ML20137X935

From kanterella
Jump to navigation Jump to search
Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1985
ML20137X935
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 12/31/1985
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML113200495 List:
References
NUDOCS 8603120044
Download: ML20137X935 (20)
v • d • e


Text

f  ;

I l

. Pago 1 fMMTICELLONUCLEARGENERATING PLANT Period: Jul - Dec 1985 lMORTHERN STATES POWER COMPANY License No. DPR-22 ,

h l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information i 1.

l1. Rogulatory Limits - Suarterly levels requiring reporting-

! to Nuclear Regulatory Commission l

I A. Noble Gases l

5 mrad / quarter gamma radiation 10 mrad / quarter beta radiation i

B. Long Lived Iodines, Particulates, and Tritium '

l 7.5 area / quarter to any organ l .

l C. Liquid Effluents:

! 1.5 mram/ quarter dose to the total body 5.0 mram/ quarter dose to any organ f

l2. Maximum Permissible Concentrations: [

l A. Noble Gasass ,

i 10 CTR Part 20, Appendix B. Table II, Column 1  !

l I

B. Long Lived Iodines, Particulates, and Tritium

, 10 CFR Part 20, Appendix B. Table II, Column 1 i l

i C. Liquid Effluents:

10 CTR Part 20, Appendix B, Table II, Column 2 2 E-04 uci/ml for dissolved and entrained gases

!3. Avorage Energy:

(Nat Applicable) f 1

l \

l l

I l

i I

i 3

s

' Page 2' 2CNTICELLO NUCLEAR GENERATING PLANT Period: Jul - Dec 1985 NCRTNERN STATES POWER COMPANY License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information (continued)

4. Maccurements and Approximations of Total Radioactivity:

A. Noble Gases:

Continuous gross activity monitors in Reactor Building Vent and plant otack exhaust streams. Weekly isotopic analysis of steam det cir ejector stream. Monthly analysis of storage tank contents.

B. Iodines in Gaseous Effluent Continuous monitoring with charcoal cartridges in Reactor Building vant and plant stack exhaust streams with weekly analysis.

C. Particulates in Gaseous Effluents Continuous monitoring with particulate filters in Reactor Building vent and plant stack exhaust streams with weekly analysis.

D. Tritium in Gaseous Effluents Continuous monitoring with silica gel cartridges in Reactor Building vant and plant stack exhaust streams with biueekly analysis.

E. Liquid Effluents:

Tank sample analyzed prior to each planned release and continuous conitoring of gross activity during planned release.

5. Botch Releases:

A. Liquid

1. Number of Batch Releases 0
2. Total Time Period For Batch Releases 0.0 Min
3. Maximum Time Period for a Batch Release 0.0 Min
4. Average Time Period for a Batch Release 0.0 Min
5. Minimum Time Period for a Batch Release 0.0 Min
6. Average River Flou During Releases 0.0 Cf/sec B. Gaseous
1. Number of Batch Releases O'
2. Total Time Period for Batch Releases MA Min
3. Maximum Time Period for a Batch Release NA Min
4. Average Time Period for a Batch Release NA Min
5. Minimum Time Period for a Batch Release NA Min
6. Abnormal Releases:

A. Liquid

1. Number of Releases 0
2. Total Activity Released 0.0 Ci B. Gaseous
1. Number of Releases 0
2. Total Activity Released 0.0 Ci

s Pogo 3 MONTICELLO NUCLEAR GENERATING PLANT Period: Jul - Dec 1985 NORTHERN STATES POWER COMPANY License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Table 1A Gaseous Effluents -

Summation of all Releases Units 1st Str 2nd Str Pcnt Est Error A. Noble Gases:

1. Total Release A. Elevated Release ci 5.50E+02 6.42E+02 B. Building Vent Release ci 1.55E+02 1.57E+02 C. Total Ci 7.05E+02 7.99E+02 5.00E+01
2. Average Release Rates A. Elevated Release uCi/sec 6.92E+01 8.08E+01 B. Building Vent Release uci/sec 1.95E+01 1.97E+01 C. Total uci/sec 8.87E+01 1.01E+02 5.00E+01
3. Percent Tech Spec Strly Reporting Level Gamma Radiation 3.801:M 0 3.4HE+00 Beta Radiation .!.39E+00 2.lHE+00 B. Iodines:
1. Total I-131:

A. Elevated Release Ci 4.41E-03 4.25E-03 B. Building Vent Release C1 1.51E-02 9.22E-03 C. Total C1 1.95E-02 1.35E-02 5.00E+01

2. Average I-131 Release Rates A. Elevated Release uCi/sec 5.55E-04 5.35E-04 B. Building Vent Release uCi/see 1.90E-03 1.16E-03 C. Total uC1/sec 2.45E-03 1.70E-03 5.00E+01 C. Long Lived Particulates and Gross Alpha Releases:
1. Total Particulates:

A. Elevated Release ci 8.54E-04 1.21E-03 B. Building Vent Release C1 2.23E-02 5.78E-04

c. Total C1 2.32E-02 1.79E-03 5.00E+01
2. Average Release Rates

)

A. Elevated Release uC1/sec 1.07E-04 1.52E-04 B. Building Vent Release uCi/sec 2.81E-03 7.28E-05 C. Total uci/sec 2.92E-03 2.25E-04 5.00E+01 3

1

Pago 4 1 OMTICELLO HUCLEAR GENERATING PLANT Period: Jul - Dec 1985 h'0RTHERNSTATES POWER COMPANY License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Tchle 1A Gaseous Effluents - Summation of All Releases (Continued)

Units 1st Str 2nd Qtr Pont Est Error

3. Gross Alpha Radioactivity:

A. Elevated Release C1 4.01E-07 3.75E-07 B. Building Vent Release ci 3.14E-05 1.82E-05 C. Total C1 3.18E-05 1.86E-05 1.00E+02

3. Tritium:
1. Total Release A. Elevated Release C1 2.42E+00 1.42E+01 B. Building Vent Release C1 1.50E+01 1.26E+01 C. Total CI 1.75E+01 2.68E+01 5.00E+01
2. Average Release Rates A. Elevated Release uC1/sec 3.05E-01 1.78E+00 B. Building Vent Release uC1/sec 1.89E+00 1.59E+00 {

C. Total uC1/sec 2.20E+00 3.37E+00 5.00E+01

3. Porcent Tech Spec Strly Reporting 5.611:+ 00 3.53t:wO Lovel for Long Lived Iodines, Patriculates, and Tritium

u Pogo 5 MONTICELLO NUCLEAR GENERATING PLANT Period: Jul - Dec 1985 NORTHERN STATES POWER COMPANY License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Table IB Gaseous Effluents - Elevated Release continuous Mode Batch Modo Nuclides Released Units 1st Str 2nd Str 1st Str 2nd Str

1. Noble Gases
  • Xo133 C1 2.46E+02 3.08E+02 0.0 0.0 Xo135 C1 3.84E+00 4.42E+00 0.0 0.0 Kr85M Ci 7.55E-01 1.02E+00 0.0 0.0  ;

Mr88 C1 2.35E+00 3.15E+00 0.0 0.0 Kr87 C1 3.28E+00 3.72E+00 0.0 0.0 Xo138 Ci 8.53E+01 7.31E+01 0.0 0.0 i Kr90 Ci 2.22E+00 2.57E+00 0.0 0.0 Xo139 C1 6.60E+00 7.65E+00 0.0 0.0  ;

Mr89 Ci 6.52E+01 7.59E+01 0.0 0.0 Xo137 C1 8.52E+01 9.92E+01 0.0 0.0 Xct35M Ci 5.01E+00 5.89E+00 0.0 0.0 Mr83M C1 7.06E-01 8.51E-01 0.0 0.0 Xo133M C1 1.07E+00 1.22E+00 0.0 0.0 Xo131M Ci 1.47E+00 1.87E+00 0.0 0.0 Mr85 C1 4.11E+01 5.38E+01 0.0 0.0 Total for Period Ci 5.50E+02 6.42E+02 0.0 0.0

2. Iodiness I-131 Ci 4.41E-03 4.25E-03 0.0 0.0 I-133 C1 1.46E-02 1.96E-02 0.0 0.0 I-135 C1 1.88E-02 1.87E-02 0.0 0.0 i

Total Ci 3.78E-02 4.26E-02 0.0 0.0 b

2

. Page 6 l .

ZONTICELLO NUCLEAR GENERATING PLANT Period Jul - Dec 1985 JORTHERN STATES POWER COMPANY License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l

Table IB Gaseous Effluents - Elevated Release (Continued)

Continuous Mode Batch Mode

[uclidos Released Units 1st Str 2nd Str 1st Str 2nd Str D. Porticulates Co144 Ci 6.06E-06 1.34E-05 0.0 0.0 C0141 Ci 0.0 2.71E-06 0.0 0.0 Bn140 Ci 6.16E-04 1.18E-03 0.0 0.0 Cs137 C1 4.54E-06 1.15E-05 0.0 0.0 Sr90 Ci 9.12E-07

  • 0.0 0.0 Sr89 C1 2.27E-04
  • 0.0 0.0 co60 C1 0.0 5.76E-06 0.0 0.0 Mn54 Ci 0.0 3.68E-07 0.0 0.0 Totc1 Ci 8.54E-04 1.21E-03 0.0 0.0
  • furnished later

. Page 7' MONTICELLO NUCLEAR GENERATING PLANT Period Jul - Dec 1985 NORTHERN STATES POWER COMPANY License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Table IC Gaseous Effluents - Building Vent Relonne Continuous Mode Batch Mode Nuclidos Released Units 1st Str 2nd 9tr 1st Str 2nd Str

1. Noble Gasesa Xo133 Ci 5.76E-01 7.13E-01 0.0 0.0 Xo135 Ci 2.44E+00 2.65E+00 0.0 0.0 Kr85M Ci 4.73E-01 5.97E-01 0.0 0.0 Mr88 C1 1.47E+00 1.84E+00 0.0 0.0 Mr87 C1 2.05E+00 2.00E+00 0.0 0.0 Xo138 Ci 4.68E+01 4.23E+01 0.0 0.0 Kr90 C1 1.36E+00 1.43E+00 0.0 0.0 Xo139 Ci 4.06E+00 4.25E+00 0.0 0.0 Kr89 C1 4.01E+01 4.22E+01 0.0 0.0 Xo137 Ci 5.24E+01 5.52E+01 0.0 0.0 Xo135M C1 3.09E+00 3.20E+00 0.0 0.0 Kr83M Ci 4.38E-01 4.81E-01 0.0 0.0 Xo133M Ci 1.80E-02 2.20E-02 0.0 0.0 Xo131M Ci 1.46E-03 1.81E-03 0.0 0.0 Kr85 C1 2.06E-02 2.53E-02 0.0 0.0 Total for Period C1 1.55E+02 1.57E+02 0.0 0.0
2. Iodiness I-131 C1 1.51E-02 9.22E-03 0.0 0.0 I-133 Ci 9.98E-02 6.05E-02 0.0 0.0 I-135 C1 1.52E-01 9.84r.-02 0.0 0.0 Totei ci 2.67E-01 1.68E-01 0.0 0.0 i

l

1

- Pcge 8 o

MONTICELLO NUCLEAR GENERATING PLANT Periode Jul - Dec 1985 MGRTHERN STATES POWER COMPANY License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT Table IC Gaseous Effluents -

Building Vent Releases (Continued)

Continuous Mode Batch Mode Nuclidos Released Units 1st Str 2nd Str 1st Str 2nd Str

3. Porticulates:

Co141 Ci 3.72E-06 0.0 0.0 0.0 Bc140 Ci 4.58E-04 4.42E-04 0.0 0.0 Cs137 C1 8.34E-04 4.21E-05 0.0 0.0 CD134 C1 1.47E-04 0.0 0.0 0.0 Sr90 Ci 8.02E-05

  • 0.0 0.0 Sr89 Ci 7.04E-05
  • 0.0 0.0 Zn65 C1 2.63E-03 0.0 0.0 0.0 Co60 C1 1.76E-02 9.07E-05 0.0 0.0 Mn54 C1 4.90E-04 0.0 0.0 0.0 1 Total C1 2.23E-02 5.78E-04 0.0 0.0
  • furnished later i

l

. Pcgo 9 MbMTICELLOMUCLEARGENERATINGPLANT Periods Jul - Dec 1985 NORTNERN STATES POWER COMPANY License No. DPR-22 [

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT  !-

Table 2A Liquid Effluents - Summation of All Releases Units 1st Str 2nd Str Pont Est Error j A. Fiasion and Activation Products: l l

1. Total Release Ci 0.0 0.0 0.0 (ExcePt H-3, Cases, and Alpha)
2. Avg Diluted Concentration uCi/mi 0.0 0.0 .

i

5. Tritiums i i
1. Total Release ci 0.0 0.0 0.0 l
2. Avg Diluted Concentration uC1/ml 0.0 0.0 l C. Diccolved and Entrained Gasess

{

1. Total Release ci 0.0 0.0 0.0 f
2. Avg Diluted Concentration uct/ml 9.0 0.0 i l

D. Porcent Strly Tech SPac Reporting  !

I Loval r

Whole Body Dose 0.0 0.0  !

Orgon Dosa 0.0 0.0 l E. Gross A1Pha Radioactivity 8

1. Total Release ci 0.0 0.0 0.0 F. Volume of Waste Re21ased Litors 0.0 0.0 0.0
c. Volume of Dilution Water Used Liters 0.0 0.0 0.0 1

l I

l i

i L .

  • Pcgo 10

. i MONTICELLO HUCLEAR GLHERATING PLANT '

Period Jul - Dec 1985 N RTHERN STATES POWER COMPANY License No. DPR-21 EFFLUEHT AND WASTE DISPOSAL SEMIAHHUAL REPORT Table 28 Liquid Effluents Continuous Modo Batch Mode Huolidos Released Units 1st Str 2nd Str 1st Str 2nd Str Hone Released This Period l

l l

i t

i i

i l

l l

l l

l l

l l

i l

i

(

I l

t I

. Pego 11 MbMTICELLO MUCLEAR GENERATING PLANT Period Jul - Doc 1985 NORTHERN STATES POWER COMPANY License No. DPR-22 EFTLUENT AND WtSTE DISPOSAL SEMIANNUAL REPORT Table 3 Solid Wasto and Irradiated Tuol ShiPmonts A. Solid Wasta Shipped offsito For Burial or Disposal

1. Type of Wasten Pent Eat Units Total Error A. Spent Resins. Tilter Sludges. Cu Mo to r H. 501:+0i Evaporator Bottoms. Etc. Ci 8.19E+02 5.00E+01 B. Dry Compressible Waste. Cu Motor 1.40E+02 Contaminated Equip. Etc. C1 3.76E+01 5.00E+01 C. Irradiated Components. Cu Motor 6.51E+00 Control Rods, Etc. C1 3.35E+03 5.00E+01 D. Other (described belou):

None 1

?

i

! - Pcgo 12 MONTICELLO HUCLEAR GENERATING PLANT Period Jul - Dec 1985 NORTHERN STATES POWER COMPANY Licenso No. DPR-22 ErrLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Table 3 Solid Wusto and Irradiated ruel Shipments (Continued)

2. Measured Major Nuclide Composition by Type of Waste 8 l

l TYPE Huclide Percent l

A Ba140 8.280-01 l

Cs137 9.69E+C0 Cs134 2.49E*00 Sr90 7.38E-01 Sr89 2.19E+00 En65 6.987.+00 Co60 1.34E+01 Co68 1.97t+00 Mn54 3.40E+00 Cr51 1.19E+01 1 131 1.t:2E+00 Tc55 3.97E+01 l

1 B na140 7.63E-03 l Cs137 3.25E+00

! Gr90 8.55E-02 Sr89 1.63E-01 Zn65 84 . 2 4 E + 0 0 t

Co60 5.91E+01 l Mn54 6.28E-01 La140 8.15E-03 re55 2.08t+01 l C Co60 6.85E+01

( ro G9 7.74E-02 l CoSS 2.97E-02 Mn S to 1.26E+00 l

Cr51 7.08E-01 ro$$ 2.50E+01 l

1

{

1

l Pcgo 13 HONTICELLO NUCLEAR GENERATING PLANT Period 8 Jul - Dec 1985 NORTHERN STATES POWER COMPANY License No. DPR-22 ErrLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Table 3 Solid Waste and Irradiated Tuel Shipments (Continued)

3. Solid Waste Dispositiont Number of Shipments Mode Destination l

9 Truck Chem-Nuo Inc., Barnuall. SC 4 Truck US Ecology. Richland. WA 10 Rail US Ecology, Richland, WA '

3. Irradiated ruel ShiPmonts:

Number of Shipments Mode Destination 7 Rail General Electric. Morris. IL  !

I 3

1

Pcgo 14 MONTICELLO HUCLEAR GENERATING PLANT period Jul - Dec 1985 NORTHERN STATES POWER COMPANY License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ,

Table 3 Solid Wasto and Irradiated Tuol shipments (Continued)

C. Shipping Container and Solidification Methods No. Volume Activity Type of Container Solidification (

(M3) (C1) Waste Code Codo (85-44) 5.66t+00 9.02E+01 A A C (85-50) 5.66t+00 1.19E+02 A A C (85-48) 5.66t+00 6.85E+01 A A , C (85-52) 5.66t+00 5.45E+01 A A C (85-53) 5.66t+00 5.59E+01 A A C l

(85-56) 1.57E+01 1.15E-01 B L (85-57) 5.66E+00 1.10E+00 B A t (85-58) 5.66E*00 5.20E+01 A A C (85-59) 3.26t+00 1.89E+03 C B (85-61) 3.81E+01 5.82E-01 B L (85-62) 5.66E+00 5.39E+01 A A C (85-64) 3.26E+00 1.47E+03 C D (85-65) 5.66E+00 6.37E+01 A A C (85-68) 3.81E+01 6.17E-01 B L (85-70) 5.66E+00 3.93E+01 A A C (85-74) 5.66E+00 3.16E+01 A A C (85-76) 5.66t+00 2.17E+01 A A C (85-78) 5.66E+00 5.83E*01 A A C (85-79) 5.66t+00 5.43E+01 A A C (85-82) 3.81E+01 9.24E-01 B L (85-81) 5.66E+00 2.19E*01 A A C (45-85) 5. 66 E+ 0 0 3. 34E + 01 A A C (85-86) 4.56t+00 3.43E+01 B A CONTAINER CODESI L - LSA A - Type A B - Type D 9 - Large Quantity 50LITICATION CODES: C - Coment U - Uran Formaldehyde b

}

i 3

1

Pogo 15

!MONTICELLO NUCLEAR GENERATING PLANT Periodt Jul - Dec 1985 NORTHERN STATES P0fdR COMPANY License No. DPR-22  ;

t i ETTLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l

lMotoot l (

1. RQ1 ease of individual noble gas isotopes from the plant i i

stock was determined using an isotopic analysis at the stena l jot cir ejector. Xe133. Xe135. Mr85H. Mr88. Mr87, and

Xo134 were measured and used to charactorine the modo of gas

,rolocco from the fuel. Other significant noble gases wore

,datorcined using known ratios, the measured total offgas Iholdup system delay time. and the known fraction of the

, effges stream released via the gland exhaust.or.

! 2. An isotopic analysis for nobio gases is normally not ipossible at the building vents. Individual isotopes are

' gonorolly belou their lower limit of de tection (LLD). <

lThorofore, for reactor building vont releases. the

!noblo gas isotopic mixture is assumed to be the name as l tho cixture determined at the steam jet air asector.

l i3. Information specified in Regulatory Guido 1.21

which is not- applicable to the Monticello plant is

!indiccted by 'NA'.

I

4. Hualides not detected in plant affluents (those bolou the LLD of the analysis) are not included in tho quantitles reported released. LLD values are recorded i cnd cust be less than the minimum LLD values stated in the ,

l M:nticello Technical Specifications.

i l

l l

I l

f -

5 i

(1-

l t I

i l l NORTHERN STATES POWER COMPANY

} MONTICELLO NUCLEAR GENERATING PLANT  !

OFFSITE RADIATION DOSE ASSESSMENT FOR I January TT0ecemoer H,~19W~~

An assessment of radiation dose due to releases from the Monticello I i Nuclear Generating Plant during 1985 was performed in accordance with the [

L Technical Specifications. Computed doses were well below the 40 CFR Part r j 190 and 10 CFR Part 50, Appendix ! standards and guidelines.

l

- Offsite dose calculation formulas and meteorological data were used from j i the Offstte Oose Calculation Manual in making this assessment. Source -

I terms were obtained from the two Effluent and Waste Disposal Semi-Annual  !

l reports prepared for NRC review during the year. -

Offsite Doses from Gaseous Release l

Computed doses due to gaseous releases are reported in Table 1. Critical  ;

receptor location and pathways for organ doses are reported in Table 2.  !

j Doses, both whole body and organ, are a sma11 percentage of Appendiz ! t i guidelines.

Offsite Ooses___from__Lt 3 uld Release ,

There were no liquid releases made fr m the Monticello Plant during the ,

1985 calendar year.

l Ooses to Individuals Due to Activities Inside

~

I ithe_fitTBpdndary f i

Occasional sportsmen will enter the Monticello site for recreational  !

activities. In addition, an Environmental Protection Agency Field  !

$tation is located at the Monticello site (See Figure 3.8.1 or Figure }

3.8.2 in the Monticello Technical Specifications). Workers at this t field station, spending an average of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> / week, are the most [

exposed individuals. Whole body doses to these individuals have been  !

computed using stack and vent X/Q values at the field station location, q Annual computed doses were reduced by the factor 40/168 to account for o the limited occupancy for workers at this location. Organ doses to I workers at the EPA ffold station due to gaseous releases have been i computed for the inhalation pathway (no other pathways esists). 00ses {

to workers at the EPA field station due to liquid releases are not }

espected to be higher than those computed for individuals beyond the L site boundary. 00$es at the EPA field ttation are reported in Table 1. l Doses to Most Exposed Meber of the General Pubite from

^

I Ve~actoe AileIWs EdiDth'er fieir'b)[liFaniuHuil' CycTe iources

[

There are no uranium fuel cycle facilities in the vicinity of the  !

Monticello site. I i

l MONT! 0FFSITE DOSE A$$ES$ LTR j i

I i

~2-The only other source of exposure to the general public in addition to

( the plant gaseous and liquid effluents is from direct radiation. Cal- >v culations performed in the past have shown this .ource to be negligible. An array of TLD monitoring locatinns at the site boundary l

has consistently indicated that plant operation in recent years has had l

no ef fect o'1 ambient gamma radiation.

t l

Therefore, the mist exposed member of the general public will not receive a radiation do*, from reactor releases and all other fuel cycle acti-l vities in *Acess of the sum of the liquid and gaseous whole body and l

organ doses reported in Table 1 for the site boundary and critical

receptor, respectively. These doses are well within the 40 CFR Part 190 l standards of 25 mrem to the whole body or any organ (except the thyroid)

! and 75 mrem to the thyroid every 12 months.

l 1

l l

l I

l l

l 1

MONT! 0FFSITE DOSE ASSES $ LTR l

L

TABLE 1 0FFSITE RA0!ATION DOSE ASSESSMENT - MONTICELLO PERIOD: JANUARY 1 THROUGH DECEMBER 31, 1985 10 CFR Part 50 Appendix !

Gaseous Releases Guideline Per Unit Per Year Maximum Site Boundary Gamma Air Oose (mrad) 0.687 10 Maximum Site Boundary Beta Air Dose (mrad)* 0.856 20 Maximum Offsite Oose to Any Organ (mrem)*

Total 96 15 EPA Field Station Oose (mrem)

Whole Body Q.031 5 Organ g.,06} 15 Qquid Releases (None Released in 1985)

Maximum Offsite Whole Body Dose (mrem) '

Total _0_ 3 Maximum Offsite Organ Dose (mrem)*

Total _0 _ 10

  • Long lived particulates, 1-131 & tritium.

i i

MONT! 0FFSITE DOSE ASSESS LTR l

TABLE 2 0FFSITE RADIATION DOSE ASSESSMENT SUPPLEMENTAL INFORAMTION - MONTICELLO PERIOD: JANUARY 1 THROUGH DECEMBER 31, 1985 Gaseous Effluents Maximum Site Boundary Dose Location (from building vents)

Sector SSE Distance (mi) 0.43 EPA Field Station Sector ESE Distance 0.31 Maximum Offsite Dose Location Sector ESE Distance (mi) 2.3 Pathways Ground, l

Inhalation, Milk i Age Group Infant l Organ Thyroid Liquid Releases Maximum Offsite '

Dose Location Downstream Pathways Ortnking Water Drinking Water, fish Age Group Infant Adult Organ Whole Body GI-LLI 1

l Oilution Factor 7.1 7.1 l (drinking water) l l

l BWC022186G0WO2 i

. . s. .

TRANSMITTAL MANIFEST NORTHERN STATES POWER COMPANY NUCLEAR GENERATION DEPARTMENT MONTICELLO NUCLEAR GENERATING PLANT Effluent and Waste Disposal Semi-Annual Report for July 1,1985 through December _J1,1985 Manifest Date: March 1, 1986 USNRC Regional Admin-III 1 General Electric 2 OCD 1 San Jose Cust. Serv Resident Inspector 1 San Jose-Fuel Proj Mgr NRR Project Manager 1 J N Sorenson (NUS) 1 R J Jensen 1 L R Eliason 1 Safety Audit Committee 9 G T Goering/G H Neils 1 0 M Musolf M B Sellman 1 K J Albrecht G Charnoff 1 M H Clarity 0 C Lower - 1 H S !sbin B W Clark 1 0 0 Lanning ERAD Dept. 1 i M Parker Attn: Records Clerk W A Shamla MOH 1 J A Thie Attn: Commissioner of Health F P Tierney MPCA 1 SAC File (Manifest Only)

Attn: J W Ferman Monticello Plant Manager 8 Prairie Island Plant 1 (E L Watz1)

Media Services Dept. 1 L H Waldinger 1 NSS Flie 1 NG File 1

!!Ag 3 ggr3 SF R-1 MANIFEST L

Retrieved from "https://kanterella.com/w/index.php?title=ML20137X935&oldid=2827739"