ML20064B694
| ML20064B694 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/1993 |
| From: | Richard Anderson NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9403080383 | |
| Download: ML20064B694 (32) | |
Text
~
r-Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401 1927 Telephone (612) 330-5500 March 1, 1994 Technical Specification 6.7.A.4 US Nuclear Regulatory Commission Attn Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Effluent and Waste Disposal Semi-Annual Report for Julv Throuah December 1993 In accordance with the Prairie Island Technical Specifications, Appendix A to Operating Licenses DPR-42 and DPR-60, we are submitting one copy of the Effluent and Waste Disposal Semi-Annual Report for the second half of year 1993.
The report is completed with the exception of the Sr-89, Sr-90, and Fe-55 composite values which are reported using default values in accordance with our Offsite Dose Calculations Manual. An amended report with the actual composite results will be forwarded with the next semi-annual report.
Also attached is the revised semi-annual report for the first semi-annual period of 1993.
This revision includes the actual composite results for 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.
This letter contains no new NRC commitments, nor does it modify any prior commitments.
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Northern States Power Company March 1, 1994 Page 2 Please contact Jack Leveille (612-388-1121, Ext. 4662) if you require further information.
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Regional Administrator - III, NRC NRR Project Manager, NRC Sr Resident Inspector, NRC State of Minnesota Attn Kris Sanda J Silberg Attachment A Effluent and Waste Disposal Semiannual Report, Period Jul-Dec 1993 (15 pages)
Attachment B Effluent and Waste Disposal Semiannual Report, Period Jan-Jul 1993, Supplemental Report (8 pages)
Attachment C Off-Site Radiation Dose Assessment for January 1, - December 31, 1993 (4 pages) i l
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Attachment A i
Effluent and Waste Disposal Semiannual Report Period Jul-Dec 1993 i
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1993 Effluen't Semiannual Report REV. 0 Page 1 of 8 Retention: Lifetime EFFLUENT SEMIANNUAL REPORT 05-JUL-93 THROUGH 02-JAN-94 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 mrom to the total body 20.0 mrom 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 mrom/ year total--body s3000 mrem / year skin T-131, H-3, LLP s1500 mrem / year-to any organ b.
The dose due to radioactive gaseous effluents'shall be limited to:
noble gases s10 mrad / quarter gamma s20 mrad / quarter beta s20 mrad / year gamma s40 mrad / year beta I-131, H-3, LLP s15 mrom/ quarter to any organ
$30 mrom/ year to any organ
4 1993 EFFLUEliT SEMIANNUAL REPORT REV. O PAGE 2 I
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 1
3.
Liquid effluents for radionuclides other than j.
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 Prairio Island regulatory limits.
1 D.
Measurements and approximations of total activity 1.
Fission and activation gases Total GeLi 25%
in gaseous releases:
Nuclide GeLi s
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.
Manutl Revisions 1.
Offsite Dose Calculations Manual latest Revision number: 12 Revision date
- 17-JUN-91
)
1993 EPFLUENT SEMIANNUAL' REPORT REV. O PAGE 3 1.0 BATCH RELEASES (LIQUID)
QTR: 03 QTR: 04 1.1 NUMBER OF BATCH RELEASES 3.80E+01 6.50E+01 1.2 TOTAL TIME PERIOD (HRS) 6.10E+01 9.64E+01 1.3 MAXIMUM TIME PERIOD (HRS) 2.25E+00 2.53E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.61E+00
-1.48E+00 1.5 MINIMUM TIME PERIOD (HRS) 1.12E+00 1.17E+00 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 5.59E+04 1.82E+04 2.0 BATCH RELEASES (GASEOUS)
QTR: 03 QTR: 04-2.1 NUMBER OF BATCH RELEASES 1.00E+00 2.10E+01' 2.2 TOTAL TIME PERIOD (HRS) 2.10E+00 2.98E+02 2.3 MAXIMUM TIME PERIOD (HRS) 2.10E+00 1.68E+02 2.4 AVERAGE TIME PERIOD (HRS) 2.10E+00 1.42E+01 2.5 MINIMUM TIME PERIOD (HRS)
-2.10E+00 1.00E-02 3.0 ABNORMAL RELEASES (LIQUID)
OTR: 03 QTR: 04 3.1 NUMBER OF 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: 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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1993 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 4-
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TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES j
OTR: 03 QTR: 04 5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 7.86E-01 3.54E+01 5.2 AVERAGE RELEASE RATE (UCI/SEC) 1.00E-01 4.50E+00 5.3 GAMMA DOSE (MRAD) 2.64E-04 1.71E-02 5.4 BETA DOSE (MRAD) 1.88E-03 5.75E-02 5.5 PERCENT OF GAMMA TECH SPEC (%)
2.64E-03 1.71E-01 '
5.6 PERCENT OF BETA TECH SPEC (%)
9.40E-03 2.88E-01 6.0 IODINES 6.1 TOTAL I-131 (CI) 0.00E+00 6.71E-04' 6.2 AVERAGE RELEASE RATE (UCI/SEC) 0.00E+00 8.54E-05 7.0 PARTICULATES 7.1 TOTAL RELEASE (CI) 0.00E+00 2.19E-05 7.2 AVERAGE RELEASE RATE (UCI/SEC) 0.00E+00 2.79E-06 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 1.39E+01 1.49E+01 8.2 AVERAGE RELEASE RATE (UCI/SEC) 1.77E+00 1.90E+00 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 1.77E+00 1.90E+00-10.0 DOSE (MREM) 2.51E-02 7.77E-02 11.0 PERCENT OF TECH SPEC (%)
1.67E-01 5.18E-01 12.0 GROSS ALPHA (CI) 0.00E+00
-2.00E-09 l
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1993 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 5" TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 13.0 FISSION AND ACTIVATION CASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 03 QTR: 04 QTR: 03 QTR: 04 KR-85 CI 1.37E-01 1.00E+00 XE-131M CI 2.23E-01 5.38E-04 2.43E-02 XE-133 CI 6.40E-01 3.09E+01 8.36E-03 2.90E+00 XE-133M CI 8.16E-02 7.86E-05 4.14E-02 XE-135 CI 1.01E-01 1.11E-05 8.97E-02 TOTAL CI 6.40E-01 3.13E+01 1.46E-01 4.06E+00 14.0 IODINES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS OTR: 03 QTR: 04 QTR: 03 QTR: 04 I-131 CI 6.65E-04 5.97E-06 I-133 CI 8.55E-05 2.30E-06 TOTAL CI 0.00E+00 7.51E-04 0.00E+00 8.27E-06 1
15.0 PARTICULATES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS OTR: 03 QTR: 04 QTR: 03 QTR: 04 CO-58 CI 3.29E-07 9.72E-06 CO-60 CI 3.21E-06 CS-134 CI 3.11E-06 CS-137 CI 1.46E-06 NB-95 CI 4.10E-06 TOTAL CI 0.00E+00 3.29E-07 0.00E+00 2.16E-05 l
1993 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 6 4
TABLE 2A LIQUID EFFLUENTS - SUMHATION OF ALL RELEASES OTR: 03 QTR: 04 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 2.44E+07 4.20E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 2.59E+11 1.43E+11 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 1.70E-02 1.01E-01 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 6.56E-11 7.06E-10 19.0 TRIT 1UM 19.1 TOTAL RELEASE (CI) 2.71E+02 1.09E+02 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.05E-06 7.62E-07 20.0 DISSOLVED AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI) 2.78E-02 1.70E-03 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.07E-10 1.19E-11 21.0 GROSS ALPHA (CI) 0.00E+00 4.20E-05 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 1.05E-06 7.63E-07 23.0 TOTAL BODY DOSE (MREM) 6.82E-03 3.27E-03 24.0 CRITICAL ORGAN i.
24.1 DOSE (MREM) 6.82E-03 3.27E-03 24.2 ORGAN TTL BODY TTL BODY 25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)
2.27E-01 1.09E-01 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)
2.27E-01 1.09E-01
l 199.3 EFFLUENT SEMIANNUAL REPORT REV. O PAGE 7 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-110M CI 1.13E-03 4.84E-03 BE-7 CI 1.31E-04 7.74E-05 CO-57 CI 3.70E-05 CO-58 CI 2.07E-04 1.16E-03 3.68E-02 CO-60 CI 2.02E-03 1.02E-02 CR-51 CI 2.86E-03 CS-134 CI 4.68E-04 2.36E-04 CS-136 CI 6.99E-06 CS-137 CI 2.97E-05 1.05E-03 3.96E-04 FE-59 CI 1.07E-03 I-131 CI 3.94E-05 3.49E-04 I-133 CI 1.59E-05 LA-140 CI 4.43E-05 MN-54 CI 2.12E-05 5.75E-04 NA-24 CI 3.50E-06 NB-95 CI 3.99E-06 2.47E-04 NB-97 CI 1.04E-05 1.03E-05 RU-103 CI 1.57E-06 RU-105 CI 1.21E-05 SB-122 CI 9.04E-04 SB-124 CI 5.82E-05 1.54E-02 SB-125 CI 7.55E-04 4.61E-03 SB-126 CI 1.32E-05 SC-47 CI 1.45E-04
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1993 EFFLUEhiT SEMIANNUAL REPORT REV. O PAGE 8 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 27.0 INDIVIDUAL LIQUID EFFLUENT (CONTINUED) 2 CONTINUOUS MODE BATCH MODE NUCLIDE UNITS OTR: 03 OTR: 04 QTR: 03 OTR: 04 SN-113 CI 1.09E-05 6.09E-04 SR-92 CI 2.89E-05 W-187 CI 3.44E-05 ZN-65 CI 9.72E-05 ZR-95 CI 1.67E-04 ZR-97 CI 1.47E-06 FE-55 CI 2.79E-03 1.18E-03 7.39E-03 1.94E-02 SR-90 CI 4.37E-05 TOTAL CI 2.79E-03 1.50E-03 1.42E-02 9.92E-02 28.0 DlSSOLVED AND ENTRAINED GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS OTR: 03 OTR: 04 QTR: 03 OTR 04 KR-85 CI 3.00E-03 XE-131M CI 7.46E-04 XE-133 CI 2.39E-02 1.68E-03 XE-133M CI 6.64E-05 9.31E-06 XE-135 CI 3.75E-05 6.94E-06 TOTAL CI-2.78E-02 1.70E-03
PINGP 753,' Rev. 5 Page 1 of 7 Retention: Life
?RAIRIE ISLAND NUCLEAR GENERATING PLANT Period:
7-1-93 to 12-31-93 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL SEMI-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:
D+ 16{h40NTHY lIES% TOT ^6 CONT %lNEW e
m inkiri l7*lEhROR$yo$
3DiSRDShus N.jT P$50FSNASTEIg]"y, <
w gT W'
MPElRIODh i y;
'(OMjE00)g 3 MOO $(ithP MOTAN.
t,% % ?!{(LIST)$$
@ m~
- ge,
Zi(0'.0.0]E0_0))
s A.
Resins m3 10.38 ft3 366.6 183.3 8.1 2.5E01 Ci B.
Dry-Compacted m3 35.88 ft3 1267.5 7.5 Ci 1.328 2 5E01 C.
Non-Compacted m3 in u s ft3 3760 96 Ci
.428 2.5E01 D.
Filter Media m3 ft3 Ci S.
Other m3 ft3 Ci M' r fp*s:
The solid waste information provided in this report is the volume and activity of the low-level waste leaving the Pralrle island site. No allowance is made for off-site volume reduction prior to burial.
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i PINGP 753, Rev. 5 Page 2 of 7 3RAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-93 to 12-31-93 NORTHERN STATES POWER License No. DPR -42/60 EFFLUENT AND WASTE DISPOSAL SEMI-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 Porcent (%)
Abundanco Nuclido (0.00EO)
A Fe-55 3.86E01 Cn-117 1.51E01 Ni-63 1.29E01 Cs-134 1.22E01 Co-60 1.09E01 Rh-l?5 4.16F00 C-14 2.03E00 Ce-144 1.23E00 Co-58 1.17E00 B
Fe-55 4.63E01 Ni-63 2.41E01 Cn-60 1.81E01 00-58 4.23E00 Mn-54 2.32E00 Cs-134 1.52E00 Cn-117 1.16F00
- - Inferred - Not Measured on Site
- l,
. PINGP 753, Rev. 5 Page 3 of 7
?RAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-93 to 12-31-93 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL SEMI-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 Nuclido (0.00E0)
C Fe-55 4.63E01 N1-63 2.41E01 Co-60 1.81E01 Co-58 4.23E00 Mn-54 2.32E00 Cs-134 1.52E00 cm-117 1.16F00
- = Inferred - Not Measured on Site i
- l, PINGi) 753,Rev.5 Page 4 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-93 t 12-31-93 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL SEMI-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:
N_ umber of Shipments Mode Destination 5
TRUCK BARNWELL 3
TRUCK SEG.
)
PINGP 753, Rev. 5 Page 5 of 7
?RAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-93 to 12-31-93 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL SEMI-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/m3)
(Ci)
Waste Code Code 93-19 1128/31.9 0.104 C
LSA N/A 93-20 510/14.4 0.824 B
LSA N/A 41-??
510/14.4 0.117 E
TSA N/A 93-26 1316/37.3 0.145 C
LSA N/A 93-27 183.3/5.2 4.08 A
LSA N/A 93-28 247.5/7.0 0.167 B
LSA N/A 93-29 183.3/5.2
'EQT A
LSA N/A 4
93-32 1316/37.3 0.179 C
LSA N/A i
e TOTALS 8
5394.1/152.7 9.816_
CONTAINER CODES:
L=
LSA (Shipment Type)
A=
Type A B = Type B O = Highway Route Controlled' Quantity -
SOLIDIFICATION CODES: C = Cement TYPES OF WASTE: A=
Rasins i
B=
Dr/ Compacted C=
Non-Compacted D=
Filte Media S= Spent Fuel
]
+
i PINGP 753,' Rev. 5
'Page 6 of 7 3RAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-93 to 12-31-93 4
NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS B.
IRRADIATED FUEL SHIPMENTS (DISPOSITION)
Number of Shipments Mode Destination n
i l
l l
l PINGP 753, Rev. 5 Page '7 of 7
'RAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 7-1-93 to 12-31-93 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C. PROCESS CONTROL PROGRAM CHANGES 1
TITLE:
Process Control Program for Solidification / Dewatering of Radioactive Waste from Liquid Systems Current Revision Number:
4 Effective Date:
5/23/91
$d.,T.E..A' 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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l Attachment B Effluent and Waste Disposal Semiannual Report Period Jan-Jul 1993 Supplemental Report l
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__w 1993 Ef' fluent Semiannual Report REV. 1 Page 1 of 8 i
Retention: Lifetime EFFLUENT SEMIANNUAL REPORT 04-JAN-93 THROUGH 04-JUL-93 SUPPLEMENTAL INFORMATION l
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 offluents 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 l
2.
Gaseous Effluents:
a.
The dose rato due to radioactive materials released in.
gaseous effluents from the site shall be limited to.
noble gases s500 mrom/ year total body s3000 mrem / year skin i
I-131, H-3, LLP s1500 mrom/ year to any organ b.
The dose due to radioactive gaseous ~ effluents shal'1 be limited to:
noble gases s10 mrad / quarter gamma s20 mrad / quarter beta s20 mrad / year gamma s40 mrad / year beta I-131, H-3, LLP s15 mrem / quarter to any organ s30 mrem / year to any organ
- ~
l, 1993 EFFLUE'NT SEMIANNUAL REPORT.
REV. 1 PAGE 2 B.
Maximum Pormissib10 Concontration 1.
Fission and activation gases in gaseous releases:
10 CFR 20, Appendix B, Table 2, Column 1 2.
Iodine and particulates with halflives greator than 8 days in gaseous releases:
10.CFR 20, Appendix B, Table 2, Column 1 3.
Liquid offluents for radionuclides other than dissolved or entrained gases:
10 CFR 20, Appendix B, Table 2, Column 2 4.
Liquid offluent dissolved and entrainod gases:
2.0E-04 uCi/ml Total Activity C.
Avorago Enorgy Not applicable to Prairlo Island regulatory limits.
4 D.
Moasuromonts and approximations of total activity 1.
Fission and activation gases Total GeLi 125%
in gaseous releases:
Nuclide GeLi 2.
Iodinos in gaseous releases:
Total GoLi 25%
Nuclide GeLi 3.
Particulates in gaseous releases:
Total GeLi 25%
Nuclido GoLi 4.
Liquid offluents Total GeLi 25%
Nuclide GeLi
.E.
Manual Rovisions 1.
Offsite Doso Calculations Manual latest Revision number:
12 Revision date
- 17-JUN-91 4
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1993 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 3 1.0 BATCH RELEASES (LI2UID)
OTR: 01 OTR: 02 1.1 NUMBER OF BATCH RELEASES 3.40E+01 2.20E+01 1.2 TOTAL TIME PERIOD (HRS) 5.40E+01
.3.44E+01' 1.3 MAXIMUM TIME PERIOD (HRS) 2.12E+00 2.55E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.59E+00_
1.56E+00 1.5 MINIMUM TIME PERIOD (HRS) 18E+00 1.33E+00 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 1.04E+04 5.68E+04' 2.0 BATCH RELEASES (GASEOUS)
OTR: 01 QTR: 02-2.1 NUMBER OF BATCH RELEASES 1.60E+01 2.00E+00 2.2 TOTAL TIME PERIOD (HRS) 7.84E+01 5.30E+00 i
2.3 MAXIMUM TIME PERIOD (HRS) 4.88E+01 3.10E+00 2.4 AVERAGE TIME PERIOD (HRS) 3.05E+00 2.65E+00' 2.5 MINIMUM TIME PERIOD (HRS) 1.20E-01 2.18E+00 3.0 ABNORMAL RELEASES (LIQUID)
OTR: 01 QTR: 02 3.1 NUMBER OF RELEASES 0.00E+00 0.00E+00 3.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 "1
3.3 TOTAL TRITIUM RELEASED (CI) 0.00E+00 0.00E+00.j j 4.0 ABNORMAL RELEASES (GASEOUS)
OTR: 01 QTR: 02 4.1 HUMBER OF RELEASES.
0.00E+00 0.00E+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00
- 0.00E+00
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a 1993 EFFLUENT SEMIANNUAL REPORT REV. 1 PAGE 4 "
TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 OTR: 02' 5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 3.51E-01 3.02E-01 5.2 AVERAGE RELEASE RATE (UCI/SEC) 4.47E-02 3.84E-02.
5.3 GAMMA DOSE (MRAD) 2.55E-05 2.47E-05 5.4 BETA DOSE (MRAD) 2.87E-03 2.46E-03 5.5 PERCENT OF GAMMA TECH SPEC (%)
2.55E-04 2.47E-04 5.6 PERCENT OF BETA TECH SPEC (%)
1.44E-02 1.23E-02 1
6.0 IODINES 6.1 TOTAL I-131 (CI) 0.00E+00 0.00E+00 6.2 AVERAGE RELEASE RATE (UCI/SEC) 0.00E+00 0.00E+00 7.0 PARTICULATES 7.1 TOTAL RELEASE (CI)
'4.61E-05 1.02E-06 7.2 AVERAGE RELEASE RATE (UCI/SEC)'
5.87E-06
'1.30E-07 8.0 TRITIUM 8.1 TOTAL h 9ASE (CI) 2.21E+01 1.21E+01-8.2 AVERAGE RELEASE RATE (UCI/SEC) 2.81E+00 1.54E+00 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 2.81E+00 1.54E+00 10.0 DOSE (MREM) 5.46E-02 2.17E-02 11.0 PERCENT OF TECH SPEC (%)
3.64E-01 1.45E 12.0 GROSS havHA. (CI) 9.67E-09 5.24E-08
1993 EF'FLUEthT SEMI ANNUAL REPORTREV. 1 PAGE-5 l
TABLE 1C GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 13.0 FISSION AND ACTIVATION GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 QTR: 02 GTA: 01 QTR: 02 KR-85 CI 3.52E-01 3.00E-01 XE-133 CI 1.31E-04 1.98E-03 XE-131M CI 3.20E-06 XE-135 CI 2.85E-06 TOTAL CI 0.00E+00 0.00E+09 3.52E-01 3.02E '
14.0 IODINES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS OTR: 01 QTR: 02 OTR: 01 QTR: 02 1
TOTAL CI 0.00E+00 0.00E+00 0.00E+00 0.00E+00 15.0 PARTICULATES CONTINUOUS MODE
-BATCH MODE NUCLIDE UNITS OTR: 01 QTR: 02 OTR: 01 OTR: 02 l
BR-82 CI 1.02E-06 CO-58 CI 3.98E-06 f
CO-60 CI 9.24E-06 CS-134 CI 1.16E-05 CS-137 CI 1.63E-05 MN-54 CI 4.70E-06 N8-95 CI 3.03E-07 i
l TOTAL CI 0.00E+00 1.02E-06 4.61E-05 0.00E+00.
1993 EFFLUEIT SEMIANNUAL REPORT REV. 1 PAGE 6 TABLE 2A
-LIQUID' EFFLUENTS - SUMMATION OF ALL RELEASES QTR: 01 QTR: 02 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 3.09E+07 2.52E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 1.36E+11 9.20E+10 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 1.23E-01 1.66E-02 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 9.04E-10
'1.80E-10 19.0 TRITIUM 19.1 TOTAL RELEASE (CI) 5.16E+01 4.79E+01 19.2 AVERAGE DILUTED CONCENT.1ATION (UCI/ML) 3.79E-07 5.22E-07 20.0 DISSOLVED AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI) 6.13E-06 2.56E-06 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 4.51E-14 2.78E-14 21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 3.79E-07 5.22E-07 23.0 TOTAL BODY DOSE (MREM) 1.44E-02 5.38E-03 24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 1.44E-02 5.38E-03 24.2 ORGAN TTL BODY TTL BODY 25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)
4.80E-01 1.79E-01 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)
4.80E-01 1.79E-01
.s 1993EFFLUEhiT'SEMIANNUALREPORT REV. 1
-PAGE 7 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 27.0 INDIVIDUAL LIQUID EFFLUEWT CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR: 01 OTR: 02 QTR: 01 OTR: 02 AG-110M CI 1.90E-02 1.53E-03 l
l CO-58 CI 1.37E-02 2.09E-03 CO-60 CI 5.17E-06 7.81E-03 2.01E-03 CR-51 CI 2.47E-03 5.71E-05 FE-59 CI 7.48E-04 2.69E-05 MN-54 CI 4.51E-04 5.08E-05 NB-95 CI 9.40E-04 9.40E-05 SB-124 CI 2.64E-03 5.41E-05 SB-125 CI 4.50E-03 4.96E-04 SN-113 CI 7.68E-04 1.21E-04 ZR-95 CI 6.85E-04 5.75E-05 CS-134 CI 1.48E-03' 5.61E-04 CO-57 CI 1.90E-05 6.27E-06 CS-137 CI 1.77E-04 1.54E-03 5.99E-04 AG-108M CI 5.43E-05 BE-7 CI 3.38E-04 5.05E-04 ZN-65 CI 9.62E-06 7.11E-06 NB-97 CI 1.48E-05 2.82E-06 2.31E-06 SC-47 CI 1.11E-05 NA-24 CI 5.56E-06 SR-90 CI 4.23E-05 FE-55 CI 6.69E-04 6.63E-02 7.65E-03 TOTAL CI 1.97E-04 7.11E-04 1.23E-01 1.59E-02 f
i*
1993'EFFLUEhiTSEMIANNUALREPORT REV. 1 PAGE 8 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 28.0 Did">OLVED AND ENTRAINED GASES CONTINUOUS MODE BATCH MODE r
NUCLIDE UNITS OTR: 01 QTR: 02 QTR: 01 QTR: 02 KR-85M CI 2.56E XE-133 CI 6.13E-06 TOTAL CI 0.00E+00 0.00E+00 6.13E-06 2.56E-06 f
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W Attachment c Off-Site Radiation Dose Assessment for January 1, - December 31, 1993 8
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i NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFF-SITE RADIATION DOSE ASSESSMENT FOR Januarv.1 through December 31, 1993 An Assessment of the radiation dose due to the release from Prairie Island Nuclear Generating Plant during 1993 was performed in accordance with the Technical Specifications.
Cumputed doses were well below the i
40 CFR Part 190 Standards and 10 CFR Part 150 Appendix I Guidelines.
Off-site dose calculation formulas and meteorological data from the Off-site Dose Calculation Manual were used in making this assessment.
Source terms were obtained from two Effluent and Waste Disposal Semi-annual Reports prepared for NRC review during the year of 1993.
QLf-site Doses from Gaseous 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 are a small percentage of Appendix I Guidelines.
Off-nite Doses from Liquid Release Computed doses due to Liquid releases are reported in Table 1.
Receptor information is reported in Table 2.
Doses, both whole body and organ, are a small percentage of Appendix I Guidelines.
Dosen to Individuals Due to Activities Inside the Site Boundary 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 plant buildings (ESE at 0.2 miles).
The gamma dose from noble gas releases and the whole body and organ doses from the inhalation pathway due to Iodine
- 131, tritium and long lived particulates were calculated for this location and occupancy time.
These doses were reported in Table 1.
i I
Ro_ses to Most Exposed Member of the General Public f rom Reactor Release and Other Uranium Fuel Cycle Sources There are no 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 array 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 f rom reactor effluent 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 mrom to any other organ.
Radiation Environmental Monitorina Procram Samolina Deviations There were no milk or vegetable sampling deviations during this reporting period.
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l Table 1 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD:
JANUARY 1 throuch DECEMBER 31, 1993 10 CFR Part 50 Appendix I Guidelines per 2-units site per year Gaseous Releases Maximum Site Boundary Gamma Air Dose (mrad) 1.74E-02 20 Maximum Site Boundary Beta Air Dose (mrad) 6.48E-02 40 Maximum Off-site Dose to any organ (mr e;a )
- 1.79E-01 30 Offshore Location Gamma Dose (mrad) 1.17E-03 Total Body (mrem)*
5.84E-03 Organ (mrem)*
6.74E-03 30 Liould Releases Maximum Off-site Dose Total Body (mrem) 2.99E-02 6
Maximum Off-site Dose Organ - Liver (mrom) 4.03E-02 20 Limiting Organ Dose Organ - Total Body 2.99E-02 6
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1 Tablo 2 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND SUPPLEMENTAL INFORMATION PERIOD: JANUARY 1 throuch DECEMBER 31, 1993 Gaseous Roloasos Maximum Site Boundary Dose Location (from Building Vents)
Sector WNW Distance (miles) 0.4 Offshore Location Within Site Boundary Sector ESE Distance (miles) 0.2 Pathway Inhalation Maximum Off-sito Sector SSE Distance (miles) 0.6 Pathways
- Plume, Ground, Inhalation, Vegetables Age Group Child Licuid Releases Maximum Off-site Dose Location Downstream Pathway Fish 4
.