3F0289-17, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1988
| ML20235S172 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/31/1988 |
| From: | Johnson S FLORIDA POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 3F0289-17, 3F289-17, NUDOCS 8903060162 | |
| Download: ML20235S172 (27) | |
Text
{{#Wiki_filter:. - - - o . e a SDEAIMRL RADIOACTIVE EFFIDDrf RELEASE REKRP 1988 JULY - IECDEER i FINIIR POWER CORMRATION CRYSTAL RIVER - UNIT 3 FACILTIY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 FEBRUARY, 1989 l Approved by: bN +h Manager, Site Nuclder Services l Date. a4.3/ 81 l l l 8903060162 DR 881231 ADOCK 05000302 PNU
\
d 02 M NIS EhGG o INIRODUCTICN 1 o 'IABUIAR IEA SEPHARIES l
, GASEQUS EFFIIENTS 2 !
LIQUID EFFIIENIS 4 I RADi@STE SHIINENTS 7 l l o TRDID GRAPHS l GASEQUS REIEASES FISSICH AND ACTIVATION PRODUCIS 9
'IRITIt.M 10 LIQUID REEEASES FISSICH AND ACTIVATION PRODUCTS 11
'IRITILM 12 SOLID RADWASTE SPINT RESINS, EIC 13 IIE CINPRESSIBIE WASIE, EIC 14 o ANNUAL DOSE SG MARIES INDIVIDUAL DOSES 15 POIUIATION DOSES 16 l
SITE BOUNDAIN AIR DOSES 17 o UNPIRNED RELEASES 18 o RADIOACTIVE WASTE 'IREADENT SYSTEMS 18 o DWIRONMENIAL RADIOIDGICAL No PROGRAM 18 o EFFIIENT PONTIOR OPERABILITY 18 o OD04 AND PCP 19 i
INIRIIK:TEBi
'Ihis report is subnitted as required by Technical Specification 6.9.1.5.d to i Crystal River Facility Operating License No. DPR-72. In accordance with Technical Specificaticris, the following information must be included in this report:
A ananary of the quantities of raMewtive liquid and emaarum effluents and solid waste released frcan the plant as outlined in Regulatory Guide 1.21 (Rev.1,1974) with data sansnarized on a quarterly basis following the format of Appendix B thereof. An annual ananary of hourly meteorological data collected over the previous year. (In lieu of subnittal this data is maintained on-site and is available to the NRC upon request) An annansunent of radiaticrt riewaaa due to the radioactive liquid and gaseous effluents relaaaewi frun the plant during the previous calendar year. An aaaaa=nant of radiation tier.aa frcan radioactive liquid and emaacun effluents to MDiBE:RS OF 'IHE RJBLIC due to their activities inside the SITE
!!OUNDARY.
An anaaaanant of radiation <iev=aa to the hypothetical worst case individual fran reactor releases. For eacit type of solid waste shipped off site: Cantainer Volume
'Ibtal Curie Quantity (specified as measured or estimated)
Principal Radionuclides (specified as measured or estimated) Type of Waste (e.g., spent resin, er=raeted 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 tuuan:,Licted areas. > l A description of any changes to the: Process Control Fiwtmu (PCP) ' Off-Site Dose Calculation Manual (OD04) Radioactive Waste Treatment Systems A listing of new Envium-ud.al Radiological Monitoring Fxwtmu dose i calculation location changes identified by the land-use census, i Information relating to effluent monitors being inoperable for thirty or more days. In addition to the required data, trend graphs of curies released per six month period have bun incitried in order to put the current data into historical perspective. l l
'IRBm 1 EFFIMNP AIO WSIE DISPOSAL SEMIMMRL REEGE - 1988 GASEOLE EFFIIENIS - SGHEICN OF AIL REEASES Unit Quarter Quarter Est.'Ibtal 3 4 Error %
A. Fission ard Activatical Gases
- 1. 'Ibtal Release Ci 2.17E+02 2.85E+03 110
- 2. Average Release Rate for Period uCi/sec 2.73E+01 3.59E+02
- 3. Percent of 'I4K:hnical Specification Limit % 6.75E-01 5.50E-00 i B. Iodines l
- 1. 'Ibtal Iodine - 131 Ci 2.22E-06 9.62E-04 110
- 2. Average Release Rate for IV.riod uCi/sec 2.79E-07 1.21E-04
- 3. IV.rcent of Technical Specification Limit 5.71E-01
% 8.80E-00 l
C. Particulate l
- 1. Particul e s with half-lives > 8 days Ci 4.62E-08 8.30E-07 100
- 2. Average Release Rate for Period uCi/sec 5.80E-09 1.11E-07
- 3. IVrcent of Technical Specification Limit % 5.71E-01 8.30E-00
- 4. Gross Alpha Radioactivity C1 3.21E-08 4.39E-07 D. Tritium l 1. 'Ibtal Release C1 2.36E-00 2.98E-00 90 l l
- 2. Average Release Rate for Period uCi/sec 2.97E-01 3.75E-01 l
- 3. Percent of 'Ibchnical Specification Limit % 5.70E-01 8.80E-00 l \
i 2 ' l
'IABLE 2 EFFIDPRP MO MPRIE DISPOERL SDUNHRL REEGT - 1988 GASEIXE EFFIIENIS - G0WD IEVEL REMASES CatTrINUOUS PODE BNICI } ODE l Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fissicri gases aruon-41 Ci krypton-85 Ci 4.99E+00 1.58E+01 l kIvoton-85m Ci 6.86E-00 1.13E-02 1.28E-02 !
krypton-87 Ci krypton-88 Ci i xenon-131m Ci 3.19E+01 2.51E+00 7.32E+00 I xenon-133 Ci 7.71E+01 2.30E+03 1.28E+02 4.28E+02 l xenon-133m Ci 7.80E-01 2.91E+00 xenon-135 Ci 2.76E+00 4.96E+01 4.19E-01 7.91E-01 xenon-135m Ci xenon-138 Ci unidentified Ci
'Ibtal for Period Ci 7.99E+01 2.39E+03 1.37E+02 4.55E+02
- 2. Iodines iodine-131 Ci 2.26E-06 5.00EH)4 4.16E-04 iodine-133 C1 1.48E-05 3.09E-05 l iodine-135 Ci l Total for Period Ci 2.22E-06 5.15E-04 0.00E-00 4.47E-04~
- 3. Particulate mancanese-54 Ci
.gobalt-58 Ci iron-59 Ci cabalt-60 Ci zino-65 Ci s'uvutium-89 Ci 4.62E-08 5.61E-07 1.97E-10 s'uvulium-90 Ci 2.69E-07 1.67E-10 nelvbdenum-99 Ci tellurium-132 Ci cesium-134 Ci cesium-137 Ci slum-138 Ci unidentified Ci 'Ibtal for Period Ci 4.62E-08 8.30E-07 0.00E-00 3.64E-10 3
ThEE 3 EFFIDEMP AND MASTE DISPOSAL SEKDUGEUL RERRP - 1988 IJQUID EFFEEMS - SGGGTIN OF AIL REZEhSES Unit Quarter Quarter Est.7btal , 3 4 Error % i A. Fissicn and Activation Products
- 1. 7btal Release (not including tritium, gases, alpha) Ci 3.22E-02 3.50E-02 100
- 2. Average diluted cum =sbation durirq period uCi/ml 2.20E-08 7.21E-08
- 3. Percent of applicable limit % 2.62E-01 1.76E-01 B. Tritium j l
- 1. Ibtal Release Ci 1.97E+02 9.68E+01 40
- 2. Average diluted cu..mkution durirn period !
uCi/ml 1.28E-05 1.32E-05
- 3. N.Icent of applicable limit % 4.27E-01 4.40E-01 !
C. Dissolved and entrained gases
- 1. Ibtal release C1 1.40E+01 9.23E-00 100
- 2. Average diluted cuuuibution duriry l period uCi/ml 8.68E-07 1.19E-06
)
- 3. Percent of applicable limit % 4.34E-01 4.40E-01 D. Gross alpha radioactivity
- 1. Total release Ci 3.26E-06 <LT.D 100 E. Volume of Waste released (prior to dilution)
- 1. Batch and Continuous Modes Liters 9.61E+06 9.16E+06 10 ,
1 F. Volume of dilution water used during period
- 1. Batch and Continuous Modes Liters 3.36E+10 1.83E+10 10 4
'5BN 4 EFFIDENF ADO MhSE ESF0 SAL SENDHEIAL REREF - 1988 IIGTID EFFIDENIS owrIN000S PODE: BNIGI} ODE Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 sodium-24 Ci duunium-51 Ci mamanese-54 Ci 3.78E-04 2.63E-04 iron-55 Ci 1.04E-03 2.17E-03 9.79E-04 cobalt-58 Ci 1.52E-03 1.26E-02 iron-59 Ci otalt-60 Ci 5.72E-03 4.43E-03 1
zino-65 Ci rubidium-88 Ci 1.13E-03 1.68E-03 l strontium-89 Ci 5.93E-04 3.99E-04 5.42E-04 l strontium-99 Ci 4.38E-05 5.84E-05 4.49E-05 l strontium-92 Ci 1.54E-03 6.98E-04 niobium-95 Ci 2.79E-05 4.02E-05 __ zirconium-95 Ci zirconium-97 Ci 2.09E-04 8.77E-05 molybdenum-99 Ci technetium-99m Ci 3.00E-04 ruthenium-103 Ci ruthenium-106 Ci 5.78E-04 3.07E-04 silver-110m Ci 4.67E-03 2.19E-03 iodine-131 Ci 9.67E-04 2.05E 03 iodine-133 Ci 3.59E-04 3.97E-05 te11urium-132 Ci iodine-133 Ci cesium-134 Ci 3.92E-03 1.88E-03 cesium-136 Ci cesium-137 Ci 8.55E-03 4.17E-03 barium-139 Ci lanthanum-140 Ci 9.20E-04 l oerium-141 Ci j oerium-144 Ci 1 unidentified Ci l Total for period Ci 0.00E-00 1.68E-03 3.22E-02 3.33E-02 5 l L__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
TMEE 4 (CINPDHD) EFFIDENT AND WME DISKSAL SMWGML RMutP - 1988 IZQUID EFFIDENIS CCNFINUQUS LODE BAIOi MXE Dissolved & Entrained Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Gases aruon-41 Ci - krvoton-85 C1 1.27E-02 4.66E-02 krvDton-85m C1 1.90E-03 6.66E-04 l krvoton-88 Ci 1.45E-04 xenon-131m Ci 1.33E-01 1.16E-01 xenon-133 Ci 4.28E-04 1.36E+01 8.96E-00 xenon-133m Ci 1.38E-01 7.08E-02 i xenon-135 Ci 1.04E-01 3.73E-02 l xenon-135m Ci tritium C1 1.57E-01 1.97E+02 9.66E+01 1 IKTTE: '1here wre no continuous liquid releases durirg the third quarter. l l l l l l l 6 1
'D R E 5 EFFIDENT AIO WASE DISPOSAL SEMDHERL REREP - 1988 SOIJD WASIE AND IRRADIA'IED PUEL SHIIMENIS A. SOLID WASTE SHIPPED OFFSITE FOR HJRIAL OR DISPOSAL (Non irradiated fuel) )
l Second
- 1. Type of waste Unit 6-manth Est. 'Ibtal period Error, %
- a. Spent resins, filter sludges, evaporator m3 2.16E+01 bottm s, etc. Ci 2.30E+02 20
- b. Dry canpressible waste, contaminated m3 7.13E+01 equip, etc. Ci 1.64E-00 50
- c. Irradiated ow_nts, control m3 rods, etc. Ci
- d. Other (describe) m3 Ci
( 2. Estimate
- of major nuclide composition (by type of waste)
- a. 00-60 6.42E+01 %
Co-58 1.68E+01 % Mn-54 1.07E+01 %
- b. Fe-55 5.01E+01 % 00-58 3.90E+00 %
Ni-63 1.40E+01 % 00-60 1.41E+01 % Cs-137 5.50E+00 % 1 C. l d. I
- 3. Solid Waste Disposition Number of Shipnents Mode of Transportation Destination 7 Transport Truck - Chem-Nuclear Systems, Inc.
Exclusive Use Vehicle Barnwell, SC B. IRRADIATED WEL SHIINENIS (Disposition) Number of Shipnents Mode of Transportation Destination 0 N/A N/A With the exception of Secondary Resin shipments all curie values and principle radionuclides are determined by indirect methods and are thereore estimates. Secondary Resin shipnents are evaluated by direct (ganna spectroscopy) ani indirect (applyirq scalirg factors) methods, with the results being a ccsubination of measured and estimated value. l 7 l l
TMEE6 EFFIDENT MO MASIE IHSIOSAL SDENGGLL RElFGE - 1988 RIIIMENT SGMARY DATE AND CCNIAINER 'IUIAL HASTE CDNIAINER SOLIDIF. SHIENDE # VOIINE* CURIES PRINCIPIE RADICMXiTM TYPE TYPE AGDE 7-15 1 @ 120 Ni-63, Fe-55, Cb-58, 00-60, 88-20 8 @ 96 5.86E-01 Cs-134, Cs-137, C-14 NW ST** - 9-21 88-21 402.2 6.58E-04 CS-134, Cs-137, H-3, Fe-55 SC ST - 11-22 Cb-98, Cb-60, Mn-54, Sn-113, 88-22 120.3 1.98E+02 Sb-125 F Type B - 12-5 Cb-60, Cs-134, Cs-137, I-131, 88-23 86 @ 7.5 2.22E-01 'Ib-99 CW ST - ( 12-6 88-24 120.3 2.99E+01 Cb-58, 00-60, Mn-54, Ag-110m F Type B l - 12-12 Ni-63, Sb-125, H-3, 00-58, 88-25 120.3 1.63E+00 00-60, Cs-134, Cs-137, Mn-54 SR Type B - l 12-20 1 @ 102 Ni-63, 00-58, 00-60, Cs-134, 88-27 9 @ 98 8.27E-01 Cs-137, C-14 NW ST - 1 l l 1 I i WASIE TYPE: SR - Spent Resin NW - Non-Otanpacted Waste CE - Contaminated Equipnent SC - Secondary Resin CW - Ctanpacted Waste IC - Irradiated Ccanponents F - Filters EB - Evaporator Bottczns ! i o Container volume in cubic feet ** ST - StrorxJ Tight l 8 I _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ Q
1 l FIGURE 1 - - 1 GASEOUS RELEASES l FISSION AND ACTIVATION PRODUCTS
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0 FIGURE 2 -
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e -~ - FIGURE 6 - 1 i SOLID RADWASTE __ T~~
' DRY COMPRESSIBLE WASTE. - - - - -
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77 78 79 80 81 82 83 84 85 86 87 88 89 90 Year 14
AttatmL nne 70 INDIVTTYudB FKM ATr. pRTFAM IIRDU 1988 Whole Body Dose Oruan Dose . (mrum) (mrm) ) ist Ouarter 1 Continuous mm m Effluents 1.91E-02 3.98E-02 < Batch m_ m s Effluents 2.44E-03 7.59E-03 l Cbntinuous Liquid Effluents 1.29E-04 3.17E-03 Batch Liquid Effluents 1.30E-03 1.96E-02 1 I 2nd Ouarter Continuous m_ m m Effluents 3.23E-03 8.92E-03 Batch me m Effluents 3.30E-03 1.20E-02 Continuous Liquid Effluents - - Batch Liquid Effluents 7.88E-03 3.02E-02 3rd Ouarteg Continuous Gaseous Effluents 8.13E-03 1.59E-02 Batch mm Js Effluents f 8.63E-03 2.69E-02 Continuous Liquid Effluents - - Batch Liquid Effluents 1.01E-03 1.31E-02 k 4th Ouarter Continuous Gaseous Effluents 8.92E-02 3.25E-01 Batch Gaseous Effluents 2.55E-02 3.35E-01 Continuous Liquid Effluents 6.81E-04 7.55E-03 Batch Liquid Effluents 6.03E-05 1.26E-03 , Annual 7btal 1.71E-01 8.46E-01 { N7FE: Quarterly doses due to gaseous releases are calculated usirq the highest site bourdary dispersion factors (X/Q) and their corresponding l deposition factors (D/Q) . ! l Doses due to liquid effluents are calculated using only the dilution i provided by Units 1, 2, and 3 cooling water (i.e. Gulf water dilution l is not accounted for) . i i 1 q 15 I
MEERL nnRPR 'IO 'IEE 10EUIRPICN FIDI ATr. perFAqFM IIRDE 1988 Whole E'dv Dose Oraan Dose ! (Rem) (Ran) l ist Ouarter Continuous Gaseous Effluents 5.46E-03 1.82E-02 Batd1 mels Effluents 7.20E-04 2.78E-03 Continuous Liquid Effluents l 1.09E-02 2.67E-01 Batch Liquid Effluents 6.07E-02 2.22E-00 2rd Ouarter l Continuous m e ls Effluents 1.30E-03 4.10E-03 j Batch mm Effluents 6.20E-04 2.95E-03 I Continuous Liquid Effluents - - l j Batch Liquid Effluents 5.11E-02 3.64E-00 l L 3rd Ouarter l Continuous Gaseous Effluents 9.10E-04 2.45E-03 Batch Gaseous Effluents 1.84E-03 7.18E-03 Continuous Liquid Effluents - - Batch Liquid Effluents 1.08E-01 1.54E-00 4th Ouarter Continuous m_ m as Effluents 3.75E-02 1.23E-01 Batd1 Gaseous Effluents 6.71E-03 2.57E-02 Ocntinuous Liquid Effluents 6.34E-03 1.07E-01 Batch Liquid Effluents 5,14E-03 7.40E-01 Annual Total 2.97E-01 8.7CE-00 Note: Population doses are cumulative doses to the estimated 462,000 people residirg within 50 miles of the plant. 16
STIE B(XMDME AIR DOSE SW99RY PGl 1988 Release Distaroe Beta Ganna ouarter Hgde sector Miles mBads mRads 1 Batch NW 1.01 1.34E-02 4.20E-03 Contirmous WSW 1.41 5.27E-02 1.98E-02 Quarterly 7btal 6.61E-02 2.40E-02 2 Batch S 1.71 2.07E-02 5.67E-03 Contirmous WSW 1.41 1.11E-02 4.46E-03 Quarterly 7btal 3.18E-02 9.13E-03 3 Batch WSW 1.41 4.73E-02 1.48E-02 i Contirmous WSW 1.41 2.02E-02 7.33E-03 Quarterly 7btal 6.75E-02 2.21E-02 4 Batch NW 1.01 1.36E-01 4.27E-02 Continuous NSW 1.41 4.14E-01 1.46E-01 Quarterly 7btal 5.50E-01 1.89E-01 l Annual Total 7.15E-01 2.44E-01 i 17 i l
i IMPUNED REZEhSES l
'Ibere were no unplanned liquid releases for the period of this report. 'Ihere were !
two unplanned gaseous releases as h ibed below: l l I IRTE DESGIPTION 10-28-89 Steam relief due to reactor trip. Estimated release amount: 3.30E-4 curies 11-8-88 Leak frun Post-Accident Sampling Sih (PASS) cw p muis in CAV-2 valve alley j during operation of PASS. l Estimated release amount: 7.34 curies ' RADIQPCPIVE WASTE 'IREA'IMENT SYSIDE i
'Ihere were no significant changes to the radioactive waste treatment systems for
( the period of this report. [ DIVIEN1ENIAL RADIOIDGICAL KNPKRING PROGRAM
'Ibe June 1988 lard-use census did not identify any new dose calculation locations.
unutNP KNPITR ORRARTT.T'lY No effluent nonitor was inoperable for a period of thirty days or more. 18
OD3 AND PCP. Theze were several changes to the ODCM (Revision 12), the descriptions of which are provided below. The revised pages have also been incitried. The PCP was not charged. QXM 09MES PAgig DESCRIPTICH 22, 23, 24 Minor changes in wording to clarify how liquid effluent nonitor setpoints are determined when the monitor flush is 5 lower limit of detecticm of the monitor. 34 Provides an action point at which to confirm continued ccmpliance with 40CRF190(b) . 52 Revised to allow dose calculation to be perfonned using the nearest residence (as established by the land-use census). The nearest residence dose calculation results may be used to verify conformance with 7bchnical specification 3.11.2.3 19
Setpoint almlation 1.4-5 Plant T4w:harge Line Manitor (%L2) (datch Type palamaam) INIrwerIm Following ccmpletion of the analyses required by Section 1.2-4 and determina-tion of release rates and cracuation limits in accordance with Section 1.3-2, the monitor setpoint requires adjustaant to ensure that alarm and pathway isolation occur if nuclide u .a:u'uation limits are avmadad. ME'IHODOIDGY Evaporator Condensate Storage Tank or Iaundry and Shower Stmp Tank contents are circulated through radiation monitor RM-I2 and retuned to the auxiliary building sunp to obtain the actual count rate at %I2 for the u mcaation contained in the tank for rulease. 'Ihe r*=arved count rate is adjusted for re-lease flow, background and statistical counting variations, particular to this release flow path. 'Ihe resulting value is used as the alarnVtrip setpoint and WI2 is adjusted to this or a more conservative value prior to initiating the release. If the unsd. ration of radionuclides to be relaaaad is less than the l effluent monitor LID set "ICi/MPCi" equal to 1 and derive " Net CIE" frcxn the l l calibration curve by determining the CEM which cou-spads to 3E-7 pCi/ml. l CMGIATIW PM-12 Setpoint (CPM) = Net CPM x AF x (E + D) + Bkg + 3.3 VBkg (I C i/MPC1 ) x E where: Net CIM =
'Ihe r*=arved %I2 count rate, in cpo, less back-greurri, or obtained from the calibration curve.
AF = Administration Factor to account for error in setpoint determination. AF = 0.8. ECi /MPCi =
'Ihe ratio of the actual gama emittire constra-tiens (excluding dimanived and entrained ga=) of the !
tank contents to be relaaaad to the Maximum Per- I missible Cirmiaation (MPC) as listed in 10 CFR 20, ! Table II, Colunn 2 for unrestricted areas. 1 E =
'Ihe release flow rate of waste to be discharged in gallons per minute. A ==v4== flow rate of 100 gpn l will be used for the Evaporator Cordermate Storage Tanks arri 40 gpn for the Iaundry and Shower Simp Tanks.
D =
'Ihe dilutico flow from the Nuclear Services Sea Water system in gallens per minute.
Bkg = RM-I2 background count rate in epn. 3.3VBkg = A statistical spread cm the background count rate I which impus-d.s a 99.95% confidence level cn acnitor counting. 'Ihis factor is included to prevent inadver-tent high/ trip alarms due to ran&nn counts on the monitor. l REVS 09 12 l l
WLrit Calculation 1.4-6 Turbine milaf rg naas==rit nier+mrge Line Manitor (IM-L7) (Ctritinuous Type Dalma===) INm000CTIM The activity relaaamd through the Turbine Building namamant Disdarge Line ! Monitor W L7 is analyzed in accordance with Section 1.2-5. The setpoint is a fixed canoentration haamd on worst case ruclide released at the worst . case rate as described in the Methodology Section below. 1he monitor setpoint is adjusted to ensure isolation of the release pathway if ruclide w.-itration limits are avr=adad. Mr]EDOEIXN The alarnVtrip setpoint determination is based on the worst case assunption ; that I-131 is L7 thetoonly This assunption equates all ' counts en W I-131reelida with anbeing MPC %of 3 x 10 uci/ml. I-131 has the most conservative MPC of tha nuclides available to this release path and " visible" ' to %L7. The setpoint is hamad cri assuring 1 MFC or less of I-131 in the disdarge canal and is derarnined by deriviry the cpm from the gL7 calibration curve whicts ws --is.13 to a concentration of 3 x 10 uci/ml and applying the flow dilution factor, b%svand ocunts, and statistical counting variations. The resulting value is used as the alarnVtrip setpoint and RM-L7 is adjusted to this or a more c mservative value to maintain control on release conditions. j GLCUIATIW_ CIM x (E + D) RM-L7 Setpoint (CIM) = E + Bkg + 3.3' Bkg where:
~
CPM = The counts per minute wis+siing to 3 x 10 uci/ml (1 MPC I-131) fra the current RM-L7 calibration curve. E = 1he navi== release flow rate of water able to be dis d arged in gallons per minute. D = The dilution flow frun the Nuclear Services Sea Water system in gallons per minute. Bkg = The background count rate at RM-L7 in cpn. l 3.3V Bkg = A statistical spread on the ber.3vgvand count rate whicti I represents a 99.95% cxmfidence level on monitor counting. This factor is included to prevent inadvertent high/ trip alarms due to rande counts e the acrtitor. REV SION 12
Wint: rw1,m1=*4,w 1.4-7 Sarbine milding namammarit niedege Line M:stitor (NL7) (Betd1 Type Releases) l INIIEXIK3'ICH { l Following otspletion of the analyses requi. red by Section 1.2-4 and determination ! of release rates and concentration limits in accordance with Section 1.3-2, the { monitor setpoint requires adjustment to ensure that alarm and pathway isolation occur if mclida concentration limits are M. ME3fEDOHXiY Station Drain Tank (SDI-1) contents are circulated through radiation monitor
%L7 and returned to the sung to obtain the actual count rate at WL7 for the m m nt. ration ocntained in the tank for release. 'Ihe observed count rate is adjusted for release flow, background and statistical counting variations, particular to this release flow path. '2ha resulting value is used as the alarg/ trip setpoint and %L7 is adjusted to this or a more conservative value prior to initiating the release. If the concentration of radionuclides to be relaaama is less than the effluent monitor II.D set "Ici/MPCi" equal to 1 and derive " Net CRf' fran the calibration curve by determining the CPM which coil iu 2 to 3E-7 #C1/ml.
ChIEDIATICN
% L7 Setpoint (CEM) = + Bkg + 3.3VBkg (E C1 /MPC1) x E _
where: Net CEM =
'Ihe observed NL7 count rate, in cpn, less background.
AF = Administration Factor to account for error in setpoint determination. AF = 0.8.
=
Eci/MPCi 'Ihm ratio of the actual gamma emitting concen-trations (excluding r h lved and entrained gaaaa) of the tank contents to be released to the Maximum Permissible concentration (MPC) as listed in 10 CFR 20, Table II, Column 2 for tuu i.ricted areas. E =
'Ihe release flow rate of waste to be discharged in gallons per mimte. A mav4== ficw rate of 600 gpm will be used. ,
I D =
'Ihe dilution ficw frun the Nuclear Services Sea Water systan in gallons per mimte.
Bkg = WL7 background count rate in cyn. 3.3YBkg = A statistical spread cm the backgound count rate which i, nd.s a 99.95% confidence level on monitor countirq. 'Ihis factor is included to prevent inadvertent high/ trip alarms due to randczn counts en the nonitor. REVISION 12
4
'IDIRL DOSE SPECIFICKERN 2.3 (LIQUID AND GSE00S RE[ EASES)
'Ihe calendar year dose or dose cannitment to any mmber of the public, due to releases of radioactivity ard Indiation fran uranium fuel cycle sources shall be limited to less than or equal to 25 mrans to the whole body or any organ, (except the thyroid whidi shall be limited to less than or equal to 75 mrems).
'Ihis specification is satisfied by meeting specifications 4.1-1, 4.1-2, and 4.1-3.
If h exceed twia the limits of specifications 4.1-1, 4.1-2, and 4.1-3 then an analysis shall be performed to confirm ocmtinued ocmpliance with 40GR190(b) .
References:
- 1) '14dinical Specification 3.11.3 <
- 2) Plant Procedures
- 3) 40 GR 190 REVISION 12
DOSE GIIIIIATICH 4.3-2 (RADIOIODDES & PARI'ICIIIATES) The dose to an individual at or beyond the SITE BOUNDARY due to Iodine-131, Tritium and radioactive particulate with half lives of greater than 8 days is calculated as follows:
-8 D = 3.17 x 10 E WRi Qi where:
D = The radiation dose to an indivMm1 at or beyond the UNRESTRICTED AREA BOUNDARY, in mrum. Ri = The dose factor for each identified radionuclides i, in m2 (mrunVyear) per uCi/sec or arenVyear per uCi/mb . W = X/Q for inhalation pathway, 2.5 x 10 sec/m3 at the. site boundary and 7.5 x 10-7 sec/m3 atthecritica[lreceptor. W = D/Q for food and ground plane patlway,1.9 x 10-8 ,-2 at the site boundary and 5.7 x 104 m-2 at tim critical receptor. Qi = Total pCi of isotope i relaaaaa during the calendar quarter or calendar year, as appropriate. 3.17 x 10 ~8 = The number of years in one ammrd, yr/sec.
Reference:
NUREG 0133, Section 5.3.1 FSAR, Table 2-20 lEVS;0\; 12
ae t' % . ) i$GI2.D5"4 f 6 0'!O G% 1 c eOh iOO* l 10
+Wc'~)n$p:
C t e og 41O a,j esse I F:lairiclei ( F)c)sareer ; CORPORATION ) l 1 February 24, 1989 I 3F0289-17 j Document Control Desk l U.S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
Crystal River Unit 3 Docket No. 50-302 i Operating License No. DPH-72 < 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 Semiennual Radioactive Effluent Release Report for the period July 1, 1988 through December 31, 1988. ) l If you have any questions concerning this matter please contact this office. 9 1 i Sincerely, l Rolf C. Widell, Director Nuclear Operations Site Support HEF:wla i cc: Regional Administrator, Hegion II l 1 Senior Resident Inspector l k I l
$I Post Office Box 219
- Crystal River, Florida 32629 + Telephone (904) 795 3802 /f A Flonda Progress Company f J
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