ML20149D938

Insp Rept 50-020/87-03 on 871202-04.Violation Noted.Major Areas Inspected:Radiological Controls,Including Status of Previously Identified Items,Implementation of Radiation Protection Program & Transportation of Radioactive Matl

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: ML20149D920 ML20149D932 ML20149D938
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: M# M /c/2fy'h

Robert Loesch, Radiati6n~ Specialist da't e

Approved by: ~fff. 3 A,1)/

Mohamed M. Shanbaky, Chief

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date

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,

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implementation of the radiation protection program, transportation of

l 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

i maintaining administrative radiological work controls was reviewed relative

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,

l 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

i 20.203(d) requires that all areas in excess of 25% of the applicable MPC

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

l 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.