Text

Exam Rept 50-440/OL-89-01 on 890626-29.Exam Results:All Crews & Individuals Passed All Portions of Exam Except One Senior Reactor Operator That Failed Written Exam
	ML20247L303
Person / Time
Site:	Perry
Issue date:	07/26/1989
From:	Todd Fish, Jordan M, Mcghee J, Morgan T, Nejfelt G; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20247L297	List: ML20247L292; ML20247L303;
References
	50-440-OL-89-01, 50-440-OL-89-1, NUDOCS 8908010208
	Download: ML20247L303 (67)
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s U.S. NUCLEAR REGULATORY COMMISSION 1

REGION III Report No. 50-440/0L-89-01 License No. NPF-58 i Docket No. 50-440 l Licensee: The Cleveland Illuminating Company 10 Center Road Perry, OH 44081 Facility Name: Perry Nuclear Power Station Examination Administered at: Perry Nuclear Power Station Perry, OH Examinations Conducted: June 26-29, 1989 NRC Examiners: T. Fish e

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Dde J. McGhee af f T. Morgan 24 f Chief Examiner: G. M. Nejfel 24 f(7'

@ , vt Date Approved By: M. J. Jordan 7[2(!97 Examination Summary

[ Date Examination administered on June 26-29, 1989 (Report No. 50-440/0L-89-01))

Written and operating requalification examinations were administered to seven Senior Reactor Operators (SR0s) and five Reactor Operators (R0s). In conjunction with the sitwlator portier, of these examinations, two shift and one non-shift crews were evaluated.

Results: The NRC passed all crews and individuals in all portioris of the examination except one SR0 that failed the written examination. The facility results satisfied the NRC criteria for parallel grading. The requalificaticn program is assigr.ed an overall rating of satisfactory. The plant showed a strong u nagement commitment to the requalification program: excellent ,

extmit:ation raterial was provided t.nd it vas observed that the licensee's r, toff was coamitted f.o further improvements in the material.

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REPORT DETAILS

1. Examiners G. Nejfelt, Chief Examiner, USNRC, Region III T. Fish, USNRC, Region I J. McGhee, Idaho Nationa:1 Engineering Laboratory (INEL)

T. Morgan, INEL

2. Exit Meeting An exit meeting was conducted on June 29, 1989, at Perry Training Center.

Cleveland Electric Illuminating Company Representatives F. R. Stead, Director, Nuclear Support Department M. W. Gmyrek, Manager, Operations D. P. Igyarto, Manager, Training M. Wesley, Supervisor, Operations Liaison with Training N. H. Johnson, Jr., Instructor, Licensing Training C. E. Persson, Instructor, Licensing Training H. L. Hegrat, Operations Engineer NRC Representative G. M. Nejfelt, Chief Examiner, USNRC T. Morgan, Examiner, INEL The following items were discussed during the exit:

a. The requalification materials that were provided were excellent.

The scope of questions asked, the scenarios conducted, and the in-plant tasks performed clearly measured expected operator knowledge. The effort expended in the development of quality requalification material is recognized. Also, the effectiveness of the licensee's systematic approach to considering various aspects of the training material, such as, importance, training cycle, and feedback, was clearly evident.

I b. During the performance of the crew simulator, the operators indepent!ently considered plant conditions and requested help, if in doubt. The fostering of this type of crew attitude by plant man 6gement is inoicative of a comitment tc excellence.

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c. The licensee comitted to develop . Job Performance Measures (JPMs) for important systw s that are presently r.ot covered (i e., main turbine, reactor water cleanup, f eedwater, and electrical diuribution).

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( .3. Examination Results Comparison

)

I' .A comparison of the examination results between the facility and the NRC grading found the grading to be very consistent.

4. Overall Requalification Program Evaluation i

The requalification program was assigned an overall program rating of l satisfactory. The evaluation criteria of NUREG-1021, Revision 5, was met. ;

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g Facility: Perry Nuclear Power Station I

Chief. Examiner:. G. M. Nejfelt J

Dates'of Evaluation: June 26-29, 1989 Areas Evaluated: Written, Oral, and Simulator Examination Results:

R0 SRO Total Evaluation Pass / Fail Pass / Fail Pass / Fail (S, M, or U)

Written Examination 5/0 6/1 11/1 S Operating

. Examination Oral 5/0 7/0 12/0 S Simulator 5/0 7/0 12/0 S Written Examination Grading: The facility grading closely matched the NRC grading.

Crew Examination Results Crew 1 .rew 2 Crew 3 Evaluation Pass / Fail Pass / Fail Pass / Fail (S, M, or U)

Pass Pass Pass S Oterall Program Evaluation j Satisfactory 1

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COURSE NUMBER OT-3058-002-05 TEST ID/ CONTROL NUMBER PERRY TRAINING SECTION WRITTEN EXAMINATION COURSE TITLE Licensed Operator Requalification - NRC ANNUAL EXAM, Scenario #07.

NAME DATE GRADED BY GRADE TEST TAKING IS AN INDIVIDUAL EFFORT: Any test misconduct is a violation of TMG-1007, Implementation of Training.

Cheating on an exam by giving or receiving help is grounds for termination of employment and, in certain cases, may be subject to criminal prosecution under federal statutes.

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TOTAL POINTS 50.00 TIME ALLOTTED 1 tour POINTS REQUIRED N/A ACTUAL TIME _

PREPARED Christopher E. Persso MMTE May 24 1989 REVIEWED Michael L. Wesley" [ [ A J h gDATE May 24, 1989 APPROVED Grecory Neifelt N/b/Jh -

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.. SSE-02 Rev. 0 Page 3 of 3 Static Simulator Lead-In i The plant was operating near full power at beginning of life. The follovir equipment was out of commission:

1. CRDH Pump 'A' for oil change.

2. NCCV Pump 'C' for coupling checks.

3. - Division I Diesel Generator for planned maintenance.

All plant equipment was in a normal lineup / operable to support Full Power Operation, with the exception that the Logic svtich is in "0FF" for Suppression Pool Makeup Train 'B' and APRM Channel 'A' is bypassed. Then a problem was encountered with the Normal Supply Breaker to Bus EH11, and the operator manually opened the normal supply breaker. A decreasing condenser vacuum was then observed.

No operator actions have been taken thus far for the breaker problem or the degraded vacuum condition.

Simulator discrepancies that may impact responses:

1. Recorders (ALL). Use recorders for present pen values only. Trending information is neither useful nor correct. For trending, use ERIS.

These values are correct.

The following ten (10) questions are related to the above scenario conditions.

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ANSVER KEY Annual NRC Requal Exam Part A, Scenario 02 l 1

Name Page no. 1 Question: A0093 Times 2 minutes Points: 2.0 QUESTION:

a. What are the Normal Preferred, the Alternate Perferred, and the Emergency power sources to EH117

b. Assuming the breaker EH1114 cannot be closed, which of these power sources is(are) presently available to supply EH117 ,

4 ANSVER:

a. Norm + LH1A (Unit 1 Startup transformer) (.50)

Alt + LH2A (Unit 2 Startup transformer) (.50)

Emerg + Div. 1 Diesel Generator (.50)

b. Alt. (LH2A) (.50)

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. ANSWER KEY j Annual NRC Requal Exam Part A, Scenario 02 1

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Name Page no. 2 ?

Question A0095

. Tiae: 3 minutes j Points: 3.0 1

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OURSTION:

Based on the present plant conditions, provide at least two (2) reasonn why the RCIC System should be placed in Secured Status.

ANSVER:

1.

2. . .Loss LossofofECC power A. to the water leg pump.

3. Loss'of RSV A.

4. Loss of ability to automatic isolation of outboard valves.

(1.5 points each for 2 ansvers) um.__m___m-__.___..___-____m..__ _ _ . - _ - _ _ . _ _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _ _ .

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ANSVER KEY

[ Annual NRC Requal Exam g Part A, Scenario 02 l

Name Page no.-3 Questions. A0099 Times 3 minutes Points: 4.0 QUES. TION:

For the current plant conditions, reactor power vill (INCREASE, DECREASE, or REMAIN THE SAME) if the RO vere to unbypass APRM Channel A. Explain.

ANSVER:

1. Decrease (1.0). ,

2. By returning APRM A to service the FLUX EST output vill be seen as 125%.

(1.5) The AFDL, set at 102%, would close the FCV's in an attempt to limit reactor power (1.5).

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- ANSVER KEY Annual NRC Requal Exam Part A, Scenario 02

Name Page no. 4 Question: A0100 Time: 5 minutes Points: 5.0 QUESTION:

a. Consider the LOAD LINIT SBTBACK circuit. Either of two (2) additional plant conditions are required to initiate a setback signal. Name them.

b. Predicts the final stable reactor power if a LDAD LIMIT SETBACK signal is generated and does not clear.

ANSVER:

a. 1. First Bypass Valve not fully shut (1.5)

2. Less than 3 Cire Water Pumps running (1.5).

b. 57-67% power (62 15%) (2.0).

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ANSWER KEY Annual NRC Requal Exam Part A, Scenario 02 Name ,.

Page no. 5 l

Question: A0096 7/ne: 4 minutes Points:- 5 points OUESTION:

Based on the current plant conditions, which of the following is a possible cause of the lowering Main condenser Vacuum condition 7

a. Insufficient circulating water flow.

b. Loss of steam seals.

c. Loss of SJAE steam flow.

d. Condenser air-inleakage.

'ANSVER: -

d.

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ANSVER KEY

.. j Annual NRC Requal Exam l Part A, Scenario 02 _

i Name Page no. 6 Question: -A0102 Timet 7 minutes Points: 8.0 t

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-QUESTION:

Explain the effects on the Suppression Pool Hakeup System if.the level of the Suppression Pool vere to decrease by three (3) feet. Include in your answer the response of both divisions of SPMU and two reasons for the response of each train.

ANSVER:

1. Division I, no response (2.0) since no valve power (1.0) and no LOCA (1.0).

2. Division II, no response (2.0) since LOGIC SVITCH is in OFF (1.0) and no LOCA (1.0). .

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ANSVER KEY Annual NRC Requal Exam

Part A, Scenario 02 Name Page no.-7 L

Question: 'A0105 Time 6 minutes Points:'7.0 QUESTION:'

Determine the position of valve E51-F064 (RCIC Outboard Steam Supply Isolation Valve).

' Justify your answer with the current plant parameter used to determine valve position.

ANSVER:

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Open (3.0) RCIC steam pressure indication is 9009. (4.0) i

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- ANSVER KEY Annual NRC Requal* Exam Part A, Scenario 02 Name Page no. 8 Outstion: A0107 Time 7 minutes' Points: 8.0 OURSTION:

If you took each of these control switches to START, would the breakers close?

a. ESV Pump A -

b. ECCW Pump A -

Justify your answers separately.

ANSVER:,

a. ESV A - No (1.0) valve F130 A unavailable (3.0).

b. ECCW A - Yes (1.0) control power available, not prevented by interlock-(3.0).

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, -ANSVER KEY Annual NRC Requal' Exam Part'A, Scenario 02 Name Page no. 9 Question: A0194 Time: 4 minutes Points: 5.0 -

CURSTION:

Based on actual process parameters or annunciators, determine if NCCW is being supplied inside the Containment and Dryvell. Justify your answer. (i.e.,

merely stating that valves should be open is not acceptable.)

ANSVER:

Yes (2.0)

Justification cannot be that valves are open. Must list an NCCW load in Containment (RR, RWCU, DW Temp, etc.) and give indications of normal parameters (3.0).

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ANSWER KEY Annual NRC Requal Exam Part A, Scenario 02 Name Page no. 10 Question: A0094 Times 2 minutes Points: 3.0 QUESTION:

Did the loss of power to the FPCC Containment Isolation kaives cause-the FPC Pumps to trip? Justify your anc.'er by using indicati'sns loated within the horseshoe area.

ANSVER:

No. (1.0).

Still have indication of FPCC flow to the upper pools -(2.0).

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PHPP No. 6390 Rev. 3/87 COURSE NUMBER OT-3058-002-05 TEST ID/ CONTROL NUMBER PERRY TRAINING SECTION WRITTEN EXAMINATION COURSE TITLE Licensed Operator Reaualificat ion - NRC ANNUAL EXAM. Part A. Scenario #06 NAME DATE GRADED BY GRADE l

TEST TAKING IS AN INDIVIDUAL EFFORT: Any test misconduct is a violation of TMG-1007, Implementation of Training.

Cheating on an exam by giving or receiving help is grounds for termination of employment and, in certain cases, may be subject to criminal prosecution under federal statutes. 1 I

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TOTAL POINTS 50.0 ,

TIME ALLOTTED _ ,,O our I

POINTS REQUIRED N/A ACTUAL TIME PREPARED Christopher E. Persso May 24, 1989 REVIEWED Michael L. Wesley a /2 / 4 h DATE May 24, 1989 APPROVED Gregory Nejfelt M _ 1 N b DATE b 2/ ./98)

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.- ~SSE-06 Rev. O Page 3 of 3 Static Simulator Lead In The plant vas initially operating at 38% power, ready to shift RR to fast speed.- All plant systems were in a normal lineup. The only inoperable equipment was NCC 'C' pump and CRCH 'A' pump.

Then a failure of ALL level instruments occurred. PEI-B13 was entered in an attempt to stabilize the plant.

Simulator discrepancies that may impact responses:

1. Recorders-(All). Use recorders for present pen values only. Trending information is neither correct nor useful. For trending, use ERIS.

These values are correct.

The following eleven (l1) questions are related to the above scenario conditions.

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ANSVER KEY Annual NRC Requal Exam Part A, Scenario 06 Name _

Page no. 1 .

Questio1: A0021 Time 4 minutes Pointst 4.0 QUESTION:

The Unit Supervisor notices the Division III Diesel Generato is running. Based on a precaution in SOI-E228 which statea that the Diesel sha'il be loaded to at least 50% for 60 minutes, he orders the 50 to parallel and load the Diesel with EH-13. Can the 50 parallel and load the Division III Diesel Generator to greater than 50% load? Explain. .

1 ANSVER: .

No, (1.0) Diesel Generator breaker vill not close with a LOCA signal (due to Div. III injection prevention or HPCS arm and depress) sealed in. (3.0) 9

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ANSWER KEY

) -Annual NRC Requal Exas 1

Part A, Scenario 06 f Page no. 2 Name i

Question: A0027 Time 7 minutes Poin t.* : 7.0 GUESTION:

vnich of the following would result if R!!R "B" injection valve, E12-F042B, control switch was taken to OPEN:

A. Valve would stroke open, the amber light would extinguish.

B. Valve vould stroke open, the amber light would stay lit.

C. Valve would not open because amber light is on.

I D. Valve vould not open because reactor pressure is too high.

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ANSVER:

B 1

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ANSVER KEY I ' . ' . .. Annual NRC Requal Exam Part A, Scenario 06 Name _ Page no. 3 Question: A0030 Times 2 minutes Points: 2.0 QUESTION:

Based on the current plant conditions, the Reactor Recire Pumps are OFF because of which of the following:

A. Reactor low water level (Level 2)'

B. Reactor high pressure (1083 psig)

C. Manual RRCS/ARI Actuation D. Manual trip pushbuttons depressed E. EOC/RPT on Main Turbine Trip

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ANSVER:

D

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Armual NRC Requal Exam !

Part A, Scenario 06 j Name Page no. 4 Questions- A0033 Times 2 minutes Points: 2.0 t

OURSTION:

From the current plant indications, choose the correct ansvers A. All scram valves are closed.

B. All scram valves are open.

C. Some scram valves are open, some scram valves are closed.

ANSVER:

B. All scram valves are open.

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.t ANSVER KEY Annual MRC Requal Exas Part A, Scenario 06 Name Page no. 5 l

l Question: A0130

- Time 3 ainutes Points: 3.0 QUESTION:

Based on the current plant status, what are the addit $ anal plant conditions that aust be present for ADS B to autoactically initiate. Include setpoints.

ANSVER:

1. RPV level less than L-3 (177.7") (1.0)

2. RPV level less than L-1 (16.5)" (1.0)

3. 105 see T/D satisfied (1.0) l

F J' - ANSVER KEY Annual NRC Requal Exam Part A, Scenario 06 Name Page no. 6 Question: A0134 Time: 5 minutes Points: 6.0 QUESTION:

A. At this time, what entry condition (s) to PEI-B13 is/are met?

' B. Do any other PEI entry conditions exist? Specify which PEI(s) if your answer is yes.

ANSVER A. 1. RPV level unknown. (2.0)

2. Scram required and reactor power greater than 4%. (2.0) n.0 B. PEI-M51/56. (2.0) yeo {l.o)

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, *- ANSWER KEY Annual NRC Requal Exam Part A, Scenario 06 l Name Page no. 7 Question: A0137 Time: 5 minutes Points: 6.0 QUESTION:

You decide to feed the vessel using the MFP. What actions must be taken to perform this evolution? (Consider only the feed system in your response and include the minimum actions required to actually cause injection in your answer.)

ANSVER:

Defeat L-8 trip (2.0)

Place SULC in manual, (2.0) and depress "0 PEN" pushbutton (2.0).

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. Annual NRC Requal Exam Part A,' Scenario 06 Name Page no. 8 Question A0179 Time 4 minutes Points: 5.0 OURSTION:

a. Specifically, what was the initiating RPS scram signalf

b. -What scram signal (s) is(are) still present?

ANSVER:

a. Hi Reactor Vater' Level (L8) (2.5)

b. Neutron monitoring system trip (or APRM upscale trip). (2.5)

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- ANSVER KEY-37:

Annual NRC Requal Exam Part A, Scenario 06 Name Page no. 9 Question: A0176 Time: 3 minutes Points: 4.0 QUESTION:

The Unit Supervisor wishes to restore bus XH-12 and start the CRD B Pump in order to insert control rods. The STA says that you are not allowed to do this for the present plant conditions. Explain why the STA is correct.

ANSVER: ,

XH12 LOCA Bypass is not allowed because level cannot be determined. ( )

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ANSVER KEY Annual NRC Requal Exam Part A, Scenario 06 Name Page.no. 10 l

i Question:' A0142 Time: 5 minutes Points: 6 points GUESTION:

List the actions that have been taken by the RO in an attempt to reduce power in this event?

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ANSVER: ,

1. Arm and depress manual scram.

2. Arm and depress manual ARI.

3. - Mode switch to shutdown.

4. RR pumps were tripped.

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.. i Annual NRC Requal Exam- !

Part A, Scenario 06 1 Name Page no. 11 Question: A0032 1 Time 4 minutes {

Points: 5 points OURSTION:

'If only 3 SRV's are capable of opening, what reactor pressure reading vill the I operators be trying to achieve to ensure that fuel temperature does not exceed 1500* F7

. ANSVER:

260 psig 4

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.'4 COURSE NUMBER OT-3058-002-05 TEST ID/ CONTROL NUMBER PERRY TRAINING SECTION t

WRITTEN EXAMINATION-Reactor Operator COURSE TITLE Licensed Operator-Requalification, NRC ANNUAL EXAM, Part B NAME DATE GRADED BY GRADE TEST TAKING IS AN INDIVIDUAL EFFORT: Any test misconduct is a violation of TMG-1007, Implementation of Training.

Cheating on an exam by giving or receiving help is grounds for termination of employment and, in certain cases, may be subject to criminal prosecution under federal statutes.

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l TOTAL POINTS 100.00 VIME ALLOTTED 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 4 POINTS REQUIRED N/A ACTUAL TIME PREPARED Christopher E. Persson W ATE May 24. 1989 REVIEWED Michael L. Wesley *,% I [d h h DATE May 24, 1989 _

APPROVED Cregory Ne jfelt [f2t d- b DATE bu #d>. /9b

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, ANNUAL EXAM' NRC Annual Requal Exam Reactor Operator - Part B Name Page no. 1 Question: B0153 Time: 5 minutes Points: 6.0 QUESTION:

With the plant operating at 100% power, you notice that reactor water level is oscillating around the level setpoint and the deviations are getting vorse. The following alarms are received on P680 and immediately cleared. Channel A is' selected for input to the Feedvater Level Control System.

- Reactor Level HI/LO L7/L4

- Reactor Level Channel Error HI You notice that the LEVEL CHANNEL A ERROR HIGH indicating light is ON.

A. Other than the ARI's, what instruction (s) should be entered to control the plant?

B. What actions should be taken to stop the oscillations or to correct the problem? ,

ANSVER:

A. ONI-C34 (3.0)

B. Place both RFPT's on manual potentiometer control and place their flow controllers to manual OR select an operable Narrow Range level instrument (3.0).

NOTE: Either answer in part B sufficient for full credit to part B.

ANNUAL EXAH NRC Annual Requal Exam Reactor Operator - Part B Name Page no. 2 Question: B0119 Time: 6 minutes Points: 6.0 QUESTION:

During full power operations a problem is encountered with Control Complex-Chiller 'A'. temperature control valve, P42-F315A, causing Chiller 'A' to trip.

Chiller 'B' is red, tagged out for maintenance. The Unit Supervisor wants tc declare Chiller 'A' Inoperable, line up Chiller 'C' to supply all the 'A' train components, and not enter Tech Specs. The Supervising Operator says that Tech Spec Action 3.0.3 must be entered even if Chiller 'C' is used. Who is correct?

Explain.

ANSVER: ,

The 5.0. is correct (2.0) SOI-P47 says that Chiller 'C' cannot be used for Tech Specs because (2.0) it does not have a Class 1E power supply (2.0).

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ANNUAL EXAH NRC. Annual Requal Exas Reactor Operator - Part B Name Page no. 3 Question: B0100 Times 3 minutes Points: 3.0 OUESTION:

Which, if any, of the following normalized jet pump differential pressure readings are not in the allowable band to meet Tech Spec Operability?

(Assume full power operation.)

Jet Pump 95 - 1.17 ,

Jet Pump.910 - 1.16 ~

Jet Pump 915 - 1.14 Jet Pump 920 = 1.11

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ANSVER:

Jet Pump 920 ,

u ANNUAL EXAM NRC Annual Requal Exam Reactor Operator - Part B a

Name Page no. 4 Question: B0186 Timer 3 minutes Points: 3.0 QUESTION:

During troubleshooting efforts on the FLUX HANUAL mode of operation of the Recire Flow Control System, an IEC Technician wishes to momentarily remove and replace a circuit card in the Flow Control Cabinet H13-P634. What actions should be taken with respect-to the Flow Control System prior to removal of the circuit card?

ANSVtL Lock up the Flow Control Valves (or Shutdown the FCV HPU's).

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* - ANNUAL EXAM 1;*I NRC Annuni R: qual Ex:a Reactor. Operator - Part B Name- Page no. 5 Question: B0181 Time: 5 minutes (

Points: 6.0 .)

9 QUESTION:

During a reactor startup you are pulling control rods to bring the reactor critical. The Unit Supervisor, in an attempt to ensure himself that you are aware of all the things you are supposed to monitor, asks you what operating conditions / parameters you are going to use to:

A. Call the reactor critical.

B. Determine that the suAH is reached.

,Vhat is your specific answer to each question?

ANSVER:

A. Constant, positive reactor period (1.0) increasing neutron count rate (1.0) with no rod motion (1.0). (Answer may contain references to actually being slightly supercritical.)

B. Neutron count rate levels out (1.5) (reactor period becomes longer) and reactor coolant temperature increases (1.5) (r-swer may refer to middle of IRM Range 7 or about 1% power.)

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, ANNUAL EXAM

~g NRC' Annual Requal Exam L

Reactor Operator - Part B Name Page no.'6 Question: B0172 Time 3 minutes Points: 4.0 OURSTION:-

q How do you perform a control rod Coupling Check? What constitutes a successful coupling check?

ANSVER:

1) Attempt to withdraw the control rod past notch 48 (1.0). 2) The check is successful if the. control rod does not go to the overtravel position (1.0) the rod overtravel alarm does not ecue on (1.0) and the Red LED which indicates Full Out on the Rod Interface System Display Mode (RDM) is ON (1.0).

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-ANNUAL EXAM

. NRC Annual Requal Exam Reactor Operator - Part B Name Page no. 7 Question: B0159 ,

Time: 7 minutes Points: 8.0 QUESTION:

Sometime after a small break loss of-coolant accider.i, the following stable plant parameters are found to exists

- Reactor Power 0%,

- Reactor Level 180",

- Reactor Pressure 600 psig,

- Containment Pressure 2.9 psig,

- Drywell Pressure 2.8 psig,

- Suppression Pool Level 30 ft.,

- Suppression Pool Temperature 140' P.

Is EMERGENCY DEPRESSURIZATION required for the current conditions? Explain.

(i.e. What limit has been exceeded, if any?)

ANSVER:

i Yes (3.0) per PEI-G42, Pigure 2, Suppression Pool Load Limit, has been exceeded, (6009 and 30 ft.) (5.0) e

ANNUAL EXAM NRC Annual Requal Exam Reactor Operator - Part B Name Page no. 8 Question: B0148 Times: 5 minutes Points: 5.5' OURSTION:

With the plant at 95% power and loop A of RHR'in Suppression Pool Cooling, the Unit. Supervisor tells you to start LPCS and run it on minimum flow for 15 minutes for ISI vibration readings. Would you violate any operational limitations if you follow his orders? Justify your answer.

ANSVER:

Yes (2.0) P&L in SOI-E21 says that LPCS may not be provided with enough minimum flow if RHR A is in test or Suppression Pool Cooling Mode. (3.5) a 1

I i

ANNUAL EXAM !

l 1

NRC Annual Requal Exam d Reactor Operator - Part B

.Name- J Page no. 9 1 l

Question: B0107 '$

Times 3 minutes i Points: 3.0 l QUESTION:

The Unit Supervisor orders you to bypass the following control rod at the Rod

{

Action Control cabinets (RACC's): The rod is fully inserted and Hydraulically '

disarmed.

10-27 A. Determine the XX and YY binary code which is to be used to bypass this rod.

B. Who must verify the bypassing operation?

ANSVER:

A. 10 - 27 - 00100 X to Xo 01000 Y to Yo (2.0)

B. Second licensed operator or technically qualified unit tech staff individual. (1.0) l

. ANNUAL EXAM NRC Annual Requal Exam

Reactor Operator - Part B.

Name Page no. 10 Question: B0091 Timet 6 minutes Points: 7.0 OUESTION -

During a post-LOCA condition, the following conditions are found to exist Vide Range indicated level 30" Containment Temperature 205' F.

Dryvell Temperature 275' F.

RPV Pressure 200 psig Determine whether or not the Vide Range level indication can be used to determine RPV level. Include in your discussion how you arrive at you'r answer including the checks required to make the determination.

ANSVER:

1. RPV Saturatio n Temperature > Dryvell/ Containment temperature near instrument runs. (2.0)

2. Vide Range reading must be greater than Figure 2e for, corresponding Containment and Dryvell temperatures. (2.0)

3. Therefore, since graph requires vide range to read at least 24", (1.0) it is an accurate indicator. (2.0) l l

l

4 ANNUAL EXAH

<.g

, NRC Annual Requal Exam Reactor Operator - Part B-1 Name Page no. 11

,i Question B0083 Time: 4 minutes .

Points: 4.0 QUESTION .

Which checks should be made on the attached P.1 edit prior to'use to ensure that the data is valid?

- - - - a******************

ANSVER:

1. Date and time correct

2. Core flow / actual power in agreement with actual flow power

3. 1KYFLG - 0

4. CRSYM 5. WT FLAG - 2 or 5 (if 5 check VTOPS correct)

6. No failed sensors (other than 7 or 8) listed (0.67) points each part NOTE: Candidate may include that a Reactor Engineer can perform an engineering evaluation to validate the P-1 Edit and authorize its use. No credit given or subtracted for this statement.

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ANNUAL EKAM

. : 1 NRC Annual Requal Exam Reactor Operator - Part B Name Page no. 12 Ouestion: B0057 Time 7 minutes

! Points: 7.5 0UESTION -

- During a plant startup the Reactor Operator selects all IRH drives and' starts to drive the detectors out of' the core just af ter taking the reactor mode switch to RUN. He notices that the IN light does not extinguish for IRH 'C' and there is no change in the recorder reading for IRM 'C'. What operator actions are required for this condition? Include in your answer the actions to be taken if the condition is not corrected.

ANSWER ,

Stop rod withdrawals (1 5) and activities with potential to increase reactor power-(1.5) verify power available to drive motor (1.5) try to move in opposite direction (1.5) bypass channel output to prevent rod block / scram (1.5) (have I&C de-energine high voltage power if required).

9

p. - _ _ _ _ __ .,_ _ _ _ _..__. . , _ _ . - _ _ g ANNUAL EXAM

-, NRC Annual Requal Exam Reactor Operator - Part B Name Page no. 13 I Question: B0050 Time: 5 minutes i Points: 5.5 QUESTION During performance of the Daily Surveillance Logs, the level indication for the Standby Liquid Control Storage Tank level reads 4800 gallons, and the Chemistry Unit reports Boron concentration in the SLC Storage Tank is 13.0%.

1. Based on the above information, does the SLC System meet minimum concentration requirements for Operability? Cite a reference.

2. What two (2) other parameters must be within limits to ensure SLC System Operability (include the limits)?

ANSVER YES - (1.0) falls within graph 3.1.s.1 of Tech Specs (2.5).

Tank Temperature 1 70' F. (1.0)

Pump Suction Temperature 2 70' F. (1.0)

I

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -. - _ _ __.__________J

, ANNt!AL EXAH NRC Annual Requal Exam Reactor Operator - Part B Name .

Page no. 14 Question: B0034 Times 3 minutes Points: 4.5 OCSTION For each of the following accident conditions, determine if adequate core cooling is assured (answer YES or NO). Consider each case independently.

a. No inf ection or alternate injection system running, Reactor level -120",

decreasing, Reactor pressure at 900 psig, one (1) SRV open,

b. No injection or alternate injection system running, Reactor level below bottom of active fuel (BAF), Reactor pressure at 900 psig, one (1) SRV open.

c. No injection or alternate injection system running, Reactor level below bottom of active fuel (BAF) Reactor pressure at 500 psig, one (1) SRV open.

d. No injection or alternate injection system running, Reactor level below bottom of active fuel (BAF), Reactor pressure at 0 psig, eight (8) SRV's open.

ANSVER

a. Yes

b. Yes

c. No

d. No (1.125 point each) h

. e:

1 i

ANNUAL EKAH !

.- \

NRC Annual Requal Exam i Reactor Operator - Part B q

Name Page no. 15 Question: B0016 Time: 7 minutes I Points: 7.0 QUESTION:

8 Assume the following Main Generator conditions l j

H2 Pressure reads 60 psig on N35-R161. Meter N41-R017 reads .85 legging.

Present Load is 800 MWe.

a. Determine the maximum HWe load permitted.

b. Predict the corresponding HVARS for the maximum permitted megawatt load.

c. For these maximum allowed conditions, what is the limiting generator component?

- - - - A*********************************************************

ANSWER:

a. 1050 MWE 25 HVe (3.0)

b. 650 MVARS (lagging) i 25 HVARS (or HVAR corresponding to answer for part a)

(3.0)

c. Generator field (or field or field heating) (1.0)

NOTE: Error carried forward allowed for part b.

9 l

I i

l 1

g-

, ANNUAL EXAM NRC Annual Requal Exam Reactor Operator - Part B Name Page no. 16 Question: B0012 Time: 5 minutes Points: 6.0 QUESTION:

Which of the below statements is(are) NOT correct with regards to Safety Tagging (more than one statement may.be incorrect).

a. When locks are used in conjunction with red tags, the locks should be placed on the component prior to the tag being placed.

b. Red and white tags are not permitted to be attached to the same device at the same time.

c. During emergency conditions as declared by the Shift Supervisor, the US may direct the use of a " human" red tag.

6

d. A valve may be red tagged in the open position to provide relief protection.

e. A breaker may be red tagged closed to provide er.ergency power.

( f. Yellow tags are required for all temporary groured connections.

i ANSVER:

a., e. (3 points each) l l

l

ANNUAL EXAM NRC Annual Requal Exam Reactor Operator - Part B Name Page no. 17 Question: B0009 Time: 5 minutes Points: 6.0 QUESTIDH During power operations, Reactor Recire Pump 'A' trips and is not recoverable.

You observe the following plant parameters; TOTAL CORE FLOV -

45 X 106 lbm/hr APRM Power - 60% rated Vhich a4: tion below is correct for the current plant conditions?

a ., Reduce 'B' loop flow to less than 45% rated loop flow.

b. Reduce reactor power with cram rods to less than ~ 47% power.

c. Determine the APRM and LPRH noise levels at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and 30 minutes after each 5% power increase.

d. Arm and depress the RPS Manual Scram Pushbuttons, e.

The Reactor Mode Svitch must be in at least STARTUP/ HOT STBY no more than 8 hour- sfter the pump trip.

- - - - mce***********************************a*********************************

ANSVER:

d.

1:

[ ANNUAL EXAH i

NRC Annual Requal Exam

] Reactor Operator - Part B j :

' Lame Page no. 18-Question: B0005 Time: 4 minutes Points: 4.0

-QUESTION:

1 Which of the following statements in correct with regards to shift staffing

. requirements?

a.' The licensed operator at the controls may take temperature readings on the Division 1 Leak Detection panel (R13-P632) in response to a RCIC ISOL TIMER RUNNING ST TNL TEMP HI annunciator.

b.. The licensed operator at the controls may shift the Off-Gas System from the AUTO mode to the TREAT Mode during a plant startup per 101-1.

c '. The licensed operator at the controls may start the Motor Driven Fire Pump if needed during fire fighting efforts.

I

- - - - (*************************

ANSVER:

c.

~ ANNUAL EXAM o

+

NRC Annual Requal Exam Reactor Operator - Part B Name Page no. 19 Ques. tion: B0004 Time: 4 minutes Points: 4.0 QUESTION:

Which of the below listed individuals may be allowed to make changes to the Reactor Recirc Flow Control valve position at full power without direct supervision?

a.' An unlicensed System Engineer to check valve response, providing the consent of the licensed operator at the controls and the Unit Supervisor is

>>btained.

b. An unlicensed individual in the SRO Training Program providing the consent of the licensed operator at the controls and the Unit Supervisor is-obtained,

c. The on-coming Unit Supervisor, providing the knowledge and consent of the licensed operator at the controls is obtained.

~

. d. The on-coming Shift Supervisor, providing the knowledge and consent of the licensed operator at the controls and the US is obtained.

e. An individual assigned to the shift in order to fulfill,his 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months on-shift requirement of the Accelerated Requalification Program.

- - - - +*******************

ANSVER: d E

-_-___-____._._.s _ _ _ _

e.- w* f

, s. .'

PNPP No. 6390 Rev. 3/87 COURSE NUMBER OT-3058-002-05 TEST ID/ CONTROL NUMBER PERRY TRAINING SECTION WRITTEN EXAMINATION Senior Reactor Operator COURSE TITLE Licensed Operator Requalification - NRC ANNUAI, EXAM. Part B NAME DATE GRADED BY GRADE TEST TAKING IS AN INDIVIDUAL EFFORT: Any test misconduct is a violation of TMG-1007, Implementation of Training.

Cheating on an exam by giving or receiving help is grounds for termination of employment and, in certain cases, may be subject to criminal prosecution under federal statutes.

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TOTAL POINTS 100.00 TIME ALLOTTED '? hours POINTS REQUIRED N/A ACTUAL TIME PREPARED Chri st opher E. Persso DATE May 24 1989 REVIEWED Michael L. Wesley 7 I M h)fa h DATE May 24, 1989 _

APPROVED Gregory Ne.i felt ((l1 Mf[h' t OATE [d<4~< 26 /N

! O.I !/

-. . .!' );

ANSVER KEY

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NRC Annual Requal Exam Senior Reactor Operator - Part B Name Page no. 1 Question: B0193 Time 8 minutes Points: 9.0 QUESTION:

a. Plant conditions at 0100 on May.1, 1988;

1. Reactor Power is 100%.

2. HPCS System is declared Inoperable.

What is the first Tech Spec action which is required to be implemented and by what time must it be complettd7

b. Plant conditions change at 0100 on May 2, 1988;

1. One ADS valve is declared Inoperable.

What actions are required to be implemented and by what time must they be completed? (Four required.)

c .- Plant conditions change at 1200 on May 2, 1988;

1. The Reactor ic in Operational Condition 2.

2. The ADS valve is returned to OPERABLE status.

Can you return the plant to 100% pover?

- - - - (-A*****

ANSVER:

a. 0100 May 15, 1988 (0.5) - Restore HPCS system to OPERABLE. (1.0)

-b. 0200 May 2, 1988 (0.5) - Initiate plant shutdown. (1.0) 0800 May 2, 1988 (0.5) - Be in at least Startup. (1.0) 1400 May 2, 1988 (0.5) - Be in at least Hot Shutdown. (1.0) 1400 May 3, 1988 (0.5) - Be in at least Cold Shutdown (0.5) or have l Reactor Pressure less than or equal to 100 psig.(0.5) l c. _No. (1.5) l

ANSWER KEY s

NRC Annual Requal Exam Senior Reactor Operator - Part B Name Page no. 2 Question: B0158 Time 7 minutes Points: 8.0

' QUESTION:

Due to a loss of all reactor water level indication, you are operating the plant in accordance with PEI-B13, Attachment 4. The following conditions currently exists:

- Two hours have elapsed since the scram.

- RPV level' instrumentation is available (but level indication is still undetermined).

- All control rods are inserted.

- The MFP is running.

- Containment pressure'is 0.5 psig.

- Drywell pressure is 1.2 psig.

- Dryvell temperature is 185' F.

- Eight SRV's are open.

- Reactor pressure is 130 psig.

- Reactor water level is pegged high on all indicators.

If injection into the vessel is to be terminated to attempt to restore level indication, how long can the operators wait for level indication to be restored while not injecting?

- - - - Li*********************

ANSWER:

6 minutes (t 30 seconds) (8.0) l

4 . ..

ANSVER KEY

'

NRC Annual Requal Exam Senior. Reactor Opecator - Part B Name Page no. 3 Question: B0144 Time: 4 minutes Points: 4.0 OURSTION:

The plant is in a Refuel Outage. During Core Alterations, the Refueling Supervisor volunteers to revise a number of surveillance instructions while he is on duty on the Refuel. Floor.

As the SS/US, would you allow /not allow the Refuel Floor SRO revise the procedures? Justify your answer.

ANSVER:

Not allow (1.0) cannot assume additional duties while he is the Refuel SRO.

(3.0).

- _ _ - _ _ _ _ _ _ _ ____e_-_ .

i

', , ' ANSWER KEY

.. i NRC Annual Requal Exam Senior Reactor. Operator - Part B )1

~Name Page no. 4 j 1

Question: B0117 !

Time: 4 minutes l Points: 3.5 OURSTION:.

During full power operations, a problem is encountered with Control Complex Chiller 'A' temperature control valve, P42-F315A, causing Chiller 'A' to trip.

Chiller B and C are not available. The Unit Supervisor enters Technical Specification Action 3.0.3. Do you agree with his decision? Explain.

ANSVER:

Yes (0.5). Both trains of Control Room Emergency Recirculation are INOPERABLE.

(1.5) In OP CON 1, no action statement exists for BOTH trains INOPERABLE.

(1.5) 6 I

i l

_______ __-_:_____=______________-__________

. .x________________

x-

,, ANSVER KEY NRC Annual Requal Exam Senior Reactor Operator - Part B Name Page no. 5 Question: B0106 Times 7 minutes Points: 7.0 t

OURSTION:

During a plant startup, the first four (4) control rods in Group 1 listed on the pull sheet are all declared Inoperable for reasons other than being mechanically bound. All four (4) rods are fully. inserted and hydraulically disarmed and verified to be separated by two control cells in all directions. The Unit Supervisor wishes to bypass all four rods at the RACS cabinets and continue the startup. Do Tech Specs allow these actions. Site the specific reference used to justify your answer.

'ANSVER:

No. (1.0)

Tech Spec 3.1.4.2 Action b.2 (3.0) prohibits bypassing more than three (3) control rods in any RPCS group (3.0).

1 i

i I

l I

l i

1

. _ _ _ . _ :-__- w --. _ _ _ _ - -__ _ -

ANSVER KEY NRC Annual Requal Exam-Senior Reactor Operator - Part L Name Page no. 6 l Question: B0029 Time: 8 minutes Points: 4 S-QUESTION:

For each of the following conditions, provide the correct Emergency '

Classification. Include the specific Emergency Action Levels to support your classification.

a. Four (4) hours ago, UNIDENTIFIED LEAKAGE was calculated to be 7 gpm. It has slowly increased to 8 gpm. The plant has been operating at power during this time.

b. Security personnel report that the Main Turbine casing has failed following an overspeed trip.

c. Reactor water chemistry results indicate 230 uci/cc DOSE EQUIVALENT IODINE and reactor water level is -20".

ANSVER: ,

a. Unusual Event (1.5) A.I.3 (1.33)

b. Alert (1.5) K.II.5.b (1.33) .

c.-Site-Area-Emergr--(h5) B.IIIT1-(1TSS) OAM

r _- _- - _ _. - - _ ..

I

. .. . 't ANSVER KEY l NRC Annual Requal Exam Senior Reactor Operator - Part B Name Page no. 7 1

Question: B0090 Time 7 minutes Points: 7.0 QUESTION:

During a post-LOCA condition, the following conditions are found to exist:

Vide Range indicated level 20" Containment Temperature 205' F.

Drywell Temperature 275' F.

RPV Pressure 200 psig Determine whether or not the Vide Range level indication is an accurate indication of actual RPV level. Include in your discussion how you arrive at your answer including the checks required to make the determination.

ANSVER:

1. RPV Saturation Temp > Drywell/ Containment temperature near instrument runs (2.0).

2. Vide Range reading eust be greater than Figure 2e for corresponding Containment and Drywell temperatures (2.0).

3. Therefore, since graph requires wide range to read at least 24" (2.0)it is NOT an accurate indicator (1.0).

_ . _ _ _ _ _ _ _ _ _ - _ . _.U - .a r . -

.- ANSVER KEY NRC Annual Requal Exam

-Senior Reactor Operator - Part B Name Page no. 8 Questions. B0085 Time: 4 minutes Points: 4.0 OURSTION:

During full power operation, rapid unloading of the Hain Turbine is. required due to a vibration problem. Which of the below best describes the actions required to unload the turbine without generating a Reactor Scram:

a. Decrease Recire flow to 52 X 106lbm/hr - perform SVI-C11-T1022 -

insert control rods to <TSV/TCV scram setpoint - downshift RR Pumps -

trip the Main Turbine..

6

b. Decrease Recire flow to 52 x 10 lbm/hr downshift RR Pumps - transfer station loads - if power is < TCV/TSV scram setpoints, trip the Main Turbine.

0

c. Decrease Recire flow to 52 X 10 lbm/hr - insert controls rods to the 80% rod line - downshif t RR Pumps - insert CR's to < TSV/TCV scram setpoint - trip the Hain Turbine.

d. Decrease Recire flow to 52 X 106 lbm/hr - insert CRAM rods - downshift RR Pumps - insert CR in sequence to < TCV/TSV scram setpoint - trip the Main Turbine.

ANSVER:

C.

ANSVER KEY

.0

NRC Annual Requal Exam Senior Reactor Operator - Part B Name ,, __

Page no. 9 Question: B0072 Times- 5 minutes Points: 4.5 OUESTION:

The unit is' operating at 85% power just prior to shif t change. The oncoming

' Unit Supervisor calls in sick. The onshift Unit Supervisor has an important meeting and must get off duty at shif t change. The Shift Supervisor cannot get another Unit Supervisor by shift change. Can the Shift Supervisor allow the onshift Unit Supervisor to go home and'get a replacement Unit Supervisor within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ? Justify your answer.

ANSVER:

No, (0.5) note to Tech Spec table 6.2.2-1 or PAP-0110, Section 6.1.2, specifically prohibits use of 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months provision for late or absent relief crew members. (4.0)

G l

. 'l

n. ;

, ANSVER KEY NRC Annual Requal Exam Senior Reactor Operator - Part B Name Page no. 10 Question: B0056 Time: 4 minutes

Points: 5.0 OUESTION:

Due to an accident with fuel damage and potential for Containment failure, the Shift Supervisor declares a General Emergency at the plant. During the initial

-notifications, the State and Counties are given protective action recommendations of " precautionary shelter" to two miles. Is this the correct protective action recommendation? Justify your answer.

ANSVER:

No (1.0), (at the Ceneral Emergency level, i.n addition to precautionary shelter to two miles), the three downvind sectors should be sheltered to 5 miles (4.0).

e

- _ - - _ _ - _ _ _ . - _ - _ _ . - _ - _ . _ _ ___l - ._ .-_ _ f

... ANSWER KEY NRC Annual Requal Exam Senior Reactor Operator - Part B-Name! Page no. 11- .

Question: .B0040 Time 6 minutes Points: 5.5 0URSTION During startup of'the Circ Vater System, valve N71-F020A (Cire Pump Discharge

, Valve) blows a fuse during stroking. The Unit Supervisor' orders the fuse

' removed and replacc4.

a. Which' drawings (in order of preference) must be used to determine the correct fuse size and type to insert?

b. If fuse Ate is not specified on the drawing, what two (2) limitations are

.placed on the replacement fuse?

c .' .Is independent verification of correctness required for removal and replacement of this fuse? Explain.

'ANSVER:

a. 208/258 - 206/256 - 209/259 (2.0)

(elementals) (one-lines) (interconnecting diagrams)-

b. Correct size, (1.0) and voltage.

important (1.0).

e.S

c. No (4,49 - not safety related (1.0).

.6 0

w _ - _ _ _ _ __ ._

,Y

M-

.,_ ANSVER KEY:

_i NRC Annual Requal Exam Senior Reactor Operator - Part B Name Page no. 12 ,

-l 1

Question: B0031 {

Time: 10 minutes '

Points: 11.0 QUESTION:

Determine the MOST LIMITING NRC Notification requirement (e.g. Immediate, one hour,.four hour, etc.) for each of the below stated events / conditions.

l

a. An HP Supervisor informs you that a maintenance worker has received an exposure of 400 Rems to his hand while handling a CRD coupling spud.

b. During power operations, Suppression Pool average temperature is 112' P.

c. Reactor water level momentarily dropped below the trp of active fuel during a loss of all high pressure injection systems.

d. Reactor water level dropped to below level 2 causing HPCS and RCIC to start, but the HPCS injection valve failed to open.

e. A startup source is received at the varehouse which reads 225 mrem on contact with the package.

- - - - kA**********************

ANSVER: ,

a. Immediate

b. I hour

c. I hour

d. I hour

e. Immediate (2.2 points each)

_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ __-__a A

l1 .

ANSWER KEY 4 -

NRC Annual Requal Exam Senior Reactor Optrator - Part B Name Page no. 13 Question: B0026 Time: 6 minutes Points: 6.0 QUESTION During the performance of SVI-C71-T0039, valve B21-F022B (in$ card MSIV)' fails to close. In accordance with the applicable Tech Spec 3.6.4, the associated penetration must be isolated. Specifically, which valves must be addressed'to comply with the Action Statement?

ANSVER B21-F028B (outboard MSIV), B21-F067B (MSIV upseat drain valve), E32-F001E (MSIV-LCS isolation valve). (2 points each)

NOTE: No credit subtracted if B21-F022B listed.

0 - - ____._-_---_--.-Q

ANSVER KEY NRC Annual Requal Exam Senior n? actor Operator - Part B .

1 Name Page no. 14 Question: B0024 Time 6 minutes Points: 6.0 QUESTION The plant is operating at 100% power.when your RO reports that Reactor Narrow Range Water Level indicator C (transmitter number IC34N004C) is pegged low while N004A and.B agree and indicate properly. Choose the correct action to take from the list below.

a. Declare the associated ADS or ECCS inoperable.

b. Place the inop" channel and/or trip system in the tripped condition within one (1) hour.

c. Restore the inoperable channel to OPERABLE within 7 days or be in at least STARTUP vithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d. Restore the inoperable channel to OPERABLE vithin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN vithin the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

e. No action is required since only two (2) OPERABLE level channels are required.

f. No action is required since the C34 level instruments are not Teca Spec related.

ANSVER C.

L abw '-

. ANSVER KEY

> ?"

NRC Annual-Requal Exam SenJor Reactor Operator - Part B Name Page no. 15 Question: B0012 Time 5 minutes Points:' 6.0 OUESTION:

Which of the belov statements is(are) NOT. correct with regards to Safety Tagging (more than one statement may be incorrect).

.a. When locks are used in conjunction with red: tags, the locks should be placed on the component prior to the tag being placed.

b. Red and white tags are not permitted to be attached to the same device at the same time,

c. During emergency conditions as declared by the Shift Supervisor, the US may direct the use of a " human" red tag.

d. A valve may be red tagged in the open position to provide relief protection,

e. A breaker may be red tagged closed to provide emergency power.

f. Yellow tags are required for all temporary ground connections.

ANSVER:

a., e.

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NRC Annual Requal Exam Senior Reactor Operator - Part B Name Page no. 16 Question: B0009 Time: 5 minutes Points: 5.0 OUESTION:

During power operations, Reactor Rectre Pump 'A' trips and is not recoverable.

You observe the f'llowing plant parameters; 6

TOTAL CORE FLOV - 45 x 10 lbm/hr APRM Power - 60% rated Vhich action below is correct for the current plant conditions?

a. Reduce 'B' loop flow to less than 45% rated loop flow,

b. Reduce reactor power with cram rods to less than ~ 47% power.

c. Determine the APRM and LPRM noise levels at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and 30 minutes after each 5% power increase.

d. Arm and depress the RPS Manual Scram Pushbuttons.

e. The Reactor Mode Switch must be in at least STARTUP/ HOT STBY no more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the pump trip.

ANSVER:

d.

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