ML20118A375

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Effluent & Waste Disposal Semiannual Rept for First Half 1992
ML20118A375
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 06/30/1992
From: Creel G
BALTIMORE GAS & ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9209020049
Download: ML20118A375 (25)
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Text

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44 GALTIMORC GAS AND ELECTRIC i

! 1650 CALVERT CUFFS PARKWAY

  • LUSBY, MARYLAND 20657-4702 Gronot t catet Auaust 28,1992 vice entsinswe 6 un .m cuene

( o) aco-4 4 ts U. S. Nuclear Regulatory Commission t

Washington, DC 20555 ATTENTION: Document Control Desk -

SUBJEQ Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2: Docket Nos. 50-317 & 50-318 Semi-Annual Ef0uent Release Report Gentlemen:

Enclosed pi.:ase find the Semi. Annual Eftluent Release Report for the first half of 1992 as required by Unit 1 and 2 Technical Specification 6.9.1.8. As required, meteorological data is being kept in our files on site and will be available upon request.

Should you have any further questions regarding this matter, we will be pleased to discuss them with you.

Very truly yours.

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RED /JAS/CDS/bjd Enclosure cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC P. R. Wilson, NRC R.1. McLean, DNR J. H. Walter, PSC 01908a 00 a 9 q g (o 9209020049 920630 PDR R

ADOCK 05000317 PDR 1-[ h/f

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CALVERT CLIFFS NUCLEAR POWER PIANT

. EFFLUENT AND WASTE DISPOSAL SEMI. ANNUAL REPORT EPPLEMENTALINFORMATION Facility ICalvert Cliffs Nuclear Power Plant Licensee . Baltimore Gas & Electric Company

1. REGULATORY LIMITS A. Fission and Activation Gases L The instantaneous release rate of noble gases in gaseous efnuents shall not result in a site boundary dose rate greater than 500 mrem / year to the whole body ' or _ greater than 3000 mrem / year to the skin- (Technical SpeciGcation 3/4.1L2.1).
2. Go,scous Radwaste 'Ircatment System ~ and the Ventilation - Exhaust Treatment System shall-'oe used to reduce gaseous emissions when the-calculated gamma dose due to gaseous efnuents exceeds 1.20 mrad or the '

calculated beta dose due to gaseous effluents exceeds 2.40 mrad at the site-p boundary in a 92 day period (Technical Specification 3/4.11.2.4).

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3. The air dose at the site boundary due to noble gases released in gaseous effluents shall not exceed (Technical Specification 3/4.11.2.2):

10 mrad /qtr, gamma air 20 mrad /qtr, beta air 20 mradlycar, gamma air 40 mradlycar, beta air

4. - All of the above parameters are calculated according to the methodology specified in the Offsite Dose Calculation Manual (ODCM).-

B Indines and Particulates with Half Lives Greater than Eicht Days

1. The . instantaneous release rate of _ iodines _ and ' particulates in ' gaseous-effluents shall not result in a site boundary dose in excess of 1500 mrem / year to any organ (Technical SpeciGcation 3/4.11.2.1).
2. ' The Gaseous Radwaste Treatment System and the Ventilation Exhaust

- Treatment System shall be used to reduce radioactive materials in gaseous effluents when calculated doses exceed 1.8 mrem to any organ in a 92 day period at or beyond the site boundary (Technical Specification 3/4.11.2.4).

3. The dose to a member of the public at or beyond the site boundary from.

L iodine-131 and particulates with half lives greater than eight days in gaseous b - efDuents shall not exceed (Technical Specification 3/4.11.2.3):

15 mrem /qtr, any organ 1

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30 mrem & car, any organ less than 0.1% of the above limits as a result of burning contaminated oil.

4. All of the above parameters are calculated according to the methodology specified in the ODCht.

C. Liauid Ef0uep_g

1. The concentra.K.a cf radionuclides in liquid effluents from the plant shall not exceed the values specified in 10 CFR Part 20, Appendix B, for unrestricted areas (Technical Specification 3/4.11.1.1).
2. The liquid radwaste treatment system shall be used to reduce the concentration of radionuclides in liquid ef0uents from the plant when the calculated doses to unrestricted areas exceed 0.36 mrem to the whole txx!y, or 1.20 mrem to any organ in a 92 day period (Technical Specification 3/4.11.1.3).

i l 3. The dose to a member of the public in unrestricted areas shall not exceed l (Technical Specification 3/4.11.1.2):

3 mrem /qtr, total body 10 mrem /qtr, any organ 6 mrem / year, total txxly 20 mrem / year, any organ

- 4. All of the liquid dose parameters are calculated according to the methodology specified in the ODChi.

1 l- 11. STAXIhf Uht PERhtISSillLE CONCENTRATIONS l

A. Fission and Activation Gases Prior to the batch release of gaseous efnuents, a sample of the source is collected and L analyzed by gamma spectroscopy for the principal gamma emitting radionuclides.

The identified radionuclide concentrations are evaluated and an acceptable release rate is determined to ensure that the dose rate limits of Technical Specificatian 3/4.11.2.1 are not exceeded.

B. Todines and Particulates with Half Lives Greater than Eicht Days Compliance with the dose rate limitations for iodines and particulates is demonstrated by analysis of the charcoal and particulate samples of the station main vents. The chrecal samples are analyzed by gamma spectroscopy for quantification of any release of rediciodines. The particulate samples are analyzed by gamma spectroscopy for quantification of particulate radioactive material. Based on guidance provided in the ODChi, compliance with dose rate limits for the 2

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radiciodines and particulates may be based on a comparison of the actual measured release quantity over a sample period with a pre-estelished upper bound.

C. Liguid Efuuents The MPCs used for radioactive materials released in liquid effluents are in accordance with Technical Specification 3/4.11.1.1 and the values from 10 CFR 20, Appendix B, including applicable table notes. In all cases, the moic restrictive (lower) MPC found for each radionuclide is used regardless of solubility.

111, IECilNICAL SPEC _lFICATION REPORTING ltEOllutEMENTS (Section 6.9.1.8)

A. Previous Calendar Year (1990) Dose Assessment Summary Not Applicable. This assessment is required only in the Radioactive Effluent Release Report to be submittee within 60 days after January 1 of each year.

B. O CI'R 190 Total Dose Compliance n; Applicable. This assessment is required only in the Radioactive Ef0uent Release Report to be submitted within 60 days after January 1 of each year.

C. Solid Waste Report Requirements During the first half of 1992, the types of radioactive solid waste shipped from Calvert Cliffs were. radioactive resin, which was dewatered and shipped in high integrity containers, low level radioactive resin which was dewatened and shipped in strong, tight containers, and dry compressible waste, which was shipped as LSA waste in strong, tight containers. Appendix A provides a detailed breakdown of the waste shipments for the first half of 1992 per the categories specified in Technical SpeciGeation 6.9.1.8.

D. ODCM and Process Control Procram (PCP) Chances -

One change was made to the ODCM during the first half of 1992. The change was reviewed by POSRC and approved by the Plant General Manager, Calvert Cliffs Nuclear Power Plant, prior to implementation. The scope and basis for this change is discussed in Appendix B. In keeping with the requirement of the Technical Specification 6.17, a copy of the change to the CCNPP ODCM is enclosed in Attachment 1. Vertical lines in the right margin of the text denote the above referenced change with accompanying change number.

No changes were made in the PCP in the first half of 1992.

E. Radioactive Gaseous Efnuent Monitorine Instrumentation No efnuent monitors were out of service for greater than 30 days.

IV. AVERAGE ENERGY Not Applicable.

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V. hjEASUltEMENTS AND APPitOXIMATIONS AND TOTAL 1(ADIOACTIVITY A. Fission and Activation Gases

1. Batch Releases Prior to each batch release of gas from a pressurized gas decay tank, a sample is collected and analyzed by gamma spectroscopy using a Germanium (Ge) detector for the principal gamma emitting noble gas radionuclides. The total activity released is based on the pressure / volume relationship (gas laws) of the tank.

Prior to and after et 4 containment purge, a gas sample is collected and analyzed by gamma spectroscopy using a Ge detector for the principal gamma emitting noble gas radionuclides. The total activity released is based on containment volume and purge rate. Activity buildup while purging is also considered.

2. Continuous Releases A gas sample is collected at least weekly from the main vents and analyzed by gamma spectroscopy using a Ge detector for the principal gamma emitting noble gas radionuclides. The total activity released for the week is based on the total sample activity decay corrected to the midpoint of the sample period multiplied by the main vent flow for the week.

A monthly composite sample is collected from the main vents and analyzed by liquid scintillation for tritium. The total tritium release for the month is based on this sample analysis and the vent flow.

B. Iodine and Particulates 1, Batch Releases -

The total activities of radiciodines and particulates released from a pressurized gas decay tank, containment purges and containment vents are accounted for by the continuous samplers on the main vent.

2. Continuous Releases During the release of gas from the main vents, samples of iodines and particulates are collected using a charcoal and particulate filter, respectively.

Tk filters are removed weekly and are analyzed by gamma spectroscopy using a Ge detector for significant gamma emitting radionuclides. The total activity released for the week is based on the total sample activity decay corrected to the midpoint of the sample period multiplied by the main vent flow for the week. These weekly particulate filters are tLen composited to form monthly and quarterly composites for the gross alpha and strontium 89 and 90 analyses.

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a.

.Ae C. Liauid Efiluents

1. Batch Releases Prior to the release of liquid from a waste tank, a sample is collected and analyzed by gamma spectroscopy for the principal gamma emiiting radionuclides. To demonstrate compliance with the requirements addressed in Section I.C.1 above, the measured radionuclide -concentrations are compared with the allowable MPCs; dilution in the discharge conduit is considered, and an allowable release rate is verified.

The total activity released in each batch is determined by multiplying the volume released by the concentration of each radionuclide. The actual volume released is based on the difference in tank levels prior to and after the -

release. A proportional composite sample is also withdrawn for each release and this is used in turn to prepare monthly and quarterly composites for ine gross alpha, strontium 89 and 90, and tritium analyses.

2. Continuous Releases Prior to discharge of any continuous releases, a sample is collected and analyzed - by gamma spectroscopy for the principal gamma emitting radionuclides. The measured radionuclide concentrations are compared with the allowable MPC concentrations in the discharge conduit, and an allowable release rate is verified.

When steam generator blowdown is discharged to the circulating water conduits, it is sampled daily and these samples are used. in turn to prepare a weekly blowdown composite based on each day's blowdown. The weekly

_ composite is analyzed- by gamma spectroscopy for the principal gamma emitting radionuclides. These results are multiplied by the actual quantity of blowdown to determine the total activity released. The weekly composite is also used to prepare monthly and quarterly composites for tritium, gross alpha, and si:7ntium 89 and 90 analyses.

l -During primary to secondary leakage, the secondary system becomes

= contaminated and subsequently, contaminates the turbine plant sumps. This low level activity (mostly tritium) water is released directly to the Chesapeake

' Bay. This water is sampled at least weekly and composited. These samples are added to a composite based on the amount released during that week.

The composite sample is analyzed monthly for tritium and for the principal gamma emitting radionuclides. The results are multiplied by the actual l quantity of liquid released to determine the total activity released. His composite is used to prepare quarterly samples for strontium 89 and 90 analyses.

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kr D. limt!Lation of Total Error Total error on all releases was estimated using as a minimum the random counting error associated with typical teleases. In addition to this random error the following i systematic errors were also examined:

1. L! quid a) Error in volume of liquid released prior to dilution during batch releases.

b) Error in volume of liquid released via steam generator blowdown.

c) Error in amount of dilution water used during the reporting period.

2. Gases a) Error in main vent release flow, b) Error in sample flow rate.

c) Error in contalnment purge 2.ase .L,w.

d) Enor in gas decay tank pressure.

Where errors could be estimated they are usually considered additive.

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VI. IIATCll itEl&tSES

.1 192 IST 2ND OUAltTEB OlfAltTElt A. Liquid

1. Number of batch releaser. 4.10E+ 01 8.70E+01
2. Total time per,od for batch releases (m'n) 1.91E+t., 1.00E +N 3 Maximum time period for a batch release (min) 1.97E+03 1.05E + 03
4. _ Average time periou for batch j releases (min) 4.t%E + 02 1.15E+02 j
5. Minimum time period for a l batch release (' a;n) 3.00E + 00 2.00E + 00 l

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6. Average stream flow during periods of effluent into a flow ng stream i (liters / min of dilution a. ater) 3.98E+ 06 4.38E + 06 l l

II. Guwous i

1. Number of batch releases 2.30E+01 3.10E + 01 j
2. Total time period for batch releases (min) 2.31E+ N 1.23E+05 1
3. Maximum time period for a bach release (min) 7.31 E+03 2.14E + 04 4, Average time period for batch I release (min) 1,01U+03 3.96E+03
5. Minimum time period for a batch release (min) 1.67E-01 1.00E +00 t

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. 1, Vll. AllNORMAI, REI,1%SES IL91 IST 2ND OtJARTI:R OllARTER A. LLqidd

1. Number of releases 0-
2. Total actkity released (Curies) 0- 0-II, ihawous
1. Number of releases 0- 2. Totalrictivity releases (Curies) 0-i l

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- [311MEtEG GUIDjiM1 CAINERT C1.IITS NUCI. EAR POWER PLANT EFFl.UENT AND WASTE DISPOSAL,SEMl ANNUAL, REPORT ,

FIRST llAl.F.1992 GASEOUS EFFI,UENTS .EUMMATION OF Al.1, REI EASES  !

I IST 2ND EST. TOTAL A. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER ERROR, %

1. Totalllelere Ci 5.66E + 03 8.32E + 01 15.40E+ 00
2. Average release rate for period uCi/sec 7.20E + 02 1.06E + 01
3. Percent of Tech. Spec. limit (!) 96 9.70E-02 1.66E-03
4. Percent of Tech. Spec. limit (2) Vc 5.38E +00 7.62E-02  ;
5. Percent of Tech. Spec. limit (3) 96 1.44 E+00 2.24E-02 ,
6. Pereent of Tech. Spec limit (4) 9'c 'i.20E-01 1.12E-02
7. Percent of Tech. Spec. limit (5) 96 2.12 E+ 00 3.34E-02
8. _ Pereent of Tech. Spec. limit (6) 7c 1.06E+ 00 1.67E-02
11. IODINES
1. Totallodinc 131 Ci 1.08E-02 4.50E-03 16.50E+ 00

'4. Average release rate for period uCi/sec 1.37E-03 5.725-04

3. Percent of Tech. Spec,linit(7) 9o 3.26E-03 1.36E-03

- 4, ' Percent of Tech. Spec. limit (8)  % 2.08E + 00 8.60E-01

5. Percent of Tech. Spec. limit (9)  %  !.04 E + 00 4.30E-01 C. PARTICUlATES
l. Particulates with halflives greater than 8 days Ci 7.40E-06 7.10E-06 2.80E + 01
2. Average release rate for period uCi/sec _ 9.41 E-07 9.03E 07 3.- Percent of Tech. Spec. limit (7) 9'c 2.24E-06 2.14 E-06

'4. Percent of TcI Spec. limit (8)  % 1.71E-03 1.64E-03

5. _Percerit of Tech. Spec. limit (9) 9o" 8.57E-4 8.22E-04 ,
6. - Gross alpha radioactivity Ci 5.77E-03 7.49E-OS 15.36E+ 01 l

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1 Dill.E 1 A REG G1RDlL12_I 2 (Cont.) ,

CALVERT CLilTS NUCLEAR POWElt PLANT {

EFFLUENT ANI) WASTE 1)lSPOSAL SEh11. ANNUAL REPORT 9 F1RST llALF .1992 G ASEOUS EITLUENTS . SUhth1 ATION OF Al.1, RELEASES ,

IST 2ND EST. TOTAL D. TRITIUh1 UNITS QUARTER QUARTER ERROR, %

1. Total Release Ci 1.31 E + 00 1.59E + 00 11.32E+ 01
2. Average release rate for period uCi/sec 1.67E 01 2.02E.01 NOTES TO TAllLE I A (1) Percent of 1.A.1 whole body dose rate limit (300 mrem / year)

(2) Percent of I.A.1 skin dose rate limit (3(XX) mrem / year)

_(3) Percent of I.A.3 gamma quarterly dose limit (10 mrad)

(4) Percent of I.A.3 gamma yearly dose limit (20 mrad)

(5) - Percent of I.A.3 beta quarterly dose limit (20 mrad)

(6) Percent of I.A.3 beta yearly dose limit (40 mrad)

(7) Percent of 1.D.1 organ dose limit (1500 miem/ycar)

(8) Percent of 1.B.3 quarterly dose limit (15 mrem)

(9) Percent of LB.3 yearly dose limit (30 mrem)

(10) Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.2.1.2, 10

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TAllt.E IC REG GUIDE 1.21 CALVEltT Cl.IITS NUCLEAR POWER Pl. ANT EITLUENT AND WASTE DISPOSAL SEh11. ANNUAL REPORT FIRST llALF .1992 (ul.SEOUS hFFLUENTS . GROUND LEVI;1, RELEASES CONTINUOUS h10l#E IIATCII h10DE IST 2NI) IST 2h1D

1. FISSION AND ACI'lVATION GASES UNITS QUAllTElt QUARTER QUARTER QUAllTER Argon -41 Ci (2) (2) 8.58E-03 6.89E-03

~

- Kiypton . 85 Ci (2) (2) 3.10E +01 2.18E+ 00 Krypton -85m Ci 4.65 E + 00 (2) 5.22E-03 6.86E-01 Krypton . 87 Ci (2) (2) 1.3SE-05 (2)

Krytni. -88 Ci (2) (2) (2) (2)

Xenon -

131rn Ci 2.02E+ 01 (2) 3.92E +0! 4.11E + 00 Xenon -

133 Ci 1.84 E + 03 ^ 37E+01

.. 3.62E + 03 4.85E + 01 Xenon - 133m Ci 1.66E + 01 (2) 3.41 E+01 1.98E-02 Xenon - 135 Ci 5.13E +01 3.95E+ 00 5.57E +00 1.31 E-02 Xenon - 138 Ci (2) (2) (2) (2)

Total for Period - Ci 1.93E4 03 2.76E + 01 3.73E+ 03 5.55E + 01 _

2. IIALOGENS lodine 131 Ci 1.0SE-02 4.50E-03 (1) 9.99E-07 Iodine 133 Ci 1.23 E-02 3.77E-03 (1) 8.25E-07 Total For Period Ci 2.31;I 02 8.27E.03 (1) 1.82E-06 11 _

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1 TAllLE IC. REG GUIDE 121 (Cont)

CALVERT CLilTS NUCLEAR l'OWER l'IANT EITLUENT AND WASTE DISPOSAL SEh11 ANNUAL REPORT FIRST llALF + 1992 G ASEOUS EFFLUENTS . GitOUND I,EVEL REl.EASILS CONTINUOUS A101)E IIATCil h10DE IST 2ND IST 2ND

3. PAltTICUIATES UNITS QUARTER QUARTER QUARTER QUARTER Manganese 54 Ci (2) (2) (1) (1)

Iron 59 Ci (2) (2) (1) (1)

Cobalt -58 Ci (2) (2) (1) (1)

=

Cobalt 60 Ci (2) (2) (1) (1)

Zine -65 Ci (2) (2) (1) (1)

Strontium -89 Ci (2) (2) (1) - (1)

Strontium 90 Ci 2.45E-07 3.36E-07 7.06E 12 3.09E 08 Molybdenum 99 Ci (2) (2) (1) (1)

Cesium 134 Ci (2) (2) (1) 2.99E-06 Cesium 137 Ci 7.10E-06 (2) (1) 3.66F 06 Cerium 141 Ci (2) (2) (1) (1)

Cerium 144 Ci (2) (2) (1) (1)

Gross Alpha Radioactivity Ci 5.6SE-08 5.95E-08 9.30E-10 1.54E-08 Total For Period Ci 7A0E-06 3.% E-07 9.37E 10 6.70E-06 NOTES TO TAllLE iC (1) ladines and particulates in batch releases are accounted for with the main vent continuous samplers when th: release is made through the plant main vent.

(2) Less than minimum detectable activity which meets the LLD requirements of TechnicelSpecification Surveillance Requirement 4.11,2.1.2.

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MllLI.UA HEG GUIDE 1.21 CAINERT Cl.IITS NUCl. EAR POWER Pl. ANT EITI UENT AND WASTE DISPOSAL, SEMl. ANNUAL, REPORT FIRST llA1.F .1992 LLQUllL1;lilit,UENTS SUMhi& TION OF Al.1,1[1;lEASliS IST 2ND EST. TOTAL A. FISSION AND ACTIVATION PRODUCTS UNITS QUARTER QUARTER ERROR, %

1. Total Release (not including tritium, gases, alpha) Ci 2.24E-01 1.29E-01 13.30E+00
2. Average diluted concentration during period uCi/mi 2.73 E.10 3.93 E.10
3. Percent of Tech. Spee. limit (1) G 2.30E-01 7.25E 01
4. Percent of Tech. Spee. limit (2) G 1.15E 01 3.63 E-01 ,
5. Percent of Tech. Spec. limh(3)  % 2.63E-01 2.16E + 00
6. Percent of Tech. Spec. limit (4)  % 1.32E-01 1.08E + 00
11. THITIUM
1. Total Release Ci 9.84 E + 02 4.85 E + 02 19.80E+ 00
2. Average diluted concentration during period uCi/ml 1.20E-06 1.48E-06
3. Percent of applicabiclimit(5)  % 4.00E 02 4.93 E.02 C. DISSOINED ANI) ENTRAINED GASES -
1. Total Release Ci 5.39E 01 2.71E 02 i4.60E+ 00
2. Average diluted concentration during period uCi/ml 6.56E- 10 8.26E-11 i

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TAlli,E 2A REG GUIDE 1.21 (ConM CALVERT CLilTS NUCLEAR POWER l'LANT EITLUENT AND WASTE DISPOSAL SEh11. ANNUAL REPORT F1RST llALF .1992 LLO.URLEFFLUENTS - SUMMATION OF ALLXELEASES i

IST 2ND EST. TOTAL D. GROSS ALP 11A ItADIOACTIVI'IT UNITS QUARTER QUARTER ERROR, %  ;

1. Total Release Ci (6) (6)

E. VOLUME OF WASTE RELEASES (prior to dilution) liters 2.12E+08 9.55E + 07 1.30E+ 00 F. VOLUME OF DILUTION WATER USED DURING PEltlOd liters 8.21 E + 11 3.28E+ 11 11.64E+01 NOTES TO TAllLE 2A (1) Percent of I.C.3 Quarterly Organ Dose Limit (10 mreru)

(2) Percent ofI.C.3 Yearly Organ Dose Limit (20 mrem)

(3) Percent of 1.C.3 Quarterly whole Body Dose Limit (3 mrem)

(4) Percent of 1.C.3 Yearly Mole Body Dose Limit (6 mrem)

($) Limit used is 3 x 10'3 uCi/ml (6) Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.1.1.1.

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IAllLE 311. REG GUIDji.idi CALVERT CLitTS NUCLEAR POWER PLANT  !

- EITLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT '

FIRST IIALF.1992 LIOUID EFFMIENTS CONTINUOUS h10DE IIATCil MODE '

IST 2ND AST 2ND <

NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Sodium -24 Ci (1) (1) 4.52E-04 (1)

Chrornium 51 Ci (1) (1) (1) 4.05E-03 Manganesc 54 Ci (1) (1) 3.52E-04 4.04 E-04 Cobalt 57 Ci (1) (1) (1) 7.73E-u?

i L Cobalt 58 Ci (1) (1) 2.29E-02 7.58E-02 lion 59 Ci (1) (1) 3.30E-04 (1)

Cobalt -60 Ci (1) (1) 5.62E 03 4.19E-03 Zine -65 Ci (1) (1) (1) (1)

Strontium -89 Ci (1) (1) 5.80E.04 5.70E-04 Strontium 90 Ci (1) (1) 7.82E-05 6.12E-05 Strontium 92 Ci (1) (1) 1.02E-04 1.15E-04 Niobium 95 Ci (1) (1) (1) 2.26E-03 i

Niobium 97 Ci (1) (1) 3.39E-03 . 4.26E-04 Zirconium 95 Ci- (1) (1) 3.44E-04 (1) l Molybdenum - 99 Ci (1) (1) 8.22E-05 (1) l Technetium 99m Ci (1) (1) 7.72E-04 (1) l L Ruthenium -103 Ci (1) (1) (1) 3.41 E-04 1'

. Ruthenium 106 Ci (1) (1) (1) (1)

- Silver -110m Ci (1) (1) 5.20E-04 7.96E4)4 Tin 113 Ci (1) (1) (1) 4.13 E-04 Antimony 122 Ci (1) (1) 4.50E-04 2.88E4M Antimony 124 Ci (1) (1) 6.67E-05 5.29E-04 15

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TAlli.E 311 - REG Gull).K1,21 (Cont,)

CALVERT CLilTS NUCLEAR l'OWER PLANT

, EFI'LUENT AND WAST : DISPOSAL SEMI ANNUAL REPOltT FIRSTIIALF 1992 1.10U11) EFFLUENTS .

CONTINUOUS MODE IIATCil MODE IST 2ND IST 2Nis NUCLIDES RELEASED UNITS QUA!!TElt QUAltTEll QUAP.TER QUAltTER Antimony 125 Ci (1) (1) (1) 7.32E4M Tellurium 129 Ci (1) (1) (1) 8.40E-03 Tellurium 132 Ci (1) (1) 1.77E-05 (1) lodine - 131 Ci (1) (1) 5.16E4)6 5.16E-03 lodine' 132 Ci (1) (1) 1.08E 04 (1) lodine 133 Ci (1) (1) 2.8?E-02 4.10E4)4 lodine 135 Ci (1) (1) 1.05 E-03 (1)

Cesium 134 Ci (1) (1) 6.24 E-02 8.48E-03 Cesium 136 Ci (1) (1) 1.06E-03 3.04E-06 Cesium -137 Ci (1) (1) 9.41 E-02 1.47E-02 Barium 140 Ci (1) (1) (1) 4.44E-05 Lanthanum -140 Ci (1) (1) 9.86E-05 1.10E-05 Cerium -141 Ci (1) (1) (1) 2.23E-04 Cerium 144 Ci (1) (1) L74E-04 1.21E-03 Tungsten 187 Ci (1) (1) 7.40E-04 (1)

Total For Period Ci (1) (1) 2.24 E-01 1.29E-01 1

I l

Krypton -85m Ci _1)

( (1) (1) 5.58E-07 l Krypton 85 Ci (1) (1) 6.54E-02 4.53L-04 Xenon. -131m Ci (1) (1) 3.13E-03 3.20E-04 Xenon -133 Ci (1) (1) 4.46E-01 2.59E-02 -1 l

l Xenon -133m Ci '1) (1) 2.33E-03 (1) 16

TA111,I.1211 - REG Gull)l;: 1.21 (Cont.)

CALVER r CLIFFS NUCLEAR POWER l'IANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT SECOND llALF.1991 LIOUID EFFLUENTS CONTINUOUS MODE IIATCil MODE IST 2ND IST 2ND NUCLIDES ItELEASED UNITS QUAltTER QUARTER QUARTER QUARTER Xenon -135 Ci (1) (1) 4.17E-03 4.37E-04 Xenon 135m Ci (1) (1) 1.43E414 (1)

Total For Period Ci (1) (1) 5.39E 01 2.71 E-02 NOTES TO TAllLE 211 (1) Less than minimum detectable acthity which meets the LLD requirements of Technical Specification Surveillt.nce Requirement 4.11.1.1.1.

l i

17 4

-,,,,s-, -w-- -

.w, - ,- ,,,,,eens,, , , ,,e v w- ,

n_-.=,,ew-_----,m-,---+m---* wn----+ww-seN-~, -----=~--w~= =-,~N'-~*'

__ _ _ _ _ . _ _ _ _ _ . _ _ . _ _ ~. _ . _ _ _ . . _ _ . _ . _ _ _

. . i TAlli.E 3A CALVERT CLe /S NUCLEAR POWER PLANT i L'.FFLUENT AND WASTE DISPOSAL SEMI ANNUAL. REPORT F1RST !!ALF .1992 >

SOI,lD WASTE AND litRADIATED FUEL,SillPMENTS A. SOLID WASTE SillPPED OFFSITE FOlulVRIAl,OR DISPOSAL,(NOT IRitADIATED FUEL) 6 MONTil EST. TOTAL

1. Type of Waste UNITS PEltlOD EltROR %
a. Dewatered spent resin m3 7.32E+ 01 Ci 1.67E+ 02 12.00E+01
b. Dry Compressible Waste (Shipped) m3 6.06E + 02 Contaminated Equipment, etc. Ci 4.69E.01 15.00E-t 01
c. Irradiated Components, m3 Control Rods, etc. Ci . .
d. 3 Other (CVCS Filters) rn -

Ci - -

2. Estimate of Major Nuclides (Hy Type of Waste - Only nuclides > l % are reported)
a. Cs-134 1.35E+017e Cs 137 2.74E+01%

11 3 3.97E +01%

Co 58 4.34E + 00%

Fe-55 4.35E+00%

Ni 63 5.48E +00Fo 1131 1.37E+007c Co-60 2.30E+00%

b. Cr 51 9.70E +00%

Fe-55 3.63E+01%

Co-58 1.56E+ 00%

Ni-63 1.34E+01%

Sb-125 4.87E + 00%

. Cs 134 2.7E.E +00%

Cs 137 1.10E+0lro A,t110m - 1.50E+00rc C-14 2.10E+00?c Co-.60 1.04E, a1fc Nb-95 1.05E+00re Ru 106 2.59E+ 00% .

Cc-144 2.0SE + 00%

18

,_.~-- . _ _ ._ . _ . . _ _ _ _ - . , . _ . _ _ , . . _ _ _ _ . _ _ . . , _.._. . _ _ _ . _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ .

TAfil,E 3A CAINERT CLitTS NUC1. EAR l'DWER l'lANT E!TLUENT AN1) W'.STE DISPOSAL SEh11 ANNUAL REPORT F1RST llALF.1992 FOI.iD WAnfE AND IRR41)]ATI:D FUEL SillPhtENT8 (Cont.)

6. SOLID. WASTE bulPPED OFFSITE FOR llURL4),OR DISPOSAL (NOT IRRADIATED FUEL)
3. Solid Wuste Disposition

?! umber of SkhuEe_0h Linde of Transocytitlen Destination 13 hiotor Surface Transit Scientific Ecology Group Oak Ridge, TN 4 hiotor Surface Transit Scientific Ecology Group Oak Ridge, TN f

L I

l

!9

. - ,..;. a... , .- . .... .. . - . . - . . - . - . . , . . - . - - . - - . - - . . . . . - . . . _ . - . - . , - - . . . . - . . ..- . . - . . .

  • s Al'PENDIX A SOLID RADWASTE SillPh1ENT DATA FOlt SEMI ANNUAL EFFLUENTltELEASEItEPollTING FillST IIALF.1992
  • lTPM WASTE: DAW 10 CFit 61 WASTE CLASS: A SOUllCE OF WASTE: Radiologically Controlled Arcas SillPPING CONTAINEll: 40' Scaland Containers TOTAL CUltlE QUAN'ITlY: L$33 Ci llOW Dl?!ERMINEI): Dose to ct.ric content, converrion by volume based on generic distribution and scaling factors TOTAL IlUI',"'n WASTE VOLUME: 21410 ft 3 l

IlOW DirrEltMINED: Container volutne and number of containers shipped SOLIDIFICATION AGENT Olt AllSOllllENT: None

'lYPE WASTE: Dewatered Resin 10 CFR 61 WASTE CL\SS: C SOURCE OF WASTE: Miscellaneous Liquid Radwaste Processing /CVCS Processing SillPPING CONTAINEI': - liigh Integrity L-8-120 liner (120.3 ft3 )

TOTAL CURIE QUANTrlT: 106 Ci llOW DETEllMINED: Gamma scan using sample of resin TOTAL WASTE VOLUME: 1203 ft3buried

-IlOW D1?fEld!INED: Weighed liner and calcuated volt.:x of resin SOLIDIFICATION AGENTOlt AllSOltilENT: None i

1.

A-1 L _ _ _ __ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ . .. . _ . _ . . .

c ,

APPENDIX A SOLID RADWASTE SillPA1ENT DATA FOR r SEh11 ANNUAL EFFLUENT RELEASE REPORTING FIRSTllALP 1992

'lYPE W.tSTE: Dewatered Resin 10 CFR 61 WASTE CLASS: B SOURCE OF WASTE: Miscellaneous Liquid Radwaste Processing /CVCS Processing hillPPING CONTAINER: liigh Integrity L-8120 liner (120.3 ft3 )

TOTAL CURIE QUANT 11Y: 6LO Ci IlOW D1?rERh11NED; Gamma scan using sampl<: from resin TOTAL WASTE v0LUh1E: 360.3 ft3 buried l IlOW DlilERhlINED: Weighed liner and calculated volume of resin SOLIDIFICATION AGENT OR AllSORilENT: None

' i c i WASTE: Dewatered Resin 4 .'FR 61 WASTE CIASS: A dOUllCE OF WASTIL Condensate Demineralizer Resin SillPPING CONTAINER: CPC B-25 Box TOTAL CURIE QUANT!1Y: 5.11E 02 Ci ilOW DETERh!!NED: Gamma scan using sample of resin -

TOTAL WASTF YOLUh1E: 3A5E+03 ft3shipped llOW DETERh11NED: Weighed liner and calculeted volume of resir.

! SOLIDIFICATION AGENTOR AllSORilANT: None A.2

. . . - . - . - - . , . ~ - . - . - - . - - - . - - . - -

9 APPENDIX 11

SUMMARY

OF CIIANGES TO TIIE CCNPP ODCM FIRST IIALF 1992 CllANGES TO Tile CCNPP ODCM IN FilGT llALF 1992

SUMMARY

AND llASIS The Calvert Cliffs Offsite Dose Calculation Manual (ODCM) is contained in the Chemistry I Procedure CP 607. Changes to this document are controlled through the ncrmal procedure change review and approval process. This pro ess meets the requirements of CCNPP Technical Specification 6.17. ,

1

- One change was made to the ODCM during the first 1.alf of the year 1992. The change was tes icwed by the Plant Operations and Safety Review Committee (POSitC) and approved by the Plant General Manager, Calvert Cliffs Nuclear Power Plant, prior to implementation. Change bars are provided in the right margin of the ODCM text to identify the changes made.

l The change was approved on April 10,1992, and designated as change 92-027. The change revised l the values for t'ic Unit 1 and Unit 2 main vent stack flow r ates. 'Ihc revised values of main vent stack flow rates are based on ar*nal measurernents obtahed during a 2. year period. 'Ihe measurements I

were made using approvec Engineering and Test Procedures. I l

I I

(

{-

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lJ D-1

)

o A'ITACllMENT (1)

OI)CM (CP 607) TEXT WITil CilANGES

>=si i

i-k 4

CP-607 Page 13 of 27 3.2.5 All iodines and particulate gamma emitters discharged from the plant shall be accounted for with the continuous main vent header samples since all gaseous effluents are discharged via this path.

3.2.6 A gaseous waste discharge permit shall be prepared for bath releases to document release conditions and approvals, sample analysis results and compliance with Technical Specifications.

3.2.7 Credit shall be taken for main vent dilution from the reactor -

unit through which a release is conducted.

3 Unit 1 - Main Vent Flow - 59.4 m /sec- lPCR 3

Unit _.2 - Main Vent Flow - 47.1 m /sec-l92-l027 3.3 Gaseous Effluent Dose Rate 3.3,1: Site Boundary Dose Rate (Total Body, Skin)

Technical Specification 3.11.2.la limits the dose rate at the '

site boundary due to noble gas releases to s 500 mrem /yr, total body s 3000 mrem /yr, skin. If any of these are exceeded, lPMF review 40CFR302 to determine if a Reportable Quantity limit l90-102 has been exceeded. (3758) Radiation monitor alarm setpoints l

~

are established to assure that these release limits are not l exceeded. In the event any gaseous releases from the station results in the alarm setpoints being exceeded, an evaluation of the unrestricted area dose rate resulting from the release may be performed using the following equations:

btb - X/Q x (I X$xQ) $

bs - X/Q x (I L$ + 1.1 M 4) x Q$

Where:

btb _= total body dose rate--(mrem /yr)

X/Q=atmosphericdigpersiontotheSEsiteboundary PMF PCR 2.2E-06 (sec/m ) 90 102 211 Rev. 1 l

- . . . . .

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