ML20041F372

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Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1981
ML20041F372
Person / Time
Site: Crane Constellation icon.png
Issue date: 03/03/1982
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20041F356 List:
References
NUDOCS 8203160436
Download: ML20041F372 (35)
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{{#Wiki_filter:.. Attichment 5 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT July 1, 1981 - December 31, 1981 SUPPLEMENTAL INFORMATION FACILITY THI-Unit-II LICENSEE DPR-73-320 i 1. Regulatory Limits I a. Fission and activation gases: Tech Specs, c. cu ates, half-lives > 8 days: f3 g d. Liquid effluents: 2. Maximem Permissible Concentrations Provide the MPCs used in determining allowable release rates or concentrations. a, Fl o a and activation gases: b. Iohnes: O CFR, Part 20, Appendix B c. Particulates, half-lives 8 days: d. Liquid effluents: 3. Average Erergy Provide the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable 0.753 MeV 4. Measurements and Approxin:ations of Total Radioactivity Provide the methods used to measure or approximate the total radioactivity in effluents ard the methods used to determine radionuclide composition. i a. Fission and activation gases: Ge(Li) Spectrometry, Liquid Scintillation i-b. Iodines: Ge(Li) Spectrometry c. Particulates: Ge(Li) 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. A. Liquid 3rd Quarter 4th Quarter 1. Number of batch releases: 2 4 y. 2. Total time period for batch release: N/A N/A 3. Maximum time period for a batch release: 4. Average time period for batch releases: 5. Minimum tine period for a batch release: 6. Average stream flow during periods of I release of effluent into flowing stream: See Note (1) on page of this 8203160436 820303 report. PDR ADOCK 05000320 R PDR -~ f f 5. Batch Releases (cont.) 3rd Quarter 4th Quarter B. Gaseous 1981 1981 1. Number of batch releases: 7 6 2. Total time period for batch releases: 6652 min. 27094 min. 3. Maximum time period for a batch release: 1890 min. 11998 min. 4. Average time period for batch release: 950 min. 4516 min. 5. Minimum time period for a batch release: 2 min. 1540 min. 6. Abnormal Releases A. Liquid 1. Number of releases: None None 2. Total activity released: N/A N/A B. Gaseous None 1. Number of releases: None 2. Total activity released: N/A N/A 9

-D I O p TABLE lA EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT 3rd 4th EST. TOTAL II QUARTER QUARTER ERROR, % 1991 1981 A. Fission & activation gases

1. Total release C1 1.44E7 3.78E1 7,sE]
4. 6EO e

P

2. Average release rr.te for period uCi/sec.

0 of // / ec

3. Percent of Tech Spec limit 3.16E-1 8.26E-2

= 1.92E4 m /sec = 5.76E3 pCi/sec B. Iodines f r KR-85

1. Total Iodine-131 Ci

<LLD <LLD 2.5 El tech spec Limit =

2. Average release rate for period uCi/aec.

N/A N/A 80% of 0.024 uCi/sec

3. Percent of Tech Spec limit N/A N/A

= 1.92E-2 pCi/sec C. Particulates

1. Particulates with half-lives 2.5'El

> 8 Davn ci 4.12E-6 1.34E-5

2. Average release rate for period pCi/sec.

5.18E-7 1.69E-6 Tech Spec Limit = 80% of 0.024 pCL/sec

3. Percent of Tech Spec limit 2.70E-3 8.78E-3

= 1.92E-2 pC1/sec

4. Cross alpha radioactivity Ci 9.43E-9 7.35E-8 D.

Tritium 2.5.El

1. Total release ci 7.45EO 1.74E1
2. Average release rate for period UCi/sec.

9.37E-1 2.19E0 Tech Spec Limit = t 3 80% of 2.4g'4 ni /sec

3. Percent of Tech Spec limit 2.44E-2 5.70E-2 1.92E4 m /sec

= 3.84E3 pCi/sec = for H-3 N/A = Not applicable 6 i e i -^ TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-CROUND LEVEL RELEASE Continuous Mode Batch Mode Nuclides UNIT 3rd 4th 3rd 4th Released II QUARTER QUARTER QUARTER QUARTER 1. Fission gases 1981 1981 1981 1981 krypton-85 Ci 1.29E2 3.01El 1.52El 7.74E0 krypton-85m uCi/cc <LLD <LLD <LLD < LLD krypton-87 uCi/cc <LLD < LLD <LLD < LLD krypton-88 uCi/cc <LLD < LLD <LLD < LLD xenon-133 uCi/cc <LLD <LLD <LLD < LLD xenon-135 uCi/cc <LLD < LLD <LLD < LLD xenon-135m uCi/cc <LLD < LLD <LLD < LLD xenon-138 uCi/cc <LI D < LLD <LLD < LLD Others (specify) C1 Ci C1 Ci Ci Unidentified uCi/cc <LLD < LLD <LLD <LLD Total for period C1 1.29E2 3.01El 1.52El 7.74E0 2. Iodines i iodine-131 n Ci/,-r- <LLn <LLD <tLD <LLD iodine-133 uCi/cc <LLD <LLD <LLD <LLD iodine-135 uCi/cc <LI.D <LLD <tLD <LLD i i Total for period Ci N/A N/A N/A N/A Note: See Table 4 for typical LLD values N/A = Not applicable I '

m C TABLE IB (cont.) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-GROUND LE7EL RELEASES Continuous Mode Batch Mode Nuclides UNIT 3rd 4th 3rd 4th Released II QUARTER QUARTER QUARTER QUARTER 1981 1981 1961 l'J oi 3. Particulates strontium-89 Ci <LLD 4LD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD cesium-134 Ci 1.45E-9 2.08E-8 <LLD <LLD. cesium-137 Ci 4.03E-7 <LLD 1.25E-6 <gtg barium-lanthanum-140 Ci <LLD <LLD <r y n ,LLD Others (specify) Cobalt-60 Ci 6.92E-8 <LLD <LLD <LLU Unidentified ll C1 3.64E-6 1.15E-5 <LLD <LLD Note: See Tabic 4 for typical LLD values l l i I l l

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMLURIUAL REPORT LIQUID EFFLUENTS-SUMMATIO'10F ALL RELEASES Tech Spec Limits = 10CFR20, Appendix B, Table II, Column 2 UNIT 3rd 1981 4th 1981 E'ST. TOTAL II QUARTER QUARTER ERROR % A. Fission and activation products

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

C1 2.52E-6 1.78E-6 2.5 El

2. Average diluted concentration durlna period 4C1/ml 1.53E-Is, 1.26E-13
3. Percent of applicable limit 7.65E-7 4.21E-4 B.

Tritium

1. Total release Ci 4.99E-2 1.9E-4 2.5 El
2. Average diluted concentration 1.35E-ll during period UCi/ml 3.n9E-9
3. Percent of applicable limit 1.01E-4 4.49E-7 C.

Dissolved and entrained gases

1. Total release Ci

<tto <LLD 2.5 El

2. Average diluted concentration durinn period uCi/nl N/A N/A
3. Percent of applicable limit N/A N/A D.

Cross alpha radioactivity

1. Total release Ci

<LLD <LLD 2.5 El E. Volume or waste released (prior to dilution) liters 6.44E4 1.96E4 2.5 El F. Volume of dilution water used durin<t nortod liters 1.65E10-1.41E10 1.0El NOTE: See Table 5 for typical LLD values. Note (1) There were no liquid releases f rom the radwaste system during the second half of 1981 nince this system is still flanged off from the discharge lines. Very low concen-t rations of radionuclides have been found occasionally in the industrial waste stream and sanitary waste. These concent rations in the TMI II industrial waste st ream are not detectable in samples of the effluent st ream f rom TMI prior to final discharge to the Susquehanna 1iver. ~ \\ TABLE 2B EFFLUENT AND WASTE DISPOSAL SaiIANNUAL REPORT LIQUID EFFLUENTS t Continuous Mode Batch Mode Nuclides UNIT 3rd 4th 3rd 4th Released II QUgR QUAL}{ER QUj\\gR Q g ER strontium-89 Ci See Note (2) See Note (2) <LLD <LLD strontium-90 C1 <LLD ELLD cesium-134 Ci <LLD <LLD cesium-137 C1 2.52E-6 <LLD iodine-131 c4 <LLD <LLD cobalt-58 Ci <LLD <LLD cobalt-60 Ci <LLD <LLD iron-59 Ci <LLD 'LLu zinc-65 Ci <LLD <tLD managanese-54 Ci <LLD <LLD chromium-51 Ci <LLD <LLD zirconium-niobium-95 Ci <LLD <LLD molybdenum-99 Ci <LLD <LLD technetium-99m C1 <LLD <LLD barium-lanthanum-140 Ci ' <LLD <LtD cerium-141 Ci <LLD <LLD Other (specifv) Ci Ci ci C1 Ci Ci r4 Unidentified A Ci < LI.D 1.78E-6 Total for period'_ Ci 2.52E-6 1./6t-o xenon-133 Ci <LLD <LLD xenon-135 Ci <l.LD 'LLu i l Note: See Table 5 for typical LLD valves Note (2) There was no continuous release of effluent from Unit Il during the second half of 1981. _ _ _ _ _ _ _ _ _.

TABLE 3A EFTLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS July 1, 1981 to December 31, 1981 Solid waste shipped off-site for burial or disposal (not irrsdiated fuel) A. 0* TOTAL .,[n$h ggjgp

1. Type of waste UNIT II
a. spent resins,111ter sludges, m'

4.42 evaporator bottoms. etc. Ci .06 n' 63.2'S

b. Dry compressible waste, contaminated 14.15 equipment. etc.

c4 3

c. Irradiated components, control m

rods. etc. Ci a3 3.16

d. Other (describe)

Ci 3.17

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

Co-60 60 % Mn-54 16./5 2 Co-56 .43 g Sr-90/4-90 .35% b. Cs-137 46.4i Ba-137m 43.9Y Cs-134 S.1 % Sr-90 2.a2 g Y-90 2.12 % c. N/A Y

d. Sr-90/Y-90 (each) 27.4/g Cs-13/

17.46 g Ba-137m

10. 74 g Sr-89

/.95 1

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 2

Tractor / Trailer (Van) Richland, Washington 1 Tractor / Trailer (Van) Barnwell, S.C. B. Irradiated Fuel Shipments (Disposition) t Number of Shionents Mode of Transportation Destination / EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT July - 1,1981 - December 31, 1981 i SUPPLEMENTAL INFORMATION TMI-Unit-11/Epicor Il l FACILITY ~ LICENSEE ~ 1. Regulatory Limits a. Fission and activation gases: c. Pa t eu ates, half-lives > 8 days: ""f# rti le 2 3 l 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. P rt 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 ,0.253 MeV. 4. Measurements and Approximations of Total Radioactivity Provide the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition. a. Fission and activation gases: Ce(Li) Spectrometry, Liquid Scintillation b. Iodines: Ge(Li) Spectrometry c. Particulates: Ce(Li) Spectrometry, Cas Flow Proportional d. Liquid effluents: Ce(Li) Spectrometry, Liquid Scintillation 5. Batch Releases y Provide the following information relating to batch releases of radioactive materials in liquid and gaseous ef';1uents. . A. Liquid 1. Number of batch releases: None 2. Total time period for batch release: N/A 3. Maximum time period for a batch release: N/A 4. Average time period for batch releases: N/A 5. Minimum time period for a batch release: N/A 6. Average stream flow during periods of release of effluent into flowing stream: N/A -

July 1,1981 - December 31, 1981 ~ e e c*- 5. Batch Releases (cont.) B. Caseous 1. Number of batch releases: None 2. Total tima period'for batch releases: N/A 3. Favimum time period for a batch release: N/A 4. Average time period for batch release: N/A 5. Minimum time period for a batch release: N/A 6. Abnormal-Releases A. Liquid 1. Number of releases: None 2. Total activity released: N/A B. Gaseous 1. Number of releases: 2. Total activity released: N/A

TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT CASE 0US EFFLUENTS-SUMMATION OF ALL P2 LEASES UNIT 3rd 4th EST. TOTAL QUARTER QUARTER ERROR, % Epicor II 1981 19g1 A. Fission & activation gases

1. Total release Ci 1.27E2 1.99El 2.5 El TechSpecLimig/sec
2. Average release rate for period pCi/sec.

1.60E1 2.50E-0 = 20%of2.gE4m

3. Percent of Tech Spec limit 1.11E0 1.74E-1

= 4.8E3 m /sec = 1.44E3 pCi/sec B. Iodines for Kr-85 2.5 El

1. Total Iodine-131 uCi/cc

<tLD <1.T n

2. Average release rate for period uC1/sec.

5/A N/A Tech Spec Limit = 20% of 0.024 pCi/sec

3. Percent of Tech Spec limit N/A g/4

= 0.0048 pCi/sec C. Particulates

1. Particulates with half-lives I

> 8 navs Ci 5.22E-7 1.42E-6 2.5 El

2. Average release rate for period pCi/sec.

6.57E-8 1.79E-7 Tech Spec Limit = 20% of 0.024 pCi/sec

3. Percent of Tech Spec limit 1.37E-3 3.73E-3

= 0.0043 pCi/sec

4. Gross alpha radioactivity Ci 1.24E-9 3.38E-9 D.

Tritium 2.5El 2.64E-3 5.33E-2

1. Total release C1
2. Average release rate for period mci /sec.

3.32E-4 6.71E-3 Tech Spec Limit = 3 20% of 2.4E4 m /sec

3. Percent of Tech Spec limit 3.46E-5 6.99E-4

= 4.8E3 m3/sec = 9.6E2 pCi/sec Note: See table 4 for typical gaseous effluent LLD values N/A = not applicable . am TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT CASE 0US EFFLUENTS-CROUND LEVEL RELEASE Continuous Mode Batch Mode Nuclides UNIT 3rd 1981 4th 1981 3rd 1981 4th 1981 Reletised Epicor II QUARTER QUARTER QUARTER QUARTER 1. Fission gases No Batch Releases in Second lialf of 1981 krypton-85 C1 1.27E2 1.99El krypton-85m uCi/cc <LLD <LLD krypton-87 uCi/cc %LD <vTn krypton-88 uCi/cc <l.CD < T.T.n xenon-133 uCi/cc < l.i.n LLD <LLD xenon-135 uCi/cc qLD xenon-135m uCi/cc <tLD < LLD < LLD xenon-138 uCi/cc <tLD Others (specify) C1 C1 C1 Ci Ci Unidentified C1 Total for period Ci 1.27E2 1.99E-1 2. Itdines <LLD iodine-131 uCi /cc < l.1.0 lodine-133 uCi/cc < 1.1.n <LLD iodine-135 "C1/CC %LD Total for period tCi/cc N/A N/A See Table 4 for typical gaseous effluent I.LD values N/A = Not applicable _4_

c / TABLE IB (cont.) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides UNIT 3rd 4th 3rd 4th Released Epicor II ggg< TER QUARTER QUARTER gUARTER 1991 losi 981 No Batch Releases in 3 Particulates Second Half of 1981 strontium-89 Ci <LLD <LLD strontium-90 Ci <LLD <LLD cesium-134 Ci <LLD g,7E_g cesium-137 Ci <LLD 8.22E-) barium-lanthanum-140 Ci <LLD <LLD Others (specify) Unidentified 5.21E-7 5.10E-7 Note: See Table 4 for typical gascous effluent LLD values

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIAN';UAL REPORT LIQUID EFFLUENTS-SU!OfATION OF ALL RELEASES 'lo Liquid Releases from Epicor-II in UNIT 3rd 1981 4th 1981 EST. TOTAL iecond half of 1981 Epicor-II QUARTER QUARTER ERROR % A. Fission and activation products

1. Total releases (not including tritium, nases, alpha)

Ci N/A N/A

2. Average diluted concentration durtnn period DCi/d N/A-
3. Percent of applicable limit N/A N/A B.

Tritium

1. Total release Ci N/A N/A
2. Average diluteu concentration during period pCi/ml N/A N/A
3. Percent of applicable limit N/A N/A C.

Dissolved rnd entrained gases

1. Total release Ci N/A N/A 7.~ Average diluted concentration durinn period UCi/n1 N/A N/A
3. Percent of applicable limit N/A N/A D.

Cross alpha radioactivity

1. Total release Ci N/A N/A E.

Volume of waste released (prior to dilution) liters N/A N/A F. of ution water used liters 1.65P.10 N/A 1.0 E1 -

I i .~r O i ~ TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIKniUAL REPORT LIQUID EFFLUENTS No Liquid Releases f rom Epicor-II in Second llalf of 1981 Continuous Mode Batch Mode Nuclides UNIT 3rd 1981 4th 1981 3rd 1981 4th 1981 Released QUARTER QUARTER QUARTER QUARTER strontium-89 Ci strontiun-90 Ci cesium-134 Ci cesium-137 Ci fodine-131 ci cobalt-58 C1 cobalt-60 Ci iron-59 Ci zine-65 Ci managanese-54 Ci chromium-51 Ci zirconium-niobium-95 Ci molybdenum-99 Ci technetium-99m Ci barium-lanthanum-140 Ci cerium-141 Ci Other (specify) Ci C1 Ci C1 CL Ci ci Unidentified Ci Total for period Ci xenon-133 Ci xenon-135 Ci

o. TABLE 3A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS EPICOR - July 1, 1981 to December 31, 1981 Solid waste shipped off-site for burial or disposal (not irradiated fuel) A. .,%h gSgT{AL 0

1. Type of waste UNIT II
a. spent resins,111ter sludges, m'

98.6 Ci 65.99 evaporator bottoms. etc. 3

b. Dry compressible vaste, contaminated N/A a

c4 equipment, etc. 3

c. Irradiated components, control m

Ci N/A rods. etc. f ma N/A

d. Other (describe)

Ci

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

Sr-90 IV-90(ench)

29. 3r7 Sb-125 18.4M Ba-137m 7.47%

Cs-13/ 6.61%

b. N/A y

Y c. N/A Y d. N/A y 1

3. Solid Waste Disposition Number of Shipments.

Mode of Transportation Destination 23 Trac tor /Trn f l or ( r-n M Richland. h hincton B. Irradiated Fuel Shipments (Disposition) Number of Shipments Mode of Transportation Destination 5 i 1 -8

TABLE 4 TYPICAL CASEOUS EFFLUENT LLD (Lower Limit of Detection) VALUES 1640 cc ASSUMPTIONS: *

  • Sample Vo.lume (Marinelli) 5.7E8 cc Sample Volume (Particulate and Charcoal Filters) 2 cfm or 5,66E4 cc/ min Sampling Rate 1 week or IE4 min Sampling Time 7.56E5 cc Sample Volume (Tritium bubbled thru water) 75 cc/ min Sampling Rate IE4 min Sampling Time Sample Counting Time: a & 'E = 20 min; 6 = 10 min; y = 1000 see 25% Ge(Li)

Sample Counters: Y emitters a or S Proportional Counter 'H Liquid Scintillation Counter ISOTOPE UCi/cc LLD TYPE SAMPLE Cross Alpha a 1E-15 Particulate Filter Paper Cross Beta B IE-14 Air bubbled thru water by a fritted 8 Tritium H IE-6 disc or Fisher Milligan gas washer Krypton-85 esKr 2E-5 Marinelli Kry pton-85m esmKr 4E-8 Krypton-87 Kr. 4E-8 s7 Krypton-88 esKr 2E-7 Xenon-133 1ssXe IE-7 Xenon-133m 138"Xe 6E-8 335 Xenon-135 Xe 3E-8 Xenon-135m assmXe 4E-7 388 Xenon-138 Xe 4E-7 232 Iodine-131 1 3E-8 Iodine-133 assI 3E-8 185 Iodine-135 I 2E-7 Iodine-131 I 2E-14 Charcoal Filter 181 338 Iodine-133 I IE-13 Iodine-135 1ssI 1E-12 Manganese-54 5"Mn 2E-14 Particulate Filter Paper Iron-59 5'Fe 2E-14 58 Cobalt-58 Co 2E-14 Cobalt-60 5'Co 2E-14 55 Zinc-65 2n SE-14 Strontium-89 8'Sr 2 E-14 Strontium-90 Sr 2E-14 Molybdenum-99 Mo 7E-15 Buthenium-103 3Ru IE-13 1385 Silver-110m Ag IE-13 Cesium-134 13"Cs 2E-14 337 Cesium-137 Cs 2E-14 242 Cerium-141 Ce IE-14 Cerium-144 3*"Ce 6E-14 l l l ~ TABLE 5 TYPICAL LIQUID EFFLUENT LLD (Lower Limit of Detection) VALUES j ASSUMPTIONS:( Except for Cross Alpha Sample volume = 1 liter = 1000 cc Gross Beta Sample counting time = 1000 see Tritium Sample counted with a 25% Ce(Li) and analysis by Teledyne) for Gamma Emitters ISOTOPE UCi/cc LLD NOTES Cross Alpha (1 1E-7 Counted with proportional counter Cross Beta 6 6E-8 Counted with proportional counter 3 Tritium H IE-5 Cgtggd with Liquid Scintillation Krypton-85 asKr 6E-5 Xenon-131m 183*Xe 4E-6 I33 Xenon-133 Xe 4E-7 I35 Xenon-135 Xe 2E-7 52 58 Chromium-51 Cr IE-6 The LLD is also <3 times Co LLD Manganese-54 5"Mn 2E-7 Cobalt-58 5'Co 2E-7 Iron-59 5'Fe 4E-7 Cobalt-60 5'Co 3E-7 55 Zine-65 Zn 4E-7 '5 Zirconium-95 Zr 3E-7 '3 Niobium-95 Nb 2E-7 Molybdenum-99 Mo 8E-8 Technetium-99m *Tc IE-7 Silver-110m 110 mag 2 :.- 7 Antimony-125 12s b 4E-7 S Cesium-134 13"Cs 2E-7 13s Cesium-136 Cs 2E-7 337 Ceslum-137 Cs 2E-7 140 Barium-140 Ba 4E-7 Lanthanum-140 I"'La 4E-7 Cerium-141 Ce 3E-7 1*3 Cerium-144

    • "Ce 7E-7 131 Iodine-131 I

2 E-7 133 Iodine-133 I 2E-7 32 Phosphorus-32 P IE-6 Liquid samples are not currently Iron-55 Fe SE-8 analyzed for.32p, ssFe, Sr, and 55 Strontium-89 8'Sr SE-8 Sr at Three Mile Island. They are Strontium-90 Sr SE-9 sent to Teledyne for analysis,therefore these are Teledyne LLD values, O ee emp

l \\ Joint Frequency Tables i Attachment I - Joint frequency table of wind speed and direction from 100 ft. versus AT 150-33 ft. for the third quarter of 1981 (7/1/81 - 9/30/81) Attachment II - Joint frequency table of wind speed and direction from 100 ft. versus AT 150-33 ft. for UNIT II specific release dates during the third quarter of 1981. Attachment III - Joint frequency tabic of wind speed and direction from 100 ft. versus AT 150-33 ft. for the fourth quarter of 1981 (10/1/81 - 12/31/81) Attachment IV - Joint frequency table of wind speed and direction from, 100 ft. versus AT 150-33 ft, for UNIT II specific release dates daring the fourth quarter of 1981.

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} n. ), Attcchment 5 e EFFLUENT AND WASTE IJSPOSAL SEMI ANNUAL REPORT July 1, 1981 - December 31, 1981 SUPPLEMENTAL INFORMATION i FACILITY THI-Unit-II LICENSEE DPR-73-320 I 1. Regulatory Limits I ~ a. Fission and activation gases: Enviro ntal Tech Specs, c. rt eu ates, half-lives > 8 days: 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. rt c ates, half-lives 8 days: d. Liquid effluents: l 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 Approxir.ations of Total Radioactivity Provide the methods used to measure or approximate 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(Li) Spectrometry, Gas Flow Proportional j d. Liquid effluents: Ge(Li) Spectrometry, Liquid Scintillation 5. Batch Releaser Provide the following information relating to batch releases of radioactive materials in liquid and gaseous effluents. A. Liquid 3rd Quarter 4th Quarter 1. Number of batch releases: 2 4 h 2. Total time period for batch release: N/A N/A 3. Maximum time period for a batch release: 4. Average time period for batch releases: 5. Minimum tine period for a batch release: 6. Average stream flow during periods of release of effluent into flowing stream: See Note (1) on page of this report. r-e o 1 5. Batch Releases (cont.) 3rd Quarter 4th Quarter B. Gaseous 1981 1981 1. Number of batch releases: 7 6 2. Total time period for batch releases: 6652 min. 27094 min. 3. Maximum time period for a batch release: 1890 min. 11998 min. 4. Average time period for batch release: 950 min. 4516 min. 5. Minimum time period for a batch relesse: 2 min. 1540 min. 6. Abnormal Releases A. Liquid 1. Number of releases: None None 2. Total activity released: N/A N/A B. Gaseous 1. Number of releases: None None 2. Total activity released: N/A N/A i 1 f I I

TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT 3rd 4th EST. TOTAL 77 QUARTER QUARTER ERROR, % 19R1 1981 ~ A. Fission & activation gases

1. Total release C1 1.44E2 3.78Ei 7,sg)

E

2. Average release rate for period pCi/sec.

7 f

3. Percent of Tech Spec limit 3.16E-1 8.26E-2

= 1.92E4 m /sec 5.76E3 pCi/sec = B. Iodines f r KR-85

1. Total Iodine-131 Ci

<LLD <LLD 2.5 El lech spec Ltmit =

2. Average release rate for period uCi/sec.

N/A N/A 80% of 0.024 uCi/sec

3. Percent of Tech Spec limit N/A N/A

= 1.92E-2 pCi/sec C. Particulates

1. Particulates with half-lives 2.5.El

> 8 Days C1 4.12E-6 1.34E-5

2. Average release rate for period pCi/sec.

5.18E-7 1.69E-6 Tech Spec Limit = 80% of 0.024 pCi/sec

3. Percent of Tech Spec limit 2.70E-3 8.78E-3

= 1.92E-2 pCi/sec

4. Gross alpha radioactivity Ci 9.43E-9 7.35E-8 D.

Tritium 2.5.El

1. Total release ci 7.45E0 1.74El
2. Average release rate for period pCi/sec.

9.37E-1 2.19E0 Tech Spec Limit = 3 80%of2.4q4m/sec

3. Percent of Tech Spec limit 2.44E-2 5.70E-2

= 1.92E4 m-/sec = 3.84E3 pCi/sec N/A = Not applicable. _. - - -

t _B TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-GROUT:D LEVEL RELEASE Continuous Mode Batch Mode Nuclides. UNIT 3rd 4th 3rd 4th Released II QUARTER QUARTER QUARTER QUARTER 1. Fission gases 1981 1981 1981 1981 krypton-85 C1 1.29E2 3.01El 1.52E1 7.74E0 krypton-85m uct/cc <LLD <LLD <LLD < LLD krypton-87 uC1/cc <LLD <LLD <LLD .- LLb krypton-88 uCi/cc <LLD < LLD <LLD < LLD xenon-133 uCi/cc <LLD < LLD <LLD < LLD xenon-135 uCi/cc <LLD < LLD <tta < LLD xenon-135m uCi/cc <LLD < LLD <LLD < LLD xenon-138 uCi/cc <LLD < LLD <LLD < LLD Others (specify) C1 Ci C1 C1 Ci Unidentified uCi/cc <LLD < LLD <LLD (LLD Total for period C1 1.29E2 3.01El 1.52E1 7.74E0 2. Iodines iodine-131 u Ci/cr. <LLD <LLD <LLD <LLD iodine-133 uCi/cc <LLD <LLD <LLD <LLD iodine-135 uCi/cc <LLD <LLD <ttg <LLD Total for period Ci N/A N/A N/A N/A Note: See Table 4 for typical LLD values N/A = Not applicable -

9 TABLE IB (cont.) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-CROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides - UNIT 3rd 4th 3rd 4th Released II QUARTER _ QUARTER QUARTER QUARTER l 1981 1981 1961 l'J ol 3 Particulates strontium-89 Ci <LLD '(LLD < LI.D <LLD strontium-90 Ci <LLD <LLD <LLD <LLD cesium-134 Ci 1.45E-9 2.08E-8 <LLD <LLD. cesium-137 C1 4.03E-7 1.25E-6 <I.I.D <LI.D barium-lanthanum-140 Ci <LLD <LLD <, y n <tLD Others (specify) Cobalt-60 Ci 6.92E-8 <I.LD <ttg <LLD Unidentified Ci 3.64E-6 1.15E-5 <LLD <LLD Note: See Table 4 for typical LLD values

/ TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Tech Spec Limits = 10CFR20, Appendix B, Table II, Column 2 UNIT 3rd 1981 4th 1981 EST. TOTAL II QUARTER QUARTER ERROR % A. Fission and activation products

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

C1 2.52E-6 1.78E-6 2.5 El

2. Average diluted concentration durinn period Ci/ml 1 53E-13
1. 2 6 E--13
3. Percent of applicable limit 7.65E-7 4.21E-4 B.

Tritium

1. Total release C1 4.99E-2 1.9E-4 2.5 El
2. Average diluted concentration 1.35E-il during period UCi/ml to7p g
3. Percent of applicable limit 1.01E-4 4.49E-7 C.

Dissolved and entrained gases

1. Total release Ci

<tto <LLD 2.5 El Z. Average diluted concentration during period UCi/n1 N/A N/A

3. Percent of applicable limit N/A N/A D.

Cross alpha radioactivity

1. Total release Ci

<LLD <LLD 2.5 El E. Volume of waste released (prior to dilution) liters 6.44E4 1.96E4 2.5 El F. Volume of dilution water used durinn period liters 1.65E10-1.41E10 1.0E1 NOTE: See Table 5 for typical LLD values. Note (1) There were no liquid releases from the radwaste system during the second half of 1981 since this system is ntill flanged off from the discharge lines. Very low concen-tra. tons of radionuclides have been found occasionally in the industrial waste stream and sanitary waste. These concentrations in the TMI II industrial waste stream are not detectable in samples of the effluent stream from TMI prior to final discharge to the Susquehanna River.

TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides UNIT 3rd 4th 3rd 4th Released - II QUgR QUgE,R QU g R Q g ER strontium-89 Ci See Note (2) See Note (2) <LLD <tLD strontium-90 Ci <LLD <LLD cesium-134 Ci <LLD <LLD cesium-137 C1 2.52E-6 <LLD iodine-131 c, 4 <LLD <LLO cobalt-58 Ci <LLD <LLD cobalt-60 Ci <LLD <LLD iron-59 Ci <LLD zine-65 Ci <LLD <LLD managanese-54 Ci <LLD <tto chromium-51 Ci <LLD <LLD zirconium-niobium-95 Ci <LLD <LLD molybdenum-99 Ci <LLD <Ltp technetium-99m Ci <LLD <LLD barium-lanthanum-140 Ci <LLD <LLD cerium-141 Ci <LLD <tLb Other (specifv) Ci Ci Ci Ci Ci Ci cf Unidentified Ci <LLD 1.78E-6 Total for period Ci 2.52F.-6 I" ~ xenon-133 Ci <LLD <LLD xenon-135 Ci <LLD 'LL" Note: See Table 5 for typical LLD valves Note (2) There was no continuous release of effluent from Unit Il during the second half of 1981. 4

s. 'l. TABLE 3A EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT SOLID WASTE AND IRBADIATED FUEL SHIPMENTS July 1, 1981 to December 31, 1981 Solid waste shipped off-site for burial or disposal (not irradiated fuel) A. f,""jh ERR 6R

1. Type of waste UNIT 11 m'

4.42

a. spent resins,111ter sludges e

Ci .04 avanorator bottoms. etc. n' 63.2'S

b. Dry compressible waste, contaminated 14.15 e,

equipment. etc.

c. Irradiated components, control m'

rods. etc. Ci m' 3.16

d. Other (describe)

Ci 3_.17

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

Co-60 80 % Mn-54 18.75 2 Co-58 .43g Sr-90/4-90 .35 % b. Cs-137 46.4 Y Ba-137m 43.9Y Cs-134 5.12 Sr-90 2.32% Y-90 2.32 % c. N/A 1 Y

d. Sr-90/Y-90 (each) 27.47Y Cs-137 17.48 g Ba-137m 16.74g Sr-89 7.95 1
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 2

Tractor / Trailer (Van) Richland, Washington 1 Tractor / Trailer (Van) Barnwell, S.C. B. Irradiated Fuel Shipments (Disposition) Number of Shipments Mods of Transportatien Destination 5 t 'l ^

EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT July 1, 1981 - December 31, 1981 SUPPLEMENTAL INFORMATION TMI-Unit-II/Epicor II ~ ~ FACILITY LICENSEE

1..

Regulatory Limits a. Fission and activation gases: c. Pa t cu ates, half-lives)>8 days: Arti e23 d. Liquid effluents: 2. Maximum Permissible Concentrations Provide the MPCs used in determining allowable release rates or concentrations, a, Fission and activation gases: O CFR, Part 20, Appendix B c Particu 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 0.253 MeV. 4. Measurements and Approximations of Total Radioactivity Provide the methods used to measure or approximate 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(Li) Spectrometry, Gas Flow Proportional d. Liquid effluents: Ge(Li) Spectrometry, Liquid Sc!.ntillation 5. Batch Releases Provide the following information relating to batch releases of radioactive materials in liquid and gaseous effluents. A. Liquid 1. Number of batch releases: None 2. Total time period for batch release: N/A 1 3. Maximum time period for a batch release: N/A 4. Average time period for batch releases: N/A 5. Minimum time period for a batch release: N/A 6. Average stream flow during periods of release of effluent into flowing stream: N/A

~ ~ July 1, 1981 - Decrmber 31, 1981 5. Batch Releases (cont.) B. Caseous 1. Number of batch releases: None 2. Total time period' for batch releases: N/A 3. ridximum time period for a batch release: N/A 4. Average time period for batch release: N/A 5. Minimum time period for a batch release: N/A 6. Abnormal Releases A. Liquid 1. Number of releases: None 2. Total activity released: N/A B. Gaseous 1. Number of releases: 2. Total activity released: N/A 1 1 J. _-_v. ...y. .-c...

TABLE 1A EFFLUENT AND WASTE 1.ISPOSAL SEMIANNUAL REPORT CASE 0US EFFLIENTS-SUMMATION OF ALL RELEASES UNIT 3rd 4th EST. TOTAL QUARTER QUARTER ERROR, % Epicor II 1981 1981 A. Fission & activation gases

1. Total release C1 1.27E2 1.99El 2.5 El TechSpecLimig/sec
2. Average release rate for period pC1/sec.

1.60El 2.50E-0 = 20%of2.jE4m

3. Percent of Tech Spec limit 1.llE0 1.74E-1 4.8E3 m /sec

= 1.44E3 pCi/sec = B. Iodines for Kr-85 2.5 El

1. Total Iodine-131 uCi/cc

<tto < t.T,n

2. Average release rate for period UC1/sec.

5/A N/A Tech Spec Limit =

3. Percent of Tech Spec limit N/A N/A

= 0.0048 pCi/sec C. Particslates

1. Particulates with half-lives

> 8 Days Ci 5.22E-7 1.42E-6 2.5 El

2. Average release rate for period pC1/sec.

6.57E-8 1.79E-7 Tech Spec Limit = 20% of 0.024 pCi/sec

3. Percent of Tech Spec limit 1.37E-3 3.73E-3

= 0.0048 pCi/sec

4. Cross alpha radioactivity Ci 1.24E-9 3.38E-9 D.

Tritium 2.5El

1. Total release C1 2.64E-3 5.33E-2
2. Average release rate for period ECi/sec.

3.32E-4 6.71E-3 Tech Spec Limit = 3 207, of 2.4E4 m /sec

3. Percent of Tech Spec limit 3.46E-5 6.99E-4 4.8E3 m3/sec

= 9.6E2 pCi/sec = Note: See table 4 for typical g.iscous effluent LLD values N/A = not applicable

TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT CASEOUS EFFLUENTS-CROUND LEVEL RELEASE Continuous Mode Batch Mode Nuclides UNIT 3rd 1981 4th 1981 3rd 1981 4th 1981 Released ' Epicor II QUARTER QUARTER QUARTER QUARTER 1. Fission gases No Batch Releases in Second licif of 1981 krypton-85 C1 1.27E2 1.99El krypton-85m uCi/cc <LLD < LLD krypton-87 uCi[cc qLD <rTn krypton-88 uCi/cc <LLD < 1,T.n xenon-133 uCi/cc qtn LLD xenon-135 uCi/cc qLD < LLD xenon-135m uCi/cc <LLD < LLD < LLD xenon-138 uCi/cc <tLD Others (specify) C1 Ci Ci ) C1 Ci Unidentified Ci. Total for period Ci 1.27E2 1.99E-1 2. Iodines iodine-131 uCi/cc <tLD <LLD lodine-133 uC1/cc <tLD <LLD iodine-135 uci/cc %LD Total for period uCi /cc N/A N/A See Tabic 4 for typical gaseous effluent LLD values N/A = Not applicable._ _.

= TABLE IB (cont.) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides. UNIT 3rd 4th 3rd 4th Released Epicor 11 g*TER QUARTER QUARTER OUARTER 19R1 1981 1981 No Batch Releases in 3, p, gg, Second 11alf of 1981 strontium-89 Ci <LLD <LLD strontium-90 Ci <LLD <LLD cesium-134 Ci <LLD 8.7E-8 cesium-137 Ci <LLD 8.22E-2 barium-lanthanum-140 Ci <LLD <LLD Others (specify) Unidentified 5.21E-7 5.10E-7 Note: See Table 4 for typical gaseous effluent LLD values _e-.

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES io Liquid Releases from Epicor-II in UNIT 3rd 1981 4th 1981 EST. TOTAL second half of 1981 Epicor-II QUARTER QUARTER ERROR % A. Fission and activation products

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

Ci N/A N/A

2. Average diluted concentration durine period mci /ml N/A N/A-
3. Percent of applicable limit N/A N/A B.

Tritium

1. Total release Ci N/A N/A
2. Average diluted concentration during period pCi/ml N/A N/A
3. Percent of applicable limit N/A N/A C.

Dissolved and entrained gases

1. Total release Ci N/A N/A
2. Average diluted concentration durinn period UCi/n1 N/A N/A
3. Percent of applicable limit N/A N/A D.

Cross alpha radioactivity

1. Total release Ci N/A N/A E. Volume of waste released (prior to dilution) liters N/A N/A F. 'olg o ution water used liters 1.65E10 N/A 1.0 El

~ TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LlQUID EFFLUENTS No Liquid Releases from Epicor-II in Second llalf of 1981 Continuous Mode Batch Mor's Nuclides. UNIT 3rd 1981 4th 1981 3rd 1981 4th 1981 Released QUARTER QUARTER QUARTER QUARTER strontium-89 Ci strontium-90 Ci cesium-134 C1 cesium-137 Ci indine-131 ci cobalt-58 C1 cobalt-60 Ci fron-59 Ci zine-65 Ci manananese-54 Ci chromium-51 Ci zirconium-niobium-95 Ci molybdenum-99 Ci technetium-99m Ci barium-lanthanum-140 C1 cerium-141 Ci Other (specify) C1 Ci C1 C1 Ci Ci c1 Unidentified Ci Total for period Ci xenon-133 Ci xenon-135 C1 _7_

4 f.

TABLE 3A IFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS EPICOR - July 1, 1981 to December 31, 1981 Solid waste shipped off-site for burial or disposal (not irradiated fuel) A. 0 %h g TOTAL

1. Type of waste UNIT 11
a. spent resins,111ter sludges, m'

98.6 C1 65.o? avaoorator bottoms. etc. 3

b. Dry compressible waste, contaminated N/A a

c, equipment. etc. 3

c. Irradiated components, control m

Ci N/A rods. etc. as N/A

d. Other (describe)

Ci

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

Sr-90 TV-90(each)

29. %%

Sb-125

18. 48r Ba-137m 7,47g Cs-13/

6.61g

b. N/A y

Y 2 c. N/A 1 d. N/A g t

3. Solid Waste Disposition Humber of Shipments.

Moda of Transportation Destination l 23 Tractor /Trai t or (c,ckT Richland. Washincton l l-I' B. Irra'.diated Fuel Shipments (Disposition) Number of Shipments Mode of Transportation Destination t It 4

d TABLE 4 TYPICAL CASEOUS EFFLUENT LLD (Lower Limit of Detection) VALUES 1640 cc ASSUMPTIONS:

  • Sample Vo.lume (Marinelli) 5.7E8 cc Sample Volume (Particulate and Charcoal Filters) 2 cfm or 5.66E4 cc/ min Sampling Rate I week or IE4 min Sampling Time 7.56E5 cc Sample Volume (Tritium bubbled thru water) 75 cc/ min Sampling Rate IE4 min Sampling Time Sample Counting Time: a & 'H = 20 min; B = 10 min; y = 1000 see 25% Ge(Li)

Sample Counters: y emitters a or B Proportional Counter 'E Liquid Scintillation Counter ISOTOPE UCi/cc LLD TYPE SAMPLE Cross Alpha a IE-15 Particulate Filter Paper Gross Beta B IE-14 Air bubbled thru water by a fritted s Tritium H IE-6 disc or Fisher Milligan gas washer Krypton-85 Kr 7E-5 Marinelli 85 Kry pt on-85m '5"Kr ',8 s7 Krypton-87 Kr. -8 as Krypton-88 Kr 2-7 Xenon-133 l "Ke IE / Xenon-133m tasmXe 6E-8 23s Xenon-135 Xe 3E-8 Xenon-135m 385"Xe 4E-7 Xenon-138 33'Xe 4E-7 232 Iodin e-131 1 3E-8 Iodine-133 3"I 3E-8 385 Iodine-135 I 2E-7 lodine-131 I 2E-14 Charcoal Filter 232 338 Iodine-133 I 1E-13 335 Iodine-135 I IE-12 Manganese-54 5"Mn 2E-14 Particulate Filter Paper Iron-59 Fe 2E-14 Cobalt-58 5'Co 2E-14 Cobalt-60 Co 2E-14 55 Zinc-65 Zn SE-14 Strontium-89 Sr 2E-14 Strontium-90 Sr 2E-14 Molybdenum-99 "Mo 7E-15 Ruthenium-103 lRu 1E-13 Silver-110m 22emAg IE-13 Cesium-134 18"Cs 2E-14 Cesium-137 Cs 2E-14 387

    • I Cerium-141 Ce IE-14 Ccrium-144 I""Ce 6E-14

~

'\\ TABLE 5 TYPICAL LIQUID EFFLUENT LLD (Lcuer Limit of Detection) VALUES ASSUMPTIONS:( Except for Gross Alpha Sample volume = 1 liter = 1000 cc Gross Beta Sample counting time = 1000 see Tritium Sample counted with a 25% Ge(Li) ~ and analysis by Teledyne) for Gamma Emitters ISOTOPE UCi/cc LLD NOiES Cross Alpha a IE-7 Counted with proportional counter Gross Beta C 6E-B Counted with proportional counter Tritium 'H IE-5 Counted with Liquid Scintillation counter 85 Krypton-85 Kr 6E-5 Xenon-131m 183*Xe 4E-6 338 Xenon-133 Xe 4E-7 135 Xenon-135 Xe 2E-7 Chromium-51 Cr IE-6 The LLD is also <3 times 5'Co LLD 52 Manganese-54 5'Mn 2E-7 Cobalt-58 5'Co 2E-7 Iron-59 5'Fe 4E-7 Cobalt-60 Co 3E-7 '5 Zinc-65 Zn 4E-7 '5 Zirconium-95 Zr 3E-7 '8 Niobium-95 Nb 2E-7 Molybdenum-99 Mo BE-8 Technetium-99m "*Tc IE-7 Silver-110m 110 mag 2E-7 Antimony-125 12sSb 4E-7 Cesium-134 13"Cs 2E-7 135 Cesiu:r-136 Cs 2E-7 is7 Cesium-137 Cs 2E-7 Barium-140

    • 'Ba 4E-7 Lanthanum-140 I"'La 4E-7 1'3 Cerium-141 Ce 3E-7 Cerium-144 I"'Ce 7E-7 133 Iodine-131 I

2 E-7 133 Iodine-133 I 2E-7 82 Phosphorus-32 P IE-6 Liquid samples are not currently Iron-55 Fe SE-8 analyzed for.32p, sspe, esSr, and 55 Strontium-89 Sr SE-8 Sr at Three Mile Island. They are Strontium-90 Sr SE-9 sent to Teledyne for analysis,therefore these are Teledyne LLD values. Y

o Ioint Frequency Tables Attachment I - Joint frequency table of wind speed and direction from 100 ft. versus AT 150-33 ft. for the third quarter of 1981 (7/1/81 - 9/30/81) Attachment II - Joint frequency table of wind speed and direction from 100 ft. versus AT 150-33 ft. for UNIT II specific release dates during the third quarter of 1981. Attachment III - Joint frequency table of wind speed and direction from 100 ft. versus AT 150-33 ft. for the fourth quarter of 1981 (10/1/81 - 12/31/81) Attachment IV - Joint frequency table of wind speed and direction from 100 ft. versus AT 150-33 ft. for UNIT II specific release dates during the fourth quarter of 1981. i

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