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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l . 1992 Effluent Semiannual Report REV. 1

( Page 1 of 9 [

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:

l l 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 DR 930827 i ADOCK 050002B2 9 PDR y

-. . . - . .- . =- .. . .

, 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.

'l m 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

4. Liquid effluents Total GeLi 25%

l Nuclide GeLi ,

- f E. Manual Revisions .!

1. Offsite Dose Calculations Manual latest Revision number: 12 f l

Revision date  : 17-JUN-91 l t

2. Process Control Program ~ Manual latest' Revision number: 14 l

Revision date  : 23-APR-91 ,

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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 {

' 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

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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 [

=i 11.0 PERCENT OF TECH SPEC (%) 2.26E-01 2.87E-01 i I

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

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1992 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 5 )

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 l

I 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 CONTINUOUS MODE l

BATCH MODE {

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 l

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 '

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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 -j.

i 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 -l s  !

SR-89 CI 5.10E-08 i TE-132 CI 3.61E-07

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, ZR-95 CI 3.36E-06 l

' I SR-90 CI 8.02E-07  ;

TOTAL CI 0.00E+00 4.86E-06 3.71E-06 3.31E-05  :

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. 1992 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 7 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES fl 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 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 7.90E-07 4.21E-07 f

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

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. ' 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 )

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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