ML19332A233

Supplemental Info to Effluent & Waste Disposal Semiannual Rept,Jan-June 1980.

ML19332A233
Person / Time
Site:	Three Mile Island
Issue date:	09/05/1980
From:	METROPOLITAN EDISON CO.
To:
Shared Package
ML19332A231	List: ML19332A233
References
NUDOCS 8009110318
Download: ML19332A233 (8)

Text

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EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT January 1, 1980-June 30, 1980 .

SUPPLEMENTAL INFORMATION FACILITY TMI-UNIT I LICENSEE DPR-50/50-289

1. Regulatory Limits

a. Fission and activation gases:

c. r u ates, half-lives > 8 days: Art 3

d. Liquid effluents:

2. Maximum Permissible Concen.. rations Provide the MPCs used in determining allowable releasa rates or concentrations.

a, Fission and activation gases:

c$ art c ates, half-lives 8 days:

10 CFR, Part 20, Appendix B

d. Liquid effluents:

3. Average Energy Provide the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable - 0.253 MeV

4. Measurements and Approximations of Total Radioactivity Provide the methods used to measure or appcoximate the total radioactivity in effluents and the methods used to determine radionuclide composition.

a. Fission and activation gases: Ge(Li) Spectrometry, Liquid Scintillation

b. Iodines: Ge(Li) Spectrometry

c. Particulates: Ge(L1) Spectrometry, Gas Flow Proportional

d. Liquid effluents: Ge(Li) Spectrometry, Liquid Scintillation

5. Batch Releases Provide the following information relating to batch releases of radioactive materials in liquid and gaseous effluents.

l A. Liquid 1st Quarter 2nd Quarter

1. Number of batch releases: 45 47

2. Total time period for batch release: 2.61E4 min. 2.85E4 min.

3. Maximum time period for a batch release: 1.39E3 min. 1.38E3 min.

l 4. Average time period for batch releases: 6.06E2 min. 6.06E2 min.

5. Minimum cima period for a batch release: 4.5El min. 1.0E1 min.

6. Average stream flow during periods of

! release of effluent into flowing stream: 2.00E6 cfm 2.91E6 cfm 1

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5. Batch Releases (cont.)

B. Caseous 1st Quarter 2nd Quarter

1. Number of batch releases: 11 11-

2. Total time period for batch releases: 6.044E3 min. 6.537E3 min.

3. Mavimin= time period for a batch release: 7.65E2 min. 6.60E2 min.

4. Average time period for batch release: 5.49E2 min. 5.94E2 min.

5. Minimum time period for a batch release: 3.0E1 min. 4.95E2 min.

6. Abnormal _ Releases /None A. Liquid

1. Number of releases:

2. Total activity released:

B. Cadeous

1. Number of releases:

2. Total activity released:

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TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES I UNIT 1st 2nd EST. TOTAL I QUARTER QUARTER ERROR, :: I A. Fission & activation gases

1. Total release ci <1E-7 4.64E-3 2.5El

2. Average release rate for period UCi/sec. N/A 5.89E-4 Tech. Spec. Limit  ;

3. Percent of Tech Spec limit  % N/A 1.03E-5 = 1.9E4 =3/sec

= 5.7E3 pCi/see B. lodines .

for Kr-85

1. Total Iodine-131 Note (1) uC1/cc <1E-13 <1E-13 2.5El

2. Average release rate for period UCi/sec. N/A N/A Tech. Spec. Limit

3. Percent of Tech Spec limit  % N/A N/A = 0.05 Ci/sec C. Particulates

1. Particulates with half-lives .

> 8 navs C1 1.79E-4 7.53E-5 2.5El

2. Average release rate for period uCi/sec. 2.26E-3 9.56E-6 Tech. Spec. Limit

3. Percent of Tech Spec limit  % 4.52E-2 1.91E-2 = 0.05 vCi/sec

4. Gross alpha radioactivity s -

vCi/cc <1E-15 <1E-15 D. Tritium

1. Total release C1 1.42E1 3.89E0 2.5El

2. Average release rate for perio UCi/sec. 1.80E-1 4.93E-1 Tech. Spec. Limit

3. Percent of Tech Spec limit  % 4.74E-3 1.30E-2 = 1.9E4 m3 /sec.

= 5.7E3 uCi/sec for Kr-85 Note (1) - all less than (<) numbers are the LLD concentrations in units of UCi/cc.

Note (2) - all less than (s) numbers are for a 1640 cc Marinelli beaker sample and a sampling time of 1000 seconds.

.)

TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-GROU:.T LEVEL RELEASE l

Continuous Mode Batch Mode l Nuclides UNIT 1st Released 2nd 1st 2nd I QUARTER QUARTER QUARTER QUARIER -

1. Fission gases Notes (1), and (2)

< L t.- > < s t.-3 < s t,-3 kryp ton-85 Ci pCi/cc pCi/cc pCi/cc 4.64E-3 krypton-85m u Ci/cc <4E-8 <4E-8 <4E-8 <4E-8 krypton-87 p C1/cc <4E-8 <4E-8 <4E-8 <4E-8 krypton-88 u Ci/cc <2E-7 <2E-7 <2E-7 <2E-7 xenon-133 uCi/cc <1E-7 <1E-7 <1E-7 <1E-7 xenon-135 4 Ci/cc <3E-8 < 3E-8 <3E-8 <3E-8 xenon-135m pCi/cc <4E-8 <4E-8 <4E-8 <4E-8 xenon-138 U Ci/cc <5E-8 <5E-8 <5E-8 <5E-8 Others (specify) C1 Ci C1 Ci Ci Unidentified Ci i e Total for period Ci 4.64E-3

2. Iodines Notes (1),(3), and (4) iodine-131 pC1/cc <1E-13 <1E-13 <1E-13 <1E-13

<1h-13 <1b-1J <1L-14 iodine-133 Ci u Ci/cc 1.81E-6 pCi/cc UCi/cc

<1E-12 1 66E-3 <1E-12 <1E-12 iodine-135 Ci , , c , f ,. ,. , , c , f ,, ,, , , c , f ,, ,,

<1E-12 <1E-12 <1E-12 Total for period Ci , c , f ,, ,, 1.84E-5 , , c , f ,, ,, , , c , f ,, ,,

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TABLE IB (cont.)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT CASEOUS EFFLUENTS-GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides UNIT 1st 2nd 1st 2nd Released I QUARTER QUARTER QUARTER QUARTER

3. Particulates Notes (1),(3), and (5)

I strontium-89 u ci/cc <1E-13 < 1E- a <1E-13 <1E-13 strontium-90 u Ci/cc <1E-13 <1E-13 <1E-13 <1E-13 cesium-134 <ic-io <2c-io <. .o C1 3.18E-5 ..c4 fre ,,c4fy, .c4 fcc cesium-137 C1 1.21E-4 5.96E-5 <l d 1. !.8E-8 barium-lanthanum-140 Ci Others (specify) cobalt-60 C1 2.16E-5 6.0'4E-6 j&{fde '.'tifde silver-110m Ci 4.32E-6 l'-l <*'-1J UCi/>c c yc4 fee < ". c< te e ruthenium-103 -

Ci <IE-1J 1.49E-6 <1L-1J <A-A>

rt !-- 1e r4 f e e ' Pt f e e cerium- _144 Ci <1E;12' 6.48E-6 <IE-12 < u.- 14 CI/w sci /:: "' ' r :

Note (3) - all less than (<) numbers are calculated for a sample volume of 5.7E8 cc which is obtained using the following assumptions; a) sample rate of 2 cfm (lowest rate used) or 5.66E4 cc/ min.

b) sample counting time of 1000 seconds c) typical sampling time of one (1) week or 1E4 minutes Note (4) - with a sample counting time of 1000 seconds and a sampling rate of 2 cfm, it would take 2.5 days to achieve Tech Spec requirements for detectable concentrations.

Note (5) - with a sample counting time of 1000 seconds and a sampling rate of 2 cfa, it would take 20 minutes to achieve Tech Spec requirements for detectable concentrations.

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a TABLE 2A EFFLUENT AND L'ASTE DISPOSAL SEMIXiNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES UNIT 1st 2nd EST. TCTTAL I QUARTER QUARTER ERROR %

A. Fission and activation products - Tech. Spec. Limit = 10CFR20, Appendix B.

Table II, Column 2

1. Total releases (not including tritium, stases aloha) Ci 6.44E-2 7.24E-2 2.5El Z. Average diluted concentration durine oeriod C1/ml 3.00E-9 3.75E-9

3. Percent of applicable limit  % 2.38E-1 4.03E-2 B. Tritium

1. Total release Ci 2.07El 6.60E0 2.5El Z. Average diluted concentration during period UCi/ml 9.63E-7 3.42E-7

3. Percent of applicable limit  %

1.14E-2 3.21E-2 C. Dissolved and entrained gases

1. Total release Note (6) u Ci/cc <4E-7 <4E7 2.5El Z. Average diluted concentration durine oeriod uCi/ml N/A N/A

3. Percent of applicable limit  % N/A N/A D. Gross alpha radioactivity

1. Total release Note (6) pC1/cc <1E-7 <1E-7 2.5El E. Volume or waste released (prior to dilution) liters 9.81E5 9.63E5 1.0E1 F. of ution water used 1.0E1 liters 2.15E10 1.93E10 Note (6) - all less than (<) numbers are in units of Ci/cc and are the LLD for a 1000 m1 sample counted for 1000 seconds on a 25% detector.

A TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS .

Continuous Mode Batch Mode j l

Nuclides CIIT lst 2nd 1st 2nd Released I QUARTER QUARTER QUARTER QUARIER

< t r.- w ' A t.- u strontium-89 Ci 1.cf /cc u ci /cc 9.72E-3 5.39E-5 4.2E-3 < lE- 15 1.39E-2 2.50E-4 strontium-90 Ci

<2g f - --

cesium-134 Ci uri/cc gE-( _ 7.10E-3 8.29E-3 cesium-137 Ci <2g

., Ci /cc f

1.1E-3 2.91E-2 2.77E-2

'2E fodine-131 l c4 *yh 1.03E-3 7L '.f p- ) ,, ,

cobalt-58 Ci 'jhij,, </$7l, 4.43E-4 2.11E-4 cobalt-60 Ci *3hijec y *3[Q, y 2.91E-3 7.79E-3 iron-59 UCi/cc <3E-7 <3E-7 <3E-7 <3E-7 zine-65 ;Ci/cc <2E-7 <2E-7 <zE-7 <2E-7

<2E-7 <2E-Z managanese-54 Ci uCi/cc uCi/cc 2.68E-4 2.41E-4 chromium-51 Ci .

zirconium-niobium-95 pCi/cc <4E-7 <4E-7 <4E-7 <4E-7 molybdenum-99 uCi/cc <8E-8 <8E-8 <8E-8 <SE-8 technetium-99m uCi/cc <1E-7 <1E-7 <1E-7 <1E-7 barium-lanthanum-140 u Ci/cc <4E-7 <4E-7 <4E-7 <4E-7 cerium-141 u Ci/cc <2E-7 <2E-7 <?E-7 <2E-7 Other (specify) Ci Silver-110m Ci ^Nbifcc u'bI/cc . 4E-4 2.53E-2 Phnsohnrous-32 Ci .MTfee ',NIfee 1.52E-4 8.63E-5

( Antimony-125 <4E-l <4E-Z Ci uci/cc uci/cc <4Ef'cc u ci 2.02E-4 Ci C1 ci l Unidentified Ci l Total for period Ci 4.2E-3 2.13E-3 6.44E-2 7.02E-2 l

xenon-133 pCi/cc <4E-7 <4E-7 <4E-7 <4E-7 xenon-135 UCi/cc <2E-7 <2E-7 <2E-7 _

<2E-7 ~_.

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TABLE 3A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)

1. Type of waste UNIT f, h ES T TAL

a. Spent resins, filter sludges, m' 17.67 evaporator bottoms, etc. Ci 228.43

b. Dry compressible waste, contaminated eq uipmen t , etc.

o' 179 cf .71974

c. Irradiated components, controi m3 rod s , e t c.

Ci ms

d. Other (describe) C1

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

n. Cs-137 66.3 %

Cs-134 24.3g Co-60 3.4 y Co-58 4  %

b.

Cs-137 55.9 x Cc-134 32.2x Co-60 5. 5 %

An-110m, 4. 5 %

c. g 2

d. g

3. Solid Waste Disposition Number of Shipments. Mode of Transportation Destination Three Tractor / Trailer Richland, Washington Seven Tractor / Trailer Barnwell, South Carolina B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination

. . ~ - . . . - _ . _ .

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