TMI-11-058, Combined 2010 Annual Radioactive Effluent Release Report

Combined 2010 Annual Radioactive Effluent Release Report

ML11119A241
Person / Time
Site:	Three Mile Island
Issue date:	04/27/2011
From:	Libra R Exelon Nuclear
To:	Document Control Desk, NRC/FSME, Office of Nuclear Reactor Regulation
References
TMI-11-058
Download: ML11119A241 (304)

Text

Exelkn.

Three Mile Island Unit 1 Telephone 717-948-8000 Nuclear Route 441 South, P.O. Box 480 Middletown, PA 17057 April 27, 2011 TMI-1 1-058 U. S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION UNIT 1 AND UNIT 2 OPERATING LICENSE NO. DPR-50 AND POSSESSION ONLY LICENSE NO. DPR 73 DOCKET NOS. 50-289 AND 50-320 COMBINED 2010 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The 2010 Annual Radioactive Effluent Release Reports required by TMI-1 Technical Specification 6.9.4.1, TMI-2 Technical Specifications 6.8.1.2, and 6.12, and the Off-Site Dose Calculation Manual Part 4, Section 2.1, is enclosed. contains a summary of the quantities of radioactive liquid and gaseous effluents released from the site as outlined in Reg. Guide 1.21, 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 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). 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 2010 to the Process Control Program (PCP) documents or to the Offsite Dose Calculation Manual (ODCM) and a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part 3, Section 8.2, of the ODCM. reports all instrumentation not returned to operable status within 30 days per the TMI ODCM Part 1, Sections 2.1.1 .b and 2.1.2.b, and Part 2, Section 2.1.2.b.

Attachment 6 is quarterly summaries of hourly meteorological data collected for 2010 in the form of joint frequency distribution of wind speed, wind direction and atmospheric stability.

2010 Annual Radioactive Effluent Release Report for TMI TMI-1 1-058 Page 2 of 2 is an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the respective unit during 2010. 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 2010. is an assessment of the radiation doses to the most likely exposed real individual from reactor releases and other nearby uranium fuel cycle sources including doses from primary effluent pathways and direct radiation for 2010. 0 is a summation of deviations from the sampling and analysis regime specified in the ODCM for TMI-1 and TMI-2. 1 contains errata reporting for previous Annual Radiological Effluent Release Reports.

Enclosure 1 is a copy of the ODCM change for TMI's Offsite Dose Calculation Manual (ODCM), CY-TM-170-300, Revision 2, which was issued on December 14, 2010, and current as of December 31, 2010.

There was one revision made to the ODCM during 2010.

Enclosure 2 is a copy of 2008 Process Control Program change, RW-AA-100, Revision 7, which was issued on December 16, 2008.

Please contact Laura Weber at extension 717-948-8947 if you have any questions concerning this report.

Sincerely, Richard W. Libra Plant Manager RWL/Ikw Attachments/Enclosures cc: Region 1 Administrator TMI Senior Resident Inspector TMI-1 Senior Project Manager TMI-2 Project Manager GPU Nuclear Cognizant Officer Department of Environmental Protection, Bureau of Radiation Protection File 08031

2010 Annual Radioactive Effluent Release Report for TMI - Page 1 of 15 Summary of Radioactive Liquid and Gaseous Effluents Released from TMI during 2010

2010 Annual Radioactive Effluent Release Report for TMI - Page 2 of 15 TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES TMI-1

- Y I EST TOTAL UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 ERROR %

A. FISSION AND ACTIVATION GASES """ . 4."" "" .

1. Total Release Ci 9.96E-01 1.86E+00 2.18E+00 1.09E+00 25%

2. Avg release rate for period pCi/S 1.28E-01 2.37E-01 2.74E-01 1.37E-01

3. Percent of applicable limit  % ....

B. IODINES N.

1. Total Iodine 1131 Ci <LLD <LLD <LLD <LLD 25%

2. Avg release rate for period pCi/S N/A N/A N/A N/A

3. Percent of applicable limit %7....

C. PARTICULATESt~A~7 t$7

1. Part. With half-life >8 days Ci 1.OOE-06 <LLD <LLD <LLD 25%

2. Avg release rate for period pCi/S 1.29E-07 N/A N/A N/A

3. Percent of applicable limit  % ....

D. TRITIUM M .M . . .....

• ,,/ .-... 4.

1. Total Release Ci 3.48E+01 3.03E-01 3.19E+01 3.47E+01 15%

2. Avg release rate for period pCi/S 4.47E+00 3.85E+00 4.02E+00 4.36E+00

3. Percent of applicable limit  %*....

E. GROSS ALPHA >----" k>4 t <s

1. Total Release Ci <LLD <LLD <LLD <LLD 25%

2. Avg release rate for period pCi/S N/A N/A N/A N/A

3. Percent of applicable limit  % .:..

F. CARBON 14 ýiý%ý Iii, 3/4. ¶WV%% "' ýZ4%h

1. Total Release Ci 2.10E+00 2.10 E+00 2.10E+00 2.1OE+00

2. Avg release rate for period pCi/S 2.66E-01 2.66E-01 2.66E-01 2.66E-01

3. Percent of applicable limit  % * * .*

Note: Table 3 contains a listing of TMI ODCM Lower Limit of Detection (LLD).

• ODCM Limits - Listed on Dose summary Table.

• • C-14 production was estimated using EPRI Technical Report 1021106 Methodology.

2010 Annual Radioactive Effluent Release Report for TMI - Page 3 of 15 TABLE 1 B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES - BATCH MODE TMI-1 Fission Aivaion And Ase Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Activation Gasses Ar-41 Ci 5.72E-02 9.02E-02 <LLD <LLD Kr-85 Ci 1.02E-01 6.17E-01 1.09E+00 7.92E-01 Kr-85m Ci <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD Xe-131m Ci 1.01E-02 3.28E-02 3.90E-02 2.54E-02 Xe-133 Ci 8.23E-01 1.12E+00 1.04E+00 2.69E-01 Xe-133m Ci 1.70E-03 2.43E-04 5.56E-03 <LLD Xe-1 35 Ci 1.90E-03 <LLD 2.19E-04 <LLD Xe-135m Ci <LLD <LLD <LLD <LLD Xe-1 38 Ci <LLD <LLD <LLD <LLD Total Ci 9.96E-01 1.86E+00 2.18E+00 1.09E+00 Radioiodines Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 I-131 Ci <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD Total Ci N/A N/A N/A N/A Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Cr-51 Ci <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD Ag-i 1Om Ci <LLD <LLD <LLD <LLD Cs-1 34 Ci <LLD <LLD <LLD <LLD Cs-1 37 Ci <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD Total Ci N/A N/A N/A N/A Note: Table 3 contains a listing of TMI ODCM Lower Limit of Detection (LLD).

2010 Annual Radioactive Effluent Release Report for TMI - Page 4 of 15 TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES - CONTINUOUS MODE TMI-1 Fission Aivaion And Ase Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Activation Gasses Ar-41 Ci <LLD <LLD <LLD <LLD Kr-85 Ci <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD Xe-133 Ci <LLD 7.65E-04 <LLD <LLD Xe-1 35 Ci <LLD 3.83E-04 <LLD <LLD Xe-1 35m Ci <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD Total Ci N/A I115E-03 N/A N/A Radioiodines Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 1-131 Ci <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD Total Ci N/A N/A N/A N/A Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Cr-51 Ci <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD Co-57 Ci <LLD <LLD <LLD <LLD Co-58 Ci 1.OOE-06 <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD Ni-63 Ci <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD Cs-1 34 Ci <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD Ce-1 41 Ci <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD Total Ci 1.OOE-6 N/A N/A N/A Tritium Units I Quarter 1 Quarter 2 Quarter 3 Quarter 4 H3 CiT 3.48E+01I 3.03E-01 3.19E+01I 3.47E+01 Carbon 14 Units I Quarter 1 I Quarter 2 1 Quarter 3 1 Quarter 4 IC-14 Ci 2.1OE+00 2.1OE+001 2.1OE+00 2.10E+00 Note: Table 3 contains a listing of TMI ODCM Lower Limit of Detection (LLD).

2010 Annual Radioactive Effluent Release Report for TMI Attachment 1 - Page 5 of 15 TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES TMI-1 EST TOTAL UNIT QUARTER1 QUARTER 2 QUARTER3 QUARTER4 ERROR %

A. FISSION AND ACTIVATION PRODUCTS'- ... - .,..Žk.&cs.t

1. Total Release (Not incl. Tritium, gases, alpha) Ci 1.18E-05 4.34E-05 1.99E-05 8.41E-05 25%

2. Avg diluted concentration during period pCi/ml 1.71E-12 7.08E-12 2.77E-12 1.28E-11

3. Percent of applicable limit  %..

B. TRITIUM " ."-.

1. Total Release Ci 1.42E+01 1.66E+01 4.40E+01 5.39E+01 25%

2. Avg diluted concentration during period pCi/mi 2.07E-06 2.71 E-06 6.13E-06 8.23E-06

3. Percent of applicable limit  % *. * * *

-C. D-ISSO-LVED AND ENTRAINED GASES ~Y~g >

1. Total Release Ci <LLD <LLD 1.07E-04 1.20E-04 25%

2. Avg diluted concentration during period pCi/ml N/A N/A 1.49E-1 1 1.83E-11

3. Percent of applicable limit  % * *

• D. GROSS ALPHA RADIOACTIVITY __ _ ______

1. Total Release Ci <LLD <LLD ___<LLD25%

E. VOLUME OF WASTE RELEASE (PRIOR TO LITERS 1.14E+08 1.12E+08 1.16E+08 1.20E+08 10%

DILUTION)

F. VOLUME OF DILUTION WATER USED LITERS 6.88E+09 6.13E+09 7.17E+09 6.55E+09 10%

Note: Table 3 contains a listing of TMI ODCM Lower Limit of Detection (LLD).

• ODCM Limits - Listed on Dose summary Table

2010 Annual Radioactive Effluent Release Report for TMI - Page 6 of 15 TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 LIQUID EFFLUENTS - BATCH MODE TMI-1 Fission A and ivaion Prd Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Activation Products H-3 Ci 1.42E+01 1.66E+01 4.38E+01 5.38E+01 Cr-51 Ci <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD Co-58 Ci 1.13E-05 1.29E-05 <LLD 7.69E-06 Fe-59 Ci <LLD <LLD <LLD <LLD Co-60 Ci <LLD 1.24E-05 <LLD 5.10E-05 Zn-65 Ci <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD Tc-99m Ci <LLD <LLD <LLD <LLD Ag- 1O1m Ci <LLD <LLD <LLD 9.38-06 1-131 Ci <LLD <LLD <LLD <LLD Cs-1 34 Ci <LLD <LLD <LLD <LLD Cs-1 37 Ci <LLD <LLD <LLD 3.07E-06 Ba-140 Ci <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD Total Ci 1.42E+01 1.66E+01 4.38E+01 5.38E+01 Dissolved and Entrained ase Units Quarter 1 Quarter 2 Quarter 3 Entrained Gases Quarter 4 Kr-87 Ci <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD 1.07E-04 1.20E-04 Xe-1 33m Ci <LLD <LLD <LLD <LLD Xe-1 35 Ci <LLD <LLD <LLD <LLD Total Ci N/A N/A 1.07E-04 1.20E-04 Note: Table 3 contains a listing of TMI ODCM Lower Limit of Detection (LLD).

2010 Annual Radioactive Effluent Release Report for TMI - Page 7 of 15 TABLE 2C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 LIQUID EFFLUENTS - CONTINUOUS MODE TMI-1 Fission and A

ivaion Prd Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Activation Products H-3 Ci 2.81E-02 7.96E-02 1.18E-01 1.11E-01 Cr-51 Ci <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD Co-58 Ci 1.12E-08 <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD Tc-99m Ci <LLD <LLD <LLD <LLD Ag-i 1Om Ci <LLD <LLD <LLD <LLD 1-131 Ci <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD Cs-137 Ci 5.03E-07 1.81 E-05 1.99E-05 1.30E-05 Ba-140 Ci <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD Ce-1 44 Ci <LLD <LLD <LLD <LLD Total Ci 2.81E-02 7.97E-02 1.18E-01 1.11E-01 Dissolved and Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Entrained Gases Kr-87 Ci <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD Xe-1 33 Ci <LLD <LLD <LLD <LLD Xe-1 33m Ci <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD Total Ci N/A N/A N/A N/A Note: Table 3 contains a listing of TMI ODCM Lower Limit of Detection (LLD).

2010 Annual Radioactive Effluent Release Report for TMI - Page 8 of 15 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 SUPPLEMENTAL INFORMATION FACILITY: TMI UNIT 1 LICENSE: DPR 50-289

1. Regulatory Limits -- Please refer to TMI Offsite Dose Calculation Manual A. Fission and Activation Gases:

B. lodines:

C. Particulates, Half-Lives > 8 Days:

D. Liquid Effluents:

2. Maximum Effluent Concentrations -- 10 Times CFR 20, Appendix B Table II Provide the maximum effluent concentrations used in determining allowable release rates or concentrations A. Fission and Activation Gases:

B. lodines:

C. Particulates, Half-Lives > 8 Days:

D. Liquid Effluents:

3. Average Energy Provide the average energy (E-BAR) of the radionuclide mixture in releases of fission and activation gases, if applicable E-BAR = 2.31 E-01

4. Measurements and Approximations of Total Radioactivity Provide the methods to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition:

A. Fission and Activ. Gases: HPGE Spectrometry, Liquid Scintillation B. lodines: HPGE Spectrometry C. Particulates: HPGE Spectrometry, Gas Flow Proportional, Beta Spectrometry D. Liquid Effluents: HPGE Spectrometry, Liquid Scintillation E. Gross Alpha Gas Flow Proportional F. Carbon 14 Estimated using the methodology included in the EPRI Technical Report 1021106.

5. Batch Releases Provide the following information relating to batch releases of radioactive materials in liquid and gaseous effluents.

Quarter 1 Quarter 2 Quarter 3 Quarter 4 A. LIQUID (ALL TIMES IN MINUTES) . '<n"'t t

1. Number of batch releases 13 16 15 19

2. Total time period for batch releases (min) 2608 3691 3311 4671

3. Maximum time period for a batch release (min) 240 270 250 540

4. Average time period for a batch release (min) 200 230 220 245

5. Minimum time period for a batch release (min) 105 200 105 212

6. Average stream flow during periods of release of 3.26E+06 1.70E+06 3.92E+05 2.55E+06 effluent into a flowing stream (cfm)

B. GASEOUS * -*t' S'll. 5'.> MCI *: *-

1. Number of batch releases 12 6 8 5

2. Total time period for batch releases (min) 10770 8178 4707 3925

3. Maximum time period for a batch release (min) 1878 4165 840 870

4. Average time period for a batch release (min) 897 1363 588 785

5. Minimum time period for a batch release (min) 295 780 570 720

6. Abnormal Releases Quarter 1 Quarter 2 Quarter 3 Quarter 4 A. LIQUID .. *,-'jQ . . - K

1. Number of releases 3 3 3 3

2. Total activity released (curies) 1.31 E-02 1.33E-02 1.34E-02 1.34E-02 B. GASEOUS ,-'*..*. 1.4 -.. 2 <--. R

1. Number of releases 1 0 1 0

2. Total activity released (curies) 1.50E-03 0 2.20E-03 0

2010 Annual Radioactive Effluent Release Report for TMI - Page 9 of 15 TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES TMI-2 EST TOTAL UNIT QUARTER1 QUARTER 2 QUARTER 3 QUARTER 4 ERROR %

A. FISSION AND ACTIVATION GASES -"> ______ "_...._ ..

Ci N/A N/A N/A N/A 25

1. Total Release

2. Avg release rate for period pCi/S N/A N/A N/A N/A

3. Percent of applicable limit  %....

B. IODINES 11317C, N/A N/A/AN/A -25%

1. Total Iodine 1131 Ci N/A N/A N/A N/A 25%

Note: Table 3 contains a listing of TMI ODCM Lower Limit of Detection (LLD).

• ODCM Limits - Listed on Dose summary Table

2010 Annual Radioactive Effluent Release Report for TMI - Page 0 of 15 TABLE 1 B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES - BATCH MODE TMI-2 Fission Aivaion And Ase Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Activation Gasses Ar-41 Ci N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A Xe-1 35 Ci N/A N/A N/A N/A Xe-1 35m Ci N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A Total Ci N/A N/A N/A N/A Radiolodines Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 1-131 Ci N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A Total Ci N/A N/A N/A N/A Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Cr-51 Ci N/A N/A N/A N/A Mn-54 Ci N/A N/A N/A N/A Co-58 Ci N/A N/A N/A N/A Fe-59 Ci N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A Mo-99 Ci N/A N/A N/A N/A Ag-110m Ci N/A N/A N/A N/A Cs-1 34 Ci N/A N/A N/A N/A Cs-137 Ci N/A N/A N/A N/A Ba-140 Ci N/A N/A N/A N/A La-140 Ci N/A N/A N/A N/A Ce-141 Ci N/A N/A N/A N/A Ce-144 Ci N/A N/A N/A N/A Total Ci N/A N/A N/A N/A Note: Table 3 contains a listing of TMI ODCM Lower Limit of Detection (LLD).

2010 Annual Radioactive Effluent Release Report for TMI - Page 11 of 15 TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES - CONTINUOUS MODE TMI-2 Fission Aivaion And Ase Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Activation Gasses Ar-41 Ci <LLD <LLD <LLD <LLD Kr-85 Ci <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD Xe-1 35m Ci <LLD <LLD <LLD <LLD Xe-1 38 Ci <LLD <LLD <LLD <LLD Total Ci N/A N/A N/A N/A Radiolodines Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 1-131 Ci N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A Total Ci N/A N/A N/A N/A Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Cr-51 Ci <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD Ag-11Orn Ci <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD Total Ci N/A N/A N/A N/A I Tritium I Units Quarter 1 Quarter 2 Quarter 3 I Quarter 4 H3 Ci 6.16E-01 4.48E-01 1.74E-01 2.29E-01 Note: Table 3 contains a listing of TMI ODCM Lower Limit of Detection (LLD).

2010 Annual Radioactive Effluent Release Report for TMI - Page 12 of 15 TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES TMI-2 N N 9 9 EST TOTAL UNIT QUARTER1 QUARTER 2 QUARTER 3 QUARTER 4 ERROR %

A. FISSION AND ACTIVATION PRODUCTS t- 4r$?; * ..

1. Total Release (Not incl. Tritium, gases, alpha) Ci 2.61 E-06 4.26E-06 3.94E-06 3.10E-06 25%

2. Avg diluted concentration during period pCi/ml 3.80E-13 6.95E-13 5.50E-13 4.73E-13

3. Percent of applicable limit  %*....

B. TRITIUM _________".t.-, i;,. "1

1. Total Release Ci 1.26E-05 2.26E-05 1.30E-05 2.97E-06 25%

2. Avg diluted concentration during period pCi/ml 1.83E-1 2 3.68E-12 1.82E-12 4.53E-1 3

3. Percent of applicable limit  % ....

C. DISSOLVED AND ENTRAINED GASES W I *

• A

1. Total Release Ci <LED <LLD <LD <LLD 25%

2. Avg diluted concentration during period pCi/ml N/A N/A N/A N/A

3. Percent of applicable limit  % ..

• .- W'2 ;

• ZA . ____ WN. AM~fJ a~Wt F WE..

D. GROSS ALPHA RADIOACTIVITY .. .4 . . OF____ K

1. Total Release Ci <LLD <LLD <LLD <LLD 25%

E. VOLUME OF WASTE RELEASE (PRIOR TO LITERS 3.55E+03 1.73E+04 1.02E+04 3.94E+0310%

DILUTION)

N .t. & !,t- - " . . . ... . .. - "'- . . . ..

F. VOLUME OF DILUTION WATER USED LITERS 6;88E+09 6.13E+09 7.17E+09 6.55E+09 10%

Note: Table 3 contains a listing of TMI ODCM Lower Limit of Detection (LLD).

• ODCM Limits - Listed on Dose summary Table

2010 Annual Radioactive Effluent Release Report for TMI - Page 13 of 15 TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 LIQUID EFFLUENTS - BATCH MODE TMI-2 Fission A and ivaion Prd Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Activation Products H-3 Ci 1.26E-05 2.26E-05 1.30E-05 2.97E-06 Cr-51 Ci <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD 5.63E-07 <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD rc-99m Ci <LLD <LLD <LLD <LLD Ag-110m Ci -LLD <LLD <LLD <LLD 1-131 Ci <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD .<LLD <LLD Cs-1 37 Ci 2.61 E-06 3.70E-06 3.94E-06 3.1OE-06 Ba-140 Ci <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD Total Ci 1.52E-05 2.68E-05 1.70E-05 6.07E-06 Dissolved Entrained and ase Units Quarter 1 Quarter 2 Quarter 3 Entrained Gases Quarter 4 Kr-87 Ci <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD Xe-133m Ci <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD Total Ci N/A N/A N/A N/A Note: Table 3 contains a listing of TMI ODCM Lower Limit of Detection (LLD).

ND - Not Detected

2010 Annual Radioactive Effluent Release Report for TMI - Page 14 of 15 TABLE 2C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2010 LIQUID EFFLUENTS - CONTINUOUS MODE TMI-2 Fission and Aivaion Prd Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Activation Products H-3 Ci N/A N/A N/A N/A Mr-51 Ci N/A N/A N/A N/A Fn-54 Ci N/A N/A N/A N/A Fe-55 Ci N/A N/A N/A N/A Co-58 Ci N/A N/A N/A N/A Fe-59 Ci N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A Zn-65 Ci N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A Zr-95 Ci N/A N/A N/A N/A Nb-95 Ci N/A N/A N/A N/A Mo-99 Ci N/A N/A N/A N/A Tc-99m Ci N/A N/A N/A N/A Ag-131 Ci N/A N/A N/A N/A C-131 Ci N/A N/A N/A N/A Cs-1 34 Ci N/A N/A N/A N/A Cs-137 Ci N/A N/A N/A N/A Ba- 140 Ci N/A N/A N/A N/A La-140 Ci N/A N/A N/A N/A Ce-141 Ci N/A N/A N/A N/A

,Ce-144 Ci N/A N/A N/A N/A Total Ci N/A N/A N/A N/A Dissolved and Entrained Gase Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Entrained Gases Kr-87 Ci N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A Xe-133m Ci N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A

,Total Ci N/A N/A N/A N/A

2010 Annual Radioactive Effluent Release Report for TMI - Page 15 of 15 TABLE 3 ODCM REQUIRED LOWER LIMIT OF DETECTION (LLD)

Gaseous Samplinq Radioisotope: LLD Value Tritium 1E-06 pCi/mI Principal Gamma Emitters Gas (Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 1E-04 pCi/ml Principal Gamma Emitters Particulate __

Mn-54 1E-11 pCi/ml Fe-59 1E-11 pCi/ml Co-58 1E-11 pCi/ml Co-60 1E-11 pCi/ml Zn-65 1E-11 pCi/ml Mo-99 1E-11 pCi/ml Cs-137 1E-11 pCi/ml Ce-141 1E-11 pCi/ml Ce-144 1E-11 pCi/ml Iodine 131 1 E-12 pCi/ml Gross Alpha 1E-11 pCi/ml Sr-89 1E-11 pCi/ml Sr-90 1E-11 pCi/ml Liquid Sampling RadioisotoDe: LLD Value Tritium 1E-05 pCi/ml Principal Gamma Emitters Mn-54 5E-07 pCi/ml Fe-59 5E-07 pCi/ml Co-58 5E-07 pCi/ml Co-60 5E-07 pCi/ml Zn-65 5E-07 pCi/ml Mo-99 5E-07 pCi/ml Cs-1 34 5E-07 pCi/ml Cs-1 37 5E-07 pCi/ml Ce-141 5E-07 pCi/ml Ce-144 5E-07 pCi/ml Iodine 131 1E-06 pCi/ml Dissolved and Entrained Gases (Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135) 1E-05 pCi/ml Fe-55 1E-06 pCi/ml Gross Alpha 1E-07 pCi/ml Sr-89 5E-08 pCi/ml Sr-90 5E-08 pCi/ml

2010 Annual Radioactive Effluent Release Report for TMI - Page I of 5 Solid Waste Shipped Offsite During 2010

2010 Annual Radioactive Effluent Release Report for TMI - Page 2 of 5 2010 TMI-1 TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)

1. Type of waste UNIT 12 Month EST. Total Period Error %

a. Spent resins, filter sludges, md N/A N/A evaporator bottoms, etc. Ci

b. Dry compressible waste, m 1050.0 m3 25%

contaminated equipment, etc. Ci 0.467 Ci

c. Irradiated components, control m N/A N/A rods, etc. Ci

d. Other (describe): N/A mo N/A N/A Ci

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

a. NA

b. Ni63 19.101%

Cs137 28.928%

Fe55 35.636%

Co60 9.551%

c. N/A

d. N/A

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination See attached for this information.

B. Irradiated Fuel Shipments (Disposition)

None Number of Shipments N/A Mode Transport IDestination

2010 Annual Radioactive Effluent Release Report for TMI - Page 3 of 5 TMI-1 WASTE SHIPPED AS FOLLOWS A.1.a None A.1.b Twenty-three (23) - Steel Cargo Containers @ 1040 ft3 each - Noncompacted DAW Seven (7) - Steel Cargo Containers @ 1040 ft3 each - Noncompacted GIC One (1) - Steel Intermodal Container @ 640 ft3 each - Concrete Rubble Seven (7) - Steel Intermodal Containers @ 640 ft3 each - Metal A.3.a None A.3.b Nine (9) Shipments Hittman Transport, Energy Solutions, Oak Ridge, TN Two (2) Shipments Hittman Transport, Energy Solutions, Oak Ridge, TN Four (4) Shipments Southern Pines Trucking, Energy Solutions, Oak Ridge, TN Two (2) Shipments Tri-State Motor Transport, Energy Solutions, Oak Ridge, TN Two (2) Shipments Hittman Transport, Energy Solutions, Gallaher Operations, Kingston, TN One (1) Shipment R & R Trucking, Energy Solutions, Gallaher Operations, Kingston, TN One (1) Shipment Southern Pines Trucking, Energy Solutions, Gallaher Operations, Kingston, TN Two (2) Shipments Tri-State Motor Transport, Energy Solutions, Gallaher Operations, Kingston, TN

2010 Annual Radioactive Effluent Release Report for TMI - Page 4 of 5 2010 TMI -2 TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid waste shipped off-site for burial or disposal (not irradiated fuel)

1. Type of waste UNIT 12 Month EST. Total Period Error %

a. Spent resins, filter sludges, m3 N/A N/A evaporator bottoms, etc. Ci

b. Dry compressible waste, m N/A N/A contaminated equipment, etc. Ci

c. Irradiated components, control m3 N/A N/A rods, etc. Ci

d. Other (describe): Mixed Waste m N/A N/A Ci

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

a. Cs137 N/A Cs134 Ni63 Fe55

b. Cs137 N/A Sr90 Ni63 Pu241

c. Ni63 N/A Co58 Fe55 Co60

d. N/A N/A

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination See attached for this information.

B. Irradiated Fuel Shipments (Disposition)

None Number of Shipments N/A Mode Transport Destination

2010 Annual Radioactive Effluent Release Report for TMI - Page 5 of 5 TMI-2 WASTE SHIPPED AS FOLLOWS A.1.a None A.1.b None A.3.a None A.3.b None

2010 Annual Radioactive Effluent Release Report for TMI Summary of Unplanned Releases from the TMI Site During 2010 There were no unplanned releases from TMI-2 in 2010. The unplanned releases for TMI-1 are summarized in the supplemental information in Attachment 1. The information is reported separately for liquid and gaseous releases, and the number of releases is reported for each quarter with a total curies released. The activity for these releases is also included in Tables 1A, 1C, 2A and 2C.

The abnormal liquid releases are monthly releases to account for the tritium in groundwater released into the river. The abnormal gaseous releases were the gaseous release during depressurization following the Integrated Leak Rate Test of the Containment Building during 1R1 8 and the steam release during the plant power reduction that occurred on September 19, 2010.

2010 Annual Radioactive Effluent Release Report for TMI CHANGES TO THE PROCESS CONTROL PROGRAM AND THE OFFSITE DOSE CALCULATION MANUAL DURING 2010 AND A LISTING OF NEW LOCATIONS FOR DOSE CALCULATIONS AND/OR ENVIRONMENTAL MONITORING IDENTIFIED BY THE LAND USE CENSUS

1. Changes to the Process Control Program There were no changes to the Process Control Program.

2. Changes to the Offsite Dose Calculation Manual There was one change to the Offsite Dose Calculation Manual. The procedure change is attached as Enclosure 1.

3. A listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census.

Based on the results of the 2010 land use census, one change was made to the Radiological Environmental Monitoring Program as required. One milk farm ceased operations in 2009 and was not included in the 2010 census. No other dairy operations located within five miles of TMINS were identified in Sector D. A New milk farm was added to the ODCM in 2010 in Sector P, Station P4-1.

2010 Annual Radioactive Effluent Release Report for TMI Instrumentation Not Returned to Operable Status Within 30 Days During 2010 There was no instrumentation not returned to operable status within 30 days per the TMI ODCM Part 1, Sections 2.1.1.b and 2.1.2.b, and Part 2, Section 2.1.2.b, during 2010.

2010 Annual Radioactive Effluent Release Report for TMI - Page 1 of 17 Annual Summary of Hourly Meteorological Data for 2010 The osprey did return and nest on the TMI meteorological tower. However, the station was able to calibrate the sensors and instrumentation before and after the osprey nested. The percent data recovery for meteorological information for 2010 was 99.1 percent. The data is presented by quarter.

2010 Annual Radioactive Effluent Release Report for TMI - Page 2 of 17 Three Mile Island Nuclear Station Period of Record: January- March 2010 Stability Class - Extremely Unstable - 15OFt-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 3 0 1 0 0 6 NNE 1 1 0 0 0 0 2 NE 0 0 0 0 0 0 0 ENE 0 3 0 0 0 0 3 E 1 6 1 0 0 0 8 ESE 1 8 11 0 0 0 20 SE 0 5 0 0 0 0 5 SSE 1 1 0 0 0 0 2 S 2 3 0 0 0 0 5 SSW 3 2 3 0 0 0 8 SW 0 3 1 1 0 0 5 WSW 1 0 1 0 0 0 2 W 1 0 13 4 0 0 18 WNW 1 1 12 12 2 0 28 NW 2 3 15 19 2 0 41 NNW 2 4 6 1 0 0 13 0 0 0 0 0 0 Variable 0 Total 18 43 63 38 4 0 166 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Three Mile Island Nuclear Station Period of Record: January - March 2010 Stability Class - Moderately Unstable - 150ht-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19 - 24 > 24 Total N 1 0 1 2 1 0 5 NNE 1 5 0 0 0 0 6 NE 0 0 0 0 0 0 0 ENE 1 0 0 0 0 0 1 E 0 2 1 0 0 0 3 ESE 1 2 3 0 0 0 6 SE 0 3 0 0 0 0 3 SSE 1 1 0 0 0 0 2 S 0 1 0 0 0 0 1 SSW 0 0 1 0 0 0 1 SW 1 1 0 0 0 2 0

WSW 0 0 1 0 0 0 1 W 0 0 12 4 0 0 16 WNW 0 1 5 12 6 0 24 NW 0 2 11 12 3 2 30 NNW 1 1 2 9 5 0 18 Variable 0 0 0 0 0 0 0 Total 7 19 37 39 15 2 119 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

2010 Annual Radioactive Effluent Release Report for TMI - Page 3 of 17 Three Mile Island Nuclear Station Period of Record: January- March 2010 Stability Class - Slightly Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19 - 24 > 24 Total N 0 0 1 0 0 0 NNE 0 1 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 1 1 0 0 0 3 ESE 0 1 0 0 0 2 SE 0 0 0 0 0 1 SSE 0 0 0 0 0 01 0 1 S 0 0 0 0 0 SSW 0 0 0 1 0 0 0 1 SW 0 0 0 0 0 0 0 WSW 1 0 0 0 1 0 0 W 0 0 3 1 1 0 8 WNW 0 5 15 4 0 24 NW 3 10 6 2 0 22 NNW 3 5 9 0 0 18 Variable 0 0 0 0 0 0 0 Total 4 13 28 31 7 0 83 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Three Mile. Island Nuclear Station Period of Record: January -March 2010 Stability Class - Neutral - 15OFt-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13- 18 19 - 24 > 24 Total N 3 29 21 6 0 0 59 NNE 4 8 5 0 0 0 17 NE 2 8 4 0 0 0 14 ENE 3 14 11 1 0 0 29 E 3 8 12 5 3 1 32 ESE 2 7 17 2 0 0 28 SE 1 5 8 1 0 0 15 SSE 0 1 1 0 0 0 2 S 1 0 1 0 0 0 2 SSW 3 3 1 0 0 0 7 SW 7 7 10 0 0 0 24 WSW 3 18 3 2 0 0 26 W 1 19 42 15 1 0 78 WNW 3 7 69 145 41 4 269 NW 3 7 73 81 24 1 189 NNW 3 10 36 55 11 0 115 Variable 0 0 0 0 0 0 0 Total 42 151 314 313 80 6 906 Hours of calm in this stability class: 3 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

2010 Annual Radioactive Effluent Release Report for TMI - Page 4 of 17 Three Mile Island Nuclear Station Period of Record: January - March 2010 Stability Class - Slightly Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13- 18 19-24 > 24 Total N 1 17 6 9 0 0 33 NNE 3 14 3 0 0 0 20 NE 3 12 2 0 0 0 17 ENE 0 13 4 1 0 0 18 E 1 13 12 15 5 1 47 ESE 4 7 14 4 0 0 29 SE 3 6 5 4 1 0 19 SSE 1 7 0 0 1 0 9 S 1 7 4 1 0 0 13 SSW 2 6 4 0 0 0 12 SW 4 9 1 1 0 0 15 WSW 4 28 4 0 0 0 36 W 5 45 42 1 0 0 93 WNW 2 19 57 13 1 0 92 NW 3 18 42 8 8 0 79 NNW 5 18 17 14 1 0 55 Variable 0 0 0 0 0 0 0 Total 42 239 217 71 17 1 587 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Three Mile Island Nuclear Station Period of Record: January- March 2010 Stability Class - Moderately Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 6 2 0 0 0 0 8 NNE 3 0 0 0 0 0 3 NE 0 1 0 0 0 0 1 ENE 3 2 0 0 0 0 5 E 3 6 0 0 0 0 9 ESE 3 3 0 0 0 0 6 SE 3 1 0 0 0 0 4 SSE 3 0 0 0 2 0 5 S 2 3 0 0 0 0 5 SSW 4 2 0 0 0 0 6 SW 4 2 0 0 0 0 6 WSW 9 9 0 1 0 0 19 W 5 9 1 0 0 0 15 WNW 5 8 0 0 0 0 13 NW 8 4 0 1 3 0 16 NNW 8 2 3 1 0 0 14 Variable 0 0 0 0 0 0 0 Total 69 54 4 3 5 0 135 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

2010 Annual Radioactive Effluent Release Report for TMI - Page 5 of 17 Three Mile Island Nuclear Station Period of Record: January- March 2010 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19 - 24 > 24 Total N 2 3 0 0 0 0 5 NNE 2 2 0 0 0 0 4 NE 2 0 0 0 0 0 2 ENE 2 1 0 0 0 0 3 E 3 0 0 0 0 0 3 ESE 9 0 0 0 0 0 9 SE 7 0 0 0 0 0 7 SSE 8 0 0 0 0 0 8 S 18 6 0 0 0 0 24 SSW 9 2 0 0 0 0 11 SW 9 6 0 0 0 0 15 WSW 12 9 0 0 0 0 21 W 11 0 0 0 0 0 11 WNW 6 3 0 0 0 0 9 NW 8 1 1 0 0 0 10 NNW 3 12 0 0 0 0 15 Variable 0 0 0 0 0 0 0 Total 111 45 1 0 0 0 157 Hours of calm in this stability class: 4 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0

2010 Annual Radioactive Effluent Release Report for TMI - Page 6 of 17 Three Mile Island Nuclear Station Period of Record: April - June 2010 Stability Class - Extremely Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19 - 24 > 24 Total N 6 3 0 0 0 0 9 NNE 1 0 0 0 0 0 1 NE 1 2 0 0 0 0 3 ENE 0 7 0 0 0 0 7 E 3 5 3 0 0 0 11 ESE 3 6 7 1 0 0 17 SE 1 7 1 0 0 0 9 SSE 2 1 2 0 0 0 5 S 2 4 1 1 0 0 8 SSW 4 23 18 1 0 0 46 SW 5 26 9 0 0 0 40 WSW 5 7 5 1 0 0 18 W 8 9 7 0 0 0 24 WNW 4 23 16 0 0 0 43 NW 10 28 10 1 0 0 49 NNW 12 20 8 0 0 0 40 Variable 0 0 0 0 0 0 0 Total 67 171 87 5 0 0 330 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 19 Three Mile Island Nuclear Station Period of Record: April - June 2010 Stability Class - Moderately Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 3 0 0 0 0 3 NNE 0 0 0 0 0 0 0 NE 1 2 0 0 0 0 3 ENE 0 0 1 0 0 0 1 E 2 1 2 0 0 0 5 ESE 1 2 1 0 0 0 4 SE 0 0 2 2 0 0 4 SSE 0 0 1 0 0 0 1 S 1 0 1 1 0 0 3 SSW 2 3 3 0 1 0 9 SW 0 6 6 0 0 0 12 WSW 0 0 2 0 0 0 2 W 1 2 5 0 0 0 8 WNW 1 4 13 10 0 0 28 NW 2 5 21 14 0 0 42 NNW 3 7 5 0 0 0 15 Variable 0 0 0 0 0 0 0 Total 14 35 63 27 1 0 140 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 19

2010 Annual Radioactive Effluent Release Report for TMI - Page 7 of 17 Three Mile Island Nuclear Station Period of Record: April - June 2010 Stability Class - Slightly Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19 - 24 > 24 Total N 0 1 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 1 1 0 0 0 0 2 ENE 0 1 0 0 0 0 1 E 0 0 0 0 0 0 0 ESE 0 0 2 0 0 0 2 SE 0 3 2 0 0 0 5 SSE 0 0 0 0 0 1 S 0 1 0 0 0 2 SSW 0 2 0 0 0 0 2 SW 3 3 6 0 0 0 12 WSW 2 0 2 0 0 0 4 W 0 0 3 2 1 0 6 WNW 2 5 11 5 2 0 25 NW 1 2 7 7 2 0 19 NNW 2 2 1 0 2 0 7 Variable 0 0 0 0 0 0 0 Total 11 22 35 14 7 0 89 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 19 Three Mile Island Nuclear Station Period of Record: April - June 2010 Stability Class - Neutral - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 1 2 1 0 0 7 NNE 0 0 0 0 0 0 0 NE 0 2 1 0 0 0 3 ENE 1 5 2 0 0 0 8 E 3 9 12 0 0 0 24 ESE 5 4 5 3 0 0 17 SE 2 3 5 1 0 0 11 SSE 0 9 3 0 0 0 12 S 2 11 5 0 0 0 18 SSW 2 8 10 3 0 0 23 SW 1 14 9 9 2 0 35 WSW 5 7 6 2 0 0 20 W 3 13 17 12 6 0 51 WNW 2 11 38 41 8 0 100 NW 3 7 21 32 5 0 68 NNW 1 7 1 7 1 0 17 Variable 0 0 0 0 0 0 0 Total 33 111 137 111 22 0 414 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 19

2010 Annual Radioactive Effluent Release Report for TMI - Page 8 of 17 Three Mile Island Nuclear Station Period of Record: April - June 2010 Stability Class - Slightly Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19 - 24 > 24 Total N 3 24 5 0 0 0 32 NNE 8 23 2 0 0 0 33 NE 7 29 0 0 0 0 36 ENE 8 18 3 0 0 0 29 E 9 19 11 0 0 0 39 ESE 10 15 25 1 0 0 51 SE 5 16 6 1 0 0 28 SSE 1 11 3 0 0 0 15 S 6 27 13 0 0 0 46 SSW 2 28 13 3 0 0 46 SW 11 41 8 2 0 0 62 WSW 8 34 3 0 1 0 46 W 9 38 12 4 0 0 63 WNW 3 29 38 13 1 0 84 NW 8 16 19 9 1 0 53 NNW 5 21 9 0 0 0 35 Variable 0 0 0 0 0 0 0 Total 103 389 170 33 3 0 698 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 19 Three Mile Island Nuclear Station Period of Record: April - June 2010 Stability Class - Moderately Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 10 1 0 0 0 14 NNE 4 7 0 0 0 0 11 NE 4 5 0 0 0 0 9 ENE 4 4 0 0 0 0 8 E 8 4 1 0 0 0 13 ESE 8 2 1 0 0 0 11 SE 9 4 0 0 0 0 13 SSE 11 7 0 0 0 0 18 S 8 12 3 0 0 0 23 SSW 8 18 4 0 0 0 30 SW 8 9 2 0 0 0 19 WSW 25 12 3 0 0 0 40 W 22 20 5 0 1 0 48 WNW 13 7 2 1 0 0 23 NW 10 6 3 0 0 0 19 NNW 5 9 2 0 0 0 16 Variable 1 0 0 0 0 0 1 Total 151 136 27 1 0 316 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 19

2010 Annual Radioactive Effluent Release Report for TMI - Page 9 of 17 Three Mile Island Nuclear Station Period of Record: April - June 2010 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 5 2 0 0 0 0 7 NNE 0 0 0 0 0 0 0 NE 2 1 0 0 0 0 3 ENE 8 1 0 0 0 0 9 E 10 0 0 0 0 0 10 ESE 5 2 0 0 0 0 7 SE 13 1 0 0 0 0 14 SSE 14 1 0 0 0 0 15 S 14 3 0 0 0 0 17 SSW 15 6 0 0 0 0 21 SW 10 4 0 0 0 0 14 WSW 13 5 0 0 0 0 18 W 3 8 0 0 0 0 11 WNW 7 0 1 0 0 0 8 NW 7 1 0 0 0 0 8 NNW 8 4 0 0 0 0 12 Variable 1 0 0 0 0 0 1 Total 135 39 1 0 0 0 175 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 19

2010 Annual Radioactive Effluent Release Report for TMI - Page 10 of 17 Three Mile Island Nuclear Station Period of Record: July - September 2010 Stability Class - Extremely Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13- 18 19 - 24 > 24 Total N 2 9 1 0 0 0 12 NNE 2 1 0 0 0 0 3 NE 0 0 0 0 0 0 0 ENE 1 2 0 0 0 0 3 E 1 2 0 0 0 0 3 ESE 1 9 5 0 0 0 15 SE 0 8 3 1 0 0 12 SSE 0 5 4 0 0 0 9 S 1 6 0 0 0 0 7 SSW 2 26 21 0 0 0 49 SW 3 15 8 0 0 0 26 WSW 7 9 5 0 0 0 21 W 9 18 9 0 0 0 36 WNW 13 32 3 0 0 0 48 NW 20 33 17 0 0 0 70 NNW 22 42 13 2 0 0 79 Variable 0 0 0 0 0 0 0 Total 84 217 89 3 0 0 393 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 28 Three Mile Island Nuclear Station Period of Record: July- September 2010 Stability Class - Moderately Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 2 0 0 0 0 4 NNE 1 1 0 0 0 0 2 NE 0 1 0 0 0 0 1 ENE 1 0 0 0 0 0 1 E 0 1 0 0 0 0 1 ESE 0 2 2 1 0 0 5 SE 0 2 5 0 0 0 7 SSE 0 2 0 0 0 0 2 S 0 1 1 1 0 0 3 SSW 0 2 6 0 0 0 8 SW 1 7 1 0 0 0 9 WSW 1 4 4 0 0 0 9 W 2 1 8 1 0 0 12 WNW 1 4 5 0 0 0 10 NW 2 6 12 3 0 0 23 NNW 4 6 8 7 0 0 25 Variable 0 0 0 0 0 0 0 Total 15 42 52 13 0 0 122 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 28

2010 Annual Radioactive Effluent Release Report for TMI - Page 11 of 17 Three Mile Island Nuclear Station Period of Record: July- September 2010 Stability Class - Slightly Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19 - 24 > 24 Total N 1 1 1 0 0 0 3 NNE 1 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 1 0 0 0 0 1 E 0 0 0 0 0 0 0 ESE 0 0 1 0 0 0 1 SE 0 0 0 0 1 1 0 SSE 0 0 0 0 1 1 0 S 0 2 0 0 0 3 SSW 1 2 2 0 0 0 5 SW 0 2 0 0 0 0 2 WSW 0 0 2 0 0 0 2 W 0 2 1 5 0 0 8 WNW 1 4 5 0 0 0 10 NW 2 0 8 5 0 0 15 NNW 1 1 3 1 0 0 6 Variable 1 0 0 0 0 0 1 Total 8 16 25 11 0 0 60 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 28 Three Mile Island Nuclear Station Period of Record: July - September 2010 Stability Class - Neutral - 15OFt-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 3 1 0 0 0 5 NNE 1 4 0 0 0 0 5 NE 0 3 0 0 0 0 3 ENE 2 6 0 0 0 0 8 E 6 6 2 0 0 0 14 ESE 3 3 3 0 0 0 9 SE 2 8 4 1 0 0 15 SSE 2 1 0 0 0 0 3 S 0 3 6 1 0 0 10 SSW 1 10 6 1 0 0 18 SW 1 15 2 0 0 0 18 WSW 3 9 5 2 0 0 19 W 2 6 8 6 1 0 23 WNW 3 8 11 3 0 0 25 NW 1 7 23 20 3 0 54 NNW 2 10 6 9 0 0 27 Variable 0 0 0 0 0 0 0 Total 30 102 77 43 4 0 256 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 28

2010 Annual Radioactive Effluent Release Report for TMI - Page 12 of 17 Three Mile Island Nuclear Station Period of Record: July - September 2010 Stability Class - Slightly Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19 - 24 > 24 Total N 4 20 11 0 0 0 35 NNE 5 12 1 0 0 0 18 NE 9 16 0 0 0 0 25 ENE 5 23 4 0 0 0 32 E 19 36 20 3 0 0 78 ESE 15 21 13 0 0 0 49 SE 10 19 13 0 0 0 42 SSE 5 33 4 0 0 0 42 S 7 38 17 4 0 0 66 SSW 9 19 11 2 0 0 41 SW 10 23 5 0 0 0 38 WSW 17 34 8 1 0 0 60 W 13 41 10 1 0 0 65 WNW 13 28 17 1 0 0 59 NW 6 24 22 7 2 0 61 NNW 5 21 29 8 0 0 63 Variable 0 0 0 0 0 0 0 Total 152 408 185 27 2 0 774 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 28 Three Mile Island Nuclear Station Period of Record: July -September 2010 Stability Class - Moderately Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 5 17 1 0 0 0 23 NNE 4 4 0 0 0 0 8 NE 3 12 0 0 0 0 15 ENE 4 7 0 0 0 0 11 E 9 14 3 0 0 0 26 ESE 15 7 3 0 0 0 25 SE 19 4 3 0 0 0 26 SSE 10 6 4 2 0 0 22 S 13 6 5 1 0 0 25 SSW 18 10 4 1 0 0 33 SW 26 7 2 0 0 0 35 WSW 24 14 0 0 0 0 38 W 18 14 1 0 0 0 33 WNW 10 6 1 0 0 0 17 NW 13 3 4 0 0 0 20 NNW 8 14 0 0 0 0 22 Variable 1 0 0 0 0 0 1 Total 200 145 31 4 0 0 380 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 28

2010 Annual Radioactive Effluent Release Report for TMI - Page 13 of 17 Three Mile Island Nuclear Station Period of Record: July- September 2010 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13- 18 19 - 24 > 24 Total N 4 2 0 0 0 0 6 NNE 3 1 0 0 0 0 4 NE 6 1 0 0 0 0 7 ENE 7 2 0 0 0 0 9 E 6 2 0 0 0 0 8 ESE 9 0 0 0 0 0 9 SE 8 0 0 0 0 0 8 SSE 5 1 0 0 0 0 6 S 11 0 0 0 0 0 11 SSW 9 3 1 0 0 0 13 SW 22 0 0 0 0 0 22 WSW 20 0 0 0 0 0 20 W 20 0 0 0 0 0 20 WNW 14 1 0 0 0 0 15 NW 18 1 0 0 0 0 19 NNW 12 4 0 0 0 0 16 Variable 0 0 0 0 0 0 0 Total 174 18 1 0 0 0 193 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 28

2010 Annual Radioactive Effluent Release Report for TMI - Page 14 of 17 Three Mile Island Nuclear Station Period of Record: October- December 2010 Stability Class - Extremely Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19 - 24 > 24 Total N 0 1 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 1 0 2 0 0 0 3 E 1 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 1 0 0 0 0 0 1 SSE 0 1 0 0 0 0 1 S 0 0 0 0 0 0 0 SSW 1 1 6 0 0 0 8 SW 0 1 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 2 2 2 1 0 0 7 WNW 1 2 3 1 0 0 7 NW 3 4 4 1 1 0 13 NNW 1 4 2 0 0 0 7 Variable 0 0 0 0 0 0 0 Total 11 16 19 3 1 0 50 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 Three Mile Island Nuclear Station Period of Record: October- December 2010 Stability Class - Moderately Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19 - 24 > 24 Total N 0 1 0 1 0 0 2 NNE 0 0 0 0 0 0 0 NE 0 0 1 0 0 0 1 ENE 0 0 3 0 0 0 3 E 0 0 0 0 0 0 0 ESE 1 1 0 0 0 0 2 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 1 3 1 0 0 0 5 SSW 0 6 1 0 0 0 7 SW 1 1 1 0 0 0 3 WSW 1 1 0 0 0 0 2 W 2 0 1 0 0 0 3 WNW 0 0 3 5 14 23 NW 1 4 2 4 6 18 NNW 1 4 0 0 2 0 7 Variable 0 0 0 0 0 0 0 Total 8 21 13 10 22 2 76 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3

2010 Annual Radioactive Effluent Release Report for TMI - Page 15 of 17 Three Mile Island Nuclear Station Period of Record: October- December 2010 Stability Class - Slightly Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 0 1 0 0 0 2 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 2 0 0 0 2 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 2 0 0 0 2 SSW 0 2 1 1 0 0 4 SW 0 1 0 0 0 0 1 WSW 2 0 0 0 0 0 2 W 0 0 1 1 2 0 4 WNW 0 1 1 6 2 0 10 NW 0 3 4 5 3 3 18 NNW 2 2 2 0 4 0 10 Variable 0 0 0 0 0 0 0 Total 5 9 14 13 11 3 55 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 Three Mile Island Nuclear Station Period of Record: October - December 2010 Stability Class - Neutral - 15OFt-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 1 4 1 0 0 9 NNE 2 0 1 0 0 0 3 NE 1 1 1 0 0 0 3 ENE 0 0 2 0 0 0 2 E 1 0 0 0 0 0 1 ESE 2 3 3 0 0 0 8 SE 3 2 0 0 0 0 5 SSE 1 6 0 0 0 0 7 S 3 3 6 1 0 0 13 SSW 2 6 3 0 0 0 11 SW 2 11 3 0 0 0 16 WSW 3 10 12 1 0 0 26 W 4 16 45 40 2 0 107 WNW 3 9 40 72 8 0 132 NW 0 12 50 90 26 10 188 NNW 3 24 20 9 3 1 60 Variable 0 0 0 0 0 0 0 Total 33 104 190 214 39 11 591 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3

2010 Annual Radioactive Effluent Release Report for TMI - Page 16 of 17 Three Mile Island Nuclear Station Period of Record: October- December 2010 Stability Class - Slightly Stable - 15OFt-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19 - 24 > 24 Total N 12 21 12 0 0 0 45 NNE 6 13 0 0 0 0 19 NE 7 13 0 0 0 0 20 ENE 4 9 2 0 0 0 15 E 6 9 8 0 0 0 23 ESE 8 12 25 4 0 0 49 SE 6 9 5 8 1 0 29 SSE 6 5 1 2 0 0 14 S 4 19 13 2 0 0 38 SSW 2 12 10 1 0 0 25 SW 11 26 2 0 1 0 40 WSW 8 39 16 8 0 0 71 W 9 41 38 6 3 0 97 WNW 5 31 69 28 4 0 137 NW 7 25 73 34 29 0 168 NNW 9 34 32 23 5 0 103 Variable 1 0 0 0 0 0 1 Total ill 318 306 116 43 0 894 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 Three Mile Island Nuclear Station Period of Record: October- December 2010 Stability Class - Moderately Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19 - 24 > 24 Total N 6 5 2 0 0 0 13 NNE 3 4 0 0 0 0 7 NE 4 2 0 0 0 0 6 ENE 4 1 0 0 0 0 5 E 5 4 0 0 0 0 9 ESE 11 5 4 4 0 0 24 SE 9 1 1 2 2 0 15 SSE 10 0 2 0 0 0 12 S 5 7 3 0 0 0 15 SSW 11 10 1 1 0 0 23 SW 14 13 2 0 0 0 29 WSW 21 20 3 0 0 0 44 W 16 6 3 1 0 0 26 WNW 6 8 3 2 0 0 19 NW 11 8 4 0 0 0 23 NNW 14 25 0 0 0 0 39 Variable 1 0 0 0 0 0 1 Total 151 119 28 10 2 0 310 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3

2010 Annual Radioactive Effluent Release Report for TMI - Page 17 of 17 Three Mile Island Nuclear Station Period of Record: October- December 2010 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 100 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13- 18 19-24 > 24 Total N 3 0 1 0 0 0 4 NNE 3 2 0 0 0 0 5 NE 1 0 0 0 0 0 1 ENE 6 0 0 0 0 0 6 E 8 0 0 0 0 0 8 ESE 12 3 0 0 0 0 15 SE 21 0 0 0 0 0 21 SSE 10 0 0 0 0 0 10 S 9 3 0 0 0 0 12 SSW 10 11 0 0 0 0 21 SW 22 0 0 1 0 0 23 WSW 10 5 0 0 0 0 15 W 10 12 0 0 0 0 22 WNW 10 2 1 0 0 0 13 NW 19 3 2 0 0 0 24 NNW 13 8 0 0 0 0 21 Variable 2 0 0 0 0 0 2 Total 169 49 4 1 0 0 223 Hours of calm in this stability class: 5 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3

2010 Annual Radioactive Effluent Release Report for TMI - Page 1 of 4 Assessment of Radiation Doses Due to Radioactive Liquid and Gaseous Effluents Released from TMI During 2010 TMI-1 The attached table presents the maximum hypothetical doses to an individual and the general population resulting from 2010 TMI-1 releases of gaseous and liquid effluents. Provided below is a brief explanation of the table.

A. Liquid (Individual)

Calculations were performed on the four age groups and seven organs recommended in Regulatory Guide 1.109. The pathways considered for TMI-1 were the consumption of drinking water and fish and standing on the shoreline influenced by TMI-1 effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the vicinity of TMI. The "critical receptor" or Receptor 1 was that individual who 1) consumed Susquehanna River water from the nearest downstream drinking water supplier (Wrightsville Water Supply), 2) consumed fish residing in the vicinity of the TMI-1 liquid discharge and 3) occupied an area of shoreline influenced by the TMI-1 liquid discharge.

For 2010 the calculated maximum whole body (or total body) dose from TMI-1 liquid effluents was 1.43E-2 mrem to an adult (line 1). The maximum organ dose was 1.50E-2 mrem to the liver of an adult (line 2).

B. Gaseous (Individual)

There were six major pathways considered in the dose calculations for TMI-1 gaseous effluents. These were: (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 is considered to be the maximum doses that would have occurred at or beyond the site boundary. The table 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 were 1.17E-4 mrad and 3.72E-4 mrad for gamma and beta, respectively.

The maximum organ dose due to the release of iodines, particulates and tritium from TMI-1 in 2010 was 1.53E-1 mrem to the bone of a child residing 2150 meters from the site in the NNE sector (line 5). This dose again reflects the maximum exposed organ for the appropriate age group.

For 2010, TMI-1 liquid and gaseous effluents resulted in maximum hypothetical doses that were a small fraction of the quarterly and yearly ODCM dose limits.

2010 Annual Radioactive Effluent Release Report for TMI - Page 2 of 4 TMI-1

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR TMI-1 FROM January 1, 2010 through December 31, 2010 ODCM Dose Dose (mrem) Ag ru it Dir  % of ODCM Dose Limit Limit (mrem)

Effluent EfletOgn Applicable Estimated AgeLocation (m) (to) Quarter Annual Quarter Annual Organ (1) Liquid Total Body 1.43E-2 Adult Receptor 1 9.53E-1 4.77E-2 1.5 3 (2) Liquid Liver 1.50E-2 Adult Receptor 1 3.OOE-1 1.50E-1 5 10 (3) Noble Gas Air Dose 1.17E-4 610 SSE 5.85E-2 1.17E-3 5 10 (gamma-mrad)

(4) Noble Gas Air Dose 3.72E-4 3000 SSE 3.72E-3 1.86E-3 10 20 (beta-mrad)

(5) Iodine, Tritium Bone 1.53E-1 Child 2150 NNE 2.04E0 1.02E0 7.5 15

& Particulates

2010 Annual Radioactive Effluent Release Report for TMI - Page 3 of 4 TMI-2 The attached table presents the maximum hypothetical doses to an individual and the general population resulting from 2010 TMI-2 releases of gaseous and liquid effluents. Provided below is a brief explanation of the table.

A. Liquid (Individual)

Calculations were performed on the four age groups and seven organs recommended in Regulatory Guide 1.109. The pathways considered for TMI-2 were the consumption of drinking water and fish and standing on the shoreline influenced by TMI-2 effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the vicinity of TMI. The "critical receptor" or Receptor 1 was that individual who 1) consumed Susquehanna River water from the nearest downstream drinking water supplier (Wrightsville Water Supply), 2) consumed fish residing in the vicinity of the TMI-2 liquid discharge and 3) occupied an area of shoreline influenced by the TMI-2 liquid discharge.

For 2010 the calculated maximum whole body (or total body) dose from TMI-2 liquid effluents was 3.04E-4 mrem to an adult (line 1). The maximum organ dose was 4.75E-4 mrem to the liver of a teen (line 2).

B. Gaseous (Individual)

There were six major pathways considered in the dose calculations for TMI-2 gaseous effluents. These were: (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.

Since there were no noble gases released from TMI-2 during 2010, the gamma and beta air doses (lines 3 and 4, respectively) were zero.

The maximum organ dose due to the release of particulates and tritium from TMI-2 in 2010 was 3.87E-5 mrem to the liver, total body, thyroid, kidney, lung, and GI tract of a child residing 2000 meters from the site in the SE sector (line 5).

For 2010, TMI-2 liquid and gaseous effluents resulted in maximum hypothetical doses that were a small fraction of the quarterly and yearly ODCM dose limits.

2010 Annual Radioactive Effluent Release Report for TMI - Page 4 of 4 TMI-2

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR TMI-2 FROM January 1. 2010 through December 31. 2010 0DCM Dose LocationDir  % of ODCM Dose Limit Limit (mrem)

Applicable Estimated Dose (mrem) Age Group Dist Effluent Organ (m) (to) Quarter Annual Quarter Annual (1) Liquid Total Body 3.04E-4 Adult Receptor 1 2.03E-2 1.01 E-2 1.5 3 (2) Liquid Liver 4.75E-4 Teen Receptor 1 9.50E-3 4.75E-3 5 10 (3) Noble Gas Air Dose 0 0 0 5 10 (gamma-mrad)

(4) Noble Gas Air Dose 0 0 0 10 20 (beta-mrad)

(5) Tritium & Liver, Total 3.87E-5 Child 2000 SE 5.16E-4 2.58E-4 7.5 15 Particulate Body, Thyroid, Kidney, Lung &

GI Tract

2010 Annual Radioactive Effluent Release Report for TMI - Page 1 of 2 Assessment of Radiation Doses from Liquid and Gaseous Effluents Releases to Members of the Public within the TMI Site Boundaries During 2010 The Offsite Dose Calculation Manual requires an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary during the reporting period. The estimated dose to a member of the public at or within the TMI Site Boundary was 0.62 mrem for 2010.

The following are the assumptions made in this assessment:

Access to the TMI Owner Controlled Area is limited to only those persons who have business related activities that support the operation of the facility. Therefore, based on the definition of a 'member of the public' in NUREG-1301, there is no credible scenario for this individual to receive non-occupational dose inside the TMI Owner Controlled Area. The scenario selected will be recreational use of the Susquehanna River and shoreline next to the Owner Controlled Area fence. Based on the two definitions of Site Boundary in the ODCM, this scenario is AT the Site Boundary for liquid releases but INSIDE the Site Boundary for gaseous releases.

A member of the public stays next to the owner controlled area for 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br />. The 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> is based upon Reg. Guide 1.109 shoreline recreation period given in Table E-5.

This is a table of recommended values to be used for the maximum exposed individual in lieu of site-specific data. Three Mile Island is co-located with other islands in the Lake Frederick area of the Susquehanna River. This area is used recreationally for boating and fishing over the summer months. The application of the 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> of recreational use from Reg. Guide 1.109 is appropriate.

The highest dose from liquid releases is characterized by the groundwater releases from the Island. These releases occur over a 31-day period. The entire dose from a monthly release will be applied to the 67-hour recreational use period. The application of the total dose from this release to 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> is conservative. The total body dose from release L201007613 was 9.OOE-4 mrem.

The highest dose from a single airborne release is characterized by release G201010556. This release was from TMI's Auxiliary and Fuel Handling Buildings ventilation system. The release contained airborne tritium from spent fuel pool evaporation. This release occurred over 167 hours0.00193 days <br />0.0464 hours <br />2.761243e-4 weeks <br />6.35435e-5 months <br />. The entire dose from this release will be applied to the 67 hour7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> recreational use period. The application of the total dose from this release to 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> is conservative. The total body dose from release G202010556 was 1.18E-03 mrem to a hypothetical receptor at the site boundary.

2010 Annual Radioactive Effluent Release Report for TMI - Page 2 of 2 The highest fenceline TLD result (assumed to be equal to dose) will be added to the dose from the highest liquid and gaseous releases to yield the hypothetical maximum dose to a member of the public within the site boundaries.

The highest fenceline TLD result for 2010 was from Station F1 -2 and was 6.6 mrem per standard month. The net TLD dose, obtained by subtracting the results from a control station TLD from the indicator results, was not used. This again is conservative.

Calculations:

6.6 mrem/std mo.

• 1/30.44 d/std mo.

• 1/24 hr/day

• 67 hr = 0.61 mrem The dose from liquid release L201007613 was 0.009 mrem.

The dose from gas release G201010556 was 0.00118 mrem.

Total Dose Calculation 0.61 mrem + 0.009 mrem + 0.00118 mrem = 0.62 mrem

2010 Annual Radioactive Effluent Release Report for TMI Assessment of Radiation Dose to Most Likely Exposed Real Individual per 40 CFR 190 Dose calculations were performed to demonstrate compliance with 40 CFR 190 (ODCM Part IV Section 2.10). Gaseous and liquid effluents released from TMI-1 and TMI-2 in 2010 resulted in maximum individual doses (regardless of age group) of 0.0554 mrem to the thyroid and 0.1686 mrem to any other organ including the whole (total) body.

The direct radiation component was determined using the highest quarterly fence-line exposure rate as measured by an environmental TLD, and subtracting from it, the lowest quarterly environmental TLD exposure rate.

Based on the maximum exposure rate of 6.6 mR/standard month, a person residing at the fence-line 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) received an exposure of 0.61 mR. Based on the lowest exposure rate of 3.4 mR/standard month and converting it by the same method yielded a background exposure of 0.31 mR.

Therefore, the net exposure from direct radiation from TMINS was 0.30 mR.

Combining the direct radiation exposure (assumed to be equal to dose) with the maximum organ doses from liquid and gaseous releases, the maximum potential (total) doses were 0.36 mrem to the thyroid and 0.47 mrem to any other organ. Both doses were well below the limits specified in 40 CFR 190.

2010 Annual Radioactive Effluent Release Report for TMI 0 Deviations From the ODCM Sampling and Analysis Regime During 2010 There were no deviations from the ODCM sampling program in 2010.

2010 Annual Radioactive Effluent Release Report for TMI 1 - Page I of 4 Errata Reporting For Previous Annual Radiological Effluent Release Reports

1. 2009 Attachment 1 Page 4 of 14, Table 1C has been updated to correct inadvertent switch of Fe-55 and Ni-63. See attached revised Table 1C with the corrections in bold.

2. 2009 Attachment 3 referenced the incorrect IR number. See attached revised Attachment 3 with the correction in bold.

3. 2008 Attachment 4 did not include reference to the detailed procedure revisions for the TMI Process Control Program. See attached revised Attachment 4 with the correction in bold and Enclosure 2.

2010 Annual Radioactive Effluent Release Report for TMI Attachment 11 - Page 2 of 4 Attachment 1 - Page 4 of 14 TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2009 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES - CONTINUOUS MODE TMI-1 Fission And Units 2009 2009 2009 2009 Activation Gasses Quarter 1 Quarter 2 Quarter 3 Quarter 4 Ar-41 Ci ND ND ND ND Kr-85 Ci ND ND ND ND Kr-85m Ci ND ND ND ND Kr-87 Ci <1.OOE-04 <1.OOE-04 <1.OOE-04 <1.OOE-04 Kr-88 Ci <1.OOE-04 <1.OOE-04 <1.OOE-04 <1.OOE-04 Xe-133 Ci <1.OOE-04 <1.OOE-04 <1.OOE-04 <1.OOE-04 Xe-135 Ci <1.OOE-04 <1.0OE-04 <1.OOE-04 1.41 E-04 Xe-135m Ci ND ND ND ND Xe-138 Ci <1.OOE-04 <1.00E-04 <1.OOE-04 <1.OOE-04 ITotal Ci N/A N/A N/A 1.41 E-04 Radiolodines Units 2009 2009 2009 2009 Quarter 1 Quarter 2 Quarter 3 Quarter 4 1-131 Ci 6.72E-07 2.72E-07 2.23E-07 1.93E-08 1-133 Ci 6.44E-06 1.83E-06 1.22E-06 ND 1-135 Ci ND ND ND ND Total Ci 7.11E-06 2.1OE-06 1.45E-06 1.93E-08 Particulates Units 2009 2009 2009 2009 P Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Cr-51 Ci ND ND ND 5.32E-04 Mn-54 Ci <1.00E-11 <1.OOE-11 <1.OOE-11 <1.OOE-11 Ci ND ND ND 5.09E-04 Fe-55 8.12E-04 Co-57 Ci ND ND ND 2.OOE-05 Co-58 Ci <1.OOE-11 <1.OOE-11 <1.OOE-11 7.73E-03 Fe-59 Ci <1.OOE-11 <1.OOE-11 <1.OOE-11 <1.OOE-11 Co-60 Ci <1.OOE-11 <1.OOE-11 <1.OOE-11 5.25E-04 Ci 8.12E-04 Ni-63 ND ND ND 5.09E-04 Sr-89 Ci <1.OOE-11 <1.OOE-11 <1.OOE-11 <1.OOE- 11 Sr-90 Ci <1.OOE-11 <1.00E-11 <1.OOE-11 <1.OOE-11 Nb-95 Ci ND ND ND 3.87E-04 Zr-95 Ci ND ND ND 2.45E-04 Mo-99 Ci <1.OOE-11 <1.O0E-11 <1.OOE-11 <1.OOE- 11 Ag-110m Ci ND ND ND ND Cs-134 Ci ND ND ND ND Cs-137 Ci <1.OOE-11 <1.OOE-11 <1.OOE-11 9.67E-05 Ba-140 Ci ND ND ND ND La-140 Ci ND ND ND ND Ce-141 Ci <1.OOE-11 <1.OOE-11 <1.OOE-11 <1.OOE- 11 Ce-144 Ci <1.OOE-11 <1.OOE-11 <1.O0E-11 <1.O0E-11 Total Ci N/A N/A N/A 1.09E-02 Note: All less than values (<) are in pCi/ml and correspond to ODCM LLDs where applicable.

ND - Not Detected

2010 Annual Radioactive Effluent Release Report for TMI 1 - Page 3 of 4 2009 Annual Radioactive Effluent Release Report for TMI TMI-1 0-031 Summary of Unplanned Releases from the TMI Site During 2009 There were no unplanned releases from TMI-2 in 2009. The unplanned releases for TMI-1 are summarized in the supplemental information in Attachment 1. The information is reported separately for liquid and gaseous releases, and the number of releases is reported for each quarter with a total curies released. The activity for these releases is also included in Tables 1A, 10C, 2A and 20.

The abnormal liquid releases are monthly releases to account for the tritium in groundwater released into the river. The abnormal gaseous releases were secondary steam leakage from relief valves and Emergency Feed Water (EFW) exhaust and releases from the construction opening created in TMI-I's Containment Building during the 1R18 Refueling Outage for steam generator replacement. A root cause investigation for the airborne release during 1R18 was performed under Issue Report 966823 996823 . The NRC conducted a special inspection for the airborne release. It is documented in NRC Inspection Report 5000289/2010007.

2010 Annual Radioactive Effluent Release Report for TMI 1 - Page 4 of 4 2008 Annual Radioactive Effluent Release Report for TMI TMI-09-047 CHANGES TO THE PROCESS CONTROL PROGRAM AND THE OFFSITE DOSE CALCULATION MANUAL DURING 2008 AND A LISTING OF NEW LOCATIONS FOR DOSE CALCULATIONS AND/OR ENVIRONMENTAL MONITORING IDENTIFIED BY THE LAND USE CENSUS

1. Changes to the Process Control Program Thcro wcrc minor I ditorial changI s to the Precess Control Program.

There was one change to the Process Control Program. The procedure change is in Enclosure 2.

2. Changes to the Offsite Dose Calculation Manual There was one change to the Offsite Dose Calculation Manual. The procedure change is attached as an attachment.

3. A listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census.

Based on the results of the 2008 land use census, no changes to the Radiological Environmental Monitoring Program are required. The garden census identified that five gardens from the 2007 census were not established in 2008. Therefore, five new gardens were identified. The locations where new gardens were identified include Sectors F (ESE), G (SE), K (SSW), M (WSW),

and Q (NW). Of the five new gardens, none were located closer to TMINS than those identified in 2007.

2010 Annual Radioactive Effluent Release Report for TMI ODCM Change For TMI Offsite Dose Calculation Manual, Revision 2 CY-TM-1 70-300 (Revision 2 was issued on December 14, 2010)

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If Yes, then attach Environmental Review dooumentat.on reMguired per EN-AA-103. ... ,

Is this a Fleet StandardDocument being processedwith form AD.AA.fO1f.1-9? NoN! or Yes "] i ye&, then aglleh Ihe letmnled form AD.AA.-O1.F0.9. skin Iho IfIlwlJing .eignn and to tn 4 innIlnuinnn A

alath - Are multiple dooumentcreatlrnslevislonsicancelatlons being Issued to add/roviselcancal them for similar requIrements? No lor Yes .lIf lYi, then Identify the highest level Uocument e*nd Issue Type below.

Cheek only one Deoument Type, [Cec only one Issue Ta: Incomorated Sits Items t"C, AR.

Level 1- Contlnuous Use Procedure N.owy IP jqjo- o_

S'18%

Level 2- Reference Use ProCedure RevlisonTuV q*7'I18 -oz Level 3- lnfonrneUon Use Procedure T&RM l CancelDocument Cancel Revision [ii on"q44t-0"3

" 9ji -0 Form Non-Permanent KIMei7 -"0 Editorial Revision I_-0 .34?..@ ,o- ...

Revision Summary: eW6, k T"-,,a. -

WAIadadditloW i5m l( 1rod)

Iecfg~ gi91M& " ndl" CONFIRM (hatgn commitments (I.e., those steps annotated with CM-X) have been changed or deleted unl -

evaluated via completionof LS-*-_,110 commitment chanoldelatlon for .nand I.N.ITIAL [Preparer]: It*rv Preparer 1/7 Validation - Is subslantlatIng thIs 4ocumaners usability via mockup, simulated performance, field walkdown, or bench top review required? No ror Yes [I If Yes. then attach validation docurentaffon.

If Yes, then print name & sign for completed validation:

NOS Review - Exduding NOE, W81.Peer Inspection or I*ndependent Verification, Is this document used to perfomi Independent Inspection for acceptance (Including field Instanllaton Inspections, fabrication Inapectons, receipt Inspections, new fuel Inspection, etc.), or for certification of Inspection personnel? No Mor Yea 03 If Yes, 4hen NOB Reviewer to print name & sign for acceptance:

Continuafton A - Is t*is a T&RM, B. Form, or EdltodelRevision? No W or Yes U] f yes, then akip the following seoolon end no Contlnualion Impact on Operating and Design Margins - NfAjor explain: -

lAflach addldcnal deBacrintfoA it teulred)

IN* ] Yes 10CFR6O.59 Applicable? TrackIng Number . .'

D'No [] Yes IPCFFR72.48 Applicable? - I-t-i7o-3ioo'

[]No J§Yes Other Regulatory Process Applicable? Other Reguislory Pmcess Number. IO *: ut.* jqeOOed f No (: Yes Potential security Impact per SY.AA.500.127? IfyYe, then geoudly Reviewer typtanoo documented by ceass dihcIplile review below a No ( Yes Surveillance Coordinator Review Required? It Yen then survellano Coordinstor Review documnted by cross discipline review below Cross Ol.selplino Review*: (lst below)

Document Site.Approval Form AD-AA-101-F-01 Page 2 of 2 Revision 3

[PORC Continuation B - Is this a T&RM, or Form? No Xor Yes [] If yes, then skip the following section and go Continuation C.

Re uired:

fNo$Yes Ifyes, then enter PORC tf if-ict L-64,- M "r(afrRCApproved):

Z ='

Plant Manager Print and Sinn (when required bvy rocedure) 0"/O-'7/0 17J-iQ9b bate' ContinuationC - Is this an EditorialRevision? No 1 or Yes El If yes, then skip the following section and go to ContinuationD.

Applicable Site Contact/Site Change Agents (SME): ,.Aekej.r

- Responsible for Change Management information in W this form or El HU-AA-1 101 Checklist (attached)

- Responsible to shepherd the document through site review, approval/authorization, and implementation.

Affected Functional Area(s) or Individuals:

Pnnt "Signature tate Affected A Print Signature Date Affected FA Print Signature Date Affected FA Attach additional if req'd Resources needed to Implement Change: !-45 (Only list, if other than Level of Effort.)

For ongoing impacts, estimate number of Full Time Equivalents (FTE). If additional resources are needed go to HU-AA-1 101.

Communication Plan: A (e.g., e-mail, Site Paper, Supervisor Briefing, Voice Mail, etc.)

Training Required / Qualifications affected: D1to El Yes If yes, list:

(e.g., Supervisory Briefing, Tailgate Briefing, Required Reading, Formal Training, recertification etc.)

Update to information infrastructure (e.g. PassPort, PIMS, EDMS workflows, or Lotus Notes, etc.) required to support implementation (including updated forms loaded into PassPort): ..P/S Records retention and document distribution requirements to be addressed with Records Management:

Continuation D - If all procedurallyrequiredactivities associatedwith this document revision have been completed and the document is ready for implementation, then SFAM to print name, sign & date for authorizationto implement.

Provide implementation date or,enter N/A then implementation will be upon the issuance by Records Management per RM requirements.Authorization below indicatesthe SFAM or a designee of the SFAM has verified the document does not alteror negatively impact compliance with regulatoryrequirementsor station commitments.

it Site Authorization:

I

. 0 S.

SFAIMIPrint and SFign

/' ok- 42=-z110 12,10 Date Imol.'

M Print and Sion SRRS Number 1B.100

EN-AA-103 Revision 3 Page 6 of 8 Attachment 1 SAMPLE - Environmental Review Checklist Page 1 of 2 Exeklon. EnvironmentalReview Checklist Nuclear Station/Unit

• Doc. No Rev. No.

Summarize Description of Proposed Activity: , I YES responses require Environmental Evaluation by Site Environmental Personnel per EN-AA-103-0001.

Does the proposed activity involve any of the following?

1. Configuration or operational changes for any system listed in Attachment 2 0] Yes 9 No

2. Removal from service of instrument air or electrical components that energize or otherwise l Yes R No affect any Priority.1 or 2 environmental equipment listed in EN-AA-103-0002

3. Increased noise levels at the site property boundary from the installation of new permanent Yes No equipment

4. Purchase, lease or sale of any land or property El Yes J No

5. Increase in the maximum reactor power level LI Yes 1 No

6. Affect operations of fish hatcheries, recreational areas, parks, or other public domains 0I Yes [] No

7. Non-editorial change to the Environmental Protection Plan or Environmental Technical 0 Yes No Specifications, NRC Operating License, Appendix B ___Yes___No

8. Oil-filled transformers or oil circuit breakers > 55 gallons in volume LI Yes

• No

9. Equipment containing PCBs LI Yes No

10. Station equipment that burns fossil fuels, i.e. internal combustion engines (gasoline or diesel), 0] Yes r No boilers, gas turbines, furnaces, heating sources, etc.

11. Chillers or refrigeration equipment containing over 50 lbs of refrigerant El Yes '9 No

12. Halon systems Ll Yes 1Q No

13. Instruments on the meteorological tower n Yes I] No

14. Vents or exhaust systems designed to exhaust vapors, fumes, mists, internal combustion engine exhaust or particulates (dusts) to the atmosphere Yes

_ _ _ _ _No

15. Tanks or tank vents that contain a chemical or fuel 0 Yes ] No

16. Cooling towers or cooling lakes Ll Yes 0 No

17. Floor drains and plumbing El Yes K No

18. Sandblasting equipment =Yes No

19. Painting operations that use more than 5,000 gallons of paint (including thinner) per year 0 Yes

20. Storm drains, ditches or swales LI Yes [* No

21. Oil separators, oil interceptors, grease traps 10 Yes M No

22. Dikes, dams or appurtenances (i.e. equipment or structures required for operation) El Yes No

23. Construction, demolition or abandon in place of any site buildings or structures 0] Yes I* No

24. Permanent or temporary storage areas for hazardous or regulated wastes J

-Yes " No

25. Chemical or oil containment or oil-filled transformer fire rock containment LI Yes No

26. Dredging or removing silt from intake structures 0 Yes K] No

EN-AA-103 Revision 3 Page 7 of 8 Attachment 1 SAMPLE - Environmental Review Checklist Page 2 of 2 Exelon,. EnvironmentalReview Checklist I Nuclear 1 1

27. Corrective maintenance WRIWO or change / deletion of preventative maintenance for Priority L- Yes j' No 1 or 2 environmental equipment listed in EN-AA-103-0002

28. Management of habitat, wildlife or vegetation (other than landscaping) on the site property, i.e. Yes &No trapping, hunting, extermination, fish electroshock, etc.

29. Temporary / portable equipment containing internal combustion engines and fuel tanks

> 55 gallons w Yes IXNo

30. Land disturbance of >1 acre (e.g. excavation, tilling, clearing away top layer of dirt for construction of building, etc.), well drilling, soil boring or change to storm water runoff, i.e. El Yes N/No more or less pavement

31. Paving of previously unpaved areas or chipping / demolition of old pavement El Yes , -No

32. Work near waterways or storm drains or work not on an impervious surface, to protect soil or Yes " No surface water, as described in EN-AA-103-0003 I

33. Friable asbestos work (non-friable gaskets, packing, etc. excluded) r- Yes U: No

34. Changes to process plant chemicals or concentrations and flow rates of existing chemicals [] Yes No

35. Increase in surface water or groundwater withdrawal or increased withdrawal pump run times -- Yes i No I

36. Increase in fossil fuel usage on site Li Yes No

37. Changes to the amountof water or effluent location discharging to the environment-1 Yes ' No

38. Changes that couldcreate a new credible mechanism for licensed material to reach Yes C9 No groundwater ___Yes____ N

39. Pesticide I herbicide application n Yes [ZN0

40. Open burning of wood, brush, weeds, oil, fossil fuels, propane, etc. Yes No

41. Maintenance on domestic water, potable water or well water systems LI Yes , No

42. Affects to Significant Environmental Aspects (SEA) Lt Yes 9 No Prepared By:

Print Name: LU,' e>1-1-,y Signature: --. NQIWA/< Date: I k1- q) 1 For any boxes checked "YES":

Environmental Personnel Contacted: Date / Time:

E] Copy of completed Attachment 1 provided to Environmental Personnel contacted.

Comments:

Exelon. CY-AA-1 70-3100 Revision 3 Page 1 of 4 Niclear ATTACHMENT 1 ODCM Change Summary Matrix Page I of 1 Item (old) (new) Determination Description of Change No. Rev. Rev. Identifier 1 2 page page No. No.

1 25 25 A Table 2.1-2 5.b action changed to 31 per lA 877896 2 55 55 A Table 3.2-1 changed LLD and gross alpha frequency to match NRC NUREG 1301 (IR877896) 3 59 59 A Section 3.2.2.6 corrected typo for units per IR998593 4 103 0-0-3" A Updated Figure 1.1 to remove U-2 CST Beand show current SNT flowpaths (IR

___ o IOY 1004299) Aa 5 185 k A Table 8.6 changed raw to surface water (SW) and finished to drinking water (DW) 9-.- &to

• ,4 be consistent with NRC NUREG 1301 terminology (IR 847641) 6 185 A Table 8.6 remove unused water station F15-1 per IR 1081894 7 186 &4iC8 A Table 8.8 remove D2-1 milk farm that closed and add P4-1 replacement (IR 11&-. _____* 976028) 8 183- 18,e A 186 180,t Update map references and delete unused stations 9 187 -FV'* A Update map 10 188 W A Updatemap 11 189 a A Updatemap ,.

- °

CY-AA-170-3100 Revision 3 Page 2 of 4 ATTACHMENT 2 ODCM Change Determination Station: Three Mile Island Page 1 of 3 ODCM Revision No. 2 Determination No. A

1. Determination Questions (Check correct response)

1. Does the ODCM change maintain the level of radioactive effluent control X YES NO required by 10CFR20.1301 ?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 10 CFR 20.1301(a)(1) requires that each licensee conduct operations so that the total effective dose equivalent to individual members of the public from TMI operation does not exceed 100 mrem in one year. Updating the tables and maps, making the tables consistent to NUREG 1301 and correcting the drawing will not increase the dose to the public or reduce TMI's ability to control or quantify releases. TMI controlled drawings already reflect the updates made to Figure 1.1, and the other updates are consistent with TMI's current sampling programs.

2. Does the ODCM change maintain the level of radioactive effluent control X YES NO required by 10CFR20.1302?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 10 CFR 20.1302 requires licensees to perform appropriate surveys in unrestricted areas and controlled areas to demonstrate compliance with dose limits for individual members of the public. The ability to perform surveys is not impacted by updating the tables and maps, making the tables consistent to NUREG 1301 and correcting the drawing. Effluent concentration limits will not be impacted by these changes. TMI will still control its effluent paths to ensure dose to the public is ALARA.

3. Does the ODCM change maintain the level of radioactive effluent control X YES NO required by 40CFR190 and 10CFR72.104?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 10CFR72.104 has requirements for Independent Spent Fuel Storage Installations (ISFSI) and Monitored Retrievable Storage (MRS) which is not applicable at TMI. 40CFR190 requires that the annual dose equivalent does not exceed 25 mrem to the whole body, 75 mrem to the thyroid and 25 mrem to any other organ of any member of the public as a result of exposure to planned discharges of radioactive materials to the environment from uranium fuel cycle operations. Updating the tables and maps, making the tables consistent to NUREG 1301 and correcting the drawing will not

CY-AA-1 70-3100 Revision 3 Page 3 of 4 ATTACHMENT 2 ODCM Change Determination increase discharges of radioactive materials nor will they negatively impact TMI's ability to control or quantify radioactive releases to the environment.

4. Does the ODCM change maintain the level of radioactive effluent control X YES NO required by 10CFR50.36a?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 10CFR 50.36a requires that operating procedures be developed and followed for the control of effluents and that the radioactive waste system be maintained and used. It also specifies that each licensee shall submit a report annually that specifies the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous effluents during the previous 12 months. These requirements will keep average annual releases of radioactive material in effluents and their resultant committed effective dose equivalents (CEDE) at small percentages of the dose limits. Operation of the rad waste system is not affected by these changes. The operation of the plant releasing and monitoring the effluents from the plant will not be impacted by updating the tables and maps, making the tables consistent to NUREG 1301 and correcting the drawing. The current practice of draining the Secondary Neutralizing Tank (SNT) provides the same level of radioactive effluent control. Since the water directed to the Turbine Building Sump is part of the continuous release composite sample, this is equivalent to the batch.

sampling process for releasing the SNT directly to the river. The revision wll not impact the annual reporting of radiological effluents to the NRC.

5. Does the ODCM change maintain the level of radioactive effluent control X YES NO required by Appendix I to 10CFR50?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change) 10CFR50 Appendix I,, Section II.A establishes the design objectives and limiting conditions for operation to meet ALARA criteria such that the calculated annual total quantity of all radioactive material above background released to unrestricted areas will not result in an estimated annual dose or dose commitment from liquid effluents in excess of 3 mrems to the total body or 10 mrems to any organ. For gaseous effluents the estimated annual air dose can not exceed 10 mrems for gamma radiation and 20 mrems for beta radiation.Section III establishes that implementation of Section IIbe demonstrated by calculational procedures based upon models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated and that the cumulative effect of all sources and pathways being influenced by the plant be considered.Section IV provides guides on limiting conditions for operation. The licensee shall establish appropriate surveillance and monitoring programs for reporting of rad effluents data, environmental monitoring data and resulting radiation doses and changes in the use of unrestricted areas surrounding the plant. If releases of effluents result in exceeding one-half the annual exposure, there are

CY-AA-170-3100 Revision 3 Page 4 of 4 ATTACHMENT 2 ODCM Change Determination investigative and reporting requirements.

Updating the tables and maps, making the tables consistent to NUREG 1301 and correcting the drawing will not impact ODCM calculations or methodologies for evaluating doses to individuals from principal pathways of exposure.

6. Does the ODCM change maintain the accuracy or reliability of effluent, dose, X YES __ NO or setpoint calculations?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change)

Updating the tables and maps, making the tables consistent to NUREG 1301 and correcting the drawing will not impact the accuracy or reliability of effluent, dose, or setpoint calculations. There are no changes to the way setpoints are being maintained.

7. Does the ODCM change maintain the accuracy of radioactive effluent control X YES __ NO required by the SAR?

Explain: (provide sufficient information including appropriate analyses justifying the ODCM change)

Chapter 11 of the UFSAR, specifically sections 11.2.4 and 11.4.3, were reviewed to determine that these ODCM changes will not impact the accuracy of radioactive effluent control required by the SAR. As stated before updating the tables and maps, making the tables consistent to NUREG 1301 and correcting the drawing will not change the release paths of effluents to the environment or any ability to control or calculate doses via these pathways.

II. If all questions are answered YES, then complete the ODCM Change Determination and implement the Change per this procedure.

I1l. If any question is answered NO, then a change to the ODCM is not permitted IV. Signoffs: See AD-AA-101-F-01

50.59 REVIEW COVERSHEET FORM LS-AA-104-1001 Revision 3 Page I of I Station/Unit(s): TMI-1 Activity/Document Number: CY-TM-170-300 Revision Number: 2

Title:

Offsite Dose Calculation Manual NOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2).

Description of Activity:

(Provide a brief, concise description of what the proposed activity involves.)

Figure 1.1 is being revised to remove pathway to U-2 CSTAand revise path from SNT. Typographical errors in Table 2.1-2 and section 3.2.2.6 are being corrected. Table 3.2-1 and Table 8.6 are being revised to be more consistent with NRC guidance. REMP tables and maps are being updated to remove unused stations as well as upgrading the maps to newer software.

Reason for Activity:

(Discuss why the proposed activity is being performed.)

Self Assessments and identification developed the changes to Figure 1.1, Table 2.1-2, 3.2-1, 8.6 and 8.8. (IRs 1004299, 877896, 847641,976028) NOS reviews and inspections identified the changes to section 3.2.2.6 and Table 8.6 (IRs 998593, 1081894)

Enhancements to the REMP tables and maps are being made to remove unused stations and upgrade the diagrams to newer software and a better layout.

Effect of Activity:

(Discuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.)

Updating Figure 1.1 will have the figure reflect the current configuration in the plant and on plant drawings. Correcting Table 2.1-2 and 3.2.2.6 will make them more accurate. Maintaining consistency with the NRC NUREG 1301 for Table 3.2-I and 8.6 will make it clearer to users and inspectors. Enhancing the REMP tables and maps will make them easier touse and will improve human performance.

Summary of Conclusion for the Activity's 50.59 Review:

(Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable, is not required.)

Per Technical Specification 6.14, ODCM changes do not require pre-NRC approval, but they do require submittal with the next annual Radiological Effluents Report to the NRC, proper justification and appropriate cross-disciplinary, RTRPSQR and PORC review.

Attachments:

Attach all 50.59 Review forms completed, as appropriate.

Forms Attached: (Check all that apply.)

X Applicability Review 50.59 Screening 50.59 Screening No. Rev.

50.59 Evaluation 50.59 Evaluation No. Rev.

LS-AA-104-1001 .FO1AA Rev 2

F Activity/Document Number:

50.59 APPLICABILITY REVIEW FORM CY-TM- 170-300 Revision Number: 2 LS-AA- 104-1002 Revision 3 Page I of I Address the questions below for all aspects of the Activity. If the answer is yes for any portion of the Activity, apply the identified process(es) to that portion of the Activity. Note that it is not unusual to have more than one process apply to a given Activity.

See Section 4 of the Resource Manual (RM) for additional guidance.

I. Does the proposed Activity involve a change:

I. Technical Specifications or Operating License (IOCFR50.90)? X NO __ YES See Section 4.2.1.1 of the RM

2. Conditions of License Quality Assurance program (IOCFR50.54(a))? X NO __ YES Security Plan (I OCFR50.54(p))? X NO __ YES See Section 4.2.1.2 of the RM Emergency Plan (IOCFR50.54(q))? X NO __ YES

3. Codes and Standards IST Program Plan (IOCFR50.55a(f))? X NO __ YES ISI Program Plan (IOCFR50.55a(g))? X NO __ YES

4. ECCS Acceptance Criteria (IOCFR50.46)? X NO __ YES See Section 4.2.1.4 of the RM

5. Specific Exemptions (IOCFR50.12)? X NO __ YES See Section 4.2.1.5 of the RM

6. Radiation Protection Program (IOCFR20)? _X NO __ YES See Section 4.2.1.6 of the RM

7. Fire Protection Program (applicable UFSAR or operating license coniton) XNO __YES See Section 4.2.1.7 of the RM condition)?

8. Programs controlled by the Operating License or the Technical NO X YES See Section 4.2.1.7 of the RM Specifications (such as the ODCM).

9. Environmental Protection Program X NO __ YES See Section 4.2.1.7 of the RM

10. Other programs controlled by other regulations. X NO __ YES See Section 4.2.1 of the RM

11. Does the proposed Activity involve maintenance which restores SSCs to their original condition or involve a temporary alteration supporting X NO YES See Section 4.2.2 of the RM maintenance that will be in effect.during at-power operations for 90 days or -

less?

Ill. Does the proposed Activity involve a change to the:

I. UFSAR (including documents incorporated by reference) that is excluded from the requirement to perform a 50.59 Review by NEI 96-07 X NO _ YES See Section 4.2.3 of the RM or NEI 98-03?

2. Managerial or administrative procedures governing the conduct of X NO YES See Section 4.2.4 of the RM facility operations (subject to the control of IOCFR50, Appendix B) -

3. Procedures for performing maintenance activities (subject to 10 CFR 50, X NO __ YES See Section 4.2.4 of the RM Appendix B)?

4. Regulatory commitment not covered by another regulation based change _X NO _ YES See Section 4.2.3/4.2.4 of the RM process (see NEI 99-04)?

IV. Does the proposed Activity involve a change to the Independent Spent Fuel - NO YES See Section 4.2.6 of the RM Storage Installation (ISFSI) (subject to control by 10 CFR 72.48) _ NO_ YES See Section 4.2.6 of the RM Check one of the following:

If all aspects of the Activity are controlled by one or more of the above processes, then a 50.59 Screening is not required and the Activity may be implemented in accordance with its governing procedure.

If any portion of the Activity is not controlled by one or more of the above processes, then process a 50.59 Screening for the portion not covered by any of the above processes. The remaining portion of the activity should be implemented in accordance with its governing procedure.

ý50.59*Screener,/5.59 Evaluator: L (-L'J'W ' Sign: J . Date:/ I?/t/ C rrcee One) (Print name) (Signature)

LS-AA-104-1002.FO1AA Rev 2

CY-TM-170-300 Revision 1 Page 25 of 208, Table 2.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNEL INSTRUMENT OPERABLE APPLICABILITY ACTION

5. Auxiliary and Fuel Handling Building Ventilation System

a. Noble Gas Activity Monitor (RM-A-8) or (RM-A-4 and RM-A-6) 1

• 27

b. Iodine Sampler (RM-A-8 or (RM-A-4 and RM-A-6) 1 * -"3

c. Particulate Sampler (RM-A-8 or (RM-A-4 and RM-A-6) 1

• 31

d. Effluent System Flow Rate Measuring Devices (FR-149 andFR-150) 1

• 26

e. Sampler Flow Rate Monitor 1

• 26

6. Fuel Handling Building ESF Air Treatment System

a. Noble Gas Activity Monitor (RM-A-14 od suitable equivalent) 1 27,33

b. Iodine Cartridge NIA(2) . 31,33

c. Particulate Filter N/A(2). 31,33

d. Effluent System Flow (UR-1 104AB) 1 . 26,33

e. Sampler Flow Rate Monitor 1 26,33 NOTE 2: No instrumentation channel is provided. However, for determining operability, the equipment named must be installed and functional or the ACTION applies.

CY-TM-170-300 Revision 1 Page 55 of 208 Table 3.2-1 Radioactive Liquid Waste Sampling and Analysis Program Lower Limit of Sampling Minimum Analysis Detection (LLD)

Liquid Release Type Frequency Frequency Type of Act ivity Analysis (g.Ci/ml) (Note a)

A. 1 Batch Waste Release Tanks (Note d) P P H1-3 1 xl0-5 7

Each Batch Each Batch Principal Gamm*a Emitters (Note f) 5 x 10o I-*131 1 x 10-6 Dissolved and Entrained Gases I x iOX5 (Gamma Emritters) (Note a)

I *f_=*¢, '/ se. ~ (M~Gross alpha 1 x 10 X1-Each Batch  : Composite (Note b) Sr-89, Sr-90 5 x 1O0 Fe-55 I 1x 1O A.2 Continuous Releases (Note e) Continuous W Principal Gamma Emitters (Note f) 5x 10.x (Note c) Uomposite (Note c) 1-131 1x10.

Grab Sample M Dissolved and Entrained Gases 1 x 10.

M (Gamma Emitters) (Note g)

Continuous M H-3 1x 10.5 (Note c) Composite (Note c) Gross alpha 1x 10-7 Continuous Q Sr-89, Sr-90 5 x 108 (Note c) Comoosite (Note c) Fe-55 1 x 10.6

CY-TM-170-300 Revision 1 Page 59 of 208 3.2.2.5 Explosive Gas Mixture 3.2.2.5.1 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the limits of Control 2.2.2.5 by monitoring the waste gases in the Waste Gas Holdup System with the hydrogen and oxygen monitors covered in Table 2.1-2 of Control 2.1.2.

3.2.2.6 Waste Gas Decay Tank 3.2.2.6.1 The concentration of radioactivity contained in the vent header shall be determined weekly. Ifthe concentration of the vent header exceeds 10 7 Ci/cc, daily samples shall be taken of each

• wae gas decay tank being added to, to determine Av if the tank(s) is less than or equal to 8800 Ci/tank.

CY-TM-170-300 Revision 1 Page 103 of 208 FIGURE 1.1 - TMI-I Liquid Effluent Pathways -

Figure 1.1 Comp TMI-1 Liquid Effluent Pathways II _Radw, Component Cooling 00o0-PCX Water TMI-1

CY-TM-170-300 Revision 1 K Page 183 of 208 TABLE 8.4 TMINS REMP Station Locations-Air Particulate and Air Iodine Station Code Distance (miles) Azimuth (0) Map No.

E1-2 0.4 97 F1-3 0.6 112 G2-1 1.4 126 e-3-.

M2-1 1.3 256 A3-1 2.7 357 H3-1 2.2 160 Q15-1 13.4 309 TABLE 8.5 TMINS REMP Station Locations-Direct Radiation (TLD)

I.,

Station Code Distance (miles) Azimuth (0) Map No.

A1-4 0.3 6 B1-1 0.6 25 B1-2 0.4 23 C1-2 0.3 50 D1-1 0.2 76 44, Vj E1-2 0.4 97 E1-4 0.2 97 F1-2 0.2 112 G1-3 0.2 130 H1-1 0.5 167 J1-1 0.8 176 J1-3 0.3 189 2-2 K1-4 0.2 209 ~24S.

L1 0.1 236 2-&j M1-1 0.1 250 N1-3 0.1 274 24-8-

K. P1-1 0.4 303 P1-2 3-2ý9-0.1 292

CY-TM-170-300 Revision 1

( Page 184 of 208 TABLE 8.5 (Cont'd)

TMINS REMP Station Locations-Direct Radiation (TLD)

Station Code Distance (miles) Azimuth (0) Map No.

Q1-2 0.2 321 Ri-i 0.2 335 C2-1 1.5 44 K2-1 1.2 200 M2-1 1.3 256 A3-1 2.7 357 4 H3-1 2.2 160 R3-1 2.6 341 A5-1 4.4 3 B5-1 4.9 19 C5-1 4.7 43

(.. E5-1 4.7 82 F5-1 4.7 109 G5-1 4.8 131 4e8 H5-1 4.1 158 J5-1 4.9 181 42, K5-1 4.9 202 L5-1 4.1 228 44~

M5-1 4.3 249 & V.-

N5-1 5.0 268 4&r P5-1 5.0 284 4i7Z Q5-1 5.0 317 R5-1 4.9 339 D6-1 5.2 66 E7-1 6.7 88 Q9-1 8.5 310 B10-1

&52- 8.3 9.2 21 G10-1 9.7 128 G15-1 14.4 126 w 9.,3 K J15-1 12.6 183 015-1 13.4 309

CY-TM-1 70-300 Revision 1 Page 185 of 208 TABLE 8.6 TMINS REMP Station Locations-Surface Water Station Code Distance (miles) Azimuth (0) Map No.

J1-2 .(Kt-<w) 0.5 188 47~- $,*A A3-2 M)(CO) 2.7 356 !59-.~.

Q9-1 (*F)(*W) 8.5 310 452 Q9-1 (R) (.5 8.5 310 G 15-2 (F) L(I>o,) r,ýg.

13.3 129 G 15-3 (?) (*DW,)

15.7 124 546-t-(FR- 2--

(.= Raw Water

("F) =F* Water TABLE 8.7 TMINS REMP Station Locations-Aquatic Sediment Station Code Distance (miles) Azimuth (0) Map No.

A1-3 0.5

,6?-p

• I 359 48,-

K1-3 0.2 212 69- I J2-1 1.4 179 s-5;,1

.,dtr:_7 l4w

CY-TM-170-300 Revision 1 Page 186 of 208 TABLE 8.8 TMINS REMP Station Locations-Milk Station Code Distance (miles) Azimuth (0) Map No.

E2-2 1.1 96 F4-1 3.2 104 G2-1 1.4 126 g4-pK1 3.1 205 --7 K15-3 14.4 205 7--? ,

TABLE 8.9 TMINS REMP Station Locations-Fish Station Code Station Location IND Downstream of Station Discharge BKG Upstream of Station Discharge TABLE 8.10 TMINS REMP Station Locations-Food Products Station Code Distance (miles) Azimuth (0) Map No.

-D,-

65-E1-2 0.4 97 7- .e- ,

H1i-2 1.0 151 B10-2 10.0 31 .5.5j- 1,3

CY-TM-170-300 Revision 1 Page 187 of 208 MAP 8.1 THREE MILE ISLAND NUCLEAR STATION LOCATIONS ADIOLOGICAL ENVIRONMENTAL MONITOR ING PROGRAM STATIONS WITHIN 1 MILE OF THE SITE

.25*

tOl.25 123.75'

L10 I

I 0

MAP 8.1 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Within I Mile of the Site

CY-TM-1 70-300 Revision 1 Page 188 of 208 MAP 8.2 REE MILE ISLAND NUCLEAR STATION LOCATIONS OF )IOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ATIONS WITHIN 5 MILES OF THE SITE 348.75" l.25*

A a

326.25" 33.75*

C 0

281.25', i7875.

N E 25B.75* _

MILES M

L 168.75°

0 0.5 1 2 3 MAP 8.2 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Within 5 Miles of the Site

CY-TM-1 70-300 Revision1 Page 189 of 208 MAP 8.3 T REE MILE ISLAND NUCLEAR STATION LOCATIONS OF RA IOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIO GREATER THAN 5 MILES FROM THE SITE 348.75 A 11.25° R 13 326.25 33.75

\ ~/ C

\ /

/ LEBANON 33I A SBURG 85 IHERSHEY I PALMYRAo

/ /~ A7 32

~

v~ J-U STOWN/

N t 258.75' 236.25*

213.75° 191.25' j 168.76,

(

0 2 4 8 12 I p I I 'Miles MAP 8.3 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Greater Than 5 Miles from the Site

CY-TM-170-300 Revision 2

. '" "n. Page 1 of 209 Nuclear Level 3 - Information Use OFFSITE DOSE CALCULATION MANUAL (ODCM)

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the Three Mile Island Nuclear Station (TMI) Unit 1 and Unit 2 PDMS Technical Specifications and implements TMI radiological effluent controls. The ODCM contains the controls, bases, and surveillance requirements for liquid and gaseous radiological effluents. In addition, the ODCM describes the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents. This document also describes the methodology used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm/trip set points. Liquid and Gaseous Radwaste Treatment System configurations are also included.

The ODCM also is used to define the requirements for the TMI radiological environmental monitoring program (REMP) and contains a list and graphical description of the specific sample locations used in the REMP.

The ODCM is maintained at the Three Mile Island (TMI) site for use as a reference guide and training document of accepted methodologies and calculations: Changes in the calculation methods or parameters will be incorporated into the ODCM to ensure the ODCM represents the present methodology in all applicable areas. Changes to the ODCM will be implemented in accordance with the TMI-1 and TMI-2 PDMS Technical Specifications.

The ODCM follows the methodology and models suggested by NUREG-0133, and Regulatory Guide 1.109, Revision 1 for calculation of off-site doses due to plant effluent releases.

Simplifying assumptions have been applied in this manual where applicable to provide a more workable document for implementation of the Radiological Effluent Controls requirements.

TMI implements the TMI Radiological Effluent Controls Program and Regulatory Guide 1.21, Revision 1 (Annual Radioactive Effluent Release Report) requirements by use of a computerized system used to determine TMI effluent releases and to update cumulative effluent doses.

This procedure replaces 6610-PLN-4200.01.

CY-TM-1 70-300 Revision 2 Page 2 of 209 TABLE OF CONTENTS PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS Section Page 1.0 DEFINITIONS 13 Table 1-1, Frequency Notation 18 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 20 2.1 Radioactive Effluent Instrumentation 20 2.1.1 Radioactive Liquid Effluent Instrumentation 20 Table 2.1-1, Radioactive Liquid Effluent Instrumentation 22 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 23 Table 2.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 24 2.2 Radiological Effluent Controls 30 2.2.1 Liquid Effluent Controls 30 2.2.2 Gaseous Effluent Controls 34 2.2.3 Total Radioactive Effluent Controls 41 3.0 SURVEILLANCES 44 3.1 Radioactive Effluent Instrumentation 44 3.1.1 Radioactive Liquid Effluent Instrumentation 44 Table 3.1-1, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 45 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 47 Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements 48

CY-TM-1 70-300 Revision 2 Page 3 of 209 TABLE OF CONTENTS (Cont'd)

PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS Section Page 3.2 Radiological Effluents 53 3.2.1 Liquid Effluents 53 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 55 3.2.2 Gaseous Effluents 58 Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 59 3.2.3 Total Radioactive Effluents 64 4.0 PART I REFERENCES 65

CY-TM-1 70-300 Revision 2 Page 4 of 209 TABLE OF CONTENTS (Cont'd)

PART II TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section Page 1.0 DEFINITIONS 67 Table 1.1, Frequency Notation 70 2.0 CONTROLS AND BASES 71 2.1 Radioactive Effluent Instrumentation 71 2.1.1 Radioactive Liquid Effluent Instrumentation 71 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 71 Table 2.1.2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 73 2.2 Radioactive Effluent Controls 74 2.2.1 Liquid Effluent Controls 74 2.2.2 Gaseous Effluent Controls 77 2.2.3 Total Radioactive Effluent Controls 84 3.0 SURVEILLANCES 86 3.1 Radioactive Effluent Instrumentation 86 3.1.1 Radioactive Liquid Effluent Instrumentation 86 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation86 Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements 87 3.2 Radiological Effluents 88 3.2.1 Liquid Effluents 88 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 89 3.2.2 Gaseous Effluents 90

CY-TM-170-300 Revision 2 Page 5 of 209 TABLE OF CONTENTS (Cont'd)

PART II TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section Paiqe Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 91 3.2.3 Total Radioactive Effluents 94 4.0 PART II REFERENCES 95

CY-TM-170-300 Revision 2 Page 6 of 209 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Paqe 1.0 LIQUID EFFLUENT MONITORS 97 1.1 TMI-1 and TMI-2 Liquid Radiation Monitor Set Points 97 1.2 TMI Liquid Release Points and Liquid Radiation Monitor Data 98 1.3 Control of Liquid Releases 100 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 105 2.1 Liquid Effluents - 10 CFR 50 Appendix I 105 2.2 TMI Liquid Radwaste System Dose Calcs Once per Month 106 2.3 Alternative Dose Calculational Methodology 107 3.0 LIQUID EFFLUENT WASTE TREATMENT SYSTEM 112 3.1 TMI-1 Liquid Effluent Waste Treatment System 112 3.2 Operability of TMI-1 Liquid Effluent Waste Treatment System 113 3.3 TMI-2 Liquid Effluent Waste Treatment System 113 4.0 GASEOUS EFFLUENT MONITORS 116 4.1 TMI-1 Noble Gas Monitor Set Points 116 4.2 TMI-1 Particulate and Radioiodine Monitor Set Points 118 4.3 TMI-2 Gaseous Radiation Monitor Set Points 119 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data120 4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data122 4.6 Control of Gaseous Effluent Releases 123

CY-TM-1 70-300 Revision 2 Page 7 of 209 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Paqe 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 135 5.1 Gaseous Effluents - Instantaneous Release Limits 135 5.1.1 Noble Gases 135 5.1.1.1 Total Body 135 5.1.1.2 Skin 136 5.1.2 lodines and Particulates 137 5.2 Gaseous Effluents - 10 CFR 50 Appendix I 138 5.2.1 Noble Gases 138 5.2.2 lodines and Particulates 139 5.3 Gaseous Radioactive System Dose Calculations Once per Month 141 5.4 Alternative Dose Calculational Methodologies 142 6.0 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM 164 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System 164 6.2 Operability of the TMI-1 Gaseous Radwaste Treatment System 164 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 166 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 167 8.1 Monitoring Program Requirements 167 8.2 Land Use Census 170 8.3 Interlaboratory Comparison Program 172 9.0 PART III REFERENCES" 187

CY-TM-1 70-300 Revision 2 Page 8 of 209 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Pacie TABLES Table 1.1 TMI-1 Liquid Release Point and Liquid Radiation Monitor Data 101 Table 1.2 TMI-2 Sump Capacities 102 Table 2.1 Liquid Dose Conversion Factors (DCF): DFj 108 Table 2.2 Bioaccumulation Factors, BFj 111 Table 4.1 TMI-1 Gaseous Release Point & Gaseous Radiation Monitor Data 124 Table 4.2 TMI-2 Gaseous Release Point & Gaseous Radiation Monitor Data 125 Table 4.3 Dose Factors for Noble Gases and Daughters 126 Table 4.4 Atmospheric Dispersion Factors for Three Mile Island - Station Vent 127 Table 4.5 Atmospheric Dispersion Factors for Three Mile Island - Ground Release 128 Table 4.6 Dose Parameters for Radioiodines and Radioactive Particulate In Gaseous Effluents 129 Table 5.2.1 Pathway Dose Factors, Ri- Infant, Inhalation 143 Table 5.2.2 Pathway Dose Factors, Ri - Child, Inhalation 144 Table 5.2.3 Pathway Dose Factors, Ri - Teen, Inhalation 145 Table 5.2.4 Pathway Dose Factors, Ri - Adult, Inhalation 146 Table 5.3.1 Pathway Dose Factors, Ri - All Age Groups, Ground Plane 147 Table 5.4.1 Pathway Dose Factors, Ri - Infant, Grass-Cow-Milk 148 Table 5.4.2 Pathway Dose Factors, Ri - Child, Grass-Cow-Milk 149 Table 5.4.3 Pathway Dose Factors, Ri - Teen, Grass-Cow-Milk 150 Table 5.4.4 Pathway Dose Factors, R - Adult, Grass-Cow-Milk 151 Table 5.5.1 Pathway Dose Factors, Ri - Infant, Grass-Goat-Milk 152

CY-TM-170-300 Revision 2 Page 9 of 209 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLES Table 5.5.2 Pathway ,Dose Factors, Rj - Child, Grass-Goat-Milk 153 Table 5.5.3 Pathway Dose Factors, Ri - Teen, Grass-Goat-Milk 154 Table 5.5.4 Pathway Dose Factors, Ri - Adult, Grass-Goat-Milk 155 Table 5.6.1 Pathway Dose Factors, R - Infant, Grass-Cow-Meat 156 Table 5.6.2 Pathway Dose Factors, Ri - Child, Grass-Cow-Meat 157 Table 5.6.3 Pathway Dose Factors, Ri - Teen, Grass-Cow-Meat 158 Table 5.6.4 Pathway Dose Factors, Ri - Adult, Grass-Cow-Meat 159 Table 5.7.1 Pathway Dose Factors, Ri - Infant, Vegetation 160 Table 5.7.2 Pathway Dose Factors, R, - Child, Vegetation 161 Table 5.7.3 Pathway Dose Factors, R1 - Teen, Vegetation 162 Table 5.7.4 Pathway Dose Factors, Ri - Adult, Vegetation 163 Table 8.1 Sample Collection and Analysis Requirements 173 Table 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 179 Table 8.3 Detection Capabilities for Environmental Sample Analysis 180 Table 8.4 TMINS REMP Station Locations - Air Particulate and Air Iodine 183 Table 8.5 TMINS REMP Station Locations - Direct Radiation (TLD) 183 Table 8.6 TMINS REMP Station Locations - Surface Water 185 Table 8.7 TMINS REMP Station Locations - Aquatic Sediment 185 Table 8.8 TMINS REMP Station Locations - Milk 186 Table 8.9 TMINS REMP Station Locations - Fish 186 Table 8.10 TMINS REMP Station Locations - Food Products 186

CY-TM-1 70-300 Revision 2 Page 10 of 209 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLES MAP 8.1 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 1 Mile of the Site 187 MAP 8.2 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 5 miles of the Site 188 MAP 8.3 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Greater than 5 miles from the Site 189 FIGURES Figure 1.1 TMI-1 Liquid Effluent Pathways 103 Figure 1.2 TMI-2 Liquid Effluent Pathways 104 Figure 3.1 TMI-1 Liquid Radwaste 114 Figure 3.2 TMI-1 Liquid Waste Evaporators 115 Figure 4.1 TMI-1 Gaseous Effluent Pathways 130 Figure 4.2 TMI-1 Auxiliary & Fuel Handling Buildings Effluent Pathways 131 Figure 4.3 TMI-1 Reactor Building Effluent Pathway 132 Figure 4.4 TMI-1 Condenser Offgas Effluent Pathway 133 Figure 4.5 TMI-2 Gaseous Effluent Filtration System/Pathways 134 Figure 6.1 Waste Gas System 165

CY-TM-170-300 Revision 2 Page 11 of 209 TABLE OF CONTENTS (Cont'd)

PART IV REPORTING REQUIREMENTS Section Paae 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 193 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 194 3.0 PART IV REFERENCES 196 APPENDICES A. Pathway Dose Rate Parameter (Pi) 197 B. Inhalation Pathway Dose Factor (R1 ) 198 C. Ground Plane Pathway Dose Factor (R,) 199 D. Grass-Cow-Milk Pathway Dose Factor (Ri) 200 E. Cow-Meat Pathway Dose Factor (RI) 202 F. Vegetation Pathway Dose Factor (Ri) 204 APPENDIX A - F REFERENCES 205

CY-TM-1 70-300 Revision 2 Page 12 of 209 PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS

CY-TM-1 70-300 Revision 2 Page 13 of 209 1.0 DEFINITIONS The following terms are defined for uniform interpretation of these controls and surveillances.

1.1 Reactor Operating Conditions 1.1.1 Cold Shutdown The reactor is in the cold shutdown condition when it is subcritical by at least one percent delta k/k and Tavg is no more than 200 0 F. Pressure is defined by Technical Specification 3.1.2.

1.1.2 Hot Shutdown The reactor is in the hot shutdown condition when it is subcritical by at least one percent delta k/k and Tavg is at or greater than 525 0 F.

1.1.3 Reactor Critical The reactor is critical when the neutron chain reaction is self-sustaining and Keff = 1.0.

1.1.4 Hot Standby The reactor is in the hot standby condition when all of the following conditions exist:

a. Tavg is greater than 525 0F

b. The reactor is critical

c. Indicated neutron power on the power range channels is less than two percent of rated power. Rated power is defined in Technical Specification Definition 1.1.

1.1.5 Power Operation The reactor is in a power operating condition when the indicated neutron power is above two percent of rated power as indicated on the power range channels. Rated power is defined in Technical Specification Definition 1.1.

CY-TM-170-300 Revision 2 Page 14 of 209 1.1.6 Refueling Shutdown The reactor is in the refueling shutdown condition when, even with all rods removed, the reactor would be subcritical by at least one percent delta k/k and the coolant temperature at the decay heat removal pump suction is no more than 1400 F. Pressure is defined by Technical Specification 3.1.2. A refueling shutdown refers to a shutdown to replace or rearrange all or a portion of the fuel assemblies and/or control rods.

1.1.7 Refueling Operation An operation involving a change in core geometry by manipulation of fuel or control rods when the reactor vessel head is removed.

1.1.8 Refueling Interval The time between normal refuelings of the reactor. This is defined as once per 24 months.

1.1.9 Startup The reactor shall be considered in the startup mode when the shutdown margin is reduced with the intent of going critical.

1.1.10 Tave Tave is defined as the arithmetic average of the coolant temperatures in the hot and cold legs of the loop with the greater number of reactor coolant pumps operating, if such a distinction of loops can be made.

1.1.11 Heatup - Cooldown Mode The heatup-cooldown mode is the range of reactor coolant temperature greater than 200OF and less than 525 0 F.

1.2 Operable A system, subsystem, train, component or device, shall be OPERABLE or have OPERABILITY when it is capable of performing it's specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s), are also capable of performing their related support function(s).

1.3 Instrument Channel An instrument channel is the combination of sensor, wires, amplifiers, and output devices, which are connected for the purpose of measuring the value of a

CY-TM-1 70-300 Revision 2 Page 15 of 209 process variable, for the purpose of observation, control, and/or protection. An instrument channel may be either analog or digital.

1.4 Instrumentation Surveillance 1.4.1 Channel Test A CHANNEL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practical to verify OPERABILITY, including alarm and/or trip functions.

1.4.2 Channel Check A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.

1.4.3 Source Check A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

1.4.4 Channel Calibration An instrument CHANNEL CALIBRATION is a test, and adjustment (if necessary), to establish that the channel output responds with acceptable range and accuracy to known values of the parameter, which the channel measures, or an accurate simulation of these values.

Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include the channel test.

1,5 Dose Equivalent 1-131 The DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcurie/gram), which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID 14844, "Calculation of Distance Factors for Power and Test Reactor Sites". [Or in Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October, 1977.]

CY-TM-170-300 Revision 2 Page 16 of 209 1.6 Offsite Dose Calculation Manual (ODCM)

The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains (1) the Radiological Effluent Controls, (2) the Radiological Environmental Monitoring Program and (3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

1.7 Gaseous Radwaste Treatment The GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluent by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

1.8 Ventilation Exhaust Treatment System A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluent by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodine or particulates from the gaseous exhaust system prior to the release to the environment.

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEMS.

1.9 Purge - Purging PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is required to purify the confinement.

1.10 Venting VENTING is the controlled process of discharging air as gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is not provided. Vent used in system name does not imply a VENTING process.

1.11 Member(s) of the Public MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupational dose.

CY-TM-170-300 Revision 2 Page 17 of 209 1.12 Site Boundary The SITE BOUNDARY used as the basis for the limits on the release of gaseous effluents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMI-1 FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Three Mile Island and between Three Mile Island and Shelley Island.

The SITE BOUNDARY used as the basis for the limits on the release of liquid effluents is as shown in Figure 1.1 in Part I of this ODCM.

1.13 Frequency Notation The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1-1. All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. The 25% extension applies to all frequency intervals with the exception of "F." No extension is allowed for intervals designated "F."

1.14 Occupational Dose OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person.

Occupational dose does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under 10CFR35.75, from voluntary participation in medical research programs, or as a member of the public.

CY-TM-1 70-300 Revision 2 Page 18 of 209 Table 1-1 Frequency Notation Notation Frequency S Shiftly (once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

D Daily (once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

W Weekly (once per 7 days)

M Monthly (once per 31 days)

Q Quarterly (once per 92 days)

S/A Semi-Annually (once per 184 days)

R Refueling Interval (once per 24 months)

P S/U Prior to each reactor startup, if not done during the previous 7 days P Completed prior to each release N/A (NA) Not applicable E Once per 18 months F Not to exceed 24 months Bases Section 1.13 establishes the limit for which the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities. It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are specified to be performed at least once each REFUELING INTERVAL. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed once each REFUELING INTERVAL. Likewise, it is not the intent that REFUELING INTERVAL surveillances be performed during power operation unless it is consistent with safe plant operation. The limitation of Section 1.13 is based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

CY-TM-1 70-300 Revision 2 Page 19 of 209 Gaseous Effluent Release Points and Liquid Effluent Outfall Locations T NO. 1 -0'--.FL N IURSINE SLOG UNIT NQI FUEL--'/

HANOLING BLDG ESF VENT STACK DSNO03

CY-TM-1 70-300 Revision 2 Page 20 of 209 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation CONTROL:

The radioactive liquid effluent monitoring instrumentation channels shown in Table 2.1-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times

• ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluent monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-1. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.

For WDL-FT-84, and RM-L-6, operability is not required when discharges are positively controlled through the closure of WDL-V-257.

For RM-L-12 and associated IWTS/IWFS flow interlocks, operability is not required when discharges are positively controlled through the closure of IW-V-72, 75 and IW-V-280, 281.

For SR-FT-146, operability is not required when discharges are positively controlled through the closure of WDL-V-257, IW-V-72, 75 and IW-V-280, 281.

CY-TM-1 70-300 Revision 2 Page 21 of 209 BASES The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluent during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding ten times the effluent concentrations of 10 CFR Part 20.

CY-TM-170-300 Revision 2 Page 22 of 209 Table 2.1-1 Radioactive Liquid Effluent Instrumentation Minimum Channels Instrument Operable ACTION

1. Gross Radioactivity Monitors Providing Automatic Termination of Release

a. Unit 1 Liquid Radwaste Effluent Line (RM-L6) 1 18

b. IWTS/IWFS Discharge Line (RM-L12) 1 20

2. Flow Rate Measurement Devices

a. Unit 1 Liquid Radwaste Effluent Line (FT-84) 1 21

b. Station Effluent Discharge (FT-146) 1 21 Table Notation ACTION 18 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue, provided that prior to initiating a release:

1. At least two independent samples are analyzed in accordance with Surveillances 3.2.1.1.1 and 3.2.1.1.2 and;

2. At least two technically qualified members of the Unit staff independently verify the release rate calculations and verify the discharge valve lineup.

3. The TMI Plant Manager shall approve each release. Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may commence or continue provided that grab samples are collected and analyzed 7 for gross radioactivity (beta or gamma) at a limit of detection of at least 1x10 microcuries/ml, prior to initiating a release and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during release.

ACTION 21 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, radioactive effluent releases via this pathway may continue, provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.

CY-TM-170-300 Revision 2 Page 23 of 209 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CONTROL:

The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 2.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: As shown in Table 2.1-2 ACTION:

a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-2. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.

BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301.

The low range condenser offgas noble gas activity monitors also provide data for determination of steam generator primary to secondary leakage rate. Channel operability requirements are based on an AmerGen letter

1. 5928-06-20449, "Request to Revise Condenser Vent System Low Range Noble Gas Monitor Operability Requirements", Pamela B. Cowan to U.S.N.R.C., May 25, 2006.

CY-TM-1 70-300 Revision 2 Page 24 of 209 Table 2.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNEL INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Waste Gas Holdup System

a. Noble Gas Activity Monitor (RM-A-7) 1 25 B. Effluent System Flow Rate Measuring Device (FT-123) 1 26

2. Waste Gas Holdup System Explosive Gas Monitoring System

a. Hydrogen Monitor 2 ** 30

b. Oxygen Monitor 2 ** 30

3. Containment Purge Monitoring System

a. Noble Gas Activity Monitor (RM-A-9) 1 # 27

b. Iodine Sampler (RM-A-9) 1 # 31

c. Particulate Sampler (RM-A-9) 1 # 31

d. Effluent System Flow Rate Measuring Device (FR-148A, FR-148B) 1 # 26

e. Sampler Flow Rate Monitor 1 # 26

4. Condenser Vent System

a. Low Range Noble Gas Activity Monitor (RM-A-5Lo or RM-A-15) 1 32

CY-TM-1 70-300 Revision 2 Page 25 of 209 Table 2.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNEL INSTRUMENT OPERABLE APPLICABILITY ACTION

5. Auxiliary and Fuel Handling Building Ventilation System

a. Noble Gas Activity Monitor (RM-A-8) or (RM-A-4 and RM-A-6) 1

• 27

b. Iodine Sampler (RM-A-8 or (RM-A-4 and RM-A-6) 1

• 31

c. Particulate Sampler (RM-A-8 or (RM-A-4 and RM-A-6) 1 31

d. Effluent System Flow Rate Measuring Devices (FR-149 andFR-150) 1

• 26

e. Sampler Flow Rate Monitor 1

• 26

6. Fuel Handling Building ESF Air Treatment System

a. Noble Gas Activity Monitor (RM-A-14 od suitable equivalent) 1 27,33

b. Iodine Cartridge N/A(2) .31,33

c. Particulate Filter N/A(2) 31,33

d. Effluent System Flow (UR-1104AIB) 1 26,33

e. Sampler Flow Rate Monitor 1 .... 26,33 NOTE 2: No instrumentation channel is provided. However, for determining operability, the equipment named must be installed and functional or the ACTION applies.

CY-TM-170-300 Revision 2 Page 26 of 209 Table 2.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNEL INSTRUMENT OPERABLE APPLICABILITY ACTION

7. Chemical Cleaning Building Ventilation System

a. Noble Gas Activity Monitor (ALC RM-I-18) 1(3) 27

b. Iodine Sampler (ALC RM-1-18) 1(3) 31

c. Particulate Sampler (ALC RM-1-18) 1 31

8. Waste Handling and Packaging Facility Ventilation System

a. Particulate Sampler (WHP-RIT-1) 1### 31

9. Respirator and Laundry Maintenance Facility Ventilation System

a. Particulate Sampler (RLM-RM-1) 1 31 NOTE 3: Channel only required when liquid radwaste is moved or processed within the facility.

CY-TM-170-300 Revision 2 Page 27 of 209 Table 2.1-2 Table Notation

-* At all times

- ** During waste gas holdup system operation

-*** Operability is not required when discharges are positively controlled through the closure of WDG-V-47 or where RM-A-8, AH-FT-149 and AH-FT-150 are operable and RM-A-8 is capable of automatic closure of WDG-V-47 S**** During Fuel Handling Building ESF Air Treatment System Operation

- # At all times during containment purging

- ## At all times when condenser vacuum is established

- ### During operation of the ventilation system ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed in accordance with Table 3.2-2, Item A, and

2. At least two technically qualified members of the Unit staff independently verify the release rate calculations and verify the discharge valve lineup.

3. The TMI Plant Manager shall approve each release. Otherwise, suspend release of radioactive effluent via this pathway.

ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the initial samples are analyzed for gross activity (gamma scan) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the channel has been declared inoperable. If RM-A-9 is declared inoperable, see also Technical Specification 3.5.1, Table 3-5.1, Item C.3.f.

CY-TM-170-300 Revision 2 Page 28 of 209 Table 2.1-2 Notations (Cont'd)

ACTION 30 1. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, a grab sample shall be collected and analyzed for the inoperable gas channel(s) at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With both channels inoperable, a grab sample shall be collected and analyzed for the inoperable gas channel(s):

(a) at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations.

(b) at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations (e.g. Feed and Bleed).

2. Ifthe inoperable gas channel(s) is not restored to service within 14 days, a special report shall be submitted to the Regional Administrator of the NRC Region I Office and a copy to the Director, Office of Inspection and Enforcement within 30 days of declaring the channel(s) inoperable. The report shall describe (a) the cause of the monitor inoperability, (b) action being taken to restore the instrument to service, and (c) action to be taken to prevent recurrence.

ACTION 31 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that within four hours after the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment.

ACTION 32 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days, provided that grab samples are taken and analyzed.

If the. primary-to-secondary leak rate was unstable*, or was indicating an increasing trend at the initial time when there was no operable channel of the Condenser Vent System Low Range Noble Gas Activity Monitor, analyze grab samples of the reactor coolant system and Condenser OffGas once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to provide an indication of primary-to-secondary leakage. Subsequent sample frequency shall be in accordance with Table 1 based on the last sample result. Otherwise, analyze grab samples of the reactor coolant system and Condenser OffGas to provide an indication of primary-to-secondary leakage at the minimum frequency indicated in Table 1, below:

CY-TM-170-300 Revision 2 Page 29 of 209 Table 1 Minimum Frequency of Grab Samples When No Condenser Vent System Low Range Noble Gas Activity Monitor is Operable Existing Total Primary-to-Secondary Leak Rate Frequency of Grab Samples (based on last monitor reading or sample result) 0 to < 5 GPD Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 5 to < 30 GPD Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 30 to < 75 GPD Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 75 GPD or greater Place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and at least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• Unstable is defined as > 10% increase during a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, as stated in the EPRI Guidelines.

Condenser Vent System Low Range Noble Gas Activity Monitor inoperable channels should be restored to operability as rapidly as practical.

After 14 days, if one OPERABLE channel is not returned to service, within I hour, the provisions of Technical Specification 3.0.1 apply, as if this Control were a Tech Spec Limiting Condition for Operation.

ACTION 33 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel to OPERABLE status within 7 days, or prepare and submit a special report within 30 days outlining the action(s) taken, the cause of the inoperability, and plans and schedule for restoring the system to OPERABLE status.

CY-TM-1 70-300 Revision 2 Page 30 of 209 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration CONTROL:

The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 3E-3 uCi/cc total activity.

APPLICABILITY: At all times ACTION:

With the concentration of radioactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within the above limits.

BASES This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures with (1) the Section Il.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1301 to the population.

The concentration limit for noble gases is based upon the assumption the Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)

Publication 2.

CY-TM-1 70-300 Revision 2 Page 31 of 209 2.2.1.2 Liquid Effluent Dose CONTROL The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to the SITE BOUNDARY shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report, which identifies the cause(s) for exceeding the limit(s), and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.

CY-TM-1 70-300 Revision 2 Page 32 of 209 BASES This control and associated action is provided to implement the requirements of Sections ILA, Ill.A, and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable".

Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 10 CFR 20.

The dose calculations in the ODCM implement the requirements in Section III.A. of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1I".

Revision 1, October, 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,"April, 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

CY-TM-1 70-300 Revision 2 Page 33 of 209 2.2.1.3 Liquid Radwaste Treatment System CONTROL:

The appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month.

APPLICABILITY: At all times ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and,

3. A summary description of action(s) taken to prevent a recurrence BASES The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable. This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The intent of Section ll.D. is to reduce effluents to as low as is reasonably achievable in a cost effective manner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section II.A of Appendix I, 10 CFR Part 50 dose requirements. This margin, a factor of 4, constitutes a reasonable reduction.

CY-TM-1 70-300 Revision 2 Page 34 of 209 2.2.1.4 Liquid Holdup Tanks CONTROL The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

a. Outside temporary tank APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

BASES Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20.1001-20-20.2401, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.

2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL:

The dose rate due to radioactive materials released in gaseous effluent from the site shall be limited to the following:

a. For noble gases: less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and

b. For 1-131, 1-133, tritium and all radionuclides in particulate form with half lives greater than 8 days:

less than or equal to 1500 mrem/yr to any organ.

APPLICABILITY: At all times

CY-TM-1 70-300 Revision 2 Page 35 of 209 ACTION:

With the release rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limit(s).

BASES The control implements the requirement in Technical Specification (6.8.4.b (7). This specification is provided to ensure that the dose from radioactive materials in gaseous effluents at and beyond the SITE BOUNDARY will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associated with 10 times the concentrations of 10 CFR Part 20, Appendix B, Table 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10 CFR Part 20.1302. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500. mrem/year to the total body, or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year (NUREG 1301).

2.2.2.2 Gaseous Effluents Dose-Noble Gases CONTROL:

The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,

CY-TM-170-300 Revision 2 Page 36 of 209

b. During any calendar year: less than or equal to.10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-I.

This control and associated action is provided to implement the requirements of Section II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable."

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in

CY-TM-1 70-300 Revision 2 Page 37 of 209 Routine Releases from Light-Water Cooled Reactors",

Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

2.2.2.3 Dose - Iodine-1 31, Iodine-1 33, Tritium, and Radionuclides in Particulate Form CONTROL:

The dose to a MEMBER OF THE PUBLIC from Iodine-1 31, Iodine-1 33, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: less than or equal to 7.5 mrem to any organ, and

b. During any calendar year: less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times ACTION:

With the calculated dose from the release of Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-1.

This control and associated action is provided to implement the requirements of Section II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in

CY-TM-1 70-300 Revision 2 Page 38 of 209 Section II.C of Appendix I. The ACTION statement provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors" Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-131, iodine-133, tritium and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

2.2.2.4 Gaseous Radwaste Treatment System CONTROL The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in the gaseous waste prior to their discharge when the monthly projected gaseous effluent air doses due to untreated gaseous effluent releases from the unit

CY-TM-1 70-300 Revision 2 Page 39 of 209 would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected doses due to gaseous effluent releases from the site would exceed 0.3 mrem to any organ.

APPLICABILITY: At all times ACTION:

a. With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. A summary description of action(s) taken to prevent a recurrence BASES The use of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment. The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections 11.B and II.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

CY-TM-170-300 Revision 2 Page 40 of 209 2.2.2.5 Explosive Gas Mixture CONTROL The concentration of oxygen in the Waste Gas Holdup System shall be limited to less than or equal to 2% by volume whenever the concentration of hydrogen in the Waste Gas Holdup System is greater than or equal to 4% by volume.

AVAILABILITY: At all times ACTION:

Whenever the concentration of hydrogen in the Waste Gas Holdup System is greater than or equal to 4% by volume, and:

a. The concentration of oxygen in the Waste Gas Holdup System is greater than 2% by volume, but less than 4% by volume, without delay, begin to reduce the oxygen concentration to within its limit.

b. The concentration of oxygen in the Waste Gas Holdup System is greater than or equal to 4% by volume, immediately suspend additions of waste gas to the Waste Gas Holdup System and without delay, begin to reduce the oxygen concentration to within its limit.

BASES:

Based on experimental data (Reference 1), lower limits of flammability for hydrogen is 5% and for oxygen is 5% by volume. Therefore, if the concentration of either gas is kept below it lower limit, the other gas may be present in higher amounts without the danger of an explosive mixture.

Maintaining the concentrations of hydrogen and oxygen such that an explosive mixture does not occur in the waste gas holdup system provides assurance that the release of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR 50.

REFERENCES (1) Bulletin 503, Bureau of Mines; Limits of Flammability of Gases and Vapors

CY-TM-1 70-300 Revision 2 Page 41 of 209 2.2.2.6 Waste Gas Decay Tanks CONTROL:

The quantity of radioactivity contained in each waste gas decay tank shall be limited to less than or equal to 8800 curies noble gases (considered as Xe-1 33).

APPLICABILITY: At all times ACTION:

a. With the quantity of radioactive material in any waste gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

BASES Restricting the quantity of radioactivity contained in each waste gas decay tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest exclusion area boundary will not exceed 0.5 rem.

This is consistent with Standard Review Plan 15.7.1, "Waste Gas System Failure."

2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose CONTROL:

The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem.

APPLICABILITY: At all times ACTION:

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a, 2.2.1.2.b, 2.2.2.2.a, 2.2.2.2.b, 2.2.2.3.a, or, 2.2.2.3.b, calculations should be made including

CY-TM-1 70-300 Revision 2 Page 42 of 209 direct radiation contributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. Ifsuch is the case, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b), shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. Ifthe estimated dose(s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

BASES This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d). This control requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be

CY-TM-170-300 Revision 2 Page 43 of 209 considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected) in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

CY-TM-170-300 Revision 2 Page 44 of 209 3.0 SURVEILLANCES 3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation Surveillance Requirements 3.1.1.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, AND CHANNEL TEST operations during the MODES and at the frequencies shown in Table 3.1-1.

CY-TM-170-300 Revision 2 Page 45 of 209 Table 3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Radioactivity Monitors Providing Alarm and Automatic Isolation

a. Unit 1 Liquid Radwaste Effluents Line (RM-L-6) D P R(2) Q(1)

b. IWTS/IWFS Discharge Line (RM-L-12) D P R(2) Q(1)

2. Flow Rate Monitors

a. Unit 1 Liquid Radwaste Effluent Line (FT-84) D(3) N/A R Q

b. Station Effluent Discharge (FT-146) D(3) N/A R Q

CY-TM-1 70-300 Revision 2 Page 46 of 209 Table 3.1-1 Table Notation (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the following condition exists: *

1. Instrument indicates measured levels above the high alarm/trip setpoint.

(Includes - circuit failure)

2. Instrument indicates a down scale failure. (Alarm function only.) (Includes -

circuit failure)

3. Instrument controls moved from the operate mode (Alarm function only).

(2) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participated in measurement assurance activities with NIST. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substitute previously established calibration procedures for this requirement)

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.

CY-TM-1 70-300 Revision 2 Page 47 of 209 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements 3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2.

CY-TM-1 70-300 Revision 2 Page 48 of 209 Table 3.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABILITY

1. Waste Gas Holdup System

a. Noble Gas Activity Monitor (RM-A7) P P E(3) Q(1)

b. Effluent System Flow Rate Measuring Device (FT-123) P N/A E Q

2. Waste Gas Holdup System Explosive Gas Monitoring System

a. Hydrogen Monitor 0 N/A Q(4) M **

b. Oxygen Monitor D N/A Q(5) M **

3. Containment Purge Vent System

a. Noble Gas Activity Monitor (RM-A9) D P E(3) M(1) #

b. Iodine Sampler (RM-A9) W N/A N/A N/A #

c. Particulate Sampler (RM-A9) W N/A N/A N/A #

d. Effluent System Flow Rate Measuring Device (FR-148) D N/A E Q #

e. Sampler Flow Rate Monitor D N/A E N/A

4. Condenser Vent System

a. Noble Gas Activity Monitor (RM-A5 and Suitable Equivalent - D M E(3) Q(2)

See Table 2.1-2, Item 4.a)

CY-TM-1 70-300 Revision 2 Page 49 of 209 Table 3.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABILITY

5. Auxiliary and Fuel Handling Building Ventilation System

a. Noble Gas Activity Monitor (RM-A8) or (RM-A4 and M-A6) D M E(3) Q(1)

b. Iodine Sampler (RM-A8) or (RM-A4 and RM-A6) W N/A N/A N/A

• r

c. Particulate Sampler (RM-A8) or (RM-A4 and RM-A6) W N/A N/A N/A

d. System Effluent Flow Rate Measurement Devices (FR-149 and FR-1 50) D N/A E Q

e. Sampler Flow Rate Monitor D N/A E N/A

6. Fuel Handling Building ESF Air Treatment System

a. Noble Gas Activity Monitor (RM-A14) D M R(3) Q(2)

b. System Effluent Flow Rate (UR-1 104 NB) D N/A R Q

c. Sampler Flow Rate Measurement Device D N/A R Q

CY-TM-1 70-300 Revision 2 Page 50 of 209 Table 3.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST AFDPLICABILITY

7. Chemical Cleaning Building Ventilation System

a. Noble Gas Activity Monitor (ALC RM-1-18) D M E(3) Q(2)

b. Iodine Sampler (ALC RM-1-18) W N/A N/A N/A

c. Particulate Sampler (ALC RM-1-18) W N/A N/A N/A

8. Waste Handling and Packaging Facility Ventilation System

a. Particulate Sampler (WHP-RIT-1) D W SA W

9. Respirator and Laundry Maintenance Ventilation System

a. Particulate Sampler (RLM-RM-1) D W SA W

CY-TM-170-300 Revision 2 Page 51 of 209 Table 3.1-2 Table Notation

• At all times

• • During waste gas holdup system operation Operability is not required when discharges are positively controlled through the closure of WDG-V-47, or where RM-A-8, AH-FT-149, and AH-FT-150 are operable and RM-A-8 is capable of automatic closure of WDG-V-47 During Fuel Handling Building ESF Air Treatment System Operation

1. At all times during containment purging

1. 1. At all times when condenser vacuum is established

1. 1. 1. During operation of the ventilation system (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway for the Auxiliary and Fuel Handling Building Ventilation System, the supply ventilation is isolated and control room alarm annunciation occurs if the following condition exists:

1. Instrument indicates measured levels above the high alarm/trip setpoint (Includes circuit failure).

2. Instrument indicates a down scale failure (Alarm function only) (Includes circuit failure).

3. Instrument controls moved from the operate mode (Alarm function only).

(2) The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1 Instrument indicates measured levels above the alarm setpoint. (includes circuit failure)

2. Instrument indicates a down scale failure (includes circuit failure).

3. Instrument controls moved from the operate mode.

CY-TM-170-300 Revision 2 Page 52 of 209 (3) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST.

These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substitute previously established calibration procedures for this requirement.)

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent hydrogen, balance nitrogen, and

2. Four volume percent hydrogen, balance nitrogen (5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, and

2. Four volume percent oxygen, balance nitrogen

CY-TM-170-300 Revision 2 Page 53 of 209 312 Radiological Effluents 3.2.1 Liquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration 3.2.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release, by sampling and analysis in accordance with Table 3.2-1. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.1.2 Post-release analysis of samples composited from batch releases shall be performed in accordance with Table 3.2-1. The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2.1.1.

3.2.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month.

3.2.1.3 Liquid Waste Treatment 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM.

CY-TM-1 70-300 Revision 2 Page 54 of 209 3.2.1.4 Liquid Holdup Tanks 3.2.1.4.1 The quantity of radioactive material contained in each of the tanks specified in Control 2.2.1.4 shall be determined to be within the limit by analyzing a representative sample of the tank's content weekly when radioactive materials are being added to the tank.

CY-TM-1 70-300 Revision 2 Page 55 of 209 Table 3.2-1 Radioactive Liquid Waste Sampling and Analysis Program Lower Limit of Sampling Minimum Analysis Detection (LLD)

Liquid Release Type Frequency Frequency Type of Activity Analysis (ýiCi/ml) (Note a)

A.1 Batch Waste Release Tanks (Note d) P P H-3 1 x 10-5 Each Batch Each Batch Principal Gamma Emitters (Note) .5 x 107 1-131 1 x 10.6 Dissolved and Entrained Gases 1 x 10-5 (Gamma Emitters) (Note g)

P M Gross alpha 1 x 10-7 Each Batch Composite (Note b)  ;

,P Q Sr-89, Sr-90 5 x 10.8 Each Batch Composite (Note b) Fe-55 1 x 10.6 A.2 Continuous Releases (Note e) Continuous W Principal Gamma Emitters (Note f) 5 x 10-7 (Note c) Composite (Note c) 1-131 1 x 10, Grab Sample M Dissolved and Entrained Gases I x 10s M (Gamma Emitters) (Note g)

Continuous M H-3 1 x 10-5

, (Note c) Composite (Note c) Gross alpha 1 x 10-7 Continuous Q Sr-89, Sr-90 5 x 10.8 (Note c) Composite (Note c) Fe-55 , x 10-

CY-TM-1 70-300 Revision 2 Page 56 of 209 Table 3.2-1 Table Notation

a. The LLD is defined, for purposes of this surveillance, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 Sb LLD =

E x V x 2.22 x 106 x Y x exp (-A At)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume) sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 2.22 E6 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)

X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting Typical values of E, V, Y and At shall be used in the calculation It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released

CY-TM-1 70-300 Revision 2 Page 57 of 209 Table 3.2-1 Notations (Cont'd)

c. To be representative of the quantities and concentrations of radioactive materials in liquid effluent, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release

d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and be thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

e. A continuous release is the discharge of liquid wastes of a non- discrete volume; e.g., from a volume or system that has an input flow during the continuous release.

f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to TS 6.9.4.

g. The gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, and Xe-135. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Effluent Release Report pursuant to T.S.

6.9.4.

CY-TM-170-300 Revision 2 Page 58 of 209 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates 3.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1 .a in accordance with the methods and procedures of the ODCM.

3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1 .b in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 3.2-2.

3.2.2.2 Dose, Noble Gas 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.3 Dose, Iodine-1 31, lodine-133, Tritium, and Radionuclides in Particulate Form 3.2.2.3.1 Cumulative dose contributions from lodine-131, Iodine-133, Tritium, and radionuclides in particulate form with half lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.4 Gaseous Waste Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM.

CY-TM-1 70-300 Revision 2 Page 59 of 209 3.2.2.5 Explosive Gas Mixture 3.2.2.5.1 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the limits of Control 2.2.2.5 by monitoring the waste gases in the Waste Gas Holdup System with the hydrogen and oxygen monitors covered in Table 2.1-2 of Control 2.1.2.

3.2.2.6 Waste Gas Decay Tank 3.2.2.6.1 The concentration of radioactivity contained in the vent header shall be determined weekly. If the concentration of the vent header exceeds 10.7 [tCi/cc, daily samples shall be taken of each waste gas decay tank being added to, to determine if the tank(s) is less than or equal to 8800 Ci/tank.

CY-TM-170-300 Revision 2 Page 60 of 209 Table 3.2-2 Radioactive Gaseous Waste Sampling and Analysis Program Minimum Lower Limit of Sampling Analysis Type of Activity Detection (LLD)

Gaseous Release Type Frequency Frequency Analysis j.Ci/ml) (Note a) p I I

EachSample Tank Principal Gamma A. Waste Gas Decay Tank Grab EachPTank Emitters (Note g)

B. Containment Purge H-3 1 x 10, P (Note b)Each P (Note b) Each Principal Gamma Purge Grab Sample Purge Emitters (Note g) 1 x 10.

C. Auxiliary and Fuel Handling Building H-3 1x 10-6 Air Treatment System M (Notes c, e) Grab M Principal Gamma '

'Sample ',Emitters (Note g) lX1x D. Fuel Handling Building ESF Air Treatment System M(during System M(during H-3 1066x Operation) System PrincipalGamma Grab Sample Operation) Emitters (Note g) I x 10 E. Condenser Vacuum Pumps Exhaust (Note h) (Noteh) M H-3M M Principal Gamma

,"_Grab Sample (Note h) , Emitters (Note g) 1 X10-4 F. Chemical Cleaning Building Air Treatment System M(Note) H-3 x 10 Grab Sale)M Principal Gamma SEmitters (Note g) 1 x 104 G. Waste Handling and Packaging Facility See Section I See Section I See Section I See Section I Air Treatment System, of this table of this table of this table of this table H. Respirator and Laundry Maintenance Facility See Section I See Section I See Section I See Section I Air Treatment System of this table , of this table of this table of this table

CY-TM-170-300 Revision 2 Page 61 of 209 Table 3.2-2 (Cont'd)

Radioactive Gaseous Waste Sampling and Analysis Program Minimum Lower Limit of Sampling Analysis Type of Activity Detection (LLD)

Gaseous Release Type Frequency Frequency Analysis (iCi/ml) (Note a)

All Release Types as Listed Above in B, C, D, F, G, Continuous  : W (Note d) 12 and H (During System Operation) (Note f) Charcoal 1-131 1 x 10.12 (t fSample (Note i) "_" _

, Principal Gamma ,

Continuous W (Note d) Emitters (Note g) 1,

, , 1 x 10"1, (Note f) , Particulate (1-131, Others)J Q

Continuous Composite (Note f) Particulate Gross Alpha 1-x 10"11 Sample Q

Continuous Composite (Note f) Particulate Sr-89, Sr-90 1 x 1011 Sample Continuous W (Note d)

J. Condenser Vent Stack Continuous Iodine Charcoal 1-131 1x 10-12 Sampler (Note j) (Note k) Sample

CY-TM-170-300 Revision 2 Page 62 of 209 Table 3.2-2 Table Notation

a. The LLD is defined, for purposes of this surveillance, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 Sb LLD =

ExVx2.22x106 xYxexp(-?At)

Where: LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume)

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 2.22 E6 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)

X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting.

Typical values of E, V, Y and At shall be used in the calculation.

It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.

b. Sampling and analysis shall also be performed following shutdown, startup, or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour, unless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

c. Tritium grab samples from the spent fuel pool area shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.

CY-TM-170-300 Revision 2 Page 63 of 209

d. Charcoal cartridges and particulate filters shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).

e. Tritium grab samples shall be taken weekly from the spent fuel pool area whenever spent fuel is in the spent fuel pool.

f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 2.2.2.1, 2.2.2.2, and 2.2.2.3.

g. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-1 38 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to TS 6.9.4.

h. Applicable only when condenser vacuum is established. Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

Gross Alpha, Sr-89, and Sr-90 analyses do not apply to the Fuel Handling Building ESF Air Treatment System.

j. If the Condenser Vent Stack Continuous Iodine Sampler is unavailable, then alternate sampling equipment will be placed in service within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or a report will be prepared, and submitted within 30 days from the time the sampler is found or made inoperable, which identifies (a) the cause of the inoperability, (b) the action taken to restore representative sampling capability, (c) the action taken to prevent recurrence, and (d) quantification of the release via the pathway during the period and comparison to the limits prescribed by Control 2.2.2.1.b.

k. Applicable only when condenser vacuum is established.

I. Applicable when liquid radwaste is moved or processed within the facility.

m. Iodine samples only required in the Chemical Cleaning Building when TMI-1 liquid radwaste is stored or processed in the facility.

CY-TM-170-300 Revision 2 Page 64 of 209 3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM.

CY-TM-1 70-300 Revision 2 Page 65 of 209 4.0 PART I REFERENCES 4.1 Title 10, Code of Federal Regulations, "Energy" 4.2 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routing Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, "Revision 1, October 1977 4.3 TMI-1 Technical Specifications, attached to Facility Operating License No.

DPR-50 4.4 TMI-1 FSAR

CY-TM-1 70-300 Revision 2 Page 66 of 209 PART II TMI-2 RADIOLOGICAL. EFFLUENT CONTROLS

CY-TM-1 70-300 Revision 2 Page 67 of 209 PART II Definitions 1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part II of the ODCM.

PDMS 1.2 Post-Defueling Monitored Storage (PDMS) is that condition where TMI-2 defueling has been completed, the core debris removed from the reactor during the clean-up period has been shipped off-site, and the facility has been placed in a stable, safe, and secure condition.

ACTION 1.3 ACTION shall be those additional requirements specified as corollary statements to each control and shall be part of the controls.

OPERABLE - OPERABILITY 1.4 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment, that are required for the system, subsystem, train, component or device to perform its function(s),

are also capable of performing their related support function(s).

CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter, which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CY-TM-170-300 Revision 2 Page 68 of 209 CHANNEL CHECK 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same. parameter.

CHANNEL FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channels - the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions.

SOURCE CHECK 1.8 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

COMPOSITE SAMPLE 1.9 A COMPOSITE SAMPLE is a combination of individual samples obtained at regular intervals over a time period. Either the volume of each individual sample is proportional to the flow rate discharge at the time of sampling or the number of equal volume samples is proportional to the time period used to produce the composite.

GRAB SAMPLE 1.10 A GRAB SAMPLE is an individual sample collected in less than fifteen minutes.

BATCH RELEASE 1.11 A BATCH RELEASE is the discharge of fluid waste of a discrete volume.

CONTINUOUS RELEASE 1.12 A CONTINUOUS RELEASE is the discharge of fluid waste of a non-discrete volume, e.g., from a volume or system that has an input flow during the CONTINUOUS RELEASE.

CY-TM-1 70-300 Revision 2 Page 69 of 209 SITE BOUNDARY 1.13 The SITE BOUNDARY used as the basis for the limits on the release of gaseous effluents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMI-1 FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Three Mile Island and between Three Mile Island and Shelley Island.

The SITE BOUNDARY used as the basis for the limits on the release of liquid effluents is as shown in Figure 1.1 in Part I of this ODCM.

FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

CY-TM-170-300 Revision 2 Page 70 of 209 TABLE 1.1 Frequency Notation NOTATION FREQUENCY S (Shiftly) At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D (Daily) At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W (Weekly) At least once per 7 days M (Monthly) At least once per 31 days Q (Quarterly) At least once per 92 days SA (Semi-Annually) At least once per 184 days A (Annually) At least once per 12 months E At least once per 18 months N.A. Not applicable P Completed prior to each release

CY-TM-170-300 Revision 2 Page 71 of 209 2.0 CONTROLS AND BASES 2.0.1 Controls and ACTION requirements shall be applicable during the conditions specified for each control.

2.0.2 Adherence to the requirements of the Control and/or associated ACTION within the specified time interval shall constitute compliance with the control. In the event the Control is restored prior to expiration to the specified time interval, completion of the ACTION statement is not required.

2.0.3 In the event the Control and associated ACTION requirements cannot be satisfied because of circumstances in excess of those addressed in the Control, initiate appropriate actions to rectify the problem to the extent possible under the circumstances, and submit a special report to the Commission pursuant to TMI-2 PDMS Technical Specification (Tech.

Spec.) Section 6.8.2 within 30 days, unless otherwise specified.

2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation Radioactive Liquid Effluent Instrumentation is common between TMI-1 and TMI-2. Controls, applicability, and actions are specified in ODCM Part I, Control 2.1.1 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CONTROL:

The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 2.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: As shown in Table 2.1-2 ACTION:

a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable.

CY-TM-170-300 Revision 2 Page 72 of 209

b. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-2. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.

BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301.

CY-TM-1 70-300 Revision 2 Page 73 of 209 Table 2.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY' ACTION

1. Containment Purge Monitoring System

a. Noble Gas Activity Monitor (2HP-R-225) 1 NOTE I NOTE 2

b. Particulate Monitor (2HP-R-225) 1 NOTE 1 NOTE 2

c. Effluent System Flow Rate Measuring Device (2AH-FR-5907 Point 1) 1 NOTE 1 NOTE 3

2. Station. Ventilation System

a. Noble Gas Activity Monitor (2HP-R-219) or (2HP-R-219A) 1 NOTE 1 NOTE 2

b. Particulate Monitor (2HP-R-219) or (2HP-R-219A) 1 NOTE 1 NOTE 2

c. Effluent System Flow Rate Monitoring Device (2AH-FR-5907 Point 6) 1 NOTE 1 NOTE 3 NOTES:

I. During operation of the monitored system.

2. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, secure Reactor Building Purge if in progress.

3. With flow rate monitoring instrumentation out of service, flow rates from the Auxiliary (2AH-FR-5907 Point 2), Fuel Handling (2AH-FR-5907 Point 4), Soiled Exhaust System (2AH-FR-5907 Point 5), and Reactor Buildings (2AH-FR-5907 Point 1) may be summed individually. Under these conditions, the flow rate monitoring device is considered operable. If the flow rates cannot be summed individually, they may be estimated using the maximum design flow for the exhaust fans, and the reporting requirements of Control 2.1.2.b are applicable.

CY-TM-170-300 Revision 2 Page 74 of 209 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration CONTROL:

The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2.

APPLICABILITY: At all times ACTION:

With the concentration of radioactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within the above limits.

BASES This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2. These Controls permit flexibility under unusual conditions, which may temporarily result in higher than normal releases, but still within ten times the concentrations, specified in 10 CFR 20. It is expected that by using this flexibility under unusual conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the annual average concentrations specified in 10 CFR 20. As a result, this Control provides reasonable assurance that the resulting annual exposure to an individual in off-site areas will not exceed the design objectives of Section II.A of Appendix I to 10 CFR Part 50, which were established as requirements for the cleanup of TMI -2 in the NRC's Statement of Policy of April 27, 1981.

CY-TM-1 70-300 Revision 2 Page 75 of 209 2.2.1.2 Liquid Effluent Dose CONTROL The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to the SITE BOUNDARY shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.

CY-TM-170-300 Revision 2 Page 76 of 209 BASES This Control requires that the dose to offsite personnel be limited to the design objectives of Appendix I of 10 CFR Part

50. This will assure the dose received by the public during PDMS is equivalent to or less than that from a normal operating reactor. The limits also assure that the environmental impacts are consistent with those assessed in NUREG-0683, the TMI-2 Programmatic Environmental Impact Statement (PEIS). The ACTION statements provide the required flexibility under unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". The dose calculations in the ODCM implement the requirements in Section III.A. of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April, 1977.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

CY-TM-170-300 Revision 2 Page 77 of 209 2.2.1.3 Liquid Radwaste Treatment System CONTROL:

The appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month.

APPLICABILITY: At all times ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and,

3. A summary description of action(s) taken to prevent a recurrence.

BASES The requirement that the appropriate portions of this system (shared with TMI-1) be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable. This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 1I.D of Appendix I to 10 CFR Part 50. The intent of Section ll.D. is to reduce effluents to as low as-is reasonably achievable in a cost effective manner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section II.A of Appendix I, 10 CFR Part 50 dose requirements.

This margin, a factor of 4, constitutes a reasonable reduction.

CY-TM-170-300 Revision 2 Page 78 of 209 2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL:

The dose rate due to radioactive materials released in gaseous effluent from the site shall be limited to the following:

a. For noble gases: less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and

b. For tritium and all radionuclides in particulate form with half lives greater than 8 days: less than or equal to 1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the release rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limit(s).

CY-TM-1 70-300 Revision 2 Page 79 of 209 BASES The control provides reasonable assurance that the annual dose at the SITE BOUNDARY from gaseous effluent from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. At the same time, these Controls permit flexibility under unusual conditions, which may temporarily result in higher than the design objective levels, but still within the dose limits specified in 10 CFR 20 and within the design objectives of Appendix I to 10 CFR 50. It is expected that using this flexibility under unusual conditions, and by exerting every effort to keep levels of radioactive material in gaseous wastes as low as practicable, the annual releases will not exceed a small fraction of the annual dose limits specified in 10 CFR 20 and will not result in doses which exceed the design objectives of Appendix I to 10 CFR 50, which were endorsed as limits for the cleanup of TMI-2 by the NRC's Statement of Policy of April 27, 1981. These gaseous release rates provide reasonable assurance that radioactive material discharged in gaseous effluent will not result in the exposure of a MEMBER OF THE PUBLIC in an unrestricted area, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the values specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. The absence of iodine ensures that the corresponding thyroid dose rate above background to a child via the inhalation pathway is less than or equal to 1500 mrem/yr (NUREG 1301), thus there is no need to specify dose rate limits for these nuclides.

CY-TM-1 70-300 Revision 2 Page 80 of 209 2.2.2.2 Gaseous Effluents Dose-Noble Gases CONTROL:

The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,

b. During any calendar year: less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-2.

CY-TM-1 70-300 Revision 2 Page 81 of 209 This control and associated action is provided to implement the requirements of Section II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide flexibility under unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable."

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"

Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

2.2.2.3 Dose - lodine-131, Iodine-1 33, Tritium, and Radionuclides In Particulate Form CONTROL:

The dose to a MEMBER OF THE PUBLIC from Tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: less than or equal to 7.5 mrem to any organ, and

b. During any calendar year: less than or equal to 15 mrem to any organ.

CY-TM-1 70-300 Revision 2 Page 82 of 209 APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of Tritium and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within, 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

CY-TM-170-300 Revision 2 Page 83 of 209 BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-2.

This control and associated action is provided to implement the requirements of Section II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in Section II.C of Appendix I. The ACTION statement provides flexibility during unusual conditions and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-1 31, iodine-1 33, tritium and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. The absence of iodines at the site eliminates the need to specify dose limits for these nuclides.

CY-TM-170-300 Revision 2 Page 84 of 209 2.2.2.4 Ventilation Exhaust Treatment System CONTROL The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected doses due to gaseous effluent releases from the site would exceed 0.3 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. A summary description of action(s) taken to prevent a recurrence.

BASES The use of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment. The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were

CY-TM-1 70-300 Revision 2 Page 85 of 209 specified as a suitable fraction of the guide set forth in Sections II.B and II.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose CONTROL:

The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a, 2.2.1.2.b, 2.2.2.2.a, 2.2.2.2.b, 2.2.2.3.a, or, 2.2.2.3.b, calculations should be made including direct radiation contributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. If such is the case, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b), shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

CY-TM-170-300 Revision 2 Page 86 of 209 BASES This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d). This control requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describea course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any member*of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

CY-TM-170-300 Revision 2 Page 87 of 209 3.0 SURVEILLANCES 3.0.1 Surveillance Requirements shall be applicable during the conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement. The Surveillance Requirements shall be performed to demonstrate compliance with the OPERABILITY requirements of the Control.

3.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

3.0.3 Failure to perform a Surveillance Requirement within the time interval specified in Section 3.0.2 shall constitute non-compliance with OPERABILITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not have to be performed on inoperable equipment.

3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation Surveillance Requirements Radioactive Liquid Effluent Instrumentation is common between TMI-1 and TMI-2. Surveillances for this instrumentation are specified in ODCM Part I, Surveillance 3.1.1.

3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation SURVEILLANCE REQUIREMENTS 3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance.of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2.

CY-TM-1 70-300 Revision 2 Page 88 of 209 Table 3.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECK CALIBRATION TEST APPLICABILITY

1. Containment Purge Monitoring System

a. Noble Gas Activity Monitor (2HP-R-225) D E M NOTE 1

b. Particulate Sampler (2HP-R-225) w N/A N/A NOTE 1

2. Station Ventilation Monitoring System

a. Noble Gas Activity Monitor (2HP-R-219) and (2HP-R-219A) D E M NOTE 1

b. Particulate Sampler (2HP-R-219) and (2HP-R-219A) w N/A N/A NOTE 1 NOTES:

1. During operation of the monitored system.

CY-TM-1 70-300 Revision 2 Page 89 of 209 3.2 Radioactive Effluents 3.2.1 Liquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration 3.2.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with Table 3.2-1. The results of analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.1.2 Analysis of samples composited from batch releases shall be performed in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2.1.1.

3.2.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month.

3.2.1.3 Dose Projections 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM.

CY-TM-1 70-300 Revision 2 Page 90 of 209 TABLE 3.2-1 Radioactive Liquid Waste Sampling and Analysis (4, 5)

A. Liquid Releases Sampling Frequency Type of Detectable

_Activity Analysis Concentration (3)

P Individual Gamma 5E-7 jiCi/ml (2)

Each Batch H-3 1E-5 ýtCi/ml Q Gross Alpha 1E-7 ýCi/ml Quarterly Composite (1) Sr-90 5E-8 piCi/ml NOTES:

(1) A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.

(2) For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near this sensitivity limit when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using measured ratios with those radionuclides, which are routinely identified and measured.

(3) The detectability limits for radioactivity analysis are based on the technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported.

(4) The results of these analyses should be used as the basis for recording and reporting the quantities of radioactive material released in liquid effluents during the sampling period. In estimating releases for a period when analyses were not performed, the average of the two adjacent data points spanning this period should be used. Such estimates should be included in the effluent records and reports; however, they should be clearly identified as estimates, and the method used to obtain these data should be described.

(5) Deviations from the sampling/analysis regime will be noted in the report specified in ODCM Part IV.

CY-TM-1 70-300 Revision 2 Page 91 of 209 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates 3.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1 .a in accordance with the methods and procedures of the ODCM.

3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 3.2-2.

3.2.2.2 Dose, Noble Gas 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.3 Dose, Tritium and Radionuclides In Particulate Form 3.2.2.3.1 Cumulative dose contributions from Tritium and radionuclides in particulate form with half lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.4 Ventilation Exhaust Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM.

CY-TM-1 70-300 Revision 2 Page 92 of 209 TABLE 3.2-2 Radioactive Gaseous Waste Sampling and Analysis (3)

SAMPLING TYPE OF DETECTABLE SAMPLE FREQUENC ACTIVITY CONCENTRATION SAMPLE POINT TYPE Y ANALYSIS (1)(a)

P H-3 1E-6 pCi/cc Reactor Building Purge Gas Individual 1E-4 pCi/cc (2)

Releases EachGamma Emitters M H-3 1E-6 jiCi/cc Unit Exhaust Vent Release Gas Individual Points Monthly Gamma Emitters 1E- jiCi/cc (2)

W Individual (b) IE-10 tCi/cc (2)

Weekly Gamma Emitters M

Particulate Monthly Sr-90 1E-1 1 pjCi/cc s Composite M Gross Alpha 1E-11 pCi/cc Monthly Emitters Composite lndv. Gamma 1E-l1 pCi/cc (2)

Reactor Building Breather SA Emitters (b) 1E-10__i/cc_(2 P Semi-Annual Sr-90 1E-1 1 pCi/cc ly Gross Alpha 1E-1 1 pCi/cc I - Emitters 1E-11_ __i/cc (1) The above detectability limits are based on technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported.

(2) For certain mixtures of gamma emitters, it may be possible to measure radionuclides at levels near their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios in the gaseous component in the reactor coolant for those radionuclides which are measurable.

(3) Deviations from the sampling and analysis regime will be noted in the report specified in ODCM Part IV.

CY-TM-1 70-300 Revision 2 Page 93 of 209 TABLE 3.2-2 Radioactive Gaseous Waste Sampling and Analysis Program Table Notation

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD = 4.66 sp E x V x 2.22 x 106 x Y x exp (-AAt)

Where LLD is the lower limit of detection as defined above (as picocurie per unit mass or volume).

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).

E is the counting efficiency (as counts per transformation),

V is the sample size (in units of mass or volume),

2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples),

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and At shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be with +/-

one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma-ray peak used for the quantitative analysis for that radionuclide.

CY-TM-170-300 Revision 2 Page 94 of 209 TABLE 3.2-2 Notation (Cont'd)

b. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations.

CY-TM-1 70-300 Revision 2 Page 95 of 209 3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM.

CY-TM'1 70-300 Revision 2 Page 96 of 209 4.0 PART II REFERENCES 4.1 NUREG-0683, "Final Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979, accident Three Mile Island Nuclear Station, Unit 2," March 1981, and its supplements.

4.2 TMI-2 PDMS Technical Specifications, attached to Facility License No. DPR-73 4.3 Title 10, Code of Federal Regulations, "Energy" 4.4 "Statement of Policy Relative to the NRC Programmatic Environmental Impact Statement on the Cleanup of Three Mile Island Unit 2," dated April 27, 1981 4.5 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 4.6 DOE/TIC-27601, Atmospheric Science and Power Reduction 4.7 TMI-1 Technical Specifications, attached to Facility Operating License No.

DPR-50 4.8 PDMS - SAR

CY-TM-170-300 Revision 2 Page 97 of 209 PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES

CY-TM-170-300 Revision 2 Page 98 of 209 1.0 LIQUID EFFLUENT MONITORS 1.1 TMI-1 and TMI-2 Liquid Radiation Monitor Set Points The liquid effluent off-line monitors are set such that the concentration(s) of radionuclides in the liquid effluents will not exceed ten times the concentrations specified in 10 CFR 20, Appendix B Table 2, Col 2. Table 1.1 lists the Liquid Effluent Release Points and their parameters; Figure 1.1 provides a Liquid Release Pathway Diagram.

To meet the above limit, the alarm/trip set points for liquid effluent monitors and flow measuring devices are set in accordance with the following equation:

C f< C (eq 1.1)

Where:

C = ten times the effluent concentration of 10 CFR 20 for the site, in gCi/ml.

c = the set point, in iiCi/ml, of the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to dilution and release.

The set point is inversely proportional to the maximum volumetric flow of the effluent line and proportional to the minimal volumetric flow of the dilution stream plus the effluent stream. The alert set point value is set to ensure that advance warning occurs prior to exceeding any limits. The high alarm set point value is such that if it were exceeded, it would result in concentrations exceeding ten times the 10 CFR 20 concentrations for the unrestricted area.

f = flow set point as measured at the radiation monitor location, in volume per unit time, but in the same units as F below.

F = flow rate of dilution water measured prior to the release point, in volume per unit time.

The set point concentration is reduced such that concentration contributions from multiple release points would not combine to exceed ten times 10 CFR 20 concentrations. The set point concentration is converted to set point scale units using appropriate radiation monitor calibration factors.

This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and, for batch releases, the Releasing Radioactive Liquid Waste procedure.

CY-TM-170-300 Revision 2 Page 99 of 209 1.2 TMI Liquid Effluent Release Points and Liquid Radiation Monitor Data TMI-1 has two required liquid radiation monitors. These are RM-L6 and RM-L12.

These liquid release point radiation monitors and sample points are shown in Table 1.1. (The TMI outfall radiation monitor, RM-L7, is also listed for information only.)

TMI-2 does not have any required liquid radiation monitors, but does utilize RM-L12, and RM-L7 for release of liquid waste.

1.2.1 RM-L6 RM-L6 is an off-line system, monitoring radioactive batch discharges from the TMI-1 liquid radwaste system (see Figure 1.1). These batch releases are sampled and analyzed per site procedures prior to release.

The release rate is based on releasing one of two Waste Evaporator Condensate Storage Tanks (WECST) at a flow which will add less than 10%, of ten times the 10 CFR 20 concentrations [20% for H-3] to radionuclide concentrations in the unrestricted area, including conservative default values for Sr-89, Sr-90, and Fe-55.

The release flow rate used is the most restrictive of two flow rates calculated for each liquid batch release, per the approved plant procedure.

Two Dilution Factors (DF) are calculated to ultimately calculate the batch release. flow rate. These two DF's are calculated to insure each radionuclide released to the unrestricted area is less than 10 percent of ten times the 10CFR20 radionuclide concentrations, (20% for H-3), and to ensure each liquid batch release boron concentration to the river will not exceed 0.7 ppm.

The maximum release flow rate is then calculated by dividing the most restrictive (largest) DF into 90 percent of the current dilution flow rate of the Mechanical Draft Cooling Tower (MDCT). This conservative flow rate is then multiplied by 0.9 for the allowable flow rate.

• Calculation of the IOCFR20 concentration DF:

DF1 = I (SA) ÷ (10% [20% for H-3] of ten times the IOCFR20 concentration)

SA = Specific Activity of each identified radionuclide

• Calculation of Boron DF:

DF2 = Actual Tank Boron Concentration - 0.7.

CY-TM-170-300 Revision 2 Page 100 of 209 Maximum release flow rate calculation:

Max Flow = [(MDCT flow gpm

• 0.9) + (Most Restrictive DF)]

• 0.9 The dilution flow rate used is the current flow rate at the site. The minimum dilution flow rate is 5000 gpm per the TMI-1 FSAR. This ensures this batch release will meet the following equation.

M.(CIXi) + (CH.3/2XH.3) < 0.1, (eq 1.2)

Where: Ci = diluted concentration of the ith radionuclide, other than H-3 Xi = Ten times the concentration for that radionuclide in the unrestricted area (10 CFR 20, App. B, Table 2, Col. 2). A value of 3E-3 ýtCi/ml for dissolved and entrained noble gases shall be used.

CH-3 = diluted concentration of H-3 XH-3 = Ten times the concentration for H-3 in the restricted area (10 CFR 20, App. B, Table 2, Col. 2).

The set points for RM-L6 are based on the maximum release rate (30 gpm), a minimum dilution flow (5000 gpm), and 25% of ten times the

-10CFR20 concentration for Cs-1 37, which is the most limiting radionuclide at a concentration of 1.OE-5 uCi/mI. These inputs are used in Equation 1.1 to determine the RM-L-6 High Alarm setpoint for all radionuclides being released. A high alarm on RM-L-6 will close valve WDL-V-257 and terminate any WECST releases to the environment.

1.2.2 RM-L12 RM-L12 is an off-line system, monitoring periodic combined releases from the Industrial Waste Treatment System/Industrial Waste Filtration System (IWTS/IWFS). The input to IWTS/IWFS originates in TMI-2 sumps, (see Figures 1.1 and 1.2) and the TMI-1 Turbine Building sump (see Figure 1.1). The set points are based on the maximum release rate from both IWTS and IWFS simultaneously, (see Figure 1.1) a minimum dilution flow rate, and 50% of ten times the 10CFR20 concentration for Cs-137, which is the most limiting radionuclide at a concentration of 1E-5 jiCi/ml. These inputs are used in equation 1.1 to determine the RM-L12 High Alarm set point for all radionuclides being released. A high alarm on RM-L12 will close IWTS and IWFS release valves and trip release pumps to stop the release.

CY-TM-1 70-300 Revision 2 Page 101 of 209 1.2.3 RM-L10 RM-L10 was a Nal detector submerged in the TMI-1 Turbine Building Sump. This detector has been removed from service.

1.2.4 RM-L7 RM-L7 is not an ODCM required liquid radiation monitor. RM-L7 is an off-line system, monitoring the TMI outfall to the Susquehanna River (see Figures 1.1 and 1.2). This monitor is the final radiation monitor for TMI-1 and TMI-2 normal liquid effluent releases.

1.3 Control of Liquid Releases TMI liquid effluent releases are controlled to less than ten times the 10CFR20 concentrations by limiting the percentage of this limit allowable from the two TMI liquid release points. RM-L6 and effluent sampling limit batch releases to less than or equal to 25% for all radionuclides, and RM-L12 and effluent sampling limit releases from TMI-1 and TMI-2 to less than or equal to 50% for Cs-1 37.

These radiation monitor set points also include built in meter error factors to further ensure that TMI liquid effluent releases are less than ten times the 10CFR20 concentrations to the environment.

The radioactivity content of each batch of radioactive liquid waste is determined prior to release by sampling and analysis in accordance with ODCM Part I Table 3.2-1 or ODCM Part II, Table 3.2-1. The results of analyses are used with the calculational methods in Section 1.1, to assure that the concentration at the point of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1.

Post-release analysis of samples composited from batch releases are performed in accordance with ODCM Part I Table 3.2-1 or ODCM Part II Table 3.2-1. The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1.

The radioactivity concentration of liquids discharged from continuous release points are determined by collection and analysis of samples in accordance with ODCM Part I Table 3.2-1, or ODCM Part II Table 3.2-1. The results of the analysis are used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1.

CY-TM-1 70-300 Revision 2 Page 102 of 209 TABLE 1.1 TMI Liquid Release Point and Liquid Radiation Monitor Data RELEASE LIQUID RADIATION LIQUID RELEASE TERMINATION MONITOR POINT (Maximum DISCHARGE FLOW INTERLOCK (DETECTOR) LOCATION Volume) RECORDER (YES/NO) VALVES RM-L6 281' Elevation WECST Batch YES (Nal) TMI-1 Auxiliary Bldg Releases (8000 gal.) WDL-V257 RM-L7 South end of TMI-1 Station Discharge YES (Nal) MDCT TMI-1 and FT-146 WDL-V257

• • TMI-2, *WDL-R-1311 YES IWTS/IWFS IW-V73, RM-L12 IWFS Building NW Continuous Releases FT-342/ IW-P16,17,18 (Nal) Corner (300,0001 FT-373 80,000 gal.) IW-V279, I _IW-P29,30

• WDL-R-1311 has been flanged off as a TMI-2 liquid outfall.

• • RM-L7 is not an ODCM required liquid radiation monitor.

CY-TM-1 70-300 Revision 2 Page 103 of 209 TABLE 1.2 TMI-2 Sump Capacities Total Capacity Gallons Sump Gallons per Inch Turbine Building Sump 1346 22.43 Circulating Water Pump House Sump 572 10.59 Control Building Area Sump 718 9.96 Tendon Access Galley Sump 538 9.96 Control to Service Building Sump 1346 22.43 Contaminated Drain Tank Room Sump 135 3.80 Chlorinator House Sump ....

Water Treatment Sump** 1615 22.43 Air Intake Tunnel Normal Sump 700 ----

Air Intake Tunnel Emergency Sump 100000 766.00 Condensate Polisher Sump* 2617 62.31 Sludge Collection Sump** 1106 26.33 Heater Drain Sump ---- --...

Solid Waste Staging Facility Sump 1476 24.00 Auxiliary Building Sump 10102 202.00 Decay Heat Vault Sump 479 10.00 Building Spray Vault Sump 479 10.00

• Condensate Polisher Sump is deactivated and in PDMS condition.

• • The Water Treatment and Sludge Collection Sumps will be deactivated for PDMS.

CY-TM-170-300 Revision 2 Page 104 of 209 Componemt. Mech~anical raft CoOling- Coting Tower 00101. .Water-TMI;-1 rI-

CY-TM-1 70-300 Revision 2 Page 105 of 209 FIGURE 1.2 TMI-2 Liquid Effluent Pathways CONTROL CONTROL &

BUILDING SERVICE SUMP AREA SUMP INDUSTRIAL WASTE TREATMENT SYSTEM

-- COMPOSITE SAMPLER

CY-TM-1 70-300 Revision 2 Page 106 of 209 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liquid Effluents - 10 CFR 50 Appendix I The dose from liquid effluents results from the consumption of fish and drinking water. The location of the nearest potable water intake is PP&L Brunner Island Steam Electric Station located downstream of TMI. The use of the flow of the Susquehanna River as the dilution flow is justified based on the complete mixing in the river prior to the first potable water supply, adequately demonstrated by flume tracer die studies and additional liquid effluent release studies conducted using actual TMI-1 tritium releases. Other pathways contribute negligibly at Three Mile Island. The dose contribution from all radionuclides in liquid effluents released to the unrestricted area is calculated using the following expression:

Dosej=. (At)X (ci) X AWij X -i + (AFij X f X 1 (eq 2.1)

[yVVJFR) FD DF Where:

Dose j = the cumulative dose commitment to the total body or any organ, j, from the liquid effluents for the total time period, in mrem.

At = the length of the time period of actual releases, over which Ci and f are averaged for all liquid releases, in hours.

C = the average concentration of radionuclide, i, in undiluted liquid effluent during time period At from any liquid release, in ýtCi/ml.

NOTE: For Fe-55, Sr-89, Sr-90, prior to batch releases conservative concentration values will be used in the initial dose calculation based on similar past plant conditions. LLD values are not used in dose calculations.

f= undiluted liquid waste flow, in gpm.

FD = plant dilution water flowrate during the period of release, in gpm FR = actual river flowrate during the period of release or average river Iowrate for the month the release is occurring, in gpm.

DF = dilution factor as a result of mixing effects in the near field of the discharge structure of 0.2 (NUREG 0133) or taken to be 5 based on the inverse of 0.2.

AWij and AFij = the site-related ingestion dose commitment factor to the total body or any organ, j, for each identified principle gamma and beta emitter, in mrem/hr per pCi/ml. AW is the factor for the water pathway and AF is the factor for the fish pathway.

CY-TM-170-300 Revision 2 Page 107 of 209 Values for AWij are determined by the following equation:

AW11 = (1.14E5) x (U,) x (DF 1j) (eq 2.2)

Where:

1.14E5 = (1.0E6 pCi/ILCi) x (1.0E3 mi/kg) - (8760 hrlyr)

Uw = Water consumption rate for adult is 730 kg/yr (Reg. Guide 1.109, Rev. 1).

DFij = ingestion dose conversion factor for radionuclide, i, for adults total body and for "worst case" organ, j, in mrem/pCi, from Table 2.1 (Reg. Guide 1.109)

Values for AFij are determined by the following equation:

AFij = (1.14E5) x (Uf) x (DFij) x (BFi) (eq 2.2.2) where:

1.14E5 = defined above Uf = adult fish consumption, assumed to be 21 kg/yr (Reg. Guide 1.109, Rev. 1).

DFij = ingestion dose conversion factor for radionuclide, i, for adult total body and for "worst case" organ, j, in mrem/pCi, from Table 2.1 (Reg. Guide 1.109, Rev. 1).

BFi = Bioaccumulation factor for radionuclide, i, in fish, in pCi/kg per pCi/L from Table 2.2 (Reg. Guide 1.109, Rev. 1).

2.2 TMI Liquid Radwaste System Dose Calcs Once/Month ODCM Part I Control 2.2.1.3 and TMI-2 PDMS Tech Spec Section 6.7.4.a.6 requires that appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the monthly projected doses due to the liquid effluent releases from each unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month. The following calculational method is provided for performing this dose projection.

At least once per month, the total dose from all liquid releases for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual releases during the period for which the projection is made. Ifthis projected dose exceeds 0.06 mrem total body or 0.2 mrem any organ, appropriate portions of the Liquid Radwaste Treatment System, as

CY-TM-170-300 Revision 2 Page 108 of 209 defined in Section 3.1, shall be used to reduce radioactivity levels prior to release.

At the discretion of the ODCM Specialist, time periods other than the current quarter-to-date may be used to project doses if the dose per day in the current quarter-to-date-is not believed to be representative of the dose per day projected for the next month.

2.3 Alternative Liquid Dose Calculational Methodology As an alternative, models in, or based upon, those presented in Regulatory Guide 1.109 (Rev. 1) may be used to make a comprehensive dose assessment.

Default parameter values from Reg. Guide 1.109 (Rev. 1) and/or actual site specific data are used where applicable.

As an alternative dose calculational methodology TMI calculates doses using SEEDS (simplified environmental effluent dosimetry system).

The onsite and SEEDS calculational models use actual liquid release data with actual monthly Susquehanna River flow data to assess the dispersion of effluents in the river.

CY-TM-1 70-300 Revision 2 Page 109 of 209 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFIj Page 1 of 3 Ingestion Dose Factors for Adults*

(MREM Per PCI Ingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 CR.51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 MN.56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91 E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO.58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01 E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI.65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.1OE-07 NO DATA 7.1OE-06 ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN.69 1.03E-08 1.97E-08 1 .37E-09 NO DATA 1 .28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21 E-08 NO DATA NO DATA NO DATA 8.36E-19 RB.89 NO DATA 4.01E-08 2,82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR. 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04

CY-TM-1 70-300 Revision 2 Page 110 of 209 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DF1 j Page 2 of 3 Ingestion Dose Factors for Adults*

(MREM Per PCI Ingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 NB-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31 E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC. 101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU 103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU 105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 RU.06 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31 E-06 NO DATA 1.78E-04 AG 110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91 E-07 NO DATA 6.04E-05 SB 125 1.79E-06 2.OOE-08 4.26E-07 1.82E-09 0.0 1.38E-06 1.97E-05 TE 125M 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE.127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE 127 1.1OE-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE 129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09

?i* i... ... ...*r;......

• b. . .....  :*

... *..... ... .3-. ....... .... .;6 *...... . i.. . ...... . ....5;f

.... .... ..* 1*6 TE - 32..13 ....... 2.5E-60.....1.66330E 6 ..... 151.35E06--------11.80.0E0- 611.557E.E ..... ..... NO DDATA... 77.. .11E--005 .

I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 I 131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 I ........ "132

---

.......... 6b3E-07 32...... 3E0 ........ 5.

.4 ..,3*-

5.43 E.....

0. -----

.... I 1-,9-

.0- E:-00 ........... 1';9.9E

-I--- ."

..-055 ........ 8,6.6-55E. 00.' -----

.... NO...

O.DATA,"".

DATA-....... I .02 -.0.7 1----

.0.....0.7 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51 E-10

CY-TM-1 70-300 Revision 2 Page 111 of 209 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 3 of 3 Ingestion Dose Factors for Adults*

(MREM Per PCI Ingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI I 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS 134 6.22E-05 1.48E-04 1.21 E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 CS 136 6.51 E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS 137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91 E-09 4.65E-13 BA 139 9.70E-08 6.91 E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 BA 140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA 141 4.71 E-08 3.56E-11 1.59E-09 NO DATA 3.31 E-11 2.02E-11 2.22E-17 BA 142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.OOE-26 LA.140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA 142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05

-1_4*........ *i65,E--9, ........ 22E ----..... 35.E5-- ...*.........NO N .D ..T ..... 5.37E-1'0 ........."N N O D TA..... 4.56E-0'5 CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21 E-07 NO DATA 1.65E-04 PR 143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR 144 3.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61 E-08 3.01 E-08 NO DATA NO DATA NO DATA 2.82E-05

... 2 *......---- .... .11*EE'9-........ 6.45*E N*A3N .. ..... ....

k"A' N_. T-0" Dose factors of internal exposure are for continuous intake over a one-year period and include the dose commitment over a 50-year period; from Reg. Guide 1.109 (Rev. 1).

Additional dose factors for nuclides not included in this table may be obtained from NUREG-0172.

CY-TM-170-300 Revision 2 Page 112 of 209 TABLE 2.2 Bioaccumulation Factors, BF, Bioaccumulation Factors to be Used in the Absence of Site-Specific Data*

(pCi/kg per pCi/liter)

ELEMENT FRESHWATER FISH -INVERTEBRATE H 9.OE-01 9.OE-01 C 4.6E+03 9.1E+03 NA 1.OE+02 2.OE+02 CR 2.OE+02 2.OE+03 MN 4.OE+02 9.OE+04 FE 1.OE+02 3.2E+03 CO 5.OE+01 2.OE+02 NI 1.OE+02 1.0E+02 CU 5.OE+01 4.OE+02 ZN 2.OE+03 1.OE+04 BR 4.2E+02 3.3E+02 RB 2.OE+03 1.OE+03 SR 3.OE+01 1.OE+02 Y 2.5E+01 1.OE+03 ZR 3.3E+00 6.7E+00 NB 3.OE+04 1.OE+02 MO 1.OE+01 1.OE+01 TC 1.5E+01 5.OE+00 RU 1.OE+01 3.OE+02 RH 1.OE+01 3.0E+02

• • • AG-110m 2.30E+1 7.70E+2

• • SB 1.OE+00 1.OE+00 TE 4.OE+02 6.1E+03 I 1.5E+01 5.OE+O0 CS 2.OE+03 1.OE+03 BA 4.OE+00 2.OE+02 LA 2.5E+01 1.OE+03 CE 1.OE+00 1.QE+03 PR 2.5E+01 1.OE+03 ND 2.5E+01 1.OE+03 W 1.2E+03 1.OE+01 NP 1.OE+O1 4.OE+02 Bioaccumulation factor values are taken from Reg. Guide 1.109 (Rev. 1), Table A-lj.

• • Sb bioaccumulation factor value is taken from EPRI NP-3840.

Ag bioaccumulation factor value is taken from Reg. Guide 1.109 (Rev. 0), Table A-8.

CY-TM-1 70-300 Revision 2 Page 113 of 209 3.0 TMI LIQUID EFFLUENT WASTE TREATMENT SYSTEMS 3.1 TMI-1 Liquid Effluent Waste Treatment System 3.1.1 Description of the Liquid Radioactive Waste Treatment System (see Figure 3.1)

Reactor Coolant Train

a. Water Sources - (3) Reactor Coolant Bleed Tanks (RCBT)

- (1) Reactor Coolant Drain Tank (RCDT)

b. Liquid Processing - Reactor Coolant Waste Evaporator

- Demineralizers prior to release (see Figure 3.2)

c. Liquid Effluent for Release- (2) Waste Evaporator Condensate Storage Tanks - (WECST)

d. Dilution - Mechanical Draft Cooling Tower (0-38k gpm)

- River Flow (2E7 gpm average)

Miscellaneous Waste Train

a. Water sources: - Auxiliary Building Sump

- Reactor Building Sump

- Miscellaneous Waste Storage Tank

- Laundry Waste Storage Tank

- Neutralizer Mixing Tank

- Neutralizer Feed Tank

- Used Precoat Tank

- Borated Water Tank Tunnel Sump

- Heat Exchanger Vault Sump

- Tendon Access Galley Sump

- Spent Fuel Pool Room Sump

- TMI-2 Miscellaneous Waste Holdup Tank

CY-TM-170-300 Revision 2 Page 114 of 209

b. Liquid Processing - Miscellaneous Waste Evaporator, MWE

- Demineralizers prior to release (see Figure 3.2)

c. Liquid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks- (WECST)

d. Dilution - Mechanical Draft Cooling Tower (0-38k gpm)

- River Flow (2E7 gpm average) 3.2 Operability of the TMI-1 Liquid Effluent Waste Treatment System 3.2.1 The TMI-1 Liquid Waste Treatment System as described in Section 11 of the TMI-1 Final Safety Analysis Report is considered to be operable when one of each of the following pieces of equipment is available to perform its intended function:

a) Miscellaneous Waste Evaporator (WDL-Z1 B) or Reactor Coolant Evaporator (WDL-Zl A) b) Waste Evaporator Condensate Demineralizer (WDL-K3 A or B) c) Waste Evaporator Condensate Storage Tank (WDL-T 11 A or B) d) Evaporator Condensate Pumps (WDL-P 14 A or B) 3.2.2 TMI-1 Representative Sampling Prior to Discharge All liquid releases from the TMI-1 Liquid Waste Treatment System are made through the Waste Evaporator Condensate Storage Tanks. To provide thorough mixing and a representative sample, the contents of the tank are recirculated using one of the Waste Evaporator Condensate Transfer Pumps.

3.3 TMI-2 Liquid Effluent Waste Treatment System 3.3.1 Description of the TMI-2. Liquid Radioactive Waste Treatment System The TMI-2 Liquid Radioactive Waste Treatment System has been out of service since the TMI-2 Accident in 1979. TMI-2 Liquid Radioactive Waste is processed by the TMI-1 system described in Section 3.1 prior to release. In addition, TMI-2 releases water from various sumps and tanks to the river (see Figures 1.1 and 1.2). These processes are governed by plant procedures that encompass proper sampling, sample analysis, and radiation monitoring techniques.

CY-TM-1 70-300 Revision 2 Page 115 of 209 FIGURE 3.1 TMI-1 Liquid Radwaste RECLAIMED WATER SYSTEM

CY-TM-1 70-300 Revision 2 Page 116 of 209 FIGURE 3.2 TMI-1 Liquid Waste Evaporators

CY-TM-1 70-300 Revision 2 Page 117 of 209 4.0 GASEOUS EFFLUENT MONITORS 4.1 TMI-1 Noble Gas Monitor Set Points The gaseous effluent monitor set points are established for each gaseous effluent radiation monitor to assure concentrations of radionuclides in gaseous effluents do not exceed the limits set forth in ODCM Part I Control 2.2.2.1.

Table 4.1 lists Gaseous Effluent Release Points and their associated parameters; Figure 4.1 provides a Gaseous Effluent Release Pathway Diagram.

The set points are established to satisfy the more restrictive set point concentration in the following two equations:

500 > i (c1)(F)(K 1)(Dv) (eq 4.1.1) and 3000 > * (cq)( 1i + 1.1 Mi)(Dv)(F) (eq 4.1.2)

Where: c1 = set point concentration based on Xe-133 equivalent, in iCi/cc F =gaseous effluent flowrate at the monitor, in cc/sec Ki =total body dose factor, in mrem/yr per p.Ci/m 3 from Table 4.3 Dv = highest sector annual average gaseous atmospheric dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/M 3 , from Table 4.4 for station vent releases and Table 4.5 for all other releases, (Condenser off gas, ESF FHB, and ground releases). Maximum values presently used are 7.17E-7 sec/m 3 at sector NNE for station vent, and 1.1 6E-5 sec/m 3 at sectors N and WNW for all other releases.

Li= skin dose factor due to beta emissions from radionuclide i, in mrem/yr per A.Ci/m 3 from Table 4.3.

Mi = air dose factor due to gamma emissions from radionuclide i, in mrad/yr per VCi/m 3 from Table 4.3.

1.1 = mrem skin dose per mrad air dose.

500 = annual whole body dose rate limit for unrestricted areas, in mrem/yr.

3000 = annual skin dose rate limit for unrestricted areas, in mrem/yr.

CY-TM-170-300 Revision 2 Page 118 of 209 The set point concentration is further reduced such that the concentration contributions from multiple release points would not combine to exceed ODCM Control limits.

The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors.

This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste.

.1

CY-TM-1 70-300 Revision 2 Page 119 of 209 4.2 TMI-1 Particulate and Radioiodine Monitor Set Points Set points for monitors which detect radionuclides other than noble gases are also established to assure that concentrations of these radionuclides in gaseous effluents do not exceed the limits of ODCM Part I Control 2.2.2.1.

Set points are established so as to satisfy the following equations:

1500 > ý (c1)(F)(Pj)(Dv) (eq 4.2)

Where: ci = set point concentration based on 1-131 equivalent for radioiodine monitor and Sr-90 for particulate monitor, in liCi/cc F = gaseous effluent flow rate at the monitor, in cc/sec Pi = pathway dose parameter, in mrem/yr per VCi/m3 for the inhalation pathway from Table 4.6. The dose factors are based on the actual individual organ and most restrictive age group (child) (NUREG-0133).

NOTE: Appendix A contains Pi calculational methodology.

1500 = annual dose rate limit to any organ from particulates and radioiodines and radionuclides (other than noble gases) with half lives greater than eight days in mrem/yr.

Dv = highest sector annual average gaseous dispersion factor (X/Q or D/Q) at or beyond the unrestricted area boundary from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. X/Q is used for the inhalation pathway. Maximum values of X/Q presently used are 7.17E-7 sec/m3 for station vent, at sector SE, and 1.16E-5 sec/m3 for all other releases, at sectors N and WNW.

The set point concentration is further reduced such that concentration contributions from multiple release points would not combine to exceed ODCM Control limits.

The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors.

This section of the ODCM is implemented by the Radiation Monitor Systems Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste.

CY-TM-1 70-300 Revision 2 Page 120 of 209 4.3 TMI-2 Gaseous Radiation Monitor Set Points TMI-2 Gaseous Radiation Monitors have their set points described in TMI Plant Procedure 1101-2.1. Figure 4.5 provides a gaseous effluent release pathway diagram. Table 4.2 provides TMI-2 Radiation Monitor Data.

These set points are set in accordance with the Controls delineated in Part II of this ODCM.

CY-TM-1 70-300 Revision 2 Page 121 of 209 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMI-1 has eleven (11) required effluent gaseous radiation monitors. These are RM-A4, RM-A5, RM-A15, RM-A6, RM-A7, RM-A8, RM-A9, RM-A14, ALC-RMI-18, WHP-RIT-1, and RLM-RM-1. These gaseous release points, radiation monitors, and sample points are shown in Table 4.1.

4.4.1 RM-A4/RM-A6 Fuel Handling and Auxiliary Building Exhaust RM-A4 is the radiation monitor for the TMI-1 Fuel Handling Building Ventilation (see Figures 4.1 and 4.2). RM-A6 is the radiation monitor for the TMI-1 Auxiliary Building Ventilation (see Figures 4.1 and 4.2). High alarms on RM-A4 or RM-A6 noble gas channels will initiate shutdown of the related building ventilation air supply system. These two radiation monitors concurrently will satisfy requirements for the Station Vent release point in place of RM-A8.

4.4.2 RM-A8 Station Ventilation Exhaust RM-A8 is the particulate, radioiodine and gaseous radiation monitor for the TMI-1 Station Ventilation (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters. High alarm on RM-A8 noble gas low channel will initiate shutdown of the Station Ventilation air supply systems. (The Fuel Handling and Auxiliary Building Ventilation).

This radiation monitor satisfies requirements for the Station Vent release point in place of RM-A4 and RM-A6.

4.4.3 RM-A5/RM-Al 5 Condenser Off Gas Exhaust RM-A5 is the gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). RM-A15 is the back up gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). High alarms on RM-A5 low channel or RM-A15 noble gas channels will initiate the MAP-5 Radioiodine Processor Station. These two radiation monitors together satisfy requirements for the Condenser Off Gas release point' 4.4.4 RM-A7 Waste Gas Decay Tank Exhaust RM-A7 is the gaseous radiation monitor for the TMI-1 Waste Gas Decay tanks (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel. High alarm on RM-A7 noble gas channel will initiate shutdown of the Waste Gas Decay Tank release in progress. This radiation monitor satisfies requirements for batch gaseous releases to the Station Vent release point.

CY-TM-170-300 Revision 2 Page 122 of 209 4.4.5 RM-A9 Reactor Building Purge Exhaust RM-A9 is the particulate, radioiodine and gaseous radiation monitor for the TMI-1 Reactor Building Purge system (see Figures 4.1 and 4.3).

This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters. High alarm on RM-A9 noble gas low channel will initiate shutdown of the Reactor Building Purge System. This radiation monitor satisfies requirements for the Reactor Building Purge System release point.

4.4.6 RM-A14 ESF FHB Ventilation System RM-A14 is the gaseous radiation monitor for the TM I-1 Emergency Safeguards Features (ESF) Fuel Handling Building Exhaust system (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sampler filters. High alarm on RM-A14 noble gas channel will initiate shutdown of the ESF Fuel Handling Building Exhaust System. This radiation monitor satisfies requirements for the ESF Fuel Handling Building Exhaust System release point.

4.4.7 ALC-RMI-18 Chemical Cleaning Facility (CCF) Ventilation Exhaust ALC-RMI-18 is an Victoreen particulate, radioiodine, and gaseous radiation monitor for the Chemical Cleaning building exhaust. This monitor is located in the Chemical Cleaning building on the ground floor, and has an associated sample panel. Sampling for particulate activity is performed off of the monitor.

4.4.8 WHP-RIT-1 Waste Handling and Packaging Facility (WHPF) Exhaust WHP-RIT-1 is an Eberline AMS-3 particulate radiation monitor for the TMI WHPF. The monitor is located in the Mechanical Equipment Room in the WHPF. Sampling for particulate activity is performed off of the monitor. A high alarm will initiate shutdown of the ventilation air exhaust system.

4.4.9 RLM-RM-1 Respirator Cleaning and Laundry Maintenance (RLM)

Facility RLM-RM-1 is an Eberline AMS-3 particulate radiation monitor for the TMI RLM Facility. The monitor is located in the Mechanical Equipment Room in the RLM. Sampling for particulate activity is performed off of the -monitor.

CY-TM-1 70-300 Revision 2 Page 123 of 209 4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMI-2 has three (3) regulatory required gaseous effluent radiation monitors.

These are HP-R-219, HP-R-219A and HP-R-225. These gaseous release points, radiation monitors, and sample points are shown in Table 4.2, and various gaseous effluent pathways are depicted in Figure 4.5.

4.5.1 HP-R-219 Station Ventilation Exhaust HP-R-219 is a Victoreen particulate and gaseous radiation monitor for the TMI-2 ventilation exhaust. This in-plant effluent radiation monitor is located in the TMI-2 Auxiliary Building 328 foot elevation and has an associated sample panel.

4.5.2 HP-R-219A Station Ventilation Exhaust HP-R-219A is a Victoreen particulate and gaseous radiation monitor for the TMI-2 ventilation exhaust. This in-plant effluent radiation monitor is located in the TMI-2 Auxiliary Building 328 foot elevation.

4.5.3 HP-R-225 Reactor Building Purge Air Exhaust Duct "A" HP-R-225 is a Victoreen particulate and gaseous radiation monitor for the TMI-2 Reactor Building Purge Air Exhaust System. This in-plant effluent radiation monitor is located in the TMI-2 Auxiliary Building 328' elevation area.

CY-TM-170-300 Revision 2 Page 124 of 209 4.6 Control of Gaseous Effluent Releases TMI gaseous effluent combined releases are controlled (per ODCM Part I for TMI-I and ODCM Part II for TMI-2) by effluent sampling and radiation monitor set points. These measures assure that releases from the various vents do not combine to produce dose rates at the site boundary exceeding the most restrictive of 500 mrem per year to the total body or 3000 mrem per year to the skin, and 1500 mrem per year to the thyroid. This is done by restricting simultaneous releases and by limiting the dose rates that may be contributed by the various vents at any time. The various vent radiation monitor set points are each based on fractions of the above limits and do not exceed the above limits when summed together. These effluent radiation monitor set points are calculated using the methodology described in equations 4.1.1, or 4.1.2 and 4.2.

The actual set points are then listed in TMI-1 Operations Procedure 1101-2.1.

The radioactive content of each batch of gaseous waste is determined prior to release by sampling and analyses in accordance with ODCM Part I for TMI-1 and ODCM Part IIfor TMI-2. The results of pre-release analyses are used with the calculational methods in Sections 4.1 and 4.2 to assure that the dose rates at the site boundary are maintained below the limits in ODCM Part I for TMI-1 and ODCM Part IIfor TMI-2.

Post-release analyses of samples composited from batch and continuous releases are performed in accordance with ODCM Part I for TMI-1 and ODCM Part II for TMI-2. The results of the analyses are used to assure that the dose rates at the site boundary are maintained within the limits of ODCM Part I for TMI-1 and ODCM Part i1 for TMI-2.

CY-TM-1 70-300 Revision 2 Page 125 of 209 TABLE 4.1 TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data GASEOUS RELEASE RADIATION GASEOUS (F) TERMINATION MONITOR RELEASE FLOW INTERLOCK (DETECTOR) LOCATION POINT RECORDER (YES/NO) VALVES YES M306 Elevation Fuel Hand. AH-E-10 FR-149 AH-D-120 Auxiliary Bldg. Building Exhaust AH-D-121 AH-D-122 306' Elevation Auxiliary YES RM-A6 Building FR-150 AH-E- 11 RM-A6_Auxiliary Bldg- Exhaust YES WDG-V47 RMA-8/9 Bldg. Station FR-149 AH-E-10 RM-A8 Near BWST Vent &FR-150 AH-E-1 I Exhaust Starts MAP-5 Radioiodine Sampler YES 322' Elevation Condenser S s S RM-A5 Second Floor Off Gas FR-1113 Radioiodtne Turbine Bldg. Exhaust Sample Sampler YES 322' Elevation Condenser SaS RM-A1 5 Second Floor Off Gas FR-1 113 Radioiodine Turbine Bldg. Exhaust Sampler Waste Gas RM-A7 306' Elevation Decay YES Auxiliary Bldg. Tanks FR123 WDG-V47 (A,B,C)

YES Reactor AH-V-1A/B/C/D RMA-8/9 Bldg. Building FR-909/ WDG-534/535 Near BWST Purge FR-148 Starts MAP-5 Exhaust Radioiodine

___________ _________ Sampler NO 331V Elevation ESF Fuel RM-A14 ESF FHB Handling FR-1104A1B Manual Outside Chem. Building Actions Addition Bldg. Exhaust Actions

CY-TM-1 70-300 Revision 2 Page 126 of 209 TABLE 4.1 (Cont'd)

TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data RELEASE GASEOUS TERMINATION RADIATION INTERLOCK MONITOR GASEOUS (YES/NO)

(DETECTOR) LOCATION RELEASE POINT VALVES Chemical CCB SytmNEExhaust ALC-RMI-18 Cleaning Bldg. System NONE 304' Elevation (Typical flow rate is 10,000 cfm)

WHPF WHPF System Exhaust YES WHP-RIT-1 Mechanical Equipment Room System (Typical flow rate WHPFTrpVentilation Equipment Room is 7,500 cfm) Trips RLM Exhaust RLM-RM-1 RLM-Mechanical System NONE Equipment Room (Typical flow rate.

__ is 900 cfm)

TABLE 4.2 TMI-2 Gaseous Release Point and Gaseous Radiation Monitor Data RELEASE GASEOUS TERMINATION RADIATION GASEOUS INTERLOCK MONITOR RELEASE (YES/NO)

(DETECTOR) LOCATION POINT VALVES 328' Elevation Station HP-R-219 Auxiliary Vent NONE Building Exhaust 328' Elevation Station Vent NONE HP-R-219A Auxiliary Exhaust Building Exhaust 328' Elevation Reactor Bldg HP-R-225 Auxiliary Building Purge Exhaust NONE Duct "A"

CY-TM-170-300 Revision 2 Page 127 of 209 TABLE 4.3 Dose Factors for Noble Gases and Daughters*

Gamma Beta Total Body Skin Dose Dose Factor(b) Gamma Air Beta Air Factor(a) Li Dose Factor Dose Factor KI (mrem/yr Mi Ni (mrem/yr per per (mrad/yr per (mrad/yr per Radionuclide PCi/m 3) iCi/m3 ) pCi/m 3 ) iCi/m3)

Kr-83m 7.56E-02** --- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 Kr-90 I .56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.511E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21EE+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 Dose factors are for immersion exposure in uniform semi-infinite cloud of noble gas radionuclides that may be detected in gaseous effluents. Dose factor values are taken from Regulatory Guide 1.109 (Rev. 1), Table B-I.

• • 7.56E-02 = 7.56 x 10-2.

(a) Total body dose factor for gamma penetration depth of 5 cm into the body.

(b) Skin dose factor at a tissue depth or tissue density thickness of 7 mg/cm2 .

CY-TM-170-300 Revision 2 Page 128 of 209 TABLE 4.4 Atmospheric Dispersion Factors for Three Mile Island

• STATION VENT DISTANCE 5~Pr'.TflP A~/FPAC~F 'i/cl (IN F~FC/M 3~ (iN MFTFRR* SEASON -ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 1.18E-07 5.32E-07 2.95E-07 1.931-07 1.39E-07 5.52E-08 1.91E-08 5.02E-09 1.88E-09 1.09E-09 NNE 1.70E-07 7.17E-07 3.45E-07 2.00E-07 1.39E-07 5.58E-08 1.70E-08 4.77E-09 1.98E-09 9.69E-10 NE 1.12E-07 1.75E-07 3.26E-07 1.86E-07 1.21E-07 5.OOE-08 1.67E-08 4.67E-09 1.85E-09 9.93E-10 ENE 1.09E-07 2.13E-07 2.67E-07 1.53E-07 1.05E-07 4.31E-08 1.42E-08 4.42E-09 1.59E-09 8.64E-10 E 2.31E-07 1.71E-07 1.52E-07 1.49E-07 1.06E-07 4.63E-08 1.52E-08 5.19E-09 2.48E-09 1.50E-09 ESE 3.50E-07 2.12E-07 2.50E-07 1.48E-07 9.48E-08 3.98E-08 1.50E-08 5.92E-09 2.92E-09 1.93E-09 SE 4.19E-07 3.79E-07 2.53E-07 1.55E-07 1.11E-07 4.82E-08 1.81E-08 6.84E-09 3.30E-09 2.22E-09 SSE 2.90E-07 3.62E-07 2.55E-07 1.49E-07 1.11E-07 5.02E-08 1.98E-08 6.97E-09 2.94E-09 1.70E-09 S 1.87E-07 6.47E-08 2.16E-07 1.30E-07 8.65E-08 4.09E-08 1.40E-08 4.96E-09 1.99E-09 1.04E-09 SSW 6.13E-08 4.16E-08 1.56E-07 1.03E-07 6.81E-08 2.72E-08 9.74E-09 3.01E-09 1.50E-09 8.23E-10 SW 5.76E-08 1,14E-07 1.70E-07 1.05E-07 6.93E-08 2.51E-08 9.34E-09 2.72E-09 1.33E-09 8.33E-10 WSW 8.52E-08 3.75E-07 2.14E-07 1.26E-07 7.74E-08 3.08E-08 1.02E-08 3.28E-09 1.39E-09 9.69E-10 W 1.15E-07 5.80E-07 2.88E-07 1.63E-07 1.18E-07 5.23E-08 1.72E-08 5.06E-09 1.98E-09 1.25E-09 WNW 1.41E-07 6.28E-07 3.30E-07 2.19E-07 1.48E-07 5.68E-08 1.95E-08 6.32E-09 2.16E-09 1.34E-09 NW 1.42E-07 5.67E-07 3.17E-07 1.93E-07 1.30E-07 5.67E-08 2.06E-08 5.90E-09 2.70E-09 1.45E-09 NNW 1.OOE-07 5.77E-07 3.18E-07 1.80E-07 1.27E-07 5.20E-08 1.77E-08 4.82E-09 2.01E-09 1.22E-09

" STATION VENT DISTANCE

• SECTOR AVERAGE D/Q (IN M) (IN METERS) SEASON - ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 2.51E-09 8.72E-10 4.84E-10 2.98E-10 2.50E-10 8.57E-11 2.51E-11 4.98E-12 1.57E-12 7.84E-13 NNE 3.89E-09 1.98E-09 9.54E-10 4.99E-10 3.38E-10 1.10E-10 2.89E-11 6.06E-12 2.10E-12 8.89E-13 NE 2.58E-09 6.70E-10 9.13E-10 4.91E-10 2.97E-10 1.04E-10 2.87E-11 6.01E-12 1.99E-12 9.23E-13 ENE 2.15E-09 5.85E-10 5.54E-10 3.06E-10 2.08E-10 8.30E-11 2.32E-11 5.41E-12 1.63E-12 7.64E-13 E 5.54E-09 1.23E-09 6.17E-10 4.59E-10 3.63E-10 1.34E-10 3.66E-11 9.44E-12 3.77E-12 1.97E-12 ESE 9.17E-09 2.05E-09 1.51E-09 8.66E-10 5.11E-10 1.82E-10 5.77E-11 1.72E-11 7.07E-12 4.07E-12 SE 1.22E-08 2.88E-09 1.84E-09 1.02E-09 6.85E-10 2.60E-10 8.30E-11 2.34E-11 9.42E-12 5.51E-12 SSE 7.50E-09 1.62E-09 1.08E-09 5.89E-10 4.49E-10 1.87E-10 6.16E-11 1.61E-11 5.67E-12 2.83E-12 S 3.86E-09 6.53E-10 6.27E-10 3.59E-10 2.32E-10 1.06E-10 3.05E-11 8.10E-12 2.73E-12 1.23E-12 SSW 1.13E-09 2.94E-10 4.19E-10 2.53E-10 1.56E-10 5.38E-11 1.68E-11 3.91E-12 1.64E-12 7.84E-13 SW 1.19E-09 3.84E-10 4.96E-10 2.80E-10 1.70E-10 5.24E-11 1.65E-11 3.62E-12 1.49E-12 8.12E-13 WSW 1.77E-09 8.31E-10 6.49E-10 3.50E-10 1.99E-10 6.73E-11 1.89E-11 4.58E-12 1.63E-12 9.90E-13 W 2.41E-09 1.29E-09 6.81E-10 3.65E-10 2.96E-10 1.12E-10 3.11E-11 6.90E-12 2.26E-12 1.25E-12 WNW 3.20E-09 1.39E-09 7.73E-10 5.91E-10 3.66E-10 1.19E-10 3.43E-11 8.36E-12 2.39E-12 1.29E-12 NW 3.25E-09 1.23E-09 7.39E-10 4.22E-10 2.77E-10 1.14E-10 7.282-11 7.61E-12 2.92E-12 1.36E-12 NNW 1.98E-09 9.88E-10 5.71E-10 3.05E-10 2.23E-10 8.21E-11 2.41E-11 4.93E-12 1.72E-12 9.03E-13 DATA FROM 1/1/78 THROUGH 12/31/86 USED IN CALCULATIONS

CY-TM-1 70-300 Revision 2 Page 129 of 209 TABLE 4.5 Atmospheric Dispersion Factors for Three Mile Island o GROUND RELEASE DISTANCE (IN MFTFRR* 5(:;AR(NJ - ANNUAL e SEC R .. . . . I __ ........ .......... -

SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 1.16E-05 1.13E-06 5.94E-07 3.80E-07 2.38E-07 9.74E-08 3.45E-08 9.28E-09 3.52E-09 2.05E-09 NNE 1.08E-05 1.10E-06 5.66E-07 3.41E-07 2.38E-07 9.55E-08 3.11E-08 8.94E-09 3.74E-09 1.84E-09 NE 7.02E-06 9.81E-07 5.42E-07 3.17E-07 2.10E-07 9.01E-08 3.10E-08 8.87E-09 3.54E-09 1.91 E-09 ENE 7.14E-06 9.64E-07 4.92E-07 2.85E-07 1.97E-07 7.82E-08 2.64E-08 8.38E-09 3.04E-09 1.66E-09 E 8.49E-06 1.09E-06 5.48E-07 2.91E-07 1.87E-07 8.40E-08 2.82E-08 9.85E-09 4.75E-09 2.87E-09 ESE 6.91E-06 9.02E-07 4.49E-07 2.57E-07 1.67E-07 7.20E-08 2.77E-08 1.12E-08 5.54E-09 3.68E-09 SE 6.70E-06 9.06E-07 4.53E-07 2.81E-07 2.03E-07 8.94E-08 3.33E-08 1.28E-08 6.19E-09 4.18E-09 SSE 7.26E-06 9.25E-07 4.91E-07 2.87E-07 2.08E-07 9.18E-08 3.72E-08 1.32E-08 5.62E-09 3.26E-09 S 8.70E-06 9.08E-07 3.99E-07 2.41E-07 1.61E-07 7.31E-08 2.57E-08 9.23E-09 3.74E-09 1.95E-09 SSW 6.05E-06 7.01E-07 2.75E-07 1.86E-07 1.24E-07 5.06E-08 1.82E-08 5.71E-09 2.87E-09 1.58E-09 SW 5.94E-06 5.71E-07 2.86E-07 1.81E-07 1.22E-07 4.50E-08 1.72E-08 5.12E-09 2.53E-09 1.59E-09 WSW 8.00E-06 7.02E-07 3.60E-07 2.15E-07 1.34E-07 5.50E-08 1.87E-08 6.12E-09 2.62E-09 1.83E-09 W 1.02E-05 1.07E-06 5.30E-07 3.02E-07 2.05E-07 9.31E-08 3.15E-08 9.48E-09 3.74E-09 2.38E-09 WNW 1.16E-05 1.13E-06 5.98E-07 3.67E-07 2.53E-07 1.00E-07 3.56E-08 1.18E-08 4.07E-09 2.54E-09 NW 1.13E-05 1.06E-06 5.70E-07 3.53E-07 2.40E-07 1.02E-07 3.82E-08 1.11E-08 5.14E-09 2.78E-09 NNW 1.08E-05 1.04E-06 5.72E-07 3.27E-07 2.22E-07 9.06E-08 3.20E-08 8.89E-09 3.75E-09 2.29E-09

" GROUND RELEASE DISTANCE

• SECTOR AVERAGE D/Q (IN M2) (IN METERS) SEASON - ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 2.30E-08 1.88E-09 8.93E-10 4.82E-10 2.70E-10 8.96E-11 2.53E-11 4.98E-12 1.57E-12 7.84E-13 NNE 2.66E-08 2.25E-09 1.06E-09 5.42E-10 3.38E-10 1.10E-10 2.89E-11 6.06E-12 2.10E-12 8.89E-13 NE 1.75E-08 2.00E-09 1.01E-09 5.04E-10 2.98E-10 1.04E-10 2.88E-11 6.01E-12 1.99E-12 9.23E-13 ENE 1.68E-08 1.85E-09 8.65E-10 4.28E-10 2.65E-10 8.57E-11 2.33E-11 5.41E-12 1.63E-12 7.64E-13 E 2.88E-08 2.99E-09 1.39E-09 6.34E-10 3.67E-10 1.35E-10 3.68E-11 9.42E-12 3.77E-12 1.97E-12 ESE 3.59E-08 3.80E-09 1.77E-09 8.79E-10 5.15E-10 1.83E-10 5.78E-11 1.71E-11 7.06E-12 4.06E-12 SE 4.12E-08 4.55E-09 2.13E-09 1.15E-09 7.50E-10 2.72E-10 8.31E-11 2.34E-11 9.42E-12 5.50E-12 SSE 3.12E-08 3.23E-09 1.59E-09 B.00E-10 5.20E-10 1.88E-10 6.18E-11 1.61E-11 5.66E-12 2.83E-12 S 2.65E-08 2.21E-09 9.07E-10 4.75E-10 2.86E-10 1.07E-10 3.06E-11 8.10E-12 2.73E-12 1.23E-12 SSW 1.45E-08 1.30E-09 4.80E-10 2.82E-10 1.70E-10 5.71E-11 1.69E-11 3.91E-12 1.64E-12 7.84E-13 SW 1.42E-08 1.10E-09 5.15E-10 2.82E-10 1.71E-10 5.24E-11 1.65E-11 3.62E-12 1.49E-12 8.12E-13 WSW 2.01E-08 1.41E-09 6.82E-10 3.54E-10 2.00E-10 6.76E-11 1.89E-11 4.58E-12 1.63E-12 9.90E-13 W 2.55E-08 2.16E-09 1.002-09 4.91E-10 3.01E-10 1.12E-10 3.11E-11 6.90E-12 2.27E-12 1.25E-12 WNW 2.88E-08 2.30E-09 1.13E-09 5.93E-10 3.67E-10 1.19E-10 3.43E-11 8.36E-12 2.39E-12 1.29E-12 NW 2.78E-08 2.15E-09 1.06E-09 5.58E-10 3.41E-10 1.19E-10 3.57E-11 7.61E-12 2.92E-12 1.36E-12 NNW 2.17E-08 1.75E-09 8.75E-10 4.24E-10 2.57E-10 8.55E-11 2.42E-11 4.93E-12 1.72E-12 9.03E-13 DATA FROM 1/1/78 THROUGH 12/31/86 USED IN CALCULATIONS

CY-TM-1 70-300 Revision 2 Page 130 of 209 TABLE 4.6 Dose Parameters for Radioiodines and Radioactive Particulate in Gaseous Effluents*

CRITICAL ORGAN CRITICAL I ORGAN NUCLIDE ORGAN FACTOR Pi*** NUCLIDE ORGAN FACTOR P H-3** TOTAL BODY 3.04E-07 1.12E+03 RU-1 03 LUNG 1.79E-04 6.62E+05 C-14 BONE 9.70E-06 3.59E+04 RU-105 GI-LLI 2.69E-05 9.95E+04 NA-24 TOTAL BODY 4.35E-06 1.61 E+04 RU-106 LUNG 3.87E-03 1.43E+07 FP-32 BONE 7.04E-04 2.60E+06 AG-110M LUNG 1.48E-03 5.48E+06 CR-51 LUNG 4.59E-06 1.70E+04 TE-125M LUNG 1.29E-04 4.77E+05 MN-54 LUNG 4.26E-04 1.58E+06 SB-125 LUNG 6.27E-04 2.32E+06 MN-56 GI-LLI 3.33E-05 1.23E+05 TE-127M LUNG 4.OOE-04 1.48E+06 FE-55 LUNG 3.OOE-05 1.11E+05 TE-127 GI-LLI 1.52E-05 5.62E+04 FE-59 LUNG 3.43E-04 1.27E+06 TE-129M LUNG 4.76E-04 1.76E+06 CO-58 LUNG 2.99E-04 1.11E+06 TE-129 GI-LLI 6.89E-06 2.55E+04 CO-60 LUNG 1.91E-03 7.07E+06 TE-131M GI-LLI 8.32E-05 3.08E+05 NI-63 BONE 2.22E-04 8.21E+05 TE-131 LUNG 5.55E-07 2.05E+03 NI-65 GI-LLI 2.27E-05 8.40E+04 TE-132 LUNG 1.02E-04 3.77E+05 CU-64 GI-LLI 9.92E-06 3.67E+04 1-130 THYROID 4.99E-04 1.85E+06 ZN-65 LUNG 2.69E-04 9.95E+05 1-131 THYROID 4.39E-03 1.62E+07 ZN-69 GI-LLI 2.75E-06 1.02E+04 1-132 THYROID 5.23E-05 1.94E+05 BR-83 TOTAL BODY 1.28E-07 4.74E+02 1-133 THYROID 1.04E-03 3.85E+06 BR-84 TOTAL BODY 1.48E-07 5.48E+02 1-134 THYROID 1.37E-05 5.07E+04 BR-85 TOTAL BODY 6.84E-09 2.53E+ý01 1-135 THYROID 2.14E-04 7.92E+05 RB-86 LIVER 5.36E-05 1.98E+05 CS-134 LIVER 2.74E-04 1.01E+06 RB-88 LIVER 1.52E-07 5.62E+02 CS-136 LIVER 4.62E-05 1.71E+05 RB-89 LIVER 9.33E-08 3.45E+02 CS-137 BONE 2.45E-04 9.07E+05 SR-89 LUNG 5.89E-04 2.16E+06 CS-1 38 LIVER 2.27E-07 8.40E+02 SR-90 BONE 2.73E-02 1.01E+08 BA-139 GI-LLI 1.56E-05 5.77E+04 SR-91 GI-LLI 4.70E-05 1.74E+05 BA-140 LUNG 4.71E-04 1.74E+06 SR-92 GI-LLI 6.55E-05 2.42E+05 BA-141 LUNG 7.89E-07 2.92E+03 Y-90 GI-LLI 7.24E-05 2.68E+05 BA-142 LUNG 4.44E-07 1.64E+03 Y-91M LUNG 7.60E-07 2.81E+03 LA-140 GI-LLI 6.1OE-05 2.26E+05 Y-91 LUNG 7.1OE-04 2.63E+06 LA-142 GI-LLI 2.05E-05 7.59E+04 Y-92 GI-LLI 6.46E-05 2.39E+05 CE-141 LUNG 1.47E-04 5.44E+05 Y-93 GI-LLI 1.05E-04 3.89E+05 CE-143 GI-LLI 3.44E-05 1.27E+05 ZR-95 LUNG 6.03E-04 2.23E+06 CE-144 LUNG 3.23E-03 1.20E+07 ZR-97 GI-LLI 9.49E-05 3.51E+05 PR-143 LUNG 1.17E-04 4.33E+05 NB-95 LUNG 1.66E-04 6.14E+05 PR-144 LUNG 4.23E-07 1.57E+03 MO-99 LUNG 3.66E-05 1.35E+05 ND-147 LUNG 8.87E-05 3.28E+05 TC-99M GI-LLI 1.30E-06 4.81E+03 W-187 GI-LLI 2.46E-05 9.1OE+04 TC-101 LUNG 1.58E-07 5.85E+02 NP-239 GI-LLI 1.73E-05 6.40E+04 The listed dose parameters are for radionuclides, other than noble gases that may be detected in gaseous effluents. Pi factors include all nonatmospheric pathway transport parameters, the receptor's usage of pathway media, and are based on the most restrictive age group (child) critical organ' Additional dose parameters for nuclides not included in this Table may be calculated using the methodology described in NUREG-0133.

Tritium dose factors include an increase of 50% to account for the additional amount of this nuclide absorbed through the skin.

mrem/year per iiCi/m 3.

CY-TM-1 70-300 Revision 2 Page 131 of 209 FIGURE 4.1 TMI-1 Gaseous Effluent Pathways

CY-TM-1 70-300 Revision 2 Page 132 of 209 FIGURE 4.2 TMI-1 Auxiliary and Fuel Handling Buildings Effluent Pathways

CY-TM-1 70-300 Revision 2 Page 133 of 209 FIGURE 4.3 TMI-1 Reactor Building Effluent Pathway 170 I FEET REACTOR BUILDING PURGE EXHAUST RADIATION MONITORS AND SAMPLING STATIONS REACTOR BUILDING M~-0 11,11-11 WP F[L1ERS IN P~IZFWV REACTOR NUM SPMKM? SYSTENS PARTIC1IATE/TR1Tl IO00?VUE GAS P PARTME]

IA: AMSUTE ClLoJ

CY-TM-1 70-300 Revision 2 Page 134 of 209 FIGURE 4.4 TMI-1 Condenser Offgas Effluent Pathway CONDENSER OFF GAS STACK CONDENSER OFF GAS EXHAUST RADIATION MONITORS AND SAMPLING STATIONS

CY-TM-170-300 Revision 2 Page 135 of 209 FIGURE 4.5 TMI-2 Gaseous Effluent Filtration System/Pathways STATION VENT 0 -- 14*.08M CPH RB BREATHER I - - - - - - - - - - - - - -

a . -9,500 cM UNIT 2 EXHAUST AIR FLOW AND RMS SCHEMATIC

CY-TM-170-300 Revision 2 Page 136 of 209 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents - Instantaneous Release Limits 5.1.1 Noble Gases For noble gases, the following equations apply for total body and skin dose rate at the unrestricted area boundary:

5.1.1.1 Total Body Dose Ratetb = * (Ki) x (Dv) x (Qj) (eq 5.1.1.1)

Where:

Dose Rate b = instantaneous total body dose rate limit, at the site boundary, in mrem/yr.

Ki = total body dose factor due to gamma emissions for each 3

identified noble gas radionuclide, in mrem/yr per pCi/m from Table 4.3.

Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m 3 , from Table 4.4 for station vent releases; and Table 4.5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases). Maximum values presently in use are 7.17E-7 sec/m 3 at sector NNE for station vent, and 1.16E-5 sec/m3 for all other releases, at sectors N and WNW.

Q= Release rate of radionuclide, i, in pCi/sec as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, i, in pCi/cc, times the release pathway flow rate, in cc/second.

CY-TM-170-300 Revision 2 Page 137 of 209 5.1.1.2 Skin Dose Ratesk = ' (LI + 1.1 Mi) X (Dv) X (Qj) (eq 5.1.1.2)

Where:

Dose Ratesk = instantaneous mrem/year skin dose rate limit, at the site boundary, in mrem/yr.

Li = skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem/yr per pCi/mr3 from Table 4.3.

Mi = air dose factor due to gamma emissions for each 3

identified noble gas radionuclide, in mrad/yr per ýiCi/m from Table 4.3.

1.1 = mrem skin dose per mrad air dose. Converts air dose to skin dose.

Qj = release rate of radionuclide, i, in [tCi/sec, as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, i, in gCi/cc, times the release pathway flow rate, in cc/second.

Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for station vent releases; and Table 4.5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases). Maximum values presently in use are 7.17E-7 sec/m3 at sector NNE for station vent, and 1.16E-5 sec/m 3 for all other releases, at sectors N and WNW.

CY-TM-1 70-300 Revision 2 Page 138 of 209 5.1.2 Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form, with Half-Lives Greater than 8 Days For 1-131, 1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, the following equation applies:

Dose Ratelp = z (Pi) (Dv) (Qi) (eq 5.1.2)

Where:

Dose Ratelp = mrem/year organ dose rate.

Pi = dose parameter for 1-131, 1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, for the inhalation pathway, in mrem/yr per

ýtCi/m 3 , from Table 4.6. The dose factors are based on the critical individual organ and most restrictive age group (child).

Dv = highest sector annual average gaseous dispersion factor (X/Q or D/Q) at or beyond the unrestricted area boundary, in sec/m 3 , from Table 4.4 for the station vent releases and Table 4.5 for all other releases. X/Q is used for the inhalation pathway. Maximum values of X/Q presently used are 7.17E-7 sec/m 3 for station vent, at sector NNE, and 1.16E-5 sec/m 3 for all other releases, at sectors N and WNW.

Q= release rate of each radionuclide, i, in ptCi/sec.

Calculated using the concentration of each radionuclide, i, in 1iCi/cc, times the release pathway flow rate, in cc/second.

CY-TM-170-300 Revision 2 Page 139 of 209 5.2 Gaseous Effluents - 10 CFR 50 Appendix I 5.2.1 Noble Gases The air dose in an unrestricted area due to noble gases released in gaseous effluents from the site is determined using the following expressions:

Dose F = (3.17E-8) x * (Mi) x (Dv) x (Qi) (eq 5.2.1) and Dose J3 = (3.17E-8) x (N) x (Dv) x (Qi) (eq 5.2.2)

Where:

Dose F = mrad gamma air dose due to gamma emissions from noble gas radionuclides.

Dose 13= mrad beta air dose due to beta emissions from noble gas radionuclides.

Mi = air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per lCi/m3, from Table 4.3.

Ni = air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per pCi/m 3 , from Table 4.3.

Dv = highest sector annual average gaseous dispersion factor, X/Q, at or beyond the unrestricted area boundary, in sec/m 3 . Values may be read or interpolated from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. Maximum values of X/Q presently used are 7.17E-7 sec/m 3 for station vent at sector NNE, and 1.16E-5 sec/m 3 for all other releases at sectors N or WNW.

Q0= release of noble gas radionuclide, i, in pCi, over the specified time period, (pCi/second

• seconds).

3.17E-8 = inverse of the number of seconds in a year.

CY-TM-170-300 Revision 2 Page 140 of 209 NOTE: If the methodology in this section is used in determining dose to an individual, rather than air dose due to noble gases, substitute Ki, from Table 4.3, for Mi, and (Li + 1.1 Mi) for Ni.

5.2.2 Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form, with Half-Lives Greater than 8 Days The dose to an individual from 1-131, 1-133, Tritium and Radionuclides in Particulate Form with half-lives greater than 8 days in gaseous effluents released from the site to an unrestricted area is determined by solving the following expression:

Doseo = * (3.17E-8) x 1 (RI) (Dv) (Qi) (eq 5.2.2)

Where:

Doseo = dose to all real pathways, p, to organ, o, of an individual in age group, a, from 1-131, 1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, in mrem, during any desired time period.

R= the dose factor for each identified radionuclide, i, pathway, p, age group, a, and organ, o, in mrem/yr per g.Ci/m 3 for the inhalation pathway and m 2 - mrem/yr per pCi/sec for other pathways, from Tables 5.2 to 5.7.

NOTE: Since there is minimal or no elemental iodine released from the condenser off-gas air ejector (see NUREG-001 7) all Iodine Ri values for all pathways, except the inhalation pathway, are considered to be zero when performing dose calculations for releases from the condenser off-gas air ejector. Only calculate the dose due to the inhalation pathway for condenser off-gas air ejector iodines.

NOTE: Tritium, H-3, dose factor is mrem/year per giCi/m 3 for all pathways.

Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3 , for the inhalation pathway, and D/Q, in mi, for other pathways. Table 4.4 is used to derive the values for station vent releases and Table 4.5 is used to derive the values for all other releases. The values used to calculate site boundary and critical receptor doses are as follows:

CY-TM-1 70-300 Revision 2 Page 141 of 209 Station Vent Releases - Boundary Inhalation X/Q 7.17 E-7 Meat D/Q 1.22 E-8 Ground D/Q 1.22 E-8 Cow/Milk/Infant D/Q 1.22 E-8 Vegetation D/Q 1.22 E-8 Station Vent Releases - Critical Receptor Inhalation X/Q 7.2 E-7 Meat D/Q 4.6 E-9 Ground D/Q 7.8 E-9 Cow/Milk/Infant D/Q3.1 E-9 Vegetation D/Q 8.9 E-9 Ground or Other Releases - Boundary Inhalation X/Q 1.16 E-5 Meat D/Q 4.12 E-8 Ground D/Q 4.12 E-8 Cow/Milk/Infant D/Q4.12 E-8 Vegetation D/Q 4.12 E-8 Ground or Other Releases - Critical Receptor Inhalation X/Q 1.2 E-5 Meat D/Q 9.2 E-9 Ground D/Q 3.0 E-8 Cow/Milk/Infant D/Q6.3 E-9 Vegetation D/Q 2.6 E-8 Dv(H-3) = In the case of H-3 only the X/Q's above are used for all pathways.

Qi = release of 1-131, 1-133, Tritium and Radionuclides, i, in Particulate Form with half-lives greater than 8 days, in

ýtCi, cumulative over the specified time period (piCi/second

• seconds).

3.17E-8 = inverse of the number of seconds in a year.

CY-TM-1 70-300 Revision 2 Page 142 of 209 5.3 Gaseous Radioactive System Dose Calculations Once per Month ODCM Part I Control 2.2.2.4 and TMI-2 PDMS Tech Spec Section 6.7.4.a.6 requires that appropriate subsystem of the Gaseous Radwaste Treatment System shall be used to reduce the radioactive materials in gaseous waste prior to their discharge. When the monthly projected doses due to the gaseous effluent releases from the site would exceed:

0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ.

The following calculational method is provided for performing this dose projection.

At least once per month, the gamma air dose, beta air dose and the maximum organ dose for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual release during the period for which the projection is made. If these projected doses exceed any of the values listed above, appropriate portions of the TMI-1 Gaseous Waste Treatment System, as defined in Section 6.0, or appropriate portions of the TMI-2 Gaseous Effluent Filtration System as shown on Figure 4.5, shall be used to reduce radioactivity levels prior to release.

At the discretion of the ODCM Specialist, time periods other than the current quarter-to-date may be used to project doses if the dose per day in the current quarter-to-date is not believed to be representative of the dose per day projected for the next month.

CY-TM-1 70-300 Revision 2 Page 143 of 209 5A4 Alternative Dose Calculational Methodologies for Gaseous Effluents As an alternative to the methods described above, the models in/or based upon, those presented in Regulatory Guide 1.109 (Rev. 1) may be used to make a comprehensive dose assessment. Default parameter values from Regulatory Guide 1.109 (Rev. 1) and/or actual site specific data can be used where applicable.

The onsite, on-line computerized system for tracking gaseous effluent dose uses annual average gaseous dispersion factors. As an alternative dose calculational methodology. TMI calculates doses using an advanced class "A" dispersion model called SEEDS (simplified environmental effluent dosimetry system).

This model incorporates the guidelines and methodology set forth in USNRC Regulatory Guide 1.109, and uses actual hourly meteorological information matched to the time of releases to more accurately assess the dispersion of effluents in the atmosphere. Combining this assessment of dispersion with TMI effluent data for each unit, postulated maximum hypothetical doses to the public are calculated.

CY-TM-1 70-300 Revision 2 Page 144 of 209 TABLE 5.2.1 Pathway Dose Factors, RI AGE GROUP: INFANT PATHWAY: INHALATION 3

NUCLIDE -- - - - - - -- ORGAN DOSE FACTORS; mrem/year per -pCi/m BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 C-14 2.65E+04 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 CR-51 0.OOE+00 0.OOE+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 MN-54 0.OOE+00 2.53E+04 4.98E+03 0.OOE+00 4.98E+03 1.OOE+06 7.06E+03 FE-55 1.97E+04 1.17E+04 3.33E+03 0.OOE+00 O.OOE+00 8.69E+04 1.09E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 O.OOE+00 0.OOE+00 1.02E+06 2.48E+04 CO-58 0.00E+00 1.22E+03 1.82E+03 0.OOE+00 0.OOE+00 7.77E+05 1.11E+04 CO-60 0.OOE+00 8.02E+03 1.18E+04 0.OOE+00 0.OOE+00 4.51E+06 3.19E+04 NI-63 3.39E+05 2.04E+04 1.16E+04 0.OOE+00 0.OOE+00 2.09E+05 2.42E+03 ZN-65 1.93E+04 6.26E+04 3.11E+04 0.OOE+00 3.25E+04 6.47E+05 5.14E+04 RB-86 0.OOE+00 1.90E+05 8.82E+04 0.OOE+00 0.OOE+00 0.OOE+00 3.04E+03 SR-89 3.98E+05 0.OOE+00 1.14E+04 O.OOE+00 O.OOE+00 2.03E+06 6.40E+04 SR-90 4.09E+07 0.OOE+00 2.59E+06 0.OOE+00 O.OOE+00 1.12E+07 1.31E+05 Y-91 5.88E+05 0.OOE+00 1.57E+04 0.OOE+00 0.OOE+00 2.45E+06 7.03E+04 ZR-95 1.15E+05 2.79E+04 2.03E+04 0.OOE+00 3.11E+04 1.75E+06 2.17E+04 NB-95 1.57E+04 6.43E+03 3.78E+03 O.OOE+00 4.72E+03 4.79E+05 1.27E+04 RU-103 2.02E+03 0.00E+00 6.79E+02 0.OOE+00 4.24E+03 5.52E+05 1.61E+04 RU-106 8.68E+04 0.OOE+00 1.09E+04 0.OOE+00 1.07E+05 1.16E+07 1.64E+05 AG-110M 9.98E+03 7.22E+03 5.OOE+03 0.OOE+00 1.09E+04 3.67E+06 3.30E+04 TE-125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 O.OOE+00 4.47E+05 1.29E+04 TE-127M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 TE-129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 1-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.OOE+00 1.06E+03 1-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.OOE+00 2.16E+03 CS-134 3.96E+05 7.03E+05 7.45E+04 0.OOE+00 1.90E+05 7.97E+04 1.33E+03 CS-136 4.83E+04 1.35E+05 5.29E+04 0.OOE+00 5.64E+04 1.18E+04 1.43E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 0.OOE+00 1.72E+05 7.13E+04 1.33E+03 BA-140 5.60E+04 5.60E+01 2.90E+03 0.OOE+00 1.34E+01 1.60E+06 3.84E+04 CE-141 2.77E+04 1.67E+04 1.99E+03 0.OOE+00 5.25E+03 5.17E+05 2.16E+04 CE-144 3.19E+06 1.21E+06 1.76E+05 0.OOE+00 5.38E+05 9.84E+06 1.48E+05 PR-143 1.40E+04 5.24E+03 6.99E+02 0.OOE+00 1.97E+03 4.33E+05 3.72E+04 ND-147 7.94E+03 8.13E+03 5.OOE+02 0.OOE+00 3.15E+03 3.22E+05 3.12E+04

CY-TM-170-300 Revision 2 Page 145 of 209 TABLE 5.2.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: INHALATION 3

per P-Ci/M NUCLIDE------ ORGAN DOSE FACTORS; mrem/year BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 C-14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 CR-51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 MN-54 0.00E+00 4.29E+04 9.51E+03 0.OOE+00 1.OOE+04 1.58E+06 2.29E+04 FE-55 4.74E+04 2.52E+04 7.77E+03 0.00 E+00 0.OOE+00 1.11E+05 2.87E+03 FE-59 2.07E+04 3.34E+04 1.67E+04 0.OOE+00 0.OOE+00 1.27E+06 7.07E+04 CO-58 0.00E+00 1.77E+03 3.16E+03 0.OOE+00 O.OOE+00 1.11E+06 3.44E+04 CO-60 O.00E+00 1.31E+04 2.26E+04 0.OOE+00 0.OOE+00 7.07E+06 9.62E+04 NI-63 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.OOE+00 2.75E+05 6.33E+03 ZN-65 4.26E+04 1.13E+05 7.03E+04 0.OOE+00 7.14E+04 9.95E+05 1.63E+04 RB-86 0.OOE+00 1.98E+05 1.14E+05 0.OOE+00 O.OOE+00 0.OOE+00 7.99E+03 SR-89 5.99E+05 0.OOE+00 1.72E+04 0.OOE+00 0.OOE+00 2.16E+06 1.67E+05 SR-90 1.01E+08 0.OOE+00 6.44E+06 0.OOE+00 0.OOE+00 1.48E+07 3.43E+05 Y-91 9.14E+05 0.OOE+00 2.44E+04 0.OOE+0Q O.OOE+00 2.63E+06 1.84E+05 ZR-95 1.90E+05 4.1 8E+04 3.70E+04 0.OOE+00 5.96E+04 2.23E+06 6.11E+04 NB-95 2.35E+04 9.18E+03 6.55E+03 0.OOE+00 8.62E+03 6.14E+05 3.70E+04 RU-103 2.79E+03 0.OOE+00 1.07E+03 0.OOE+00 7.03E+03 6.62E+05 4.48E+04 RU-1 06 1.36E+05 0.OOE+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 AG-110M 1.69E+04 1.14E+04 9.14E+03 0.OOE+00 2.12E+04 5.48E+06 1.OOE+05 TE-125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 O.OOE+00 4.77E+05 3.38E+04 TE-127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 TE-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 1-131 4.81 E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.OOE+00 2.84E+03 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 O.OOE+00 5.48E+03 CS-134 6.51 E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21 E+05 3.85E+03 CS-1 36 6.51 E+04 1.71 E+05 1.16E+05 0.OOE+00 9.55E+04 1.45E+04 4.18E+03 CS-1 37 9.07E+05 8.25E+05 1.28E+05 0.OOE+00 2.82E+05 1.04E+05 3.62E+03 BA-140 7.40E+04 6.48E+01 4.33E+03 0.OOE+00 2.11E+01 1.74E+06 1.02E+05 CE-141 3.92E+04 1.95E+04 2.90E+03 0.OOE+00 8.55E+03 5.44E+05 5.66E+04 CE-144 6.77E+06 2.12E+06 3.61E+05 0.OOE+00 1.17E+06 1.20E+07 3.89E+05 PR-143 1.85E+04 5.55E+03 9.14E+02 0.OOE+00 3.OOE+03 4.33E+05 9.73E+04 ND-147 1,08E+04 8.73E+03 6.81E+02 0.OOE+00 4.81E+03 3.28E+05 8.21E+04

CY-TM-170-300 Revision 2 Page 146 of 209 TABLE 5.2.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: INHALATION 3

per piCi/m NUCLIDE ORGAN DOSE FACTORS; mrem/year

[ BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 CR-51 0.OOE+00 0.OOE+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.OOE+03 MN-54 O.00E+00 5.11E+04 8.40E+03 0.OOE+00 1.27E+04 1.98E+06 6.68E+04 FE-55 3.34E+04 2.38E+04 5.54E+03 0.OOE+00 0.00E+00 1.24E+05 6.39E+03 FE-59 1.59E+04 3.70E+04 1.43E+04 0.OOE+00 0.OOE+00 1.53E+06 1.78E+05 CO-58 0.OOE+00 2.07E+03 2.78E+03 0.OOE+00 0.OOE+00 1.34E+06 9.52E+04 CO-60 0.OOE+00 1.51E+04 1.98E+04 0.OOE+00 0.OOE+00 8.72E+06 2.59E+05 NI-63 5.80E+05 4.34E+04 1.98E+04 0.00E+00 0.OOE+00 3.07E+05 1.42E+04 ZN-65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 RB-86 0.OOE+00 1.90E+05 8.40E+04 0.0OE+00 0.00E+00 0.00E+00 1.77E+04 SR-89 4.34E+05 0.OOE+00 1.25E+04 0.00E+00 0.OOE+00 2.42E+06 3.71E+05 SR-90 1.08E+08 O.00E+00 6.68E+06 0.OOE+00 0.00E+00 1.65E+07 7.65E+05 Y-91 6.61E+05 0.00E+00 1.77E+04 0.OOE+00 0.OOE+00 2.94E+06 4.09E+05 ZR-95 1.46E+05 4.58E+04 3.15E+04 0.OOE+00 6.74E+04 2.69E+06 1.49E+05 NB-95 1.86E+04 1.03E+04 5.66E+03 0.00E+00 1.00E+04 7.51E+05 9.68E+04 RU-103 2.10E+03 0.00E+00 8.96E+02 O.OOE+00 7.43E+03 7.83E+05 1.09E+05 RU-106 9.84E+04 0.OOE+00 1.24E+04 0.00E+00 1.90E+05 1.61E+07 9.60E+05 AG-110M 1.38E+04 1.31E+04 7.99E+03 0.00E+00 2.50E+04 6.75E+06 2.73E+05 TE-125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.OOE+00 5.36E+05 7.50E+04 TE-127M 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 TE-129M 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 1-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.OOE+00 6.49E+03 1-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.OOE+00 1.03E+04 CS-134 5.02E+05 1.13E+06 5.49E+05 0.OOE+00 3.75E+05 1.46E+05 9.76E+03 CS-136 5.15E+04 1.94E+05 1.37E+05 0.OOE+00 1.10E+05 1.78E+04 1.09E+04 CS-137 6.70E+05 8.48E+05 3.11E+05 0.OOE+00 3.04E+05 1.21E+05 8.48E+03 BA-140 5.47E+04 6.70E+01 3.52E+03 0.OOE+00 2.28E+01 2.03E+06 2.29E+05 CE-141 2.84E+04 1.90E+04 2.17E+03 0.OOE+00 8.88E+03 6.14E+05 1.26E+05 CE-144 4.89E+06 2.02E+06 2.62E+05 0.OOE+00 1.21E+06 1.34E+07 8.64E+05 PR-143 1.34E+04 5.31E+03 6.62E+02 0.OOE+00 3.09E+03 4.83E+05 2.14E+05 ND-147 7.86E+03 8.56E+03 5.13E+02 0.OOE+00 5.02E+03 3.72E+05 1.82E+05

CY-TM-1 70-300 Revision 2 Page 147 of 209 TABLE 5.2.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: INHALATION 3

LIORGAN DOSE FACTORS; mrem-year per L'CiIm NUCLIDE ------------------------- ----------------------------

I BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 1.26E+03 1.26E+(03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 C-14 1.82E+04 3.41E+03 3.41E+(03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 CR-51 0.0OE+00 0.00E+00 1.00E+(02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 MN-54 0.OOE+00 3.96E+04 6.30E+ 03 0.OOE+00 9.84E+03 1.40E+06 7.74E+04 FE-55 2.46E+04 1.70E+04 3.94E+ 03 0.00E+00 O.00E+00 7.21E+04 6.03E+03 FE-59 1.18E+04 2.78E+04 1.06E+ 04 0.OOE+00 0.OOE+00 1.02E+06 1.88E+05 CO-58 0.OOE+00 1.58E+03 2.07E+ 03 0.00E+00 O.00E+00 9.28E+05 1.06E+05 CO-60 0.OOE+00 1.15E+04 1.48E+ 04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 NI-63 4.32E+05 3.14E+04 1.45E+ 04 0.00E+00 0.OOE+00 1.78E+05 1.34E+04 ZN-65 3.24E+04 1.03E+05 4.66E+(04 0.OOE+00 6.90E+04 8.64E+05 5.34E+04 RB-86 0.OOE+00 1.35E+05 5.90E+ 04 0.OOE+00 0.OOE+00 0.OOE+00 1.66E+04 SR-89 3.04E+05 0.OOE+00 8.72E+ 03 0.OOE+00 0.OOE+00 1.40E+06 3.50E+05 SR-90 9.92E+07 0.OOE+00 6.10E+06 0.OOE+00 0.OOE+00 9.60E+06 7.22E+05 Y-91 4.62E+05 O.OOE+00 1.24E+04 0.OOE+00 0.OOE+00 1.70E+06 3.85E+05 ZR-95 1.07E+05 3.44E+04 2.33E+04 0.OOE+00 5.42E+04 1.77E+06 1.50E+05 NB-95 1.41E+04 7.82E+03 4.21E+03 0.OOE+00 7.74E+03 5.05E+05 1.04E+05 RU-103 1.53E+03 0.OOE+00 6.58E+02 0.OOE+00 5.83E+03 5.05E+05 1.10E+05 RU-106 6.91E+04 0.OOE+00 8.72E+03 0.OOE+00 1.34E+05 9.36E+06 9.12E+05 AG-A11M 1.08E+04 1.OOE+04 5.94E+03 0.OOE+00 1.97E+04 4.63E+06 3.02E+05 TE-125M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 TE-127M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E÷04 9.60E+05 1.50E+05 TE-129M 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 1-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.OOE+00 6.28E+03 1-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.OOE+00 8.88E+03 CS-134 3.73E+05 8.48E+05 7.28E+05 0.OOE+00 2.87E+05 9.76E+04 1.04E+04 CS-136 3.90E+04 1.46E+05 1.10E+05 0.OOE+00 8.56E+04 1.20E+04 1.17E+04 CS-137 4.78E+05 6.21E+05 4.28E+05 0.OOE+00 2.22E+05 7.52E+04 8.40E+03 BA-140 3.90E+04 4.90E+01 2.57E+03 0.OOE+00 1.67E+01 1.27E+06 2.18E+05 CE-141 1.99E+04 1.35E+04 1.53E+03 0.OOE+00 6.26E+03 3.62E+05 1.20E+05 CE-144 3.43E+06 1.43E+06 1.84E+05 0.OOE+00 8.48E+05 7.78E+06 8.16E+05 PR-143 9.36E+03 3.75E+03 4.64E+02 0.OOE+00 2.16E+03 2.81E+05 2.OOE+05 ND-147 5.27E+03 6.10E+03 3.65E+02 0.OOE+00 3.56E+03 2.21E+05 1.73E+05

CY-TM-1 70-300 Revision 2 Page 148 of 209 TABLE 5.3.1 Pathway Dose Factors, Ri AGE GROUP: ALL PATHWAY: GROUND PLANE ORGAN DOSE FACTORS*

NUCLIDE T.BODY SKIN H-3 0.00E+00 0.OOE+00 C-14 0.OOE+00 0.OOE+00 CR-51 4.65E+06 5.50E+06 MN-54 1.39E+09 1.62E+09 FE-55 0.OOE+00 0.OOE+00 FE-59 2.73E+08 3.21E+08 CO-58 3.79E+08 4.44E+08 CO-60 2.15E+10 2.53E+10 NI-63 0.OOE+00 0.OOE+00 ZN-65 7.47E+08 8.59E+08 RB-86 8.97E+06 1.03E+07 SR-89 2.16E+04 2.51E+04 SR-90 0.OOE+00 0.OOE+00 Y-91 1.07E+06 1.21E+06 ZR-95 2.45E+08 2.84E+08 I-------- ------

NB-95 1.37E+08 1.61E+08 RU-103 1.08E+08 1.26E+08 RU-106 4.22E+08 5.06E+08 I------------- ------ *

,AG-110M 3.44E+09 4.01E+09 TE-125M 1.55E+06 2.13E+06 TE-127M 9.17E+04 1.08E+05 TE-129M 1.98E+07 2.31 E+07

1-131 1.72E+07 2.09E+07

1-133 2.45E+06 2.98E+06 CS-1I34 6.86E+09 8.00E+09

'CS-136 1.51E+08 1.71E+08

'CS-137 1.03E+ 10 1.20E+10 BA-140 2.06E+07 2.36E+07 CE-141 1.37E+07 1.54E+07 CE-144 6.96E+07 8.05E+07 PR-143 0.OOE+00 0.OOE+00 ND-147 8.39E+06 1.01E+07

• m2 _mrem/year per pCi/sec.

CY-TM-170-300 Revision 2 Page 149 of 209 TABLE 5.4.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MILK 2

NUCLIDE ------- ORGAN DOSE FACTORS; M - mrem/year per _iCi/sec

-BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 C-14 2.34E+09 5.OOE+08 5.OOE+08 5.OOE+08 5.OOE+08 5.OOE+08 5.OOE+08 CR-51 0.OOE+00 0.OOE+00 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 MN-54 0.OOE+00 3.91 E+07 8.85E+06 0.OOE+00 8.65E+06 0.OOE+00 1.43E+07 FE-55 1.35E+08 8.74E+07 2.34E+07 O.OOE+00 O.OOE+00 4.27E+07 1.11E+07 FE-59 2.25E+08 3.93E+08 1.55E+08 O.OOE+00 O.OOE+00 1.16E+08 1.88E+08 CO-58 0.OOE+00 2.43E+07 6.06E+07 0.OOE+00 0.OOE+00 0.OOE+00 6.05E+07 CO-60 O.OOE+0O 8.83E+07 2.08E+08 0.OOE+00 0.OOE+00 0.OOE+00 2.1OE+08 NI-63 3.50E+1 0 2.16E+09 1.21 E+09 0.OOE+00 0.OOE+00 0.OOE+00 1.08E+08 ZN-65 5.56E+09 1.91E+10 8.79E+09 0.OOE+0O 9.24E+09 0.OOE+00 1.61E+10 RB-86 0.00E+00 2.23E+10 1.10E+10 0.OOE+00 0.OOE+00 0.OOE+00 5.70E+08 SR-89 1.26E+10 O.OOE+00 3.62E+08 0.OOE+0O 0.00E+00 0.OOE+00 2.59E+08 SR-90 1.22E+11 O.OOE+00 3.10E+10 0.OOE+00 0.O0E+00 0.OOE+00 1.52E+09 Y-91 7.34E+04 0.OOE+00 1.95E+03 0.OOE+00 0.OOE+00 0.OOE+00 5.26E+06 ZR-95 6.81E+03 1.66E+03 1.18E+03 0.OOE+00 1.79E+03 O.OOE+00 8.27E+05 NB-95 5.94E+05 2.45E+05 1.41E+05 0.OOE+00 1.75E+05 0.OOE+00 2.07E+08 RU-103 8.68E+03 O.OE+00 2.90E+03 O.OOE+00 1.81E+04 0.OOE+00 1.06E+05 RU-106 1.91E+05 0.OOE+00 2.38E+04 0.OOE+00 2.25E+05 0.OOE+00 1.45E+06 AG-110M 3.86E+08 2.82E+08 1.87E+08 0.OOE+00 4.03E+08 0.OOE+00 1.46E+10 TE-125M 1.51E+08 5.05E+07 2.04E+07 5.08E+07 0.OOE+00 O.OOE+00 7.19E+07 TE-127M 4.22E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 0.OOE+00 1.70E+08 TE-129M 5.58E+08 1.91E+08 8.59E+07 2.14E+08 1.39E+09 0.OOE+00 3.33E+08 1-131 2.72E+09 3.21E+09 1.41E+09 1.05E+12 3.75E+09 0.OOE+00 1.15E+08 1-133 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E÷07 O.OOE+00 8.96E+06 CS-134 3.65E+10 6.81E+10 6.88E+09 0.OOE+00 1.75E+10 7.19E+09 1.85E+08 CS-136 1.98E+09 5.83E+09 . 2.18E+09 0.OOE+00 2.32E+09 4.75E+08 8.85E+07 CS-137 5.15E+10 6.03E+10 4.27E+09 0.OOE+00 1.62E+10 6.55E+09 1.89E+08 O.OOE+00--

BA-140 2.42E+i08 2.42E+05 1.25E+07 5.75E+04 1.49E+05 5.94E+07 0.OOE+00 CE-141 4.34E+04 2.65E+04 3.12E+03 8.17E+03 O.OOE+00 1.37E+07 1.30E+05 0.OOE+00 CE-144 2.33E+06 9.53E+05 3.85E+05 0.OOE+00 1.34E+08 PR-143 1.49E+03 5.56E+02 7.37E+01 0.OOE+00 2.07E+02 0.OOE+00 7.84E+05 ND-147 8.83E+02 9.07E+02 5.55E+01 0.OOE+00 3.50E+02 0.OOE+00 5.75E+05

CY-TM-1 70-300 Revision 2 Page 150 of 209 TABLE 5.4.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-COW-MILK NUCLIDEORGAN DOSE FACTORS; M2 mremyear per Ci/sec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 CR-51 0.00E+00 O.OOE+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 MN-54 0.OOE+00 2.10E+07 5.59E+06 0.OOE+00 5.89E+06 0.OOE+00 1.76E+07 FE-55 1.12E+08 5.94E+07 1.84E+07 0.OOE+00 0.OOE+00 3.36E+07 1.10E+07 FE-59 1.20E+08 1.95E+08 9.70E+07 0.OOE+00 0.OOE+00 5.65E+07 2.03E+08 CO-58 0.OOE+00 1.21E+07 3.72E+07 0.( )OE+00 0.OOE+00 0.OOE+00 7.08E+07 CO-60 0.OOE+00 4.32E+07 1.27E+08 0.( )OE+00 0.OOE+00 O.OOE+00 2.39E+08 NI-63 2.97E+10 1.59E+09 1.01E+09 0.()OE+00 0.OOE+00 0.OOE+00 1.07E+08 ZN-65 4.14E+09 1.10E+10 6.86E+09 0.(0OE+00 6.95E+09 0.OOE+00 1.94E+09 RB-86 0.O0E+00 8.78E+09 5.40E+09 0.( )OE+00 O.OOE+00 0.OOE+00 5.65E+08 SR-89 6.63E+09 0.OOE+00 1.89E+08 0.(0OE+00 0.O0E+00 0.OOE+00 2.57E+08 SR-90 1.12E+11 0.OOE+00 2.84E+10 0.()OE+00 O.OOE+00 0.OOE+00 1.51E+09 Y-91 3.91E+04 0.OOE+00 1.05E+03 0.()OE+00 0.OOE+00 O.OOE+00 5.21E+06 ZR-95 3.84E+03 8.43E+02 7.51 E+02 0.()OE+0O 1.21E+03 0.OOE+00 8.80E+05 NB-95 3.18E+05 1.24E+05 8.86E+04 0.()OE+00 1.16E+05 O.OOE+00 2.29E+08 RU-103 4.29E+03 0.OOE+00 1.65E+03 0.()OE+00 1.08E+04 0.OOE+00 1.11E+05 RU-1 OE 9.25E+04 0.OOE+00 1.15E+04 0. )QE+0O 1.25E+05 0.OOE+00 1.44E+06 AG-11i )M 2.09E+08 1.41E+08 1.13E+08 0.( )OE+00 2.63E+08 0.OOE+00 1.68E+10 TE-125 M 7.39E+07 2.OOE+07 9.85E+06 2.()7E+07 O.OOE+00 0.OOE+00 7.13E+07 TE-127 M 2.08E+08 5.61E+07 2.47E+07 4.*)8E+07 5.94E+08 0.OOE+00 1.69E+08 TE-129 M 2.72E+08 7.59E+07 4.22E+07 8. !'6E+07 7.98E+08 0.OOE+00 3.31E+08 1-131 1.31E+09 1.31E+09 7.46E+08 4.C~4E+11 2.16E+09 0.OOE+00 1.17E+08 1-133 1.72E+07 2.13E+07 8.05E+06 3.ý ~5E+09 3.55E+07 0.OOE+00 8.58E+06 CS-134 2.27E+10 3.72E+10 7.85E+09 0.OOE+00 1.15E+10 4.14E+09 2.01 E+08 CS-136 1.01E+09 2.79E+09 1.80E+09 0.OOE+O0 1.49E+09 2.21 E+08 9:80E+07 CS-137 3.23E+10 3.09E+10 4.56E+09 0.OOE+00 1.01E+10 3.62E+09 1.93E+08 BA-140 1.18E+08 1.03E+05 6.86E+06 0.OOE+00 3.35E+04 6.14E+04 5.96E+07 CE-141 2.19E+04 1.09E+04 1.62E+03 Q.OOE+00 4.79E+03 0.00E+00 1.36E+07 CE-144 1.63E+06 5.09E+05 8.67E+04 0.OOE+00 2.82E+05 0.OOE+00 1.33E+08 PR-143 7.18E+02 2.16E+02 3.56E+01 O.OOE+00 1.17E+02 0.OOE+00 7.75E+05 ND-147 4.45E+02 3.61E+02 2.79E+01 0.OOE+00 1.98E+02 0.OOE+00 5.71E+05

CY-TM-1 70-300 Revision 2 Page 151 of 209 TABLE 5.4.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-COW-MILK NUCLIDE -- ORGAN DOSE FACTORS; M 2 _

BONE LIVER -- TOBODY -- THYROID mrem/year -- KIDNEYper

- pCi/sec------

LUING- . GI-LLI H-3 0.OOE+00 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 C-14 4.86E+08 9.73E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 CR-51 O.OOE+00 0.OOE+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 MN-54 0.OOE+00 1.40E+07 2.78E+06 0.OOE+00 4.19E+06 0.OOE+00 2.88E+07 FE-55 4.46E+07 3.16E+07 7.37E+06 0.OOE+00 0.OOE+00 2.01E+07 1.37E+07 FE-59 5.19E+07 1.21E+08 4.68E+07 0.OOE+00 0.OOE+00 3.82E+07 2.86E+08 CO-58 0.OOE+00 7.94E+06 1.83E+07 0.OOE+00 0.OOE+00 0.00E+00 1.10E+08 CO-60 0.OOE+00 2.78E+07 6.27E+07 0.00E+00 0.OOE+00 0.00E+00 3.62E+08 NI-63 1.18E+10 8.36E+08 4.01E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.33E+08 ZN-65 2.11E+09 7.32E+09 3.42E+09 O.OOE+00 4.69E+09 0.OOE+00 3.10E+09 RB-86 0.00E+00 4.73E+09 2.22E+09 0.OOE+00 0.OOE+00 0.O0E+00 7.OOE+08 SR-89 2.68E+09 0.OOE+00 7.67E+07 0.OOE+00 0.OOE+00 0.OOE+00 3.19E+08 SR-90 6.62E+10 0.OOE+00 1.63E+10 0.OOE+00 0.OOE+00 0.OOE+00 1.86E+09 Y-91 1.58E+04 0.OOE+00 4.24E+02 0.00E+00 0.OOE+00 0.OOE+00 6.48E+06 ZR-95 1.65E+03 5.21E+02 3.58E+02 0.OOE+00 7.65E+02 0.OOE+00 1.20E+06 NB-95 1.41E+05 7.82E+04 4.30E+04 0.OOE+00 7.58E+04 0.OOE+00 3.34E+08 RU-103 1.81E+03 0.OOE+00 7.75E+02 0.OOE+00 6.39E+03 0.OOE+00 1.51E+05 RU-106 3.76E+04 0.OOE+00 4.73E+03 0.OOE+00 7.24E+04 0.OOE+00 1.80E+06 AG-110M 9.64E+07 9.12E+07 5.55E+07 0.OOE+00 1.74E+08 0.OOE+00 2.56E+10 TE-125M 3.01E+07 1.08E+07 4.02E+06 8.40E+06 0.OOE+00 0.OOE+00 8.87E+07 TE-127M 8.45E+07 3.OOE+07 1.OOE+07 2.01E+07 3.42E+08 0.OOE+00 2.11E+08 TE-129M 1.1OE+08 4.09E+07 1.74E+07 3.56E+07 4.61E+08 0.OOE+00 4.14E+08 1-131 5.38E+08 7.53E+08 4.05E+08 2.20E+1 1 1.30E+09 0.OOE+00 1.49E+08 1-133 7.08E+06 1.20E+07 3.66E+06 1.68E+09 2.11E+07 0.OOE+00 9.09E+06 CS-134 9.83E+09 2.31E+10 1.07E+10 0.OOE+00 7.35E+09 2.81E+09 2.88E+08 CS-136 4.49E+08 1.77E+09 1.19E+09 0.OOE+00 9.63E+08 1.52E+08 1.42E+08 CS-137 1.34E+10 1.78E+10 6.21E+09 0.OOE+00 6.06E+09 2.36E+09 2.54E+08 BA-140 4.87E+07 5.97E+04 3.14E+06 0.OOE+00 2.02E+04 4.01E+04 7.51E+07 CE-141 8.89E+03 5.94E+03 6.82E+02 0.OOE+00 2.80E+03 0.OOE+00 1.70E+07 CE-144 6.59E+05 2.73E+05 3.54E+04 0.OOE+00 1.63E+05 0.OOE+00 1.66E+08 PR-143 2.90E+02 1.16E+02 1.44E+01 0.00E÷00 6.73E+01 0.O0E+00 9.55E+05 ND-147 1.81E+02 1.97E+02 1.18E+01 0.OOE+00 1.16E+02 0.OOE+00 7.12E+05

CY-TM-170-300 Revision 2 Page 152 of 209 TABLE 5.4.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MILK NUCLIDE ORGAN DOSE FACTORS; M - mrem/year per pCi/sec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 C-14 2.63E+08 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 CR-51 0.00E+00 0.00E+00 2.85E+04 1.70E+04 6.28E+03 3.78E+04 7.17E+06 MN-54 0.OOE+00 8.40E+06 1.60E+06 0.00E+00 2.50E+06 0.OOE+00 2.57E+07 FE-55 2.51E+07 1.73E+07 4.04E+06 0.OOE+00 0.00E+00 9.66E+06 9.93E+06 FE-59  :" 2.97E+07 6.97E+07 2.67E+07 0.OOE+00 0.OOE+00 1.95E+07 2.32E+08 CO-58 0.OOE+00 4.71E+06 1.05E+07 0.OOE+00 0.00E+00 0.OOE+00 9.54E+07 CO-60 0.OOE+00 1.64E+07 3.61E+07 0.OOE+00 0.OOE+00 0.OOE+00 3.08E+08 NI-63 6.72E+09 4.65E+08 2.25E+08 0.OOE+00 0.OOE+00 0.OOE+00 9.71E+07 ZN-65 1.37E+09 4.36E+09 1.97E+09 O.OOE+00 2.91 E+09 0.OOE+0O 2.74E+09 RB-86 0.OOE+00 2.59E+09 1.21E+09 0.OOE+00 0.OOE+00 0.OOE+00 5.1 OE+08 SR-89 1.45E+09 O.OOE+00 4.16E+07 0.OOE+00 0.OOE+00 O.OOE+0O 2.32E+08

--.-OE+--

SR-90 4.67E+10 0.OOE+00 1.15E+10 O.O0E+00 0.OOE+00 1.35E+09 Y-91 0.OOE+00 8.57E+03 0.OOE+00 2.29E+02 0.OOE+00 0.OOE+00 4.72E+06 ZR-95 9.41E+02 3.02E+02 2.04E+02 0.OOE+00 4.74E+02 0.OOE+00 9.57E+05 NB-95 8.24E+04 4.58E+04 2.46E+04 0.OOE+00 4.53E+04 O.OOE+00 2.78E+08 RU-103 1.02E+03 0.OOE+00 4.38E+02 0.OOE+00 3.88E+03 0.OOE+00 1.19E+05 RU-10E 2.04E+04 0.OOE+00 2.58E+03 0.OOE+00 3.93E+04 0.OOE+00 1.32E+06 AG-110M 5.81E+07 5.38E+07 3.19E+07 0.OOE+00 1.06E+08 0.OOE+00 2.19E+10 TE-125M 1.63E+07 5.89E+06 2.18E+06 4 .89E+06 6.61E+07 0.OOE+00 6.49E+07 TE-127M 4.57E+07 1.63E+07 5.57E+06 1.17E+07 1.86E+08 0.OOE+00 1.53E+08 TE-129M 6.01E+07 2.24E+07 9.51E+06 2.06E+07 2.51 E+08 0.OOE+00 3.02E+08 1-131 2.96E+08 4.23E+08 2.42E+08 1.39E+11 7.25E+08 0.OOE+00 1.12E+08 1-133 3.87E+06 6.73E+06 2.05E+06 9.88E+I08 1.17E+07 0.OOE+00 6.04E+06 CS-1 34 5.64E+09 1.34E+10 1.10E+10 0.00E+00 4.34E+09 1.44E+09 2.35E+08 CS-1 36 2.63E+08 1.04E+09 7.48E+08 0.OOE+00 5.78E+08 7.92E+07 1.18E+08 CS-1 37 7.37E+09 1.01E+10 6.60E+09 0.OOE+00 3.42E+09 1.14E+09 1.95E+08 BA-140 2.69E+07 3.38E+04 1.76E+06 0.OOE+00 1.15E+04 1.94E+04 5.54E+07 CE-141 4.84E+03 3.27E+03 3.71E+02 0.OOE+00 1.52E+03 0.OOE+00 1.25E+07 CE-144 3.57E+05 1.49E+05 1.92E+04 O.00E+00 8.85E+04 0.001E+00 1.21 E+08 PR-143 1.57E+02 6.32E+01 7.81E+00 0.00E+00 3.65E+01 0.OOE+00 6.90E+05 ND-147 9.40E+01 1.09E+02 6.50E+0O 0.OOE+00 6.35E+01 0.OOE+00 5.22E+05

CY-TM-170-300 Revision 2 Page 153 of 209 TABLE 5.5.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK NUCLIDE DORGA DOSE FACTORS; M 2 - mrem/year per pCi/sec

[ BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 C-14 2.34E+09 5.OOE+08 5.OOE+08 5.OOE+08 5.OOE+08 5.OOE+08 5.OOE+08 CR-51 0.00E+00 0.00E+00 1.94E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05 MN-54 O.OOE+00 4.68E+06 1.06E+06 0.OOE+00 1.04E+06 0.OOE+00 1.72E+06 FE-55 1.76E+06 1.14E+06 3.03E+05 0.OOE+00 0.OOE+00 5.55E+05 1.44E+05 FE-59 2.92E+06 5.10E+06 2.01E+06 0.OOE+00 0.OOE+00 1.51E+06 2.44E+06 CO-58 0.OOE+00 2.91E+06 7.26E+06 0.OOE+00 O.OOE+00 0.OOE+00 7.25E+06 CO-60 0.OOE+00 1.06E+07 2.50E+07 0.OOE+00. 0.OOE+00 0.OOE+00 2.52E+07 NI-63 4.19E+09 2.59E+08 1.46E+08 0.OOE+00 0.OOE+00 O.OOE+00 1.29E+07 ZN-65 6.67E+08 2.29E+09 1.05E+09 O.OE+00 1.11E+09 0.OOE+00 1.93E+09 RB-86 0.OOE+00 2.67E+09 1.32E+09 0.OOE+00 0.OOE+00 O.OOE+00 6.83E+07 SR-89 2.65E+10 0.OOE+00 7.59E+08 0.OOE+00 O.0OE+00 0.OOE+00 5.44E+08 SR-90 2.55E+1 1 0.OOE+00 6.50E+10 0.OOE+00 0.OOE--00 0.00E+00 3.19E+09 Y-91 8.80E+03 0.OOE+00 2.34E+02 0.OOE+00 0.OOE+00 0.OOE+00 6.31 E+05 ZR-95 8.17E+02 1.99E+02 1.41E+02 Q.OOE+00 2.15E+02 0.OOE+0Q 9.91 E+04

---

E---

NB-95 7.13E+04 2.93E+04 1.70E+04 2.1 OE+04 0.00E+00 2.48E+07 RU-103 1.04E+03 0.OOE+00 0.OOE+00 3.48E+02 2.17E+03 0.OOE+00 1.27E+04 RU-106 2.28E+04 2.85E+03 0.OOE+O0 0.OOE+00 2.70E+04 0.OOE+00 1.73E+05 0.OOE+00 AG-110M 4.63E+07 3.38E+07 2.24E+07 4.84E+07 0.OOE+00 1.75E+09 TE-125M 1.81 E+07 6.05E+06 2.45E+06 6.09E+06 0.OOE+C0 0.OOE+00 8.62E+06 TE-127M 5.06E+07 1.68E+07 6.12E+06 1 .46E+07 1 .24E+08 0.OOE+00 2.04E+07 TE-129M 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 0.O0E+00 3.99E+07 1-131 3.27E+09 3.85E+09 1.69E+09 1.27E+12 4.50E+09 O.OOE+00 1.37E+08 1-133 4.36E+07 6.35E+07 1.86E+07 1.15E+10 7.46E+07 0.OOE+00 1.07E+07 CS-134 1.09E+11 2.04E+11 2.06E+10 O.OOE+00 5.26E+10 2.15E+10 5.55E+08 CS-136 5.94E+09 1.75E+10 6.52E+09 0.OOE+00 6.96E+09 1.42E+09 2.65E+08 CS-137 1.54E+11 1.81E+11 1.28E+10 0.OOE+00 4.85E+10 1.96E+10 5.65E+08 BA-140 2.90E+07 2.90E+04 1.50E+06 0.OOE+00 6.89E+03 1.78E+04 7.13E+06 CE-141 5.21E+03 3.18E+03 3.74E+02 0.OOE+00 9.79E+02 O.OOE+00 1.64E+06 CE-144 2.79E+05 1.14E+05 1.56E+04 0.OOE+00 4.62E+04 0.OOE+00 1.60E+07 PR-143 1.78E+02 6.66E+01 8.83E+00 0.OOE+00 2.48E+01 0.OOE+00 9.40E+04 ND-147 1.06E+02 1.09E+02 6.66E+00 0.OOE+00 4.19E+01 0.OOE+00 6.89E+04

CY-TM-170-300 Revision 2 Page 154 of 209 TABLE 5.5.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-GOAT-MILK NUCID IORGAN DOSE FACTORS; M2 _- mrem/year per jiCi/sec

---

BONE --- LIVER T.BODY -- THYROID -KIDNEY -- LUNG GI-LLI__

H-3 0.OOE+00 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 CR-51 0.OOE+00 0.OOE+00 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.48E+05 MN-54 0.O0E+00 2.52E+06 6.71E+05 O.OOE+00 7.06E+05 0.OOE+00 2.11E+06 FE-55 1.45E+06 7.71E+05 2.39E+05 0.OOE+00 0.OOE+00 4.36E+05 1.43E+05 FE-59 1.56E+06 2.53E+06 1.26E+06 0.OOE+00 0.OOE+00 7.34E+05 2.64E+06 CO-58 0.OOE+00 1.46E+06 4.46E+06 0.OOE+00 0.OOE+00 0.OOE+00 8.49E+06 CO-60 0.OOE+00 5.18E+06 1.53E+07 O.OOE+00 0.OOE+00 0.OOE+00 2.87E+07 NI-63 3.56E+09 1.91E+08 1.21E+08 O.OOE+00 0.OOE+00 0.OOE+00 1.28E+07 ZN-65 4.96E+08 1.32E+09 8.22E+08 0.OOE+00 8.33E+08 0.OOE+00 2.32E+08 RB-86 0.OOE+00 1.05E+09 6.47E+08 O.OOE+00 0.OOE+00 0.OOE+00 6.77E+07 SR-89 1.39E+10 0.OOE+00 3.97E+08 0.OOE+00 O.OOE+00 0.OOE+00 5.39E+08 SR-90 2.35E+11 0.OOE+00 5.95E+10 0.OOE+00 0.OOE+00 0.OOE+00 3.16E+09 Y-91 4.69E+03 0.OOE+00 1.25E+02 0.OOE+00 O.OOE+00 0.OOE+00 6.24E+05 ZR-95 4.60E+02 1.01E+02 9.OOE+01 0.OOE+00 1.45E+02 0.OOE+00 1.05E+05 NB-95 3.82E+04 1.49E+04 1.06E+04 0.OOE+00 1.40E+04 0.O0E+00 2.75E+07 RU-103 5.14E+02 O.OOE+00 1.98E+02 0.OOE+00 1.29E+03 0.OOE+00 1.33E+04 RU-106 1.11E+04 0.OOE+00 1.38E+03 0.OOE+00 1.50E+04 0.OOE+00 1.73E+05 AG-110M 2.51E+07 1.69E+07 1.35E+07 0.OOE+00 3.15E+07 0.OOE+00 2.01E+09 TE-125M 8.86E+06 2.40E+06 1.18E+06 2.49E+06 0.OOE+00 0.OOE+00 8.55E+06 TE-127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 0.OOE+00 2.02E+07 TE-129M 3.26E+07 9.10E+06 5.06E+06 1.05E+07 9.56E+07 O.OOE+00 3.97E+07 1-131 1.57E+09 1.57E+09 8.95E+08 5.21E+11 2.58E+09 0.OOE+00 1.40E+08 1-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 0.OOE+00 1.03E+07 CS-134 6.80E+10 1.12E+11 2.35E+10 0.OOE+00 3.46E+10 1.24E+10 6.01E+08 CS-1 36 3.04E+09 8.36E+09 5.41E+09 0.OOE+00 4.45E+09 6.64E+08 2.94E+08 CS-137 9.68E+10 9.26E+10 1.37E+10 O.OOE+00 3.02E+10 1.09E+10 5.80E+08 BA-140 1.41E+07 1.24E+04 8.23E+05 0.OOE+00 4.02E+03 7.37E+03 7.15E+06 CE-141 2.63E+03 1.31E+03 1.95E+02 O.OOE+00 5.74E+02 0.OOE+00 1.63E+06 CE-144 1.95E+05 6.11E+04 1.04E+04 O.OOE+00 3.38E+04 0.OOE+00 1.59E+07 PR-143 8.61E+01 2.59E+01 4.27E+00 O.OOE+00 1.40E+01 0.OOE+00 9.29E+04 ND-147 5.34E+01 4.33E+01 3.35E+00 0.OOE+00 2.37E+01 0.OOE+00 6.85E+04

CY-TM-1 70-300 Revision 2 Page 155 of 209 TABLE 5.5.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK NUCLIDE ---- ORGAN DOSE FACTORS; M2 _ mrem/year per jýiCilsec --*-----

-BONE - LIVER - _T. BODY -- THYROID - KIDNEY _ -LUNG GI-LLI_

H-3 o.00E+00 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 C-14 4.86E+08 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 CR-51 0.OOE+00 0.OOE+00 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+06 MN-54 O.OOE+00 1.68E+06 3.34E+05 0.OOE+00 5.02E+05 0.OOE+00 3.45E+06 FE-55 5.79E+05 4.11E+05 9.58E+04 0.OOE+00 0.OOE+00 2.61E+05 1.78E+05 FE-59 6.74E+05 1.57E+06 6.08E+05 0.OOE+00 0.00E+00 4.96E+05 3.72E+06 CO-58 0.OOE+00 9.53E+05 2.20E+06 0.00E+00 0.OOE+00 0.OOE+00 1.31 E+07 CO-60 0.00E+00 3.34E+06 7.52E+06 0.00E+00 0.OOE+00 O.OOE+00 4.35E+07 NI-63 1.42E+09 1.00E+08 4.81E+07 0.OOE+00 O.00E+00 O.OOE+00 1.60E+07 ZN-65 2.53E+08 8.78E+08 4.10E+08 0.00E+00 5.62E+08 0.00E+00 3.72E+08 RB-86 0.OOE+00 5.67E+08 2.67E+08 O.OOE+00 0.OOE+00 O.OOE+00 8.40E+07 SR-89 5.62E+09 0.00E+00 1.61E+08 O.00E+00 0.OOE+00 0.OOE+00 6.69E+08 SR-90 1.39E+l1 0.OOE+00 3.43E+10 0.OOE+00 0.00E+00 0.OOE+00 3.90E+09 Y-91 1.90E+03 0.OOE+00 5.09E+01 0.00E+00 0.00E+00 0.OOE+00 7.78E+05 ZR-95 1.98E+02 6.25E+01 4.30E+01 0.OOE+00 9.18E+01 0.0OE+00 1.44E+05 NB-95 1.69E+04 9.38E+03 5.16E+03 0.OOE+00 9.09E+03 0.OOE+00 4.01E+07 RU-103 2.17E+02 0.OOE+00 9.29E+01 0.00E+00 7.66E+02 O.OOE+00 1.82E+04 RU-106 4.50E+03 0.OOE+00 5.68E+02 O.00E+00 8.69E+03 0.OOE+00 2.16E+05 AG-11OM 1.16E+07 1.09E+07 6.65E+06 O.OOE+00 2.09E+07 0.00E+00 3.07E+09 TE-125M 3.61 E+06 1.30E+06 4.82E+05 1.01E+06 O.00E+00 0.O0E+00 1.06E+07 TE-127M 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.11E+07 0.O0E+00 2.52E+07 TE-129M 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 0.OOE+00 4.96E+07 1-131 6.45E+08 9.03E+08 4.85E+08 2.64E+i 1 1.56E+09 0.00E+00 1.79E+08 1-133 8.49E+06 1.44E+07 4.40E+06 2.01 E+09 2.53E+07 0.OOE+00 1.09E+07 CS-1 34 2.95E4-10 6.93E+10 3.22E+10 0.00E+00 2.20E+10 8.41E+09 8.62E+08 CS-1 36 1.35E+09 5.30E+09 3.56E+09 0.OOE+00 2.89E+09 4.55E+08 4.27E+08 CS-1 37 4.02E+1 0 5.34E+10 1.86E+10 0.00E+00 1.82E+10 7.07E+09 7.60E+08 BA-140 5.84E+06 7.16E+03 3.76E+05 0.OOE+00 2.43E+03 4.81E+03 9.01 E+06 CE-141 1.07E+03 7.12E+02 8.18E+01 O.OOE+00 3.35E+02 0.OOE+00 2.04E+06 CE-144 7.90E+04 3.27E+04 4.25E+03 0.OOE+00 1.95E+04 0.00E+00 1.99E+07 PR-143 3.48E+01 1.39E+01 1.73E+00 0.OOE+00 8.08E+00 0.OOE+00 1.15E+05 ND-147 2.18E+01 2.37E+01 1.42E+00 O.OOE+00 1.39E+01 0.OOE+00 8.54E+04

CY-TM-170-300 Revision 2 Page 156 of 209 TABLE 5.5.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-GOAT-MILK NUCLIDE .ORGANOSE FACT  ;;m. - mrem/year per -iCi/sec---------

---

BONE --- LIVER ___T.BODY -- THYROID -KIDNEY -- LUNG--- GI-LLI.ý H-3 0.OOE+00 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 C-14 2.64E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 CR-51 0.OOE+00 O.OOE+00 3.43E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+05 MN-54 0.OOE+00 1.01E+06 1.93E+05 0.OOE+00 3.01E+05 0.OOE+00 3.10E+06 FE-55 3.27E+05 2.26E+05 5.26E+04 O.OOE+00 0.OOE+00 1.26E+05 1.30E+05 FE-59 3.87E+05 9.09E+05 3.48E+05 0.OOE+00 0.OOE+00 2.54E+05 3.03E+06 CO-58 0.OOE+00 5.66E+05 1.27E+06 0.OOE+00 O.OOE+00 O.OOE+00 1.15E+07 CO-60 0.00E+00 1.97E+06 4.35E+06 0.OOE+00 0.OOE+00 0OOE+00 3.70E+07 NI-63 8.08E+08 5.60E+07 2.71E+07 0.O0E+00 0.OOE+00 0.OOE+00 1.17E+07 ZN-65 1.65E+08 5.24E+08 2.37E+08 0.OOE+00 3.51E+08 0.OOE+00 3.30E+08 RB-86 0.OOE+00 3.12E+08 1.45E+08 0.OOE+00, 0.00E+00 0.OOE+00 6.14E+07 SR-89 3.05E+09 0.OOE+00 8.76E+07 0.OOE+00 0.OOE+00 O.OOE+00 4.89E+08 SR-90 9.84E+10 0.OOE+00 2.41E+10 O.OOE+00 O.OOE+00 0.OOE+00 2.84E+09 Y-91 1.03E+03 0.OOE+00 2.76E+01 0.OOE+00 O.OOE+00 O.OOE+00 5.68E+05 ZR-95 1.13E+02 3.63E+01 2.46E+01 O.OOE+00 5.70E+01 O.OOE+00 1.15E+05 NB-95 9.92E+03 5.52E+03 2.97E+03 0.OOE+00 5.45E+03 0.OOE+00 3.35E+07 RU-103 1.22E+02 0.OOE+00 5.27E+01 0.OOE+00 4.67E+02 0.OOE+00 1.43E+04 RU-106 2.45E+03 0.OOE+00 3.10E+02 0.OOE+00 4.73E+03 0.OOE+00 1.59E+05 AG-110M 6.99E+06 6.47E+06 3.84E+06 0.OOE+00 1.27E+07 0.QOE+00 2.64E+09 TE-125M 1.96E+06 7.09E+05 2.62E+05 5.89E+05 7.96E+06 O.OOE+00 7.81E+06 TE-127M 5.50E+06 1.97E+06 6.70E+05 1.41E+06 2.23E+07 0.OOE+00 1.84E+07 TE-129M 7.23E+06 2.70E+06 1.14E+06 2.48E+06 3.02E+07 0.OOE+00 3.64E+07 1-131 3.56E+08 5.09E+08 2.92E+08 1.67E+11 8.73E+08 0.OOE+00 1.34E+08 1-133 4.65E+06 8.1OE+06 2.47E+06 1.19E+09 1.41 E+07 0 .OOE+0O 7.28E+06 CS-134 1.70E+10 4.04E+10 3.30E+10 0.00 E+00 1.31E+10 4.34E+09 7.07E+08 0.OOE+00 CS-1 36 7.92E+08 3.13E+09 2.25E+09 0.OOE+00 1.74E+09 2.38E+08 3.55E+08 CS-137 2.22E+10 3.03E+10 1.99E+10 1.03E+10 3.42E+09 5.87E+08 0.OOE+00 BA-140 3.24E+06 4.07E+03 2.12E+05 0.OOE+00 1.38E+03 2.33E+03 6.67E+06 CE-141 5.82E+02 3.94E+02 4.47E+01 0.00E+00 1.83E+02 0.OOE+00 1.51 E+06 CE-144 4.30E+04 1.80E+04 2.31 E+03 1.07E+04 0.OOE+00 1.45E+07 PR-143 1.90E+01 7.60E+00 9.40e-01 0.OOE+00 4.39E+00 0.OOE+00 8.30E+04 ND-147 1.13E+01 1.31E+01 7.82e-01 0.OOE+00 7.65E+00 0.OOE+00 6.28E+04

CY-TM-1 70-300 Revision 2 Page 157 of 209 TABLE 5.6.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT NDUECL --- --- ---OR GA N *D OS E FA CT O R S; -m 2

- m re m/y ea r pe r giCi/s ec - -- - - - -

NUCL_ __IDEBONE LIVER --- T.BODY -THYROID -KIDNEY -- LUING--- GI-LLI__

H-3 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 C-14 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 CR-51 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

. . . . . . . . ÷ . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . .

MN-54 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE-i00 0.OOE+00 0.OOE+O0 0.OOE+00 FE-55 0.OOE+00 0.OOE+00 0.OOE-'00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 FE-59 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 O.OOE+O0- 0.OOE+00--

CO-58 0.OOE+00 0.OOE+00 0.COE+0O 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 CO-60 0.OOE+00 0.OOE+00 0.OOE-'00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 NI-63 0.OOE+00 0.OOE+00 0.OOE-'00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 ZN-65 0.OOE+00 0.OOE+00 --.- OE--- 0.OOE+O0--

RB-86 0.OOE+00 0.OOE-s00 0.OOEi-00 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 SR-89 Q.OOE+00 0.OOE-'00 O.OOE-'00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OO-i---0--.---E-0---O.OOE+00 SR-90 Y-91 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 ZR-95 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-s00 O.OOE+00 0.COE+OQ 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 NB-95 0.OOE+00O .OOE+00 RU-103 O.OOE+00 0.OOE.O0 Q.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 RU-106 0.OOE+O0 0.OOE+0Q O.OOE+O0 0.OOE+00 AG-1 10M 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 TE-125M 0.OOE+00O .OOE-i00 0.OOE+00 O.0OE+00 O.OOE-'0Q Q.OOE+Q0 Q.OOE+00 TE-127M 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00

---

OE+0---.--OE+O --.- QE+O ----.OQE+O - 0.OOE+0O 0.OOE+00--

TE-129M 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+O0 1-131 0.OOE+00 0.OOE+00 0.OOE-.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-133 0.OOE+00 0.OOE+00 0.OOE-I00 0.OOE+00 O.OOE+00 O.OOE+O0 0.OOE+00 CS-134 0.OOE+00 0.OO-'----- 0.O--E+-0---.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CS-1 36 0.OOE+00 0.OOE+00O .OOE+00 0.00E+00 0.OOE+00 0.OOE.OO CS-137 0.OOE+O0 BA-140 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 CE-141 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CE-144 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 PR-143 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 ND-147 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00

CY-TM-170-300 Revision 2 Page 158 of 209 TABLE 5.6.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-COW-MEAT NUC LIDE ------------ORGAN . . . .- DOSE FACTORS; m2 - mrem/year

---

. . per

---

. . piCi/sec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 C-14 3.84E+08 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 CR-51 0.OOE+00 0.OOE+00 8.78E+03 4.88E+03 1.33E+03 8.90E+03 4.66E+05 MN-54 0.OOE+00 8.01E+06 2.13E+06 0.OOE+00 2.25E+06 0.OOE+00 6.73E+06 FE-55 4.57E+08 2.43E+08 7.52E+07 O.OOE+00 0.OOE+00 1.37E+08 4.49E+07 FE-59 3.77E+08 6.10E+08 3.04E+08 0.OOE+00 0.OOE+00 1.77E+08 6.35E+08 CO-58 0.OOE+00 1.64E+07 5.03E+07 0.OOE+00 0.OOE+00 0.OOE+00 9.58E+07 CO-60 0.OOE+00 6.93E+07 2.04E+08 0.OOE+00 0.00E+00 0.OOE+00 3.84E+08 NI-63 2.91E+10 1.56E+09 9.91E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.05E+08 ZN-65 3.76E+08 1.OOE+09 6.22E+08 0.OOE+00 6.31E+08 0.OOE+00 1.76E+08 RB-86 0.OOE+00 5.76E+08 3.54E+08 0.OOE+00 O.OOE+00 0.OOE+00 3.71E+07 SR-89 4.82E+08 0.OOE+00 1.38E+07 O.OOE+00 O.OOE+00 0.OOE+00 1.87E+07 SR-90 1.04E+10 0.OOE+00 2.64E+09 0.OOE+00 0.OOE+00 0.OOE+00 1.40E+08 Y-91 1.80E+06 0.OOE+00 4.82E+04 0.OOE+00 0.00E+00 0.OOE+00 2.40E+08 ZR-95 2.66E+06 5.86E+05 5.21E+05 0.OOE+00 8.38E+05 0.OOE+00 6.11E+08 NB-95 3.10E+06 1.21E+06 8.63E+05 0.OOE+00 1.13E+06 0.OOE+00 2.23E+09 RU-1 03 1.55E+08 0.OOE+00 5.96E+07 0.OOE+00 3.90E+08 0.OOE+00 4.01E+09 RU-1 06 4.44E+09 0.OOE+00 5.54E+08 0.OOE+00 6.OOE+09 O.OOE+00 6.91E+10 AG-110M 8.39E+06 5.67E+06 4.53E+06 0.OOE+00 1.06E+07 0.OOE+00 6.74E+08 TE-125M 5.69E+08 1.54E+08 7.59E+07 1.60E+08 0.OOE+00 0.OOE+00 5.49E+08 TE-127M 1.78E+09 4.78E+08 2.11E+08 4.25E+08 5.06E+09 0.OOE+00 1.44E+09 TE-129M 1.79E+09 5.OOE+08 2.78E+08 5.77E+08 5.26E+09 0.OOE+00 2.18E+09 1-131 1.66E+07 1.67E+07 9.48E+06 5.52E+09 2.74E+07 0.OOE+00 1.48E+06 1-133 5.72e-01 7.08e-01 2.68e-01 1.31 E+02 1.18E+00 0.OOE+00 2.85e-01 CS-134 9.23E+08 1.51E+09 3.19E+08 0.OOE+00 4.69E+08 1.68E+08 8.16E+06 CS-136 1.63E+07 4.48E+07 2.90E+07 0.OOE+00 2.39E+07 3.56E+06 1.57E+06 CS-137 1.33E+09 1.28E+09 1.89E+08 0.OOE+00 4.16E+08 1.50E+08 8.OOE+06 BA-140 4.42E+07 3.87E+04 2.58E+06 0.OOE+00 1.26E+04 2.31 E+04 2.24E+07 CE-141 2.22E+04 1.11E+04 1.65E+03 0.OOE+00 4.86E+03 0.OOE+00 1.38E+07 CE-144 2.32E+06 7.26E+05 1.24E+05 0.OOE+00 4.02E+05 0.OOE+00 1.89E+08 PR-143 3.33E+04 1.00E+04 1.65E+03 0.OOE+00 5.42E+03 0.00E+00 3.60E+07 ND-147 1.17E+04 9.48E+03 7.34E+02 0.OOE+00 5.20E+03 0.OOE+00 1.50E+07

CY-TM-1 70-300 Revision 2 Page 159 of 209 TABLE 5.6.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-COW-MEAT NUCLIDE ORGAN DOSE FACTORS; M 2 - mrem/year per pCi/sec..

O----

---

BONE -_ -LIVER _ T.BODY -- THYROID -KIDNEY -- LUNG GI-LLI__

H-3 0.OOE+00 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 C-14 2.04E+08 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 CR-51 0.00E+00 0.OOE+00 5.63E+03 3.13E+03 1.23E+03 8.03E+03 9.46E+05 MN-54 0.OOE+00 7.OOE+06 1.39E+06 0.OOE+00 2.09E+06 0.OOE+00 1.44E+07 FE-55 2.38E+08 1.69E+08 3.94E+07 0.OOE+00 0.OOE+00 "1.07E+08 7.31E+07 FE-59 2.12E+08 4.95E+08 1.91E+08 0.OOE+00 0.OOE+00 1.56E+08 1.17E+09 CO-58 0.OOE+00 1.40E+07 3.24E+07 0.OOE+00 0.OOE+00 0.OOE+00 1.94E+08 CO-60 0.OOE+00 5.83E+07 1.31 E+08 0.OOE+00 0.OOE+00 0.OOE+00 7.60E+08 NI-63 1.52E+10 1.07E+09 5.15E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.71 E+08 ZN-65 2.50E+08 8.68E+08 4.05E+08 0.00E+00 5.56E+08 0.OOE+00 3.68E+08 RB-86 0.OOE-00 4.06E+08 1.91 E+08 0.00E+00 0.OOE+00 0.OOE+00 6.OOE+07 SR-89 2.55E+08 0.OOE+00 7.29E+06 0.OOE+00 0.OOE+00 0.OOE+00 3.03E+07 SR-90 8.04E+09 0.00E+00 1.99E+09 0.OOE+00 0.OOE+00 0.OOE+00 2.26E+08 Y-91 9.54E+05 0.OOE+00 2.56E+04 0.OOE+00 0.OOE+00 0.OOE+00 3.91E+08 ZR-95 1.50E+06 4.73E+05 3.25E+05 0.OOE+00 6.95E+05 0.OOE+00 1.09E+09 NB-95 1.79E+06 9.95E+05 5.48E+05 0.OOE+00 9.64E+05 0.OOE+00 4.25E+09 RU-103 8.56E+07 O.OE+00 3.66E+07 0.OOE+00 3.02E+08 0.OOE+00 7.15E+09 RU-106 2.36E+09 0.OOE+00 2.97E+08 0.OOE+00 4.54E+09 0.OOE+00 1.13E+11 AG-110M 5.06E+06 4.78E+06 2.91E+06 0.OOE+00 9.13E+06 0.OOE+00 1.34E+09 TE-125M 3.03E+08 1.09E+08 4.05E+07 8.46E+07 0.OOE+00 0.OOE+00 8.94E+08 TE-127M 9.41 E+08 3.34E+08 1 .12E+08 2.24E+08 3.81 E+09 0.OOE+00 2.35E+09 TE-129M 9.49E+08 3.52E+08 1.50E+08 3.06E+08 3.97E+09 0.OOE+00 3.56E+09 1-131 8.93E+06 1.25E+07 6.72E+06 3.65E+09 2.15E+07 0.OOE+00 2.47E+06 1-133 3.08e-01 5.22e-01 1.59e-01 7.29E+01 9.16e-01 0.OOE+00 3.95e-01 CS-134 5.23E+08 1.23E+09 5.71E+08 0.OOE+00 3.91E+08 1.49E+08 1.53E+07 CS-136 9.43E+06 3.71E+07 2.49E+07 0.OOE+00 2.02E+07 3.18E+06 2.99E+06 CS-137 7.24E+08 9.63E+08 3.35E+08 0.OOE+00 3.28E+08 1.27E+08 1.37E+07 BA-140 2.39E+07 2.93E+04 1.54E+06 0.OOE+00 9.94E+03 1.97E+04 3.69E+07 CE-141 1.18E+04 7.87E+03 9.05E+02 0.OOE+00 3.71E+03 0.OOE+00 2.25E+07 CE-144 1.23E+06 5.08E+05 6.60E+04 0.OOE+00 3.03E+05 0.OOE+00 3.09E+08 PR-143 1.76E+04 7.03E+03 8.76E+02 0.00E+00 4.08E+03 0.OOE+00 5.79E+07 ND-147 6.23E+03 6.78E+03 4.06E+02 0.OOE+00 3.98E+03 0.OOE+00 2.44E+07

CY-TM-1 70-300 Revision 2 Page 160 of 209 TABLE 5.6.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT NUCL- DE ----- - ORGAN DOSE FACTORS;-m- - mrem/year per VtCi/sec .............

- BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 C-14 2.42E+08 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 CR-51 O.0OE+00 O.OOE+00 7.04E+03 4.21E+03 1.55E+03 9.35E+03 1.77E+06 MN-54 O.OOE+00 9.18E+06 1.75E+06 O.OOE+00 2.73E+06 O.OOE+00 2.81E+07 FE-55 2.93E+08 2.03E+08 4.73E+07 O.OOE+00 O.O0E+00 1.13E+08 1.16E+08 FE-59 2.66E+08 6.25E+08 2.39E+08 O.OOE+00 O.OOE+00 1.75E+08 2.08E+09 CO-58 O.OOE+00 1.82E+07 4.09E+07 O.OOE+00 O.OOE+00 O.OOE+00 3.70E+08 CO-60 O.OOE+00 7.52E+07 1.66E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.41E+09 NI-63 1.89E+10 1.31E+09 6.33E+08 O.OOE+00 O.OOE+00 O.OOE+00 2.73E+08 ZN-65 3.56E+08 1.13E+09 5.12E+08 O.OOE+00 7.57E+08 O.OOE+00 7.13E+08 RB-86 O.O0E+00 4.87E+08 2.27E+08 O.OOE+00 O.OE+00 O.OOE+00 9.59E+07 SR-89 3.02E+08 O.OOE+00 8.66E+06 O.OOE+00 O.OOE+00 O.OOE+00 4.84E+07 SR-90 1.24E+10 O.OOE+00 3.05E+09 O.OOE+00 O.OOE+00 O.OOE+00 3.60E+08 Y-91 1.13E+06 O.OOE+00 3.03E+04 O.OOE+00 O.OOE+00 O.OOE+00 6.24E+08 ZR-95 1.87E+06 6.01E+05 4.07E+05 O.OOE+00 9.43E+05 O.OOE+00 1.90E+09 NB-95 2.30E+06 1.28E+06 6.87E+05 0.OOE+00 1.26E+06 O.OOE+00 7.76E+09 RU-103 1.05E+08 O.OOE+00 4.53E+07 O.OOE+00 4.02E+08 O.OOE+00 1.23E+10 RU-106 2.80E+09 O.OOE+00 3.54E+08 O.OOE+00 5.41E+09 O.OOE+00 1.81E+11 AG-110M 6.68E+06 6.18E+06 3.67E+06 0.OOE+00 1.22E+07 O.OOE+00 2.52E+09 TE-125M 3.59E+08 1.30E+08 4.81E+07 1.08E+08 1.46E+09 O.OOE+00 1.43E+09 TE-127M 1.12E+09 3.99E+08 1.36E+08 2.85E+08 4.53E+09 O.OOE+00 3.74E+09 TE-129M 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 O.OOE+O0 5.71E+09 1-131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 O.OOE+O0 4.06E+06 1-133 3.68e-01 6.41e-01 1.95e-01 9.42E+01 1.12E+00 O.OOE+00 5.76e-01 CS-134 6.58E+08 1.57E+09 1.28E+09 O.00E+00 5.07E+08 1.68E+08 2.74E+07 CS-136 1.21E+07 4.78E+07 3.44E+07 O.OOE+00 2.66E+07 3.65E+06 5.43E+06 CS-137 8.72E+08 1.19E+09 7.82E+08 O.OOE+00 4.05E+08 1.35E+08 2.31E+07 BA-140 2.90E+07 3.64E+04 1.90E+06 O.OE+00 1.24E+04 2.08E+04 5.96E+07 CE-141 1.41E+04 9.51E+03 1.08E+03 0.OOE+00 4.42E+03 O.QOE+00 3.64E+07 CE-144 1.46E+06 6.10E+05 7.83E+04 O.OE+00 3.62E+05 0.00E+00 4.93E+08 PR-143 2.09E+04 8.40E+03 1.04E+03 O.OOE+00 4.85E+03 O.OOE+00 9.17E+07 ND-147 7.08E+03 8.18E+03 4.90E+02 Q.OOE+00 4.78E+03 O.OOE+00 3.93E+07

CY-TM-170-300 Revision 2 Page 161 of 209 TABLE 5.7.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: VEGETATION NUCLIDE ---- ORGAN DOSE FACTORS; M2 _-mrem/year per !ICilsec

-BONE - LIVER -_ T.BODY -- THYROID - KIDNEY - -LUNG ---- GI-LLI_

H-3 O.OOE+00 0.OOE+00 O.OOE+0O O.OOE+00 0.OOE+O0 0.OOE+00 O.OOE+00 C-14 O.OOE+O0 0.OQE+00 O.OOE+00 O.OOE+00 O.OOE+O0 0.OOE+00 0.OOE+00 CR-51 0.00E+00 O.OOE+O0 O.OOE+00 O.JOE+OO 0.OOE+00 0.OOE+00 O.OOE+00 ......................

MN-54 0.OOE+00 O.OOE+O0 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+O0 0.OOE+O0 FE-55 0.OOE+00 0.OOE+O0 0.OOE+00 O.OOE+00 FE-59 0.OOE+00 O.OOE+QO o.OOE+a0 O.OOE+O0 o.OOE+O0 0.OOE+OO O.OOE+00 0.OOE+00 CO-58 O.OOE+OO O.OOE+00 O.OOE+OO O.OOE+O0 0.O0E+00 000OE+00 CO-60 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 NI-63 0.OOE+00 O.OOE+O0 0.OOE+00 O.OOE+OO O.OOE+00 0.OOE+0O O.OOE+00 O.OOE+00 0.OOE+00 ZN-65 0.OOE+O0 O.OOE-'00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 RB-86 0.OOE+00 0.OOE+00 o .OOE+O0- -- OQ---O- 0.OOE+00 O.OOE+O0 O.OOE+00 SR-89 0.OOE+0O 0.OOE+00 O.OOE+00 O.OOE+00 0.00 E+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 SR-90 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+OO 0.OOE+O0 0.OOE+00 O.OOE+00 Y-91 0.OOE+00 0.OOE-'00 0.OOE+00 0.00E+00 0.00E+00 ZR-95 0.OOE+00 0.OOE+O0 0.OOE+00 O... . . . . . . .... . . . . . .

NB-95 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 RU-103 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 RU-106 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 AG-110M 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 TE-125M 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 TE-127M 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 TE-129M 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-131 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-133 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CS-1 34 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 CS-1 36 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CS-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BA-140 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CE-141 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CE-144 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 PR-143 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 ND-147 .00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

CY-TM-1 70-300 Revision 2 Page 162 of 209 TABLE 5.7.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: VEGETATION NUCLIDEORGAN DOSE FACTORS; mrem/year per pCi/sec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 C-14 8.89E+08 1.78E+08 1.78E+08 1.78E+OB 1.78E+08 1.78E+08 1.78E+08 CR-51 O.OOE+00 O.OOE+00 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 MN-54 O.OOE+00 6.65E+08 1.77E+08 O.OOE+00 1.86E+08 O.OOE+00 5.58E+08 FE-55 8.01E+08 4.25E+08 1.32E+08 O.OOE+00 O.OOE+00 2.40E+08 7.87E+07 FE-59 3.98E+08 6.44E+08 3.21E+08 O.OOE+00 O.OOE+00 1.87E+08 6.71E+08 CO-58 O.OOE+00 6.44E+07 1.97E+08 O.OOE+00 O.OOE+00 O.OOE+00 3.76E+08 CO-60 0.OOE+00 3.78E+08 1.12E+09 0.OOE+00 O.OOE+00 O.OOE+00 2.10E+09 NI-63 3.95E+10 2.11E+09 1.34E+09 0.OOE+00 0.O0E+00 0.OOE+00 1.42E+08 ZN-65 8.12E+08 2.16E+09 1.35E+09 0.OOE+00 1.36E+09 0.OOE+00 3.80E+08 RB-86 0.OOE+00 4.51E+08 2.77E+08 0.OOE+00 O.OOE+00 O.OOE+00 2.90E+07 SR-89 3.60E+10 O.OOE+00 1.03E+09 O.OOE+00 O.OOE+00 O.OOE+00 1.39E+09 SR-90 1.24E+12 O.OOE+00 3.15E+11 0.OOE+00 0.OOE+O0 0.OOE+00 1.67E+10 Y-91 1.87E+07 0.OOE+00 4.99E+05 0.O0E+00 0.OOE-'-O O.OOE+00 2.49E+09 ZR-95 3.86E+06 8.48E+05 7.55E+05 O.OOE+00 1.2 1E+06 0.OOE+00 8.85E+08 NB-95 4.11E+05 1.60E+05 1.14E+05 0.OOE+00 1.50E+05 0.OOE+00 2.96E+08 RU-103 1.53E+07 O.OOE+00 5.90E+06 0.OOE+00 3.86E+07 O.OOE+00 3.97E+08 RU-106 7.45E+08 O.OOE+00 9.30E+07 O.0OE+00 1.01E+09 0.OOE+00 1.16E+10 AG-110M 3.21E+07 2.17E+07 1.73E+07 0.OOE+00 4.04E+07 0.0OE+00 2.58E+09 TE-125M 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.OOE+00 0.OOE+00 3.38E+08 TE-127M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 O.OOE+00 1.07E+09 TE-129M 8.40E+08 2.35E+08 1.30E+08 2.71E+08 2.47E+09 O.OOE+00 1.02E+09 1-131 1.43E+08 1.44E+08 8.18E+07 4.76E+10 2.36E+08 0.OOE+00 1.28E+07 1-133 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 0.OOE+00 1.76E+06 CS-1 34 1.60E+10 2.63Ei-10 5.55E+09 0.OOE+00 8.15E+09 2.93E+09 1.42E+08 CS-1 36 8.28E+07 2.28E+08 1.47E+08 0.OOE+O0 1.21E+08 1.81 E+07 8.OOE+06 CS-1 37 2.39E+10 2.29E+10 3.38E+09 0.OOE+O0 7.46E+09 2.68E+09 1.43E+08 BA-140 2.79E+08 2.44E+05 1.63E+07 O.OOE+00 7.96E+04 1.46E+05 1.41E+08 CE-141 6.57E+05 3.28E+05 4.86E+04 0.OOE+00 1.44E+05 0.OOE+00 4.09E+08 CE-144 1.27E+08 3.99E+07 6.79E+06 0.OOE+00 2.21E+07 0.OOE+00 1.04E+10 PR-143 1.45E+05 4.36E+04 7.21E+03 0.OOE+00 2.36E+04 0.OOE+00 1.57E+08 ND-147 7.15E+04 5.79E+04 4.49E+03 0.OOE+00 3.18E+04 O.OOE+00 9.18E+07

CY-TM-170-300 Revision 2 Page 163 of 209 TABLE 5.7.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: VEGETATION NUCLIDE - ORGAN DOSE FACTORS; m- - mrem/year per piCi/sec NUCLI BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 C-14 3.69E+08 7.38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 CR-51 0.OOE+00 O.OOE+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 0.OOE+00-MN-54 0.OOE+00 4.54E+08 9.01 E+07 1.36E+08 0.OOE+00 9.32E+08 FE-55 3.26E+08 2.31 E+08 5.39E+07 0.OOE+00 0.00E+00 1.47E+08 1.00E+08 FE-59 1.80E+08 4.19E+08 1.62E+08 0.OOE+00 0.00E+00 1.32E+08 9.91E+08 0.OOE+00 CO-58 0.OOE+00 4.36E+07 1.01 E+08 --.- OE+-- 0.OOE+00 0.00E+00 6.01E+08 CO-60 0.OOE+00 2.49E+08 5.60E+08 0.OOE+00 0.00E+00 0.00E+00 3.24E+09 NI-63 1.61E+10 1.13E+09 5.45E+08 0.OOE+00 0.OOE+00 1.81E+08 0.OOE+00 ZN-65 4.24E+08 1.47E+09 6.86E+08 0.00E+00 9.42E+08 0.00E+00 6.23E+08 RB-86 0.OOE+00 2.73E+08 1.28E+08 0.OOE+00 0.00E+00 0.00E+00 4.04E+07 SR-89 1.52E+10 0.OOE+00 4.34E+08 0.00E+00 0.OOE+00 1.80E+09 SR-90 7.51 E+11 0.OOE+00 1.85E+11 0.OOE+00 0.OOE+00 O.OOE+00 2.11E+10 Y-91 7.84E+06 0.OOE+00 2.10E+05 0.00E+00 0.00E+00 0.OOE+00 3.22E+09 ZR-95 1.72E+06 5.43E4-05 3.73E+05 0.00E+00 7.98E+05 0.OOE+00 1.25E+09 NB-95 1.92E+05 1.07E+05 5.87E+04 0.OOE+00 1.03E+05 0.OOE+00 4.56E+08 RU-103 6,82E+06 0.OOE+00 2.92E+06 0.OOE+00 2.41E+07 0.00E+00- 5.70E+08 RU-1 06 3.09E+08 0.OOE+00 3.90E+07 0.OOE+00 5.97E+08 0.00E+00 1.48E+10 AG-110M 1.52E+07 1.43E+07 8.72E+06 0.OOE+00 2.74E+07 0.OOE+00 4.03E+09 TE-125M 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0.OOE+00 4.37E+08 TE-127M 5.52E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 0.OOE+00 1.37E+09 5.72E+07 TE-129M 3.61E+08 1.34E+'08 5.78E+07 1.17E+08 1.51E+09 0.OOE+00 1.36E+09 1-131 7.69E+07 1.08E+08 3.14E+10 1.85E+08 0.OOE+00 2.13E+07 1-133 1.94E+06 3.29E+06 1.OOE+06 4.59E+08 5.77E+06 0.OOE+00 2.49E+06 CS-134 7.10E+09 1.67E+10 7.75E+09 0.OOE+00 5.31E+09 2.03E+09 2.08E+08 CS-136 4.39E+07 1.73E+08 1.16E+08 0.00E+00 9.41E+07 1.48E+07 1.39E+07 CS-137 1.01E+10 1.35E+10 4.69E+09 0.OOE+00 4.59E+09 1.78E+09 1.92E+08 BA-140 1.39E+08 1.71 E+05 8.97E+06 0.OOE+00 5.78E+04 1.15E+05 2.15E+08 CE-141 2.83E+05 1.89E+05 2.17E+04 0.OOE+00 8.90E+04 0.OOE+00 5.41E+08 CE-144 5.28E+07 2.18E+07 2.83E+06 0.OOE+00 1.30E+07 0.OOE+00 1.33E+10 PR-143 6.99E+04 2.79E+04 3.48E+03 0.OOE+00 1.62E+04 0.OOE+00 2.30E+08 ND-147 3.62E+04 3.94E+04 2.36E+03 0.OOE+00 2.31E+04 0.OOE+00 1.42E+08

CY-TM-1 70-300 Revision 2 Page 164 of 209 TABLE 5.7.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: VEGETATION NUCLIDE ORGAN DOSE FACTORS; mi- mrem/year per pCi/sec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 C-14 2.28E+08 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 CR-51 0.OOE+00 0.OOE+00 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 MN-54 0.OOE+00 3.13E+08 5.97E+07 0.00E+00 9.31E+07 0.OOE+00 9.58E+08 FE-55 2.10E+08 1.45E+08 3.38E+07 0.00E+00 0.OOE+00 8.08E+07 8.31E+07 FE-59 1.26E+08 2.97E+08 1.14E+08 0.OOE+00 0.OOE+00 8.29E+07 9.89E+08 CO-58 0.OOE+00 3.07E+07 6.89E+07 0.OOE+00 0.OOE+00 0.OOE+00 6.23E+08 CO-60 O.OOE+00 1.67E+08 3.69E+08 0.OOE+00 O.OOE+00 0.OOE+00 3.14E+09 NI-63 1.04E+10 7.21E+08 3.49E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.50E+08 ZN-65 3.17E+08 1.01E+09 4.56E+08 0.OOE+00 6.75E+08 O.OOE+00 6.36E+08 RB-86 0.OOE+00 2.19E+08 1.02E+08 0.OOE+00 0.OOE+00 0.0OE+00 4.32E+07 SR-89 9.98E+09 0.OOE+00 2.86E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.60E+09 SR-90 6.05E+11 0.OOE+00 1.48E+11 0.OOE+00 0.OOE+00 0.OOE+00 1.75E+10 Y-91 5.12E+06 0.OOE+00 1.37E+05 0.OOE+00 0.OOE+00 0.OOE+00 2.82E+09 ZR-95 1.17E+06 3.77E+05 2.55E+05 0.OOE+00 5.91E+05 0.OOE+00 1.19E+09 NB-95 1.42E+05 7.92E+04 4.26E+04 O.OOE+0O 7.83E+04 0.OOE+00 4.81E+08 RU-103 4.77E+06 0.OOE+00 2.06E+06 0.OOE+00 1.82E+07 0.OOE+00 5.57E+08 RU-106 1.93E+08 0.OOE+00 2.44E+07 0.OOE+0O 3.72E+08 0.OOE+00 1.25E+10 AG-110M 1.05E+07 9.75E+06 5.79E+06 0.OOE+00 1.92E+07 0.OOE+00 3.98E+09 TE-125M 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 O.OOE+00 3.86E+08 TE-127M 3.49E+08 1.25E+08 4.26E+07 8.93E+07 1.42E+09 0.OOE+00 1.17E+09 TE-129M 2.51 E+08 9.37E+07 3.97E+07 8.63E+07 1.05E+09 0.OOE+00 1.26E+09 1-131 8.08E+07 1.16E+08 6.62E+07 3.79E+1 0 1.98E+08 0.OOE+00 3.05E+07 1-133 2.09E+06 3.63E+06 1.11E+06 5.34E+08 6.33E+06 0.OOE+00 3.26E+06 CS-I 34 4.67E+09 1.11E+10 9.08E+09 0.OOE+00 3.59E+09 1.19E+09 1.94E+08 CS-136 4.28E+07 1.69E+08 1.22E+08 0.OOE+O0 9.41E+07 1.29E+07 1.92E+07 CS-1 37 6.36E+09 8.70E+09 5.70E+09 0.OOE+00 2.95E+09 9.81 E+08 1.68E+08 BA-140 1.29E+08 1.62E+05 8.47E+06 0.OOE+00 5.52E+04 9.29E+04 2.66E+08 CE-141 1.97E+05 1.33E+05 1.51E+04 0.OOE+00 6.20E+04 0.OOE+00 5.10E+08 CE-144 3.29E+07 1.38E+07 1.77E+06 0.OOE+00 8.16E+06 0.OOE+00 1.11E+10 PR-143 6.25E+04 2.51E+04 3.10E+03 0.00E+00 1.45E+04 0.OOE+00 2.74E+08 ND-147 3.34E+04 3.85E+04 2.31E+03 0.OOE+00 2.25E+04 O.OOE+00 1.85E+08

CY-TM-170-300 Revision 2 Page 165 of 209 6.0 TMI-1 GASEOUS WASTE TREATMENT SYSTEM 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System (see Fiqure 6.1) 6.1.1 Waste Gas System

a. Reactor Building:

- Reactor Coolant Drain Tank (RCDT) header

b. Auxiliary Building:

- Vent Header from

1. Miscellaneous Waste Storage Tank (MWST)

2. Three (3) Reactor Coolant Bleed Tanks (RCBT)

- Waste Gas Delay Tank

- Two (2) Waste Gas Compressors

-Three (3) Waste Gas Decay Tanks (WGDT)

c. Filtration and dilution provided by the Station Ventilation System.

6.2 Operability Operability of the Gaseous Waste Treatment System is defined as the ability to remove gas from the vent header/tank gas spaces and store it under a higher pressure in the Waste Gas Decay Tanks for subsequent release.

Except for initiating the make up tank sample and waste gas venting and the recycle or disposal of compressed waste gases stored in the waste gas decay tanks, the operation of the waste gas system is entirely automatic. One waste gas compressor comes on automatically, removing gases from the vent header system as required, to maintain the pressure in the system at a maximum of about 16.4 psia.

CY-TM-170-300 Revision 2 Page 166 of 209 FIGURE 6.1 Waste Gas System peainuMI sages Ad $wT

-0

CY-TM-1 70-300 Revision 2 Page 167 of 209 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 7.1 Total Dose Calculation The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem.

This control is provided in order to meet the dose limitations of 40 CFR 190.

The total dose from TMI-1 and TMI-2 (uranium fuel cycle facilities within 8 kilometers) is calculated by summing the calculated annual doses to critical organs of a real individual for liquid effluent using Section 2.1 methodology, for gaseous effluent using Section 5.2.1 and 5.2.2 methodology, and the direct radiation from the site from the environmental monitoring program's direct radiation (TLD) monitors.

CY-TM-170-300 Revision 2 Page 168 of 209 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitoring Pro-gram Requirements 8.1.1 Controls In accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech.

Specs., the radiological environmental monitoring program shall be conducted as specified in Table 8.1.

8.1.2 Applicability At all times.

8.1.3 Action

a. With the radiological environmental monitoring program not being conducted as specified in Table 8.1, prepare and submit to the Commission in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 8.2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a special report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part II Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3. When more than one of the radionuclides in Table 8.2 are detected as the result of plant effluents in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + > 1.0 reportinglevel (1) reporting level (2) -

When radionuclides other than those in Table 8.2 are detected and are the result of plant effluents, this report shall be The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.

CY-TM-170-300 Revision 2 Page 169 of 209 submitted if the potential annual dose* to a member of the public is equal to or greater than the calendar year limits of ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part II, Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 8.1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to TMI-1 Tech. Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

8.1.4 Bases The radiological monitoring program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of members of the general public resulting from the station operation. This monitoring program implementsSection IV B.2 of Appendix I to 10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

Guidance for this monitoring is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring (Revision 1, November 1979). Program changes may be initiated based on operational experience.

8.1.5 Surveillance Requirements The radiological environmental monitoring samples shall be collected pursuant to Table 8.1, from the specific locations given in Tables 8.4 through 8.10 and Maps 8.1 through 8.3, and shall be analyzed pursuant

CY-TM-1 70-300 Revision 2 Page 170 of 209 to the requirements of Table 8.1 and the detection capabilities required by Table 8.3.

CY-TM-170-300 Revision 2 Page 171 of 209 8.2 Land Use Census 8.2.1 Controls In accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech.

Specs., a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden* of greater than 50 m 2 (500 ft2 ) producing broad leaf vegetation.

8.2.2 Applicability At all times.

8.2.3 Action

a. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in ODCM Part I Surveillance 3.2.2.3.1, pursuant to ODCM, Part IV, Section 2.0, identify the new location(s) in the next Annual Radioactive Effluent Release Report.

b. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Table 8.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to TMI-1 Tech.

Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different sectors with the highest predicted D/Qs in lieu of the garden census.

Requirements for broad leaf sampling in Table 8.1 shall be followed, including analysis of control samples.

CY-TM-1 70-300 Revision 2 Page 172 of 209 8.2.4 Bases This Control is provided to ensure that changes in the use of unrestricted areas are identified and modifications to the monitoring program are made if required by the results of this census. The best information from the door-to-door survey, aerial surveys, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR 50. Restricting the census to gardens of greater than 500 square feet (50 M2) provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr)of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.

8.2.5 Surveillance Requirements The Land Use Census shall be conducted during the growing season at least once per 12 months, using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Part IV, Section 1.0.

CY-TM-170-300 Revision 2 Page 173 of 209 8.3 Interlaboratory Comparison Program 8.3.1 Controls In accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech.

Specs., analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission (NRC). Only those samples and analyses which are required by Table 8.1 shall be performed.

8.3.2 Applicability At all times.

8.3.3 Action With analysis not being performed as required above, report the corrective action taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

8.3.4 Bases The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purpose of Section IV, B.2 of Appendix I to 10 CFR 50.

8.3.5 Surveillance Requirements A summary of the Interlaboratory Comparison Program results shall be included in the Annual Radiological Environmental Operating Report.

CY-TM-1 70-300 Revision 2 Page 174 of 209 TABLE 8.1 Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample [ Sample Locationsa Collection Frequencyb of Analysisb

1. Airborne Radioiodine and Samples from 5 locations Continuous sampler operation Radioiodine Canister:

Particulates from Table 8.4. with sample collection weekly, Analyze weekly for 1-131.

or more frequently if required Particulate Filter:

Three of these samples by dust loading. Analyze for gross beta should be close to the Site radioactivity following filter Boundary, in different changed. Perform gamma sectors, of the highest isotopic analysise on calculated annual average composite (by location) ground level D/Q. sample quarterly.

One of the samples should be from the vicinity of a community having the highest calculated annual average ground level D/Q.

And one sample should be from a control location 15 to 30 km distant in a less prevalent wind direction.

CY-TM-1 70-300 Revision 2 Page 175 of 209 TABLE 8.1 (Cont'd)

Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locationsa Collection Frequencyb of Analysisb

2. Direct Radiationc Samples from 40 locations Sample Quarterly Analyze for gamma dose from Table 8.5 (using either quarterly.

2 dosimeters or at least 1 instrument for continuously measuring and recording dose rate at each location).

Placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the site boundary; An outer ring of stations, one in each meteorological sector in the 6 to 8 km from the site; and the balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in at least one or two areas to serve as control stations.

CY-TM-1 70-300 Revision 2 Page 176 of 209 TABLE 8.1 (Cont'd)

Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locationsa Collection Frequencyb of Analysis b

3. Waterborne

a. Surfacef Samples from 2 locations Compositeg sample over Perform gamma isotopic from Table 8.6. 1 monthly period. analysise monthly.

Composite for tritium

• 1 sample from analysis quarterly.

downstream (indicator) location

• 1 sample from upstream (control) location (or location not influenced by the station discharge)

b. Drinking Samples from 2 locations Composite' sample over Perform gross beta and from Table 8.6. 1 monthly period, gamma isotopic analysise monthly. Perform Sr-90 1 sample at the location analysis if gross beta of of the nearest water monthly composite >10 supply that could be times control. Composite for affected by the station tritium analysis quarterly.

discharge.

• 1 sample from a control location.

c. Sediment from Samples from 2 locations Sample twice per year Perform gamma isotopic Shoreline (1 Control and 1 Indicator) (Spring and Fall) analysise on each sample.

1from Table 8.7. 1 1

CY-TM-170-300 Revision 2 Page 177 of 209 TABLE 8.1 (Cont'd)

Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locationsa Collection Frequencyb of Analysisb

4. Ingestion

a. Milk Samples from 4 locations from Sample semimonthly when Perform gamma isotopic Table 8.8. animals are on pasture; analysise and 1-131 monthly at other times. analysis on each sample.

Samples should be from Composite for Sr-90 milking animals in three analysis quarterly.

locations within 5 km distance having the highest dose potential. If there are none, then one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per year.

One sample from milking animals at a control location 15 to 30 km distant in a less prevalent wind direction.

b. Fish Samples from 2 locations from Sample twice per year Perform gamma isotopice Table 8.9. (Spring and Fall). and Sr-90 analysis on edible portions.

• 1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators in the vicinity of the station discharge.

• 1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators from an area not influenced by the station discharge.

____________________ ____________________________ J __________________________ J _________________________

CY-TM-1 70-300 Revision 2 Page 178 of 209 TABLE 8.1 (Cont'd)

Sample Collection and Analysis Requirements Exposure Pathway and/or Sample Number of Samples and

_§amle L~cationsa f Sampling and Collection Frequencyb Type and Frequency of Analysisb

4. Ingestion (contd)

c. Food Samples from 2 locations Sample at time of harvest. Perform gamma Products from Table 8.10 (when isotopice, and 1-131, available) analysis on edible portions. Sr-90 analysis 1 sample of each principle on green leafy class of food products at a vegetables or vegetation location in the immediate only.

vicinity of the station.

(indicator)

• 1 sample of same species or group from a location not influenced by the

.station discharge.

Samples of three different Monthly during growing Perform gamma kinds of broad leaf vegetation season isotopice 1-131 analysis.

grown nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milking sampling is not performed.

One sample of each of the similar broad leaf vegetation grown 15 to 30 km distant in a less prevalent wind direction if milk sampling is not performed.

CY-TM-1 70-300 Revision 2 Page 179 of 209 TABLE 8.1 Sample Collection and Analysis Requirements Table Notation

a. Sampling locations are provided in Tables 8.4 through 8.10. They are depicted in Maps 8.1 through 8.3. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. All deviations from the sampling schedule shall be explained in the Annual Radiological Environmental Operating Report.

b. Frequency notation: weekly (7 days), semimonthly (15 days), monthly (31 days), and quarterly (92 days). All surveillance requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. A total maximum combined interval time for any 4 consecutive tests shall not exceed 3.25 times the specified collection or analysis interval.

c. One or more instruments, such as a pressurized ion chamber for measuring and recording dose rate continuously, may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

d. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in an air particulate sample(s) is greater than ten times the calendar year mean of control samples, Sr-90 and gamma isotopic analysis shall be performed on the individual sample(s).

e. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

f. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream sample" shall be taken in an area beyond but near the mixing zone.

g. Composite sample aliquots shall be collected at time intervals that are short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

CY-TM-170-300 Revision 2 Page 180 of 209 TABLE 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne Particulate Water or gas Fish Milk Food Products Analysis (pCi/L) (pCi/m 3) (pCi/kg,wet) (pCi/L) (pCi/kg, wet)

H-3 20,000(a)

Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Sr-90 8 0.1 100 8 100 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1000 60 1000 Cs-1 37 50 20 2000 70 2000 Ba-La-140 200 300 (al For drinking water samples. This is 40 CFR Part 141 value.

CY-TM-1 70-300 Revision 2 Page 181 of 209 TABLE 8.3 Detection Capabilities for Environmental Sample Analysisa Lower Limit of Detection (LLD)b'c Airborne Particulate Fish Food Sediment Water or Gas (pCi/kg, Milk Products (pCi/kg, Analysis (pCi/L) (pCi/m 3) wet) (pCi/L) (pCi/lkg,wet) dry)

Gross Beta 4 0.01 H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Sr-90 2 0.01 10 2 10 Nb-95 15 1-131 1d 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15

CY-TM-1 70-300 Revision 2 Page 182 of 209 TABLE 8.3 Detection Capabilities for Environmental Sample Analysisa Table Notation

a. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, which may be related to plant operations, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

b. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13 (Rev. 1).

c. The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD = 4.66 Sb E* V 2.22 o Y

• exp (-kAt)

Where:

LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume.

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

is the radioactive decay constant for the particular radionuclide and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting.

Typical values of E, V, Y and At should be used in the calculation.

CY-TM-1 70-300 Revision 2 Page 183 of 209 TABLE 8.3 (Cont'd)

Detection Capabilities for Environmental Sample Analysisa Table Notation It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small samples sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

d. LLD for drinking water.

CY-TM-1 70-300 Revision 2 Page 184 of 209 TABLE 8.4 TMINS REMP Station Locations-Air Particulate and Air Iodine Station Code Distance (miles) Azimuth (0) Map No.

E1-2 0.4 97 8.1 F1-3 0.6 112 8.1 G2-1 1.4 126 8.2 M2-1 1.3 256 8.2 A3-1 2.7 357 8.2 H3-1 2.2 160 8.2 Q15-1 13.4 309 8.3 TABLE 8.5 TMINS REMP Station Locations-Direct Radiation (TLD)

Station Code Distance (miles) Azimuth (0) Map No.

A1-4 0.3 6 8.1 B1-1 0.6 25 8.1 B1-2 0.4 23 8.1 C1-2 0.3 50 8.1 D1-1 0.2 76 8.1 E1-2 0.4 97 8.1 E1-4 0.2 97 8.1 F1-2 0.2 112 8.1 G1-3 0.2 130 8.1 H1-1 0.5 167 8.1 J 1-1 0.8 176 8.1 J1-3 0.3 189 8.1 K1-4 0.2 209 8.1 Li-1 0.1 236 8.1 M1-1 0.1 250 8.1 NI-3 0.1 274 8.1 P1-1 0.4 303 8.1 P1-2 0.1 292 8.1

CY-TM-1 70-300 Revision 2 Page 185 of 209 TABLE 8.5 (Cont'd)

TMINS REMP Station Locations-Direct Radiation (TLD)

Station Code Distance (miles) Azimuth (0) Map No.

Q1-2 0.2 321 8.1 0.2 335 8.1 C2-1 1.5 44 8.2 K2-1 1.2 200 8.2 M2-1 1.3 256 8.2 A3-1 2.7 357 8.2 H3-1 2.2 160 8.2 R3-1 2.6 341 8.2 A5-1 4.4 3 8.2 B5-1 4.9 19 8.2 C5-1 4.7 43 8.2 E5-1 4.7 82 8.2 F5-1 4.7 109 8.2 G5-1 4.8 131 8.2 H5-1 4.1 158 8.2 J5-1 4.9 181 8.2 K5-1 4.9 202 8.2 15-1 4.1 228 8.2 M5-1 4.3 249 8.2 N5-1 5.0 268 8.2 P5-1 5.0 284 8.2 Q5-1 5.0 317 8.2 R5-1 4.9 339 8.2 D6-1 5.2 66 8.3 E7-1 6.7 88 8.3 Q9-1 8.5 310 8.3 B10-1 9.2 21 8.3 G10-1 9.7 128 8.3 G15-1 14.4 126 8.3 J15-1 12.6 183 8.3 Q15-1 13.4 309 8.3

CY-TM-1 70-300 Revision 2 Page 186 of 209 TABLE 8.6 TMINS REMP Station Locations-Surface Water Station Code Distance (miles) Azimuth (°) Map No.

J1-2 (SW) .0.5 188 8.1 A3-2 (SW) 2.7 356 8.2 Q9-1 (DW) 8.5 310 8.3 Q9-1 (SW) 8.5 310 8.3 G15-2 (DW) 13.3 129 8.3 G15-3 (DW) 15.7 124 8.3 (SW) = Surface Water (DW) = Drinking Water TABLE 8.7 TMINS REMP Station Locations-Aquatic Sediment Station Code Distance (miles) Azimuth (°) Map No.

A1-3 0.5 359 8.1 K1-3 0.2 212 8.1 J2-1 1.4 179 8.2

CY-TM-170-300 Revision 2 Page 187 of 209 TABLE 8.8 TMINS REMP Station Locations-Milk Station Code Distance (miles) Azimuth (0) Map No.

E2-2 1.1 96 8.2 F4-1 3.2 104 8.2 G2-1 *1.4 126 8.2 P4-1 3.7 295 8.2 K15-3 14.4 205 8.3 TABLE 8.9 TMINS REMP Station Locations-Fish Station Code Station Location IND Downstream of Station Discharge BKG Upstream of Station Discharge TABLE 8.10 TMINS REMP Station Locations-Food Products Station Code Distance (miles) Azimuth (0) Map No.

E1-2 0.4 97 8.1 H11-2 1.0 151 8.1 B10-2 10.0 31 8.3

CY-TM-170-300 Revision 2 Page 188 of 209 MAP 8.1 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 1 MILE OF THE SITE MAP 8.1 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Within 1 Mile of the Site

CY-TM-170-300 Revision 2 Page 189 of 209 MAP 8.2 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 5 MILES OF THE SITE MAP 8.2 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Within 5 Miles of the Site

CY-TM-1 70-300 Revision 2 Page 190 of 209 MAP 8.3 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS GREATER THAN 5 MILES FROM THE SITE MAP 8.3 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Greater Than 5 Miles from the Site

CY-TM-170-300 Revision 2 Page 191 of 209 9.0 PART III REFERENCES

1. EPRI NP-3840, RP 1560-3 Final Report, "Environmental Radiation Doses From Difficult-To-Measure Nuclides," January 1985

2. "Evaluation of the Three Mile Island Nuclear Station Unit 1 to Demonstrate Conformance to the Design Objectives of 10 CFR 50, Appendix I," Nuclear Safety Associates, May 1976

3. TMI-1 Final Safety Analysis Report (FSAR)

4. TMI-2 Final Safety Analysis Report (FSAR)

5. Meteorological Information and Dose Assessment System (MIDAS)

6. NUREG-0017, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWR," Revision 1, 1985

7. NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978

8. NUREG-0172, "Age-Specific Radiation Dose Commitment Factors For A One-Year Chronic Intake," November 1977

9. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," Revision 1, June 1974

10. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October 1977

11. Simplified Environmental Effluent Dosimetry System (SEEDS)

12. TMI Recirculation Factor Memos, April 12, 1988 and March 17, 1988

13. TMI-1 Operations Procedure, 1101-2.1, "Radiation Monitor Set Points"

14. Title 10, Code of Federal Regulations, "Energy"

15. TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50

16. Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977

17. TMI-2 PDMS Technical Specifications, attached to Facility License No. DPR-73

CY-TM-1 70-300 Revision 2 Page 192 of 209

18. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979

19. Title 40, Code of Federal Regulations, "Protection of Environment"

20. Regulatory Guide 4.13, "Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications," Revision 1, July 1977

21. Post-Defueling Monitored Storage Safety Analysis Report (PDMS SAR)

CY-TM-170-300 Revision 2 Page 193 of 209 PART IV REPORTING REQUIREMENTS

CY-TM-1 70-300 Revision 2 Page 194 of 209 PART IV Reporting Requirements 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.

1.1 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted to the Commission prior to May 1 of each year.

1.2 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring activities for the report period, including a comparison with pre-operational studies, with operational controls as appropriate, and with previous environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of Land Use Censuses required by Part Ill, Section 8.2.

1.3 The Annual Radiological Environmental Operating Reports shall include the summarized tabulated results of analysis of all radiological environmental samples and environmental radiation measurements required by Part III Table 8.1 taken during the period pursuant to the locations specified in the tables and figures in this ODCM, as well as summarized and tabulated results of these analyses and measurements in a format similar to the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

1.4 The reports shall also include the following: A summary description of the radiological environments monitoring program; a map(s) of all sampling locations keyed to a table giving distances and directions from a point that is midway between the Reactor Buildings of TMI-1 and TMI-2; the results of licensee participation in the Interlaboratory Comparison Program, required by Part III, Section 8.3; discussion of all deviations from the sampling schedule of Part III, Table 8.1; discussion of all the required analyses in which the LLD required by Part III, Table 8.3 was not achievable.

A single submittal may be made for the station.

CY-TM-1 70-300 Revision 2 Page 195 of 209 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NOTE: A single submittal may be made for the station. The submittal should combine those sections that are common to both units at the station however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit.

2.1 Routine Radioactive Effluent Release Reports covering the operations of the unit during the previous 12 months of operation shall be submitted prior to May 1 for TMI-1 and TMI-2.

2.2 The following information shall be included in both Radioactive Effluent Release Reports to be submitted each year:

The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Reg. Guide 1.21, Rev. 1, with data summarized on a quarterly basis following the format of Appendix B thereof.

2.3 The Radioactive Effluent Release Reports shall include the following information for each type of solid waste shipped offsite during the report period:

a. Container volume

b. Total curie quantity (specify whether determined by measurement or estimate)

c. Principal radionuclides (specify whether determined by measurement or estimate)

D. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms)

e. Type of shipment (e.g., Isa, type a, type b) and

f. Solidification agent (e.g., cement) 2.4 The Radioactive Effluent Release Reports shall include a summary of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.

2.5 The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part III Section 8.2.

CY-TM-1 70-300 Revision 2 Page 196 of 209 2.6 The Radioactive Effluent Release Reports shall include the instrumentation not returned to OPERABLE status within 30 days per ODCM Part I Controls 2.1:1 b and 2.1.2b, and ODCM Part II Control 2.1.2b.

2.7 The Radioactive Effluent Release Report to be submitted shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmosphere stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability.

2.8 The Radioactive Effluent Release Report shall include an assessment of the radiation doses to MEMBERS OF THE PUBLIC due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses.

The assessment of radiation doses shall be performed in accordance with this ODCM.

2.9 The Radioactive Effluent Release Report shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period, to verify compliance with the limits of 10CFR20.1301(a)(1). All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports.

2.10 The Radioactive Effluent Release Report shall also include an assessment of 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 the previous 12 consecutive months, to show conformance with 40 CFR 190 "Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contributions from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.

CY-TM-1 70-300 Revision 2 Page 197 of 209 3.0 PART IV REFERENCES 3.1 Radiological Assessment Branch Technical Position, Revision 1, November 1979 3.2 Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974 3.3 TMI-1 Technical Specifications, attached to Facility Operating License No.

DPR-50 3.4 Title 40, Code of Federal Regulations, "Protection of Environment" 3.5 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 3.6 Title 10, Code of Federal Regulations, "Energy" 3.7 Regulatory Guide 1.111, "Methods of Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977 3.8 Regulatory Guide 1.112, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors,"

Revision O-R, April 1976 3.9 Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," Revision 1, April 1977

CY-TM-170-300 Revision 2 Page 198 of 209 APPENDIX A Page 1 of 1 Pi - Pathway Dose Rate Parameter P, (inhalation) = k' (BR) DFA, (Eq A-I)

Where:

P, = the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the inhalation pathway, in mrem/yr per microcurie/m 3 . The dose factors are based on the critical individual organ for the child age group.

k' = conversion factor, 1E6 pCi/microcurie BR = 3700 m3/yr, breathing rate for child (Reg. Guide 1.109, Rev. 1, Table E-5)

DFA, = the maximum organ inhalation dose factor for the infant age group for the ith adionuclide (mRem/pCi). Values are taken from Table E-10, Reg. Guide 1.109 (Rev. 1), or NUREG-0172.

Resolution of the units yields: (ODCM Part III Table 4.6)

P, (inhalation) = 3.7E9 DFAJ (mrem/yr per pCi/m 3) (Eq A-2)

NOTE: The latest NRC Guidance has deleted the requirement to determine Pi (ground plane) and Pi (food). In addition, the critical age group has been changed from infant to child.

CY-TM-1 70-300 Revision 2 Page 199 of 209 APPENDIX B Page 1 of 1 Ri - Inhalation Pathway Dose Factor Ri k' (BR) (DFA-,a,a) (mrem/yr per microcurie/m3) (Eq B-i)

Where:

k' = conversion factor, 1E6 pCi/microcurie BR = breathing rate, 1400, 3700, 8000, 8000 m3/yr for infant, child, teenager, and adult age groups, respectively. (Reg. Guide 1.109, Rev. 1, Table E-5)

DFAi,a,o = the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclide, in mrem/pCi. The total body is considered as an organ in the selection of DFAi~a.o. Values are taken from Tables E-7 through E-10, Reg. Guide 1.109 (Rev. 1), or NUREG 0172.

Resolutions of the units yields:

Ri = (1.4E9) (DFAi,a,o) infant (ODCM Part III Table 5.2.1)

Ri = (3.7E9) (DFAia,o) child (ODCM Part III Table 5.2.2)

Ri = (8.0E9) (DFAi,a,o) teen and adult (ODCM Part IlII Tables 5.2.3 and 5.2.4)

CY-TM-170-300 Revision 2 Page 200 of 209 APPENDIX C Page 1 of 1 Ri - Ground Plane Pathway Dose Factor R, = k' k" (SF) (DFG1 ) [(1-e "it)lix] (Eq C-1)

Where:

k' = conversion factor, 1E6 pCi/microcurie k" = conversion factor, 8760 hr/yr

= decay constant for the

=i ith radionuclide, sec t = the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 108 sec. (15 yrs), Reg. Guide 1.109 (Rev. 1),

Appendix C DFGj = the ground plane dose conversion factor for the ith radionuclide (mrem/hr per pCi/m 2). Values are taken from Table E-6, Reg. Guide 1.109 (Rev. 1), or NUREG 0172. These values apply to all age groups.

SF = 0.7, shielding factor, from Table E-15 Reg. Guide 1.109 (Rev. 1)

Reference ODCM Part III Table 5.3.1

CY-TM-170-300 Revision 2 Page 201 of 209 APPENDIX D Page I of 2 Ri - Grass Cow-Milk Pathway Dose Factor Ri= k' [(QF X UAp) I (Xi + Xw)] X (Fm) x (r) x (DFLi,a,o) x

[((fp x fs)/Yp) + ((I-fp x f.) e "1ith)/Ys] e&itf (Eq D-1)

Where:

k' = conversion factor, I E6 picocurie/microcurie (pCi/Vtci)

OF = cow consumption rate, 50 kg/day, (Reg. Guide 1.109, Rev. 1) goat consumption rate, 6 kg/day, (Reg. Guide 1.109, Rev. 1, Table E-2)

UAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for infant, child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev. 1) 2 Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kg/m (NUREG-0133)

Y, = agricultural productivity by unit area of stored feed, 2.0 kg/mr2 (NUREG-0133)

Fm = stable element transfer coefficient (Table E-1, Reg. Guide 1.109, Rev. 1) r = fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E-15, Reg. Guide 1.109, Rev. 1)

DFLi,a,o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1), or NUREG 0172.

ý.j = decay constant for the ith radionuclide, sec-1

= decay constant for weathering, 5.73 x 10-7 sec1 (NUREG-0133); based on a 14 day half life tf = 1.73 x 10 5 sec, the transport time from pasture to cow to milk to receptor (Table E-15, Reg. Guide 1.109, Rev. 1), or 2 days th = 7.78 x 106 sec, the transport time from pasture to harvest to cow to milk to receptor (Table E-15, Reg. Guide 1.109, Rev. 1), or 90 days f, = 1.0, the fraction of the year that the cow is on pasture fS = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture

CY-TM-1 70-300 Revision 2 Page 202 of 209 APPENDIX D Page 2 of 2 The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, Ri is based on (X/Q):

Rct,a,o = k'k"' Fm QF UApDFLt,a,o (.75 [.5/H]) (Eq D-2)

Where:

k'" = 1E3 grams/kg H = 8 grams/m3 , absolute humidity of the atmosphere

.75 = fraction of the total feed grass mass that is water

.5 = ratio of the specific activity of the feed grass water to the atmospheric water (NUREG-0133)

DFLt,a,o = the ingestion dose factor for tritium and organ, o, for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1), or NUREG 0172.

All other parameters and values are as given above.

NOTE: Goat-milk pathway factor, Ri, will be computed using the cow-milk pathway factor equation. Fm factor for goat-milk will be from Table E-2 Reg. Guide 1.109, Rev. 1.

Reference:

ODCM Part III Tables 5.4.1 to 5.4.4

CY-TM-1 70-300 Revision 2 Page 203 of 209 APPENDIX E Page I of 2 Ri - Cow-Meat Pathway Dose Factor Ri= k' [(QF X UAP) I (Xi + ,w)] X (Ff) x (r) x (DFLi,a,o) x

[((fp x fs)/Yp) + ((I-fpfs) e 'xith)IY5J x e'itf (Eq E-1)

Where:

k' = conversion factor, 1E6 picocurie/microcurie (pCi/gci)

QF = cow consumption rate, 50 kg/day, (Reg. Guide 1.109, Rev. 1)

UAP = Receptor's meat consumption rate; 0, 41, 65, 110 kg/yr for infant, child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev. 1)

Ff = the stable element transfer coefficients, days/kg (Table E-1, Reg. Guide 1.109, Rev. 1) r = fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E-15, Reg. Guide 1.109, Rev. 1)

DFLi,a,o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1), or NUREG 0172.

ki = decay constant for the radionuclide i, sec"1 X, = decay constant for weathering, 5.73 x 10-7 sec-1 (NUREG-0133), based on a 14 day half life tf = 1.73 x 106 sec, the transport time from pasture to receptor (NUREG-01 33) th = 7.78 x 106 sec, the transport time from crop to receptor (NUREG-0133) 2 Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kg/m (NUREG-0133)

Ys = agricultural productivity by unit area of stored feed, 2.0 kg/m 2 (NUREG-0133) fp = 1.0, the fraction of the year that the cow is on pasture f, = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture

CY-TM-170-300 Revision 2 Page 204 of 209 APPENDIX E PAGE 2 OF 2 The concentration of tritium in meat is based on the airborne concentration rather than the deposition. Therefore, R1 is based on (X/Q):

Rt,a,o = k'k"' Ff QF UAp (DFLt,a,o) x 0.75 x (0.5/1H]) (Eq E-2)

Where:

All terms are as defined above and in Appendix D.

Reference:

ODCM Part III, Tables 5.6.1 to 5.6.4

CY-TM-170-300 Revision 2 Page 205 of 209 APPENDIX F PAGE 1 OF I Ri - Vegetation Pathway Dose Factor R= k' x [r/ (Y, (XI + Xw))] x (DFLI, a,o) x [(U'A) fL e'itL + USA fg e'Xith] (Eq F-1)

Where:

k' = 1E6 picocurie/microcurie (pCi/ýci)

ULA = the consumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for infant, child,

-teenager, or adult age groups, respectively (Reg. Guide 1.109, Rev. 1)

UsA = the consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for infant, child, teenager, or adult age groups respectively (Reg. Guide 1.109, Rev. 1) fL = the fraction of the annual intake of fresh leafy vegetation grown locally, = 1.0 (NUREG-0133) fg = the fraction of the stored vegetation grown locally = 0.76 (NUREG-0133) tL = the average time between harvest of leafy vegetation and its consumption, 8.6 x 104 seconds [Table E-15, Reg. Guide 1.109, Rev. 1 (24 hrs)]

th = the average time between harvest of stored leafy vegetation and its consumption, 5.18 x 10 seconds, [Table E-15, Reg. Guide 1.109, Rev. 1 (60 days)]

Yv = the vegetation area density, 2.0 kg/mr2 (Table E-15, Reg. Guide 1.109, Rev. 1)

All other parameters are as previously defined.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, Ri is based on (X/Q)

Rt,a,o = k'k'"[ULA fL + USA fgQ (DFLt,a,o) (.75 [.5/H]) (Eq F-2)

Where:

All terms are as defined above and in Appendix D.

Reference:

ODCM Part III, Tables 5.7.1 to 5.7.4

CY-TM-170-300 Revision 2.

Page 206 of 209 APPENDIX A-F REFERENCES (Page 1 of 4)

Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site-Parameter Value R.G. 1.109 NUREG-0133 , Specific DFAi Each radionuclide E-9 Note 1 BR 3700 m3/yr (child) E-5

• • • For RI (Vegetation)***

r Each element type E-1 Y4 2.0 kg/m2 E-15 1

?,w 5.73 E-7 sec 5.3.1.3 DFLI Each age group and radionuclide E-11 thru E-14 Note 1 UlaL Each age group E-5 fL 1.0 5.3.1.5 tL 8.6 E + 4 seconds E-15 Uas Each age group E-5 fg 0.76 5.3.1.5 t

h 5.18 E + 6 seconds E-15 H 8.0 grams/kg 5.2.1.3

• • • For Ri (Inhalation)***

BR Each age group E-5 DFAI Each age group and nuclide E-7 thru E-10 Note 1

CY-TM-1 70-300 Revision 2 Page 207 of 209 APPENDIX A-F REFERENCES (Page 2 of 4)

Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site-Parameter Value R.G. 1.109 NUREG-0133 Specific For R, (Ground Plane)

SF 0.7 E-15 DFGj Each radionuclide E-6 t 4.73 E + 8 sec 5.3.1.2 For Ri (Grass/AnimallMeat)

QF(Cow) 50 kg/day E-3 QF (Goat) 6 kg/day E-3 Ref. Only Uap Each age group E-5 1

Xw 5.73 E-7 sec 5.3.1.3 Ff (Both) Each element E-1 r Each element type E-15 DFLi Each age group and nuclide E-11 thru E-14 Note 1 fp 1.0 5.3.1.3 Note 2 fr 1.0 5.3.1.3 Note 2 Yp 0.7 kg/m 3 E-1 5 th 7.78 E + 6 sec E-15 Yý 2.0 kg/m2 E-15 tf 1.73 E + 6 sec E-15 H 8.0 grams/kg 5.2.1.3

CY-TM-170-300 Revision. 2 Page 208 of 209 APPENDIX A-F REFERENCES (Page 3 of 4)

Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site-Parameter Value R.G. 1.109 NUREG-0133 Specific

• • • For Ri (Grass/CowIMlik) ***

Qf 50 kg/day E-3 Uap Each age group E-5 X.w 5.73 E-7 sec 1 5.3.1.3 Fm Each element E-1 r Each element type E-1 5 DFL1 Each age group and nuclide E-1 1 thru E-14 Note 1 YP 0.7 kg/M 2 E-15 th 7.78 E + 6 sec E-15 Ys 2.0 kg/mr2 E-15 tf 1.73 E + 5 sec E-15 fp 1.0 5.3.1.3 fs 1.0 5.3.1.3 H 8.0 grams/kg 5.2.1.3

CY-TM-170-300 Revision 2 Page 209 of 209 APPENDIX A-F REFERENCES (Page 4 of 4)

NOTES

1. Inhalation and ingestion dose factors were taken from the indicated source. For each age group, for each nuclide, the organ dose factor used was the highest dose factor for that nuclide and age group in the referenced table.

2. Typically, beef cattle are raised all year on pasture. Annual land surveys have indicated that the small number of goats raised within 5 miles, typically are used for grass control and not food or milk. Nevertheless, the goats can be treated as full meat sources where present, despite the fact that their numbers cannot sustain the meat consumption rates of Table E-5, NUREG-0133.

REFERENCES

1. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.

2. TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50.

3. NUREG-01 33, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978.

2010 Annual Radioactive Effluent Release Report for TMI Process Control Program for Radioactive Wastes, Revision 7 RW-AA-100 (Revision 7 was issued on December 16, 2008)

Procedure Approval Form AD-AA-101 -F-01 Page 1 of 1 Revision 1 Document Number: RW-AA-100 Revision: 7-

Title:

Process Control Program for Radioactive Wastes 5

0 New 0 Cancel 0I Cancel H Revision EC#:__ PCR#: 1=7..- LQ(a PPIStM -

Document Revision 0 Editorial 13 Batch ER#:__ ARM: 0:

E] Supersede corporate document(s) List:

Revision Summary: This revision has been prepared to correct and standardize the use of "shall', "should".

Attach adcd descript. Ifreqd "may', and 'will" in accordance with AD-AA-101-1002, moves records retention requirements to section 5, corrects reference at 4.3.1. Several other format corrections were also made.

Impact on Operating D N/A and Design Margins:

Attach add'i descript, Ifreq'd CONFIRM that na commitments (i.e.. those steps annotated with CM-X) have been changed or deleted unless evaluated via completion of LS-AA-1 10 commitment change/deletion form and INITIAL [Preparer]: RMC Preparer: RM Claes 1010212008 CAN/3214 Print Date Location/Ext Applicable BR 3 Marcia Morris DR 0 Sandy Lvecchl QC C1 Terry Barber Site Contacts BY 0 Norma Jean Gordon LA H9 Lynn Kofold-Durdan CL 0 Robert Campbell Check box and PB H George Th"pe OC 0 Michael Smeloff LG H Linda Knapp provide name TMIH8 Jessica Spagnuolo ZN 0 Other [0 Validation Req'd: H No 0 Yes (attach) Common Training Req'd: H9 No 0 Yes (Validation requirement see AD-AA.10) Print/Signature Site Specific Training Req'd: 11 No 0 Yes Change Management: El HU-AA-1 101 Chan C klist Attached [3 Documer it Traveler [ None Required Level of Use: 0 Level 1-Contln U vze2- Rerence Use 0 Level 3 - Information Use Approval Miguel Azarl 10/030m0 CAN/3200 N W IX Date I ý11-=v*

Approval Site Document(s) to be superseded:

Location: Use additional sheets as necessary. Assure that all pending chs nge are dlep Itoned.

"Tornp. Change Int.erim Change Temp or Interim Change 4: Interi Change expiration:

10CFR50.59 Applicable: I"NoU U Yes Tn mcldng Numbmr. .__________ I 10CFR72.48 Applicable: ENo 01 Yes Other Regulatory Process Apy*lcable: [I No [I Yes Other Regulatory Process Number:

PORC Required; fNo0[]s POAC Number (after PORC Approved):

Environmental Review Required: lVNo0 0 Yes If "Yes" then attach c ompleted EN-AA-1 03 Attachment 1.

E" it svuwcedbNg a documemntOning comltrnaita. notify the Commitnent Tracking Coordnnator per LS.AA. 1 0 so the CTO can be updated as a0ppglpate.

Rvw ( bordinator ._M I Review Req'd I No 0 Yes, list below SiWenr

&CfW wt0oe or 04%

P&*1 iSOWen ofte apwwt Pft1 Date ~ rnu~

Temp Change Authorlzilon Only SRO Print/SigVDate SOR Pdnt/SlgnrDate Impl Date Exp. Date SQR Approval indicates that al required Cross-Disclpllnary reviews have been performed and the reviewers have signed this form. This procedure is technically and fuiattonally accurate for all ft~nal areas. (Refer to AD-AA-102)

SOR Approval:M g Prl1/ig we req ,

FlbslnData DWlineo r Site Authorzt~ion: We it ~

~ ~ Ipil Date Plant Managear PrIASign (when requiref'by gggend~jr) D

50.59 REVIEW COVERSHEET FORM LS-AA-104-1001 Revision 2 Page I of 1 Statinn/Unit(s): , /

Activity/Document Number: 1?&Iu A4 - / *o Revision Number: 7

Title:

()PIorC-qTf C6,ý t& ( & gKprAA,&a 7(> k vAerfvg57 tVAs Te NOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(dX2).

Description of Activity:

(Provide a brief, concise description of what the proposed activity involves.)

vl.' 4 .,* ed,'f-°,,e,' / .&L( .'d,,, -* (Žw.- A* /ok Ije~o,..es, C,.,E., (/eI,.,,.,

{-a,'., Ibtguy-A0qg- /00 c6W Reason for Activity:

(Discuss why the proposed activity is being performed.)

RUV'LW W^ PrE-O4dtGZi 40 a'c~A-4 , r.2A,,

o,.a -TAW AP-,4o_,o ,., - C.. t-4

• N 64-60' f,3.I Effect of Activity:

(Discuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.*

-r-l..,tr-,, e- 0F6A, oot.CPIEI ,.,o÷ Ua5.,' A.- L(,- o .1.,A Summary of Conclusion for the Activity's 50.59 Review:

(Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable, is not required.)

64L° /.-Cs-ts C,.d1.i A. 'T-fc/,

S ',fC, r-. q;'.eo

. 4a, &,,.a Attachments: 507 Attach all 50.59 Review forms completed, as appropriate. I I

• p. .5'O, .

(NOTE: if both a Screening and Evaluation are completed, no Screening No. is required.)

Forms Attached: (Check all that apply.)

S ApplicabIlity Review 50.59 Screening 50.59 Screening No. Rev.

50.59 Evaluation 50.59 Evaluation No. Rev.

LS-AA-104-1001 F1AA Rev 2

50.59 APPLICABILITY REVIEW FORM LS-AA-104-1002 Revision 2 Page 1 of I Activity/Document Number: &' /- e9tA /-0 0 Revision Number: Q7 Address the questions below for all aspects of the Activity. If the answer is yes for any portion of the Activity, apply the identified process(es) to that portion of the Activity. Note that it is not unusual to have more than one process apply to a given Activity.

See Section 4 of the Resource Manual (RM) for additional guidance.

I. Does the proposed Activity involve a change: ..

1. Technical Specifications or Operating License (I OCFRS0.90)? PC NO __ YES See Section 4.2.1.1 of the RM

2. Conditions of License Quality Assurance program (IOCFRS0.54(a))? .KNO _ YES Security Plan (IOCFR50.54(p))? ,.NO __ YES See Section 4.2.1.2 of the RM Emergency Plan (I OCFRS0.54(q))? 6NO YES

3. Codes and Standards IST Program Plan (IOCFR50.55a(f))? A NO YES See Section 4.2.1. of theRM IS] Program Plan (I0CFR50.55a(g))? )(NO _YES

4. ECCS Acceptance Criteria (I0CFR50.46)? XNO _ YES See Section 4.2.1.4 of the RM

5. Specific Exemptions (IOCFR50.12)7 Ž5NO __ YES See Section 4.2.1.5 of the RM

6. Radiation Protection Program (I0CFR20)? -NO XYES See Section 4.2.1.6 ofthe RM

7. Fire Protection Program (applicable UFSAR or operating license $ NO YES See Section 4.2.1.7 of the RM condition)?

S. Programs controlled by the Operating License or the Technical ANO YES See Section 4.2.1.7 of the RM Specifications (such as the ODCM). __NO __ _________ton4.21. __fthR

9. Environmental Protection Program ,NO YES See Section 4.2.1.7 of the RM

10. Other programs controlled by other regulations.

IOCF(61./o0C(71. Lq CP. Ill. /73 NO XYES SeeSection4.2.1oftheRM I1. Does the proposed Activity involve maintenance which restores SSCs to their original condition or involve a temporary alteration supporting X NO YES See Section 4.2.2 of the RM maintenance that will be in effect during at-power operations for 90 days or less?

I1.IDoes the proposed Activity involve a change to the: ......

1. UFSAR (including documents incorporated by reference) that is excluded from the requirement to perform a 50.59 Review by NEI 96-07 )NO __ YES See Section 4.2.3 of the RM or NEI 98-03?

2. Managerial or administrative procedures governing the conduct of facility operations (subject to the control of I OCFR50, Appendix B) - NO YES See Section 4.2.4 of the RM

3. Procedures for performing maintenance activities (subject to 10 CFR 50, .XNO YES See Section 4.2.4 of the RM Appendix B)p

4. Regulatory commitment not covered by another regulation based change 4 NO YES See Section 4.2.3/4.2.4 of the RM process (see NEI 99-04)7 -- ....

IV. Does the proposed Activity involve a change to the Independent Spent Fuel NO YES See Section 4.2.6 of the RM

-Storage Installation (ISFSI) (subject to control by 10 CFR 72.48)

Check one of the following:

'i _snects of the Activity are controlled by one or more of the above processes, then a 50.59 Screening is = required and if all the Activity may be implemented in accordance with its governing procedure.

if any portion ofthe Activity is not controlled by one or more of the above processes, then process a 50.59 Screening for the portion not covered by any of the above processes. The remaining portion of the activity should be implemented in accordance with its governing procedure.

Signoff:

50.59 Screener/50.59 Evaluator: Sign:

S,. Date: I-Of If (Circle One) (Print name) (Signature) .

LS-AA-1I04-1002.FOIMA Rev 2

LS-AA-106 Revision 4 Page 20 of 23 ATTACHMENT 3 Nuclear Safety Significance Assessment Form Page I of I Item

Title:

F*-,ce.. C-.,+r.b( 6 Of A,'. f6. tZ 48r,.r/3tJ-.s7)Ef Item Number: -LW-414-- /oo Revision No. _ 7 Does the proposed change: YES NO 1 Result in a change to a procedure affecting Technical Specifications, ECCS, ESF, or PRA risk significant equipment or systems?

2 Result in a modification or change to a ECCS, ESF, or PRA risk significant system?

3 Consist of a major change to the facility and/or a major test or experiment? -

4 Consist of a major change to a plant process? IX 5 Change the qualification or operational characteristics of installed components or systems classified as safety related. x 6 Change the nuclear safety response of the plant to normal evolutions, anticipated operational occurrences, or design basis accidents? 7' 7 Have the potential to reduce the ability of the operator to assess or control the nuclear safety status of the plant?

8 Result from investigations of significant operational abnormalities including accidental unplanned or uncontrolled radioactive releases?

9 Increase the potential for a plant trip or present a challenge to safety systems?

10 Require NRC approval prior to implementation, e.g., TS, Security Plan, Emergency Plan?

11 10 CFR 50.59/10 CFR 72.48 written evaluation be prepared? - "-

If any answer to the above questions is "Yes", a full PORC review is required. If all questions are answered "No", a full PORC review is not required. Assumptions must be documented In the Comments Section below.

COMMENTS (Use additonal pages as necessary)

Circle as applicable THiS ITEM DOES/DOES NOT REQUIRE FULL PORC REVIEW.

PORC Member's Name .{ 4 Etk*l' 0 Department: (?J('ro PORC Member's _ __ _ _ __ _ _ Date: If 121) i Signfature

Assumptions for Attachment 3 to LS-AA-106

1) NO-RW-AA- 100 rev. 7 "Process Control Program for Radioactive Waste is being revised to standardize the usage of, shall, should, may and will lAW LS-AA-101-1002. And to correct the reference in step 4.3.1.

2) NO-Changes to RW-AA-100 are minor editorial changes and are making no modifications or changes to the facility.

3) NO- Changes to RW-AA-100 are minor editorial changes and are making no modifications or changes to the facility. The revision does not conduct any tests or experiments.

4) NO-The changes to RW-AA-100 are editorial in nature and do not make any changes to the facility Process Control Program or its requirements. Changes are to standardize the procedure wording IAW- LS-AA-101-1002.

5) NO - The radwaste system or its components are not considered as a safety related system. RW-AA-100 is administrative and does not manipulate any plant systems or components. RW-AA does not change any operational characteristics of the radwaste systems.

6) NO-Procedure RW-AA-100 has no effect on any nuclear safety response as it is administrative in nature and not used for any plant manipulation.

7) NO- RW-AA- 100 has no effect on the ability of an operator to assess or control the nuclear safety status of the plant. This procedure is administrative and does not control the plant in any way. All radwaste system manipulations will continue to be performed and controlled by approved station procedures.

8) NO- RW-AA-100 does not manipulate the plant in any way and has no control or effect on radioactive releases from the plant. All radwaste system operations will continue to be controlled by approved station procedures.

9) NO-RW-AA-1 00 has no potential to cause a plant trip and causes no plant manipulations. This procedure is administrative.

10) NO-Changes to RW-AA-100 does not make changes that require prior NRC approval. The changes to RW-AA-100 do not require a Tech Spec change.

Changes to this document will not change the physical processing of radioactive wastes or any requirements to meet applicable criteria and regulations for the safe transport and disposal of radioactive wastes.

I 1)NO- 10 CFR 50.59 and 10 CFR 72.48 evaluations are not required for the changes to RW-AA-100. Changes are editorial in nature for standardization of the procedure to LS-AA-101-1002.

Exe nRW-AA-100 Revision 7 Page 1 of 9 Nuclear Level 3 - Information Use PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES

1. PURPOSE 1.1. The purpose of the Process Control Program (PCP) is to:

1.1.1. Establish the process and boundary conditions for the preparation of specific procedures for processing, sampling, analysis, packaging, storage, and shipment of solid radwaste in accordance with local, state, and federal requirements. (CM-1) 1.1.2. Establish parameters which will provide reasonable assurance that all Low Level Radioactive Wastes (LLRW), processed by the in-plant waste process systems on-site OR by on-site vendor supplied waste processing systems, meet the acceptance criteria to a Licensed Burial Facility, as required by 10CFR Part 20, 10CFR Part 61, 10CFR Part 71, 49CFR Parts 171-172, "Technical Position on Waste Form (Revision 1)" [1/91], "Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification" [5/83], and the Station Technical Specifications, as applicable.

1.1.3. Provide reasonable assurance that waste placed in "on-site storage" meets the requirements as addressed within the Safety Analysis Reports for the low level radwaste storage facilities for dry and/or processed wet waste.

2. TERMS AND DEFINITIONS 2.1. Process Control Program (PCP): The program which contains the current formulas, sampling, analysis, tests, and determinations to be made to ensure that processing and packaging of solid radioactive waste based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure the waste meets the stabilization criteria specified in 10CFR Parts 20, 61 and 71, state regulations, and burial site requirements.

2.2. Solidification

Liquid waste processed to either an unstable or stable form per 10CFR61 requirements. Waste solidified does not have to meet the 300-year free standing monolith criteria. Approved formulas, samples and tests do not have to meet NRC approval for wastes solidified in a container meeting stability (e.g. High Integrity Container).

2.3. Stabilization

Liquid waste processed to a "stable state" per 10CFR61 Requirements. Established formulas, samples, and tests shall be approved by the NRC in order to meet solidification "stabilization" criteria. This processing method is currently not available, because the NRC recognizes that waste packed in a High Integrity Container meets the 300-year stabilization criteria. In the event that this processing method becomes an acceptable method, then the NRC shall approve the stabilization formulas, samples, tests, etc.

RW-AA-100 Revision 7 Page 2 of 9 2.4. Solidification Media: An approved media (e.g. Bamwell - vinyl ester styrene, cement, bitumen) when waste containing greater than 5-year half lives is solidified in a container when the activity is greater than 1 micro curie/cc. Waste solidified in a HIC is approved by the commission meeting the 10CFR61 stabilization criteria, including 1% free standing liquids by volume when the waste is packaged to a "stable" form and < 0.5% when waste is packaged to an "unstable" form. The formulas, sampling, analysis, and test do not require NRC approval, because the HIC meets the stability criteria.

2.4.1. Solidification to an unstable or stable state are performed by vendors, when applicable. Liquid waste solidified to meet stabilization criteria (10CFR61 and 01-91 Branch Technical Requirements) shall have documentation available that shows that the process is approved by the NRC or disposal facility.

2.5. Dewatering

The process of removing fluids from liquid waste streams to produce a waste form that meets the requirements of 10CFR Part 61 and applicable burial site criteria, <0.5% by volume when the waste is packaged to an "unstable" state, or

<1% by volume when the waste is packaged to a "stable" form.

2.6. High Integrity Container (HIC): A disposable container that is approved to the Requirements of 10CFR61. The use of HIC's is an alternative to solidification or encapsulation in a steel container to meet burial stability. HIC's are used to package dewatered liquid wastes, (e.g. filter cartridges, filter media, resin, sludges, etc), or dry active waste.

2.7. Encapsulation

The process of placing a component (e.g. cartridge filters or mechanical components) into a special purpose disposable container and then completely surrounding the waste material with an approved stabilization media, such as cement.

2.8. Liquid Waste Processing Systems: In-plant or vendor supplied processing systems consisting of equipment utilized for evaporation, filtration, demineralization, dewatering, compression dewatering, solidification, or reverse osmosis (RO) for the treatment of liquid wastes (such as Floor Drains, Chemical Drains and Equipment Drain inputs).

2.9. Incineration, RVR, and/or Glass Vitrification of Liquid or Solid: Dry or wet waste processed via incineration and/or thermal processing where the volume is reduced by thermal means meets 10CFR61 requirements.

2.10. Compaction: When dry wastes such as paper, wood, plastic, cardboard, incinerator ash, and etc. are volume reduced through the use of a compactor.

2.11. Waste Streams: Consist of but are not limited to

- Filter media (powdered, bead resin and fiber),

- Filter cartridges,

- Pre-coat body feed material,

- Contaminated charcoal,

RW-AA-100 Revision 7 Page 3 of 9

- Fuel pool activated hardware,

- Oil Dry absorbent material added to a container to absorb liquids

- Fuel Pool Crud

- Sump and tank sludges,

- High activity filter cartridges,

- Concentrated liquids,

- Contaminated waste oil,

- Dried sewage or wastewater plant waste,

- Dry Active Waste (DAW): Waste such as filters, air filters, low activity cartridge filters, paper, wood, glass, plastic, cardboard, hoses, cloth, and metals, etc, which have become contaminated as a consequence of normal operating, housekeeping and maintenance activities.

Other radioactive waste generated from cleanup of inadvertent contamination.

3. RESPONSIBILITIES 3.1. Implementation of this Process Control Program (PCP) is described in procedures at each station and is the responsibility of the each site to implement.

4. MAIN BODY 4.1. Process Control Program Requirements 4.1.1. A change to this PCP (Radioactive Waste Treatment Systems) may be made provided that the change is reported as part of the annual radioactive effluent release report, Regulatory Guide 1.21, and is approved by the Plant Operations Review Committee (PORC).

4.1.2. Changes become effective upon acceptance per station requirements.

4.1.3. A solidification media, approved by the burial site, may be REQUIRED when liquid radwaste is solidified to a stable/unstable state.

4.1.4. When processing liquid radwaste to meet solidification stability using a vendor supplied solidification system:

1. If the vendor has its own Quality Assurance (QA) Program, then the vendor shall ADHERE to its own QA Program and shall have SUBMITTED its process system topical report to the NRC or agreement state.

2. If the vendor does not HAVE its own Quality Assurance Program, then the vendor shall ADHERE to an approved Quality Assurance Topical Report standard belonging to the Station or to another vendor.

RW-AA-100 Revision 7 Page 4 of 9 4.1.5. The vendor processing system(s) is/are controlled per the following:

1. A commercial vendor supplied processing system(s) may be USED for the processing of LLRW streams.

2. Vendors that process liquid LLRW at the sites shall MEET applicable QA Topical Report and Augmented Quality Requirements.

4.1.6. Vendor processing system(s) operated at the site shall be OPERATED and CONTROLLED in accordance with vendor approved procedures or station procedures based upon vendor approved documents.

4.1.7. All waste streams processed for burial or long term on-site storage shall MEET the waste classification and characteristics specified in 10CFR Part 61.55, Part 61.56, the 5-83 Branch Technical Position for waste classification, and the applicable burial site acceptance criteria (for any burial site operating at the time the waste was processed).

4.2. General Waste Processing Requirements NOTE: On-site resin processing involves tank mixing and settling, transferring to the station or vendor processing system via resin water slurry or vacuuming into approved waste containers, and, when applicable, dewatering for burial.

4.2.1. Vendor resin beds may be USED for decontamination of plant systems, such as, Spent Fuel Pool, RWCU (reactor water cleanup), and SDC (Shut Down Cooling).

These resins are then PROCESSED via the station or vendor processing system.

4.2.2. Various drains and sump discharges will be COLLECTED in tanks or suitable containers for processing treatment. Water from these tanks may be SENT through a filter, demineralizer, concentrator or vendor supplied processing systems.

4.2.3. Process waste (e.g. filter media, sludges, resin, etc) will be periodically DISCHARGED to the station or vendor processing system for onsite waste treatment or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.

4.2.4. Process water (e.g. chemical, floor, equipment drain, etc.) may be SENT to either the site waste process systems or vendor waste processing systems for further filtration, demineralization for plant re-use, or discharge.

4.2.5. All dewatering and solidification/stabilization will be PERFORMED by either utility site personnel or by on-site vendors or will be PACKAGED and SHIPPED to an off-site vendor low-level radwaste processing facility.

RW-AA-100 Revision 7 Page 5 of 9 4.2.6. Dry Active Waste (DAW) will be HANDLED and PROCESSED per the following:

1. DAW will be COLLECTED and SURVEYED and may be SORTED for compactable and non-compactable wastes.

2. "DAW may be packaged in containers to facilitate on-site pre-compaction and/or off-site vendor contract requirements

3. DAW items may be SURVEYED for release onsite or offsite when applicable.

4. Contaminated filter cartridges will be PLACED into a HIC or will be ENCAPSULATED in an in-situ liner for disposal or SHIPPED to an offsite waste processor in drums, boxes or steel liners per the vendor site criteria for processing and disposal.

4.2.7. Filtering devices using pre-coat media may be USED for the removal of suspended solids from liquid waste streams. The pre-coat material or cartridges from these devices may be routinely REMOVED from the filter vessel and discharged to a Filter Sludge Tank or Liner/HIC. Periodically, the filter sludge may be DISCHARGED to the vendor processing system for waste treatment onsite or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.

4.2.8. Activated hardware stored in the Spent Fuel Pools will be PROCESSED periodically using remote handling equipment and may then be PUT into a container for shipment or storage 4.2.9. High Integrity Containers (HIC):

1. For Barnwell disposal vendors who supply HIC's to the station shall PROVIDE a copy of the HIC Certificate of Compliance, which details specific limitations on use of the HIC.

2. For Disposal at Clive vendors who supply HIC's to the station shall PROVIDE a copy of the HIC Certificate of Conformance, which details specific limitations on use of the HIC.

3. Vendors who supply HIC's to the station shall PROVIDE a handling procedure, which establishes guidelines for the utilization of the HIC. These guidelines serve to protect the integrity of the HIC and ensure the HIC is handled in accordance with the requirements of the Certificate of Compliance or Certificate of Conformance.

4.2.10. Lubricants and oils contaminated as a consequence of normal operating and maintenance activities may be PROCESSED on-site (by incineration, for oils meeting 10CFR20.2004 and applicable state requirements, or by an approved vendor process) or SHIPPED offsite (for incineration or other acceptable processing method).

4.2.11. Former in-plant systems GE or Stock Drum Transfer Cart and Drum Storage Areas may be USED for higher dose DAW storage at Clinton, Dresden, Quad Cities, Braidwood and Byron.

RW-AA-100 Revision 7 Page 6 of 9 4.2.13 Certain waste, including flowable solids from holding pond, oily waste separator, cooling tower basin and emergency spray pond, may be disposed of onsite under the provisions of 10CFR20.2002 permit. Specific requirements associated with the disposal shall be incorporated into station implementing procedures. (CM-2) 4.3. Burial Site Requirements 4.3.1. Waste sent directly to burial shall COMPLY with the applicable parts of 49CFR171-172, 10CFR61, 10CFR71, and the acceptance criteria for the applicable burial site.

4.4. Shipping and Inspection Requirements 4.4.1. All shipping/storage containers shall be INSPECTED, as required by station procedures, for compliance with applicable requirements (Department Of Transportation (DOT), Nuclear Regulatory Commission (NRC), station, on-site storage, and/or burial site requirements) prior to use.

4.4.2. Containers of solidified liquid waste shall be INSPECTED for solidification quality and/or dewatering requirements per the burial site, offsite vendor acceptance, or station acceptance criteria, as applicable.

4.4.3. Shipments sent to an off site processor shall be INSPECTED to ensure that the applicable processor's waste acceptance criteria are being met.

4.5. Inspection and Corrective Action 4.5.1. Inspection results that indicate non-compliance with applicable NRC, State, vendor, or site requirements shall be IDENTIFIED and TRACKED through the Corrective Action Program.

4.5.2. Administrative controls for preventing unsatisfactory waste forms from being released for shipment are described in applicable station procedures. Ifthe provisions of the Process Control Program are not satisfied, then SUSPEND shipments of defectively packaged radioactive waste from the site. (CM-1) 4.5.3. If freestanding water or solidification not meeting program requirements is observed, then samples of the particular series of batches shall be TAKEN to determine the cause. Additional samples shall be TAKEN, as warranted, to ensure that no freestanding water is present and solidification requirements are maintained.

4.6. Procedure and Process Reviews 4.6.1. The Exelon Nuclear Process Control Program and changes to it (other than editorial/minor changes) shall be REVIEWED and APPROVED in accordance with the station procedures, plant-specific Technical Specifications (Tech Spec),

Technical Requirements Manual (T&RM), Operation Requirements Manual (ORM),

as applicable, for the respective station and LS-AA-1 06. Changes to the Licensees Controlled Documents, UFSAR, ORM, or TRM are controlled by the provisions of 10CFR 50.59.

RW-AA-100 Revision 7 Page 7 of 9 4.6.2. Any changes to the PCP shall be reviewed to determine if reportability is required in the Annual Radiological Effluent Release Report (ARERR). The Radwaste Specialist shall ensure correct information is SUBMITTED to the ODCM program owner prior to submittal of the ARERR.

4.6.3. Station processes, cask manual procedures as applicable to your station, or other vendor waste processing/operating procedures shall be approved per RM-AA-102-1006. Procedures related to waste manifests, shipment inspections, and container activity determination are CONTROLLED by Radiation Protection Standard Procedures (RP-AA-600 Series).

1. Site waste processing IS CONTROLLED by site operating procedures.

2. Liquid processed by vendor equipment shall be DONE in accordance with I vendor procedures.

4.7. Waste Types, Point of Generation, and Processing Method Methods of processing and individual vendors may CHANGE due to changing financial and regulatory options. The table below is a representative sample. It is not intended be all encompassing.

AVAILABLE WASTE WASTE STREAM POINTS OF GENERATION POEING M E PROCESSING METHODS Bead Resin Systems - Fuel Pool, Condensate, Dewatering, solidification to an Reactor Water Cleanup, Blowdown, unstable/stable state Equipment Drain, Chemical and Thermal Processing Volume Control Systems, Floor Drain, Maximum Recycle, Blowdown, Boric Free Release to a Land Fill Acid Recycling System, Vendor Supplied Processing Systems, and Portable Demin System Powdered Resin Systems - (Condensate System, Floor Dewatering, solidification to an Drain/Equipment Drain filtration, Fuel unstable/stable state Pool) Thermal Processing Concentrated Waste Waste generated from Site Solidification to an unstable/stable Evaporators resulting typically from the state Floor Drain and Equipment Drain Thermal Processing Systems Sludge Sedimentation resulting from various Dewatering, solidification to an sumps, condensers, tanks, cooling unstable/stable state tower, emergency spray pond, holding Thermal Processing pond, and oily waste separators..

Evaporation on-site or at an offsite processor On-site disposal per 10CFR20.2002 permit

RW-AA-100 Revision 7 Page 8 of 9 AVAILABLE M POEING WASTEE WASTE STREAM POINTS OF GENERATION PROCESSING METHODS Filter cartridges Systems - Floor/Equipment Drains, Dewatering, solidification to an Fuel Pool; cartridge filters are typically unstable/stable state generated from clean up activities Processed by a vendor for volume within the fuel pool, torus, etc. reduction Dry Active Waste Paper, wood, plastic, rubber, glass, Decon/Sorting for Free Release, metal, and etc. resulting from daily Compaction/Super-compaction plant activities.

Thermal Processing by Incineration or glass vitrification Sorting for Free Release Metal melting to an ingot Contaminated Oil Oil contaminated with radioactive Solidification unstable state materials from any in-plant system. Thermal Processing by Incineration

....... _ Free Release for recycling Drying Bed Sludge Sewage Treatment and Waste Water Free release to a landfill or burial Treatment Facilities Metals See DAW See DAW Irradiated Hardware Fuel Pool, Reactor Components Volume Reduction for packaging efficiencies

5. DOCUMENTATION 5.1.1. Records of reviews performed shall be retained for the duration of the unit operating license. This documentation shall contain:

1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change, and

2. A determination which documents that the change will maintain the overall conformance of waste products to Federal (10CFR61 and the Branch Technical Position), State, or other applicable requirements, including applicable burial site criteria.

6. REFERENCES 6.1. Technical Specifications:

6.1.1. The details contained in Current Tech Specs (CTS) or Improved Technical Specifications (ITS), as applicable, in regard to the Process Control Program (PCP),

are to be relocated to the Licensee Controlled Documents. Some facilities have elected to relocate these details into the Operational Requirements Manual (ORM).

Relocation of the description of the PCP from the CTS or ITS does not affect the safe operation of the facility. Therefore, the relocation details are no...t required to be in the CTS or the ITS to provide adequate protection of the public health and safety.

RW-AA-100 Revision 7 Page 9 of 9 6.2. Writers'

References:

6.2.1. Code Of Federal Regulations: 10 CFR Part 20, Part 61, Part 71, 49 CFR Parts 171-172 6.2.2. Low Level Waste Licensing Branch Technical Position On Radioactive Waste Classification, May 1983 6.2.3. Technical Position on Waste Form (Revision 1), January 1991 6.2.4. Branch Technical Position on Concentration Averaging and Encapsulation, January 1995 6.2.5. Regulatory Guide 1.21 6.2.6. I.E. Circular 80.18, 10CFR 50.59 Safety Evaluation for Changes to Radioactive Waste Treatment Systems 6.3. User References 6.3.1. Quality Assurance Program 6.3.2. LS-AA-106 6.3.3. RM-AA-102-1006 6.3.4. RP-AA-600 Series 6.3.5. CY-AA-170-2000, Annual Radioactive Effluent Release Report 6.4. Station Commitments:

6.4.1. Peach Bottom CM-1, T03819, Letter from G.A. Hunger, Jr., dated Sept. 29,94, transmitting TSCR 93-16 (Improved Technical Specifications).

6.4.2. Limerick CM-2, T03896, 10CFR20.2002 permit granted to Limerick via letter dated July 10, 1996.

7. ATTACHMENTS - None