ML041420504

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2003 Annual Radioactive Effluent Report for Prairie Island Nuclear Generating Plant Units 1 and 2
ML041420504
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 12/31/2003
From:
Nuclear Management Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML041420504 (18)


Text

ENCLOSURE 2

  • 0 Annual Radioactive Effluent Report Supplemental Information, Revision 0 0

(9 pages follow) 0 '

2003 Annual Radioactive Effluent Report REV. 0 Page 1 of 9 Retention: Lifetime ANNUAL RADIOACTIVE EFFLUENT REPORT 01-JAN-03 THROUGH 31-DEC-03 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

  • 500 mrem/year total body
  • 3000 mrem/year skin I-131, I-133, H-3, LLP *1500 mrem/year to any organ
b. The dose due to radioactive gaseous effluents released from the site shall be limited to:

noble gases *10 mrad/quarter gamma

  • 20 mrad/quarter beta

<20 mrad/year gamma

  • 40 mrad/year beta I-131, I-133, H-3, LLP *15 mrem/quarter to any organ

<30 mrem/year to any organ

2003 Annual Radioactive Effluent Report Rev. 0 PAGE 2 B. Water Effluent Concentration

1. Fission and activation gases in gaseous releases:

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

2. Iodine and particulates with half lives 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.OE-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 Gem +/-25%

in gaseous releases: Nuclide Gem

2. Iodines in gaseous releases: Total Gem +/-25%

Nuclide Gem

3. Particulates in gaseous releases: Total Gem +/-25%

Nuclide Gem

4. Liquid effluents Total Gem +/-25%

Nuclide Gem E. Manual Revisions

1. Offsite Dose Calculations Manual latest Revision number: jg Revision date  : (O/26/0o3

2003 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PACE 3 1.0 BATCH RRELASES (LIQUID)

QTRs 01 QTRs 02 QTR: 03 QTRs 04 1.1 NUMBER OF BATCH RELEASES 1.703+01 2.10E+01 5.60E+01 4.90E+01 1.2 TOTAL TIME PERIOD (ERS) 3.05E+01 4.13Z+01 9.79E+01 9.OOE+01 1.3 MAXIMUM TIME PERIOD (HRS) 2.083+00 3.80E+00 2.67E+00 3.42E+00 1.4 AVERAGE TIME PERIOD (ERS) 1.793+00 1.973+00 1.75E+00 1.84E+00 1.5 MINIMUM TIME PERIOD (HRS) 1.583+00 1.03E+00 7.33E-01 9.67E-01 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CPS) 1.02E+04 3.19Z+04 1.67E+04 7.74E+03 2.0 BATCH RELEASES (AIRBORNE)

QTRs 01 QTR: 02 QTR: 03 QTR: 04 2.1 NUMBER OF BATCH RELEASES 1.00E+00 1.00E+00 1.00E+00 1.50E+01 2.2 TOTAL TIME PERIOD (HRS) 5.75E+00 4.53E+00 2.92Z-01 2.23Z+02 2.3 MAXIMUM TIME PERIOD (HRS) 5.75E+00 4.53E+00 2.92E-01 2.40E+01 2.4 AVERAGE TIME PERIOD (HRS) 5.75E+00 4.53E+00 2.92E-01 1.49E+01 2.5 MINIMUM TIME PERIOD (HRS) 5.75E+00 4.53E+00 2.92E-01 2.25E+00 3.0 ABNORMAL RELEASES (LIQUID)

QTR: 01 QTR: 02 QTRs 03 QTRs 04 3.1 NUMBER OF BATCH RELEASES O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 3.2 TOTAL ACTIVITY RELEASED (CI) O.OOE+00 O.OOE+00 O.OO+00 0.003+00 3.3 TOTAL TRITIUM RELEASED (CI) 0.003+00 0.00Z+00 0.00B+00 0.00E+00 4.0 ABNORMAL RELEASES (AIRBORNE)

QTRs 01 QTR: 02 QTR: 03 QTRs 04 4.1 NUMBER OF BATCH RELEASES O.OOE+00 O.OOZ+00 O.OO+00 O.OOZ+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00Z+00 0.OOE+00 0.00E+00 0.00Z+00

2003 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 4 TABLE IA GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 QTRS 02 QTRt 03 QTR: 04 5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 3.75E-01 5.15E-01 2.02E-02 0.00B+00 5.2 AVERAGE RELEASE RATE (UCI/SEC) 4.77E-02 6.55E-02 2.57E-03 0.OOE+00 5.3 GAMMA DOSE (HRAD) 2.70E-05 2.90E-05 6.07E-07 0.00E+00 5.4 BETA DOSE (MRAD) 3.06E-03 3.03E-03 4.17E-05 0.00E+00 5.5 PERCENT OF GAMMA TECH SPEC (%) 2.70E-04 2.90E-Oi 6.07E-06 0.00E400 5.6 PERCENT OF BETA TECH SPEC (%) 1.53E-02 1.52E-02 2.08E-04 O.OOE+00 6.0 IODINES 6.1 TOTAL 1-131 (CI) O.OOE+00 0.00B+00 l 0.00B+00 0.OOE+00 6.2 AVERAGE RELEASE RATE (UCI/SEC) 0.0O0+00 J 0.OOE+00 0.OOE+00 0.OOE+0 7.0 PARTICULATES 7.1 TOTAL RELEASE (CI) 0.OOE+00 0.0o0+00 0.OOE+00 2.20E-08 7.2 AVERAGE RELEASE RATE (UCI/SEC) 0.OOE+00 0.OOE+00 l 0.OOE+00 2.80E-09 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 4.64E+00 7.56E+00 3.30E+00 1.74E+00 8.2 AVERAGE RELEASE RATE (UCI/SEC) 5.90E-01 T 9.61E-01 l 4.20E-01 2.21E-01 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 5.90Z-01 9.61E-01 4.20E-01 T2.21E-01 10.0 DOSE FROM IODINE, LLP, AND TRITIUM (HREM) 8.30E-03 1.35E-02 5.90E-03 5.44E-03 11.0 PERCENT OF TECH SPEC (%) 5.54E-02 9.01E-02 3.94E-02 3.63E-02 12.0 GROSS ALPHA (CI) °.OOE+00 0.00B+00 0.OOE+00 0.OOE+00

2003 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 5 TABLE IC GASEOUS EFFLUENTS - GROUND LEVEL RELEASES (CI) 13.0 FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE LNUCLIDE I UNITS I QTR: 01 IQTR: 02 lQTR: 03 l QTR: 04 QTR: 01. QTR: 02 lQTRs 03 l QTRs 04 l KR-85 CI 1.86B-01 1.96Z-02 3.75E-01l 3.23E-01 XE-133 CI 5.15E-03 5.42Z-04 XE-133M CI 9.28B-05 9.77E-06 XE-135 CI 1.69E-04 1.78B-05 TOTALS CI O.OOE+00 1.92B-01o 2.02E-02 0.00Z+00 3.75E-01 3.23E-01 0.00E+00 l0.00+00 14.0 IODINES CONTINUOUS MODE BATCH MODE l NUCLIDE U UNITSI FQTR: 01 IQTRs 02 1 QTRs 03 l QTR: 04 lQTRs 01 QTRs 02 lQTR 03 lQTR 04 l TOTALS 00+00 I 0.00B+00 0.005+00 0.005+00 0.00+00 I 0.005+00 I °.00°+00 0°.00°+00 I

2003 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 6 TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES (CONTINUED) 15.0 PARTICULATES CONTINUOUS MODE BATCH MODE INUCLID UNITS QTRt 01 I QTRt 02 l QTR: 03 TR 04 QTR: 01 I QTR: 02 lQTR: 03 l QTR: 04 lCS-137 CZ I lI Il I I 2.20E-08 I lTOTALS lC 0.00E+00 0.00E+00 0.00E+00 I O.00E+00 I lo .E+00 0.00E00 O.00E+00 2.20E-08 l

2003 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 7 TABLE LA LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 QTRt 03 QTR: 04 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 4.80eB+07 2.66B+07 4.OOE+07 3.65E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 1.49E+11 1.01E+1L 2.40E+11 2.03E+ll 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASES W/O H-3, RADGAS, ALPHA (CI) l 1.30E-02 6.91E-03 l 1.69E-02 4.16E-02 l 18.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 8.76E-11 6.86B-11 7.05E-11 J 2.05E-10 J 19.0 TRITIUM 19.1 TOTAL RELEASE (CI) l 9.43E+01 2.14Z+02 1.70E+02 1.03E+02 19.2 'AVERAGE DILUTION CONCENTRATION (UCI/HL) l 6.34E-07 l 2.12E-06 7.09E-07 5.05E-07 l 20.0 DISSOLVED AND ENTRAINED CASES 20.1 TOTAL RELEASE (CI) [ 0.00E+00 2.35E-05 3.25E-04 l 8.31E-05 20.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 0.00Z+00 j 2.33E-13 1.35E-12 J 4.09E-13 21.0 GROSS ALPHA (CI) O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 22.0 TOTAL TRITIUH, FISSION & ACTIVATION PRODUCTS (UCI/HL) 6.34E-07 2.12E-06 7.09E-07 5.05E-07 23.0 TOTAL BODY DOSE (HREM) 4.30E-04 7.06E-04 4.81E-04 T4.44E-04 l 24.0 CRITICAL ORGAN 24.1 DOSE (HREM) 4.30E-04 7.06E-04 4.81E-04 1.67B-03 24.2 ORGAN TOT BODY TOT BODY TOT BODY GI TRACT 25.0 PERCENT OF TECHNICAL SPECIFICATIONS LIMIT (%) 1.43E-02 2.35E-02 1.60E-02 1.48E-02 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%) 1.43E-02 2.35E-02 1.60E-02 1.67E-02

2003 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 8 TABXL 2A LIQUID EFFLURNTS - SUMMATION O0 ALL RRELASRS (CI) 27.0 INDIVIDUAL LIQUID NFFLUNNT CONTINUOUS MODE BATCH MODE I NUCLIDE l UNITS ll QTRt 01 IQTR: 02 l QTR: 03 l QTR: 04 IQTR: 01 I QTR: 02 I QTR: 03 l QTR: 04 AG-108H CI 1.25E-06 AG-llOH CI 1.52E-04 4.80E-04 5.06B-04 1.80E-03 BE-7 CI 7.90E-06 CO-57 CI 9.83E-06 1.61B-06 3.773-06 Co-58 CI 5.98E-03 8.42E-04 1.59E-03 7.093-03 CO-60 CI 3.23E-04 4.03E-04 1.30E-03 9.22E-04 CR-51 CI 2.46E-04 7.70E-O5 3.09E-03 CS-134 CI 1.55E-05 2.06E-OS 4.67E-06 CS-137 CI 2.04E-06 3.52E-05 3.03E-05 3.12E-05 l.55E-05 1.04E-06 FR-55 CI 7.45R-06 4.39E-07 1.12E-03 3.813-03 6.303-03 5.98Z-03 FE-59 CI 3.98E-O5 5.35Z-06 1.36E-05 2.08E-03 LA-140 CI 2.42E-05 MN-54 CI 7.38E-06 4.34E-06 1.27E-05 3.14E-OS NA-24 CI 1.87E-06 NB-95 CI 3.003-OS 3.89E-06 8.21E-OS NE-97 CI 2.90E-06 1.81E-06 6.4SE-06 PR-144 CI 3.95E-05 RU-103 CI 1.253-06 SB-122 CI 8.0SE-07 7.33E-05 1.01E-05 SB-124 CI 1.123-05 1.68E-06 8.683-04 l.513-03 SB-125 CI 5.68E-04 8.34E-04 6.06E-03 8.28E-03 SB-126 CI 9.64E-06 3.99E-06 SN-113 CI 6.66R-06 5.78E-06 1.09E-04 SR-92 CI 8.60E-06 4.44E-07 3.69E-OS TE-123M CI 2.693-05 8.63E-07 4.22E-05 S.30E-04 (CONTINUED)

2003 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 9 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (CONTINUED) 27.0 INDIVIDUAL LIQUID EFFLUENT CONTINUOUS MODE BATCH MODE NUCLIDE I UNITS 11 QTRs 01 I QTR: 02 l QTR, 03 l QTRs 04 l QTRs 01 QTRs 02 QTRs 03 QTR: 04 TB-125M CI 4.44E-03 4.473-04 9.81B-03 TE-132 CI 8.74B-07 2.56Z-06 W-187 CI 4.27Z-06 4.53Z-05 ZN-65 CI 3.45B-06 1.23B-06 4.56B-06 5.383-05 ZR-95 CI 1.81B-05 3.89B-06 5.51B-05 ZR-97 CI 1.233-06 TOTALS CI 7.453-06 4.393-07 2.043-06 3.523-05 1.303-02 6.913-03 1.69E-02 4.163-02 28.0 DISSOLVED AND ENTRAINED CASES CONTINUOUS MODE BATCH MODE I DUCIDE I UNITS ll QOTs 01 I QTR: 02 I QTRs 03 l QTR: 04 ll QTR: 01 I QTRs 02 I QTRs 03 l QTRs 04 1 LDIIjQTR: 03 QTR:

QTR:

01 QTR:

04 02 QER: 01 QTR: 02 QTR: 03 QTR: 04

ENCLOSURE 3 Effluent and Waste Disposal Annual Report Solid Waste and Irradiated Fuel Shipments (7 pages follow) i

PINGP 753, Rev. 7 Page 1 of 7 Retention: Life PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01/0103 to 12/31/03 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

1. Solid Waste Total Volumes and Total Curie Quantities:

-CONTAINER

-PERIOD:': :EST.- TOTAL: DISPOSAL TYPE OF WASTE TOTALS :UNITS ERROR, % - .VOL(ft3)

-_ _ _ _ _ _ _ - -; I E00)-- :; (0.00

-----:.::-:(0.00 EOO). (LIST)-

A. Resins m 3.85E+00 135.8 Bead Resin ft3 1.36E+02 Ci 8.15E+01 +/- 2.50E+01 B. Dry-Compacted mi .

ft3 _ _ _ _ _ _ _ _ _ _

Ci-C. Non-Compacted m 1.60E+02 94 DAW, Wood, Metal ft3 5.64E+03 Ci 8.52E-01 +/- 2.50E+01 D. Filter Media m3 ft3 S. Other (furnish description) m _

3 ft _ _ _ _ _ __ _ _ _ _ _

_i _ .

The solid waste information provided in this report is the volume NOTE-: and activity of the low-level waste leaving the Prairie Island site.

No allowance is made for off-site volume reduction prior to disposal.

Documenti

PINGP 753, Rev. 7 Page 2of7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01101/03 to 12/31/03 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]

2. Principal Radionuclide Composition by Type of Waste:

(Bold letter designation from Page 1)

TYPE Percent %

Abundance Nuclide (0.OOEO)

A Mn-54 1.14E+00

  • Fe-55 9.29E+00 Co-58 5.08E+00 Percent Co-60 1.47E+01 Cutoff: 1
  • Ni-63 3.16E+01 Cs-1 34 1.79E+01 Cs-137 2.02E+01 C Mn-54 1.09E+00
  • Fe-55 6.61 E+OI Co-58 9.28E+00 Percent Co-60 7.64E+00 Cutoff: 1
  • Ni-63 7.77E+00 Zr-95 2.08E+00 Nb-95 1.81 E+00 Sb-1 25 1.26E+00 Cs-134 1.06E+00
  • = Inferred - Not Measured on Site

PINGP 753, Rev. 7 Page 3 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01/01/03 to 12/31/03 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]

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

(Bold letter designation from Page 1)

TYPE Percent %

Abundance Nuclide (O.OOEO)

  • = Inferred - Not Measured on Site

PINGP 753, Rev. 7 Page 4 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01/01103 to 12131/03 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]

3. Solid Waste Disposition:

Number of Shipments Mode Destination 1 T.A.G. Transport, Barnwell Waste Inc. Management Facility 4 Hittman Transport Duratek, Inc.

Services

PINGP 753, Rev. 7 Page 5 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01/01/03 to 12/31/03 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]

4. Shipping Container and Solidification Method:

Disposal No. Volume Activity Type of Container Solidif.

(Ft3 Im3 ) (Ci) Waste Code Code 03-004 1410/40 0.214 C L N/A 03-006 1410/40 0.144 C L N/A 03-008 1410/40 0.141 C L N/A 03-010 1410/40 0.352 C L N/A 03-012 136/3.85 81.500 A A N/A TOTA 5 5776 / 82.351 LS 163.85 CONTAINER CODES: L = LSA (Shipment type) A = Type A B = Type B Q = Highway Route Controlled Quantity SOLIDIFICATION CODES: C = Cement TYPES OF WASTES: A = Resins B = Dry Compacted C = Non-Compacted D = Filter Media S = Other

PINGP 753, Rev. 7 Page 6 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01/01/03 to 12/31/03 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

Number of Shipments Mode Destination 0 _

PINGP 753, Rev. 7 Page 7 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01/01/03 to 12/31/03 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C. PROCESS CONTROL PROGRAM CHANGES TITLE: Process Control for Solidification/Dewatering of Radioactive Waste from Liquid Systems Current Revision Number: 8 Effective Date: 8/25/1999 If the effective date of the PCP Is within the period covered by this report, NOTEthen a description and Justification of the changes to the PCP Is required (T.S.6.5.D) iTS.5.5.4). Attach the sidelined pages to this report. I Changes/Justification: N/A