ML20214U071
| ML20214U071 | |
| Person / Time | |
|---|---|
| Site: | University of Wisconsin |
| Issue date: | 12/01/1986 |
| From: | Burdick T, Ridgway K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20214U032 | List: |
| References | |
| 50-156-OL-86-01, 50-156-OL-86-1, NUDOCS 8612090124 | |
| Download: ML20214U071 (46) | |
Text
-
U.S. NUCLEAR REGULATORY CO MISSION REGION III Report No. 50-156/0L-86-01 Docket No. 50-156 License No. R-74 Licensee: ' University of Wisconsin
- Facility Name: University of Wisconsin Nuclear Reactor Examination Administered At: -Madison, Wisconsin Examination Conducted: November 4-6, 1986 Examiner: Kn[th hay N/ry/st, Date '
Approved By: ho M Br ck, [2// 8b I Operating Licensing Section Date' i
Examination Summary Examination administered on November 4-6, 1986 (Report No. 50-156/0L-86-01)
Examinations were administered to three operator candidates.
Results: All candidates passed these examinations.
i ht 8612090124 861202 PDR ADOCK 05000156 V PDR
REPORT DETAILS 4
- 1. Examiners K. R. Ridgway, Chief Examiner
- 2. Examination Review Meeting An examination review meeting is no longer conducted. Specific comments.
concerning written examination questions, followed by NRC responses, are enumerated in Attachment 1. Other question / answer changes noted following the examination are shown in Attachment 2.
- 3. . Exit Meeting At the conclusion of the examination an exit meeting was held.
The following personnel attended this meeting:
Facility Representatives
- -R. J. Cashwell, Reactor Director i
S. M.- Matusewic, Reactor Supervisor.
NRC Representative K. R. Ridgway, Chief, Operator Licensing Examiner
- The following observation were discussed:
i- During the oral examinations, the examiner noted two areas in which the 4
candidates were somewhat weak in their responses.
- a. Personal surveys when handling or. working with irradiated samples.
- b. Some of the immediate actions required by the operator in charge during emergency conditions such as high radiation or bomb threat evacuations.
Training in these areas should be emphasized.
p i
2 t
-~ ,,,m..-.-, r _ , - - . - , s., _ - , -m_--. , ,-,.-,,..,s.,,$~~---,m-ww,--%r,,--.,_,,w.,m,r_,-,ww
, m_..-ecy -,-
g
, ATTACHMENT I j RESOLUTION TO UNIVERSITY OF WISCONSIN'S COMMENTS ON NRC R0 EXAMINATION OF NOVEMBER 4, 1986 Facility Comments on Question / Answer A.01a Students may also state the safety limit for standard TRIGA Fuel (1000 C), and this should not detract from their grade.
Examiners Resolution Disagree: The facility Technical Specifications (TS) are specific to the University of Wisconsin Nuclear Reactor (UWNR).
Facility Comments on Question / Answer A.03b The question asked how delayed neutron fraction is related to reactivity of the reactor. The answer allows either of two responses.
The question asks for a relation between two quantities that are not directly related. The delayed neutron fraction does not vary as core reactivity is varied, nor does core reactivity (^k/k) vary as delayed neutron fraction is changed. What is related is the time response of the reactor to a positive reactivity change, as intimated by the answers given on the answer sheet.
The inhour equation is a relation between period and reactivity, in which the value of effective is treated as a constant in a reactor such as UWNR.
We believe part "b" of this question should be deleted.
Examiners Resolution Agree: Although the use of dollar as an expression for reactivity is mentioned in the Operator Training Manual (Reactor Physics II, Page 2); it is not used at the UWNR and not emphasized in the
. training program. Part b was deleted.
Facility Comments on Answer B.01, Item 9 Answer Item 9, Pneumatic sampler tube, is not standard facility nomenclature.
The grade should accept any of the following:
- 1. Rabbit tube.
- 2. Pn tube.
- 3. Pneumatic tube.
Examiner Resolution Agree: The answer has been changed so that any of the above are acceptable.
3
-_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ 1
Facility Comments.on Question / Answer B.06a
- The question does not address the pressure differential, only the flow.
Therefore, the answer should only require that flow in from primary to secondary.
Examiners Resolution Disagree: To obtain.a flow, gravity or differential pcessure must'be present; however, no points will be taken off if diffecential pressure is not included in the answer.
- Facility Comments on Answer to B.07 The answers given is relatively faithful to the SAR reference, but the explanation given to trainees at the facility is that electronic scram biases the magnet power supply output transistor off, while relay scram removes-the
'AC. power to the magnet power supply (actuator amplifier). This explanation should be accepted for full credit. Reference OTM-C&I IV.
Examiners Resolution Agree: The answer has been reworded to the above.
Facility Comments on Answer on C.08 Answer 2 refers to deletion of flow to cooling tower on low sump temperature.
This is not a part of the primary water temperature control, but is instead protection against freeze-up of the tower when the primary water temperature control system has operated to stop cooling of the primary system by bypassing the heat exchanger.
Thus, in order to provide three responses to the question, the candidates are likely to suggest cooling at the pool surface or evaporation, either of which should be accepted as an alternative to answer 2.
Examiners Response Agree: The answer for Part 2 will be modified by replacing " temperature diversion" with bypass." While pool surface evaporation affects pool temperatures, it is not considered a means of controlling the pool temperature and will not be included as an answer.
Facility Comments Question / Answer C.09 The question and answer written are faithful to the Technical Specifications (TS) cited (5.7.b and .c), but there is a possibility of confusion in the minds 4
of operators because TS No. 5.7.d also refers to 15 feet of water being the maximum which can be drained for any piping (including the pneumatic tube)
- which enters the pool. Therefore, the following systems should be acceptable answers:
J 4
- 1. Demineralizer
- 2. Diffuser 3ystem
- 3. Cooling system
- 4. Pneumatic tube I
- 5. Whale tube system
- 6. Any other piping entering pool Examiners Resolution Agree: This question will be modified by deleting "two" from "two pool systems" and the answer by adding cooling system, pneumatic tube system hnd whale tube system and giving the choice of any two systems.
Facility Comments on Answer D.03b The answer given requires "following a shutdown from a high power level" in addition to " low or intermediate power." Compensation is always necessary at low and intermediate. power unless the core is all new fuel. The answer should read, "any time except when at high power levels." Requiring a second condition will p'robably get the second response of, "when the gamma probably get the second response of, "when the gamma flux is high" or "when the detector is properly compensated." These should be acceptable answers.
Examiners Resolution Agree: Full credit was given if the answer included a statement equivalent to "any time except when at high power levels." The question has been changed by deleting "two" and adding to the answer the above statement for full credit or the existing answers for partial credits.
Facility Comments on Question D.04 The question is open-ended in that it does not specify the number of discrete responses required. Further, the answer included scrams, permissives, alarms, interlocks, and inputs to the automatic control . systems. The combination of ambiguities of no number of responses required and reference to automatic functions rather than the specific items indicated above make it unlikely that any candidate could get full credit on this question, despite his knowledge level. The question is, therefore, unfair.
Examiners Resoiution Agree: The question will be modified by adding after " automatic functions" (scrams, interlocks, auto control and alarms). This was clarified during the examination.
5
Facility Comments on Question / Answer D.05a The answer requires the number of thermocouples and their placement in the fuel element. Only one thermocouple is required, and only one is normally read out.
The wording of the question is more likely to get a response that a thermocouple is read out at the console with a temperature meter.
Examiners Resolution Agree: The answer will be modified deleting the location of the thermocouples in the fuel elements.
~ Facility Comments on Question / Answer D.07 Primary water temperature is actually measured and recorded at four points --
three on the systems temperature recorder and one on the core inlet temperature recorder. The answer should, therefore, accept three of the following responses:
Core inlet - RTD Primary Hx inlet - Thermocouple Primary Hx outlet - Thermocouple Demineralizer inlet - Thermocouple Examiners Resolution Agree: The question will be modified to "at what four points," and the assigned points adjusted to a.(8) and b.(7). The answer will be modified adding the.demineralizer inlet to parts a and b and adjusting the assigned points in both parts a and b.
Facility Comments on Question / Answer E.01 Since there are two linear power level channels, a response that uses them as two of the five required responses should be acceptable. Pulsing power level is required to be operable only for pulsing, and, thus, is not a required response for the way the question is worded.
Examiners Resolution Agree: The question will be modified by adding required "by Technical Specification" and the answer by adding 2 linear power channels (pico-animeters). Credit was given if two linear power channels were given in place of the pulsing power level channel.
Facility Comments on Question / Answer E.02 The question does not indicate the required number of responses, although the j answer gives three specific responses for full credit.
6
n'
..- UWNR 151,' Emergency Procedure, Leak Resulting in Draining of Reactor Pool, lists nine initiating events and indicators. -Those that are automatic are:
- 1. Pool Level Annunciator (high or. low)
- 2. Area Radiation (Bridge Monitor) annunciator
- 3. Tank Level Annunciator
- 4. Loss of pump running indicators on cooling system. mimic board.
Any of the four above listed items is correct,-and only two should be
. required, since no number of. responses was indicated.
Examiners Resolution Agree: The question will be changed to "the leakage of water from the pool can automatically (scram, interlock, auto controller, alarm) be detected by five different means, list four of these."- The answer will be modified by adding the bridge ARM alarm and the loss.of pump running indicators on cooling system mimic board, deleting the locations of the low pool level alarm, and adding (Any 4).
Facility. Comments on Question / Answer E.07
--The use-of the term " automatic function" at this facility usually refers to an action initiated by the instrument, as opposed to an alarm. Therefore, "no
. automatic action" would be an acceptable answer to this question.
Examiners Resolution Disagree: But, the question will be modified to state that automatic.means (scrams, interlocks, automatic controls or alarms). The definition
'of automatic was explained during the. examination.
Facility Comments cn Answer F.01 4
i Per the referenced procedure, a SR0 must be present at the facility, not necessarily in the control room.
Examiners Resolution 11 .
i The answer has been changed to "be present at the facility during the startup."
( Facility Comments on Answer F.08
! The procedure number, UWNR 130, should be accepted with, or instead of, the
[ procedure name.
Examiners Resolution f Agree: The answer has been modified by adding "or a UWNR 130 Form."
l 7
l
Facility Comments on Answer G.03 Answer number 2 is not applicable -- the system is a closed loop system.
Correct possible answers are:
- 1. CO2 gas is used as cover gas.
.2. Send-receive station.is located in a fume hood.
3.~ Pipes are curvec' through the pool water to prevent radiation streaming.'
- 4. The rabbit (sample carrier) is an airtight sample containment.
- 5. Gate valves that isolate the in pool portion of the system are closed except when the blower is running.
(Any two)
Examiners Resolution Agree: The answer has been modified by replacing Item 2 with 2 above, and adding Items 4 and 5 above.
The above resolutions, and the changes made in Attachment 2, either did no affect the applicants answers or were taken into account when assigning point value to the applicants answers.
8
q ATTACHMENT II
~
CORRECTION OR CLARIFICATION ON UNIVERSIT1 0F WISCONSIN EXAMINATION OF NOVEMBER 4,'1986.
Answer C.01
" Flooding of the beam parts and Pn tube" was included as an acceptable answer.
?
~
9
! A\%/N COPY U. S. NUCLEAR REGULATORY COMMISSION
- t ik - * !
l REAClDR OPERATOR LICENSE EXAMINATION F ACIL11 Y: _UNiyERSITY_QF_WlSCQUSly_
REACTOR TYPE: _TRIGA_MS_E______________
DATE ADMINISTERED: _8p/I1/99________________
EXAMINER: _RIpGWEY2 K.
CANDIDATE: _________________________
JNSIBUCIlgUS_IO_C69DJD91El Use separate paper for the answers. Write answers on one si de or I y.
Stcple question sheet on top of the answer sheets. Points for each question are indicated in par entheses af ter the question. The passing grade requires at least 70% in each category. Examination papers will be picked up sin (6) hours oftcr the examination statts.
% OF CATEGORY % OF CANDIDATE'S CATECORY
__YOLUE_ _19106 ___SCObE___ _YOLUE__ ______________C01Egggy_____________
PRINCIPLEE OF REACTOR OPERATION
_10:99__ _19 19 ___________ ________
A.
_19 99__ _19:1; ___________ ________ b. FEATURES OF FACILITY DESIGN
_12:59__ _11 63 ___________ ________ C. GENERAL OPERATING CH4RACTERISTICS
_13299__ _13:13 ___________ ________ D. INSTRUMENTS AND CONTROLS
_13 E9__ _16:bb ___________ ________ E. SAFE 1Y AND EMERGENCY SYSTEMS
_12:E9__ _12.b} ___________ ________ F. STANDARD AND EMERGENCY OPERAT]NG PROCEDURES
_16:99__ _15 sp ___________ ________ G. RADIATION CONTROL AND SA E1Y
_22299__ ___________
Totals Final Gr ade .
AlI wor L done on thi s ex anii nati on is my own. I have neither given nor received aid.
Candidate's Signature-
d v NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIDNS 1
During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. 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 cheating.
- 3. Use black ink or dark pencil gely to f acilitate legible reproductions. l 1
l
- 4. Print your name in the blank provided on the cover sheet of the examination. t
- 5. Fill in the date on the cover sheet of the examination (if necessary) .
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
O. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write gnly gn gng sidg of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least tht gg lines between each answer.
i
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they ar2 commonly used in f acility litgtatutg.
- 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 required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the gxamingt only.
i 17. You must sign the statement on the cover sheet that indicates that the i 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 completed.
-. . - - _ -. _. _ - - - - . - _ . . _ - -__. -. -~
d
- 10. When you complete your examination, you shells
- o. Assemble your examination as in11ows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are part of the answer.
- 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 examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked. .
-- , - - , , , , , , , , - , - - , , , - , , , - - - - - - - - - - - - - , - - - - + - - - - - - - - - - - - - - , - - -
8 __EBING1ELEE_DE_BE9GIDB_DEEBBIIDN PAGE 2 GUESTION A.01 (3.00)
- c. What is the safety limit specified in the f acility Technical Specifications? (1)
- b. How is it assured? (2)
DUESTION A.02 (1.00)
If _ the reactor period im 80 seconds what is the doubling .
time? Show your work.
QUESTION A.03 (2.00)
- c. Define delayed neutron fraction. (1)
- b. List one reason why delayed neutrons are important in reactor operations. (1)
QUESTION A.04 (1.00)
R actor power is at 10 watts and increasing on a 10 second psriod. How much time is required for the reactor to reach 200 kilowatts? Show your work. (Neglect heating effects)
QUESTION A.05 (3.00)
)
The following terms sound similar but are very different.
Explain the difference betweens
- c. Fast and prompt neutrons. (1) b Slow and delayed neutrons. (1)
- c. Activity and Reactivity. (1)
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
8t__EBING1!1EE_DE_BEeGIDB_DEEBBI19N PAGE 3 t >
g s s GUEST 10N A.06 (1.00) ,
' , i
-i x List two reasons why.the neutron sour,c.e '
is needed,71uring ctartup of the reactor. ,
i I.,
s, QUESTION A.07 (1.00) '
Define reactor period.
QUESTION A.08 (2.00) ,
Explain how Xenon is formed and dehleted during reactor ~
operations. s t
QUESTION A.09 (1.00)
What is meant by the term " Multiplication Factor" or Keff?
(***** END OF CATEGORY A *****)
Ea.__EEeIWBER_QE_EeG1611LDESIGN PAGE 4
-90ESTION B.01 (2.50)
- From Figure 1, name the teen components of the reactor core.
(O.25 ea)
QUESTION B.02 (2.00)
What type of startup source is used at your facility and how does it work?
QUESTION B.03 (2.00)
Correctly match the piping color codes. (0.5 each)
- a. Contaminated water discharge. 1. Green
- b. Softened water. 2. Black
- c. City water. 3. Red
- d. Air line. 4. Blue QUESTION B.04 (1.00)
Briefly describe the action of the regulating rod following the receipt of a scram signal.
QUESTION B.05 (1.50)
List the three nuclear instrument channels used at your facility (0.75) and their ranges. (0.75)
QUESTION B.06 (2.00)
- c. Describe the flow of water if a leak should develop in a heat exchanger tube. (1)
- b. How could a very small leak of this type be detected.(1) l
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
Bi__EEBIWBEE_DE_E9GILIILDESIGN
- PAGE 5 QUESTION B.07 (1.00)
The safety channels (picommmeters) have two different scram circuits. Explain the functional difference between these circuits.
QUESTION B.08 (2.00)
Nrme the two types of control blades and the neutron cbsorbing materials used in them.
. DUESTION B.09 (1.00) - ,
l Siet materials are the moderators in your reactor?
t
(***** END OF CATEGORY B *****) ;
1 '
- - - - - , - - . - - , . - - - -- , or,- .,- -.-.e-.--w. .--- ---w-.--.r-r - - - - - .,- - - - - .--,-,-v.- ww-+ .--- , , - - .
Gi__SENEBOL_DEEB811NG_GNeBeGIEsigI1gg pagg 6 QUESTIDN C.01 (1.00)
What fuel configuration is specified by Technical Specifications to prevent flux peaking in a mixed core?
QUESTION C.02 (1.00)
What are the normal steady state values shown on the Startup Checklist fort
- c. Control blade magnet currents? (0.5)
- b. Exhaust filter differential pressures? (0.5)
QUESTION C.03 (2.00)
- o. Define moderator temperature coefficient. (1)
- b. Why is it important to have a negative coefficient? (1)
QUESTION C.04 :2.00)
State the Technir Specification maximum value for:
- c. Nonsecured aperiments. (1)
- b. The worth of .ny single experiment. (1) i QUESTION C.05 (1.00)
The Facility Technical Specifications require the cciety blade scram times to be measured annually. Following what other two circumstances must the drop times be measured?
QUESTION C.06 (1.50)
What three conditions must be fully satisfied to have the roactor secured?
l
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
l t
G,._ENEBBLEEB911NG_GL40BAGIEBIEIIGE_ PAGE 7 l
I QUESTIDN C.07 (1.50)
List three dif f erent f actors that may cause a core rcactivity change other than a control blade position change.
QUESTION C.OB (2.00)
' Describe the three means by which the primary water tcmperature is controlled.
QUESTION C.09 (1.50) .
Tachnical Specifications require pool systems to be no more than 15 f eet below the pool surface.
- c. List two of these systems. (1)
- b. Why do these limitations exist? (0.5) i
(***** END OF CATEGORY C *****)
Dz__INDIBUM NIE_8tfD_GQNIBQL3 PAGE O QUESTION D.01 (2.00)
- c. Briefly describe how a fission chamber or counter works. (1)
-b. Where is a fission chamber used at your facility? (1)
QUESTION D.02 (2.00)
What f our protective actions are provided by the Log Countrate startup channel?
QUESTIDN D.03 (2.00)
- o. Briefly describe the distinguishing features / functions of a compensated ion chamber (CIC). (1)
, b. Under what condition or conditions is the CIC performance superior to an uncompensated chamber in determining the power level? (1)
QUESTION D.04 (3.00)
List all automatic functions (scrams, interlocks, auto controls, cnd alarms) that are provided by the nuclear instruments using compensated ion chambers. (3)
QUESTION D.05 (2.00)
- c. Describe how the fuel temperature is measured? (1)
- b. What automati c f unction is provided by the f uel temperature channel? (0.5) and what is the set point?
(0.5)
QUESTION D.06 (1.50)
What control blades or rods can be used for automatic control?
l
~
(***** CATEGDRY D CONTINUED ON NEXT PAGE *****)
D,.__INSIBWtNNIS_eND_GDNIBAr PAGE 9 QUESTION D.07 (1.50)
- c. Primary water temperature is measured at what f our points? (0.8)
- b. What type of detectors are used? (0.7) l I
(***** END OF CATEGORY D *****)
l 1
Es.__E9EEIY_GUQ_E!!EBGENGY_EYEIE53 PAGE 10 l 4
QUESTION E.01 (2.50)
List the five safety system channels that are required by Tech. Specs.
to be operable before the reactor can be operated (1.25) and give the operating modes in which they are required. (1.25)
QUESTIDN E.02 (2.00)
The leakage of water from the pool can be automatically (scrams, interlocks, auto controls, alarms) be detected by five different means. List four of these.
QUESTION E.03 (2.00)
Criefly describe the Thermal Column and Beam Port V ntilation System.
QUESTION E.04 (2.00)
Since the pneumatic sampler piping enters the pool below the water level, what precautions have been taken to prevent oiphon action if the piping should leak?
QUESTION E.05 (1.00)
- c. By Technical Specification, when is the ventilation
'eystem required to operate? (0.5)
- b. How is the operation assured? (0.5)
QUESTION E.06 (3.00)
W e are the four radiation area monitors located (2.0) and what are their set points? (1.0)
(***** CATEGORY E CONTINUED ON NEXT PAGE *****)
Ez__BBEEIY_BNQ_g!!EBQgNQy_gyglggg PAGE 11 QUESTION E.07 (2.00)
- c. What is the f unction of the Beam Port Monitor? (1)
- b. Where are the detectors located? (0.5) and what automatic function (scram, interlock, auto control, or alarm) do they have? (0.5) l
(***** END OF CATEGORY E *****)
I'. . ' G~ ,41;1. .l G + e v ::. l. hL. . i.d Cl. 3C. ..V. . t._i.i.'.i.. R.. .'.1._l i_ si . f.. l u. t .L. .i_'i f.i tt. i. ;.
I 's .i I. .
t UL5 l'1 (*; , I.O1 ( 1. vW lo Ur.% 101 O .. wl.nl .o.- 1 1.( -- +1es4ine . c q u i e < ii et : t f c.i - es.
--i ru 11 c l *. L o r t t , of t he r e,w t or '
UUL:i302, F.N i 'J. 00 )
ti. L .4 e i . t er.c . t -. nt y w! .ul t ! vo y t; cit e i t. perniitted it. Le v t e 12 i L.? (1:
ls . - l .!s .c) L.or a rien i 2 e iisiE c1 < r 9c *i: y d:.t e' ( 3 ',
LUL..r1 10: iF ( 1. im l
[ i+ , & i .1 l a e c 5 m,- s : i i: t e at t i o*:t t.h otn d i.c t ! c . 1.y 1i.e .
i O p tl httl UpO. F a ut-il t Of e- 6 e is l t U t.~ t5Vii' u,T.U*is.Asal O?
L l
ut Li E.'i 1 U' .' i . O. ( 1. 00'/
l .'t i v t t.t e t h e . . r e f i n t, requ,6 er .t ' il s . 't ; t ified 2i UWMir EDI t'(e 1. te..C.. L i s c. _ . l O!' i= O F ' t t ' d. 's. i s ! g : 'J QULSfIDe F . R- ( 1. OCO Wi:o ten cutlic" . :: e r eactor- r c : L w i. . si l t.e:1.ip a s c r e.m or Ul!) I t t On t i O! 6 0 . Cp cri (di D: H.O' C C DI. ' D3 0 3 L-hief :Ii 9 UU'.S / i Ib ; F' 0- ( 1. OO 's Uiiut l es m- d; ii ; t. ;.:_1 i ti . s l io _d t' t.f i e.ct i b ', in cper Lier ai ti:c c oi s aol o i -f c- r ;:1 Icvel c l o rr. 1, t.;c i s eG UUi 5110 ! F.Oi (2.D0)
'i t' o t.e. i et tti mt i,.b er or e dl oi.i c'i evutueiiv- e 3 er ::. ic VUCLi Vc G e tLt . .E iiC i i Oll E, lO p Cl i Ci s'. . e i ..tN. S*1%. a.
4- .)+- (.. t i[ E I:.i th i l f ' ' '> i ? .' _ l[ . '
- M* ~ \ 'I I ( ,[-> i' + ' - - a
Es.__SI9ND9BD_MD_Et!EBGENGX_DEEBBIING_EBDREDUB5s pase as QUESTION F.08 (1.00)
Before a pneumatic tube experiment can be performed, what form must be complete and approved?
QUESTION F.09 (1.50)
What three primary actions should the operator on duty take (
if a bomb threat is received while the reactor is operating? L k
1
(
(***** END OF CATEGORY F *****)
Es.- B0DieIIDtLCDt!IBQL_et!D_SeEEIY PAGE 14 QUESTION G.01 (2.00)
- o. If the gamma dose rate from a point source is 1.6 rem /hr at 25 centimeters from the source, what is the dose rate at 2 meters? Show your work. (1)
- b. How 3ong could you remain at the 25 centimeter location without exceeding the 10CFR2O quarterly whole body dose limit? Ignore-the closeness to the source. Show your work. (1)
QUESTION G.02 (2.00)
- c. Facility SOls require that the nitrogen diffuser be operated when needed. Describe the operation of the diffuser. (1) '
- b. Why is it necessary? (1)
QUESTION G.03 (2.00)
Nrme two features of the pneumatic sample transfer system dssign that are utilized to reduce radiation or
- rcdioactivity.
QUESTION G.04 (1.50)
Name three types of personal monitoring devices.
QUESTION G.05 (2.00)
What are the 10CFR2O regulations f or posting the f ollowing creas?
- 1. Radiation area (1)
- 2. High radiation area (1)
QUESTION G.06 (1.00)
In addition to posting, name two additional 10CFR2O l rcquirements for a high radiation area? (1)
(***** CATEGORY G CONTINUED ON NEXT PAGE *****)
1 Ea.__B9D1911W _G W IB E _9NQ_E9EEIY PAGE 15 QUESTION G.07 (2.00) l
- o. Define curie. (1) j
- b. Why is it necessary to use more shielding for a curie '
of one material than is required for a curie of another material. (1)
QUESTION G.08 (2.00)
State the whole body dose limits of 10CFR20.101. Include all prerequisites if any.
l l
(***** END OF CSTEGORY G *****)
(************* END OF EXAMINATION ***************)
8,.__EBINGlELEli_QE_BE9GlQB_QEEB911Qt4 PAGE 16 ANSWERS -- UNIVERSITY OF WISCONSIN -86/11/04-RIDGWAY, K.
ANSWER A.01 (3.00)
MASTER COPY
- c. Fuel element temperature shall not exceed 1150 degrees C. (1)
- b. By limiting fuel temperature to 400 degrees C (750 F)
(1) and by limiting reactor power to 1.25 MW. (1)
REFERENCE Fccility Technical Specifications 2.1 and 2.2 ANSWER A.02 (1.00)
Doubling time = Period times 0.6'73
= 80 X O.693
= 55.4 secs.
REFERENCE UWNR Operato s Training Manual (OTM) i l
ANSWER A.03 (2.00) l o. Delayed neutron fraction = delayed neutrons /
delayed neutrons + prompt neutrons (1)
- b. If the inserted reactivity exceeds the delayed neutron fraction, the reactor will not be controllable. (1)
, REFERENCE UWNR OTM ANSWER A.04 (1.00)
P= P* exp (t/T) 200000 = 10
- exp (t/10)
In 20000 = t/10 t= 9.90
- 10 = 99 sec = 1.65 min. (1.0) i REFERENCE UWNR OTM 4
'4
l l.
Br__EBING1ELgs_DE_BEBGIQB_QEEBBI1QN PAGE 17 ANSWERS -- UNIVERSITY DF WISCONSIN -86/11/04-RIDGWAY, K.
ANSWER A.05 (3.00)
- c. Fast neutrons refer to those at high energy levels (0.5); while prompt neutrons are those released at the time of fission. (0.5)
- b. Slow neutrons are neutrons at low energy levels (0.5);
while delayed neutrons are those that are emitted from fission fragments after the fission event. (0.5)
- c. Activity is the rate of radioactivity decay (0.5);
while reactivity is the amount of deviation of a reactor from the just critical condition. (0.5)
REFERENCE UWNR OTH ANSWER A.06 (1.00)
To provide sufficient neutrons to get the chain reaction going. (O.5)
To generate a reliable signal to the neutron detectors that monitor the startup range of power. (0.5)
REFERENCE UWNR OTM ANSWER A.07 (1.00)
The time to change the neutron flux or reactor power by a factor of e (2.718). (1)
REFERENCE UWNR OTM ANSWER A.08 (2.00)
Xenon is formed directly as a fission product (0.5) and by the decay of 1135 (0.5). It is depleted by decay (0.5) and by neutron absorption (0.5).
es.__t'BINQlEkEE_QE_BE9Q1QB_QEE8@llQN PAGE 10 ANSWERS - UNIVERSITY DF WISCONSIN -86/11/04-RIDGWAY, K.
REFERENCE !
UWNR UTH ANSWER A.09 (1.00)
It is the ratio of the number of neutrons of any one ccneration to the number of neutrons in the preceding ceneration. (1)
REFERENCE Facility DTM I
Ea__EEGIURgE_QE_E9Q1(IIY_Qgg1EN PAGE 19
, ANSWERS -- UNIVERSITY OF WISCONSIN -86/11/04-RIDGWAY, K.
ANSWER B.01 (2.50)
- 1. CIC detector. (0.25)
- 2. Log N detector. (0.25)
- 3. Fission counter detector. (0.25)
- 4. Regulating blade. (0.25)
- 5. Safety blade.. (0.25) ,
- 4. Gamma chamber. (0.25)
- 7. Safety blade. (0.25)
D. Beam port. (0.25)
- 9. Pneumatic tube, rabbit, or PN tube. (0.25)
- 10. Safety blade. (0.25)
REFERENCE ,
Facility SAR Figure 11 ANSWER B.02 (2.00)
Radium - Beryllium source. (1)
Ra (alpha, neutron) Be. (1)
REFERENCE UWNR OTM ANSWER B.03 (2.00)
- a. 3. Red (0.5)
- b. 4. Blue (0.5)
- c. 1. Green (O.5) l
- d. 2. Black (0.5)
REFERENCE UWNR OTM ANSWER B.04 (1.00)
The regulating rod'does not scram (0.5) and is not driven in automatically. (0.5)
REFERENCE Facility SAR 3.2.3 l
)
Es.__EEOIURgg_QE_E@Q1(LIY_QEgl@N PAGE 20
, ANSWERS -- UNIVERSITY OF WISCONSIN -86/11/04-RIDGWAY, K.
ANSWER B.05 -
(1.50)
Log count rate (0.25) Source range to full power. (0.25)
Log N (0.25) Intermediate range to full power. (0.25)
Picoammeter (0.25) High source range or (2 decades above shutdown) to full power. (0.25) -
REFERENCE Fccility OTM I & C ANSWER B.06 (2.00)
- c. During normal operation secondary water is at a higher -
pressure and would flow into the primary system. (1) b By high conductivity in the primary water. (1)
REFEhENCE Fccility SAR 2.3.2 ANSWER B.07 (1.00)
When tripped the electronic (f ast scram) biases the magnet power supply output transistor off (0.5) while the relay scram (slow scram) cuts off AC power to the magnet power supply. (0.5)
REFERENCE Fccility SAR 2.5.7 ANSWER B.OB (2.00)
- 1. Safety blade (0.5) - Boral or baron carbide (0.5)
- 2. Regulating blade (0.5) -
Stainless steel (0.5)
REFERENCE Fccility SAR 2.1.5 and 2.1.6 ANSWER B.09 (1.00)
Zirconium hydride (0.5) and water (0.5)
Ez__EEBIWBEE_DE_E9G161Iy_DEgigN PAGE 21 l
ANSWERS -- UNIVERSITY OF WISCONSIN
- f. -86/11/04-RIDGWAY, K.
REFERENCE Fccility OTM D
9 9
d
Ca.__SEMBOL_QE TitMii_Gt!960GIEBIEIIGE PAGE 22
. ANSWERS -- UNIVERSITY OF WISCONSIN -86/11/04-RIDGWAY, K.
ANSWER C.01 (1.00)
FLIP fuel used will comprise at leased 35 fuel elements (0.5) and will be contiguous (0.25) in the central region of the core. (0.25)
REFERENCE Fccility Technical Specification 5.2.b and c.
ANSWER C.02 ,
(1.00)
- c. O.6 to 0.7 amps "
- b. O.25 to 2.5 inches REFERENCE Fccility SDI 111 ANSWER C.03 (2.00)
- o. Ratio of change in reactivity to change in moderator temperature. (1)
- b. An increase in temperature from a transient leads to a decrease in reactivity (0.5) with a decrease in power.
(0.5)
REFERENCE Fccility OTM Reactor Physics ANSWER C.04 (2.00)
- c. O.7% delta k/k. (1)
- b. 1.4% delta k/k. (1)
REFERENCE Fccility Technical Specification 3.6 ANSWER C.05 (1.00) 3 Scram time must be measured following modifications (0.5) or maintenance. (0.5)
i Ga.__EEt!EBOL_QLEBBIltMi_Gt!980GIEBIEIIGE PAGE 23 ANSWERS - UNIVERSITY OF WISCONSIN -86/11/04-RIDGWAY, K.
REFERENCE Fccility Technical Specification 4.1 ANSWER C.06 (1.50)
- c. The reactor is shut down. (0.5)
- b. Console key DFF (0.25) and removed. (0.25)
- c. No in-core work in progress (0.5) or there is no work in progress involving fuel (0.2), experiments (0.1), or reactor maintenance (0.1), and no maintenance work on control blades. (0.1)
REFERENCE Facility Technical Specification 1.2 ,
ANSWER C.07 (1.50)
- n. Temperature (0.5)
- b. Core change (0.5)
- c. Experiments (0.5)
- d. Xenon (0.5)
- o. Fuel depletion (0.5)
- f. Flooding of beam ports or PN tube (0.5)
(Any 3)
REFERENCE Casic reactor theory ANSWER C.08 (2.00)
\
- 1. By primary water temperature control of the secondary water flow to the heat exchanger. (0.8)
- 2. By bypassing flow from the cooling tower sump to the cooling tower. (0.8)
- 3. By changing the cooling tower fan speed. (0.4)
REFERENCE Facility SAR 2.3.2.
4
Gs.__GENEB86_QL2EB8IING_GUBB9GIEBIEIIGE PAGE 24
, ANSWERS -- UNIVERSITY DF WISCONSIN -86/11/04-RIDGWAY, K.
ANSWER C.09 (1.50)
- c. 1. Diffuser and other auxiliary system pumps. (0.5)
- 2. Cooling system. (0.5)
- 3. PN System. (0.5)
- 4. Whale tube system. (0.5)
- 5. Domineralizer inlet and outlet piping. (0.5)
(Any 2)
- b. In case of a leak, pool water will drop no lower than 15 feet from the top of the pool. (0.5)
REFERENCE Fccility Technical Specifications 5.7.b and c
. - - - , . - , - . _ . , . . , . . , . , , . _ ..-._y . _ . . , . ,, , , , _ . , _ - - _ _ _ _ , _ _ ~ , _ _ . _ _ - _ _. ___ _ _ _____ __ _ __
Dz__INEIBWUENIE_9ND_GDNIBDLE PAGE 25 ANSWERS - UNIVERSITY OF WISCONSIN -86/11/04-RIDGWAY, K.
ANSWER D.01 (2.00)
- c. The inner chamber wall of a fission chamber is coated with enriched uranium (0.25). Fission products resultir.g from the fission of the uranium atoms (0.25) cause ionization of the chamber gas (0.25) proportional to the neutron flux. (0.25)
- b. The startup or Log rate channel. (1)
REFERENCE Facility SAR 2.5.1 ANSWER D.02 (2.00)
- c. Blade withdrawal prohibit when log count rate is less than 120 cpm. (0.5)
- b. Blade withdrawal prohibit when fission counter is moving. (0.5)
- c. Fission counter insert prohibit when log count rate is greater than 10E6 cpm. (0.5)
, d. Alarm if log count rate is greater than 10E6 cpm (0.25) or if the interlock switch is placed in " Defeat" position. (0.25)
REFERENCE Facility OTM C&I ANSWER D.03 (2.00)
! c. One region of the CIC detector is filled with boron gas l or coated with boron (0.25). Alpha particles produced
, by the n-alpha reaction in baron produces ionization in l
the gas along with gamma ionization (0.25). The other region of the detector has gamma produced ions only (0.25). The difference in currents produced in these regions is proportional to the neutron flux. (0.25)
- b. Any time except when at high power levels (1) or At low or intermediate power levels (0.5) and for the indicated power level f ollowing a shutdown f rom a high power level. (0.5)
REFERENCE Facility OTM C&I 1
., . - . ,.- __---_-- - - - -.... ,- ~ - .---_ - .. ,. . - _ _ . - . _ - - - . - - . . - - _ - - . - . -- . - . _ . . . , - - . - . - - - - - -
Da.__INEIBWUENIE_0ND_GQUIBQLE PAGE 26 ANSWERS -- UNIVERSITY OF WISCONSIN -36/11/04-RIDGWAY, K.
ANSWER- D.04 (3.00)
- 1. Two safety channels (0.4) -
auto control (0.2),
electronic and relay scrams if power exceeds 125%
(0.2), electronic scram on loss of picommmeter r'.gnal (0.2), and alarm for power greater than 115% (0.2).
- 2. Log N Channel (0.4) -
1KW pulse and square wave permissive. (0.2)
Period (0.4) -
electronic scram if period is less than 3 sec. (0.2), relay scram f or period less than 5 sec.
(0.2), alarm for period less than 10 sec. (0.2), and period limit of 20 sec. in auto control. (0.2)
REFERENCE "
Facility SAR 2.5 ANSWER D.05 (2.00)
- c. By thermocouples (0.5) placed in the fuel-moderator material of the fuel element. (0.5)
- b. Trip point of 400 degrees C. (0.5) causes a scram in all modes. (0.5)
REFERENCE Facility Technical Specifications 3.3 and SAR 2.1.3 ANSWER D.06 (1.50)
No. 2 Shim blade. (0.5)
Transient Rod. (0.5)
Regulating Blade. (0.5)
REFERENCE Facility OTM C&I ANSWER D.07 (1.50)
- c. At core inlet, at heat exchanger inlet, at heat exchanger
- outlet, and demineralizer inlet. (0.2 each)
- b. Core inlet - Resistance temperature device or RTD (0. 3)
Heat exchanger inlet and outlet and demin inlet - thermocouples (0.4) 1 l
- _ _ - _ . . _ ____ _ __.-_..-_--____ _ __._._-__ __-._._ _ _-~ _ _ _ _ _
E^- lW IBU N NIE_eND_cgw1gggy PAGE 27
. ANSWERS -- UNIVERSITY OF WISCONSIN -86/11/04-RIDGWAY, g, REFERENCE Fccility SAR 2.5.1 l
t i
I
, l l l l
l l
l l
Es.__E9EEIY_850_EUEBEENGY_EYSIE55 PAGE 28 ANSWERS -- UNIVERSITY DF WIBCONSIN -86/11/04-RIDGWAY, K.
ANSWER E.01 (2.50)
Fuel element temperature (0.25) - All modes (0.25) l Log power level (0.25) - Steady state (0.15) and square wave (0.1)
Two Linear power level (Picommmeters) (0.25) - Steady state (0.15) and square wave (0.1)
Ctartup countrate (0.25) -
During startup (0.25)
Pulsing power level (0.25) - Pulse mode (0.25)
REFERENCE Fccility Technical Specification 3.3.2 ANSWER E.02 (2.00)
- 1. Low pool level reactor scram (0.5)
- 2. Alarm, low pool level (0.5)
- 3. Alarm, bridge area radiation monitor (0.5)
- 4. Alarm, Hold Tank high level (O.5)
- 5. Alarm, loss of pump running indicators on cooling system mimic board (0.5)
(Any 4)
REFERENCE Facility SAR 2.5.7 and 2.5.8 ANSWER E.03 (2.00)
A system with blower (0.5) and HEPA filters (0.5) that I cpplies a negative air pressure (0.5) in the open column and ports to prevent contaminated gases (AR41) from backing into the reactor room. (0.5)
REFERENCE Facility SAR 2.4.3 ANSWER E.04 (2.00)
A solenoid valve at the highest point of the system (0.5) i opens (0.5) when the blower is off (0.5) allowing air to Gnter if a siphon action starts. (0.5)
l
- l E,.__E9EEIY_9ND_EUEBSENGY_EYSIEME PAGE 29 l ANSWERS -- UNIVERSITY OF WISCONSIN -86/11/04-RIDGWAY, K.
REFERENCE Fccility SAR 2.4.4 ANSWER E.05 . (1.00)
- c. When reactor is operating (0.4) except for 2 days for repairs. (0.1)
. b. By daily Prestartup Checks (0.4) and weekly operation verification (0.1)
REFERENCE Fccility Technical Specification 3.5 and 4.2.4 and SGI 110 ANSWER E.06 (3.00)
- 1. Reactor Bridge (0.5) Just above 100% power or 50 mr/hr. (0.25)
- 2. Domineralizer (0.5) Just above 100% powe* or 90 mr/hr. (0.25)
- 3. Thermal Column Door (0.5) Just above 100% power or 10 mr/hr (0.25)
- 4. At pneumatic sampler send-receive station (0.5) 10 mr/hr (0.25)
REFERENCE Fccility SAR 2.5.9 and SOT 110 and 131 ANSWER E.07 (2.00)
- c. A radiation monitor used to prevent unknowingly generating high radiation levels from open beam ports (1)
- b. The detectors are located on the reactor room walls in direct line with the beam pcrts (0.5) and give audible and visual alarm at the console. (0.5) l
_ . . - _ _ - _ _ . _ . _ . _ _ . _ . _ - , . ~ . _ _ . _ . . _ _ _ _ _ _ . _ _ _ _ , . . _ _ . _ . - _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ - _ _ . . _ _ . _ _ . . . , _ _ _ _ . _ _ _ - -
Em__HIOND9BD_9ND_EUEBGENQy_DEEB911NG_EBDGEDWBE@ PAGE 30 ANSWERS -- UNIVERSITY DF WISCDNSIN -86/11/04-RIDGWAY, K.
ANSWER F.01 (1.00)
A licensed operator in the control room. (0.5)
A senior operator will be present at the facility during the startup. (0.5)
REFERENCE Fccility SDI 001 ANSWER F.02 (2.00)
- c. 25 rems or less. (1)
- b. Reactor Director. (1) ,
REFERENCE Fccility SOI 006 ANSWER F.03 (1.50)
- 1. Determine whether it is a gaseous or particulate alarm from the recorder. (0.5)
- 2. If reading is above the alarm set point, shutdown the reactor. (0.5)
- 3. Determine if the reading is real (0.3) or due to external sources (0.1) or instrument malfunctions.
(0.1)
REFERENCE Fccility SOI 155 ANSWER F.04 (1.00)
Licensed operator in the control room (0.5) and a Senior Operator in the building or readily available on call. (0.5)
REFERENCE Facility SDI 001 ANSWER F.05 (1.00)
Senior Operator (1)
E __EIGND9BD_8NQ_EGESQENGY R EBBIlNQ_EBQQEDWBEE PAGE 31 ANSWERS -- UNIVERSITY OF WISCONSIN -86/11/04-RIDGWAY, K.
REFERENCE Fccility SDI 001 ANSWER F.06 (1.00)
If reactor has not scrammed automatically, manually scram it.
(0.6) Notify Police & Security that the laboratory is manned (0.2) and corrective action is being taken. (0.2)
REFERENCE Fccility SDI 150 ANSWER F.07 (2.50)
- 1. Assure the reactor is shut down. (0.5)
- 2. Assure the evacuation alarm has sounded. (0.5)
- 3. Evaluate situation (0.25) and take isotope production forms along. (0.25)
- 4. Delegate staff to assure all areas are evacuated (0.25) and to block off Johnson Drive (0.25)
- 5. Notify Reactor Supervisor (0.25) and Reactor Director.
(0.25)
REFERENCE Fccility SOI 150 ANSWER F.08 (1.00)
A Request for Isotope Production Form or a UWNR 130 Form. (1)
REFERENCE Fccility SOI 130 ANSWER F.09 (1.50) l l 1. Shut down the reactor. (0.5)
- 2. Notify a SRO and the campus Police & Security. (0.5)
- 3. Place the reactor laboratory in maximum security condition. (0.5) elEFERENCE Fccility SOI 153
E __EleNDeBD_eNQ_EUEBEENGr_QEEBBIINQ_EBQGEDMBEE PAGE 32 ANSWERS -- UNIVERSITY OF WISCONSIN -86/11/04-RIDGWAY, K.
Fccility SDP 600 9
9 l
1
-- . -__ _ _ _ . _ - . . . . , ~ . - . - . . ..... . _ . - . . . - _ - - _ - - , - . . _ . . . _ _ , , . , . , _ . _ , . . . . - _ - . . . . _ -
PAGE 33 Et__B001011QN_QQNIBQ(_@NQ_E9EEIY ANSWERS -- UNIVERSITY DF WISCONSIN -86/11/04-RIDGWAY, K.
ANSWER G.01 (2.00)
- b. Quarterly whole body dose = 1.25 rem or 1250 mrem (0.5) 1250 mrem /hr/1600 mrem /hr = 0.78 hrs or 47 min. (0.5)
REFERENCE Casic theory and 10CFR20.101 ANSWER G.02 (2.00)
- c. A water pump directs surface water downward across the top of the core. (0.5)
- b. To delay the surfacing of radioactive nitrogen formed by the 016(n,p)N16 reaction (0.5). Since N16 has a 7 second half life, most of it will be decayed before it surfaces, reducing the exposure rate above the pool.
(0.5)
REFERENCE Facility OTM IV ANSWER G.03 (2.00)
- 1. CO2 gas is used as the transport medium.. (1) l 2. Send - receive station is in a fume hood. (1) l 3. The sample container (rabbit) is air tight. (1)
! 4. Pipes are curved thru the pool water to prevent radiation streaming. (1)
- 5. Isolation of the in pool portion of the system when it is not operating. (1)
(Any 2)
REFERENCE Facility OTM I
Es__BeDiel1QN_GQNIBQL_gNQ_EGEEIY PAGE 33 ANSWERS -- UNIVERSITY OF WISCDNSIN -86/11/04-RIDGWAY, K.
ANSWER G.04 (1.50)
- 1. Film badges (0.5)
- 2. Thermoluminescent dosimeters (0.5)
- 3. Pocket ion chamber (0.5)
- 4. Finger ring (0.5)
(Any three)
REFERENCE Casic practice ANSWER G.05 (2.00)
- 1. A doserate in excess of 5 mrem /hr (0.8) or 100 mrem in 5 censecutive days. (0.2)
- 2. A dose in excess of 100 mrem /hr. (1)
REFERENCE 10CFR20.202 ANSWER G.06 (1.00)
High radiation areas are equipped with controls such as chielding (0.5), alarms (0.5), or locks (0.5). Direct curveillance for entries may be used for less than 30 days.
(0.5) (Any 2)
REFERENCE 10CFR20.202 ANSWER G.07 (2.00)
- c. The amount of radioactive material that emits 2.22E12 dpm or 3.7E10 dps
- b. Effectiveness of shielding depends upon the type of radioactivity emitted (0.5) and its energy. (0.5)
REFERENCE Casic theory i
- - - - . . . , _ _ _ . _ _ . , . _ . - . . _ _ , - _ - _ . . , , . . . . , _ ~ . . _ . _ . - - , _ - _ , _ _ _ _ _ _ - - . . , - , , . _ - - - - . _ - - - _ - - - - -
E,.__B9Q18IlgN_GQtil8QL_8ND_59EEIY PAGE 35 ANSWERS -- UNIVERSITY OF WISCONSIN -86/11/04-RIDGWAY, K.
1 ANSWER G.08 (2.00)
- o. 1-1/4 rems per calendar quarter (0.5) or
- b. 3 rems per calendar (0.5) IF
- 1. Dose does not exceed 5(N-18) rems (0.5) and
- 2. Dose records are kept current. (0.5)
REFERENCE 10CFR20.101 e
I i
1 i
t
. . , _ . , . _ . - _ . _ _ _ . . _ _ _ . . . . . _ _ _ _ _ _ . . _ _ . . _ _ . . . . . _ . _ . _ _ _ . _ _ _ . _ _ _ _ . _ .