ML20153D462

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Semiannual Effluent Release Rept,Calvert Cliffs Nuclear Power Plant,First Half 1988
ML20153D462
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 06/30/1988
From: Tiernan J
BALTIMORE GAS & ELECTRIC CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8809020211
Download: ML20153D462 (21)
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Text

  • SEMI-ANNUAL EFFLUENT RELEASE REPORT CALVERT CLIFFS NUCLEAR POWER PIANT FIRST HALF - 1988 TABLE OF CONTENTS I. REGULATORY LIMITS....................................................... 1 A. Fission and Activation Cases........................................ 1 B. Iodines and Particulates with Half Lives Greater than Eight Days.... 1 C. Liquid Effluents,................................................... 2 II. MAXIMUM PERMISSABLE CONCENTRATIONS...................................... 2 A. Fission and Activation Cases........................................ 2 B. Iodines and Particulares with Half Lives Greater than Eight Days.... 3 C. Liquid Effluents.................................................... 3 III. TECHNICAL S PECIFICATION REQUIRFMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 IV. AV ERAC E EN ER GY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 V. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADI0 ACTIVITY . ............. 4 A. Fission and Activation Cases................................ ....... 4
1. Batch Releases.................................................. 4
2. Continuous Releases............................................. 4 B. Iodine and Particulates............................................. 4
1. Batch Releases.................................................. 4
2. Continuous Releases............................................. 5 C. Liquid Effluents.................................................... 5
1. Batch Releases.................................................. 5
2. Continuous Releases............................................. 5 D. Es tima t ion o f To tal Er ro r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
1. Liquid.......................................................... 6
2. Cases........................................................... 6 VI. KATCH RELEASES.................... ..................................... 7 A. Liquid.............................................................. 7 B. Caseous............................................................. 7 VI I . ABNORMAL RELEAS ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........................ 8 A. Liquid............................................................ .8 B. Caseous............................................................. 8 TABLES 1A Caseous Ef fluents Sanaation of Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 1C - Caseous Ef fluents Cr >und Level Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 2A Liquid Ef fluents - Summation of All Releases . . . . . . . . . . . . . . . . . . . . . . . . . . 13 2B . Liquid Effluents...................................................... 15 3A . Solid Waste and Irradiated Fuel Shipments............................. 18 ,

1 8809020211 000630 r PDR ADOCK 05000317 k R pnu

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CALVERT CLIFFS NUCLEAR POWER FIANT EFF111ENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SUPPLEMENTAL INFORMATION Facility - Calvert Cliffs Nuclesr Power Plant Licensee - Baltimore Gas & Electric Company I. REGUIATORY LIMITS A. Fission and Activation Cases

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 arem/ year to the skin.
2. Caseous 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 gamina 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).  !

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

1. The instantaneous release rate of Iodines and particulates in gaseous effluents shall not result in a site boundary j dose in excess of 1500 arem/ year to any organ. L
2. The Caseous 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 arem 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 particulates with half lives greater than eight days in gaseous effluents shall no'; excoed:

15 mrem to any organ per quarter 30 mrem to any organ per year i less than .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 che ODCM.

C. Liould 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. The 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 arem to the whole body, or 1.20 mtem to any organ in a 92 i day period.

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

3 mrem whole body dose por quarter  ;

i 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 paraseters are calculated according -

to the methodology specified in the ODCM.

II. MAXINUN . PERMISSAB12 CONCENTRATIONS A. Fission and Activation Cases Prior to the batch release of gaseous effluents, the gas gamma activities are sumned. If the total does not exceed the dose rate limitations for the most limiting isotope, then the batch is ,

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

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

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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 1-131 (most limiting iso.

tope) reles.ses in a seven day period do not exceed 12.5 Ci, then l

no further analyses are needed to verify compliance without ex-ceeding the limits of 1.B.3.

C. L!auid Effluents The MPCs used for radioactive materials released in liquid effluents are in accordance with Technical Specifications and/or  ;

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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.

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III. TECHNICAL SPECIFICATION REPORTING REQUIREMENTS (Section 6.9.1.8)

A. Previous Calendar Year (1987) Dose Assessment Summarv

! During 1987 liquid releases from Calvert Cliffs resulted in a l l

maximum organ dose of 0.80 mrem and a maximum whole body dose of e 0.085 mrem. This was less than 5% of the allowable yearly Tech- '

nical Specification organ dose limit and less than 2% of the al.

lowable yearly Technical Specification whole body dose limit.

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

Caseous Noble Gas Releases resulted in a maximum of 0.13 mrad I

gamma and 0.35 mrad beta exposure. Particulate releases from Calvert Cliffs resulted in a maximum organ exposure of 0.44 mrem 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 1987.

B. 40 CFR 190 Total Dose Como11aDR1 i l

Based upon the releases for the first half of 1988 and the ODCM calculations, the maximum exposed individual would receive less l 1% of the allowable dose. This does not include the direct radiation contribution which did not show a statistical '

l difference greater than the normal background. A more detailed '

I evaluation will be conducted for the entire year in the next ,

j semi annual report. l i

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C. Solid Vaste Report Reauirements During the first half of 1988, the only type of radioactive solid waste shipped from Calvert Cliffs was radioactive resin, which was dewatered and shipped in high integrity containers.

D. ODCM and PCP Chanzes g

No changes were made in the first half af 1988.

IV. AVERACE ENPRbY Not Applicable V. MEASUREMENTS AND APPROXIMATIONS Alm TOTAL RADI0 ACTIVITY l A. Fission and Activation Cases

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

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

B. Iodine and Particulates

1. Batch Releases The total act.ivity released from a pressurized gas decay tank, containment purges and containment vents as Iodines and particulates is accounted for by the main vent Iodine and particulate continuous samples.

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2. Continuous Releases buring 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 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. Liauld Effluents

1. Batch Releases Prior to the release of liquid from a vaste tank, a sample is collected and analyzed for the concentration of each sig-nificant gamma energy radionuclide 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 qui.,tity 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.

2. Continuous Releases None 5

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 addi-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 samp*e pipetting error.

More specifically the following other systematic errors were also j examined:

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

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

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

l 2. Gases I

a) Error in main vent release flow.

b) Error in sample flow rate.

2 c) Error in containment purge release flow.

l d) Error in gas decay tank pressure.

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Where errors could be estimated they are usually considered additive.

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F VI. BATCH RELEASES 12.0.

IST 2ND OUARTER OUARTER A. Liould

1. Number of batch releases 5.40E+01 4.00E+01
2. Total time period for batch releases (min) 1.40E+04 1.18E+04
3. Maximum time period for a batch release (min) 6.41E+02 6.95E+02 4 Average time period for batch releases (min) 2.59E+02 3.01E+02
5. Minimum time period fot a batch release (min) 5.00E+00 2.00E+00
6. Average stream flow during periods of effluent into a flowing stream (liters / min of dilution water) 4.54E+06 4.54E>06 B. Caseous
1. Number of batch releases 1.40E+01 2.10E+01
2. Total time period for batch releases (min) 3.94E+04 5.68E+04
3. Maximum time period for a batch release (min) 9.61E+03 1.01E+04
4. Average time period for batch release (min) 2 81E+03 2.70E+03
5. Minimum time period for a batch release (min) 1.33E+02 4.50E+01 l

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VII. ABNORMAL PELEASES 12.6.E IST 2ND OUARTER OUARTER A. Liould

1. Number of releases 0-
2. Total activity released (Curics) 0- 0-B. g.gr,ggtg
1. Number of releases 0-
2. Total activity releases (Curies) l 8

TABLE LA - REC CUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1988 GASEOUS EFFIDENTS - SUMMATION OF All RELEASER IST 2ND EST. TOTAL A. FISSION AND ACTIVATION CASES UNITS OUARTER OUARTER ERROR.1

1. Total Release C1 3.60E+03 1.63E+03 2.15E4 01
2. Averare release rate for oeriod uCi/see 4.58E+02 2.07E+02
3. Percent of tech.soes. limit (1)  % 6.34E 02 3.77E 02
4. Percent of tech.soec. limit (2) 1 2.53E-02 1.79E 02
3. Percent of tech.soce.11mit(3)  % 9.40E 01 5.32E 01
6. Percent of tech.soee.11mit(4)  % 4.70E 01 2.66E 01 ___
7. Porcent of tech.soce. limit (5)  % 1.36E+00 7.77E 01 1 _,,Asreent of tech.soce. limit (6)  % 6.80E-01 3.88E 01 B. IODINES
1. Total todine - 131 C1 4.77E 02 5.55E 02 1.84E+01
2. Averace release rate for period uCi/sec 6.07E 03 7.06E 03
3. Percent of tech.soee.11mit(7)  % 1.44E-02 1.58E 02
4. Percent of tech.soce. limit (8)  % 1.54E+00 1.79E+00 i
5. Percent of tech.soce.11mit(9)  % 7.68E-01 8.95E-01 C. PARTICUIATES
1. Particulates with half ILves creater than 8 days Ci 3.63E 05 1.16E 02 1.84E+01
2. Averare release rate for period uCi/see 4.62E 06 1.48E 03
1. Percent of tech.soce.11mit(7)  % 1.10E 05 3.52E 03 _
4. Percent of tech.soee. limit (8) 2 1.17E 03 3.73E 01
5. Percent of tech.soce.11mit(9)  % 5.84E 04 1.86E-01
6. Cross alpha radionetivity Ci <1.15E 05 <3.37E-06 9

TABER LA RRd CUIDE 1.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PIANT EFFIEENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1988 GASEOUS EFF11JENTS - SUMMATION OF ALL RELEASES IST 2ND EST. TOTAL D. 11LITIUM UNITS OUARTER OUARTER ERROR.I

1. Total Release C1 1.89E 01 6.81E 01 2.18E+01
2. Averare release rate for eeriod uCi/see 2.40E 02 8.66E 02 NOTES TO TABLE 1A (1) Percent of I.A.1 whole body dose rate limit (500 arem/ year)

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

(3) Percent of 1.A.3 gamma quarterly dose limit (10 mrad)

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

(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 mrom/ year)

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

(9) Percent of 1.B.3 yearly dose limit (30 mrem) 10

TARIE IC - RfD CUIDE 1.21 CALVERT CLIFFS NUCl2AR POWER PIANT EFFIEENT AND WASTE DISPOSAL SENI ANNUAL REPCRT FIRST HALF - 1988 CASE 00S EFFIDENTS - CROUND 12 VEL RELEASES L

CONTINUOUS MODE BATCH MODE IST 2ND IST 2ND

1. FISSION AND ACTIVATION CASES UNITS OUARTER OUARTER OUARTER OUARTER Argon -41 ri - - 6.02E 03 1.95E 02 ,

Krveton -85 Ci - - 1.92E+01 2.74E+02 Krvoton 85m Ci 3.20E+00 2.09E+01 1.85E 01 2.81E 01 Krvoton -87 Ci - 1.53E+00 1.10E 02 2.92E 03 Krvton -88 Ci - - 2.59E 02 1.33E 01 Xenon 131m C1 - 1.09E+01 1.73E+01 9.98E 01  !

Xenon -133 Ci 5.72E+02 6.76E+02 2.91E+03 4.72E+02 ,

Xenon -133m C1 1.31E+00 1.02E+01 2.35E+01 3.58E+00 Xenon -135 C1 3.50E+01 1.57E+02 1.94E+01 3.84E+00 6

Xenon -135m Ci - - 3.26E 03 -

Total for Period Ci 6.12E+0? 8.77E+02 2.99E+03 7.55E+02 i

2. HALOGENS Iodine -131 Ci 4.77E-02 5.55E-02 (1) (1)

Iodine -133 C1 3.25E-02 3.00E 02 (1) (1)

Total For Period Ci 8.02E 02 8.55E 02 (1) (1)

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

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TAB 12 1C -REC GUIDE 1.21 (Cont. )

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT FIR 3T HALF - 1988 CASEOUS EFFIEENTS - CROUND LEVEL RELEASES CONTINUOUS MODE BATCH NODE IST 2ND IST 2ND

3. PARTICUIATES UNITS OUARTER OUARTER OUARTER OUARTER Berv111um -7 Ci - 5.46E 06 (1) (1)

Cobalt -57 Ci - 4.97E 07 (1) (1)

Cobalt -58 Ci 7.23E 06 _ 1.38E 05 (1) (1)

Strontium -89 Ci (2) (3) (1) (1)

Strontium 90 Ci (2) (3) (1) (1)

Tellurium -132 Ci - 6.82E-07 (1) (1)

Cesium -134 Ci 6.43E 06 1.40E 05 (1) (1)

Cesium 137 Ci 2.26E-05 1.16E 02 (1) (1)

Cerium -144 Ci - 9.86E 06 (1) (1)

Total For Period Ci 3.63E 05 1.16E 02 (1) (1)

(1) Particulates in batch releases are accounted for with the main vent continuous particulate samplers when the release is mads throug,h the plant main vent.

(2) Less than minimum detectable activity which meets the LLD requirements of Technical Specification 3.11.2.1.

(3) Analysis for the 2nd quarter not completed.

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TABLE 2A - REC CUIDE 1.21 CALVERT CLIFFS NUC12AR POWER PIANT EFFIEENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1988 LIOUID EFFIEENTS - SUMMATION OF ALL RELEASES

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IST 2ND EST. TOTAL A. FISSION AND ACTIVATION PRODUCTS UNITS OUARTER OUARTER ERROR.!

1. Total Release (not including tritium. gases.alche) Ci 7.40E-01 9.63E 01 2.16E+01
2. Average diluted concentration during ocriod uCi/mi 1.24E 09 1.62E 09
3. Percent of tech.soce. limit (1)  % 4.60E 01 2.37E+00
4. Percent of tech.soce.11mit(2)  % 2.30E 01 1.18E+00
5. Percent of tech.soce.11mit(3)  % 6.28E.01 2.60E 01 _
6. Percent of tech.soec. limit (4)  % 3.14E 01 1.3CE 01 B. TRITIUM 4.68E+01 2.33E+01 1.81E+01
1. Total Release Ci
3. Average diluted concentration during veriod uCi/mi 7.P7E 08 3.92E 08
3. Percent of acolicable limit (5) 1 2.62E-03 1.31E 03 C. DISSOLVED AND ENTRAINED CASES 1
1. Total Release Ci 9.48E 02 1.48E-01 2.00E+01
3. Average diluted concentration during verlod uCi/mi 1.59E 10 2.49E 10 13

TABLE 2A - REC CUIDE 1.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PIANT EFFw ENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1988 LIOUID EFFGENTS - SUMMATION OF Af 1. RK1 EASES IST 2ND EST. TOTAL W OSS ALPHA RADIGACTIVITY UNITS OUARTER OUARTER . E OR.1

1. Total Release Ci <2.67E 04 8.07E 05 3.00E+00 E. V0wME OF WASTE RELFASES (orior to dilution) 1Lters 5.87E+06 4.68E+06 3.00E+00 ,

F. V0 GME OF DILUTION WATER USED DURING PERIOD liters 5.95E+11 5.95E+11 1.40E+01 ,__

NOTES TO TABLE 2A (1) Percent of I.C.3 Quarterly Organ Dose Limit (10 arem)

(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 uCi/ml i

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TABLE 25 RKO CUIDE 1.21

(2ERT CLIFFS NUCLEAR POWFR PIANT EFFIDENT AND WASTE DISPOSAL SENI-ANNUAL REPORT FIRST HALF - 1988 14'0UID EFFIRENTS CONTINUOUS MODE (1) BATCH NODE IST 2ND IST 2ND NUCLIDES BRfEASED UNITS OUARTER OUARTER OUARTER OUARTER Be ryllium 7 Ci 0 0 - 7.97E 05 Sodium -24 Ci 0 0 1.10E 05 1.04E-Q1__

Chromium 51 Ci 0 0 2.69E 05 8.10E 02 Manranese 54 Ci 0 0 2.28E 03 4.78E 03 Cobalt 57 Ci 0 0 6.17E-05 2.03E 04 Cobalt 58 Ci 0 __

0 9.36E 02 3.32E 01 Cobalt 60 Ci 0 0 5.31E 03 1.69E 02 Iron -59 Ci 0 0  ; ___ - 2.16E-04 Strontium -89 Ci 0 6_ <2.88E 04 (2)

Strontium 90 Ci 0 0 <4.23E 05 (2)

Zirconium 95 Ci 0 0 - 1.23E 02 Niobium -95 Ci 0 0 1.31E 03 2.27E 02 Niobium -97 Ci 0 0 - 5.83E 03 Molybdenum -99 Ci 0 0 - 9.60E 05 Techntelum -99m Ci 0 0 6.52E 04 1.92E 03 l

Ruthenium -103 Ci 0 0 - 2.06E 03 Cadmium 109 Ci 0 0 , , ,

5.02E 04 1.07E 02 111Xer -108m Ci 0 0 - 1.84E.05 Silver -110m Ci 0 0 1.51E 02 4.17E 02 Tin -111 Ci 0 0 - 4.89E 04 bntimony -124 Ci 0 0 - 1.62E 02 Antimony 125 Ci 0 0 4.23E 02 8.47E 02 15

TAR 12 2B - REC CUIDE 1.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT FIRST HALF - 1988 LIOUID EFFIEENTS CONTINUOUS MODE (1) BATCH MODE IST 2ND IST 2ND NUCLIDES RK1 EASED UNITS OUARTER OUARTER OUARTER OUARTER Tellurium -129 Ci 0 0 - 4.47E 05 Tellurium -132 C1 0 0 1.07E 05 6.64E 04 Iodine -131 Ci 0 0 7.25E-02 1.60E 01 Iodine -132 Ci 0 0 2.39E-05 1.68E-03 Iodine 133 Ci 0 0 5.47E 03 7 . 6 3 E OL.,

Iodine -135 Ci 0 0 3.08E 04 9.29E 05 Cesium 134 Ci 0 0 1.88E-01 5.35E 02 Cesium -136 , ci 0 0 3.19E 03 8.74F-04 Cesium 137 Ci 0 0 3.09E 01 1.02E 01 lanthanum -140 Ci 0 0 1.99E 04 1.28E-04 Cerium -141 Ci 0 0 - 5.74E-04

< Total For Period Ci 0 0 7.40E 01 9.63E 01 i

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, o TABIE 25 - REC CUIDE 1.21 (Cont. )

CALVERT CLIFFS NUCLEAR POWER PIANT EFFIDENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1988 LIOUID EFF1EENTS CONTINUOUS MODE (1) BATCH MODE IST 2ND IST 2ND NUCLIDES BRIMASED UNITS OUARTER OUARTER OUARTER OUARTER ._

Arron -41 C1 0 0 - 2.28E 04 ,

Xenon -131m Ci 0 0 3.70E 04 -

Xenon 133 Ci 0 0 9.30E-02 1.47E 01 Xenon 133m Ci 0 0 5.15E 04 -

Xenon -135 Ci _

0 0 2.97E 04 7.78E 04 Xenon -135m Ci 0 0 5.94E-04 -

Total For Period Ci 0 0 9.48E-02 1.48E 01 (1) There were no continuous liquid releases during the 3rd and 4th quarters.

(2) Analysis for the 2nd quarter not completed.

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, e TABLE 3A CALVERT CLIFFS NUCLEAR POWER FIANT EFFLUENT AND WASTE DISPOSAL SENI-ANNUAL REPORT FIRST HALF - 1988 SOLID WASTE AND 1RRADIATED IVEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE MR BURIAL OR DISPOSAL (NOTE IRRADIATED WEL) 6 MONTH EST. TOTAL

1. Tyne of Waste UNITS PERIOD ERRORI 3
a. Dewatered spent resin m 7.86E+00 Ci 4.18E+02 2.00E+01 3
b. Dry Compressible Waste, m ---

Contaminated Equipment, etc. C1 --

3

c. Irradiated Corsponents, m ---

Control Rods, etc. Ci --

3

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

C1 --

2. Estimate of Major Nuclides (By Type of Waste)* ,
a. Cobalt 58 7.50E+00 %

Cobalt 60 1.70E+00 %  ;

Nickel 63 5.10E+00 %

Cesium 134 3.34E+01 %

cesium -137 5.02E+01 %  !

Manganese -54 1.00E+00 %

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  • Only nuclides greater than 11 are reported
3. Solid Waste Disposition l

Number of Shipments Mode of Transportation Destination ,

2 Motor Surface Transit Barnwell, S.C.  :

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B ALTIMORE GAS AND ELECTRIC CHARLES CENTER P. O. BOX 1475 BALTIMORE. MARYLAND 21203 JostPM A.TitRN AN Vect PassiotNT NvcaAm Ensen August 26, 1988 U. S. Nuclear Regulatory Commission Washingtor., DC 20555 ATTENTION: Document Control Desk SUBJ ECT: Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50 317 6 50-318 Semi Annual Effluent Release Report Gentlemen:

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, and an update of Table 1A for the second half of 1987. This report does not in-clude the analytical results for strontium for the second quarter. These values will be provided in an updated report as soon as these results are available. As required, the meteorological data is on file.

Very truly yours,

/

hC& W G JAT/PTC/jmh Enclosure l

l cc: D. A. Brune. Esquire J. E. Silberg, Esquire R. A. Capra, NRC S. A. McNeil, NRC V. T. Russell, NRC D C. Trimble/V. L. Pritchett, NRC T. Magette, DNR 3E4 T

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Document Control Desk August 26, 1988 Page 2 bec: P. E. Katz/R C. L. Olson C. H. Cruse /R, F. Ash R. E. Denton/J. A, Mihalcik R. M. Douglass/J. T. Carroll J. R. Lemons /R. P. Heibel W. J . Lippold/L. E. Salyards F. J. Manno /M, Gravrilas R. B. Pond, Jr./S. R. Buxbaum T. N. Pritchett/E. I. Bauereis L. B. Russell /R L. Venderlich C. C. Lawrence , III/M. J. Miernicki A. R. Thornton/M. E. Rowman R. E. Lapp R. C. DeYoung C. M. Ric' R, G. S'aker L. F. 'onatell D. L, Shaw, J r ,

S. R. Cowne P. E. McCrane

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