ML20112A467
| ML20112A467 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/1984 |
| From: | Fey F NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8503180314 | |
| Download: ML20112A467 (20) | |
Text
_ __ -_ _ _ _ ___ ____- __ _ _________ ____ __ ___ __ ____ __
TRANSMITTAL MANIFEST NORTHERN STATES POWER COMPANY NUCLEAR GENERATION DEPARTMENT PRAIRIE ISLAND NUCLEAR GENERATING PLANT Effluent and Waste Disposal Semi-Annual Report for July 1,1984 through December 31, 1984 Manifest Date: March 1, 1985 USNRC Regional Admin-III 1 ANI Library 1 NRR Project Manager, NRC 1 Westinghouse Electric 2 DCD 1 W J Johnson Resident Inspector 1 R T Meyer R J Jensen 1 J N Sorensen (NUS) 1 L R Eliason 1 C E Agan (FPSI) 3 3 T Goering/G H Neils 1 (C E Agan, Al Garrow 9 Charnoff 1 and Corporate Library) ;
B Sellman 1 PI SAC Secretary 1 B W Clark 1 D C Lcwens 1 ERAD Dept. 1 Safety Audit Committee 8 Attn: Records Clerk D M Musolf MDH 1 K J Albrecht Attn: Commissioner of Health C W Giesler MPCA 1 F W Hartley
- Attn: J W Ferman H S Isbin Prairie Island Plant Manager 10 J A Thie Monticello Plant 1 F P Tierney (W A Shamla) E L Watzl Media Services Dept. 1 SAC File (Manifest Only)
NSS File 1 NG File 1 8503180314 e41231 gDR ADOCK 05000282 PDR BWC020685GDWO3
[
/
l
' PINGP 158, Bw. 6 Page 1 ef 8 Retention: Lifetime EFFLUENT SEMI-ANNUAL REPORT JULY THROUGH DECEMBER 1984 SUPPLEMENTAL INFORMATION Facility - Prairie Island Nuclear Generatina Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60 A. Regulatory Limits
- 1. Liquid Effluents:
- a. The dose or dose commitment to an individual from radio-active materials in liquid effluents released from the site shall be limited:
for the Quarter 3.0 mees Total' Body 10.0 mrem Any Organ for the Year 6.0 mrem Total Body 20.0 mrem Any Organ
- 2. Gaseous Effluents:
- a. The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to:
Noble Gases 1500 mrem / Year Total Body 1 3000 mrem / Year Skin I-131, H-3, LLP $ 1500 arem/ Year Any Organ
- b. The dose due to radioactive gaseous effluents shall be limited to:
Noble Gases i 10 mrad /Qtr Gamma 1 20 mrad /Qtr Beta
< 20 mrad / Year Gamma
{40 mead /YearBeta I-131, H-3, LLP 115 arem/Qtr i 30 mrem / Year
c so
. , PINGP 158, R:v. 6 Pag 2 2 cf 8 m
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 and entrained gases:
2.0E-04 pei/ml Total Activity C. Average Energy Not applicable to Prairie Island Regulatory Limits.
D. Measurements 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 3 QTR 4 1.1 Number of Batch Releases l 6.50E+01 1.23E+02 l 1.2 Total Time Period for a Batch Release l (hr.) ll 9.54E+01 2.20E+02 l 1.3 Maximum Time for a Batch Release (br) l 1.78E+00 4.00E+00 l 1.4 Average Time for a Batch Release (br) l 1.47E+00 1.79E+00 l 1.5 Minimum Time for a Batch Release (br) l 7.80E-01 1.00E+00 l 1.6 Ave Mississippi flow during Quarter (CFS)l 2.04E+04 2.22E+04 l l
l l
)
FIAGP 135, NIV O P:Es 3 of 8 2.0. BATCH RELEASES (Gaseous)
2.1 Number of Batch Releases 13.00E40 9.00E+00 l 2.2 Total Time Period for a Batch Release (hr) l1.71E+01 9.88E+01 l 2.3 Maximus Time for a Batch Release (hr) l8.90E+00 2.71E+01 l 2.4 Average Time for a Batch Release (br) l5.70E+00 L.10E+01 l 2.5 Minimus Time for a Batch Release (hr) lE01E-01 8.78E-02 l 3.0 ABNORMAL RELEASES (Liquid)
QTR 3 QTR 4 3.1 Number of Batch Releases l 0.00E+00 0.00E+00 l 3.2 Total Activity Release (C1) 1 0.00E+00 0.00E+00 l 3.3 Total Tritium Release (Ci) l 0.00r+00 0.00E+00 l 4.0. ABNORMAL RELEASES (Gaseous)
QTR 3 .QTR 4 4.1 Number of Batch Releases 1 0.00E+00 0.00E+00 l 4.2 Total Activity Release (Ci) l 0.00E+00 0.00E+00 l l
t l
4 j
l i
l
, I i
ruur iss, n;v. o Pero 4 af 8 TABLE 1A EFFLUENT SEMIANNUAL REPORT .
GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES l UNIT l QTR 3 l QTR 4 lES I I I I I 5.0 FISSION AND ACTIVATION GASES 5.1 Total Release (Ci) l 7.08E-01 7.42E+01 2.50E+01l 5.2 Average Release Rate (pci/sec) l 9.01E-02 9.44E+00 5.3 Gamma Dose (arad) l 8.78E-05 3.68E-02 l 5.4 Beta Dose (mrad) l 1.57E-03 1.20E-01 l 5.5 % of Gamma T.S. Limit (%) l 8.78E-04 3.68E-01 l 5.6 % of Beta T.S. Limit (%) l 7.85E-03 6.00E-01 l 6.0 IODINES 6.1 Total I-131 (Ci) l 1.24E-06 1.30E-03 2.50E+01 l 6.2 Average Release Rate (pci/sec) l 1.58E-07 1.65E-04 7.0 PARTICULATES 7.1 Total Release (Ci) l 1.30E-il 9.75E-05 2. 50E+01 l 7.2 Average Release Rate (pCi/sec) l 1.65E-12 1.24E-05 8.0 TRITIUM 8.1 Total Release (C1) l 1.29E+01 1 2.00E+01 12.50E+01l 8.2 Average Release Rate (pCi/sec) l 2.28E+00 1 2.54E+00 l 9.0 TOTAL IODINE PARTICULATES AND l l TRITIUM (pci/sec) l 2.28E+00 l 2.54E+00 ll 2.50E+01l l 10.0 DOSE (area) l 3.23E-02 l 2.60E-OL l 11.0 % OF T.S. LIMIT (%) l 2.15E-01 l L.73E+00 l 12.0 GROSS ALPHA 12.1 Total Release, (C1) l 0.00EM 0 l 5.06E-09 l 2.50E+0lj
, e eme. e m e =====e*
F1Mr 133, Nev. e Pass 5 of 8 i
TABLE IC
^
EHLUENT SEMIANNUAL REPORT GASEOUS EHLUENTS GROUND LEVEL RELEASES
~ .
CONTINUOUS MODE BATCH MODE I I i . 1 I i l l NUCLIDE l UNIT l QTR 3 l QTR 4 l QTR 3 l QTR 4 l
'. I I I I i l l 13.0 INDIVIDUAL FISSION AND ACTIVATION GASES l Kr85 Ci 6.41E-01 2.19E+00 7.31E-01 l j l Kr85e Ci l
- j. l Kr87 Ci l j^ l Kr88 Ci l l Xe133 Ci 6.66E-02 6.23E+01 6.76E+00 l l Xe135 Ci 1.00E-04 9.07E-01 4.85E-03 l 2
l Xe135m Ci l
- l Xe138 Ci i .
l l Xel31m Ci 5.29E-02 1.61E-01 l l Ar41 Ci l
} l %4133m Ci 6.45E-04 1.06E+00 3.33E-02 l
! I I
^
l l l 1 1 l Total Ci 7.08E-01 6.65E+01 0.00E+00 -
7.69E+00 l
- 14.0 IODINES (Ci) l I131 Ci 8.48E-07 8.63E-04 3.96E-07 4.36E-04 l l l 1133 Ci 3.40E-05 1.91E-04 l l
l l 1135 Ci 7.50E-05 -l l Total Ci 8.48E-07 8.97E-04 3.96E-07 7.02E-04 l f
CONTINUGUS MODE BATCH MODE I I I I I I l
] l NUCLIDE l UNIT l QTRl l QTR 4 l QTR 3 l QTR 4 l
- l l I l l l l
- 15.0 PARTICULATES (Ci) l Sr89 C1 1.30E-11 ~
0.00E+0 l l Sr90 Ci 0.00E+0 0.00E+0 l l l Cs134 Ci 4.43E-05 l t
l Cs137 Ci 3.48E-05 l
'. l Ba-L4140 Ci l
!* l CoS8 Ci 1.98E-06 l i l Co60 1 Ci 9.82E-07 l l 1.54E-05 l j l Total C1 1.30E-11 0.00E+00 9.75E-05 l l t
, ., - ,.- . ......, -.-, ,_ _,- _ - . - . - = . . _ - . - .. . .-. . . . - . - - . - . . . - . . . - - . . . - . . . . -
m I
f1NUF 133, saw. O Par;n 6 of 8 TABLE 2A EFFLUENT SEMIANNUAL REPORT - l LIQUID EFFLUENTS - SLHMATION OF ALL RELEASES ,
UNIT l QTR 3 l QTR 4 l l l 1 I I 16.0 VOLUME OF WASTE (Prior to Dilution) l Liters i 5.46E+07 l 5.45E+07 i 2.50E+01l 17.0 VOLLHE OF DILUTION Water (liters) l Liters i 2.18E+11 l 1.61E+11 l 2.50E+01l 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 Total Release W/0 H-3, (Ci) l '
Rad Gas, Alpha i 8.12E-03 l 8.12E-03 ' 2.50E+01' I
18.2 Average Diluted (pCi/ml) l '
Concentration 3.72E-11 l 5.04E-11 l l 19.0 TRITILH 19.1 Total Release (Ci) l 2.56E+02 1.30E+02 2.50E+01 l 19.2 Average Diluted (pCi/ml) l Concentration 1.17E-06 8.07E-07 l l l 20.0 DISSOLVED AND ENTRAINED GASES 20.1 Total Release (CL) l 2.83E-02 1.00E-01 2.50E+01l 20.2 Average Diluted (pCi/ml) l Concentration 1.30E-10 6.21E-10 l l l 21.0 GROSS ALPNA 21.1 Total Release (C1) l 0.00E+00 l 0.00E+00 12.50E+01 l 22.0 TOTAL TRITILM, FISSION AND ACTIVATION 1RODUCTS (pCi/ml) l 1.17E-06 l 8.07E-07 l 2.50E+01_ l
- - - - - , . _ - . ----,w - ,r .,a-,. , , , -._-,,,a,, - -, -
. "'** 0 ISS, 2,7. 5 Page 7 of 8 TABLE 2A l
EFFLUENT SEMIANNUAL REPORT -
LIQUID EFFLUENTS - S12fMATION OF ALL RELEASES l UNIT QTR 3 4
l l
l l
l QTR 4 l l hll if 23.0 TOTAL BODY DOSE (mrem) l 5.85E-04 l 4.53E-03 l 24.0 CRITICAL ORGAN DOSE (mrem) l 6.03E-04 5.92E-03 l l (organ) l G.I. Liver .l 15.0 % TOTAL BODY T.S. LIMIT (*,) I 1.95E-02 1 1.51E-01 l 26.0 '.,0F CRITICAL ORGAN (*.) l I !
6.03E-03 5.92E-02
! :.a. Limit i I l J
9 I
l l
)
i i
l
. PINGP 158, Rev, o Page 8 cf 8 I
! TABLE 2A I
! EFFI.UENT SEMIANNUAL RPEORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES CONTINUOUS MODE BATCH N0DE l l l l 1 I l l NUCLIDE l UNIT l QTR 3 l QTR 4 l QTR 3 l QTR 4 l r l l l l i I I 37.0 INDIVIDUAL LIOUID EFFLUENT l Sr89 Ci 0.00E+00 1 - 0.00E+00 ' -
l l Sr90 Ci 0.00E+00 - 0.00E+00 - l 2
l Csl34 Ci 5.12E-04 l i
l Cs137 i Ci 9.83E-05 2.50E-06 4.14E-04 l l 1131 ! Ci 1.47E-03 l j l CoS8 1 Ci 4.7aE-05 2.46E-04 7.26E-04 3. S aE-0 3 l
) ! Cn0 C1 1.61E-04 3.04E-04 l l l Fe59 Ci 5.73E-05 9.80E-05 l
! l 2n65 Ci l l l Mn54 Ci l l l Cr51 C1 1.46E-04 l l Zr-Nb95 Ci 6.87E-06 l ;
l Mo99 Ci l l l Ba-Lal40 Ci l l Fe-55 Ci 0.00E+00 - 1.82E-04 - l l Subtotal ' C1 4.78E-05 3.44E-04 1.11r-01 4 str-n1 l l Total * ' Ci 3.93E-03 1.11E-03 4. tor-03 7 ntr n1 l
- SEE ATTACHED SHEET OF ADDITIONAL NUCLIDES j CONTINUOUS MODE BATCH MODE j i l i 1- 1 i l 1 NUCLIDE l UNIT l QTR 1 l QTR A l QTRL l QTRL l l l l l l l l 28.0 DISS0!NED AND ENTRAINED GASES l l Xel33 Ci i 1.3aE-02 a.4tr-02 l l Xe133m C1 1 4.ott-os t.Ar.r ns l
} l Xel31m -
Ci 4.54E-03 l l Xel35 Ci i 1.26E-05 7.24E-04 l l Kr85m Ci I
. I Kr85 Ci 1.44E-02 1.llE-02 l l Kr88 Ci l
, l I l l l Total Ci 0.00E+00 0.00E+00 '
2.83E-02 1.00E-01 l l
I
ADDITIONAL NUCLIDES CONTINUOUS HODE BATCH MODE .
NUCLIDE UNIT GTR 3 GTR 4 GTR 3 GTR 4
- _________g____;____________i____________;____________;____________
l A9-110m l Ci l l l l 1.70E-05 l i_________;____l____________i____________l____________l____________l l I-133 l Ci l 1.27E-03 l 3.082-04 l l l g_________i____;-___________l____________;-___________i____________l l I-134 l Ci l l 1.33E-04 l l l l_________;____;____________l____________l____________!____________;
l Na-24 l Ci l 3.07E-03 l 3.19E-04 l l l
- .________l____j____________;-___________;____________i____________[
l sb-1:4 i Ci l l l 1.10E-03 1 3.06E-04 I l_________!____j.___________;____________;-___________[____________;
I 3b-103 l Ci l i i 1.96E-03 l 0.56E-05 l i_________l____;____________; .;____________;____________;
I 3c-47 l Ci l l l l 9.64E-05 l l_________j____;____________;____________;________<.___! ___________!
I Sn-113 i Ci l l l 5.10E-06 2.99E-05 l_________;____[____________l____________;____________
l_________!____;____________l____________l____________j_.__________;
I Subtotall Ci i 3.34E-03 l 7.62E-04 l 3.06E-03 4.34E-04 l_________;____;____________ ____________j____________jl____________;l
~
PINGP 753, Rev. O Rotention: Lifetima Pege 1 of 5 g PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: July-Dec 1984 i NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I: Solid Waste and Irradiated Fuel Shipments A. Solid Waste Total Volumes and Measured Curie Quantities:
- 1. Type of Waste:
Container Units Total Volumes A. Spent Resin __31... 2,4,. 0 6 , , ,, 4.,811 ,,,
_.ct.._ _U 22%_ ..__ ....
M3 9.11 0.212 B. Drv Compacted Trash ------ - ------- ---------
..Ct... . JL109. . .... ....
None C. Non-Comoacted Trash ------- ------' ---------
D. Waste Concentrates .. h.... . 8 .69. ,,,
0.
,,,,2,12 ,,,
..C1,,,, ,,%jgq, ,,,,,,,,,
e..ee.. ..W..e6 66.e.6.G G
- q
.. .)
1 I
l
PINGP 753, Rev. 0 Ratcntion: Lifotime Pega 2 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: July-Dec 1984 NORTHERN STATES POWER , License No. DPR-42 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:
TYPE Nuclide Percent
- H-3 3.9
. _ _A. . .
3g.5g_ 333...
- cro 36 - 37:5 - - -
- ro:56 c - -
1 I---
- - yq:f $ ~ -~~g---
- cis IIC 1 1:6---
.--.c.;I5_7
.. -13. .:6....- - -
B *
....._ . .H. .3 , . 31_. 7. . . .
- Fe-33 16.8
- ro150-c - 7 :5---
- - &185-s -1o :2---
- 11125 s 1:i---
- is1I5E c 9 7-~~
~-cs1157 1
3:6---
re I---
.....3g g.-3 9 .-
- Inferred (Not by Direct Measurement)
IBM
~PINGP 753, Rcv. O Rotention: Lifetima Page 3 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: July-Dec 1984 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT rable I: Solid Waste and Irradiated Fuel Shipments (Continued)
- 2. Measured Major Nuclide Composition by Type of Waste (Continuation):
TYPE Nuclide Percent
..D...
. . H _3ms. 40. . 7...
..fe ,aa.
. 0o.-23
. 8 6. . .
g__g_ . 3 2. . .
- - gr 63-
~~f.8 ---
- gb-123 - f. 4
~ ~ci 134 fi.Y - -
- di 137 *
- f9.8 g.t.m..
. . . 3. . .
t I
[
- Inferred (Not by Direct Measurement) l l
IBM 1
f
. . PINGP 753, Rev. 0 Retention: Lifetime Page 4'of 5 -
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: July-Dec 1984 NORTHERN STATES POWER License No. DPR-42 SOLID RADIQACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I: Solid Waste and Irradiated Fuel Shipments (Continued)
- 3. Solid Waste Disposition:
Number o f Shipments Mode Destination 6 Truck Richland, Washington J
B. Irradiated Fuel Shipments: -
Number of Shipments Mode Destination None i
~
I i IBM i
PINGP 753, Rev. O Retention: Lifetime Page 5 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: Juiv-Dec 1984 License No. DPR-42
~
NORTHERN STATES POWER SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I: Solid Waste and Irradiated Fuel Shipments (Continued)
C. Shipping Container and Solidification Method:
No. Volume Activity Type of Container Solidify (M3) (Ci) Waste Code Code R4-26 9.11 .109 B L R4-26 8.69 .366 D L c R4-25 4.R11 5.572 A L R4-21 4.311 .654 A L R4-2O_ 4.811 .800 A L R4-14 4.811 2.010 A L R4-in 4.R11 2.160 A L ,
CONTAINER CODES: L = LSA .
A = Type A B = Type B Q = Large Quanity SOLIDIFICATION CODES: C = Cement I
IBM
+c,. , , - - , . - , - - , . - ,_, -. --r--. -
l NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFFSITE RADIATION DOSE ASSESSMENT for JANUARY 1 - DECEMBER 31 1984
, An assessment of radiation dose due to releases from the Prairie Island
- Nuclear Generating Plant during 1984 was performed in accordance with the Technical Specifications. Computed doses were well below the 40 CFR Part 190 and 10 CFR Part 50, Appendix I standards and guidelines.
Offsite dose calculation formulas and meteorological data were used from the Offsite Dose Calculation Manual in making this assessment. Source terms were obtained from the two Effluent and Waste Disposal i Semi-Annual reports prepared for NRC review during the year.
1 Offsite Doses from Gaseous Release Computed doses due to gaseous releases a~re 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 L guidelines.
Offsite Doses from Liquid Release Computed doses due to liquid releases are reported in Table 1. Receptor information is reported in Table 2. Doses, both whole body and organ, are a small percentage of Appendix I guidlines.
- Doses -to Individuals Due to Activities Inside the Site Boundary Occasional sportsmen will enter the Prairie Island site for recreational i
activities. These individuals are not expected to spend more than a i
few hours per year within the site boundary. Commercial and recreational river traffic exists through this area.
For purposes of estimating dose due to recreational and river
- transporation activities within the site boundary, it is assumed that
' the limiting dose within the site boundary would be 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 l and inhalation organ doses were calculated for this location and occupancy time. These doses are reported in Table 1.
Doses to Most Exposed Member of the General Public from Reactor Releases and Other Nearby Uranium Fuel Cycle Sources There are no uranium fuel cycle facilities in the vicinity of the Prairie Island site.
(
- FLF021585GDWO2 i
The only other source of exposure to the general public in addition to the plant gaseous and liquid effluents is from direct radiation.
Pressurized water reactor direct radiation has been shown to be negligible. An array of TLD monitoring locations at the site boundary has consistently indicated that plant operation in recent years has had no effect on ambient gamma radiation.
Therefore, the most exposed member of the general public will not receive a radiation dose from reactor 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 within the 40 CFR Part 190 standards of 25 mrem to the whole body or any organ (except the thyroid) and 75 mrem to the thyroid every 12 months.
L 3
n FLF021585G0WO2
TABLE 1 0FFSITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND -
PERIOD: JANUARY 1 THROUGH DECEMBER 31, 1984 10 CFR Part 50 Appendix I Gaseous Releases' Guideline Per Year Maximum Site Boundary j Gamma Air Dose (mrad) 0.04 20 Maximum Site Boundary Beta Air Dose (mrad)* 0.12 40 Maximum Offsite Dose to Any Organ (mrem)
Total 0.40 30 Offshore Location
! (mrem, 7 days /. year)
Whole Body 0.0002 10 Organ D UDU2 30 Liquid Releases Maximum Offsite Whole Body Dose (mrem)
Total 0.006 6 Maximum Offsite Organ Dose (mrem)*
Total 0.01 20
1 1
FLF021585GDWO2
~-
TABLE 2 0FFSITE RADIATION DOSE ASSESSMENT :
SUPPLEMENTAL INFORAMTION - PRAIRIE ISLAND I PERIOD: JANUARY 1 THROUGH DECEMBER 31, 1984 Gaseous Effluents l i
Maximum Site Boundary Dose Location .
(from building vents) '
Sector WNW Distance (mi) 0.36 Offshore Location Within Site Boundary Sector ESE Distance (mi) 0,2 Maximum Offsite i Dose Location !
Sector SSE Distance (mi) 0.6 Pathways Ground, j inhalation, vegetables i
Age Group Child Organ Thyroid Lipuid Effluents Maximum Offsite Dose Location Downstream i Pathways Fish I Age Group Adult Organ Throid l l
FLF021585GDW02 1
o '.
TMO Northem States Power Company 414 Nicollet Mail Minneapons. Minnesota 55401 Te'epnone i612) 330 5500 March 1, 1985 FRIC11TY ROUTING w
u pc1L Regional Administrator hj- ig Region III b i at l U S Nuclear Regulatory Commission 6 ./ ms om yg-
) 799 Roosevelt Road l
Glen Ellyn, Illinois 60137 FILE _/u2.0 i
Prairie Island Nuclear Generatiiig Diant Docket No. 50-282 License No. DPR-42
[ 50-306 DPR-60 Effluent and Waste Disposal Semi-Annual Report for July 1,1984 through December 31, 1984 In accordance with the Prairie Island Technical Specifications, Appendix A to Operating License DPR-42 and DPR-60, we are submitting one copy of the Effluent and Waste Disposal Semi-Annual Report, covering the last half of 1984.
Analyses for isotopes, Sr-89, Sr-90 and Fe-55 were not completed for Quarter 4 in time to be included in this report. A separate submittal will be made when they are available.
I 1 F. L. Fey, Jr., General Superintendent Radiological Protection and Chemistry Nuclear Generation Department Attachment cc: U. S. NRC, Document Control Desk (1)
G. Charnoff (w/o attachment)
MPCA - Attn: J. W. Ferman Resident Inspector, U. S. NRC Project Manager, U. S. NRC gdw
/
]E}D lll BWC020685GDWO4 4
_ _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ _ _