IR 05000170/1986001: Difference between revisions

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{{Adams
{{Adams
| number = ML20140A804
| number = ML20215M604
| issue date = 02/06/1986
| issue date = 10/23/1986
| title = Exam Rept 50-170/86-01 on 860107-08.Exam Results:Both Senior Reactor Operator Candidates Passed.Problems Identified W/ Housekeeping & Maint Controls Outside Reactor Area
| title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-170/86-01
| author name = Dudley N, Keller R, Kister H
| author name = Wenzinger E
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| addressee name =  
| addressee name = Conklin J
| addressee affiliation =  
| addressee affiliation = ARMED FORCES RADIOBIOLOGICAL RESEARCH INSTITUTE
| docket = 05000170
| docket = 05000170
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = 50-170-86-01, 50-170-86-1, NUDOCS 8603210231
| document report number = NUDOCS 8611030053
| package number = ML20140A796
| title reference date = 04-29-1986
| document type = EXAMINATION REPORT, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| document type = CORRESPONDENCE-LETTERS, NRC TO RESEARCH INSTITUTION/LABORATORY, OUTGOING CORRESPONDENCE
| page count = 37
| page count = 2
}}
}}


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U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N FACI!ITY DOCKET NO. 50-170 FACILITY LICENSE N LICENSEE: Defense Nuclear Agency Bethesda, Maryland 20014 FACILITY: Armed Forces Radiobiology Research Institute EXAMINATION DATES: January 7 and 8, 1986 CHIEF EXAMINER:  /46 Ctp  /~b Ib N. Dudley, Lead R " tor Engineer Date REVIEWED BY: If   2-[3[k Rotiert M. Keller, Chief, Projects Section 1C Date APPROVED BY:   d HarfyB.Kittyr, Chief,  D6te I /
Docket No: 50-170 Defense Nuclear Agency Armed Forces Radiobiology Research Institute   ,
Projects Branch No. 1 SUMMARY: Examinations were administered to two Senior Reactor Operator Can-didates and two licenses were issued. Problems were identified with house-keeping and maintenance control for areas outside the reactor are hbh kD K ho v
ATTN: Colonel James Conklin, MC, USAF   l Director Bethesda, Maryland 20014 Gentlemen:
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Subject: Inspection No. 50-170/86-01(0L)
This refers to your letter dated April 29, 1986 in response to our letter dated March 5, 1986.


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Thank you for informing us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed program.
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Your cooperation with us is appreciated.
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REPORT DETAILS TYPE OF EXAMS: Replacement EXAM RESULTS:
l SR0 l l Pass / Fail - l l  l l l  1 l Written Examl 2/0 l-1  I  i i l  I l Oral Exam l 2/0 l l l  l l l l Overall l 2/0 l l  l  l CHIEF EXAMINER AT SITE: N. Dudley, NRC Summary of generic strengths or deficiencies noted on oral examinations:
Although candidates were knowledgeable' of reactor systems and operations they did not display a strong working knowledge of the electrical distri-bution system, the radiological waste disposal system, or the ventilation system. Neither candidate was able to correctly determine whether the discharge pressure of the supply fan to the reactor room was sufficient to lift the building overpressure relief valve if the exhaust damper was shut, and whether a release through the relief system would be unmoni-tored. Neither candidate was able to locate up-to-date, as-built, draw-ings to evaluate the consequences of the hypothesized malfunction Candidates were unable to identify out of service equipment connected with auxiliary and support systems not directly addressed by the Technt-cal Specifications. Candidates stated that there is no management system available to the operators to track out of service equipment which is not directly under the cognizance of the operations departmen Housekeeping outside the reactor building is inadequate. In the Reactor Control Area Room there was a hose which the operator was forced to step on and over during completion of the startup check-list. There were rusting cans and buckets on the floor, a fan belt hung from a valve stem, and an overflowing trash barrel was in the middle of the room. In the second floor ventilation room valve bodies and diaphragms were laying loose on top of ventilation equipmen __ ____-_  -
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  ' . Personnel Present at Exit. Interview:
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NRC Personnel
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    'N. Dudley
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    -Facility Personnel M. Moore,-React'or Facility Director Summary of NRC Comments made at exit interview:    i A. discussion was. held concerning the details of facility operations to clarify questions which. arose during the oral examinations. Also,'a discussion of-facility comments on the written examination was conducted.


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Sincerely, Origina1 Signed Byr Edward C. Wenzinger, Chief Project Branch No. 3 Division of Reactor Projects cc w/ encl:
The examiner ques'tioned why f!re extinguishers had been checked monthly i    until August of 1985 and.had not been checked for five months. The'Reac-  ~!
M. Moore, Reactor Facility Director Public Document Room (PDR)
. tor Facility Director explained that the fire department had lengthened the surveillance periodicity on the fire extinguishers to six month F
Nuclear Safety Information Center (NSIC)
;. The examiner noted that housekeeping outside the reactor area was unsatis-  :
State of Maryland (2)
,    factory. The. Reactor Facility ' Director agreed but sta.ted he had no con-trol over the cleanliness of those areas since they had been turned over   l to contractors'for facility modifications.
bcc w/ encl:
DRP Section Chief D. Coe OL File 12.0 Region I Docket Room (with concurrences)
0FFICIAL RECORD COPY OL RL DNA - 0001.0.0 10/15/86 _rgro/
e611030053 e61023 0   g\
PDR ADOCK 05000


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The examiner noted that there was an apparent' lack of management control for facility maintenance and modification Indications of the lack of
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management. control included unavailability of.as-built prints and the lack
RI:DRP RI: R P kl.RP RI Dudley/bc Kel Kis".!r Elsasser WpMinger 10//6/86 10/ /86 10/ 0/86 10/3./86 10/ /86 app 0FF:CIAL RECORD COPY OL}HLDNA- 0002.0.0 DJ  10/15/86
:    of an out of service equipment' tracking system. .The Reactor Facility
[,  . Director stated 'that the operations department-does not track "non-re-
    . quired systems" because there is no requirements and that it is too dif-
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ficult to obtain information from the other. departments. He continued,-
that there is' no integrated control system at the facility to monitor and   ;
track maintenance being conducted by each departmen '
4 Unresolved Items:
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    -The status of housekeeping outside the reactor area will be evaluated  i during future inspections. (50-170-86-01-01)    F The apparent lack of management controls for facility maintenance and  i modifications may. result in the inability to identify the effects of planned maintenance on the safety of the reactor area. This is an unresol'v ed item pending further discussions between the licensee and NRC
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Region I. (50-170/86-01-02)
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DEFENSE NUCLEAR AGENCY ARMEo FORCES RADICBIOLOGY RESEARCH INSilfuTE BETHESDA, MARYLAND 20814 DIR 29 April 1986 01004 United States Nuclear Regulatory Commission Mr. Edward C. Wenizinger Project Branch No. 3 King of Prussia, PA 19406
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==Dear Sir:==
' Changes made to written exam during examination review:
Dis letter is in reply to NRC examination report number 60-170/86-01 conducted by Mr. Noel Dudley on 6 January 1986. Mr. Dudley% report contains statements about the facility that do not accurately describe conditions in the facility. Bis letter is the requested reply describing measures taken to assure reactor safety, services, and fire prevention during the pending construction activities. %c Armed Forces Radiobiology Research Institute's comments concerning the NRC report (#50-170/86-01) are discussed beginning with page 3, number 3, " Summary of NRC comments made at exit interview," followed by license examination report, item number 1, " Summary of generic strengths of deficiencies noted on oral examinations"(see enclosure).
Consideration was made of facility comments. However, not all comments resulted in change to the answer ke Answer N Change  Reason Change to "2, 4, 3,1" In practice, calibration of the transient rod is performed after a full core loa K.10 Add " Presently one Statement of present plant top and one center configuration is required thermocouple are for full credi selected."


K.14 Add "for worth per rod; Allows answer for highest D - most reactive ring". rod worth or highest ring wort Add "4. Do not lock Corresponds to newly reactor door". revised procedure Change "15 Watts" to Corresponds to newly
For information on matters discussed in this letter, the point of contact is the Reactor Facility Director, Mr. Mark Moore. He can be reached at the letterhead address or on telephone number (301) 295-1290.
  "above source level". revised procedure . Written Examination and Answer Key (SRO) Facility Comments on Written Examinations made af ter Exam Review


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Sincerely yours, l
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U. S. NUCLEAR REGULATORY COMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION
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,    Facility: AFRRI Reactor Type:' TRIGA Date Administered:
Examiner: ~ NOEL DUOLEY Candidate:
INSTRUCTIONS TO CANDIDATE:
Use separate paper for the answers. Write on one side only. ' Staple question sheet on top of the' answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours after the examination start ~
Category % of Candidate's _ % of-Value Total Score Cat. Value Category  -m - - -
20 20  H.. Reactor Theory 20 20  I. Radioactive Materials Handling,. Disposal, and Hazards 20 20  J. Specific Operating Characteristics
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20 20  K. Fuel Handling and Core Parameters 20 20  L. Administrative Procedures, Conditions, and-Limitations 100    TOTALS Final Grade  %
All work done on this examination is my own; I have neither given nor received
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Enclosure:
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as stated    {#3 MES J. CONKLIN Colonel, USAF, MC Director 3n ,
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t : REACTOR THEORY'(20 POINTS)
            < Assume the reactor is critical at I watt. . What effect, if any,   ;
will be observed if the source is removed at this point?
Explai (1.5) j Calculate how long it will take to increase the reactor period    *
from 15 W to l' MW on a stable 5 second perio (1.5) Estimate the shutdown margin of a fully loaded AFRRI core using given dat (1.5) !
Rod worth Trans  $3.63  - -
Safe  $1.88 Shim  $1.90 Reg  $1.87    _;
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Normal excess infinite H 2O = $4.25      i Natural convection of the water in the reactor tank cools the reactor core. Explain how natural convection takes place, l
including how a doubling of power would affect the flow past the elements and the change in temperature between the bottom.and    ,
top of the cor (3.0) A K excess is measured on Honday morning (no weekend
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operations). The reactor is then operated at full power for 5 hrs, shut down, and K excess is measured 4 hours -later. ~ Would you expect the K excess to be greater or less than that measured    t in the morning? WA?      (2.0)
            ! Explain where the large negative temperature coefficient of reactivity comes from, give all three (3) components, and briefly describe each one. List in order of importanc (4.0) The following statements are concerned with subcritical multiplication. Choose the one underlined word that will make the sentence correc , As K ff approaches unity, a larger / smaller change in neutron
    'aveiresultsfromagivenchangeinK ef (0.5) As K ff approaches unity, a shorter / longer period of time is required to reach the equilibrium neutron level for a given change in Kef (0.5)
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AFRRI COMMENTS ON NRC REPORT 50-170/86-01
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  'Ihe following are responses to NRC Examination Report No. 50-170/86-01:
1. In item 3, paragraph 2, Mr. Dudley implies that fire extinguishers within the reactor facility had not been checked for 5 months. 'Ihe day fonowing his visit a survey showed that of the extinguishers in the faculty, one was dated Sept 1985, and one dated Nov 1985. All the rest were dated Dec 1985 (the Jan check had not been completed at the time of the operator's exam). In fact, the longest unchecked span noted on the unit tags was 3 months.1he base (NMCNCR) fire department was in the process of having a special hydrostatic testing done (off base) on all units in AFRRI, not just the reactor, and this would require about 6 months to complete as the testing is accomplished there wul be months shown as not being checked on the tags. ToHow-up checking revealed that1he'two units thateter.


  - Answer the following True or False:          d A week after a reactor shutdown,- a Xe-135-free core is also
Tudley had seen*8 sert returned from the pool of tested imits and had not been back
   . an I-135-free cor (0.5)
   'long enough for a date in the regular monthly check. All facility units have been ehoeked and are current.
b. . The equilibrium Xe-135 reactivity at 70% power is less than twice the equilibrium Xe-135 reactivity-at 35% powe (0.5) The reactor is shut down by 6% delta K/K with a source range neutron count rate indication of 50 CPS. How much reactivity will have to be added through rod withdrawal to raise the source range count rate indication to 300 CPS 7        (2.0)
H.10 J oes Wh d Xenon peak later following a shutdown from high power than it does when.following a shutdown from a low power level?-        (2.0) (
H.11 According to Fuch's Pulse Model Equations, which parameter given
  .below is the pulse power proportional to: Select on The initial temperature T Thesquarerootofreact10ityinserted The reactivity inserted The square of reactivity inserted Beta-effective          (0.5)
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2. Item 3, paragraph 3, and item 4, paragraph 1, concern the same issue.1he operator licensing examiner viewed areas peripheral to the reactor area (equipment rooms) that were under construction and undergoing removal and installation of equipment, including the drining of concrete and the unpacking and placement of i  electrical components. At no time did the Reactor Director state that he had no control over the areas. On the contrary, it was explained to Mr. Dudley that at
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;  that time, the equipment rooms were involved in heavy construction work and as i  work progressed, debris would be removed consistent with safe work practices. At no time did the area or materials in the area present any safety hazard to personnel or to the reactor systems. The following week, the areas in question were thoroughly cleaned and prepared for the next phase of construction. It should be noted that earlier and later inspections, including an unannounced operational inspection (No. 50-170/85-03) shortly before and a speelal security inspection shortly after (No Report No. to date) the license exam by operational inspectors have found this facility to have excellent housekeeping over the course of many years. Quoting from Report 50-170/85-03 " Facility tour . . . 'Ihe areas were clean, free of debris and well maintained."
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3 RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS (20 POINTS)
1.1 If the reactor was operating at 1 MW and a fuel element developed a~ crack in the cladding, how would the operator first receive an indication of the failure? As the senior reactor operator on duty, what would be your immediate actions upon suspecting the cladding had failed?  (3.0) .
I.2 You are the SRO on duty. -You learn that an experimenter has made the following changes in his experiment ~ after it had been approved for irradiation in the Core Experiment Tube. (CET). He will use an aluminum rabbit instead of plasti .. t He will clean the experiment with acetone.(CH3)2C0 rather than alcohol C 25 H 0 . He will place the experiment in a gold-silver capsule with a sodium chloride solution instead of a quartz ~ glass with a distilled water solutio ~ The run will be reduced from 1 MW hr to 55 min at 1 M ____________________________ Will you permit the experimenter to place this experiment in the Core Experiment Tube (CET)? Briefly explain your answe (1.0) For the changes 1-4 explain how and why each would affect the radiological hazards associated with the experiment (i.e., no significant change, or increase or decrease hazard and reason for change).  (3.0) If the experiment as changed is eventually performed, what precautions would you suggest for handling the rabbit after exposure?    (1.0)
1.3 Explain the operation of the N-16 Diffuser System and wA the system is rarely use (2.0)
I.4 True or False: The Remote Area Monitor (RAM) System consists of detectors to measure neutron radiation levels in various areas of the plant where radiation hazards may exis (0.5)
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Construction on this facility will continue for approximately 6 months. During this time the reester staff win perform housekeeping inspections en a frequent basis to
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ensure maximum area cleanliness and that construction will not~lmpact the safety ~
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~ List the three (3) principal nuclides potentially present in the gaseous effluent measured by the stack gas monitoring syste Also state the primary source for eac (2.5) Why are all six (6) surfaces of the exposure room lined with a P oot thick wood lining?  (2.0) What prevents upward streaming of radiation from the Core Experiment Tube (CET)?  (1.0) Two identical samples are irradiated in the same flux; one for 20 minutes, and the other for 10 minutes. What will determine the ratio of activities .of the two samples T6TTowing irradiation? Explai (2.0) ,
3. We would like to point out that item 1, paragraph 3 has nothing to do with the exam given to the reactor trainees. Also, it does not indicate generic deficiencies on the part of the trainees. Instead, it is simply an opinion on the part of the examiner.
6 The radiation level in a planned maintenance work area is 150
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mrem /hr. Work in that area is expected to take three (3) people
  . working 5 hours apiece. For each of the following options, calculate the ex ected total man-rem exposure (including maintenance work - Temporary shielding is installed by two (2) worker d ho stay '
one hour in the 150 mrem /hr area, then the maintenance work begins. A tenth thickness of shielding M installe (1.0) The radiation source is found to be a point source, where the 150 mrem /hr is the exposure at four (4) feet. By using extender tools, half the work is done at four (4) feet and half the work is done at eight (8) fee (1.0)
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5 SPECIFIC OPERATING CHARACTERISTICS (20 POINTS)
  ' Given the following rod configurations: safe-up, shim 60%,
reg-up, trans servoing at steady 800 KW - what changes, if any, will occur if the shim rod up switch is depressed? If the safe down switch is depressed? Explai (2.0) Explain the " isolation" capabilities of the air system in the reactor roo (2.0) List five (5) conditions that will cause a RWP (Rod Withdrawal Permit) for one or all rod (2.5) What design feature minimizes the bottoming impact of a control rod drive piston?  ~
      (1.0) Explain the difference between Safety Channel 1 and Safety '
Channel (1.5) What is the range of the wide range log channel in the nuclear instrumentation system?  (1.0) , What two (2) techniques are used for covering the upper and lower ranges?    (1.0) For the electrical loads listed below, indicate whether power comes from Transformer 42A or 42 Reactor Console Cooling tower fan motors Radiation Monitor Power Panel Lightin (2.0) Briefly describe the differences in physical operation between the regulating rod drive mechanism and that of the shim and safety rod drive (1.5) Why is air pressure at 9 psi supplied to the shield door bearings?    (1.0)
J.10 On a loss of air pressure, what will happen to the supply dampers (S1, S2, and S3) and to the exhaust damper (E1) located in the heating and ventilating ducts of the Reactor Room? (1.0)
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l Mr. Dudley has relayed a situation in his report concerning management controls for facility maintenance and modifications that is inaccurate. AB items relating to reactor safety, reactor systems, reactor modifications, and reactor maintenance including records and procedures are current and available in the facility. The examiner, Mr. Dudley, did not ask to see any of these documents. 'Ihe reactor staff has a group of support test equipment, including voltmeters, current meters,
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J.11 What are the three (3) basic functions of'the water purification C
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J.12 Two 1tems, frequently associated _with in-tank experimental
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devices, are mercury thermometers and dosimetry devices. Why is
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it important to ensure neither of these items are introducW into the reactor coolant?   (1.0)
J.13 What would happen if the rods failed to scram after a pulse?
Draw or describe'in detail the power respons (1.0)
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and electrometers, that are used in reactor calibration. His equipment is sent to
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7 FUEL HANDLING AND CORE PARAMETERS (20 POINTS) Briefly describe the procedure to be used in detemining a steady state power coefficient. of re~ activity?  (3.0) True or False: In-core experimer.ts shall not be placed in
  - adjacent fuel positions of the B-ring and/or C-rin (0.5)
; What is the minimum number of nuclear instrument channels
!  (with capability to detect' source neutrons) needed for fuel l
movement during core loading?  (0,5) During unloading?  (0.5)
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! K4 In what order are the rings ~ loaded?  (1.0) How many elements are loaded per step until critical loading l
1s achieved?    (0.5)
! What three (3) inspections and measurements must be conducted on a new fuel element received at AFRRI prior to it being loaded into the core?
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      (1.5) The following steps are taken ff6m' the AFRRI operating procedure for reactor core loading. Rearrange in the order that they will
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l Calibrate the transient rod j' Load elements until critical loading is achieved
; Load core to full operational load l Load core to $2.00 excess reactivit (2.0) How does the operator ensure that the fuel element is properly l  seated in the lower grid plate during the loading of F28 during Core Experiment Tube (CET) removal from the core?  (1.0)
l l According to the AFRRI Reactor Core Loading and Unloading Procedure (VII), who are the minimum personnel that must be present for the core loading operation?  (2.0)
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  , an Institute calibration facility and their either calibrated or sent out for calibration. Als is accomplished under Institute procedures, not reactor facility procedures. When the unit is calibrated, it is returned with a calibration sticker in place on the unit. If a unit is out for calibration, a backup unit is always available in the faculty; if the facility does not have a spare unit, one is borrowed from the calibration group. %e records or " tracks" of any reactor system, safety or otherwise, can be readily produced in the faellity, the support equipment records are available in the appropriate area. AFRRI's record of previous inspections both NRC, and independent audit by the Office of the Inspector General, for example 50-170/85-03 Item 5, IG Inspection report, 21 June 1985 and IG Inspection 17 June 1983 TAB G, has shown the maintenance system used in the reactor facility to be more than adequate. his system ensures that the facility maintenance and modifications are performed in a planned manner that guarantees the safety of the reactor and reactor systems.
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8 What is the purpose of the. graphite slugs at each end of the U TueT-moderator rods?  (1.0)
K.10 Which fuel temperature thermocouple readings are fed to fuel safety ~ channels one and two?  .(2.0)
K.11 What would happen if while operating at 1 MW the CET came loose
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and popped out of the core? 37 W  (2.0)
K.12 What is the maximum allowable K excess with a fully loaded core?    (0,5)
K.13 W M is samarium included in each fuel element?  (1.0)
K.14 Which fuel element ring has the. highest worth?  (1.0) '
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l 1 ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS (20 P0lNTS) List five (5) items that require daily checks for operation by (2.5)
the Technical Specification List three (3) things an operator must do upon hearing a fire (1.5)
alar What conditions must be met for the reactor to be considered (3.5)
  $ECURED? Who is allowed unescorted access to the reactor Controlled (1,0)
Access Area (CAA)?
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~ What actions must an operator take on an AFRRI Complex Emergency Evacuation according to Procedure VI (Emergency Procedures)? (2.0)
Include what actions are taken with reactor area door Entries to the Reactor Operations Logbook are occasionally made Give two (2) examples for each color '
in Red or Green color (red, green) of an entries that might be designated by that (3.0)
color indicatio What is the maximum power limit for square wave operation? (0.5) What is the maximum power allowable before pulse (Mode III)
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operation? What is the minimum power? According to the AFRRI Emergency Plan, define _both Emergency (2.5)
Action levels (EAL's) and Emergency Classes? What is the order of succession for.the Emergency Command Post (1.5) .
  (ECP) Commander?
L.10 AccordingtoTechnicalSpectfications,whatarettEeminimum number of fuel elements that are required in a closely packed array to achieve criticality? Select on elements elements elements    (1.0) element End of Category L -
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On the issue of as-built prints available in the facility as referenced in Item 3 paragraph 4, AFRRI contains far more than just a reactor facility. The AFRRI Logistics Department (LOGF) maintairs the building proper and the installed building equipment. Many changes have been made over the last 20 years. These changes are documented on building prints located in the LOGF office. However, because of the large mass of documentation, locating a particular item can
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  'sometimes be difficult for a newly licensed operator. AFRRI construction,
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primarily on the facility air and ventilation system, is being conducted in phases.
EQUATION SHEET  -
  .____..._________________________________........__...______ ....... __....
  . .      +
l  - Where mi = m2 (density)1(velocity)i(area)1 = (density)2(velocity)2(area)2
  ,
____.......____________________________.............____ ........._____ __
l  ~ KE = mv2 PE = mgh PEi +KEi +Pi Yi = PE +KE  where Y = specific
!  - li  2 +P 2 Y22 volume P = Pressure
  .. ______...... _______...... __...______...__ ......._____..__....____ ..
(  Q = ic p(Tou t-Tin)  Q = UA (Tave-Tstm)  Q = m(hi -h2 ) *
____________ .______.. _______________..______ ..__ ..........___..__..... _
        ,,
P = P e10(.SUR)(t) p p et/T SUR = 26.06 T = (B-p)t I  p
  ...__.u __.....___________.. ___.__..__._..___.......____.. .....____...
      .- -
delta K = (Ke f f-1)  CR1 (1-Keffi) =.CR 2 II-Keff2)
CR = S/(1-Keff) e r -
,  M = (1-Keffi)  SDM = (1.Keff) x 100%
!
  (1-Keff2)    K eff
__...___ ......____..______._____...__......._......._______........ __...
l  decay constant =
in (2) = 0.693  A 1 = Ag e-(decay constant)x(t)-
  -, t t 1/2 1/2
____.........._________________.___.........__..__.__ ____......___.._....
L  Water Parameters  Miscellaneous Conversions  #
,
i l  1 gallon = 8.345 lbs  1 Curie = 3.7 x 1010 dps l
I 1 gallon = 3.78 liters  1 kg = 2.21 lbs 1 ft3 = 7.48 gallons  1 hp = 2.54 x 103Btu /hr
!  3
  ' Density =62.4lbg/ft  1 MW = 3.41 x 106 Btu /hr Density = 1 gm/cm  1 Btu = 778 f t-lbf Heat of Vaporization = 970 Dtu/lbm  Degrees F = (1.8 x Degrees C) + 32
  - Heat of Fusion = 144 Btu /lbm  1 inch = 2.54 centimeters -
1 Atm = 14.7' psia = 29.9 in Hg  g = 32.174 f t-lbm/lbf-sec2
  ...__..__..___......___....______..............._.......______... _____...
O


      **
A complete set of building plans is available as each phase of construction is completed. The scheduled completion date for the reactor area is September 1986.
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* . . .
nis construction was submitted to the NRC as a planned modification in 1983. It was approved in Aug 1984 with the new facility SAR. When complete, these modifications will be shown on a complete set of current as-built drawings. %ey will combine the drawings of the last 20 years, combining the various historical changes and the current modifications into one set of plans. %ese plans will be available in the reactor facility for immediate use by the facility staff as each phase of construction is complete.
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U. S. NUCLEAR REGULATORY C0ftt!SS10N SENIOR REACTOR OPERATOR LICENSE EXAMirMTI(N


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AFRRI believes that the management controls for facility maintenance and
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Facility: AFRRI Reactor Type TRIGA
modifications are adequate to ensure the safety for the reactor and associated ( equipment.
.
Da te Administered:
Examiner: NOEL DVDLEY Candidates ANSWER KEY
: INSTRUCTIONS TO CANDIDATE:
Use separate paper for'the answers. Write on one side only. Staple question  -
sheet on top of the answer sheets. Points for each question are indicated in
,
parentheses after the question. The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours after the examination start Category % of Candidate's % of Value Total Score Cat. Value Cateocry 20 20  H. Reactor Theory 20 20  1. Radioactive Materlaks .
Handling, Disposal,'and **
  , . ,  Hazards 20 20  J. Specific Operating Ch ar ac ter i st ics
      ~
20 20  K. Fue1 Handling and
  . . . ,  g Core Parameters 20 20  L. Administrative Procedures, Conditions, and ,.
Limitations '
100    TOTALS Final Grade %
All. work done on this examination is my own! I have neither given nor received ai Candidate's Signature
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+ .
l r 5. As a last point, item 5 indicates changes made to the answer key used in correcting the exam. It may be interesting to note that a significantly greater number of comments were given to the examiner. Most of these were not included on the comment page. Since they represent, from the facility point of view, incon-sistencies in the exam as written, they should be included in the comment section whether used by the examiner or not.
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1 REACTOR THEORY (20 POINTS) If source is removed when critical at 1 W, a slight positive period will result due to the source having a negative reactivity (about 5 cents)
worth at this power level (source absorbs more neutrons than producing) .
Referenc2: AFRRI Question Bank A.16 P = Poet /T 10' .5 sec = 55.5 sec
    ~
in . E i,
Reference: AFRRI Question Bank A.14 w Total rod worth $9.28 K excess -4.25 Shutdown $5.03 Reference: AFRRI Question Bank Natural convection is caused by the principle that as water is heated it becomes lighter and rises causing flow past the elements - 1.5 pts. The heat removed is equal to mCp (Tto -Tc .75 pt Therefore, as the power is doubled, the heat reSovedttTi-)l w .be double ^ (Ttop-T '
will nearly double and m will increase, but not quite double 73p .b tt{m)
Reference: Basic Fluid Theory / Equation Sheet
      . K excess less (1 pt) due to: heat up of core (because of increase in H O temp) .5 pt . slight buildup of xenon .5 pt Reference: AFRRI Question Bank , cf"
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- tH disadvantage factor. The heatup of the zirconium hydride prevents a neutrons from scattering down to reach thermal energ Doppler broadening. T apparent increase in wW of de resonance capture integrals of. Ugg8causes the loss of neutrons thru resonance captur Density. The thermal expansion causes a loss of moderator effectiveness
  .thereby decreasing the neutrons reaching thermal energ I pt each description 1 pt order t
Reference: AFRRI Question Bank i a. larger b... longer -
Reference: Basic Reactor Theory True  - - - -
      '' True Reference: Basic Reactor Theory Given (delta K) = - 6%, Cf = 50 cps,'Cf = 300 cps
  *
6.=
    .943 / Assumption- (del ta K) = K-1 K = 1-(de ta K)- 1 C 1-K    '
1 2* 50 * 1-K2  -
  {*1-K
    ~


300 1 .943  /
50 057) , y,g *
  ** K,2 = .9905  -
  '(delta K) = ~I =* ~
g- 5
    = .00959 or about 1% S/D /
Reference: AFRRI Reference Package, p. 1 Formula Sheet-
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H.10 Equilibrium todine is proportional to power, while equilibrium xenon is g not.- Therefore, you have a higher ratio of.I to Xe at higher power levels. The greater the I-to Xe ratio, the longer it takes for sufficient .I to decay to Xe such that an equilibrium production and decay of Xe is occurring (i.e., the peak).
Reference: Basic Reactor Theory i
  .H.11 The square of the reactivity inserte Reference: AFRRI Reference Package, p. 1
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- RADIOACTIVE MATERIALS WV4DLING DISPOSAL AND HAZARDS (20 POINTS) Reactor room CAM. Fission product gasses decay to particulate and collect on the CAM filter. R1 would probably not alarm (unless levels are greater than 500 mR/hr). Criticality monitor also would not alarm (unless levels at room are greater than 10 mR/hr) -1p Scram the reactor. Activate emergency pla Isolate are Insure CAM alarm triggered close of dampers. Assess and evaluate situation - 2 pt ;
Reference: AFRR1 Question Bank N It is not the same experiment. There will have to be a new RU . Significant change, Al will activate but short lived so not a large problem if decay.is allowe ' No significant' change as both will evaporate but they are very'
similan chemicall . The capsule will be a very significant change as the gold and silver will activate. Although the gold is practically opaque to neutrons, if the solution is exposed to any flux at all, it will activate. Gold wil1~ ac tivate wi th a high cross sect io . No significant change.- Leave experiment in CET for short lived isotopes to decay of Af terwards use Time / Distance / Shielding when~ working wi th rabbi Have a lead rask nearby as necessar t Reference: AFRRI Question Bank ,  ta  '
I.3 'The diffuser system is a pump mounted on the carriage above the reactor
      ~
tank. The piping of the diffuser system, located on the inside of the core-support structure, passes pool water through an opening in the side approximately 4 feet from the top of the support cylinder. The wa ter, discharged inside the support structure in a tangential direction, causes the water.above the core to swirl. This action breaks up the vapor formations, thereby increasing bubble rise time and reducing the radiation level at the top'of the reactor poei. This system-does not reduce the levels by more than about 25% and it is therefore rarely use .5 pts - description of system 0.5 pts - why not use .
Reference: AFRR1 Hanual 82-1, p. 48
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5 False - measure gamma    ,
Reference: AFRRI Manual 81-1, p. 111 AR-41 - Reactor 0 -15 LINA N -13 LINAC 0.5 for each gas; 1/3 point for each sourc Reference: AFRRI Manual-82-1, p. 139 'It is there to prevent activation of the-12-foot thick concrete biological shield by4hermalizing the fast neutrons and thereby reducing #
the secondary gamma ra91ation emitted from the concrete.-
      .
Reference: AFRRI Manual 82-1, p. 157 The tube has a large "S" bend in i ~''
      -
i Reference:~ AFRRI Manual 82-1, p. 188
- Activity is proportional to lambda, the ' decay constant for the materia = lambd A = Ag e-AE +~(flux)'N (cross section) (1-e' )
    (,
If you double the time a material is irradiated, you will not double the activation. Because it is a LN function. The' lower the lambda (higher the half life), the closer you will come to. almost having a doublin ,
  ~
Reference: AFRRI R'eference Package, '
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* EXP = (2 men)x(150 mrem /hr)x(1 hr)
  .+ (.1)x(3 men)x(5 hrs)x(150 mrem /hr)
  . = 300 mrem + 225 mrem    I
  = 525 mrem ~or .525 Man-Rem b. EXP = (3 men)x(2.5 hrs)x(150 mrem /hr)
  + (.25)x(3 men)x(2.5 hrs)x(150 mrem /hr)'
  = 1125 mrem + 281.25 mrem
  = 1406.25 mrem or 1.40625 Man-Rem ~
Reference ALARA and Shielding / Attenuation Basic Theory
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J.0 ~ SPECIFIC OPERATING CHARACTERISTICS (20 POINTS) If shim up switch is depressed, no change will. occur (in square wave the trans rod will servo, all other rods up, movement' is prevented).
If safe down is depressed, trans will servo out further to compensate since downward movement is allowe Reference: AFRRI Question Bank-A.17
# During any alarm from the primary reactor room CAM, the. positive sealing dampers of the reactor air system will close. .The dampers can also be closed manually. The doors and hatch to the reactor room are sealed with gaskets to prevent air leakage from the reactor roo Reference: AFRRI Question Bank B.21 . HV-loss on fission chamber
  . fast period 3 sec
  . pool water temp 50 C
  .. source level (RWP unless operational channel sees source level neutrons)
  . IKW interlock - no air to trans rod
  . operational calibrate - if operational channel is in any mode-except operat . .
Reference: AFRRI Manual 82-1, pp. - 92-23 AFRRI Question Bank J.18 The upper portion of.the barrel is well ventilated by slotted vents, so the piston moves freely in this range. However, when the- piston is within 2 inches of the bottom of its travel', its movement is restrained Hby a dashpot action of the graded vents in the lower end of the barre This action reduces the bottoming impac ,
      ,
Reference: AFRRI Manual 82-1, p. 27 Safety channel two operates exactly like safety channel one in the -
steady-state modes. In pulse mode, however, the safety channel input is changed so that a separate ion chamber or other detector is placed on
'
the. channel input. This channel reads the peak output on the console recorder blue pen and the energy produced during the pulse on the NVT meter in the right drawer, and supplies the scram signal based on a 110%
current signal from the detector.
:
  ' Reference: AFRRI Manual 82-1, p. 89
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c ~3 watt to 1 MW (ten decades)
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  ~ The lower six decades uses a pulse log-count technique; the upper four decades uses a log campbelling techniqu Reference: AFRRI Manual 82-1, p. 83 A c '. 428 d. 42A-Reference: AFRRI Manual 82-1, p. 70 + 74 The regulating rod has a unique drive motor and drive control circuitr A. tachometer feedback drive motor moves the regulating rod. This system interacts with the servo controller circuit in the control console. The tachometer feedback drive motor is actuated by a variable signal from the output of the servo controller. The tachometer in turn feeds back -
information on its rate and direction of travel to the servo controller circui Reference: AFRRI Manual 82-1, p. 28 To minimize the likelihood of water leaking into the housing if the seal should ruptur Reference: AFRRI Manual 82-1, p. 68
  .
a J.10 'The~ air dampers are spring-loaded with pneumatic solenoids. Air pressure is required to hold them'open; when the air pressure is removed, the dampers spring close Reference: AFRRI Manual 82-1, p. 68 J.11 . It maintains. low electrical conductivity of the reactor coolant to minimize the corrosion of all reactor component . It reduces radioactivity in the water by removing particulates and soluble. impuritie ,
  . It helps to maintain the optical clarity of the wate Reference: AFRRI Manual 82-1, p. 41
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J.12 Both are highly' corrosive agents on the ~ aluminum tank and components
  .(dosimeterscontainsalt).
 
Reference: AFRRI Question Bank, A.19
  ~J.13 The pulse'would terminate and convert to a steady state condition the .
'-
_ power of which would be detenmined by the amount inserted to cause the pulse. For example, a $3.40 pulse would convert to 1 MW steady state run after a few second Reference: AFRRI Question Bank, J.13
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. FUEL HANDLING AND CORE PARAMETERS (20 POINTS) The procedure to-determine a steady state power coefficient of reactivity is as follows:
. Bring the reactor to a cold critical conditio . Bring reactor- critical at desired higher power, measure' and record the worth of control rod used to achieve this level or 2 Using current control rod worth curves, insert a set amoun t of reactivity (by withdrawing a rod to the appropriate ~ position). Plot these values on a curve _ of power vs. reactivity in dollar Reference: AFRRI Exam Bank K.2' True Reference: AFRRI SP 84-2, p. 27 Reference: AFRRI Operating Proced'sres VII, p. 1
      . B--------)5 ~~
    ! '2  i
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Reference: AFRRI Operating Procedure VII, p. 2 o ' visual defects (af ter cleaning) length measurement bow measuremen *
      ..
Reference: AFRRI Operating Procedures, Procedure VII K.6- 2, 4, 4 T-9-t 3,: 1 Reference: AFRRI Operating Procedures, Procedure VII
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. 11 There should be an audible " double click."    -
d Reference: AFRRI Operating' Procedure, TAB B-
  ~
K.8 ~ a' . The-Reactor Facility Director- or the Reactor Operations Supervisor, One other licensed SRO or R Reference: AFRRI Operating Procedure, VII K.9- They are reflector Reference: AFRRI Operations Manual, p. 20    i K.10 Instrumented fuel elements, with three thermocouples each, are located at selected positions in the B and C rings. Generally, the center thermocouple (the one physically located in the center of the fuel section), of the hottest reading element from one B ring and one C ring, is' fed to fuel safety channels one and two, respectively. I'4f5fva r ur icp t.vc car cwice rnewc:ett Mr Snczrto,    ,
Reference: AFRRI Manual 82-1,,p. 89 K.11 Especially if experiment was in CET (usually neg) a pos insertion is made. The position of the CET occupied is then replaced with wate which is a reflector which is also positive worth. Therefore the power  ' -*
would increase unless in servo whereby the reg rod would lowe Reference: AFRRI Question ~ Bank, J.10 K.12 -$5.00  g    4 Reference: AFRRI Operating Procedures, VII
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K.13 As a burnable poison to minimize reactivity changes resulting'from
 
i fission-product buildup and fuel burnu Reference: AFRRI Manual 82-1,'p. 2 K.14 8 - all worths' decrea~se going from B to F. Fca weerre Nt /?ct, D - Nsr Rentt<K Dn Reference: AFRRI Reference Package. -Reactor Parameters
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L .'O ' ADMINISTRATIVE PROCEDURES. CONDITIONS AND LIMITATIONS (20 ' P01NTS)
  :
d . Functional performance check of the transient rod system
      ~
2. Measurement of core excess reactivi ty 3. Check of-the scram function of the high-flux safety channels 4. Check of the fuel temperature scrams 5. Pool water. temperature measured at inlet to the purification system 6.. Channel check of RAMS and CAN Reference: AFRRI Question Bank L.14 L.2- Scram the reactor (if operating)
  . Secure any exposure facilities open or in use Remove the: log book, keys, AFRRI Fire and Emergency Evacuation Information Guide. Carry _them to the Emergency Action Station and g 4,
prepare Oc to M gar L M support AcTCAemergency acch actions as require Reference: .AFRRI Question Bank L.18
    --
  %    _ The reactor is shut down - 1 p m The console key switch is in the "off" position, and the key is removed from the console and is under the control'of a licensed operator, or is stored in a locked storage area - 1 p No work is in progress involving in-core fuel handling or refueling operations, maintenance of the reactor or its control mechanisms, or insertion or withdrawal of in-cor(' experiments, unless sufficient fuel is removed to insure a $0.50 (or greater) shutdown margin with the most reactive control rod removed - 1.5 pt Reference: AFRRI Question Bank AFRRI SP84-2, p. 3 9  & Reactor staff'and any~other person who is designated on the Reactor Access Roste '
      ..
Reference: AFRRI Operating Procedure V
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,    14 . Scram reacto . Secure any. exposure facilities which are in us ~ \
Remove logbook, emergency guide and keys: 'and report to- EA . Do NOT lock reactor area door Reference: AFRRI Operating Procedures VI L.6 ' RED
  . K-excess measurements, to include experiment worth determination .i Actions which affect reactivity: Core movemen Fuel movemen c Control r,od physical removal for maintenanc ' Experiment' loading and removal from the CET, PTS, Pool, or Cor ,
GREEN Reactor malfunction, to include the reactor systems and support
  . equipment taken out of service for maintenance and returned to service. . Additional items entered at the discretion of the operator such as addition of makeup water to the reactor pool, et Reference: AFRRI Ope, rating Procedures, TAB A, p. 2, o a. ~900 KW KW / 15-Matts a cca . sc nc u s%
Reference: AFRRI Operating Procedure, TAB D (b).  *
      *
TAB E (a)
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,    15
    : Emergency Action ' Levels (EAL's). "EAL's" are specific. reactor-related i instrument readings, or observations; radiological dose or dose. rates; or specific contamination levels of airborne, waterborne, or surface-deposited radioactive materials, which relate to the AFRRI Reactor Facility, that are used as thresholds for establishing and achieving emergency classes and initiating appropriate emergenc measures or procedures under this Emergency Plan - 1 p Emergency Classe " Emergency classes" are generally accepted classification labels for accident situations. grouped by severity level for which predetermined emergency measures or procedures have been addressed, considered, or provided .5 pts. The four emergency 'classes are: (1) Notification of Unusual Event;.(2) Alert; '(3) Site Area Emergency; and (4) General Emergency - 1 p Reference: AFRRI Emergency Plan, p. 9 + 35
    . . Director, AFRRI Deputy Director, AFRRI Senior Military Officer present in the AFRRI chain-of comman s Reference: AFRRI Emergency Plan, p. 22 s
L.10 other answers obviously wron Reference: AFRRI Tech Specs, p. 28
  , ..,_  -END of KEY-
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Revision as of 18:02, 18 April 2021

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-170/86-01
ML20215M604
Person / Time
Site: Armed Forces Radiobiology Research Institute
Issue date: 10/23/1986
From: Wenzinger E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Conklin J
ARMED FORCES RADIOBIOLOGICAL RESEARCH INSTITUTE
References
NUDOCS 8611030053
Download: ML20215M604 (2)
v • d • e


Text

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OCT 2 3 E06

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Docket No: 50-170 Defense Nuclear Agency Armed Forces Radiobiology Research Institute ,

ATTN: Colonel James Conklin, MC, USAF l Director Bethesda, Maryland 20014 Gentlemen:

Subject: Inspection No. 50-170/86-01(0L)

This refers to your letter dated April 29, 1986 in response to our letter dated March 5, 1986.

Thank you for informing us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed program.

Your cooperation with us is appreciated.

Sincerely, Origina1 Signed Byr Edward C. Wenzinger, Chief Project Branch No. 3 Division of Reactor Projects cc w/ encl:

M. Moore, Reactor Facility Director Public Document Room (PDR)

Nuclear Safety Information Center (NSIC)

State of Maryland (2)

bcc w/ encl:

DRP Section Chief D. Coe OL File 12.0 Region I Docket Room (with concurrences)

0FFICIAL RECORD COPY OL RL DNA - 0001.0.0 10/15/86 _rgro/

e611030053 e61023 0 g\

PDR ADOCK 05000

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RI:DRP RI: R P kl.RP RI Dudley/bc Kel Kis".!r Elsasser WpMinger 10//6/86 10/ /86 10/ 0/86 10/3./86 10/ /86 app 0FF:CIAL RECORD COPY OL}HLDNA- 0002.0.0 DJ 10/15/86

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DEFENSE NUCLEAR AGENCY ARMEo FORCES RADICBIOLOGY RESEARCH INSilfuTE BETHESDA, MARYLAND 20814 DIR 29 April 1986 01004 United States Nuclear Regulatory Commission Mr. Edward C. Wenizinger Project Branch No. 3 King of Prussia, PA 19406

Dear Sir:

Dis letter is in reply to NRC examination report number 60-170/86-01 conducted by Mr. Noel Dudley on 6 January 1986. Mr. Dudley% report contains statements about the facility that do not accurately describe conditions in the facility. Bis letter is the requested reply describing measures taken to assure reactor safety, services, and fire prevention during the pending construction activities. %c Armed Forces Radiobiology Research Institute's comments concerning the NRC report (#50-170/86-01) are discussed beginning with page 3, number 3, " Summary of NRC comments made at exit interview," followed by license examination report, item number 1, " Summary of generic strengths of deficiencies noted on oral examinations"(see enclosure).

For information on matters discussed in this letter, the point of contact is the Reactor Facility Director, Mr. Mark Moore. He can be reached at the letterhead address or on telephone number (301) 295-1290.

Sincerely yours, l

Enclosure:

as stated {#3 MES J. CONKLIN Colonel, USAF, MC Director 3n ,

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AFRRI COMMENTS ON NRC REPORT 50-170/86-01

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'Ihe following are responses to NRC Examination Report No. 50-170/86-01:

1. In item 3, paragraph 2, Mr. Dudley implies that fire extinguishers within the reactor facility had not been checked for 5 months. 'Ihe day fonowing his visit a survey showed that of the extinguishers in the faculty, one was dated Sept 1985, and one dated Nov 1985. All the rest were dated Dec 1985 (the Jan check had not been completed at the time of the operator's exam). In fact, the longest unchecked span noted on the unit tags was 3 months.1he base (NMCNCR) fire department was in the process of having a special hydrostatic testing done (off base) on all units in AFRRI, not just the reactor, and this would require about 6 months to complete as the testing is accomplished there wul be months shown as not being checked on the tags. ToHow-up checking revealed that1he'two units thateter.

Tudley had seen*8 sert returned from the pool of tested imits and had not been back

'long enough for a date in the regular monthly check. All facility units have been ehoeked and are current.

2. Item 3, paragraph 3, and item 4, paragraph 1, concern the same issue.1he operator licensing examiner viewed areas peripheral to the reactor area (equipment rooms) that were under construction and undergoing removal and installation of equipment, including the drining of concrete and the unpacking and placement of i electrical components. At no time did the Reactor Director state that he had no control over the areas. On the contrary, it was explained to Mr. Dudley that at

that time, the equipment rooms were involved in heavy construction work and as i work progressed, debris would be removed consistent with safe work practices. At no time did the area or materials in the area present any safety hazard to personnel or to the reactor systems. The following week, the areas in question were thoroughly cleaned and prepared for the next phase of construction. It should be noted that earlier and later inspections, including an unannounced operational inspection (No. 50-170/85-03) shortly before and a speelal security inspection shortly after (No Report No. to date) the license exam by operational inspectors have found this facility to have excellent housekeeping over the course of many years. Quoting from Report 50-170/85-03 " Facility tour . . . 'Ihe areas were clean, free of debris and well maintained."

Construction on this facility will continue for approximately 6 months. During this time the reester staff win perform housekeeping inspections en a frequent basis to

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ensure maximum area cleanliness and that construction will not~lmpact the safety ~

' of the reactor or reactor systems.

3. We would like to point out that item 1, paragraph 3 has nothing to do with the exam given to the reactor trainees. Also, it does not indicate generic deficiencies on the part of the trainees. Instead, it is simply an opinion on the part of the examiner.

! 4. Item 3, paragraph 4, and item 4, paragraph 2, again concern the same issue.

l Mr. Dudley has relayed a situation in his report concerning management controls for facility maintenance and modifications that is inaccurate. AB items relating to reactor safety, reactor systems, reactor modifications, and reactor maintenance including records and procedures are current and available in the facility. The examiner, Mr. Dudley, did not ask to see any of these documents. 'Ihe reactor staff has a group of support test equipment, including voltmeters, current meters,

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and electrometers, that are used in reactor calibration. His equipment is sent to

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, an Institute calibration facility and their either calibrated or sent out for calibration. Als is accomplished under Institute procedures, not reactor facility procedures. When the unit is calibrated, it is returned with a calibration sticker in place on the unit. If a unit is out for calibration, a backup unit is always available in the faculty; if the facility does not have a spare unit, one is borrowed from the calibration group. %e records or " tracks" of any reactor system, safety or otherwise, can be readily produced in the faellity, the support equipment records are available in the appropriate area. AFRRI's record of previous inspections both NRC, and independent audit by the Office of the Inspector General, for example 50-170/85-03 Item 5, IG Inspection report, 21 June 1985 and IG Inspection 17 June 1983 TAB G, has shown the maintenance system used in the reactor facility to be more than adequate. his system ensures that the facility maintenance and modifications are performed in a planned manner that guarantees the safety of the reactor and reactor systems.

On the issue of as-built prints available in the facility as referenced in Item 3 paragraph 4, AFRRI contains far more than just a reactor facility. The AFRRI Logistics Department (LOGF) maintairs the building proper and the installed building equipment. Many changes have been made over the last 20 years. These changes are documented on building prints located in the LOGF office. However, because of the large mass of documentation, locating a particular item can

'sometimes be difficult for a newly licensed operator. AFRRI construction,

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primarily on the facility air and ventilation system, is being conducted in phases.

A complete set of building plans is available as each phase of construction is completed. The scheduled completion date for the reactor area is September 1986.

nis construction was submitted to the NRC as a planned modification in 1983. It was approved in Aug 1984 with the new facility SAR. When complete, these modifications will be shown on a complete set of current as-built drawings. %ey will combine the drawings of the last 20 years, combining the various historical changes and the current modifications into one set of plans. %ese plans will be available in the reactor facility for immediate use by the facility staff as each phase of construction is complete.

AFRRI believes that the management controls for facility maintenance and

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modifications are adequate to ensure the safety for the reactor and associated ( equipment.

l r 5. As a last point, item 5 indicates changes made to the answer key used in correcting the exam. It may be interesting to note that a significantly greater number of comments were given to the examiner. Most of these were not included on the comment page. Since they represent, from the facility point of view, incon-sistencies in the exam as written, they should be included in the comment section whether used by the examiner or not.

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