IR 05000193/1985001
| ML20126L886 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 06/03/1985 |
| From: | Dudley N, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20126L878 | List: |
| References | |
| 50-193-85-01, 50-193-85-1, NUDOCS 8506200167 | |
| Download: ML20126L886 (46) | |
Text
{{#Wiki_filter:' ,- _ . U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO.
50-193/85-01 FACILITY DOCKET NO.
50-193 FACILITY LICENSE NO.
R-95 LICENSEE: Rhode Island Atomic Energy Commission Narragansett, Rhode Island FACILITY: Rhode Island Atomic Energy Commission EXAMINATION DATES: April 24, 1985 CHIEF EXAMINER: [' A/~88 N. Dudley, Reacto Engitieer (Examiner) Date REVIEWED BY: I
'> 1/[ff , R. M. Keller,7ro'jects Section No. IC Date APPROVED BY: bd H. 6. Kist'e'r,\\ Chief, Projects Branch No.1 /Datte SUMMARY: One candidate was examined and one SR0 license was issued.
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..____. _ ________.__ ____ ___-_.-_________..__ __ _ _ , . I ! REPORT 0: TAILS l TYPE OF EXAMS: Replacement X ! ! EXAM RESULTS: l l l SR3 l l l Pass / Fail l ' l I I I I l Written Exas l 1/0 l l l
I ' I I i 10ral Exas l 1/0 l
I I I I I 1&<erall l 1/0 l l l
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Chief Exaniner at Site: N. Dudley, NRC l l > - - - m . . m . . . m
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1.
Personnel Present at Exit Interview: NRC Personnel N. Dudley, Lead Reactor Engineer (Examiner) Facility Personnel Dr. F. DiMeglio, Director M. Doyle, Assistant Director 2.
Summary of NRC Comments made at exit interview: The candidate passed the oral portion of the examination due to his knowledge of the facility systems and operations. He displayed weaknesses ir, the areas of thermo hydraulics, subcritical multiplication, and use of the emergency plan.
There were no emergency implementing procedures in the Horn Building ~, which is used as the control center during a reactor ~ building evacuation. The candidate had difficulty making decisions using-the information provided during oral scenarios.
More than one set of prints is maintained in the control room which may.
lead to problems in control of the prints.
3.
Summary of facility comments and commitments made at exit interview: The facility recognized the need to provide future SRO candidates with additional training in decision making.. The facility noted that other NRC inspections had identified the need to decentralize or formalize the functions held by the director and assistant director.
4.
Changes Made to Written Exam During Examination Review: Answer No.
Change Reason .I.05a Question Change " scintillating"~to Identifies correct type of " ion chamber".
' gamma monitors -installed at facility.
K.05 Question Change to "If a leak The primary coolant pump does developed by the primary not have a vent.
cooling pump during refueling could the core be uncovered? Explain."
L.07c Question Change "of 5 ppm" to Recently approved T.S.
have "above T.S. Limit. - Also removed chemistry limits on provide the T.S. Limit."
makeup wate. O
Answer No.
Change Reason J.04b Delete The neutron source is not removed during routine startups.
H.02 Add "(small effect at Incorporates facility plant)".
comment.
H.03b Change to "No difference Power levels are below the [0.4] because the reactor point of adding heat.
is below power level at which the power coefficient begins adding negative reactivity".
H.07b Change " Convective flow to The pool acts as heat sink atmosphere" to " Natural and heat transferred to convective flow to pool atmosphere is minimal.
which acts as heat sink".
I.Olb Change to " Post as radiation Conforms to facility area (2h mr/hr)".
procedures.
I.04b Correct for distant of 1 ft.
Incorrect distance for desired radiation level calculation was used in the answer.
J.01 Add " accept other Allows other SOM calculations calculations of SDM [1.0]". to be accepted for partial credit.
J.04a Change to " Prevent overload Corrects for. facility of detectors and loss of equipment configuration.
indication".
J.07 Change " Reactor power will Corrects for proper plant decrease; no scram" to "High response.
temperature scram".
K.0lb Delete "at pool".
SR0 not required to be at pool.
K.03d Change "6" to "3".
Criticality is expected with 26 fuel elements and 20 are loaded.
' Allowed to -load h the difference.
-, - .. A ... . - - . - .
.- .. . - - .- . -. . ... . -
i Answer No.
Change Reason , K.06 Delete " Assure the".
Add Ventilation system does not " Check for fuel damage", automatically realign on stack monitor alarms.
< K.08a Add "or low power section".
Dry gamma room maybe used.
L.01 Add " Changes to reactivity".
Identifies additional - required log entry.
L.06c Change to "H.P.". Conforms to facility . procedure.
L'.07a-Change to " Shutdown Rx".
Conforms to facility requirement.
- L.08 Change to "a.
Prevent Provides original reasons for , - reactivity excursions; inclusion of each requirement b.
Reactivity effects of in the Technical loading fuel in vacancies; Specifications.
c.
Shielding and N" decay".
Attachment: Written Examination and Answer Key-(SRO)' t
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_________________________ AF PLIC ANT : _________________ TNRTRUCTIONE TO APPLICANT: __________________________ Use separate paper for the answers.
Write answers on one side only.
Statie quest 2or.
sheet on top of the enswe? sheets.
F c 2 nt s for each question are indicated i r, p a r e r. t h + s e s after tne q u + s,1 c r. The passing
3r &de requires et least 70L in each crtegory anc e final grade of rt least EOL.
Enamination papers will be pt:*ec up si.
isi acurs after the cueniination starts.
L OF CATEGOPY L OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY ________ ______ ___________ ________ ___________________________________ 20.00 20.00 ________ H.
REACTOR THEORY ________ ______ ___________ 19.50 15.50 ________ ______ ___________ ________ I.
RACIGACTIVE MATERIALE HANDLING C # U 3"
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"^ * U /f, 5 , ' - t =- e.
. eu _1_____'_ _1.i__ ___________ ________ J.
5FECIFIC OPERATING CHARACTERISTICE 19.00 19.00 K.
FUEL HANDLING AND CORE ________ ______ ___________ ________ PARAMETEFE ,3*cc o.. .. _ _' _ _ _ _ _ _ _ ' _' _' _ _" ________ L.
ADnINISTRATIVE PROCEDUREE.
_ ___________ CONDITIONE AND LIMITATIONE W.S 1: 100.0( _____'_"__ ______ TOTALE ___________ ________ FINAL GRADE _________________L All wore cone en tnis enamination is n. y own. I have nc;ther 9tven not received aid.
___________________________________ APPLICANT'E EIGNATURE .
, . . - H.
REACTOP THEORY PAGE
.-------------
DUESTION H.01 (3 00) Let us assume that we have a reactor just critical at 100 MW, Dy some means we remove all the delayed ncutrons, a. Explain how and 9hy reactor power would respond to this change. (1.0) b_.
Earlain how and ehy reactor power vould r espond just prior to and just after removel of all the delayed neutrons if the reactor was prompt critical at 100 MW.
(2.0) OUESTION H.02 (3.00) Explain why the neutron startup source appears as positive, negative and zero reectivity worth depending on the powcr levcl.
QUESTION H.03 (2.00) a. Under steady-state operation, would there be any significant difference between the control rod positions at 100 watts and 1000 watts? Explain.
b.
Under steady-state operation, would there be any significant difference between the control rod positions at 100 KW and 1000 MW? Explain.
a , GUESTION H.04 (3.00) 6.
In a soberitical reactor enough reactivity is added to double the count rate.
What would be the ef f ect of adding the same amount of reactivity assin? Explain your answer.
b.
With an initial power level of 10 KWe reactivity is added to raise power to 20 KW.
What would be the effect of adding the same a nioun t of reactivity again? Explain your answer.
i i '
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., , . H.
REACTDE THE0E1 PAGE
__________________ GUESTION b.05 (3 00) Assume that a reactor has been at rated power for 72 hours and then 2s shutdown for one hour.
Sketch a continous trsee of xenor. c on:en-tration and briefly explain any changes for the following schedule * a.
Show xenon concentration for one hour before shutdown.
(1.0) 6. One hour after shutdown a reactor startup is made.
Fower is increased to 50% of rated and c.a2ntained for 12 hour s.
(1.0) c. At 12 hours the reactor power is increased to rated conditions and maintained for 24 hours.
(1.0) GUESTION H.06 (3.00) The reactor operator is conductin3 a routine reactor startup after it has been shutdown for several days.
Fi l or t o w 2 thdr a wing i-Enis blade he reads a stable count of 50 ces on the startup channel.
Immediately after withdrawing this blade he reads a count of 80 eps, s.
If he performed no blade motion for five minutes, would the count rate increase, decrease or remain the same? Explain, assuming the reactor is suberitical at 80 cps.
(1.0) b.
After 5 minutes he withdraws another blade the same distance ^ but the reactor is still soberitical.
Would the change in count rate (time and magnitude) be different than he saw in part ta) above; Explain.
(1.0) c.
What Iridicetions would the oper ator observe to determine wnen the reactor had gone critica10 (1.0 GUESTION h.07 (3.00) a.
Enplain why the gate will open on loss of p r i m a r _. flow.
o.
Euplain how heat is removed from tne cor e on loss of pr imar y flow.
(xxxxx END OF CATECORY H axxxx) . -. .
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L A.
O ACT!VE n ATE F I AL L HMCLINE IIE.i05AL AtJI H A AELI.
F ACE
.. _ _ _ _ _ " _ _ _ _ _ _ _ _ _ _ _. - _ _ _.... _ _. -. - - - _. - - _ _ _ _ - - - _ GUESTIO4 2.0; (2.00, A 23 vear old indtstdval has accusolatec a Itfettse cccupsticnal cose of 24 rek of whole booy e::posur e cotusentet i r..:: ct d a r.: e w2th 10CFh20 and has received no exposure durir.3 the present calender quarter.
a.
How long mey he wor 6 2 r.
e 3 mreA/nr ares :f he wor k s ar, E hour day h e r.c a y thrcugn Fricsy5 Shcw. cur wcr e. 41.5-b.
What 5 2 3ri postir 3 lebt11n3 s:3na;, or :cr.i r c ; reqv: resents entst.
I f any, for the work area desertbec tr. part a5 (0.5) GUESTION I.02 (1.50) The f c11 cw s r.3 t-questrens concerr, the c;c-stten cf the nestatt toce systes; a.
Wnst is the santant en-cor. tact resting i : r. a r e e.c h r i a;1c ec ci a sample before speesti permission is r equ:r e c to r emove 2t from tne reactor roca; b.
Whc is author 1:ed to give the special peratssicn for removal of the samples OUESTION I.03 (1.00) As a general guide, the tarisus peratssible level for teta ganza contaminetter. tsfter o e c o rs efforts have Deer, s a ce * Es mezsvrec with a thin winocw Ch cetector at the surface of tne c ontat:r a+ ;:n shall re ar/hr for n a a r d o. r c up s I anc 2 a r.c - ...--..ar/r,r fer ht:grt
groups 3 and 4.
fasssa CATEG0r* I C0riT!NUE: ON NEnT PAGE sassa.
- > u .. . .. . . . . .. . . ... . . . . .___.__._.___________;
. , . . I FADIDACT3Vi nATERIALE H ArJDL I N C. DI 5F'DT AL AND HA:ARD5 F AC E
_______________________________________________________ O UE 5 T I Ori I.04 (5.00) A 10 ml vtal of s mined 3 a m n.a and bets source in 11autd form with a beta particle enetgy of 0.5 neV has been spilled on the floor of the reactor room.
Readings at 10 feet indicate 1.0 mr/hr on a beta samma survey meter.
Give any thunb rules used in answerin3 the following questions: a.
At what cistance from the spill will the beta gamms readings start to incloce the betasi (0.5) b.
If the reading at one foot is 100 mr/hr wnat is the beta to Samma ratto? Show your calculations.
(1.5) GUE5 TION I.05 (5.00, JW! CHhMB E R 'I n;t t pe gamma monitor s placed a.
List the locations of tnree ;. +
atound or near the reactor.
(1.5) b.
What type of monitor is employed at the pneva.atic systen, receiver stations and beam port ar ea s? (0.5) c.
What condition or conditions cause the staci exhaust gas monitor system to alarm and for what purpose? (1.0) 00ESTION I.06 (3.00) During reactor operation. the cose rate from the delay tank may be in e:r e e t s of 100 arem/nr.
4.
Why b.
Who is required to have possession of the entrance key when the entrance is locked) c.
What facility requirements entst when entering tne delay tank room 7
- CATEGORY I CONTINUED ON NEAT FAGE *****,
' . , . . I.
RADIDA;TIVE n AT ERI AL E H ANDLItJG DISPOSAL AND HAZAF:: FAGE
QUESTION I.07 (3.00) 8.
Does the biological effect of a 100 REn dose cepend on whether it is a rieutr on or gamma dose? Enplain.
b.
Does the biological effect resulting from bodily intake of a given quantity ( I r. terms of nit er ocur i e s ) of a radioactive material depend on which par ticular isctope is i r.. ; 1 e d : Enplein.
GUESTION I.06 (3.00) A fuel element 25 suspended in the Reactor Pool appr oximately 1 meter under water.
A radiation survey meter held at the surface of the wate* reats 10 0 n: r e n, ' hi. a.
Ignorir.g bu11 cup. what raciation level wculd you enpect if the fuel e l e m e re t er ot e the water? Assus4 1 cc of water weignts 1 gm and that Figure 5.3 is applicable to your plant.
(1.0) b.
If the fuel e l e n.e n t was placed in a 1 inch lead shield ess6 what would the ractation level be at the surface 5 Assume a tenth thickness of 2 inches for lesd.
(1.0) c.
If the radioactive isotopes in the fuel element had an average half life of 30 minutes. how long would it take for the radiation level at the surface of the cask to drop to 2 0 n.r e ni / hr t (1.0: (****s END OF CATEGORY I
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MeV MASS A'ITESTATION COEFFICIENTS FOR GAMMA RAYS IN WATER
Fro. The At e-i c Nucleus, by R. D. Evans, ' , l Cop yr i j:h t 1953 l (Courtesy of McGraw-Hill, New York, N.Y.)
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_ _ _ - _ _ _ _ _ - r , . ,- .. - . Y J.. SPECIFIC OFCFATING CHAEACTERISTICE PAGE
______________________________________ ? . -DUELIION J.01 (2.50 ' / EXPLAIN anc CALCULATE what the r equir ed - shutdown m a r s tr.15 for 1 a r.
accor dar c e with the Techr.2 c al Specif 2 c atiores.
reacter opet stt or3 .0UESTION J.02 (1.50) . What actions shoolc be taken f an irradiatec vial euploces when the _, rabbst ha s ' r etvi ned to the r ec e 2 vir.3 s tat s or.
- GUESTION J.03 (2.50) What actions.should-the.5,entor Operator take following a scram?
, 4 GUESTIOri J.04 (~.50i
- a.:Duringa'reahter startup, what wovic be the effect on plant
. o p e r a t t e/,s 2f the ' star tup cour ter is not moved to its cereter pos t tlordanc then to its out position as the counts build up' (1.0) -bhIbbIf ive * te dr e J c-i ; : St -te; te 31101 010:22' 0' t *- ?
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- t-:- III - sc ce? ~1
GUESTION J.05 (3.00) a. What automatic actions will occur if normal electr.ical pcue-is lost wher. the reactor i s at 500 KW: b.
What Icaos, if any, shcolo be energ::ec fo!1ow2n3 a loss of norms! poser? J / / isasan CATEGORY.J CONTINUED ON NEXT' NAGE.armm > , o l a _i
., . . J.
GFECIFIC DEELAT3t:G CHARACTERISTICE PAGE
______________________________________ DUESTIOf-J.0c <3 00i Assuming the reactor is operating at 95% power, Indicate for each of the f ollowirig si tuat t oris whether the r(octor should be SCRAnnE~. s SHUTDOWN, REDUCED IN FOWER, or MAINTAINED AT POWER.
Consider each si tuatiori sep er at el y. a.
Reactor power orops one.:;ectecly to 9 2 ".. b.
Reactor power increaser to 97*a as the pool water ten.per at ur e increases.
c.
The alarn, for the high neutron flux on one of the compensated ion chaniber safety channels becomes inoperable due to a faulty relay.
c.
The temperature of tne coolant leaving the core during f or ceo convection coo 11 rig r eac hes 120 F.
e.
Primsry flow inoication begins to decrease due to a detector failure.
( Assvare p i r. h ol e leal in the dp cell di aphr ani. ) DUESTION J.07 (2.50) What would be the effect on the plant of securing the secondary circulating pump? Assume plant was initially at 100% power, with all rods in n.anual control, and that systems operate normally and no oper ator action is taken.
Include the safety channel, if any, which causes a s c r a n.. QUESTION J.0E (3.00) What four automatic f unctions should occur if the evacuation button is depressed 5 (***** END OF CATEGOPi J
- )
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., . . 6.. TUEL H A f;D L I t M. A N [e CDFE F A E u.E T E F E FACE ~ _____________________________________ DUE5 TION L.Oi (3.00 a.
Wno must authorice any a. o v e n. e r. t et the core; b. W r.a t operstors must be pr eser t f or any s. o v e s. e r. t of the core and where should they be located? c.
What instrus.entation must be available for any movenert of the core' c.
What must be acequately shielcec wnen the core as to be s.oved to the low power s e c t i ori of the pooli GUESTI0tJ K.02 (2.00) a. How is a fuel element constructed to prevent release of radiosetive fission products 0 (0.5, t.
Wnat THREE indications would be indicative of e relesse of fission products f r o n. tne ivel elements
- 1.~>
00ESTION M.03 (3.00) For each one of the four attached 1/M plots indicate the maxie4um no s.b e r of fuel elements which may be loaded. I ri accoroance with procedure, before ar other count rate reading should be taken.
QUESTION K.04 (2.00) a.
Euplain why the 1/n plot cannet be usec during fuel loading or ce a eritical mass has beer. established.
c.
How wcule an excess reactivity m e a su r e m e r, t ce ccncocted after a fuel element is aoded to a cere which has been deter ainec to ce a critical s. ass? OUEETION K.05 (1.50s atrAu cur.dre er If #' - -'-
- - the primary cocling pump 2: : '. - ' '
c,-- cur ing r ef ue llr.3 coule the core be encovered? Euplain.
taxmas CATEGOE! K C0t;TINUED ON NEXT FAGE xxxxm> .
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FUEL H A tiDL I rJ G At4D CORE F AF AF.E TE R; PAGE . :- _____________________________________ DUEETI0t.
l.. D e.
(1.50> If during refueling operations a r. Irradiated fuel element is droPFed orato the top of the core, whst a c t i ore s, if a re y. should be t al e re. The stack monitor has alarmed and radiation levels around the pool are 10 mr/hr.
QUESTION V.07 (3.00) a.
How is new fuel stored? (0.751 b.
How is irradiated fuel stor ed? (0.75) c.
Explain why different storage arrangements are necessary for new and irradisted fuelo (1.5) GUEETION V.05 (3.00> In what area or areas of the pool will fuel be located to provide: a.
Gamma radiation b.
Neutrcn and gamma radiation c.
Radiation to the Beam Forts d.
Radiation to the Pneumatic Tubes e.
Radiation to the Dry Gamma Facility (mx*** END OF CATEGORY K rrxxx
., " . . . L.
ADnINISTRATIVE Pf:DCEDURE E. CONDITIONE AND LI*.ITATIONS FACE
GUESTION L.02 (2.00) a.
What are THREE ttems that should be recorded in the reactor los book? (1.2> b.
When should an entry be recorded in the reactor los book? (0.8) GUESTION L.02 12.00) For each of the following procedural changes indicate whether or not the change can be approved by a licensed SRO.
Justify your answer.
a.
A temporary change to the startup procedure which allows pulling two rods at once.
o. A change te s n.a l n t e n a n c e procecure which cnanges the specifications for the container to collect water f r o ni a flush of secondary piping.
QUESTION L.03 (2.50) a.
At what THREE times is the Senior Reactor Operator required to be present at the facility? (1.5) b.
What is the Senior Peactor Operator's responsible for when he is assigned to a shift? (1.0) GUEETION L.04 (1.50) For each'of the following situations determine what En:ergency Classification. if any, should b e n. a d e. Table 1.1 is provided.
s.
A small private plane carrying radiactive isotopes f or a hospital crashes across the road from the facility.
b.
All water is lost f r o n, the pool ares resulting in radiation levels of 500 mr/hr in the reactor builcing.
All automatic equipment has functioned properly.
c.
The gate valve remains shut after the primar. coolant pump is secured during oper ations at 500 wttts.
(***** CATEGORY L CONTINUED ON NEXT PAGE
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, e: - > L 4.DNT riT RT R AT T UF P E D r.F D ilR F E. CONDITIONS AND iiniiATinNc.
PAGE
GUE5TIDd L.05 (3.004 ,The reactor is at 100% power with enperiments in progress.
An excited experimenter calls you, the on duty Senior Reactor Oper stor. and reports that the wall monitor near the receiver station is alarming, s.
What'adottional Information do you need from-the experimenter to analyze the situation; b.
What should be your major concerns? 00ESTION L.06 (3.00) For each of the following, indicate who in the organi stional chain is authorized to: a.
Allow an experimenter to insert and remcve hisLown euperiments.
b.
Supervise snort repetative irradiations which have been approved by a signed Irradiation Request Form.
c.
Approve the removal of a sasiple following a long irradiation.
d.
Give permission to startup whe reactor.
e.
Review and approve all experiments before they are initially performed.
GUESTION L.07 (3.00) What' actions, if any. are required in each of the following situations? a.
The reactor is operating at 500 MW when the tr ucV door must be opened.
b.
The reactor is operating,at 100 watts when'the ' building ventilation fan becomes inoperable.
-l c.
The reactor is operating at_500 Kw when the-effluent water in the ,siskeup system is a.easuree to have a particulate-level n' 5--- Agffe 7,6' Liet1T. ALK htniDC T S, L ssz s*. ~ d.
The reacter is at 100 watts when the! effluent water of the cleanup system I t' measured te have a resistance of 9X 10E5 ohm-cm.
- (ummax CATEGORY L CONTINUED:0N NEXT PAGE *****i
... }- ,, ,,,, J ' a , ,
.- - - . . . . - -- . ... -. _ .
~, , , c-e.- ! J.. - SPECIFIC OPERATIrJG CHAR ACT ERItiICS PAGE
------------------------
. Ml 5 W E R S -- P H O D'E I S L A N D & P R O'>. P'AEC-SS./04.'4-DUDLE).
N.
,
REFERENCE.
Operating Procedures' -p 7-3 < ANSWER: J.05-(3 00) a., Reactor scrams CO.5] ' -Propane gas generator unit starts. [0.53
-nutor.at':c-transfer switch operates E0.53 ^ b'. C4F Fffrt6cn f t.16tiIS' Sung Panf . peete - A vitis A dst'; TC SAFETY SYSTEMC ' . . REFERENCE' Operating Frocedures pz 10-1 ' ANSWER-J.06 (3.00) a'. Shutdown , b.~, Ser am c..naintain power E d.'Haintaan power' e. Scram.
REFERENCE' ' Operating lProcecures .p 8-2 T.S.
p 12. 26, 29 ANSWER-J.07 (2.50) . Pool temperature will increase adding l negative-react 2vity. CO.752 5 ;:t:- ,10 2 :- : uill 5::::::: ! O.' 5 pocl high temperature.alars activated E0.53 u_ _ _ _ _ _ -r e-- liun?rist.' 5'Ohh REFERENCE 054: TS p.;.9 05-01-1--and'DS:02-2 170: Operations hanval. Chap.-3 -nReactor?Wster.15ysten:s ' Reference Package. Reactor 1Paranieters ! - u w e-a w-l s,.- ' l _.
f -' 4J ,, , p., l - '
+1 _7--* ^ " % ~ -] . ' ' ' ' ~ s-N >. ' ,', , , , , - +, - - . -..,,. -,...... - - - -,. - -. ' ' -, , ,<
., . . . L.
A D nIrJIST R A T I V E PFDCEDURES, CONDITIONE AND LInITATIOt?! PACE
GUELTION L.0E (4.00i E:: P l a i n the reason or basis for each of the following Technical Specification oper ating limits.
a.
The absolute value of the reactivity worth of any single independent e::per iment shall not e::c eed 0. 006.
b.
There shall be no more than one vacant fuel element position within the periphery of the active section of the core.
c.
The minimum depth of water above the top of the_ active core shall be 23 feet.
d.
No experiment shall be installed in the reactor in such a manner that it could shadow the nuclear instrumentation systen moniters.
. (xxxxx END OF CATEGORY L xxxxx) (xxxsxzzar**** END OF EXAMINATION **xxxxar***xxami
,,...... ., d Cycle efficiency o (Networt . . v o s/t . f o.at out)/(Energy in) ,
s=V ! "~ w = mg o
- A *' E = mc
A = AN A = A;e KE = 1/2 my a = (Vf - V )/t PE = mgn 1= Ln2/t1/2 = 0.693/t1/2 w = e/t Vf = V, + at t eff = ((t3f7)(t)]
y, y gp - 1/2 I * It I) ((t1/2 o aE = 931 sn-I X I=Ieo . . Q = mCpat - nx I=Ie g Q = UA ct 10-x/TVL I=I a Pwr = W ah f TVL = 1.3/u sur(t) HVL = -0.593/u P = P*10 P = P e /T t SCR = 5/(1 - K,ff) o SUR = 25.06/T CR = 5/(I - Keffx) x-() CR,(1 - K,ff)) = CR (1 - keff2) SUR = 25c/t= - (s - o)T
M = 1/;' - K ff) = CR)/:R, ._ T = (1*/o) + [(5 -o)/le] M = (1 - K,,,_)/(i - K,,,, T = L/ ( o - B ) . .... ' SDM = 1'1 - K,f, /K,,f , T = (5 - c)/(1:} , l' = 10~ secones = ;K,ff-1;/K,f, = K,f,/<,fe
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- =
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- = :$
i Mis:eilaneous Conversions d ete-D ar amete"? IC 1 curie = 3.7 x 10 cps 1 gal. = 5.345 lom.
1 kg = 2.21 iom _ ' ;a!. = 1.75 l':ers ~ n- = :.5 'Of 5:; --
if0 = 7.45 gai.
i am = 3.41 x 100 Stu/nr ~
Density = 62.4 lom/f: lin = 2.54 cm fs) Oc9sity = 1 gm/c.P
- F = 9/5*C - 32
'- of vacorization = 970 3:u/lom
- C = 5/9 (*F-32)
Heit Heat of fusion = 144 Bru/lem ,, i Atm = 14.7 psi = 29.9 in. Hg.
I BTU = 778 ft-lbf
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F E ACTGF: THE0Ei FAGE
__________________ AW5WEF5 -.RHODE'ISLANC ! FFGV.-F AEC-EL 04/24-0U0cE(, rJ. ANSWER H.01 (3.00) a.
Reactor power would decrease since delayed neutrons were required to maintain the initial critical condition. (1.0) b.
Reactor power would be increasing prior to removing the delayed ' neutt ons and steady immediately after due to the reactor sustaining criticality on pron.pt neutrons alone.
(2.0/ . i ' ANSWER H.'0 2 (3.00) Below a given power ~1evel the source is adding more. neutrons than it is
absorbing ar.d it_has. ;-positive worth. E1.03 t At.a given power level the source is adoing the same nun.ber o+ neutrons ! as it is absor bing and has a reto worth. E1.03 Above a given power level the source absorbs more neutrons than it adds and has' a -neoative wor th. E1.03 UMML carect nr psisMy) REFERENCE
Operating-Procedores p 7-3 Safeguards-Report p 10 . , ,
ANSWER H.03 (2.00) a.
No difference EO.43 because the reactor i s below heat range and ' -the power coefficient does not add any _nesstive reactivity. [0.63 t.
r:d: - e-:Ic t= k_7-
- *00? ' ' "
E' r 'tc ::,--.::te - en e, <c- +N .,_4 ,.,,_ ,4 , ,4 . -s, s. +x,- _ .... ,,..m<< ,-,m,
jio'biiiinrkii TirY ' NGr%5Vr'i irdcred Tis bia.a ~NHor iC.7/ [hr wasc n REFEREHCE y t1 E PC W FA (CEf RCsC47 6t St Wu M C.tWe NfyA 72e7 ff4 C T2 elff a Safeguards Report (1962) p 44
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REACTOR THEGFY.
FACE
__________________ ANSWERS -- AHGDE ISLArJD E FF0V. F AEC-GS<04/;4-DUDLEY.
N.
ANSWER-H.04 13.00) a.
Reactor would be supercritical. [0.753 By doubling count rate 1-Keff is halved.
0.90 at 20 ces then Keff = 0.95 at 40 cps Assume Keff = 5.85% delta K/h
- change in react 2v2ty = 0.05/(0.9 x 0.95) =
reactivity need for criticality = 0.05/(0.9 X 1.0) = 5.26% delta K'N .5*4 delta K/K excess reactivity would be added. [0.753 (Calculations not required for full credit) b.
30% power [0.753-power coefficient of reactivity is linear [0.753 REFERENCE Nuclear Energy Training, hodule 3 Rv Ops. Unit 12.1 ANSWER H.05 (3.00) A.1 Std.
Es Psosaw
rg #c(Ar ff? 8 8#A'I' ANSWER H.06-t3 00) 'Tg gesur.
a._ Increase slightly then level out due to sub-critical mult.
(1,0) b.
Larger-increase and longer to level out greater. number of generations. (1.0). c.
Steadily-increasing count rate or slight positive period with no rod-withdrawal. (1.0) ANSWER H.07 (3.00) a.
When flow is-lost, the pressure crop across the core decreases. [0.53 Pressure differential across the gate-decreases. [0.53 The counter weight. opens the gate. [0.53 Hb._ Conductive heat' flow across fuel into coolant. [0.53 Natural convective' flow to surface of the pool. [0.53 -- e- - ..a.
. r.
....<.-..... [b stk' ^ cis Nc izs t ' i d T E UP?lt %nith MD ' As negt SZt'd [0. 5] ' REFERENCE Safeguarc Report (1962) p 54 .
- ..
- g I.
RADI0 ACTIVE MAIERIAL5 HArJDLING DISPO5AL AND HAZARDS FiGE'
-----------------------------------------------
ANSWEF S -- ~ 6HODE - ISL Ar/D' A FROV. P ACC-85/04.'" 4-DODLE (, H.
ANSWER I.01 (2.00) a... Han. Dose = Dose Rate X Time' [0.53-1.25 Rem = 0.003 Rem /hr X-8 hr/ day X No. of Days E0.73 ' No. of Days = 52 days or 10.4 weeks CO.33 " - ^ - ~ " - ^ - ' --- * --- --' ----- - NGi ' M ' $n cin ticu hRm' Tx*91M/h) ~ ~ ' EO. 53 b* . REFERENCE Radiation Safety Guide p 20, 21, 30 ANSWER-I.02 ( 1.' 5 0 ) a. 200 mren C0;753 b. W.SRO n H fsWFl O. 753 REFEREriCE Oper atires -Pr ocedur e p 12-4-ANSWER.
I.03 '(1.00) 0.~ 1 ar/ht-1.0'ar/hr 'CO.5,each3-REFERENCE-RINSC Radi'ation Safety Guide pg. 32 - ANSWEE- -I.04 (3.001 a.
-12 ft/hev v 0.5'Nev= 6'ft [0.53 - o b.
d w-(t)^2 = D x (R)^2 j E0.63 . . 1,ar/hr x-(10)^2 = D-x Mi^2 CO.33 D = (T mr/hr EO 13 0~
- ICC 100 m r / h r -~ E-88 m r / h r'
' C 0 '. 5 3 Beta cose = = *** m r / h r CO.13 'o~ E-.; t: 5 ;;.. o
- .1 -;.- ~5'
- 5
CO.63' = A/, BrTA's : P4f 5E N T ,t ,
.s ,.- - - -
' ,w g r- , w_ - .-
~
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. .*. (I. (RADIDACTIVE riATERIAL5 HANDLING DISPDSAL AND HAZARD 5 PACE
- -------------------------------------------------------
ANE.WER5 -- RHODE ISL AtJD !. FROV. P AEC-85/04/24-DVDLE1 N.
'ANSW'ER I.05 (3.00) stack wf 3 0 st2CVc - rort m l w W omswERu i s cg ^a..CAF E0.5 each3.
putt S4rt - HX 6.
Geiger tubes CO.53 - e..Betsiparticulate monitor CO.53 Gas monitor E0.53 REFERENCE T.' S. p 14, 15 ANSWER I.06 (3.00) a.
Holdup tank allows N 16 to decay away. The N le produces high ener gy gammas and have a short half life. E1 03 ' b.
SFO C1.03 ( CCA7 AMD 2N htY SAFE) .c.'CAFEUse portable radiac when entering room. E1.03 ANSWER I.07 (3.00) a. No:EO.53-A-Rem dose accounts for the type and energy of radistion.'[1.03- ~ - b.
Yes E0.53 Internal dose depends on biological and physical T 1/2, referred' organ, type of radiation. E1.03 - REFERENCE Radiatzon Safety Guide p 25
ANSWER I.08' (3.00) a.
-I = Ic e{-ox}- CO.43 100 mrem /hr = Io e{-0.035 cm(-1) 100 cm>' E0.43 Io = 3311 mrem E0.23 'Io 10-{-x/TVL} .[0.43 b.
I = 100-arem/hr'~10'{1 in/ 2-in} EO.43 = .=. 69. mrem /hr JEO.03 c.- A.= Ao e{-0.693/' half = life X. t) [0.43 t-= (In A/Ao)-.x half--life /-0.693 = In"20/100~ X.-30. min./-0 693 [0.43 t:= 70 min- .E0.23: . > ,. . ~. . . -, ~ m _ um
_.
'm ' ,, , , .O f-J.'- SPECIFIC OPEEATING EHARACTEPISTICE PACE
.... --------------------------------- ! A s,5 R E F:5.-- RHODE ISLA* [ t PROV. F AEE-E5/04/24-DUDLE1 N.
- l i ! Atl5WER-J.01 (0.50) Eeactor must be sober:tical if any single control element and the ! regulating element wer e withdr awn. E1. 3 minieve.-ED = reactivity of most reacti.e ccr,tal e l e c e r.t e3 cd - - 0 07 + 0.007 l -~~ l' MWT CWK ub. drNher sen [1.Q l-FEFERENCE I T.S.
p. 27,28 AN5uEP J.02 (1.50) L use interect to inform RO l P i r.s e c ont a mi re r te d 56 in i Wait.for H.P.
CO.5 each] REFERENCE Operating Procecures p.12-4 l ANSWER J.03 (2.50) Assure actions-requirec for the safety of_perscr.nel cr protection of equ2 pmer.t.have been taken.
E0.73: l Determine cause EO.5; Correct.sonorssi c or.d i t t or. [0.52 Complete. applicable pertions of the. check cut procecure anc - avtr.cr ire startup of resetcr :0.53 ! Assure.acticos are reccrded in log CO.33 REFERENCE.
, ~ p_C-2 l Operating Procedures l ANSNER J.0- - (2.50) PRit(sT HidMAb CF Cn rrsrChpeU55 f f J H*M IIW A r-
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, . . . . .. - . 'e .'y i 'J.- SF ECIFIC. 0PERATING CHAF: ACTERISTICS FACE
. -______________________________________ MJ5WERS J -JRHODE ISL ArJO A P P C 'J. P AEC-85/04/24-000 LEY, rJ. ' REFERENCE-Operating Procedures-p 7-3 ANSWER J.05' (3.00) a.
Reacter serams CO.51~ . Propane gas generstor unit starts [0.53 Automatic transfer switch' operates E0.53 b'. C AV it McR6cNt f L1Hi.5 SUMP PanC . .. 70 SAFETY.SYSTEMC . . A. ca ' n yazs n osE . REFERENCE Operating Frocedures p 10-1 ' ANSWER ' J.06 (3.00) .a.
Shutdown-b.
Scram c. Maintain, power-. d. Maintain power.
e. Scram REFERENCE Operating Procecures o 8-2 T.S.
p 12 28. 29 ANSWER J.07 (2.50 Flocl temperature will increase adding negative reactivity.-.CO.753 E ::t:- ; :::: ri:1 -i :::::;- :2.75: Pool high. temperature alars activated CO.52 !! 5: N :- ::::: ~ SCRAM - TE MP- - Hiln-REFERENCE 054:.TS'p.
-
- .
'DS-01-1'and OS 02-2 170: Oper ations: hanual, Chap.- 3 Reactor. Water ' Systems Reference Package, Reactor l Parameters .
\\ f vr f , . -- Y
. * * - ~ f,4
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. , . .1 - U*F r.i F T r. AP F R AT T N C r.H AR ACT E F.I ST I C E PAGE
______________________________________ A rJ L W E F. E -- RF10DE ISLAND F P F D L'. F' AEC-85..4,21-DUDLEN. t4. A rJS WER J.08 (3.00) Evacuation hor n blows.
Air conditioning and normal ventilation turns off.
. Dan per s on all ventilating ducts leadir s to the outside have closed.
Butiding cleanvF systen. air scrubber c o n.e s on.
E4 at 0.75 each] ~ REFERENCE T.S.
p. 24 . _
... . . . . F:. FUEL HArJDLING ' AND COEE P AR ANETERS PAGE
A rJ 9 W E E E -- FHODE 15L ArJD A F F O '). P AEC-E/04f:4-DUDLEr, ri. ANSWER K.01 (3.00s a.
Assistant Director CO.75] b.
RO in MCR [0.353 \\ SRO ' c^b CO.43 c.
Control and safety system Instrumentation E0.751 d.
Dry Irradiation Facility [0.753 REFERENCE Oper ating Procedur es p.
5-1 ANSWER K.02 (2. M) a.
Fuel is contained i uminum clsccing i15 mils tnicki EC.52 b.
Inc r e e sing r e s dir.3
- ec monitor Increasing reading r monitor Incressing readin,e sch exhaust gas or particulate monitor Increasing activi'
31 samples Cany 3 0 0.4 each] REFERENCE Safeguards Report Emergency Plan p.
ANSWER K.05
b.
c. 3 ( Atesr once Ivo c. tA3 CO.75 eact.
REFERENCE Operating Procecures, 2-4 c ANSWER L.04 (2.00) a.
If a critical mass exists a constant subcritical power level cannot be establishec with all blades out.
c. Use in-hour method elaborat _ _ , _ *. . m -, _ 3.
/,._ - f UEL H'AtJDLItJG' AND CORE f AF AMETERS PAGE
i i .K.
. ------------------------------------- ' AtJ5WERS ' RHO'DE I$L AND g perfj. F AEC-85/04 / M rOJC LE r, rJ. ' - 1TFERENCE ' Operating Procedure, p 2-4 , -ANSWER.
K.05~ 'il.50 ) - No.<CO.53fThere is.an automatic anti-stphon loop connectec te each of;the prin.ary lines. E1.03 REFERENCE Saf eguar ds Repor.t-.-(1962) p 24 ANSWER-K".06 (1.50) - venttistion systen. realignc. 00.753 - - - ' ' recover _ dropped e l e r.ie n t. [0.75) e Hec a -ren' ruta cAnn&C REFEREr4CE
- Emergency Plan p_ 13
- ANSWER-K.' 0 7 ~
.(3.00) a. Stored in egg crates-which contain not more than 3 fuel elements.JW FW' - 6WM M.
Haybe-stored dry. CO.753 - b. Storec in racks in the fuel. pool.
(_9 or -- 18 element r acks. ) CO.753 c. Irradiated fuel.contains decay hest, which must~be ren;ovede: CO.753 ano fission. decay products, which require shielding. 00.753-REFERENCE T.S.
p
' -ANSWER K.05- .(3.00) a.' Fuel storage en f.e d l**'r k ib..-High and Low-Power-.seet:ons - ic. High, Power'seetion d.-High Po'wer. seetion - ~ ' e._ Low'Fower section-CO.6 eacn3
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FUEL HAtJDLItJG AND COFE F ARAMETERS PAGE
...-_____-_________
At45WERS -- RHODE ISLArJD d P R O '). F AEC-55/04/24-DUCLEr. rJ. REFERENCE Safeguards Report (1962) p 23, 30, 33 l
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p .4- ..... > I _ _
. _ _ _ _. __ , . . . . . L.
A D nI N I S T R A T I'.'E F'F: 0 C E D ttP E 5 C Ot4DIT10r45 AND L InI~ A T IOtJ5 ""
ANLVERE -- RHODE ISLAND f F F:OV. P A E C - 8 5 / 0 4 - : 4 -- D U D E t. N.
ANSWER L.01 (2.00) c.
All control blades and regulatin3 rod movements All experiment insertions and removals Changes in Operators and Senior Operators Inpor tant instruct 2cns to the relief oFerster Cany 3 0 0.4 each] Lhno th rc RE A C TI v1 T y b.
F. e c or d at the time and in the ordet in which they occur. CO.53 REFERENCE Operating Procedure p 8-1 ANSWER L.02 (2.00) a.
No CO.63 Procedure change effects safe operation of the plant. CO.4] b.
Yes CO.63 Does not change intent of procedure. [0.4] ANSWER L.03 (2.50) a.
Initial startup and approach to power.
Recovery from unplanned shutdown or power reduction.
Refueling.
CO.5 each] b.
Responsible for all activities which may affect reactor operations or involve r adiati on harar ds. C1.03 REFERENCE T.S.
p 20 g ANSWER L.04 (1.50) a.
No classification . b.
Site Emergenev c.
Unusual Event { CO.5] { REFERENCE Emergency Plan Implementin Prceedores, Table 1.1 ' I i i l.
'
. . . _ _ - ~. ..
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- n :*. '. L. NDhIN157kATIVE. PROCEDURES. CONDITIONS AND LItiIT ATIONS FAGE " , .--------------------------------------------------------- 4NSWERI -- RHDDE-ISLAND E FROV. P AEC-85/04d4-DUDLEY.
N.
ANSWER-L.05 '(3.00) a. Has a' sample been withdr awn.f r om-the cor e? EO.63 Is;the-sample'still in the receiver? CO.63 What was the reading onthe1 wall monitor? E0.33 b Minimize exposure of experimenter. [0.63 , .h2 nimize spreed: of contamination. - EO.63 Reduce radiation levels at the reciever station. E0.33 ~ REFERENCE Operating. Procedures p.12-3 ,
- ANSWER L.06'
(3.00) a.cAssistant Director
- b. ROL c.' bess ;.nt C. : : ; 7. u ; HR
' d.
SRO e.cReactor Utill:ation Committee EO.6 each] . REFERENCE Operating Procedures p-7-1,'12-1,l12-2 T.S. p 23 ANSWER . L. 07-(3.00i' snr occf Rx a. 'E+2tir" ~ -- e r e * c' +"e stst:c-c e t:c 4-:tr
- ' ts e
'f - E0.753 - b. Scr am*'de r e a c tor. [0.753 ' l c. ' Dr ain and f refill the makeup ~ system'. CO.753 d.
No action requ2 red..CO.753 . REFERENCE-T.S p.24,-25 . $ e
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a---,2 n - - - .- a ,x, , - _ _ _. . .,'. . . e: ADcItJISTRATI'_JE PROCEDURES.
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CONDITI0tJS ArJD LIttITATIGN5 FACE
________ ________________________________________ ________
ArJ5WEP3 -.RHOCE 'ISL ArG E F R O 'J. F'. A E C -8 5.' 0 4 < 2 4 -DU D L E Y, rJ. i-ANSWER L.08 (4.001 1Ri v tr/T RCnLTiv;TY Ct:ufS10$s a..Wi!! .c t cc: ce # 101 telt* ; r > e r-t c e::+c-
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e.. m., g g g - r 7,, ti7+ q..g gm ,,ggg s77, ,7t ig c1,93 gencrupr rfiruts rF uht;a.- rah. O e+s VAcn$1ES, <:...-s.,, ... ...,.. ' I"i
- El'03 23TI E F;33EEli
- i l I hi[rihi'M24 mmc "ofNr "' ' C l d.
Prevent erroneous and unreliable information from being sent to.the control system safety circuits. E1.0] I REFERENCE-T.S.. p 23-25.
i " Ssfe9parde Report-(1962) p 6B
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L.02 2.00 DUD 0000818 L.03 2.50 0U00000829 i L.04 1.50 DVD0000831 L.05 3.00 DVD0000821 L.06 - 3.00 DVD0000822 L.07 3.00 DUD 0000830 L.: w __.
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