ML19224A931
| ML19224A931 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/03/1979 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 1950, TM-0186, TM-186, NUDOCS 7906130250 | |
| Download: ML19224A931 (4) | |
Text
lt TMI DOCU"ENTS f ~h DOCUMENT NO:
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OF DOCUv2NT PROVIDED BY CCFf MADE CN s
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men OPOLITAN EDISON CCMPA!Pl.
/IM4V "Jilda R. Mullinix, NRC 177 258 7906:307 @.h 5
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1950 Revision 3 02/03/79
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..;RiiE MILE ISLAND NUCLEAR STATION STATION CHEMISTRY PROCEDURE 1950 DETERMINATION OF GROSS BETA GAMMA DO NOI REVOVE Tme of Eneaive eas" CONTROLLED COM.
Pm Date Revision Pace Date Revision P3 Date R evision 1.0 06/23/76 2
26.0 51.0 2.0 02/03/79 3
27.0 52.0 3.0 06/23/76 2
28.0 53.0 4.0 29.0 54.0 5.0 30.0 55.0 6.0 31.0 56.0 7.0 32.0 57.0 8.0 33.0 58.0 9.0 34.0 59.0 10.0 35.0 60.0 11.0 36.0 61.0 12.0 37.0 62.0 13.0 38.0 63.0 14.0 39.0 64.0 15.0 40.0 65.0 16.0 41.0 66.0 17.0
. 42.0 67.0 18.0 43.0 68.0 19.0 20.0
' 44.0 69.0 45.0 70.0 21.0 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0
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1950 Revision 2 DETERMINATION OF GROSS BETA GAMMA 06/23/76 STATION CHEMISTRY P.40CEDURE NO. 1050 1.0 _
SUMMARY
Various systems in the plant are ranitored for gross beta gamma activi ty.
Changes in or the presence of activity are valuable aids in the determination of fuel rupture, leakage into buffer cooling systems, etc.
In cases where fresh fission products are known to be present, it is often desirable to save the sample for recounting at a later date.
2.0 APPARATUS 2.1 Pipets 2.2 Micro pipets
?.3 Anaiytical Balance 2.4 Drying lamp
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2.5 Planchets
^0 REAGENTS None required.
a.0 PROCEDURE 4.1 For samples of low activities (environmental, seccndary side steam generators, condensate, closed cooling, etc.) a large sample volume may be necessary.
Evaporate the larger volume in a beaker over a hot plate to near dryness.
4.2 Rinse beaker with small portion of denineralized water and transfer this anc;nt to a tared planchet.
Rinse a second time then proceed with step 4.4.
I 1.0 177 260 i
1950
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Revision 3 02/03/79 4.3 For higher activity samples pipet an appropriate volume of the sample into a tared planchet.
If the pipet is designated TC, rinse it twica with demineralized water into the planchet.
4.4 Dry under an infrared lamp, cool and count.
Those samples containing fresh fission products must be counted at a specified time after sampling.
Determine the counting time as follows:
Estimated Activity Count Time Less than 10 times MDA 20 min.
10-1000 times MDA 10 min.
Greater than 1000 times MDA 1 min.
4.5 Weigh the planchet after counting; calculate the density of the deposit and determine its presentage transmittance frcm the calibration graphs found in the Radiological Healtn landbook,Section II.
2 NOTE:
If the deposit density is <0.5 mg/cm, correction for percentage transmittance is not necessary.
4.6 Determine the minimum detectable count rate from PCP 1950.2.
If the net sample count rate
- less than the MOCR, substitute the MCCR for net count rate in 4.7 and report the activity as less than the value calculated in 4.7.
4.7 Calculate the uCi/ml using the following formula:
uCi/ml =
net counts cer minute (cont com Efficiency (dpm) X 2.22 x 106 (dpm/uCi) x volume (ml) x 5 trans.
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2.0 177 257
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,t 15;J Revision 2 06/23/76 4.8 Calculate the standard deviation to the 95% C.L. as follows:
/ cpm (samole & bka)
+
com (bkg)
Std.Dev.(2 sigma)=2\\]oi: 1 Time (sample & bkg)
Total Time (bkg) 4.9 The sample may then be discarded or raved for other analyses such as gross alpha.
5.0 REFERENCE 5.1 Radiological Health Handbook i
b2 3.0 I
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