ML20246P098

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Revised, Effluent & Waste Disposal Semiannual Rept for First Half 1987
ML20246P098
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 06/30/1987
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20246K241 List:
References
NUDOCS 8909110040
Download: ML20246P098 (14)
v • d • e


Text

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' AMENDMENT to the PRAIRIE ISLAND Effluent and Waste Disposal Seniannual Report (for the 1st Half year of 1987)

This 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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8909110040 990828 PDR - ADOCK 050002B2 '

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b..o.,va i19871 Effluent. Semiannual Report-Rev. 3:

-Paga'1:of'8

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. Retention:-Lifetime-t' EFFLUENT SEMIANNUAL REPORT l-JAN-87 THROUGH 30-JUN-87

' SUPPLEMENTAL INFORMATION m

Facility:

Prairie Island Nuclear Generating Plant Licensee:

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

Liquid Effluents:

a.

The dose or dose commitment to an individual from radioactive 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 Effluents:

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 / year skin I-131, H-3, LLP (1500 mrem / year'to any. organ b.

The dose due to radioactive gaseous effluents shall be

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limited to:

1 noble gases 410 mrad / quarter gamma 420 mrad / quarter beta 420 mrad / year gamma (40 mrad / year beta I-131, H-3, LLP 415 mrad / quarter 430 mrad / year l

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i W'A 1987? EFFLUENT-SEMIANNUAL REPORT' REV..3 PAGE 3 p

5.

i B.' - Maximum Permissible Concentration

-1.

-: Fission and activation; gases'in gaseous releases:

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

Iodine and particulate with halflives 5. cater than 8 days in gaseous releases:

10 CFR 20, Appendix B, Table 2, Column 1 3.

Liquid effluents for radionuclides other.than dissolved or entra'ined 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 applicable to. Prairie Island regulatory limits.

D.

Measurements and approximations of total activity l '. -

Fission and= activation gases Total GeLi 25%

in gaseous releases:

Nuclide GeLi 2.

. Iodines in gaseous releases:

Total.

-GeLi

~ d25%.

Nuclide GeLi

-3.

Particulate in gaseous releases:

Total GeLi 25%

Nuclide GeLi

'4.

Liquid effluents Total GeLi 125%

Nuclide GeLi

J 1987.' EFFLUENT SEMIANNUAL REPORT LREV. 3' PAGE 3

~

1.~ 0 BATCH RELEASES (LIQUID)

OTR: 01-QTR: 02 1.1. NUMBER OF BATCH RELEASES 9.40E+01

-7.00E+01 1.2 TOTAL TIME PERIOD (HRS) 1.61E+02 1.07E+02-

'1.3 MAXIMUM TIME PERIOD (HRS) 2.50E+00 2.70E+00 1.4. AVERAGE TIME PERIOD (HRS) 1.71E+00 1.53E+00 1.5 MINIMUM TIME PERIOD (HRS)

'1.30E+00.

4.00E-01 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 1.46E+04 1.62E+04

.2.0 BATCH RELEASES (GASEOUS)

QTR: 01 QTR: 02.

L 2.1.

NUMBER OF BATCH RELEASES 6.00E+00 1.40E+01 2.2 TOTAL TIME PERIOD (HRS) 1.48E+01 5.75E+02 2.3 MAXIMUM TIME PERIOD (HRS) 1.01E+01 8.78E+01 2.4 AVERAGE TIME PERIOD (HRS) 2.47E+00 4.11E+01 2.5 MINIMUM TIME PERIOD (HRS) 7.00E-01 6.00E-02 l

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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 10.00E+00 3.3 TOTAL TRITIUM RELEASED (CI) 0.00E+00 0.00E+00 4.0-hBNORMAL 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

1987 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) 5.17E-01 2.36E-01 5.2 AVERAGE RELEASE RATE (UCI/SEC) 6.58E-02 3.00E-02 5.3 GAMMA DOSE (MRAD) 1.75E-04 6.09E-05 5.4 BETA DOSE ("R?n) 4.02E-03 1.83E-03 5.5 PERCENT OF GAMMA TECH SPEC (%)

1.75E-03 6.09E-04 I

5.6 PERCENT OF BETA TECH SPEC (%)

2.01E-02 9.15E-03 1

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 1.99E-07 7.2 AVERAGE RELEASE RATE (UCI/SEC) 0.00E+00 2.53E-08 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 1.20E+01 1.26E+01 8.2 AVERAGE RELEASE RATE (UCI/SEC) 1.53E+00 1.60E+00 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 1.53E+00 1.60E+00 10.0 DOSE (MREM) 2.16E-02 2.31E-02 11.0 PERCENT OF TECH SPEC (%)

1.44E-01 1.54E-01 l 12.0 GROSS ALPHA (CI) 1.51E-07 9.46E-08

1987 EFFLUENT SEMIANNUAL REPORT REV. 3 PAGE 5 TABLE IC GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 13.0 FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 AR-41 CI 2.18E-03 KR-85 CI 4.61E-01 2.10E-01 KR-85M CI 2.90E-04 KR-87 CI 6.63E-04 KR-88 CI 7.01E-04 XE-133 CI 1.12E-03 4.31E-02 2.57E-02 XE-133M CI 2.78E-04 XE-135 CI 1.98E-03 5.21E-05 9.91E-04 XE-135M CI 1.88E-03 XE-137 CI 2.05E-03 XE-138.

CI 2.58E-03 TOTAL CI 1.34E-02 0.00E+00 5.04E-01 2.36E-01 14.0 IODINES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 I-131 CI TOTAL CI 0.00E+00 0.00E+00 0.00E+00 0.00E+00 15.0 PARTICULATE CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 l

CS-137 CI 1.99E-07 TOTAL CI 0.00E+00 1.99E-07 0.00E+00 0.00E+00

= =.

1987 EFFLUENT SEMIANNUAL REPORT REV. 3 PAGE 6 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 3.20E+07 5.49E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 1.60E+11 9.48E+10 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 3.97E-02 1.03E-02 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 2.48E-10 1.08E-10 19.0 TRITIUM 19.1 TOTAL RELEASE (CI) 1.82E+02 4.77E+01 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.14E-06 5.03E-07 1

20.0 DISSOLVED AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI) 6.82E-03 1.67E-06 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 4.26E-11 1.76E-14 21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 1.14E-06 5.03E-07 23.0 TOTAL BODY DOSE (MAEM) 4.78E-04 1.28E-04 24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 6.34E-04 1.25E-03 24.2 ORGAN GI-LLI GI-LLI 25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)

1.59E-02 4.27E-03 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)

6.34E-03 1.25E-02

-1987 EFFLUENT SEMIANNUAL REPORT' REV-3 PAGE 7 l

TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL' RELEASES

-27.0 INDIVIDUAL LIQUID EFFLUENT i

CONTINUOUS MODE BATCH MODE NUCLIDE UNITS-QTR: 01 QTR: 02 QTR: 01 QTR: 02 L

AG-110M CI 3.02E-04 7.21E-04 UA-140 CI 3.34E-05 i

f CO-58 CI 1.30E-05 4.80E-03 2.11E-03 CO-60 CI 6.53E-04 6.15E-04 CR-51 CI 1.87E-04 7.45E-04 CS-137 CI 7.71E-06 FE-55 CI 1.06E-03 3.05E-02 1.87E-03 FE-59 CI 2.62E-04 4.98E-05 I-131 CI 1.76E-06 I-133 CI 1.97E-05 MN-54 CI 1.56E-05 4.11E-06 1.53E-05 NB-95 CI 7.14E-05 NB-97 CI 2.99E-05 7.97E-06 RH-105 CI 1.93E-04 SB-124 CI 6.09E-04 1.54E-04 SB-125 C;

5.52E-04 1.45E-05 SC-47 CI 1.51E-03 2.46E-03 SN-113 CI 3.96E-05 5.12E-05 SR-85 CI 4.07E-06 SR-89 CI 2.30E-04 4.72E-05 ISR-90 CI 8.26E-06 SR-92 CI 1.30E-06 5.25E-06 TC-99M CI 2.93E-06 ZR-95 CI 3.09E-05 ZR-97 CI 3.55E-06 1.19E-05

TOTA, CI 2.94E-04 9.80E-05 3.94E-02 9.16E-03 i

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.1987 EFFLUENT SEMIANNUAL REPORT REV. 3' PAGE 8 TABLEL2A-(CONTINUED)

LIQUID EFFLUENTS'- SUMMATION OF ALL RELEASES 28.0 : DISSOLVED AND ENTRAINED GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 i

AR-41 CI 6.06E-05 KR-85 CI 9.37E-04 I

XE-133 CI 4.93E-03 XE-135 CI 8.93E-04 1.67E-06 TOTAL CI 0.00E+00 0.00E+00 6.82E-03 1,67E-06 l

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I' PINGP 753, Rev..-1 Retention:

Lifetime

.Page 1 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: :_i_g7 en 7_3_g7

' NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1:

Solid Waste and Irradiated Fuel Shipments j

'A.

Solid Waste Total' Volumes and Measured Curie Quantities:

1.

Type of Waste:

Container Units Total Volumes A.

Spent Resins J U-FT 690 172.5 c4 in A9 B.

C.

Non-Decontaminable CU-FT 350

, Scrap Metal D.

Filter Media CU-FT

_163

_,_,,16 3 Ci 1.975.

S.

  • Mac'1s disposed of under curallocation at Barnwell by vendor when said items could not be decontaminated.

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o g >..,

l ePINGP-753,-Rev._1

-Rotention:- Lifetime LPage 2 of-5

' PRAIRIE I'SLAND-NUCLEAR GENERATING PLANT Period: 1-1-87 to 7-1-87

. NORTHERN STATES' POWER.

License To. DPR-42 y

SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT

' Table I:

Solid Waste and Irradiated Fuel Shipments (Continued)

~

lj 2.

Measured Major Nuclide Composition by Type of Vaste:

TYPE (From Page 1)_

Nuclide Percent A

  • H-3 34.1
  • Ni-63 23.6 Co-60 5.6 Co-58 19.9 Mn 54 0.8

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  • C-14 44.4 Co-60 10.4 Sb-125 1.1
  • Fe-55 24.3
  • Ni-63 4.2
  • Sr-90 1.0
  • = Inferred - Not Measured on Site

= _

[3.

  • h

' -l PINGPi753, Rev. 1 Retention:. Lifetime

'Page 3 of.5

~ PRAIRIE ISLAND NUCLEAR GENERATING PLANT

~

Period: 1-1-8 87 NORTHERN STATES POWER License No. h SOLID RADIOACTIVE ~ WASTE DISPOSAL SEMI-ANNUAL REPORT

-Table 1:. Solid Waste-and Irradiated Fuel Shipments (Continued) o 2.

Measured Major Nuclide Composition by Type of Waste (Continuation):

TYPE (From Page=1)

Nuclide Percent C-

  • Fe-55 24.8-Co-60 6.8
  • Ni-63 13.7 Sb-125 54.0 l

l 1

  • = Inferred - Not Measured on Site

'[

PINGP 753, Rcv. 1 Ratcntion:

Lifetima l*

Page 4 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-87 to 7-1-87 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:

1 Number of Shipments Mode Destination 5

Truck Richland, Wash.

1 1

Truck Barnwell, S.C.

~

B.

Irradiated Fuel Shipments:

Number of SH oments Mode Destination y

-N PINGP 753,iRav. 1 9

Retention:

Lifetime:-

I

~Page-.5'of 5' u /-

. PRAIRIE' ISLAND NUCLEAR GENERATING PLANT Period: 1-1-87 to 7-1-87 NORTHERN--STATES POWER' License No. DPR-42

,j SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT-Table I:' Solid Waste and Irradiated Fuel Shipments (Continued) l

.C.

Shipping Container and Solidification Method:

No.

Volume Activity Type of Container Solidif;;

(Ft3)

(Ci)

Waste Code Code i

4 87-4 172.6 1.211 A

L MA I

87-5 172.5 2.789 A

L MA 87-6 172.5 1.741 A

L NA 87-7 172.5 4.876 A

L MA 87-9 163 1.975 D

T Ma j

i 350 c

T.

NA 1

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' CONTAINER CODES:

L = LSA l

i 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 = Filter Media

~

S = Spent Fuel i

  • Mat'l was non decontaminable items and disposed of by vender under our ellocation

. at Barnwell.

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