ML20012A031

Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1989

ML20012A031
Person / Time
Site:	Monticello
Issue date:	12/31/1989
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20012A032	List: ML20012A031 ML20012A180 ML20012A183
References
NUDOCS 9003080161
Download: ML20012A031 (14)

Text

- _ _ _. _ _ _ _ _ _

. TRANSMITTAL MANIFEST NORTHERN STATES POWER COMPANY NUCLEAR GENERATION DEPARTMENT-00NTICELLO NUCLEAR GENERATING PLANT Effluent and Waste Disposal Semiannual Report for July 1.1989 throuah December 31. 1989

. Manifest Date:' February 26, 1990 USNRC.

4 ANI Library

'l Regional Admin-III General Electric 2

NRR Project Manager.

San Jose Cust. Serv.

DCD San Jose Fuel Prof. Mgr.

Resident inspector NUS 1

S D Weerakkody L R Eliason 1

Shaw Pittman Potts &

S D Northard 1

Trowbridge 1

l P H Kamman 1

G Charnoff Monticello Plant Manager 8

Prairie Island Plant Manager 1 ERAD Dept.

1 Attn: Records Clerk Safety Audit Committee 10 Media Services Dept.

1 G H Neils.

NRS File 1

K J Albrecht'

.NSS File 1

R L Hannen MDH 1

H^S Isbin Attn: Comissioner of Health D D Lanning MPCA 1

T M Parker Attn: J W Ferman' D D Antony i

J A Thie 1

D E Gilberts Secretary File (Manifest only) 1 i

90030B0161 900228 DR ADOCK 0500 3

w 4:

p NO2THERN: STATES PONE 3 CINPANY-

f ',,9 NONTICELLO NUCLEAR' GENERATING PLANT-License No. DPR-22 1

i EFFLUENT AND' WASTE. DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1989' g

Supplemental.Information

1. R0gulatory! Limits'--Quarterly levels requiring-reporting to Nuclear Regulatory Commission s

AS. Noble'G'ases :'

s 5 mrad / quarter gamma radiation 10~ mrad / quarter beta radiation lB.;Long Lived Iodines,;Particulates,'and Tritium :

4 7.5'arem/ quarter dose to any organ j

i (C. Liquid Effluents :=

~1.5 mrem / quarter dose'to the total body D

4

[

-5.0 mrem / quarter done=to any organ o

L 2.fMDximum-Permissible Concentrations-2 A. Noble Gases :.

10 CFRrPartc20, Appendix B,LTable II,. Column 1 B.,Long Livedflodines, Particulates, and Tritium :.

i; 10 CFR Part=20,; Appendix B, Table II, Column 1-

{

~C.

Liquid' Effluents's 10'CFR=Part 20, Appendix B, Table II,' Column'2' 2.01E-47uci/ml for. dissolved and entrained. gases L 3.f Average: Energy' d

L(Not Appl'icable) 1 o!'

t i

L i

a.

4

'li

'E

Page 2

EFFLUENT AND WASTE DISPOSAL-SEMIANNUAL REPORT Period : Jul'- Dec 1989 Supplemental Information (continued) 4.-Measurements and Approximations of Total Radioactivty A. Noble Gases :

Continuous gross activity monitors in Reactor Building Vent and Plant Stack exhaust streams.

Weekly isotopic analysis of exhaust streams.

Monthly analysis of storage tank contents.

B.

Iodines in Gaseous Effluent :

Continuous monitoring with charcoal cartridges in Reactor Building vent and Plant Stack exhaust streams with weekly analysis.

C. Paritculates in Gaseous Effluent :

Continuous monitoring with particulate filters in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.

D.

Tritium-in Gaseous Effluent :

Continous monitoring with silica gel cartridges in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.

E.

Liquid Effluents :

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

-5.l Batch Releases A.

Liquid :-

1. Number of Batch Releases 0

2.. Total Time Period for Batch Releases NA 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.-Average River Flow During Release NA cf/sec B.

Gaseous :

'l. Number of Batch Releases 3

2. Total Time Period for Batch Releases 2821.0 min

3. Maximum Time Period for a Batch Release 2160.0 min

4. Average Time Period for a Batch Release 940.3 min

'5. Minimum Time Period for a Batch Release 136.0 min 1

i

-.s

PQg3;: '3' A

EFFLUENT AND MASTE-DISPOSAL SEMIANNUAL REPORT Period = ~Jul --Dec 1989 4

-Suppl'emental Information (continued) 6.JAbnormal-Releases-A.-Liquid i 1-.-Number'of Releases 0

'2.

Total Activity Released NA Ci

.B.-Gaseous :

1.-Number-of Releases 0

2. Total-Activity Released 0.0 Ci Y

1 l

o

.A-.n-

.~--

_ - - _ - - - - - w

PQge_ 4 =-

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period-t Jul - Dec 1989 Table 1A - Gaseous Ef fluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error, %

A.

rission & Activation gases 1.

Total Release Ci 6.85E+02 5.74E+02 5.00E+01 l 2.

Average Release Rate uci/sec 8.61E+01 7.23E+01 3.

Percent Tech Spec Qtrly Reporting Level Gamma Radiation 4.09E+00 7.92E-01 Beta Radiation 2.45E+00 4.25E-01 B.

Iodines 1.

Total I-131 Release Ci 2.54E-02 2.95E-03 5.00E+01 l

2. Average I-131 Release Rate uci/sec 3.20E-03 3.71E-04 C.-Particulates 1.-Total Particulates Ci 1.03E-02 8.97E-04 5.00E+01 l

2. Average Release Rate uci/sec 1.30E-03 1.13E-04 3.

Gross Alpha Radioactivity Ci 2.89E-05 1.54E-05 D. Tritium 1.

Total Release Ci 2.67E+01 1.21E+01 1 5.00f+UT~l

2. Average Release Rato uci/sec 3.36E+00 1.52E+00 j E.

Percent Qtrly Tech Spec Reporting Levels

1. ~

.l.

Iodines, Particulates, and Tritium 4.74E+00 5.26E-01

Pago 5

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1989 Table 1B Gaseous Effluents - Elevated Releases l

l l

Continuous Mode l

Batch Mode l

l Nuclides Released l Unit l 3rd Otr l 4th Otr i 3rd Otr l 4th Otr l

1.

Fission Gases KR-85 Ci 1.46E+01 1.50E+01 0.00E+00 0.00E+00 KR-85M Ci 8.92E-01 1.48E+00 0.00E+00 0.00E+00 KR-87 Ci 4.33E+00 9.17E+00 0.00E+00 0.00E+00 KR-88 Ci 3.05E+00 4.28E+00 0.00E+00 0.00E+00 KR-89 Ci 8.34E+01 1.32E-02 0.00E+00 0.00E+00 KR-90 Ci 2.83E+00 4.402 04 0.00E+00 0.00E+00 XE-131M Ci 8.48E-01 6. ~ T E'- 0 2 0.00E+00 0.00E+00 XE-133 Ci 2.llE+02 3.78E+01 0.00E+00 0.00E+00 XE-133M Ci 1.55E+00 8.96E-01 0.00E+00 0.00E+00 XE-135 Ci 4.65E+00 3.58E+01 0.00E+00 0.00E+00 XE-135M Ci 6.43E+00 4.13E+01 0.00E+00 0.00E+00 XE-137 Ci 1.09E+02 1.76E+02 0.00E+00 0.00E+00 XE-138 Ci 8.68E+01 1.18E+02 0.00E+00 0.00E+00 XE-139 Ci 8.41E+00 1.33E-03 0.00E+00 0.00E+00 l

Total for Period Ci 5.38E+02 4.40E+02 0.00E+00 0.00E+00 l 2.

Iodines 1

1-131 Ci 6.09E-03 1.49E-03 0.00E+00 0.00E+00 I-133 Ci 1.10E-02 5.85E-03 0.00E+00 0.00E+00 I-135 Ci 8.09E-03 6.77E-03 0.00E+00 0.00E+00 I

Total for Period Ci 2.52E-02 1.41E-02 0.00E+00 0.00E+00 l 3.

Particulates CR-51 Ci 0.00E+00 7.96E-07 0.00E+00 0.00r+00 l MN-54 Ci 5.47E-06 8.70E-06 0.00E+00 0.00E+00 CO-58 Ci 1.39E-06 5.72E-07 0.00E+00 0.00E+00 FE-59 Ci 0.00E+00 1.10E-06 0.00E+00 0.00E+00 CO-60 Ci 3.78E-05 2.58E-05 0.00E+00 0.00E+00 i

ZN-65 Ci 2.74E-06 1.87E-06 0.00E+00 0.00E+00 CS-134 Ci 1.08E-06 4.03E-07 0.00E+00 0.00E+00 CS-137 Ci 3.02E-05 1.27E-05 0.00E+00 0.00E+00 BA-140 Ci 2.70E-04 3.94E-04 0.00E+00 0.00E+00 CE-141 Ci 9.30E-07 1.81E-07 0.00E+00 0.00E+00 CE-144 Ci 0.00E+00 3.56E-07 0.00E+00 0.00E+00 l SR-89 Ci 3.57E-04 0.00E+00 0.00E+00 0.00E+00 l SR-90 Ci 3.40E-06 0.00E+00 0.00E+00 0.00E+00 l l

Total for Period Ci 7.10E-04 4.46E-04 0.00E+00 0.00E+00 l Analysis of Sr-89 & 90 for the 4th Qtr was not completed in time for this report, results will be included with the next semiannual report.

P0ge 6

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I

Period : Jul - Dec 1989 Table 1C Gaseous Effluents - Building Vent Releases i

Continuous Mode Batch Mode Nuclides Released Unit 3rd Qtr i 4th Otr 3rd Otr l 4th Otr t

1. rission Gases KR-85 Ci 5.5BE-03 4.52E+01 0.00E+00 0.00E+00 KR-85M Ci 4.23E-01 3.61E-03 0.00E+00 0.00E+00 KR-87 Ci 2.07E+00 1.79E-02 0.00E+00 0.00E+00 FR-88 Ci 1.44E+00 l'.22E-02 0.00E+00 0.00E+00 KR-89 Ci 3.94E+01 3.34E-01 0.00E+00 0.00E+00 KR-90 Ci 1.33E+00 1.13E-02 0.00E+00 0.00E+00 XE-131M Ci 5.64E-04 1.65E-01 0.00E+00 0.00E+00 XE-133 Ci 2.53E-01 1.49E+01 3.85E-01 0.00E+00~

~ ~ ~

lE-133M C1 1.01E-02 8.71E-05 0.00E+00 0.00E+00 13:373' Ci 2.00E+00 2.84E+01 2.38E-01 6.31E-04 XE-135M Ci 3.04E+00 4.42E+01 0.00E+00 0.00E+00 XE-137 Ci 5.15E+01 4.39E-01 0.00E+00 0.00E+00 XE-138 Ci 4.0BE+01 3.46E-01 0.00E+00 0.00E+00

[~,

XE-139 Ci 3.97E+00 3.37E-02 0.00E+00 0.00E+00 1

Total for Period Ci 1.46E+02 1.34E+02 6.23E-01 6.31E-04 20 Iodines 1-131 1

Ci 1.93E-02 1.45E-03 1.30E-05 0.00E+00 I-133 Ci 2.90E-02 1.26E-02 0.00E+00 0.00E+00 I-135 Ci 3.27E-02 1.44E-02 0.00E+00 0.00E+00 Total for Furiod Ci 8.10E-02 2.85E-02 1.30E-05 0.00E+00 l

3. Particulates l

l CR-51 Ci i

9.52E-04 0.00E+00 0.00E+00 0.00E+00 MN-54 Ci 7.04E-05 1.99E-05 0.00E+00 0.00E+00 CO-58 Ci 8.75E-05 0.00E+00 0.00E+00 0.00E+00 C6~B0 Ci 1.63E-03 2.42E-04 0.00E+00 0.00E+00

~~~fR ~6b~

Ci 6.42E-03 1.47E-05 0.00E+00 0.00E+00

~"'~~hU-103 C1 2.61E-05 0.00E+00 0.00E+00 0.00E+00

~~

CS-134 Ci 0.00E+00 2.96E-06 0.00E+00 0.00E+00

• ES-137 Ci 5.48E-05 7.54E-05 0.00E+00 0.00E+00 BA-140 Ci 2.87E-04 9.17E-05 0.00E+00 0.00E+00

~'

i CE-143 Ci 2.06E-06 3.94E-06 0.00E+00 0.00E+00 SR-89 Ci 5.11E-05 0.00E+00 0.00E+00 0.00E+00 SR-90 Ci 9 1.91E-06 0.00E+00 0.00E+00 0.00E+00 Total for Period Ci 9.58E-03 4.50E-04 0.00E+00 0.00E+00 Analysis of Sr-89 & 90 for the 4th Otr was not completed in time for this report, results will be included with the next semiannual report.

P;ge 7

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT t

c Period : Jul - Dec 1989 i

Table 2A Liquid Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error, %

A. Fission & Activation products 1.

Total Release (not including tritium, gases, alpha)

Ci 0.00E+00 0.00E+00 0.00E+00

2. Avg Diluted Concentration uci/ml 0.00E+00 0.00E+00 B. Tritium 1.

Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l

2. Avg Diluted Concentration uci/ml 0.00E+00 0.00E+00 C. Dissolved and Entrained Gases

~

1.

Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l

2. Avg Diluted Concentration uci/ml 0.00E+00 0.00E+00 D. Percent Qtrly Tech Spec Reporting Level

1. Whole Body Dose 0.00E+00 0.00E+00 2.

Organ Dose 0.00E+00 0.00'l+00 E. Gross Alpha Radioactivity l_

l.

Total Release l

Ci l 0.00E+00 l 0.00E+00 l 0.00E+00 l

-lF. Volume of Waste Released l

Liters l 0.00E+00 l 0.00E+00 1 0.00E+00 l jr. Volume of Dilution Water Used l Liters l 0.00E+00 l 0.00E+00 l 0.00E+00 l Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 3rd Qtr i 4th Qtr 3rd Qtr 1 4th Qtr None Released This Period

Pag]

8

+

+

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1989 Table 3 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel) 1.

Type of Waste Units 6-month Est. Total Period Error, %

a. Spent resins, filter sludgest Cu. Meter 2.57E+01 evaporator bottoms, etc.

Ci 3.52E+02 5.00E+01 b.

Dry compressible waste, Cu. Meter 1.6BE+02 contaminated equipment, etc.

Ci 6.13E+00 5.00E+01

c. Irradiated components, Cu. Meter 0.00E+00 control rods, etc.

Ci 0.00E+00 5.00E+01

d. Other (describe)

Cu. Meter 0.00E+00 Ci 0.00E+00 5.00E+01 2.

Estimate of major nuclide Nuclide Percent composition (by type of waste)

A Mn-54 5.14E+00 Fe-55 2.55E+01 Co-58 1.14E+00 Fe-59 2.91E-01 Co-60 5.54E+01 Zn-65 5.75E+00 Sr-89 4.03E-01 Sr-90 1.67E-01 Zr-95 2.45E-02 Ru-103 1.23E-01 2-131 8.35E-02 Cs-134 9.12E-01 Cs-137 3.07E+00 Ba-140 8.87E-02 Ce-141 1.34E-01 B

Cr-51 2.58E+00 Mn-54 1.12E+01 Fe-55 3.07E+01 Co-58 5.72E-01 Fe-59 7.76E-01 Co-60 3.19E+01 Zn-65 3.15E+00 St-89 1.02E+00 Sr-90 3.47E-01 Cs-134 1.43E+00 Cs-137 4.75E+00 Ba-140 4.47E-01 l

La-140 4.37E-01 l

L P^g) 9 s.

4 i

CrFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1.-

F Period : Jul - Dec 1989 t

Table 3 Solid Waste and Irradiated ruel Shipments i

3. Solid' waste disposal i

Number of Mode of Destination i

Shipments Transportation 3

Truck Chen-Nuc Inc., Barnwell, SC.

3 Railway Chem-Nuc Inc., Barnwell, SC.

1 7

Truck US Ecology, Richland, WA.

I B.

Irradiated ruel Shipments L

1.= Disposition Nu ber of Mode of Destination Shipments Transportation i

None This Period j

L 1

C. Shipping Container and Solidification Method i

No..

Volume Activity Type of Container Solidification M3 Ci Waste Code Code 89-24 5.83E+00 2.29E+01 A

A D

I 89-26 3.41E+00

.1.33E+02' A

A D

89-34 3.81E+01 1.14E+00 B

L N

40 3.55E+00 7.32E+01 A

A C

89-47 3.55E+00 2.23E+01 A

A C

89-57 1.70E+01 5.85E-01 B

L N

89-61 1.70E+01 7.79E-01 B

L N

89-52 3.55E+00-8.71E+00 A

A C

89-74 1.70E+01 5.60E-01 B

L N

89-89' 1.70E+01 6.05E-01 B

L N

I 89-91 3.79E+01 1.84E+00 B

L N

i 92 5.83E+00 9.11E+01 A

A D

i 89-99 2.40E+01 6.24E-01 B

L N

f l 'Ccntoiner Codes :

Solidification Codes :

L --LSA C - Cement A - Type A U - Urea Formaldehyde l

B - Type B D - Dewatering Q - Large Quantity N - Not Applica1ble-1 i

6 t

• m

J a

l j

3 NORTMERN STATES POWER CONPANY l

RQEtICELLO NUCLEAR GENERATING PLhMT OFF-82TE RADIATION DOSE ASSESSMENT FOR January 1-Dec==her 31, 1989 i

An assessment of radiation dose due to release from the Monticello Nuclear Generating Plant during 1989 was performed in accordance l

with the Technical Specifications. Computed doses were well below

.the 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidelines.

I Off-site dose calculation formulas and meteorological data from the Off-site Dose Calculation Manual were used in making this i

assessment. Source terms were obtained from the two Effluent and Waste Disposal Semiannual Reports prepared for NRC review during the year of 1989.

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.

1 Off-site Domes from Lieuid Release There were no liquid releases made from the Monticello Plant during the 1989 calendar year.

Doses to Individuals Due to Activities Inside the Site Boundarv occasionally sportsmen enter the Monticello site for recreational activities, in addition, an Environmental Protection Agency Field Station is located at the Monticello site (see Figure 3.8.1 and Figure 3.8.2 of Monticello Technical Specifications). Workers at this 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 for the Field Station location. Annual computed doses were reduced by the factor of 40/168 to account for the limited occupancy for workers at this location. Organ doses to workers at the EPA Field Station due to i

gaseous releases have been computed for inhalation pathway (no l

other pathway exists). Doses at this location were reported in l

Table 1.

I l-l 1:

o

[

Doses to Most evnosed Maker of the General Public from Reactor Releases and Other Uranium Puel Cycle Sources There are no other uranium fuel facilities in the vicinity of the Monticello site. The only other artificial source of exposure to i

the general public in addition to the plant effluent releases is from direct radiation of the reactor. Calculations performed in the past have shown this source to be negligible. An array of TLD monitoring stations around the perimeter of the site boundary has consistently indicated that plant operation in the 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, 75 mrem to the thyroid, and 25 mrem to any other organ.

4 l

IL I

loi i

L[,, o TABLE 1 j

h OFF-SITE RADIATION DOSE A&3ESSMENT - MONTICELLO PERIOD: JhMUARY 1 through DECEMEER 31. 1989 10 CFR Part:50 Appendix I Guidelines per unit per year Gaseous Releases I

~ Maximum Site Boundary Gamma Air Dose (mrad) 0.103 10 I

Maximum Site Boundary a

Beta Air Dose (mrad) 0.123 20 l

t Maximum Off-site Dose to Any Organ (mrem)*

i o

Total 0.786 15 EPA Field Station (mrem, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> / week)

Whole Body 0.20 5

Organ ~

0.28 15 l

l Liquid Releases l

Maximum Off-site Dose Whole Body (mrem) 0.0 3

Maximum'off-site Dose Organ, Total 0.0 10 V'

t L

l

• Long-lived Particulates, I-131, and H-3 1-L l

l l

I f

f I

---w

~,--,e

l t

o.

t o.i l

l TABLE 2

}

h 0FF-SITE RADIATION DOSE ASSESSMENT - NONTICILLO SUPPLEMENTAL INFORMATION j

PERIOD JANUhRY 1 through DECEMEER 31,.1989 l

easeous Releases h

Maximum Site Boundary l

Dose Location E

-(from building vents) i i

Sector SSE i

Distance (miles) 0.43

{

EPA Field Station i

Sector ESE Distance (miles) 0.31 Maximum Off-site 1

Dose Location Sector ESE Distance (miles) 2.6

(

Pathways Ground,'

Inhalation, Cow Milk Age _ Group Infant organ Thyroid t

Lieuld Releases Maximum Off-site Dose l

Location Downstream Pathways Drinking Water Drinking Water Fish Age Group Infant Adult Organ Whole Body GI-LLI Dilution Factor 7.1 7.1 (drinking water) i

-e

-,.w~__

.m