ML20034F289
| ML20034F289 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/1992 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20034F288 | List: |
| References | |
| NUDOCS 9303020561 | |
| Download: ML20034F289 (19) | |
Text
- _ _
l 1992 Effluent Semiannual Report REV. O Page 1 of 9 Retention: Lifetime EFFLUENT SEMIANNUAL REPORT l
06-JUL-92 THROUGH 03-JAN-93 SUPPLEMENTAL INFORMATION I
Facility:
Prairie Island Nuclear Generating Plant Licensee:
Northern States Power Company License Numbers: DPR-42 & DPR-60 A.
Regulatory Limits 1.
Liquid Effluents:
a.
The dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site shal; e
limited to:
for the quarter 3.0 mrem to the total body l
10.0 mrem to any organ i
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 to:
i noble gases 4500 mrem / year total body (3000 mrem / year skin I-131, H-3, LLP (1500 mrem / year to any organ l
b.
The dose due to radioactive gaseous effluents shall be limited to:
l noble gases (10 mrad / quarter gamma (20 mrad / quarter beta (20 mrad / year gamma 440 mrad / year beta I-131, H-3, LLP (15 mrem / quarter to any organ i
(30 mrem / year to any organ 9303020561 930226 l
PDR ADOCK 05000282 R
t 1
l 1992 EFFLUENT SEMIANNUAL ~ REPORT REV. O PAGE 2 B.
Maximum Permissible Concentration 1.
Fission and activation gases in 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 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 and entrained gases:
2.0E-04 uCi/ml Total Activity C.
Average Energy Not applicable to Prairie Island regulatory limits.
Measurements and approximations of total activity D.
1.
Fission and activation gases Total GeLi 25%
Nuclide GeLi in gaseous releases:
2.
Iodines in gaseous releases:
Total GeLi 25%
Nuclide GeLi 3.
Particulates in gaseous releases:
Total GeLi i25%
Nuclide GeLi~
Total GeLi 25%
4.
Liquid effluents Nuclide GeLi i
E.
Manual Revisions 12 1.
Offsite Dose Calculations Manual latest Revision number:
Revision date
- 17-JUN-92 2.
Process Control Program Manual latest Revision number:
4 Revision date
- 23-APR-91
1992 EFFLUENT SEMIANNUAL REPORT REV. 0
-PAGE 3
^
1.0 BATCH RELEASES (LIQUID)
QTR: 03 QTR: 04 1.1 NUMBER OF BATCH RELEASES 5.00E+01 1.03E+02 1.2 TOTAL TIME PERIOD (HRS) 2.24E+02 1.91E+02 1.3 MAXIMUM TIME PERIOD (HRS) 7.53E+00 4.62E+00 1.4 AVERAGE TIME PERIOD (HRS) 4.48E+00 1.86E+00 1
1.5 MINIMUM TIME PERIOD (HRS) 2.83E+00 1.20E+00 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS)
I.95E+04 5.76E+04 2.0 BATCH RELEASES (GASEOUS)
QTR: 03 QTR: 04 2.1 NUMBER OF BATCH RELEASES 6.00E+00 1.30E+01 2.2 TOTAL TIME PERIOD (HRS) 1.42E+01 2.98E+01 2.3 MAXIMUM TIME PERIOD (HRS) 8.00E+00 8.10E+00 2.4 AVERAGE TIME PERIOD (HRS) 1.33E+00 2.29E+00 2.5 MINIMUM TIME PERIOD (HRS) 2.50E-01 2.50E-01 3.0 ABNORMAL RELEASES (LIQUID)
QTR: 03 QTR: 04 3.1 NUMBER OF RELEASES 0.00E+00 1.00E+00 3.2 TOTAL ACTIVITY RELEASED (C1) 0.00E+00 3.70E-03 3.3 TOTAL TRITIUM RELEASED (CI) 0.00E+00 2.96E-02 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 l
l
.- =
1992 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 4 j
TABLE 1A i
GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES l
QTR: 03 QTR: 04 5.0 FISSION AND ACTIVATION GASES 1
5.1 TOTAL RELEASE (CI) 1.73E+01 3.52E+00 5.2 AVERAGE RELEASE RATE (UCI/SEC) 2.20E+00 4.48E-01 l
l 5.3 GAMMA DOSE (MRAD) 7.46E-03 2.05E-03 5.4 BETA DOSE (MRAD) 2.39E-02 1.16E-02 5.5 PERCENT OF GAMMA TECH SPEC (%)
7.46E-02 2.05E-02 i
5.6 PERCENT OF BETA TECH SPEC (%)
1.20E-01 5.80E-02 l
i 6.0 IODINES 6.1 TOTAL I-131 (CI) 1.48E-05 1.72E-04 l
6.2 AVERAGE RELEASE RATE (UCI/SEC) 1.88E-06 2.19E-05 i
7.0 PARTICULATES 7.1 TOTAL RELEASE (CI) 3.71E-06 3.72E-05
}
7.2 AVERAGE RELEASE RATE (UCI/SEC) 4.72E-07 4.73E-06 i
8.0 TRITIUM l
8.1 TOTAL RELEASE (CI) 1.59E+01 9.80E+00
)
8.2 AVERAGE RELEASE RATE (UCI/SEC) 2.02E+00 1.25E+00 l
9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 2.02E+00 1.25E+00 10.0 DOSE (MREM) 3.39E 1.50E-02 11.0 PERCENT OF TECH SPEC (%)
2.26E-01 1.00E-01 12.0 GROSS ALPHA (CI) 0.00E+00 5.39E-06 lu
4 1992 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 5 TABLE l'C I
GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 13,0 FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 KR-85 CI 2.74E-01 7.90E-01 a
XE-131M CI 2.41E-02 XE-133 CI 1.61E+01 1.85E+00 6.58E-01 8.10E-01 XE-133M CI 1.67E-01 5.66E-04 XE-135 CI 1.58E-01 4.15E-02 1.43E-04 2.06E-05 XE-135M CI 5.72E-04 t
TOTAL CI 1.64E+01 1.90E+00 9.33E-01 1.62E+00 i
i 14.0 IODINES CONTINUOUS MODE BATCH MODE
^
NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 I-131 CI 1.07E-05 1.65E-04 4.08E-06 7.11E-06 1
I-132 CI 5.73E-10 i
)
I-133 CI 2.97E-06 1.02E-07 I-134 CI 5.29E-10 I-135 CI 4.87E-07 TOTAL CI 1.07E-05 1.65E-04 7.54E-06 7.21E-06 i
1
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+.,n,,
..,..,n-
1992 EFFLUENT SEMIANNUAL REPORT REv. O PAGE 6 TABLE l'C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 15.0 PARTICULATES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 OTR: 04 QTR: 03 OTR: 04 AG-110M CI 7.01E-07 l
CO-58 CI 3.36E-06 5.61E-06 C0-60 CI 1.67E-06 CS-134 CI 1.88E-06 8.83E-06 CS-136 CI 2.35E-07 l
CS-137 CI 1.56E-06 7.68E-06 MN-54 CI 3.80E-08 l
NA-24 CI 2.81E-10 1
NB-97 CI 1.51E-07 NB-95 CI 5.47E-06 SR-89 CI 5.10E-08 TE-132 CI 3.61E-07 ZR-95 CI 3.36E-06 TOTAL CI 0.00E+00 4.06E-06 3.71E-06 3.31E-05 l
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1992 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 7 TABLE 2'A j
LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES i
QTR: 03 QTR: 04 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 2.77E+07 3.09E+08 17.0 VOLUME OF DILUTION WATER (LITERS) 2.66E+11 9.35E+10 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 1.11E-01 5.79E-01 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 4.17E-10 6.17E-09 19.0 TRITIUM i
19.1 TOTAL RELEASE (CI) 2.10E+02 3.93E+01 l
19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 7.90E-07 4.19E-07 20.0 DISSOLVED AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI) 2.39E-02 2.20E-02 i
20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 8.99E-11 2.35E-10 l
21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 7.90E-07 4.25E-07 l
23.0 TOTAL BODY DOSE (MREM) 8.12E-04 4.19E-03 24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 8.12E-04 4.19E-03 24.2 ORGAN TTL BODY TTL BODY 25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)
2.71E-02 1.37E-01 l
l 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)
2.71E-02 1.37E-01 I
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1992 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 8 TAELE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES i
27.0 INDIVIDUAL LIQUID EFFLUENT l
CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 t
AG-108M CI 2.66E-06 AG-110M CI 1.15E-04 2.17E-02 1.34E-02 BE-7 CI 4.26E-04 5.75E-05 CO-57 CI 5.29E-05 1.59E-05 CO-58 CI 5.93E-05 1.83E-02 5.43E-02 CO-60 CI 7.21E-03 9.82E-03 CR-51 CI 1.95E-03 1.39E-02 l
CS-134 CI 3.40E-05 3.06E-04 CS-137 CI 2.78E-05 5.84E-05 4.21E-04 CU-64 CI 8.17E-04 FE-55 CI 1.88E-01 5.19E-02 2.18E-01 FE-59 CI 1.34E-03 6.04E-03 I-131 CI 5.56E-06 8.19E-05 3.03E-03 I-133 CI 6.91E-06 LA-140 CI 1.00E-04 3.44E-04 MN-54 CI 7.29E-04 1.61E-03 MO-99 CI 1.58E-05 1.37E-05 NA-24 CI 8.06E-07 NB-95 CI 3.29E-04 NB-97 CI 7.93E-06 5.25E-06 RH-105 CI 2.20E-05 RU-103 CI 3.17E-06 SB-122 CI 2.08E-05 3.60E-03 SB-124 CI 1.09E-03 3.59E-02
1992 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 9 l
TABLE 2A i
l LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 27.0 INDIVIDUAL LIQUID EFFLUENT (CONTINUED)
SB-125 CI 4.46E-03 2.63E-02 1.29E-04 f
SB-126 CI SC-47 CI 6.67E-05 5.06E-04 SN-113 CI 1.36E-03 1.61E-03 I
l SR-92 CI 7.56E-06 1.66E-05 l
TC-99M CI 2.12E-05 1.45E-05 i
7.88E-06 TE-132 CI W-187 CI 1.76E-05 3.31E-05 l
l Y-93 CI 1.66E-05 ZN-65 CI 3.69E-05 i
ZR-95 CI 2.03E-04 5.64E-04 ZR-97 CI 4.75E-06 TOTAL CI 0.00E+00 1.88E-01 1.11E-01 3.91E-01 l
28.0 DISSOLVED AND ENTRAINED GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 KR-85M CI 3.18E-06 XE-133 CI 2.75E-05 2.39E-02 2.15E-02 XE-133M CI 1.32E-05 XE-135 CI 4.40E-06 4.77E-04 XE-135M CI 1.94E-05 TOTAL CI 0.00E+00 2.75E-05 2.39E-02 2.20E-02
Subject:
Northern States Power, Prairie Island Liquid Effluent Release Abnormal Release during 4th Quarter 1992.
i i
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On Dec 6, 1992 two liquid waste tanks were placed on recirculation for release.
One of the tanks were sampled and processed for release prior to the second tank.
The release authorization papers and operations procedures became mixed up and the tank that was not yet sampled and authorized was released.
The mistake was realized later in the day when the sample and release authorization papers were being prepared for the i
second tank to be released.
Follow-up samples were taken and compared to projected and actual observed radiation monitor readings.
The two tanks were very similar in concentration and it was determined that the original pre-release dose calculatio.is were reasonably accurate.
The tank was released at a rate that was 0.22% of the maximum release rate limit based on MPCs as per the ODCM.
Operations and Effluent Release procedures have been altered to prevent re-occurance.
This event has been investigated and the corrective actions determined adequate.
Further information concerning this event can be found in Prairie Island LER for Unit #1 92-16.
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i PINGP 753, Rev. 3 l
Page 1 of 6 j,
Retention:
Lifetime PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-92 to 12-31-92 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 Total Volumes and Total Curie Quantities:
I l
l l
Container I
l l
l l
Disposal I
I Type of Waste i
Units i
Totals l
Volumes I
I (List)
I 3
I A. Resins i
ft 1
366.6 l
183.3cf I
)
i I
I I
I l
l Ci l 2.71E+01 I
I I
I (+/-25%)
i I
I i
l I
I i
I l
3 B. Dry-Compacted I
ft l
982.6 1
7.5cf I
i Ol l
l
- 2. m -e1 C1 m.oe I
I (+/-25%)
I i
l i
I I
I I
I l
3 C. Non-Compacted I
ft l
16.8 1
96cf i
I I
I I
t l
1 l
Ci I
6.82t-02 I
I I
I
(+/-25%)
l I
I l
1 I
I I
i l
1 1
l 3
D. Filter Media I
ft l
l l
l 1
l l
l Ci I
i I
I I
I I
I I
I I
I I
I l
!s. Spent l
3 Fuel I
ft l
l l
l l
1 l
Ci l
l I
I I
I I
I I
I I
I l
l l
l l
l IBM
PINGP 753, Rev. 3 Page 2 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period:
7-1-92 to 12-31-92 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:
Percent TYPE (From Page 1)
Nuclide Abundance I
A FE-55 71.83 C-14 8.75 NI-63 8.33 Co-60 7.15 CO-58 1.78 AG-Il0M 1.22 CS-137 0.72 l
l l
O l
l B
Co-58 50.46 FE-55 23.66 NI-63 9.11 Co-60 7.23 ZR-95 3.53 MN-54 2.57 NB-95 1.71 CR-51 1.26 C-14 0.47 l
l l
l l
%)
- = Inferred - Not Measured on Site l
IBM
PINGP 753, Rev. 3 Page 3
?
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-92 to 12-31-92 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT i
Table I:
Solid Waste and Irradiated Fuel Shipments (Continued) 2.
Principal Radionuclide Composition by Type of Waste (Continuation):
l Percent l
TYPE (From Page 1)
Nuclide Abundance C
CO-58 50.46 FE-55 23.66 NI-63 9.11 co-60 7.23 i
ZR-95 3.53 I
l MN-54 2.57 i
NB-95 1.71 CR-51 1.26 i
C-14 0.47 i
i O
l i
l O
- = Inferred - Not Measured on Site i
i IBM i
PINGP 753, Rev. 3 Page 4 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-92 to 12-31-92 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:
Solid Waste and Irradiated Fuel Shipments (Continued) f 3.
Solid Waste Disposition:
Number of Shipments Mode Destination 4
Truck Richland 1
Truck Quadrex i
4.
Irradiated Fuel Shipments:
Number of Shipments Mode Destination 0
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9 PINGP 753, Rev. 3 Page 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7 - I -91 % vt. A t.
NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:
Solid Waste and Irradiated Fuel Shipments (Continued) 5.
Shipping Container and Solidification Method:
Disposal l
No.
Volume Activity Type of Container Solidif.
(Ft3)
(Ci)
Waste Code Code 1
l 92-02 16.8 0.0682 C
L N/A l
92-12 480.0 0.3107 B
L N/A l
92-17 502.6 0.4124 B
L N/A 92-?O 183.3 0.6665 A
L N/A 97-71 183.3 26.4285 A
L N/A O
t l
1 TOTALS 5
1366 27.886 CONTAINER CODES:
L = LSA (Shipment Type)
A = Type A B = Type B Q = Highway Route Controlled Quantity i
l l
SOLIDIFICATION CODES:
C = Cement l
TYPES OF WASTE:
A = Resins B = Dry Compacted C = Non-Compacted
(
D = Filter Media S = Spent Fuel IBM i
^
4 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFF-SITE RADIATION DOSE ASSESSMENT FOR January 1-December 31, 1992 4
An assessment of radiation dose due to release from the Prairie i
Island Nuclear Generating Plant during 1992 was performed in accordance with the Technical Specifications. Computed doses were i
well below the 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidelines.
Off-site dose calculation formulas and meteorological data from the off-site Dose Calculation Manual were used in making this assessment. Source terms were obtained from the two Effluent and Waste Disposal Semiannual Reports prepared for NRC review during I
the year of 1992.
Off-site Doses from Gaseous Release Computed doses due to gaseous releases are reported in Table 1.
Critical receptor location and pathways for organ doses are reported in Table 2. Doses, both whole body and organ, are a small percentage of Appendix I Guidelines.
j off-site Doses from Licuid Release Computed doses due to liquid releases are reported in Table 1.
Receptor information is reported in Table 2. Both whole body dose l
and organ dose are a small percentage of Appendix I Guidelines.
Doses to Individuals Due to Activities Inside the Site Boundarv Occasionally sportsmen enter the Prairie Island site for recreational activities. These individuals are not expected to spend more than a few hours per year within the site boundary.
Commercial and recreational river traffic exists through this area.
For purposes of estimating the dose due to recreational and river water transportation activities within the site boundary, it is assumed that the limiting dose within the site boundary would be 4
received by an individual who spends a total of seven days per year on the river just off shore from the main plant buildings (ESE at 0.2 miles). Whole body and inhalation organ doses were calculated for this location and occupancy time. These doses were reported in Table 1.
Doses to Most Exposed Member of the General Public from Reactor Beleases and Other Uranium Fuel Cycle Sources i
There are no other uranium fuel facilities in the vicinity of the Prairie Island site. The only other artificial source of exposure to the general public in addition to the plant effluent releases is j
from direct radiation of the reactors. This direct radiation from pressurized water reactors has been shown to be negligible. An I
array of TLD monitoring stations around the perimeter of the site boundary has consistently indicated that plant operation in the l
past years has no effect on ambient gamma radiation.
Therefore, the most exposed member of the general public will not receive an annual radiation dose from reactor effluent releases and all other fuel cycle activities in excess of the sum of the liquid and gaseous whole body and organ doses reported in Table 1 for the site boundary and critical receptor, respectively. These doses are well below 40 CFR Part 190 standards of 25 mrem to the whole body, l
75 mrem to the thyroid, and 25 mrem to any other organ.
Radiation Environmental Monitorina Procram Samplina Deviations There were no milk or vegetable sampling deviations during this reporting period.
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I TABLE 1 OFF-SITE RADIATION DOSE ASSESSNENT - PRAIRIE ISLAND PERIOD: JANUARY 1 throuch DECEMBER 31, 1992
[
Guidelines per 2-units site per year Gaseous Releases Maximum Site Boundary l
Gamma Air Dose (mrad) 9.37E-03 20 Maximum Site Boundary Beta Air Dose (mrad) 3.00E-02 40 Maximum Off-site Dose to Any Organ (mrem)
- Total 1.14E-01 30 l
Offshore Location (mrem)
Whole Body 5.40E-03 10
)
Organ 5.60E-03 30 i
Licuid Releases i
Maximum Off-site Dose i
Whole Body (mrem) 7.00E-03 6
Maximum Off-site Dose Organ, Total 7.00E-03 20
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P r
TABLE 2 i
OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND i
SUPPLEMENTAL INFORMATION
{
i L
PERIOD: JANUARY 1 through DECEMBER 31, 1992 I
l Gaseous Releases l
i Maximum Site Boundary
[
Dose Location i
(from Building vents)
Sector WNW
(
Distance (miles) 0.4 l
l i
Offshore Location l
l Within Site Boundary Sector ESE i
Distance (miles) 0.2 I
l Maximum Off-site i
Dose Location l
1 l
Sector SSE Distance (miles) 0.6 Pathways
- Plume, i
- Ground, Inhalation, i
Vegetables l
l' l
Age Group Child l
Organ Thyroid l
l Liquid Releases I
Maximum Off-site Dose Location Downstream I
Pathways Fish l
Organ Whole Body l
i a
i i
[
i
,