ML19351A437

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Rev 9 to 9110.PLN-4200.02, Emergency Dose Calculation Manual.
ML19351A437
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 11/30/1989
From:
GENERAL PUBLIC UTILITIES CORP.
To:
References
9110.PLN-4200.0, NUDOCS 8912140003
Download: ML19351A437 (23)
v • d • e


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.- Date /dl @ [9 THI-1 EMERGENCY DOSE, CALCULATION MANUAL (EDCM)

INSTRUCTION MEMO

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  • iRETURNTO: Betty.Nash .

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Procedure Distribution Control '

Unit 2 Admin.-Bldg. . d

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i Please update your Copy of the THI-1 Emergency Dose Calculation Manual (EDCM) as

, instructed below. Also, please s,ign.the acknowledgement at the bottom of-this memo land.. return to Betty Nash as shown above.

REMOVE INSERT

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-ADDITIONAL INSTRUCTIONS / COMMENTS

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I hereby acknowledge receipt of the item above and have complied with the instructions. 3 (Signature) (Ext. No.) (Date)

E- 2175B/0033b DC 8912140003 09113o l PDR ADOCK 05000289 F PNU --

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Nuclear TMI-1 Nueer .

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i j' Title Rtvision No.

TMI Emercency Dose Calculation Manual (EDCM) 9 Applicability / Scope The EDCM is applicable to all qualified Responsible Office Radiological Assessment Coordinators. This manual provides the  !

methods used to,, perform dose projections durino emergencies .. 9100

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This document is within QA plan scope X Yes No Effective Date Safety Reviews Required X Yes No 12/05/89 List of Effective Pages

.j ; Pace Revision Pace Revision Pace Revision Page Revision 1.0 9 27.0 9 53.0 8 79.0 8 2.0 8 28.0 9 54.0 8 80.0 8 3.0 8 29.0 9 55.0 8 81.

4.0- 7 30.0 9 56.0 8 5.0 7 31.0 '9 57.0 8 -8 6.0 7 32.0 9 58.0 8 4 8 7.0 7 33.0 8 59.0 8 8 p 8.0 8 34.0 8 Q 0 .0 8 9.0 7 35.0 ' .0 87.0 8 10.0 7 36.0 62.0 88.0 8 11.0 8 37.0 8 63.0 wV 8 89.0 8 12.0 7 38. 64 90.0 8 13.0 7 39 8 8 91.0 8 14.0 40.0 92.0

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16.0 7 42.0 9 94.0 8 17.0 8 43.0 ' .0 8 5.0 8 18.0 8 44.0 70.0 8 96.0 8 19.0 7 45.0 8 71.0 97.0 8 20.0 7 46.0 72. 98.0 8 l 21.0 8 4 7 99.0 8 22.0 7 8 . 8 100.0 8 l- 23.0 7 49. 8 0 8 101.0 9 L 24.0 8 0. 8 7 8 102.0 8 L 25.0 A .0 8 .0 8 103.0 8 l 26.0 s2.0 8 78.0 8 104.0 8

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ID/ Stanature l Concurrina Organizational Element i Date Orlainatorli bN'dA N8'O I Radioloolcal Encineer I/0"W'27 l Concurred ll ;N l Environmental Scientist I<//r'/f7 l By ll [Yb/'N I Emercency Preparedness l ////1[ff ll' d [ N M e [ b l Radiological Engineering Mgr.TMI-1l [f o 'M" 77 ll bMd 4

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t v r l Mar. Rad Engineerino THI-2 l </<d29/89 p i ll  !  !

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! Approved ll MDdC l Rad Con Director, THI-1 l J i- 30 -M

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) Title- Revistor No. .

TMI Emeraency Dose Calculation Manual (EDCM) l- 9

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Therefore, as an example: NRC Dart. ige Class-6.would consist of-

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100% RCS Activity, plus 100% of the GAP. Activity, plus 53% of the fuel Matrix Activity. ,

5.3.3.I' THI-1 Normal RCS Activity - TMI-l normal RCS Activity (NRC  ;

. Damage Class-1) and the rapid power transient RCS Activity (NRC Damage Class-1A) are Itsted in the next table. The normal RCS Activity is based on operational RCS activity during THI-1, ,

operating cycles.

  • 5.3.3.1.1 Rapid Power Transient RCS Activity represents the " spiking" of the radiolodines during power changes of greater than or equal to 10% over one minute (>10%). The radiolodines are considered-to spike (100) times norEal RCS, and the Noble gases (2) times normal RCS. This activity represents only a spike of radio--

nuclides and not fuel damage.

  • TMI-l NORMAL RCS RAPID POWER TRANSIENT RCS DAMAGE DAMAGE em CLASS 1 CLASS 1A

[V h I-131 I-132 UC1/cc" 4.83E-02 1.91E-01 Percent 0.56 2.21 Curles 1.04E+01 4.09E+01 UCl/cc'*

4.83E+00 1.91E+01 Percent 4.57 18.06 Curies 1.04E+03 4.09E+03

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I-133 1.47E-01 1.71 3.16E+01 1.47E+01 13.93 3.16E+03 I-134 3.01E-01 3.48 6.44E+01 3.01E+01 28.40 6.44E+03 I-135 2.16E-01 2.50 4.62E+01 2.16E+01 20.41 4.62E+03

-SUBTOTAL 9.03E-01 10.46 193.48 9.03E+01 85.38 1.93E+04 KR-85M 1.54E-01 1.78 3.30E+01 3.08E-01 0.29 6.60E+01 KR-85 0.00E+00 0.00 0.00E+00 0.00E+00 0.00 0.00E+00 KR-87 1.65E-01 1.91 3.53E+01 3.29E-01 0.31 7.06E+01 -

KR-88 2.91E-01 3.37 6.23E+01 5.82E-01 0.55 1.25E+02 XE-131M 0.00E+00 0.00 0.00E+00 0.00E+00' O.00 0.00E+00 XE-133M 1.14E-01 1.32 2.44E+01 2.28E-01 0.22 4.88E+01 XE-133' 5.66E+00 65.57 1.21E+03 1.13E+01 10.71 2.43E+03 XE-135M 1.04E-01 1.20 2.23E+01 2.08E-01 0.20 4.46E+01 XE-135 1.07E+00 12.42 2.30E+02 2.15E+00 2.03 4.60E+02 XE-138 1.70E-01 1.97 3.64E+01 3.40E-01 0.32 7.27E+01 SUBTOTAL 7.73E+00 89.54 1656.80 1.55E+01 14.62 3.31E+03 TOTAL 8.64E+00 100.00 1.85E+03 1.06E+02 100.00 2.27E+04 NOBLE GAS TO 8.56 8.56 8.56 0.17 0.17 0.17 IODINE RATIO

  • " NORMAL" RCS CONCENTRATION AND PERCENTAGES ARE FROM NORMAL RCS OPERATIONAL DATA kj **THESE pC1/cc VALUES ARE BASED ON NORMAL RCS VOLUME OF 56,595 GALLONS 26.0 1572c

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Radiological' Controls Department 9100-PLN 4200.02

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Revision No.

TMI Emergency Dose Calculation Manual (EDCM) 9 5.3.3.2 Gap Activity and Fuel Matrix Activity - Gap activity and Fuel Matrix activity used in-the program are determined from.

TDR-431. These curie activities are based on irradiation of the entire core at full power, 2535 MWt ,'for 930 days.

. THI Unit 1

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GAP Fuel Matrig fuel Act, GAP Act.- Matrix ,

Isotope Curles  % Curies  %

-Kr-85m 4.84E+04 0.45 2.13E+07 2.36 Kr-85 7.48E+04 0.70 8.59E+04 0.01: ,

Kr-87 2.63E+04- 0.25 3.90E+07 '4.33 Kr-88 6.67E+04- 0.63 5.91E+07 -6.56 Xe-131m 7.96E+04 0.75 -5.40E+05 0.06 Xe-133m 9.30E+04 0.87 3.09E+06 0.34 Xe-133 8.34E+06 78.31 1.28E+08 14.20 Xe-135m- 2.72E+04 0.26 3.37E+07 3.74 Xe-135 3.45E+04 0.32 1.59E+07 1.76 Xe-138 0.00E+00 0.00 0.00E+00 0.00 I-131 1.29E+06 12.11 6.37E+07 7.07 L j )/ 1-132 1.85E+05 1.74 9.70E+07 10.76 I-133 2.79E+05 2.62 1.43E+08 15.86

'\'#' I-134 1.74E+04 0.16 1.67E+08 18.53 1-135 8.83E+04 0.83 1.30E+08 14.42 Sum 1.13E+07 100.0 Sum 9.02E+08 100.0 i

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Controls Department 9100-PLN 4200.02 Title

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Revision No.

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TMI Emeroency Dose Calculation Manual (EDCM) 9 1 5.3.3.3 The fo11cwthg tables represent the NRC Damage Class 2 - 10 mixes, percentages, curies, and concentrations ussd in the RAC code.

DAMAGE -DAMAGE.

CLASS 2 CLASS 3 __

uCl/cc**- Percent Curiss UC1/cc** ~

Percent Curtes I-131 6.03E+02 12.09 1.29E+05 3.01E+03 12.11 6.45E+05 I-132 8.66E+01 1.74 1.85E+04 4.32E+02 1.74- 9.25E+0A- 1 I-133- 1.31E+02 2.62 2.79E+04 - 6.52E+02 2.62 1.40E+05

l I-134 8.43E+00 0.17 1.80E+03 4.10E+G1 0.16 8-76E+03 .

I-135 4.15E+01 0.83 8.88E+03 ~2.07E+02 0.83 4.42E+04 ,

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I SUBTOTAL 8.70E+02 17.45 1.86E+05 4.35E+03 17.46 9.30E+05 1

KR-85M 2.28E+01 0.46 4.87E+03 1.13E+02 0.45 2.42E+04 l KR-86 3.50E+01 0.70 .7.48E+03- 1.75E+02 0.70 3.74E+04

'KR-87 1.25E+01 0.25 2.67E+03 6.16E+01 0.25 1.32E+04 KR-88 3.15E+01 0.63 6.73C+03 1.56E+02 0.63 3.34E+04 ,

XE-131M 3.72E+01 0.75 7.96E+03 1.86E+02 0.75 3.98E.+04 XE-133M 4.36E+01 0.87 9.32E+03 2.17E+02 0.87 4.65E+04

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XE-133 3.90E+03 78.29 8.35E+05 1.95E+04 78.30 4.17E+06

/ \ XE-135M 1.28E+01 0.26 2.74E+03 6.37E+01 0.26 1.35E+04

~ (' ') XE-135 l1.72E+01 'O.34 3.6BE+03 8.17E+01 0.33 1.75E+04 ,

XE-138 1.70E-01 0.00 3.64E+01 1.70E-01 0.00 3.64E+01 1 SUBTOTAL 4.12E+03 82.55 8.81E+05 2.05E+04 82.54 4.40E+06  ;

l TOTAL 4.99E+03 100.00 1.07E+06 2.49E+04 100.00 5.33E+06 l NOBLE GAS 4.73 4.73 4.73 4.73 4.73 4.73 TO IODINE I RATIO

    • THESE pCl/cc VALUES ARE BASED ON NORMAL RCS VOLUME OF S6.595 GALLONS l l

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e TMI Emeroency Do:L Olculation Manual (EOCM)  ; 9_

DAMAGE DAMAGE CLASS 4 CLASS 5

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uCi/cc** Percent Curies UCi/cc** Percent Curies I-131 6.03E+03 12.11 1.29E+06 3.58E+04 7.60  ?.66E+06 I-132 8.65E+02 1.74 1.85E+05 4.62E+04 9.81 9.89E+06 I-133 1.30E+03 2.62 2.79E+05 6.81E+04. 14.45 1.46E+07 I-134 8.16E+01 0.16 1.75E+04 7.81E+04 '6.59 1.67E+07 I-135 4.13E+02 0.83 8.83E+04 6.12E+04 12.99 .l.31E+07

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SUBTOTAL 8.69E+03 17.46 1.86E+06 2.89E+05- 61.44 6.19E+07

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KR-65M 2.26E+02 0.45 4.84E+04 1.02E+04 2.16 2.18E+06  !

KR-85 3.50E+02 0.70 7.48E+04 3.90E+02 0.08 8.34E+04 KR-87 1.23E+02 0.25 2.63E+04 1.83E+04 3.90 3.93E+06

'KR-88 3.12E+02 0.63 6.68E+04 2.79E+04 5.93 5.98E+06 1 XE-131H 3.72E+02 0.75 7.96E+04 6.24E+02 0.13 1.34E+05 l XE-133M. 4.35E+02 0.87 9.30E+04 1.88E+03 0.40 4.02E+05  ;

3.90E+04 78.31 8.34E+06 9.88E+04 20.97 2.11E+07 -l XE-133 XE-135M 1.27E+02 0.26 2.72E+04 1.59E+04 3.37 3.40E+06.

XE-135 1.62E+02 0.33 3.47E+04 7.59E+03 1.61 1.62E+06 XE-138 1.70E-01 0.00 3.64E+01 1.70E-01 0.00 3.64E+01

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SUBTOTAL 4.'ITE+04 82.54 8.79E+06 1.82E+05 38.56 3.89E+07 ] ;

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TOTAL 4.98E+04 100.00 1.07E+07 4.71E+05 100.00 1.01E+08 NOBLE GAS 4.73 4.73 4.73 0.63 0,63 0.63 IODINE i RATIO

'THESE pC1/cc VALUES ARE BASED ON NORMAL RCS VOLUME OF 56,595 GALLONS l

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TMI Emergency Dose Calculation Manual (EOCM) 9 3

OAMAGE DAMAGE CLASS 6 CLASS 7 uCt/cc** Percent Curies uC1/cc*^ Percent Curies 1-13I 1.55E+05 7.18 3.31E+07 3.04E+05 7.13 6.50E+07 I-132 2.28E+05 10.55 4.87E+07 4.54E+05 10.66 9.72E+07 I-133 3.35E+05 15.56 7.18E+07 6.70E+05 15.71 1.43E+08 I-134 3.90E+05 18.10 8.35E+07 7.80E+05 18.31 1.67E+0B I-135 3.04E+05 14.11 6.51E+07- 6.08E+05 14.26 1.30E+08 5UBTOTAL 1.41E+06 65.50 3.02E+08 2.82E+06 66.07 6.03E+08 KR-85M 5.00E+04 2.32- 1.07E+07 9.98E+C4 2.34 2.13E+07 KR-65 5.50E+02 0.03 1.18E+05 7.51E+02 0.02 1.61E+05 KR-87 9.1?.E+04 4.23 1.95E+07 1.82E+05 4.28 3.90E+07 KR-88 1.38E+05 6.42- 2.96E+07 2.76E+05 6.49 5.92E+07 XE-131H 1.63E+03 0.08 3.50E+05 2.90E+03 0.07 6.20E+05 XE-133M 7.65E+03 0.36 1.64E+06 1.49E+04 0.35 3.18E+06 XE-133 3.38E+05 15.68 7.23E+07 6.37E+05 14.95 1.36E+08 XE-135M 7.89E+04 3.66 1.69E+07 1.58E+05 3.70 3.37E+07 XE-135 3.73E+04 1.73 7.98E+06 7.45E+04 1.75 1.59E+07 XE-138 - 1.70E-01 0.00 3.64E+01 1,70E-01 0.00 3.64E+01

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SUBTOTAL 7,44E+05 34,50 1.59E+08 1.45E+06 33.93 3.10E+08

'd TOTAL 2.16E+06 100.00 4.61E+08 4.26E+06 i00.00 9.12E+08

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NOBLE GAS 0.53 0.53 0.53 0.51 0.51 0.51 IODINE RATIO

    • THESE pCi/cc VALUES ARE BASED ON NORMAL RCS VOLUME OF 56.595 GALLONS 1

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  • ('~Tv)-THI~Errercency Ocse Calculation Manual (EDCM)

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9 DAMAGE DAMAGE CLASS 8 CLASS 9 uCt/cc'* Percent Curies uC1/cc'*- Percent Curies I-131 3.04E+05 7.13 6.50E+07 3.04E+05 7.13 6.50;+07 I-132 4.54E+05 10.66 9.72E+07- 4.54E+05 10.66 9.72E+07 I-133 6.70E+05 1 5.71 1.43E+08 6.70E+05 15,71- 1.43E+08 I-134 7.80E+05 18.31 1.67E+08 7.80E+05 18.31 1.67E+08 I-135 6.08E+05 14.26- 1.30E+08 6.08E+05 14.26 1.30E+08 SUBTOTAL 2.82E+06 66.07 6.03E+08 2.82E+06 66.07 6.03E+08  !

KR-85M ~9.98E+04 2.34' 2.13E+07 9.98E+04 2.34 2.13E+07 KR-85 7.51E+02 0.02 1.61E+05 7.51E+02 0.02 1.61E+05 KR-87 1.82E+05 4.28 3.90C+07 1.82E+05 4.28 3.90E+07 KR-88 2.76E+05 6.49 5.92E+07 2.76E+05 6.49 5.92E+07 XE-131M 2.90E+03 0.07 6.20E+05 2.90E+03 0.07 6.20E+05 XE 133M 1.49E+04 0.35 3.18E+06 1.49E+04 0.35 3.18E+06 XE-133 6.37E+05 14.95 1.36E+08 6.37E+05 14.95 1.36E+08 XE-135M 1.58E+05 3.70 3.37E+07 1.58E+05 3.70 3.37E+07 XE-135 7.45E+04 1.75 1.59E+07 7.45E+04 1.75 1.59E+07 XE-138 1.70E-01 0.00 - 3.64E+01 1.70E-01 0.00 3.64E+01

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f SUBTOTAL .l.45E+06- 33.93 3.10E+08 1.45E+06 33.93 3.10E+08

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TOTAL- 4.26E+06 100.00 9.12E+08 4.26E+06 100.00 9.12E+08 NOBLE GAS 0.51- 0.51 0.51 0.51 0.51 0.51 IODINE-RATIO

    • THESE pC1/cc VALUES ARE BASED ON NORMAL RCS VOLUME OF 56.595 GALLONS

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,,_311,E.1*ercencyDose_CalculationManual(EDCM) 9

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DAMAGE CLASS 10 uC1/cc'* Percent Curies I-131 3.04E+05 7.13 6.50E+07 I-132 4.54E+05 10.66- 9.?2E+07 ,

I-133 6.70E+05 15.71 1.43E+08 I-134 7.80E+05 18.31 1.67E+0B I-135 6.08E+05 14.26 1.30E+08 SUBT07AL 2.82E+06 66.07 6.03E+08 KR-85M 9.98E+04 2.34 -.13E+07 KR-85 7.51E+02 0.02 1.61E+05 KR-87 1.82E+05 4.28 3.90E+07 iR-88 2.76E+05 6.49 5.92F.+07 XE-131M 2.90E+03 0.07 6.20E+05 XE-133M 1.49E+04 0.35 3.18E+06 XE-133 6.37E+05 14.95 1.36E+08 XE-135M 1.58E+05 3.70 3.37E+07 XE-135 7.45E+04 1.75 1.59E+07 XE-138 1.70E-01 0.00 3.64E+01

/h t / \ SUBIOTAL 1.45E+0f. 33.93 3.10E+08

(= ]

i 70TAL 4.26E+06 100.00 9.12E+08 NOBLE GAS 0.51 0,51 0.51 10 DINE RATIO "THESE pC1/cc VALUES ARE BASED ON NORMAL RCS VOL'?4E OF 56.595 GALLONS 5.3.3.4 Calculation of RadioNclide Mix Percentages - Once the computer has determined the total amount of combined activities or curies for a certain NRC Damage Class, these curies are then normali;:ed to 100%, i.e., the percentage of each radionuclide in the total mix is cait.ulated. These percentages are then disp 1Syed on the screen along wi n the NRC Damage Class, 1 - 10.

Exceptions - The above percentages are replaced in cases where an assumed mix is more appropriate. These cases are:

1. Contingency calculations for:
a. Spent Fuel Accident in the Fuel Handling Building -

FSAR mix is assumed.

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4. Default to a RCS concentration dependent on the NRC Damage Class:

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RCS Default NRC Damage CIR$$ UCi/cc i

i 1 8.64E+00 IA 1.06E+02 2 4.99E+03 3 2.49E+04 4 4.98E+04 5 4.71E+05 6 2.16E+06 ,

7 4.26E+06 8 4.26E+06 9 4.26E+06 10 4.26E+06 '

5.6.2.2 The " Primary to Secondary Leakage" is determined utilizing:

1. RCS tdentified leakage (D2) gpm
2. Default to 400 gpm for a double-ended tube shear (D2) ,

'f 5.6.2.3 The " Transport Fraction" (D3) is a function of the release I pathway. (03) is calculated by the equation: D3.Fr *

! 0.0075 + (1-Fr) where Fr fraction of the release via the '

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condenser off-gas. For a r61 ease through the condenser off-gas the noble gas transport is l'.00, the radiotodine transport '

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fraction is 0.0075. The radiolodine trrnsport fraction is a product of: The fraction of radiciodine entering the OTSG from '

the RCS thst is a volatile lodine species (.05) and the partition factors for volatile looine species in the main condenser (.15). k a-vo!attle iodine species have a partition factor of zero in the condenser off-gas. For a release direct to atmosphere the noble gas and radiolodine transport fractions use the fraction of steam released to total steam flow from the OTSG. An additional partition factor (Tfcf) is applicable for ,

a two phase direct release. The resultant source terms in pC1/sec are calculated by:

l Ngst = DI

  • D2
  • Ng/100
  • 63.09 Rist D1
  • D2
  • D3
  • RI/100
  • 63.09
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TMI Emercency Dose Calculation Manual (EDCM) 9

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i 5.6.3 A " Reactor Building Release" is calculated by one of two l methods. If the accident type is a LOCA then four parameters  !

are identified:

1

1. RCS Activity (A2) pC1/cc l

?. RCS Leakage to RB (A3) gpm

3. Transport Fraction. E4 0.1 or 1.0 depending on the ,

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Reactor Building Spray status 4 Release Flow Rate CFM; E3 flow

  • 472 to convert CFM to I cc/sec

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5.6.3.1 The RCS Activity is determined utilizing:

1. RM-L1 High Channel (All com; (A2) (A1)/22.2 pCi/cc
2. RM-L1 Low Channel (All cpm; [A2) . [A1)/1270 pC1/cc
3. Representative RCS Sample results (A2) in pCl/cc l 4. Default to a RCS concentration dependent on the NRC Damage

( ,/ Class:

RCS Default NRC Damage Class uti/cc 1 8.64E+00 1A 1.06E+02 2 4.99E+03 3 2.49E+04 4 4.98E+04 5 4.71E+05 6 2.16E+06 7 4.26E+06 8 4.26E+06 9 4.26E+06 10 4.26E+06

4. Default mix according to core condition as previously identified. The noble gas and radiolodine released to the ,

Reactor Building is calculated as follows:

E1 . A2

  • A3
  • Ng/100
  • 3785/5.6E10 pCi E2 A2
  • A3
  • R1/100
  • 3785/5.6E10 pC)

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7.0 REFERENCES

i 7.1 American National Standard (ANS), ANSI /ANS-18.1 - 1984, Radioactive Source I i

Term for Normal Operations of Light Water Reactors 7.2 APS Source Term Report - Report to the American Physical Society of the Study Group on Radionuclide Releases From Severe Accidents at Nuclear Power Plants, February 1985

.

7.3 Dose Assessment Manual for Emergency Preparedness Coordinators, February 1986, INPO 86-008 7.4 EDCM Flowchart Block Diagram 7.5 Efficiency Check using an Air 1-131 Source Cartridge and a Ba-133 Source Cartridge, Memorandum 9502-88-Oi39 September 28, 1988 7.6 Emergency Dose Calculation Manual (EDCM) Source Code Listing ,

7.7 EPA 520/1-75-001 - Manual of Protective Action Guides and Protective Actions for Nuclear Incidents ,

V 7.8 EPIP 6415 IMP-1300.07 - Off-site /On-site Dose Projections 7.9 Evaluation of a Front Loaded Iodine Cartridge using Various Survey

,

Equipment, Memorandum 9100-88-0194, May 12, 1988 7.10 Field Measureuents of Airborne Releases of Radioactive Material, Memorandum 9502-88-0098, May 25, 1988 7.11 FSAR, THI-l Chapter 11, Radioactive Waste and Radiation Protection 7.12 FSAR, THI-1 Chapter 14 - Safety Analysis 7.13 FSAR, THI-2, Volume 10, Section 15, Accident Analysis 7.14 GPUNC Emergency Plan, 1000-PLN-1300.01 7.15 GPUNC Emergency Preparedness Program, 1000-ADM-1319.01 7.16 ICRP Report of the Task Group on Reference Man, 1981 7.17 INPO SOER 83-2 " Steam Generator Tube Ruptures" 7.18 Introduction to Health Physics, Herman Cember, 2nd Edition, 1985 b)

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TMI Emercency Dose Calculation Manual (EDCM) 9 Applicability / Scope The EDCM is applicabic to all qualified Responsible OfficT  !

Radiolo9ttal Assessment Coordinators. This manuti provides the methods used to perform dose projections durino emeroencies 9100 This document is within QA plan scope 1 Yes _

No Effective Date Safety Reviews Required X,,_ Yes No

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12/05/89 List of Effective Pages Pace Revision D_ge Revision Page Revision Pace Revision 1.0 9 27.0 9 53.0 8 7 9.0 8 2.0 8 28.0 9 54.0 8 80.0 8 3.0 8 29.0 9 55.0 8 81  !'

4.0 7 30.0 9 56.0 8 5.0 7 31.0 9 57.0 8 8 i 6.0 7 32.0 9 58.0 8 4. 8 7.0 7 33.0 8 59.0 8 8 8.0 8 34.0 8 9 0 6.0 8 9.0 7 35.0 .0 87.0 8 10.0 7 36.0 62.0 88.0 8 11.0 8 37.0 8 63.0 K 89.0 8 12.0 7 38. 64 V 90.0 8 13.0 7 39 8 8 91.0 8

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,Ortainatorll SIMMY2<N MM*"' l Radiotecital Eneineer I /b y 'z' ?

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ll MP[A~[ kV" l Mar. Rad Engineerino TM,I-2

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Therefore, as an example: NRC Damage Class-6 would consist of '

100% RCS Activity, p.in 100% of the GAP Activity, p. lyt 50% of the Fuel Matrix Activity.

r 5.3.3.1 TMI-1 Normal RCS Activity - TMI-1 normal RCS Activity (NRC  :

Damage C1455-1) and the rapid power transient RCS Activity (NRC Damage Class-1A) are listed in the next table. The normal RCS '

Activity is based on operational RCS activity during TMI-I  ;

operating cycles.

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5.3.3.1.1 Rapid Power Transient RCS Activity represents the " spiking" of the radiolodines during power changes of greater than or equal to 10% over one minute Q10%). The radiciodines are considered to spike (100) times normal RCS, and the Noble gases (2) times .

normal RCS. This activity represents only a spike of radio-nuclides and not fuel damage.

  • THI-I NORMAL RCS RAPIO POWER TRANSIENT RCS DAMAGE DAMAGE o CLASS 1 CLASS 1A j j uC1/cc** Percent Curtes uCi / c e' Percent Curies

(~j - 1-131 4.83E-02 0.56 1.04E+01 4.83E+00 4.57 1.04E+03 1-132 1.91E-01 2.21 4.09E+01 1.91E+01 18.06 4.09E+03 1-133 1.47E-01 1.71 3.16E+01 1.47E+01 13.93 3.16E+03 I-134 3.01E-01 3.48 6.44E+01 3.01E+01 28.40 6.44E+03 1-135 2.16E-01 2.50 4.62E,01 2.16E+01 20.41 4.62E+03

.

SUBIOTAL 9.03E-01 10.46 193.48 9.03E+01 85.38 1.93E+04 KR-85M 1.54E-01 1.78 3.30E+01 3.08E-01 0.29 6.60E+01 KR-85 0.00E+00 0.00 0.00E+00 0.00E+00 0.00 0.00E+00 KR-87 1.65E-01 1.91 3.53E+01 3.29E-01 0.31 7.06E+01 KR-88 2.91E-01 3.37 6.23E+01 5.82E-Oi 0.55 1.25E+02 XE-131M 0.00E+00 0.00 0.00E+00 0.00E+00 0.00 0.00E+00 XE-133M 1.14E-01 1.32 2.44E+01 2.28E-01 0.22 4.88E+01 XE-133 5.66E+00 65.57 1.21E+03 1.13E+01 10.71 2.43E+03 XE-135M 1.04E-01 1.20 2.23E+01 2.08E-01 0.20 4.46E+01 XE-135 1.07E+00 12.42 2.30E+02 2.15E+00 2.03 4.60E+02 XE-138 1.70E-01 1.97 3.64E+01 3.40E-01 0.32 7.27E+01 SUBTOTAL 7.73E+00 89.54 1656.80 1.55E+01 14.62 3.31E+63-TOTAL B.64E+00 100.00 1.85E+03 1.06E+02 100.00 2.27E+04 NOBLE GAS TO 8.56 8.56 8.56 0.17 0.17 0.17 IODINE RATIO O * " NORMAL" RCS CONCENTRATION AND PERCENTAGES ARE FROM NORMAL RCS OPERATIONAL DATA C/ 'THESE pC1/cc VALUES ARE BASED ON NORMAL RCS VOLUME OF 56.595 GALLONS 26.0 1572c

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_( ) ittle Revision No. l TMI Emercency Dose Calculation Manual (EDCM) 9 l 5.3.3.2 Gap Activity and Fuel Matrix Activity - Gap activity and Fuel Matrix activity used in the program are determined from j TDR-431. These curie activities are based on irradiation of the entire core at full power, 2535 MW t, for 930 . days. ,

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TMI Unit 1 GAP Fuel Matrix Fuel Act. GAP Act. Matrix l Isotope Ceries  % Curies  % i Kr-85m 4.84E+04 0.45 2.13E+07 2.36 Kr-85 7.48E+04 0.70 8.59E+04 0.01 >

Kr-87 2.63E+04 0.25 3.90E+07 4.33 I Kr-88 6.67E+04 0.63 5.91E+07 6.56 Xe-131m 7.95E+04 0.75 5.40E+05 0.06 Xe-133m 9.30E+04 0.87 3.09E+06 0.34 Xe-133 8.34E+06 78.31 1.28E+0S 14.20 Xe-135m 2.72E+04 0.26 3.37E+07 3.74 Xe-135 3.45E+04 0.32 1.59E+07 1.76 l

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Xe-138 0.00E+00 0.00 0.00E+00 0.00 I-131 1.29E+06 12.11 6.37E+07 7.07

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'v I-132 I-133 1.85E+05 2.79E+05 1.74 2.62 9.70E+07 1.43E+08 10.76 15.86

  • 0.16 18.53 I-134 1.74E+04 1.67E+08 4 1-135 8.83E+04 0.83 1.30E+08 14.42 I Sum 1.13E+07 100.0 Sum 9.02E+08 100.0 l

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5.3.3.3 The following tables represent the NRC Damage Class 2 - 10 mires, percentages, curies, and concentrations used in the RAC Code.

DAMAGE DAMAGE CLASS 2 CLASS 3

~~" uC) / c c " Percent Curies UC1/ c c" Percent Curtes 1-131 6.03E+02 12.09 1.29E+05 3.01E+03 12.11 6.45E+05 1-132 8.66E+01 1,74 1.85E+04 4.32E+02 1.74 9.25E+04 1-133 1.31E+02 2.62 2.79E+04 6.52E+02 2.62 1.40E+05 I-134 8.43E+00 0.17 1.80E+03 4.10E+01 0.16 8.76E+03 1-135 4.15E+01 0.83 8.88E+03 2.07E+02 0.83 4.42E+04 SUBTOTAL 8.70E+02 17.45 1.86E+05 4.35E+03 17.46 9.30E+05  ;

KR-85M 2.28E+01 0.46 4.87E+03 1.13E+02 0.45 2.42E+04 KR-85 3.50E+01 0.70 7.48E+03 1.75E+02 0.70 3.74E+04 KR-87 1.25E+01 0.25 2.67E+03 6.16E+01 0.25 1.32E+04 KR-88 3.15E+01 0.63 6.73E+03 1.56E+02 0.63 3.34E+04 XE-131M 3.72E+01 0.75 7.96E+03 1.86E+02 0.75 3.98E+04 >

XE-133M 4.36E+01 0.87 9.32E+03 2.17E+02 0.87 4.65E+04 rx XE-133 3.90E+03 76.29 8.35E+05 1.95E+04 78.30 4.17E+06 l  ; XE-135M 1.2EE+01 0.26 2.74E+03 6.37E+01 0.26 1.35E+04 V XE-135 XE-138 1.72E+01 1.70E-01 0.34 0.00 3.68E+03 3.64E+01 8.17E+01 1.70E-01 0.33 0.00 1.75E+04 3.64E+01 SUBTOTAL 4.12E+03 82.55 8.81E+05 2.05E+04 82.54 4.40E+06 TOTAL 4.99E+03 100.00 1.07E+06 2.49E+04 100.00 5.33E+06 NOBLE GAS 4.73 4.73 4.73 4.73 4.73 4.73 TO IODINE RATIO

'THESE pCl/cc VALUES ARE BASED ON NORMAL RCS VOLUME OF 56.595 GALLONS

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THI Emeroency Dose Calculation Manual (EOCM) 9 DAMAGE CAMAGE CLASS 4 CLASS 5 uC1/cc** Percent Curles uC1/ce'* Percent Curies 1-131 6.03E+03 12.1) 1.29E+06 3.58E+04 7.60 7.66E+C6

'I-132 8.65E+02 1.74 1.85E+05 4.62E+04 9.81 9.89E+06 1-133 1.30E+03 2.62 2.79E+05 6.81E+04 14.46 1.46E+07 l-134 8.16E+01 0.16 1.75E+04 7.81E+04 16.59 1.67E+07 I-135 4.13E+02 0.83 8.83E+04 6.12E+04 12.99 1.31E+07 SUBTOTAL 8.69E+03 17.46 1.86E+06 2.89E+05 61.44 6.19E+07 KR-85M 2.26E+02 0.45 4.84E+04 1.02E+04 2.16 2.18E+06 KR-85 3.50E+02 0.70 7.48E+04 3.90E+02 0.08 8.34E+04 KR-87 1.23E+02 0.25 2.63E+04 1.83E+04 3.90 3.93E+06 KR-86 3.12E,02 0.63 6.68E+04 2.79E+04 5.93 5.98E+06 XE-131M 3.72E+02 0.75 7.96E+04 6.24E+02 0.13 1.34E+05 XE-133M 4.35E+02 0.87 9.30E+04 1.BBE+03 0.40 4.02E+05 XE-133 3.90E+04 78.31 8.34E+06 9.88E+04 20.97 2.11E+07 XE-135H 1.27E+02 0.26 2.72E+04 1.59E+04 3.37 3.40E+06 XE-135 1.62E+02 0.33 3.47E+04 7.59E+03 1.61 1.62E+06 XE-138 1.70E-01 0.00 3.64E+01 1.70E-01 0.00 3.64E+01

["'T SUBTOTAL 4.11E+04 82.54 8.79E+06 1.82E+05 38.56 3.89E+07

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TOTAL 4.98E,04 100.00 1.07E+07 4.71E+05 100.00 1.01E+08 NOBLE GAS 4.73 4.iJ 4.73 0.63 0.63 0.63  !

IODINE RATIO "THESE pC1/cc VALUES ARE BASED ON NORMAL RCS VOLUME OF 56.595 GALLONS r

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DAMAGE DAMACE CLASS 6 CLASS 7 uC1/cca

  • Percent Curies uCl/cc'* Percent Curies I-131 1.55E+05 7.18 3.31E+07 3.04E+05 7.13 6.50E+07 I-132 2.28E+05 10.55 4.87E+07 4.54E+05 10.66 9.72E+07 I-133 3.35E+05 15.56 7.18E+07 6.70E+05 15.71 'l.43E+08 I-134 3.90E+05 18.10- 8.35E+07 7.80E+05 18.31 1.67E+08 I-135 3.04E+05 14.11 6.51E+07 6.08E+05 14.26 1.30E+08 SU8 TOTAL I.41E+06 65.50 3.02E+08 2.82E+06 66.07 6.03E+08' KR-85M 5.00E+04 2.32 1.07E+07 9.98E+04 2.34 2.13E+07 KR-85 5.50E+02 0.03 1.18E+05 7.51E+02 0.02 1.61E.05 KR-87 9.12E+04 4.23 1.95E+07 1.82E+05 4.28 3.90E+07 KR-88 1.38E+05 6.42 2.96E+07 2.76E+05 6.49 5.92E+07 XE-131M 1.63E+03 0.08 3.50E+05 2.90E+03 0.07 6.20E+05 XE-133M 7.65E+03 0.36 1.64E+06 1.49E+04 0.35 3.18E+06 XE-133 3.38E+05 15.68 7.23E+07 6.37E+05 14.95 1.36E+08 XE-135M 7.89E+04 3.66 1.69E+07 1.58E+05 3.70 3.37E+07 XE-135 3.73E+04 1,73 7.98E+06 7.45E+04 1.75 1.59E+07 XE-138 1.70E-01 0.00 3.64E+01 1.70E-01 0.00 3.64E+01  ;

( SUBTOTAL 7.44E+05 34.50 1.59E+08 1.45E+06 33.93 3.10E+0S TOTAL 2.16E+06 100.00 4.61E+08 4.26E+06 100.00 9.12E+08

. NOBLE GAS 0.53 0.53 0.53 0.51 0.51 0.51 IODINE RATIO "THESE pC1/cc VALUES ARE BASED ON NCRMAL RCS VOLUME OF 56.595 CALLONS

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TMI Emeraency Dose Calculation Manual (EDCM) 9 OAMAGE DAMAGE CLASS 8 CLASS 9 UCt/cc** Percent Curies uCi/cc** Percent Curies 1-131 3.04E+05 7.13 6.50E+07 3.04E+05 7.13 6.50E+07 I-132 4.54E+05 10.66 9.72E+07 4.54E+05 10.66 9.72E+07 I-133 6.70E+05 15.71 1.43E+08 6.70E+05 15.71 1.43E+08 I-134 7.80E+05 18.31 1.67E+08 7.80E+05 18.31 1.67E+08 I-135 6.08E+05 14.26 1.30E+08 6.08E+05 14.26 1.30E+08 SUBTOlAL 2.82E+06 66.07 6.03f*08 2.82E+06 66.07 6.03E+08 KR-85M 9.98E+04 2.34 2.13E+07 9.98E+04 2.34 2.13E+07 I

KR-85 7.51E+02 0.02 1.61E+05 7.51E+02 0.02 1.61E+05 KR-87 1.82E+05 4.28 3.90E+07 1.82E+05 4.28 3.90E+07 KR-88 2.76E+05 6.49 5.92E+07 2.76E+05 6.49 5.92E+07 XE-131M 2.90E+03 0.07 6.20E+05 2.90E+03 0.07 6.20E+05  :

XE-133M 1.49E+04 0.35 3.18E+06 1.49E+04 0.35 3.18E+06 XE-133 6.37E+05 14.95 1.36E+08 6.37E+05 14.95 1.35E+08 i XE-135M 1.58E+05 3.70 3.37E+07 1.58E+05 3.70 3.37E+07 i XE-135 7.45E+04 1.75 1.59E+07 7.45E+04 1.75 1.59E+07 I XE-138 1.70E-01 0.00 3.64E+01 1.70E-01 0.00 3.64E+01

/ } SUBTOTAL 1.45E+06 33.93 3.10E+08 1.45E+06 .R 93 3.10E+08 i

TOTAL 4.26E+06 100.00 9.12E+08 4.26E+06 100.00 9.12E+08 NOBLE GAS 0.51 0.51 0.51 0.51 0.51 0.51  !

IODINE RATIO

    • THESE pC1/cc VALUES ARE BASED ON NORMAL RCS VOLUME OF 56,595 GALLONS

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CLASS 10 uCi/cc** Percent Curies 1-131 3.04E+05 7.I3 6.50E+07 1-132 4.54E+05 10.66 9.72E+07 I-133 6.70E+05 15.71 1.43E+08 I-134 7.80E+05 18.31 1.67E+08 I-135 6.08E+05 14.26 1.30E+08 SUBTOTAL 2.82E+06 66.07 6.03E+08 KR-85M 9.98E+04 2.34 2.13E+07 KR-85 7.51E+02 0.02 1.61E+05 KR-87 1.82E+05 4.28 3.90E+07 KR-88 2.76E+05 6.49 5.92E+07 XE-131M 2.90E+03 0.07 6.20E+05 XE-133M 1.49E+04 0.35 3.18E+06 XE-133 6.37E+05- 14.95 1.36E+08 XE-135M 1.58E+05 3,70 3.37E+07 XE-135 7.45E+04 1.75 1.59E+07 XE-138 1.70E-01 0.00 3.64E+01 SUBTOTAL 1.45E+06 33.93 3.10E+08 70TAL 4.26E+06 100.00 9.12E+08 NOBLE GAS 0.51 0.51 0.51 IODINE RATIO "THESE pC1/cc VALUES ARE BASED ON NORMAL RCS VOLUME OF 56,595 GALLONS 5.3.3.4 Calculation of Radionuclide Mix Percentages - Once the computer has determined the total amount of combined activities or curies for a certain NRC Damage Class, these curies are then normalized to 1007., i.e., the percentage of each radionuclide in the total mix is calculated. These percentages are then displayed on the screen along with the NRC Damage Class, 1 - 10.

Exceptions - The above percentages are replaced in cases where an assurred mix is more appropriate. These cases are:

1. Contingency calculations for:
a. Spent Fuel Accident in the Fuel Handling Building -

FSAR mix is assumed.

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4. Default to a RCS concentration dependent on the NRC Damage Class:  !
  • RCS Default NRC Damaae Class uC1/cc 1 8.64E+00 1A 1.06E+02 2 4.99E+03 3 2.49E+04 4 4.98E+04 5 4.71E+05 6 2.16E+06 7 4.26E+06 8 4.26E+06 9 4.26E+06 10 4.26E+06 5.6.2.2 The " Primary to Secondary Leakage" is determined utilizing:
1. RCS identified leakage (02) gpm-f 2. Default to 400 gpm for a double-ended tube shear (D2)

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5.6.2.3 The " Transport Fraction" (D3) is a function of the release pathway. (D3) is calculated by the ecuation: D3 Fr

  • 0.0075 + (1-Fr) whera Fr fractica of the' release-vla the condenser off-gas. For a release through the condenser off-gas the noble gas transport is 1.00, the radioiodine transport fraction is 0.0075. The radiotodine transport fraction is a product of: The fraction of radiotodine entering the OTSG from the RCS that is a volatile iodine species (.05) and the partition factors for volatile iodine species in the main condenser (.15). Non-volatile iodine species have a partition factor of zero in the condenser off-gas. For a release direct to atmosphere the noble gas and radiolodine transport fra:tions use the fraction of steam released to total steam flow from the -

OTSG. An additional partition factor (Tfcf3 is applicable fer ,

a two phase direct relea?e. The resultant source terms in pC1/sec are calculated t,y:

Ngst = 01

  • 02
  • Ng/100
  • 63.09 A st = DI
  • 02
  • 03
  • RI/100
  • 63.09
  • 1/Tfcf.

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5.6.3 A " Reactor Building Release" is calculated by one of two  !

methods. If the accident type is a LOCA then four parameters

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are identified:

  • 1. RCS Activity (A2] pCl/cc i
2. RCS Leakage to RB (A3] gpm

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n 3. Transport Fraction E4 0.1 or 1.0 depending on the Reactor Butiding Spray status

4. Release Flow Rate CFM; E3 . flow
  • 472 to convert CFM to cc/sec

5.6.3.1 The RCS Activtty is determined utilizing:

1. RM-L1 High Channel (A1) cpm; (A2) . (A1)/22.2 pC1/cc

.

2. RM-L1 Low Channel (A1) com; (A2) . (A1)/1270 pC1/cc i
3. Representative RCS sample results (A2) in pCi/cc

,+

-( j' 4. Default to a RCS concentration dependent on the NRC Damage (A Class:

RCS Default NRC Damage Class UC1/cc 1 8.64E+00 1A 1.06E+02 2 4.99E+03 3 2.49E+04' 4 4.98E+04 '

5 4.71E+05 6 2.16E+06 7 4.26E+06 8 4.26E+06 9 4.26E+06 10 4.26E+06

4. Default mix accordir.g to core condition as previously ,

identifico. The noble gas and radiolodine released to the Reactor Butiding is calculated as follows:

El s. A2

  • A3
  • Ng/100
  • 3785/5.6E10 pC1

.

'

E2 . A2

  • A3
  • R1/100
  • 3785/5.6E10 pCi

-

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. Nucisar THI-1 Nueer

'('v's) Radiolocical Controls Department 9100-PLN 4200.02 Revision No.

ittie TMI Emeraency Dose Calculation Manual (EDCM) l' 9

,

7.0 REFERENCES

7.1 American National Standard (ANS) ANSI /ANS-18.1 - 1984, Radtonctive Source

!crut for Normal Operations of Light Water Reactors 7.2 APS Source Term Report - Report to the American Physical Society of the >

Study Group on Radionuclide Releaset from Severe Accidents at Nuclear Power P) ants, february 1985 7.3 Dose Assessment Manual for Emergency Preparedness Coordinators February 1986, INPO 86-008 ,

7.4 EDCM Flowchart Block Otagram .

7.5 Efficiency Check using an Air I-131 Source Cartridge and a Ba-133 Source Cartridge, Menorandum 9502-88-0139. September 28, 1988 7.6 Emergency Dose Calculation Manual (EOCM) Source Code Ltsting

'

7.7 EPA 520/1-75-001 - Manual of Protective Action Guides and Protective n Actions for Nuclear Incidents 7.8 EPIP 6415-IMP-1300.07 - Off-site /On-site Dose Projections 7.9 Evaluation of a Front Loaded Iodine Cartridge using Various Survey .'

Equipment, Memorandum 9100-63-0194, May 12, 1988

'

7.10 Field Measurements of Airborne Releases of Radioactive Material, Memorandum 9502-88-0098, May 25, 1988 7.11 FSAR, THI-1 Chapter 11, Radioactive Waste and Radiation Protection 7.12 FSAR, THI-1 Chapter 14 - Safety Analysts 7.13 FSAR, TMI-2, Volume 10. Section 15. Accident Analysis 7.14 GPUclC Emergency Plan, 1000-PLN-1300.01 7.15 GPUNC Emergency Preparedness Program, 1000-ADM-1319.01 7.16 ICRP Report of the Task Group on Reference Man, 1981 7.17 INPO SOER 83-2 " Steam Generator Tube Ruptures" 7.18 Introduction to Health Physics, Herman Cember, 2nd Edition, 1985 l

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