Text

Effluent & Waste Disposal Semiannual Rept,July-Dec 1978
	ML19282B503
Person / Time
Site:	Maine Yankee
Issue date:	12/31/1978
From:	; Maine Yankee
To:	;
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ML19282B501	List: ML19282B500; ML19282B503;
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	NUDOCS 7903150226
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MAINE YANKEE ATOMIC POWER COMPANY EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JULY - DECEMBER 1978 790315 0 AJ 4

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4 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FACILITY': MAINE YANKEE ATOMIC POWER COMPANY LICENSEE: MAINE YANKEE ATOMIC POWER COMPANY 1.

Regulatory Limits a.

Fission and activation gases:

10 CFR 20; Paragraph 20.106 b.

Iodines:

c.

Particulates, half lives 8 days:

d.

Liquid effluents:

2.

Misimum Permissible Concentrations a.

Fission and actuation gases:

10 CFR 20; App. B. Table 2 Col.1 b.

Iodines:

c.

Particulates, half lives 8 days d.

Liquid effluents:

3.

Average Energy - Not Applicable 4.

Measurements and Approximations of Radioactivity a.

Fission and activation gases:

Continuous discharge - Vent stack samples are analyzed monthly and the levels of activities determined are assumed to hold for the period between samples.

The continuous vent stack monitor reading is used as a basis for increasing periodic sample frequency.

Air ejector is sampled monthly and on any increase in continuous air ejector monitor reading.

Batch discharges - Direct measurement of waste gas hold up drums are made before discharge.

Contain:ent vents and purges are analyzed by direct measurement of the containment atmosphere at periodic intervals during the discharge.

b.

Continuous monitoring of primary vent stack iodines are made by veckly measurements of an in-line charcoal filter.

Batch discharges - Direct measurement of waste gas hold up drums before discharge.

c.

Particulates - Continuous monitoring of primary vent stack is made by weekly measurement of an in-line particulate filter.

Batch discharges - Direct measurement of vaste gas hold up drums before discharge.

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d.

Liquid Effluents Weekly sample of secondary systems liquid effluents for gross Seta-gamma, alpha, tritium, dissolved gases and gamma emitting isotopes each batch release.

Composite samples are made of secondary and primary systems liquid effluents for a quarterly analysis of strontium 90 and 89.

5.

Batch Releases a.

Liquid 1.

Number of releases:

174 2.

Total time for batch releases:

304 hrs.

53 min.

3.

Maximum time for batch releases:

18 hrs.

28 min.

4.

Average time for batch releases:

1 hr.

45 min.

5.

Minimum time for batch releases:

30 min.

6.

Average stream flow during periods of release.of effluent into a flowing stream:

7.

Maximum gross release rate (s<ci/ml) 8.13E-08 b.

Gaseous 1.

Number of batch releases:

29 2.

Total time period for batch releases:

1,505 hrs.

36 min.

3.

Maximum time period for a batch release:

724 hrs.

55 min.

4.

Average time period for a batch release:

51 hrs.

4 min.

5.

Minimum time for a batch release:

1 hr.

50 min.

6.

Maximum gress release rate ( qci/sec) 5.70E-03 aci/sec.

6.

Abnormal Releases a.

Liquid 1.

None.

b.

Gaseous 1.

None.

The following table is not attached since there was no applicable release during the reporting period.

Table 1C Gaseous Effluents, Ground-Level Releases.

TABLE 1A EFFLUENT AND h'ASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS - SU't ATION OF ALL RELEASES Unit Quarter QuTrter 3rd 1978 4th 1978 A. Fission G activation gases

1. Total release Ci 1.04E+03 3.34E+02

2. Average release rate for period pCi/sec 1.32E+02 4.25E+01

3. Percent of technical specification linit 1,13pton 2. 7 0E_-01 I

B. Iodines

1. Total iodine-131 Ci 1.46E-03 1.00E-04

2. Average release rate for period pCi/sec 1.86E-04 1.27E-05

3. Percent of technical specification limit 4.86E-03 3.03E-04 C. Particulates

1. Particulates with half-lives >8 days Ci 1.80E-05 1.22E-05

2. Average release rate for period pCi/sec 1.92E-06 1.55E-06

?4 4.67E-06 2.62E-04

3. Percent of technical specification limit

4. Gress alpha radioactivity Ci 1.87E-07 3.46E-07 D. Tritium

1. Total release Ci 4.llE-01 3.92E-01

2. Average release rate for period pCi/ sect 5.23E-02 4.99E-02

3. Percent of technical specification lic.it 4

l 6.77E-04 6.467-na

\\~

TABLE IB EFFLUENT AND NASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS - RELEASED FROM STACK CONTINUQUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclide.s Released Unit Quarter Quarter Quarter Quarter 1978 1979 1978 1978

1. Fission gases krypton-SS Ci

<8E-05*

(8E-05*

1.43E+00 1.20E+00 krypton-85m Ci

<1E-07*

<1r-07*

<1r n7*

krypton-S7 Ci

<3E-07*

<1r-07*

<1r n?*

<3r-9'^

krypton-83 Ci

<3.5E-07*

< 3. 5E-07*

(3.5E-07*

(1 ;r-n7*

xenon-133 Ci 1.32E+01 8.79E+01 1.01E+03 2.67r+09 xenon-135 Ci

<7E-07*

3.37F40n 2.36E+00 xenon-135m Ci

<5E-07*

<st-07*

xenon-13S Ci (1.7E-07*

<1.7E-07*

<l.7E-07x Others (soccify)Xe 133m Ci

<5.0E-07*

<5E-07*

5.45E-03

<sr-07*

Ar-41 Ci

<1.7E-06*

<1.7F n6*

<r 7F-nA*

(1.7E-06*

Xe-131n Ci

<1.0E-06*

<1.0E-06A 1.07F+01 (1.E-06*

unidentified Ci U.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for pericd Ci 1.32E+01 8.79E+01 1.03E+03 2.46E+02

2. Iodines iodine-131 Ci 1.46E-03 1.00E-04

<1.0E-05**

l <1.0E-05**

iodine-133 Ci 3.17E-05

<1E-13*

<1.0E-05**

<1'. 0 E-0 5 *

iodine-135 Ci

<2E-12*

< 2 E-12 *

(1.0E-04**

<1.0E-04**

Total for period Ci 1.49E-03 1.00E-04 0.0E+00 0 0.0E+004

3. Particulates strontium-89 Ci

<7E-15*

1.05E-06 strontium-90 Ci 5.87E-08 2.57E-08 cesium-134 Ci (JE-14r (3E-14*

<1E-04**

(IE-04**

cesium-137 Ci

<3E-14*

8.47E-07

<lE-04**

<1E-04**

barium-lanthanua-l..C Ci

<1E-13*

<1E-04**

(IE-04**

Others (specifv)

Ci Co-53 Ci 1.6SE-05 2.42E-06

<1E-04**

<1F-ni**

Co-60 Ci 1.15E-06

<3E-14*

<1E-05**

<1E-04**

unidentified Ci 0.00E+00 4.34E-06

Mininua detectable activity in Uci/cc

- Iodine and particulates collected on centinuous mode filters include batch mode releases.

- - Batch mode strontium is collected on continuous code sample. filters.

O No detectable activity.

TABLE 2A EFFLUENT A'!D WASTE DISPOSAL SE:lIANNUAL REPORT LIQUID EFFLUENTS - SU a!ATION OF ALL RELEASES i

Unit Quarter Quarter 3rd 4th A. Fission and activation products

1. Total release (not including tritium, 7.62E-02 1.20E-02 gases, alnha)

C1

2. Average dilutea concentration during period uCi/ml 6.63E-10 5.56E-11

3. Percent of applicaole limit 1.61E-01 6.0?r-01__,

B. Tritiun

1. Total release Ci 1.41E+01 4.14E+01

2. Average diluted concentration during period UCi/ml 1.26E-07 1.92E-07

3. Percent of arplicable linit 4.20E-03 6.39E-03 C. Disso.1ved and entrained gases

1. Total release Ci 4.53E-02 2.88E-01

2. Average diluted concentration during period UCi/ml 3.96E-11 1.33E-09

3. Percent of apolicable limit 1.35E-02 4.44E-02 D. Gross alpha radioactivity

1. Total release Ci 5.47E-07 1.36E-07 E. Volume of waste released (prior to dilution) liters 2.67E+07

1. 47 E+07 F. Volume of dilutien water used during period liters 1.12E+11 2.16E+11

TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter 1978 1978 1978 1978 strontium-89 Ci 2.00E-03

<5E-08

i_ocr_n,

<3E-08 strontiua-90 Ci

<1E-OS*

<7E-08

<7E-09*

<7E-09 ccsium-134 Ci

<5E-OS*

<5E-08*

1.20E-03 2.05E-04 cesiun-137 Ci

<6E-OS*

(6E-08*

t.42E-01 6.52E-04 iodine-151 Ci

'5E-05*

<5E-08*

6.43E-02 l 3.867-n3 cobalt-SS Ci

<5E-08*

(SE-08*

5.62E-03 7.25E-03 cobalt-60 Ci (6E-080

<6E-08*

1.19E-04

< 6E-07 f iron-59 Ci (IE-07*

(IE-07*

<1E-06*

c1E-06*

zinc-65 Ci

<9E-08*

< 9 E-07 *

<oE-07*

manganese-54 Ci

<5E-08*

<5E-OS*

7. 04E-05 l < 5E-07*

chromiua-51 Ci (3E-07*

<3E-07*

<3E-06*

I <3E-06*

_l zirconium-niobium-95 Ci

< 8 E- 0S *

<8E-08*

<. 8 E-07 *

<8E-07*

molyb.lenun-99 Ci

<4E-08*

(4E-07*

< 4 E-07

technet s om-99n Ci

'4E-080

<4E-08*

< 4 E-07 *

< 4 E-07*

barium-liist'hanua-140 1

Ci

< 2 E-0 7 )<

<2E-07*

< 2 E-06*

< 2 C-06

ceriui lil C1

'4E-08*

<4E-08*

< 4 E-07 *

<4E-07*

l Other (specify)

Ci Ci 1-133 Ci

< 4 E-07*

(4E-07*

4.61E 04

< 4 r n6 +

CO-57 Ci

'1E-05*

<1E-08*

<.1 E-0 7

6.53E-05 Ci unidentified Ci 0.00E+00 0.00E+00 l 0.00E+00 Total for period -(above)

Ci 2.00E-03 0.0**

7.42E-02 1.20E-02

-+

xenon-133 Ci

<1E-07*

4.53E-02 2.87E-01 xenon-135 Ci

<6E-06*

<bE-06*

<6E-056 3.27E-04

Minimum detectabic activity in uci/=1

- No detectable activity f'

TABLE 3 EFFLUENT AND WASTE DISPOSAL SEIIIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMEhTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL GR DISPOSAL (Not irradiated fuel)

1. Type of waste Unit 6-month Est. Total Period Error, %

a. Spent resins, filter sludges, evaporator na 1.14+E02 3*0 + E01 bottoms, etc.

C1 5.79+E01 3

2.103+E02

b. Dry compressible waste, contaminated m

3*0 + E01 couip, etc.

Ci 1.48+E01

c. Irradiated components, control m3 rods, etc.

Ci 3

m

d. Other (describe)

Ci

2. Estimate.of major nuclide composition (by type of waste) a.

Cs-137 1

4.5 + E01 2.6 + E01 Cs-134

- Lo-ou, Lo-5o 2.7 + E01 b.

Cs-137 4.0 + E01 Co-60 3.0 + En1 Cs-134, Co-58 3,0 + Eq1 4

c.

d.

g 9:

h

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 27 Truck Chem. - Nuclear Ba rnwell, S. C.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 1

.

ML19282B503

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