IR 05000264/1974001

From kanterella
Jump to navigation Jump to search
RO Insp Rept 50-264/74-01 on 740306 & 07.No Violations Noted.Areas Inspected:Personnel Monitoring,Surveys & Survey Instruments,Rabbit Sys,Radwaste,Area Radiation Monitor,Water Monitor & Continuous Air Monitor
ML20136H207
Person / Time
Site: Dow Chemical Company
Issue date: 04/02/1974
From: Finn J, Fisher W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20136C633 List:
References
FOIA-85-483 50-264-74-01, 50-264-74-1, NUDOCS 8508200228
Download: ML20136H207 (5)


Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

-

.

.

E (

c

.

.

.

U. S. ATOMIC ENERGY COMMISSION DIRECTORATE OF REGULATORY OPERATIONS

,

REGION III

Report of Operations Radiological Protection

.

RO Inspection Report No. 050-264/74-01 Licensee: The Dow Chemical Company

1701 Building Midland, Michigan 48640 TRIGA Reactor License No. R-108 Midland, Michigan Category:

F

--

Type of Licensee:

100 Kw, TRIGA (Non Pulsing)

.

i Type of Inspection:

Unannounced

_

Dates of Inspection March 6 and 7, 1974 Dates of Previous Inspection:

Septecher 20 and 21, 1973 (Operations)

D T

Principal Inspector:

J. A. Finn I

b d - 2'/

/

(Date)

Accompanying Inspectors: None

'

_

_

Other Accompanying Personnel: None

[ / L./

.5

f. d. p.)

,1 /

) -

W. L. Fisher,,M M Reviewed By:

Senior !!calth Physicist 7/A/ 7'/

'

Facilities Radiological Protection (Date)

Section

'

+

_

'

3

..

8508200228 850725 h

J.+:

PDR FDIA '

s-

'

'

~" *

CONDITB5-483 PDR

_

'

,.

e

>

.

.

C (

'

.

.

SUMMARY OF FINDINGS Enforcement Action: None.

Licensee Action on Previously Identified Enforcement Matters None reported within the scope of the inspection.

--r*,*

Unusual Occurrences: None.

-

_Other Sienificant Findings A.

Current Findings: None.

B.

Unresolved Items: None.

C.

Status of Previously Reported Unresolved Items: None reported.

Management Interview The following individuals were present during the management interview:

Dr. O. U. Anders, Reactor Supervisor Dr. J. W. Turley, Laboratory Director

.

Mr. L. G. Silversteir., Radiological Safety Officer Mr. G. U. Engdahl, Health Physicist The scope and findings of the inspection were discussed. The inspector stated that no items of noncompliance had been identified.

.-w

-2-

-g'.'}

.

.ap -

..

e

.

-

(

(

-

.

l

,

REPORT DETAILS 1.

Persons Contacted

-

,.

Dr. O. U. Anderc, Reactor Supervisor Mr. L. G. Silverstein, Radiological Safety Officer 2.

Personnel Monitoring u

Film badges are obtained from a commercial supplier on a monthly basis.

-

The badges monitor beta, ga==a and fast neutrons. Visitors are provided badges. Forms AEC-4 are not completed for reactor personnel. The badge suppliers' report is the equivalent of Form AEC-5.

Self-reading dosimeters are used as deemed appropriate. Ranges avail-able include O to 200 milliroentgens and O to I roentgen. Results are recorded in the experimental logbook.

A review of film badge reports for 1971, 1972 and 1973 showed the max-imum annual whole body exposure was 50 millirem. Skin exposures have been minimal. No reports had been received to date in 1974.

3.

Surveys and Survey Instruments The licensee has on hand survey instruments capable of measuring beta, ga=ca and neutrons. These are calibrated semiannually.

The reactor room sample storage area is surveyed daily. Surveys made during removal of experiments from the lazy susan or from the rabbit system are recorded in the experimental log books, w

4.

Rabbit System The rabbit system is a closed system provided with a high ef ficiency part-iculate filter upstream from the blower. The blower exhausts into the hot laboratory hood exhaust pipe, which, in turn, exhausts through a high efficiency particulate filter to the roof stack.

.

The sender-receiver station is in the hot laboratory hood. A seal cover plate is in place during sending and receiving operations. The station is under vacuum relative to the pressure in the hood.

Rabbit samples are doubly contained. The sample is sealed in a plastic container, which is then sealed in a plastic outer container. Remote handling tools are available.

-3-5~:k m ai

- - - _ _

,

.

.

<

c

.

.

5.

Radioactive Waste Solid waste from the reactor consists mostly of spent decineralizer resins. About 10 gallons of resin are transferred annually to a licensed waste burial service. Activity consists mostly of sodium 24.

In addition, a small quantity of liquids generated during chemical separations of experimental samples are " solidified" with ver=iculite and -hipped as solid waste. There is no liquid waste from the reactor

.

pool.

'

wa Particulate gaseous effluents are measured by the continuous air monitor.

~

There has been nothing above background, which is of the order of 10-14

'

microcuries per milliliter. Argon 41 concentration calculations in the SAP. assuming continous generations of argon are below Part 20 limits.

However, the rabbit system is used only about 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per week.

6.

Area Radiation Monitor (Technical Specifications G.1 & G.2)

The area radiation monitor consists of a geiger tube mounted on the reactor room wall about 13 feet from the reactor, and a meter readout and alarm at the operating panel.

The meter readout and alarm are shared with the water monitor. The area radiation monitor is calibrated semiannually with a 10 milligram radium source. Ine alarm is set daily at 1 milliroentgen per hour as part of the Daily Startup Checklist.

7 Water Monitor Pool water is filtered and portions are demineralized. Prior to filtering, the water passes through a water monitor vessel containing a geiger tube.

The signal is fed to the area radiation monitor-water monitor readout at the operation console. The readout represents the cor.bined signals from both probes.

,,,,

The water monitor is calibrated semi'.nnually. The alarm is set daily at 1 milliroentgen per hour as part of t*,e Daily Startup Checklist.

8.

Continuous Air Monitor (Technical Specifications G.2 6 G.3)

The continuous air monitor (particulate) is located in the reactor room with readout 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 filter is moved, the background is recorded ( e.g. 50 counts per minute) and the alarm points are set.

The low alarm is set at 1000 counts per minute (equivalent to about 2 x 10-11 microcuries per milliliter on an eight hour sample). The high alarm is set at 5000 counts per minute. The monitor is calibrated weekly with a beta source.

-4-

.;i5

,

t M

-

.

.

___

.

.

.-

.,

'

(

(

..

.

-

9.

Records The following records were reviewed for items concerned with radiation protection and radwaste:

a.

Daily Startup Check List b.

k'eekly Instrumentation Checklist

  • [**

c.

Monthly Checklist d.

Semiannual Checklist e.

Reactor Operating Log f.

Experimental ~ Log g.

Radiation Monitoring Instruments Calibration Book h.

Film Badge Reports

,

m

.

,

s 5-

-

,3c; m?q -

.

f.

-

-,,,

n aa w-

,

,-

m y

~-

-,----- -, -

,