ML20246P061

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Revised, Effluent & Waste Disposal Semiannual Rept for First Half 1988
ML20246P061
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 06/30/1988
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20246K241 List:
References
NUDOCS 8909110032
Download: ML20246P061 (14)
v • d • e


Text

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o AMENDMENT to the PRAIRIE ISLAND Effluent and Waste Disposal-Senfannual Report (for the 1st Half year of 1988)

Thisireport is being resubmitted to address discrepancies between the report filed to update the composite results and the report submitted to correct the airborne tritium -

problem detected in'1988.

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19.881Effluentjsemiannual Report- ~REV.l3 ,

-_ _iPtgaHl:of 8' Retention

  • Lifetime EFFLUENT SEMIANNUAL REPORT.

01-JAN-88 THROUGH 30-JUN-88 SUPPLEMENTAL INFORMATION Facility: Prairie _ Island Nuclear Generating' Plant-Licensee: Northern States Power Company License Numbers:-DPR-42 & DPR-60 A. Regulstory Limits

1. Liquid Effluents:

a '. 'The dose or dose commitment to an' individual from radioactive-

-materialstin liquid effluents released from the site shall be limited.to:.

for the quarter 3.0 mrem to the total body 10.0 mrem'to any organ-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 L gaseous effluents from the site shall be limited to:

noble gases 4500 mrem / year total body (3000 mrem / year skin l

I-131, H-3, LLP 41500 mrem / year to any organ

b. The dose due to radioactive gaseous effluents shall be limited'to:

noble' gases 410 mrad / quarter gamma 420 mrad / quarter beta (20 mrad / year gamma 440 mrad / year beta l' I-131, H-3, LLP (15 mrad / quarter 1 430 mrad / year j

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,f 1988 EFFLUENT 3EMIANNUALLREPORT- REV. 3 PAGE 2

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<S B. Maximum Permissible Concentration-11 . Fission and activation;. gases.in gaseous releases:

10 CFR 20,: Appendix B, Table 2, Column l-2.- Iodine.and' particulate with~ halflives greater than-OLdays in gaseous releases:

10 CFR 20, Appendix B,. Table 2, Column'1 E3 . . 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-applicablesto Prairie Island regulatory limits.

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D. Measurements and approximations of total activity

1. Fission'and activation gases Total GeLi 25%

in gaseous-releases: Nuclide GeLi

2. -Iodines in gaseous releases: . Total GeLi 25%

Nuclide GeLi 3.- Particulate in gaseous releases: Total GeLi 125%

Nuclide GeLi

4. . Liquid effluents Total GeLi 125%

Nuclide GeLi l

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-1988 EFFLUENT SEMIANNUAL REPORT REV. 3 PAGE 3 1.0 BATCH RELEASES (LIQUID) QTR: 01 QTR: 02 1.1 NUMBER OF BATCH RELEASES 5.50E+01 2.80E+01 1.2 TOTAL TIME PERIOD (HRS) 8.60E+01 4.58E+01 1.3 MAXIMUM TIME PERIOD (HRS) 1.90E+00 2.30E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.56E+00 1.64E+00 1.5 MINIMUM TIME PERIOD (HRS) 1.00E+00 1.30E+00 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 1.01E+04 1.32E+04 2.0 BATCH RELEASES (GASEOUS) QTR: 01 QTR: 02 2.1 NUMBER OF BATCH RELEASES 1.60E+01 1.00E+00 2.2 TOTAL TIME PERIOD (HRS) 1.27E+02 2.90E+00 2.3 MAXIMUM TIME PERIOD (HRS) 3.27E+01 2.90E+00 2.4 AVERAGE TIME PERIOD (HRS) 7.92E+00 2.90E400 2.5 MINIMUM TIME PERIOD (HRS) 3.00E-02 2.90E+00 3.0 ABNORMAL RELEASES (LIQUID) QTR: 01 QTR: 02 3.1 NUMBER OF BATCH RELEASES 0.00E+00 0.00E+00 3.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 3.3 TOTAL TRITIUM RELEASED (CI) 0.00E+00 0.00E+00 4.0 ABNORMAL RELEASES (GASEOUS) QTR: 01 QTR: 02 4.1 NUMBER OF BATCH RELEASES 0.00E+00 0.00E+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00

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1988 EFFLUENT SEMIANNUAL REPORT REV. 3 PAGE 4

! TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 6.60E-02 3.75E-02 5.2 AVERAGE RELEASE RATE (UCI/SEC) 8.40E-03 4.77E-03 5.3 GAMMA DOSE (MRAD) 2.86E-05 4.21E-06 5.4 BETA DOSE (MRAD) 4.86E-04 3.01E-04 5.5 PERCENT OF GAMMA TECH SPEC (%) 2.86E-04 4.21E-05 5.6 PERCENT OF BETA TECH SPEC ( % ) 2.43E-03 1.51E-03 6.0 IODINES 6.1 TOTAL I-131 (CI) 0.00E+00 6.49E-07 6.2 AVERAGE RELEASE RATE (UCI/SEC) 0.00E+00 8.26E-08 7.0 PARTICULATE 7.1 TOTAL RELEASE (CI) 9.25E-07 2.78E-07 7.7 AVERAGE RELEASE RATE (UCI/SEC) 1.18E-07 3.54E-08 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 3.53E+01 3.29E+01 8.2 AVERAGE RELEASE RATE (UCI/SEC) 4.48E+00 4.19E+00 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 4.48E+00 4.19E+00 10.0 DOSE (MREM) 6.36E-02 5.93E-02 11.0 PERCENT OF TECH SPEC (%) 4.24E-01 3.59E-01 12.0 GROSS ALPHA (CI) 5.02E-07 3.44E-07

1988" EFFLUENT SEMIANNUAL REPORT REV.'3 PAGE 5

'- TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 13.0 FISSION AND ACTIVATION GASES CONTINUOUS MODE . BATCH MODE NUCLIDE UN I'.?S QTR: 01 QTR: 02 QTR: 01 QTR: 02

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KR-85 CI 5.14E-02 3.64E-02 XE-133 CI 1.41E-02 1.08E-03 XE-135 CI 5.12E TOTAL CI 0.00E+00 0.00E+00 6.60E-02 3.75E-02 14.0 IODINES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS OTR: 01 QTR: 02 QTR: 01 QTR: 02 1-131 CI 6.49E-07 I-133 CI 2.00E-05

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TOTAL CI 0.00E+00 2.06E-05 0.00E+00 0.00E,00 15.0 PARTICULATE CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 CO-60 CI 6.86E-07 CS-137 CI 2.78E-07 2.08E-07 l

SR-90 CI 3.07E-08 TOTAL CI 7.17E-07 2.78E-07 2.08E-07 0.00E+00 I

'1988' EFFLUENT SEMIANN AL REPORT REV. 3' PAGE 6 i-TABLE 2A-LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 7.58E+07 3.36E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 1.08E+11 7.97E+10 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 1.26E-02 5.54E-03 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.17E-10 6.95E-11 19.0 TRITIUM 19.1 TOTAL RELEASE (CI) 1.60E+02 6.14E+01 19.2' AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.48E-06 '7.70E-07 20.0 DISSOLVED AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI) 1.75E-03l1.94E-03 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.62E-11 2.44E-11 1988 EFFLUENT SEMIANNUAL REPORT REV. 3 PAGE 7 21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 1.48E-06 7.70E-07 23.0 TOTAL BODY DOSE (MREM) 4.13E-04 2.09E-04 24.0 CRITICAL ORGAN 2G.1 DOSE (MREM) 3.15E-03 2.09E-04 2 4 . .' ORGAN GI-LLI TTL BODY PS.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%) 1.37E-02 6.97E-03 26.0 PERCENT OF CRITICAL ODGAN TECH SPEC LIMIT (%) 3.15E-02 l6.97E-03

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1988 EFFLUENT SEMIANNUAL REPORT REV. 3 PAGE 7 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 27.0 INDIVIDUAL LIQUID EFFLUENT CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 AG-110M CI 3.34E-04 7.67E-04 CO-57 CI 2.13E-06 CO-58 CI 5.22E-03 4.33E-04 CO-60 CI 5.12E-04 1.63E-03 5.92E-04 CR-51 CI 4.03E-04 2.04E-04 CS-137 CI 2.22E-06 CS-138 CI 4.75E-06 FE-59 CI 7.28E-04 3.29E-05 FE-55 CI 6.20E-04 1.84E-03 MN-54 CI 3.13E-04 9.33E-06 NA-24 CI 1.11E-06 NB-95 CI 2.42E-04 7.20E-06 NB-97 CI 3.69E-05 1.48E-05 SB-122 CI 6.54E-06 SB-124 CI 4.94E-04 1.88E-04 SB-125 CI 4.35E-04 5.08E-04 SC-47 CI 3.29E-04 SN-113 CI 6.99E-05 SR-89 CI 1.24E-03 8.01E-04 SR-90 CI 4.58E-05 7.02E-06 l

SR-92 CI 2.27E-06 ZN-65 CI 7.63E-06 5.26E-06 ZR-97 CI 1.43E-05 TOTAL CI 2.37E-03 6.47E-04 1.02E-02 4.69E-03

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1988 EFFLUENT SEMIANMUAL REPORT REV. 3 PAGE 8 TABLE 2A (CONTINUED)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 28.3 DISSOLVED AND ENTRAINED GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 XE-133 CI l 1.73E-03' 1.79E-03 XE-135 CI 2.36E-05 1 54E-04 TOTAL CI 0.00E+00 0.00E+00 1.75E-03 1.94E-03 4

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e PINGP'753, Rev. 1 Retention: Lifetime Page 1 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-88 to 6-30-88 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1: Solid Waste and Irradiated Fuel Shipments A. Solid Waste Total Volumes and Measured Curie Quantities:

1. Type of Waste:

Container Units Total Volumes A.

B.

C. Non Compacted ft 748.8 96 DAW C1 1.458 D.

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Q_* .i yb PINGP;753,.Rev. 1 Retention: Lifetime j Page 2 of 5.:

T ' PRAIRIE ISLAND: NUCLEAR-GENERATING: PLANT Period: 1-1-88 to 6-30-88~

NORTHERN STATES POWER- License No. DPR-42 SOLID'RADI0 ACTIVE WASTE DISPOSAL' SEMI-ANNUAL REPORT.

Table I::. Solid Waste and Irradiated Fuel Shipments (Continued) l

. 2. Measured Major Nuclide' Composition by Type of Waste: .!:

l TYPE .(From Page.1) Nuclide Percent l

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  • NI-63 16.0 -i Co-60 7.9 Co-58 0.8 l i SB-125 0.7 j l

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  • = Inferred -- Not Measured on Site 1

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.l' PINGP 753, Rev. 1 Retention: Lifetime Page 3 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-88 to 6-30-88 NORTHERN STATES POWER License No. DPR-42 I

SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL FEPORT Table I: Solid Waste hnd Irradiated Fuel Shipments (Continued)

2. Measured Major.Nuclide Composition by Type of Waste (Continuation): J TYPE (From Page 1) Nu' elide Percent 1

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  • = Inferred - Not Measured on Site

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. PINGP 753, Rev. 1 Retention: Lifetime Page 4 of 5

-PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-88 to 6-30-88 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I: Solid Waste and Irradiated Fuel Shipments (Continued)

3. Solid Waste Disposition:

Number of Shipments Mode Destination 2 Truck Scientific Ecology Group 1 Truck Quadrex Recycle Center B. Irradiated Fuel Shipments:

Number of Shipments Mode Destination 0 _

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PINGP 753, Rev. 1 Retention: Lifetime Page 5 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-88 to 6-30-88 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I: Solid Waste and Irradiated Fuel Shipments (Continued)

C. Shipping Container and Solidification Method:

Volume Actidty Type of Container Solidify No. Code (Ft3) (Ci) _ Vaste Code 87-39 240.0 _

0.541 ,

C L N/A 87-40 96.3 0.366 C T. w/a 87-42 412.5 0.551 _

c T. ___y/a TOTALS 3 748.8 1.458 CONTAINER CODES: L = LSA A = Type A B = Type B Q = Large Quantity SOLIDIFICATION CODES: ,,

C = Cement TYPES OF WASTE: A = Resins B = Dry Compacted C = Non-Compacted D = Wst. Conc.

S = Spent Fuel

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