IR 05000054/1989003
| ML20246C491 | |
| Person / Time | |
|---|---|
| Site: | 05000054 |
| Issue date: | 08/10/1989 |
| From: | Eselgroth P, David Silk NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20246C490 | List: |
| References | |
| 50-054-89-03OL, 50-54-89-3OL, NUDOCS 8908240407 | |
| Download: ML20246C491 (11) | |
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I U.S.NUCLEhRREGULATORYCOMMISSIONREGION'I
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OPERATOR LICENSING EXAMINATION REPORT u'.
_l EXAMINATION REPORT N (0L)-
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FACILITY DOCKET NO.: 50-054-R FACILITY 'ICENSE L NO.: R-81 LICENSEE: Cintichem, In P.O. Box 816-Tuxedo, New York 10987 F CILITY: 'Cintichem Reactor EXAMINATION DATES: -July.18-20, 1989
, - CHIEF EXAMINER: &
I D. M. Si' k, Senior Operations Engineer - (Date
- APPROVED BY: M S 7/O///
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K' W. Eselgroth, Chief,[PWR Section '0att /
. SUMMARY: Written examinations and operating tests were administered to three reactor operator (RO) candidates. All candidates passed the operating portion of the examination. One candidate failed Section A of.the-written examination.
p The other two candidates were issued licenses.
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8908240407 890815 PDR ADOCK 05000054
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DETAILS
' TYPE OF EXAMINATIONS: Replacement
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EXAMINATION RESULTS:
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l l l l 1 CHIEF EXAMINER AT SITE: D. M. Silk The following is a summary of generic deficiencies noted on the operating tests. This information.is being provided to aid the licensee-in upgrad-ing license and requalification training programs. No licensee response is require The candidates had difficulty explaining how the TLD badges are able to distinguish between whole body and skin dose There appeared to be a minor inconsistency in the candidates' know-ledge of and performance of various checklist items. While perform-ing RS-01, Reactor Console Checklist, and RS-02, Process . Equipment Checklist, the following examples were observed: The reason for the period meter indicating a sudden. positive or negative change when switching the Log Count Rate and Period Meters to CAL (calibrate) . (RS-01, step E.1). Checking battery water.on the 50 KW emergency generator (RS-02, step 11 L). Verifying that the secondary side of the heat exchangers are full (RS-02, step III F). Obtaining the reading for the canal makeup flow meter (RS-02, step VIII C).
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' The 'following is a summary of generic deficiencies noted from the grading of written examinations. (Note: Deficiency is considered to be present when all candidates lose points in a question that total 50% or greater of-the total point value of that question). This information is being l
provided to aid the licensee in upgrading license and requalification training programs. No licensee response is require Question N Knowledge
'A.02a- Subcritical Multiplication A.02b Neutron source strength and its relation to critical rod position A.05a Effect that power change has on shut down margin B.11 Negative reactivity sources that shutdown the reactor in the event of a loss of coolant D.05a Required operability of the Core Delta T Channel
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E.04 Mechanical design features of the safety flapper E.05d Conditions that will cause the emergency generator to trip F.08b Conditions in which the initiation of the evacu-ation sequence would not require the building to be evacuated G.08 Exposure limits (Quarterly vs. lifetime) Personnel Present at Exit Interview:
NRC Personnel: D. M. Silk, Chief Examiner Cintichem Personnel: W. G. Ruzicka, Manager of Nuclear Operations J. R. Stewart, Health Physics Supervisor S. E. Lupinski, Chief Reactor Operator M. D. Johnson, Reactor Supervisor Exit interview topics:
- The NRC received clarification from licensee personnel regarding the performance of various steps in the startup checklist The NRC and licensee personnel briefly discussed comments relating 1 to the written examination review (See Attachment 3). !
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- Earlier in the week, the NRC questioned the use of a personnel contami-nation monitor (PCM-1B, Eberline) that required the individual to first insert the right side of his body into the monitor and then with the unfrisked left hand depress a button to start the monitor. If the left hand was contaminated, the button would become contaminated and, thus, spread contamination to the next user's left hand. The licensee resolved this issue by requiring individuals to perform a hand frisk prior to using the personnel contamination monito Attachments: Written Examination and Answer Key (RO) Facility Comments on Written Examination NRC Response to Facility Cor.1ments and NRC Modifications to Answers as a Result of Grading Attachment 2 - Facility Comments on Written Examination
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Attachment 2-Facility Comments on Written Examination
A.01
. Another i source of- neutrons when shutdown is from.the decay of some fission fragments (delayed neutrons) as discussed in the pre-exam revie A.04 Another reason is due to the added uranium (reactivity).
- .Another possible answer. is: If the detector were-placed near enough to the . core, it would displace reflector and -absorb neutrons, thereby less thermal neutrons would be bounced into the core, thereby you must make up for loss - of . thermal - neutrons by pulling rod Sectio . There are only six (6) questions. We do not feel that this tests a- broad enough area of knowledg A - knowledgeable
. candidate could get less than 70% on a six question section and still-have adequate knowledge. - More questions in each
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section ' should be given or the . test should be ~ rearranged into fewer section We note that initial utility exams have three section ' B.03 Another reason is. that if the beam tube is ' dry (or partially dry), if it subsequently fills, positive reactivity will be added to the cor Another reason is to prevent build-up l from activation of radioactive corrosion products (T.M.
i page B-ll, RM-06-05).
B.04 .
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The Tech Specs are misleadin The 50kw emergency generator is NOT required to shut the damper Loss of electrical .
power will de-energize an electrical / pneumatic solenoid to i l shut the damper Electricity is used to keep the dampers j ope Recommend making the answer the two critical loads supplied by the generator (Training Manual, page D-13) Emergency Exhaust Fan Console (NIs, Area Radiation Monitors, etc).
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B.05 The. Technical Specifications also list another r equ i rement '-
IT.S. : 3.7 (2) "The minimum number of fuel elements in the core 'shall be
'3 Each control element shall count as'1/2 fuel element h
for'this purpose."
Recommend adding this as the third requiremen B.10 In,accordance with our refuel ' sheet (RM-10-13), when calculating " shutdown margin above Tech Spec minimum"' you first account for excess reactivity remaining in the core by using the critical gang heigh B.ll Another answer is control rod insertion (manual shutdown)
duelto the bridge excursion monitors alarming due to loss of-shield water.- When the bridge excursion monitors alarm, the evacuation sequence starts (RM-07-03). This warrants an-immediate shutdown.(RM-04-04).
C.02 Question . is worded such that - you could assume that the you are -looking for the change in- regulating rod height from'
when you feach 400kw to a later tim C.03 During the pre-exam review we asked that the third answer (bulk pool temperature changes) - be remove We would like to have it reinserte .
C.0 ;
k We'do not use the SER as a training document and therefore j use different nomenclatur Pool top detectors are bridge-excursion monitor Building air monitors are the l: continuous air monitors (CAMS) and the area radiation l monitors (T.S. page 11). Also, fission product radiation would be detected by the N-16 monitor located downstream of the core (T.M. page D-47).
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The Tech _ Spec requirement. of. 3.3 for peak to average flux (TS - 3.6.C page 20) is1 synonymous with peaking facto The answer should stand alon The question did not ask for the basi C.08 Another answer is the Reactor is required to be shutdown'du to loss of normal Reactor ventilation (RM-04 Section 4 .1, _
page RM-04-5).
The last two. answer key answers are " double jeopardy". They require that you get.the answer "Hx temp control valve fails closed" before'you can deduce the last two occurrence D.01 As discussed in the pre-exam review, pegged off-scale low recorder-is the same respons D.02-This question was discussed in the pre-exam review and was supposed to be reworde BON to perform a heat balance was not asked for. The only answer should be adjustment of the NI D.03 As discussed in the pre-exam review, each log count rate-(LCR) inhibit should be a separate answe Also, the .001% applies to all of the LCR inhibits (T.M. D-24, RM-03-02). .
E.04 Low plenum pressure is synonymous with suction pressure to the holdup tank (T.M. Figure B-7).
E.05 The' question did not ask for the voltage at which this occur RM-08-1 says "Upon loss of commercial power the emergency section is disconnected from the normal supply and powered by a 50kw motor generator set located in the facility transformer room." . .
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-E.06-100kw.'is equal to 2NL INp =. Full (100%) power, NL = Low (1%)
power,.2NL = 2% of Smw = 100kw] (T.M. Page D-24).
F.01 Two other-ways to manually actuate the emergency ventilation system are:
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-Initiate evacuation by Turning off the Reactor. Building's (Building #1)
. commercial power in'the control center in the Hot La Building-(Building #2) (RM-07-03, B.5). Lowering the area radiation' monitor (ARM) set point of~
~the bridge radiation monitor (RM-07-03, B.4).
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' This could . be interpreted as asking for the conditions that' satisfy. RS-44, .namely 750 milliseconds (RS-44 l 2.3). 50 milliseconds is also a requirement mentioned l: in RS-4 4, Section Recommend deleting this part and making Part 6 worth: 2.5 points.
.. Replacing control elements is another answer (RS-44 Section 2.2.2).
F.07 Another answer is: If a Tech Spec required piece of equipment fails or operates improperly, you would have to shutdown (RM-04-04).
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. Attachment 3 NRC Response to Facility Comments and Modifications to Answer Key
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Question No.' ' Response l
.A.01 Will accept " neutrons from the decay of fission products"
[ as an acceptable alternate answe A.04c Will accept "due to added uranium (reactivity)" as an acceptable alternate explanatio A.04d Will accept " HIGHER due to neutrons being absorbed-by boron-lined detector" as an acceptable alternate answe Section A The questions in Section A are in accordance with Examiner Standard ES-404 and 10 CFR 55.41. Regardless of the number of questions, a candidate must score at least 70% to pass the section. Four of the six questions had multiple parts and since there-is a possibility for obtaining partial
. credit, a knowledgeable candidate would not be at an unfair disadvantag B.03' Will not accept ". . . if the beam tube is dry. .." because the beam tube is always full. Also, will not accept "
prevent buildup from activation of radioactive corrosion products" because.it is encompassed in the two reasons stated in the answer ke B.0'4 Will' delete "and close building damper valves" because the dampers close on loss of power. Will required "
Energize console (NIs, ARMS, etc) as an answer for point B.05 Will accept " The minimum number of fuel elements in the core shall be 30" as an acceptable alternate answe B.10 Will accept " Excess reactivity remaining in the core " as an acceptable alternate answe B.11- Will only require " Control rod insertion" as an answer -
the reason for the insertion is not required because it was not asked for in the questio C.02 The answers will be graded based upon the assumptions made by the candidates.
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" Bulk pool temperature changes" will not be accepted because no reference material supports this answe C.06 Will note nomenclature differences. Will accept "N-16 Monitor" as an acceptable alternate answe C.08 Will accept " Reactor is required to be shutdown" as an explanation of power change. The question is not " double
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jeopardy" because the question tests the candidates'
knowledge of integrated plant response which are cause/
effert relationships.
! C.09 Will accept responses that state that the 3.3 peak to
average flux ratio is not to be exceede D.01a Will accept " Recorder pegged off scale low " as an accept-able alternate answe .02 The question was reworded and mutually agreed upon by l
the NRC and the facility representative. The answer will be change to better fit the question to the following:
" Heat power [0.5] will be compared to N1 power [0.5] and-the NIs will be adju.ted accordingly to correspond to o reactorpower[0.5]."
D.03 The responses in No. 2 in the answer key will be considered four separate responses.-
E.02a* This question was deleted because there is only one water source for the core spray while the question implies that there is more than one. Part b. of E.02 will be worth point E.02b The answer was changed to the following: "when pool leve decreases due to an uncontrolled loss of coolant."
E.04 " Low plenum pressure" will be acceptable for " loss of suction pressure to the holdup tank" in the answe E.05a Since the question did not specify a voltage, " Loss of power" will be an acceptable alternate answe E.06 Will note nomenclature difference F.01 Will accept " Turning off the Reactor Building commercial power..." and " Lowering the ARM set point of the bridge radiation monitor" as possible answer F.06a Question was deleted due to ambiguit Part b. of F.06 will be worth 2.50 point .
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p F.06b Will accept " Replacing control elements" as an acceptable alternate answe F.07b An additional required response'will be " shutdown the reactor" for 0.25 points and " Notify the SR0" will now be worth 0.25 points also.
- - F.08b # An additional required response will be " Performing an l
evacuation test" since the question does ask for more than
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one conditio NOTE: * - Discussed with licensee personnel during week of examination
- - Answer key changed as a result of checking reference material during grading t.f written examination.
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