ML19305A553

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Effluent & Waste Disposal Semiannual Rept, Jan-Jun 1979
ML19305A553
Person / Time
Site: Crane  
Issue date: 08/30/1979
From:
Metropolitan Edison Co
To:
Shared Package
ML19305A551 List:
References
NUDOCS 7909050412
Download: ML19305A553 (9)


Text

'

l-l TMI - Unit 1 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT January 1 - June 30,1979 SUPPLEMEN.TAL INFORMATION FACILITY Three Mile Island, Unit I LICENSEE DPR 289 1.

Regulatory Limits a.

Fission and activation gases:

b.

Iodines:

Environmental Tech Specs, c.

Particulates, half-lives > 8 days:

Article 2.3 d.

Liquid effluents:

2.

Maximum Permissible Concentrations Provide the MPCs used in determining allowable release rates or concentrations.

a.

Fission and activation gases:

10 CFR, Part 20, Appendix B c.

Part cu ates, half-lives 8 days:

d.

Liquid effluents:

3.

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

E 0.085 MeV and E 0.11 HeV Y

8 T-4.

Measurements and Approximations of Total Radioactivity

~

Provide the metho:t used to measure or approximate the total radioactivity in ef fluents and the methods used to determine radionuclide composition.

a.

Fission and activation gases: Ce(L1) Spectrometry, Liquid Scintillation b.

Iodines: Cc(Li) Spectrometry c.

Particulates:

Ge(Li) Spectrometry, Gas Flow Proportional d.

Liquid effluents: Ge(L1) Spectrometry, Liquid Scintillation

~

5.

Batch Releases Provide the following information relating to batch releases of radioactive materials

'~4 in liquid and gaseous effluents.

~~

~

A.

Liquid lat. Qtr.

2nd. Qtr.

1.

Number of batch releases:

46 44

- 2.- Total time period for batch release:

1.89E+4 min.

3.15E+4 min.

3.

Maximum time period for a batch release:

1.23E+3 min.

1.29E&3 min.

4.

Average time period for batch releases:

4.llEF2 min.

7.17E+2 min.

5.

Minimum time period for a batch release:

1.70E+2 min.

2.65E+2 min.

6.

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

3 3

4.87E+6 ft / min.

2.47E+6 ft / min.

. 70000509'/24

l1 TMI - Unit I 5.

Batch Releases (cont.)

B.

Gaseous 1st Qtr.

2nd Qtr.

1.

Number of batch releases:

35 17 2.

Total time period for batch releases:

9.85E+4 min.

1.36E+5 min.

3.

Mawf== time period for a batch release:

3.56E+4 min.

6.05E+4 min.

4.

Average time period for batch release:

2.82E+3 min.

8.00E+3 min.

5.

Minimum time period for a batch release:

6.00E+1 min.

5.40E+2 min.

l 6.

Abnormal Releases A.

Liquid 1.

Number of releases:

None None 2.

Total activity released:

B.

Gaseous 1.

Number of releases:

1 None 2.

Total activity released:

1.27 Ci Noble Gas (Jan., 79) as e

4 e.

we

._~. _

TMI - Unit 1 f

TABLE 1A EFFLUENT AND tJASTE DISPOSAL SEMIANNUAL REPORT - 1979 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT First Second EST. TOTAL QUARTER QUARTER ERROR, %

7 A.

Fission & activation gases j

1. Total release Ci 2.14 E+3
9. 80.E+1 2.5E+1
2. Average release rate for period UCi/sec.

2.71E+2

. t c e;r o

3. Percent of Tech Spec limit 2.04E+1 8.63E-1 B.

Iodines

1. Total Iodine-131 Ci 3.82E-3 7.02E-3 2.5E+1
2. Average release rate for period uCi/sec.

4.85E-4 8.91E-4

3. Percent of Tech Spec limit 8.08E+0
1. 49 E+1 C.

Particulates

1. Particulates with half-lives

> 8 navs Ci 8.21E-4 1.54E-4 2.5E+1

2. Average release rate for period pC1/sec.

1.04E-4 1.95E-5

3. Percent of Tech Spec limit 3.0E-2 5.51E-2
4. Gross alpha radioactivity Ci 1.59E-7

<MDA D.

Tritium

1. Total release C1 2.70E+1 1.52E+1 2.5E+1
2. Average release rate for period UCi/sec.

Y.43E+0 1.93E O

3. Percent of Tech Spec limit NA NA

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l 1 '

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+

TMI - Unit 1 TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1979 GASEOUS EFFLUENTS-GR01mD LEVEL RELEASE Continuous Mode Batch Mode Nuclides UNII First Second First Second Released I

QUARTER QUARTER QUARTER QUARTER j

1.

Fission gases (1)

(2) ___.

kryp ton-85 Ci

< MDA

< MDA

<MDA 1.13E-1 krypton-85m Ci

< MDA

< MDA 8.87E-2

< MDA krypton-87 Ci e MDA

< MDA

< MDA

< MDA krypton-88 Ci

< MDA

< MDA 1.85E-1

< MDA xenon-133 C1 1.60E+1 7.08E+1 2.07E+3 l2.69E+1 xenon-135 C1

< MDA

< MDA 2.57 N 3.35E-5 xenon-135m Ci

< MDA

< MDA

< MDA

< MDA xenon-138 Ci

< MDA

< MDA

< MDA

< MDA Others (specify) II 8 ke Ci

< MDA

< MDA 7.00E O 4.28E-2 I

  • I ""

Ci

< MDA

< MDA 2.42E O 9.70E-2 IIAr Ci

< MDA

< MDA 1.82E+1

< MDA Ci Ci

-Unidentified Ci '

< MDA

< MDA NA ~

NA Total for period Ci 1.60E+1 7.08E+1 2.12E+3 2,72E+1 N

~

~

~

2.

Iodines

~ 1odine-131 Ci 8.86E-4 5.85E-3

2. 9 3 E-3 1.17E-3 iodine-133

~

Ci

<MDA

< MDA

< MDA 4.07E-6 iodine-135 Ci

<MDA

< MDA

< MDA

< MDA Total for oeriod Ci 8.86E-4 5.85E-3 2.93E-3 1.17E-3 3

~

. i m

- m w-a w

-gw--

r.

m-7

+r'e-e-g

.-**--ey--

e

~

TMI - Unit 1 TABLE IB (cont.)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1979 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES

~

Continuous Mode Batch Mode Nuclides UNIT First Second First Second

~

Released I

QUARTER QUARTER QUARTER QUARTER j

3 Particulates '(3) strontium-89 Ci

<MDA 4.65E-5

<MDA 1.49E-6

- strontium-90 Ci

'umA 1.64E-6

<MDA 1.32E-7 cesium-134 Ci

<MDA

<MDA

<MDA

<MDA cesium-137 C1 1.44E-4 7.47E-5 1.03E-4 1.83E-5 barium-lanthanum-140 Ci

<MDA

'<MDA

<MDA

<MDA Others (specify) 103 Ru Ci.

5.45E-5

<MDA

<MDA

<MDA so Co Ci

<MDA-

<MDA 2.75E-5 8.04E-6 ssCo Ci 1.27E-4 2.18E-6 3.47E-4 8.28E-7 ss Nb Ci

. <MDA

<MDA 1.79E-5

<MDA v?t M etrittMi 6,

~

same esw m

h 6_m 6

M

. umes emei Se e

M h

w S

I I

TMI - Unit 1 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1979 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES UNIT First Second EST. TOTAL I

QUARTER QUARTER ERROR %

A.

Fission and activation products

(.'

1. Total releases (not including tritium, gases, aloha)

C1 3.64E-2 3.14E-1 2.5E+1

4. Average diluted concentration durine oeriod pC1/ml 1.69E-9 1.32E-8
3. Percent of applicable limit 1.46E+0 1.26E+1 B.

Tritium

1. Total release Ci 2.54E+1 1.53E-1 2.5E+1
2. Average diAutea concentration durine oeriod UCi/mi 1.30E-6 6.55E-7
3. Percent of applicabla limit 4.33E-2 2.18E-2 C.

Dissolved and entrai aed gases

1. Total release C1 1.00E-2 1.21E-2 2.5E+1
2. Average diluted conceatration durine oeriod UCi/ml 5.13E-10 5.17E-10
3. Percent of applicable limit NA NA D.

Cross alpha radioactivity

1. Total release Ci

<MDA

<MDA 2.5E+1 E. Volume or waste released (prior to dilution) liters 1.11E+6 2.84E+7 1.0E+1 F. Volume of dilution water used dortne neriod

liters, 2.15E+10 2.35E+10 1.0E+1 e

I

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TMI - Unie 1 TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1979 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides UNIT First Second First (3)

Second Released I

QUARTER QUARTER QUARTER QUARTER 4

strontium-89 Ci

<MDA

<MDA 3.30E-4 7.71E-2 i

strontium-90 Ci

<MDA

<MDA 3.1E-5 2.43E-3 cesium-134 Ci

<MDA

<MDA 3.21E-3 6.31E-3 cesium-137 Ci

<MDA

<MDA 4.55E-3 1.71E-2 iodine-131 c4

<MDA

<MDA 2.54E-4 1.34E-1 cobalt-58 Ci

<MDA

<MDA 2.13E-2 3.62E-2 cob &lt-60 C1

<MDA

<MDA 1.19E-3

9. 09 E-3 iron-59 Ci

<MDA

<MDA 1.33E-4 diDA zinc-65 Ci

-MDA

-MDA 3.94E-4

<MDA manacanese-54 Ci

<MDA

<MDA 3.36E-4 6.49E-4 chromium-51 l

Ci

<MDA

<MDA 1.65E-3 5.14E-3

~

zirconium-niobium-95 Ci

<MDA

<MDA 1.43E-3 1.57E-3 molybdenum-99 Ci

<MDA

<MDA 8.56E-6

<MDA I

technetium-99m Ci

<MDA

<MDA

<MDA

<MDA barium-lanthanum-140 Ci

<MDA

<MDA 4.23E-4 2.24E-2 cerium-141 Ci

<MDA

<MDA

<MDA 3.15E-5 Other (specifv) 97Zr Ci

<MDA

<MDA 8.88E-5

<MDA 103 Ru Ci

<MDA

<MDA 7.37E-5 otDA II'Ac Ci

<MDA

<MDA 8.32E-4 8.99E-5 122<;h Ci

<MDA

<MDA 5.78E-5

<MDA

~ 12"Sb Ci

<MDA

<MDA 3.77E-5

<MDA

~

188 Cs Ci dIDA diDA 1.22E-5 1.57E-3

)

Unidentified Ci Total for period Ci

<MDA

<MDA 3.64E-2 3.14E-1 j

~

xenon-133 Ci d!DA 41DA 1.00E-2 1.21E-2 i

xenon-135 C1 otDA d!DA d1DA diDA 1

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..e 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 I & II f,*{nh E

T TAL

a. Spent resins,111te. sludges,

m' 6.80E+0 evaporator bottoms, etc.

Ci 1.64E-2 2.5E+1

)

b. Dry compressible waste, contaminated m

1.28E+2 3

eq uipmen t, etc.

c4 5.n2r+0 2.5E+1

c. Irradiated components, control 3

m rod s, etc.

Ci aa

d. Other (describe)

C1

2. Estimate. of major nuclide composition (bv type of waste) a.6b.

cq 19%

'*Co 19%

=

    • Co y

19/.

3*Mn toy

'*'Cs y

1g,3 y

'"'I y

3y

'Sr 0.53%

~Xe 0.32%

    • 3 Ve 0.27%

'**Ba 0.25%

    1. Mo jg 0,jsg ICS 0.126%

1"' T n 0.06%

    • Mr 0.02%

'7 0e T

0.019%

1321 0.00617

.222 Sb 1'

=

0.0017

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  1. H 1.

i o onos4

3. Solid Waste Disposition Number or Shipments.

Mode of Transportation Destination 12 Sole use Truck Barnwell, S. C.

4 Sole use Truck Lynchburg, VA.

3 Soln use truck Richland, WA.

B.

Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination None i

There were no Unit 11 solid waste or irradiated ruel shipments f rom March 2/,

i 9 / ')

tnru aune du, 19sv for burial or disposal.

+

TMI-UNIT I Note (1)- As a result of the Unit II accident on March 28, 1979, noble gases and radiciodines were released from the Unit I station vent because of the commonality of the FHB. Since the radioiodines originated from Unit II, they are treated as Unit II releases.The activity of radiciodines were determined from Ge(Li) analysis of charcoals taken from RMA-8. The releases were considered to be continuous from March 28, 1979 thru April 30, 1979.

Note (2)- The single April reactor purge particulate and iodine samples'were lost, as a result of the Unit II accident. The calculated April purge releases 60Co (8.04E-6), 58Co (5.87E-7), 131I (9.33E-5) and 133I (4.07E-6) are Curies;. assuming a 90% filter efficiency for particulates and radiciodines.

Note-(3)- The liquid samples that had been collected for the March, 1979 composite 89Sr and 90Sr were in the Unit I and Unit II Health Physics Lab analysis of areas on March 28, 1979. As a result of the accident on March 28, 1979, bothsamgSrandles became highly contaminated and were discarded. The best estimate of the 8 90 Sr released during March 1979 was to weight the concentrations in the preceeding two months with the actual volume discharged thru the liquid rad system for January and February, 1979, and multiplied the weighted average by the volume released in March, 1979.

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