ML20090C191

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Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1991
ML20090C191
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 12/31/1991
From: Fey F
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9203040301
Download: ML20090C191 (27)
v • d • e


Text

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Northem States Power Company 414 Nicollet Mall Minneapohs, Minnesota 55401 1927 Telephone (612) 330 5500 February 26, 1992 Prairie Island Technical Specification TS6.7A S&6 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Prairie Island Nuclear Generating Plant Docket No. 50-282 License No. DPR-42 Docket No. 50-306 License No. DPR-60 Effluent and Waste Disposal Semiannual Report q

LoJM yly 1, 1991 throuc1h December 31, 1991 In accordance with the Prairie Island Technical Specifications, Appendix A to Operating License DPR-42 and DPR-60, we are submitting one copy of the Effluent and Waste Disposal Semiannual Report, covering the last half year of 1991.

l Analysis for isotopes Sr-69, Sr-90 and Fe-55 for the fourth quarter were not completed in time to be included with this report, therefore, the third quarter values are used as an estimate for the fourth quarter values. The analyses results are not expected to significantly change the computed of f-site doses, and will be included with the next semiannual report.

Enclosed with this report is an amended Effluent and Waste Disposal Semiannual Report for the first half of 1991 which includes the previously omitted second quarter analyses results of Sr-89, Sr-90 and Fe-55.

The Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) Manual are not attached since they remained unchanged during the reporting period, s ..

N F.L. Fey, Jr., Manager Nuclear Radiological Services j Attachment 9203040301 911231 2 ADOCK 0500

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PDR R

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TRANSMITTAL MANIFEST NORTHERN STATES POWER COMPANY NUCLEAR GENERATION DEPARTMENT PRAIRIE ISLAND NUCLEAR GENERATING PLANT Effluent and Wasto Disposal Senlannual Report for July 1. 1991 throuch December 31. 1991 MANIFEST DATE: FEBRUARY 27, 1992 USNRC 4 ANI Library 1 Regional Admin III Fluor Daniels 3 NRR Project Manager J Gelston DCD T Synder Resident Inspector Corporate Library Shaw Pittman Potts &

K M Beadell 1 Trowbridge 1 D A Schuelke 1 J Silberg P H-Kamman 1 Westinghouse Electric 2 PI Site General Mgr. 1 G Goldberg Monticello Plant Mgr. 1 D Sommers l ERAD Dept. 1 Safety Audit Committee 10 Attn: Records Clerk K J Albrecht Communications Department 1 A B Cutter NRS File 1 F W Hartley NSS File 1 D M Musolf MDH 1 G H Neils Attn: Comm. of Health T M Parker M B Sellman C R Steinhardt J A Thie Secretary Manifest File l

l l . . _ _

19,91 Eftluent Semiannual Report REV. 0 Page: 1 of 8

-Retention: Lifetime i

EFFLUENT SEMIANNUAL REPORT 01-JUL-91 THROUGH 05-JAN-92 SUPPLEMENTAL INFORMATION Facility: Prairie Island Nuclear Generating Plant Licensee: Northern States Power Company License Numbers: DPR-42 & DPR-60 A. Regulatory Limits

( 1. Liquid Effluents:

a. The dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site shall be limited to:

for the quarter 3.0 mrem to the total body 10.0 mrem to any organ for the year 6.0 mrem to the total body 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 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 mrem / quarter to any organ 430 mrem / year to any organ i

19,91. EFFLUENT SEMZANNUAL REPORT REV. O PAGE 2 B. Maximum Permissible Concentration

1. Fission and activation 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:

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 and entrained gases:

2.0E-04 uCi/ml Total Activity C. Average Energy Not applicable to Prairie Island regulatory limits.

D. Measurements and approximations of total activity

1. Fission and activation gases Total GeLi 25%

in' gaseous releases: Nuclide GeLi

2. Iodines in gaseous releases: Total GeLi 25%

Nuclide GeLi

3. Particulates in gaseous releases: Total GeLi 25%

Nuclide GeLi

4. Liquid effluents Total GeLi 25%

Nuclide GeLi E. Manual Revisions 12

1. Offsite Dose Calculations Manual latest Revision number:

Revision.date  : 30-JUN-91

2. Process Control Program Manual latest Revision number: 4 Revision date  : 23-APR-91 i

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PAGE 3 1991 EFFLUENT. SEMIANNUAL REPORT, REV. O

-1. 0 BATCH RELEASES (LIQUID) QTR: 03 QTR: 04 1.1 NUMBER OF BATCH RELEASES 2.90E+01 2.80E+01 i (HRS) 4.82E+01 4.21E+01 1.2 TOTAL TIME-PERIOD 1.3 MAXIMUM TIME PERIOD (HRS) 2.75E+00 1.83E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.66E+00 1.50E+00 MINIMUM TIME PERIOD (HRS) 9.50E-01 1.27E+00 1.5 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 2.70E+04 1.98E+04-

.2.0 BATCH RELEASES (GASEOUS) QTR: 03 QTR: 04 2.1 NUMBER OF' BATCH RELEASES 5.00E+00 0.00E+00 2.2 TOTAL TIME PERIOD (HRS) 4.30E+00 0.00E+00 2.3 MAXIMUM TIME PERIOD (HRS) 3.80E+00 0.00E+00 2.4 AVERAGE TIME PERIOD (HRS) 8.60E-01 0.00E+00 2.5 MINIMUM TIME PERIOD (HRS) 2.00E-02 0.00E+00 3.0 ABNCRMAL RELEASES (LIQUID) QTR: 03 'OTR: 04 3.1-. NUMBER OF RELEASES 0.00E+00 0.00E+00 3.2 TOTAL ACTIVITY. RELEASED (CI) 0.00E+00 0.00E+00 13 . 3 TOTAL TRITIUM RELEASED (CI)- 0.00E+00 0.00E+00

(

4.0 . ABNORMAL RELEASES (GASEOUS) QTR: 03 QTR: 04

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4 ' 1 . NUMBER OF RELEASES 0.00E400 0.00E+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 l

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1991 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 4 ,

. TABLE 1A

. GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 03 QTR: 04 5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 2.19E-01 0.00E+00 1 5.2 AVERAGE RELEASE RATE (UCI/SEC) 2.78E-02 0.00E+00 5.3 GAMMA DOSE (MRAD) 1.70E-05 0.00E+00 I 5.4 BETA DOSE (MRAD) 1.78E-03 0.00E+00 <

5.5 PERCENT OF GAMMA TECH SPEC (%) 1.70E-04 0.00E+00 5.6 PERCENT OF BETA TECH SPEC (%) 8.90E-03 0.00E+00 16 . 0 IODINES 6.1 TOTAL I-131 (CI) 4.59E-06 0.00E+00 6.2 AVERAGE RELEASE RATE (UCI/SEC) 5.84E-07 0.00EA00 7.0 PARTICULATES 7.1 TOTAL RELEASE (CI) 3.90E-07 0.00E+00 7.2 AVERAGE RELEASE RATE (UCI/SEC) 4.96E-08 0.00E+00 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 1.83E+01 1.35E+01 8.2 AVERAGE RELEASE RATE (UCI/SEC) 2.33E+00 1.59E+00 9.0 TOTAL-IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 2.33E+00 1.59E+00 10.0 DOSE (MREM) 3.34E-02 2.43E-02 11.0 PERCENT OF TECH SPEC (%) 2.23E-01 1.62E-01

'12.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 l.

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REV. O PAGE 5-

, 1991 EFFLUENT SEMIANNUAL REPORT TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 13.0 FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 KR-85 CI 2.18E-01 XE-133 CI 9.27E-04 TOTAL CI 0.00E+00 0.00E+00 2.19E-01 0.00E+00 14.0 IODINES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 I-131 CI 4.59E-06 TOTAL CI 4.59E-06 0.00E+00 0.00E+00 0.00E+00 15.0 PARTICULATES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 -

CS-134 CI 1.58E-07 CS-137 CI 2.32E-07 TOTAL CI 0.00E+00 0.00E+00 3.90E-07 0.00E+00

'o mm i ii i a us si h ii . ..

REV. O. PAGE 6 19.h,1EFFLUENTSEMIANNUALREPORT TABLE 2A

-LIQUID EFFLUENTE - SUMMATION OF ALL RELEASES QTR: 03 QTR: 04 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 3.25E+07 4.23E+07 16.0 2.65E+11 1.90E+11 17.0 VOLUME OF. DILUTION WATER (LITERS) 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 4.13E-02 3.12E-02 E18.2 AVERAGE DILUTED CONCENTRATION (UCA/ML) 1.56E-10 1.64E-10 19.0 TRITIUM 19.1 TOTAL RELEASE (CI) 1.62E+02 1.56E+02 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 6.11E-07 8.21E-07

.20.0 DISSOLVED AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI) 2.'15E 9.23E-04 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 8.11E-12 4.86E-12 21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 6.11E-07 8.21E-07 23.0 TOTAL BODY DOSE (MREM) 5.45E-04 5.18E-04.

24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 5.45E-04 5.18E-04 24.2 ORGAN TTL BODY TTL BODY L

25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%) 1.82E-02 1.73E-02 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%) 1.82E-02 1.73E-02 l

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,' 9 1,,91 EFFLUENT SEMIANNUAL REPORT' REV. O 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 3.60E-06 AG-110M CI 2.42E-02 1.57E-02~

BE-7 CI 1.95E-04 1.10E-03 CO-57 CI 5.90E-06 CO-58 CI 9.50E-04 1.12E-03 CO-60 CI 7.?8E-04 3.13E-03 CR-51 CI- 2.05E-03 2.12E-04 f

CS-134 CI 8.98E-06 8.54E-06 CS-137 CI 3.46E-05 2.70E-05 FE-55 CI 3.17E-03 8.09E-03 6.34E-03 FE-59 CI 1.71E-04 2.68E-04 I-131 CI 4.54E-06 LA-140 CI 6.67E-06 MN-54 CI 5.41E-06 1.55E-04 NB-97 CI 4.61E-06 SC-47 CI 1.45E-05 3.89E-05 SB-124 CI 4.75E-04 2.80E-04 SB-125 CI 8.52E-04 2.20E-03 SN-113 CI 3.23E-04 4.22E-04 SR-92 CI 5.44E-06 W-187 CI 9.09E-06

[

ZR-95 CI 6.25E-05 TOTAL i CI 3.17E-03 0.00E+00 3.81E-02 3.12E-02 .1 I

REV. O PAGE 8 l'9'91 EFFLUENT SEMIANNUAL REPORT TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 28.0 DISSOLVED AND ENTRAINED GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 KR-85 CI l 2.31E-04 XE-133 CI 1.91E-03 9.03E-04 XE-135. CI 8.56E-06 1.99E-05

' TOTAL CI 0.00E+00 0.00E+00 2.15E-03 9.23E-04

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- 'PINGP 753, Rev. 3 Page 1 of 6 Retention: Lifetime i

PRAIRIE ISLAND NUCLEAR GENERATING PLG'T Period: 7-1-91 to 12-31-9 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSA' 'EMI-ANNUAL REPORT Table I: Solid Waste and Irradiated Fuel Shipments

1. Solid Waste Total Volumes and Total Curie Quantities:

l l l l Container I l l l l Disposal l l Type of Waste i Units l Totals l Volumes l l (List) I 3

l A. Resins I ft l1052.3 1 183.3 l 1 I I I I l l Ci I 180.088 l 135.8 I I I I I I I I I I I I I 3

B. Dry-Compacted l ft 12572.5 1 7.5 I I I I I i l l Ci _l 8.197 l l l l 1 I I I I I I I I I I I I I 3

I C. Non-Compacted I ft l 270.6 I 96 I I l l l I l l Ci I .472 l l l 1 1 I I l l I I I I I I i i l I I 3

l D. Filter Media l ft l l l l I I I I l l Ci l l l i l l l l I I I I I I I 3

S. Spent Fuel I ft  ; l 1 I I I I l l Ci l l l l l l l I I I I I I I I I I I IBM

' PINGP 753, Rev. 3 Page 2 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period : 7-1-91 to 12-31-9:

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 Waste:

Percent TYPE (From Page 1) Nuclide Abundance A CO-60 40.6 NI-63 28.5 CO-58 *" 18.6 l CS-137 5.5

  • = Inferred - Not Measured on Site IBM

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', " PINGP 753, Rev.

~

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-91 to 12-31-9 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL-REPORT Table 1: Solid Waste and Irradiated Fuel-Shipments (Continued)

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

Percent TYPE (From Page 1) Nuclide Abundance C

CS-137 22.6 C-14 21.3 CA-134 16,6 CO-60 1.6

l i

  • = Inferred - Not Measured on Site IBM

PINGP 753, Rev. 3 Page 4 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period : 7-1-91 to 12-31-9:

NORTHERN STATES POWER License No. DPR-67 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I: Solid Waste and Irradiated Fuel Shipments (Continued)

3. Solid Waste Disposition:

Number of Shipments Mode Destination ..

10 Truck Richland, WA 2 Truck Oak Ridge, TN 1 Truck Barnwell. SC

4. Irradiated Fuel Shipments:

Number of Shipments Mode Destination 4

IBM

PINGP 753, Rev. 3 j Page 5 J PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-91 to 12-31-9

' NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I: Solid Waste and Irradiated Fuel Shipments (Continued)

5. Shipping Container and Solidification Method:

, Disposal i

No. Volume Activity Type of Container Solidif.

(Ft3) (Ci) Waste code Code 91-09 153.8 0.363 c L N/A 91-10 116.8 0.109 C L N/A 91-20 510.0 1.439 R L N/A 91 510.0 2_s67 R L N/A 91-23 193_3 3.160 A L N/A 91-25 1R3.1 1.741 A L N/A 91-22 510.0  ? 3ns B L N/A 91-27 193_3 1.374 A L N/A 91-29 193_3 0.966 A L N/A 91-24 510.0 0.970 'B L N/A 91-26 532.s 0.916 B L N/A 91-29 1R3.3 3.528 A L N/A 91-30 las.R 169.314 A L N/A TOTALS 13 3895.4 188.756 l CONTAINER CODES: L = LSA ji (Shipment Type) A = Type ~A l

B = Type B

! Q = Highway Route Controlled Quantity SOLIDIFICATION CODES: C = Cement TYPES OF WASTE: A = Resins B = Dry Compacted L C = Non-Compacted D = Filter Media S = Spent Fuel IBM

4 PINGP 753, Rev. 3 Page 6 of 6 PRAIRIE ISLAND NUCLEAR GENERATING PLA!Tf Period: 7-1-91 to 12-31-91 IDRTHERN STATES POh'ER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table II: Process Control Program Changes

Title:

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

Current Revision Number: 4 Effective Date: 5-23-91 TOTE: If the effective date of the PCP is within the period 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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1991 Effluent Semiannual Report REV. 1 P' age 1 of 8 Retention: Lifetime EFFLUENT SEMIANNUAL REPORT 30-DEC-90 THROUGH 30-JUN-91 SUPPLEMENTAL INFORMATION Facility: Prairie Island Nuclear Generating Plant Licensee: Northern States Power Company License Numbers: DPR-42 & DPR-60 A. Regulatory-Limits

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

for the quarter 3.0 mrem to the total body 10.0 mrem to any organ for the year 6.0 mrem to the total body 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 (1500 mrem / year to any organ

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

noble gases 410 mrad / quarter gamma l 420 mrad / quarter beta l

420 mrad / year gamma 440 mrad / year beta l

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

REV. 1 PAGE 2 19 1 EFFLUENT SEMIANNUAL REPORT ~

B. Maximum Permissible Concentration

1. Fission and activation 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:

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 and entrained gases:

L 2.0E-04 uCi/ml Total Activity C. Average Energy l

f Not applicable to Prairie Island regulatory limits.

D. Measurements and approximations of total activity

1. Fission and activation gases Total- GeLi 25%

in gaseous releases: Nuclide GeLi

.2. Iodines in gaseous releases: Total GeLi 25%

Nuclide GeLi

3. Particulates-in gaseous releases: Total GeLi 125%

Nuclide GeLi

4. Liquid effluents Total GeLi 125%

Nuclide GeLi E.- Manual Revisions 12

l. Offsite Dose Calculations Manual latest Revision number:

Revision date  : 30-JUN-91

2. Process Control Program Manual latest Revision number: 4 Revision date  : 23-APR-91 l

l l

1 PAGE 3 1991-EFFLUENT SEMIANNUAL REPORT REV. 1 1.0 . BATCH RELEASES (LIQUID)

QTR: 01 QTR: 02 1.1 NUMBER OF BATCH RELEASES 3.00E+01 6.90E+01 1.2 TOTAL TIME PERIOD (HRS) 4.42E+01 1.19E+02 1.3 MAXIMUM TIME PERIOD (HRS) 2.00E+00 3.58E+00 1.4 AVERAGE TIME PERIOD (HRS)- 1.47E+00 1.72E+00 1.5 MINIMUM TIME PERIOD (HRS) 4.20E-01 1.17E+00 1.6 AVERAGE MTSSISSIPPI RIVER FLOW (CFS) .9.21E+03 4.14E+04 L

1 I

2.0 BATCH RELEASES (GASEOUS) QTR: 01 'QTR: 02 2.1 NUMBER OF BATCH RELEASES 3.00E+00 1.80E+01 2.2 TOTAL TIME PERIOD (HRS) 1.40E+00 1.37E+02 2.3 MAXIMUM TIME PERIOD (HRS) 1~.20E+00 1.99E+01 2.4 AVERAGE TIME PERIOD (HRS) 4.67E-01 7.60E+00 2.5 MINIMUM TIME PERIOD (HRS) 6.00E-02 1.00E-01 l-3.0 ABNORMAL RELEASES (LIQUID) QTR: 01 QTR: 02 3.1 : NUMBER OF RELEASES 0.00E+00 0.00E+00 l

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

, 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 RELEASES 0.00E+00 0.00E+00 L 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00EF00 0.00E+00

REV. 1 PAGE 4 1991 EFFLUENT SEMIANNUAL REPORT TABLE 1A I GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES OTR: 01 QTR: 02 5.0 FISSION AND ACTIVATION GASES 2.13E-01 5.56E+01 5.1 TOTAL RELEASE (CI) _

2.71E-02 7.07E+00 5.2 AVERAGE RELEASE RATE (UCI/SEC) .

8.05E-05 2.24E-02 5.3 GAMMA DOSE (MRAD) 2.39E-04 7.34E-02 5.4 BETA DOSE (MRAD) 8.05E-04 2.24E-01 PERCENT OF GAMMA TECH SPEC (%)

5.5 1.20E "' 3.67E-01 5.6 PERCENT OF BETA TECH SPEC (%)

6.0 IODINES

0. 00 E+t 1.14E-04 6.1 TOTAL I-131 (CI) 0.00F+00 1.45E-05 6.2 AVERAGE RELEASE RATE (UCI/SEC) 7.0 PARTICULATES 0.00E+00 3.68E-04 7.1 TOTAL RELEASE (CI) 0.00E+00 4.68E-05 7.2 AVERAGE RELEASE RATE (UCI/SEC) 8.0 TRITIUM 1.46E+01 2.40E+01 8.1 TOTAL RELEASE (CI) -

1.86E+00 3.05E+00 8.2 AVERAGE RELEASE RATE (UCI/SEC) trial IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 1.86E+00 3.05E+00 9.0 2.70E-02 1.25E-01 10.0 DOSE (MREM) 1.80E-01 8.33E-01 11.0 PERCENT OF TECH SPEC (%)

0.00E+00 4.43E-08 12.0 GROSS ALPHA (CI)

REV. 1 PAGE 5 19 1 EFFLUENT SEMIANNUAL REPORT I

  • l TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES i

13.0 FISSION AND ACTIVATION GASES I CONTINUOUS MODE BATCH MODE {

1, NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 l I'

AR-41 CI 6.54E-03

, KR-85 CI 1.18E+00 8.05E-01 i XE-131M CI 8.71E-03 '

)

! XE-133 CI 2.13E-01 5.16E+01 9.43E-01  :

5.69E-01 i, XE-133M CI 4

i XE-135 CI 4.45E-01 3.42E-03 h TOTAL CI 2.13E-01 5.38E+01 0.00E+00 1.77E+00 I

I  ;

14.0 IODINES CONTINUOUS MODE BATCH MODE

/

NUCLIDE UNITS .QTR: 01 QTR: 02 QTR 01 QTR: 02

! I I-131 CI 1.14F-04

~

I-133 CI 1.32E-05 9.07E-09 4

TOTAL CI 0.00E+00 1.27E-04 0.00E+00 9.07E-09 15.0 PARTICULATES CONTINUOUS MODE BATCH MODE j

NUCLIDE UNITS QTR: 01 QTR: 02 QTR: 01 QTR: 02 CS -137 CI 7.95E-05 -

CS-134' CI 6.67E-05 Co-50 CI 2.39E-07 2.14E-05 Co-60 CI 1.88E-04 MN-54 CI 1.18E-05 NB-95 CI 1.15E-06 TOTAL CI j 0.00E+00 1.39E-06 0.00E+00 3.67E-04

PAGE 6 19h1EFFLUENTSEMIANNUALREPORTREV. 1 TABLE 2A LIQUID FFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 2.04E+07 3.66E+07 16.0 VOLUME OF DILUTION WATER (LITERS) 1.46E+11 6.94E+10 17.0 18,0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 3.29E-02 7.94E-02 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 2.25E-10 1.14E-09 19.0 TRITIUM 19.1 TOTAL RELEASE (CI) 1.64E+02 7.64E+01 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.12E-06 1.10E-06 20.0 DISSOLVED AND ENThAINED GASES 20.1 TOTAL RELEASE (CI) 5.99E-03 1.07c-03 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 4.10E-11 1.54E-11 0.00E+00 0 00E+00 21.0 GROSS ALPHA (CI) 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 1.12E-06 1.10E-06 TOTAL BODY DOSE (MREM) 5.98E-04 1.21E-03 23.0 l 24.0 CRITICAL ORGAN

! 24.1 DOSE (MREM) 5.98E-04 1.21E-03 ORGAN TTL BODY TTL BODY 24.2 I

l 25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%) 1.99E-02 4.04E-02 l

26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%) 1.99E-02 4.04E-02

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REV. 1 PAGE 7 1991 EFFLUENT SEMIANNUAL RE! ORT TABLE 2A  !

LIQUID EFFLUENTS - SUMMATION C7 ALL RELEASES 37.0 INDIVIDUAL LIQUID EFFLUENT

' CONTINUOUS MODE BATCH MOEE NUCLIDE UNITS QTR: 01 QTR: 02 QTR 01 QTR 02 i

AG-110M CI 1.06E-02 3.39E-02 BE-7 CI 5.38E-05 Co-57 CI 7.12E-06 ,

co-58 CI 6.02E-06 4.99E-04 1.36E-02 Co-60 CI 4.57E-06 2.15E-03 2.42E-03 CR-51 CI 5.35E-04 4.64E-03 CS-134 CI 6.37E-05 1.22E-05 1.27E-05 CS-137 CI 1.25E-04 3.90E-05 3.66E-05 FE-55 CI 2.69E-04 1.71E-02 1.54E-02 FE-59 CI 2.06E-04 8.56E-04 1.50E-04  !

I-131 CI LA-140 CI 3.95E-05 MN-54 CI 3.84E-05 2.21E-04 NB-95 CI 8.48E-05 i 5

RH-105 CI 1.21E-05 l SB-122 CI 2.64E-04

? , -

SB-124 CI 2.16E-04 4.06E-03 2.47E-03 SB-125 CI 7.40E-04 E SB-126 CI 5.96E-06 SC-47 CI 4.41E-06 2.20E-04 SE-75 CI 1.34E-05 SN-113 CI 3.04E-04 5.29E-04

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SR-92 CI 2.86E-06 3.22E-04 CONTINUED ,

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PAGE 8 19h1EFFLUENTSEMIANNUALREPORT REV. 1 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 27.0 INDIVIDUAL LIQUID EFFLUENT (CONTINUED)

CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTRI' O2- QTR: 01 OTR: 02 W-187 CI 1.45E-05 ZN-65 CI 6.26E-06 ZR-95 CI 4.10E-05 ZR-97 CI 1.33E-06 TOTAL CI 2.74E-04 1.95E-04 3.26E-02 7.94E-02 28.0 DISSOLVED AND ENTRAINED GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 QTR 01 QTR: 02 XE-131M CI 3.18E-05 xd-133 CI 2.64E-05 5.96E-03 */.62E-04 XE-133M CI 2.72E-05 4.61E-06 l- 2.40E-04 i XE-137 CI TOTAL CI 0.00E+00 2.64E-05 5.99E-03 1.04E-03 i

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NORTHERN STF.TES POWER COMPANY PJLhlRIE ISLAND NUQLEAR GENEBATIliG_P_LAN_T OPP-BITE RADIATION DQSE__AEERSEMIliT_IQB January 1- December 31, 1991 An assessment of radiation dose due to release from the Prairie Island Nuclear Generating Plant during 1991 was performed in '

accordance with the Technical Specifications. Computed doses were well below the 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidelines.

Of f-site dose calculation f ormulas and meteorological data from the off-site Dose Calculation Manual were used in making this assessment. Source terms were obtained from the two Effluent and Waste Disposal Semiannual Reports prepared fer NRC review during the year of 1991.

91f-pite Doses f tsLm Gases _us Release Computed doses due-to gaseous releases are reported in Table 1.

critical receptor location and pathways for organ doses are reported in Table 2. Doses, both whole body and organ, are a small percentage of Appendix I Guidelines.

Off-site Doses from Liq 1 Lid Releap_e_

Computed doses due to liquid releases are reported in Table 1.

Receptor information is reported in Table 2. Both whole body dose and organ dose are a small percentage of Appendix I Guidelines.

Doses to Individuals Due to Ac.ilyities Inside__the Site Doundary.

Occasionally sportsmen enter the Prairie Island site for

-recreational activities. These individuals are not expected to spend more than a few hours per year within the site boundary.

Commercial and recreational river traffic exists through this area.

For purposes of estimating the dose due to recreational and river water transportation activities within the site boundary, it is assumed that the limiting dose within the site boundary would be-received by an individual who spends a total of seven days per year on the river just off shore from the main plant buildings (ESE at 0.2 miles). Whole body and inhalation organ doses were calculated for this location and occupancy time. These doses were reported in Table-1.

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t P' f

poses to Most Fmpased Member o_f tlle_ General Public f rom EnttM Relea_ses and Oth.er Uranium Fuel Cycle Bources

. There are no other uranium fuel facilities in the vicinity of the Prairie Island site. The only other artificial source of exposure to the general public in addition to the plant effluent releases is from direct radiation of the reactors. This direct radiation from pressurized water reactors has been shown to be negligible. An e ray of TLD monitoring stations around the perimeter of the site boundary has consistently indicated that plant operation in the past years has no effect on ambient gamma radiation.

Therefore, the most exposed member of the general public will not receive an annual radiation dose from reactor ef fluent releases and all other fuel cycle activities in excess of the sum of the liquid and gaseous whole body and organ doses reported in Table 1 for the site boundary and critical receptor, respectively. These doses are well below 40 CFR Part 190 standards of 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.

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TABLE 1 OFF-SITE RADIATION DOSE ASSESSMEN't - PRAIRIE ISLAND i PERIODI JANUARY 1 tArough DECEMDER 31, 1991 10 CFR Part 50 Appendix I Guidelines por 2-units site por year p_aleous Releasel Maximum Site Boundary '

Gamma Air Dose (mrad) 0.0212 20  ;

Maximum Site Boundary Beta Air Dose (mrad) 0.0661 40 Maximum Off-site Dose to Any Organ (mrom)*

Total 0.194 30 Offshore Location (mrom)

Whole Body 2.09E-04 10 Organ 2.12E-04 30 Liquid Releases Maximum Off-site Dose Whole Body (mrom) 2.89E-03 6 Maximum Off-site Dose Organ, Total 2.89E-03 20

1

i e ~ s TABLE 2 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND SUPPLEMENTAL INFORMATION PERIOD: JANUARY 1 through DIREHRER 31, 1991 GAAeous Rpleas.gg Maximum Site Boundary Dose Location (from Building vents)

Sector WNW Distance (miles) 0.4 O'fshore Location Within Site Boundary Sector ESE Distance (miles) 0.2 Maximum Off-site Dose Location Sector SSE Distance (miles) 0.6 Pathwayu Plume, Ground, Inhalation, I

Vegetables Age Group Child Organ Skin Licuid Releases Maximum Off-site Dose Location Downstream Pathways Fish Organ Whole Body i

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