3F0291-12, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1990
| ML20070F149 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/31/1990 |
| From: | Boldt G FLORIDA POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 3F0291-12, 3F291-12, NUDOCS 9103080148 | |
| Download: ML20070F149 (18) | |
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Florida Power C 0 R P O P AT I O N Crystal River Unit 3 Docket No. 50 302 February 28, 1991 3F0291-12 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Semiannual Radioactive Effluent Release Report
Dear Sir:
Pursuant to Title 10, Code of Federal Regulations, Part 50.36(a) (2) and Crystal River Unit 3 Technical Specification 6.9.1.5(d), Florida Power Corporation hereby submits the Crystal River Unit 3 Semiannual Radioactive Effluent Release Report for the period July 1, 1990 through December 31, 1990.
Sincerely, Yh G.L.
oldt, Vice President Nuclear Production Attachment
-REF:wla xc:
Regional Administrator, Region II Senior Resident Inspector NRR Project Manager pi IJ A
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POST OFFME BOX 219
- CRYSTAL RIVER, FLORIDA 32629-0219 + (904) 563-2943
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A Florida Progress Company
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SEMIANNVAL RADI0 ACTIVE EFFLVENT RELEASE REPORT 1990 JULY - DECDiBER FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 FACILITY OPERATING LICENSE N0, DPR 72 DOCKET N0. 50-302 FEBRUARY, 1991 Approved by: bdAAlO-h* horn Manager, Sitg/ Nuclear Services Date: M A5l4 I
i CONTENTS PA01 o INTRODUCTION 1
o TABULAR DATA SUMMARIES GASEOUS EFFLUENTS 2
LIQUID EFFLUENTS 4
RADWASTE SHIPMENTS 7
o GRAPMS GASEOUS RELEASES FISSION AND ACTIVATION PRODUCTS 9
LIQUID RELEASES
~
FISSION AND iCTIVATION PRODUCTS 10 TRITIUM 11 o ANNVAL DOSE SUMMARIES INDIVIDUAL DOSES 12 POPULATION DOSES 13 SITE B0UNDARY AIR DOSES 14 o UNPLANNED RELEASES 15 o RADI0 ACTIVE WASTE TREATMENT SYSTEMS 15 o ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM 15 o EFFLUENT MONITOR OPERABILITY 15 o 0DCM AND PCP 15 i
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INTRODUCTION This report is submitted as required by Technical Specification 6,9.1.5.d to Crystal River-Facility-Operating License No. OPR 72.
In accordance with Technical Specifications, the following information must be included in this report:-
A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant as outlined in Regulatory Guide 1.21 (Rev. 1, 1974) with data summarized-on a quarterly basis following the format of Appendix B thereof.
An annual summary of hourly meteorological data collected over the-previous years. (In lieu of submittal this data 11s maintained on site and is available to the NRC upon request)
An assessment of radiation doses due to the radioactive liquid and gaseous effluents released from the plant during the previous calendar year.
An assessment of radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE B0UNDARY.
An assessment of-radiation doses to the hypothetical worst case individual from reactor releases.
For each type of solid waste shipped off site:
Container Volume Total-Curie Quantity (specified as measur?d or estimated)
Principal Radionuclides (specified as measured or estimated)
Type of Waste (e.g., spent resin, compacted dry waste)
Type of container (e.g., LSA, Type A, Type B)
Solidification Agent (e.g., cement)
A list and description of unplarmed releases to-unrestricted areas.
A-description of any changes to the:
Process Control Program (PCP)-
Off-Site-Dose Calculation Manual (00CM)'
Radioactive Waste Treatment Systems A listing of new Environmental Radiological Monitoring Program dose calculation location changes identified by the land-use census.
Information relating. to effluent monitors being inoperable = for thirty-or more days.
TABLE 1 EFFLUENT AND WASTE DISPOSAL SEM! ANNUAL REPORT - 1990 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3
4 Error %
A.
Fission and Activation Gases 1.
Total Release Ci 4.42E+00 7.10E+02 30 2.
Average Release Rate for Period uC1/sec 5.56E-01 8.93E+01 3.
Percent of Technical Specification Limit 7.41E-02 5.64E+00 8.
lodines 1.
Total lodine 131 Ci 1.34E-04 1.97E-04 30 2.
Average Release Rate for Period uCi/sec 1.69E-05 2.48E-05 3.
Percent of Technical Specification Limit 2.39E-01 5.27E-01 C.
Particulates 1.
Particulates with half-lives > 8 days Ci 1.53E-06 2.61E-06 30 2.
Average Release Rate for Period uCi/:ec 1.93E-07 3.28E-07 3.
Percent of Technical Specification Limit 2.39E-01 5.27E 01 4.
Gross Alpha Radioactivity Ci 5.24E 05
< LLO D.
Tritium 1.
Total Release Ci 1.04E+01 6.09E+00 30 2.
Average Release Rate for Period uCi/sec 1.31E+00 7.66E-04 3.
Percent of Technical Specification limit 2.39E-01 5.27E-01
. _ _._ ~._ _ __
TABLE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1990 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINU0US MODE BATCH MODE Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 1.
Fis;1on gases araon Ci krvoton-85 Ci 6.04E-01 9.64E+00 krvoton-85m Ci krvoton-87 Ci krvoton 88 Ci xenon-131m C1 3.34E-02 7.87E 01 xenon-133 C1 4.06E-01 6.19E+02 3.33E+00 6.28E+01 _
xenon-133m Ci 8.01E+00 1.58E-02 6.48E 01 xenon-135 Ci 3.52E-02 8.88E+00 2.03E 03 1.92E-01 xenon 135m Ci xenon-138 Ci unidentified Ci Total for Period Ci 4.41E-01 6.36E+02 3.99E+00 7.41E+01
-2.
Iodines iodine 131 Ci 1.34E-04 1.97E-04 1.08E-08 6.41E-08 iodine-133 C1 8.40E-05 1.19E-05 9.68E 09 iodine-135 Ci Total for Period' Ci 2.18E 04 2.09E 1.08E-08 7.38E-08 3.
Particulates manaanese-54 Ci cobalt-58 Ci 3.96E-07 iron-59 Ci cobalt Ci 1.53E-06 1.56E-06 zine-65 Ci strontium 89 Ci 1.86E-09 2.54E-09 1.36E 7.38E-ll strontium-90 Ci 7.0lE-ll 5.93E 07-8.92E-10 molybdenum 99 Ci tellurium-132 Ci cesium 134 Ci cesium 137 Ci unidentified Ci Total for Period Ci 1.53E-06 2.61E-06 1.36E-10 9.66E-10 l
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TABLE 3 EFFLUENT AND WASTE DISPOSAL SENIANNAUL REPORT - 1990 LIQUID EFFLUENTS - SUNNATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3
4 Error %
A.
Fission and Activation Products 1.
Total. Release gases, alpha) (not including tritium, Ci 3.56E-02 1.41E-01 25 2.
Average diluted concentration during period 1.72E-08 4,32E 08 3.
Percent of applicable limit 2.70E-01 1.62E400 8.
Tritium 1.
Total Release C1 4.33E+01 2.93E+02 30 2.
' Average diluted concentration during period uri/mi 1.05E 05 3.35E-05 3.
Percent of applicable limit 3.50E 01 1.12E+00-C.. Dissolved and entrained gases 1.
Total release C1 1.73E 01 3.14E+00 25
- 2. ' Average diluted concentration during i
period uC1/ml 4.20E-08 3.52E 07 3.
Percent of applicable limit 8.60E-03 2.16E 02
- 0. -G_ross alpha-. radioactivity 1.-
Total release Ci 1.12E-05
< LLO 30:
E.
Volume of Waste released (prior to dilution)
- 1. ~ Batch and Continuous Modes Liters 4.89E+06 1.42E+07 10 j
F. -Volume of dilution ~ water used during period.
- l. ; Batch and Continuous Modes Liters 1.38E+10 3.29E+10-10 n
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4
l TABLE 4 i
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1990 LIQUID EFFLUENTS CONTINU0US MODE BATCH MODE Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 sodium 24 Ci 1.88E-05 chromium 51 Ci manganese 54 Ci 7.40E-04 5.10E-03 iron 55 Ci 1.20E-02 1.33E-03 cobalt-58 Ci iron 59 Ci 1.70E-04 cobalt-60 Ci 7.05E-03 5.13E-02 Finc-65 Ci rubidium-88 Ci 9.30E-04 strontium-89 Ci 2.50E 05 6.86E-05 strontium-90 Ci strontium 92 Ci 1.68E-05 6.54E 03 vttrium-91m Ci 1.35E 07 vttrium 92 Ci 3.64E-05 niobium 95 C1 4.14E 04 3.75E-03 zirconium-95 Ci 4.31E 05 5 13E-04 zirconium 97 Ci 9.llE-04 molybdenum 99 Ci technetium 99m Ci 3.61E-05 1.44E-04 ruthenium-103 Ci ruthenium-106 Ci 7.63E-03 silver-110m Ci 3.12E 05 1.79E-02 iodine 131 Ci 1,53E-04 1 17E-03 1
iodine-133 C1 3.22E-04 tellurium 132 Ci iodine-133 Ci cesium-134 Ci 6.06E-03 1.51E-02 gesium-136 Ci cesium 137 Ci 8.10E-03 2.70E-02 barium 139 Ci 2.60E-04 lanthanum-140 Ci 4.62E-04 cerium-141 Ci cerium-144 Ci 1.10E-03 unidentified Ci i
Total for period Ci 3.56E-02 1.41E-01 1
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- TABLE 4:(CONTINUED)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1990 LIQUID EFFLUENTS-CONTINU0US MODE-BATCH MODE Dissolved & Entrained Unit Quarter 3 Quarter 4 Quarter 3 Quarter-4 Gases araon-4!-
Ci krvoton-85 Ci 5.68E-02 krvDton 85m Ci 2.31E 04 1.76E-04 kryoton-88 Ci 1.51E-04 xenon-131m Ci 1.75E-02 xenon-133 Ci 1.64E-01 2.99E+00 xenon 133m Ci 1.26E-03 3.60E-02 xgnon 135 Ci 7.73E-03 3.57E 02 xenon-135m Ci tritium Cl 1.30E-01
' 4.33E+01 2.93E+02 i
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I TABLE 5 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1990 SOLID WASTE AND 1RRADIATED FUEL SHIPMENTS A.
SOLID WASTE SHIPPED OFFSITE F0P, BURIAL OR DISPOSAL (Non irradiated fuel)
Second 1.
Type of waste Unit 6-month Est. Total period Error, f, a.
Spent resins, filter sludges, evaporator m3 1.51E+01 bottoms, etc.
Ci 7.29E+01 20 b.
Dry compressible waste, contaminated m3 2.20E+02 equip, etc.
Ci 9.40E+00 50 c.
Irradiated components, control m3 rods, etc.
Ci d.
Other (describe) m3 2.71E+01 Solidified phosphoric acid and sludge Ci 5.40E+00 50 2.
Estimate
- of major nuclide composition (by type of waste in %)
a.
Cs-137 37.9 Co-60 11.8 Sb-122 1.2 Cs-134 14.4 Fe-55 9.5
.,Qo-58 12.0 Ni-63 8.7 b,
Fe-55 76.0 C -58 3.3 9
Ni-63 9.9 Cs-137 1.8 Co-60 5.5 C-14 1.0 c.
d.
Co-60 48.3 C-14 1.1 Ni-63 30.4 Fe-55 19.5 3.
Solid Waste Disposition Number of Shipments Mode of Transporation Destination 8
Exclusive Use Vehicle Barnwell, SC (CNSI) 4 Exclusive Use Vehicle Oak Ridge, TN (SEG)**
B.
IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transporation Destination 0
N/A N/A Curie values and principle radionuclides are determined by a combination of direct and indirect methods, and are therefore estimates.
Scientific Ecology Group (SEG) repacks secondary plant resin and non-compacted dry waste in order to reduce burial volume.
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TABLE 6 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1990 SHIPMENT
SUMMARY
DATE AND CONTAINER TOTAL WASTE CONTAINER SOLIDif.
SHIPMENT #
VOLUME
- CURIES
- PRINCir, RA010NUCL10ES TYPE TYPE AGENT 7 6-90 10 Cs 137, Fe 55, Cs 134, Sb 122, 90 56 120.3 50.9 Co 60, Ni-63 SR Hic N/A 8-17 90 10 0 Fe 55, Co-58, Ni-63, C-14, 90-66 100.0 2.0 Co 60, Cs-137 NW ST N/A 8-20-90 79 @
Fe 55, C-14, Ni-63, Cs 134, 90-67 7.5 0.5 Co 60, Cs-137 CW ST N/A 9-13 90 32 @
90-73 7.5 2.8 Co-60, Ni-63, Fe 55, C-14 SW ST CEMENT I 9 18-90 3 0 11.6 90 74 43 0 7.5 1.5 Co 60, Ni 63, Fe-55, C-14 SW ST CEMENT 9-19 90 2 0 11.6 Co-60, Cs-137, Ni 63, Fe-55, 90-75 43 0 7.5 1.1 C-14 SW ST CEMENT 9-25-90 20 Fe 55, Mn-54, Ni-63, C-14, 90 77 1280.0 4.9 Co-60, Co 58 NW ST N/A 10-23-90 1@
Fe 55, Pu-241, Cs-137, Cs-134, 90 85 1280.0 0.4 Ni-63, Co-60 NW ST N/A 11-14-90 10 Fe-55, C-14, Ni-63, Co-60, 90-90 1040.0 1.0 Cs-137 NW ST N/A
~12-10-90 10 Co-58, Cs-137, Co-60, Cs-134, 90-92 205.8 12.4 Fe 55, C-14, Ni 63, H-3 SR HIC N/A 12-14-90 10 Fe-55, C 14, Ni-63, C0 60, 90-94 1280.0 0.5 Co 58 NW ST N/A 12 17-90 10 Cs-137, Fe-55, Cs-134, Ni-63, 90-96 205.8 9.6 Co-58, Mn 54, Co-60, C-14 SR Hic N/A WASTE TYPE:
SR - Spent Resin NW - Non-Compacted Waste CE - Contaminated Equipment SC - Secondary Resin CW - Compacted Waste IC Irradiated Components F
- Filters EB - Evaporator Bottoms SW - Solidified Wastes
- Cono.1ner volume in cubic feet ST - Strong Tight 8
W W
6 GASEOUS RELEASES FISSION & ACTIVATION PRODUCTS Curies 100,000 m
10.000 l
1,000 77 78 79 80 81 82 83 84 85 86 87 88 89 90 Years
i i
LIQUID RELEASES 1
FISSION & ACTIVATION PRODUCTS l
Curies l
1 5
l 0.1 0.01 77 78 79 80 81 82.
83 84 85 86 87 88 89 90 Years
LIQUID RELEASES - TRITIUM Curies 1,000 C
\\
100 50 77 78 79 80 81 82 83 84 85 86 87 88 89 90 Years
TABLE 7
&NNUAL DOSES _19_IN0lV10VALS FROM ALL RELEASES OURING 1990 Whole Body Dose Oraan dose (mrem)
(mrem) lat ouarter Continuous Gaseous Effluents 2.22E 02 6.60E-02 Batch Gaseous Ef fluents 1.73E-01 4.92E 01 Continuous Liquid Effluents 7.63E-05 5.17E 03 Batch Liquid Effluents 2.42E 03 4.88E-02 2nd Ouarter Continuous Gaseous Effluents 8.38E 03 4.34E-02 Batch Gaseous Effluents 1.15E-03 4.85E 03 Continuous Liquid Effluents 8.57E-09 8.57E-09 Batch Liquid Effluents 5.33E-03 9.47E-02 3rd Quarter Continuous Gaseous Effluents 1.28E-02 1.29E-Oi Batch Gaseous Effluents 6.13E-03 9.37E-03 Continuous Liquid Effluents Batch Liquid Effluents 1.27E-03 1.35E-02 4th Ouarter Continuous Gaseous Effluents 9.64E-02 2.40E 01 Batch Gaseous Effluents 4.74E 02 1.25E-01 Continuous Liquid Effluents 1.86E-07 1.86E-07 Batch liquid Ef fluents 4.72E-03 8.09E-02 ANNUAL T0TAL.....................................
3.81E-01 1.24E+00 NOTE:
Quarterly doses due to gaseous releases are calculated using the highest site boundary dispersion factors (X/Q) and their corresponding deposition factors (0/Q).
Doses due to liquid effluents are calculated using only the dilution provided by Units 1, 2, and 3 cooling water (Gulf water dilution is not accounted for).
12 l
1 l
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TABLE 8 l
LANNUAL DOSES TO THE POPULATION FROM ALL RELEASES DURING 1990 1
Whole Body Dose Oraan dose 1st Ouarter Continuous Gaseous Effluents 8.62E-02 2.99E-01 Batch-Gaseous Effluents 8.20E-03 2.99E-02 Continuous Liquid Effluents 6.47E 03 1.30E-01 Batch liquid Effluents 1.86E-01 4.41E+00 2nd Ouarter Continuous Gaseous Effluents 2.55E 03 2.88E-03 Batch Gaseous Effluents 2.41E-04 1.31E-03
. Continuous Liquid Effluents.
1.13E-06 1.17E-06 Batch: Liquid Effluents _
2.71E-01 1.02E+01 3rd Ouarter Continuous Gaseous Effluents 2.08E-03 2.09E -Batch Gaseous Effluents 8.15E-05 1.88E 04 Continuous Liquid Effluents Batch LiquidLEffluents 1.20E-01 1.15E+00 4th-Ouarter Continuous Gaseous Effluents 1.74E-02 5.51E-02 Batch Gaseous Effluents 1.01E 4.24E 03 Continuous Liquid Effluents 2.45E-05 2.59E-05 Batch Liquid Effluents 3.05E-01 9.37E+00 ANNUAL T0TAL......................................
1.01E+00
'2.57E+01-NOTE:
Population ~ doses are cumulative doses to the estimated 488,000 people residing within 50 miles of.the plant.
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TABLE 9 SITE BOUNDARY AIR DOSE
SUMMARY
FOR 1990 Release Distance Beta Gamma 0uarter 1101c Sgtg Bilgi g6Adi mR di A
1 Batch N
0.83 1.17E 01 3.80E-02 Continuous N
0.83 8.66E-0!
2.93E-01 Quarterly Total 9.83E-01 3.31E 01 2
Batch NNW 0.86 8.22E 03 1.99E-03 Continuous NNW 0.86 9.77E-04 3.28E-04 Quarterly Total 9.20E 03 2.32E-03 3
Batch NW l.01 7.31E 03 1.83E-03 Continuous WSW 1,41 9.61E-05 3.76E-05 Quarterly Total 7.41E-03 1.87E-03 4
Batch WSW 1,41 1.78E-01 4.63E-02 Continuous SSW l.48 3.86E 01 1.32E-01 Quarterly Total 5.64E-01 1.78E-01 ANNUAL TOTAL 1.56E+00 5.14E-01 NOTE: Quarterly doses were calculated using the highest site bandary dispersion factor (X/0),
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.e UNPLANNULBELIA$1.1 There were no unplanned liquid or gaseous releases for the period of this report.
RADIOACTIVE WASTE TREATMENT SYSTEMS There were no significant changes to the radioactive waste treatment systems for the period of this report, fM 1flQRUjilAL RADIOLOGICAL MONITORING PROGRA_B The June 1989 land use census did not identify any new dose calculation locations, EFFLUENT MONITOR INSTRUMENTATION OPERABILITY No effluent monitor was inoperable for a period of thirty days or more for the period of this report, QD2 LAND PCP There were no changes to the Offsite Dose Calculation Manual or the Process Control Program for the period of this report, 15