IR 05000223/1998200
| ML20217Q215 | |
| Person / Time | |
|---|---|
| Site: | University of Lowell |
| Issue date: | 04/07/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217Q196 | List: |
| References | |
| 50-223-98-200, NUDOCS 9804100344 | |
| Download: ML20217Q215 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION Docket No:
50 223 License No:
R-125 Report No:
50-223/1998200 Licensee:
University of Massachusetts Facility:
Lowell University Research Reactor i
Location:
1 University Avenue Lowell, Massachusetts Dates:
March 17-20,1998 i
inspector:
Thomas F. Dragoun, Reactor inspector i
Approved by:
Marvin M. Mendonca, Acting Director Non-Power Reactors and Decommissioning j
Project Directorate l
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PDR ADOCK 05000223 i
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EXECUTIVE SUMMARY
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The licensee's programs were directed toward the protection of public health and safety l
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violations of reguietory requirements were identifico. Management attention should be directed to issues raised by firefighters during orientation tours.
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. Report Details
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Summary of Plant Status The ' reactor was secured. ;lnstallation and operational checks for the new area radiation
. monitoring system and new nuclear instrumentation amplifiers were in progress.
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- Orientation for groups of firefighters were conducted in accordance with the Emergency d
Plan.' Two new fuel elements recently transferred to the site had been installed in the core.
Specimens were irradiated with the Co-60 source.
R1 Radiological Protection
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a. Inspection Scopa (Inspection Procedure 40750)
- The inspector reviewed:
o Staffing, e Radiation protection policies and procedures.
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- Routine radiation surveys, e Exit surveys, o Radiological controls, e Personnel exposure records,.
e Portable survey meter maintenance and calibration, e University Radiation Safety Committee oversight,
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e Audits, o Control of solid waste, and
- e' Training of personnel.
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Observations and Findings
. The Reactor Supervisor resigned in December 1997, but continued to serve as a consultant. The Director of the Radiation Laboratory indicated that the search for a replacement was progressing satisfactorily. A new Reactor Supervisor will be named by May 1998.
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The RSO stated that arrangements will be made for the recently appointed HP
. technician to. visit nearby nonpower reactors to become familiar with other HP -
programs and participate in equipment vendor training programs on using laboratory counting instruments. These actions will provide the technician with experience and allow him to assist in improving the research reactor HP program.
. The inspector observed several survey meters in storage needed repair. The HP technician indicated that he did not have the equipment or knowledge to make repairs. The RSO stated that assistance from an electronics technician would be obtained. An adequate number of operable survey meters were on hand.
HP program policies, including ALARA, are described in the Radiation Safety Guide that was revised in June 1997. However, the inspector noted that some HP
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implementing procedures, such as the routine survey procedure, lacked detail. The RSO stated that these would be reviewed and improved as required. The requirements of 10 CFR 20.1101 for a documented program were satisfied.
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Routine surveys for loose contamination and beta-gamma dose rates were
. performed monthly by the HP technician and clearly recorded on maps. Results were reviewed by the RSO.- Loose contamination over 500 dpm/100 cm8 was
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reported to the users who were responsible for decontamination and resurveys.
Personnel leaving reactor containment used an automatic hand and foot monitor for
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an exit survey. Howeveri the monitor at the upper air lock (third floor) was out of
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commission and personnel descended through the building to use the monitor at the lower airlock. The inspector noted that survey records showed occasional loose-l
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contamination on the floor leading to this airlock from the inside (reactor side). Tha-j RSO stated that pancake probe friskers will be sought for this location and used i
inside containment. This matter 'will be reviewed in a future inspection (Inspector Follow-up item 50-223/1998200-01).
Radiological waming signs, postings, and NRC-3 forms were satisfactory.
Personnel dosimetry was processed monthly. At mid-year the processing vendor was changed to another NVLAP certified laboratory and continuity of dose records
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was maintained.~ Extremity monitoring was used as required. Annual doses were
.within NRC limits and were based on an academic year that began on July 1'.
- Gamma and neutron portable survey meters were properly calibrated using generally accepted techniques. Calibration procedure, HPP-1, conforms to the
- recommendations in ANSI Standard #323.
l Minutes of meeting indicated'that the Reactor Safety Subcommittee met more frequently than required by TS 6.2 and provided appropriate oversight. An
.j independent HP program audit was completed in December and recommended
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certain program improvements. The RSO stated that implementation of these improvements is in progress.
j Solid radioactive waste was properly packaged, inventoried, and stored in a
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shielded, posted, and locked location.
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HP refresher training for reactor operators and experimenters was provided by the
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= RSO. Attendance and written exam records indicated that reactor operators and R
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- others received three 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> training sessions in March 1997.~ Lesson content
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satisfied requirementis in 10 CFR 19.12.
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Conclusions L
' The ' radiation protection program met regulatory requirements.
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R2 Effluent and Environmental Monitoring a
inspection Scope (inspection' Procedure 40750)
The inspector reviewed:
o Calibration and maintenance of the exhaust stack monitor, o Airborne effluent release data, e Control of liquid releases, and e Environmental TLD monitoring.
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Observations and Findings
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The exhaust stack monitor calibration procedure was hand written and issued on July 25,1989. To calibrate, activated P-10 gas with a known quantity of Ar-41 i
fiHed a container. placed over the GM detector with a closed loop recirculating pump
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ensuring uniform distribution. This technique was acceptable. The calculated conversion factor, monitor CPM reading to Ci/cc of Ar-41 in the stack, appeared appropriate.
Use of the EPA COMPLY computer code demonstrated that airborne emissions were i
well below the constraint value of 10 millirem per year to the public. Liquid waste was stored in a tank farm consisting of three 2,000 gallon and two 7,500 gallon tanks in a basement room of the Pinanski Building. All tanks were fiberglass and in very good condition. Selection of the on-line tank configuration was by the HP technician who was a licensed reactor operator. Floor drains recirculated back to the tanks so that an unmonitored release to the sewer system could not occur.
Sampling and analysis of tank contents was appropriate. Control of discharges by the RSO were proper.
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The inspector verified the location of selected environmental TLDs surrounding the reactor containment. TLD records indicated that exposures to the public were below NRC limits.
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Conclusions i
Effluent releases and doses to the public were properly controlled and monitored.
EP1 Emergency Preparedness a.
Inspection Scope (Inspection Procedure 40750)
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The inspector reviewed:
e. conduct and results of the annual drill, and i
e orientation briefings for firefighters.
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Observations and Findinos
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The annual drill scanario simulated the collapse of a radiation shield wallin the pump
. room, which sheats the primary water pipe causing flooding and release of v
hazardous resin regenerating chemicals. The drill was held in December 1997.
Records indicate that the drill was effective and resulted in the identification of several items for improvement.
Multiple orientation)ours in groups of twenty were conducted for officers and men from the city fire deg.artment. The tour included all areas of reactor containment.-
The presentation was thorough'and participation by the firefighters was very, good.
The inspector noted thet two issues raised by the firefighters were not answered i
during the tour as follows:
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A reactor operations escort will be needed to accompany firefighters into.
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containment yet escorts were not respirator qualified. It was anticipated that even a small fire will require respirator use.
The rack mounted two inch fire hose inside containment may be hazardous to
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untrained personnel when used at full pressure.
Licensee resolution of these matters will be reviewed in a future inspection.
(Inspector Follow-up ! tem 50-223/1998200-02)
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Conclusions
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implementation of the Emergency Plan was acceptable, but fire response issues remain open.
' MA1 Material Control and Accounting
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insoection Scone (insoection Procedure 85102)
The inspector reviewed:
e the system for tracking the quantity, identity, and location of SNM, e. assignment of responsibilities,
' e shipment, receipt, and burnup records, e inventory results, and e reports.
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Observations and Findinas t
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Records indicated that all nuclear material was accurately accounted for. The
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licensee had no receipts and made no shipments between September 30,1994 and September 30,' 1997. All Material Balance Reports (DOE /NRC Form-742) submitted by the licensee for this period satisfied the requirements specified in 10 CFR 70.53.
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Two new fuel elements were received during the current reporting period ending March 31,1998. During this inspection, an updated Material Balance Report and a
. Transaction Report (DOE /NRC Form-741) to account for the new fuel were in
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preparation.
. All SNM was stored in designated areas which included the reactor core, reactor pool,'and security cabinet.
Physicalinventories were conducted' monthly which exceeds the requirements-specified in 10 CFR 70.51(d).
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Conclunigan No deficiencies were identified in the licensee's Material Control and Accounting program.
SG1 General Physical Security Requirements For Special Nuclear Material Of Moderate Strategic Significance a.
Insoection Scone (Insoection Procedure 81421)
The inspector reviewed:
o records and reports,
- key control, I
e tests of detection sids,
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e screening and access controls, e provisions for contingencies, and e audits, b.
Observations and Findinas The CRO performed a key inventory audit in April 1997. Later that month, another '
audit by the CRO verified the reactor staff's knowledge of the security plan, the i
staff's ability to carry out the plan, and the key control program. The routine annual audit was completed in May 1997, and the current review was in progress. All identified weaknesses were corrected.
- i The daily security check was performed during the routine reactor equipment status inspection. Security system checks were conducted at the required intervals and recorded in the console log. Access keys were secured in a safe at the end of the i
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The inspector noted that the dedicated silent alarm was not functionally checked.
I The licensee stated that this alarm was used to summon armed response from off campus before the campus police were armed, it was no longer needed and the H
r system will be deleted in a future change to the Security Plan.
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Screening of personnel for unescorted access was conducted in accordance with the Plan. Required records were complete.
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Conclusions The NRC approved security program was acceptably implemented.
X1. Exit Meeting Summary (Inspection Procedure 30703)
The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on March 20,1998. The licensee acknowledged the fi.1 dings presented.
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PARTIAL LIST OF PERSONS CONTACTED Licensee -
L. Bettenhausen, previous Reactor Supervisor
- W. Church, Rediation Safety Officer
- G. Kegel, Director, Radiation Laboratory B. Stymest, Health Physics Technician
- notes those present at the exit meeting.
INSPECTION PROCEDURES USED lP 30703:
ENTRANCE ANO EXIT INTERVIEWS IP' 40750:
CLASS 11 NON-POWER REACTORS
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IP 85102:
MATERIAL CONTROL AND ACCOUNTING - REACTORS IP 81421:
F!XED SITE PHYSICAL PROTECTION OF SPECIAL MATERIAL OF MODERATE STRATEGIC SIGNIFICANCE ITEMS OPENED, CLOSED, AND DISCUSSED
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l Opened 50-223/1998200-01 IFl Provide additional frisking stations.
50-223/1998200-02 IFl Resolve comments by firefighters.
Closed none LIST OF ACRONYMS USED ALARA As Low As Reasonably Achievable i
CFR Code of Federal Regulations CRO Chief Reactor Operator EP.
HP Health Physics IFl Inspector Follow-up item IP inspection Procedure I
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NRC Nuclear Regulatory' Commission NVLAP ~ National Voluntary Laboratory Accreditation Program
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RSO Radiation Safety Officer SNM
- Special Nuclear Material SRO-Senior reactor operator TLD
. Thermoluminescent dosimeter TS Technical Specifications I
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