ML20246K583

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Semiannual Effluent Release Rept for Calvert Cliffs Nuclear Power Plant First Half 1989
ML20246K583
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 06/30/1989
From: Creel G
BALTIMORE GAS & ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8909060009
Download: ML20246K583 (20)
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BALTIMORE , '

GAS?AND'  !

ELECTRIC -!

CHARLES CENTER. P. O. BOX 1475 BALTIMORE, MARYLAND 21203  ;

I GEORGE C. CREEL Vict PassiotNT ,,

Nu:: Lean Ewenov 1 (301)#60 4466 l August 28, 1989

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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 Report (l

' Gentlemen:

1 Enclosed please find the Semi-Annual Effluent Release Report in compliance -)

with paragraph - 6.9.1.8 of the Unit 1 and Unit 2 Technical Specifications.

This report contains the strontium results for the first and second quarters.  :) "

As required, the meteorological data is being kept in our files on site and will be available to you if requested.

Very truly yours, l

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' GCC/PTC/jmh Enclosure cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC S. A. McNeil, NRC W. T. Russell, NRC V. L. Pritchett, NRC LT. Magette, DNR ]

8909060009 890630 >

PDR ADOCK 05000317 $

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[- o Document Control Desk August 28, 1989 Page 2 1

bec: C. H. Cruse /A. R. Thornton R. E Denton/J. T. Carroll P. E. Katz/R. C. L. Olson C. C. Lawrence, III/M. J. Miernicki J. R._ Lemons /R. F. Ash W. J. Lippold/B. S. Montgomery F. J. Munno/M. Gavrilas R. B. Pond,Jr./S. R. Buxbaum T. N. Pritchett/E. I. Bauereis L. B. Russell /R. P. Heibel M. E. Bowman R. M. Douglass l- J . M . Kupko , J r .

R. C. DeYoung R. E. Lapp C. M. Rice R. G. Staker J. J, Connolly G. J . Falibota D. L. Shaw, Jr.

M. L. Stone 1

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t SEMI-ANNUAL EFFLUEh; RELEASE REPORT CALVERT CLIFFS NUCLEAR POWER PLANT i

FIRST HALF - 1989 TABLE OF CONTENTS I. REGULATORY LIMITS....................................................... 1 A. . Fission and Activation Gases........................................ 1 B. lodines and Particulate 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 PERMISSABLE CONCENTRATIONS...................................... 2 A. Fission and Activation Gases........................................ 2 B. Iodines and Particulate with Half Lives Greater than Eight Days.... 3 C. L i q u i d E f fl 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. Ba t c h Rel e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
2. Co nti n uou s Rel e a se s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 B. Iod i ne and Pa rti cul at es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
1. Batch Releases.................................................. 5
2. Co nt i n u ou s Rel e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 C. L i q u i d E f fl u e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
1. B a t c h Rel e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
2. Co n t i nuou s Rel e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 D. Es t i mat i on o f Tot al Error. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
1. Liquid.......................................................... 6
2. Gases........................................................... 6 VI. B ATC H R E L EAS ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 A. Liquid.............................................................. 7 B. Gaseous............................................................. 7 VII. ABNORMAL RELEASES....................................................... 8 A. Liquid.............................................................. 8 B. Gaseous............................................................. 8 TABLES 1 A - Gaseous Effl uents - Summation of Rel eases. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 1C - Gaseous Effluents - Ground Level Rel eases. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 2A - Liquid Effl uents - Summation of All Rel eases. . . . . . . . . . . . . . . . . . . . . . . . . . 13 2 8 - L i qu i d E f fl u e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 3 A - Solid Waste and Irradi ated Fuel Shipments. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17

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 I. REGULATORY E IiLIS A. Fission and Activation Gases

1. The instantaneous release rate of noble gases in gaseous effluents 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.
2. Gaseous Radwaste Treatment System and the Ventilation Ex-haust Treatment System shall be used to reduce gaseous emis-sions 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.
3. The air dose at the site boundary due to noble gases re-leased in gaseous effluents shall not exceed:

10 mrad gamma radiation / quarter 20 mrad beta radiation / quarter 20 mrad gamma radiation / year 40 mrad beta radiation / year

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

B. Iodines and Particulate with Half Lives Greater than Eiaht Days

1. The instantaneous release rate of Iodines and particulate in gaseous effluents shall not result in a site boundary dose in excess of 1500 mrem / year to any organ.
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 the site bounda-ry.

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3. The dose to a member of the public at the site boundary from Iodine 131 and particulate with half lives greater than L '

eight days in gaseous effluents shall not Exceed:

15 mrem to any organ per quarter 30 mrem to any organ per year less than .1% of the above limits as a result of burning contaminated oil 1

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

C. Liouid Effluents-

1. The concentrations of radioactive isotopes in liquid effluents from the plant' shall not exceed the values speci-fied in 10 CFR, Part 20, Appendix B, for unrestricted areas.
2. lhe liquid radwaste treatment system shall be used to reduce the radioactive isotopes in liquid effluents from the plant 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.
3. The dose to a member of the public in unrestricted areas shall not exceed:

3 mrem whole body dose per quarter 10 mrem dose to any organ per quarter 6 mrem whole body dose per year 20 mrem dose to any organ per year

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

II. MAXIMUM PERMISSABLE CONCENTRATIONS A. Fission and Activation Gases Prior to the batch release of gaseous effluents, the gas gamma activities are summed. If the total does not exceed the dose rate limitations for the most limiting isotope, then the batch is released. If the most lin.iting isotope criteria is not met, then a detailed dose rate calculation is performed as described in the ODCM.

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eg.1 B .- Iodines and Particulate with Half Lives Greater than Eicht Days Compliance to the dose rate limitations from Iodines and particu-lates is demonstrated by calculating the maximum quantity that could be seen on a weekly sample. This is reduced by a factor of 0.5 for conservatism. As long 'as the I-131 (most limiting iso-tope) releases in a seven. day period do not exceed 12.5 Ci, then no further analyses are needed to verify compliance without ex-ceeding the limits of 1.B.3.

C. Liouid Effluents The .MPCs used for radioactive materials released in liquid effluents are in accordance with Technical Specifications and/or are derived from the use.of notes to Appendix B, 10 CFR, Part 20.

In all cases, the most restrictive (lowest) MPC found for each isotope is used regardless of solubility.

III. TECHNICAL SPECIFICATION REPORTING REQUIREMENTS (Section 6.9.1.8)

A. Previous Calendar Year (1988) Dose Assessment Summary During.1988 liquid releases from Calvert Cliffs resulted in a maximum organ dose of 3.67E-01 mrem and a maximum whole body dose of 5.36E-02 mrem. This was less than 2% of the allowable yearly Technical Specification organ dose limit and less than 1% of.the allowable yearly Technical Specification whole body dose limit.

This dose was calculated using ODCM methodology (Adult Fish and Shellfish Pathways). The Gastro-Intestinal Tract was the maximum organ dose pathway.

Gaseous Noble Gas Releases resulted in a maximum of 1.84E-01 mrad gamma and 4.84E-01 mrad beta exposure. Iodine and particulate releases from Calvert Cliffs resulted in a maximum organ exposure of 5.37E-01 via the Thyroid Pathway. These doses were calculated using ODCM methodology. All gaseous release pathways were below 2% of their allowable Technical Specification limits for 1988.

B. 40 CFR 190 Total Dose Comoliance Based upon the releases for the first half of 1989 and the ODCM calculations, the maximum exposed individual would receive less than 2% of the allowable dose. This does not include the direct radiation contribution which did not show a statistical difference greater than the normal background. A more detailed evaluation will be reported in the Annual Radiological

! Environmental Monitoring Report.

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O C. Solid Waste Report Requirements During the first half of 1989, the types of radioactive solid waste shipped from Calvert Cliffs were radioactive resin, which was dewatered and shipped in high integrity containers, dry compressible waste, which was shipped in Type H containers, and CYCS filter waste, which was shipped in a steel liner stablilized with concrete.

D. DDCM and PCP Chances No changes were made in the first half of 1989.

E. Radioactive Gaseous Effluent Monitorina Instrumentatiorl The Unit 2 Main Vent Gaseous Effluent Monitor (2-RI-5415) was out of service for greater than thirty days. This notification is required by Technical Specification 3.3.3.9. The monitor was declared out of service on March 26, 1989, due to the pump tripping on high flow. Due the inability to obtain spare parts, the monitor remained out of service until May 5, 1989.

IV. AVERAGE ENERGY Not Applicable V. MEASUREMENTS AND APPROX 1MATIONS AND TOTAL RADI0 ACTIVITY A. Fission and Activation Gases

1. Batch Releases Prior to each batch release of gas from a priasurized gas decay tank, a sample is collected and analyzed for each sig-nificant gaseous isotope using a Ge detector. The total ac-tivity released is based on the pressure / volume relationship (gas laws) of the tank.

Prior to and after the release of gas as a result of purging containment, samples are collected and analyzed for each significant gaseous isotope using a Ge detector. The total activity released is based on containment volume and purge rate. Activity buildup while purging is also considered.

l 2. Continuous Releases l

During the release of gas from the main vents, samples are l

collected and analyzed at least weekly for each significant gaseous isotope using a Ge detector. The total activity re-leased ^ the week is based on the total sample activity decay sorrected to the midpoint of the sample period and multiplied by the main vent flow for the week.

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1 B. Iodine and Particulate

l. Batch Releases The total activity released- from a pressurized gas decay tank, containment purges and containment vents as Iodines and particulate is accounted for by- the main vent Iodine and particulate continuous samples.
2. ' Continuous Releases During the release of gas from the main vents, samples of Iodines and particulate are collected using a charcoal and particulate filter, respectively. The filters are removed weekly and are analyzed for each significant gamma isotope using a Ge detector. The total activity _ released for the week is based on the total sample activity found on the fil-ters decay corrected to the midpoint of the sample period and multiplied by the main vent flow for the week. These weekly particulate filters are then composited to form monthly and quarterly composites at which time gross alpha and strontium 89 and 90 are analyzed.

C. Liouid Effluents r 1. Batch Re'ieases Prior to the reletse of liquid from a waste tank, a sample is collected. and analyzed for the concentration of each sig-nificant ga:mra energy radionuclides to demonstrate compliance with Section I.C.1 above using the water flow rate in each discharge conduit into which the effluent is discharged at the time of discharge. The total activity released in each batch is determined by multiplying the volume released times the concentration of each isotope. The actual volume re-leased 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 use in analyses of gross alpha, strontium 89 and 90, and tritium.

When steam generator blowdown is discharged to the circulat-ing 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 ana-lyzed for each significant isotope using a Ge detector and 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 quar-terly composites for use in analyses of tritium, gross alpha, and strontium 89 and 90.

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L 2.- Continuous Releases l None F D .- Estimation of Total Error Total error on all releases was estimated using as a minimum the j

-random counting error associated with typical releases. . In addi- i tion to the random error, the detector to sample geometry system- '

atic error during gamma counting was determined. This included an estimate of sample volume error.and sample pipetting error.

More'specifically the following other systematic errors were also examined: .

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

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

c) Error in amount of dilution water used during the re-porting period.

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

c) Error in containment purge release flow.

d) Error in gas decay tank pressure.

Where errors could be estimated they are usually considered

, additive.

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b VI. BATCH RELEASES 12.62 IST 2ND OUARTER 00ARTER Liouid A.

1. Number of batch releases 6.90E+01 1.90E+01
2. Totti time period for batch  !

releases (min) 1.59E+04 8.55E+03

3. Maximum time period for a batch release (min) 6.28E+02 6.46E+02
4. Average time period for batch release.s (min) 2.31E+02 4.50E+02
5. Minimum time period for a  !

batch release (min) 2.00E+00 3.00E+01

6. Average stream flow during periods of effluent into a flowing stream (liters / min of dilution water) 4.44E+06 4.29E+06
8. Gaseous
1. Number of batch releases 1.40E+01 3.30E+01 j
2. Total time period for batch  !

releases (min) 2.09E+04 1.23E+05 l

3. Maximum time period for a batch release (min) 9.84E+03 1.04E+04
4. Average time period for batch release (min) 1.49E+03 3.74E403
5. Minimum time period for a batch release (min) 1.20E+02 8.00E+00 l

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- VI.I. ABNORMAL RELEASES 1101 IST .2ND OUARTER OUARTER

.i A .' Liouid.

1. . Number of releases - 2. . Total activity released (Curies). * ' B. Gaseous
1. Number of releases' .  ?. Total activity releases (Curies). ,

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  • TABLE 1A - REG GUIDE 1.21 l ,

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-AN'10AL REPORT ~

FIRST HALF - 1989

, GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES.

IST 2ND EST. TOTAL A. FISSION AND ACTIVATION GASES UNITS OUARTER OUARTER ERROR.%

1. Total Release Ci 2.78E+03 5.03E+02 2.15E+01
2. Averaae release rate for oeriod uti/sec 3.54E+02 6.40E+01
3. Percent of tech.soec. limit (1)  % 7.56E-02 8.12E-03
4. Percent of tech. spec. limit (2)  % 2.67E-02 3.55E-03
5. Percent of tech.soec.limitf3)  % 1.07E+00 1.22E-01
6. Percent of tech.soec. limit (4)  % 5.35E-01 6.10E-02
7. Percent of tech.soec. limit (5)  % 1.12E+00 1.94E-01
8. Percent of tech.soec. limit (6)  % 5.60E-01 9.70E-02 B. 10 DINES
1. Total Iodine - 131 Ci 4.20E-02 3.28E-03 1.84E+01
2. Averaae release rate for period uCi/sec 5.34E-03 4.17E-04
3. Percent of tech.soec. limit (7)  % 5.77E-04 4.50E-05 4 Percent of tech. spec. limit (8)  % 4.22E-01 3.30E-02
5. Percent of tech. spec. limit (9)  % 2.11E-01 1.65E-02 C. PARTICULATE
1. Particulate with half lives areater than 8 days Ci 5.95E-06 1.94E-05 1.84E+01
2. Averaae release rate for period uCi/sec 7.57E-07 2.47E-06
3. Percent of tech.soec.limitf 7)  % 8.18E-08 2.67E-07 4 Percent of tech. spec. limit (8)  % 5.99E-05 1.95E-04 5 Percent of tech.soec. limit (9)  % 2.99E-05 9.75E-05
6. Gross alpha radioactivity Ci <1.25E-06 <1.72E-05 9

Tf.BLE 1A - REG GUIDE 1.21 (Cont.1

~.' .

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT FIRST HALF - 1989

$8 SEQ 9S EFFLUENTS - SUPMATION OF ALL RELEASES IST 2ND EST. TOTAL D. TRITIUN UNITS 00ARTER 00ARTER ERROR,%

1. Total Release Ci 3.56E+00 1.44E+01 2.18E+01,
2. Averaae release rate for period uti/sec 4.53E-01 1.83E+00 NOTES TO TABLE 1A (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)

(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 I.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

i TABLE IC-- REG GUIDE 1.21 '

CALVERT CLIFFS NUCLEAR POWER PLANT l

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1989 i

GASEOUS EFFLUENTS - GROUND LEVEL REl. EASES CONTINUOUS MODE BATCH MODE IST 2ND IST 2ND

'1. FISSION AND ACTIVATION GASES UNITS 00ARTER 00ARTER OUARTER DUARTER-Arcon -41 Ci 6.76E-01 (2) 1.53E-02 (2)

Krvoton -85 Ci (2) (2) 2.11E+01 1.71E401 Krvoton -85m Ci 2.08E+01 (2) 9.19E+00 6.64E-04 Krvoton -87 Ci 8.26E+00 (2) (2) (2)

Krvton_ C1 2.34E+01 (2) 7.83E-03 (2)

Xenon -131m Ci (2) (2) 8.01E+00 9.90E+00 l

Xenon -133 Ci 1.80E+03 4.25E+01 7.80E+02 4.15E402 Xenon -133m Ci 2.20E+01 (2) 1.75E+00 1.62E401 Xenon -135 Ci 8.26E+01 2.87E+00 7.90E-01 7.38E'-03 Xenon -138 Ci (2) (2) (2) (2)

Total for Period Ci 1.96E+03 4.54E+01 8.21E+02 4.58E+02

2. HALOGENS lodine -131 Ci 4.20E-02 3.28E-03 (1) (1)

Iodine -133 Ci 4.67E-02 3.31E-03 (1) (1)

Total For Period Ci 8.87E-E2 6.59E-03 (1) (1) 11

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  • TABLE IC -REG GUIDE 1.21 (Cont.)

, -CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL' REPORT

p FIRST HALF - 1989 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE IST 2ND IST 2ND
3. PARTICULATE UNITS DUARTER DUARTER QUARTER OUARTER Mancanese -54 Ci (2) (2) (1) (1)

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

Iron -59 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) (2) (1) (1)

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

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

Cesium -137 . Ci 2.73E-06 1.94E-05 (1) (1)

Cerium -141 Ci (2) (2) (1) (1)

Cerium -144 Ci 3.*i? E-06 (2) (1) (1)

Total For Period Ci 5.95E-06 1.94E-05 (1) (1)

(1) Iodines and particulate 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.

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? TABLE 2A - REG GUIDE l-21.

CALVERT Cl.IFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT FIRST HALF. - 1989 LIOUID EFFLUENTS'- SUMATION OF ALL RELEASES IST -2ND EST. TOTAL A. FISSION AND ACTIVATION PRODUCTS UNITS 00ARTER QUARTER ERROR.%

11 . Total Release (not-including '

' tritium.aases. alpha) Ci 7.62E-01 3.37E-01 2.16E+01

2. Average' diluted concentration durino period uCi/ml 1.31E-09 6.00E-10
3. Percent of tech.soec.limitfl)  % 1.05E+00 7.21E-01
4. Percent of tech.soec. limit (2)  % 5.25E-01 3.61E-01
5. Percent of tech. spec. limit (3)  %- 5.64E-01 2.90E-01
6. Percent of tech. spec.limitf 4)  % 2.82E-01 1.45E-01 B.'TRITIUN
1. Total Release Ci 1.97E+02 2.40E+01 1.81E+01 2 .- Average diluted concentration durina period UCi/ml 3.39E-07 4.27E-08
3. Percent of applicable limit (5)  % 1.13E-02 1.42E-03 C. DISSOLVED AND EKTRAINED GASES
1. Total Release Ci 2.87E-01 7.38E-03 2.00E+01
2. Average diluted concentration durina ceriod uti/ml 4.94E-10 1.31E-11 13
  • TABLE 2A - REG GUIDE 1.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT FIRST HALF - 1989 LIQUID EFFLUENTS - SUPMATION OF ALL RELEASES IST 2ND EST. TOTAL D. GROSS ALPHA RADI0 ACTIVITY UNITS 00ARTER OUARTER ERROR.%

1. Total Release Ci <1.94E-04 <2.97E-04 3.00E+00 E. VOLUNE OF WASTE RELEASES forior to dilution) liters 6.44E+06 3.31E+06 3.00E+00 l F. VOLUNE OF DILUTION WATER USED DURING PERIOD liters 5.81E+11 5.62E+11 1.40E+01 NOTES TO TABLE 2A (1) Percent of I.C.3 Quarterly Organ Dose Limit (10 mrem)

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

(3) Percent of I.C.3 Quarterly Whole 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 uC1/ml 14

  • TABLE 2B - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1989

~LIOUID EFFLUENTS CONTINUCMS MODE BATCH MODE IST 2ND IST 2ND-NUCLIDES RELEASED UNITS DUARTER DUARTER OUARTER OUARTER Sodium -24 Ci (1) (1) (2) 7.12E-05 Chromium -51 (i (1) (1) 2.03E-02 8.73E-03 Manaanese -54 Ci (1) (1) 5.29E-03 3.30E-03 Cobalt -57 C1 (1) (1) 7.98E-05 (2)

Cobalt -58 Ci (1) (1) 8.20E-02 2.22E-02 fron -59 Ci (1) (1) (2) (2)

Cobalt -60 Ci (1) (1) 1.80E-02 6.29E-03 Zine -65 Ci (1) (1) 1.88E-04 (2)

Strontium -89 Ci (1) (1) 3.45E-02 <7.94E-05 31rontium -90 Ci (1) (1) 3.20E-03 3.97E-04 Zirconium -95 Ci (1) (1) 1.65E-02 4.04E-03 Niobium -95 Ci (1) (1) 2.87E-03 8.85E-03' Technicium -99m Ci (1) (1) 1.94E-04 (2)

Ruthenium -103 C1 (1) (1) 4.05E-03 1.54E-04 Silver -110m Ci (1) (1) 3.32E-02 9.10E-03 Tin -113 Ci (1) (1) 6.43E-03 (2)

Antimony -124 Ci (1) (1) (2) 5.58E-04 Antimony -125 C1 (1) (1) 4.31E-02 1.85E-02 Iodine -131 Ci (1) (1) 2.77E-02 1.46E-03 Iodine -133 Ci (1) (1) 1.96E-03 4.55E-05 Cesium -134 Ci (1) (1) 1.07E-01 5.76E-02 Cesium' -136 Ci (1) (1) 7.92E-05 (2) 15 c___--_.____

p,, ,.*' TABLE 2B - REG GUIDE 1.21 (Cont.1 ,

i e

CALVERT CLIFFS NU W J.4 POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1989 LIOUID EFFLUENTS CONTINUOUS MODE BATCH MODE IST 2ND IST 2ND NUCLIDES RELEASED UNITS OUARTER DUARTFR OUARTER OUARTER Cesium -137 Ci (1) (1) 3.40E-01 1.93E-01 Cerium -139 C1 (1) (1) 2.64E-06 (2)

Cerium -141 Ci (1) (1) 6.34E-04 (2)

Cerium -144 Ci (1) (1) 1.39E-02 2.23E-03 Lanthanum -140 Ci (1) (1) 1.18E-03 (2)

Total For Period ,

Ci (1) (1) 7.62E-01 3.37E-01

'Krvoton -85m Ci (1) (1) 1.76E-05 (2)

Krvoton -88 Ci (1) (1) 8.40E-06 (2)

Xenon -131m Ci (1) (1) 9.92E-05 (2)

Xenon -133 Ci (1) (1) 2.86E-01 7.38E-03 Xenon -133m Ci (1) (1) 2.00E-04 (2)

Xenon -135 C1 (1) (1) 6.24E-04 (2)

Total For Feriod C1 (1) (1) 2.87E-01 7.38E-03 _

(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.

16

l ,

2,: F 3. ; TABLE 3A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1989 L SOLID WASTE AND IRRADIATED FUEL SHIPMit!JJ 1'

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL fMOTE IRRADIATED FUEL) l 6-MONTH EST. TOTAL

1. Tvoe of Waste UNITS PERIOD ERRORE j

.a. Dewatered spent resin m3 6.50E+00 C1 1.19E+01 2.00E+01

b. Dry Compressible Waste, m3 8.41E+01 Contaminated Equipment,,etc. Ci 2.60E+00 5.00E+01 3
c. Irradiated Components, m ,,,,,

Control Rods, etc. C1 -----

5.00E+01

d. Other (CVCS Filters) m3 3.60E+00 C1 3.69E+02 2.00E+01

^

2. Estimate of Major Nuclides (By Type of Waste)* ,
a. Manganese -54 1.50E+00 %

Iron -55 2.60E+00 %

Cobalt -58 9.90E+00 % -i Cobalt -60 2.70E+00 %

Nickel -63 3.50E+00 % <

Cesium -134 1.86E+01 %

Cesium -137 5.90E+01 %  !

b. Iron -55 4.10E+01 % i Cobalt -58 3.20E+00 %

Cobalt -60 1.40E+01 % i Nickel -63 8.90E+00 % l Cesium -134 8.30E+00 %

Cesium -137 2.10E+01 %

  • Only nuclides greater than 1% are reported i l
3. Solid Waste Disposition Number of Shioments Mode of Transportation Destination 3 Motor Surface Transit Barnwell, S.C. I 3 Motor Surface Transit Scientific Ecology Group i Oakridge, TN 17 1

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