ML20054C682
| ML20054C682 | |
| Person / Time | |
|---|---|
| Site: | 05000142 |
| Issue date: | 04/08/1982 |
| From: | Kathren R Battelle Memorial Institute, PACIFIC NORTHWEST NATION, NRC COMMISSION (OCM) |
| To: | |
| Shared Package | |
| ML20054C649 | List: |
| References | |
| NUDOCS 8204210498 | |
| Download: ML20054C682 (10) | |
Text
,
UNITED STATES OF AMERICA NUCLEAR REGULATORY COPMISSION l
BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
4 Docket No. 50-142 i
THE REGENTS OF THE UNIVERSITY OF CALIFORNIA (Proposed Renewal of Facility License)
(UCLA Research Reactor)
AFFIDAVIT OF RONALD L. KATHREN i
TI,iBonald 1.. Kathren, do hereby depose and state:
1)
I am a staff scientist employed by Battelle, Pacific Northwest Laboratory in the Occupational and Environmental Protection Department. A statement of nty professional qualifications is attached to this affidavit.
2)
I have read " Interrogatories To S. C. Hawley, R. L. Kathren and M. A. Robkin As To ' Analysis of Credible Accidents for Argor.aut Reactors' NUREG/CR-2079 PNL-3691". The responses that follow explain I
or interpret the research or results from NUREG/CR-2079, of which I was a principal author and which is based on research at the Pacific Northwest Laboratory operated by Battelle Memorial Institute. My i
responses are numbered to correspond to selected interrogatories.
l 3.
Examination of the references listed on pages 53-55 of the report will show the specific works used; by referring to the dates of these works, it can be readily be ascertained which of these have been published since the late 1950's. Numerous others were, of course, also consulted.
In addition, the lack of reported serious or otherwise significant operational accidents at Argonaut reactors, 8204210498 820419 PDR ADOCK 05000142 O
coupled with the evolving safety and radiation protection philosophy during the more than two decades since the initial Argonaut SARs were prepared, were applied to the preparation of this report.
21.
The prompt neutron lifetime is affected by all processes which slow down the fission energy neutrons to thermal energy, and by the average diffusion time.
29.
The credibility and analysis of a graphite fire is covered on pages 30-43; the final paragraph on page 43 stanmarizes the graphite fire analysis, and concludes "...it appears unlikely that any graphite e
fire that did get started would burn long enough to put the fuel at risk."
.34.
There are other forms of the so called inhour equation.
Perhaps the true or most rigorous form is 6
8 1
9 I~I
+ ^I P
Ih =
6 8
1 9
7666+j,1 1 + 3600 A 1
4 i
which is relatively complex and ctsnbersome, ard is used to calculate Ih, the reactivity in inhours. Other forms or equations known as the inhour equation include 6
8 1
4
" h 1,1 1+A T
i which gives a close approximation of the relationship between reactivity and stable (rather than prompt) period, and
6 wS P " T + gh w + j el Aj which relates the parameter w to the properties of the reactor.
Yet another form is p=p (1 + 6 T) which relates inverse reactor period (p) to other operating parameters and is usually used with long periods.
The version used in the report is the most applicable end. direct form, consierbg only prompt neutrons.
50.' The determination of temperature rise is a difficult and complex matter, and the precise minimal safety margin is, among other things, determined by the asstnptions made.
Since these assumptions are not exact, but indeed deliberately conservative, there is a built-in i
tendency, as it were, to err on the side of safety.
Based on this particular situation, which includes consideration of the additional energy required to raise the temperature of the fuel, t
l as well as the conservatism of the assumptions and uncertainty of the l
empirical data cited, the minimal safety margin might reasonably be taken to be on the order of 20 below the fuel meat melting point.
l 53.
A stepwise insertion of 2.6% Ak/k will simply not provide enough l {
energy to cause significant physical disruption of the flooded Argonaut core.
i l 5 i
67.
The initial paragraph in the section entitled " Core-Crushing Accident" clearly implies that a core-crushing accident is not credible because of the presence of shielding blocks.
Thus, there is no j
contradiction.
Note that this does not preclude development of 1
various core-crushing accident scenarios.
&nce, the concluding l
l l
statement of the section entitled " Core-Crushing Accident" was included to enable the consequences of such scenarios to be readily determined, if desired.
Also note that the whole body dose equivalent should be 0.066 rem, rather than 2 rem, as noted in the errata to the report.
91.
The x/Q value of 10-2 was selected as being the maximum credible value; the downwind distance at which this value might occur is site and time specific.
The report assumed that this value to occur at the location of a downwind observer irrespective of the distance '
. hat observer. from.the point of release.
I zSECTION II B(1).: A current resume and statement of professional qualifications for R. L. Kathren are attached to this affidavit.
l B(2).
Af filiate Assistant Professor of Radiological Sciences, University of Washington, Joint Center for Graduate Study, Richland,1978 to date; Coordinator in Radiological Sciences, Joint Center for Graduate Study, Richland,1980 to date.
Have also given occasional lectures / seminars at the University of Washington, Seattle, in Radiological Sciences and i
Environmental &alth classes and have taught continuing education I
classes through Joint Center for Graduate Study, Richland.
B(3).
See 3(2) above.
B(4). My professional acquaintances and associations are many, and I am unaware of the specific background experience of each nor am I cognizant of the current or past staff of the five Argonaut facilities.
Needless to say, I am acquainted with some members of the staff at the University of Washington Argonaut reactor.
If specific names of interest are provided, I will endeavor to accurately identify the nature of my association with each.
l 1
l ll
B(5).
I am not certain as to precisely what information is being requested, and request clarification of this question.
B(6).
No.
B(7).
No.
B(8).
While I did not personally perform all of the calculations or research used in this report, I have nonetheless reviewed the document and find nothing illogical or unreasonable. Thus, I endorse the report as written, with the erreta dated July 21 1981, and the correction of j
the typographical errors on page 39, line 10, fifth word ("present,"
I rather than " prevent") and en.page.43, line 3, which.should read
...Since the open..." rather. than "... Since opening..." and on page 19, lines 13 and 16, which should read ".. 54 C... rather than
.. 74 C...".
l B(9).
No.
B(10).
Yes, with errata dated July 21, 1981.
B(11).
No, but this seems redundant with regard to question 10.
l B(12).
The number of potentially credible accident scenarios is limitless; the report focuses on generic rather than specific accidents, and evaluates " worst case" credible accidents.
I t
B(13).
See B(12).
I B(14).
No.
B(15).
No.
1 l
t I
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t
3)
I hereby certify that the preceding information based on research conducted in connection with NUREG/CR-2029 is true and correct to the best of my knowledge and belief.
f
?!K Ronald L. Kathren Subscribed and sworn before me on this 2
day of April 1982.
4#_
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RONALD L. KATHREN Professional Qualifications My name is Ronald L. Kathren.
I am Staff Scientist Occupational and Environmental Protection Department of Battelle, Pacific Northwest Laboratory, Richland, Washington.
In addition, I serve as Affiliate Assistant Professor of Radiological Sciences and Program Coordinator in Radiological Sciences at the Joint Center for Graduate Study in Richland Washington.
t I was awarded the Bachelor of Science degree from the thiversity of California, i.es,Mgeles,in 1%7, end the Master of Science from the l
University of Pittsburgh in 1962.
In addition, I have taken extension
{
courseert through:the thiversity of California, Berkeley, sporadically during the 1%0's.
My professional experience includes two years as a health physicist at Mare Island Naval Shipyard (1959-1961) and five years at the Lawrence Radiation Laboratory at the University of California (1962-1967)..In 1967, I joined Battelle-Northwest serving as section manager and senior research scientist largely working in the area of radiation dosimetry and instrumentation.
For six years I served as corporate nealth physicist to Portland General Electric Company, rejoining Battelle in 1978.
I am a member of the Health Physics Society, having served on the Board of Directors of that organization, the Anerican Association of Physicists in Medicine, Anerican Association for Advancement of Science, Anerican Academy of l!
Environmental Engineers, and Anrican Nuclear Society where I serve as a member of Executive Council of the Radiation Protection and Shielding i
Division.
In 1966, I was certified by the Anerican Board of Italth Physics, and am now a member of that Board.
I have been a licensed Senior Reactor Operator (TRIGA), and am a registered professional engineer in the State of California.
I have also been a consultant to the USNRC with regard to the Three Mile Island Accident.
RONALD L. KATHREN, Staff Scientist, Occupational & Environmental Protection Department Education B.S., University of California, Los Angeles 1957 M.S., University of Pittsburgh 1962 Additional Study, University of California, Berkeley, 1960-1961 Extension 1962-1964 Experience Mr. Kathren has more than 20 years of broad experience in health physics and related areas
'He originally joined Battelle-Ibrthwest'in.1967, serving first as a section manager and then as senior research scientist with responsibilities in the areas of radiological'. calibration and standardization,
. instrumentation, and radiation. dosimetry. :Following six years as 1 corporate
-health physicist to Portland General Electric Company, he rejoined Battelle-Northwest in 1978 as staff scientist with broad responsibilities in the areas of health physics, dosimetry, and reactor safety.
His other special interests include education and training and the historical aspects of radiation protection.
His prior experience five years as a health physicist at Lawrence Livermore Laboratory of the University of California, where he was involved in a variety of applied health physics research activities, and two years as supervisory health physicist at Mare Island Naval Shipyard where he was responsible for the dosimetry program and environmental monitoring.
Mr. Kathren is a member of the faculty of the University of Washington at the Joint Center for Graduate Study, and also served on the adjunct faculty of Oregon State University.
From 1973-1978, he served as health physicist to Reed College.
In 1977 he received the Elda Anderson Award for outstanding contributions to the science and are of health physics and has been elected to the Anerican Academy of Environmental Engineers.
He is certified by the Anerican Board of fealth Physics, and as a registered professional engineer.
Mr. Kathren is an active member of the Health Physics Society, Anerican Nuclear Society, Anerican Association for Advancement of Science, and Anerican Association of Physicists in Medicine.
Publications Mr. Kathren has authored or coauthored more than 50 scientific journal articles and book chapters, the book Fbalth Physics:
A Backward Glance, many technical reports, several miscellaneous popular articles, and three curriculum texts for technicians, Nuclear Safety, Reactor Physics, and Radiation Detection and Measurements.
He has been an editor of the scientific
journal, Walth Physics and is currently a member of the advisory panel to the
&ndbook of Radiation Protection and Measurement.
Professional Associations Walth Physics Society - Board of Directors (1973-1976); President, Columbia Chapter (1971); Chairman, History Committee (1969-1974); Chairman, Subcommittee on Walth Physics Technicians (1968-1970); Member, M tbc Committee on X-Ray Protocol (1973-1975); Society Historian (19747
)
Anerican Association on Physicists in Medicine--1962 Anerican Association for Mvancement of Science--1962 American Nuclear. Society--1972; Divisional Executive Comittee--(1980-1983)
Oregon Acadenty of Science--1972-1978 (Executive Council 1976-1977).
Licenses andr Certifications Certified Walth Physicist, Anerican Board of Walth Physics--1966 Licensed Professional Engineer, California--1975 Senior Reactor Operator, USNRC (TRIGA MK I)--1977-1981 Diplomate, Anerican kademy of Environmental Engineers--1978 Awards and ibnors Elda E. Anderson Award--1977 U.S. Public &alth Service Fellow (Radiological Walth), University of Pittsburgh (1961-1962)
U.S. Delegate, Second, Third, and Fif th International Congress on Radiation Protection--1970,1973, and 1980 Academic Appointments Instructor in Radiation Technology, Chabot College (California)--1966-1967; Columbia Basin College--1967-1968 Lecturer, Joint Center for Graduate Study, University of Washington--1971-1972 Mjunct Professor, Oregon State Division of Continuing Education--1973-1978 lbalth Physicist, Reed College--1973-1978 Af filiate Assistant Professor, University of Washington, Joint Center for Graduate Study--1978; Coordinator, Radiological Sciences,1980-l
J Professional Activities Anerican Board of Health Physics,1982-
- Member of Panel of Examiners--
1978-1981 Editor, fealth Physics--1976-1980 Abstractor, Chemical Abstracts--1962-1978 Oregon Radiation Advisory Committee--1977-1978 Member, Joint Subcommittee N13/42--1968-1980; Anerican National Standards Institute N41--1971-Portland Chamber of Commerce Environmental Standards Committee--1972; Chairman, Subcomittee of mise--1975-1978; Energy Comittee--1974-1979.
Dregon Department of Environmental Quality, Commercial and Industrial hise Afvisory.0munittee-1974 U.S. Atomic Energy Commission, Traineeship Advisory Committee--1973-1974 Member, National Advisory Committee on Nuclear Technicians, Technical Education Research Center--1975-1980 Radiation Technology Advisory Committee, Columbia Basin College--1967-1968 Member, Special Panel on Three Mile Island Unit 2 Radiation Protection Program, U.S. Nuclear Regulatory Ccomission--1979 Consultant, Nuclear Regulatory Commission Special Inquiry Group (Rogovin Commission), Three Mile Island--1979 Consul tant, Advisory Committee on Reactor Safeguards--1979-U.S. Expert, International Atomic Energy Agency, Regional Conference on Radiological and Environmental Protection in Nuclear Facilities, Caracas--1977 i
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Walter F. Wegst, Director, Research & Occupational Saf+
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NRC Investigation of Manipulation of Reactor Controit
Subject:
by Nonlicensed persons.
This refers to the investigation conducted by Messrs 0. C. Shackleton Jr., and A.D. Johnson of this office on June 10, 1961, of activities authorized by NRC License No. R-71 and to the discussion of our finc.
ings held by Mr. Johnson with Mr. Ostrander and other members of your staf f at the conclusion of the investigation.
Areas examined during this investigation are described in the enclosed investigation report. Within these areas, tne inves'.iq.ition consis'er of selective examination of records, interviews with perscnr,I a r.c observations by the investigators.
We have evaluated the circumstances and management controls that existed in the past wherein high school and other students had been permitted to manipulate the switch controlling movement of a reactor contrsl blece.
l We have concluded that your actions may et be in strict compliance with NRC rules and -egulations. The provisions of 10 CFR 50.54(1), 55.9 anu i
l 55.4(d), which.'oly to these circumstances are subject to differing interpretation..ianipulations of a reactor control blade by individuals not exempt under 10 CFR 55.9 with only general supervision but without i
direct specific instructions from a licensed operator would be deemed a clear violation of NRC rules. We recognize that specific direction to the high school students was providea by a licensed operator in the programs you have conducted in the past and aiscontinued about 1 1/2 Nevertheless, to assure strict compliance with NRC rules and years ago.
l regulations, we believe you should seek NRC approval for your educational or other programs wherein unlicensed incividuals may manipulate reactar controls under '.he direction of licensec personnel anc nay not be spec t-f'cally exems't pursuant to 10 CFR 55.9.
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4 If this report contains any information i
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tr.at >ou believe to be exer.pt from disclosure under 10 0FP 9.J(a)(C.. It is n cessary that you (a) notify this office by telephone within t(r (1:,) ocys f rom the date of this letter of your intention to file a reau. cst for withholding; and (b) sutunit within 25 days from the date of this li tter a written application to this office to withhold such If you-receipt of tesis letter ees.been delayea such taat less it,ar. seven (7) days are available for your review, please notify inf cn ation.
Cim-tnis.-
- tite promptly so that a new due date aty be established.. esty.such sistent.<with secth.2.790(b)(1)bwner of the infomation which identifies I
by an affidavit executed by:thethe aucuc=nt or part sought.to be withheld,
' statement of the basis on which it! is claimed that the infomation 4'
This secties further requires should be withheld from pubite disclosure.
the statement to address with specificity the considerations listed in 10CFR2.790(b)(4). The infomation sought to be withheld shall be incorporated as far as possible into a separate part of the affidavit.
If we ao not hear from you in this regarc within the specified periods noted above, the report will be placed in the Public Decament Room.
Snoulu you have any questions concerning this investigation, we.till be glad to oiscuss them with you.
f Sincerely.
Original signed by i
R. D. Johnson A. D. Johnson Director. Enforcement and Investigations
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A.D.Johnso Director Enforceme
& Investigations Suma ry :
Investigation on June 10, 1981, Report No. 50-142/81-01 Area Investigated: Nonroutine ant.unced Investigation of circumstances surrounding manipulation of the control of the reactor regulating blade by unlicensed science students not enrolled in nuclear engineering courses and by Utility Company personnel in training for Operator licensees for nuclear power plants. The investigation involved 12 investigator hours on site by two investigators.
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- N. Ostrander, Manaaee. h iear incr iv L
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- A. Zane, Reactor wper,iser tal c' W. Parker, Assistant Chief Engineci. Ih,'i Evraets UCLA Radiation Safety Offices 1
. Sime, Peactor Operator
' Denotes those attending the exit interview.
rpl,lo g of Inspect _or identified items 2.
During inspection 50-142/80-02, it was observed that the lisensee f'
Pre-Startup Check Off Sheet did not fully check the area radiatiot.
The inspector verified that the Prestartup Check Off %eet
'was revised to ensure that the Area Radiation Monitors, including cnonitors.
Item 80-02-0; the detectors, are verified operable before each Startup.
is closed.
The inspector examined the corrective actions taken by the licensee in response to an item of noncompliance identified duri 50-142/80-02 The inspector examined the licensee's " Procedures to a dropped rod. Delineate Operator Actions," for " Failure of a Reacto and for " Uncontrolled Reactivity Changes."
the item of noncompilance and corrective actions identified in thet Itcensee's letter of March 29, 1980, actions had been taken.
Item 80-02-02 is closed.
l 50-142/80-02 it was observed that the Failed Rabbit During inspection procedure was an61guous in that it did not identify whether or not The inspector a cracked rabbit cap was considered a failed rabbit.
examined the licensce's revised failed rabbit procedure to verify Item 80-02-93 is closed.
that it was more explicit for operators.
50-142/80-02, it was observed that the licensee's During inspectionsurveillance of neutron channels occurred 13 months apa 1978 to January 9,1980) as opposed to the 12 months written in the Based on an examination of the licensee's
'echr.ical Specifications.
and followup corrective actions, letter response dated March 20, 1980, the inspector concluded that the licensee had taken appropriate correc Item 80-02-04 is closed.
,yactions.
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nriectiveacti6ns'
. hing insen tion 53-142/O-02, it an ob;ersed thatof the "abnomal o 6
'M f>e taken as a resul thd not been completed. The inspector veriffed on Dececoer 19. 1779, that the Radiation Use. Corr'ittee had evaluated and accepted the changas and that these changes (i.e., automatic scram if th i !c alarm if any inhibit signal occu ; during operation) were comp!M. t Iten 80-02-05 is closed.
',a items of noncompliance or deviations were identifie f Ini,lpyyp on Licensee Reportable item 3.
An " abnormal occurrence" (as defined by -t!CLA Tectmica took place on JanuaryThe inspector examined the circumstances surroundin; January 26, 1981).
the event and corrective actions taken or planned by the licensee.
Based on discussions with licensee personnel and examination of a records, the inspector detemined that the licensee's corrective action dition.
were adequate and that the reactor was malt,tained in a safe con No items of noncompliance or deviations were identified.
O ganization, to g and Records i
4 Mr. Jack Horner, the former Health Physicist (HP), has lef t the org Two senine Mr. Bob Reyes was acting HP at the time of the inspe 1
license were granted since the previous inspection.
I The records of operations for the period since the last inspec (March, 1980) were examined.
procedures, the reactor operator log, pre-startup checklists, and maint The data of the 1980 Annual Report was also and calibration togs.
confirmed.
No items of noncorpliance or deviations were identified.
5.
Sy,r ve,111 ant,e, The inspector examed selected surveillance records and discussedSu
?.these surveillances with licensee personnel. rod worth,
$alibration of neutron instruments, and calibration of primary and tacluded:
g secondary flow meters.
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i e. ac(brMance witti W CD 2.790 of the Consnission's regulattoi.s. a copy hp~i of this letter or.; trie erslosed investigatlan report will be placec in the 'J ' 's Public Document Room.
If this report tor.tains any information believe to be exer.pt from disclosure under 10 0FP C.J(a)(4',. It l l tr.a t nu is ntcetsary ti.at you (a) notify this office by telephone within te' f
(lu) acys f rom the date of this letter of your intention to file a for withholding; and (b) submit within 25 days from the date of rego.st this letter a written application to this office to withhold such infor attan.
If you receipt of this letter has been delayeo o;ch taat less tt.ai seven (7) days are available for your review, pleest notify I
this
- rice promptly so that a new due date any be estah116hed. Con -
sistent with section 2.7!,0(b)(1), any such application must be accompaniec
,by an offidavit_ executed by the gemer of the infomation which;14entifies the aucument or' part sought to be withheld, and which contains a full staterent o,f the basis on which it is claimed that the infomation should be withheld from public disclosure. This section further requires the statment to address with specificity the considerations listed in 10CFR2.790(b)(4). The infomation sought to be withheld shall be incorporated as far as possible into a separate part of the affidavit.
If we ao not hear from you in this regara within the specified periods noteo above, the report will be placed in the Public Document Room.
Snoulu you have any questions concerning this investigar1or., we.till be glaa to oiscuss then: with yoa.
Sincerely.
i Original signed by f
R. D. Johnson A. D. Johnson Director. Enforcement and Investigations u %, o a ttactsNnt ur. 1. Ca tt on, Direc tor, hlL. UCLA
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Investigation on June 10, 1981, Report No. 50-142/81-01 Area Investigated: Nonroutine ant.unced Investigation of circumstances surrounding manipulation of the control of the reactor regulating blade by unlicensed science students not enrolled in nuclear engineering courses and by Utility Company personnel in training for Operator licensees for nuclear power plants. The investigation involved 12 investigator hours on site by two investigators.
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Mr. N. Ostrander, Manager, NH Hr. A. lane, Reactor Supervuoi Mr. C. Ashbaugh Senior Operator Mr. W. Comier, Counselor,-At-Law l
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Ba c,kground.
Region V staff members were made aware that during the current licensing proceeding before the Ator.ic Safety and Licensing Board for the relicensing of the research reactor at UCLA. the intervenor.
Caiunittee sto tridoe the Gap, propounded.1nterrogatories,deted April
~
i 470, 1981, concerning operation of the reactor by unlicensed individuals.
'The licensee responses to the interrogatories affirmed that unlicensed individuals had manipulated the reactor controls. The pertinent interrogatories and licensee response follow:
In.terrona tory "54.
On page 16 of the NEL Annual (Specialized Activity) Report for 1976 it is indicated that a group of students from Culver City High School were able to come to UCLA to individually operate and observe the UCL A reactor....
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"c. Did any of these visitors with or without supervision, manipulate l
the controls of the reactor during this visit...
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"Yes I
i "e.
If the answer to c. is yes, precisely which controls were manipulated and precisely which reactor operations were nanipulated.
If power or reactivity was altered by the I
visitor, plea n specify the range of alteration...
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" control rods were manipulated.
See the operatino logs and strip charts.
"j. Please specify the age and educational background in nuclear
,f engineering for each visitor who operated the reactor...
. rt Responge j u "A,e 16 to 18 vears, hich school physics students with previaus orienta-tien in nuclear reactor physics."
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'.to.l.-nts f ron Culver City liigh Schoci manipula ted the...-
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conte (l', did not constitute unlicensed operation?
If so, please.
reactor in Applicant's possession which support such a conteeg.,
det941 all fe t,
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Response
f "Yes; in all cases applicant's licensed reactor operator is dom ' t-have operated the controls of the reactor.'
In vie w of the above, the investigators visited the subject facility on fune 10, 1981, to obtain the facts and ciremstances relatinq tc manipula-tion of reactor controls.by unlicensed persons.
4 3.
_ Manipulation of,_ Reactor Control by unlicensed persons.
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'According to the licensee representatives, one of the primary purposes of the reactor at UCLA is for u:e as an education tool to s interest students and teach them the principles of nuclear physics.
1 engineering, reactor operation, and associated subjects.
To further this purpose, the licensee explained that the university cooperates with other colleges in the area by providing instruction at the laboratory in the control of radiation, and the theories and principles associated with the controls of nuclear reactors. In addition, instruction had been provided to amployees of utilities that were in training for reactor operator licenses for nuclear power plants.
Also, to encourage high school students studing physics and interested in nuclear energy, the Licensee had provided a half day indoctrination type tour where these special students received lectures in control of radioactive waste, radiation, and reactor operations.
As a part of the instruction given to the special students the instructor, an NRC senior licensed operator, demons '
how the reactor power level was increased and decreased by tienj each student to sit at the reactor control opnsole while the reactor was operating. Af ter cuestioning and receiving appedpr(ate answers f rari the student on how to increase and decrease the power level, the instructor would direct the student to depress the appropirate spring return switch to either withdraw or insert the reactor control blade. Upon reaching a predetemined rod position the instructor would direct the student to release the contrt i switch.
Af ter completing the foregoing exercise the student would then discuss what had occurred.
Each student was thereaf ter given the opportunity to manipulate the control switch for the control blade According to the instructor.
I. In the foregoinq described manner.
. the individuals, especially the high school physics students, had k participated in the exercise with enthusiasm.
4 N
9 l
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L
-S.
'he recor<1 of reactor operations were examined for the years of *e' 1977 thru 1981 to the date of the investigation.
Entries in the.
ifeconis show that the most recent hi h school igs c" ass persi c
eenipulate the reactor control b1 tes on
-58,h979.
The I
". icedsee representative stated that practics s discontinued a
t la early 1980 when questions arose withis Muclear Energy Laboratory as to whether the$he s of the UCLA l
pr of $11 ewing high school students to manipulate the castrwl 4th was la com-I p11ance with NRC rules and regulation. The tor / Instructor contended that the provisions of M CFR ES.4(d) the practice. Other members of the staff agtted, masset of what NRC's interpretation of the provision mouM 10 CFR 55.4(d).
the provision relied on iqy the Senter% tor
" Operator is asty individual aho manipulates a control of a facility. An individual..isvdamsed tosmelpstate a control if 5,
(tie 49fects?anotherito annipulate a control."
4 Exit Interview The Investigators met with Nessrs Ostrander Zane and Cormier at the conclusion of the fewestigation to discuss:the'seg e findings of the investigation Itceasee ta)i that the prDgram involv' high S 1 IAqysic 5 e
insti-tuted until the 1
of $6e up
.ppsfj y
investigators fadi ted ths11 s pre Ivfag utility personnel and s ts fem ether colid es das universities I
appeared to be pemitted by the provisions of IU CFR 55.9 Exemption from License.
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.,=
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISS1014 BEFORE THE AT0!i!C SAFETY AND LICENSING BOARD In the Matter of
)
Docket Ho. 50-142 THE REGENTS OF THE UNIVERSITY 0F
)
CALIFORHIA
)
Proposed Renewal of Facility
)
License)
(UCLA Research Reactor)
)
, CERTIFICATE OF SERVICE
~.I hergby certify that copies of "NRC Staff Supplemental Response to Intervenor's Interrogatories" in the above-captioned proceeding have been served on the following through deposit in the Nuclear Regulatory Commission's internal mail system, this 19th day of April, 1982:
John H. Frye, III, Chairman Mr. John Bay Administrative Judge 3755 Divisadero #203 Atomic Safety and Licensing Board San Francisco, CA '94123 U.S. Nuclear Regulatory Comission Washington, DC 20555 Christine Helwick, Esq.
Glenn R. Woods, Esq.
Dr. Emmeth A. Luebke*
Office of General Counsel Administrative Judge 2200 University Avenue Atomic Safety and Licensing Board 590 University Hall i
U.S. Nuclear Regulatory Conaission Berkeley, CA 94720 Washington, DC 20565 Roger Holt, Esq.
Dr. Uscar H. Paris
- Office of City Attorney Adiainistrative Judge 200 North Main Street Atomic Safety and Licensing Board City Hall East, Room 1700 i
U.S. Nuclear Regulatory Conaission Los Angeles, CA 90012 Washington, DC 20555 l
Daniel Hirsch i
Mr. Daniel Hirsch Box 686 l
Committee to Bridge the Gap Ben Lomond, CA 95005 1637 Butler Avenue, #203 Los Angeles, CA 90025 William H. Cormier, Esq.
Office of Administrative Vice Chancellor University of California at Atomic Safety and Licensing Board Los Angeles Panel
- 405 Hilgard Avenue U.S. Nuclear Regulatory Comission Los Angeles, CA 90024 Washington, DC 20555
.,e Atomic Safety and Licensing Appeal Panel (5)
U.S. Nuclear Regulatory Comission Washington, DC 205SS Docketing and Service Section ( )*
Office of the Secretary U.S. Nuclear Regulatory Cocnission Washington, DC 20556
/,Y d4 tolleen P. Woodhead Counsel for NRC Staff