ML20247K421
| ML20247K421 | |
| Person / Time | |
|---|---|
| Site: | University of Wisconsin |
| Issue date: | 07/24/1989 |
| From: | Jordan M, Shepard D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20247K396 | List: |
| References | |
| 50-156-OL-89-01, 50-156-OL-89-1, NUDOCS 8907310544 | |
| Download: ML20247K421 (12) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-156/0L-89-01 Docket No. 50-156 License No. R-74 Licensee: University of Wisconsin Nuclear Engineering Department 4 Madison, WI 53705 Facility Name: University of Wisconsin Nuclear Reactor Examination Ariministered At: Madison, Wisconsin Examination Conducted: May 30-June 1, 1989 Chief Examiner: /gt 7/5/f? I Douglas / L. Shepard Date Approved By: 7 (7 M.' J.7Jyrdan Date i
Examination Summary Examination administered on week of May 30, 1989, Report No. 50-156/0L-89-01 Examinations were to three reactor operator candidates.
Results: All candidates passed the examination.
8907310344 890724 PDR ADOCK 05000156 V PDC
REPORT DETAILS
- 1. Examiners Douglas L. Shepard
- 2. Exit M*eting At the conclusion of the examination, the examiner held an exit meeting.
The following facility personnel attended the coeting:
R. J. Cashwell, Reactor Director S. M. Matusewic, Reactor Supervisor No generic comments were noted.
- 3. An examination review was held on June 1, 1989. Specific comments concerning written examination questions and NRC resolutions are contained in Enclosure 2.
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REACTOR OPERATOR EXAMINATION I
QUESTION A.07 FACILITY COMMENTS:
Selection of the "best" moderator for high energy neutrons depends upon amount of weighting given to. slowing-down. length and absorption cross section. Both.
- a. and c. are possible correct answers. Note question A.01 indicated there is 1 more than.one desirable characteristic of a " good" moderator. Full. credit should be given for either a. or c.
NRC RESOLUTION:
Concur, question deleted.
QUESTION A.10 FACILITY COMMENTS:
Answer incorrectly multiplies number of radioactive atoms times decay constant, while question asks for calculation of number of radioactive atoms. Numerical y answer is thus incorrect. Should be-2.32E+05 atoms.
NRC RESOLUTION:
Concur, answer key modified.
QUESTION A.11 FACILITY COMMENTS:
Although Xe concentration does change at' low power l'evels, for the range of' powers indicated in the question Xe effects are entirely negligible, and operators might answer " remains the same" because they know they will see absolutely no change in reactor operation.
NRC RESOLUTION: l Do not concur, question elicits knowledge of the process.
QUESTION B.01 FACILITY COMMENTS:
The one correct response is asked for, but answer a. is also true. The whale pump starts when the diffuser pump starts, and a' failure of.the whale pump light to turn on can be (and has been in the past) the result of loss of prime. Either answer a. or d. or both should be accepted.
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NRC RESOLUTION:
Do not concur, loss of prime is not only~ reason for the _ light not operating.
QUESTION B.04 FACILITY COMMENTS:
The examiner should note that there are two neutrons sources installed in the-reactor pool- the startup source and the " bugging" source used for checking LCR channel response during prestartup checkout. The question should clarify that the startup source is the object of the question, as answer a. and c.
would be incorrect for the bugging source. _ The work " hold" in' Part c of the answer should be " holder".
NRC RESOLUTION:
Concur, no confusion on part of candidates occurred.
9 QUESTION B.05 FACILITY COMMENTS:
This question concerns the " Porpoise. tube" irradiation facility which has not' been installed in the reactor pool for the past several years.
In addition, expecting specific wording as indicated on the answer sheet would
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require specific memorization of unimportant information. Where the answer sheet has two blanks filled with " vacant grid" position, several alternative .
wordings would give the. same information (e.g. , reflector element, empty lattice, unused grid, open grid, open lattice, etc.). . The fourth and fifth' blanks, required by answer sheet to be filled with " bypass flow". Acceptable alternate answers could be " delta P", " excess flow", " flow induced", " pressure
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differences" and the like. Full credit should be given-for any equivalent wording indicating that the diffuser pump provides the motive flow for. sample movement.
,NRC RESOLUTION:
Equivalent answers as listed above are acceptable.
QUESTION B.06 FACILITY COMMENTS:
Answer b. for this question states a limit from the SAR. UWNR 110, Prestartup Checklist, Item 1.C. indicates the limit of 1 Megohm-cm. Either answer should -
be accepted. Answer c. is missing a negative sign in the exponent.
NRC RESOLUTION:
Concur, answer key modified.
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e QUESTION B.08 l FACILITY COMMENTS:
The question incorrectly quotes the function of the locating plate, and is likely to confuse the reader. It implies that the rod drive mechanisms are within the core. It should indicate that the locating plate aligns the rod drives with the core.
We do not believe that this question covers a significant feature of the facility design, as removal of the locating plate is not covered by our maintenance procedure (UWNR 200, Section 2.4). Maintenance of that portion of the facility is limited to painting.
NRC RESOLUTION:
Concur, question deleted.
QUESTION C.01 FACILITY COMMENTS:
Correct response to this question depends upon memorized values from a table of reactivity values stated in the safety analysis report, some of which are insignificant 1y small reactivity changes. There is absolutely no reason for an operator to have such data committed to memory, so there is no basis for ordering the data in increasing positive reactivity worth. Even a senior operator has no need for such information. This question is outside the scope of knowledge for an operator and should be deleted.
NRC RESOLUTION:
Do not concur, question asked for relative worths, not exact values. I QUESTION C.02 FACILITY COMMENTS:
J Blades 1 and 2 have essentially the same reactivity worth, and this point is taught in our training program. Full credit should be given for the answer given and for the sequence d, e, a, b, c.
NRC RESOLUTION: j Concur, answer key modified.
l QUESTION C.03 FACILITY COMMENTS: 1 i
This question is beyond the scope of required knowledge for operators.
Correct response to this question would require memorization of flux _ values i given on UWNR 130. Further, UWNR 131, page 6 states that the porpoise tube is l
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I usually positioned in the maximum available thermal neutron flux (although it is not presently installed). The flux in irradiation positions is of primary interest of the senior operator approving the irradiation. Finally, if an operator (or SRO) is asked to calculate the activity produced in an irradiation he will use tables which are specific to presently installed irradiation facility. Knowledge of neutron flux is not necessary for this calculation.
NRC RESOLUTION:
Comment is noted. Question will remain, the question asks for relative fluxes within the core and does not require specific valves.
QUESTION C.04 FACILITY COMMENTS:
Correct response to this question would require memorization of information contained in a posted maintenance procedure (UWNR 163). It does not concern Technical Specification values, and is beyond the scope of required knowledge for operators since it is from a maintenance procedure.
NRC RESOLUTION:
Concur, question deleted.
QUESTION C.07 FACILITY COMMENTS:
UWNR 154, Leak Resulting In Draining of Reactor Pool, Item 8, does not address the 15 foot limit from Technical Specifications. Instead, it indicates the approximate water loss from the pool from piping ruptures to be approximately one foot for all piping systems except for the pneumatic tube, and to entry point of pneumatic tube (approximately seven feet below pool surface).
Therefore an answer of seven feet should be accepted based on procedural guidance.
NRC RESOLUTION:
Concur, answer key modified.
QUESTION C.09/C.10 FACILITY COMMENTS:
Correct response to this question would require memorization of information contained in UWNR 110, Daily Reactor Prestartup Checklist, as limits to which compliance must be demonstrated during the checkout. Since this procedure is required to be in-hand with entries made during performance memorization of these limits is beyond the scope of required knowledge for operators.
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1 NRC RESOLUTION:
Do not concur, this is knowledge that a competent operator will know due to having performed the actions numerous times.
l QUESTION D.b3 FACILITY COMMENTS:
Answer c. should accept wording similar to "under the bridge", since that is 1 where it is located. It is visible from the console area, but not located !
there. j 1
NRC RESOLUTION:
Concur, answer key modified.
QUESTION D.05 FACILITY COMMENTS:
The log-N channel has a minimum reading of 0.1 watt ud is required (UWNR111) to be on scale before picoammeters exceed a reading of 0.5 watts. Either of these answers should be accepted in lieu of " intermediate range".
NRC RESOLUTION:
Concur, will accept values for intermediate range.
QUESTION D.07 )
FACILITY COMMENTS:
Answer j. is given as "both". The servo error meter indicates in all modes, l so "all" should be accepted.
NRC RESOLUTION: !
Concur, answer key modified.
QUESTION D.08 FACILITY COMIENTS:
The term " Alarm System" is used in this question and in D.09 and D.10. The j answer given in this question appears to apply only to the evacuation alarm, l however, not the annunciators. If clarified during exam administration as being the evacuation alarm the answer is correct as given. If not clarified, Items b. and c. are both correct answers, since " chain switch deactuated" could refer to opening the chain switch which will be annunciated.
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i NRC RESOLUTION:
Concur, question deleted.
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l QUESTION D.10 W l
FACILITY COMMENTS.
The answer here also indicates Annunciator is the meaning of " Alarm System".
We object to answer choice a. (450 F.) as stating the question in a different unit than used at the facility, but above the numerical value of the alarm i point. Fuel temperatures are recorded and quoted in C. And alarm points '
memorized in C. We believe this to be misleading, especially in view of the other comment below. The Question asks which ONE of the listed conditions ,
will actuate the alarm system. The answer sheet -:-dicates only b., Manual i Reactor Scram as correct. In reality answer c. s equally valid, since the alarm occurs at 2 inches above or below the normai cand. Reference UWNR 155, page 7.
NRC RESOLUTION:
Concur, question deleted.
l l QUESTION E.01 FACILITY COMMENTS:
The answer correctly indicates the SAR value of time delay of 30 seconds.
Full credit should be given for 20 seconds, since the actual delay is set below the SAR limit. Not also that students will probably identify monitors connected to evacuation alarm by location (Demineralized, Pool top, and Thermal column or three left-hand monitors) rather than by number and should I i be given full credit for such responses. J NRC RESOLUTION:
l Concur, answer key modified.
QUESTION E.02 FACILITY COMMENTS:
i Candidates should be given full credit for indicating the location of the !
valves which must be manually opened to direct flow to the pool rather than i location of the nozzle. The valves are located above the west basement i entrance to the Reactor Laboratory. i NRC RESOLUTION:
Concur, answer key modified.
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QUESTION E.03 i FACILITY COMMENTS:
The candidates should know when the system is required to be operable, but the 1 exception should not be required. It is inappropriate to require a reactor l operator to memorize a 2-day action statement, especially since a SR0 would have to authorize operation if the fan were inoperable. UWNR 110 and UWNR 111 l both require checks of operation of ventilation system as Part of the startup.
NRC RESOLUTION:
Do not concur, answer only requires operators to know of general concept.
QUESTION E.05 FACILITY COMMENTS: 1 The first blank required entry of a word to modify the " stack" monitored by the Stack Air Monitor. This facility has only one stack, and it is called "the stack".
The blank requiring flow rate information should not be required. This value is given on the posted procedure (UWNR 117) at the stack monitor location and should not be memorized by an operator.
The last blank indicates the sample is returned to the Reactor Laboratory.
This has been changed to return to the Beam Port and Thermal Column Ventilation System. Training information has not yet been updated, but instruction covered the change.
NRC RESOLUTION:
Partially Concur, Part a deleted and Part f is revised. l QUESTION E.06 FACILITY COMMENTS:
Terminology used in the question is incorrect. The question applies to the Pneumatic Tube. It is not a sampling system.
NRC RESOLUTION: ,
Comment noted, no change to questions due to no confusion on part of candidates. !
QUESTION E.07 ;
FACILITY COMMENTS:
One incorrect response among the four possible responses was requested. This will cause a problem, since all responses, (including the indicated answer c.)
can be considered correct. All electronic scrams serve as backup to relay 7
scrams, and thus the same signals d_o give both relay and electronic scrams.
The relay and electronic scrams for the pocoammeters occur from the same-bistable. The period relay scram occurs from a different bistable, but the same signal. Since this eliminated the " incorrect" answer, the candidates may be forced to assume another correct response is incorrect. Because of this, answer b. may be selected since we do not emphasize absolute value of delay time. (Delay time is not included in Technical Specifications- only total scram time limit of 2 seconds is specified).
NRC RESOLUTION:
Concur, question deleted.
QUESTION E.08:
FACILITY COMMENT:
The possible answer concerning Log-N switch position should indicated "not in operate" instead of "not in input," since that is the way the switch is labled. The answer for pool level should accept high or low level-trip.
NRC RESOLUTION:
Concur, answer key modified.
QUESTION E.10:
FACILITY COMMENTS:
The question uses "c. Startup mode" as one of the modes. There is no such mode since there is no such mode switch position. The question as written includes mode responses of a through f. and c. is a required answer for two matches. The technical specification wording is.such that the answer "all modes"'would be correct for Item 1 (in technical specifications). . Inclusion of two deliberately added non-existent modes and one additioral mode that does not exist makes it impossible to answer per tech spec wording. Procedures require log power level operable except for pulse mode opeation.. It is required for startup since UWNR 111 (Startup Checklist) requires it onscale to complete startup. Startup count rate is required operable event after startup due to the control element withdrawal interlock. Linear power is required operable during startup by UWNR 110 u.eckout and UWNR 111 response criteria.
Completely correct answers are impossible the way the question is worded. The
- question should be deleted and rewritten if used in the future.
NRC RESOLUTION:
Partially concur, answer key modified to not require c. as correct answer.
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QUESTION F.01:
FACILITY COMMENTS:
The question states setpoints are requried. Safety limits are limits, and not setpoints. The limit for fuel temperature is incorrectly indicated as F.,
while it should be C. (See comment to question D.10. The LSSS do have setpoints but are not included in the answer. Operators will likely include the actual protective setpoints of 125% on any picoammeter range and 400 C on 19M1, and should be given full credit for these answers.
NRC RESOLUTION:
Do not concur, no confusion on part of candidate. 1 l
QUESTION F.02:
FACILITY COMMENTS:
i Answer that person placing a tag can remove it "any time" is not correct - should only remove if condition requiring placement is no longer applicable.
NRC RESOLUTION:
l Concur, will accept answers similar to above. ;
QUESTION F.05: !
I FACILITY COMMENTS:
Part a. uses the term " sample" to refer to whale carriers. Any number of samples that will fit can be placed in a whale carrier, although operators may respond 36, since that is the usual number loaded into a whale carrier. In addition, whales are loaded one-at-a-time to assure whale rotation, per the caution on the referenced procedure.
Part b. The requirement for floating is for all whale samples, whether they have holes or not.
NRC RESOLUTION:
Concur, will accept 36 if given as answer. Also discussed with the facility at the exit meeting to accept one since normally used.
QUESTION F.09:
l FACILITY COMMENTS:
This question asks for placing an order steps from a posted procedure.
Operators are not expected to memorize such procedure steps. The only
( significance of the order of steps in this procedure is that the heat 9
exchanger pump be started before the primary pump is started. Candidates should be given full credit for any sequence that indicates this precedence of operations.
NRC RESOLUTION:
Do not concur, this information is within the knowledge of a competent operator who has performed these steps numerous times.
QUESTION G.01:
FACILITY COMMENTS:
l There is no reason why an operator should be expected to remember the " maximum .
dose rate range" for a particular instrument when he does not have the l instrument in hand. In particular, the instrument is not used for routine surveys, so the operator will have very little experience with it. Finally, the operator may answer Part d. by including the general use requirements for j any survey instrument as requested in QUESTION G.ll.
NRC RESOLUTION:
Concur, Part a deleted and will not subtract credit for additional answers on j Part d.
QUESTION G.09 FACILITY COMMENTS:
Choice b. in the answers used incorrect terminology. Alpha emitters and '
neutron emitters cannot be specified in roentgen /hr. See Health Physics I and II, page 2 for definition of roentgen. Question should be deleted due to improper use of terminology.
l NRC RESOLUTION:
Do not concur, all candidates realized intent of question, j QUESTION G.10 FACILITY COMMENTS:
Answer given varies from our calculations, so that the correct answer is barely within the range of answers allowed. We calculate attenuation in water of 3.16E + 07 and total dose of 5.06E8 versus the 4.8 + or - 0.3E8 given on the l answer sheet.
NRC RESOLUTION:
Concur, will accept valid answers which used 3.16 vice 3.
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