ML20149D938
| ML20149D938 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 12/28/1987 |
| From: | Loesch R, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20149D925 | List: |
| References | |
| 50-020-87-03, 50-20-87-3, NUDOCS 8801130173 | |
| Download: ML20149D938 (5) | |
See also: IR 05000020/1987003
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-20/87-03
Docket No.
50-20
License No.
R-37
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Licensee:
Massachusetts Institute of Technology
138 Albany Street
Cambridge, Massachusetts 02139
Facility Name:
MIT Research Reactor
Inspection At:
Cambridge, Massachusetts
Inspection Conducted:
December 2-4, 1987
Inspector:
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Robert Loesch, Radiati6n~ Specialist
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Approved by:
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Mohamed M. Shanbaky, Chief
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Facilities Radiation Protection Section
Inspection Summary:
Inspection Conducted on December 2-4, 1987,
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(Inspection Report No. 50-20/87-03)
Areas Inspected:
Routine, unannounced inspection of radiological controls at
the MIT Research Reactor, including: status of previously identified items,
implementation of the radiation protection program, transportation of
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radioactive material, and effluent and environmental monitoring.
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Results: One apparent violation was identified:
failure to post area as
airborne radioactivity area in accordance with 10 CFR 20.203(d) requirements.
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DETAILS
1.0 Personnel Contacted
- P. Menadier, Acting Reactor Superintendent
- L. Clark, Director, Reactor Operations
- F. McWilliams, Reactor Radiation Protection Officer
- denotes attendance at exit interview.
Other licensee personnel were also contacted or interviewed.
2.0 Purpose
The purpose of this routine health physics inspection was to review the
licensee's radiation protection program with respect to the following
elements:
- Status of Previously Identified Items;
- Implementation of the Radiation Protection Program;
- Transportation of Radioactive Materials; and
- Effluent and Environmental Monitoring.
3.0 Status of Previously Identified Items
(Closed) 86-02-02 (Inspector Follow-up) Exposure controls associated with
the 5 Ci Cs-137 Calibrator. The licensee has repaired the shutter
indication lamps and operation was verified by the inspector. Calibrations
are performed by qualified members of the Health Physics staff. During
periods of source operation, access to the calibration area is roped off
and posted as a High Radiation Area.
4.0 Implementation of the Radiation Protection Program
The licensee's program for controlling radioactive materials and
contamination, providing surveillance and monitoring, and establishing and
maintaining administrative radiological work controls was reviewed relative
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to criteria in:
- 10 CFR 19.11, 19.12, 20.201, 20.203, and 20.401;
- Technical Specification 3.8, "Radioactive Effluents and
Radiation Monitors";
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- Technical Specification 4.3, "Reactor Control, Safety,
and Radiation Monitoring System Surveillance"; and
- Technical Specification 7.10, "Radiation Protection Program."
The licensee's performance related to the above criteria was determined by:
- facility tours to observe work in progress; postings, signs
and labels; and radiation monitoring instrumentation;
- review of instrument and monitor calibration records;
- review of survey records for radiation, contamination, and
airborne radioactivity;
- review of the Annual Report for the period July 1,1986 to
June 30, 1987;
- review of Memorandum dated November 20, 1987, "Report of
Annual Independent Audit 1986/1987"; and
- discussions with licensee personnel.
The licensee has an adequate program for the control of contamination and
radiation exposures.
Routine surveys are performed weekly of various areas
within the facility.
During a review of the logs, the inspector noted that
when unacceptable levels of contamination were found, appropriate steps
were taken to decontaminate the areas.
The Equipment Room, a high radiation area which contains components
associated with the ventilation and water purification systems, is
maintained locked and under the control of the Reactor Operator. Access is
restricted except during periods when the reactor is shutdown. Replacement
of resins used to maintain water quality and verification of valve lineups
for startup typically require room entries of up to one or two hours. The
inspector noted during a review of the weekly air sample results for 1987,
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that higher than expected levels of tritium are routinely identified in
the Equipment Room. The licensee stated that this was possibly due to the
buildup of tritium (approximately 2 Ci/1) in the deuterium reflector dump
tank. The tritium air concentration for the week ending November 20 was
4.2E-6 uCi/cc, 84% of the maximum permissible concentration (MPC). The
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inspector noted that the Equipment Room was posted as a High Radiation
Area, but was not posted as an Airborne Radioactivity Area. 10 CFR
20.203(d) requires that all areas in excess of 25% of the applicable MPC
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limits shall be posted with the words "Caution: Airborne Radioactivity
Area." This is an apparent violation of regulatory requirements
(50-20/87-03-01). The licensee initiated steps to bring postings of the
Equipment Room into compliance with the regulations. Subsequent to the
inspection, the licensee stated that the contents of the deuterium
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reflector will be replaced during the next maintenance outage. This will
remove the tritium source term and reduce tritium airborne concentrations
within the Equipment Room.
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Gamma spectroscopic analyses are performed using a solid state germanium
detector and a stand-alone multi-channel analyzer. Calibrations of the
system are currently performed utilizing a mixed nuclide source prepared by
the licensee with standards obtained from the Environmental Protection
Agency (EPA). The current source geometry used for calibrations is a steel
planchet contained within a plastic bag. The inspector noted that some of
the dried source material had become loose and fallen out of the planchet-
and into the plastic bag, thereby changing the original geometry of the
source. This item was brought to the attention of licensee management who
stated that the need for preparing a new source would be evaluated.
5.0 Transportation of Radioactive Materials
The licensee's program for the shipment of radioactive waste was reviewed
against criteria provided in:
- Technical Specification 7.13.5;
- 10 CFR 71; and
- 49 CFR 171-178.
The licensee's performance related to the above criteria was determined by:
- tour and observation of the waste processing area;
- review of the waste manifest logs;
- review of the 1987 Annual Report; and
- discussions with licensee personnel.
Within the scope of this review, no violations or deviations were
identified. The waste manifest logs verified the information presented in
the annual report. The licensee made one shipment in FY87 and has made one
shipment to date in FY88.
6.0 Effluent and Environmental Monitoring
The licensee's program for monitoring liquid and gaseous effluents was
reviewed with respect to criteria contained in:
- 10 CFR 20.106; and
- Technical Specifications (T.S.) 3.8, 4.3 and 7.13.5.
The licensee's performance related to the above criteria was determined by:
- tours and observations of the control room effluent radiation
monitor indications, and monitor locations within the facility;
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- review of effluent monitor logs;
- review of effluent analysis logs;
- review of the 1987 Annual Report; and
- discussions with licensee personnel.
Within the scope of this review, no violations were identified.
The
licensee was calibrating all effluent and environmental monitors in
accordance with license conditions.
Environmental surveys indicated that
there were no inconsistencies for the monitoring period during 1987. No
changes have been made to the environmental monitoring system described in
Inspection Report 85-01.
During a review of the Annual Report for the period ending June 30, 1987,
the inspector noted that some of the information for the facilities liquid
effluent releases was not provided. The specific items brought to the
licensee's attention were:
- total gross beta (Ci), less tritium
- total tritium (Ci)
- average tritium concentration
The inspector reviewed the liquid effluent records for this period and
verified that the above items were within regulatory limits for release to
the sanitary sewer system.
The licensee committed to providing a
- upplemental report with all the T.S. required data by the end of January,
1988. This additional information will be evaluated during a future
inspection (50-20/87-03-02).
7.0 Exit Interview
The inspector met with the licensee's management (denoted in paragraph 1)
at the conclusion of the Inspection on December 4, 1987. The inspector
summarized the purpose and scope of the inspection and findings as
described in this report.