IR 05000289/1993020

Exam Rept 50-289/93-20OL on 930830-0902.Exam Results:Written & Operating Exams Administered to Two SRO-upgrade Candidates & Both Passed Exam & Were Issued Licenses

ML20057F720
Person / Time
Site:	Crane
Issue date:	10/07/1993
From:	Meyer G, Prell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20057F716	List: IR 05000289/1993020 ML20057F715
References
50-289-93-20OL, NUDOCS 9310190022
Download: ML20057F720 (102)

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I U.S. NUCLEAR REGULATORY COMMISSION REGION 1 OPERATOR LICENSING EXAMINATION REPORT i

EXAMINATION REPORT NO.

50-289/93-20 (OL)

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i FACILITY DOCKET NO.

50-289 FACILITY LICENSE NO.

DPR-50 LICENSEE:

GPU Nuclear Corporation

P.O. Box 480 Middletown, Pennsylvania 17057 FACILITY:

TMI-l EXAMINATION DATES:

August 30 - September 2,1993 NRC EXAMINERS:

J. Prell, Chief Examiner R. Cain, EG&G CHIEF EXAMINER:

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// [

A6/'7 f3

[ftJamesfEell, Sr. Opetiti6ns Engr.

Date Operations Branch, DRS i

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/6 '7 98 APPROVED BY:

[ftdlenq/ feyer, SectisFChief Date PWR Section, Operations Branch, DRS SUMMARY: Written and operating examinations were administered to two Senior Reactor Operator - Upgrade candidates. Both candidates passed their examination and were issued licenses. There were no generic findings regarding strengths and weaknesses. Minor problems were noted regarding the documentation of tagging closeouts on the tag out sheet and the ability of the simulator to model one instance of low pressure injection flow.

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9310190022 931007 PDR ADOCK 05000289 V

PDR

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DETAILS TYPE OF EXAMINATION: SRO-Upgrade Initial Examination

1.0 EXAMINATION RESULTS INITIAL EXAM SRO TOTAL PASS / FAIL PASS / FAIL t

WRITTEN 2/0 2/0 SIMULATOR 2/0 2/0 WALK-THROUGH 2/0 2/0 OVERALL 2/0 2/0 t

2.0 OBSERVATIONS

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P As only two candidates were examined there was no basis for determination of generic strengths and weaknesses. The examiners had the following observations.

Inconsistent communication, command and control skills between the two candidates was noted. One candidate did not maintain good overall command of what was occurring in the i

control room because he tended to crowd the control panels, failed to keep the crew fully informed of where he was heading in his mitigation strategy, and performed many of the initial panel readings himself. The second candidate stood further back from the panels and thus maintained a better overall awareness of plant status and kept the crew better informed on where they were in the procedures and the proposed mitigation strategy. This allowed the crew members to anticipate and prepare for potential problems.

During the administration of the plant walkthrough examination, a minor documentation

problem was noted with the computerized tagging program. Multiple examples were found were the person responsible for verifying the closecut of the tags failed to initial the tag out sheet.

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A simulator fidelity problem was discovered during a Job Performance Measure which required both candidates to place the safety injection system into the " piggy back" mode of j

operation. -When the system was realigned in the piggy back mode however, the simulator i

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did not indicate low pressure injection flow in the B loop.

3.0 EXIT INTERVIEW

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A summary of the week's activities was presented and discussed, including the items presented above. The facility commented that the simulator fidelity problem was due to a recent design change which cut off flow indications to the low pressure injection flow meter when flows were less than 600 gallons per minute. Facility management said they will

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reconsider lowering the cutoff to a value less than what is expected during piggy back operations. Facility management did not identify any problems with the written or operating

examinations.

The following people were contacted:

i GPU Nuclear Corr > oration D. Boltz Manager, Simulator Management (2)

T. Broughton Director, TMI-1 (2)

R. Hess Lead Instructor, Operator Training (1,2)

A. Miller Licensing Engineer (2)

M. Ross Director, Operations & Maintenance (2)

O. Shalikashvili Manager, Plant Training (2)

j H. Shipman Director, Plant Operations (1,2)

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M. Trump Manager, Operator Training (1,2)

LEGEND:

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(1) Participated in the examination development (2) Attended the exit meeting on September 2,1993

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Attachment 1:

Written Examination and Answer Key Attachment 2:

Simulation Facility Report

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ATTACIIMENT 1

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WRITTEN EXAMINATION AND ANSWER KEY t

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-. 5 NRC Official Use Only i

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i Nuclear Regulatory Commission Operator Licensing Examination

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This document is removed from Official Use Only category on

date of examination.

NRC Official Use Only

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j U. S. NUCLEAR REGULATORY COMMISSION SITE-SPECIFIC WRITTEN EXAMINATION A'PPLICANT INFORMATION Name:

Region:

I Date: August 31, 1993 Facility / Unit: TMI-l License Level:

SRO Reactor Type:

BW INSTRUCTIONS Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets.

Points for each question are indicated in parentheses after the question. The passing grade requires a final grade of at least 80 percent.

Examination papers will be picked up 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the examination starts.

All work done on this examination is my own.

I have neither given nor received aid.

Applicant's Signature RESULTS Examination Value 100.00 Points Applicant's Score Points Applicant's Grade Percent

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.t ANSWER S H E E T-l

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Multiple Choice (Circle or X your choice)

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If you change your answer, write your selection in the blank.

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MULTIPLE CHOICE 023 a

b c

d

001 a

b c

d 024 a

b c

d

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b c

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d l

f 004 a

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d f

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d 028 a

b-c d-006 a

b c

d 029 a

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d l

007 a

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d 030 a

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d i

008'

a b

c d

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d 034 a

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d 013 a

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d 036 a

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d l

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d 037 a

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d

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ANSWER SHEET I

i Multiple choice (Circle or X your choice)

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If you change your answer, write your selection in the blank.

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b c

d 068 a

b c

d MULTIPLE CHOICE 069 a

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i 047 a

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d 060 a

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d 062 a

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d 085 a

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l ANSWER SHEET j

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Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

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091 a

b c

d

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MULTIPLE CHOICE j

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d j

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i (********** END OF EXAMINATION **********)

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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS

'l During the administration of this examination, the following rules apply:

1.

Cheating on the examination will result in a denial of your application l

and could result in more severe penalties.

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2.

After you complete the examination, sign the statement on the cover-l sheet indicating that the work is your own and you have not received or

given assistance in completing the examination.

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3.

To pass the examination, you must achieve a grade of 80 percent or I

greater.

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4.

The point value for each question is indicated in parentheses after the question number, j

5.

There is a time limit of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for completing the examination.

i 6.

Use only black ink or dark pencil to ensure legible copies.

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Print your name in the blank provided on the examination cover sheet and the answer sheet.

I 8.

Mark your answers on the answer sheet provided and do not leave any l

question blank.

9.

If the intent of a question is unclear, ask questions of the examiner only.

i 10.

Restroom trips are permitted, but only one applicant at a time will be

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allowed to leave. Avoid all contact with anyone outside the examination

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room to eliminate even the appearance or possibility of cheating.

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i 11.

When you complete the examination, assemble a package including the i

examination questions, examination aids, and answer sheets and give it

to the examiner or proctor.

Remember to sign the statement on the i

examination cover sheet.

j 12.

After you have turned in your examination, leave the examination area as l

defined by the examiner.

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QUESTION: 001 (1.00)

s Given the following conditions:

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A 20 year old, female radiation worker

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t On 1/1/93 she notified her supervisor that she is pregnant

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She is fully qualified and trained All previous radiation. exposure history is on file (NRC Form 4)

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Current total lifetime whole body exposure is 3000 mrem

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In accordance with 10CFR20 Radiation Exposure Limits, what is the i

Maximum Whole body exposure allowed for this individual during

1993?(Assumes a 9 month pregnancy)

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3,000 mrem

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3,500 mrem c.

5,000 mrem

d.

7,500 mrem t

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QUESTION: 002 (1.00)

Given the following conditions:

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Reactor power is 20%.

The minimum shift operations manning requirements per

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administrative procedure 1029 are met.

The normal, on-shift, fire briigade would consist of:

i Shift Foreman

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3 Control Room Operators.

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1 Auxiliary Operator

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b.

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Maintenance Foreman 2 Control Room Operators

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2 Auxiliary Operators

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I Shift Supervisor c.

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Shift Foreman

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2 Control Room Operators

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1 Auxiliary Operator Maintenance Foreman d.

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2 Maintenance Personnel

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2 Auxiliary Operators

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QUESTION: 003 (1.00)

When is a Radiation Work Permit NOT required for INITIAL entry into the

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Reactor Building?

a.

The Reactor is not critical.

b.

An Emergency Entry is being performed.

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The Reactor Building Purge has been completed.

d.

Containment Isolation is no longer required.

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QUESTION: 004 (1.00)

Under certain circumstances OFFICIAL verk may be conducted using

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procedures that do not have the most current revision incorporated.

l Select the ONE type of procedure that is applicable for this statement.

j a.

Operating Procedures

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Survel.11ance Procedures j

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Maintenance Procedures

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d.

Radiological Control Procedures

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QUESTION: 005 (1.00)

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An Operations procedure contains prereguisites or steps which are not applicable for the actual plant conditions encountered.

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From the list below, select one of the individuals who is REQUIRED to j

initial an explanation for a step marked "N/A" (Not Applicable).

t a.

The Control Room Operator b.

The Plant Operations Director i

c.

The Shift Technical Advisor,

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The Shift Foreman

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i QUESTION: 006 (1. 00 ) ~

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Given the following conditions:

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Reactor power is 35%.

The plant is in steady state conditions.

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Select the conditions allowing " Global Silence" of the Control Room f

annunciators.

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Silence " Nuisance Alarms" l

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Enhance crew performance

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During ESAS testing

d.

Complete shift turnover I

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QUESTION: 007 (1.00)

It has been determined that a Motor Operated Valve (MOV) is leaking past

its seat.

The Auxiliary operator has been ordered to hand crank the MOV

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closed.

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Identify the individual REQUIRED to witness the hand cranking.

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A Control Room Operator l

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The Plant Maintenance Supervisor i

c.

The Shift Supervisor / Shift Foreman

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d.

The second, on-shift, Auxiliary Operator

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QUESTION: 008 (1.00)

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Given the following conditions:

i The Reactor Coolant System is LESS THAN 200 degrees F.

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Select the MINIMUM requirement for licensed operators present in the Control Room, according to Administration Procedure 1029.

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1 SRO OR 1 RO.

b.

1 SRO AND 1 RO.

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c.

1 SRO, who is in charge of fuel handling.

d.

The Plant Opertions Director with an " inactive" SRO license.

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QUESTION: 009 (1.00)

What is REQUIRED before trainees can manipulate the controls that

directly affect the reactivity or power level of the reactor?

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They must be under the direct supervision of:

i a.

the training supervisor.

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a licensed operator.

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an NRC exami er.

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d.

the Shift Technical Advisor.

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t QUESTION: 010 (1.00)

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Given the following conditions:

A valve line-up (Procedure Valve Checklist) has been

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performed.

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A valve is reguired to be in a position other than the

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position required by the valve checklist.

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Select the individual (s) REQUIRED to review and approve this deviation.

a.

2 Control Room Operators, both holding Reactor Operator r

licenses.

b.

The Shift Supervisor, acting for the Plant Operations Director.

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2 licensed Operators, one of whom must be a Shift i

Supervisor / Shift Foreman.

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The Shift Foreman, acting for the Shift Supervisor.

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QUESTION: 011 (1. 00)

l A Temporary Change Notice (TCN) is being implemented.via the "Two Member

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of GPUN Management Staff Approval Route."

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Responsible Technical Reviewers (RTRs) ?

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Both RTRs can sign via telecon and one must be on-site.

a.

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b.

One RTR can sign via telecon and he/she must be on-site.

Both RTRs can sign via telecon with the TMI-1 Plant Director j

c.

approval.

I d.

One RTR can sign via telecon and the second RTR must sign in i

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SENIOR REACTOR OPERATOR Page 13 QUESTION: 012 (1.00)

Given the following conditions:

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MU-V-20 has a " Blue Tag" and has been operated.

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MU-V-20 must remain in the "OUT of TAGGED" position.

Select the individual REQUIRED to concur that this condition does not

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represent an unsafe condition.'

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a The employee performing the work l

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A licensed Control Room Operator

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The Shift Foreman d.

The Maintenance Supervisor

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QUESTION: 013 (1.00)

What is the MINIMUM voltage requiring a grounding device be applied to a i

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circuit being tagged out?

r a.

480 volts.

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600 volts.

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4160 volts.

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6900 volts.

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L QUESTION: 014 (1.00)

Who authorizes changing the position of a valve on the " locked valve list?"

a.

The TMI-1 Operations Director b.

A licensed Control Room Operator i

c.

The Shift Technical Advisor i

d.

The Shift Foreman-

i QUESTION: 015 (1.00)

i What is the purpose of the Engineering Safeguards (ES) Checklist?

f It helps assure cognizance of ES components at shift relief, a.

b.

It verifies the line up of the ES components for surveillances.

f c.

It verifies ES components have activated.

d.

It is used to perform a " bulb check" for ES component breakers.

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QUESTION: 016 (1.00)

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In the absence of the Shift Supervisor, who can authorize bypassing a Safety Function?

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The TMI-1 Operations Director i

b.

The licensed Control Room Operator

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The Shift Foreman d.

The Shift Technical Advisor

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QUESTION: 017 (1.00)

A plant' emergency has occurred during normal, weekday, working hours.

You are the RELIEF Shift Foreman.

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Which of the following areas should you report to?

a.

The Control Room

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b.

The Operations support Center i

c.

.The Technical Support Center j

d.

The Emergency Assembly Area f

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QUESTION: 018 (1.00)

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t Which of the following persons can authorize exposures in excess of the i

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limits of 10CFR20.101 during a declared General Emergency?

a.

The Emergency Response Coordinator.

I b.

The Radiological Controls Coordinator.

c.

The Emergency Director.

f d.

The Director of Site Operations.

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i QUESTION: 019 (1.00)

Given the following conditions:

l Reactor power is 90%, steady state, beginning of life.

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The Reactor Demand station is in " Manual", ICS is in

" Track".

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The remaining ICS stations are in " Automatic".

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The contol Room Operator performs a 3 ppm boron dilution.

30 minutes has elapsed since the dilution with NO operator

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action.

i Which of the following describes the expected Tave response?

I a.

Tave will increase and stabilize at a higher value.

b.

Tave will decrease and stabilize at a lower value.

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Tave will vary and return to the same value.

d.

Tave will decrease and then increase to a higher value.

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QUESTION: 020 (1.00)

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Given the following conditions:

Rod withdrawal is in progress for a reactor start-up.

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Group 7 rods are at 50% withdrawn by Relative Position Indication.

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A7 inch, " Asymmetric Rod Fault" alarm is illuminated.

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Rod 7-3 indicates 7.5 inches lower than the group indication by Absolute Position Indication.

Select the method to verify Rod 7-3 position.

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a.

Perform a check of the imbalance and quadrant tilt values.

j b.

Drive Group 7 rods to the inlimit position.

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c.

Perform a check of the zone reference position lamps.

j d.

Withdraw Group 7 rods to the outlimit position.

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QUESTION: 021 (1.00)

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Which of the following conditions will cause an "Out-Inhibit" lamp to

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illuminate on the Diamond Rod Control Panel?

a.

A 1.5 dpm start-up rate in the source range has occurred.

t b.

A 3.0 dpm start-up r te in the intermediate range has occurred.

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c.

Reactor power is greater than 50% and safety rods are not out.

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d.

Reactor power is greater than 60% and a 7-inch asymmetric fault exists.

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QUESTION: 022 (1.00)

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Given the following conditions:

A turbine trip has occurred with reactor power at 80%.

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The reactor did not trip.

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The ICS is in " Manual".

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NO run-back is in progress.

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No operator action has been taken.

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Select the expected primary plant response.

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P a.

Tave Increases

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Th Increases

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Tc Increases b.

Tave Increases l

Th Increases

j Tc Decreases.

c.

Tave remains constant I

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Th Increases Tc Decreases i

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d.

Tave Decreases Th Decreases Tc Increases

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QUESTION: 023 (1.00)

Given the following Technical Specification:

The specific activity of the secondary coolant system shall

--

be less than or equal to 0.10 micro Ci/ gram Dose Equivalent

'

i I-131.

Select the basis for this limit.

This ensures that in the event of a steam line rupture:

'

a.

non-radiation areas inside the plant protected area will be less than 0.80 mr/hr.

b.

" General Area" radiation inside-the plant protected area will

be less than 2.5 mr/hr.

,

c.

" Turbine Building Areas" will be less than 2.5 mr/hr.

d.

off-site radiation doses will be less than the 10CFR100 limits.-

j l

t

.

!

QUESTION: 024 (1.00)

!

i

'

Given the following conditions:

<

High Pressure Injection (HPI) is necessary.

!

--

The Control Room Operator has opened the HPI injection

!

--

valves on the Standby HPI p0mp prior to starting the pump.

i Annunciator alarm, "RC Pump Seal Injection Flow Low" is i

--

illuminated.

,

Why has this alarm been received?

l

'

i l Seal injection flow has decreased because of:

j d

I a.

increased seal injection temperature.

!

t j

b.

decreased letdown flow.

c.

diverting.the seal injection flow to HPI.

l

!

d.

increased flow to Pressurizer makeup system.

!

'

,

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!

.

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,

SEM50R REACTOR OPERATOR Page 19

,

!

.

i QUESTION: 025 (1.00)

-

Given the following conditions:

,

--

Reactor power is 40%.

"

ICS is in " Automatic."

--

The Auto-Inhibit Lamp on the Control Rod Drive system is

'

--

illuminated.

,

What is a possible cause for the Auto-Inhibit Lamp being illuminated?

'

P a.

Reactor-Feedwater error has exceeded plus or minus 0.5%.

,

b.

Rod 3-7 has dropped, which supplied the Group 3 out-limit

{

indication.

c.

Neutron error has exceeded plus or minus 0.5%.

d.

nod 7-5 has dropped, which supplied the Group 7 out-limit indication.

i QUESTION: 026 (1.00)

,

Relative Rod Position differs from Absolute Rod Position indication by

!

90%.

Identify the cause for the difference between the two indications.

l

,

A Reactor Trip has occurred'

a.

.

.

b.

A loss of ICS auto power has occurred.

c.

There is Control Rod "out" motion with an "in" command.

!

d.

A Sequence-Inhibit exists.

.

,

d -~

.

,

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.

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.,,.

.

.

.

.

SENIOR REACTOR OPERATOR Page 20

.

t QUESTION: 027 (1.00)

f Given the following conditions:

i

,

NI-5 has failed and Channel

"A" Reactor Protection System

--

(RPS) is in bypass.

The I&C technician must perform NI-6, Channel

"B" RPS,

,

--

testing.

A " Minimum Degree of5 Redundancy" of ONE must be maintained.

--

i What must be done with Channel

"A" and

"B" in order to perform Channel

"B" testing?

i Place channel

"B" RPS:

in " bypass" and leave channel "A" RPS in " bypass."

a.

b.

in " bypass" and channel

"A" RPS " tripped."

c.

in " shutdown bypass" and channel "A" RPS " tripped."

d.

in " Normal" and channel

"A" RPS " tripped."

(

QUESTION: 028 (1.00)

.The Reactor has tripped from 100% power and no reactor coolant pumps are in operation.

Which of the following is one of the' indications required to verify that natural circulation has been established?

Reactor coolant system delta T is 90 degrees F and increasing.

a.

b.

Cold leg temperatures approach saturation temperature for pressurizer pressure.

,

c.

Reactor coolant system flow is indicated by Non Nuclear Instrumentation indication.

.

d.

Incore thermocouple temperatures stabilize, and are tracking T-hot.

>

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.

.

I SEMIOR REACTOR GPERATOR Page 21 QUESTION: 029 (1.00)

A waste gas release permit has been submitted to, and returned by, the Chemistry department.

Identify the 2 individuals whose signatures are required prior to commencing the release.

l

,

Radiation Control Department and the Shift Supervisor / Foreman..

a.

b.

Radiation Control Department and the Operations Director.

,

c.

Chemistry Supervisor and the Shift Supervisor / Foreman, d.

Chemistry Supervisor and the Operations Director.

j i

!

'

)

>

. QUESTION: 030 (1.00)

!

!

During a loss of off-site power, what is the source of electrical power l

to Reactor Building Spray Pump BS-P-1A?

a.

1E 4160 volt ES Bus.

,

b.

Diesel Generator 1B.

t c.

Diesel Generator 1A.

i d.

The Unit Auxiliary Transforper.

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SENIOR' REACTOR OPERATOR Page 22 i

r

,

QUESTION: 031 (1.00)

Given the following conditions:

Natural Circulation is being established following a loss

--

of off-site power.

Subcooling Margin is 60 degrees F.

--

OTSG levels are 30% on the Operating Range.

--

--

Maximum EFW flow is being delivered to the OTSGs.-

Select the PREFERRED parameter used for control'of emergency feedwater

,

FEEDRATE.

r a.

RCS cold leg temperature.

,

b.

Steam generator pressure.

c.

RCS pressure.

d.

Steam' generator level.

<

!

i

i QUESTION: 032 (1.00)

i Given the following conditions:

Both Main Feedwater Pumps have tripped.

,

--

--

The Reactor has tripped and emergency feedwater has

initiated.

l

--

The Condensate Storage Tank low-low level alarm is

illuminated.

,

--

The Condensate Storage Tank level reads 2.0 feet.

Select the PREFERRED source and flow path of water to the Emergency

Feedwater Pumps.

.

a.

The Condensate Storage Tanks.

!

b.

The Million Gallon Tank.

,.

c.

River water via the Reactor Building Emergency Cooling System.

j d.

The condenser hotwell.

,

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!

SENIOR REACTOR OPERATOR Page 23

t

!

QUESTION: 033 (1.00)

i

'

!

!

Given the formula for BTU limits:

BTU Limit = (Thl + Tfwl + Psgl -

j

-

200) (Frc1) (0. 01).

-j i

Identify the parameter, and its direction of change, that increases the l

!

BTU-limit (Causes the calculated value to increase).

i a.

Steam Generator pressure decreasing, b.

Reactor coolant flow decreasing j

c.

Steam-Generator pressure increasing.

I d.

Feedwater temperature decreasing, t

i

!

QUESTION: 034 (1.00)

-

Given the following conditions:

!

!

'

--

The Reactor power is 95%.

--

Reactor Building average temperature is 128 degrees F and

increasing to 130 degrees F.

--

The Shift Supervisor has determined it is desirable to use

.

Reactor Building Emergency Cooling.

!

!

Choose the heat sink for the Reactor Building Emergency Coolers.

'

Nuclear Services Closed Cooling Water.

a.

b.

Nuclear Services River Water.

I c.

Reactor River Water.

i d.

Emergency Feedwater.

!

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.

i SENIOR REACTOR OPERATOR-Page 24 QUESTION: 035 (1.00)-

[

I What is the purpose of maintaining a minimum of 3 gpm make-up flow when the RCS is greater than 250 degrees F?

!

!

a.

This maintains the Pressurizer Spray nozzle at thermal equilibrium.

j i

b.

This prevents thermal shock to the Make-up line.

.;

This preheats the High Pressure Injection nozzles.

c.

d.

This prevents back flow through the Reactor Coolant Pump seals.

.

!

QUESTION: 036 (1.00)

,

Given the following conditions:

A LOCA has occurred.

--

The Reactor has tripped and is subcritical.

--

Full High Pressure Injection (HPI) is in progress.

!

--

,

Select the criteria requiring HPI to be lined up in the " Piggyback" mode

<

of operation.

RCS pressure stabilizes at a pressure higher than LPI discharge a.

,

pressure.

l b.

The PORV has been opened to' establish heat transfer.

f c.

Subcooling Margin (SCM) of 25 degrees or greater has been

.

established.

!

d.

Borated Water Storage Tank (BWST) level reaches 6.0 feet, 4

>

inches before LPI flow has been established.

i i

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a s

.

.

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SENIOR REACTOR OPERATOR Page 25 l

i i

I QUESTION: 037 (1.00)

i Given the following conditions:

Fuel Handling is in progress inside the Reactor Building.

--

RM-A-9, GAS Channel increases to its HIGH ALARM.

l

--

.

Which of the following AUTOMATIC actions occur?

{

a. Purge Valves, AH-V-1A,B,C and D "OPEN."

-l i

b..RB Sump Drain valves, WDL-V-534 and 535 "CLOSE."

j c. Release Isolation valve, WDL-V-257 " CLOSES."

!

d. Waste Gas Release valve, WDG-V-47 " CLOSES."

!

t

!

QUESTION: 038 (1.00)

!

!

Select the conditions which indicate a small break LOCA has occurred i

inside the Reactor Building.

ESAS has NOT actuated.

?

a.

Tave decreasing i

RCS pressure decreasing i

i Reactor Building pressure constant RM A-2, RB Atmospheric Monitor, increasing b.

Tave constant

[

RCS pressure decreasing Reactor Building pressure increasing

RM A-2, RB Atmospheric Monitor, constant c.

Tave constant RCS pressure decreasing i

Reactor Building pressure increasing l

RM A-2, RB Atmospheric Monitor, increasing l

d.

Tave decreasing

+

RCS pressure decreasing Reactor Building pressure constant l

RM A-2, RB Atmospheric Monitor, constant l

i f

!

!

,

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.

SENIOR REACTOR OPERATOR Page 26

!

.

' QUESTION: 039 (1.00)

l Given the following conditions:

t A loss of off-site power has occurred.

l

--

The Reactor has tripped

'

--

RCS T-cold is NOT tracking OTSG saturation pressure.

--

Choose an acceptable temperature indicator to be used to determine i

"

subcooling margin.

t a.

T-hot i

b.

Incore thermocouples

>

l c.

Tave-i

i d.

Tsat for OTSG pressure t

i QUESTION: 040 (1.00)

{

i

!

Given the following conditions:

'

,

RCS pressure has decreased to 1550 psig.

--

Reactor building pressure is 1 psig.

--

,

'

ECCS has actuated.

--

Make-up tank outlet check, MU-V-112 has seated.

--

What is the Make-op Tank (MU-T-1) level response and the reason for that

response?

!

Make-up Tank level:

i a.

increases, because of RCP seal leak off.

'

b.

decreases, because of HPI injection.

l

,

'

c.

increases, because of Make-up pump recire.

l d.

decreases, because of letdown flow.

l t

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.

.

.

.

.

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.

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.

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.

SEMIOR REACTOR OPERATOR Page 27

'

i i

QUESTION: 041 (1.00)

l

,

Given the following conditions:

t

'

'

--

Reactor power is 100%.

All ICS control stations are in " Automatic."

--

SASS is not operational.

>

--

--

Selected T-hot fails " low."

l i

'

Identify the expected ICS (Plant) response.

(Assume no operator actions

.

taken.)

j

$

a.

Feedwater demand increases.

b.

Neutron crosslimits cause reactor power to decrease.

c.

Control rods drive inward to limit reactor power.

d.

BTU limits will decrease feedwater demand.

,

t

QUESTION: 042 (1.00)

,

!

'Given the following c'onditions:

A Natural Circulation cooldown is in progress.

--

--

Pressurizer level is increasing.

--

RCS pressure is decreasing.

,

Identify the cause for these plant conditions.

'

.

a.

Normal plant cooldown is in progress.

b.

A Reactor vessel head bubble has developed.

c.

T-hot vents are open.

!

d.

Pressurizer steam bubble formation is in progress.

,

b i

'

!

,

I a

,

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-

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.

,

SEN10R REACTOR OPERATOR Page 28 QUESTION

043 (1.00)

.

Given the following conditions:

A loss of off-site power has occurred.

j

--

--

A large break LOCA has occurred.

,

I ECCS has actuated with a combined HPI flow of 1200 gpm.

--

RCS pressure is 800 psig.

!

--

SCM reads 0 degrees P (RCS is at saturation).

--

For these conditions, choose the " Rule" requiring HPI " throttling."

l

!

a.

LPI flow is greater than 1000 gpm in each line and stable for

.

20 minutes.

b.

Subcooling margin is less than 25 degrees F.

c.

HPI must be throttled to prevent pump runout.

't i

d.

HPI must be throttled to prevent violation of the applicable Brittle Fracture / Thermal Shock curve limitations.

!

!

.

QUESTION: 044 (1.00)

Given the following conditions:

l

--

A large tear has developed in the expansion joint between

[

the Main turbine and condenger.

!

--

The Reactor has tripped due to a turbine trip.

!

The turbine trip was due to high condenser pressure.

i

--

Identify the method for controlling OTSG pressure once hot shutdown

!

conditions are met.

(RCS Tave = 532 degrees F).

I

!

a.

Turbine bypass control i

i b.

Periodically lifting of the OTSG steam safeties j

i c.

Feeding the OTSGs with emergency feedwater

!

I d.

Atmospheric dump valve control

!

!

!

!

!

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' SENIOR REACTOR OPERATOR Page 29 QUESTION: 045 (1.00)

Given the following conditions:

The plant is in cold shutdown.

--

Refueling operations are in progress.

--

A continuous containment purge is in progress.

--

The I&C technician needs to tag out RM-A-9, Reactor Building Purge Exhaust Radiation Monitor, for calibration.

All three channels,

,

particulate, iodine, and gaseous, will be out of service.

Choose the action required to support this calibration.

-

a.

Stop the containment purge, b.

Take containment air samples every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with RM-A9 isolated.

$

c.

Notify the SRO in charge of Fuel Handling operations, d.

Place a portable air sampler in the containment building, i

e QUESTION: 046 (1.00)

Which of the following indicates a " Dry OTSG" ?

OTSG start-up range level is:

a.

zero and OTSG pressure is 200 psig.

]

b.

zero and OTSG pressure is 250 psi " greater than" saturation pressure for T-cold in that loop.

c.

7 inches and OTSG pressure indicates 0.0 psig.

<

d.

Zero and OTSG pressure is 250 psi "less-than" saturation pressure for T-cold in that loop.

l i

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.

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.

.

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.

.

.

SENIOR REACTOR OPERATOR Page 30 ^

,

QUESTION: 047-(1.00)

!

From 0 to 15 % reactor power, OTSG level is maintained at low level limits.

!

Identify the reactor coolant system response as a result of this operational. characteristic.

a.

Tave remains constant RCS delta T increases b.

Tave increases

i RCS delta T remains constant i

c.

Tave increases

'

RCS delta T increases d.

Tave remains constant RCS delta T remains constant

.

QUESTION: 048 (1.00)

!

Given the following Conditions:

l

.

--

Reactor power is 100% with all ICS control systems in

" automatic."

.

!

"A" OTSG pressure instrument fails high (1200 psig).

--

"A" OTSG Turbine bypass valyes open to 100%.

--

.

Select the expected feedwater response.

(Assume no operator action is

,

taken.)

,

a.

Feedwater Demand accepts Tave control.

l b.

The

"A" OTSG's feedwater demand signal becomes BTU' limited.

i c.

Total feedwater demand signal remains constant, d.

Feedwater demand signal increases.

,

!

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.

.

,

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.

.

-SENIOR REACTOR OPERATOR Page 31

!

,

QUESTION: 049 (1.00)

!

Given the following conditions:

'

i RCS pressure is decreasing.

.

--

'

Pressurizer level is constant.

--

Make-up tank level is decreasing.

--

,

Identify a possible cause for'these conditions.

a.

A large break LOCA has occurred.

b.

A large main steam leak has occurred.

c.

A steam leak in the Pressurizer steam space has occurred.

~

.

d.

RCS letdown has been isolated.

^

.

QUESTION: 050 (1.00)

!

A RCS fill is in progress and a 5 minute vent of the pressurizer is required.

.

Choose the reason for this venting requirement.

l Venting is required to:

i a.

remove non-condensable gases.

,

!

b.

draw a bubble in the Pressurizer.

,

!

c.

verify the PORV operability.

l d.

verify pressurizer heater capacity.

i

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.

. -

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-

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._

_

_

_ _ _.. _

.-

.

.

SENIOR REACTOR OPERATOR Page 32

.

!

QUESTION: 051 (1.00)

!

!

Given the following conditions:

The reactor is in cold shutdown.

--

Refueling operations are in progress.

--

An irradiated fuel assembly is in the Main bridge mast.

--

--

A Reactor Building evacuation has just been announced.

--

Time and conditions permit the Fuel Handling Supervisor to take actions prior to leaving the refueling area.

What should be done with the fuel assembly in the Main bridge mast?

a.

Leave the fuel assembly in the mast, and move Main bridge over fuel transfer canal.

,

b.

Insert the fuel assembly into the core and disengage the grapple.

c.

Insert the fuel assembly into the upender and transfer it to the spent fuel pool.

d.

Insert the fuel assembly into a designated storage location and do not disengage the grapple.

QUESTION: 052 (1.00)

i

!-

Given the following conditions:

.

--

Refueling operations are in progress.

--

A fuel assembly is experiencing Grid interference while being removed from the core.

,

,

Whose permission is required to bypass the overload cut-out?

I a.

The Core Load Engineer b.

The Fuel Handling Supervisor

[

c.

The Bridge Operator

'

d.

The Shift Supervisor

.

t

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.

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,

.

.

,

SENIOR REACTOR OPERATOR Page 33

QUESTION: 053 (1.00)

j

\\

Given the following conditions:

i Reactor power was 100%.

!

--

A loss of off-site power has occurred.

j

--

An ES signal is present.

'

--

Instrument air header pressure is decreasing.

I

--

'Why is instrument air header pressure decreasing?

a.

Air-operated valves are repositioning due to ES actuation.

b.

IA-V-1, cross-connect between instrument and service air, has

opened.

l

>

c.

A loss of power to the instrument air compressors has occurred.

!

!

d.

Air-operated valves are cycling in-response to the l

Reactor / Turbine trip.

l

!i l

t QUESTION: 054 (1.00)

{

r Given the following condition:

!

A loss of

"A" DC distribution has occurred.

.;

--

i What is required to be done with the, emergency diesel generator, EG-Y-1A?

,

The operator must:

l i

!

a.

perform a " loss of DC control power" start, synchronize and load EG-Y-1A.

b.

trip EG-Y-1A.

[

i c.

start EG-Y-1A and leave in no load condition (idle).

l i

d.

synchronize and load EG-Y-1A.

{

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SENEOR REACTOR OPERATOR Page 34 l

t T-QUESTION: 055 (1.00)

i Given the following conditions:

?

--

The plant is in cold shutdown.

Decay Heat Removal (DHR) is in operation.

--

The RCS is open with the vessel head removed.

--

--

The RCS must be drained down for RCP seal replacement.

'

.

Why is the DHR system operated to the left and above the "RCS level verses Decay Heat flow curve" during LOW RCS LEVEL conditions?

!

The DHR system is operated to the left and above the "RCS level verses Decay Heat flow curve" to prevent:

!

a.

RCS heat up.

t f

b.

vortex formation.

c.

stratification of chemicals in the RCS.

i d.

exceeding the delta T across the Decay Heat cooler.

p

!

QUESTION: 056 (l'. 0 0)

!

!

Given the following conditions:

{

The Decay Heat Removal (DHR) system in operation.

--

No Reactor Coolant Pumps are in operation.

--

Select the temperature indicator used to ensure compliance with the i

'

plant heat-up and cooldown curves.

l a.

Core exit thermocouples l

-

r j

b.

Decay Heat Pump suction temperature

{

.

.

)

c.

Decay Heat system cooler outlet temperature r

d.

Reactor Coolant System T-hot and T-cold as~ indicated by Non-i Nuclear Instrumentation j

.

>

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,

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!

!

r i

F

.

.

.

-

.

I

--

-

-

-

b

.

,

.

SENIOR REACTOR OPERATOR Page 35 i

t i

. QUESTION: 057 (1.00)

l Given the following conditions:

--

Reactor Coolant System pressure is 2500 psig.

,

"

Pressurizer temperature is 648 degrees F.

--

A Pressurizer code safety has lifted and is stuck open.

--

The Reactor Coolant Drain Tank (RCDT) rupture disc has

--

i ruptured.

,

--

Reactor Building pressure is O psig.

.

What is the expected RCDT temperature?

'

a.

~212 degrees F.

b.

~300_ degrees F.

,

c.

555' degrees F.

d.

648 degrees F.

,

,

QUESTION: 058 (1.00)

After a reactor trip occurs, the turbine bypass valves have an additional bias applied to their signal.

l k

' Select the purpose for applying this bias.

,

'

This bias signal will prevent:

e

!

a.

Main turbine governor and turbine bypass valves from competing for OTSG pressure control, b.

a large insurge into the pressurizer, c.

atmospheric. dump and turbine bypass valves from competing for

OTSG pressure control.

!

i d.

excessive cooling of the RCS.

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,

?

QUESTION: 059 (1.00)

Given the following conditions:

Reactor power is 75%.

--

All-ICS stations are in " automatic."

--

A 7 inch asymmetric rod alarm has illuminated.

--

,

'

A rod bottom light for rod 7-4 has illuminated.

--

Select the immediate Manual operator required action.

!

'

a.

Trip the reactor and verify all rods on the bottom.

b.

Verify runback / manually reduce power to less than 60% thermal

.

power for the allowable quadrant tilt.

Verify runback / manually reduce power to less than 60% thermal

!

c.

power for the RCP combination.

,

J d.

Verify runback / manually reduce power to less than 60% thermal power for the allowable power imbalance.

QUESTION: 060 (1.00)

,

'

Given the following conditions:

Reactor power is 70%.

--

--

All ICS stations are in " automatic."

--

The Control Room Operator has decreased power by using the Unit Load Demand station.

--

A motor fault lamp has illuminated.

.

A constant, positive, start-up rate is indicated.

t

--

Identify the cause for the motor fault alarm, a.

Neutron error has exceeded 1%.

f b.

Programmers have out motion with an "in" command.

c.

Loss of programmer 24 volt de power supplies.

d.

A high start-up rate of 3 DPM.

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!

'!

QUESTION: 061 (1.00)

i Given the following conditions:

}

Tne reactor has been at 100% power for 28 days.

}

--

A stuck rod has been found.

--

Shutdown margin must be verified.

--

Choose the worth (delta k/k) that must be combined with the inoperable rod for shutdown margin verification.

a.

Peak lencn worth r

b.

Peak samarium worth

c.

Tave correction

i d.

The highest worth operable rod

QUESTION: 062 (1.00)

i Given the following conditions:

!

Reactor Coolant Pumps (RCPs) are "off".

--

--

A large break LOCA has occurred.

,

ECCS Systems have functioned as designed.

(

--

Pressurizer level indicates

"0" inches.

--

Reflood of the Reactor Core,has been completed..

l

--

Identify the RCS pressure and temperature relationship for the above l

conditions.

!

}

Core exit thermocouples will indicate saturation temperature

'

a.

for the existing RCS pressure.

b.

T-cold will indicate saturation temperature for the existing

!

OTSG pressure.

l t

c.

Core exit thermocouples vill indicate superheat temperature for

!

the existing OTSG prf:ss,'e.

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d.

T-cold will indicato superheat temperature for the existing RCS pressure.

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i SENFOR REACTOR OPERATOR Page 38 i

I QUESTION: 063 (1.00)

,

Incore thermocouple temperatures are beyond Curve

"C",

Tclad is greater than 1800 degrees F, and Reactor Coolant Pumps (RCPs) are required to be i

operated.

Select the requirements for RCP operation in this condition.

,

Start one RCP per loop if possible, without defeating starting i

a.

interlocks.

l t

b.

Start one RCP per loop if possible, defeating starting interlocks.

'

c.

Start all available RCPs without defeating starting interlocks.

j d.

Start all.= /ailable RCPs, defeating starting interlocks.

!;

!

t QUESTION: 064 (1.00)

{

i I

.Given the following conditions:

I Reactor power is 100%.

I

--

Reactor Coolant Pump (RCP) seal injection has been isolated

~

'

--

,

for repairs on MU-V-20 (RCP seal injection isolation).

pump "IC-P-1B" is Intermediate Closed Cooling Water (ICCW)ipped on overload.

'

--

tagged for repairs, and "IC-P-1A" has tr

!

The Auxiliary Operator has reported that the packing on IC-

-

--

P-1A has overheated and seized the pump.

.

Identify the required operator action for these conditions.

t a.

Trip the Reactor.

b.

Trip the Reactor and trip the RCPs.

f c.

Shutdown the Reactor, and secure RCPs as soon as possible.

d.

Trip 2 RCPs, leave 1 RCP running per loop.

!

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SENIOR REACTOR OPERATOR Page 39 l

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i l

!

QUESTION: 065 (1.00)

{

i l

Given the following conditions:

,

.

Reactor power is 100%.

l

--

Low motor current is indicated for

"A" Reactor Coolant Pump

,

--

(RCP).

.

--

Low RCS flow is indicated.

t'

--

High RCP vibration on

"A" RCP is indicated.

Identify the required operator response, a.

Trip the reactor and secure "A" RCP.

,

b.

Secure

"A" RCP and verify runback to less than 75% reactor power.

c.

Commence a plant shutdown and secure

"A" RCP.

I d.

Shutdown plant to 50% power with 1 RCP running per Joop.

l l

F

QUESTION: 066 (1.00)

Given the following conditions:

,

The reactor has been shutdown due to a loss of offsite

--

,

power.

.

--

Natural circulation has been established.

--

RCS flow indication reads "d" lbm/hr.

'

Which of the following is the reason for the

"0" RCS flow indication.

!

a.

Natural circulation flow is a fraction of forced RCS flow.

!

b.

Natural circulation flow is in reverse of normal RCS flow.

'

!

c.

Natural circulation flow collapses RCS voids, which causes RCS

?

flow to surge then stop.

d.

Low RCS flow indication has not been selected.

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,

-

i QUESTION: 067 (1.00)

,

Given the following conditions:

!

--

A reactor trip has occurred from 100% power.

2 rods have remained at 100% withdrawn.

l

--

--

The Boric' Acid Mix Tank has 7000 gallons at 12,250 ppm i

boron.

!

i Which of the following would require delaying emergency boration?

i a.

The boric acid injection line heat trace needs to be energized.

,

b.

There is insufficient capacity in the make-up tank.

c.

The 2 stuck rods need to be re-latched and driven into the

-

Core.

d.

The shift foreman has not completed the boric acid injection calculation.

QUESTION: 068 (1.00)

,

Given the following conditions:

--

Reactor power is 100% and steady state.

'

All ICS stations are in " automatic".

--

--

Control rods have been movi*ng in over the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The RCS leak rate has decreased over the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

--

--

Tave and pressurizer level have been constant.

l Which of the following could cause these changes?

a.

Xenon has been increasing to reach equilibrium.

[

b.

An inadvertent boration is occurring.

L c.

An inadvertent boron dilution is occurring.

l d.

Samarium has been decreasing to reach equilibrium.

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1 QUESTION: 069 (1.00)

.

!

Given the following conditions:

i Reactor power is 100%.

--

A loss of Intermediate Closed Cooling Water (ICCW) has j

--

occurred.

!

--

Pressurizer level is 330 inches and increasing.

-;

Letdown cannot be re-established.

.l

--

Control Rod Drive _(CRD) stator temperatures are increasing I

--

with one at 181 degrees F and another at 183 degrees F.

,

i Identify the required operator actions.

Commence unit shutdown and trip the reactor at 380 inches in

~f a.

the pressurizer.

l i

b.

Trip the reactor and follow 1210-1, " Reactor Trip" procedure.

f

'

c.

Place the CRDs with high stator temperatures on the hold bus.

.

!

i d.

Isolate make-up to the pressurizer.

!

-

I

QUESTION: 070 (1.00)

)

Given the following conditions:

i Reactor Power is 100%.

--

--

A turbine trip has occurred'.

!

The reactor DID NOT trip.

.;

--

What parameter, and its' response, is DIFFERENT from the standard 100%

l power reactor trip (where the turbine trips following the reactor trip)?

j Reoctor power will decrease.

a.

t b.

Reactor coolant pressure will decrease initially.

j OTSG pressure will increase to the safety setpoint initially.

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c.

,

d.

Tava will increase initially.

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SENIOR. REACTOR. OPERATOR Page 42

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I

!

QUESTION: 071 (1.00)

-l

!

i

!

'Given the following conditions:

'

A steam leak has occurred.

l

--

The Heat Sink Protection System (HSPS) has initiated j

--

!

on low "A" OTSG pressure.

Reactor Building temperature is normal.

--

,

"A" OTSG pressure continues to' decrease.

--

The Reactor coolant system pressure and temperature e

--

'

are decreasing.

Select the location of the steam leak.

a.

"A" OTSG steam line inside the Reactor Building.

b.

"B" OTSG Main Steam Safety.

c.

"B" steam line downstream of the Main Steam Isolation Valves.

l

'

,

d.

"A" steam line to the emergency feed. pump turbine.

!

j

QUESTION: 072 (1.00)

During a " Station Blackout", what is the purpose of venting the hydrogen from the main generator?

The purpose of venting the hydrogen is to:

a.

allow the main generator emergency seal oil pump to be secured.

.

i b.

prevent overpressurization of the main generator.

,

c.

reduce the heat load on the main generator.

d.

prepare the main generator for cold shutdown conditions.

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SENIOR REACTOR OPERATOR Page'43

.

,

QUESTION: 07'3 (1.00)

i Given the following. conditions:

A station Blackout has occurred.

--

The reactor has tripped from 100% power.

--

Subcooling Margin is 20 degrees F.

!

--

)

OTSG level should be raised to/ maintained at:

.;

greater than or equal to 25 inches in the start-up range.

t a.

b.

greater than or equal to 50% in the operating range.

'

c.

75 to 85% level in the operating range.

h-i d.

95 to 100% level in the operating range.

!

t i

QUESTION: 074 (1.00)

f f

A reactor trip has occurred due to a station _ blackout.

IMMEDIATELY i

after the reactor trip the' Shift Supervisor (SS) has asked the Control l

Room Operator (CRO) to verify natural circulation.

t Natural Circulation:

!

a.

can be immediately verified by observing Reactor Coolant System i

(RCS) delta T is increasing,

,

b.

can be immediately verified by observing OTSG safeties are

opening indicating steam flow.

,

c.

CANNOT be immediately verified.

A 5 minute wait is required to

~ ;

verify feed flow decreasing to low level limits.

,

d.

CANNOT be immediately verified.

A 15 to 30 minute wait may be required for plant conditions to stabilize.

f

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SENIOR REACTOR OPERATOR-Page 44

,

QUESTION: 075 (1.00)

During a station blackout, why-shouldn't the atmospheric radiation monitors be used for calculating offsite doses?

a.

The air pumps on the atmospheric radiation monitors are "Not l

r Available".

b.

The supply and return valves for the atmospheric radiation

,

monitors fail closed.

The atmospheric radiation monitors have failed "high."

i c.

d.

The atmospheric radiation monitors do not monitor the required

,

release paths.

QUESTION: 076 (1.00)

Control Room evacuation is required.

The reactor was tripped prior to

.

evacuation.

How is the reactor verified shutdown from the "B" Remote Shutdown Panel (RSD)?

.

a.

All rod bottom lights are on.

l b.

Source range counts are on scale and decreasing.

Power Range meter reads "0%

power.

c.

d.

Turbine throttle and governor valves indicate shut, t

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- SENIOR REACTOR OPERATOR Page 45

-

,

~

. QUESTION: 077 (1.00)

The Shift Supervisor / Foreman is directing a "Cooldown from Outside the Control Room".

,

.

Why is it important to establish OTSG pressure and level control as soon as possible during this procedure?

a.

To establish / control iprimary to secondary heat transfer.

l

!

b.

To verify the reactor is shutdown.

c.

To establish / control off-site radiation releases.

d.

To verify the ICS has performed its function.

!

!

' QUESTION: 078 (1.00)

!

During a "Cooldown from Outside the Control Room," how does the operator

[

at Remote Shutdown Panel (RSD)

"B" verify the 1E 4160V bus is energized?

l t

RSD "B" is verified energized by.

j a.

a voltage meter deflection of 3/4 scale at the panel.

I b.

a white light illuminated at the panel.

c.

contacting the operator at the 1E Bus.

f

.

,

d.

indication of 1B Diesel Generator running and loaded.

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SENI-OR REACTOR OPERATOR'

Page 46 l

!

!

QUESTION: 079 (1.00)

-;

Given the following conditions:

i The reactor has tripped from 100% power.

'

--

The Subcooling Margin indicates."0" degrees F.

'i

--

RCPs are "off."

l

--

!

--

Incore thermocouples are alternating between saturated and superheat conditions.'

}

!

Select the mode of RCS cooling occurring for the present conditions.

i a.

Natural _ Circulation

b.

Forced convection f

i c.

Boiling-condenser d.

Natural Conduction

!

>

e

,

P QUESTION: 080 (1.00)

When the RCS indicates superheat, secondary'Tsat is to be maintained 100 degrees F less than Tsat for the RCS.

i

!

One method of lowering secondary Tsat could be:

'

l a.

lowering turbine bypass control setpoints.

.j b.

isolating the atmospheric dump valves.

,

c.

raising the turbine bypass control setpoints.

j d.

isolating the turbine bypass valves.

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,

SENIOR REACTOR OPERATOR Page 47 i

QUESTION: 081 (1.00)

Given the following conditions:

RM-L-1 (HI Channel), Letdown Radiation Monitor, "high"

--

alarm is in.

--

The Shift Supervisor has determined that high activity exists in the Reacto Coolant System (RCS) letdown."

.

The SS has decided to reduce activity by increasing purification flow.

What must be done in order to balance RCS make-up and purification flow?

a.

A second make-up and purification demineralizer must be valved in.

b.

Reactor Coolant Pump (RCP) seal injection flow must be increased.

c.

Pressurizer level setpoint must be increased.

d.

Letdown flow must be re-established.

QUESTION: 082 (1.00)

,

!

'

Given the following conditions:

A reactor trip has occurred.

--

'

--

Subcooling Margin (SCM) is 35 degrees.

--

T-cold is approximately equal to T-Sat for OTSG pressure.

Pressurizer level is 15 inches and steady.

--

t Select the required operator response.

a.

Isolate letdown b.

Initiate HPI c.

Initiate EFW d.

Trip both MFW pumps i

h

.

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SENIOR REACTOR OPERATOR Page 48

,

QUESTION: 083 (1.00)

,

Given the following conditions:

The reactor has tripped.

l

--

Reactor Building pressure is 4 psig.

l

--

e The Shift Foreman wants to re-establish normal cooling to the reactor i

. building coolers.

-

Whose permission is required to realign the valves to the reactor

!

building coolerr,?

,

!

a.

shift Foreman

,

b.

Control Room Operator

,

c.

Emergency Director

d.

Shift Technical Advisor i

,

P QUESTION: 084 (1.00)

.

J

Given the following conditions:

f I

The reactor has tripped.

l

--

--

A small break LOCA cooldown is in progress.

--

RCPs are off and unavailable due to a locs of off-site

[

'

'

power.

I

--

Subcooling Margin has been regained.

--

Core Cooldown rate is 150 degrees F per hour.

It is desired to throttle HPI to control the cooldown rate.

,

!

'

The maximum band given to control RCS pressure-temperature should be between:

a.

the Sat curve and the 25 degrees SCM curve.

I b.

the 25 degrees SCM curve and PTC curve.

!

c.

the NPSil curve and the PTS curve.

'

'

d.

the PTS curve and the RV P-T curve.

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SENIOR REACTOR OPERATOR Page 49

l QUESTION: 085 (1.00)

j A large break LOCA has occurred. 'The Borated _ Water Storage Tank (BWST)

low level alarm has come in and BWST level.is 30 feet..The Control Room Operators have taken the appropriate actions.

What is the source of water to the LPI pumps?

,

a.

The Reactor Building isump.

b.

The BWST.

!

c.

The RCS.

d.

The High Pressure Injection pumps.

!

,

QUESTION: 086 (1.00)

Given the following conditions:

--

A large break LOCA has occurred.

--

The "Large Break LOCA Cooldown" procedure is in use.

Low Pressure Injection (LPI) flow reads

"O" gpm in both

--

legs.

RCS pressure is starting to stabilize near 500 psig.

!

--

'

Identify the procedure the operators are directed to follow.

'

a.

Stay in the "Large Break LOUA Cooldown" procedure.

b.

Transition to the "RCS Superheated" procedure.

c.

Transition to the " Loss of 25 degrees F sub-cooled margin" procedure.

,

d.

Transition to the "Small Break LOCA Cooldown" procedure.

!

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I SENI.OR REACTOR OPERATOR Page 50 i

QUESTION: 087 (1.00)

,

Abnormal Transient Procedure (ATP) 1210-8 requires that if incore thermocouple temperatures are beyond curve B and Primary.to Secondary j

Heat Transfer is established then the PORV should be cycled to maintain RCS pressure at 25 to 100 psi above OTSG pressure.

Which of the following is the reason for maintaining RCS pressure at least 25 psi above OTSG pressure.

'

a.

Reduce OTSG tube stresses

,

b.

Prevent leakage fror the OTSGs to the RCS

,

c.

Maintain Primary to Secondary Heat Transfer

,

d.

Ensure adequate Reactor Coolant Pump NPSH QUESTION: 088 (1.00)

Given the following conditions:

--

The Pressurizer Spray Valve has failed open.

!

--

The Control Room Operator (CRO) has closed RC-V-3, the

'

Spray Block Valve.

f

'

How is Pressurizer spray line temperature kept within 250 degrees of

!

Pressurizer temperature?

,

I c.

Cycle RC-V-3, spray block valve, as necessary.

Insurge and outsurge the Pressurizer by increasing and

.

o.

'

decreasing letdown flow.

c.

Cycle the pressurizer heater banks.

d.

Insurge and outsurge the Pressurizer by increasing and decreasing make-up flow.

.

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'

.

.

E SENIOR REACTOR OPERATOR page 51

,

-QUESTION: 089 (1.00)

,

Given the following conditions:

'

An OTSG tube leak of 2.0 gpm is present.

--

The' reactor has not tripped.

'

--

'

Choose the required action and objective for these conditions.

a.

Trip the reactor, perform immediate actions for " Reactor Trip" concurrent with "OTSG Tube Leakage" in order to place the plant

,

in cold shutdown as soon as possible, b.

Shutdown the reactor and isolate the affected OTSG with OTSG

,

pressure at 1010 psig to prevent the release of contamination.

l

'

c.

Trip the reactor, and immediately isolate the affected OTSG to prevent the contamination of the secondary systems.

,

d.

Shutdown the reactor and minimize the risk of Main Steam safety

'

valve lifting.

i

i QUESTION: 090 (1.00)

!

Given the following conditios:

--

An OTSG tube leak has occurred.

The leak is approximately 1.5 gpm.

<

--

--

The Emergency Director has authorized an emergency cooldown

,

rate of 150 degrees F per hour.

Prior to reducing RCS temperature below 500 degrees F, what is required by procedure?

'

a.

Isolate the affected OTSG.

b.

Perform secondary system (valve leak off, domineralizer regeneration, etc.) isolation.

c.

Stop one RCP. (3 RCPs or less can be running).

d.

Commence depressurization of the Reactor Coolant System (RCS)

by intermittently spraying the Pressurize l, s

.

.

SEN60R REACTOR OPERATOR Page.52 i

!

!

QUESTION: 091 (1.00)

,

t Which of the following would be an indication of an EXCESSIVE RCS

'i cooldown rate?

'

a.

Subcooling Margin (SCM) reads LESS THAN or equal to 10 degrees F.

b.

Tube to shell delta T indicates LESS THAN or equal to Minus 70 degrees F (MORE NEGATIVE).

c.

Tube to shell delta T indicates GREATER THAN or equal to Plus i

70 degrees F (MORE POSITIVE).

i d.

The plant computer indicates a cooldown rate of 50.0 degrees F per hour.

.

!

,

QUESTION: 092 (1.00)

.

.

Given the following conditions:

'

--

A tube leak of 3 gpm has occurred in the

"A" OTSG.

--

RCS T-hot reads 490 degrees F.

'

RCS pressure is 900 psig.

--

--

BWST level is 20.5 feet.

The tube leak is increasing according to the mass balance and chemistry samples.

Radiation levels on the turbine deck, outside of controlled

.

access, have increased.

l

.

Select the required action.

a.

Increase cooldown rate and depressurization of the RCS.

,

b.

Use the atmospheric dumps instead of the turbine bypass valves.

l c.

Perform a High Pressure Injection (HPI) cooldown.

i d.

Isolate the

"A" OTSG.

!

,

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.

.

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,

.

.

i SENLOR REACTOR OPERATOR Page.53 i

.

QUESTION: 093 (1.00)

}

i Given the following conditions:

A loss of offsite power has occurred.

--

The reactor has tripped.

!

--

Natural circulation has been verified.

--

When offsite power has been restored, it is desired to start a Reactor

' Coolant Pump (RCP).

i

!

The expected response of OTSG pressure and RCS pressure when the RCP is started would be:

,

OTSG pressure:

l increases rapidly and RCS pressure decreases rapidly.'

i a.

b.

increases rapidly and RCS pressure increases rapidly.

c.

decreases rapidly and RCS pressure decreases rapidly.

.

l d.

decreases rapidly and RCS pressure increases rapidly.

i

?

QUESTION: 094 (1.00)

!

,

Given the following conditions:

i

--

A reactor / turbine trip has 6ccurred.

i

--

The Control Room Operator (CRO) has reported a loss of "A"

,

DC distribution System power.

Select the immediate action per 1210-1, " Reactor Trip", which must be performed LOCALLY outside the Control Room.

a.

Manually trip / Verify all rods are on the bottom.

'

b.

Check / verify ICS/NNI are energized.

Manually trip / Verify generator field breaker is open.

c.

'

d.

Check / verify sub-cooling margin is greater than or equal to 25 degrees F.

!

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!

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.

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.

. SENIOR REACTOR OPERATOR Page 54 i

l

QUESTION:'095 (1.00)

i

'

'The Control Room Operator (CRO) reports to the SS that main feed, pump speed is erratic on both pumps and condenser pressure is increasing.

Secondary plant instrument air pressure is 58 psig.

.

Identify the required operator action.

l a.

Attempt to start backup instrument air compressors.

b.

Trip the reactor.

j i

c.

Control OTSG pressure with the atmospheric dump valves.

d.

Monitor backup sources of instrument air.

i i

,

QUESTION: 096 (1.00)

Given the following conditions:

,

Instrument air pressure is decreasing.

-~

IA-V-26 is shut, isolating the turbine and intermediate

--

'

building headers.

--

A controlled shutdown of the unit is possible with air j

supplied to critical components.

,

What systems provide this air during a loss of instrument air?

l l

a.

The service air system and the two hour back-up bottled air system.

b.

The instrument air system and the portable air system.

'

c.

The portable air system and the service air system.

d.

The back-up instrument air system and the two hour back-up bottled air system.

,

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.

.

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SENIOR : REACTOR OPERATOR Page 55

,

1 QUESTION: 097 (1.00)

J

When feeding a " dry OTSG", why is it desirable to use Main Feedwater?

'

Main Feedwater:

a.

sprays directly on the OTSG tubes.

,

b.

is of higher qualityithan Emergency Feedwater,

,

c.

results in less thermal stress on the OTSG tubes,

!

d.

provides better level control than EFW.

i

%

QUESTION: 098 (1.00)

'

Given the following conditions:

The plant is in cold shutdown.

'

--

--

Refueling operations are in progress.

{

Following the insertion of a fuel assembly into the core, count rate exceeds 2 times base line count.

Select the required operator action.

a.

Withdraw the fuel assembly from the core and place the main

,

bridge over the transfer ca,nal.

b.

Disengage the fuel assembly, leaving it in the core, and-position the main. bridge over the transfer canal.

c.

Disengage the fuel assembly, leaving it in the core, and evacuate the reactor building.

,

d.

Stop fuel handling, leave the fuel assembly engaged, and have

,

the Fuel Handling Supervisor and Core Load Engineer evaluate.

'

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.

- SENIOR REACTOR OPERATOR Page 56 l

l

.

QUESTIONi 099 (1.00)

Given the following conditions:

j A loss of off-site power has occurred.

--

Natural Circulation has been established.

.

--

Condenser vacuum is 10 inches of Hg absolute.

I

--

'

It is desired to increase theiamount of natural circulation (cooldown-rate).

Select the operator action required to perform this task.

'

!

-

-The operator should:

increase steam flow by increasing the amount the turbine bypass a.

valves are open.

i b.

increase steam flow by increasing the amount the atmospheric l

dump valves are open.

>

'

c.

decrease OTSG level to 25 inches in the start-up range.

d.

decrease steam flow by decreasing the amount the turbine bypass valves are open.

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I SENIOR REACTOR' OPERATOR Page 57

,

QUESTION: 100 (1.00)

Given the following conditions:

,

Plant initially at 100% power.

--

Then 4 and 8 230 KV Buses drop to 0 volts.

--

,

Breaker status for main generator breakers shows amber.and

--

green lights.

EG-Y-1B energizes the 1E 4160 Bus.

--

Which of the following actions will NOT occur?

a.

A reactor trip.

b.

DC oil lift pumps start for RCPs.

Turbine bypass valves will control OTSG pressure at 1010 psig.

c.

d.

Screenhouse and circulating water house diesel fire pumps start.

i i

,

. ;

.

.

,

b

,

,

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(********** END OF EXAMINATION **********)

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i ANSWER:

001 (1.00)

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b.

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REFERENCE:

i 10CFR20.1208, Dose to embryo / fetus"

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GET/ Radiological, III.F.02.01

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[2.8/3.4]

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Administrative Procedure 1038, " Fire Protection Program", Section 4.10.2, Lesson Objective, V.A.10.08

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REFERENCE:

'I-Procedure 6610-ADM-4110.09, Step 4.3.1,

" Reactor Building Entry"

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[3.3/3.5]

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i Administrative Procedure 1001G, " Procedure Utilization", Step 4.6.4 l

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t Admin Proc. 1029, Step 4.7,

" Conduct of Operations"

L.O. V.A.10.08

{2.5/3.4]

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l Admin Proc 1029, " Conduct of Operations", Steps 4.2.8 & 4.2.9 L.O.

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REFERENCE:

Admin Proc. 1002, " Rules for the Protection of Employees Working on i

Electrical and Mechanical Apparatus," Step 4.1.7.b

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REFERENCE:

EPIP-TMI

.09, Step 5.2.1,

"In-plant Radiological Controls During

,

Emergencies."

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Task No. 5001045013

{3.1/4.4]

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TMI Operations Plant Manual # 3, Section F-3, page 116, Step 3.A

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Operating Procedure 1105-9, " Control Rod Drive System", Step 3.4.3

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Emergency Procedure 1202-08, "CRD Equipment Failures,...", Step 3.A.5

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REFERENCE:

Operations Plant Manual, #3, F-1, page 64, D.

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IV.E.13.22

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L.O. V.E.04.06

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000 Need to contact facility on ATWS.

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SENLOR REACTOR OPERATOR Page 67 REFERENCE:

.

Technical Specifications, 3.13, " Secondary Coolant System Activity."

No facility L.O.

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[2.7/3.8)

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Operating Procedure 1104-02, " Makeup and Purification System" Step 2.9 L.O.

V.C.05.01

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REFERENCE:

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Operations Plant Manual, #3, Section F-1, page 64.

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REFERENCE:

Operations Plant Manual, #3, Section F-1, Control Rod Drives, Step IX.

L.O.

IV.E.13.16

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Operations Plant Manual #3, Section F-4, page 42.

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SENFOR REACTOR OPERATOR Page 69 REFERENCE:

Procedure 1210-10," Abnormal Transients Rules, Guides and Graphs", Step 2.8 i

L.O.

III.C.08.03 i

(3.6/3.8]

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Operating Procedure 1104-27, Waste Disposal-Gaseous, Step 3.7.2.2 L.O.

IV.B.08.08

[2.9/3.4]

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Operations Plant Manual #1, Section A-1, page 31 L.O.

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Operations Plant Manual #4, Section I-1, page 14 (I).

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REFERENCE:

Operations Plant Manual #3, Section F-3, page 46.

-L.O.

IV.E.27.28-l t

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Operating Procedure 1104-38, page 7, Step 3.2

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IV.A.17.07

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Operations Plant Manual # 1, Section B-5, page 29.

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REFERENCE:

Abnormal Transient Procedure, 1210-6, Step 2.22.

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V.E.06.07

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TMI-OPM, F-7, Radiation Monitoring System, Rev.

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Page 73

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REFERENCE:

l Operating Procedure 1105-10, " Plant' Computer. Operations", Step 6.2.8 f

L.O.

IV.E.23.02

[4.3/4.4]

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REFERENCE:

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Page 75

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Abnormal Transients Rules, Guides and Graphs, 1210-10, page 4.

L.O. V.E.10.08

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Operations Plant Manual, Section F-3, page 57 and 58.

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SEN)bR REACTOR OPERATOR Page 77 REFERENCE:

Operations Plant Manual #3, Section F-3, page 173.

L.O.

IV.E.27.62

[3.4/3.7]

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REFERENCE:

Emergency procedure, 1202-29, Section A, page 3.

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V.D.11.03

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REFERENCE:

Operating Procedure, 1103-5, page 10, step 6.

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IV.A.01.07

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ANSWER:

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REFERENCE:

Refueling procedure 1505-1, page 8, step 5.3.12.

L.O.

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( * * * * * * * * * * E!JD OF EXAMINATION **********)

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O ATTACHMENT 2 SIMULATION FACILITY REPORT Facility Licensee:

Three Mile Island, Unit 1 Facility Docket No.:

50-289 Operating Tests Administered On: August 31 and September 1,1993 This report is used only to report observations. These observations do not constitute audit or inspection findings and are not, without further verification and review, indicative of non-cc,mpliance with 10 CFR 55.45 (b). These observations do not affect NRC certification or approval of the simulation facility other than provide information which may be used in future evaluations. No licensee action is required in response to thew observations.

During the conduct of the Job Performance Measures portion of the operating tests, one problem with the simulator was observed which had a minor impact on the conduct of the examination. After the candidates realigned the safety injection sy. stem for piggy back mode of operation, there was no Low Pressure Injection flow indication in the B loop. This was due to a recent design change which cut offlow flow indications, flows less than 600 gpm, to the Low Pressure Injection system flow indicator. Licensee management indicated they would reconsider lowering the cutoff to a value below that which would be expected for piggy back operation.