Text

Exam Rept 50-440/OL-90-01 on 900514-18.Exam Results:Nrc Passed All Individuals in All Portions of Exam.One Nonshift Crew Failed Sumulator Portion
	ML20043H732
Person / Time
Site:	Perry
Issue date:	06/19/1990
From:	Bielby M, Hanek J, Jordan M, Tyner C; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20043H729	List: ML20043H728; ML20043H732;
References
	50-440-OL-90-01, 50-440-OL-90-1, NUDOCS 9006260372
	Download: ML20043H732 (67)
	v • d • e

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i U.S. NUCLEAR REGULATORY COMMISSION REGION 111 j

t Report No._ 50-440/0L-90-01 Docket Hos. 50-440.

License No. NPF-58 Licensee: The Cleveland Electric 111uminating Company-10 Center Road Perry, OH 44081 Facility Name: Perry Nuclear Power Station Examination Administered At:

Perry Nuclear Power Station Perry, OH 3

Examination Conducted: May 14-18, 1990 Rlli Examiners:

6//r/po-J. Hanek Date k

b/N//0 p

C. Tyner Date Chief Examiner:

h, 6//r/fo

-M. Bielby-Date

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Approved By:

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0' fl.Jfdpdan,-Chief Date Operator Licensing Section'l Examination Summary Examination administered on May 14-18, 1990 (Report No. 50-440/0L-90-01)).

Requalification Examinations were administered to eight Senior Reactor Operators (SR0s)andfour'ReactorOperators(R0s).

Because of a previously satisfactory Requalification Program evaluation, the NRC observed two

. operators per examiner in the simulator, and each operator performed five (vice ten) Job Performance Measures (JPMs) and answered ten (vice twenty) JPM questions. One shift and two non-shift crews were evaluated.

Results: The NRC passed all: individuals in all portions of the examination; however, one non-shift crew failed the simulator portion.

Independent grading by the facility and NRC satisfied the criteria for parallel grading contained in NUREG 1021, Operator Licensing Examiner Standards, ES-601. Revision 5.

As a result, the Perry Requalification Program is assigned an overall rating of SATISFACTORY.

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Operator connunication'.-

--. 0perator persiste'nce at returning to correcti.ve: actions i-:

Facility evaluator) demeanor. -

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. Weaknesses,(Refer?toparagraph.2b1for. details):

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. Operator uselof Perry Emergency, Instructions;(PEls);

LDefinition'ofLscenariocritica1(task (s)..

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REPORT DETAILS

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-Examiners

,M..Bielby, Sr.,-Chief Examiner, NRC, Region 111 C. Tyner, Examiner, Idaho' National Engineering Laboratories.

J. Hanek, Eraminer, Idaho National Engineering Laboratories m

2.

Exit Meeting 1,

An exit meeting was conducted on May 18, 1990 at'the Perry Training.

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Facility, j

f Cleveland Electric Illuminating Company Representatives:-

o D. P. Igyarto, Manager, Training M. W Gmyrek,- Manager, Operations j

M. Wesley, Supervisor, Operations Training q

N.' H. _ Johnson, Jr., Instructor, Requal License Training _

1 H. L.'Hegrat,. Licensing Compliance Engineer

-i NRC Representatives:

M.;Bielby, NRC Chief' Examiner 1

-Following a pre-exit meeting with the Training Staff,'a formal Management Exit meeting was-conducted.- The following. items'were discussed during.

J 1

these meetings:

-a.

~ Strengths

.(1) Operators communicated well.among themselves during the.

scenarios. The Shif t Supervisors periodically briefed the crew-on; current plant conditions and-future operations. :During 1

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performance of JPMs, operators clearly-indicated meters, 3

lights, and alarms they were? observing to the evaluators.

(2) As time permitted.during simulator scenarios, operators were persistent at resuming corrective action (s) on system / components.that were out of commission, and considering alternatives'to use.

l (3)': The f acility evaluators performed in a satisfactory manner-during the operating examinations. They were not observed inadvertently giving verbal or non-verbal (e.g.. body language) cues to the operators during-JPM and simulator scenario performance. They-properly recorded operator responses to JPM questions, and operator actions during JPM'and scenario performance.

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b.

Weaknesses'

~(1)Duringplant'conditionsz requiring'use of PEls; the Unit-3

. Supervisor (US) was observed relying on memory to accomplish r-initial steps, then attempting'to find the appropriate place in the procedure..In one scenario the US' appeared to be unable to-

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find.his place and ordered injection;of Standby Liquid Control-

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without securing other systems-that were already injecting (e.g., RCIC and LPCI) as required by a step in the PEl. cln addition, one of the initial PEI steps.for an ATWS condition is-to manually attempt insertion of individual rods from the P680^

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console. This method would have worked-but was never attempted. The' crew received UNSATISFACTORY performance grades-in two of-four' rating factors for COMPLIANCE /USE OF PROCEDURES and failed that competency resulting'in overall failure in-accordance with Examiner Standards ES-601,: Revision 5;, Instruction 4.

t A situation requiring'the concurrent use ofidiffer'ent PEl-sections would.. appear to increase ~the chances of missing lor

.' skipping steps. :

The use.of flowcharts and a marking pen may help alleviate this.

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problem, j

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(2). The NRC assisted your Training Staff in reviewing' the following _.

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. examination materials:

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-(a) The question format was revised to satisfy guidelines of f

, HUREG/BR-0122, Revision 4', Examiners Handbook:for 'Developingi 1

- Operator Licensing Examinations.=

=( b~) JPH procedures and, questions-were reviewed 1for-content and i

1 critical tasks. The NRC woul_d encourage' future JPM questions place more emphasis on knowledge required for

.ask performance and ensure the answerSis-nottmerely a-4

~ " procedure look-up"..

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(c) Simulator scenarios were' reviewed for.' content and' critical

-tasks. The:NRC spent a consi e rable amount of-time chenging and adding critical ta W..

c.

Training inadequa q

'f n During one scenario 'the-Reactor Operator.-(RO)_ reduced. recirculation'-

. flow and entered the Instability Region as defined by the Power-to Flow Map (recirculation flow less than 48 M1bm/hr and 100% rod line).

101-3' required the operator to arm and depress-the Manual Scram Pushbuttons. Although this action was eventually performed, there was a time delay while the R0 attempted to inform the-US whose attention was diverted to another problem.

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1 Human' Factors inadequacy:

mF, MAIN-TURB & FDW TRIP RCIC t.8, was mis _ interpreted as a RCIC turbinei DuHng' performance of one scenario 4 it was noted that alarm P680-3A-A8,:

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trip ~on reactor waterflevel 8.

One. crew: member eventually-realized; that,RCIC was still operable and-informed,the US, another crew; 3

h member then stated that the' alarm didinotiindicate a RCIC-turbine trip.

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. Examination Results. Comparison-

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'Aicomparison of th'e exam results between'the facilityy and-the NRC grading.

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was1.found to belvery consistent.

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.'Overal'1:Requalificati'n Program Evaluation f,i o

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The Requalification Program was' assigned an overa11' program rating of.

j SATISTACTDRY.: The evaluation criteria of NUREG-1021 Revision 5 was met.

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!REQU^LIFICATION PROGRAM EVALUATION ' REPORT:

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i n 'kfacilityi-Perry: Nuclear ' Generating Plant'-

1 5 Examiners:: M.iE. Bielby, Sr.

Date(s)fofEva10ation: May-14.-18 1990 i

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A LAreas Evaluated:.

Written X Oral X

-Simulator'X 1:

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= Examination:Results:

R0 SRO

. Total-.

Evaluation

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Pass / Fail Pass / Fail.

Pass / Fails (S or U)

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., Written Examination 4/0 8/0 12/0 ~

S-60p'eratingiExamination y

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. Simulator:-

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Evaluation.ofifacility written examination grading

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Written Examiration Grading.

The facility grading;closelyimatched the-NRC grading..The examination =used multiple schoice -type questions. -

q, Crew Examination Results:-

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. Crew 1?

Crew 2,

' Crew 3

-Evaluation J

Pass / Fail Pass / Fail.

--Pass / Fail

'(S'or;U) h I

e0perating Examination Pass Fail Pass 415.

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0vera11EProgram Evaluation j

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T rSatisfactory:

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1 JSubmitted:

Forwa pprcved:

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Examiner-Secti n Chief Branch Chief (6/j/7/90.

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twa.4::3 COURSE NUMBER 07-3070-000-00 TEST ID NUMBER 90-003 Control #9020015 PERRY TRAINING SECTION WRITTEN EXAMINATION COVER SHEET COURSE. TITLE NRC Requalification Exam (Part A - Static Simulator 03)

NAME SSN DATE GRADED BY GRADE RESULTS REVIEWED DATE TEST TAKING IS AN INDIVIDUAL EFFORT:

Any test mise ndu is a violation of. TMG-1C07, Implementation Tra g.

Cheating on an exam by yiving or receiving i

rounds for termination of emp.'.o t

in certain cases, may besubjecttocQ ip utron under federal statutes.

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TOTAL POINTS 12.00 TIME ALLOTTED I hour POINTS REQUIRED N/A TIME USED N/A 1

PREPARED Niles H. Jihnson AC m

DATE May 9 1990 REVIEWED Michael L. W sley M

DATE 0

, 9n WRC. APPROVED

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DATE

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SSE-03 Rev. O Page 3 of 3 Static Simulator Lead-In

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The plant was operacing near full power at end of life with all rods out.

ECCV ' A' Pump is out of commission.

Then several transients occurred, and the unit was placed in its present status. Operators took appropriate actions to combat the problem vith Recire Pump A.

No other operator actions have been taken for any other transients.

Simulator discrepancies that may impact responses:

1.

Recorders (All).. Use recorders for present pen value only.

Trending.information is neither useful nor correct.

For trending, use ERIS. These values are correct.

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ANSVER KEY NRC ANNUAL REQUAL EYAM Part A Exam, Scenario 03 OT-3070-000-00 Page no. 1 Question: A0307, Rev. 2 Points:

1.00 QUESTION:

For the current plant conditions, which of the following actions should be performed?

Reduce reactor power to less than 45% power using CRAM RODS.

a.

Reduce reactor power to within the confines of the pover/ flow map vith b.

CRAN RODS.

LArm and depress the manual scram pushbuttons, c.

6 d.

Increase flov vith Reactor Recire FCV B to 2 52 X 10 lbm/hr.

I ANSVER:

c.

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ANSVER KEY l

NRC ANNUAL REQUAL EXAM Part A Exam,-Scenario 03 j

OT-3070-000-00 1

Page no. 2 j

-Question:

A0313, Rev. 1 Points:

1.00 QUESTION:

Assume that the "A" C85 pressure instrument fails high. Which of he following vill results The CBS System vill auto transfer to the "B" pressure regulator -

a.

Control valves vill close.

j b.

The C85 System vill auto transfer to the "B" pressure regulator -

Control valves vill open.

The "A" pressure regulator vill remain in control - Control valves c.

vill'open.

d.

The "A" pressure regulator vill remain in control - Control valves vill close.

ANSVER:

c.

ANSVER KEY NRC ANNUAL REQUAL EXAH Part A Exam, Scenario 03 OT-3070-000-00 Page no. 3 Question:

A0314, Rev. 1 Points:

1.00 QUESTION:

Vhich of the following explains why the MFP Discharge Flow Control Valves (N27-F110 and N27-F0101) are partially open?

The Start-Up Level Controller is in MANUAL calling for a valve a.

open signal.

b.

The MFP Recire Control is set at '80', allowing 20% flov through the

. discharge line.

The MFP Manual Flov Controller is in MANUAL, set at 20%.

c.

d.

The Master Level Controller is calling for a valve open signal.

ANSVER c.

9

-ANSVER KEY NRC ANNUAL REQUAL EXAM Part A Exam, Scenario 03 OT-3070-000-00 Page no. 4-Question: A0315, Rev. 1 Points 1.00-OtTESTION:

Assume the Reactor Recire Pump is restored to operation. Vhat vill the generator MVe limitation be due to the loss of feedvater heating?'

a.

1250 b.

1188 c.-

1125 d.

1000 g$kkkkkkkkk h ANSVER a.

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4 ANSVER KET NRC ANNUAL REQUAL EXAM Part A Exam, Scenario 03 OT-3070-000-00 Page no. 5 Question: A0323, Rev. O Points:

1.00 OUESTION:

Vhich of the following statements is/are correct regarding Narrow Range Channel B7 If selected, an interlock prevents its use by the Feedvater Control A.

System.

B.

I6C has NOT equalized and isolated the transmitter.

C.

16C has equalized and isolated the transmitter.

D.

I6C has NOT depressed the local "Out of Service" pushbutton.

- - - - w**************

ANSVER:

i B.

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ANSVER KEY NRC ANNUAL REQUAL EXAM Part A Exam, Scenario 03 OT-3070-000-00 Page no. 6 Question: A0322, Rev. 0 Points:

1.00 OUESTION:

r

-Vhich one of the reasons listed below is correct regarding why SVI-R10-TS217, sections 5.1.3.a through e, is required to be performed within one hour?

A.

ECCV pump A vas tagged out.

B.-

One'off-site pover source has been lost.

C.

Reactor Recirculation Pump 'A' has been lost.

D.

Loop flov mismatch is >10%.

l' ANSVER:

B.

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ANSVER KET NRC ANNUAL REQUAL EXAM i

Part A Exam, Scenario 03 t

OT-3070-000-00 Page no. 7.

Ouestion: A0321, Rev. O Points:

1.00 i

OUESTION:

Consider the.RHR System only.- From the list belov,' choose which Active Tech Spec LCO's associated _vith the RHR System should NOT be entered j

i vhen the ECCV Pump vas tagged out?

.l.:

~A.

3.4.9.1 - Shutdovn Cooling l

B '.

3.5.1 - LPCI A C.

3.6.3.3 - Suppression Pool Cooling D.

3.6.3.2 - containment Spray 1

i ANSVER:

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A.

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ANSVER KEY-NRC ANNUAL REQUAL EXAM h

Part A Exam, Scenario 03 OT-3070-000-00 Page no. 8 Questions A0320, Rev. O Points:

1.00 QUESTION:

(

Vhich one of the choices below is correct regarding the status of the

'A' Recirculation. Pump-Seal?.

A.

Neither seal has failed.

B.

The outer seal has failed.

l C.

The inner seal has failed.

D.

The inner and outer seals have failed.

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~C.

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i l ANSVER KEY NRC ANNUAL REQUAL EXAM-Part A Exam, Scenario 03 OT-3070-000-00 Page no. 9 Ouestion:

A0319 Rev. O Points:

1.00 QUESTION:

Vhy is an auto transfer to slov speed NOT available for Reactor Recirculation Pump A?

l A.

The ' A' Loop discharge valve is closed.

B.

Circuit breakers 3A and 4A are open.

C.

CB-SA is open.

D.

The 'A' Loop FCV is < 10% open.

ANSVER:

A.

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ANSVER KEY NRC ANNUAL REQUAL EXAM Part A Exam, Scenario 03 OT-3070-000-00 Page no. 10 Question:

A0318, Rev.

0--

Points:

1.00 QUESTION:

What should the adjusted trip value (pressure setpoint) of the TSV/TCV scram-

-bypass setpoint be assuming that Feedvater Heater 6A vill M be-returned to service, and the final Feedvater temperature is 300? F.?

A.

f178.77 B.

$ 147.79-

-C.

5 126.68 D.

f 105.57' ANSVER C.

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ANSVER KEY NRC ANNUAL REQUAL EXAH Part A Exam, Scenari@ 03 OT-3070-000-00' Page no. 11 Question: A0324, Rev. O Points:

1.00 QUESTION:

Vhich one of the belov statements describes the potential problem with operating at the present values of reactor power and core flow?

A.

MCPR limits could be exceeded without causing a reactor scram.

B.

LHGR limits could be exceeded without causing a reactor scram.

C.

An unnecessary power to flov scram could occur.

D.

Recirculation loop temperature stratification could occur.

.ANSVER:

A.

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ANSVER KEY l

NRC ANNUAL REQUAL EXAM

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Part A Exam, Scenario 03 l

l OT-3070-000-00 Page no. 12 Question: A0325, Rev. O Points:

1 minutes OUESTION:

'Vhich.of the following describes the plant reponse, if a Main Turbine Trip vere to occur at the present plant conditions?

A.

The Reactor vould scram on high pressure.

B.

An EOC/RPT vould occur.

C.

An EOC/RPT vould NOT occur.

D.

No Reactor scram signals vould occur.

- - - - n******************************************************************

ANSVER:

B.

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COURSE NUMBER

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TEST' ID NUMBER 90-O'02 Control i 9020015 PERRY TRAINING SECTION

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WRITTEN EXAMINATION COVER SHEET COURSE TITLE NRC Recustification Exam (Part A - Statte Simulator 406)

NAME SSN DATE GRADED BY GRADE RESULTS REVIEWED DATE TEST TAKING IS AN INDIVIDUAL EFFORT:

Any test si du is a violation of TMG-1007. Implementatic Tra Cheating on an exam by giving eceiving is grounds for termimtion of e p1 ta in certain cases, may besubjecQoc 1p ution under federal statutes, w-M4J eie 7

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TOTAL POINTS 13.00 TIME ALLOTTED I hour

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'i POINTS REQUIRED N //.

TIME USED N/A.

PREPARED Niles H. hhnson

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DATE hv'9. 1990

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REVIEWED.

Michael L. Weslev

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NRC AP ROVED

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

Then a major plant transient occurred. PEI-B13 vas entered in an attempt to stabilise the plant.

i 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.

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ANSVER KEY NRC ANNUAL REQUAL EXAM Part A Exam, Scenario 06 OT-3070-000-00 Page no. 1 Question: A0610, Rev. 1 Points:

1.00 l

QUESTION:

Vhich of the following would result if RiiR "B" injection valve, E12-PO42B, control svitch vas taken to OPEN:

A.

Valve vould stroke open, the amber light vould extinguish.

B.

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

C.

Valve vould not open because amber light is on.

D.

Valve vould not open because reactor pressure is too high.

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ANSVER KEY NRC ANNUAL REQUAL EXAM Part A Exam, Scenario 06 0T-3070-000-00 i

Page no. 2 Question: A0613, Rev. 1 Points:

1.00 OUESTION:

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

A.

Reactor lov vater level (Level 2)

B.

Reactor high pressure (1083 psig)

C.

Manual RRCS/ARI Ac*

'on D.

Manual trip pusht tienu 4 pressed ANSVER:

D.

ANSVER KEY NRC ANNUAL REQUAL EXAM Part A Exam, scenario 06 0T-3070-000-00 Page no. 3 Question:

A0616, Rev. 1 Points:.

1.00 QUESTION:

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.

D.

Scram valve status cannot be determined.

t ANSVER:

B.

All scram valves are open, e

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ANSVER KEY NRC ANNUAL REQUAL EXAH Part A Exam, Scenario 06 OT-3070-000-00 Page no. 4 Question: A0620, Rev. 1 Points:

1.00 QUESTION:

Predict the response of the RCIC System if the RCIC MAN INIT pushbutton i

vere armed and depressed, n.

Starts and injects the RPV.

b.

Starts and goes on minimum flov.

c.

Starts and trips due to L-8.

d.

Does not start.

ANSVER:

d.

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ANSVER KEY NRC ANNUAL REQUAL EXAH Part A Exam, Scenario 06 07-3070-000-00 Page no. 5 Question: A0622 Rev. 1 Points:

1.00 OUESTION:

Pertaining to the EPCS Injection Valve (E22-F004). The valve vill open if:

High Dryvell pressure logic for E22 is satisfied.

a.

b.

Vith RPV level < LB, the Operator resets L8 logic and manually opens the valve.

Vith RPV level < L8, the Operator resets HPCS logic and manually opens c.

the valve.

d.

Level decreases to < L2.

ANSVER:

b.

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ANSWER KEY NRC ANNUAL REQUAL EXAM Part A Exam, Scenario 06 0T-3070-000-00 Paga no. 6 Ques '. ion: A0623, Rev. 1 Points:

1.00 QUESTION:

Feedvater pumps are not available to feed the RPV; this is because a.

A Feedvater runback has occurred, b.

Feed pumps have tripped on RPV L-8.

Feedvater pumps have tripped due to RCIC initiation.

c.

d.

Condensate Booster pumps have tripped due to the Main Turbine Trip.

i ANSVER:

l b.

l

1 ANSVER KEY NRC ANNUAL REQUAL EXAH Part A Exam, Scenario 06 OT-3070-000-00 Page no. 7

+

Question: A0632, Rev. 1 Points:

1.00 QUESTION:

Vhich of the following best describes why ESV and ECC Loop A is running?

a.

RCIC auto start.

b.

Div. I liigh Dryvell Pressure initiation.

c.

Manually started.

r d.

Div. I RPV Level 1 initiation.

- - - - =***********

ANSVER:

c.

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ANSVER KEY NRC ANNUAL REQUAL EKAM Part A Exam, Scenario 06 0T-3070-000-00 Page no. 8 Question: A0640, Rev. O Points:

1.00 QUESTION:

i The U.S. has ordered the S.O.'s to preform Injection Prevention. On which of the belov systems have the S.O.'s preformed Injection Prevention?

i

a. HPCS, RHR B, RHR C

b. HPCS, RHR A RHR B

c. LPCS, RHR A, RHR C

d. HPCS, LPCS, RHR A i

- - - - t********************************

ANSVER a.

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ANSVER KEY NRC ANNUAL REQUAL EXAM Part A Exam, Scenario 06 OT-3070-000-00 Page no. 9 Question: A0639 Rev. O Points:

1.00 QUESTION:

The U.S. directs you to arm and depress both the A and B Suppression Pool Makeup Manual Initiation pushbuttons. The expected response of the Suppression Pool Makeup System would bet a.

The A train vould initiate b.

The B train vould initiate c.

The A and B train vould initiate d.

Neither train vould initiate

- - - - o******

ANSVER:

b.

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ANSVER KEY NRC ANNUAL REQUAL EXAM Part A Exam, Scenario 06 OT-3070-000-00 Pege no. 10 Question: A0641, Rev. O Points:

1.00 QUESTION:

From the conditions listed belov, select the one that vould result in an ADS initiation.

Arming and depressing the ADS A Instantaneous Logic and ADS B a.

Instantaneous Logic Manual Initiation Pushbuttons.

b.

Arming and depressing the ADS A Time Delay Logic and ADS A Instantaneous Logic Manual Initiation pushbuttons.

Arming and depressing the ADS B Time Delay Logic and ADS B c.

Instantaneous Logie Manual Initiation pushbuttons.

d.

Arming and depressing the ADS B Time Delay Logic and ADS A Instantaneous Logic Manual Initiation pushbuttons.

l ANSVF2:

l c.

I I

i I

ANSVER KEY NRC ANNUAL REQUAL EXAH Part A Exam, Scenario 06 OT-3070-000-00 Page no. 11 Question: A0644, Rev. O Points:

1.00 QUESTION:

The Unit Supervisor vants to lineup to inject outside the RPV Shroud.

Based on current plant conditions, on which of th,e belov listed pump (s) does the operator have the capability of lining-up to inject outside the Shroud?

A.

RHR A. RHR B, HPCS l

B.

RilR B RHR C, MFP C.

RHR A RHR B, MFP D.

RHR A, RER C, HPCS ANSVER:

C.

s l

l l

i ANSVP.R KEY NRC ANNUAL REQUAL EXAM Part A Exas, Scenario 06 0T-3070-000-00 Page no. 12 Question: A0643. Rev. O Points:

1.00 OUESTION:

Which one of the belov reasons is the most probable cause of the present trend in Dryvell temperature?

A.

No NCC Pumps are running.

B.

No Instrument Air is available in the Dryvell.

C.

A steam leak exists in the Dryvell.

D.

No NCC flov is available in the Dryvell.

ANSVERt D.

9

ANSVER KEY NRC ANNUAL REQUAL EXAM Part A Exam, Scenario 06 OT-3070-000-00 Page no. 13 Question: A0642 Rev. O Points:

1.00 QUESTION:

Vhich one of the following would result to Bus EH-13, if a loss of incoming power f rom transf ormer LH-1-A vere to occur?

A.

Bus EH-13 vould automatically re-energize from the Alternate Preferred Source.

B.

Bus EH-13 vould automatically re-energize from the Div. 3 Diesel Generator.

C.

Bus EH-13 vould de-energize, requiring operator action to re-energize the bus from either source.

D.

Bus EH-13 vould remain energized from the Normal Preferred Source since this is automatically back-fed from Unit 2.

ANSVER:

B.

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- TEST'ID NUMBER 90-oo't Control # 9020015 PERRY TRAINING SECTION WRITTEN EXAMINATION COVER SHEET 2

c COURSE TITLE NRC Requalification Exam (R0 - Part B)

NAME SSN DATE GRADED BY GRADE j

RESULTS REVIEWED DATE TEST TAKING IS AN INDIVIOUAL EFFORT:

Any test mj ndu is a violation of TNG-1007, Implementatic Tr g

Cheating on an exam by giving eceivin p is grounds for termination of sp1 nt in certain cases, may be subject to al p cution under federal statutes, m

'Y

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TOYAL POINTS 20.00 TIME ALLOTTED 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POINTS REQUIRE 0 N/A TIME USED N/A PREPARED Niles H. Johnson Af7 DATE Msi 9, 1990 REVIEWED Michael 1,. Veslev OATE'

/

6 NRC A PROVED I/

DATE 1

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ANSVER KEY NRC ANNUAL REGUAL EXAM PART B - RO EXAM OT-3070-000-00 Page no. 1 Question: B0216, Rev. O Time 5 minutes Points:

1.00 QUESTION:

Vhich of the folloving statements is correct?

All control pover fuses must be removed anytime a 480V breaker is a.

racked out of its cubicle.

b.

After clearing red tags, fuse continuity shall be checked with the fuses installed.

The operation of any component protected by a white tag shall require c.

prior approval of the Supervising Operator and the person-in-charge of the tag-out, d.

A component with a red tag and a vhite tag shall only be operated by the person-in-charge or a tag-out rider.

ANSVER:

i b.

l l

i 1

ANSWER KEY NRC ANNUAL REQUAL EXAM PART B - RO EXAM OT-3070-000-00 Page no. 2 Question: B0005, Rev. 1 Time:

4 minutes Points:

1.00 QUESTION:

Which of the following statements is currect with.regards to shift staffing requirements?

a.

The licensed operator at the controls may take temperature readings on the Division 1 Leak Detection panel (H13-P632) in response to a RCIC ISOL TIMER RUNNING ST TNL TEMP HI annunciator.

b.

The licensed operator at the controls may shif t the Of f-Gas System f rom the AUTO mode to the TREAT Mode during a plan,t startup per 101-1.

c.

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

d.

The licensed operator at the controls may hang a red tag on the AEGTS Exhaust Fan A control svitch on P800 during normal plant operations.

I

- - - - .e************************************************

ANSVER:

c.

i 1

ANSWF.R KEY FRC ANNUAL REQUAL EXAM PART B - R0 EXAM 07-3070-000-00 Page no. 3

}

Question:

B0197, Rev. O Times 2 minutes Points:

1.00 OUESTION:

The plant is operating at rated conditions when APRM "C" fails upscale and initiates a half-scram.

All other APRM channels are operable. A PPO reports that RPS "B" MG Set is noisier than usual and is very hot to the touch.

Considering these set of conditions, neither of which have yet been acted upon by the operator, the FIRST action the operator should perform ist (Choose one of the following.)

a.

Scram the Reactor and enter ORI-C71.

b.

Transfer RPS Bus B to Alternate power.

c.

Bypass the failed APRM channel and reset the scram.

d.

Trip the RPS 'B' MG Set.

ANSVER:

[

C.

3 1

ANSVER KEY NRC ANNUAL RE0 VAL EXAM PART B - RO EXAM 0T-3070-000-00 Page no. 4 Question: B0219. Rev. O Time:

4 minutes Points:

1.00 QUESTION:

Vith the Suppression Pool Makeup System aligned for normal operations, select the condition (s) belov vhich vould NOT result in an automatic initiation of the SPMU System.

Reactor level of 110.5" and high Dryvell pressure of 1.68 psig a.

and Suppression Pool Level of 16'-4".

b.

Reactor level of 125" and suppression Pool level of 16'-4".

SPMU dump test svitches in the TEST position and both manual c.

initiation pushbuttons depressed.

d.

!!!gh Dryvell pressure of 1.68 psig and SPMU timers timed out.

.*****************************v******************************************

ANSVER:

b.

l l

f

ANSVER C Y NRC ANNUAL REQUAL EXAM PART B - RO EXAM OT-3070-000-00 Page no. 5 Coestion: B0198, Rev. O Times 3 minutes Points:

1.00 QUESTION:

A containmen* threatening event has occ' erred requiring the initiation of containment sprays. When is it permissible to secure containment sprays?

(Choose one of the following.)

j a.

Vhen containment pressure esn be maintained below the pressure suppression pressure.

b.

Vhen containment pressure drops belov 1.5 psig but before it drops to O psig.

c.

Vhen the reactor has been depressurized to less than 200 psig.

d.

When the reactor has been cooled dovn to < 200' P.

t ANSVER:

b.

ANSVER KEY NRC ANNUAL REQUAL EXAM PART B - RO EXAM OT-3070-000-00 Page no. 6 Ouestion:

B0209, Rev. O Time 4 minutes Points:

1.00 QUESTION:

Vith the unit operating at power, a reactor scram occurs due to a Feed Pump Trip. The operators enter PEI-B13 because of the low reactor vater level. The operator at the controls reports five control rods are stuck at position 48, and all other rods are full in.

Vhich of the following conditions vill permit the operators to commence a reactor cooldown?

a.

The SRO determines an emergency no longer exists and exits the PEI's.

b.

All control rods all" fully inserted to position 00 or 02, c.

The Reactor Engineer reports the reactor vill st.sy shutdown until reactor coolant temperature reaches 300' F.

d.

The operators determine boren injection is not required.

ANSVER:

b.

l

ANSVER KEY NRC ANNUAL REQUAL EXAH PART B - R0 EXAH OT-3070-000-00 Page no. 7 Question:

B0196, Rev. 1 Time:

5 minutes Points:

1.00 OUESTION:

Required tracking of LCO's can be done by entry in the Unit Log instead of a LCO tracking sheets a.

At any time.

b.

For SVI's only.

c.

For potential LCO's only, d.

At no time.

- - - - v.**************************************************

ANSVER:

a.

i r

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ANSVER KEY NRC ANNUAL REQUAL EXAM PART B - R0 EXAM OT-3070-000-00 Page no. 8 Ouestion:

B0242, Rev. O Time:

8 minutes Points:

1.00 QUESTION:

Consider the following Post-LOCA, Reactor, Containment, and Dryvell parameters:

Reactor Level 10 inches Dryvell Pressure 2.0 psig Containment Pressure 2.0 prig Dryvell H, Concentration 5%

Containment H Concentration 5%

ContainmentT$mperature 160' P.

Dryvell Temperature 212' F.

Based only on the above parameters, determine which one of the following hydrogen control measures should be currently employed:

a)

H, Recombiners C6ntainment Venting Containment Spray Purge Backup H2 b) Combustible Gas Mixing Compressors H, Igniters C5ntainment Spray Backup H Purge 2

c) H Recombiners 2

Combustible Gas Mixing Compressors Containment Spray H Igniters 2

d)

H, Recombiners C5ntainment Venting Backup H Purge 2

H Igniters 2

ANSVER:

c.

i ANSVER KEY NRC ANNUAL REQUAL EXAH PART B - R0 EXAM OT-3070-000-00 Page no. 9 Ouestion:

B0220, Rev. O Time:

4 minutes Points:

1.00 QUESTION:

The Control Room operator raised the voltage regulator setting to increase reactive load to 500 MVARS on the Main Generator. Generator hydrogen pressure is 60 psig. Vhat is the maximum Megavatt output alloved for this condition?

Choose the most correct answer a.

1000 MVe b.

1040 MVe c.

1200 MVe d.

1225 MVe ANSVER:

d.

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ANSVER KEY NRC ANNUAL REQUAL EXAM PART B - RO EXAH OT-3070-000-00 4

Page no. 10 Question:

B0210, Rev. O Tine:

8 minutes Points:

1.00 QUESTION:

Vhich of the following conditions vould NOT allov'an OPERATIONAL CONDITION MODE CHANGE from Condition 4 to Condition 7.

One inoperable control rod due to a position indication failure.

a.

b.

One inoperable control rod that is immovable because of excessive friction.

One inoperable control rod that has an accumulator that cannot be c.

charged.

d.

One control rod is determined inoperable during scram time testing.

ANSVER:

b.

l.

ANSVER KEY NRC ANNUAL REQUAL EXAM PART B - RO EXAM OT-3070-000-00 Page no. 11 Question:

B0227, Rev. O Time:

4 minutes Points:

1.00 QUESTION:

Vhich of the following evolutions require Independent Verification?

(More than one may be correct.)

a.

Installing a blank flange in an HPCS Diesel Generator fuel oil line during a Div. III outage.

b.

Placing Suppression Pool Cleanup (SPCU) in service via the SPCU Demineralizer.

c.

Shifting til and L12 to the Auxiliary Transformer during a plant startup.

d.

Shifting Feedvater Flov control from the STARTUP Level Controller to the MASTER Level Controller.

- - - - =***********************************************

ANSVER:

b.

l i

L l

ANSVER KEY NRC ANNUAL. REQUAL EXAM PART D - R0 EXAM OT-3070-000-00 Page no. 12 Question: B0226 Rev. O Time:

5 minutes Points:

1.00 QUESTION:

Vhich of the following has the greatest protectio.n factor against ambient airborne radionuclido concentratfens?

a.

Air Purifying Respirators with a full faceplate.

b.

Self-contained Breathing Apparatus.

c.

Air Line Respirators.

d.

Combination Air Line-Air Purifying Respirators.

ANSVER:

b.

ANSVER KEY NRC ANNUAL REQUAL EXAM PART B - RO EXAH 07-3070-000-00 Page no. 13 Question:

B0225, Rev. O p

Time:

5 minutes Points:

1.00 OUESTION:

You are operating en the 97% rod line at 70% pover. When geactor Recirc A Flov Control Valve malfunctions and runs flov to 45 X 10 mlb/hr.

Based on these plant conditions, your response should bei A.

Insert a manual reactor scram.

B.

Insert cram rods.

c.

Insert centrol rods in the prescribed sequence.

d.

Insert cram rods, then increase recire flov to exit shaded area.

ANSVER:

b.

1 b

tem. m

t ANSVER KET NRC ANNUAL REQUAL EXAM t

PART B - R0 EXAM OT-3070-000-00 I

Page no. 14 Question:

B0224, Rev.'O Timet 6 minutes Points:

1.00 QUESTION:

Which of the following vill NOT produce a control. rod withdraval block with the Reactor Mode Svitch in STARTUP?

A.

An IRM detector not fully inserted.

b.

An APRM INOP.

c.

Refuel Bridge over the core.

d.

A SRH detector not full in and all SRM's reading > 100 eps.

AHSVER:

i d.

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I l

l l

1

ANSVER KEY NRC ANNUAL REQUAL EXAH PART B - R0 EXAH OT-3070-000-00 Page no. 15 Question:

B0223, Rev. O Time

- 5 minutes Points:

1.00 QUESTION:

During a plant cooldovn from 1% power at normal operating pressure to 120' F. and 0 psig, the Narrow Range Level instrument is selected from display on P680.

Assuming that actual water level remains at 200" for the entire time, what vill the indicated level be when the final plant conditions are reached?

i a.

190" b.

195" c.

200" d.

212" ANSVER:

c d.

3

y J

ANSVER KET NRC ANNUAL REQUAL EXAM

-l PART B - RO EXAM OT-3070-000-00 Page no. 16 Question:

B0222, Rev. 0 Times 3 minutes Points:

1.00 QUESTION:

Assume the Main Generator is loaded to 313 KVe.

C. hoose the minimum time permissible for a step change in load to 1190 MVe.

(Assume exhaust hood temperature is less than 125' F.)

a.

30 minutes i

b.

20 minutes c.

10 minutes i

d.

5 rd ov;,,a i

- - - - w**********************n******************************

ANSVER:

b.

ANSVER KEY NRC ANNUAL REQUAL EXAH PART B - R0 EXAH OT-3070-000-00 Page no. 17 Ouestions-B0086, Rev. 1 Times.

3 minutes-Points:

1.00 QUESTION:

During a plant shutdovn and cooldown, at 540 psig, you receive a "HPCS OUT OT SERVICE" alarm. The amber 00S target matrix HPCS LEAK DETECTED is illumina ted.

Investigation reveals the HPCS line break instrument, 1E31-N681, on H13-P625 (HPCS back panel) reads -3.2 psid. Which of the following statements best describes your required action (only one correct ansver):

a.

Place the HPCS System in Secured Status, b.

Declare the HPCS System inoperable and take the required Action.

c.

Declare the line break instrument inoperable and take the required Actions.

d.

No action is required.

i ANSVER:

d.

9

\\

'I ANSVER KEY NRC ANNUAL REQUAL EXAH PART B - R0 EXAH 0T-3070-000-00 Page no. 18 Question:

B0208, Rev. O Time 5 minutes Points:

1.00 QUESTION:

A plant startup is in progress vith two Circulating Vater Pumps operating.

The Hot Vater Inlet Valves 1N71-F345 and 1N71-F634 are open with three condenser trains operating due to existing condition. The two running pumps have a discharge pressure of 38 psig.

Based on the above conditions, the Control Room operator should:

Throttle the running Cire Vater Pump Discharge Valves in the close a.

direction, b.

Throttle the running Cire Vater Pump Discharge Valves in the open direction.

c.

Start the third Cire Vater Pump.

d.

Start the third Cire Water Pump and place the fourth ' condenser train in service.

ANSVER:

a.

t I

ANSVER KEY NRC ANNUAL REQUAL EXAH PART B - RO EXAH OT-3070-000-00 Page no. 19 Question: B0228, Rev. O Time 4 minutes j

Points:

1.00 QUESTION:

The Reactor is in Condition 4 with one loop of RHR in Shutdovn Cooling.

Both Recire pumps are OFF. Reactor level should be mair.tained using the A.

Narrov Range Indication.

B.

Shutdovn Range Indication.

C.

Upset Range Indication.

D.

Vide Range Indication.

ANSER:

B.

ANSVER KEY NRC ANNUAL REQUAL EXAM PART B - RO EXAM 0T-3070-000-00 Page no. 20 Question:

B0004, Rev. 1 Times 3 minutes Points:

1.00

[

QUESTION:

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

An unlicensed System Engineer to check valve response, providing the consent a.

of the licensed operator at the controls and the Unit. Supervisor is obtained.

Eb.

An unlicensed individual in the SRO Training Program providing the consent l

of the licensed operator at the controls and the Unit Supervisor is obtained.

The on-coming Unit Supervisor,.providing the knowledge and consent of the c.

licensed operator at the controls is obtained, d.

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

ANSVER:

d.

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g-fNF9 NO. 090 '. Rev. 8149 IMA-4113 T.,

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' COURSE' NUMBER OT-3070-000-00

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,i TEST 10.N. UMBER 90'004 i

control #9020015

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PERRY TRAINING SECTION J

q WRITTEN EXAMINATION COVER SHEET i

g.

a COURSE TITLE NRC Requalification Exam (Part B - SRO Exam)

NAME SSN DATE GRADED BY GRADE RESULTS REVIEWED-DATE TEST.TAKING IS AN INDIVIOUAL EFFORT:

Any test m ndu j

is a violation of TMG-1007, Implementatic Tr i

g.

Cheating on an exF hy giving or receivin p is grounds for termination of empi nt in certain cases, c:ay be subject to g al p -

cution under federal statutes.

3D

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TOTAL POINTS 23.00 TIME ALLOTTED 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

' POINTS REQUIRED N/A TIME USED N/A PREPARED Niles H. Johnson AC[

DATE May 9, 1990 f4/

/W O

REVIEWED Michael L. Wesley DATE i

/4 Md NRC' APPROVED' AE +

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ANSVER KEY NRC ANNUAL REQUAL EXAM-PART B - SRO EXAM OT-3070-000-00 Page no. 1 Question: B0211, Rev. O Time 5 minutes Points:

1.00 QUESTION:

A GENERAL EMEGENCY has been declared and Containment failure is likely.

Containment High Range Recorders D19R100 and D19R200 both read 15,000 R/hr.. The reactor has been shutdown for twenty (20) hours. The appropriate Protective Action Recommendations, based on the above information, vould bet (choose one) 360 degree shelter to 2 miles, precautionary shelter in at-least three a.

downvind sectors to 5 miles.

b.

360 degree evacuation to 2 miles, 360 degree shelter between 2 and 3 miles, and shelter in at least 3 dovnvind sectors betveen 3 and 5 miles.

360 degree evacuation to 2 miles,' evacuation in at least three c.

downvind sectors between 2 and 5 miles, shelter between 2 and 3 miles in unaffected areas.

d.

360 degree evacuation to 3 miles,-evacuation in at least three dovnvind sectors between 3 and 5 miles, shelter between 3 and 4-miles in unaffected areas.

ANSVER:

b.-

.=

ANSVER KET NRC-ANNUAL REQUAL EXAH PART B - SRO EXAH l

OT-3070-000-00 Page no. 2 Question:

B0212, Rev. O Timet 7 minutes Points:

1.00 OUESTION -

Due to a loss of NCCV, the plant is in Hot Shutdown with the following current conditions:

-Reactor pressure 350 psig

-Containment temperature 155 F.

-Dryvell temperature-300 F.

-Narrov Range Vater level 180"

-Vide Range Water level 191"

-Fuel Zone VATER level.

+50"

-Upset Range Vater level 180"

-Shutdovn Range Vater Level 185" Vhich' of the belov listed vater level instruments (s) is/are NOT allowed to be used?

a. Narrow Range

b. Vide Range-

c. Shutdown Range

d. Fuel Zone Range

'************************************************************************.6,*****

ANSVER:

4 1

C.

l l

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L

ANSVER KEY NRC ANNUAL REQUAL EXAM PART B - SRO EXAM OT-3070-000-00 Page no. 3 Question: B0213, Rev. O Time:

8 minutes Points:

1.00 QUESTION:

Unit 1 is operating at 80% power. Control Rod 30-19 is inoperable due to.a leaking scram accumulator. The rod is disarmed hydraulically and fully incerted. During a surveillance, Rod 30-23 is declared inoperable because of r

excessive scram insertion times.

If both rods remain 11 operable, when must the=

i plant be in HOT SHUTDOVN'?

a.

Vithin the next 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s-b.

Vithin the next 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months c.

Vithin the next 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s-d.

There is no requirement to be in HOT SHUTDOVN ANSVER:

r a.

1 s

L c

1'

t ANSVER KEY NRC ANNUAL REQUAL EXAH PART B - SRO EXAH OT-3070-000-00 Page no. 4 Question: B0214, Rev.-0 Time:

4 minutes Points:

1.00 QUESTION:

You are the Supervising Operator at the controls,'vith the Reactor operating at approximately 70% of Rated Thermal Power.

Both Recirculation Pumps trip due to an operator error. Which of_the belov listed responses best describe the actions you should take?

a.

Commence to reduce thermal power to less than or below the limit specified in the ONI-by inserting cram rods, b.

Commence a plant shutdown per 10I-4.

c.

Arm and depress the RPS manual scram pushbuttoms, d.

Monitor and control Reactor vater level within the normal operating range, and make preparations to attempt to restart at least one of the pumps.

ANSVER:

-c.

r

ANSVER KEY NRC ANNUAL REQUAL EXAM PART B - SRO EXAM OT-3070-000-00 Page no. 5 Question:

B0215, Rev. O Times 3 minutes

-Points:

1.00 i

QUESTION:

For which of the belov listed conditions of reactor power voul6 a notification to the NRC NOT have to be made i

a.

Average thermal power (30 min.) - 3618 MVT b.

Average thermal power (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) - 3593 MVT c.

Average thermal power (8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shif t) - 3581 MVT d.

Average thermal pover.(1 min. peak) -3656 MVT

'**********************w*****************************w***************************>

ANSVER:

s b.

7 L

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a ANSWER KEY NRC ANNUAL REQUAL EXAH PART B - SRO EXAH OT-3070-000-00 Page no. 6 Ouestion: B0217, Rev. 0

.imes 3 minutes Points:

1.00 QUESTION:

i Which of the following requires a Radiation Vork Permit?

A person is to enter an area vith' an Airborne activity of.17 mpc.

a.

b.

Performing a visual inspection of the scram discharge valve for Control Rod 30-15.

c.

Fire vatch for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months in an area vith a dose rate of 15 mrem /hr.

r I

d.

Entering an area where the dose rate may exceed 50 mrem /hr.

- - - - w*********************************

ANSVER:

i b.

t i

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ANSVER KEY NRC ANNUAL REQUAL EXAM PART B - ?.P0 EXAM OT-3070-030-v'O Page no. 7 Ouestion:

B0218, Rev. O Times 3 minutes Points:

1.00 QUESTION:

Vhich of tho following water hammer events must b.e reported to the l

Operations Manager?

a.

Vater hammer in the Condensate piping due to starting a llotvell pump.

b.

Vater hammer in the Feedvater piping due to starting an additional Reactor Feed Booster pump.

c.

Vater hammer due to placing the RHR System, Loop A, in Suppression Pool Cooling.

+

l d.

Vater hammer due to lining up second stage extraction steam to the Moisture Separator Reheaters.

)

ANSVER:

c.

I

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l 1

ANSVER KEY NRC ANNUAL REQUAL EMM PART B - SRO EXAM-OT-3070-000-00 Page no. 8 Question:

B0011, Rev. 1 Times 2 minutes 1

Points:

1.00 OUESTION:

During Power Operations on May 18 the secondary vindings on transformer LH-2A

[

fails, and the transformer is declared Inoperable at 0800 that day.

The

~

following is a record of the surveillances completed due to this event'during the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; SVI-R43-T1317 Start 1000 5/18, complete 1300 5/18-SVI-R43-T1318 Start 0300 5/19, complete 0750 5/19 SVI-R10-T5217 Start 0805 5/18, complete 0822 5/18 Start 1545 5/18, complete 1600 5/18 i

Start 2340 5/18, complete 2345 5/18 i

Start 0720 5/19, complete 0740 5/19 Vhat is the LATEST that you can satisfactorily complete the next required SVI-R10-T5217 and NOT violate Tech Specs.

a.

1520, May 19 b

-1540, May 19 c.

1740, May-19 d..

1800, May 19

- e. ~2200, May 19

- - - - w**********************************A*******************

ANSVER:

b.

ll t

i

7 ANSVER KEY NRC ANNUAL REQUAL EXAM

.PART B - SRO EXAM OT-3070-000-00 I

Page no. 9 Question: B0203, Rev. 0 l

Time 8 minutes i

Points:

3.00 QUESTION:

i Hatch the conditions in Column A vith the vent rad monitor in Column B vhich vould provide the operator with the first indicat' ion of a potential radiological-problem.

(NOTE:

each rad monitor in column B may be used more than once.)

Column A Column B a.

Movement of the steam dryer 1.

Unit 1 Plant Vent Rad Monitor during refueling operations.

b.

Fuel clad rupture during power 2.

Unit 2 Plant Vent Rad Monitor.

operations.

I 3.

TB/HB Plant Vent Rad Monitor, c.

Overheating of the AEGTS

'B' charcoal beds.

4.

Of f-Gas Vent Rad Monitor.

ANSVER:

a.

1 b.

4-c.

2 9

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ANSVER KEY NRC ANNUAL RE0 VAL EXAH PART B - SRO EXAM OT-3070-000-00 Page no. 10 Question: B0201, Rev. O Times 2 minutes Points:

1.00 QUESTION:

The plant is operating at 100% pover.

For which of the belov cases is Primary Containment Integrity NOT being maintained? (SELECT ONE) a.

Suppression Pool temperature is 101' F. during a RCIC full flov test CST to CST.

b.

Suppression Pool level is 18'-8".

A PPO reports that the Dryvell outer airlock door is found open and c.

cannot be closed.

d.

The annulus door to the Auxiliary Building is found propped open.

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ANSVER:

-b.

nt' 9

ANSVER KEY NRC ANNUAL REQUAL EXAM PART B - SRO EXAM OT-3070-000-00 Page no, 11 Question:

B0200, Rev. 0 Times 3 minutes Points:

1.00 l

QUESTION:

An alert has been declared and all required facilities have been activated.

The 1

Emergency Coordinator'vould be found in thes a.

Emergency Operations Facility b.

Technical Support Center c.

Operations Support Center-d.

Control Room i

ANSVER.

b.

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1 ANSVER KET i

NRC ANNUAL REQUAL EXAM l

PART B - SRO EXAM l

OT-3070-000-00 l

Page no. 12 l

Question: B0024, Rev. 1 i

Time:

6 minutes Points:

1.00 QUESTION i

The plant is operating at 100% power when your RO, reports that Reactor Narrow i

Range Vater Level indicator C (transmitter number IC34N0040) is pegged lov vhile N004A and B agree and indicate properly.

Choose the correct action to take from the list below.

j Place the inop channel and/or trip system in the tripped condition within a.

one (1) hour.

b.

Restore the inoperable channel to OPERABLE vithin 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 , c.

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 SHUTDOVN vithin the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d.

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

j j

i ANSVER' 4

b.

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ANSVER KEY'

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NRC ANNUAL REQUAL EXAM PART B - SRO EXAM OT-3070-000-00 Page no. 13 Question: B0028, Rev. 1 Time:

6 minutes o

L Points:

1.00 OUESTION

-Choose the statement.which is(are)-correct regarding refueling operations.

a.

At least 23 feet of water shall be maintained over the top of the Reactor l

Pressure Vessel Flange, j

'b.

The Containment Building overhead ~ crane may be used to handle control rods in the RPV.

c.

All CORE ALTERNATIONS vill be observed and directly supervised by an SR0 licensed individual who has no other concurrent responsibilities during this, operation, d.

During fuel loading into the RPV, only SRM's A and C need to be OPERABLE.

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ANSVER c.

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it ANSVER KEY NRC ANNUAL REQUAL EXAM PART B - SR0 EXAH 1,

OT-3070-000-00 Page no. 14 Question:

B0196, Rev. 1 Time 3 minutes i

Points:

1.00 QUESTION:

i 11 Required tracking of LCO's can be done by entry in the Unit Log instead of a LCO tracking sheets a.' At any' time.

.I b.

For SVI's only.

c.

For potential LCO's only.

d.

For active LCO's only.

S.

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i ANSVER:

a.

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ANSVER KEY NRC ANNUAL REQUAL EXAM PART B - SRO EXAM OT-3070-000-00 Page no. 15 Question: B0205, Rev. O Time 4 minutes Points:

1.00 I

OUESTION:

The plant is operating at 100% power with only the following outstanding LCO:

Liv. II D/G is INOP

?

The diesel was declared INOP on the previous shift and all initial action requirements of TS 3.8.1.1.a have been taken.

Shortly after turnover, a condition report is received that requires the Division 1 Suppression Pool Makeup Line to be declared INOP.

Vhich.of the following actions correctly details the allowances and/or limitations imposed by Tech Specs.

a.

Restore the INOP SPMU Line to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be.in at least Hot Shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Cold Shutdown in the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i b.

Be in at least STARTUP in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , HOT SHUTDOVN in' the following 6-hours COLD SHUTDOVN in the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.. Be in at least HOT SHUTDOVN vithin the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and COLD SHUTDOVN in.

the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .-

d.

Restot e Division 2 D/G to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the initial

=!

failure or be in at least HOT SHUTD0VN in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and COLD SHUTDOVN in the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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ANSVER:

3 C.

I

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ANSVER IEY NRC ANNUAL REQUAL EXAH g

PART B - SRO EXAM OT-3070-000-00 Page no. 16 Question: B0209, Rev. O Time 4 minutes Points:

.l.00 i

OUESTION:

Vith the unit operating at power, a reactor scram. occurs due to a Feed Pump Trip. The operators enter PEI-B13 because of the low reactor water level. The operator at the controls reports five control rods are stuck at position 48, and all other rods are full in.

..i Vhich of the'following conditions vill permit-the operators to commence a

. reactor cooldovn?

a.

The SRO determines an emergency no longer exists and exits -the PEI's.

b.

All control rods all fully inserted to position 00 or 02.

c.

The Reactor Engineer reports the reactor vill stay shutdovn until reactor coolant temperature reaches 300' F.

d.

The operators determine boron injection is not required.

ANSVER:

.q b.

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ANSVER KEY NRC ANNUAL REQUAL EXAM PART B--

SRO EXAM OT-3070-000-00 Page no. 17 Question: B0206, Rev. O Time 4 minutes Points:

1.00 QUESTION:

f Unit 1, operating at 98% power, is beginning the. third day of a 14 day LCO due-to an INOP HPCS system. Repair estimates indicate HPCS could could be returned to service in as fev as 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ..Four hours into the shift during the performance of a full flov functional test, RCIC is capable of developing a maximum pump flov of only-650 gpm at rated pressure.

~!

conditions.. Upon declaring RCIC INOP, which of the following actions most

[

correctly details the allovances and/or limitations imposed by Tech Spec?

a.

Rostore either HPCS or RCIC to OPERABLE status within-14' days.

b.

Be in at least HOT SHUTDOVN vithin the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOVN vithin the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

Be in at least HOT SHUTDOVN vithin the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 'and reduce steam dome pressure to less than or equal to 150 psig.

d.

Vithin one hour, initiate actions to be in at least STARTUP vithin the next six hours, at.least HOT SHUTDOVN vithin the following six hours i

-and at'least COLD SHUTDOVN vithin tht subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ANSVER

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t ANSVER KEY NRC ANNUAL REQUAL EXAH PART B - SRO EXAH OT-3070-000-00 Page no. 18 Question: B0210, Rev. 0 Time 4 minutes Points:

1.00 QUESTION:

Which of the following conditions vould NOT allov,an OPERATIONAL CONDITION H0DE CHANGE from Condition 4 to Condition 2.

Ono inoperable control rod due to a position indication failure.

a.

b.

One inoperable control rod that is immovable because of excessive friction.

One inoperable control rod that has an accumulator that cannot be c.

charged.

i

d.. One control rod is determined inoperable during scram time testing.

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ANSVER:

b.

1 4

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ANSVER KEY t

NRC ANNUAL REQUAL EXAH PART B - SRO EXAM OT-3070-000-00 Page no. 19 Question:

B0194, Rev. 2 Times 1 minute

{

Points:-

1.00-i i

QUESTION:

I If attaching a yellow tag to a device you must also:

I a.

Attach-a white tag.

j b.

Attach a Lift Lead and Jumper Tag.

Attach an information tag (explaining reason for yellow tag).

c.

d.

Attach a red tag, f

D i

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ANSVER KEY NRC ANNUAL REQUAL EXAH PART B - SRO EKAM OT-3070-000-00 Page no. 20 Ouestion: B0094 Rev. 1 Time:

5 minutes Points:

1.00 QUESTION:

The Reactor is operating at 95% pover. Recorder IC51-R603C (IRM C/APRM C/IRH G/APRH G) has failed and has been removed to be repaired. No spare is available to replace it.

Which of the following actiono is required by Technical Specifications for this condition?

l A.

Restore the recorder within 7 days or be in Hot Shutdovn in the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Cold Shutdovn vithin the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B.

Restore the recorder vithin one (1) hour or place a scram signal in the RPS A logic.

C.

Restore the recorder within one hour or be in startup in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Hot Shutdovn within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and cold shutdovn within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

D.

No actions are required by Technical Specifications.

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d 6 $ $ $ $ $

ANSVER:

D.

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6 ANSVER KEY NRC ANNUAL REQUAL EXAH PART B - SRO EKAM 0T-3070-000-00 Page no. 21 Question: B0030, Rev. 1 Time:

5 minutes Points:

1.00 QUESTION During a plant startup, the Reactor Mode Svitch is.placed in RUN just prior to observing that Containment vacuum breaker M17-F010 is open due to M14 System operatiot.. Choose an action from the list belov vhich vill meet the Technical Specification requirements for this condition.

a.

Operation may continue, the provisions of Specification 3.0.4 do not apply.

b.

Vithin four (4) hours, close the associated MOV.

c.

Vithin one (1) hour, restore M17-F010 to closed or be in at lea 9t HOT SHUTDOVN vithin the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d.

Vithin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , restore M17-F010 to OPERABLE or be in at least HOT SHUTDOVN vithin the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

t ANSVER b.

-

ML20043H732

Text

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