IR 05000223/1996002
| ML20135A147 | |
| Person / Time | |
|---|---|
| Site: | University of Lowell |
| Issue date: | 10/10/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20135A134 | List: |
| References | |
| 50-223-96-02, 50-223-96-2, NUDOCS 9612030087 | |
| Download: ML20135A147 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION l
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Docket No:
50-223 i
License No:
R-125
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i Report No:
50-223/96-02 i
Licensee:
University of Massachusetts
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j Facility:
Lowell University Research Reactor
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I Location:
1 University Avenue Lowell, Massachusetts
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Dates:
October 7-10,1996 Inspector:
Thomas F. Dragoun, Project Scientist i
Approved by:
John R. White, Chief, Radiation Protection Branch D! vision of Reactor Safety
J 9612030087 961126 PDR ADOCK 05000223 G
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EXECUTIVE SUMMARY Control and monitoring of effluent releases were good. The radiation protection program was effective. Correction of recordkeeping weaknesses is expected after filling the full-time HP technician position.
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1 Reoort Details
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Summarv of Plant Status i
Tours for high school students were held. The reactor water cleanup demineralizer was regenerated. Surgical apparatus was sterilized by exposure to the cobalt 60 source.
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R1 Radiological Protection l
R1.1 Imolementation of Revised 49 CFR Parts 100-179 and 10 CFR Part 71 a.
Insoection Scope (Temocrary Instruction 2515/133)
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i The inspector reviewed:
Training and qualification of personnel preparing or overseeing radioactive
j materials shipments,
Implementation of SI units and revised A1/A2 values
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Completed shipping documents i
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Observations and Findinas i
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l Interviews and a review of records indicated that shipments of radioactive material i
are infrequent and one-of-a-kind. The RSO stated that updated regulations are
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reviewed prior to each shipment and separate procedures are unneeded. He is the
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only person authorized to package, prepare the documentation, and arrange the
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transport of any shipment. Records of a September 1996 shipment of U-233
indicated that regulatory requirements were met, c.
Conclusions J
Revised DOT and NRC transportation regulations effective April 1,1996, were
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properly implemented.
R1.2 Effluent and Environmental Monitorina a.
Insoection Scope (Inspection Procedure 80745)
The inspector reviewed:
Control of effluents,
Calibration, maintenance, and setpoints of gaseous and liquid effluent monitors,
Location and maintenance of environmental monitors, and
Effluent release and environmental monitoring data and calculations
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Observations and Findinas The inspector walked down the liquid waste processing system, accompanied by
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the HP technician. One of the 2,000 gallon waste holdup tanks was lined up for recirculation. A simulated sample was taken and analyzed in accordance with
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procedure S.P.10 (pH, gross beta, gamma activity). The RSO stated that solubility
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requirements in 10 CFR 20.2003 for discharges to the sewer were assured by HP
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control of material dumped into the radwaste system. However, the control procedure will be changed to require that samples be passed through a micron filter, j
recounted, and compared to acceptance criteria to ensure solubility before the tank is released. These changes will be made by November 30,1996. This matter will be reviewed in a future inspection (Inspector Follow item 50-233/96-02-01).
d Records indicated that liquid releases were properly controlled and below the concentration limits specified in 10 CFR 20 Appendix B.
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Doses to the public resulting from releases of argon 41 in the reactor stack were I
calculated as 3.06 mrem per year using a balloon model. Estimates using the EPA COMPLY computer code at level 4 projected 0.2 mrem per year public dose.
q The municipal water supply drawn from the river adjacent tc the facility is analyzed
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for activity bimonthly. Particulate samples taken from a continuous air monitor on j
the Pinanski Building roof are analyzed weekly. Twenty one environmental TLDs
located in occupied office areas are exchanged quarterly. All data indicated that the exposure to the public was below regulatory limits.
The inspector noted that some periodic environmental sample data and quality
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control checks on laboratory counting equipment appeared to be missing. However, there are no specific regulatory requirements for these checks. The licensee stated that the individual responsible for this program had unexpectedly retired in August
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l and a change in the oversight of these activities will prevent similar occurrences in the future. Further improvement is expected when the HP technician position,
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discussed in a June 3,1996 letter to the NRC, is filled. The status of this position will be reviewed in a future inspection (Inspector Follow item 50-233/96-02-02).
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Conclusions Effluent releases and doses to the public were properly controlled and monitore _
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R1.3 ' Radiation Protection a.
Insoection Scope (Inspection Procedure 83743)
The inspector reviewed:
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e Radiation Safety Guide,
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e Radiological controls, o
Protective clothing use, l
e Personnel dosimetry and exposure records, o
Routine area and personnel exit surveys, o
Personnel training,
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e Calibration of portable survey instruments, o
Control of doses to embryo / fetus, e
Audits and oversight b.
Observations and Findinas Calibration records for certain portable survey instruments could not be located although the instruments had updated stickers indicating the calibration was current. The part-time HP technician stated that the previous stall technician stored records at different locations and the replacement will be tasked with consolidating instrument records.
Performance in the other areas reviewed was satisfactory.
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Conclusions j
The radiation protection program was maintained in accordance with regulatory requirements and licensee commitments.
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X1 Exit interview (Inspection Procedure 30703)
The inspector presented the inspection results to members of licensee management at the
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conclusion of the inspection on October 10,1996. The licensee acknowledged the findings presented.
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5 PARTIAL LIST OF PERSONS CONTACTED
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l Licensee I
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- L. Bettenhausen, Reactor Supervisor s
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- W. Church, Radiation Safety Officer
- G. Kegel, Director, Radiation Laboratory R. Wagner, Provost and Vice Chancellor for Academic Affairs
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- Denotes those present at the exit meeting.
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INSPECTION PROCEDURES USED j
l IP 30703:
ENTRANCE AND EXIT INTERVIEWS l
IP 80745:
CLASS 1 NON-POWER REACTORS EFFLUENT AND ENVIRONMENTAL-i l
MONITORING IP 83743: CLASS I NON-POWER REACTORS RADIATION i
PROTECTION Tl 2515/133 IMPLEMENTATION OF REVISED 49 CFR PARTS 100-179 AND 10 CFR PART
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ITEMS OPENED, CLOSED, AND DISCUSSED
Ooened 50-233/96-02-01 IFl
~ Ensure solubility of liquid discharges to the sewer 50-233/96-02-02 IFl Fill the permanent staff HP technician position
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'I Closed i
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LIST OF ACRONYMS USED l
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CFR Code of Federal Regulations DOT Department of Transportation EPA Environmental Protection Agency HP Health Physics i,
NRC Nuclear Regulatory Commission
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RSO Radiation Safety Officer SI international System of Units
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.TLD Thermoluminescent Dosimeter l'
TS Technical Specifications I
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