ML19294B794

Semiannual Effluent Release Rept,Jul-Dec 1979.

ML19294B794
Person / Time
Site:	Calvert Cliffs
Issue date:	02/29/1980
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19294B791	List: ML19294B790 ML19294B794
References
NUDOCS 8003060041
Download: ML19294B794 (18)

Text

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SEMI-ANNUAL EFFLUENT RELEASE REPORT FOR CALVERT CLIFFS I;UCLEAR PCWER PLANT SECOND ,FJLLF - 1979 LIST OF ENCLOSURES TITLE PAGE/ TABLE Regulatory Limits 1 Maximum Permissable Ccncentration 2 Measurements and Approximation of Total Radicaccivity 3 Batch Releases T Abnormal Release T Gasecus Effluents - S m tion of Releases lA Gaseous Effluents - Isotopic Breakdown 1C Liquid Effluents - Su==ation of Releases 2A Liquid Effluents - Isotope Breakdevn 2B Solid Waste Shipments 3A Meteorological Su==ary Not Included O

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CALVERT CLIFFS NUCLEAR POWER PLANT 1

EFFLUENT AND WASTE DISPOSAL SE4I-ANNUAL REPORT]

SUPPLHEITAL I?TFCF14ATION Facility - Calvert Cliffs Nuclear Power Plant Licensee - Baltimore Gas & Electric Cenpany I. REGULATORY LIMITS A. Fission and Activation Gases:

1. The instantaneous release rate of gross activity, except for I-131 and particulates with half-lives longer than eight days shall not exceed Oi g

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, (3.85 x 105) (leC)1 where Qi is the release rate in Ci/see for isotope 'i and MFCi is the =aximum permissible concentration of isotope i as defined in Appendix B, Table II, Column 1,10 CFR 20.

2. The release rates of gross gaseous activity shall not exceed 16 percent of the values specified in I.A.1. above when averaged over any calendar quarter. See Table 1A, A3.

3. The release rates of gross gaseous activity shall not exceed 8 percent of the values specified in I. A.1. above when averaged over 12 consecutive months. See Table IA, Ah.

B. Iodines and Particulates, Half-Lives > 8 Days:

1. The release rate from the main vents of I-131 and particulates vith half-lives greater than eight days released to the environs lj Submitted in accordance with Technical Specification 5.6.1.b. . , .

i as part of airborne effluents shall not exceed 2.0 uCi/sec (I-131 equivalent).

2. The release rates of I-131 and particulates shall not exceed 8 percent of the value specified in I.B.1. above when averaged over any calendar quarter. See Table 1A, 33

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3 It should be noted that " iodines" as used here includes only iodine-131 since the technical specifications caly refer to it specifically. Such other iodines, i.e. , iodine-133, iodine-135, etc. , are treated as gross activity and are included in I.A.1. and 1.A.2.

h. The release rates of I-131 and particulates shall not exceed h percent of the values specified in I.B.1. above when. averaged over any 12 consecutive months. See Table 1A, Bh.

C. Liquid Effluents:

1. The release rate of radioactive liquid effluents, excluding tritium and noble gases, shall not exceed 10 curies per unit during any calendar quarter.

2. The radioactivity release concentrations in liquid effluents frca the plant shall not exceed the values specified in 10 CFR Part 20, Appendix B, for unrestricted areas.

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II. MAXIMUM PERMISSIBLE CONCENTRATIONS The MPC's used for radioactive =aterials released in liquid and gaseous effluents are in accordance with Technical Specifications and/or are derived from the use of notes to Appendix 3,10 CFR Part 20. In - . -

all cases the most restrictive (lovest) MFC found for each isotope is used regardless of solubility.

The following limits were used to calculate the percent of applicable limit in Table 2A.

A. Fission and Activation Products - Limit used 1 x 10-I uCi/=1.

This li=it was used as given in the notes to Appendix B,10 CFR 20.

B. Tritium - Li=it used 3 x 10-3 uC1/=1.

This l'imit was used as given in Appendix 3, Table II, Colu=n 2 of 10 CFR 20.

C. Dissolved and Entrained Gases - Li=it used 3 x 10-6 uCi/=1.

This li=it was used as given in Appendix B, Table II, Column 2 of 10 CFR 20. .

III. AVERAGE EIERGY - not applicable IV. MEASUREMENTS AITD APPROXIMATIONS OF TOTAL RADI0 ACTIVITY A. Fission and Activation Gases:

1. Batch releases Prier to each batch release of gas from a pressurized gas decay tank, a sa=ple is collected and analyzed for each significant isotope using a Ge(L1) detector. The total activity released is based on the pressure /volu=e relationship (gas lavs) of the tank prior to and after the release.

Prior to and after the release of gas as a result of purging containment, sa=ples are collected and analyzed for each significant isotope using a Ge(Li) detector. The total , ,

activity released is based on containment volu=e and purge rate with activity buildup while purging being considered.

2. Continuous releases During the release of gas from the main vents, sa=ples are collected and analyzed at least weekly for each significant isotope using a Ge(Li) detector. The total activity released for the week is based on the weekly result multiplied by the main vent flow for the week.

B. Iodines and Particulates:

1. Batch releases Total activity released frem a pressurized gas decay tank as iodines and particulates is measured by the same methods as fission and activgtion gases.

Prior to and after the release of gas as a result of purging containment, iodines are sampled using a charecal filter and particulates are sampled using a particulate filter.

These filters are analyzed for each significant isotope using a Ge(Li) detector. The total activity released is based on containment volune and purge rate with activity buildup while purging being considered.

2. Continuous releases During the release of gas from the main vents, samples of iodines and particulates are collected using a chared end particulate filter respectively. The filters are removed weekly and are analyzed for each significant isotope using a Ge(Li) detector. The total activity released for the week is based on the activity found on the filters r:ultiplied by the mai'n vent flov for the week. - The activity on the filters

is corrected for decay and buildup during the sa=pling period.

These weekly particulate filters are then composited to for=

onthly and quarterly ec=posites at which time gross alpha and strontium 89 and 90 are analyzed.

Total activity released via condenser vacuum pu=p releases

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is measured by the same methods e= ployed for fission and activation gases.

C. Liquid Effluents:

1. Batch releases Prior to the release of liquid frc= a monitor tank, a sa=ple is collected and analyzed for the concentration of each significant ga==a energy peak to demonstrate co=pliance with Section 1.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 deternined by multiplying the volu=e released times the concentration of each' isotope. The actual volume released is based en the difference in tank levels prior to and after the release. A proportional ec=posite sa=ple is also withdrawn for each week's releases, and this is used in turn to prepare monthly and' quarterly co=posites for use in analyses of gross ,

alpha and strontium 89 and 90.

2. Contir.uous releases Steam generator blevdown is sa= pled daily and these samples are used in turn to prepare a weekly blovdown composite based

- on each day's blevdown. The weekly ec=posite is analyzed for

each significant isotope using a Ge(Li) detector and these results are multiplied by the actual quantity of blevdown to deter =ine the total activity released. The weekly ec=posite is also used to prepare monthly and quarterly ecmposites for use in analyses of tritium, gross alpha, and strontium 89 and 90.

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D. Estimation of Total Error:

Total error on all releases was esti=ated using as a =inimu=

the randes counting error associated with typical releases. In addition to the random error the detector to sample gecnetry systematic error during gn==a counting was determined. This included an estimate of sa=ple volu=e error and sample pipetting error. More specifically the following other systematic errors vere also examined:

1. Licuid -

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

b. Error in volune of liquid released via steam generator blevdown.

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

2. Gases

a. Error in main vent release flow,

b. Error in sa=ple flow rate.

c. Error in containment purge release flow.

d. Error in gas decay tank pressure.

Where errors could be esti=ated they were usually considered additive.

V. BATCH RELEASES A. Liquid:

Third Fourth Quarter Quarter

1. Nu=ber of batch releases 8.10E+01 6.70E+01

2. Total time period for batch 5.27E+02 h.25E+02 release (hrs. )

3. Maximum time period for a 7 38E+02 8.85E+02 Batch release (min.)

h. Average time period for batch 3.90E+02 3.80E+02 releases (nin. )

5 Minimum time period for a 5.00E+00 2 50E+01 batch release (min. )

6. Average strees flow during periods h.6hE+06 4.6hE+06 of effluent into a fleving stream (liters / min. of dilution water)

• B. Gaseous Third Fourth Quarter Quarter

1. Number of batch releases 9.00E+00 2.20E+01

2. Total time period for batch h.79E+03 5 19E+04 releases (min. )

3 Maxi =um time period for a batch 2.30E+03 3 50E+0h release (min.)

h. Average time period for batch 5.32E+02 2.36E+03 releases (min.)

5 Minicum time period for a batch 7.80E+01 1.05E+02 release (=in.)

VI. ABNOPMAL RELEASES . . . -

A. Liquid:

! Third Fourth Quarter Quarter

1. Nu=ber of releases 2. Total activity released (Curies 12]

UExcluding tritiu= and dissolved gases

B. Gaseous:

Third Fourth Quarter Quarter

1. Nu=ber of releases _o_ _o_

2. Total activity releases (Curies)

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1~/FLUEIiT AllD '#3TE DISPOGAL SCIIAT;UAL BEFORT GECCI:D HALF - 1979 GASEOUS EFFLUE:;TS ';U'C'.ATIC:T CF ALL RELEASES A.

3rd kth Fst. Total Fission and netivation rases Units Quarter Cuarter Error, i

1. Total release Ci 5 76E+03 1.0hE+03 2. 80 E+01

2. Average rel:a':e rate for neriod I uCi/ ec 7 91E+02 1 1.32E+02

3. Percent of technical scecification limit (1)  % 3. 98 E+00 7.30E-01

h. Percent of technical specification limit (2) 5 5.2SE+00 h.98E+00

3. Iodines

1. Total icdine - 131 Ci 5.05E-02 2.91E-02 h.00E+01

2. Average release rate for teriod uCi/sec 6.h1E-03 3.69E-03

3. Peregnt of tc-etnical specification _ linit___(3)  % h.00E+00 2.31E+C0

h. Percent of technical snecification linit (h) ",

1.29E+01 1.2CE+01 C. Particulates

1. Perticulates with half lives >8 days Ci h.?OE-C2 5.85E-03 2.6CE+01

2. Averare release rate for period uCi/sec 6.09E-03 7.k2E-Oh

3. Percent of technical specification linit (5) < h.<'cr+00 2.31E+00

h. Gross alpha radioactivity Ci 2.31E-C6 1.h52-05 D. Tritium

1. Total release Ci 3.h0E+C0 8.892-01 1.60E+01 .

2. Avernce release rate for ceriod uCi/see h.31E-01 1.13E-01 ,

3. Percent of -technical scecification limit (6)  % 3.98E+00 7.3cE-01_

(1) Percent of I.A.2 for each quarter (2) Percent of I. A.3 for previous 12 nonths (3) Percent of I.3.2 for each quarter (4) Percent of I.3.3 for previous 12 =cnths '

(5) Percent of technical specificatica limits for iodines including particulates) 8 da/s (6) Percent of technical specification li:its for gases inclu.ies tritium .

CALVERT CLIFFS NUCLEAR POWER PLANT SECCND HALF - 1979 GASEOUS EFFLUEI;TS - OROUND LEVEL RELEASES Continuous Mode Batch Mode 3rd hth 3rd hth

1. Fission and activation gases Unit Quarter Quarter Quarter Quarter krypton -

85m Ci > 3.h3E-02 1.35E-01 krypton -

87 Ci 1.96E-03 krypton

- }8 Ci 2.30E-02 1.36E-02 1 xenon -

131m Ci 3.69E-01 h.61E-01 xenon -

133 Ci 9.06E+02 9.53E+02 h.85E+03 7.70E+01 xenon -

133s ci 1.05E+00 >1.32E+00 xenon -

135 Ci i 2.12E+00 6.h0E+00 l

argon - h1 Ci 3.95E-02 2.70E-02 i i total for period Ci 9.06E+02 9.53E+02 h.85E+03 '8.5LE+01_

2. Halogens iodine -

131 Ci 9.30E-03 1.h0E-02 h.12E-02 1.51E-02 iodine -

132 Ci 7.80E-07 9.ShE-071 iodine -

133 Ci h.06E-03 1.02E-02 2.80E-03 3 30E-03 I

iodine - 13h Ci I 1 97E-06 i'odine - 135 Ci h.67E-06 1.53E-05 I

l brcsine - 82 Ci I 7.80E-0512.96E-05 total for period Ci 1.3hE-02 2.h2E-02 h.k12-02 1.8hE ')2

3. Particulates strontium -

89 Ci 3.3hE-ch 5.23E-Oh l

strontium -

90 Ci 1.h0E-05 h.87E-05 barium - 1h0 Ci 3.29E-02 strontium -

85 Ci- 9 8E203 -

rubidium - 88 Ci 5.62E-03 h.13E-03 molybdenum - 99 Ci 2.89E-07 canganese -

54 , Ci 5.03E-06 1 1.82E-05 cesium -

138 Ci 1.6cE-05 9.2hE-05

CALVERT CLIFFS NUCLEAR P0k'ER PLAIiT SECOND HAIJ - 1979 OASECUS EFFLUDITS - GROUITD LEVEL RELEASES (Continued) Continuous Mode Batch Mode 3rd hth 3rd hth 3 Particulates (Continued) Unit ouarter Quarter Quarter Quarter cobalt -

58 Ci 7.96E-05 9 13E-oh strontium -

91 C1 1.53E-06 niobium -

l95 Ci h.50E-06 ruthenium - 106 Ci h.08E-06 1

cesium -

137 Ci h.00E-06 l 1.87E-05 sodium - 2h Ci '

2.39E-06 manganese -

56 Ci i 3.27E-06 l i j l' barium -

139 Ci 5.05E-06 l

chro=ium - 51 l Ci 5.12E-06 I i  !

total for period Ci '3.h8E-Oh 6.60E-Oh h.77E-02 i 5.19E-O'll e

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TABLE 2A REG. CUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECCND HALF - 1979 LIQUID EFFLUEUTS - SUM'ATION OF ALL RELEASES 3rd 4th Est. Total A. Fission and activation products Units Quarter Quarter Error, T Total release (not including 1.' tritium, cases, alpha) Ci- 9.12E-01 h.5hE+00 1.20E+01_

Average diluted concentration

2. during neriod uCi/ml 1.65E-09 7.68E-09

3. Percent of anolicable limit 5 1.65E+00 7.68E+00 B. Tritium * *

1. Total release Ci 1.31E+02 1.33E+02 1.20E+00 Average diluted concentration

2. during neriod uCi/=1 l2.37E-07 i 3.10E-07 1

3. Percent of applicable limit  % 7. 90E-03 1. 03E :02 C. Dissolved and entrained cases

1. 1'otal release l Ci 5.97E+00 2.27E+00 9 00E+00 Average diluted concentration  !

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2. during period uCi/ml 1.08E-08 3.8hE-09 3 Percent of applicable limit 5 3.60E-01 1.28E-01i D. Gross alpha radioactivity -

1. Total release Ci lK1.87E-03 <8.32E-Oh1.60E+01 (prior to l }

E. Volume of Waste Releases dilution) i liters  ! 2.19E+07 1.05E+07 2.70E+00 Volume of dilution water used l  ! j F. during nariod '

liters  ! 5.53E+11 5 91E+11 l 3.36E+00

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TABLE 2B REG. GUIDE 1.21 CALVERT CLIFFS ITUCLEAR POWER PLAIiT EFFLUENT AND WASTE DISPOSAL SEMIANIiUAL REPORT 1979 LIQUID EFFLUENTS Continuous Mode (1) Eatch Mode 3rd hth 3rd hth Nuclides Released Units Quarter Quarter Quarter Quarter strontium - 89 Ci 1.28E-Oh  ! 3.00E-06 2.01E-Oh 1.55E-Oh strontium - 90 Ci 1.06F-Oh '

1.20E-06 2.1hE-Ch 1.65F-Oh cesium - 13h Ci 5.52E-02 1.6hE-01 cesium - 137 Ci 8.75E-02 2.31E-01 i iodine - 131 Ci (6.96E-03 (1.16E-oh 1.21E-02 3.05E-01

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)

cobalt - 58 Ci h.33E-01 2.61E600 cobalt - 60 l. Ci i h.80E-02 1.70E-01

, I Iiron - 59 ci 1. hoe-02 ! 1.32E-02 manranese - Sh Ci 9.36E-03 8.27E-02 chromium - 51 Ci 8.76E-02 3.89E-01 zirconium - 95 Ci 2.69E-02 ! 7.73E-02_

nicbium - 95 Ci 3.25E-03 h.56E-03 i

molybedenum - 99 Ci '

2.01E-03 2.85E-03'

i i barium ,- 1LO ' Ci i i 3.63E-Oh 7.68E-03 antimony - 12h Ci  ! 6.19E-05 2.23E-32 iodinR - 133 Ci I 1.h9E-02 ! 1.85E-01 i I antimony - 125 Ci  !

3.72E-02 1.78E-01 -

I I l l obalt - 57 Ci 6.06E 6.35E-03 tin 113 Ci 8.70E-Oh l 6 i ruthenium - 103 '

Ci- I h.85E-03 ! 2.85E-03 ,

, t j 1 iodine - 135  ! Ci I 1 59E-02 3

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! Ci circonium - 97 2 3 96E-05 '

6.03E-Ohl

' iodine - 132 Ci . # 2.h8E-03

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TABLE 2B RE3. CUIDE 1.21 CALVERT CLIFFS NUCLEAR PC'a*ER PLANT EFFLUENT AND WASTE DISPOSAL SD4IAliNUAL REPORT 1979 LIQUID EFFLUENTS (CONTINUED)

Continuous Mode (2) Batch Mode 3rd hth 3rd hth Nuclides Released Units Quarter Quarter Quarter Quarter ruthenium - 106 Ci 2 35E-03 cerium - 1h1 Ci '

6.36E-Oh 9.h2E-Oh silver - 110m Ci h.31E-02 2.21E-02

, lanthanum - 1ho Ci 2.2hE-03 3 52E-02 manganese -

56 C. 2 77E-Oh 3.82E-Oh strontiva -

85 Ci 7.2hE-Oh ,

unidentified Ci  ! 7.132-03 1.67E-Oh 1.12E-02 8.61E-03l 1

, Total for neriod (above) Ci 1.h3E-02 2.89E-Ohl8.98E-01

, k.5kE+00;

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TABLE 23 REG. GUIDE 1.21 CALVERT CLIFFS fiUCLEAR POWER PLAliT EFFLUEIiT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS Continuous Mode Batch Mode 3rd hth 3rd hth Nuclides Released Unit Quarter Quarter Quarter Quarter l

Xenon -

133 Ci <1.2hE-02 c2.07E-Oh 5.78E+00 2.15E+00 Xenon -

135 Ci 1.h0E-01

• 1. 032-01 l

Ii i i 3.h3E-02 Tenen -

133m Ci 2.05E-02 l '

iKrycton - 87 Ci 2.27E-05 (1) Continuous mode releases, i.e. nuclides released, are less than

" unidentified" unless otherwise noted.

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. TMM M EFFLUENT AND WASTE DISPOSAL SEMIANNUAL PIPORT SECOND HALF - 1979 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL ON DISPOSAL (NOT IRRADIATED FUEL) 6-Month Est Total

1. Type of Waste Unit Period Error %

a. Spent resin, filter sludge, m3 1.92E+01 2.00E+01 evaporator bottoms, etc. Ci 2.25E+01

b. Dry compressible vaste, m3 1.1hE+02 5.00E+01 contaminated equipment, etc. Ci 4.19E-01

c. Irradiated components, centrol m3 3.26E+01 5.00E+01 rods, etc. Ci- 2.0hE-02

d. Other (describe) -- ---- - - - - - -

2. Estimate of major nuclides (by type of vaste)

Units

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a. Cobalt -

58  % 6.25E+01 Cesium -

137 f, 8.09E+00 Cobalt - 60  % T.68E+00 Cesium -

13h  % 5.00E+00 Manganese -

Sh  % 3.79E+00 Iodine -

131  % h.10E+00 Chromium -

51  % 1.57E+00 Ruthenium - 106  % 2.17E+00 Antimony -

125  % 2.38E+00

b. Cobalt - 60  % 1.00E+02

c. Cobalt - 60  % 1.00E+02

d. ------ --- - --

TABLE 3A (CONTINUED)

SOLID WASTE AND IRRADIATED WEL SHIPMENTS

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 14 Motor surface transit Barnvell, S. C.

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