ML20059D251

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Semi-Annual Effluent Release Rept for Calvert Cliffs Nuclear Power Plant First Half 1990
ML20059D251
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 06/30/1990
From: Creel G
BALTIMORE GAS & ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9009060185
Download: ML20059D251 (21)
v • d • e


Text

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e, BALTIMORE GAS AND ELECTRI CHARLES CENTER.P.O. BOX 1476 BALTIMORE MARYLAND 21203 Gromot C. CRttL vice Passiocu, Nucat ah [htmov Doo ** o a a ** August 28, 1990 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50 317 & 50 318 Semi Annual Effluent Release Revort

,. Gentlemen:

Enclosed please find the Semi Annual Effluent Reicase Report in compliance with paragraph 6.9.1.8 of the Unit 1 and Jnit 2 Technical Specifications.

This report does not include the analytical results for strontium for the second quarter. These values vill be provided in an updated report as soon as they are available. As required, the meteorological data is bcIng kept in our files on site and vill be available to you if requested.

Very truly yours,

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4 GCC/PTC/jmh Enclosure cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. C. Mcdonald, Jr., NRC T. T. Martin: NRC Resident inspector (s), NRC R, 1. McLean, DNR

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6 bcc: J. A. Tiernan/C. J. Franklin, Jr.

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C. H. Cruse /P. E. Katz l

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R. 1. Nelbel/T. N. Pritchett  ;

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J. E. Baum i C. L. Bell

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J. J. Connolly R. E. Denton l G. L..Detter. t C. J. Fallbato t L. D. Graber:  ;

L. S.; Larragoite

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, . SEMI-ANNUAL EFFLUENT RELEASE REPORT  ;

CALVERT CLIFFS NUCLEAR POWER PLANT '

FIRST HALF - 1990 TABLE OF CONTENTS  !

I. REGULATORY LIMIT 1....................................................... 1 A. Fission and Activation Gases.........................................!  ;

B. Iodines and Particulates with Half Lives Greater than Eight Days....1  ;

C. L i q u i d E f fl u e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 [

II. MAXIMUM PERMISSIBLE CONCENTRATIONS...................................... 2 ;

A. Fission and Activation Gases........................................ 2 B. Iodines and Particulates with Half Lives Greater than Eight Days.... 3 C. L i qu i d E f f l u e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 III. TECHNICAL SPECIFICATION REQUIREMENTS.................................... 3 IV. AVERAGE ENERGY.......................................................... 4 V. MEASUREMENTS AND APPR0XIMATIONS OF TOTAL RADI0 ACTIVITY. . . . . . . . . . . . . . . . . . 4 A. Fission and Activation Gases........................................ 4

1. B a t c h Rel e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
2. Co n t i n uou s Rel e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 B. l od i ne and Part i cul a t e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
1. B a t c h Rel e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
2. Co n t i n u o u s Rel e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 C. L i qu i d E f fl u e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
1. B a t c h Re l e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
2. Continuous Releases............................................. 5 D. Estimati on o f Tot al Error. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
1. Liqu1d.......................................................... 6
2. Gas 0s .......................................................... 6 VI. BATCH RELEASES.......................................................... 7 A. L1guid..............................................................7 B. Gaseous............................................................. 7 VII. ABNORMAL RELEASES....................................................... 8 A. Liquid..............................................................8

! B. Gaseous............................................................. 8 TABLES 1 A - Gaseous Effluents - Sunnation of Releases. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 '

1C - Gaseous Ef fluents - Ground Level Rel eases. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 2A - Liquid Effluents - Summation of All Releases. . . . . . . . . . . . . . . . . . . . . . . . . . 13 2 B - L i q u i d E f fl u e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 3A - Solid Waste and Irradi ated fuel Shipment s. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 APPENDIXA.................................................................A-1

1 4 1 CALVERT CLIFFS NUCLEAR POWER PLANT +

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SUPPLEMENTAL INFORMATION Facility - Calvert Cliffs Nuclear Power Plant ,

Licensee - Baltimore Gas & Electric Company l

1. REG'JLATORY LIMIT 1 A. Fission and Activation Gases
1. The instantaneous release rate of noble gases in gaseous effluents l shall not result in a site boundary dose rate greater than 500 mre# year to the whole body or greater than 3000 mrem / year to the j skin (Technical Specification 3/4.11.2.1). i
2. Gaseous Radwaste Treatment System and the Ventilation Exhaust {

Treatment System shall be used to reduce gaseous emissions when the calculated gamma dose due to gaseous effluents exceeds 1.20 -

mrad or the calculated beta dose due to gaseous effluents exceeds.

2.40 mrad at the site boundary in a 92 day period (Technical

, Specification 3/4.11.2.4).

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 mrad / year, gamma air 40 mrad / year, beta air .

l 4. All of the above parameters are calculated according to the methodology specified in the Offsite Dose Calculation Manual (0DCM).

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B. Iodines and Particulates with Half lives Greater than Eiaht Days

1. The instantaneous release rate of iodines and particulates in gaseous effluents shall not result in a site boundary dose in L excess of 1500 mrem / year to any organ (Technical Specification 3/4.11.2.1).
2. The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materit.ls 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).

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

from iodine-131 and particulates with half lives greater than  !

eight days in gaseous effluents shall not exceed (Technical Specification 3/4.11.2.3):

15 mrern/qtr, any orgu 30 mrem / year, 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 ODCM.  :

C. Liouid Effluents

1. The concentrations of radionuclides in liquid effluents from the l plant shall not exceed the values specified in 10 CFR Part 20, [

Appendix B, for unrestricted areas (Technical Specification 3/4.11.1.1).

l 2. The liquid radwaste treatment system shall be used to reduce the t I concentration of radionuclides in liquid effluents from the plant 1 when the calculated doses to unrestricted areas exceed 0.36 mrem to the whole body, or 1.20 mrem to any organ in a 92 day period (Technical Specification 3/4.11.1.3).

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

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

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

II. MAXIMUM PERMISSIBLE CONCENTRATIONS A. Fission and Ac+ivation Gases Prior to the batch release of gaseous effluents, a sample of the source is collected and 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 Specification 3/4.11.2.1 are not exceeded.

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B. Iodines and Particulates with Half Lives Greater than Eioht Day 1 ,

a 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 charcoal samples are analyzed by gamma spectroscopy for quantification of any release of radioiodines. The particulate samples are analyzed by gamma spectroscopy for quantification of particulate radioactive material. Based on guidance provided in the ODCM, compliance with dose rate limits for the radioiodines and particulates may be based on a comparison of the actual measured release quantity over a sample period with a pre-established upper bound.

C. Liouid Effluents ,

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 more restrictive (lower) MPC found for each radionuclide is used regardless of solubility.

III. TECHNICAL SPECIFICATION REPORTING REQUIREMENTS (Section 6.9.1.8)

A. Previous Calendar Year (QQ9LQose Assessment Summary During 1989 liquid releases from Calvert Cliffs resulted in a calculated maximum organ dose of 5.38E-01 mrem and a maximum whole  :

body dose of 4.74E-02 mrem. These doses are less than 3% of the Technical Specification yearly organ dose limit and less than 1% of the Technical Specification year' y dose limit for the whole body.

These doses were calculated using ODCM methodology. The controlling pathway was the fish and shellfish pathway with adult as the controlling age group, and the Gastro-Intestinal Tract representing the organ with the highest calculated dose.

Gaseous releases of noble gases resulted in a maximum air dose of l.19E-01 mrad, gamma and 2.63E-01 mrad, beta. Iodine and particulate releases from Calvert Cliffs resulted in a maximum organ dose of 8.78E-01 mrem for the year via the milk-infant-thyroid pathway. These doses were calculated using ODCM methodology. For 1989, calculated offsite doses via the gaseous release pathways were below 3% of their allowable Technical Specification limits.

-B. 40 CFR 190 Total Dose Como11ance Based upon all releases for 1989 and the ODCM calculations, the maximum exposed individual would receive less than 3% of the allowable dose. During 1989, there were no on site sources of direct radiation that would have contributed to a significant or measurable offsite dose. The direct radiation contribution is measured by both on-site j and off-site thermoluminescent dosimeters (TLD). The results of these measurements did not indicate any statistical increase in off-site radiation doses attributable to on-site sources. Therefore, no increase in the off site calculated doses is attributable to the 3

direct exposure from on-site sources. A more detailed evaluation will be reported in the Annual Radiological Environmental Monitoring Report.

C. Eglid Waste Report Reouirements During the first half of 1990, the type of radioactive solid waste shipped from Calvert Cliffs was dry compressible waste, which was shipped as LSA waste in strong, tight containers. Table 3A summarizes the waste shipment data. Also, Appendix A provides a detailed breakdown of the waste shipments for 1990 per the categories as specified in Technical Specification 6.9.1.8.

D. ODCM and PCP Chances No changes were made in the PCP in the first half of 1990.

IV. AVERAGE ENERGY Not Applicable V. MEASUREINTS AND APPR0XIMATIONS AND TOTAL RADI0 ACTIVITY A. Fi Lion 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 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 each containment purge, a gas sample is collected and enalyzed 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.

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B. lodine and Particulates

1. Batch Releases The total activities of radioiodines 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.

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

filter, respectively. The 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 .i 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. 1hese weekly particulate filters are then composited to form monthly and quarterly composites for the gross alpha and strontium 89 and 90 analyses.

e t C. Liouid Effluents

1. Batch Releases Prior to the rele' *e of liquid from a waste tank, a sample is collected and an 'ed by gamma spectroscopy for the principal ,

gamma emitting r: *nuclides. To demonstrate compliance with the requirements 1 -sed in Section I.C.1 above, the measured radionuclide c, . rations ara comparu with the allowable MPCs; '

dilution in the . , charge conduit is considered, and an allowable release rate is verified. l 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 the gross alpha, strontium 89 and 90, and tritium analyses.

2. Continuous Releases 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 L blowdown. The weekly compcsite 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 l

prepare monthly and quarterly composites for tritium, gross alpha, and strontium 89 and 90 analyses, l

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4 D. Estimation of Total Error Total error on all releases was estimated using as a minimum the random counting error associated with typical . releases. In addition c to this random error the following systematic errors were also l examined:

l. Liquid a) Error in volume of liquid released prior to dilution during batch releases. ,

b) Error in volume of liquid released via steam gelierator ,

blowdown. >

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

2. Gases a) Error in main vent release flow.

Error in sample flow rate.

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c) Error in containment purge release flow, i d) Error in gas decay tank pressure.

Where errors could be estimated they are usually' considered additive, r

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O f VI. BATCH RELEASES HiQ IST 2ND OVARTER 00ARTER A. Liouid E 1. Number of batch releases 8.30E+01 3.30E+01

_ 2. Total time period for batch releases (min) 2.49E+04 6.25E+03 3 Maximum time period for a batch release (min) 5.19E+03 6.40E+02

4. Average time p9riod for batch releases (min) 2.99E+02 1.89E+02 y 5. Minimum time period for a batch release (min) 2.00E+00 3.00E+00

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r 6. Average stream flow during periods of effluent into a flowing stream (liters / min of dilution water) 3.22E+06 3.29E+06 i B. Gaseous

1. Number of batch releases 2.90E+01 3.80E+01
2. Total time period for batch releases (min) 6.93E+04 2.09E+05

__ 3. Maximum time period for a batch release (min) 1.06E+04 1.06E+04

4. - Average time period for batch release (min) 2.39E+03 5.49E+03
5. Minimum time period for a batch release (min) 3.00E+01 7.00E+01 1

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.VII.ABN0RMAL RELEASES 19E IST 2ND OVARTER OVARTER A. Liouid

1. Number of releases 2. Total activity released (Curies) B. Gaseous
1. Number of releases 1.00E+00
2. Total activity releases (Curies) 5.58E-01 NOTE LER 90-16 Waste Gas Decay Tank mistakenly discharged without prior sample.  ;

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i o . , TABLE 1A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT '

EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT FIRST HALF - 1990 i

GASE0US EFFLUENTS - SUMMATION OF ALL RELEASES IST 2ND EST. TOTAL A. FIS$10N AND ACTIVATION GASES UNITS OUARTER QUARTER ERROR.%

1. Total Release Ci 2.34E+00 2.93E401 6.20E+00
2. Averaae release rate for oeriod uti/sec 2.98E-01 3.73E+00
3. Percent of tech.soec. limit (1)  % 3.06E-05 7.27E-04
4. Percent of tech.soce. limit (2)  % 2.96E-05 2.80E-04
5. Percent of tech.soec. limit (3)  % 4.97E-04 1.04E-02 i
6. Percent of tech.soec. limit (4)  % 2.48E-04 5.20E-03
7. Percent of tech.soec. limit (5)  % 1.24E-03 1.22E-02
8. Percent of tech.soec. limit (6)  % 6.18E-04 6.10E-03 B. 10 DINES
1. Total Iodine - 131 Ci (2) 3.27E-04 6.50E+00 -
2. Averaae release rate for period uCi/sec -

4.16E-05

! 3. Percent of tech.soec. lim 4 t(7)  % - 9.88E-05

4. Percent of tech.soec. limit (8)  % -

7.57E-02

5. Percent of tech.soec. limit (9)  % -

3.79E-02

  • C. PARTICULATES
1. Particulates with half lives areater than 8 days Ci 4.68E-05 7.71E-05 2.80E+01 L '2. Averaae release rate for period uCi/sec 5.95E-06 9.81E-06 l 3. Percent of tech.soec. limit (7)  % 1.41E-05 2.33E-05
4. Percent of tech.soec. limit (8)  % 1.08E-02 1.79E-02
5. Percent of tech.soec limit (9)  % 5.40E-03 8.93E-03
6. Gross aloha radioactivity Ci (2) 4.43E-07 6.54E+01 l

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TABLE 1A - REG GUIDE 1.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PLANT I EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT FIRST HALF - 1990  !

GASE0US EFFLUENTS - SUNNATION OF ALL RELEASES IST 2ND EST. TOTAL ,

D. TRITIUN UNITS OUARTER QUARTER ERROR.%

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1. Total Release Ci 1.05E-01 2.50E-01 +1.32E+01 i
2. Averaae release rate for period uCi/sec 1.34E-02 3.18E-02 4

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NOTES TO TABLE 1A i (1) Percent of I.A.1 whole body dose rate limit (500 mrem / year)

(2) Percent of I.A.1 skin dose rate limit (3000 mrem / year)

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

i (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) l (7) Percent of 1.B.1 organ dose limit (1500 mrem / year)

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

(9) Percent of I.B.3 yearly dose limit (30 mrem) 10

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,9 , TABLE IC - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WA5TE DISPOSAL SENI-ANNUAL REPORT  :

FIRST HALF - 1990 l GASEOU$ EFFLUENTS - GROUND LEVEL RELEASE 1 CONTINUOU$ NODE BATCH N0DE IST 2ND 15T 2ND

1. FISSION AND ACTIVATION GASES UNITS OUARTER 00ARTER QUARTER 00ARTF1_

Krvoton -85 Ci (2) (2) 1.71E-01 1.16E-01 i Krvoton -85m Ci (2) (2) 9.15E-05 (2)

. Krvoton -87 .Ci (2) (2) (2). (2)

Krvton -88 C1 (2) (2) (2) (2)

Xenon -133 C1 (2) 1.25E+01 (2) 1.37E+01 Xenon -133m C1 (2) (2) 2.17E+00 8.54E 02

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Xenon -135 Ci (2) 2.90E+00 (2) 1.87E 02 Xenon -138 Ci (2) (2) (2) (2)

Total for Period Ci (2) 1.54E+01 2.34E+00 1.39E+01 I

2. HALOGENS Iodine -131 Ci (2) 3.27E-04 (1) (1)

Iodine -133 Ci (2) 5.64E-04 (1) , (1)  !

Total For Period Ci (2) 8.91E-04 (1) (1) i i

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, :a TABLE IC .RES GUIDE 1.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT FIRST HALF - 1990 GA$E00$ EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS N0DE BATCH N0DE IST 2ND IST 2ND

3. PARTICULATES UNITS QUARTER 00ARTER QUARTER 00ARTER

' Chromium -51 C1 (2) 2.67E-05 (1) (1)

L Manannese -54 Ci (2) (2) (1) (1)

I fron -59 C1 (2) (2) (1) (1) e Cobalt 58 C1 (2) (2) (1) (1)

Cobalt -60 Ci (2) (2) (1) (1) I i

Zine -65 Ci (2) (2) (1) (1)  !

Strontium -89 C1 (2) (3) (1) (1)  !

l Strontium -90 C1 (2) (3) (1) (1)

Molybdenum -99 Ci (2) (2) (1) (1)

Cesium -134 Ci (2) (2) (1) (1)

(. Cesium -137 Ci 4.68E-05 5.04E-05 (1) (1) l Cerium -141 Ci (2) (2) (1) (1)

Cerium -144 Ci (2) (2) (1) (1) l Total for Period Ci 4.68E-05 7.71E-05 (1) (1) 1 1

(1)_ Iodines and particulates in batch releases are accounted for with the main vent continuous samplers when the release is made through the plant main vent.

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

l. (3) Analysis not completed for 2nd Quarter.

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TABLE 2A - REs GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT I FIRST HALF - 1990 j 1

LICUID EFFLUENTS - $UMMATION 0F ALL RELEASES  !

IST 2ND EST.T0TAL  ;

A. FISSION AND ACTIVATION PRODUCTS UNITS OUARTER OUARTER ERR 0d.% j 10 Total Release (not including tritium.aases.alcha) C1 1.30E-01 1.05E-01 fl . 03 E+01

2. Average diluted concentration  !

durina period uCi/ml 3.08E-10 2.44E-10

3. Percent of tech.soec. limit (1)  % 6.70E-02 3.50E 02  ;
4. Percent of tech.soce. limit (2)  % 3.35E-02 1.75E-02 '
5. Percent of tech.soec.limitf3)  % 4.69E-01 8.45F 01
6. Percent of tech.soec. limit (4)  % 2.34E-01 4.22E 01 f B. TRITION
1. Total Release C1 1.15E401 4.15E+00 1.04E+01
2. Average diluted concentration

-durina ceriod uti/ml 2.73E-08 9.63E-09

3. Percent of aoolicab'le limitf5)  % 9.10E-04 3.21E-04 C. DISSOLVED AND ENTRAINED GASES i l 1. ' Total Release Ci (2) 1.50E-02 4.80E400 1
2. Average diluted concentration durina ceriod uti/ml - 3.48E-11 13

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TABLE 1A - REG GUIDE I.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WA$TE DISPOSAL $EN!-AMUAL REPORT FIR $T HALF - 1990 (19Q10 EFFLUENTS - $UMATION OF ALL RELEASE 1 1$T 2ND EST.T0TAL D. SRoss ALPHA RAD 10 ACTIVITY UNITS QUARTER QUARTER ERROR.%

1. Total Release Ci 1.48E-04 1.30E-05 +3.34E+01 E. VOLUME CF WA$TE RELEASES (nrior to. dilution) liters 5.60E+06 2.40E+06 +1.30E+00 Fi VOLUME OF DILUTION WATER USED .

DURING PERIOD liters 4.22E+11 4.31E+11 fl.64E401 NOTES TO TABLE 2A (1) Percent of I.C.3 Quarterly Organ Dose Limit (10 mrem)

(2) Percent of 1.C.3 Yearly Organ Dose limit (20 mrem)

(3) Percent of I.C.3 Quarterly Wholo Body Dose Limit (3 mrem)

(4) Percent of I.C.3 Yearly Whole Body Dose Limit (6 mrem)

(5) Limit used is 3 x 10-3 uti/mi 14

A i

, e ,

TABLE 2B RES SUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT FIRST HALF - 1990 LIQUID EFFLUENTS CONTINUOUS N0DE BATCH N0DE IST 2ND 1ST 2ND NUCLIDES RELEASED UNITS OUARTER 00ARTER 00ARTER QUARTER Chromium -51 Ci (1) (1) 2.16E-05 3 36E-04 Nanaanese -54 Ci (1) (1) 2.27E-03 2.68E-03 Cobalt -57 C1 (1) (1) 2.37E-05 1.07E-06 Cobalt -58 Ci (1) (1) 5.49E-03 3.08E-03 fron -59 Ci (1) (1) (2) (2)

Cobalt -60 Ci (1) (1) 1.63E-02 3.54E-02 Zinc -65 C1 (1) (1) (2) (2) ,

Strontium -89 Ci- (1) (1) (2) (3) j Strontium -90 Ci (1) (1) 4.44E-04 (3)

Niobium -95 Ci (1) (1) 4.41E-03 5.80E-04 Zirconium -95 Ci (1) (1) 9.13E-04 (2) __ l Technetium -99m Ci (1) (1) (2) 3.11E-05 i Ruthenium -106 Ci (1) (1) 2.48E-03 2.80E-03 Silver -110m Ci (1) (1) 7.63E-03 3.43E-02 Tin -113 Ci (1) (1) 4.07E-04 8.70E-05 l

Antimony -125 C1 (1) (1) 3.39E-02 8.73E-03 Iodine -131 Ci (1) (1) -

6.96E-04 t

Iodine -133 Ci (1) (1) - 1.75E-04  ;

Cesium -134 Ci (1) (1) 1.19E-02 2.40E-03 I Cesium -137 Ci (1) (1) 3.61E-02 9.92E-03 Cerium -139 Ci (1) (1) 1.05E-06 (2) i i 15

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,.q TABLE 28 - REG SulDE 1.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WA$TE DISPOSAL SEN!-ANNUAL REPORT FIRST HALF - 1990 LIQUID EFFLUENTS CONTINUOUS NODE BATCH N0DE IST 2ND IST 2HU NUCL1 DES RELEASED UNITS DUARTER 00ARTER QUARTER QUARTER Cerium -141 C1 (1) (1) 4.12E-06 (2)

Cerium -144 Ci (1) (1) 0 06E-03 3.59E-03 Total For Period Ci (1) (1) 1.30E 01 1.05E-01 Xenon -133 C1 (1) (1) - 1.48E-02 Xenon -135 Ci (1) (1) -

1.59E-04 Total For Period Ci (1) (1) - 1.50E-02 ,

(1) There were no continuous liquid releases during the 1st and 2nd quarters.

(2) Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.1.1.1.

(3) Analysis not completed for. 2nd Quarter.

16

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.;g .. . TABLE 3A CALVERT CLIFFS NUCLEAR POWER PLANT EFFL9ENT AND WASTE DISPOSAL SENI-ANNUAL REPORT FIRST HALF - 1990 SOLID WASTE AE IRRADIATED FUEL $HIPNENTS A. SOLID WASTE SHIPPED OFF5ITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-NONTH EST.T0TAL

1. Yvoe of Waste UNITS PERIOD ERRORE
a. . Dewatered spent resin m3 ....

Ci ----

2.00E+01

b. Dry Compressible Waste, m3 2.04E+01 Contaminated Equipment, etc. Ci 4.57E+00 5.00E+01

.c. Irradiated Components, m3 ....

Control Rods, etc. Ci ----

5.00E+01

d. Other (CVCS Filters) m3 ----

Ci ----

2.00E+01 2.- Estimate of Major Nuclides (By Type of Waste)*

b. Tritium -3 3.14E+00 %

. Carbon -14 1.10E+00 %

fron -55 4.47E+01 %

Cobalt -58 1.44E400 %

Cobalt -60 1.41E+01 %

Nickel -63 1.73E+01 %

Cesium -13a 3.03E+00 %

Cesium -137 1.10E+01 %

Antimony -125 1.42E+00 %

  • Only nuclides greater than 1% are reported
3. Solid Waste Disposition Number of Shioments Mode of Transportation - Destination 8 Motor St rface Transit Scientific Ecology Group Oak Ridge, TN 17

q

., [; APPENDIX A l

. . = . '

1 4

, SOLIO RADWASTE $NIPMENT DATA l ti FOR j V , SEN!-ANNUAL EFFLUENT RELEASE REPORTING f FIRST HALF - 1990 TYPE WASTE: DAW 1

10 CFR 61 WA$TE CLASS: A j SOURCE OF WASTE: Radiologically Controlled Areas  !

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$ NIPPING CONTAINER: CPC B-25 Box TOTAL CURIE QUANTITY: 4.57 Ci l NOW DETERNINED: Dose to curie content conversion by volume based on generic i distribution and scaling factors.  !

TOTAL WA5TE VOLUNE: 7200 ft3 l 1

HOW DETERNINED: Container volume and number of containers snipped  !

l SOLIDIFICATION AGENT OR ABSORBENT: None j i

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l= A-1

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