ML20153B940
| ML20153B940 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/30/1988 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20153B884 | List: |
| References | |
| NUDOCS 8808310160 | |
| Download: ML20153B940 (14) | |
Text
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PINGP 158, Rev. 6 Page 1 of 8 Retention: Lifetime l
l EFFLUENT SEMI-ANNVAL REPORT 1
L Jan. 1988 THROUGH June 1988
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SUPPLEMENTAL INFORMATION I
Tacility - Prairie Island Nuclear Generatina Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60
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A.
Regulatory Limits 1.
Liquid Effluents:
a.
The dose or dose commitment to an individual from radio-i accive materials in liquid effluents released from the l
site shall be limited:
t for the Quarter 3.0 mrem Total Body f
10.0 mren Any Organ for the Year 6.0 mrem Total Body l
20.0'erem Any Organ 2.
Gaseous Effluents:
i a.
The dose rate due to radioactive materials released in l
gaseous effluents from the site shall be limited to:
7 i
Noble Gases i 500 mres/ Year Total Body l
[ 4000 mrea/ Year Skin l
$ 1500 mree/ Year Any Organ l
b.
The dose due to radioactive gaseous effluents shall be limited tot j
i Noble Gases i 10 mrad /Qtr Gamma j
$ 20 mrad /Qtr Beta i 20 mrad / Year Gamma 5 40 mrad / Year Beta 1-131. H-3, LLP i 15 ares /Qtr 1 30 ares / Year
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G800310160 080826
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PINGP 158. Rsv. 6 Page 2 of 8 B.
Maximum Permissible Concentrations 1.
Fission and activation, gases in gaseous releases:
10 CFR 20, Appendix B, Table 2, Column.1 2.
Iodine and particulates with half-lives greater than 8 days in gaseous releases:
10 CFR 20, Appendix B, Table 2, Column 1 3.
Liquid Effluents for radionuclides other than dissolved or entrained gases:
10 CFR 20, Appendix B, Table 2, Column 2 4.
Liquid Effluent dissolved..nd entrained gases:
2.0E-04 pei/ml Total Activity C.
Average Energy Not applicable to Prairie Island Regulatory Limits.
D.
M,easurements and Approximations of Total Radioactivity 1.
Fission and activation gases Total Geli in gaseous releases:
Nuclide Geli 2.
Iodines in gaseous releases Total Geli Nuclide Geli 3.
Particulates in gaseous Total Geli releases:
Nuclide Geli-4.
Liquid Effluents:
Total Geli Nuclide Geli
)
1.0 BATCH RELEASES (Liquid)
QTR 1 QTR 2 1.1 Number of Batch Releases l 5.50E+01 2.80E+01 l 1.2 Total Time Period for a Batch Release l
l (hr.)
i 8.60E+01 4.58E+01 l 1.3 Maximum Time for a Batch Release (hr) l 1.90E+00 2.30E+00 l 1.4 Average Time for a Batch Release (hr) l 1.56E+00 1.64E+00 l 1.5 Minimum Time for a Batch Release (hr) l 1.00E+00 1.30E+00 l 1.6 Ave Mississippi flow during Quarter (CFS)l 1.01E+04 1.32E+04 l j
IBM
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PINGP 158,-Rev. 6 Paga<3 of 8 2.0. BATCH RELEASES (Gaseous)
QTR 1 QTR 2 2.1 Number of Batch Releases l
1.60E+01 1.00E+00 l 2.2 ' Total Time Period for a Batch Release (hr) 1 1.27E+02 2.90E+00 l 2.3. Maximum Time for a Batch Release (hr) l 3.27E+01 2.90E+00 l 2.4 Average Time for a Batch Release (hr) l 7.92E+00 2.90E+00 l 2.5 Minimum Time for a Batch Release (hr)-
l 3.00E-02 2.90E+00 l 3.0 ABNORMAL RELEASES (Liquid)
QTR 1 QTR 2 3.1 Number of Batch Re'_ases l
0.00E+00 0.00E+00 l 3.2 Total Activity Release (Ci)
-l 0.00E+00 0.00E+00 l 3.3 Total Tritium Release (Ci) l 0.00E+00 0.00E+00 l 4.0. ABNORMAL RELEASES (Gaceous)
~
4.1 Number of Batch Releases
]
0.00E+00 0.00E+0'0 l 4.2 Total Activity Release (Ci) l 0.00E+00 0.00E+00 l l
1
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I IBM
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PINGP 158, Rev. 6 Page 4 of.8 TABLE 1A Ei..UENT SEMIANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR 1-l QTR 2 lEST I
RR R I
I I
I I
5.0 FISSION AND ACTIVATION GASES 5.1 Totol Release (Ci) l 6.60E 3.75E-02 2.50E+01l 5.2 Average Release Rate (pCi/sec) l 8.40E-03 4.77E-03 5.3 Gamma Dose (mrad) l 2.86E-05 4.21E-06 l
5.4 Beta Dose (mrad).
l 4.86E-04 3.01E-04 l
5.5 % of Gamma T.S. Limit (%)
l 2.86E-04 4.21E-05 l
5.6 % of Beta T.S. Limit
(%)
l 2.43E-03 1.51E-03 1
6.0 IODINES 6.1 Total I-131 (Ci) l 0.00E+00 6.49E-07 2.50E+01l 6.2 Average Release Rate (pCi/sec) 1 0.00E+00 8.26E-08 7.0 PARTICULATES 7.1 Total Release (Ci) l 9.25E-07 l
2.78E-07 2.50E+01l 7.2 Average Release Rate (pCi/sec) l 1.18E-07 l
3.54E-08 8.0 TRITIUM 8.1 Total Release (Ci) l 7.20E+00 9.48E+00 l 2.50E+01]
8.2 Average Release Rate (pCi/sec) l 9.16E-01 1.21E+00 l
9.0 TOTAL IODINE PARTICULATES AND l
l l
l TRITIUM (pCi/sec) l 9.16E-01 l
1.21E+00 l 2.50E+01l 1
10.0 DOSE (mrem) i 1.31E-02 l
1.71E-02 l
11.0 % OF T.S. LIMIT
(%)
l 8.73E-02 l
1.14E-01 l
12.0 GROSS ALPHA 12.1 Total Release (Ci)
{
5.02E-07 1
3.44E-07 l 2.50E+01l IBM
PINGP 158, Rav. 6 Page 5 of 8 TABLE IC EFFLUENT SEMIANNUAL REPORT GASE0US EFFLUENTS GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE l
l l
l-1 I
I l'NUCLIDE l UNIT l
QTR 1 l
QTR 2 l
QTR 1 l
QTR 2
'l I
l l
l l
l~
l 13.0 INDIVIDUAL FISSTON AND ACTIVATION GASES l Kr85 Ci 5.14E-02 3.64E-02 l
l Kr85m Ci l
l Kr87 Ci l'
l Kr88 Ci l-l Xe133 Ci i
1.41E-02 1.08E-03 l
l Xe135 Ci 5.12E-04 l
l Xe135m Ci l
l Xe138 Ci l
l Xe131m Ci l
l Ar41 Ci l
l Xe133m Ci l
l l
I I
I l
l l Total l Ci l
0.00E+00 0.00E+00 6.60E-02 3.75E-02 l
14.0 10 DINES (Ci) l 1131 l Ci j
6.49E-07 l
"ll l I133 l Ci l
2.00E-05 l I135 l Ci l
l l Total l Ci l
0.00E+00 2.06E-05 O.00E+00 1
0.00E+00 l
CONTINUOUS MODE BATCH N0DE 1
1 I
I I
I I
l NUCLIDE l UNIT l
QTR 1 l
QTR 2 l
QTR 1 l
QTR 2 l
l l
l l
1 I
i 15.0 PARTICULATES (Ci) l SrL9 Ci l
l Sr90 Ci 3.07E-08 l
l Cs134 Ci l
l l Cs137 Ci 2.78E-07 2.0SE-07 l
l Ba-La140 Ci l
l CoS8 l Ci l
l l Co60 l Ci l
6.86E-07 l
I I
I I
l Total Ci l
7.17E-07 l
2.78E-07 2.08E-07 0.00E+00 IBM
PINGP 158, Rev. 6 Page.6 of 8 TABLE 2A EFFLUENT SEMIANNUAL REPORT LIQUID EFFL'JENTS - SUMMATION OF ALL RELEASES
. UNIT QTR 1
.I QTR 2
~
E R%
l
-l I
I l
16.0 VOLUME OF WASTE (Prior.to Dilution) l Liters l
7.58E+07 l
3.36E+07 l 2.50E+01l-17.0 VOLUME OF DILUTION Water (liters) l Liters l
1.08E+11 l
7.97E+10-l 2.50E+01l 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 Total Release W/0 H-3, (Ci) l l
l l
Rad Gas, Alpha l
1.20E-02 5.13E-03 l 2.50E+01l 18.2 Average Diluted (pCi/ml) l 1
Concentration l,
1.11E-10 l
3.93E-11'
'l 19.0 TRITIUM 19.1 Total Release (Ci) l 1.60E+02 l
6.14E+01 2.50E+01]
19.2 Average Diluted (pCi/ml) l l
Concentration l
1.48E-6 l
7.70E-07 l
20.0 DISSOLVED AND ENTRAINED GASES 20.1 Total Release (C1) l 1.75E-03 l
1.94E-03 2.50E-01]
l 20.2 Average Diluted (pCi/ml) l l
l Concentration i
1.62E-11 l
2.44E-11 l
l 21.0 GROSS ALPHA i
1 21.1 Total Release (Ci) l 0.00E+00 l
0.00E+00 l 2.50E+01l 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (pCi/ml) l 1.48E-06 l
7.70E-07 l 2.50E+0_1l IBM J
4 PINGP 158, Rev. 6
- Page 7 of 8' TABLE 2A EFFLUENT' SEMIANNUAL' REPORT i
LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES l
UNIT' QTR'l l
QTR 2 ERROR %
l l
1 l
I 23.0 TOTAL BODY DOSE (mrem) l 4.12E-04 l
2.86E-04 l
,24.0 CRITICAL ORGAN DOSE (mrem) l 3.15E-03
-2.86E-04 l
(organ) l GI TOTAL BODY
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25.0 % TOTAL BODY T.S. LIMIT (%).
l 1.37E-02 l
9.53E-03 l
l 26.0 % OF CRITICAL ORGAN
(%)
l l
l T.S. Limit l
3.15E-02 l
9.53E-03 l
l IBM
PINGP 158, Rav. 6 Page 8 of 8 l
TABLE 2A EFFLUENT SEMIANNUAL RPEORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES CONTINUOUS MODE BATCH MODE l
NUCLIDE l UNIT l
QTR 1 l
I
-l l-I I
I I
.QTR 2 l
QTR 1 l
QTR 2 l
l l
l 1
I I
I 27.0 INDIVIDUAL LIQUID EFFLUENT I Sr89 Ci 1.24E-03 1.66E-04 l
l Sr90 Ci 1.05E-04 7.02E-06 3.89E-06 l
l Cs134 Ci l
l Cs137 Ci 2.22E-06 l
l 1131 Ci l
l CoS8 Ci 5.22E-03 4.33E-04 l
l Co60 Ci 5.12E-04 1.63E-03 5.92E-04 l
l Fe59 Ci 7.28E-04 3.29E-05 l
l Zn65 Ci 7.63E-06 5.26E-06 l
l Mn54 Ci 3.13E-04 9.33E-06 l
l Cr51 Ci 4.03E-04
-2.04E-04
_ l l Zr-Nb95 Ci 2.42E-04 7.20E-06 l
l Mo99 Ci l
l Ba-La140 Ci l
1 l
l k
Ci 0.00E+00 0.00E+00 1.64E-03 1.57E-03 l
l Total Ci 1.75E-03 2.71E-04 1.02E-02 1
2.86E-03 l
- From Attachment #1, Additional Nuclides CONTINUOUS MODE BATCH MODE l
l l
l l
l l
l NUCLIDE l UNIT l
QTR 1 l
QTR 2 l
QTR 1 l
QTR 2 l
l l
1 I
I I
l 28.0 DISSOLVED AND ENTRAINED GASES l Xe133 Ci 1.73E-03 1.79E-03 l
l Xe133m Ci l
l Xe131m Ci l
l Xe135 Ci 2.36E-05 1.54E-04 l
l Kr85m Ci l
l Kr85 Ci l
l Kr88 Ci l
l l
l I
l Total Ci 0.00E+00 0.00E+00 1.75E-03 1.94E-03 l
1 IBM
ATTACHMENT 1 ADDITIONAL NUCLIDES
. LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QTR 01 QTR 02 QTR 01 QTR 02 AG-110M CI 3.34E-04 7.67E-04 CO-57 CI 2.13E-06 CS-138 CI 4.75E-06 NA-24 CI 1.11E-06 j
NB-97 CI 3.69E-05 1.48E-05 SB-122 CI 6.54E-06 SB-124 CI 4.94E-04 1.88E-04 i
SB-125 CI 4.35E-04 5. 0 8 E-O'4 SN-113 CI 6.99E-05 SC-47 CI 3.29E-04 SR-92 CI 2.27E-06 ZR-97 CI 1.43E-05 SUBTOTAL CI 0.00E+00 0.00E+00 1.64E-03 1.57E-03 1
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PINGP 753, Rev. 1 Retention:
Lifetime Page 1 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-88 to 6-30-88 NORTHERN STATES POWER License No. ITPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1:
Solid Waste and Irradiated Fuel Shipments A.
Solid Waste Total Volumes and Measured Curie Quantities:
1.
Type of Waste:
Container Units Total Volumes A.
i B.
C.
Non Compacted ft 748.8 96 DAW C1 1.458 D.
S.
I
PINGP 753, Rev. 1 Retention:
Lifetime Page 2 of 5 F.lAIRIE ISLAND NUCLEAR GENERATING PLANT Period:
1-1-88 to 6-30-88 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1:
Solid Waste and Irradiated Fuel Shipments (Continued) 2.
Measured Major Nuclide Composition by Type of Waste:
TYPE (From Page 1)
Nuclide Percent H-3 40.5 C
C-14 3.8 Fe-55 28.7 NI-63 16.0 Co-60___
7.9 Co-58 0.8 SB-125 0.7 1
- = Inferred - Not Measured on Site
o o
.O PINGP 753, Rev. 1 Retent'on:
Lifetime Page 3 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLWT Period: 1-1-88 to 6-30-88 NORTHERN STATES POWER License-No. DPR-47 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:
Solid Waste and Irradiated Fuel Shipments (Continued) 2.
Measured Major Nuclide Composition by Type of Waste (Continuation):
TYPE (From Page 1)
Nuclide Percent
- = Inferred - Not Measured on Site
4 PINGP 753, Rev. 1 Retention:
Lifetime Page 4 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-88 to 6-30-88 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:
Solid Waste and Irradiated Fuel Shipments (Continued) 3.
Solid Waste Disposition:
Number of Shipmencs Mode Destination 2
Truck Scientific Ecology Group 1
Truck Quadrex Racycle Center B.
Irradiated Fuel Shipments:
Number of Shipments Mode Destination 0
i
d O'
PINGP 753, Rev. 1 Retention:
Lifetir-Page 5 of 5 PPAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-88 to 6-30-88 NM THERN STATES POWER-License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1.
Solid Waste and Irradiated Fuel Shipments (Continued)
C.
Shipping Container and Solidification Method:
No.
Volume Activity Type of Container Solidify (Ft3)
(Ci)
Waste' Code Code 87-39 240.0 0.541 c
L N/A 87-40 96.3,
0.366 C
1.
n/A 87-42 412.5 0.551 C
1.
n/A b
TOTALS 3
748.8 1.458 CONTAINER CODES:
L = LSA A = Type A B = Type B Q = Large Quantity l
SOLIDIFICATION CODES:
C = Cement TYPES OF WASTE:
A = Resins B = Dry Compacted C = Non~ Compacted D = Wst. Conc.
i S = Spent Fuel i
,