IR 05000020/1998203

Insp Rept 50-020/98-203 on 981207-10.No Violations Noted. Major Areas Inspected:Radiological Control During Major Facility Mod Projects

ML20206S465
Person / Time
Site:	MIT Nuclear Research Reactor
Issue date:	02/01/1999
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20206S457	List: IR 05000020/1998203 ML20206S454
References
50-020-98-203, 50-20-98-203, NUDOCS 9902090237
Download: ML20206S465 (7)

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U. S. NUCLEAR REGULATORY COMMISSION Docket No: 50-20 License No: R-37 Report No: 50-20/98-203 i

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Licensee: Massachusetts Institute of Technology Facility: MIT Research Reactor I i

. Location: 138 Albany Street Cambridge, Massachusetts Dates: December 7-10,1998

' Inspector: Thomas F. Dragoun l Approved by: Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate I Division of Reactor Program Management /NRR ;

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9902090237 990201 PDR ADOCK 05000020

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l t- EXECUTIVE SUMMAR l l

Radiological control during major facility modification projects, as well as routine operations, was satisfactory. Significant improvements were noted in the radiological l sample analysis laboratory and the reactor effluent release monitoring systems. The .

revised Emergency Plan appears to be properly implemented.

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Reoort Details Summary of Plant Status The reactor was in continuous operation for experiments and silicon ingot irradiation. The Boron Test Facility (BTF) was disassembled with the curtain (shutter) replaced with a lead shield. Shield blocks removed from the BTF were being reconditioned for use as walls of the new BNCT treatment room that will use the proposed fission converter. Housekeeping improvements were made in preparation for hosting the TRTR conference. Emergency response refresher training was provided to a group of campus police. The reactor containment building air conditioners were replace .0 Radiological Protection Insoection Scope (Inspection Procedure 83743)

The inspector reviewed:

o work planning and control, e ALARA reviews, e maintenance and calibration of analytical laboratory apparatus, e routine surveys and monitoring, e exit radiation surveys, e audits, and e calibration and use of portable survey meter Observations and Findinas l Records of work planning and radiological controls during disassembly of the BTF and fit testing of the fission converter mockup demonstrated adequate precautions were take Personnel exposures were reasonable for the radiological conditions in the work area Plans for removal of abandoned underground liquid radwaste tanks were oriented to the preverition of the spread of contamination. Management satisfactorily incorporated radiological controls into work plans. A major outage was planned for the Spring of 1999 to replace the cooling towers, install the fission converter, and perform other maintenance. In addition, the number of patients undergoing BNCT therapy willincrease and the facility must renew its reactor license. The RRSO expressed confidence that the workload could be completed safel ;

The RRSO perforrns ongoing ALARA reviews with results and recommendations discussed l during the weekly coordination meetings with reactor operations staff. The RRSO stated )

that the most beneficial, but not all, ALARA recommendations for the silicon irradiation l project, which causes about 32% of staff exposures, were implemented due to the heavy l workload from other projects. implementation of an ALARA program was acceptabl *

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2-Analytical laboratory equipment reviewed included an intrinsic germanium detector and attached spectrum analyzer, a new low background proportional counter, and gas-flow detector. Isotope identification on the gamma detection apparatus is accomplished by a recently enhanced software program. Equipment maintenance, calibration, daily checks, quality controls, activity standards, and sample counting procedures followed currently accepted good practices. The well maintained and operated equipment results in good confidence in the analytical data outpu Routine radiological surveys are done daily, weekly, and monthly. The monthly surveys are the most extensive and detailed. Daily surveys are completed before the start of day shift. Standardized maps with set survey points ensure consistency while the data is recorded in tabular form. The extent of the surveys appeared appropriate. Records are reviewed by supervision prior to filing. A random review of records indicated that the survey schedule was completed and data was acceptable. The area radiation monitoring system was fully operational with ten functioning channels. The radiological conditions in the facility are adequatuly characterized by the monitoring progra Exit frisking practices were satisfactory. A new, more sensitive hand and foot monitor, which is also capable of detecting alpha contamination, was installed at the CV exit. This improves control of loose contaminatio I An annual review of the radiation protection program was completed as required by 1 10 CFR 20.1101. The review included all areas and no weaknesses were reported. A quarterly audit by reactor operations staff confirms completion of all required radiation surveys and that results are within specificatio Portable beta-gamma survey meters are calibrated on site using cesium-137 and cobalt-60 sources. Calibrations are done on weekends due to the high radiation areas needed to calibrate certain instruments. Calibration procedures incorporate the latest ANSI recommended techniqces. Records were properly maintained. The supply of calibrated equipment on hand was adequat ! Conclusions The radiation protection program has been maintained in accordance with regulatory requirement I

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I-3- ' ' Effluent and Environmental Monitoring (inspection Procedure 80745) Inspection Scope (Inspection Procedure 80745)

l The inspector reviewed:

e Hardware changes to'the effluent monitor system, e installation of new effluent channel instrumentation, and e Channel calibratio Observations and Findinos System hardware upgrades included new power and signal wiring to the detectors, detector probe modifications, new connectors and sample lines. Systems that were refurbished included botn channels of plenum gas and particulate, exhaust stack gas and particulate, liquid effluent, core purge, and sewer discharge monito During an inspection of this area in April 1997, the licensee indicated that replacement of the effluent monitoring instrumentation was anticipated. The readouts and controls were 4 designed and fabricated in-house. The inspector observed that this equipment was )

installed and operational. The readouts and wiring appeared to be of professional qualit Interviews with reactor operators indicated that the equipment was significantly more j

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stable than the old syste j Records indicated that the effluent monitors were properly calibrated annually. Quarterly source checks were completed as require ) Conclusions The effluent monitoring systems have been effectively maintained to meet regulatory requirement .0 Emerger.cy Preparedness

- Inspection Scope (Insoection Procedure 82745)

. The inspector reviewed:

e Refresher tra'aing for campus police, e implementation of the revised Emergency Plan, o Status of support agreements, e Emergency supplie's, and j e Training drills and exercises, j i

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4 Observations and Findinas Besides security, the Emergency Plan specifies that campus police provide ambulance service, first aid, and conduct radiation surveys. The inspector observed annual refresher training for a group of campus police lasting about three hours. The subject matter was appropriate, the instructors were knowledgeable, and class participation was enthusiasti The inspector concluded that the training was effectiv Selected sections from the revised portion of the Emergency Plan were found to be properly implemente Agreements for support with the City of Cambridge Police, Fire, and Emergency Management agencies were current and in effec A sampling of emergency supply cabinets indicated that essential supplies were availabl The annual building evacuation drill and annual radiological emergency exercise were developed and conducted in accordance with detailed procedures. The exercise scenario was designed to test overall emergency preparedness as well as previously identified weaknesses. It simulated a design basis accident (partial fuel element melt) and required use of the reactor operator duress signal. Exercise observers recorded both strengths and weaknesses for future improvement of emergency response. The inspector concluded that the exercise was very effectiv Conclusions The emergency preparedness program was maintained in a state of operational readines .0 Exit interview

i The inspector presented the inspection results to members of licensee management at the i conclusion of the inspection on December 10,1998. The licensee acknowledged the !

findings presente I

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PARTIAL LIST OF PERSONS CONTACTED Licensee J. Bernard, Director of Reactor Operations T. Date, Assistant Reactor Radiation Protection Officer E. Lau, Assistant Operations Superintendent F. McWilliams, Reactor Radiation Protection Officer (RRPO)

INSPECTION PROCEDURES USED

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I IP 80745: CLASS 1 NON-POWER REACTORS EFFLUENT AND ENVIRONMENTAL MONITORING IP 83743: CLASS I NON-POWER REACTORS RADIATION PROTECTION IP 82745: CLASS I NON-POWER EMERGENCY PREPAREDNESS ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None LIST OF ACRONYMS USED ALARA - As Low As Reasonably Achievable ARM -

Area Radiation Monitor BNCT- -

Boron neutron capture therapy

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Boron Test Facility CFR --

Code of Federal Regulations IP- - Inspection Procedure NRC -

Nuclear Regulatory Commission-RRP Reactor Radiation Protection Officer l

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