IR 05000134/1985004
| ML20136F331 | |
| Person / Time | |
|---|---|
| Site: | 05000134 |
| Issue date: | 12/23/1985 |
| From: | Keller R, Kister H, David Silk NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20136F317 | List: |
| References | |
| 50-134-85-04, 50-134-85-4, NUDOCS 8601070345 | |
| Download: ML20136F331 (38) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 50-134/85-04 (0L)
FACILITY DOCKET N0. 50-134 FACILITY LICENSE NO. R-61 LICENSEE: Worcester Polytechnic Institute Worcester, Massachusetts 01609 FACILITY: Worcester Polytechnic Institute Reactor
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' EXAMINATION DATES: November 5 and 6, 1985 CHIEF EXAMINER: I / <
'/ F04 /2-3-85 David M. Silk,' ctor Engineer (Examiner) Date REVIEWED BY: /1/9M Robert M. Kel'Tef, Chief, Projects Section 1C Date ~
APPROVED BY: A / d F H'arry B. V/1)ter, TtRef, Da/e [
Projects EManch No. 1 SUMMARY: Oral and written examinations were administered to one SRO upgrade candidate. Candidate passed both examination {g $
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REPORT DETAILS
- TYPE OF EXAMS: Replacement
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EXAM RESULTS:
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-l SRO l l Pass / Fail l 1 I I .I I l Written Exam l 1/0 l l l l l l l l Oral Exam i 1/0 l l l l l l i I l Overall l 1/0 l ,
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> CHIEF EXAMINER AT SITE: David Silk OTHER' EXAMINERS: Gordon Robinson (Observer)
' Comments on availability of, and candidate familiarization with plant reference material in the control room:
Candidate could not locate electrical diagram of consol . Personnel Present at Exit I m;rview:
NRC Personnel David Silk [
' Facility Personnel L. C. Wilbur ; Summary of NRC Comments made at exit interview:
Candidate passed oral eiaminatio &
Good Housekeeping practices as evident by clean and orderly facilit Suggested that reference material used to train candidates in the area o)
Reactor Theory be included in material sent to examiners for future ex- ,
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- CHANGE MADE TO WRITTEN EXAM DURING EXAMINATION REVIEW:
Question N Change Reason H.05 Delete second response Modify answer ke in answer' key and redis-
-tribute point I.03' Include in answer b): Modify answer ke "To'save a life" and
"To correct an emergency situation."
Attachments:
1. Written Examination and Answer Key (SRO)
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U. S. NUCLEAR REGULATORY COMMISSION f($ g >
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[ SENIOR REACTOR OPERATOR LICENSE EXAMINATION
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__{{{{}_}_{g{}i_}_N}}}}[ E i REACTOR TYPE: TEST _________________________ DATE ADMINISTERED: 85/11/05 _________________________ EXAMINER: SILK, _________________________ APPLICANT __A_%wgT_h_____________ INSTRUCTIONS TO APPLICANT! ____-_____________________ Uce separate paper for the answer Write answers on one side onl Staple question sheet on top of the answer sheet Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination start % OF CATEGORY % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY ________ ______ ___________ ________ ___________________________________ 20 0 20 8 ___I_0___ ___I_3 _ ___________ ________ REACTOR THEORY 20.00 20 8 ________ ___1_3_ ___________ ________ RADI0 ACTIVE MATERIALS HANDLING
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DISPOSAL AND HAZARDS 18.00 18 7 ________ ___1_5 _ ___________ ________ SPECIFIC OPERATING CHARACTERISTICS 18.00 18.75 ________ ______ ___________ ________ FUEL HANDLING AND CORE PARAMETERS 20.00 20.83 ________ ______ ___________ ________ ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS
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96.00 100.00 TOTALS ________ ______ ___________ ________ FINAL GRADE _________________% All work done on this cvimination is my own. I have neither Sivon nor received ai ~~~~~~~~~~~~~~ kPPL5CdUTIs~55GUITURE
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GUESTION H.01 (3.00) , Given K-eff, what will tne neutron population do with and without a source present? Assume K-eff is the result of neutrons created from the fission of fuel onl Place the letter of the best response in the proper locat-ion in the table belo K-eff Without source With source added a. Linear increase
<1 b. Equilibrium 1 c. Exponential increase >1 d. Large Exponential increase e. Vanishes QUESTION H.02 (2.00)
How would you determine the half-life of an isotope created from an irradiated specimen? Give your answer in equation for QUESTION H.03 (3.00) The reactor is critical at 10 watts and the regulating rod is withdrawn to cause reactor power to increas What would happen to reactor power if the void and temperature coefficients were positive? QUESTION H.04 (3.00) The reactor goes from 500 watts to 1 KW in 35 second By using a simpli-fied version of the inhour equation ( h = .08 sec^-1 rj6' = .0065) the amount of reactivity added to the core determine QUESTION H.05 (3.00) Explain the different modes of heat transfer by which heat is removed from the fuel. Include major components involved in the heat removal process starting with the fuel and ending at the ultimate heat sin How long will the reactpr have to operate at 10 KW to raise the temper-ature of the pool one degree celcius. Assume all heat remains in the pool and the mass of water in the pool is 27105 kg, the specific heat of water is 4.18 kJ/ks-C, and 1.055 BTU's equal one k (xxxxx CATEGORY H CONTINUED ON NEXT PAGE xxxxx)
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QUESTION H.06 (2.00) e With the reactor critical, a lead plate is suspended from the bridge along cide the cor What will reactor power do and why? GUESTION H.07 (2.00) What changes, if any, will occur to the thermal neutron flux at 100% power ever the life of the core? OUESTION H.08 (2.00) How much reactivity has been added to a suberitical reactor if the count rate has increased from 100 cps to 150 eps and if the initial value of K-eff was .95?
(xxxxx END OF CATEGORY H Exxxx)
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I< RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 4 _______________________________________________________
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e OUESTION I.01 (4.00)
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When accepting the delivery of commercially prepared isotopes What three steps need to be completed to verify that the shipment is not contaminated? (1.5) What two precautions are taken to prevent the spread of contamin-ation? (1.0) The external surface of the package containing the radioactive material is determined to have a dose rate in excess of 10 CFR 20.205 limit What is the dose rate limit and who is to be notified? (1.5) QUESTION I.02 (2.00) a. What personnel monitoring is required for an individual entering a rad-istion posted area? b.-When surveying the facility for samma detection during critical operat-ion, what four places should be given particular attention? QUESTION I.03 (4.00) A 23 year old individual has accumulated a lifetime occupational dose of 24 rem of whole body exposure documented in accordance with 10 CFR 20 and has received no exposure during the present calender quarte How long may he work in a 3 mR/hr area if he works an 8 hour day Monday through Friday? Show your wor (2.0) Any individual in a restricted area may be allowed to receive a whole body dose in excess of the administrative quarterly limit under cer-tain conditions. Name three condition (2 0) QUESTION I.04 (2.00) A mixed samma and beta source in liquid form spills on the floor. Readings at 10 feet indicate 1.0 mR/hr on a beta gamma survey meter. If beta's are not detected further than six feet from the spill and if the combined beta samma dose rate at one foot is 120 mR/hr, what is the beta to gamma ratio? Show your calculations.
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(xxxxx CATEGORY I CONTINUED ON NEXT PAGE *****)
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- '00ESTION I.05 (3.00)
, c. Does the biological effect of a 100 REM dose depend on whether it is a neutron or gamna dose? Explai Does the biological effect resulting from bodily intake of a given quantity (in terms of microcuries) of a radioactive material depend on which particular i sotope is involved? Explai QUESTION I.06 (3.00) A fuel element is suspended in the reactor pool approximately 1 meter under water. A radiation survey meter held at the surface of the water reads 100 mR/h a. Ignoring buildup, what radiation level would you expect if the fuel element broke the water? Assume an attenuation coefficient of 0 035 cm^- (1.0) b. 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 a one inch lead shield cask to drop to 20 mR/hr? Assume an initial contact dose of 2 R/hr for the fuel element and a tenth thickness of two inches for lea (2.0)
-GUESTION I.07 (2.00)
What radioactive gas is produced from operating the reactor, where is the Sas produced, and how is it made?
(***** END OF CATEGORY I xmmma)
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GUESTION J.01 (1.00) . Why will the ventilation system continue to operate in case of a radio-active spill? OUESTION J.02 (3.00) ; Control blades drive motors are interlocked against withdrawal of blades under what five conditions? GUESTION J.03 (3.00) Explain how a Compensated Ion Chamber (CIC) work (2.0) If a CIC is undercompensated, what would be the relation between actual and indicated neutron? (1.0) GUESTION J.04 (3.00) In regards to an excursion, explain why the temperature coefficient is positive in the gap in Figure QUESTION J.05 (3.00) Why does the thermal neutron flux peak just outside of the core region, as indicated in Figure 27 (2.5) If the thermal flux paralleled the fast flux (i.e. no thermal flux peak outside the core) how would the ratio of maximum to average thermal flux deviate from the present ratio (increase, decreaser or remain the same)? (0.5) QUESTION J.06 (3.00) Draw a block diagram of the safety instrumentatio "
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Jt SPECIFIC' OPERATING CHP.RACTERISTICS PAGE 7
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When should a sample or an experiment be ' doubly encapsulated and ensured leak-tight? GUESTION J.08 (1.00) Why.is the Boron 10 proportional counter fully withdrawn to its uppermost position during full power operations? s
(***** END OF CATEGORY J mummm)
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. GUESTION K.01 ( .50)
, .What must be the minimum regulating blade worth if it is designed to hold the reactor soberitical with all three safety blades withdrawn? -GUESTION K.02 ( .50)
What is the minimum number of instrumentation channels required to obtain suberitical avitiplication plots during a critical experiment of a new (not previously used) core configuration? QUESTION K.03 (1.50) Is it acceptable, according to Technical Specifications, to load fuel in the followin3 manner? (0.5) Explain. (1.0) See. Aynr 3 Increment Number Fuel Element To Be Loaded 1 F7, 1, 2, 3, 10, 6, 5, 4, 9 2 F13, 12, 14, 11, 15, 19 3 F20, 16, 18, 17, 8, 24 4 F21 5 F23 6 F22 OUESTION K.04 (1.50) The reactor is at 100% power. Consider four concurrent failures: an instanteous addition of excess reactivity and three failures to scra What reactivity effects will cause the excess reactivity to diminish? QUESTION K.05 (1.00) What is the reason for being able to invert and/or rotate a fuel element in the core? OUESTION- K.06 (1.00) What limit is there on"the temperature coefficient of reactivi.ty? During critical reactor operations, what is the maximum and minimum temperatures of the reactor pool water? e (mmmmm CATEGORY K CONTINUED ON NEXT PAGE mamma)
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1 2 3 4 5 6 7 8 9 . A B C D E F X - 1 X X X
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TYPICAL CORE ARRANGEMENT NORTH FUEL RACKS (
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* .- GUESTION K.07 (1.00) , . Unless otherwise authorized by the licensed senior operator in charge, what requirement is there on fuel stored in the storaSe racks when the reactor contains a critical mass?
GUESTION K.08 (1.00) If one of the control rods is removed for maintenance purposes, what must first be done to the core? GUESTION K.09 (1.00) Is poisoning required for reactivity control for the fuel elements in the storage racks? Why or why not? GUESTION K.10 (3.00) p When more than one grid position is involved in a loading changer what ), physical evolutions does the core experience and what calculations are made during the alteration and subsequent reloading? , GUESTION K.11 (3.00) During fuel unloading What is the minimum number of personnel required to be present? What qualifications are required by those present? Where are they to be stationed? What parameters are monitored?
(xxxxx CATEGORY K CONTINUED ON NEXT PAGE xxxxx) ..- :-. - - ._ --. - . - - - - --
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- GUESTION K.12 (3.00)
. What is the approximate melting point of the clad? (0 5) If the pool drained instantly to below the grid plate no fuel melting or dangerous release of radioactive fission products are anticipate Why? (1.5) If the pool water level went below , the grid plate, how would the core be cooled? (1.0) . . (***** END OF CATEGORY K *****)
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. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE /j#
_________________________________________________________ QUESTION L.01 (1.50) Who reviews experimental procedures at WPI? If an experiment is considered unsafe, final approval is withheld until what measures are taken and who gives final approval? OUESTION L.02 (2.50) If your name is on the emergency list and there is a radiological emergen-cy and you are the first to arrive at the Washburn Laboratory, what are you to do? QUESTION L.03 (1.50) Who can authorize use of temporary procedures that do not change the intent of the initially approved procedures? (1.0) Who subsequently reviews these temporary procedures? (0.5) GUESTION L.04 . ,
( 1.50) Where should persons, who have reason to believe they have been contam-insted, report durin3 an evacuation? Contaminated areas will be isolated and cleaned up under whose super-vision? All decontamination procedures will be under whose supervision?
QUESTION L.05 (1.50) What three actions will thh Reactor Operator or the Facility Director perform before evacuatin3 the reactor building during an emergency? z QUESTION L.06 (1.50) In the event of an actual emergency, list the six organizations and/or persons the Facility Director or the Ranking Senior Operator would contac .
(xxxxx CATEGORY L CONTINUED ON NEXT PAGE xxxxx) .- _ - . . _ _ _ _. --_ _ . - - - _ -
L e, ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 12 _________________________________________________________ ' QUESTION L.07 (1.00)
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When is a channel or instrument considered operational? OUESTION L.08 (1.00) The licensed senior operator on duty is "readily available on call' if what two criteria are met? QUESTION L.09 (1.00) Where is the Emergency Support Center?
' Who determines the reason for an evacuation and corrective measures needed?
GUESTION L.10 (1.00) If you as an operator experience a physical disability, such as might cause operational errors endangering public health and safety, who is to be notified and how soon after the occurrence of the disability should the notification be made? OUESTION L.11 (2.00) Give two examples of surveillances required by Technical Specifications done on the following frequencies Daily Guarterly Semiannually Annually (***** CATEGORY L CONTINUED ON NEXT PAGE **xxx)
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' GUESTION L.12 (4.00) . Indicate if each of the following is or is not a Reportable Occurrenc If it is not, how would you change the statement to make it a Reportable Occurrence? A radiation level of 25 mR/hr 1 meter above the poc1 surface The weekly RSO survey of the purification demineralizer indicates a dose rate of 10 R/hr A safety system setting more conservative than the limiting setting established by Technical Specifications A contaminated person leaving Washburn Laboratory No senior operator is present during reactor operation (mmuum END OF CATEGORY L mauxx)
(zummmmmmmmmma END OF EXAMINATION mamanummmmmmmmm)
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w = og s = V,t + 1/2 at l z 2 . me : KE = 1/2 av a = (Vf - V,)/t A = AN A = A g e"** PE = ogn Vf = V, + at w = e/t A = an2/t1/2 = 0.693/t1/2 1/2 8## * E(*1/7)(*h)3
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Q = aCpat Q = QAgt [=[o Pwr = Wf4h I = I,10~*/U L TVL = 1.3/u sur(t) HVL = -0.693/u - ' P = P*10 * p , pa ,t/T - SUR = 26.06/T SCR = S/(1 - K,g ) l CR x = S/(1 - K,gx) SUR = 26e/t* + (s - o)T CR j (1 - K,gj) = CR 2 (I - "eff2) ' -
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T=(&*/s)+[(s-e)/Se] M = 1/(1 - K ,g) = CR j/CR,
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T = s/(o - 8) M = (1 - K,go)/(1 - K,gj) T = (a - e)/(la) SDM = (1 - K ,g)/K ,g e = (K,g-1)/K,g = AK,ff/K,g t* = 10-5 seconds
_ T = 0.1 seconds e = ((&*/(T K,g)] + [i,g/(1 + AT)] Id ' jj=Id2 ,2gd2 i P = (z+V)/(3 x 1010) Id jj 22 2 I = eN R/hr = (0.5 CE)/d (meters)
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R/hr = 6 CE/d2 (feet)
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Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lem.- I curie = 3.7 x 1010gp, 1 ga . = 3.78 liters I kg = 2.21 lbm I ft* = 7.48 ga I hp'= 2.54 x 103 Stu/hr '. Density = 62.4 lbg/ft3 1 av = 3.41 x 106 Stu/hr
' Density = 1 ge/c# ,
lin = 2.54 cm Heat of vaporization = 970 Stu/lem *F = 9/5'C + 32 , Heat of fusion = 144 Stu/lbe *C = 5/9 (*F-32)
- 1 Atm = 14.7 psi = 29.9 in. H BTU = 778 ft-lbf 1 ft. H 2O = 0.4335 lbf/i __...__ _ _ _ ___.__ _ ____ ___ _ .
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. CNSWERS -- WORCESTER POLY. INSTITUTE -85/11/05-SILK, *
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. CNSWER H.01 (3.00)
K-eff Without source With source
<1 e b 1 b a >1 e d (0.5 pts each)
REFERENCE Introduction to Nuclear Engineering' Ps 245-256, J R Lamarsh ANSWER H.02 (2.00) A(T1) = Ao e^- XT1 A(T2) = Ao e^-AT2 A(T1)/A(T2) = e^- AT1 e^h T2 In(A((1)/A(T2)) = h (T2-T1) Half-life = (.693(T2-T1))/(In(A(T1)/A(T2))) REFERENCE Introduction to Nuclear Engineering, pg 21 22, J R Lamarsh ANSWER H.03 (3.00) An increase in temperature or voids in the core would add positive react-ivity to the core. Power would increase thus raising the temperature and creating more voids which would then add more positive reactivity to the core and the power would continue to increase uncontrollabl If the temperature dropped and voids deminished, negative reactivity would be add-od to the core and power would decrease. A drop in power would lower temp-orature and further dominish the voids resulting again in a negative reactivity addition. This would continue until the reactor was shutdow REFERENCE Introduction to Nuclear Engineering, chapter 7 pg. 273,274,281,282; Lamarsh
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6 PAGE 15 __________________ , CNSWERS -- WORCESTER POLY. INSTITUTE -85/11/05-SILK, D.
, ANSWER H.04 (3.00) P = Po e^t/T P/Po = 2 = e^t/T
.693 = t/T T = 50.5 see T= (j9 - /0 ) /h/*
ja = /P/(T)g+ 1) = 0.00129 delta-k/k = 20 cents REFERENCE Introduction to Nuclear Engineering, pg 245-256, J R Lamarsh Equation Sheet ANSWER H.05 (3.00) Conduction through the fuel C:nducti r : r::: the :r Conduction through the cladding Natural convection away from the core (1 C)(27105 kg)(4.18 kJ/ks-C)(1.055 BTU /kJ)(1 KW/3410 BTU /hr)(1/10 KW)
= 3.5 hrs REFERENCE Introduction to Nuclear Engineering, chapter 8, J R Lamarsh ANSWER H.06 (2.00)
The lead plate will act as a reflector and cause neutrons to diffuse back into the core thus increasing the neutron population causing power to increas REFERENCE Introduction to Nuclear Engineering, pg 220 221, J R Lamarsh ANSWER H.07 (2.00) The thermal neutron flux increases since more thermal neutrons are required l to produce the same number of fissions at the end of life due to the in-creased absorption by fission product , ws td3LiswwnAaASfv (AJdis LG __________________
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-REFERENCE , Introduction to Nuclear Engineering, section 7.5, J R Lamarsh ANSWER H.08 (2.00)
cr1/cr2 = (1-Keff2)/(1-Keff1) 100/150 = (1-Keff2)/(1 .95) ' 1-Keff2 = 10/15 x .05 Keff2 = .967 (1.0) Change in reactivity = (1-Keff2/Keff2) - (1-Keff1/Keff1)
= (Keff2 - Keff1)/Keffi x Keff2 ' = (0.967 - .95)/.95 x .967 = 1.85% de}ta-k/k (1.0)
REFERENCE Equation Sheet
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. ,NSWERS A -- WORCESTER POLY. INSTITUTE -85/11/05-SILK, .'
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. ANSWER I.01 (4.00)
c. Container will be surveyed with an appropriate low range radiation non-itor (0.5) Wipe test the outside of the container and count the wipe sample before openin3 the container (0.5) Open container and wipe test inner containers (0.5) Container will be opened on a protective absorbant paper-covered table under the supervision of the radiolo3i cal safety officer and/or the facility director (0.5) Protective gloves shall be used (0.5) mR/hr (0.5) Notify NRC Regional Office, final delivering carrier, RHSC (Radiation, Health, and Safeguards Committee), and the manufacturer (.25 pts each) REFERENCE Procedures pg. 27, 10 CFR 20.205 ANSWER I.02 (2.00) c. Film badge and/or pencil-type dosimeters b. Beam port shield, thermal column face, domineralizer, and hold-up tank REFERENCE FSAR pg. 32
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Cif.SWER I.03 (4.00) (N-18) = 5(23-18) = 25 25 - 24 = 1.0 Rem = Man. Dose (1.0) Ma tt . Dose = Dose Rate X Time 1.0 Rem = 0.003 Rem /hr X 8 hr/ day X No. of Days No. of Days = 41.6 Days (1.0) Provided that (1) He does not exceed 3 Rem per quarter (.66)
(2) His radiation history is known and recorded on the proper form (NRC Form 4) (.67) (3) The dose received when added to his radiation history does not exceed 5(N-18) Rems where N = the person's age at his last birtyday (.67)
REFERENCE 10 CFR 20.101 ANSWER I.04 (2.00) dX (r)^2 = D X (R)^2 1 mR/hr X (10)^2 = D X (1)^2 0 = 100 mR/hr (1.0) Beta Dose = 120 mR/hr - 100 mR/hr
= 20 mR/hr Beta to Gamma ratio = 20/100 = 1/5 (1.0)
REFERENCE Introduction to Nuclear Engineering, Chapter 9 pg 409, 4108 J R Lamarsh AN!nCR I.05 (3.00)
.. No (0.5). A Rem dose accounts for the type and energy of radiation (1.0). Yes (0.5). Internal dose depends on biological and physical half-life, referred organ, type of radiation (1.0).
! l
- . - - , - . , - - - . -- - - . _ .- -.n..- . - . - --,a RADI0 ACTIVE NATERIALS HOEDLICG DISPOSAL AND HAZARDS PAGE 19 . ' ANSWERS -- WORCESTER POLY. INSTITUTE -85/11/05-SILK, *
. REFERENCE
.
Introduction to Nuclear Engineering, Chapter 98 J R Lamarsh ANSWER I.06 (3.00) I = Io e { - u :-: } 100 mR/hr = Io e{-0.035 cm^-1 X 100 cm> Io = 3311 mR (1.0) I = Io 10{-x/TVL} (TVL is Tenth Thickness) Io = I 10{x/TVL} = 63.25 mR/hr (1.0) Io = Ii e{-(.693/ half-life)t> (where Ii is initial contact dose) t = -(half-life /.693) In(Io/Ii) t = -(30 min /.693) In(63.25/2000) = 149.5 minutes (1.0) REFERENCE Introduction to Nuclear Engineering, pgs 22,83; J R Lamarsh ANSWER I.07 (2.00) Ar-41 is produced in the Beam Port when Ar-40 in the air becomes irradiated by neutron REFERENCE Procedures pg 42 43
Jo SPECIFIC OPERATING CHARACTERISTICS PAGE 20
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.- ANSWERS -- WORCESTER POLY. INSTITUTE -85/11/05-SILK, Do ..' - ANSWER J.01 (1.00) The ventilation system will quickly and safely dilute and discharge a volatile isotope at a negligible concentratio REFERENCE FSAR pgs 15, 16 ANSWER J.02 (3.00) During a 7 second delay period subsequent to reactor startup With the los CRM count below 50/see If the regulating blade is withdrawn from its lowest position If the fluit rises above a preset level before the safety blades are completely withdrawn If the reactor is in the scram condition (0.6 pts each) REFERENCE FSAR pg 24 ANSWER J.03 (3.00) A CIC consists of two chambers - one chamber is neutron and gamma sensitive while the other is just gamma sensitive. Each chamber is attached to a voltage source of a different polarity. The currents created from ionization within each chamber are then added to give a total current equivalent to that caused by neutron ionizatio (2.0) The indicated level of neutrons would be higher than the actual. (1.0) REFERENCE FSAR pg 23
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c;. (PQGE 21
- --------------------. --..------------- , 'CNSWERS -- WORCESTER POLY. INSTITUTE -85/11/05-SILK, .
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, . CNSWER J.04 (3.00)
The water in the control blade gaps wi11 not be heated to the same temp-
'
erature as the water flowing through the fuel element. The cooler the moderator the denser it will be, making for better moderation of neutrons which will have a positive reactivity effec REFERENCE * FSAR pg 29 ANSWER J.05 (3.00)
. ., The peak is due to the thermalization of fast neutrons escaping from the core. These thermalized neutrons are not absorbed as quickly in the water as neutrons thermalizing in the core because water has a much smaller absorption' cross sectio (2.5) Increase (0.5) *
REFERENCE WPI Figure 6, Introduction to Nuclear Engineerin3' PS 220-221, J R Lamarsh ANSWER J.06 (3.00) FSAR Figure 21
.
REFERENCE -
-
FSAR Figure 21 ANSWER J.07 '(1.00) When the release of the contained materials could cause corrosive attack to the facility or excessive contamination of the pool wate REFERENCE T.S. 2.3.'5 pg 4
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PAGE 22 T~~~~~~~~~~~~~~~~~~~~~~~~>~~~~~~~~~~~~~
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ANSWERS -- WORCESTER POLY. INSTITUTE -85/11/05-SILK, s
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' - ANSWER J.08 (1.00) ,
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To prevent radiation damage to the counter REFERENCE FSAR 4.3.0 Ps 24 - ,
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L PAGE 23 , ANSWhRS--WORCESTERPblY. INSTkTUTk-85/11/05-SILK, . ..' , ANSWER K.01 ( .50) 0.5% delta k/k (haximum Excess Reactivi+") REFERENCE FSAR pg 18, Technical Specifications (T.S.) 2.1 pg 3 ANSWER K.02 ( .50) Tuo REFERENCE T.S. 5.9.1 pg 14 ANSWER K.03 (1.50) No (0.5). procedures for reloadin3 the last half of the core shall prescribe the loading of fuel nearest the grid box center first uith load-ing thereafter proceedin3 outward (1.0) REFERENCE T.S. 5.10 pg 14, Fuel Reloading Procedures pg 12, 13 ANSWER K.04 (1.50) Steam voids Core temperatur.e rise Buildup of fission product poison in the fuel (0.5 pts each) REFERENCE FSAR 7.4.2 pg 42 ANSWER K.05 (1.00) To achieve more efficient ultilization of fuel REFERENCE
*
, FSAR pg 17
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, UUL% ULUl%LG W10 LQTJs IPCMEEVEES PAGE 24 . _____________________________________
.
,CNSWERS -- WORCESTER POLYo INSTITUTE -85/11/05-SILKr .'
. ANSWER K.06 (1.00) The temperature coefficient of reactivity shall be more negative than-2X 10^-5 delta k/k The temperature limits shall be 100 and 60 degrees F respectively REFERENCE T.S. 2.1 pg 3, 4 ANSWER K.07 (1.00) All additional fuel elements not in the core shall be locked in place REFERENCE T.S. 5.9 pg 13 ANSWER K.08 (1.00) All fuel must be removed from the cor REFERENCE FSAR 6.3.2 ps 34 ANSWER K.09 (1.00) No (0.5) because of the geometric configuration of the storage racks (0.5) REFERENCE FSAR 6.3.3 pg 35
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. K- FUEL HANDLING AND CORE PARAMETERS PAGE 25 - -------------------------------------
. ANSWERS -- WORCESTER POLY. INSTITUTE -85/11/05-SILK, D.
. ANSWER K.10 (3.00) The core shall be unloaded to less than one-half the estimated critical mass All core e::periments shall be removed Multiplication information with all blades fully withdrawn shall be in-corporated in a reciprocal multiplication curve and a new value of criti-cal mass extrapolated The fuel mass in each loading step shall not be more than one-half the difference between loaded and extrapolated critical fuel mass until such difference is less than a single standard element Blades shall not be more than 50% withdrawn durin3 the actual loading of fuel into the core Test if excess reactivity is within specification (0.5 pts each) REFERENCE T.S. 5.10.3 pg 14 ANSWER K.11 (3.00) Three persons One shall b'e a licensed senior operator and a licensed operator One licensed operater must be at the console and one must be in the bridge area before fuel removal may begin Staff members will continuously monitor the operations using the appropriate radiation monitoring and core nuclear instrumentation REFERENCE T.S. 5.9 pg 14, Fuel Unloading Procedures pg 11 m
.
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. ,--- .........----------------------- , , ANSWERS -- WORCESTER POLY. INSTITUTE -85/11/05-SILKr *
,
- , ANSWER K.12 (3.00) degrees F for aluminum (0.5) ' The loss of water moderator would shut the reactor down (.75', and the rate of inte nal heat generation would rapidly decay to a small fract-ion of the calculated safe 5 kw limit (.75). Natural convection of air through and around the core (1.0)
REFERENCE
,
FSAR 7.2.4 pg 40 V e
, - -
t3 . . LQQEVDV8 LOW pAGE 27
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, , ANSWERS -- WORCESTER POLY. INSTITUTE -85/11/05-SILK, . ..
. ANSWER L.01 (1.50) Radiation, Health and Safeguards Committee (RHSC) (0.5) Adequate safeguard provisions must be made before final approval is given by the Facility Directo (1.0)
REFERENCE FSAR 6.3.4 pg 35 ANSWER L.02 (2.50) Verify that the building is under svar . Procure a portable radiation monitor from its storage place in the Sercurity Police Offic . Check individuals who have reported personal contamination and instruct them on decontamination procedure Check buildings as may be Judged appropriat . Ascertain the radiation levels at the reactor facility building and entrance, continuing into the reactor site as the radiation level permit . Isolate reactor and/or building area with police assistance if it is ascertained that a radiation hazard exists. Check reactor walls and doors for leakage and seal if necessary, post the area, and notify the NR (0.5 pts each) REFERENCE FSAR 6.5.4 pg 38 ANSWER L.03 (1.50) Two members of the facility staff at least one of whom shall be a licensed senior operato RHSC l
. L .- CLMEUUVLOVLCL( M - ,------------------------------,------------------------- . ,
ANSWERS -- WORCESTER POLY. INSTITUTE -85/11/05-SILKr REFERENCE
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T.S. 5.5 pg 12 ANSWER L.04 (1.50) Security Office Radiological Safety Officer (RS0) At least one member of the RHSC REFERENCE Emergency Plan (EP) 4.4 pg 6, 7 ANSWER L.05 (1.50) Open the master powc? switch to the reactor Turn room ventilation on in case of a spill and off in case of a fire Leave the reactor area, closing the automatically locking door behind him REFERENCE EP 4.4 pg 7 ANSWER L.06 (1.50) HRC WPI Public Relations American Nuclear Insurers Chairman, RHSC Radiological Safety Officer Campus Security (0.25 pts each) REFERENCE EP Appendix A ANSWER L.07 (1.00) When that channel or instrument is installed, energized, and in all other respects performing the monitoring and safety functions for which it was intended.
i
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z -- Lw, - (PAGE 29
.j , , ANSWERS -- WORCESTER POLY. INSTITUTE -85/11/05-SILK, ~
REFERENCE
, T.S. 1.0 pg 1
.
ANSWER L.08 (1.00) If he/sha ic within a reasonable driving time (half hour) from the reactor and the licensed operator is informed of where he/she may be contacte REFERENCE T.S. 1.0 PS 2 ANSWER L.09 - (1.00) WPI Security Office, located in Stratton Hall Authorized members of the RHSC REFERENCE EP 5.1 pg 7 Evacuation Procedures P3 9 ANSWER L.10 (1.00) Notify the NRC within 15 days after the occurrence of the disabilit REFERENCE
'
10 CFR 55.41
- .
ANSWER L.11 (2.00) The two safety channels, the log-N period channel, the console annunciator system Area radiation monitoring system and the pool water level switch Excess reactivity, console instrumentation calibration, pool water pH, and conductivity and pH devices calibrated Control blades inspectpd, blade drives lubricated, blade drop times,
-
and magnet release times (any two per response, .25 pts each)
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i (5. , GB) LQQlftfRVMLCl2 PAGE 30 _________________________________________________________
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ANSWERS -- WORCESTER POLY. INSTITUTE -85/11/05-SILK, .
REFERENCE
. T.S. 3.1 ps 6 ANSWER L.12 (4.00) .- N If the radiation level 1 meter above the pocl surfsce we3 3reater than 50 mR/hr (1.0) Yes (0.5) N If the safety setting is less conservative (1.0) Yes (0.5) N If staffin3 requirements are not satisfied (1.0)
REFERENCE T.S. pg 2
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