ML20153B940

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Effluent Semiannual Rept for Jan-June 1988
ML20153B940
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 06/30/1988
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20153B884 List:
References
NUDOCS 8808310160
Download: ML20153B940 (14)


Text

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PINGP 158, Rev. 6 Page 1 of 8 Retention: Lifetime l

l EFFLUENT SEMI-ANNVAL REPORT  :

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Jan. 1988 THROUGH June 1988  !

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SUPPLEMENTAL INFORMATION Tacility - Prairie Island Nuclear Generatina Plant I

Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60

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A. Regulatory Limits

1. Liquid Effluents:
a. The dose or dose commitment to an individual from radio- i accive materials in liquid effluents released from the l site shall be limited:

t for the Quarter 3.0 mrem Total Body f 10.0 mren Any Organ for the Year 6.0 mrem Total Body l 20.0'erem Any Organ  ;

2. Gaseous Effluents:

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

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Noble Gases i 500 mres/ Year Total Body l

[ 4000 mrea/ Year Skin l l

I-131, H-3, LLP $ 1500 mree/ Year Any Organ  ;

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b. The dose due to radioactive gaseous effluents shall be  !

limited tot j i

Noble Gases i 10 mrad /Qtr Gamma j

$ 20 mrad /Qtr Beta i 20 mrad / Year Gamma 5 40 mrad / Year Beta 1-131. H-3, LLP i 15 ares /Qtr 1 30 ares / Year

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PINGP 158. Rsv. 6

. Page 2 of 8 B. Maximum Permissible Concentrations

1. Fission and activation, gases in gaseous releases:

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

2. Iodine and particulates with half-lives greater than 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 CFR 20, Appendix B, Table 2, Column 2

4. Liquid Effluent dissolved ..nd entrained gases:

2.0E-04 pei/ml Total Activity C. Average Energy Not applicable to Prairie Island Regulatory Limits.

D. M,easurements and Approximations of Total Radioactivity

1. Fission and activation gases Total Geli in gaseous releases: Nuclide Geli
2. Iodines in gaseous releases Total Geli Nuclide Geli
3. Particulates in gaseous Total Geli releases: Nuclide Geli-
4. Liquid Effluents: Total Geli Nuclide Geli )

1.0 BATCH RELEASES (Liquid)

QTR 1 QTR 2 l 1.1 Number of Batch Releases l 5.50E+01 2.80E+01 l 1.2 Total Time Period for a Batch Release l l (hr.) i 8.60E+01 4.58E+01 l 1.3 Maximum Time for a Batch Release (hr) l 1.90E+00 2.30E+00 l 1.4 Average Time for a Batch Release (hr) l 1.56E+00 1.64E+00 l 1.5 Minimum Time for a Batch Release (hr) l 1.00E+00 1.30E+00 l 1.6 Ave Mississippi flow during Quarter (CFS)l 1.01E+04 1.32E+04 l j IBM

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PINGP 158,-Rev. 6 Paga<3 of 8 2.0. BATCH RELEASES (Gaseous)

QTR 1 QTR 2 2.1 Number of Batch Releases l 1.60E+01 1.00E+00 l 2.2 ' Total Time Period for a Batch Release (hr) 1 1.27E+02 2.90E+00 l 2.3 . Maximum Time for a Batch Release (hr) l 3.27E+01 2.90E+00 l 2.4 Average Time for a Batch Release (hr) l 7.92E+00 2.90E+00 l 2.5 Minimum Time for a Batch Release (hr)- l 3.00E-02 2.90E+00 l 3.0 ABNORMAL RELEASES (Liquid)

QTR 1 QTR 2 3.1 Number of Batch Re'_ases l 0.00E+00 0.00E+00 l 3.2 Total Activity Release (Ci) -l 0.00E+00 0.00E+00 l 3.3 Total Tritium Release (Ci) l 0.00E+00 0.00E+00 l 4.0. ABNORMAL RELEASES (Gaceous)

QTR 1 QTR 2 ~

4.1 Number of Batch Releases ] 0.00E+00 0.00E+0'0 l I 4.2 Total Activity Release (Ci) l 0.00E+00 0.00E+00 l l

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PINGP 158, Rev. 6 Page 4 of.8 TABLE 1A Ei..UENT SEMIANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR 1- l QTR 2 lEST RR R I I I I I I 5.0 FISSION AND ACTIVATION GASES 5.1 Totol Release (Ci) l 6.60E 3.75E-02 2.50E+01l 5.2 Average Release Rate (pCi/sec) l 8.40E-03 4.77E-03 5.3 Gamma Dose (mrad) l 2.86E-05 4.21E-06 l 5.4 Beta Dose (mrad). l 4.86E-04 3.01E-04 l 5.5 % of Gamma T.S. Limit (%) l 2.86E-04 4.21E-05 l 5.6 % of Beta T.S. Limit (%) l 2.43E-03 1.51E-03 1 6.0 IODINES 6.1 Total I-131 (Ci) l 0.00E+00 6.49E-07 2.50E+01l 6.2 Average Release Rate (pCi/sec) 1 0.00E+00 8.26E-08 7.0 PARTICULATES 7.1 Total Release (Ci) l 9.25E-07 l 2.78E-07 2.50E+01l 7.2 Average Release Rate (pCi/sec) l 1.18E-07 l 3.54E-08 8.0 TRITIUM .

8.1 Total Release (Ci) l 7.20E+00 9.48E+00 l 2.50E+01]

8.2 Average Release Rate (pCi/sec) l 9.16E-01 1.21E+00 l 9.0 TOTAL IODINE PARTICULATES AND l l l l TRITIUM (pCi/sec) l 9.16E-01 l 1.21E+00 l 2.50E+01l 1

10.0 DOSE (mrem) i 1.31E-02 l 1.71E-02 l 11.0 % OF T.S. LIMIT (%) l 8.73E-02 l 1.14E-01 l 12.0 GROSS ALPHA 12.1 Total Release (Ci) { 5.02E-07 1 3.44E-07 l 2.50E+01l IBM

PINGP 158, Rav. 6 Page 5 of 8 TABLE IC EFFLUENT SEMIANNUAL REPORT GASE0US EFFLUENTS GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE l l l l- 1 I I l'NUCLIDE l UNIT l QTR 1 l QTR 2 l QTR 1 l QTR 2 'l I l l l l l~ l 13.0 INDIVIDUAL FISSTON AND ACTIVATION GASES l Kr85 Ci 5.14E-02 3.64E-02 l l Kr85m Ci l l Kr87 Ci ;_ l' l Kr88 Ci l-l Xe133 Ci i 1.41E-02 1.08E-03 l l Xe135 Ci 5.12E-04 l l Xe135m Ci l l Xe138 Ci l l Xe131m Ci l l Ar41 Ci l l Xe133m Ci l l l I I I l l l Total l Ci l 0.00E+00 0.00E+00 6.60E-02 3.75E-02 l 14.0 10 DINES (Ci) l 1131 l Ci j 6.49E-07 l l I133 l Ci l 2.00E-05 l I135 l Ci l l "ll l Total l Ci l 0.00E+00 2.06E-05 '

O.00E+00 1 0.00E+00 l CONTINUOUS MODE BATCH N0DE 1 1 I I I I I l NUCLIDE l UNIT l QTR 1 l QTR 2 l QTR 1 l QTR 2 l l l l l 1 I i 15.0 PARTICULATES (Ci) l SrL9 Ci l l Sr90 Ci 3.07E-08 l l Cs134 Ci l l l Cs137 Ci 2.78E-07 2.0SE-07 l l Ba-La140 Ci l l CoS8 l Ci l l l Co60 l Ci l 6.86E-07 l I . '

I I I l Total Ci l 7.17E-07 l 2.78E-07 2.08E-07 0.00E+00  !

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PINGP 158, Rev. 6

. Page.6 of 8 TABLE 2A EFFLUENT SEMIANNUAL REPORT LIQUID EFFL'JENTS - SUMMATION OF ALL RELEASES

. UNIT QTR 1 .I QTR 2 ~

E R%

l -l I I l 16.0 VOLUME OF WASTE (Prior.to Dilution) l Liters l 7.58E+07 l 3.36E+07 l 2.50E+01l-17.0 VOLUME OF DILUTION Water (liters) l Liters l 1.08E+11 l 7.97E+10- l 2.50E+01l 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 Total Release W/0 H-3, (Ci) l l l l Rad Gas, Alpha l 1.20E-02 5.13E-03 l 2.50E+01l 18.2 Average Diluted (pCi/ml) l .

1 Concentration l, 1.11E-10 l 3.93E-11' 'l 19.0 TRITIUM 19.1 Total Release (Ci) l 1.60E+02 l 6.14E+01 2.50E+01]

19.2 Average Diluted (pCi/ml) l l Concentration l 1.48E-6 l 7.70E-07 l 20.0 DISSOLVED AND ENTRAINED GASES 20.1 Total Release (C1) l 1.75E-03 l 1.94E-03 2.50E-01] l 20.2 Average Diluted (pCi/ml) l l l Concentration i 1.62E-11 l 2.44E-11 l l 21.0 GROSS ALPHA i

1 21.1 Total Release (Ci) l 0.00E+00 l 0.00E+00 l 2.50E+01l 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (pCi/ml) l 1.48E-06 l 7.70E-07 l 2.50E+0_1l IBM J

4 PINGP 158, Rev. 6

- Page 7 of 8' TABLE 2A EFFLUENT' SEMIANNUAL' REPORT i

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES l UNIT' QTR'l l QTR 2 ERROR %

l l 1 l I 23.0 TOTAL BODY DOSE (mrem) l 4.12E-04 l 2.86E-04 l

,24.0 CRITICAL ORGAN DOSE (mrem) l 3.15E-03 -2.86E-04 l (organ) l GI TOTAL BODY }

I 25.0 % TOTAL BODY T.S. LIMIT (%). l 1.37E-02 l 9.53E-03 l l l

26.0 % OF CRITICAL ORGAN (%) l l l T.S. Limit l 3.15E-02 l 9.53E-03 l l

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PINGP 158, Rav. 6 l

  • Page 8 of 8 TABLE 2A EFFLUENT SEMIANNUAL RPEORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES CONTINUOUS MODE BATCH MODE I I I I - I -l -

l-l NUCLIDE l UNIT l QTR 1 l .QTR 2 l QTR 1 l QTR 2 l l l l 1 I I I 27.0 INDIVIDUAL LIQUID EFFLUENT I Sr89 Ci 1.24E-03 1.66E-04 l l Sr90 Ci 1.05E-04 7.02E-06 3.89E-06 l l Cs134 Ci l l Cs137 Ci 2.22E-06 l l 1131 Ci l l CoS8 Ci 5.22E-03 4.33E-04 l l Co60 Ci 5.12E-04 1.63E-03 5.92E-04 l l Fe59 Ci 7.28E-04 3.29E-05 l l Zn65 Ci 7.63E-06 5.26E-06 l l Mn54 Ci 3.13E-04 9.33E-06 l l Cr51 Ci 4.03E-04 -2.04E-04 _l l Zr-Nb95 Ci 2.42E-04 7.20E-06 l l Mo99 Ci l l Ba-La140 Ci l 1 l l

k Ci 0.00E+00 0.00E+00 1.64E-03 1.57E-03 l l Total Ci 1.75E-03 2.71E-04 1.02E-02 1 2.86E-03 l

  • From Attachment #1, Additional Nuclides CONTINUOUS MODE BATCH MODE l l l l l l l l NUCLIDE l UNIT l QTR 1 l QTR 2 l QTR 1 l QTR 2 l l l 1 I I I l 28.0 DISSOLVED AND ENTRAINED GASES I

l Xe133 Ci 1.73E-03 1.79E-03 l l Xe133m Ci l l Xe131m Ci l l Xe135 Ci 2.36E-05 1.54E-04 l l Kr85m Ci l l Kr85 Ci l l l Kr88 Ci l !

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l Total Ci 0.00E+00 0.00E+00 1.75E-03 1.94E-03 l l

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ATTACHMENT 1 -

ADDITIONAL NUCLIDES

. LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QTR 01 QTR 02 QTR 01 QTR 02 AG-110M CI 3.34E-04 7.67E-04 CO-57 CI 2.13E-06 CS-138 CI '

4.75E-06 NA-24 CI 1.11E-06 j 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 . 0 8 E- O'4 i

1 SN-113 CI 6.99E-05 SC-47 CI 3.29E-04 SR-92 CI 2.27E-06 ZR-97 CI 1.43E-05 SUBTOTAL CI 0.00E+00 0.00E+00 1.64E-03 1.57E-03 1 l

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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. ITPR-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. i B. ,

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

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PINGP 753, Rev. 1 Retention: Lifetime Page 2 of 5 F.lAIRIE 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 (Continued)

2. Measured Major Nuclide Composition by Type of Waste:

TYPE (From Page 1) Nuclide Percent C

  • NI-63 16.0 Co-60___ 7.9 Co-58 0.8 SB-125 0.7 1

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  • = Inferred - Not Measured on Site

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.O PINGP 753, Rev. 1 Retent'on: Lifetime Page 3 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLWT Period: 1-1-88 to 6-30-88 NORTHERN STATES POWER License-No. DPR-47 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

  • = Inferred - Not Measured on Site

4 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 Shipmencs Mode Destination 2 Truck Scientific Ecology Group 1 Truck Quadrex Racycle Center B. Irradiated Fuel Shipments:

Number of Shipments Mode Destination 0 l l

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PINGP 753, Rev. 1 Retention: Lifetir- '

Page 5 of 5 PPAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-88 to 6-30-88 NM THERN STATES POWER- License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1. 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 87-39 240.0 0.541 c L N/A 87-40 96.3 , 0.366 C 1. n/A 87-42 412.5 0.551 C 1. n/A b

TOTALS 3 748.8 1.458 CONTAINER CODES: L = LSA A = Type A B = Type B Q = Large Quantity l

SOLIDIFICATION CODES: C = Cement TYPES OF WASTE: A = Resins B = Dry Compacted C = Non~ Compacted D = Wst. Conc. i S = Spent Fuel i

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