ML20196B969

Exam Rept 50-002/OLS-88-01 on 880118-21.Exam Results:Three Candidates Passed All Portions of Exams & One Failed Written Exam But Passed Operating Exam.Exam & Answer Keys Encl

ML20196B969
Person / Time
Site:	University of Michigan
Issue date:	02/09/1988
From:	Burdick T, Hare E, Dave Hills, Keeton J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20196B922	List: ML20196B916 ML20196B969
References
50-002-OL-88-01, 50-2-OL-88-1, NUDOCS 8802120208
Download: ML20196B969 (93)

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U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-002/0LS-88-01(0RS)

Docket No.50-002 License No. R-28 Licensee: University of Michigan Phoenix Memorial Laboratory Ann Arbor, MI 48105 Facility Name:

Ford Nuclear Reactor Examination Administered At: University of Michigan, Ford Nuclear Reactor Examination Conducted: January 19-21, 1988 Examiners:

E. A. Hare bh b MLAO._

O Date M

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D. E. Hills 7-/f ///

Date

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/,t 68 9 Approved By:

. Burdick, Chief Operating Licensing Section Date/

r Examination Summary Examinations were administered on January 18-21,1988 (Report No. 50-002/0LS-88-01(DRS)). One Senior Reactor Operator and three Reactor Operator candidates were administered written and operating t

examinations.

Results: Three Reactor Operator candidates passed all portions of the examinations. One Senior Reactor Operator failed the written exam and passed the operating examination.

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ADOCK 05000002 PDR i

P REPORT DETAILS 1.

Examiners E.-A. Hare, Chief Examiner J. M.'Keeton, Examiner D. E. Hills, Examiner 2.

Exit Meeting On January 21, 1988, at the conclusion of the examination. A meeting was held to discuss generic findings made during the course of the examination.

The following personnel attended the meeting.

Facility Representatives R. Burn, Reactor Manager G. Cook, Assistant Reactor Manager NRC Representative E. Hare The following item was discussed during this meeting:

Two instances of out-of-date material were noted. The licensee was told to ensure that up-to-date material for exam preparation is sent for future examinations.

There were'no generic concerns identified during the examinations.

3.

Examination Review Refer to Attachment.

Attachment:

Facility Comments and Resolutions 2

ATTACHMENT University of Michigan Ford Nuclear Reactor Reactor Operator and Senior Operator Examinations January 19, 1988 Facility Comments and NRC Resolutions Question A.07 Facility Comment:

In a real prompt critical reactor, the value for_ reactivity must be beta

.plus.0001.

If beta were.007 as was used in some of the questions, reactivity would be.0071, not.0001 as in the solution.

The confusion here comes from the context of my text, INTRODUCTION TO NUCLEAR REACTOR OPERATIONS. On Page 4-7, I used the example of a hypothetical reactor that had only prompt neutrons.

The purpose of the example was to show that a reactor with only prompt neutrons would be uncontrollable. On Page 4-22, an example of a real reactor with both prompt and delayed neutrons is used. We expect that an operator would answer this question by saying, if K=1.0001, the reactor is not prompt critical.

If a calculation were performed, an operator might use reactivity of.0001 or

.0071 as he or she tried to interpret your wording of the question. We feel credit should be given for use of reactivity equal to.0001 or.0071,

-at that.0071 is more correct for a real reactor.

NRC Resolution:

Comment noted. The question was stated as a means of evaluating the candidates' ability to determine the correct calculational method and to execute those calculations.

Any correct assumption would be equally acceptable if so stated.

The answer key was not changed.

4 Question B.04 Facility Comment:

The question should have asked for three types of of experimental facilities.

The way it was worded, the most logical answer would be:

P-tube, in-core, and experimental grid, because that is the way we complete the experiment location section on our reactor utilization requests.

Beamport might not have been included as an answer if the other three were selected.

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NRC Resolution:

Comment noted. The answer key was changed to accept "experimental grid" as an additional correct response and to show that any three of the four were acceptable for full credit.

Question 8.09 Facility Comment:

(a) Y panel is a very specific acronym for the emergency supply or emergency load panel which should also be given credit as correct.

The panel is referred to as the Y panel because emergency loads, symbolically at the base of the Y, can be fed by normal power through one arm of the Y or by the emergency generator through the other arm.

(b) It was not clear whether you wanted the test start position to initiate the engine start sequence when starting the engine during a manual test or whether you wanted the normal position for an automatic start sequence initiated in the event of power failure.

NRC Resolution:

Comment noted.

The answer key was changed to include "Emergency load or supply panel" as alternate correct responses for Part a.

Part b was deleted because of possible confusion and the point value of the question was changed on the exam.

Question C.02 Facility Comment:

The values in our Systems Descriptions book are nominal and sometimes historical estimates.

Based on our most recent operating experience, we might expect these current correct answers to be out of the range in your answer key.

(b) Current hot demineralizer flow is closer to 20 gpm than the nominal 25 gpm.

(d) Current evaporation and leakage rates are closer to 200-250 gpd r

rather than the nominal 150 gpd.

Operators may have answered with Systems Descriptions values or recent operational values.

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NRC Resolution:

Comment noted. The answer was changed to accept 20 to 25 gpm with no additional tolerance in Part b.,

and 150 to 250 gpm with no additional tolerance in Part d.

Question D.07 Facility Comment:

The answer with our modified automatic control system is:

The reactor would remain in automatic control.

If the control rod were at the upper limit, power would continue to drift down due to xenon buildup, fuel burnup, or because of the negative reactivity that had made it decline to -5% initially. Without operator action, the reactor would eventually shutdown completely.

If the control rod were not at the upper limit, it would respond normally to being below the setpoint, withdraw automatically, and restore power to the setpoint level.

NRC Resolution:

Comment noted. The response you have stated above was accepted as the correct answer.

The answer key was changed.

Please update your training material to reflect this.

Question F.02 Facility Comment:

The answer key lists only the specific room numbers.

Few of us memorize room numbers. A sketch or verbal description should be given credit.

Room 2074 is also called the coffee room, the lunch room, and the cafeteria.

Room 3073 is generally called the third floor fan room.

NRC Resolution:

Comment noted. Any correct description of the room is equally acceptable for full credit.

The answer key was changed to include room descriptions. ~

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^ Question H.03 h

facility Comment:

(b) Reactivity coefficient values are nominal values listed in our Systems Descriptions. They are not in Technical Specifications.

Leeway should be given in the answer because the values are nominal.

and because they vary significantly with core condition and fuel

-loading.

Temp Coefficient

- 3.0 to 10.0 X 10 3 %

Void Coefficient

- 0.5 to 2.0%

The answer for void coefficient may also have been given in %

reactivity per ce rather than per % core volume as published.

One percent core volume is about 1800 cc.

NRC Resolution:

Comment noted. A tolerance of 120% was added to the answers.

Reference to FNR Technical Specifications has been removed. Your values above were not substantiated by the supporting documentation.

Question H.07 Facility Comment:

In a real prompt critical reactor, the value for reactivity must be beta plus - 0001.

If beta were.007 as was used in some of the questions, reactivity would be.0071, not.0001 as in the solution. The confusion here comes from the context of my text, INTRODUCTION TO NUCLEAR REACTOR OPERATIONS. On Page 4-7, I used the example of a hypothetical reactor-that had only prompt neutrons. The purpose of the example was to show that a reactor with only prompt neutrons would be uncontrollable. On Page 4-22, an example of a real reactor with both prompt and delayed neutrons is used. We expect that an operator would answer this question by saying, if K=1.0001, the reactor is not prompt critical.

If a calculation were performed, an operator might use reactivity of.0001 or

.0071 as he or she tried to interpret your wording of the question. We feel credit should be given for use of reactivity equal to.0001 or.0071, but that.0071 is more correct for a real reactor.

NRC Resolution:

Comment noted.

The question was stated as a means of evaluating the candidates' ability to determine the correct calculational method and to i

execute those calculations. Any correct assumption would be equally acceptable if so stated. The answer key was not changed.

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r Question H.08 Facility Comment:

Two minutes after shutdown, a large number of prompt neutrons from fission are still being produced.

Delayed neutrons with half lives less than that of bromine-87 are still being produced.

Neutrons in large numbers are sent into the core from our heavy water tank and installed neutron source.

NRC Resolution:

Comment not accepted. The candidate was told to consider only neutrons from decay (no free neutrons) to answer the question when he asked for clarification of the intent of the question. 'We do not disagree that neutrons are continuing to be produced; however, 2 minutes _after SCRAM from full power, 87 Br is the major daughter product remaining from the full power fission process. The answer key was not changed.

The facility did not comment on the identical RO Question A.2.

Question H.11:

Facility comment:

We have no measurable Doppler effect. Doppler results primarily because of large temperature gradients across fuel pins and the high density of U238 in power reactors. Our temperature rise across a fuel plate is i

about one-fourth of a degree. Our maximum fuel temperature is only about 150 F.

In addition, while we are low enriched, we still have twenty percent U235 and the dominant atoms in our fuel plates are not U238, but aluminum because our fuel is so lightly loaded with uranium isotopes. The U238 is so diffuse throughout the fuel that Doppler is negligible.

Doppler only exists because the U238 in power reactor fuel is so densely packed. The entire rod is uranium oxide; most of the uranium in the oxide is U238.

That is not our case.

We do not teach Doppler to our reactor operators. Would you please not ask questions about Doppler because they truly to no apply to us.

NRC Resolution:

Comment noted.

The question is theoretical in nature more so than plant specific. The question was deleted. We will refrain from asking questions on Doppler effect in the future. The facility did not comment on the identical RO Question A 04.

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Question I.05 r.-

Facility Comment:

The reactor _ operators do not perform pool water analyses. Mr. Birdsall probably knew the answer to this question because he runs-our counting room and his equipment is used for the analysis.

The ordinary operator would not know the answer to this question. We do not reqatre our operators to memorize the Health Physics manual from which the question was extracted. We request that this question be deleted.

NRC Resolution:

Comment not accepted.

The intent of the question was to test the candidates understanding of why the analysis is done.

It did not required any memorization of procedural steps. The question was not deleted.

Question I.09 Facility Comment:

Both of the parts to this question were extracted from the Health Physics Manual. We do not require our operators to memorize radiation levels from radioactive storage drums. Our facility Health Physicist performs this function. We request that this question be deleted.

NRC Resolution:

Comment noted.

The question was deleted and point values were changed.

Question I.12

. Facility Comment:

(a) Some leeway should be given in the half-lives of nitrogen-16 (a few seconds), argon-41 (a few hours), and tritium (long, years). The exact values are unimportant.

(b) The only gas used in our pneumatic tube system is air, NRC Resolution:

Comment noted. Part a of the answer key gave a tolerance of 50% of actual half-life. The answer was not changed.

Part b of the answer key was changed to identify air as the gas used.

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Question J.06 Facility Comment:

.(a) Primary flow with our 11ew pump is closer to 1100 gpm.

(b) ' Core differential temperature at increased-flow is 13.2 to 14.0 F.

NRC Resolution:

Comment noted.

The tolerance of 10% on 1000 gpm takes into account 1100 gpm as a correct answer.

Part a of the answer key was not changed.

Part b of the answer key was changed to 13.2 to 14.0'F.

The facility did not send any supporting documentation.

Question J.07 Facility Comment:

Question should end:

. greater hydrostatic head than the primary coolant.

-(a) How is the differencial hydrostatic head between the primary and secondary coolant physically determined for the secondary coolant.

If this clarification is not made, the head of the secondary coolant is the height of water between the heat exchanger and the secondary sump in the cooling tower.

NRC Resolution:

Comment accepted. The question was taken directly from the facility supplied reference material.

The reference does not differentiate between primary and secondary coolant.

However, due to the way the question was asked, the above answer could also be correct.

The answer key was changed to accept either answer. We would like you to consider changing your system description to help clarify the hydrostatic head.

It only discusses secondary coolant hydrostatic head.

I Question K.07 Facility Comment:

The answer with our modified automatic cuntrol system is:

The reactor would remain in automatic control.

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If the control rod were at the upper limit, power would continue to drift down due to xenon butidup, fuel burnup, or because of the negative reactivity that had made it decline to -5% initially. Without operator action, the reactor would eventually shutdown completely.

If the control rod were not at the upper limit, it would respond normally to being below the setpoint, withdraw automatically, and restore power to the setpoint level.

NRC Resolution:

Comment noted. The response you have stated above was accepted as the correct answer. The answer key was changed.

Please update your training material to reflect this.

Question L.07 Facility Comment:

(a) Operating rule is within 10% which for our 24 inch rods is 2.4 inches.

NRC Resolution:

Comment accepted. Although the comment is not supported by documentation the recommended answer is within an acceptable tolerance of 5%. The answer key was changed to allow this tolerance.

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ADDITIONAL CHANGES r

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.Following administration of the examinations and more indepth review of the facility material, the NRC has taken the initiative to make.these additional changes to the written examinations:

Question A.04 Question was deleted to be consistent with Question H.11 being deleted on SRO exam.

Answer C.09(b)

The facility has recently installed a new primary pump that has increased the

. primary flow rate from about 960 gpm to about 1100 gpm.

The answer key was changed'to accept flow in the range of 900-1150 gpm.

Answer D.03(b)

A new radiation recorder has been installed in the control room. The new recorder alarms at actual setpoints vs % of scale on the older recorder.

l The answer key was changed to accept either answer, Answer I.12(b)

Added "maintain tritium content'below 50 curies" to the answer key as an additional correct answer.

Answer J.06(e)

Added "0.1 micrmhos (+/- 20%) for demineralizer outlet conductivity" to the answer key as an alternative answer.

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S. NUCLEAR REGULATORY COMMISSION j

REACTDR DPERATOR LICENSE EXAMINATION

.i FACILITY:

_UNJygRgjTy_pf_MIgMIgAN__

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I REACTDR TYPE:

_TggI____________________

DATE ADMINISTERED _gef91fl9________________

_KggTQN _yz_M ___________

EXAMINER:

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CANDIDATE:

10!IB99II905_I9_90N9199IE1 Use separate paper for the answers.

Write answers on one side only.

Staple question sheet on top of the answer sheets.

Points for each question are indicated in parentheses after the question.

The passing grade requires at l east 70% in each category.

Examination papers will be picked up six (6) hours after the examination starts.

% OF CATEGORY

% OF CANDIDATE'S CATEGORY

__Y0695_ _I9106

___5G96E___

_YebyE__ ______________GQIggg6y_____________

E2.00

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________ A.

PRINCIPLES OF REACTOR OPERATION

/,50

_4{=z29__ _1Ez99

________ B.

FEATURES OF FACILITY DESIGN

_1EzE9__ _1EzE9

________ C.

GENERAL OPERATING CHARACTERISTICS

_19z99__

19199

________ D.

INSTRUMENTS AND CONTROLS

_19z99__ _19299

________ E.

SAFETY AND EMERGENCY SYSTEMS

_19199 _ _19199

________ F.

STANDARD AND EMERGENCY OPERATING PROCEDURES

_1Ez99__ _1Ez99

________ G.

RADIATION CONTROL AND SAFETY l

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Final GF Abi i

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AII work dene on this examination is my own.

I have neither given nor received aid.

I Candidate's Signature

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NRC RULES AND GUIDELINES FDR LICENSE EXAMINATIONS During the administration of this examination the f ollowing rules apply 1.

Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2.

Restroom trips are to be limited and only one candidate at a time may leave.

You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

3.

Use black ink or dark pencil gnly to f acilitate legible reproductions.

4.

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

5.

Fill in the date on the cover sheet of the examination (if necessary).

6.

Use only the paper provided for answers.

7.

Print your name in the upper right-hand corner of the first page of each section of the answer sheet.

8.

Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write gnly gn gne side of the paper, and write "Last Page" on the last answer sheet.

9.

Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

12. Lise abbreviations onl y if they are commonly used in facility litetatute.

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may beggi ven.

Therefore, ANSWER ALL PARTS OF THE I

QUESTION AND DO NOT LEAV2 ANY ANSWER BLANK.

16. If parts of the examination i not clear as to intent, ask questi ons of the examinet only.

17. You must sign the statemen6 on i t cover sheet that indicates that the work i s your own and you v o...

received or been given assistance in completing the examination Th-. must be done after the examination has been completed.

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18. When you complete your examination, you shall a.

Assemble your examination as f ollows:

(1)

Exam questions on top.

(2)

Exam aids - figures, tables, etc.

(3)

Answer pages including figures which are part of the answer.

b.,

Turn in your copy of the examination and all pages used to answer the examination questions.

c.

Turn in all scrap paper and the balance of the paper that you did not use f or answering tee questions, d.

Leave the examination area, as defined by the examiner.

If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.

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QUESTION A.01 (2.00)

STATE the REASDN the neutron flux increases rapidly and then settles into the stable period when positive reactivity is added to make the reactor supercritical.

QUESTION A.02 (1.50)

Two minutes af ter a scram f rom power, a l arge number of neutrons are still present in the core.

DISCUSS the reason and IDENTIFY the source (s) of these neutrons.

(Be specific.)

DUESTION A.03 (2.00)

In each of the f ollowing cases:

STATE which of the TWO choicen is the pref erred characteristic for a moderator and briefly EXPLAIN why that characteristic is preferred.

a.

Absorbs neutrons - or - scatters neutrons?

b.

Have a high atomic weight - or - low atomic weight?

QUESTION A.04 12.50; -

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STATE er/ i;.e real i.J.per:turr en=334ei-at 5:cen.ee 12..

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GUESTION A.OS (1.00)

Fill in the Blanks.

a.

The equilibrium concentration f or Xe is reached after about i

hours of steady state operation.

b.

Whenever a reactor is shut down, Xe rapidly builds up, reaching a peak after about _________ hours.

(s****

CATEGORY A CONTINUED ON NEXT PAGE *ssss)

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QUESTION A.06 (1.00)

DEFINE Shutdown Margin.

QUESTION A.07 (2.50)

CALCULATE the reactor period for the given conditions:

(Assume that Beff =.007 and show all work.)

c.

Keff = 1.0001 for a prompt critical reactor.

b.

Keff = 1.0001 for a delayed critical reactor.

QUESTION A.OB (2.00) o.

EXPLAIN what is meant by the term "delayed neutron fraction."

b.

Does the value of the delayed neutron f raction change over core life? EXPLAIN your answer.

teases END D CATEG RY

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t' 09EST!DN B.01 (2.00)

Fill in the Blanks a

Irradiated fuel elements must be stored in a geometric array whi ch assures ___ (a) ___ and which permits sufficient natural convection cooling by ___ (b).__ or. _(c).__ such that element temperature will not exceed. _(d) ___.

QUESTION B.02 (1.50)

With regards to the heavy water tanks a.

STATE the purpose.

(0.5) b.

STATE the reason that contaminated water ik periodically removed and STATE the LIMIT.

(1.0)

QUESTION B.03 (2.00)

TRUE or FALSE a.

Two ion Chambers are located along the perimeter of and above the core in posi tions L-9 and L-79.

b.

The surface of the pool is kept clean by two skimmers and a sand fil ter.

c.

When the reactor is operating in the f orced circulation mode, water flows up through the 63 holes drilled diagonally between the f uel element holes.

d.

The three shim saf ety rods are stainless steel containing 1.5% enriched boron.

GUESTION B.04 (1.50)

FNR has THREE Experimental Facilities available during high power operation.

LIST all THREE.

(esses CATEGORY B CONTINUED ON NEXT PAGE sesss)

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DUESTIDN 5.05 (1.50)

STATE the purpose of the holdown mechanisms and DESCRIBE the event that could occur without the holdown.

QUESTION B.06 (1.00)

ETATE the f unction of the "water lock system."

QUESTION B.07 (2.00)

STATE TWO f unctions provided by the steam line in the secondary heat exchanger.

QUCSTION B.OB (2.50) i According to the FNR Systems Description, the highly demineralized water in the pool serves FIVE functions.

STATE those FIVE functions.

o.s' QUESTION B.09 W

Fill in the Blanks.

When doing a System Load test of the emergency generator, as soon as the engine starts and is running at the prescribed rate, all emergency (a) _____ panel loads transfer to the generator.

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QUESTION C.01

({.50)

STATE TWO reasons f or adding sulf uric acid to the secondary system and the OPTIMUM control band you are trying to achieve.

QUESTION

'C.02 (3.00)

STATE tne typical values of the following parameters at 2MW power operation.

a.

Core exit t emp?r at ure b.

Hot demineralizer. flow c.

Pool level d.

Normal Primary systdm loss due to evaporation and leakage (daily) e.

Volume of city water makeup to Secondary system (daily) f.

Secondary flow rate GUESTION C.03 (1.00) a.

STATE the MAXIMUM position difference allowable for shim rods during reactor startup.

b.

WHEN can this requirement be waived?

QUESTION C.04 (1.50)

To determine excess core reactivity (OP-221), the reactor is started up and power is increased to the shim range between 1 kW and 20 kW.

6.

STFSE the reason that MINIMUM power must be at least 5 times gamma background.

(0.5) b.

STATE TWO reasons WHY MAXIMUM power is limited to 20 kW.

(1.0)

(*****

CATEGORY C CONTINUED ON NEXT PAGE

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I QUESTION C.05 (1.50)

Fill in the Blanks:

Normal l y, nitrogen is supplied f rom th? liquid nitrogen tana through.an 80 psig pressure regulator and a ____(a) psig pressure regulator, which supplies the ____(b) ____ psig pressure regulator on the header.

If nitrogen pressure from the liquid nitrogen tank f alls below ____ c) ____ psig, the four

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backup nitrogen bottles will maintain header pressure.

QUESTION C.06 (1.00)

The reactor must be shut down prior to performing a heavy water transfer.

STATE the maximum Kef f allowable prior to transfer.

QUESTION C.07 (1.50)

During operation at full power, a leak develops in Beamport B that results in draining the port.

STATE whether you would expect to see any indication in the control room and STATE WHY or WHY NOT and WHERE.

l QUESTION C.OB (1.50) a.

STATE the U235 burnup rate in g/ day at a power level of 2 MW.

(0.5) b.

At WHAT % burnup are the f ollowing f uel elements retired?

1.

Standard I

Control (1.0) l l

l QUEST 1DN C.09 (1.00) l o.

CTATE the MAXIMUM allowable power level WITHOUT primary flow.

b.

STATE the typical flow rate f or full power operation.

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~ CATEGORY C ("'s "U" ll," [T' L[y' fe.N p

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PAGE B

D___INSIBydENIg_9NQ_CQNIBQLg QUESTION D.01 (1.00)

STATE the number and location of the conductivity cells in the primary system.

QUESTION D.02 (2.00)

STATE the conditions and setpoints that will cause the "control rod limit" alarm.

QUESTION D.03 (2.50)

With reguards to the Control Consol e, STATE the cause(s) of the f ollowing alarms:

(Be Specific) a.

The Safety Amplifier Trouble (SAT) alarm.

(0.5) b.

The High Radiation recorder alarm.

(0.5) c.

The stack alarm. (Three sources)

(1.5)

DUESTION D.04 (2.00)

EXPLAIN HOW the follow.1g differential temperatures are determined and WHERE they are sensed:

a.

Core differential temperature b.

Secondary differential temperature QUESTION D.05 (2.00)

LIST FOUR of the five alarms that annunciate on the "cubicle annunciator panel."

QUESTION D.06 (1.00)

DESCRIBE the f unctions of the TWO inhibit switches associated with the Period Recorder.

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re-(*****

CATEGORY D k

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i "m

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(

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n Dz__INgIB_UDENI)_$Np_gQNIBpbS PAGE 9

fy ?

t 6

4 [g f,,, //4*

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QUESTION D.07 (1.00) hereacgr is operating in automatic control, STATE t4EM+-e-Jdt-+t

_r%f M ":__ - M 'ithd t:1 i: p-r /

ted i f the setpoint potentiometer is lost and the -5% dropout fails.

QUESTJON D.08 (1.00)

You are at the console with the reactor shutdown when you notice a GREEN Beamport status light come ON.

WHAT does thi s mean?

QUEET10N D.09 (1.50)

STATE the difference between an uncompensated ion chamber and a compensated ion chamber.

I i

f l

(*****

END OF CATEGORY D

• • • • • )

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r; PAGE 10 Ez__fBFEIy_9ND_[DEBgENCy_gy!IED)

QUESTION E.01 (2.00) a.

EXPLAIN the function of the Holdup Tank.

b.

STATE TWO scram f unctions associated with the Holdup Tank.

QUESTION E.02 (2.50)

LIST FIVE systems or major components that can be supplied by the Emergency Generator.

QUESTION E.03 (1.00)

STATE the Emergency Pool Fill water source and HOW much it is capable of providing.

DUESTION E.04 (2.00)

During full power operation primary flow decreases below the setpoint.

DESCRIBE the sequence of events that will occur at the Header and Hopper.

DUESTION E.05 (2.00)

EXPLAIN the difference between a "slow" and a "fast" scram.

QUESTION E.06 (1.00)

DESCRIBE the DESIGN FEATURE that prevents leakage of primary coolant to the secondary coolant if a tube leak develops in the Heat Exchanger and STATE HOW it is accomplished.

QUESTION E.07 (2.00)

LIST FOUR interlock circuits that prevent moving the bridge when the reactor is at full power.

g s ts. s f:-

a n

y a w t t w %. u n: y D ON niE XT P AGE * * * * * ),

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(*****

CATEGORY E a

Ez__f9EEIY_9NQ_gDEBgENQY_gyglgME PAGE 11 QUESTIDN E.08 (1.50)

The reactor safety system consists of Channel s A, B,

and C.

IDENTIFY the type of detector and scram setpoint for each channel.

I I

t l

l f

1 ENDOF,C}TEGRYE.*****)

(*****

4,

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Er E_ _ _ sIeNp3Bp_ gNp_ E DE B@E Ng Y_ DfE SSIJ Up_ f 8pg E ppBE @

PAGE 12 QUESTION F.01 (2.50)

You are the Control Room Operator.

An event has occurred that requires IMMEDIATE Building Evacuation.

STATE the FIVE actions you are required to take to "secure the reactor" prior to leaving the the Control Room according to OP-101, "Reactor Building Emergency."

QUESTION F.02 (1.00)

When restoring systems to normal f oll owing a power interruption if the Phoenix Laboratory stack system exhaust fans have tripped, the circuit breakers must be "started" and the mercury switches reset.

STATE the room (s) where these breakers and switches are located.

QUESTION F.03 (2.00)

A power failure occurs that lasts for longer than los, STATE WHY it is necessary to open the main control system isolation breaker and individual control systems isolation switches according to OP-108, "Building Power Failure."

QUESTION F.04 (2.00)

When operating the Cooling Tower Fans during cold weather in accordance with OP-304, "Cooling Tower Fan Operation Procedure":

a.

HOW long must you wait before starting the fan in reverse and WHY?

b.

STATE TWO possible consequences of not taking this precaution.

(*****

CATEGORY F CONTINUED ON NEXT PAGE *****)

j.

A

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l '..

l'

< is '

L :. c

)

[

b

3.

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3 I:

Ex__EIOND9BD_9ND_EDEBEENGY_DEEB911ND_EBDGEDVBEE PAGE 13 l

QUESTIDN F.05 (2.50)

You are performing Fission Chamber Response Checks in accordance with DP-110 a.

The fission chamber is positioned to read 1000 on the count rate recorder, withdrawn 2%, and returned to i ts original position.

DESCRIBE the indication you expect to see on the recorder and STATE the SIGNIFICANCE of the indication.

(1.5) b.

The fission chamber is then withdrawn to its upper limit and reposi tioned to read 1000 cps.

EXPLAIN WHY this is necessary if the previous step proved detector operability.

(1.0)

QUESTION F.06 (1.50)

LIST THREE scram interlocks that may be bypassed according to OP-111, "Defeating Reactor Interlock Scrams."

DUESTION F.07 (2.50) l Answer the f ollowing questions regarding the Startup Procedure OP-102:

l a.

STATE TWO actions that must be taken if the Log-N channel starts acting erratic.

(1.0) b.

STATE TWD actions that must be taken if the reactor goes critical with the shim rods below the shim range.

(1.0) c.

WHO is responsible f or directing reactor startup?

(0.5) l l

1 l

(*****

END F C,ATEpORY,F, * * * * * )

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Ez__B9919IIDW_E96IB96.0Np_f9EEIY PAGE 14 DUESTION G.01 (2.00) a.

STATE the quarterly occupational dose limi t f or whole body, hands and f eet, and skin of the whole body.

(1.5) b.

STATE the dose limit for individuals under the age of 18.

(0.5)

QUESTION G.02 (1.50)

STATE the type of monitor it is and WHAT it detects for each of the f ollowing of radiation monitors:

a.

Mobile air particulate monitors b.

NMC c.

Gaseous activity detector i

l DUESTION G.03 (1.00)

The beamporte at FRN are equipped with plugs.

STATE the TWO f unctions that they serve.

QUESTION G.04 (1.50)

A material decays at a rate of 40 percent per day.

CALCULATE the hal f-li f e.

Show all work.

QUESTION G.05 (2.00) l During reactor operation, Argon 41 is produced, s.

S? ATE the source, half-life, and decay mode.

1 I

b.

WHERE is it produced?

l l

(*****

CATEGORY G CONTINUED DN NEXT PAGE

• • • • • )

l l

PAGE 15 Ez__B9919IlpN_GQUI6QL_gND_ggEgIY DUESTION G.06 (2.00)

Does the biological effect of 100 rem depend on whether it is a neutron or a gamma done?

EXPLAIN your answer.

QUESTION G.07 (1.50)

While working in an area marked "Caution, Radiation Area," an operator discovers his dosimeter is off-scale and leaves the area.

Assuming he had been working in the area for 45 minutes, DETERMINE the MAXIMUM dose he would have received.

(Show all work and state any assumption you have made.)

QUESTION G.OB (2.00)

STATE FOUR automatic actions that will occtn if the building exhaust NMC radiation moni tor reaches i ts al arm setpoint.

QUESTION G.09 (1.50) l The f ollowing questions are in regards to the FNR-PML Tour Exposure Guidelines.

a.

Fill in the blanks:

The time spent by a tour at the pool rail will be limited to approx i mat el y _____ (1 ) _____ minutes.

When away from the pool rail, an additional _____ 2) _____ minutes may be

(

spent on the pool floor.

(1.0) l b.

STATE the type (s) of radiation area (s) tours are not permitted.

l (0,5) i l

l l

l

(*****

END OF CATEGORY G

• • • • • )

t p 4 C..,,p_4t*,4,*qt******y XQMINATION l

(*************

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Page 1 Gt 9 Dele _ststi BE6CISB_ItEQBY.E08tKL85:

(t)

P=Pe P = P 10 o

0 EI V

th SUR = 26.06/v P = -------- g f i ssi ons/sec 3.12 x to

= 1* + WIII--

2

-(B Lg)

P p

th 2

2 v

1+

v 1+

(B L

th

~I

-(B L

)

P, = e f

P = -----

K p,,-[N3[I,,,3/SI, AP = In IbOf1--

initial

~@

eff C

(1-Keff!) =C (1-Keff2)

Ap T = - - - - - - - -

1 2

1 C

l' bbOfb--

T = --

m = ---

=

1-K Cinitial 1 of 1 op AL 2 + oL 2

2 (-

g o

=

- -- + - -- - B T

f at p at at at l

if~~~~

f 71 P

=P e ( P, p Pg 3

K,,,

l O *eu P 1

Page 2 of 3 Jg PeIe_Etfggy IBE BOQQXNed1C E _eN D _ELU12_t!EC 60 NIC S _EQBOUL OS :

E = & ah 2 w LAT G = -----------------------

1 In R /R in g/R2 2

3

,0=UA (AT )

- + -------- + --------

K K

K 2

3 6=Ec (AT) p h = or 4 A R4 n=

!O "t

n = - !O---

"t ) CEt!--

O G

(h

-h Q

(h

-hg ) ideal in ih actual 1 1 22 W

T T

supplied 1

2 A = pAv pAV

=pAv 3 3 3 222 3

$e KA J4.P p 5

= KA E = KA ST M = KA op J AP x

nc Q

E AT (in) - AT (out)

G = -f th AT

= ------------------

AT (in) 8.Bx10 in

(-------->

AT (out)

Gr kAAT T

-T

= ---

Q = -----

c1 ps g

3, total

,Q = gg--- 3g--

AX a

b n

___+_.

+

K K

K a

b n

's P09' 3 O' 8 CEWIBIEUGOL_EUDE_LeWS:

1.&

N (N )

H (N )

P I

1 I

1

..I N

4 (N

H (N

P y

2 2

2 2

2 BeQ1eIl0N_eND CUED 1SIBLEQBdWL95:

R/hr = 6CE/d I

IO*

Uv

=Cv

=

l t 22 0.ill"

~

G = Dilutlen_Batt I=1 C=C O' Vol ume 10

- At A=A e

g, gg n

CQWEBS10NS:

3 62.4 lbm/ft Density of water (20 C) = 62.4 lbm/ft 1 gm/cm n

1 gal = 8.345 lbm 1 ft

= 7.48 gal Avogadro's Number 6.023 x 10

=

1 gal = 3.78 liters Heat of Vapor (H O) = 970 Btu /lbm 2

1 lbm = 454 grams Heat of Fusion (ICE) 144 Btu /lbm

=

~

e = 2.72 1 AMU = 1.66 x 10 grams n = 3.14159 Mass of Neutron = 1.008665 AMU 1 KW = 738 ft-lbf/sec Mass of Proton = 1.007277 ANU 1 KW = 3413 Btu /hr Mass of Electron = 0.000549 AMU 1 HP = 550 f t-lbf /sec One atmosphere = 14.7 psia = 29.92 in. Hg 1 HP =.746 KW

'F = 9/5 *C + 32 l

1 HP = 2545 Btu /hr

'C = 5/9 (*F - 32) 1 Btu = 77B ft-1bf

'R = 'F + 460

-16 1 MEV = 1.54 x 10 Btu

'K = 'C + 273

-21 h = 4.13 x 10 g_,,c 10 1 W = 3.12 x 10 fissions /sec u 32.2 lbm-ft/lbf-sec c

= 931 MEV/ AMU g

1 inch = 2.54 cm C=3x 108,f,,c r = 0.1714 x 10 Btu /hr ft R*

~

I l

1

y c-O___EBINCIP(ES_QE_SEBCIQB QEEB911DN PAGE 16 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J.

M.

ANSWER A.01 (2.00)

There is a prompt jump caused by immediate ef f ects of prompt neutrons. [1.03 A stable period follows which is determined by the amount of reactivity inserted and the delayed neutron generation time. C1.03 REFERENCE Introduction to Nuclear Reactor Operations pg 4-39 ANSWER A.02 (1.50)

The core neutron population is sustained by decay of the longest lived fission product precusor [1.03, bromine-87 C O. 5 3.

REFERENCE Intro, to Nuclear Reactor Operations pg 4-15 ANSWER A.03 (2.00) 1 l

a.

Scatter (0.5), so neutrons are lowered in energy rather than i

lost.

(0.5) b.

Low atomic weight (0.5) so fewer scattering collisions l

are required.

(0.5) i I

l REFERENCE Intro to Nuclear Reactor Operations pg 2-45 Dele ed ANSWER A.04 M 2. 50 3 -

l m.

ss a nuc4eus increases an temperatur e li b a c c.ne, th:- ally l

_ agitated. The ther==1

=n& inn nf

+h=

nerleue maken no"+rens l

oy=r r ng: ci mueryie. ;.c. d cel::itic:)

h=um

+he dentroM j

r=1m+4ue -n=ry/ 2e-ab: rptic-by th-nuwl-u..

' 1. 7) 6.

in general. the f racti nn=1 r=ductina !- ::1 ' sh i gi di r.;

n=r-l

_ The dere=ased at: Of deppler br rad =ni nn done-- "in 1:::

t Si;F t p--=&nre than at in" t==pmenture.

de; er e 4mel n=r

_ terp;reiur = wii.uw-.i highe.- tc.mperatures m unes less a r rer-ea se fn th; r;;cnznr e =n=eny canna 41mv==-- by cente-14_ag_ nuclei R woulu be th: :::: et inw fuel temoeratures.

(1.5)

( AI L-, c.et e crdi ; ecceptable 2e- 'u!! cr:di o. R f

i

{.

p r-r.

Vak YL IN.

l

a.

l..J

( o s

j ez__EBINQ186Ef_Qf_Bg8CIQB_QBgB911pN PAGE 17 ANSWERS -- UNIVERSITY OF MICHIGAN

-BB/01/19-KEETON, J. M.

l l

REFERENCE Intro to Nuclear Reactor Operations pg 6-39 ANSWER A.05 (1.00) a.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

(+/- 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />)

(0.5) b.

6-10 hours (0.5)

REFERENCE Intro To Nuclear Reactor Operations pg 8-9, 8-13 ANSWER A.06 (1.00)

SDM is the amount of negative reactivity that would be added to a core if the rods in a critical, cold, clean reactor were f ully inserted.

(1.0)

REFERENCE Intro to Nuclear Operations pg 6-10 ANSWER A.07 (2.50) p = Keff - 1/ Keff (1.0001 - 1)/ 1.0001

=

= 0.0001 dK/K CO.53 a.

Reactor period T= 1*/p

[0.53 (1 E -4 sec)/1 E -4 dK/K l

=

= 1 second CO.53 l

l l

b.

T=

(Beff - p)/Lp

[0.53

= (0.07 - 0.0001)/ (0.1)(0.0001)

= 690 seconds

[0.53 REFERENCE Intro to Nuclear Reactor Operations pg 4-7, 4-9 1

i l

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j 7:M.

k i

L.24 d (

h

(

]

a g

l l

l

Y ez__EBJNQ1ELES_QE_Bg89IQB_QEEB81]QN PAGE 18 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J.

M.

(

l.

ANSWER A.OB (2.00) a.

The fraction of all neutrons in a given generation which are emitted from the decay of fission fragments at a significant time after the actual fission event.

(1.0) b.

Yes (0.25)

As core exposure increases, the buildup of Pu239 and Pu241 causes the effective Beta fraction to decrease because of their smaller Beta fraction. (0.75)

(Alternate wording is acceptable.)

REFERENCE Intro. to Nuclear Reactor Operation pg 3-7, 3-11 t

5 4

's

,s e,

,f* 4,

s.

'\\ j e

't g

i V 5 /"W a '

Ls y[

t

}

s.

e W.

Sz__EE9IpRgg_QE_E9Q1Lil,Y_pggigN PAGE 19 ANSWERS -- UNIVERSITY OF MICHIGAN

-8B/01/19-KEETON, J.

M.

8 ANSWER B.01 (2.00) c.

suberiticality b.

water (air) c.

air (water) d.

100 degree C (0.5 pts each)

REFERENCE FNR System Description 3.8 ANSWER B 02 (1.50) o.

Provides an enhanced thermal neutron spectrum to the beamports.

(0.5) b.

Keep the tritium activity below the license limit (0.5).

50 Ci (0.5)

REFERENCE FNR Systems Descriptions 3.9 ANSWER B.03 (2.00) a.

False b.

True c.

False d.

False (0.5 pts each)

REFERENCE FNR Systems Descritions 3.1, 3.5, 3.3, 3.4 I

l l

ANSWER B.04

( '.. b O )

1.

Beamports 2.

Pneumatic tube stations 3.

Areas within the core i

an =

_m_

_.,s3 I

4e fjeM5'rM'a.

rid REF b FNR Systems Descriptions 3.1 q en..e

. r.

fr..

f,(. -

)i;i.2 k.'

j \\" ( j,^k\\ d, i to ' N.

b v..+ b n

(

f a

N a

E___EEBIW8EE_gE_E991(IIY_QEE1@N PAGE 20 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J. M.

i ANSWER B.05 (1.50)

The holdown mechanism prevents inadvertent withdrawal of a fuel element [0.53.

The control rod could jam in the element such that both are lifted from the core [0.53 the control element could drop back into the lattice resulting in a sudden positive reactivity insertion and a short period [0.53.

(Alternate wording is acceptable.)

REFERENCE FNR System Description 3.4 ANSWER B.06 (1.00)

Provides a means of transf erring highly radioactive samples, experiments, and reactor fuel from the pool to a shielded hot cave.

(1.0)

REFERENCE FNR Systems Descriptions 3.1 ANSWER B.07 (2.00) 1.

Provides f or heating of primary cool ant. [1.03 2.

Provides steam f or cleaning heat exchanger tubes. [1.03

[

REFERENCE I

FNR Systems Descriptions 5.3.3 i

ANSWER B.OB (2.50) 1.

Radiation shield 2.

Neutron moderator 3.

Neutron reflector 4.

Reactor core coolant 5.

A viewing window for the core (0.5 pts each)

REFERENCE FNR System Descriptions 3.1 p-t W,,f^ i b

i; (

s#

?

PAGE 21 h-EEeIL>BgS_9E_EeG161IY_REE1QN ANSWERS -- UNIVERSITY DF MICHIGAN

-BB/01/19-KEETON, J.

M.

l-ll f

o,Fo ANSWER B.09 (w)

(0.5) (or he'dency Sqfoed wpe

/

a.

"Y"

. n pelefe s.

REFERENCE FNR Operating Procedure, OP-501, Sec. 7.4 L

l l

,!..'s

(*s f *.' /* w s-t f

s%4 il I

j V 'g f"%',g),[ Lf [ %

-.-l a

Gz__9ENEB96_gPgBSIJNg,QH9899IEBJgIJQ)

PAGE 22 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J.

M.

ANSWER C.01 (1.50)

City (or makeup) water has a high pH (9 to 9.5) [0.53, and secondary water must be kept at a lower pH (<7 to keep zinc in solution or to insures Hagatreat stays in solution) CO.53. (Alternate wording is acc ep t abl e. )

Optimum pH is 6.4 to 6.0 (0.5).

REFERENCE FNR Systems Descriptions, Ch 5, Sec. 5.3.9 ANSWER C.02 (3.00) a.

119 F

(+/-

10)

b. #-25 gpm i*'

T'#

Wi t_h g' 5 inches of overflow c.

d.

150 ta / day

. L.,

c.

30 000 gal / day

(+/-

10%)

f.

1000 gpm

(+/-

10%)

(0.5 pts each)

REFERENCE FNR Systems Descriptions, Ch 4 and 5 ANSWER C.03 (1.00) c.

2.5 inches (0.5) b.

During rod calibrations (0.5)

REFERENCE FNR Operating Procedure, OP-102, 4.6 ANSWER C.04 (1.50) o.

Minimum power must be at least 5 times the gamma background Irvel to insure instruments are giving a true power indication (0.5).

b.

Maximum, power should be kept as low as possible to reduce the effects of Xenon (0.5) and temperature (0,5).

REFERENCE I

FNR Operating Procedures, OP-221, ec.

4.

_ _ p _,

MAdsLa.

M r' i

Gz__DENgB96_pfgB911N9_GH989EIEBigI1GE PAGE 23 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J.

M.

ANSWER C.05 (1.50) a.

40

(+/- 5) b.

15

(+/- 5) c.

20

(+/- 5 but must be higher than answer in b.)

(0.5 pts each)

REFERENCE FNR Systems Descriptions, Ch 3, Sec. 3.6 ANSWER C.06 (1.00)

Keff

<0.9 REFERENCE FNR Operating Procedures, OP-402, Sec. 9.1.1 ANSWER C.07 (1.50)

Yes (0.5) Beamport B may effect power indication (coupling ef f ect to the reactor instrument channels)

(0.5), because the ion chambers are directly above B port (0.5).

REFERENCE FNR Operating Procedures, OP-401, Sec. 4.2 1

ANSWER C.08 (1.50) a.

2.46 g/ day (0.5) b.

1.

20% (0.5) 2.

40% (0.6, REFERENCE l

FNR Systems Descriptions, Ch 2, Sec. 2.1 ANSWER C.09 (1.00) 4.

100 kW (O.

b.

960 (900 -

) gpm (0.5)

A'*

(. s. ;-

l f's/'gpQD, $ LILT bf8 d

Et__DENEBOL R EBBIING_GUSBOGIEBIEIlGE PAGE 24 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J.

M.

REFERENCE FNR Systems Descriptions, Ch 4

~

l I

i I

l r

l l

l I

t 9-P

.ma (

• g g

• • s e 9,* Pa h.

f#

rh g'.

's.

e L '\\.

-f % '- 5 L

Ez__INSIggD[NIg_gNQ_QQNISQLH PAGE 25 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J.

M.

ANSWER D.01 (1.00) 3 (0.5)

Located in the hot DI system (0.5)

REFERENCE FNR Systems Descriptions, Ch 13, Sec. 13.8.1 ANSWER D.02 (2.00)

Control rod above upper limit (0.5) 23.5 inches (0.5)

Control rod below lower limit (0.5) 5.0 inches (0. 5)

REFERENCE FNR Systems Descriptions, Ch 13, Sec. 13.2.1 ANSWER D.03 (2.50) a.

A safety system channel alarm at the safety system monitor and test unit.

(0.5) b.

A switch on the rad a i on recorder whe any eading excee s 10 mrem.

(0.5)

At=%.Fe*<wd/

AW v.

c.

EITHER mobile air particulate monitor (MAPP) [1.03 or gaseous activity detector (GAD) [0.53.

REFERENCE FNR Systems Descriptions, Ch 13, Sec. 13.1.1 ANSWER D.04 (2.00) a.

Core delta T is calculated by subtracting bulk pool l

temperature 20 f t below the surface (RS) from primary heat exchanger inlet (R1 or R2).

(1.0) l b.

Secondary delta T is calculated by subtracting secondary heat exchanger outlet (R7) from secondary heat excnanger l

inlet (R6).

(1.0)

REFERENCE FNR Systems Descriptions, Ch 13, Sec. 13.6.1 l

f f<

l

,~

A N

('s;

.i w.

Dz__IN!ISpDENIS_9yp_ggyISp(S PAGE 26 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J.

M.

ANSWER D.05 (2.00) 1.

Low pool l evel 2.

Pool level auto rundown 3.

FNR GAD 4.

Floor duress 5.

Linear level abnormal (Any 4 @ O.5 pts each)

REFERENCE FNR Systems Descriptions, Ch 13, Sec. 13.1.2 ANSWER D.06 (1.00) 1.

A 30s inhibit prevents control rod withdrawal if reactor period is <30s.

(0.5) 2.

If period reaches <10s, automatic rundown of the shim saf ety rods is ini tiated. (0.5)

REFERENCE FNR Systems Descriptions, Ch 13, Sec. 13.3.3 ANSWER D.07 (1.00)

.The reactor would remain in automatic control.

g "P"

If the control rod were at the upper limit, power would continue to drift down due to xenon buildup, REFERENC FNR Syst fuel burnup, or because of the negative reactivity that had made it decline to -5% initially.

Without operator action, the reactor would eventually shutdown completely.

ANSWER If the control rod were not at the upper limit, it would respond normally to being below the setpoint, The door withdraw automatically, and restore power to the REFERENC setpoink, leye.l..,

FNR Systems Descriptions, Ch 13, Sec. 13.1.1

)

<~'.>c-

= v ' m ':~

.m f.,i

~

i6h % Lu.

O b..:.

i v-

,.-w--

~ ---

i f

El-INSIBgDENIg_9Np_ggNIRQLg PAGE 27 ANSWERS -- UNIVERSITY OF MICHIGAN

-BB/01/19-KEETON, J. M.

s ANSWER D.09 (1.50)

The uncompensated ion chamber detects both neutrons and gammas (0.5).

The compensated ion chamber has an additional chamber that is insensitive to neutrons (0.5), and is electrically connected to cancel current produced by gammas in both chambers leaving the net output from neutrons only (0.5).

REFERENCE FNR Systems Descriptions, Ch 13, Sec. 13.13,4 h

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e Ez__E9EEIY_9ND_gDEBQENGY_EXEIgd5 PAGE 28 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J. M.

E n

ANSWER E.01 (2.00) a.

Provides about a 1 min delay time f or water exiting the reactor (0.5) to allow N-16 to decay to a safe level (0.5).

b.

3.

Butterfly valve not full open (0.5) 2.

Low pressure in the tank (0.5)

REFERENCE FNR Systems Descriptions, Ch 4, Sec. 4.3.3 ANSWER E.02 (2.50) 1.

Radiation monitoring systems 2.

Some building lighting 3.

Alarm systems 4

Ventilation system 5.

Telephone system 6.

Pneumatic tube system 7.

Backup air compressor 8.

Bridge drive circui t 9.

Heavy water tank control unit

^,

(Any 5,0 9 5 pts each) w-w a

_.-,a'-

gg REFERENCE FNR Systems Descriptions, Ch 14 ANSWER E.03 (1.00)

City water (0.5) 400 gpm (0.5)

REFERENCE FNR Systems Descriptions, Ch 4, Sec. 4.3.8 ANSWER E.04 (2.00)

The holding electromagnet on the header latch mechanism deenergizes (0.5), the header swings down to the lowered position (0.5), closing the microswa tch in the bridge and reactor control circuit (0.5), causing a header down scram e

i cignal (0.5).

I e

3 E t _ _E9EE IY _9NQ_[d[R Qg NC Y _E Y EIE M 5 PAGE 29 NNSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J.

M.

l REFERENCE FNR Systems Descri pti ons, Ch 4, Sec. 4.3.2 ANSWER E.05 (2.00)

A slow scram operates relays that turn off magnet power in that channel only. (1.0)

A fast scram uses a swi tching transistor that turns off magnet power in all three channel s.

(1.0)

REFERENCE FNR Systems Descriptions, Ch 13, Sec. 13.2.1 ANSWER E.06 (1.00)

The cooling tower sump is higher than the top of the pool (0,5),

resulting in a greater hydrostatic head on the secondary side (0.5).

REFERENCE FNR Systems Descriptions, Ch 5, Sec.

5.3.3 ANSWER E.07 (2.00) i 1.

Primary coolant pump circuit

(

2.

Safety and control rod circuit 3.

Bridge locking circuit 4.

Rod magnet circuit (0.5 pts each) l REFERENCE FNR Systems Descripti ons, Ch 3, Sec. 3.3 i

ANSWER E.OO (1.50) f Ch A - Uncomp. ion chamber (0.25) 2.4 MW (0.25)

Ch B - Uncomp. ion chamber (0.25) 2.4 MW (0.25) j' Ch C - Log N comp. ion chamber (0.25)

<5s period (0.25)

I i

REFERENCE i,

FNR Systems Descriptions, Ch 13, 13.2.1 1

l{

f'$ f

/j I

(.e n-

/'s -:.

n, I t t v (i s.

-w e m Qjj.

g 1

Ez__EIONpgRp_9Np_EMEBgENQy_QPE891]Ng_P89QE99855 PAGE 30 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J.

M.

ANSWER F.01 (2.50) 1.

Push console scram button 2.

Place rod drive switches in the insert position 3.

Verify scram has occurred 4.

Turn off pneumatic blower if running 5.

Remove magnet key and take it and logbook with you (0.5 pts each)

REFERENCE FNR Operating Procedure, OP-101, Sec. 7.3 ANSWER F.02 (1.00)

YNW{

k 4/'**

Breakers are i com 2074 (0.5) and mercury swi tches.e e i n McM, &

(room 3073)

(O.

REFERENCE FNR Operating Procedures, OP-108, Sec. 4.3 ANSWER F.03 (2.00)

B2cause, power inte.ruptions may cause large voltage surges (1.0) that can damage electronic equipment (1.0).

REFERENCE FNR Operating Procedure, OP-108, Sec. 3 and 4 i

r ANSWER F.04 (2.00) c.

5 min (0.5) to allow the f an to completely stop (C.5) b.

1.

Fan blades may be thrown from the hub 2.

May shear gears in the gear box 3.

May trip vibration switch (Any 2 O O.5 pts each)

REFERENCE FNR Operating Procedure, OP-304

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l Ez__SIONQeB9_eUD_EDESQENGY_DEE60IINQ_EBQGEQWBES PAGE 31 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J.

M.

ANSWER F.05 (2.50) a.

The counts should decrease (by a factor of 2) [0.53 then return to 1000 cps when the detector reaches its original 4

posi ti on (0.5).

Thf.s shows th(t the detector is U

responding to neutrons (0.5).

b.

This checks response to noise (0,5) which could defeat the 5 cps interlock (0.5)

REFERENCE FNR Operating Procedure, OP-110, Sec. 5 ANSWER F.06 (1.50) 1.

Individual beamport door scrams 2.

Thermal column door scram 3.

Shim range bypassed scram (3 rods)

(0.5 pts each)

REFERENCE FNR Operating Procedure, OP-111, Sec. 4 ANSWER F.07 (2.50) a.

Scram the reactor.

(0.5)

Immediately notif y Supervisor of Reactor Op er a t i er.s (Assistant Reactor Manager or Reactor P.aager)

(0.5) b.

Shutdown the reactor.

(0.5)

Notify the Supervisor of Reactor Operations (Assistant Reactor Manager or Reactor Manager)

(0.5) c.

Lead Operator (0.5) p P5FERENCE g

r, Operating Procedure, OP-102 Y. a;,

1..,.,

4 A

. ~.. n.

c Et__B8918I19N_QQNISQL_gNQ,ggEgIY PAGE 32 ANSWERS -- UNIVERSITY DF MICHIGAN

-88/01/19-KEETON, J.

M.

ANSWER G.01 (2.00) a.

whole body 1.25 rem hands and f eet 18.75 ren skin 7.50 rem (0.5 pts each) b.

10% of the above limits (0.5)

REFERENCE 10CFR20.101 and 10CFR20.104 ANSWER G.02 (1.50) a.

G-M detector [.25), particulate [.253 b.

Na-1 detector [.253, Gamma [.253 c.

G-M detector [.253, Argon 41 [.25]

REFERENCE FNR systems description table 13.1 ANSWER G.03 (1.00) 1.

Designed to serve as a receptacles f or samples to be l

irradiated.

(0.5) 2.

Serve as a radiation shields.

(0,5)

REFERENCE FRN System Description 3.2 l

ANSWER G.04 (1.50) 1 l

[-lambda x t3 l

N = No e

[0.53 l

[-lambda x t3 (200-40)/100 = e I n O. 6 = l ambda

.51 = l a;nbda

{

j T 1/2 = In 2/ lambda

[0,53 T 1/2 = 0.693'.51 T 1/2 = 1.36 days

[0.53 I

),

/.

A r' '. ' r -

f.

r-"

[Y k ~b N

..u a

s. h-

"~

-,- - ~ _ -. _. l f

9t__B9D19IIDN_GQNIBDL_9ND_feECIY PAGE 33 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J. M.

REFERENCE Intro, to Nuclear Reactor Oper ations, pg 1-2 ANSWER G.05 (2.00) a.

Ar-40 (n, gamma) -> Ar-41 Half-life = 1.9 hrs

(+/- 50%)

Decay by Beta emission (0.5 pts each) b.

It is produced in air in the experimental facilities.(0.5)

REFERENCE FNR Systems Descriptions, Ch 4, pg 4-5, Nuclear Power Plant Health Physics and Radiation Protection, Ch 5 ANSWER G.06 (2.00)

No (0.5).

The unit rem already considers the different effects (quality factors).

Rem is a biological unit thus, different types ot radiation causing the same dose in rem will have the same bi ol ogi cal effect. (1.5)

REFE9ENCE 10CFR2O ANSWER G.07 (1.50)

A radiation area is

>5 mr/hr.

A high adiation area is >100 nr/hr.

Therefore, the maximum dose he could hav? received in a properly raseked radiation area is 100 mr/hr.

Calculated maximum dose is 45/60 x 100 = 75 mr (1.5)

REFERENCE 10CFR2O t

I 8

i F

g 6

h 'y L.

2' L

e 3

Et__ bed 19I196_E961RQL,gNQ_g9EEIY PAGE 34 ANSWERS -- UNIVERSITY OF MICHIGAN

-88/01/19-KEETON, J. M.

4 ANSWER G.OB (2.00) 1.

Initiate building evacuation alarm 2.

Scram the reactor 3.

Shutdown the FNR supply and exhaust fans 4.

Close the BHF dampers 5.

Shutdown the FNR ventilation fans 6.

Shutdown the PML supply and vent fans 7.

Actuate the "radioactivity in building air" annunciator (Any 4 0 0.5 pts each)

REFERENCE FNR Systems Descriptions, Ch 13, 13.9.1 ANSWER G.09 (1.50) a.

1.

5 min 2.

15 min (0.5 pts each) 6.

High radi ation areas (0.5)

REFERENCE FNR Health Physics Manual, pg 2 l

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5 (E. - 7 g

i TEST CROS3 REFERENCE PAGE 1

QUESTION VALUE REFERENCE A.01 2.00 KMJOOOOO58 A.02 1.50 KMJOOOOO59 A.03 2.00 KMJOOOOO60 A.04 2.50 KMJOOOOO61 A.05 1.00 KMJOOOOO62 A.06 1.00 KMJOOOOO63 A.07 2.50 KMJOOOOO64 A.OB 2.00 KMJOOOOO65 14.50 B.01 2.00 KMJOOOOO66 B.02 1.50 KMJOOOOO67 B.03 2.00 KMJ0000060 B.04 1.50 KMJOOOOO69 B.05 1.50 KMJOOOOO70 B.06 1.00 KMJOOOOO71 B.07 2.00 KMJOOOOO72 B.OB 2.50 KMJOOOOO73 B.09 1.00 KMJOOOOO74 15.00 C.01 1.50 KMJOOOOO75 C.02 3.00 KMJOOOOO76 C.03 1.00 KMJOOOOO77 C.04 1.50 KMJOOOOO78 C.05 1.50 KMJOOOOO79 C.06 1.00 KMJOOOOOBO C.07 1.50 KMJOOOOOB1 C.OB 1.50 KMJOOOOOB2 C.09 1.00 KMJOOOOOB3 13.50 D.01 1.00 KMJOOOOOB4 D.02 2.00 KMJOOOOOB5 D.03 2.50 KMJOOOOOB6 D.04 2.00 KMJOOOOOB7 D.05 2.00 KMJOOOOOe8 D.06 1.00 KMJOOOOOB9 D.07 1.00 KMJOOOOO90 D.OB 1.00 KMJOOOOO91 b.09 1.50 KMJOOOOO92 14.00 E.01 2.00 KMJOOOOO93 E.02 2.50 KMJOOOOO94 E.03 1.00 KMJOOOOO95

M' TEST CROSS REFERENCE PAGE 2

DUESTION VALUE REFERENCE E.04 2.00 KMJOOOOO96 i

E.05 2.00 KMJOOOOO97 E.06 1.00 KMJOOOOO98 E.07 2.00 KMJOOOOO99 E.08 1.50 KMJOOOO100 14.00 F.01 2.50 KMJOOOO101 F.02 1.00 KMJOOOO102 F.03 2.00 KMJOOOO103 F.04 2.00 KMJOOOO104 F.05 2.50 KMJOOOO105 F.06 1.50 KMJOOOO106 F.07 2.50 KMJOOOO107 14.00 G.01 2.00 KMJOOOO108 G.02 1.50 KMJOOOO109 G.03 1.00 KMJOOOO110 G.04 1.50 KMJOOOO111 G.05 2.00 KMJOOOO112 G.06 2.00 KMJOOOO113 G.07 1.50 KMJOOOO114 G.08 2.00 KMJOOOO115 G.09 1.50 KMJOOOO116 15.00 100.00 DOCKET NO 2

i

/

)

l U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:

..tJNIVE_RSITY OF MI_CHIGAN REACTOR TYPE:

IEET DATE ADMINSTERED:

66/01/19 EXAMINER:

HABE%E. A.

CANDIDATE INSTRUCIIONS_TO C6NDIDAIE1 Use separate paper for the answe.rs.

Writo answers on one side only.

Staple question sheet on top of the answer sheets.

Points for each question are indicated in parentheses after the question.

The passing crade requires at least 70% in each category.

Examination papers will be picked up six (6) hours after the examination starts.

% OF CATFGORY

% OF CANDIDATE'S CATEGORY VALUE_

TOTAL SCOBE

_26LUE__

____f6IEGQBY W.*kO H.

REACTOR THEORY

_tfM *f_ _1H E

\\ %.'I

_istsL__ _20.10

_ I.

RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS

_EldO.__ _Z12 J.

SPECI71C OPERATING CHARACTERISTICS

_lEJO

_12 2 K.

FUEL HANDLING AND CORE PARAMETERS JQJQ__ _20.35 L.

ADMINISTRATIVE PROCEDURES, 9,(ogf CONDITIONS AND LIMITATIONS

_g" Totals W

1I Final Grade All work done on this examination is my cwn.

I have neither given nor received aid.

Candidate's Signature f

~D L Le j" h [

s f iUNV i: Li\\

(

c c :-

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1.

Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2.

Restroom trips are to be limited and only one candidate at li time may

-leave.

You must avoid all contacts with anyone outside the examination

. room to avoid even the appearance or possibility of cheating.

3.

Use' black ink or dark pencil only to facilitate legible reproductions.

4.

Print yoor name in the blank provided on the cover sheet of the examination.

5.

Fill in the date on the cover sheet of the examination (if necessary).

6.

Use only the paper provided for answers.

7.

Print your name in the upper right-hand corner of the first page of each section of the answer sheet.

8.

Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.

9.

Number each answer as to category and number, for example, 1.4, 6.3.

20. Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

22. Use abbreviations only if they are commonly used in facility literature.

33. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

26. If parts of the examination are not clear as to intent, ask questions of the examiner only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.

This must be done after the examination has been completed.

-18.'When you complete your examination, you shall:

C.-

Assemble your-examination as follows:

(1)

Exam-questions on top.

(2)

Exam aids - figures, tables, etc.

(3)

Answer pages including figures which are part of the answer.-

b.

Turn-in your copy of the examination and all pages used to answer the examination questions.

c.

Turn in all scrap paper and the balance of.the-paper that you did not-use for_ answering the questions.

d.

Leave-the examination area, as defined by the examiner.

If after leaving, you are found in this' area while the examination is still in progress, your license may be denied or revoked.

T i:

I L

E ii n..

H; ~ REACTOR-THESRY Pcgp 4

QDESTION H.01 (1.00)

What is the purpose of the "moderator" in the reactor?

Explain.

QUESTION-H.02 (2.00)

In each of the following cases, STATE the preferred' characteristics for.a moderator.

Briefly explain why for each answer.

a.

Absorb neutrons or scatter neutrons.

(1.0) b.

Have a high atomic weight or low atomic weight.

(1.0) i t

QUESTION

H.03 (2.00) a.

List the two major negative reactivity coefficients which can halt the rapid power escalation following a positive step reactivity insertion.

(1.0) 1 t

b.

What are'their values'as listed in your Technical Specifications.

(1.0)

QUESTION H.04 (2.00) a.

Explain what is meant by the term "delayed neutron fraction".

(1,0) b.

Does the value of the delayed neutron fraction change over core life?

Explain.

(1.0) i QUESTION H.05 (1.50)

Figure 9.6, attached, shows how reactor core flux changes from BOL to EOL.

State the three (3) reasons why Flux shifts upwards by the end of core life.

(1.5) l E

i I

(*****

CATEGORY H CONTINUED ON NEXT PAGE *****)

t 9

4

INTRODUCTION TO NUCLEAR REACTOR OPERATIONS Rocctor Coro Anclycto Reed Robert Burn June, 1984 0

Figure 9.6 Reactor Core Flux Pattern

{

Shif ts Over Core Lif e Core 4

T

\\

\\*EOL

\\

\\

Peak I

/

j

, Peak i

l Constant

/

4 Power ML

/

m Page 9-11

H '.

REACTOR THEORY Pcg2 5

QUESTION H.06 (1.00)

A person being trained on the reactor has developed a system for reactor startups.

He noted that the last time he did a startup the reactor was critical at 5000 CPS.

He reasons that for his next startup (some months later) when he reaches 5000 CPS the reactor will.be critical.

In this person's system valid?

Explain your answer.

(1.0)

QUESTION H.07 (2.50)

Calculate the reactor period for the given conditions: Beff :.007.

a.

Keff 1.0001 for a prompt critical reactor.

b.

Keff : 1.0001 for a delayed critical reactor.

(Show all work)

QUESTION H.08 (1.50)

Two minutes efter a scram from power, a large number of neutrons are still present in the core.

Discuss the reason and identify the source (s) of all these neutrons.

(Be specific)

QUESTION H.09 (2.00)

State the reason the neutron flux increase rapidly and then settle into a stable period when positive reactivity is added to make the reactor supercritical?

QUESTION H.10 (1.00)

Fill in the Blanks.

a.

The equilibrium concentration for Xe is reached after about hours of steady state aperation.

(0,5) b.

Whenever a reactor is shut down, Xe rapidly builds up, reaching a peak after about hours.

(0,5)

(*****

CATEGORY H CONTINUED ON NEXT PAGE *****)

j

?:

H.

REACTOR THEQBY Pcga 6

DC.k the QUESTION H.11-(2.50) a--

B ::.-ibu che Dverici effect,

+t-&)

b.

^ ;' '3000 L}c fuel I,empezabusu cc6f ficiCT.t h000.% luco. 060ti'?? 15 foal ts...pm aLuso increc;;;?

(1.5b

(*****

END OF CATEGORY H *****)

- 1.

RADIOACTIVE MATEBIALE_ HANDLING DISPOSAL Pcgo 7

AED_B&lABDE QUESTION I.01 (1.50)

If the dose rate from a radiation source is 100 mrem /hr at 1 meter, what is the dose rate at 25 cm?

Show work.

(1.5)

- QUESTION I.02 (2.00) a.

STATE the quarterly occupational dose limit for whole body, hands and feet, and skin of the whole body.

(1.5) b.

STATE the' dose limit for individuals under the age of 187 (0.5)

QUESTION I.03 (1.50)

Before an experiment is removed from the reactor pool, four (4) items should be on hand.

State 3 of the 4 items.

(1.5)

QUESTION I.04 (1.00)

Personnel entering the FNR-FML faci 3ity will be issued film badges except three specific categories.

State 2 of the 3 categories.

(1.0)

QUESTION I.05 (1.50)

The following questions are in regards to Pool Water Analysis.

a.

How often will pool water be sampled.

(0.5) b.

What is the reason for conducting two gamma isotopic analyses?

(1.0)

QUESTION I.06 (1.50)

While working in an area marked "Caution, Radiation Area," an operator discovers his dosimeter is off scale and leaves the area.

Assuming he had been working in the area for 45 minutes, what is the maximum dose he i

would have received?

(Show all work and state any assumptions you have made.)

(

(*****

CATEGORY I CONTINUED ON NEXT PAGE *****)

i L

I,..!B&DlQ&GIlYE MATERIALS HANDLING DISPOSAL Pega 8

at!D_HAIABDE QUESTION I.07 (0.50)

How many curies of radioactive liquids does the University of Michigan allot to the FNR to discharge into the sanitary sewer. system per year?

QUESTION I.08 (1.50)

For the following types of radiation monitors, STATE the type of monitor it is AND what it detects, a.

Mobile air particulate monitors.

(0.5) b.

NMC.

(0.5)

.c.

Gaseous activity detector.

(0,5)

~ QUESTION I.09 (1.50) De\\thqc F112 the blank, um dose rate at the external surface of a yellow The m radioac (tive wa (/hourn a.

e can or fiber drum should not normally exceed (1) mrem (0.5) b.

In temporary situations, radi'oastive waste materials with does rates greater than __ (2) __ mrem / hour, but-less._he-Health than (3) mrem /hr depending on t hysicist's may be stored in work areas, discretion.

(

1-QUESTION I.10 (2,50)

Name 5 of the 6 radiation monitors, which must be operable prior to making the reactor crit al.

(*****

CAT /30RY I CONTINUED ON NEXT PAGE *****)

n-I.

RADIOAQIlYE.MATli316I4_ HANDLING DIEEQEAL Pcg2 9

&ND-HAZABDS

-QUESTION I.'11 (1.50)

The following questions are in regards to FNR-FML Tour Exposure Guidelines, a.

Fill in the blank.

The time spent by a tour at the pool rail will be limited to approximately (1)_

minutes.

When.away from the pool rail, an additional ___(2) minutes may be spent on the pool floor.

(1.0) b.

What type (s) of radiation area (s) is (are) tours not permitted.

(0.5)

QUESTION

-I.12 (3.75)

Radioactive isotopes that are common from the operation of a research reactor are N-16, A-41 and, H-3.

(3.75) a.

For each of the above, give the source, where it would be found, and the half-life.

(.25 each, total 2.25) b.

What, if any, precautions or design attributes are taken to reduce the effect of these isotopes at Ford Nuclear Reactor?

(0.5 each, total 1.5)

(***** END OF CATEGORY I *****)

1 t

a J,

SPECIFIC _ OPERATING. CHARACTERISTICS Poco 10 QUESTION J.01 (1.00)

The beamports at FNR are equipped with plugs.

State the two (2) functions that they serve.

(1.0)

QUESTION J.02 (2.00)

List the four (4) circuits that are interconnected with the power to run the bridge.

QUESTION J.03 (2.00)

Describe two ways in which the nitrogen system can be utilized to supply to the heavy water tank.

QUESTION J.04 (1.00)

The nitrogen system supplies are utilized to maintain dry environments around cables and equipment for what two (2) reasons?

(1.0)

QUESTION J.05 (2.00)

The following questions deal with the Header Latching Mechanism:

a.

How is coupling made between the header and the latching mechanism?

(1.0) b.

Under what two conditions will the header be released?

(1.0)

QUESTION J.06 (2.50)

List the typical values for the following operating parameters at 2 Mw.

a.

Primary Coolant Flow Rate (0.5) b.

Core Differential Teuperature (0,5) c.

Ileat Exchanger Inlet Temperature-Pump 2 (0,5) d.

Heat Exchanger Outlet Temperature (Primary Side)

(0,5) e.

Primary Coolant Conductivity (0,5) t

(*****

CATEGORY J CONTINUED ON NEXT PAGE *****)

L... _ SEEQ1Elg __0PERAT I NG ' CHAB&QIEBIST I CS Pcgo 11 QUESTION J.07 (2.00)

The secondary coolant through the heat exchanger has a greater hydrostatic head, a.

How is the hydrostatic head physically determined for the secondary coolant?

(1.0) b.

Why is it preferred to have a greater hydrostatic head on the secondary side?

(1.0)

QUESTION J.08 (2.00)

State the two (2) purposes of the steam line which enters the secondary coolant at the inlet to the heat exchanger.

QUESTION J.09 (1.00)

Specify the position (open/ shut) in which valves 1, 2, 3, and 4 of Figure 11.1 must be placed in order to return the rabbit to the dispatch station.

QUESTION J.10 (1.00)

The Interlock Scram Defeat Switches in the rear of the console defeat what two (2) scrams?

QUESTION J.11 (2.50)

Name five conditions, including setpoints, which will cause an automatic reactor scram.

QUESTION J.12 (2.50)

In th' event of loss of normal power, emergency power is supplied to certain vital loads by the emergency generator.

List five (5) vital loads the emergency generator powers, i

L

( * 's *

• END OF CATEGORY J *****)

Ford Nuclocr Rocctor Syctcca Deccriptiono Pneumatic Tube System January 9, 1985 Figure 11.1 Typical P-Tube Run Reactor Core Irradiation Station l

_]

Reactor Pool F,abbit Track 4

Vent Diepatch Station 4)

Reactor Basement Vent Blower Suction whe Blwers lI Pneumatic B

l B

l e

Stack 2 Exhaust i

i p

e 9

r 9 69 4

wn:

p.

IK FUEL HANDLING AND CORE PAB M IEBS Pcga 12 QUESTION K.01

'(1.00)

FNR Technical Specifications limits the fission density limit to 1.5 x E 21 fissions /cc.

What is the bases (i.e.,

reason) for this limit.

~ QUESTION K.02 (1.00)

How much excess reactivity is permitte, by FNR Technical Specification (including moveable experiments).

QUESTION K.03 (2.50)

What conditions constitute shutdown margin (both conditions).

Include values.

QUESTION K.04 (3.00)

What four (4) conditions must be met prior to the reactor being made critical per FNR Technical Specifications?

QUESTION K.05 (2.00)

Your facility Technical Specifications places two limitations on Reactivity Limits which apply to all experiments.

State the two limitations.

QUESTION K.06 (2.00)

List two requirements in your facility Technical Specifications which apply to fuel storage at your facility, QUESTION K.07 (2,00)

The reactor is operating in automatic control when the -5% dropout feature fails.

Explain what will happen to reactor operations.

(Assume no operator action).

(***** CATEGORY K CONTINUED ON NEXT PAGE *****)

S Ki_ FUEk_ HANDLING AND CORE PARAMETERS Pcco 13 QUESTION K 08 (1.50)

Describe the haterial~ construction of the:

a.

Shim rods.

(0.75) b.

Control rods.

(0.75)

QUESTION K.09 (2.00)-

-Your facility has fuel storage racks installed at-the north and south end of the pool.

What are these racks (discuss individually) utilized for.

QUESTION K.10 (1.00)

What is the purpose of the holes drilled through the gridplate at the locations on the diagonal.between the fuel element holes?

(1.0)

QUESTION K.11 (1.50)

The following is a list of items that are required to be met prior to fuel transfer in and out of the core. Which of these items are not required if loading fuel will result in a core which is not capable of going critical?

a.

Be done in accordance with a FUEL MOVEMENT SCHEDULE approved by the Reactor Manager, Assistant Reactor Manager or On-call Supervisor; b.

Be done in the presence of a Lead Operator; c.

Be done with an operator in the control room, who is responsible for monitoring an operating Log Count Rate channel; d.

Be done only with communication established between the bridge and the control room:

(

c.

Be recorded in the Fuel Logbook;

[

f f.

Be done under the precautions from the control room operator.

l i

1 l

(***** END OF CATEGORY K *****)

l t

L.

ADMINISTRATIVE PROCEDURESm CONDITIQHS P so 14 AND LIMITATIONS QUESTION

-L.01 (2.00) a.

Who can initiate the building emergency procedure?

(0,5) b.

Where can the building alarm horn be manually initiated from?

(1.5)

QUESTION L.02 (1.50)

Immediately after an unscheduled shutdown, the control console operator is required to do certain actions per OP-104, Reactor Operations.

What are his immediate actions?

QUESTION L.03 (2.50)

For the following plant conditions, state the correct operator action per OP-104, "Reactor Operations".

Choices are scram reactor, insert all rods, or maintain power.

(0.5 each) f a.

Reactor critical with shim rods below "shim range".

b.

Inability to control primary coolant.Fiou3 c.

Loss of period safety channel.

d.

Loss of 2 NMC's, either GAD, or Stack 2 MAPP.

e.

Malfunction of auto - rundown circuit.

?

QUESTION L.04 (3.50) a.

Why do the Tech Specs have safety limits and limiting safety system settings?

(2.0)

~

b.

List the values of the safety limits in the Natural Convection Mode for the following:

(1.5) l l

1.

Reactor Thermal Power.

2.

Reactor Coolant Inlet Temperature.

3.

Height of Water Above the Top of the Core.

P QUESTION L 05 (1.00)

What two (2) operations during reactor shutdown require the presence of a Lead Operator.

(1.0)

(*****

CATEGORY L CONTINUED ON NEXT PAGE *****)

L.

ADH1HISIB&TIVE PROCEDURES,_COGIIIQHS-Pro 15 AN_Q_LlH11&I1QES QUESTION

L.06 (2.00)

What are the. Lead Reactor Operator's two (2) responsibilities during initial. loading of the experiment.

-QUESTION L.07 (1.50)

' Fill in the blank.

a.

During startups, except rod calibration, shim rod positions will be kept within a distance of of each other.

(0.5) b.

Power level increases will not be made with the reactor on a stable

_ 0.5)

(

positive period of less than _

c.

For startups following shutdown in excess of one hour, reactor power shall be raised to a maximum of (0,5)

QUESTION L 08 (1.00)

What two (2) actions must the operator on duty perform if he is informed that the Ann Arbor area has been placed under a tornado warning?

(1,0)

QUESTION L 09 (1.00)

Fill in the Blank a.

As a temporary condition while transferring unirradiated fuel between the vault and the reactor pool, the fuel can be laid down in a row on a flat surface with not less than a distance of between each element.

(0.5) b.

The control system isolation switches should be opened whenever a power failure persists for a period of time in excess of (0,5)

(***** CATEGORY L CONTINUED ON NEXT PAGE *****)

L.

ADti1ELETRATlYE_ERQQEDURESi CONDITIOt!E PCs3 16 i

&MQ_LIMITATIONE QUESTION L.10 (2.50)

What five (5) actions must the console operator take during a building evacuation in order to secure the reactor.

(2.0)

QUESTION L.11 (2.00)

During an evacuation due to a fire, the lead operator will await the arrival of the'fita department at the south side door entrance to PML.

a.

What three items of information are required to be given to the fire captain by the lead operator when the fire department arrives?

(1.5) b.

What other duty is the lead operator required to perform when the fire department arrives?

(0.5) f

(*****

END OF CATEGORY L *****)

(**********

END OF EXAMI N A'.' ION * * * * * * * * * * )

l EQUATION ENEET f = ma y = s/t Cycle efficiency = (Metwork i

out)/(Energyin) t w = ag s = V,t + 1/2 at 2

c = ac 2

KE = 1/2 an a = (Vf-V,)/t A = 14 A=Ae**

g PE = agn f = V, + at w = e/t A = an2/tg q = 0.593/t1/2 V

if2*ff = :(tus)(t ))

f t

s y.,,P.

,o I

1/2

• I*b)3 4

EIt st = 931 sn a = y,,As

, -rx Q = aCpat 6 = UA4 T I = I e'"*

n I = I, 10~*E Pwr = W ah r

TYL = 1.3/u sur(t)

P = P 10 HYL = -0.693/u P = P e /T t

o SUR = 26.06/T SCR=5/(1-K,ff)

'2, = Si (1 - K,ff,)

CR (1 - K,ff)) = CR II ~ Ieff2)

SUR = 26a/t* + (s - p)T j

2 T = (1*/s) + [(a - eVis]

N = 1/(1 - K,ff) = CR /G, j

T = s/(e - s)

M = (1 - K,ff,)/(1 - K,ff j)

T = (s - e)/(Te)

SDM = (1 - K,ff)/K,ff a = (K,ff-1)/K,ff = aK,ff/K,ff

• • = 10 seconds I = 0.1 seconds *I e = [(t*/(T K,ff)] + [s,ff (1 + IT)]-

/

Idl1*Id2,2 2 P = (E4V)/(3 x 1010)

Id gd jj 22 E

I = eN R/hr = (0.5 CE)/d (meters)

R/hr = 6 CE/d2 (feet) i Water Paraneters Miscellaneous Conversions I gal. = 8.345 Ice.

1 curie = 3.7 x 1010dps i

1 ga;. = 3.78 liters i kg = 2.21 tbm 3 8tu/hr l

1 fte = 7.48 gal.

I hp = 2.54 x 10 l

Density = 62.4

/ft3 1 aw = 3.41 x 106 8tu/hr Density = 1 gm/

lin = 2.54 cm Heat of vaporization = 970 Stu/lem

• F = 9/5'C + 32 Heat of fusion = 114 Stu/lbm

'C = 5/9 ('F-32) 1 Atm = 14.7 psi = 29.9 in. Hg.

1 BTU = 778 ft-Ibf 1 f t. H O = 0.4335 lbf/in.

2

) (1:* 7"' tN

.[

Pcga.17-H.

REACTOR TiiEQ8Y f % ; ~%

["e f'

,W

}g g

ANSWER H.01 (1.00)

Neutrons of low energy have the highest probability of causing fission in the fuel.

Most neutrons are born of high energy levels.

The moderator reduces the neutron energy lov.s1.

(1,0)

REFERENCE Intro to Nuclear Reactor Operations pg 2-45 ANSWER H 02 (2.00) a.

Scatter, so neutrons are lowered in energy rather than lost, b.

Low atomic weight so the fewer scattering collisions are required.

REFERENCE Intro to Nuclear Reactor Operations pg 2-45 ANSUER H.03 (2.00) a.

Void coefficient.

(0,5)

Temperature coefficient.

(0,5) b.

- 1.0 % d k/k/ % Void (0.5)

- 5.5 x E -3

% d k/k /F (0,5)

REFERENCE kO[- 90 /D bNN

-F o n icvh Cpccer FNR System Description Table 2.3 ANSWER H.04

( 2. 00 h a.

The fraction of all neutrons in a given generation which are emitted from the decay of fission fragments at a significant time after the actual fission event.

(1.0) b.

Yes (0.25), as core exposure increases, the build-up of Pu-239 and Pu-241, causes beta-fraction to decrease due to their different Beta-fraction. [0.75]

(1.0)

(exact wording not required)

(*****

CATEGORY H CONTINUED ON NEXT PAGE *****)

[

[H.

REACTOR THEORY Pcga 18:

REFERENCE Intro'to Nuclear Reactor Operations pg 3-7, 3-11 ANSWER H.05 (1.50) a.

Rod motion out of the core, b.

Burnup of fuel in the lower region, c.

Xenon buildup in the lower core region.

(3 @ 0.5 each : 1.5)

REFERENCE Introduction to Nuclear Reactor Operations - Pg. 9-8.

ANSWER H.06 (1.00)

Not valid (0,5) - The count rate at critical is a function of starting count rate (source) and the shutdown margin.

Also several months later.

burnup, poisons, and any changes in experiments will have some effect.

(0,5)

REFERENCE Intro to Nuclear Reactor Operations pg. 3-20, 6-10 ANSWER H.07 (2.50) p = Keff - 1/Keff l

(1.0001 - 1)/1.0001

= 0.0001 dk/k

'[0.6) a.

Reactor period T = 1*/p

[0.5)

(1 x E -4 see) /(1 x E -4 dk/h)

1 sec

[0,5) b.

T = (Beff p)/(L p)

[0.5]

= (.007 - 0.0001)/((0.1) (0.0001))

690 aec.

[0,5)

(*****

CATEGCRY H CONTINUED ON NEXT PAGE *****)

?

,~

i-l H.

REAQ10B_IHEQBY

'Pcgo 19:

1p REFERENCE Introduction to. Nuclear Reactor Operations - Pg. 4-7, 4-9.

ANSWER H.08 (1.50)

The core neutron population is sustained by decay of the longest lived fission product precusor [1.0), bromine-87 [0.5).

(1.5)

REFERENCE

~ Introduction to Nuclear Reactor Operations - Pg 4-15.

ANSWER H.09 (2.00)

There is-a prompt jump caused by immediate effects of prompt neutrons.

[1.0)

A stable period follows which is determined by the amount of reactivity inserted and the delayed neutron generation time.

[1.0)

REFERENCE Introduction to Nuclear Reactor Operations - Pg 4-39.

ANSUER H.10 (1.00) a.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> (+/- 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />).

(0.5) b.

6 - 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

(0.5)

REFERENCE Introduction to Nuclear Reacto.c Operations - Pg. 8-9.

8-13.

(*****

CATEGORY H CONTINUED ON NEXT PAGE *****)

r

~

- 1..REbEIQB ItiEORY Pcsa 20 h

h-ANSWER 1

(2.50) a.

As a n leus increases in temperature it becomes thermally agitated.

The the al motion of the nucleus makes neutrons over a range of energies nd velocities) have the desired relative enerr;y for absorption the nucleus.

(1.0) b.

In general, the ractional reduction in self-shielding per degree F is less at high t.peratures than at low' temperatures.

The decreased rate of ppler broadening per degree F fuel temperature change at higher tem 'ratures causes less increase in the resonance energy range flux seen y centerline nuclei than would be the case at low fuel temperatures (1.5)

(Exact wording not required or full credit.)

REFERENCE Introduction to Nuclear Reactor Operatio - - Pg 6-39.

P

(*****

END OF CATEGORY H *****)

W-

~

n:,

' 1 __B6D1Q6CTIVE' MATEB16LS HANDLINQ_DISEOSAL Pcga 21 AND_HAZ6BDS ANSWER I.01 (1.50)

I1D12 : I2D22 (100 mrem /hr) (im) 2 = 12 (.25m) 2.

1600 mrem /hr = I2.

(1.5)

REFERENCE Nuclear Power Plant He;'th Physics and Radiation Protection pg. 3-11.

ANSWER I 02 (2.00) a.

'Whole body 1.25 rem.

Hands and feet 18.75 rem.

Skin 7.5 rem.

(3 @-0.5 each = 1.5) b.

10% of the above limits.

(0.5)

REFERENCE 10 CFR 20.101 and 10 CFR 20.104.

ANSWER I.03 (1.50) 1.

Functioning ion chamber survey meter.

2.

Piece of blotting paper.

3.

Eye Protection.

4.

Rubber gloves.

(3 of 4 required @ 0.5 each : 1.5)

REFERENCE Health Physics Manual - Pg. 3.

i

(*****

CATEGORY I CONTINUED ON NEXT PAGE *****)

n. _

^

y

1.

-RADlQ&Q1IVE MATEBl&LSill&HDLING DISPOSAL ~

Pcg2 ~ 22

.68Q HAZ68DE-ANSWER

- I.'0 4 (1.00) 1.

Visitors.

2.

Tours.

3.

Individuals specified by the Reactor Manager, Assistant Reactor Manager, or Health Physics.

(2 of 3 required @ 0.5 each = 1.0)

REFERENCE

. Health Physics Manual - Pg.

1.

ANSWER I.05 (1.50) a.

Weekly.

(0.5) b.

The first is to account for short lived radioactivity, the second for long lived radioactivity.

(1.0)

REFERENCE Health Physics Manaul - Pg.

6.

i ANSWER I.06 (1.50)

A radiation area is > 5 mr/hr.

A high radiation area is > 100 mr/hr.

The maximum dose rate in a properly marked radiation area.4s 100 mr/hr.

The maximum dose is calculated is as follows:

45/60 x 100 75 mr (1.5)

REFERENCE l

10 CFR 20.

t b

ANSWER I.07 (0,50)

.5 curies.

(0.5) i:

.i n

(*****

CATEGORY I CONTINUED ON NEXT PAGE *****)

t

p.-

q 41.

-RAD 1QAQIlYE_MATERIALE_ HANDLING DISPOEAL Pcg2 23

&ED_HAIABDE REFERENCE FNR System Description 9.1.

ANSWER I.08 (1.50) a.

G-M detector (0.25), Particulate (0.25).

b.

Na-I detector (0.25), Gamma (0.25).

c.

G-M detector (0.25), Argon 41 (0.25).

REFENENCE FNR System Description Table 13.1.

DE \\ Ek'.h ANS R

I.09 (1.50) a.

(1) 50 b.

2) 5

(-

50 (3

0.5 each : 1.5)

REFERENCE Health Physic Ma al - Pg.

8.

ANSWER I.10 (2.50) 1.

Building Air Exhaust, 2.

Bridge.

3.

Northwest Column.

4.

North wall.

5.

Northeast Column.

6.

Hot DI.

(5 of 6 required @ 0.5 each : 2.5)

REFERENCE a

FNR System Description 13.9.1.

(***** CATEGORY I CONTINUED ON NEXT FAGE *****)

1

,y

3 3' ^

'l.'

B&D10&GIIE _MAIERIALE_3ANDLING DISPOSAL P0g2 24

&ED_BALABES ANSWER I.11 (1.50) 5 minutes.

a.

(1) 15 minutes, (2) b.

Tours will not be permitted in high radiation' areas.

REFERENCE Health Physic Manual - Pg. 2.

ANSWER I.12

-(3.75) a.

0-16 (n, p) N-16; Primary coolant water; 7 seconds.

A-40 (n, gamma) A-41; air space near reactor and primary water with dissolved air; 1.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.

H-2 (n, gamma) H-3; Primary coolant water and air above pool; also heavy water in reflector tank; 12 years.

(Exact half-life not required, must be within 50% of actual half-life)-

(0.25 each for a total of 2.25) b.

N-16 : Hold-up tanks in primary coolant and domineralicer.

A-41 : Some held in beam ports; use of other gases in pneumatic systems.

H-3 : Vents at top of pool e b u M d..

(cLw)

'wn (0.5 each for a total)pb 1.5) e. mTe w+ be(M 6 0 Mu c REFERENCE Nuclear Power Plant Health Physics and Radiation Protection, Chapter 5 FNR Systems Descriptions P. 4-5, P.

12-1, P. 3-12.

i

(*****

END OF CATEGORY I *****)

p-SPECIFIC OPER' TING CHARACTEBISTICS

.Pcga 25

. J; A

ANSWER J.01 (1.00) 1.

Designed to serve as a receptacle for samples-to be irradiated'.

2.

Serve as a radiation shield.

(2 @ 0.5 each : 1.0)

REFERENCE FFR System Description 3.2.

ANSWER J.02 (2.00) 1.

Primary coolant pump circuit.

2.

Safety and control rod circuit.

3.

Bridge locking circuit.

4.

Rod magnet circuit.

(4 @ 0.5 each = 2.0)

REFERENCE FNR System Description 3.3.

ANSWER J.03 (2.00) 1.

Utilized in the transfer of water from the supply tank down into the heavy water tank in case of a low level.

(1,0) 2.

Transfer water from heavy water tank back into the supply tank in case of a high level.

(1.0)

REFERENCE FNR System Description 3.6.

ANSWER J.04 (1.00)

To prevent corrosion (0.5] and electrical failure [0.5).

(1.0)

(*****

CATEGORY J CONTINUED ON NEXT PAGE *****)

c-a TJ.

-SEEQIFIC OPERATING _QHARACTERISTICS Pcga 26 REFERENCE FNR System Description 3.6.

ANSWER J.05 (2.00)

-Made by means of an aluminum hook that is-open ong'one side.

(1.0) a.

b.

1.

Primary coolant flow drops below 900 gpm. [0.5) 2.

Event of power failure.

[0.5)

(1.0)

REFERENCE

'FNR Systems Description 4.3.2.

ANSWER J.06 (2.50) a.

1000 gpm (+/- 10%)

(0.5) b.

15.0 N

.4 degrcc; F) i3 3 + c) 14 0 F (0.5) c.

115 - 125 degrees F (0.5) d.

100 - 110 degrees F (0.5)

I micromho

(+/- 20%)

(0.5) e.

. l erwAe (4 t-x *4) ( Ova-nJM)

REFERENCE FNR System Descriptions 4.4, 7.4.

ANSWER J.07 (2.00) a.

The difference in the elevation between the top of the pool and the water level in the cooling tower sump.

(1,0) b.

Any tube leak will result in flow from the secondary side into the primary side of the heat exchanger.

(1.0)

REFERENCE FNR System Description 5.3.3.

t I

l l

(*****

CATEGORY J CONTINUED ON NEXT PAGE *****)

i

J.

SPECIFIC OPERATING CHARACTERISTICS Pcra-27

-ANSWER J.08 (2.00) 1.

Provides heating of primary coolant (should the temperature fall too low).

(1.0) 2.

Ready source of steam to clean the tubes within the heat exchanger (if an accumulation of minerals obstruct coolant flow).

(l'.0)

REFERENCE FNR Systems Description 5.3.3.

~

ANSWER J.09 (1.00)

Valve 1 - Shut (0.25)

Valve 2 - Open (0.25]

l Valve 3 - Open

[0.25]

Valve 4 - Shut (0.25]

REFERENCE FNR System Description Figure 11.1.

ANSWER J.10 (1.00) 1.

Thermal Column Door open.

(0.5) 2.

Shim Range.

(0.5)

REFERENCE FNR System Description 13.1.

I i

i

(***** CATEGORY J CONTINUED ON NEXT PAGE *****)

i

-J.

SPECIFIC--QEERATING CH&BACTERIEI1CS Phga 28 ANSWER ~

J 11 (2.50)

(Any five of the following at.5 each).

1.

Period safety - 5 seconds or less, 2.

Level safety - 120% (2.4 MW) or greater.

3.

High power (above 100 KW/no water flow)- a, 900 gpm or less, or b.

holding tank isolation valve not fully open.

or c.

holdup tank static pressure 1 psig below the full power value.

4, High power (above 100 KW)/ header down.

5.

Header up/no water flow - 900 gpm or less.

~

6.

Building exhaust radiation level - 1 mr/hr or greater.

7.

Bridge not clamped - when clamps released.

8.

Beamport door - opened when interlocked.

9.

Fuel vault criticality detector - 5 mr/hr or greater.

' REFERENCE Tech Specs Tab 1:

3.1.

System Description 13.1.1 ANSWER J.12 (2.50) 1.

Radiation monitoring equipment.

2.

Limited building lighting.

3.

Alarm systems.

4.

Ventilation system, 5.

Backup reactor air compressor.

6.

Bridge drive circuit.

7.

Heavy water tank control circuit.

8.

Telephone system.

9.

Pneumatic tube system.

(5 of the required @ 0.5 each : 2.5)

REFERENCE FNR System Description 14.

(***** END OF CATF'ORY J *****)

T Ki FUEL' HANDLING AND CORE PARAMEIERS Pcso 29 ANSWER K.01 (1.00)

To prevent fuel plate swelling which could result in clad rupture and release of radioactive fission products.

(1.0)

REFERENCE FNR Tech Spec 3.9.

ANSWER K.02 (1.00) 0.038 delta k/k.

(1,0)

REFERENCE FNR Tech Spec 3.1.

ANSWER K.03 (2,50) 1.

The chutdown margin relative to the cold xenon free critical condition [0.5) shall be at least.025 delta K/K (0.25) with all three shim safety rods fully inserted and the regulating rod fully withdrawn (0.75) and 0.0045 delta K/K (0.25) with the most reactive shim safety rod and the regulating rod fully withdrawn. [0.75).

(2.5)

REFERENCE FNR Tech Spec 3.1.

(*****

CATEGORY K CONTINUED ON NEXT PAGE *****)

r:

K.

FUEL HANDLING AND CQBE_EABAMETERE Pcg3 30 ANSWER K.04 (3.00)

The reactor shall not be nade critical unless:

1.

The reactor safety systems and safety related instrumentation are operable in accordance with Tables 3.1 and 3.2 including the minimum number of channels and the indicated maximum or minimum setpoints; 2.

All shim safety rods are operable; 3.

The time from the initiation of a scram condition in the scram circuit until the shim safety rods are fully inserted (release-drop time) shall not exceed 500 milliseconds; 4.

Mechanical devices are installed which prevent the lifting of fuel elements through the movement of control rods.

(4 @ 0.75-each = 3.0)

REFERENCE FNR Tech Spec - Pg. 11.

ANSWER K.05 (2.00) 1.

The total reactivity worth of all experiments shall not exceed 0.012 delta K/K.

(1.0) 2.

The reactivity worth of each experiment shall be limited as follows:

Movable 0.0012 delta K/K

[0.5)

Secured 0.012 delta K/K

[0.5]

REFERENCE FNR Tech Spec 3.1.

(***** CATEGORY K CONTINUED ON NEXT PAGE *****)

i

s K.

FUEL _BAEDLING AND COBE_EABadELEBS Pcga 31 1 ANSWER K.06 (2.00) 1.

All reactor fuel elements and fueled devices shall be stored in a geometric array which assures suberiticality.

(1,0) 2.

Irradiated fuel elements and fueled devices shall be in an array which will permit sufficient natural convection cooling by water or air such that the fuel element or fueled device temperature will not exceed 100 C.

(1.0)

REFERENCE FNR Tech Spec 5.4.

ANSWER K.07

(

The reactor would remain in automatic control.

A continuous cc If the control rod were at the upper limit, power i ^

drops 15% belot would continue to drift down due to xenon buildup, tod is inserted.

fuel burnup, or because of the negative reactivity that had made it decline to -5% initially.

Without REFERENCE operator action, the reactor would eventually shutdown completely.

FNR System Description 13.b.

If the control rod were not at the upper limit, it would respond normally to being below the setpoint, withdraw automatically, and restore power to the ANSWER K 08 (1.50) setpoint.levela.

( P.. C).)

a.

Stainless steel w/1.5% boron (0.75) b.

Hollow stainless steel shell (0.75)

REFERENCE FNR System Description 3.4.

ANSWER K.09 (2.00)

South end - utilized for retired fuel elements.

(1.0)

North end - utilized for partially depleted fuel element which can be reused in the reactor core.

(1.0)

(*****

CATEGORY K CONTINUED ON NEXT PAGE *****)

Ki__ FUEL HANDLING AND CORE PARAMETERS Pcg3 32 REFERENCE FNR System Description 3.8.

ANSWER K.10 (1.00) 1.

Permit circulation-cf cooling water.between fuel elements.

OR 2.

Supplement flow moving through the fuel element proper.

(Either answer acceptable for full credit)

REFERENCE FNR System Description 3.3.

e ANSWER K.11 (1.50) c.d f (0.5 each : 1.5, subtract 0.5 for each wrong answer up to 1.5)

REFERENCE OP-106, Pg. 4.

t i

l I

(*****

END OF CATEGORY K *****)

)

-4 L.

ADM1HISIB&TIVE EBOCEDURES. COdDITIONS Pcso 33 AND_LittlI&Il0HS ANSWER L.01.

(2.00) a; Anyone.

(0,5) b.

1.

Reactor console.

2.

On the wall inside the reactor basement.

3.

On the beamport floor by the north stairwell.

(3 @ 0.5 each = 1.5)

REFERENCE OP-101, Pg.

3.

ANSWER L.02 (1.50) a.

Announce the shutdown.

b.

Notify the Lead Operator onshift.

c.

If evacuation of the building is indicated, immediately initiate the Reactor Building Emergency Procedure.

(3 @ 0.5 each = 1.5)

REFERENCE OP-104, Pg. 6.

ANSWER L.03 (2.50) a.

Insert all rods, b.

Scram reactor, c.

Scram reactor, d.

Maintain power.

e.

Insert all rods.

(5 @ 0.5 each = 2.5)

REFERENCE OP-104, Pg.

7, 8.

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AD11HISTRAI1VE' EROCEQM(L QQ@lI1QM Pfga'34

&H LLIMITATIONS f

I ANSWER L.04 (3.50) a.

The safety limits shall assure that the integrity of the fr.ol clad is maintained.

(1.0)

The LSSS shall prevent the safety limits from being exceeded under the most severe abnormal situation. (1.0) b.

1.

380 Kw 2.

131 degrees F 3.

18 feet (3 @ 0.5 each : 1.5)

REFERENCE Technical Specifications 2.1 and 2.2.

ANSWER L.05 (1.00)

I '.

Shim rod reactivity measurements.

2.

Shim rod inspection.

(2 @ 0.5 each : 1.0)

REFERENCE OP-104, Pg.9.

ANSWER L.06 (2.00) 1.

Responsible for measuring the experiment's reactivity.

2.

Classifying it as movable or secured.

(2 @ 1.0 = 2.0)

REFERENCE AP-3, Pg. 4.

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ADMlHISIB&TIYE.EBQQEDUBEE d QHDlIlQHE Pcs3 35

&HD_LlHITATIONS ANSWER L.07 (1.50) a.

2.5 inches (0,5) Y N' b.

30 seconds (0.5) c.

1 MW (0.5)

REFERENCE OP-102, Pg. 2, 4.

ANSWER L.08 (1.00) 1.

Reactor will be shutdown by-insertion of rods.

2.

Three personnel access doors will be propped open.

(2 @ 0.5 each : 1.0)

REFERENCE OP 101 pg 3 ANSWER L.09 (1.00) a.

6 inches (+/- 1 in.) (0,5) b.

10 seconds (+/- 1 sec.)

(0.5)

. REFERENCE OP-106, Pg.

1.

OP-108, Pg. 7 ANSWER L.10 (2.50) 1.

Pushing the console scram button.

2.

Placing the rod drive switches in the insert position.

3.

Verify that a scram has occurred.

4.

Turning off pneumatic blower if it is running.

5.

Removing magnet key and retaining it and the logbook.

(5 @ 0.5 each : 2.5)

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D Lt.__4D61HIEIBAI 3E_PROCEQQBEE d QEDlIIQHS.

Pcg3 36 AND LIMITAT"ONS REFERENCE OP-101, Pg. 4.

ANSWER L.11 (2.00) a.

(.5 each) 1.

Whether the radiation levels were normal prior to the fire.

2.

Location of any high level radiation sources.

3.

Whether the MAP monitors were alarming at the time of the building evacuation, b.

Issue film badges to fire department personnel.

(0.5)

REFERENCE OP-101, Pg. 6, 7, I

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TEST CROSS REFERENCE Pega 1

QUESTIQH

_.YEEE BEEERENCE

H.01 1.00 ZZZ0000001 H.02 2.00 ZZZ0000002 H.03 2.00 ZZZ0000003 H.04

-2.00 ZZZ0000004 H.05

-1.50 ZZZ0000005 H.06 1.00 ZZZ0000006

'H.07 2.50 ZZZ0000007 H.08 1.50 ZZZ0000008 H.09

-2.00 ZZZ0000009~

H.10 1.00 ZZZ0000010~

H.11 2.50 Z7,Z0000011 19.00 1.01 1.50 ZZZ0000012 I.02-2.00 ZZZ0000013 I.03 1.50 ZZZ0000014 I.04-1.00 ZZZ0000015 I.05 1.50 Z220000016 I 06 1.50 ZZZ0000017 l

1.07 0.50 ZZZ0000018 I 08 1.50 ZZZ0000019 I.09 1.50 ZZZ0000020 I.10 2.50 ZZZ0000021 I.11 1,50 ZZZ0000022 i

I.12 3.75-2ZZ0000023 20.25 J.01 1.00 ZZZ0000024 l

J.02 2.00 ZZZ0000025 J.03 2.00 ZZZ0000026 J.04 1.00 ZZZ0000027 J.05 2.00 ZZZ0000028 J.06 2.50 ZZZ0000029 J.07 2.00 ZZZ0000030 J.08 2.00 ZZZ0000031 J.09 1,00 ZZ20000032 J.10 1.00 ZZZ0000033 J.11 2.50 ZZZ0000034 J.12 2.50 ZZZ0000035 21.5C K.01 1.00 ZZZ0000036 K.02 1.00 ZZZ0000037 K 03 2.50 ZZZ0000038 K.04 3.00 ZZZ0000039 K.05 2.00 ZZZ0000040 K.06 2.00 ZZZ0000041 K.07 2.00 ZZZ00000'4 2 K 08 1.50 ZZZ0000043 K.09 2.00 ZZZ0000044 K 10 1.00 ZZZ0000045 K.11 1.50 ZZZ0000046 L

p TEST CROSS REFERENCE Pega 2

QLIISTION

_y& idle BEEEBEEE.,-

19.50 L.01.

2.00

%ZZ0000047'

L.02 1-50 ZZZ0000048 L.03 2.50

-ZZZ0000049 L.04 3.50 ZZZ0000050 L,05 1.00 ZZZ0000051-L.06 2.00

-ZZZ0000052 L.07 1.50 ZZZ0000053 L 08 1.00

.ZZZ0000054 L.09-1.00 ZZZ0000055 L.10 2.50 ZZZ0000056 L.11' 2.00 Z220000057-20.50 Se__me 100.7 r

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