IR 05000170/1988001
| ML20151B125 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 03/30/1988 |
| From: | Eselgroth P, Norris B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20151B119 | List: |
| References | |
| 50-170-88-01OL, 50-170-88-1OL, NUDOCS 8804080072 | |
| Download: ML20151B125 (77) | |
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U.S. NVCLEAR REGULATORY COMMISSION REGION I
<. OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N /88-01(OL) -FACILITY DOCKET N FACILITY LICENSE N R-84 LICENSEE: Defense Nuclear Agency Armed Forces Radiobiology Research Institute Bethesda, Maryland 20814 FACILITY: Armed Forces Radiobiology Research Institute EXAMINATION DATES: February 24 and 25, 1988 i
CHIEF EXAMINER: kTo S. Norris J a)/ L TE~ Date iarry'rOperationsEngineer,DRS Seni6 APPROVED BY: 8#e6
'Peteg W. Ef(Tgroth, Chief Jov b TT Date
- 'PWR Section, Division of Reactor Safety l
SUMMARY: Written and operating examinations tests were administered to one Senior Reactor Operator candidate. The candidate prssed the operating examination but failed two sections of the written examination.
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DETAILS TYPE OF EXAMINATIONS: Replacement EXAMINATION RESULTS: l SRO l l Pass / Fail l I l 1 I I l Written 1 0/1 l l l l 1 I l l Operating l 1/0 l 1 l 1 l l l l Overall l 0/1 l 1 I - CHIEF EXAMINER AT SITE: B. S. Norris, USNRC OTHER EXAMINERS: W. S. Roesener, EG&G No exit meeting was held since there was only a single candidate. Mr. Moore, of your staff, and the examiners resolved the facility comments on the written examination ( Attachment 2).
Attachments: SRO Written Examination and Answer Key Facility Comments on Written Examination and NRC Resolution
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* U. S. i!UCLEAR hEGULATORY CCt' MISSION SENIOR REACTOR OPERATOR LICEt;dE EXAMINATION FACILITY: AFRRI REACTOR TYPE: TRICA MARK-F
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DATE ADMINSTERED: 83/02/24 _ -_-
*** = &R EXAMIt;ER: ROESENER, ,
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CANDIDATE INSTRUCTIONS TO CANDIDATE: Use separate paper for the answer Write ant.wels on one side onl Staple question aheet on top oi the answer cheet Points for each questior, are indicated in parentheses af ter the question. The passing grhde requires at least 70% in each categor Examination papers will be picked up six (6) hours after the examinatien start F CATEGORY i. OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY
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18. o O M 20.00 REACTOR THEORY
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20.00 20.00 RADI0 ACTIVE MATERI ALG L'ANDLING _ DIGFOSAL AND HAZARD 3 C0.00 20.00 SPECIFIC OPERATING
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CHARACTERISTIC 5 19.00 t' -M J0.00 FUEL HANDLING AND CORE _- --- - _ . . _ PARAMETERG 20.00 ,_C.00 ADMINISTRATIVE FROCEDURES,
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M' '4 T CONDITIONS AND .sIMITATIONG
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/ r6<.sT All word done on this examination ic my ow I hsve neither given nor rc etveu ai "1-MASTR :0)Y
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NEC RULES AND GUIDELINES FOR LICENSE EXAMISATIONS " During the scministration of thir., examination the following rules apply; r.' heating on' the examination means an automatic' denial' of your application and coulu result in more suvere penaltie Restroom tript are to be limited and only one candidate at a time may leave. 'You must avoid all contactc with anyone cutside the examination rocm to avoid even the appearance or poscibility of cheatin . Use black ink or data pencil only to facilitate legible reproduction . Frint your name in the blank provided en the cover sheet of the examinatio . Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answer . Print'your name in the upper right-hand corner of the first page of each section of the answer chee G.neecutively . amber each answer sheet. Write 'End of Category __" as
.: ppro pri ate , ctart each category en a new page, write only on one side of *.he pwper, and write "Last Pade" :>n the last ancwer shee . Number each answer as to category ano number, for example- , 1.4, . Skip at least three lines between each answe , Geparate answer cheets from pad and place finished answer sheets face down on your desk or tstbl . Ute abbreviations only if they are commonly used in facility literatur . The point value for each question is indicated in parentheses after the question and can be used as a guide f or the depth of answer require . Show ail calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or no . Partial credit may be give Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of the exeminer onl Yoa must cien the statement on the cover sheet that indicates that the worF. is ycur own :$nd you have not receivea or been oven ast.istance in 2 :,m ple t ing the examination. This mu:st be done af ter the exanination hu been compi.e:e . - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ .__ __-_ __ ________ __ -_ _____--__ _ ___-__ _ ___ _- _ _ _ _ - _ - __ _
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; 16..When you 4;omplete your examinaticn. you shall:
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i g Assemole your examination as follows: ;
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(1) Exam questions on tc t')J Exam aide - figures, tables, et i
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(3) Answer pages including figures which are part of the answe ; Turn in your copy of the examination and all page.s used to answer [
the examination question ;
: Turn in all scrap paper and the balance.of the paper that you did r not <tse for answering the question Leave tl'e examination area, as delined by the examine If after -
leaving, you are found in thiu area while the examinhtion is still in progress, your license may be denied or revoke t
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. , liu hE6GIOB_fdEQB1 Page 4 0011.3T 1011 H.01 (1.00)
The reactor is cperating at 1 .MW as indicate oy tne nuclear
. instruments. Using the diven information, determine 1:. the power indleated by the instruments is correc GIVEN:
Primary cooling system accured Pool temperature rise in 30 minutes is 7.b deg C JHOW YOUR WOR Helpful equations and constante are included in attachments A-1 thru A- GUESTION H.02 (1.00) Anume thot the primary ecoling system heat ex: hanger had a : dnificant bui.aup of cvrrosion products and other deposita en the incide of the
: aces, and , hat primary flow through the heat exchanger was held constant, iiow would the dif f erence in primary side temperature betuven the heat exchanger inlet and outlet be utfected? EXPLAIN WH J.co GUE0 TION H.03 (; , -)
Explain why the transient. rod is worth approximately twice as much as the reguistirW ro QUESTION H.04 (2.00) bl
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State TWO reasons for includinE the Samarium wafers in the +=..tn.. rods.
. I QUESTION H.05 lu.u0) Define BETA EFFECTIV (1.00) is . Explain why BETA EFFECTIVE is greater the 8 ET (1.00) i i I l l (***o CATEUCRY H CONTINUED UN NEXT FAGE **+**) i {
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e MACDOhlflEGh1 Page 5 UUESTIC!! H.06 (u.00) State TWO reasons for using a neutron source to perform startups at AFFR GUESTIO:1 H.07 (3.00) Define EXCESS REACT!VIT (1.00) List FOUR ways in which AFFRI personnel :nay adjust excess reactivit .00) VUESTIU!1 d.06 s .
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The reactor operator as conductang a routine reactor startup after it hhs been enutdown for several day Prior to withdrawing b tod she reads a stable power of 10 eps on the wide range log chanae Imnediately after withdrawing this blado che reads a power of 16 cps, If che 6ormed no ro f . minutes, w d he 'Oc/ercl counk e .. otion e !t'CREAS" DECREASE or f or [aAIN THE GA! r .
.JECAIN, assumi . the reacto /r ' suberitica E at 10 ep ,- ,. eu
...n After 5 minutes she withdraws another rod such that the same amount of reactivity is added as in 'a" above but the reactor is still c,uberitica Is the change in power for this second rod withdrawal GhEATER THAN, LESS THAN or THE SAME AS the change in power observed for the first red withdrawal?
EXfLAIN your answe (1.50) WUESTICN H.09 (2.00) Assuming the reactor to be critical at 100 kW: l Explain the initial (prompt) response of the ree.ct.or power to I a ten inch drssp of the regulating rod. A deneral explanation le desired NOT a calcatatio (1.00) I Describe the tmhavior of reactor pcwer at two ruinutes rollowing the ten inch red dro (1.00)
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.. L_ 86DiRAGil23_14IEB16k2_U6tiDLi'lG.212!256L hse 7 AtG_LiMalms -
e E i QUESTION 1.01 (2.00) ;
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List the location of FOUR of the HOT wante drains located on the first floor witnin the boundaries of the REACTOR FACILIT t l f
it QUESTION I 03 (3.00) I I What kind af discharges is.the WARM waste drain system designed to , accept? (1.00) l tate the capacity and number of tanks dedicated to WAP.M discharge .
(1.00) ; State T'WO ways bi which WARM drain s are identified? (1.00) I f
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QUESTION I.03 (3.00) ; i Atter irradiation, a rabbit is to be removed from the CET (Core l r Experiment Tube): State the dosimetry requirements for the personnel present t in the reactor room (at the CET). (1.00) j , Name the throw minimum required personnel (by title [ ! or department) that must be present for this operation and f i ctate where they shall oe located (by room). (2.00) l
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i ^ QUESTION I.04 (2.00) - List the FOUR general actions that a radiation worker should take to contrcl a spill of radioactive liqui ! i
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. . f L' h6kiC6C.115.3615816kE.lldflEkiEG_21EEQE6 L Page 3 60t_U6%adR4 QUESTION 1.05 (4.00)
Fer the following radiation equipment list:
' .. The type of detecto L. The location of ALL readout meters (Scme may readout'in MORE than one location).
3. The high level alarm setpoin Reactor room CAM (Itimary). (1.00 R- (1.'00) Criticailty Monitor (Both day and night alarm cetpointa).. (1.00) Stack Gas Monito (1.00) WUESTION !.06 (2.00) l what TWO radiologien1 condit.lons wl;l nece sitate leaving the primary i Emergency Action Station (EAS) and goind to the secondary EAS7 I l , QUESTION I.07 (2.00) State the type and range of the portable radiation detectors available INS 11E the reactor control roc (D0 NCT include the instrumente in tne emergency eache Just outcide the control room door.)
QUESTICN I.08 (2.00) Define the following: By-product Material (1.00) High Radiation Area (1.00) i'**++ END OF 'ATEG0RY I *****)
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- , , . e._ dEEGlZiC_QtsMILEG._JUabau1E81dI21 Paae 3 VUEST.'.ON J.C1 (;: . 00 )
Half way through a 6 hour reactor operatica ran you discover that the ' normal ventilat:.cn exnaust damper u -. .6.; iurae .wvu has been blocked open by a utudent pcrforming experiments in the hoo Y,.,a can not close the dampe:,* because it was domaded, What action.s should be taken relative to reactor operation't (1.00) Is the event report able'! Why or why not? (1.00) iA copy .f the ventilation Technical Specification is included as attachment A-2 JESTION J.02 (1.vo) Expl81n the mechanian by which the transient control rod 2; dropped into the core on 5 scram signa , QUECTION J.03 (1.00) WHAT prutects the roactor control console from voltage surges an. WHY l is thin protection needed? 40ESTION J.04 t1.00) l Multipls Choice: Whien cre of the tolicwing receives its power from transformer 42A ! (locatec in roem 3152)? l l i. ecoling tower fans l ' b. ventilation exhaust fan EF-1 radiation nonitor panel reactcr <;ntrol panel
, st i r cOTup re t tf o r for tran$1'Jul TOd and lead dour 't o l . + * * i A! E U C T,i' ..' .'m.NT ! S U E D .N NEXT 1 AGE *****)
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i e e,. d4 _AiECIFIC CEE!BIlM_WAIM9IEE1E2122 Fage 10 ' 4-i f f CUESTION J.06 (3.00) !
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Liot FOUR of'the interlocks associated with the Rod Withdrawal Prevent l circuit any one'of wnich will prevent witndrawal of ALL rod Include ; in your answer the associsted satpoin ,
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QUESTION J 06 -(1.00) i What design :eature minimices the tottoming impact of ! I a control rod drive piston? : 1 .i I , r QUESTION J.07 '(1.00) !
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, What are the THREE basic functions of the water purification system?
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QUESTION J.03 (2.00) I
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) List the THREE apecial indications in effect only in the Pulse Mode of ' operatio Include in your answer EQTH the parameter and the method of 4 dicula ! i i i I L j QUESTIO!4 J..o (1.00) [ } l
- If a pulse of $0.50 is fired from cold criticsl conditions and a !
j subsequent scram does, not occur, what will be the final steady state ! j power assumine no 6rerator action. Useful reactivity curves are ! ' included as attachments A-b thru A-2 ! i i
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QUESTION J.11 (2.50) During the performance of a normal K excess esiculation. the operator l decides to pull the transient rod first, the safety rod next then the i shim rod and finally to go critical on the redulating ro The operator I mak(s a mistake on the first withdrawal, pulling the transient rod to 650 instead af 25%. Assume the power with the transient rod at 65% is
.05 watts ar.d assume that the core is in position 56 '
i i If the operator does not notice her mistako and continues withdrawal of the other rods, which rod will be moving when the reactor goes critical? Ehow all calculations used to arrive at ycur answe (0.00) If the operator continues -t o pull the rod in "a" above, what will be the first automatic action to take place, a FERIOD RWF, a POWER l 3 CRAM, or e TEMPERATORE d. CRAM? (0.50) l I
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Useful constants equations and reactivity curves are included as attact.ments A-1 thru A-22.
. QUESTION J.12 (0.50) l TROE OR FALSE , i i A rupture in the primary coolant return piping is prevented from l , draining the care below the top of the core by small holes drilled in l , both the suction and return piping level three feet above the top of the core.
e i , l QUESTION J.13 (1.00) State tne complete Technical Specification limits on bulk and l
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i purification outlet conductivity.
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. . ii . FUEk HMQkiECi_6EQl2EE_EAHAMETERS hge 10 QUESTION K.01 I3.00)
Explair. any the procedure for loading fuel frcm the inside ring cut , :.; more cca:,ervative than loading fuel f rom t ne outside i Inciade in your ariswer a sketch of the 1/M plots for each loading schem QUESTION K.02 (1.00)
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I If the reactor was operating at i MW and a fuel element developed a crack in the cladding, how weald the operator first receive an indication or the failure? QUEST;ON K,03 : 1.UO) State the Safety Limit and the Sarety dystem Setting Include both the parameter and the setpoin QUESTION K.04 (3.00)
According to Technical Specifications, with fuel present in the cc>re, when is the res.ctor considered secured? QUESTION K.05 (1.00) TRUE or FALSE? The iechnical Specificatica limit an transn>_rse bend la based in part on the preventica cf hot spots resulting from touching fuel rod (0.50) The Technica .:pecification Aimit en fuel rod elungation is cased in part ..n ensuring adequate molant flo (0.00) k i...~ cATErny n o.m: yuu .n uen eAm , - . ; ,
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a. An experiment is loaded into the B-ring of the core when the reactor is operating at i M After loading the experiment, the reactor power level decreases to 600 K How much reactivity was acced by the experiment? Useful reactivity curves are included as attachments A-5 thru A-2 (*. 00) o. rt) b. If tne same experiment had been loaded in the outer ring would you expect the final power level to be GREATER THAN, LESS THAN or EQUAL TO SCO kW7 EXPLAIN your choic (1.00) I.ro GUESTION K.07 (2.00) The reactor coro 3 in posit on 231, power is 1.0 MW, Mode I eperation. The shield doors are fully open and both expvaure room doors are close If the core carriage control (core dully) malfanctions and starts driving the core toward the center of the ?.ank, will the reactor be SUPER-CRITICAL, SUB-CRITICAL, or CRITICAL when the core reacnos position 567. JUSTIFY your answe ASSUME: NO DPERATOR ACTIONS ALL OTHER SYSTEMS FUNCTIONING NORMALLY (2.00)
QUESTION K.08 (1.00) The inspection of the huc Nl rods required annually is scheduled this I week. The three previous inspections were conducted 14, 25, and 40 l months ag Can an experiment be run this week without inspecting l the control rods? Justify your answer. A copy of the applicable t Technical Specification is included as attachment A-25.
l QUESTION K.09 (0.S0) l ' RUE or FALSE? ! l In-coro experiments anall not be placed in adjacent f ue > positi;no of the B ring and/or C-rin (0.00)
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.- - _ _ - . . . , EEEh_EaGP_klGE_aEP CaEE_EAE&'dEIEEE Page 14 GUESTION K.10 (2.00)
In the core loauing procedure, fuel reds are inserted in large groups
.:ntil there are a total of 66 rode in the core, thereafter the rods are inserted 2 at a time, Explain why rods are added in such large grcups up co 66 and then only added two at a time thereafte How is criticality tested for after each group ;f rods is inserted? -QUESTTON K.11 , .;--)(2. M Assume that the core can be Jr.ade critical with an excess reactivity of 3.40 with 68 fuel elements in the cur Escimate the maximum number of fuel rods that can be inserted without exceeding Teebnical Specification excese delta K Limit (1.00) If no experimer+ are to be loaded, how many extra core sites will be left to f17 nee all the fuel is loaded? (0.60)
A --42n dvue w1Tu t,ne non 2 uuim. ,~ m m . .; di m. ,wd 1 ~ aum u? De /c re d C+-49) l l d If an experiment is added tc the core that is worth a NEGATIVE $.50 l of reactivity, would the maximum number of rof.s allowed in "a" above INCREASE, DECREACE or EEMAIN THE SAME? (0.50)
.e If an experiment is added to the core that la uu ;h a POSITIVE 5. 50 of reactivity, would the maximum number of rods allowed in "a" above INCREASE, DECREASE or REMAIN THE SAME? (0.50)
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AQUld SIBhTIVEiEROCEDUEES.'COND1TIONS Page 15l Ah'D_LIMIIATIONS L.01 '(2.'00)
~ : QUESTION What is the minimum, staff required whenLthe reactor is NOT secured?
QUESTION L.02 -(3.00) For each of the following, state who (by title.or position), His responsible: For final approval on a Reactor Use Reques (0.50) - For authorising entry of a visitor into an exposure room. (TWO answers required). (1.00) For Reactor Facility Key Contro (0.50) For supervising the insertion of an approved in-core experimen (0.50) For supervision of the loading of the cor (0.50) QUESTION L 03 (4.00) Indicate whether each of the following situations would require immediate shutdown of the reactor. Consider each situation separately JUSTIFY your answe Reactor power spiked to 1.15 MW during Mode I operations and is now at 900 K (1.00) The log power channel fails while operating in the Pulae mode.(1.00) Power increases as rods are manually driven into the core while at 500 k Pool temperature is 95 F and the primary and secondary pumps are operating. The reason for the increase is not know (1.00)- An area radiation monitor (R-3) in the reactor room is found to be inoperabl (1.00)
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QUESTION L.04 (2.00) 10CFR55 defines an operator as any individual who manipulates a control of a facility: Define the term "control" . (1.00) Under what conditions is the person physically manipulating a control not required to hold a valid operator's license? (1.00) QUESTION L.05 (2.00) While showing a trainee how to operate a reactor control room fire alarm, you accidentally set it off. State your immediate action Assume that the reactor is critical and that you are the current operator in charg QUESTION L.06 (2.00) State the order of succession of command for the Emergency Action Station (EAS) Commander according to the "Emer.tency Plan for the AFRRI TRIGA Reactor Facility".
QUESTION L.07 (1.00) ( How could the EAS commander determine who was inside the AFRRI complex during nonduty hours? l QUESTION L.08 (0.50) l l TRUE or FALSE 7 i The EAS Commander has the authority to make on-the-spot decisions and to
- direct or perform immediate actions deemed necessary provided that the
- ECP Commander is informed of such immediate decisions and actions as soon after the fact as possible.
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Lu.__ADillu1&IEAILEE_EBQQEDURES. cQtLrgnQu& Page 17
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QUESTION L.09 -(3.00) . Define Emergency Action Levels (EAL)? (1.00) Give example EALs for two of the emergency classes used at AFFR (2.00)
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Page 18
, .' . REMIQ8_.IBEQ81 li ANSWER H.01 (1.00)
Tank' constant is.l.48 deg C/100 kW-hr [0.25]
[7.5 deg C/0.5 hr]'[100 kW-hr/1.48 deg C] = 1013 kW or 1.013'MW [0.50]
Indication is correct [0.25] (1.00) REFERENCE AFERI Sample Questions F.6 and ANSWER H.02 (1.00) The elta T sill d' rease r .00] b ause th ,orrosi ayer wi act as nsul- on ai reduc he he transfp coeffi t redu g the at rr ioved .50]. (1.00) REFERENCE Murray, R. L.; Nuclear Energy . O e < < " > *- r ke re<**lc' r eol l> I* <* re A !* * f* * * b L J,;y ee fiv>< us ws,fe red to the re g leri<3 re d OK ge er v,e r%e ree.es:c e r r ed < & >- G a s or e n e ar.,, r t, , , rl, e_ ANSWER H.03 (b) r' P l ***) "*d-
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4= m entica [0.5 ] Since he abe rber po tions of he two ' ntrol ro a are and ince t e trans nt rod i located n a reg n of 'gher f x
[0 0), t trans nt rod w 1 absor more ne rons a d will hero ore wort more [ .00]. (4-60-)
REFERENCE Fundamentals of Nuclear Reactor Engineering, Ch. 3, Para. 8 > Tuo p a s > ] b le a.s. vers dej> < . d:.<3 o ., s ss p rien s, I. //..s ., : T he aT uill de c res s e C o. ro 3 y I. ., , n,, , : Ihe caeros: , i. k;)te, 4e< r re. a , fer a < r. s a rhe
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.. , REACTOR THEORX Page 19 ANSWER H.04 (2.00) Functions'as a burnable poiso OR Extends the life of a rod by limiting the excess reactivity of a new fuel rod and then burning out as the rod ages to help account for fuel burnup and fission product buildu . Functions as a flux suppresso OR Helps to flatten out the axial flux distribution by suppressing the flux peaks at the ends of the fueled region of the ro REFERENCE Fundamentals of Nuclear Reactor Engineering, Ch. 4, Paras. 101 & 1C AFRRI Sample Questions ANSWER H.05 (2.00) The fraction of the thermal neutron population that was born delaye (1.00) Since delayed neutrons are born at lower energies than prompt neutrons [0.5v) they are more likely to reach thermal energie [0.50). (Therefore, the fraction of delayed neutrons at thermal energies (beta effective) is greater than the fraction of delayed neutrons at birth (beta).) (1.00)
REFERENCE A Listing of Terms / Concepts / Definitions for the AFFRI TRIGA Reactor, . AFRRI Sample Questions H.2 & (**x** CATEGORY !4 CONTINUED CN NEXT PAGE *****) , . . _ . - _ _ - _ _ . .-. _ - .
. Bu__ REACTOR THEQEY Page 20 ANSWER H.06 (2.00) The source is used to check low level instrumentation [1.00]. The source is used to insure safe, controlled startup of the reactor [1.00]. (2.00)
REFERENCE AFRRI Sample Questions Fundamentals of Nuclear Reactor Engineering, Ch. 4, Para. 14 ANSWER H.07 (3.00) That amount of reactivity remaining in the core greater than what is needed to bring the reactor cold critica (1.00) Any four of the following at 0.50 each: Moving the cor . Adding (removing) fue . Reshuffling fue . Changing fuel (refueling).
! Changing experiments (including exposure room modifications).
! Installing (removing) the core experiment tube (CET). (2.00)
* # '
l REFERENCE' U ") ' , i AFFRI Sample Questions A.6.
l A Listing of Terms / Concepts / Definitions for the AFFRI TRIGA Reactor, l < l (***** CATEGORY H CONTINUED ON NEXT PAGE *****) l - - -
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B2__EEACIOR THEORY Page 21 ANSWER H.08 ( ? 10 )(/,fd) INCREA [0.50]. Right af+ r the rod - ion cea - subcri ~ al mult licatio- equilibr m level is ot yet ee ablishe .50]. The pe/crch lel will ontinue + increase itil the .w equil ' rium is eached .50]. C'. EO) GREATER THAN [0.50]. As the multiplication factor approaches one (or as the reactor approaches criticality) [0.50], the number of generations required to reach equilibrium increases [0.50] and therefore the change in count rate increase (1.50) OR The final equilibrium level is proportional to [1/(1-K)] = (1 -1/p).
As K approaches 1, p approaches sero from the negative side and each step change in reactivity causes (1 - 1/p) to change (increase) by a larger amount resulting in a larger increase in the associated neutron level (or count rate).
(As p approaches O from the negative side (1 - 1/p) approaches infinity.) (Note Bien: p: rho.) (1.50) REFERENCE Fundamentals of Nuclear Reactor Engineering, C , Para. 15 ANSWER H.09 (2.00) The reactor power will drop immediately [0.50] due to the quick response of the prompt neutrons to the change in reactivity [0.50]. l (1.00) At two minutes the reactor power will be decreasing [0.60] at a rate controlled by the decay of delayed neutron precursors [0,50]. (1.00) REFERENCE Fundamentals of Nuclear Reactor Engineering, C , Para. 79.
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(***** CATEGORY H CONTINUED CN NEXT PAGE <****)
1 REagTOR THEOBX Page 22
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ANSWER H.10 (2.50)
(The reactor will go on a positive period of 25 see based on the inhour curv The reactor will rise to a stable power level with a reactivity change due to the negative temperature coefficient equal and opposite to that added by the rod It will rise at the 25 second period at first and then tail off as the power r'se begins to add significant negative reactivit .165% delta K/K = $.235 so power will rise to approximately 30 kW.)
*
*
300 sec - 30 kW
*
275 sec ;-
*
L 150 sec r Period = 25 seconds
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l l
1 75 sec -
+
l l 0 sec - * I { k 1
, 1 1 '
1W 10 W 100 W 1 kW 10 kW 100 kW (***** CATEGORY H CONTINUED ON NEXT PAGE *****)
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arjee a ,d /oc - wereer rim e fro m la lrir l to - Grading : Correct period,(+/- 1 sec) [1.00] dn* / n'm e. 356sec ( g nosey 30 L W Correct final power (+/- 20 kW) [1.00] b ea*I s h /c of Graph [0.50] REFERENCE Fundamentals of Nuclear Reactor Engineering. C , paras. 78,79, & 8 (***vt END OF CA'IEGORY H *****)
, .. . RADIQAETIVE MATEBIES_HAMLING DISPOSE Page 24 AND HAZABDS ANSWER I.01 (2.00)
Any four of the following at 0.50 each: Floor of Exposure Room # . Floor of Exposure Room # I Floor of $at'E$c'h'a'ng*e com (1121).
C'l vExchangbe) Floor of hallway to Heat r <m > nes Room (1120) . r REFERENCE Operations Manual for the AFRRI TRIGA Mark-F Reactor, Figure 3-13 l ' Liquid radioactive waste drains located on the first floor of AFFRI".
I
l ANSWER I.02 (3.00) Liquid wastes containing low-level radioactive activation and contaminatio (1.00)
1 , tanks at 5000 gallons eac (1.00) l . Painted yellow [0,50]. Marked with a yellow "WARM DRAIN" sign (0.50]. (1.00) REFERENCE l Operations Manual for the AFRRI TRIGA Mark-F Reactor, C , p. 5 AFERI Radiological Safety Manual, p. 4 (***4* CATEGORY I CONTINUED ON NEXT PAGE u***)
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L._ lAE10ACIlEE_t1AIERIALE_HAN DL I NG D I S POEAL Page~ .2 ." l ~
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il ANSWER- I.03 (5.00)
;; ' AFRRI. radiation dosimetry device [0.33]. , ; Pockel ion chamber dosimeter-[0.33).
- Wrist dosimetry [0.34).. (1.00). = Reactor: Room-[0 25]- .
.
SAF monitor [0.50] reactorfstaff' member [0.50] Control Room [0.25) - a reactor operator (SRO acceptable) [0.50] (2.00),
,
REFERENCE Operations Procedures.for the AFRRI TRIGA Mark-F Reactor, Pro I, Tab , AFRRI-Radiological Safety Manual, .
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ANSWER I.04 (2.00) r Contain the spill [ 0 .'q0 ] li.Rus can be ochly uvae [0.2G). Inform nearby people [0. (0 ) se Llwy cen eit!.-;r a ;ist [0.10 eimmuu;s [0.10]. ,
' Isolate the' area [0.50] (so no one else can be contaminated).
l ', Call SAF [0,50], (even if it involves contaminating the telephone).
(2,00)
>.
" REFERENCE 't AFRRI Radiological Safety Manual, . j r ! l-I ! ,
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l-
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(***** CATEGORY I CONTINUED CN NEXT PAGE ** * ** )
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. RADIOACTIVE _MAIEEIALE_BANDLIBG DISPOSAL Page 26 bbD_BhZb8DS ANSWER I.05 (4.00)
(0.25 points for each part) . GM-Tube 2. On unit (Reactor Room)
Control Room 3. 10 Kcpm . Scintillation Control Room Y eewrity Cfficc ( 31 * 2-) E w y e up E** *f * * * ' I<* * S ' "" mr . Scintillation . Control Room ~ Og d /.5s 6//9D#4 mr by day y, g, g,/ goom 20 mr by night g,, , ,, g,, g . Proportional Counter 3, g g y cpm Control Room ' Environmental Surveillance Room (Uppur-Equipment Room)(3152) cpm REFERENCE Operations Manual for the AFRRI TRIGA Mark-F Reactor, Ch. 6, p.115, 125, 126, 139-15 AFRRI Sample Questions G-2 Operations Procedures for the AFRRI TRIGA Mark-F Reactor, Proc. VIII, Tab Emergency Plan for the AFRRI TRIGA Reactor Facility, pp. 56 - 5 ANSWER I.06 (2.00) Radiation levels greater than 100 mr/hr [0.50] at the center of the control room [0.50). Reactor room CAM high-level alarm [0.50] in conjunction with compromise of the reactor room to reactor control room boundary
[0.50] (such that there is airborne contamination in the control room). (2.00) (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
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I.- EARIQ6GIlLE_t!aIElilALE_BASQLLEG E DISEOSAL Page 27 AUR_BALABEE REFERENCE e Emergency Plan for the AFRRI TRIGA Reactor Facility, pp. 56 - 5 Tele ree m e - lHyh + h ~ (?* ~3 e ANSWER I.07 (2.00) g. , 7, ,, , e _ g o , g, c CAF There is a high range and a low range at 1.00 point eac (2.00) REFERENCE Emergency Plan for the AFRRI TRIGA Reactor Facility, . ANSWER I.06 (2.00) Any radioactive material, except special nuclear material, yielded in or made radioactive by exposure to the radiation incident to the process of producing or using special nuclear materia (1.00) !:r4y area accessible to personnel in which there exists Jadiation,( originating in whole or in part within licensed material) at such levels that a major portion of the body [0.25] could receive in any one hour a dose in excess of 100 mr [0.75).
(1.00) REFERENCE A Listing of Terms / Concepts / Definitions for the AFFRI TRIGA Reactor, pp. 8 & 2 (***** END OF CATEGORY I *****)
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_ slm_1EEGIElG 0_EEB&IlNG CdAB&QIEBLEILGs Page 28 ANSWER J.01 (2.00) (Since the system is incapable of performing its intended functions in a normal manner, i.e. since the system is inoperable) it is necessary to immediately secure reactor operatio (1.00) The event is reportable since the reactor was operated in violation of a limiting condition for operatio (Specifically, the reactor was operated with the ventilation system inoperable AND not secured). (Note - the 48 hour time limit applies to operation with the ventilation system SECURED!) (1.00) REFERENCE Technical Specifications, Sec 3.4 & ANSWER J.02 (1.00) Scram signal deenergises a three way air solenoid valve [0.25) which interrupts the air supply and relieves pressure on the air cylinder
[0.50) allowing the piston to drop by gravity [0.25). (1.00)
l REFERENCE l ' Operations Manual for the AFRRI TRIGA Mark-F Reactor, C , pp. 28-3 ANSWER J.03 (1.00) ! A voltage regulator [0.50) to prevent overloading circuits in the reactor console [0.50). (1.00) REFERENCE Operations Manual for the AFRRI TRIGA Mark-F Reactor, C , p. 7 (u*** CATEGORY J CONTINUED ON liEXT PAGE **4**)
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. Jm SPECJFIC t]fEBAIING CBAFACTERISTICS Page 29 ANSWER J.04 (1.00) REFERENCE Operations Manual for the AFRRI TRIGA Mark-F Reactor, Ch. 4, Figs. 4-7 "Electric power distribution system for reactor building" & 4-11 "MCC power distribution for reactor support equipment".
ANSWER J.05 (3.00) Any four of the following at 0.50 for the interlock and 0.25 for the setpoint: Period 3 seconds Source - .5 cps Water bulk temperature - 50 C Fission chamber high voltage loss - 20% Operational calibrate - Operational channel in any position except operate (3.00) REFERENCE Operating Procedure for the AFRRI TRIGA Mark-F Reactor, Sec VIII, Tab- Operations Manual for the AFRRI TRIGA Mark-F Reactor, Ch. 7, pp. 92 & 93.
i ANSWER J.06 (1.00) l l When the piston is near (within 2 inches of) the bottom of its l travel, its movement is restrained by the dashpot action of the graded i vents in the lower end of the guide barre (1.00) l l l (***+* CATEGORY J CONTINUED ON NEXT PAGE *****)
. - - , . .. SPECIFIC OPERATING CHARACTERISTICS Page 30 REFERENCE Operations Manual for the AFRRI TRIGA Mark-F Reactor, Ch. 2, p. 2 ANSWER J.07 (1.00)
To minimise the likelihood of water leaking into the housing if the seal should ruptur (1.00) REFERENCE Operations Manual for the AFRRI TRIGA Mark-F Reactor, C , p. 68.
, I ANSWER J.08 (3.00) It maintains low electrical conductivity of the reactor coolant (to minimine the corrosion of all reactor components) [1.00]. It reduces radioactivity in the water (by removing particulates and soluble impurities) [1.00]. It helps to maintain the optical clarity of the water [1.00]. (3.00) REFERENCE i Operations Manual for the AFRRI TRIGA Mark-F Reactor, C , p. 41.
i l ANSWER J.09 (2.00) , Peak power level [0.33] is displayed on the chart recorder [0.33).
! Integrated power [0.34) is displayed on the safety channel 2 meter (the megawatt-sec meter) [0.34). Fuel temperature (0.33) is displayed on the chart recorder [0.33).
l (2.00) ! j (***** CATEGORY J CONTINUED ON NEXT PAGE *****) l l I
- . .- SFECIFIC OEEBAIldG_CBABAGIEBISTICS Page 31 REFERENCE Operations Manus 1 for the.AFRRI TRIGA Mark-F Reactor, Ch. 5, pp. 98 & 9 ANSWER J.10 (1.00)
580 kW (+/- 20 kW) (The $2.50 insertion is offset by the negative reactivity inserted by the fuel at a power of 580 kW). (1.00) REFERENCE AFRRI Sample Questions J.1 ANSWER J.11 (2.50) Normal criticality for this configuration occurs when rods have added $1.85 + $1.86 + $.71 + $.63 : $5.05 [1.00]. 65% of the transient rod is worth $2.79 and all of the safety rod is worth $1.86 leaving $5.05 - $2./9 - $1.86 : $.40 to criticality
[0.50). Therefore, the shim rod will be moving (through 37.5) at criticality [0.50). (2.00) PERIOD RWP [0.50]. (EXPLANATION) (A 3 second period occurs at $ 75. (Known from square wave operation or may be calculated). For the situation discussed, an l
i insertion of $.75 would occur at 63.5 on the shim rod. With a rod l speed of about 8 sec per 1% rod motion the total time to 63.5 beyond . criticali+-y is 21 seconds. Even conservatively assuming an average ! 3 second period for the entire 31 seconds gives a power increase of only.
l 21/3 ' e : *096 or a final power of the order of 500 watts
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which is well belos the power scram and well below the point of any significant heat addition to the fuel to either cause a scram or to l insert significant negative reactivity via the temperature ! coefficient.)
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. _ . ' . , SEECIFIC QEEBATING CHARAQIEBIEllGE Page 32 a
REFERENCE Operating Procedure for the AFRRI TRIGA Mark-F Reactor, Sec. VIII, Taba D & Worth curves for position 56 ANSWER J.12 (0.50) FALSE (0.50) REFERENCE Operations Manual for the AFRRI TRIGA Mark-F Reactor, C , p. 4 ANSWER J.13 (1.00) Purification - 2 micromhos/cm [0.25] averaged over one week [0.25]. Bulk - 5 micromhos/cm [0.25] averaged over one week [0.25]. (1.00) REFERENCE l AFRRI Technical Specifications 3.3.
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s FUEL HANDLING AND CORE PARAMETERS Page 33 ANSWER K.01 (3.00) See attached FIGURE F-1 [1.00 each).
Because the fuel worth increases from the outside edge to the inside ring of the core-[0.25), the outside to inside loading scheme leads to an initial overestimate of the number of fuel elements required for criticality [0.25] while the procedure used at AFRRI (inside out) leads to an initial underestimate [0.25) which is more conservative and safer [0.25). (3.00) REFERENCE Fundamentals of Nuclear Reactor Engineering, Ch. 5, Para. 16 ANSWER K.02 (1.00) The reactor room CAM would alar REFERENCE AFRRI Sample Questions ANSWER K.03 (1.00) l Maximum fuel temperature [0.25) shall not exceed 1000 C [0.25). Measured fuel temperature [0.25] shall not exceed 600 C [0.25).
(1.00) l REFERENCE AFRRI Technical Specifications 2.1 & 2.2.
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, . , , FUEL _liMDLllLG_AND core _fASMEIEE5 Fage 34 ANSWER K.04 (3.00) The reactor is shut down [0.50). The console key switch is in the "0FF" position [0.25), and the key is removed from the console [0.25] and is under the control of a -
licensed operator (0.25), vr is stored in a locked storage area
[0.25). No work is in progress $nvolving in-core fuel handling [0.10] or refueling operations [0.10), n:aintenance of the reactor [0.10] or control mechanisms [0.103, or insertion or withdrawal of in-core experiments [0.10], unless sufficient fuel is removed to insure a $0.50 (or greater) shutdown margin [0.50] with the most reactive control rod removed [0.50]. (3.00)
REFERENCE AFRRI Technical Specification 3 1.1 ANSWER K.05 (1.00) a. FALSE (0.50) b. TRUE (0.50) REFERENCE AFRRI Technical Specifications 5.2.2.
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- ANSWER K.06 (2.00)
a. $1.12 (+/- 3.1) (0.50) l b. GREATER THAN [0.50]. . ! l The core outer ring has a lower flux and therefore the experiment would not insert as much negative reactivity [1.00]. (1.50) l (***** CATEGORY K CONTINUED ON NEXT PAGE *****) l l l
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. FUELtiat@ LING Al{p__GQBE_EABat1FlEBE Page 35 REFERENCE Fundamentals of Nuclear Reactor Engineering, C , Para. 82 - 8 AFRRI Sample Questions C.1 ANSWER K.07 (2.00)
SUBCRITICAL [0.b]. As the reactor moves positive reactivity is added (from t increased reflection) [0.50]. The rods are in manual thus power ir 2ases [0.50]. When the HI-FLUX scram setpoint (1.1 MW) is reached, the reactor scrams [0.50]. (2.00) REFERENCE Fundamentals of Nuclear Reactor Engineering, C , Para. 8 ANSWER K.08 (1.00) Yes (0.50]. TS surveillance is one year not to exceed 15 months and was not violated in any of the above cases [0.50]. (Note: AFRRI TS do not include 3.25 x interval requirement.)
REFERENCE AFRRI Technical Specifications ANSWER K.09 (0.50) ! TRUE l l r l l l l <
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. , FUEL _ HANDLING AtlD CORE _EARAMETERS Fage 36 REFERENCE AFRRI Technical Specifications 5. ANSWER K.10 (2.00) Experience showu that approximately 67 fuel elements are required to go critical [0.50]. Therefore, 66 elements should not normally cause criticality to occur and therefore it is not necessary to predict criticality conditions as of ter. [0. 50] . Control rods are withdrawn to 50% and 100% [0.33], changes in detector readings are noted [0.33] and a 1/M plot is constructed to predict criticality [0.34]. (2.00)
REFERENCE AFRRI Technical Specifications Operating Procedure for the AFRRI TRIGA Mark-F Reactor, Sec VI ANSWER K.11 (3.P b(.t.ro)
' Max excess = $5.00 [0.50]
Fuel rod worth in the F ring is $.28/ rod i Therefore: ($5.00 - S.40)/ $.28/ rod = 1 rods may be added [0.50). (1.00) (87 -68 -16) (0.50) ,
-. _ -C?" sAlumlaum dummies!; pe /e red (1 00) REMAIN THE SAME (0.50) DECREASE (0.50)
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.. ) FUEL 1]]AEkIl3G AtJD CORE PARAME_IEM Page 37 REFEREllCE Operations Manual for the AFARI TRIGA Mark-F Reactor, Ch. 1, . AFRRI Technical Specifications 3. i l
(***** E!iD OF CATEGORY K ****)
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kDdlELE'GATIVE PROCEDMRES. ' CONDITIONS Pace 3 AUQ_LidJTATIONS ANSWER L.01 (2.00) SRO on call [0.5]. RO or SRO in the control room (0.5). Radiation Contro] Technician on call (0.5). Another person within the AFRRI complex [0.5). (2.00) REFERENCE TechnL0al Specifications, 6.1. ANSWER L.02 (3.00) Reactor Facility Directo (0.50) Reactor Facility Director [0.50) AND the Head of Radiation Safety Dept. [0.50). (1.C0) Reactor Operations Superviso (0.!0) SR ( 0. !iO ) Reactor Facility Director OR Reactor Operations Superviso (0.S0) REFERENCE Operating Procedure for the AFERI TRIGA Mark-F Reactor: a. Gec I b. See I, Tab A Sec V Sec I, Tab E Sec VII (***** CATEGORY L CONTINUED CN NEXT FAGE *****) '
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, AQUI!1ISTRATIVE PROCEDURES, CONDITIONS Page 39 6N_R LLMITATIONS ,
ANSWER L.03 (4.00) Shutdown is required [0.50] since safety system has failed to operate [0.50). (1.00) Shutdown is not required [0.50] since the log p..+"' channel is not required to be operational in the pulse mode [0.;e (1.00) Shutdown [0.50) (to avoid an accident) since the operator cannot control the reactor by normal meant [0.50). (1.00) Shutdown is not required [0.50] sinc ^ R-3 is an additional area monitor not required by Technical Specifications [0,50), (1.00) REFERENCE Technical Specifications: . . . Operating Procedure for the AFRRI TRIGA Mark-F Reactor: Sec. VI.
l AMSWER L.04 (2.00) ! ' Devices (apparatus and mechanisms) of a nuclear reactor, the manipulation of which directly affect tne reactivity or power of the reacto (1.00) The indiv.tdual manipulating the control must be under the direction l of and in the presence of a licensed reactor operator [0.50] and ' the manipulation must be part of the individuals training as a I student [0.50). (1.00) REFERENCE 10CFR55, Part 55.4 , 55.9 and 55.13.
l l I (*"*** CATEGORY L CONTINUED O!1 NEXT PAGE "*") l
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Lu. _ADiilMFeIB3IllE_flQ.CLEMBEL.f9ED1 rIONS 'Page 40 AER_LIMlIBIIRES ANSWER L.05 (2.50) SCRAM the reactor [0.50]. Secure any exposure facilities which are in ase [0,50]. Remove the logbook [0.10], emergency guide [0.10), radios [0.10), teletector [0.10.7, tool kit [0,10), and keys [0.10] and report to the EAS [0.40]. Do NOT: lock reactor area doors [0,50] . (2.50) REFERENCE Operating Procedure for the AFRRI TRIGA Mark-F Reactor, Sec. VI AFRRI 3020.2H, Enclosure 4, p. 1 ANSWER L.06 (2.00) Reactor Physicist-in-Charge (Will accept Reactor Facility Director) [0.50]. Reactor Operations Supervisor [0.50]. Most-senior licensed SRO present [0,50]. Most-senior licensed RO present [0.60). (2.00) REFERENCE Emergency Plan for the AFRRI TRIGA Reactor Facility, p. 2 ANSWER L.07 (1.00) He can look at the Security Area Registe (1.00) i l (***** CATEGORY L CCNTINUED CN NEXT PAGE *****)
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,o- L _ADB2UITHEAIl2EJJ10CEDUBE32_sDUD1I2 OHS Page 41 ABD LibbibTloDB REFERENCE AFRRI 3020,2H, Enclosure 4, .
ANSWER L.08 (0.50)
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TRUE REFERENCE Emergency Plan for the AFRRI TRIGA Reactor Facility, . ANSWER L.09 (3.00) EALs are thresholds for establishing Centering) an emergency clas (1.00) Any two of the following at 1.00 each: See the attached Emergency Classification Guide.
l Parts of any one of the EALs that are ccmplete within themselves i such as "Receipt of a vague bomb threat" for Class 0, or "Verified visual observation of fuel damage involving multiple clad failures," for Class 2 are accepted for full credi (2.00) t ! REFERENCE Emergency Plan for the AFRRI TRIGA Reactor Facility, . I ! l l I i
(***** END OF CATEGORY L *****) (********** END OF EX/tMINATION ******&***)
l l l
-. . . ?= u:: : u . *.-: :. u u 1 : . .- - . , __, _ .,
Table 5.1. Emergency Classification Guide
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Emergency Purpose Class Emergency Action Level (EAL)
:
Class #i Receigt or notifleadon of vague bomb tf rsau or civil di.rtv-banees 1. Alert staff to poseuge Events Less rWe to the resetor escaladen severe Than the Lowest Otmervadon or notifloaden of personnel injury or dLaanlerpsnt withtn the operstiers beimdary 2. IAf tiate j Category unessment and i i
)(otifloadon er rvesipt of offloially decla;ed severe weather warn- or confirmatory actcru, as l Ings for the area ,
f***'**P7 Observation of a staall but wrusual lams er esp of narrnal resetor l ' pool water that le deter 9thod to be within the empabilities of the i l. Prmde normal maaeg water system (s) treatment and/ or trutiate ' Observeues et a rainer redation insident within the operadors aorrective - settnes, as . twundary to ineinade an empenment fM postMrradattan durvig, rieeemmary for exa% normal retrieval er W eperatione er vu receipt of wwupeeted hittier thaa normal remeter faeQlty radiation rose-ings er alarm (s) below the IAL ttreanalds identitled for a Cass "Notification of Dramal Event' emerTeney eenditten Listed below Fire alare er esservatiervnetilleaien et a nre er esplosien determined to be eutada of sai not immedataly adiaeont to the
;
resetor operetters benssnary er nei urvolvW the reteter fat *J1t I i
+
.
;
l - l (continued next page)
. _ . _ _ _ _ . - -
. .
Table 5.1-cont:nued
,
Emergency i
'
Clus Emergency Action Level (EAL) Purpose I l l Classit R emot or mouneauon of domb threats or cavd c.stuttances I 1. Assure that Neufloation spectleally dreeted ag a.itu t the resetor and marity potential e m e rf e' icy j of gw radalogteal release or reactor fandity structi.raj camage irepuce- per,on, net are i Event tief8 reacdy avadable , to respond, u Notifteetion or receipt of an ur.ariticipated reseter fae:Lity intrv- neeenaary sten detteuen ryetem aJarm(s). (Notei Sven evenu wiu be acted gon in accorcance with the AFRR! Resetor Feetbtv Pavsical 1. Perform , Security Plan, wNem u protectecTri paue caciosse.# confir m a tory aA4/or extent * iustained fire (110 minute curation) or minor erplosion witNa the of consecuences ' operauers *ndary (especia.;ly witNa the reactor room) =Neh usessmenu, u could adverseJy affect the resetor or su control rystemst eeter" necessary mined vte ooserveuen, nouflestaon. or a fire alarm cetermined to be irutlated from witma the reactor operations Doundary ~ p ,g offletal report /noufleeuen or oceervauen of entsung or imminent ruun and pro-severe naturni phenomena in the immedate local area wruch might tuttu acuore, esume teatter feedary structural damage as nuesmary
!.ow peel water level alarm actueuen fleas of 20 inches of water 4. Provide from the normal pool water level) in con;uneuer with ooservation apprognate off-or notificauon of a continuant unusuaJ or sagruf cant loss of pool site agencies with w a ter, to include coservation/notifleation of unplan current status leaxa/breexs in the primary coolant boundary, all of =Nen are information either taoistacle or determined to be within the espect!Jties of the normal and emerteney mamew water erstems suen that core uncovenng is not possible or is not Ukely without f arther eses:4 tion .
!
V!sual ocaervatiert eues of actual of tuspected tresool fuel dansge ' or elad fadure(s) or setuauen of unantteipated taciation alarms I (with of without vuual cues for an expentnant ladure). specifi- i cadyt Al radlauon area morutor (RA M). located rear the st.rface i of the resetor pool. ASCO m A/hr for11 minutet R;t RAM. located l . on the weet wall of the esector room.210 m A/hr for2.1 minutet E3 i l AAM. loested on the west wall of the resetor prep area ediscent to l , i and setirg as a redLauen streamtig detector for expnette room e l l 210 mA/rv for21 minutot El AAM. loested on the west waJ of the ' resetor prep area ad;aeont to and acurg u a radiation streaming i de:eef.se for espesure room 81. A 10 m A/hr for i.1 minute: RS i , RAM. locetod on the easle trad Wm to the naetor core couy ' tu'tage and eeurg as e ertticality morutor cun 4 resetor snut-dews or seeseaJ peneda.2 SJ mA/hr for2.1 mi sutet starv gu memter, whteh earnples and moeiters the gaseost ra dios etive ,, 2 effluents from the AFRRI resetor stsen. ecuivalenti> 1900 ttrnes (Rev 3/84)
'
WPCair for Ar-41 funrestricted area) for 11 minuter ut the resetor , room continuous air reonator (CAM). when samples air fspecificauy '
'
partleviates eoritained within the air) from directly over the core '
'
near the pool surface, eovivalently .t100 times v'Cair for i unnowns (restricted areal for 21 minute--eu cf when must tm
. unanticipated alarms j t n (continued nett pa(e)
l l _ _ _ _ _ _ _ . . _ _ - _ _ _ . _ . -- - _ _ _ _
. .
Table 5.1-continued _ E mergency l' Ernergercy Action Level (EAL) Purpose Clus . l 1
~
.
g.,3,,g, Cheervauen of an irrggated fwal alement ej.ad rupture curtry a g* 4 4gapg IWel handl11g operauof% Seeif1ea.dy Lf the oce'.httenee La ou1*of* poed. La. sn air rather than =ater ', ,y rte , ; ofn.a2 report o, o arvauen of -v e oiurna pnen. mens nsas enumng *.amage to the resetor faedJty structure in conyuricuan
=' a ad with the unantta: pated EAL radiation tjArmis) idenufled under '
elaas 1. *Notificauen of Unwual tvenk' above hW[ aunues. as d
*
Resetor faedjty fite ajatm or report /ooservation of a e sta.ined "" "**#7 fire Q10 minute ewsuon) or erplosen (ineJudtry musde impacti wit *Jn the operauere coundary that ts determined to have dtrecuy 3, pg,g ecmpegmtsed the reactor feedjty structwe (especially and partiev- " * 'W d ' ' N " * larly the reaeter roomt ut etarunedon with the unantletpeted EAL @" # "' 8 3' radiatten alarm (s) tdenufled under Class 1. "Notificauon of Unir= " eual Event.' above
* :
Lee peel water level alarm actuadon Goes of 2 8 (nenes of water g, i from the normal pool arter levad in conjuneuen with eenervauen and extent f-l or neufleetion
, I waie, wnien of a very
. dei drasue.er
, mined .e ,acontaniang esee. of the angrufleant ea,amuu. less of a m,,, -
,,,
of the normal and emergency mamee water erstems and wrwen can ,, ,"*"#7 ! ulumately or does actually lead to the core becomirt uneovered , I * I '# '# * "'" Vertfled vuual odeervauen of severa/estensive fwal damage inve'-- twtan uuor try muluple clad fadures (alone), or unatt.eipated alarms of the '8 " *'#7 reseter room CAM (at the EAL threshold identtfled for a Class "Neufleauen of Unusual f vonk' asevel m eenruneuen with radi ,, y ,, g ,
'
tjen alarma fori Rt. A3 and Rt. stw1/or the starz gas er eeuter ta;ae tuun ecuo at the EAL thresnold levels identified for a Class 1. *Nottfleston "'""'#7 of Unusual Ennt.'saeve) provided the slatrr.s are concurrent, for ' l a duranon21 retnute, and unancetpeted
'
t. Prmee netsfication to f and consultation with appropriate offsite agenetes, as necessary I
. 9. Provadr. inf orma*
tion for the pucLie throvg'n the Defewe Nwelear Agency QN Al Puntae Aff airs / Inf orm ation Of flee
. -
Notesill 'Ur4rttletpat 4' withLn Table 5.1 and seerms 4.0 and l.0 essentially is used to ensare that the ala.'er e* other threshold tedication ts in fact asmoetated with a real emergency f sued and not, for example. as a retalt of a teet or eskt>ratten of the ryttem or as a feruit of planned and approved smeefal wore permit operations =Pete rach a! arms or thresholds sowid t.e antie pated as a matter of cours . 2) 100 times MPCair fuere*tricted area) foe Ar l at tre top of the stace is i (ggy 3730 , I equivalent to 11.3 s 10*I m R,t.r at the AF R R! site teuncar . I 3) 100 VPCs,.=inutes for urimeens frestricted areal in tPe resetor aoom is eovivalent to 0.375 M PC,i, day for unanewns Nerestricted area) et tre l ' tcp of t*e ATRRI staca iths uruma na HEP A filttation and a ddwtion fatter of C 18).
N\ l l l
-- - - - - - - - - -- -- ---- ------ - . . .
FIGURE F-l _.._ _ .__ _ 1 s ss
,
M N's s N N g N s Early s s N N Actual s s indications N
's s
% %
, % %
%, N g Number of Fuel Elements Needed to Reach Criticality OUTSIDE ELEMENTS ARE LOADED FIRST
,
i s l E l l
'
..
\
\
\ Actual
\\
\ \\
\g Early \ .
Indications \ g g\ *
\ \ _,,
Nuri.hr of Fuil Elements Needed to Reach Criticolity , l l CENTER ELEMENTS ARE t.OADED FIRST .
.- ~ -- - --
_ _ --- _ _
..
'
ATTACHmwT
'^
A-l 9 SEP 87 AFRRI-TRIGA REACTOR PARAMETERS Prompt Neutron Lifetime 39 uSec
' Beta effective (8,fp) 0.0070 Prompt Negative Temperature Coefficient of Reactivity-1.26 X 10~4 "k/k/ C (-$0.018/ 0C) -
Steady State Temperature Coefficient of. Reactivity-5.1 X 10-5 k/k/ C (-$0.007/ C) Vold Coefficient of Rc+ictivity-0.2 X 10-4 "k/k/1% Vold Tank Constant 1.48 C/100 KW-hr Power Coefficient of Reactivity: 15 Watts to 100KW $0.59 15 Watts to 1 MW $3.47 Nominal Fuel Element Worth (compared to H2O) RING %^k/k ($) 8 0.89 1.27 C 0.73 1.04 0 0.57 0.82 E 0.31 0.44 F 0.20 0.28 Nominal Control Rod Worths: Standard Control Rod $1.84 Tran*,ient Control Rod 3.66 Stanuard Control Rod Follower 0.20 Transient Control Rod Follower 0.30 Other Magic Numbers: E = 3.1 X 10 10 fissions / Watt-second v = 2.47 neutrons / fission
., , REFLECTOR COEFFIENTS Core Posit Position Measured Excess Difference from Pos 567 231 REG 6 $3.66 $0.51 567 'f. REG 4 .17 ----
833 REG 4 .12 0.05 903 REG 6 .68 0.49 in all positions, the remaining control rods were configured as followst SAFETY ~ UP SHIM - UP TRANS - 2 b) _ - - _ --- -- - --
. . .. A .t BASE DATA FOR CONTROL ROD CALIBRATION .
POSITIVE PERIOD METHOD For use with the inaccr equation:
(N * *
8 ggT 8
i1 1 (T (Nste: The .'irst term may be neglected).
Where te , [ ; I = 39 x 10'0 seconds k eff T= period in seconds, (k,fp),, :::: 1.024 6,gg,,ggy, a 0.007 (reference Oct 1975 Technical Specifications) The delayed neutron group data was derived from data presented by Keepin, Winett, and Zeigler in PHYSICAL REVIEW, Vol 107, pp 1044-1049, (1975) and is as follows: Orcup S (5)
. f1/2 53' ) I3'O )
,
0.0213 2 .002 55 72 2 1.18 0.01244 y 2 0.1418 g .007 22.72 + 0.71 0.03051 ) 3 0.1270 g .015 6.22 g 0.23 0.1114 4 0.2557 g .011 2 30 2 0.09 0 3014 5 0.0746 g .006 0.610 2 0.083 1.1363 6 0.0270 g .003 0.230 1 0.025 3 0137
,
8, s 0.6474 g 0.044 T 1/2 9 022 sea (half life) V= 2.44 7" ,"' fa 13 016 soo (mean life)
- .c hu ' / ?A t T.i. -
n : ~[J R. M. SAVA0E PIC, 3 10-80
% .
-
. . .
A -3 REFERENCE EQUATIONS ACTIVATION A=Ae' out
* E'
A.= ON$tA R/Mr elft = 6CEn FLUX $ = nv (neutrons /cm -sac FUCH'S PUIJE MODEL EQUATIONS
'
T = T + 2( -3 ) ( C) E = 0-8) M max o a tot k(s) P max" k)t . T = ,,g initial period j=39psec 2 = 1.8/ C = 1.26 x 10 ak/k 8 = .007 h af q,9 Assumptions: Point Source, Adiabatic System, No Delayed Neutrons IN-HOUR EQUATION p vs T O 0 1 i 6
# " Tk,gg +6$1+AT g ' 1+A
T
og = g For T >10 se SUBCRITICAL MULTIPLICATION TAC E R M,
" " l-k 1/M = C ,/C Plotted vs Puel Added (Bod Withdrawn)
LEUTRON SOURCE
3Ci Am Be 10 neutrons /sec 241 , Am + He + b'p I yk[+4Be' + (6C' ) + 6 + o" , , . i ~;. : l PERIOD T, g[,
. N=Ne o
I . l POWER P P= '* Watts 10 Where V = Volume (cm ) j 3.1x10 p = p,e /4) t l l \ L
- 3
,~ ._ _ _ _ . - . - - _ - - - - _ . - - . - - - . - . - - - - - - - - - - - - . - . . - - - . - __ - - _ - - - - _ _ _ _ . . , .c .
l} REFERENCE EQUATIONS i (Cont.)
.
.'
,
REACTIVITY Measure of departure from prompt critical
, . k-1 6k s1-s,,,f k-1
,, . x ,,eff oere ,,,.. ,
;
.
REAC'ICR SCRAM DECAY TIME From Group 6: T = 80se tg = 55.6 rec Precursor mean 3.ife = 12.7 see-nx Ie (1+px) Ie- 8 , 4Wrd l l l l
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. .
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A-2r _ d 4.2.5, REACTOR FUEL ELEMENTS Applicability This specification applies to the surveillance requirements for the fuel
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element Objective The ob'jective is to verify the integrity of the fuel element claddin Specifications All thi. fuel elements shall be inspected for damage or deterioration, and measured for length and bow at intervals separated by not more than 500 pulses of insertion greater than $2.00 or annually (not to exceed 15 months), whichever occurs firs : I
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. * h ')b VENTILATION SYSTEM Applicability This specification applies to the operation of the facility ventilation syste Objective The objective is to assure that the ventilation system is operabl Specification The reactor shall not be operated unless the facility ventilation system is operable, except for periods of time necessary (up to 48 hours) to test or permit minor repair of the system. In the event of a significant release of airborne radioactivity in the reactor room, the ventilation system to the reactor room shall be secured via closure dampers automatically by a signal from the reactor deck air particulate monito Basis ,
During normal operation of the ventilation system, the concentration of argon-41 in unrestricted areas is below the i.lPC. In the event of a clad rupture resulting in a substantial release of airborne particulate radioactivity, the ventilation system shall be shut down, thereby isolating the reactor room automatically by spring-loeded, positive scaling dampers. Therefore, operation of the reactor with the ventilation system shut down for short periods of time to test or make repairs insures the same degree of control of release of radioactive materials. Moreover, radiation monitors within the building independent of those in the ventilation system will give warning of high levels of radiation that might occur during operation with the vent!!ation system secure .4 VENTILATION SYSTEM Applicability This specification applies to the facility ventilation system isolatio Objective 1 The objective is to assure the proper operation of the ventilaticn system in controlling the release of radioactive materialinto the unrestricted environmen Specification The operating mechanism of the positive sealing dampers in the reaccor room ventilation system shall be verified to be operable and visually inspected at least monthly.
l Basis Experience accumulated over years of operation has demonstrated that the tests of the ventilation system on a monthly basis are sufficient to assure proper operation of the system and control of the release af radioactive material.
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REVIEW COMMENTS FOR THE
'ARMi.0 FORCES RAD 10810 LOGY RESEARCH INSTITUTE . SENIOR REACTOR OPERATOR WRITTEN EXAMINATION FEBRUARY 24, 1988 The specific facility comments concerning the requalification examinations, followed by the NRC resolution, are listed in the following paragraph Question H.08 Facility Comment: Part "a" can be interpreted as a question on what the count rate is doing five minutos after the rod motion ceases as opposed to the change over the five minute period as implied by the question. Recommend that the answer, "REMAIN THE SAME", be allowed as a correct answe NRC Resolution: It is agreed that the question may be interpreted in two way Since the interpretation may not be apparent in the answer given by the candidate and, therefore, since the correctness of the candidates answer may not be apparent, the question is delete Question J.01 Facility Comment: The exhaust damper is not located above the fume hoo NRC Resolution: The words, "above the fume hood," will be deleted from the question in the exam bank. This discrepancy is not considered to have invalidated the question and the
, question remains intact, l l Ouestion J.05 Facility Comment: The question was confusing in that the word, "ALL", i could be easily missed and, therefore, an incorrect l answer could be given.
i NRC Resolution: The question is valid and remains intact. The question will be reworded in the exam bank to place the, "ALL", in a more visible position.
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Ouestion J.12
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Facility Comment: The question is confusing in that the first part about the existence of anti-siphoning holes is true but the second part dealing with hole location is fals Additionally the location of the holes is not considered to be very important informatio NRC Resolution: The entire question must be true for the correct answer to be, "TRUE". The question is not considered to be confusing and remains intact. Additionally, a feeling for whether the holes are located near the top of the pool or near the core is considered important from the standpoint of radiological concerns since the water is a very important shiel Answer I.01 Facility Comment: The Heat Exchanger Room and Hallway are more co'mmonly known as the warm storage area. Recommend you accept warm storage area as a correct answe Reference: AFRRI SAR page 3-3 NRC Resolution: Use of warm storage in place of Heat Exchanger Room and in place of Hallway to Heat Exchanger Room is accepte Answer is changed to add, "(Warm Storage)" to both parts 3 and enswer I.0J Facility Comment: Part b - The meter readout has been moved to the Emergency Response Team center in room (3434).
Part d - A second stack gas monitor has been installed with the following characteristics: Scintillation Device Readout meters in Control Room & Retator . Room Setpoint 889 cpm Additionally room 3152 is called "Equipment Room", not "Upper Equipment Room" Reference: AFRRI SAR, page 3-43, 44
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_ NRC Resolution: Part b.- changed as follows: .
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Deleted "Security Office (3112)" Added -
"Emergency Response Team Center (3434)"
Part d - Added -
"0R Scintillation Control Room Reactor Room cpm" Deleted "Upper" Answer I-07 Facility Comment: Detectors rsormally in control room are:
Teletector - High & Low range Victorene - Low Range NRC Resolution: Answers added as follows:
"Teletector (0.50] - High and Low Range (0.50]
Victorene (0.50] - Low Range (0.50]" Answer K.ll Facility Comment: Part c - Either non-fueled elements or left empty would be acceptable. This situation has never been encountered as the reactor has never approached the excess reactivity limits noted in Technical Specification NRC Resolution: Part c - Since no reference and no precedure exists to cover this situation, and since the reactor has never been operated in this condition, the question is considered inappropriate and,is
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delete The following changes were made to the examination as a result of final review an/or candidate questions during exam administration. All the changes to the ouestion statements were publicly announced to the candidate during the exam by the exam procto _ _ _ _ _ _ - _ _ _ _ o O
. Question H.04 ,
The word "control" was changed to "fuel".
Question K.08 The word "control" was changed to "fuel".
Answer H.02 II.001 Replace answer with the following:
"Two possible answers depending on assumptions as follows:
The T will decrease [0.50).
EXPLANATION: The corrosion layer inhibits heat transfer across the primary to secondary boundary [0.10]. In order to continue to transfer adequate heat across this boundary the primary temperature must rise (0.10]. Assuming that this rise results in significant additional losses of heat to ambient
[0.10), the heat transferred across the heat exchanger will decrease [0.10]. With constant primary flow and a decrease in heat transferred [1.10) the T will decrease."
OR The T will remain constant [0.50).
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EXPLANATION: If losses to ambient do not change significantly [0.20] then the heat transferred in the heat exchanger must remain constant [0.20]. With constant primary flow and constant heat transfer the T will remain constant [0.10]." Answer H.03 Replace answer given with following:
"Because the transient rod is located in a region of higher flux as compared to the regulating rod."
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Because the transient rod absorbs more neutrons than the regulaiiing ro (1.00)" Change point value to 1.0 Justification: The answer was changed to appropriately reflect the question as state The point value was adjusted to be consistent with the difficulty of the altered question / answer pair.
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Answer H 07 4 Add the following answer:
" By depleting the fuel (operating the reactor).
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Alternate correct answe Answer H.10 Alter grading to indicate the following: Correct period 25 sec (+/-l sec) and or correct time from initial to final time 350 sec (+/- 100 sec) [1.00] Correct final power 30 kW (+/-20 kW) [1.00] General Shape of Sketch [0.50] Justification: l Clarify grading.
l Answer I.04 Delete "if this can be safely done," and make first part of answer worth 0.5 Delete "so they can either assist or evacuate," and make first part of answer worth 0.50.
l ! Justification: l Questions asked for actions not for reasons for action Question K.06 l Change point value such that: l Part a. is worth 0.5 Part'b.'is worth 1.5 Justification: Correction of editorial ' erro }}