ML20127K204

Exam Rept 50-156/OL-85-01 on 850604-06.Exam Results:Three Candidates Passed Written Exam & Three Passed Oral Exam

ML20127K204
Person / Time
Site:	University of Wisconsin
Issue date:	06/24/1985
From:	Burdick T, Mcmillen J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20127K187	List: ML20127K183 ML20127K204
References
50-156-OL-85-01, 50-156-OL-85-1, NUDOCS 8506270310
Download: ML20127K204 (41)

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{{#Wiki_filter:, U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-156/0L-85-01 Docket No. 50-156 License No. R-74 Licensee: University of Wisconsin Madison, WI 53706 Facility Name: UWNR(TRIGA) Examination Administered At: UWNR Examination Conducted: Reactor Operator Y g jlf-f$~ G Examiner: T. Burdick Date 6/.29 b Approved By: M (Tate' Examination Summary Examination administered on June 4-6, 1985 (Report No. 50-1560L-85-01) Written and oral examinations were administered to five reactor operator candidates. Results: Three candidates passed the written examination and three candidates passed the oral examination. 8506270310 850624ADOCK 05000156 PDR PDR 0

REPORT DETAILS 1. Examiners T. Burdick 2. Examination Review Meeting The examiner met on June 4, 1985, with University representatives following the written examination. Comments and their resolution are included in enclosure three. 3. Exit Meeting The examiner met on June 6,1985, with University representatives to indicate those candidates that clearly passed the oral examination and note any significant problems. m

University of Wisconsin Comments and Resolution Comment:A.3.b. "For higher enrichment [ fuel] (70L) fast fission in [ Uranium] 238 is not significant. [Univeristy of Wisconsin] ex [that] Beff [is] greater than Beta because of lower [ plains neutron] leakage." Resolution: The examiner corrected the answer key to incorporate this answer. Comment:A.4. "We don't use PCM here unless we're training outside operators. They may be confused by the term. We don't use dollars either." t Resolution: The examiner did not delete this question since it was part of the candidates' training. Comment:A.S.b. "It sounds as if one answer is sufficient for this part." Resolution: The examiner agreed and indicated such on the answer key. Comment:A.6.6. ""Because of low flux level" should be sufficient. Resolution: The examiner made no changes to answer key in this regard. Comment:B.1.b.;Thequestion]"Couldbeansweredas"tohave[a]positionfor . instrumented elements] and to allow for location of [ transient] rod." Resolution: The examiner made no changes to the answer key in this regard since the reviewer did not support his comment with documentation. Comment:B.4.b. The examiner determined and corrected an error in the answer key. Comment:C.I.c. "0k but, "less than or equal to." [is more accurate] Resolution: The examiner agreed and corrected the answer key. Comment:C.3.b. [You will] "probably lose them on humidity control. Room air conditioning is supposed to be able to control that now." Resolution: The examiner did not change tne answer key since no documentation to support the comment was submitted. Comment:C.S. "UWNR has no xenon problems. If [the question was] asked to determine [the candidates'] knowledge of xenon ok. This is really a power plant question." Resolution: The examiner agreed and deleted this entire question. i .. ~..

~ l Comment:C.6.a. " Control element speeds are fixed. [ Withdrawal] rate doesn't make a [ difference]". Resolution: The examiner did not change the answer key since all control element speeds are not the same. Comment:C.6.b. [The answer is] ""No effect" because fuel and [ water] coefficients dre equal and opposite." Resolution: The examiner agreed and changed the answer key to reflect this. 7 Comment:D.1.a. "Startu channel is Log [ count] Rate channel [and] 10-10 cpm or [zero if off scale low." Resolution: The examiner agreed and changed the answer key accordingly. Comment:D.2.b. " Trainees should give response that they would "see no significant change at power"." Resolution: The examiner agreed and changed the answer key to include this possible answer. Comment:D.3. The examiner determined other possible answers and included these in the answer key. Comment:D.5.a. "Only safety blade No. 2 should be indicated under answer three." Resolution: The examiner agreed and changed the answer key accordingly. Comment:D.6.a. "If the pressure switch fails it can fail open or closed. If it fails closed the light will be on; if fails open then the light will be off." Resolution: The examiner agrees and changed the answer key accordingly. Comment:D.6.b. " System temperatures - thermocouple, recorder; fails high (upscale burnout feature) for open, low for shorted. Core inlet - RTD, fails high for open, low for shorted." Resolution: The examiner agrees and the answer key was changed accordingly. Comment:E.2. " Log N calibrate switch not in "0PERATE." Pool level trip is LOW or HIGH. [ Transient] rod scram in pulse mode is not equivalent to other " scrams" listed because scram relays do not drop out and logic element does not send trip signal to trip actuators." Resolution: The examiner agreed with the first two coments and changed the answer key accordingly but did not change the answer in regard to the third comment since it is listed as a scram in the SAR.

~ Comment:E.3.a. "You will probably get the response that a relay must dropout for a relay scram while the electrcaic scram biases a transistor into non-conduction. Also, [the transient] rod does not drop on electronic scram." Resolution: The examiner agrees and changed the answer key accordingly. Comment:E.3.b. "A more correct answer would be that " magnet current that turns off allowing the blade to fall in and/or solenoid valve opens to vent air from under piston allowing [ transient] rod to drop"." Resolution: The examiner agrees but did not require such detail for full credit. Comment:E.4.a. " Control element must be selected, scram relay reset" is sufficient since it cannot be reset if scram condition is present." Resolution: The examiner did not accept the first statement without documentation but agrees with the second statement and changed the answer key accordingly. Comment:F.4. "UWNR 001 item eight states "it is the policy of the facility to shut down whenever the operator has any doubt of safe conditions." Therefore an answer of " shut down" should be accepted." Resolution: The examiner agrees and changed the answer key accordingly. Comment:F.6.b. "For fuel handling the SR0 must be present in the lab during fuel movements. Reference UWNR 143A.1 which requires direct supervision of fuel handling. Also after a scram UWNR 115 requires [an] SR0 present in the lab to complete the form and investigate [the] reason for scram." Resolution: The examiner agrees and changed the answer key accordingly. Comment:G.3.a. "" Silence" if you're doing]precrit and waiting for " bugging" or " scram" if [the reactor is operating." Resolution: The examiner required the candidate to answer " scram" for full credit. L

~ i MASTER COP 3 U. S. NUCLEAR REGULA10RY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: UNIVERSITY OF WISCONSIN REACTOR TYPE: TRIGA DATE ADMINISTERED: 85/06/04 EXAMINER: T BURDICH APPLICANT: INSTRUCTIONS 10 APPLICANT Uso 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 least 70% in each category and a final grade of at least 80%. Examination papers will be picked up si:. (6) hours after tho exaniination starts. % OF CATEGORY % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY _557___________ 14.00 _ _ _ _ _ _ _ _ _ _" "79 7p ________ A. PRINCIPLES OF REACTOR OPERATION I' 13.00 FEATURES OF FACILITY DESIGGN _ _ _ _ _ f } 3{ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ E:. _'1_"I [ ________ C. GENERAL OPERATING CHARACTERISTICS ) _ _1 ________ D. INSTRUMENTS AND CONTROLS 133__ _[ ;_}(( ___________ ________ E. SAFETY AND EMERGENCY SYSTEMS 14.00 Ld)S4 ________ F. STANDARD AND EMERGENCY OPERATING PROCEDURES ~~ /q.6f I ________ G. RADIATION CONTROL AND SAFETY Tf P.'8D 30.00 100.00 TOTALS FINAL GRADE _________________% All wotI. done on this exaninstion is niy own. I hrve neither given not received sid. EPPL5CEUYI5~55GU TURE ~~~~~~~~~~~~~~

?. s / A. PRINCIPLES OF REACTOR UPERATION PAGE 2 QUESTION A.01 (2.00)

c. Refer to figure A-1 and calculate the stable reactor period for the indicated transient. Show all your work.

[1.53

b. Calculate'the doubling time. Show all your work.

[0.53 QUESTION A.02 (2.00)

a. Refer to figure A-2 and state whether the reactor period is stable, increasing or decreasing.

E1.03

b. Also state whether the Startup Rate is stable, increasing or decreasing.

E1.03 00ESTION A.03 (3.00)

a. Define Beta C1.03 b.

If Bete for U-235 is.0065 then why is Beta for the UWNR.007? [1.03 c. Being so small, why does Beta have such a great impact upon reactor operation? [1.03 DUESlION A.04 (3.00) Express 100 pcm in units of:

a. % Delta K/K

b. Delta K/K

c. dollars GUESTION A.05 (2.00)

c. What two purposes does Erbium serve in the UWNR?

E1.03

b. What prompted the need for Erbium in FLIP fuel in both cases far part a E 1. 01-above?

(mmmum CATEGORY A CONTINUED ON NEXT PAGE xxxxx)

s o' A. PRINCIPLES OF REACTOR DPERATION PAGE 3 00ESTION A.06 (2.00)

o. Will equilibrium Samarium vary with power level? Why?

E1.03 b. Why are significant Xenon transients on the UWNR difficult to achieve? E1.03 4 pm (***** END OF CATEGORY A

• • • • • )

e em b

s / B. FEATURES OF FACILITY DESIGGN PAGE 4 GUESTION B.01 (3.00)

c. State the purpose of the graphite end pieces in each fuel element. E1.03 b.

State the,two purposes of a three-element bundle. E1.03 c. How are reflector elements identified when viewed in the core or storage racks? [1.03 OUESTION B.02 (3.00) State the number and type of moveable control elements used in the UWNR. E1.53 OUESTION B.03 (1.50) Label the three components indicated on figure B-3. QUESTION B.04 (2.00) Refer to figure B-4 a. State which control elements are driven by each of the mechanism:- EA and B3. E1.03 b.'How fast can each of these drive mechanisms move the control elements? [1.03 GUESTION B.05 (2.00)

c. State the purpose of the jet pump diffuser 1ccated above the core. E1.03 b.

How is makeup water processed and provided to the pool normally? [1.03 ..~ (mmman CATEGORY B CONTINUED ON NEXT PAGE musum) 1

9 s FEATURESOFFACILhTYDESIGGN PAGE 5 B. QUESTION B.06 (1.50) c._Why is there an interlock that prevents startin3 the primary cooling pump bef ore the heat e>: changer pump is running? [1 03

b. State the' color code for E.253 1.

contaminated water discharge E.25] 2. city water l (szuss END OF CATEGORY B

• • • • • )

e oe-me f 9 _ _ _ _ _ _ _ -. _ _. _..,, _ _ _ ~. _. _.. _. -

s W C. GENERAL OPERATING CHARACTERISTICS PAGE 6 DUESTION C.01 (2.00) State the steady state values for

e. core excess reactivity E.53 be core shutdown margin E.53 c.

transient rod worth E.53 d. full power fuel temperature E.53 QUESTION C.02 (2.50) Refer to figure C-2

o. Identify the three plots as either ideal, conservative or noncon-servative in regard to predicting criticality.

E1.53

t.. Indicate whether the following would make the 1/n Plot niore conservative or less conservative.

[1.03 1. longer count times 2. move the detector directly adjacent to the source DUESTION C.03 (3.00) a. State the reector pool temperature limit. E1.03 b. State the two bases for the t e niper a tur e limit. [2.03 QUESTION C.04 (2.00) Draw a typical radial flux profile for a reflected and unreflected thermal flux for the UWNR. [2.03 (mansa CATEGORY C CONTINUED ON NEXT PAGE ***x*)

C. GENERAL OPERATING CHARACTERISTICS PAGE 7 QUESTION C.05 (1.50) i Hew long does it take for Xenon to'

c. reach equi, librium from a clean start %

E. 53-b. peak from a trip at full power [.53 c. effectively decay off following a trip from full power equilibrium E.53 QUESTION C.06 (2.00) State the affect,'if any, each change given will have on critical rod haight at UWNR.

c. Withdrawing rods faster to approach critical.

b. Lowering the pool temperature 20 deg. F. (samma END OF CATEGORY C mamma) 9 9m m

W D. INSTRUMENTS AND CONTROL-S PAGE 8 QUESTION D.01 (2.00) O. State the range and units displayed for the startup channel C1 03 b. State the nuclear instrument channel that provides: [1. 03-1. rate in'dication 2. servo control 00ESTION D.02 (2.00)

c. What two types of neutron detectors are used for nuclear instrumentation at UWNR?

[1.03

b. How would a failure of compensation voltage affect indication from the nuclear instrumentation?

[1.03 DUE9 TION D.03 (2.50) State the five differences between pulse and square wave operations. [2.53 OUESTION D.04 (2.00) State the difference between lowering and raising the startup detector [2.03 regarding the drive system operation. QUESTION D.05 (1.50)

c. Which rods are cr9able of being positioned automatically?

E.753

b. How many elements can be automatically positioned at one time?

433[,36fk b

c. What is the rate-of-change limitation while in automatic?

[.53 "~ (xxxxx CATEGORY D CONTINUED ON NEXT PAGE

• • • • • )

D. INSTRUMENTS.AND CONTROL *S PAGE 9 00ESTION D.06 (2.00) State,the type of sensor and indication for the following and also indicate tha failure mode for each (e.g. one off, high, low)

c. primary cooling pump status

b. primary system temperature 7 W h

b e N a (mxmum END OF CATECORY D

• • • • • )

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5 / E. SAFETY AND EMERGENCY SYSTEMS PAGE 10 QUESTION E.01 (2.00)

o. List.the four alarms and interlocks from the startup nuclear instrument channel.

[2. 0 3. QUESTION E.02 (5.00) List all reactor trips with setpoints where applicable. E5C /h% '*1 I QUESTION E.03 (2.00) D. How does an electronic scram differ from a relay scram? [1.03

b. What allows rapid insertion of control elements during a scram?

[1.03 QUESTION E.04 (2.00) What two permissives, not associated with the startup channel, must be satisfied in order to withdraw the control elements? (muumm END OF CATEGORY E mamma) emee

/ _________________-_________' OPERATING PROCEDURES F. STANDARD AND EMERGENCY PAGE 11 QUESTION F.01 (2.00)

c. Define ' reactor shutdown' per the Technmical Specifications.

b. Define 're, actor secured' per the Technical Specifications.

QUESTION F.02 (2.00) State the Safety Limit (s) applicable to yWNR. QUESTION F.03 (3.00) State the minimum number of operable channels and applicable operating nodes fort c. fuel temperature b. linear power level c. log power level OUESTION F.04 (2.00) For an unexpected shift in reactivity and/or power level when is a scram warranted by the procedure? GUESTION F.05 (2.00) Ao a Reactor Operator at UWNR:

c. Who do you notify immediatly upon occurence of an unexpected scram?

b. In what form is authority given to you to operate the reactor following an unexpected scram?

00ESTION F.06 (3.00)

o. WHEN and WHERE must a licensed Reactor Operator be present at the UWNR?

b. WHEN and WHERE must a licensed Senior Reactor Operator be presynt at the, UWNR? Include all circumstances.

(urwx* END OF CATEGORY F

• • • • • )

'I k / G. RADIATION CONTROL AND S"AFETY PAGE 12 QUESTION G.01 (3.00) + Whct are the minimum number and types of fixed radiation monitors required to be operabl,e by Technical Specifications? DUESTION G.02 (2.00)

o. What is the gaseous radiation hazard associated with the use of the thermal column and beam ports?

[1.0] b. How is this hazard minimized?- [1.03 OUESTION G.03 (2.00)

a. What is the required immediate operator action for ' THERMAL COLUMN DOOR OPEN' alarm?

[1.03 b. What controlled radiation een cause higher than normal readings on the CAM? E1.03 OUESTION G 04 (2.00) / State the AUDIBLE and VISUAL warnings used for evacuation. QUESTION G.05 (2.00) If you were the RO on duty when the evacuation alarm initiated *

o. What immediate act on(s) would you take before leaving?

[1.5]

b. Where would you go t'or assembly?

E0.53 r i DUESTION G.06 (2.00) Stote the whole body dose limits per 10 CFR 20.101. Include all prerequi-cites if any. (xxxxx END OF CATEGORY G xxxxx) (*****xxxxxxxx END OF EXAMINATION xxxxxxxxxxxxxxx) I /'

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