ML20214T856

Semiannual Effluent Release Rept,Second Half 1985

ML20214T856
Person / Time
Site:	Calvert Cliffs
Issue date:	12/31/1985
From:	Tiernan J BALTIMORE GAS & ELECTRIC CO.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8612090035
Download: ML20214T856 (20)

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SEMI ANNUAL EFFLUENT RELEASE REPORT FOR CALVERT CLIFFS NUCLEAR POWER PLANT SECOND HALF - 1985 LIST OF ENCLOSURES I

TITLE PAGE Regulatory Limits 1 Maximum Permissible Concentrations 2 Offsite Dose Calculation Manual Reporting Requirements 3 Measurements and Approximations of Total Radioactivity 4 Batch Releases 7 Abnormal Releases 7 Gaseous Effluents -Summation of Releases 8 Gaseous Effluents - Ground Level Releases 10 Liquid Effluents - Summation of All Releases 12 Liquid Effluents 13 Solid Waste and Irradiated Fuel Shipments 16 g - )lT ggn5 0612090035 051231 PDR ADOCK 05000317 l R PDR 1

.o CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT i

SUPPLEMENTAL INFORMATION Fac!11ty - Calvert Cliffs Nuclear Power Plant Licensee - Baltimore Gas & Electric Company I. REGULATORY LIMITS l

l A. Fission and Activation Gases:

l l 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. The Gaseous Ra6 waste Treatment System and the Ventillation Exhaust Treatment System shall be used to reduce gaseous emmissions 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 released 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 (ODCM).

D. .lodines and Particulates with half lives greater than eight days:

1. The instantaneous release rate of lodines and Particulates in gaseous offluents shall not result in a site boundary dose in excess of 1500 mrem / year to any organ.

2. The Gascous lirid-Waste Treatment System and the Ventillation 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 boundary.

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. 3. The dose to a member of the public at the site boimdary from Iodine 131 and i Particulates with half lives is greater than eight days in gaseous effluents shall not exceed:

j 15 mrem to any organ per quarter I

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

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

-) C. Liquid Effluents:

j 1. The concentrations of radioactive isotopes in liquid effluents from the plant j shall not exceed the values specified in 10 CFR, Part 20, Appendix B, for

unrestricted areas. ,

2. The liquid radweste treatment system shall be used to reduce the i{ radioactive isotopes in liquid effluents from the plant when the calculated

! doses to unrestricted areas exceeds .36 mrem to the whole body, or 1.20

! mrem to any organ in a 92 day period. 1 4

3. The dose to a member of the public in unrestricted areas shall not exceed:

l 3 mrem whole body dose per quarter i 10 mrem dose to any organ per quarter 6 mrem whole body dose per year 4

20 mrem dose to any organ per year a

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

) B. MAXIMUM PERMWABLE CONCENTRATIONS  :

A. Plssion and Activation Gases:

. Prior to the batch release of gaseous effluents, the gas activities are summed. if  !

the total does not exceed the dose rate limitations for the most limiting isotopes,  ;

then the batch is released. If the most limiting isotope criteria is not met, then i tne detailed dose rate calculation is performed as described in the ODCM. l c

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B. Iodines and Particulates with half lives greater than eight days:

Compliance to the dose rate limitations from lodines and Particulates is demonstrated by calculating the maximum quantity that could be seen on a weekly sample. This is reduced by factor of 0.5 for conservatism. As long as the I-131 (most limiting isotope) releases in a seven day period do not exceed 12.5 Cl, then no further analysis are needed to verify compliance without exceeding the limits of 1.B.3.

C. Liquid 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.

The following limits were used to calculate the percent of applicable limit in Table 2 A A. Fission and Activation Products - Limit used 1. x 10-7 uCl/ml. This limit was used as given in the notes to Appendix B, Table II, Column 2 of 10 CPR 20.

B. Tritium - Limit used 3 x 10-3 uCl/ml.

III. ODCM Reporting Requirements in accordance with the requirements of the ODCM, one change was made during the second half of 1985. In order to ensure that the steam generator blowdown is continuously monitored, the monitor used was changed from RE 4095 to RE 4014. This change was made because RE 4095 can be bypassed under some conditions. Enclosed is a drawing showing the revised ODCM page.

IV. AVERAGE ENERGY - not applicable V. MEASUREMENTS AND APPROXIMATIONS AND TOTAL RADIOACTIVITl A. Fission and Activation Gasos:

1. Batch Releases Prior to each batch release of gas from a pressurized gas decay tank, a sample is collected and analyzed for each significant gaseous isotope using a Ge(LI) detector. The total activity released is based on the pressure / volume relationship (gas laws) of 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(LI) detector. The total activity released is based on containment volume and purge rate with activity buildup while purging is being considered.

2. Continuous releases During the release of gas from the main vents, samples are collected and analyzed at least weekly for each significant gaseous isotope using a Ge(LI) detector. The total activity released for the week is based on the total sample activity decay corrected to the midpoint of the sample period and multiplied by the main vent flow for the week.

D. Iodine and Particulates:

1. Datch releases The total activity released from a pressurized gas decay tank, containment purges and containment vents as lodines and particulates is accounted for by the main vent iodine and particulate continuous samp!crs.

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. The filters are removed weekly eM are analyzed for each  ;

significant isotope using a Ge(It) detector. The total activity released for l

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the week is based on the total sample activity found on the filters decay l corrected to the midpoint of tha sample period and multiplied by the main vent flow for the week. The activity on the filters is corrected for decay and buildup during the sample period. These weekly particulate filters are I then composited to form monthly and quarterly composites at which time E gross alpha and strontium 89 and 90 are analyzed.

C. Liquid Effluents:

1. Datch releases Prior to the release of liquid from a waste tank, a sample is collected and analyzed for the concentration of each significant gamma energy peak 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 released is based on the difference in tank levels prior to and af ter the release. A proportional composite sample is also withdrawn for each week's releases, 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.

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? When steam generator blowdown is discharged to the circulating water i 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 l composite is analyzed for each significant isotope using a Ge(Li) detector l

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 quarterly composites for use in analyses of tritium, gross alpha, and strontium 89 and 90.

2. Continuous releases:

None D. Estimation of Total Error:

Total error on all releases was estimated ustrg as a minimum the random counting urror assoelated with typical releases. In addition to the random error, the detector to sample geometry systematic 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 l a. Error in volume of liquid released prior to dilution during batch l releases.

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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.

t b. Error in sample flow rate.

c. Error in containment purge release flow.

d. Error in gas decay tank pressure.

i Where errors could be estimated they were usually considered additive. l l

VI. BATCH RELEASES 1985 3rd 4th Quarter Quarter A. Liquid:

1. Number of batch releases 4.00 E+01 5.0 GE+01 l

2. Total time period for batch I releases (hours) 3.37 E+02 3.81 E+02 )

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3. Maximum time period for a batch release (min) 8.65 E+02 9.75 E4 02

4. Average time period for batch releases (min) 5.05 E+05 4.57 E+02

5. Minimum time period for a batch release (min) 3.50 E+01 1.70 E+01

6. Average stream flow during periods of effluent into a f.owing stream (liters / min of dilution water) 4.50 E+06 4.54 E+06 B. Gaseous:

1. Number of batch releases 2.90 E+01 3.70 E+01

2. Total time period for batch releases (min) 4.54 E+04 3.92 E+04

3. Maximum time period for a batch release (min) 1.050 E+04 1.14 E+04

4. Average time period for batch release (min 1.57 E+03 1.06 E+03

5. Minimum time period for a batch release (min) 1.50 E&O2 9.00 E+01

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VII. ABNORMAL RELEASES A. Liquid .

1. Number of releases -o. .o.

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2. Total activity released (Curles) ,-0 -

B. Gaseous:

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1. Number of releases 2. Total activity releases (Curles) .

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-8 TABLE l A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1985 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 3rd 4th Est. Total A. Fission and activation gases Units Quarter Quarter Error, %

1. Total Release Cl 7.53E+02 2.09E+03 2.15E+01

2. Average release rate for period uCl/sec 9.57E+01 2.66E+02

3. Percent of tech. spec. limit (1)  % 1.65E-02 3.82E-02

4. Percent of tech. spec. limit (2)  % 6.47E-03 1.51E-02

5. Percent of tech. spec. limit (3)  % 2.36E-01 5.58E-01

6. Percent at tech. spec. limit (4)  % 4.72E-01 1.12E-00

7. Percent of tech. spec. limit (5)  % 3.01E-01 7.95E-01

8. Percent of tech. spec. limit (6)  % 6.01E-01 1.59E+00 B, lodines l

1. Total lodine - 131 C1 4.58E-03 1.4 IE-02 1.84E+01

2. Average release rate for period uCl/sec 5.83E-04 1.79E-03

3. Percent of tech. spec. limit (7)  % 1.42E-03 4.37E-03

4. Percent of tech. spec. limit (8)  % 1.47E-01 4.54E-01

5. Percent of tech. spec. limit (9)  % 7.37E-02 2.27E-01 C. Particulates

1. Particulates with half lives greater than 8 days Cl 8.73E-06 3.34 E-05 1.84 E+01

2. Average release rate for period uCl/sec 1.10E-06 4.20E-06

3. Percent of tech. spec. Ilmit (7)  % 2.71 E-06 1.04E-05

4. Percent of tech. spec. limit (8)  % 2.81E-04 1.08 E-03

5. Percent of tech. spec. limit (9)  % 1.41E-04 5.40E-04

6. Gross alpha radioactivity Cl 6.30E-07 < !.19 E-06

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TABLE l A'- REG GUIDE 1.21 (Cont'd) 7 CALVERT CUFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT

'\ SECOND HALF - 1985 i

c GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES D, Tritium s

1. Total Release Ci 1.38E+00 5.4E-01 2.18E+01 2 ' Avdrage release rate for period uCi/sec 1.8E-01 6.9E-02 NOTES TO TABLE 1 A (1) Percent of I.A.1 whole body limit roo na,/y-('2) Percen't of I.A.1 skin limit so oo -

(3) Percent of I.A.3 gamma quarterly limit /e d (4) Percent ol'-I.A.3 gamma yearly limit 2o (5) Percent of I.A.3 beta quarterly limit ,, .

(6) hercent of 1.A.3 beta yearly limit .

(7) Percent of I.B.1 organ limit /soo ,

f, (8)' Percent of I.B.3 quarterly limit e5 em (9) Percent of I.B.3 yearly limit lo -*'

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TABLF IC REG GUIDE 1.21 CALVERT CUFFS NUCLEAR POWER PLANT FIRST HALF - 1985 G ASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode 3rd 4th 3rd 4th

1. Fission and activation gases Units Quarter Quarter Quarter Quarter argon - 41 Cl 0 0 2.72E-02 3.08E-03 ,

krypton - 85 Cl 0 0 3.18E+00 5.83E+00 krypton - 85m Ci 6.39E-01 0 3.30E-02 5.44E-01 krypton - 87 Cl 0 0 2.llE-03 1.26E-04 krypton - 88 Ci 0 0 1.50E-02 4.08E-03 xenon - 131m Ci 0 0 4.37E+00 6.90E+00 xenon - 133 Ci 4.89E+02 7.35E+02 2.03E+02 1.28E+03 ~

xenon - 133m Ci 3.82E+00 9.54E+00 7.69E+01 1.03E+01 xenon - 135 Ci 4.67E+01 3.57E+01. 5.04E-01 5.96E+00 Total For Period Ci 5.40E+02 7.80E+02 2.12E+02 1.31E+03

2. Halogens bromine - 82 C1 3.76E-06 0 iodine - 131 Ci 4.58E-03 1.41E-02 (1) 4.03E-Il lodine - 132 Ci 0 0 (1) (1) iodine - 133 Cl 6.65E-03 1.60E-02 (1) (1) iodine - 134 Ci 0 0 (1) (1) iodine - 135 C1 2.50E-04 0 (1) (1)

Total For Period Ci 1.148E-02 3.01E-02 3.76E-06 4.03E-11 (1) Iodines in batch releases are accounted for with the continuous main vent samplers when the release is made through the plant main vent.

TABLE IC REG GUIDE 1.21 (CONT'D)

CALVERT CLIFFS NUCLEAR POWER PLANT SECOND HALF - 1985 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode 3rd 4th 3rd 4th 3, Particulates Units Quarter Quarter Quarter Quarter chromium - 51 Ci 0 7.24E-06 cobalt - 58 Ci 4.46E-06 0 (1) 1.37E-12 strontium - 89(2) C1 - -

(1) (1) strontium - 90(2) Ci - -

(1) (1) tin - 113 Ci 0 0 (1) 2.96E-13 cesium - 134 Ci 0 0 (1) 1.11E-12 cesium - 137 Ci 1.71E-06 1.51E-06 (1) (1) lanthium - 140 Cl 0 1.23E-05 (1) (1) barium - 140 Ci 0 1.23E-05 (1) (1) cerium - 144 Ci 2.56E-06 0 (1) (1)

Total For Period Ci 8.73E-06 3.34E-05 2.78E-12

-(1) Particulates in Sa _h releases are accounted for with the main vent continuous particulate samplers when the release is made through the plant main vent.

(2) Does not include strontium values l

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TABLE 2A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1985 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 3rd 4th Est. Total A. Fission and activation products Units Quarter Quarter Error, %

1. Total Release (not including tritium, gases, alpha) Ci 2.03E-01 1.23E+00 2.16E+01

2. Average diluted concentration during period uCi/mi 3.44E-10 2.07E-09

3. Percent of tech. spec. limit (1)  % 3.44E-01 2.07E+00

4. Percent of tech. spec limit (2)  % 7.60E-01 4.60E+00

5. Percent of tech, spec. limit (3)  % 3.80E+01 2.30E+00

6. Percent of tech spec. limit (4)  % 3.30E-01 2.00E+00

7. Percent of tech. spec. limit (5)  % 1.65E-01 1.00E+00 B., Tritium

1. Total Release Ci 9.58E+01 9.12E+01 1.81E+01

2. Average diluted concentration during period uCi/ml 1.62E-07 1.53E-07

3. Percent of applicable limit  % 5.40E-03 5.10E-03 C. Dissolved and entrained gases

1. Total Release Ci 4.41E-02 1.36E-01 2.00E+01

2. Average diluted concentration during period uCi/ml 7.47E-11 2.29E-10

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TABLE 2A - REG GUIDE 1.21 (CONT'D)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1985 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES D. Gross alpha radioactivity

1. Total Release Ci 3.02E-03 8.77E-03 3.00E+00 E. Volume of Waste Releases (prior to dilution) liters 8.26E+06 8.66E+06 3.00E+00 F. Volume of dilution water used during period liters 5.90E+11 5.95E+11 1.40E+01 (1) Percent of C.1 limit /0 c#4 2* AN 8 (2) Percent of C.3 Quarterly organ dose limit /9 *

(3) Percent of C.3 Yearly organ dose limit 28 *

(4) Percent of C.3 Quarterly Whole body dose limit 3 (5) Percent of C.3 Yearly Whole body dose limit /

TABLE 2B REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1985 LIQUID EFFLUENTS Continuous Mode (1) Batch Mode 3rd 4th 3rd 4th Nuclides Released Units Quarter Quarter Quarter Quarter sodium - 24 Ci 0 0 0 1.21E-03 chromium - 51 Ci 0 0 6.47E-03 1.25E-01 manganese - 54 Ci 0 0 5.31E-03 1.29E-02 c:balt - 58 Ci 0 0 4.50E-02 3.30E-01 cobalt - - 60 Ci 0 0 1.87E-02 5.81E-02 strontium - 89(2) Ci 0 0 - -

strontium - 90(2) Ci 0 0 - -

niobium - 95 Ci 0 0 1.42E-02 3.05E-02 zirconium - 95 Cl 0 0 6.45E-03 1.49E-02 ni:blum - 97 Ci 0 0 2.61E-04 2.15E-03 ruthenium - 103 Ci 0 0 0 1.20E-03 silver - Il0m Ci 0 0 2.34E-03 1.46E-01 tin - 113 Ci 0 0 0 2.46E-03 antimony - 122 Ci 0 0 2.08E-04 1.09E-03 antimony - 124 Ci 0 0 0 1.07E-02 antimony - 125 Ci 0 0 1.88E-02 1.06E-01 iodine - 131 Ci 0 0 2.19E-02 9.69E-02 t:llurium - 132 Ci 0 0 0 1.26E-03 iodine - 133 Ci 0 0 5.62E-03 4.84E-02 l

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TABLE 2B REG GUIDE 1.21 (CONT'D)

CALVERT CLIFFS NUCLEAR POtiifER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1985 LIQUID EFFLUENTS Continuous Mode (1) Batch Mode 3rd 4th 3rd 4th  ;

Nuclides Released Units Quarter Quarter Quarter Quarter lodine - 132 Ci 0 0 0 8.25E-04 technicium - 99m Ci 0 0 0 6.87E-04 iodine - 124 Ci 0 0 0 1.31E-03 cesium - 134 Ci 0 0 1.65E-02 7.40E-02 iodine - 135 Ci 0 0 0 3.42E-03 cesium - 136 Ci 0 0 0 9.60E-04 cesium - 137 Ci 0 0 3.20E-02 1.36E-01 barium - 140 Cl 0 0 4.38E-03 0 lanthanum - 140 Ci 0 0 4.43E-03 0 c:rium - 144 Ci 0 0 0 5.00E-04 Total For Period Ci 0 0 2.03E-01 1.23E+00 l

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TABLE 2B REG GUIDE 1.21 (CONT'D)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF- 1985 LIQUID EFFLUENTS Continuous Mode (1) Batch Mode 3rd 4th 3rd 4th Nuclides Released Units Quarter Quarter Quarter Quarter X:non - 133 Ci 0 0 4.28E-02 1.22E-01 Xenon - 135 Ci 0 0 1.29E-03 7.54E-03 X:non - 135m Ci 0 0 0 5.59E-03 Xtnon 133 m Ci 0 0 0 9.19E-04 Tctal For Period Ci 0 0 4.41E-02 1.36E-01 (1) There were no continuous liquid releases during the 3rd and 4th quarters.

(2) Does not include strontium values.

TABLE 3A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1985 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-Month Est. Total

1. Type of Waste Units Period Error %

a. Spent resin, filter sludge m3 1.34E+01 evaporator bottoms, etc. Ci 7.3E+01 2.00E+01

b. Dry compressible waste, 3 m 1.46E+02 contaminated equipment, etc. Ci 3.02E+00 5.00E+01

c. Irradiated components, 3 m 0 control rods, etc. Ci 0 5.00E+01

d. 3 Other (CVCS Filters) m 3.57E+00 Ci 3.15E+01 2.00E+1

2. Estimate of major nuclides (by type of waste)*

a. Nickel - 63 5.3E+01 %

Cobalt - 58 1.0E+01 %

Cesium - 137 1.5E+01 %

Cesium - 134 8E+00 %

Manganese - 54 3E+00 %

Cobalt - 60 9E+00 %

Antimony - 125 IE-01 %

Strontium - 90 IE-01 %

Others 1.8E+00 %

b. Cobalt - 60 2.0E+01 %

Cesium - 137 1.7E+00 %

Cesium - 134 4.4E+01 %

Nickel - 63 1.7E+01 %

Strontium - 90 3E-03 %

Others 2E+00 %

c. Manganese - 54 1.5E+00 %

Cobalt - 60 1.19E+01 %

Nickel - 63 7.15E+01 %

Others 1.5E+01 %

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 9 Motor surface transit Barnwell, S. C.

l 3 Motor surface transit Richland, Wash.

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ATTACllMEN1 d) .

If!P ItADIOACTIVE LIQUID WASTE SYSTEMS CALVEltT Cl.IFFS NUCLEAlt l>OWElt PLANT l

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l l Itcactor Coolant Waste Miscellaneous Waste l .

ju-lCVCS U-2-CVCS U-1 Steam U-2 Steam Aux Building Laundry &

l 1.o t down Letdown Generator Generator Drains (U-l Laboratory i Blowdown lilowdown & U-2) Draina p

if V 11-1 CVCS U-2 CVCS

'Filtura (2) Filters (2) 120 gem 120 gpm Rf .

11 - 1 V y Degastfier 11 & 12 U-2 -

R C Waste 4- Degasifier Hiscellaneous Ion Excliangers Waste Receiver Tank 4,000 gal

' l-RE- 4 014 2-RE-4014 y 11 & 12 R C Waste Miscellaneous ,

Receiver Tanks R- Waste Ion R -

90,000 gal Excliange r g I l i i Evaporators  :

20 gpm Y Automatic' , V i _ _A Isolation A L V

- 4 Valves i1 & 14 R C Waste iI R C Waste f / V lliscellaneous

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Waste los Excleanner Honitor Tank -

Honitor Tank

-._.___ Turlaine Illdg i 2 It C Hani e 8""D y lion i t o s Tank y V Cliesapeake

, , > Circulating Water > Hay

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.' 0-RE-220I Aut.omatIc 1notaLlon

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. BALTIMORE GAS AND ELECTRIC  ;

CHARLES CENTER P.O. BOX 1475 BALTIMORE, MARYLAND 21203 JOSEPH A.TIERN AN VICE PREsioENT NUCLEAR ENEROY February 26,1986 I Dr. Thomas E. Murley Regional Administrator U. S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406

Subject:

Calvert Cliffs Nuclear Power Plant Docket Nos. 50-317 and 50-318 Semi-Annual Effluent Release Report

Dear Dr. Murley:

85 in Enclosed please find the Semi-Annual Effluent Release Report ification. The for the seco compliance with paragraph 6.9.1.8 of the Unit 1 and Unit ill be 2provided in Technical Spec report does not include the analytical results for strontium. These values wThe liqu an updated report as soon as these results are available. Dose Calculation lt obtained using the simplified dose calculation as described The meteorological data required by the semi-annual report is on file.

Very truly yours,

< b h e-t --

J. A. Tiernan Vice President Nuclear Energy Division Attachments cc: Director, Office of Management Information and Program Control 9a e h

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