IR 05000184/1986002
| ML20214G787 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 10/30/1986 |
| From: | Coe D, Keller R, Kister H, Kolonauski L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20214G767 | List: |
| References | |
| 50-184-86-02, 50-184-86-2, NUDOCS 8611260188 | |
| Download: ML20214G787 (37) | |
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{{#Wiki_filter:w . U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N (0L) FACILITY DOCKET NO. 50-184 FACILITY LICENSE NO. TR-5 LICENSEE: U.S. Department of Commerce National Bureau of Standards Reactor Radiation Division Washington, FACILITY: U.S. Department of Commerce National Bureau of Standards EXAMINATION DATES: October 1-2, 1986 CHIEF EXAMINER: ,EM lC0(CrnaAAakg l 0 /30/ F6 _
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Lyn:JKolonauski,ReactorEngineer Date (Examiner) REVIEWED BY: /M - /o[se!F Dou las Co , ; Examiner Date
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REVIEWED BY: /0/ 3c7&6 Robert Keller, Chief, Projects Section 1C Date APPROVED BY: Lt / 8d N Hdrry KistbChief, Projects Branch 1 Dath I / SUMMARY: Operator Licensing examinations were administered at NBS on October 1-2, 1986. Two Senior Operator candidates were examined. Both candidates passed all portions of the examination PDR ADOCK 05000184 V PDR
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. REPORT DETAILS TYPE OF EXAMS: Replacement EXAM RESULTS: l SR0 l l Pass / Fail l l l l l l l Written Exam l 2/0 l l _l i I ~ I I l Oral Exam l 2/0 l l l 1 ' 1 I I l0verall i 2/0 l l l l CHIEF EXAMINER AT SITE: Douglas Coe OTHER EXAMINERS: Lynn Kolonauski ' Summary of generic strengths or deficiencies noted on oral exams: The candidates were well trained in the use of the NBSR Technical Speciff-cations and the Emergency Pla . Comments on availability of, and candidate familiarization with plant reference material in the control room: Plant reference material was readily available for use during the operating examination; both candidates were practiced in its us . Comments on availability of, and candidate familiarization with design, procedure, and T. S. changes, and with LERs and recent significant event The candidates were adequately familiar with changes in plant design and operating procedure . Personnel Fresent at Exit Interview: NRC Personnel Douglas Coe, Lead Reactor Engineer (Examiner), NRC Region I Lynn Kolonauski, Reactor Engineer (Examiner), NRC Region I
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Facility Personnel Tawfik Raby, Reactor Supervisor 7. Summary of NRC Comments made at exit interview: The NBSR Technical Specifications, the Emergency Instructions, and the Health Physics, Administrative, and System Operating Procedures comprised the only current information supplied to the NRC for preparation of the examination The copy of the NBSR FSAR sent as part of the facility reference material did not include any information about the many modifications made to the facilit The examiner requested that in the future more reference material including applicable Reactor Theory, the NBSR Alarm Response Procedures, and current systems descriptions be sent to the examiners for use in preparing NBSR Operator Licensing examiration . Summary of facility comments and commitments made at exit interview: Dr. Raby apologized for the lack of current systems descriptions and other reference material available for the NBS facility. He stated that he had plans to develop up-to-date' system descriptions for the NBS facil-it . The following list represents significant changes made to the written examination as a result of the comments submitted by Dr. Raby on October 2, 1986. The examiners left the facility with no unresolved comment . CHANGES MADE TO WRITTEN EXAM DURING EXAMINATION REVIEW: Question N Change Reason H.05 If the worth of the Reg Rd NBS does not take is removed from the calculation credit for the of SDM, the result is still a worth of the Reg correct and more conservative Rod in calculating answe SD H.07b Credit should be given if the Density of D20 not density of either H2O (given on given on the exam the exam) or D20 is use H.08 Question should be dropped The class was not from the examinatio trained to use pump curve _
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H.10 Correct answer should be: Answer on key is increased fast and thermal incorrect for a leakag heavy water reactor with highly enriched fue I.05c An alarm is not received in The reference the Health Physics Office, contained this erro I.07b The internal damage caused Ar-41 is a noble by Ar-41 is inconsequential, gas; it does not stay in the body for any appreciable amount of tim I.08a 2.5 mrem /hr may also be use A Radiation Area may also be defined as 100 mrem /hr in one (40 hour) week, J.01 The inner reserve tank also Additional correct drain answer J.08b Answer should state "I of 3", The referenced OI instead of "2 of 3". contained this erro K.03a An increase in activity Additional correct indicated on RD 3-4 and/or answers an increase in conductivity could also indicate a fuel cladding lea Attachments: 1. Written Examination and Answer Key (SRO)
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. U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: N _- BUREAU OF STANDARDS
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REACTOR TYPE: _ TEST ____ _______ DATE ADMINISTERED: ---_/10/01 86 _ __ EXAMINER: _KQLQNAugKIz __ CANDIDATE: __ _ __ INST - ------------
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Uo 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 grzde requires at least 70% in each category. Examination papers will bm picked up six (6) hours after the examination start % O'F CATEGORY % OF CANDIDATE'S CATEGORY VALUE _TO_TAL_ _ -- V ----- -- - _ _ _ S_ C O R_ E-- _----_A_LUE CATEGORY ! )C \7. SD _1?.00 19.00 __ REACTOR THEORY _31:29__ _21 99 ___________ ________ RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS _Z1z99__ _Z1199 _ ____ ________ SPECIFIC OPERATING CHARACTERISTICS _19 90_ __19.00 ___________ __ FUEL HANDLING AhD CORE PARAMETERS 12199_- _121@9 _________ ________ ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS 9F.TD 4GG,49 Totals Final Grade All work done on this examination is my ow I have neither given nor received ai ' -- - Candidate s Signature
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS
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During the administration of this examination the f ollowing rules apply: > Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . Restroom trips are to be limited and only one candidate at a time may leav You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheatin . Use black ink or dark pencil gnly to facilitate legible reproduction . Print your name in the blank provided on 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 tection of the answer shee Consecutively number each answer sheet, write "End of Category __" as rppropriate, start each category on a new page, write gnly gn gne side of the paper, and write "Last Page" on the last answer shee . Number each answer as to category and number, for example, 1.4, . Skip at least three lines between each answe . Separate answer sheets from pad and place finished answer sheets face down on your desk or tabl . Use abbreviations only if they are commonly used in facility literatur . The point value for cach question is indicated in parentheses after the question and can be used as a guide for the depth of answer require . Show all 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 BLANK.
! 16. If parts of the examination are not clear as to intent, ask questions of the examiner onl . You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examinatio This must be done after the examination has been complete !
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c. Assemble your examination as follows:
(1) Exam questions on to (2) Exam aids - figures, tables, et (3) Answer pages including figures which are part of the answe b. Turn in your copy of the examination and all pages used to answer the examination question c. Turn in all scrap paper and the balance of the paper that you did not use for answering the question d. Leave the examination area, as defined by the examine If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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H._ REACTOR THEORY PAGE 2
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QUESTION f.01 (2.50) With the rods fully inserted, Keff = 0.5. If the shim rods are (2.5) pulled 10 degrees, $5 of reactivity is adde By what factor will count rate increase? Show all wor QUESTION pf. 02 (2.00) If NBSR power level increases from 10W to I kW in 250 seconds, (2.0) uhat was the doubling time? Assume a positive step change in reactivit QUESTION /.03 (1.00) , What is the principal source of heat in the NBS reactor siter (1.0) shutdown? QUESTION H.04 (1.50) List three (3) factors that can affect the estimated shim arm (1.5) critical position at NBS . QUESTION W.05 (1.00) Estimate the shutdown margin of a fully loaded NBSR core using the (1.0) following dat Total worth of all 4 shim arms $32.00 Worth of a single shim arm 8.00 l Worth of regulating rod 0.80 l Total excess reactivity 10.00 l QUESTION H.06 (2.00) l N me the principal source of neutrons in the shutdown NBSR, and (2.0) give the primary reason for the importance of this source.
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l QUESTION S.07 (3.00) For the Main Heat Exchanger HE-1, calculate: a. the outlet temperature of the secondary light water, and (1.5) b. the outlet temperature of the primary coolan (1.5) Given: 5 (tubeside) = 5100 gpm m (shellside) = 4950 gpm Cp = 1 BTU /lbm-deg F HX duty = 34.6 million BTU /hr Operating temperatures at design flow- D20 in = 112 deg F Secondary Cooling in = B4 deg F
.QUE TION N'. OB (1.50) .
Gi v p' Figure 1, the Primary Pump Performance Curves (f or a single pump), cal, late the hydraulic power for a primary pump operating at its rpted capacity of 1955 gp ,
$H f W W [iX \0NN QUESTION y'. 09 (2.50)
Using the f ollowing inf ormation, Plot a 1/M curve. Be sure to label the axe (1.0) Is it a safe or unsafe curve? Explain your answe (1.0) If Keff at point 4 is O.9, what was Keff at point 2? (0.5)
-Point- -Elements- -Count Rate-
' 1 0 10 ! 2 5 20 l 3 10 50 l 4 20 100 QUESTION d.10 (2.00)
.The NBSR core has a large negative temperature coefficient of (2.0)
reactivity. List two factors that contribute to the presence of ) this coefficient and explain how each causes an insertion of negative reactivity when power increase (***** END OF CATEGORY H *****) l '
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QUESTION f. O l (2.00) On your answer sheet, draw and fill in the following table concerning (2.0) VOLUNTARY EXPOSURE LIMIl5 at the NBSR facilit : With prior approval : Without prior approval Situation I of the Emergency : of the Emergency
: Director : Director
__________- -_;- _ _ _ _ _ _________;_________ == _- __ 1. Lifesaving i 2. Other serious : Event : : QUESTION j f.02 (2.00) If the dose rate from a fixed gamma source is 5 rem /hr at a (2.0) distance of 10 feet, what will the dose rate be 90 minutes later at a distance of 20 feet? The half life of the gamma source is I hour. Show your calculations.
- QUESTION 7 03 (1.50) List the maximum permissible personnel exposures (in rem /qtr) ( 1. 0) as given in 10 CFR 20 for whole body, extremities, and skin of whole body, b. HP Procedure 2.1, " Radiation Exposure Limits" states that the (0.5) NBSR local limits established for planned exposure doses may be exceeded if approval is obtained from either the Health Physics section or the Reactor Supervisor. State these limits for daily and weekly whole body exposure for personnel employed at NBS QUESTION 7 04 (2.00) Calculate the dose rate in an area located six feet from a 500 (2.0) gillicurie source which emits gammas with an average energy of 1.2 Me (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
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QUESTION F{ OS (2.00) Answer the following questions concerning the Area Radiation Monitors RD-1 through RD-10.
! a. What type of detector is employed? (0.5) ' b. What type of radiation is measured by these detectors? (0.5) c. If measured dose rates exceeded the levels preset for each (O.5) indicator, at what locations would alarms be received? d. Briefly explain the procedure for verifying the operability of (0.5) the alarm system for an Area Radiation Monito QUESTION J'. 06 (2.00) What action would you take in response to each of the following events? n. While frisk 2 ig your feet at the Restricted Area Exit, you set off (1.0) the monitor's alar b. While working with contaminated material, a sharp edge cuts your (1.0) hand. Which should take precedence: decontamination or medical care? QUESTION f.07 (3.00) a. Explain how Ar-41 and N-16 are formed at the NBSR facilit (2.0) b. How do the radiological hazards caused by each differ? (1.0) QUESTION jf. 08 (1.50) A spent fuel element is removed from the poo a. If you determine that the radiation dose rate at 10 feet is (1.0) 10 n.r/hr, at what distance from the source would you post a " Radiation Area" (as defined by 10 CFR 20) sign? l b. At what dose level must an area be declared a "High Radiation (0.5) Area" according to 10 CFR 2O? l ! i (***** CATEGORY I CONTINUED ON NEXT PAGE *****) i
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QUESTION f.09 e. What types of materials would you use to shield against gammas? (0.5) Why do these materials work weMP.? b. What types of materials would you use to sheild against neutrons? (0.5) Why do these materials work well? QUESTION I . L6 (2.00) a. How is Tritium formed at the NBS facility? (0.5) b. What type of radiation hazard does Tritium present? (0.5) c. The half life of Tritium is 12.3 years; the biological half life (1.0) is about twelve days. Explain the difference between half life and biological half lif QUESTION f.11 (1.00) Nrme two locations where emergency survey and decontamination (1.0) squipment may be foun QUESTION J'.12 (1.50) How much material is required to reduce the intensity of 1 MeV (1.5) grmmas from 8 x 10 exp5 MeV/cm2-sec to 1 MeV/cm2-sec? Do not consider buildu Given: for 1 MeV gammas in this " material", the tenth value thickness = 1.15 inches the half value thickness = 0.33 inches (***** END OF CATEGORY I *****)
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. QUESTION [. 01 (1.50) In the event of a D20 system rupture, what three automatic actions (1.0)
(ie. plant component and/or system response) would you expect to occur?
QUESTION J.02 (3.00) e. Give two functions of the Helium Sweep syste (1.0) b. List the five major components swept with Heliu (1.0) c. The NBSR Technical Specifications limit the D2 concentration in (1.0) the Helium Sweep System to no greater than 4*/. by vol ume. State the basis for this requiremen QUESTION
[.03 (1.50)
List the three reactor shutdown mechanisms available at NBSR, and (1.5) give the Tech Spec definition for eac QUESTION /.04 (3.00) The NBS reactor is operating at full power. For the following situations, state whether a positive, negative, or no reactivity change occurs, AND give the automatic control system action, if an e. A small sample of U 235 is inserted into the core through the (1.5) rabbit syste The secondary water leaks into the primary coolan (1.5)
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J.__ SPECIFIC OPERATING _ CHARACTERISTICS PAGE 8
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QUESTION 7 05 (3.00) y
~9 1 Arsume the reactor is at full power in the 2 of JI Scram mod (3.0) l Mstch each of the following annunciators with the appropriate '
cutomatic action (if any) that occurs as a result of the annunciato ,
- Annunciator - - Automatic Action -
Hi Diff Temp Hi Reactor Outlet Temp a. Major Scram Nuclear Instr Power Off b. Scram Low Flow 14" Inlet c. Rundown
~[[ Irradiated Air Hi Activity
_ d. No Automatic Action ___ Thermal Shield Low Flow (NOTE: FIGURE 2 ILLUSTRATES ANNUNCIATOR PANEL NUMBER 4.)
QUESTION ).06 (2.00) What two automatic actions will occur if, after power is lost (1.0) on the emergency motor control center 480 volt bus, the "A" diesel generator fails to start after four (4) attempts? Under what condition would the diesel generator automatically (1.0) supply power to the Emergency Power system? QUESTION J.07 (3.00) Ruactor control will revert back to manual from automatic control (3.0) when certain specific conditions are present. Describe three of these condition QUESTION ,J.08 (1.50) Answer the following questions in accordance with DI 5.4, " Operation of the Nuclear Instrumentation System".
e.-Why is it inadvisable to put the reactor on automatic control (0.75) below 100 KW? In the event that one power channel or associated trip becomes (0.75) inoperative while at power, the reactor may continue to operate under certain conditions. State thesa condition (***** CATEGORY J CONTINUED ON NEXT PAGE *****)
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QUESTION j f. <09 (2.50) e. Explain the plant system and component response if high radiation (1.0) is sensed in the air exhausted from the containment buildin b. What is the purpose of the charcoal filters in the Emergency (0. 5) Exhaust system? c. Explain the purpose and operation of the two subsystems which (1.0) comprise the Emergency Ventilation system.
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QUESTION K.01 (2.50' e. As the SRO on shift at NBSR, what four (4) immediate actions (2.0) should you take if fuel element damage has been visually verified in the Storage Pool? The NBS reactor has just been shutdown for refueling after a (0.5) run in which the highest sustained power level was 10 MW. How soon can irradiated fuel be moved from the reactor vessel to the storage pool? Where is this inf ormation located? QUESTION /. 02 (2.00) What two immediate actions would you ts!ce if a Local Area Radiation (2.0) Monitor alarms while you are touring tie area? QUESTION /I.03 (2.00) e. Ei.ve the two most likely means of detecting fuel element damage (1.0) in the core. State which will give the first indicatio If severe fuel damage is suspected, what two operator actions (1.0) should be taken immediately? QUESTION pf. 04 (2.00) Assume that fuel .novements are being made within the core are (2.0) For this situation, state the minimum NBSR staffing requirements for operations and support personne Where applicable, indicate the type of NRC license that must be held and the duty station to which tha individual is assigne QUESTION [.05 (2.00) T.S. 3.8, " Fuel Handling Within Reactor Vessel" states that, (2.0)
"Following fuel handling within the reactor vessel, the reactor shall not be operated until all fuel elements that have been moved are inspected to determine that they ere locked in their proper position in the core grid structure."
l Explain the two inspection methods that may be employe (8**** CATEGORY K CONTINUED ON NEXT PAGE *****) 1 . - . - . _ _ _ _ . _ . . - _ _ - _ _ , _ _ _ _ - . _ _ _ _ _ _ _ , _ _ - . _ _
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. DUESTION F( O6 (1.50) TS 3.4 states that the reactor shall not be operated if the (1,0) reactivity insertion rate using all four shim arms exceeds 5.0 x 10 exp(-4) op/se What is the basis behind this requirement? b. What is the Technical Specification limit for the maximum amount (0.5) of excess reactivity for the NBSR core at normal operating temperatures? . QUESTION ,k'. 07 (2.00) How is water purity maintained in the Spent Fuel Pool Cooling (1.0) System? How is the water level controlled in the Spent Fuel Pool? (1.0) QUESTION (. 08 (1.50) Describe two separate methods of providing auxiliary cooling to a (1.5) fuel element that is stuck in the Transfer' Chut QUESTION K.Od (1.00) Explain why the delayed neutron fraction at your facility is higher (1.0) than for most other water moderated reactor QUESTION K.16 (2.50) Azsume that the NBS reactor is operating at full power in automatic (2.5) control and has been for several days. The position of the Regulating Rod is 26.0 inche After an experimenter inserts a sample in a vertical thimble, the Regulating Rod is at 21.0 inche . If this total worth of the remaining experiments in the reactor have o total worth of 27.4p, have any violations of the NBSR Technical Specifications occurred? Figure 3 contains NBSR Technical Specificatica 4.0, " Experiments".
Also, current NBSR rod worth curves are attached for your us Em sure to explain your answer and show all work and calculation (***** END OF CATEGORY K *****)
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l DUESTION [.01 (2.00) In the event of an emergency at NBSR, what TWO people may serve (1.0) as the Emergency Director until relinved by a higher authority within the Emergency Organization? The Reactor Control Room is the initial location for Emergency (1.0) Control. If the Control Room must be evacuated, to where is Emergency Control moved? (Be specific.)
QUESTION jf. 02 (1.50) According to the NBSR Technical Specifications, the reactor is (1.5) defined to be shutdown if any of three specific conditions exis State each of these condition QUESTION fi. 03 (1.00) Why do the NBS Technical Specifications limit the absolute (1.0) reactivi ty value of any experiment in the reactor and the facility to 0.57.bp? QUESTION 4 04 (2.00) Assume the reactor is not being operated (i e. no control rods (1.0) withdrawn) but that the control power key is in the switch, and it is NOT locked in DFF. What is the minimum shift complement? What control room staffing requirements must be met during (1.0) startup? QUESTION %'. 05 (2.00) If the building evacuation siren is sculded, in the event of (0.5) a Site Area Emergency, where is the personnel assembly area? , Assume that you are on shift at NBSR when a control room evacuation l becomes necessar What THREE actions should be taken prior to control room (1.5) evacuation according to the control room evacuation procedure, l EI 3.2.4? l l
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QUESTION )L. 06 (3.00)
c. What is.the objective of establishing the NBS Safety Limits as (1.0) given in 2.1 of the NBS Technical Specifications? State two specific actions that must be taken in the event that (1.5) a Safety Limit is exceede TRUE or FALSE: If a Safety Limit is exceeded, reactor operation (O.5) is NOT to resume until authorized by the NR QUESTION j f. 07 (2.50)
' Define " Limiting Safety System Setting" as used in your (1.0) Technical Specification Give the three Limiting Safety System Trip Settings for reactor (1.5) operations at the NBS QUESTION y.08 (1.00) According to the NBSR Technical Specifications, c. What level of review and approval must a major procedure change (0.5) receive? b. What level of approval must a minor procedure change (i e. , one (0.5) that does not significantly change the intent of a procedure) receive? QUESTION L.09 (2.50) Answer the following questions as TRUE or FALS (2.5) If FALSE, explain WH a. The reactor shall not be operated unless both shutdown cooling pumps are operabl Reactor operation may continue if one of the Emergency Exhaust fans must be taken out of servic Only one diesel generator is required for reactor operatio (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
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- L.__ ADMINISTRATIVE _ PROCEDURES, CONDITIONS AND_ LIMITATIONS PAGE 14 . QUESTION L.10 (2.00) a. Explain the difference between white and red tags as used at NB (1.0) b. Who may issue red tags? (0.5) c. Who may give permission to operate equipment over a white tag? (0.5)
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ANSWERS -- NAT'L BUREAU OF STANDARDS -86/10/01-KOLONAUSKI, l . ANSWER H.01 (2.50) D21ta Reactivity = $5 * (beta /$1) =5 (0.008) = 0.04 = 4 (0.5) Delta Rho = (K2 - KI)/(K2*K1) -> O.04 = (K2 - O.5)/ O.5K2 (1.0) K2 = 0.510 CR2/CR1 = (1-K1)/(1-K7) = (1-0.5)/(1-0.51) = 0.5/O.49 = 1.02 (1.0) REFERENCE LeMarsh, " Introduction to Nuclear Engineering", page 252 NUS Corporation, NET, Module 3, pages 6.1-3, 12.1-3 ANSWER H.02 (2.00) t/T P = Po e (1.0) In(1000/10) = t/T T = 54.3 sec T (In 2) = t --> t=/37.6 sec (1.0)
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REFERENCE NUS, Nuclear Energy Training, Module 3, page 6.3-1 ANSWER H.03 (1.00) Decay of fission products (1.0) REFERENCE LEMarsh, pages 318-320 ANSWER H.04 (1.50) Moderator density (0.5) 2. Core age (0.5) 3. Concentration of neutron poisons (0.5)
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di__B{ggIOR THE001 PAGE 16 l dNSWERS -- NAT'L BUREAU OF STANDARDS -86/10/01-KOLONAUSK1, REFERENCE NUS, Nuclear Energy Training, Module 3, pages 9.5-1, 9.5-2 het p rb ANSWER H.05 (1.00) {dgfg k N Cktdi k & Total rod worth = 32.00 + Ordo = 32.80 32-M ,2hyc (1.0) SDM = 32.80 - 10.00 = 72.80 MO vt Cenit MVC-REFERENCE kfTT NUS Corporation, Nuclear Energy Training, Module 3, page 11.1-2 ANSWER H.06 (2.00) Photoneutrons from gamma interaction with D20 are the main source of (1.0) nxutrons in the shutdown NBS It will provide required initial indication on the monitoring channel . (1.0)
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REFERENCE NUS Corporation, Nuclear Energy Training, Module 2, pages 11.2-3, 11.3-2 ANSWER H.07 (3.00) 3 h MChy( uot of D = m Cp AT v ' dhir/. (1.5 each) Un(t f%d J c. 34,600,000 BTU /hr = 4950 gpm*1 BTU /lbm-F*(Tout-84)F88.345 lbm/ga1860 T out = 98 F b. 34,600,000 BTU /hr = 5100 gpm*1 BTU /lbm-F4(112-Tout)F*B.345360 T out = 98.5 F REFERENCE i General Electric, Heat Transfer and Fluid Flow Chapter 8 ' NBS FSAR Section ANSWER H.08 g Mechanical Efficiency = 0.85 = Po/ bhp (1.5) Po = 80 (0.85) - N O f f yt1 W ,
= 68 hp Clycyfrpyw Est l
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ANSWERS -- NAT'L BUREAU OF STANDARDS -86/10/01-KOLONAUSKI, REFERENCE , G:neral Electric HT and FF, page 7-87 l ANSWER H.09 (2.50) Point 1/M = Cs/Ct (1.0) 1.04 1 10/10 = 1 Cji 2 10/20 = Ct O.5: * 3 10/50 = : * 4 10/100 = O :-----------------*---- O 5 10 15 20 SAFE; these predictions are conservative because they under- (1.0) estimate the critical positio CR1/CR2 = (1-K2)/(1-K1) (0.5) 20/100 = (1-0.9)/(1-K1) K1 = REFERENCE NUS, Nuclear Energy Training, Module 3, Unit 12 ANSWER H.10 (2.00) , c,g g.g, pler Broadening- Increase in width of re=onance peaks' *
(1.0) '
g g More neutrons lost to resonance c pturu erator Density- As the moderator thermally exp nds, it becomes (1.0) a less effective moderator. Erc:ene neutre-na cread = ara + i - zi ti.m r==unance energies, m=ra raran'n-= e - + ur-e-escur- corrt4t 2. w weyr
> 3htvMLei fD.It eM MM lecd<. ==
REFERENT:C NUS Co poration, Nuclear Energy Training Module 2, pages 13.4-1, 16.2-3 Podule 3, page 8.3-2
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I.__RADIDACTIVE MATERIALS _ HANDLING _ DISPOSAL AND HAZARDS _ PAGE 18 ANSWERG -- NAT'l BUREAU OF STANDARDS -86/10/01-KOLONAUSKI, ANSWER I.01 (2.00) rem : 25 rem (0.5 each) rem : 5 rem REFERENCE El 1.5, page 5 ANSWER I.02 (2.00) A = Ao e* * (- A t) = Ao e* * (-0. 693/t ) (T1/2) (1.0) A = 5 rem /hr e * * (-0. 693/1 ) ( 1. 5) = 1.77 rem /hr at 90 min at 10 feet At 20 feet- D2 = D1 d1**2/d2**2 = 1.77 (100)/400 = 442 mrem /hr (1.0) REFERENCE LaMarsh, page 22 Fundamentals of Radiation Shielding ANSWER I.03 (1.50) .25 rem /qtr -W6 * 18.75 rem /qtr - exWC/mtMO 7.5 rem /qtr - Sk(n ef WB mrem / day, 300 mrem / week (0.5) REFERENCE HP 2.1, pages 1,2 ANSWER I.04 (2.00) R/hr = 6 CE/d**2 = 6 (0.5)(1.2)/36 = 0.1 R/hr = 100 mrem /hr (2.0) REFERENCE i Fundamentals of Radiation Shielding i _
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ANSWER I.05 (2.00) NOD (L h d N e. The detectors are/(halogen-qcenched) GM tube (0.5) b. The detectory/'are gamma sensitiv (0.5) c. Yrsaul ...d .udible alarms are energized at the detector, the (0.5) control room, and the ^==1+h anysi r-- of f i c d. The check source will be actuated from the control room. Local (0.5) alarms and the Area Monitor High' Radiation annunciator should come o REFERENCE DI 5.3,'page 2 M lhC0frtCY NHS FSAR Section 9. ANSWER I.06 (2.00) , s. Put on shoe covers, reset alarm, proceed to the change room or (1.0) to A-134, start decontamination procedures at once. Notify H b. Notify Health Physics. The wound should be allowed to bleed (1.0) freely and the area around the wound should be washed by stroking away from the wound. Decontamination shall not interfere or take precedence over proper medical car REFERENCE HP 2.10 l ANSWER I.07 (3.00) a. Both appear only during power operation. Ar-41 comes from neutron (2.0) activaticn of the Ar-40 present in air. N-16 comes from neutron i activation of the 0-16 found in the primary loop wate r MU #t it*7 TCMS d h g had / - I b. Ar-41 is a beta emitter; it c r ,ccunc ir.ternal _2_ gc if inhale (1.0) N-16 is a gamma emitter; 't represents whole body dos REFERENCE NBSR FSAR Section 1 NUS Nuclear Energy Training, Module 2, page 11.5-2 Ridiation Protection Fundamentals, HP ,
* - . . RADIOACTIVE _ MATERIALS HANDLING DISPOSAL _AND_ HAZARDS PAGE 20 ANSWERS -- NAT'L BUREAU"OF STANDARDS -86/lO/01-KOLONAUSKI, .
ANSWER 1.08 (1.50) e. R1 D1**2 = R2 D2**2 (1.0) D2882 = 10 (100)/5 = 200 D2 = 14.14 ft N1 M' of b-Radiation Area- 5 mrem /hr % (0 0 mh [hr- A y wcJ = 20 mw (clay b. Hi gh Radiation Area- 100 mrem /hr 40Wr av go,33 2.5mrjky REFERENCE 10 CFR 20.202 Fundamentals of Radiation Shielding ANSWER I.09 ,
(1.00) Concrete and lead are effective in shielding against gammas (0.5)
because of their high eensity and therefore high gamma inter-action rat b. Hydrogeneous materials (water, concrete) are used because of (0.b) their effectiveness in slowing down neutrons through elastic collision REFERENCE LaMarsh, " Introduction to Nuclear Engineering", page 449 NUS, Nuclear Energy Training Module 2, page 8.4-2 ANSWER I.10 (2.00) a. Tritium is formed by neutron activation of deuteriu (0.5) b. Tritium is a very weak beta emitter. Tritium is assimilated into (0.5) the body by respiration or absorbtion through the skin. The tritium oxide mixes with body water and reaches equillibrium i within a few hours and thus represents whole body radiation dos c. The half life is the amount of time it takes for radioactivity (1.0) to lose-half of its activity by decay. Biological half life is the amount of time it takes the body to lose half of the substance taken in through natural eliminatio REFERENCE Rrdiation Protection Fundamentals HP 3.8 >
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1.__ RADIOACTIVE MATERIALS HANDLING _DISPOgAL_AND' HAZARD @ PAGE 21 ANSWERS -- NAT'L BUREAU OF STANDARDS -86/10/01-KOLONAUSKI, . ANSWER I.11 (1.00) Front lobby locker and Emergency Control Station cabinet (1.0) REFERENCE El ANSWER I.12 (1.50) Five tenth value thicknesses will reduce the intensity from (0.5) 8x 10 exp5 MeV/cm2-sec to 8 MeV/cm2-sec. 5* 1.15" = 5.75" Three half value thicknesses will reduce the intensity from (0.5) 8 MeV/cm2-sec to 1 MeV/cm2-se * O.33" = 0.99" maWial TotalAyeed needed: 5.75" + 0.99" = 6.74 inches (0.5) REFERENCE NUS, Nuclear Energy Training, Module 2, Section 8.5 Basic Shielding
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PAGE 22 e kNSWERS -- NAT'L BUREAU OF STANDARDS -86/10/01-KOLONAUSKI, , ANSWER J.01 (1.50) 1. Re' actor scram on low level (0.5) 2. Main D20 pumps go off and associated discharge valves shu (0.5)
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3 Both D20 shutdown pumps go on and their discharge valves ope (3.5) 4 b & WkW M dro<Lcuint, a REFERENCE MQ1 EI 2.4, page 1 ANSWER J.02 (3.00) c. 1. Provides an inert He atmosphere over all vessels and tanks (1.0) which normally contain-heavy wate . It recombines any disassociated D2O which might be.present, and 3. maintains the proper oxygen concentration in the sweep ga (2 req'd) b. Reactor vessel, storage tank, emergency cooling tank, the thermal (1.0) column tank, the purge tan c. Damage to the primary system could occur if the deuterium gas (1.0) in the helium cover gas system were to reach an explosive concentratio REFERENCE NBS FSAR Section 7. NBS TS 3.2 Basis i ANSWER J.03 (1.50) l l ! 1. Rundown is the electrically driven insertion .?f all shim safety (0.5) arms and the regulating rod at their normal operating spee . Scram is the spring assisted gravity insertion of all shim (0.5) l safety arms.
! 3. Major scram is the spring assisted gravity insertion of all shim (0.5) i safety arms and automatic isolation of the confinement buildin REFERENCE NBS TS 1.8 , , ! l l l l
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- SfEg{FIC DPERATING CHARACTERISTICS PAGE 23 ANSWCRS -- NAT'L BUREAU OF STANDARDG -06/10/01-KOLONAUSKI, .
ANSWER J.04 (3.00) c. Positive reactivity addition- servo deviation, regulating rod (1.5) would be inserte b. Negative reactivity addition- servo deviation, regulating rod (1.5) would be withdraw REFERENCE TS 4.3.2, 4.6.10 ANSWER J.05 (3.00) b-c-d-b-a-c (0.5 each, 3.0) REFERENCE DI 5.7 and Check List, DI 1.1 Check List page 8 NBS FSAR 9. ANSWER J.06 (2.00) . The diesel engine trouble light will alar (0.5) 2. A start signal will be sent to the "B" diesel generato (O.5) If power from both substations faile (1.0) REFERENCE NBS FSAR 7.3.1.1, 7.3.1.2 . ANSWER J.07 (3.00) 1. Operation of the regulating rod manual control switch 2. The regulating rod exceeds the travel limits 3. The servo deviation exceeds 107. of the setpoint, indicating that
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the controller is unable to control the reacto . A rod rundown occurs through the de-energizing of K-107 5. A rod withdraw prohibit condition occurs (1.0 each, 3.0)
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kNSWERS -- NAT'L BUREAU OF STANDARDS -86/10/01-KOLONAUSK1, REFERENCE NHS FSAR 9.5. ANSWER J.08 (1.50) a. The resultant control action will be subject to noise and power (0.75) level may not be controlled to within 0.57. of leve b. Power operations may continue provided no major rod program (0.75) change is carried out and provided that the scram logic selector scram protection is set for,2'of sh M & kae m 1o0 3 , ( l of a > REFERENCE DI 5.4 - (wcewt.c.t yvtcf du.,s - ggirt.s yty(s(e -py lof C - ANSWER J.09 (2.50) a. A major scram signal is generated; the confinement building is (1.0) automatically isol ated, the emergency ventilation system is brought into operation, and the normal ventilation system is secure The charcoal filters absorb radioactive iodin (0.5) The first subsystem control in-leakage to the confinement (O.5) building by maintaining a negative pressure differential of one quarter inch of water across the building wal The second subsystem recirculates the air within the confinement (0.5) building through filters to remove radioactive contaminant REFERENCE NBS FSAR 3.6.2, 3.6.5- !
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Ki__ FUEL _ HANDLING AND CORE PARAMETERS _ __ PAGE 25 heNSWERS -- NAT'L BUREAU OF STANDARDS -86/10/01-KOLONAUSKI, ANSWER K.01 (2.50) . Notify the Reactor Supervisor and Health Physic (0.5) Suspend all movement of fuel element (0.5) Evacuate the Storage Pool Area and start radiation survey (0.5) 4. Monitor RD 3-5 (Normal Air) and RD 4-1 (Stack Exhaust) for (0.5) increase b. Ten hours after shutdown (0.5)
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REFERENCE El 2.5, page 1 DI 6.1 page 3, OI ANSWER K.02 (2.00) Evacuate the affected area and assist others in evacuatin (1.0) Notify Health Physics or the Control Room and await instruction (1.0) REFERENCE EI 3.2.1, page 1 le D 3 -4 413 d ~ (Ndia.kd. air - Em. Eh 4 sg ANSWER K.O3 (2.00) emd2xcyyg _ epc, . The fission product monitor usually gives the first (0.5) indication of a fuel cladding lea . Increase in RD 4-1 Stack Exhaust (to 1,000,000 cpm) (0.5) . Initiate a major scram, if one has not occurre (0.5) Declare an Alert. (Refer to Emergency Plan) (0.5) l REFERENCE ' EI 2.5, FSAR 9.7.3 ! I , l l
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h Q RUJT b Mw SYC0 ANSWER K.04- (2.00)
'tA A minimum shift complime of three actor personnel (0.25) including one Reactor Supervisor (0.25) who holds an NRC SRO license (0.25) shall bn present in the facility (0.25) during fuel movements in the core are An NRC licensed operator (0.25) shall be stationed in the Control Room (0.25) during fuel movements in the core are A representative of Health Physi cs (0.25) shall be present at the facility (0.25) during fuel transfer movement REFERENCE DI 6.2, pages 1-2 AR ANSWER K.05 (2.00) A periscope may be used for visual inspectio (1.0)
2. A pickup tool can be positioned at or near the top of each (1.0) element, one at a time. (Tests have shown that flow from a primary pump will raise an unlatched fuel element above its normal position and thus will be detected by the pickup tool.)
REFERENCE TS ANSWER K.06 (1.50) The Rod Withdrawal Accidents f or the NBSR were analyzed using a (1.0) maximum withdrawal rate of 5.0 x 10 exp (-4) A p/sec. These analyses showed that for the most severe accident the core is not expected to heat up to the point of fuel cladding failur p (0.5) REFERENCE TS 3.3, 3.4 !
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I i i l ANSWER , . 07 (2.00) a. The system maintains the pool water purity by circulating the (1.0) through an ion exchanger and cellulose fiber filter b. A level instrument senses the storage pool level and sends an (1.0) appropriate signal to valve WTV-1 which controls the makeup flow of demineralized water from the water treatment syste REFERENCE NBS FSAR 7. ANSWER K.OB (1.50) 1. If the element is above the bottom valve, the valve can be (0.75) closed and the chute flooded with water. (D20 or H2O) 2. D20, He, or H2O may be sprayed on the element in the fuel (0.75) transfer chamber if the bottom valve was blocked from closin ' REFERENCE NBSR FSAR Section 7.2. ANSWER K.09 (1.00) The D20 moderated reactor differs from other reactors in that the (1.0) number of effective neutron groups is augmented by those delayed nrutrons caused by photoneutron production in D2 REFERENCE NBS FSAR Section 4.6.12.2 l l e l l t l l
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i ANSWER K.10 (2.50) Using the integral rod worth curve for the Reg Rod: (1.0) 26" to 21" -> 754 - 62.54 = 12.5( added-12.5( * ($1/100() * (O. E7./ $ 1 ) = 0.1% op Worth of single experiment: O.1% dp (0.5) Total worth of all experiments: 2.0 + 0.1 = 2.1%op No, the TS limits for total reactivity worth of all experiments (1.0) in the reactor (2. 6% A p ) and for the worth of a single experiment (0.5%Ap) have not been exceede REFERENCE NBSR Technical Specifications, Sectiva 4.0 i l l l , I l
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ANSWER L.01 (2.00) c. The duty Reactor. Supervisor or in his absence, the SR (1.0) b. The Emergency Control Station in Rm A-22 of the (B-2) basement (1.0) under the office portion of the reactor building (Bldg 235).
REFERENCE EI 1.1, page 1; EI 1.2, page 2 El Figure ANSWER L.02 (1.50) The reactor shall be considered shutdown if any of the following (1.5) conditions exist: 1. The reactor contains less than 2.2 kg/U235 The reactor control power and the rod drive power key switches are locked in their OFF posiito . The reactor is in the rod drop test mode, and a senior licensed operator is in direct charge of the operatio REFERENCE TS ANSWER L.03 (1.00) This limit is chosen so that the failure of an experimental (1.0) installation or component will not cause a reactivity increase creater than that which can be controlled by the regulating ro REFERENCE NIS TS 4.0 Basis ANSWER L.04 (2.00) a. NRC licensed operator in control room and NRC licensed SRO (1.0) at facility l l l b. Two reactor personnel, one of whom is NRC licensed (1.0) l
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I l I REFERENCE AR ANSWER L.05 (2.00) In front of Building 235 (0.5) . Make provisions for shutdown cooling or emergency coolin (O.5) 2. Note Emergency Cooling Tank leve (0.5) 3. Connect emergency light water injection spool piec (O.5) REFERENCE El 4.2, 1.3, 3. ANSWER L.06 (3.00) c. The SL are established to maintain the integrity of the fuel (1.0) cladding and prevent the release of significant amounts of fission product . Shutdown the reacto (0.75) 2. The NRC shall be notified in accordance with TS (0.75)
(By telephone not later than the following working day and in writing within two weeks.)
c. TRUE (0.5) REFERENCE NBS TS 2.1, 7.5, ANSWER L.07 (2.50) ! e. Limiting Safety System Settings provide significant margin from (1.0) l the Safety Limits by initiating some type of protective action when reache b. Reactor Power- 130 (0.5) ! Reactor Outlet Temperature- 147 deg F (0.5) Coolant Flow- 60 gpm/MW fnner (0.5) 235 gnm/MW outer r
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ANSWERS -- NAT'L BUREAU OF STANDARDS -86/10/01-KOLONAUSKI, . REFERENCE TS ANSWER L.OB (1.00) c. Reviewed by the Saf ety Evaluation Comniittee (0.25) ' Approved by the Chief, Reactor Operations or his Deputy sO.25)
'b. Approved by the Chief, Reactor Operations or his Deputy (0.50)
REFERENCE TS ANSWER L.09 (2.50) e. False (0.25), only one shutdown cooling pump is required for reactor operations (0.75).
b. False (0.25), bot h Emergency Exhaust Fans are required to be operable during power operation (0.75).
c. True (0.5).
i REFERENCE NBS TS 3.2, 3.9, 3.10 ' ANSWER L.10 (2.00) ! a. A red tag is used only where harm may result to personnel or (0.5) equipment. A white tag is used to control unauthorized operation (0.5) of equipmen b. the Reactor Supervisor on duty (0.5) c. the Reactor Supervisor on duty (0.5) l REFERENCE AR 11.0 I L }}