ML19224B129

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Submits Chemistry Procedure 1959,Revision 2:determination of E (Unit 1 Only)
ML19224B129
Person / Time
Site: Crane  Constellation icon.png
Issue date: 01/14/1977
From:
Metropolitan Edison Co
To: Mullinix W
NRC/IE
References
1959, TM-0071, TM-71, NUDOCS 7906140082
Download: ML19224B129 (8)


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TMI EOCUMENTS DOCUMENT NO:

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OF DOCUMENT PROVIDED BY COPY MADE ON METROPOLITAN EDISON COMFMIY.

Wilda R. Mullinix, NRC 9

I 7906140082 9

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MASTER COPY

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959 Revision 2 DO NOT REMOVE THREE MILE ISLAND NUCLEAR STATION STATION CHEt11STRY PROCEDURE 1959 Determination of E (Unit 1 Only)

Table of Effective Pages C0XTROL ED COPY Pace Date Revision Pace Date Revision Pace Date Revision 1.0 01/14/77 2

26.0 51.0 2.0 01/14/77 2

27.0 52.0 3.0 01/14/77 2

28.0 53.0 4.0 12/14/73 0

29.0 54.0 5.0 12/14/73 0

30.0 55.0 6.0 09/04/74 1

31.0 56.0 7.0 01/14/77 2

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 44.0 69.0 20.0 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 Unit 1 Staff Recom e s pproval Unit 2 Staff Reco me de Approval

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Approval e

Date Approval Date Cognizjntle/t. head CogrdzanY[$pl. Head Unit 1 PORC Recommends A proval Unit 2 PORC R mmen s A ]roval f

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Date / - / b VQ' I\\

Date

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i PORC comments of included PORC comme s of included

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Approval Date Approval Od a e /-//-77 Mgr., O perational Statidd S' perintend[nt/

d Quality Assurance Unit Superintenden't 5

1959 Revision 2 01/14/77 THREE MILE ISLAND NUCLEAR STATION STATION CHEMISTRY PROCEDURE 1959 (Unit i Only)

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Detarmination of E 1.0

SUMMARY

E is defined as the av? rage (mean) beta plus the average (mean) gamma energies per disintegration, in Mev, weighted in proportion to the measured activity of each specific radionuclide in the sample.

A calculation of E for reactor coolant should include a minimum of 95% of those isotopes having a half-life greater than 30 minutes.

The average gamma-ray energy per disintegration is a sum of the gamma and x-rays emitted by each nuclide.

The full gamma-ray energies are multiplied by their respective abundance in the decay scheme and summed.

The x-rcy energy which corresponds to the total binding energy in an internal conversion process is added to the total gamma energy.

Also, the x-ray por. tion of the binding energy in an electron capture event is added to the total gamma energy.

The average beta energy per disintegration is obtained by summing one-third of the maximum beta decay energy and all of the conversion and auger electron energy.

The abundance for each decay process is considered before summation of the total beta energy.

2.0 Accaratus 2.1 As described in Station Chemistry Procedures Nos. 1951, 1952, 1955, 1957 and 1958.

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3.0 REAGENTS 3.1 As described in Station Chemistry Procedures Nos. 1951, 1952, 1955, 1957 and 1958.

1.0 188 158

i 1959 Revision 2 01/14/77 a.0 PROCEDURE 7

4.1 Sampie the RC sy;+em using the bomb as per Station Chemistry Procedure 1957.

4.2 Count the gas aliquot from Step 4.1 on a Ge(Li) detector per Statica Chemistry Procedure No.1958.2 and 1958.3 and recor o the ensul ts on data sheet for isotopes aavinc half-lives greater than 30 minutc;.

4.3 Count the liquid aliquot from Step 4.1 on a GE(Li) detector per Station Chemistry Procedure No.1958.2 and 1958.3 sad record the results on data sheet for isotopes having a half-lives greater than 30 min. Add the sctivities of any gasses still present in the degassed liquid sample to the activities of gasses from Step 4.2.

4.4 Determine the tritium concentration per Station Chemistry Procedure No.1951, Determination of Tritium and record the result on data sheet.

4.5 Determine the concentrations of Sr-89 and SR-90 per Station Chemistry Procedure No.1955, Determination of Strontium and record the results on data sheet.

NOTE:

Analysis may be done by off site laboratory.

4.6 Back calculate the activity of each isotope to the time of initial 89 90 sampling and record on data sheet, i.e. H, Sr and Sr 4.7 From Appendix 1 and Appendix 2 select the average gamma energy (Mev/ dis) and the average beta energy for each isotope present with a half-life greater than 30 min.

Record on data sheet.

4.8 For each isotope having a half-life greater than 30 min, multiply 3

the activity at time of sampling by the average ganh.a energy per disintegration ar.d enter the result in Column 6, multiply the activity at the time of sampling by the average beta energy per J 88 159 2.0 e

i 1959 Revision 2 01/14/77 disintegration ind enter the result in Column 8, add the products obtained in Columns 6 and 8 and enter the result in Column :

4 4.9 Total thr sums of the average beta and gamma energies (Column 9) for all nf the isotopes having greater than 30 min half-lives.

4.10 Total tiie initial activities (time of samoling) for all of the isotopes having greater than 30 min half-lives.

4.11 Calculate E by dividing the total from Step 4.9 by the total from Step 4.10.

4.12 The 9830 Computer Program can also be used to calculate E-Bar.

5.0 REFEREtiCES 5.1 Technical Specifications.

5.2 B&W Radiochemistry Manual.

h 188 160 3.0

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1959 12/14/73 Revision 0 Data Sheet, if Determination

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Sample Date Time Col.1 Col.2 Col.3 Col.4 Col.5 Col.6 Col.7 Col.8 Col.9 Initial Avg. Gamma Avg. Beta Isotope Activity Date/ Time Activity Energy / dis Col.4XCol.5 Energy / dis Col.4XCol.7 Col.6+ Col.8 l

l il 4

i il il Fotals j

E = Totrr Col.9 To ff},' Col.4 C7s 4.0

1959 12/14/73 Revision 0

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Appendix One

- FIssIO:: PnocccTs Isotope Ave. Ca=$a Ave. Beta Energy (MeV/ dis.)

Energy (::eV/ dis.)

Kras 2.11 x 10-3 2.22 x 101 Kr8DI 1.52 x 10-1 2.43 x 10-1 Kr87 1.42 x 10 0

,1.05 x 10-0 Kr88 1.74 x 10 0 3.40 x 10-1 Xc133 4,97 x 10-2

, 1.46 x 10-1

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1.77 x 10-1 Xc133M 5,67 x 10-2 i

Xel35 2.48 x 10-1 ~

3.16 x 10-1 Br64 1.72 x 10 0 9.43 x 10-1 Sr19 8.19 x 10-5 4.37 x 10-1 Sr90 Zero 1.82 x 10-1 Sr91 7.41 x 10-1 5.33 10-1 Sr92 1.26 x 10 0 2.15 x 10 1 Y30 Zero 7.57 x 10-1 Y91 3.63 x 10-3 5.13 x 10-1 Y91M 3.10 x 10-1 2.70 x 10-2 Ys2 2.95 x 10-1 1.13 x 10-0 Nb95

'7.65 x 10-1

' 5.34 x 10-2

'3.65 x 10'~1 Mo99 1.56 x 10-1 1131 3.72 x 10-1 1.95 x 10-1 0

4.22 x 10-1 I132 2.39 x 10 Il33 6.39 x 10-1 4.0S x 10-1 I 34 1.83 x 10~ 0 5.48 x 10-1 1

1135 1.77 x 10 0 3.03 x 10-1 Tc132 2.56 x 10-1 9.97 x 10-2 C.sl34 1.59 x 10 0 1.66 x 10-1 Cs136 2.34 x 10 0 1.37 x 10-I Csl37 5.66 x 10-1 2.36 x 10 2 Csl3C 2.03 x 10 0 8.99 x 10-1 j

Bal39 4.65 x 10-2 7.49 x 10-1 Ba140 2.41 x 10-1 2.83 x 10-1

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La140 2.12 x 10'O 4.36 x 10-1 i--

- - - - - -- - g3gg

. 2.07 x 10-2 -- ~

1.02~x 10-1

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10'{l ( {

l3IM 2.71 x 10-2 1.3 Xc 5.0

.1959 Revision 1 5

9/04/74 APPENDIX T'n'0 - CORROSION PRODUCTS t

Isotope Ave. Gamma Ave. Beta Energy (MeV/ dis.)

Energy (MeV/ dis.)

51

-2

-3 Cr 3.00 x 10 3.69 x 10 Mn 8.36 x 10' 4.16 x 10 '

56 o

_3 Mn 1.76 x 10 6.48 x 10 58

-1

-2 Co 9.82 x 10 2.79 x 10 60 0

-1 Co 2.51 x 10 1.06 x 10 ~

55

_3

_3 Fe 1.75 x 10 5.25 x 10 59 o

_3 Fe 1.19 x 10 1.28 x 19 Zr 7.25 x 10' 1.32 x 10'*

Zr' 8.41 x 10'*

6.07 x 10

  • isoM o

_2 Ag 2.50 x 10 8.13 x 10 187

_g

_g W

4.11 x 10 2.44 x 10 i:

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188 163

,.'1959 Revision 2

,e' 01/14/77 APPENDIX THREE - ACTIVATION PRODUCTS Isotope Ave. Gama Ave. Beta Energy (MeV/ dis.)

Fnergy (MeV/ dis.)

3

-s H

0.000 6.2 x 10 F'

9.91 x 10'*

2.12 x 10~

Ar 1.293 x 10~

3.99 x 10~

2s

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-1 Na 4.123 x 10 4.63 x 10 188 164

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