ML20071Q160

Forwards Responses to 731106 Questions,Indicating Specified Locations on Floor Plan

ML20071Q160
Person / Time
Site:	05000148
Issue date:	12/06/1973
From:	Will Smith KANSAS, UNIV. OF, LAWRENCE, KS
To:	Ziemann D US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20071Q157	List: ML20071Q160
References
FOIA-83-126 8759, NUDOCS 8306080316
Download: ML20071Q160 (8)

Text

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'. - 7 J LJ THE UNIVERSITY OF KANSAS / LAWRENCE, KANSAS 66044

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SCHOOL oF ENGINE ERING O'fice of the Dean liL 111/Aarvin Hall Qgj 913 E6t3881 IAa!!ing address: P. O. Box 2067 e

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DeceT.ber 6, 1973 g allllTo a ~

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Mr. Dennis L. Ziemann, Chief l6Il i

Opera 11ng Reaciors Branch #2 Directorate of Licensing US AEC i Washington, D.C. 20545 Re: Docket tJo. 50-148

Dear Mr. Ziemann:

In response to your leiier of November 6, 1973, our staff has prepared replies io the series of questions you posed. I enclose one original and fificen additional copies of our replies as you wished.

Should there be any clarification or additional information required, you may call the reactor supcrvisor, Professor Russell Mester (913-864-3938) or the University Health Physicist, Mr. Guy Oldfield (913-864-3857) or drop us a letier.

Very truly yours,

{j(, ^*,-' [

- William P. Smith Dean pc Enclosures g i[ P cc: Russell Moster k -

Harold Rosson 1 DEC 111973 Hobart Woody di E Guy 0idfieId -

n;,,cic,,,, c, p,y:..ory em.:.cns Robert Friauf Repen IV S759 8306080316 830406 PDR FOIA DARNES83-126 PDR kl l

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UNIVERSITY 0F KANSAS REPLIES TO A SERIES OF QUESTIONS CONTAINED IN A LETTER ADDRESSED TO . DR. WI LLI AM P. SMITH DATED NOV. 6, 1973

. The pneumatic tube _ exhaust and receiving station

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1 a, b are at the: same location designated "T" on the following floor plan.

1.c Air particulate samples are collected at variable locations indicated by "A" on the floor plan.

1d The pressure differential was measured as .04 inches of water. Air flow paths between the pneumatic tube area and the outside of the building are- indicated ~ on the floor plan.

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.. No. I.667 -

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\ ('a) ' 7.3 ,c ach , 2 5m1 of CC-14 and' 5 each, 25 ml of 4 % CC1 4 in

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hexane; all shielded by 0.9 mm Cd.

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(b) .E3dion,uclides produced: Cd, approx. 3m Ci.

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i ('c)~ Lhngth of irradiation ranged from 30 sec at 1 kw to 4

' min at 10 kw.

(d) The packing material was polyurethane foam.

(e) The CC1 samples were contained in a glass scintillation 4

vial, sealed in a polyethylene bag. The CC1 4 - Hexane samples vefe contained in a polyethylene scintillation vial.

s (f) The thermal neutron flux density was 6.5 x 10 n/cm 10 sec at 1 kw and 6.5 x 10 n/cm sec at 10 kw.

s No. 2-668 1/19/72 *

- ( a) 4 each, Fricke dosimeters (20 ml) and 8,each 22 ml of 4% CC1 in Hexane; all shielded by 0.9 mm of Cd.

4 (b) Radionuclides produced: P, approx. 1pCi and Cd, approx.

3raCi .

l (c) Length of irradiation: 30 sec. to 4 min..

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(d) Packing material: Polyurethane foam.

(e) All sampics were. contained in polyethylene vials.

l 10 2 l- ( f) The thermal neutron tiux density was 6.5 x 10 n/cm sec. The f ast' neutron flux density was approximately

'- 10 4 2 10 n/cm sec.

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, (a) .8 each,+O'.5 gm In foils.

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(b) Radionuclid'es Produced: 116S.n, approx'.' SpCi.

(c) IrradiatioE time: ~

1 min. ,

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Packing n5terial: Polyurethane foam. '

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, (b)^ Foils were not encapsulated

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(f)j ;ThermV1 ' neutron flux was 6. 5 x 10 6 n/cm 2 sec.

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.f . '* y l-J No. M-671 f<

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I cobalt foil packed in ca ier with polyurethane.

-Exposure time was I. minute. INeutron Flux 6.6 x 10 10 n/cm 2 sec. .

60 Principle radioactive .r.,

1. content Co ,

ij Activity of content 01pCi.

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No. S-670 '

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Identical to S-669 0

No. B-672 11/27/72

-2 -2 (a) 2 cach 0.1 ml 10 M Nacl in H20; 2 cach 0.1.m1 l'0 M KC1

! in H20,1 each aqueous suspension of 0. 018 'gm of acellular Physarum polycephalum.

24 38 (b) Radionuclides produced: Na, .2pCi; C1, 2.0pCi; and 42 K, .03.

(c) Length of irradiation 10 minutes (d) There was no. packing material.

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(e) All samples were contained in pokyethylene vials, scaled in polyethylene bags.

12 2 sec.

The thermal neutron flux was~ approximately '10 n/cm

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No. B-673 .

12/4/ 73 16 samples total

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2 empty vials (polyethylene) . 6 Nacl standards -10 ,

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milliliter each. (polyethylene vials)

-2 8 biological specimens between 10' g-2 x 10 g wt polyethylene vials.

Exposure time 10 minutes. Samples were irradiated in two runs -p 8 each time, with above exposure time, reactor power Icvel ,

12 150 kw (10 n/cm sec).  :

24 38 activity of content  :

. Principle radioactive content Na , C1 38 1pCi 24 Na, 6pCi C1 for both runs. - .

No. F-674 -

12/4/72

f. Poly-I' 2 Indium foils (1 was placed between 2 cadmium foils.

Reactor urethane packing was used. Exposure time 2 minutes.

6 Principle radio-power level I watt (6.5 x 10 n/cm s ec) .

_ 6 activity of content ~1.0pCi/ foil.

active content In I No. M-675

i. 12/13/72 l Identical to M-671 e

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No. M-676 12/15/72 6 samples total -

-2 1 10 M Nacl 1 milliliter. .

-2 2 specimens Physarum polyceph-lum at approx. 1.3 x 10 g.

2 2 specimens Physarum polycephalum at approx. 0.4 x 10 g.

1 specimen Physarum polycephalum at approx. 0.2 x 10 2 g.

The above samples were all put in polyethylene vials and then scaled in polyethylene bags. ,

12 2 Exposure time 10 minutes. Reactor power level 150 kw (10 .n/cm sec).

24 0 Principle radioactive content Na, C1. Activity content 8

2pCi C1, .3pCi Na.

No. M-677 12/18/72 Identical to M-671 -

No. M-678 12/20/72 6 samples total

-3 1.1 milliliter Nacl 10 M 1,'.2% agar solid 4,1.0 to 1. 8 x 10' g specimens Physarum pblycephalum

• Polyethylene vials used and then placed in a polyethylene bag which

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was sealed. ~

l Exposure time 10 minutes. Reactor power level 150 kw (1012) 24 38 principle radioac.tive content Na, C1. Activity of contents 24 2pCi 3'8 C1, .3pCi Na.

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! 3. The technical specifications do not require that the

airborne radioactive material concentration be measured during I cach pneumatic tube operation. The airborne contamination t

! IcVels were monitored during the pneumatic tube operation on 7 January , 19 7 2. The measured gross beta concentration was

-16 less than 7 x 10 Ci/ml, which was the minimum detectable concentration.

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4. CO2 gas is used to propel the pneumatic carriers. A gas cylinder, pressure regulator and solenoid operated valve constitute the equipment provided for this.

A Lamson terminal (Model . YB871) permits dispatch and receipt of the carrier providing a seal against escape of -

CO Eas at the station. CO is discharged just above the .

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- floor, below the station. Several simple improvements in the seal are under consideration. .

5. We plan to install a filter in the CO2 discharge lines.

We are seeking information on prospective filters in order ,

to make an optimum choice.

. 6. A scalco receiving station is aircady supplied. See No.'4.

The pneumatic tube is powered by industrial grade CO2 7.

(99. 5% CO2 ) . Likely impurities are CO and N2 but A may be present in lesser amounts. Let us assume only 10% of the -

impurities is . A (. 05 % A in the CO2) . The volume in the pneumatic tube exposed to the neutrcn flux is about 400 cm which 1 would

~4 The saturated activity of A at 250 contain 4 x 10 g A.

12 kw (1.67 x 10 n/cm sec) is 370ECi/g. Three hours is the 2

maximum time and' the specific activity then would be 250  ; .

41 A would be 100 pCi. If this should be mc/g. The total ,

distributed into the reactor room the concentration would ,

be 10'7 pCi/cm 3 which averaged over 747 hrs. , the time until the reactor could be operated again at 250 kw, would be 3.5 -

-10 pCi/cm 3. This is well below the non' occupational 6 - ,I x 10

-8 level of 4 x 10 Ci/cm .

Our pneumatic tube is constructed of aluminum. We have observed no corrosion products nor have we been able to detect -

radioactivity which might have come from corrosion products.

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Ruisell B. Meslet Uuy GPUTield r

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%4 "w-* S e# %r hw 4-u e s . :o July 23 1962 Directer Division of Reactor Licensing Nuclear Regulatory Cummission Washington, D.C. 20545 RE: Itocket No. 50-148

Dear Sir:

In accordance with Facility License R-78 I rubmit the following annual re-port f or the period July 1,1981 to June 30, 1982.

1. Routine operation of the reactor accumulated .28 megswatt hours mostly at 250 kv.

2. Unscheduled shutdown occurred on March 31, April 7, 16 and 29, 1982.

The cause was electrical transients of unknown origin.

3. Routine maintenance has been successful in avoiding any necessity for performing special preventative and corrective maintenance having safety significance.

4. There have been no changes in the facility or in the procedures nor have any test or experiments been carried out without prior approval by the NRC pursuant to 10 CFR 50.59.

5. Cross Beta and Camma activities released to the sanitary sewer system f rom the demineralizer regeneration ef fluent hold-up tank was less than .029 pCi and less than .61 pCi respectively.

6. Air samples taken outside of the Reactor Building were as follows for the period 7-01-81 to 6-30-82 (error given at 20 level):

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Beta Activity Average (1.2 i 1.8) x 10 pC1 Gamma Activity Average (10.2 15.7) x 10- pCi

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:aission July 23, BE2 pne :

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7. Air sanples taken inside the Reactor Building were as follows for the period 7-01-81 to 6-30-82 (error given at 20 level):

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Ects Activity Average (1.1 ! 1.6) x 10 ' pC1

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Cam == Activity Average (6.4 I 1.5) x 10 pCi

8. 'No facility personnel or visitors received any significant radiation exposure.

9. The membership of the University's Comittee on Radiation Sources remains unchanged. The Nuclear Reactor Co ::sittee remains the sa=e.

Very truly yours, M s Russell B. Mesler Professor

REM /dm ec

Nuclear Reactor Cccanittee f

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