ML20064C308

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Effluent & Waste Disposal Annual Rept 1993 TMI-1
ML20064C308
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 12/31/1993
From: Broughton T
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-94-2021, NUDOCS 9403090272
Download: ML20064C308 (35)
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GPU Nuclear Corporation v Nuclear 5,.

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Middletown, Pennsylvania 17057-0480 (717) 944 7621 Writer's Direct Dial Number:

(717) 948-8005 March 1, 1994 C311-94-2021 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

Dear Sir:

Subject:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 1993 Annual Radioactive Effluent Releases Report The TMI-1 Annual Radioactive Effluent Releases Report required by TMI-1 Technical Specification 6.9.4.1 and the Off-Site Dose Calculation Manual Part 3, Section 2.1 is enclosed.

Attachment I contains a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Reg. i Guide 1.21, Rev.1, with data summarized on a quarterly basis following the  !

format of Appendix B thereof.

Attachment 2 contains information for each type of solid waste shipped offsite during the report period including the container volume, total curie quantity (specified as determined by measurement or estimate), principal radionuclides (specified as determined by measurement or estimate), type of waste, type of l shipment and solidification agent (s).

Attachment 3 includes a summary of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.

Attachment 4 describes any changes made during 1993 to the Process Control Program (PCP) documents or to the Offsite Dose Calculational Manual (0DCM) and a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part 1, Section 8.2 of the ODCM.

Attachment 5 reports all instrumentation not returned to operable status within 30 days per TMI-l Technical Specification Sections 3.21.1.b and 3.21.2.b.

Attachment 6 is an annual summary of hourly meteorological data collected over the previous year in the form of joint frequency distribution of wind speed, wind direction and atmosoheric stability.

9403090272 931231 PDR ADOCK 05000289 (y R PDR //l {j 0 S O O 8 21 oPu nuclear corporet,on is a subs,a,ary of ceneral Public Utikties Corporation/

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. i Document Controls Desk C311-94-2021 Page 2 Attachment 7 is an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit during 1993.

Attachment 8 is an assessment of the radiation doses from the radioactive liquid and gaseous effluents to members of the public due to their activities '

inside the site boundary during 1993.

Attachment 9 is an assessment of the radiation doses to the likely most exposed real individual from reactor releases and other nearby uranium fuel cycle sources including doses from primary effluent pathways and direct radiation for 1993. This assessment shows conformance with 40 CFR 190 " Environmental Radiation Protection Standards for Nuclear Power Operation."

Please contact Mr. John Schork, TMI Licensing at 717-948-8832 if you have any questions concerning this report.

Sincerely, h%> _

UM T. G. Brough n Vice President and Director, TMI JSS/ emf Attachments cc: M. G. Evans - TMI Senior Resident Inspector R. W. Hernan - TMI Senior Project Manager T. T. Martin - Region I Administrator File T94042

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ATTACHMENT 1 C311-94-2021 l

l Summary of Radioactive Liquid and Gaseous Effluents i and Solid Waste Released from TMI-1 l l

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION FACILi1Y: TMI UNIT 1 LICENSE: DPR 50-289 <

1. REGULATORY LIMITS - - - REFER TO TMI UNIT 1 TECHNICAL SPECIFICATIONS A. FISSION AND ACTIVATION GASES:
8. IODINES:

C. PARTICULATES. HALF-UVES > 8 DAYS:

D. LIQUID EFFLUENTS:

2. MAXIMUM PERMISSIBLE CONCENTRATIONS - - - 10 CFR 20. APPENDIX B TABLE 11 PROVIDE THE MPCS USED IN DETERMINING ALLOWABLE RELEASE RATES OR CONCENTRATIONS.

A. FISSION AND ACTIVATION GASES:

B. IODINES:

C. PARTICULATES. HALF-UVES > 8 DAYS:

D. UQUID EFFLUENTS:

3. AVERAGE ENERGY PROVIDE THE AVERAGE ENERGY (E-BAR) OF THE RADIONUCUDE MIXTURE IN RELEASES OF FISSION AND ACTIVATION GASES,IF APPLICABLE E-BAR BETA = 1.96E-01 E-BAR GAMMA = 1.82E-01 E-BAR BETA AND GAMMA = 3.78E-01
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 RADIONUCUDE COMPOSITION:

l A. FISSION AND ACTIVATION GASES: HPGE SPECTROMETRY, UQUID SCINTILLATION B. lODINES: HPGE SPECTROMETRY l C. PARTICULATES HPGE SPECTROMETRY, GAS FLOW PROPORTIONAL l BETA SPECTROMETRY l D. LIQUID EFFLUENTS: HPGE SPECTROMETRY, UQUID SCINTILLATION

5. BATCH RELEASES PROVIDE THE FOLLOWING INFORMATION RELATING TO BATCH RELEASES OF RADICACTIVITY MATERIALS IN UQUID AND GASEOUS EFFLUENTS.

A. LlOUID (ALL TIMES IN MINUTES) OUARTER 1 QUARTER 2 QUARTER 3 OUARTER 41

1. NUMBER OF BATCH RELEASES: 20 18 22 33
2. TOTAL TIME PERIOD FOR BATCH RELEASES: 9890. 4767. 6274. 9212,
3. MAXIMUM TIME PERIOD FOR A BATCH RELEASE: 1195. 310. 330. 345.
4. AVERAGE TIME PERIOD FOR BATCH RELEASES: 495. 265. 285. 279.
5. MINIMUM TIME PERIOD FOR A BATCH RELEASE: 255. 68. 75. 150.
6. AVERAGE STREAM FLOW DURING PERIODS OF RELEASE j j _ OF EFFLUENTINTO A FLOWING STREAM: (CFM) 2.85E + 06 5.48E + 06 3.83E +05 2.17E + 06 I l

l B GASEOUS 1ALL TIMES IN MINUTES)

1. NUMBER OF BATCH RELEASES: 19 18 30 37  !

l l SL TOTAL TIME PERIOD FOR BATCH RELEASES: 148838 156508 247071 85344.  !

3. MAXIMUM TIME PERIOD FOR A BATCH RELEASE: 44600. 44600. 44600. 15500.
4. AVERAGE TIME PERIOD FOR BATCH RELEASES: 7834. 8695. 8236. 2307.
5. MINIMUM TIME PERIOD FOR A BATCH RELEASE: 1. 22. 1. 7.
6. ABNORMAL RELEASES A. LlOUID l
1. NUMBER OF RELEASES: , l
2. TOTAL ACTIVITY RELEASED: (CURIES) N/A j N/A N/A N/A  !

l B. GASEOUS

1. NUMBER OF RELEASES: 1 3
2. TOTAL ACTIVITY RELEASED: (CURIES) N/A N/A N/A l N/A

TABLE 1 A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1993)

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES

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f~ 5SY.~EUT C l UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 ERROR.% i A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE Ci 4.08E+ 02 4.98E+ 02 1.43E + 03 6.37E + 01 l 2.50E + 01 I
2. AVG. RELEASE RATE FOR PERIOD uCi/sec 5.25E+ 01 6.34E + 01 1.80E+ 02 8.01 E + 00
3. PERCENT OF TECH.

SPECIFICATION LIMIT  %

B. IODINES

1. TOTAL IODINE l l-131 Ci 1.00E-03 4.04E- 04 5.07E-03 8.95E-04 2.50E+ 01~ 1
2. AVG. RELEASE 5 ATE FOR PERIOD uCi/sec 1.29E- 04 5.13E-05 6.38E-04 1.13E- 04 l 3. PERCENT OF TECH.

SPECIFICATION LIMIT  %

C. PARTICULATES l 1. PART. WITH HALF-LIVES > 8 DAYS Ci < 1.00E-04 < 1.00E- 04 3.95E-06 1.89E-07 2.50E+ 01

2. AVG. RELEASE RATE l FOR PERIOD uCi/sec NA NA 4.97E-07 2.37E-08
3. PERCENT OF TECH.

SPECIFICATION LIMIT  % NA NA

4. GROSS ALPHA RADIOACTIVITY Ci < 1.00E- 11 <1.00E 21 < 1.00E- 11 < 1.00E- 11 D. TRITIUM

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l 1. TOTAL RELEASE Ci 1.15E+ 00 6.19E+ 00 7.12E+ 00 7.43E- 01 2.50E + 01 ~i

2. AVG. RELEASE RATE l FOR PERIOD uCl/sec 1.48E-01 7.87E-01 8.96E-01 9.35E-02
3. PERCENT OF TECH.

SPECIFICATION LIMIT  %

NOTE: ALL LESS THAN VALUES (<) ARE IN uCi/ml. I

  • % TECH. SPEC. LIMITS: LISTED ON DOSE

SUMMARY

TABLE.

TABLE 1C .

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1993)

GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES

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CORTINODUS MDDN BKTCITMOb8 CGhilNUOUS" MODE

-~BATCR MODE NUCUDES RELEASED UNIT QUARTER 1 l QUARTER 2 OUARTER 1 l QUARTER 2 QUARTER 3TOUARTERTOU~ARTERROUARTER 4

1. FISSION GASES _ _ _ _ ._ _ . _ _ _ _ ._

AR 41 Ci 1.83E-03 1.01E-02 6.59E-02 7.72E-02 1.97E-02} 8.08E-02. _ __1.69.E + 00' 6.9_2E-03 KR 85M Ci 2.19E +00 4.12E + 00 8.85E-03 1.96E-02 5.29E + 00 1.01 E-02 1.06E-01 1.04E-04 Ci < 8.00E-06 1.45E-01 2.84E + 01 3.24E +01 < 8.00E-06 < 8.00E-06 T 3.23E401 2.00E+01 KR 85 KR 87 Ci 1.80E+ 00 3.65E + 00 8.27E-06 4.55E-04 5.23E + 00 2.64E-02I <8.00E-08 < 8.00E-08 3.99E+ 00 7.94E + 00 1.13E-03 4.62E-03 1.07E + 01 2.67E-02 6.20E-03i < 1.00E-07 1 88_ Ci Ci <3.00E-07 < 3.00E-07 5.94E + 00 5.28E +00 < 3.00E-07 <3.00E-07 1.22E + 01 3.35E + 00 XE 131M XE 133M Ci 1.66E +00 2.74E + 00 7.82E-01 6.81 E-01 3.29E + 00 < 2.00E-07 3.77E +00 4.90E-02

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Ci 1.25E + 02 2.17E + 02 2.20E + 02 1.90E +02 4.96E + 02 7.01 E + 00 7.95E + 0 3.25E + 01

'XE 133 -

MET 35M Ci 1.36E +00 2.62E + 00 6.17E-06 2.54E-05 3.82E+00 2.10E -01 <5.00E-07"< 5.0DE 67 XE 135 Ci 1.55E +01 2.89E+01 1.27E-01 3.24E-01 5.16E + 01 1.73E-01 3.66E + 00 2.28E-01 XE 138 Ci 9.52E-01 1.92E + 00 4.64E-06 <3.00E-07 3.99E + 00 6.43E-02 < 3.00E-07 < 3.00E-07 TOTAL FOR PERIOD Ci 1.53E +02 2.69E +02 2.56E + 02 2.29E + 02 5.80E + 02 7.60E +00 8.49E + 02 5.61 E + 01

2. lODINES ~ ~~

1131 Ci 9.968 - 04 4.035 -04 7.16E-06 4.84E-07 2.30E -03 I~70E-04 2.77E- 5I-~ 7.25E-04 1133 Ci 1.105T05 7.71 E-04 6.66E-07 4.14E-08 1.75EZU5 - ~2T7$ZUA 243ET07 ~ <E00ElZdi TOTAL FOR PERIOD Ci 2.09E-03 1.17E-03 7.83E-06 5.25E-07 4.05E-03 3.87E-04 2.77E-03 7.25E-04

3. PARTICULATES ~

Ci < 1.00E-12 < 1.00$-12 < 1.0dE-12 < 1.00$-12 < 1.00E-12 < 1.00E-12 < 1.00E-12 1.85E-07

_C O 58 CS 134 Ci < 1.00E-11 < 1.00E-11 < 1.00E-08 < 1.00E-08 < 1.00E-11 1.33E-06 < 1.00E-08

< 1.00E --08 CS 137 Ci < 1.00E-11 < 1.00E- 11 < 1.00E-08 < 1.00E-08 I 2.62E-06 < 1.00E-1171.00$-08 l < 1.00E-08]

NOTE: ALL LESS THAN VALUES (<) ARE IN uCi/ml.

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. l TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1993) {

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES '

EST. TOTAL UNIT QUARTER 1 QUARTER 2 OUARTER 3 QUARTER 4 ERROR.%

A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEA'SE (EX.

H-3, GASES, ALPHA) Cl 3.09E-03 3.58E-03 6.68E-02 1.47E-02 2.50E+ 01

2. AVG. DILUTED CONC. DURING PERIOD uCl/mi 2.67E-10 3.13E-10 5.10E-09 1.70E-09
3. PERCENT OF APPLICABLE LIMIT  %

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! B. TRITIUM i

, 1. TOTAL RELEASE Ci 2.24E + 02 5.13E + 01 1 3.50E+ 01 6.61 E+ 01 2.50E+ 01 l

2. AVG. DILUTED CONC. DURING PERIOD uCl/mi 1.93E-05 4.49E-06 2.67E-06 7.65E-06
3. PERCENT OF APPLICABLE LIMIT  %

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE Ci 4.37E-01 5.40E - 02 6.05E-03 1.24E-03 2.50E+ 01 i
2. AVG. DILUTED CONC. DURING PERIOD uCi/ml 3.78E-08 4.73E-09 4.62E-10 1.44E-10
3. PERCENT OF APPLICABLE LIMIT .  %

l D. GROSS ALPHA RADIOACTIVITY l1. TOTAL RELEASE l Ci l <1.00E-07 l <1.00E-07 l <1.00E-07 l <1.00E-07 l 2.50E+ 01 l l

2 E. VOL. OF WASTE l RELEASED (NO DIL.) LITERS 8.92E+ 06 7.64E + 06 1.37E+ 07 1.97E+ 07 1.00E+ 01

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F. VOL. OF DILUTION WATER IN PERIOD LITERS 1.16E + 10 1.14E + 10 1.31 E+ 10 8.64E+09 1.00E+ 01 NOTE: ALL LESS THAN VALUES (<) ARE IN uCl/ml.

  • % TECH. SPEC. LIMITS: LISTED ON DOSE

SUMMARY

TABLE.

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TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1993)

LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE CONTINUOUS MODE 7 B4TCl-iffdDE UNIT ~6U RTER 1 dUARTEWOUARTER_1 QUKRT$R 2 QUhRTER 3 QUERTER[QU~ARTER'3JOUARTEM N_U C_UDES RELEASED <5.00E-07 < 5.00E-07 < 5.00E-07 CR 51 Ci < 5.00E-07 < 5.00E-07 < 5.00E-07 <5.00E-074_ <5.00E-07 Ci < 5.00E-07 < 5.00E--07 < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E -07 < 5.00E-07 MN54 5.38E-04 2.45E-04 Ci < 1.00E-06 < 1.00E-06 < 1.00E-06 8.63E-05 < 1.00E-06 < 1.00E-06 FE 55 < 5.00E -07 < 5.00E-07 Ci < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E -07 < 5.00E -07 < 5.00E -07

_FE 59 8.65E-05 1.78E-04 1.86E-04 4.36E-05 4.99E-04 4.26E-05 Ci < 5.00E-07 < 5.00E-07

.C_O 58 4.55$-06 <5.00ET 077 <5.00E-07 7.81 E-06 < 5.00E-07 CO 60 Ci < 5.00$-07 < 5.00E-07 9.21 E-06 Ci < 5.00E-07 < 5.00E-07 < 5.00E -07 < 5.00E-07 < 5.00E -07 < 5.00E-07 < 5.00E -07 < 5.00E-G7

~ZN 65 < 5.00E-08 3.40E-05 < 5.00E-08 < 5.00E-08 < 5.00E-08 c.GGti-08 SR 89 Ci < 5.00E-08 < 5.00E-08 Ci < 5.00E-08 1.05E-04 < 5.00E -08 3.04E-05 2.26E-06 < 5.00E-08 < 5.00E-08 < 5.00E-08 SR 90 Ci < 5.00E-07 < 5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 < 5.00E-07' < 5.00E-07 < 5.00E-07

~ZR 95 Ci < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E -07 < 5.00E-07 < 5.00E-07

-NB 95 Ci < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E -07 < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E -07 MO 99 < 5.00E-07 < 5.00E-07

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~T d ~99M Ci < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E -07 < 5.00E -07 Ci < 5.00E-07 < 5.00E-07 7.04E-06 2.69E-05 < 5.00E -07 < 5.00E-07 3.57E-05 < 5.00E-07 AG 110M

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di < 5.00E -07 < 5.00E -07 < 5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 5.51 E-05 3.01E-06 SB 125 Ci 1.22E-03 1.15E-04 < 1.00E -06 < 1.00E-06 2.40E-02 6.68E-04 5.91E-04 1.97E-04 l131 < 5.00E-07 < 5.00E-071 Ti33 Ci < 5.00$-07 2.99E-04 < 5.00E-07 < 5.00E-07 1.73E-03 2.45E-05 Ci 6.01E-04 1.078 - 03 5.13E-05 4.96E-05 1.76E-02 5.74$-03 2.95$-04 6.54E-05 CS 134 Ci 6.15E-05 < 5.00E-07 < 5.00E-07 < 5.00E-07 1.52E-03 3.70E -04 < 5.00E-07 r < 5.00E-07 jCS.136 CS 137 Ci 9.14E-04 1.48E-03 1.35E-04 1.03E-04 1.91E-02 7.15E-03 6.06E-04 1.54E-04 Ci <5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E-07 BA 140 LA 140 Ci < 5.00E-07 < 5.00$-07 < 5.00$-07 < 5.00E-07 4.63E-05 < 5.00E-07 <5.00E-07I <5.00E-07

< 5.00E-07 f Ci < 5.00E-07 < 5.00$-07 < 5.00$-07 < 5.00E-07 < 5.00E-07 < 5.00E-07 < 5.00E-07~T < 5.00E-07'

^de 141 TOTAL FOR PERIOD Ci 2.80E-03 3.07E-03 2.89E-04 5.13E-04 6.42E-02 1.40E-02 2.62E-03 7.07E-04

-KR 85M Ci < 1.005-04 < 1.00E-04 4.98E106 < 1.00$-04 < 1.0L .* 04 <1.00ET04 < 1.00$-04 < 1.00EM Ci < 1.00E-04 < 1.00E-04 6.76E-03 < 1.00E-04 < 1.00E-04 < 1.00E-04 < 1.00E-04 < 1.00E-04

.XE 131M 8.82E-06 < 1.00E-04 < 1.00E -04 < 1.00E -04 < 1.00E-04 XE 133M Ci < 1.00E-04 < 1.00E-04 2.65E-03 Ci < 1.00E-04 1.42E-03 4.10E-01 6.15E-03 5.74E-03 < 1.00E -04 3.08E-04n_1.08E-03 XE133_ < 1.00E-04 < 1.00E-04 < 1.00E-04 < 1.00E -04 3.21 E-06 ! < 1.00E-04l XE 135M Ci < 1.00E-04 < 1.00E-04

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'XE i35 Ci 1.56E-02 4.64E-02 2.63$-03 7.60E-05 < 1.00E-04 < 1.00E-04 < 1.00E-04 C 1.60E {04]

NOTE: ALL LESS THAN VALUES (<) ARE IN uCi/mi.

ATTACHMENT 2 C311-94-2021 Solid Waste Shipped Offsite During 1993

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o . I TMI-1 1/1/93 to 12/31/93 TABLE 3A ETTLLU T AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FLTL SHIPMCETS A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)

1. Type of waste UNIT h,NN hhoRk
a. 5 pent resina, zilter sluoges. s' 70 4 m3 evaoorator bottone, ere. ci 5.19 C1 5 "*
b. Dry compressible waste, contaminated m 3 544.4 m3 oc uieteen t , etc.

e4 2.4 Ci 5%

c. Irractatec components, control m*

rod s . etc. Ci N/A N/A

d. Other (describe) i N/A N/A
2. Estimate of major nuclide cotnoosition (bv type of waste) fl0TE: TOTAL CURIE
n. H3 ' QUAL:TITY AliD 77.6 a Cs137 PRif1CIPAL RADIC-7.99 Ni63 4.8 -

1:UCLIDES WERE Co58 DETERftlf:ED DY 4.63 : ESTit%TE.

b. CoS8 32.14-tsl37 27.5 -

Fe155 24.9

  • h103 0.63 :

Co60

e. 2.89 :

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3. Solid Waste Disposition
u .ber of Shionents Mode of Transoortation Destinatien See Attached for this Information
3. Irradiated Tuel Shipments (Disposition)

':u=ber of Shio=ents Mode of Transoortation Oestinaticn N/A i

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TM1-1 Effluent & Waste Disposal Annual Report ,

January 1, 1993 through December 31, 1993 l 4

A.1.a - Material Shipped as Follows: .

I Five (5) Steel Liners at 196 ft3 each - (Powdex Resin for V/R)

Three (3) Steel Liners at 191 ft3 each - (Powdex Resin for V/R)

Two (2) Steel Liners at 199 ft3 each - (Powdex Resin for V/R)

Three (3) Steel Liners at 177.9 ft3 each - (Concentrated waste -

Solidified with cement)

A.1.b Seventeen (17) Cargo Containers at 1040 ft3 each - (Non-compacted DAW l for V/R)

Six (6) Steel Boxes at 44 ft3 each - (Non-compacted Filter Cake)

One (1) Cargo Container at 1280 ft3 - (Non-compacted DAW for V/R)

A.3.a No. of Shipments Mode of Transportation Destination Seven (7) Shipments Tractor - Flatbed SEG - Oak Ridge, TN.

Two (2) Shipments Tractor - Flatbed CNSI - Barnwell, SC .

A.3.b No. of Shipments Mode of Transportation Destination Twelve (12) Shipments Tractor - Flatbed SEG - Oak Ridge, TN.

Two (2) Shipments Tractor - Flatbed CNSI - Barnwell, SC .

One (1) Shipment Tractor - Flatbed Quadrex - Oak Ridge, TN.

NOTE: All Shipments made from THI-1 were Type A - LSA.

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ATTACHMENT 3 C311-94-2021 Summary of Unplanned Releases From The THI-1 Site During 1993 As shown in Section 6 of Attachment 1, there no unplanned releases from the TMI-1 site to unrestricted areas during 1993.

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ATTACHMENT 4 C311-94-2021 Changes to the Process Control Program and  !

the Offsite Dose Calculation Manual During 1993

1. There were no changes made to the Process Control Program documents during 1993.  !
2. The Off-Site Dose Calculation Manual (ODCM) was modified four (4) times during 1993.

Revision 3 of the ODCM was issued on January 28, 1993. Revision 3 of the ODCM changed to increase the allowable release concentration for H-3 (Tritium) from the Waste Evaporator Condensate Storage Tank from 10% of the Maximum Permissible Concentration (MPC) to 20% of the MPC. This change was necessitated by the increased concentration of Tritium in the TMI-1 Reactor Coolant that resulted from the longer operating cycle (18 months as compared to the previous approximately 12 month operating cycle).

Revision 4 of the ODCM was issued on June 15, 1993. ODCM, Rev. 4 changed Radiological Environmental Monitoring Program ' requirements in Part I, Section 8 to be consistent with Draft 8 of NUREG 0472, Rev. 3, changed the required frequency of effluent reports from semi-annual to annual consistent with TMI-1 License Amendment 173 and made some minor typographical error corrections.

Revision 5 of the ODCM was issued on July 21, 1993. Revision 5 of the ODCM added certain operating and shutdown requirements related to PWD-RML-1, a radiation monitor for the TMI-2 Processed Water Disposal System, to the ODCM consistent with TMI-2 Recovery Operations Plan Change Request 47. The ,

changes related to PWD-RML-1 did not impact any portion of the ODCM related 1 to TMI-1. In addition, Revision 5 changed the approver of the ODCM from the Director, Nuclear Assurance to Rad con Director, TMI in accordance with Revision 10 of 1000-ADM-1291.01, Nuclear Safety Review and Approval Procedure for TMI-1 and Oyster Creek.

On August 2,1993 Revision 6 of the ODCM was issued. Revision 6 changed the configuration of two (2) TMI-2 radiation monitors, HP-R-219 and HP-R-219A to delete the requirement to monitor for radiciodine from TMI-2 exhaust pathways. Revision 6 to the ODCM did not impact any portion of the ODCM related to TMI-1. J

3. There were no new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part 1, Section 8.2 of the ODCM.

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ATTACHMENT 5
C311-94-2021 Instrumentation Not Returned to Operable Status Within 30 Days There was no instrumentation that was not returned to operable status within 30 days per TMI-1 Technical Specification Sections 3.21.1.b and 3.21.2.b during 1993.

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d ATTACHMENT 6 C311-94-2021 Annual Summary of Hourly Meteorological Data For 1993 i

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I THREE MILE ISLAND METEROLOGICAL DATA l JOINT FREQUENCY TABLES

! VERSION: 93.2 PRINTED 02-10-1994 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 93010100 TO 93123123 STABILITY CLASS A WIND SPEED SECTOR WINDS TO FROM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N S 10 8 10 0 0 0 28 NNE SSW 8 31 38 3 0 0 80 NE SW 22 48 31' 1 0 0 102 ENE WSW 23 29 6 0 0 0 58 E W 20 17 28 5 1 0 71 ESE WNW 25 51 46 12 4 0 138 SE NW 41 89 84 25 4 1 244 SSE NNW 43 102 41 19 8 2 215 S N 20 37 12 6 0 1 76 SSW NNE 9 1 0 0 0 0 10 SW NE 7 1 0 0 0 0 8 WSW ENE 4 11 3 1 0 0 19 W E 9 17 1 0 2 0 29 WNW ESE 5 20 13 2 0 0 40 NW SE 1 15 6 0 0 0 22 NNW SSE 1 11 6 0 0 0 18 TOTAL 248 488 325 74 19 4 1158

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

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THREE MILE ISLAND METEROLOGICAL DATA-JOINT FREQUENCY TABLES VERSION: 93.2 PRINTED 02-10-1994 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 93010100 TO 93123123 STABILITY CLASS B

! WIND SPEED

! SECTOR WINDS TO FROM 1-3 4 8-12 13-18 19-24 >24 TOTAL N S 2 10 5 1 0 0 18 NNE SSW O 18 23 1 0 0 42 NE SW 5 5 8 1 0 0 19 ENE WSW 6 3 3 1 0 0 13 E W 3 3 7 11 0 0 24 ESE WNW 12 12 15 12 3 0 54 SE NW 12 21 30 17 9 1 90 SSE NNW 7 21 20 8 7 6 69 S N O 9 8 1 2 0 20 SSW NNE O 1 1 0 0 0 2 SW NE 3 6 6 0 0 0 15 WSW ENE 2 8 1 0 0 0 11 W E 4 9 2 0 1 1 17 WNW ESE 3 8 11 1 0 0 23 NW SE 3 8 5 0 0 0 16 NNW SSE O 5 2 0 0 0 7 TOTAL 62 147 147 54 22 8 440 1

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THREE MILE ISLAND METEROLOGICAL DATA JOINT FREQUENCY TABLES VERSION: 93.2 PRINTED 02-10-1994 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 93010100 TO 93123123 STABILITY CLASS C WIND SPEED SECTOR WINDS TO FROM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL M S 0 2 5 2 0 0 9 NNE SSW 4 8 11 2 0 0 25 NE SW 3 7 5 1 0 0 ,16 ENE WSW 3 7 4 1 0 0 15 E W 2 9 5 3 0 0 19 ESE WNW 6 2 16 3 4 0 31 SE NW 4 9 14 12 7 0 46 SSE NNW 6 11 15 4 6 5 47 S N 4 5 1 1 0 0 11 SSW NNE 1 2 0 0 0 0 3 SW NE 2 6 0 0 0 0 8 WSW ENE 1 4 4 0 0 0 9 W E 2 3 8 0 1 0 14 WNW ESE 3 7 7 6 0 0 23 )

l NW SE 1 10 8 2 0 0 21 i l

NNW SSE 4 10 3 0 0 0 17 t

TOTAL 46 102 106 37 18 5 314 i

THREE MILE ISLAND METEROLOGICAL DATA'  !

JOINT FREQUENCY TABLES VERSION: 93.2 PRINTED 02-10-1994 l

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 93010100 TO 93123123 STABILITY CLASS D j l

WIND SPEED SECTOR WINDS TO FROM 1-3 4-7 8-12 13 'e 19-24 >24 TOTAL l N S 16 107 37 0 0 0 160 -

l NNE SSW 19 96 36 4 0 0 155 NE SW 18 47 16 0 0 0 81 ENE WSW 21 31 10 1 0 0 63 E W 16 75 87 36 8 0 222 ESE WNW 24 76 151 120 17 1 389 SE NW 37 82 125 114 44 7 409 l

i l SSE NNW 42 67 37 31 13 1 191 l

S N 52 83 28 15 4 0 182 SSW NNE 42 59 7 2 0 0 110 i

SW NE 52 70 10 1 0 0 133 l l l WSW ENE 50 92 37 1 1 0 181 l

W E 65 99 74 6 5 2 251 WNW ESE 39 91 119 11 3 0 263 NW SE 26 61 39 9 2 0 137 NNW SSE 21 65 22 3 0 0 111 l

TOTAL 540 1201 835 354 97 11 3038 j 1

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i i THREE MILE ISLAND METEROLOGICAL DATA l JOINT FREQUENCY TABLES i VERSION: 93.2 PRINTED 02-10-1994 l

l HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 93010100 TO 93123123 STABILITY CLASS E l

WIND SPEED SECTOR WINDS TO FROM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N S 38 94 13 1 0 0 146 NNE SSW 41 137 37 4 0 0 219 ,

NE SW 46 84 26 4 0 0 160 ENE WSW 58 86 9 2 0 0 155 E W 56 100 46 7 0 0 209 ESE WNW 71 84 52 12 2 0 221 SE NW 56 66 46 21 8 1 198 l

SSE NNW 56 75 34 31 12 3 211 S N 58 80 16 8 0 0 162 SSW NNE 42 56 4 0 0 0 102 SW NE 31 44 0 1 0 0 76 WSW ENE 34 44 3 0 0 0 81 W E 37 67 10 2 1 1 118 WNW ESE 68 47 27 5 1 0 148 ,

NW SE 44 33 12 4 1 0 94 NNW SSE 42 52 10 3 0 0 107 l

l TOTAL 778 1149 345 105 25 5 2407 s

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THREE MILE ISLAND METEROLOGICAL DATA JOINT FREQUENCY TABLES l VERSION: 93.2 PRINTED 02-10-1994 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 93010100 TO 93123123 STABILITY CLASS F WIND SPEED  ;

SECTOR WINDS )

TO FROM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N S 52 13 0 0 0 0 65 NNE SSW 38 10 1 0 0 0 49 NE SW 48 20 1 0 0 0 69 ENE WSW 44 10 2 0 0 0 56 E W 48 26 4 0 0 0 78 ESE WNW 44 19 4 0 1 0 68 SE NW 35 28 1 1 0 0 65 SSE NNW 26 44 6 2 0 0 78 S N. 30 41 5 0 0 0 76 SSW NNE 22 9 0 0 0 0 31 SW NE 22 6 0 0 0 0 28 WSW ENE 22 20 0 0 0 0 42 W E 37 16 0 0 0 0 53 WNW ESE 62 12 2 0 0 0 76 NW SE 52 10 0 0 0 0 62 NNW SSE 35 6 0 0 0 0 41 TOTAL 617 290 26 3 1 0 937

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THREE MILE ISLAND METEROLOGICAL DATA l JOINT FREQUENCY TABLES I VERSION: 93.2 PRINTED 02-10-1994 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 93010100 TO 93123123 STABILITY CLASS G WIND SPEED SECTOR WINDS TO FROM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N S 23 7 0 0 0 0 30 l I

NNE SSW 27 19 1 0 0 0 -47 NE SW 24 10 2 0 0 0 36 ENE WSW 18 4 0 0 0 0 22 i

E W 15 5 0 0 0 0 20 ESE WNW 26 9 0 0 0 0 35 SE NW 22 17 1 0 -0 0 40 SSE NNW 9 20 1 0 0 0 30 ,

S N 8 14 0 0 0 0 22 i SSW NNE 13 6 1 0 0 0 20 SW E 12 7 0 0 0 0 19 WSW ENE 10 9 0 0 0 0 19 W E 16 9 0 0 0 0 25  ;

WNW ESE 24 6 0 0 0 0 30 NW SE 20 0 0 0 0 0 20 NNW SSE 16 4 0 0 0 0 20 TOTAL 283 146 6 0 0 0 435 ll

l THREE MILE ISLAND METEROLOGICAL DATA JOINT FREQUENCY TABLES VERSION: 93.2 PRINTED 02-10-1994 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD 93010100 TO 93123123 STABILITY CLASS ALL WIND SPEED SECTOR WINDS i TO FROM 1-3 4-7 8 13-18 19-24 >24 TOTAL I l

N S 141 241 70 4 0 0 456 l NNE SSW 137 319 147 14 0 0 617 NE SW 166 221 89 7 0 0 483 ENE WSW 173 170 34 5 0 0 382 E -W 160 235 177 62 9 0 -643 ESE WNW 208 253 284 159 31 1 936 SE NW 207 312 301 190 72 10 1092 SSE NNW 189 340 154 95 46 17 841 S N 172 269 70 31 6 1 549 SSW NNE 129 134 13 2 0 0 278 SW NE 129 140 16 2 0 0 287 WSW ENE 123 188 48 2 1 0 362 W E 170 220 95 8 10 4 507 WNW ESE 204 191 179 25 4 0 603 NW SE 147 137 70 15 3 0 372 NNW SSE 119 153 43 6 0 0 321 i l

TOTAL 2574 3523 1790 627 182 33 8729 Hours of Missing / Invalid Data: 31 1

8 ATTACHMENT 7 C311-94-2021 Assessment of Radiation Doses Due to Radioactive Liquid and Gaseous Effluents Released From TMI-1 During 1993 ,

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_ ..._.,_._.__._._m,-____.m _ . _ _ . . . . . . . . _ -

TABLE 1 ,

THI-1

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR TMI-1 FROM January 1. 1993 through June 30. 1993 Estimated Location  % of Technical Applicable Dose Age Dist Dir Applicable. Specification Effluent Organ (mrem) Group (m) (toward) Limit Limits (mrem)

Ouarterly Annual Ouarterly Annual (1) Liquid Total Body 7.36E-2 Adult Receptor 1 4.91E0 2.45E0 1.5 3.0 (2) Liquid Liver 1.01E-1 Teen Receptor 1 2.02E-1 1.01E-2 5.0 10.0 '

(3) Noble Gas Air Dose 2.63E0 --- 160 WNW 5.26El 2.63E1 5.0 10.0 (gamma-mrad)

(4) Noble Gas Air Dose 2.85E0 --- 160 WNW 2.85El 1.42E1 10.0 20.0 (beta-mrad) ,

(5) Noble Gas Total Body 1.74E-1 All 580 WNW --- --- --- ---

l (6) Noble Gas Skin 3.53E-1 All 580 WNW --- --- --- ---

(7) Iodine & Thyroid 7.30E-2 Infant 580 WNW 9.73E-1 4.87E-1 7.5 15.0 Particulates

SUMMARY

OF MAXIMUM POPULATION DOSES FOR TMI-1 FROM January 1. 1993 through June 30. 1993 Estimated Applicable Population Dose Effluent Oraan foerson-rem)

! (8) Liquid Total Body 1.11E0 (9) Liquid Thyroid 1.18E0 (10) Gaseous Total Body 4.17E-1 (11) Gaseous Thyroid 8.18E-1 ,

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INTERPRETATION OF DOSE

SUMMARY

TABLE 1 Dose Summary Table 1 presents the maximum hypothetical doses to an individualand the general population resulting from the release of gaseous and liquid effluents from TMI-1 during the first half reporting period of 1993.

A. Liouid (IndividuaD  !

The first two lines present the maximum hypothetical dose to an individual. Presented are the whole body and critical organ doses.

Calculations are performed on the four age groups and eight organs recommended in Regulatory Guide 1.109. The pathways considered for ,

TMI are the consumption of drinking water and fish and standing on the i shoreline influenced by TMI effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna Riverin the vicinity of TMI. The " receptor" would be that individual who consumes water from the Susquehanna River and fish i residing in the plant discharge, while occupying an area of shoreline influenced by the plant discharge.

After calculating the doses to all age groups for all eight organs resulting l from the three pathways described above, Dose Summary Table 1 l presents the maximum whole body dose and affected age group along with the organ and associated age group that received the largest dose.

For the first half of 1993 the calculated maximum whole body dose would  ;

have been 7.36E-2 mrem to an adult.Similarly,the maximum organ dose would have been 1.01E-1 mrem to the liver of a teen.

B. Gaseous (Individual)

There are six major pathways considered in the dose calculations for gaseous efnuents. These are: (1) plume exposure, (2) inhalation, consumption of; (3) cow milk,(4) vegetables and fruits, (5) meat, and (6) standingon contaminated ground. Real-timemeteorology was usedin all dose calculations for gaseous effluents.

1 Lines 3 and 4 present the maximum plume exposure at or beyond the site boundary. The notation of " air dose"is interpreted to mean that these doses are not to an individual,but are considered to be the maximum doses that would have occurred at or beyond the site boundary. Dose Summary Table 1 presents the distance in meters to the location in the l affected sector (compass point) where the theoretical maximum plume l exposures occurred. The calculated maximum plume exposures would l have been 2.63E0 mrad and 2.85E0 mrad for gamma and beta, respectively.

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Lines 5 and 6 present the doses which could actually be received by an individualfrom the noble gas effluents for the first half of 1993. The calculated maximum whole body dose received by anyone from noble gases would have been 1.74E-1 mrem and the maximum dose to the skin would have been 3.53E-1 mrem.

l Line 7 represents the maximum exposed organ due to iodine, particulates and tritium. The dose presented in this section again reflects the .

I j maximum exposed organ for the appropriate age group.

l l The iodines, particulates and tritium released in the first half of 1993 would have resulted in a maximum dose of 7.30E-2 mrem to the thyroid of an infant residing 580 meters from the site in the WNW sector. No I other organ of any age group would have received a greater dose.

1 C. Liouid and Gaseous (Ponulation) 1 l Lines 8 - 11 present the person-rem doses resulting from the liquid and l gaseous efiluents. These doses are summed over all pathways and the  :

l affected populations. The person-rem doses from liquid efiluents are based upon the population encompassed within the region from the TMI l outfall extending down to the Chesapeake Bay. The person-rem doses from gaseous effluents are based upon the 1980 population and consider the population out to a distance of 50 miles around TML Population doses are summed over all distances and sectors to give an aggregate dose.

Based upon the calculations performed for the first half of 1993, liquid effluents resulted in a whole body population dose of 1.11E0 person-rem.

The maximum critical organ population dose from liquid efIluents was i 1.18E0 person-rem to the thyroid. Gaseous effluents resulted in a whole l l body population dose of 4.17E-1 person-rem and a maximum critical l

organ population dose of 8.18E-1 person-rem to the skin. i l

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l INTERPRETATION OF DOSE

SUMMARY

TABLE 2 Dose Summary Table 2 presents the maximum hypothetical doses to an individualand the ,

, general population resulting from the release of gaseous and liquid effluents from TMI-1 l during the second half reporting period of 1993.  ;

i A. Liouid (IndividuaD The first two lines present the maximum hypothetical dose to an individual.

Presented are the whole body and critical organ doses. Calculations are l performed on the four age groups and eight organs recommended in i Regulatory Guide 1.109. The pathways considered for TMI are the '

consumption of drinking water and fish and standing on the shoreline i influenced by TMI effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the vicinity of TMI. The " receptor" would be that individualwho consumes water from the Susquehanna River and fish residingin thL plant discharge, while occupying an area of shoreline influenced by the plant discharge.

After calculating the doses to all age groups for all eight organs resulting from the three pathways described above, Dose Summary Table 2 presents the maximum whole body dose and affected age group along with the organ and associated age group that received the largest dose.

For the second half of 1993 the calculated maximum whole body dose would have been 7.88E-1 mrem to an adult. Similarly,the maximum organ dose i would have been 1.09E0 mrem to the liver of a teen. l B. Gaseous (IndividuaD l There are six major pathways considered in the dose calculations for gaseous effluents. These are: (1) plume exposure (2) inhalation, consumption of; (3) cow milk, (4) vegetables and fruits, (5) meat, and (6) standing on contaminated ground. Real-time meteorology was used in all dose i calculations for gaseous effluents.

Lines 3 and 4 present the maximum plume exposure at or beyond the site l boundary. The notation of" air dose"is interpreted to mean that these doses '

are not to an individual,but are considered to be the maximum doses that would have occurred at or beyond the site boundary. Dose Summary Table 2 presents the distance in meters to the location in the affected sector (compass point) where the theoretical maximum plume exposures occurred.

The calculated maximum plume exposures would have been 2.47E0 mrad and 2.49E0 mrad for gamma and beta, respectively.

Lines 5 and 6 present the doses which could actually be received by an individual from the noble gas efnuents for the second half of 1993. The calculated maximum whole body dose received by anyone from noble gases would have been 1.57E-1 mrem and the maximum dose to the skin would have been 3.16E-1 mrem.

)

Line 7 represents the maximum exposed organ due to iodines, particulates and tritium. The dose presented in this section again reflects the maximum exposed organ for the appropriate age group.

The iodines, particulates and tritium released in the second half of 1993 would have resulted in a maximum dose of 2.88E-1 mrem to the thyroid of an infant residing 580 meters from the site in the WNW sector. No other organ of any age group would have received a greater dose.

C. Liauid and Gaseous (Ponulation)

Lines 8 - 11 present the person-rem doses resulting from the liquid and gaseous effluents. These doses are summed over all pathways and the affected populations. The person-rem doses from liquid effluents are based upon the population encompassed within the region from the TMI outfall extending down to the ChesapeakeBay. The person-rem doses from gaseous effluents are based upon the 1980 population and consider the population out to a distance of 50 miles around TMI. Population doses are summed over all distances and sectors to give an aggregate dose.

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Based upon the calculations performed for the second half of 1993, liquid effluents resulted in a whole body population dose of 3.15E0 person-rem.

The maximum critical organ population dose from liquid effluents was 1.90E1 person-rem to the thyroid. Gaseous effluents resulted in a whole body population dose of 5.48E-1 person-rem and a maximum critical organ population dose of 2.63E0 person-rem to the thyroid.

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TABLE 2 TMI-1 Second Half 1993 Dose Report

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR TMI-1 FROM July 1. 1993 through December 31. 1993 Estimated Location  % of Applicable Dose Age Dist Dir Applicable Limits (mrem)

Effluent Organ (mrem) Group (m) (toward) Limit 10 CFR 50 Appendix I Ouarterly Annual Ouarterly Annual (1) Liquid Total Body 7.88E-1 Adult Receptor 1 5.25El 2.63E1 1.5 3.0 (2) Liquid Liver 1.09E0 Teen Receptor 1 2.18E1 1.09El 5.0 10.0 (3) Noble Gas Air Dose 2.47E0 --- 160 WNW 4.94E1 2.47El 5.0 10.0 (gamma-mrad) 2.49E0 160 WNW 2.49El 1.24E1 10.0 20.0 (4) Noble Gas Air Dose ---

(beta-mrad)

(5) Noble Gas Total Body 1.57E-1 All 580 WNW --- --- --- ---

(6) Noble Gas Skin 3.16E-1 All 580 WNW --- --- --- ---

(7) Iodine & Thyroid 2.88E-1 Infant 580 WNW 3.84E0 1.92E0 7.5 15.0 Particulates

SUMMARY

OF MAXIMUM POPULATION DOSES FOR THI-1 FROM July 1. 1993 through December 31, 1993 Estimated Applicable Population Dose Effluent Oroan foerson-remi (8) Liquid Total Body 3.15E0 (9) Liquid Thyroid 1.90E1 (10) Gaseous Total Body 5.48E-1 (11) Gaseous Thyroid 2.63E0

INTERPRETATION OF DOSE

SUMMARY

TABLE 3 Dose Summary Table 3 presents the total maximum hypothetical doses to an individual and the general population resulting from the release of gaseous and liquid effluents from TMI-1 during 1993.

1 Liouid (Individual)

The first two lines present the maximum hypothetical dose to an individual.

Presented are the whole body and critical organ doses. Calculations are performed on the four age groups and eight organs recommended in Regulatory Guide 1.109. The pathways considered for TMI are the consumption of drinking water and fish and standing on the shoreline influenced by TMI effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the vicinity of TML The " receptor" would be that individ.alwho consumes water from the Susquehanna River and fish residingin the plant discharge, while occupying an area of shoreline influenced by the plant discharge.

After calculating the doses to all age groups for all eight organs resulting from the three pathways described above, Dose Summary Table 3 presents the maximum whole body dose and affected age group along with the organ and associated age group that received the largest dose.

For 1993 the calculated maximum whole body dose would have been 8.62E-1 mrem to an adult. Similarly, the maximum organ dose would have been 1.19E0 mrem to the liver of a teen.

B. Gaseous (Individual)

There are six major pathways consideredin the dose calculations for gaseous effluents. These are: (1) plume exposure (2) inhalation, consumption of; ( 3) cow milk, (4) vegetables and fruits, (5) meat, and (6) standing on contaminated ground. Real-time meteorology was used in all dose calculations for gaseous effluents.

Lines 3 and 4 present the maximum plume exposure at or beyond the site boundary. The notation of" air dose"is interpreted to mean that these doses are not to an individual,but are considered to be the maximum doses that would have occurred at or beyond the site boundary. Dose Summary Table 3 presents the distance in meters to the location in the affected sector (compass point) where the theoretical maximum plume exposures occurred.

The calculated maximum plume exposures would have been 5.10E0 mrad and 5.34E0 mrad for gamma and beta, respectively.  !

Lines 5 and 6 present the doses which could actually be received by an individualfrom the noble gas effluents for 1993. The calculated maximum whole body dose received by anyone from noble gases would have been j 3.31E-1 mrem and the maximum dose to the skin would have been 6.69E-1 l mrem.

Line 7 represents the maximum exposed organ due to iodines, particulates l and tritium. The dose presented in this section again reflects the maximum l exposed organ for the appropriate age group.

1 The iodines, particulates and tritium released in 1993 would have resulted in a maximum dose of 3.61E-1 mrem to the thyroid of an infant residing 580 meters from the site in the WNW sector. No other organ of any age group would have received a greater dose.

C. Liauid and Gaseous (Pon@,n)

Lines 8 - 11 present the s n-rem doses resulting from the liquid and gaseous effluents. These doses are summed over all pathways and the affected populations. The person-rem doses from liquid effluents are based upon the population encompassed within the region from the TMI outfall extending down to the ChesapeakeBay. '"he person-rem doses from gaseous effluents are based upon the 1980 popul . ,nd consider the populationout ,

to a distance of 50 miles around TMI.1 mtion doses are summed over all distances and sectors to give an aggregate dose.

Based upon the calculations performed for 1993, liquid effluents resulted in a whole body population dose of 4.26E0 person-rem. The maximum critical organ population dose from liquid effluents was 2.02E1 person-rem to the thyroid. Gaseous effluents resulted in a whole body population dose of 9.66E-1 person-rem and a maximum < N alorgan population dose of 3.36E0 person-rem to the thyroid.

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TABLE 3 TMI-1 Annual 1993 Dose ReDort

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR TMI-1 FROM January 1, 1993 through December 31. 1993 Estimated Location  % of Applicable Dose Age Dist Dir Applicable Limits (mrem)

Effluent Organ (mrem) Group (m) (toward) Limit 10 CFR 50 Appendix I Ouarterly Annual Ouarterly Annual (1) Liquid Total Body 8.62E-1 Adult Receptor 1 --- 2.87El ---

3.0 (2) Liquid Liver 1.19E0 Teen Receptor 1 ---

1.19El --- 10.0 (3) Noble Gas Air Dose 5.10E0 --- 160 WNW ---

5.10E1 ---

10.0 (gamma-mrad)

(4) Noble Gas Air Dose 5.34E0 --- 160 FNW ---

2.67El --- 20.0 (beta-mrad)

(5) Noble Gas Total Body 3.31E-1 All 580 WNW --- --- --- ---

(6) Noble Gas Skin 6.69E-1 All 580 WNW --- --- --- ---

(7) Iodine & Thyroid 3.61E-1 Infant 580 WNW ---

2.41E0 ---

15.0 Particulates

SUMMARY

OF MAXIMUM POPULATION DOSES FOR TMI-l FROM January 1. 1993 through December 31. 1993 Estimated Applicable Population Dose Effluent Orcan (Derson-rem)

(8) Liquid Total Body 4.26E0 (9) Liquid Thyroid 2.02El (10) Gaseous Total Body 9.66E-1 (11) Gaseous Thyroid 3.36E0 Annual summations may not equal the sum of each periodic report due to receptor location changes and interpolation results.

s ATTACHMENT 8

) C311-94-2021 i

Assessment of Radiation Doses From Liquid and Gaseous Effluents Releases to Members of the Public Within The TMI-l Site Boundaries During 1993 l The Offsite Dose Calculation Manual requires an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of public due to their activities inside the site boundary (figure 5.3, TMI-l Technical Specifications) during the reporting period. The public did not have unrestricted access to the TMI-l site during 1993. Therefore no assessment of this dose is applicable.

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ATTACHMENT 9 i C311-94-2021 Assessment of Radiation Dose to Most Likely Exposed Real Individual Per 40 CFR 190 The Offsite Dose Calculation Manual (0DCM) Part 3, Section 2.10 requires an annual assessment of radiation dose to the most likely exposed real individual from reactor releases and other nearby uranium fuel cycle sources (TMI Unit 2) to demonstrate compliance with 40 CFR 190 " Environmental Radiation Protection Standards for Nuclear Power Operations." The annual dose to the maximum exposed individual (regardless of age group) from gaseous and liquid effluents released from TMI-1 and TMI-2 in 1993 w>uld be no greater than 0.87 mrem to the thyroid 2

and 1.64 mrem to any other organ including the whole body. The direct radiation component was determined using the highest 1993 fenceline exposure rate as measured by a TLD. Based on the maximum exposure rate of 6.9 mr/ standard month, a person residing at the fenceline for 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> (shoreline exposure from Reg.

Guide 1.109) would have received an exposure of 0.63 mR. combining the direct l

radiation exposure (assumed to equal to dose) with the maximum organ doses from liquid and gaseous releases, the maximum potential (total) dose would have been 1.50 mrem to the thyroid and 2.27 mrem to any other organ. Both doses are well below the limits specified in 40 CFR 190.

2 The data for the TMI-2 portion of the combined Station dose is a best estimate utilizing the available station data. Analyses of a liquid sump sample and an isotopic characterization of the alpha radiation in an air particulate sample were not completed at the time of this report. The calculation of the radiation dose to the most likely exposed real individual will be updated when the analyses results are available. It is believed that the combined Station dose will not significantly change when the missing data is incorporated into the current calculation.

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