ML20248D537
| ML20248D537 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 09/26/1989 |
| From: | Bill Dean, Richard Laufer, Shepard D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20248D532 | List: |
| References | |
| 50-116-OL-89-01, 50-116-OL-89-1, NUDOCS 8910040307 | |
| Download: ML20248D537 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-116/0L-89-01 Docket No. 50-116 License No. R-59 Licensee: Iowa State University Nuclear Engineering Department l 2E1 Sweeney Hall Ames, IA. 50011 l
Facility Name: Iowa State University UTR-10 Reactor Examination Administered At: Iowa State University, Ames, IA Examination Conducted: August 23 and 24, 1989 l Examiners: 7/X[6 W. Dean ,/ /./'[W[rl Date l R.Lauferf;f )g / kP7 Chief Examiner: D. Shepard -
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Approved By: Mic 1 J. Jordan, Chief f!24 I7 Operator Licensing Section 1 Date Examination Summary Examination administered on August 23 and 24, 1989 (Report No. 50-116/0L-89-01) 4 to three Reactor Operator (RO) and one Senior Reactor Operator (SRO) l candidates.
Results: All candidates passed the examination.
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l 8910040307 890927 FDR ADOCK 05000114 V FDC l
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REPORT DETAILS
- 3. Examiners W. Dean, Headquarters R. Laufer, Headquarters
- 2. Exit Meeting An exit meeting was conducted on August 24, 1989 between the examiners and Mr. Robert Williams, Reactor Supervisor.
The following topics were discussed at the exit meeting:
- a. Demarcations on the Log Power Meters (Red Bands) are invisible, but indications are required by operating procedures to be in the red bands during pre-critical checks.
- b. Recommend that operators become familiar with Technical Specification surveillance and rod worth experiments as part of training.
- c. Generic knowledge weaknesses noted with respect to:
(1) the basis for ensuring at least a 9 minute fill time for the core tanks.
(2) what constitutes out of specification readings.
- 3. NRC resolution of the written exam concerns are contained in Enclosure 2.
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Enclosure 2 NRC RESOLUTIONS TO FACILITY WRITTEN EXAM COMMENTS A. RX THEORY, THERM 0 & FAC OP CHARS QUESTION A.05 (2.00)
List four interactions that a fission neutron may experience during its lifetime.
ANSWER A.05 (2.00)
- 1. Cause a new fission
- 2. Leak from the reactor
- 3. Capture by Rx material
- 4. Capture by fission products
- 5. Non fission capture by fuel (Any four of the above 0.5 each)
COMMENT The word " interaction" implies a list of neutron-induced reactions is sought. For future use, substitute " fates" for interactions. (This was explained to the candidates during the exam.)
NRC RESOLUTION Comment accepted. This was explained to the candidates during the exam.
QUESTION A.06 (1.00)
Which one of the following correctly describes the effect of an overcompensated neutron detector on indicated count rate? j
- a. Higher since more gammas are counted.
- b. Higher since more neutrons are counted.
- c. Lower since less gammas are counted. !
- d. Lower since less neutrons are counted. l ANSWER A.06 (1.00) d.
i COMMENT The term " current" is more appropriate than count rate for a CIC. An overcompensated CIC will produce a current from the gamma-sensitive i detector that is too large, and since it is electronically subtracted from the neutron-and gamma-sensitive detector, the net current (neutron) is too lew.
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NRC RESOLUTION Comment noted. Questions will be modified prior to uploading to the exam bank.
O'JESTIONS A.13 (2.00)
List the four types of fuel plates used in the UTR-10 reactor.
ANSWER A.13 (2.00)
Full load Hald load Quarter load Dummy load (0.50 each)
COMMENT A " dummy" is not a fuel plate. Reword as follows, " List the four types of plates used in UTR-10 fuel assemblies".
NRC RESOLUTION NRC Resolution: Comment noted. Question will be modified prior.to uploading to the exam bank.
QUESTIONS A.15 (1.00)
What is meant by the term Reactor Period?
ANSWER A.15 (1.00)
The time required for reactor power to increase by a factor of e.
COMMENT Negative periods are also possible since power can decrease. Accept also the response "the time required for reactor power to change by a factor of e".
REFERENCE I SV RX Oper. Proj. (p. 17)
NRC RESOLUTION l Comment accepted. Answer key changed.
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QUESTIONS A.19 (1.00)
Which one of the following has the LEAST affect on rod worth?
- a. Number and location of adjacent control rods.
- b. Temperature of the moderator.
- c. Temperature of the fuel.
- d. Core age.
ANSWER A.19 (1.00) c.
COMMENT Since reactivity changes due to burnup are not a consideration at our facility, the candidates would have no idea whether "c" or "d" is the most appropriate answer. There is no indication in the cited reference that "c" is the correct response. Delete this question from the exam and the question bank.
NRC RESOLUTION Comment accepted. Question deleted from the exam and question bank.
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v B. NORMAL /EMERG PROCEDURES & RAD CON QUESTION B.04 (1.50)
List the three conditions which must be met before the person assigned to monitor the physical security of the fuel and reactor can leave the reactor room during fuel transfer operations.
ANSWER B.04 (1.50)
Storage pit closed and locked (0.5)
Operating closures in place is fuel is in the core (0.5)
Overhead crane is secured (0.5)
COMMENT The answer is correct but the responsibility for the security of SNM must belong to the Senior Operator.. We request the question be withdrawn from the bank of R0 exam questions.
NRC RESOLUTION Comment not accepted. A reactor operator could be assigned to monitor the physical security of the fuel and reactor during fuel transfer operations and therefore needs to know these requirements of the ISU Fuel Transfer Procedure (p.2).
QUESTIONS B.15 (1.00)
Which one of the following is the required reactor condition to insert an experiment with a worth of $0.25?
- a. Normal operation with no restrictions
- b. All control rods fully inserted
- c. Hot Standby operation
- d. Operating with power < 1 kw ANSWER B.15 (1.00) b.
COMMENT The answer is correct, but candidates were confused by an apparent conflict with technical specification 3.8.3.C, stating 0.22$ is the maximum value for an experiment. Reword for future use: "Which of the following is the required reactor condition to add more than 0.22$ of reactivity?"
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NOTE We will reword our procedure, also, to eliminate the word " experiment".
NRC RESOLUTION Comment noted. Questions deleted due to conflicting statements between facility's Technical Specifications and operating procedures. The procedure needs to be modified to delete the work " experiment".
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C. PLANT AND RAD MONITORING SYSTEMS QUESTION C.06 (1.00) j List two ways that a tube leak in the primary cooler could be detected.
ANSWER C.06 (1.00)
Measurement of primary coolant volume (0.5)
Loss of suction head to the pump (0.5)
COMMENT A third possibility is listed in the Abnormal and Emergency Operations Procedure. Accept also the response "Below-normal flow rate".
NRC RESOLUTION NRC Resolution: Comment accepted. Answer key changed.
QUESTION C.16 (2.00)
Match the below listed conditions with the type of signal they provide:
(responses may be used more than once)
- a. period < 5 sec.
. b. period < .001 watt
- c. period > 5 sec. and < 10 sec. S - Scram
- d. coolant inlet temperature < T(min) A - Alarm
- e. coolant flow < 5 gpm I - Interlock
- f. moderator level > 55 in. N - No signal provided
- g. area monitor > 5 mr/hr
- h. power > 10 kw ANSWER C.16 (2.00)
- a. S e. A
- b. I f. S
- c. A g. A
- d. I h. N (0.25 each) )
i COMMENT There is no signal at P = .001W. (Candidates might be tricked by this since there is an interlock if P < .0001 W!). The answer for b is N, not I.
Tin < Tmin would be an alarm rather than an interlock if the dump valve is already close. The correct answer for d is both I and A.
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NRC RESOLUTION ,
i Comment accepted. Answer key changed. l QUESTION C.19 (1.00)
The fail-safe principle as it applies to the reactor safety system requires:
- a. that the dump valve automatically open on a scram or loss of power. !
- b. that the standby power supply be available to supp'.y the relay coils of the scram circuit on a loss of AC power.
- c. That the relay coils be energized to hold the relay contacts closed in the scram circuit.
- d. That only one out of two signals is required for a scram on duplicate nuclear instrumentation signals.
ANSWER C.19 (1.00) c.
COMMENT While "c" is the best answer (taken verbatum from the SAR), "a" is also true. The dump valve does indeed open upon loss of power. Accept either "a" or "c" as correct.
NRC RESOLUTION Comment partially accepted. Since two possible correct answers exist, this question is deleted.
QUESTION C.20 (1.00)
Which one of the following operations is inhibited by the moderator level
< 42 in. interlock?
- a. closing the dump valve
- b. opening the dump valve
- c. withdrawing only the regulating rod
- d. withdrawing any control rod 1
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ANSWER C.20 (1.00) 1
- b. ,
COMMENT Probably a typo, the answer is obviously wrong. Accept "d" as the correct answer.
NRC RESOLUTION Comment accepted. Answer key corrected.
QUESTIONS C.21 (1.00)
List four of the radiation monitoring components which must be operable, according to Technical Specifications, prior to taking the reactor critical.
ANSWER C.21 (1.00) air particulate unit de-ionizer unit area units door way monitor environmental (film badge or equivalent)
(Any four, 0.25 each)
COMMENT The air particulate unit is not always necessary to make the reactor critical. It may be specified by certain procedures or experiments.
Change "murt" to "may" in the question.
NRC RESOLUTION Comment noted. Question will be modified prior to uploading to the exam bank.
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