ML20056G716

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Effluent Semiannual Rept 920706-930103, Supplemental Info
ML20056G716
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 01/03/1993
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20056G694 List:
References
NUDOCS 9309070083
Download: ML20056G716 (9)
v • d • e


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1992 Effluent Semiannual Report REV. 1

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Page 1 of 9

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Retention: Lifetime i

EFFLUENT SEMIANNUAL REPORT 5

06-JUL-92 THROUGH 03-JAN-93 SUPPLEMENTAL INFORMATION Facility:

Prairie Island Nuclear Generating Plant l

Licensee:

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

Regulatory Limits 1.

Liquid Effluents:

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a.

The dose or dose commitment to an individual from radioactive.

I materials in liquid effluents released from the site shall be limited to:

for the quarter 3.0 mrem to the total body I

10.0 mrem to any organ i

for the year 6.0 mrem to the total body l

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 41500 mrem / year to any crgan b.

The dose due to radioactive gaseous effluents shall be limited to:

l noble gases 410 mrad / quarter gamma l

420 mrad / quarter beta 420 mrad / year gamma 440 mrad / year beta 1

I-131, H-3, LLP 415 mrem / quarter to any organ 430 mrem / year to any organ 9309070083 930827 i

DR ADOCK 050002B2 9

PDR y

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1992 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 2 B.

Maximum Permissible Concentration 1.

Fission and activat. ion gases in gaseous releases:

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

Iodine and particulates with halflives greater than 8 days in gaseous releases:

i 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 l

4.

Liquid effluent dissolved and entrained gases:

2.0E-04 uCi/ml Total Activity C.

Average Energy Not applicable to 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 r

t 2.

Iodines in gaseous releases:

Total GeLi

' i25%

Nuclide GeLi t

3.

Particulates in gaseous releases:

Total GeLi 25%

Nuclide GeLi l

4.

Liquid effluents Total GeLi 25%

Nuclide GeLi f

E.

Manual Revisions f

1.

Offsite Dose Calculations Manual latest Revision number:

12 l

Revision date

17-JUN-91 l

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2.

Process Control Program ~ Manual latest' Revision number:

14 Revision date

23-APR-91 i

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<=+:

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1992 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 3 1.0 BATCH RELEASES (LIQUID)

QTR: 03 QTR: 04 1.1 NUMBER OF BATCH RELEASES 5.00E+01 1.03E+02 1.2 TOTAL TIME PERIOD (HRS) 2.24E+02 1.91E+02 1.3 MAXIMUM TIME PERIOD (HRS) 7.53E+00 4.62E+00 1.4 AVERAGE TIME PERIOD (HRS) 4.48E+00 1.86E+00 1.5 MINIMUM TIME PERIOD (HRS) 2.83E+00 1.20E+00 I

l 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 1.95E+04 5.76E+04 l

l 2.0 BATCH RELEASES (GASEOUS)

QTR: 03 QTR: 04 2.1 NUMBER OF BATCH RELEASES 6.00E+00 1.30E+01 2.2 TOTAL TIME PERIOD (HRS) 1.42E+01 2.98E+01 2.3 MAXIMUM TIME PERIOD (HRS) 8.00E+00 8.10E+00 2.4 AVERAGE TIME PERIOD (HRS) 1.33E+00 2.29E+00 2.5 MINIMUM TIME PERIOD (HRS) 2.50E-01 2.50E-01 1

3.0 ABNORMAL RELEASES (LIQUID)

QTR: 03 QTR: 04 3.1 NUMBER OF RELEASES 0.00E+00-1.00E+00 3.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 3.70E-03 3.3 TOTAL TRITIUM RELEASED (CI) 0.00E+00 2.96E 4.0 ABNORMAL RELEASES (GASEOUS)

QTR: 03 QTR: 04 4.1 NUMBER OF RELEASES 0.00E+00 0.00E+00 4. 2.

TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00

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1992-EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE e

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' TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 03 QTR: 04 2

5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 1.73E+01 3.52E+00 5.2 AVERAGE RELEASE RATE (UCI/SEC) 2.20E+00 4.48E-01 i

5.3 GAMMA DOSE (MRAD) 7.46E-03 2.05E-03 4

5.4 BETA DOSE (MRAD) 2.39E-02 1.16E-02

-l 5.5 PERCENT OF GAMMA TECH SPEC (%)

7.46E-02 2.05E-02 5.6 PERCENT OF BETA TECH SPEC (%)

1.20E-01 5.80E-02 6.0 IODINES 6.1 TOTAL I-131 (CI) 1.48E 1.72E-04 6.2 AVERAGE RELEASE RATE (UCI/SEC) 1.88E-06 2.19E-05 7.0 PARTICULATES 7.1 TOTAL RELEASE (CI) 3.71E-06 3.80E-05 7.2 AVERAGE RELEASE RATE (UCI/SEC) 4.72E-07 4.83E-06 1

8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 1.59E+01 9.80E+00 8.2 AVERAGE RELEASE RATE (UCI/SEC) 2.02E+00-1.25E+00

)

t 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 2.02E+00 1.25E+00 l

1 10.0 DOSE (MREM) 3.39E-02 4.31E-02

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=i 11.0 PERCENT OF TECH SPEC (%)

2.26E-01 2.87E-01 i

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12.0 GROSS ALPHA (CI) 0.00E+00 5.39E-08 i

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1992 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 5

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TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES i

f 13.0 FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE i

NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 i

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KR-85 CI 2.74E-01 7.90E-01 i

XE-131M CI 2.41E-02 XE-133 CI 1.61E+01 1.85E+00 6.58E-01 8.10E-01 XE-133M CI 1.67E-01 5.66E-04 j

XE-135 CI 1.58E-01 4.15E-02 1.43E-04 2.06E-05 XE-135M CI 5.72E-04 TOTAL CI 1.64E+01 1.90E+00 9.33E-01 1.62E+00 14.0 IODINES l

CONTINUOUS MODE BATCH MODE

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NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 i

I-131 CI 1.07E-05 1.65E-04 4.08E-06 7.11E-06 I-132 CI 5.73E-10 i

I-133 CI 2.97E-06 1.02E-07 r

I-134 CI 5.29E-10 l

I-135 CI 4.87E-07 TOTAL CI 1.07E-05 1.65E-04 7.54E-06 7.21E-06 i

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s 1992 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 6 TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES i

15.0 PARTICULATES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS OTR: 03 QTR: 04 QTR: 03 QTR: 04 I

AG-110M CI 7.01E-07 i

CO-58 CI 3.36E-06 5.61E-06 f

C0-60 CI 1.67E-06 i

CS-134 CI 1.88E-06 8.83E-06

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CS-136 CI 2.35E-07 l

CS-137 CI 1.56E-06 7.68E-06 MN-54 CI 3.80E-08 l

i NA-24 CI 2.81E-10 l

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NB-97 CI 1.51I-07 NB-95 CI 5.47E-06

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SR-89 CI 5.10E-08 i

TE-132 CI 3.61E-07 a

ZR-95 CI 3.36E-06 I.

SR-90 CI 8.02E-07 TOTAL CI 0.00E+00 4.86E-06 3.71E-06 3.31E-05 i

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1992 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 7 TABLE 2A f

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES l

9 QTR: 03 QTR: 04 1

16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 2.77E+07 3.09E+08 17.0 VOLUME OF DILUTION WATER (LITERS) 2.66E+11 9.35E+10 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 1.11E-01 2.23E-01 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 4.17E-10 2.39E-09 19.0 TRITIUM 19.1 TOTAL RELEASE (CI) 2.10E+02 3.93E+01 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 7.90E-07 4.19E-07 20.0 DISSOLVED AND ENTRAINED GASES I

20.1 TOTAL RELEASE (CI) 2.39E-02 2.20E-02 l

20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 8.99E-11 2.35E-10 21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 e

f 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 7.90E-07 4.21E-07 1

23.0 TOTAL BODY DOSE (MREM) 8.12E-04 3.82E-03 l

i 24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 8.12E-04 3.82E-03 24.2 ORGAN TTL BODY TTL BODY 1

25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)

2.71E-02 1.27E-01 i

j 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)

2.71E-02 1.27E-01 l

. ' 1992-EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 8 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 27.0 INDIVIDUAL LIQUID EFFLUENT CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 AG-108M CI 2.66E-06 AG-110M CI 1.15E-04 2.17E-02 1.34E-02 BE-7 CI 4.26E-04 5.75E-05 CO-57 CI 5.29E-05 1.59E-05 CO-58 CI 5.93E-05 1.83E-02 5.43E-02 CO-60 CI 7.21E-03 9.82E-03 CR-51 CI 1.95E-03 1.39E-02 CS-134 CI 3.40E-05 3.06E-04 CS-137 CI 2.78E-05 5.84E-05 4.21E-04 CU-64 CI 8.17E-04 FE-55 CI 5.19E-02 4.99E-02 FE-59 CI 1.34E-03 6.04E-03 I-131 CI 5.56E-06 8.19E-05 3.03E-03 I-133 CI 6.91E-06 LA-140 CI 1.00E-04 3.44E-04 MN-54 CI 7.29E-04~

1.61E-03 MO-99 CI 1.58E-05 1.37E-05 NA-24 CI 8.06E-07 NB-95 CI 3.29E NB-97 CI 7.93E-06 5.25E-06 RH-105 CI 2.20E-05 RU-103 CI 3.17E-06 l

SB-122 CI 2.08E-05 3.60E-03 58-124 CI 1.09E-03 3.59E-02

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Subject:

Northern States Power, Prairie Island Liquid Effluent Release Abnormal Release during 4th Quarter 1992.

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On Dec 6, 1992 two liquid waste tanks were placed on recirculation for release.

One of the tanks were sampled and processed for release prior to the second tank.

The release authorization papers and operations l

procedures became mixed up and the tank that was not yet sampled and

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authorized was released.

The mistake was realized later in the day when the sample and release authorization papers were being prepared for the second tank to be released.

Follow-up samples were taken and compared to projected and actual observed radiation monitor readings.

The two tanks were very similar in concentration and it was determined that the original pre-release dose calculations were reasonably accurate.

The tank was released at a rate that was 0.22% of the maximum release rate limit based on MPCs as per the ODCM.

Operations and Effluent Release procedures have been altered to prevent re-occurance.

This event has been investigated and the corrective actions determined adequate.

Further information concerning this event can be found in Prairie Island LER for Unit #1 92-16.

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