ML021150047
| ML021150047 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/17/2002 |
| From: | George Gellrich AmerGen Energy Co |
| To: | Document Control Desk, NRC/FSME |
| References | |
| +kBR1SISP20060424, -RFPFR, 5928-02-20095, RG-1.021, Rev 1 | |
| Download: ML021150047 (126) | |
Text
TMI - Unit I Radiological Controls Procedure Number Title Revision No.
Ofsite Dose Calculation Manual (ODCM).22 TABLE 4.5 Atmospheric Dispersion Factors for Three Mile Island
- GROUND RELEASE DISTANCE SECTOR AVERAGE X/Q (IN SECIM3)
(IN METERS)
SEASON - ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N
1.16E-05 1.13E-06 5.94E-07 3.80E-07 2.38E-07 9.74E-08 3.45E-08 9.28E-09 3.52E-09 2.05E-09 NNE 1.08E-05 1.10E-06 5.66E-07 3.41E-07 2.38E-07 9.55E-08 3.11 E-08 8.94E-09 3.74E-09 1.84E-09 NE 7.02E-06 9-81E-07 5.42E-07 3.17E-07 2.10E-07 9.01E-08 3.10E-08 8.87E-09 3.54E-09 1.91E-09 ENE 7.14E-06 9.64E-07 4.92E-07 2.85E-07 1.97E-07 7.82E-08 2.64E-08 8.38E-:
3.04E-09 1.66E-09 E
8.49E-06 1.09E-06 5.48E-07 2.91E-07 1.87E-07 8.40E-08 2.82E-08 9.85(-09
.75E-09 2.87E-09 ESE 6.91E-06 9.02E-07 4.49E-07 2.57E-07 1.67E-07 7.20E-08 2.77E-08
- t.
J.54E-09 3.68E-09 SE 6.70E-06 9.06E-07 4.53E-07 2.81 E-07 2.03E-07 8.94E-08 3.33E-08f.i*-08 6.19E-09 4,18E-09 SSE 7.26E-06 9.25E-07 4.91 E-07 2.87E-07 2.08E-07 9-18E-08 3.72Ek 1.)W-08 5.62E-09 3.26E-09 S:
8.70E-06 9.08E-07 3.992-07 2AI1E-07 1.61 E-07 7.312E-08 2
23-93.74E-09 1.95E-09 SSW 6.05E-06 7.01E-07 2,75E-07 1.86E-07 1.24E-07 5.06E-08.82-5.71E-09 2.87E-09 1.58E-09 SW 5.94E-06 5.71E-07 2.86E-07 1.81E-07 1.22E-07 4.50E-08 1.N 8
5.12E-09 2.53E-09 1.59E-09 WSW 8.00E-06 7.02E-07 3.60E-07 2.15E-07 1.34E-07 5.502-08 1.9-08 6.12E-09 2.62E-09 1.83E-09 W
1.02E-05 1.07E-06 5.30E-07 3:02E-07 2.05E-07
@.31*-08 3.15E-08 9.48E-09 3.74E-09 2.38E-09 WNW 1.16E-05 1.13E-06 5.98E-07 3.67E-07 2.53E-0A..00E-07 3,56E-08 1.18E-08 4.07E-09 2.54E-09 NW 1.13E-05 1.06E-06 5.70E-07 3.53E-07 2.40 7
- 1.
-07 382E-08 1.11E-08 5.14E-09 2.78E-09 NNW 1.08E-05 1.04E-06 5.72E-07 3.27E-07 2 2AE-
.%E-08 3.20E-08 8.89E-09 3.752-09 2.29E-09
- GROUND RELEASE D[NA E
SECTOR AVERAGE DIQ ([N M (IN TlETERS)
SEASON - ANNUAL SECTOR 610 2413 402-2 1 -'T240 12067 24135 40225 56315 72405 N
2.30E-08 1.88E-09 8.93E-10,4.2E-V 2.70E-10 8.96E-11 2.53E-11 4.98E-12 1.57E-12 7,84E-13 NNE 2.66E-08 2.25E-09 1.06E2
.2-r0 3.38E-10 1.10E-10 2.89E-11 6.06E-12 2.10E-12 8.89E-13 NE 1.75E-08 2.00E-09 1.2fE-09
- 5.
2-10 2.98E-10 1.04E-10 2.88E-11 6.01E-12 1.99E-12 9.23E-13 ENE 1.68E-08 1.85E-09
.6
-10
.28E-10 2.65E-10 8.57E-11 2.33E-11 5.41 E-12 1.63E-12 7.64E-13 E
2.88E-08 2.99E-
.39E2 6.34E-10 3.67E-10 1.35E-10 3.68E-11 9.42E-12 3.772-12 1.97E-12 ESE 3.59E-08 3.80 -
- 1.
-09 8.79E-10 5.15E-10 1.83E-10 5.78E-11 1.71E-11 7.062-12 4.06E-12 SE 4.12E-08 4.55E-09
.1312-09 1.15E-09 7.50E-10 2.72E-10 8.31E-11 *2.34E-11 9.42E-12 5.50E-12 SSE 3.12E-08 3.23E-09 1,59E-09 8.00E-10 5.20E-10 1.88E-10 6.18E-11 1.61E-11 5.66E-12 2.83E-12 S
2.65E-08 2.21E-09 9.07E-10 4.75E-10 2.882-10 1.07E-10 3.06E-11 8.10-E12 2.73E-12 1.23E-12 SSW 1.45E-08 1,30E-09 4.80E-10 2.82E-10 1:70E-10 5.71E-11 1.69E-11 3.91E-12 1.64E-12 7.84E-13 SW 1.42E-08 1.10E-09 5.15E-10 2.82E-10 1.71E-10 5.24E-11 1.65E-11 3.62E-12 1.49E-12 8.12E-13 WSW 2.01E-08 1.41E-09 6.82E-10 3.54E-10 2.00E-10 6.76E-11 1.89E-11 4.58E-12 1.63E-12 9.90E-13 W
2.55E-08 2.162-09 1.002-09 4.91E-10 3,01E-10 1.12E-10 3.11E-11 6,90E-12 2.27E-12 1.25E-12 WNW 2.88E-08 2.30E-09 1.13E-09 5.93E-10 3.67E-10 1.19E-10 3.43E-11 8,36E-12 2.39E-12 1.29F-12 NW 2.78E-08 2.15E-09 1.06E-09 5.58E-10 3.41E-10 1.19E-10 3.57E-11 7.61E-12 2.92E-12 1.36E-12 NNW 2.17E-08 1.75E-09 8.75E-10 4.24E-10 2,57E-10 8.55E-11 2.42E-11 4.93E-12 1.72E-12. 9.03E-13 DATA FROM 111178 THROUGH 12131/86 USED IN CALCULATIONS 120
TMI - Unit 1 Radiological Controls Procedure Number 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 4.6 Dose Parameters for Radioiodines and Radioactive Particulate in Gaseous Effluents*
CRITICAL ORGAN I CRITICAL ORGAN NUCLIDE ORGAN FACTOR
_[
Pi--
NUCLIDE J ORGAN FACTOR Pi***
H-3**
TOTAL BODY 3.04E-07 1.12E+03 RU-103 LUNG 1.79E-04 6.62E+05 C-14 BONE 9.70E-05 3.59E+04 RU-105 GI-LLI 2.69E-05 9.95E+04 NA-24 TOTAL BODY 4.35E-06 1.61 E+04 RU-106 LUNG 3.87E-03 1.43E+07 P-32 BONE 7.04E-04 2.60E+06 AG-110M LUNG 1.48E-03 5.48E+06 CR-51 LUNG 4.59E-06 1.70E+04 TE-125M LUNG 1.29E-04 4.77E+05 MN-54 LUNG 4.26E-04 1.58E+06 SB-125 LUNG 44T%,,04 2.32E+06 MN-56 GI-LLl 3.33E-05 1.23E+05 TE-127M LUNG 1.00E-'14 1.48E+06 FE-55 LUNG 3.OOE-05 1.11E+05 TE-127 G,-LL[
I2RM5 5.62E+04 FE-59 LUNG 3.43E-04 1.27E+06 TE-129M LUNG k,4.76E-04 1.76E+06 CO-58 LUNG 2.99E-04 1.11E+06 6 TE-129 GI-LU
?89E-06 2.55E+04 CO-60 LUNG 1.91 E-03 7.07E+06 TE-131M GI-L
..32E-05 3.08E+05 NI-63 BONE 2.22E-04 8.21 E+05 TE-131 L
G 5.55E-07 2.05E+03 NI-65 GI-LLI 2.27E-05 8.40E+04 TE-132 G
1.02E-04 3.77E+05 CU-64 GI-LLI 9.92E-06 3.67E+04 1-130 TY D
4.99E-04 1.85E+06 ZN-65 LUNG 2.69E-04 9.95E+05 1-131 THY ID 4.39E-03 1.62E+07 ZN-69 GI-LLI-2.75E-06 1.02E+04' 1-132 THYROID 5.23E-05 1.94E+05 BR-83 TOTAL BODY 1.28E-07 4.74E+02 1-1i4 THYROID 1.04E-03.
3.85E+06 BR-84 TOTAL BODY 1.48E-07 5.48E+02 I-1t'4*
THYROID 1.37E-05 5.07E+04 BR-85 TOTAL BODY 6.84E-09 2.53E+01 35 THYROID 2.14E-04 7.92E+05 RB-86 LIVER 5.36E-05 1.98E+05-4 LIVER 2.74E-04 1.01 E+06 RB-88 LIVER 1.52E-07 5.62
-136 LIVER 4.62E-05 1,71 E+05 RB-89 LIVER 9.33E-08 3.45 02
-137 BONE 2.45E-04 9,07E+05 SR-89 LUNG 5.89E-04 2
6 CS-138 LIVER 2.27E-07 8.40E+02 SR-90 BONE 2.73E-02
.E+0 BA-1 39 GI-LLI 1.56E-05 5.77E+04 SR-91 GI-LLI 4.70E-05
.74 5
BA-140 LUNG 4.71 E-04 1.74E+06 SR-92 GI-LLI 6.55E-05
-2.42 +05 BA-141 LUNG 7.89E-07 2.92E+03 Y-90 GI-LLI 7.24E-,5C-8E+05 BA-142 LUNG 4.44E-07 1.64E+03 Y-91M LUNG 7.6SE077 1.81E+03 LA-140 GI-LLI 6.10E-05 2.26E+05 Y-91 LUNG 7 10E-N~ 2.63E+06 LA-142 GI-LLI 2.05E-05 7.59E-04 Y-92 GI-LLI
.E-0r-2.39E+05 CE-141 LUNG 1.47E-04 5.44E+05 Y-93 GI-LLI 3.89E+05 CE-143 GI-LLI 3.44E-05 1.27E+05 ZR-95 LUNG9.
-04 2.23E+06 CE-144 LUNG 3.23E-03 1.20E+07 ZR-97 GI-LLI
- 9. 9E-05 3.51 E+05 PR-143 LUNG 1.17E-04 4.33E+05 NB-95 LUNG 1.66E-04 6.14E+05 PR-144 LUNG 4.23E-07 1.57E+03 MO-99 LUNG 3.66E-05 1.35E+05 ND-147 LUNG 8,87E-05 3.28E+05 TC-99M GI-LLI 1.30E-06 4.81E+03 W-187 GI-LLI 2.46E-05 9.10E+04 TC-1 01 LUNG I 1.58E-07 5.85E+02 j NP-239 IGI-LLI 1.73E-05 6.40E+04 The listed dose parameters are for radionuclides, other than noble gases that may be detected in gaseous effluents. Pi factors include all nonatmospheric pathway transport parameters, the receptor's usage of pathway media, and are based on the most restrictive age group (child) critical organ. Additional dose parameters for nuclides not included in this Table may be calculated using the methodology described in NUREG-0133.
Tritium dose factors include an increase of 50% to account for the additional amount of this nuclide absorbed through the skin.
mremlyear per C[Oi/m
- 3.
12i
TMI - Unit I Radiological Controls Procedure Number 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 FIGURE 4.1 TMI-1 Gaseous Effluent Pathways 122
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 FIGURE 4.2 TMI-1 Auxiliary and Fuel Handling Buildings Effluent Pathways 123
TMI - Unit I Radiological Controls Procedure Number 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM)
R No22 FIGURE 4.3 TMI-1 Reactor Building Effluent Pathway 124
TMI - Unit I Number T
Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 FIGURE 4.4 TMI-1 Condenser Offgas Effluent Pathway 125 4
6610-PLN-4200.01 Revision 22 FIGURE 4.5 TMI-2 Gaseous Effluent Filtration SystemlPathways STATION VENT RB BREATHER I~
0 UNIT 2 EXHAUST AIR FLOW AND RMS SCHEMATIC 126 I -
0. -142,01i0 ¢:ff
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No, Offsite Dose Calculation Manual (ODCM) 22
.5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents-Instantaneous Release Limits 5.1.1 Noble Gases For noble gases, the following equations apply for total body and skin dose rate at the unrestricted area boundary:
5.1.1.1 Total Body Dose Rate,= j (Kj) x (Dv) x (Q')
(eq 5.1.1.1) where:
Dose Ratet b = instantaneous total body dose rate heite boundary, in mrem/yr.
K. = total body dose factor due to g a e slons for each identified noble gas radionuclide, in mremlyr per ý-
3 from Table 4.3.
Dv = highest sector annual verage gaseous dispersion factor (X/Q) at or beyond the unrestrit area boundary, in seclm 3, from Table 4.4 for station vent relea
- d Table 4.5 for all other releases (Condenser Off Gas, ESF FHMa'lud gronid releases). Maximum values presently in use are 7.17E-7
/cq.
ector NNE for station vent, and 1.1 6E-5 sec/mr3 for all other e
9t sectors N and WNW.'
= Rel[
te radionuclide, i, in jlCi/sec as determined by sampling and a
is. Calculated using the concentration of noble gas radionuclide, i,
/Ci,times the release pathway flow rate, in cc/second.
127
TMI - Unit I Number Radiological Controls Procedure 6610-PLN-4200,01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 5.1.1.2 Skin Dose Ratelk =
(LI + 1.1 MI) X (Dv) X (Q1)
(eq 5.1.1.2) where:
Dose Ratesk = instantaneous mrerm/year skin dose rate limit, at the site boundary, in torero/yr.
L4 = skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrern/yr per jICitm3 from Table M, = air dose factor due to gamma emissions fo c
ified noble gas radionuclide, in mradfyr per RCifmý from J4.3.
1.1 mrem skin dose per mrad air dose ir dose to skin dose.
Qi release rate of radionuclide, i, *as determined by sampling and analysis. Calculated using the cor yration of noble gas radionuclide, j, in pCi/cc, times the release pathwafflow rate, in cc/second.
Dv = highest sector ann I verage gaseous dispersion factor (XIQ) at or "beyond the unrest[n r a boundary, in sec/r 3, from Table 4.4 for station vent r 0es 1Table 4.5 for all other releases (Condenser Off Gas, ESF F und releases). Maximum values presently in use are 7.17
,c at sector NNE for station vent, and 1.16E-5 sec/m3 for all othe relea s,at sectors N and WNW.
128
TMI - Unit 1 Radiological Controls Procedure Number 6610-PLN-4200.01 Revision No.
22 5.1.2 Iodine-131, Iodine-1 33, Tritium and Radionuclides in Particulate Form, with Half-Lives Greater than 8 Days For 1-131, 1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, the following equation applies:
Dose Rate1p =
(Pi) (Dv) (Qi) where:
Dose Ra (eq 5.1.2) tejp = mrem/year organ dose rate.
Pi = dose parameter for 1-131,1-133, Tritium an N.ides in Particulate Form, with half-lives greater than 8 days,, r.r i inhalation pathway, in mremlyr per g.Ci/m3, from Table 4.6.
d actors are based on the crtical individual organ and most r a
group (child).
Dv = highest sector annual averag
,=seous spersion factor (X/Q or DIQ) at or beyond the unrestricted area bo,oary, in sec/rn, from Table 4.4 for the station vent releases and Table.5 for all other releases. X/Q is used for the inhalation path ay. Maximum values of XIQ presently used are 7.17E-7 secim3 forstaon vent, at sector NNE, and 1,16E-5 sec/m0 for all other releases, at N and WNW.,
Q= release rate ionuclide, i, in tiCifsec. Calculated using the concen ran a-h radionuclide, i, in p.Cilcc, times the release pathway flow ratd in cc nefnd 129 I Ie Offsite Dose Calculation Manual (ODCM)
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 5.2 Gaseous Effluents - 10 CFR 50 Appendix I 5.2.1 Noble Gases The air dose in an unrestricted area due to noble gases released in gaseous effluents from the site is determined using the following expressions:
Dose IF = (3.17E-8) x j (MI) x (Dv) x (Qi) and Dose wher A
(eq 5.2.1)
(3.17E-8) x (NI) x (Dv) x(Qi)
(eq 5.2.2)
Dose F = mrad gamma air dose due to garn fom noble gas radionuclides.
Dose 3 = mrad beta air dose due to ns from noble gas radionuclides.
M, = air dose factor due tolamrma emissions for each identified noble gas radionuclide, in mrA pr iiCilm3, from Table 4.3.
N, = air dose facto u to b emissions for each identified noble gas radionuclidek r per g.Cifn, from Table 4.3.
Dv = highest ector nnual average gaseous dispersion factor, X/Q, at or be*fi tJe,,l(estricted area boundary, in seclm 3. Values may be read or inr lated from Table 4.4 for releases from the station vent and
,Ta le for all other releases. Maximum values of X=Q presently used E!lE-7 sec/m3 for station vent at sector NNE, and 1.16E-5 sec/m3 for
, :1 ther releases at sectors N or WNW.
release of noble gas radionuclide, i, in J.Ci, over the specified time period,
- (p.itsecnd
- seconds),
"7E-8 = inverse of the number of seconds in a year.
NOTE.
If the methodology in this section is used in determining dose to an individual, rather than air dose due to noble gases, substitute Ki, from Table 4.3, for Mi, and (Li + 1.1 Mi) for Ni.
130
TMI - Unit I Number S
'Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 5.2.2 Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form, with Half-Lives Greater than 8 Days The dose to an individual from 1-131, 1-133, Tritium and Radionuclides in Particulate Form with half-lives greater than 8 days in gaseous effluents released from the site to an unrestricted area is determined by solving the following expression:
Dose, = (3.17E-8) x (R,) (DR) (Q1}
where:
(eq 5.2.2)
Doseo = dose to all real pathways, p, to organ, o, of an i Idd in age group, a, from 1-131, 1-133, Tritium and Radionuclided Ie ate Form, with half-lives greater than 8 days, in
- flrem, ny desired time period.
Ri the dose factor for each identified r*ionld,
,d pathway, p, age group, a, and organ, o, in mremlyr per ii orre inhalation pathway and m2 mrem/yr per iiCi/sec for other ways m Tables 5.2 to 5.7.
?r piCi/m3 for all pathways.
I= lghest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3, for the inhalation pathway, and D/Q, in m2, for other pathways. Table 4.4 is used to derive the values for station vent releases and Table 4.5 is used to derive the values for all other releases. The values used to calculate site boundary and critical receptor doses are as follows:
Station Vent Releases - Boundary Inhalation XJQ 7.17 E-7 Meat D1Q 1.22 E-8 Cow/Milk/Infant DIQ 1.22 E-8 Station Vent Releases - Critical Receptor Inhalation X1Q 7.2 E-7 Meat D/Q 4.6 E-9
- CowlMilk/infant DIQ 3.1 E-9 Ground D/Q Vegetation D/Q Ground D0Q Vegetation DIQ 131 NOTE J
Since there is minimal or no elemental i kin released from the condenser off-gas air ejector (see NUR
- 17) all Iodine RI values for all pathways, except the inhalation $Tay, considered to be zero when performing dose calculationges from the condenser off-gas air ejector. Only calcu e '
due to the inhalation pathway for condenser off-gas air eiecrr iod e.
1.22 E-8 1.22 E-8 7.8 E-9 8.9 E-9 T
T I
I
Number TMI - Unit I Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 Ground or Other Rleases - Boundary Inhalation X/Q 1.16 E-5 Meat D/Q 4.12 E-8 Ground DIQ 4.12 E-8 Cow/Milk/Infant DIQ 4.12 E-8 Vegetation D/Q 4.12 E-8 Ground or Other Rleases - Critical Receptor Inhalation X/Q 1.2 E-5 Meat DIQ 9.2 E-9 Ground DIQ 3.0 E-8 CowIMilkIlnfant DIQ 6.3 E-9 Vegetation DIQ 2.6 E-8 Dv(H-3) = In the case of H-3 only the X/Q's above are used for all pathways, Qi = release of 1-131,1-133, Tritium and Radionuclid
,-in Particulate Form with half-lives greater than 8 days, in pCi, cum ative ver the specified time period (piCi/second
- seconds).
3.17E-8 = inverse of.the number of seconds in ar.
a 132
TM!- Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Revision No.
Offsite Dose Calculation Manual (ODCM) 22 5.3 Gaseous Radioactive System Dose Calculations Once per Month ODCM Part I Control 2.2.2.4 and TMI-2 PDMS Tech Spec Section 6.7.4.a.6 requires that appropriate subsystem of the Gaseous Radwaste Treatment System shall be used to reduce the radioactive materials in gaseous waste prior to their discharge. When the monthly projected doses due to the gaseous effluent releases from the site would exceed:
0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ.
The following calculational method is provided for performing this dose pro'
' n.
At least once per month the gamma air dose, beta air dose and the nI,.*an dose for the quarter-to-date will be divided by the number of days into the quarte multiplied by 31. Also, this dose projection shall include the estimated dose due to any anti'tek n nsual release during the period for which the projection is made. If these projected do,,,eny of the values listed above, appropriate portions of the TMI-1 Gaseous Waste Tj, eati n-iFstem, as defined in Section 6.0, or appropriate portions of the TMI-2 Gaseo rffluentltration System as shown on Figure 4.5, shall be used to reduce radioactivity levels prior tý/ease.
At the discretion of Radiological Engineering, timr periods other than the current quarter-to-date may be used to project doses if the dose per 'a-?n the current quarter-to-date is not believed to be representative of the dose per day projected n1ti next month.
00
.4 44j
Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 5.4 Alternative Dose Calculational Methodologies for Gaseous Effluents As an alternative to the methods described above, the models in/or based upon, those presented in Regulatory Guide 1.109 (Rev. 1) may be used to make a comprehensive dose assessment. Default parametervalues from Regulatory Guide 1.109 (Rev. 1) and/or actual site specific data can be used The onsite, on-line computerized system for tracking gaseous effluent dose uses annual average gaseous dispersion factors. As an alternative dose calculational methodology. TMi calculates doses using an advanced class "A' dispersion model called SEEDS (simplified environmental effluent dosimetry system).
This model incorporates the guidelines and methodology set forth in USN R
ulatory Guide 1.109, and uses actual hourly meteorological information matc t4e e of releases to more accurately assess the dispersion of effluents in the atmosphe mbining this assessment of dispersion with TMI effluent data for each unit postulated mt' um thetical doses to the public are calculated.
0 "I"MV i34
Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.o1 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.2.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: INHALATION N...
ORGAN DOSE FACTORS; mrern/year per gCi/m3 NUCLIDE i--
L--
I BOE LIVER T.BODY THYROID -KIDNYý LU CNG ----
GJ]-LU H-3 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 C-14 2.65E+04 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 CR-51 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E2 3.57E+02
- *3;_,*--O;-E;----
E0--
_-o---
MN-54 0.00E+00 2.53E+04 4.98E-+03 0.00E+00 4.98E+03 1I
.06E+03 FE-55 1.97E+04 1.17E+04 3.33E+03 0.OOE+00 0.00E÷00 6
+0 1.09E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 0.002+00 0.00E+0Q1.KEtOS 2.48E+04 CO-58 0.OOEi0O 1.22E+03 1.82E+03 0.O0E+00 O.00E g7 E+05 1.11E+04 CO-60 0.00E+00 8.02E403 1,18E+04 O.OOE+0
- 0.
2E+O
.51E+06 3.19E+04 NI-63 3.39E+05 2.04E+04 1.16E+04 0.O0E+.0 0+0 2.09E+05 2.42E+03 ZN-65 1.93E+04 6.26E+04 3.11E+04 0.00E+00 3.25E104 6.47E+05 5.14E+04 RB-86 0.00E+00 1.90E+05 8.82E+04 0.00E-O0 0.00E+00 0.00E+00 3.04E+03 SR-89 3.98E+05 O.OOE+00 1..14E+04 O.gaE0
-O.00E+_00 2.03E+05 6.40E+04 SR-90 4.09E+07 0.OOE+00 2.59E+06,¶y0E+O*
O.OOE+O0 1.12E+07 1.31E+05 Y-91 5.88E+05 0.00E+00 1.57E+00o 0.00E+00 2.45E+06 7.03E+04 ZR-95
.. 15E+05 2.79E+04 2.03 EOE+00 3.11E+04 1.75E+06 2.17E+04 NB-95 1.57E+04 6.432+03 3
0.002+00 4.72E+03 4.79E+05 1.27E+04 RU-103 2.02E+03.
0.00E+00 9E+0 0.00E÷00 4,24E+03 5.52E+05 1,61E404 RU-106 8.68E+04 0.OOE+g_
1.0 04 0.OOE+00 1.07E+05 1.16E+07 1.64E+05 AG-I1OM 9.98E+03 7.4 E
-?E C.OOE+03 0.OOE+00 1.09E+04 3.67E+06 3.30E+04 TE-125M 4.76E+03 9E+034.58E+02 1.62E+03 0.002+00 4.47E+05 1.29E+04 TE-127M 1.67E+04 B.9X+Q3 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2,73E+04 A
TE-129M 1.412 092+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.902+04 1-131 3.79E÷0 4.oEo04 1.96E+04 1.48E+07 5.18E+04 0.00E+00 1.06E+03 1-133 1.32E+04
.192E+04 5.60E+03 3.56E+06 2.24E+04 0.00E+00 2.16E+03 CS-134 3.96E+05 7.03E+05 7.45E+04 O.OOE0O-1.90E+05 7.97E+04 1.33E+03 CS-136 4.83E+04 1.35E+05 5.29E+04 0.OOE+00 5.64E+04 1.18E+04 1.43E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7,13E+04 1.33E203 BA-140 5.60E+04 5.60E+01 2.90E+03 0.00+E00 1.34E+01 1.60E+06 3.84E+04 CE-141 2.77E+04 1.67E+04 1.99E+03 0.00E+00 5.25E+03 5,17E+06 2.16E+04 CE-144 3.19E+06 1.21E+06 1.76E+05 0.OOE+00 5.38E+05 9.84E+08 1.48E+05 PR-143 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1.97E+03 4.33E+05 3.72E+04 ND-147 7.94E+03 8.13E+03 5.OOE+02 0.00E+00 3.15E+03 3.22E+05 3.12E+04" 135
TMI.- Unit 1 Number Radiologica[ Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.2.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: INHALATION 6 -- *
- r * ; ; -
NUCLIDE 1
- ORGAN DOSE FACTORS; mremlyear per u+/-CiWm NUC"D
- -,b..
1_BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 1.12E+03 1.12E+03 1.12E+03 1,12E+03 1.12E+03 1.12E+03 C-14 3.59E+04 6.73E+03 6.732+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 CR-51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70OE 1.08E+03 MN-54 0.00E+00 4.29E+04 9.512E+03 0.00E+00 1.0E00E04 7E6 9.29E+04 FE-55 4.74E304 2.52E+04 7.77E03 O.OOE+O00
.O0*O0
'5+0Q a87,E+03 FE-59 2.07E+04 3.34E+04 1.67E+04 0.002+00 0.00E+00 1.1E+06 7.07E+04 YO-58 0.001+00 1.77E+03 3-16E003 O.00+00 0.00 12E+06 3.44E+04 CO-60 0.O02+00 1.31 E+04 2.26E+04 0.OOE+0D0 OE+OO y.07 E+06 9.62E+04 NI-93 8.21E+05 4.63E+04 2.80E+04 0.00+0...0 096E+0 2.75E+05 6.33E+03
-B---
- OOO';0 ;* ;S-.* 0 -
ZN-65 4.26E+04 1.13E+05 7.03E+04 0.00E+0O 7.14E 04 9.95E+05 1.63E+04 RB-86 0.0E0+00 1.98.E+05 1.14E+05 0.00E+00 0.02E+00 0.00E+00 7.99E+03 SR-SQ 5.99E+05 0.00E+00 1,72E+04 0.9WE0O 0.00E+00 2.16E+06 1.67E+05 SR-90 1.01E+08 0.0E0400 6.442+06 0E+
0.00E+-00 1.48E+0 7 343E+_05 Y-91 9.14E+05 0.OOE+00 2.442E+
00
.OOE+00 2.632E+06 1.84E+05 ZR-95 1.90E+05 4.I1E+04 3.70 16E03E+00 5+90E+6 45E+
6.11E+04 NB-95 2.352+04 9.18E+03 30 0.00E+00 8.62E+03 6.14E+05 3.702+04 RU-10 2.79E+03 0.OOE+00 7+03 0.00E+00 7.03E+03 6.62E+05 4.482+04 RU-1OG 1.36E+05 0.00E+98-
- 1. 6 04 0.002+00 1.84E+05 1.43E+07 4.292+05 AG-10M 1.692+04 1.1-5E4E
.14iE+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 TE-125M 6.73E+03 32+12E÷0 3.14E+02 1.92E+03 0.00E+0 4.772E+05 3.38E+04 TE-127M 2.49E+04 8.55E+3 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 TE-129M 1.928E+048,3+203 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 1-131 4.81 E-r04.441E+04 2.73E+04 1.62E+07 7.88E+04 0.002+00 2.84E+03 1-133 1.662+%04 '.032+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.482+03 CS-134 6.51E+05 1.012+06 2.252+05 0.002+00 3.302+05 1.21E+05 3.85E+03 C8-136 6.51E+04 1.71E+05 1.162+05 0.002+00 9.55E+04 1.452+04 4.182+03 CS-137 9.072+05 8.252+05 1.282+05 0.002+00 2.822+05 1.04E+05 3.622+03 BA-140 7.40E+04 6.482+01 4.33E+03 0.002+00 2.112+01 1.74E+06 1.02E+05 CE-141
- 3.92E+04 1.95E+04 2.902+03 0.002+00 8.55E+03 5.44E+05 5.66E+04 0E-144 6.77E+06 2.122+06 3.61E2+05 0.002+00 1.17E+06 1.20E+07 3.892+05 PR-143 1.85E+04 5.552+03 9.14E+02 0.002+00 3.002+03 4.332+05 9.732+04 ND-I147' 1.082+04 8.732+03 6.812E+02 0.002+00 4.81E+03 3.282+05 8.21E+04 136
TMI - Unit I Radiolcaical controls Proc~hm.mr_
Number itoe fl.Di NLA'nn n_
Revision No.
I.-
TABLE 5.2.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: INHALATION NUCLIDE ORGAN DOSE FACTORS; mremtyear per g Ci/m5 NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU
-m-Z-._
U.UU0+0U 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4,87E+03 CR-51 0.00E+00 0.OOE+00 1.35E+02 7.50E+01 3.07E+01 2.102 3.00E,03 o
MN-54 0.002+00 5.11E+04 8.40E+03 O.60E+0O 1.27E+04
- 1.
Q
- .68E+04 FE-55 3.34E+04 2.38E+04 5,54E+03 0,00E+00 O.OOE+00
+0 6.39E+03 FE-59 1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+0._*1* o06 1.78E+05 o-8- ----
- .* o*
-* o -o O --O --; o--o-
"--:O--""
00-58 0.00E+00 2.072+03 2.78E+03 0.002+00 0.00 E
E+08 9.52E+04 CO-60 0_00E+00 1.51E+04 1.98E+04 0.00E+00
- 0.
E+0
.72E+06 2.59E+05 NI-63 5.80E+05 4.34E+04 1.98E+04 0.00E+00
.0 0
3.07E+05 1.42E+04 ZN-65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E204 1.24E+06 4.66E+04 RB-86 O.00E+00 1.90E+05 8.40E+04 0.00 0.00E+00 0.002+00 1.77E+04 SR-89 4.342+05 0.002+00 1.25E+04 0.E1ODO0.00E+0O 2.42E+06 3.71 E+05 SR-90 1.08E+08 0.00E+00 6.68E+08,
,0E+÷ 0.OOE+00 1.65E"07 7.65E+05 Y-91 6.61E+05 0.OOE+00 1.77E+u00 0,00E+00 2.94E+06 4.09E+05 ZR-95 1.46E+05 4.58E+04 3.15TV 90E+00 6.74E+04 2.69E+06 1.49E+05 NB-95 1.862+04 1.032+04 3 03 002O+00 1.00E+04 7.51E+05 9.68E+04 RU-103 2.i0E+03 0.OOE+00 0" 0.02E+00 7.43E+03 7.83E+05 1.09E+05.
RU-1O0 9.84E+04 o.ooE+
"_.0*Wo4 O.OOE+00 1.90E+05 1.61E+07 9.60E+05 AG-110M 1.382+04 1.31E$QC
.99E+03s 0.002+00 2.50E+04 6.75E+06 2.732+05 TE-125M 4.582+03 4E+04.67E202 1.40E+03 0.00E+00 5.36E+05 7.50E+04 TE-127M 1.80E+04 D.1 4g3 2,18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 TE-129M 1.39E 44,48 g03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.OSE+05 1-131 3.54E+0
-4.-1E+04 2.64E+04 1.16E+07 8.40E+04 0.OOE+00 6.49E+03 1-133 1.22E+04
".05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 CS-134 5.02E+05 1.13E+06 5.49E+05 0.00E+00 CS-136 5.15E+04 1.94E+05 1.37E+05 0.00E+00 CS-137 6.70E+05 8.48E+05 3.11 E+05 0.00E+00 BA-140 5.47E+04 6.70E+01 3.52E+03 0.00E+00 CE-141 2.84E+04 1.90E+04 2.17E+03 O.OOE+00 CE-144 4.89E+06 2.02E+06 2.62E+05 0.00E+00 3.75E+05 1.46E+05 1.10E+05 1.78E+04 3.04E+05 1.21E+05 2.28E+01 2,03E+06 8.88E+03 6:14E+05 1.21E+06 1.34E+07 9.76E+03 1.09E+04 8.48E+03 2.29E+05 1.26E+05 8.64E+05 PR-143 1.34E+04 5.31E+03 6.62E+02 0.00E+00 3,09E+03 4.83E+05 2.14E+05 ND-147 7.86E+03 8.56E+03 5.13E+02 9.00E+00 5.02E+03 3.72E+05 1.82E+05 137
'ii Offsite Dose Calculation Manual (ODCM) 199 Title I
Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.2.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: INHALATION NUCLEDE -------
ORGAN DOSE FACTORS; mremfyear per pCi/r BONE LIVER T.BDY_
THYROl
_ KDNE LUNG GI-LLI H-3 0.OOE+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 C-14 1.82E+04 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 CR-51 0.00E+00 0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E24 3.32E+03 "MN-54 O.OOE+00 3.962+04 6.30E+03 0.0OE+00 9.64E+03 I
.74E+04 FE-55 2.46E+04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 2
+
6.03E+03 FE-59 1.18E+04 2.78E+04 1.06E+04 0.00E+00 01E._QEO06 1.88E+05 CO-58 0.OOE+00 1.58E+03 2.07E+03-0.002+00 0.00E 80E+05
.1.06E+05 CSO 0.00E+05 1.15E+04 1.48E+04 0.002+00 0,0÷0
.940E06 2.85E+O5 NI-63 4.32E+05 3.14E+04 1.45E+04 O0O.0+00 0,00E+
1.78E+05 1.34E+04 ZN-O5 3.24E+04 1.03E+05 4.862+04 0.00IE+00 8.92E04 8.64E+06 5.34E+04 RB-86 0.00E+00 1.35E005 5.90E+04 0.009t00 0.00+00 0.5.OOE+00 1.66E+04 SR-89 3.04E+05 0.00E+00 8.72E+03 0.00E00 1.40E+05 1.34E+06 93.5E+05 SR-90 9.922+07 0.E0 6.OE+00 E+06 1E+
0.97E+00 9.60E+06 7.22E+05 T-'91 4.62E+05 O0O.E+00 1.24+0 E 00 0,002+00 1.702+06 3.52E+05 ZR-95 107E+05 3.442+04 E+03 5.42E+04 1.77E+06 1.50E+05 NB-95 1.41 E+04 7.82 2E+0 3
O2OE+Q0 7.74E+03 5.05E+05 1.04E+05 RU-103 1.53E+03 O.OOE+00 8E+0 0.00E-+00 6.83E+03 5.75E+05 1.10E+05 RU-1 06 6.910+04
,4000E+0
- 1.
03 0.OOE+00 1.34E+05 9.36E+06 9.12E+05 AG-1i7M 1.08E+04 1-.1E$
.9428E+03 0.OOE+00 1.972E+04.
4.63E+06 3.02E+05 TE-125M 3.42E+03 4E+0124.67E+02 1.05E+03 1.24E+04 3.14E205 7.06E+04 TE-127M 1.26E+044 5.7+, 3 1.57E+03 3.29E+03 4.62E+04 9.602E+05 1.0E+05 TE-129M 9.76E4 A-.,f7+03 i.58E+03 3.44E+03 3.682+04 1.162+06 3.832+05 1-131 2.52E+0$3.
35E+/-04 2.05E+04 1.19E+/-07 8.132+04 0.002+/-00 6.28E+03
.1-133 8.64E+03 1.48E4-04 4.52E+O3 2.15E+06 2.58E+04 0.002+00.- 8.88E+03 CS-134 3.73E+06 8.48E+05 7.28E+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04 CS-136 3.902+04 1.46E+05 1.10E+05 0.00E+00 8.562+04 1.20E+04 1.172+04 CS-137 4.78E+06 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 BA-140 3.902+04 4.902+01 2.57E+03 0.002+00 1.672+01 1.272+06 2.182+05 CE-141 1.99E+04 1.35E+04 1.53E+03 0.002+00 6.26E+03 3.622+06 1.20E+05 0E-144 3.43E+06 1.432+06 1.842+05 0.002+00 8.482+05 7.-78E+06 8.162+05 PR-I143 9.36E+03 3.75E+03 4.64E+02 0.OOE+00 2.16E+03 2.81E+05 2.OOE+05 ND-147 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05 138
TMI - Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.3.1 Pathway Dose Factors, Ri AGE GROUP: ALL PATHWAY: GROUND PLANE
r--- 7-----------------------------------------------
ORGAN DOSE FACTORS*
NUCLIDE T.BODY.
SKIN o--
H-O.0.0E+00 O.O12+O00 C-14 0.00E+00 0.00E+00/
CR-51 4.65E+06 5.50E+06
- 0- ---- ** *-
M-4 1.39E+09 1-52E+09 FE-55 0.OOE+00 O.OOE+00 IFE-59 2.73E+08 3.21E+4 9 CO-58 3.79E+08 4.44E+080U0
'CO-60 2.15E+10 2.53E+10,'
NI-63 O.OOE+0O
,0.OOE+00
,ZN-65 7.47E+I08 L".. 59E+08 RB-86 8.97E+08
'?E+07
- SR-89 2.16 1 E04' Srk-9
- 0.
b(
.OOE+OO Y-91
.07 06Y 1.21E+06 ZR-95 45E 8
2.84E+08 NB-9
.3+08 1.61 E+08
,RU *E+08 1.26E+08
-1
.22E+i08 5.06E+08
'TE-$ 7 1.55E+06 2.13E+06 127M 9.17E+04 1.08E+05 4~* J E12M 1.98E+07 2.31 E+07 r 1-131 1.72E+07 2.09E+07
- ,'1-133 2.45E+06 2.98E+06 CS-1 34 6.86E+09 8.OOE+09
- CS-136 1.51 E+08 1.71 E+08 CS-137 1.03E+10 1.20E+10 CE-141 1.37E+07 1.54E+07 CE-144 6.96E+07 8.05E+07 PR-143 0.OOE+00 O.OOE+00 ND-147 8.39E+06 1.01E÷07
- r----------------------m M2 _Mrem/year per gCilsec. 139
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.4.1 Pathway Dose Factors, RI AGE GROUP: INFANT.
PATHWAY: GRASS-COW-MILK NUCLIDE ---
ORGAN DOSE FACTORS; mS - mremlyear per jiC_.sec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 C-14 2.34E+09 5.00E+08 5.OOE+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 CR-51 0.00E+00 0.00E+00 1.61E+05 1.05E+05 2.30E+04 2.05E1"\\.70E+06 MN-54 O.OOE+00 3.91E+07 8,85E+06 O.OOE+00 8.66E+06 0
f+6...
3E+07 FE-55 1.35E+08 8,74E+07 2.34E+07 0.OOE+00 0.00E+00
.+07 1.112E07 FE-59 2.25E+08 3.93E+08 1-55E+08 0.002+00 0.002+0 1-1
+8 1.88E+08 CO-58 0.002+00 2.43E+07 6.06E+07 0.00E+00 0.00,Vf E+.00 6.05E+07 CO-60 0.00E+00 8.83E+07 2.08E+08 0.00E+00 0.9+00
.OOE+00 2.10E+08 NI-63 3.50E+10 2.16E+09 1.21E+09 0.00E+00 0:00 0.00E+00 1.08E+08
-z--- --- ---
E+ *- 9; :; -- -* E 0-- 0-------
0---
t:E 0
o ZN-65 5.56E+09 1.91E+10 8.79E+09 0.002+00 9.24E409 0.00E4-O0 1.61E+10 RB-86 0.00E+00 2.23E+10 1E10E+10 0.006400 0.OOE+00 0.00E+00 5.70E+08 SR-89 1.26E+10 0.00E+00 3.62E+08
- 0. QA30 0.OOE+00 0.00E+00 2.59E+08 SR-90 1.22E+11 0.ooE+00 3.10E+10 E
OE+-E ".OOE+00 0.OOE+00 1.522E09 Y-91 7.34E+04 0.00E+00 1.95E+0 3" 00 0.00E+00 0.OOE+00 5.26E+06 ZR-95 6.81E+03 1.66E+03 1.1E+00 1.79E+03 0.00E+00 8.27E+05 NB-95 5.94E+0-5 2,45E+05
&5
)0.0OE+00 1.75E+05 0.E0E-Q0 2.07E+08 RU-I 03 8.68E+03 0.00E+00
&oE+0O 0.00+E00 1.81E+04 0.00E+00 1.06E+05 RU-106 1.912+05 0.00E+_
.3 04 0.00E+00 2.25E+05 0.00E+00 1.45E+06 AG-110M 3.86E+08 2.8 E-SE-
' 87E+08 O-OOE+00 4.03E+08
.000E+00 1.46E+10 TE-125M 1.51E+08
,E+07*,*.04E+07 5.08E+07 O.OOE+00 0.00E+00 7.19E+07 TE-127M 4.22E+08 i.4-i+0' 5.10E+07 1.22E+08 1.04E+09 0.00E+00 1.70E+08 TE-129M 5,58E4')~ 1 08 8.592+07 2.14E+08 1.39E+09 0.002+00 3,33E+08 1-131 2.72E+0 3.t1E+09 1.41E+09 1.05E+12 3.75E+09 0.ooE+00 1.15E+08 1-133 3.63E+07 ).29E+07 1.55E+07 9.62E+09 6.22E+07 0.001+00 8.962+06 CS-1 34 3.65E1+10 6.81E+10 6.88E+09 0.OOE+00 1.75E+10 7.19E+09 1.85E+08 CS-136 1.98E+09 5.83E+09 2.18E+09 0.00+E00 2.32E+09 4.75E+08 8.85E+07 CS-137 5.15E+10 6.03E+10 4.27E+09 0.00E+00 1.62E+10 6.55E+09 1.89E+08 BA-140 2.42E+08 2.42E+05 1.25E+07 0.OOE+00 5.75E+04 1.49E+05 5.94E+07 CE-141 4.34E+04 2.65E+04 3.12E+03 0.OOE+00 8.17E+03 O.00E+00 1.37E+07 CE-144 2.33E+06 9.53E+05 1.30E+05 0.00E+00 3.85E+05 0.00E+00 1.34E+08 PR-143 1.49E+03 5.56E+02 7.37E+01.
0.002E00 2.07E+02 0.00E+00 7.84E+05 ND-147 8.83E+02 9.07E+02 5.55E+01 0.00E+00 3.50E+02 0.00E+00 5.75E+05 140
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.4.2 Pathway Dose Factors, RI AGE GROUP: CHILD PATHWAY: GRASS-COW-MILK
- mrem/year per
.i.s.....-
NUCLIDE BONE LIVER T.BODY THYROID -
KIDNEY LUNG GI-LLI
~----
H-3 0.00E+00 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+908 CR-51 O.OOE+00 0.OOE.00 1.02E+05 5.65E+04 1.54E+04 1.03E!*M%5.40E+06 MN-54 0.ooE+0o 2.1oE+07 5.59E+06 O.OOE+00 5.89E+06 0),
) " 6E-t FE-55 1.12E+08 5.94E+07 1.84E+07 O.OOE+00 O.OOE+00 P3+0T 1.17E+07 FE-59 1.20E+08 1.95E+08 9.70E+07 O.OOE+0O 0.0OOE÷0l
- 5. E 07 2.03E+08 c---
÷ * ;;:o-oý o& o -o o;E(--- -- --- &---
0O-58 0.OOE+00 1.21 E+07 3.72E+07 O.OOE+00O;ý OE0 7.08E+07 CO-60 0.OOE+00 4.32E+07 1.27E+08 0.OOE+00 0AE+00X.OOE+00 2.39E+08 NI-63 2.97E+10 1.59E+09 1,01E+09 O.OOE+00
.00-0-.OOE+00 1.07E+08 ZN-65 4.14E+09 1.10E+10 6.86E+09 0.00E+00 6.95E 09 O.00E-00 1.94E+-09 RB-86 0.OOE+00 8.78E+09 5.40E+09 0.00600 0.OOE+00 0.OOE+00 5.65E+08 SR-89 6.63E+09 0.OOE+00 1.89E+08 0.RQEA00, 0.OOE+00 0.OOE+00 2.57E+08 SR-90 1.12E+11
- .OOE+0-2.84E+1;O* OES+-"
O-OEO0E.OO-- 0-O
=-E+00 1.51E+09 Y-91 3.91E+04 0.00E+00 1.05E+0S 00 0.00E+00 0.00E+00 5.21E+06 ZR-95 3.84E+03 8.43E+02 7.51
_OE+06 1.21E+03 0.OOE+00 8.80E+05 NB-95 3.18E+05 1.24E+05 I4~40.OOE+00 1.16E+05 0.OOE-'00 2.29E+08 RU-103 4.29E+03 0.00E+00
. 5E+03 0.00E+00 1.08E+04 0.OOE+00 1.11E+05 RU-lO6 9.25E+04 0.OOE*pI
- 1.
04 O.OOE+Q0 1.25E+05 0.00E+00 1,44E+06 AG-11OM 2.09E+08 1.4'1E El;*
.13E+08 0.OOE+00 2.63E+08 -. OOE+00 1.68E+10 TE-125M 7.39E+07
- 0E+07d.85E+06 2.07E+07 0.00E+00 0.00E+00 7.13E+07 TE-127M 2.08E+08 5.6
+ 7 2.47E+07 4.98E+07 5.94E+08 0.002+00 1.69E+08 E
TE-129M 2.72E 4
+p07 4.22E+07 8.76E2+07 7.98E+08 0.OOE+00 3.31 E+08 1-131 1.31E+0 1.j 1E+09 7.46E+08 4.34E+11 2.16E+09 0.00E+00 1.17E+08 1-133 1.72E+07 I.13E+07 8.05E+06 3.95E+09 3.55E+07 0.00E+00 8.58E+06 CS-134 2.27E+10 3.72E+10 7.86E+09 0.00E+00 1.15FE+10 4.14E+09 2.01E+08 CS-1 36 1.01E+09 2.79E+09 1.80E+09 0.00E+00 1,49E+09 2.21E+08 9.80E+07 CS-137 3.23E+10 3.09E+10 4.56E+09 OOOF+0f 1
.nl n
.').J.J
!.no.in "BA-1 40 1.18E+08 1.03E+05 6.86E+06 CE-141 2.19E+04 1,09E+04 1.62E+03 CE-144 1.63E+06 5.09E+05 8.67E+04 O.OOE+00 3.35E+04 6.14E=-+04 5.96E+07 0.OOE+00 4.79E+03 O.OOE+00 1.36E+07 0.OOE+00 2.82E+05 0.00E+00 1.33E+08 PR-143 7.18E+02 2.16E+02 3.56E+01 0.0OE+00 1.17E+02 0.00E+00 7.75E+05.
ND-147 4.46E+02 3.61E+02 2.79E+01 0.OOE+00 1.98E+02 0.00E+00 5.71E+05 141 I...
I*
U.l*,l..,. r U
- I.l*
l...T UO
TMi - Unit Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.4.3 Pathway Dose Factors, RI AGE GROUP: TEEN PATHWAY: GRASS-COW-MILK NUCLDORGAN DOSE F m - mremiyear per p.Cilsec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 C-14 4.86E+08 9:73E+07 9173E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 CR-51 0.00E+00 0,00E+00 4.99E+04 2.77E+04 1.09E+04 7.13E-1 Pf,39E+06 MN-54 0.OOE+00 1,40E+07 2.78E+06 0-.0o+00 4.19E+06 0^+NQJa.88E+07 FE-55 4.46E+07 3.16E+07 7.37E+06 0.00E+00 O.00E+00
'+07 1.37E+07 FE-59 5.19E+07 1.21E+08 4.682+07 0.002+00 0.00E+0.0A3.s+J7 2.862+08
-c-&;;
~~~-
o*
-o ;;,E:d "** ;; o-dG CO-5B 0.0012+00 7.94E+06 1.83E+07 0.002+00 0.,005 I15 E+00 1.102+08 CO-1O 0.00E+00 2.78E+07 6.27E+07 O.OOE+00 0.g+00X*_.00E+00 3.62E+08 NI-63 1.18E+10 8.36E+08 4.01E+08 0.00E+00 O.A00_
0.00 E+00 1.33E+08 ZN-65 2.11E+09 7.32E+09 3.42E+09 0.002÷00 4.6924Y9 0.002+00 3.10E+09 RB-86 0.00E+00 4.73E409 2.22E409 0.00-00 0,00E+00 0,OOE+00 7.00E+08 SR-89 2.68E+09 0.00E+00 7.67E+07 0.0E(* 0 0.00E+00 0.OOE+00 3.19E+08 SR-90 6.62E+10 0.00E+00 1.63E+10'/.OE+
-0.00E+00 0.00E+00 1.86E+09 Y-91 1.58E+04 0.00E+00 4.24E+O00 0.00E+00 0.00E+00 6.48E+06 ZR-95 1.65E+03 5.21E+02 3.58E+00 7.65E+02 0.00E+00 1.20E+06 NB-95 1.41E+05 7.82E+04 4
04.0002+00 7.58E+04 0.002+00 3,342+08
-i- --
E*O -
-2* 0 " ---;O0E;-
0-------
RU-1 03 1.81E+03 0.002+00 52+
0.00E+00 6.39E+03 0.00E+00 1.51E+05 RU-I06 3.76E+04 0.00E+0*- 7 03 0.OOE+00 7.24E+04 0.OOE+00 1.80E+06 AG-I10M 9.64E+07 9.i2E I
.552E+07 O.OOE+00 1.74E+208 O0.E;0 0
-2.56E+10 TE-125M 3.01E+07 1*E+07.A.02E+06 8.40E+06 0.00E+00 0.OOE+00 8.87E+07 TE-127M 8.45E+07 3.0'1*+03 1.00E+07 2.01E+07 3.42E+08 0.00E+00 2.11E+08 TE-129M 1.10E+q M09-+07 1.74E+07 3.56E--07 4.61E+08 O.0E+00 4.14E+08 1-131 5.38E+0 7.rE+08 4.05E+08 2.20E+11 1.30E+09 0.00E+00 1.49E+08 1-133 7.08E+06 >!.20E+07 3.66E+06 1.68E+09 2.11E+07 0.00E+00 9.09E+06 CS-134 9.83E+09 2.31E+10 1.07E+10 0.00E+00 7.35E+09 2.81E+09 2.88E+08 CS-136 4.49E+08 1.77E+09 1.19E+09 0.00E+00 9.63E+08 1.52E+08 1.42E+08 CS-137 1.34E+10 1.78E+10 6.21E+09 0.002E00 6.06E+09 2.36E+09 2.54E+08 BA-140 4.87E+07 5.97E+04 3.14E+06 0.00E+00 2.02E+04 4.01E+04 7.51E+07 CE-141 8.89E+03 5.94Et03 6.82E+02 0.002E00 2.80E+03 0.00E+00 "1.70E+07 CE-144 6.59E+05 2.73E+05 3.54E+04 0.002E00 1.63E+05 0.00E+00 1.66E+08 PR-143 2.90E+02 1.16E+02 1.44E+01 0.00E+00
.6.73E+01 ND-147 1.81E+02 1.97E+02 1.18E+01
.0.00E+00 1.16E+02 0.00E+00 9.55E+05 0.00E+00 7.12E+05 142
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.4.4 Pathway Dose Factors, RI AGE GROUP: ADULT PATHWAY: GRASS-COW-MILK 2--
2-NUCLIDE1 ------
ORGAN -DOSE FACTORS;.m - mnreml/year per gCi/sec-----
BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 C-14 2.63E+08 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 CR-51 0.00E+00 0.00E+00 2.85E+04 1.70E+04.
6.28E÷03 3.78EtM%. 7.17E+06 MN-54 ----
0-OE.00-0 8.40E-5
-6 62 0
-0.00+00-- -. 00E0
-0PI-2.57E+*7 FE-55 2.61E+07 1.73E+07 4.04E+06 0.O0E+00 0.00E+00
&6-+t0-9.93E+06 FE-5Q 2.97E+07 6.97E+07 2.67E+07 0.00E+00 0.OOE0OX 1.
E- 07 2.32E+08 CO-58 0-00E+00 4.712+06 1.05E+07 0.002+00 0.Oi
~
E400 9.54E+07 CO-60 0.00E+00 1.64E+07 3.61E+07 0.00E÷00 0AE+00"EO.OOE+00 3.08E+08 NI-63 6.72E+09 4.65E+08 2.25E+08 0.OOE+00
- -*o--0*
.O00E+00 9.71E+07 ZN-65 1.37E+09 4.36E+09 1.97E+09 0.00E+00 2.91 09 O0OOE+00 2.74E+09 RB-86 0.00E+00 2.59E÷09 1.21E+09 0.00*-00 0.OOE+00 0.00E+00 5.10E+08 SR-89 1.45E+09 0.00E+00 4.16E+07 0.A 00,_ 0.00E+00 0.00E+00 2.32E+08 G
k ----
Z4 -& ;
-0; E 0 --
0--
0
--*;- +-0---
SR-SO 4,67E+10 0.OOE+00 1.15E4.10y' 0E+X 0.00E+00 0.002+00 1.35E+09 Y-91 8.57E+03 0.00E+00 2.29E+0 00 0.00E+00 0.00E+00 4.72E+06 ZR-S9 9.41"E+02 3.02E+02 2.04 "N
0 OE+00 4.74E-02 O.0E0+00 9.572+05 NB-95 8.24E+04 4.58E+04 t04J 0.002+00 4.53E+64 0.00E4-00 2.78E+08 RU-103.
1.02E+03 0.00E+00 82+--W 0.00E+00 3.88E+03 0.OOE+00 1.19E+05 RU-I 06 2.04E+04 0.00OE+
2 03 0.OOE+00 3.93E+04 0.00E+00 1.32E+06 AG-110M 5.81E+07 r53 E
.19E+07 0.00E+00 1.06E+08 0.002+00 2.19E+10 TE-125M 1.63E+07 I 9E+
.18E+06 4.89E+06 6.61E+07 0.00E+00 6.49E+07 TE-127M 4.57E+07 il.S)
+Q7 5.57E+06 1.17E+07 1.86E+08 0.00E+00 1.53E+08 TE-129M 6.01E 4L+07 9.51E+06 2.06E+07 2.51E+08 - OOOE-00 3.02E+08 1-131 2.96E+0n
- 4. 3E+08 2.42E+08 1.39E+11 7.25E+08 O.00E+00 1.12E+08 1-133 3.87E+06
.673E+06 2.05E+06 9 88E+08 1 17F+n7 n nnfFnn A nl*Af:.L.,n 0-1"34 5.54E+09 1.34E+10 1.102E-10 O+00 4.34E+09 1.4427+09 2.35E+08 CS-136 2.63E+08 1.04E+09 7.48E+08 0.00E+00 5.78E+08 7.92E+07 1.18E+08 CS-137 7.37E+09 1.01E+10 6.60E+09 0.00E+00 3.42E+09 1.14E+09 1.95E+08 BA-1 40 2.69E+07 3.38E+04
.1.76E+06 0.O0+00 1.16E+04 1.94E+04 5.54E+-07 CE-141 4,84E+03 3.27E+03 3.71E+02 O.OOE+00 1,52E+03 O.OOE-00 1.25E+07 CE-144 3.57E+05 1.49E+05 1-92E+04 O.OOE+00 8,85E+04 O.OOE+O0 1.21E+08 PR-143 1.57E+02 6.32E+01 ND-147 9.40E+01 1.09E+02 7.81E+00 O.OOE+00 3.65E+01 O.OOE+00 6.90E+05 6.50E+00 O.OOE+00 6.35E÷01 O.OOE+00 5.22E+05 143
TMi - Unit I Number I
Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.5.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK
2-----------
NUCLIDE -----
ORGAN DOSE FACTORS; m2 mremlyear per p.Ci/ser, BONE LIVER T.B-O-DY-T-H-Y-RO JOD--
K-ID-NE-Y
-LUNG ----
GI1-LLY M-0.
u.uut-uu 4.86E+U0 4.86E+03 4.86E+03 4.86E+03 4.86E+03 C-14 2.34E+09 5,OOE+08 5.00E+08 5.00E+08 5.OOE+08 5.OOE+08 5.OOE+08 CR-51 0.OOE+0O 0.00E+00 1.94E+04 1.26E+04 2.76E+03 2.46E+f4N,.64E+05 MN-54 0.00E+00 4.68E+06 1.06E+06 0.002+00 1.04E+06 0.Al-%QJ.72E+06 FE-55 1.76E+06 1.14E+06 3.03E+05 0.OOE+00 0.OOE+00 5-05 1.44E+05 FE-59 2.92E+06 5.10E+06 2.01E+06 0.OQE+00 0.00E-s00OAl.¶EQ 2.44E+06 0O-58 0.002+00 2.91E+06 7.25E+06 0.OOE4.OO 0.600
. E+00O 7.25E+06 co-60 0.OOE+00 I.06E+07 2.50E+07 0.00E+00 0.Q+0O00E.+00 2.52E+07 NI-63 4.19E+09 2.59E+08 1.46E+08 0.00E+00
- 0. 0 00 - 0.00E+00 1.29E+07 ZN-65 6.67E+08 2.29E+09 1.05E+09 0.00E+00 1.11E 9
0.OOE+00 1.93E+09 RB-86 0.00E+00 2.67E+09 1.32E+09 0.00F.00 0.00E+00 0.0OE+00 6.83E+07 SR-89 2.65E+10 0.00E+00 7.59E+08
- 0. Q:*0 0.OOE+00 0.00E+00 5.44E+08 SR-90 2.552+1 1 0.002+00 6.502+10,/O0SE+0V 0.00E+00 0.OOE+00 3.19E+09 Y-91 8.80E+03 0.002+00 2.34E+02'\\,weu.o0 0.'OOEE+00 0.OOE+00 6.31E+05 ZR-95 8.17E+02 1.99E+02 1.41 --
0E+00 2.15E+02 0.00E+00 9.91E+04 NB-95 7.13E+04 2.93E+04
~Q40.0E+OO 2.16E+04 0.002+00 2.48E+07 RU-103 1.04E+03 0.00E+00 8E+
O.OOE+00 2.17E+03 O.OOE+00 1.27E+04 RU-106 2.28E+04 0.00E+0O
'.8
_3 0.00E+00 2.70E+04 0.00E+00 1.73E+05 AG-I oM 4.63E+07 3.38E 24E+07 0.00E+00 4.84E+07 0.-0E+00 1.7-5+09 TE-125M 1.81E+07 6
E+0_
.45E+06 6.00E+06 O.OOE+00 0.O0E+00 8.62E+06 TE-127M 5.06E+07
.6
+07 6.12E+06 1.46E+07 1.24E+08 0.00+E00 2.04E407 TE-129M 6.69Ei'~2
+07 1.03Ei-07 2.57E=+07 1.67E+08 0.00E+00 3.99E+07 1-13t 3.27E+0X 3-E+09 1.69E+09 1.27E+12 4.60E+09 0.00E+00 1.37E+08 1-1.33 4.36E+07 )6.35E+07 1,86E+07 1.15E+10 7.46E+07 0,00E+00 1.07E+07 CS-134 1.09E+11 CS-1 36 5.94E+09 CS-137 1.54E+11 BA-140 2.90E+07 CE-141 5.21 E+03 CE-144 2.79E+05 2.04E+11 2.06E+10 0.00E+00 5.26E+10 2.15E+10 5.55E+08 1.75E+10 6.52E+09 0.00E+00 6.96E+09 1.42E+09 2.65E+08 1.81E+11 1.28E+10 0.00E+00 4.85E+10 1.96E+10 5.65E+08 2.90E+04 1.50E+06 0.00E+00 6.89E+03 1.78E+04 7.13E+06 3.18E+03 3,74E+02 0,00+E00 9.79E+02 O.OOE+00 1.64E+06 1.14E+05 1.566E04 0.00+E00 4.62E+04 0.OOE+00 1.60E+07 PR-143 1.78E+02 6.66E+01 8,83E+00 0.00E+00 2.48E+01 0.00E+00 9.40E+04 ND-147 1.06E+02 1.09E+02 6.66E+00 0.OOE+00 4.19E+01 0,OOE+00 6.89E+04 144
Number TMI - Unit 1 Radiolocical Controls Procedure 6610O-PLN-42D0.fl1 Title Revision No.
OfTite Dose Calculation Manual (ODCM) 22 TABLE 5.5.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-GOAT-MILK BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 CR-51 0.00E+00 O.OOE+00 1.22E+04 6.78E+03 1.85E+03 1.24EtM,-2 6.48E+05 MN-54 O.00E+00 2.52E+06 6.71E+05 0.OOE+00 7.06E.+05 0
11E+06 FE-55 1.45E+06 7.71E+05 2.39E+05 0.OOE+0O 0.00E+00
- 3
+0 1.43E+05 FE-59 1.56E+06 2.53E+06 1.26E+06 0.OOE+00 0.0OE+OX 7.
Ej05 2.64E+06 CO-58 0.002+00 1.46E+06 4.46E+06 0.00E+00 0.;00y¶B AOtE.'00 8.49E+06 CO-6S 0.00E+00 5,18E+06 1.53E+07 0.OOE+0O 0SQE+0 00OE+00 2.87E+07 NI-63 3.56E+09 1.912+08 1.21 E+08 0.00E+00 dd 00-0 0.00E+00 1.28E+07 ZN-65 4.96 Et08 1.32E+09 8.22E+08 0.002+00) 8.33E 08 0.002+00 2.32E+06 RB-86 0.OOE+00 1.05E+09 6.47E+08 0.00t-00 O.00E+0 0.00E+00 6.77E+07 SR-89 1.39E+10 0.00E+00 3.97E+08 0.94400 0.00E+00 0.OOE+00 5.39E+08 "SR-90 2.35E+11 0.OOE+00 6.952+10 Y-91 4.69E+03 0.00E+00 1.25E+0
-00 0.OOE÷0O 0.00E+00 6.24E+05 ZR-95 4.60E+02 1.01E+02 9.00E+00 1.45E+02 0.O0E+00 1.05E+05 NB-O5 3.82E+04 1.492+04 04 0 002+00 1.40E+04 0.002+00 2.752+07 RU-103 5.14E+02 0.0OE+00 8 82+0 0.00E+00 1.29E+03 0.002E00 1.33E+04 RU-106 1.11E+04 0.00E+,9 1.3
,3 0.00E+00 1.50E+04 0.00E+00 1.73E+05 AG-i110M 2.51 E+07 1.6 EJY~).352*07 0.00E+00 3.1-5E+07 0.00E=-00 2.01E+09 TE-125M 8.86E+06 02+0& -1.18E+06 2.49E+06 0.OOE+00 0.00E+00 8.55E+06 TE-127M 2.50E+07
.7
+ 6 2.t6E+06 5.97E+06 7.12E+07 0.00E+00 2.02E+07
- ------------ A-TE-129M 3.26E4 1J0 +06 5.06E+06 1.05E+07 9.66E+07 0.00E+00 3.972+07 1-131 1.57E+0N1.57E+09 8.95E+08 5.21E+11 2.58E+09 0.00E+00 1.40E+08 1-133 2.06E+07 12.55E+07 9.66E+06 4.74E+09 4.252+07 0.OOE+00 1.03E+07 CS-134 6.80E+10 1.12E+11 2.35E+10 0.00E+00 3.46E+10 1.24E+10 6.01E+08 CS-136 3.04E+09 8.36E+09 5.41E+09 0.002+00 4.45E+09 6.64E+08 2-94E+08 C0-137 9.68E+10 9.26E+10 1.37E+10 0.00E+00 3.02E+10 1.09E+10 5.80E+08 BA-140 1.41E+07 1.24E+04 8.23E+05 0.00E+00 4.02E+03 7.37E+03 7.15E+06 CE-141 2.63E+03 1.31E+03 1.95E+02 0.00E+00 5.74E+02 0,00E+00 1.63E+06 CE-144 1.95E+05 6.11E+04 1.04E+04 0.OOE+00 3.38E+04 0.002E00 1.59E+07 PR-143 8.61E+01 2.59E+01 4.27E+00 0.00E+00 1.40E+01 000E+00 9.29E+04 ND-147 5.34E+01 4.33E+01 3.35E+00 0.OOE+00 2.37E+01 0.00+E00 6.85E+04 145
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.5.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK N UC.L* -IE ORGAN..6
- B*h - 6 DOS FACTO:¥b R'S; -; *-m're m/year pr;, p-*
- i-/.......
-G I-NE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3*
0.00E+00 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2,04E+03 2.04E+03 C-14 4.86E+08 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 CR-51 0.00E+00 0.00E+00 5,99E+03 3.33E+03 1.31 E+03 8.55E *3"1..01_*. E+06 MN:-54
-oOO-E+o-- 1-.68E+06-3.34E+05- "-OOE-+0"" 5.02E 05 '" 0 0-.45E+06 FE-55 5.79E+05 4.11E+05 9.58E+04 0.00E+00 0.00E+00 AQ6*+0
.7E5 CO*0~~~~~~~~~
_.0EO 3.4+6
,2÷6
.0÷0..E0
.0E
.35E*07 FE-59 6.742E+05 1.07E+06 6.08E+05 0.00E+00 -.00E0g 0,00E+00 3.72E+06 8 + 8 -4 1 E O
-_ O +0--5-E 08 O E 0 -3 7E---
GO-586 0.0E+00 953E7+05 2.20E+06 0.0O*0 0E+00 0.00E E+00 1.310E+07 CO-60 13E1 0.00E÷00 3.34E÷10 7,52E÷06 0.00E*00 0.00O OE+00 4359E-+07 NY-63 1.42E+09 0.00E+08 4.81E+07
.OE00 *.00E+00 0.0E+00 1.78E+07
- o --
o o- 0E *0--
- ; -* --0 O-- 0--"-
ZN-653 2.63E+08 8.78E+080 4.1E+08 0.00E+00 7.562E+02 0,00E+00 3.72E+08 RB-106 4.50E+00 5.67E+08 25.67E08 0.005t00 8.69E+03 0.00E+00 8.40E+07 SR-9012.M39E+11 O.0E+00 3.43E+105 01E+X 0.00E+00 0,00E+00 1.906E+09 ZR-957 1.98E+072 6.25+06 4.23 0
24E+00 9.18E+01 0.00E+00 1.44E+05 1G-133M 8.16E+07 1.44E0 4.40E+06 2.01E+09 2.09E+07 0,00E+00 3.07E+09 3.22E+10 O.00E+00 2.20E+10 3.66E+09 0.00E+00 2.89E+09 1.86E+10 0.00E+00 1.82E+10 g--
0------
-- 2--------
8.18E+01 0-00E+00 3.35E+02 4.25E+03 0.00E+00 1.95E+04 8.41 E+09 8.62E+08 4.56E+08 4.27E5+08 7.07E+09 7.60E+08 0.00E+00 2.'04E+06 0.00E+00- 1.99E-+07 CS-134 2.9.5E+10 6.93E+10 CS-136 1.35E+09 5.30E+09 CS-137 4.02E+10 6.34E+10 CE-141 1.07E+03 7.12E+02 CE-144 7.90E+04 3.27E+04 PR-143 3.48E+01 1.39E+01 1.73E+00 0.00E+00 8-08E÷00 0.00E+00 1.15E+05 ND-147 2.18E+01 2.37E-101 1.42E+00 0.00E+00 1.39E+01 0.00E+00 8.54E+04 146
TMI - Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.5.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-GOAT-MILK 1-6 _E_-Wf6&,
m_ýa_ jý~sec-----------
NU ------
E
BO6NE_
LIVER --
T.BODY -THYROID KI DN EY --- LUNG ---
GI-LLI H-3 0.OOE+00 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 0-14 2.64E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 CR-5I 0.OOE+00 0.00E+00 3.43E+03 2.05E+03 7.56E+02 45 8.63E+05 MN-54 0.005+00 1.01E+06 l:'93E+05 O.OOE+OO 3.01E+05 Q$EO
-,3.IE+06 FE-55 3.27E÷05 2.26E+05 5.26E+04 0.002+00 O.OOE+00
&2
+0W 1.30E+05 FE-59 3.87E+05 9.09E+05 3.48E+05 0.002+00 0CE0 2E053.03E+06 co-*8~~~~~~~~~~~
o-o-o-.;*o-TEo-o~o+ooo_
o---------T CO-5B 0.002+00 5.66E-i05
.1.27E+06 0.002+00 0.00E OE+0O 1.15E+07 CO-60 0.OOE+00 1.97E206 4.35E+06 0.00+E00 0E,0O O.00E+00 3,70E+07 NI-63 8.08E+08 5.60E+07 2.71E+07 o.oo0+00 C00o 0
o o.0oo+00 1.172+07 ZN-65 1.65E+08 524E+08 2.37E+08 0.00E+00 3.51 0E(8 0.00E+00 3.30E+08 RB-86 0.OOE+00 3.12E+08 1.45E+08 0-006f00 0.00E+00 0.00E+00 6.14E+07 SR-89 3.05E+09. 0.00E+00 8.76E+07 0.*E 00 0.00E+O0 0.00E+00 4.89E+08 SR-90 9.84E+10 O.00E+00 2.41E+10 /
Et0E+x 0,00E.00 0.00E.00.842+_-09 Y-91 1.03E+03 0.00E+00 2.76E+0*.
00 0.00E+00 0.OOE+00 5.68E+05 ZR-95 1.13E+02 3.63E+01 2.46 E+00 5.70E+01 0.00E+00 1.15E+05 NB-9S 9.92E+03 5.52E+03 03 0.OOE+/-00 5.452+03 0.002+00 3,35E+07 RU-103 1.22E+02 0.00E+00 7E+0r 0.00+E00 4.67E+02 0.00+E00 1.43E+04 RU-1 06 2.45E+03 0.0OE+
- 3.
2 0.00E+00 4.73E+03 0.00E+00 1.59E+05 AG-I10M 6.99*+06 6.4]
¢ qF 4.8E+06 0.00E*00 1*27E+07 0.OOE+00 2.64E+09 TE-125M 1.96E+06 9,E+0
.62E+05 5.89E405 7.96E+06 0.00E+00 7.81E+06 TE-127M 5.50E+06 1.9) +96 6.70E+05 1.41E+06 2.231t+07 0.OOE+00 1.84E+07 TE-129M 7.23E 706' 1.142+06 2.48E+06 3.022+07 0.OOE+00 3.64E+07 1-131 3.56E+0 5.O9E+08 2.922+08 1.672+11 8.732+08 0.OOE+00 1.342+08 1-133 4.65E+05 8.1OE+o6 2.47E+06 1.19E+09 1.41E+07 0.00E+00 7.282E06 CS-134 1.70E+10 4.04E+10 3.30E+10 0.00E+00 1.31E+10 4.34-+09.
7.07E208 CS-136 7.92E+08 3.13E+09 2.25E+09 0.OOE+00 1.74E+09 2.382+08 3.55E+08 CS-137 2.22E+10 3.03E+10 1.99E+10 0.00E+00 1.03E+10 3.42E+09 5.87E+08 BA-140 3.24E+06 4.07E+03 2.12E+05 0.00E+00 1.38E+03 2.33E+03 6.67E506 CE-141 5.82E+02 3.94E+02 4.47E+01 0.00E÷00 1.83E402 0.00E+00 1.51E+06 CE-144 4.30E+04 1,80E+04 2.31E+03 0.00E+00 1.07E+04 0.OOE+00 1.45E+07 PR-143 1.90E+01 7.60E+00 9.40e-01 0.002+00 4.39E-00 0.00E+00 8.30E+04 ND-¶147 1.13E+01 1.31E+01 7.82e-01 0.00E+00 7.65E+00 0.00E+00 6.28E+04 147
SK4 00+RaOO-009ý00'0 00+300'0 00+A9000 00+A00'0 00+300'0 00+2;00'0 LfrL-QN 00+E]00'0 00+200'0 00+300,0 00+B3000 00+300'0 00+3-00,0 00~a9000 S4-~18d 00O+00'0 00+300'0,00+300'0 00+300'0 00+300'0 00+300*0 00+300*0 "V3L-0
- 00+300'0 00+300'0 00+300'0 O0+3OcrO 00+300*0 00+E]00*0 00+]00*0 Lti--0 00+900'0 ao+ý100o 00+300'0 00+300'0 00+300-0 00+B9000 00+300'0 014ý-Vs 00+300'0 00+300'0 00O+200'0 00+300*0 00+300"0 00+BG000 00+B9000 00+300,0 00+300'0 00+300'0 00+300*0 00+300'0 00+300'0 004-300,0 00-300'0 00+300*0 00+300'0 00+900'0 00+9300'0 00+200*0 00+300'0 00+300*0 00+900,0 0+2100*0 00+300'0 00+300'0 00+3 00'0 00+300'0 00+300'0 00+300'0' 00+E]00'0 00+300mm0 00+300*0 004-300 00+3-00,0 00+900 O0-+3000 0oao~
00+900'0 9000oo 00+300-0 00+300 00+B9000 00+M0,0 00+300'0 00+300'0 00+300*0 00+300*0 004-2000 00OM0*0 00+300'0 00+900*0 00+A9000 L-CL-so 00+900,0 00+BJ000 9S k-G0 00+300'0 00+300'0 i~chSo 00+300o0 00+300*0 00+300'0 00+300' 00+300*0 00+300*0 00+300'D 00+300"o 00+30k 0O+300*0 00+300*0 00+300'0 00+300'0 00-'-
0 900'0 00+300'0 00+300'0 00+300' p0
+00+00 00+300'0 00+300'0 00+3000 z++
00 O030 00+900Q~E
>0+060 00+300 r 0 90 O + 00 00+300'0 00+9000O 00+300'
~-00.0 00+B3000 00+300'0 00+200*0 0+30ýQ 0+300*0 00+300,0 00+300"0 00-300,0 0+30 00+300*0 00+300*0 00+300'0 00+aO' 0 0-0 00+300'0 00+300*0 00+00000~
00'-00 00+300'0 00+300'0 004300'0 00+90 0+300'0 00+900*0 00+300'0 003;.
0O+0 0
00+9100,0 00+900*0 00+900*0 OJ0 af 0 00+ý100'0 00+300'0 00+3@00*0 00+ý100'0 O4000 0+300'0 00+300'0 00+300-a Oo+300-n
~0+300'0 00+300*0 00 +3000 00+300,0 00+300,0 00+300,0 00+300*0 00+300"0 00+200*0 00+300'0 00+E9000 00+300-0 00+300"0 00+M 0,0 00+9 00 0 00+2:00*0 00+3-9000 00+300'0 00+300'0 00+300,0 00+900-0 00+a9000 00+300,0 00+300*0 MUL-3i NM9~-31 90 V-fl LB-A 06-)iS 99-NZ
£9-IN
.09-00 00+300'0 62-2=1 00+300'0 99-31 00+E]00'0 tg9-NIN 00+300*0 L9-mI0 00+300*0 K4-0 00+300'0 1-11-IE9 EONf A3NC[rA GIONAHJ.
,C1OS"J.
IABAII BN02 oes9/!Oyd.id jaiA/wa1w -
W,SMO-L0V4 3SOa NVE)N0 lV9VdI-AOO-SSV8
- AVMAHIVdI INVziN : dfltD0 Vf Rf ' SIZOejsoA BO em41Bd V9*9 alsv1 zz (woao) panuiew uoijulnole3 asoa all-.rWo
-ON UGISIAGH ala LO*OOZtr-N'ld-OL99 ajnP90OJd SIO.4uOO 18016010!PeM I L mun -mi jeqwnN
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 6.6.2 Pathway Dose Factors, Ri AGE GROUP: CHILD - PATHWAY: GRASS-COW-MEAT
-- ~-------------------------------------
BONE ---
LIVER --
T.BODY - THYROID -- KIDNEY --- LUNG -
GI-LLI H-3 0.00E+00 C-14 3.84E+08 CR-51 0.00E+00 MN-54 0.OOE+O0 FE-55 4.57E+08 FE-59 3.77E+08 2.34E402 7.67E+07 0.QOE+00 8.01 E+06 2.43E+08 6.10E+08 CO O.00-+00 1.64E+07 CO-60 0.00E+00 6.93E+07 NI-63 2.91E+10 1.56E+09 2.34E+02 7.67E+07 8.78E+03 2.13E+06 7.52E+07 3.04E+08 5.03E+07 2.04E+08 9.91E+08 2.34E+0 7.67E+0 4.88E+0 0.00E+0 0.00E+0 0.00E+0 0.00E+0 0.00E+0 0.OOE-'-
2 2.34E+02 2.34E+02 2.34E+02 7
7.67E+07 7.67E+07 7.67E+07 3
1.33E+03 8.90E 3%4.66E+05 0
0.00E+00 3 j_+0O' 4.49E+07 o
0*ooE+0J
-E-0 8
6.35E+08 0
0.00ý 'E E+00 9.58E+07 o
O*E+0dV.OOE+00 3.84E+08 0
o0_0 0.00E+00 1o05E+08 ZN-65 3.76E+08 11.00E+09 6.22E+08 O.OOE+00 6.31 E08 RB-86 0.00E+00 5.76E+08 3.54E+08 0.00 F-00 0.00E+00 SR-89 4.82E+08 0.00E+00 1.38E+07 0.9 E 00 0.00E+00 SR-90 1.04E+10 0.002+00 2.64E+09 0E9-"
0+00E+00 Y-91 1.80E+06 0.00E+00 4.82E+0 00 0.OOE+00 ZR-95 2.66E+06 5.86E+05 5.21f+'M,ý VE+00 8.38E+05 NB-95 3.10E+06 1.21E+06 5NM 0.OOE+00 1.13E+06 RU-103 1.55E+08 0.00E+00 E+'r 0.00E÷00 3.90E+08 RU-106 4.44E+09 0.00E+t*
- 5.
08 0.OOE+00 6.OOE+09 AG-110M 8.39E+06 5.67EeQ').53E÷06 0.OOE+00 1.06E+07 TE-125M 5.69E+08 6 4E+0 8e7.59E+07 1.60E+08 0.00E+00 TE-127M 1.78E+09
+4.71+
8 2.11E+08 4.25E+08 5.06E+09 TE-129M 1.79E. 4$
0+08 2.78E+08 5.77E+08 5.26E+09 1-131 1.66E+0
- 1. 7E+07 9.48E+06 5.52E+09 2.74E+07 1-133 5.72e-01 7 7.08e-01 2.68e-01 1.31 E÷02 1.182+00 0.00E+00 1.76E+08 0.00E+00 3.71E+07 0.00E+00 1.87E+07
- 0. 00E+O0 O.OOE+00 O.OOE+00 1.40E+08 2.40E+08 6.11E+08 0.O0E+00 2.23E+09 0.00E+00 4.01E+09 0.00E+00 6.91E+10 "o-o--OO-----------
0.00 E+00 6.74E+08 0.00+E00 5.49E+08 0.00E+00 1.44E+09 O.OO-+00 2.18E+09 0.00E+00 1.48E+06 0.00E+00 2.85e-01 CS-134 9.23E+08 CS-136 1.63r+07 CS-137 1.33E+09 BA-140 4.42E+07 CE-141 2.22E+04 CE-144 2.32E+06 1.51E+09 3.19E+08 0.00E+00 4.69E+08 1.68E+08 8.16E+06 4.48E+07 2.90E+07 0.00E+00 2,39E÷07 3.56E+06 1.57E+06 1.28E+09 1.89E+08 0.00E+00 4.16E+08 1.50E+08 8.00E+06 3.87E+04 2.58E+06 000E+00 1.26E+04 2.31E+04 2.24E+07 1.11E+04 1.65E+03
-O00E+00 4.86E+03 0.00E+00 1.38E+07 7.26E+05 1.24E+05 0.00E+00 4.02E+05 0.00E+00 1.89E+08 PR-143 3.33E+04 1.00E+04 1.65E+03 0.00E+00 5.42E+03 0.00+E00 3.60E+07 ND-147 1.17E+04 9.48E+03 7.34E+02 0.00E+00 5.20E+03 0.00E+00 1.50E+07 149
TMI - Unit I Number I
Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.6.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-COW-MEAT NUCLIDE ----
ORGAN DOSE FACTORS; mnz - mnrem/year per pACisec H-3 0.00E+00 1.93E+02 C-14 2.04E+08 4.08E+07 CR-51 0.00E+00 0.O0E+O0 O'0;0;0E--&"
MN-54 0.002+00 7.OOE+06 FE-55 2.38E+08 1.69E+08 FE-59 2.12E+08 4.95E+08 1.40E+07 5.83E+07 1.07E+09 CO-58 0.00E+00 CO-60 0.00E+00 NI-63 1.52E+10 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 5.63E+03 3.13E+03 1.23E+03 8.03E 9..46E+05 "1
.39E+06 0.OOE+00 2.09E+06 0 O42-07 3.94E+07 0.OE+00 0.00E+00 *03W÷00 7.31 E+07 1.91E+08 0.OOE+00 0.O+
I.E 08 1.17E+09 3.24E+07 0.002+00 0.0 0+00 1-94E+08 "1.31E+08 0.OOE+00
- 0. 2+00
,00E+00 7.60E+08 5.15E+08 0.00E÷00 0.00 0
O.0E+00 1.71 2+08 ZN-65 2.50E+08 8.68E+08 4.05E+08 0.OOE+00 5.56E-f08 RB-86 0.00E+00 4.06E+08 1.91E+08 0.005t00 0.00+00 SR-89 2.55E+08 0.00E+00 7.29E+06 0.gQlk0, O.OOE+00 s-------------8-E*
'-----------o--
]-9*o;;-o-- *-.0;O S-90 8,04E+'09 0.OOE+00 1.99E+09 E+'
-0.002+00 Y-91 9.54E+05 0.00E+00 2.56E+O 00 0.00E+00 ZR-95 1,50E+06 4.73E+05 3.25E+00 6.95E+05 O------- ----------
NB-95 1.79E+06 9.95E+05 N.05 0.OOE+00 9.64E+05 RU-103 8.56E+07 0.OOE+00
. 6E+07 0.00E+00 3.02E+08 RU-1 06 2.36E+09 0.00E+
08 0.00E+00 4.54E+09 AG-I IOM 5.06E+06 4.7 E 91E+06 0.OOE+00 9-13E+06 TE-125M 3.03E+08 9E+0,4.05E407 8.46E+07 0.OOE+00 TE-127M 9.41E+08
+
1.12E+08 2.24E+08 3.81E+09 TE-129M 9.49E-t~\\
+08 1.50E+08 3.06E+08 3.97E+09 1-131.
8.93E+06
.*5E+07 6.72E+06 3.65E+09 2.15E+07 1-133 3.08e-01 (5.22e-01 1.59e-01 7.29E+01 9.16e-01 CS-134 5.23E+08 1.23E+09 5.71E+08 0.OOE+00 3.91E+08 CS-136 9.43E+06 3.71E+07 2.49E+07 0.00E+00 2.02E+07 CS-137 7.24E+08 9.63E+08 3.35E+08 OfOOF+00 3 28F+fA 0.00E+00
- 3.68E+08 0.OOE+00 6.00E+07 0.OOE+00 3.03E+07 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+/-00 0.00E+00 O.OOE+00 0.002+00 2.26E+08 3.91E+08 1.09E+09 4.25E+09 7.15E+09 1.13E+11 1-34E+09 8.94E+08 2.35E+09 3.56E+09 2.47E+06 3.95e-0t 1,49E+08 1.53E+07 3.18E+06 2.99E+06 I "27F=+fl I 'k7fI+A~7 BA-1 40 2.39E+07 2.93E+04 1.54E÷06 CE-141 1.18E+04 7.87E+03 9.05E+02 CE-144 1.23E+06 -5.08E+05 6.60E+04 PR-143 1.76E+04 7.03E+03 8.76E+02 ND-;147 6.23E+03 6.78E+03 4.06E+02 0.00E+00 9.94E+03 1.97E+04 3.69E+07 0.00E+00 3.71E+03 0.00E+00 2.25E+07 0.00E+00 3.03E+05 0.00E+00 3.09E+08 O.00E+00 4.08E+03 0.00E+00 5.79E+07 0.00E+00 3.98E+03 O0.00E00 2.44E+07 150
Number TMI - Unit I Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.6.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT
-N U C L D E
--.....- -6 R 'A h -6 6 § E * =A;
- :r b-R -S i ;-m ------/y e a ----p---C -;I
- F -s &-
ORGAN.DOSE.FACTORS;.m -_reiya pe-pi/e NULD--------------------------
H-3 0.OOE+00 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 C-14 2.42E+08 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 CR-51 o.OOE+00 0.OOE+00 7.04E+03 4.21E+03 1.55E+03 9.3!EIe
..77E+06 MN-54 0.OOE+00 9.18E+06 1.75E+06 0.O0E+00 2.73E+06 0~E).
81E+07 FE-55 2.93E+08 2.03E+08 4.73E+07 0.OOE+00 0.OOE+00 o
+0 1.16E+08 FE-59 2,66E+08 6.25E+08 2.39E+08 0.00E+00 0.00E 08 2.08E+09
--oo-------- ---------
- -T -
- -. o"o----'-o---=o*o-------- V
£o;*
CO-58 0.OOE+00 1-82E+07 4.09E+07 0.002+00 0.00 O~~E+00 3.70E+08 CO-6o o.OOE+00 7.52E+07 1.66E+08 0.OOE+00
- 0.
+00
- .00E+00 1.41E+09 NI-63 1.89E+10 1.31E+09 6.33E+08 0.00E+00 0'0015ýOg 0.00E+00 2.73E+08 ZN-65 3.56E+08 1.13E+09 5.12E+08 0.00E+O0 7.572(08 O.OOE+00 7.13E+08 RB-86 0.00E+00 4.87E+08 2.27E+08 0.00 00 0.00E+00 0.OOE+00 9.59E+07 SR-89 3.02E+08 0.00E+00 8.66E+06
- 0.
k00 0.OOE+00 O.OOE+00 4.84E+07
- -o ---
o--o ---
o----*i *-oo* o o-------
SR-90 1.24E+10 0.OOE+00 3.05E+09Z. 0~E+~ 0.00E400 O.OOE+0O 3.60E+08 Y-91 1.13E+06 0.OOE+00 3.03E+04N.
00 0.OOE÷00 0.OOE+00 6.24E+08 ZR-95 1.87E+06 6.01E+05 4.07 T
-YE+00- 9.43E+05 O.00E+00 1.90E+09 NB-95 2.80E+06 1.28E+06 W
05 j0.002+00 1.26E+06 0.OOE+00 7.76E+09 RU-103 1.05E4+08 O.OOE+00
.0 3E+r 0.00E+00 4.02E+08 0.OOE+00 1.23E+10 RU-1 06 2.80E+09 0.00E+'g
.5 08 0.00E+00 5.41E+09 0.00E+00 1.81E+11 AG-I1OM 6.68E+06 6.1 E '
.67E+06 0.OOE+00 1.22E+07 0.00E+00 2.52E+09 TE-125M 3.59E+08 OE+08.4.81E+07 1.08E+08 1.46E+09 0.OOE+00 1.43E+09 TE-127M 1.12E+09.
3.9
+g 1.36E+08 2.85E+08 4.53E+09 0.00E+00 3.74E+09 TE-129M "1113E.08 1.79E+08 3.89E+08 4.73E+09 O0.OE+00 5.71E+09 1-131 1.08E+0Xi.
4E+07.
8.82E+05 5.04E+09 2.64E+07 0.00E÷00 4.06E+06 1-133 3.68e-01
- .41e-01 1.95e-01 9.42E+01 1.12E+00 0.00E+00 5.76e-01 CS-134 6.58E+08 1.57E+09 1.28E+09 0.00E+00 5.07E+08 1.68E+08 2.74E+07 CS-136 1.21rE+07 4.78E+07 3.44E+07 O.OOE+00 2.66E+07 3.65E+06 5.43E+06 CS-137 8.72E+08 1.19E+09 7.82E+08 0.00E+00 4.05E+08 1.35E+08 2.31E+07 BA-140 2.90E÷07 3.64E+04 1.90E+06 O.OOE+00 1.24E1=04 2.08E1+04 5.96E+07 CE-141 1.41E+04 9.51E+03 1.08E+03 0.OOE+00 4.42E+03 0.00E+00 3.64E+07 CE-144 1.46E+06 6.10E+05 7.83E+04 0.OOE+00 3.62E+05 0.00E+00 4.93E+08 PR-143 2.09E+04 8.40E+03 1.04E+03 0.00E+00 4.85E+03 0.00E+00 9.17E+07 ND-147 7.08E+03 8.18E+03 4.90E+02 0.OOE+00 4.78E+03 0,00E+00 3.93E+07 151
z9 L.
00+B3O00 O+200"0 OD+3000O 00+300*0 00+9O000 00+900'0 00+300"0 Lt4-CON 00+ý3O00*
00+300'0 00+300'0 00+900*0 O00300'0 00+300'0 O00+900'0 CK"->8d 00+300'0 00+R3000 00+300*0 00+300*0 00+300'0 00+300,0 00+300,0 11t4-30 00+300'0 00+900'0 00+300'0 00+300'0 00+300'0 OD+A0O*0 00+200*0 I14'-~3 00+300o0 00+300'0 00+300'0 00+300'0 00+A00'0 00BO'-30*
00+300'0 ov.-Vs 00+300*0 00+300'0.
o~0o 00+300* 0 00O+300'0 00+20000 00+300000200 Le L-80 00+300*0 00+3100*0 00+3O00' 00+300*0 00+300*0 00+-300*0 004-300'0 9cV-S3 00+300*0 00+200*0 00+300*0 00+'300'0 00+300'0 00+-300O 00'-3000 U
00+300.0 00+200*0 O00'300'0 00+300'0 00+300*0 00-'330 '0 0i300"0 C
00+300O0 O00+300,0 00+300*0 0C~0+90O 00+300,0 00+ 00 0300,0 I'fIý-3L 7----------------------
00+300*0 00+300'0 00+300'0 00+300'0 00+300*0 0X 0 00+300'0 V'JLýV3L 00+R300 0 0+E300*0 00+300*O O+00
' 0a O o+3o0*q0*I,.eo aro 0O*~o-30O VIOg- ýAL.
00+300'0 00+300'0 00+300'0 00+300*0 00+300'"
0.i300'0 00+300*0 WOýL-flf 0o+300'0 OO+a00'0 00+300*0 00+300-0 00 0
- e0+;3000 0o+3000 go6-8W 00+300'0 00+900'0.
00+900*o o
~0 00+3000 00+0 o~aooo+30oo~
co6vniZ 00+00, 009000 0+30*0 0+BD'O0000+B3000 00+B3000 96-XS 00+/-2000o 00+B3000 00+200*0 00~
+00'0 00+B3000 00+300'0 1-6-M 00+300*0
.00+300'0 00+30L0,00 004-3000' 00 3 0 0+3000 0
00+20 0 0 4300'0 00+300'0 69-AI 0O+F100*0 00+BO000 00+300 00+000 00+3000 0+00 00i300'0 06-1S oo+;300'0 00+300*0 00+30;0; 00+3a0 00+900,0 00+M-000 00+'300'0 69-NS 00+900*0 0o0+D0ff0 00+300n 00+300,0 00+D300*0 00+M00.0 0O+300*Q W9iN 00+300'0 00+300'0'S0+OO'O 00+300'0 00+300'0 001-300'0 00+300'0 09-NZ
- 00+300"0 0+1'0 o+00 100+300'0 00+'300*0 O00+300'0 00+'300*0 69-IN 00+300'0 0-'- 0 00+3 0 00+300'0 004-900'0 00+43000 00i-30W0 09900 00+-300*
0 00+0 V300,0 00+300,0 0O+39000 0Qao~o0+3000 Q+0Q t9g-00~
00+R3'000+300 0I' 0+300'0 00+300'0 00+3000' 00+300'0 00+300'0 6-q-I31 00+300'0 00+300'0
- 00+300'0 00+300'0 00+300'0 00+900*0 00+200'0 t
00+300'0 00+'300'0 00+300*0 00+300'0 00+300*0 00-300'0 00+300'0 H
MIDb E)Nfl JNON>
GI0OiAH.L A0061U U3AI1 3N08 oaiT.jad.ie~A/we.jw - W !SNIO.LOVA 3S00 NVOHIO 3I~
NOlIVI3!03A :A'k'MHiVd INVANI :dfl0~o a!Dv WSOV
'soo soa ARMIUd (WOCIO) jenudn uopinoleo aso(3 o;!s.40
'ON UOIS!AQU OWL W'OOZtr-Nld-M99 eJnPBOOJcf S]04UOO 18016010IMi
.L:Pun -iva
"TMI-Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.7.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: VEGETATION NUCLIDE --
ORGAN DOSE FACTORS; m2 remlyear per jiCi/sec, BONE LIVER TBODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4:02E+03 4.02E+03 C-14 8.89E+08 1.78E+08 1.78E+08 1.78E÷08 1.78E+08 1.78E+08 1.78E+08 CR-51 0.00+E00 0.OOE+00 1.17E+05 6.49E+04 1,77E+04 l.18E*5%6.20E+06 o--; - *o8-*
- o
-o*
-,o- ------ o---
- I,--0---
MN-54 0.OOE+00 6.65E+08 1.77E+08 0.002+00 1.,86E+08 046EQp h.58E+08 FE-55 8.01E+08 4.25E+08 1.32E+08 0.00E+00 0.00E+00 44 +0"9ý 7.87E+07 FE-59 3.98E+08 6.44E+08 3.21E+08
-OO-E+00 0.00E+0"
- 1. E08 6.71E+08 CO-58 0.002+00 6.44E+07 1.97E+08 0.O0E+00 0.00E.
O0+00 3.76E+08 CO-60 0.00E+00 3.78E+08 1.12E+09 0.00E+00
- 0.
E+01 V0.00E+00 2.10E+09 NI-63 3.95E+10 2.11E+09 1.34*+09 0.OOE+00
.0+0Q 0.00E+00 1.42E+08.
- *O--
-? ; --o-O G- ---
E--
0----------
ZN-65 8.12E+08 2.16E+09 1.35E+09 0.OOE+00 1.36E~ 09.00+00 3.80E+08 RB-86 O.OOE+00 4.51E+08 2.77E+08 0,00 00 0.00E+00 0.OOE+00 2.90E+07 SR-89 3.60E+10 O.OOE+00 1.03E+09 0,*EI00 O.00E+00 0.OOE+00 1.39E+09 SR-90 1.24E+12 0.00E4-00 3.15E+11eVE Y-91 1.87E+07 0.00E+00 4.99E+0OdJe&-00 ZR-95 3.88E+06 8.48E+05 7.55'
'NWpE+00 T;*0';0'
- --O-E----
NB-95 4.112-E-05 1.60E+05
$iGd0~5 0.O0E+00 RU-1 03 1.53E+07 0.OOE+00 0E+0W 0.00E+00 RU-1 06 7.45E+08 0.00E+_
9.1' 07 0.00E+00 AG-110M 3.21 E+07 21E;
"'.73E+
0.00E+00 TE-125M 3.51 E+08
+V0E+0.4.67E+07 9.84E+07 TE-127M 1.32E+09
+08 1.57E+08 3.16E+08 TE-129M 8.40E-180 35 +08 1.30E+08 2.71E+08 1-131 1.43E+0
- 1. 4E+08 8.18E+07 4.76E+10 1-133 3.53E+06 4.37E+06 1.65E+06 8.12E+08 I
I I
- CS-134 1.60E+10 CS-136 8.28E+07 CS-137 2.39E+10 BA-140 2.79E+08 CE-141 6.57E+05 CE-144 1.27E+08 2.63E+10 5.56E+09 0.00E+00 2.28E+08 1.47E+08 0.OOE+00 2.29E+10 3.38E+09 0.00E+00 2.44E+05 1.63E+07 O.OOE+00 3.28E+05 4.86E+04 0,OE+00 3.99E+07 6.79E+06 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.21E+06 0.OOE+00 1.50E+05 0.00E+01) 3.86E+07 O.OOE+00 1.01E+09 0.00E+00 4.04E+07 0.002+00 0.OOE+00 0.00E+00 3.77E+09 0.00E+00 2.47E+09 0.002+00 2.36E+08 0.OOE+00 7.28E+06 0.00E+00 SA5E+09 2.93E÷09 1.21E+08 1.81E+07 7.46E+09 2.68E+09 7.96E+04 1.46E+05 1.44E+05 0.OOE+00 2.21 E+07 0.OOE+00 PR-143 1.45E+05 4.36E+04 7.21E+03 ND-147 7.15E+04 5.79E+04 4.49E+03 0.00E+00 2.36E+04 0.00E+00 1.57E+08 0.00E+00 3.18E+04 0.00E+00 9.18E+07 153 1.67E+ 10 2.49E+09 8.85E+08 2.96E+08 3.97E+08 1.16E+10 2,513E+09 3.38E+08 1.07E+09 1.02E+09 1.28E+07 1.76E+06 1.42E+08 8.00E+06 1.43E+08 1.41E+08 4.09E+08 1.04E+10
TMI - Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.7.3 Pathway Dose Factors, RI AGE GROUP: TEEN PATHWAY: VEGETATION NUCLIDE ORGAN.DOSE FACTORS: m. - mrem/year per pC/sec ONE UVER T.BODY THYROID KIDNEY LUNG GI-LL H-3 0.00E+00 C-14 3.69E+08 CR-51 0.00E+00 MN-54 0.002+00 FE-55 3.26E+08 FE-59 1.80E+08 2.59E+03 7-38E+07 0.00E+00 4.54E+08 2.31E+08 4.19E+08
-cog-
-- --&-&-.-oo-'-------"
00-58 0.OOE+00 4.36E+07 C0-60 0.00E+00 2.49E+08 NI-63 1.61E+i0 1.13E+09 2.59E+03 7.38E+07 6.16E+04 9.01E+07 5.39E+07 1.62E+08 1.01E+08 5.60E+08 5.45E+08 2.59E+03 2.59E+03 2.59E+03 2.59E+03 7.38E+07 7.38E+07 7.38E+07 7.38E+07 342E-04 1.35EE+04 8.79E 1.03E+07 0.OOE+00 1.36E+08 00 0-3-2-E-+-8 O.OOE+00 0.OOE+00,R& +0-1.00E+08 0,00E+00 0.00E+0 1.oE08 9.91 E+08 0_00E+00 0.00 OE+00 6.01 E+08 O.
000E+00 0
E+0O
.00E+00 3.24E+09 0.00E+00 :0.0 0
0.00E200 1.81 E+08 ZN-65 4.24E+08 1.47E+09 6.86E+08 0.00E+00 9.42E208 0.00E+00 6.23E+08 RB-86 0.00E+00 2.73E+08 1.28E+08 0.00o&O0 0.00E+00 0.OOE+00 4.04E+07 SR-89 1.52E+10 0.00E+00 4.34E+08 0.9&E-00 0.00E+00 0.00E+00 1.80E+09 SR-90 7.51E-11 0.002+00 1.85E+11 0E4-X" 0O00+00 00*0o+00 2.1IE+10 Y-91 7.84E+06 0.00E+00 2.10E+0O 00 0.OOE+00 0.00E+00 3.22E+09 ZR-95 1.72E+06 5.43E+05 3.73!!
N IVE+O0 7.98E+05 0.OOE+00 1.25E+09 NB-95 1.92E+05 1.07E+05'
.002+00
-1.03E+05 0.00E+00 4.56E+08 RU-1 03 6.82E+06 0.00E+00
.*2E+0 0.00E÷00 2.41E÷07 0.OOE+00 5-70E+08 RU-106 3.09E+08 0.00E 07 0.OOE+00 5.97E+08 0.OOE+00 1-48E+10 A-I-hOM-1.52 7
"4 pE
.72E-"06 O.00+00 2.74E+07 O.00E+00 4-3E-+09 TE-125M 1.48E+08
,E+07*;
1.98E+07 4.14E+07 0.00E+00 0.OOE+00 4.37E+08 TE-127M 5.52E+08 1.9
+ 8 6.56E+07 1.31E+08 2.24E+09 0,OOE+00 1.37E+09 TE-129M 3.61 E-'~rA
+08 5.72E+07 1.172+08 1.51E+09 0.OOE÷00 1.36E+09 1-131 7.69E+2-.
1.8SE+08 5.78E+07 3.14E+10 1.85E+08 O.OOE+00 2.13E+07
.1-133 1.94E+06
--.29E+06 1.00E+06 4.59E÷08 5.77E+06 O.OOE+00 2.49E+06 CS-134 7.10E+09 1.67E+10 CS-136 4.39E+07 1.73E+08 CS-137 1.01E+10 1.35E+10 BA-140 1.39E+08 1.71E+05 CE-141 2.83E÷05 1.89E+05 CE-144 5.28E+07-2.18E+07 7.75E÷09 1.16E+08 4.69E+09 O.OOE÷00 O.OOE+00 O.OOE+00 5.31E+09 9.41 E+07 4.59E+09 2.03E+09 2.08E+08 1.48E+07 1.39E+07 1.78E+09 1.92E+08 8.97E+06 0.00E+00 5.78E+04 1.15E+05 2,15E+08 2.17E+04 O.OOE+00 8.90E+04 0.00E+00 5.41E+08 2.83E+06 O.OOE+00 1.30E+07 O,OOE+00 - 1.33E+10 PR-143 6.99E+04 2.79E+04 3.48E÷03 0.00E+00 1.62E+04 ND-147 3.62E+04 3.94E+04 2.36E+03 0.OOE+00 2.31E+04 0.00E+00 2.30E+08 0.00E+00 1.42E+08 154 r,t.
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 5.74 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: VEGETATION NUCLIDE...
OR GANDOSE FACTORS; m -nmrem/year per p.Cilsec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 C-14 2.28E+08 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 CR-51 o.0ooE+0 0.00+E00 4.64E+04 2.77E+04 1.02E+04 6.15E 1.*1*7E+07 MN-54 0.OOE+00 3.13E+08 5.97E+07 0.002+00 9.31E+07
- 0) a -
58E+08 FE-55 2.10E+08 1.45E+08 3.38E+07.
0.00E÷00 0.OOE+00,0o *+0 B.31 E+07 FE-59 1.26E+08 2.97E+08 1..14E+08 0.ooE+00 OOE+
8 E 07 989E+08 Z--------------- -------------- ----------------.; '* - E--
0--- ;--------
RB-58 0.00E+00 3.07E+07 6.89E+07 0.00-+00 0.00 E 0
0E+00 6.32E+08 00-60 0.00E+00 1.67E+08 3.69E+08 0-0OE+00 0
E+0
.00E+00 3.14E+09 NY-63 1.042+10 7.21E+08 3.49E+08 0.OOE+00 00 0.OOE+00 1.50E+08 ZN-65 3.17E+08 1.01E+09 42.56+08 O.*0E+00 6.75 E08 O.OOE+00 6.36E+08 RB-86 0.7E0+00 2.19E+08 1.02E+08 0.00E÷0 0.002+00 OOE+00 4.32E+07 SR-89 9.98E+09 0.00E00 "2.86E+08 0.0EO+ 00.02E+00 0.0E+00 1.60E+09 SR-90 6.05E+11 0.00E+00 1.48E+10 0.0E+
1.OOE+07 0.OOE+00 1.75E+10 Y-91 5.1 2E+06
,O.0E+00 I.37E+O7 R.900 3.OOE+08 0.OOE+00 2.82E+09 ZR-91 1.17E+06 3.77E+05 2.556
.E+00 5.912E+05 0.00+E00 1.19E+09 NB-95 1.42E+05 7.92E+04 07 7
OOE+00 7.83E+04 0.00E+00 4.81 E+08 RU-103 4.77E+06 0.01+00 11E+086 0.02E+00 1.82E+07 0.OOE+00 5.57E+08 RU-106 1.93E+08 01,OE+08 7.2_
8 0.00E+00 3.72E+08 0.O9E+00 1.25E+10 AG-I137 6.36E-÷0798.70E0 5.79E+09 0.00E+00 1.922+07 9.81E4-0O 3.98E+08 AG-110M 1.05E+07 1.72E+6'05 9AE+06 0.00E+00 1.92E+07 9.29E+04 3.98E÷09 TE-125M 9,66E+07 3E+05 1.29E+07 2.90E+07 3.932+08 0.00E+00 3.86E+08 TE-127M 3.49E+08 1.2
+ 8 4.26E+07 8.93E0+07 1.42E+09 0.00E+00 1.17E+09 TE-129M 6.25E0
+07 3.97E+07 8.63E+07 1.05E+09 0.00E+00 1.26E.+09 1-131 8.08E+001. 6E+08 6.62E+07 3.79E+10 1.98E+08 0.OOE+i00 3.05E+07 1-13:3 2.09E+06 ~3.63E+06 1.11 E+06 5.34E+08 6.33E+06 0.OOE.00 3.26E+06 7-------------------
CS-134 4.67E+09 1.112+10 9.08E+09 0.002+00 3.59E+09 1.19E+09 1.94E+08 CS-136 4.28E+07 1.692+08 1.22E+08 0.O0E+00 9.41E+07 1.292+07 1.92E+07
ýCS-137 6.36E+09 8.70E+09 5.70E+09 0.002+00 2.95E+09 9.81 2. 08 1.68E+08 BA-140 1.29E+08 1.62E+05 8.472+06 0.002+00 5.522+04 9.29E+04 2.66E+08 CE-141 1-972405 1.33E+05 1.61E+04 0.OOE+00 6.20E+04 Q.OOE+00 5.10E+08 CE-144 3.292+07 1.38E+07 1.772+06 0.002+00 8.16E+06 0.002+00 1.11E+10 PR-143 6.25E+04 2.51E+04 3.10E+03 0,00E+00 -1.45E+04 0.002+00 2.74E+08 ND-147 3.34E+04 3.85E+04 2.31E+03 0.OOE+00 2.25E+04 0.00E+00 1.85E+08 155
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 "Wle Revision No.
Offsite Dose Calculation Manual (ODCM) 22 6,0 TMI-1 GASEOUS WASTE TREATMENT SYSTEM 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System (see Figure 6.1) 6.1.1 Waste Gas System
- a.
Reactor Building:
- Reactor Coolant Drain Tank (RCDT) header
- b.
Auxiliary Building:
- Vent Header from
- 1.
Miscellaneous Waste Storage Tan
- 2.
Three (3) Reactor Coolant Bleed (RCBT)
- Waste Gas Delay Tank 4
- Two (2) Waste Gas Compressors
- Three (3) Waste Gas Decay Tanks/G
- c.
Filtration and dilution provided by the
- n Ventilation System.
6.2 Operabilitv Operability of the Gaseous Waste Treatmen mis defined as the ability to remove gas from the vent header/tank gas spaces and store i 1"er a I~er pressure in the Waste Gas Decay Tanks for subsequent release.
Except for initiating the make up t k
pland waste gas venting and the recycle or disposal of compressed waste gases stor e
ste gas decay tanks, the operation of the waste gas system is entirely automatic.e was e gas compressor comes on automatically, removing gases from the vent header syst
?s r
ired, to maintain the pressure in the system at a maximum of about 16.4 psia.
156
TMI - Unit 1 Radiological Controls Procedure Number 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 FIGURE 6.1 Waste Gas System MnsUlam A~
s p q-
"OlT 157
TM! - Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 7.1 Total Dose Calculation The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem. This control is provided in order to meet the dose limitations of 40 CFR 190.
The total dose from TMI-1 and TMI-2 (uranium fuel cycle facilities within 8 kilometers) is calculated by summing the calculated annual doses to critical organs of a real individual for liquid effluent using Section 2.1 methodology, for gaseous effluent using Section 5.2.1 and 5.2 thodology, and the direct radiation from the site from the environmental monitoring program's [1irect' adiation (TLD) monitors.
4A, 158
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitoring Program Requirements 8.1.1 Controls In accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., the radiological environmental monitoring program shall be conducted as specified in Table 8.1.
8.1.2 Applicability At all times.
8.1.3 Action a.
With the radiological environmental mo ri r
ram not being conducted as specified in Table 8.1, prepare an s "the Commission in the Annual Radiological Environmen'erati Report, a description of the reasons for not conducting the progra a required and the plans for preventing a recurrence.
- b.
With the level of radioacti ty as the result of plant effluents in an environmental sampli ium exceeding the reporting levels of Table 8.2 when averaged ov ny ca dar quarter, prepare and submit to the Commission wit* l fm the end of the affected calendar quarter, a spec tpo i
ntifies the cause(s) for exceeding the limit(s) and defin the orr vections to be taken to reduce radioactive effluents so that the
- Ial nual dose7 to a member of the public is less than the calen ear of ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODlPa lIControls 2.2.1.2, 2.2.2.2 and 2.2.2.3. When more than one of tra ion ides in Table 8.2 are detected as the result of plant effluents in t
a ling medium, this report shall be submitted if:
c ncentration (1) concentration (2) +> 1 eportinglevel (1) +reporing level (2)
When radionuclides other than those in Table 8.2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a member of the public is equal to or greater than the calendar year limits of ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part 11, Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.
159
TMI - Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22
- c.
With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 8.1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to TMI-1 Tech. Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.
8.1,4 Bases The radiological monitoring program required by this con I
vides representative measurements of radiation and of radioactive materiakn the exposure pathways and for those radlonuclides which lead to the highest poti d-ion exposures of members of the general public resulting from the fafflp*ration. This monitoring program implementsSection IV B.2 of Appen i to I1OFR50 and thereby supplements the radiological effluent monitoring program by ve 1 that the measurable concentrations of radioactive materials and levels cf~adiation are not higher than expected on the basis of the effluent rgeasurements and modeling of the environmental exposure pathways. Guidance for th monitoring is provided by the Radiological Assessment Branch Technical Po on Environmental Monitoring (Revision'l, November 1979). Program ch s ma e initiated based on operational experience.
8.1.5 Surveillance Requireme
'4 The radiological env monitoring samples shall be collected pursuant to Table 8.1, from t ecific cations given in Tables 8.4 through 8.10 and Maps 8.1 through 8.3, anq
- 11 nalyzed pursuant to the requirements of Table 8.1 and the detection caq*bTJrs uired by Table 8.3.
160
TMI - Unit 1 Radiological Controls Procedure Number 6610-PLN-4200.01 Title Revision No.
Offite Dose Calculation Manual (ODCM) 22 8.2 Land Use Census 8.2.1 Controls In accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden of greater than 50 m2 (500 ft2) producing broad leaf vegetation.
8.2.2 ApDlicabilitv At all times.
Q 8.2.3 Action
- a.
With a Land Use Census identifying a I o
at yields a calculated dose or dose commitment greater than thn val s c ently being calculated in ODCM Part I Surveillance 3.2.2.3, ursua to ODCNA, Part IV, Section 2.0, identify the new location(s) in the next'[]pual Radioactive Effluent Release Report.
With a Land Use Cens si entifying a location(s) that yields a calculated dose or dose commitment (*s me exposure pathway) 20% greater than at a location from whic V~nple,,
re currently being obtained in accordance with Table 8.1, add t 04aion(s) within 30 days to the Radiological Environmen ni
" g Program given in the ODCM. The sampling location(s), xclu he control station location, having the lowest calculated dose or jt mnnitment(s), via the same exposure pathway, may be delet m this-monitoring program after October 31 of the year in which tha d
Census was conducted. Pursuant to TMI-1 Tech. Spec. 6.14 1-2 DMS Tech. Spec. 6.12, submit in the next Annual Radioactive E;*en Release Report documentation for a change in the ODCM including a rerevi* figure(s) and table(s) for the ODCM reflecting the new location(s) with 11 rmation supporting the change in sampling locations.
L Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different sectors with the highest predicted D/Qs in lieu of the garden census.
Requirements for broad leaf sampling in Table 8.1 shall be followed, including analysis of control samples.
161 b.
.,S NQ
TMI - Unit I Radiological Controls Procedure Number 6610-PLN-4200.01 Title Revision No.
Offite Dose Calculation Manual (ODCM) 22 8.2.4 Bases This Control is provided to ensure that changes in the use of unrestricted areas are identified and modifications to the monitoring program are made if required by the results of this census. The best information from the door-to-door survey, aerial surveys, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR 50. Restricting the census to gardens of greater than 500 square feet (50 im) provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kglyr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1)*
0% of the garden was used for growing broad leaf vegetation (i.e., similar to lettu [ and bbage), and 2) a vegetation yield of 2 kg/square meter.
8.2.5 Surveillance Requirements The Land Use Census shall be conducted duriithe g ing season at least once per 12 months, using that information that will provide th results, such as by a door-to-door survey, aerial survey, or by consulting local agricult I authorities. The results of the Land Use Census shall be included in heAnnual Radiological Environmental Operating Report pursuant to ODCM, Part IV, S4 ton 1.0.
162
TMI - Unit I Radiological Controls Procedure Number 6610-PLN-4200.01 T
D lMe Revision No.
Offsite Dose Calculation Manual (ODCM) 22 8.3 Interlaboratory Comparison Program B.3.1 Controls In accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., analyses shall be performed on radioactive materials supplied as part of an Interlaboratory.
Comparison Program which has been approved by the Commission (NRC). Only those samples and analyses which are required by Table 8.1 shall be performed.
8.3.2 Applicability 8.3.3 Action With analysis not being performed as required above, 4o) e corrective action taken to prevent a recurrence to the Commission in the Ann; R. joloical Environmental Operating Report.
8.3.4 Bases The requirement for participation in an pproved Interiaboratory Comparison Program is provided to ensure that independent dlecks on precision and accuracy of the measurements of radioactive mate#al-kenvironmental sample matrices are performed as part of a quality assurance pro;en for eironmental monitoring in order to demonstrate that the results are reasonal:.Aamajg; the purpose of Section IV, B.2 of Appendix I to 10CFR50.
N 8.3.5 Comparison Program results shall be included in the al Operating Report.
163
TMI - Unit 1 Radiological Controls Procedure Number 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 8.1 Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequencyb of Analysisb
- 1. Airborne Radioiodine and Samples from 5 locations Continuous sampler operation Ra ne Canister:
Particulates from Table 8.4.
with sample collection weekly, AnkIyze jeekly for 1-131.
or more frequently if required raluA Filter:
by dust loading.
alyze for gross beta activity following filter c anged. Perform gamma
/isotopic analysis8 on composite (by location) sample quarterly.
- 2. Direct Radiationc Samples from 40 locations Sample u rterly Analyze for gamma dose from Table 8.5 (using either quarterly.
2 dosimeters or at least I1 U" e instrument for continuously measuring and recording N
dose rate at each location)(
164
TMI - Unit 1 Radiological Controls Procedure Number 6610O-PLN-4200.01I Title Revision No.
Mite Dose Calculation Manual (ODCM) 22 TABLE 8.1 Sample Collection and Analysis Requirements I' 'Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locationsa Collection Frequencyb of Analysisb
- 3. Waterborne
- a. Surfacer Samples from 2 locations Compositeg sample over Perform gamma isotopic from Table 8.6.
1 monthly period.
an" monthly.
cposl for tritium I I sample from a
uarterly.
downstream (indicator) location
- 1 sample from upstream (control) location (or location not influenced by..
the station discharge)
- b. Drinking Samples from 2 locations Comp it sample over
. Perform gross beta and from Table 8.6.
1 monthly
- d.
a s
i i
I gamma isotopic analysise monthly. Perform Sr-90 I sample at the location analysis if gross beta of
- of the nearest water monthly composite >10 supply that could be times control-Composite for affected by the stajn tritium analysis quarterly.
discharge.
.1 sample froL trol location.
- c. Sediment from Sampl*from
'cations Sample twice per year Perform gamma isotopic Shoreline (1 C~ntr)nd" Indicator)
(Spring and Fall) analysie on each sample.
from 1e
.7.
165 4
f
TMI - Unit I Radiological Controls Procedure Number 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) j 22 TABLE 8.1 Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations' Collection Frequencyl.
of Analysis"
- a. Milk
- b. Fish
- c. Food Products Samples from 4 locations from Table 8.8.
Samples from 2 locations from Table 8.9.
I sample of recreationally important bottom feeders and I sample of recreationally important predators in the vicinity of the station discharge.
1 1 sample of recreational important bottom feeder 1 sample of recrea Il important predato fTr area not influi by station disch rqe,.
Sal
"* I saple of green leafy vegetables or leafy vegetation at a location in the immediate vicinity of the station. (indicator)
"* I sample of same species or group from a location not influenced by the station discharge.
Sample semimonthly when animals are on pasture; monthly at other times.
Sample twice per es (Spring and Fl Sample at time of harvest.
Perform gamma isotopic analysise-and 1-131 ar
.cj on each sample.
C'mpoote for Sr-90 anb,,Wquarterly.
Yerform gamma isotopice and Sr-90 analysis on edible portions.
Perform gamma isotopice, 1-131, and Sr-90 analysis on edible portions.
. _______________________________
166
- 4. Ingestion ii
Number TMI-Unit I Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 8.1 Sample Collection and Analysis Requirements Table Notation
- a.
Sampling locations are provided in Tables 8.4 through 8.10. They are depicted in Maps 8.1 through 8.3.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. All deviations from the sampling schedule shall be explained in the Annual Radiological Environmental Operating Report.
- b.
Frequency notation: weekly (7 days), semimonthly (15 days), monthly (31 days),
d q rtedy (92 days).
All surveillance requirements shall be performed within the specified time te
'h a aximum allowable extension not to exceed 25% of the surveillance interval. A total maximu
.ne rerval time for any 4 consecutive tests shall not exceed 3.25 times the specified collection orin erval.
- c.
One or more instruments, such as a pressurized ion chamber for mas recording dose rate continuously, may be used in place of, or in addition to, integratin osim rs. For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one o phor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall t be used as dosimeters for measuring direct radiation.
- d.
Airborne particulate sample filters shall be analyzed 4 ss beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter y_ If Pss beta activity in an air particulate sample(s) is greater than ten times the calendar year meaof ;
Fr samples, Sr-90 and gamma isotopic analysis shall be performed on the individual sample,,
- e.
Gamma isotopic analysis means the id tiatio, and quantification of gamma-emitting radionuclides that may be attributable to the effluents frte tffty
- f.
The "upstream sample" shall b rat astance" beyond significant influence of the discharge. The "downstream sample" shall be t i an area beyond but near the mixing zone.
- g.
Composite sample lbe collected at time intervals that are short (e.g., hourly) relative to the compositing pin order to assure obtaining a representative sample.
167
TMI - Unit A Radiological Controls Procedure Number Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne Particulate Water or gas Fish Milk Food Products Analysis (pCi/L)
(pCi/mr)
(pCi/kg,wet)
(pCi/L)
(pCi/kg, wet)
H-3 20,000(a)
Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Aký Co-60 300 10,000 A
Zn-65 300 20,000 Sr-90 8
0.1 100 100 Zr-Nb-95 400 1-131 2
0.9 3
100 Cs-134 30 10 000 >
60 1000 Cs-137 50 20 2.N*
700 70 2000 Ba-La-14G 200 OF300
(
For drinking water samples. This is 141 value.
168 6610-PLN-4200..O1
TM] - Unit I Radiologica] Controls Procedure Number 6610-PLN-4200.01 Title Revision No.
OffsiteDose Calculation Manual (ODCM)
.22 TABLE 8.3 Detection Capabilities for Environmental Sample Analysise Lower Limit of Detection (LLD)b'c Airborne Particulate Fish Food Sediment Water or Gas (pCi/kg, Milk Products (pCi/kg, Analysis (pCi/L)
(pCiim3) wet)
(pCiIL)
(pCifkg,wet) dry)
Gross Beta 4
Fe-59 30 1260AN Co-58. 60 15 130 Zn-65 30 260 Zr-95 30 Sr-90 2
0,01 10 2
10 Nb-95 15 1-131 id 0.07 1
60 Cs-1 34 15 0.05 0`*
is 60 150 Cs-137 18 0.0 0
18 80 180 Ba-140 60 60 La-140 15 s15 169
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 8,3 Detection Capabilities for Environmental Sample Analysis' Table Notation
- a.
This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, which may be related to plant operations, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.
- b.
Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13 (Rev. 1).
- c.
The LLD is defined, for purposes of these controls, as the smallest concentration 9ra active material in a sample that will yield a net count, above system background, that will be detectd Vith 91% probability with only 5% probability of falsely concluding that a blank observation represents al'*weal.
For a particular measurement system (which may include radiochemical, ar
).
LLD 4.66Sb S.
E o V
- 2.22
- Y 9 exp (-XAt)
Where:
LLD is the "a priorr' lower limit of detection as defined~ a ve, as picocuries per unit mass or volume.
sb is the standard deviation of the background co g rat r of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per isin* rn, V is the sample size in units of mass4 )u r ;n 2.22 is the number of disintegraI er nute per picocurie, Y is the fractional radioch calyieýwhen applicable),
Sis the radioactive
- con nt for the particular radionuclide and At for environmental s is the elapsed time between sample collection, or end of the sample collection period, and time of cour ing.
Typical values of E, V, Y and At should be used in the calculation.
It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posterior" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small samples sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.
- d.
LLD for drinking water.
170
TMI - Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 8.4 TMINS REMP Station Locations-Air Particulate and Air Iodine Station Code BI-4 El-2 F1-3 G2-1 M2-1 A3-1 H3-1 Q4-1 Q15-1 Distance (miles) 0.8 0.4 0.6 1.4 1.3 2.6 2.3 3.5 13.5 TMINS REMP Station Station Code A1-4 B1-1 BI-2 Cl -2 D1-1 El -2 El-4 F1-2 G1-3 HI-I Ji-1 J1-3 K1-4 LI-1 MIA N1-3 P1-1 P1-2 Distance (miles) 0.3 0.6 0.4 0.3 0.2 0.4 0.2, 0.1 0.1 0.1 0.4 0.2 1..,L
- o.
Locations-Direct Radia D)
Azimuth (0)
A' 5
25 26 54 74 95 98 109 129 167 184 189 208 235 249 270 293 290 171 Map No.
Azimuth (0) 28 95 105 125 253 358 159 325 305 60 2
70 74 3
4 5
61 8
0 Map No.
9 10 11 13 14 2
16 17 18 19
- 21.
22 24 26 27 28 29 30
TMI - Unit 1 Radiological Controls Procedure Number 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 8.4 TMINS REMP Station Locations-Air Particulate and Air Iodine Station Code B1-4 E1-2 F1-3 G2-1 M2-1 A3-1 H3-1 Q4-1 Q15-1 Distance (miles) 0.8 0.4 0.6 1.4 1.3 2.6 2.3 3.5 13.5 Station Code Distance (miles)
Azimuth (0)
Map No.
0.3 0.6 0.4 0.3 0.2 0.4 A1-4 131-1 "
BI-2 C1-2 D1-1 E1-2 El -4 F1-2 G1-3 HI-I J 1-3 KI-4 L1-1 MIA NW-3 P1-I P1-2 0.1 0.1 0.1 0.4 0.2 5
25 26 54 74 95 98 109 129 167 184 189 208 235 249 270 293 290 9
10 I1 13 14 2
16 17 18 19
- 21.
22 24 26 27 28 29 30 171 Azimuth (0)
Map No.
28 95 105 125 253 358 159 325 305 60 2
70 74 3
4 5
61 8
0 TABLE 8.5
Number TMI - Unit I Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE &5 TMINS REMP Station Locations-Direct Radiation {TLD)
Station Code Distance (miles.
Azimuth (No.
Q1-2 0.2 318 31 Ri-I 0.2 335 32 C2-1 1.6 48 33 K2-1 1.1 200
- 34.
M2-1 1.3 253 3
A3-1 2.6 358 4
H3-1 2.3 159 5
R3-1 2.6 338 35 BS-1 4.8 18 36 C5-1 4.5 42 37 E5-I 4.6 81 38 F5-.1 4.7 107 39 G5-1 4.8 i3 40 H5-1 4.1 157 41 J5-1 4.9 182 42 K(5-1 5.0 200 43 L5-1 4.1 228 44 M5-1 4.3 249 45 N5-1 4.9 68 46 P5-1 4.9 285 47 05-1 5.0 318 48 RS-1 4.9
.0' 339
- 49.
D6-1 5.2 65 50 E7-1 6.8 86 51 21 53 G10-I 127 6
G15-1 14.4~
12-4
- 54.
J15-1 180
.7 Qi 5-1 3058 172 5.
TMI-Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 TMe Revision No.
Offsite Dose Calculation Manuai (ODCM) 22 TABLE 8.6 TMINS REMP Station Locations-Surface Water Station Code J1-2 (R)
A3-2 (R)
Q9-1 (F)
Q9-1 (R)
G15-2 (F)
G15-3 (F)
F15-1 (R)
Distance (miles) 0.5 2.5 8.5 8.5 13.6 14.8 12.6 Azimuth° 188 355 308 308 128 124 122 (R) = Raw Water (F) = Finished Water TABLE 8.7 TMINS REMP Station Locations-Aquatic Sed(t Station Code Al-3 GI-1 KI-3 J2-1 JI-2 Distance (miles) 0.5 0.3 0.3 1.5 0.5 Azimuth (0)
L*
137 202 182 188 173 57 59 52 52 62 63 65
.0 Map No.
67 68 69 58 57
TMI - Unit I Number I
Radiological Controls Procedure 6610-PLN-4200.01
-t'ie Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 8.8 TMINS REMP Station Locations-Milk Station Code D2-1 E2-2 G2-1 P7-1 K15-3 Distance (miles) 1.1 1.1 1.4 6.7 14.5 TABLE 8.9 TMINS REMP Station Locations-F i n Code Station Locat Downst am of Station Discharge UpS Station Discharge 174 Azimuth (0) 65 93 125 293 205 72 73 74 77 78 Statio IND BKG
TMI - Unit 1 Radiological Controls Procedure Number 6610o-PLN-4200.01 Tide Revision No.
Offsite Dose Calculation Manual (ODCM) 22 TABLE 8.10 TMSNS REMP Station Locations-Food Products Station Code D1-3 El -2 Ft-I A15-1 B10-2 Distance (mites) 0.5 0.4 0.5 10.5 10.1 Azimuth (0)
Map No.
79 2
80 85 55 65 95 117 10 28
/4 0
/4 175
TMI - Unit 1 Radroloaical Controls Prot~diir*
NumbeT nrtln.-p
-5r7nn r
Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 MAP 8.1 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 1 MILE OF THE SITE 26125" 101.05 21675 176
TMI - Unit 1 Radioloioo~[Contr l.SPrei_*rtn rji Tit~le Revision No.
Offsite Dose Calculation Manual (ODCM) 22 Number gRdllI Of
_lA'ottn
- MAP 8.2 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 5 MILES OF THE SITE 177 2
TMI - Unit 1 Radiological Controls Procedure Number 661 O-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (00CM) 22 MAP 8.3 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS GREATER THAN 5 MILES FROM THE SITE 348,75" A
11.26, 178
"Title Offsite Dose Calculation Manual (ODCM)
TMI - Unit I Radiolooic! Contrnols Prnniri=rr Number SI I.,I-II'P
.U I
Revision No.
9.0 179 22 PART lII REFERENCES
- 1.
EPRI NP-3840, RP 1560-3 Final Report, "Environmental Radiation Doses From Difficult-To-Measure Nuclides," January 1985
- 2.
"Evaluation of the Three Mile Island Nuclear Station Unit I to Demonstrate Conformance to the Design Objectives of 10 CFR 50, Appendix I," Nuclear Safety Associates, May 1976
- 3.
TMI-1. Final Safety Analysis Report (FSAR)
- 4.
TMI-2 Final Safety Analysis Report (FSAR)
- 5.
Meteorological Information and Dose Assessment System (MIDAS)
- 6.
NUREG-0017, "Calculation of Releases of Radioactive Materials in us and Liquid Effluents from PWR," Revision 1, 1985
- 7.
NUREG-0133, "Preparation of Radiological Effluent TechniI SO ifi tions for Nuclear Power Plants," October 1978
- 8.
NUREG-0172, "Age-Specific Radiation Dose Commitment Fa trrs For A One-Year Chronic Intake,"
November 1977
- 9.
Regulatory Guide 1.21, "Measuring, Evaluatir geporting Radioactivity in Solid:Wastes and Releases of Radioactive Materials in Liq54-Itd Gaous Effluents from Light-Water Cooled Nuclear Power Plants," Revision 1,-June 1974
- 10.
Regulatory Guide 1.109, "Calculati n of Ibn aln Doses to Man from Routine Releasesof Reactor Effluents forthe Purpose of EvietN pliance with 10 CFR 50, Appendix I," Revision 1, OCtober 1977
- 11.
Simplified Environment E
nt Iosimetry System (SEEDS)
- 12.
TMI Recirculation or os, April 12, 1988 and March 17, 1988
- 13.
TMI-1 Operi Pro ure, 1101 -2. 1, "Radiation Monitor Set Points"
- 14.
Title 10, Code jederal Regulations, "Energy"
- 15.
TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50
- 16.
Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of
.Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977
- 17.
TM[-2 PDMS Technical Specifications, attached to Facility License No. DPR-73
- 18.
Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979
- 19.
Title 40, Code of Federal Regulations, "Protection of Environment' I*R4$'tDI IMA")an a,*
TMI - Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 T-itle Revision No.
Offsite Dose Calculation Manual (ODCM) 22 180
- 20.
Regulatory Guide 4.13, "Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications," Revision 1, July 197.7
- 21.
Post-Defueling Monitored Storage Safety Analysis Report (PDMS SAR)
A4
TMI - Unit I Radiological Controls Procedure Offsite Dose Calculation Manual (ODCM)
Number 6610-PLN-4200.01 Revisfon No.
22 0
181 PA;ý Mfl.
I I
l *LIK*:
TMI - Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 PART IV Reporting Requirements 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1.1 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted to the Commission prior to May I of each year.
1.2 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring activities for the report period, including a comparison with pre-operational studies, with opvgn l controls as appropriate, and with previous environmental monitoring reports, and an. aessr ent of the observed impacts of the plant operation on the environment. The rep fssL o include the results of Land Use Censuses required by Part Ill, Section 8.2.
1.3 The Annual Radiological Environmental Operating Reports sh eae summarized tabulated results of analysis of all radiological environmental samples And vird mental radiation measurements required by Part II Table 8.1 taken durin perlo ursuant to the locations specified in the tables and figures in this ODCM, as well as S rized and tabulated results of these analyses and measurements in a format similar to the tae in the Radiological Assessment Branch Technical Position, Revision 1, Novembe 1979. In the event that some individual results are not available for inclusion with the report, t e port shall be submitted explaining the reasons for the missing results. The missing data sh ubmitted as soon as possible in a supplementary report.
1.4 The reports shall also include the fo
- g.
ummary description of the radiological environments monitoring program; a map(s) of al pnocations keyed to a table giving distances and directions from a point that is be een the Reactor Buildings of TMI-1 and TMI-2; the results of licensee participation in th, edabo?"tory Comparison Program, required by Part [11, Section 8.3; discussion of all deviation fr t
ampling schedule of Part Ill, Table 8.1; discussion of all the required analyses in wh LL required by Part Ili, Table 8.3 was not achievable.
A single submittal may be made for the station.
182
TM! - Unit I Number M
Radiological Controls Procedure 6610-PLN-4200.01 Tille Revision No.
Offsite Dose Calculation Manual (ODCM}
22 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NOTE A single submittal may be made for the station. The submittal should combine those sections that are common to both units at the station however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit.
2.1 Routine Radioactive Effluent Release Reports covering the operations of the unit during the previous 12 months of operation shall be submitted prior to May 1 for TMI-I and TMI-2.
2.2 The following information shall be included in both Radioactive Effluent eaeeports to be submitted each year.
- 0.
The Radioactive Effluent Release Reports shall include a summa f
antities of radioactive liquid and gaseous effluents and solid waste released from ti uined in Reg. Guide 1.21, Rev. 1, with data summarized on a quarterly basis folowin he a of Appendix B thereof.
2-3 The Radioactive Effluent Release Reports shall include the fo ng information for each type of solid waste shipped offsite during the report period:
- a.
container volume,
- b.
total curie quantity (specify whee mtifed by measurement or estimate),
- 0.
principal radionuclides (sp*
her determined by measurement or estimate),
- d.
type of waste (e.g., s e
mpacted dry waste, evaporator bottoms),
- e.
type of shipmen g., L
'ype A, Type B) and
- f.
solidificatogent(e)., cement).
2.4 The Radioactiv EffMu elease Reports shall include a summary of unplanned releases from the site to unrerict are of radioactive materials in gaseous and liquid effluents made during the reporting pe 2.5 The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part III Section 8.2.
2.6 The Radioactive Effluent Release Reports shall include the instrumentation not returned to OPERABLE status within 30 days per ODCM Part.I Controls 2,1.11b and 2.1,2b, and ODCM Part II Control 2.1.2b.
183
Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Revision No.
Offsite Dose Calculation Manual (ODCM) 22 2.7 The Radioactive Effluent Release Report to be submitted shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmosphere stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, wind
.direction, and atmospheric stability.
2.8 The Radioactive Effluent Release Report shall include an assessment of the radiation doses to MEMBERS OF THE PUBLIC due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with this ODCM.
2.9 The Radioactive Effluent Release Report shall include an assessmen4h tion doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PU B*3yjie to their activities inside the SITE BOUNDARY during the report period, to verify complian swit limits of 10CFR20.1301 (a)(1). All assumptions used in making these s en (i.e., specific activity, exposure time and location) shall be included in these repo.
2.10 The Radioactive Effluent Release Report shall also include a essment of radiation doses to the likely most exposed real individual.from reactor releases and cer nearby uranium fuel cycle sources including doses from primary effluent pa~ways and direct radiation for the previous 12 consecutive months to show conformance with 4q CFR 190 "Environmental Radiation Protection Standards for Nuclear Power Operation' Acde!4 le methods for calculating the dose contributions from liquid and gaseous effluents are giuplory Guide 1.109, Rev. 1.
0,o- -.
184
TMI - Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 "fitie Revision No.
Offsite Dose Calculation Manual (ODCM) 22 185 3.0 PART IV REFERENCES 3.1 Radiological Assessment Branch Technical Position, Revision 1, November 1979 3.2 Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974 3.3 TMI-I Technical Specifications, attached to Facility Operating License No. DPR-50 3.4 Title 40, Code of Federal Regulations, "Protection of Environment' 3.5 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Rou *n ses of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part A1,AD x I," Revision 1, October 1977 3.6 Title 10, Code of Federal Regulations, "Energy" 3.7 Regulatory Guide 1.111, "Methods of Estimating Atmosp I Tra ort and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled React/
Revision 1, July 1977 3.8 Regulatory Guide 1.112, "Calculation of Releasel of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reac,"
Revision O-R, April 1976 3.9 Regulatory Guide 1.113, "Estimating Aq ~!lDisp ton of Effluents from Accidental and Routine Reactor Releases for the Purpose of I
Appendix I," Revision 1, April 1977
- 0
TMI - Unit I Number T
Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 APPENDIX A Page 1 of I P1-Pathway Dose Rate Parameter P, (inhalation) = k' (BR) DFAI (Eq A-I)
Where:
P, = the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the inhalation pathway, in mrem/yr per microcurielm3. The dose factors are based on the critical individual organ for the child age group.
k'= conversion factor, I E6 pCi/microcude 00^
BR = 3700 m3/yr, breathing rate for child (Reg. Guide 1.109, Rev. 1, Table E DFA1 = the maximum organ inhalation dose factor for the infant age grouph dionuclide(mRempCi).
Values are taken from Table E-10, Reg. Guide 1.109 (Rev. 1),F N172.
Resolution of the units yields: (ODCM Part [II Table 4.6)
P, (inhalation) = 3.7E9 DFAi (mremlyr per l.Ci/m 3) 4 (Eq A-2)
The latest NRC Guidance has delekIJaequirement to determine P, (ground plane) and Pi (food). 1p
,ithe critical age group has been changed from infant to child. {
186
Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 APPENDIX B Page 1 of 1 Ri - Inhalation Pathway Dose Factor R= =k' (BR) (DFAg,ao) (mremlyr per mIcrocurfelim)
(Eq B-1)
Where:
= conversion factor, 1 E6 pCilmicrocurie BR = breathing rate, 1400, 3700, 8000, 8000 m3lyr for infant, child, teenager, and adult age groups, respectively. (Reg. Guide 1.109, Rev. 1, Table E-5)
DFAI,,,o = the inhalation dose factor for organ, o, of the receptor of a given age a
for the ith radionuclide, inf mrem/pCi. The total body is considered as.an orgartfl se ection of DFA9 o.
Values are taken from Tables E-7 through E-10, Reg. Guide 1.10 Re1 or NUREG 0172.
Resolutions of the units yields:
RI= (1.4E9) (DFAjao) infant (ODCM Part III Table 5.2.1)
RI = (3.7E9) (DFA1,.,0) child (ODCM Part III Table 5.2.)
Ri= (8.0E9) (DFA-,80.) teen and adult (ODCM Part les 5.2.3 and 5.2.4) 0
<2 187 TM[ - Unit 1
Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Tifle Revision No.
Offsite Dose Calculation Manual (ODCM) 22 APPENDIX C Page 1 of 1 Ri - Ground Plane Pathway Dose Factor R, = k' k" (SF) (DFG,) [(I-e -"it)lXj (Eq C-1)
Where:
k' = conversion factor, 11E6 pCi/microcurie W' = conversion factor, 8760 hrlyr X, = decay constant for the P radionuclide, sec 1 t = the exposure time (this calculation assumes that decay is the only ol 4
g removal mechanism) 4.73 x 10& sec. (15 yrs), Reg. Guide 1.109 (Rev. 1), Appendix C, DFGj = the ground plane dose conversion factor for the igb radionu e' e r per pCi/m 2). Values are taken from Table E-6, Reg. Guide 1.109 (Rev. 1), or NURq0172Vrhese values apply to all age
-groups.
- 4 SF = 0.7, shielding factor, from Table E-15 Reg. Guid 1.109(Rev. 1)
Reference ODCM Part Ill Table 5.3.1 188 A
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 APPENDIX D Page 1 of 2 Ri - Grass Cow-Milk Pathway Dose Factor
=
k' [(QF x UAP) 1 (A4 + Aj)] x (Fm) x (r) x (DFLia.o) x Where:
k= conversion factor, 1 E6 picocuriefmicrocurie (pCilici)
OF
.cow consumption rate, 50 kg/day, (Reg. Guide 1.109, Rev. 1) goat consumption rate, 6 kg/day, (Reg. Guide 1.109, Rev. 1, Table E-2)
UAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for inf ild, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev. 1)
Yp= agricultural productivity by unit area of pasture feed grass, 7
REG-01 33)
Yý = agricultural productivity by unit area of stored feed, 2.0 kg/rm EG-0133)
Fm = stable element transfer coefficient (Table E-1, Re. Guide 1.109, Rev. 1) r = fraction of deposited activity retained in cow' rass, 0.2 for particulates, 1.0 for radiciodine (Table E-15, Reg. Guide 1.109, Rev. 1)
DFL,o, 0 = the ingestion dose factor for organ, d e ith radionuclide for each respective age group, a (Tables E-1 Ito E-14, Reg. Guide 109, e.1), or NUREG 0172.
X=
decay constant for the ith ra clide,-1id6
=
ec.1 w= decay constant for wea en
- 5.
X10 sei " (NUREG-0133); based on a 14 day half life tf =
1.73 x 10 sec, th ansp e from pasture to cow to milk to receptor (Table E-1 5, Reg.
Guide 1.109, iv. I,) r days th = 7.78 x 16 OPnsport time from pasture to harvest to cow to milk to receptor (Table E-15, Reg. Guide 1.
Pev. 1), or90 days fp = 1.0, the fraction of the year that the cow is on pasture f,.=
1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture 189
TMI - Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 APPENDIX D Page 2 of 2 The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, R1 is based on (X/Q):
RXc, ao = k'k" Frn QF UApDFLt,,o (.75 [.51H1)
(Eq D-2)
Where:
k'" = 1 E3 grams/kg H = 8 grams/rn 3, absolute humidity of the atmosphere
.75 = fraction of the total feed grass mass that is water CI)
.5 = ratio of the specific activity of the feed grass water to the atmasp ic te (NUREG-0133)
DFLt,a,o = the ingestion dose factor for tritium and organ, o, for each pe'v e group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1), or NUREG 0172-All other parameters and values are as given above.
NOTE Goat-milk pathway factor, R1, will beeTputec'sing the cow-milk pathway factor equation. Fm fact r
ilk will be from Table E-2 Reg. Guide 1.109, Rev. 1.
Reference:
ODCM Part III Tables 5.4.1 to 5.4.4o -.
J 190
TMI - Unit.1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 APPENDIX E RI - Cow-Meat Pathway Dose Factor R=
k' [QF X UAP) / (11 + ?J x (Ff) x (r) x (DFLI,,o0 ) x
[((fp x f5)IYp) + ((Q-fpf5) e "ith)/Y5] x e'itf (Eq E-i)
Where:
k' = conversion factor, IE6 picocurie/microcurie (pCVi/ci)
OF:= cow consumption rate, 50 kg/day, (Reg. Guide 1.109, Rev. 1)
UA. = Receptor's meat consumption rate; 0, 41, 65, 110 kg/yr for infant, chilI n,
and groups, respectively (Reg. Guide 1.109, Rev. 1)fr l
F, = the stable element transfer coefficients, days/kg (Table -i, R 09, Rev..I) r = fraction of deposited activity retained in cow's feed grass forp culates, 1.0 for radiofodine (Table E-15, Reg. Guide 1.109, Rev. 1)
DFL=a,0, = the ingestion dose factor for organ, o, and the ithadionuclide for each respective age group, a (Tables E-11 to E&14, Reg. Guide 1.109, Rev. ),QrNUREGo172.
X. = decay constant for the radionuclide i, sed, 1w = decay constant for weathering, 57 UREG-01 33), based on a 14 day half life t = 1.73 x 106 sec, the transport..
ture to receptor (NUREG-0133) th= 7.78 x 10 sec,.the trans time crop to receptor (NUREG-0133)
Y',
agricultural productiity b un rea of pasture feed grass, 0.7 kg/rn 2 (NUREG-0133)
Y, agriculturalpr uctivi b unit area of stored feed, 2.0 kg/M 2 (NUREG-0133) f= 1.0, the fra year that the cow is on pasture f= 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture The concentration of tritium in meat is based on the airborne concentration rather than the deposition. Therefore, R1 is based on (X/Q):
Rt,,o = k'k"' F QOF MAp (DFLtA.) x 0.75 x (0.5/1-])
(Eq E-2)
Where:
All terms are as defined above and in Appendix D.
Reference:
ODOM Part Ill, Tables 5.6.1 to 5.6.4 191
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 APPENDIX F Ri - Vegetation Pathway Dose Factor R=
k' x [rl (Y. (X1 + ;.w))] x (DFLIao) x [(ULA) fL e-OilL + USA fg e'Xith]
(Eq F-1)
Where:
W =
I E6 picocurie/microcurie (pCi/pci)
ULA = the consumption rate of fresh leafy vegetation, 0, 26, 42, 64 kgtyr for infant, child, teenager, or adult age groups, respectively (Reg. Guide 1.109, Rev. 1)
Us the consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for i t
- eenager, Sage groups respectively (Reg. Guide 1.109, Rev. 1) e or adult ft = the fraction of the annual intake of fresh leafy vegetation grow
.0 (NUREG-Ol33) fq= the fraction of the stored vegetation grown locally = 0.76 REG-33) tL = the average time between harvest of leafy vegetation and its sumption, 8.6 x 104 seconds
[Table E-15, Reg. Guide 1.109, Rev. 1 (24 hrs)]
t, = the average time between harvest of stored I&
.egetation and its consumption, 5.18 x 106 seconds, [Table E-15, Reg. Guide 1.109^
1 (6 days)]
Yv = the vegetation area density, 2.0 kg a
E-15, Reg. Guide 1.109, Rev. 1)
All other parameters are as previously defined.
The concentration of tritium in vegetation i b the airborne concentration rather than the deposition.
Therefore, R, isbased on (X[Q)
Rt.' = k'k" EULA fL + USA fg] (DFL
) (.75 (Eq F-2)
Where:
All terms are as defined abov
,drn Appendix D.
Reference:
ODCM Part Ill, Tables 5.7.1 to 5.7.4 192
- g.
TMI - Unit I Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No, Offsite Dose Calculation Manual (ODCM) 22 APPENDIX A-F REFERENCES (Page I of 4)
Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site Parameter Value R.G. 1.109 NUREG-0133 Specific
- For P, ***
DFA.
Each radionuclide E-9 Note I BR 3700 m3/yr(child)
E-5
.For Ri (Vegetation)***
r Each element type E-1
-0 YV 2.0 kglm2 E-15 xw 5.73 E-7 sec' 5.3.1.
DFL1 Each age group and radionuclide E-14 Note 1 uaL Each age group
____ _1.0__
5.3.1.5 tL 8.6 E + 4 seconds E-15 Each age group E-5 f9 0.76 5.3.1.5 th 5.18_E_+6s nds E-1 5
__8,0______
5.2.1.3
- For Ri Khalation)r*
BR Each age group E-5 DFA-Each age group and E-7 thru E-10 nuclide 193
TMI - Unit I Radiological Controls Procedure Number Title Revision No.
Mite Dose Calculation Manual (ODCM) 22 APPENDIX A-F REFERENCES (Page 2 of 4)
Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site Parameter Value R.G. 1.109 NUREG-0133 Specific For R, (Ground Plane)
SF 0.7 E-1 5
- DFG, Each radionuclide E-6 t
4.73 E + 8 sec 5.3.
SFor Ri (GrasslAnlmal/Meat) *Y QF(Cow) 50 kg/day E-3 QO (Goat) 6 kgfday E-3 Ref. Only Uap
- Each age group
ý.w 5.73 E-7 secl
',,,M#"'
5.3.1.3 Ff (Both)
Each element E-1 r
Each element type E-1 5 DFL1 Each age group and nuc,*
E-1 I thru E-14 Note I fp 5.3.1.3 Note 2 5.3.1.3 Note 2 Yp 0.7 kg/mr E-15 S 7.78 Ei cE-15 Y.
2.0 kg/mr2 E-1 5 tf 1.73 E + 6 sec E-1 5 H
8.0 grams/kg 5.2.1.3 194
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No..
Offsite Dose Calculation Manual (ODCM) 22 APPENDIX A-F REFERENCES (Page 3 of 4)
Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site Parameter Value R.G. 1.109 NUREG-0133 Specific For R, (GrasslCow/Milk)
I Of 50 kglday E-3 Uap Each age group E-5 x.w 5.73 E-7 sec' A
Fm Each element E-1 r
Each element type E 5
- DFL, Each age group and nuclide E-11 thru E-14 Note Yp 0.7 kg/m2
-1 th 7.78 E + 6 sec A
Yo 2.0 kgIM2
, J tf 1.73 E + 5 sec*
A lt. E-15 fp 1.0 AO\\
... 5.3.1.3
- f.
1.0 5.3.1.3 H
8.0 grams/kg 5213 195
Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 22 APPENDIX A-F REFERENCES (Page 4 of 4)
NOTES
- 1.
Inhalation and ingestion dose factors were taken from the indicated source. For each age group, for each nuclide, the organ dose factor used was the highest dose factor for that nuclide and age group in the referenced table.
- 2.
Typically beef cattle are raised all year on pasture. Annual land surveys have indicated that the small number of goats raised within 5 miles typically are used for grass control and not fo milk. Nevertheless, the goats can be treated as full meat sources where present, despite the fact that t eir nd bers cannot sustain the meat consumption rates of Table E-5, NUREG-0133.
REFERENCES
- 1.
Regulatory Guide 1-109, "Calculation of Annual Doses to Man fro outin eleases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appei I," Revision 1, October 1977.
- 2.
TMI-1 Technical Specifications, attached to Facility Ope ring License No. DPR-50.
- 3.
NUREG-0133, "Preparation of Radiological Effluent T aI Specifications for Nuclear Power Plants,"
October 1978.
196 2001 Annual Radioactive Effluent Releases Report for TMI 5928-02-20095 Procedure Change Request PCR-00-2365 to the ODCM, 6610-PLN-4200.01
I001A FIGURE 1 of 1 PROCEDURE REQUEST FORM (PRF) PR1ORtlYI (Refer to I 001A When Completing This Form)PRI....
1000-ADM-1291.01 Revision *4 EXH1IBlT 5 Page I of 1 Reference Number:
Safety Determ irkation/SO,59 ScreenLing Review Division Doo, No. (ot,
-pLO 00, o I Rev. No.
SE No.
Rev.No. °
-"A D oc* nn'eAvivity "le 0-C K Yes No "1.
Is this a new document or activity or a substantive revision to an eYcstng document?.
L Z JA n*w document is con sdered equivalent to a substantive revision.) If YES, proceed to answer Question 2.
If NO, then procedure 1 000-ADM-1l291-01 Is not app]c.bls and documentation of nuclearsafely determinalion is not required.
- 2.
Does the dfocumnent or 2acVity Change the designcor description of thle faclitty, even temp~orarily, (rain thatwhich Is contained in the SAR?
- 3.
Does the docurrient or aclMtiy change a procedusal or operatIngdecription, even temporarily, I
which Is contained in the SAR?
- 4.
Does the document or activity involve any tests or experiments that are not described iI i
- 5.
Does this dacu ment or acivity ofliot withthe requirementssa the pant Tchnic Ifrbot 7
If any ofthe answers to Questions 2, 3,4 or 5 are YR*%, prepare a written a luation. Ifthtanswers to uestlons2 3,4, and 6 are No, this prec*ues%6 occurrence of the Uzreviewed Safety Question retcalSp
[on -*imnge and a writtan Safety Evaklation is NOT required. Provide wrtten statements which support t.e determinalqrfto unre ed Safety Question or Technical Specrfation change is involved. These written statements shall provide justification for th e
a tehets"iorons2-3,4rnd.
Specify the Licensing B.asis documnents and sections which were researched during this review. U? eparaEe sheets for dccumenttbig your statements and attach them to this f win. Provide page nurnben; (with this form identified as 7g 1f e
PRINT OR TYPE NAME AND SIGN:
Owner:
_j Responsible Technical Reviewer /
37
SAFETY DETERMINATION FOR PCR to 6610-PLN-4200.01 Page 2 of 2 Description of the Change This PCR is being submitted to perform the following:
"* Eliminate references to GPU Nuclear
"* Change the title of Director Operations and Maintenance to Plant Manager since the former position no longer exists.
Clarifies the TMI-2 effluent flow rate as a monitoring device, since this recorder sums the flows from individual measuring devices. It also clarifies the available compensatory action if this monitoring device is out of service.
Clarifies that releases from WECST tanks uses 20% of OD CM liquid concentration limits for tritium and 10% for other isotopes as an administrative means of ensuring compliance with ODCM Control 2.2.1.1. The limits specified in ODCM Control 2.2.1.1 are not affected.
- 2.
Does the document or activity change the design or description of the facility, even temporarily, from that which is contained in the SAR?
No. No changes are being made to the design or description of the fcilient and methods used to monitoring TMI-2 gaseous effluent flow rates are not d d
in Section 7.2.4.3 of the PDMS SAI.
"y
- 3.
Does the document or activity change a procedural or ohper.gjc oni, even temporarily, from that which is contained in the SAg?
tx Y
No. The equipment and methods used to monitoring TMI-2 gaseZ effluent flow rates are not described in Section 7.2.4.3 of the PDMS SAR. -
nistraive methods used to control liquid effluent concentrations at fractions less than limits are not described in Section 11.2 of the TME-1 UFSAR. Only the ODCM concentrationz" t of Control 2.2.1.1 are described, and those limits are not changing. Organiza~tiWe atownership changes being made are consistent with the UFSAR.
- 4.
Does the document or activity tvea tests or experiments that are not described in the SAR6 No special tests or expe, jts ar erformedc
- 5.
Does this docum*t or acV conflitt with the requirements of the plant Technical Specifications?
No. Effi t
ots are contained in the ODCM. No changes are being made to ODCM Control 2.2.,VIich implements the requirements of Technical Specification 6.8.4.b(2).
Safety Analysis Renort Document Sections Reviewed FSAR Section 11.2 Technical Specification 6.8.4 PDMS SAR Section 7.2 Signature B. A. Parfitt
.Date 12/26/2000
\\j
AmerGen TMI - Unit 1 Radioioolcal Controls Procedure Number 661 0-P LN-4200.0O1 Tilre ReviWon No.
Offsite Dose Calculation Manual (ODCM) 20 Appricabidty/Soope USAGE LEVEL Effaeeve Date TMI Division 3
NOV 8Y200 This document is within QA plan scope X
Yes No Safety Reviews Required X
Yes No List of Effective Pages Page Revision pace Revision PAge Revision Page Revsion 1
20 21 20 41 20 61 20 2
20 22 20 42 20 62 20 3
20 23 20 43 20 63 20 4
20 24 20 44 20 P
20 5
20 25 20 45 20 20 6
20 26 20 46 20 vi 20 7
20 27 20 47 20 4,
67 20 8
20 28 20 48 20 a
20 9
20 29 20 49 2.
9 20 10 20-30 20 50
,.70 20 11 20 31 20 51 20 71 20 12 20 32 20 52 72 20 13 20 33 20 53 2
73 20 14 20-34 20 54 2
74 20 15 20 35 20 5
20 75 20 16 20 36 20 6
20 76 20 17 20 37 20 20 77 20 Is 20 38 20 58 20 78 20 19 20 39 20 AN/
w" 20 79
.20 20 20 40 201D s'o60 20 80 20 Originator 0AB adIe Procedure Owner W0r B. A. Parf/03/00 PRG WI H. K. Olive for J. 5. Schork 10/10/00 Approver W J. Telfer oi0/10i0 1
TM]- Unit I 1 Number I
Radiological Controls Procedure 6610-PLN-4200.01 Tilie Revision No.
Offsite Dose Calculation Manual (ODCM) 20 INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the-ePUe-Three Mile Island Nuclear Station (TMING) Unit I and Unit 2 PDMS Technical Specifications and impleerients TMI radiological effluent controls. The ODCM contains the controls, bases, and surveillance requirements for liquid and gaseous radiological effluents. In addition, the ODCM describesthe methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents. This document also describes the methodology uised for calculation of the liquid and gaseous effluent monitoring instrumentation alarm/trip set points. Liquid and Gaseous Radwaste Treatment System configurations are also Included.
The ODCM also is used to define the requirements forthe TMIN&radioldgical environmental mpa~orng program (REMP) and contains a list and graphical description of the specific sample locations used in teRIP.
The ODCM is maintained at the Three Mile Island C"ML) site for use as a reference guidyCtNiiddocument of accepted.methodologies and calculations. Changes in the calculation methods or pa will be incorporated i to the ODCM to ensure the ODCM represents the present methodology In all appwoNle cru enges to the 00CM will be imptemented in accordance with the TMI-1 and TI 8e echnicai Specifications.
The ODOM follows the methodology and models suggested by NUREG-01*Ind R ilatory Guide 1.109, Revision I for calculation of off-site doses due to plant effluent releases. Simplj assumptions have been applied in this manual where applicable to provide a more workable document for imple pntation of the Radiological Effluent Controls requirements.
-GJUAN implements the TMI Radiologioal Effluent Controls Pro nd Regulatory Guide 1.21, Revision I (Annual Radioactive Effluent Release Report).requirements by use a courn rized system used to determine TMI effluent releases and to update cumulative effluent doses.
3
TMI-Unit I Number Radiological Controls Procedure 6610-PLN-4200.O1 Tile jRevision No.
Offsite Dose Calculation Manual (ODCM) 20 Table 2.1-1 Radioactive Liquid Effluent Instrumentation Minimum Channels Instrument Operable ACTION
- 1.
Gross Radioactivity Monitors Providing Automatic Termination of Release
- a.
unit I Liquid Radwaste Effluent 1
Line (RM-L5)
- b.
IWTS/IWFS Discharge Line (RM-L12) 20
- 2.
Flow Rate Measurement Devices C
- a.
Unit I Liquid Radwaste Effluent 21 Line (F'r84)
- b.
Station Effluent Discharge 1
21 (FT-1 46)
Table Nota on ACTION 18 With the number of channels OPERABI required by the Minimum Channels OPERABLE requirement effluent releases may ri ided that prior to initiating a release:
312
.1.1.1 a n d 3.2a l(
)e 1
At least two Indepen mp are analyzed in accordance with Surveillances 3.2.1.1.1 and 3..
,and;"
- 2.
At least two ically alifled members of the Unit staff independently verify the release rate a
ns and verify the dischare valve lineup.
TMI -shall approve each release.
t spend release of radioactive effluents via this pathway.
ACTION 20 With tha number of cannels OPERABLE lessthan required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may commence or continue provided that grab samples are collected and analyzed for gross radioactivity (beta orgamma) ata limit of detection of at least 1x1 0"7 microcunieslml. priorto initiating a release and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during release.
ACTION 21 With the number of channels OPERABLE Jess than required by the Minimum Channels OPERABLE requirement, radioactive effluent releases via this pathway may continue, provided the flow rate is estimated at least once per4 hours during actual releases. Pump curves, may be used to estimate flow.
22
Number TMI - Unit 1 Radiologqical Controls Procedure 661 0-PLN-4200.O1 Revision No.
Offsite Dose Calculation Manual (ODCM) 20 Table 2.1-2 Table Notation
- At all times.
During waste gas hotdup system operation.
Operability is not required when discharges are positively controlled through the closure of.
WDG-V47 and where RM-AB (or RM-A4 and RM-AG), FT-1 49, and FT-150 are operable.
Owuring Fuel Handling Building ESF Air Treatment System Operation.
- At all times during containment purging,
- At all times when condenser vacuum is established.
- During operation of the ventilation system.
ACTION 25 With the number of channels OPERABLE less than required bythe Minim (Zhanns OPERABLE requirement, the contents of the tank may be released to the environme p
at prior to initiating the release:
N?
"I.
At least two independent samples of the tank's conte al ed in accordance with Table S.2-2, hem A, and
- 2.
At least two technic-ally qualified members of the tin Independently verify the release rate calculations and verify the discharge valv neup.
- 3.
The a approve each release.
Otherwise, suspend release of rdjoactiv uent via this pathway.
ACTION 26 Wilh the number of channels OPERABLlfT required by the Minimum Channels OPERABLE requirement, effluent releases via t9bpmay continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, ACTION 27 With the number of channel 4
RABEE less than required by the Minimum Channels OPERABLE requirement, effluent relee via'Ijs pathway may continue provided grab samples are taken at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />snd*e in fial samples are analyzed for gross activity (gamma scan) within' 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the ctanba4 been declared Inoperable. If RM-A9 Is declared inoperable, see also Technical Specifl
[on 3.,
able 3-5.1, Item C.31.
ACTION 30
- 1.
W 4enuZ $r of channels OPERABLE less than required by the Minimum Channels P
.,requirement, a grab sample shall be collected and analyzed for the inera re gas channel(s) at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With both channels inoperable, a grab)W mple shall be collected and analyzed forthe inoperable gas channel(s):
(a) at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations.
(b) at least once. per24 hours during other operations (e.g. Feed and Bleed).
28
6610-PLN-4200.01 Revision 20 IN8 Table 2.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNELS TRUMENT
- OPERBL,
- 1.
Containment Purge Monetorin em
- a.
Noble Gas Activity *oq rk(2HR-225)
- b.
Particulate Monitor (2HP-
<5)
- c.
Effluent System Flow Rate Meo4 N
- 2, Station Ventilation System 0
- a.
Noble Gas Activity Monitor (2HP-R-219) or
- b.
Partibulate Monitor (2HP-R-219) or (2HP-R-21
- c.
Effluent System Flow Rate Measuring Device r01 4.A&%
1 b-ý
{2AH-FR-5907 Pen 1) 16)
- 1 1
1 I
kPPLICABILLTY NOTE I NOTE I NOTE I NOTE 1 NOTE I NOTE 1 t.-
During operation of the monitored system.
- 2.
With the number of channels OPERABLE less than required by the Minimum Cle progress.
- 3.
WRh flow rate monitoring instrumentation out of service, flow rates from the Auxiliary, maximum design flow for the exhaust fans in operation.
BLE requirement, secure Reactor'Building Purge If In 4n and Reactor Buildings may beA'stimatad using the 0.
67 NOTES:
ACTION NOTE 2 NOTE 2 NOTE 3 NOTE 2 NOTE 2 NOTE 3
TMI - Unit I Title%1%
Revfsion No.
Offsite Dose Calculation Manual LODCM) 2 Number
.9 I Un T1 KEA
.UA 1.2 TMI Liquid Effluent Release Points and Liquid Radiatlor Monitor Data TMI-1 has two required liquid radiation monitors. These are RM-L6 and RM-L12. These liquid release point radiation monitors and sample points are shown in Table 1.1. (The TMI outfall radiation monitor, RM-L7, Is also listed for information only.)
TMI-2 does not have. any required liquid radiation monitors, but does utilize RM-L12, and RM-L7 for release of liquid waste.
1.2.1 EML§ RM-L6 Is an off-line system, monitoring radioactive batch discharges radwaste system (see Figure 1.1). These batch releases are sami site procedures prior to release. The release rate is based on r TesI Evaporator Condensate Storage Tanks (WCOST) at a flow wf'*&wft often times the 10 CFR 20 ncentralions o radionuolide c trat unrestricted are including conservative default values Sr (Z&% for t4-3)
The release flow rate used is the most restrictive of trP tes t liquid batch release, per the approved plant procqpjure.
from the TMI-i liquid g'w14d analyzed per ng Dje of two Waste
- 0iess than 10%,
ions In the 90, and Fe-55.
alculated for each Three Dilution Factors (DF) are 4qalculated to ultimate, aculate the batch release flow rate. These three DFs are calculated to: 1) insure each radlonuclide released to the nrestdce ara Is less than loper of ten times the I0CFR20 radionuclide
'cancentrations 2) ensure each liqW' ch release boron concentration to the river will not exceed 0.7ppm, and 3), ensure ten the IOCFR20 concentration for Cesium-1 37 (IE-5 p.CVml) will not be exce e)ased *n the calculated high alarm set point and the expected response of RM-L t*
tcenaton of Cs-137.
The naxlmum re[a s flw rat ijs n calculated bytdviding 1he most restrictive (largest)
OF into 90 percent
- dilution flow rate of the Mechanical Draft Cooling Tower (MDCT). This co ie ow rate Is then multiplied by 0.9 for the allowable flow rate.
" Cal
[at*ofthe IOCFR20 concentration DF:
C~o¶rv 5-r I4-33
/
(11
%kf ten times the IOCFR20 concentration)
, SA Spacific Activity of each identified radionuclide "N,* 'Calculation of Boron DF:
DF2 = Actual Tank Boron Concentration + 0.7.
Calculation of Cs-437 Limit; DF2 = High Alarm Set Point- (I.E-5
.CXimi
- I.O518 cpm per ICi/ml)
Maximum release flow rate calculation:
Max Flow = [(MDCT flow gpm
- 0.9) ÷ (Most Restrictive DF)]
- 0.9 9o (z
-3,F 0
Number TMI - Unit 1 Radioilogical Controls Procedure 6610-PLN-4200.0i Te Revfslon No.
Qffsite Dose Calculation Manual (0DCM) 20 The dilution flow rate used is the current flow rate at the site. The minimum dilution flow rate is 6000 gpm per the TMI-1 FSAR. This ensures this batch release will meet the following equation.
where:
Cl= diluted concentration of the i" radionuclide,,.taar 4t,4n 14-3 A=
Ten times the concentration for that radionuclide In the unrestricted area (10 CFR 20, App. B, Table 2, Co]. 2). A value of 3E-3 gCVml for C,. LA= e,\\.)*
on f 14 -3
-'--...31 dissolved and entrained noble gases shall be used.
Te,. j 1me 4_-
- The set poInts for RM-LS are set for each release based on the m 1ITPN'esponse to each cmna~caion
~..~
radionuclidle identified In the gamma scan sample results as; (iocn
, Ap...Tal.
6 t_ Zl -ot -Z).
10
(
1V (v "
i f cU)C (CPM11zCifcc)ci + (CPMWM),l yRT CPM (2,.0)' [_,i (zCllcc)j (OP Mf.Citcc)d] + (CPj* i*
ALARM CPM where:
O(iCco)1 =
positively identified 4ytucTh*s (CPM(ICi/cc), = RM-L6 senstivity to mdicudide I.
(CPMsm) -
RM-LS baground prior to batch release A high alarm on RM-LS will close valve v
W V-257 and terminate any WECST releases to the environment, 1.2.2 RM--12 RM-L12 is an off-i Me/,
onitoring periodic combined releases from the Industrial Waste Treatmen tPqem/l~nstria] Waste Filtration System (IWTSIWFS). The input to IWTS/IWFS on mes MI-2 sumps, (see Figures 1.1 and 1,2) and the TMI-1 Turbine Building sur Fige 1.1). The set points are based on the maximum release rate from both 1.an* IWFS simultaneously, (see Figure 1.1) a minimum dilution flow rate, arid of ten4 the 10CFR20 cbncentration for Cs-137, which is the most limiting radio ucke at a concentration of 1 E-5 iCi/ml. These inputs are used In equation 1,1 to de*,,nine M
L12 High Alarm set poaint for all radienucdides being released. A high r9taip RM-Ll2 will dose IWTS and I.WFS release valves and trip release pumps to t
lease.
1-2,3 RM-LIO RM-10 was a Nal detector submerged in the TMI-1 Turbine Building Sump. This detector has been removed from service.
1.2.4
~L RM-L7 is not an ODCM required liquid radiation monitor. RM-L7 Is an oft-line system, monitoring the TMINS-outfall to the Susquehanna River (see Figures 1.1 and 1-2). This monitor is the final radiation monitorfor TMI-1 and TMI-2 normal liquid effluent releases, 91
TMI - Unit I Numtber Radiological Controls Procedure 6610-PLN.4200.01 Thfre RevisCona No.
Offsite Dose Calculation Manual (ODCM) 20 13 Control of Liquid Releases TMI liquid effluen releases are controlled to less than ten times the IOCFR20 concentrations by limiting the percentage of this limit allowable from the two TMI liquid release points. RM-L6, and effluent sampling, limits batch releasesto less than or equal to 10% for all radlonuclide.
and RM-L12, and effluent sampling, Olmits releases from TMI-i and TMI-2 to less than or eqal to 50%
for Cs-137.
J These radiation monitor set points also include built in meter error factors to further ensure that TMI liquid effluent releases are less than ten times the 10CFR20 concentrations to the environment.
The radioactivity content of each batch of radioactive liquid waste is determinedgior to release by sampling and analysis in accordance with ODCM Part ! Table 3.2-1 or ODC a
, Table 3.2-1.
The results of analyses are used with the calculafionaf methods in Section 1. to as ure that the concentration at the point of release is maintained within the ODCM Pa9
- on-t-
.1.., and ODCM Part 11 Control 2.2.1.1-
'N Post-release analysis of samples composited from bAtch releas rf ed in accordance with ODCM Part I Table 3-2-1 or ODCM Part II Table 3,2-1. The rsut f
previous post-release analysis shall be used with the calculational methods in th§4QCM t ssure that the concentrations at the point of release were maintained within the ODCM Part No trol 2.2.11, and ODCM Part I1 Contrpl 2.2.1.1.
7" The radioactivity concentration of liquids diseharg*i from continuous release points are determined by collection and analysis of samples in acc6ton with ODCM Part I Table 3.2-1, or ODCM Part II Table 3.2-4. The results of the analysis arn".sed. wivJhe calculational methods of the ODCM to assure that the concentration at the poinf ease f maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part II Cont I.
92
TdIle Offsate Dose Calculation Manual (O Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-420D.01 RoevsIon No.
DCM) 20 2.3 Alternative Liquid Dose Calculational Methodology As an alternative, models in, or based upon, those presented In Regulatory Guide 1.109 (Rev. 1) may be used to make a comprehensive dose assessment. Default parameter values from Reg.
Guide 1.109 (Rev. 1) and/or actual site specific data are used where applicable.
As an alternative dose calculational methodology 4a.tf*a calculates doses using SEEDS (simplified environmental effluent dosimetry system).
The onsite and SEEDS calculational models use actual liquid release data with actual monthly Susquehanna River flow data to assess the dispersion of effluents in the river.
AAX 99 i
%*SY41
TMI-Unit I Number I
Radiological Controls Procedure 6610-PLN-4200,01 Tille Revision No.
Offsite Dose Calculation Manual (ODCM) 20 5.4 Alternative Dose Calculational Methodologies for Gaseous Effluents As an altemative to the methods described above, the mode]s inior based upon, those presented in Regulatory Guide 1.109 (Rev. 1) may be used to make a comprehensive dose assessment. Default parameter values from Regulatory Guide 1,109 (Rev. 1) andfor actual site specific data can be used where applicable The onsite, on-line computerized system for tracking gaseous effluent dose uses annual average gaseous dispersion factors. As an alternative dose calculattonal methodology. GPý-nt r UT1M1 calculates doses using an advanced class "N' dispersion model called SEEDS (simplified environmental effluent dosimetry system).
This model incorporates the guidelines and methodology set forth in USNRC tory Guide 1.109, and uses actual hourly meteorological InformAtion matclied ot time f releases to more accurately assess the dispersion of effluents in the atmosphere. CSi*
assessment of dispersion with TMINSeffluent data for each unit, postulated maximnu Ikpothetical doses to the public are calculated.
A;\\
TMI WORD PROCESSING FORM 1001A tpD D
TV Revision 45 FIGURE r j.1 Page-1 of 1 DUE DATE:
'/-c
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- Reference Number:
cQ8IbS Procedure Number:
.vipt-PLtJ-Wix:-.cI Revision Number:
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To Word Processing:-
Z/ !
DjL Special Handling:
PROOFREAD SECTION:
Document Converted YES or IF DOCUMENT WAS CONVERTED YOU WILL NEED TO REVIEW THE ENTIRE PROCEDURE VERY CAREFULLY!!!
I.
Proofreader: *-'0t*-.
r Corr ections/Changes Y or NO Make corrections IN RED I K.
By:
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'96
- 2.
]
- 4.
- 5.
- 6.
7.
32.
TMI -Unit 1 Radiological Controls Procedure Number Title Revision No.
Offsite Dose Calculation Manual (ODCM) 21 TABLE OF CONTENTS TMI-1 RADIOLOGICAL EFFLUENT CONTROLS 1.0 DEFINITIONS Table 1-1, Frequency Notation/
2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation 2.1.2 Radioactive Gaseous Process and Effluent Monitori lInsm*
t tion Table 2.1-1, Radioactive Liquid Effluent Instrumentation "able 2.1-2, Radioactive Gaseous Process and Effluent Monit ngInstrumentation 2.2 Radiological Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.2 Gaseous Effluent Controls 2.2.3 Total Radioactive E~fflnConi Is 3.0 SURVEILLANCES T
C 3.1 Radioactive Effluent Ins etion 3.1.1 Radioa LiquiEffluent Instrumentation 3.1.2 i*
've aseous Process and Effluent Monitoring Instrumentation Table 3.1-1, Ra ractive Liquid Effluent Monitoring Instrumentation Surveillance Requirements "Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation
-Surveillance Requirements 3.2 Radiological Effluents 3.2.1 Liquid Effluents 3.2.2 Gaseous Effluents PART I Section Pa*e
~-933 Ae3?
X*5 53
-4*91 SAr:4 /
6610-PLN-4200.01 4
"s.
TMI - Unit I Radiological Controls Procedure Number Title Revision No.
Offsite Dose Calculation Manual (ODCM) 21 TABLE OF CONTENTS (Cont'd)
PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS Section Pap~e Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 3.2.3 Total Radioactive Effluents 4.0 PARTI REFERENCES 4;
6610-PLN-4200.01
TMI - Unit I I
-!Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 21 6
TABLE OF CONTENTS (Cont'd)
PART II TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section Page 1.0 DEFINITIONS
>S Table 1.1, Frequency Notation 6
-l/
2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES
'0 2.1 Radioactive Effluent Instrumentation
(,"5) 2.1.1 Radioactive Liquid Effluent Instrumentation 2.1.2 Radioactive Gaseous Process and Effluent Monitorin m tation 9
Table 2.1.2, Radioactive Gaseous Process and Effluent Mitrin strumentation
,&:7 2.2 Radioactive Effluent Controls">9 2.2.1 Liquid Effluent Controls f, & ?
2.2.2 Gaseous Effluent Controls X
2.2.3 Total Radioactive Effluen*t s
7(7 3.0 SURVEILLANCES X)'
3.1 Radioactive Effluent Instru Ita-7 3.1.1 Radioactive L uent Instrumentation 7
]
7 3.1.2 Gaseous Process and Effluents Monitoring Instrumentation 7?,
Table 3.1-2 d ctio e Gaseous Process and Effluent Monitoring Instrumentation
' 7 9 re ance Requirements 3.2 Radiological Effluents 3.2.1 Liquid Effluents 3.2.2 Gaseous Effluents Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program,"
3.2.3 Total Radioactive Effluents
<V TMI - Unit 1 Number Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 21 TABLE OF CONTENTS (Cont'd)
TMI-2 RADIOLOGICAL EFFLUENT CONTROLS SPa*e*
PART 11 REFERENCES 0
A-7 PART I1 Section 4.0
TMI - Unit I Radiological Controls Procedure Number Title Revision No.
Offsrte Dose Calculation Manual (ODCM)
.21 TABLE OF CONTENTS (Cont'd)
EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENT MONITORS 1.1 TMI-1 and TMI-2 Liquid Radiation Monitor Set Points 1.2 TMI Liquid Release Points and Liquid Radiation Monitor Data 1,3 Control of Liquid Releases
(
2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liquid Effluents - 10 CFR 50 Appendix I 2.2 TMI Liquid Radwaste System Dose Calcs Once per Mont 2.3 Alternative Dose Calculational Methodology 3.0 LIQUID EFFLUENT WASTE TREATMENT SYSTEM 3.1 TMI-1 Liquid Effluent Waste Treatment S 3.2 Operability of TMI-1 Liquid Effluent eatnent System 3.3 TMI-2 Liquid Effluent Waste Tretnt S tern 4.0 GASEOUS EFFLUENT MONITOR 4.1 TMI-1 Noble Gas Monitc tloints 4.2 TMI-1 Particulate n adio odine Monitor Set Points 4.3 TMI-2 Gas s
diji on Monitor Set Points 4.4 TMI-1 Gaseous iuent Release Points and Gaseous Radiation Monitor Data 4.5 TMI-2 Gaseous Effluent ReLease Points and Gaseous Radiation Monitor Data 4.6 Control of Gaseous Effluent Releases I)
PART III Section 6610-PLN-4200.01 Page 1q1 108
- '5 0ii
ý0610 10 /015 W(i6
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Tite Revision No.
Offsite Dose Calculation Manual (ODCM) 21 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents - DQsZ Roto Limitc 5.1.1 Noble Gases 5.1.1.1 Total Body 5.1.1.2 Skin 5.1.2 Iodintes and Particulates 5.2 Gaseous Effluents - 10 CFR 50 Appendix 5
5.2.1 Noble Gases 5.2.2 lodines and Particulates 5.3 Gaseous Radioactive System Dose Calcu ns 0 per Month 5.4 Alternative Dose Calculational MethyoQ los 6.0 GASEOUS EFFLUENT WASTE TREA STEM 6.1 Description of the TMI-1 Gas u
dwaste Treatment System 6.2
- Operability of the TMI-1 s Radwaste Treatment System 7.0 EFFLUENT TOTAL DOS SESENT 8.0 TMINS RADIOLO A
VONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitoring Prog m Requirements 8.2 Land Use Census 8.3 Interlaboratory Comparison Program 9.0 PART ]Il REFERENCES PART III Section Pa-7 13 0 06C r5-9
)ýe jIg9
,j 1('
- 94 ((Vq TABLE OF CONTENTS (Cont'd)
EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES 9
TMI - Unit I Radiological Controls Procedure Number 6610-PLN-4200.01 TABLE OF CONTENTS (Cont'd)
EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Page PART III Section TABLES Table 1.1 Table 1.2 Table 2.1 Table 2.2 Table 4.1 Table 4.2 Table 4.3 Table 4.4 Table 4.5 Table 4.6 Table 5.2.1 Table 5.2.2 Table 5.2.3 Table 5.2.4 Table 5.3.1 Table 5.4.1 Table 5.4.2 Table 5.4.3 Table 5.4.4 Table 5.5.1 10 Tise Revision No.
Offsite Dose Calculation Manual (ODCM) 121 TMI-1 Liquid Release Point and Liquid Radiation Monitor Data TMI-2 Sump Capacities Liquid Dose Conversion Factors (DCF): DF1j Bioaccumulation Factors, BF, TMI-1 Gaseous Release Point & Gaseous Radiation MonitorD TMI-2 Gaseous Release Point & Gaseous Radiation Mon Data Dose Factors for Noble Gases and Daughters Atmospheric Dispersion Factors for Three Mile Ilnd - Station Vent Atmospheric Dispersion Factors for Three e Is Ground Release Dose Parameters for Radioiodines a R
oactive Particulate~aseous/6fuents Pathway Dose Factors, Ri - Inj
, *a n
Pathway Dose Factors, Ri -
n alation Pathway Dose Factors, n, Inhalation Pathway DoeF ct
,R Adult, Inhalation Pathway D or R-R,-
All Age Groups, Ground Plane Pathway Dose ctors, Rj - Infant, Grass-Cow-Milk Pathway Dose Factors, Ri - Child, Grass-Cow-Milk Pathway Dose Factors, R - Teen, Grass-Cow-Milk Pathway Dose Factors, R1 -Adult, Grass-Cow-Milk Pathway Dose Factors, Rj - Infant, Grass-Goat-Milk 10r1 100 3 17 12(5 lfI Nq0 le( lq W i'q3
Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Ttle Revision No.
Offsite Dose Calculation Manual (ODCM) 21 TABLE OF CONTENTS (Cont'd).
EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Pag*
PART IlI Section TABLES Table 5.5.2 Table 5.5.3 Table 5.5.4 Table 5.6.1 Table 5.6.2 Table 5.6.3 Table 5.6.4 Table 5.7.1 Table 5.7.2 Table 5.7.3 Table 5.7.4 Table 8.1 Table 8.2 Table 8.3 Table 8.4 Table 8.5 Table 8.6 Table 8.7 Table 8.8 Table 8.9 Table 8.10 6
!f
- /Tq 1~7Y
_t-6' (7 Pathway Dose Factors, Ri - Child, Grass-Goat-Milk Pathway Dose Factors, Ri - Teen, Grass-Goat-Milk Pathway Dose Factors, R1 -Adult, Grass-Goat-Milk
(
Pathway Dose Factors, Ri - Infant, Grass-Cow-Meat Pathway Dose Factors, R, - Child, Grass-Cow-Meat Pathway Dose Factors, R, - Teen, Grass-Cow-Meat Pathway Dose Factors, R, - Adult, Grass-Cow-Meat Pathway Dose Factors, R, - Infant, Vegetation Pathway Dose Factors, R, - Child, Ve eta Pathway Dose Factors, R, - Teen, 'V
\\
Pathway Dose Factors, Ri-Ad* t geton Sample Collection and An y*s irements Reporting Levels for Ra ity Concentrations in Environmental Samples Detection. CapaE Environmental Sample Analysis TMINS RE &ocations
- Air Particulate and Air Iodine TMINS REMP ltion Locations - Direct Radiation (TLD)
TMINS REMP Station Locations - Surface Water TMINS REMP Station Locations - Aquatic Sediment TMINS REMP Station Locations - Milk TMINS REMP Station Locations - Fish TMINS REMP Station Locations - Food Products ill
TMI - Unit 1 Radiological Controls Procedure Number I
661 O-PLN-4200.01 "Tte Revision No.
Offsite Dose Calculation Manual (ODCM) 21 TABLE OF CONTENTS (Cont'd)
EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Page-PART III Section TABLES MAP 8.1 MAP 8.2 MAP 8.3 FIGURES Figure 1.1 Figure 1.2 Figure 3.1 Figure 3.2 Figure 4.1 Figure 4.2 Figure 4.3 Figure 4.4 Figure 4.5 Figure 6.1 f )-7 LU Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within I Mile of the Site Three Mile lsland Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 5 miles of the Site Three Mile Island Nuclear Station Locations of Radiological Environm"',
\\l Monitoring Program Stations Greater than 5 miles from the Site TMI-1 Liquid Effluent Pathways TMI-2 Liquid Effluent Pathways T M J-1 Liq u id R a dw a ste AA TMI-1 Liquid Waste Evaporators TMI-1 Gaseous Effluent Pathways TMI-1 Auxiliary & Fuel Handli nu Effluent Pathways TMI-1 Reactor Building Eff(
t 9 ay TM1-1 Condenser Offga, u nt Pathway TMI-2 Gaseous
ýt Filtration System/Pathways Waste Gasv A.n e*' 10(0
- 12; ir 0-7
)~i, &(
Number TMI - Unit I Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 21 TABLE OF CONTENTS (Cont'd)
PART IV REPORTING REQUIREMENTS Section Pacqe 1.0' TM! ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT W i,?
2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Ik 3 3.0 PART IV REFERENCES 5
APPENDICES.
A.
Pathway Dose Rate Parameter (P1)
B.
Inhalation Pathway Dose Factor (RI)
/"-7 C.
Ground Plane Pathway Dose Factor (R1) 11,
"D.
Grass-Cow-Milk Pathway Dose Factor (R1)
E.
Cow-Meat Pathway Dose Factor (Ri) 1/9/
F.
Vegetation Pathway Dose Factor (Re)
/ q0?
APPENDIX A-F REFERENCES 1973 4>,
13
Number TMI - Unit 1 Radiological Controls Procedure 661 O-PLN-4200.0t Title Revi~sion No.
Offsite Dose Calculation Manual (ODCM) 21 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation SURVEILLANCE RjQIREMENTS
-.~
-ffi,nt m nitnrinn-iqstrumentation ce of the CHANNEL nd CHANNEL Or cm.0ýOýv_.N %\\I.4 44
TMI - Unit 1 Number Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 21 49 3.2
-,e
,ieW Effluents t,
,.S EQUIREMENTS tration 1
The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and ana]ysis in accordance with Table 3.2-1. The results of pre-release analyses shall be used with the calculational met
- n the ODCM to assure that the concentration at the poi t of r ease is maintained within the limits of Control 2.2.1.1.I i,,*
3.2.1.1.2 Post-release analysis of samp4 co sited from batch releases shall be performed in acco iltfable 3.2-1. The results of the previous post-relea, an sis-'
all be used with the calculational methods~ e 0 to assure that the concentrations at the poinclease were maintained within the limits of Control 2.2.1.1.
l 3.2.1.1.3 The radioa tiry concentration of liquids discharged from continuou "3asj points shall be determined by collection and analy96"N samp s in accordance with Table 3.2-1. The results of th shall be used with the calculational methods of the 9@A %&ssure that the concentration at the point of release is ine'dd within the limits of Control 2.2.1.1.
3.2.1.2 Dose ulations
.1 "Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month.
lat 3X
/
Xquid Waste Treatment 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM.
3.2.1.4 Liquid Holdup Tanks 3.2.1.4.1 The quantity of radioactive material contained in each of the tanks specified in Control 2.2.1.4 shall be determined to be within the limit by analyzing a representative sample of the tank's content weekly when radioactive materials are being added to the tank.
TMI - Unit I Number Radiological Controls Procedure 6610-PLN-4200.0I Title Revision No.
Offsite Dose Calculation Manual (ODCM) 21 APPENDIX D RI - Grass Cow-Milk Pathway Dose Factor k' [(QF X UAp) / (14
+ )j x (Fm) x (r) x (DFLI,,) x
[((fp x f.)/Y,) + ((4-f. x f,) e "Xith)iY.] e'itf (Eq D-1)
Where:
k'= conversion factor, I E6 picocurielmicrocurie (pCi/pci)
QF= cow consumption rate, 50 kg/day, (Reg. Guide 1.109, Rev. 1) goat consumption rate, 6 kg/day, (Reg. Guide 1.109, Rev. 1, Table E-2)
UAp = Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for ir f ild, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev. 1)
Yp = agricultural.productivity by unit area of pasture feed grass,7 k9
,JREG-0133)
Y= agricultural productivity by unit area of stored feed, 2.0 kg/m2 REG-01 33)
F, = stable element transfer coefficient (Table E-1, R*. Guide 1.109, Rev. 1) r= fraction of deposited activity retained in cow's r~ss, 0.2 for particulates, 1.0 for radioiodine (Table E-15, Reg. Guide 1.109, Rev. 1) 7 DFLIao =the ingestion dose factor for organ, rM th radionuclide for each respective age group, a (Tables E-1 Ito E-14, Reg-Guid
, e.. 1), or NUREG 0172, X=
decay constant for the ith ra clide, sed" S= decay constant for weat eri 5.-x 10-7 sec-1 (NUREG-0133); based on a 14 day half life tf = 1.73 x l05 sec, th nspo me from pasture to cow to milk to receptor (Table E-1 5, Reg.
Guide 1.109, v.1,1days th = 7.78 x 106 se e
nsport time from pasture to harvest to cow to milk to receptor (Table E-1 5, Reg. Guide 1.1 ev. 1), or 90 days fp =
1.0, the fraction of the year that the cow is on pasture f, =
1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture 189
TMI - Unit 1 Number Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 21 APPENDIX D The concentration of tritium in milk is based on the airbi~me concentration rather than the deposition. Therefore, Rj is based on (X/Q):
R,,k'k Fm QF UAPDFLta,o (.75 [.51Hj)
(Eq D-2)
Where:
k'= I E3 grams/kg H = 8 grams/rn3, absolute humidity of the atmosphere
.75 = fraction of the total feed grass mass that is water
.5 = ratio of the specific activity of the feed grass water to the atmosp c w (NUREG-0133)
DFLt,,o = the ingestion dose factor for tritium and organ, o, for each r pe ve e group, a (Tables E-1 1 to E-14, Reg. Guide 1.109, Rev. 1), or NUREG 0172.
All other parameters and values are as given above.
hNOTE*.
Goat-milk pathway factor, Ri, will be pute sing the cow-milk pIathway factor equation. Fm facto r
ilk will be from Table E-2 Reg. Guide 1.109, Rev. 1.
Reference:
0DCM Part III Tables 5.4.1 to 5.4.4,9 190
- ANY,
TMI - Unit 1 Number Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 21 PART I Section TABLE OF CONTENTS TMI-1 RADIOLOGICAL EFFLUENT CONTROLS 1.0 DEFINITIONS Table 1-1, Frequency Notation 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation Table 2.1-1, Radioactive Liquid Effluent Instrumentation
'0 2.1.2 Radioactive Gaseous Process and Effluent Mo~94,ig numentation Table 2.1-2, Radioactive Gaseous Process and Effluent MoniXg Instrumentation 2.2 Radiological Effluent Controls AA 2.2.1 Liquid Effluent Controls 2.2.2 Gaseous Effluent Control 2.2.3 Total Radioactive E n
nDon'ls 3.0 SURVEILLANCES 3.1 Radioactive Effluent Ins en tion 3.1.1 Radioac'ti icid Effluent Instrumentation Table 3.1-1, 8 tive Liquid Effluent Monitoring Instrumentation etirance Requirements 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring, Instrumentation Surveillance Requirements 3.2 Radiological Effluents 3.2.1 Liquid Effluents 3.2.2 Gaseous Effluents Paqe 15 19 21 21 21 22 23 24 30 30 33 39 41 41 41 42 44 45 49 49 50 53 4
I.
KO 11) vi
ýr
TMI - Unit 1 Number Radiological Controls Procedure 661 O-PLN-4200.01 Thie Revision No Offsite Dose Calculation Manual (ODCM) 21 TABLE OF CONTENTS (Cont'd)
PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS Section Pame Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 50 Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 55 3.2.3 Total Radioactive Effluents 4.0 PART I REFERENCES 0
59 60 5
A-IN I x A
2001 Annual Radioactive Effluent Releases Report for TMI 5928-02-20095 Procedure Change Request PCR-00-3246 to the ODCM, 6610-PLN-4200.01
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- 1. Procedtirwetanord No: 4WO -FLA-A ZOO CurrentRwWorr (Not reVfad forTM Tiae:
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OTISIAL-DIM&
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-44A AfPtIdAj&u" LWMSTASLE S-Z-7, 2-Recommended Change.
As IIJIPICATrizo O&J A*TM",ejý.
MARXtb UP copy I
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- 8. CAMWAVON CAM 1T
EXHIBIT S Reference Numbera
__f___
e_
tn__regee SafetY DeterMinatlonI60.5S Screening~ Review 1000-AD M-1291.01 Revision 26 Page i of i Diviion R-.N.(4l J'4 o o
- a.
No.
SE io No.
Z Rev. No.
010 C M Yes No i s this a. newdocument or activity or a substantive revision to an existing document?
[
[
]
(A new document Is Considered equivalent to a substantive revision.) If YES, proceed to answer Question 2.
If NO, then procedure 1000-ADM-l291.01 is not applicable and documentation of nuclearsafety dMterminatlaon is not required.
- 2.
Does the document or activity change the design ordescription of the facility, even temporarily, from that *thich is contained in the SARI ?
- 3.
Does the document or activity change a procedural or operating description, even temporarily, fro h
LF which is contained In 1te SAR?
- 4.
Doesthe document or activity Involve any tests or expeAments that are not descibe"d in
- 5.
Does thisdocumnent or gotivity~connifct Wt the requireme~nts of the plant Technic' foton f arny of the answers to Questios 2,3, 4 or 5 are YES, prepte a. wiMen saf*
.lon. If the answers to Quest.ons 2, 3,4, and 5 are NO, his.precludes the occuwrenc oethe Unreviewed Safety Question or Tecth m Speci on change and a written Safety Evaluation Is NOT requ-red. Provide written statements which supportthe determinafon t no nrleyled Safety Question orTechnIcal Specincation change Is involved. These m ritten statements shall providedjutloation fort*f N Questlonsr dou4and S. Specify the Licentsing Basis.
documents and sections which were researched during lhis r!ýev p"ie o let sheets for documenting your statemrentz and attach them to this forn. Provide Page numbers (withi this form identife as T
PRINT OR TYPE NAME AND SIGN:~t
~
DATE
~.f 37 Owe
.>\\_.
aye 7 -
~AGOW018 1-30-200
SAFETY'DETERMINATION FOR PCR to 6610-PLN-4200.01 Page 2 of 2 Description of the Change This PCR is being submitted to eliminate the need to change the alarm setpoint for RM-L-6 each time a Waste Evaporator Condensate Storage Tank (WECST) is released. The change does not affect the type or quantity of radiological effluents released from the plant The calculation of an individual alarm set point and the installation of the set point on the monitor, for each WECST release is not necessary to ensure that effluent releases via this pathway are maintained with the limits of ODCM Control 2.2. 1. 1. A fixed alarm setpoint corresponding to 25% of the limit using the maximum possible release rate and the minimum allowable dilution flow will provide assurance that ODCMrelease rates will not be exceeded.
The use of a fixed setpoint for RM-L-6 will limit release rates via this pathway to 25% of the ODCM limit. The use of the existing RM-L-l2 setpoint will continue to limit release rates via that pathway to 50% of the ODCM limit These setpoints will continue tb ensure that the total releases from the two TMI liquid release points do not exceed the QDCM limit In addition, calculational methodologies for establishing allowable release rates based on dilution flow are not being changed. As a result, actual releases from WECSTs willicontinue to be controlled at 10% of the concentrations allowed by the ODCM for all isotopes other than tritium. Tritium will continue to be controlled at 20% of th CM limit.
- 2.
Does the document or activity change the design or description of the eve tem p orarily, from that w hich is contained in the SA R ??
I a, 2 v
No. No changes are being made to the design or descripto Of ty s procedure describes the calculational methodologies to ensure release raesfn-Tflliquid radwaste system are within ODCM limits.
A\\Y
- 3.
Does the document or activity change a procedural or operatŽ description, even temporarily, from that which is contained in the SAR?
No, The change does not conflict with the de nI f effluent monitoring in Sections 11.2. 1, 11.4.4, 1.4.17, 14.70, and 11.5.8.1 of thtl
-1 ErR or Sections 2-4 and 7.2.4.of the PDMS SAR. Section 11.2.1.3 of the TME-l FSthat "Set points on the flow and activity monitors (providing direct surveill*
,*Že discharge of a batch) are set accordingly before initiating the discharge". ThMs rewiuremi t will be maintained using a fixed setpoint for RM-L
- 6.
- 4.
Does the document or i
e any tests or experiments that are not described in the SAR??
No special t o
nts are performed.
- 5.
Does
?h, activity conflict with the requirements of the plant Technical Specificati
?
No. The change does not conflict with Technical Specification 6.S.4.b(2) and continues to provide a methodology for compliance with this limit.
Safety Analysis ReDort Document Sections Reviewed FSAR Chapters 1 and 11 Technical Specification Section 6 PDMS SAR Sections 2 and 7 Signature B. A. Parfitt D
nate 3/6/.O01
1001A FIGURE 7 Page 1 of I Change Management Process for Implementation of New Procedures, Temporary Procedures and Procedure Changes Procedure Review Form Number:
Procedure Number: 6610-ADM-4200.01 List below or on an attached sheet all new procedures, temporary procedures and/or procedure changes that are to be implemented concurrent with the document listed above (indicate none if none):
1101-2.1 1104-29S 1430-RMS-1 4 6610-ADM-4200.01 6610-ADM-4250.01 661 0-AD M-4250.11 6610-ADM-4250.12 661 0-ADM-4250.07 66I 0-ADM-4250.09 661 0-ADM-4250.05 In addition, the new LAGER effluent software muj implemented concurrent with these procedures. Contact Brad Parfitt X8090 prio t imp enting these procedures.
List below or on an attached sheet all
,ernt positionings/repositionings that are required to be coordinated with the i pie ation of the document listed above (indicate none if none):
None List below or on an *t edsheet all instrument re-calibrations andlor valve system lineup performances pe ormances that are required to be coordinated with the implementation of the alcument listed above (indicate none if none):
None AGOS13 (03113/01)
AmerGen TIUi Aitle r
en Radiolo ictrs Procedure Offsite Dose Calculation Manual (ODCM)
ApplicabiltylScape USAGE LEVEL TM[ Division 3
This document is within QA plan scope X
Yes No "X Yes No List of Effective Pages Revision 1
2 3
4 5
6 7
.8 10 11 12 13 14 15 16
- 17.
18 19 20 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 Page 21 22 23 24 25 26 27 28 "29 30 31 32 33
~34 35 36 37 38 39 40 Revision 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21t Revision 41 42 43 44 45 46 47 48 49 50
$1 52 53
$4 21 21 21 21 21 21 21 21
'69 21 70 21ý 71 72 73 21 74 21 75 21 76 21 77 21 78 21 79 21 80 "Number 6610-PLN-4200.o0 Revision No.
21 Effective Date 01119101 S~Revision 61 62 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 1
Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01
,-tie Revision No.
Off-ite Dose Calculation Manual (ODCM) 21 Table 3.1-1 Table Notation.
(1)
The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs.if the following condition exists:
- 1.
Instrument indicates measured [evels above the high alarm/trip setpoint. (Includes - circuit failure)
- 2.
Instrument indicates a down scale failure. (Alarm function only.) (Includes - circuit failure)
- 3.
Instrument controls moved from the operate mode (Alarm function only...
Td (2)
The initial CHANNEL CALIBRATION for radioactivity saueetnsrmn.
hall e performed using one or more of the reference standards certified by the sing standards that have been obtained from suppliers that participated in measurement assup tivities with M3BS..ese standards should permit calibrating the system over its intended range o.
r measurement range..
For subsequent CHANNEL CALIBRATION, sources that have been ree initial calibration should be used. (Operating plants may substitute previously established libra
- n procedures for this requirement)
(3)
CHANNEL CHECK shall consist of verifying indication of flow dunng riods of release. CHANNEL CHECK shall be made at least once daily on any day on which tinuous, periodic, or batch releases are made.
43
Mle Offsite Dose Calculation TMI - Unit I Radiolooical Controls Procedure Manual (ODCM)
Number Radilooia Cntros Prcedue 61 0-P LN-4AA>
n-i RevIsion NO.
Table 3.1-2 Table Notation At all times.
During waste gas holdup system operation.
Operability is not required when discharges are positively controlled through the closure of WDG-V47, and where RM-A8 (or RM-A4 and RM-A6), FT-149, and FT-1 50 are operable.
During Fuel Handling Building ESF Air Treatment System Operation.
At all times during containment purging.
At all times when condenser vacuum is established.
During onra'tion nf the= ventil=finn
+v=÷M (1)
The CHANNEL TEST shall also demonstrate that automatic isolation of this pa for e Auxiliary and Fuel Handling Building Ventilation System, the supply ventilation is isolated nt om alarm annunciation occurs if the following condition exists:
- 1.
Instrument indicates measured levels above the high alarm]
(Includes circuit-failure).
- 2.
Instrument indicates a down scale failure (Alarm function-o (Inc des circuit failure),.
- 3.
Instrument controls moved from the operate mode (Alarm fun *on only).
,2)
The CHANNEL TEST shall also demonstrate that co I oom alarm annunciation occurs if any of the following conditions exist:
1 Instrument indicates measured levels larm setpoint (includes circuit failure)
- 2.
Instrument indicates a down scale ailure in udes circuit failure).,
- 3.
Instrument controls moved he operate mode.
(3)
The initial CHANNEL CALIBRA 1O0 r r~dioactivity nieasurement instrumentation shall be performed using one or more of the referenc s t ard) certified by the-4ational Barer__ _*f Standar-o or using standards that have been obtained from pliers at participate in measurement assurance activities with MI-DS.These standards should per t calib tjpg the system over its intended range of energy and measurement range.
For subsequent CHIIL CaBRATION, sources that have been related to the initial calibration should be used. (Operatil n
nay substitute previously established calibration procedures for this requirement.)
N>
(4)
The CHANNEL CALIBRATION shall include the use of standard gas saml3les containing a nominal:
- 1.
One volume percent hydrogen, balance nitrogen, and
- 2.
Four volume percent hydrogen, balance nitrogen.
(5)
The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
- 1.
One volume percent oxygen, balance nitrogen, and
- 2.
Four volume percent oxygen, balance nitrogen.
48 Manual (0113 M1
.9.1
.*4
6610-PLN-4..
Revision 21 Table 3,2-2 Radioactive Gaseous Waste Sampling and Analysis Program
=
Minimum
ýa,,,ig I
I
,,Lower Limit of S1 Samping Analysis Type of Activity Detection (LLD)
Gaseous Release Type F
I Ceuec
- i.
y p r q e c F re qu e ncy A na lysis
( C m ) ( o e a All Release Types as Listed Above ln F,B, W# (Nt d)
.(During System Operation Co u
Charcoal 1-131 1 x1 (Notef)
Sampe
, ontinuous CW (Note d)
Principal Gamma (Nt Patclt Emitters (Note g)
- 1. AX 10-11 Continuous Composite (Note f).
Prticulate S(-131, Othrs)
(Nonten0L Copst Gross Alpha I x 10",
(*
Particulate
),
Sample I
,,(
..J..
Q.
Continuo*
Composite.I 01 (Note 9) '
(;
ample J.
Condenser Vent Stack Continuous Iodine nto ote )
Sampler (Note j)*
Continuous VebI d)
Sample (Not (Note k) 1-131 56 I'
Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN4200.01 Revision No.
Offsite Dose Calculation Manual (ODCM) 21 1.2 TMI Liauid Effluent Release Points and Liquid Radiation Monitor Data TMI-1 has two required liquid radiation monitors. These are RM-L6 and RM-L12. These liquid release point radiation monitors and sample points are shown in Table 1.1. (The TMI outfall radiation monitor, RM-L7, is also listed for information only.)
TMI-2 does not have any required liquid radiation monitors, but does utilize RM-LI2. and RM-L7 for release of liquid waste.
1.2.1 RM-L. 6 RM-L6 is an off-line system, monitoring radioactive batch dischargek the TMI-1 liquid radwaste system (see Figure 1.1). These batch releases are sam ed a analyzed per site procedures prior to release. The release rate is based on. r ng e of two Waste Evaporator Condensate Storage Tanks (WECST) at a flow c will less than 10%,
of ten times the 10 CFR 20 concentrations [20% for H-3] tara uclide concentrations in the unrestricted area, including conservative default values, Sr
The release flow rate used is the most restrictive *rtes calculated for each liquid batch release, per the approved plant pro du
-T=hee Dilution Factors (DF) are calculated to ultimatel calculate the batch release flow rate. These ithree-DF's are-calculated to insure each radionuclide released to the
- unrestricted area is less than 10 perc~n', ten times the IOCFR20 radionuclide concentrations, (20% ' for H-3), Z~ensure-*,
, liquid batch release boron concentration to the river will not exceed 0.7 ppm The maximum releas te " then calculated by dividing the most restrictive (largest)
DF into 90 percent current dilution flow rate of the Mechanical Draft Cooling Tower (MDCT). This cc e ati ow rate is then multiplied by 0.9 for the allowable flow rate.
Cal ul " n the IOCFR20 concentration DF:
DF1 Al) - (10% [20% for H-31 of ten times the IOCFR20 concentration)
Specific Activity of each identified radionuclide alculation of Boron DF:
DF 2 = Actual Tank Boron Concentration 0.7.
"C"*"" culItln,-"f*,*'
= 137 L1 nF-WfgI-1--hr 06 Pain. (4E 6 +/-im.~
C~l Maximum release flow rate calculation:
Max Flow = I(MDCT flow gpm
- 0.9) - (Most Restrictive DF)]
- 0.9 90
TMI - Unit I Radiological Controls Procedure Number 6610-PLN-4200.01 R(Bvision NO, 21 The dilution flow rate used is the current flow rate at the site. The minimum dilution flow rate is 5000 gpm per the TMI-1 FSAR. This ensures this batch release will meet the following equation.
7E(C 1IX,) + (CN.I2XH.):)< 0.1, where:
Ci = diluted concentration of the P radionuclide, other than H-3 (eq 1.2)
X= Ten times the concentration for that radionuclide in the unrestricted area (10 CFR 20, App. B, Table 2, Col. 2). A value of.3E-3 iCi/ml for dissolved and entrained noble gases shall be used.
CH.3 =diluted concentration of H-3 XK =Ten times the concentration for H-3 in th s 'ted area (10 CFR 20, App. B, Table 2, Col. 2).
"set points for RM-Lb are bse n
monitor respons each rad
?iold'e ~denrtifie: in the gamma scan samp suits Iols
(
I(g.CffCC)1*(CPM1tCi/cC)Jj+ (C RCP (2-o* jin (Ac CPMIj+/-
cO)d +
mme) =HIGH ALARM CPM where:
(ACi/'cc),
posi I
radi*nuclides (CPMCI RM-sen itivity to radio nucli CP~
=M G6 background prior to batch release M
z -:.k...-
V--'7 1,d t1rmir.cz.,y
-'JtZZT e1,.
"RM-. -nrrft=_"
RM-'12 is t line system, monitoring periodic combined releases from the Industrial 128-reatnt Systemn/Industrial Waste Filtration System (IWTS/IWFS). The input to originates in TMI-2 sumps, (see Figures 1.1 and 1.2) and the TMI-1 Turbine Bulld sump (see Figure 1.1). The set points are based on the maximum release rate from b th IWTS and IWFS simultaneously, (see Figure 1.1) a minimum dilution flow rate, and 50% of ten times the IOCFR20 concentration for Cs-137, which is the most limiting radionuclide at a concentratiori of 1 E-5 pCi/ml. These. inputs are used in equation 1.1 to determine'the RM-L12 High Alarm set point for all radionuclides being released. A high alarm on RM-L12 will close IWTS and IWFS release valves and trip release pumps to stop the release.
1.2.3 RM-LI0 RM-L0 was a Nal detector submerged in the TMI-1 Turbine Building Sump. This detector has been removed from service.
91 Offsite Dose Calculation Manual (ODCM)
-rT,+t 1.2.2 I 4LI*
2t
The setpoints for RM-L-6 are based on the maximum release rate (30 gpm), a minimum dilution flow (5000 gpm), and 25% of ten times the I OCFR20 concentration for Cs-1 37, which is the most limiting radionuclide at a concentration of I.OE-5 uCIml. These inputs are used in Equation 1.1 to determine the RM-L-6 High Alarm setpoint for all radionuclides being released. A high alarm on RM-L-6 will close valve WDL-V-257 and terminate any WECST releases to the environment.
0
Number TMI - Unit I Radiological Controls Procedure 6610-PLN-4200.01 Wie Revision No.
Offaite Dose Calculation Manual (ODCM) 21 1.2.4 RM-L7 RM-L7 is not an ODCM required liquid radiation monitor. RM-L7 is an off-line system, monitoring the TMI outfall to the Susquehanna River (see Figures 1.1 and 1.2). This monitor is the final radiation monitor for TMI-1 and TMI-2 normal liquid effluent releases.
1.3 Control of Liquid Releases TMI liquid effluent releases are controlled to less than ten times the I0CFR20 concentrations by limiting the percentage of this limit allowable from the two TMI liquid release points. RM-LS6 and effluent sampling/limitf batch releases to less than or equal tot,/o for all radionuclides
+-14, and RM-L12/ and effluent sampling1 limitj releases from (IM 1-1 and TMI-ess than or equal to 50% for Cs-137.t These radiation monitor set points also include built in meter error fact otfurt ensure that TMI liquid effluent releases are less than ten times the.1 OCFR20 concen tio a the environment, The radioactivity content of each batch of radioactive liquid was fned prior to release by sampling and analysis in accordance with ODCM Part I Tab[
.2-1 DCM Part II, Table 3.2-1.
The results of analyses are used with the ca[culational met a nnSe on 1.1, to assure that the concentration at the point of release is maintained withiri the OD Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1.
Post-release analysis of samples composited frjmjtatch releases are performed in accordance with ODCM Part l Table 3-2-1 or ODCM Part 11 Tab ?e The results of the previous post-release analysis shall be used with the calculation; thodsA the 00CM to assure that the concentrations at the point of release were maintained ODCM Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1.
.The radioactivity concentration o Ls di.jharged from continuous release points are determined by collection and analysis of les in--cordance with ODCM Part I Table 3.2-1, or ODCM Part II Table 3.2-1. The results ofeh n
are used with the calculational methods of the ODCM to assure that the conen t
the oint of release is maintained within the ODCM Part I Control 2.2.1.1, and OD a r)II Control 2.2.1.1.
92
Number TMI - Unit 1 Tle Radiological Controls Procedure 6610-PLN-4200.O1 Revision No.
Offsite Dose Calculation Manual (ODCM) 21 TABLE 4.1 TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data
-(Typtc~a ýIoL% m~p Ls e-I'S 117 GAEU A
UE RELEASE GASEOUS TERMINATION RADIATION G
O INTERLOCK MONITOR LEASE (YES/NO)
(DETECTOR)
LOCATpN!,
POINT VALVES 3281 Elevation Reactior HP-R-219 Auxil di g :Vent NONE Buitdl Exhaust H P3FR-2 9AlvU)
Station Vent HP-~29A Exhaust NONE HP-R 25*
328'lSEevation "Reactor Bfdag 25,
- xiliary Ildn
!Pu'rge Exhaust NONE EExlr 3Nidn Duct "AK
TMI WORD PROCESSING FORM 1001A Revision 45 F.I.G.URE..S Page Iofl PRIOR M-fTE:
Reference Number:
Procedure Number: b,/o-OLkf- */-t2. t/
Revision Number:
To Word Processing:______________
PROOFREAD SECTION:
Document Converted YES or U
iF DOCUMENT WAS CONVERTED YOU WILL NEED TO REVIEW THE ENTIRE PROCEDURE VERY CAREFULLYUI
- 1. Proofreader:,
Correction&1lChanges.
0 nlk
UNIT I PACKAGE NOTICE April 28, 2001 The attached package must be issued together with the effective date of May 4, 2001.
NOTE This package includes cancellations, replacements, and stand-alone revisions.
PROCEDURE NO.
1104-29S 1101-2.1 1430-RMS-1 4 6610-PLN-4200.01 6610-ADM-4250.01 6610-ADM-4250,11 661 0-ADM-4250.12 6610-ADM-4250.05 6610-ADMMA250.07 661 0-ADM-4250,09 PCR NUMBER(S),
PCR-00-3243 PCR-00-3244 PCR-00-3245 PCR-00-3246 PCR-00-3247
.. COMMENTS A
/Y N
A I
1ý
1001A.3 ENCLOSURE 2 TEMPORARY CHANGE FORM Page I of 2 PART A - INITIATION It '
TC NUMBER:.gLf
- 9ýI f
- 1 UNIT APPLICABILITY:
1 2
- 2.
TC CLASSIFICATION (Check One):
Conditional (C) X Permanent Rev (R) _
Single Use (S)
If Conditional, A/R or W1O activity that will restore and eliminate need for Conditional TC: Oe, LAt.-se-.. "IsTvTE OPE*
- 3.
PROCEDURE NUMBER:
6610-PLN-4200.O'l REV: 22
- 4.
PROCEDURE TITLE:
- 5.
PAGES AFFECTED: Paces 90 and 91 6-Does this TC supersede or replace existing TCs (Check One)?
YES NO X If YES, list TCa to be DELETED and removed from distribution:
- 7.
TC DESCRIPTION: Restore previous alarm setnoint methodology for RM-L-,
- 8.
REASON for TC: Implementatlon of new setp olnt methodolojly can not be ]--
LAGER effluent dose tracking system is Imp~lemented,
- 9.
INITIATOR:_/PafitWLSn4;n:E JR,,m E:4L
'R gC Print Name Initial Work Group Phone PART B - REVIEW & APPROVAL ITEMS 1 THRU S TO CONTINUE PROCESSING AS A TC 1 sr RTR 2f1 RTR/SRO
{
Circle O"e_
1 ARE THE CHANGES IN ACCORDANCE WITH TH T
THEPROCEDUREPERENCLOSURE I?
Y(
NO NO 2
Is the change TECHNICALLY AND OPERATIO CORRECT?
"NO NO
- 3.
Is the change SAFE from the standpoint U LEAR INDUSTRIAL SAFETY?"
NO O
NO
- 4.
Is the change IN CONFORMANCE H TECH kAL SPECIFICATIONS?
6 NO y3NO
- 5.
Is the CLASSIFICATION of th mo ag PROPERLY ESTABLISHED?
O
~NO
(~NO 6.*
Are TCs required to 0TH PIR DU ES assa result of this change?
(23 NO NO 7."
Are SPECIAL ASSIGNMENTS RAINING required to implement this TC?
YEN.N YES
- 8.
Does potential Ops Impact of this TC warrant IMMEDIATE DISTRIBUTION?
N/A 9
NO
- lf answered YES, explain here: "- L 4.0 -R, L-*I U*,e*0-A
-AZ.SbO A
I Ik 11,04-Z9.
,gZ7 1;e-Z4ARE APVTC,-M NOTE: The Reviewers shall verify the above steps are completed prior to signature.
Responsible Technical Reviewer:
199A 'HA:"
J' ifi' e" I
I ni til -a[
f,
/,ll,.e Responsible Technical Reviewer/SRO:
Initia'r lf" 5
j
(
Print Name Initial Date j--CA1 QZ?37 AGOS528 (05.101)