ML20071E559

Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1982

ML20071E559
Person / Time
Site:	Prairie Island
Issue date:	03/01/1983
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20071E548	List: ML20071E546 ML20071E559
References
NUDOCS 8303150280
Download: ML20071E559 (20)

Text

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PINGP #158, Rtv. 4

. i l

EFFLUENT AND WASTE DISPOSAL SDE-ANhTAL REPOPJ Tulv THROUGH December, 1982

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SUPPLDENTAL INFORMATION Facility - Prairie Island Nuclear Generating Plant Licensee - Northern States Power Companz License Nos. - DPR-42 & DPR-60

1. Regulatory Limits Action is required if the rate of release of radioactive caterials, when averaged over a three-cronth period, is such that these quantities, if continued at the sane release rate for a year, would exceed twice the design objectives. Design objectives are:

a.

Fission and activation gases (and all other radioactive isotopes except halogen and particulate isotopes with half-lives greater than 8 days) in gaseous releases:

Qi < 1300 m /see MPC f

b. Iodines and particulates with half-lives greater than 8 days in gaseous releases:

Qi <

_ 67 m /sec i 1 -

c. Liquid Effluents:

l. Annual total quantity of radioactive material in liquid waste, excluding tritium and dissolved gases, of 5 Ci per unit.

2.

Annual average concentration of radioactive caterial in liquid waste, prior to dilution in the Missisgppi River, excluding tritium and dissolved gases, of 2 X 10 pCi/ml.

3.

Annual average concentration of tritium in liqug waste, prior to dilution in the Mississippi River, of 5 X 10 pCi/ml.

2. Maximum Pernissible Concentrations a.

Fission and activation gases (and all other radioactive isotopes except halogen and particulate isotopes with half-lives greater than 8 days) in gaseous releases:

10 CFR 20, Appendix B, Table 2, Colucn 1 8303150280 830301 PDR ADOCK 05000282 R ,

PDR

PINGP 158 Rev. 4

. 2. Maximum Parmissible Concentrations b.

Iodine and particulates with half-lives greater than 8 days in gaseous releases:

10 CFR 20, Appendix B Table 2, Column 1 a

c. Liquid Effluents:

10 CFR 20, Appendix B Table 2, Column 2

3. Average Energy Not applicable to Prairie Island Regulatory Limits.

4. Measurements and Approximations of Total Radioactivity

a. Fission and activation gases Total Geli in gaseous releases: Nuclide Geli

b. Iodines in gaseous releases Total Geli Nuclide Geli

c. Particulates in gaseous Total Geli releases: Nuclide Geli

d. Liquid Effluents: '

Total Gross Eeta Gamma Nuclide Geli BATCH RELEASES

a. Liquid QTR 3 QTR 4 -

Number of Batch Releases 48 83 Total Time Period for a Batch Release (hr) 68.1 121 Maximum Time for a Batch Release (hr) 1.75 2.25 Average Time for a Batch Release (hr) 1.42 1.46 Minimum Time for a Batch Release (hr) 1.33 0.78 Ave Mississippi flow during Quarter (CFS) r' 12049 23932

b. Gaseous QIR 3 QTR 4 Number of Batch Releases 2 4 Total Time Period for Batch Releases (hr) 16.7 31.4 Maximum Time for a Batch Release (hr) 14.7 15.0 Average Time for a Batch Release (hr) 8.35 7.86 Minimum Time for a Batch Release (hr) 2.00 1.00

PINCP 158

. ABNORMAL RELEASES Ray. 4

a. Liquid QTR 3 QTR 4 Number of Releases 0 0 Total Activity Released (Ci) 0 0 Total Tritium Released (Ci) 0 0 .

b. Gaseous QTR 3 QTR 3 Number of Releases 1 0 Total Activity Releases (C1) 1.3E01 0 NA NA e G A

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9

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.g ,- , , , - - - - , . - - _ , - -

PINCP 158

. TABLE 1A Rev. 4 EFFLUENT AND k'ASTE DISPOSAL SEMI /5.iUAL REPORT CASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES -

UNIT QTR 1 QTR 1 E Jt R A. Fission and Activation Gases Total Release Ci 1.2pn? 2.1En2 Average Release Rate UCi/sec 1.sE01 7.7pn1

/ ,

B. Short Lived Particulate (+1/2 8 days)

, ~. .

Total Release '

_ . _ Ci 7.4E-07 0.OEGO Average Releare Rate -

1 LpCi/sec 1.0E-07 0.0?:00 C. Tritiun. , , e ~

Total Release Ci A.3E01 2.9E01 Average Release Rate pCi/sec 5.4E00 3.7E00

, ~1 Total A & B & C pCi/sde i 2.0E01 3.lE01

% of Design Objective Z 7.4E00 1.lE01 Iodines

^

D. -

Total 1131 Ci 2.2E-03 1.3E-03 Average Release Rate DCi/sec 2.8E-04 1.7E-04 E. Long Lived Particulates (+1/2 > 8 days)

Total Release Ci 1.3E-06 Average Release Rate 4.3E-05 pCi/sec __ l.7E-07 5.5E-06 s /

Total D & E pCi/sec '

2.8E-04 1.8E-04 3 of Design Objective  % h 1,3. 7_E00 2.4E00 F. Gross Alpha '

l Total Release lCi I'_ ~0.0E00 i Oa 0E00 l 1 W

s' or s i /

~ . - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ __.

l

' PINCP 158 TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT CASEOUS EFFLUENTS CONTINUOUS MODE BATCil MODE NUCLIDE UNIT QTR 3_ QTR i QTR .3__ QTR L

3. Fission and Activation Gases Kr65- Ci 2.8E-01 4.3E00 2.2E-01 7.6E-01 Kr85m Ci 2.9E-01 1.8E-01 Kr87 Ci 8.5E-02 7.4E-02 Kr88 Ci 2.3E-01 Xe133' Ci 1.2E02 2.0E02 8.3E-03 1.7E00 Xel35 Ci 9.9E-01 3.5E00 3.9E-07 2.5E-03 Xe135a Ci 3.1E-02 1.8E-02 Xe138' Ci '4.7E-02 Xe131m Ci 2.2E00 3.2E-03 5.6E-02 Ar41 Ci 1.2E-02 9.6E-03 1.2E-01 6.4E-01 Xe133m Ci 3.9E-01 1.3E00 1.1E-04 _

Total C1 1.2E02 2.lE02 2.3E-01 2.5E00

2. Iodines 1131 Ci 2.2E-03 1.3E-01 1133 Ci 2.9E-04 1.sE-06 1135 Ci Total Ci 2.5E-03 1.5E-01 CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QTR 1 QTR ,4__ QIR 3__ QIR ,4,

3. Particulates Sr89 Ci Sr90 Ci Cs134 Ci Cs137 Ci 3.lE-07 Ba-La140 Ci CoS8 Ci 1.3E-06 Co60 C1 Cd109 - Ci 4.3E-05 Sb124 Ci Na24 Ci C oS7 Ci Cel44 Ci Zr-Nb95 Ci Rb86 Ci

. - . . . . = . . .-. . - . . .. ..- - __. - . ._ ..

1

. , e

• i PINGP 158  ;

R2v. 4

TABLE IB EFFLUENT AND WASTE DISPOSAL SDilANWAL REPORT CASEOUS EFFLUEhTS

3. Particulates Sr85 Ci None Hn54 C1 Cal 38 Ci Y88 Ci 4

m b

PINGP 158 Rev. 4 TABLE 2A EFFLUENT AND WASTE DISPOAL SDf1Ah7UAL REPORT LIQUID EFFLUENTS - SU)D!ATION OF ALL RELEASES UNIT TO QTR 1 QTR 1 .

A. Fission and Activation Products Total Release W/011-3, Rad Gas, Alpha C1 1. 4 r-o r, 1.7E-03 Average Diluted Concentration pCi/ml 1.6E-12 2.8E-Il 2 of T. S. Annual Curie Design Objective .% 3.4E-03 1.7E-02 B. Tritium Total Release Ci 1.6E02 1.5E02 Average Diluted Concentration

• pCi/nl 7.6E-07 2.5E-06 3 of T. S. Annual Design Objective Conc *  % 15.2 50.0 C. Dissolved and Entrained Cases Total Release Ci 1.0E-01 2.2E-02 Average Diluted Concentration

• pCi/n1 4.8E-10 3.7E-10 D. Gross Alpha Total Release (Ci I 4.5E-08 l 2.0E-06 I E. Volume of Waste (Prior to Dilution) l liters l 5.6E07 1 3.2E07 l F. Volume of Dilution Water

• l liters l 2.lEll l 6.0E10 l

• Flow through Truttman's slough was terminated during this reporting period due to change in cire water discharge path. The volume of dilution water is calculated from cooling tower blowdown flow.

- =

PINGP 158 R2v. 4 TABLE 2A EFFLUENT AND WASTE DISPOSAL SDIIANhTAL REPORT LIQUID EFFLUENTS - SU)2!ATION OF ALL RELEASES Continuous Mode Batch Mode NUCLIDE UNIT QTR L QTR _4 QIR 1 QTR i Sr89 Ci S r90 Ci Cs134 Ct Cs137 Ci 1131 Ci 9.lE-07 4.8E-06 Co38 Ci- 9.9E-06 2.3E-04 1.0E-05 Co60 Ci 6.1E-06 7.9E-06 1.8E-05 Fe59 Ci Zn65 Ci tb54 C1 Cr51 Ci Z r-Nb95 Ci Mo99 Ci Ba-la140 Ci Ag110m Ci Na24 Ci W187 Ci Sb124 - Ci Sr85 Ci Cs136 Ci Z r-Nb9 7 Ci Cd109 Ci Rb88 Ci Total Ci 1.7E-05 0.0E00 2.4E-04 3.3E-05 Continuous Mode Batch Mode NUCLIDE UNIT QTR l QTR 4 QTR 1 QTR 4 Xe133 Ci 2.1E-03 6.5E-05 9.6E-02 2.2E-02 X=133m Ci 8.0E-04 Xo131m Ci 9.0E-04 1.4E-04 X2135 Ci 2.4E-04 3.7E-05 Kr85m Ci Kr85 Ci Kr88 Ci

I PINGP 158 Rsv. 4 TABLE 3 EFFLUENT AND WASTE DISPOSAL SDf1 ANNUAL REPORT j July through December 1982 Solid Waste and Irradiatted Fuel Shipments A. Solid waste shipped offsite 'for burial or disposal (not irradiated fuel)

1. Type of Waste Unit 6 !!onth l Est. Total Period Error %

a. Spent Resins ftJ Ci NONE

b. Dry compressible waste, contaninated ft3 645 + 15%

equipment, evaporator, bottoes, etc. Ci 33.94

c. Irradlated components, control rods, ft3 etc. Ci NONE

d. Other (describe) fh NONE

2. Estimate of major nuclide composition (by type of waste).

a. NONE  % l

% l f  %

b. Co38 1.0 % 10%

Co60 86 % 10%

Cs137 9.0 % 10%

Cs134 2.0 % 10%

Mn54 2.0 % 10%

c.  %

d.  %

3. Solid Waste Disposition Number of Shipments  !! ode of Transportation Destination 5 Truck U.S. Ecology, Richland, Washington B. Irradiated Fuel Shipments (disposition)

NONE

SOLID RADIOACTIVE WASTE SEMI-ANNUAL REPORT July 1982 through December 1982 l

.. .. . . . . . I Volume Curie Quantity Radionuclides Percent Container j (FT3) (measured) (measured) Abundance Type Quantity :

Cemented 577.5 31.541 a. C060 74 DOT 7A 77 Waste b. C058 24 Type A

c. CS137 1 55 gal

d. Mn54 0.4 Drum

e. SB124 0.3

f. C057 0.3 Compacted 67.5 2.396 a. C060 65 DOT 7A 9 Trash b. C058 20 Type A

c. CS134 5 55 gal

d. CS137 4 Drum

e. NB95 3

f. ZR95 3 Dewatered 0 0 a. None None 0 Resin b.

c.

d.

e.

f.

Non-com- 0 0 a. None None OI pacted b.

-Trash or c.

other: d.

e.

f.

Total Volume 645 FT3 Total Curie Content 33.937 1

\

• 4 Prairie Island Nuclear Generating Plant Change to Offsite Dose Calculation Manual (ODCM)

Table 5.1-1 Radiation Environmental Monitoring Program, Sampling Locations In accordance with the Prairie Island Technical Specifications Section 6.5 E Offsite Dose Calculation Manual (ODCM), a change to Table 5.1-1 Radiation Environmental Monitoring Program, Sampling Locations is sub-mitted.

One of three farms located in different sectors required by the sampling program is located 2.5 miles at 39*/NE from the facility. The owner of the farm has decided to discontinue the dairy portion of his farming operation in favor of a less confining beef cattle operation. We have collected raw milk from this farm since May 28, 1970. Beginning with the October 1982 collection date, we have begun collecting raw milk from a farm located 2.6 miles at 60* ENE from the facility. This is the closest dairy farm to the farm being discontinued, and Figure 5.1-1, map showing sampling locations does not require a change as the two above sites are within the circle identifying the sampling location.

Instructions for Entering Rev. 3 to the Prairie Island ODCM

1. Remove OIK21 cover page and pages v, vi, 5-1, and 5-2.

2. Replace ODCM cover page and pages v, vi, and 5-2 with Rev 3 pages. Replace page 5-1 with reprinted Rev 1 page (pages 5-1 and 5-2 are now printed on a single sheet).

3. Use ODCM page vi to page check you manual if desired.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)

REV. 3 DOCKET NO. 50-282 and 50-306 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA OPERATIONS 1 ITTEE F iAL RE7 EW DATE: 2 -/p .M REVIEWED Bl. 1 _ d/2#72/.# .DATE: c2 o2/-M APPROVED BY: . . / + - DATE: 1-2/-N

RECORD OF REVISIONS Revision No. Date -Reason for Revision Original June 7, 1979 -

1 April 15, 1980 Incorporation of NRC Staff comments and correction of miscellaneous errors 2 Aug 6, 1982 Incorporation of NRC Sta !f connents 3 Feb 21, 1983 Change in milk sampling location 4

o v Rev. 3

LIST OF EFFEClIVE PAGES Psee No. Revision No. Pare No. Revision No.

Cover 3 3-11 2 1 2 3-12 0 ti 1 3-13 2 111 0 3-14 2 iv 0 3-15 2 v 3 3-16 2 vi 3 3-17 0 1-1 1 3-18 1 2-1 2 3-19 0 2-2 2 3-20 2 2-3 2 3-21 2 2-4 1 3-22 2 2-5 1 3-23 2 2-6 1 3-24 2 2-7 2 3-25 2 2-7a 2 3-26 2 2-8 2 3-27 2 2-9 0 3-28 2 2-10 2 3-29 2 2-11 2 3-30 2 2-12 2 3-31 2 2-13 1 3-32 2 2-14 2 3-33 2 -

2- 13 2 3-34 2 3-1 2 3-35 2 3-2 1 3-36 2 3-3 1 3-37 2 3-4 2 3-38 2 3-5 2 4-1 1 3-6 1 4-2 0 3-7 1 4-3 0 3-8 2 5-1 1 3-9 2 5-2 3 3-10 2 5-3 2 i

5-4 1 5-5 1 5-6 2 5-7 2 5-8 1 A-1 thru O A-39 B-1 thru O B-8 C-1 thru 2 C-14 v1 Rev. 3

5.0 RADIATION ENVIRONMENTAL MONITORING PROGR AM 5.1 Sameline Table 5.1-1 and Figures 3.1 1 5.1-2, and 5.1-3 specify the current sampling locations based on the latest land use census.

If it is learned from an annual census that milk animals or gardens are present at a location which yields a calculated thyroid dose greater than those previously

. sampled, the new milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program as soon as practicable. Sample locations (except the control) having lower calculated doses may be dropped from the program at the end of the grazing or growing season (October 31) to keep the total numoer of sample locations constant.

5.2 Inter!aboratorv Comearison Prerram Analyses shall be performed on radioactive samples supplied by the EPA crosscheck program. This program involves the analyses of samples provided by a control laboratory and comparison of results with those of the controllaboratory as well as

' with other laboratories which receive portions of the same samples. Media used in thIs program (air, milk, water, etc.) shall be limitec to tho.=e found in the radiation environmental monitoring program. The'results of analyses performed as a part of -

the crosscheck program shall be included in the Annual Radiacion Environmental Monitoring Rep' ort.

I 1

i I

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5-1 Rev.t

TABLE 3.1-1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS ,

Typ of Same!e Code Collection Site Loestien River Water P-3* Upstream of Plant River Water P-6 0.6 ini @ 60*/ENE Lock & Dam #3 Drinking Water 1.6 mi @ 12**/55 P-Il City of Red Wing

' Wen Water e 7.1 mi @ 135*/55 P-23 Kinneman Farm Wen Water 11.1 mi @ 331*/NN%

P-6 Lock & Dam #3 Well Water 1.6 mi @ 129*/SE P-8 Kinney Store Well Water 2.0 mi @ 280*/W P-9 Plant Well #2 0.3 mi @ 306*/NW Sediment-River P-3 C Upstream of Plant 5ediment-River P-6 0.6 mi @ 60*/ENE Lock & Dam #3 Sediment-Shoreline 1.6 mi @ 129*/5E P-12 Recreation Area Periphyton or P-5 c 3.4 mi @ !!6*/ESE

. Upstream of Plant Macroinvertebrates P-6 Lock & Dam f/3 0.6 mi @ 60*lENE

. Fish 1.6 mi @ 129'/SE P-5* Upstream of Plant Fish 0.6 mi @ 6C /ENE P-6 Lock & Dam #3 Milk C 1.6 mi @ 129 /SE P-25 Kinneman Farm MUk 11.1 mi @ 331 /NNW P-14 Gustafson Farm Milk 2.2 mi @ 161*/SSE P-16 Johnson Farm - '

Milk P-17 2.6 mi @ 60 /ENE Place Farm Milk 3.3 mi @ 25 /NNE P-11 Birk Farm 3.3 mi @ 131*/;

5-2 R*v 3

Northern States Power Company Prairie Island Nuclear Generating Plant Offsite Radiation Dose Assessment for January 1 - December 31, 1982 An assessment of radiation dose due to releases from the Prairie Island l Nuclear Generating Plant during 1982 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.

NRC Computer programs GASPAR and LADTAP were used in conjunction with metero-rological parameters from the Offsite Dose Calculation Manual in making this assessment. Source terms were obtained from the two Effluent and Waste Disposal Semiannual Reports prepared for NRC review during the year.

Offsite Doses from Gaseous Releases Computed doses due to gaseous releases are reported in Table 1. Critical receptor location and pathways for organ dose are reported in Table 2. Doses, both whole body and organ, are a small percentage of Appendix I guidelines.

Offsite Doses from Liquid Releases 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 guidelines.

Doses to Individuals Due to Activities Inside the Site Boundary Occasional sportmen will 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 the area.

For purposes of estimating dose due to recreational and river transportation

' 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 and inhalation organ doses were calculated for this location and occupancy time. These doses are reported in Table 1.

i Doses to Most Exposed Member of the General Public from Reactor Releases and l Other Nearby Uranium Fuel Cycle Sources There are no uranium fuel cycle facilities in the vicinity of the Prairie Island site.

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.

l j '

1 I

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.

1

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TABLE 1 0FFSITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD: JANUARY 1 THROUGH DECEMBER 31, 1982 10 CFR Part 50 Appendix I Gaseous Releases Guideline per year Maximum Site Boundary 0.23~ 20 Gamma Air Dose (mrad)

Maximum Site Boundary 0.58 40 Beta Air Dose (mrad)

Maximum Offsite Dose to Any Organ *

(mrem)

Total 0.34 30 H-3 Dost 0.25 -

Offshore Location (mrem, 7 days / year)

Whole Body 0.02 10 Organ 0.01 30 Liquid Releases -

Maximum Offsite Whole Body Dose (mrem)

Total 0.00113 6 H-3 Dose 0.00112 -

Maximum Offsite Organ Dose (mrem)*

Total 0.00114 20 H-3 Dose 0.00113 -

• Long lived particulates, I-131, and tritium.

TABLE 2 GTFSITE RADIATION DOSE ASSESSMENT SUPPLEMENTAL INFORMATION - PRAIRIE ISLAND PERIOD: JANUARY I THROUGH DECEMBER 31, 1982 Gaseous Effluents 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 Dose Location Sector WNW Distance (mi) 0.7 Pathways Ground, inhalation, vegetables Age Group Child Organ Thyroid Liquid Effluents Maximum Offsite Dose Location Downstream Pathways Fish Age Group Adult Organ Thyroid L