ML20154J114

Effluent & Waste Disposal Semiannual Rept Jan-Jun 1986 Supplemental Info

ML20154J114
Person / Time
Site:	Three Mile Island
Issue date:	06/30/1986
From:	Rogan R GENERAL PUBLIC UTILITIES CORP.
To:
References
4410-88-0022-01, 4410-88-22-1, NUDOCS 8805260176
Download: ML20154J114 (12)

Text

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' - EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT l

- January 1, 1986 to June 30, 1986

!* SUPPLEMENTAL INFORMATION OPR-73-320 FACILITY TMI Unit 2 (includina EPICOR_II) LICENSEE

1. Regulatory Limits

a. Fission and activation gases:

b. Iodines: Environmental Tech Specs,

c. Particulates, half-lives >8 days:

d. Liquid effluents: Article 2.3

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

a. Fission and activation gases:

b. Iodines: 10 CFR, Part 20, Appendix 8

c. Particulates, 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. 0.253 MeV(Kr-85)

4. Measurements and Approximations of Total Radioactivity Provide the methods used to measure or approximate the total radioactivity in ef fluents 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(Li) Spectrometry, Gas Flow Proportional Counting

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.

A. Liquid 1986 1986 1st Ouarter 2nd Quarter

1. Number of batch releases: 35 31

2. Total time period for batch release: N/A N/A

3. 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. Average stream flow during periods of relesse of effluent into flowing stream: N/A N/A See Note (1) on Page 5 of this report N/A = Not Applicable

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5. Batch Releases (cont'd) 1986 1986

8. Gaseous 2nd Quarter 1st Ouarter 0 0

1. Number of batch releases: N/A

2. Total time period for batch releases: N/A

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

4. Average time period for batch release: N/A N/A S. Minimum time period for a batch release: N/A N/A

6. Abnormal Releases A. Liquid None None

1. Number of releases: N/A

2. Total activity released: N/A B. Gaseous None None

1. Number of releases:

2. Total activity released: N/A N/A 1

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• TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 1986 1986 UNIT ist 2nd EST. TOTAL II QUARTER QUARTER ERROR, %

A. Fission & activation gases

<LLD <LLO 60%

1. Total release C1 Average release rate for period pCi/sec. N/A N/A Tech Spec Limit =

2. 7.20E3 pCi/sec

3. Percent of Tech Spec limit  % N/A N/A for Kr-85 B. Iodines

1. Total Iodine-131 (Note 1) C1 1.11E-6 3.94E-6 1 60%

Average release rate for period pCi/sec. 1.43E-7 5.01E-7 Tech Spec Limit =

2. 2.40E-2 pCi/sec

3. Percent of Tech Spec limit  % 5.96E-4 2.09E-3 C. Particulates

1. Particulates with half-lives Ci 8.54E-6 3.02E-6 1 60%

>8 days

2. Average release rate for period pCi/sec. 1.10E-6 3.84E-7 Tech Spec Limit =

2.40E-2 pC1/sec

3. Percent of Tech Spec limit  % 4,58E-3 1.60E-3

4. Gross alpha radioactivity Ci 5.77E-8 2.85E-8

0. Tritium l

1. Total release Ci 6.00E0 5.70E0 1 60%

2. Average release rate for period pCi/sec. 7.72E-1 7.25E-1 Tech Spec Limit =

4.80E3 pCi/sec

3. Percent of Tech Spec limit  % 1.61E-2 1.51E-2 for H-3 Note (1) TMI Unit 1 origin i

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• ' TABLE 18 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT j GASEOUS EFFLUENTS-GROUND LEVEL RELEASE i Continuous Mode Batch Mode )

1986 1986 l 1986 1986 l

Nuclides UNIT 1st 2nd 1st 2nd '

II QUARTER QUARTER QUARTER QUARTER Released

1. Fission gases Ci <LLO <LLO N/A N/A l krypton-85 N/A l Ci <LLO _ <ll0 N/A krypton-85m Ci < LO <LLO N/A N/A krypton-87 -

Ci < . '. 0 <LLO N/A N/A j krypton-88 Ci <LLO <LLO N/A N/A xenon-133 Ci <LLD <LLD N/A N/A j xenon-135 Ci <LLO <LLO N/A N/A f xenon-135m Ci <LLO <LLO N/A N/A xenon-138 others (specify) Ci <LLO <LLD N/A N/A Ci Unidentified Ci <LLO <LLO N/A N/A {

Total for period Ci N/A N/A N/A N/A 1

2. Iodines iodine-131 (Note 1) Ci 1.11E-6 3.94E-6 N/A N/A _ l iodine-133 Ci <LLD <LLD__ N/A N/A iodine-135 Ci <LLO <LLO N/A N/A Total for period C1 1.11E-6 3.94E-6 N/A N/A

3. Particulates strontium-89 Ci <LLO <LLD N/A N/A strontium-90 Ci <LLO <LLD N/A N/A c esium-134 Ci <LLO <LLO N/A N/A l c esium-137 Ci 2.46E-6 7.24E-7 N/A N/A barium-lanthanum-140 Ci <_L L O <LLD N/A N/A I

others (specify) Ci Ci Unidentified C1 4.97E-6 2.29E-6 N/A N/A Note (1) TML Unit-1 origin

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TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Tech Spec Limit = 10CFR20, Appendix B. Table II, Column 2 1986 1986 UNIT lst 2nd EST. TOTAL QUARTER ERROR, %

II QUARTER A. Fission & activation products Total releases (not including C1 3.53E-5 3.37E-5. i 60%

1.

tritium, gases, alpha) pCi/ml 2. 9 2 E-12 3.18 E-12 Based on 2E-5

2. Average release rate for period Ci/ml (Cs-137 Percent of applicable limit  % 1.46E-5 1.59E-5 3.

B. Tritium Ci 5.71E-4 3.17E-4 1 60%

1. Total release Average diluted concentration pCi/ml 4.72E-11 2.99E-11 Based on 3E-3 2.

during period Ci/ml (H-3)

Percent of applicable limit  % 1.57E-6 9.97E-7 3.

C. Dissolved and entrained gases Ci <LLO <LLO 1 60%

1. Total release Average diluted concentration pCi/ml N/A N/A 2.

during period

, 3. Percent of applicable limit  % N/A __N/A

0. Gross alpha radioactivity

1. Total release Ci Note 1 Note 1 60%

E. Volume of waste released (prior to dilution) liters 1.26E5 8.99E4 1 25%

F. Volume of dilution water used during period liters 1.21E10 1.06E10 1 10%

Includes only those releases mentioned in Note (1) which were found to contain radioisotope concentration > LLD.

Note (1) There were no liquid releases from the radwaste system during the first half of 1987 since this system is flanged off from the discharge lines. However, low concentrations of radionuclides have been occasionally found in the industrial waste stream and are appropriately included in Item A2.

Note (2) Refer to Table 5 for Typical LLD values.

Note (3) The values reported include Sr-90 activity and any activity no specifically identified. Thus, the reported Sr-90 value represents a conservative estimate (i.e. overestimate) and contains activity from other beta-gamma emitters which were not positively identified during conduct of analytical procedures.

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TABLE 2B l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS Continuous Mode Batch Mode 1986 1986 1986 1986 UNIT 1st 2nd 1st 2nd Nuclides QUARTER QUARTER QUARTER QUARTER Released II See See Strcntium-89 Ci Note (2) Note (2) <LLO <L L O ,__

2.40E-5 2.21E-5 Strontium-90 C1 Ci <tLD <LLO cesium-134 1.13E-5 1.16E-5 ,

cesium-137 C1 Ci <LLO <LLO iodine-131

<LLO <LLO cobalt-58 Ci _

Ci <LLD <LLO cobalt-60 Ci <LLO <LLO f iron-59 Ci <LLO <LLO zinc-65 managanese-54 Ci <LLO <LLO Ci <LLO <LLO chromium-51 l zirconium-niobium-95 Ci <LLO <LLO molybdenum-99 Ci <LLO <LLO technetium-99 Ci <LLO <LLO barium-lanthanum-140 Ci <LLO <LLO ce rium-141 Ci <ll0 <LLO i others (specify) C1 i

Ci Unidentified Ci <LLO <LLO Total for period C1 3.53E-5 3.37E-5 xenon-133 Ci <LLO <LLO xenon-135 Ci <LLO _<LLO

Attachment Page 1 of 2 TABLE 4 TYPICAL LIOUID EFFLUENT LLD (Lower Limit of Detection) VALUES ASSUMPTIONS: Sample volume = 1 liter = 1000 cc Sample counting time = 1000 see Sample counted with a 25% Ge(Li) for Gamma Emitters ISOTOPE pCi/cc LLD NOTES Gross Alpha a 4E-9 Counted with proportional counter Gross Beta $ 7E-8 Counted with proportional counter Tritium 4-3 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 3E-7 Chromium-51 Cr-151 3E-6 Manganese-54 Mn-54 4E-7 Cobalt-58 Co-58 4 E-7 Iron-59 Fe-59 9E-7 Cobalt-60 Co-60 6E-7 Zinc-65 2n-65 1E-6 Zirconium-95 Zr-95 7E-7 Niobium-95 Hb-95 4E-7 Molybdenum-99 Mo-99 3E-7 Technetium-99m Tc-99m 3E-7 Silve r-110m Ag-110m 6E-7 Antimony-125 5b-125 3E-7 Cesium-134 Cs-134 SE-7 Cesium-136 Cs-136 4E-7 Cesium-137 Cs-137 SE-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 Iodine-131 1-131 3E-7 lodine-133 1-133 4E-7 Phosphorus-32 p-32 1E-6 These LLD values for liquid Iron-55 Fe-55 SE-B sample analyses of gross alpha, Strontium-89 Sr-89 SE-8 P-32, Fe-55, Sr-89, and Sr-90 Strontium-90 Sr-90 SE-8 are the same as Unit 1 which are Gross Alpha a 1E-7 offsite vendor LLD values.

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Attachment Page 2 of 2 TA8LE 5 ,

TYPICAL GASEOUS EFFLUENT LLD (lower limit of Detection) VALUES ASSUMPTIONS: Sample volume (Marinelli) 1640cc Sample volume (Particulate & Charcoal Filters) 5.7E8cc Sampling Rate 2 cfm or 5.66E4cc/ min Sampling Time 1 week or 1E4 min Sample volume (tritium bubbled thru water) 7.56E5cc Sampling Rate 75cc/ min Sampling Time 1E4 min Sample Counting Time: a & H-3 =20 min; $ =10 min; 7 =1000sec Sample Counters: y emitters 25% Ge(Li) a or S Proportional Counter H-3 Liquid Scintillation Counter ISOTOPE Ci/cc LLO NOTES Gross Alpha a 1 E-15 Particulate Filter Paper Gross 8 eta # 1 E-14 Tritium H-3 1 E-10 Air bubbled thru water by a fritted disc or Fisher Hilligan gas washer Krypton-85 Kr-85 SE-6 Marinelli Krypton-85m Kr-85m 2E-8 Krypton-87 Kr-87 6E-8 Krypton-88 Kr-88 SE-8 Xenon-133 Xe-133 4E-8 l Xenon-133m Xe-133m 1 E-7 l Xenon-135 Xe-135 2E-8 l Xenon-135m Xe-135m 3E-7 Xenon-138 Xe-138 3E-7 1

Iodine-131 1-131 2E-8 l Iodine-133 1-133 3E-8 Iodine-135 1-135 2E-7 ' l Iodine-131 1-131 3 E-14 Charcoal Filter Iodine-133 1-133 4 E-14 Iodine-135 I-135 3E-13 Manganese-54 Mn-54 3E-14 Particulate filter Paper Iron-59 Fe-59 8E-14 Cobalt-58 Co-58 3 E-14 Cobalt-60 Co-60 SE-14 Zinc-65 Zn-65 9 E-14 Strontium-89 Sr-89 2E-14 Strontium-90 Sr-90 2 E-14 Molybdenum-99 Mo-99 2 E-14 Ruthenium-103 Ru-103 2 E-14 Silve r-110m Ag-110m 3E-14 Cesium-134 Cs-134 4 E-14 Cesium-137 Cs-137 3E-14 "

Cerium-141 Ce-141 3E-14 Cerium-144 Ce-144 C E-14

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TA31.E 3A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS i

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• A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)

1. Type of waste 6 month EST. TOTAL UNIT oeriod ,__

ERROR %

a. Spent resins , tilter slud ges , m' 19.9m3 5%

evarerator botto=s etc. Ci 10.39 Ci;

b. Dry co=pressible vaste, contar.inated m3 N/A N/A ecu1=nent, etc. e4

c. Irra:1ateo cc ponents, control m 3 rods, etc. Ci N/A N/A

d. Other (describe) [g* 1 N/A N/A

2. Esti= ate of major nuclide conoosition (bv type of vaste)

a. Sbl25 42.92%

Pm147 18.40t Sr90 16.05r Tel25m 9.87 %

b. N/A y Y

c. N/A I t

d. N/A g l l

3. Solid Waste Disposition Nurber of Shipnents Mode of Transportation Destination

• 3 shirnents Tractor-Cask (NuPac 14 /190M) Hanford -Richinnd.VA.

1 Shipment Tractor-Cask (HN-100, series 2) Hanford-Richland,WA.

• 1 Shipment Tractor-Flatbed Hanford-Richland,WA.

B. Irradiated Fuel Ship =er.cs (Disposition)

Nu=ber of Ship =ents Mode of Transportation Destination N/A

• This material was shipped as follows: one(l) 30 ft 3 sted merj

~ 3 three(3) steel finer's 161 f t3 each jand one(l) 170 Ft steel liner

. 8-

d Unit II LSA (DRUMS 6 BOXES)

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

1. Type of vaste UNIT 6 conth EST. TOTAL eeriod ERROR %

a. 5 pent resirs, filter sludges , m* N/A N/A evaeorater botte=s, etc. Ci

b. Dry co=pressible waste, contaminated m3 141 3 ecuipment, etc. 1.02C1. 5%

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c. Irra:1atec cc=ponents, control m 3 N/A N/A rod s , etc. Ci ma s

d. Other (describe) Ci N/A N/A l l

2. Esti= ate of =ajor nuclide )

coneosition (bv type of vaste)

a. N/A  %

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b. Csl37 83.883 br90 10.95; csl34 3.037%

Poi */ ./913%

Cn60 _ ?QQ' %

c. N/A t t

% l

d. N/A g e

3. Solid Waste Disposition Nurber of Shi =ents Mode of Transportation Destinos n 0 3 Shierents Iractor-Glosed Van Hanford-R.' aland,WA.

o 2 Shipments O Tractor-Flatbed Hanford-Richland.WA.

1 Shipment Tractor-Shielded Van Hanford.Richland.WA.

B. Irradiated Fuel Ship =ents (Disposition)

Number of Shio=ents Mod'e of Transportation Destination N/A

• Thiswastewasshippedin299steeldrums@7.5ftjeach.

28 steel boxes @ 98 ft each, aes

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Unit 2 H.I.C. . _ _ _,

TABLE 3A '

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

1. Type of waste UNIT ET TOTAL g,mengho

a. Spent resins, filter slucges, m' N/A N/A evaporater bottees. etc. Ci

b. Dry co=pressibic waste, conta=1nated m3 1.416m>

5%

ee uip r.en t , etc. e4 .874 Ci. I

c. Irrastatec co:ponents, control m 3 reist_ ate. Ci N/A N/A aa

d. Other (describe) Ci N/A N/A l

2. Estimate of major nuclide cocoosition (by type of vaste)

a. N/A  %

t t

b. Cs137 56.92 y Sr90 38.33 t '

Csl34 1.945 % -

Sb125 .396 %

Pn147 .178 %

c. y t

% l 1

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3. Solid Waste Disposition 1 N'J:ber of Shipments Mode of Transportation Ecstination i

e 1 Ship =ent l Tractor-Cask (NuPac 14D-2.0) Hanford-Richland,WA.

B. Irradiated Fuel Shipments (Disposition)

Number of Ship ents Mode of Transportation Destination N/A

• Shipped in one(l) 50 cubic foot High Integrity Container

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GPU Nuclear Corporation QQlgg7 Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

(717) 948-8461 May 16, 1988 4410-88-0022/0145P Atmospheric Sciences Division Attn: Ms. J. Tichler Brookhaven National Laboratory Upton, NY 11973

SUBJECT:

THI-2 Semi-Annual Effluent Report In response to your March 30, 1988, request, attached is a copy of the data on We are currently reviewing ef fluents from TMI-2 for the first half of 1986.

the data provided for the second half of 1986. Following receipt of the complete annual report from you, we shall expeditiously provide our comments.

Sincerely,

/s/ J. J. Byrne for R. E. Rogan Director, Licensing and Nuclear Safety EDS/ emf Attachment cc: Senior Resident Inspector, TMI - R. J. Conte Regional Administrator, Region 1 - W. T. Russell Director, Plant Directorate IV - J. F. Stolz l Systems Engineer, TMI Site - L. H. Thonus I

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l GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation i