ML18010A547

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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)
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Text

,OS2 SHEARON 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 4/2 PDR ADOCK 05000400 R PDR

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 ( W

+ 21BFg) DFg (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 Rev. 3.0 4/3

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 Rev. 3.0 4/4

OS2 Deleted by AC 3/4 DCM/ODC-2 2-18a Rev. 3.0 4/5

<< H 0

C.

OS2 Sheet 1 of 2 TABLE 2.2-1 A;, VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT Ag~ =

1. 14E+05 ( 730 + 21BFg) DFg~

(mrem/hr per micro-Ci/ml)

Nuclide Bone Liver Trod T~hroid ~Kidne ~Lun GI-LLI H-3 0.008+00 8.508-01 8.508-01 8.5081 8.508%1 8.50M)1 8.50841 ) ac3/5 C-14 , 3.13E+04 6.268+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 Na-24 P-32 4.178+02 4.628+07 4.17E+02 2.87E+06 4.17E+02 1.798+06 4.17E+02 0.008+00 4.17E+02 O.OOE+00 4.17E+02 0.008+00 4.17E+02 5.208+06 its Cr-51 0.008+M 0.008+00 1.298+00 7.718%1 2.848%1 1.71E+00 3.23E+02 Mn-54 O.OOE+00 4.40E+03 8.40E+02 0.008+M 1.318+03 0.008+00 1.35E+04 Mn-56 O.OOE+00 1.11E+02 1.978+01 0.008+00 1.418+02 0.00E+00 3.54E+03 Fe-55 6.75E+02 4.66E+02 1.09E+02 O.OOE+00 0.008+00 2.608+02 2.678+02 Fe-59 1.06E+03 2.50E+03 9.59E+02 0.008+00 O.OOE+00 6.998+02 8.34E+03 Co-58 0.00E+00 9.36E+01, 2.10E+02 0.008+00 O.OOE+00 0.008+00 1.90E+03 Co-60 0.00E+00 2.69E+02 5.93E+02 0.008+00 0.008+00 0.008+00 5.058+03 Ni43 3.19E+04 2.21E+03 1.07E+03 0.008+00 O.OOE+00 0.008+00 4.618+02 Ni-65 1.308+02 1.688+01 7.688+00 O.OOE+00 O.OOE+00 O.OOE+00 4.27E+02 Cu44 0.008+00 1.05E+01 4.91E+00 O.ME+00 2.648+01 O.OOE+00 8.928+02 Zn-65 2.328+04 7.38E+04 3.34E+04 O.OOE+00 4.94E+04 O.OOE+00 4.658+04 Zn49 4.948+01 9A48+01 6.578+00 0.008+00 6.14E+Ol O.OOE+00 1.428+01 Br 83 0.008+00 0.00E+00 4.07E+01 O.OOE+00 0.00E+00 0.008+M 5.86E+01 Br 84 O.OOE+00 0.008+00 5.278+01 0.008+00 O.OOE+00 O.MB+00 4.14844 Br85 0.008+00 0.008+00 2.16E+00 O.OOE+00 O.OOE+00 0.00E+00 1.008-15 Rb-86 O.OOE+00 1.01E+05 4.718+04 O.OOE+00 O.OOE+00 0.008+00 1.99E+04 Rb-88 0.008+00 2.908+02 1.54E+02 0.008+00 0.008+00 O.OOE+00 4.018%9 Rb-89 0.008+00 1.928+02 1.358+02 0.00E+00 O.OOE+00 O.OOE+00 1.128-11 Sr 89 2.40E+04 0.00E+00 6.878+02 O.OOE.+00 O.OOE+00 O.OOE+00 3.84E+03 Sr-90 5.89E+05 O.OOE+00 1.45E+05 0.008+00 0.008+00 O.OOE+00 1.708+04 Sr-91 4.418+02 O.MB+00 1.788+01 0.008+M 0.008+00 0.008+M 2.108+03 Sr-92 1.67E+02 0.008+00 7.238+00 0.008+00 0.00E+00 O.ME+00 3.31E+03 Y-90 6.33M)1 O.OOE+M 1.708%2 O.OOE+00 O.MB+00 O.OOE+00 6.718+03 Y-91m 5.988%3 O.OOE+M 2.328<4 O.OOE+00 0.008+M O.OOE+00 1.768<2 Y-91 9.28E+00 0.00E+00 2.488<1 0.008+00 0.008+00 0.008+00 5.118+03 Y-92 5.568%2 0.008+00 1.638%3 O.OOE+00 O.OOE+M O.OOE+M 9.74E+02 Y-93 1.768<1 0.00E+00 4.87E-03 0.008+00 0.008+M 0.008+00 5.598+03 iQs-Zr-95 4.218%1 1.3581- 9.148%2 O.OOE+00 2.128%1 0.008+M 4.28E+02 Zr-97 2.338%2 4.69E-03 2.15E-03 0.008+00 7.098%3 0.00E+00 1.458+03 Nb-95 4.478+02 2.49E+02 1.348+02 0.00E+00 2.468+02 0.00E+00 1.518+06 Mo-99 0.008+00 1.29E+02 2.458+01 0.008+00 2.92E+02 0.008+00 2.998+02 Tc-99m 1.038%2 2.92E-02 3.728%1 0.008+00 4.448%1 1.438-02 1.738+01 Tc-101 1.068%2 1.538%2 1.508<1 0.008+00 2.768%1 7.838%3 4.608-14 Ru-103 5.538+00 0.00E+00 2.38E+00 0.008+00 2.11E+01 O.OOE+00 6.46E+02 Ru-105 4.60M)1 O.OOE+00 1.828<1 O.ME+00 5.95E+00 O.MB+00 2.82E+02 DCM/ODC-2 2-26 Rev. 3.0 4/6

av'>> 1 0-L'g e

'w4

OS2 Table 3.2-2 Dist ance to the Nea rest Special Locations

'for the S hearon Harris Nuclear Power P lant (miles)*

(Comparison of 1990/1991 Da ta)

Residence Milk Animal Garden Meat Animal Exclusion Sector Boundary 1990 1991 1990 1991 1990 1991 1990 1991 N

NNE NE

'.33 1.32 1.33 2.2 1.8 2.3 2.2 1.8 2.3 2.2 4.6 2.2 2.2 1.7 2.3 2.2 1.7 2.3 2.2 3.5 2.3 2.2 3.5 2'

ENE 1.33 2.0 3.6 3.6 3' E 1 33

~ 1.9 1.9 4.7 4,7 2.2 2.2 ESE 1.33 2.7 2.7 2.7 4.4 4,4 SE 1.33 4.3 4.3 4.3 4.4 4.3 SSE 1.33 4,4 4.

1.36 6'.9 SSW 1.33 3.9 3.9 3.9

'.8 SW 1.33 2.8 2.8 2.8 WSW 1.33 4.3 4.3 4 3

~ 4.3 4.3 1.33 2.8 2.8 2.9 2.9 2.9 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 Rev. 3.0 4/7

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.

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Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 6 : Additional Technical Specification Responsibilities Enclosure 1 : Inoperability of Liquid Effluent Monitors Technical Specification 3.3.3.10, Action b Monitors Out-of-Service > 30 Days During the Report Period Days Effluent Monitor Inop Reason for Inoperability FT-21WL-6119 Both of these flow indicators have Vaste Monitor Tank / Paste been inoperable becaus'e of a scaling Evaporator Condensate Tank 184 problem between the readout and the Discharge Flow Rate Monitor associated measuring orifice. A modification to correct this has been FT-*1WL-6193 completed and the monitors will be Treated Laundry & Hot returned to service following Shower Tanks Discharge Flow calibration.

Rate Monitor

Semiannual Radioactive Effluent Release Report July 1, 1991 to December 31, 1991 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 2 : Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service ) 30 Days During the Report Period Days Effluent Monitor Inop Reason for Inoperability PNL-21AV-3509-SA Problems with calibration of flow PNL-21AV-3509-1SA measurement system resulting in Plant Vent Stack Plow Rate 184 discrepancies between actual and Monitor expected flow rates. Modification initiated to correct'.

RM-01TV-3536-1 Moisture interferences with the flow Turbine Building Vent Stack measurement system resulting in 3A Flow Rate Monitor 184 discrepancies betveen actual and expected flow rates. Modification initiated to correct.

PNL-1WV-3546 6 Problems with calibration of flow PNL-1WV-3546-1 measurement system resulting in WPB Vent Stack 5 Plow Rate 184 discrepancies between actual and Monitor expected flov rates. Modification initiated to correct.

PNL-1WV-3547 6 Problems with calibration of flow PNL-1WV-3547-1 measurement system resulting in WPB Vent Stack 5A Plow Rate 184 discrepancies between actual and Monitor 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 Enclosure 2 : Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service > 30 Days During the Report Period Days Effluent Monitor Inop Reason for Inoperability HAIC-21WG-1118A A modification to improve the Waste Gas Recombiner "A" 68 reliability of the waste gas Outlet Gas Hydrogen Monitor analyzers (A-train) was ongoing and completed; During the periods of OARC-21WG-1119A inoperability, the B-train components Waste Gas Recombiner "A" were operable.

Outlet Gas Oxygen Monitor OAI-21WG-1101 This monitor was included in the A-Waste Gas Compressor 68 train modifications.

Discharge Oxygen Monitor HAIC-21WG-1118B A modification to improve the Waste Gas Recomb'incr "B" reliability of the waste gas Outlet Gas Hydrogen Monitor analyzers (B-train) was begun. The B-train components were not made OARC-21WG-1119B operable until the A-train components Waste Gas Recombiner "B" were operable. The modification is Outlet Gas Oxygen Monitor 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 Enclosure 3 : 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 Enclosure 4 : 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.

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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 ~ The Radwaste Demineralization System was changed from an alternate process system to the primary process system for liquid radioactive waste.

2. The RO/Evaporator systems were designated as alternate process systems to be place in long term shutdown.

3~ 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.

4. 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.

6. 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.

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.

2~ . 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.

4, 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.

6. 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 Limit 10mrem/year Predicted 2.10 mrem 1988 Prior to change 0.49 mrem 1991 After change 0.017 mrem Fission & Activation Products Release I Predicted 1.00 curies 1988 Prior to change 0.08 curies 1991 After change 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 2210 cubic feet 1988 Prior to change 4328 cubic feet 1991 After change 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.

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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 2.29 E-02 3.55 E-02 2.19 E-02 1.15 E-03 1.23 E-02 5.04 E-03 9.09 E-03 0.00 E+00 Conn Fish 0.00 E+00 0.00 E+00 0.00 E+00 0 00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Sport Znvert 0.00 E+00 0.00 E+00 0.00 .E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Conn Invert 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 ~ 0.00 E+00 0.00 K+00 0.00 E+00 0.00 E+00 Drinking Water 3.92 E-03 2.66 E-01 2.66 E-01 2. 61 E-01 2.61 E-01 2. 61 E-01 2.91 E-01 0.00 E+00 Shoreline 1.83 E-02 1.83 E-02 1.83 E-02 1.83 E>>02 1.83 E-02 1. 83 E-02 1.83 E-02 2.15 E-02 Swinning 1. 14 E-04 1.14 E-04 1.14 E 04 1.14 E-04 1.14 E-04 1. 14 E-04 1.14 E-04 0.00 E+00 Boating 5.80 E-05 5.80 E-05 5.80 E-QS 5.80 E-05 5.80 E-05 5.80 E-05 5.80 E-05 Irri Veg 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0 00 0.00 E+00 E+00 Zrri Leafy Veg 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Zrri Milk 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Zrri Meat 0.00 E+00 0.00 E+00 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 1.67 E-01 1.67 E-01 1. 67 E-01 1. 67 E-01 1.67 E-01 1. 67 E-01 1. 77 E-01 5.72 E-01 Ground 6.68 E-04 6 68 E-04 6.68 E-04 6.68 E-04 6.68 E-04 6.68 E-04 6.68 E-04 7.86 E-04 Inhalation 1.40 E-03 1.'41 E-03 0.00 E+00 1.40 E-03 1.40 E-03 1.40 E-03 1.62 E-03 1.40 E-03 Vegetation 4.32 E-04 4.42 E-04 0.00 E+00 4.30 E-04 4.29 E-04 4.29 E-04 4.29 E-04 4.29 E 04 Cow Milk 1.69 E-04 1.69 E-04 0.00 E+00 1. 68 E-04 1.68 E-04 1.68 E-04 1.68 E-04 1.68 E-04 Meat a Poultry 2.08 E 04 2. 12 E-04 0.00 E+00 2.07 E-04 2 06 E-04 2.06 E-04 2.06 E-04 2.06 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.)

Bone Liver W. Body Thyroid Kid11e'y Lung GI-LLI Skin ADULT Fish 2.38 E-02 3.99 E-02 2.93 E-02 1.43 E-03 1.40 E-02 5.65 E-03 1.22 E-02 Shoreline 1.80 E-03 1.80 E-03 1.80 E-03 1.80 E-03 1.80 E-03 1.80 E-03 1.80 E-03 2.12 E-03 Swimming 1.24 E-04 1.24 E-04 1.24 E-04 1.24 E-04 1-24 E-04 1.24 E-04 1.24 E-04 Boating 1.42 E-04 1.42 E-04 1.42 E-04 1.42 E-04 1 42 E-04

~ 1.42 E-04 1.42 E-04 TOTAL 2.59 E-02 4.20 E-02 3.14 E-02 3.50 E-02 1.60 E-02 7.70 E-03 1.43 E-02 2.12 E-03 TEEN Fish 2.52 E-02 4.08 E-02 1.73 E-02 1. 11 E-03 1.40 E-02 6.18 E-03 8. 58 E-03 Shoreline 1.01 E-02 1. 01 E-02 1.01 E-02 1.01 E-02 1.01 E-02 1.01 E-02 1.01 E-02 1. 18 E-02 Swimming 1.86 E-04 1.86 E-04 1.86 E-04 1.86 E-04 1.86 E-04 1.86 E-04 1.86 E-04 Boating 2.07 E-04 2.07 E-04 2 07 E 04 2.07 E-04 2.07 E-04 2.07 E-04 2.07 E-04 TOTAL 3 '7 E-02 5. 13 E-02 2.77 E-02 1.16 E-02 2.45 E-02 1.66 E-02 1.90 E-02 1. 18 E-02 CHILD Fish 3.15 E-02 3.60 E-02 7.83 E-03 9.37 E-04 1.19 E-02 4.94 E-03 3.48 E-03 Shoreline 2.10 E-03 2.10 E-03 2. 10 E-03 2. 10 E-03 2. 10 E-03 2.10 E-03 2.10 E-03 2.47 E-03 Swimming 6.21 E-05 6. 21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 Boating 7.77 E-05 7.77 E-05 7.77 E-05 7.77 E-05 7.77 E-05 7.77 E-05 7.77 E-05 TOTAL 3.37 E-02 3.82 E-02 1. 10 E-02 3. 18 E-03 1.42 E-02 7.19 E-03 5.73 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.)

W. Body GZ-LLZ Bone Liver Kidney Thyroid Lung Skin ADULT Plume 4.78 E-03 4.78 E-03 4.78 E-03 4.78 E-03 4.78 E-03 4.78 E-03 4.95 E-03 1.29 E-02 Ground 4.37 E-05 4.37 E-05 4.37 E-05 4.37 E-05 4.37 E-05 4.37 E-05 4.37 E-05 5.14 E-05 Inhalation 1.73 E-05 1.75 E-05 0 00 E+00 1.73 E-05 1.73 E-05 1.73 E-05 2. 12 E-05 1.73 E-05 TOTAL 4.84 E-03 4.84 E-03 4.83 E-03 4.84 E-03 4.84 E-03 4.84 E-03 5.02 E-03 1.29 E-02 TEEN Plume 4.78 E-03 4.78 E-03 4.78 E-03 4:78 E-03 4.78 E-03 4.78 E-03 4.95 E-03 1.29 E-02 Ground 4.37 E-05 4.37 E-05 4.37 E-05 4.37 E-05 4.37 E-05 4.37 E-05 4.37 E-05 5. 14 E-05 Inhalation 1.74 E-05 1.75 E-05 F 00 E+00 1.74 E-05 1.74 E-05 1.74 E-05 2.31 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 4.78 E-03 4.37 E-05 4.78 E-03 4.37 E-05 4.78 E-03 4.37 E-05 4 '8 E-03 4.37 E-05 4.78 E-03 4.78 E-03 4.95 E-03 1.29 E-02 Ground 4.37 E-05 4.37 E-05 4.37 E-05 5.14 E-05 Inhalation 1.54 E-05 1.54 E-05 0.00 E+00 1.54 E-05 1.54 E-05 1.54 E-05 "2.00 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 4.78 E-03 4.78 E-03 4.78 E-03 4.78 E-03 4.78 E-03 4.78 E-03 4.95 E-03 1.29 E-02 Ground 4.37 E-05 4.37 E-05 4,37 E-05 4.37 E-05 4.37 E-05 4.37 E-05 4.37 E-05 5. 14 E-05 Inhalation 8.84 E-06 8.85 E-06 0.00 E+00 8.84 E-06 8.83 E-06 8.83 E-06 1.18 E-05 8.83 E-06 TOTAL 4.83 E-03 4.83 E-03 4.83 E-03 4.83 E-03 4.83 E-03 4.83 E-03 5. 01 E-03 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.)

Bone Liver W. Body Thyroid Lung GI-LLI Skin ADULT Fish 2.38 E-02 3.99 E-02 2.93 E-02 1.43 E-03 1. 40 E-02 5.65 E-03 1.22 E-02 Drinking 1.50 E-04 1.31 E-02 1.31 E-02 1.29 E-02 1.29 E-02 1.29 E-02 1.46 E-02 Shoreline 1.80 E-03 1.80 E-03 1.80 E-03 1.80 E-03 1.80 E-03 1.80 E-03 1.80 E-03 2.12 E-03 Swimming Boating 1.24 1.42 E-04 E-04 1.24 E-04 1.24 E-04 1 ~ 24 E-04 1 ~ 24 E-04 l. 24 E-04 1.24 E-04 1.42 E-04 1.42 E-04 1.42 E-04 1.42 E-04 1.42 E-04 1.42 E-04 TOTAL 2.60 E-02 5.50 E-02 4.45 E-02 1.64 E-02 2.89 E-02 2.06 E-02 2.89 E-02 2.12 E-03 TEEN Fish Drinking 2.52 0.00 E-02 4.08 E-02 1.73 E-02 l. 11 E-03 1.40 E-02 6.18 E-03 8.58 E-03 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Shoreline 1. 01 E-02 1.01 E-02 1. 01 E-02 1.01 E-02 1. 01 E-02 1.01 E-02 1. 01 E-02 1.18 E-02 Swimming 1.86 E-04 1.86 E-04 1. 86 E-04 1.86 E-04 1.86 E-04 1.86 E-04 1.86 E-04 Boating 2.07 E-04 2.07 E-04 2.07 E-04 2.07 E-04 2.07 E-04 2.07 E-04 2.07 E-04 TOTAL 3.57 E-02 5. 13 E-02 2.77 E-02 1.16 E-02 2.45 E-02 1.66 E-02 1.90 E-02 1.18 E-02 CHILD Fish Drinking

3. 15 0.00 E-02 E+00 3.60 0.00 E-02 7.83 0.00 E-03 9.37 0.00 E-04 l.

0.00 19 E-02 4.94 E-03 3.48 E-03 E+00 E+00 E+00 E+00 0.00 E+00 0.00 E+00 Shoreline 2. 10 E-03 2.10 E-03 2.10 E-03 2. 10 E-03 2.10 E-03 2.10 E-03 2.10 E-03 2.47 E-03 Swimming 6.21 E-05 6. 21 E-05 6. 21 E-05 6. 21 E-05 6. 21 E-05 6.21 E-05 6. 21 E-05 Boating 7.77 E-05 7.77 E-05 7.77 E-05 7.77 E-05 7.77 E-05 7.77 E-05 7.77 E-05 TOTAL 3.37 E-02 3.82 E-02 1.10 E-02 3.18 E-03 1.42 E-02 7.19 E-03 5.73 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 W. Body GZ-LLZ Bone Liver Kidney Thyroid Lung Skin ADULT Plume Ground 6.27 2.94 E-02 E-04 6.27 2.94 E-02 E-04 6 '7 2.94 E-02 E-04 6.27 2.94 E-02 6.27 E-02 6.27 E-02 6.50 E-02 1.71 E-01 E 04 2.94 E-04 2.94 E-04 2.94 E-04 3.46 E-04 Znhalation 2.49 E-04 2.51 E-04 0.00 E+00 2.49 E-04 2.49 E-04 2.49 E-04 3.03 E-04 2.49 E-04 Vegetation 4.27 E-04 4.61 E-04 0.00 E+00 4.25 E-04 4.23 E-04 4.23 E 04 4.23 E-04 4.23 E-04 Milk 1.00 E-04 1.02 E-04 0.00 E+00 1.00 E-04 1.00 E-04 1.00 E-04 1.00 E-04 1.00 E-04 Goat Milk 3.09 E-04 3.09 E-04 0.00 K+00 3.09 E 04 3.09 E-04 .3. 09 E-04 3.09 E-04 3.09 E-04 Meat a Poultry 4.35 E-05 5.04 E-05 0.00 K+00 4.30 E-05 4.26 E-05 4.26 E-05 4.26 E-05 4.26 E-05 TOTAL 6.41 E-02 6. 41 E-02 6.30 E-02 6.41 E-02 6.41 E-02 6.41 E 02 6.65 E-02 1.72 E-01 TEEN Plume 6.27 6.27 E-02 6.27 E-02 6.27 E-02 6.27 E-02 6.27 E-02 6.50 E-02 1.71 E-01 Ground 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 3.46 E-04 Znhalation 2.51 E-04 2.53 E-04 0.00 E+00 2.50 E 04 2.50 E-04 2.50 E-04 3.29 E-04 2.50 E-04 Vegetation 5.04 E-04 43'-02 5.37 E-04 0.00 E+00 5.00 E-04 4.97 E-04 4.97 E-04 4.97 E-04 4.97 E-04 Milk 1.31 E-04 1.32 E-04 0.00 E+00 1.30 E-04 1.30 E-04 1.30 E-04 1.30 E-04 1.30 E-04 Goat Milk 4.03 E-04 4.03 E-04 0.00 E+00 4'. 03 E-04 4.03 E-04 4.03 E-04 4.03 E-04 4.03 E-04 Meat a Poultry 2.61 E-05 2.96 E-05 0.00 E+00 2.57 E-05 2.54 E-05 2.54 E-05 2.54 E-05 2.54 E-05

6. E-02 "

TOTAL 6.43 E-02 6.30 E-02, 6.43 E-02 6.43 E-02 6.43 E-02 6.67 E-02 1.73 E-01 CHZLD Plume 6.27 E-02 6.27 E-02 6.27 E-02 6.27 E-02 6.27 E-02 6.27 E-02 6.50 E-02 1. 71 E-01 Ground 2.94 E-04 2-94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 3.46 E-04 Znhalation 2.22 E-04 2.22 E-04 0.00 E+00 2.21 E-04 2.21 E-04 2.21 E-04 2.85 E-04 2.21 E-04 Vegetation 7.89 E-04 8.02 E-04 0.00 E+00 7.80 E-04 7.75 E-04 7.75 E-04 7.75 E 04 7.75 E-04 Milk Goat Milk 2.07 6.36 E-04 E-04 2.07 E-04 6.36 E-04 0.00 0.00 E+00 2.06 6.36 E-04 E-04 2 '6 6.36 E 04 2.06 6.36 E 04 E-04 2.06 E-04 2.06 E-04 E+00 E 04 6.36 E-04 6.36 E-04 Meat a Poultry 3.18 E-OS 3.28 E-05 0.00 E+00 3.11 E-05 3.07 E 05 3.07 E-05 3.07 E-05 3.07 E-05 TOTAL 6.49 E-02 6.49 E-02 6.30 E-02 6.48 E-02 6.48 E-02 6.48 E-02 6.73 E-02 1. 73 E-01 ZNFANT Plume Ground 6.27 2.94 E-02 E-04 6 '7 2.94 E-02 E-04 6.27 2.94 E-02 E-04 6.27 E-02 6.27 E-02 6.27 E-02 6.50 E-02 1. 71 E-01 2.94 E-04 2.94 E 04 2.94 E-04 2.94 E-04 3.46 E-04 Znhalation Milk 1.27 3.13 E-04 E-04 1.28 3.13 E-04 E-04 0.00 0.00 E+00 1.27 E-04 E-04 1.27 E 04 l. 27 E 04 1.68 E-04 1.27 E-04 E+00 3.13 3.12 E-04 3. 12 E-04 3.12 E-04 3.12 E-04 Goat Milk 9.66 E-04 9.66 E-04 0'. 00 E+00 9.65 E-04 9.65 E-04 9.65 E-04 9.65 E 04 9.65 E-04 TOTAL 6.44 E-02 6.44 E-02 6.30 E-02 6.44 E-02 6.44 E-02 6.44 E-02 6.68 E-02 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 M. Body GI-LLI Bono Liver Kidnoy Thyroid Lung Skin ADULT Plume 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.59 E-02 4.17 E-02 Ground 1.20 E-04 1.2Q E-04" 1 2Q E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.42 E-04 Znhalation 5.95 E 05 6.01 E-05 0.00 E+00 5.95 E-05 5.95 E-05 5.95 E-05 7.22 E-05 5.95 E-05 Vegetation 1.03 E-04 1.17 E-04 0.00 E+00 1. 02 E-04 1. Ql E-04 1. 01 E-04 1. 01 E-04 1.01 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 TEEN Plume 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.59 E-02 4.17 E-02 Ground 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.42 E-04 Inhalation 5.99 E-05 6.05 E-05 0.00 E+00 5.99 E-05 5.99 E-05 5.99 E-05 7.84 E-05 5.99 E-04 Vegetation 1.22 E-Q4 1.35 E-04 0.00 E+00 1.20 E 04 1.19 E-04 1.19 E-04 1. 19 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 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.59 E-02 4.17 E-02 Ground 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1 ~ 42 E-04 Znhalation 5.30 E-05 5.32 E-05 0.00 E+00 5.30 E-05 5.30 E-05 5.30 E-05 6.80 E-05 5.30 E-05 Vegetation 1.91 E-04 1.96 E-04 0.00 E+00 1.88 E-04 1.86 E-04 1.86 E-04 1.86 E-04 1.86 E-04 TOTAL 1.57 E-02 1.57 E-02 1.54 E-02 1.57 E-02 1.57 E-02 1 ~ 57 E-02 1.63 E-02 4.21 E-02 INFANT Plume 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.59 E-02 4.17 E-02 Ground 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.42 E-04 Inhalation 3.05 E~QS 3.05 E-05 0.00 E+00 3.05 E-05 3.05 E-05 3.05 E-05 4.00 E-'5 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 1. 00 E+0 1 Shoreline, Swimming, Boating, Fish Consumption Cape Fear River 6.67 E+02 Shoreline, Drinking Water (for Harnett County, Lillington, Dunn, and Fayetteville)

Cape Fear River/

Raven Rock Park 1.62 E+03 Boating B. Populations Affected Location Value Ex osure Pathwa s Harris Lake 1.10 E+05 person-hours Shoreline, Swimming Harnett County 4.53 E+04 persons Drinking Water Dunn Intake 1.67 E+04 persons Drinking Water Fayetteville Area 1.40 E+05 persons Drinking Water

  • Fuquay-Varina 5.36 E+03 persons Drinking Water
  • Holly Springs 9.08 E+02 persons Drinking Water * ***

Harris Lake/

Cape Fear River 7.84 E+03 person-hours Fishing Cape Fear River/

Raven Rock Park 5.00 E+04 person-hours Boating Raven Rock Park 4.40 E+05 person-hours Shoreline The Drinking Water values have been revised to show current usage and consumption.

  • 0 The consumption values for Fuquay-Varina have been reduced by 1/2 to account for dual-supplied drinking water.:
    • 1 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.)

Bone Liver W Body Thyroid Kidney Lung GI-LLI Skin ADULT Pish 2.38 E-02 3.99 E-02 2.93 E-02 1.43 E-03 1.40 E-02 5.65 E-03 1.22 E-02 Drinking 1.50 E-04 1.31 E-02 1.31 E-02 1.29 E-02 1.29 E-02 1.29 E-02 1.46 E-02 Shoreline 1.80 E-03 1.80 E-03 1.80 E-03 1.80 E-03 1.80 E-03 1.80 E-03 1.80 E-03 2.12 E-03 Swinning 1.24 E<<04 1.24 E-04 1.24 E-04 1.24 E-04 1.24 E-04 1.24 E-04 1.24 E-04 Boating 1.42 E-04 1.42 E-04 1.42 E-04 1.42 E-04 1.42 E 04 1.42 E-04 1.42 E-04 TOTAL 2.60 E-02 5.50 E-02 4.45 E-02 1.64 E-02 2.89 E 02 2 06 E-02 2.89 E-02 2.12 E-03 TEEN Pish 2.52 E-02 4.08 E-02 1. IA E-02 1. 11 E-03 1.40 E-02 6.18 E-03 8.58 E-03 Drinking 0.00 E+00 0.00 E+00 0.00 E+00 0 F 00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Shoreline 1.01 E-02 1.01 E-02 1. 01 E-02 1. 01 E-02 l. 01 E-02 1.01 E-02 1.01 E-02 1. 18 E-02 Swi nni ng Boating 1.86 2.07 E-04 E-04 1.86 2.07 E-04 E-04 1.86 2.07 E-04 E-04

l. 86 E-04 1.86 E-04 1.86 E-04 1.86 E-04 2.07 E-04 2.07 E-04 2.07 E-04 2.07 E-04 TOTAL 3.57 E-02 5. 13 E-02 2.77 E-02 1. 16 E-02 2.45 E-02 1.66 E<<02 1 ~ 90 E-02 1.18 E-02 CHILD Pish 3.15 E-02 3.60 E-02 7.83 E-03 9.37 E-04 1.19 E-02 4-94 E-03 3.48 E-03 Drinking 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Shoreline 2.10 E-03 2.10 E-03 2. 10 E-03 2. 10 E-03 2.10 E-03 2.10 E-03 2.10 E-03 2.47 E-03 Swinning 6.21 E-05 6.21 E-05 6.21 E-05 6. 21 E-05 6.21 E-05 6.21 E-05 6. 21 E-05 Boating 7.77 E-05 7.77 E-05 7.77 E-05'. 7.77 E-05 7.77 E-05 7.77 E-05 7-77 E-05 TOTAL ,3. 37 E-02 3.82 E-02 10 E-02 3. 18 E-03 1.42 E-02 7.19 E-03 5.73 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 W. Body GZ-LLI Bone Liver Kidney Thyroid Lung Skin ADULT Plume 6.27 E-02 6.27 E-02 6.27 E-02 6.27 E-02 6.27 E-02 6.27 E-02 6.50 E-02 1.71 E-01 Ground 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E 04 3.46 E-04 Inhalation 2.49 E-04 2.51 E-04 0 00 E+00 2.49 E-04 2.49 E-04 2.49 E-04 3.03 E-04 2 49 E-04 Vegetation 4.27 E-04 4.61 E-04 0.00 E+00 F 25 E-04 4.23 E-04 4.23 E-04 4.23 E 04 4.23 E-04 Milk F 00 E-04 1.02 E-04 0 00 E+00 1.00 E-04 1.00 E-04 1.00 E-04 1.00 E-04 1.00 E-04 Goat Milk 3.09 E-04 3.09 E-04 0.00 E+00 3.09 E-04 3.09 E-04 3.09 E-04 3.09 E-04 3.09 E-04 Meat a Poultry 4 '5 E-05 6.41 E-02 5.04 6.41 E-05 E-02 0 00 E+00 6.30 E-02 4.30 E-05 4 '6 E-05 4.26 E-05 4.26 E-05 4 26 E-05 TOTAL 6.41 E-02 6.41 E-02 6.41 E-02 6.65 E-02 1.72 E-01 TEEN Plume Ground 6.27 E-02 2.94 E-04 6 '7 2.94 E-02 6.27 2.94 E-02 E-04 6.27 E-02 E-04 6.27 E-02 6.27 E-02 6.50 E-02 1.71 E-01 E 04 2.94 2.94 E-04 2.94 E-04 2.94 E-04 3.46 E-04 Inhalation 2 ~ 51 E-04 2.53 E-04 0.00 E+00 2.50 E-04 2.50 E-04 2.50 E-04 3.29 E 04 2 50 E-04 Vegetation 5.04 E 04 5.37 E-04 0.00 E+00 5.00 E-04 4.97 E-04 4.97 E-04 4.97 E-04 4.97 E-04 Milk 1. 31 E-04 1.32 E-04 0.00 E+00 1.30 E-04 1.30 E-04 1.30 E-04 1.30 E 04 1.30 E-04 Goat Milk 4.03 E-04 4.03 E-04 0.00 E+00 4.03 E 04 4.03 E-04 4.03 E-04 4.03 E-04 4.03 E-04 Meat a Poultry 2. 61 E-05 2.96 E-05 0.00 E+00 2.57 E-05 2.54 E-05 2.54 E-05 2.54 E-05 2.54 E-05 TOTAL 6.43'-02 6.43 E-02 6.30 E-02 6.43 E-02 6.43 E-02 '6.43 E-02 6.67 E-02 1.73 E-01 CHILD Plume 6.27 E-02 6.27 E-02 6.27 E-02 6.27 E-02 6.27 E-02 6.27 E-02 6.50 E-02 1. 71 E-01 Ground 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 2.94 E-04 3.46 E-04

,Inhalation 2.22 E-04 2.22 E 04 0.00 E+00 2.21 E-04 2.21 E-04 2.21 E-04 2.85 E-04 2. 21 E-04 Vegetation 7.89 E-04 8.02 E-04 0.00 E+00 7.80 E-04 7.75 E-04 7.75 E-04 7.75 E-04 7.75 E 04 Milk 2.07 E-04 2.07 E-04 0.00 E+00 2.06 E-04 2.06 E-04 2.06 E-04 2.06 E-04 2.06 E-04 Goat Milk 6.36 E-04 6.36 E-04 0 00 E+00 6.36 E-04 6.36 E 04 6.36 E-04 6.36 E 04 6.36 E-04

.Meat a Poultry 3. 18 E-05 F 28 E-05 0.00 E+00 3.11 E-05 3.07 E-05 3.07 E-05 3.07 E 05 3.07 E-05 TOTAL 6.49 E-02 6.49 E-02 6.30 E-02 6.48 E-02 6.48 E-02 6 '8 E-02 6.73 E-02 1. 73 E-01 INFANT Plume 6 '7 E-02 6.27 E-02 6.27 E-02 6.27 E-02 '6.27 E-02 6 '7 E-02 6.50 E-02 1.71 E-01 Ground Znhalation 2.94 1.27 E-04 E-04 2.94 1.28 E-04 E-04 2.94 0.00 E-04 E+00 2.94 1.27 E-04 E 04 2.94 1.27 E-04 E-04 2 '4 1.27 E-04 E-04 2.94 1.68 E-04 E-04 3.46 1.27 E-04 E-04 Milk 3.13 E 04 3.13 E-04 0.00 E+00 3.13 E-04 3.12 E-04 3. 12 E-04 3.12 E-04 3.12 E-04 Goat Milk 9.66 E-04 9.66 E-04 0.00 E+00 9.65 E-04 9.65 E-04 9.65 E-04 9.65 E-04 9.65 E-04 TOTAL 6.44 E-02 6.44 E-02 6.30 E-02 6.44 E-02 6.44 E-02 6.44 E-02 6.68 E-02 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 ll Body'Z-LLZ Bone Liver Kidney Thyroid Lung Skin ADULT Plume 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1. 59 E-02 4.17 E-02 Ground 1 20 E-04

~ 1 ~ 20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 , 1.20 E-04 1.42 E-04 Znhalation 5.95 E-OS 6.01 E-05 0.00 E+00 5.95 E 05 5.95 E-OS 5.95 E-05 7.22 E-05 5.95 E-05 Vegetation 1.Q3 E-04 1. 17 E-04 0.00 E+00 1.02 E-04 1.01 E-04 1.01 E-04 1 ~ 01 E-04 1.01 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-Q2 4.20 E-02 TEEN Plume 1.53 E 02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.59 E-02 4.17 E-02 Ground 1.20 E 04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E 04 1.20 E-04 1.20 E-04 1.42 E-04 Inhalation 5.99 E-QS 6.05 E-05 0.00 E+00 5.99 E-05 5.99 E-05 5.99 E-05 7.84 E-05 5.99 E-04 Vegetation 1.22 E-04 1.35 E-04 0.00 E+QO 1.20 E 04 1.19 E-04 1.19 E<<04 1.19 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 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.59 E-02 4.17 E-02 Ground 1.20 E-04 1.20 E-04 F 20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.20 E-04 1.42 E-04 Inhalation 5.30 E-05 5.32 E-OS 0.00 E+00 . 5.30 E-05 5.30 E-OS 5.30 E-05 6.80 E-05 5.30 E-OS Vegetation 1.91 E-04 1 ~ 96 E-04 0.00 E+00 1.88 E-04 1.86 E-04 1.86 E-04 1.86 E 04 1 86 E-04 TOTAL 1 ~ 57 E 02 1.57 E-02 1.54 E-02 1.57 E-02 1.57 E-02 1.57 E-02 1.63 E-02 4.21 E-02 IHPAHT Plume 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.53 E-02 1.59 E-02 4. 17 E-02 Ground 1.20 E 04 1.20 E-04 1 20 E-04 1.20 E 04 1.20 E-04 1.20 E-04 1.20 E-04 1.42 E-04 Inhalation 3.05 E~OS 3.05 E-05 0.00 E+00 3.05 E-05 3 05 E-05 3.05 E-05 4.00 E-05 3.05 E-OS 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

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: Beta ~ 2.35 E-01 Ganna ~ 1.02 E-01 B. Maxinun Real Individual: .Beta ~ 5.70 E-02 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.

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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 1. 00 E+01 Shoreline, Swinning, Boating, Fish Consunption Cape Fear River 6.67 E+02 Shoreline, Drinking Water

{for Harnett County, Lillington, Dunn, and Fayetteville)

Cape Fear River/

Raven Rock Park 1.62 E+03 Boating B. Populations Affected Location Value Ex osure Pathwa s Harris Lake 1.10 E+05 person-hours Shoreline, Swinning Harnett County 4.53 E+04 persons Drinking Water Dunn Zntake 1.67 E+04 persons Drinking Water Fayetteville Area 1.40 E+05 persons Drinking Water Fuquay-Varina 5.36 E+03 persons Drinking Water Holly Springs 9.08 E+02 persons Drinking Water Harris Lake/

Cape Fear River 7.84 E+03 person-hour:. Fishing Cape Fear River/

Raven Rock Park 5.00 Et04 person-hours Boating Raven Rock Park 4.40 E+05 person-hours Shoreline 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.

  • ee 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 hours/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.

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