ML20040D170
| ML20040D170 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 12/11/1981 |
| From: | Cendu E, Ruenth P ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML20040D168 | List: |
| References | |
| 20058, DDH-81-206, NUDOCS 8201300372 | |
| Download: ML20040D170 (10) | |
Text
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DDil-81-206 Y
i ATTACIMENT B-4 INS 3RUME!!f CALIBRATION PROCEDURE PROCEDURE NO.
DDII-81-206 LUDIRI MODEL 12 S MICR0 R MEfER 4
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PREPARED BY:
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IN DATE:
' APPROVED BY:
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DDil-81-206 1
1.0 PUltl'0",E/nefjpg 1.1 This procedure cstablishes the minimum requiicments needt d to calibrate the indlun Mode 12 S MICI'O R MET 121.
Calibretion is perfonned to ensure accuracy while taking radiation measurements with the instruments.
~ 2.0 REFElll7:CES 2.1 Instruction Mantal Model 12 S MICR0 R METER, Ixdlum Measurements, Inc.
3.0 LIHLTII:G C0"DITIO':S
'3.1 A, pulser capabit of producing 360,000 cpm wi:h a 80 millivolt pulse is 4
required.
3.2 Two (2) Ims traceable sources will be required to complete the calibration.
An Am-241 check source and a Cs-137 source capable' of delivering 2 mr/hr.
3.3. The model 12 S shall be calibrated every 3 menths..
3.4' 'Ibtn the meter hwitch to the "BATT" position to ensure the batteries are good. If they cre nom they should be replaced.
4.0 PROCFHJRE
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4.1 Unsnap the two 1.atches on either end of the instrument and lift the front panel and the rist of the instrunent out of :.ts container.
4.2 Turn the high v:1tage fully counter clockwise for a minimum high voltage setting.
4.3 Coanect the pulcer to the coaxial connection on the board in parallel with the detector with an imput pulse of a negative 40 millivolts.
4.3.1 ~ The pulse should be five micro secondn in duration and have a 1 micro-second rise time or less with a tail of 10 -Lo 20 micro-seconds.
4.3.2 The gain should be set for 40 millivolt sensitively.
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~DDil-81-206L i
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'4.4 Calibr$tethe: instrument in counts per minute (Cl?!) on the X1000 scale.
Provide 360,000 cpn from the pulser with an to mv pulse and calibrate the meter to read 2000 ur/hr (2 on the scale).
4.4.1 Decre$se the counts by a factor of 10 and do the same for the-X100, X10 and X1 ranges.
4.5 With the detector shicided from any sources, turn up the high voltage in increments c~ 50 volts and make a plot of hi h voltage vs. count rate until i
t the voltage ratin; (obvious breakdot.u) is recched.
1:0fE: A1mys replace the instrument back in the can after each high voltage adjustment.
4.6 Expose the inst $r.;ent to an 21-241 check source and repeat step 4.5.
4.6.1 Determine the operating voltage plateau from the curves.
4.7 Expose the instru.'ent to 2 mr/hr from an NBS t accable Cs-137 source.
I Adjust the range calibration pot as necessary to read a true 2000 ur/hr on the meter sca12.
4.7.1 Disconnect the high oltage and reconnect the pulser to the instrument.
4.7.2 Determinn _he cpn required for a 2000 ur/hr meter deficction.
-4.7.3 Decrease the cpm liy factors of 10 and etlibrate the X100, X10 and X1 scales.
4.8 Record all the esta and place ih the instrumcat file.
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Page 1 of 3 DDil-81-204 Attachnent B-5 Background Radiation Irvel Detennination
-Determination of the area background radiation levels will be made by taking radiation measurements in unrestricted locations both on and off the Canbus-tion Engineering, Inc. site. The sites where these radiation measuranents will be taken will be chosen at random (possible sampling locations have been included as part of this attachment but are subject to change).
Measurements will be taken at each of the locations using a calibrated in-strument (see Attachments B-3 and B-4) on a relatively dlear day with air temperatures between 5.0 C and 25.00C : and windspeeds between calm and 10 mph. This weather information may be as measured at Bradley International Airport in Windsor Locks, Connecticut. All measurements will be made at one (1) meter above'the ground as far from trees, rock outcroping and man made structures as is possible at each location. Three (3) radiation measurements will be made at each site no less than seven (7) days apart. The instrument will be set on its longest response time (slow) and will remain in place at least twice that time prior to recording the reading. 'Once all the measurements have been taken an average background reading will be determined for each_of the sampling locations. The area background radiation level to be used for comparison will be the average _of all the sampling location average background levels.
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- 13 ATTACHMiNT B 5[
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DDil-81-204 Attachment B-6 Support Infonnation The appendix to the letter fran Mr. R.G. Page, Chief, Uranium Fuel Licensing Branch,. Division of Fuel Cycle and Materini Safety, U.S.N.R.C. section II paragraph C, sub paragraph 1 " External Radiation", states: "The~d'irect radiation dose rate can be measured with instruments after the decontamination operation to demonstrate compliance with the external radiation criteria...In order to meet the target criteria the following conditions have to be met: External radiation (ganma dose rate in air one meter above ground level) not to exceed 10ur/hr (not in-cluding background) for a diffuse source area (a contaminated area greater than 30' x 30') and not to exceed 20ur/hr (not including background) for a discrete area (a contaminated area smaller than 30' x 30')." It is interpreted that this is to mean that the average exposure rate in a 30' x 30' area may not exceed 10ur/hr (not including background) and that no single measuronent in the 30' x 30' grid section may exceed 20ur/hr (not including background). A 10ur/hr exposure limit with a pogtlation shielding factor of 0.5 and a resistence time of 807. (which is very conservative since the area in question is located in a wooded area far fran populated areas) would limit whole body doses to less than 35 mrem / year and is consistant with both the proposed EPA criteria for a clean-up standard for inactive uranium processing sites (35 mrem /yr) and the proposed NRC standards for Disposal or Onsite Storage of 'Ihorium or Uranium Nastes fran Past Operations (Federal Register Vol. 46 No. 205 Friday, October 23, 1981) which referer.ces the EPA guidelines. This 35 mrem / year limit is also below the 10CFR20 and the FRC guidelines.
DDil-81-204 Attachnent B-7 Soil Sample Criteria Using the proposed EPA guidelines ti at have been adopted by the NRC for disposal or onsite storage of Thoritnn or Uranium wastes fran past operations (Federal Register Vol. 46 No. 205 Friday, October 23, 1981) the dose cannittment to the lung should be less than 10mran/ year. Using the lung dose conversion factors (DCF) fo' Y canponents of various nuclides with an average median aerodynamic r diameter (MIAD) of 1 um listed in Attachnent B-8 (these DCF's are taken frem the task group on Lung Dynamics for Cmmittee II of the ICRP) the dose cannitt-ment to the lung will be calculated as follows: Dose (mrem /yr) = soil concentration x soil density x soil depth x resuspension factor x yearly breathing rate x occupancy factor x DCF OR b x.8* x DCF(* *i) i Dose (mrem /yr) = E x luci x 2.5 x 5x10-9m-1 x 7300 yr uc gm 6 cm 10 pci Since the soil contains a mixture of radionuclides contributing individually to the lung dose cmmittment fran inhalation of the resuspended particulates the dose calculation will be based on the average concentrations of the radionuclides in the soil. The limit for release of the waste materials staging area will be achieved if the sum of the major radionuclides does not contribute to a total lung dose greater than 10 mrem /yr.
- raken fran the EPA's proposed transuranic guidance.
p v- - 3-I D0sc Conversion Factors from Inhalation of DDil-81-204 _Radiantclides ;_(Clear. int:e ILite Class Y, l' article _ Size AMAD - I um Dose Conversion Factors (Rem /uci-Inhaled) Radionuclides Lung
- Bone, 1
3.9E+2 3.6E-0 U-238 i U-235 4.2E+2 3.8E-0 U-234
- 4. 5E4 2 3.9E-0 5.'2 E+2 9.3E+2 Th-232 Ra-228' 1.1E+3 8.1E+1
~ l Th-228 1.3E+3 8.9E+1 ti The dose conversion factors are derived based on the ICRP Task Group Lung Dynamics and computer code "DACRI!!" developed by Battelle Pacific Northwest i 1 Laboratories.- ( w ,,,,s
j- .[dL., -- - -- d @ @ b _ m - _ - ~.... - - ~- - 9 C a f1/ .i / lL '" LICENSE' AMENDMENTS" Docket No. 7 0 - II D D William 0. Miller, License Fee Management Branch, ADM ,q MATERIALS LICENSE AMENDMENT CLASSIFICATION 4 Applicant: CE. 9mmt b4Qom License No: S 4> 44 - e o 6, Fee Category: /S Application Dated: / L - /a - o0/ Received: / t - A / V/ Applicant's Classification:' Eu and.D The above application for amendment has been reviewed by NMSS in accordance with S170.31 of P3rt 170, and is classified as follows: 1. Safety and Environmental Amendments to Licenses in Fee Catecories IA throuch'1H,'2A, 2B, 2C, and 4A (a) Major safety and environmental (b) Minor safety and envirtnmental (c) Safety and environmental (Categories ID through 1G only) (d) Administrative-2 Justification for reclassification: uxn ~~ 3. The application was filed (a) pursuant to written NRC request and the amendment is being issued for the convenience of the conmission, or (b) Other (State reason): 1 Signature ,64/ J Division of Fuel Cycle & Material j Safety Date M2 mq2 / 97, $4&i ' 2 O OM e- _ _ _ ___ _ _ ____m _}}