IR 05000116/1978004
| ML19282B241 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 01/12/1979 |
| From: | Dubry N, Fisher W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19282B232 | List: |
| References | |
| 50-116-78-04, 50-116-78-4, NUDOCS 7903120025 | |
| Download: ML19282B241 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
50-116/78-04 Report No.
License No. R-59 Docket No. 50-116 Iowa State University Department of Nuclear Engineering Licensee:
Ames, Iowa 50010 UTR-10 Training and Research Reactor Facility Name:
Iowa Iowa State University, Ames, Inspection At:
12-13, 1978 December Inspection Conducted:
!.2 h ~ ~ < y N7)
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N. E. DuBry Inspector:
/ / /2 /b['/,
W. L.' Fisher, Chief
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Approved By:
Fuel Facility Projects and Radiation Support Section Inspection Summary :
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50-116/78-04)
12-13, 1978 (Report No.
Inspection on December d rad-Routine, unannounced radiation protection anfacilities Areas _ Inspected:
fications inspection, including: releases; solid radioactive waste; q waste management otection procedures; radioactive effluent and training; licensee audits; radiation prexposure control; posting, label d
instruments and equipment; d notifications and reports.
i by one NRC inspe; tor.
control; materials control; surveys; an The inspection involved 12 inspector-hours ons teNo d tified.
_Results:
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DETAILS Persons Contacted
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- Emery E. Sobottka, Radiation Safety Of ficerChairman, Radiation d of Nuclear Engineering
- Dr. Adolph F. Voight,
- Dr. George Burnet, Department HeaDr. Richard A. He i
James F. Hrabak, Health Physics TechnicianRic
- denotes those present at the exit interview 2.
General rvation of the reactor b
This inspection, which began with a visual o se11:00 a.m. on Lecem facility and health physics counting room at ement and radiation 1978, was conducted to examine the radwaste managthe U A
Reactor.
protection programs atdetailed tour of the facility was conducted o Records and Safety Officer.
contacting Mr. E. E. Sobottka, Radiationlogs we d radiation areaand monitors were found to have had timely caHousekeeping appears to be goo functional tests as required.
Facilities and Equipment is by entry through
Access to the Nuclear Engineering Laboratorytransfer door which ipment one of three doors, one of which is an equ The other two personnel d
is shut and locked unless use is require.
and 5:00 p.m.
doors were found to be open only between 8:00 a.m.f two doors Entry to the reactor facility is through one oDosimeter and entry info combination lock mechanism.The Radiation Area Monitor (RAM) wasHousekee recorded in a log book.found operable and with the proper i
was good.
identified.
No items of noncompliance or deviations were i
0,rganization,Aalification, and Train n_g t of Chemical Engineering 4.
r responsibility for the l'TR-10 A recent change, which divided the Departmen and Nuclear Engineering, now places t ef Nuclear Engineering, of h
reactor program with the Department o Dr. Richard Hendrickson is the is the Department Head.
Dr. G. Burnet Reactor Supervisor.
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ible for all uses The Radiation Safety Committee (RSC) is respons Dr. Adolf Voight mpus.
of radiation and radioactive material on caNo recent changes in staffing is the chairman of this committee.
diological Services Group or organization have occu.r ed in the Ra i n service This group is responsible for radiation pr SO compose (RSG).
on campus.
the RSG, which operates within the and Safety.
d to be qualified d
Those responsible for radiation safety are ju geThe RSO holds inform The ide on-going training.
by training and lengthy experience.with the Radiological S Interviews i
technicians also attend off-site train ngt d that e.acuation seminars with the Health Physics personnel indica ell personnel working in and tests are conducted quarterly; also, asion covering health physics.
the building attend an annual review ses d
tified.
No items of noncomplian:e or deviations were i en Licensee Audits hensive semi-5.
The Reactor Safety Subcommittee performs a compred reactor opera The annual audit of the UTR-10 facilities an followup action is d that minutes of the two 1978 meetings revealebeing ta h the audit.
ified.
No items of noncompliance or deviations were ident Radiation Protection Procedures ion required to have formalized radiation protect 6.
of The licensee is notProcedures of a general type, which include area radiation protection, are contained in the Ra This manual has rules procedurcs.
Radiation Safety Manual, revised January 19 dioactive material at ISU.
being reviewed by The proposed Reactor Technical Specifications, h ISU license.
NRC licensing, have not been impicmented i ding renewal in October 1979.
d tified.
No items of noncompliance or deviations were i en i
t
_I_nstruments and Equ pmen d calibrated survey 7.
The licensee 1ts an adequate number of operable anfficient typ Survey meters and monitoring equipment of su
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diation levels are cali-meters used to measure gamma and neutron ra i
The licensee has recently changed to a radiat o brated quarterly.
area monitoring (RAM) system, manufacture Alarm and trip detectors.
which consists of five ha, logen quench 1:00 p.m., and calibrations functions are performed each Wednesday at are donc quarterly.
during the inspection A review of the records and ooservat.ons made deviatione.
revealed neither items of noncompliance nor Exposure Control Services, Inc. is used 8.
Monthly film badge service from Health PhysicsRecords we 78 to 10 mrers.
by the licensee. Monthly beta-gamma doses are generally less than The maximum dose, according to film hadge recorof which 70 mrens wa present.
associated with the reactor was 203 mrems,A major portion of the individu nt calibrations.
attributed to neutrons.
are due to sealed source checks and instrume 9.
ALARA s a member of i
To minimize personal exposure, the licensee requ repotential radia i
the Radiological Services Group to mon torThe licensee also has a t An example of the exposure situations.
procedure for sample irradiation requests. proce 1978 h July-August material activation.
Radioactive Effluent Releases and Solid Radwaste is argon-41.
10.
The only gaseous waste identified by the licensee 77, to September Reactor power generation from October 1, 19 Based on 1978, was 100.8 KWh.
power as related to measured concentrations, Releases a this facility.
was released.
there is no ventilation system at Liquid losses released from this facility.A monthly four-lite No radioactive liquid is lpha are from evaporation and sampling.is evaporated to dryness and c The concentration range from reactor coolant 6.8E-9 pCi/ml gross and gross alpha-beta activity. February 1978 to Novem alpha-beta, and 1.0E-ll to 2.0E-ll pCi m
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lid radwaste to Anes The licensee has provisions for transferring soTheISUWasteLogandth f depleted resin.-
Laboratory for disposal.
d showed the last major transfer was 14 poun s o ified.
No items of noncompliance or deviations were ident Materials Control and Surveys records for 1978 were reviewed with attentio 11.
This being given to the 1-curie Pu-Be UTR-10 Start-Up Source.(NDC) w The semiannual test source revealed no detectable contamination Written procedures sensitivity of 3.0E-6 microcuries for the test.
lts for opening packages require surveys to be done i
d recorded.
disposal of radioactive materials.
d monthly.
A review Contamination and radiation surveys are conducteJanuary 1978 to the p of these survey records for the period ofIn addition, special radiation The special levels.
full power.
indicates no significant surveys are conducted when the reactor is at dings from 0.06 mR/hr 30, 1978, gave rea In the survey conducted on Octoberof 7 mR/hr in the restricted area.
to 16 mR/hr with a mean
/hr to 1.8 mR/hr unrestricted area the range was 0.05 mR t mination The records indicated no significant radiation or con a levels.
d Control _
12.
_ Posting,_Labeline, an or labeling i
The inspection reveal d no problems regarding post ngSurveys are and 10 CFR 20.203. d or removed from the required by 10 CFR 19. 1 when handling fuel or when items are inserteis required to be present.
reactor, and the IIcalth Physicist Notification and Reports _
d by the inspector 13.
Statements made by the licensee and record
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nal overexposure, or excessive levels of radiation or concentra materials have occurred.
Exit Interview (denoted in 14.
_The inspector met with the licensee representatives December 13, 1978.
Paragraph 1) at the conclusion of the inspection on The following items were discussed:
50-116/78-03.
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Refer to Report No.
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liance or devi-The inspector stated that no items of noncomp were identified.
inspection 2/
a.
ations the The inspector noted that during a previous minimum sensitivity i
equation used by the licensee to determ neThe correction h b.
was incorrect.
inspection.
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Ibid.
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