IR 05000057/1987001
| ML20215K109 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 04/28/1987 |
| From: | Coe D, Collins S, Keller R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20215K082 | List: |
| References | |
| 50-057-87-01-OL, 50-57-87-1-OL, NUDOCS 8705110073 | |
| Download: ML20215K109 (31) | |
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ENCLOSURE 2 U.S. NUCLEAR REGULATORY COMMISSION
REGION I
REQUALIFICATION EVALUATION REPORT Evaluation Report N /87-01(0L) Facility Docket N Facility License No. R-77 Licensee: State University of New York at Buffalo Rotary Road Buffalo, New York 14214 Facility: Buffalo Materials Research Center Examination Dates: February 13, 1987 Chief Examiner -[ b D.Coe, Lead R f or Engineer 4!2Y!S7
' date Reviewed By R. Keller, Chief, Projects Section 1C 2.k6 date Approved by: )TnunO[O/]]/M 'S. J. Collins, Dep~uty Director 4/f8[87 date Division of Reactor Projects Summary: The NRC audited the facility licensee's administration of its 1987 requalification written examination to ten licensed operators. Ten percent of the examination was replaced with NRC questions, fifty percent of the examina-tions were parallel graded by the NRC, and the other fifty percent were re-viewed for adequate facility grading. All operators achieved a passing overall score and facility administration of this examination was determined to be satisfactor I l
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DETAILS EXAMINATION RESULTS: R0 SR0 TOTAL Pass / Fail Pass / Fail Pass / Fail Written Examination 2/0 8/0 10/0 Evaluation of Facility Written Examination: Satisfactory Grading: Satisfactory 2 SCOPE The facility prepared requalification written examination was reviewed by the NRC prior to administration. The examination was administered to ten out of eleven total licensed operators. The same examination was used for both R0 and SRO's, and the NRC was present to monitor the proctoring methods used by the facility. The NRC graded five examinations in paral-lel with facility graders and reviewed facility grading on the other five examination Ten percent of the total examination value was replaced with NRC written questions to provide an independent check on examination , validit I 1 WRITTEN EXAMINATION j The ten section written examination reviewed by the NRC was adequate to l determine individual as well as generic knowledge deficiencies. Some ; answers did not adequately identify partial credit for various parts and consequently resulted in minor variance between NRC and facility gradin In general, NRC and facility grading were within 10% of each other, except i for two individual sections which were due to incorrect facility grading ) of two question The criteria for a passing examination, as represented in paragraph one, was 70% overal Sectional scores less than 70% did not automatically fail an operator if the overall examination score was greater than 70%. However, due to sectional scores of less than 80% in sections on Proced-ures, and Technical Specifications, the following generic deficiencies ' were noted: l Operators were not knowledgeable of:
(1) stack exhaust yearly average or instantaneous release limit (2) criteria for re-entering the facility following emergency evacuatio The licensee's requalification program requires re-training and re-evaluation for any operator scoring less than 80% on a section. Oper-ator performance on NRC written questions was not significantly better or worse than on facility written questions, thus providing an independent check on the security of the exam prior to its administration and on the validity of the exam result _ ._ . .
4. . FINDINGS I In response to a self-identified examination integrity problem, the facil-ity licensee properly administered and graded a written requalification examination which was adequate to identify individual and generic knowl-edge weaknesses. All operators achieved the minimum passing score of 70% overall, although each operator scored less than 80% on at least two sectinns of the ten section examination and required remediation and i further evaluation by the facilit Review of these actions was not with-4 in the scope of this audit, but is subject to future review on NRC inspec- , tions and examinations. The NRC participation in this process to the l extent of prior exam review, replacement of 10 percent of the exam, NRC , presence during exam administration, and parallel grading and review of facility graded exams has satisfied the fundamental safety question that the knowledgeability of the operators has been shown to be adequate over-al The licensee commitment to continue to administer its requalification program in accordance with NRC policy as expressed in Generic Letter 83-17 and in the facility's NRC approved requalification program is noted and will be subject to future audit and inspectio Attachment: 1987 Requalification Examination .
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ATTACHMENT to ENCLOSURE 2 t . REQUAL 1987
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I Section A ' L. C. Henry THEORY AND PRINCIPLES OF OPERATION 1 Why 1,s a neutron source used for startup in your reactor? (6 fts) What material is used in the source, and how does it produce neutrgns (6il>/ Where should the neutron source be placed relative to the fuel and the fission chamber? [( rfs) If the reactor is exactly critical at a power of 5 watts: a) what is the current reactivity? [5ffd b) what would happen if the start up source were removed? lid (ts) If: 1) the reactor is critical at 5 watts 2) reactivity is inserted and the reactor achieves a stable period 3) the time it takes to go from 50 to 500 watts is measured to be 1.15 minute a) What was the reactor period? f (lof$) b) How long will it take to reach 2500 watts (from 500)? (Icpfi l c) If the operator takes no action, what will happen te the reactor? (Iagts) The reactor is scrammed from 2 power for the next 5 minute Describe what will happen to reactor Explain your answe / / S~ph) 5, The reactor is operatine with a primary flow rate of 10S0 GP.M and the
" delta-T" is 15 F. What is the true reactor power? (I7 t.s)
f 6, T h e r ear i rr is mace tc te subcriticalWILL b, c .e , s m.a ; l ame_r* e4 react 2v-Ity (less than the value of beta). the resultant stable negative , period approach -80 seconds? EXPLAI [/o
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O , , REQUAL 1987 Section B P. M. Orlosky GENERAL AND SPECIFIC PLANT OPERATING CHARACTERISTICS (12) List three things that determine the " worth" of a control blad . (10) Very briefly explain why a rod differential worth curve is bell shape . a (5) Draw the thermal flux profile horizontally across an empty (water filled) in-core fuel positio b (5) Draw the profile of this hole if it is filled with an air-filled aluminum bo c (5) Draw the profile if the hole is filled with an iron block, d (5) Would the empty box cause a + or - reactivity change? e (5) Would the iron block cause a + or - reactivity change? (12) Na-24 and Ag-110m are two of the major activities found in our pool water. Where do they come from? a (5) How much reactivity must be added to the core to change the reactor power from a stable 200 watts to a stable 2000 watts? b (5) How much reactivity must be added to the core to change the reactor power from a stable 200 Kw to a stabla 2 Mw? c (5) Briefly explain why your answers to a and b are either the same or differen . (20) Dra- a sieten or t r. e s e r. c r Curve 4c- tre reatter assaitng that ecs: . j rium .eran c onc en tr a t t ori It achel vec ther the reactor :s sh u t c owrs . Place approximate values on the X and Y axe l
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REQUAL 1987 Section C P. M. Orlosky Plant Instrumentation & Control Systems (21) There are 4 RTD and 3 TC sensors in the primary coolant system.
i List them and specify their location, and purpose. ! (9) Sketch 3 traces of a reactor scram from 2 Mw as seen on our log N recorder for the following - a properly compensated CIC a grossly overcompensated CIC a grossly undercompensated CI . (18) our cooling tower is now controlled by 3 switches cach having 3 position List the purpose of each switch and the function of each positio . (12) When the cooling tower is in "AUT0" mode, 4 distinct states for tower operation can be automatically selected by the control system to maintain secondary water temperature. What are they? (10) We have a great deal of confidence in our N-16 channe If it is so darn good, then why are there no control or safety functions associated with it? (10) How do you determine the best position for the fission chamber when preparing for a cold start-up? (G) Wntle at pcter. c at effect en eacte- pool temperature. :f anv. would result from the e panc:ng flulc temperature sensor at the heat exchanger prima-. Cutlct 4;;1Ing i c v, . f_xp1ain your answe .
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, , REQUAL 1987 Section D P. M. Orlosky Plant Design Features & Mechanical Systems (4) Describe 3 features built into our reactor system that limit personnel exposures from N-16 radiatio . (f2) Most research reactors are housed in " confinement" building A few like us have true " containment" buildings. List at least 6 features of our building that help qualify it as a containment buildin . (10) Sketch our EPF syste Identify major component . (IT) Under emergency conditions, briefly describe what fans stay on and what turns off and what ducts close and which stay ope . (IT) What physical features of our plant prevent the uncontrolled release of radioactive water to the sewer system? I do not want fine details of syste . (9) List at least 9 things that receive power from our emergency generato (JC) When normal power is restored to the facility, the emergency generator continues to run for 1 minute. Why? 7, In the core of your reactor the fuel assemblies are to be oriented in a certain wa how should they be oriented ? [Tf What is the reason for loading the core with this fuel element
: :entation?
(T M 8, a . Give two indications you would have if the resins in the demineralizer in the puri fication system become depleted? If t5) f b. Give four effects of operating for a long period of time with depleted resins? [Qg)
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.. REQUAL 1987 Section E James Griffin EMERGENCY PLAN and EMERGENCY OPERATING PROCEDURES What are the three classifications of Emergency at the Buffalo Materials Research Center, in order of least to most severe? (6 points) Who are the first four people on the Emergency Directors Candidate list, in order from first to fourth? (4 points) In the event of an emergency evacuation, what criteria must be met for re-entry to the facility? (10 points)
4. In accordance with E.P. #5, Reactor Fuel Failure Accident, what are six indications used to verify failed fuel. ( 15 por#rs) An accident at the facility results in a person's legs being trapped beneath a heavy piece of equipment. There is 50 Ci worth of material, in the form of irradiated steel specimens, scattered around the victi a) If you are alone in the area and unable to extricate the victim, what action would you take? (15 points) , b) Once the victim has been removed from containment, it is apparent that his injuries require immediate transport to a hospital.
discovered that the victim has 5,000 dpm contamination onIthis is also clothing ! and skin. What actions should be taken and what hospital should the victim be transported to? (15 points)
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* . . . REQUAL 1987 Section E L. G. Henry NORMAL OPERATING PROCEDURES Area Monitor System:
a) Under what conditions may the hot cell monitor be out of service? I'Of S) f b) The reactor has been operating at 500 Kw for two hours, and the bridge monitor is out of service for calibration. A customer wishes to increase power to 1 M Is it OK to increase power to 1 Mw? (to etS) c) What does a yellow alarm indicate? How should the control room operator respond? (lupts) Pneumatic Tube System: a) Fill in the following Table of r$1obo" VAIve 5 ih Oe receiver bu , /;pp h} AFTER A STEADY READING OF ACTION Remove rabbi Request instructions from reactor operator Secure the area and notify Health Physics b) Who is authorized to use the PNC? [ks pfs) Dry Chamber Operation: a) What gases may be used to void the D.C. nosepiece? ((pfs) b) When the nosepiece is voided, periodic checks should be made to verify that the tank is fully voided. How is this done? (icpf3) c) Describe two interlocks associated with the dry chamber. (h?pf s ) Isotope Production Facilities: a) Describe the procedure for leak testing ampules to be irradiated in the IF tube. [lopts) b) Why are there restrictions on loading IF samples at powers below I mW7 What are they? (topis)
. Special Vertical Stand Pipe: ,
i ' a) What is the reactivity worth of the movable cadmium shield? Can it be l moved with the reactor at power? [ 40 pts) b) What must be done before removing the entire facility if the reactor is operating? [lopts) c) Can the entire facility be lowered into the reflector with the reactor operating?
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_ .. - , Section E - Quhstions , , d) Where should the cd sleeve be stored when the facility is not in use; why? e) What is the minimum sample decay time before recovery? [ldf S) Y (wers) f) Samples less than ot lk mR/hrg may be removed without Health Physics approval. [ioph) b1AV g) Samples less than mR/hr may be transferred with an unshielded A transfercart.[gg73) b- List three administrative f unctions that must taNh place bef ore active waste water can be released to the sewer. (9ppq ,
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REQUAL 1987 SECTION F - *
.l. Griffin Radiation Control and Safety Questions The dose rate from a Co-60 source is 15 mR/hr at 12 feet unshielde (10) What is the unshielded dose rate from this source at I foot? (assume a point source.)
(10) What would the dose rate from this source be at one~fict, if the source was placed behind a 2-inch lead shield?
(p, = .059 cm2 /g) (Density Pb = 11.35 g/cm3) /lo) What is the dose rate at one foot from a 3 Ci Cs-137 source? (Cs-137 has a 89.9% intense gamma at 661.5 Ke V).
3. (10) What 7.5 Ciwould be the dose rate one meter away from a sample containing of Na-24?
(T Na-24 = 1.84 R/hr/Ci @ l meter)
4. (10) How long could a person remain in a 1.5 Rem /hr radiation field before receiving 100 mrem? A sample removed from the dry chamber, after irradiation, has a dose rate of 5 R/hr at I foo (10) At what distance from the sample must a high radiation area be posted?
(10) In addition to posting the area, what other precautions must be impleasated?
6. (10) If the will original remain activity after of a Co-60 source is 5 C1, how much activity 17 years? T g = Co-60 - 5 years 7, wHAT must be done if the reactor is o:erating witn the stack particulate monitor out o' service?
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. . REQUAL 1987 Section G L. G. Henry TECHNICAL SPECIFICATIONS /SAR What are our safety limits for: a) forced convection mode? (lorh) b) natural convection mode? (logd<>) What are our limiting safety system settings for: a) forced convection mode? (wg) b) natural convection mode? (loF f5) For the power plant stack exhaust release limits: N a) Yearly Average I Q /MPC i=1 f
.1 ? ? [foh) (provide limit and units)
N b) Instantaneously I Q /MPCg 1 i=1 7 7 [g (provide limits and units) For the building air duct: N a) Yearly Average I (C i MPCg) ? i=1
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(provida limit and units)
b) Instantaneously I (C + MPC g ) 1
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(provide listis and units) claw cf In questions 3 and 4 above, which MPC's f should be used? Why? [2C N) Why is there a " Flapper Open" Scram? b5' pts) Why are there interlocks on the log count rate channel? Explain all 3 interlocks associated with this channel. What is the " weak point" of this cvster llTpb}
E Technical Specifications list three (3) criteria for determining whethe-or not experiments should be doubly encapsulate STATE two (2) of these tbree (3) criteri (10ph)
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- , . . e SECTION H - 10CFR Mark A. Pierro 1/2O(87 Multiple Choice - Choose the single best response (5 points each)
1) A Class 104 license is issued to a qualified applicant of a: a) Medical Therapy Facility b) Research & Development Facility c) Commercial Facility d) Industrial Facility e) a and b f) c and d
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2) A Limiting Safety System Settings are settings: a) for manual protective devices related to safety function b) for automatic protective devices related to safety functions, c) if e::ceeded . protective action will correct the abnormal situation before a safety limit is exceede d) if exceeded, protective action will correct the abnormal situation after a safety limit is exceede e) a and c f) b and c ' 3) Technical Specifications must include: a) Safety Limits b) Limiting Conditions for Operation c) Surveillance Requirements d) Design Features e) Administrative Controls f) All of the above 4) LJh i c h NRC Program Office investigates accidents, allegations and unusual circumstances 7 a) I!uclear Material Safety & Safeguards b) Nuclear Reactor Regulation c) Standardn Development d) Inspection L Enforcement e) None of the above 5) Which items need to be posted, or if posting is not practicable, e notice. stating where they can be examined.?
, a) Regulations of Part 19 L 20 b) Facility License c) Operating Procedures ,
d) Notice of Violations e) a, b and c f) a, b, c, and d
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6) Which of the following is false: a) NRC can perform an inspection at any reasonable time b) Workers can consult with an Inspector only with a representative of Management c) Representatives of the licensee can accompany an Inspector d) b and c 7) Special Nuclear Material ist a) Uranium or Thorium in any combination in any physical or chemical form b) Plutonium, U-233, Uranium enriched with U-233 or U-235 c) U-235 contained in Uranium enriched to 20% or more in U-235, U-233 or Plutonium d) none of the above 8) The allowed average quarterly Federal Exposure Limit to the Whole Dody for radiation workers is: a) 1.25 Rem b) 3 Rem c) 5 Rem d) 12 Rem 9) The allowed quarterly Federal Exposure Limit to the extremities is: a) 5 Rem b) 7.5 Rem c) 12 Rem d) . 18.75 Rem
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W2$ 10) Which of the following is false 7 a) A worker's request for an NRC inspection must be in writin b) A worker is responsible to report violations or conditions that may lead to violation c) Worker's must be kept informed of the storage transfer and use of radioactive materia d) The quality factor for fast neutrons is 1 e) F'rocoduces must be established for safely opening packages in which licended material is receive f) A special operatoi's l i ceiis e is required for nuclear engineering students or operator trainees in order to operate the reacto I 11) No prior NRC approval is required for a licensee to make chances in the fa ility, procedures, and conduct tests or experiments not
' described in the safety analysis report as long as the change a) does not require a change in the Technical Specifications b) does not pose an unreviewed safety question j c) receives Nuclear Safety Committee approval d) a and b e) a, b. and c .bd( ) . . _ -- .. . _ .
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12) In order for you to have your operator's license renewed, you must: ! a) successfully complete requalification b) be able to competently and safely discharge your duties l c) be in good physical condition and general health d) have been active as an operator e) all of the above 13) Which of the following is true 7 a) An Senior Reactor operator must be at the controls at all times e during the operation of the facilit ~ b) A Senior Reactor operator must be.present at the facility during the recovery from an unplanned shut-dow c) A Reactor Operator must be readily available on call at all . times during the operation of the facilit d) none of the above ' 14) The yearly Federal whole body exposure limit for individual non-radiation workers is: a) 0.17 Rem b) 0.3 Rem c) 0.5 Rem d) none of the above 15) Which of the following is false ? a) You cannot be fired for reporting unsafe conditions to the NR b) You can be fined and or imprisoned for willfully violating NRC
. regulations, c) The NCR regional office for our area is located in King of Prussia, P d) Radiation exposure data must be reported to you e) A "whole body dose" includes any dose to the whole body, gonads, active blood forming organs, head and trunk, or lens of the ey f) All of the ebove u) None of the above ,
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' . , , REQUAL 1987 Section I L. G. Henry SECURITY AND REQUAL 1. Underwhatconditionfisanoperatorexemptfromsomeorallofthe requal exam? (12 ph) If an operator is away on leave for six months, what must be done before he or she may resume his/her duties? /trph)
' 3. Where do we store the following? a) Cold fuel Wd5I f or isk) e b) PuBe sources (not in use) [f f/5) c) Spent fuel (Tds) or (seh) What would happen if the multiplex link between BMRC and Public Safety were disrupted? (ITpb) WhomayauthorizeaccesstothecontainmentCAA?'[/Teb) Whatmustbedoneifthetruckdoorisnotclosedandlocked?[ Iffy 5) . Where is the nearest City of Buffalo precinct station? //Sg6) Who msut be notified if SNM is missing or attempted theft is discovered? [/ Fp/t) ! How would we respond to a mob attack on the Center? [l Ff /s)
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REQUAL 1987
, , Section A TilEORY AND PRINCIPLES OF OPERATION Answers [ -. p....,. t . . . . _ in t t- ' < tt rw . .. t ri --
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reacts with I. r- to f or r., s ,. 'o tr on plus C ~12
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l a) The current reactivity is zer I.e., K-1 = l-1 = 0 l K 1 b) Nothing; if the reactor were subcritical the population would diminish, but since it is critical, the population will remain constan (Since at 5 the reactor neutron population >> the source term). a) 1.15 min - 60 - 69 seconds (decade time)
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In (10) = 69 , T , i r 2.303 = g ,T T - 69 , 2.303 = 30 sec l l _ _ __ _ . _ , __. . -- --- - - - - * + - - - -
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3. b) P=PE o t 30 2500 = 500 e 5=e/0 t In5 = t/30 1.609 = t/30 t = 48 seconds c) The reactor fuel will increase in. temperature and doppler.effect will negate the positive reactivity and the reactor will settle at some power > 100 K . The reactor power will promptly jump downwards because of the large negative reactivity. It will then continue to lose power more slowly, and will eventually assume a negative 80 second period which re30lts fcces the half life of the longest lived neutron precursor ( 5'jr se cad 5) P = 0 Cp AT; at 2 Mw AT = 11.86 when flow = 1150
$ = K (flow)
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, N cp AT1 = K flow g cp AT g P
2 H2 CP AT 2 K flowy cp AT
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2Mw = .84 . ' , P = 2.38 F1 Watts
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Section B Answers . Elemental composition.' Mass of materia . Relative flux in the vicinity of the blad . Only the tip of the blade creates a reactivity change as it moves up and is replaced by water. In its travel up g the tip moves from a region of low flux to high flux and back to low flux. Hence the bell shaped curv ?
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I Al-27 (N.q)Na-2 l t Ag-110m comes from thermal activation of silver from control blade . none approximately 0.4% delta K/K
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There are no power related reactivity effects other than
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temperatue changes. Below approximately 100 Kw temperature changes are insignificant. Above approximately 100 Kw the
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doppler temperature coefficient is very significant, t
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2 . e REQUAL 1987 Section B - Answers Page 2 1 _ . ,.- _ _ . _ .._. . . XENCH .CUnv ConL IM A -.. g,4 ... n ru(3(
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REQUAL 1987
.
Section C Answers ) T1 - lower reactor tank - measures bulk pool temperature - RT ) T2 - in core out pipe outside biological shield - measures core discharge temp. - RT ) T 3 - primary llX inlet - measures llX primary inlet temp. - RT ) T4 - primary IIX outlet - measures llX primary outlet temp. - RT ) Bulk pool - lower reactor tank - measures bulk pool tem and provides bulk pool temperature scram - ) AT - lower reactor tank - of delta T system - ) AT - core discharge pipe - b of delta T system - I ,
A i T I M li pwg a i p w e -? l PW R 4 a b c Mode - hand off auto
. . Speed - hi off ,
low Direction - forward off reverse
- . - . - - .- . - - - _ _ -- - - . - - _. -- - . _ - - - - - - . _ - - _ . .- .
e REQUAL 1987 --
- , , Section C Page 2 i Answers ) fan on high
- 2) fan on low 3) fan stopped 4) fan stopped and flow diverted from top to basi . There is considerable fluctuation of the signal 'around the average value. There is a approximately 7 second delay after a power change before the instrument respond , Lower the fission chamber until you achieve a maxir st count rate. This will not be the full in position since the
. ' electronics saturate in the high gansna fiel '/ . Reactor pool t emperature would increese because 11 t h -'
sene :r failed ]nu tot- sccandar y c t'ol a nt b y p ac t. 'al ve ' o', 71 rj ;c;.a_t f ', -- i e t- , n c r ra c e o the .c-sctor non! temorr
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- * REQUAL 1987 Section D Answers ) Forced flow is downward so N-16 cannot rise to the pool surface 2) Pipes containing N-16 are shielded by earth or concret ) A shielded hold-tank allows deca . 1) Construction is of solid reinforced concret ) There are no window . - i~ y 3) Sealed doors and airlocks are provide ~
4) All penetrations are seale i 5) Air ducts have airtight dampers in the ) Controls maintain a negative pressur . St PIIp!/ BA%dK -
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REQUAL 1987 Answers
* . Page 2 . Section D . #
l All fans in containment turn off. The basement stack fan turns of Power house fan stays on. Dampers close in l stack, conditioned air supply, fume hood supply, and build-ing air exhaust ducts. Emergency duct damper modulates to control negative pressur I l All drains in the containment building discharge to under-ground storage tanks. The valve between these tanks and the sewer is locked close .:
~
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. -z.~ (a) 1) Fire alarm 1 2) Stack gas and particulate monitors 3) Primary water monitor 4) Hot cell monitor 5) Building air monitor 6) Bridge monitor 7) Monitor recorders 8) Exit lights 9) Containment intercom 10) Damper scram solenoids (b) When power is restored, it is frequently intermittent or trips out again. The generator cannot follow such transient It is programmed not to shed its load unless power has been on without interuption for a full minut . 4 ionc a;1- intersects tne t h er roa l c ol i trr.n . :'r' -
r.a r c , t o - si .. F oi c ote ,i .m
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4.,du +2vit, t o c r e a r.e . activity increas . c i t.;l
- .. m . : urs bui l dup , fuel temperatur- 1>crS'.
I i. t 1 j U 1 af * Ji . r .' O f t I D'/el s increase
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l l e REQUAL 1987
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a s ution 5 Answers EMERGENCY PLAN and EMERGENCY OPERATING PROCEDURES
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1. Notification of unusual even Emergency aler Site area Emergenc l 2. Lou Henry Phil Orlosky Mark Pierro Jim Griffin 3. a) Two-man teams b) Adequate dosimetry and protective equipment c) Anticipated exposures consistent with: 1) < 1.25' Rem / quarter or 2) < 3 Rem / quarter is not to exceed 5 (N-18) limit or 3) <25 Rem if volunteers, approved by E.P., and necessary to mitigate hazar or 4) <75 Rem if volunteers, approved by E.P., and necessary to effect l life saving rescue, d) Re-entry personnel usut be familiar with consequences of radiation exposur l . Pool tmter analysis Pr imar y water monitor incrcane !
' Building air monitor increase Particulate monitor increasc N-l e racni tor increase c, Pridge mon) tor increate h M ' E U E i'4 L E. --
5:JNY EP ttL
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5. Parts to be covered: a) Remove sources from proximity to victi . Reassure victi ' l 3. Seek help from response agenciesRPS, (other staff, Public Safety, Buffalo Fire Department, etc.). 4. Provide proper dosimetry and escort to response tea , 5. Re-enter in accordance with Emergency Pla . Rescue victi b) Victim should be transported to the V.A. Medical Cente . If time permits, victim could be wrapped in blanket to contain contaminatio . Victim tag containing pertinent radiologic information should be ] attached to outside of blanke . No attempt at contamination control should la any way delay 1 transport of a seriously injured perso i 5. If staffing allows, Health Physics or Operations staff member should accompany the victim to the hospita !
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REQUAI, 1987 - o Section E' NORMAL OPERATING PROCEDURES Answers 1. a) For repair or calibration, provided the hot cell key is administratively controlled (OP. 26 IV A.2), b) The bridge monitor may be out of service for up to 4 hours; however, reactor power may not be increased (OP. 26 IV A.3.). c) Yellow alarms indicate instrument failure (low rate); notify 4 shift
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supervisor or Health Physics (Op.26 Ill. A.). 2. a) Dose Rate < l. R/hr Op. 42. IV D) 1. < Dose Rate < 10.R/hr Dose Rate >10.R/hr b) Only those persons who understand OP. 42 and have been checked out by the reactor supervisor or his designe (OP. 42 V. A.). a) CO 2 rN
(OP. 48 V.E.)
b) Momentarily crack open valve DC-2, bubbles should immediately be discharge (OP. 48 11 A.8.) . c) - Retedte $(R4P,1f door is opene Shutter full down in order to open doo (OP. 48. V. B, C)
~ Oo.e- mush be closed du cPen shb r 4. a) - Let sample stand for 30 minutes offer hevP $6 Dim) - Submerge sample in near-boiling H Check for bubble (OP. 49. B 1, 2, 3)
b) - There is no doppler feedback to oppose the power change, so normal peaking procedures don't wor rfconal
- Loading must be approved by the Operations Manager, an under the j direct supervision of a senior reactor operato (OP. 49 c) !
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5. a) ev(-) .06% AK/K, yes l b) Secure the cd shield in the Up positio I c) N d) In the "Up" position to avoid unnecessary activation and burnup of the c (Op. 50. B) e) 2'.0 hours (Op. 50. F. 1)
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f) 100 (Op. 50. F. 4) - g) 10 (Op. 50. F. 9) l g' 1) The tank is circulated to mix its content ) The tank water is assaye ) RPD aust authorize the dump and release the valve key to operation .
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_ _ . -__--____ __ SECTION F ~ r Radiation Centrol cnd Safety
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ANSWERS - 0 ' 2 2 l. Idii = 1d22 11
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15 mR/hr 15 x (12)2 = X(1)2 dl = 12 feet 2,160 mR/hr = X 2"X or d2= 1 foot
*
2.16 R/hr I = Io e "*
~ p=y .p Io - 2.16R/hr I = Ioe (* - )I * ) y = 1.35 x .059 X = 2 inches - 5.08 cm I - 2.16 R/hr x .03 p = .67 ca~ "a= .059 cm3 /g a = 11.35 g/ce?
I = .072 R/hr = 72 mR/hr R/hr @ l ft. = 6 CEN C=3Ci
. = 6 (3) (.661 x .899) E = .661 MEV = 10.696 R/hr 9 1 f n = .899 Dose rate = Activity x i = 7.5 x 1.84 R/hr 9 1 meter /Ci = 33.8 R/hr 9 1 meter . Staytime = Limit = 100 mrem = .067hr - 4 minutes Dose rate 1500 mrem /hr 2 2 5. Igd =
Id22 1
=
5 R/hr (5) (1)* =
.100 (I)* di = 1 f ft = x a 2
=
.100 R/hr !
d, = X Since the radiation area will exist for less than 30 days, direct surveillance may be used to prevent unauthorized access to the high
*
radiation are . A = Ace * ' Ao = 5 Ci is
,
t = 17 years
- =
Se .693(17) Tg = 5 years
= .474Ci
=
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, REQUAL 1987 * 4 Section G TECHNICAL SPECIFICATIONS /SAR Answers a) Power not to exceed 3.3 M . Water level top of core to surface not less than 17 fee . Primary flow not less than 1,000 GP . Bulk pool temperature not greater than 140 b) Power shall not exceed 500 . a) Control blade reverse @ 2.2 M . Control blade scram @ 2.4 M . Control blade scram H O depth @ 20 fee . Control blade scram H 0 flow @ 1080 GP o Control blade scram H 2O T Bulk *
b) Reactor scram @ 250 K I a) 1 8.1 x 10 Ci x sec-3 Ci x m
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1 2.4 x 10 Ci x sec
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. ! a) 1 1 dimensionless b) 1 2 dimensionless For the stack - unrestricte For building air - restricte ,
Stack limits are based on population exposures from diluted plume, building air limits are based on occupational exposures to workers within the buildin . The flapper open scram prevents core flow bypass when operating in the forced convection mode at powers in excess of the natural convection LS . The " low" and "high" count rate interlocks ensure that the channel is operational, thechannelfbnscale,andthedetectorfbroperlypositione The recorder inoperative interlock ensures that the recorder is turoCd on The interlocks do not function if the log-N recorder is positioned at P > 4 watts (even if not energized).
" F, 1 Le -,- - - ' - a t -a ' t * r" rt ' ' ' i'":"te ' tac 111tv, , E;;c es si ve . ontami na ti o! . c. i- ;rocuction o1 , , r o c.r me r M i N c . v)ty.
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SECTION H - 10CFR : ANSWERS 1) e 2) f 3) f 4) d 5) f b .;p 6) ' 4' #~d, .. 7) b 8) a 9) d 1O) f 11) d 12) e 13) b 14) c 15) g
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\ * > ! R EQllAl. 1987 I
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<d Section 1 SECllRl*l Y AND REQliAl, Answers 1. An operator is exempt if: - he/she is the Operations Manager, or - if he/she served as a training assistant, he/she is exempt from the applicable exam topic ke]$Q teleived a litenfe in Sh y&r 2. The operator must pass an oral exam on facility or procedure, changes and perform a reactivity manipulation under the observation of a member of the Facility "re-training group".
3. a) reactor tank fuel vaults b) inside locked drums within the controlled access area [acrewUy AI /Ol/ c) reactor tank hot cell 4. Disruption of the multiplex link would be sensed by the Public Safety computer, and trigger an alar . Director, Operations Manager, Reactor Enginee ' 6. It must be attended by an authorized staff membe . Precinct 16,1.2 miles south on Bailey Avenu . NRC, FBI, Public Safet . - Reactor shutdow Secure support systems to extent possibl Move all personnel into containmen Barricade airlock door Await hel i l
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