IR 05000264/1977001
| ML20136H292 | |
| Person / Time | |
|---|---|
| Site: | Dow Chemical Company |
| Issue date: | 05/11/1977 |
| From: | Finn J, Fisher W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20136C633 | List: |
| References | |
| FOIA-85-483 50-264-77-01, 50-264-77-1, NUDOCS 8508200257 | |
| Download: ML20136H292 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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0FFICE OF INSPECTION AND ENFORCEMENT
REGION III
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l Report No. 50-264/77-01 l
Docket No. 50-264 License No. R-108 l.
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Licensee:
Dow Chemical U.S.A.
1803 Building
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Midland, MI 48640 Facility Name:
TRIGA Reactor Inspection at:
Midland, MI Inspection Conducted:
April 25 and 26, 1977 Inspector:
J. A. Finn P
f/h/7 7
' (Date)
7f Approved by:
W.L. Fisher,'C$iief
.5 //[7 7 Fuel Facility Projects and (Date)
Radiation Support Section Inspection Summary:
Inspection on April 25 r.nd 26, 1977 (Report No. 50-264/77-01)
Areas Inspected:
Facilities and equipment; organization; training;
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radiation protection procedures; health physics instrumentation; exposure control; posting, labeling, and control; materials records; surveys; notifications and reports; radioactive ef fluent releases; and liquid and solid waste. The inspection involved seven inspector-
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hours onsite by one NRC inspector.
I Results: No items of noncompliance or deviations were identified in
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the twelve areas inspected.
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DETAILS 1.
Persons Contacted G. L. Kochanny, Jr., Manager, 1602 Building 0. V. Anders, Reactor Supervisor R. A. Olson, Health Physicist
Denotes those present at the exit interview.
.M 2.
Facilities and Equipment
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The inspector toured the facility to observe housekeeping, equipment,
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storage, and posting.
3.
Radiation Protection Staffing R. A. Olson continued as Reactor Health Physicist.
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health physics ccverage is available from the licensee's Industrial Hygiene staff.
4.
Licensee Audits Industrial Hygiene (Health Physics) performs audits and surveys quarterly.
The inspector reviewed audit records for the period April 1976 to April 1977.
5.
Training Reactor operators undergo annual requalification training and testing. This program includes lectures on radiation protection, radwaste, license requirements, and NRC requirements.
This train-
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ing meets the requirements of 10 CFR 19.12.
6.
Radiation Protection Procedures Radiation protection and radwaste procedures are available and appear to be adequate.
7.
Health Physics Instrumentation a.
Portable Survey Instruments The licensee has on hand survey instrumenta capable of measuring beta, gamma, and neutrons.
These are calibrated semiannually.
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b.
Area Radiation Monitor (Technical Specifications G.1 and G.2)
The area radiation monitor consists of a Geiger tube mounted on the reactor room wall about 13 feet from the reactor, and
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a meter readout and alarm at the operating panel.
The area radiation monitor is calibrated semiannually with a 10 milli-gram radium source The alarm is set daily at 0.6 milli-
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roentgens per hour as part of the Daily Startup Checklist.
c.
Water Monitor-ed Pool water is filtered and portions are demineralized.
Before filtering, the water passes through a water monitor vessel
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containing a Geiger tube..The signal is fed to a readout and alarm located at the operation console.
The water monitor is calibrated semiannually. The alarm is set daily at 80 counts per second as part of the Daily Startup Checklist.
d.
Continuous Air Monitor (Technical Specifications G.2 and G. 3)
The continuous air monitor (particulate) is located in the reactor room with readout (chart) and alarm on the monitor itself.
The monitor is operated in the fixed air sample mode.
Each day as part of the Daily Startup Checklist the chart reading is recorded, the filter is moved, and the alarm points The low alarm is s9{ at 1,000 counts per minute are set.
(equivalent to about 2 x 10 microcuries per milliliter on an eight-hour sample).
The high alarm is set at 5,000 counts per minute. The monitor is calibrated weekly with a beta source.
l 8.
Exposure Control d4"**
a.
External Exposure Assigned personnel use beta-gamma-fast neutron film badges provided monthly by R. S. Landauer. Visitors are also pro-vided badges. The badge supplier's report is the equivalent of Form NRC-5.
Self-reading dosimeters are used as deemed appropriate.
Ranges available include O t o 200 milliroentgens and 0 to I roentgen.
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A review of film badge reports for CY1976 and CY1977 through January 14, 1977, showed the maximum annual whole body ex-posure was 470 millirems.
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Internal Exposure l
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Particulate air activity is measured by a continuous air
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monitor located in the reactor room.
The readout chart is checked daily when the sample filter is changed. Charts are maintained on file.
In the 12-month period from April 1976
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to April 1977, no particulate activity was detected.
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Argon-41 concentration calculations in the SAR, assuming continuous generation of argon in the rabbit system, are below Part 20 limits. The rabbit system is used less than i
five percent of the time.
Film badge data indicate no overexposures to argon-41.
9.
Posting, Labeling, and Control During a tour of the f acility, the inspector observed that posting
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and labeling were in accordance with 10 CFR 20.203 requirements.
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The licensee's response to IE Circular No. 76-03 was reviewed.
At the time of the inspection no high radiation areas existed.
Radiation areas that exist temporarily following removal of activated samples are surveyed and controlled administratively.
Notices required by 10 CFR 19.11 were posted at the entrance to
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the building.
l 10. Materials Records of receipt, transfer, and disposal of licensable material
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l were-reviewed. No problems were identified.
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11.
Surveys l
l The reactor room sample storage area is surveyed daily.
Surveys are
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also made during removal of samples from the lazy susan or from the l
rabbit system.
During a tour of the f acility the inspector made surveys of the l
i reactor room, the storage arcas, and the water treatment system.
No unusual radiation levels were observed.
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12.
Notifications and Repctts Reports are made as required.
Individuals are notified if any radiation exposure is incurred.
13.
Radioactive Effluent Releases No radioactive liquids are released from the reactor.
Liquids are transferred to the licensee's byproduct material license for solidification.
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Particulate gaseous effluents are measured by the continuous air
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monitor located in the reactor room.
(See paragraph 8.b) No particulate activity has been detected in the latest 12-month period.
Argon-41 concentration calculations in the SAR, assuming continuous generation of argon in the rabbit system, are below Part 20 limits.
The rabbit system is used less than five percent of the time.
14.
Solid Waste i.
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Solid radwaste is transferred to the company byproduct material license for shipment to a licensed waste disposal agency.
Liquid wastes are also transferred for solidification before shipment
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offsite.
There have been no shipments of reactor waste in the
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latest 12-month period.
15.
Records and Documents Reviewed a.
Daily Startup Checklist b.
Weekly Instrumentation Checklist c.
Monthly Checklist
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Semiannual Checklist e.
Radiation Monitoring Instruments Calibration Book f.
Film Badge Reports, CY1976 and CY1977 g.
Reactor Operations Committec Meeting Minutes g.
Reactor Operators Requalification File and Tests 1.
Reactor Activation Request Forms i
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