ML19308B915

Responds to NRC Request to Expose Number of TLD to Radiation Under Specified Conditions.Photon Exposure Rate Was 107 Millirem Per Hour.Unable to Provide Quantitative Data for Photon & Beta Exposure

ML19308B915
Person / Time
Site:	Crane
Issue date:	04/20/1979
From:	Eisenhower E NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL
To:	Cohen L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
TASK-TF, TASK-TMR NUDOCS 8001170621
Download: ML19308B915 (5)

Text

{{#Wiki_filter:f D / ~^ f I E ttNITFn RTSTFR nFMOTMl;NT OF COMIhpr0 Nsti nut Buraru of Senndarda ,( f wzohington. D.C. e0234 m, "., ~. 20 April 1979 .(:f, O %% 5. 4. 'S D 3, Dr, Lawrence K. Cohen Division of Fuel Facility F and Materials Safety Inspection d' Office of Inspection and Enforcement sp :.. U.S. Nuclear Regulatory Commission., e c.. <.. i,;, -. ' n ~ ~ ". . ~" M" ' Washington, 'D.C. 20555 ' ^ ' s F. Mi %.'s, h 3 :.!r:2. p 4 9 ifi.5 % @ = " i W'. Dear Dr. Cohen ("B"We4b' ' ' ' M m;.' W ' ~ V ,u. In response to your request, NBS exposed a number of thermoluminescence F dosimeters to radiation under specified conditions. This letter des-cribes the important characteristics of the radiation fields used to expose the dosimeters provided by you on April 6. Two distinct proce were errployed, and they are described separately. .7 Photon Exposure The photon source was 179 mci of xenon-133 gas sealed in a glass b ampoule. The. dosimeters were exposed for one. hour at a distance of 11 inches (28 cm) from the center.of _ the source.ZThe~ calculated value of the exposure was 104 milliroentgens,1taking _into account absorption'of the 81. icv gamma rays and 30-kev x rays by the_ ampoule walls and 28.1cm.of air. The measured value7afiexposure rate at_the pointfof exposure was 1.07 mR/h. using ionization 1 chamber instruments. The estimated maximum uncertainty in the calculated and measured values of total exposure is 15 percent. During exposure, the dosimeters were attached to a nominal 2" x ~4"i6" block of wood to simulate field l-conoitions. The following dosimeters were exposed under the conditions described b: above:

3 Number Source or Type of Identification Exposed Manufacturer User Material Numbers l

2 RMC Metropolitan CaSO (Tm) 460077 Edison powder 460258 1 Teledyne Metropolitan CaS0s(Dy) TM-9Gl 3,- Edison }. 1 Harshaw BRH UF 177 f*[ 1 Harshaw EPA CaF2(Dy) 29 7 3 RMC (red) NRC Li 8,02 2 CaS0.,(Tm) 4,6,7 3 RMC (green) HRC Li2B,07 CaSO,(Tm) 15,58,60 ).? 8 0 01170 d / g i / l

T ' -2 p. - I These exposed dosimeters were returned to you on April 7 for subsequent evaluation by the users. At the same time, those dosimeters which served.as controls were also returned to you. 7 L Photon and Beta-Radiation Exposure P3-The radiation source 'was 7.6 millicuries of ' xenon-133 contained in

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a sealed hollow glass sphere with an internal radius of 10.8 cm and a contained volume of 5.290 milliliters. The length of exposure was m 7. 7.42 hours, and the dosimeters were located on the lower inside surface : of the' sphere. The~ xenon has' was'added to the ' air contained at room ~. 4 J^ '1 temperature and' atmospheric pressdre.- The dosimeters were irradiated - ~ k't ~ v in the' plastic dontainers"used for deployment in field locations. Upon termination of the irradiation, it was nhserved that xenon gas had ~ permeated the plastic containers. No circulation or mechanical mixing of the contained xenon.and air was provided during irradiation.

.n At this time we are unable to provide a quantitative characterization, within acceptable limits of uncertainty, of the radiation field at 'the pu t ri t or t reactotion.

Ihcre is sume pussibl]ILY LilaL an acceptable ~. quantificarinn mny hr nutninMd wl Ll In beveral weeks bdsed on a Inorough evaluation of the response of lithium fluoride chips which were irradiated c imul taneousiv wi th a l .ilas t ~r m - The following dosimeters were irradiated within the sphere: 't ~Q Number Source or Type of IdentificatiC Exposed Manufacturer User Material _ Numbers e unc necropoiltan Ladu tim) 4buluz (- Edison powder 460219 1 Telndyne Notropolitan Edicon CaSO,(Dy) TH 4C1 1 Harshaw BRH LiF 190 1 Ha rshaw EPA .caF,(Dy) 400 4 RMC (red) NRC L11= 0, b,8,9,10 f'2 CaSO.(Tm) J 4 RMC (green) NRC Li28.0, 11,12,18,57 i s, CaSO,(Tm) l -r These exposed dosimeters were returned to you on April 7 for subsequent ovaluation by the users. At the came time the following dosimeters, wnicn served as controls for both tvoes of exonsure, were also returned to you: i DRM (Lir) dostmerers numbered 175, l'/b,192, and ' 9 3. 5 RMC (CaSO powder) dosimeters numbered 460020, 460052, 460187, Q, and 460702 p l GN-l:l r. G M, )

[ ~ ~ -3 EPA (Harshaw) dosimeter number 489 RMC (green, NilC) dosim6ter number 59 i Telodyne (Mctropolitan Edison) dasimater number TM-1DR1 I We would like to make it. clear that the services provided by NBS were r limit J Lu wayvcure of the doc 1metern to rac10 tion t1cids as charac-terized above, under the specific conditions described. Since it was not requestod, no ovaluation of the radiation dose absorbed by the i"; 9 dosimeters was provided by NB5. Except as, described above, no.at. tempt 'was made to simulate field conditions that may have existed as a result of the Three Mile. Island reactor incident. It should not be assumed User efore, that the dos 1 meter responses tu 'Line radial'iun expusure pro-vidad 1,y NCO wa 1J L4 U.u name as the responses to radiation emitted during the incident. f>" Sincerely, %4N4b Elmer H.' Fisonhower Chief, Office of Radiation Measurement y. b [.' e f,** m s 5 I P4 ,',a e ei '? 6 l:;- sf

I \\ +- -y u r. ~. _.. _. _. - I ; g M DD%l E7AIEATION OF RADIATION MONITORDiG [3 'T/ lli 7 .s...c.. EQUIPMEXr P2SPONSE TO I33Xe /J 4 c' 'c 6 M C H.

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7-z 2 1. The co2tainar of the 133 Xe should be larga enough to approximt'2 a seul-laEicite cloud. 2. Several dif ferent concentrations of 333Xe should be used to verify the expected lineat relationship of ccr. centration to response. 3. At least 6 71.D's should be exposed at a time for a period sufficient to acesculate exposures >10 cit. l 4. Replicate swasure:sents should be cade of the 133Xe concentration to .detornine the precision of the ceasurements. Other instru:arents such as survey ceters, and gamma rate recorders should also be exposed to a semi-infinite cloud of 333Xe.. The instruments should be

• exposed ia grocps of 5 or 6 to several different concentrations of 133Xe.

Saveral censurements of the 133Xe concentration should be cade for determination of precislan in the reasurement. e yJu u nh Jt =}}