IR 05000225/1987002

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Exam Rept 50-225/87-02(OL) on 871201-02.Exam Results:One Senior Reactor Operator Passed Written & Operating Exam & One Failed Operating Exam
ML20149M726
Person / Time
Site: Rensselaer Polytechnic Institute
Issue date: 02/01/1988
From: Keller R, Norris B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20149M677 List:
References
50-225-87-02OL, 50-225-87-2OL, NUDOCS 8802290010
Download: ML20149M726 (50)
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U.S.NUCLEARREGULATORYCOMMISSIONREGIONI

. OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N /87-02(0L) ,

FACILITY DOCKET N FACILITY LICENSE N CX-22 LICENSEE: Rensselaer Polytechnic Institute Troy, New York 12181 FACILITY: Rensselaer Polytechnic I?stitute EXAMINATION DATES: December 1-2, 198 CHIEF EXAMINER: g_ * ,7f1(

nrry ' Norris, Senior Operations

. Da(e Eng neer (Examiner / Inspector)

r APPROVED BY: ) F /jdp[

Robert M. Keller, Chief . Date ;

PWR Section, Division of Reactor Safety ,

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SUMMARY: Written and operating examinations were administered to two Senior !

Reactor Operator (SRO) candidates. Gne candidate failed the operating

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examination, the other candidate was issued a licens !

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8802290010 08C219 )

PDR AEK}CK 050K)0225 +

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EXAMINATION DETAILS TYPE OF EXAMINATIONS: Replacement EXAMINATION RESULTS:

l SR0 l l Pass / Fail l l l l 1 l ~ ~ ~ ~

l Written Exam l 2/0 I l i I I I I

[0perating Examl 1/1 l 1 I I l l I l0verall l 1/1 l l 1 _l EXAMINER AT SITE: L. S. Defferding (PNL) Personnel Present at Exit Interview:

NRC Contractor Personnel L. S. Defferding (PNL)

Facility Personnel P. Rodriquez, Operations Supervisor The written examination was reviewed by the facility after the candidates t had completed the examination. The reviewer was P. Rodriquez. The facility comments and the NRC resolution to those comments is enclosed as Attachment Attachments: SRO Written Examination and Answer Key Facility Comments and NRC Resolution on Written Examination

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V. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION .

FACILITY: RENSSELAER REACTOR TYPE: TEST DATE ADMINISTERED: 87/12/01 EXAMINER: UPTON, CANDIDATE: FINAL INSTRUCTIONS TO CANDIDATE:

Use separate paper for the answers. Write answers on one side onl 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 least 70% in each category. Examination papers will be picked up six (6) hours after the examination start % OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGODY 20.00 20.00 H. REACTOR THEORY 20.00 20.00 I. RADIDACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS 20.00 20.00 J. SPECIFIC GPERATING CHARACTERISTICS .

20.00 20.00 K. FUEL HANDLING AND CORE -

PARAMETERS 20.00 20.00 L. ADMINISTR;TIVE PROCEDURES, CONDITIONS AND LIMITATIONS 100.00  % Totals finai Grade All work done on this examination is my ow I have neither given nor received ai Canaidate's Signature

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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS ,

During the administration of this examination the following rules apply: Cheating on the examination means an automatic denial of your application ;

and could result in more severe penaltie ,

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 cheatin . Use black ink or dark pencil only to facilitate legible reproduction ' Print your name in the blank provided on the cover sheet of examination.

i Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answer . Print your name in the upper right-hand corner of the first page of each section of the answer shee , 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 shee . Number each answer as to category and number, for example, 1.4, 6.3.

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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 tabl . Use abbreviations only if they are commonly used in facility literatur ,

- 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 require . Show all calculations, methods, or assumptions used to obtain an answer

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to mathematical problems whether indicated in the question or no .

15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.

! 16. If parts of the examination are not clear as to intent, ask questions of l j the examiner onl l

! 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 i

completing the examination. This must be done after the examination has i

been complete '

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18. When you complete your examination, you shall:

a. Assemble your examination as follows:

(1) Exam questions on top.

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(2) Exam aids - figures, tables, et (3) Answer pages including' figures which are part of the answer, i 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 examine If after leaving, you are found in this area while the examination is still

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in progress, your license may be denied or revoke f d

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, REACTOR THEORY ,

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QUESTION H.01 (1.00) j If a fission fragment decayed by two successive beta-minus 1 i

' emissions to 62-Sm-149, the originel fission fragment was:

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(CHOOSEthecorrectstatementbelow.) (1.0)

i i (a.) 62-Sm-15 (b.)-62-Sm-147.

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(c.) 60-Nd-149.

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(d.) 64-Gd-149.

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s QUESTION H.02 (1.00)

If the reactor power increased by 1/2 decade in one minute, WHAT would be the reactor period? (1.0) ,

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QUESTION H.03 (2.50) t The "in-hour" equation, as given below, relates reactivity to

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reactor perio i

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', WHY does the sum go from 1 to 67 (1.0) l r

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l QUESTION H.04 (1.50) .

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figure H-1 provides the graphical relationship for the RPI facility between reactivity and reactor period. If the reactor period were l t measurea as 30 seconds, WHAT would be the value of k-eff for the L core? (1.5) ;

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PERIOD IN SEC0!OS

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. REACTOR THEORY PAGE 3

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QUESTION H.05 (2.00)

WHY is excess reactivity needed for routine operationsi GIVE four (4) reason (2.0)

QUESTION H.06 (1.50)

In the process of calibrating the control rods, the technique of suberitical multiplication is typically used. To use the suberitical multiplication technique, the countrate from a detector due only to the source must be know From the following information, DETERMINE the value of the countrate due to the source alon (1.5)

critical rod position = 19.0 in, withdrawn differential rod worth at 19.0 in. = 30 c/i at 18.8 in. countrate = 2000 cps QUESTION H.07 (2.00)

EXPLA:N the impact of increasing the temperature of the reactor core on the "resonance escape probability" factor, "p". That is, HOW and WHY does resonance escape probability p change with an

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increase in the temperature of the reactor core? (2.0)

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QUESTION H.08 (1.00) r a

A moderator is necessary to slow neutrons down to thormal i energies. WHICH of the following is the correct reason for  ;

a reactor operating with thermal instead of fast neutrons?  :

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l (a.) Increased. neutron efficiency since thermal neutrons are less >

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likely to leak out of the core than fast neutron (b.) Reactors operating primarily on fast neutrons are inherently unstable and cannot be safely controlle l I

4 (c.) The fission cross section of the fuel is much higher for j thennal energy neutrons than fast neutrons, j 4 i

(d.) Doppler and moderator temperature coefficients become positive j as neutron energy increase (

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QUESTION H.09 (1.50) f

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) Specify TRUE or FALSE for each of the followin [

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I Reactivity effects of placing samples of boron in the core I are used to calibrate the core in order to determine the i neutron absorption cross sections of other 1/v material (0.5) -

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! The primary impact on k-eff of placing boron samples in the i core is on the "resonance escape probability" factor "p". (0,5) i

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' The reactivity effects of the boron samples are measured by

noting the difference in critical position of a calibrated ,
control rod located as far away as possible from the test f
locatio (0,5) ,

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r4!ESTION H.10 (1.50)

i If B-eff for the RPI Critical Facility reactor was reduced from [

i the actual 0.0077 to 0.0055, HOW and WHY would the reactor j l respond to a small addition of positive reactivity? (1.5) 9 I I 1 t

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. REACTOR THEORY PAGE 5

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QUESTION H.11 (2.00)

Assume the reactor is operating at 270 watts power and a boron strip worth 60 cents falls out of the core. The reactor power takes a prompt jump to 675 watts followed by a subsequent power rise on a 6.7 perio WHY is there a prompt jump and a period-type of response? (1.0) If a scram were not initiated for 8.6 sec, WHAT power level would the reactor obtain? (1.0)

QUESTION H.12 (2.50)

Assume that the reactor power level changes linearly in time from 675 to 3000 watt HOW MUCH energy in Btu would be produced during the second excurston? (1.5) Assume that your answer to part "a." was 20 Btu, that there was no heat transfer from the fuel during the excursion, that the specific hest of the fuel was 0.12 Btu /lbm deg F, and that the weight of the fuel was 10 lbm. WHAT would be the rise in fuel temperature? (1.0)

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. l RADIOACTIVE HATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 6 l ~

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QUESTION I.01 (2.50) l The RPI Critical Facilit uses an Area Radiation Monitoring System to ensure radiolo ical safety. LIST the' locations of '

the four (4) detectors ( hannels) and INDICATE which channel has the highest trip setpoin (2.5) '

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QUESTION I.02 (2.00) l l

i l LIST the two (2) classes of radiological emergencies as defined i

! in the emergency procedure (2.0)

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QUESTION I.03 (1.00)

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Water from released to the river directly via two the RPI Critical Facility may(2) routes. WHAT  :

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are the two (2) sources / locations from which the water releases can occur? (1.0) -

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j QUESTION I.04 (2.00)  ;

1 The radiation level due to a known small radioactive deposit in j a pipe fitting is 1 r/hr (gamma) measured 15 feet away. An 4 operator must operate a valve located 5 feet from the pipe fittin WHAT is the dose rate at the valve? (1.0) , If it takes the operator 2 minutes to operate the valve,

WHA 7 radiation dose (mrem) will the operator receive? (1.0)

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QUESTION I.05 (1.00)  ;

! ANSWER TRUE or FALSE for each of the following statement !

' If the vault were loaded with the total inventories of

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. HEU fuel plates and LEV fuel pins for the new core, -

k-inf would be less than 0.90 under flooded condition (0.5) ,

~ Criticality in the fuel storage vault is monitored by l

radiation detector on the reactor dec (0.5) l

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! In accordance with the Emergency Procedures, WHAT two (2) l l radiological conditions will require that the reactor be  !

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QUESTION I.07 (1.00) l Whenever the reactor is operated, the particulate activity monitor

is used. ANSWER the following questions with respect to the .

particulate monito '

j i i Air, for the sample, is drawn from WHAT location? (0.5)

WHAT type of radioactivity is measured (neutron, alpha, i l beta,orgamma)? (0,5)

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I QUESTION I.08 (1.50)  ;

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Sn (2) identical samples are irradiated in the same flux; l me for 20 minutes, and the other for 10 minutes. WILL the l 20-minute sample contain exactly twice the activity of the  !

10-minute sample? EXPLAI (1.5) i

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PAGE 8 RADIOACTIVE MATERIALS HANDLING OISPOSAL AND HAZARDS

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QUESTION I.09 (1.50)

A radiation source emits 0.90 MeV gamma rays and produces a reading of 10 rad /h on a detector 3 feet away. What thickness of lead shielding is required to be placed between the source and the detector to reduce the reading to 5 mrad /h? Assume that the tenth value layer (TVL) for lead is one (1) inc (SHOWyourwork.) (1.5)

QUESTION I.10 (3.00)

Based on 10 CFR 20, WHAT are the maximum allowable exposure quarterly limits for the whole body, extremities, and skin for a radiation worker who has an NRC Form 4 on file? (3.0)

QUESTION I.11 (2.00)

PROVIDE the definitions of the following two (2) terms that pertain to radiolo;ical protectio (2.0) rad rem QUESTION !.12 (1.50)

EXPLAIN the operation of a thermoluminescent dosimeter, or TLO, i.e., what is measured and how? (1.5)

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PAGE 9 SPECIFIC OPERATING CHARACTERISTIC .

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QUESTION J.01 (1.00)

DESCRIBE HOW the presence of a neutron is detected in a DF-3

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detecto (1.0)

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QUESTION J.02 (1.00)

l When the reactor console switch is turned on:

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(a.) all scrams are cleared in the safety system, and power is supplied to the control rod magnets.- f i

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(b.) the scram circuits are activated, and power is supplied to the

! control rod magnet l (c.) the scre.m circuits are activated, and any watse dump bypass is ,

f i remove .

(d.) all scrams are cleared, and any water dump bypass is remove ;

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! The solenoid current to the dump valve is:  ;

(CHOOSEthecorrectstatementbelow.) (1.0)  ;

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~l (a.)90to110mADCtoholdthevalveclosedanddropstozero -

to open the valve due to a scram signa l

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(b.) zero mA when the valve is closed and changes to 90 to 110 mA  !

DC to open the valve due to a scram signa .{-

! (c.) 3 A, 40C Hz to hold the valve closed and drops to zero to open l i the valve due to a scram signa !

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i i 4 (d.) zero A when the valve is closed and changes to 3 A, 400 Hz to '

l open the valve due to a scram signal.

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! SPECIFIC OPERATING CHARACTERISTICS

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QUESTION J.04 (1.50)

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According to the Operating Procedures, no more than four (4)

control rods may be withdrawn simultaneously as a ban l

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, (4) rods as a bank? -(1.0)

i What is the steady rate of withdrawal for a control r<>d

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QUESTION J.05 (1.50)  ;

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i There are three (3) scram functions that have the built-in capability of being placed in bypass. LIST these three (3)

i function (1.5)

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! QUESTION J.05 (2.00)

i The following four (4) statements (a, b, c, and d) refer to the ,

a Solenoid Interrupt Circuit. Respond to each with TRUE or FALS ;

! If one of the electrical leads in one of the instrument i

scrams' external contacts broke (open circuit), it would

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cause a scra (0.5) r i If one of the electrical leads in one of the manual scrams'

- external contacts broke (open circuit), it would cause a  !

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scra (0.5)

, The rectified DC current flows through two series instrument- ,

scram relays, the opening of either of which would cause a i

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If one of the electrical leads in one of the c rol rod

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solenoid circuits broke (open circuit), it would cause all i of the control rod to dro (0.5) ,

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QUESTION J.07 (1.50)

Shown in the upper half of Figure J-1 is an outline of one quadrant of core A. On the lower half of the figure is an empty graph drawn to the same radial scale as the core outline. On the lower-half graph, SKETCH the relative neutron flux variations for the fast neutron flux AND the thermal neutron flu (1.5)

QUESTION J.08 (1.50)

WHAT are the three (3) steps required to determine the overall temperature coefficient of reactivit (1.5)

QUESTION J.09 (1.00)

The Limiting Conditions for Operation include the specification that: (CHOOSEthecorrectstatementbelow.) (1.0)

(a.) the excess reactivity of the reactor core above cold, clean critical shall not exceed $0.6 (b.) the maximum control rod reactivity rate shall be less than

$0.05/see up to 10 times the source level and less than

$0.12/see at all higher flux level (c.) the normal moderator / reflector water level shall be

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established such that the auxiliary reactor scram shall add negative reactivity within one minute of its activation.

(d.) the reactor shal' be subtritical by at least $5.50 with the most reactive control rod fully withdraw QUESTION J.10 (1.00)

The excess Core reactivity (CM00SE the correct statement below.)at 68 B to be about: deg F is calcula (1.0) ,

(a.) 0.00053

! (b.) 0.0046 l (c.) 0.018 (d.) 0.023

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QUESTIONJ.07 Upton, .

RPI

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QUESTION J.11 (1.00)

The shutdown margin is calculated'for the LEU Core 81 to be:

(CHOOSEthecorrectstatementbelow.) (1.0)

(a.) 0.00053 (b.)0.0046 (c.) 0.018 (d.) 0.023 QUESTION .J.12 (1.50)

For the new LEU core HOW many control rods are used? (0.5) WHAT is the worth of each control rod? (0.5) . WHAT is the drive length of each control rod? (0.5)

QUESTION J.13 (2.50)

The following parts of this question pertain to the reactivity worth of the centrol rod SKETCH a control rod differential worth curve, and EXPLAIN the reason for the shap (1.5) If, near the end of its withdrawal range, a control rod had a rod worth reversal. (Rod worth reversal means that a '

control rod withdrawal would result in a decrease in reactivity.) WHAT could cause this rod reversal? (1.0)

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PAGE 13 SPECIFIC OPERATING CHARACTERISTICS

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QUESTION J.14 (1.00)

According to the Limiting Conditions for Operation with respect to reactor parameters, the minimum operating temperature shall be such as to ensure that above that temperature:

(CHOOSE the correct statement below.)

(1.0)

.(a.) the core has a negative isothermal temperature coefficien (b.) the core has a negative void coefficien (c.) the core would require the addition of no more than $0.15 in reactivity to reach a negative isothermal temperature coefficient conditio (d.) three (3) control rods inserted (assuming the minimum number of 4 rods with 1 stuck out) into the core would be sufficient to shutdown the reacto QUESTION J.15 (1.00)

If a previously-untested type of control rod were inserted into the core, several parameters shall be determined in order to comply with the Technical Specifications. One such parameter shall be the control rod and control rod bank reactivity worth LIST two (2) other parameters that must be determine (1.0)

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. FUEL HANDLING'AND CORE PARAMETERS PAGE' 14

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QUESTION K.01 (1.00)

Suberitical multiplication, M, is defined as the ratio of neutron. fluxes (or their corresponding countrates). SPECIFY the numerator and the denominator of this rati (1.0)

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QUESTION K.02 (2.50)

Figure K-1 shows several 1/M plots for fuel loadin WHICH of the three curves is considered to be the LEAST conservative when predicting criticality? (0,5) EXPLAIN the conditions that would produce the shape of

, cu'rve No. 3 instead of that of curve No. (1.0) Assume that curve No. 2 was obtained with all control rods inserted into the core. Using the same source size and location and the same detector sensitivity and location, DRAW on Figure K-1 the 1/M curve for the condition of all-rods-ou (1.0)

QUESTION K.03 (1.50)

One of the guidelines of the fuel loading procedure states:

Fuel additions will be limited to one-half the difference between the loaded mass and the extrapolated critical mass or to four (4)

stationary elements, whichever is lowes WHY is this fuel load critepia used? (1.0) WHY is the other criterion set on the addition of 4 fuel elements? Why not 3 or 57 (0.5)

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w/ \

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FIGUPE V-1

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- - - - - , - - - -

_- .- c, -,. -- , ,

_-

.

. FUEL HANDLING AND CORE PARAMETERS PAGE 15

.

QUESTION K.04 (1.00)

CHOOSE from the list below the one item that is NOT in accordance with fuel load procedure (1.0)

(a.) After the minimum critical mass is attained, fuel additions will be limited to one (1) fuel elemen (b.) Each fuel element will be added in a lattice position such that the minimum surface to volume ratio is achieve (c.) The number of elements to be added at any given step should not exceed that of the previous ste (d.) The control rod assemblies are loaded after the fuel elements have been loaded to obtain the minimum critical mas QUESTION K.05 (2.00)

For the following material and worth restrictions on placing experiments in the RPI Critical Facility fill-in-the-blank For movable experiments with an absolute worth greater than $0.35, the maximum reactivity change for withdrawal and insertion shall be $ /sec. Moving parts worth less than $0.35 may be osciiTated at higher frequencie in the cor (0.5) The maximum positive step insertion of reactivity which can be caused by an experimental accident or experimental equipment failure of a movable or unsecured experiment shall not exceed $ . (0.5) Experiments shall not contain a material which may produce a' chemical reaction and/or radioactivit (0.5) Experiments containing known or highly flammable materials shall not be installed in the reacto (0.5)

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

i

.

.

O FUEL HANDLING AND CORE PARAMETERS PAGE 16 [

QUESTION K.06 (1.00)

The RPI facility was informed of the accident at the Argentine j Critical Facility (RA-2) that occurred on September 23, 198 l The report of the accident stated that: r (CHOOSEthecorrectstatementbelow.) (1.0) !

(a.) one operator received a lethal, absorbed dose of about i 100 rad of neutrons and 40 rad of gamm ;

(b.) the moderator was not completely removed from the core i before the core configuration was modifie '

(c.) the excursion occurred when a control rod was remove ;

(d.) the operating procedures were correctly followed but poorly writte I QUESTION K.07 (2.00)

A 5-curie neutron source is used at the RPI Critical Facilit i ANSWER the following parts of this question concerning that sourc j

' DESCRIBE the nuclear processes by which the source produces neutron (1.0) [ Over what period of time would the activity of the neutron  !

source be reduced to 2.5 curies? For your answer, CHOOSE  !

from 1 month, 1 year, 10 years, or 100 year (0,5)

' HOW PANY neutrons /sec are emitted by this source? For your answer, choose from 10**2, 10**7, 10**11, or 10**1 (0.5) ,

'

!

B'

QUESTION K.08 (1.00) ,

LIST the two (2) separate ways that fuel should be controlled by l the fuel handle (1.0) i

!

!

.

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

t

_ _ . . ,_ _ _

_ __ . _ _ . _ _

.

.

. FUEL HANDLING AND CORE PARAMETERS PAGE 17

QUESTION K.09 (1.00)

Respond to each with TRUE or FALS The core structure consists of a thick top plate which is drilled through with 1/2-inch diameter holes on the prescribed pitch for the fuel pin (0.5) The core structure consists of a fuel pin support plate drilled with 1/4-inch diameter holes to accept the tips of the fuel pin (0.5)

.

QUESTION K.10 (3.00)

SPECIFY the following core parameters for a Spert fuel pin or ro (3.0) rod overall length cladding outside diameter active fuel length fuel pellet chemical form (name or formula) fuel pellet enrichment cladding material QUESTION K.11 (2.00)

FILL-in-the-blank Housed in each of the control rod "baskets" is the "absorber."

Number of absorber sections in each control rod .,_ (0.5)

Absorber material (0.5)

Absorber contained in (0.5)

Cladding material _ (0.5)

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

, - .- ,,.- .- . . - - - . _ . . , - ---. - - - - - - , .

.. * ,

FUEL HANDLING'AND CORE PARAMETERSL PAGE 18

- K .

QUESTION K.12 (2.00) For a reactor that is over mojerated'the introduction of i void into.the core will cause (POSITIVE or NEGATIVE)

reactivity citang .(0.5) Voids introduced into the core of the RPI critical facility  ;

will cause a.(POSITIVE or' NEGATIVE) in reactivit (0.5):

' HOW are volds introduced into the core of the RPI critical facility.during an experiment to determine the void coefficient? (1,0)

l l

'

,

i

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i

,

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

'

.

I

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L. ' ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 19

.

QUESTION L.01 (2.00).

Assume during operation of the Critical Facility, water is observed leaking from the moderator tank. WHAT are your four (4) immediate actions? (2.0)

QUESTION L.02 (1.00)

According to the Technical Specifications as approved by the NRC on July 1987, the thermal power and the integrated therm 6 power for any given 365 days.are limited. WHAT are these two limits? (1.0)

QUESTION L.03 (1.50)

The Technical Specifications itemize three conditions that must be satisfied in order to consider that the reactor is "secured."

LIST these three (3) condition (1.5)

QUESTION L.04 (1.00)

According to the Technical Specifications, the reactor meets the definition of "shutdown" if:

(CHOOSEthecorrectstatementbelow.) (1.0)

(a.) the Licensed Senior Operator (LS0) on duty is within 15 mil 6s of the facility, and all control rods are inserted into the reacto l (b.) the Licensed Senior Operator (LS0) on duty is within 30 minutes travel time of the facility, and the excess reactivity is less than $1.0 (c.) the control rods are inserted, and the moderator dump valve is ope (d.) the reacto- is suberitical by at least $1.00, and the control rods are inserte (***" CATEGORY L CONTINUED ON NEXT PAGE *****)

_ _ _ _ - - _ _ _ _ _ _ _ _ _ - - _ _ _ _ - _ _ _ - _

. - __ . . .

.  !

l

. ADMINISTRATIVE' PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 20

?

QUESTION L.05 (1.00)

t certain calibration has been conducted on November 15th and December.1st. This calibration has a Surveillance. frequency requirement that is "weekly;" the Surveillance Interval is 10 days. By WHAT date must the next calibration bc conducted? (1.0)

QUESTION L.06 (1.50)

SPECIFY the limiting safety system settings required by the Technical Specifications for: (1.5) maximum power level minimum flux level s minimum period QUESTION L.07 (2.00)

t According to the Limiting Conditions for' 0peration, four "channels" of scram shall be operating during reactor operation (neglecting any bypasses authorized for maintenance checks and radiation surveys). SPECIFY these four (4) channels of scra (2.0)

QUESTION L.08 (2.00)

According to the Limiting Conditions for Operation, certain interlocks shall be operable during reactor operations. Five (5)

of these interlocks prevent control rod withdrawal but do not cause a reactor scram. LIST four (4) of these interlock (2.0)

.

QUESTION L.09 (1.00)

WHAT types of fires can a CO2 # ire extinguisher in the reactor room be used to extinguish? (1.0)

l 1

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

i

,

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r- --

r r , -,,-- ,

. . . - .

.

.

ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 21 ,

QUESTION L.10 (1.50) 1 In the Code of Federal Regulations, 10 CFR 50,.the terms "safety limit" and "limiting safety system setting" are defined. Based on those definitions, specify if each of the statements below is TRUE or FALS (1.5) If a-safety limit had been exceeded, the licensee shall notify the Commissio Operation shall not be resumed until

,

authorized by the Commissio If a limiting safety system setting has Deen exceeded, the licensee shall notify the Commissio ' For each limiting safety system setting for a process variable, there is a corresponding safety limit for that variabl QUESTION L.11 (.50)

ANSWER TRUE or FALS According to the RPI emergency procedures, in case of a bonafide accident involving risk of life or limb or destruction

of valuable property an adult can be given a one time exposure ,

of up to 25 rem (0.5)

.

QUESTION L.12 (1.00) l According to the Technical Specifications, there is a minimal staffing requirement when the reactor is not shutdown. Specify l

this staffing requiremen (1.0)

QUESTION L.13 (1.50)

According to the emergency procedures "any radiological "

emergency shall include immediate notification of

-

.

,

LIST these three (3) persons that must be notified (by position). (1.5)

'

I (***** CATEGORY L CONTINUEDONNEXTPAGE*****)

i

!

. - - - -

. - -

., - - - - . - ,. .-. , , . , ~ . . . , , ,

- .- - .- . - - ~ _ .

.

. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 22 v

QUESTION L.14 (1.00)

According to the Operating Procedures, chhhhanges to the core configuration that involve the movement (insertion or removal) -

of control rods will be under the direct control of:

(CHOOSE the correct statement below.) (1.0)

(a.) the licensed operator in the control roo (b.) the senior operator on dut (c.) the reactor facility superviso (d.) the Director, Office of Radiation and Nuclear Safet QUESTION L.15 (1.00)

The following step / action is part of the Pre-startup Procedurcs and Checklist. WHY is this step performed? (1.0)

Adjust the fine voltage setting on the startup channels +/- 50 -

volt .

4- ,

QUESTION L.16 (.50)

According to the Operating Procedures, WHAT is the acceptable range of positive period for increasing reactor power level? (0.5)

<

i

,

(***** END OF CATEGORY L *****)

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

i

._ . . _ . . . . _ _ . ..

.

.

j

___.. .........__.___...____.....___ ........._____.....______.........._ EQUATION SHEET

..____...._.......___...........__............_......__....__..._____.......

'

. .

-Where mi = m2 (density)3(velocity)3(area); = (density)2(velocity)2(area)2

............._...._.._....._.........____...__......._.........__._..... _ .

PE1 + KE1+P73V = PE +KE where V = specific KE="{2 PE = mgh 2 2+P22 Y volume Pressure

.............._ _.....__...__......__._...._....___..._.......__....__._....

.

.

Q = mcp(Tout -Tin) Q = UA 4T ave -Tstm) Q=m(h-h)i 2

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

P = Po 10(SUR)(t)

t P = Po e /T SUR = 26.06 T = (B-o)t p

T

.__......________.____.._ ........._-____. _..__ ..__.... ___..._........... '

delta X = (K,ff-1) CRi (1-K,ffy) = CR2 (1-Keff2) CR = S/(1-K,ff)

(1-Keff1) (1-Keff) x 100%

!

SOM =

h,e f f a

M = (1-Keff2)

...... __.... _____..__________.....________... _ ....__. ___.........__.... 7

-

decay constant = in (2)- = 0.693 1 I A 1 = A0 e (decay constant)x(t)

!

1/2 I/2

........__ ....____ .___.. __.. __________..........__....____......._ .....

Wa'ter Parameters Miscellaneous Conversions

>

'

1 gallon = 8.345 lbs 1 Curie = ?.7 x 10 dps  ;

1 gallon = 3.78 liters 1 kg = 2.21 lbs

,

I ft = 7.48 gallons I hp = 2.54 x 103 Btu /hr I 3 6 n ensity=62.4lbg/ft 1 KW = 3.41 x 10 Btu /hr Oensity = 1 gm/cm 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters 2 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft_lbm/lbf.sec  !

.______......______... _____................_....... ____...................

.

. . - - -. . - . - - - . _ - _ . - _ _ _

.

. REACTOR THE0RY PAGE 23

'

ANSWERS -- RENSSELAER - 87/12/01-UPTON, ,

ANSWER H.01 (1.00) ,

(d.) [+1.0]

REFERENCE Generic: "Academic. Program for Nuclear Power Plant Personnel,"

Volume II, Physics, General Physics Corporation, pp. 3-62 to 3-66.

-

ANSWER H.02 (1.00)

T=t/{ln(p-2/p-1)}

=60/{ln(5)}

= 60/1.61

= 37.3 sec (0.621 min) [+1.0)

REFERENCE RPI: "A Manual of Experiments for the Rensselaer Reactor Facility," Richard M. Kacich, May 1975, p. 37.-

.

=

t - - - - -

.m, rr - - ,e-- + , , , -, , , ,e4, ,--,,,,,r ,3-+ -

--*.v-+ --

a ee w-

_ . _

.-

)

J e

H .~ REACTOR THEORY ~

PAGE 24~

.

ANSWERS -- RENSSELAER -87/12/01-UPTON, ANSWER H.03 (2.50) * = prompt neutron generation time beta-i = average fraction of neutrons per fission due to the i-th group of delayed neutrons ,

lambda-i = decay constant for the i-th group of delayed neutrons

[+0.5each] . There are six predominant groups of delayed neutrons, i.e.,

the fission process can be adequately de. scribed by assuming six radioactive decay chains that generate all-of the delayed neutron [+1.0]

REFERENCE RPI: "A Manual of Experiments for the Rensselaer Reactor _

Facility," Richard M. Kacich, May, 1975, pp. 37,3 i Generic: "Nuclear Reactor Engineering," Samuel Glasstone'and Alexander Sesenske, 1963, pp. 93, 233-25 ANSWER H.04 (1.50) l using Figure H-1, 30 sec = 22.5 c [+0.5 for 22 to 23 c]

rho = $ (beta-eff)

(0.225)(0.008)

'

0.00180 (0.002 or 0.0018) [+0.5, using the value of cfromabove]

k-eff = 1/(1 - rho)

1/(1-0.00180) l 1.00180 (1.002or1.0018) [+0.5, using value for ,

'

rho from above]

REFERENCE RPI; "A Manual of Experinents for the Rensselaer Reactor Facility," Richard M. Kacich, May, 1975, p. 4 . . . - . . . - .. .

.

. REACTOR THEORY PAGE 25

> ANSWERS -- RENSSELAER -87/12/01-UPTON, ANSWER H.05 (2.00) ., to overcome negative power coefficients to overcome neutron losses (poisons / leakage)

' to give operating flexibility rate; (i.e., permit power increases at a reasonable rate) to compensate for fuel burn-up to accommodate negative reactivity of experiments Any four (4) [+0.5] each, +2.0 maximu .

REFERENCE RPI: Manual of Experiments for Rensselaer Reactor Facility, p. 3 .

H.06 i ANSWER (1.50)

delta-k = (0.2 in.)(30 c/in.)

(0.008 beta was used in

= 0.06 $ calculation. A reasonable

'

= (0.06)(0.008) = 0.00048 [+0.75] acp$ )

C-s = C-t (delta-k) .

)

= (2000 cps)(0.00048) j

.

= 0.96 cps [+0.75] l REFERENCE RPlh "A Manual of Experiments for the Renssslaer Reactor Facility," Richard M. Kacich, May, 1975, pp. 44-46.

i i

l

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PAGE 26~

' REACTOR THEORY s

ANSWERS -- RENSSELAER -87/12/01-UPTON, ANSWER H.07 (2.00)

As the temperature of the core (including the fuel _ pins) increases, the value of p decreases [+0.5]. This occurs because of the Doppler effect in U-238 [+0.5]. The Doppler effect is the term applied to the effective broadening and lowering of the microscopic cross section for neutron absorption [+0.5] because of the higher average neutron er.crgy [+0.5].

REFERENCE RPI: "A Manual of Experiments for the Rensselaer Reactor Facility," Ricnard M. Kacich, May, 1975, pp. 59, 6 .

ANSWER H.08 (1.00)

(c.) [+1.0]

REFERENCE , RPI: Principles of Nuclear Reactor Engineering, Glasstone, Sect!.on 1.6 ANSWER H.09 (1.50)  : TRUE [+0.5] FALSE (An absorber primarily affects the thermal utilization f actor.) [+0. 5] TRUE [+0.5]

REFERENCE RPI: "A Manual of Experiments for the Rensselaer Reactor  !

Facility," Richard M. Kacich, May, 1975, pp. 6-1 to 6- i

,- -

, . ,_ _ - . . _ . -,--, - - - - .

.

..Q PAGE 27 REACTOR THEORY e

ANSWERS -- RENSSELAER-87/12/01-UPTON, ANSWER H.10 (1.50)

-The reactor would respond faster [+0.5], because of the shorter average neutron lifetimes [+1.0]. ,

REFERENCE

' RPI: Manual of Experiments for Rensselaer Reactor Facility, pp. 38 and 39.

.

ANSWER H.11 (2.00) The prompt jump is the change in the power level due to the prompt neutrons only [+0.5]. The period type response is i determined largely by the properties of the delayed neutrons

[+0.5]. p-2=(p-1)exp(t/T) [+0.5]

= (675)exp(8.6/6.7) ,

= 2436 W [+0.5]

REFERENCE , RPI: Attachment 2 to letter, Harris and Wicks (RPI) to Thomas (NRC), September 21, 1983, no page numbers in Attachment ,

ANSWER H.12 (2.50) E = (3000 + 675/2)(8.6)

= 15,800 watt sec [+1.0]

= 15 Btu [+0.5] Btu = (0.12 Btu /lbm deg F)(delta deg F)(10 lbm) [+0.5)

delta deg F = (20)/(10)(0.12)

'

= 16.7 deg F [+0.5]

REFERENCE RPI: Attachment 2 to letter, Harris and Wicks (RPI) to Thomas (NRC),

September 21, 1983, no page numbers in Attachment l

!

-

,

- - - - - . , _ _ , . _ , . , . , , . _ , --~--_,__y__,

. _

.

4 RADI0 ACTIVE MATERIALS HANDLING' DISPOSAL AND HAZARDS PAGE 28

ANSWERS -- RENSSELAER -87/12/01-UPTON, ANSWER I.01 (2.50) control room reactor window reactor room reactor deck

[+0.5each]

No. 5. (reactor deck) has the highest setpoint [+0.5]

REFERENCE RPI: "Startup Procedures for Critical Facility," Donald Harris, March 1985, p. .

ANSWER I.02 (2.00)  ;

An emergency that involves either excessive exposure of personnel to ionizing radiation OR release of radioactive materials

[+1.0 each]

,

REFERENCE 4 RPI: Emergency Procedures for the RPI Critical Facility, p. (7.0).

ANSWER I.03 (1.00)

'

- from the sterage tank 2, from the storage pit

[+1.0each]

REFERENCE RPI: "Operating Procedures for the RPI Critical Facility,"

Donald R. Harris, March 1985, pp. 5 and :

I

-

!

!

- .- __

.-.

, _ . _ _

.

. RAD'I0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE .29 ,

~

ANSWERS -- RENSSELAER -87/12/01-UPTON, ANSWER I.04 (2.00) dose rate (dr) = 1000 mrem /hr x 152/52 [+1.0]

(at 5 feet)

= 9000 mrem /hr dose = dr x time

'

= 9000 mrem /hr x 2/60 hr/ min [+1.0]

=-300 mrem REFERENCE  : RPI: "Personal Safety and Radiation Monitoring for the RPI Critical Facility," F. - Rodriguez-Vera, April 1985, p. 2.

.

ANSWER I.05- (1.00) TRUE

, FALSE

[+0.5each]

.

REFERENCE j RPI: Technical Specifications, I.06 'l ANSWER (1.00)

l ecqtaminated moaerator [+0.5] l clad rupture (+0.5]

release of radionuclides to building [40. 5] j

!

F1.0 maximum )

'

REFERENCE RPI: "Rensselaer Polytechnic Institute, Critical Facility, Safety Analysis Report," Docket No. 50-225, License No. CX-22, June 1986, p. 11.

l l

!

_

- _ w -

.

. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 30 s

ANSWERS -- RENSSELAER -87/12/01-UPTON, ANSWER I.07 (1.00) fr;; :t :k 60t (ac+"=1 wire cage around reactor Y

'

top side - deckh-[+0.5] beta [+0.5]

REFERENCE RPI: "Rensselaer Polytechnic Institute, Critical Facility, Safety Analysis Report," Docket No. 50-225, License No. CX-22, June 1986, pp. 3, 4 ANSWER I.08 (1.50)

No [+0.5]. Radioactive decay and activation are related to the half-life or decay constant of the material. The exponential nature of that buildup means that the activation during the second half-life will be less than during the first [+1.0].

REFERENCE Generic: Introduction to Nuclear Reactor Operations, Burn, p. 2-5 ANSWER I.09 (1.50)

(10 rad /h)(1/10)(1/10)(1/10)=10 mrad /h;+0.5; half value layer = (0.3)(TVL) = 0.3 in. + Therefore, 3.3 in. of lead is required [+0.5].

REFERENCE Generic: "Reactor Operator Study Handbook, ORNL-TM-2034,

!

1968, Volume 2, p. 10 .

o RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 31 ANSWERS -- RENSSELAER -87/12/01-UPTON, ANSWER I.10 (3.'00) whole body: 3 rem / quarter not to exceed 5(N-18) [+0.75]]

[+0.75 extremities: 18.75 rem / quarter [+0. 75] skin: 7.5 rem / quarter [+0.75]

REFERENCE Generic: "Code of Federal Regulations, Title 10," 10 CFR 20, Section 20.101, p. 239, January 198 .

ANSWER I.11 (2.00) The unit of rad is defined as an absorbed radiation dose of 100 ergs per gram of tissu [+1.0] The unit of rem is a biological dose unit defined by the relation: (dose in rems) = (dose in rads) x (RBE). [+1.0]

(RBE is the relative biological effectiveness and compares a dose's effectiveness to that of 200 kev X-rays).

REFEREhCE

, RPI: ' Personal Safety and Radiation Monitoring for the RPI Critical Facility," F. Rodriguez-Vera, April 1985, pp. 3, ,

ANSWER I.12 (1.50)

., .

!

TLDs measure the integrated (over time) exposure to beta, gamma, and neutron radiations. When certain substances such as Lif or

'MF-3 containing Mn as an impurity are exposed to such radiation, the absorption of the energy will excite the atoms of the crysta By heating the crystal, the captured energy will be released in the ,

form of pulses of light. [+1.5)

REFERENCE RPI: "Personal Safety and Radiation Monitoring for the RPI Critical Facility," F. Rodriguez-Vera, April 1985, pp. 3, ,

, ~ --

_ , - - - -

- - - - - - .

.

O

, SPECIFIC OPERATING CHARACTERISTIC PAGE 32

ANSWERS -- RENSSELAER -87/12/01-UPTON, ANSWER J.01 (1.00)

The neutron undergoes an (n, alpha) reaction with a B-10 nucleus

.

[+0.5]f.+0.25] The gas .Theionizedalpha charges particle move travelunder causestheionization pull of the of the BF-3 electric field resulting in an electrical pulse in the detector circuitry [+0.25].

REFERENCE RPI: "A Manual of Experiments for the Rensselaer Reactor Facility," Richard M. Kacich, May, 1975, p. 1 ,

ANSWER J.02 (1.00)

f (b.) [+1.0]

REFERENCE RPI: "Startup Procedures for Critical Facility," Donald Harris, March 1985, p. ,

ANSWER J.03 (1.00)

(a.) [+1.0]

REFERENCE RPI: "Startup Procedures for Critical Facility," Donald Harris, March 1985, p. 4, ;

J.04

'

"1SWER (1.50)

(a.) This is permitted only when the source channel has increased ,

by less than one decade from the shutdown condition [+1.0].  !

(b.)3in./ min [+0.5]

REFERENCE RPI: "Operating Procedures for the RPI Critical Facility," i j Donald R. Harris, March 19F5, p. 1.

!

!

' '

.,. -. _ _ _

,, .,_._ _ __ . , _ . . _ _ __ .,. - . _ . . . . , _ _ _ _ _ , _ _ _ _ . . _ _ _ . . _

_

.

..

'J . SPECIFIC OPERATING CHARACTERISTICS-PAGE 33 ANSWERS -- RENSSELAER -87/12/01-UPTON, ANSWER J.05 (1.50)

1.- door scram period scram water dump valve scram

[+0.5 each] .

REFERENCE RPI: "Operating Procedures for the RPI Critical Facility,"

Donald R. Harris, March, 1985, p. 4.

.

J.06  :

ANSWER (2.00) FALSE (The contacts are in parallel and normally OPEN) TRUE (ThecontactsareinseriesandnormallyCLOSED) TRUE FALSE (only one will drop)

[+0.5each] ,

REFERENCE RPI: "Solenoid Interrupt Circuit for the RPI Critical Facility," Appendix to Question 6, pp. 2, 3, .

l ANSWER J.07 (1.50) j

'

See Figure J-1-ANSWE i>0.75foreachcurve]

REFERENCE RPI: "Rensselaer Polytechnic Institute Critical Facility, !

Safety Analysis Report," Docket No. 50-225, License N I CX-22, June 1986, Figure :

i

___ _ ___ --_-----

. .

. .

RPI ANSWER J.07 Upton, .

.

.

.

.

CONT 10'. RCD C0KI

.

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CORI A CONN 03 AC ON AND R C P.AP FIGURE J-1-ANSWER L

. . . ._ .

.

.

'J.- SPECIFIC OPERATING CHARACTERISTICS PAGE 34 :

.

ANSWERS -- RENSSELAER -87/12/01-UPTON, '

ANSWER J 08 (1.50) bring reactor critical at uniform temperature heat the reactor water with the immersion heaters measure reactivity change by movement of calibrated control rod

[+0.5 each]

REFERENCE

, ,RPI: "Rensselaer Polytechnic Institute Critical Facility, Safety Analy.-is Report," June 1986, 7.10, p. 2 ANSWER J.09 (1.00)

(c.) [+1.0]

REFERENCE RPI: "Technical Specifications and Bases for the Rensselaer Polytechnic Institute Critical Experiments Facility," p. 3- . RPI: "Replacement Pages for Technical Specifications Approved by NRC (July 1987)," p. 3- '

]

J.10

~

ANSWER (1.00)

(b.) [+1.0]

REFERENCE 1 RPI: "Rensselaer Polytechnic Institute, Responses to Questions Sent by January 6,1987 Letter from Mr. John J. Dosa to Dr. Donald R. Harris Concerning HEU/ LEU Core Conversion Proposal," March 3, 1987, Figure i l

'

I

t

'

l

.

.

' SPECIFIC OPERATING CHARACTERISTICS PAGE 35

ANSWERS -- RENSSELAER -87/12/01-UPTON, ANSWER J.11 (1.00)

(d.) [+1.0]

REFERENCE RPI: "Rensselaer Polytechnic Institute, Responses to Questions Sent by January 6,1987. Letter from Mr. John J. Dosa to Dr. Denald R. Harris Concerning HEU/ LEU Core Conversion Proposal," Harch 3, 1987, Figure ANSWER J.12 (1.50) .007 (nodimension($xbeta) inches

[+0.5 each]

'

REFERENCE RPI: "Rensselaer Polytechnic Institute, Responses to Questions Sent by January 6,1987 Letter from Mr. John J. Dosa to Dr. Donald R. Harris Concerning HEU/ LEU Core Conversion Proposal," March 3, 1987, p. ,

,

ANSWER J.13 (2.50) See Figure J-2-ANSWE [+0.5]

The reason for the bell-shaped curve is that the impact on reactivity of a small change in control rod position is dependent on the magnitude of the neutron flux level in the .

vicinity of the change in poison concentration (+0.5]. The l neutron flux is at a axial maximum near the axial center plane

[+0.5]. The rod reversal is caused by a length of fuel that is placed ,

below tne control rod [+0.5]. As the rod is withdrawn  !

additional fuel is inserted in the core [+0.5]. l l

REFERENCE RPI: "A Manual of Experiments for the Rensselaer Reactor Facility," Richard M. Katich, May, 1975, pp. 41-4 . , . . . . . . . . . _ _ _ _ _ .

,,.

._...._.... . . . . . . . . . . - . . .- - - - -

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UPTON, J.

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(w:r ruvc) IN:nts

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l t i Tigure I. Differential Control twd korth nirve '

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r i t FIGURE J-2-ANSWER  ; ,

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, SPECIFIC OPERATING CHARACTERISTICS 'PAGE 36

ANSWERS -- RENSSELAER -87/12/01-UPTON, ,

f (1.0f'

-

ANSWER J.14_ .

t (c.) [+1.0)

REFERENCE k?I: "Replacement Pages for Technical Specifications Approved by NRC (July 1987)," p. 3- ,

ANSWER J.15 (1.00)

1. temperature coefficient of reactivity l 2. void coefficient of reactivity 3. reactor power measurement E

.

! 4. shutdown margin

. [+0.5 each, +1.0 maximum)  ;

l REFERENCE { RPI: "Technical Specifications and Bases for the Rensselaer

,

Polytechnic Institute Critical Experiments facility," p. 4- . RPI: "Replacement Pages for Technical Specifications Approved I by NRC (July 1987)," p. 4- ,

,

,

P t

e

.

-4 FUEL HANDLING AND CORE-PARAMETERS PAGE -37

~

ANSWERS -- RENSSELAER -87/12/01-UPTON, ANSWER K.01 (1.00)

M = countrate due to the source-and core fissions /

countrate due to the source only

[+1.0)

REFERENCE

,

' RPI: "A Manual of Experiments for the Rensselaer Reactor Facility," Richard M. i3ci9h, May, 1975, p. 2 ANSWER K.02 (2.50)

a, curve No. 1 [+0.5) For curve No. 3, the detector / source geometry (too great a distance) is such ^3at the detector does not "see" the source to the same degree as that correspond.ing to curve No. 2;

hence,1/M is lower in curve No. [+1.0] See Figure K-2-ANSWE [+1.0]

REFERENCE RPI: "A Manual of Experiments for the Rensselaer F3 actor Facility," Richard M. Kacich, Hay, 1975, pp. 24-2 ANSWER K.03 (1.50) this provides a reasonable ra+.e for loading fuel without going critical before it is desired [+1.0) to maintain symmetry [+0.5]

REFERENC . RPI: "A Manual of Experiments for the Rensselaer Reactor Facility," Richard M. Kacich, Hay, 1975, p. 30, 3 >

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, FUEL HANDLING AND CORE PARAMETERS PAGE 38 ANSWERS -- RENSSELAER -87/12/01-UPTON, '

t ANSWER K.04 (1.00)

(d.) [+1.0] .

'

REFERENCE

. RPI: "A Manual of Experiments for the Rensselaer Reactor i Facility," Richard M. Kacich, May, 1975, p. 30, 3 ,

l

ANSWER' K.05 (2.00) $0.20/sec [+0.5] $0.60 violent [+0.5]],

[+0.25 significant airborne [+0.25] explosives [+0.5] ,

,

REFERENCE RPI: Technical Specifications 3.4, p. 3-7.

a ANSWER K.06 (1.00)

-

>

(b.) [+1.0]

i ~

REFERENCE RPI: "IE Informatien Notice No. 83-66, Supplement 1: Fatality l at Argentine Critical Facility, May 25, 1984, pp. 1- !

.. i i

!

!

l

_

.

.

' FUEL HANDLING AND CORE PARAMETERS PAGE 39 ANSWERS -- RENSSELAER -87/12/01-UPTON,J.

~

ANSWER K.07 (2.00). Pu-238 = U-234 + alpha Pu-239 = U-235 + alpha alpha + Be-9 = C-12 + n

[+0.5 each, +1.0 maximum]

' years [+0.5] **7 neutrons /sec [+0.5] .

,

REFERENCE RPI: "Rensselaer Polytechnic Institute, Critical Facility, Safety Analysis Report," Docket No. 50-225, License No. CX-22, -

January 1983, p. 2 f Generic: "Academic Program for Nuclear Power Plant Personnel "

Volume II, Physics, General Physics Corporation, pp. 5-2 and 5- ,

i ANSWER K.08 (1.00) fuel load hook hand

-

[+0.5each)

REFERENCE RPI: Operating Proc'CJres, p. t

' iWER

-

K.09 (1.00) FALSE (An upper fuel pin lattice plate contains the holes and rests on the thick top plate.) [+0.5)

i TRUE [+0.5) ,

,

REFERENCE l

. RP!: "Rensselaer Polytechnic Institute Critical Facility, 4 Safety Analysis Report, Docket No. 50-225, License No. CX-22, June 1985, pp. 5, L

, - .. . . . . - .

.

+

<. PAGE 40 FUEL HANDLING AND CORE PARAMETE95%

'

ANSWERS -- RENS$ELAER -87/12/01-UPTON, q

. ANEWER K.10 -(3.00)

' .75 i [+0.5for40to42.in.] ,

, .466 i [+0.'5for0.43to0.50in.) t .00 i [+0.5 for 35 to 37 in.]  ;

J

~ U0-2 [+0.5forU0-2oruraniumoxide] [

!

~

l .81 w/o [+0.5 for 4.7 to 4.9 w/o)

- l; 4 stainless steel [+0.5]

il i

REFERENCE

,

! RPI: "Rensselaer Polytechnic Institute Critical Facility,  ;

Safety Analysis Report," Docket No. 50-225, License N !

l CX-22, June 1986, pp. 6, 7, and Figure j

'

ANSWER K.11 (2.00)

I [+0.5] Boron enriched in B-10 [+0.5]  :

l stainless steel cermet [+0.5] [

>

stainless steel [+0.5]  !

{

1 REFERENCE a

"Rensselaet Polytechnic Institute Critical Facility,

' RPI: r Safety Analysis Report," Docket No. 50-225, License N !

"

CX-22, June 1986, p. j

+

.

1 i

,

,

!

l I

.

.

r

>

!

.

-. - .- .. - -. . - . - . . . - . -

.

..

K. -FUEL HANDLING AND CORE PARAMETERS PAGE 41

'

ANSWERS -- RENSSELAER -87/12/01-UPTON, ' ANSWER K.12 - (2.00) . positive [+0.5] negative _[+0.5) using]a

[+ stainless steel chamber [+0.5] filled with polystyrene REFERENCE RPI: Manual of experiments, Chapter VII, p. 7- . RPI: SAR, Proposed Modification, October 1986, p. 15, Table .-

e

.

, . , . . . . . . , , ,

,

-,

'

x ADMINISTRATIVE-PROCEDURES, CONDITIONS ANO LIMITATIONS PAGE 42- ,

"

ANSWERS -- RENSSELAER -81/12/01-UPTON/ '

,

-

ANSWER L.01 .(2.G]) shutdown and secure the reactor j

-  ;

, isolate the leak ,

i de-energize equipment as needed for personnel safety and prevention of equipment damage

.

i ( 4 notify Operations Supervisor

[+0.5each]

-

j REFERENCE I

J RPI: Emergency Procedures for RPI Critical Facility, p. i

!

ANSWER L.02 (1.00)

!

,

100 W thermal and 200 kWh integrated power [+0.5each] '

,

REFERENCE RPI: "Replacement Pages for Technical Specifications Approved I by NRC (July 1987)," p. 3- l

<

,

f 4 -

'

ANSWER L.03 (1.50)

s , The full insertion of all control rods has been wrifir  ;

! The console key has been remove ;

, There is no operation in progress that involves the moving of .

j fuel pins in the reactor vessel, the insertion or removal of l

experiments from the reactor vessel, or control red ,

!

maintenanc [+0.5each]  !

) REFERENCE i

i

.' RPI: "Technical Specifications and Basns for the Rensselaer l j Polytechnic Institute Critical Experiments facility," p. 1- {

!

'RPI: "Replacement Pages for Technical Specifications Approved j !

!

!

_ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - . - -.

.

'

.

s ADMINISTRATIVE PROCEDURES.-CONDITIONS AND LIMITATIONS PAGE 43 '

9 -87/12/01-UPTON, ANSWERS -- RENSSELAER by NRC (July 1987)," p.1- ANSWER L.04 (1.00)

(d.) [+1.0)

REFERENCE RPI: "Technical Specifications and Bases for the Rensselaer Polytechnic Institute Critical Experiments Facility," p. 1- . RPI: "Replacement Pages for Technical Specifications Approved '

by NRC (July 1987)," p. 1-2.

J ANSWER L.05 (1.00) ,

December 5th(20daysafterNovember15th) [+1.0] t

'

REFERENCE

,

!

a RPI: "Technical Specifications and Bases for the Rensselaer i Dolytechnic Institute Critical Experiments Facility," p. 1-3

and 1- l RPI
"Replacement Pages for Technical Specifications Approved by NRC (July 1987)," p.1- ANSWER L.06 (1.50)

' watts [+0.5] ,

<

i .0 cps [+0.5] -

)

seconds ;+0.5]

JEfERENCE RPI: "Technical Specifications and Bases for the Rensselaer

-

Polytechnic Institute Critical Experiments facility," p. 2- ; RPI: "Replacement Pages for Technical Specifi:ations Approved

'

by NRC (July 1987)," p. 2- i

.

e 4 --a l- 6 A 4 5 s

-

r ? m +4

.

.

.. , ,

L. ' ADMINISTRATIVE-PROCEDURES; CONDITIONS AND LIMITATIONS - PACE 44 e- -;

'g

-

ANSWERS -- RENSSELAER - 87/12/01-UPTON, ,

, .f

/  !

'

-

i

L.07 l ANSWER (2.00)

i

] 1. - regular manual scram'(red button)-

. reactor console key i 1 loss of building power reactor' door scram I

[+0.5each]

REFERENCE f RPI: Technical Speifications and Bases for the Rensselaer

"

Polytechnic Institute Critical Experiments Facility," p. 3- . RPI: Replacement

"

Pages for Technical Specifications Approved .

, by NRC (July 1987)," p. 3- ;

!

ANSWER L.08 (2.00) reactor period < 15 see .

! neutron flux < 2 cps  :

.:

i failure of 400 Hz power supply to synchro ,

! failure of line voltage to the recorders  ;

i i moderator-reflector water fill ON  :

I r

[+0.5 each, +2.0 maximum] g REFERENCE l

'

$ 1, RPI: Technical Specifications and Bases fer the Rensselaer

"

i Polytechnic Institute Critical Experiments Facility," p. 3-?. .

I RP1: "Replacement Pages for Technical Specifications Approved by NR; (July 1987)," p. 3-3.

!

.

i j

__ .

';

.

- ADMINISTRATIVE PROCEDURES, CONDITiUNS AND LIMITATIONS PAGE 45

ANSWERS -- RENSSELAER -87/12/01-UPTON, ;

-

,

,

ANSWER L.09 (1.00)  ;

'

Type B electrical [+0.5] and Type C flammable liquids [+0.5]

REFERENC . RPI: Fire extinguishe I

.

ANSWER L.10 (1.50) TRUE FALSE (It is necessary for the automatic protective action i to fail in order to be required to report to the Commissio ,

i SeethenoteinReference2.) < FALSE (There is no one-for-one correspondence between a safety limit and a limiting safety system setting.) '

'

] [+0.5 each]

REFERENCE

' Generic: "Code of Federal Regulations, Title 10," 10 CFR 4 50.36, pp. 418, 419.

' RPI: "Replacement Pages for Technical Specifications Approved by NRC (July 1987)," p. 1-2, 2-2, 6-5, 6-6. There ap> ears to be an error in the Tech Specs at this point. The Tec1 Specs -

,

seem to imply that by simply exceeding the limiting safety system setting the 24 h report to the Commission is required.

{ This is not required by 10 CFR 50.36; 10 CFR 50.36 is

' 'XWER L.11 (.50) l False (up to 12.5 rems) [+0.5] ,

REFERENCE

)

RP'
Emergency Procedures for RPI Critical Facility, p. 1 ;

.

t

'

!

.

. - - - _ - - _ _ _ _ - _

._ .

. .

.

-

. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 46

!.NSUERS -- RENSSELAER -87/12/01-UPTON,. ANSWER L.12 (1.00)

1. An RO or an SRO shall be at the control . An SRO shall be present or readily available-(on call).

[+0.5 each)

REFERENCE RFI: "Technical Specifications and Bases for the Rensselaer Polytechnic Institute Critical Experiments Facility," p. 6- ANSWER L.13 (1.50) Radiation Safety Officer [+0.5) Director of the Critical Facility l+0.5] Critical Facility Supervisor [+0.5?

. REFERENCE RPI: Emergency Procedures, Section 7.2.

!

ANSWER L.14 (1.00)

(c.) [+1.0)

REFERENCE

' RPI: "Operating Procedures for the RPI Critical Facility,"

, Donald R. Harris, March 1985, p. 5.

USWER L.15 (1.00)

'

to check the high voltage plateau [+0.5) and to compare the

'

countrate to previous readinas [+0.5)

REFERENCE RPI: "Startup Procedures for Critical Facility," Donald R.

Harris, March, 3985, pp.1 to 4.
.

l

- . . _

..

'!

e I

ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE .47-

'~

ANSWERS -- RENSSELAER -87/12/01-UPTON, !

,

h ANSWER L.16 (.50)

30 to 50 se j

[+0.5 for 20 to 50 sec.)

REFERENCE

, RPI: "Operating Procedures for the RPI Critical Facility," '

,

Donald R. Harris, March 1985, p. .

i i

t

.,

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Attachment 2 FACILITY COMMENTS AND NRC RESOLUTION Question H.05 Comment:

Answer 4, Burnup, is not a factor in the RPI reactor since operation is limited to 200 kW per yea Resolution:

Comment not accepte Facility reference material cites burnup as a tacto Question H.06 Comment:

Beta of 0.008 was used in answer calculation, Beta for RPI is 0.007 Resolution:

Comment accepted. Reasonable values of Beta will be accepted, and arithmetic will be checked. Answer key modified accordingl Question H.12 An error in the answer key calculation was found during the grading of the examinations, answer key correcte Ovestion 1.01 Choment:

RPI presently uses only four area monitors (as required by Tech Specs).

Resolution:

Comment accepted. Deleted Answer #3 ("pit"). Question and answer modified accordingl Question I.03 Comment:

RPI uses a swimming pool filter to clean up water in the storage pit and can return the water to the storage tank instead of the rive Resolution:

Comment not accepte The question asked for the two sources / locations that water T.ay be released from the facility directly to the rive Your comment states that the water in one of the locations may, by choice, be rout:d elsewhere; that did not answer the questio Question 1.06 During grading, an additional correct answer was noted and added to the answer ke Question I.07 Comment:

The air sample is presently being drawn from the wire cage around the reactor dec Resolution:

Comment accepted, the was observed by the examiner, Anse:i' key change _

F-

>

l 2 Attachment 2

.

Question J.12 Comment:

Part b has no dimensions (Dollar x Beta)

Resolution:

Comment noted. Answer key modified accordingl Question K.03 Comment:

Question related to tb? old core but was part of the material supplied for the examination and is therefore acceptabl Resolution:

Commert note Question L.06 Comment:

Minimum flux level has been increased from 2 cps to 5 cps, but it is not in the manual Resolution:

Comment not accepte The question asked for the minimum flux level in accordance with the Technical Specification I l

l I

I t.

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