ML20153D743

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Effluent & Waste Disposal Semiannual Rept,Jan-June 1988
ML20153D743
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 06/30/1988
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20153D725 List:
References
4410-88-L-0142, 4410-88-L-142, NUDOCS 8809060026
Download: ML20153D743 (11)
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Text

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ATTACHMENT 5 4410-88-L-0142 11 Pages r? FLUENT AND WASTE DISPOSAL SEMI !.NNUAL REPORT '

January 1, 1988 to June 30, 1938 SUPPLEMENTAL INFORMATION FACILITY TMr Unit 2 (including Epicor II) LICENSEE 'DPR-73-320

1. Regulatory Limits
a. Fission and activation gases
b. Iodines s t
c. Particulates, half-lives > 8 days: ""
d. Liquid effluents: Ar i e23 2.

Maximum Permissible Concentrations Provide the MPCs used in determining allowable release rates or concer.trations. i a, Fission and activation gases:

b. Iodiness  ;
c. Particulates, half-lives 8 days: FR, Part 20. Appendix B I
d. Liquid effluents:

! 3. Average Energy Provide the avera3a energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable ,L 4.

Measurements and Approximations of Total Radioactivity s

Provide the methods used to ceasure or approximate the total radioactivity in effluents '

and the cathods used to determine radionuclide composition.

a. Fission and activation gases:
b. Iodines: Ge (L1) Spectrometry, Liquid Scintillation
c. Particulates: Ge (Li) Spectrometry
d. Liquid effluents: Ge (Li) Spectrometry, Gas Flow Froportional Ge (Li) Spectrometry, Liquid Scintillation
5. Batch Releases i

Provide the following in liquid and gaseous information effluents. relating to batch releases of radioactive =aterials l A. Liquid l J 1988 1988 1.

1st Quarter 2nd Quarter '

Number of batch releases: 20

, 2. Total time period for batch release: 51

3. N/A N/A Maximum time period for a batch release (

4 N/A N/A

5. Average time period for batch releases: N/A l

Mini =um time period for a batch release: N/A

6. N/A N/A Average stream flow during periods of '

release of effluent into flowing stream N/A N/A t

I N/A = Not applicable ,

I 8809060026 000029

PDR ADOCK OJ'OOO3 0 R 3

, l l

5. Batch Releases (cone.)

B. Caseous 1988 1988 1st Quarter 2nd Quarter

1. Number of batch releases: 0 0
2. Total time period for batch releases: N/A
3. N/A Maximum time period for a batch release: N/A N/A
4. Average time period for batch release: N/A N/A
5. Minimum time period for a batch release: N/A N/A
6. Abnormal Releases A. Liq t./. 3
1. Number of releases: None None
2. Total activity released: N/A N/A B. Caseous
1. Number of releases: None None
2. Total activity released: N/A N/A l

1 e

1 b

t

TABLE LA EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT CASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT 1st 2nd EST. TOTAL QUARTER QUARTER ERROR, %

A. Fission & activation gases

__1. Total release Ci <LL D <LLO 1 60%

2. Average release rate for period uCi/sec. N/A N/A Tech. Spec. Limit =
3. Percent of Tech Spec limit  % 7.20 E+3 uCi/ rec N/A N/A for Kr-85 B. Iodines .
1. Total Iodine-131 Ci

?

<LLD <LLO i 60% i

2. Average release rate for period uCi/sec. N/A N/A Tech. Spec. Limit = I
3. Percent of Tech Spec limi:  % N/A N/A
2. sec C. Particulates
1. ' articulates with half-lives 5 e navs C1 1.00E-5 4.11E-6 +

_ gnv

2. Average release rate for period UCi/Jec. 1.27E-6 5.23E-7 Tech. Spec. Limit =
3. Percent of Tech Spec limit  % 5.29E-3 2.18E-3 2.40 E-2 uCi/sec l
4. Cross alpha radioactivity Ci <llD 1.39E-7 D. Tritium

.j 1. Total release ci 2.61E0 1.89E0 1 60% l

2. Average release rate for period UCi/sec. 3.32E-1 2.41E-1 Tech. Spec. Limit = l
3. Percent of Tech Spec limit t 6.92E-3 5.02E-3 4.80E+3 uCi/sec for H-3

}

l i

i i

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. .I TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIAh3UAL REPORT "utSEOUS EFFLUENTS-GROUND LEVEL RELEASE Continuous Mode Batch Mode Nuclides UNIT 1988 1900 Released QUAkikR QUAkhR 190f If8 QUAfER QUART R

1. Fission gases krypton-85 Ci <LLD <LLD <LLD <LLD krypton-85m Ci <lLD <lLD <llD <lLD krypton-87 Ci <f i n <i t n <LLD <LLD kryp ton-88 Ci <LLD <LLD <LLD <LLD xenon-133 Ci <i LD <tLD <LLD <LLD xenon-135 Ci <LLD <LLD <tLD <LLD xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci

<LLQ <llD <llD <LLD others (specify) Ci <LLD <LLD <LLD <LLD ci C1 C1 Ci Unidentified Ci <LLD <LLD <LLD <LLD Total for period Ci N/A N/A N/A N/A

2. Iodines

--< a todine-131 Ci <tLD <ll D N/A N/A todine-133 <LLD

_ Ci <LLD N/A N/A iodine-135 Ci <lLD <l I D N/A N/A Total for , rt,i ci N/A N/A N/A N/A j

-4

^ '

  • 4 TABLE IB (cont.)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released UNIT 1 66 gp 1ygg INnb i

QUARb QUARTER QUARTER QUARTER

3. Particulates strontium-89 Ci '

<LLD <LLD N/A strontium-90 N/A Ci <LLO <LLD cesium-134 N/A N/A Ci <tLD <LLD N/A costum-137 N/A

_ _ _ _ ci <tI D <LLD N/A barite-lan thanum-140 Ci _

N/A

<lLD <llD N/A Others (specify) __

N/A (Sidentified 1.00E-5 4.11E-6 N/A N/A i

l -s-

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RETTASES UNIT hff QUARTER Ih QUARTER EST. TOTAL ERROR %

A. Fission and activation products

1. Total releases (not including tritium, nases, alpha) C1
2. Average diluted concentration 3.15E-4 4.66E-4 1 60%

durine ceriod '

uCi/mi B65ed on 2E-5 2.37E-11 3.26E-11

3. Percent of applicable limit  % uC1/ml (Cs-137) 1.19E-4 1.63E-4 B. Tritium
1. Total release C1
2. Average diluted concentration 1.43E-4 4.12 E- 3 1 60%

during period UCi/mi 1.08E-11 2.87E-10

3. Percent of applicable limit  % j 0fg,)3 3.60E-7 9.57E-6 C. Dissolved and entrained gases
1. Total rq1 ease Ci
4. Average diluted concentration N/A N/A + 60%

durine eeriod UCi/mi N/A N/A

3. Percent of applicable limit  %

Pl/A N/A D. Cross alpha radioactivity

1. Total release Ci Note (1) Note (1) i E.

Volume of waste releasea *

(prior to dilution) liters 4.46E+4 1.80E+5 1 25% i F. Volume of dilution water used dortnc wrted liters

  • 1. 33E +10 1.43E+10 10%

loc 19 des only concentration LLD. those releases mentioned in Note (1) which were found to contain radioisotope Note ())

this system is flanged off from the discharge lines.There were no liquid release However, low concentration of radionuclides app have t.een cpriately included occasionally in Item A2 found in the industrial waste stream and are Note (2) Refer to Table 5 for Typical LLD values.

Note (3)

The values reported include :,r.90 activity and any activity not srecifically identified Thus, the reported Sr.70 v 'ue represents a conservative estimate (i.e. overestimate) and .

conduct of analytical procedures.contains activity frem oth r bete.gew emitters which were not p

TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides 1988 1988 1968 L' NIT lst 1966 Released 2nd 1st 2nd QUARTER QUARTER QUARTER QUARTER strontium-89 Ci  !?ye gte 2 ge,Ngte2 N

<RD CD strontium-90 Note 3 Pace 6 C1 eesium-134 1.76E 4 2,40E-4 C1 cesium-137 2.73E-6 9.17 E- 7 C1 fodig?-131 1 16F a  ? ?;F 4 c4 7.~

Arn Ain cobalt-58 Ci cobalt-60 <llD <t L D C1 iron-59 Ci

<t L D <L L D zine-65 Ci

<L L D <t L D

<t i n <t L D manaeanese-54 _ Ci chronium-51 Ci

<t L D <LLD

<LLD <llD zirconium-niobium-95 Ci molybdenum _99 <LLD <tLD Ci technetium-99m Ci <LLD <lLD

<t i n <llD barium-lanthanum-140 Ci cerium-141 <tLD <LLD

_ Ci

_Q.th q,r_ ( s p e c i f y) <tLD <lLD C1 Ci

__ C1 71 Ci

=

Cf I Unidentified C1 Tctal for period __

<LLD <LLD

,_ Qi j_

7.14r.a a.66E-4 xenon-13; a----

I 1

Ci

<enon- 13 5 i

<LLD < LLD

- Cf

~~~

I 'l l 0 <lLD f

f-1

TA3LE 3A EFFLL'ENT 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 0 E TOTAL 3,"0Djh
a. 5 pent resins, filter slucges, m* 87.16 m3 evaporator bottoms, etc. Ci 2524.P rur!cr 5<
b. Dry co=pressible vaste, conta=inated m 3 9mJ eauienent, etc.
c. Irradiateo ce=ponents, control c4 274.L5
11 rurier 9T rod s , e t c . m* ~~~~~ ~~~~~

Ci m3

d. Other (describe) Ci ~---- ~~~~-
2. Estimate of major nuclide composition (bv type of waste) ,
s. CrGO 67.1 %

c c 197 22.6 i P-1L7 5.yC; Pb125 1.00%

Da c roO 83.14i Cs137 1s,2 -

c r i1b . c y ?*

meco . coa; Fm147 [, 272%

c. .! / .a e,

% e

d. M/A  ;
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination rca Attnched
3. Irradiated 1.el Shipments (Disposition)

Number of Shipments Mode of Transportation Destination o chirnnnts Pnil Car - NuPac lebb INEL . P ville. Idaho I

.a.

Effluent & !!aste Disposal Sebi-Annual Rsport, TMI 2 Page 2

3. A) Number of Shipments bbde of Transportation Destination 12 Tractor - Cack (NuPac 14/190M) Hanford - Richland, WA 3 Tractor - Flatbed Hanford - Richland, WA 1 Tractor - Cask (HN-200) Hanford - Richland, WA 8 Tractor - Cack (CNSI 8-120B) Barnwell, SC
3. B) Number of shipments 1.bde of Transportation restination 5 Tractor - Flatbed Hanford - Richland, WA 5 Tractor - Closed Van Hanford - Richland, WA 8 Tractor - Cask (HH-200) Hanford - Richland, WA k Tractor - Cask (NuPac 1k/190M) Hanford - Richland, WA i

s 9

l E

. . l Attachment Page 1 of 2 TABLE 1 TYPICAL L10Uf D FFFLUENT LLD flower Limit of Detection) VALUES ASSUMPTIONS: Sample volume = 1 liter = 1000 cc Sample counting time = 1000 sec Sample counted with a 25% Ge(Li) for Gamma Emitters 11QlgP{, uti/cc LLD ggTQ Gross Alpha a 4E-9 Counted with proportional counter Gross Beta 6 1E-8 Counted with proportional counter Tritium H-3 4E-6 Counted with liquid scintillation counter Krypton-85 Kr-85 1 E-4 Xenon-131m Xe-131m 2E-5 Xenon-133 Xe-133 1E-6 Xenon-135 Xe-135 3 E -7 Chromium-51 C r-151 3E-6 Manganese-54 Mn-54 4E-7 Cobalt-58 Co-58 4E-7 Iron-59 Fe-59 9E-7 Cobalt-60 Co-60 6E-7 Zine-65 2n-65 1E-5 Zirconium-95 Zr-95 7E-7 Niobium-95 Nb-95 4E-7 Molybdenum-99 Mo-99 3E-7 Technetium-99m Tc-99m 3E-7 Silver-110m Ag-110m 6E-7 Antimony-125 Sb-125 9E-7 Ce sium-134 Cs-134 SE-7 Cesium-136 Cs-136 4E-7 Ce s ium-137 C S-137 5E-7 Barium-140 Ba-140 1E-6 Lanthanum-140 La-140 7E-7 Cerium-141 Ce-141 SE-7 '

Cerium-144 Ce-144 3E-6 lodine-131 1-1 31 3E-7 lodine-133 1-133 4E-7 Phosphorus-32 P-32 1E-6 Iron-55 These LLD values for liquid Fe-55 $E-B sample analyses of gross alpha, Strontium *89 Sr-89 $E-8 P-32 Fe-55. Sr-89, and Sr-90 Strontium-90 Sr-90 SE-8 Gross Alpha are the same as Unit I which are 1E-1 offsite vendor LLO values, r l

L

.' o' .

Attachment Page 2 of 2

, TABLE 2 l

TYPICAL GASEOUS EFFLUENT LLO flower Limit of Detection) VALUES A53UMPTIONS: Sample volume (Marinelli) 1640cc Sample volume (Particulate & Charcoal Filters) 5.7E8cc Sampling R*<te 2 cfm or 5.66E4cc/ min Sampling Tirs 1 week or 1E4 min

! ample volutae (tellium bubbled thru watcr) 7.56E5cc Sampling Rett 75cc/ min Samplina t ube 1E4 min Sample Countihg fist:4.& H-3 =?Omin; = levin; =1000sec Sample Countert, celtttrs 25% Ge(Li) rr Proportional Counter H-3 Liquid 3tintillation Counter ISOTOPE Ci/cc y j g Gross Alpha e 1 E-15 Particilate Filter Paper Gross Beta # 1 E-14

Krypton-87 Kr-87 6E-8

  • Krypton-88 Kr-88 SE-8 '

Xenon-133 Xe-133 4E-8 '

Xenon-133m Xe-133m 1E-7 '

Xenon-135 Xe-135 2E-8 '

Xenon-135m Xe-135m 3E-7

  • Xenon-138 Xe-138 3E-7
  • lodine-131 1-1 31 2E-8 '

lodine-133 1-133 3E-8 '

lodine-135 1-135 2E-7

  • lodine-131 1-1 31 3E-14 Charcoal Filter losine-133 1-133 4E-14 "

lodine-135 1-135 3E-13

  • Manganese-54 Mn-54 3E-14 Particulate filter Paper Iron-59 Fe-59 8E-14 '

Cobalt-58 Co-58 3E-14 "

Cobalt-60 Co-60 5E-14

Molybdenum-99 Mo-99 2E-14

  • Ruthenium-103 Ru-103 2E-14

Ce rium-141 C e-141 3E-14

  • Ce rium-144 Ce-144 9E-14 *
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