ML20246P074

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Revised, Effluent & Waste Disposal Semiannual Rept for Second Half 1987
ML20246P074
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 12/31/1987
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20246K241 List:
References
NUDOCS 8909110036
Download: ML20246P074 (13)
v • d • e


Text

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1 AMENDNENT; to the PRAIRIE ISLAND

-Effluent and Waste Disposal Seniannual Report (for the 2nd Half year of 1987) 7.his report 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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?l987pEffluent Semiannual Report Rev. 3 q

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lPage 1'of 7-Retention:1 Lifetime-EFFLUENT SEMIANNUAL REPORT

'l-JUL-87 THROUGH.31-DEC-87 SUPPLEMENTAL INFORMATION lFacilityi Prairie Island Nuclear Generating Plant Licensee:

Northern. States Power. Company License Numbers: DPR-42 & DPR-60 A.-Regulatory Limits 1.

Liquid. Effluents:

LThe dose or dose commitment to an individual from radioactive.

a.

materials in. 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 - Ef flueists :

a.: The' dose rate due.to radioactive materials. released in gaseous' effluents from the site shall be limited to:

noble gases 4500. mrem / year total body 43000 mrem /ycar skin 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 i

420 mrad / year g:mma 440 mrad / year beta I-131, H-3, LLP 415 mrad / quarter 430 mrad / year l:

-1987 EFFLUENT SEMIANNUAL REPORT REV. 3 PAGE 2 B.

Maximum Permissible Concentration i

1.

Fission and activation gases in gaseous releases:

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

Iodine and particulate with halflives greater than i

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 C 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 applicable to Prairie Island regulatory limits.

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 25%

Nuclide GeLi 4.

Liquid effluents Total GeLi 25%

Nuclide GeLi

1987 EFFLUENT SEMIANNUAL REPORT REV. 3 PAGE 3 1.0 BATCH RELEASES (LIQUID)

QTR: 03 QTR: 04 1.1 - NUMBER OF BATCH RELEASES 4.80E+01 4.20E+01-1.2 TOTAL TIME P2RIOD (HRS) 9.13E+01 6.28E+01 1.3 MAXIMUM TIME PERIOD (HRS) 2.16E+01 1.90E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.90E+00 1.50E+00 1.5 MINIMUM TIME PERIOD (HRS) 3.00E-01 1.30E+00 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 9.73E+03 8.50E+03 12. 0 BATCH RELEASES (GASEOUS)

QTR: 03 QTR: 04 2.1 NUMBER OF BATCH RELEASES 1.00E+00 1.00E+00 2.2 TOTAL TIME PERIOD (HRS) 2.80E+00 2.80E+00 2.3 MAXIMUM TIME PERIOD (HRS) 2.80E+00 2.80E+00 2.4 AVERAGE TIME PERIOD (HRS) 2.80E+00 2.80E+00 2.5 MINIMUM TIME PERIOD (HRS) 2.80E+00 2.80E+00 3.0 ABNORMAL RELEASES (LIQUID)

QTR: 03 QTR: 04 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: 03 QTR: 04 4.1 NUMBER OF BATCH RELEASES 0.00E+00 0.00E+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00

1987' EFFLUENT SEMIANNUAL REPORT REV. 3 PAGE 4 TABLE 1A.

GASEOUS' EFFLUENTS - SUMMATION OF ALL RELEASES l

QTR: 03 QTR: 04 5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 5.44E-02 6.95E-021 5.2-AVERAGE RELEASE RATE (UCI/SEC) 6.92E-03 8.84E-03 5.3 GAMMA DOSE (MRAD) 4.40E-06 5.20E-06 5.4 BETA DOSE (MRAD) 4.42E-04 5.66E-04 5.5 PERCENT OF GAMMA TECH SPEC (%)

4.40E-05 5.20E-05 5.6 PERCENT OF BETA TECH SPEC (%)

2.21E-03 2.83E-03 6.0 IODINES 6.1 TOTAL I-131.(CI) 0.00E+00 0.00E+00 6.2 AVERAGE RELEASE RATE (UCI/SEC) 0.00E+00 0.00E+00 7.0 PARTICULATE 7.1 ~ TOTAL RELEASE (CI) 0.00E+00 0.00E+00 7.2 AVERAGE RELEASE RATE (UCI/SEC) 0.00E+00-0.00E+00 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 1.25E+01

.2.44E+01 8.2 AVERAGE RELEASE RATE (UCI/SEC) 1.59E+00 3.10E+00 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 1.59E+00 3.10E+00 10.0 DOSE (MREM) 2.24E-02 4.40E-02 11.0 PERCENT OF TECH SPEC (%)

1.49E-01 2.93E-01 12.0 GROSS ALPHA (CI) 1.38E-07 3.68E-08

)

l

1987. EFFLUENT SEMIANNUAL' REPORT REV.

3' PAGE 5 1

TABLE SC

-GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 13.0 FISSION AND ACTIVATION GASES l

CONTINUOUS MODE BATCH MODE NUCLIDE UNITS

-QTR: 03 QTR: 04 QTR: 03 QTR: 04 KR-85 CI 5.40E-02 6.94E-02 1

XE-133 CI 3.52E-04 1.20E-04 XE-135 CI 4.62E+00 TOTAL CI 0.00E+00 0.00E+00 5.44E-02 6.95E-02 14.0 IODINES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTP: 03 QTR: 04 QTR: 03 QTR: 04 I-131 CI 0.00E+00 Or00E+00 0.00E+00 0.00E+00 TOTAL CI 0.00E+00 0.00E+00 0.00E+00 0.00E+00 g

15.0 PARTICULATE CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 SR-89 CI 9.06E-05 SR-90 CI 1.42E-04 TOTAL CI 0.00E+00 0.00E+00 0.00E+00 2.33E-04 I

_.__m_

__ _ _ _ _ - _ _ =

1987-EFFLUENT SEMIANNUAL REPORT REV. 3 PAGE'6 TABLE'2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 03 QTR: 04 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 4.93E+07 4.16E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 2.56E+11 1.79E+11 18.0~ FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 8.16E-03 2.19E-03 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 3.19E-11~

1.23E-11 19.0 TRITIUM 19.1 TOTAL RELEASE (CI) 1.21E+02 9.86E+01 19.2 AVERAGE DILUTBD CONCENTRATION (UCI/ML) 4.73E-07 5.51E-07 20.0 DISSOLVED ".ND ENTRAINED GASES

~

20.1 TOTAL RELEASE (CI) 2.61E-04 9.32E-04 20.2-AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.02E-12 5.21E-12 21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 4.73E-07 5.51E-07 l

23.0 TOTAL BODY DOSE (MREM) 2.94E-04 4.69E-04 l

l 24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 2.94E-04 4.69E-04 24.2 ORGAN TTL BODY TTL BODY 25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)

9.80E-03 1.56E-02 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)

9.80E-03 1.56E-02 i

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1987-EFFLUENT SEMZANNUAL REPORT REV. 3 PAGE 7 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1

1 1

27.0 INDIVIDUAL LIOGiD EFFLUENT CONTINUOUS MODE BATCH MODE I

NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 1

AG-110M CI 5.76E-05 4.59E-04 CO-58 CI 4.42E-04 5.28E-05 CO-60 CI 2.57E-04 4.69E-04 CR-51 CI 4.57E-05 CS-134 CI 1.77E-06 CS-137 CI 6.92E-06 1.32E CS-138 CI 6.15E-05 NA-24 CI 3.43E-06 NB-97' CI 1.99E-05 2.50E-05 SB-124 CI 4.32E-03 7.49E-05 SB-125 CI 2.71E-03 2.90E-04 SC-47 CI 2.49E-04 5.47E-04 SR-89 CI 9.06E-05 SR-90 CI 1.42E-04 4.48E-06 ZR-97 CI 3.55E-06 1.79E-05 TOTAL CI 0.00E+00 2.33E-04 8.16E-03 1.96E-03 CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 OTR: 03 QTR: 04 XE-133 CI 2.59E-04 8.72E-04 XE-135 CI 1.77E-06 5.98E-05 TOTAL CI 0.00E+00 0.00E+00 2.61E-04 9.32E-04 I

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PINGP 753, Rev. 1 Retention:

Lifetime Page 1 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-87 to 12-31-87 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:

Solid Waste and Irradiated Fuel Shipments A.

Solid Wasta Total Volumes and Measured Curie Quantities:

1.

Type of Waste:

Container Units Total Volumes A.

Resin Cu - ft 810.3 172.5 (1 @ 120.3)

C1 391.814 B.

Drv Compacted Cu

.fe 2829 7.5 C1 23.899 C.

-Non-Comcacted Cu - f t 20.8 Ci 0.037 D.

Filter Cartridges Cu - ft 163.3 163.3 C1 1.922 S.

p.-

4 PINGP 753, Rcv. 1 Retention:

Lifetime Page 2 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-87 to 12-31-87 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 (From Page 1)

Nuclide Percent A

  • H-3 15.0 CO-36 21.1 SB-125 0.8

~

l 1

  • = Inferred - Not Measured on Site
  • c' PINGP 753, Rev. 1 Retention:

Lifetime Page 3 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-87 to 12-31-87 NORTHERN STATES POWER Lice.nse 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 (Continuation):

TYPE (From Page 1)

Nuclide Percent i

CO-60 2.3. 7 C-14 4.8

0.8

  • 6 W
  • = Inferred - Not Measured on Site

[...

PINGP 753, Rev. 1

-Retention:

Lifetime Page 4 of 5 l

t PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-87 to 12-31-87 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT l

Table I:

Solid Waste and Irradiated Fuel Shipments (Continued) 3.

Solid Waste Disposition:

Number of Shipments Mode Destination 10 Truck Richland, Washington 1

Truck Barnwell, S.C.

1 Truck Beaty, Nevada B.

Irradiated Fuel Shipments:

Number of Shipments Mode Destination I

l l

I

l' -

PINGP 753, Rev. 1 Retention:

Lifetime Page 5 of 5 PRAIRIE ~ISLt.ND NUCLEAR GENERATING PLANT Period: 7-1-87 to 12-31-87 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:

No.

Volume Activity Type of Container /

Solidify (Ft3)

(Ci)

Waste Code Code 87-26 172.5 2.758 A

L NA 87-27 585.0 7.225 B

L NA 87-28 172.5 7.496 A

L NA 87-29 570.0 3.586 B

L NA 87-30 163.3 1.922 D

L NA 87-32 120.3 373.448 A

B NA 87-34 172.5 2.014 A

L NA 87-38 570.0 5.962 B

L NA 87-41 172.5 6.098 A

L NA 87-43 534.0 3.563 B

L NA 87-31 570.0 3.563 B

L NA 87-39 20.8 0.037 C

L NA TOTALS 12 3823.4 417.672 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 = Wsm=48nt=. Filter Cartridges S = Spent Fuel

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