3F0889-11, Semiannual Radioactive Effluent Release Rept,Jan-June 1989

Semiannual Radioactive Effluent Release Rept,Jan-June 1989

ML20246D111
Person / Time
Site:	Crystal River
Issue date:	06/30/1989
From:	Johnson S, Widell R FLORIDA POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F0889-11, 3F889-11, NUDOCS 8908250256
Download: ML20246D111 (19)

Text

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eo e e 8 o' ese Florida Power C O R P O R AT 10 N August 17, 1989 3F0889-11 U.S. Nuclear Regulatory Commission ATIN: Documnt Control Desk Washirgton, D.C. 20555 SURTECT: Crystal River Onit 3 Docket No. 50-302 Operatirg License No. DPR-72 Semiannual Radioactive Effluent Release Report

Dear Sir:

Pursuant to Title 10, Code of Federal Regulations, Part 50.36(a) (2) ard 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 January 1,1989 through June 30, 1989.

If you have any questions concerning this matter please contact this office.

Sincerely,

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< . r Rolf . Widell, Director Nuclear Operations Site Support REF:wla xc: Regional Administrator, Region II Senior Resident Inspector 8908250256 Es90630 FDR ADOCK 05000302 ' t R PDC POST OFFICE BOX 219 + CRYSTAL RIVER, FLORIDA 32629 0219 (904) 79 % 486 A Florida Progress Company

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SDiIA!R40AL RADICRCTIVE EITIUDTP REIZASE i

REPORT L

1989 JANUARY - JUNE l: . -

FIORIDA POWER CDRPORATIGi CRYSTAL RIVER - LNIT 3 FACILITY OPERATING IJCENSE NO. DPR-72 DOCKET NO. 50-302 AUGUST, 1989

. Approved by: bb .2 A a

Manager, Site ? lear Services Date: 3-9.56

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02f1TNIS l

PE o INIRODUCTICH 1 o TABUIAR IATA SUNRRIES CASEOUS DTIIHNIS 2 LIQUID EFFIIHNIS 4 RADWASTE SHIPMENIS 7 l-l.

o 'IREND GRAMiS CASBJUS REMASES FISSION AND ACITVATION PRODUCIS 9

'IRITIUM 10 LIQUID REGASES l

FISSION AND ACTIVATION PR)DUCIS 11 TRITIUM 12 SOLID RADRSTE SPENT RESINS, EIC 13 IRY CI2(PRESSIBLE WASTE, EIC 14 o UNPIANNED REIEASES 15 o RADICACIT/E WASTE TREXINENT SYSTDiS 15 o ENVIRCl@(ENTAL RADIOIDGICAL MONI'IORING PROGRAM 15 o EFFIIRNT IONTIOR INS'IRUMENIATION OPERABILITY 15 o ODQ4 AND ICP 16 i

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I Dm0LT)CTIQi

'Ittis report is sukunitted as required by Technical Specification 6.9.1.5.d ,

to Crystal River Facility Operating License No. DPR-72. In accordance with Tactinical Specifications, the following inforetion must be included j- in this report:

l A sumary of the quantities of radioactive liquid and gacarne effluents and solid waste released frtxn the plant as outlined in Regulatory Guide 1.21 (Rev. 1, 1974) with data summarized on a quarterly basis following the fonnat of Appendix B thereof.

p For each type of solid waste shipped off site:

1 Container Volume Total Curie Quantity (specified as measured or estimted)

Principal Radionuclides (specified as measured or estimted)

Type of Waste (e.g., spent resin, r=weted dry waste)

Type of container (e.g., ISA, Type A, Type B)

Solidification Agent (e.g., cement)

A list and description of unplanned releases to unrestricted areas.

A description of any changes to the:

Process Contrul Ft Wrwa (PCP).

Off-Site Ebse Calculation Manual (ODO()

Radioactive Waste Treat 2nent Systems A listing of new Environmental Radiological Monitoring Fr%tcun dose calculation location changes identified by the land-use census.

Informtion relating to effluent monitor instrumentation being inoperable for thirty or more days.

Informtion regarding meteorological data and environmental dose (

assessments will be included in the year-end semiannual report as required i by Technical Specifications.-

In addition to the required data, trend stogs of curies released per six month period have been included in order to put the current data into historical perspective.

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TMEE1 EFFIMNT MO MMITE DIS 10 SAL SEKDMGL REEUU - 1989 GASHIE EFFIMNIS - SQ99EICH OF AIL REIEASES Unit Quarter Quarter Est.htal 1 2 Error. %

A. Fission and Activation Gases

1. Etal Release Ci 8.30E+02 8.93E+01 110

2. Average Release Rate for Period uCi/sec 1.07E+02 1.14E+01

3. Percent of Technical Specification Limit  % 4.66E-01 5.55E-01 k B. Iodines

1. Total Iodine - 131 Ci 2.09E-04 1.50E-04 110

2. . Average Release Rate for Period uCi/sec 2.69E-05 1.91E-05

3. Percent of Technical Specification Limit  % 1.79E-00 1.56E-00  !

C. Particulate'

1. Particulate with half-lives > 8 days Ci 1.60E-07 1.19E-06 100 1

2. Average Release Rate for Period uCi/sec 2.06E-08 1.51E-07

3. Percent of Technical Specification Limit  % 1.79E-00 1.56E-00 -i

4. Gross Alpha Radioactivity Ci < LID 2.28E-08 D. Tritium

1. ' Total Release Ci 5.92E+00 5.70E+00 90

2. Average Release Rate for Period uCi/sec 7.61E-01 7.25E-01 1

3. Percent of Technical Specification Limit  % 1.79E-00 1.56E-00 I w-_ _- _- - - .i

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TMEE 2 EFFINNF AIO MMME IKSPOSAL SENDWNRL RERRP - 1989 GASHIE EFFIIENIS - GRIMD IEVEL REIEASES CONITUQUS M3DE BA'IDI M3DE Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

'1. Fission gases aruon-41 Ci krvaton-85 Ci 8.32E+00 7.97E-01 krvoton-85m Ci 5.72E-03 kivoton-87 Ci krvDton-88 Ci genon-131m Ci 2.16E+00 1.28E-02 xenon-133 Ci 6.26E+02 6.93E+01 1.85E+02 1.00E+01 xenon-133m Ci 4.03E+00 1.28E+00 2.09E+00 1.96E-01 xrson-135 Ci 1.82E+00 7.52E+00 8.51E-01 1.51E-01 xenon-135m Ci 5.52E-04 xenon-138- Ci unidentified Ci ,

Total for Period Ci I 6.32E+02 7.81E+01 1.98E+02 1.12E+01

2. Iodines iodine-131 Ci 2.00E-04 1.49E-04 9.05E-06 6.65E-07 iodine-133- Ci 1.46E-06 1.29E-04 2.63E-06 2.87E-07 iodine-135 Ci- , . .

3 I

Total for leriod Ci 2.01E-04 2. */8E-04 1.17E-05 9.51E-07

3. Particulate manaanese-54 Ci cobalt-58 Ci iron-59 Ci 5 cobalt-60 Ci zino Ci strontium-89 Ci 1.25E-07 9.13E-07 1.70E-10 strontium-90 Ci 3.52E-08 1.51E-07  !

molybdenum-99 Ci tellurium-132 Ci cesium-134 Ci 4.88E-09 cesium-137 Ci 7.01E-09 cesium-138 Ci t cerium-143 Ci 1.17E-07 l unidentified Ci i Total for Period Ci 1.60E-07 1.19E-6 1.70E-10 I

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TMEE 3 EFFIDENP AIO WMME DISKEAL fJMUNGL REKRP - 1989 IJ(NID EFFIDElf1S - SWOUGICN OF ALL REL' EASES Unit Quarter Quarter Est. Total 1 2 Error %

A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) Ci 6.31E-02 2.14E-02 100

2. Average diluted v.4a.= h ation during period uCi/ml 1.47E-07 4.39E-08

3. Percent of applicable limit  % 8.40E-00 8.40E-01 B. Tritium

1. Total Release Ci 5.60E+01 3.60E+01 40

2. Average diluted concentration during period uCi/ml 2.18E-05 2.38E-05 .

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3. Percent of applicable limit  % 7.27E-01 7.93E-01 1 I

C. Dissolved ard entrained gases

1. Tbtal release Ci 9.30E-01 7.24E-02 100

2. Average diluted concentration durirg period uCi/ml 3.48E-07 5.26E-08

3. Permnt of applicable limit  % 1.74E-01 2.63E-02 D. Gross alpha radioactivity 1

1. 7btal release Ci < LT.D 4.73E-06 100 E. Volume of Waste release:1 (prior to dilution)  ;

1. Batch and Continuous W Liters 5.75E+06 8.10E+06 10 F. Volume of dilution water used during period

1. Batch and Continuous Modes Liters 7.68E+09 5.00E+09 10 f i

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'DMEE 4 EFFIHNP AND 10SIE DISPOSAL SEMIADF'3L RER3R - 1989 LIQUID EFFIDENIS carrINDOUS LODE IRTCH MODE Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 sodium-24 Ci 3.38E-06 chtunium-51 C1 2.57E-03 2.55E-04 marnanese-54 Ci 5.59E-04 3.65E-04 11ur-55 Ci 1.02E-02 1.42E-03 1.40E-02 2.99E-03 cobalt-58 Ci 9.46E-03 3.79E 03 iron-59 Ci 1.38E-04 cobalt-60 Ci 8.3CE-03 5.97E-03 zinc-65 Ci rubidium-88 Ci stxuiLium-89 Ci 4.73E-05 5.46E-05 sL uilium-90 Ci 8.88E-07

=L uitium-92 Ci 5.06E-04 3.85E-04 vLL ium-92 Ci 1.30E-04 niobium-95 Ci 1.93E-04 1.33E-04 zirconium-95 Ci 3.73E-05 zirconium-97 Ci molybdenum-99 Ci 9.05E-04 3.65E-05 tedinetium-99m Ci _ 1.87E-03 1.11E-04 ruthenium-103 Ci 1.01E-04 rathenium-106 Ci s11ver-110m C1 1.50E-03 1.07E-03 iodine-131 Ci 5.63E-04 lodine-133 Ci te11urium-132 Ci iodine-133 Ci cesium-134 Ci 2.15E-03 1.74E-03 cesium-136 Ci cesium-137 Ci 5.53E-03 3.09E-03 barium-139 Ci barium-140 Ci 5.27E-05 lgothanum-140 Ci 3.78E-03 cerium-141 Ci

_ogrium-144 Ci unidentified Ci l

1 7btal for period Ci 1.02E-02 1.42E-03 5.28E-02 2.00E-02 TABW 4 (CINfDUED)

EFFIDENP AND WAS1E DISPOSAL SENDMUL RERRP - 1989 LIGJID EFFIDENIS CINTDUQUS KDE BATOI MODE Dissolved & Entrained Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Gases aroon-41 Ci krvDton-85 Ci 4.37E-03 krvoton-85m Ci 5.68E-05 krvoton-88 Ci xenon-131m Ci 1.10E-02 xenon-133 Ci 9.01E-01 6.86E-02 xenon-133m Ci 7.11E-03 1.84E-03 xenon-135 Ci 6.49E-03 1.97E-03 xenon-135m Ci tritium Ci 5.16E-02 2.80E-02 5.59E+01 3.60E+01 l~ l

'IABm 5 EFFIDEh? AIO hMS'IE DISPOSAL SDEMNIAL RERRI' - 1989 SOIJD WMTIE AND TiRRADIA'ITD FUEL SHIIMENIS A. SOLID WASTE SHIPPED OFFdut; FOR BURIAL OR DISPCCAL (Non irradiated fuel)

Second

1. Type of waste Unit 6-month Est. Total period Error, %

a. Spent resins, filter sludges, evaporator m3 1.29E+01 bottoms, etc. C1 1.91E+01 20

b. Dry u.mp=:ssible waste, contaminated m3 1.82E+02 equip, etc. Ci 1.80E+00 50

c. Irradiated components, control m3 rods, etc. Ci

d. Other (describe) m3 C1

2. Estimate

• of major nuclide composition (by type of waste)

a. Co-60 7.23E+01 % Mn-54 5.70E+00 %

l 'Cs-137 7.60E+00 % Cs-134 .~}.60E+00 %

C0-58 7.20E+00 %

b. Fe-55 4.35E+01 % Ni-63 1.21E+01 %

00-60 2.14E+01 % Cr-51 4.67E+00 %

Co-58 1.51E+01 %

3. Solid Waste Disposition Number of Shipnents Mode of Transportation Destination 5 Transport Truck - Chem-Nuclear Systens, Inc.

Exclusive Use Vehicle Barnwell, SC 6 Same SEG**

Oak Ridge, 'IN B. IRRADIATED FUEL SHIFtOTIS (Disposition)

Number of Shipnents Mode of Transportation Destination j' O N/A N/A With the exception of Secondary Resin shipnents all curie values and principle radionuclides are determined by indirect methods ard are therefore estimates.

Secorrlary Resin shipments are evaluated by direct (gama spectroscopy) ard l' indirect (applyirg realing factors) methods, with the results being a combination of measured and estimated value.

• • Scientific Ecology Group repacks secondary plant resin and non W M dry waste in order to redu burial volume, l

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'IABIE 6 EFFIIENT AND MASIE DIS 10 SAL SEMIMMRL REEGT - 1989 SHIIMENT SCHERY DATE AND CDICAINER 'IUTAL WASTE CDICAINER SOLIDIF.

SHIPME!E # VOI11ME* CIIRIES PRINCIPIE RADIONUCLIDES TYPE TYPE AGENT 1-24 00-58, Co-60, Os-134, Cs-137 89-2 205.8 1.18E+00 H-3, Ni-63 SR Type B NA 1-27 l 89-5 86 @ 7.5 4.30E-01 Co-60, Ni-63, Fe-55 CW ST** la 19 Cs-134, Cs-137, Sb-122, H-3, 89-16 386 2.50E-04 Fe-55 SC ST NA 4-21 Co-60, Cs-137, C-14, Ni-63, 89-19 86 @ 7.5 2.30E-01 Fe-55 CW ST la 4-26 89-20 380 9.66E-04 Cs-134, Cs-137, H-3 SC ST la 4-28 Cb-58, Co-60, Cr-51, Ni-63, 89-21 2,560 1.14E+00 Fe55 NW ST 1

la 5-3 89-22 380 3.98E-04 Cs-r4, Cs-137, H-3 SC .ST la 5-10 89-24 385.8 1.26E-03 Cs-134, Cs-137, Sb-122, H-3 SC ST NA  ;

5-12 89-25 120.3 1.79E+01 Co-60, Cs-134, Cs-137, Mn-54 F Type B NA 5-17  !

89-26 386 1.02E-02 Cs-134, Cs-137, Sb-122, H-3 SC ST la 6-5 24011.6 Fe-55, Co-60, Cs-134, Cs-137, 89-27 510 7.5 1.97E-01 Ni-63, Tc-99 CW ST la

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1 WASIE TYPE: SR - Spent Resin NW - Non-C%rpacted Waste CE - Contaminated Equip:ent SC - Secondary Resin CN - Cccpacted Waste IC - Irradiated Components F - Filters FB - Evaporator Battaras

• Container volume in cubic feet ** ST - Strong Tight 1

!KTTE: Shipaents 89-16, -20, -21, -22, -24, and -26 were sent to Scientific Ecology Group i for repackaging.

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;. -- FIGURE GASEOUS RELEASES FISSION AND ACTIVATION PRODUCTS 10,000 l

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1 IMPL1HGD REURSES

'Ihere were no unplanned liquid releases for the period of this report.

'Ihere were two unplanned gaseous releases as described below:  !

DMZ DESCRIPTION 1-25-89 Isak frun Post-Accident Sanpling System (PASS) unsa.ncs in CAV-2 valve alley during routine operation of system.

Estimated release arount: 0.41 curie 1-27-89 Isak frtra Post-Accident Sampling System (PASS) ccmptnents in CAV-2 valve alley during system troubleshooting.

Estimated release amount: 0.9 curie RADIOPCPIVE WASTE 'IREA'IMERP SYETIDE

'Ihere were no significant changes to the radioactive waste treatment systems for the period of this report.

DWIR019EWIAL RADIOLOGICAL ICNI'IMING WDGRAM

'Ihe June 1989 land-use census did not identify any new dose calculation locations.

EWIDENI' ENJ'!W DE75UWf!RTICN OPERANTTJ'IY This report is submitted pursuant to Technical Specification 3.3.3.9, Action b to describe reasons for inoperability and lack of timely corrective action for WI)-19-FE, the Waste Gas Decay Tank Flow Rate Monitor (item 1.b, table 3.3-13). 'Ihis flow rate monitor was inoperable from P+J -3r 28, 1988 until April 7,1989 (ref. NOCR 89-74) .

'Ihe monitor was 69 by water that had condensed in the discharge line.

'Ihe lack of timely corrective action was caused by a combination of events. 'Ibe major contributor was the lack of a single point of contact with responsibility to assure timely repair and resolution. During the repair of the flow element several additional discrepancies were found which required correcting and delayed a restoration of the flow element to operable. A procedure revision was e ca y to specify values in scfm instead of acfm, stan$ard instead of absolute. At one point the flow element was installed backwards due to misleading information on the discharge pipe. Approximately two nonths were taken to troubleshoot and repair the regulator valve for the discharge line, WIN-857.

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L ODCM AND FCP

'Ihere were no changes to the ODCM ard the PCP for the period of this report.

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