ML18010A547

From kanterella
Revision as of 01:22, 10 September 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Rev 3 to Odcm.
ML18010A547
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 12/18/1991
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML18010A543 List:
References
PROC-911218, NUDOCS 9202270217
Download: ML18010A547 (57)
v • d • e


Text

,OS2SHEARON HARRIS NUCLEAR POWER PLANT OPP" SITE DOSE CALCULATIOH MANUAL (ODCM)Revision 3 Advance Change 3/4 Docket No.STN-50-400 CAROLINA POWER&LIGHT COMPANY PNSC Chairman's Approval Effective Date 9202270217 911218 PDR ADOCK 05000400 R PDR 4/2 0 V OS2 2.2.1 Cumulation of Doses (continued)

The Dose factor A~, (see NUREG-0133, Section 4.3.1)was calculated for an adult for each isotope"i" using the following equation: Ag~=1.14E+05 (-+21BFg)DFg W (2.2-3)where: 0S 10 PCi 1000 ml 1 yr 1 pCi 1 liter 8760 hrs 21 Adult fish consumption rate (from Table E-5 of Regulatury Guide 1~109, Rev.1), kg/yr;A<<.The ingestion dose commitment factor to the whole body or any organ, r, for an adult for each isotope"i." Corresponding to dilution by the Cape Fear River for drinking water and fish consumption at Lillington, North Carolina.Values for the adult total body and organs in mrem/hr, per uCi/ml are given in Table 2.2-1.730 Adult water consumption rate (from Table E-5 of Regulatory Guide 1.109, Rev.1), liters/yr.

Dw Dilution factor from the near-field area within one-quarter (4)mile of the release point to the closest potable water inlet for the adult water consumption pathway.(Reference Shearin-to-Varriner memo N0-83-H1483, File 12610B3, dated October 21, 1983.DCM/ODC-2 2-18 4/3 Rev.3.0

OS2 2.2.1 Cumulation of Doses (continued)

The Dose factor A~, (see NUREG-0133, Section 4.3.1)was calculated for an adult for each isotope"i" using the following equation: Ag~=1.14E+05 (-+21BFg)DF~~(2.2-3)where: 10~pCi 1000 ml 1 yr 1 pCi 1 liter 8760 hrs 21 Adult fish consumption rate (from Table E-5 of Regulatury Guide 1.109, Rev.1), kg/yr;The ingestion dose commitment factor to the whole body or any organ,~, for an adult for each isotope"i." Corresponding to dilution by the Cape Fear River for drinking water and fish consumption at Lillington, North Carolina.Values for the adult total body and organs in mrem/hr per uCi/ml are given in Table 2.2-1.730 Adult water consumption rate (from Table E-5 of Regulatory Guide 1.109, Rev.1), liters/yr.

Dw Dilution factor from the near-field area within one-I quarter (4)mile of the release point to the closest potable water inlet for the adult water consumption pathway.(Reference Shearin-to-Warriner memo N0-83-H1483, File 12610B3, dated October 21, 1983.DCM/ODC-2 2-18 4/4 Rev.3.0 OS2 Deleted by AC 3/4 DCM/ODC-2 2-18a 4/5 Rev.3.0

<<H 0 C.

OS2 TABLE 2.2-1 Sheet 1 of 2 A;, VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR Ag~=1.14E+05 (-+21BFg)DFg~730 (mrem/hr per micro-Ci/ml)

POWER PLANT Nuclide Bone Liver Trod T~hroid~Kid ne~Lun GI-LLIH-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni43 Ni-65 Cu44 Zn-65 Zn49 Br 83 Br 84 Br85 Rb-86 Rb-88 Rb-89 Sr 89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 0.008+00 , 3.13E+04 4.178+02 4.628+07 0.008+M O.OOE+00 O.OOE+00 6.75E+02 1.06E+03 0.00E+00 0.00E+00 3.19E+04 1.308+02 0.008+00 2.328+04 4.948+01 0.008+00 O.OOE+00 0.008+00 O.OOE+00 0.008+00 0.008+00 2.40E+04 5.89E+05 4.418+02 1.67E+02 6.33M)1 5.988%3 9.28E+00 5.568%2 1.768<1 4.218%1 2.338%2 4.478+02 0.008+00 1.038%2 1.068%2 5.538+00 4.60M)1 8.508-01 6.268+03 4.17E+02 2.87E+06 0.008+00 4.40E+03 1.11E+02 4.66E+02 2.50E+03 9.36E+01, 2.69E+02 2.21E+03 1.688+01 1.05E+01 7.38E+04 9A48+01 0.00E+00 0.008+00 0.008+00 1.01E+05 2.908+02 1.928+02 0.00E+00 O.OOE+00 O.MB+00 0.008+00 O.OOE+M O.OOE+M 0.00E+00 0.008+00 0.00E+00 1.3581-4.69E-03 2.49E+02 1.29E+02 2.92E-02 1.538%2 0.00E+00 O.OOE+00 8.508-01 6.26E+03 4.17E+02 1.798+06 1.298+00 8.40E+02 1.978+01 1.09E+02 9.59E+02 2.10E+02 5.93E+02 1.07E+03 7.688+00 4.91E+00 3.34E+04 6.578+00 4.07E+01 5.278+01 2.16E+00 4.718+04 1.54E+02 1.358+02 6.878+02 1.45E+05 1.788+01 7.238+00 1.708%2 2.328<4 2.488<1 1.638%3 4.87E-03 9.148%2 2.15E-03 1.348+02 2.458+01 3.728%1 1.508<1 2.38E+00 1.828<1 8.5081 6.26E+03 4.17E+02 0.008+00 7.718%1 0.008+M 0.008+00 O.OOE+00 0.008+00 0.008+00 0.008+00 0.008+00 O.OOE+00 O.ME+00 O.OOE+00 0.008+00 O.OOE+00 0.008+00 O.OOE+00 O.OOE+00 0.008+00 0.00E+00 O.OOE.+00 0.008+00 0.008+M 0.008+00 O.OOE+00 O.OOE+00 0.008+00 O.OOE+00 0.008+00 O.OOE+00 0.008+00 0.00E+00 0.008+00 0.008+00 0.008+00 0.008+00 O.ME+00 8.508%1 6.26E+03 4.17E+02 O.OOE+00 2.848%1 1.318+03 1.418+02 0.008+00 O.OOE+00 O.OOE+00 0.008+00 O.OOE+00 O.OOE+00 2.648+01 4.94E+04 6.14E+Ol 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.008+00 O.OOE+00 O.OOE+00 0.008+00 0.008+00 0.00E+00 O.MB+00 0.008+M 0.008+00 O.OOE+M 0.008+M 2.128%1 7.098%3 2.468+02 2.92E+02 4.448%1 2.768%1 2.11E+01 5.95E+00 8.50M)1 6.26E+03 4.17E+02 0.008+00 1.71E+00 0.008+00 0.00E+00 2.608+02 6.998+02 0.008+00 0.008+00 0.008+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.008+M O.MB+00 0.00E+00 0.008+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.008+M O.ME+00 O.OOE+00 O.OOE+00 0.008+00 O.OOE+M 0.008+00 0.008+M 0.00E+00 0.00E+00 0.008+00 1.438-02 7.838%3 O.OOE+00 O.MB+00 8.50841 6.26E+03 4.17E+02 5.208+06 3.23E+02 1.35E+04 3.54E+03 2.678+02 8.34E+03 1.90E+03 5.058+03 4.618+02 4.27E+02 8.928+02 4.658+04 1.428+01 5.86E+01 4.14844 1.008-15 1.99E+04 4.018%9 1.128-11 3.84E+03 1.708+04 2.108+03 3.31E+03 6.718+03 1.768<2 5.118+03 9.74E+02 5.598+03 4.28E+02 1.458+03 1.518+06 2.998+02 1.738+01 4.608-14 6.46E+02 2.82E+02)ac3/5 its iQs-DCM/ODC-2 2-26 4/6 Rev.3.0 av'>>1 0-L'g e'w4 OS2 Table 3.2-2 rest Special L uclear Power P 1990/1991 Da ocations lant (miles)*ta)Dist'for the S ance to the Nea hearon Harris N (Comparison of Residence Milk Animal Garden Meat Animal Sector Exclusion Boundary 1990 1991 1990 1991 1990 1991 1990 1991 N 1.32 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 NNE'.33 1.8 1.8 4.6 1.7 1.7 3.5 3.5 NE ENE 1.33 1.33 2.3 2.0 2.3 3.6 2.3 3.6 2.3 3'2.3 2'E ESE SE SSE SSW SW WSW 1~33 1.33 1.33 1.33 1.36 1.33 1.33 1.33 1.33 1.9 2.7 4.3 4,4 3.9 2.8 4.3 2.8 1.9 2.7 4.3 3.9 2.8 4.3 2.8 4.7 2.7 4.3 3.9 2.8 4~3 2.9 4,7 4.4 4.4 4.6'.9'.8 4.3 2.9 2.2 4,4 4.3 4.3 2.9 2.2 2.9 1.33 2.1 2.1 2.1 2.9'.6 1.26 2.1 2.1 3.8 3.8 3.8 3.8 1.26 1.5 1.5 1.7 1.7 1.7'.7 As of June, 1991.*Distance estimates are+O.l miles except at the exclusion boundary.DCM/ODC-3 3-18 4/7 Rev.3.0

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 5: Changes to the Environmental Monitoring Program Enclosure 1: Environmental Monitoring Program Technical Specifications 3.11.2.3 3.12.1 3.12.1.c No changes were made to the Environmental Monitoring Program during this Monitoring Period.

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 5: Changes to the Environmental Monitoring Program Enclosure 2: Land Use Census Technical Specifications 3.12.2.a 3.12.2.b No changes were made to the Land Use Census during the Report period.The change referenced in Appendix 4 was made and reported in the previous monitoring period.5/2

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 6: Additional Technical Specification Responsibilities : Inoperability of Liquid Effluent Monitors Technical Specification 3.3.3.10, Action b Monitors Out-of-Service

>30 Days During the Report Period Effluent Monitor Days Inop Reason for Inoperability FT-21WL-6119 Vaste Monitor Tank/Paste Evaporator Condensate Tank Discharge Flow Rate Monitor FT-*1WL-6193 Treated Laundry&Hot Shower Tanks Discharge Flow Rate Monitor 184 Both of these flow indicators have been inoperable becaus'e of a scaling problem between the readout and the associated measuring orifice.A modification to correct this has been completed and the monitors will be returned to service following calibration.

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 6 (Continued):

Additional Technical Specification Responsibilities : Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service

)30 Days During the Report Period Effluent Monitor PNL-21AV-3509-SA PNL-21AV-3509-1SA Plant Vent Stack Plow Rate Monitor RM-01TV-3536-1 Turbine Building Vent Stack 3A Flow Rate Monitor PNL-1WV-3546 6 PNL-1WV-3546-1 WPB Vent Stack 5 Plow Rate Monitor PNL-1WV-3547 6 PNL-1WV-3547-1 WPB Vent Stack 5A Plow Rate Monitor Days Inop 184 184 184 184 Reason for Inoperability Problems with calibration of flow measurement system resulting in discrepancies between actual and expected flow rates.Modification initiated to correct'.Moisture interferences with the flow measurement system resulting in discrepancies betveen actual and expected flow rates.Modification initiated to correct.Problems with calibration of flow measurement system resulting in discrepancies between actual and expected flov rates.Modification initiated to correct.Problems with calibration of flow measurement system resulting in discrepancies between actual and expected flov rates.Modification initiated to correct.6/2

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 6 (Continued):

Additional Technical Specification Responsibilities : Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service

>30 Days During the Report Period Effluent Monitor HAIC-21WG-1118A Waste Gas Recombiner"A" Outlet Gas Hydrogen Monitor OARC-21WG-1119A Waste Gas Recombiner"A" Outlet Gas Oxygen Monitor OAI-21WG-1101 Waste Gas Compressor Discharge Oxygen Monitor HAIC-21WG-1118B Waste Gas Recomb'incr"B" Outlet Gas Hydrogen Monitor OARC-21WG-1119B Waste Gas Recombiner"B" Outlet Gas Oxygen Monitor Days Inop 68 68 Reason for Inoperability A modification to improve the reliability of the waste gas analyzers (A-train)was ongoing and completed; During the periods of inoperability, the B-train components were operable.This monitor was included in the A-train modifications.

A modification to improve the reliability of the waste gas analyzers (B-train)was begun.The B-train components were not made operable until the A-train components were operable.The modification is expected to be completed by mid-1992.6/3 Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 6 (Continued):.Additional Technical Specification Responsibilities : Unprotected Outdoor Tanks Exceeding Limits Technical Specification 3.11.1.4, Action a No unprotected outdoor tank exceeded the, Technical Specification limit during this Report period.6/4 Semiannual Radi'oactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 6 (Continued):

Additional Technical Specification Responsibilities : Gas Storage Tanks Exceeding Limits Technical Specification 3.11.2.6, Action a No gas storage tank exceeded the Technical Specification limit during this Report period.6/5

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 7: Major Modifications to Radwaste System Technical Specification 6.15.1 In September 1991 Chapter 11 of the Shearon Harris Nuclear Power Plant FSAR was updated to show the following changes in Radioactive Waste Management System: 1~2.3~4.6.The Radwaste Demineralization System was changed from an alternate process system to the primary process system for liquid radioactive waste.The RO/Evaporator systems were designated as alternate process systems to be place in long term shutdown.The Volume Reduction System, Secondary Waste Evaporators, and the Solid Radwaste System was deleted from the FSAR.This equipment is to.be abandoned in place.The Solid Radwaste section was updated to reflect liquid waste and dry active waste being processed by vendor services.The Liquid Radwaste section was updated to reflect current input volumes, no segregation of floor drains, equipment drains, chemical drains, or laundry and hot shower drains for processing through the Radwaste Demineralizer System, and zero recycle of processed waste.The source terms and input volumes were updated to reflect the impact of spent fuel shipment from other CP&L Plants and draining of water from spent fuel pools to the R'adwaste System.These changes were provided in Amendment No.43 of'the FSAR submitted to the NRC on October 24, 1991 (Letter NLS-91-276).

J

SUMMARY

OF 10CFR 50.59 REVIEW The 10CFR50.59 safety review concluded that these changes did not involve an unreviewed safety question but required a Plant Nuclear Safety Committee (PNSC)Review.This conclusion was based on the following.

The affected systems are not mitigating systems for any Chapter 15 accident analysis.The-liquid radwaste system is an initiating system for a Chapter 15 accident analysis, however, the changes had no impact on any evaluated accident or any other safety equipment; Gale Code and LADTAP II computer programs were run to show compliance with 10CFR20 and 10CFR50 design objectives.

The computer codes showed an increase in the concentration of radioactive isotopes in the liquid waste effluent and a corresponding increase in effluent dose.This increase was small and in compliance with 10 CFR20 and 10CFR50 design objectives.

Due to the increase the change was determined to be a major change to a Radwaste Process System requiring PNSC review.7/1

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 7 (Continued):

Major Modifications to Radwaste System Technical Specification 6.15.1 The PNSC review concluded that although the concentrations in the revised FSAR tables were increased, the increases were below 10CFR release concentration levels and a minor infringement on the margin of safety.REASON FOR THE CHANGE Several changes have been made to the Radioactive Waste Management System which required the FSAR to be updated.2~.4,~.6.In January 1989 a Radwaste Demineralizer System was installed as an alternate process system.The system has proven to be an effective and reliable liquid radwaste process system and is being used as the primary system for processing liquid radioactive waste.The actual plant liquid radwaste volumes were above those predicted in the FSAR.In response to NRC IE Informat'ion Notice 83-49"Sampling and Prevention of Intrusion of Organic Chemicals into Reactor Coolant Systems" and to prevent introduction of potentially corrosive organics to the steam generators the decision was made not to recycle liquid radwaste, except for boric acid, to the primary or secondary systems.Since the processed liquid is not being recycle segregation of liquid waste streams is not required.'he installed Solid Radwaste Process System failed to meet the stability requirements of 10CFR61 for solidified waste and vendor processing capabilities were installed as required by Technical Specifications.

The receipt of spent fuel from other CPSL plants has caused an increase in the source terms due to corrosion products that are sloughed from the spent fuel.Draining of liquids from the spent fuel pools was not provided for in the FSAR.The FSAR was updated to reflect these changes and current operating practices as required by 10CFR50.71e.

This FSAR change also allows certain liquid radwaste equipment to be place in long term shutdown or to be abandoned in'lace.'ESCRIPTION A detailed description of the equipment, components, and processes involved ,and the interfaces with other plant systems is contained in Amendment 43 to the FSAR submitted to the NRC on October 24, 1991 (Letter NLS-91-276).

CHANGES IN PREDICTED CONCENTRATION DOSES AND VOLUMES The predicted release of radioactive materials have changed from those previously predicted as follows.7/2

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 7 (Continued):

Major Modifications to Radwaste System Technical Specification 6;15.1 The annual activity released as listed in the FSAR Table 11.2.3-1 is increased from 2.3E-1 to 1.0E+0 curies/year.

Tritium release increased from 1.5E+2 to 1.04E+3 curies/year.

The average reservoir normal concentration of radioisotopes per maximum permissible concentration as listed.in FSAR Table 11.2.3-3 increased from 1.44E-4 to 1.92E-2 C/MPC.The cooling tower discharge normal concentration per maximum permissible concentration increased from 5.74E-2 to 1.07E-1 C/MPC.The individual dose to the public as listed in the FSAR Table 11.2.3-4 for Adult Total Body increased from 0.79 to 1.46 mrem/year and for Adult Liver Dose increased from 1.08 to 2.1 mrem/year.

/The average reservoir design basis concentration of radionuclides released as listed in FSAR Table 11.2.3-5 increased from 1.34E-3 to 8.8E-2 C/MPC.The cooling tower discharge design basis release concentration increased from 5.52E-1 to 7.2E-1 C/MPC.The predicted solid radwaste volumes (excluding dry solids which did not change)was reduced from 5,915 to 2,210 cubic feet per year.Although the concentration and the doses in the above listed tables increased the increase is well below the limits of 10CFR20 and the design guidance of 10CFR50.The increase is primarily due to zero recycle of liquid radwaste and not to the instillation of the Radwaste Demineralizer System.It should be noted that these are predicted values and that normal operating values as reported in the Semiannual Reports are less than these predicted values.COMPARISON OF PREDICTED VALUES TO ACTUAL RELEASES A comparison of predicted values to actual releases is given below.Total Body Dose from Liquid Releases-Limit 3.0 mrem/year Predicted 1.46 mrem 1988 Prior to change 0.012 mrem 1991 After change 0.008 mrem Critical Organ Dose from Liquid Releases Predicted 1988 Prior to change 1991 After change-Limit 10mrem/year 2.10 mrem 0.49 mrem 0.017 mrem Fission&Activation Products Release Predicted 1988 Prior to change 1991 After change I 1.00 curies 0.08 curies 0.66 curies 7/3

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 7 (Continued):

Major Modifications to Radwaste System Technical Specification 6.15.1 Tritium Release Predicted 1040 curies 1988 Prior to change'00 curies 1991 After change 290 curies Solid Radwaste (Excluding DAW)Predicted 1988 Prior to change 1991 After change 2210 cubic feet 4328 cubic feet 1393 cubic feet EXPOSURE TO PLANT OPERATING PERSONNEL It is expected that these changes will show an overall decrease in exposure to plant personnel due to less maintenance activity required for the operating system and due to placing equipment in long term shutdown.SAFETY AND TECHNICAL REVIEWS Documented safety and technical review in accordance with Technical Specification 6.5.1 have been completed as part of FSAR Amendment Review Approval Form (RAF)1645.The Plant Nuclear Safety reviewed and approved the changes on September 23, 1991.Documentation of the PNSC review.is contained in the safety analysis and the meeting minutes.7/4 I

Semiannual Radioactive Effluent Release Report July 1,'1991 to December 31, 1991 Appendix 8: Meteorological Data Technical Specification 6.9.1.4 As allowed by the Footnote to Technical Specification 6.9;1;4, the'annual summary of meteorological data will be retained in a file.These data will be provided to the NRC upon request.

Seniannual Radioactive Effluent Release Report July 1, 1991 to Decenber 31, 1991 Appendix 9: Assessnent of Radiation Doses Enclosure 1: Population Doses Outside Site Boundary Due to Effluent Releases 1.Zntegrated Population Dose Due to Liquid Effluents (nan-ren)A 50 nile Ingestion Zone Bone Liver W.Body Thyroid Kidney Lung GZ LLI Skin sport Fish Conn Fish Sport Znvert Conn Invert Drinking Water Shoreline Swinning Boating Irri Veg Zrri Leafy Veg Zrri Milk Zrri Meat 2.29 E-02 0.00 E+00 0.00 E+00 0.00 E+00 3.92 E-03 1.83 E-02 1.14 E-04 5.80 E-05 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 3.55 E-02 0.00 E+00 0.00 E+00 0.00 E+00 2.66 E-01 1.83 E-02 1.14 E-04 5.80 E-05 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 2.19 0.00 0.00 0.00 2.66 1.83 1.14 5.80 0.00 0.00 0.00 0.00 E-02 E+00.E+00 E+00 E-01 E-02 E 04 E-QS E+00 E+00 E+00 E+00 1.15 E-03 0 00 E+00 0.00 E+00 0.00 E+00~2.61 E-01 1.83 E>>02 1.14 E-04 5.80 E-05 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 1.23 0.00 0.00 0.00 2.61 1.83 1.14 5.80 0.00 0.00 0.00 0.00 E-02 E+00 E+00 E+00 E-01 E-02 E-04 E-05 E+00 E+00 E+00 E+00 5.04 0.00 0.00 0.00 2.61 1.83 1.14 5.80 0.00 0.00 0.00 0.00 E-03 E+00 E+00 K+00 E-01 E-02 E-04 E-05 E+00 E+00 E+00 E+00 9.09 0.00 0.00 0.00 2.91 1.83 1.14 5.80 0.00 0.00 0.00 0.00 E-03 E+00 E+00 E+00 E-01 E-02 E-04 E-05 E+00 E+00 E+00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 2.15 E-02 0.00 E+00 0 00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 Et00 ALL PATHWAYS 4.53 E-02 3.20 E-01 3.07 E-01 2.81 E-01 2.92 E-01 2.85 E-01 3.18 E-01 2.15 E-02 B.Tritiun (Hydrosphere)

Bone Liver W.Body Thyroid Kidney Lung GZ-LLI Total 0.00 E+00 3.90 E-03 3.90 E-03 3.90 E-03 3.90 E-03 3.90 E-03 3.90 E-03 2.Ihtegrated Population Dose Due to Gaseous Effluents (nan-ren)50 nile Ingestion Zone W.Body GZ-LLI Bone Liver Kidney Thyroid Lung Skin Plune Ground Inhalation Vegetation Cow Milk Meat a Poultry 1.67 6.68 1.40 4.32 1.69 2.08 E-01 E-04 E-03 E-04 E-04 E 04 1.67 E-01 6 68 E-04 1.'41 E-03 4.42 E-04 1.69 E-04 2.12 E-04 1.67 E-01 6.68 E-04 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 1.67 6.68 1.40 4.30 1.68 2.07 E-01 E-04 E-03 E-04 E-04 E-04 1.67 E-01 6.68 E-04 1.40 E-03 4.29 E-04 1.68 E-04 2 06 E-04 1.67 E-01 6.68 E-04 1.40 E-03 4.29 E-04 1.68 E-04 2.06 E-04 1.77 6.68 1.62 4.29 1.68 2.06 E-01 E-04 E-03 E-04 E-04 E-04 5.72 7.86 1.40 4.29 1.68 2.06 E-01 E-04 E-03 E 04 E-04 E 04 Total 1.69 E-01 1.70 E-01 1.67 E-01 1.69 E-01 1.69 E-Ql 1.69 E-01 1.81 E-01 5.75 E-01 9/1

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 9: Assessment of Radiation Doses Enclosure 2: Doses to General Public Due to Activities Znside Site Boundary Individual Dose Due to Liquid Effluents (arem/yr.)

ADULT Bone Liver W.Body Thyroid Ki d11e'y Lung GI-LLI Skin Fish Shoreline Swimming Boating TOTAL 2.38 E-02 1.80 E-03 1.24 E-04 1.42 E-04 2.59 E-02 3.99 E-02 1.80 E-03 1.24 E-04 1.42 E-04 4.20 E-02 2.93 E-02 1.80 E-03 1.24 E-04 1.42 E-04 3.14 E-02 1.43 E-03 1.80 E-03 1.24 E-04 1.42 E-04 3.50 E-02 1.40 E-02 1.80 E-03 1-24 E-04 1~42 E-04 1.60 E-02 5.65 E-03 1.80 E-03 1.24 E-04 1.42 E-04 7.70 E-03 1.22 E-02 1.80 E-03 1.24 E-04 1.42 E-04 1.43 E-02 2.12 E-03 2.12 E-03 TEEN Fish Shoreline Swimming Boating TOTAL 2.52 E-02 1.01 E-02 1.86 E-04 2.07 E-04 3'7 E-02 4.08 E-02 1.01 E-02 1.86 E-04 2.07 E-04 5.13 E-02 1.73 E-02 1.01 E-02 1.86 E-04 2 07 E 04 2.77 E-02 1.11 E-03 1.01 E-02 1.86 E-04 2.07 E-04 1.16 E-02 1.40 E-02 1.01 E-02 1.86 E-04 2.07 E-04 2.45 E-02 6.18 E-03 1.01 E-02 1.86 E-04 2.07 E-04 1.66 E-02 8.58 1.01 1.86 2.07 1.90 E-03 E-02 E-04 E-04 E-02 1.18 E-02 1.18 E-02 CHILD Fish Shoreline Swimming Boating TOTAL 3.15 E-02 2.10 E-03 6.21 E-05 7.77 E-05 3.37 E-02 3.60 E-02 2.10 E-03 6.21 E-05 7.77 E-05 3.82 E-02 7.83 E-03 2.10 E-03 6.21 E-05 7.77 E-05 1.10 E-02 9.37 E-04 2.10 E-03 6.21 E-05 7.77 E-05 3.18 E-03 1.19 E-02 2.10 E-03 6.21 E-05 7.77 E-05 1.42 E-02 4.94 2.10 6.21 7.77 7.19 E-03 E-03 E-05 E-05 E-03 3.48 E-03 2.10 E-03 6.21 E-05 7.77 E-05 5.73 E-03 2.47 E-03 2.47 E-03 9/2

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 9: Assessment of Radiation Doses Enclosure 2 (Continued):

Doses to General Public Due.to ActivitieS Inside Site Boundary 2.Individual Dose Due to Gaseous EfPluents (nrem/yr.)

ADULT W.Body GZ-LLZ Bone Liver Kidney Thyroid Lung Skin Plume Ground Inhalation TOTAL 4.78 E-03 4.37 E-05 1.73 E-05 4.84 E-03 4.78 E-03 4.37 E-05 1.75 E-05 4.84 E-03 4.78 E-03 4.37 E-05 0 00 E+00 4.83 E-03 4.78 E-03 4.37 E-05 1.73 E-05 4.84 E-03 4.78 E-03 4.37 E-05 1.73 E-05 4.84 E-03 4.78 E-03 4.37 E-05 1.73 E-05 4.84 E-03 4.95 E-03 4.37 E-05 2.12 E-05 5.02 E-03 1.29 E-02 5.14 E-05 1.73 E-05 1.29 E-02 TEEN Plume Ground Inhalation 4.78 E-03 4.37 E-05 1.74 E-05 4.78 E-03 4.37 E-05 1.75 E-05 4.78 E-03 4.37 E-05 F 00 E+00 4:78 E-03 4.37 E-05 1.74 E-05 4.78 E-03 4.37 E-05 1.74 E-05 4.78 E-03 4.37 E-05 1.74 E-05 4.95 E-03 4.37 E-05 2.31 E-05 1.29 E-02 5.14 E-05 1.74 E-05 TOTAL 4.84 E-03 4.84 E-03 4.83 E-03 4 F 84 E-03 4.84 E-03 4.84 E-03 5.02 E-03 1.29 E-02 CHILD Plume Ground Inhalation 4.78 E-03 4.37 E-05 1.54 E-05 4.78 E-03 4.37 E-05 1.54 E-05 4.78 E-03 4.37 E-05 0.00 E+00 4'8 E-03 4.37 E-05 1.54 E-05 4.78 E-03 4.37 E-05 1.54 E-05 4.78 E-03 4.37 E-05 1.54 E-05 4.95 E-03 4.37 E-05"2.00 E-05 1.29 E-02 5.14 E-05 1.54 E-05 TOTAL 4.84 E-03 4.84 E-03 4.83 E-03 4'4 E-03 4.84 E-03 4.84 E-03 5.02 E-03 1.29 E-02 INFANT Plume Ground Inhalation TOTAL 4.78 E-03 4.37 E-05 8.84 E-06 4.83 E-03 4.78 E-03 4.37 E-05 8.85 E-06 4.83 E-03 4.78 E-03 4,37 E-05 0.00 E+00 4.83 E-03 4.78 E-03 4.37 E-05 8.84 E-06 4.83 E-03 4.78 E-03 4.37 E-05 8.83 E-06 4.83 E-03 4.78 4.37 8.83 4.83 E-03 E-05 E-06 E-03 4.95 E-03 4.37 E-05 1.18 E-05 5.01 E-03 1.29 E-02 5.14 E-05 8.83 E-06 1.29 E-02 9/3 4 c Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 9: Assessment of Radiation Doses Enclosure 3: Doses to Likely Most Exposed Member of the Public Individual Dose Due to Liquid Effluents (nrem/yr.)

ADULT Bone Liver W.Body Thyroid Lung GI-LLI Skin Fish Drinking Shoreline Swimming Boating TOTAL 2.38 E-02 1.50 E-04 1.80 E-03 1.24 E-04 1.42 E-04 2.60 E-02 3.99 E-02 1.31 E-02 1.80 E-03 1.24 E-04 1.42 E-04 5.50 E-02 2.93 E-02 1.31 E-02 1.80 E-03 1.24 E-04 1.42 E-04 4.45 E-02 1.43 E-03 1.29 E-02 1.80 E-03 1~24 E-04 1.42 E-04 1.64 E-02 1.40 E-02 1.29 E-02 1.80 E-03 1~24 E-04 1.42 E-04 2.89 E-02 5.65 1.29 1.80 l.24 1.42 2.06 E-03 E-02 E-03 E-04 E-04 E-02 1.22 1.46 1.80 1.24 1.42 2.89 E-02 E-02 E-03 E-04 E-04 E-02 2.12 E-03 2.12 E-03 TEEN Fish Drinking Shoreline Swimming Boating TOTAL 2.52 E-02 0.00 E+00 1.01 E-02 1.86 E-04 2.07 E-04 3.57 E-02 4.08 E-02 0.00 E+00 1.01 E-02 1.86 E-04 2.07 E-04 5.13 E-02 1.73 E-02 0.00 E+00 1.01 E-02 1.86 E-04 2.07 E-04 2.77 E-02 l.11 0.00 1.01 1.86 2.07 1.16 E-03 E+00 E-02 E-04 E-04 E-02 1.40 E-02 0.00 E+00 1.01 E-02 1.86 E-04 2.07 E-04 2.45 E-02 6.18 E-03 0.00 E+00 1.01 E-02 1.86 E-04 2.07 E-04 1.66 E-02 8.58 E-03 0.00 E+00 1.01 E-02 1.86 E-04 2.07 E-04 1.90 E-02 1.18 E-02 1.18 E-02 CHILD Fish Drinking Shoreline Swimming Boating TOTAL 3.15 E-02 0.00 E+00 2.10 E-03 6.21 E-05 7.77 E-05 3.37 E-02 3.60 0.00 2.10 6.21 7.77 3.82 E-02 E+00 E-03 E-05 E-05 E-02 7.83 0.00 2.10 6.21 7.77 1.10 E-03 E+00 E-03 E-05 E-05 E-02 9.37 E-04 0.00 E+00 2.10 E-03 6.21 E-05 7.77 E-05 3.18 E-03 l.19 0.00 2.10 6.21 7.77 1.42 E-02 E+00 E-03 E-05 E-05 E-02 4.94 0.00 2.10 6.21 7.77 7.19 E-03 E+00 E-03 E-05 E-05 E-03 3.48 E-03 0.00 E+00 2.10 E-03 6.21 E-05 7.77 E-05 5.73 E-03 2.47 E-03 2.47 E-03 Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 9: Assessment of Radiation Doses Enclosure 3 (Continued):

Doses to Likely Most Exposed Member of the Public 2.Zndividual Dose Due to Gaseous Effluents{mrem/yr.)

A.Maximum Hypothetical Zndividual

-Exposure from Noble Gases, Particulates, Zodines, and Tritium ADULT Plume Ground Znhalation Vegetation Milk Goat Milk Meat a Poultry TOTAL 6.27 2.94 2.49 4.27 1.00 3.09 4.35 6.41 E-02 E-04 E-04 E-04 E-04 E-04 E-05 E-02 W.Body GZ-LLZ 6.27 E-02 2.94 E-04 2.51 E-04 4.61 E-04 1.02 E-04 3.09 E-04 5.04 E-05 6.41 E-02 Bone 6'7 E-02 2.94 E-04 0.00 E+00 0.00 E+00 0.00 E+00 0.00 K+00 0.00 K+00 6.30 E-02 6.27 2.94 2.49 4.25 1.00 3.09 4.30 6.41 E-02 E 04 E-04 E-04 E-04 E 04 E-05 E-02 Liver Kidney 6.27 E-02 2.94 E-04 2.49 E-04 4.23 E-04 1.00 E-04 3.09 E-04 4.26 E-05 6.41 E-02 6.27 2.94 2.49 4.23 1.00.3.09 4.26 6.41 E-02 E-04 E-04 E 04 E-04 E-04 E-05 E 02 Thyroid Lung 6.50 E-02 2.94 E-04 3.03 E-04 4.23 E-04 1.00 E-04 3.09 E-04 4.26 E-05 6.65 E-02 Skin 1.71 E-01 3.46 E-04 2.49 E-04 4.23 E-04 1.00 E-04 3.09 E-04 4.26 E-05 1.72 E-01 TEEN Plume Ground Znhalation Vegetation Milk Goat Milk Meat a Poultry TOTAL 6.27 2.94 2.51 5.04 1.31 4.03 2.61 6.43'-02 E-04 E-04 E-04 E-04 E-04 E-05 E-02 6.27 E-02 2.94 E-04 2.53 E-04 5.37 E-04 1.32 E-04 4.03 E-04 2.96 E-05 6.43 E-02 6.27 E-02 2.94 E-04 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 6.30 E-02, 6.27 2.94 2.50 5.00 1.30 4'.03 2.57" 6.43 E-02 E-04 E 04 E-04 E-04 E-04 E-05 E-02 6.27 2.94 2.50 4.97 1.30 4.03 2.54 6.43 E-02 E-04 E-04 E-04 E-04 E-04 E-05 E-02 6.27 2.94 2.50 4.97 1.30 4.03 2.54 6.43 E-02 E-04 E-04 E-04 E-04 E-04 E-05 E-02 6.50 E-02 2.94 E-04 3.29 E-04 4.97 E-04 1.30 E-04 4.03 E-04 2.54 E-05 6.67 E-02 1.71 E-01 3.46 E-04 2.50 E-04 4.97 E-04 1.30 E-04 4.03 E-04 2.54 E-05 1.73 E-01 CHZLD Plume Ground Znhalation Vegetation Milk Goat Milk Meat a Poultry TOTAL 6.27 2.94 2.22 7.89 2.07 6.36 3.18 6.49 E-02 E-04 E-04 E-04 E-04 E-04 E-OS E-02 6.27 E-02 2-94 E-04 2.22 E-04 8.02 E-04 2.07 E-04 6.36 E-04 3.28 E-05 6.49 E-02 6.27 2.94 0.00 0.00 0.00 0.00 0.00 6.30 E-02 E-04 E+00 E+00 E+00 E+00 E+00 E-02 6.27 2.94 2.21 7.80 2.06 6.36 3.11 6.48 E-02 E-04 E-04 E-04 E-04 E-04 E-05 E-02 6.27 2.94 2.21 7.75 2'6 6.36 3.07 6.48 E-02 E-04 E-04 E-04 E 04 E 04 E 05 E-02 6.27 2.94 2.21 7.75 2.06 6.36 3.07 6.48 E-02 E-04 E-04 E-04 E 04 E-04 E-05 E-02 6.50 2.94 2.85 7.75 2.06 6.36 3.07 6.73 E-02 E-04 E-04 E 04 E-04 E-04 E-05 E-02 1.71 E-01 3.46 E-04 2.21 E-04 7.75 E-04 2.06 E-04 6.36 E-04 3.07 E-05 1.73 E-01 ZNFANT Plume Ground Znhalation Milk Goat Milk TOTAL 6.27 E-02 2.94 E-04 1.27 E-04 3.13 E-04 9.66 E-04 6.44 E-02 6'7 E-02 2.94 E-04 1.28 E-04 3.13 E-04 9.66 E-04 6.44 E-02 6.27 2.94 0.00 0.00 0'.00 6.30 E-02 E-04 E+00 E+00 E+00 E-02 6.27 2.94 1.27 3.13 9.65 6.44 E-02 E-04 E-04 E-04 E-04 E-02 6.27 2.94 1.27 3.12 9.65 6.44 E-02 E 04 E 04 E-04 E-04 E-02 6.27 2.94 l.27 3.12 9.65 6.44 E-02 E-04 E 04 E-04 E-04 E-02 6.50 2.94 1.68 3.12 9.65 6.68 E-02 E-04 E-04 E-04 E 04 E-02 1.71 E-01 3.46 E-04 1.27 E-04 3.12 E-04 9.65 E-04 1.73 E-01 9/5

Semiannual Radioactive Effluent Release Report July 1, 1991 to-December 31, 1991 Appendix 9: Assessment of Radiation Doses Enclosure 3 (Continued):

Doses to Likely Most Exposed Member of the Public 2.Individual Dose Due to Gaseous Effluents (nrem/yr.)

B.Maximum Real Individual

-Exposure.from Noble Gases, Particulates, Zodines, and Tritium ADULT M.Body GI-LLI Bono Liver Kidnoy Thyroid Lung Skin Plume Ground Znhalation Vegetation TOTAL TEEN 1.53 E-02 1.20 E-04 5.95 E 05 1.03 E-04 1.56 E-02 1.53 E-02 1.2Q E-04" 6.01 E-05 1.17 E-04 1.56 E-02 1.53 E-02 1 2Q E-04 0.00 E+00 0.00 E+00 1.54 E-02 1.53 E-02 1.53 E-02 1.20 E-04 1.20 E-04 5.95 E-05 5.95 E-05 1.02 E-04 1.Ql E-04 1.56 E-02 1.56 E-02 1.53 E-02 1.20 E-04 5.95 E-05 1.01 E-04 1.56 E-02 1.59 E-02 1.20 E-04 7.22 E-05 1.01 E-04 1.62 E-02 4.17 E-02 1.42 E-04 5.95 E-05 1.01 E-04 4.20 E-02 Plume Ground Inhalation Vegetation 1.53 E-02 1.20 E-04 5.99 E-05 1.22 E-Q4 1.53 E-02 1.20 E-04 6.05 E-05 1.35 E-04 1.53 E-02 1.20 E-04 0.00 E+00 0.00 E+00 1.53 E-02 1.20 E-04 5.99 E-05 1.20 E 04 1.53 E-02 1.20 E-04 5.99 E-05 1.19 E-04 1.53 E-02 1.20 E-04 5.99 E-05 1.19 E-04 1.59 E-02 1.20 E-04 7.84 E-05 1.19 E-04 4.17 E-02 1.42 E-04 5.99 E-04 1.19 E-04 TOTAL 1.56 E-02 1.56 E-02 1.54 E-02 1.56 E-02 1.56 E-02 1.56 E-02 1.62 E-02 4.20 E-02 CHILD Plume Ground Znhalation Vegetation TOTAL INFANT 1.53 E-02 1.20 E-04 5.30 E-05 1.91 E-04 1.57 E-02 1.53 E-02 1.20 E-04 5.32 E-05 1.96 E-04 1.57 E-02 1.53 E-02 1.20 E-04 0.00 E+00 0.00 E+00 1.54 E-02 1.53 E-02 1.20 E-04 5.30 E-05 1.88 E-04 1.57 E-02 1.53 E-02 1.20 E-04 5.30 E-05 1.86 E-04 1.57 E-02 1.53 E-02 1.20 E-04 5.30 E-05 1.86 E-04 1~57 E-02 1.59 E-02 1.20 E-04 6.80 E-05 1.86 E-04 1.63 E-02 4.17 E-02 1~42 E-04 5.30 E-05 1.86 E-04 4.21 E-02 Plume Ground Inhalation 1.53 E-02 1.20 E-04 3.05 E~QS 1.53 E-02 1.20 E-04 3.05 E-05 1.53 E-02 1.20 E-04 0.00 E+00 1.53 E-02 1.20 E-04 3.05 E-05 1.53 E-02 1.20 E-04 3.05 E-05 1.53 E-02 1.20 E-04 3.05 E-05 1.59 E-02 1.20 E-04 4.00 E-'5 4.17 E-02 1.42 E-04 3.05 E-05 TOTAL 1.55 E-02 1.55 E-02 1.54 E-02 1.55 E-02 1.55 E-02 1.55 E-02 1.60 E-02 4.19 E-02 9/6

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 9: Assessment of Radiation Doses Enclosure 3 (Continued):

Doses to likely Most Exposed Member of the Public 3.Annual Air Dose (mrad)A.Maximum Hypothetical Zndividual:

Beta~2.35 E-01 Gamma~1.02 E-01 B.Maximum Real Zndividual: ,Beta~5.70 E-02 Gamma=2.49 E-02 4.Doses Due to Direct Radiation from the Harris Plant On-going environmental-TLD dose measurements show that the offsite Direct Radiation Dose is negligible.

9/.7

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 9: Assessment of Radiation Doses Enclosure 4: Major Assumptions Used to Calculate Radiation Doses 1.Doses Due to Liquid Effluents Dilution Factors Location Value Ex osure Pathwa s Harris Lake Cape Fear River Cape Fear River/Raven Rock Park 1.00 E+0 1 6.67 E+02 1.62 E+03 Shoreline, Swimming, Boating, Fish Consumption Shoreline, Drinking Water (for Harnett County, Lillington, Dunn, and Fayetteville)

Boating B.Populations Affected Location Value Ex osure Pathwa s Harris Lake Harnett County Dunn Intake Fayetteville Area Fuquay-Varina Holly Springs Harris Lake/Cape Fear River Cape Fear River/Raven Rock Park Raven Rock Park 1.10 E+05 4.53 E+04 1.67 E+04 1.40 E+05 5.36 E+03 9.08 E+02 person-hours persons persons persons persons persons 5.00 E+04 person-hours 4.40 E+05 person-hours 7.84 E+03 person-hours Shoreline, Swimming Drinking Water Drinking Water Drinking Water*Drinking Water*Drinking Water****Fishing Boating Shoreline*0**1 The Drinking Water values have been revised to show current usage and consumption.

The consumption values for Fuquay-Varina have been reduced by 1/2 to account for dual-supplied drinking water.: The consumption values for Holly Springs have been reduced by 1/4 to account for dual-supplied drinking water..C.Doses for"Activities Inside the Site Boundary" and the"Likely Most Exposed Member of the Public" use the Cape Fear River as the Drinking Water supply and Harris Lake as the source of all other liquid pathway doses.9/8

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 9: Assessment of Radiation Doses Enclosure 4 (Continued):

Major Assumptions Used to Calculate Radiation Doses Doses Due to Gaseous Effluents The 50 mile Zngestion Zone population is 1.47 E+06 persons.B.The Maximum Real Individual is located at 2897 meters (1.8 miles)in the NNE sector.This individual has a garden located at 2736 meters (1.7 miles)in the same sector.The garden location was used to determine the annual exposure.The Maximum Hypothetical Individual is located on the site boundary at 2140 meters in the SSW sector.D.For the Inside Site Boundary Individual, access time is assumed to be 400 hour0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />s/yr at 1207 meters (3/4 mile)in, the NNE sector from the plant, which is the closest accessible lake location.E.Concurrent meteorology is applied separately to batch and continuous release source terms.The dose commitment from each mode was summed to obtain annual dose.9/9

Seniannual Radioactive Effluent Release Report July 1, 1991 to Decenber 31, 1991 Appendix 9: Assessnent of-Radiation Doses Enclosure 3: Doses to Likely Host Exposed Henber of the Public Individual Dose Due to Liquid Effluents (nren/yr.)

ADULT Bone Liver W Body Thyroid Kidney Lung GI-LLI Skin Pish Drinking Shoreline Swinning Boating TOTAL 2.38 1.50 1.80 1.24 1.42 2.60 E-02 E-04 E-03 E<<04 E-04 E-02 3.99 1.31 1.80 1.24 1.42 5.50 E-02 E-02 E-03 E-04 E-04 E-02 2.93 1.31 1.80 1.24 1.42 4.45 E-02 E-02 E-03 E-04 E-04 E-02 1.43 E-03 1.29 E-02 1.80 E-03 1.24 E-04 1.42 E-04 1.64 E-02 1.40 1.29 1.80 1.24 1.42 2.89 E-02 E-02 E-03 E-04 E 04 E 02 5.65 E-03 1.29 E-02 1.80 E-03 1.24 E-04 1.42 E-04 2 06 E-02 1.22 1.46 1.80 1.24 1.42 2.89 E-02 E-02 E-03 E-04 E-04 E-02 2.12 E-03 2.12 E-03 TEEN Pish Drinking Shoreline Swi nni ng Boating TOTAL 2.52 0.00 1.01 1.86 2.07 3.57 E-02 E+00 E-02 E-04 E-04 E-02 4.08 E-02 0.00 E+00 1.01 E-02 1.86 E-04 2.07 E-04 5.13 E-02 1.IA E-02 0.00 E+00 1.01 E-02 1.86 E-04 2.07 E-04 2.77 E-02 1.11 E-03 0 F 00 E+00 1.01 E-02 l.86 E-04 2.07 E-04 1.16 E-02 1.40 0.00 l.01 1.86 2.07 2.45 E-02 E+00 E-02 E-04 E-04 E-02 6.18 E-03 0.00 E+00 1.01 E-02 1.86 E-04 2.07 E-04 1.66 E<<02 8.58 0.00 1.01 1.86 2.07 1~90 E-03 E+00 E-02 E-04 E-04 E-02 1.18 E-02 1.18 E-02 CHILD Pish Drinking Shoreline Swinning Boating TOTAL 3.15 0.00 2.10 6.21 7.77 ,3.37 E-02 E+00 E-03 E-05 E-05 E-02 3.60 0.00 2.10 6.21 7.77 3.82 E-02 E+00 E-03 E-05 E-05 E-02 7.83 E-03 0.00 E+00 2.10 E-03 6.21 E-05 7.77 E-05'.10 E-02 9.37 E-04 0.00 E+00 2.10 E-03 6.21 E-05 7.77 E-05 3.18 E-03 1.19 0.00 2.10 6.21 7.77 1.42 E-02 E+00 E-03 E-05 E-05 E-02 4-94 E-03 0.00 E+00 2.10 E-03 6.21 E-05 7.77 E-05 7.19 E-03 3.48 0.00 2.10 6.21 7-77 5.73 E-03 E+00 E-03 E-05 E-05 E-03 2.47 E-03 2.47 E-03 9/4 Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 9 Assessment of Radiation Doses Enclosure 3 (Continued):

Doses to Likely Most Exposed Member of the Public Individual Dose Due to Gaseous Effluents (nrem/yr.)

A.Maximum Hypothetical Individual

-Exposure from Noble Gases, Particulates, Zodines, and Tritium ADULT Plume Ground Inhalation Vegetation Milk Goat Milk Meat a Poultry TOTAL W.Body 6.27 E-02 2.94 E-04 2.49 E-04 4.27 E-04 F 00 E-04 3.09 E-04 4'5 E-05 6.41 E-02 6.27 2.94 2.51 4.61 1.02 3.09 5.04 6.41 E-02 E-04 E-04 E-04 E-04 E-04 E-05 E-02 GZ-LLI Bone 6.27 E-02 2.94 E-04 0 00 E+00 0.00 E+00 0 00 E+00 0.00 E+00 0 00 E+00 6.30 E-02 6.27 2.94 2.49 F 25 1.00 3.09 4.30 6.41 E-02 E-04 E-04 E-04 E-04 E-04 E-05 E-02 Liver 6.27 2.94 2.49 4.23 1.00 3.09 4'6 6.41 E-02 E-04 E-04 E-04 E-04 E-04 E-05 E-02 Kidney Thyroid 6.27 E-02 2.94 E-04 2.49 E-04 4.23 E-04 1.00 E-04 3.09 E-04 4.26 E-05 6.41 E-02 6.50 2.94 3.03 4.23 1.00 3.09 4.26 6.65 E-02 E 04 E-04 E 04 E-04 E-04 E-05 E-02 Lung Skin 1.71 E-01 3.46 E-04 2 49 E-04 4.23 E-04 1.00 E-04 3.09 E-04 4 26 E-05 1.72 E-01 TEEN Plume Ground Inhalation Vegetation Milk Goat Milk Meat a Poultry TOTAL CHILD Plume Ground ,Inhalation Vegetation Milk Goat Milk.Meat a Poultry TOTAL 6.27 E-02 2.94 E-04 2~51 E-04 5.04 E 04 1.31 E-04 4.03 E-04 2.61 E-05 6.43'-02 6.27 E-02 2.94 E-04 2.22 E-04 7.89 E-04 2.07 E-04 6.36 E-04 3.18 E-05 6.49 E-02 6'7 2.94 2.53 5.37 1.32 4.03 2.96 6.43 6.27 2.94 2.22 8.02 2.07 6.36 F 28 6.49 E-02 E 04 E-04 E-04 E-04 E-04 E-05 E-02 E-02 E-04 E 04 E-04 E-04 E-04 E-05 E-02 6.27 E-02 2.94 E-04 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 6.30 E-02 6.27 E-02 2.94 E-04 0.00 E+00 0.00 E+00 0.00 E+00 0 00 E+00 0.00 E+00 6.30 E-02 6.27 2.94 2.50 5.00 1.30 4.03 2.57 6.43 6.27 2.94 2.21 7.80 2.06 6.36 3.11 6.48 E-02 E-04 E-04 E-04 E-04 E 04 E-05 E-02 E-02 E-04 E-04 E-04 E-04 E-04 E-05 E-02 6.27 2.94 2.50 4.97 1.30 4.03 2.54 6.43 6.27 2.94 2.21 7.75 2.06 6.36 3.07 6.48 E-02 E-04 E-04 E-04 E-04 E-04 E-05 E-02 E-02 E-04 E-04 E-04 E-04 E 04 E-05 E-02 6.27 E-02 2.94 E-04 2.50 E-04 4.97 E-04 1.30 E-04 4.03 E-04 2.54 E-05'6.43 E-02 6.27 E-02 2.94 E-04 2.21 E-04 7.75 E-04 2.06 E-04 6.36 E-04 3.07 E-05 6'8 E-02 6.50 2.94 3.29 4.97 1.30 4.03 2.54 6.67 6.50 2.94 2.85 7.75 2.06 6.36 3.07 6.73 E-02 E-04 E 04 E-04 E 04 E-04 E-05 E-02 E-02 E-04 E-04 E-04 E-04 E 04 E 05 E-02 1.71 E-01 3.46 E-04 2 50 E-04 4.97 E-04 1.30 E-04 4.03 E-04 2.54 E-05 1.73 E-01 1.71 E-01 3.46 E-04 2.21 E-04 7.75 E 04 2.06 E-04 6.36 E-04 3.07 E-05 1.73 E-01 INFANT Plume Ground Znhalation Milk Goat Milk TOTAL 6'7 E-02 2.94 E-04 1.27 E-04 3.13 E 04 9.66 E-04 6.44 E-02 6.27 2.94 1.28 3.13 9.66 6.44 E-02 E-04 E-04 E-04 E-04 E-02 6.27 E-02 2.94 E-04 0.00 E+00 0.00 E+00 0.00 E+00 6.30 E-02 6.27 2.94 1.27 3.13 9.65 6.44 E-02 E-04 E 04 E-04 E-04 E-02'6.27 2.94 1.27 3.12 9.65 6.44 E-02 E-04 E-04 E-04 E-04 E-02 6'7 E-02 2'4 E-04 1.27 E-04 3.12 E-04 9.65 E-04 6.44 E-02 6.50 2.94 1.68 3.12 9.65 6.68 E-02 E-04 E-04 E-04 E-04 E-02 1.71 E-01 3.46 E-04 1.27 E-04 3.12 E-04 9.65 E-04 1.73 E-01 9/5 Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 9: Assessment of Radiation Doses Enclosure 3 (Continued):

Doses to Likely Most Exposed Member of the Public 2.Individual Dose Due to Gaseous Effluents (mrem/yr.)

B.Maximum Real Individual

-Exposure from Noble Gases, Particulates, Zodines, and Tritium ADULT ll Body'Z-LLZ Bone Liver Kidney Thyroid Lung Skin Plume Ground Znhalation Vegetation 1.53 E-02 1~20 E-04 5.95 E-OS 1.Q3 E-04 1.53 E-02 1~20 E-04 6.01 E-05 1.17 E-04 1.53 E-02 1.20 E-04 0.00 E+00 0.00 E+00 1.53 E-02 1.20 E-04 5.95 E 05 1.02 E-04 1.53 E-02 1.20 E-04 5.95 E-OS 1.01 E-04 1.53 E-02 1.20 E-04 5.95 E-05 1.01 E-04 1.59 , 1.20 7.22 1~01 E-02 E-04 E-05 E-04 4.17 E-02 1.42 E-04 5.95 E-05 1.01 E-04 TOTAL TEEN Plume Ground Inhalation Vegetation TOTAL 1.56 E-02 1.53 E 02 1.20 E 04 5.99 E-QS 1.22 E-04 1.56 E-02 1.56 E-02 1.53 E-02 1.20 E-04 6.05 E-05 1.35 E-04 1.56 E-02 1.54 E-02 1.53 E-02 1.20 E-04 0.00 E+00 0.00 E+QO 1.54 E-02 1.56 E-02 1.53 E-02 1.20 E-04 5.99 E-05 1.20 E 04 1.56 E-02 1.56 E-02 1.53 E-02 1.20 E 04 5.99 E-05 1.19 E-04 1.56 E-02 1.56 E-02 1.53 E-02 1.20 E-04 5.99 E-05 1.19 E<<04 1.56 E-02 1.62 E-Q2 1.59 E-02 1.20 E-04 7.84 E-05 1.19 E-04 1.62 E-02 4.20 E-02 4.17 E-02 1.42 E-04 5.99 E-04 1.19 E-04 4.20 E-02 CHILD Plume Ground Inhalation Vegetation TOTAL IHPAHT 1.53 E-02 1.20 E-04 5.30 E-05 1.91 E-04 1~57 E 02 1.53 E-02 1.20 E-04 5.32 E-OS 1~96 E-04 1.57 E-02 1.53 E-02 F 20 E-04 0.00 E+00.0.00 E+00 1.54 E-02 1.53 E-02 1.20 E-04 5.30 E-05 1.88 E-04 1.57 E-02 1.53 E-02 1.20 E-04 5.30 E-OS 1.86 E-04 1.57 E-02 1.53 E-02 1.20 E-04 5.30 E-05 1.86 E-04 1.57 E-02 1.59 E-02 1.20 E-04 6.80 E-05 1.86 E 04 1.63 E-02 4.17 E-02 1.42 E-04 5.30 E-OS 1 86 E-04 4.21 E-02 Plume Ground Inhalation TOTAL 1.53 E-02 1.20 E 04 3.05 E~OS 1.55 E-02 1.53 E-02 1.20 E-04 3.05 E-05 1.55 E-02 1.53 E-02 1 20 E-04 0.00 E+00 1.54 E-02 1.53 E-02 1.20 E 04 3.05 E-05 1.55 E-02 1.53 E-02 1.20 E-04 3 05 E-05 1.55 E-02 1.53 E-02 1.20 E-04 3.05 E-05 1.55 E-02 1.59 E-02 1.20 E-04 4.00 E-05 1.60 E-02 4.17 E-02 1.42 E-04 3.05 E-OS 4.19 E-02 9/6 Seniannual Radioactive Effluent Release Report July 1, 1991 to Decenber 31, 1991 Appendix 9: Assessnent of Radiation Doses Enclosure 3 (Continued):

Doses to Likely Host Exposed Heaber of the Public 3.Annual Air Dose (nrad)A.Maxinun Hypothetical Zndividual:

B.Maxinun Real Individual:

Beta~2.35 E-01.Beta~5.70 E-02 Ganna~1.02 E-01 Ganja~2.49 E-02 4.Doses Due to Direct Radiation fron the Harris Plant On-going environnental TLD dose neasurenents show that the offsite Direct Radiation Dose is negligible.

9/7 Seniannual Radioactive Effluent Release Report July 1, 1991 to Decenber 31, 1991 Appendix 9: Assessnent of Radiation Doses Enclosure 4: Major Assunptions Used to Calculate Radiation Doses 1.Doses Due to Liquid Ef f luents Dilution Factors Location Value Ex osure Pathwa s Harris Lake Cape Fear River Cape Fear River/Raven Rock Park 1.00 E+01 6.67 E+02 1.62 E+03 Shoreline, Swinning, Boating, Fish Consunption Shoreline, Drinking Water{for Harnett County, Lillington, Dunn, and Fayetteville)

Boating B.Populations Affected Location Value Ex osure Pathwa s Harris Lake Harnett County Dunn Zntake Fayetteville Area Fuquay-Varina Holly Springs Harris Lake/Cape Fear River Cape Fear River/Raven Rock Park Raven Rock Park 1.10 E+05 4.53 E+04 1.67 E+04 1.40 E+05 5.36 E+03 9.08 E+02 person-hours persons persons persons persons persons 7.84 E+03 person-hour:.

5.00 Et04 person-hours 4.40 E+05 person-hours Shoreline, Swinning Drinking Water Drinking Water Drinking Water Drinking Water Drinking Water Fishing Boating Shoreline*ee The Drinking Water values have been revised to show current usage and consunption.

The consunption values for Fuquay-Varina have been reduced by 1/2 to account for dual-supplied drinking water.The consunption values for Holly Springs have been reduced by 1/4 to account for dual-supplied drinking water..C~Doses for"Activities Znside the Site Boundary" and the"Likely Most Exposed Meaber of the Public" use the Cape Fear River as the Drinking Water supply and Harris Lake as the source of all other liquid pathway doses.9/8

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 9: Assessment of Radiation Doses Enclosure 4 (Continued):

Major Assumptions Used to Calculate Radiation Doses'Doses Due to Gaseous Effluents The 50 mile Ingestion tone population is 1.47 E+06 persons.B.The Maximum Real Individual is located at 2897 meters ("1.8 miles)in the HHE sector.This individual has a garden located at 2736 meters (1.7 miles)in the same sector.The garden location was used to determine the annual exposure.C.The Maximum Hypothetical Individual is located on the site boundary at 2140 meters in the SSW sector.D.Por the Inside Site Boundary Individual, access time is assumed to be 400 hour0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />s/yr at 1207 meters (3/4 mile)in the HHE sector from the plant, which is the closest accessible lake location.Concurrent meteorology is applied separately to batch and continuous release source terms.The dose commitment from each mode was summed to obtain annual dose.9/9 l-l t~f

Retrieved from "https://kanterella.com/w/index.php?title=ML18010A547&oldid=1022924"