ML19256E604
| ML19256E604 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 10/04/1979 |
| From: | Greger L, Hiatt J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19256E599 | List: |
| References | |
| 50-186-79-06, 50-186-79-6, NUDOCS 7911080130 | |
| Download: ML19256E604 (9) | |
See also: IR 05000186/1979006
Text
U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-166/79-06
Docket No. 50-186
License No. R-103
Licensee: University of Missouri
Research Park
Columbia, M0 @5201
Facility Name: Research Reactor Facility
Inspection At: Rese. rch Reactor Site, Columbia, M0
Inspection Conducted:
September 11-13, 1979
Inspector:
J. U. Hiatt
.t). h
10 / </71
/d/Y!79
Approved By:
L.R.GregrI
n
if
Fuel Facility Projects and
Radiation Support Section
Inspection Summary
Inspection on September 11-13, 1979 (Report No. 50-186/79-06)
Areas Inspected: Routine, unannounced inspection of radiation protection
and radwaste management programs, including: qualifications; training;
procedures; instruments and equipment; audits; posting, labeling, and
control; exposure control; surveys; notifications and reports;
effluent
releases; effluent control instrumentation; records of effluents;
reactor
coolant water quality; receipt and transfer of radioactive material;
and
previous items of noncompliance and commitments. The inspection involved
21 inspector-hours onsite by one NRC inspector.
Results: Of the fifteen areas inspected, no items of noncompliance or
deviations were found in fourteen areas; one apparent item of noncompliance
was found in one area (deficiency - failure to maintain records required
by 10 CFR 71.62(a)(10) - Paragraph 15).
.
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DETAILS
1.
Persons Contacted
- D. Alger, Associate Director, Research Reactor Facility
- K. Armbruster, Research Laboratory Technician
R. Brugger, Director, Research Reactor Facility
- C. Edwards, Reactor Plant Engineer
- P. Keenan, Assistant to the Vice President - Research
- J. Naylor, Health Physics Technician
- 0. Olson, Manager, Reactor Health Physics
- N. Sunderland, Assistant Campus Radiation Safety Officer
- C. Thompson, Chairman, Reactor Advisory Committee
- M. Vonk, Operations Engineer
V. Zager, Chief Research Electronics Technician
The inspector also interviewed other licensee employees, including
chemistry technicians, licensed operators, and facility researchers.
- Denotes those present at the exit inte. view.
2.
General
This inspection, which began with visual observation of facilities
and equipment, posting, labeling, and access controls at 8:30 a.m.
on September 11, 1979, was conducted to examine the routine operational
radiation protection and radwaste management programs. During the
initial tour of the facility, the inspector used a licensee survey
meter to perform surveys at selected locations. Posting and labeling
of the areas conformed with regulatory requirements. Areas visited
during this and other tours included the reactor control room, the
Medi-Physics hot cell area, the beam port floor, and laboratories in
the reactor building.
On September 13, 1979, the inspector observed the transfer of several
molybdenum-99 samples from the reactor flux trap to the Medi-Physics
hot cell. A non-routine transfer route was required because the
elevator in the reactor containment was brobn.
Self reader dosimetry
data indicates that a Medi-Physics employee received the highest
dose (160 mrems) during the transfer.
3.
Licensee Action on Previous Inspection Findings
(Closed) Noncompliance (50-186/78-01):
Inadequate (evelopment of
health physics procedures. The licensee has compleed the development
of the procedures (See Paragraph 7).
(Open) Commitment (50-186/77-04): Evaluation of the collection
efficiency of the charcoal sampler due to high flow rate. A student
research project to determine the efficiency at various flow rates
continues.
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1294 312
.
4.
Organization
A full time nealth physics technician was hired in June 1979. The
health phy:,ics organization now consists of the Manager, Reactor
Health Physics, three full time technicians, and three part time
laboratory assistants. With this increased staffing it appears that
the problem are
identified in a previous inspection report are
j
being addressed
No items of noncompliance were identified.
5.
Licensee Audits
Minutes of the Reactor Advisory Committee meeting held in June 1979
were reviewed. The Committee's membership and meeting frequencies
were as required. Health physics related items were discussed at
the meeting (e.g. addition of the new health physics technician,
results of May 1979 NRC inspection).
No items of noncompliance were identified.
6.
Training
The Manager, Reactor Health Physics, continues to provide and docueent
radiation protection orientatio- for experimenters and other personnel
new to the freility. A review of records indicates that since May
1979 about 60 people have been trained.
In August 1979 facility operators were briefed on the newly issued
Health Physics Standard Operating Procedures (See Paragraph 7). The
Manager, Reactor Health Physics, plans to brief other employees
during meetings with their respective work groups (e.g. reactor
services, electronics technicians and mechanics, research and
applications, etc.).
Health physics technicians have met about weekly with the Manager,
Reactor Health Physics for training courses. Topics covered include
air sampling, advantages and disadvantages of film dosimetry, spent
fuel shipment procedures, and instrument sensitivity.
No items of noncompliance were identified.
7.
Procedures
In response to a previous item of noncompliance,2/ the licensee
stated that eight health physics procedures would be in use by
,
1/
IE Inspection Report No. 50-186/79-03.
2/
IE Inspection Report No. 78-01 and licensee letter dated July 20,1978.
hk
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.
August 31, 1979. The licensee completed d2velopment of
ese procedures
in July 1979, bringing the total number of Health Physics Standard
Operating Procedures in use to sixteen. Additional procedures will
be developed as needed.
The inspector reviewed the zo11owing procedures:
HP-7
" Response to Medi-Physics Hot Cell Gamma Alarm"
HP-17
"H-3 Air Samples"
HP-18
" Calibration of G.M. Survey Instruments"
HP-19
"Self Reading Dosimeter Calibration"
HP-20
" Report of Personnel Contamination"
The inspector noted that HP-18 requires only a one point per scale
calibrations for certain survey meters.jyy of two points per scale
calibration and discussed the desirabil
The licensee stated that
it would be considered. This item will be reviewed further during a
future inspection.
No items of noncompliance were identified.
8.
Exposure Control
a.
External
The vendor's film badge reports for the period May through
August 1979 were r(viewed. The greatest whole body dose recorded
for CY 1979 to date was about 2000 mrems. Records showed that
this individual, a Medi-Physics employee, did not receive above
1250 mrems in any calendar quarter in 1979 (the highest being
1000 mrems in the first quarter). The highest extremity dose
for the year to date was about 5000 mrems.
Self reading pocket dosimeters are issued to individuals with
the greatest exposure potential. The inspector compared film
badge and dosimeter data for two individuals and noted that the
doses estimated on dosimeter results were about 10-15% less
than that actually assigned based on film badge results. The
licensee stated that this discrepancy will be evaluated. This
item will be reviewed duriag a future inspection.
b.
Internal
The licensee routinely performs tritium analysis on urine
samples collected from one reactor operator per shift each
month. Results of these samples from May 1979 to date were
reviewed; no problems were noted. The health physics and
.
3/
ANSI N323-1978 " Radiation Protection Instrumentation Test and
Calibration."
.
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radiochemistry departments independently analyze the samples.
Results were compared; no major discrepancies were noted.
Continous air samples, daily tritium air samples, and smear
surveys are alsc used to define any problem areas. Records of
these indicat:rs were reviewed; no pr H ems were noted.
No items of noncompliance were identified.
9.
Posting, Labeling, and Control
During facility tours the inspector reviewed the licensee's compliance
with posting and labeling requirements specified in 10 CFR 19.11 and
10 CFR 20.203. No problems were noted.
Four radiativa work permits (RWP's) were written since May 1979.
The preface to the Health Physics Standard Operating Procedures
specifies conditions and jobs which require issuance of an RWP.4j
No items of noncompliance were identified.
10.
Surveys
The inspactor selectively reviewed records of direct radiation,
swipe, and air sample surveys conducted since tn' last radiation
protection inspection. Observed results were com;irable to those
obtained during the inspector's tours of the facility.
Containment air samples are taken and analyzed for tritium daily by
the health physics and radiochemistry departments. Results of
samples taken from May 1979 to date were reviewed.
Concentrations
normally ranged from 7.0 E-8 to 1.0 E-7 uCi/cc. The highest
concentration noted was 3 E-7 uCi/cc.
No items of noncompliance were identified.
11.
Instruments and Equipment
,
a.
Portable Survey Instruments
Records of instruments calibrated since May 1979 were reviewed.
The licensee logs the calibration dates on file cards maintained
ftr each instrument and status charts posted in the health
physics office. The inspector noted that the transfer of data
between the status charts and file cards was not timely
(e.g. the latest calibration data was logged on the status
'
4/
IE Inspection Report No. 50-186/78-01.
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1294
315
.
board but not on the file cards). The licensee stated that the
'
file cards would be updated. Calibration
quencies were the
same as noted during a previous inspection
b.
Area Radiation Monitoring System (ARMS)
The seven area monitors were last calibrated in June 1979 and
were checked for operability and alarm response before reactor
startups. No problems were noted during a review of logs and
startup checklists since May 1979.
c.
Stack Monitor System
The particulate, gaseous, and iodine monitors were calibrated
in August 1979. However, the radiochemist who has the records
was not available during this inspection. The calibration data
will be reviewed during a future inspection.
Gaseous monitor alarm setpoint calculations were reviewed. The
inspector noted that the setpoint was about 200 cpm greater than
the alculated monitor response at the instantaneous technical
speci- 'ation limit for Ar-41 (based on the instantaneous gaseous
te chr...
specification limit, 3500 times MPC for Ar-41, and the
February 1979 calibration data). The licensee stated that the
setpoint would be evaluated. This item and the clarm setpoints of the
particulate and iodine monitors will be reviewed further during
future inspections.
No items of noncompliance were identified.
12.
Primary Coolant Activity
Records of primary coolant water sampling and analyses were reviewed
from May 1979 to date. The technical specificati'n requirements for
sampling frequency and maximum permissible I-131 concentration were met.
No items of noncompliance were identified.
13.
Reactor Building Isolation Functional Testing
Verification of ventilation isolation is made during reactor startups
by exposing the reactor bridge monitor, building exhaust plenum
monitor and backup building exhaust plenum monitor to check sources
and observing closure of valves A16A and A16B (indicated by lights on
the control panel). Startup check sheets were reviewed from May 1979
to date; no problems were noted.
No items of noncompliance were identified.
,
S/
IE Inspection Report No. 50-186/79-03.
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316
14.
Radwaste Management
a.
Liquid Radwaste
Isotopic analysis is made on each sample of liquid radwaste
before discharge to either the sanitary sewer or the cooling
tower basin. Since May 1979 there have been twenty-one releases
to the sanitary sewer, totaling 0.04 curies, and three releases
to the cooling tower, totaling 0.04 curies.
Liquids containing
radioative material other than tritium are not discharged to
the cooling tower basin.
The licensee calculated the amount of tritium that could have
been discharged to tg sanitary sewer during blowdowns of the
cooling tower basin.-
For reporting period 1977-1978, 2.7 mci
were discharged; for 1978-1979, 1.8 mci. The inspector reviewed
the licensee's calculation and concurred with the results.
b.
Gaseous Radwaste
Daily grab samples are taken from the stack and analyzed for
Ar-41.
Graphs of the daily sample results were reviewed for
May 1979 to date; none exceeded the instantaneous technical
specification limit. The licensee stated that the gaseous
effluent monitor's strip chart would indicate any sudden
increases in Ar-41.
A re"iew of the licensee's annual report, covering the period
from July 1, 1978,.to Jse 30, 1979, indicated that the average
annual concentration of Ar-41 discharged to the environment was
97% of the technical specification limit (250 times MPC). The
inspector reviewed the licensee's calculations and noted that
the method used to calculste the average concentration was
different from that used in the FY 1977-1978 Annual Report.7j
For FY 1978-1979 the licensee multiplied the average daily
Ar-41 concentration by the total volume of air disc *nrged from
the facility (based on a measured exhaust flow rate and continuous
reactor operation). This method appears conservative because
the reactor does not operate continuously (maintenance shutdowns
occur at least biweekly), and the licensee used a conservative
estimate of the average daily Ar-41 concentration. At the
inspector's request the licensee calculated the 1978-1979
annual average using the 1977-1978 method; the recalculated
number was slightly less than that obtained using the above
method (about 95% of the technical specification limit).
'
6/
IE Inspection Report No. 50-186/78-05.
7/
Described in IE Inspection Report No. 50-186/79-03.
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Facility License Aiendment No. 12, issued in July 1979, increased
the maximum allowable instantaneous and annual discharge limits
for gaseous effluents.
No items of noncompliance were identified.
c.
Solid Radwaste
The licensee has made two shipments of barrels and boxes of
solid waste since May 1979. A total of about 1200 cubic feet
containing about 200 mci's was shipped to a licensed facility
for disposal.
During a tour of the Medi-Physics hot cell, the inspector noted
radiation levels of 60-80 mR/hr near radwaste drums stored in
the area.
Postings were as required; however, Medi-Physics
personnel, who are in the area at least twice weekly, work near
and are exposed to the radiation from the drums. Radioactive
waste storage goblems contributed to a previous item of
noncompliance.-
The licensee stated that arrangements have
been made with a licensed disposal agency for routine pickup
and dispcual of solia waste. This lack of radwaste storage
space will be reviewed during future inspections.
15.
Receipt and Transfer of Radioactive Material
The licensee stated that the only radioactive material received
under the reactor license since the previous inspection was new
fuel. According to the licensee, contamination surveys were made on
the fuel and no contamination was detected.
The inspector reviewed the licensee's records of transfer of licensed
byproduct material from May 1979 to date. Material is transferred
to both on and off campus users at a rate of 4.t.
least one shipment
per day. A review of shipment records indicated that records required
by 10 CFR 71.62(a)(10) were not maintained for several Type B
shipments, including shipments 17252, 17237, and 17144, in August
1979.
This is an item of noncompliance.
Three shipments of spent reactor fuel were made since Mty 1979.
Records of the shipments were reviewed for compliance with 10 CFF 71
requirements.
No problems were noted.
16.
Notifications and Reports
A review of records and discussions with licensee representatives
indicated that the licensee has complied with 10 CFR 19 end 10 CFR 20 reporting requirements. The inspector reviewed the licensee's FY
8/
IE Inspection Report No. 50-186/78-01.
-8-
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318'
.
1978-1979 Reactor 0 nrations Annual Report. No problems concerning
technical specification requirements for frequency or content were
noted.
17. Exit Interview
The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusien of the inspection on September 13, 1979, and
further discussed the inspection findings with Mr. Olson on September 17,
1979. The following matters were discusced;
a.
The purpose and scope of the inspection.
b.
The item of noncompliance (Paragraph 15).
c.
The status of a previous item of noncompliance and a commitment
(Paragraph 3).
d.
The solid waste storage problem (Paragraph 14.c).
The licensee
stated that a contract with a
csed disposal firm was being
negotiated.
e.
Minor discrepancies in instrun n .41ibration records (Paragraph 11).
The licensee stated that the logs would be updated.
f.
The setpoint of the gaseous effluent monitor (Paragraph 14.b).
The licensee stated that the setpoint would be evaluated.
g.
The discrepancy between dosimeter and film badge results
(Paragraph 8.a).
The licensee stated that the discrepancies
would be evaluated.
.
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