ML20028G843
| ML20028G843 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/1989 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20028G841 | List: |
| References | |
| NUDOCS 9009050108 | |
| Download: ML20028G843 (15) | |
Text
L 1
l l'989 Efflucht S6biennual R0p?rt REV. 1 Pag 3 1 Cf 8'
' Retention Lifetime EFFLUENT SEMIANNUAL REPORT 02-J"L-89 THROUGH 30-DEC-89 SUPPLEMENTAL INFORMATION i
Facility:
Prairie Island Nuclear Generating Plant Licensee Northern States Power Company License Numbers: DPR-42 & DPR-60 j
A. Regulatory Limits 1.
Liquid Effluents:
s a.
The dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site shall be limited to' 1
for the quarter 3.0 mrem to the total body 10.0 mrem to any organ for the year 6.0 mrem to the total body 20.0 mrem to any organ 2.
Gaseous Effluents:
a.
The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited tot noble gases 4500 mrem / year total body i
(3000 mrem / year skin 1
1-131, H-3, LLP (1500 mrem / year to any organ b.
The dose due to radioactive gaseous effluents shall be limited tot noble gases (10 mrad / quarter gamma (20 mrad / quarter beta 420 mrad / year gamma 440 mrad / year beta I-131, H-3, LLP (15 mrem / quarter to any organ 430 mrem / year to any organ R
l'989 EFFLUE'NT SEMIANNUAL REPORT REVo 1 PAGE 2 B.
Maximum Permissible Concentration 1.
Fission and activation gases it. gaseous releases:
10 CFR 20, Appendix B, Table 2, Column 1 2.
Iodine and particulates with halflives greater than 8 days in gaseous releases:
10 CPR 20, Appendix B, Table 2, C olumn 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 and entrained gases:
2.0E-04 uCi/ml Total Activity C.
Average Energy Not applicable to Prairie Island regulatory limits.
D.
Measurements and approximations of total activity 1.
Fission and activation gases Total GeLi i25%
l in gaseous releases:
Nuclide GeLi 2.
Iodines in gaseous releases:
Total GeLi 125%
Nuclide GeLi 3.
Particulates in gaseous releases:
Total GeLi i25%
Nuclide GeLi 4.
Liquid effluents Total GeLi i25%
Nuclide GeLi
(.
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A
l'989 EFFLUENT SEMIANNUAL REPORT REV. 1 PACE 3 1.0 BATCH RELEASES (LIQUID)
QTR: 03 QTR: 04 1.1 NUMBER OF BATCH RELEASES 4.10E+01 4.70E+01 1.2 TOTAL TIME PERIOD (HRS) 6.55E+01 7.62E+01 1.3 MAXIMUM TIME PERIOD (HRS) 2.33E+00 4.67E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.60E+00 1.62E+00 1.5 MINIMUM TIME PERIOD (HRS) 1.20E+00 3.30E-01 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 6.98E+03 6.10E+03 2.0 BATCH RELEASES (GASEOUS)
QTR: 03 QTR 04 2.1 NUMBER OF BATCH RELEASES 1.10E+01 1.50E+01 2.2 TOTAL TIME PERIOD (HRS) 2.54E+02 1.33E+02 2.3 MAXIMUM TIME PERIOD (HRS) 1.39E+02 2.40E+01 2.4 AVERAGE TIME PERIOD (HRS) 2.31E+01 8.87E+01 2.5 MINIMUM TIMU PERIOD (HRS) 2.80E-01 5.00E-02 3.0 ABNORMAL RELEASES (LIQUID)
QTR: 03 QTR: 04 3.1 NUMBER OF RELEASES 0.00E+00 0.00E+00 3.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 3.3 TOTAL TRITIUM RELEASED (CI)
-0.00E+00 0.00E+00 i
l l
4.0 ABNORMAL RELEASES (GASEOUS)
QTR: 03 QTR: 04 4.1 NUMBER OF RELEASES 0.00E+00 0.00E+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 i
i
'1'989 EFFLUENT SEMIANNUAL REPORT REVe 1 PAGE 4 TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES r
QTR: 03 QTR: 04 5.0 FISSION AND ACTIVATION GASES i
5.1 TOTAL RELEASE (CI) 2.33E+01 1.37E+02 5.2 AVERAGE RELEASE RATE (UCI/SEC) 2.96E+00 1.74E+01 5.3 GAMMA DOSE (MRAD) 2.07E-02 5.83E-02 5.4 BETA DOSE (MRAD) 2.86E-02 1.60E-01 5.5 PERCENT OF GAMMA TECH SPEC (%)
1.07E-01 5.83E-01 5.6 PERCENT OF BETA TECH SPEC (%)
1.43E-01 8.00E-01 6.0 IODINES 6.1 TOTAL I-131 (CI) 4.00E-06 0.00E+00 6.2 AVERAGE RELEASE RATE (UCI/SEC) 5.09E-07 0.00E+00 t
7.0 PARTICULATES-7.1 TOTAL RELEASE (CI) 3.14E-06 7.13E-06 7.2 AVERAGE RELEASE RATE (UCI/SEC) 3.99E-07 9.07E-07 8.0 TRITIUM 8.1-TOTAL RELEASE (CI) 3.20E+01 S.69E+01 8.2 AVERAGE RELEASE RATE (UCI/SEC) 4.07E+00 4.70E+00 L
9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 4.07E+00 4.70E+00 10.0 DOSE (MREM) 5.84E-02 6.65E-02 11.0 PERCENT OF TECH SPEC (%)
3.89E-01 4.43E-01 12.0 GROSS ALPHA (CI) 8.60E-08 1.07E-08 i
l'989 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 5 TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES l
13.0 FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 1
AR-41 CI 3.26E-02 1.88E-02 l
KR-85 C1 1.61E-01 KR-85M CI 2.35E-03 XE-131M CI 1.30E-02 I.38E-03 XE-133 CI 2.26E+01 1.33E+02 6.04E-01 1.30E-02 XE-133M CI 1.56E-03 XE-135 CI 1.50r,-02 3.62E400 1.97E-04 4.65E-05 TOTAL CI 2.26E+01 1.37E+02 6.51E-01 1.96E-01 14.0 IODINES CONTINUOUS MODE BATCH MODE l
i NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 I-131 CI 4.00E-06 TOTAL CI 4.00E-06 0.00E+00 0.00E+00 0.00E+00 15.0 PARTICULATES l
CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 I
CO-60 CI 7.57E-07 1
CD-109 CI 2.04E-06 7.13E-06 j
SR-89 CI 1.37E-07 l
SR-90 CI 2.02E-07 TOTAL CI 3.00E-06 7.13E-06 1.37E-07 l
1~989 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 6 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 03 QTR: 04 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 2.60E+07 3.99E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 2.61E+11 1.77E+11 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 4.98E-03 1.39E-02 P
18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.91E-11 7.85E-11 19.0 TRITIUM
- SEE ATTACHED NOTE FOR ADDITIONAL TRITIUM DOSE CALCULATIONS 19.1 TOTAL RELEASE (CI) 1.68E+02 1.29E+02 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 6.44E-07 7.29E-07 20.0 DISSOLVED AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI) 2.59E-03 9.93E-03 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 9.92E-12 5.61E-11 21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 22.0 TOTAL TRITIUM,-FISSION AND ACTIVATION l
PRODUCTS (UCI/ML) 6.44E-07 7.29E-07 23.0 TOTAL BODY DOSE (MREM) 3.78E-04 3.30E-04 l
24.0 CRITICAL ORGAN 24.7 DOSE (MREM) 3.78E-04 3.30E-04 l
24.2 ORGAN TTL BODY TTL BODY 25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)
1.26E-02 1.10E-02 l
l 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)
1.26E-02 1.10E-02
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1'989 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 7 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 27.0 ' INDIVIDUAL LIQUID EFFLUENT
[
t CONTINUOUS MODE BATCH MODE l
NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 i
I-131-CI 1.50E-04 8.04E-06 8.34E-05 t
f.
1-133 CI.
8.11E-05 AG-110M CI 1.85E-04 6.52E-03 CO-58 CI 2.10E-04 8.24E-04 CO-60 CI 3.71E-04 1.27E-03 l
FE CI 3.72E-05
'l CS-137 CI 9.68E-06 i
MN-54 CI 5.32E-06 5.65E-05 NB-97 CI 2.77E-05 3.00E-05 SN-113 CI 6.13E-05 2.41E-04 l
NA-24 CI 1.16E-06 l
SB-124 CI 1.69E-03 4.40E-04 SB-125 CI 1.97E-03 1.54E-03 CS-138 CI 2.28E-05
~TC-99M CI 9.37E,
ZR-97 CI 2.94E-06 3.29E-04 1
SR-92 CI 7.40E-06 i
FE-55 CI 1.50E-04 2.51E-03 TOTAL CI ll3.81E-04 0.00E+00 4.60E-03 1.39E-02 l
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l'989LEFFLUENT SEMIANNUAL REPORT REVi 1, PAGE 8 i
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-28.0; DI58OLVED AND ENTRAINED GASES
. {
e" CONTINUOUS MODE BATCH MODE I
NUCLIDE UNITS QTR 03 QTR: 04 QTR: 03-QTR: 04'
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1 L
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XE-133 CI 2.59E-03 9.86E-03 XE-133M CI 4.55E-05 l
XE-135 CI
.3.77E-06 2.77E >
TOTAL CI 2.59E-05 9.93E i r
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ATTACHMENT TO THE 1989 ErrLUENT S2MIANNUAL REPORT l
Liquid Pathway Dose Calculation l
Quarters 3 and 4 1989 1
l Summary The total liquid doses to the critical receptor for the third and fourth quarters of 1989 are 0.0167 and 0.0190 mrem, respectively.
These doses are reported in this attachment to the semiannual report.
Background
In October, 1989 a well water sample of a residence close to PI showed low-levels of tritium.
Initial dose calculation results showed ostimated liquid pathway doses a hundred times higher than those reported in past semiannual reports.
These results indicated that a new dose pathway should be considered.
Investigation into the cause of the tritium contamination led to the ossumption that the flow of water is from the discharge canal downhill toward the Vermilion river.
The resident's well draws from the groundwater between the canal and the Vermilion river.
ODCM Considerations The following calculation is independent of the ODCM.
At this time no change will be made to the ODCM.
Efforts are currently under way to determine if the tritium levels in the well can be reduced by physical modifications to the discharge structures and/or adjustments to the discharge methods.
Results of these efforts should be available in 1990 and the problem will be eliminated or appropriate ODCM changes will be made.
Dose Calculation Assumptions For the purpose of dose calculation, the dose-maximizing assumption was made that the receptor's concentration of tritium in body water and organic molecules is equal to the average concentration in the discharge canal.
The dose conversion factor for this assumption is taken from page 9-3 of NUREG/CR-3332.
Its value is 102 mrem / year per uCi/ liter of tritium in the body.
When adjusted for the units reported for the discharge canal concentration, the dose conversion factor is 2.55E4 mrem / quarter per uCi/ml.
Discussion The elevated tritium levels were found at the residence which is the critical receptor (0.6 miles to the SSE of the site) for Prairie Island.
Therefore, the dose calculated for waterborne tritium is added to the critical receptor's fish pathway dose.
This overestimates the dose because the tritium dose from eating fish is accounted for twice.
POgO 2
. should be noted that the total airborne dose (99% plus of which is l
ue to tritium) is greater than the total waterborne tritium dose.
Even though the newly identified pathway delivers additional tritium to the critical receptor it is a lower concentration than that already in the body due to airborne exposure.
Dose calculation Average Dose Diluted Whole Fish Total Quarter Conversion X
Tritium Body
+ Pathway =
Liquid
=
Factor Concentration Dose Dose Dose (mrem / quarter (uCi/ml)
(mrem)
(mrem)
(mrem) per uci/ml) 3 2.55E4 6.44E-7 1.64E-2 3.78E-4 1.68E-2 4
2.55E4 7.29E-7 1.86E-2 3.85E-4 1.90E-2 Dose Report i
LIQUID EFFLUENTS - SUMMATION OF WATERBORNE TRITIUM AND FISH PATHWAYS QTR:
03 QTR:
04 TOTAL BODY DOSE (MREM) 1.68E-02 1.90E-02 CRITICAL ORGAN 1
s DOSE (MREM) 1.68E-02 1.90E-02 ORGAN TTL BODY TTL BODY PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)
5.60E-01 6.33E-01 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)
5.60E-01 6.33E-01 l
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lPINGP753', Rov.2 Paga 1 of 5 Retention:
Lifetime PRAIRIE ISLAND NUCLEAR GEHERATING PLANT Period: 7-1-89 to 12-31-89 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:
Solid Waste and Irradiated Fuel Shipments 1.
Solid Waste Totcl Volumes and Total Curie Quantities:
I i
l Container 1
1; l
i Disposal 1
Volumes Type of Waste Units Totals (List) l A. Resins ft>
847.8 178 i
l Ci 51.426 135.8 j
l o
l l
I 3
I B. Dry-Compacted ft 2730.1 7.5 l
l Ci 37.373 11.3 4
3 C. Non-Compacted I
ft l
$4.8 96 I
I 1
l i
II l
Ci 0.044 u
ll l
l l
l i
1 3
D. Filter Media l
ft 461.8 l
163 I
1; l
Ci 13.762 135.8 l
ll l
l ll
\\
\\
i l
t 3
S. Spent Fuel ll ft l
j I
(
i l
Ci I
I 1
1 I
I I
l I
I l
)
IBM i
'lPINGP 753, R $. 2 l
Pasa 2
' PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-89 to 12-31-89 i
NORTHERN STATES POWER License No. DPR-42 J
SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1:
Solid Vaste and Irradiated Fuel Shipments (Continued) f 2.
Principal Radionuclide Composition by Type of Waste:
Percent i
TYPE (From Page 1)
Nuclide Abundance A
_C0-60 45.0
- NI-63 25.9
3.3
- H-3 l.1 I
f B
- C-14 10.7
D
- = Inferred - Not Measured on Site IBM
PINGP-753', Rsv. 2
'Pogo 3 l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-89 to 12-31-89 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:
Solid Waste and Irradiated Fuel Shipments (Continued) 2.
Principal Radionuclide Composition by Type of Waste (Continuation):
Percent TYPE (From Page 1)
Nuclide Abundance C
- C-14 68.0
- NI-63 2.4 AG-110M 2.L SB-125 0.8
,C0-58 0.7 CS-137 0.3 D
- = Inferred - Not Measured on Site IBM
+
.PINGP 753, R;v. 2 Pcgo 4 l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-89 to 12-21-89 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table It solid Waste and Irradiated Fuel Shipments (Continued) 3.
Solid Waste Disposition:
Number of Shipments
' Mode Destination
[
14 Truck
._.Richland. WA 1
Truck Barnwell. SC 2
Truck Oakridae. TN 4.
Irradiated Fuel Shipments:
Number of Shipments Mode Destination 0
l
?
E IBM
]
'PINGP 753,'R,v'. 2 Pcg] 5 i
[
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-89 to 12-31-89 NORTHERN STATES POWER License No. DPR-42 SOLID RADIO.'.CTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT i
Table 1:
Solid Waste and Irradiated Fuel Shipments (Continued) 5.
Shipping container and Solidification Method:
Disposal No.
Volume Activity Type of-Container Solidif.
(Ft3)
(Ci)
Waste Code Code 89-15 510.0 2.55647 3
L
_. L 89-18 510.0 1.31359 B
L N /A j
89-19 510.0 1.20141 B
L N/A l
89-22 510.0 1.64668 B
L N/A 89-23 480.1 1.77159 B
L N /A 89-28 178.0 1.19304 A
L N/A
~
89-29 163.0 0.94613 D
L N/A 89-31 163.0 0.86818_
D L
N /A 89-32 135.8 45.3338 A
L N/A 89-34 178.0 1.39951 A
L N/A 89-35 105.0 14.1488 B
L N /A 89-36 178.0
__2.26993 A
L N/A 89-37 105.0 14.73528 B
L N/A 89-39 135.8 11.94816 D
L N/A 89-40 178.0 1.22945 A
L N/A 88-35 44.4 0.044 C
L N/A 87-40 10.4 0.00001 C
L N/A
[
TOTALS 17 4094.5 102.606 CONTAINER CODES:
L = LSA (Shipment Type)
A = Type A B = Type B Q = Highway Route Controlled Quantity SOLIDIFICATION CODES:
C = Cement l
TYPES OF WASTE:
A = Resins B = Dry Compacted I
C = Non-Compacted D = Filter Media S = Spent Fuel IBM
-