ML20141M512

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Effluent Semiannual Rept,920106-0705,Supplemental Info
ML20141M512
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 07/05/1992
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20141M514 List:
References
NUDOCS 9209010037
Download: ML20141M512 (16)
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Text

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  • 1992 Effluent Semiannual Report l Page 'l ci 8 j j Retention: Lifetime 1

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l EFFLUENT SEMIANNUAL REPORT i 06-JAN-92 THROUGH 05-JUL-92 SUPPLEMENTAL INFORMATION f i i l 1

j Facility: Prairie Island Nuclear Generating Plant

! Licensee: Northern States Power Company i License Numbers: DPR-42 & DPR-60 1

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i- A. Regulatory Limits i

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} 1. Liquid Effluents:

a. The dose or dose commi tn e n t to an individual-from radioactive i materials in liquid effluents-released from the site shall be

/

limited to:

n for the quarter 3.0 mrem to the total body f

, 10.0 mrem to any organ I

for the year 6.0 mrem to the total body i

i 20.0 mrem to any organ i

j 2. Gaseous Effluents:

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

i

noble gases 4500 mrem / year total body

= 43000 mrem / year. skin l I-131, H-3, LLP .41500 mrem / year to any organ 4

! b. The dose due to radioactive gaseous effluent shall be limi ted to:

l noble gases 410 mrad / quarter gamma 420_ mrad / quarter beta (20 mead / year gamma 440 mrad / year beta i

I-131, H-3, LLP 415 mrem / quarter to any organ

430 mrer/ year to any organ
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.l'992 EFFI.UENT SEMIANNUAL REPORT REV. O PAGE 2 B. Maximum Permissible concentration

1. Fir,sion and activation gases in gaseous releasect 8

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

2. Iodine and particulates with halflives greater than 1 8 days in gaseous releases:

1.0 CFR 20, Appendix B, Table 2, Colunin 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 and entrained gases

~2'0E-04 uCi/ml Total Activity C. Average Energy Not applicable to Prairie Island regulatory limits.

D. Mearurements and approximations of total activity

1. rission and activation gases Total GeLi i25%

in gaseous releasect Nuclide GeLi

2. Iodines in gaseous releasess. Total gel 1 125%

Nuclide GeLi

3. Particulates in gaseous releases: Total GeLi 125%

Nuclide GeLi

4. Liquid effluents Total GeLi i25%

Nuclide- GeLi e

s E. Manual Revisions

1. Offsite Dose Calculations Manual latest Revision number: 12 Revision date  : 30 JUN 91-
2. Process Control Program Manual lateot Revision number: 4 Revision date  : 23-APR-91 l

- _. . . .. .. . . _ _ - _ _ _ a

1992 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 3 1.0 BATCH RELEASES (LIQUID) QTR: 01 QTR: 02 1.1 NUMBER OF BATCH RELEASES 4.40E+01 1.60E+01 1.2 TOTAL TIME PERIOD (HRS) 6.67E+01 5.97E+01 1.3 MAXIMUM TIME PERIOD (HRS) 2.33E+00 7.75E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.52E+00 3.73E+00 1.5 MINIMUM TIME PERIOD (MRS) 1.22E+00 1.17E+00 1.6 kVERAGE MISSISSIPPI RIVER FLOW (CFS) 1.42E+04 3.49E+04 2.0 BATCH RELEASES (GASEOUS) QTR: 01 QTR: 02 2.1 NUMBER OF BATCH RELEASES 1.80E+01 1.00E+00 2.2 TOTAL TIME PERIOD (HRS) 1.93E+02 2.20E+00 2.3 -MAXIMUM TIME PERIOD (HRS) 2.40E+01 2.20E+00 2.4 AVERAGE TIME PERIOD (HRS) 1.07E+01 2.20E+00 2.5 '7NIMUM TIME PERIOD (HRS) 3.30E-01 2.20E+00 s

3.0 ABNORMAL RELEASES (LIQUID) I QTR: 01 QTR: 02 -

3.1 NUMBER OF RELEASES 1.00E+00 -0.00E+00 3.2 TOTAL ACTIVITY RELEASED (CI) 1.38E-03 0.00E+00 3.3 ' TOTAL TRITIUt. RELEASED (CI) 9.46E 0.00E+00

~

4.0 ABNORMAL RELEASES (GASEOUS) QTR: 01 QTR: 02 4.1 NUMBER.OP RELEASES 0.00E+00 0.00E+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00

.1992 EFFLUENT SEMIANNUAL REPORT REV. O 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)- 1.03E-01 4.40E+00 5.2 AVERAGE RELEASE RATE (UCI/SEC) 1.31E-02 5.60E-01 5.3 GAMMA DOSE (MRAD) 1.52E-05 1.59E-03 5.4 BETA DOSE (MRAD) 2.25E-04 6.59E-OS 5.5 PERCENT OF GAMMA TECH SPEC (%) 1.52E-04 1.59E-02 5.6 PERCENT OF BETA TECH SPEC (1) 1.13E-03 3.30E-02 6.0 IODINES 6.1 TOTAL I-131 (CI) 9.70E-07 0.00E+00 6.2 AVERAGE RELEASE RATE (UCI/SEC) 1.23E-07 0.00E+00 7.0 PARTICULATES 7.1 TOTAL RELEASE (CI) 3.07E-06 2.33E-05 7.2 AVERAGE RELEASE RATE (UCI/SEC) 3.91E-07 2.96E-06 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 8.22E+00 8.44E+00 8.2 AVERAGE RELEASE R..TE (UCI/SEC) 1.05E+00 1.07E+00 9.0 TOTAL. IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 1.05E+00 1.07E+00 10.0 DOSE (MREM) 1.48E-02 1.52E-02 i

11.0 PERCENT OF TECH SPEC (%) 9.90E-02. 1.01E-01 12.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00

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. 1992 ErrLUENT SEMIANNUAL REPORT REV. O TABLE 1C GASEOUS EFTLUENTS - GROUND LEVEL RELEASES 13.0 FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 KR-85 CI 8.87E-02 2.33E-01 XE-133 CI 7.51E-03 4.17E+00 7.25E-03 2.64E-04 XE-135' CI 1.40E-05 TOTAL CI 9.62E-02 4.17E+00 7.26E-03 2.33E-01 14.0 IODINES CONTINUOUS MODE BATCH MODE MUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 I-131 CI 9.70E-07 TOTAL CI 9.70E-07 0.00E+00 0.00E+00 0.00E+00 15.0 PARTICULATES CONTINUOUS MODE BATCH MODE NUCLIDE Ut;ITS OTR: 01 QTR: 02 QTR: 01 QTR: 02 BR-82 CI 3.07E-06' 6.72E-10 4 FS-97 CI 2.33E-05 TOTAL CI 3.07E-06 2.33E-05 6.72E-10 0.00E+00 3-

1 i .

1992 EFFLUENT SEMIANh0Al REPORT REV. O PAGE 6 J TABLE 2A j LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES l

i I

3 QTR: 01 QTR 02 f

I l

. 16.0 VOLUME Or WASTE PRIOR TO DILUTION (LITERS) 4.21E+07 4.12E+07 1

1 8

17.0 VOLUME Of DILUTION WATER (LITERS) 1.57E+11 8.70E+10  ;

l l 18.0 FISSION AND ACTIVATION PRODUCTS

18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 1.32E-01 9.78E-02 18.2 AVERAFE DILUTED CONCENTRATION (UCI/ML) 8.41E-10 1.12E-09 '

i- 19.0 TRITIUM 1

4 19.1 TOTAL RELEASE (CI) 1.1 E+02 1.05E+02

! 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 7.52E-07 1.21E-06 i

l 20.0 DISSOLVED AND ENTRAINED GASES

20.1 TOTAL RELEASE (CI) 1.90E-03 1.52E-03 l 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.21E-11 1.75E-11 i

21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 7.52E-07 1.21E-06 23.0 TOTAL BODY DOSE (MREM) 1.53E-03 4.09E-04 i

I 24.0 CRITICAL ORGAN 24.1 DOSE (ML'M) 1.53E-03 1.73E-03 1

24.2 ORGAN TTL BODY GI TRACT 4

25.0 PERCENT 0F TOTAL BODY TECH SPEC LIMIT (%) 5.10E-02 1.36E-02

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26.0 PERCENT OF LRITICAL ORGAN TECH SPEC LIMIT (%) 5.10E-02 1.73E-02 i

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) 1h92 E'FFLU.ENT SEMIANNUAL REPORT REV. O PAGE 7 I TABLE 24  ;

LIQUID 'FLUENTS - SUMMATION Or ALL RELEASES l 27.0 INDIVIDUAL LIQUID E . UENT i

I COMTINUOUS MODE BATCH MODE

, - .i

. HUCLIDE UNITS OTR: 01 QTR 02 QTR: 01 QTR: 02 7

l AG-110M CI 1.68E-02 1.32E-02

' BE-7 CI 1.15E-03 4.14E-05 Co-57 at 6.88E-05 1.10E-04 l

i Co-58 CI 2.82E-02 - 3.18E-02 Co-60 CI 1.19E-02 6.S2E-03 i

CR-51 CI 6.44E-03 9.85E-04 9

CS-134 CI 6.54E-06 3.44E-06 i

CS-137 CI 2.20E-04

{ CU-64 CI 1.56E-03 FE-55 CI 2.42E-03. 3.05E-02 3.44E-02 i -

FE-50 CI 6.63E-03 1.55E-03 l I-133 CI 4.81E-06 i I-134 CI 4.97E-06.

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I LA-140 CI 7.0dE-06  ;

i MN-54 CI 7.34E-04 ' 3.02E-04

- NA-24 CI 1.71E-05 NB-95 CI' 1.45E-04 2.00E-05 NB-97 CI 6.37E-06'
RH-105 CI 3.32E 05 SB-122 CI 2.51E-03 i

SB-124 CI 1.29E-02 4.74E-03 SB-125 CI ' 1.03E-02 4.75E-03 SB-12f CI 6.25E-05 t --

l CONTINUED

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19'92 ErPLUENT SEMIANNUAL REPORT REV. O PAGE 8 1

TABLE 2A i LIQUID ErrLUENTS - SUMMATION OF ALL RELEASES  ;

f 27.0 INDIVIDUAL LIQUID EFFLUENT (CONTINUED) .

SC-47 CI 4.28E-04 1.29E-05 ,

SN-113 CI 1.30E-03 5.67E-04 SR-92 CI 1.22E-05 W-187 CI 1.58E-05 4.78E-06 Y-93 CI 3.42E-05 ZN-65 CI 1.53E-05 i

ZR-95 CI 1.65E-04 8.65E-05 ZR-97 CI 3.88E-06 TOTAL CI 2.42E=03 0.00E+00 1.30E-01 9.78E-02 i t-28.0 DISEDLVED AND ENTRAINED GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR 01 QTR: 02 l

! -XE-133 CI 1.88E-03 1.52E-03 XE-135 CI 2.15E-05 TOTAL CI 0.00E+00 0.00E+00. 1.90E-03 1.52E-03 V -

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'PINGP 753, Rev. 3 Page l'of 6

, Retention: Lifetime PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/92 to 7/1/92 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1: Solid Waste and Irradiated Fuel Shipments 1.

Solid Waste Total Volumes and Total Curie Quantities:

l l

l l l Container l l l L Disposal l l Type of Waste l' Units l

i Totals l Volumec l (List)

A. Resins 3 ll -ft 1 L l i l

l Ci l l '

l l l

I I I I I

I B. Dry-Compacted 3 I

I 1

ft  ;

1 l

I I l -Ci I

l l l- 1 l l I I I I l i I I i

1-C.- Non-Compacted 3 l ft 10.5 l 96 cf I I I I I l l 0,014 I l 1 I

I I . Ci I I I i 1 I I I l

D. Filter Media 3

_I ft  ; -g g i I I I I l l' -Ci l i l I l l l l I l l l- I l

1 S. Spent Fuel 3 l ft g  ;

I l- 1 I I l l. Ci i l l l l l l l l i l i I I l I- 1 I IDM

PINGP 753, Rev. 3 Page 2 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/92 to 7/1/92 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I: Solid Waste and Irradiated Fuel Shipments / Continued)

2. Principal Radionuclide Composition by Type of Vaste:

Percent TYPE (From Page 1) Nuclide Abundance c co-60 41.4 NI-63 27.5 FE-55 18.2 CS-137 -3.3 C0-58 2.5 MN-54 2.2

_SB-125 1.5 NE-95 1.0

__AG-110M 0.7 t

  • = Inferred - Not Measured on Site IBM

PINCP 753, Rev. 3 Page 3 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/92 to 7/1/92 NORTHERN STATES POWER License No. DPR 42 ,

SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Tab): I: Solid Waste and Irradiated Fuel Shipments (Continued)

2. Principal Radionuclide Composition by Type of Waste (Continuation):

Percent TYPE (From Page 1) Nuclide Abundance I

  • = Inferred - Not Measured on Site IBM

PINGP 753, Rev. 3 Page 4 PRA1RIE ISLANE WUCLEAR GFNERATING PLANT Period: 1, l92 to 7/1/92 NORTHERN STATES POWER License F6. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1: Solid Waste and Irradiated Fuel Shipments (Continued)

3. Solid Waste Disposition:

Number of Shipments Mode Destination

._J TRUCK OAK RIDGE. TENNESSEE

4. Irradiated Fuel Shipments:

Number of Shipments Mode Destination 0

IBM

. _ . . - ~ . _ _ _ _ _ _ . . _ _ . . _ _ _ _ _ . ____ _ _ . . _ _

l

] PINCP 753, Rev. 3  !

Page 5 i

i PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/92 to 7/1/92

, NORTHERN STATES POWER License No. DPR-42 i

1 SOLID RADIOACTIVE VASTE DISPOSAL SEMI-ANNUAL REPORT l

Table I: Solid Waste and Irradiated Fuel Shipments (Continued)

! 5. Shipping Container and Solidification Method:  !

t i l Disposal

! No. Volume Activity Type of Container Solidif.

4 (Ft3) (C1) Vaste Code code ,

92-02 10.5 0.014 C _ L N/A i

l I  !

i i _

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1 f, .

t 4 i i

, TOTALS 1 10.5 0.014 CONTAINER CODES: L = LSA

. ( Shipmen t'_ Type ) A = Type A

, -8 =. Type B Q =-Highway Route Controlled _ Quantity

SOLIDIFICATION CODES
C = Cement-TYPES OF WASTE: A = Resins l

B = Dry Compacted C = Non-Compacted D = Filter Media >.

S = Spent Fuel r

IBM a--.--_-__-..-,,-........-....~.--._.-.

f PINGP 753, Rev. 3 Page 6 of 6 PRAIRIE ISLAND NUCLEAR GENERATING PLA!TT Period: 1/1/92 to 7/1/92

!ORTHERN STATES PCEER License No. DPR-42 SOLID RADIOACIVE WASTE DISPOSAL SEMI-ANWAL REPORT Table II: Process Control Program Changes

Title:

Process Control Program for Solidification / Dewatering of Radioactive Waste Prom Liquid Systems.

Current Revision Number: 4 Effective Date: 05/23/91 TOTE: If the effective date of the PCP is within the teriod covered by this report, then a description and justification of the changes to the PCP is required (T.S. 6.7.A.4). Attach the sidelined pages-to this report.

Changes / Justification:

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3 Sub-)cct: Northern States Power, Prairie Island, Abnormal Liquid Release first quarter 1992 Normal radioact'"e liquid vaste is released to the river through an unr'_ t ground eight and twelve inch cast iron pipe to the dischar p canal. The cast iron pipe connects to a twelve P inch poli propylene pipe which extends to near the sluice gates at the end of the discharge snal. The r a c' 7, s t e discharge pipe was designed to trans'ec liquid radioactive waste from the auxiliary building to th< discharge canal where it is combined with cooling towet olowdown wat>r.

P Tritium was detected in or.-nite test wel s located southwest of the radwaste pipe. Based on the anticipated groundwater flow direction.,

a hydrostatic test of the underground portion of the quid radwaste discharge pipe was conducted or April 30, 1992. This test showed the pipe to be ler.ki'ig slightly.

Immediately after the hydro, the liquid waste discharge pipe was isolated and all subsequent radioactive releases were cupleted to the dischargt. canal vir Snorary, above-ground discharge line. Some accessi! of the old discharge y pipe we re excavated ar.3 cam' ed 4kage point was found.

Nork is in progress to int i anderground discharge ,,

pipe.

Without confirming that a leak existed under release conditions, 1* is our assumption that 2 inik existed in r,ome section of the pipe. Given the normal discharge

.:l ow rate (less than 100 gpm) whien reen ts in the pipe beinc en'* partialli filled, the release to the soil bas bee- - n;m vatively calculated at less than 0.5 gallons ,

per m aute. The leak would have occurred in the unsaturated zone above the groundwater and flowed down s unti) it is entrained in the groundwater. All C radit.,nuclides except for tritium would have been removed soon after the liquid enters the soil. Soil is an axcellent filter for innic molecules as well as particulate material. No radionuclides other than trit!um (and naturally-occurring uranium decay products) have been found in the test wells.

The released radioactivity would form a plume in the groundwater. This plume would have been diluted as it fanned out in the crossflow direction and as it asved in the direction of flow. Radioactive decay also would serve to reduce the concentration. Groundwater flow estimates i.ndicated tha t a release may take from 10 to 70 years to

6 Page 2 3 travel from the Mississippi River to the-well distances in the direction of the Vermillion River. This would j translate into significant dilution as well as decay for

! tritium whi:h has a radioactive half-life of 12.3. years.

Sampling of surface and groundwater sources by the Radiological and Environmental Monitoring Program (REMP) l identified some areas on site which may have been affected by

the discharge pipe leak. Sample results.have shown tritium

, slightly higher than normal background levels. Besides J tritium, no othcr icotopes other than normal background nuclides have been detected. Test well P-10 showed the

highest tritium concentrations at 1.5E-6 pCi/ml. The most recent' results are about 6.5E-07 pCi/r- The EPA drinking water limit is 2E-5 vCi/ml. It is possihte that the activity

! seen in P-10 is from past releases co the head of the i discharge canal before we added the polypropylene extension to the discharge line.

For the semi-annual period of 06-Jan-92 to 05-Jul-92, there _

were 47 liquid waste discharges up until 30-Apr-92. The

duration of these releases totaled-71.45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />. Assuming the
leak existed throughout the entire reporting. period at the 4

conservative leak rate of 0.5 gpm, a-total voluat of 8.12E+06 j mis would have been released to the soil in the ares i surrounding the leak. Using the concentration and nuclide mix of the waste tanks released during the period, a total i- activity (excluding tritium) of 1.38E+03 Ci and 9.46E+05 vCi of tritium would have been released. This activity has-been reported as a single abnormal release in the first quacter of-4 the semi-annual report.

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