Text

1993 Annual Radioactive Effluent Release Rept for TMI-2
	ML20029D047
Person / Time
Site:	Three Mile Island
Issue date:	12/31/1993
From:	Broughton T; GENERAL PUBLIC UTILITIES CORP.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	C311-94-2062, NUDOCS 9405030329
	Download: ML20029D047 (35)
	v • d • e

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GPU Nuclear Corporation U Nuclear "n:nir" a

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

(717) 948-8005 P

April 26,1994 C311-94-2062 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Dear Sirs:

Subject:

Three Mile Island Nuclear Station, Unit 2 (TMI-2)

Operating License No. DPR-73 Docket No. 50-320 1993 Annual Radioactive Effluent Releases Report The TMI-2 Aar.nl Radioactive Effluent Peleases Report required by TMI-2 Technical Specit:= tion 6.8.1.2 and the Off-Site Dose Calculation Manual Part 3, Section 2.1 is enclosed.

h tachment I contains a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Reg.

Guide 121, Rev.1, with data summarized on a quarterly basis following the format of Appendix B thereof.

-) contains information for each type of solid waste shipped offsite j

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 shipment and solidification agent (s).

i l 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. describes any changes made during 1993 to the Process Control Program _ (PCP) documents or to the Offsite Dose Calculational Manual -(ODCM) 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. 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.

9405030329 931231 PDR ADDCK 05000320 f

R PDR GPU Nuclear Corporation is a subsidiary of General Public Utihties Cc'poration y

Document ' Control Desk C311-94-2062 Page 2 of 2 is an assessment of the radiation doses due to the radioactive liquid and gaseous. effluents released from the unit during 1993. 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. is an assessment of the radiation doses to the likely most exposed real individual from reactor releases and cther nearby uranium fuel cycle snurres 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."

A deviation from the sampling and analysis regime specified in Section 3.1.J and Table 3.1-3 of Revision 3 of the ODCM occurred during 1993.

Specifically, the tritium weekly grab samples were not obtained and the analysis of the monthly composite of the weekly grab samples for the Chemical Cleaning Building i

was not performed for the month of May,1993.

The tritium bubbler device that was placed in service at the beginning of May to continuously collect the tritium sample for the Chemical Cleaning Building was found to be dry on June 1, 1993, when it was changed out.

Since the tritium bubbler was dry, there was no sample to analyze. To compensate for the loss of this sample, and to prevent future losses, the following actions were taken:

1.

The highest monthly tritium value measured for this release pathway in 1993 was used to calculate the amount of tritium released during May.

The concentration used was 1.7E-9 uCi/cc measured in January. The monthly samples for the rest of the year ranged from <LLD to 8.8E-10 uCi/cc.

Utilizing this method provides a conservative estimate of what was released during May,1993 because an' evaluation of Chemical Cleaning Building activities determined that a greater volume of water was processed in the Chemical Cleaning Building during January, 1993 as-compared to May 1993 and the concentration of tritium per unit volume was essentially the same.

2.

The surveillance procedure for the Chemical Cleaning Building tritium sample was modified to incorporate a weekly check for proper water level in the sampler device.

Please contact Mr. John Schork, TMI Licensing at'717-948-8832 if you have any :

questions concerning this report.

Sincerely, f%

$An T.-G. Brou on Vice President and Director, TMI JSS/ emf-cc:

M. Evans - TMI Senior Resident inspector T. Martin - Regional Administrator, Region I M. Masnik - NRR TMI-2 Senior Project Manager L. Thonus.- TMI-2 Project Manager v

i

ATTACHMENT 1

'C3))-94-2062 Summary of Radioactive Liquid and Gaseous Effluents and Solid Waste Released from TMI-2

-y e-

TABLE 1 A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT-GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES i

1993 1993 1993 1993.

EST. TOTAL UNITS 1ST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER

' ERROR %

A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE Ci 4.95E-03

< LLD 3.91 E-02

<LLD 25%

l l

2. AVERAGE RELEASE RATE FOR PERIOD uCi/sec 6.37E-04 N/A 4.92E-03 N/A-

3. PERCENT OF ODCM LIMIT 1

B. LOD!NES I

' 1. TOTAL '9 DINE-131 Ci

<LLD

< LLD

<LLD

< LLD 25%-

}

i

2. AVERxGE RELEASE RATE FOR PERIOD uCi/sec N/A N/A N/A N/A

3. PERCENT OF ODCM UMIT C. PARTICULATES :

1. PARTICULATES WITH HALF-UVES

>8 DAYS Ci 1.30E-05 5.46E-02 4.53E-03 1.78E-07 25 %

2. AVERAGE RELEASE RATE FOR PERIOD uCi/sec 1.67E-06 6.94E-03 5.70E-04 2.25E-08

3. PERCENT OF ODCM UMIT

4. GROSS ALPHA RADIOACTIVITY Ci

< LLD

< LLD.

<LLD

<LLD D.' TRITIUM

1. TOTAL RELEASE Ci 7.11 E+01 5.93E+01 3.65E+01 8.29E-01 25 %

-l l

2. AVERAGE RELEASE RATE FOR PERIOD uCi/sec 9.15E+00 7.54E+00 4.59E+00 1.04E-01 1

3. PERCENT OF ODCM LIMIT

-l NUMBER OF BATCH RELEASES 1

1l 0l 1l 0l

% ODCM UMITS: USTED ON DOSE

SUMMARY

TABLE I!

l

.n

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE NUCUDES 1993 1993 1993 1993 1993 1993 1993 1993 RELEASED UNIT 1STQUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER 1STQUARTER 2ND QUARTER 3RD QUARTER 4114 QUARTER

1. FISSION GASES VMpiON-85 Ci

< LID

<t1D

<LLD 4.95E-03

<LLD 3.91 E-02

<LLD KRYPTON-8SM Ci

<tLD

<L1D

<LlD

<LLD

<LlD KRYPTON-87 Ci

<llD

<LLD

< LLC

<t1D

<L1D

<LLD

<LLD KRYPTON-88 Ci

< LID

<t1D

<LLD

<L1D XENON-133 Ci

<LLD

<LlD

<LLD

<L1D

<LLD

<LlD

<t1D

< lid XENON-135 Ci

<LLD

<L1D

<LLD

< LID

<LlD

<LLD

<L1D XENON-135M Ci

<t1D

<L1D

<t1D

<LLD

<L1D

<LLD XENON-138 Ci

<t1D

<LLD

< LLD

<L1D OTHERS (SPECIFY)

Ci

<t1D

<L1D

<t1D

< LID

<LLD

<t1D

<LLD UN! DENT 1FIED Ci

<llD

<LlD

< LID

<LLD

<L1D

<LLD

<LLD TOTAL FOR PERIOD Ci N/A N/A N/A N/A 4.95E-03 N/A 3.91E-02 N/A

2. IODINES LODINE-131 Ci

< LID

<LLD

<L1D l

<LLD

<t1D

<L1D

<LLD

<LLD IODINE-133 Ci

< LID

<LLD

<t1D

<L1D

<LLD

< L1D IODINE-135 Ci

<L1D

<t1D

<LLD

<L1D

<LLD

<Li'D TOTAL FOR PERIOD Cl N/A N/A N/A N/A N/A N/A N/A N/A

3. PARTICULATES STRONTlUM-89 Ci

<LLD

<L1D

<llD

<LLD

<t1D

<LLD

<LLD TT5DNTlUM-90 Ci 5.32E-08 4.71 E-08 1.93E-07

< LID

<LLD

<[LD CESIUM-134 Ci

_ < LID

<LLD

< LID 1.19E-07

<LLD

<LLD CESIUM-137 Ci 7.01E-07 7.91E-07 5.04E-07 5.94E-08

<t1D

<LlD

<L1D

<t1D BARtUM-LANTHANUM-140 Ci

<LLD

<L1D

<LLD

<LlD

<LLD

<LLD CARBON-14 C1 1.22E-05 5.46E-02 4.53E-03

<LLD

<[LD~

ANTlWlONY-125 Ci

<LLD

<t1D COBALT-58 Ci

<LLD

<LLD 3.44E-08

<LLD

<t1D

< LL'D

{UAiD$ Nil #i$D l

Ci i

N/A l

^~N/A-~ j

4 TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1993 1993 1993 1993 EST. TOTAL UNITS 1ST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER ERROR %

A. FISSION AND ACTIVATION PRODUCTS

'1. TOTAL RELEASES (NOT INCLUDING Ci 6.69E-06 2.22E-04 2.06E-05 5.19E-04 2.50E+01 TRITIUM, GASES, ALPHA)

2. AVERAGE DILUTED CONCENTRATION uCi/mi 5.72E-13 1.92E-11 1.57E-12 1.56E-11 DURING PERIOD

3. PERCENT OF ODCM UMIT B. TRITIUM

1. TOTAL RELEASE Ci 9.21 E-04 1.25E-02 1.77E-03 6.91 E-04 2.50E+01 l

2. AVERAGE DILUTED CONCENTRATION uCi/mi 7.88E-11 1.08E-09 1.35E-10 2.08E-11 DURING PERIOD

3. PERCENT OF ODCM UMIT C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE Ci

< LLD

<LLD

< LLD

<LLD 2.50E+01 l

2. AVERAGE DILUTED CONCENTRATION uCi/mi N/A N/A N/A N/A DURING PERIOD

~3. PERCENT OF ODCM LIMIT N/A N/A N/A N/4 D. GROSS ALPHA ACTIVITY -

l1. TOTAL RELEASE l

Ci

<LLD l

< LLD l

<LLD l

<LLD l 2.50E+01 l

'E. VOLUME OF WASTE RELEASED liters 9.73E+ 04 3.26E+05 2.49E+05 2.04E+05 1.00E+ 01 (PRIOR TO DILUTION)

IF. VOLUME OF DILUTION WATER USED l

liters l

1.17E+ 10 l 1.16E+10 l 1.31 E+10 l 3.32E+10 l 1.00E+01 l

[ NUMBER OF BATCH RELEASES I

21l 30l 54l 29l

% ODCM LIMITS: LISTED ON DOSE

SUMMARY

TABLE.

T TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT UQUID EFFLUENTS CONTINUOUS MODE BATCH MODE NUCUDES 1993 1993 1993 1993 1993 1993 1993 1993 RELEASED UNIT 1ST QUARTER 2ND QUARTER 3RD OUARTER 4TH QUARTER IST QUARTER 2ND OUARTER 3RD QUARTER 4TH OUARTER STRONTIUM-49 O-

< LLD

<LLD

<uD

<LLD

<LLD 2.01 E-04 8.32E-06 4 81E-04 STRONTIUM-90 Q

<LLD

< LLD

<LLD

<uD CESIUM-134 Cl 6.69E-06 2.08E-05 1.23E-05 3.79E-05 CESIUM-137 O

< LLD

<LLD

<LLD-

<LLD IODINE-131 Cl COBALT-58 Cl NO CONTINUOUS RELEASES

<LLD

< LLD

<tLD

<dD

<tLD

< LLD

<LLD

<tLD COBALT-60 Cl

<LLD

< LLD

<LLD

<LLD IRON-59 Ce

<LLD

< LLD ZINC-65 Cl

<LLD

<LLD MANAGAN ESE-54 Cl

<LLD

< LLD

<LLD..

< tid CHROMtUM-51 Ci

<LLD

<RD ZlRCONIUM -NIOBluid -95 Ci

< LLD

<LLD-

<LLD MOLYBDENUM-99 Ci

<tLD

< LLD

<LLD

<LLD TECHNETtUM-99M Q

<LLD

<iLD

<LLD BARIUM-LANTHANUM -140 Ci

<LLD

< LLD

< LLD CERUM-141 Ci N/A N/A N/A N/A OTHERjSPECIFY)

Cl

<LLD

< LLD UNIDENTIFIED Ci 6.69E-06 2.22E-04 2.06E-05 5.19E-04 TOTAL FOR PEROD Ci

<LLD

<LLD XENON-133 Cl

<LLD

<uD XENON-135 Cl

_ _ _ - _ _ _ _ _ - - _ _ _ _. _ - _ _ _ _ = _ _ _ _.

' ATTACHMENT 2 C311-94-2062 Solid Waste Shipped Offsite During 1993 o

i i

i-

. - - +

1 TMI-2 1/1/93 to 12/31/93 4

TABLE 3A ETTLUE:;T AND WASTE DISPOSAL ANNUAL REPORT-SOLID WASTE AND 11GADIATED TUEL S'dIPMESTS 4

A.

Solid waste shipped of f-site for burial or disposal (not irradiated fuel)

1. Type of waste 6monjh

{gjg gTAL T

UNIT y,

a. Spent resins, 211ter slunges*

4 m

7.66 m3 evaporator bottees, etc.

Ci 323.5 Ci S,e

b. Dry ce=pressible vaste, contaminated 2

m 528.3 m3 eauiement, etc.

c4 7.46 Ci 5,,

c. Irractatec components, control m'

rod s e t c.

Ci N/A N/A

d. Other (describe)

[

N/A N/A

2. Estimate of major nuclide comoosition (bv t' toe of waste) 9.

Esl37 85.04 '4 Sr90 12.11-Pml47 1.04 Rul06

.47 b.

Sr90 41.6 H3 24.5 Cs137 16.1 Ni63 d.4 Pu241 5.02 %

c.

~

2.

~

3. Solid Waste Disposition Sumber of Shioments Mode of Transportation Destinatien See Attached for this In fo rma tion 3.

Irradiated Fuel Shipments (Disposition) c=ber of Shioments Mode of Transoortation Destination N/A,

TMI-2 Effluent & Waste Disposal Annual Report January 1, 1993 through December 31, 1993 A.1.a - Material Shipped as Follows:

One (1) Cargo Steel Liner at 105 ft3 - (Resin for V/R)

One (1) Radlok 179 HIC at 115.5 ft3 - (Resin for V/R)

One (1) Enviralloy HIC at 49.9 ft3 - (Resin)

A.1.b One Hundred and Fifty Six (156) Steel Boxes at 96 ft3 each -

(Non-compacted DAW for V/R)

Two (2) Steel Boxes at 57 ft3 each - (Non-compacted DAW for V/R)

Two (2) Carbon Steel Liners at 170 ft3 each - (Non-compacted DAW)

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

One (1) Cargo Container at 640 ft3 - (Non-compacted DAW for V/R)-

One (1) Enviralloy HIC at 130.8 ft3 - (Non-compacted DAW)

One Hundred Fifty-Seven (157) Steel Drums at 7.5 ft3 each -

(Dried Solid Evaporator Waste)

A.3.a No. of Shipments Mode of Transportation Destination One (1) Shipments Tractor - Flatbed SEG - Oak Ridge, TN.

0ne (1) Shipment Tractor-Cask (CNS8-1208)

CNSI - Barnwell, SC.

A.3.b No. of Shipments Mode of Transportation Destination Nine (9) Shipments Tractor - Flatbed SEG - Oak Ridge, TN.

Two (2) Shipments Tractor - Flatbed Quadrex - Oak Ridge, TN.

One (1) Shipment Tractor - Flatbed CNSI - Barnwell, SC.

- 0ne (1) Shipment Tractor-Cask (NuPac 14/190m)

CNSI - Barnwell, SC.

Two (2) Shipment Tractor-Closed Van CNSI - Barnwell, SC.

NOTE: *This was a greater than Type A Shipment

- This was a greater than Type A-LSA Shipment All Other Shipment from THI-2 were Type A-LSA 1

4

ATTACliMENT 3

' C311-94-2062 Summary of Unplanned Releases From The TMI-2 Site During 1993 As shown in Section 6 of Attachment 1, there no unplanned releases from the TMI-2 site to unrestricted areas during 1993.

?

s P

s's

ATTACHMENT 4 C311-94-2062 i

Changes te 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 (0DCM) 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 TMI-l 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).

-i 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-l 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 4

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 THI-1 and Oyster Creek.

7 On August 2,1993 Revision 6 of the ODCM was issued. Revision _6 changed the configuration of two (2) THI-2 radiation monitors, HP-R-219 and HP-R-219A '

to delete the requirement to monitor for radioicdine. from TMI-2 exhaust pathways.

Revision 5 to the ODCM did not impact any portion of the 0DCM related to TMI-1.

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 1

of the ODCM.

l

. ATTACHMENT 5-C311-94-2062 r

Instrumentation Not Returned to. Operable Status Within 30 Days As. noted in;the TMI-l Annual Effluent Report that was submitted March 1,1994, there was no instrumentation that was not returned to operable status within 30 days per THI-l Technical Specification Sections 3.21.1.b and 3.21.2.b during 1993.

i NOTE:

This information is not pertinent to TMI-2 activities but is' provided in accordance with ODCM Part 3, Section 2.1 reporting requirements.

)

j

i ATTACHMENT 6' C311-94-2062-Annual Summary of' Hourly Meteorological Data For 1993 1

~

.]

~.

I

.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 l

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

0 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 j

ESE WNW 25 51 46 12 4

0 138 l

SE NW 41 89 84 25 4

1

'244 1

SSE NNW 43 102 41 19 8

2 215 S

N 20 37 12 6

0 1

7 16 SSW NNE 9

1 0

0 0

0 10 j

SW NE 7

1 0

0 0

0 8-

)

1 WSW ENE 4

11 3

1 0

0 19 W

E' 9

17 1

0 2

0' WNW ESE 5

20 13 2

0 0

40.

^1 NW SE 1

15 6

0 0

0 22 NNW SSE 1

11' 6

0 0

.0-18 a

TOTAL 248 488 325~

74 19 4

1158-i

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 4-7 8-12 13-18 19-24

>24 TOTAL N

S 2

10 5

1 0

0 18 NNE SSW 0

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

4 5

0 0

0 16 NNW' SSE

'O 5

2 0

0 0

7 TOTAL 62 147 147 54 22 8'

440

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 N

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

,'6 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 NW SE 1

10 8

2 0

0 21 NNW SSE 4

10 3

0 0

0 17 TOTAL 46 102 106 37 18 5

314

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 D WIND SPEED SECTOR WINDS TO FROM 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

S 16 107 37 0

0 0

160 NNE SSW 19 96 36 4

0 0

155 NE SW 18 47 16 0

0 0

'al 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 SSE NNW 42 67 37 31 13 1

191 S

N 52 83 28 15 4

0 182 SSW NNE 42 59 7

2 0

0 110 SW NE 52 70 10 1

0 0

133 WSW ENE 50 92 37 1

1 0

181 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 TOTAL 540 1201 835 354 97 11 3038

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 E 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 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 SSR 42 52 10 3

0 0

107 TOTAL 778 1149 345 105 25 5

2407 I

l l

i

i 1

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 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 G5 NNE SSW 38 10 1

0 0

0 49 NE SW 48 20 1

0 0

0

.9 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

31 SW NE 22 6

0 0

28 WSW ENE 22 20 0

0 0

0 42 W

E 37 16" * ** W" 0

0 0

53 WNW ESE 62 12 -

2' O

O O

76 NW SE 52 10 O

O O

O 62 NNW SSE 35 6

0 0

41 TOTAL 617 290 26 3

1 0

937

TNREE 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 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

30 NNE SSW 27 19 1

0 0

0 47 NE SW 24 10 2

0 0

0 36 ENE WSW 18 4

0 0

22 E

W 15 5

0 0

20 t

ESE WNW 26 9

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 SSW NNE 13 6

1 0

0 0

20 SW NE

,12 7

0 0

19 WSW ENE 10 9

0 0

19 W

E 16 9

0 0

0 0.

25 WNW ESE -

24 6

0 0

30 NW SR 20 0

0 0

20 NNW SSE 16 4

0 0

20 TOTAL 283 146 6

0 0

0 435

i l

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 ALL WIND SPEED SECTOR WINDS TO FROM 1-3 4-7 8-12 13-18 19-24

>24 TOTAL

'l N

S 141 241 70 4

0 0

456 NNE SSW 137 319 147 14 0

0 617

'l NE SW 166 221 89, 7

0 0

483 ENE WSW 173 170 34 5

0 0

382 E

-h 160 235 177 62 9

0 643 ESE WNW 202 253 284 159 31 1

936 1

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.

ll

.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 i

NNW SSE 119 153 43 6

0 0

321-TOTAL 2574 3523 1790-627 182 33 8729 Hours of Missing / Invalid Data:

31 a

j t

'~

2

.. ~..

ATTACHMENT'7

- C311-94-2062 Assessment of Radiation Doses Due to Radioactive Liquid and Gaseous Effluents Released From TMI-2 During 1993 4

I

(

j

INTERPRETATION OF DOSE SU11MARYTABLE 1 Dose Summary Table 1 presents the maximum hypothetical doses to an individualand the general population resulting from tl e release of gaseous and liquid effluents from TMI-2 during the first half reporting period of 1993.

A.

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 Riverin the vicinity of TMI. The " receptor" would be that individual who consumes water from the Susquehanna River and fish 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 organa resulting from the three pathways described above, Dose Summary Table 1 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 1.36E-3 mrem to an adult. Similarly, the maximum organ dose would have been 4.51E-3 mrem to the bone of an adult.

B.

Gaseous (Individual)

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 calculations for gwums effluents.

Lines 3 and 4 presan the mas imum 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 affected sector (compass point) where the theoretical maximum plume exposures occurred. The calculated maximum plume exposures would have been 3.23E-9 mrad and 3.66E-7 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 the first half of 1993. The calculated maximum _whole body dose received by anyone from noble gases would have been 1.96E-9 mrem and the maximum dose to the skin would have been 2.35E-7 mrem.

Line 7 represents the maximum exposed organ due to iodine, 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 first half of 1993 would have resulted in a maximum dose of 7.28E-2 mrem to the liver of a child residing 580 meters from the site in the WNW sector. No other organ of any age group would have received a greater dose.

C.

Liouid 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 Chesapeake Bay. The person-rem doses from gaseous efiluents 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.

Based upon the calculations performed for the first half of 1993, liquid effluents resulted in a whole body population dose of 2.58E-2 person-rem.

The maximum critical organ population dose from liquid effluents was 1.04E-1 person-rem to the bone. Gaseous effluents resulted in a whole body population dose of 4.84E-1 person-rem and a maximum critical organ population dose of 4.84E-1 person-rem to the liver, thyroid, kidney, lung and GILLI.

i

INTERPRETATION OF DOSE

SUMMARY

TABLE 2 Dose SummaryTable 2 presents the maximum hypothetical doses to an individualand the general population resulting from the release of gaseous and liquid effluents from TMI-2_during the second half reporting period of 1993.

A.

Lionid (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 drinkmg water and fish and standing on the shoreline influenced by TMI emuents. 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 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 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 4.18E-3 mrem to an adult. Similarly, the maximum organ dose would have been 1.47E-2 mrem to the bone of an adult.

B.

Daseous (IndividuaD There are six major pathways considered in the dose calculations for gaseous emuents.

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 doso"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 1.66E-7 mrad and 1.88E-5 mrad for gamma and beta, respectively.

g 4

Lines 5 and 6 present the doses which could actually be received by an individualfrom the noble gas effluents for the second half of 1993. The calculated maximum whole body dose received by anyone from noble gases would have been 2.76E-8 mrem and the maximum dose to the skin would have been 3.32E-6 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 releasedin the second half of 1993 would have resulted in a maximum dose of 3.33E-2 mrem to the total body of a child residing 580 meters from the site in the WNW sector. No other organ of any age group would have received a greater dose.

C.

Liould and Gaseous (Pouulation)

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 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 TMI. Population doses are summed over all distances and sectors to give an aggregate dose.

Basedupon the calculationsperformed for the second halfof 1993, liquid effluents resulted in a whole body population' dose of 8.44E-2 person-rem.

The maximum critical organ population dose from liquid effluents was 3.38E-1 person-rem to the bone. Gaseous effluents resulted in a whole body population dose of 2.59E-1 person-rem and a maximum critical organ population dose of 2.59E-1 person-rem to the liver, thyroid, kidney, lung, and GILLL

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 efHuents from TMI-2 during 1993.

A.

Liould (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 e01uents. 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 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 5.54E-3 mrem to an adult. Similarly, the maximum organ dose would have been 1.92E-2 mrem to the bone of an adult.

B.

Gaseous (Individual)

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 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 1.66E-7 mrad.

and 1.88E-5 mrad for gamma and beta, respectively.

Lines 5 and 6 present the doses which could actually be received by an individualfrom the noble gas efiluents.for 1993. The calculated maximum vhole body dose received by anyone from noble gases would have been 2.76E-8 mrem and the maximum dose to the skin would have been 3.32E-6 mrem.

1

9 INTERPRETATION OF DOSE

SUMMARY

TABLE 3 Dose Summary Table 3 preser

% total maximum hypothetical doses to an individual and the general popula 2 resulting from the release of gaseous and liqu' '

effluents from TMI-2 during 1993.

A.

Liauid (IndividuaD The first two lines present the maximum hypothetical dose to an i

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 influ mced by TMI effluents. The latter two pathways are considered to 'fe the primary recreational activities associated with the Susquehama River in the vicinity of TMI. The " receptor" would be that individual w'm consumes water from the Susquehanna River and fish 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 crgans resulting H

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 5.54E-3 mrem to an adult. Similarly,the maximum organ dose would have been 1.92E-2 mrem to the bone of an adult.

q B.

Gaseous (IndividuaD There are six major pathways considered in the dose calculations for gaseous effluents.

These am:

(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 1.66E-7 mrad and 1.88E-5 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 effluents for 1993.

The calculated maximum whole body dose received by anyone from noble gases would have been 2.76E-8 mrem and the maximum dose to the skin would have been 3.32E-6 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 1993 would have resulted in a maximum dose of 1.06E-1 mrem to the total body of a child -

residing 580 meters from the site in the WNW sector. No other organ of.

any age group would have received a greater dose.

C.

Lionid 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 afTected 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 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 TMI. Population 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 1.10E-1 person-rem. The maximum critical organ population dose from liquid effluents was 4.43E-1 person-rem to the bone. Gaseous effluents resulted in a whole body population dose of 7.44E-1 person-rem and a maximum critical organ.

population dose of 7.44E-1 person-rem to the liver, thyroid, kidney, lung, and GILLI.

1

TABLE 1 TMI-2

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR TMI-2 FROM January 1.

1993 tnrough 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 1.36E-3 Adult Receptor 1 9.07E-2 4.53E-2 1.5

-3.0 (2) Liquid Bone 4.51E-3 Adult Receptor 1 9.02E-2 4.51E-2 5.0 10.0 (3) Noble Gas Air Dose 3.23E-9 3000 E

6.46E-8 3.23E-8 5.0 10.0 (gamma-mrad)

(4) Noble Gas Air Dose 3.66E-7 3000 E

3.66E-6 1.83E-6 10.0 20.0 (beta-mrad)

(5) Noble Gas Total Body 1.96E-9 All 1100 ENE (6) Noble Gas Skin 2.35E-7 All 1100 ENE (7) Iodine &

Liver 7.28E-2 Child 580 WNW 9.71E-1 4.85E-1 7.5 15.0 Particulates

SUMMARY

OF MAXIMUM POPULATION DOSES FOR TMI-2 FROM January 1.

1993 through June 30, 1993 Estimated Applicable Population Dose Effluent Orcan toerson-rem)

(8) Liquid.

Total Body 2.58E-2 (9) Liquid Thyroid 1.04E-1 (10) Gaseous Total Body 4.84E-1 (11) Gaseous Liver, Thyroid, 4.84E-1 Kidney, Lung,

.GILLI

TABLE 2 TMI-2 Second Half 1993 Dose Report

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR THI-2 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 4.18E-3 Adult Receptor 1 2.79E-I' 1.39E-1 1.5 3.0 (2) Liquid Bone 1.47E-2 Teen Receptor 1 2.94E-1 1.47E-1 5.0 10.0 (3) Noble Gas Air Dose 1.66E-7 500 SSE 3.32E-6 1.66E-6 5.0 10.0 (gamma-mrad)

(4) Noble Gas Air Dose 1.88E-5 500 SSE 1.88E-4 9.40E-5 10.0 20.0 (beta-mrad)

(5) Noble Gas Total Body 2.76E-8 All 700 E

(6) Noble Gas Skin 3.32E-6 All 700 E

(7) Iodine &

Total Body 3.33E-2 Child 580 WNW 4.44E-1 2.22E-1 7.5 15.0 Particulates

SUMMARY

OF MAXIMUM POPULATION DOSES FOR TMI-2 FROM July 1.

1993 through December 31. 1993 Estimated Applicable Population Dose Effluent Oroan (person-rem)

(8) Liquid Total Body 8.44E-2 (9) Liquid Bone 3.38E-1 (10) Gaseous Total Body 2.59E-1 (11) Gaseous Liver,' Thyroid, 2.59E-1 Lung, Kidney, GILLI

=

s_

TABLE 3 TMI-2 Annual 1993 Dose ReDort

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR TMI-2 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 I

Ouarterly Annual Ouarterly Annual (1) Liquid Total Body 5.54E-3

. Adult Receptor 1 1.84E-3 1.5 3.0 (2) Liquid Bone 1.92E-2 Adult Receptor 1 1.92E-1 5.0 10.0 (3) Noble Gas Air Dose 1.66E-7 500 SSE 1.66E-6 5.0 10.0 (gamma-mrad)

(4) Noble Gas Air, Dose 1.88E-5 500 SSE 9.40E-5 10.0 20.0 (beta-mrad)

(5) Noble Gas Total Body 2.76E-8 All 700 E

(6) Noble Gas Skin 3.32E-6 All 700 E

(7) Iodine &

Total Body 1.06E-1 Child 580 WNW 7.07E-1 7.5 15.0 Particulates l

SUMMARY

OF MAXIMUM POPULATION DOSES FOR TMI-2 FROM January 1.

1993 through December 31. 1993 Estimated Applicable Population Dose Effluent Oroan foerson-rem)

(8) Liquid-Total Body 1.10E-1

-(9)- Liquid Bone 4.43E-1 (10} Gaseous

' Total Body 7.44E-1 (11) Gaseous Liver, Thyroid, 7.44E-1 Kidney, Lung, GILLI Annual summations may not equal the sum of each periodic report due to receptor location changes and interpolation results.

ATTACHMENT'8:

- C311-94-2062 Assessment of Radiation Doses From Liquid and Gaseous. Effluents Releases to Members of the Public

-Within The TMI-2 Site Boundaries During 1993 The Offsite Dese 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-1 Technical Specifications) during the reporting period. The public did not have unrestricted access to the TMI-2 site during 1993.

Therefore, no assessment of this dose is applicable.

e y

l 1

)

r ATTACHMENT 9 C311-94-2062 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 1) 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 TMl-1 and TMI-2' in 1993 would be no greater than 0.54 mrem to the thyroid and 1.65 mrem to any other organ sncluding 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 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 1.17 mrem to the thyroid and 2.28 mrem to any other organ.

Both doses are well below the limits specified in 40 CFR 190.

2 The data for the combined Station dose is a revision from the data reported in March,1994 with the TMI-1 Annual Effluent Report. 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 to organs other than the thyroid has been revised from the estimated value of 1.64 mrem reported in the TMI-l Annual Effluent Report to 1.65 mrem. The Total dose to the maximum exposed individual-has been revised from 2.27' mrem to 2.28 mrem. The revised doses are based on the analysis of a liquid sump sample and an isotopic characterization of the alpha radiation in an air particulate sample. This data was not available for inclusion in the THI-l Annual Effluent Report.

-A_.

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