ML20059D776

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Semiannual Radioactive Effluent Release Rept for Jan-June 1990 for Crystal River Unit 3
ML20059D776
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 06/30/1990
From:
FLORIDA POWER CORP.
To:
Shared Package
ML20059D770 List:
References
NUDOCS 9009070178
Download: ML20059D776 (15)
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Text

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l SEMIANNUAL RADIDACTIVE )

EFFLUENT RELEASE ,

REPORT 1990 JANUARY - JUNE FLORIDA POWER CORPORATION CRYSTAL RIVER - UNIT 3 FAClllTY OPERATING LICENSE NO. DPR 72 DOCKET NO. 50 302 AUGUST, 1990 l

4 Approved by: , ,

Mana9er,SiteNt/clearSerfces Date: . I!/

I SO 900907017e 900823 , I PDR ADOCK0500g{,g,&

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i CONTENTS PXtl o INTRODUCTION 1 ,

o TABULAR DATA SUMMARIES ,

GASEOUS EFFLUENTS 2 LIQU10 EFFLUENTS 4 RADWASTE SHIPMENTS 7 o GRAPHS GASEOUS RELEASES Fl!SION AND ACTIVATION PRODUCTS 9 LIQUID RELEASES FISSION AND ACTIVATION PRODUCTS 10 TRITIUM 11 o UNPLANNED RELEASES 12 o RADI0 ACTIVE WASTE TREATMENT SYSTEMS 12 o ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM 12 o EFFLUENT MONITOR INSTRUMENTATION OPERABILITY 12 o ODCM AND PCP 13 l

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JNTRODUCl.19ti This report is submitted as required by Technical Specification 6.9.1.5.d to Crystal River f acility Operating License No. DPR-72. In accordance with l Technical Specifications, the following information must be included in this l

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, for each type of solid waste shipped off site:

Container Volume Total Curie Quantity (specified as measured or estimated)

Principal Radionuclides (specified as measured or estimated)

Type Type ofofcontainer Waste (e.g(., spent e.g., LSA, resin, Type compacted A Type B) dry waste)

Solidification Agent (e.g., cement)

A list and description of unplanned releases to unrestricted areas.

A description of any changes to the:

Process Control Program (PCP)

Off-Site Dose Calculation Manual (ODCM)

Radioactive Waste Treatment Systems i A listing of new Environmental Radiological Monitoring Program dose I calculation location changes identified by the land use census.  ;

Information relating to effluent monitor instrumentation being inoperable i for thirty or more days, r

Information regarding meteorological data and environmental dose assessments l will be included in the year end semiannual report as required by Technical )

Specifications.  ;

In addition to the required data, graphs have been included so that the i current data for certain types of radionuclides can be quickly compared to  !

previous years values.

1 No adverse trends are evident in the data as the doses associated with the releases continue to be a small fraction of the limits.

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TABLE 1 EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT - 1990 SA5E005 EFFLUENTS $UMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1 2 Error %

A. Fission and Activation Gases i

1. Total Release Ci 6.58E+03 2.10E+01 30
2. Average Release Rate for Period uti/sec 8.44E+02 2.67E+00
3. Percent of Technical Specification Limit  % 5.56E+00 1.37E 02
8. Iodines
1. Total lodine - 131 Ci 4.06E-4 2.62E-5 30
2. Average Release Rate for Period uti/sec 5.22E-05 3.33E 06
3. Percent of Technical Specification Limit  % 3.53E+00 1.77E 01 C. Particulates

, 1. Particulates with half-lives > 8 days Ci 1.86E-07 4.68E-07 30 1

2. Average Release Rate for Period uC1/sec 2.39E-08 5.95E 08
3. Percent of Technical Specification Limit  % 3.63E+00 1.77E 01
4. Gross Alpha Radioactivity Ci s LLD 1.70E 08 D. Tristum II . Total Release Ci 1.64E+00 B.31E+00 30
2. Average Release Rate for Period uti/sec 2.llE-01 1.06E+00 l
3. Percent of Technical Specification Limit  % 3.53E+00 1.77E-01 l

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TABLE 2 EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT - 1990 GASE0US EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission gases araon-41 Ci krvoton 85 Ci 1.36E+01 2.37E+00 (rvoton 85m Ci 1.13E+00 3.32E-02 ,

(rvoton-87 Ci 1.17E400 (rvoton-88 Ci xenon-131rc Ci 6.02E+01 1.26E+01 5.21E-01 xenon-133 Ci 5.6)E403 6.52E+00 7.71E+02 _1.15E+01 xenon 133m Ci 4.90E+01 4.56E+00 9.15E-03 xenon 135 Ci 3.47E+01 1.51E+00 xenon-135m Ci xenon-138 Ci unidentified Ci

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Total for Period Ci 5.78E+03 6.52E+00 8.03E+02 1.44E+01

2. Iodines iodine-131 Ci 4.06E-04 2.62E-0E 6.33E-09 iodine 133 Ci 9.91E-06 1.41E-06 iodine-135 Ci Total for Period Ci 4.16E-04 2.76E-05 6.33E-09
3. Particulates mitag_anese 54 Ci cobalt-58 Ci iron-59 C1 cobalt-60 Ci zinc-65 Ci strontium 89 Ci 1 43E-07 strontium-90 C1 4.32E-08 4.68E-07 m21ybdenum-99 Ci tellurium-132 Ci cesium 134 Ci cesium-137 C1 cesium-138 Ci l

l l unidentified Ci l

Total for Period Ci 1.86E-07 4.68E-07 l-3

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. 1 TABLE 3 EFFLUENT AND WA5T5 DISPOSAL SENIANNUAL REPORT - 1990 LIQUID EFFLUENTS - SUNNATION 0F ALL RELEASES l

Unit Quarter Quarter Est. Total :

1 2 Error % t A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) Ci 1.83E-01 2.59E-01 25
2. Average diluted concentration during period uti/mi 8.05E-08 1.22E-07
3. Percent of applicable limit  % 4.66E+00 5.44E+00 B. Tritium
1. Total Release Ci 1.26E402 4.79E+01 30
2. Average diluted concentration during period uti/ml 7.49E 06 1.73E-05
3. Percent of applicable limit  % 2.50E-01 5.77E-01 C. Dissolved and entrained gases
1. Total release C1 4.08E+01 1.43E-01 25
2. Average diluted concentration during period uCi/mi 2.24E-06 5.16E-08
3. Percent of applicable limit  % 1.12E+00 2.58E-02 l D. Gross alpha radioactivity i
1. Total release Ci 1.37E-05 4.18E 05 30 l

E. Volume of Waste released (prior to dilution)

1. Batch and Continuous Modes Liters 1.24E+07 1.08E+07 10
f. Volume of <tilution water used during period
1. Batch and Continuous Modes Liters 3.86E10 7.91E+09 10 I

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l TABLE 4 EFFLUENT AND WA5TE DI5POSAL SEMIANNUAL REPORT - 1990 .

LIQUID EFFLUENTS t

CONTINUOUS MOUE BATCH MODE Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 sodium 24 Ci .

chromitim 51 C1 2.49E 02 i.05E-02 manganese-54 _ CJ 2.66E-03 5.84E 03 iron-55 _

N l.78E-03 5.89E-03 2.89E 02 cobal1 58 (- 9.67E-02 1.31E-01 iron !.9 C1 2.72E-03 8.2EL.04 cobalt-60 Ci 9.82E-03 5.91E-02 .

zinc-65 Ci ~

rubidium 88 Ci 5.42E-03 .

strontium 89 Ci 7.85E-05 1.34E-04 strontium 90 Ci 1.06E-04 1.90E-04 3.331 -05 strontium-92 Ci 1.971 03 niobium 95 Ci 3.51E-03 6J5E-03 zirconium-95 .Ci 2.55E-03 3.27E-03 zirconium 97 Ci 1.61E 04 Lnolybdenum 99 Ci 2.78E-03 ,

technetium 99m C1 4.64E-03 ruthenium 103 Ci 1.33E-03 1.13E-03 GLthenium 106 C1 1 silver-110m Ci 5.39E 03 iodine 131 _. C i 7.28E-03 L96E-04 indine-133 Ci 1ellurium 132 Ci 4.98E 04 2.49E 05 iidine 133 Ci 1.66E-04 smsium-134 Cl . 6.31E-04 ~ 6.42E 04 sgsium-136 Ci cesium 137 Ci 1.13E-03 2.12E-03 barium 139 Ci barium-140 Ci 1.16E-04 '

lanthanum 140 Ci 8.32E-03 3.76E 04 cerium 141 Ci 2.00E-04 8.57E-05 skrium 144 Ci 3.48E-04 i

unidentified C1  ;

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Total for period. Ci 1.89E 03 1.82E-01 2.59E-01 l 1

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TABL.E4(CONTINUED)

EFFLUENT AND WA$TE DISPOSAL SEN! ANNUAL REPORT1990 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Dissolved & Entrained Unit Quarter 1 Quarter 2 Quarter 1 Gases Quarter 2 troon 41 C1 9.06E-06 (rvoton-85 Ci 6.38E-02 (rvoton-85a Ci 1.95 -04 (rvaton-88 C1 2.90 :-04 xenon 131m C1 4.47E-01 9.17E 03 xenon-133 Ci xenon-133m 3.9&E-01 1.34E-01 C1 3.39E-01 xenon-135 Ci 4.06E 05 2.03E 01 5.48E-05 xenon-135m Ci tritium Ci 1.13E 01 3.64E 03 1.26E+02 4.79E401 i

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EFFLUENT AND WASTE D15POSAL SEMIANNUAL REPORT - 1990 SOLID WA$TE AND 1RRADIATED FUEL $HIPMENTS A. SOLID WASTE SHIPPE0 0FFSITE FOR BURIAL OR O!SPOSAL (Non irradiated fuel)

1. Type of waste Unit 6 month Est. lotal period Error, %
a. Spent resins, filter sludges, evaporator m3 4.33E+01 bottoms, etc. Ci 5.13E+00 20
b. Dry compressible waste, contaminated m3 6.16E+02 equip, etc. Ci 1.74E+01 50
c. Irradiated components, control m3 4.16E-01 rods, etc. Ci 1.10E+02 50
d. Other(describe) m3 Ci
2. Estimate
  • of major nuclide composition (by type of waste)
a. Cs-137 2.36E401% Co 60 8.75E+00%

Cs-134 1.86E401% Fe 55 7.15E+00%

H-3 1.71E+01%

Co-58 1.20E+01%

b. Fe-55 6.04E+01% Co 60 4.41E400%

Ni 63 7.89E+00% Cs-134 2.6811Q0%

Cs 137 5.48E400% Mn-54 2 63E400%

Co 58 4.73E+00%

c. Fe-55 6.57E+01% Co 60 3.30E+01%
3. Solid Waste Dis >osition Number of $11pments Mode of Transportation Destination 3 Transport Truck - Chem Nuclear Systems, Inc.

Exclusive Use Vehicle Barnwell, SC 13 SEG**, Oak Ridge, TN.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A ,

  • With the exception of Secondary Resin shipments all curie values and principle radionuclides are determined t.; indirect methods and are therefore estimates. Secondary Resin shipments are evaluated by direct (gamma spectroscopy) and indirect (applying scaling factors) methods, with the results being a combination of measured and estimated j value.
    • Scientific Ecology Group repacks and incinerates waste to reduce burial volume.

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TABLE 6 I l

i l EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT - 1990 ,

SHIPMENT

SUMMARY

DATE AND CONTAINER TOTAL WASTE CONTAINER SOLIDif.

SHIPMENT # VOLUME

  • CURIES PRINCIPLE RADIONUCLIDES TYPE TYPE AGENT  :

26 Cs-134, Cs-137, Sr-89, H 3, 90 06 372 9.76E 4 Sb 122 SC ST ** NA 28 Cs-134, Cs-137, H 3, Sb 122, 90 08 372 3.29E 4 Sr 89 SC ST NA 2-13 Cs-134, Cs-137, H 3, Sb-122, 90 09 375 1.37E 3 Sr 89 SC ST NA 3-30 Fe 55, Co 60, Cs-134, Cs-137, 90-13 1280 1.87 l-131, Ni 63 NW ST NA 45 Fe 55 Co 60, Cs 137, Ni 63, 90 15 1280 1.28 Cs-134 NW ST NA 4-10 Fe 55 Co 60 90 17 1280 3.49 Ni 63,, 00-58, Cs-137, 1-131, NW ST NA 4 20 Co 58 Co-60 90 20

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. 205.8 H 3, $b-122 , Cs-134, Cs-137, SR HIC *** NA 4-25 Co 58, C0 60, Cs 137, Ni 63, 90 22 2 9 1280 1.63 Fe 55 NW ST NA 51 Co 58, Co 60, Cs 137, Cs 134, 90 26 2 9 1280 0.772 Ni-63 Fe 55 NW ST NA 5-8 90 29 14.7 110. Co 60, Fe 55 IC SS Liner NA 5 16 Cs-134, Cs-137, Fe-55, Ni-63, 90 36 2 9 1280 0.349 Pu 241 NW ST NA 5 25 Co 58, Co-60, Cs 137, iti-63, 90-41 2 9 1280 2.79 Fe-55 NW ST NA 1

Co-58 Co 60, Cs-137, Ni-63, 6-6 90-45 2 9 1280 1.13 Fe 55 NW ST NA 6-14 Co 58, Co 60, Cs-137, Ni-63, 90 48 2 9 1280 2.08 Fe 55 NW ST NA 6-18 Co 58, C0-60, H 3, C-14, Ni-63, 90 49 205.8 1.98 Fe-55 SR HIC NA 6-29 90 55 2 9 1280 2.03 Co 58, 00 60, Ni-63, Fe-55 NW ST NA 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

  • Container volume in cubic feet ** ST - Strong Tight *** High Integrity Container 8

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GASEOUS RELEASES FISSION & ACTIVATION PRODUCTS Curies 100,000 10.000 .-

1,000 -

77 78 79 80 81 82 83 84 85 86 87 88 89 90 Years we

  • 9 di Curies 1

0.1 -

b k

0.07 e , , '

h 77 78 79 g 8 84 sh5 g6 87 Years

LIQUID RELEASES - TRITIUM Curies 1.000

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50 80 81 82 83 84 85 86 87 88 89 go Years T m v- _ _ _ _. -.-.*

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l UNPLANNED RELEASES I l

l There were no unplanned liquid or gaseous releases for the period of this report.

RADI0 ACTIVE WASTE TREATNENT SYSTEMS There were no significant changes to the radioactive waste treatment systems for the period of this report. '

ENVIRONNENTAL RADIOLOGICAL NONITORING PROGRAN The June 1990 land-use :ensus did not identify any new dose calculation locations.

EFFLUENT MONITOR INSTRUMENTATION OPERABILITY This report is submitted pursuant to Technical Specification 3.3.3.9, Action b to describe reasons for inoperability of flow element WD 19-FE. This flow rate monitor was inoperable from February 3,1990 until June 19, 1990. ,

Flow element WD-19-FE measures the flow of effluent gases during releases from the Waste Gas system. Effluent flows from one of three Waste Gas Decay Tanks, through control valve WDV-857, WD-19 FE, and the Auxiliary Building l Ventilation Filters and is monitored by RM A2.

! The flow element has been rendered inoperable on several occac%s due to moisture condensing in the gas lines. Moisture caused corrosion of the metallic bearings within the flow element. Corroded bearirgs resulted in diminished or lost flow element output.

In January of 1990, plant engineers decided to replace the flow element with an element equipped with jeweled bearings, which would not be subject to moisture induced corrosion. Replacement parts were received in May,1990.

The new flow element was installed on June 18, 1990 and returned to service on June 19, 1990.

The extended period during which the monitor was inoperable was caused by long lead times for procuring parts. Crystal River Unit 3 was in a refueling outage from March 14, 1990 to June 23, 1990. During this period, the Waste Gas system was aligned directly to the Auxiliary Building Ventilation Filters.

This alignment bypassed WD-19-FE.

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9.sCM AND PCP 1 1

A description of the cb v ,. to the ODCM (Rev. 15) follows. The revised pages have also been includew. 'The PCP was not changed.

EASA 60 Correct typographical error: 1.73x106 changed to 1.73x105 87,88 Added a definition of

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