concerning the voltage adjusting'rhoostat?

a. With the DG output breaker closed, any switch manipulation will' adjust the DG KVAR output.

b. With the DG output breaker closed, any switch manipulation will' adjust the DG Stator Voltage,

c. With the DG output breaker open, any switch manipulation Will adjust the DG KVAR and field amps.

d. With-the DG output breaker open, any switch manipulation will adjust the DG AC amps.

ANSWER: 27 a.

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QUESTION: 28 RECORD: 194, LLN0117 POINT VALUE:-1.00 LESSON PLAN: 25-2A Objectives: 03 ,

Which SRM 'A' rod block conditions are automatically bypassed when the IRM range switch for IRMs A, C, E, and G are all on range 37

a. downscale, upscale

b. INOP, downscale

c. downscale, retract permit

d. INOP, retract permit ANSWER: 28

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QUESTION: 29 RECORD: 195, LLN0118- POINT VALUE: 1.00 LESSON PLAN: 27-2B Objectives: 7C ,

The operator is increasing reactor power during a reactor startup. The mode switch is in startup,.the core is post checkerboard, and RSCS is in A34. the last- rod in Step 9,: has been withdrawn to position 12. Rod 26-23,irst The-f rod in Step 10, rod 50-31, is selected and the operator observes the RWM OD screen: ,

SELF-TEST: FAULT SEQUENCE: A2 BPWS MODE: OPERATE BLOCKS: INSERT STEP: 10 POWER: BELOW LPSP SR 50 - 31 : 12 IB A2 - 10 HELP DISPLAY OFF ETC The reason for insert block is: ,

a. Insert blocks will be initiated-for any rod positioned at the insert limit except position O.

b. The previous rod 26-23 is not fully withdrawn.

c. A select error.

! d. A critical self-test failure.

ANSWER: 29 a.

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1 QUESTION: 30 RECORD: 209, LLA0029 POINT-VALUE: 1.00 l LESSON PLAN: RTT' Objectives: 01 ,

i '

l Given the following plant conditions:

-the 2C TBCCW pump is lined up and operating on the unit 1 TBCCW i system.

-the 2C TBCCW pump' unit 2 selector switch is placed-in " operate" and the unit 2 control switch is placed in " start."

Choose the answer that correctly states what will happen to the 2C TBCCW pump and the unit 1 and unit 2 notor operated suction and discharge valves,

a. The pump will continue to: opera +- the unit 1. valves will stay open, and the unit 2 valves wi;' -pen.

b. The pump will immediately trip, tho1 unit i valves will stay open, and the unit 2 valvos will stay. closed,

c. The pump will continue to operate, the unit'1 valves will close, and the unit 2 valves will open.

d. The pump will immediately trip, the unit 1 valves will close, and the unit 2 valves will stayLclosed.

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ANSWER: 30 d.

- END OF_ EXAM **

30.00 POINTS 100% VALUE, 24.000 POINTS 80% VALUE I

ESTIMATED TIME TO COMPLETE: 132 MINUTES REQUIRED

REFERENCES:

SD-44,BECT. 2.2.1, REV. 5*

1 PAGE 27 OP 27 ,

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, w NAME:

DATE: 10/17/90 CLASS: IDR _

EXAM: LOR-10-90 SRO PREPARED-BY:-JERNIGAN~

GRADED Bi ALTERNATE GRADER:

(if required)

TOTAL POINTS: 30.00 -i.

. POINTS MISSED:

SCORE:

1. EXAM TIME LIM'IT IS 2.0 HOURS

2. Do not write on-exam. .(except.on attachments)

3. Do :ot write on back of pages.

4.

]1 A score of 80% is required for passing.

5. Use only black ink on thisJexe.m. Cross out all . .]

errors with a single line and' initial and-date.

j I have neither given nor received help on this exam.: ]

All work is my own. _

1 signature-

.l t

Exam Reviewer Approved . is

... . . +

0 0

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- HLOR-10-90 SR0" EXAMINATION **

QUESTION 1 POINT VALUst 1.00 A loss of which one of the following power sources would affect the u.ain stack radiation monitors, recorders and sample skidst (select the correct answer.)

a. RPS distribution panel

b. Distribution panel 2D-TB2

c. U-2 120V UPS distribution Pane] 2A

d. MCC-2XG QUESTION 2 POINT VALUE: 1.00 Current Plant Conditions Primary Containment 02 Conc 3.1%

Drywell Temperature 350'F increacing at 2'P/ min Drywell Pressure 66 psig increasing at 1 psig/ min Suppression Pool Level 0 inches Reactor Water Level +170 inches All Rods In Given that an event has occurred to cause an increase in Drywell Prcssure with the current conditions as listed above, the crew should..

a. Purge the Primary Containment with Nitrogen

b. Vent the Primary Containment regardless of off-site release rate

c. Spray the Drywell

d. Emergency Depressurize the Reactor and establish minimum Alternate Flooding Pressure l

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- " LOR-10-90 SRO" EXAMINATION **

QUESTION 3 POINT VALUE: 1.00 The plant (Unit 2) is operating at 100% steady state power when a Loss of Coolant Accident occurs due to a cracked recirculation suction line.

You (the operator) are assessing the plant conditions to determine reactor power, reactor pressure and reactor water level. With a drywell reference leg area temperature of 375'F, drywell pressure of

+5 Psig and reactor pressure of 500 Psig, which of the following reactor water level instruments will you use to t>termine actual reactor water level? (Select the correct answer.)

a. Fuel Zono (with a reading of > +150")

b. Narrow Range (with a reading of +152")

c. Wide Range (with a reading of +152")

d. Shutdown Range (with a reading of +152")

QUESTION 4 POINT VALUE: 1.00 Plant conditions:

ATWS Reactor Power 10%

Reactor Pressure 1000 psig Reactor Water Level + 1" SLC injecting Torus Water Temperature 165*F Torus Water Level - 2 feet Suppression Chamber Pressure 2 psig Given the plant conditions above, which of the following statements describes the crew response:

a. The Heat Capacity Level Limit is being exceeded. The crew should emergency depressurize the reactor.

b. The Heat Capacity Temperature Limit 's being exceeded. The crew should open MSIVs and rapidly depressuri'a to the i condenser,

c. The Pressure Suppression Pressure limit is being exceeded. The crew should vent the drywell.

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d. The Heat Capacity Temperature limit is being exceeded. The crew should emergency depressurize the reactor. ;

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QUESTION 5 POINT VALUE: 1.00 Assume that during a serious accident, local actions are necessary on the -17 foot elevation of the reactor building to ensure a safe shutdown of the reactor. If the radiological conditions in that area prohibit personnel entry, the radioactivity levels aret (Select the .

correct answer) 1

a. Said to be in excess of the maximum allowable radiation level

b. Above the high radiation exposure limit of EOP-4

c. considered to be above the maximum safe operating value

d. In excess of the site emergency declaration value l

QUESTION 6 POINT VALUE 1.00 Assume that during an ATWS event the core-is damaged and an unisolatable break from the reactor is causing a radioactivity release.

The crew is injecting boron (tank level 50%) and maintaining the RPV level at TAP. Reactor power is 8% and reactor pressure is 920 psig.

When the release rate is approaching the General Emergency Release, the l crew shouldt -

a. Anticipate emergency depressurization.per the guidance of the Reactor Vessel Control Procedure,

b. Increase RPV water level enough to get good mixing of the boron and shut the reactor down.

c. Decrease injection to the reactor and lower the RPV water level to the Minimum Steam Cooling Water Level.

d. Terminate injection to the reactor from all systems except RCIC, CRD, and SLC and manually open seven ADS Valves.

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QUESTION 7 POINT VALUE: 1.00 Plant conditions:

Reactor power 2%

Reactor pressure 1000 psig (stabilized)

Reactor water level +40 inches decreasing MSIVs closed condensate pump B running Assume that during an ).TWS and low reactor water livel emergency evolution there is no high pressure injection systam available and the ADS timer is running. Under these conditions and f.he ones listed above the operating crew should: (Select the correct answar.)

I

a. manually inhibit ADS, install jumpers per SEP-10 to defeat LL-3 Group 1 isolation, reopen MSIVs, then rapidly depressurize the reactor to the main condenser,

b. manually inhibit ADS and when water level decreases below -37.5 inches, terminate low pressure injection and caergency depressurize the RPV.

c. emergency depressurize the reactor immediately when it is obvious that no high pressure system is available for injection.

d. Manually inhibit ADS to prevent automatic blowdown until level decreases to TAF, then emergency depressurize the reactor.

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i QUESTION 8 POINT VALUE: 1.00 Plant Conditions: $

ATWS SLC injecting Suppression pool temperature 130*F i

During an emergency evolution with the above conditions present, the primary containment control procedure directs the operating crew to commence a reactor cooldown at a rate less than 100'F/hr. The crew should commence the cooldown when: (Select the correct answer.)

a. the SLC tank level is less than 20%.

b. the entire contents of the SLC tank have been injected,

c. all but one control rod is inserted beyond position 02.

d. reactor pressure is less than approximately 500 psig. !

i QUESTION 9 POINT VALUEt 1.00 Assume that during a Non-ATWS emergency condition RPV emergancy depressurization is required. Prior to opening the SRV's, the operating crew should verify... (select the correct answer) a.. RPV injection is terminated.

b. suppression pool cooling is operable or in service.

c. the ring header downcomer openings are submerged.

d. the SRV discharge device (Tee-Qucnchers) are submerged.

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QUESTION 10 POINT VALUE: 1.00 -

Plant Conditions Reactor Pressure 950 PSIG Reactor Water Level +180 inches All Rods In .

HPCI Inop A Group One Isolation has occurred due to Main Steam Line High Radiation. The current plant conditions are listed above. Subsequent '

plant degradation results in the- requirment to Emergency Depressurize ;

the reactor. Upon commencing emergency depressurization the crew determines that no SRVs will open. The crew should..(select one)

I

a. Terminate injection to the reactor until reactor pressure is !

below the Minimum Alternate Flooding Pressure. !

b. Start RCIC and maintain Reactor Pressure at it's current value until SRVs can be restored to operation.

c. Bigass MSIV interlocks and reopen MSIVs to depressurize the reactor to the Main condenser. ,

d. Allow Reactor Pressuru to be controlled by SRV cycling. When SRVs are returned to service, open seven SRVs.

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QUESTION 11 POINT VALUE 1.00 Given procedure E0P-01-PCFP (Primary Containment Flooding) and the following information, determine required operator actions:

i Suppression Chamber Pressure 52 psig l Drywell Pressure 23 psig

't31oct the correct answer.)

a. Maintain reactor water level above -37.5".

b. Establish alternate reactor flooding pressure with at least 1 SRV open with all available HP, LP and alternate injection j systems,

c. Terminate injection into the reactor vessel from sources '

external to the primary containment.

d. Ensure adequate core cooling by maintaining core spray in service taking suction from the CST.

QUESTION 12 POINT VALUE 1.00 Plant Conditions :

Drywell Pressure 10 psig (increasing)

Drywell Temperature 280 *F (increasin RPV water level +175 inches (stead Torus Pressurc 9 psig (increasin Suppression Chamber Spray initiated MSIV's closed i

During an omorgency evolution in which the above listed conditions

( exist, the operating crew should... (select the correct answer)

a. anticipato emergency depressurization.

b. commence a reactor cooldown.

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c. emergency depressurize the RPV.

d. initiato drywell sprays.

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QUESTION 13 POINT VALUEt 1 00 Two minutes ago while executing E0P-01-LPC, you answerea a decision step YES. Th0 parameter has changed. As the SRO reading the i flowchart,.ycus (Select the correct answer.)

1

a. SHALL go back to the top of the flowchart. ;

b. SHOULD go back to the top of the flowchart.

c. MAY go back to the step that changed.

\

d. MUST go to Reactor Scram Procedure. '

QUESTION 14 POINT VALUE: 1.00 Plant conditions Group 1 Isolation Reactor Power 10%

Reactor Water Level +75" Reactor Pressure 1000 PSIG Suppression Pool Temperature 125'F Drywell Pressure 2 PSIG An EHC Pressure Regulator failure has occurred resulting in a Group 1 Isolation. The reactor has failed to scram. The crew is currently lowering Reactor Water Level to reduce reactor power. The crew should stop lowering level when. . . . (select the correct answer)

a. All SRVs are closed

b. Suppression Pool temperature stabilizes

c. Reactor Power is less than 3%

d. Reactor Pressure is less than the Minimum Alternate Flooding Pressure PAGE 8 i

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- " LOR-10-90 SROH EXAMINATION **

QUESTION 15 POINT VALUEt 1.00 During an ATWS condition when Emergency RPV Depressurization is required and only 4 SRV's can be opened, how does the operating crew assure adequate core cooling during the reactor depressurization:

(Select the correct answer.)

a. resubmergence of the core when the reactor is depressurized.

b. maintain a differential pressure of 50 psid between the RPV and torus for the minimum core flooding interval.

c. inject to the reactor when the RPV pressure is below the minimum alternate flooding pressure,

d. slowl psig.y commence RPV injection w?9n RPV pressure is below 100 QUESTION 16 POINT VALUE: 1.00 Current Plant Conditions Reactor Water Level 0 inches Condenser Vacuum 0 inches Reactor Power 1%

A loss of Circulating Water has caused a Reactor Scram. All rods did

not fully insert. The crew has lowered Reactor Water Level to control .

Reactor Power and the above plant conditions have been established.

Which of the following will prevent the operator from taking action to open the MSIVs.

a. The operator notices that Load set has decreased to 0%

b. Only the "A" condensate Pump is available for operation

c. The Steam Line HI Flow Alarms have alarmed but are now clear

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- " LOR-10-90 SROH EXAMINATION **

l QUESTION 17 POINT VALUE: 1.00 The reactor has been shutdown for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 20 minutes. The crew has completed flooding the Reactor Vessel per procedure and is currently draining the vessel to bring lovel instrumentation on scale. Draining has been in progress for 7 minutes and instrumentation is still not on scale. This... (Select the correct answer)

a. Is an acceptable time for draining the reactor during these conditions and will maintain peak clad temperature between 1500 and 1800*F

b. Is an acceptable time for draining the vessel and will maintain peak clad temperature < 1500'F

c. Is an unacceptable time for draining the vessel and will cause ,

peak clad temperature to exceed 1500*F

d. Is an unacceptable timo and will cause peak clad temperature to be maintained between 1800 and 2200'F i

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QUESTION 18 POINT VALUE 1.00 Plant conditions Reactor Pressure 50 PSIG Drywell Temp 150'F Reactor Water Level 20" NO36 15" NO37 35" NO26A/B Reactor is Shut Down Following a steam line break on the outboard MSIV in which the inboard MSIV would not isolate the crew has emergency depressurized the Reactor. Depressurization was performed due to exceeding the Maximum Safe Radiation Levels in two areas of the Reactor Bldg. The crew should....(select one)

a. Use NO26A and B to trend reactor water level because NO36 and NO37 are incorrect due to reactor pressure

b. Use NO36 only to trend reactor water level because NO37 is below it's variable leg tap and NO26A/B are erroneous because of high density water in their reference leg.

c. Determined that no reactor water level instrumentation is valid Limit, due to exceeding the Reactor Saturation Temperature

d. Use NO36 and NO37 to trend reactor water level because NO26A and B are erroneous due to low density water in their reference leg.

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- " LOR-10-90 SROH EXAMINATION **

r QUE8 TION 19 POINT VALUE: 1.00 .

Plant Conditions: [

Reactor pressure .910 psig Reactor water level: -12 inches ,

During a serious reactor low water level evolution, while the' operating crew is executing the Steam Cooling Procedure, a low pressure source of ;

injection that will deliver five gpm is found to be available. The operating crew should: (Select the correct answer.)- ,

a. wait until the level has decreased to -50 inches, then. blow down. ,

1

b. decrease RPV pressure just enough to inject with the available l system.

c. immediately emergency depressurize the reactor by opening seven SRVs.

d. open one SRV until reactor pressure decreases to 700 psig, then open six more.

QUESTION 20 POINT VaIUE: 1.00 -

The plant has been opera *,ing at a constant power for 106 hours0.00123 days 0.0294 hours 1.752645e-4 weeks 4.0333e-5 months when "A" recirculation pump motor generator develope a fault and trips. Reactor l power stabilizes at 56% and core flow stabilizes at'33 mlbs/hr. Which of the following is the correct action to be taken in response _to this condition? (Select the correct answer.)

a. Manually scram the reactor.

, b. Raise reactor core flow to greater than 35 mlbs/hr or reduce reactor power to less than 45%.

c. Check the di:!ferential temperature (d/t) between the bottom head and ves3el saturation temperature. If the d/t is less than 145'F try immediately increasing speed of running pump until d/t Is within specifications.- J

d. Shut the discharge valve of tho' tripped pump. Verify there are no power oscillations which would cause an automatic reactor I scram.

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I ** " LOR-10-90 SRO" EXAMINATION **

QUESTION 21 POINT VALUEt 1.00 Unit 2 is at rated conditions. While running HPCI: System Operability Test (CST to CST , the E41-F002 (HPCI Steam Isolation) inadvertently \

closes causing a)HPCI Turbine Trip. The RHR Containment Spr y >

Isolation Valve E11-F028A is shut and inoperable due to a va ve actuator failure. Given the above plant conditions, determine which of the following statements meets Unit 2 Technical Specification requirements: (Select the correct answer.)

a. If the RHR Valvo cannot be repaired, shut down the plant to Hot shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,

b. If the RHR Valve cannot be repaired within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , shut down the plant to Hot shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to Cold shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. If the HPCI Valve cannot be repaired within the next 14 days, shut down the plant to Hot shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to less than 150 psig within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d. If the HPCI Valve cannot be repaired within the next 14 days, shut down and cold shutdown the plant to less than 150 psig within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

QUESTION 22 POINT VALUE: 1.00 A small fire has been found and extinguished in Reactor Building 250V MCC 2XDB, Compartment No. B38, Condensato Storage Tank Suction Valve, E51-F010 Circuit Breaker. Upon investigation, electrical maintenance reports the circuit breaker is damaged and will take approximately eighteen hours to repair. Reactor core Isolation Cooling (RCIC) is in ,

a normal standby lineup. From the following list, select the correct i' statement concerning RCIC status.

u. The RCIC system is still operable with no impact on plant operations,

b. The RCIC system is operable but must be repaired within 31 days i or the plant be shutdown.

c. The RCIC system is inoperable until the suction valve lineup is realigned manually. It is then operable again,

d. The RCIC system is functional but the flow path is inoperable, requiring repair within 31 days or a plant shutdown.

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- " LOR-10-90 SROH EXAMINATION **

QUESTION 23 POINT VALUE 1.00 Plant Status:

All control rods are rully inserted.

Reactor pressure: 117 psig i RHR shutdown cooling is unavailable, Both reactor recirculation pumps.are shut down.

It has been determined the reactor needs cooli.1g after.an accident.

Alternate shutdown cooling is necessary as all other methods of shutdown cooling attempted have failed.- Under these conditions and using the plant status given above which one raf the following actions concerning alternate shutdown coollng is correct? (Select the correct answer.)

a. Alternate shutdown cooling CANNOT be used. Reactor pressure is '

too high.

t

b. Alternate shutdown cooling CANNOT be used. RHR. shutdown cooling ie unavailable for use,

c. Alternate shutdown cooling can be used, but only after the entire contents of the SLC storage tank have been injected into the plant.

d. Alternate shutdown cooling can be used. The SRV being used should discharge 180' awa suppression pool cooling.y from cho nuction of the RHR loop in QUESTION 24 POINT VALUEt 1.00 l A failure of the UPS-input to'the Feed Water Level Control System will result in which one of the following plant conditions assuming no operator actions occur? (Select the correct answer.)

l

a. All 3 High level av.ber trip lights illuminate but no actual trip occurs.

b. The N005A pressure transmitter fails downscale.and the plant Will suffer a turbine trip due to High vessel level.

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c. Both steam flow and feed flow signals fail downscale, but level controls slightly lower than normal,

d. The N004A level transmitter fails downscale and the plant will scram on a low water level signal. 1 l

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I QUESTION 25 POINT VALUE 1.00 The output of the on-line EHC pressure regulator fails HIGH causing a bypass valve to open. Which one of the following will cause the bypass ;

to close?

a. Decrease the bypass jack.

b.

Decrease the load limit pot.

c. Decrease the pressure setpoint.

d. Decrease the maximum combined flow pot.

QUESTION 26 POINT VALUE 1.00 During a routine diesel engine test, the diesel engine trips and locks out on a high lube oil temperature signal. Choose the correct statement for the condition described

a. The red Hot Available light on the CA module is illuminated but the DG will attempt one Auto Start if a valid Auto Start Signal is received.

b. The green Available light on the CA module is extinguished and the DG will not start if a valid Auto Start Signal is received.

c. The yellow light is extinguished and the green Auto Mode Stop Switch on the CA module is illuminated and the DG will not stop.

d. The red Not Available light on the CA module is illuminated and the DG will not start if a valid Auto Start Signal is received.

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- " LOR-10-9 0 SROH EXAMINATION **

QUESTION 27 POINT VALUE: 1.00 Diesel Generator #2 has been started and is ready to be synchronized to the E-bus. . Which one of the following is correct concerning the '

voltage adjusting rheostat?

a. With the DG output breaker closed, any switch manipulation will adjust the DG KVAR output.

b. With the DG output breaker closed, any switch manipulation will adjust the DG Stator Voltage.

c. With the DG output breaker open, any switch manipulation will adjust the DG KVAR cnd field amps.

d. With the DG output breaker open, any switch manipulation will adjust the DG AC amps.

QUESTION 28 POINT VALUE: 1.00 ,

During a reactor startup, a rod block is activated if the IFAs are on range 2 and an SRM channel indicates: (Select the aorrect answer.)

a. greater than 100 cps when the detector is fullv inserted.

b. less than 1E4 cps.

c. greater than 100 cps with the SRM detector partially withdrawn.

d. less than 100 cps with the detector not fully inserted.

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- " LOR-10-9 0 SROH EXAMINATION **

QUESTION 29 POINT VALUEt 1.00 A reactor sthrtup is in progress. The control rods are in a post checkerboard pattern wita reactor power 9%. Step 13 of GP-10 with four rods having a withdraw limit of position 04 is entered. The four rods are withdrawn in sequence to position 02. Next, the first rod of the group is withdrawn to position 04. Which of the following conditions is correct after the f.rst rod reaches position 04? (Select the correct answer.)

a. The 30 secona RWM annunciator alarms, the RWM OD screen displays a withdraw block, the Display Matrix Rod Select light is extinge.1shed and the rod withdraw permissive light is extinguished,

b. The RWM OD screen displays a withdraw block, the Display Matrix >

Rod Select light is illuminated, and the rod withdraw light "

is extinguished.

c. The RWM OD screen displays a withdraw block, the Display Matrix Rod Select light is extinguished, the Rod Select Matrix light is extinguished and the rod withdraw light is extinguished,

d. The constant RWM annunciator alarms, the RWM OD screen displays withdraw and insert blocks, and the rod withdraw permissive light is extinguished, i

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QUESTION 30 POINT VALUE: 1.00 Given the following plant conditions on unit #2:

-the startup auxiliary transformer (SAT) is supplying the 2B, 2C and 2D 4160 volt buses ( unit 2 is shutdown), h,

-annunciator UA-13, 4-10 comes in alarm.

The auxiliary erator investi ating notices that the resistor i~

bank for the " winding groun detection circuit is hot. Choose the j answer that correctly describes the function of the resistor bank. '

a. to ensure that the voltage across the alarm relay does not exceed ,

70 volts.

t j

b. to prevent the SAT from locking"out by limiting differential overcurrent to 8 amps when two Y" winding phases are grounded. j

c. to minimize damage to the SAT and other components when a differential overcurrent trip is received.

d. to limit the ground current to 8 amps so that the SAT will not lock 4 out when only one "Y" winding phase is grounded.

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QUESTION: 1 RECORD: 160, LLN0092 POINT VALUE: 1.00 LESSON PLAN: 03-2B Objectives: 07 ,

. A loss of which one of the following power sources would affect the 1

main stack radiation monitors, recorders and sample skids: (Select the correct answer.)

a. RPS distribution panel

b. Distribution panel 2D-TB2

c. U-2 120V UPS distribution Panel 2A

d. MCC-2XG ANSWER: 1 c.

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QUESTION: 2 RECORD: 232, LLE0074 POINT VALUE: 1.00 LESSON PLAN: 07-2K.01 Objectives: 12 , i f

Current Plant Conditions Primary Containment 02 Conc 3.1%

Drywell Temperature 350*F increasing at 2'F/ min Drywell Pressure 66 psig increasing at 1 psig/ min Suppression Pool Level 0 inches Reactor Water Level +170 inches All Rods In Given that an event has occurred to cause an increase in Drywell ,

Pressure with the current conditions as listed above, the crew should.. ,

a. Purge the Primary Containment with Nitrogen I

b. Vent the Primary Containment regardless of off-site release l rate

c. Spray the Drywell ;

d. Emergency Depressurize the Reactor and establish minimum Alternate Flooding Pressure ANSWER: 2 b

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I QUESTION: 3 RECORD: 25, LLE0025 POINT VALUE: 1.00 -

LESSON PLAN 07-2K.01 Objectivest 16 ,

The plant (Unit 2) is operating at 100% steady state power when a Loss of Coolant Accident occurs due to a cracked recirculation suction line.

You (the operator) are assessing'the plant conditions to determine reactor power, reactor pressure and reactor water level. With a drywell reference leg area temperature of 375'F, drywell pressure of

+5 Psig and reactor pressure of 500 Psig, which of the following reactor water level instruments will you use to determine actual -

reactor water level? (Select the correct answer.)

a. Fuel Zone (with a reading of > +150") :

b. Narrow Rango (with a reading of +152") ,

c. Wide Range (with a reading of +152") ,

d. Shutdown Range (with a reading of +152")

ANSWER: 3 c.

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QUESTION: 4 RECORD: 207, LLE0061 POINT VALUE: 1.00 LESSON PLAN: 07-2K.01 Objectives: 5A ,

Plant Conditions:

ATWS Reactor Power 10%

Reactor Pressure 1000 psig Reactor Water Level + 1" SLC injecting Torus Water Temperature 165'F Torus Water Level - 2 feet Suppression Chamber Pressure 2 psig Given the plant conditions above, which of the following statements describes the crew response:

a. The Heat Capacity Level Limit is being exceeded. The crew should emergency depressurize the reactor,

b. The Heat capacity Temperature Limit is being exceeded. The crew should open MSIVs and rapidly depressurize to the Condenser.

c. The Preasure Suppression Pressure limit is being exceeded. The crew should vent the drywell,

d. The Heat Capacity Temperature limit is being exceeded. The crew should emergency depressurize the reactor.

ANSWER: 4

d. t i

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QUESTION: 5 RECORD: 231, LLE0073 POINT VALUE: 1.00 LESSON PLANT 07-2K.02 Objectivest 06 , 04 )

Assume that during a cerious accident, local actions are necessary on j the -17 foot elevation of the reactor building to ensure a safe shutdown of the reactor. If the radiological conditions in that area prohibit personnel entry, the radioactivity levels aret (Select the correct answer) 1

a. Said to be in excess of the maximum allowable radiation level '

b. Abovo the high radiation exposure limit of EOP-4

c. considered to be above the maximum safe operating value

d. In excess of the site emergency declaration value i

ANSWER: 5 c.

e.ee................................................................

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QUESTION: 6 RECORD: 230, LLE0072 POINT VALUE: 1.00 LESSON PLAN: 07-2K.03 Objectives 05 , 07 Assume that during an ATWS event the core is damaged and an unisolatable break from the reactor is causing a radioactivity-release.

The crew is injecting boron (tank level 50%) and maintaining the RPV -

level at TAF. Reactor power is 8% and reactor pressure is 920 psig.

When the release rate-is approaching the General Emergency Release, the crew should

a. Anticipate emergency depressurization per the guidance of the

Reactor Vessel Control Procedure. ;

b. Increase RPV water level enough to get good mixing of the boron and shut the reactor down.

c. Decrease injection to the reactor and lower the RPV water level to the Minimum Steam Cooling Water Level.

d. Terminate injection to the reactor from all systems except RCIC, CRD, and SLC and manually open seven ADS Valves. .

ANSWER: 6 d.

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- HLOR-10-90 BROH ANSWER KEY CONTINUED ** I QUESTION: 7 RECORD: 89, LLE0041 POINT VALUE: 1.00 LESSON PLAN: 07-2K.04 Objectives: 07 , 10 Plant conditions:

Reactor power 2%

Reactor pressure 1000 psig (stabilized)

Reactor water level +40 inches decreasing MSIVs closed Condensato pump D running Assume that during an ATWS and low reactor water level emergency evolution there is no high pressure injection system available and the 1 ADS timer is runninge Under these conditions and the ones listed above the operating crew should: (Select the correct answere) ao manually inhibit ADS, install jumpers per SEP-10 to defeat LL-3 i Group 1 isolation, reopen MSIVs, then rapidly depressurize !

the reactor to the main condensere

b. manually inhibit ADS and when water level decreases below -37e5 inches, terminate low pressure injection and emergency depressurize the RPVe ce emergency depressurize too reactor immediately when it is obvious that no high pressure system is available for injectione de Manually inhibit ADS to prevent automatic blowdown until level decreases to TAF, then emergency depressurize the reactore ANSWER: 7 l b. !

i eoeeeeoeeeeeeoeeeoeeoee,eoeeeeee,,,,,eeees,... ...,,,,,,,,,,,,,,,,,,

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QUESTION: 8 RECORD: 5, LLE0005 POINT VALUh. 1.00 i

LESSON PLAN: 07-2K.04 Objectives: 11 ,

1 Plant Conditions:

ATWS SLC injecting Suppression pool temperature 130'F During an emergency evolution with the above. conditions present, the primary containment control procedure directs the operating crew to commence a reactor cooldown at a rate less than 100*F/hr. The crew should commonce the cooldown when: (Select the correct answer.)

a. the SLC tank level is less than 20%.

b. the entire contents of the SLC tank have been injected.

c. all but one control rod is inserted beyond position 02.

d. reactor pressure is less than approximately 500 psig.

i

ANSWER: 8 l

b. ;

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P QUESTION: 9 RECORD: 229, LLE0071 POINT VALUE: 1.00 LESSON PLAN: 07-2K.05 Objectivest 08 , 11 1

Assumo that during a Non-ATWS omergency condition RPV emergency depressurization is required. Prior to opening the SRV's, the operating crew should verify... (select the correct answer)

a. RPV injection is terminat ed. -

b, suppression pool cooling is operable or in service. ,

c. the ring heador dovacomer openings are submerged.

d. the SRV discharge device (Teo-Quonchers) are submerged.

ANSWER 9 d.

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QUESTION: 10 RECORD: 228, LLE0070 POINT VALUE: 1.00 LESSON PLAN: 07-2R.06 Objectivest 05 , 04 Plant Conditions Reactor Pressure 950 PSIG Reactor Water Level +180 inches All Rods In HPCI Inop A Group One Isolation has occurred due to Main Steam Line High Radiation. The current plant conditions are listed above. Subsequent plant degradation results in the requirment to Emergency Depressurize the reactor. Upon commencing emer dotermines that no SRVs will open.gencyThe depressurization the crew crew should..(select one)

a. Terminate injection to the reactor until reactor pressure is below the Minimum Alternate Flooding Pressure. '

b. Start RCIC and maintain Reactor Pressure at it's current value until SRVs can be restored to operation.

c. Bypass MSIV interlocks and reopen MSIVs to depressurizo the reactor to the Main condenser,

d. Allow Reactor Pressure to be controlled by SRV cycling. .When SRVs are returned-to service, open seven SRV3.

ANSWERI 10 c

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QUESTION: 11 RECORD: 234, LLE0076 POINT VALUE: 1.00 LESSON PLAN: 07-2K.06 Objectives: B5 ,

Given procedure EOP-01-PCFP (Primary Containment Flooding) and the following information, determine required operator actions:

Suppression Chamber Pressure 52 psig Drywell Pressure 23 psig (Select the correct answer.)

a. Maintain. reactor water level'above -37.5".

b. Establish alternate reactor flooding pressure with at least 1 SRV open with all available HP, LP and alternate injection systems,

c. Terminate injection into the reactor vessel from sources external to the primary containment.

d. Ensure adequate core cooling by maintaining cf.'n spray in service taking suction from the CST.

ANSWER: 11 c.

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Drywell Pressure I Drywell Temperature 10 psig

-280 'F ((increasin increasin RPV water level Torus Pressure

+175 inches (stead 9 psig Suppression Chamber Spray-initiated (increasing)

MSIV's closed During an emergency evolution-in which the above listed conditions exist, the operating crew should... (select the correct answer)

a. anticipate emergency depressurization.

b, commence a reactor cooldown.

c. emergency depressuriza the RPV.

d. initiate drywell sprays.

ANSWER: 12

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QUESTION: 13 RECORD: 37, LLS0037 POINT VALUE: 1.00-LESSON PLAN: 07-2K.09 Objectives:'07 ,

Two minutes ago while executing EOP-01-LPC, you answered a decision step YES. The parameter has changed. As the SRO reading the flowchart, you: (Select the correct answer.)

a. SIIALL go back to the top of the flowchart.

b. SHOULD go back to the top of the flowchart.

c. MAY go back to the step that changed,

d. MUST go to Reactor Scram Procedure.

ANSWER: 13 c.

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QUESTION: 14 RECORD: 2 2 4 ,- LLE0066 POINT VALUE: 1.00 LESSON PLAN: 07-2K.10 Objectives: 09 , 19 !

Plant conditions Group 1 Isolation Reactor Power 10%

Reactor Water Level +75" Reactor Pressure 1000 PSIG Suppression-Pool Temperature 125'F Drywell Pressure 2 PSIG !

An EHC Pressure Regulator failure has cccurred resulting-in a Group 1 Isolation. The reactor has failed to scram. The crew is currently :

lowering Reactor Water Level to reduce reactor power. The crew should1 stop lowering level when....(select the correct answer)

a. All SRVs are closed

b. Suppression Pool temperature stabilizes

c. Reactor Power is less than 3%

d. Reactor Pressure is-less than the Minimum-Alternate Flooding Pressure l

ANSWER: 14 C.

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QUESTION: 15 RECORD: 226, LLE0068 POINT VALUE: 1.00 LESSON PLAN: 07-2K.10 Objectives: 19 ,

During an ATWS condition when Emergency RPV Depressurization is required and only 4 SRV's can be opened, how does the operating crew assure adequate core cot'ing during the reactor depressurization:

(Select the correct answer.)

a. resubmergence of the core when the reactor is depressurized,

b. maintain a differential pressure of 50 psid between the RPV and torus for the minimum core flooding interval,

c. Inject to the reactor when the RPV pressure is below the minimum alternate flooding pressure.

i d. slowly commence RPV injection when RPV pressure is below 100 psig.

ANSWER: 15 c.

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QUESTION: 16 RECORD: 225, LLE0067- POINT VALUE: 1.00 LESSON PLAN: 07-2K.10 Objectives: 19 , 05 j Current Plant Conditions Reactor Water Level 0 inches Condenser Vacuum 0 inches Reactor Power 1%

A loss of Circulating Water has caused a Reactor Scram. All rods did not fully insert. The crew has lowered Reactor Water Level to control Reactor Power and the above plant conditions have been established.

Which of the following will prevent the operator from taking action to open the MSIVs.

i

a. The operator notices that Load Set has decreased to 0%

b. Only the "A" condensate Pump is available for operation

c. The Steam Line HI Flow Alarms have alarmed but are now clear

d. SJAE "A" first Stage Steam Supply Valve will not en ANSWER: 16 c,

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QUESTION: 17 RECORD: 222, LLE0064 POINT VALUE: 1.00 l

LESSON PLAN: 07-2K.11 Objectives: 04.,. 10 The reactor has been shutdown for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 20 minutes. The crew has '

completed flooding the Reactor Vessel per procedure and is currently draining the vessel to bring level instrumentation on scale. Draining )

has been in progress for 7 minutes and instrumentation is still-not on scale. This... (Select the correct answer)

a. Is an acceptable time for draining the reactor during these. .

conditions and will maintain peak clad temperature between 1500 and 1800*F

b. Is-an acceptable time for draining the vessel and will maintain peak clad temperature < 1500'F

c. Is an unacceptable time for draining the vessel and will cause peak clad temperature to exceed 1500'F

d. Is an unacceptable time and will cause.poak clad temperature to be maintained between 1800 and 2200'F ANSWER: 17

! c.

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l-QUESTION: 18 RECORD: 223, LLE0065 POINT.VALUE: 1.00 LESSON PLAN: 07-2K.11 Objectives: 10 ,

Plant conditions Beactor Pressure 50 PSIG~

Drywell Temp 150'F Reactor Water Level 20" NO36 .

15" NO37 35" .NO26A/B l

1 i Reactor is Shut Down '

l Following a steam line break on the outboard MSIV in which the inboard MSIV would not isolate the crew has emergency depressurized the t Reactor. Depressurization was performed due to exceeding the Maximum ,

l Safe Radiation Levels in two areas 7f the Reactor Bldg. The. crew. o should....(select one) !

a. Use NO26A and B to trend reactor water level because NO36 and NO37 are incorrect'due to reactor' pressure ,

b. Use NO36 only to trend reactor water level because NO37 is-below it's variable leg tap and NO26A/B are erroneous;because of high density water in their-reference leg.- .

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c. Determined that no reactor water level instrumentation is !

valid due to exceeding the Reactor Saturation Temperature l Limit.

d. Use NO36 and NO37 to trend reactor water level because NO26A and B are erroneous due to low density water in their reference leg.

i ANSWER: 18 d

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, QUESTION: 19 RECORD:-11, LLE0011' POINT VALUE: 1.00 ,

LESSON PLAN: 07-2K.12 Objectives: 05 , ;

Plant Conditions:

Reactor pressure: 910 psig l Reactor water level: -12 inches During a serious reactor low water level evolution, while the operating-crew is executing the Steam Cooling Procedure, a low pressure source of injection that will deliver five gpm is found to be available. The l operating crew should: (Select the correct answer.)

l

a. wait until the level has decreased to -50 inches, thenLblow l down. l

b. decrease RPV pressure just enough to. inject with the available system.

c. immediately emergency depressurize the reactor by opening seven i

SRVs.

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d. open one SRV until reactor pressure decreases to 700 psig, then open six more.

ANSWER: 19 l c.

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QUESTION: 20 RECORD: 41, LLA0003 POINT VALUE: 1.00 -

LESSON PLAN 10-2A Objectives: 37.D,- -'

The plant has been operating at a constant power for 106 hours0.00123 days 0.0294 hours 1.752645e-4 weeks 4.0333e-5 months when "A" recirculation pump motor generator develops a fault and trips. Reactor power stabilizes at 56% and core flow stabilizes at 33 mlbs/hr. Which of the following is the correct action to be taken in response to this condition? (Select the correct answer.) l

a. Manually scram the reactor,

b. Raise reactor core flow to greater than 35 mlbs/hr or_ reduce reactor power to~1ess than 45%.

c. Check the differentia 1' temperature (d/t)'between the bottom head and vessel saturation temperature. If the d/t is less thaa 145'F tr immediatel increasing speed of running pump untild/t1swfthinspecifcations..~ ,

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d. Shut the discharge valve of the tripped pump. Verify there are no power oscillations which would cause an automatic reactor scram, j

l ANSWER: 20 b.

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QUESTION: 21 RECORD:-236, LLA0035 POINT VALUE:-1.00 LESSON PLA!': 14-2B Objectives: 17 ,

Unit 2 is at rated conditions. While running HPCI: System Operability Test (CST to CST , the E41-F002 (HPCI Steam Isolation) inadvertently closes-causing a)HPCI Turbine Trip. The RHR Containment Spray Isolation Valve E11-F028A is shut and inoperable due to a valve i actuator failure. Given the above plant conditions, determine which of -

the following statements meets Unit 2 Technical Specification requirements: (Select the correct answer.)

a. If the RHR Valve cannot be repaired,_ shut down the plant to Hot shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to Cold. shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

}

b. If the RHR Valve cannot be repaired within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , shut down the plant to Hot shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to Cold shutdown within_the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. If the HPCI Valvo cannot be repaired within the next 14 days, shut down the plant to Hot shutdown within.the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to less than 150 psig within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

d. If the HPCI Valve cannot be repaired within the next 14 days, shut down and cold shutdown the plant to less than 150 psig within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ANSWER: 21 c.

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A small fire has been found and extinguished in Reactor Building 250V MCC 2XDB, Compartment No. B38, Condensate Storage Tank Suction Valve, E51-F010 Circuit Breaker. Upon investigation, electrical maintenance I

reports the circuit breaker is damaged and will-take approximately eighteen hours to repair. Reactor Core Isolation Cooling (RCIC) is in-a normal standby lineup. From the following list,-select-the correct statement cons:rning PClC' status. l

a. The RCIC system is still' operable with no impact on plantL operations. ,i

b. The RCIC system is operable but must be repaired within 31 days or the plant be shutdown.

c. The RCIC system is inoperable until the suction valve lineup is-realigned manually. It is then operable again..

d. The RCIC system is functional but the flow path is inoperable, requiring repair within 31 days or a plant shutdown.. _

ANSWER: 22 k f

C.

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QUESTION: 23 RECORD: 52, LLA0014 POINT VALUE: 11.00 LESSON PLAN:-14-2D Objectives: 05 , 23 Plant Status; j All control rods are fully inserted. . l Reactor pressure: 117 psig ;

RHR shutdown cooling is unavailable. '

Both reactor recirculation pumps are shut down. :

It has been determined the reactor needs cooling after an accident. ,

Alternate shutdown cooling is necessary as all other methods of shutdown cooling attempted have failed. Under these conditions and I using the plant status given above, which one of the following actions !

concerning alternate shutdown cooling is correct? (Select the correct j answer.) j

a. Alternate shutdown cooling CANNOT be used. . Reactor. pressure is too high.

b. Alternate shutdown cooling CANNOT be used.. RHR shutdown cooling is unavailable for use.

c. Alternate shutdown cooling can be used, but only .fter the entire contents of the SLC storage tank have been Linjected into

. the plant, i

d. Alternate shutdown cooling can be used. .The SRV being used should discharge 180* away from the suction of the RHR loop in 1 suppression pool cooling. !

ANSWER: 23 i d.

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a QUESTION: 24 RECORD: 217, LLA0033 POINT VALUE: 1.00 LESSON PLAN: 17-2B Objectives: 9 , 15 A failure of the UPS input to the Feed' Water Level Control System will result in which one of the following plant conditions assuming no operator actions occur? (Select the correct answer.) '

a. All 3 High level amber trip lights illuminate but no actual trip occurs,

b. The NOOSA pressure transmitter fails downscale and the plant will suffer a turbine trip due to High vessel level,

c. Both steam flow and feea flow signals fail downscale, but level controls slightly lower than normal.

d. The N004A level transmitter fails downscale and the plant'will scram on a low water level' signal.

ANSWER: 24 b.

l QUESTION: 25 RECORD: 219, LLA0034 - . POINT VALUE: '1.00 LESSON PLAN: 19-2B Objectives: 11 ,

The output of the on-line EHC pressure regulator fails HIGH causing a bypass valve to open. Which one of the following will cause the bypass to close?

a. Decrease the bypass jack.

b. Decrease the load limit pot.

c. Decrease the pressure setpoint.

d. Decrease the maximum combined flow pot.

ANSWER: 25 d.

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During a routine diesel engine test, the diesel engine trips and locks i out on a high lube oil temperature signal. Choose the correct j statement for the condition described:

a. The red Not Available light on the CA module is illuminated but the DG will attempt one Auto Start-if a valid Auto Start Signal is received,

b. The green Available light on-the=CA bodule is extinguished and the DG will not start-if a valid Auto Start Signal is-received.

c. The yellow light is extinguished and the green Auto Mode Stop Switch on the CA module is illuminated and the DG will not stop.

d. The red Not Available light on the CA module is illuminated and the DG will not start if a valid Auto Start Signal is received.

ANSWER: 26 a.

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i QUESTION: 27 RECORD: 240, LSE0101 POINT VALUE: 1.00- -

LESSON PLAN: 20-2D objectives: 23 , 1 Diesel Generator #2 has been started and is ready to be synchronized to ;

the E-bus. Which one of the following is' correct concerning the l voltage adjusting rhoostat?

a. With the DG output breaker closed, any switch-manipulation will adjust the DG KVAR output,

b. With the DG output breaker closed, any switch manipulation will adjust the DG Stator Voltage.

c. With the DG output breaker open, any switch manipulation will adjust the DG KVAR.and-field amps.

d. With the DG output breaker open, any switch manipulation will adjust the DG AC amps.

ANSWER: 27 a.

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QUESTION: 28 RECORD: 66, LLN0001 POINT VALUE: 1.00 LESSON PLAN: 25-2A Objectivos: 03.A ,-

During a reactor startup, a rod block is activated-if the IFW!s are on range 2 and an SRM channel indicates: (Select the correct answer.)

a. greater than 100 cps when the-detector is fully inserted,

b. less than IE4 cps,

c. greater than 100 cps with the SRM detector partially withdrawn,

d. less than 100 cps with'the detector not fully inserted.

ANSWER: 28 d.

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QUESTION: 29 RECORD: 221, LLE0063 POINT VALUE: 1.00 LESSON PLAN: 27-2B Objectives: 7C ,

A reactor startup is in progress. The. control rods are in a post-checkerboard pattern with reactor power 9%. Step 13 of GP-10 witu four rods having a withdraw limit of position 04 is ontered. The four rods are withdrawn in sequence to position 02. Next, the first rod of the group is withdrawn to position 04. Which of the following conditions-is correct after the first rod reaches position 047 (Select the-correct answer.)

a. The 30 second RWM annunciator alarms, the RWM OD screen displays a withdraw block,. the Display Matri:: Rod Select light is extinguished and the rod withdraw permissive light is-extinguished.

b. The RWM OD screen displays a withdraw block, the Display Matrix Rod Select-light is illuminated, and the rod withdraw light is extinguished,

c. The RWM OD screen displays.a withdraw block, the Display Matrix Rod Select light is extinguished, the Rod Select Matrix light is extinguished and the rod withdraw light is extinguished.

d. The constant RWM. annunciator alarms, the RWM OD screen' displays withdraw and insert blocks, and the rod withdraw permissive light is extinguished.

ANSWER: 29 b.

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l QUESTION: 30 RECORD: 214, LLN0121 POINT VALUE: 1.00 LESSON PLAN: RTT Objectives: 02 , !

Given the following plant conditions on unit #2:

is su

-the andstartup 2D 4160auxiliary transformer (SAT)( unit 2 is shutdown) .pplying the 2B, -2C volt buses .

-annunciator UA-13, 4-10 comes in alarm.

The auxiliary operator investigating notices that the resistor ;

bank for the "Y" winding ground detection circuit is hot. Choose the i answer that correctly describes the function of the resistor bank.

a. to ensure that the voltage across the alarm relay does not exceed 70 volts,

b. to prevent the SAT from locking out by limiting differential.

overcurrent to 8 amps when two "Y" winding phases are grounded.

c. to minimize damage to the SAT and other components when a. i differential overcurrent trip is received. '

d. to limit the ground current to 8-amps!so that the SAT will not lock j out when only one "Y" winding phase is grounded. p AN8WER: 30 d.

- END OF EXAM **

30.00 POINTS 100% VALUE, 24.000 POINTS 80% VALUE ESTIMATED TIME TO COMPLETE: 142 MINUTES REQUIRED

REFERENCES:

FWLCS NORM

PAGE 28 OF 28

0 O L NAME:

DATE: 10/17/90 CLASS: LOR EXAM: LOR-10-90-El_RO PREPARED BY: J ERNIGAh' GRADED BY: l' ALTERNATE GRADER:

(if required)

TOTAL POINTS: . 15.00 POINTS MISSED:

SCORE: 'q

1. EXAM TIME LIMIT IS 1.0 HOURS

2. Do not write on exam. (except on attacP"ints)

3. Do not write on back'of'pages. .

4. A score'of 80%-is required for passing. .

5. Use only black ink on this exam. Cross out all errors with a single line and initial'and date.

I have neither given nor received help on this exam. j All work is my own, i Signature Exam Reviewer Approved ll A

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- " LOR-10-90-El RO" EXAMINATION **

.l, QUESTION 1 TOINT VALUE3 1.00.

The lowest INDICATED RPV WATER LEVEL which' assures. adequate core-cooling is: { Select the correct answers) -

n. -60 inches

b. -40 inches

c. -70 inches

d. -37.5 inches QUESTION 2 POINT VALUE: 1.00

- THIS QUESTION IS NOT DEPENDENT ON THIS SCENARIO!**

During an ATWS, the-jumpers have been installed per EOP-01-LEP-02, Section 3 and the scram has been reset. One minute later, steam flow drops below 3x10 61bm/hr. Choose the correct statement:-

a. The mode switch may be placed in shutdown withino subsequent -

RPS trip.

b. The mode switch position is of no consequence while performing LEP-02,

c. The mode switch should be left in "RUN" to-facilitate control '

rod insertion via the Rx Manual control System.

d. The mode switch will activate an RPS trip when placed to '

L shutdown, ,

-QUESTION 3 POINT VALUE: 1.00 The liquid poison solution currently being injected into-the reactor

! vessel will not bring the reactor core to a shutdown condition due to:

(Select the correct answer.)

a. Low natural circulation.

l b. Excessive positive reactivity.

c. Control rod positions,

d. Moderator temperature decrease.

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- HLOR-10-90-El ROH EXAMINATION- **

f QUESTION 4 POINT VALUEt 1.00 .

1 Prioritize the performance of various sections of_EOP-01-LEP-02 and choose from the following the best answer:

a. Sections 2,3,4,5,6 then 7. The procedure has already ,

prioritized the ordor to be performed.

b. Sections 6 and 5 should be performed first.

c. Sections 5 and 3 should be performed first.

d. Sections 3 and 4 should be performed first.- .

QUESTION $ POINT VALUE: 1.00 The SCO has directed the BOP operator to take the main generator off line. As a result of this action: (Select the_ correct answer.)

a. The Rx water level must be deliberately lowered to suppress Rx-power.

b. One or two SRV's will cycle,

c. Reactor power will increase due to the loss'of Feedwater heating, l d. More energy will be dissipated by the circ water system.

QUESTION 6 POINT VALUE: 1.00 Which of the following statements best describes the status of the RWCU System? (Select the correct answer.)

a. Both 2G31-F001 and F004 should be closed due to SLC initiation,

b. Both 2G31-F001 and F004 should be open.

! c. G31-F004 should be closed, RWCU has correctly isolated.

d. Both 2G31-F001 and F004 should be closed due to an isolation condition.

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- " LOR-10-90-El RO" EXAMINATION -**

QUESTION 7 POINT VALUE: 1.00 Which of the following statements best describe the correct 1 operator !

actions for these plant conditions? ,

n. Terminate and prevent-HPCI, RCIC, Cond. and FW, RHR and C.S.

b.

~

Run HPCI in manual and inject to control level above -37.5 ^

inches.

c. Run HPCI on the Test Pot and inject to control level =above

-37.S inches.

d. Shutdown and isolate HPCI, 1,

QUESTION 8 POINT VALUE 1.00 Prior to placing 'B' Loop RHR in su the operator must: (Select the correct answer.)ppression pool cooling,

a. Place the 2/3 core height override switch in the override position.

b. Reset the LOCA logic.

I

c. Override 2/3 core height and place the think switch in manual,

d. Line up for suppression because DW pressure is 2.5 < poolpsig. cooling with no restrictions QUESTION 9 POINT VALUE: 1.00 Choose from the following the one which best describes the ADS response to the present plant conditions:

a. 7 ADS valves will open,

b. ADS Will not actuate.

c. Only 4 ADS valves will open.

d. ADS will only actuate if 2 'B' RHR Pump is running.

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- " LOR-10-90-El ROH EXAMINATION **

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QUESTION 10 POINT VALUE: 1.00 Assuming the SLC pumps had failed to operate in the current plant condition, you should first attempt to injeet liquid poison with:

(Select the correct answer.)

a. A submersible pump and CRD.

b. RWCU using borax,

c. Gravity foed and CRD.

d. A hydro pump.

QUESTION 11 POINT VALUE: 1.00 The basis for running.two SLC pumps under current plant conditions is to: (Select the correct answer.)

a. avoid precipitation of sodium pentaborate,

b. avoid stagnation of solution in the lower plenum,

c. protect primary containment,

d. protect the reactor core by shutting it down quicker.

QUESTION 12 POINT VALUE: 1.00 The MSIV's are open. For the current plant condition: (Select ~the correct answer.)

l a. This is correct because during an ATWS with the condenser available, the MSIV's should remain open.

b. This is correct because even though PNS has isolated, back-up nitrogen is supplying pneumatics.

c. This is incorrect because of the mode switch position with current reactor pressure.

d. This is incorrect because the operator, by procedure, should have closed the MSIV's.

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QUESTION 13 POINT VALUES.l.00 Consider #4 Emergency Diesel-Generator: (Select the correct' answer.) L

a. There is no'need.to start the DG'because E-4 is powered from Bus 2C.

b. The DG is locked out and must be started locally by the AO-resoting the lock out,

c. The DG should not-have started because the control station is in the control room manual,

d. The DG should be started but not loaded. !

QUESTION 14 POINT VALUE: 1.00:

While inserting control' rods with the Rx Manual'. Control System, the operator is directed to place the Rx Mode Switch-to the refuel position. This action: (Select the correct answer.) -

a. Allows selecting and drivingt one control rod at a time, while in shutdown, control rods cannot be driven in 'cnr out.

b. Bypasses the RSCS select blocks,

c. Allows reseting.the, mode switch:to shutdown scram without waiting for the timer to be timed out.

d. Bypasses all rod blocks except the RWM which-is also bypassed' l per-the procedure.

QUESTION 15 POINT VALUE: 1.00 The rod worth minim.izer screen was initiated by: (Select the correct answer.)

a. ARI

b. Operator request

c. Mode switch in shutdown

d. RPS trip signal l

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QUESTION: 1 RECORD: 840, LSE0120 POINT VALUE: 1.00 !

LESSON PLAN: 07-2K.01 Objectives: 05 , i The lowest INDICATED RPV WATER LEVEL which assures adequate core I cooling is: (Select the correct answer.) {

a. -60 inches

b. -40 inches

c. -70 inches

d. -37.5 inches ANSWER: 1 !

a.

...e................................................................- 4 QUESTION: 2 RECORD: 852, LSE0124 POINT VALUE: 1.00 LESSON PLAN: 07-2K.04. Objectives: 05 , 10 $

- THIS QUESTION IS NOT DEPENDENT ON THIS SCENARIO!**

During an ATWS, the jumpers have been installed'per EOP-01-LEP-02, Section 3 and the scram has been' reset. One minute later, steam flow drops below 3x10 61bm/hr. Choose the correct statement:

a. The mode switch may be placed in shutdown with no subsequent RPS trip.

b. The mode switch position is of no consequence while performing LEP-02. ,

c.

The mode switch should be left in "RUN" to facilitate control rod insertion via the Rx Manual Control System. '

d. The mode switch will activate an RPS trip when placed to shutdown.

ANSWER: 2 d.

PAGE 1 l

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A /9 U 'u) t

- " LOR-10-90-El RO" ANSWER KEY CONTINUED ** '

L QUESTION: 3 RECORD: 657, LS E0110 POINT VALUE: 1.00 i LESSON PLAN: 07-2K.06- Objectives: 08 ,

The liquid poison solution currently being injected into the reactor vessel will not bring the reactor core to a. shutdown condition due to:

(Select the correct answer.)

l a. Low natural circulation.

! b. Excessive positive reactivity.

l

c. Control rod positions.

d. Moderator temperature decrease.

ANSWER: 3 a.

QUESTION: 4 RECORD: 857, LSE0127 POINT VALUE: 1.00 !

LESSON PLAN: 07-2K.07 Objectives: 05: ,

Prioritize the performance of various sections of EOP-01-LEP-02 and choose from the following the best answer:

a. Sections 2,3,4,5,6 then 7. The procedure has already prioritized the order to be performed,

b. Sections 6 and 5 should be-performed ~first.

c. Sections 5 and 3 should be performed first.

d. Sections 3 and-4 should be performed first.

ANSWER: 4 c.

l 1,

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l l

4 o o I

- " LOR-10-90-El RO" ANSWER KEY CONTINUED **

QUESTION: 5 RECORD: 853, LSE0125 POINT VALUE: 1.00 LESSON PLAN: 07-2K.10 Objectives: 02 , 19 The SCO has directed'the BOP operator to take the main generator off. ,

line. As a result of this action: (Select the correct answer.) l

a. The Rx water level must be deliberately lowered to suppress Foc 'l power.

b. One or two SRV's will cycle.

)'

c. Reactor power will increase due~to the loss of:Feedwater j heating, j.

d. More energy will be dissipated by the circ water system.

ANSWER: 5 1 d.

i QUESTION: 6 RECORD: 863, LSE0130 POINT VALUE: 1.00 LESSON PLAN: 11-2A Obj ectivera t 13D ,

Which of the following statements best. describes the status of the RWCU System? (Select the correct answer.)

a. Both 2G31-F001 and F004 should be closed due to SLC initiation.

b. Both 2G31-F001 and F004 should be open,

c. G31-F004 should b' closed, RWCU has correctly isolated.

d.

Both 2G31-F001 and F004 should be closed due to an isolation condition. ;

=)

ANSWER: 6

d. f I

PAGE 3 n __

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- " LOR-10-90-El ROH ANSWER KEY CONTINUED **

QUESTION: 7 RECORD: 837, LSE0118 POINT VALUE: 1.00 LESSON PLAN: 14-2A Objectives: 15 ,

Which of the following statements best describe the correct operator actions for those plant conditions?

a. Terminate and prevent HPCI, RCIC, Cond. and FW, RHR and C.S.

b. Run HPCl in manual and inject to control level above -37.5 inches,

c. Run HPCI on the Test Pot and inject to control level above

-37.5 inches.

d. Shutdown and isolate HPCI.

ANSWER: 7 i d. ,

.s.

QUESTION: 8 RECORD: 843, LSE0123 POINT VALUE: 1.00 LESSON PLAN: 14-2D Objectives: 05.,

Prior to placing 'B' Loop RHR in su the operator must: (Select the correct answer.)ppression pool cooling,

a. Place the 2/3 core height overrido switch in the override position.

b. Reset the LOCA logic. ;

c. Override 2/3 core height and place the think switch in manual.

d. Line up for suppression because DW pressure is 2.5 < pool cooling with no restrictions psig.

ANSWER: 8 b.

.s.........................< ........................................

l l

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V C]- 1 I

- " LOR-10-90-El ROH ANSWER KEY CONTINUEL to l

I QUESTION: 9 RECORD: 856, LSE0126 POINT VALUE: 1.00 LESSON PLAN: 14-2F Objectives: 11 ,

choose from the following the one which best describes the ADS response to the present plant conditions:

a. 7 ADS valves will open.

i

b. ADS will not actuate.

c. Only 4 ADS Valves will open.

d. ADS will only actuate if 2 'B' RHR Pump is running.

ANSWER: 9 a.

I l

OUESTION: 10 RECORD: 70s, LSE0114 POINT VALUE: 1.00 LESSON PLAFi 14-2H Objectives: 11 ,

Assuming the SLC pumps had failed to operate in the current plant condition, you should first attempt to inject liquid poison withs (Select the correit answer.)

a. A submersible pump and CRD.

b. RWCU using borax.

=

c. Gravity feed and CRD.

d. A hydro pump.

ANSWER: 10 a.

PAGE 5

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- " LOR-10-90-El ROH ANSWER KEY CONTINUED **

QUESTION: 11 RECORD: 706, LSE0113 POINT VALUE: 1.00 LESSON PLAN: 14-2H Objectives: 13 ,

The basis for running two SLC pumps under current plant conditions is to: (Select the correct answer.)

a. avoid precipitation of sodium pentaborate.

b. avoid stagnation of solution in the lower plenum. l

c. protect primary containment.

d. protect the reactor core by shutting it down quicker.

ANSWEh 11 c.

QUESTION: 12 RECORD: 865, LSE0131 POINT VALUE: 1.00 LESSON PLAN: 15-2E Objectives 04 ,

The MFIV's are open. For the current plant conditions (Select the correct answer.)

a. This is correct because during an ATWS with the condenser available, the MSIV's should remain open. ,

b. This is correct because even though PNS has isolated, back-up nitrogen is supplying pneumatics,

c. This is incorrect because of the modo switch position with current reactor pressure.

d. This is incorrect because the operator, by procedure, should have closed the MSIV's.

ANSWER: 12 d.

PAGE 6 n

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b

- " LOR-10-90-El ROH ANSWER KEY CONTINUED ** !

QUESTION: 13 RECORD: 841, LSE0121 POINT VALUE: 1.00 LESSON PLAN: 20-2D Objectives: 23 ,

consider #4 Emergency Diesel Generator: (Select the correct answer.)

a. There is no need to start the DG because E-4 is powered from Bus 2C.

b. The DG is locked out and must be started locally by the AO reseting the lock out,

c. The DG should not have started because the control station is in the control room manual.

d. The DG should be started but not loaded.

l ANSWER: 13 d.

QUESTION: 14 RECORD: 839,. LSE0119 POINT VALUE: 1.00 LESSON PLAN: 27-2A Objectives: 09 ,

While inserting control rods with the Rx Manual Control System, the operator is directed to place the Rx Modo Svitch to the refuel position. This action: (Select the correct answer.)

a. Allows selecting and driving one control rod at a time, while in shutdown, control rods cannot be driven in or out, i

b. Bypasses the RSCS select blocks.

c. Allows reseting the mode switch to shutdown scram without waiting for the timer to be timed out.

d. Bypasses all rod blocks except the RWM'which is also bypassed por the procedure.

ANSWER: 14 b.

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- " LOR-10-90-El ROH ANSWER KEY OONT1WUED **

QUESTION: 15 RECORD: 842, LSE0122 POINT VALUE: 1.00 LESSON PLAN: 27-2B Objectives: 20 ,

The rod worth minimizer screen was initiated by: (select the correct ,

answer.)

a. ARI

b. Operator request

c. Mode switch in shutdown

d. RPS trip sig: a1 ANSWER: 15 d.

- END OF EXAM **

15.00 POINTS 100% VALUE, 12.000 POINTS 80% VALUE ESTIMATED TIME TO COMPLETE: 60 MINUTES REQUIRED

REFERENCES:

l I

PAGE 8 OF 8 l

1 l

m- _

O O

NAME:

DATE: 10/17/90 CLASS: LOR EXAM: LOR-10-90-El SRO PREPARED BY: JERNICAN GRADED BY:

ALTERNATE GRADER:

(if required)

TOTAL POINTS: 16.00 POINTS MISSED:

SCORE:

l

1. EXAM TIME LIMIT IS 1.0 HOURS

2. Do not write on exam. (except on attachments)

3. Do not write on back of pages.

4. A score of 80% is required for passing. '

5. Use only black ink on this exam. Cross out all errors with a single line and initial and date. -

I have neither given nor received help on this exam. l All work is my own.

Signature ;

l Exam Reviewer Approved l

1

C' ('b b) V

- " LOR-10-90-El BROH EXAMINATION **

QUESTION 1 POINT VALUE: 1.00 The lowest INDICATED RPV WATER LEVEL which assures adequate core cooling ist (Select the correct answer.)

a. -60 inches

b. -40 inches

c. -70 inches

d. -37.5 inches QUESTION 2 POINT VALUE: 1.00 Assume the liquid poison currently being pumped from the SLC storage tank is not reaching the reactor vessel. You will become aware of this condition whent (Select the correct answer.)

a. The SLC tank level is zero,

b. You raise the RPV water level,

c. The reactor power fails to change,

d. You start *.o cool the reactor down.

QUESTION 3 POINT VALUE: 1.00 Prioritize the performance of various sections of EOP-01-LEP-02 and choose from the following the best answert

a. Sections 2,3,4,5,6 then 7. The procedure has already prioritized the order to be performed.

l b. Sections 6 and 5 should be performed first.

l l c. Sections 5 and 3 should be performed first.

d. Sections 3 and 4 should be performed first.

PAGE 1

e i (o)

- " LOR-10-90-El SROH EXAMINATION **

QUESTION 4 POINT VALUE: 1.00 The SCO has directed the BOP operator to take the main generator off line. As a result of this action: (Select the correct answer.)

a. The Rx water level must be deliberately lowered to suppress Rx power.

b. One or two SRV's will cycle. '

c. Reactor heating, power will increase due to the loss of Feedwater

d. More energy will be dissipated by the circ water system.

9 QUESTION 5 POINT VALUEt 1.00 ,

1 The SCO, after answering the questions in table 3 of Level / Power Control, should: (Select the correct answer.)

a. Bypass Group I Low Level Isolation per Jumper Installation Procedure.

b. Emergency depressurize the reactor per the RC/P section of ,

Level / Power Centrol,

c. Restore and maintain level between +170" and +200".

d. Maintain level between +200" and TAF.

QUESTION 6 POINT VALUE: 1.00 1

The following NRC notifications are required as a result of the current plant conditions: (select the correct answer.)

a. No report required.

b. One hour red phone report.

c. Four hour red phone report.

d. Twenty four hour red phone report.

l l

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- " LOR-10-90-El SRO" EXAMINATION **

QUESTION 7 POINT VALUE: 1.00 After assessing the current status of the plant, the appropriate classification of the event would bot (select the correct answer.)

a. Nonc required

b. Unusual Event

c. Alert -

d. Site Emergency

e. General Emergency QUT,8 TION 8 POINT VALUE 1.00 Which of the following statements best describes the status of the RWCU System? (Select the correct answer.)

a. Both 2G31-F001 and F004 should be closed due to SLC initiation.

b. Both 2G31-F001 and F004 should be open.

c. G31-F004 should be closed, RWCU has correctly isolated,

d. Both 2G31-F001 and F004 should be closed due to an isolation condition.

QUESTION 9 POINT VALUE 1.00 Which of the following statements best describe the correct ope- :or actions for these plant conditions?

a. Terminate and prevent HPCI, RCIC, Cond. and FW, RHR and C.S.

b. Run HPCI in manual and inject to control level above -37.5 inches,

c. Run HPCI on the Test Pot and inject to control level above

-37.5 inches.

d. Shutdown and isolate HPCI.

PAGE 3

+

,e b)

'd

- " LOR-10-90-El SRO" EXAMINATION **

QUESTION 10 POINT VALUE: 1.00 I Prior to placing 'B' Loop RHR in suppression pool cooling, the operator must: (Select the correct answer.)

a. Place the 2/3 core height override switch in the override position,

b. Reset the LOCA logic,

c. Override 2/3 core height and place the think switch in manual,

d. Line up for suppression pool cooling with no restrictions l because DW pressure is <2.5 psig.

QUESTION 11 POINT VALUE: 1.00 1

Choose from the following the one which best describes the ADS response to the present plant conditions:

a. 7 ADS valves will open.

b. ADS will not actuate.

I c.

Only 4 ADS valves will open.

d. ADS will only actuate if 2 'B' RHR Pump is running.

QUESTION 12 POItiT VALUE: 1.00 The basis for running two SLC pumps under current plant conditions is )

to: (Select the correct answer.)

a. avoid precipitation of sodium pentaborate.

b. avoid stagnation of solution in the lower plenum,

c. protect primary containment. .

l d. protect the reactor core by shutting it down quicker, j i

i PAGE 4 j

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0 v

- HLOR-10-90-El BROH EXAMINATION **

QUESTION 13 POINT VALUEt 1.00 The MSIV's are open. For the current plant conditions (Sclect the correct answer.)

a. This is correct because during an ATWS with the condenser available, the MSIV's should remain open.

b. This is correct because even though PNS has isolated, back-up nitrogen is supplying pneumatics.

c. This is incorrect because of the mode switch position witu current reactor pressure.

d. This is incorrect because the operator, by procedure, .ald have closed the MSIV's.

QUESTION 14 POINT VALUE: 1.00 Consider #4 Emergency Diesel Generators (Select the. correct answer.)

a. There is no need to start the DG because E-4 is powered from Bus 2C.

b. The DG is locked out and must be started locally by the AO.

reseting the lock out.

c. The DG should not have started because the control station is in the control room manual.

d. The DG should be started but not loaded. >

i l

PAGE 5

Q b

(3 U

\

- " LOR-10-90-El SROH EXAMINATION **

QUESTION 15 POINT VALUE: 1.00 t While inserting control rods with the Rx Manual control System, the operator is directed to place the Rx Mode Switch to the refuel position. This action: (select the correct answer.)

a. Allows selecting and driving one control rod at a time, while ,

in shutdown, control rods cannot be driven in or out. :

b. Bypasses the RSCS select blocks.

c. Allows resoting the mode switch to shutdown scram without waiting for the timer to be timed out.

d. Bypasses all rod blocks except the RWM which is also bypassed per the procedure.

QUESTION 16 POINT VALUE: 1.00 The rod worth minimizer screen was initiated by: (Select the correct answer.)

a. ARI

b. Operator request

c. Mode switch in shutdown

d. RPS trip signal

- END OF EXAM **

i PAGE 6 OP 6 l

/

(']

- " LOR-10-90-El BROH ANSWER KEY **

QUESTION: 1 RECORD: 840, LSE0120 POINT VALUE: 1.00 LESSON PLAN: 07-2N.01 Objectives 05 ,

The lowest IFDICATED RPV WATER LEVEL which assures adequate core cooling is: (Select the correct answer.)

a. -60 inches

b. -40 inches

c. -70 inches

d. -37.5 inches ANSWER: 1 a.

I QUESTION: 2 RECORD: 57, LSE0105 POINT VALUE: 1.00 ?

LESSON PLAN: 07-2K.06 Objectives: 09 ,

Assume the liquid poison currently being pumped from the SLO storage tank is not reaching the reactor vessel. You will become aware of this condition when: (Select the correct answer.) j

a. The SLC tank level is zero,

b. You raise the RPV water level.

l' l c. The reactor power fails to change.

d. You start to cool the reactor down.

ANSWER: 2 b.

PAGE 1

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1

- " LOR-10-90-El SROH ANSWER KEY CONTINUED **

QUESTION: 1 RECORD: 857, LSE0127 POINT VALUE: 1.00 LESSON PLAN: 07-2K.07 Objectives: 05 ,

i Prioritize the performance of various sections of EOP-01-LEP-02 and choose from the following the best answer:

a. Sections 2,3,4,5,6 then 7. The procedure has already prioritized the order to be performed.

b. Sections 6 and 5 should be performed first.

c. Sections 5 and 3 should be performed first.

d. Sections 3 and 4 should be performed first.

ANSWER: 3 l c.

QUESTION: 4 RECORD: 853, LSE0125 POINT VALUE: 1.00 LESSON PLAN: 07-2K.10 Objectives: 02 , 19 The SCO has directed the BOP operator to take the main generator off line. As a result of this action: (select the correct answer.)

a. The Rx water level must be deliberately lowered to suppress Rx power.

b. One or two SRV's will cycle, i

l c. Reactor power will increase due to the loss of Feedwater l hea*'79 l

d. More energy will be dissipated by the. circ water system.

ANSWER: 4 l

l d.

l l ....................................................................

PAGE 2

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- " LOR-10-90-El SRO" ANSWER KEY CONTINUED **

QUESTION: 5 RECORD: 861, LSE0128 POINT VALUE: 1.00 LESSON PLAN: 07-2K.10 Objectives: 19 ,

The SCO, after answering the questions in table 3 of Level / Power control, should: (Select the correct answer.)

a. Bypass Group I Low Level Isolation per Jumper Installation Procedure.

b. Emergency depressurize the reactor per the RC/P section of Level / Power Control,

c. Restore and maintain level between +170" and +200".

d. Maintain level between +200" and TAF. )

l ANSWER: 5 d.

QUESTION: 6 RECORD: 168, LSE03 04 POINT VALUE: 1.00 LESSON PLAN: 07-2L Objectives: 08 ,

The following NRC notifications are required as a result of the current plant conditions: (Select the correct answer.)

a. No report required,

b. One hour red phone report.

B

c. h ur hour red phone repore.

d. Twenty four hour red phone report.

ANSWER: 6 b.

l l

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- " LOR-10-9 0-El SROH ANSWER KEY CCNTINUED **

QUESTION: 7 RECORD: 283, LSE0605 POINT VALUE: 1.00 LESSON PLAN: 07-2L Objectives: 13 ,

After assessing the current status of the plant, the appropriate classification of the event would be: (Select the correct answer.)

a. None required

b. Unusual Event

c. Alert e

d. Site Emergency

e. General Emergency ANSWER: 7 C.

QUESTION: 8 RECORD: 863, LSE0130 POINT VALUE: 1.00 LESSON PLAN: 11-2A Objectives: 13D ,

Which of the 'ollowing statements best describes the status of the RWCU System? (Sel et the correct answer.)

a. Both 2G31-F001 and F004 should be closed due to SLC initiation,

b. Both 2G31-F001 and F004 should be open,

c. G31-F004 should be closed, RWCU has correctly isolated.

d. Both 2G31-F001 and F004 should be closed due to an isolation condition.

ANSWER: 8 d.

s ....................................................................

[

PAGE 4 l

r

(

(> \_/ ,

I

- " LOR-10-90-El SRO" ANSWER KEY CONTINUED **

QUESTION: 9 RECORD: 837, LSE0118 POINT VALUE: 1.00 LESSON PLAN: 14-2A Objectives: 15 , ;

Which of the following statements best describe the correct operator actions for these plant conditions?

a. Terminate and prevent HPCI, RCIC, Cond. and FW, RHR and C.S.

b. Run HPCI in manual and inject to control level above -37.5 inches,

c. Run HPCI on the Test Pot and inject to control level above

-37.5 inches.

d. Shutdown and isolate HPCI.

ANSWER: 9 d.

QUESTION: 10 RECORD: 843, LSE0123 POINT VALUE: 1.00 LESSON PLAN: 14-2D Objectives: 05 ,

Prior to placing 'B' Loop RHR in suppression pool cooling, the operator must: (Select the correct answer.)

a. Place the 2/3 core height override switch in the override position.

b. Reset the LOCA logic,

c. Override 2/3 core height and place the think switch in manual,

d. Line up for suppression because DW pressure is 2.5 < pool cooling with no restrictions psig.

ANSWER: 10 l b.

PAGE 5

F

's (~)'r

's_

- " LOR-10-90-El BROH ANSWER KEY CONTINUED **

QUESTION: 11 RECORD: 856, LSE012 6 POINT VALUE: 1.00 ,

LESSON PLAN: 14-2F Objectives: 11 ,

I Choose from the following the one which best describes the ADS response to the present plant conditions:

I

a. 7 ADS valves will open.

b. ADS will not actuate.

c. Only 4 ADS valves will open.

d. ADS will only actuate if 2 'B' RHR Pump is running.

ANSWER: 11 l

a. i QUESTION: 12 RECORD: 706, LSE0113 POINT VALUE: 1.00 LESSON PLAN: 14-2H Objectives: 13 ,

The basis for running two SLC pumps under current plant conditions is to: (Select the correct answer.)

a. avoid precipitation of sodium pentaborate.

b. avoid stagnation of solution in the lower plenum,

c. protect primary containment.

d. protect the reactor core by shutting it down quicker.

ANSWER: 12 C.

1 i

{

PAGE 6 l

i 1

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- " LOR-10-90-El SRO" ANSWER KEY CONTINUED **

QUESTION: 13 RECORD: 865, LSE0131 POINT VALUE: 1.00 LESSON PLAN: 15-22 Objectives: 04 ,

The MSIV's are open. For the current plant conditions (Select the correct answer.)

a. This is correct because during an ATWS with the condenser available, the MSIV's should remain open,

b. This is correct because even though PNS has isolated, back-up nitrogen is supplying pneumatics.

c. This is incorrect because of the mode switch position with current reactor pressure,

d. This is incorrect because the operator, by procedure, should have closed the MSIV's.

ANSWER: 13

d. {

QUESTION: 14 RECORD: 841, LSE0121 POINT VALUE: 1.00 LESSON PLAN: 20-2D Objectives: 23 ,

Consider #4 Emergency Diesel Generator: (Select the correct answer.)

a. There is no need to start the DG because E-4 is powered from Bus 2C.

j

b. The DG is locked out and must be started locally by the AO resoting the lock out,

c. The DG should not have started because the control station is in the control room manual.

d. The DG should be started but not loaded.

ANSWER: 14 d.

PAGE 7 j

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.. ~) ('

(V s I

- HLOR-10-90-El SROH ANSWER KEY CONTINUED **

QUESTION: 15 RECORD: 839,. LSE0119 POINT VALUE: 1.00 I LESSON PLAN: 27-2A Objectives: 09 ,

While inserting control rods with the Rx Manual Control System, the l operator is directed to place the Rx Mode Switch to the refuel position. This action: (Select the correct answer.)

a. Allows selecting and driving one control rod at a time, while in shutdown, control rods cannot be driven in or out.

b. Bypasses the RSCS select blocks.

c. Allows resoting the mode switch to shutdown scram without waiting for the timer to be timed out.

d. Bypasses all rod blocks except the RWM which is also bypassed L per the procedure.

ANSWER: 15 b.

QUESTION: 16 RECORD: 842, LSE0122 POINT VALUT: 1.00 LESSON PLAN: 27-2B Objectives: 20 ,

The rod worth minimizer screen was initiated by: (Select the correct answer.)

a. ARI

b. Operator request

c. Mode switch in shutdown

d. RPS trip signal ANSWER: 16 d.

- END OF EXAM **

PAGE 8 l

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NAME: _

DATE: 10/25/90 __

CLASS: LOR EXAM: LOR-10-90-A5-SRO PREPARED BYt JERNIGAN GRADED BY:

ALTERNATE GRADER:

(if required)- )

TOTAL POINTS: 15.00-POINTS MISSED:

SCORE:

1. EKAM TIME LIMIT IS 1.0 HOURS

2. Do not write on exam. (except on attachments)

3. Do not write on back of pages.

4. A score of 80% is required for paasing.

5. Use only black ink on this exam. Cross out all errors with a single line and initial and date.

I have neither given nor received help on this exam.

All work is my own.

Signature 1

Exam Reviewer l

I Approved 4

a V. -

o o

- " LOR-10-90-A5 SROH EXAMINATION **

QUESTION 1 POINT VALUE 1.00 What sample requirements exist for the present plant' conditions?

(Select the correct answer.)

a. Isotopic analysis for dose equivalent I-131 concentration.

b. Chlorides and conductivity.

c. Isotopic analysis for I-131, I-133 and I-135.

d. none until RWCU is restored to service.

QUESTION 2 POINT VALUE 1.00 Assume that under current plant conditions the No. 4 Diesel Generator tripped due to an electrical fault. For what period of time may the plant continue to operate in this new configuration with the mode switch in RUN? (Select the correct answer.)

a. 8 hours

b. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

c. 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months i

d. 46 hours5.324074e-4 days 0.0128 hours 7.60582e-5 weeks 1.7503e-5 months QUESTION 3 POINT VALUEt 1.00 Assume that the RO has increased the running recirc pump speed to obtain a core flow of 40 M1bm/hr; what is the maximum time the reactor !

may continue to operate within the Limiting conditi.ons for Operation, before the mode switch is placed to the SHUTDOWN r.osition? (1.0 Pt.)

(Select the correct answer.)

a. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

b. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

c. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

d. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months PAGE 1

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- " LOR-10-90-A5 SROH EXAMINATION **

QUESTION 4 POINT VALUEt 1.00 After assessing the current status of the plant, the appropriate classification of the event would be: (Select the correct answer.)

a. None required

b. Unusual Event

c. Alert

d. Site Emergency

e. General Emergency QUESTION 5 POINT VALUE 1.00 When preparing to return to two 1 cop recirculation operation, which of the following will help minimize the differential temperature between loops: (Select the correct answer.)

a. raising the speed of the operating pump.

b. lowering the speed of the operating pump.

c. reducing purge flow to the operating pump.

d. reducing CRD flow.

QUESTION 6 POINT VALUEt 1.00 With the current plant condition, if HPCI received an Auto Start signal on >2 psi DW pressure: (Select the correct answer.)

a. HPCI would not auto start due to the HPCI Logic Power Failure.

b. HPCI would start and inject,

c. HPCI would start and run at 2000 RPM with no other parameters operable due to the HPCI Logic Power Failure.

d. HPCI will not start but can be run in manual.

i 4

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- " LOR-10-90-A5 BROH EXAMINATION **

QUESTION 7 POINT VALUE: 1.00 Considering the current RCIC system status, if RCIC received a valid initiation signal: (Select the correct answer.)

a. E51-F029 will not open and RCIC will trip on low suction pressure.

b. E51-F010 will open and (E51-F029 and E51-F031) will remain as is,

c. E51-F010 will open and E51-F031 will close when the E51-F010 is not fully closed.

d. E51-F029 will open and RCIC will inject into the vessel.

PAGE 3

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- " LOR-10-90-A5 SROH EXAMINATION **

QUESTION 8 POINT VALUE 1.00

- - - This question is not related to the present simulator setup ****

Unit 2 is experiencing a steam leak in the drywell with the following conditionst All control rods fully inserted MSIV's closed RPV level 50 inches Drywell temperature 250*F Drywell pressure 25 psig Suppression pool level -3 inches Suppression pool temperature 140'F If HPCI is unavailable but CRD and RCIC are bejng used for level control, thent (Select the correct answsr. )

a. Drywell sprays should be initiated to reduce drywell pressure thus preventing a RCIC trip on high exaust pressure.

b. The reactor should be emergency depressurized due to drywell pressure being in the unsafe region of the pressure suppression pressure curve. ;

c. CRD flow should be maximized since RCIC may trip on high exhaust pressure.

d. The reactor should be emergency depressurized to allow core i spray and LPCI injection.

l u

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- " LOR-10-90-A5 SRO" EXAMINATION ** ,

QUESTION 9 POINT VALUE: 1.00 For the present plant conditions, the affected DW cooltrat (select the correct answer.)

a. must be restarted.

i

b. tripped on 'B' RPS power loss.

c. should not have tripped since #4 DG is carryir.g E-4. ,

d. have tripped due to 'B' LOCA Logic power.lo9s.

QUESTION 10 POINT VALUE 1.00 For the current plant conditions, which RFP should be secured and why.

Provide two short reasons why.

QUESTION 11 POINT VALUEt 1.00 Which of the following plant initial conditions would have led to both number 2 and number 4 DG's starting: (Select the correct answer.)

a. Unit 2 house loads on the SAT.

b. Unit 1 house loads on the SAT.

l c. Number 2 DG should have started.

I

d. No initial condition would make #2 DG start from a Unit 2 bus loss.

PAGE 5

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- HLOR-10-90-A5 BROH EXAMINATION **

QUESTION 1: POINT VALUE 1.00 The ca'ase of the Reactor Building ventilation isolation ist (Select the cesrrect answer.) ,

a. Loss of power to the CAC-1264 reactor building roof vent rad l monitor,

b. Loss of power to the isolation dampers.

c. Loss of power to the stack rad monitor.

d. Loss of power to the reactor building vent rad monitor.

QUESTION 13 POINT VALUE: 1.00 For the present plant conditions which of the following would be the appropriate method for reenergizing tho 'D' RPS bus? (Select the correct answer.)

a. Transfer RPS bus 'B' to alternate power panel 2E7

b. Transfer RPS bus 'B' to alternate power panel 2EB.

c. Restart the RPS MG Set.

d. Restore 'B' RPS bus only when bus 2C has been recovered.

QUESTION 14 POINT VALUE 1.00 Explain the changes on the A channel SJAE rad monitor.

PAGE 6 i

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- HLOR-10-90-A5 BRO" EXAMINATION **

QUESTION 15 POINT VALUE: 1.00 With the present Electric Plant configuration, if an ATWS with a Group

~

I isolation were to tako place, what actions would you take to terminate and prevent injection from condensate /feedwater? (Select the correct answer.)

a. Close the FW-V6 and FW-V8 with the SULCV valve in manual closed,

b. Close the FW-V118 and'FW-V119 with the SULCV valve in manual closed,

c. Trip the 2B condensate booster pump.

d. Close the B21-F032A and B21-F032B.

- END OF EXAM **

PAGE 7 OF 7

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- " LOR-10-90-A5 BRO" ANSWER KEY. **

i i

QUESTION: 1 RECORD: 845, LSA0529 POINT VALUE: 1.00 i LESSON PLAN: 01-2C Objectives: 27 ,

What sample requirements exist for the present plant conditions?

(Select the correct answer.)

i

a. Isotopic analysis for dose equivalentfI-131 concentiation,

b. Chlorides and conductivity.

c. Isotopic analysis for I-131, I-133 and I-135,

d. none until RWCU is restored to service, i

ANSWER: 1 l C. U N

..e.................................................................

QUESTION: 2 RECORD: 147, LSA0507 POINT VALUE: 1.00 LESSON PLAN: 07-2B Objectives: 05 ,

Assume that under current plant conditions the No. 4 Diesel' Generator tripped due to an electrical fault. For what period of time may the plant continue to operate in this'ne,w configuration with the mode switch in RUN? (Select the correct answer.) i

a. 8 hours "

I

b. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months '

c. 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months i

d. 46 hours5.324074e-4 days 0.0128 hours 7.60582e-5 weeks 1.7503e-5 months '

ANSWER: 2 c.

i PAGE 1

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- " LOR-10-90-A5 SROH ANSWER KEY CONTINUED **

l QUESTION: 3 RECORD: 868, LSA0519 POINT VALUE: 1.00 LESSON PLAN: 07-2B Objectives: 05 , i Assume that the RO has increased the running recirc pump speed'to ,

obtain a core. flow of 40 Mlbm/hr; what is the maximum time the reactor l may continue to operate within the Limiting Conditions-for Operation, l before the mode switch is placed to the SHUTDOWN position? (1.0 Pt.) ;

(Select the correct answer.) l

a. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months !

l

b. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

c. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

d. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ANSWER: 3 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (1.0 Pt.) due to single Reactor Recirculation Pump operation d.

k QUESTION: 4 RECORD: 158, LSE0404 POINT VALUE: 1.00 LESSON PLAN: 07-2L Objectives: 13 ,

After assessing the current status of the plant, the appropriate classification of the event would be: (select the correct answer.)

a. None required

b. Unusual Event

c. Alert

d. Site Emergency

e. General Emergency ANSWER: 4 a.

.eee.................................................................

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- HLOR-10-90-A5 BROH ANSWER KEY CONTINUED **

l QUESTIOM! 5 RECORD: 844, LSA0528 POINT VALUE: l'00 .

LESSON PLAN: 10-2A- Objectives: 23 ,

When preparing to return to two loop recirculation operation, which of the following will help minimize the differential temperature between loops: (Select the correct answer.)~

a. raising the speed of the operating pump.

b. lowering the speed of the operating pump.

i

c. reducing purge flow t4 the operating pump,

d. reducing CRD flow.

t ANSWER: 5

d. ,

QUESTION: 6 RECORD: 847, LSA0531 POINT VALUE: 1.00 LESSON PLAN: 14-2B Objectives: 11 - ,

t With the current plant condition, if HPCI received an-Auto Start signal I

on >2 psi DW pressure: (Select the correct answer.)

I

a. HPCI would not auto start due to-the HPCI Logic Power Failure.

b. HPCI would start and inject,

c. HPCI would start and run at 2000 RPM with=no other parameters operable due to the HPCI Logic Power Failure, j d. HPCI will not start but can be run in manual.

l ANSWER: 6 b.

. . . . ....................................g eg , eg eeg ee,,e,,eee,g g g g , , , e f

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- " LOR-10-90-A5 SRO" ANSWER KEY CONTINUED **

QUESTION: 7 RECORD: 860,- LSA0539 POINT VALUE: 1.00-LESSON PLAN: 14-20 Objectives: 10 ,

Considering the current RCIC system status, if RCIC received a valid.

initiation signal: (Select the correct answer.)

a. E51-F029 will not open and RCIC will trip on low' suction pressure.

b. E51-F010 will open and (E51-F029 and E51-F031) will remain as is,

c. E51-F010 will open and E51-F031 will close when the E51-F010 is not fully closed.

d. E51-F029 will open and RCIC will_ inject into-the vessel. ,

ANSWER: 7 b.

f PAGE' 4 l

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- " LOR-10-90-A5 SROH ANSWER KEY CONTINUED **

QUESTION: 8 RECORD: 866, LSA0541 POINT VALUE: 1.00 LESSON PLAN: 14-2C Objectives: 32 ,

- - - This question is not related to the present simulator setup ****

Unit 2 is experiencin following conditions:g a steam leak in the drywell with the >

All control rods fully inserted MSIV's closed RPV level 50 inches '

Drywell temperature 250*F-Drywell pressure 25 psig Suppression pool level -3 inches

Suppression pool temperature 140'F. ,

If HPCI is unavailable but CRD and RCIC are being_used for level ,

control, then: (Select the correct answer.)

a. Drywell sprays should be initiated to reduce drywell-pressure thus preventing a RCIC trip on high exaust q pressure.

b. The reactor should be emergency depressurized due to drywell.

pressure being in the unsafe region of.the pressure' suppression pressure curve.

c. CRD flow should be maximized since RCIC may trip on high exhaust pressure.

d. The reactor should be emergency depressurized to allow core spray-and LPCI injection.

ANSWER: 8 C. ,

e....................................................................

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- HLOR-10-90-A5 BRO" ANSWER KEY OONTINUED **

QUESTION: 9 RECORD: 858, LSA0538 POINT VALUE: 1.00 LESSON PLAN: 15-2A Objectives: 09 ,

For the present plant conditions, the affected DW coolers (Select.the correct answer.)

a. must be restarted.

b. tripped on 'B' RPS power loss,

c. should not have tripped since #4 DG is carrying E-4.

d. have tripped due to 'B' LOCA Logic power loss.

ANSWER: 9 a.

l QUESTION: 10 RECORD: 855, LSA0537 POINT 1VALUE: 1.00 I LESSON PLAN: 17-2B Objectives: 13 ,

For the current plant conditions, which RFP should be secured and why.

Provide two shor* reasons why.

ANSWER: 10

'A' RFP; 'B' has no power to: FW-V4 Discharge Valve; Auxiliary oil Pump.

PAGE 6 l

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QUESTION: 11 RECORD: 848, LS A0532 POINT VALUE: 1.00 LESSON PLAN: 20-2D Objectives:-23 ,

]

Which of the following plant initial conditions would.have' led to both .

number 2 and number 4 DG's starting: (Select the correct answer.)

a. Unit 2 house loads on the SAT.

b. Unit 1 house loads on the-SAT.

c. Number 2 DG should have started'.

d. No initial condition would make #2 DG start from 0 Unit 2 ous loss.

ANSWER: 11 a.

QUESTION: 12 RECORD: 859,- LSA0501 POINT VALUE:.1.00 LESSON PLAN: 35-2A: Objectives: 8F ,

The cause of the Reactor Building ventilation isolation'is:- '(Select the correct answer.)

a. Loss of power to the CAC-1264 reactor building roof. vent rad monitor,

b. Loss of power to the isolation dampers.

c. Loss of power to the stack rad monitor,

d. Loss of power to the reactor building vent rad monitor.

ANSWER: 12 d.

1 PAGE 7

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QUESTION: 13 RECORD: 849, LSA0533 POINT VALUE: 1.00 LESSON PLAN: LORX-001 Objectives: A2 ,

For the present plant conditions which of the following would'be the appropriate method for reenergizing the 'B' RPS bus? (Select the .

correct answer.)

a. Transfer RPS bus 'B' to alternate power panel 2E7

b. Transfer RPS bus 'B' to alternate power panel 2E8.

c. Restart the RPS MG Set.

d. Restore 'B' RPS bus only when. bus-2C has been recovered.

ANSWER: 13 c.

QUESTION: 14 RECORD: 851, LSA0535 POINT VALUE: 1.00 LESSON PLAN: RTT Objectives: 02 ,

Explain the changes on-the A channel SJAE rad monitor.

ANSWER: 14 When the B train SJAE lost power, A was placed in Full Load. ,

l l

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- " LOR-10-90-A5 SRO" ANSWER KEY CONTINUED **

l QUESTION: 15 RECORD: 650,- LSA0534 POINT VALUE: 1.00 LESSON PLAN: RTT Objectives: 03 ,.

With the present Electric Plant config;uration, if an ATWS with a Group I isolation were to take place, what actions would you take to terminate and prevent injection from condensate /feedwater? (Select the l correct answer,) ;

a. Close the PW-V6 and FW-V8 with the SULCV valve in manual closed,

b. Close the FW-V118 and FW-V119 with the SULCV valve in manual closed,

c. Trip the 2B condensate booster pump,

d. Close the B21-F032A and B21-F032B.

ANSWER: 15 d.

l l

l

- END OF EXAM **

15.00 POINTS 100% VALUE, 12.000 POINTS 80% VALUE ESTIMATED TIME TO COMPLETE: 63 MINUTES REQUIRED

REFERENCES:

l l

PAGE 9 OF 9 L

{

NAME:-

DATE:. 10/25/90 CLASS: LOR EXAM: LOR-10-90-A5 RO PREPARED BY: JERNIGAN GRADED BY:

ALTERNATE GRADER:'

(if required).

TOTAL POINTS: 15.-00 POINTS MISSED:

SCORE:

1. EXAM TIME LIMIT IS~1.0 HOURS

2. Do not write on exam. (except on attachments)

3. Do not write on back of pages.

4. A score of 80% is required for passing. <,

S. Use only black ink on this exam. Cross out all. ,

errors with a single line and initial and date. l

)

I have neither given nor received: help cn1 this exam.

All work is my own..

Signature Exam Reviewer Approved r I-

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- " LOR-10-90-A5 ROH EXAMINATION **

i i

QUESTION 1 POINT VALUE: 1.00 i i

What sample requirements exist for the present plant conditions?:

(Select the correct answer.)

1

a. Isotopic analysis for dose equivalent I-131 concentration. }

b. Chlorides and conductivity. l

c. Isotopic analysis for I-131, I-133 and'I-135.

d. none until RWCU-is restored to service.

QUESTION 2 POINT'VALUE: 1.00 When preparing to return to two loop recirculationLoperation, which of the following will help minimize the differential temperature between=

loops: (Select the correct answer.)

a. raising the speed of the operating pump.

b. lowering the speed of the operating pump.

c. reducing purge flow'to the operating pump,

d. reducing CRD flow.

QUESTION 3 POINT VALUEt 1.00 With on >2 the current psi DW plant condition, if HPCI received an Auto Start signal pressure: (Select the correct answer.);

a. HPCI would not auto start due to'the HPCI Logic-Power Failure.

b. HPCI would start and inject.

c. HPCI would start and run at 2000 RPM-with no other parameters operable due to-the HPCI Logic Power Failure, d.

HPCI will not start but can be run in manual. '

PAGE 1 l

a

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- " LOR-10-90-A5 RO" EXAMINATION **

QUESTION 4 POINT VALUE 1.00 Considering the current RCIC system status, if RCIC received a, valid initiation signal: (Select the correct answer.) _;

a. E51-F029 will not open and RCIC will trip on low suction pressure.

b. E51-F010 will open and (E51-F029 and E51-F031) will remain so is,

c. E51-F010 will open and E51-F031 will close when the E51-F010 is not fully closed,

d. E51-F029 will open and RCIC will inject into the vesse).

i PAGE 2

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- HLOR-10-90-A5 ROH EXAMINATION **

I QUESTION 5 POINT VALUE: 1.00

- - - This question is not related to the present simulator setup ****

Unit 2 is-experiencin following conditions:g a steam. leak in the drywell with-the 2

All control rods fully inserted MSIV's closed RPV level-50 inches Drywell temperature 250'F Drywell pressure 25 psig Suppression pool level -3 inches !

Suppression pool temperature-140*F If HPCI is unavailable but CRD and RCIC are being used for level ,

control, then: -(Select the correct answer.) ;

a. Drywell sprays should be initiated to reduce drywell pressure thus preventing a RCIC trip on high exaust ,

pressure,

b. The reactor should be emergency'depressurized due to drywell '

pressure being in the unsafe region of-the_ pressure .

suppression pressure curve. '

j i

c. CRD flow should be maximized since RCIC may trip on high ij exhaust pressure.

d. The reactor should be emergency depressurized to allow core spray and LPCI injection.

i i

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v 0V i

e 5

- " LOR-10-90-A5 RO" EXAMINATION * 's QUESTION 6 POINT VALUE: 1.00 For the present plant conditions, the affected'DW coolers: (Select the correct answer.) i

a. must be restarted.

b. tripped on 'B' RPS power loss.

c. should not have tripped since #4 DG is carrying E-4.

d. have tripped due to 'B' LOCA Logic power loss..

i QUESTION 7 POINT VALUE: 1.00 The current status of the plant electrical system'affects the primary a containmer.b drainage system as follows: (Select the correct answer.)

a. Makes sump pumps start only on High High sump level,

b. Causes sump pump discharge valves-to fail. closed.

l c. Causes the sump pump flow integrators to be inoperable,

d. Makes the pumps start in recirc only.

QUESTION 8 POIN'T VALUE: 1.00 For the current plant conditions, which RFP should be secured.and why.

Provide two short reasons why.

1 l

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- " LOR-10-90-A5 RO" EXAMINATION. **

t

! QUESTION 9 POINT VALUE: 1.00 l ,

Which of the following plant-initial conditions would have led to both I number 2 and number 4 DG's starting: (Select the correct answer.)

a.

Unit 2 house loads on the SAT.

b. Unit 1 house loads on the SAT.

c. Number 2 DG should have started,

d. No initial condition would make #2 DG' start from a Unit 2 bus loss.

QUESTION 10 POINT VALUE: 1.00 The cause of the Reactor Building ventilation isolation is: (Select the correct answer.) 1

a. Loss of power to the CAC-1264 reactor building roof vent rad monitor, b.

Loss of power to the isolation dampers.

c. Loss of power to the stack rad monitor.

d. Loss of power to the reactor building vent rad monitor.

QUESTION 11 POINT VALUE: 1.00 For current plant conditions, what is the maximum reactor power '(%)

that can be generated (0.50 Pt. )1 and what plant conditions establish this maximum. power level? (0.50 Pt.)

l 1

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- HLOR-10-90-A5 ROH EXAMINATION **

}

QUESTION 12 POINT VALUE 1.00 What caused the-B Reactor Recirculation Pump to tript (Select the correct answer.)

a. Loss of 2B MG Set vent fans

b. Loss of control power

c. Loss of two AC lube oil pumps,

d. Loss of 'B' ARI Logic.

QUESTION 13 POINT VALUE: 1.00 For the present plant conditions which of the-following would be the appropriate method for reenergiz1ng the 'B' -RPS bus? (Select the-correct answer.)

a. Transfer RPS bus 'B' to alternate power panel 2E7'

b. Transfer RFS bus 'B' to alternate power panel 2E8. I

c. Restart the RPS MG Set.

d. Restore 'B' RPS bus only when bus 2C has been recovered.

QUESTION 14 POINT VALUE 1.00 Explain the changes on the A channel SJAE rad monitor. 1 PAGE 6

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- " LOR-10-90-A5 RO" EXAMINATION **

QUESTION 15 POINT VALUE: 1.00 With the present Electric Plant configuration, if an ATWS with a Group i I isolation were to take place, what actions would you take to H terminate and prevent injection from condensate /feedwater? , (Select the correct answer.) !

a. Close the FW-V6 and FW-V8 with the SULCV valve in manual closed.

b. Close the FW-V118 and FW-V119 with the SULCV valve in manual closed.

c. Trip the 2B condensate booster pump.

d. Close the B21-F032A and B21-F032B.

- END OF EXAM **

t a

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- " LOR-10-90-A5 RO" ANSWER KEY **

QUESTION: 1 RECORD: 845, LSA0529 POINT VALUE: 1.00 LESSON PLAN: 01-20 Objectives: 27 , ,

What sample requirements exist for the present plant conditions?

(Select the correct answer.)

a. Isotopic analysis for dose equivalent I-131 concentration.

b. Chlorides and conductivity. ,

c. Isotopic analysis for I-131, I-133 and I-135.

d. none until RWCU is restored to service.

ANSWER: 1 c.

QUESTION: 2 RECORD: 844, LSA0528 POINT VALUE: 1.00 LESSON PLAN: 10-2A Objectives: 23 ,

When preparing to return to two loop recirculation operation, which of !

the following will help minimize the differential temperature between l loops: (Select the correct answer.) .

a. raising the speed of the operating pump. ;

b. lowering the speed of the operating pump.

c. reducing purge flow to the operating pump. ,

d. reducing CRD flow.

l ANSWER: 2 I

a,

.......................................................... ..g .a.g . .

1 l

l

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- " LOR-10-90-AS ROH ANSWER KEY CONTINUED ** 1

$ p QUESTION: 3 RECORD: 847, LSA0531 POINT VALUE: 1. 0 0 LESSON PLAN: 14-2B Objectives: 11:, !

With the current plant condition, if HPCI received an Auto. Start' signal on >2 psi DW pressure:. (Select the correct' answer.) .

a. HPCI would not auto . start-due to the HPCI Logic Power failure - ,

j b. HPCI would start and inject.

l c. HPCI would start and run at 2000 RPM with' no other paramators )

operable due v.o the HPCI Logic Power Failure.

=

d. HPCI wi?.ll not start but can be run in manual.

i 5

KWSNER: 3

., b.

e i

2 i QUESTION: 4 RECORD: 860, LSA0539- POINT VALUE: 1.00 j LESSON PLAN: 14-2C Objectives: 10 ,

4 2

Considering the current RCIC system status, if RCIC received a valid j initiation signal: (Select the correct answer.)

1

a. E51-F029 will not open and RCIC will trip'on low suction

pressure.

s

. b. E51-F010 will open and (E51-F029 and E51-F031) will remain as is.

I

c. E51-F010 Will open and E51-F031 will close when the E51-F010 is not fully closed.

-j d. E51-F029 will open and RCIC will. inject into the vessel.

~

ANSWER: 4 b.

i a

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=

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- " LOR-10-90-A5 RO" ANSWER KEY CONTINUED **-

1 QUESTION: 5 RECORD: 866, LSA0541 POINT VALUE: 1.00 ;

. LESSON PLAN: 14-2C Objectives: _32',

- - - This question is not related to the present simulator setup ****

Unit 2 is experiencing a ste'am leak in the drywell with the l following conditions:

All control' rods fully inserted MSIV's closed' RPV level 50 inches Drywell temperature 250*F Drywell pressure 25 psig Suppression pool level -3 inches Suppression pool temperature 140'F If HPCI is unavailable but CRD and RCIC are being used for level control, then: (select the c.orrect answer. )

a. Drywell sprays should be initiated to reduce drywell pressure thus Freventing a RCIC trip on.high exaust pressure,

b. The reactor .enould be emergency-depressurized due to drywell- 3 pressure be.ng in the unsafe region of the pressure i

suppression pressure curve.

c. CRD flow should be maximized since RCIC may trip on high l exhaust pressure.

l l

d. The reactor should be emergency depressurized to allow core I spray and LPCI injection.

\

l l

ANSWER: 5 i c.

l ....................................................................

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_ ._ _m _ . . _ ____ _ . _ _ _ _ _ _ . _ _ _ __

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HLOR-10-90-A5 ROH ANSWER KEY CONTINUED **

j QUESTION: 6 RECORD: 858, LSA0538 POINT VALUE: 1.00- )

LESSON PLAN: 15-2A Objectives: 09 ,

For the present plant conditions, the affected DW coolers: (Select the correct answer.)

a. must be restarted.

b. tripped on 'B' RPS power loss,

c. should not have tripped since #4 IX3 is carrying E-4.-

d. have tripped due to 'B' LOCA Logic power loss.

i ANSWER: 6 a.

QUESTION: 7 RECORD: 61, LSA0504 POINT VALUE: 1.00 LESSON PLAN: 15-2E Objectives: 05 ,

The current status of the plant electrical system affects the primary containment drainage system-as follows: (Select'the correct answer.)

a. Makes sump pumps start only on High.High sump. level.

b. Causes sump pump discharge valves tcnfailiclosed. 3

c. Causes the sump pump flow integrators to be inoperable,

d. Makes the~ pumps start in recirc only.

ANSWER: 7 ;

b.

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- " LOR-10-90-A5 ROH ANSWER KEY CONTINUED ** ~ l QUESTION: 8 RECORD: 855, LSA0537 PO7'..P VALUE: 1.00 LESSON PLAN: 17-2B Objectives: 13 ,

For the current plant conditions, which RFP should be secured and why.

Provide two short reasons why.

i ANSWER: 8

'A' RFP; 'B' hac no power to: FW-V4 Discharge Valve; Auxiliary Oil Pump.

4 QUESTION: 9 RECORD: 848, LSA0532 POINT VALUE: =1.00 LESSON PLAN: 20-2D Objectives: 23 ,

Which of the following plant initial' conditions would have led to both '!

number 2 and number 4 DG's starting: (Select the correct answer.) {

a. Unit 2 house loads on the SAT.

b. Unit 1 house loads on the SAT.

c. Number 2 DG should have started.

d. No initial condition would make #2 DG start from a Unit 2 bus loss.

ANSWER: 9 a.

i PAGE 5 1

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- " LOR-10-90-A5 RO" ANSWER KEY CONTINUED **

QUESTION: 10 RECORD: 859, LS A0501 POINT VALUE: 1.00 LESSON PLAM: 35-2A Objectives: 8F ,

The cause of the Reactor Building ventilation isolation ist (Select the correct answer.)

a. Loss of power to the CAC-1264 reactor building roof vent rad monitor,

b. Loss of power to the isolation dampers.

c. Loss of poder to the stack rad monitor.

d. Loss of power to the reactor building vent rad monitor.

ANSWER: 10 d.

QUESTION: 11 RECORD: 269, LSA0511 POINT VALUE: 1.00-LESSON PLAN: LOR-88-22-1 Objectives: 05 ,

For current plant conditions, what is the maximum reactor' power (%)

that can be generated (0.50 Pt.) and what plant conditions-establish this maximum power level? (0.50 Pt.)

APSWER: 11 \

66% (0.50 Pt.).

Due to only one reactor Recirculation Pump.being in service'(0.50 Pt.)

PAGE 6 t .

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- " LOR-10-90-A5 RO" ANSWER KEY CONTINUED **

QUESTION: 12 RECORD: 17, LSA0501 POINT VALUE: 1.00 LESSON PLAN: LOR-88-22-1 Objectives: 10 ,

What caused the B Reactor Recirculation Pump to trip: (Select the ;

correct answer.)

a. Loss of 2B MG Set vent fans

b. Loss of control power I

c. Loss of two AC lube oil pumps.

d. Loss of 'B'~ARI Logic.

ANSWER: 12 c.

QUESTION: 13 RECORD: 849, LSA0533 POINT VALUE: 1.00 j LESSON PLAN: LORX-001 Objectives: A2 ,

For the present plant conditions which of the following would be the appropriate method for reenergizing the 'B' RPS bus? (Select the correct answer.)

a. Transfer RPS bus 'B' to alternate power panel 2E7

b. Transfer RPS bus 'B' to alternate power panel 2E8.

c. Restart the RPS MG Set.

d. Restore 'B' RPS bus only when bus 2C has been recovered.

ANSWER: 13 c.

PAGE 7

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- " LOR-10-90-A5 ROH ANSWER KEY CONTINUED ** '

QUESTION: 14 RECORD: 851, LSA0535 POIl?T VALUE: 1.00 LESSON PLAN: RTT Objectives: 02 ,- i Explain the changes on the A channel SJAE rad monitor. l ANSWER: 14 ~l When the B train SJAE lost power, A was placed in Full Load.

QUESTION: 15 RECORD: 850, LSA0534 POINT ~ VALUE: 1.00 LESSON PLAN: RTT Objectives: 03 , ,

With the present Electric Plant configuration,11f an ATWS with~a Group- l I isolation were to take place, what actions would'you take.to !

terminate and prevent injection from condensate /feedwater? (Select the correct answer.)

a. Close-the FW-V6 and FW-V8 with the SULCV valve-in manual closed,

b. Close the FW-V118 and FW-V119 with the SULCV valve in manual closed. L

c. Trip the 2B condensate booster pump.

d. Close the B21-F032A and B21-F032B, ANSWER: 15 d.

- END OF EXAM **

15.00 POINTS 100% VALUE, 12.000 POINTS 80% VALUE ESTIMATED TIME TO COMPLETE: 61 MINUTES REQUIRED

REFERENCES:

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