B14599, Radioactive Effluents Release Rept Jan-June 1993
| ML20056G081 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/30/1993 |
| From: | Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B14599, NUDOCS 9309020024 | |
| Download: ML20056G081 (150) | |
Text
-
l 1
NORTHEAST UTILITIES cenee, On,ce,. seen sueet, Berhn. Connecticut 1
)s UdI,7S $2 P.O. BOX 270
~w-.I5((N$[1,
HARTFORD, CONNECTICUT 06141-0210 k
J c wo m-. w.
(203) 665-5000 August 30, 1993 Docket Nos. 50-245 50-336 50-423 B14599 Re:
10CFR50.36a U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 Gentlemen:
Millstone Nuclear Power Station, Unit Nos. 1, 2, and 3 Semiannual Radioactive Effluents Release Report In accordance with the requirements of 10CFR50.36a, the Millstone Unit Nos. 1, 2, and 3 Technical Specifications, and the Radiological Effluents Monitoring Manual, a copy of the semiannual Radioactive Effluents Release Report is herewith submitted.
This report includes a summary of the quantities of solid radioactive wastes and liquid and gaseous effluents for the period of January through June 1993.
The report has been prepared in accordance with the format of Regulatory Guide 1.21, and copies of the report are being forwarded in accordance with the provisions of 10CFR50.4(b)(1).
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
% F Cwh.
J. F. O'peka t>
Executive Vice President cc:
see page 2 0100'; e
/[
9309020024 930630 PDR ADOCK 05000245 b
R PDR Ld pV f
I, OS3422 REV 4-8B k---.
U.S. Nuclear Regulatory Commission B14599/Page 2 August 30, 1993 cc:
T. T. Martin, P.egion I Administrator J. W. Andersen, NRC Acting Project Manager, Millstone Unit No. 1 G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 D. H. Jaffe, NRC Project Manager, Millstone Station P. D. Swetland, Senior Resident inspector, Millstone Unit Nos.1, 2, and 3
. l a
i NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION UNITS 1, 2 & 3
]
5 T
l RADIOACTIVE EFFLUENTS RELEASE REPORT i
l JANUARY - JUNE 1993
)
I l
i J
.i i
i e
i f
i 1
i OPERA TING LICENSES DPR-21, DPR-65, & NPF-49 l
DOCKET 50-245,00-336, & 50-423 1
,.r--_
,_,,-c-n-
.,-,,,..,,,. _ -,, -e.e.,,-,
,,,,--gw
Table of Contents 1
I i
1.0 Introduction i'
2.0 Radioactive Effluent Releases i
3.0 Radioactive Solid Waste i
i 4.0 Measurement of Radioactivity I'
5.0 REMM/ODCM/PCP Changes 6.0 Effluent Monitor inoperability 1
a i
7.0 Errata l
y I
I a
1 4
l 1
1.0 Introduction This report is being submitted for Northeast Nuclear Energy Company's Millstone Power Station Units 1,2, and 3, in accordance with 10CFR50.36a and the Radiological Effluent Technical Specifications and in the U.S. NRC Regulatory Guide 1.21 format. A combined report is being submitted for all three units because they share some common effluent facilities.
The dose consequences of the radioactive effluents considered in this report will be addressed in the Radioactive Effluents Dose Report. However, based upon previous experience, the dose consequences are anticipated to be well 4
within regulatory limits.
Listed below are the unit capacity factors and major shutdowns for the i-report period January 1 - June 30,1993:
Capacity Unit Factor 1
92.8 %
2 86.7 %
y i
3 88.5 %
i V
b b-e i
1
i 2.0 Radioactive Effluent Releases The plants were operated in accordance with the Technical Specifications.
The liquid and airborne effluents are given in the attached tables as follows.
Table 2.1-1 Unit 1 Liquid Effluents - Summary Table 2.1-2 Unit 1 Liquid Effluents-Batch Table 2.1-3 Unit 1 Airborne Effluents-Summary f
Table 2.1-4 Unit 1 Airborne Effluents - Elevated Continuous i
Table 2.2-1 Unit 2 Liquid Effluents - Summary Table 2.2-2 Unit 2 Liquid Effluents-Continuous - SGBD Table 2.2-3 Unit 2 Liquid Effluents-Batch Table 2.2-4 Unit 2 Airborne Effluents Summary Table 2.2-5 Unit 2 Airborne Ef';uents-Mixed Continuous -
i Vent and SGBD Tank Vent Table 2.2-6 Unit 2 Airborne Effluents - Mixed Batch -
Containment Purges Table 2.2-7 Unit 2 Airborne Effluents - Elevated Batch - WGDT Table 2.3-1 Unit 3 Liquid Effluents-Summary Table 2.3-2 Unit 3 Liquid Effluents - Continuous - SGBD Table 2.3-3 Unit 3 Liquid Effluents-Batch - LWS Table 2.3-4 Unit 3 Liquid Effluents - Batch - CPF WN Sumps Table 2.3-5 Unit 3 Airborne Effluents-Summary 7
Table 2.3-6 Unit 3 Airborne Effluents-Mixed Continuous-Normal Ventilation Table 2.3-7 Unit 3 Airborne Effluents-Mixed Continuous -
3 ESF Building Ventilation Table 2.3-8 Unit 3 Airborne Effluents-Mixed Batch -
Containment Drawdown Table 2.3-9 Unit 3 Airborne Effluents-Mixed Batch -
Containment Purges 1
i
l i
Table 2.1-1 Millstone Unit No.1 Liquid Effluents - Release Summary l
i First Quarter 1993 Units January l Fet*uary l March l Totat A. Fission and Activation Products 1.
Total Actwty Ci 1.84E-02 1.42E-02 2.44E-02 t 5.70E-02 k
Released 2.
Average Perod uCem!
2.49E-10 ! 2.13E-10 3.?1E-10 l 2.66E-10 i
f Diluted ActN#y f
B. Tritium 1.
Total Actwity Ci l 7.54 E-01 j 1.95E+00 2.47E+00 5.17E+00 l
E Released j
1.02E-08 l 2.92E-08 3.34E-08 2.41E-08 l
2.
Average Penod uCami Diluted Actwity i
l C. Dissolved and Entrained Gases i
1.
Total Actwty Ci 8.51E-06 l N/D N/D l 6.51 E-06 Released f
2.
Average DMed uCUml 1.15E-13 l
3.96E-14__
Activty D. Gross Alpha 1.
Total Actwty Ci N/D l
N/D l
N/D 1
N/D i
Released No Activity Detected I
E. Volume 1.
Released Waste Liters ! 7.84E+05 7.63E+05 l 9.92E+05 !!
.54E+06 2
vm I
2.
DMon Volume uers l 2.'71E+09 2.64E+09 ' 3.26E+09 l S.61E+09 j
Dunng Releases i
i 3 Duon volume uers 7.41 E+ 10 6.6BE+10 l 7.39E+10 i 2.15E+11 Dunng Penod l
f i
L N/D = Not Detected t
I I
i h
i i
t F
4
Table 2.1-1 Millstone Unit No.1 Liquid Effluents - Release Summary i
s Second Quader 1993 Units Apnl l
May l
June l
Total
}
A. Fission and Activation Products 1.
Total Activty Ci 1.14E-02 4.81E-03 i 1.88E-02 l 3.50E-02 j
Released I
i 2.
Average Penod uCi/mi 1.78E-10 6.49E-11 ! 2.62E-10 ; 1.67E-10 Diluted Activty t
4 B. Tritium 1.
Total Actidy Ci ! 1.25E+00 8.59E-01 ' 1.00E+00 3.11 E+ 00 f
Reieased f
I 2.
Average Penod lUCvml. 1.95E-08 l 1.16E-08 j 1.40E-08 l 1.48E-08 Diluted Actedy i I
I 1
C. Dissolved and Entrained Gases 1.
Tual Activey Ci 7.4BE-05 N/D l
N/D 7.48E-05 Released 1.16E-12; l
3.56E-13 2.
Average DilJted uCemi Actrdy I
i D. Gross Alpha 1.
Total Activty Ci j N/D i
N/D N/D N/D Released i
N3 Activity Detected E. Volume 1.
Released Waste Uters 9.61E+ 05 8.18E+ 05 7.11E+05 : 2.49E+06 vsume 1
2.
Deiution volume uters 2.75E+09 2.68E+ 09 2.45E+ 09 7.885 49-I Dunng Releases 3 Diiution volume, uters 6 42E+10 j 7.41E+10 l 7.15E+10 __2.10E+11 Dunng Penod i
I N/D = Not Detected i
)
9 t
l
.i t
i
i Table 2.1-2 Millstone Unit No.1 Liquid Effluents - Batch i
Nuclides First Quarter 1993 i
Released Units January l February l March l
Total r
A. Fission & Activation Products Ba-140 1 Ci
! 2.80E-05 2.80E-05 Ce-143 i Ci 1.60E-05 1.60E-05 Co-60 Ci 1.56E-02 1.19E-02 1.70E-02 4.45E-02 Cs-137 Ci 2.54E-04 7.33E-04 5.12E-03 6.11E-03 Fe-55 Ci 2.67E-04 2.67E-04 1-131 Ci 8.25E-06 8.25E-06 l-133 Ci 8.27E-06 8.27E-06 Mn-54 I Ci 2.47E-05 4.60E-05 7.07E-05 Mo-99 Ci 4.93E-05 4.93E-05 l
Na-24 Ci 7.86E-05 7.86E-05 l
Tc-99m Ci 5.41 E-05 5.41 E-05 i
Zn-65 Ci 2.27E-03 > 1.53E-03 2.06E-03 1 5.86E-03 i
Total Activity i Ci i 1.84E-02 i 1.42E-02 1 2.44E-02 1 5.70E-02 B. Tritium lH-3 i Ci I 7.54 E-01 1 1.95E+00 1 2.47E+00 1 5.17E+00 l j
i C. Dissolved & Entrained Gases I
Xe-135 i Ci 1 8.51E-06 I I
i 8.51E-06 Total Activity i Ci t 8.51 E-06 1 1
1 8.51 E-06
[
D. Gross Alpha l Gross Alpha i Ci !
I i
i l
l i
t l
1 l
i
?
Table 2.1-2 Millstone Unit No.1 Liquid Effluents - Batch i
Nuclides Second Quarter 1993 Released Units April l
May l
June l
Total A. Fission & Activation Products l
Co-60 Ci 7.82E-03 1.96E-03 I 8.74E-03 1.85E-02 Cr-51 Ci 9.02E-05 2.21E-04 J 3.11 E-04 Cs-134 Ci 9.38E-06 l 9.38E-06 Cs-137 Ci 1.13E-03
[ 1.99E-03 3.12E-03 Fe-55 Ci 1.09E-03 2.81 E-04 1.37E-03 1-131 Ci 2.00E-05 2.00E-05 l-133 Ci 3.30E-05 1.22E-05 4.52E-05 Mn-54 Ci 2.03E-04 2.91 E-04 1.39E-04 6.33E-04 Mo-99 Ci 2.40E-04 1.64E-05 l 2.56E-04 Na-24 Ci 2.34E-05 i 2.34E-05 St-90 Ci 8.02E-05 ;
8.02E-05 Tc-99m Ci 2.58E-04 ! 1.76E-05 l 2.76E-04 Zn-65 Ci i 5.29E-04 i 2.19E-03 i 7.605-03 1 1.03E-02 Total Activity 1 Ci 1.14E-02 1 4.81 E-03 1 1.88E-02 1 3.50E 02 B. Tritium lH-3 i Ci i 1.25E+00 t 8.59E-01 i 1.00E+00 t 3.11E+00 l C. Dissolved & Entrained Gases Xe-133 Ci 6.90E-05 1 l
6.90E-05 Xe-135 Ci 5.78E-06 i i
5.78E-06 Total Activity i Ci I 7.48E-05 1 I
i 7.4BE-05 D. Gross Alpha
[ Gross Alpha i Ci )
i 1
l t
i t
f V
Table 2.1-3 Millstone Unit No.1 Airbome Effluents-Release Summary First Quarter 1993 Units January l February l March l
Total A. Fission & Activation Gases 1.
Total Activey Ci j 2.27E+02 3.46E+ 01 3.82E+01 l 3.00E+02 l
Released l
- 2. Average Pered UCi'sec { 9.40E+01 1.43E+ 01 1.58E+01 l 4.14E+01 Release Rate I
{
i B. lodine-131 1.
Total ActMty Ci 9.27E-04 i 1.49E-04 8.79E-05 l 1.16E-03 i
1 1
c Released f
I j
- 2. Average Pened uCi'sec 3.83E-04 j 6.16E-05 3.63E-05 1.60E-04 Release Rate l
j C. Par 1iculates 1.53E-04 j 2.09E-04 ; 6.88E-04 1.
Total ActMty Ci < 3.27E-04 j
Released
_j j_
2.
Average Diluted UCesec 1.35E-04 i 6.32E-05 l 8.64E-05, 9.48E-05 ActMty l
I i
D. Gross Alpha 1.
Total Activty Ci j 3.59E-07 j 2.86E-07 ) 4.97E-07 l 1.14E-06 Released l
l l
l E. Tritium 1.
Total Act!dy Ci 2.66E+00 ; 5.08E+00 2.82E+00 ' 1.06E+01 Reieased i
- 2. Average Penod uCvsee 1.10E+00 " 2.10E+00 1.17E+ 00
_1.46 E+ 00 Release Rate N/D = Not Detected l
4 4
[
1 Table 2.1-3 1
Millstone Unit No.1 Airbome Effluents-Release Summary 1
Second Quarter 1993 l
Units April l
May l
June l
Total 1
t A. Fiss!on & Activation Gases 1.
Total Actwty C6 {
N/D 4.97E+00 2.49E-01 j 5.22E+00 Released l
I 2.
Average Pered uCisec 2.05E+00 8.23E-02 i 6.16E-01 l
Release Rate 1
B. lodine-131 1.
Totar Activty Ci 4.58E-05 2.82E-05 4.77E-05 i 1.22E-04 i
Re6 eased i
2 Average Penod uCPsee 1.52E-05 l 1.17E-05 1.58E-05 } 1.44E-05 Release Rate i
t C. Particulates 3
7.92E-05 9.09E-04 ! 1.81E-03 1.
Total Actwty ci 8.21 E-04 f
Released 3.01E-04 2.14 E-04 l
l 3.27E-05 2 Average Diluted uCesee-2.72E-04 i
Actway I
D. Gross Alpha
)
1.
Total ActNay Ci 1.59E-07 2.00E-07 1.49E-06 i 1.85E-06 i
I Released E. Tritium 1.25E+00 l 1.58E+00 j N/D 2.83E+00 1 Totaf Activty Ci Released I
- 2. Average Pered uCusec 4.14 E-01 6.53E-01
~ "
3.34E-01 i
Release Rate N/D = Not Detected t
I i
1 1
Table 2.1-4 l
Millstone Unit No.1 Airbome Effluents - Elevated Continuous j
Nuclides First Quarter 1993 Released Units January l February l March l Total A. Fission & Activation Gases Ar-41 Ci 9.00E-01 1.55E-01 1.05E-01 l 1.16E+00 l
Kr-85 Ci 1.29E+ 01
~ 1.29E+01 Kr-85m Ci 5.34E+ 00 9.28E-01 1.01E+00 7.28E+ 00 Kr-87 Ci 2.85E+01 4.68E+00 4.99E+ 00 3.82E+01 Kr-88 Cl 1.80E+ 01 3.31E+00 3.66E+ 00 2.50E+01 Xe-133 Ci 1.09E+ 00 1.93E-01 1.15E-01 1.40E+00 Xe-135 Ci 3.38E+01 5.51E+00 6.25E+00 4.56E+ 01
.Xe-135m Ci 2.58E+01 4.35E+00 4.68E+00 3.48E+01 i
Xe-138 Ci 1.01E+ 02 1.55E+01 1.74E+01 l 1.34E+02 Total Activity i Ci i 2.27E+02 1 3.46E+01 1 3.82E+01 1 3.00E+02 B. lodines 1-131 1 Ci ! 9.27E-04 1.49E-04 I 8.79E-05 1 1.16E-03 1-133 I Ci I 9.64E-03 1.56E-03 i 6.49E-04 i 1.18E-02 Total Activity 1 Ci i 1.06E-02 l 1.71E-03 i 7.37E-04 I 1.30E-02 C. Particulates 1-131 Ci I
Ba-140 Ci 1.77E-04 7.10E-05 7.34E-05 3.21 E-04 l
Co-58 Cl 1.58E-06 1.04E-06 2.62E-06 6
Co-60 Ci j 3.34E-06 l 7.93E-06 2.77E-05 3.90E-05 Cr-51 Ci ! 4.81E-05 ' 2.45E-05 3.04E-05 1.03E-04 Cs-137 Cil 2.93E-06 9.63E-06 1.26E-05 Mn-54 Ci i l
1.04E-06 1.04E-06 Sr-89 Ci l 7.16E-05 2.72E-05 2.72E-05 1.26E-04 d
Sr-90 Ci ~ 3.68E-07 3.68E-07 Zn-65 Ci 2.61 E-05 1.77E-05 __3.85E-05 8.23E-05 Total Activity i Ci I 3.27E-04 1 1.53E-04 I 2.09E-04 I 6.88E-04_
D. Gross Alpha l Gross Alpha i Ci I 3.59E-07 1 2.86E-07 1 4.97E-07 1 1.14E-06 l E. Tritium lH-3 1 Ci 1 2.66E+00 i 5.08E+00 1 2.82E+00 i 1.06E+01 l 1
l
Table 2.1-4 Millstone Unit No.1 Airborne Effluents-Elevated Continuous 1
l 1
Nuclides Second Quarter 1993 Released Units April l
May l
June l
Total A. Fission & Activation Gases Ar-41 Ci I 6.48E-02 2.38E-02 l 8.86E-02
)
Kr-85m Ci l 1.18E-01 1.18E-01 Kr-87 Ci !
6.37E-01 6.37E-01 Kr-88 Ci i 4.62E-01 4.62E-01 Xe-133 Ci 9.15E-02 1.20E-01 2.12E-01 Xe-135
" Ci j 7.70E-01 1.05E-01 8.75E-01 Xe-135m Ci
! 5.33E-01 i 5.33E-01 l
Xe-138 Ci l 2.29E+00 i 2.29E+00 Total Activity 1 Ci i i 4.97E+00 1 2.49E-01 1 5.22E+00 B. lodines 1-131 Cl i 4.58E-05 2.82E-05 ! 4.65E-05 1.21 E-04 l-133 Ci j 3.54E-04 3.93E-04 ! 2.18E-04 9.65E-04 Total Activity 1 Ci i 4.00E-04 i 4.21 E-04 ! 2.65E-04 1 1.09E-03 I
C. Particulates l-131 Ci [
[ 1.24 E-06 1.24 E-06 Ba-140 Ci !
1.94E-05 ! 4.96E-06 2.44 E-05 Ce-141 Ci i I
l 9.49E-07 9.49E-07 Co-58
, Ci ' 6.31E-05 1.17E-05 7.48E-05 Co-60 l Ci 1.21 E-04 1.52E-05 2.5BE-04 3.94 E-04 Cr-51
} Ci 2.68E-04 1.32E-04 4.00E-04 Cs-137 Ci 1.31 E-05 5.45E-06 6.35E-06 2.49E-05 Fe-59 Ci 8.44E-06 5.13E-05 5.97E-05 Mn-54 Ci 6.45E-05 l 2.46E-04 3.11E-04 Sr-89 Ci 2.91E-06 ! 1.32E-05 3.64 E-06 1.98E-05 Zn-65 i Ci i 2.80E-04 1 2.59E-05 1.93E-04 4.99E-04 Total Activity i Ci i 8.21E-04 1 7.92E-05 i 9.09E-04 ! 1.81 E-03 D. Gross Alpha l Gross Alpha I Ci i 1.59E-07 ! 2.00E-07 i 1.49E-06 1 1.85E-06 l E. Tritium lH-3 i Ci i 1.25E+00 1 1.58E+00 i i 2.83E+00 l I
1 i
Table 2.2-1 Millstone Unit No. 2 l
Liquid Effluents - Release Summary 2
I I
First Quarter 1993 i
Units January l February l March l Total f
A. Fission and Activation Products 1.
Total Actwdy Cs l 3.09E-01 2.62E-01 1.59E-02 { 5.87E-01 l
Released l
l f
2.
Average Pero 1 uCvml i 7.22E-09 5.75E-09 j 2.29E-10 1 3.72E-09 l
Diluted Activty l
I i
B. Tritium 2.55E+00 l 4.89E+00 l 1.59E+01 ; 2.33E+01 f
1.
Total Activity Ci j
Released 1
[
2.
Average Penod ' uCum!
5.95E-08 i 1.07E-07 4 2.28E-07 1.47E-07
)
Diluted Activity.
f J
C. Dissolved and Entrained Gases 1
1.
Total Activry Ci l 2.70E-04 1.08E-02 l 2.24E-02 3.34E-02
{
l Released l
3.21E-10 [ f~12E-10 s
j 2.
Average Diluted uCUmll 6.30E-12 ; 2.37E-10 l Activity l
l 1
i I
q a
D. Gross Alpha N/D l
N/D i
N/D l
N/D 1.
Total Actwdy l Ci No Activity Detected Released a
]
E. Volume 7
l 1.
Reieased Waste i uters 6.07E+ 07 1.33E+07 1.90E+07 i 9.30E+07 i
1 volume j
l uters l 6.51E+09 8.79E+09 1.36E+10 { 2 89E+10 2.
Duion volume j
During Releases !
uters l 4.28E+10, 4.56E+10 j 6.96E+10 j 1.58E+11
]
3 Diiut.on volume During Penod I
[
N/D = Not Detected I
t i
l l
i 4
l 4
a l
L lt I
t m
e i
i Table 2.2-1 i
Millstone Unit.No. 2
(
Liguid Effluents-Release Summary I
I Second Quaner 1993 Units Apnl l
May l
June l
Total A. Fission and Activation Products 1.
Tv4 Actvdy ci ! 9.48E-03 1.94E-02 ! 1.44E-02 4.33E-02 l
)
l Released 2 Average Perod } UCi/ml j 1.01E-10 l 2.07E-10 i 1.54E-10 1.54E-10 Diluted Activny l I
I s
B. Tritium 1.
Total Actvny
- ci 1.57E+01 ! 3.79E+01 i 6.17E+01 1.15E+02 Released j
l I
j 2 Average Pered I uCUml 1.67E-07, 4.04E-07 6.59E-07 l 4.10E-07 Diluted Activity f
{
[
4 C. Dissolved and Entrained Gases 1.
Total t ctwny ci ! 8.71E-03 ! 9.85E-02 8.84E-02, 1.96E-01 Released l
i 2 Average Dued uccmil 9.29E-11 [ 1.05E-09] 9.44E-10 i 6.96E-10
?
Actudy i
I I
=
1
~
D. Gross Alpha N/D i
N/D i
1.
Total Actmty l Ct N/D N/D No Activity Detected j
I Released i
i E. Volume Lners j 1.59E+05 ; 2.27E+07 l' 2.86E+05, 2.31E+07 1.
Released Waste 1
volume i
2 Diluton vo!ume Leers i 1.14E+10, 9.71E+09 8.20E+09 l 2.93E+10 During Releases l
l 3 Dauton vuume uters l 9.37E+10 t 9.38E+10 1 9.37E+10 2.81E+11 i
Dunng Penod f
f N/D = Not Detected f
i i
w
l Table 2.2-2 l
Millstone Unit No. 2 Liquid Effluents - Continuous - SGBD i
i Nuclides First Quarter 1993 Released Units January l February l March l
Total I
A. Fission & Activation Products 1.51 E-04 l-134 i Ci 1.51 E-04 i Na-24 i Ci 1.42E-04 I 2.25E-01 2.25E-01 Total Activity i Ci l 2.93E-04 1 2.25E-01 i I 2.25E-01 i
l B. Tritium lH-3 i Ci !
i 3.14E-02 t 1.01E-02 i 4.15E-02 l C. Dissolved & Entrained Gases f
Total Activity C i i
D. Gross Alpha 1
l Gross Alpha 1 Ci i I
i l
t i
i I
I i
l
)
i i
1 h
t W
l t
Table 2.2-2 i
Millstone Unit No. 2 Liquid Effluents - Continuous - SGBD T
Nuclides Second Quarter 1993 l
Released Units Apnl l
May l
June l
Total 1
A. Fission & Activation Products Ce-144 i Ci I l 2.35E-05 i i ic.35E-05 Total Activity l Ci l i 2.35E-05 I I 2.35E-05 B. Tritium lH-3
- Ci !
I i
l f
C. Dissolved & Entrained Gases i Ci i l
l i
Total Activity l Ci I i
i l
D. Gross Alpha l Gross Alpha I Ci i i
i i
l t
}
t 1
i 1
i
Table 2.2-3 Millstone Unit No. 2 Lic,uid Effluents - Batch i
Nuchdes First Quarter 1993 Released Units January l February l March l
Total A. Fission & Activation Products Ag-110m Ci 2.53E-02 8.01 E-03 2.32E-03 3.56E-02 Ce-144 Ci 6.17E-05 6.17E-05 Co-57 Ci 4.68E-05 4.68E-05 Co-58 Cl 1.08E-02 2.53E-03 6.96E-04 1.41 E-02 Co-60 Ci 7.60E-02 1.24E-02 5.22E-03 l 9.36E-02 Cs-134 Ci 1.66E-02 3.13E-04 6.51E-05 l 1.70E-02 Cs-137 Ci 7.53E-02 1.38E-03 4.40E-04 7.71 E-02 Fe-55 Ci 9.40E-02 1.16E-02 6.33E-03 1.12E-01 Fe-59 Ci 3.07E-04 i
3.07E-04 Fu-105 Ci 6.71 E-04 l
6.71 E-04 i
I 1-131 Ci
! 1.70E-05 8.25E-05 i 9.95E-05 La-140 Ci 2.76E-05 2.18E-05 2.16E-04 2.65E-04 Mn-54 Ci 1.14E-03 9.68E-05 2.81E-05 1.27E-03 Mo-99 Ci 1.55E-05 l 1.55E-05 Nb-95 Ci 1.13E-03 8.20E-05 8.32E-06 i 1.22E-03 Sb-124 Ci 4.48E-04 3.52E-05 4.83E-04 Sb-125 Ci 6.60E-03 3.01 E-04 5.31 E-04 7.43E-03 St-89 Ci 1.17E-05 1.17E-05 St-90 Ci 1.93E-05 6.71E-06 l 2.60E-05 Sr-92 Ci l 1.63E-04 3.44E-05 l 2.97E-04 Tc-99m Ci l 1.68E-05 i 1.68E-05 Zr-95 Ci i 3.36E-04 i
3.36E-04 Total Activity i Ci i 3.09E-01 i 3.70E-02 ! 1.59E-02 i 3.62E-01 B. Tritium lH-3 i Ci l 2.55E+00 1 4.86E+00 i 1.59E+01 ! 2.33E+01 l C. Dissolved & Entrained Gases Kr-85 Ci l
l 1.00E-02 ! 1.00E-02 Kr-88 Ci i 1.10E-05 l 1.10E-05 Xe-133 i Ci 2.70E-04 j 1.04E-02 l 1.23E-02 l 2.30E-02 Xe-135 i Ci 4 i 3.55E-04 1 2.74E-05 i 3.82E-04 Total Activity 1 Ci i 2.70E-04 1 1.08E-02 t 2.24E-02 I 3.34 E-02 D. Gross Alpha l Gross Alpha i Ci i I
i 1
l
i Table 2.2-3 Millstone Unit No. 2 Liquid Effluents-Batch i
Nuclides Second Quarter 1993 Released Units April l
May l
June l
Total A. Fission & Activation Products Ap-110m Ci 9.17E-04 5.88E-04 7.49E-04 2.2SE-03 Be-7 Ci 6.91E-05 6.32E-05 1.32E-04 Co-58 Ci 5.45E-04 i 1.33E-04 6.52E-04 1.33E-03 Co-60 i Ci 3.50E-03 1.52E-02 4.74E-03 2.34E-02 t
Cs-134 Ci 1.33E-04 1.16E-05 4.91 E-04 6.35E-04 Cs-137 Ci 5.07E-04 2.57E-04 1.38E-03 2.14 E-03 Fe-55 Ci 3.62E-03 2.51E-03 4.69E-03 1.08E-02 i
1-131 Ci 4.42E-05 5.55E-05 1.37E-04 2.37E-04 La-140 Ci 8.29E-06 2.74E-04 2.82E-04 Mn-54 Ci _
1.06E-05 3.80E-05 4.86E-05 i
Mo-99 Ci {
2.49E-05 2.49E-05 Nb-95 Ci i 1.56E-05 1 1.56E-05 j
Nb 97 Ci 5.95E-05 l 1.67E-04 2.27E-04 Sb-124 I Ci i
7.76E-06 7.76E-06 i
Sb-125 Ci l 1.17E-04 j 5.21 E-04 9.82E-04 1.62E-03 l
Sr-89 Ci 1.21E-05 !
2.29E-06 1.44E-05 Sr-90 Ci 2.75E-06 i 1.44E-06 4.19E-06 i
Tc-104 Ci 5.94E-05 5.94E-05 Tc-99m Ci 2.66E-05 2.66E-05 Total Activity i Ci i 9.48E-03 t 1.94E-02 1 1.44E-02 i 4.33E-02 t
B. Tritium lH-3 I Ci i 1.57E+01 1 3.79E+01 1 6.17E+01 1 1.15E+02 l C. Dissolved & Entrained Gases Kr-85 Ci
{ 6.76E-03 9.90E-03 1.67E-02 Xe-133
. Ci 8.49E-03 l 8.22E-02 7.65E-02 1.67E-01 Xe-133m l Ci i 1.59E-03 1.20E-03 2.79E-03 Xe-135
! Ci 2.21 E-04 i 8.01E-03 i 8.20E-04 i 9.05E-03 l
Total Activity ! Ci i 8.71E-03 t 9 85E-02 ! 8.84E-02 1 1.96E-01 D. Gross Alpha l Gross Alpha i Ci i l
i l
i i
I
e i
Table 2.2-4
.j Millstone Unit No. 2 Airbome Effluents - Release Summary I
First Quarter 1993 Units January l February l March l
Total i
A. Fission & Activation Gases 1.
Total Actwny Ci 1.23E-01 9.94 E-01 4.36E-01 l 1.55E+00
{
Releat.ed
)
2.
Average Perod uC hec 4.07E-02 3.29E-01 l 1.80E-01 1.84 E-01 Release Rate
~.
l B. lodine 131 1.
Total Activny Ci I 5.81 E-06 2.81E 3 28E-05 4 6.67E-05 Rekased 2.
Average Period uCPsec 1.92E-06 9.30E-06 1.36E-05 7.89E-06 Release Rate l
C. Particulates 1.
Tota! Activny Ci j 4.87E-06 l N/D 1.03E-05 l 1.52E-05 Released l
I I
2 Average DiMed uCPsec 1.61E-05 l-
{ 4.26E-06 1.50E-06 Activity I
i i
i D. Gross Alpha i
1.
Total Actray Ci i N/D l
N/D l
N/D
{
N/D Released l
No Activity Detected E. Tritium 1.
Total Actnary Ci 1.26E+ 00 2.95E+ 01 5.53E+00 j 3.63E+01 Rekased 2 Average Penod uCPsec 4.17E-01 9.77E+00 ! 2.29E+00 4.29E+ 00 Release Rate I
i N/D = Not Detected t
i 4
i P
Table 2.2-4 Millstone Unit N3,2 Airbome Effluents - Release Summary f
l i
Second Quarter 1993 Units April l
May l
June l
Total A. Fission & Activation Gases i
i 1.
Total Actvey Ci 1.30E-01 j 5.41E-01 1.76E+00 { 2.43E+00
]
I Released 2 Avempe Perod uCi'sec 5.37E-02 ' 1.79E-01 l 7.26E-01 { 3.09E-01 Release Rate i
l B. lodine-131 1.
Total Activey i Ci 6.34E-05 1.00E-04 1.30E-04 l 2.93E-04 Released l
2.
Average Perod l uCusec 2.62E-05 3.31 E-05 5.37E-05 i 3.73E-05 Release Rate
}
C. Particulates 1.
Total Actwey l Ci N/D i
N/D N/D l
N/D Released I
No Activity Detected j
t j
I 2.
Average Datuted l uCt'sec l l
Activity I
a D. Gross Alpha i
1.
Total Actwey l Ci N/D l
N/D j
N/D l
N/D
{
Reieased No Activity Detected E. Tritium 1.
Total Actwity Ci 1 5.14E-01 1 6.13E-01 ! 8.60E-01 i 1.99E+00 Reieased 2.
Average Penod uCPsee j 2.12E-01 2.03E-01 iSSE-01 2.53E-01 I
Release Rate
\\
i N/D = Not Detected l
I l
l i
i
Table 2.2-5 Mi!! stone Unit No. 2 Airbome Effluents - Mixed Continuous - Vent & SGBD Tank Vent l
l 1
l Nuclides First Quarter 1993 Released Units January l February l March l
Total A. Fission & Activation Gases Kr-85 Ci 2.77E-01 I i 2.77E-01 Xe-135 Ci 1.23E-01 2.24 E-01 1 127E-01 1 4.74E-01 Total Activity i Ci i 1.23E-01 i 5 01E-01 l 1.27E-01 1 7.51 E-01 B. lodines 1-131 Ci 1 5.81 E-06 2.81 E-05 3.28E-05 1 6.67E-05
' i 1-133 Ci i 8.13E-06 7.03E-05 8.82E-05 ! 1.67E-04 f
Total Activity i Ci i 1.39E-05 I 9.84E-05 1 1.21 E-04 l 2.33E-04 C. Particulates 1-131 Ci !
I J
l Ce-144 Ci, 2.49E-06 ;
i 2.49E-06 Co-58 Ci 2.38E-06 i T
2.38E-06 i
Co-60 Ci 1
{ 8.68E-06 8.68E-06 Cs-137 Ci j
i 1.64E-06 1 1.64E-06 Total Activity i Ci I 4.87E-06 I i 1.03E-05 l 1.52E-05 I
D. Gross Alpha J
l Gross Alpha i Ci l i
i i
E. Tritium lH-3 I Ci i 1.26E+00 1 2.95E+01 i 5.53E+00 1 3.63E+01 l f
i i
I 1
l
L Table 2.2-5 MH! stone Unit No. 2 Airbome Effluents-Mixed Continuous-Vent & SGBD Tank Vent f
i I
Nuclides Second Quarter 1993 Released Units April l
May l
June l
Total i
1 A. Fission & Activation Gases Kr-88 Ci i j 3.88E-01 1 3.8BE-01 Xe-133 Ci i
! 1.05E+00 1.05E400 Xe-135 Cil 1.30E-01 1.53E-01 i 6.89E-01 i 9.72E-01 Total Activity i Ci i 1.30E-01 1 5.41 E-01 1 1.74E+00 1 2.41 E+00 B. lodines l-131 l Ci l 6.34E-05 ! 1.00E-04 ! 1.30E-04 ! 2.93E-04 3.83E-04 i 6.50E-04 1-133 I Ci i 1.65E-04 i 1.02E-04 Total Activity i Ci 1 2.28 E-04 I 2.02E-04 l 5.13E-04 I 9.43E-04 i
C. Particulates 1-131 1 Ci i
t i Ci i
l I
Total Activity l Ci l l
I i
D. Gross Alpha l
l Gross Alpha l Ci i t
1 l
E. Tritium lH-3 I Ci i 5.14 E-01 1 6.13E-01 ! 8.60E-01,1.99E+00 l t
9
i Table 2.2-6 l
Mi!! stone Unit No. 2 Airbome Effluents - Mixed Batch - Containment Purges r
i
<< No Activity Detected >>
l Nuclides First Quarter 1993 Released Units January l February l March l
Total i
i A. Fission & Activation Gases
+
l Ci I i
i i
Total Activity i Ci i l
I i
B. lodines 1-131 l Ci I
I 1 Ci i
i Total Activity 1 Ci i i
l C. Particulates 1-131 Ci !
l t
[
Ci i I
i Total Activity l Ci !
l i
D. Gross Alpha i
l Gross Alpha l Ci i i
i I
l l
E. Tritium l
l H-3 I Ci ;
i i
1 l
5 n
9 I
i h
I 1
i 4
l
?
i Table 2.2-6
~
Millstone Unit No. 2 Airbome Effluents - Mixed Batch - Containment Purges i
<< No Activity Detected >>
Nuclides Second Quarter 1993 Released Units April l
May l
June l
Total A. Fission & Activation Gases I Ci !
i 1
Total Activity i Ci I i
i I
{
B. lodines l
j l-131 Ci !
l Ci i t
Total Activity i Ci f I
C. Particulates i
1-131 i Ci i 1
I
! Ci j 7
i Total Activity i Ci i
t i
D. Gross Alpha l Gross Alpha l Ci t t
i l
7 E. Tritium
H-3 i Ci 6
1 i
l t
e 0
l e
Table 2.2-7 Millstone '> nit No. 2 Airbome Effluents - Elevated Batch - WGDT r
Nuclides First Quarter 1993 Released Units January l February l March l
Total A. Fission & Activation Gases I
Kr-85 Ci
! 4.93E-01 3.09E-01 I 8.03E-01 s
Xe-135 Ci i 1.21 E-05 i 1.21E-05 l
Total Activity l Ci i I 4.93E-01 i 3.09E-01 -i 8.03E-01 B. lodines 1-131 Ci t l
l Ci !
I i
Total Activity i Ci i I
l C. Particulates l-131 Ci i l
Ci i i
Total Activity 1 Ci i i
i D. Gross Alpha i
l Gross Alpha I Ci i i
I i
l l
i E. Tritium lH-3 i Ci i 1.36E-04 i 1.43E-04 i 2.79E-04 l I
i I
I l
Table 2.2-7 Millstone Unit No. 2 Airbome Effluents - Elevated Batch - WGDT l
Nuclides Second Quarter 1993 Released Units April l
May l
June l
Total A. Fission & Activation Gases Kr-85 Ci 1.70E-02 1.70E-02 Xe-131m Ci 2.29E-04 2.29E-04 Xe-133 Ci i 1
3.41 E-04 3.41 E-04 Total Activity i Ci i l
i 1.7SE-02 1 1.76E-02 B. lodines I-131 Ci l j
Ci i i
Total Activity i Ci i i
i i
C. Particulates 1-131 Ci I l
l f
Ci l l
l Total Activity i Ci i i
D. Gross Alpha l Gross Alpha I Ci i l
i i
l 4
E. Tritium lH-3 i Ci l i
i 6.36E-05 1 6.36E-05 l I
i r
b i
i I
[
{
i s
I t
Table 2.3-1 l
Millstone Unit No. 3 i
Liquid Effluents - Release Summary i
First Quarter 1993 l
~
Units ~ January l February l March l Tota!
A. Fission and Activation Products 1.
Total Actuey l 0 ' 2.60E-02 l 5.50E-02 4.26E-02 1.24E-01 a
Released i
2.
Average Penod uCL'mi 1.65E-10 4.02E-10 1 2.84E-10 1 2.78E-10 j
i k
l Diluted Actwry B. Tritium 1.58E+01 i 9.02E+01 l 9.16E+01 j 1.98E*02 l
1.
Total ActNey Ci Released i
l 2.
Average Penod UCs/ml j 1.00E-07, 6.59E-07 ) 6.10E-07 j 4.45E-07 Diued Actwey I
l I
s h'
C. Dissolved and Entrained Gases i
1.
Total Activey ci 9.91 E-04 3.25E-03 j 5.71E-03 ; 9.95E-03 9
Released I
(
2 Average Diluted uCa/mi j 6.29E-12 l 2.38E-11 j 3.80E-11 l 2.24E-11 Actwry I.
I i
t D. Gloss Alpha l
N/D
}
N/D l
N/D N/D 1.
Total Actuey ci Reieased i
No Activity Detected l
E. Volume volume I,1.13E+06 j 3.02E+06 i
1.
Reieased Waste U ers ' 8.37E+05, 1.05E+06 i
I 2.
Douton volume uers 4.85E+0F 5.51E+09 6.17E+ 09 1 1.65E+10 During Releases 1.58E+11 l 1.37E+ 11 ; 1.50E+11 l 4.44E+11 3 Dituton volume u ers I
l Dunng Penod t
N/D = Not Detected I
[
I i
i i
l 4
i f
Table 2.3-1 Millstone Unit No. 3 Liquid Effluents-Release Summary l
i Second Quarter 1993
[
Units Apnl l
May l
June l
Total i
t A. Fission and Activation Products 1.
Total ActMty Cl 1.74 E-01 2.22E-02 5.01 E-02 2.46E-01 Released 2.
Average Penod uCi/mi 1.21 E-09 1.40E-10 3.30E-10 l 5.42E-10 Diluted Actrvity i
t B. Tritium 1.
Total Actwty l Cl 1.05E+02 1.94 E+01 3.28E+01 1.57E+ 02 ReWased l
?
2.
Average Pered j uCi/mi 7.27E-07 1.22E-07 2.16E-07 3.46E-07 Diluted Activity I t
I C. Dissolved and Entrained Gases j
1.
Total Actmty Cl 1.57E-03 4.29E-03 8.05E-03 1.39E-02 Released 2.
Average Diluted uCani 1.08E-11 l 2.71E-11 5.31 E-11 3.06E-11 Activity 1
D. Gross Alpha l
1.
Total Actway C#
N/D l
N/D i
N/D l
N/D Rekased No Activity Detected i
r E. Volume 1.
Released Waste Liters 1.35E+06 l 1.23E+06 1.74 E+ 0S 4.32E+06 votume 2.
Diluten volume Leers 7.10E+ 09 6.04E+0F f 8.49F+09 2.16E+ 10 3
Dunng Releases 3 Dilu*en volume utes 1.45E+ 11 1.59E-iO 4.55E+11 i
l Dunng Perod N/D = Not Detected
)
e i
i
Table 2.3-2
[
Millstone Unit No. 3 Liquid Effluents - Continuous - SGBD
<< No Activity Detected >>
Nuclides First Quarter 1993 Released Units January l February l March l
Total A. Fission & Activation Products l Ci I
[
Total Activity l Ci I i
i i
B. Tritium lH-3 i Cl i i
l i
l C. Dissolved & Entrained Gases I - Ci i I
t Total Activity l Ci I i
I i
D. Gross Alpha l Gross Alpha 1 Ci '
I i
l i
I l
I I
I l
i
Table 2.3-2 Millstone Unit No. 3 Liquid Effluents - Continuous - SGBD
<< No Activity Detected >>
Nuclides Second Quarter 1993 Released Units Apnl l
May l
June l
Total A. Fission & Activation Products
! Ci I I
I i
Total Activity 1 Ci i i
i B. Tritium lH-3 i Ci i I
I l
l C. Dissolved & Entrained Gases l Ci i i
l l
Total Activity i Ci i I
l I
D. Gross Alpha l Gross Alpha l Ci t I
i l
k k
P j
i c
-e
Table 2.3-3 Mi!! stone Unit No. 3 Liquid Effluents - Batch - LWS I
Nuclides First Quarter 1993 Released Units January l February l March l
Total A. Fission & Activation Products Ag-110m Ci 3.33E-04 1.19E-03 9.53E-04 2.48E-03 Ba-140 Ci 5.64E-06 5.64E-06 Ba-142 Ci 5.02E-05 5.02E-05 Be-7 Ci 1.15E-04 1.32E-04 2.47E-04 Co-57 Ci 4.06E-05 4.9BE-05 9.04E-05 Co-58 Ci 3.92E-03 3.4BE-03 2.63E-03 1.00E-02 Co-60 Ci 4.10E-03 1.83E-02 2.72E-02 4.96E-02 Cr-51 Cl 1.15E-04 1.15E-04 Cs-134 Ci 4.25E-03 4.68E-03 5.04E-04 9.43E-03 Cs-137 Ci 6.97E-03 8.15E-03 9.9!,E-04 1.01E-02 Cs-138 Ci 9.87E-05
. 9.87E-05 Fe-55 Ci 8.37E-04 2.62E-03 1.46E-03 1 4.92E-03 1-131 Ci 4.98E-05 1.79E-04 4.47E-05 2.74E-04 l-133 Ci 2.65E-05 8.87E-05 1.19E-05 1.27E-04 Mn-54 Ci 7.73E-04 2.71E-03 3.66E-03 7.14E-03 Na-24 Cl 2.52E-04 1.05E-03 1.30E-03 Nb-95 Ci 3.20E-04 3.20E-04 4
Nb-97 Ci 2.08E-05 4.05E-05 1.50E-03 1.56E-03 Pr-144 Ci 5.69E-03 5.69E-03 i
Sb-122 Ci 4.90E-04 4.9BE-04 1.09E-05 9.99E-04 Sb-124 Ci 5.42E-05 8.31 E-06 6.25E-05 Sb-125 Ci 3.75E-03 5.04E-03 3.35E-03 1.21 E-02 Sr-89 Ci 8.08E-04 8.08E-04 Te-132 Ci i 1.66E-06 1.66E-06 Total Activity l Ci 1 2.60E-02 1 5.50E-02 1 4.26E-02 i 1.24 E-01 B. Tritium lH-3 I Ci i 1.58E+01 1 9.02E+01 l 9.16E+01 1 1.98E+02 l
{
C. Dissolved & Entrained Gases Kr-85m Ci 3.65E-05 3.30E-06 1 3.98E-05 Xe-133 Ci 5.4 0E-O ',
1.32E-03 9.76E-04 [~~2.84E-03 Xe-135 Ci 4.32E-04 1.26E-03 1.32E-03 3.01 E-03 Xe-135m Ci 1.85E-05 6.81 E-06 2.53E-05 Xe-138 Ci 5.32E-05 5.32E-05 Kr-85 Ci 5.85E-04 3.40E-03 3.99E-03 Total Activity i Ci i 9.91E-04 1 3.25E-03 1 5.71E-03 I 9.95E-03 D. Gross Alpha l Gross Alpha i Ci i i
i l
Table 2.3-3 Millstone Unit No. 3 Liquid Effluents - Batch - LWS Nuclides 0*cond Quarter 1993 Released Units April l
May l
June l
Total A. Fission & Activation Products Ag-110m Ci 3.55E-03 1.26E-03 4.81 E-03 Ba-140 Ci 7.54E-05 7.54E-05 Co-57 Ci 3.46E-04 3.50E-07 3.46E-04
^
Co-58 Ci 1.53E-02 6.75E-03 1.52E-02 3.73E-02 Co-60 Ci 1.09E-01 6.29E-03 5.97E-03 1.21 E-01 Cr-51 Ci 3.26E-04 ! 4.83E-04 4.5BE-03 5.39E-03 Cs-134 Ci { 2.20E-04 4.57E-04 1.74 E-03] 2.42E-03 Cs-137 Ci t 8.59E-04 8.62E-04 3.84E-03 I 5.56E-03 Fe-55 Ci i 1.11 E-02 2.71E-03 I 8.53E-03 T23E-02 Fe-59 Ci l 1.55E-04 1.55E-04 l-131 Ci i 7.04E-05 3.77E-04 6,.23E-04 1.07E-03 1-133 Ci 4.31 E-05 2.27E 04 4.95E-04 7.65E-04 l-135 Cl 4.09E-05 4.09E-05 La-140 Ci 7.85E-05 7.85E-05 Mn-54 Ci 1.43E-02 I 1.50E-03 2.45E-03 1.83E-02 Mo-99 Ci 1.30E-05 1.30E-05 Nb-95 Ci 1.38E-05 2.02E-05 6.70E-04 7.04E-04 Nb-97 Ci 5.82E-03 2.21 E-04 1.78E-03 7.82E-03 Ru-106 Ci 2.74E-03 2.96E-04 3.04E-03 Sb-122 Ci i 2.48E-05 1.04 E-04 1.29E-04 Sb-125 Ci 9.52E-03 l 1.91E-03 2.37E-03 1.38E-02 i
Sn-113 Ci j
1.94 E-05 1.94 E-05 Sn-117m Ci 1.54E-05 1.54 E-05 Sr-87m Ci 2.15E-06 2.15E-06 Sr-89 Ci 9.31E-05 I 9.31 E-05 Sr-92 Ci 2.71E-05 l 2.71 E-05 Tc-99m Ci 1.40E-05 1.40E-05 Te-132 Cl j
1.30E-06 1.30E-06 t
Zn-65 Ci 6.79E-04 i 2.2SE-05
! 7.02E-04 Zr-95 Ci l I
1.96E-04 i 1.96E-04 Total Activity i Ci ! 1.74 E-01 1 2.22E-02 ! 5.01E-02 ! 2.46E-01 B. Tritium lH-3
! Ci i 1.05E+02 1 1.94 E+ 01 1 3.28E+01 1 1.57E+02 l C. Dissolved & Entrained Gases Xe-131m Ci 9.46E-05 9.46E-05 Xe-133 Ci 6.42E-04 1.83E-03 3.10E-03 5.57E-03 Xe-133m Ci 7.55E-06 7.55E-06 Xe-135 Ci 9.25E-04 2.40E-03 I 4.84E-03 8.17E-03 Xe-135m Ci l 6.40E-06 6.40E-06 Xe-137 Ci 6.43E-05 i i 6.43E-05
Table 2.3-3 Millstone Unit No. 3 Liquid Effluents - Batch - LWS Nuclides Second Quarter 1993 Released Units Apri!
l May l
June l
Total C. Dissolved & Entrained Gases (Continued) l Total Activity 1 Ci : 1.57E-03 t 4.29E-03 l 8.05E-03 i 1.39E-02 !
D. Gross Alpha l Gross Alpha i Ci i l
i i
i
{
l
Table 2.3-4 Millstone Unit No. 3 Liquid Effluents - Batch - CPF WN Sumps
<< No Activity Detected >>
Nuclides First Quarter 1993 Released Units January l February l March l Total A. Fission & Activation Products I Cl i I
I Total Activity l Ci 1
I B. Tritium lH-3 i Ci t i
I i
l C. Dissolved & Entrained Gases l Ci 1 i
i Total Activity 1 Ci l I
i i
D. Gross Alpha l Gross Alpha l Ci l i
i l
Table 2.3-4 r
Millstone Unit No. 3 Liquid Effluents - Batch - CPF WN Sumps
<< No Activity Detected >>
Nuclides Second Quarter 1993 Released Units Apnl l
May l
June l
Total A. Fission & Activation Products i Ci i I
i Total Activity 1 Ci i i
I B. Tritium lH-3 i Ci !
I t
I l
5 C. Dissolved & Entrained Gases
! Ci I I
I i
Total Activity i Ci t i
I D. Gross Alpha l Gross Alpha ! Ci !
I i
l l
?
1 i
n d
t i
l I
t
Table 2.3-5 Mi!! stone Unit No. 3 Airbome Effluents - Release Sum..lary i
First Quarter 1993 Units January l February l March l Total A. Fission & Activation Gases 1.
Total Activtry Cl N/D
[
N/D l
N/D l
N/D Released No Activity Detected 2.
Average Penod uCVsec f
Release Rate i
B. lodine-131 1.
Total Actnnty j Ci 3.37E-05 ! 2.43E-05 l 2.95E-05 ! 8.75E-05 Released I
l l
2 Average Pened uCesee 1.09E-05 i 1.00E-05 l 1.22E-05] 1.10E-05 Reiease Rate l
i C. Particulates 1.
Total Actety Ci N/D 3.12E-06 7.15E-06 1.03E-05 Released 2 Average Diluted uCesec 1.29E-06 l 2.96E-06 1.29E-06 Activity i
D. Gross Alpha 1.
Total Actrvty Ci 1.33E-08 j 4.41E-07 4.63E-07 9.17E-07 Released l
1 E. Tritium ci N/D l
N/D 2.69E+01 l 2.69E+01 1.
Total Activey l
i Released l
l
[
2.
Average Penad UCvsec 1.11 E+01 3.39E+00 Release Rate 2
N/D = Not Detected l
t L
?
i
Table 2 4 i
Millstone Ui... 40. 3 Airbome Effluents - Release Summary i
1 Second Quaner 1993 j
Units Apnl l
May l
June l
Total i
i A. Fission & Activation Gases a
1.
Tdal ActWy Ci N/D 2.93E+01 N/D 2.93E+ 01 Rekased
- 2. Average Penod uCusec 1.21 E+ 01 3.72E+ 00 Rekase Rate B. lodine-131 1.
Total Activey Ci 1.42E-05, 1.86E-05 j 3.78E-05 ; 7.07E-05 Remased i
2.
Average Perod uCusec 4.69E-06 : 7.70E-06 1.56E-05 [ 8.9BE-06 Reiease Rate l
l C. Particulates 1.
Tdal Actnnty Ci 1.01 E-05 5.45E-06 1.61 E-05 3.17E-05 Released 2,
Average DMed uCesec ! 3.35E-06 I 2.25E-06 6.65E-06 j 4.02E-06 Actrvey l
l 4
D. Gross Alpha 1.
Tdal Actrvey Ci l N/D l 1.48E-08 1.10E-07 1.25E-07 Released i
E. Tritium N/D j
N/D l
N/D i
N/D 1.
Tdal Actwty l' Ci 1
Released No Activit:r Detected i
2.
Average Pered UCksec j
Reiease Rate I
N/D = Not Detected i
I I
a t
I t
I
Table 2.3-6 Millstone Unit No. 3 Airbome Effluents-Mixed Continuous - Normal Ventilation h
Nuclides First Quarter 1993 Released Units January l February l March l Total A. Fission & Activation Gases I Ci i t
1 1
Total Activity I Ci t I
i I
B. Iodines 1-131 Ci 3.37E-05 2.43E-05 1 2.95E-05] 8.75E-05 1-133 Ci 6.20E-05 5.08E-05 ! 6.22E-05 i 1.75E-04 Total Activity i Ci I 9.57E-05 1 7.51E-05 I 9.17E-05 1 2.63E-04 t
C. Particulates l-131 Ci I
Cs-134 Ci l 6.93E-06 6.93E-06 Ru-103 Ci 2.70E-06 i 2.70E-06 Total Activity 1 Ci 4 i 2.70E-06 I 6.93E-06 1 9.63E-06 D. Gross Alpha l Gross Alpha I Ci t i 4.32E-07 1 4.32E-07 I 8.64E-07 l E. Tritium lH-3 i Ci i l
I 2.69E+01 1 2.69E+01 l l
i I
i I
1 I
Table 2.3-6 Millstone Unit No. 3 Airtome Effluents - Mixed Continuous - Normal Ventilation Nuclides Second Quarter 1993 Released Units April l
May l
June l
Total A. Fission & Activation Gases Xe-135 i Ci 1 i 2.93E+01 I i 2.93E+01 Total Activity i Ci I i 2.93E+01 1 1 2.93E+01 B. todines 1-131 Ci i 1.41 E-05 1.86E-05 I 3.78E-05 7.05E-05 l-133 Ci i 1.71E-05 5.11E-05 i 6.55E-05 1.34 E-04 Total Activity i C.
! 3.12E-05 < 6.97E-05 i 1.03E-04 1 2.04 E-04 C. Particulates 1-131 Ci 1 Be-7 Ci J l 1.14E-05 1.14 E-05 Ce-144 Cl i 9.15E-06 i l
9.15E-06 Co-58 Ci i I
l 3.98E-06 i 3.98E-06 Sb-125 Ci i I 5.30E-06 i i 5.30E-06 Total Activity l Ci i 9.15E-06 i 5.30E-06 i 1.54E-05 1 2.98E-05 D. Gross Alpha l Gross Alpha I Ci i I
i l
E. Tritium lH-3 i Ci t I
i i
l P
r i
Table 2.3-7 Millstone Unit No. 3 Airborne Effluents - Mixed Continuous - ESF Building Ventitation t
i Nuclides First Quarter 1993 Released Units January l February l March ]
Total A. Fission & Activation Gases i
l i Ci t i
1 l
Total Activity 1 Ci i i
i B. lodines 1-131 Ci !
4 l
r 1-133 Cil 7
i i
Total Activity 1 Ci i i
C. Particulates i
1-131 Ci i i
^
Cs-137 Cil 4.59E-08 4.59E-08 4.16E 07 ! 1.76E-07 5.92E-07' T
Be-7 Ci i Total Activity i Ci I
! 4.16E-07 i 2.22E-07 i 6.3BE-07 D. Gross Alpha l Gross Alpna l Ci 1.33E-08 8.90E-09. 3.12E-08 5.34E-08 l E. Tritium l
lH-3 I Ci i i
i l
r
[
l I
s
Table 2.3-7 Millstone Unit No. 3 Airborne Effluents - Mixed Continuous - ESF Building Ventilation Nuchdes Second Quarter 1993 Released Units April l
May l
June l
Total A. Fission & Activation Gases
! Ci i 1
Total Activity i Ci i i
i B. lodines 1-131 t Ci l 1.18E-07 1 3.70E-08 !
i 1.55E-07 l-133 i Ci i 1.46E-07 i 1.45E-07 l i 2.91 E-07 Total Activity i Ci i 2.64E-07 6 1.82E-07 !
i 4.46E-07 C. Particulates 1-131 1 Ci l I
i j 9.66E-08 Co-58 Ci j 9.66E-08
_ 6.92E-07 i 1.73E-06 Be-7 Ci I 8.89E-07 1.45E-07 I Sn-117m Ci I
! 2.02E-08 l 2.02E-08 Total Activity i Ci ! 9.86E-07 i 1.45E-07 1 7.12E-07 1 1.84 E-06 D. Gross Alpha l Gross Alpha i Ci l 1.48E-08 t 1.10E-07 ; 1.25E-07 l E. Tritium lH-3 1 Ci !
I f
1 l
t 9
a b
Table 2.3-8 Millstone Unit No. 3 Airbome Effluents - Mixed Batch - Containment Drawdown
<< No Activity Detected >>
Nuclides First Quarter 1993 Released Units January l February l March l
Total A. Fission & Activation Gases i Ci i i
i Total Activity i Ci i i
i i
B. lodines 1-131 Ci l l
l 1-133 Ci i i
Total Activity l Ci l i
i C. Particulates 1-131 l Ci i i
i Ci i i
Total Activity 1 Ci i
I i
D. Gross Alpha l Gross Alpha I Ci i l
l E. Tritium lH-3 1 Ci i i
i l
l l
i 1
i i
1 4
i I
s
i Table 2.3-8 Millstone Unit No. 3 Airbome Effluents - Mixed Batch - Containment Drawdown i
<< No Activity Detected >>
Nuclides Second Quarter 1993 Released Units April l
May l
June l
Total A. Fission & Activation Gases i Ci i i
i i
Total Activity i Ci l i
i I
l B. lodines l-131 Ci l
I 1-133 Ci i
Total Activity 1 Ci I i
i i
C. Particulates 1-131 Ci !
J l
Ci i i
i Total Activity i Ci i i
l I
D. Gross Alpha l Gross Alpha i Ci l i
i I
l E. Tritium lH-3 i Ci i i
i l
c
?
r
~i
t Table 2.3-9 l
Millstone Unit No. 3 l
Airbome Effluents - Mixed Batch - Containment Purges i
<< No Activity Detected >>
Nuclides First Quarter 1993 Released Units January l February l March l
Total A. Fission & Activation Gases i Ci i i
i i
Total Activity i Ci 1
i 1
B. lodines 1-131 Cij l
1 1-133 Ci !
i Total Activity i Ci i i
i l
4 C. Particulates l-131 Ci {
I Cl I i
Total Activity i Ci i i
t i
D. Gross Alpha j
l Gross Alpha i Ci I i
i l
E. Tritium lH-3 i Ci i i
t l
l i
I 1
h i
k i
[
t i
Table 2.3-9 Millstone Unit No. 3 Airbome Effluents - Mixed Batch - Containment Purges t
<< No Activity Detected >>
Nuclides Second Quaner 1993
[
Released Units April l
May l
June l
Total A. Fission & Activation Gases j
l Ci i i
f I
Total Activity i Ci I I
I i
B. todines 1-131 Ci
__j i
l l-133 Ci 1
Total Activity i Ci i i
i C. Particulates ll131 l Ci i j
I Ci !
Total Activity i Ci i l
I i
t D. Gross Alpha l Gross Alpha i Ci i i
i I
l E. Tritium lH-3 i Ci i i
i l
F i
f e
P l
i i
i
i 3.0 Radioactive Solid Waste Summaries of solid waste shipment for each unit are given in the attached Tables. The principal radionuclides were considered to be those included on the shipping manifest.
Solidification Agent (s):
Portland 1 Cement Types and Typical Volumes of Containers:
55 gallon steel drum DOT 17-H contaitier 202 ft3 steel container 87 ft3 LSA steel box 132 ft3 Polyethylene high integrity container 173 ft3 Polyethylene high integrity container 202 ft 3 Polyethylene high integrity container 92.7 ft steel box 3
h t
l 1
9 i
a f
I Page 1 of 14 Effluent and Waste Disposal Semiannual Report Solid Waste and Irradiated Component Shipments I
Stillstone Unit 1 January 1,1993 -June 31,1993 6-Month Period Estimated Total
- 1. Type of Waste Disposition Units Totals Error %
3 a) Spent Resin, Filter Sludge, (CNS!)
m 3.09E+01 Evaporator Bottoms, Etc.
Burial Ci 3.14E-01 25 %
+
3 (SEG) m 0
Supercompaction Ci 0
N/A 3
8 07E-00 b) Dry Compressible Waste.
(CNSI) m Cont minated Equipment, Etc.
Burial Ci 2.17E-01 25"i 3
(SEG) m 0
Supercompaction Ci 0
N/A (SEG) f 3
Burial m
4.41E-01 CNSI Ci 1.29E-03 25'fi 3
(Quadrex) m 2.27E-01 Decontamination Ci 1.34E-02 25a'.
j (Cuadrex) t 3
l Burial m
1.71E-02 CNSI Ci 2.30E-05 25*h 3
c) Irradiated Components, Control (CNSI) m 0
Rods. Etc.
Burial C.i 0
,3/A l
r I
t b
(
i i
Page 2 of 14 i
t
- 2. Estimates of Major Nuclide Composition (By Type of Waste) a) Spent Resin, Filter Sludges, Evaporator Bottoms s
Millstone to CNSI for Burial Nuclide l
% of Total 0.03 %
P
~
H-3 0.36 %
C-14 0.82 %
Cr-51 3.60 %
Mn-54 40.45%
Fe-55 l
0.12 %
Co-58 9.39 %
Co-60 f
0.73 %
Ni-63 f
35.67 %
Zn45 0.01%
St-89 0.04 %
Sr 90 0.02 %
Ag-110m l-131
<001%
8.60 %
Cs-137 La-140
<0 01%
Cc-141
<0.01%
<0.01%
Np-237 Pu-238
<001%
f Pu-239
<0.01%
j I
0.03*i Am-24.?
0.04 %
Pu-241 Cm-242
<0.01%
Pu 242
<0.01%
0.05%
Cm-244 Millstone to SEG for Supercompachon f
Nuclide
% of Total f
None N/A r
l i
I f
i e
h i
F i
3 i
I
t t
Page 3 of 14 l
b) Dry Compressible Waste, Contaminated Equipment, Etc.
l t
Millstone to CNSI for Burial Nuclide
% of Total H-3 0.57 %
t Cr-51 1.41 %
(
f Mn-54 5.27 %
Fe-55 69.23 %
Co-60 16.68 %
Zn45 4.46 %
Pu-241 2.38%
i Millstone to SEG for Supercornpaction Nuclide
% of Total None N/A
-i i
SEG to CNSI for Burial I
f Nuclide
% of Total i
H-3 10.39 %
Cr-51 0.25 %
l Mn-54 0.76 %
i Fe-55 40.47 %
f Co 58 0.82 %
Co-60 21.16 %
Ni-63 6.49%
I Zn-65 0.44 %
Cs-134 4.65 %
Cs-137 14.11%
Pu-241 0.I8%
l Millstone to Quadrex for Decontaminanon i
Nuclide
% of Total I H-3 15.82 %
Cr-51 0.97 %
I Mn-54 1.56 %
l Fe-55 47.00?s Co-58 1.94 %
Co-60 13.21 %
Ni-63 4.21%
Zn-65 0.94 %
Nb-95 0.16 %
Zr-95 0.08 %
-l Cs-134 4.83 %
f Cs-137 9.26 %
l i
1
Page 4 of 14 Quadrex to CNSI for Burial Nuclide
% of Total H-3 9.83 %
i Cr-51 0.78 %
i Mn-54 1.57 %
}
Fe-55 50.43 %
I Co-58 1.97*'o Co40 15.00 %
Ni-63 4.35 %
Zn-65 1.17 %
+
Cs-134 4.74 %
Cs-137 9 91 %
l c) Irradiated Components, Control Rods, Etc.
Millstone to CNSI for Burial Nuclide
% of Total None N/A t
i i
i i
h I
l r
s 5
e
Page 5 of 14
- 3. Solid Waste Dts>osition Number of Shipments Mode of Transportation Destination Chem-Nucicar Services. Inc.
5 Truck (Sole Use Vehicle)
Barnw ell. SC Scientific Ecology Group O
Truck (Sole Use Vehicle)
Oak Ridge. TN Quadrcx 1
Truck (Sole Use vehicle)
Oak Ridge. TN 6
i s
l b
i
1 L
Page 6 of 14 Effluent and Waste Disposal Semiannual Report Solid Waste and Irradiated Component Shipments Millstone Unit 2 January 1,1993 - June 31,1993 6-Month Period Estimated Total
- 1. Type of Waste Disposition Units Totals Error, %
3 3.40E+00 i
a) Spent Resin, Filter Sludge.
(CNSI) m Evaporator Bottoms. Etc.
Burial Ci 1.9]E+00 25 %
3 (SEG) m 0
Supercompaction Ci 0
N/A 3
4 84E-01 b) Dry Compressible Waste.
(CNSI) m Contaminated Equipment. Etc.
Burial Ci 4 52E-01 25 %
3 0
(SEG) m Supercompaction Ci 0
N/A (SEG) 3 Burial m
3.84E-00 CNSI Ci 1.28E-02 25 %
(Quadrex) m 1.76E+02 3
Decontamination Ci 7.5SE-02 25 %
(Quadrex) 3 Burial m
Ci 2.19E-03 25 %
3 c) Irradiated Components, Control (CNSI) m 0
Rods, Etc.
Burial Ci 0
N/A J
i I
I 1
Page 7 of 14 -
i 1
- 2. Estimates of Major Nuclide Composition (By Type of Waste) t
?
a) Spent Resin. Filter Studges. Evaporator Bottoms 4
Millstone to CNSI for Burial
)
Nuclide
% of Total H-3 0.40 %
C-14 5.11 %
j Cr-51 0 60 %
Mn-54 0.78 %
l Fe-55 20.51 %
Co-57 0.07 %
Co-58 6.73 %
Co-60 45.65 %
Ni-63 10.42 %
~
r St-89
<001%
i, Sr-90 0.04 %
Nb-95 1.01 %
Zr-95 0.68 %
j 2
Tc-99 0.58 %
Ru-103 0.12 %
Ru-106 2.62 %
Ag-110m 0.55 %
Sb-125 1.14 %
1 Cs-134 0.17 %
Cs-137 1.59 %
Ce-144 0.32 %
Pb-210 0.77 %
Np-237
<0.01%
<0.01%
<0.01%
<0.01%
Pu-241 0.15 %
Cm-242
<0.01%
Pu-242
<0.01%
~
Cm-244 l<0.01%
Millstone to SEG for Supercompaction i
Nuclide
% of Total None N/A j
i 1
i l
6 i
4 i
i J
Page 8 of 14 I
b) Day Compressible Waste, Contaminated Equipment, Etc.
Millstone to CNSI for Burial Fe-55 20.24 %
Nuclide
% of Total H-3 0.72 %
I Co-58 1.40 %
Co-60 30.92 %
Ni-63 10.79 %
Cs-134 10.42 %
Cs-137 25.51 %
f Millstone to SEG for Supercompaction l
r Nuclide
% of Total
[
None N/A SEG to CNSI for Burial j
Nuclide
% of Total l
H-3 12.50 %
[
Cr-51 0.30 %
Mn-54 0.94 %
(
Fe-55 31.25 %
.j Co-58 1.09 %
i Co-60 24.22 %
{
Ni-63 7.42 %
Zn-65 0 53 %
Cs-134 6.17 %
Cs-137 15.63 %
-t Pu-241 0.21%
i Millstone to Quadrcx for Decontamination Nuclide
% of Total H-3 1175%
Cr-51 0.92 %
Mn-54 1.59 %
Fe-55 47.22 %
l Co-58 1.79 %
Co-60 13 46 %
Ni-63 4.25 %
f Zn-65 1.00 %
Nb-95 0.09 %
i Zr-95 0.05 %
i Cs-134 4.70 %
i
.C.s-137 9.19 %
L i
i
.I f
1 i
I Page 9 of 14 Quadrex to Ci 51 for Burial I
s
.I a
Nuclide
% of Total t
11-3 16.48 %
Cr-51 0 08 %
Mn-54 1,76 %
i Fc-55 55.25 %
t Co-58 0.29 %
Co40 16.80 %
j Ni43 2.68 %
Zn-65 0.99 %
Cs-134 1.35%
Cs-137 4.25%
i l
c) Inadiated Components. Control Rods. Etc.
.)
e Millstone to CNSI for Burial i
Nuclide
% of Total l
None N/A l
l l
1 l
t
-i.
t j
9
+
i f
1 I
l l
3 l
I q
Page 10 of 14 i
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination Chem-Nuclear Senices,Inc-4 Truck (Sole Use Vehicle)
Barnwell SC Scientific Ecology Group 0
Truck (Sole Use Vehicle)
Oak Ridee. TN Quadrex 6
Truck (Sole Use Vehiclet Oak Ridee. TN l
k
1 J
1 1
Page 11 of 14 I
EIT1uent and Waste Disposal Semiannual Report Solid Waste and Irradiated Component Shipments 1
Millstone Unit 3 i
January 1,1993 - June 31,1993 6-Month Period Estimated Total
- 1. Type of Waste Disposition Units Totals I rcr, %
3 a) Spent Resin, Filter Sludge, (CNSI) m 0
Evaporator Bottoms. Etc' Burial Ci 0
N/A f
3 l
(SEG) m 0
Supercompaction Ci 0
N/A 3
b) Dry Compressible Waste, (CNSI) m 2.69E40 Contaminated Equipment, Etc.
Burial Ci 9.52E-03 25 6 3
(SEG) m 0
Supercompaction Ci 0
N/A l
(SEG)
Burial m
9.10E-02 l
3 CNSI Ci 3.2 ' E-04 25 %
(Quadrex) m 100E41 l
3 Decontamination Ci 1.02E-02 25?'o I
l (Quadrex) 3 Burial m
5.73E-03 CNSI Ci 6 43E-06 25"b
[
c) Irradiated Components, Control (CNSI) m 0
3 Rods. Etc.
Burial Cl 0
N/A I
J F
P
t l
i Page 12 of 14 i
- 2. Estimates of Major Nuclide Composition (By Type of Waste) a) Spent Resin, Filter Studges, Evaporator Bottoms Millstone to CNSI for Burial i
Nuclide
% of Total None N/A i
Millstone to SEG for Supercompaction
!4 Nuclide
% of Total None N/A
~
i i
b) Dry Compressible Waste, Contaminated Equipment. Etc.
t Millstone to CNSI for Burial i
Nuclide
% of Total H-3 2.73 %
Cr-51 2.61 %
Mn-54 1 75 %
Fe-55 59.36 %
Co-58 6.06%;
Co40 5.3." ' '
Ni-63 2.44 %
Nb-95 1.94 %
Zr-95 0.97 %
Cs-134 8.16 %
Cs-137 8 62 %
i Millstone to SEG for Supercompaction r
Nuclide
% of Total None N/A 4
?
4 SEG to CNSI for Burial j
l Nuclide
% of Total H-3 9.84 %
Cr-51 0.13 %
I Mn-54 0 40%
Fe-55 40.81 %
Co-58 0.76 %
[
Co40 20.78 %
Ni43 6 64 %
Zn45 0 23 %
Cs-134 4.77 %
Cs-137 15.45 %
Pu-241 0 09 %
i
+
e 2
i Pagc I3 of 44 I
Millstone to Quadrcx for Decontarnination Nuclide
% of Total i
H-3 13.91 %
Cr-51 1.09 %
f Mn-54 1.60 %
Fe-55 48.45%
Co-58 2.24 %
Co-60 12.84 %
Ni-63 4.14 %
l Zn-65 0.89 %
i Nb-95 0.28%
i Zr-95 0.14%
Cs-134 5.09 %
Cs-137 9.32 %
Quadrcx to CNSI for Burial i
Nuclide
% of Total H-3 9.82 %
Cr-51 0.78 %
Mn-54 1.56 %
[
Fe-55 50.59 %
Co-58 1.97 %
I Co-60 15.12 %
Ni-63 4.37 %
Zn-65 1.17 %
l Cs-134 4.76 %
Cs-137 9.95 %
i c) Irradiated Components. Control Rods. Etc.
Millstone to CNSI for Burial Nuclide
% of Total None N/A i
1 I
e
Page 14 of 14
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination Chem-Nuclear Senices Inc.
I O
Truck (Sole Use Vehicle)
Barnwell, SC Scientific Ecology Group 0
Truck (Sole Use Vehicle)
Oak Ridge, TN Quadrex 0
Truck (Sole Use Vehicle)
Oak Ridee. TN i
r s
j
4.0 Measurements of Radioactivity 4.1 Gaseous Releases a.
Unit 1 Stack (1) Fission and Activation Gases Stack monitors continuously record the effluent activity and flow rate. During periods when the augmented off-gas system is not operable, the radiation monitor reading is related to pCi by off-gas sampling at the steam air ejectors and subsequent isotopic analysis. The isotopic activity at the SJAE is mathematically decayed to establish the activity in the stack using the known holdup time. During periods of augmented off-gas systern operation, samples are taken directly from the stack with a subsequent isotopic analysis.
In both cases, the calculated activity in the stack is then correlated to the monitor reading.
The isotopic concentrations at the release point are multiplied by the total stack flow to obtain total pCi release for each isotope.
l (2) todines and Particulates Charcoal cartridges and particulate filters are used to collect iodines and particulates, respectively. The filters are then i
analyzed for isotopic content using a gamma spectrometer, particulate filters are also analyzed for strontium. Isotopic concentrations are multiplied by the release flow rate to determine the total amount of activity released l
b.
Unit 2 Vent Total effluent volume from the Unit 2 Vent per month is multiplied by the isotopic concentrations as measured by gamma spectrometer Ge(Li) analysis of grab samples of gases, iodine and particulates to obtain total pCi released from the Vent.
c.
Unit 2 Containment Purges Grab samples are taken for gaseous, particulate, and iodine.
These are analyzed on Ge(Li) gamma spectrometer and concentrations computed. Computed concentrations are then multiplied by the purge volume for total pCi released.
l Tritium collection is accomplished by the gas washing bottle method. The sample is counted on a liquid scintillation counter.
Concentration is computed using worst possible case,100%
humidity. Concentration is multiplied by volume purged to give j
total pCi reteased.
f 1
a d.
Unit 2 Steam Generator Blowdown Tank Vent A decontamination factor (DF) across the steam generator blowdown tank vent has _ been determined for iodines by comparison of the results of gamma spectrometry, Ge(Li),
analysis of steam generator blowdown water and grab samples of condensed steam exiting the blowdown tank vent. This DF was then applied to the total iodine releases via the steam l
generator blowdown water to determine the iodine releases out of the blowdown tank vent. An additional factor of 0.33 was utilized to account for the fraction of blowdown volume actually flashing to steam in the blowdown tank.
j e.
Unit 3 Vent and ESF Building Vent The Unit 3 Ventilation Vent collects gas streams from the Auxiliary, Fuel, Waste Disposal, and Service Building exhausts, containment purge and gaseous waste process vent. The Unit 3 Vent is located on the roof of the turbine building and discharges 133 feet above grade. The Unit 3 ESF Building Vent j
collects gas streams from the Engineered Safety Features i
Building Ventilation System. This vent is located on the south wall and discharges 23 feet above grade. Total Effluent Volume l
per month is multiplied by isotopic concentrations from the analysis of grab samples to obtain the total activity released.
l 1
These grab samples are obtained monthly for fission gas and tritium, weekly filters for iodines and particulates, monthly composites of particulate filters for gross alpha and strontium.
f.
Unit 3 Containment Drawdown and Purge 1
Unit 3 Containment is drawn down and purged intermittently.
The drawdown is accomplished by using the containment vacuum steam jet ejector and releases through an unmonitored vent on the roof of the Auxiliary Building. The containment vacuum pump discharge, which maintains subatmospheric pressure following the initial drawdown, is released through the Unit 1 Stack. The purge is the process of discharging air from i
containment to maintain temperature humidity, pressure, concentration, etc., where air is replaced. Purges are filtered and i
normally released through th.e Unit 3 Vent but may use the Unit 1 Stack. Purges and Drawdowns are intermittent and are therefore considered batch releases. Calculated volume discharged is multiplied by isotopic concentrations from the analysis of grab samples to obtain activity released.
i t
4.2 Liquid Effluents a.
Liquid Tanks There are numerous tanks which are used to discharge liquids i
containing radioactivity to the environs; they are:
i 1
l i
l
i l
Unit 1 - Decontamination Solution Tank Unit 1 - Floor Drain Sample Tanks (2)
Unit 1 - Waste Sample Tanks (2)
Unit 2 - Clean Waste Monitor Tanks (2)
Unit 2 - Aerated Waste MonitorTank Unit 3 - High Level Waste Test Tanks (2) i Unit 3 - Low Level Waste Tanks (2)
I r
Prior to release, a tank is recirculated for two equivalent tank volumes, a sample is drawn and analyzed on the Ge(Li) gamma spectrometer for individual radionuclide composition. An aliquot of the sample is composited and analyzed for H-3, Fe-55, Sr-89/90. Isotopic concentrations are multiplied by the volurne l
released to obtain the total activity released. A proportional aliquot of each discharge is retained for composite analysis for strontium and gross alpha.
b.
Unit 2 and Unit 3 Steam Generator Blowdown Grab samples are taken to steam generator blowdown water, and are analyzed by gamma spectrometry, Ge(Li). Total volume of blowdown is multiplied by the isotopic concentrations to determine the total activity released via blowdown. The calculated activity released out of the blowdown tank vent is accounted for pending the point of blowdown sampling.
j Tritium is determined through liquid scintillation counting and strontiums are analyzed by radiochemical separations and i
appropriate counting techniques.
4.3 Estimate of Errors a
Estimates of errors associated with radioactivity measurements were t
made usmg the following guidelines:
l Sampling / Data 10 % Variation in data collection i
Collection t
Calibration 5% Calibration to NBS standards Sample Counting 10 % Maximum error for counting statistics Flow & Level 10 % Maximum error for release volumes Measurements i
4.4 Batch Releases Liquid Unit 1 Unit 2 Unit 3 i
- a. Number of Batches 146 229 289
- b. TotalTime(Minutes) 10,729 41,220 20,713
- c. MaximumTime(Minutes) 126 629 225
- d. AverageTime(Minutes) 73 180 72
- e. MinimumTime(Minutes) 45 5
5
- f. Average Stream Flow Not Applicable-Ocean Site i
e Unit 2 Unit 2 Unit 3 Unit 3 Airborne Purge WGDT Purge Drawdown
- a. Numberof Batches 0
4 0
0
- b. TotalTime(Minutes) 0 1,042 0
0
- c. MaximumTime(Minutes) 0 430 0
0 I
- d. AverageTime(Minutes) 0 260 0
0
- e. MinimumTime(Minutes) 0 139 0
0 t
4.5 Abnormal Releases - None l
t s
L l
I f
1 I
F l
r f
5.0 Changes t
The following change to the REMM/ODCM/PCP was issued during this report of January 1 - June 30,1993.
P G
r
'i I
P l
I f
I f
t 6
i Y
I I
i
i Dsc5 V Wr. 5?45' 50-336 50-423 License :!cs. DPR-21 i
RADIOLOGICAL EFFLUENT I,
MONITORING AND OFFSITE DOSE i
CALCULATION MANUAL AND PROCESS CONTROL PROGRAM i
I MILLSTONE UNIT NOS.1,2, & 3 l
i Northeast Nuclear Energy Company i
e
?
d May 1993 Revision 5 r-
SECTION l RADIOLOGICAL EFFLUENT MONITORING MANUAL FORTHE MILLSTONE NUCLEAR POWER STATION UNIT NOS.1,2, & 3 DOCKETNO. 50 245 50-336 50-423 l
May 1993 Revision 4
Rev. 4 TABLE E-1 MILLSTONE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling and s
Exposure Pathway Number of Collection
[
and/or Sample Locations Frequency Type and Frequency of Analysis 1.o. Gamma Dose -
EnvironmentalTLD 17 Monthly Gamma Dose - Monthly l
1.b. Gamma Dose -
Accident TLD 22 Quarterly (a)
N/A(a) 2.
Airborne Particulate 8
Continuous Gross Beta-Weekly sampler Gamma Spectrum - Quarterly on weekly filter composite (by location), and on change individual sample if gross beta is greater than 10 times the mean of the weekly control station's gross beta results.
3.
Airborne lodine 8
Continuous 1-131 -Weekly sampler -
weekly canister change 4.
Vegetation 5
One sample Gamma isotopic on each sample near middle and one near end of grow-4 ing season 5.
Milk 6
Monthly Gamma isotopic,1-131, Sr-89 and Sr-90 on each sample 6.
Sea Water 2
Ouarterly -
Quarterly - Gamma Isotopic, and Composite of Tritium 6 weekly grab on each composite samples 7.
Bottom Sediment 5
Semiannual Gamma Isotopic on each sample l
E-5
i
.i SECTION il
.1 b
?
t OFFSITEDOSE i
i CALCULATION MANUAL I
!'i FOR THE l
f MILLSTONE NUCLEAR POWER STATION t
UNIT NOS.1,2. & 3 l
DOCKETS: No. 50-245
- i 50-336 i
50-423
.i I
l q
1.
a
)
May 1993 Revision 5 1
5/1/93 Ree. 5 t
OFFSITEDOSE CALCULATION MANUAL TABLE OF CONTENTS i
SECTION PAGE NO.
REV. N O.
DATE I
A.
INTRODUCTION A-1 2
7/1/90 i
B.
RESPONSIBILITIES B-1 2
7/1/90 C.
LIQUID DO5E CALCULATIONS
- 1. QUARTERLY-TOTAL BODY DOSE l
1 a.
Method 1 - Any Unit C-1 2
7/1/90 b.
Method 2 - Any Unit C-1 2
7/1/90
- 2. QUARTERLY-MAXIMUM ORGAN DOSE
[
a.
Method 1 - Any Unit C-1 2
7/1/90
~
b.
Method 2-Any Unit C-2 2
7/1/90
- 3. ANNUAL-TOTAL BODY DOSE C-2 2
7/1/90 I
- 4. ANNUAL-MAXIMUM ORGAN DOSE C-2 2
7/1/90
- 5. MONTHLY DOSE PROJECTIONS a.
Unit 1 C-3 2
7/1/90 b.
Unit 7. and Unit 3 C-4 2
7/1/90
- 6. QUARTERLY DOSE CALCULATIONS FOR SEMI-ANNUAL RADIOACTIVE EFFLUENT REPORT C-4 2
7/1/90 D.
GASEOUS DOSE CALCULATIONS
- 1. 10CFR20 UMITS (" INSTANTANEOUS")
4 a.
Noble Gases-All Units D-1 3
5/1/93 b.
todines, Particulates and Other-D-1 3
5/1/93 All Units D-2 3
5/1/93 D-3 2
7/1/90 1
- 2. 10CFR50 APPENDIX l-NOBLE GAS UMITS a.
Quarterly Air Dose - Method 1 All Units D-4 2
7/1/90 b.
Quarterly Air Dose - Method 2 All Units D-5 2
7/1/90 c.
Annual Air Dose - All Units D-5 2
7/1/90 T of C1
Rev.5
-l TABLE OF CONTENTS (Cont'd) i k
SECTION PAGE NO.
R EV. N O.
DATE D.
GASEOUS DOSE CALCULATIONS (CONT'DJ 3.10CFR50 APPENDIXl-IODINE AND PARTICULATE DOSES i
a.
Quarterly Doses-Unit 1 D-6 3
5/1/93 D-7 3
5/1/93 I
b.
Quarterly Doses-Unit 2 & Unit 3 D-8 3
5/1/93 D-9 3
5/1/93 l
c.
Annual Doses-All Units D-10 3
5/1/93
- 4. GASEOUS EFFLUENT MONTHLY DOSE PROJECTIONS j
a.
Unit 1 D-11 2
7/1/90 D-12 2
7/1/90 1
b.
Unit 2 D-12 2
7/1/90-c.
Unit 3 D-13 2
7/1/90 l
i
- 5. QUARTERLY DOSE CALCULATIONS FOR SEMI-ANNUAL REPORT D-13 2
7/1/90
- 6. COMPLIANCE WITH 40CFR190 D-14 2
7/1/90
)
E.
LIQUID MONITOR SETPOINT CALCULATIONS j
- 1. UNIT 1 UQUID RADWASTE EFFLUENT LINE E-1 2
7/1/90
(
- 2. UNIT 1 SERVICE WATER EFFLUENT LINE E-2 2
7/1/90 l
- 3. UNIT 2 CLEAN LIQUID RADWASTE E-2 2
7/1/90 i
EFFLUENT LINE E-3 2
7/1/90 l
- 4. UNIT 2 AERATED UQUID RADWASTE l
EFFLUENT LINE AND CPF -WASTE i
NEUT.5 UMP EFFLUENT LINE E-4 2
7/1/90 i
- 5. UNIT 2 STEAM GENERATOR BLOWDOWN E-4 2
7/1/90 l
l E. UNIT 2 CONDENSER AIR EJECTOR E-5 2
7/1/90
- 7. UNIT 2 REACTOR BUILDING CLOSED COOLING WATER E-5 2
7/1/90
- 8. UNIT 3 LIQUID WASTE EFFLUENT LINE E-6 2
7/1/90 E-7
- c. UNIT 3 REGENERANT EVAPORATOR EFFLUENT LINE E-8 2
7/1/90
- 10. UNIT 3 WASTE NEUTRAllZATION SUMP EFFLUENT LINE E-8 2
7/1/90 T of C2
Rev.5 TABLE OF CONTENTS (Cont'd)
SECTION PAGE NO.
R EV. N O.
DATE E.
LIQUID MONITOR SETPOINT CALCULATIONS (CONT'D.)
- 11. UNIT 3 STEAM GENERATOR BLOWDOWN E-8 2
7/1/90
- 12. UNIT 3 TURBINE BUILDING FLOOR DRAINS EFFLUENT LINE E-9 2
7/1/90 F.
G ASEOUS - M ONITOR S ETPOINT CALCULATIONS F-1 2
7/1/90
- 1. UNIT 1 HYDROGEN MONITOR F-1 2
7/1/90
- 2. UNIT 1 STEAM JET AIR EJECTOR OFF GAS MONITOR F-1 2
7/1/90
- 3. UNIT 1 MAIN STACK NOBLE GAS MONITOR F-1 2
7/1/90
- 4. UNIT 1 MAIN STACK SAMPLER FLOW RATE MONITOR F-2 2
7/1/90
- 5. UNIT 2 VENT NOBLE GAS MONITOR F-2 2
7/1/90
- 6. UNIT 2 WASTE GAS DECAY TANK MONITOR F-2 2
7/1/90
- 7. UNIT 3 VENT NOBLE GAS MONITOR F-3 2
7/1/90
- 8. UNIT 3 ENGINEERING SAFEGUARDS BUILDING MONITOR F-3 2
7/1/90 T of C3
- >/ I/US Rev. 5 l
TABLE OF CONTENTS (Cont'd)
LISTOFFIGURES A
l FIGURE NAME i
t FIGURE NUMBER R EV. NO.
DATE j
i G-1 Inner AirParticulate and
}
Vegetation Monitoring Stations 2
7/1/90 l
i G-2 Outer Terrestrial Monitoring Stations 2
7/1/90 G-3 Aquatic Sampling Stations 2
7/1/90 l
r i
9 l
l l
l 1
[
i 1
6 W
t k
i l
i I
T of C4 l
f
?
.><. o n Rev.5 t
TABLE OF CONTENTS (Cont'd) i i
i APPENDICES i
I R EV. NO.
DATE j
APPENDIX A Derivation of Factors for Section C.1 - Liquid Doses 2
7/1/90 APPENDIX B Derivation of Factors for Section i
C.2 - Liquid Doses 2
7/1/90 l
l APPENDIX C Liquid Dose Calculations-LADTAP 2
7/1/90.
APPENDIX D Derivation of Factors for Section D Gaseous Doses 3
5/1/93
-l l
l APPENDIX E Gaseous Dose Calculations-GASPAR 2
7/1/90 l
APPENDIX F Gaseous Dose Calculations-AIREM 2
7/1/90 i
APPENDIX G Environmental Monitoring Program Sampling l
Locations 5
5/1/93 l
j r
~h I
l i
-t f
i k
i Tof C5 8
t i
.I
~
3/ I/'.:f 3 Rev.3 D. GASEOUS DOSE CALCULATIONS D.1. 10CFR20 Limits (" Instantaneous")
a.
Instantaneous Noble Gas Release Rate Limits - All Units The instantaneous noble gas release rate limit from the site shall be:
O 0
0 s
2 3
1,100,000 290,000 290,000 Where:
Q1 = Noble gas release rate from MP1 Stack (pCi/sec)
Q2 = Noble gas release rate from MP2 Vent (pCi/sec)
Q3 = Noble gas release rate from MP3 Vent (pCi/sec)
See Appendix D for derivation of this limit.
As long as the above is less than or equal to 1, the doses will be less than or equal to 500 mrem to the total body and less than 3000 mrem to the skin.
b.
Release Rate Limit - I-131,1133, Particulates With Half Lives Greater Than 8 Days, and Radionuclides Other Than Noble Gases With Half Lives Greater Than 8 Days-All Units Release rate of I-131 from MP1 Stack -(pCi/sec) 131 0:1 =
Release rate of I-133 from MP1 Stack -(pCi/sec) 133011
=
Release rate of I-131 from MP2 Vent -(pCi/sec)*
131 0:2 =
Release rate of I-133 from MP2 Vent -(pCi/sec)*
133012
=
i Release rate of I-131 from MP3 Vent -(pCi/sec)*
131 0 3 =
Release rate of I-133 from MP3 Vent -(pCi/sec)*
1330:3 =
Ost = Release rate of tritium from MP1 Stack-(pCi/sec)
QH2 = Release rate of tritium from MP2 Vent -(pCi/sec)*
Os3 = Release rate of tritium from MP3 Vent-(pCi/ set)*
OP1 = Release rate of total particulates with half-lives greater than 8 days from the MP1 Stack (pCi/sec) l QP2 = Release rate of total particulates with half-lives greater than 8 days from the MP2 Vent (pCi/sec)
OP3 = Release rate of total particulates with half-lives greater than 8 days from the MP3 Vent (pCi/sec)
- Includes releases via the steam generator blowdown tank vent.
D-1 l
Rev. 3 (1) The r:1;cse r:te limit of I-131,1-133, end tritium from the site shcIl be:
1 i.
Method 1 l
Assuming milk animals on pasture, harvest season, and milk animals at maximum resident D/O locations:
1.171310ii + 43.5131012 + 43.5531013 +.011 1330s +.413 3302+
+.4131330:3 + 3.47x 10-7 Ost + 3.27 x 10-5 Os2 + 3.27 x 10 5 Og3 s 1 ii.
Method 2 (a) First Quarter-Inhalation doses only 5.5 x 10-4 133Q:1 + 5.1 x 10-2 131Q12 + 5.1 x 10-2 333 Qi3 + 1.33 x 10-4 r
13301 + 1.2 5 x 10-2 133Q12 + 1.25 x 10-2 333Qi34.4 x 10-8 Qg t
+ 4.2 x 10 6 0x2 + 4.2 x 10-6 Qg3 s 1 (b) Fourth Quarter -Inhalation and milk doses 1.13 1330:1 + 421310,2 + 42131013 +.01 1330:1 +.391330:2 +.39 i
133Q13 + 2.11 x 10-7 Ost + 1.98 x 10-5 Os2 + 1.98 x 10-5 og3 s 1 r
(c) If it can be verified that milk and/or vegetation doses need not be considered, use one of the above, or for Inhalation and vecetation doses only:
4.0 x 10-2 330:1 + 1.51310 2 + 1.513iOi3 + 8.53 x 10-4 333Q:1+
3.92 x 10-2 3330:2 + 3.92 x 10-2 133 0:3 + 1.8 x 10 7 Osi
+ 1.7 x 10-5 Qs2 + 1.7 x 10-5 Qg3 s 1 lii. Method 3 If it can be verified that the Appendix D.7 D/O data for milk animals is acceptable (Note: if not, see guidance in Appendix D):
(a) Second and Third Quarter-All Pathways 0.31 1310:1 + 3.2 131Q12 + 3.213 0:3 + 3.28 x 10-3 133Qit + 4 13302
+.4 1330:3 + 3.5 x 10-7 Os3 + 3.3 x 10-5 Os2 + 3.3 x 10-5 Os3 s 1 (b) Fourth Quarter-Inhalation and milk pathways 0.27131Qii + 1.7 333 0:2 + 1.7131013 + 2.56 x 10-3 133Q t + 3.86 x 10-1 133 0:2 + 3.86 x 10-1 333 0 3 + 2.1 x 10-7 Osi + 2.0 x 10-5 Os2 +
2.0 x 10-5 Og3 s 1 b
D-2
Rev.3 (2) If the d:tsil:d calculttions cre not complete for a particular quarter, use the results as determined above in Section D.2.a or D.2.b.
(3) If Dyci,2, or 3, are greater than 10 mrad or Dysi,2, or 3, are greater than 20 mrad and any corresponding quarterly dose was not calculated using Section D.2.6 - real-time meteorology, recalculate the quarterly dose using real-time meteorology.
D.3 10 CFR50 Appendix 1 - lodine and Particulate Doses Doses from tritium (for Methods 1-4 only) for Unit 1 may be neglected if the total tritium curies from the quarter are less than 500.
a.
QuarterIV Doses-Unit 1 (1) Method t - Unit 1 Determine 133C which is the total curies of I-131 and 133 i C
Step 1 which is the total curies of I-133 released in gaseous effluents from Unit 1 during the quarter.
Determine Cp which is the total curies of particulates with Step 2 half-lives greater than 8 days released in gaseous effluents from Unit 1 during the calendar quarter.
Determine Cs which is the total curies of tritium released in Step 3 gaseous effluents from Unit 1 during the quarter.
Determine Do7 which equals the quarterly thyroid dose as Step 4 follows:
133Ci + 1.13133 i + 2.0 x 10-5 CH
[
dot = 1.22 x 102 C
Determine Doo which equals the quarterly dose to the Step 5 maximum organ other than the thyroid:
Doo = 42.3 Cp + 2.0 x 10-5 Cs The maximum organ dose is the greater of dot or Doo. If it Step 6 is greater than 2.5 mrem, go to Method 2.
(2) Method 2 - Unit 1 Doses from vegetation consumption can be neglected during the 1st and 4th quarters and doses from milk consumption can be neglected during the 1st quarter. These time frames can be extended for short term releases (batch releases and weekly continuous,if necessary)if it can be verified that the milk animals were not on pasture and/or vegetation is not available for harvest. Therefore, calculate doses to the thyroid and maximum organ for pathways that actually exist. Sum pathways if necessary.
Perform Steps 1 through 3 as in Method 1, above. Then:
Step 4 i.
Inhalation Pathway 133 i + 2.6 x 10 6 Cs l
D T = 3.2 x 10 2 13tC + 7.8 x 10-3 C
O Doo = 3.2 x 10-2 Cp + 2.6 x 10-6 Cs D-6
Rev. 3 ii. V g:tstion Pcthw:y dot = 4.113tCi + 7.48 x 10-2 333Ci + 8.0 x 10-6 CH Doo = 4.9 Cp + 8.0 x 10-6 CH iii. Milk Pathway i
Ci + 1.05 333 i + 9.8 x 10 6 CH C
dot = 118133 Doo = 38 Cp + 9.8 x 10-6 Cs Sum above pathways, as appropriate (Note: sum of all three pathways is Method 7)
Step 5 - The maximum organ dose is the greater of dot or Doo. If it is greater than 2.5 mrem, go to the next method.
(3) Method 3 - Unit 1 After reviewing the existing cow and goat farms,if it can be determined i
that the 1983-1987 D/Q data is acceptable (Note: If not,see guidance in Appendix D), then fo!\\ow Method 2 above, except for iii. where milk pathway dose is:
C +.249133Ci + 9.8 x 10-6 Cs Doi = 2813t i
Doo = 8.9 Cp + 9.8 x 10-6 Cs Note:
During the 2nd and 3rd quarters also add (to the above) the Inhalation and Vegetation Pathways from Step 4 of Method 2; during the 4th quarter add Inhalation and Milk (above) only.
(4) Method 4 - Unit 1 Use the GASPAR code to determine the maximum organ dose. For the Special Location, enter the following worst case quarterly average i
meteorology as taken from Appendix D:
X/O = 6.1 x 10-8 sec/m3 D/O = 5.9 x 10-9 m-2 (Milk and Vegetation) and/or D/O = 1.4 x 10-9 m-2 (If 1983-1987 D/O data is acceptable for existing milk locations. If not,see guidance in Appendix D.)
Use the inhalation, Milk and Vegetation pathways (if applicable) in totaling the dose. If the maximum organ dose is greater than 3.8 mrem, go to Method 5.
(5) Method 5-Unit 1 Use the GASPAR code with actual locations, real-time meteorology and the pathways which actually exist at the time at those locations.
D-7
Rev.3 b.
Quart rly D*s s-Unit 2 rnd Unit 3 I
(1) Method 1 - Unit 2 and Unit 3 Determine Ci which is the total curies of I-131 and i33C Step 1 which is the total curies of I-133 in gaseous effluents from Unit 2 or 3 during the quarter.
Determine Cp which is the total curies of particulates with Step 2 half-lives greater than 8 days released in gaseous effluents from Unit 2 or 3 during the calendar quarter.
Determine Cs which is the total curies of tritium released in Step 3 gaseous effluents from Unit 2 or 3 during the calendar l
quarter.
Determine D T which equals the quarterly thyroid dose as Step 4 O
follows:
133Ci + 29.53133 i + 2.6 x 10-3 Cs dot = 3.1 x 103 C
Determine Doo which equals the quarterly dose to the Step 5 maximum organ other than the thyroid:
Doo = 1.1 x 103 Cp + 2.6 x 10 3 Cs The maximum orgart dose is the greater of dot or Doo. If Step 6 greater than 2.5 mrem, go to Method 2.
(2) Methoct 2 - Unit 2 and Unit 3 Doses from vegetation consumption can be neglected during the 1st and 4th quarters and doses from milk consumption can be neglected during the 1st quarter. These time frames can be extended for short term releases (batch releases and weekly continuous,if necessary) if it can be verified that the milk animals were not on pasture and/or vegetation was not available for harvest. Therefore, calculate doses to the thyroid and maximum organ for pathways that actually exist. Sum pathways if necessary.
Perform Steps 7 through 3 as in Method f, then:
Step 4 i.
Inhalation Pathway dot = 4.113tC + 1.0133Ci + 3.3 x 10-4 CH Doo = 4.1 Cp + 3.3 x 10-4 Cs ii. Vegetation Pathway dot = 105133Ci + 1.9133C + 1.0 x 10 3 Cs
(
Doo = 124 Cp + 1.0 x 10-3 CH iii. Milk Pathway dot = 3000133Ci + 26.6133Ci + 1.3 x 10-3 Cs l
Doo = 951 Cp + 1.3 x 10 3 Cs D-8
bl 110 Rev.3 Sum cbove pathways, es appropriate (Note: sum of all three pathways is Method 1)
Step 5 - The maximum organ dose is the greater of dot or Doo. If it is greater than 2.5 mrem, go to the next method.
(3) Method 3 - Unit 2 and Unit 3 After reviewing the existing cow and goat farms,if it can be determined that the 1983-1987 D/O data is acceptable (Note: If not, see guidance in Appendix D), then follow Method 2, above, except for lii, where the milk pathway dose is:
dot = 122131C + 1.08133 i + 1.3 x 10-3 Cs C
Doo = 40 Cp + 1.3 x 10-3 CH Note:
During the 2nd and 3rd quarters also add (to the above) the Inhalation and Vegetation Pathways from Step 4 of Method 2; during the 4th quarter add Inhalation and Milk (above) only.
(4) Method 4 - Unit 2 and Unit 3 Use the GASPAR code to determine the maximum organ dose. For the Special Location, enter the following worst case quarterly average meteorology as taken from Appendix D:
X/O = 8.1 x 10-6 sec/m3 D/O = 1.5 x 10-7 m-2 (Milk and Vegetation) and/or D/O = 6.1 x 10-9 m-2 (if 1983-1987 D/O data is acceptable for existing milk locations. If not, see guidance in Appendix D.)
As shown in Appendix D, the same meteorology can be used for both continuous and batch releases. Therefore, the program need only be run once using the total curies from all releases from Unit 2 or 3.
Use the inhalation, Milk and Vegetation pathways (if applicable) in totaling the dose. If the maximum organ dose is greater than 3.8 mrem, go to Method 5.
(5) Method 5 - Unit 2 Use the GASPAR code with the actual locations, real-time meteorology and the pathways which actually exist at the time at these locations. The code should be run separately for steam generator blowdown tank vents and ventilation releases, containment purges and waste gas tank releases.
t (5) Method 5 - Unit 3 Use the GASPAR code with the actual locations, real-time meteorology and the pathways which actually exist at these locations. The code should be run separately for ventilation, process gas, containment vacuum system, aerated ventilation and containment purges.
D-9
Rev. 3 it would also be unnecessarily restrictive to assume the worst possible mixture and use that as the limit for all situations. Therefore, a practical solution is to use a conservatively determined empirical method as given above.
3.
Section D.1.b - Release Rate Limit-lodine and Particulates Doses are calculated using the methods of NUREG-0133 dated October 1978 and NRC Regulatory Guide 1.109, Revision 1. Note that the equation of page 27 of NUREG-0133 (for all radionuclides, except tritium) has been corrected for the elemental iodine fraction, as in Regulatory Guide 1.109, Revision 1.
Since the doses are dependent on the season, (i.e., milk animals on pasture, harvest season), and the exact locations of milking animals, use three methods when performing these calculations.
Method 1 Assume milk animals are on pasture, vegetation is being harvested, and milk animals are at maximum land D/O location.
Method 2 Assume annual average X/Q and D/O as above, however:
i.
If 1st quarter, neglect vegetation and milk doses.
ii.
If 4th quarter, neglect vegetation doses.
iii. For batch releases (including weekly continuous releases, if necessary), if it can be verified that milk animals are not on pasture and/or vegetation is not being harvested, these may be neglected.
Method 3 Review existing cow and goat locations. Determine if the average of the maximum quarterly D/Q data from Appendix D.1 is acceptable to use (i.e., no milk animal likely to be more critical than the data for 1983-1987). If acceptable, use the calculated average D/Q If not, determine an acceptable D/O by averaging at least 10 quarters of l
meteorological data.
Dose formula foriodine is:
t DlQ P,
gQ, D lQ P,
,3,Q,
XIQ P,
,gQ
+
D
=
+
+
Inhalation Vegetation Milk DlQ P,
m,Q DiQ P,
m,Q
+
XIQ-P, mQ
+
inhalation Vegetation Milk where: DT, = thyroid dose rate from iodine releases 131 0
= release rate of1131,pci/sec 133Qi
= release rate of1133,pCi/sec X/Q = meteorologicaldispersion factor,sec/m3 D/Q = deposition factor, m-2 Pi
= values derived from NUREG-0133 and Regulatory Guide 1.109 (see Table 1). !
5/1/93 Reu.3 Dose formula for tritiumis:
D
=
r XIQ P, - Qg
.% P - Qy M
P, - Q,,
+
+
3 II Inhalation Vegetation Milk where:
Din = &yrod (or any o&er organ) dose rate from Wum releases Os
= release rate of H-3,pCi/sec other parameters as described above, except units for P. Since milk and i
vegetable doses from tritium are related to X/O and not D/Q, use the unsts for inhalation (see NUREG-0133 and/or Regulatory Guide 1.109, Revision 1 for details).
Dose formula for particulates is:
D
=
o!
XIQ P, - Q,,
DlQ P,- Q,,
+
D:Q P, - Q,,
+
t inhalation Vegetation Milk j
where:
Dog = maximum organ dose rate from particulate releases Op
= release rate of particulates,pCi/sec other parameters as described for iodine, above.
a.
ThVroid Doses Release rate limit is 1500 mrem / year, using the average worst case x/O and D/Q's and P, values from Table 1 results in:
i.
Method 1 UNIT 1 33 j3 + 6.63 x 10-6Q
+ 59.4 Q,3 + 1.08 Q,3 + 2.04 x 10 ~ 4Qy3 Dr=
.82 9
+.20 Q
331 11 33 333 33 inhalation Vegetation
+(1700 Q,3 + 15.12 Q,3 + 2.50 x 10-* Q,
=
333 33 u
Milk 9 : + 16.40 Qn + 5 20 x 10"Q Dr = 1760 231 1
333 u3 UNIT 2 and UNIT 3 r=
76.8 Q, + 18.72 Q + 6.24 x 10-8Q
+ 2200 9+0 9 + O2x mi D
333 333 f y
232 1 133 1 g
inhalation Vegetation
+ 63,000 Q, + 560 Q, + 2.35 x 10-2Q
=
333 33 3
Milk Q, + 618.7 Q, + 4.90 210-2qH Dr = 65,280 333 33 Rev.3 Summing all three units, and setting s 1500 mrcm/ year results in:
17601330:i + 16.4 1330:3 + 5.20 x 10-4 Ost + 65,280131012 + 618.71330:2+
4.90 x 10 2 Os2 & 65,280131Q13 + 618.7 333Qi3 + 4.90 x 10-2 Og3 s 1500 mrem /yr dividing by 1500 gives:
1.171310:1 +.0111330:3 + 43.5 5330:2 +.4131330 2 + 43.51350 34
.413133Q:3 + 3.47 x 10-7 Oss 4 3.27 x 10-5 Os2 + 3.27 x 10-5 Os3 s 1 11.
Method 2 For the 1st quarter, neglect both milk and vegetation doses (i.e., do inhalation dose calculations only).
UNIT 1 DT = 0.82 1310 +.201330: + 6.63 x 10 5 Os UNIT 2 and UNIT 3 DT = 76.81310: + 18.721330 + 6.24 x 10-3 Os Summing all three units, and setting s 1500 mrem' year results in:
0.82 33tOsi +.201330:1 + 6.63 x 10-5 Ost + 76.81350:2+
18.72 133 0:2 + 6.24 x 10-3 Os2 + 76.81330:3 + 18.72 3330 3+
6.24 x 10-3 Os3 s 1500 mrem /yr dividing by 1500 gives:
5.5 x 10-4 133Q:1 + 5.1 x 10-2 131012 + 5.1 x 10-2 133Qi3 +
1.33 x 10-4 133On + 1.25 x 10-2 1330:2 + 1.25 x 10-2 133 0:3+
4.4 x 10-8 Os1 + 4.2 x 10-6 Os2 + 4.2 x 10-6 Og3 s 1 For the 4th quarter, neglect vegetation doses.
UNIT 1 DT = 0.82 1310 + 1700 333O: +.201330: + 15.12133Q: +
6.63 x 10 5 Os + 2.50 x 10-4 Os i
DT = 170113 Qi + 15.321330 + 3.16 x 10-4 Os UNIT 2 and UNIT 3 DT = 76.81350 + 63000131Q: + 18.721330: + 560133Oi + 6.24 x 10 3 Os + 2.35 x 10-2 Os DT = 63.0001350 + 578.721330: + 2.97 1"r2 Og l
5/1/93 Rev. 3 Summing all three units, and setting s 1500 mrerWyear results in:
1701i33Q:1 + 63,0001350:2 + 63,000131Q:3 + 15.32 133O:1+
578.72 3330 2 + 578.72133Q:3 + 3.16 x 10-4 Os1 + 2.97 x 10 2 Os2 +
2.97 x 10 2 Os3 s 1500 mrem /yr dividing by 1500 gives:
1.13 13 061 + 421310 2 + 42 1310i3 +.011330 1 +.39133Oi2 +.391330 3+
2.11 x 10-7 Osi + 1.98 x 10 5 Os2 + 1.98 x 10 5 og3 s 1 iii. Method 3 2nd and 3rd Quarters Assuming Appendix D.7 D/O data for milk animals is acceptable.
UNIT 1 t
DT = 0.821310: + 59.4 1330 + 409.51310: +.20 133 Q + 1.08 1330i +
3.64 133 Qi + 5.2 x 10-4 Os DT = 470131 Q + 4.92 1330 + 5.2 x 10-4 Os UNIT 2 AND UNIT 3 DT = 76.8131Qi + 22001330 + 24601330, # 18.72 3330: + 21.84 1330: +
56013301 + 4.90 x 10-2 og DT = 47401330 + 600.61330: + 4.90 x 10-2 Os Summing all three units, and setting s 1F00 mrenvyear results in:
470 13iQi1 + 4740131Q12 + 4740 131Qi3 + 4.92 i33Q:1 + 600.6133012 +
600.6 333013 + 5.2 x 10-4 Ost + 4.90 x 10-2 Os2 + 4.90 x 10-2 Qg3 s 1500 mrem /yr dividing by 1500 gives:
0.31131Qn + 3.2133012 + 3.2131Q:3 + 3.28 x 10-3 133 0:1 + 0.40133Oi2 +
0.401330:3 + 3.5 x 10-7 Ost + 3.3 x 10-5 0s2 + 3.3 x 10 5 0g3 s 1 4th Quarter-Inhalation and milk pathways same as above, however delete vegetation contribution.
UNIT 1 DT = 410.31310: + 3.84 133Oi + 3.16 x 10-4 Os UNIT 2 and UNIT 3 DT = 2336.813i0 + 579133Q + 2.97 x 10 2 Qg,
Ji 8 4 3J Rev. 3 Summing all three units,and setting s 1500 mrem / year:
41t,.3131Qn + 2537 13 012 + 2537 131 0:3 + 3.84 133 0:1 + 579133Q:2+
579 1330:3 + 3.16 x 104 QH1 + 2,97 x 10-2 Os2 + 2.97 x 10-2 og3 s 1500 mrem /yr Dividing by 1500 gives:
0.271330st + 1.7 1310i2 + 1.7 1310i3 + 2.56 x 10 3 133041 + 3.86 x 10-1 333Oi2 + 3.86 x 10-1 133Oi3 + 2.1 x 10-7 Ost + 2.0 x 10-5 QH2 +
2.0 x 10-5 Og3 s 1 b.
Maximum Organ (other than thyroid) Doses Release rate limit is 1500 mrem / year. Usin the 1980-1987 average worst case X/Q and D/Q's :,nd P values (conservative mix)g from Table f results in:
i i.
Method 1 UNIT 1 7
2.7 x 10-8 2.6110" - Q 5.1 x 10 ~ 8 - 1.6 x 10 - Q,,
+
D =
p g
inhalation vegetation 3
+
5.1 x 10-8 1.3 x 10 - Q,,
+
2.7210 2.0 x ; 0" - Q,,
Milk inhalation 3
3 5.1 x 10-8 4.9 x 10 - Q,,
+
5.1 x 10 ~ 8 4.0 x 10 - Q,,
+
Vegetation Milk 6.63 110-5 q,,
540 Q,,
7 0.2 Q,,
0.82 Q,,
+
D
=
+
+
g inh Veg Milk inh 2.50 x 10" Q,,
2.04 x 10" Q,,
+
+
Vegetation Milk 5.2 x 10" Q,,
Dg = 611 Q
+
p
- Sr-90 values are too conservative. Review of the 1978-1988 effluent data shows Sr-90 has never contributed to greater than 2% of the total curies; use the next limiting nuclide (other than Sr-89). Comparison with ODCM Rev. O, shows this results in a conservative calculation.
t i
t 5/1/93 Rev. 3 Method 3 Determine if the maximum quarterly D/Q data from Appendix D.1 is acceptable to use (i.e., no milk animal likely to be more critical than the data for 1983-1987). If acceptable, use worst case year D/Q for milk locations. If not, an acceptable D/O for use is the worst case quarter of at least the past three years.
Dose formula foriodine is:
DiQ O,
C, DiQ O,
C, XIQ O,
C, D.,.
+
+
=
q Inhalation Vegetation Milk DTQi = quarterly thyroid dose from iodine releases where:
131C
= curies of iodine-131 released 133 i = curies ofiodine-133 released C
X/Q
= meteorological dispersion factor, sec/m3 D/Q
= deposition factor, m-2
= P x 3.17 x 10 2* mrem. m3/Ci. sec.for inhalation and Oi i
mrem. m2/Ci for food consumption Pi
= values derived from NUREG-0133 and Regulatory Guide 1.109 (see Table 1).
- pCi/ set per Ci/yr conversion factor Dose formula for tritiumis:
XQ O,
C XIQ O,
C XIQ O,
C D
=
+
+
g y
y q
Inhalation Vegetation Milk D Tg = quarterly thyroid (or any other organ) dose from tritium releases where:
O Cs
= curiesof tritium released Other parameters as described above, except units for Oi and P. Since milk and vegetable doses from tritium are related to X/O and not D/O, use the units for inhalation (see NUREG-0133 and/or Regulatory Guide 1.10'i, Revision 1 for details).
Dose formula for particulates is:
+
DtQ O C
l D!Q O, - C, XIQ - O, Cp D
=
+
g p
Inhalation Vegetation Milk where:
Doop = quarterly maximum organ dose from particulate releases Cp
= curies of particulates released and other parameters as described for iodine, above.
i Rev. 3 i
a.
UNIT 1 i.
Method 1 Using the worst case quarters as explained earlier and P/s* from Table 7 results in:
- For particulates, Sr-90 Pi values are too conservative. Review of the 1978-1988 effluent data shows that Sr-90 has not contributed to greater than 2%
of the total curies. Therefore use the next most limiting nuclide (other than Sr-89). Comparison with ODCM Rev. O shows that this still results in a conservative calculation.
l f 1.047 C
D
=
0.032
+
4.1
+
118 C, +
.0078
+
.0748
+
g, q7
,g inhalation Veg Milk inhalation Veg Milk 9.79 x 10 ~'
C,,
2.60 x 10 ~'
+
7.99 x 10~'
+
D
=
er y
Inhalation Vegetation Milk 0.032
+
4.86
+
37.41 C,
D
=
f Inhalation Vegetation Milk r
C D
= 122 C, + 1.13 mi QT 3g y
D
= 2.04 x 10 ~ 5 C er y
H i
D
= 42.3 C;,
qg ii.
Method 2 Use same formulas as for Method 1, however, delete vegetables and/or milk when applicable.
iii. Method 3 After review of existing cow and goat farms, if the 1983-1987 milk animal D/O data is determined to be acceptable, then:
~
Rev. 3 Milk Pathwsy Das2s:
C C, +.24 9 D
28 er, =
in i u1 9.8 x 10-' C,,
D
=
q7 il D
= 8.9 C,,
qo b.
UNIT 2 and UNIT 3 i.
Method 1 Using the worst case quarters as explained earlier and P;'s from Table f resultsin:
D
=
4.1
+
105
+
2996 C, +
1.0
+
1.9
+
26.63 C,
g3 333 QT, k
inhalation Vegetation Mdk inhalation Vegetation Mdk 1.03 x 10~ 8
+
1.26 x 10-3 C,,
3.33 210-d D
=
+
QTg inhalation Vegetation Mdk
=
4.1
+
124
+
951 C,,
D F
inhalation Vegetation Milk 3.1210-3 g,C, + 29.53 33,
C D
=
QT, D
= 2.62 210-3 C,,
Qrn D
= 1,080 C,,
ii.
Method 2 Use same formulas as for Method 1, however, delete vegetables and/or milk when applicable.
l-lii. Method 3 After review of existing cow and goat farms,if the D/Q for milk animals for the 1983-1987 data is determined to be acceptable, then:
Milk Pathway Doses:
C 122 C, + 1.08,3,
I'Qr,
=
7 g3 1.3 x 10-3 C, D
.7,
=
j q
4 0 C,,
D
=
5/1/93 Rev. 3 t
T_ABLE1 DOSE FACTORS FOR IODINES & PARTICULATES P*
i I * " */Y ' P " '
(mrenVyr oer pCi/sec) pCi/m3)
Radionuclide inhalation Vegetables Goat Milk Cow Milk f
H-3 1.3(3) 4.0 (3)*
- 4.9 (3)*
- Cr-51 2.1(4) 6.4 (6)
Mn-54 2.0(6) 3.0 (9) i Fe-59 1.5(6) 6.8 (8)
I Co-58 1.3(6) 3.8 (8)
Co. 60 8.7 (6) 2.1(9) 2n-65 1.2(6) 2.2 (9) 1.9(10)
Rb-86 2.0(5)
Sr-89 2.4(6) 3.7(10) 2.7(10) 1.3(10)
Sr-90 1.1(8) 1.25(12) 2.6 (11) 1.2(11)
Y-91 2.9(6)
Zr-95 2.7(6)
Nb-95 7.5(5)
Ru-103 7.8(5)
Ru-106 1.6(7) 1.2(10)
Ag-110m 6.8(6)
Te-127m 1.7 (6) i Te-129m 2.0(6)
Cs-134 1.1(6) 2.6(10) 2.0(11) 6.8(10)
Cs-136 1.9(5)
Cs-137 9.1(5) 2.4(10) 1.8(11) 6.0(10) i i
Ba-140 2.0(6)
]
Ce-141 6.1(5)
Ce-144 1.3(7) 1.0 (10) l-131 1.6(7) 2.2(10) 6.3(11) 5.3(11) l-133 3.9(6) 4.0 (8) 5.6 (9) 4.7 (9)
- Pi are the inhalation and consumption factors derived from NRC Regulatory Guidef.109, Rev. f. For inhalation, the teen is the critical age group for all nuclides except Rb-86, Cs-137,1-131, and 1-133, which are for the child. For vegetables, the child is critical; for milk, the infant. Maximum organs are:
whole body for H-3, bone for Sr-90 and thyroid for I-131,133.
Same units as for Inhalation for H-3, based on NUREG O133 assumptions.
~ ~ '.is u na
~
7 Rev.5 t
APPENDIX G ENVIRONMENTAL MONITORING PROGRAM i
Samplina Locations The following lists the environmental sampling locations and the types of samples i
obtained at each location.
Sampling locations are also shown on figures G-T, G-2 and G.
t 3.
j i
Direction & Distance From P* umber Name Release Point * *
- Samole Tvoes
[
1 -l*
On-site-Old Millstone Rd.
0 6 Mi, NNW TLD, Air Particulate, lodine, Vegetation
{
2-1 On-site -Weather Shack 0.3 Mi,5 TLD, Air Particulate, lodine 3-1 On-site-Bird Sanctuary 0.3 Mi, NE TLD, Air Particulate, lodine 4-1 On-site-Albacore Drive 1.0 Mi, N TLD, Air Particu* ate, lodine 5-1 MP3 Discharge 0.1 Mi, SSE TLD l
6-1 Quarry Discharge 0.3 Mi,55E TLD 7-1 Environmental Lab Dock O.3 Mi,5E TLD fl 8-1 Environmental Lab 0.3 Mi,SE TLD 9-1 Bay Point Beach 0 4 Mi, W TLD 10-1 Pleasure Beach 1.2 Mi, E TLD, Air Particufate, Iodine 11-1 New London Country Club 1.6 Mi, ENE TLD, Air Particulate, lodine 12-C Fisher's Island, NY 8 7 Mi, ESE TLD
~
13-C Mystic, CT 11.5 Mi, ENE TLD j
14-C Ledyard, CT 12.0 Mi, NE -
TLD l
15-C Norwich, CT 14.0 Mi, N TLD, Air Particulate, lodine I
16-C Old Lyme, CT 8.8 Mi, W TLD j
17-l Site Boundary 0.5 Mi, NE Vegetation l
18-1 Pleasure Beach 1.2 Mi, E Vegetation -
f 19-1 Cow Location # 1 9.5 Mi,WNW Milk f
20-C Cow Location # 2 16.0 Mi, NNW Milk i
21-1 Goat Location #1 2.0 Mi, N Milk 22-1 Goat Location #2 5.2 Mi, NNE Milk l
23-1 Goat Location #3 2.0 Mi, ENE Milk f
24-C Goat Location #4 14.0 Mi, NE Milk l
25-1 Fruits & Vegetables Within 10 Miles Vegetation i
26-C fruits & vegetabtes Beyond to Miles Vegetation I -
27-1 Niantic 1.7 Mi,WNW TLD, Air Particulate, fodine
- j 28-1 Two Tree island 0.8 Mi, SSE Mussels I ;
l 29-1 West Jordan Cove 0.4 Mi, NNE Clams l
30-C Golden Spur 4.7 Mi, NNW
' 31-1.
Niantic Shoals 1.8 Mi, NW Bottom 5ediment. Oysters
- i lll 1.5 Mi, NNW Mussels Bottom 5ediment, Oysters, Lobster, 32-1 vicinity of Discharge Fish, Seawater 33-1 seaside Point 1.8 Mi, ESE Bottom Sediment.
i
6.0 Effluent Monitor inoperability l
During this report period, January 1 through June 30,1993, the following monitors were inoperable for more than 30 days.
6.1 Unit 3 Liquid Waste Discharge Monitor (3LWS-70)
The Liquid Waste Discharge Monitor was administratively declared inoperable on June 13, 1992. The inoperability is a result of a check source failure because the built-in check source no longer has sufficient i
strength to exceed the increased monitor background. This is a result of plateout of contamination on the sample line. Based on functional checks and calibrations, the monitor will perform its intended function and has sufficient sensitivity to detect actively well below release rate limits. The monitor is in service during all discharges. Because of the administrative inoperability, redundant sampling and valve line-ups are performed in accordance with Technical Specification action statements.
Options to eliminate the check source failure are being evaluated.
6.2 Unit 3 Steam Generator Blowdown Monitor (3SSR-RE-08)
The Steam Generator Blowdown Monitor was declared inoperable on September 14,1992 due to low flow alarms. The monitor remains in service and based on functional checks and calibrations would perform its intended function..During the period there was no detectable activity released to the environment from blowdown. Normally, all blowdown is recovered. The monitor was retamed to service on May 21, 1993. Options to eliminate the low flow alarms are being evaluated.
I G
l
_.=
f 7.0 Errata I
j.
The attached pages provide corrections to the data in previous reports. Most of the changes to the data were minor in nature; however, a few data numbers changed significantly.
For example, previously reported values of Millstone Unit 2 Spent Resin for the period July 1,1992 through December 31,1992 were reported for the l
entire year rather than just for the 6-month period. In addition, Millstone i
Unit 3 Tritium analyses were reported low by 20 percent due to the loss of l
the quench curve from the analyzer memory for the fourth quarter 1992.
Overall, the corrections do not significantly impact the total reported radioactive effluents released from Millstone Station.
+
9 i
}
i I
f l
I l
l 1
Table 2.1-2 Mittstone Unit No.1 Liquid Effluents - Batch Nuclides Fourth Quarter 1991 l
Released Und October l November l December l Total i
Cr-51 j Ci i 4.62E-061 1
4.62E-06 Mn-54 Ci i 1.06E-03j 2.55E-02i 5.12E-02[
7.78E-02
~~ 3507
~
Co-58 2.84 E-04 5.82E-0 8
Co-60 i Ci 4.26E-02 i 4.20E-02 4.61 E-02 i 1.31 E-01 i
1-131 i Ci l 3.92E-05 ;
3 91E-05!
-]
7.83E-05 l-133 i Ci -~
I i
~
~~I Ci i l-135 ~
[ Ci
~li5565I N-~~--~ ~ ~ ^ "5.~755T 5 Cs1'34 0
2.24E-03 ;
7.30E-04 5 9.52E-03
~
M&99 t Ci I
i
'Ce!ii1 _ TCi:
t
~
Ce-144 i Ci I i
i Zn-65 1 CN 8.2950Y 1.175-62'I~T9iE 62T 335505
~-
Fe-59 Ci !
i 1.32E-03 ;
i 1.32E-03 1
Ag-110m CTl 4.945!66][376E[ 3.45E-04 Sb-124 1 Ci 1
100E-06 l l
1.00E-06 i CiI I
l
^
4 u______
_j__ _ _ _j _ __ _
! Ci t Fe-55
! Ci !
2.47E-03 '
6.80E-02 i 2_._4 2E.0. 2 ;
9.47E-02 U
~155E 65l 6.-IEE-06i i
2.285f-~65 Ci i T
Sr-90 Total Activity i Ci 1 6.11 E-22 !
1.51 E-01 i 1.42E-01 i 3.54E-01 Xe-133 I Ci i i
l l
Xe-135
! Ci i i
l
~~~ I Xe-135m N~i~
1 7
I i
~
Xe-131m 1 Ci i
_____...__.I. _ _.. _
1 Ci i
Total Activity i Ci i
b
i 4
Table 2.1-3 i
Millstone Unit No.1 l
Airbome Effluents - Sum Of All Releases j
i i
Second Quarter 1991 Unit April l
May l
June l
Total l
t A. Fission and Activation Gases I
1.
Total ActMty Ci 2.07E+ 01 N/D N/D 2.07E+ 01 l
Released
- 2. Avrage Perod uCtsec 8.56E+00 2.64E+00 Reiease Rate t
B. todines l
9.35E-05 i
1.
Total 1131 Ci 6.28E-05 '
2.33E-05 7.43E-06lr Achty Remased i
2 Average Perod uCesec ;
2.60E-05 3
__ 7.72E-06 3.07E-06l 1.19E-05 Release Rate l
l 1
C. Particulates 1.
Total Particutate Ci 2.85E-04 1.26E-04 1.56E-04 5.66E-02 ActMty Released 2.
Average Diluted UCvsec 1.18E-04 4.16E-05 6.43E-05 7.20E-05 l
Activtty i
3.
Total Gross Alpha ! Cl 2.78E-06 3 74E-07 3.27E-07 3.48E-06 ActMty Released D. Tritium l 1.59E+01 i
1.
Total Actrvty Ci l 7.06E+00 8.81 E+ 00 N/D Released i
{2.02E+ 00 i
2 Average Perod j uCrsee i 2.92E+00 2.92E+00 Reiease Rate l
l i
l i
N/D = Not Detected f
a 4
l I
i
i Table 2.1-4 Millstone Unit No.1 Airborne Effluents - Elevated Continuous Nuclides Second Quarter 1991 Released Unit Apnl l
May l
June l
Total Xe-138 Ci 4.12E+ 00 !
l 4.12E+00 Kr-87 Ci 8.88535I i
~I 8.8BE-01 Kr-88 Ci ;
7.165-01!
7
~~ [ 7.16E-01 Kr-85m
. Ci !
1.73E-01 !
7 i
1.73$T01 Xe-135 j Ci i 1.48E+ 00!
l l
1.4BE+ 00 Xe-133
' Ci i 1.23E+0Y^~~~ ~I 7 1.235i01
'XT135rn Ci.
9.54 E-011 ~-~~~~ T- ~ ~T T Si.s-~0.1 Ar-41 Ci !
8.30E-02 8.30E-02 1
i
! Ci >
Total Activity Ci 2.07E+ 01 :
2.07E+ 01 4
6 i
1-131 1 C i
6.2BE 2.33E-05 7.43E-06 l 9.35E-05 l-133 I Ci 1.64E-04 :
i 1.64 E-04 l
i Cr-51 l Ci ;
4.22E-05 :
i 4.22E-05 Mn-54 l Ci _
1.09E-05i 3.58E-06 :
1.72E-05 !
3.17E-05 Fe-59 I Ci !
i Co-58 l Ci I 1.77E-06) 7.20E-05I 1.96E-04 1.77E-06 Co-60 l Ci 5.82E-05 :
6.60E-05!
Zn-65
! Cij 1.37E-04 !
4.86E-05; 5.96E-05 2.45E-04 i
1-131 i Ci i
e C&134
- Ci.
! Ci 1.05E-05 6.88E-06 i 6.87E-06 !
2.43E-05 Ba-140 f Ci I
44 6.64E-N ~
~
~6.64E-06
! Ci I
l 1.72E-05 __ _ _
1.725T5' Sr-89 j Ci 1
! Ci 1.65E-07 !
5.58E-07 =
7.23E-07 i
Total Activity i Ci !
2.85E-04 :
1.26E-04l 1.5SE-04l 5 66E-04 2
3 l
I
I Table 2.2-1 Millstone Unit No. 2 Liquid Effluents - Sum Of All Releases l
Foudh Quader 1992 Unit October l November l December l Total A. Fission and Activation Products 1.
Total Actwty Ci 4.86E-03 3.81 E-01 2.40E-01 6.26E-01 j
Released
- 2. Average Pered uCi'ml 1.00E 10 8.13E-09 4.91 E-09 4.34E-09 Dduted Activity B. Tritium i
- 1. Total Actwity ci 1.54 E-01 9.04 E-01' 3.50E-01 1.41 E+ 0C Released
- 2. Average Perod uCi/mi 3.19E-09 1.93E-DE 7.15E-09 9 77E-09 Dduted Actuty t
C. Dissolved and Entrained Gases l
1.
Total Actuey ci 7.72E-05 '
2.02E-06 '
7.93E-05
[
Released 2.
Average Dduted uCFml 1.60E-12 4.13E-14 5.50E-13 Ac9vity D. Gross Alpha f
1.
Totaf Actwity Ci Released No Activity Detected
[
f E. Volume l
1.
Released Waste L#ere 1.05E+06 5.6SE+ 05 ' 1.11 E+ 06 2.72E+06 Volume 2.
Diiuton Votume Lners 3.50E+09 2.09E+09 4.65E+09 1.02E+10
.j Dunng Releases 3.
Dituton Volume uters 4.84E+10 4.68E+10 4.90E+ 10 1.44 E+ 11 f
Dunng Pened t
l 6
i 1
t e
l p.
e
,v
+w
... ~ -
~_
N Table 2.2-3 Millstone Unit No. 2 Liquid Effluents - Batch i
Nuclides Fourth Quarter 1992 Released Unit October l November l December l Total Co-58 i Ci !
2.58E-04 6.20E-02!
2.44 E-02 !
8.66E-02 Co-60 l Ci i 3.69E-04 1.44E-01i 1.06E-01 i 2.50E-01 i
Ag-110m i Ci i 8.41 E-06 1.11E-02 5.41 E-03 1.65E-02 Sb-125 i Ci !
1.76E-04 7.64E-03 1.25E-02 2.03E-02 l
Cs-134 i Ci !
3.12E-05T 2.69E-02
~ 6.04E-02]
1.48E-01 1.39E-02!
4.09E-02 Cs-137
! CL 1.28E-04 I 8.73E-02 a
l Nb-97 I Ci i 3.62E-06 :
8.18E-OSi 8.02E-04 l 8.14 E-04 La-142 i Ci I 2 68E-05 i
i 2.68E-05 5
Mn-54 Ci i 3.09E-03i 1.99E-0E 5.08E-03 3
Cr-51
! Ci 1 2.23E-04 :
2.23E-04 5
Sr-92 i Ci ;
7.05E-06 3.52E-04 !
3.59E-04 Nb-95 Ci !
2.86E-03 !
2 94E-03!
L80E-03 3
1.25E-031 1.18E-03 i 2.43E-03 Zr-95
! Ci i i
q 1.08E-03E 1.05E-03i Ru-105 Ci i 2.12E-03 4
i Sb-124
! Ci [
i 1.40E-03l 1.4BE-03!
2.88E-03 Co-57 Ci 2.71 E-05!
1.77E-05i 4.47E-05 l
]
Cili Ru-103 I
5.83E-041 l
5.83E-04 Ru-106 i Ci I l
1.09E-02) i 1.09E-02.
Ba-142 l Ci !
l 1.30E-04 !
1.30E-04 l
Sr-89
! Ci i i
8.25E-05j l
8.25E-05 i
- Ci l
8.76E-051 3.04E-05!
1.18E-04 Fe-55 l Ci I 3.86E-03!
2.04 E-02i 7.93E-03i 3.22E-02 l
i Total Activity ' Ci i 4.86E-031 3.81 E-01 !
2.40E-011 6.26E-01 l
i Gross Alpha i Ci i 1
i i
l H-3 l Cil 1.54 E-01]
9.04 E-01l 3.50E-01l 1.41 E+ 00 l
1 i
Ar-41 Ci i i
2.02E-OS i 2.02E-06 j
Xe-133m l Ci !
9.89E-06l 9.89E-06 Xe-138 i Ci i 6.74E-05!
i 1
6.74 E-05 l
Total Activity ! Ci i 7.72E-05 !
2.02E-06i 7.93E-05 l
t 1
I 1
l 5
d 8
I
.e.-
Tcblo 2.2-4 t
Millstone Unit No. 2 Airbome Effluents - Sum Of All Releases i
i Second Quarter 1991 l
Unit Apnl l
May l
June l
Total l
t i
A. Fission and Activation Gases 1.
Tdal Activty Cl 1.6BE+02 4.31 E+ 01 1.43E+01 2.25E+ 02 Remased 2.
Average Penod uci'sec 5.55E+01 1.78E+ 01 4.74E+00 2.66E+01 Release Rate r
B. lodines 1.
Tdai Actuey Ci 4.2SE-03 1.50E-03 1.58E-03 7.33E-03 Released 2.
Amrage Penod juCvsec 1.41 E-03 6.20E-04 f 5.23E-04 j 8.66E-04
{
l Release Rate I
1 i
C. Particulates 1.
Taal Activny Cl 1.22E-05 l N/D N/D l
1.22E-05 f
f Re' eased 2.
Average DMed UCvsec 4.04E-06 j 1.44E-06 Activty l
3 Total Gross Alpha Ci j
j i
Actrvity Released No Activity Detected i
D. Tntium 1.
Tda! Actretty Ci 8.06E+00 1.53E+ 00 2.44 E+ 00
.1.20E+ 01 i
e Released
~
l 2.
Average Penod uCi/sec 2.67E+00 6.31 E-01 8.08E-01 1.42E+ 00 f
Release Rate i
N/D = Not Detected l
i l
1.
l
.i
Table 2.2-4 Millstone Unit No. 2 Airbome Effluents - Sum Of All Releases Third Quarter 1991 Unit July l August l September l Total A. Fission and Activation Gases 1.
Total Actidy ci 1.35E+ 01 2.00E+01 1.18E+ 01 4.53E+01 Released 2.
Average Penod UCvsec 5.58E+0C 7.46E+00 4.42E+00 5.83E+0C Reicase Rate B. lodines 1 Total Actuity l C l
2.00E-04 j t03E-03l 1.70E-04 l 1.40E-03 Released l
I j
i 2 Avem p Penod UCrsec i 8 26E-05 l 3.84 E-04 i 6.34E-05; 1.80E-04 Release Rate l
C. Particulates 1.
Total Partculate Cl j
i i
Actwity Released i
No Activity Detected 2.
Average Diluted uCisecj
{
Actrvity l
3 Total Gross Alpha l Cl j i
i ActMtv Rekased !
No Activity Detected D. Tritium 1.
Total Actwty Ci {
3.30E-01 ; 2.29E+00:
1.30E+ 00.
3.92E+00 Released i
}
2.
Average Pered uCeseej 1.36E-01 l 8.55E-01 l 4.85E-01 !
5.04 E-01 Release Ra+e I
a l
}
l Table 2.2-4 l
Millstone Unit No. 2 Airbome Effluents-Sum Of All Releases I
i Fourth Quarter 1991 Unit October l November l December l Total i
A. Fission and Activation Gases 1.
Total Actwy C6 1.56E+ 01 9.66E+00 2.13E+ 0 3 '
4.65E+01 Rebased uCi 6.44E+00 3.20E+0C 8.80E+00 592E+0C 2.
Average Penad f
'sec Re4 ease Rate I
I B. lodines 1.
Total Actwy Ci l 6.18E-04 !
3.65E-04 123E-04 ;
1.11 E-03 Rebased l
2.
Average Perod uCt%e 2.55E-04 l 1.21 E-04 !
5.07E-05 t 1.41 E-04 Reiease Rate l
C. Particulates l
1.
Tdal Partculate C
l l
l Actrvey Rekased No Activity Detected l
3
- 2. Average Diluted uCt'sec l
l l
Actwy
_ _ y_
3 Total Gross Alpha Ci l l
l Activny Released i
No Activity Detected I
q D. Tritium f
]
1.
Total Activey Ci 1.68E+ 00l 1.38E+ 00 8.38E+ 00 1.14 E+ 01 Rekased I
i 4
4 j
2.
Average Penod uCesec 6.94E-011 4.57E-01 3.46E+0C 1.46E+00 l
Release Rate l
l i
i l
l l
d i
i i
k I
i
(
i t
i 8
f a
i I
^
N
i Table 2.3-1 Millstone Unit No. 3 Liquid Effluents-Sum Of All Releases Second Quarter 1991 Unit Apnl l
May l
June l
Total A. Fission and Activation Products 1 Txa:Actray l Ci !
5.99E-01 i 2.33E-01 :
7.40E-02 9.05E-01 Re6 eased l
l 2 Average Perod l uCvm1 4.64 E-09 1.46E-05 5.56E-10 2.15E-09 Ddufed Actidy i B. Tntium 1.
Taal Actrdy
- Ct i 5 80E+00j 2,20E+ 011 3.94 E+01
- 6.72E + 01 R ***5*d I
....)_.._______)_._..-._-.
_. _.2 2 Aarage Pered j uCvml; 4.50E-08; 1.38E-07 ;
2.96E-07 1.60E-07 i
D.ued Actwey I i
i r
C. Dissolved and Entrained Gases 1.
TNai Activey j Cl l 6.14 E-04 ;
4.40E-03; 4.61 E-03 9 63E-03 Re6 eased i
2.
Average Diluted i uCE 4.76E-12 2.77E-11 3.47E-11 2.29E-11 Actrvey D. Gross Alpha 1.
Taa! Actrvey Ci.
j No Activity Detected Reieased r
E. Volume 1.
Released Waste Laers.
1.17E+ 06 1.3SE+ 06: 1.55E+06 !
4.10E+ 06 i
i j
'Tiii5 ION 5155+05I7195+U9 1T795 Aid
~
2.
D Volume Leers Dunng Reieases I
3.
Diuon Volume l Lnem ' 1.29E+11 ; 1.59E+11 ; 1.33E+11 : 4.21 E+ 11 Dunng Pered I
L b
1
t
[
Table 2.3-1 i
Millstone Unit No. 3 i
Liquid Effluents - Sum Of All Releases i
Fourth Quarter 1991
[
Unit October l November l December l Total
(
a A. Fission and Activation Products I
1.
Tsar Actuey ci l 1.2SE-01 1.84 E-01 2.91 E-01 6.00E-01
[
Released 2.
Average Penad uCVml 5.39E-09 2.4 BE-09 5.15E-09j 3.90E-09 l
Dduted Actwey l
- 8. Tritium i
1.
Total Actrvey ci 9.28E+00 6.52E+ 01 1.23E+ 01 8.68E+01 l
Released 2.
Average Perod uCvml 4.00E-07 8.8DE-07 2.18E-07 5.64E-07' l
Diluted Activey
[
e C. D.ssolved and Entrained Gases l
1.
Total Activey ci N/D 2.61 E-05 7.92E-06l 3.40E-05 I
Released l
3.52E-13 1.40E-13 l 2.21E-13 l
2.
Average Datuted ucemi Actwey l
j i
D. Gross Alpha f
- 1. Tota! Activity ci N/D N/D 8.10E-05 8.10E-05 j
Released i
E. Volume
]
1.
Released Waste Liters i 4.99E+05 9.17E+05 7.34 E+05 2.15E+06 i
]
votume 2.
Diuen volume ues 1.52E+09 5.02E+09
- 2.07E+09 8.62E+ 09 l
Dunng Releases
[
3 Diiuton volume uters 2.32E+ 10 7.41E+10 5.65E+10 1.54 E+ 11 i
Dunng Penod I
}
N/D = Not Detected i
I
[
t 3
l I
i i
a y
.w
Table 2.3-3 Millstone Unit No. 3 Liquid Effluents - Batch - LWS Nuclides Second Quarter 1991 Released Unit April l
May l
June l
Total Cr-51
! Ci i 2.32E-02 1.23E-03 1 16E-04 t 2.45E-02 Mn-54 ICi I 9 64E-031 4 29E-03l 9.60E-04j_ _ 1 49E-02
~
Tc-99rn i Ci :
i
/.99E-05 i
! _4.99E-05 Co-58 j Ci i 4.01 E-02l 1.42E-02j 4.15E-03; 5.85E-02 l
Co-60 i Ci !
4.23E-021 2.31 E-02i 5.33E-034 7.07E-02 3 27E 05E 6.03E-05I 2.69E-05' 1.20E-04 T
l-131 Ci i l-133 Ci j l
6.73E-04 j 6.47E-04 l 1.32E-03 1-135 Ci !
_L 7.75E-04l 1.55E-04 j 9.30ET4 C.s-134
! Ci i 1.88E-01 ;
7.61 E-02 !
2.12E-02 l 2.85E-01 Cs-137 j Ci i 1.76E-01 j 7.21E-02!
2.08E-02( 2.69E-01 M&99 Ci !
j i
Ce-141 Ci l l
Ce-144
! Ci i 2.15E-03 !
2.15E-03 Zn-65 I Ci i 4 04E-04l 2 655-04!
6.73E-04
[
Fe-59 i Ci 1.19E-03!
1.19E-03 i
Nt> 95 i Ci !
4.71E-03!
1.86E-03l 4.30E-04 ;
7.00E-03 Nb-97 i Ci 1 5.33E-03 l 1.18E-02i 2.60E-03I 1.97E-02 i
Sb-124 l Ci 1.145 63l 1.77E-04 'i 1.86E-04 !
1.50E-03 Sb-125 1 Ci i 1.47E-02i 3.27E-03i 6.64E-03i 2.46E-02 Sr-92 Ci i 1.16E-03 !
3.02E-03i 3.83E-04 !
4.56E-03 Zr-95 i Ci !
1.94 E-03!
1.87E-04 !
2.23E-06 '
2.13E-03 Ag-110m i CiI 2.7 A5-03l 9.30E-03i 1.59E-03!
1.36E-02~
~
l Hf-181
! Cil 5.52E-04l l
5.52E-04 Co-57
- Ci i 1.28E-04 i i
5.37E-06 i 1.33E-04 Na-24
! Ci 1.26E-03 !
2.15E-03!
1.74E-04 !
3.58E-03 j
'l-132 Ci l 1.78E 64I 1.49E-04; 3.27E-04 Sb-122 Ci i i
i 2.62E-03 i 2.62E-03 1-134 Ci i
l 2.56E-04 l 2.56E-04 Rb-88 i Ci !
j 9.84E-05!
9.84E-05
[
Rb-89 I Ci :
J 8 38E-05!
8.38E-05 Cs-138 i Ci !
l 2.85E-04 !
2.85E-04 Ba-139 l Ci i i
l 3.21 E-05 j 3.21 E-05 Ru-106 i Ci i i
j 2.40E-04 i 2.40E-04 l
Fe-55 l Ci !
819E-02 7.73E-03 l 4.81 E-03) 9.44E-02 Sr-89 I Ci i Sr-90
! Ci i Total Activity i Ci !
5 99E-01 <
2.33E-011 7.40E-02 9.05E-01 l
f Gross Alpha ! Ci i l
i i
H-3 I Ci i 5.80E+001 2.20E+ 01 !
3.94E+ 011 6.72E+ 01 Xe-138
! Ci !
i 1.09E-04 i 1.09E-04 Xe-133 Ci i
1.505:05I 1.75E-03!
3.25E-03
~
Xe-135 Ci ;
6.14E-04 :
2.38E-03l 2.62E-03l 5.61 E-03 Xe-135rn Ci i 3 89E-04 j 7.12E-051 4.60E-04 Ar-41 l Ci i
1.35E-04 l 1.35E-Oi i
i
Table 2.3-3 Millstone Unit No. 3 Liquid Effluents - Batch - LWS Nuclides Second Quarter 1991 j
Released Unit April l
May l
June l
Total s
Rr-87
' Ci i j
8.09E-OSI 8.09E-06 Kr-85m Ci i T~ ~ ~~ ~
l 2.65E-05!
2.68E-05
~~
Kr-88 Ci i 2.80EJ5I 2.80E'05~
~ ~ "
Total Activity i Ci l 6.1_4E-04 ;
4.40E-03 !
4.61E-03[
9.63E-03 i
4 4
l v
P
\\
)
l l
l I
1
i t
Table 2.3-5 Millstone Unit No. 3 Airborne Effluents-Sum Of All Releases
)I
{
First Quarter 1991 Unit January l February l March l Total I
A. Fission and Activation Gases 1.
Total Activfty c
- 3. 82E+ 01 1.35E+ 01 4.70E+01 9.87E+01 i
Released 2 Average renad ucusec 1.26E+01 5.59E+00 1.94E+01 125E+ 01 i
Reesse Rate B. lodines 1.
Teean-131 ci j 1.34 E-03 l 2.55E-03 1.41 E-04 l 4.03E-03 Activey Released l
l l
2.
Average Period uCi'sec }
4.42E-04 !
1.05E-03 5.83E-05 i 512E 64
{
Release Rate i
I i
l C. Particulates l
1.
Total Particulate l
Ci ll 1.09E-05 1.77E-05 3.72E-04; 4.01 E-04 Activry Re+ eased {
f f
2 Average Diluted ucesec 3.60E-05 7.31 E-06 1.54E-04 !
5.10E-05 Actrvty f
f 3 Total Gross Alpha ci 2 20E-08 7.20E-09 N/D 2.92E-08
.i Activity Reicased a
D. Tritium 1.
Tota! Actwty Ci l
Released i
No Activity Detected i
2.
Average Penod uCesec l l
Releaso Rate j
i N/D = Not Detected 1
l 1
)
I e
Table 2.3-5 Millstone Unit No. 3 Airt>ome Effluents - Sum Of All Releases i
c Second Quarter 19tti f
Unit Apnl l
May l
June l
Total A. Fission and Activation Gases 1.
Tmat Actwity ci i 2.07E+01 N/D 1.75E-02 2.07E+01 Reieased l
- 2. Average Perod UCusec 8.63E+00 7.20E-03 2.64E+ 06 Release Ra'e I
B. lodines 1.
Total b131 ci 1.15E-05 2.87E-05 7.45E-06 4.77E-05 Actway Released l
2.
Average Perod uCusec 4.79E-06 9.53E-06 3.07E-06 j 6.08E-06 Release Rate i
r C. Particulates 1.
Total Pa$cula'e ci 1.52E-05 1.57E-05 9.00E-06 3.99E-05 Activity Released
- 2. Average Diluted uCesec 6.35E-06 5.22E-06 3 70E-06 5.10E-06 ActMty 3.
Total Gross Alpha C4 l
l
)
r Actwfty Re6 eased No Activity Detected D. Tritium 1.
Total Actwity ci 1.41 E-03 N/D N/D 1.41 E-03l Released 2.
Average Perod uCusec 5.88E-04 1.80E-04 Rebease Rate N/D = Not Detected 4
l
~f i
i t
4 l
1
Table 2.3-5 f
Millstone Unit No. 3 f
Airt>crne Effluents-Sum Of All Releases l
i Third Quarter 1991 r
Unit July l August l Septemtier }
Total f
A. Fission and Activation Gases 1.
Totai Actwy Ci 1.12E-01 5.78E+001 N/D
$89E+00 Reinased f
2.
Average Penod uCisec 4.32E-02 2.39E+00l 7.93E-01 Re6 ease Rate j
i B. lodines t
1.
Tot.al l-131 Ci 6.29E-05 N/D l
N/D 6.29E-05 Actmty Released l
---. _m 2.
Average Penod juCPsec 2.43E-05 8.46E-06 Release Ra'e i
i t
C. Particulates 1.
Total Partculate Ci 2.35E-05 4.03E-06 2.32E-07 2.78E-05 Actuty Reieased 2.
Average Diluted uCVsec 9.07E-06 1.67E-06 9.59E-08 3.74E-06 ActMty 3 Totat Gross Alpha Ci i 7.04E-07 3.70E-08 1.90E-08 7.60E-07 Actury Released D. Tritium 1.
Total ActM!y
{ Ci 4 1.29E-02 !
N/D N/D 1.29E-02 l
ReleaseJ i
j 2.
Average Penod I UCvsec :
4.9BE-03, 1.74E-03 Release Rate i
i N/D = Not Detected
\\
l l
i 1
Table 2.3-5 Mittstone Unit No. 3 Airt>ome Etfluents - Sum Of All Releases Fourth Quarter 1991 Unit October l November l December l Total j
A. Fission and Activation Gases t
l 1.
Tdal Actrdy Ci l
l j
Released No Activity Detected l
~
2.
Average Pered uCPsee Rebase Rate B. lodines I
j 1.
Total l-131 Ci j
j
{
ActMty Released No Activity Detected 2.
Average Penod uCLsec f
I Rebase Rate C. Particulates 1.
Total Partculate C6 N/D N/D 1.07E-05 1.07E-05 Activey Released 2.
Average Dduted uCusec 4.42E-06 1.44 E-06 Activty i
l 3.
TotalGross Alpha Ci 6.59E-06 8.90E-09 4.43E-07 7.04E-06 Activity Rebased i
D. Tritium h
1.
Tdal Activty Ci l
l
[
l f
Rekased No Activity Detected 2.
Average Pernd uCiwe Release Rate l
i N/D = Not Detected 1
N i
4 e
i I
1 i
i
l 1
Table 2.3-6 Millstone Unit No. 3 i
Airbome Effluents - Mixed Continuous - Normal Ventilation i
Nuclides First Quarter 1991 l
Released Unit January l Februsty l March l Total l
i
- 1. Fission Gases 1
Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Kr-89 Ci r
Xe-131m Ci Xe-133 Ci 3.80E+ 01 1.12E+ 01 4.70E+ 01 9.62E+ 01 Xe-133m Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci Ar-41 Cl 1
Ci Ci i
s Total Activity l Ci ! 3.80E+011 1.12E+01 ! 4.70E+011 9.62E+ 01 r
2 lodines 7
l-131 Ci l 1.33E-03!
2.54E-03 1.41 E-04 i 4.01 E-03 1-133 Ci i 1.10E-031 4.19E-04 1.73E-04 l 1.69E-03
- 3. Particulates l
1.04E-04 1.04E-04 f
Cr-51 Ci l
Mn-54 Ci i
1.93E-05 1.93E-05 l
Fe-59 Ci l
[
I Co-58 Ci j
1.77E-05 1.67E-04l 1.85E-04 Co-60 Ci
~
3.27E-05 3.27E-05 l
Zn-65 Ci 1-131 Ci 1.09E-05 1.09E-05 l
Cs-134 Ci Cs-137 Ci 1.07E-05 1.07E-05 i
Ba-140 Ci I
l Ce-141 Ci l.
[
Ce-144 Ci 1
1.05E-05 1.05E-05 Nb-95 Ci 2.15E-05 2.15E-05 j
Zr-95 Ci 6.65E-06 6.65E-06 p
Sr-89 Ci j
j Sr-90 Ci t i
Total Activity i Ci i 1.09E-05 !
1.77E-05 I 3.72E-041 4.01 E-04 i
t H-3 Ci i l
i 1
I Gross Alpha Ci l l
l l
[
t h
t l
i i
i Table 2.3-6 i
Millstone Unit No. 3 Airborr.e FJfluents - Mixed Continuous - Normal Ventilation i
Nuclides Second Quarter 1991 Released Unit April l
May l
June l
Total i
- 1. Fission Gases Kr-85 Ci l
Kr-85m Ci
}
Kr-87 Ci Kr-88 Ci l
Kr-89 Ci Xe-131m Ci Xe-133 Ci 2.07E+01 1.75E-02 2.07E+01 l
Xe-133m Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci Ar-41 Cl l
l Ci 1 Ci i i
i Total Activity i Ci 1 2.07E+011 i
1.75E-02 l 2.07E+01
- 2. lodines l
l-131 Ci 1.15E-05 2.87E-05 7.45E-06l 4.77E-05 1-133 Ci 7.21 E-06 3.22E-05 1.38E-061 4.08E-05
}
- 3. Particulates Cr-51 Ci i
f Mn-54 Ci i
Fe-59 Ci i~
l Co-58 Ci 6.51 E-06 '
6.51 E-06 i
Co-60 Ci f
4 Zn-65 Ci J
1-131 Ci Cs-134 Ci i
i Cs-137 Ci
{
Ba-140 Ci t
Ge-141 Cl Ce-144 Ci i
Nd-147 Ci 8.66E-06 1.57E-05 9.00E-06 3.34E-05 Ci l
Sr-89 Ci I
Sr-90 1 Ci l
Total Activity 1 Ci i 1.52E-051 1.57E-05i 9.00E-061 3.99E-05 H-3 Ci I i
i i
Gross Alpha Ci l l
l
[
{
l l
t I
l I
Table 2.3-6 Millstone Unit No. 3
.Nrt>ome Effluents - Mixed Continuous - Normal Ventilation f
Nuclides Third Quarter 1991 Released Unit,~
Jcly l Au0ust l September l Total
- 1. Fission Gases Kr-85 Ci Kr-85m Ci Kr-o7 Ci Kr-88 Ci Kr-89 Ci i
Xe-131m Ci 5.78E+00 5.78E+00 i
Xe-133 Ci l
Xe-133m Ci 3_
-l Xe-135 Ci Xe-135m Ci Xe-138 Ci Ar-41 Cl I
l Ci _
i Ci i i
I i
Total Activity i Ci I i 5.78E+00i 1 5.78E+00 i
- 2. lodines l
l-131
" Ci i
6.19E-05 I
6.19E-05 i
1-133 1 Ci i 9.34E-05
}
9.34E-05
- 3. Particulates I
Cr-51 Ci i
~
Mn-54 Ci l
Fe-59 Ci i
i Co-58 Ci Co-60 Ci Zn-65 Ci I
~
l-131 Ci Cs-134 Ci 5.3BE-06 5.38E-06 Cs-137 Ci 4.87E-06 4.03E'-06 8.90E-06 i
Ba-140 Ci i
Ce-141 Ci Ce-144 Ci l Nd-147 Cl i 1.30E-05 1.30E-05 Ci i Sr-89 Ci Sr-90 l Ci Total Activity 1 Ci 2.33E-05 4.03E-06 2.73E-05 l
H-3 Ci l i
i I
Gross Alpha Ci l - 6.88E-07l l
l 6.88E-07 1
l Table 2.3-6 Millstone Unit No. 3 Airbome Effluents - Mixed Continuous - Normal Ventilation Nuclides Fourth Quarter 1991 Released Unit October l November l Decerrber l Total
- 1. Fission Gases g
Kr-85 Ci !
l l
Kr-85m Ci Kr-87 Ci I
Kr-88 Ci Kr-89 Ci i'
Xe-131m Ci Xe-133 Ci Xe-133m Ci f
Xe-135 Ci l
Xe-135m Ci j
l Xe-138 Ci l
[
Ar-41 Ci j
l Ci j
j I
I Ci i l
I l
Total Activity i Ci i i
i t
- 2. lodines l-131 l Ci l l
l l-133 i Ci i i
l
- 3. Particulates Cr-51 Ci i Mn-54 Ci {
l Fe-59 Ci }
j
}
l C SS8 Ci i
i l
Co-60 Ci j
i 1
l Zn-65 Ci l
5 l-131 Ci l Cs-134 Ci j Cs-137 Ci j j
l Ce-141 Ci i
j Ba-140 1 Ci l
l Ce-144 Ci i i
i Nd-147 Ci l E
Be-7 Ci i i
1.07E-051 1.07E-05 St-89 Ci Sr-90 Ci Total Activity l Ci 1.07E-05 1.07 E-05 i
H-3 l Ci {
- l i
j Gross Alpha i Ci !
6.5BE-06I 4.32E-07 7.01 E-06 i
i
1 1
Table 2.3-7 Millstone Unit No. 3 Airbome Effluents - Mixed Continuous - ESF Building Ventilation Nuclides First Quarter 1991 Released Unit January l February l March l Total
- 1. Fission Gases Kr-85 Ci l l
Kr-85m Ci l
Kr-87 Ci Kr-88 Ci Kr-89 Ci !
Xe-131 m Ci i f
Xe-133 Ci 1.75E-011 5.94E-01 i 7.69E-01 Xe-133m I Ci i
l i
Xe-135
! Ci i l
Xe-135m Ci l I
l l
Xe-138 Ci i l
i Ar-41 Ci !
i l
l Ci l l
i
! Ci !
l I
Total Activity i Ci !
1.75E-011 5.94 E-011 t
7.69E-01
- 2. lodines I-131 Ci i 8.1BE-06!
7.41 E-06 !
1.56E-05 l-133 Ci i 7.54 E-06 l 1.24E-06!
i 8.78E-06 i
- 3. Particulates Cr-51
! Ci !
j i
Mn-54 j Ci i i
Fe-59
! Ci i
~l l
Co-58 i Ci l j
9.01 E-08 l 9.01 E-08 Co-60 l Ci l l
1 i
Zn-65 i Ci i l
l 1-131 l Ci i I
i i
C&134 l Ci i Cs-137 j Ci l i
Ba-140 i Ci !
I i
Ce-141 l Ci i I
Ce-144
! Ci i i
i i Ci i
i i
i Ci i
Sr-89 i Ci r
Sr-90 i Ci i
Total Activity l Ci i i
I 9.01 E-081 9.01 E-08 H-3 Ci i
Gross Alpha Ci 2.20E-0BI 7.20E-09l l
2.92E-DE i
i
i l
Table 2.3-7 s
Millstone Unit No. 3 Airborne Effluents - Mixed Continuous - ESF Building Ventilation i
Nuclides Second Quarter 1991 l
Released Unit April l
May l
June l
Total i
i
- 1. Fission Gases Kr-85 i Ci j
i Kr-85m Ci Kr-87 Ci i
Kr-88 Ci i
Kr-89 Ci i t
Xe-131m Ci i i
Xe-133 Ci l i
l I
Xe-133m Ci i j
Xe-135 Ci l
l Xe-135m Ci J
t Xe-138 Ci l
Ar-41 Ci l
l Ci
}
Ci i
i Total Activity i Ci i i
i
- 2. lodines f
I-131 l Cl i
i i
l-133 i Cl I
I I
- 3. Particulates i
Cr-51 Ci i i
i Mn-54 Ci Fe-59 Ci j
j Co-58 Ci I 4.78E-08 i
i 4.78E-08
}
Co-60 Ci i
Zn-65 Ci i
1-131 Ci y
Cs-134 Ci !
[
Cs-137 Cl j l
j Ba-140 Ci Ce-141 Ci Ce-144 Ci.
Ci i Ci I i
i Sr-89 Ci i 1.50E-08 9.40E-09!
I 2.44E-08 Sr-90 Ci i 2.90E-09 3.80E-09 5 i
6.70E-09 Total Activity i Ci I 6.57E-081 1.32E-08 !
7.89E-08 H-3 Ci :
I i
Gross Alpha Ci l l
l
[
t h
5
t I
-t
['
Table 2.3-7 Millstone Unit No. 3 Airbome Effluents - Mixed Continuous - ESF Building Ventilation j
?
i Nuclides Third Quarter 1991 l
Released Unit July l August l September l Total l
I
- 1. Fission Gases Kr-85 Ci I l
Kr-85m Ci j i
l Kr-87 Ci l
Kr-88 Ci Kr-89 Ci f
Xe-131m Ci
[
f a
Xe-133 Ci l
l Xe-133m Ci j
l Xe-135 Ci l l
Xe-135m Ci i i
f Xe-138 Ci i
l i
Ar-41 Ci I
l l
Ci l
l j
Ci i
i Total Activrty 1 Ci i I
I
- 2. todines l-131 Ci j 3.46E-07 l l
1 3.46E-07 f
I-133 Ci i 7.90E-07 i I
I 7.90E-07
- 3. Particulates l
Cr-51 Ci i
2.32E-07 ;
2.32E-07 Mn-54 Ci i
Fe-59 Ci l
2 CoSB Ci l
Co-60 Ci Zn-65 Ci l-131 Ci l
Cs-134 Ci i
i Cs-137 Ci Ba-140 Cl l
l
.Ce-141 Ci I
Ce-144 Ci j
l Be-7 Ci 2.36E-07 i
2.36E-07 Co-57 Ci 1.47E-08 1
1.47E-08 Sr-89 Ci Sr-90 Ci Total Activity i Ci 2.51 E-07 2.32E-07 4.83E-07 j
H-3 Ci j
i Gross Alpha Ci 1.57E-08 3.70E-081 1.90E-08I 7.17E-08 e
Table 2.3-7 Millstone Unit No. 3 Airbome Effluents - Mixed Continuous - ESF Building Ventilation Nuclides Fourth Quarter 1991 Released Unit October l November l December l Total i
- 1. Fission Gases l
Kr-85 Ci i
Kr-85m Ci
[
Kr-87 Ci Kr-88 Ci Kr-89 Ci Xe-131m Ci Xe-133 Ci Xe-133m Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci Ar-41 Ci Ci l i
Ci l i
I Total Activity i Ci i I
i
- 2. lodines 1-131 Ci l I
I l
l-133 Ci i I
I l
- 3. Particulates Cr-51 Ci 1
j Mn-54 Ci Fe-59 Ci Co-58 Ci Co-60 Ci j
Zn-65 Ci l
l-131 Ci Cs-134 Ci j
Cs-137 Ci Ba-140 Ci Ce-141 Ci I
(
Ce-144 Ci
(
Be-7 Ci Co-57 Ci 1
Sr-89 Ci Sr-90 Ci Total Activily Ci H-3 Cl l l
j Gross Alpha Ci I 1.30E-08 8.90E-091 1.10E-08l 329E-08 f
Table 2.3-9 Millstone Unit No. 3 Airtome Effluents - M;xed Batch - Containment Purges Nuchdes Third Quarter 1991 Released Unit July l August l September l Total
- 1. Fission Gases Xe-138 I Ci l 1
j Kr-87 Ci Kr-88 Ci Kr-85m Ci Xe-135 Ci 1.70E-02' 1.70E-02 Xe-133 Ci 9.2-t E-02 9.24E-02 Kr-89 Ci Xe-137 Ci Xe-135m Ci ;
Kr-83m Ci l i
Xe-133m Ci l 2.57E-03 )
2.57E-03 Xe-131m Ci !
i l
Kr-85 Ci i
i i
Ar-37 l Ci i i
i i
Total Activity i Ci i 1.12E-011 i
1 1.12E-01
- 2. lodines 1-131 Ci i 6.25E-07l l
l 6.25E-07 l-133 Ci i I
i f
- 3. Particulates Cr-51 Ci i
i Mn-54 Ci i
i I
fos 9 Ci i
l Co-58 Ci i d
C&60 Ci j
i Zn-65 Ci i
l l-131 Ci i
CS134 Ci j
i Cs-137 Ci l
l Ba-140 Ci l
i Ce-141 Ci l
Ce-144 Ci j i
Mo-99 Ci I
)
Be-7 Ci i l
i Ci}
j Sr-89 Sr-90 Ci i Total Activity i Ci i l
I j
i H-3 Ci l 1.29E-02 1.29E-02 Gross Alpha Ci !
i i
I Paue 8 of 21 i
Effluent and Waste Disposal Semiannual Report j
Solid Waste and Irradiated Component Shipments l
31illstone Unit 2 July 1,1992 - December 31,1992 6-Month Period Estimated Total
- 1. Type of Waste Disposition Units Totals Error. %
3 10.8 l
a) Spent Resin, Fitter Studge-(CNSI) m l
Evaporator Bottoms, Etc.
Burial Ci 2 80E-01 25?L l
1 3
2.5 (SEG) m Supercompaction Ci 2.54E-04 25*h b) Dry Compressible Waste.
(CNSI) m3 640 3 i
Contaminated Equipment. Etc.
Burial Ci 2.70E+03 25 %
l 3
(SEG) m 1itt9 Supercompaction Ci 9 29E-n2 25 %
(SEG) 3 o
i Burial m
CNSI Ci 0
N/A i
(SEG) 3 22.4 Burial m
US Ecology Ci 217E-01 25?L l
3 139.6 (Quadrex) m i
Decontamination Ci 8 81E-02 25?b (Quadrex) 3 Burial m
3o CNSI Ci 1.32E-01 25?L i
(Quadrex) 3 Bunal m
o; USEcology Ci 3.74E-n3 25 %
3 2.0 i
c) Irradiated Components Control (CNSI) m Rods, Etc' Bunal Ci 1.44 E-00 25?L I
l
~.
i i
1 1
Page 9 of 21
-l
- 2. Estimates of Major Nuclide Composition (By Type of Waste)
{
a) Spent Resin, Filter Sludges, Evaporator Bottoms Millstone to CNSI for Burial l
- Nuclide
% of Total H-3 0.03 %
j C-14 1.74 %
Mn-54 1.35 %
i Fe-55 19.75 %
j Co-58 7.39%
j Co-60 52.12 %
j Ni-63 11.41 %
'{
St-89 co Ola' Sr-90 0.08 %
l Nb-95 0.10a'.
Zr-95 0.32 %
.j Tc-99 1.20 %
Ag-110m 0.17 %
f Sb-125 3.86 %
L Cs-134 0.06 %
Cs-137 0.23 %
l Np-237
<0.1%
<0.01%
<0.01%
l Am-241
<0.01%
Pu-241 0.17 %
Cm-242
<0.01%
i Pu-242
<0.01%
l Cm-244
<0.01%
i l
Millstone to SEG for Supercompaction Nuclide
% of Total Co-60 100.00 %
l i
I