ML20012A320

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Amend to Effluent & Waste Disposal Semiannual Rept for First Half 1989, Incorporating Previously Omitted Second Quarter Analyses Results of Sr-89 & Sr-90
ML20012A320
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 06/30/1989
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20012A314 List:
References
NUDOCS 9003090227
Download: ML20012A320 (11)
v • d • e


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r AMENDNENT to the  !

. PRAIRIE ISLAND

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Effluent' and Weste Disposal Seelannual Report l1

, (forthe1stHalfyearof1989) y This report provides'the previously omitted 2nd quarter analyses results of Sr-89 and Sr-90. '

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- Retention: Lifetime-n n- 1

~ EFFLUENT SEMIANNUAL REPORT

$ 01-JAN-89"THROUGH 01-JUL-89 -

SUPPLEMENTAL INFORMATION

(? Facility: Prairie Island' Nuclear Generating Plant:

- Licensee Northern States Power Company ,_

License' Numbers: DPR-42 & DPR-60 ,

Y A. :-- Regulatory Limits

.l.. 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:

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.for~the quarter 3.0 mrem to the total body i 10.0 mrem to any_ organ for.the year 6.0 mrem to the total body 20.0 mrem to any; organ  !

s K 12. Gaseous Effluents:

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a. The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited toi noble' gases 4500 mrem / year total body ,

43000 mrem / year 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 '

420 mrad / year gamma 440 mrad / year beta I-131, H-3, LLP 415 mrad / quarter 430 mrad / year

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'1989/ EFFLUENT. SEMIANNUAL REPORT- REV. 1 PAGE 2 i

g -. B. ' Maximum Permissible Concentration i Fission and-activation gases in gaseous releases:.

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'10 CFR 20, Appendix B,-Table 2, Column 1 r

2. Iodine and particulates with-halflives greater.than
8. days in gaseous releases:
3. Liquid effluents for radionuclides other than dissolved or entrained gases:

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

4. Liquid effluent dissolved and entrained gases:

.i 2.0E-04 uci/ml Total Activity t

1 C. Average Energy Not applicable to Prairie Island regulatory limits.

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D. Measurements and approximations of total activity ll . Fission and activation gases Total GeLi 125%

in. gaseous releases: -Nuclide GeLi

2. Iodines in gaseous releases: Total GeLi 25%

Nuclide GeLi .i

3. Particulates in gaseous releases: Total GeLi 125%

Nuclide GeLi

4. Liquid effluents Total GeLi i25%:

Nuclide GeLi

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, ' ' '1989tEFFLUENT SEMIANNUAL REPORT- REV. 1 PAGE 3-11.0 . BATCH RELEASES (LIQUID)- QTR: 01 '.QTR: 02 ,

.1.' 1 NUMBER OF BATCH RELEASES 3.40E+01 5.10E+01

'1.2 TOTAL TIME PERIOD (HRS) 5.31E+01 7.92E+01-1.3 MAXIMUM TIME PERIOD (HRS) 1.97E+00 2.12E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.56E+00 1.55E+00 1.5 MINIMUM TIME PERIOD (HRS) 2.00E-02 l'.27E+00 1~.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 6.01E+03: .6.57E+03-L l 2.0 BATCH RELEASES (GASEOUS) QTR: 01 .QTR:102 L 2.1 NUMBER OF BATCH RELEASES 6.00E+00 1.80E+01 2.2 TOTAL TIME PERIOD (HRS) 1.00E+01L 1.04E+02 i

2.3 MAXIMUM TIME PERIOD (HRS) 6.70E+00 1.93E+01 2.4 AVERAGE TIME PERIOD' (HRS) 1.67E+01 5.81E+00 '

2.5 MINIMUM TIME ~ PERIOD (HRS) 2.00E-02 5.28E-03 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- 0.00E+00-

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

cm 19893 EFFLUENT SEMIANNUAL REPORT- REV. 1 PAGEL4 TABLE : 1 A

i. GASEOUS EFFLUENTS -~ SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 5.0- FISSION AND ACTIVATION GASES t-

, - 5 . 11 ' TOTAL RELEASE (CI) 8.16E-02 1.29E+01 5.2 AVERAGE RELEASE RATE (UCI/SEC) 1.04E-02: 6.10E L 5.3 GAMMA DOSE (MRAD)- 1.02E-04~ 5.70E-03' 5.4 BETA DOSE (MRAD) 4.17E-04 1.61E-02 5.5 PERCENT OF GAMMA TECH SPEC (%) 1.02E-03 5.70E 5.6 . PERCENT OF BETA TECH SPEC (%) 2.09E-03 8.05E-02 6.0 IODINES Y.

6.1 TOTAL I-131 (CI) 6.74E-07 0.00E+00 6.2 -AVERAGE ~ RELEASE RATE (UCI/SEC) 8.58E-08 0.00E+00

7. 0 PARTICULATES 7.1 TOTAL RELEASE (CI) 1.71E-06 4.30E+06 7.2 AVERAGE RELEASE RATE (UCI/SEC) 2.18E-07 5.47E-07 8.0 TRITIUM

= 8.1 TOTAL' RELEASE (CI) 2.12E+01 2.79E+01' 8 '. 2 AVERAGE RELEASE RATE (UCI/SEC) 2.70E+00- 3.55E+00

' 9. 0 TOTAL' IODINE, PARTICULATE AND TRITIUM (UCI/SEC)' 2.70E+00 '3.55E+00 10.0 -DOSE (MREM) 3.83E-02 5.07E-02

. 11.0 PERCENT OF TECH SPEC (%) 2.55E-01 3.38E-01 12.0 GROSS ALPHA (CI) 1.75E-08 4.99E-08 1

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"1989? EFFLUENT SEMIANNUAL' REPORT REV. 1 PAGE 5- <

- TABLE.1C l

' GASEOUS EFFLUENTS - GROUND LEVEL RELEASES l 4 +

13'.0 FISSION-ANDfACTIVATION GASES 1

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

AR-41 CI 1.17E-02 KR-85 CI 1.45E-02 3.47E-02 KR-85M CI- 1.45E-05 3.28E-06 XE-131M CI 4.87E-04 7.14E-03 XE-133 CI- 1.25E+01 6.54E-02 3.38E-01 XE-133M - CI 8.47E-04 2.14E-03 '

XE-135: CI 3.98E-04 1.18E .

TOTAL CI 0.00E+00 1.25E+01 8.16E-02 3.95E-01 14.0 -IODINES CONTINUOUS MODE' BATCH MODE

NUCLIDE' UNITS- QTR: 01 QTR: 02 QTR: 01 QTR:-02 l

I-131 CI 6.74E-07 TOTAL. CI 6.74E-07 .0.00E+00 0.00E+00 0.00E+00 L15.0' PARTICULATES CONTINUOUS MODE BATCH MODE b NUCLIDE UNITS QTR: 01 QTR: 02 QTR: '01 QTR: 02 i CO-60 CI 1.30E-06 i

CS-137 CI 4.13E-07 SR-89 CI 2.63E-06 1.67E-06 TOTAL CI 1.71E-06 2.63E-06 0.00E+00 1.57E-06 L

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'1989: EFFLUENT-SEMIANNUAL REPORT 'REV. 1 PAGE 6" d ?TABLEi2A . , . .

4 LIQUID EFFLUENTS,- SUMMATION OF ALL' RELEASES QTR: 01- QTR: 02; _j i

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L16.01.' VOLUME [OF WASTE PRIOR TO DILUTION (LITERS) 4.04E+07; 4.21E+07 i s >17.0 LVOLUME OF DILUTION WATER (LITERS)~ 1.29E+11 7.95E+10 $

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,18. 0 - FISSIONLAND' ACTIVATION-PRODUCTS -i Q, .

-~18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI)- 1.12E-01 '4.14E-O'2 D t 18.2: AVERAGE DILUTED CONCENTRATION (UCI/ML) 8.68E 5.21E l l

c19.0 _ TRITIUM. *** SEE ATTACHED NOTE FOR ADDITIONAL

' TRITIUM DOSE' CALCULATIONS  :

19.1. TOTAL RELEASE (CI) 6.20E+01 1.05E+02; 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 4'.81E-07 1.32E 20.0 DISSOLVED'AND ENTRAINED GASES .;

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, 20.1 TOTAL RELEASE (CI) 5.11E-03 2.89E-021 '

20.2 . AVERAGE DILUTED CONCENTRATION-(UCI/ML) :3.96E-11 3.64E-103 q i

21.0' GROSS ALPHA (CI) 0.00E+00 0.00E+00

-22.0l TOTAL TRITIUM, FISSION AND ACTIVATION . 3

. PRODUCTS-(UCI/ML) 4.81E-07 1.32E-06 1

'23.0 TOTAL, BODY DOSE (MREM) 2.60E-04 -2.92E-04 24.0 CRITICAL' ORGAN '

!c j 24.1 DOSE-(MREM) 2.60E-04 9.82E-04 24.2. ORGAN TTL BODY GI TRACT 25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%) 8.67E-03 9.73E-03 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%) 8.67E-03 9.82E-03 i

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. 71989-EFFLUENT SEMIANNUAL REPORT REV. 1 PAGEs7- ]

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LTABLE 2A. ,

. LIQUID EFFLUENTS 2- _ SUMMATION OF'ALL_ RELEASES 1

'27.0. INDIVIDUAL LIQUID ~ EFFLUENT

  • CONTINUOUS MODE BATCH MODE i

NUCLIDE UNITS .QTR: 01 'QTR: 02 QTR: 01 QTR: 02 ,

l AG-110M- CI 3.27E-05 '6.48E-04  ;

CO-58 CI 2.30E-04 1.46E-03 t

CO-60 CI 1.26E-04 6.25E-04 t CR-51 CI 5.55E '

CS-134 CI 9.74E-08 CS-137- CI- 5.56E-07 FE-59 CI 4.07E-04 l'.69E-03  ;

FE-55 CI' 1.11E-01 3.43E-02 -

I-131 CI 2.96E-05 MN-54 CI 1.27E-06 4.00E-05 NB-95 -CI 3.10E-05 NB CI 9.11E-06 7.95E-06 SB-122 CI' 5.86E-06 2.99E-05 SB-124- CI 8'88E-05 8.05E-04 SB-125 CI 2.44E '4.51E-04 SC-47 CI 2.48E-06 1.16E-04 SN-113 CI 1.22E-04 6~.05E-04 h

SR-92 CI 1.50E-06 1

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.ZR-97 CI 6.52E-06 TOTAL CI 0.00E+00 0.00E+00 1.12E-01 4.14E-02 L

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[4 ' / 1989'EFFLUENTESEMIANNUAL' REPORT REV.>1' PAGE 8 2r u- . TABLE 2A (CONTINUED)

LIQUID EFFLUENTS -' SUMMATION Or ALL. RELEASES

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' 2 8 . 0 .' DISSOLVED'AND ENTRAINED GASES CONTINUOUS MODE BATCH MODE l-NUCLIDE ' UNITS QTR:-01 lQTR: 02 QTR: 01 QTR: 02 n

AR-41 CI 3.09E-06 KR-85M' CI 5.58E-06 XE-131M CI 6.28E i XE-133 CI 4.53E-03 2.80E-02 .!

l XE-133M CI 7.67E-05 1.85E-04 I XE-135 CI 5.01E-04 9. 5 7 E- 0 5 .

7 TOTAL CI 0.00E+00- 0.00E+00 5.11E-03 2.89E-02 j

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g ' ATTACHMENT TO THE 1989-EFFLUENT SEMIANNUAL REPORT Liquid Pathway Dose calculation-Quarters 1 and 2, 1989 Summary The total liquid doses to the critical receptor for the first and second quarters of'1989 are 0.0126 and 0.0340 mrem,Jrespectively.

These: doses are reported in this attachment to the semiannual; report.

Background

In' October, 1989 a.well water sample of a residence close.to PI.showed low. levels of tritium. Initial dose calculation results.showed estimated-liquid pathway doses a hundred_ times higher than those reported in past semiannual reports. These results indicated that a new! dose pathway should be considered.

Investigation into the cause of the tritium contamination led to the-assumption that the: flow of water is' f rom the- discharge canal downhill toward the Vermilion river. The resident's well draws from the-

! groundwater between the. canal and the Vermilion river.

ODCM Considerations The following-calculation is! independent of the ODCM. At this time no change will be made to the ODCM. Efforts are currently under way to determine if.the; tritium levels in the well can be reduced by physical

modifications to the discharge structures and/or adjustments to the-discharge-methods. Results of these efforts should be available~in 1990.and the problem will be eliminated or appropriate ODCM changes will be made.

Dose-Calculation Assumptions For the purpose of dose calculation, the dose-maximizing assumption was made that'the receptor's: concentration of tritium in body water and organic molecules is equal to the average concentration in'the discharge? canal. The dose conversion factor for this assumption is taken;from page 9-3 of NUREG/CR-3332. Its'value is 102 mrem / year per uCi/ liter of_ tritium in the_ body. When adjusted for the units

' reported for the discharge canal concentration, the dose conversion factor is 2.55E4 mrem / quarter per uCi/ml.

Discussion The' elevated tritium levels were found at the residence which is the critical. receptor (0.6 miles to the SSE of the site) for Prairie Island. Therefore, the dose calculated for waterborne tritium is added to the critical receptor's fish pathway dose. This

, overestimates the-dose because the tritium dose from eating fish is accounted for twice.

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  • Ithshould be noted:that'the total airborne dose-(99%'plus of which is '

Edue.to tritium) is1 greater than the total' waterborne tritium dose.  !

.Even though the newly identified pathway delivers additional tritium:

to the critical receptor it'is a: lower concentration than that already: i

'inLthe body:due to airborne exposure.

, Dose calculation Average Dose Diluted Whole Fish Total' Quarter Conversion X. Tritium = Body + Pathway = Liquid i

' Factor Concentration Dose Dose Dose w -(mrem / quarter (uCi/ml) (mrem) .'

(mrem) (mrem). ,

U per uCi/ml) '

1 2.55E4 4.81E 1.23E-2 2.72E-4 1.26E 2. 2.55E4 1.32E-6 ~3.37E-2 2.92E-4 3.40E-2 Dose Report

-LIQUID EFFLUENTS - SUMMATION OF WATERBORNE TRITIUM AND FISH PATHWAYS QTR: 01 QTR: 02. ;

' TOTAL BODY DOSE'(MREM) 1.26E-02 3.40E-02 F

! ' CRITICAL ORGAN DOSE'(MREM) l'.26E-02 '3.40E-02 l-

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' ORGAN TTL BODY TTL BODY ,

PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)' 4.20E-01 1.10E+00 PERCENTLOF CRITICAL ORGAN TECH SPEC LIMIT (%) 4.20E-01 1.10E+00 M

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