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{{#Wiki_filter:A 6; . . . | {{#Wiki_filter:A 6; . . . | ||
f lIL.) | f lIL.) | ||
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1 Jan 1980 THROUGH June 30, 1980 SUPPLEMENTAL INFORMATION Facility - Prairie Island Nuclear Generating Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60 | EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1 Jan 1980 THROUGH June 30, 1980 SUPPLEMENTAL INFORMATION Facility - Prairie Island Nuclear Generating Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60 | ||
Line 35: | Line 33: | ||
: 2. Maximum Permissible Concentrations a.- Fission and activation gases (and all other radioactive isotopes except halogen and particulate isotopes with half-lives greater than 8 days) in gaseous releases: | : 2. Maximum Permissible Concentrations a.- Fission and activation gases (and all other radioactive isotopes except halogen and particulate isotopes with half-lives greater than 8 days) in gaseous releases: | ||
10 CFR 20,' Appendix B, Table 2, Column 1 4009090 M4, | 10 CFR 20,' Appendix B, Table 2, Column 1 4009090 M4, | ||
; ' T n; - | ; ' T n; - | ||
, ' 's | , ' 's | ||
. 2. ; Maximum Permissible ~ Concentrations | . 2. ; Maximum Permissible ~ Concentrations z b '.' . - Iodine.and particulates.with half-lives greater than 8 days in gaseous releases: p t | ||
z b '.' . - Iodine.and particulates.with half-lives greater than 8 days in gaseous releases: p t | |||
10 CFR 20, Appendix.B, Table 2. Column 1 | 10 CFR 20, Appendix.B, Table 2. Column 1 | ||
_ c. Liquid. Effluents: | _ c. Liquid. Effluents: | ||
10 CFR 20 Appendix B,' Table 2, Column 2 | 10 CFR 20 Appendix B,' Table 2, Column 2 | ||
: 3. .-Average Energy Not applicable to Prairie Island Regulatory Limits. | : 3. .-Average Energy Not applicable to Prairie Island Regulatory Limits. | ||
! 4. Measurements and Approximations of Total Radioactivity | ! 4. Measurements and Approximations of Total Radioactivity | ||
: a. ' Fission and' activation gases Total Geli - | : a. ' Fission and' activation gases Total Geli - | ||
in gaseous releases: Nuclide Geli | in gaseous releases: Nuclide Geli | ||
: b. Iodines' in gaseous releases Total Gell 4 | : b. Iodines' in gaseous releases Total Gell 4 | ||
Nuclide Geli | Nuclide Geli j' c. Particulates in gaseous Total Geli releases: Nuclide Geli , | ||
'd.- _ Liquid' Effluents: Total Gross Beta Gamma j Nuclide Geli j BATCH RELEASES a.. Liquid' . QTR 1 QTR 2 Number of Batch Releases 6.40E01 4.40E01 | |||
j' c. Particulates in gaseous Total Geli | |||
'd.- _ Liquid' Effluents: Total Gross Beta Gamma j Nuclide Geli j BATCH RELEASES | |||
a.. Liquid' . QTR 1 QTR 2 Number of Batch Releases 6.40E01 4.40E01 | |||
' Total . Time Period 'for a Batch Release (hr) 1.03E02 6.62E01 Maximum Time for a Batch Release (hr) 4.20E00 2.30E00 Average Time for a Batch Release (hr) 1.61E00 1.50E00 Minimum Time. for a Batch-Release .(hr) 8.00E-01 1.00E00 | ' Total . Time Period 'for a Batch Release (hr) 1.03E02 6.62E01 Maximum Time for a Batch Release (hr) 4.20E00 2.30E00 Average Time for a Batch Release (hr) 1.61E00 1.50E00 Minimum Time. for a Batch-Release .(hr) 8.00E-01 1.00E00 | ||
' Ave Mississippi flow during Quarter (CFS) | ' Ave Mississippi flow during Quarter (CFS) 8.36E03 1 2.08E04 | ||
8.36E03 1 2.08E04 | |||
: b. . Gaseous QTR l' QTR ' Number of Batch Releases 1.00E01 3.00E00- | : b. . Gaseous QTR l' QTR ' Number of Batch Releases 1.00E01 3.00E00- | ||
-Total Tine Period for Batch Releases (hr) 1.62E02 3.32E01 Maximum Time for:a Batch Release (hr) " 5.39E01 2.34E01 | -Total Tine Period for Batch Releases (hr) 1.62E02 3.32E01 Maximum Time for:a Batch Release (hr) " 5.39E01 2.34E01 | ||
_ Average' Time for a Batch Release (hr) | _ Average' Time for a Batch Release (hr) | ||
~ | ~ | ||
. 1.62E01- 1.11E01 | . 1.62E01- 1.11E01 Minimum Time for a: Batch Release (hr) 1.20E00 1.80E00 v | ||
v | |||
= | = | ||
9 L y | 9 L y | ||
' ' ,j i , _ | ' ' ,j i , _ | ||
1 m , ...w | 1 m , ...w | ||
[ . 's. . | [ . 's. . | ||
ABNORMAL' RELEASES | ABNORMAL' RELEASES | ||
: a. ' Liquid QTR 1 QTR 2 | : a. ' Liquid QTR 1 QTR 2 Number of Releases 0.00E00 O.00E00 | ||
Number of Releases 0.00E00 O.00E00 | |||
-Total Activity Released (C1) 0.00E00 i-0.00E00 Total Tritium Released (C1) 0.00E00 1 0.00E00 | -Total Activity Released (C1) 0.00E00 i-0.00E00 Total Tritium Released (C1) 0.00E00 1 0.00E00 | ||
~b.: [ Gaseous. OTR 1 QTR 2 Number of Releases- 0.00E00 l1.00E00 | ~b.: [ Gaseous. OTR 1 QTR 2 Number of Releases- 0.00E00 l1.00E00 | ||
~ Total; Activity Releases (C1) 0.00E00 i1.59E-01 | ~ Total; Activity Releases (C1) 0.00E00 i1.59E-01 | ||
? | ? | ||
1 i | 1 i | ||
s l l | s l l | ||
u | u | ||
, . .~ . . _ . - - . . - _ | , . .~ . . _ . - - . . - _ | ||
l cr i | l cr i | ||
)7 TABLE'lA' | )7 TABLE'lA' | ||
. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS -'SUFJfATION OF ALL RELEASES UNIT QTR L QTR L ERR R A. Fission and Activation Cases | . EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS -'SUFJfATION OF ALL RELEASES UNIT QTR L QTR L ERR R A. Fission and Activation Cases Total Release Ci l 1.24E02 3.69E01 1 50% | ||
Average Release Rate pCi/seei 1.35E01 4.69E00 B. Short Lived Particulate (t1/2 < 8 days) , | |||
Total Release Ci l 1.24E02 3.69E01 1 50% | |||
Average Release Rate pCi/seei 1.35E01 4.69E00 | |||
B. Short Lived Particulate (t1/2 < 8 days) , | |||
Total Release ci 7.65E-04 1 4.03E-01 I. 50% | Total Release ci 7.65E-04 1 4.03E-01 I. 50% | ||
Averare Release Rate- UCi/sec 9.73E-05 1 5.13E-04 i | Averare Release Rate- UCi/sec 9.73E-05 1 5.13E-04 i | ||
'C.. Tritium Total Re'1 ease Ci 3.19E01 1.33E01 2. 50% | |||
'C.. Tritium | |||
Average Release Rate pCi/sec 4.06E00 1.69E00 i Total A & B & C- pCi/sec 1.99E01 6.38E00 2 of Design Objective % 5.26E00 1.69E00 i- | Average Release Rate pCi/sec 4.06E00 1.69E00 i Total A & B & C- pCi/sec 1.99E01 6.38E00 2 of Design Objective % 5.26E00 1.69E00 i- | ||
, D. Iodines i' | , D. Iodines i' | ||
'! Total 1131 Ci 2.19E-04 4.32E-05 2; 50% | '! Total 1131 Ci 2.19E-04 4.32E-05 2; 50% | ||
lAverage Release Rate UCi/sec 2.79E-05 5.50E-06 i E. Long-Lived Particulates (t1/2 > 8 days) | lAverage Release Rate UCi/sec 2.79E-05 5.50E-06 i E. Long-Lived Particulates (t1/2 > 8 days) | ||
Total Release Ci 5.78E-05 0.00F00 d; 50% | Total Release Ci 5.78E-05 0.00F00 d; 50% | ||
Average Release Rate pCi/sec 7.35E 0,6 0.00E00 Total D & E- UCi/sec 3.53E-05 5.50E-06 | Average Release Rate pCi/sec 7.35E 0,6 0.00E00 Total D & E- UCi/sec 3.53E-05 5.50E-06 | ||
% of Design Objective % 5.271:-01 8.21E-02 F. Gross Alpha. | % of Design Objective % 5.271:-01 8.21E-02 F. Gross Alpha. | ||
' lTo tal - Re lease (Ci l' 4.97E-09 'l 1.99E-08 l d; 100% l P | |||
' lTo tal - Re lease (Ci l' 4.97E-09 'l 1.99E-08 l d; 100% l | |||
P | |||
L ! | L ! | ||
L. | L. | ||
;y , " ' ; | ;y , " ' ; | ||
TABLE 13. | TABLE 13. | ||
~ EFFLUENT AND WASTE DISPOSAL-SEMIANNUAL REPORT | ~ EFFLUENT AND WASTE DISPOSAL-SEMIANNUAL REPORT | ||
. GASEOUS EFFLUENTS | . GASEOUS EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDE- UNIT; .QTRj(, QTRjL, QTRJ, QTR 2 | ||
CONTINUOUS MODE BATCH MODE NUCLIDE- UNIT; .QTRj(, QTRjL, QTRJ, QTR 2 | |||
_, i | _, i | ||
: 1. Fission and Activation Gases | : 1. Fission and Activation Gases Kr85- Ci t 4.71E-01 2.18E-01 Kr85m- C1 -7.76E-01 i 3.45E-04 Kr87- Ci 1.82E00 1 3.40E-04 Kr88 Ci 1.35E-04 Xe133' Ci 9.98E01 3.61E01 5.99E00 3.21E-01 Xe135- C1 4.72E00 , 6.13E-02 2.50E-01 Xe135'm Ci Xe138' C1 Xe131m C1- 1.54E-03 Ar41 Ci 1.01E01 1.51E-02 4.49E-02 1.69E-04 Xe133m C1 2.42E-02 Total C1 1.1/EUZ 3.61E01 6.56E00 8.36E-01 | ||
Kr85- Ci t 4.71E-01 2.18E-01 Kr85m- C1 -7.76E-01 i 3.45E-04 | |||
Kr87- Ci 1.82E00 1 3.40E-04 Kr88 Ci 1.35E-04 Xe133' Ci 9.98E01 3.61E01 5.99E00 3.21E-01 Xe135- C1 4.72E00 , 6.13E-02 2.50E-01 | |||
Xe133m C1 2.42E-02 Total C1 1.1/EUZ 3.61E01 6.56E00 8.36E-01 | |||
' 2. Iodines Il31 C1 2.18E-04 4.32E-05 6.77E-07 4.91E-08 1133 C1 2.03E-08 1135 Ci-Total- Ci _ | ' 2. Iodines Il31 C1 2.18E-04 4.32E-05 6.77E-07 4.91E-08 1133 C1 2.03E-08 1135 Ci-Total- Ci _ | ||
2.18E-04 4.32E-05 6.97E-07 4.91E-08 CONTINUOUS MODE BATCH MODE | 2.18E-04 4.32E-05 6.97E-07 4.91E-08 CONTINUOUS MODE BATCH MODE NUCLIDE. -UNIT QTR L QTR L QTR J QTR J | ||
NUCLIDE. -UNIT QTR L QTR L QTR J QTR J | |||
, 3. Particulates Sr89 'Ci Sr90- Ci- | , 3. Particulates Sr89 'Ci Sr90- Ci- | ||
_.^ | _.^ | ||
Cs134 Ci- ' | Cs134 Ci- ' | ||
Cs137- ~Ci ' '''~~~' | Cs137- ~Ci ' '''~~~' | ||
i Ea-Lal40 Ci- l CoS8 C1 3.63E-05 1 ~ ~ '' ' ~~~ i Co60' Ci '' 2.15E-05 [ "' [, | i Ea-Lal40 Ci- l CoS8 C1 3.63E-05 1 ~ ~ '' ' ~~~ i Co60' Ci '' 2.15E-05 [ "' [, | ||
Line 178: | Line 106: | ||
Sbl24 Ci Na24 'Ci Co57- Ci'- | Sbl24 Ci Na24 'Ci Co57- Ci'- | ||
Cel44 Ci , | Cel44 Ci , | ||
Zr-Nb 9 5 ' -Ci i | Zr-Nb 9 5 ' -Ci i Rb86- l Ci- __ | ||
Rb86- l Ci- __ | |||
7 . 6 5 E- 4 '+ i 4.03E-03 T | 7 . 6 5 E- 4 '+ i 4.03E-03 T | ||
+ % | + % | ||
f TABLE 13 EFFLUENT AND WASTE DISPOSAL SD1IANNUAL REPORT . | f TABLE 13 EFFLUENT AND WASTE DISPOSAL SD1IANNUAL REPORT . | ||
CASE 00S EFFLUENTS. | CASE 00S EFFLUENTS. | ||
Line 194: | Line 116: | ||
, Y88- C1 2_RQF-OR 7 | , Y88- C1 2_RQF-OR 7 | ||
Zr-97 C1 1.65E-07 | Zr-97 C1 1.65E-07 | ||
) TOTAL ~' Ci 5.80E-05 0.00F00 1 7.65v-04 &_017 n1 | ) TOTAL ~' Ci 5.80E-05 0.00F00 1 7.65v-04 &_017 n1 2-4 4 | ||
2-4 | |||
4 | |||
c -s- | c -s- | ||
w . . '' | w . . '' | ||
TABLE.2A EFFLUENT AND WASTE DISP 0AL SEMIINNUAL REPORT LIQUID EFFLUENTS - SUh7ATION OF ALL RELEASES UNIT TOTAL QTR 1 QTR 1 ERROR L A. Fission and Activation Products-To tal Release W/0 H-3, Rad Gas , Alpha Ci 1.67E-03 1.73E-03 + 5.0E01 Averane = Diluted Concentration pCi/ml 7.70E-12 3.90E-12 | TABLE.2A EFFLUENT AND WASTE DISP 0AL SEMIINNUAL REPORT LIQUID EFFLUENTS - SUh7ATION OF ALL RELEASES UNIT TOTAL QTR 1 QTR 1 ERROR L A. Fission and Activation Products-To tal Release W/0 H-3, Rad Gas , Alpha Ci 1.67E-03 1.73E-03 + 5.0E01 Averane = Diluted Concentration pCi/ml 7.70E-12 3.90E-12 | ||
% of T. S. Annual Curie Design Objective .%. 1.67E-02 1.73E-02 1 B.: Tritium Total Release Ci 1.02E02 1.60E02 + 2.5E01 Average Diluted Concentration pCi/ml 4.70E-07 3.60E-07 3 of T. S. Annual Design Objective Conc c% 9.40E00 7.20E00 _ | % of T. S. Annual Curie Design Objective .%. 1.67E-02 1.73E-02 1 B.: Tritium Total Release Ci 1.02E02 1.60E02 + 2.5E01 Average Diluted Concentration pCi/ml 4.70E-07 3.60E-07 3 of T. S. Annual Design Objective Conc c% 9.40E00 7.20E00 _ | ||
C. Dissolved and Entrained Gases | C. Dissolved and Entrained Gases | ||
; Total Release Ci 5.24E-03 l 3.24E-02 + 5.0E01-Ave rage Diluted Concentration uC1/ml 2.41E-11 l 7.30E-ll | ; Total Release Ci 5.24E-03 l 3.24E-02 + 5.0E01-Ave rage Diluted Concentration uC1/ml 2.41E-11 l 7.30E-ll D. Gross Alph-s trotal Release (Ci i 1.22E-05 I 3.70E-09 f + 5.0E01' E. .Volme of Waste (Prior to Dilution) l liters i 4.79E07 1 3.91E07 !~+ 2.5E01 F. Volume of Dilution Water l liters i 2.17E11 1 4.44 Ell i +5.0E01 | ||
D. Gross Alph-s trotal Release (Ci i 1.22E-05 I 3.70E-09 f + 5.0E01' E. .Volme of Waste (Prior to Dilution) l liters i 4.79E07 1 3.91E07 !~+ 2.5E01 | |||
F. Volume of Dilution Water l liters i 2.17E11 1 4.44 Ell i +5.0E01 | |||
-7~ l l | -7~ l l | ||
) | ) | ||
w | w | ||
w ., | w ., | ||
s -TABLE 2A' EFFLUENT-AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID' EFFLUENTS --SUMMATION OF.ALL RELEASES | s -TABLE 2A' EFFLUENT-AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID' EFFLUENTS --SUMMATION OF.ALL RELEASES | ||
? Continuous Mode Batch Mode-. | ? Continuous Mode Batch Mode-. | ||
NUCLIDE1 UNIT QTR L . . | NUCLIDE1 UNIT QTR L . . | ||
QTR l QTR 1 QTR | QTR l QTR 1 QTR Sr89 Ci I I - | ||
Sr89 Ci I I - | |||
S r90' Ci I l~ | S r90' Ci I l~ | ||
Cal 34 C1 - I- . | Cal 34 C1 - I- . | ||
Cs137 ' | Cs137 ' | ||
C1 R.Rav-06 1 Il31 Ci s.osv-as l' | C1 R.Rav-06 1 Il31 Ci s.osv-as l' CoS8 C1 1.33E-04 9.09E-05 8.60E-04 I 3.45E-04 Co60 C1 2.30E-04 I -2.30E-04 1.79E-04 i 6.20E-04 Fe59 Ci i Zn65- Ci i I Mn54- Ci- 2.22E-05 1 1.26E-04 1.07E-05 i - | ||
CoS8 C1 1.33E-04 9.09E-05 8.60E-04 I 3.45E-04 Co60 C1 2.30E-04 I -2.30E-04 1.79E-04 i 6.20E-04 Fe59 Ci i Zn65- Ci i I Mn54- Ci- 2.22E-05 1 1.26E-04 1.07E-05 i - | |||
Cr51 Ci l i I l Zr-Nb95- Ci i 1.56E-05 i 9.42E-06 i Mo99 Ci i- I j Ba-la140 Ci- I ! | Cr51 Ci l i I l Zr-Nb95- Ci i 1.56E-05 i 9.42E-06 i Mo99 Ci i- I j Ba-la140 Ci- I ! | ||
Ag110m Ci i i 2.98E-05 : | Ag110m Ci i i 2.98E-05 : | ||
Line 251: | Line 144: | ||
CdlC9 C1 i Rb88 ~Ci _ | CdlC9 C1 i Rb88 ~Ci _ | ||
l | l | ||
. I | . I To tal -' C1 3.85E 4.56E 1.12E-03 1.00E-03 l' Continuous Mode Batch Mode i | ||
To tal -' C1 3.85E 4.56E 1.12E-03 1.00E-03 l' Continuous Mode Batch Mode i | |||
NUCLIDE . UNIT 'QTR l_. QTR 2_. .ylk 1 QTF 2_j e | NUCLIDE . UNIT 'QTR l_. QTR 2_. .ylk 1 QTF 2_j e | ||
Xt133 Ci .I 5.24E-03 3.22E-02 l-Xs133m Ci 1.34E-04 ! | Xt133 Ci .I 5.24E-03 3.22E-02 l-Xs133m Ci 1.34E-04 ! | ||
Line 259: | Line 150: | ||
Kr85m- Ci l Kr85 Ci , | Kr85m- Ci l Kr85 Ci , | ||
Kr88 C1 i Kr87 .Ci 4.69E-06 | Kr88 C1 i Kr87 .Ci 4.69E-06 | ||
.I | .I k * | ||
k * | |||
; rn. , | ; rn. , | ||
- y.y -p | - y.y -p n , | ||
t 1 4 - | |||
, ; TABLE.3 EFFLUENT AND WASTE DISPOSAL SEMIA!DIUAL REPORT-1-l-80 through- 6-30-80 | |||
n , | |||
t 1 | |||
4 - | |||
, ; TABLE.3 | |||
EFFLUENT AND WASTE DISPOSAL SEMIA!DIUAL REPORT-1-l-80 through- 6-30-80 | |||
..-Solid. Waste and Irradiatted Fuel Shipments | ..-Solid. Waste and Irradiatted Fuel Shipments | ||
% d | % d | ||
. A.. ' Solid waste shipped'offsite for burial or disposal (not irradiated fuel) , | . A.. ' Solid waste shipped'offsite for burial or disposal (not irradiated fuel) , | ||
Line 290: | Line 164: | ||
Ci 0- i | Ci 0- i | ||
: b. . Dry compressible. waste... contaminated ft3 12951.8' equipment, evaporator, bottoms, etc. Ci 23.7 -+-25% | : b. . Dry compressible. waste... contaminated ft3 12951.8' equipment, evaporator, bottoms, etc. Ci 23.7 -+-25% | ||
: c. =Ir:-adiated components, control rods, | : c. =Ir:-adiated components, control rods, fc3 0 __, | ||
fc3 0 __, | |||
etc. Ci 0 | etc. Ci 0 | ||
: d. Other (describe) lfh l 0 j ~~ | : d. Other (describe) lfh l 0 j ~~ | ||
: 2. Estimate .of major nuclide- composition _ (by type of waste) . | : 2. Estimate .of major nuclide- composition _ (by type of waste) . | ||
p , | p , | ||
a.- None % | |||
i % + | i % + | ||
t i % !' | t i % !' | ||
l ! | l ! | ||
! i | ! i | ||
- b. Co-60' +68.1 % i | - b. Co-60' +68.1 % i do-58 ,10.8' % ! | ||
Cs-137- f3.9 : I Mn-54' ' | |||
do-58 ,10.8' % ! | |||
Cs-137- f3.9 : I | |||
Mn-54' ' | |||
! 6.2 % | ! 6.2 % | ||
Cs-134 l1.2-g l Zr-95 l 5.1-1 | Cs-134 l1.2-g l Zr-95 l 5.1-1 | ||
- %L . . I. .- - - . --- - | - %L . . I. .- - - . --- - | ||
Line 321: | Line 182: | ||
--a1 4.7 % ., | --a1 4.7 % ., | ||
l . . - . | l . . - . | ||
I L. | I L. | ||
I % | I % | ||
.i - | .i - | ||
3.. Solid-Waste Disposition | 3.. Solid-Waste Disposition | ||
.Nu'mber of Shipments Mode of Transportation Destination | .Nu'mber of Shipments Mode of Transportation Destination 15' _ Truck- Richland, WA | ||
15' _ Truck- Richland, WA | |||
-B. Irradiated ' Fuel- Shipments (disposition) | -B. Irradiated ' Fuel- Shipments (disposition) | ||
.9.- | .9.- | ||
1 i | 1 i | ||
2 ..}} | 2 ..}} |
Latest revision as of 11:45, 18 February 2020
ML19337A211 | |
Person / Time | |
---|---|
Site: | Prairie Island |
Issue date: | 08/28/1980 |
From: | NORTHERN STATES POWER CO. |
To: | |
Shared Package | |
ML19337A209 | List: |
References | |
NUDOCS 8009090302 | |
Download: ML19337A211 (9) | |
Text
A 6; . . .
f lIL.)
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1 Jan 1980 THROUGH June 30, 1980 SUPPLEMENTAL INFORMATION Facility - Prairie Island Nuclear Generating Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60
- 1. Regulatorv Limits Action is required if the rate of release of radioactive materials, when averaged over a three-month period, is such that these quantities, if continued at the same release race for a year, would exceed twice the design objectives. Design objectives are:
- a. Fission and activation gases (and all other radioactive isotopes except halogen and particulate isotopes with half-lives greater than 8 days) in gaseous releases:
3 41 <
_ 1300 m /sec MPC g
- b. Iodines and.particulates with half-lives greater than 8 days in gaseous releases:
Qi <
_ 67 m /sec i i
- c. Liquid Effluents:
- 1. Annual total quantity of radioactive material in liquid waste, excluding tritium and dissolved gases, of 5 Ci per unit.
- 2. Annual average concentration of radioactive material in liquid waste, prior to dilucion in the Mississgppi River, excluding tritium and dissolved gases, of 2 X 10 pC1/ml.
- 3. Annua 1' average concentration of tritium in liqug waste, prior to dilution in the Mississippi River, of 5 X 10 pC1/ml.
- 2. Maximum Permissible Concentrations a.- Fission and activation gases (and all other radioactive isotopes except halogen and particulate isotopes with half-lives greater than 8 days) in gaseous releases:
10 CFR 20,' Appendix B, Table 2, Column 1 4009090 M4,
- ' T n; -
, ' 's
. 2. ; Maximum Permissible ~ Concentrations z b '.' . - Iodine.and particulates.with half-lives greater than 8 days in gaseous releases: p t
10 CFR 20, Appendix.B, Table 2. Column 1
_ c. Liquid. Effluents:
10 CFR 20 Appendix B,' Table 2, Column 2
- 3. .-Average Energy Not applicable to Prairie Island Regulatory Limits.
! 4. Measurements and Approximations of Total Radioactivity
- a. ' Fission and' activation gases Total Geli -
in gaseous releases: Nuclide Geli
- b. Iodines' in gaseous releases Total Gell 4
Nuclide Geli j' c. Particulates in gaseous Total Geli releases: Nuclide Geli ,
'd.- _ Liquid' Effluents: Total Gross Beta Gamma j Nuclide Geli j BATCH RELEASES a.. Liquid' . QTR 1 QTR 2 Number of Batch Releases 6.40E01 4.40E01
' Total . Time Period 'for a Batch Release (hr) 1.03E02 6.62E01 Maximum Time for a Batch Release (hr) 4.20E00 2.30E00 Average Time for a Batch Release (hr) 1.61E00 1.50E00 Minimum Time. for a Batch-Release .(hr) 8.00E-01 1.00E00
' Ave Mississippi flow during Quarter (CFS) 8.36E03 1 2.08E04
-Total Tine Period for Batch Releases (hr) 1.62E02 3.32E01 Maximum Time for:a Batch Release (hr) " 5.39E01 2.34E01
_ Average' Time for a Batch Release (hr)
~
. 1.62E01- 1.11E01 Minimum Time for a: Batch Release (hr) 1.20E00 1.80E00 v
=
9 L y
' ' ,j i , _
1 m , ...w
[ . 's. .
ABNORMAL' RELEASES
-Total Activity Released (C1) 0.00E00 i-0.00E00 Total Tritium Released (C1) 0.00E00 1 0.00E00
~b.: [ Gaseous. OTR 1 QTR 2 Number of Releases- 0.00E00 l1.00E00
~ Total; Activity Releases (C1) 0.00E00 i1.59E-01
?
1 i
s l l
u
, . .~ . . _ . - - . . - _
l cr i
)7 TABLE'lA'
. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS -'SUFJfATION OF ALL RELEASES UNIT QTR L QTR L ERR R A. Fission and Activation Cases Total Release Ci l 1.24E02 3.69E01 1 50%
Average Release Rate pCi/seei 1.35E01 4.69E00 B. Short Lived Particulate (t1/2 < 8 days) ,
Total Release ci 7.65E-04 1 4.03E-01 I. 50%
Averare Release Rate- UCi/sec 9.73E-05 1 5.13E-04 i
'C.. Tritium Total Re'1 ease Ci 3.19E01 1.33E01 2. 50%
Average Release Rate pCi/sec 4.06E00 1.69E00 i Total A & B & C- pCi/sec 1.99E01 6.38E00 2 of Design Objective % 5.26E00 1.69E00 i-
, D. Iodines i'
'! Total 1131 Ci 2.19E-04 4.32E-05 2; 50%
lAverage Release Rate UCi/sec 2.79E-05 5.50E-06 i E. Long-Lived Particulates (t1/2 > 8 days)
Total Release Ci 5.78E-05 0.00F00 d; 50%
Average Release Rate pCi/sec 7.35E 0,6 0.00E00 Total D & E- UCi/sec 3.53E-05 5.50E-06
% of Design Objective % 5.271:-01 8.21E-02 F. Gross Alpha.
' lTo tal - Re lease (Ci l' 4.97E-09 'l 1.99E-08 l d; 100% l P
L !
L.
- y , " ' ;
TABLE 13.
~ EFFLUENT AND WASTE DISPOSAL-SEMIANNUAL REPORT
. GASEOUS EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDE- UNIT; .QTRj(, QTRjL, QTRJ, QTR 2
_, i
- 1. Fission and Activation Gases Kr85- Ci t 4.71E-01 2.18E-01 Kr85m- C1 -7.76E-01 i 3.45E-04 Kr87- Ci 1.82E00 1 3.40E-04 Kr88 Ci 1.35E-04 Xe133' Ci 9.98E01 3.61E01 5.99E00 3.21E-01 Xe135- C1 4.72E00 , 6.13E-02 2.50E-01 Xe135'm Ci Xe138' C1 Xe131m C1- 1.54E-03 Ar41 Ci 1.01E01 1.51E-02 4.49E-02 1.69E-04 Xe133m C1 2.42E-02 Total C1 1.1/EUZ 3.61E01 6.56E00 8.36E-01
' 2. Iodines Il31 C1 2.18E-04 4.32E-05 6.77E-07 4.91E-08 1133 C1 2.03E-08 1135 Ci-Total- Ci _
2.18E-04 4.32E-05 6.97E-07 4.91E-08 CONTINUOUS MODE BATCH MODE NUCLIDE. -UNIT QTR L QTR L QTR J QTR J
, 3. Particulates Sr89 'Ci Sr90- Ci-
_.^
Cs134 Ci- '
Cs137- ~Ci ' ~~~'
i Ea-Lal40 Ci- l CoS8 C1 3.63E-05 1 ~ ~ ' ~~~ i Co60' Ci 2.15E-05 [ "' [,
Cd109 - Ci s
~~
Sbl24 Ci Na24 'Ci Co57- Ci'-
Cel44 Ci ,
Zr-Nb 9 5 ' -Ci i Rb86- l Ci- __
7 . 6 5 E- 4 '+ i 4.03E-03 T
+ %
f TABLE 13 EFFLUENT AND WASTE DISPOSAL SD1IANNUAL REPORT .
CASE 00S EFFLUENTS.
, ^ 3. Particulates-Sr85 C1 '
i I Mn54 C1 Cs138 Ci
, Y88- C1 2_RQF-OR 7
Zr-97 C1 1.65E-07
) TOTAL ~' Ci 5.80E-05 0.00F00 1 7.65v-04 &_017 n1 2-4 4
c -s-
w . .
TABLE.2A EFFLUENT AND WASTE DISP 0AL SEMIINNUAL REPORT LIQUID EFFLUENTS - SUh7ATION OF ALL RELEASES UNIT TOTAL QTR 1 QTR 1 ERROR L A. Fission and Activation Products-To tal Release W/0 H-3, Rad Gas , Alpha Ci 1.67E-03 1.73E-03 + 5.0E01 Averane = Diluted Concentration pCi/ml 7.70E-12 3.90E-12
% of T. S. Annual Curie Design Objective .%. 1.67E-02 1.73E-02 1 B.: Tritium Total Release Ci 1.02E02 1.60E02 + 2.5E01 Average Diluted Concentration pCi/ml 4.70E-07 3.60E-07 3 of T. S. Annual Design Objective Conc c% 9.40E00 7.20E00 _
C. Dissolved and Entrained Gases
- Total Release Ci 5.24E-03 l 3.24E-02 + 5.0E01-Ave rage Diluted Concentration uC1/ml 2.41E-11 l 7.30E-ll D. Gross Alph-s trotal Release (Ci i 1.22E-05 I 3.70E-09 f + 5.0E01' E. .Volme of Waste (Prior to Dilution) l liters i 4.79E07 1 3.91E07 !~+ 2.5E01 F. Volume of Dilution Water l liters i 2.17E11 1 4.44 Ell i +5.0E01
-7~ l l
)
w
w .,
s -TABLE 2A' EFFLUENT-AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID' EFFLUENTS --SUMMATION OF.ALL RELEASES
? Continuous Mode Batch Mode-.
NUCLIDE1 UNIT QTR L . .
S r90' Ci I l~
Cal 34 C1 - I- .
Cs137 '
C1 R.Rav-06 1 Il31 Ci s.osv-as l' CoS8 C1 1.33E-04 9.09E-05 8.60E-04 I 3.45E-04 Co60 C1 2.30E-04 I -2.30E-04 1.79E-04 i 6.20E-04 Fe59 Ci i Zn65- Ci i I Mn54- Ci- 2.22E-05 1 1.26E-04 1.07E-05 i -
Cr51 Ci l i I l Zr-Nb95- Ci i 1.56E-05 i 9.42E-06 i Mo99 Ci i- I j Ba-la140 Ci- I !
Ag110m Ci i i 2.98E-05 :
Na24 Ci t I W187 ~Ci i i ,
Sbl24- Ci 1 i Sr85' Ci i-Cal 36 C1 !
Zr-Nb97 Ci '
CdlC9 C1 i Rb88 ~Ci _
l
. I To tal -' C1 3.85E 4.56E 1.12E-03 1.00E-03 l' Continuous Mode Batch Mode i
NUCLIDE . UNIT 'QTR l_. QTR 2_. .ylk 1 QTF 2_j e
Xt133 Ci .I 5.24E-03 3.22E-02 l-Xs133m Ci 1.34E-04 !
Xal31m - Ci i Xs135 C1' 9.03E !
Kr85m- Ci l Kr85 Ci ,
Kr88 C1 i Kr87 .Ci 4.69E-06
.I k *
- rn. ,
- y.y -p n ,
t 1 4 -
, ; TABLE.3 EFFLUENT AND WASTE DISPOSAL SEMIA!DIUAL REPORT-1-l-80 through- 6-30-80
..-Solid. Waste and Irradiatted Fuel Shipments
% d
. A.. ' Solid waste shipped'offsite for burial or disposal (not irradiated fuel) ,
- . 1.- Type-of: Waste Unit '6 Month Est. Total !
Period Error %
u- a. Spent Resinsy feJ 0. ( __
Ci 0- i
- b. . Dry compressible. waste... contaminated ft3 12951.8' equipment, evaporator, bottoms, etc. Ci 23.7 -+-25%
- c. =Ir:-adiated components, control rods, fc3 0 __,
etc. Ci 0
- d. Other (describe) lfh l 0 j ~~
- 2. Estimate .of major nuclide- composition _ (by type of waste) .
p ,
a.- None %
i % +
t i % !'
l !
! i
- b. Co-60' +68.1 % i do-58 ,10.8' % !
Cs-137- f3.9 : I Mn-54' '
! 6.2 %
Cs-134 l1.2-g l Zr-95 l 5.1-1
- %L . . I. .- - - . --- -
2 Nb 95
--a1 4.7 % .,
l . . - .
I L.
I %
.i -
3.. Solid-Waste Disposition
.Nu'mber of Shipments Mode of Transportation Destination 15' _ Truck- Richland, WA
-B. Irradiated ' Fuel- Shipments (disposition)
.9.-
1 i
2 ..