Text

Transmittal of 2018 Annual Radioactive Effluent Release Report - Report 42
	ML19126A086
Person / Time
Site:	Wolf Creek
Issue date:	04/30/2019
From:	Benham R; Wolf Creek
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	RA 19-0051
	Download: ML19126A086 (337)
	v • d • e

\ W$LFCREEK 'NUCLEAR OPERATING CORPORATION Ron Benham Manager Nuclear and Regulatory Affairs April 30, 2019 RA 19-0051 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Docket No. 50-482: Wolf Creek Generating Station 2018 Annual Radioactive Effluent Release Report - Report 42 To Whom It May Concern:

The purpose of this letter is to transmit the enclosed Wolf Creek Generating Station (WCGS)

Annual Radioactive Effluent Release Report. The report covers the period from January 1, 2018 through December 31, 2018. It is being submitted pursuant to Section 5.6.3 of the WCGS Technical Specifications. The report provides procedures AP O?B-003, Revision 9, "Offsite Dose Calculation Manual," AP O?B-004, Revision 22, "Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program}," and AP 31A-100, Revisions 8 and 9, "Solid Radwaste Process Control Program" that are included as part of the report in accordance with Section 5.5.1 of the WCGS Technical Specifications. These procedures have the changes made during the reporting period marked as required.

This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4204.

Sincerely, RDB/rlt

Enclosure:

2018 Annual Radioactive Effluent Release Report - Report 42 cc: S. A. Morris (NRC}, w/e B. K. Singal (NRC), w/e N. H. Taylor (NRC}, w/e.

Senior Resident Inspector (NRC}, w/e P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET

Enclosure to RA 19-0051

Wolf Creek Generating Station 2018 Annual Radioactive Effluent Release Report- Report 42 (336 pages including this page)

This enclosure contains three enclosures:

Enclosure I Offsite Dose Calculation Manual, AP 078-003, Revision 9 1 Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program), AP 078-004, Revision 22 Enclosure Ill Solid Radwaste Process Control Program, AP 31A-100, Revision 8 and 9

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WOLF CREEK NUCLEAR OPERATING CORPORATION 2018 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Wolf Creek Generating Station Docket Number 50-482 Renewed Facility Operating License NPF-42 Report Number 42

WOLF CREEK NUCLEAR OPERATING CORPORATION 2018 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Introduction This Annual Radioactive Effluent Release Report (ARERR) covers the operation of Wolf Creek Generating Station (WCGS) from January 1, 2018 through December 31, 2018. The ARERR includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit in accordance with Technical Specification 5.6.3. The content of this ARERR is presented in the general format of Revision 1 of Regulatory Guide 1.21.

2018 Annual Radioactive Effluent Release Report

I. SUPPLEMENTAL INFORMATION A. Regulatory Limits The Offsite Dose Calculation Manual (ODCM) describes the . methodology and parameters used in the calcul~tion of offsite doses due to radioactive liquid and gaseous effluents. The following are limits required by the ODCM:

1. GASEOUS EFFLUENTS The dose rate due to .radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

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

For lodine-131, lodine-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.

The air dose due to noble gases released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:

During any calendar quarter: Less than or equal to 5 mrads for gamma radiation

. and less than or equal to 10 mrads for beta radiation, and During any calendar year: Less than or equal to 10 mrads for gamma radiation

and less than or equal to 20 mrads for beta radiation.*

The dose to a member of the public from lodine-131, lodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary. shall be limited to

. the following:

During any calendar qL,1arter: Less than or equal to 7.5 mrems to any organ, and During any calendar year: Less than or equal to 15 mrems to any organ.

2. LIQUID EFFLUENTS The concentration of radioactive material released in liquid *effluents to unrestricted ar~as shall be limited to 10 times the limit specified in 10 CFR 20, 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 2.00E-04 µCi/ml total.activity.

2018 Annual Radioactive Effluent Release Report .

The dose or dose commitment to a

member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited:

During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 1O mrems to any organ.

B. Effluent Concentration Limit (ECL)

The concentration of radioactive material released in liquid effluent~ to unrestricted areas shall be limited to 10 times the limit specified in 10 CFR 20, 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 2.ooE:..04 µCi/ml total activity. The percent of ECL values are found in Appendix A, Table 4A.

C. Average Energy Average energy of fission and activation gaseous effluents is not applicable. See ODCM section 3.1 for the methodology used in determining the release rate limits from nqble gas releases.

D. Measurements and Approximations of Total Radioactivity Measurements of total radioactivity were performed in accordance with the sampling and analysis requirements of Tables 2-1 and 3-1 of the ODCM (Enclosure I).

Gamma spectroscopy is used as the primary method in determining radionuclide.

composition and concentration of liquid and gaseous effluents. Liquid composites are sent off site for analysis of Sr-89, Sr-90,_ Fe-55 and Ni-63. Gaseous composites are also sent off site for Sr-89 and Sr-90 analysis. Liquid scintillation and scintillation alpha counters are used to measure tritium and gross alpha.

E. Batch Releases

1. LIQUID

Number of batch releases - 53 Total time period for batch release -6,410 minutes Maximum time period for a batch release - 270 minutes Average time period_ for batch releases - 120.9 minutes Minimum time period for a batch release - 36 minutes

Average stream flow during periods of release of effluent into a flowing stream-Not applicable

. 2018 Annual Radioactive Effluent Release Report

2. GASEOUS Number of batch releases - 61 Total time period for batch release - 57,997 minutes Maximum time period for a batch release - 8,777 minutes Average time period for batch releases - 950.8 minutes Minimum time period for a batch release -.17 minutes F. Continuous Releases

1. GASES Continuous gaseous release. pathways include t.he Unit Vent and Radwaste Vent.

2. LIQUID Continuous liquid release pathways include Steam Generator Slowdown, Lime Sludge Pond, Turbine Building Sump and Waste Water Treatm,ent.

G. Abnormal Releases There were no unplanned or uncontrolled releases of radioactive material from the site boundary in 2018.

Update c,n CR 00084942: On June 14, 2013, approximately 100 gallons of contaminated water leaked from the Spent Fuel Pool into the Component Cooling Water A train, (CCW). The primary gamma emitting isotope (Cs-137) was removed from'CCW by ion exchange to below detection limits. By the end of 2014, the CCW tritium concentration equalized in both trains to 1.00E-03 uCi/ml and no gamma emitting isotopes were* detected. A portion .of the CCW system was drained through the normal discharge path dyring the 2015, 2016 and 2018 refueling outages. After partially draining and refilling the system, tritium values in the CCW are now approximately 1.00E-05 µCi/ml. The CCVV system is scheduled to be partially released and* monitored through defined ODCM discharge paths during the 2019 refueling outage for system maintenance. The following CRs document the event and evaluation: 70420, 70451, 70546 and 72212.

II. GASEOUS EFFLUENTS An elevated release pathway does not exist at WCGS. All airborne releases are considered to be ground level releases. Appendix A, Table 1A contains the summation of all gaseous effluent discharges, while Table 1B shows the quarterly sums of curies discharged and is divided according to batch or conti_nuous mode. ,

2018 Annual Radioactive Effluent Release Report

111.

LIQUID EFFLUENTS Summary information can be found in Appendix A, Tables 2A and 28. Table 2A contains the summation of all liquid effluent discharges, while Table 28 reports the quarterly sums of total curies released and is divided according to batch or continuous mode.

IV. SOLID WASTE Appendix A, Table 3 contains information on shipments of solid waste and irradiated fuel .

transported from the site during the period.

V. RADIOLOGICAL IMPACT ON MAN No ODCM dose limits* were exceeded in 2018.

Dose calculations are performed for the limiting age group i.e., adult age group for the liquid pathway and the child age group for gaseous effluent' organ* doses. All calculations were performed in accordance with the methodology and parameters in the ODCM. A conservative error of thirty percent has been estimated in the effluent data for liquid and gaseous dose.

A. Dose Due to Liquid Effluents The dose due to liquid effluents was calculated in accordance with the methodology and parameters* in the ODCM and can be found in Appendix A, Tables 48 and 4C. Table 4-C is included to show the correlation between curies released and the associated calculated maximum organ dose.

Wolf Creek ODCM methodology is used to calculate the maximum organ dose which assumes that an individual drinks the water and eats the fish from the* discharge point.

ODCM section 2.2 organ dose limits are used.

B. Dose Due to Gaseous Effluents The dose due to gaseous effluents can be found in Appendix A, Tables 40 and 4E and is calculated in accordance with the methodology and parameters in the ODCM. Table 4E is included to show the correlation between curies released and the associated calculated maximum organ dose. The gaseous pathway dose determination is met by the ODCM methodology of assigning all gase.ous pathways to a hypothetical individual residing at the *highest annual X/Q and D/Q location, which assumes that an individual actually resides at the site boundary. This results in a conservative estimate of dose to a member of the public, rather .than determining each pathway dose for each release condition. ODCM section 3.2.2 organ dose limits are used.

2018 Annual Radioactive Effluent Release Report u,

C. Dose to a Member of the Public from Activities Inside the Site Boundary Four activities by members of the public were considered in this evaluation. The dose calculated for the maximum exposed individual is as follows:

Total Dose Personnel making deliveries to the plant 2. 72E-01 mrem/yr Workers at the William Allen White Building 6.1 OE-03 mrem/yr located outside the protected area boundary Use of the access road south of the Radwaste 2. 79E-03 mrem/yr Building Public use of the cooling lake during times 3.74E-02 mrem/yr when fishing was allowed The plant delivery calculations were based on deliveries being made 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months per week for 50 weeks per year. The William Allen White Building occupancy was based on

. normal working hours of 2,000 per year. The usage factor for the access road south of the Radwaste Building was 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months per year. The dose* to anglers on the lake was based upon 3,600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months a day for 300 days, based on the number of days that the lake was open to anglers). The Submersion, Inhalation and Ground Plane pathway doses were added to derive the total dose. All calculations were performed in accordance with the methodology and parameters in the ODCM.

VI. METEOROLOGICAL DATA Appendix B documents WCGS meteorological data for wind speed, wind direction* and atmospheric stability. The meteorological data supplied in the tables covers the period from January 1, 2018 through December 31, 2018, and indicates the number of hours at each wind speed and direction for each stability class. All gaseous releases at the WCGS are ground level releases.

WCGS did not meet Regulatory Guide 1.23 requirement for data recovery, for all instruments.

The 60 Meter Wind Direction, due to instrument problems and weather concerns in the fourth quarter, had an 89.89% data recovery. Condition Report 131756 was written on the issue and work orders have since been completed fixing the issues. The 60 Meter Temperature instrument had* an 88.97% data recovery for 2018, due to issues in the third quarter which calibration performance resolved. The remaining instruments, both at 1O and 60 meters, met or exceeded a 90% meteorological data recovery for 2018.

2018 Annual Radioactive Effluent Release Report

VII. ADDITIONAL INFORMATION

. A. Unplanned Releases There were no unplanned releases in 2018.

B. ODCM The ODCM is in the form of two separate procedures. They 'are AP 078-003 (Offsite Dose Calculation Manual) and AP 078-004 (Offsite Dose Calculation Manual-Radiological Environmental Monitoring Program). Both procedures are attached as enclosures.

AP 078-003 (Offsite Dose Calculation Manual) was revised during the reporting period.

A complete copy of revision 9 with revision bars showing the .areas of change is attached.

C?* Radwaste Treatment System Changes There were no major changes made to the Liquid, Solid or Gaseous Radwaste Systems in 2018 that alter the capacity or handling of radioactive wastes or differ in the method of treatment.

D. Annual Land Use Census Changes Per the Annual Land Use Census, three changes were identified for the nearest occupied residence in each sector. Six changes were noted for the nearest garden producing broadleaf vegetation. There were. no changes regarding milk sample locations: No locations were identified that milked animals for human consumption.

E. Liquid Holdup or Gas Storage Tanks

No limits were exceeded in 2018 for Technical Requirement 3.10.1 (Liquid Holdup Tanks) or Technical Surveillance Requirement 3.10.3.1 (Gas Storage Tanks).

F. Functionality of Effluent Monitoring Instrumentation Effluent monitoring instrumentation returned to functional status within specified time:*

G. Missed samples There were no missed samples during the reporting period.

H. NEI Groundwater Protection Industry Initiative See Appendix C.

2018 Annual Radioactive Effluent Release Report

I. Other PERMIT U1GB2019-034 On 02/06/2018, GERE92 (Condenser Air Removal System Radiation Detector) was removed from service to support a planned Unit Vent Outage lasting approximately three days .. During this time we were discharging directly to the turbine building and routing aux building air to radwaste to discharge through the radwaste vent monitors. The air routed to radwaste was considered a monitored release while the air directed to the turbine building was considered unmonitored. With GERE92 being nonfunctional, compensatory samples were pulled. At the time, we were seeing XE-133 and occasionally XE-135 in our condenser off gas samples due to failed fuel. A preliminary permit was generated using the maximum isotope activities during the time. period to evaluate dose and later an actual miscellaneous permit was generated. The total curies and dose were well below ODCM limits. No required samples were missed.

CR 00127292 ..

During the review of monthly and quarterly composite paperwork, it was found that an incorrect volume was used on the September monthly batch composite which led to an incorrect volume also being used. on the 3rd quarter batch composite which was mailed offsite for analysis. There was enough weekly and monthly composite remaining to.

make a new monthly and quarterly batch composite which was shipped for analysis. No composites were missed or excluded, resulting in no missed ODCM surveillances.

CR 00127659 An error was identified on gas release permit U1GB2018-136 for containment purge.

The release occurred on October 10, 2018 at 0756 using an incorrect, non-conservative Expected Monitor Response (EMR) value. The error was caused by using the incorrect radiation monitor background reading. The background was reading 3.39E-06 µCi/ml, but the technician entered 3.39E-07 µCi/ml. This reading is used to calculate the EMR which is compared to the monitor low setpoint. An EMR of 1.25E-06 µCi/ml was used on the permit, but should have been 4.31 E-06 µCi/ml. The setpoints used on the permit were calculated correctly and not exceeded.

CR 00120547 Verifications and approvals were not obtained for release permit U1 LC2018-003 prior to initiating a Turbine Building Sump release on 03/19/18 at 1506. These verifications include entering the setpoints, verifying the setpoints and authorization of the release by the shift manager. When this was discovered on 03/21/18, the setpoints were verified and the release was authorized by the shift manager. The setpoints were at the required value when it was checked. Chemistry sampled as required per the ODCM-no samples were missed. Procedure Change Requests were made to applicable procedures to address better documentation and include them in the prerequisite sections.

2018 Annual Radioactive Effluent Release Report

CR 00128946 On 12/25/2018, operations commenced hanging C22 D-KC-N-26 for radwaste fire protection work to start on 12/26/2018. Around 1700, the .control room received a call that water was seen crossing the RCA boundary by security camera. The flushing of isolation valves had been conducted earlier which allowed tritiated water to come in contact with the soil rather than flow directly into a storm drain due to spillover from the drain and the ground being sloped. The fire protection water had been sampled prior to work with the following results: pH of 8.9, gross activity was O.OOE+OO µCi/ml and a tritium value of 1.442E-05 µCi/ml which is roughly equivalent to our lake tritium.

CARBON-14 (CR 36059)

Regulation 10CFR50.36a requires nuclear power plants to report quantities of principal radionuclides in the annual radioactive effluent release report. In the early 1980s, the NRC decided that C-14 radionuclide would not be required to be reported because it would not make a significant contribution to dose. Since this time, technology has advanced both for effluent isotopic reduction and isotope detection and estimation. It is*

more likely the C-14 meets the definition of a principal radionuclide in accordance with the newly published Regulatory Guide 1.21 Revision 2 (June 2009).

The NRC allows the reporting of this isotope based on estimation methods. EPRI TR 1021106 developed an estimation method based on peer-reviewed research that incorporates parameters of Wolf Creek's reactor design to estimate the gross amount of C-14 produced annually. This value is fed into additional calculations, based on 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, to provide an estimation of annual dose. Based on the 2010 theoretical calculations and assuming the maximum percentage of inorganic C-14 compounds (30%), Wolf Creek has estimated the annual release of C-14 to be 10.7 curies. This will give rnaximum dose values of 4.60 mrem/yr child bone dose and 0.921 mrem/yr child total body dose. This is well below the 10CFR50, Appendix I, ALARA design objective of 15 mrem/yr. Additionally, this value is on par with the dose expected from naturally occurring radiocarbon.

2018 Annual Radioactive Effluent Release Report CD

Appendix A (Effluent Tables) 2018 Annual Radioactive Effluent Release Report

TABLE 1A:

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error,%*

Fission & Activation Gases Total Release Ci 3.48E+OO 1.99E+01 2.45E+OO 6.87E-02 3.00E+01 Average Release Rate µCi/sec 4.48E-01 2.53E+OO 3.09E-01 8.64E-03 for period Percent of ODCM limit % 3.34E-03 1.48E-02 3.39E-03 8.91E-04 Iodines Total lodine-131 Ci 3.73E-07 8.53E-05 O.OOE+OO O.OOE+OO 3.00E+01 Average Release Rate µCi/sec 4.79E-08 1.0BE-05 O.OOE+OO O.OOE+OO for period Percent of ODCM limit % 3.73E-05 8.53E-03 O.OOE+OO O.OOE+OO Particulates Particulates with half- Ci O.OOE+OO 5.72E-06 O.OOE+OO O.OOE+OO 3.00E+01 lives >8 days Average Release Rate µCi/sec O.OOE+OO 7.28E-07 O.OOE+OO O.OOE+OO for period '

Percent of OOCM limit % O.OOE+OO 4.06E-05 o:ooE+oo O.OOE+OO Gross alpha radioactivity Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.00E+01 Tritium Total release Ci 4.61E+OO 1.56E+01 5.91E+OO 9.53E+OO 3.00E+01 Average Release Rate µCi/sec 5.93E-01 1.98E+OO 7.43E-01 1.20E+OO for period Percent of ODCM limit % 4.35E-02 1.47E-01 5.57E-02 8.98E-02 2018 Annual Radioactive Effluent Release Report

TABLE 18:

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES-BATCH MODE J Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Fission gases Argon-41 Ci 1*.34E-01 2.84E-02 5.58E-02 6.87E-02 Xenon-133 Ci 1.93E-01 1.66E+01 1.28E-04 <2.67E-03 Krypton-85 Ci 1.06E-01 2.13E-01 2.40E+OO O.OOE+OO Krypton-87 Ci <4.62E-03 <8.89E-01 <2.49E-03 <2.87E-03 Krypton-BB Ci <5.81E-03 <1.12E+OO <3.13E-03 <3.61E-03 Xenon-133m Ci 6.15E-05 <2.34E+OO <6.57E-03 <7.56E-03 Xenon-135 Ci 1.16E-05 1.BBE-04 <7.53E-04 <8.67E-04 Xenon-138 Ci <1.41E-01 <2.71 E+01 <7.59E-02 <8.73E-02 Xenon-131m Ci 2:51E-03 2.81 E-04 O.OOE+OO O.OOE+OO Total for period* Ci 4.35E-01 1.68E+01 2.45E+OO 6.87E-02 Iodines lodine-131 Ci <1.22E-07 <2.34E-05 <6.57E-08 <7.56E-08 lodine-133 Ci <1.22E-05 <2.34E-03 <6.57E-06 <7.56E-06 Total for period* Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates Strontium-89 Ci <1.22E-06 <2.34E-04 <6.57E-07 <7.56E-07 Strontium-90 Ci <1.22E-06 <2.34E-04 <6.57E-07 <7.56E-07 Cesium-134 Ci <1.22E-06 <2.34E-04 <6.57E-07 . <7.56E-07 Cesium-137 Ci <1.22E-06 <2.34E-04 <6.57E-07 <7.56E-07 Manganese-54 Ci <1.22E-06 <2.34E-04 <6.57E-07 <7.56E-07 lron-59 Ci *<1.22E-06 <2.34E-04 <6.57E-07 <7.56E-07 Cobalt-58 Ci <1.22E-06 <2.34E-04 <6.57E-07 <7.56E-07 Cobalt-60 Ci <1.22E-06 <2.34E-04 <6.57E-07 <7.56E-07 Zinc-65 Ci <1.22E-06 <2.34E-04 <6.57E-07 <7.56E-07 Molybdenum-99 Ci <1.22E-06 <2.34E-04 <6.57E-07 <7.56E-07 Cerium-141 'Ci <1.22E-06 <2.34E-04 <6.57E-07 <7.56E-07 Cerium-144 Ci <1.22E-06 <2 ..34E-04 <6.57E-07 <7.56E-07 Total for period* Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium I Ci 7.77E-02 3.56E+OO 4.47E-01 4.35E-01 Gross Alpha Ci <1.22E-06 <2.34E-04 <6.57E-07 <7.56E-07

Less than values are not included in the summation for the total release values.

2018 Annual Radioactive Effluent Release Report

TABLE 18:

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES -CONTINUOUS MODE I Nuclides Released I Unit I Quarter 1 I Quarter 2 I Quarter 3 I Quarter4 I

Fission gases Xenon-133 Ci 3.0SE+OO 3.12E+OO <8.84E+OO <8.SOE+OO Krypton-87 Ci <9.04E+OO <8.79E+OO <9.SOE+OO <9.14E+OO Krypton-BB Ci <1.14E+01 <1.10E+01 <1.19E+01 <1.15E+01

' Xenon-133m Ci <2.38E+01 <2.31E+01 <2.50E+01 <2.41E+01 Xenon-135 Ci <2.73E+OO <2.66E+OO <2.87E+OO <2.76E+OO

., Xenon-138 Ci <2.75E+02 <2.68E+02 <2.89E+02 <2.78E+02 Total for period Ci 3.0SE+OO 3.12E+OO O.OOE+OO O.OOE+OO Iodines lodine-131 Ci 3.73E-07 8.53E-05 <2.SOE-04 <2.41E-04 lodine-133 Ci <2.38E-02 <2.31E-02 <2.SOE-02 <2.41E-02 Total for period Ci 3.73E-07 8.53E-05 O.OOE+OO O.OOE+OO

Particulates Strontium-89 Ci <2.38E-03 <2.31E-03 <2.SOE-03 <2.41E-03 Strontium-90 Ci <2.38E-03 <2.31E-03 <2.SOE-03 <2.41E-03 Cesium-134 Ci <2.38E-03 <2.31 E-03 <2.SOE-03 <2.41E-03 Cesium-137 Ci <2.38E-03 <2.31E-03 <2.SOE-03 <2.41E-03 Manganese-54 Ci <2.38E-03 <2.31E-03 <2.SOE-03 <2.41E-03 lron-59 Ci <2.38E-03 <2.31E-03 <2.SOE-03 <2.41E-03 Cobalt-SB Ci <2.38E-03 5.72E-06 -<2.SOE-03 <2.41E-03 Cobalt-60 Ci <2.38E-03 <2.31E-03 <2.SOE-03 <2.41 E-03 Zinc-65 Ci <2.38E-03 <2.31E-03 <2.SOE-03 <2.41E-03 Molybdenum-99 Ci <2.38E-03 <2.31E-03 <2.SOE-03 <2.41E-03 Cerium-141 Ci <2.38E-03 <2.31E-03 <2.SOE-03 <2.41E-03 Cerium-144 Ci <2.38E-03 <2.31 E-03 <2.SOE-03 <2.41 E-03 Total for period Ci O.OOE+OO 5.72E-06 O.OOE+OO O.OOE+OO I Tritium I Ci I 4.53E+OO I 1.20E+01 I 5.46E+OO I -9.o9E+oo I I Gross Alpha Ci <2.38E-03 I <2.31E-03 I <2.SOE-031 <2.41E-03 /

I I

Less than values are not included in the summation for the total release values.

~

2018 Annual Radioactive Effluent Release Report w

TABLE 2A:

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error,%

FISSION AND ACTIVATION PRODUCTS Total Release (not including Ci 3.03E-03 1.15E-03 1.57E-03 3.85E-04 3.00E+01 tritium, gases, alpha)

Average Diluted µCi/ 1.18E-11 8.04E-12 5.70E-12 1.43E-12 Concentration during period ml Percent of Applicable Limit % 6.06E-02 2.30E-02 3.14E-02 7.69E-03 TRITIUM Total Release Ci 6.19E+02 2.31E+02 2.76E+01 1.38E+02 3.00E+01 Average Diluted µCi/ 2.41 E-06 1.61 E-06 9.99E-08 5.15E-07 Concentration during period ml -

Percent of Applicable Limit % 2.41 E-01 1.61 E-01 9.99E-03 5.15E-02 DISSOLVED AND ENTRAINED GASES Total Release Ci 4.60E-01 4.00E-01 O.OOE+OO O.OOE+OO 3.00E+01 Average Diluted µCi/ 1.79E-09 2.79E-09 O.OOE+OO O.OOE+OO Concentration during period ml Percent of Applicable Limit % 8.96E-04 1.40E-03 O.OOE+OO O.OOE+OO GROSS ALPHA RADIOACTIVITY I Total Release Ci ,1 O.OOE+OO I O.OOE+OO I O.OOE+OO I O.OOE+OO I 3.00E+01 Volume of waste released L 9.96E+07 7.07E+07 1.09E+08 1.05E+08 3.00E+01 (prior to dilution)

Volume of dilution water used L 2.57E+11 1.43E+11 2.76E+11 2.68E+11 3.00E+01 during period 2018 Annual Radioactive Effluent Release Report

TABLE 28: LIQUID EFFLUENTS- BATCH MODE I Nuclides Released Unit I Quarter 1 I Quarter 2

I Quarter 3 I Quarter 4 Fission & Activation Products Strontium-89 Ci <4.19E-05 <5.35E-05 <1.38E-05 <1.58E-05 Strontium-90 Ci <4.19E-05 <5.35E-05 <1.38E-05 <1.58E-05

- Cesium-134 Ci <4.19E-04 6.52E-07 <1.38E-04 <1.58E-04 Cesium-137 Ci <4.19E-04 1.03E-06 <1.38E-04 1.81 E-05 Cobalt-58 Ci

6.78E-05 4.30E-04 3.25E-04 2.02E-05 Cobalt-60 Ci 2.67E-05 2.49E-05 1.97E-05 <1.58E-04 lron-55 Ci <8.37E-04 <1.07E-03 <2.75E-04 <3.15E-04 lron-59 Ci <4.19E-04 <5.35E-04 <1.38E-04 <1.58E-04 Zinc-65 Ci <4.19E-04 <5.35E-04 <1.38E-04 <1.58E-04 Manganese-54 Ci <4.19E-04 <5.35E-04 <1.38E-04 <1.58E-04 Nickel-63 Ci 1.34E-03 1.72E-04 1.40E-04 2.96~-05 Antimony-125 Ci 1.58E-03 3.52E-04 .1.09E-03 3.17E-04 Molybdenum-99 Ci <4.19E-04 <5.35E-04 <1.38E-04 <1.58E-04 Cerium-141 Ci <4.19E-04 <5.35E-04 <1.38E-04 <1.58E-04 Cerium-144 Ci <4.19E-04 <5.35E-04 <1.38E-04 <1.58E-04 lodine-131 Ci 1.29E-05 1.11 E-04 <2.75E-04 <3.15E-04 lodine-133 Ci O.OOE+OO 1.00E-05. O.OOE+OO O.OOE+OO Total for period* Ci 3.03E-03.

1.10E-03 1.57E-03 3.85E-04 Dissolved & Entrained Gases Xenon-133 Ci 4.35E-01 3.78E-01 <2.75E-03 <3.15E-03 Xenon-133m Ci 2.22E-03 5.31E-03 <2.75E-03 <3.15E-03 Xenon-135 Ci 4.28E-05 1.14E-03 <2.75E-03 <3.15E-03 Xenon-131m Ci 1.11 E-02 7.05E-03 <2.75E-03 <3.15E-03 Krypton-85 Ci 1.21 E-02 8.97E-03 <2.75E-03* <3.15E-03 Total for period* Ci 4.60E-01 4.00E-01 O.OOE+OO O.OOE+OO Tritium Ci 6.17E+02 2.29E+02 2.58E+01 1.37E+02 Gross Alpha Ci <8.37E-05 <1.07E-04 <2~75E~05 * <3.15E-05

Less than values are not included in the summation for the total release values.

2018 Annual Radioactive Effluent Release Report

TABLE 28: LIQUID EFFLUENTS- CONTINUOUS MODE I Nuclides Released Unit Quarter1 Quarter2 Quarter3 Quarter4 Fission & Activation Products Strontium-89 Ci <4.94E-03 <3.48E-03 <5.40E-03 <5.25E-03 Strontium-90 Ci <4.94E-03 <3.48E-03 <5.40E-03 <5.25E-03 Cesium-134 Ci <4.94E-02 2.59E-05 <5.40E-02 <5.25E-02 Cesium-136 Ci O.OOE+OO 3.33E-06 O.OOE+OO O.OOE+OO Cesium-137 Ci <4.94E-02 9.88E-06 <5.40E-02 <5.25E-02 Cobalt-58 Ci <4.94E-02 <3.48E-02 <5.40E-02 <5.25E-02 Cobalt-60 Ci <4.94E-02 <3.48E-02 <5.40E-02. <5.25E-02 lron-55 Ci <9.88E-02 <6.96E-02 <1.0BE-01 <1.05E-01 lron-59 Ci <4.94E-02 <3.'48E-02 <5.40E-02 <5.25E-02 .

Zinc-65 Ci <4.94E-02 <3.48E-02 <5.40E-02 <5.25E-02 Manganese-54 Ci <4.94E~02 <3.48E-02 <5.40E-02 <5.25E-02 Nickel-63 Ci <9.88E-02 <6.96E-02 <1.0BE-01 <1.0SE-01 Molybdenum-99 Ci <4.94E-02 <3.48E-02 <5.40E-02 <5.25E-02 Cerium-141 Ci <4.94E-02 <3.48E-02 <5.40E-02 <5.25E-02 Cerium-144 Ci <4.94E-02 <3.48E-02 <5.40E-02 <5.25E-02 lodine-131 Ci <9.88E-02 1.20E-05 . <1.0BE-01 <1.05E-01 Total for period* Ci O.OOE+OO 5.11E-05 O.OOE+OO O.OOE+OO Dissolved & Entrained Gases Xenon-133 Ci <9.88E-01 2.7'8E-05 <1.08E+OO <1.05E+OO Total for period* Ci O.OOE+OO 2.78E-05 O.OOE+OO O.OOE+OO Tritium Ci 2.17E+OO 1.45E+OO 1.77E+OO 1.91E+OO Gross Alpha Ci <9.88E-03 <6.96E-03 <1.0BE-02 <1.0SE-02

Less than values are not included in the summation for the total release values.

2018 Annual Radioactive Effluent Release Report

TABLE 3:

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Units 1-Year Est. Total

1. Type of Waste .

Period Error(%)

3*

a. Spent resins, filter sludges, evaporator bottoms, etc. m 3.06E+01 Ci 2.37E+02 2.50E+01 3*

b. Dry compressible waste, contaminated equip., etc. m 3.33E+02 Ci 1.29E-01 2.50E+01 3*

c. Irradiated components, control rods, etc. m 0.0 Ci 0.0 3*

d. Other m 5.66E+OO Ci 1.74E-05 2.50E+01

This is the volume sent offsite for volume reduction prior to disposal (waste volume).

2. Estimate of Major Nuclide Composition (by Type of Waste)

[Nuclides listed with % abundance greater than 10%]

a. Spent resins, filter sludges, evaporator bottoms, etc.

Nuclide % Abundance Curies Ni-63 83.02 1.97E+02

b. Dry compressible waste, contaminated equipment, etc.

Nuclide % Abundance Curies Co-58 51.01 6.56E-02 Co-60 24.66 3.17E:-02

c. Irradiated components, control rods, etc. - None

d. Other- Oil Nuclide % Abundance Curies Fe-55 11.81 2.05E-06 Co-60 58.78 1.02E-05 Ni-63 15.37 2.67E-06 2018 Annual Radioactive Effluent Release Report

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 10 Tru~ Energy Solutions (Hittman Transport Services) Oak Ridge, TN (Bear Creek) 1 Truck Energy Solutions (Hittman Transport Services) Erwin, TN (Resin Solutions) 1 Truck Alaron Corporation (Visionary Solutions, LLC) Wampum, PA

4. Class of Solid Waste

a. Class A, Class B, Class C - corresponding to 2a

b. Class A -Corresponding to 2b

c. Not applicable

d. Class A -Corresponding to 2d

5. Type of Container

a. LSA (General Design), Type A - corresponding to 2a

. b. LSA (General Design) - corresponding to 2b

c. Not applicable

d. LSA (General Design) - corresponding to 2d

6. Solidification Agent

a. Not applicable

b. Not applicable

c. Not applicable

d. Not applicable B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

No irradiated fuel shipments occurred during the 2018 period.

2018 Annual Radioactive Effluent Release Report

TABLE 4A: 2018 EFFLUENT CONCENTRATION LIMITS Average Diluted 10 CFR 20 Nuclides Curies Concentration EGL %EGL

(µCi/ml) (µCi/ml)

Tritium 1.02E+03 1.08E-06 1.00E-03 1.08E-01 Cobalt-58 8.44E-04 8.93E 2.00E-05 4.46E-06 Cobalt-60 7.12E-05 7.SSE-14 3.00E-06 2.52E-06 Nickel-63 1.68E-03 1.78E-12 1.00E-04 1.78E-06 Antimony-125 3.34E-03 3.54E-12 3.00E-05 1.18E-05 lodine-131 1.36E-04 1.44E-13 1.00E-06 1.44E-05

/odine-133 1.00E-05 1.06E-14 7.00E-06 1.51 E-07 Cesium-134 2.65E-05 2.81 E-14 9.00E-07 3.12E-06 Cesium-136 3.33E-06 3.53E-15 6.00E-06 5:88E-08 Cesium-137 2.90E-05 3.0?E-14 1.00E-06 3.0?E-06 Xenon-133m 7.52E-03 7.97E-12 2.00E-04 3.99E-06 Xenon-.133 8.12E-01 8.61E-10 2.00E-04 4.30E-04 Xenon-135 1.19E-03 1.25E-12 2.00E-04 6.26E-07 Krypton-85 2.11 E-02 2.23E-11 2.00E-04 1.12E-05 Xenon-131m 1.81 E-'02 1.92E-11 2.00E-04 9.61 E-06 2018 Annual Radioactive Effluent Release Report

TABLE 4B: 2018 UQUHl CUMULATIVE DOSE

SUMMARY

ODCM ODCM Limit % of Limit QUARTER 1 OF 2018 (MREM) Calculated Dose (mrem)

Total Dose for Bone 5.28E-04 5.00E+OO 1.06E-02 Total Dose for Liver 7.35E-02 5.00E+OO 1.47E+OO Total Dose for Total Body 7.35E-02 1.50E+OO 4.90E+OO Total Dose for Thyroid 7.35E-:02 5.00E+OO 1.47E+OO Total Dose for Kidney 7.35E-02 5.00E+OO 1.47E+OO Total Dose for Lung 7.35E-02 5.00E+OO 1.47E+OO Total Dose for GI-LU 7.35E-02 5.00E+OO 1.47E+OO QUARTER 2 OF 2018 (MREM)

Total Dose for Bone 3.92E-03 5.00E+OO 7.84E-02 Total Dose for Liver 1.14E-01 5.00E+OO 2.28E+OO Total Dose for Total Body 1.12E-01 1.50E+OO 7.47E+OO Total Dose for Thyroid 1.09E-01 5.00E+OO 2.18E+OO Total Dose for Kidney 1.09E-01 5.00E+OO 2.18E+OO Total Dose for Lung 1.07E-01 5.00E+OO 2.14E+OO Total Dose for GI-LU . 1.06E-01 5.00E+OO 2.12E+OO QUARTER 3 OF 2018 (MREM)

Total Dose for Bone 4.92E-05 5.00E+OO 9.84E-04 Total Dose for Liver 1.98E-02 5.00E+OO 3.96E-01 Total Dose for Total Body 1.98E-02 1.50E+OO 1.32E+OO Total Dose for Thyroid 1.98E-02 5.00E+OO 3.96E-01 Total Dose for Kidney 1.98E-02 5.00E+OO 3.96E-01 Total Dose for Lung 1.98E-02 5.00E+OO 3.96E-01 Total Dose for GI-LU 1.99E-02 5.00E+OO 3.98E-01 QUARTER 4 OF 2018 (MREM)

Total Dose for Bone

6.99E-05 5.00E+OO 1.40E-03 Total Dose for Liver 3.76E-02 5.00E+OO 7.52E-01 Total Dose for Total Body 3.76E-02 1.50E+OO 2.51E+OO Total Dose for Thyroid 3.75E-02 5.00E+OO 7.50E-01 Total Dose for Kidney 3.75E-02 5.00E+OO 7.SOE-01 Total Dose for Lung 3.75E-02 5.00E+OO 7.SOE-01 Total Dose for GI-LU 3.75E-02 5.00E+OO 7.50E-01 TOTALS FOR 2018 (MREM)

Total Dose for Bone 4.57E-03 1.00E+01 4.57E-02 Total Dose for Liver 2.45E-01 1.00E+01 2.45E+OO Total Dose for Total Body 2.43E-01 3.00E+OO 8.10E+OO Total Dose for Thyroid 2.40E-01 1.00E+01 2.40E+OO Total Dose for Kidney 2.40E-01 1.00E+01 2.40E+OO Total Dose for Lung 2.38E-01 1.00E+01 2.38E+OO Total Dose for GI-LU 2.37E-01 1.00E+01 2.37E+OO N

2018 Annual Radioactive Effluent Release Report 0

TABLE 4C:

LIQUID CUMULATIVE DOSE

SUMMARY

Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission & Activation Products*

Total Release (Ci) 3.03E-03 1.15E-03 1.57E-03 3.BsE:.04 6.14E-03 Maximum Organ Dose (mrem) 5.28E-04 7.46E-03 4.92E-05 8.17E-05 7.58E-03 Organ Dose Limit (mrem) 5.00E+OO 5.00E+OO 5.00E+OO 5.00E+OO 1.00E+01 Percent of Limit 1.06E-02 1.49E-01 9.83E-04 1.63E-03 7.58E-02 Tritium Total Release (Ci) 6.19E+02 2.31E+02 2.76E+01 1.38E+02 1.02E+03 Maximum Organ Dose (mrem) 7.35E-02 1.06E-01 1.98E-02 3.75E-02 2.37E-01 Organ Dose Limit (mrem) 5.00E+OO 5.00E+OO 5:00E+OO 5.00E+OO 1.00E+01 Percent of Limit 1.47E+OO 2.13E+OO 3.97E-01 7.SOE-01 2.37E+OO Dissolved & Entrained Gases I Total Release (Ci) I 4.60E-01 I 4.0QE,.Q1 I O.OOE+OO I O.OOE+OO I 8.60E-01 I Gross Alpha Radioactivity J Total Release (Ci) I O.OOE+OO I O.OOE+OO I O.OOE+OO I O.OOE+OO I O.OOE+OO I

Does not include H-3, gases or alpha 2018 Annual Radioactive Effluent Release Report

TABLE 4D: 2018 GASEOUS CUMULATHVE DOSE

SUMMARY

ODCM ODCM Limit % of Limit QUARTER 1 OF 2018 (MREM) Calculated Dose (mrem)

Total Dose for Bone 6.49E-07 7.50E+OO 8.65E-06 Total Dose for Liver 3.26E-03 7.50E+OO 4.35E-02 Total Dose for Total Body 3.26E-03 7.50E+OO 4.35E-02 Total Dose for Thyroid 3.48E-03 7.50E+OO 4.64E-02 Total Dose for Kidney 3.26E-03 7.50E+OO 4.35E-02 Total Dose for Lung 3.26E-03 7.50E+OO 4.35E-02 Total Dos*e for GI-LU 3.26E-03 7.50E+OO 4.35E-02 QUARTER 2 OF 2018 (MREM)

Total Dose for Bone 1.SOE-04 7.50E+OO 2.00E-03 Total Dose for Liver 1.12E-02 7.50E+OO 1.49E-01 Total Dose forTotal Body 1.11 E-02 7.50E+OO 1.48E-01 Total Dose for Thyroid 6.01E-02 7.50E+OO 8.01 E-01 Total Dose for Kidney 1.13E-02 7.50E+OO 1.51 E-01 Total Dose for Lung 1.10E-02 7.50E+OO 1.47E-01 Total Dose for GI-LU 1.10E-02 7.50E+OO 1.47E-01 QUARTER 3 OF 2018 (MREM)

Total Dose for Bone O.OOE+OO 7.50E+OO O.OOE+OO Total Dose for Liver 4.18E-03 7.50E+OO 5.57E-02 Total Dose for Total Body 4.18E-03 7.50E+OO 5.57E-02 Total Dose for Thyroid 4.18E-03 7.50E+OO 5.57E-02 Total Dose for Kidney 4.18E-03 7.50E+OO 5.57E-02 Total Dose for Lung 4.18E-03 7.50E+OO 5.57E-02 Total Dose for GI-LU 4.18E-03 7.50E+OO 5.57E-02 QUARTER 4 OF 2018 (MREM) /

Total Dose for Bone O.OOE+OO 7.50E+OO O.OOE+OO Total Dose for Liver 6.74E-03 7.50E+OO 8.99E-02 Total Dose for Total Body 6.74E-03 7.50E+OO 8.99E-02 Total Dose for Thyroid 6.74E-03 7.50E+OO 8.99E-02 Total Dose for Kidney 6.74Ea.03 7.50E+OO 8.99E-02 Total Dose for Lung 6.74E-03 7.50E+OO 8.99E-02 Total Dose for GI-LU 6.74E-03 7.50E+OO 8.99E-02 TOTALS FOR 2018 (MREM)

Total Dose for Bone 1.SOE-04 1.50E+01 1.00E-03 Total Dose for Liver 2.54E-02 1.50E+01 1.69E-01 Total Dose for Total Body 2.53E-02 1.50E+01 1.69E-01 Total Dose for Thyroid 7.45E-02 1.50E+01 4.97E-01 Total Dose for Kidney 2.55E-02 1.50E+01 1.70E-01 Total Dose for Lung 2.52E-02 1.50E+01 1.68E-01 Total Dose for GI-LU 2.52E-02 1.50E+01 1.68E-01 N

2018 Annual Radioactive Effluent Release Report N

TABLE 4E: 2018 GASEOUS CUMULATIVE DOSE

SUMMARY

I Quarter 1 I Quarter 2 I Quarter 3 *I Quarter 4 I Total .

Fission & Activation Gases Total Release (Ci) 3.48E+OO 1.99E+01 2.45E+OO 6.87E-02 2.59E+01 Total Gamma Air Dose (mrad) 1.67E-04 5.03E-04 3.91E-05 4.45E-05 7.54E-04 Gamma Air Dose Limit (mrad) 5.00E+OO 5.00E+OO 5.00E+OO 5.00E+OO 1.00E+01 Percent of Gamma Air Dose Limit 3.34E-03 1.01E-02 7.81 E-04 8.91 E-04 7.54E-03 Total Beta Air Dose (mrad) 2.82E-04 1.48E-03 3.39E-04 1.57E-05 2.11 E-03 Beta Air Dose Limit (mrad) 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+'01 Percent of Beta Air Dose Limit 2.82E-03 1.48E-02 3.39E-03 1.57E-04 1.06E-02 Particulates Total Particulates (Ci) O.OOE+OO 5.72E-06 O.OOE+OO O.OOE+OO 5.72E-06 Maximum Organ Dose (mrem) O.OOE+OO 3.0SE-06 O.OOE+OO 0.00E+OO 3.0SE-06 Organ Dose Limit (mrem) 7.50E+OO 7.50E+OO 7.50E+OO 7.50E+OO 1.50E+01 Percent of Limit O.OOE+OO 4.06E-05 *O.OOE+OO O.OOE+OO 1 2.03E-05 Tritium Total Release (Ci) 4.61E+OO 1.56E+01 5.91E+OO 9.53E+OO 3.56E+01 Maximum Organ Dose (mrem) 3.26E-03 1.10E-02 4.18E-03 6.74E-03 2.52E-02 Organ Dose Limit (mrem) 7.50E+OO 7.50E+OO 7.50E+OO 7.50E+OO 1.50E+01 Percent of Limit 4.35E-02 1.47E-01 5.57E-02 8.98E-02 1.68E-01 Iodine Total Release (C.i) 3.73E-07 8.53E-05 O.OOE+OO O.OOE+OO 8.57E-05 Maximum Organ Dose (mrem) 2.15E-04 4.91 E-02 O.OOE+OO O.OOE+OO 4.93E-02 Organ Dose Limit (mrem) 7.50E+OO 7.50E+OO 7.50E+OO 7.50E+OO 1.50E+01 Percent of Limit 2.86E-03 6.54E-01 O.OOE+OO O.OOE+OO 3.29E-01 2018 Annual Radioactive Effluent Release Report

CALCULATIONS:

Gases:

1. The percent of ODCM limit for fission and activation gases is calculated using the following methodology: (The larger value calculated between Gamma and Beta air dose is listed as the

% of ODCM Limit)

(Quarterly Total BetaAirdose)(100)

% of ODCM Limit= - - - - - - - - - - - - -

10 mrad OR (Quarterly Total Gamma Airdose)(100)

% of ODCM Limit= - - - - - - - - - - - - - -

5 mrad

2. The percent of ODCM limit for iodine is calculated using the following methodology:

(Total Curies of Iodine - 131)(100)

% of ODCM Limit= l C .

urze

3. The percent of ODCM limit for particulates is calculated using the following methodology:

(Highest Organ Dose due to Particulates)(100)

% of ODCM Limit= - - - - - - - - - - - - - - - - -

7.5 mrem

4. The percent of ODCM limit for tritium is calculated using the following methodology (this type of methodology is used since the Wolf Creek, ODCM ties release limits to doses rather than curie release rates:

(Highest Organ Dose due to H - 3)(100)

% of ODCM Limit= S

7. mrem

5. Less than values for Noble Gases are calculated using the* Lower Limit of Detection (LLD) values obtained at WCGS multiplied by the volume of air discharged during the respective quarter. For the Halogens and Particulates, the ODCM LLD values are used.

Liquids:

1. The Applicable Limit for fission and activation products at WCGS is 5 curies per year (reference 10CFR50, Appendix I, paragraph A2). The percent of Applicable Limit is derived by the following:

(Total Release Ci)(100)

% of Applicable Limit.= Ci 5

2. The percent of Applicable Limit for tritium is derived by the following formula:

(Average Diluted Concentration)(100)

% of Applicable Limit= (ECL*) .

The ECL can be found in 10CFR20, Appendix B, Table 2 2018 Annual Radioactive Effluent Release Report

3. The percent of Applicable Limit for dissolved and entrained gases is derived by the following formula:

(Average Diluted Concentration) (100)

% of Applicable Limit= . * (Z.OOE _ 04 *)

From ODCM, section 2.1

4. Less than values are calculated using the Lower Limit of Detection (LLD) values listed in Table 2-1 of the ODCM multiplied by the volume of waste discharged during the respective quarter.

The less than values are not included in the summation for the total release values.

N 2018 Annual Radioactive Effluent Release Report u,

AppendixB Meteorological Data I\).

2018 Annual Radioactive Effluent Release Report en

HOURS AT EACH WIND SPEED AND DIRECTION This section documents WCGS meteorological data for wind speed, wind direction, and atmospheric stability.

The meteorological data supplied in the following tables covers the period from January 1, 2018, through December 31,' 2018, and ind_icates the number of hours at each wind speed and direction for each stability class. All gaseous releases at the WCGS are ground level releases.

WCGS did not meet Regulatory Guide 1.23 requirement for data recovery, for all instruments. The 60 Meter Wind Direction, due to instrument problems and weather concerns in the fourth quarter, had an 89.89% data recovery. Condition Report 131756 was written on the issue and work orders have since been completed fixing the issues. The 60 Meter Temperature instrument had an 88.97% data recovery for 2018, due to issues in the third quarter which calibration performance resolved. The remaining instruments, both at 10 and 60. meters, met or exceeded a 90% meteorological data recovery for 2018.

2018 Annual Radioactive Effluent Release Report

Hours At Each Wind Speed and Direction Period of Record: JANUARY 1 THROUGH DECEMBER 31, 2018 Stability Class: A Elevation: 10 Meters Wind Speed (mph)

-Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total Cardinals N 0.75 8.50 12.25 7.75 2.00 0.00 31.25 NNE 5.75 30.25 24.50 3.75 2.00 0.00 66.25 NE 4.50 36.50 12.25 2.25 0.00 0.00 55.50 ENE 6.00 36.00 22.75 1.00 0.00 0.00 65.75 E 5.25 34.50 25.75 6.00 0.00 0.00 71.50 ESE 5.50 22.50 24.25 1.75 0.00 0.00

54.00 SE 7.50 44.25 42.50 10.50 0.50 0.00

105.25 SSE 6.25 57:25 84.25 49.50 4.25 0.50 202.00 s 3.00. 42.50 68.75 139.25 83.00 20.00 356.50 SSW 2.50 21.75 46.50 55.50 10.00 4:00 140.25 SW 7.00 22.00 23.25 3.00 0.00 0.00 55.25 WSW 8.75 26.50 16.25 8.00 0.00 0.00 59.50 w 4.75 31.25 29.00 6.75 0.50 0.00 72.25 WNW 3.00

29.50 28.25 14.00 7.75 3.50 86.00 NW . 2.50 20.50 20.75 7.00 4.75 4.50 60.00 NNW 1.50 12.00 20.00 17.00 4.00 0.75 55.25 Total . 74.50 475.75 501.25 333.00 118.75 33.25 1536.50 Hours of Calm (<1.0 mph): 16.50 2018 Annual Radioactive Effluent Release Report

Hours At Each Wind Speed and Direction Period of Record: JANUARY 1 THROUGH DECEMBER 31, 2018 Stability Class: B Elevation: 10 Meters Wind Speed (mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total Cardinals N 0.00 3.00 7.75 7.50 1.50 0.00 19.75 NNE 1.25 6.25 8.75 1.00 0.50 0.00 17.75 NE 0.75 8.50 4.50 0.00 0.00 0.25 14.00 ENE 0.50 5.25 7.75 0.25 0.25 0.00 14.00 E 0.75 2.25 6.00 1.25 0.00 0.00 10.25 ESE 0.25 3.00 7.00 0.25 0.00 0.00 10.50 SE 1.50 3.75 7.75 2.75 0.00 0.00 15.75 SSE 1.00 11.00 17.00 9.25 2.25 0.00 40.50 s 1.75 7.50 18.50 20.75 5.25 2.00 55.75 SSW 0.00 5.00 12.25 7.75 0.75 0.25 26.00 SW 1.25 5.25 4.00 1.50 0.25 0.00 12.25 WSW 1.50 5.75 2.25 0.50 2.50 0.00 12.50 w 0.50 7.50 5.50 2.00 0.00 1.00. 16.50 WNW 0.50 6.00 2.25 4.00 1.50 1.00 15.25 NW 0.25 4.00 7.75 2.75 3.75 4.00 22.50 NNW 0.50 3.25 12.50 11.25 5.75 1.00 34.25 Total 12.25 87.25 131.50 72.75 *24.25 9.50 337.50 Hours of Calm (<1.0 mph): 3.75 2018 Annual Radioactive Effluent Release Report

Hours At Each Wind Speed and Direction Period of Record: JANUARY 1 THROUGH DECEMBER 31, 2018 Stability Class: C Elevation:

1O Meters Wind Speed (mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total Cardinals N 0.00, 3.50 15.25 10.25 2.25 0.25 31.50 NNE 0.75 16.50 15.00 7.00 2.50 0.00 41.75 NE 1.25 10.75 6.25 0.50 0.00 0.00 18.75 ENE 1.00 8.25 7.00 1.00 0.00 0.00 17.25 E 1.25 3.75 5.00 1.25 0.00 0.00 11.25 ESE 0.75 4.75 6.75 0.00 0.00 0.00 12.25 SE 0.50 7.00 11.50 3.00 0.00 0.00 22.00 SSE

1.00 14.25 13.25 10.00 2.00 0.25 40.75 s 1.00 10.50 15.25 23.00 7.00 2.75 59.50 SSW 1.50 5.75 8.75 5.75 1.00 0.25. 23.00 SW 2.25 7.00 3.25 0.50 0.00 0.00 13.00 WSW 2.25 8.00 4.00 4.00 0.50 0.00 18.75 w 1.25 7.50 1.75 2.75 2.50 1.25 17.00 WNW 0.75 6.25 0.75 6.50 6.25 1.25 21..75 NW 0.50 3.50 11.25 10.50 4.00 3.75 33.50 NNW 0.00 3.75 13.00 9.00 10.75 2.25 38.75 Total 16.00 121.00 138.00 95.00 38.75 12.00 420.75 Hours of Calm (<1.0 mph): 6.50 w

C) 2018 Annual Radioactive Effluent Release Report

r-------

Hours At Each Wind Speed and Direction Period of Record: JANUARY 1 THROUGH OECEMBER 31, 2018 Stability Class: D Elevation: 10 Meters Wind Speed (mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total Cardinals N 3.50 37.00 101.50 106.00 23.25 .2.50 273.75 NNE 13.00 93.25 93.75 47.50 3.75 0.75 252.00 NE 16.25 65.50 33.75 3.50 0.50. 1.00 120.50 ENE 15.00 43.50 29.50 11.50 1.25 0.50 101.25 E 18.50 56.25 38.50 6.50 0.50 0.75 121.00 ESE 13.75 51.25 33.75 8.00 2.00 0.50 109.25 SE 6.25 37.25 63.25 22.25 3.75 1.75 134.50 SSE 7.25 57.50 136.00 80.00 13.00 0.75 294.50.

s 8.50 35.00 123.50 150.25 48.25 10.75 376.25 SSW 7.00 26.75 88.75 37.75 12.75 5.00 178.00 SW 7.75 32.75 19.50 7.75 0.50 0.00 68.25 WSW. 5.75 15.50 15.50 9.25 2.00 2.50 50.50 w 3.25 18.00 21.50 15.50 11.50 2.75 72.50 WNW 1.25 16.75 36.50 31.75 15.75 1.00 103.00 NW 4.25 27.00 66.00 59.75 19.00 6.50 182.50 NNW 7.25 56.25 143.25 88.50 34.00 9.25 338.50 Total 138.50

669.50 1044.50 685.75 J 191.75 46.25 2776.25 Hours of Calm (<1.0 mph): 70.00 2018 Annual Radioactive Effluent Release Report

Hours At Each Wind Speed and Direction Period of Record: JANUARY 1 THROUGH DECEMBER 31, 2018 Stability Class: E Elevation: 1O Meters Wind Speed (mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total Cardinals N 4.75 33.00 30.00 4.25 0.25 0.75 73.00 NNE 22.50 56.00 11.75 0.25 0.25 0.50 91.25 NE 24.00 38.75 9.75 0.75 0.00 0.25 73.50 ENE 22.00 54.75 22.00 1.25 0.00 0.00 100.00 E 24.75 54.00 23.00 0.75 0.25 0.25 103.00 ESE 22.25 86.50 25.75 5.00 0.25 0.00 139.75 SE 20.25 104.50 58.00 18.00 1.50 0.00 202.25 SSE 8.00 114.50 190.00 83.75 12.50 1.00 409.75 s 5.75 52.25 137.75 88:75 50.50 11.25 346.25 SSW 9.50 47.50 64.00 13.00 0.75 0.00 134.75 SW 21.75 55.75 6.75 1.75 1.25 0.00 87.25 WSW 7.75 24.00 9.25 0.75 0.25 0.25 42.25 w 4.50 20.00 8.50 2.25 0.75 0.25 36.25 WNW 3.50 19.50 16.00 1.75 0.75 0.25 41.75 NW 5.75 35.75 24.75 2.50 0.00 0.25 69.00 NNW 5.75 52.50 43.00 8.25 0.00 0.50 110.00 Total 212.75 849.25 680.25 233.00 69.25 15.50 2060.00 Hours of Calm (<1.0 mph): 47.25 2018 Annual Radioactive Effluent Release Report

Hours At Each Wind Speed and Direction Period of Record: JANUARY 1 THROUGH DECEMBER 31, 2018 Stability Class: F Elevation: 1O Meters Wind Speed {mph)

Wind*

Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total Cardinals N 5.25 33.75 3.50 0.00 0.00 0.00 42.50 NNE 23.25 38.50 .. 1.75 0.00 0.00 0.00 63.50 NE 21.25 23.75 0.75

0.00 0.00 0.00 45.75 ENE 13.50 45.50 3.75* 0.00 0.00 0.00 62.75 E 23.25 63.50 5.75

0.00 0.00 0.00 92.50 ESE 27.75 86.50 . 4.25 0.00 0.00 0.00 118.50 SE 31.25 74.25 9.50 0.25 0.00 0.00 115.25 SSE 14.00 58.50 28.25 9.25 .1.00 0.50 111.50 s 7.75 18.50 34.00 17.50 2:00 0.50 80.25 SSW 5.25 10.25 7.75 0.00 0.00 0.00 23.25 SW 6.50 17.50 1.50 0.25 0.00 0.50 26.25 WSW 7.00 8.25 4.00 0.25 0.00 0.00 19.50 w 3.00 7.50 2.00 0.00 0.00 0.00 12.50 WNW 4.50 4.00 0.00 0.00 0.00 0.50 - 9.00 NW 9.50 15.50 2.25 0.00 0.00 0.75 28.00 NNW 11.50 41.75 4.00 0.00 0.00 0.25 57.50 Total 214.50 547.50 113.00 27.50 3.00 3:00 908.50 Hours of Calm (<1.0 mph): 4.00 2018 Annual Radioactive Effluent Release Report

Hours At Each Wind Speed and Direction Period of Record: JANUARY 1 THROUGH DECEMBER 31, 2018 Stability Class: G Elevation: 1O Meters Wind Speed (mph)

('

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total Cardinals N 7.50 21.25 3.25 0.00 0.00 0.00 32.00 NNE 25.75 45.50 1.00 0.00 0.00 0.00. 72.25

NE 36.50 24.75 0.25 0.00 0.00 0.00 61.50 ENE 18.00 30.50 1.50 0.00 0.00 0.00 50.00 E 21.00 48.25 2.00* 0.00 0.00 0.00 71.25 ESE 24.25 60.00 0.50 0.00 0.00 0.00 84.75 SE 19.00 39.00 0.50 0.00 0.50. 0.00 59.00 SSE 9.25 22.50 2.25 1.00 0.25 0.00 35.25 s 3.50 5.75 0.75 0.25 0.25 0.25 10.75 SSW 6.75 0.75 0.75 0.00 0.00 0.25 8.50 SW 1.75 3.25 0.25 0.00 0.00 0.25 5.50 WSW 5.25 1.50 0.00 0.00 0.00 0.25 7.00 w 3.50 .1.25 0.25 , 0.00 . 0.00 0.25 5.25 WNW 5.75 0.75 0.00 0.00 0.00 0.25 6.75 NW 6.75 12.00 0.25 0.00 0.00 0.00 19.00 NNW

13.75 20.75 2.00 0.00 0.00 0.00 36.50 Total 208.25 337.75 15.50 1.25 1.00 1.50 565.25 Hours of Calm (<1.0 mph): 3.00 2018 Annual Radioactive Effluent Release Report

Hours At Each Wind Speed and Direction Period of Record: JANUARY 1 THROUGH DECEMBER 31, 2018 Stability Class: ALL Elevation: 1O Meters Wind Speed (mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total Cardinals N* 21.75 140.00 173.50 135.75 29.25 3.50 503.75 NNE 92.25 286.25 156.50 59.50 9.00 1.25 604.75 NE 104.50 208.50 67.50 7.00 0.50 1.50 389.50 ENE 76.00 223.75 94.25 15.00 1.50 0.50 411.00 E 94.75 262.50 106 ..00 15.75 0.75 1.00 480.75 ESE 94.50 314.50 102.25 15.00 2.25 0.50 529.00 SE 86.25 310.00 193.00 56.75 6.25 1.75 654.00 SSE 46.75 335.50 471.00 242.75 35.25 3.00 1134.25 s 31.25 172.00 398.50 439.75 196.25 47.50 1285.25 SSW 32.50 117.75 228.75 119.75 25.25 9.75 533.75 SW 48.25 143.50 58.50 14.75 2.00 0.75 267.75 WSW 38.25 89.50 51.25 22:75 5.25 3.00 210.00 w 20.75 93.00 68.50 29.25 15.25 5.50 232.25 WNW 19.25 82.75 83.75 58.00 32.00 7.75 283.50 NW 29.50 118.25 133.00 82.50 31.50 19.75 414.50 NNW 40.25 190.25 237.75 134.00 54.50 14.00 670.75 Total 876.75 3088.00 2624.00 1448.25 446.75 121.00 8604.75 Hours of Calm (<1.0 mph): 151.00 Maximum Hours of invalid Data:* 2043.50 2018 Annual Radioactive Effluent Release Report

Appendix C ONSITE GROUNDWATER PROTECTION PROGRAM MONITORING

\

w 2018 Annual Radioactive Effluent Release Report en

Objective The objective of onsite groundwater protection program monitoring is to ensure timely detection of inadvertent radiological releases to ground water. At the Wolf Creek Generating Station, some background tritium influences from lake water reuse are normal *and expected.

Basis The onsite groundwater protection program monitoring sample results are being reported in the Radioactive Effluent Release Report per guidance received in association with the Nuclear Energy Institute (NEI) Groundwater Protection Industry Initiative. The following information is also being reported in association with the NEI Groundwater Protection Industry Initiative:

1. Describe any onsite licensed radioactive materials releases or spills that were voluntarily communicated to State/Local officials during the calendar year. - None

2. Describe any onsite groundwater sample results that exceeded the reporting thresholds that were voluntarily communicated to State/Local officials during the. calendar year. - None There were no radioactive materials releases, spills, or reporting level exceedances reported to State/Local officials during 2018.

Onsite Groundwater Protection Program Monitoring Description In March of 2006, Wolf Creek Generating Station (WCGS) established an onsite groundwater protection monitoring program. During 2008, thirteen monitoring wells were added *to the onsite groundwater protection monitoring program. During 2018, an additional five wells were installed. The onsite groundwater protection program monitoring is implemented via procedure Al 07-007, Onsite Groundwater Protection Program Monitoring. The onsite groundwater samples were collected by the WCGS Environmental Management group and were analyzed, by Environmental, Inc., Midwest Laboratory. Onsite groundwater samples were collected quarterly when available and were analyzed by gamma isotopic analysis, radiochemical analysis for 1-131 and tritium analysis. The vendor lab (Environmental, Inc., Midwest Laboratory) participated in an interlaboratory comparison program. The following tables describe the sample locations, the lower limits of detection and the reporting levels for radioactivity detected.

2018 Annual Radioactive Effluent Release Report

Sample Location Sample Location Description AUX Dewatering Well located near the Auxiliary Building, on East Side EAST ESW-W Essential Service Water Dewatering Well, East Group, West well,

-- located southeast of the reactor MW-01A Monitoring Well, shallow depth, located northeast of the reactor (control sample location)

MW-018 Monitori_ng Well, mid-range depth, located northeast of the reactor *

(control sample location)

MW-01C Monitoring Well, deep depth, located northeast of the reactor (control sample location) \

MW-02A Monitoring Well, shallow depth, located northwest of the reactor -

MW-028 Monitoring Well, mid-range depth, located northwest of the reactor MW-03A Monitoring Well, shallow depth, located southwest of the reactor MW-038 Monitoring Well, mid-range depth, located southwest of the re.actor MW-03C Monitoring Well, deep depth, located southwest of the reactor MW-05C Monitoring Well, deep depth, located south of the reactor MW--:11A Monitoring Well, shallow depth, located southwest of the reactor MW-118 Monitoring Well, mid-range depth, located southwest of the reactor MW-12A Monitoring Well, shallow depth, located south of the reactor MW-128 Monitoring Well, mid-range depth, located south of the reactor MW-13 Monitoring Well, mid-range depth, located south of the reactor MW-14 Monitoring Well, mid-range depth, located southeast of the reactor MW-15 Monitoring Well, mid-range depth, located southeast of the reactor MW-16 Monitoring-Well, mid-range depth, located southeast of the reactor MW-17 Monitoring Well, mid-range depth, located southeast of the reactor WESTESW-W Essential Service Water Dewatering Well, West Group, West well, located south of the reactor Onsite Groundwater Lower Limits of Detection Analysis (pCi/L) Analysis (pCi/L)

H-3 2,000 Zr-Nb-95 15 Mn-54 15 1-131 1 Co-58 15 Cs-134 15 Fe-59 30 Cs-:137 18 Co-60 15 Ba-La-140 15.

Zn-65 30 w

2018 Annual Radioactive Effluent Release Report co

Reporting Levels for: Radioactivity Detected in Onsite Groundwater Analysis (pCi/L) Analysis (pCi/L)

H-3 20,000 Zr-Nb-95 400 Mn-54 1,000 1-131 2 Co-58 1,000 Cs-134 30 Fe-59 400 Cs-137 50 Co-60 300 Ba-La-140 200 Zn-65 300 Discussion of Results Low levels of tritium were detected in an Essential Service Water dewatering well (EAST ESW-W),

MW-15, MW-17, MW-12A and in the dewatering well located near the Auxiliary Building (AUX), all within areas. of backfill during plant construction. This has been attributed to the Pla_nt's reuse of

tritiated lake water and is consistent with gaseous tritium deposition during normal operation. Lake water is used for plant cooling, which includes- essential service water, and in the Fire Protection System.

The monitoring well sample with the highest level of tritium detected (590 +/- 102 pCi/L) was collected on 02-26-18 from the MW-15 location. The measured monitoring well tritium levels are significantly

lower than the tritium levels routinely detected in surface water collected from Coffey County Lake (2018 range was 9,101 to 14,775 pCi/L).

The tritium activity was the only activity detected in the orisite gro1..mdwater samples. Lower limits of

_detection were met and sample analysis results were below the applicable reporting levels.

Subsurface Water V

Due to Industry Operating Experience, the Wolf Creek Generating Station started collecting and analyzing subsurfacewater during 2010. Subsurface water monitoring is a portion of the Groundwater Protection Program and is implemented via procedure Al 07-007, Onsite Groundwater Protection Program Monitoring. The definitions for subsurface water include:

1. Water that is encountered below grade while excavating, trenching, or drilling outside of the Radiologically Controlled Area and within the area displayed in Figure 1 (of Al 07-007). This excludes recent rainfall build.:up in open excavation trenches. *

2. Water. that is encountered below grade or water that needs to be removed that is outside of a building, *outside of the Radiologically Controlled Area and within the area displayed in Figure 1 (of Al 07-007). Examples include electrical vaults, piping vaults, valve pits, manholes, concrete pits, etc. Excludes removing water from powerblock sumps, sanitc;1ry sewers, spill containment berms _or.

from within buildings.

The subsurface water samples were analyzed by the WCGS Chemistry Laboratory and the results were* reviewed by Environmental Management. The- subsurface water samples were analyzed for tritium. The following table identifies the sample dates, sample locations, and the analysis results.

w 2018 Annual Radioactive Effluent Release Report CD

Date Location Description Tritium (pCi/L}

01/30/18 CW-1 (1 CW0006C) Manhole North of the Turbine Building 18,420 01/31/18 CW-1 (1 CW0006C) Manhole North of the Turbine Building 17,062 03/20/18 EMH101 Electrical Manhole North of the Turbine Building <2,210 03/20/18 EMH102 Electrical Manhole NW of Maintenance Shop <1,990 03/20/18 EMH104 Electrical Manhole West of Shop Building <1,742 03/20/18 EMH105 Electrical Manhole West of Olive Ann Beech Building. <1,938 05/01/18 CW-1 (1 CW0006C) Manhole North of the Turbine Building <2,402 05/29/18 Dewaterino Well #1 (1 DW0001) - East of the Turbine Buildino 10,000 05/29/18 Dewatering Well #5 (1 DW0005) - West of Hot Machine Shop 3,580 05/29/18 Dewatering Well #7 (1 DW0007) - SW of Com. Corridor 4,200 XMA01A, XMA01B, XMA01C & XMA02 Transformer Discharge 07/10/18 Vault, Sump 097 (Main); Transformer NW of Turbine Building <1,847 XMA01 D Transformer Discharge Vault, Sump 0725; 07/10/18 Transformer NW of Turbine Building <1,830 XMR01 Transformer Discharge Vault, Sump 096; Transformer 07/10/18 NW of Turbine Building <2,176 XNB01 & XNB02 Transformer Discharge Vault, Sump 095; 4,809 07/10/18 Transformer NW of Turbine Building 07/30/18 CW-1 (1 CW0006C) Manhole North of the Turbine Building <1,920 07/30/18 CW-3 (1 CW0008C) Manhole near the Radwaste Building 2,386 08/27/18 CW-1 (1 CWOOb6C) Manhole North of the Turbine Building <;:2,071 08/27/18 CW-2 (1 CW0007C) Manhole East of Condensate Storage Tank <2,233 08/27/18 CW-3 (1 CW0008C) Manhole near the Radwaste Building <1,950 08/27/18 Dewaterino Well #1 (1 DW0001) - East of the Turbine Buildino 10,000 08/27/18 Dewatering Well #5 (1 DW0005) -West of Hot Machine Shop 3,580 08/27/18 Dewatering Well #7 (1 DW0007) - SW of Com. Corridor 4,200 09/25/18 EMH105 Electrical Manhole West of Olive Ann Beech Building. <2,051 09/25/18 EMH105 Electrical Manhole West of Olive Ann Beech Building. <1,757 09/25/18 EMH105 Electrical Manhole West of Olive Ann Beech Building. <1,896 09/25/18 EMH105 Electrical Manhole West of Olive Ann Beech Building. 5,883 09/26/18 AUX remediation well located near CST 5,832 10/08/18 EMH105 Electrical Manhole West of Olive Ann Beech Buildino. <.j ,827 10/08/18 EMH119 located NW of Main and Aux. Yard Transformers 2,'299 10/08/18 EMH 120 located NE of Turbine Building 1,870 10/08/18 EMH137 between Security Building and Containment. 5,346 10/16/18 CW-3 (1 CW0008C) Manhole near the Radwaste Building <1,937 10/16/18 EMH104 West of the Mechanical Maintenance Shop <2,034 10/29/18 CW-1 (1 CW0006C) Manhole North of the Turbine Buildino 4,799 11/26/18 Dewatering Well #1 (1DW0001) - East of the Turbine Building <2, 122 11/26/18 Dewatering Well #2 (1 DW0002) - East of the Turbine Building 14,110 11/26/18 Dewatering Well #3 (1 DW0003) - West of the Turbine Building <1,866

.* 11/26/18 Dewatering Well #5 (1 DW0005) - West of Hot Machine Shop <2,412 11/26/18 Dewatering Well #7 (1 DW0007) - SW of Com. Corridor 6,676 12/10/18 EMH104 Electrical Manhole West of Shop Building <1,938 12/10/18 EMH 119 Electrical Manhole NW of Main & Aux. Transformers 4,747 12/10/18 EMH125 Electrical Manhole East of Turbine Building 2,610 12/10/18 ~MH135 Electrical Manhole West of Radwaste Building <1,872 2018 Annual Radioactive Effluent Release Report

As expected, tritium activity was detected in some of the subsurface water samples. The highest detected tritium measured was 18,420 pCi/L in a sample collected 01-30-18 from manhole CW-1 (1 CW0006C) located north of the Turbine Building. Gamma activity was not detected in the Of-30-18

subsurface water sample. Again, the detected tritium activity is likely due to the Plant's reuse of tritiated lake water. Lake water is used for plant cooling, which includes essential service water, and in the Fire Protection System. The measured tritium levels from subsurface water monitoring were lower than the onsite groundwater tritium reporting level of 20,000 pCi/L. Condition Report 119118 was created to document occurrence. Follow-up analysis detect~d 17,062 pCi/L.

Conclusion Based upon the results . of the water samples that were analyzed in association with the Onsite Groundwater Protection Program, no inadvertent radiological releases to ground water were identified.

2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE AUX 26-Sep-18 H-3 5183 +/-

EAST ESW-W 26-Feb-18 MN-54 < 3.2 EAST ESW-W 26-Feb-18 C0-58 < 2.3 EAST ESW-W 26-Feb-18 FE-59 < 4.4 EAST ESW-W 26-Feb-18 C0-60 < 1.7 EAST ESW-W 26-Feb-18 ZN-65 < 4.7

. EASTESW-W 26-Feb-18 ZR-NB-95 < 3.4 EASTESW-W 26-Feb-18 1-131 < 0.31

, EAST ESW-W 26-Feb-18 CS-134 < 2.7 EAST ESW-W 26-Feb-18 CS-137 < 2.7 EAST ESW-W 26-Feb-18 BA-LA-140 < 2.6 EAST ESW-W 26-Feb-18 H-3 < 162 EAST ESW-W 02-May-18 MN-54 < 2.6 EAST ESW-W 02-May-18. C0-58 < 3.1 EASTESW-W 02-May-18 FE-59 < 4.6 EASTESW-W 02-May-18 C0-60 < 2.4 EASTESW-W 02-May-18 ZN-65 < 3.4 EASTESW-W 02-May-18 ZR-NB-95 < 2.8 EASTESW-W 02-May-18 1-131 < 0.303 EAST ESW-W 02-May-18 CS-134 < 2.6 EASTESW-W 02-May-18 CS-137 < 2.9 EAST ESW-W 02-May-18 BA-LA-140. < 3.8 EAST ESW-W 02-May-18 H-3 180 +/- 102 EAST ESW-W 29-Aug-18 MN-54 < 1.8 EAST ESW-W 29-Aug-18 C0-58 < 1.3 EAST ESW-W 29-Aug-18 FE-59 < 5.3 EAST ESW-W 29-Aug-18 C0-60 < 1.3 EAST ESW-W 29-Aug-18 ZN-65 < 5 EAST ESW-W 29-Aug-18 ZR-NB-95 < 3.4 EAST ESW-W 29-Aug-18 1-131 < 0.479 EASTESW-W 29-Aug-18 CS-134 < 3 EAST ESW-W 29-AUQ-18 CS-137 < 3 EASTESW-W 29-AuQ-18 BA-LA-140 < 3.5 EASTESW-W 29-AUQ-18 H-3 < 156 EASTESW-W 04-Dec-18 MN-54 < 3.6 EAST ESW-W 04-Dec-18 C0-58 < 1.8 EAST ESW-W 04-Dec-18 FE-59 < 6.9 EAST ESW-W 04-Dec-18 C0-60 < 3.7 EAST ESW-W 04-Dec-18 ZN-65 < 7.2 EAST ESW-W 04-Dec-18 ZR-NB-95 < 4 EAST ESW-W . 04-Dec-18 1-131 < 0.319 2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results

. Concentration (pCi/L)

LOCATION -DATE NUCLIDE ACTIVITY SIGN ERROR NOTE EAST ESW-W 04-Dec-18 CS-134 < 4.1 EAST ESW-W 04-Dec-18 CS-137 < 3.7 EASTESW-W 04-Dec-18 BA-LA-140 < 1.9 EAST ESW-W 04-Dec-18 H-3 189 +/- 82 MW-01A 26-Feb-18 MN-54 < 3.9 MW-01A . 26-Feb-18 C0-58 < 2.5 MW-01A 26-Feb-18 FE-59 < 4.2

, MW-01A 26-Feb-18 C0-60 < 4 MW.,.01A 26-Feb-18 ZN-65 < 8.1 MW-01A 26-Feb-18 ZR-NB-95 < 2 MW-01A 26-Feb-18 1-131 < 0.304 MW-01A 26-Feb-18 CS:-134 < 3.7 MW-01A 26-Feb-18 CS-137 < .4 MW-01A 26-Feb-18 BA-LA-140 < 4*

MW-01A 26-Feb-18 H-3 < 155 MW-01A 02-May-18 MN-54 < 4.3 MW-01A 02-May-18 C0-58 < 2.3 MW-01A 02-May-18 FE-59 < 2.7 MW-01A 02-Mav-18 C0-60 < 4 MW-01A 02-May-18 ZN-65 < 5.4 MW-01A 02-May-18 ZR-NB-95 < 2.8 MW-01A 02-May-18 1-131 < 0.321 MW-01A 02-May-18 CS-134 < 4.9 MW-01A . 02-May-18 CS-137 < 4.5 MW-01A 02-May-18 BA-LA-140 < 1.9 MW-01A 02-May-18 H-3 < 154 MW-01A 29-Aug,.18 MN-54 < 2.1 MW-01A 29-Aug-18 C0-58 < 2.5 MW-01A 29-Aug-18 FE-59 < 4 MW-01A 29-AuQ-18 C0-60 < 1.2 MW-01A 29-AuQ-18. ZN-65 < 3.5 MW-01A 29-Aug-18 ZR-NB-95 < 3.2 MW-01A 29-Aug-18 1-131 < 0.442

MW-01A 29-Aug-18 CS-134 < 3.1 MW-01A Aug-18 CS-137 < 3.2 MW-01A 29-AUQ-18 BA-LA-140 < 2.6 MW-01A 29-AUQ-18 H-3 < 156 MW-01A 05-Dec-18 MN-54 < 2.5 MW-01A 05-Dec-18 C0-58 < .3.4 MW-01A 05-Dec-18 FE-59 < 6_.3 2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-01A 05-Dec-18 C0-60 < 2.2 MW-01A 05-Dec-18 ZN-65 < 6.8 MW-01A 05-Dec-18 ZR-NB-95 < 2.6 MW-01A 05-Dec-18 1-131 < 0.467 MW-01A 05-Dec-18 CS-134 < 3.8 MW-01A 05-Dec-18 CS-137 < 3.2 MW-01A 05-Dec-18 BA-LA-140 < 4.1 MW-01A 05-Dec-18 H-3 < 157 MW-018 26-Feb-18' MN-54 < 2.7 MW-018 26-Feb-18 C0-58 < 2.4 MW-018 26-Feb-18 FE-59 < 3.5 MW-018 *26-Feb-18 C0-60 < 1.9 MW-018 26-Feb-18 ZN-65 <

5.7 MW-018 26-Feb-18 ZR-NB-95 < 2.2 MW-018 26-Feb-18 1-131 * < 0.25 MW-018 26-Feb-18 CS-134 < 3 MW-018 26-Feb-18 ,CS-137 < 3.1 MW-018 26-Feb-18 BA-LA-140 ' < 3.2 MW-018 26-Feb-18 H-3 < 155 MW-018 02-Mav-18 MN-54 < 2.1 MW-018 02-May-18 C0-58 < 3.2

. MW-018 02-May-18 FE-59 < 4.9

.MW-018 02-May-18 C0-60 < 1.2 MW-018 02-May-18

ZN-65 < 2.7 MW-018 02-May-18 ZR-NB-95 < 2 MW-018 02-May-18 1-131 < 0.472 MW-018 02-May-18 CS-134 < 3.2 MW-018 02-May-18 CS-137 < 2.6 MW-018 02-May-18 BA-LA-140 <* 3 MW-018 02-May-18 *' H-3. < 156 MW-018 29-Auo-18 MN-54 < 1.2 MW-018 29-Auo-18 C0-58 < 3.1 1 MW-018 29-Aug-18 '* FE-59 < 6.3 MW-018 29-Aug-18 C0-60 < 2.3 MW-018 29-Aug-18 ZN-65 < 3.5 MW-018 29-Aug-18 ZR-NB-95 < 3.6 MW-018 29-Aug-18 1-131 < 0.462 MW-018

29-Aug-18 CS-134 < 3.8 MW-018 29-Aug-18 CS-137 < 3.2 MW-018 29-Aug-18 BA-LA-140 < 2.2 2018 Annual Radioactive Effluent Release Report /

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE . NUCLIDE ACTIVITY . SIGN ERROR NOTE MW-018 29-Aug-18 H-3 < 156 MW-018 04-Dec-18 MN-54 < 2.2 MW-018 04-Dec-18 C0-58 < 2.2 MW-018 04-Dec-18 FE-59 < 4.4 MW-018 04-Dec-18 C0-60 < 2.5 MW-018 04-Dec-18 ZN-65 < 2.9 MW-018 04-Dec-18 ZR-NB-95 < 3.4 MW-018 04-Dec-18 1-131 < 0.28 MW-018 04-Dec-18 CS-134 < 3.5 MW-018 04-Dec-18 CS-137 < 3.9 MW-018 04-Dec-18 BA-LA-140 < 1.5 MW-018 04-Dec-18 H-3 < 153 MW-01C 26-Feb-18 MN-54 < 2 MW-01C 26-Feb-18 C0-58 < 2.3 MW-01C 26-Feb-18 FE-59 < 4.3 MW-01C 26-Feb-18 C0-60 < 2.2 MW-01C 26-Feb-18 ZN-65 <* 3.8 MW-01C 26-Feb-18 ZR-NB-95 < 3.2 MW-01C 26-Feb-18 1-131 < 0.293 MW-01C 26-Feb-18 CS-134 < 3.4 MW-01C 26-Feb-18 CS-137 < 2.9 MW-01C 26-Feb-18 BA-LA-140 < 2 MW-01C 26-Feb-18 H-3 < 155 MW-01C 02-May-18 MN-54 < 2.4 MW-01C 02-May-18 C0-58 < 1.9 MW-01C 02-May-18 FE-59 < 4.5 MW-01C 02-May-18 C0-60 < 2.1 MW-01C 02-May-18 ZN-65 < 3.3 MW-01C 02-May-18 ZR-NB-95 < 1.9 MW-01C 02-May-18 1-131 < 0.423 MW-01C 02-May-18 CS-134 < 3.4 MW-01C 02-Mav-18 CS-137 < 2.4 MW-01C 02-Mav-18 BA-LA-140 < 3.2 MW-01C 02-Mav-18 H-3 < 156 MW-01C 29-Auo-18 . MN-54 < 3 MW-01C 29-Auo-18 C0-58 < 2.8 MW-01C 29-Auo-18 FE-59 < 5.2 MW-01C 29-Auo-18 C0-60 < 2.3 MW-01C 29-Auo-18 ZN-65. < 4.5 MW-01C 29-Aug-18 ZR-NB-95 < 3.3 2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-01C 29-Aug-18 1-131 < 0.469 MW-01C 29-Aug-18 CS-134 < 4.3 MW-01C 29-Aug-18 CS-137 < 4.1 MW-01C 29-Aug-18 BA-LA-140 < 3.5 MW-01C 29-Aug-18 H-3 < 156 MW-01C 05-Dec-18 MN-54 < 2.7 MW-01C 05-Dec-18 C0-58 < 3.2 MW-01C 05-Dec-18 FE-59 < 6.1 MW-01C 05-Dec-18 C0-60 < 2.5 MW-01C 05-Dec-18 ZN-65 < 4.8 MW-01C 05-Dec-18 ZR-NB-95 < 2.3 MW-01C 05-Dec-18 1-131 < 0.365 -

MW-01C 05-Dec-18 CS-134 < 3.5 MW-01C 05-Dec-18 CS-137 < 3.9 MW-01C 05-Dec-18 BA-LA-140 < 2 MW-01C 05-Dec-18 H-3 < 157 MW-02A 26-Feb-18 MN-54 < 2.9 MW-02A 26-Feb-18 C0-58 < 3 MW-02A 26-Feb-18 FE < 5 MW-02A 26-Feb-18 C0~60 < 3.2 MW-02A 26-Feb-18 ZN-65 < 6.4 MW-02A 26-Feb-18 ZR-NB-95 < 2.7 MW-02A 26-Feb-18 1-131 < 0.27 MW-02A 26-Feb-18 CS-134 < 3.7 MW-02A 26-Feb-18 CS-137 < 2.5 MW-02A 26-Feb-18 BA-LA-140 < 2.3 MW.,02A 26-Feb-18 H-3 <. 155 MW-02A 02-May-18_ MN-54 < 2.4 MW-02A 02-May-18 C0-58 < 2.2 MW-02A 02-May-18 FE-59 < 8.2 MW-02A 02-May-18 C0-60 < 3.9 MW-02A 02-May-18 ZN-65 < 5.2 MW-02A 02-May-18 ZR-NB-95 < 3.3 MW-02A 02-Mav-18 1-131 < 0.379 MW-02A 02-Mav-18 CS-134 < 4.4 MW-02A 02-May-18 CS-137 < 3.3 MW-02A 02-Mav-18 BA-LA-140 < 3 MW-02A 02-May-18 H-3 < 156 MW-02A 29-Auo-18 MN-54 < 4.6

. MW-02A 29-Auo-18 C0-58 < 3.8 2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-02A 29-Aug-18 FE-59 < 9.7 MW-02A 29-Aug-18 C0-60 < 3 MW-02A 29-Aug-18 ZN-65 < 10.8 MW-02A 29-Aug-18 ZR-NB-95 < 5.4 MW-02A 29-Aua-18 1-131 < 0.399 MW-02A 29-Aua-18 CS-134 < 5.2 MW-02A 29-Aua-18 CS-137 < 4.5 MW-02A 29-Aug-18 BA-LA-140 < 5 MW-02A 29-Aug-18 H-3 < 156 MW-02A 04-Dec-18 MN-54 < 2.6 MW-02A 04-Dec-18 C0-58 < 3.2 MW-02A 04-Dec-18 FE-59 < 5.9 MW-02A 04-Dec-18 C0-60 < 3.1 MW-02A 04-Dec-18 ZN-65 < 3.2 MW-02A 04-Dec-18 ZR-NB-95 < 4.5 MW-02A 04-Dec-18 1-131 - < 0.282 MW-02A 04-Dec-18 CS-134 < 4.2 MW-02A 04-Dec-18 CS-137 < 4.9 MW-02A 04-Dec-18 BA-LA-140 < 3.8 MW-02A 04-Dec-18 H-3 < 153 MW-028 26-Feb-18 MN-54 < 3.4 MW-028 26-Feb-18 C0-58 < 2.5 MW-028 26-Feb-18 FE-59 < 3.4 MW-028 26-Feb-18 C0-60 < 3.1 MW-028 26-Feb-18 ZN-65 < 7 MW-028 26-Feb-18 ZR-NB-95 < 3.6 MW-028 26-Feb-18 1-131 < 0.245 MW-028 26-Feb-18 CS-134 < 3.1 MW-028 26-Feb-18* CS-137 < 2.8 MW-028 26-Feb-18 BA-LA-140 *< 3.3 MW-028 26--Feb-18 H-3 < 155 MW-028 02-May-18 MN-54 < 2.6 MW-028 02-May-18 C0-58 < 2.8 MW-028 02-May-18 FE-59 < 4.7 MW-028 02-May-18 C0-60 < 2.4 -

MW-028 02-May-18 ZN-65 < 3.8 MW-028 02-May-18 ZR-NB-95 < 2.9 MW-028 02-May-18 1-131 < 0.484 MW-028 02-May-18 CS-134 < 3.4 MW-028 02-Mav-18 CS-137 < 2.3 2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN E;RROR NOTE MW-028 02-May-18 BA-LA-140 < 1.7 MW-028 02-May-18 H-3 < 156 MW-028 29-Aug-18 MN-54 < 2.5 MW-028, 29-Aug-18 C0-58 < 1.5 MW-028 29-Aug-18 FE-59 < 6 MW-028 29-AUQ-18 C0-60 < 2.8 MW-028 29-AUQ-18 ZN-65 < 6.4 MW-028 29-AuQ.:.18 ZR-NB-95 < 3.3 MW-028 29-Aug-18 1-131 < 0.461 MW-028 29-Aug-18 CS-134 < 3.3 MW-028 29-Aug-18 cs.:137 < 2.9 MW-028

29-Aug-18 BA-LA-140 < 5.3 MW-028 29-Aug-18 H-3 < 156 MW-028 04-Dec-18 MN-54 < 3.3 MW-028 04-Dec-18 C0-58 < 2.2 MW-028 04-Dec-18 FE-59 < 4.8 MW-028 04-Dec-18 C0-60 < 1.8 MW-028 04-Dec-18 ZN-65 < 4.1 MW-028 04-Dec-18 ZR-NB-95 < 3.1 MW-028 04-Dec-18 1-131 < 0.308 MW-028 04-Dec-18 CS-134 < 3 MW-028 04-Dec-18 CS-137 < 2.2 MW-028 04-Dec-18 BA-LA-140 < 2.1 MW-028 04-Dec-18 H-3 < 153 MW-03A 26-Feb-18 MN-54 < 3.2 MW-03A 26-Feb-18 C0-58 < 5.5 MW-03A 26-Feb-18 FE-59 < 5.5 MW-03A 26-Feb-18 C0-60 < 4.7 MW-03A 26-Feb-18 ZN-65 < 8.2 MW-03A 26-Feb-18 ZR-NB-95 < 4.1 MW-03A 26-Feb-18 1-131 < 0.367 MW-03A 26-Feb-18 CS-134 < 5.5 MW-03A 26-Feb-18 CS-137 < 4.2 MW-03A 26-Feb-18 BA-LA-140 < 4 MW-03A 26-Feb-18 H-3 < 155 MW-03A 02-Mav-18 MN-54 < 4.4 MW-03A 02-Mav-18 C0-58 < 3.9 MW-03A 02-Mav-18 FE-59 < 6.7 MW-03A 02-Mav-18 C0-60 < 2.4 MW-03A 02-Mav-18 ZN-65 < 5.2 2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-03A 02-May-18 ZR-NB-95 < 3.6 MW-03A 02-May-18 1-131 < 0.316 MW-03A 02-May-18 CS-134 < 4.7 MW-03A 02-May-18 CS-137 < 2.4 MW-03A 02-May-18 BA-LA-140 < 1.8 MW-03A 02-May-18 H-3 < 156 MW-03A 29-Aug-18 MN-54 < 3.5 MW-03A 29-Aug-18 C0-58 < 1.7 MW-03A 29-Aug-18 FE-59 < 5.8 MW-03A 29-Aug-18 C0-60 < 3 MW-03A 29-Aug-18 ZN-65 ' < 5.6 MW-03A 29-Aug-18 ZR-NB-95 < 2.9 MW-03A 29-Aug-18 1-131 < 0.43 MW-03A 29-Aug-18 CS-134 < 4.2 MW-03A 29-Aug-18 CS-137 < 3 MW-03A 29-Aug-18 BA-LA-140 < 3.8 MW-03A 29-Aug-18 H-3 < 156 MW-03A 04-Dec-18 MN-54 < 3.4 MW-03A 04-Dec-18 C0-58 < 1.9 MW-03A 04-Dec.,.18 FE-59 < 8.2 MW-03A 04-Dec-18 C0-60 < 3.7 MW'-03A 04-Dec-18 ZN-65 < 6.3 MW-03A 04-Dec-18 ZR-NB-95 < 4.3 MW-03A 04-Dec-18 1-131 < 0.306 MW-03A 04-Dec-18 CS-134 < 4.5 MW-03A 04-Dec-18 CS-137 < 3.4 MW-03A 04-Dec-18 BA-LA-140 < 2.2 MW-03A 04-Dec-18 H-3 < 153 MW-038 26-Feb-18 MN-54 < 1.6 MW-038 26-Feb-18 C0-58 < 1.7 MW-038 26-Feb-18 FE-59 < 3.7 Mw.:.039 26-Feb-18 C0-60 < 2.3 MW-038 26-Feb-18 ZN-65 < 3.1 MW-038 26-Feb-18 ZR-NB-95 < 3.2 MW-038 Feb-18 1-131 < 0.374 MW-038 26-Feb-18 CS-134 < 3.4

. MW-038

26-Feb-18 CS-137 * <* 2.9 MW-038 26-Feb-18 BA-LA-140 < 1.8 MW-038 26-Feb-18 H-3 < 155 MW-038 02-May-18 MN-54 < 2.7 2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results Concentration (pCi/L)

LOCATION

DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-038 02-Mav-18 Cb-58 < 2 MW-038 02-May-18 FE-59 < 5 MW-038 02-May-18 C0-60 < 1.5 MW-038 02-May-18 ZN-65 < 6.7 MW-038 02-May.,18 ZR-NB-95 < 2.9 MW-038 02-May-18 1-131 < 0.42 MW-038 02-,May-18 CS-134 < 3.1 MW-038 02-May-18 CS-137 < 3.3 MW-038 02-May-18 BA-LA-140 < 2.4 MW-038 02-May-18 H-3 <

156 MW-038 29-Aug-18 MN-54 < 2.1 MW-038 29-Aug-18 C0-58 < 1.6 MW-038 29-Aug-18 FE-59 < 3.6 MW-038 29-Aug-18 C0-60 < 3 MW-038 29-Aug-18 ZN-65 < 2.1 MW-038 29-Aug-18 ZR-NB-95 < 3.2 MW-038 29-Aug-18 1-131 < 0.433 MW-038 29-Aug-18 CS-134 < 2.9 MW-038 29-Aug-18 CS-1.37 < 3.7 MW-038 29-Aug-18 BA-LA-140 < 2.2 MW-038 29-Aug..:18 H.;.3 < 156 MW-038 04-Dec-18 MN-54 < 2.6 MW-038 04-Dec-18 C0-58 < 1.1 MW-038 04-Dec-18 FE-59 < 6.4 MW-038 04-Dec-18 C0-60 < 2.6 MW-038 04-Dec-18 ZN-65 < 4.6 MW~03B 04-Dec-18 ZR-NB-95 < 3 MW-038 04-Dec-18 1-131 < 0.266 MW-038 04-Dec-18 CS-134 < 4.1 MW-038 04-Dec-18 CS-137 < 3.4 MW-038 04-Dec-18 BA-LA-140 < 3.9 MW-038 04-Dec-18 H-3 < 153 Mw-*03c 26-Feb-18 MN-54 < 3.1 MW-03C 26-Feb-18 C0-58 <* 4 MW-03C 26-Feb-18 FE-59 < 5.1 MW-03C

26-Feb-18 C0-60 < 1.9 MW-03C 26-Feb-18 ZN-65 < 3.6 MW-03C 26-Feb-18 ZR-NB-95 < 2.4 MW-03C 26-Feb-18 1-131 < 0.426 MW-03C 26-Feb-18 CS-134 < 2.8 u,

2018 Annual Radioactive Effluent Release Report C)

Onsite Groundwater Results Concentration (pCi/L)

LOCATION. DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-03C 26-Feb-18 CS-137 < 3.2 MW-03C 26-Feb-18 BA-LA-140 < 1.9 MW-03C 26-Feb-18 H-3 < 155 MW-03C 02-May-18 MN-54 < 3.1 MW-03C 02-May-18 C0-58 < 2.6 MW-03C 02-May-18 FE-59 < 2.6 MW-03C 02-May-18 C0-60 < 1.6 MW-03C 02-May-18 ZN-65 < 2.6 MW-03C. 02-May-18 ZR-NB-95 < 2 MW-03C 02-Mav-18 1-131 < 0.307 MW-03C 02-May-18 CS-134 < 2.9 MW-03C 02-May-18 . CS-137 < 4 MW-03C 02-May-18 BA-LA-140 < 3 MW-03C 02-May-18 H-3 < 156 MW-03C 29-Aug-18 MN-54 < 3.1 MW-03C 29-Aug-18 C0-58 < 1.5 MW-03C 29-Aug-18 FE-59 < 5.1 MW-03C 29-Aug-18 C0-60 < 1.8 '

MW-03C 29-Aug-18 ZN-65 < 4.6 MW-03C 29-Aug-18 ZR-NB-95 < 3.7 MW-03C 29-Aug-18 1-131 < 0.425 MW-03C 29-Aug-18 CS-134 < 3.4 MW-03C 29.:.Aug-18 *cS-137 < 4.1 MW-03C 29-Aug-18 BA-LA-140 < 2.4 MW-03C 29-Aug-18 H-3 < . 156 MW-03C 04:..oec-18 MN-54 * < 1.7 MW-03C 04-Dec-18 C0-58 < 1.2 MW-03C

04-Dec-18* FE-59 < 5.8 MW-03C 04-Dec-18 C0-60 < 3.1 MW-03C 04-Dec-18 ZN-65 < 3.4 MW-03C 04-Dec-18 ZR-NB-95 < 2.2 MW-03C 04-Dec-18 1-131 < 0.264 MW-03C 04-Dec-18 CS-134 < 2.8 MW-03C 04-Dec-18 CS-137 < 3.8 MW-03C 04-Dec-18 BA-LA-140 < 3.3 MW-03C 04-Dec-18 H-3 < 153 MW-05C 26-Feb-18 MN-54 <

2.5 MW-05C 26-Feb-18 C0-58 < 1 MW-05C 26-Feb-18 FE-59 < 3.1 MW-05C 26-Feb-18 C0-60 < 2.4 2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-05C 26-Feb-18 ZN-65 < 3.9 MW-05C 26-Feb-18 ZR-NB-95 < 2.5 MW-05C 26-Feb-18 1-131 < 0.32 MW-05C 26-Feb-18 CS-134 < 2.6 MW-05C 26-Feb-18 CS-137 < 3.2 MW-05C 26-Feb-18 BA-LA-140 < 2.2 MW-05C 26-Feb-18 H-3 < 155 MW-05C 02-May-18 MN-54 < 2.9 MW-05C 02-May-18 C0-58 < 1.4 MW-05C 02-May-18 FE-59 < 2.9 MW-05C 02-May-18 C0-60 < 2.7 MW-05C 02-May-18 ZN-65 ' <' 2.6 MW-05C 02-May-18 ZR-NB-95 < 3 MW-05C 02-May-18 1-131 < 0.286 MW-05C 02-May-18 CS-134 < 2.9 \

MW-05C 02-Mav-18 CS-137 < 1.6 MW-05C 02-Mav-18 BA-LA-140 < 3.1 MW-05C 02-May-18 H-3 < 156 MW-05C 29-AuQ-18 MN-54 < 3.4 MW-05C 29-AuQ-18 C0-58 < 3.4 MW-05C 29-AUQ-18 FE-59 < 7.9 MW-05C 29-AUQ-18 C0-60 < 3.1 MW-05C 29-AUQ-18 ZN-65 < 4.4 MW-05C 29-Aug-18 ZR-NB-95 < 2.8 MW-05C 29-Aug-18 1-131 < 0.448 MW-05C 29-Aug-18 CS-134 ._

< 4.4 MW-05C 29-Aug-18 CS-137 < 4.1 MW-05C 29-Aug-18 BA-LA-140 < 3.4 MW-05C 29-Au_q-18 H-3 < 148 MW-05C 04-Dec-18 MN-54 < 4 MW-05C 04-Dec-18 C0-58 < 4.7 MW-05C 04-Dec-18 FE-59 < 6.9 MW-05C 04-Dec-18 C0-60 < 2.6 MW-05C 04-Dec-18 ZN-65 < 3.8 MW-05C. 04-Dec-18 ZR-NB-95 < 4.5 MW-05C 04-Dec-18 1-131 < 0.268 MW-05C 04-Dec-18 CS-134 < 4.9 MW-05C 04-Dec-18 CS~137 < 2.8 MW-05C 04-Dec-18 BA-LA-140 < 2.5 MW-05C 04-Dec-18 H-3 < 153 c.n 2018 Annual Radioactive Effluent Release Report N

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-11A 26-Feb-18 MN-54 < 2.7 MW-11A 26-Feb-18 MN-54 < 2.5 MW-11A 26-Feb-18 C0-58 < 1.9 .

MW-11A

26-Feb-18 C0-58 < -2.2 MW-11A 26-Feb-18 FE-59 < 4.1 MW-11A 26-Feb-18 FE-59 < 3.7 MW-11A 26-Feb-18 C0-60 < 2.1 MW-11A 26-Feb-18 C0-60 < 2.5 MW-11A 26-Feb-18 ZN-65 < 2 MW-11A 26-Feb-18 ZN-65 < 4.3 MW-11A 26-Feb-18 ZR-NB-95 < 2.3 MW-11A 26-Feb-18 ZR-NB-95 < 1.9 MW-11A 26-Feb-18 1-131 < 0.466 MW-11A 26-Feb-18 1-131 < 0.405 MW-11A 26-Feb-18 CS-134 < 3.1 MW-11A 26-Feb-18 CS-134 / < 3.6 MW-11A 26-Feb-18 CS-137 < 3.2 MW-11A 26-Feb-18 CS-137 < 2.1 MW-11A 26-Feb-18 . BA-LA-140 < 2.5 MW-11A 26-Feb-18 BA-LA-140 < 3.3 MW-11A 26-Feb-18 H-3 < 155 MW-11A 26-Feb-18 H-3 < 155 MW-11A 02-May-18 MN-54 < 1.8 MW-11A 02-May-18 C0-58 < 2.4 MW-11A 02-Mav-18 FE-59 < 3.4 MW-11A 02-Mav-18 C0-60 < 1.6 MW-11A 02-May-18 ZN-65 < 4.3 MW-11A 02-Mav-18 ZR-NB-95 < 1.6

MW-11A 02-May-18 1-131 < 0.497 MW-11A 02-May-18 CS-134 < 2.9 MW-11A 02-May-18 CS-137 < 2.8

MW-11A 02-May-18 BA-LA-140 < 2.6 MW-11A 02-May-18 H-3 < 156 MW-11A 29-Aug-18 MN-54 < 1.9 MW-11A 29-Aug-18 C0-58 < 2.5

-, MW-11A 29-Aug-18 FE-59 < 4.2 MW-11A 29-Aug-18 C0-60 < 2.9 MW-:11A 29-Aug-18 ZN-65 < 4 MW-11A 29-Aug-18 ZR-NB-95 < 2.7 MW-11A 29-Aug-18 1-131 < 0.453 u,

2018 Annual Radioactive Effluent Release Report w

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY* SIGN ERROR NOTE MW-11A 29-Aug-18 CS-134 - < 3.7 MW-11A 29-Aug-18 CS-137 < 4.2 MW-11A 29-Aug-18 BA-LA-140 < 1.7 MW-11A 29-Aug-18 H-3 < 156 MW-11A 04-Dec-18 MN-54 < 3 MW-11A 04-Dec-18 C0-58 < 1.2 MW-11A 04-Dec-18 FE-59 < 4.7 MW-11A 04-Dec-18 C0-60 < 1.2 MW-11A 04-Dec-18 ZN-65 < 4.1 MW-11A 04-Dec-18 ZR-NB-95 < 2.1 MW-11A 04-Dec-18 1-131 < 0.255 MW-11A 04-Dec-18 CS-134 < 3.2 MW-11A 04-Dec-18 CS-137 < 2.4 MW-11A 04-Dec-18 BA-LA-140 < 1:9 MW-11A 04-Dec-18 H-3 <* 153 MW-118 26-Feb-18 MN-54 < 4.6 MW-118 26-Feb-18 C0-58 < 4 MW-118. 26-Feb-18 FE-59 < 5.7 MW-118 26-Feb-18

C0-60 < 2.7 MW-118 26-Feb-18

ZN-65 < 8.8 MW-118 26-Feb-18 ZR-NB-95 < 3.3 MW-118 26-Feb-18 1-131 < 0.383 MW-118 26-Feb-18 CS-134 < 4.9 MW-118 26-Feb-.18 CS-137 < 3.6 MW-118 26-Feb-18 BA-LA-140 < 2.5 MW-118 26-Feb-18 H-3 < 155 MW-118 02-May-18 MN-54 < 3.9 MW-118 02-May-18 co.:58 < 2.9 MW-118 02-May-18 FE-59 < 6.2 MW-118 02-May-18 C0-60 < 2.3 MW-118 02-May-18 ZN-65 < 5.1 MW-118 02-May-18 ZR-NB-95 < 3.4 MW-118 02-Mav-18 1-131 < 0.408 MW-118 02-Mav-18 CS-134 < 4.3 MW-118 02-Mav-18 CS-137 < 2.8 MW-118 02-Mav-18 BA-LA-140 < 2.6 MW-118 02-Mav-18 H-3 < 156 MW'-118 ' 29-AUQ-18 MN-54 < 3.5 MW-118 29-AUQ-18 C0-58 < 1.8 MW-118 29-AuQ-18 FE-59 < 5.4 2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-118 29-Aug-18 C0-60 < 2.4 MW-118 . 29-AuQ-18 ZN-65 < 4.7 MW-118 29-Aug-18 ZR-NB-95 < 4 MW-118 29-Aug-18 1-131 < 0.47 MW-118 29-Aug-18 CS-134 < 4.1 MW-118 29-Aug-18 CS-137 < 2.6 MW-118 29-Aug-18 BA-LA-140 < 3.7 MW-118 29-Aug-18 H-3 < 156 MW-118 04-Dec~18 MN-54 < 3.6 MW-118 04-Dec-18 MN-54 < 2.2 MW-118 04-Dec-18 C0-58 < 3.1 MW-118 04-Dec-18 C0-58 < 4 MW-118 04-Dec-18 FE-59 < 8.6 MW-118 Dec-18 FE-59 < 5.2 MW-118 04-Dec-18 C0-60 < 3.2 MW-118 04-Dec-18 C0-60 < . 3.3 MW-118 04-Dec-18 ZN-65 < 5.1 MW-118 04-Dec-18 ZN-65 < 4.7 MW-118 04-Dec-18 ZR-NB-95 < 5 MW-118 04-Dec-18 ZR-NB-95 < 3.7 MW-118 04-Dec-18 1-131 < 0.215 MW-118 04-Dec-18 1-131 < 0.482 MW-118 04-Dec-18 CS-134 < 4.6 MW-118 04-Dec-18 CS-134 < 5.1 MW-118 04-Dec-18 CS-137 < 2 MW-118 04-Dec-18 CS-137 < 4.5 MW-118 04-Dec-18 BA-LA-140 < 3.2 MW-118 04-Dec-18 BA-LA-140 < 4.3 MW-118 04-Dec-18 H-3 *< 153 MW-118 04-Dec-18 H-3 < 153 MW-12A 26-Feb-18 MN-54 < 2..1 MW-12A 26-Feb-18 C0-58 < 2 MW-12A 26-Feb-18 FE-59 < 6.6 MW-12A 26-Feb-18 C0-60 <' 2.9 MW-12A 26-Feb-18 ZN-65 < 6.8 MW-12A 26-Feb-18 ZR-NB-95 < 3.7 MW-12A 26.:.Feb-18 1-131 < 0.227 MW-12A 26-Feb-18 CS-134 < 3 MW-12A 26-Feb-18 CS-137 < 3.2 MW-12A 26-Feb-18 BA-LA-140 < 2.5 (JI 2018 Annual Radioactive Effluent Release Report (JI

Onsite Groundwater Res.ults Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN

ERROR NOTE MW-12A 26-Feb-18 H-3 < 155 MW-12A 02-Mav-18 MN-54 < 2.9 MW-12A 02-May-18 C0-58 < 2.5 MW-12A 02-May-18 FE-59 < 4 MW-12A 02-May-18 C0-60 < 2.1 MW-12A 02-May-18 ZN-65 < 3.2 MW-12A 02-Mav-18 ZR-NB-95 < 2.5 MW-12A 02-Mav-18 1~131 < 0.387 MW-12A 02-Mav-18 CS-134 <" 2.9

MW-12A 02-Mav-18 CS-137 < 4.2

MW-12A 02-May-18 BA-LA-140 < 2.8 MW-12A 02-May-18 H-3 < 156 MW-12A

29-Aug-18 MN-54 < 3.3 MW-12A 29-Aug-18

C0-58 . *< 1.6 MW-12A 29-Aug-18 FE-59 < 4.6 MW-12A 29-Aug-18 C0-60 < 2.4 MW-12A 29-Aug-18 ZN-65 < 5.2 MW-12A 29-Aug-18 ZR-NB-95 < 2.1 Mw:.12A 29-Aug-18 1-131 < 0.478 MW-12A 29-Aug-18 CS-134 < 3.8 MW-12A 29-Aug-18 CS-137 < 3.4 MW-12A 29-Aug-18 BA-LA-140 < 4 MW-12A 29-Aug-18 H-3 158 +/- 79 MW-12A 04-Dec-18 MN-54 < 4 MW-12A 04-Dec-18 C0-58 < 2.4 MW-12A 04-Dec-18 FE-59 < 4.9 MW-12A 04-Dec-18 C0-60 < 4.4 MW-12A 04-Dec-18 ZN-65 < 2.1 MW-12A

04-Dec-18 ZR-NB-95 < 3.7 MW-12A 04-Dec-18 1-131 < 0.247 MW-12A 04-Dec-18 CS-134 < 4.6 MW-12A 04-Dec-18 CS-137 < 5.8 MW-12A 04-Dec-18 BA-LA-140 < 3.9 MW-12A 04-Dec-18 H-3 < 153 MW-128 26-Feb-18 MN-54 < 2.8 MW-128 26-Feb-18 C0-58 < 2.1 MW-128 . 26-Feb-18 FE-59 < 3.9 MW-128 26-Feb-18 C0-60 < 2.6 MW-128 26-Feb-18 ZN-65 < 3.4

.MW-128 26-Feb-18 ZR-NB-95 < 2

\

u, 2018 Annual Radioactive Effluent Release Report en

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN . ERROR NOTE

MW-128 26-Feb-18 1-131 < 0.202 MW-128 26-Feb-18 CS-134 < 3.6 MW-128 26-Feb 718 CS-137 < 3.3 MW-128 26-Feb-18 BA-LA-140 < 1.3 MW-128 26-Feb-18 H-3 < 156 MW-128 02-May-18 MN-54 < 2.4 MW-128 02-May-18 C0-58 < 2 MW-128 02-May-18

FE-59 < 3.5 MW-128 02-May-18 C0-60 < 1.1 MW-128 02-May-18 ZN-65 < 3.5 MW-128 02-May-18 ZR-NB-95 < 2.2 MW-128 02-May-18 1-131 < 0.475 MW-128 02-May-18 CS-134 < 2.6 MW-128 02-Mav-18 CS-137 < 2.3 MW-128 02-May-18 BA-LA-140 .< 1.7 MW-128 02-May-18 H-3 < 156 MW-128 29-Aug-18 MN-54 < 2.8 MW-128 29-Aug-18 C0-58 < 2.7 MW-'128 29-Aug-18 FE-59 < 5.9 MW-128 29-Aug-18 C0-60 < 3.4 MW-128 29-Aug-18 ZN-65 < 4.9 MW-128 29-Aug-18 ZR-NB-95 < 3 MW-128 29-Aug-18 1-131 ,< 0.474 MW-128 29-Aug-18 CS-134 < 3.2 MW-128 29-Aug-18 CS-137 < 2.8 MW-128 29-Aug-18 BA-LA-140 < 1.5 MW-128 29-Aug-18 H-3 < 148 MW-128 04-Dec-18 MN-54 < 2.5, MW-128 04-Dec-18 C0-58 < 2.9 MW-128 04-Dec-18 FE-59 < 4.9 MW-128 04-Dec-18 C0-60 < 2.7 MW-128 04-Dec-18 ZN-65 < 4.9 MW-128 04-Dec-18 ZR-NB-95 < 2.8

< .. 0.259 MW-128 04-Dec-18 1-131 MW-128 04-Dec-18 CS-134 < 3.7 MW-128 04-Dec-18 CS-137 < 4.1 MW-128 04-Dec-18 BA-LA-140 < 3.9 MW-128 04-Dec-18 H~3 < 153 MW-13 , 26-Feb-18 MN-54 < 2.9 MW-13 26-Feb-18 C0-58 < 3.2 2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-13 26-Feb-18 FE-59 < 4.3 MW-13 26-Feb-18 C0-60 < 2.3 MW-13 26-Feb-18 ZN-65 < 5 MW-13 26-Feb-18 ZR-NB-95 < 2.2 MW-13 26-Feb-18 1-131 < 0.353 MW-13 26-Feb-18 CS-134 < 3.1 MW-13 26-Feb-18 CS-137 < 2.7 MW-13 26-Feb-18 BA-LA-140 < 2.3 MW-13 26-Feb-18 H-3 < 156 MW-13 02-May-18 MN-54 < 4.2 MW-13 02-May-18 MN-54 < 3.2 MW-13 02-May-18 C0-58 < 3 MW-13 02-Mav-18 C0-58. < 3.5 MW-13 02-Mav-18 FE-59 < 8.1 MW-13 02-May-18 FE-59 < 5.5 MW-13 02-May-18 C0-60 < 2 MW-13 02-May-18 C0-60 < 3.8 MW-13 02-May-18 ZN-65 < 5.5 MW-13 02-Mav-18

ZN-65 < 2.3 MW-13 02-May-18 ZR-NB-95 < 1.9 MW-13 02-May-18 ZR-NB-95 < 4.4 MW-13 02-Mav-18 1-131 < 0.423 MW-13 02-Mav-18 1-131 <

0.433 MW-13 02-Mav-18, CS-134 < 3.1 MW-13 02-Mav-18 CS-134 < 4.8 MW-13 02-Mav-18 CS-137 < 3.9 MW-13 02-Mav-18 CS-137 < 4.5 MW-13 02-Mav-18 BA-LA-140 < 4.5 MW-13 02-Mav-18 BA-LA-140 < 3.6 MW-13 02-May-18 H-3 < 156 MW-13 02-May-18 . H-3 < 156 MW-13 29-Aug-18 MN-54 < 3.9 MW-13 29-Aug-18 C0-58 < 2.6 MW-13 29-Aug~18 FE-59 < 6.9 MW-13 29-Aug-18 C0-60 < 1.9 MW-13 29-Aug-18 ZN-65 < 5.1 MW-13 29-Aug-18 ZR-NB-95 < 2.8 MW-13 29-Aug-18

1-131 < 0.342 MW-13 29-Aug-18 CS-134 < 4.3 MW-13 29-Aug-18 CS-137 < 4.2 UI 2018 Annual Radioactive Effluent Release Report 00

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-13 29-Aug-18 BA-LA-140 < 1.9 MW-13 29-Aug-18 H-3 < 148 MW-13 04-Dec-18 MN-54 < 2 MW-13 04-Dec-18 C0-58 <* 2.9 MW-13 04-Dec-18 FE-59 < 5.2 MW-13 04-Dec-18 C0-60 < 2.3 MW-13 . 04-Dec-18 ZN-65 < 2.7 MW-13 04-Dec-18 ZR-NB-95 < 3.8 MW-13 04-Dec-18 1-131 < 0.413 MW-13 04-Dec-18 CS-134 < 2.9 MW-13 04-Dec-18 CS-137 < 3.9 MW-13 04-Dec-18 BA-LA-140 < 3.7 MW-13 04-Dec-18 H-3 < 153 MW-14 26-Feb-18 MN-54 < 2.6 MW-14 26-Feb-18 C0-58 < 1.3 MW-14 26-Feb-"18 FE-59 < 2.5 MW-14 26-Feb-18 C0-60 < 3 MW-14 26-Feb-18 ZN-65 < 3.6 MW-14 26-Feb-18 ZR-NB-95 < 3.1 MW-14 26-Feb-18 1-131 < 0.346 MW-14. 26-Feb-18 CS-134 < 2.8 MW-14 26-Feb-18 CS-137 < 3 MW-14 26-Feb-18 BA-LA-140 < 2.9 MW-14 26-Feb-18' H-3 <; 156 MW-14 02-May-18 MN-54 < 3.6 MW-14 02-May-18 C0-58 < 2.1 MW-14 02-May-18 FE-59 < 4.6 MW-14 02-May-18 C0-60 < 1.4 MW-14 02-Mav-18 ZN-65 < 2.5 MW-14 02-Mav-18 ZR-NB-95 < 2.9 MW-14 02-Mav-18 1-131 < 0.46 MW-14 02-May-18 CS-134 < 3.7 MW-14 02-May-18 CS-137 < 3.9 MW-14 02-May-18 BA-LA-140 < 3.1 MW-14 02-May-18 H-3 < 156 MW-14 29-Aug-18 MN-54 < 3.3 MW-14 29-Aug-18 C0-58 < 2.7 MW-14 29-Aug-18 FE-59 < 6.2 MW-14 29-Aug-18 C0-60 < 2.1 MW-14 29-Aug-18 ZN-65 < 5.9 CJI 2018 Annual Radioactive Effluent Release Report CD

Onsite ~roundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-14 29-Aug-18 ZR-NB-95 < 4.9 MW-14 29-Aug-18 1-131 < 0.42 MW-14 29-Aug-18 CS-134 < 3.7 MW-14 29-Aug-18 CS-137 < 2.8 MW-14 29-Aug-18 BA-LA-140 . < 3 MW-14 29-Aug-18 H-3 < 148 MW-14 04-Dec-18 MN-54 < 2.2 MW-14 04-Dec-18 C0-58 < - 3.5 MW-14 04-Dec-18 FE-59 < 10.8 MW-14 04-Dec-18 C0-60 < 3.5 MW-14 04-Dec-18 ZN-65 < 3 MW-14 04-Dec-18 ZR-NB-95 < 3.7 MW-14 04-Dec-18 1-131 < 0.338 MW-14 04-Dec-18 CS-134 < 3.9 MW-14 04-Dec-18 CS-137 < 3.6 MW-14 04-Dec-18 BA-LA-140 < 4.9 MW-14 04-Dec-18 H-3 < 153 MW-15 26-Feb-18 MN-54 < 2.1 MW-15 26-Feb-18 C0-58 < 2.1 MW-15 26-Feb-18 FE-59 < 6.1 MW-15 26-Feb-18 C0-60 < 3 MW-15 26-Feb-18 ZN-65 < 5.9 MW-15

26-Feb-18 ZR-NB-95 < 3.7 MW-15 26-Feb-18 1-131 < 0.39 MW-15 . 26-Feb-18 CS-134 < 3.8 MW-15 26-Feb-18 CS-137 < 3.4 MW-15 26-Feb-18 BA-LA-140 < 1.3 MW-15 26-Feb-18 H-3 590 +/- 102 MW-15 02-May-18 MN-54 < 4 MW-15 02-May-18 .CQ-58 < 4.6 MW-15 02-May-18 FE-59 < 8.7 MW-15

02-May-18 C0-60 < 3.4 MW-15 02-May-18 ZN-65 < 9 MW-15 02-Mav-18 ZR-NB-95 < 3.3 MW-15 02-Mav-18 1-131 < 0.46 MW-15 02-May-18 CS-134 < 4.5 MW-15 02-May-18 CS-137 < 2.7 MW-15 02-May-18 BA-LA-140 < 3.2 MW-15 02-May-18 H-3 352 +/- 109 MW-15 29-Aug-18 . MN-54 < 2 en 2018 Annual Radioactive Effluent Release Report 0

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-15 29-Aug-18 C0-58 < 2.2 MW-15 29-Aug-18 FE-59 < 5.6 MW-15 29-Aug-18 C0-60 < 1.4 MW-15 29-Aug-18 ZN-65 < 5.1 MW-15 29-Aug-18 ZR-NB-95 < 2.7 MW-15 29-Aug-18 1-131 < 0.359 MW-15 29-Aug-18 CS-134 < 3.1 MW-15 29-Aug-18 CS-137 < 2.5 MW-15 29-Aug-18 BA-LA-140 < 2.3 MW-15 29-Aug-18 H-3 256 +/- 84 MW-15 04-Dec-18 MN-54 < 2.9 MW-15 04-Dec-18 C0-58 < 3.8 MW-15 04-Dec-18 FE-59 < 6.5 MW-15 04"'-Dec-18 C0-60 < 2.1 MW-15 04-Dec-18 ZN-65 < 2.7 MW-15 04-Dec-18 ZR-NB-95 < 4.3 MW-15 04-Dec-18 1-131 < 0.442 MW-15 04-Dec-18 CS-134 < 3.5 MW-15 04-Dec-18 CS-137 < 3.6 MW-15 04-Dec-18 BA-LA-140 < 3.8 MW-15 04-Dec-18 H-3 221 +/- 83 MW-16 26-Feb-18 MN-54 < 2.6

'MW-16 26-Feb-18 C0-58 < 2.7 MW-16 26-Feb-18 FE-59 < 5.2 MW-16 26-Feb-18 C0-60 < 2.3 MW-16 26-Feb-18 ZN-65 < 2.9 MW-16 26-Feb-18 ZR-NB-95 < 1.9 MW-16 26-Feb-18 1-131 < 0.495 MW-16 26-Feb-18 CS-134 < 2.6 MW-16 26-Feb-18 CS-137 < 2.1 MW-16 26-Feb-18 BA-LA-140 < 2.5 MW-16 26-Feb-18 H-3 < 156 MW-16 02-May-18 MN-54 < 2.9 MW-16 02-Mav-18 C0-58 < 2.9 MW-16 02-May-18 FE-59 < 3.1 MW-16 02-May-18 C0-60 < 2.3 MW-16 02-Mav-18 ZN-65 < 2.7 MW-16 02-Mav-18 ZR-NB-95 < 3.5 MW-16 02-Mav-18 1-131 < 0.386 MW-16 02-Mav-18 CS-134 < 2.8 2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-16 02-May-18 CS-137 < 2.6 MW-16 02-May-18 BA-LA-140 < 2.8 MW-16 02-May-18 H-3 ' < 156 MW-16 29-Aug-18 MN-54 < 3.3

- MW-16 29-Aug-18 C0-58 < 2.6 MW-16 29-Aug-18 FE-59 . < 3.2 MW-16 29-Aug-18 C0-60 < 3.1 MW-16 29-Aug-18 ZN-65 < 5.7 MW-16 29-Aug-18 ZR-NB-95 *< 4.5 MW-16 29-Aug-18 1-131 < 0.359 MW-16 29-Aug-18 CS-134 < 4.8 MW-16 29-Aug-18 CS-137 < 3.9 MW-16 29-Aug-18 BA-LA-140 < 3.2 MW-16 29-Aug-18 -H-3 < 148 MW-16 04-Dec-18 . MN-54 < 3.3 MW-16 04-Dec-18 ~._ C0-58 < 4.6 MW-16 04-Dec-18 FE-59 < 5.4 MW-16 04-Dec-18 C0-60 < 2.3 MW-16 04-Dec-18 ZN-65 < 4.9 MW-16 04-Dec-18 ZR-NB-95 < 4.2 MW-16 04-Dec-18 1-131 < 0.304 MW-16 04-Dec-18 CS-134 < 3.5

', MW-16 04-Dec-18 CS-137 < 3 MW-16 04-Dec-18 BA-LA-140. < 5.1 MW-16 04-Dec-18 H-3 < 153

MW-17 26-Feb"'.18 MN-54 < 3.1 MW-17 26-Feb-18 C0-58 < 3.2 MW-17 26-Feb-18 FE-59 < 4.4

MW-17 26-Feb-18 C0-60 < 2.7 MW-17 26-Feb-18 ZN-65 .< 2.7 MW-17 26-Feb-18 ZR-NB-95 < 3.6 MW-17 26-Feb-18 1-131 < 0.342 MW-17 26-Feb-18 CS-134 < 3.8 MW-17 26-Feb-18 CS-137 < 2.9 MW-17 26-Feb-18 BA-LA-140 <i 1.5 MW-17 26-Feb-18 H-3 267 +/- 87 MW-17 02-May-18 MN-54 < 2.6 MW-17 02-May-18 C0-58 < 0.9 MW-17 02-May-18 FE-'59 < 4.3 MW-17 02-May-18 C0-60 < 3 2018 Annual Radioactive Effluent Release Report

Onsite Groundwater Results Concentration (pCi/L)

LOCATION DATE NUCLIDE ACTIVITY SIGN ERROR NOTE MW-17 02-May-18 ZN-65 < 4.8

MW-17 02-May-18 ZR-NB-95 < 1.6 MW-17 02-Mav-18 1-131 < 0.345 MW-17 02-Mav-18 CS-134 < 3.1 MW-17 02-May-18 CS-137 < 3.6

. MW-17 02-Mav-18 BA-LA-140 < 2.9

MW-17 02-Mav-18* H-3 < 156 MW-17 29-Aug-18 MN-54 < 3.6 MW-17 29-Aug-18 C0-58 < 2.8 MW-17 29-Aug-18 FE-59 < 3.1 MW-17 29-Aug-18 C0-60 < 1.4 MW-17 29-Aug-18 ZN-65 < 3.9 MW-17 29-Aug-18 ZR-NB-95 < 3.8 MW-17 29-Aug-18 1-131 < 0.356 MW-17 29-Aug-18 CS-134 < 3.4 MW-17 29-Aug-18 CS-137 < 3 MW-17 29-Aug:-18 BA-LA-140 < 5.9 MW-17 29-AuQ-18 .H-3 < 148 MW-.17 04-Dec-18 MN-54 < 3.5 MW-17 04-Dec-18 C0-58 < 2.7 MW-17 04-Dec-18 FE-59 < 5.1 MW-17 04-Dec-18 C0-60 < 1.4 MW-17 04-Dec-18 ZN-65 < 2.9 MW-17 04-Dec-18 ZR-NB-95 < 2.9 MW-17 04-Dec-18 . 1-131 < 0.328 MW-17 04-Dec-18 CS-134 < 4.2 MW-17 04-Dec-18 CS-137 < 3.1 MW-17 04-Dec-18 BA-LA-140 < 3.2 MW-17 04-Dec-18 H-3 < 153 2018 Annual Radioactive Effluent Release Report

ENCLOSURES TO WCGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosure I contains the Offsite Dose Calculation Manual, AP 078-003, Revislon 9 Enclosure II contains the Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program), AP 078-004, Revision 22 Enclosure Ill contains the Solid Radwaste Process Control Program, AP 31A-100, Revision 8 & 9 (both revisions included as revision 9 came out late in 2018) en 2018 Annual Radioactive Effluent Release Report .s:=.'

Enclosure I to 2018 Annual Radioactive Effluent Release Report - Report 42 Wolt Creek Nuclear Operating Corporation Procedure, AP 078-003, Revision 9, "Offsite Dose Calculation Manual"

FCREEK

'NUCLEAR OPERATINGCORPORATION AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Responsible Manager MANAGER CHEMISTRY I. ~e~-~~-~~n Number 1

9 I Use Category Information I Administrative Controls Procedure Yes I :~:::::~::~::rsight ~v;l~~i~~-- No 07B DC 12 03/29/2018

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 1 of 160

_ TABLE OF CONTENTS SECTION TITLE 1.0 PURPOSE 2 2.0 SCOPE 2

3.0 REFERENCES

AND COMMITMENTS 2 4.0 DEFINITIONS 3 5.0 RESPONSIBILITIES 6 6.0 PROCEDURE 7 6.1 Revision Of The ODCM 7 6.2 ODCM Submittal To NRC 8 7.0 RECORDS 8

8. 0 FORMS 8 ATTACHMENT A OFFSITE DOSE CALCULATION MANUAL 9

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Us.e [Page 2 of 160 1.0 PURPOSE 1.1 This procedure contains the Offsite Dose Calculation Manual (ODCM) and the requirements for revision and submittal to the NRC.

1.2 This procedure is written in accordance with and satisfies commitments to Regulatory Guide 1.21 Rev. 1 and Regulatory Guide 1. 10 9 Rev. 1. [ 3. 2. 1, 3. 2. 2 J 2.0 SCOPE 2.1 This procedure partially fulfills the requirements of Technical Specifications: 3;3.6 Containment Purge Isolation Instrumentation; 3.3.7 Control Room Emergency Ventilation System Actuation Instrumentation; 3.3.8 Emergency Exhaust System (EES) Actuation Instrumentation; 5.5.2 Primary Coolant s6urces Outside Containment; 5.6.3 Radioactive Effluent Release Report; 5.5.1 Offsite Dose Calculation Manual; and 5.5.4 Radioactive Effluent Controls Program.

2.2 Requirements for the Radiological Environmental Monitoring Program have been moved to AP 07B-004.

3.0 REFERENCES

AND COMMITMENTS 3.1 References 3 .1.1 WCGS Technical Specifications 3 .1. 2 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants 3 .1. 3 AP 07B-004, OFFSITE DOSE CALCULATION MANUAL (RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM) 3 .1. 4 PIR 98-0112, Revising the ODCM with.an OTSC 3 .1. 5 Technical Requirements Manual 3 .1. 6 NEI Letters 06-00288, 06-00331, 06-00332 3 .1. 7 Regulatory Guide 1.21, Revision 2 3 .1. 8 CR 29301, "Document Estimates for Tritium Release from Auxiliary Boiler" 3 .1. 9 CR 36059, "EPRI and NEI C-14 Training Workshop" 3 .1.10 CR 28094, "ODCM Does Not Fully Implement Regulatory Guide 1.21" 3 .1.11 CR 48258, "ODCM Terminology: Operable/Functiona l Usage"

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use ~age 3 of 160

3. 1. 12 PIR 2002-0975, "ODCM Revision Process Inconslstencies" 3 .1. 13 CR 47483, "Ni-63 in Liquid Effluents: OE 34998"

3. 1. 14 Wolf Creek Updated Safety Analysis Report (USAR) 3/18 3.2 Commitments 3.2.1 Regulatory Guide 1. 21*, Revision 1 "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" 3.2.2 Regulatory Guide 1.109, Revision 1, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part50, Appendix I

4.0 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout the ODCM.

4.1 ACTIONS

Shall be that part*of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times. 3/18 4.2 CALENDAR MONTH: The period of time from the beginning of the month to the end of the month.

4.3 CHANNEL CALIBRATION: Shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an in place qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps. 3/18

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 4 of 160 4.4 CHANNEL CHECK: Shall be the qualitative assessment, by obs~rvation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter. 3/18 4.5 CHANNEL OPERATIONAL TEST (COT): Shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, of all devices in tpe channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping or total channel steps.3/18 4.6 DOSE EQUIVALENT I-131: Shall be that concentration of I-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes I-131, I-132, I-133, I-134, and I-135 actually present. 3/18

4.7 FUNCTIONAL-FUNCTIONALITY

An attribute of an SSC not controlled by TSs. An SSC is FUNCTIONAL or has FUNCTIONALITY when it is capable of performing its specified function, as set forth in the current licensing basis. Functionality does not apply to TS specified safety functions, but does apply to the ability of non-TS SSCs to perform other specified functions that have a necessary support function. 3/18 4.8 MEMBER OF THE PUBLIC (10 CFR 20): Means any individual except when that individual is receiving an occupational dose. 3/18 4.9 MEMBER OF THE PUBLIC (40 CFR 190): Means any individual that can receive a radiation dose in the general environment, whether he may or may not also be exposed to radiation in an occupation associated with a nuclear fuel cycle. H9weyer, an individual is not considered a member the public during any period in which the individual is engaged in carrying out any operation which is part of a nuclear fuel cycle. 3/18 4.10 PROCESS CONTROL PROGRAM (PCP): Shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes, based on demonstrated processing of actual or simulated wet solid wastes, will be accomplished in such a way as to assure compliance with 10 CFR Part 20, 10 CFR Part 71, and Federal & State regulations and other requirements governing the disposal for the radioactive waste.

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL.

Information Use Dage 5 of 160 4.11 PURGE/PURGING: The controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

4.12 RATED THERMAL POWER (RTP): RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3565 MWt. 3/18 4.13 RESTRICTED AREA: 10 CFR 20 defines it as an area, access to which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials. Restricted area does not include areas used as residential quarters, but separate rooms in a residential building may be set apart as a restricted area; per the USAR, the RESTRICTED AREA=

EXCLUSION AREA. 3/18 4.14 SOURCE CHECK: Shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

4.15 SITE BOUNDARY: Per the USAR, this is considered the boundary between the UNRESTRICTED and RESTRICTED AREAS for radioactive effluent limits; the SITE BOUNDARY= Exclusion Area Boundary.

3/18 4.16 THERMAL POWER: Shall be the total reactoE core heat transfer*

rate to the reactor coolant. 3/18 4.17 TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT): Shall consist of operating the trip actuating device and verifying the OPERABILITY of all devices in the channel required for trip actuating device OPERABILITY. The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the necessary accuracy. The TADOT may be performed by means of any series of sequential, overlapping, or total channel steps. 3/18 4.18 UNRESTRICTED AREA: Per the USAR, this is the area that begins at the unrestricted/restricted boundary and extends outward. 3/18 4.19 VENTING: The controlled process of discharging air or gas from a confineme.nt to maintain temperature, pressure, humidity, concentratiori or other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does not imply a venting process.

Revision: 9 ' AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 6 of 160 4.20 VENTILATION EXHAUST TREATMENT SYSTEM (NUREG-1301): Shall be any system designed.and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety* Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST .

TREATMENT SYSTEM components. 3/18 4.21 WASTE GAS HOLDUP SYSTEM (NUREG-1301): Shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. 3/18 4.22 X/Q (Regulatory Guide 1.21, Rev 2): The average atmospheric effluent concentration, X, normalized by release rate, Q, at a distance (or location) in a given downwind direction.

Expressed in another way, X/Q, is the concentration (X) of airborne radioactive material (e.g., in units of µCi/m 3 )

divided by the release rate (Q) (e.g., in units of µCi/s) at a specified distance and direction downwind of the release point. 3/18 4.23 X/Q: Wolf Creek Generating Station uses a value of 2.2E-06 sec/m3 at the 1200 meter boundary in the north sector. 3/18 I.

5.0 RESPONSIBILITIES 5.1 The Manager Chemistry is responsible for the ODCM.

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use !Page 7 of 160 6.0 PROCEDURE 6.1 Revision Of The ODCM To comply with Technical Specification 5.5.1, revisions to the ODCM are not permitted via. APF 15C-004-04, ON THE SPOT CHANGE form (3.1.4).

6.1.1 All revisions to the ODCM are to be submitted through the Manager Chemistry via a document revision request (APF 15C-004-01).

6.1. 2 The Manager Chemistry shall ensure the Document Revision Request (APF 15C-004-01) package includes the following:

1. Each change shall be identified by markings irr the margins of the affected pages, clearly indicating the area of the page that was

.changed, and shall indicate. the date (e.g~,

month/year) the change was implemented.

Pursuant to TS 5.5.1, revision bars indicating changes prior to the current reporting period may be removed.

2. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

3. A determination that the change will maintain the level of Radioactive Effluent Control required by Wolf Creek Technical Specification 5.5.4.g (gaseous effluent), 10 CFR 20.1302 (liquid effluent), 40 CFR Part 190, 10 CFR 50.36A, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.

6. l ;3 The ODCM revision shall become effective after review and acceptance by the PSRC and the approval of the Plant Manager.

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use !Page 8 of 160 6.2 ODCM Submittal To NRC 6.2.1 Changes to the ODCM shall be submitted to the Commission in the form of a complete, .legible copy of the entire ODCM as a part of or concurrent with the Annual Radioact~Ve Effluent Release Report for the period of the report in which any change to the ODCM was made.

7.0 RECORDS 7.1 The following is a lifetime QA Record:

7 .1.1 AP 07B-003, OFFSITE DOSE CALCULATION MANUAL 8.0 FORMS 8.1 None

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OFFSITE DOSE CALCULATION MANUAL Wolf Creek Generating Station Offsite Dose Calculation Manual

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OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS

1.0 INTRODUCTION

5 2.0 LIQUID EFFLUENTS 6 2.1 DOSE RATE-COMPLIANCE WITH 10 CFR 20 6 2.2 DOSE-COMPLIANCE WITH 10 CFR 50 APPENDIX I 11 2.3 PROJECTED DOSE 13 2.4 INSTRUMENTATION 14 3.0 GASEOUS EFFLUENTS 28 3.1 DOSE RATE-COMPLIANCE WITH TECHNICAL SPECIFICATION 29 5.5.4.g 3.2 DOSE - COMPLIANCE WITH 10 CFR 50 APPENDIX I 35 3.3 PROJECTED DOSE 43 3.4 INSTRUMENTATION 44 4.0 TOTAL DOSE 60 4.1 REMEDIAL ACTION 60 4.2 SURVEILLANCE REQUIREMENTS 60 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 61 (Contained in AP 07B-004) 6.0 BASES 61 7.0 REPORTS 67 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 67 (contained in AP 07B-004) 7.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 68 APPENDIX A: DOSE CONVERSION FACTOR TABLES 71 APPENDIX B: METEOROLOGICAL MODEL 147

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ATTACHMENT A (Page 3 of 152)

OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES Table Page 2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 7 2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 15 2-3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 17 SURVEILLANCE REQUIREMENTS 3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS 31 PROGRAM 3-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING 46 INSTRUMENTATION 3-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING 48 INSTRUMENTATION SURVEILLANCE REQUIREMENTS A.1-1 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF 72 SITE SPECIFIC DATA A.1-2 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS 73 A.2-1 INHALATION DOSE FACTORS FOR ADULTS 74 A.2-2 INHALATION DOSE FACTORS FOR TEENAGER 76 A. 2-3 INHALATION DOSE FACTORS FOR CHILD 78 A. 2-4 INHALATION DOSE FACTORS FOR INFANT 80 A. 2-5 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED 82 GROUND A. 3-1 INGESTION DOSE FACTORS FOR ADULTS 84 A. 3-2 INGESTION DOSE FACTORS FOR TEENAGERS 87 A. 3-3 INGESTION DOSE FACTORS FOR CHILD 90 A. 3-4 INGESTION DOSE FACTORS FOR INFANT 93 A. 3-5 STABLE ELEMENT TRANSFER DATA 96 A. 4-1 SITE RELATED DOSE COMMITMENT FACTOR FOR ADULT 97 A. 4-2 SITE RELATED DOSE COMMITMENT FACTOR FOR TEEN 100 A.4-3 SITE RELATED DOSE COMMITMENT FACTOR FOR CHILD 103 A. 4-4 SITE RELATED DOSE COMMITMENT FACTOR FOR INFANT 106 A.5-1 INHALATION DOSE PARAMETER FOR THE CHILD 109 A.5-2 INHALATION PATHWAY FACTOR FOR ADULT (RI FACTORS) 110 A.5-3 INHALATION PATHWAY FACTOR FOR TEEN (RI FACTORS) 112 A.5-4 JNHALATION PATHWAY FACTOR FOR CHILD (RI FACTORS) 114 A.5-5 INHALATION PATHWAY FACTOR FOR INFANT (RI FACTORS) 116 A.5-6 GRASS-COW-MILK PATHWAY FACTOR ADULT (RI FACTORS) 118 A.5-7 GRASS-COW-MILK PATHWAY FACTOR TEEN (RI FACTORS) 120 A.5-8 GRASS-COW-MILK PATHWAY FACTOR CHILD (RI FACTORS) 122 A.5-9 GRASS-COW-MILK PATHWAY FACTOR INFANT (RI FACTORS) 124 A.5-10 GRASS-COW-MEAT PATHWAY FACTOR ADULT (RI FACTORS) 126

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OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES CONTINUED Table Page A.5-11 GRASS-COW-MEAT PATHWAY FACTOR TEEN (RI FACTORS) 128 A.5-12 GRASS-COW-MEAT PATHWAY FACTOR CHILD (RI FACTORS) 130 A.5-13 VEGETATION PATHWAY FACTOR ADULT (RI FACTORS) 132 A.5-14 VEGETATION PATHWAY FACTOR TEEN (RI FACTORS) 134 A;5-15 VEGETATION PATHWAY FACTOR CHILD (RI FACTORS) 136 A.5-16 GROUND PLANE PATHWAY FACTOR (RI FACTOR) 138 A.5-17 GRASS-GOAT-MILK PATHWAY FACTOR ADULT 139 A.5-18 GRASS-GOAT-MILK PArHWAY FACTOR TEEN 141

A.5-19 GRASS-GOAT-MILK PATHWAY FACTOR CHILD 143 A.5-20 GRASS-GOAT-MILK PATHWAY FACTOR INFANT 145 LIST OF FIGURES Figure Page B-1 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 150 B-2 PLUME TRAVEL DISTANCE VERSUS FRACTION REMAINING IN 151 PLUME B-3 PLUME TRAVEL DISTANCE VERSUS RELATIVE DEPOSITION 152 RATE

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OFFSITE DOSE CALCULATION MANUAL 1.0 Introduction The Offsite Dose Calculation Manual describes the ~adioactive Effluent Controls Program. The implementation of this program ensures compliance with the requirements of 10 CFR 50. 36, 10 CFR 20.106, 10 CFR 20.1302, 10 CFR 50 Appendix I and 40 CFR 190.

On January 1, 1994, 10 CFR 20.1001-20.2402 was implemented. Wolf Creek maintains the existing level of gaseous effluent control established from specifications in the first implementation of 10 CFR 20.106, now contained in Wolf Creek Technical Specification 5.5.4.g.

Compliance with Technical Specification 5.5.4.g has been determined by the NRC to be As Low As Reasonably Achievable (ALARA).

On December 18, 1999 Wolf Creek implemented,.10 CFR 20.1302 limits for radioactive liquid effluents. The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREA conforms to 10 times the concentration values in Appendix B, Table .2, Column 2, to 10 CFR 20.1001-20.2402.

The ODCM describes the methodology and parameters used in the calculation of off site doses due to radioactive liquid and gaseous effluents. The ODCM contents for calculation of dose are based on "Preparation of Radiological Effluent Technical Specifications for

_Nuclear Power Plants (NUREG-0133) ," and Regulatory Guide 1.109, Revision 1.

Dose calculations are performed for the limiting age group i.e. ,

Adult age group for the liquid pathway, and the Child age group for gaseous effluent organ doses.

The ODCM provides the limitations on the FUNCTIONALITY of radio~ctive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination. Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified interval.

The ODCM provides descriptions of the information that should be included in the Annual Radioactive Effluent Release* Reports.

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OFFSITE DOSE CALCULATION MANUAL 2.0 Liquid Effluents 2.1 Concentration - Compliance with 10 CFR 20 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to 10 times the limit specified in 10 CFR Part 20, Appendix B, Table 2, Column 2, for radionuclide~ other than dissolved or entrained noble gases. For dissolved or entrained ,noble gases, the concentration shall be 4

limited to 2x10- microCurie/mL total activity. (USAR Chapter 11) 2.1.1 Remedial Action W:L th the concentration of radioactive material released in liquid effluents

to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

2.1.2 Surveillance Requirements To show compliance with this requirement, concentrations of actual liquid effluents will be determined by performing Isotopic Analyses.

Radioactive liquid wastes shall be sampled and analyzed according to the sampling ahd analysis program of Table 2-1.

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OFFSITE DOSE CALCULATION MANUAL TABLE 2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM DISSOLVED/

LIQUID PRINCIPAL ENTRAINED GROSS RELEASE SAMPLE GAMMA GASES ALPHA AND Sr-89, Fe-55, TYPE FREQUENCY EMMITERS I-131 (GAMMA) H-3 Sr-90 Ni-63

1. Batch Tanks(2)

THB07A&B *p P(3) p M M Q Q Composite Composite Composite

( 4) ( 4) ( 4)

LLD (1) 5E-7 lE-6 lE-5 lE-7 Alpha 5E-8 lE-6 lE-5 H-3 THF04A&B p p (3) p M M Q Q Composite Composite Composite (4) ( 4) ( 4)

LLD (1) 5E-7 lE-6 lE-5 lE-7 Alpha 5E-8 lE-6 lE-5 H-3

2. Continuous Releases(5)

Steam D (6) W(3) w M M Q Q Generator Composite Composite Composite Composite Composite Blowdown (4) (4) (4) (4) (4)

LLD(l) 5E-7 lE-6 lE-5 lE-7 Alpha 5E-B lE-6 lE-5 H-3 Turbine D (6) W(3) w M M Q Q Building Composite Composite Composite Composite Composite Sump (4) ( 4) (4) ( 4) (4)

LLD(l) 5E-7 lE-6 lE-5 lE-7 Alpha 5E-8 lE-6 lE-5 H-3 Waste Water D (6) W(3) w M M Q Q Treatment Composite Composite Composite Composite Composite (4) (4) (4) (4) (4)

LLD (1). 5E-7 lE-6 lE-5 lE-7 Alpha 5E-8 lE-6 lE-5 H-3 Lj.me Sludge D (6) W(3) w M M Q Q Pond Composite Composite Composite Composite Composite

( 4) ( 4) ( 4) (4) ( 4)

LLD (1) 5E-7 lE-6 lE-5 lE-7 Alpha 5E-8 lE-6 lE-5 H-3 LLD = (µCi/ml)

NOTATION FREQUENCY NOTATION FREQUENCY s At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SA At least once per 184 days 1

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months R At least onc e per 18 months w At least once* per 7 days S/U Prior to each reactor startup M At least once per 31 days N.A. Not Applicable Q At least once per 92 days p Completed prior to each release

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OFFSITE DOSE CALCULATION MANUAL TABLE 2-1 (Continued)

TABLE NOTATIONS (1) The LLD is defined, 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:

4.66 Sb LLD=

ExVx2.22x 10 6 xYxDecay Eq. 1 Where:

LLD = the "a priori" lower limit of detection (microCuries per unit mass or volume) sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute Eq.2 Where:

B = background sum (counts)

LT= live time (minutes)

E the counting efficiency (counts per disintegration)

V = the sample size (units of mass or volume) 2.22x10 6 = the number of disintegrations per minute per microCurie Y = the fractional radiochemical yield, when applicable Decay= decay factor(s); there are three decay factors that may be appropriate for use depending on the nature of the sample and the half-life of the nuclide; any combination of the three may be used; the factors are as follows:

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OFFSITE DOSE CALCULATION MANUAL TABLE 2-1 (Continue--d)

TABLE NOTATIONS a) This decay factor corrects for decay from the time of sampling to the start of the analysis.

e-Mts Eq.3 Where:

Ats= decay time= acquisition start time - sample time A~ ln2/half-life b) This decay factor corrects for decay during the analysis.

1- e *ART A.XRT Eq.4 Where:

1 = ln2/half-life RT= real time of counting c) This decay factor corrects for decay during sampling.

1-e -.wd iAtd Eq.S Where:

A= ln2/half-life A'tci = deposition time = ( sample . time - deposition start time) ,

or for effluents only (sample time - midpoint of sample period)

NOTE All times used in decay calculations should be *in the same units.

Typical values of E, V, Y, ts, td should 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.

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL

Information Use !Page 18 of 160 ATTACHMENT A (Page 10 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE 2-1 (Continued)

TABLE NOTATIONS For very low background counting, the LLD can optionally be calculated as follows:

LLD= 2.71 + 4.66 Sb E x V x 2.22 x 10 6 x Y x Decay Eq.6 (2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in plant

.procedures to assure representative sampling.

(3) The principal gamma emitters for which the LLD specification applies include 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. 3/18 (4) 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 that is representative of the liquids released. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite samples to be representative of the effluent release..

(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6) Samples shall be -taken at the initiation of effluent flow and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter while the release is occurring.

To be representative of the liquid effluent, the sample volume shall be proportioned to the efflu~nt stream discharge volume. The ratio of sample volume to effluent discharge volume shall be maintained constant for all samples taken fo:rf the composite sample.

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OFFSITE DOSE CALCULATION MANUAL 2.2 Dose - Compliance With 10 CFR 50 Appendix I The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS s.hall be limited:

a. During any calendar quarter to less than or equal to 1~5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the

~"

whole body and to less than or equal to 10 mrems to any organ.

2.2.1 Remedial Action With the calculated dose from the release of-radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 .days, a Special Report that

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. This Special Report shall also include the results of radiological analyses of the drinking water source, and the. radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Clean Drinking Water Act. This requirement of (a.) and (b.) are applicable only if drinking water supply is taken from the receiving body within 3 miles of the plant discha~ge.

2.2.2 Surveillance Requirements Cumulative dose contributions from liquid effluents for the. current calendar quarter . and the current calendar year shall be determined using the following methodology at least once per 31 days.

D, = Li (Ai, f A tACi,..FAJ N=I Eq. 7 Where:

D, = cumulative dose commitment to .the total body or any organ, r, m

from the liquid effluent for the total time period LA t1..,in mrem J..=I AtA = the length of the Lth time period over which CiA and FA are averaged for all liquid releases, in hours

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OFFSITE DOSE CALCULATION MANUAL C11 the average concentration of radionucl~de i, in undiluted liquid effluent flow during time period ~t 1 , in µCi/ml F 1 = the near field average dilution factor for Ci 1 during any liquid effluent release; it is calculated as follows:

F =

1 f

(f +F)K Eq.8 Where:

f = liquid.radioactive waste flow (waste water flow)

F = liquid dilution flow, the average dilution flow during release K = applicable factor; the site dependent value for the mixing effect of the discharge structure; this value is conservatively assumed to be 1 (one) for this section A1 , = the site related ingestion dose commitment factor to- the total body or any organ, T, for each identified principal gamma and. beta emitter in mrem/hr per µCi/ml; see Tables A.4-1 through A.4-4 The limiting age group for liquid dose calculations is the Adult a~e group.

Eq.9 Where:

Dw = dilution factor from the near field area to the potable water

. \.. *.

intake fo~ water consumption; for Wolf Creek Generating Station, this factor is 1 (one)

BFi = bioaccumulation factor for radionuclide i in fish, in pCi/kg per pCi/1 (Table A.1-1 from Regulatory Guide 1.109, Rev. 1)

DFi adult dose conversion factor for radionuclide i, in mrem/pCi (Table A.3-1 from Regulatory Guide 1.109, Rev. 1)

Uw = adult water consumption, 730 1/yr (Regulatory Guide 1.109)*

UF = adult fish consumption, 21 kg/yr (Regulatory Guide 1.109)

10 6 pCi/µCi x 10 3 ml/l

1. 14E5 = Units, conversion factor = hr /yr .

8760

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OFFSITE DOSE CALCULATION MANUAL The dose calculations are based on the actual isotopic analysis of the radioactive liquid effluents, the radioactive liquid effluent flow and the dilution flow.

The above dose calculati9ns utilize NUREG-0133 equations and Regulatory Guide 1.109 tables. For the effluent pathways in use at Wolf Creek, NUREG-0133 and Regulatory Guide 1.109 are equivalent calculations when the 'nuclide transit time to point of exposure',

used in Regulatory Guide 1.109, is set to zero. NUREG~0133 calculations are dev~loped and used here for calculation simplification in the event manual calculations are needed. Software currently in use utilizes the equivalent Regulatory Guide 1.109 equations to provide greater software versatility. Equations have been proven equivalent algebraically and numerically.

2.3 Projected Dose The Liquid Radwaste Treatment System shall be FUNCTIONAL and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to liquid ef{luent, from each unit, to UNRESTRICTED AREAS would exceed 0.06 mrem to the whole body or 0.2 mrem to any*organ in a 31 day period.

2.3.1 Remedial Action With ~adioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, a Special Report that includes the following information:

a. Explanation of why liquid radwaste was being discharged without treatment, identification of any nonfunctional equipment or subsystems, and the reason for the nonfunctionality,

b. Action(s) taken to restore the nonfunctional equipment to FUNCTIONAL status, and

c. Summary description of action(s) taken to prevent a recurrence.

2.3.2 Surveillance Requirements 2.3.2.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with_

the following methodology when Liquid Radwaste Treat~ent Systems are not being fully utilized.

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OFFSITE DOSE CALCULATION MANUAL D31 = [~ J x 31 Eq.10 Where:

D31 = projected 31 day dose A cumulative dose for previous three calendar months T = number of days that the cumulative dose occurred in A above 2.3 .. 2.2 The installed Liquid Radwaste Treatment System shall be considered FUNCTIONAL by meeting the requirements of Sections 2.1 and

2. 2:

2.4 Instrumentation The radioactive liquid effluent monitoring instrumentation channels shown in Table 2-2 shall be FUNCTIONAL with their Alarm/Trip Setpoints set to ensure that the limits of $ection 2.1 are not exceeded. The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters described in Section 2.4.4.

2.4.1 Remedial Action 2.4.1.1 With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above, immediately suspend the release of .radioactive liquid effluents monitored by the affected channel, or declare the channel nonfunctional.

2. 4 .1. 2 With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels* FUNCTIONAL, take the ACTION shown in Table 2-2. Restore the nonfunctional instrumentation to FUNCTIONAL status within the time specified in the ACTION, or expl_ain in the next Annual Radioactive Effluent Release Report *why this nonfunctionality was not corrected within the time specified.

2.4.2 Surveillance Requirements Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 2-3.

_J

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OFFSITE DOSE CALCULATION MANUAL TABLE 2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM ACTION CHANNELS FUNCTIONAL

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Discharge Monitor 1 31 (HB-RE-18)

b. Steam Generator Blowdown Discharge 1 32 Monitor (BM-RE-52)

c. Turbina Building Drain Monitor 1 32 (LE-RE-59)

d. Secondary Liquid Waste System 1 31 Monitor (HF-RE-45)

e. Wastewater Treatment System 1 32 Influent Monitor (HF-RE-95)

2. Flow Rate Measurement Devices

a. Liquid Radwaste Discharge Line

1) Waste Monitor Tank A Discharge 1 33 Line

2) Waste Monitor Tank B Discharge 1 33 Line

b. Steam Generator Blowdown Discharge 1 33 Line

c. Secondary Liquid Waste System Discharge Line

1) Secondary Liquid Waste Monitor 1 33 Tank A Discharge Line

2) Secondary Liquid Waste Monitor 1 33 Tank B Discharge Llne

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OFFSITE DOSE CALCULATION MANUAL TABLE 2-2 (Continued)

ACTION STATEMENTS Action 31 - With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Section 2.1.2, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

Action 32 - With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for principle gamma emitters and I-131 at a lower limit of detection as specified in Table 2-1.

a. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 microCurie/gram DOSE EQUIVALENT I-131, or

b. At least once per 2 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when the specific activity of the secondary coolant is less than: or equal to O. 01 microCurie/gram DOSE EQUIVALENT I-131.

Action 33 - With the number 'of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated in place may be used to estimate flow.

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OFFSITE DOSE CALCULATION MANUAL TABLE 2-3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT CHANNEL SOURCE CHANNEL CHANNEL CHECK CHECK CALIBRATION OPERATIONAL TEST

1. Radioactivity Monitors providing alarm and automatic termination of release

a. Liquid Radwaste Discharge D p R(2) Q (1)

Monitor (HB-RE-18)

b. Stearn Generator Blowdown D M R(2) Q (1)

Discharge Monitor (BM-RE-52)

c. Turbine Building Drain D M R(2) Q (1)

Monitor (LE-RE-59)

d. Secondary Liquid Waste System D p R(2) Q (1)

Monitor (HF-RE-45)

e. Wastewater Treatment System D M .R(2) Q (1)

Influent Monitor (HF-RE-95)

2. Flow Rate Measurement Devices

a. Liquid Radwaste Discharge 0(3) N.A. R N.A.

Line

b. Stearn Generator Blowdown 0(3) N.A. R N.A.

Discharge Line

c. Secondary Liquid Waste System 0(3) N.A. R N.A.

Discharge Line

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OFFSITE DOSE CALCULATION MANUAL TABLE 2-3 (Continued)

TABLE NOTATIONS (1) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur as appropriate if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm/Trip Setpoint (isolation and alarm), or

b. Circuit failure (alarm only), or

c. Instrument indicates a downscale failure (al.arm only), or

d. Instrument controls not set in operate mode (alarm only).

(2) The initial CHANNEL CALIBRATION for each model detector shall be performed using one or more of the reference (gas, liquid and/ or solid) standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range or energy, measurement range, and establish monitor response to solid secondary calibration source ( s) . For subsequent CHANNEL CALIBRATION, NIST traceable standard (gas, liquid and/or solid) may be used; or a solid source that has been correlated to the detectors initial CHANNEL CALIBRATION that was previously (within 30 days) calibrated by the same geometry and type of source standard traceable to NIST. 3/18 With vendor concurrence, initial CHANNEL CALIBRATIONS for the same model and type detector are representative of all detectors of the same model and type. 3/18 Initial detector CHANNEL CALIBRATIONS may be performed by a vendor in place of on-site initial CHANNEL CALIBRATION, providing all of the requirements specified in the ODCM and USAR are met. 3/18 (3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANN~L CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which .continuous, periodic, or batch releases are made.

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OFFSITE DOSE CALCULATION MANUAL 2.4.3 Liquid Monitor Calibration Methodology The five monitors ~ssociated with liquid releases are listed below:

Monitor ID Description 0-BM-RE-52 Steam Generator Blowdown Discharge Monitor 0-cLE-RE-59 Turbine Building Drain.Monitor 0-HF-RE-45 Secondary Liquid Waste System Monitor 0-HB-RE-18 Liquid Radwaste Discharge Monitor 0-HF-RE-95 Wastewater Treatment System Influent Monitor Liquid effluent streams are monitored by an NaI (Tl) Detector. The detector operates in a gross counting mode and is gamma sensitive.

Calibration of the liquid monitors shall be performed using at least three standard solutions of Cs-137. The standards shall cover the appropriate range of the detector and have concentrations of approximately 5 x 10-7 µCi/cc, 1 x 10-5 µCi/cc, and 1 x 10-3 µCi/cc.

The standards shall be presented to the detector and the meter reading in counts per minute shall be recorded. A determination of linearity shall be produced using the counts per minute vs.

concentration data. 3/18 2.4.4 Liquid Effluent Monitor Setpoints The High Alarm/Trip Setpoints for the Liquid Effluent Radiation

~onitors are based on 10 times the initantaneous concentration limits of 10 CFR 20, Appendix B, Table 2, Column 2 applied at the boundary of the restricted area. Specifically, the High Alarm Setpoint will correspond to 10 times the 10 CFR Part 20 limits at the boundary of the restricted area. Since the high alarm/trip initiates isolation of the particular system and termination of the release, this setpoint represents assurance that 10 times the instantaneous liquid release limit of 16 CFR Part 20 is not exceeded. Auditable records shall be maintained indicating the actual setpoints used at all times.

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OFFSITE DOSE CALCULATION MANUAL The following discussion explains the setpoint methodology, which is applied in greater detail in subsequent sections. The calculated Alarm and Trip Action Setpoints for the Liquid Effluent Line Monitors must satisfy the following equation:

c(-f)sECL F+f Eq. 11 Where:

ECL = ten times the liquid Effluent Concentration Limit of 10 CFR 20, which implements Section 2 .1 in µCi/ml; for dissolved or entrained noble gases, the concentration shall be limited to 2x10- 4 µCi/ml total activity 3/18 c .= the setpoint, in µCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line (waste water line) prior to dilution and subsequent release; the setpoint is inversely proportional to the volumetric flow of the effluent line and directly proportional to the volumetric flow of the dilution stream plus the effluent stream; the setpoint represents a value, which if exceeded would result in concentrations exceeding 10 times the limits of 10 CFR 20 in the restricted area f = the effluent pump flow rate (waste water flow rate) as measured at the radiation monitor location, in volume per unit time, but. in the same units as F below F = the dilution water flow rate as measured prior to the release point, in .volume per unit time Rearranged, the expression for determining the setpoint on the liquid radwaste effluent line monitor becomes:

cs ECL( F; f) (µCi/ml)

Eq. 12 If no gamma activity is detected, calculate the monitor setpoint by assigning the available ECL fraction to 10 times the 10 CFR 20 ECL for I-131.

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OFFSITE DOSE CALCULATION MANUAL 2.4.4.1 Continuous Liquid Effluent Monitors The three monitors associated with continuous

liquid releases are listed below:

Monitor ID Description 0-BM-RE-52 Steam Generator Blowdown Discharge Monitor 0-LE-RE-59 Turbine Building Drain Monitor 0-HF-RE-95 Waste Water Treatment System Influent Monitor The Steam Generator Blowdown Discharge Effluent Monitor continuously monitors the Blowdown Discharge Pump Outlet to detect excess radioactivity due to System Demineralizer breakthrough or abnormal Primary to* Secondary *leakage. The Blowdown Discharge Monitor's High Alarm Setpoint initiates CLOSURE of the Blowdown Isolation Valves and the Blowdown Discharge Valve. Similarly, the High Radiation Alarm on the Turbine Building Drain Monitor and Waste Water Treatment Monitor initiates CLOSURE of the Drain Line. Isolation Valves to prevent the release of radioactive effluents.

Monitor setpoints will be conservatively based *on I-131, the most restrictive isotope expected to be present. This is particularly appropriate for the Turbine Building Drain Line Monitor since the most probable source is the Secondary Steam System which is expected to have negligible activity unless there is a significant Primary to Secondary leak. Due to changing activities, it will not be possible to select a radionuclide distribution on which to base the monitor setpoint. Additionally, maximum effluent flows and minimum dilution flows will normally be assumed.

The High Alarm/Trip Setpoint will be set to correspond to 10 times the I-131 ECL limit at the boundary of the restricted area from 10 CFR

Part 20, Appendix B, Table 2, Column 2. The alert alarm is set one order of magnitude below the High Alarm/Trip Setpoirit for release points that have d;i.lution and to the High Alarm value for those wi th9ut dilution. This High Alarm/Trip Setpoint assures the* limits of Section 2. 1 are not exceeded at . the boundary of the restricted area.

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OFFSITE DOSE CALCULATION MANUAL The above continuous liquid effluents are not radioactive effluents until. activity has been detected by the liquid effluent moni to-r, a tritium analysis of the secondary system, or a gross beta analysis of the secondary sy~tem. At that time, an analysis of the effluent will be made to verify activity in the system effluent. During periods of time when the* above liquid effluents are not radioactive, the High Alarm/Trip . Setpoint may be set to 1. 5 times the background count rate.

The high alarm/trip setpoints for continuous releases are calculated using the following methodology:

SETPOINT (µCi/ml) = ECL 1_131 x F; f x AF x SF Eq.13 Where:

ECLr~31 lE-5 µCi/ml (this .value equals 10 times the Effluent Concentration Limit of I-131) 3/18 F = dilution flow rate f effluent (waste water) flow rate through any of the. three previously named monitors AF= the allocation fraction; a conservative factor used to allocate portions of a shared dilution stream to separate concurrent releases '

to ensure the concentration limits of section 2 .1 are not .exceeded. I The sum of allocation fractions for concurrent releases with a shared discharge point shall not exceed 1. 0 and may be altered based on plant need. For cases where the ECL fraction exceeds 1. 0, dilution is required to ensure compliance with section 2.1, and the allocation fraction must be applied to ensure this compliance is met.

SF = the safety factor; a conservative fas::tor used to compensate *for statistical fiuctuations and errors of measurement; the default value is 1. 0, however, this value may be set, administr.ati vely, to values less than 1.0 The setpoint calculation is based on the minimum dilution flow rate, the maximum possible effluent flow rate and due to changing conditions, I-131, which is the most restrictive isotope expected to be present.

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OFFSITE DOSE CALCULATION MANUAL In the event that a high alarm/trip is reached, the release will be terminated and evaluated to see if the limit of Section 2. 1 was exceeded by using the actual Dilution Flow Rate, the actual Effluent Flow Rate and the actual isotopic analysis as . outlined in Section 2.4.4.2. The setpoint will still be based on 10 times the 10 CFR 20 ECL of I-131 due to the changing conditions of activity and I-131 being the most restrictive isotope. 3/18 2.4.4.2 Batch Radioactive Liquid Effluent Monitor The two monitors associated with liquid batch releases are listed below:

Monitor ID Description 0-HF-RE-45 Secondary Liquid Waste System Monitor 0-HB-RE-18 Liquid Radwaste Discharge Monitor The High Alarm/Trip setpoint is a function of dilution flow rate, tank flow rate, and isotopic composition. A laboratory isotopic analysis is made of each batch prior to discharge. Based on the isotopic analysis and existing flow condition, the setpoint will be calculated and set on the appropriate monitor to ensure the 10 times the Effluent Concentration Limits of 10 CFR 20, Appendix B, Table 2, Column 2 (WCNOC ODCM

Attachment A, Section 2. 1) are not exceeded.

The Alert/Alarm Setpoint is set to 80% of the High Alarm/Trip setpoint.

The High Alarm/Trip setpoints are determined using the following methodology:

a. Determine concentrations of radioactivity of the batch being considered for release.

The isotopic concentration of the batch is the sum of the concentrations for the isotopes present as determined from the analysis required in Table 2-1.

Lei = Leg +Ca +Cs +Ct +Cf i g Eq. 14 Where:

Ci= the concentration of nuclide i as determined by the analysis of the waste sample

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OFFSITE DOSE CALCULATION MANUAL Cg the sum of the concentrations Cg of each measured gamma emitting nuclide observed by gamma-ray spectroscopy of the waste sample

Ca the measured concentration Ca of alpha emitting nuclides I

observed by gro.ss alpha analysis of the monthly composite sample

Cs= the measured concentrations of Sr-89 and Sr-90 in liquid waste as determined by analysis of the quarterly composite sample

Ct= the measured concentration of H-3 in liquid waste

Cf= the measured concentration of Fe-55 and Ni-63 in liquid waste as determined by analysis of the quarterly composite

Values for these concentrations will be based on previous composite sample analysis as required by Table 2-1.

b. The measured radio'nuclide conc:entrations are used to calculate the Required Dilution Factor (RDF) which is the ratio of total dilution flow rate to tank flpw rate required to assure .that the limiting concentrations of Section 2. 1 are met at the point of discharge. This is referred to as the Required Dilution Factor and is determined according to:

Eq. 15 Where:

RDF = required dilution factor to meet 10 times 10 CFR 20 ECLs at point of discharge Ci = measured concentrations of Cg, Ca, Cs, Ct* and Cf as defined previously; terms Ca, Cs, Ct and Cf will be included in the calculation as appropriate 3/18 ECLi = ECLg, ECLa, ECLs, ECLt and ECLf ar_e 10 times the limiting concentration of the appropriate radionuclide from 10 CFR 20, Appendix B, Table 2, Column 2; for dissolved or entrained noble gases, the concentration shall be limited .to 2. OE-04 µCi/ml total activity

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OFFSITE DOSE CALCULATION MANUAL AF= the allocation fraction; a conservative factor used to allocate portions of a shared dilution stream to separate concurrent releases to ensure the concentration limits of section 2.1 are not exceeded.

The ~um of allocation fractions for concurrent releases with a shared discharge point shall not exceed 1. 0 and may _be altered bas_ed on plant need. For cases where the ECL fraction exceeds 1. 0, dilution is required to ensure compliance with s*ection 2. 1, and the allocation fraction must be applied to ensure this compliance is met.

SF= the safety factor; a conservative factor used to compensate for statistical fluctuations and errors of measurement; the default value is 1. 0 F dilution flow rate f = effluent flow rate (waste water flow rate)

c. The calculated maximum permissible waste tank effluent flow rate (fmaxl is based on the Required Dilution Factor (RDF) and the effective dilution flow rate (Feffl.

Feff +f ~~for F

f(ffi f :$;

max RDF . RDF \1-eff Eq. 16 Where:

fmax = the calculated maximum permissible waste tank effluent flow rate f = the expected effluent (waste stream) flow rate; normally the rated capacity of the effluent pump RDF = the required dilution factor; as defined previously Eq. 17 Where:

Faff= effective dilution flow rate; this is applied since the cooling lake into which the effluent is

discharged is also the dilution stream; this accounts for the

recirculation of previously emitted radionuclides should they be detected by sample analysis of the cooling lake water Fm= the expected minimum dilution water flow rate; for the purpose of setpoint calculations, the expected minimum dilution flow rate is assigned a value based upon the type and number of pumps running into the circulating water piping LCi = the measured concentration of nuclide i in the cooling lake water sample

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OFFSITE DOSE CALCULATION MANUAL ECLi = Effluent Concentration Limit;* set to 10 times the Effluent Concentration Limit of nuclide's from 10 CFR 20, Appendix B, Table 2, Column 2 in accordance with ODCM Attachment A, Section 2.1 Thus the pump flow rate, f, in the above equation is set at or below

. fmax. Even though the value of fmax may be* larger than the actual effluent pump capacity, it does represent the upper limit to the effluent flow rate, whereby the requirement of 10 CFR 20 may still be met. If RDF < 1, the effluent pump flow rate may be assigned any value since the waste tank effluent concentration meets the limits of 10 CFR 2P without dilution and the release may be made without regard to the setpoints for other release pathways. For. those discharge pathways selected to be secureq during the release under consideration, the pump flow rate should be set at as low a value as practicable to detect any inadvertent release. A setpoint for the dilution stream flow rate is not applicable since the minimum flow rate is administratively set.

d. The liquid radiation monitor setpoint may now be determined based on the values of ~i, Ci, f, and fmax as previously defined. The monitor response is primarily du,e to gamma radiation; therefore, the actual setpoint is based on ~g and Cg. The calculated monitor setpoint concentration is determined as follows:

Eq.18 Where:

A= idjustment factor which will allow the setpoint to be established in a practical manner for convenience and to prevent spurious alarms A= fmax f

Eq.19 If A> 1, calculate c to determine the maximum value for the actual monitor setpoint (µCi/ml).

If A< 1, no release may be made. Calculations must be repeated to reduce monitor setpoint by applying a combination of higher dilution flow, lower tank/ system release rate, or increased allocation fraction (AF) .

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OFFSITE DOSE CALCULATION MANUAL If RDF < 1, no further dilution is required and the release.may be made without regard to available dilution or to other releases made simultaneously. However, it is necessary to establish a monitor setpoint which will provide alarm should the release concentration inadvertently exceed 10 CFR. 20 limits; This can be accomplished by establishing the adjustment factor as follows:

1 A=--

RDF Eq.20

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OFFSITE DOSE CALCULATION MANUAL 3.0 Gaseous Effluents Gaseous effluent releases from the Unit Vent and Radwaste Building Vent are monitored continuously. The Unit Vent is the release point for the Fuel/Auxiliary _Building, access control area, containment purge, and condenser air discharge. The Radwaste Building Vent is the release point for Waste Gas Decay Tanks and the Radwaste Building Ventilation System.

Waste Gai Decay_Tank releases and Containment Building releases are treated as batch releases. Waste Gas Decay Tank releases are monitored by the Radwaste Building Exhaust Monitor. Containment Building releases (purges) are monitored by the Containment Purge System monitors and the Plant Unit Vent Monitor.

Monitor identifications are as follows:

Monitor ID Release Point Description 0-GT-RE-21 A and B Unit Vent (Fuel/Auxiliary Building, access control area, containment purge, condenser air discharge) 0-GH-RE-10 A and B Radwaste Building Vent (Radwaste Building, waste gas decay tank discharge. Acts to isolate Waste Gas Decay Tank discharge) 0-GT-RE-22 and 33 Containment Purge System Monitor (acts to isolate the purge; is not an effluent monitor) 0-GT-RE-31 and 32 Containment Atmosphere Monitor (acts to isolate purge; not an effluent monitor)

The set point for monitors may be determined either based on total body dose or skin dose rate. The dose rate .limits are for dose rates at the SITE BOUNDARY. The monitor setpoint is the lesser of the total body dose rate or skin dose rate. 3/18

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OFFSITE DOSE CALCULATION MANUAL 3.1 Dose Rate - Compliance with Technical Specification 5.5.4.g The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

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

b. For Iodine-131 and 133, *for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

3.1.1 Remedial Action With the dose rate(s) exceeding the above limits, immediately restore the release to within the above limit(s).

3.1.2 Surveillance Requirements The dose rate to radionuclides in gaseous effluents shall be determined to be within the above limits in accordance with the methodology described below by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3-1.

Based on the methodology of NUREG-0133:

Release rate limit for noble gases:

(X!Q~Ki Qi <500mrem/yrfor thetotalbody Eq.21 (X!Q)L (Li + 1.1 Mi) Qi < 3000 mrem/yr for the skin i

Eq.22 Where:

Ki = the total body dose factor due to gamma emissions for . each 3

identified noble gas radionuclide, in mrem/yr per µCi/m (Table A.1-2)

. (X!Q) = 2.2E-06 sec/m 3 at 1200 meters 3/18 Qi= the release rate of radionuclide i in gaseous effluent from all vent releases, in µCi/sec 3/18

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OFFSITE DOSE CALCULATION MANUAL Li= the skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem/yr per µCi/m 3 (~able A.1-2)

Mi= the air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per µCi/m 3 (Table A.1-2) 1.1 = unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose 3/18 Release rate limit for all radionuclides and radioactive materials in particulate form and radionuclides other than noble gases:

(x;Q)LR~ijQi < 1500 mrem/yr to any organ G) i Eq.23 Where:

(x/Q) = 2.2E-06 sec/m 3 at 1200 meters 3/18 RI aij = the dose parameter for radionuclides other than noble gases for the inhalation pathway (I) summed separately over the radionuclides ( i) for each organ ( j) and age group (a) , in mrem/yr per µCi/m 3 (Table A. 5-4); see step 3. 2. 2. 2 (R\ij for Inhalation Pathway Factor) for the calculation of R1 aij for the child age group Qi= the release rate of radionuclide i in gaseous effluent from all vent releases, in µCi/sec All radioiodines are assumed to be released in elemental form. The limit is applicable to the location (unrestricted area boundary or beyond), characterized by the value of X/Q which results in . the maximum total body or skin dose commitment. The factors Ki, Li, and Mi relate the* radionuclide airborne concentrations to various dose rates assuming a semi-infinite cloud. These factors are taken from Table B-1 of the Regulatory Guide 1.109 and multiplied by 106 to convert pci-1 to µci-1 and listed in.Table A.1-2.

_ ______J'

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OFFSITE DOSE CALCULATION MANUAL TABLE 3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Principal Gaseous Sample Gamma H-3 I-131/ Gross Release Type Frequency Emitters (Oxide*) I-133 Alpha Sr-89,Sr-90 1.Unit Vent:

Gas M M(3) (2) M(4)

LLD(l) lE-4 lE-6 Particulate Continuous(5) W(6) (2) M Q Composite LLD(l) lE-1'1 lE-11 lE-11 Charcoal Continuous(5) W(6)

LLD(l) lE-12/

lE-10 2.Radwaste Building Vent:

Gas M M(2) M LLD(l) lE-4 lE-6 Particulate Continuous(5) W(6) (2) M Q Composite LLD(l) lE-11 lE-11 lE-11 Charcoal Continuous(5) W(6)

LLD(l) lE-12/

lE-10 3.Containment Purge or Vent:

Gas I P(3) P (3) (2) M LLD(l) I lE-4 I lE-6 I

.4. Waste Gas Decay Tanks:

p P(2)

Gas I LLD(l) I lE-4 I LLD = (µCi/ml)

NOTATION FREQUENCY s At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months w At' least once per 7 days M At least once per 31 days Q At least once per 92 days SA At least once per 184 days R At least once per 18 months*

S/U Prior to each reactor startup N.A. Not Applicable p Completed prior to each release '

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OFFSITE DOSE CALCULATION MANUAL TABLE 3-1 (Continued)

TABLE NOTATIONS (1) The LLD is defined, 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 paxticular measurement system, which may include radiochemical separation:

4.66 Sb LLD=

Ex Vx (2.22E+6) x YxDecay Eq.24 Where:

LLD = the "a priori" lower limit of detection (microCuries per unit mass or volume)

Sb= the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, in counts per minute Eq.25 Where:

B = background sum (counts)

LT= live time (minutes)

E = the counting efficiency (counts per disintegration)

V the sample size (units of mass or volume) 1

2. 22xl 0 6 = the number of disintegrations per minute per microCurie Y = the fractional radiochemical yield, when applicable Decay = decay factor ( s) ; there are three decay factors that may be appropriate for use depending on the nature of the sample and the half-life of the nuclide; any combination of the three may be used; the factors are as follows:

I

_ _ _ ____________J

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OFFSITE DOSE CALCULATION MANUAL TABLE 3-1 (Continued)

TABLE NOTATIONS a) This decay factor corrects for decay from the time of sampling to the start of the analysis:

-JAt e '

Eq.26 Where:

Ats= decay time= acquisition start time - sample time A= ln2/half-life b) This decay factor corrects for decay during the analysis:

} - e -,1R.T JxRT Eq.27 Where:

.A= ln2/half-lif~

RT= real time of counting c) This decay factor corrects for decay during sampling:

1-e -Mt4 Mtd Eq.28 Where:

A= ln2/half-life A'tci = deposition time= (sample time - deposition start time), or for effluents only (sample time - midpoint of sample period)

NOTE All times used in decay calculations should be in the same units.

Typical values of E, V, Y, ts, td sh~uld be used in the calculation.

It should be recognized that* the LLD is defined as an ~ 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.

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OFFSITE DOSE CALCULATION MANUAL TABLE 3-1 (Continued)

TABLE NOTATIONS For very low background counting, the LLD can be optionally calculated as follows:

LLD= 2.71 + 4.66 Sb Ex Vx2.22x 10 6 x YxDecay Eq. 29 (2) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate releases. 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. 3/18 (3) Sampling and analysis shall also be performed foilowing shutdown, startup, or a THERMAL POWER.change greater than or equal to 15% of RATED THERMAL POWER within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period.

(4) Tritium grab samples shall be taken and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

(5) 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 Sections 3.1, 3.2 and 3.).

(6) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler. For unit vent, sampling shall also be performed at le~st once.per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period, and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement to sample once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months does not apply if analysis shows that both the DOSE EQUIVALENT I-131 concentration in the reactor coolant and the unit vent noble gas monitor activity have not increased more than a factor of' 3.

__J

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OFFSITE DOSE CALCULATION MANUAL 3.2 Dose - Compliance With 10 CFR 50 Appendix I 3.2.1 Noble Gases The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY shall be limited to th~ following:

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

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

3.2.1.1 Remedial Action With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a special report that 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.

3.2.1.2 Surveillance Requirements Cumulative dose contributions for the current calendar quarter and calendar year for noble gases shall be determined in accordance with the following methodology at least once per 31 days. *The dose calculations for the actual releases of radioactive noble gases in gaseous effluent will be consistent with the methodology provided in Regulatory Guide 1.109, Rev. 1. The following dose calculations will be performed:

During any calendar quarter, for gamma radiation:

i=l Eq.30

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OFFSITE DOSE CALCULATION MANUAL During any calendar quarter, for beta radiation:

i=l Eq.31 During any calendar year, for gamma radiation:

i=l Eq.32 During any calendar year, for b~ta radiation:

. i=l Eq.33 Where:

3.17E-8 = the inverse of the number of seconds in a year Mi= the air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per µCi/m 3 ; Table A.1-2 (Regulatory Guide 1.109, Table B-1, Column 4)

Ni= the air dose factor due to beta emissions for each identified noble gas radionuclide, in mra'd/yr per µCi/m 3 ; Table A.1-2 (Regulatory Guide 1.109, Table B-1, Column 2)

(x!Q) = 2.2E-06 sec/m3 at 1200 meters 3/18 Qi= the release of noble gas radionuclides i in gaseous effluents, in µCi; releases shall be cumulative over the calendar quarter or year as appropriate 3.2.2 Radioiodines, Particulates and Other Radionuclides The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each 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 mrems to any organ; and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

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OFFSITE DOSE CALCULATION MANUAL 3.2.2.1 Remedial Action With the calculated dose from

the release of Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than- 8 days, in gaseous effluent,s exceeding any of the above limits, prepare and submit to the Commission within 30 days, a special report that identifies the cause(s) for exceeding the limits 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.

3.2.2.2 Surveillance Requirements Cumulat,ive dose contributions for the current calendar quarter and current calendar year for Iodine-131 and 133, tritium, arid radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the following methodology at least once per 31 days.* To show compliance, the dose calculations for the actual releases of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, Revision 1. The following dose calculations will be performed:

For the calendar quarter: D (mrem)= 3.l 7E-8 LRaiJ(WQi )] s 7.5 mrem Eq.34 For the calendar year: D (mrem)= 3.l 7E-8 LRaij [(WQi )] s 15 mrem Eq.35 Where:

3.17E-8 = the inverse of the number of seconds in a year Qi the release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents i, in µCi. Releases shall be cumulative over the calendar quarter or year as appropriate. The Qi value shall be determined as the product of the flow rate through the release point and grab samples of the effluent analyzed in accordance with Table 3-1.

W = the annual average dispersion parameter for estimating the dose to an individual at the controlling location W (X/Q), 2.2E-6 sec/m 3 for the inhalation pathwa~

W (D/Q), l.BE-8 m- 2 for the food and ground plane pathways Raij = the dose factor for each identified radionuclide i, in mrem/yr per µCi/m 3 , for each age group a and target organ j; Tables A. 5-2 through A.5-20

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OFFSITE DOSE CALCULATION MANQAL Inhalation Pathway Factor, RI aij [X/Q]

R\ii [X!Q]= K'(BRt(DF~t)mrem/yrper µCi/m 3 )

Eq.36 Where:

K' = a constant of unit conversion, 106pci/µCi (BR)a = the breathing rate of the receptor age group a, in m3 /yr (Regulatory Guide 1.109, Table E-5)

Infant 1400 m3 /yr Child 3700 m3 /yr Teen 8000 m3 /yr Adult 8000 m3 /yr (DFAd aj = the maximum organ inhalation dose* factor for age group a, organ j and radionuclide i, in mrem/pCi; the body is considered an organ in _the selection of (DFAi) a; see Tables A. 2-1 through A. 2-4 (Regulatory Guide 1.109, Tables E-7 through E-10)

Ground Plane Pathway Factor, RGi[D/QJ

[D!Q] = K'K" (SF)DFG; ~(1-2 R G; e*"' A;]

1

); (m *mrem/yr)

~ µCi/sec Eq.37 Where:

K' = a constant of unit conversion, 106 pCi/µCi K" = a constant of unit conversion, 8760 hr/year Ai= the decay constant for radionuclide i, sec- 1 t = the exposure time, 9.47EB sec (30 years)

DFGi = the ground plane dose conversion factor for radionuclide i, in mrem/hr per pCi/m2 ; note that all age groups and organs are assumed to receive the same dose for the total body; see Table A.2-5

{Regulatory Guide 1.109, Table E-6)

SF= the shielding factor 0.7, dimensionless {Regulatory Guide 1.109, Table E-15)

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OFFSITE DOSE CALCULATION MANUAL Grass-Cow-Milk Pathway Factor, Re aij [D/Q]

R;Jo!Q]- K' ( ~;, ~U,d)r. (r) (DFL.),,{r, IY,Xe-<*, ) (m'~;,;,7/')

Eq.38 Where:

K' = a constant of unit conversion, 106 pCi/µCi QF = the cow's consumption rate, 50 kg/day (wet weight) (Regulatory Guide 1.109, Table E-3)

Uap = the receptor's milk consumption

rate for age group a, in liters/yr (Regulatory Guide 1.109, Table E-5)

Infant = 330 1/yr Child 330 1/yr Teen = 400 1/yr Adult 310 1/yr Yp the agricultural productivity by unit , area of pasture feed grass, 0.7 kg/m 2 (Regulatory Guide 1.109, Table E-15)

Fm = the stable element transfer coefficient, in days/liter; see Table A.3-5 (Regulatory Guide 1.109, Table E-1) r = the fraction of deposited activity retained on the cow's feed grass; a value of 1.0 is used for radioiodines and 0.2 for particulates (Regulatory Guide 1.109, Table E-15)

(DFLd aj = the ingestion dose factor for age group a, radionuclide i and organ j, in units of mrem/pCi ingested; .see Tables A.3-1 through A.3-4 (Regulatory Guide 1.109, Tables E-11 through E-14)

Ai= the decay constant for radionuclide i, in sec- 1 Aw =. the decay constant for removal of activity on leaf and plant surfaces by the process of weathering, 5. 73E-7 sec- 1 (corresponding to a 14 day half-life) fp = the product of the fraction of the year that the cow is on pasture and the fraction of cow feed that is pasture grass; the value is assumed to be 1.0, which is the most restrictive case tf = the transport time for consumption of fresh pasture grass; the time from pasture, to cow, to milk, to receptor, in units of seconds; 1.73E5 sec (2 days) (Regulatory Guide 1.109, Table E-15) 3/18

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OFFSITE DOSE CALCULATION MANUAL Grass-Goat-Milk Pathway Factor, Rcaij [D/Q]

. Re"' [D!Q] ~ Kc~ ~U/JF (r) (DFL;),J, /de ) (m';;;;;,:?r) m Eq.39 Where:

QF = the goat's consumption rate, 6 kg/day (wet weight) (Regulatory Guide 1.109, Table E~3) tf ~ the transport time for consumption of fresh pasture grass; the time from pasture, to goat, to milk, to receptor, in units of

seconds; l.73E5 sec (2 days) (Regulatory Guide 1.109, Table E-15) 3/18 fp = the product of the fraction of the year that the goat is on pasture and the fraction of goat feed that is pasture grass; the value is assumed to be 1.0, which is the most restrictive case All other terms are defined under the Grass-Cow-Milk-Pathway Factor.

The concentration of tritium in cow or goat milk is based on the airborne concentration rather than the deposition. Therefore, the R\ij is based on (X/Q) ,

R c aii[X!Q]= K'K"'FmQFUap(DFL1J0.75 (0.5/H)](mrem/yrper µCi/m 3 }

Eq.40 Where:

3 K"' = a constant of unit conversion, 10 gm/kg H = absolute humidity of the atmosphere, 8 gm/m 3 (Regulatory Guide 1.109) 0.75 = the fraction of total feed that is water (NUREG 0133) 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water (NUREG 0133)

All other terms are previously defined.

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OFFSITE DOSE CALCULATION MANUAL Grass-Cow-Meat Pathway Factor, RMaij [D/Q]

R~ [DiQ] ~ K'( ~:~:))Fm (r) (DFL;).;{r,!Y,Xe-,,, ) (m';:;'.~1';;;:,")

Eq.41 Where:

Fm = the* stable element transfer coefficient, in days/kg; see Table A.3-5 (Regulatory Guide 1.109, Table E-1)

Uap = the receptor's meat consumption rate for age group a, in kg/yr (Regulatory Guide 1.109, Table E-5)

Infant 0 kg/yr Child = 41 kg/yr Teen = 65 kg/yr Adult 110 kg/yr tf = the transport time for consumption of fresh pasture grass; the time from pasture, to cow, to receptor, in units of seconds; l.73E6 seconds (20 days) (Regulatory Guide 1.109, Table E-15) 3/18 All other terms are previously defined.

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the RMaij is based on (X/Q): (terms defined previously)

R~[X!Q]= K'K"'FmQFUap(DFL1J0.75 (0.5/H)](mrem/yrper µCi/m 3 )

Eq.42

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OFFSITE DOSE CALCULATION MANUAL Vegetation Pathway Factor, Rvaij [D/Q]

Man is considered to consume two types of vegetation ( fresh and stored) that differs only in the time period between harvest and consumption, therefore:

m 2 *mrem/yr)'*

R:j [D!Q]~ K'[ YJ~ir+Aw)JDFL;).J(u; xfJ(e-""' )+(u: Xt'gXe-A;lh )] ( µCi/sec Eq.43 Where:

6 K' = a constant of unit conversion, 10 pCi/µCi ULa = the consumption rate of fresh leafy vegetation by the receptor for age group a, in kg/yr (Regulatory Guide 1.109, Table E-5)

Infant 0 kg/yr Child 26 kg/yr

, Teen 42 kg/yr Adult 64 kg/yr U8 a = the consumptio~ rate of stored vegetation by the receptor for age group a, in kg/yr (Regulatory Guide 1~109, Table E-5)

Infant 0 kg/yr Child 520 kg/yr Teen 630 kg/yr Adult 520 kg/yr fL = the fraction of the annual intake of fresh leafy vegetation grown locally; the default value is 1. 0 (Regulatory Guide 1.109, Table E-15) fg = the fraction of the annual- intake of stored vegetation grown locally; the default value is 0.76 (Regulatory Guide 1.109, Table E-15) tL = the average time between harvest of leafy vegetation and its consumption, in units of seconds; the default value is 8.6E4 seconds (1 day) (Regulatory Guide 1.109) th = the average time between harvest of stored vegetation and its consumption, in units of seconds; the default value is 5.18E6 seconds (60 days) (Regulatory Guide 1.109, Table E-15)

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OFFSITE DOSE CALCULATION MANUAL Yv = the agricultural productivity by unit area of leafy vegetation, in units of kg/m 2 ; the default value is 2.0 kg/m 2 (Regulatory Guide 1.109, Table E-15) 3/18 All other factors previously defined.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Rvaij is based on (X/Q) :

3 s ] mrem m v

Rai)X/Q] = K' K'" [UafL L

+ Uafg (DFLaaj[0.75(0.5/H)] in yr

-C.

µ i Eq.44 All terms defined previously. All values indicated are default values from Regulatory Guide 1.109, Rev. 1.

3.3 Projected Dose The

VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be FUNCTIONAL and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

3.3.1 Remedial Action With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, a special report that includes the following information:

a. Identification of any nonfunctional equipment or subsystems, and the reason for the nonfunctionality,

b. Action ( s) taken to restore the nonfunctional equipment to FUNCTIONAL status, and

c. Summary description of action(s) taken to prevent a recurrence.

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OFFSITE DOSE CALCULATION MANUAL 3.3.2 Surveillance Requirements 3.3.2.1 Doses due to gaseous releases from each unit to areas at and beyond the*SITE BOUNDARY shall be projected at least once per 31 days in accordance with the following methodology when Gaseous Radwaste Treatment Systems are not being fully utilized.

D31 =[~Jx31 Eq.45 Where:

D31 = projected 31 day dose A cumulative dose for previous three calendar months T = number of days that the cumulative dose occurred in A above 3.3.2.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered FUNCTIONAL by meeting Section 3.1 and 3.2 limits.

3.4 Instrumentation The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3-2 shall be FUNCTIONAL with their Alarm/Trip Setpoints set to ensure that the limiti of Section 3.1 are not exceeded. The Alarm/Trip Setpoints of these channels meeting Section 3.1 shall be determined and adjusted in accordance with the methodology and parameters of Section 3.4.4.

3.4.1 Remedial Action

a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm/Trip Set point less *conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel nonfunctional.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels FUNCTIONAL take the ACTION shown in Table 3-2. Restore the nonfunctiorial instrumentation to FUNCTIONAL status within the time specified in the ACTION, or explain in the next annual Radioactive Effluent Release Report why this nonfunctionality was not corrected within the time specified.

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OFFSITE DOSE CALCULATION MANUAL 3.4.2 Surveillance Requirements Each radioactive gaseous effluent monitoring instrumentation channel

I shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 3-3.

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OFFSITE DOSE CALCULATION MANUAL TABLE 3-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT - MINIMUM APPLICABILITV ACTION CHANNELS FUNCTIONAL

1. Unit Vent System

a. Noble Gas Activity Monitor - 1

40 Providing Alarm (GT-RE-21B)

b. Iodine Sampler i

43 (GT-RE-21A, GT-RE-21B)

c. Particulate Sampler 1

43 (GT-RE-21A, GT-RE-21B)

d. Flow Rate N.A.

45

e. Sampler Flow Rate Monitor 1

39

2. Containment Purge System

a. Noble Gas Activity Monitor - 1

41 Providing Alarm and Automatic Termination of Release (GT-RE-22, GT-RE-33)

b. Flow Rate N.A.

45

3. Radwaste Building Vent System

a. Noble Gas Activity Monitor - 1

38,40 Providing Alarm and Automatic Termination of Release (GH-RE-lOB)

b. Iodine Sampler 1

43 (GH-RE-lOA, GH-RE-lOB)

c. Particulate Sampler 1

43 (GH-RE-lOA, GH-RE-lOB)

d. Flow Rate N.A.

45

e. Sampler Flow Rate Monitor 1

39

At all times.

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OFFSITE DOSE CALCULATION MANUAL TABLE 3-2 (Continued)

ACTION STATEMENTS ACTION 38 - With the number of channels FUNCTIONAL less than required by the minimum channels FUNCTIONAL requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

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

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 39 - With the number of channels FUNCTIONAL less than r~quired by the minimum channels FUNCTIONAL requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 40 - With the number of channels FUNCTIONAL less than required by the minimum channels FUNCTIONAL requirement, effluent releases via

this pathway may continue for up to 30 days provided grab samples are taken at least onci per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 41 - With the number of channels FUNCTIONAL less than required by the minimum channels FUNCTIONAL requirement, immediately suspend PURGING of radioactive effluents via this pathway.

ACTION 43 - With the number of channels FUNCTIONAL less than required by the minimum channels FUNCTIONAL requirement, effluent releases via th*e affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sample equipment as required in Table 3-1. Revised 08/11 to include either 'A' or 'B' pathways as options for fulfilling this requirement, as both fulfill the requirement of being samplers by plant design.

ACTION 45 - Flow rate for this system shall be based on fan status and operating curves or actual measurements.

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OFFSITE DOSE CALCULATION MANUAL TABLE 3-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT CHANNEL SOURCE CHANNEL CHANNEL MODES FOR CHECK CHECK CALIBRATION OPERATIONAL WHICH TEST SURVEILLANCE IS REQUIRED

1. Unit Vent System

a. Noble Gas Activity D M' R(3) Q (2)

Monitor-Providing Alarm (GT-RE-21)

b. Iodine Sampler w N.A. N.A. N.A.

C. Particulate Sampler w N.A. N.A. N.A. *

d. Flow Rate N.A. N.A. R(4.) N.A. *

e. Sampler Flow Rate Monitor D N.A. R Q *

2. Containment Purge System

a. Noble Gas* Activity D p R(3) Q (1)

Monitor~Providing Alarm and Automatic Termination of Release (GT-RE-22, GT-RE-33)

b. Iodine Sampler w N.A. N.A. N.A.

C. Particulate .Sampler. w N.A. N.A. N.A. *

d. Flow Rate N.A. N.A. R(4) N.A. *

e. Sampler Flow Rate Monitor D N.A. R N.A. *

3. Radwaste Building Vent System

a. Noble Gas Activity D,P M,P R(3) Q(l)

Monitor-Providing Alarm and Automatic Termination of Release (GH-RE-10)

b. Iodine Sampler w N.A. N.A. N.A. *

c. Particulate Sampler w N.A. N.A. N.A. *

d. Flow Rate N.A. N.A. R(4) N.A. *

e. Sampler Flow Rate Monitor D N.A. R N.A. *

At all times.

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ATTACHMENT A (Page 49 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE 3-3 (Continued)

TABLE NOTATIONS (1) The CHANNEL . OPERATIONAL TEST (COT) and TRIP ACTUATING DEVICE TEST (TADOT) shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation, as appropriate, occur if

.any of the follo~ing conditions exists: 3/18

a. Instrument indicates measured levels above the Alarm/Trip Setpoint (isolation and alarm), or

b. Circuit failure (alarm only), or

c. Instrument indicates a downscale failure (alarm only) or

d. Instrument controls not set in operate mode (alarm only).

The quarterly requirements will be met, with the exception of the Shutdown. Purge Dampers, which are isolated during Mode 1-4 and not available for testing. The Shutdown Purge Dampers will be tested every 18. months in Mode 5, 6, defueled per Technical Specification

3. 6. 3. The basis for Technical Specification 3. 6. 3 states that the 3 6 inch containment purge . valves shall be sealed closed or closed with a blind flange installed in Mode 1, 2, 3 or* 4. The safety analysis assumes that the 36 inch shutdown purge valves are ciosed at event initiation since they may be unable to close against the buildup of pressure following a LOCA. 3/18 (2) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any one or combination of the following conditions exists:

a. Instrument indicates measured levels above the alarm setpoint

b. Circuit failure

c. Instrument indicates a downscale failure

d. Instrument controls not set in operate mode

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OFFSITE DOSE CALCULATION MANUAL TABLE 3-3 (Continued)

TABLE NOTATIONS (3) The initial CHANNEL CALIBRATION for each model detector shall be performed using one or more of the reference * (gas, liquid and/ or solid) standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These. standards shall permit calibrating the system over its intended range of energy, measurement ra,nge, and establish monitor response to solid secondary calibration source ( s) . For subsequent CHANNEL CALIBRATION, NIST traceable standard (gas, liquid and/or.

solid) may be used; or a gas, liquid or solid source that has been correlated to the detectors initial CHANNEL CALIBRATION by relating it to equipment that was previously (within 30 days) calibrated by the same geometry and type of source traceable to NIST. 3/18 With vendor concurrence, initial CHANNEL CALIBRATIONS for the same model and type detector are representative of all detectors of the same model and type. 3/18 Initial detector CHA~NEL CALIBRATIONS may be performed by a vendor in place of on-site initial CHANNEL CALIBRATION, providing all of the requirements specified in the ODCM and USAR are met. 3/18 (4) If flow rate is determined by exhaust fan status and fan performance curves, the :following. surveillance operations shall be performed at least once per 18 months:

a. The specific vent flows by direct measurement, or

b. The* differential pressure across the exhaust fan and vent flow established by the fan's "flow- P" curve, or

c. The fan motor horsepower measured and vent flow established by the fan's "flow-horsepower" curve.

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OFFSITE DOSE CALCULATION MANUAL 3.4.3 Airborne Radiation Monitor Calibration Methodology The following monitors are associated with gaseous* releases:

Monitor ID Monitor Description Monitor Type 0-GT-RE--'21A Plant Unit Vent Particulate, Iodine 0-GH-RE-lOA Radwaste Building Effluent Particulate, Iodine 0-GT"-RE-21B Plant Unit Vent Wide Range Gas 0-GH-RE-lOB Radwaste Building Effluent Wide Range Gas 0-GT-RE-22 & 33 Containment Purge Exhaust Particulate, Iodine,, Gas.

0-GT-RE-31 & 32 Containment Atmosphere Particulate, Iodine, Gas 3.4.3.1 Particulate Detector Beta particulate is monitored by a 50 mm diameter by 0.25 mm thick plastic scintillator optically coupled to a 50 mm diameter photomultiplier tube. This detector shall be calibrated over its range of energy and rate capabilities.

For energy range calibration, multiple sources shall be used (typically four). Each source consists of a filter paper disk impregnated with a beta emitting radionuclide. Typical radionuclides used include Tc-99, Cs-137, Cl-36, and Rh-106. Each source shall be positioned in the -filter paper retaining ring and counted separately.

The count rates for each radionuclide source shall be recorded and the data plotted on a graph of cpm/µCi versus average beta energy.

This curve represents the detectors response characteristics over the range of beta energies observed. The efficiency for setpoint calculations shall be based on the efficiency of tqe detector for Cs-137. 3/18 The detector shall be calibrated for its rate capabilities using a filter paper impregnated with standard activities of Cs-137.

Increasing amounts of a standard Cs-137 solution shall pe impregnated on a filter paper. The counts per minute for each cs:....137 standard shall be recorded. A determination of linearity shall be produced using the counts per minute vs. concentration data. At least three sources covering approximately ~' ~' and ~ of full scale shall be checked.

With vendor concurrence, initial CHANNEL CALIBRATIONS for the same model and type detector are representative of all detectors of the same model and type. 3/18

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OFFSITE DOSE CALCULATION MANUAL Initial detector CHANNEL CALIBRATIONS may be performed by a vendor in place of on-site initial CHANNEL CALIBRATION, providing all of the requirements specified in the ODCM and USAR are met. 3/18 3.4.3.2 Iodine Detector Iodine gas is monitored by absorbing the gas on a charcoal filter element. The charcoal filter is viewed by an NaI(Tl) integral line gamma scintillator assembly.

Because of its short half-life and the difficulty in handling gaseous iodine, barium sources shall be used for calibration. The photo peaks of interest are as follows:

Ba-133: 356 KeV gamma is 0.69 efficient/disintegration I-131: 364 KeV gamma is 0.82 efficient/disintegration Therefore, each iodine disintegration will produce 0.82/0.69 x barium disintegrations. Assuming that the detector efficiency for 356 KeV is the same as for the 364 KeV, the sensitivity for I-131 equals 1.19 x Ba-133 (counts/min) µCi. The standard sources shall be constructed by impregnating a standard Ba-133 standard into the charcoal filter element. The geometry shall simulate the iodine retention on the first surface of the charcoal. Sources shall be prepared to cover approximately~'~ and~ of full scale. The barium counts per minute for each standard shall be adjusted to iodine counts per minute. as described above. A determination of linearity shall be produced using the corrected counts per minute vs. concentration data. 3/18 With vendor concurrence, initial CHANNEL CALIBRAT:I:ONS for the same model and type detector are representative of all detectors of the same model and type. 3/18 Initial detector CHANNEL CALIBRATIONS may be performed by a vendor in place of on-site initial CHANNEL CALIBRATION, providing all of the requirements specified in the ODCM and USAR are met. 3/18 3.4.3.3 Gas Detector The gas detectors associated with monitors 0-GT-RE-22 & 33, O-GT-RE-31 &.32 and1 the low-range detectors of monitors 0-GT-RE-21B and 0-GH-RE-lOB are a plastic scintillator identical to the particulate.

detector. The mid-range and high-range detectors of monitors O-GT-RE-21B and 0-GH-RE-lOB are cadmium telluride, solid state sensors.

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OFFSITE DOSE CALCULATION MANUAL Sources for all gas detectors shall be produced by evacuating the sample chamber with a vacuum pump. The sample chamber then shall be backfilled to the desired pressure with a source of standard Xe-133.

The source is then counted and the counts per minute recorded. A determination of linearity shall* be produced *using the counts* per minute vs. concentration data. Sources shall be prepared to cover approximately~' ~and~ 0£ full scale for the detectors associated with monitors O-G*T-RE-22 and 33, 0-GT-RE-31 and 32 and the low-range detectors of monitors 0-GT-RE-21B and 0-GH-RE-lOB. At least one source shall be prepared for the mid/high range detector(s) to cover at least one point on the mid/high-range scale. For ALARA purposes, additional higher decades for the mid/high-range scaie may be extrapolated using the data from the mid-range calibration and/or determined by the corresponding response to a solid source with emissive characteristics similar to that of Xe-133. 3/18 With vendor concurrence, initial CHANNEL CALIBRATIONS for the same model

and type detector are representative of all detectors of the same model and type. 3/18 Initial detector CHANNEL CALIBRATIONS may be performed by a vendor in place of on-site initial CHANNEL CALIBRATION, providing all of the requirements specified in the ODCM and USAR are met. 3/18

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OFFSITE DOSE CALCULATION MANUAL 3.4.4 Airborne Monitor Setpoints High Alarm Trip Setpoint Calculations The alarm trip setpoint is set to the lesser of the Total Body Dose Rate Setpoint or Skin Dose Rate Setpoint calculations, if the calculated setpoint does not exceed default maximum values.

Total Body Dose Rate Setpoint Calculations The limit of the total body dose rate is 500 mrem/yr at the .SITE BOUNDARY. The monitor alarm/trip setpoint based on total body dose will be calculated as follows: 3/18 S,b ~ (SFxAF) xD 1bxR, Eq.46 Where:

Stb = the monitors alarm/trip setpoint based on the total body dose rate, in units of µCi/cc Dtb = limit of 500 mrem/yr total body, conservatively interpreted as a continuous release over a one year period SF= normally, the safety factor will be set to 0.85; this number is chosen since the gaseous monitors are set using Xe-133 energy level; Xe-133 comprises 85% of total noble gaseous activity expected (see USAR Table 11.1-1); if desired, the 0.85 can be further modified to compensate for statistical fluctuations and errors of measurement AF= allocation factor for each release so that simultaneous releases can be made without exceeding the limit; the AF may be calculated as follows:

AF= RF TF Eq.47 Where:

RF= release flow rate of the release point under consideration TF .total flow rate of all release points including release under consideration I'

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IF the monitor setpoint (Stb) units desired are µCi/sec, THEN use 'c' in place of 'Q' as shown in the* following equation for Rt (Rt, however, is no longer representing monitor response per mrem/yr) ;

this results in:

. C R = .

, ((XtQ~K, c,)

Eq.48 Rt= monitor response per mrem/yr to the total body, determined acc;:ording to:

C Rt=------~

((xio)tKi oi)

Eq.49 Where:

c the monitor response to the gaseous effluent noble gas, in

µCi/cc, .corresponding to grab sample radionuclide concentrations (x1Q) 2.2E-06 sec/m 3 at 1200 meters 3/18 Ki* the total body <;iose factor due to gamma emissions from isotope i, in mrem/yr per µCi/m 3 (Table A.1-2)

Qi= rate of release of noble gas radionuclide i, in µCi/sec; it is calculated by multiplying the concentration of radionuclide i by the waste stream release flow rate Skin Dose Rate Setpoint Calculations The limit of the skin dose rate is 3000 mrem/yr at the SITE BOUNDARY.

The monitor alarm/trip setpoint is calculated as follows: 3/18 Ss S (SFxAF)xD 5 XR 5 Eq.50 Where:

Ss = the monitors alarm/trip setpoint based on the skin dose rate in

µCi/cc Ds = the dose rate limit of 3000 mrem/yr to the skin of the body, conservatively interpreted as a continuous release over a one year period

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OFFSITE DOSE CALCULATION MANUAL IF the monitor setpoint (Ss) units.desired are µCi/sec, THEN use 'c' in place of 'Q' as shown in the following equation for Rs (Rs, however, is no longer representing monitor response per mrem/yr) ,

this results in:

R = C

' ( (xiQ~(L; +1.IM;)c;J Eq.51 Rs= monitor response per mrem/yr to the skin of the body; determined according to:

R = C s ((,uQ)~(Li +l.IMJQi)

Eq.52 Where:

Li= the skin dose factor due to beta emissions from isotope i, in 3 .

mrem/yr per µCi/m (Table A.1-2) 1.1 = the unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose 3/18 Mi =

the air dose factor due to gamma emissions from isotope i, in 3

mrad/yr per µCi/m (Table A.1-2)

The factors SF, AF, c, (x IQ) and Qi are as defined under the Total Body Dose Rate Setpoint Calculations.

The actual monitor setpoint is the lower of the two values calculated (Total Body vs. Skin). 3/18 A pre-release isotopic analysis is performed for batch releases from Waste Gas Decay Tanks and Containment Building purges to determine the identity and quantity of the principal radionuclides. The appropriate alarm/trip setpoint(s) are adjusted accordingly to ensure that the limits of 3.1 are not exceeded.

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OFFSITE DOSE CALCULATION MANUAL Alert Alarm Setpoint Calculations The Noble Gas Alert Alarm for the Plant Unit Vent (0-GT-RE-21) and Radwaste Building Exhaust Monitor (0-GH-RE-10), is set to alert operators to that average concentration which if maintained for a full year would result in the 10 CFR 50, Appendix I Annual Dose Guidelines being reached. Section 3. 2. 1 limits the annual dose due to noble gases to~ 10 mrads for gamma radiation and~ 20 mrads for beta radiation. Section 3.2.2 limits the annual dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents to~ 15 mrem to any organ. These two sections contain the

.annual dose limits due to gaseous releases found in 10 CFR 50, Appendix I.

Noble Gas Alert Alarm Setpoint Calculation The alert alarm setpoint is the lesser of:

Sy < (SF x AF) X Dy X Ry Eq.53 Sp < (SF x AF) x Op X Rp Eq.54 Where:

The factors SF and AF are as previously defined. 3/18

Sy = monitor setpoint based on gamma radiation Dy= limit of 10 mrad/yr, conservatively interpreted as a continuous release over a one year period Ry = monitor response per mrad/yr; determined according to the following equation: (see Total Body or Skin Dose Rate Setpoint Calculations for calculation of the setpoint in µCi/sec; Equation 48 or 51)

C Ry = - - - - - - ~ -

((x!Q) tMi xQi)

Eq.55 Where:

The factors c, (X/Q) and Qi are as previously defined. 3/18

_/

Mi = the air dose factor due to gamma emissions for each 3

identified noble gas radionuclide, in mrad/yr per µCi/m (Table A.1-2) 3/18

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OFFSITE DOSE CALCULATION MANUAL S~ = monitor setpoint based on beta radiation D~ = limit of 20 mrad/yr, conservatively interpreted as a continuous release over a one year period*

Rp = monitor response per mrad/yr; determined according to the following equation: (see Total Body or Skin Dose Rate Setpoint Calculations for calculation of the setpoint in µCi/sec; Equation 48 or 51)

. C Rp =-------

((xtQ}tNi xQi)

Eq.56 Where:

The factors c, (X/Q) and Qi are as previously defined. 3/18 Ni the air dose factor due to beta emissions for each

3 identified noble gas radionuclide, i, in mrad/yr per µCi/m (Table A.1-2) 3/18 A semi-fixed alert alarm setpoint for the Plant Unit Vent Monitor (O-GT-RE-21) and Radwaste Building Vent Monitor (O-GH-RE-10) is calculated using the following equation:

Setpoint (µCi / cc) = (~d / yr)(.85)(AF) ]

[ ( (X!Q) ~pi xMi xQ)

Eq.57 Where:

AF= either Unit Vent flow or Radwaste Building Vent flow divided by the combined flow of the Unit Vent and Radwaste Building Vent Pi= fractional value of isotope expected, Ci/CT Ci concentration in µCi/cc of isotope CT total gaseous activity from USAR Table 11.1-1 Q = vent flow rate in cc/sec The factors (X/Q) and Mi are as previously defined. 3/18

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OFFSITE DOSE CALCULATION MANUAL Isotopes used and Pi values *are as follows:

ISOTOPE pi Kr-85M .018 Kr-87 .010 Kr-88 .033 Xe-133M .017 Xe-133 .851 Xe-135- .051 Should this semi-fixed alert alarm cause a continuous alarm condition, then actual setpoints will be calculated.

Particulate And Iodine Alarm Setpoints Setpoints for the gaseous effluent particulate

and iodine channels are set using Cs-137 MPC for particulat~s and I-131 MPC for iodines.

The following is the calculation used:

Setpoint (µCi/ cc) = (TvIPCJ~(SF)

. (Q)(x; Q)

Eq.58 Where:

5 x 10- 10 µCi/cc for Cs-137 1 x 10- 10 µCi/ cc for I-131 AF= as defined previously SF= 0.0625 for I-131 1 0.9375 for Cs-1371 Q = vent flow in m3 /sec This will provide the hi alarm setpoint. The alert alarm setpoint is 10% of the hi alarm setpoint.

1 Derived from ratio of isotope activity (either I-131 or Cs-137) to sumo~ activity of Cs-137 and I-131 found in USAR Table 11.1-1 for reactor coolant.

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OFFSITE DOSE CALCULATION MANUAL 4.0 Total Dose 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 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

4.1 Remedial Action With the calculated aoses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Section 2.2a, 2.2b, 3.2.la, 3.2.lb, 3.2.2a and 3.2.2b calculation should be" made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Section 4. 0 above have been exceeded. If such is the case, prepare and submit to_ the Commiss.ion within 30 days, a special report that defines the corrective action to be taken to reduce subsequent re-leases

to prevent recurrence of exceeding the above limits. This special ~eport, as defined in 10 CFR 20.4~5e and 10CFR20.2203, shall include an analysis that 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 cif radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 4 0 CFR Part 190 has not already been corrected, the special report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is cons_idered a timely request, and a variance is granted until staff action on the reqµest is

complete.

4.2 Surveillance Requirements 4.2.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with the* methodology of Sections 2.2 and 3.2 at least once per 31 days when the release of radioactiye materials in liquid or gaseous effluents exceed twice the limits of*

Section 2.2a, 2.2b, 3.2.la, 3.2.lb, 3.2.2a and 3.2.2b. Otherwise, no further evaluation is required.

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4. 2. 2 Cumulative dose contribution from

direct radiation from the reactor unit and from Radwaste storage tanks shall be

determined utilizing .the results of routine plane perimeter surveys, DLR data or a combination of both, when necessary. This requirement is applicable only under conditions set f o_rth in the remedial action above. 3/18

5. 0 *Radiological Environmental Monitoring Program (Contained in AP 07B-004) 6.0 Bases The bases contained on the succeeding pages summarizes th~ general requirements of Section 2.0, 3.0, 4.0 and 5.0 of the ODCM.

' ~

S.ection 2. 0 Liquid Effluents Section 2.1 Concentration This section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNR~STRICTED AREAS will be less than 10 times the \ concentrat{on

,levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

This limitation provides addit~onal assJrance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section II. A design objective of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and .(2) the.

limits of 10 CFR Part 20.1301(e) to the population. The concentration limit for dis~olved or entrained noble gases are based upon the assump.tion that Xe-135 is the controlling radioisotope and its effluent* concentration in air ( submersion) was

converted 'to an equivalent concentration in water using the methods described in International Commission on Radiological Protection ( ICRP)

Publication 2. This specification does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301.

The required detection capabilities- for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of det~ction (LLDs). Detailed discussion of the LLD, and other detection limits can be, found in HASL Procedures Manual, , HASL-300

( revised annually) , Currie, L.A. , "Limits for Qual*i tati ve Detection and Quantitative Determination Application to Radiochemistry,"

Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques, "Atlantic Richfield Hanford Company Report ARH-SA-.215 (June 1975).

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OFFSITE DOSE CALCULATION MANUAL Section 2.2 Dose This section is provided to implement

the requirements of Section II .A, III .A and IV .A of Appendix I, 10 CFR Part 50. The reme.dial.

action implements the guides set forth in Section II.A of Appendix I and provides 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 to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, £or fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that th~ operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix. I which specify 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 u~likely 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.

Section 2.3 Liquid Radwaste Treatment System The FUNCTIONALITY of the Liquid Radwaste Treatment Systems ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. 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 section implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objective set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

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OFFSITE DOSE CALCULATION MANUAL Section 2.4 Radioactive Liquid Effluent Monitoring Instrumentation The radioactive liquid effluent instrvmentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits

of 10 CFR Part 20. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

Section 3.0 Gaseous Effluents Section 3.1 Dose Rate This section provide.s reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA either at or beyond the SITE BOUNDARY in excess of the design objectives of Wolf Creek Technical Specification 5.5.4.g. This specification is provided to ensure that gaseous effluents from all uni ts on the site will be appropriately controlled. It provides operational .flexibility for the release of gaseous effluents to satisfy Wolf Creek Technical Specification 5.5.4.g. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE 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 mrems/year to the whole body or to less than or equal to 3000 mrems/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 mrems/year. This specification does not affect the requirement to comply with the annual limitations of 10 CFR 20. 1301.

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OFFSITE DOSE CALCULATION MANUAL The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination Application to Radiochemistry,"

Anal. Chem 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Section 3.2.1 Dose - Noble Gases This section is provided to implement the requirements of Section II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The remedial action implements the guides set forth in Section II.B of Appendix I and provides the required oparat£ng 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 to UNRESTRICTED AREAS 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 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 materials in gaseous 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 1.111, "Methods for Estimating Atmospheric Transport ~nd 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.

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OFFSITE DOSE CALCULATION MANUAL Section 3. 2. 2 Dose Iodine-131 and 133, Tritium and Radioactive Material in Particulate Form This section is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The remedial actions are the guides set forth in Section II. C of Appendix I, and 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 materials in gaseous effluents to UNRESTRICTED AREAS 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

~f 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 consist.ent with the methodology provided in Regulatory Guide 1. 10 9,'

"Calculational 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 provide for determining the actual doses* based upon historical average conditions. The release rate limits for Iodine~131 and 133, tritium, and radionuclides in particulate form with half lives greater that 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOON.DARY. 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, (4) deposition on the ground with subsequent exposure of man.

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OFFSITE DOSE CALCULATION MANUAL Section 3.3 Gaseous Radwaste Treatment System The. FUNCTIONALITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable." This section implements the requirements of 10 CFR 50. 36a, General Design Criterion 60 of App_endix 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 dose design objectives set forth in Section II.Band II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

Section 3.4 Radioactive Gaseous Effluent Monitoring Instrumentation rhe radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip Setpoints for these instruments shall be adjusted to values calculated in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of Wolf Creek Technical Specification 5. 5. 4. g. The FUNCTIONALITY and use of this instrumentation is cons{~tent *with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitor used to show compliance with the gaseous effluent release requirements of Section 3.2 shall be such that concentrations as low as 1 x 10-6 µCi/cc are measurable.

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OFFSITE *oosE CALCULATION MANUAL Section 4.0 Total Dose This section is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525.

The section requires the preparation and submittal of .a special report whenever the calculated doses due to releases of radioactivity and the radiation from uran~um fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 7 5 mrems. For sites containing up to four 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 Uni ts and from 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 196 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 t6 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 190.11 and 10 CFR 20.2203, is consid~red to be a timely request and fulfills the require~ent~ of 4 0 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. 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.

7.0 Reports 7.1 Annual Radiological Environmental Operating Report (contained in AP 07B-004)

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OFFSITE DOSE CALCULATION MANUAL 7.2 Annual Radioactive Effluent Release Report The Annual Radioactive Effluent Release Report (ARERR) shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the Unit* as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Re~orting 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, with data summarized on a quarterly basis following the format of Appendix B thereof. The ARERR is to be submitted before May 1 of each year.

For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid waste (as defined by 10 CFR Part 61), type of container (e.g., LSA, Type A, Type B, Large Quantity), and SOLIDIFICATION agent or absorbent (e.g.,

cement, urea formaldehyde)

The ARERR shall also 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 on magnetic tape of wind speed, wind direction, and atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. 2 This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Statioti during the previous calendar year. This same report shall also 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. All assumptions used in making these assessments, i.e.,

specific activity, exposure time and location, shall be included in these reports. Historical average meteorological conditions or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, sh~ll be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM.

2 In lieu of submission with the ARERR, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

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OFFSITE DOSE CALCULATION MANUAL The ARERR shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

The ARERR shall include a list and description, including total Curies, of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The ARERR shall include any changes made during the reporting period to the ODCM, pursuant to ~echnical Sp~cification 5.5.1.

The ARERR shall include major changes to the Radwaste Treatment Systems. for the period in which the evaluation was reviewed and accepted by the PSRC. The discussion of each change shall contain:

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

2. Sufficient detailed information to totally support the reason for the change without benefit of additional and supplemental information;

3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.

4. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

5. An evaluation of the change, which shows the expected . maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto;

6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

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7. An estimate of the exposure to plant operating personnel as a result of the change; and

8. Documentation of the fact that the change was reviewed and found acceptable by the PSRC.

The ARERR shall include a listing of new locations for dose calculations identified by the Land Use Census.

I The ARERR shall include a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of TR 3.10.1 OR TSR 3.10.3.1.

The ARERR.shall include an explanation as to why the nonfunctionality of a liquid or gaseous effluent moni taring instrumentation was not corrected within the time specified.

The ARERR shall include a description of the events leading to a missed sample required by Table 2-1 or 3-1.

The ARERR shall include NEI Groundwater Protection Initiative requirements (Ref. 3.1.6)

1. A report of onsite groundwater sample results.

2. A description of dose calculations for releases from site.

3. A summary of onsi te spills & leaks that require notification to county, state & NRC.

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use age 79 of 160 ATTACHMENT A (Page 71 of 152)

OFFSITE DOSE CALCULATION MANUAL APPENDIX A Dose Conversion Factor Tables

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULA,TION MANUAL Information Use Page 80 c:if 160 ATTACHMENT A (Page 72 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.1-1*

BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIED DATA (pCi/kg per pCi/liter)

ELEMENT FRESHWATER FISH H 9.0E-01 C 4.6E 03 Na 1. OE 02 p 1. OE 05 Cr 2.0E 02 Mn 4.0E 02 Fe l.OE 02 Co 5.0E 01 Ni 1. OE 02 Cu 5.0E 01 Zn 2.0E 03 Br 4.2E 02 Rb 2.0E 03 Sr 3.0E 01 y 2.SE 01 Zr 3.3E 00 Nb 3.0E 04 Mo 1. OE 01 Tc 1. SE 01 Ru 1. OE 01 Rh* 1. OE 01*

Te 4.0E 02 I 1. SE 01 Cs 2.0E 03 Ba 4.0E 00 La 2.SE 01 Ce 1. OE 00 Pr 2.SE 01 Nd 2.SE 01 w 1. 2E 03 Np 1. OE 01

- Ag 2.3E 00

- Sb 1. OE 00

Taken from Regulatory Guide 1.109 (Rev.1)

- Taken from Regulatory Guide 1.109 (Rev. 0)

Revision:

9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use ~age 81 of 160 ATTACHMENT A (Page 73 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.1-2 DOSE FACTORS FOR NOBLE GASES AND. DAUGHTERS*

Radionuclide Total Body Skin Dose Factor Gamma Air Beta Air Dose Factor Li Dose Factor Dose Factor Ki (mrem/yr per Mi Ni (mrem/yr per µCi/m 3 ) (mrad/yr per (mrad/yr

µCi/m 3 ) µCi/m 3 ) per µCi/m 3 )

Kr-83M 7.56E-02** 1.93E+Ol 2.88E+02 Kr-85M l.17E+03 1.46E+03 1.23E+03 l.97E+03 Kr-85 1.61E+Ol 1.34E+03 1.72E+Ol l.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 l.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1. 66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1. 56E+04 7.29E+03 1;63E+04 7.83E+03 Xe-131M 9.15E+Ol 4.76E+02 1. 56E+02 1. 11E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 l.05E+03 Xe-133M 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-135M 3.12E+03 *7. 11E+02 3.36E+03 7.39E+02 Xe-135 l.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 l.42E+03 1.22E+04 1.51E+03 l.27E+04

,Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

Based on Regulatory Guide 1.109 (Rev.1)

- 7.56E-02 = 7.56 x 10 -z

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use ~age 82 of 160 ATTACHMENT A (Page 74 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.2-1*

INHALATION DOSE FACTORS FOR ADULTS (MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA l.58E-07 l.58E-07 1. 58E-07 1.58E-07 1. 58E-07 1. 58E-07 C 14 2.27E-06 4.26E-07 4. 26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 NA 24 1. 28E-06 l _-28E-06 1. 28E-06 1. 28E-06 l.28E-06 l.28E-06 1. 28E-06 p 32 1. 65E....:04 9.64E-06 6.26E-06 NO DATA NO DATA NO DATA 1. 08E-05 CR 51 NO DATA NO DATA 1. 25E-08 7.44E-09 2.85E-09 1. 80E-06 4.15E-07 MN 54 NO DATA 4.95E-06 7.87E-07 NO DATA l.23E-06 1. 75E-04 9.67E-06 MN 56 NO DATA 1. 55E-10 2. 29E-:-ll NO DATA 1. 63E-10 l. lBE-06 2.53E-06 FE 55 3.07E-06 2.12E-06 4.93E-07 NO DATA NO DATA 9.0lE-06 7.54E-07 FE 59 l.47E-06 3.47E-06 1. 32E-06 NO DATA NO DATA 1. 27E-04 2.35E-05 co 58 NO DATA l.98E-07 2.59E-07 NO DATA NO DATA l. l6E-04 l.33E-05 co 60 NO DATA 1. 44E-06 1. 85E-06 NO DATA NO DATA 7.46E-04 3.56E-05 NI 63 5.40E-05

3. 93E-06 1. BlE-06 NO DATA NO DATA 2.23E-05 l.67E-06 NI 65 1. 92E-10 2.62E-il l.14E-ll NO DATA NO DATA 7.00E-07 l.54E-06 cu 64 NO DATA l.83E-10 7. 69E-ll NO DATA 5.78E-10 8.48E-07 6.12E-06 ZN 65 4.05E-06 l.29E-05 5.82E-06 NO DATA 8.62E-06 1 :08E-04 6.68E-06 ZN 69 4.23E-12 8.14E-12 5. 65E-13 NO DATA 5.27E-12 l.15E-07 2.04E-09 BR 83 NO DATA NO DATA 3.0lE-08 NO DATA NO DATA NO DATA 2.90E-08 BR 84 NO DATA NO DATA 3.91E-08 NO DATA NO DATA NO DATA 2.05E-13 BR 85 NO DATA NO DATA l.60E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1. 69E-05 7.37E-06 NO DATA NO DATA NO DATA 2.08E-06 RB 88 NO DATA 4.84E-08 2.41E-08 NO DATA NO DATA NO DATA 4.18E-19 RB 89 NO DATA 3.20E-08 2.12E-08 NO DATA NO DATA NO DATA l.16E-21 SR 89 3.80E-05* NO DATA 1. 09E-06 NO DATA NO DATA l.75E-04 4.37E-05 SR 90 l.24E-02 NO DATA 7.62E-04 NO DATA NO DATA 1. 20E-03 9.02E-05 SR 91 7.74E-09 NO DATA 3 .13E-10 NO DATA NO DATA 4.56E-06 2.39E-05 SR 92 8.43E-10 NO DATA 3. 64E-cll NO DATA NO DATA 2.06E-06 5.38E-06 y 90 2.61E-07 NO DATA 7.0lE-09 NO DATA NO DATA 2.12E-05 6.32E-05 y 91M 3. 26E-ll NO DATA l.27E-12 NO DATA NO DATA 2.40E-07 l.66E-10 y 91 5.78E-05 NO DATA l.55E-06 NO DATA NO DATA 2.13E-04 4.81E-05 y 92 1. 29E-09 NO DATA 3. 77E-ll NO DATA NO DATA l.96E-06 9.19E-06 y 93 l.18E-08 NO DATA 3.26E-10 NO DATA NO DATA 6.06E-06 5.27E-05 ZR 95 l.34E-05 4.30E-06 2.91E-06 NO DATA 6.77E-06 2.21E-04 l.88E-05 ZR 97 1. 21E-08 2.45E-09 l.13E-09 NO DATA 3.71E-09 9.84E-06 6.54E-05 NB 95 1. 7 6E,-06 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 MO 99 NO DATA 1. 51E-08 2.87E-09 NO DATA 3.64E-08 l.14E-05 3.lOE-05 TC 99M 1. 29E-13 3. 64E-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.. 20E-07 ./

Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 9 AP 07B-003" OFFSITE DOSE CALCULATION MANUAL Information Use age 83 of 160 ATTACHMENT A (Page 75 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.2-l*(cont'd)

INHALATION DOSE FACTORS FOR ADULTS (MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 5.22E-15 7.52E-15 7.38E-14 NO DATA 1.35E-13 4.99E-08 1. 36E-21 RU 103 1.91E-07 NO DATA 8.23E-08 NO DATA 7.29E-07 6.31E-05 1.38E-05 RU 105 9.88E-ll NO DATA 3. 89E-11 NO DATA 1.27E-10 1.37E-06 6.02E-06 RU 106 8.64E-06 NO DATA 1. 09E-06 NO DATA 1.67E-05 l.17E-03 1.14E-04 AG 110M 1.35E-06 1.25E-06 7.43E-07 NO DATA 2.46E-06 5.79E-04 3.78E-05 TE 125M 4.27E-07 l.98E-07 5.84E-08 1. 31E-07 1.55E-06 3.92E-05 8.83E-06 TE 127M 1.58E-06 7.21E-07 1. 96E-07 4. llE-07 5.72E-06 l.20E-04 1. 87E-05 TE 127 1.75E-10 8.03E-11 3.87E-11 1. 32E-10 6.37E-10 8.14E-07 7.17E-06 TE 129M l.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE 129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1. 96E-08 TE 131M 8,74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 l.82E-05 6.95E-05 TE 131 l.39E-12 7.44E-13 4.49E-13 l.17E-12 5.46E-12 l.74E-07 2.30E-09 TE 132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I 130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 NO DATA 9.61E-07 I 131 3.15E-06 4.47E-06 2.56E-06 1. 4 9E-03 7.66E-06 NO DATA 7.85E-07 I 132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6. 48E-07 NO DATA 5.08E-08 I 133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA l. llE-06 I 134 8.05E-b8 2.16E-07 7.69E-08 3.73E-06 3. 44E-07 NO DATA 1. 2 6E-10 I 135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 NO DATA 6.56E-07 cs 134 4.66E-05 1.06E-04 9.lOE-05 NO DATA 3.59E-05 1.22E-05 1.30E-06 cs 136 4.88E-06 l.83E-05 1.38E-05 NO DATA l.07E-05 1.50E-06 1.46E-06 cs 137 5.98E~05 7.76E-05 5.35E-05 NO DATA 2.78E-05 9.40E-06 1. 05E-06 cs 138 4.14E-08 7.76E-08 4.05E-08 NO DATA 6.00E-08 6.07E-09 2. 33E-13 BA 139 l.17E-10 8.32E-14 3.42E-12 NO DATA 7.78E-14 4.70E-07 1.12E-07 BA 140 4.88E-06 6.13E-09 3.21E-07 NO DATA 2.09E-09 1.59E-04 2.73E-05 BA 141 l.25E-11 9.41E-15 4.20E-13 NO DATA 8.75E-15 2.42E-07 1.45E-17 BA 142 3.29E-12 3.38E-15 2.07E-13 NO DATA 2.86E-15 l.49E-07 1. 96E-26 LA 140 4.30E-08 2.17E-08 5.73E-09 NO DATA NO DATA 1. 70E-05 5.73E-05 LA 142 8.54E-ll 3.88E-11 9.65E-12 NO DATA NO DATA 7.91E-07 2.64E-07 CE 141 2.49E-06 1.69E-06 l.91E-07 NO DATA 7.83E-07 4.52E-05 l.50E-05 CE 143 2.33E-08 1.72E-08 1. 91E-09 NO DATA 7.60E-09 9.97E-06 2.83E-05 CE 144 4.29E-04 1.79E-04 2.30E-05 NO DATA l.06E-04 9.72E-04 1.02E-04 PR 143 l.17E-06 4.69E-07 5.80E-08 NO DATA 2.70E-07 3.51E-05 2.50E-05 PR 144 3.76E-12 1.56E-12 1. 91E-13 NO DATA 8.81E-13 l.27E-07 2.69E-18 ND 147 6.59E-07 7.62E-07 4.56E-08 NO DATA 4.45E-07 2.76E-05 2.16E-05 w 187 1.06E~09 8.85E-10 3.lOE-10 NO DATA NO DATA 3.63E-06 l.94E-05 NP 239 2.87E-08 2.82E-09 1. 55E-09 NO DATA 8.75E-09 4.70E-06 l.49E-05

Revision: 9 AP 07B~003 OFFSITE DOSE CALCULATION MANUAL Information Use *Page 84 of 160 ATTACHMENT A (Page 76 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 2-2*

INHALATION DOSE FACTORS FOR TEENAGER (MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA l.59E-07 1. 59E-07 1.59E-07 1. 59E-07 1.59E-07 1. 59E-07 C 14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 NA 24 1. 72E-06 1. 72E-06 1. 72E-06 1. 72E-06 1. 72E-06 1. 72E-06 1. 72E-06 p 32 2.36E-04 1.37E-05 8.95E-06 NO DATA NO DATA NO DATA 1.16E-05 CR 51 NO DATA NO DATA 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN 54 .NO DATA 6.39E-06 1.05E-06 NO DATA 1. 59E-06 2.48E-04 8.35E-06 MN 56 NO DATA 2.12E-10 3 .15E-11 NO DATA 2.24E-10 1.90E-06 7.18E-06 FE 55 4.18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 7.99E-07 FE 59 1. 99E-06 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E-04 2.23E-05 co 58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA l.68E-04 1.19E-05 co 60 NO DATA 1. 89E-06 2.48E-06 NO DATA NO DATA 1. 09E-03 3.24E-05 NI 63 7.25E-05 5.43E-06 2.47E-06 NO DATA NO DATA 3. 84E-05 . 1. 77E-06 NI 65 2.73E-10 3. 66E-ll 1. 59E-11 NO DATA NO DATA 1.17E-06

4.59E-06 cu 64 NO DATA 2.54E-10 1. 06E-10 NO DATA 8.0lE-10 1. 39E-06 7.68E-06 ZN 65 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.08E-05 1. 55E-04 5.83E-06 ZN 69 6.04E-12 1.15E-11 8.07E-13 NO DATA 7.53E-12 1.98E-07 3.56E-08 BR 83 NO DATA NO DATA 4.30E'-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 5. 41E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 2.29E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.38E-05 1. 05E-05 NO DATA NO DATA NO DATA 2.21E-06 RB 88 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 RB 89 NO DATA 4.40E-08 2.91E-08 NO DATA NO DATA NO DATA 4.22E-17 SR 89 5.43E-05 NO DATA 1. 56E-06 NO DATA NO DATA 3.02E-04 4.64E-05 SR 90 l.35E-02 NO DATA 8.35E-04 NO DATA NO DATA 2.06E-03 9.56E-05 SR 91 1. lOE-08 NO DATA 4.39E-10 NO DATA NO DATA 7.59E-06 3.24E-05 SR 92 1.19E-09 NO PATA 5. 08E-11 NO DATA NO DATA 3.43E-06 1. 4 9E-05 y 90 3.73E-07 NO DATA 1. OOE-08 NO DATA NO DATA 3.66E-05 6.99E-05 y 91M 4.63E-11 NO DATA 1. 77E-12 NO DATA NO DATA 4.00E-07 3.77E-09 y 91 8.26E-05 NO DATA 2.21E-06 NO DATA NO DATA 3.67E-04 5. llE-05 y 92 1. 84E-09 NO DATA 5. 36E-11 NO DATA NO DATA 3.35E-06 2.06E-05 y 93 1. 69E-08 NO DATA 4.65E-10 NO DATA NO DATA l.04E-05 7.24E-05 ZR 95 1. 82E-05 5.73E-06 3.94E-06 NO DAT.A 8.42E-06 3.36E-04 1.86E-05 ZR 97 1. 72E-08 3.40E-09 1. 57E-09 NO DATA 5.15E-09 1.62E-05 7.88E-05 NB 95 2.32E-06 1. 29E-06 7.08E-07 NO DATA 1.25E-06 9.39E-05 l.21E-05 MO 99 NO DATA 2. llE-08 4.03E-09 NO DATA 5.14E-08 1.92E-05 3.36E-05 TC 99M 1. 73E-13 4.83E-13 6.24E-12 NO DATA 7.20E-12 1.44E-07 7.66E-07

Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 9 AP 07B-"003 OFFSITE DOSE CALCULATION MANUAL' Information Use Page 85 of 160 ATTACHMENT A (Page 77 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 2-2* (cont'd)

INHALATION DOSE FACTORS FOR TEENAGER (MREM PER PCI INHALED}

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI.:.LLI TC 101 7.40E-15 1. 05E-14 1. 03E-13 NO DATA 1. 90E-13 8.34E-08 l.09E-16 RU 103 2.63E-07 NO DATA 1.12E-07 NO DATA 9.29E-07 9.79E-05 1.36E-05 RU 105 1. 40E-10 NO DATA 5. 42E-ll NO DATA 1.76E-10 2.27E-06 1.13E-05 RU 106 1. 23E-05 NO DATA 1.55E-06 NO DATA 2.38E-05 2.0lE-03 1. 20E-04 AG 110M 1. 73E-06 1. 64E-06 9.99E-07 NO DATA 3.13E-06 8.44E-04 3.41E-05 TE 125M 6.lOE-07 2.80E-07 8.34E-08 1. 7 5E-07 NO DATA 6 ..70E-05 9.38E-06 TE 127M 2.25E-06 1. 02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1. 99E-05 TE 127 2. 51E-10 1.14E-10 5. 52E-ll 1. 77E-10 9.lOE-10 1.40E-06 1.0lE-05 TE 129M 1. 74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06. 2.47E-04 5.06E-05 TE 129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3. 32E-ll 4.12E-07 2.02E-07 TE 131M 1. 23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE 131 1. 97E-12 1. 04E-12 6.30E-13 1.55E-12 7.. 72E-12 2.92E-07 1. 89E-09 TE 132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I 130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 NO DATA 1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1. 83E-03 1. 05E-05 NO DATA 8. llE-07 I 132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 NO DATA 1. 59E-07 I 133 1. 52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA l.29E-06 I 134 1. llE-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09 I 135 4.62E-07 1.18E-06 4.36E-07 7. 76E-05 1. 86E-06 NO DATA 8.69E-07 cs 134 6.28E-05 1. 41E-04 6.86E-05 NO DATA 4.69E-05 1.83E-05 1. 22E-06 cs 136 6.44E-06 2.42E-05 1. 71E-05 NO DATA 1. 38E-05 2.22E-06 1. 36E-06 cs 137 8.38E-05 1. 06E-04 3.89E-05 NO DATA 3.80E-05 1. 51E-05 1. 06E:..06 cs 138 5.82E-08 1. 07E-07 5.58E-08 NO DATA 8.28E-08 9.84E-09 3. 38E-ll BA 139 1. 67E-10 1.18E-13 4.87E-12 NO DATA 1. llE-13 8.08E-07 8.06E-07 BA 140 6.84E-06 8.38E-09 4.40E-07 NO DATA 2.85E-09 2.54E-04 2. 86E-05 BA* 141 1.78E-ll 1. 32E-14 5.93E-13 NO DATA 1. 23E-14 4. llE-07 9.33E-14

BA 142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3.92E-15 2.39E-07 5.99E-20 LA 140 5.99E-08 2.95E-08 7.82E-09 NO DATA NO DATA 2.68E-05 6.09E-05 LA 142 1. 20E-10 5.31E-ll 1. 32E-ll NO DATA NO DATA 1.27E-06 1. 50E-06 CE 141 3.55E-06 2.37E-06 2. 71E-07 NO DATA 1.llE-06 7.67E-05 1. 58E-05 CE 143 3.32E-08 2.42E-08 2.70E-09 NO DATA 1. 08E-08 1.63E-05 3.19E-05 CE 144 6. llE-04 2.53E-04 3.28E-05 NO DATA 1. 51E-04 1. 67E-03 1.08E-04 PR 143 1. 67E-06 6.64E-07 8.28E-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 PR 144 5.37E-12 2.20E-12 2.72E-13 NO DATA 1. 26E-12 2.19E-07 2.94E-14 ND 147 9.83E-07 1.07E-06 6.41E-08 NO DATA 6.28E-07 4.65E-05 2.28E-05 w 187 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.21E-05 NP 239 4.23E-08 3.99E-09 2.21E-09 NO DATA 1. 25E-08 8. llE-06 1.65E-05

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use ~age 86 of 160 ATTACHMENT A (Page 78 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.2-3*

INHALATION DOSE FACTORS FOR CHILD.

(MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C 14 9.70E-06 1. 82E-06 1. 82E-06 1. 82E-06 1. 82E-06 1. 82E-06 1.82E-06 NA 24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 p 32 7.04E-04 3.09E-05 2.67E-05 NO DATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA NO DATA 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 MN 54 NO DATA 1.16E-05 2.57E-06 NO DATA 2.71E-06 4.26E-04 6.19E-06 MN 56 NO DATA 4.48E-10 8.43E-11 NO DATA 4.52E-10 3.55E-06 3.33E-05 FE 55 1. 28E-05 6.80E-06 2.lOE-06 NO DATA NO DATA 3.00E-05 7.75E-07 FE. 59 5.59E-06 9.04E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 co 58 NO DATA 4.79E-07 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 co 60 NO DATA 3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-03 2.60E-05 NI 63 2.22E-04 1.25E-05 7.56E-06 NO DATA NO DATA 7.43E-05 1. 71E-06 NI 65 8.08E-10 7.99E-11 4.44E-11 NO DATA NO DATA 2.21E-06 2.27E-05 cu 64 NO DATA 5.39E-10 2.90E-10 NO DATA 1. 63E-09 2.59E-06 9.92E-06 ZN 65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06 ZN 69 1. 81E-11 2.61E-11 2.41E-12 NO DATA 1. 58E-11 3.84E-07 2.75E-06 BR 83 NO DATA NO DATA l.28E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO.DATA 1.48E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 6.84E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 5.36E-05 3.09E-05 NO DATA NO DATA NO DATA 2.16E-06 RB 88 NO DATA 1.52E-07 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09 RB 89 NO DATA 9.33E-08 7.83E-08 NO DATA NO DATA NO DATA 5.llE-10 SR 89 l.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.83E-04 4.52E-05 SR 90 2.73E-02 NO DATA l.74E-03 NO DATA NO DATA 3.99E-03 9.28E-05 SR 91 3.28E-08 NO DATA 1. 24E-09 NO DATA NO DATA 1. 44E-05 4.70E-05 SR 92 3.54E-09 NO DATA 1. 42E-10 NO DATA NO DATA 6.49E-06 6.55E-05 y 90 1. llE-06 NO DATA 2.99E-08 NO DATA NO DATA. 7.07E-05 7.24E-05 y 91M 1.37E-10 NO DATA 4. 98E-.12 NO DATA NO DATA 7.60E-07 4.64E-07 y 91 2.47E-04 NO DATA *6.59E-06 NO DATA NO DATA 7.lOE-04 4.97E-05 y 92 5.50E-09 NO DATA 1. 57E-10 NO DATA NO DATA 6.46E-06 6.46E-05 y 93 5.04E-08 NO DATA 1. 38E-09 NO DATA NO DATA 2.0lE-05 1. 05E-04 ZR 95 5.13E-05 1.13E-05 1.00E-05 NO DATA 1.61E-05 6.03E-04 1.65E-05 ZR 97 5.07E-08 7.34E-09 4.32E-09 NO DATA 1.05E-08 3.06E-05 9.49E-05 NB 95 6.35E-06 2.48E-06 1. 77E-06 NO DATA 2.33E-06 1.66E-04 1. OOE-05 MO 99 NO DATA 4.66E-08 1.15E-08 NO DATA 1. 06E-07 3.66E-05 3.42E-05 TC 99M 4.81E-13 9. 41E-13 1.56E-11 NO DATA 1. 37E-11 2.57E-07 1. 30E-06

Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 87 of 160 ATTACHMENT A (Page 79 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 2-3* (cont'd)

INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 2.19E-14 2.30E-14 2.91E-13 NO DATA 3.92E-13 1. 58E-07 4.41E-09 RU 103 7.55E-07 NO DATA 2.90E-07 NO DATA 1. 90E-06 1. 7 9E-04 1. 21E-05 RU 105 4.13E-10 NO DATA 1. 50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 RU 106 3.68E-05 NO DATA 4.57E-06 NO DATA 4.97E-05 3.87E-03 1.16E-04 AG 110M 4.56E-06 3.08E-06 2.47E-06 NO DATA 5.74E-06 1.48E-03 2.71E-05 TE 125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 NO DATA 1.29E-04 9.13E-06 TE 127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1. 72E-05 4.00E-04 l.93E-05 TE 127 7.49E-10 2.57E-10 1. 65E-10 5.30E-10 1. 91E-09 2. 71E-06 1. 52K-05 TE 129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1. 36E-05 4.76E-04 4.91E-05 TE 129 2. 64E-11 9.45E-12 6.44E-12 1. 93E-11 6.94E-11 7.93E-07 6.89E-06 TE 131M 3.63E-08 1.60E-08 1. 37E-08 2.64E-08 1. 08E-07 5.56E-05 8.32E-05 TE 131 5.87E-12 2.28E-12 1. 78E-12 4.59E-12 1. 59E-ll 5.55E-07 3.6QE-07 TE 132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 l.02E-04 3.72E-05 I 130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 NO DATA 1. 38E-06 I 131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 NO DATA 7.68E-07 I 132 5.72E-07 1.lOE-06 5.07E-07 5. 23E...:05 1. 69E-06 NO DATA 8.65E-07 I 133 4.48E-06 5.49E-06 2.08E-06 1. 04E-03 9.13E-06 NO DATA 1.48E-06 I 134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07 I 135 1. 33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 NO DATA 1. 20E-06 cs 134 1. 7 6E-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 cs 136 1. 7 6E-05 4.62E-05 3.14E-05 NO DATA 2. 58E-05* 3.93E-06 L13E-o6*

cs 137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 cs 138 1. 71E-07 2.27E-07 l.50E-07 NO DATA l.68E-07 1. 84E-08 7.29E-08 BA 139 4.98E-10 2.66E-13 1. 45E-11 NO DATA 2.33E-13 1. 56E-06 1. 56E-05 BA 140 2.00E-05 1. 75E-08 1.17E-06 NO DATA 5. 71E-09 4. 71E-04 2.75E-05 BA 141 5. 29E-11 2.95E-14 1. 72E-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 BA 142 1. 35E-11 9.73E-15 7.54E-13 NO DATA 7.87E-15 4.44E-07 7.41E-10 LA 140 1.74E-07 6.08E-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.lOE-05 LA 142 3.50E-10 1. llE-10 3. 49E-11 NO DATA, NO DATA 2.35E-06 2.05E-05 CE 141 1. 06E-05 5.28E-06 7.83E-07 NO DATA 2.31E-06 1. 4 7E-04 1.53E-05 CE 143 9.89E-08 5.37E-08 7.77E-09 NO DATA 2.26E-08 3.12E-05 3.44E-05 CE 144 1.83E-03 5. 72E-04 9.77E-05 . NO DATA 3.17E-04 3.23E-03 1.05E-04 PR 143 4.99E-06 1.50E-06 2.47E-07 NO DATA 8. llE-07 1.17E-04 2.63E-05 PR 144 1. 61E-11 4.99E-12 8.lOE-13 NO DATA 2.64E-12 4.23E-07 5.32E-08 ND 147 2.92E-06 2. 36E-06* l.84E-07 NO DATA 1. 30E-06 8.87E-05 2.22E-05 w 187 4.41E-09 2.61E-09 1.17E-09 NO DATA NO DATA 1. llE-05 2.46E-05 NP 239 1. 26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 1. 57E-05 1. 731'-05

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use !Page 88 of 160 ATTACHMENT A (Page 80 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.2-4*

INHALATION DOSE FACTORS FOR INFANT (MREM PER PC! INHALED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LL!

H 3 NO DATA 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 NA 24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 p 32 1. 45E-03 8.03E-05 5.53E-05 NO DATA NO DATA NO DATA 1.15E-05 CR 51 NO DATA NO DATA 6.39E-08 4.llE-08 9.45E-09 9.17E-06 2.55E-07 MN 54 NO DATA 1. 81E-05 3.56E-06 NO DATA 3.56E-06 7.14E-D4 5.04E-06 MN 56 NO DATA 1. lOE-09 1. 58E-10 NO DATA 7. 86E-10 8.95E-06 5.12E-05 FE 55 1. 41E-05 8.39E-06 2.38E-06 NO DATA NO DATA 6.21E-05 7.82E-07 FE 59 9.69E-06 1.68E-05 6.77E-06 NO DATA NO DATA 7.25E-04 1. 77E-05 co 58 NO DATA 8.71E-07 1. 30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 co 60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 NI 63 2.42E-04 1. 4 6E-05 8.29E-06 NO DATA NO DATA 1.49E-04 1. 7 3E-06 NI 65 1. 71E-09 2.03E-10 8.79E-11 NO DATA NO DATA 5.80E-06 3.58E-05 cu 64 NO DATA 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 l.07E-05 ZN 65 1. 38E-05 4.47E-05 2.22E-05 NO DATA 2.32E-05 4.62E-04 3.67E-05 ZN 69 3.85E-11 6.91E-11 5.13E-12 NO DATA 2.87E-11 1.05E-06 9.44E-06 BR 83 NO DATA NO DATA 2.72E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 2.86E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 1.46E-08 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1. 36E-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 RB 88 NO DATA 3. 98E-07 , 2.05E-07 NO DATA NO DATA NO DATA 2.42E-07 RB 89 NO DATA 2.29E-07 1. 4 7E-07 NO DATA NO DATA NO DATA 4.87E-08 SR 89 2.84E-04 NO DATA 8.15E-06 NO DATA NO DATA 1.45E-03 4.57E-05 SR 90 2. 92E-02 NO DATA 1.85E-03 NO DATA NO DATA 8.03E-03 9.36E-05 SR 91 6.83E-08 NO DATA 2.47E-09 NO DATA NO DATA 3.76E-05 5.24E-05 SR 92 7.50E-09 NO DATA 2.79E-10 NO DATA NO DATA 1. 70E-05 l.OOE-04 y 90 2.35E-06 NO DATA 6.30E-08 NO DATA NO DATA l.92E-04 7.43E-05 y 91M 2.91E-10 NO DATA 9.90E-12 NO DATA NO DATA 1. 99E-06 1.68E-06 y 91 4.20E-04 NO DATA 1.12E-05 NO DATA NO DATA 1. 7 5E-03 5.02E-05 y 92 1.17E-08 , NO DATA 3.29E-10 NO DATA NO DATA 1. 7 5E-05 9.04E-05 y 93 1.07E-07 NO DATA 2. 9rn:...09 NO DATA NO DATA 5.46E-05 1.19E-04 ZR 95 8.24E-05 1. 99E-05 1.45E-05 NO DATA 2.22E-05 1. 25E-03 1. 55E-05 ZR 97 1.07E-07 1. 83E-08 8.36E-09 NO DATA 1.85E-08 7.88E-05 1. OOE-04 NB 95 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 MO 99 NO DATA 1.18E-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3.48E-05 TC 99M 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-07 1.45E-06

Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 89 of 160 ATTACHMENT A (Page 81 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 2-4* (cont'd)

INHALATION DOSE FACTORS FOR INFANT

(~REM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 4.65E-14 5.88E-14 5. 80E-13 NO DATA 6.99E-13 4.17E-07 6.03E-07 RU 103 1. 44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 l.15E-05 RU 105 8.74E-10 NO DATA 2.93E-10 NO DATA 6.42E-10 l.12E-05 3.46E-05 RU 106 6.20E-05 NO DATA 7.77E-06 NO DATA 7.61E-05 8.26E-03 l.17E-04 AG llOM 7.13E-06 5.16E-06 3.57E-06 NO DATA 7.80E-06 2.62E-03 2.36E-05 TE 125M .3.40E-06 1. 42E-06 4.70E-07 l.16E-06 NO DATA 3.19E-04 9.22E-06 TE 127M l.19E-05 4.93E-06 1. 48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE 127 l.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1. 7 4E-05 TE 129M 1.0lE-05 4.35E-06 1. 59E-06 3.91E-06 2.27E-05 1. 20E-03 4.93E-05 TE 129 5. 63E-ll 2.48E-ll 1. 34E-ll 4.82E-ll 1. 25E-10 2.14E-06 1. 88E-05 TE 131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08. 1.89E-07 1.42E-04 8.51E-05 TE 131 1. 24E-ll 5. 87E-12. 3.57E-12 l.13E-ll 2.85E-ll 1.47E-06 5.87E-06 TE 132 2.66E-07 1.69E-07 1.26E-07 l.99E-07 7.39E-07 2.43E-04 3.15E-05 I 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1. 42E-06 I 131 2.71E-05 3.17E-05 1. 40E-05 1. 06E-02 3.70E-05 NO DATA 7.56E-07 I 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 NO DATA 1. 36E-06 I 133 9.46E-06 l.37E-05 4.00E-06 2.54E-03 l.60E-05 NO DATA 1. 54E-06 I 134 6.58E-07 1. 34E-06 4.75E-07 3.18E-05 1. 49E-06 NO DATA 9.21E-07 I 135 2.76E-06 5.43E-06 l.98E-06 4.97E-04 6.05E-06 NO DATA 1. 31E-06 cs 134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1. 36E-04 5.69E-05 9.53E-07 cs 136 3.45E-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 cs 137 3.92E-04 4.37E-04 3.25E-05 NO *DATA 1.23E-04 5.09E-05 9.53E-07 cs 138 3. 61E-:-07 5.58E-07 2.84E-07 NO DATA 2.93E-07 4.67E-08 6.26E-07 BA 139 1. 06E-09 7.03E-13 3.07E-ll NO DATA 4.23E-13 4.25E-06 3.64E-05 BA 140 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 BA 141 l.12E-10 7.70E-14 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06 BA 142 2.84E-ll 2.36E-14 1.40E-12 NO DATA 1.36E-14 l. llE-06 4.95E-07 LA 140 3.61E-07 1.43E-07 3.68E-08 NO DATA NO DATA 1.20E-04 6.06E-05 LA 142 7.36E-10 2.69E-10 6. 4 6E-ll NO DATA NO DATA 5.87E-06 4.25E-05 CE 141 1.98E-05 1.19E-05 1. 42E-06 NO DATA 3.75E-06 3.69E-04 l.54E-05 CE 143 2.09E-07 1.38E-07 1. 58E-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 CE 144 2.28E-03 8.65E-04 1.26E-04 NO DATA 3.84E-04 7.03E-03 1.06E-04 PR 143 1. OOE-05 3.74E-06 4.99E-07 NO DATA 1. 41E-06 3.09E-04 2.66E-05 PR 144 3.. 42E-ll 1. 32E-ll 1. 72E-12 NO DATA 4.80E-12 1.15E-06 3.06E-06 ND 147 5.67E-06 5. 81E-06 3.57E-07 NO DATA 2.25E-06 2.30E-04 2.23E-05 w 187 9.26E-09 6.44E-09 2.23E-09 NO DATA NO DATA 2.83E-05 2.54E-05 NP 239 2.65E-07 2.37E-08 1. 34E-08 NO DATA 4.73E-08 4.25E-05 1.78E-05

Revision: 9 AP. 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 90 of 160 ATTACHMENT A (Page 82 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.2-5*

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (rnrern/hr per pCi /rn2 )

ELEMENT TOTAL BODY SKIN H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.SOE-09 6.SOE-09 Mn-56 1.lOE-08 1. 30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1. 70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1. 70E-09 Zn-.65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-ll 9. 30E-ll Br-84 1. 20E-08 1.40E-08 Br-85 0.0 0.0

. Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1. 50E-08 1.SOE-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.lOE-09 8.30E-09 Sr-92 9.00E-09 1. OOE-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.BOE-09 4.40E-09 Y-91 2.40E-ll 2.70E-ll Y-92 1.60E-09

1. 90E-09 Y-93 5.70E-10 7.SOE-10 Zr-95 5.00E-09 5.SOE-09 Zr-97 5.SOE-09 6.40E-09 Nb-95 5.lOE-09 6.00E-09 Mo-99 1. 90E-09 2.20E-09 Tc-99M 9.60E-10 1. lOE-09 Tc-101 2.70E-09 3.00E-09 Ru-103 . 3. 60E-09 4.20E-09 Ru-105 4.SOE-09 5.lOE-09 Ru-106 1. SOE-09 1. BOE-09 Ag-llOM 1. SOE-08 2.lOE-08 Te-125M 3. SOE-11 4.BOE-11 Te-127M 1. lOE-12 1.30E-12 Te-127 1. OOE-11 l.lOE-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.lOE-10 8.40E-10

Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use !Page 91 of 160 ATTACHMENT A (Page 83 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.2-5* (cont'd)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem/hr per pCi/m2 )

ELEMENT TOTAL BODY SKIN Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1. 70E-09 2.00E-09 I-130 1. 40E-08 1. 70E-08 I-131 2.80E-09 3.40E-09 I-132 1. 70E-08 2.00E-08 I-133 3.70E-09 4.SOE-09 I-134 l.60E-08 l.90E-08 I-135 l.20E-08 l.40E-08 Cs-134 l.20E-08 l.40E-08 Cs-136 1. SOE-08 1. 70E-08 Cs-137 4.20E-09 '4.90E-09 Cs-138 2.lOE-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.lOE-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1. SOE-08 1. 70E-08 La-142 l.SOE-08 l.80E-08 Ce-141 5.SOE-10 6.20E-10 Ce-143 2.20E-09 2. SOE...:09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1. OOE-09 l.20E-09 W-187 3.lOE-09 3.60E-09 Np-239 9.SOE-10 1. lOE-09

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 92 of 160 ATTACHMENT A (Page 84 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 3-1*

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 p 32 1. 93E-04 1. 20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 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 l.40E-05 MN 56 NO DATA l.15E-07 2.04E-08 NO DATA 1. 4 6E-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* l.02E-05 3.91E-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 9.0lE-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.lOE-07 NO DATA 7.lOE-06 ZN 65 4.84E-06 1. 54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9. 7.0E-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. llE-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-'19 RB 89 NO DATA 4.0lE-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08];:-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 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. lOE-.05 MO 99 NO DATA 4.31E-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

Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use ~age 93 of 160 ATTACHMENT A (Page 85 of 152)

OFFSITE DOSE CA.LCULATION MANUAL TABLE A. 3-1* (cont'd)

INGESTION DOSE FACTORS FOR ADULTS (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1. 87E-10 1. lOE-21 RU 103' l.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU 105 l.54E-08 NO DATA 6.08E-09 NO DATA 1. 99E-07 NO DATA 9.42E-06 RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1. 78E-04 AG llOM l.60E-07 l.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 TE 125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 l.09E-05 NO DATA l.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 l.lOE-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE 129M l.15E-05 4.29E-06 l.82E-06 3.95E-06 4.80E-05 NO DATA *5.79E-05 TE 129 3.14E-08 l.18E-08 7.65E-09 2.41E-08 l.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 l.97E-08 8.23E-09 6.22E-09 l.62E-08 8.63E-08 NO DATA 2.79E-09 0

TE 132 , 2.52E-06 1.63E-06 l . 53E-06 1. 80E-06 1. 57E-05 NO DATA 7.71E-05 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 3.41E-06 l.95E-03 l.02E-05 NO DATA 1. 57E-06 I 132 2.03E-07 5.43E-07 l.90E-07 l.90E-05 8.65E-07 NO DATA l.02E-07 I 133 l.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA* 2.22E-06 I 134 1. 06E-07 2.88E-07 l.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 I 135 4'. 43E:-07 l.16E..:06 4.28E-07 7.65E-05 1. 86E-06. NO DATA l.31E-06 cs 134 6.22E-05 1. 48E-04 1. 21E-04 NO DATA 4.79E-05 1. 59E-05 2.59E-06 cs 136 6.51E-06 2.57E-05 1.85E-05 NO DATA 1. 43E-05 l.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. llE-06 cs 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.0lE-08 7. 91E-09 4.65E-13 BA 139 9.70E-08 6.91E-ll 2.84E-09 NO DATA 6.46E-ll 3. 92E-ll 1. 72E-07 BA 140 2.03E-05 2.55E-08 l.33E-06 NO DATA 8.67E-09 l.46E-08 4.18E-05 BA 141 4. 71E-08 3.56E-ll 1. 59E-09 NO DATA 3.31E-ll 2. 02E-ll 2.22E-17 BA 142 2.13E-08 2 .19E-ll 1. 34E-09

NO DATA 1. 85E-ll 1. 24E-ll 3.00E-26 LA 140 2.50E-09 1. 2 6E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA 142 l.28E-10 5. 82E-ll 1. 45E-ll 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 CE 143 1.65E-09 1. 22E-06 1. 35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 . NO DATA 1. 21E-07 NO DATA l.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. OlE-ll 1. 25E-ll 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 8.61E-08 3.0lE-08 NO DATA NO DATA NO DATA 2.82E-05

' AP 07B-003 Revision: 9 OFFSITE DOSE CALCULATION MANUAL Information Use Page 94 of 160 ATTACHMENT A (Page 86 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.3-1* (cont'd)

INGESTION DOSE FACTORS FOR ADULTS (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 l.19E-09 l.17E-10 6.45E-ll NO DATA 3.65E-10 NO DATA 2.40E-05 Sb 124** 2.BOE-06 5.29E-08 l. llE-06 6.79E-09 NO DATA 2.lBE-06 7.95E-05 Sb 125** l.79E-06 2.00E-08 4. 26E-07 1. 82E-09 NO DATA 1. 38E-06 l.97E-05 Sb 126** l.15E-06 2.34E-08 4.15E-07 7.04E-09 NO DATA 7.05E-07 9.40E-05 Co 57** NO DATA 1. 7 5E-07 2. 91E-07 NO DATA NO DATA NO DATA 4.44E-06

- Taken from Regulatory Guide 1.109 (Rev. 0)

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use !Page 95 of 160 ATTACHMENT A (Page 87 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A-3.2 INGESTION DOSE FACTORS FOR TEENAGERS (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA l.06E-07 l.06E-07 1. 06E-07 1. 06E-07 1. 06E-07 1. 06E-07 C 14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 NA 24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 p 32 2.76E-04 l.71E-05 l.07E-05 NO DATA NO DATA NO DATA 2.32E-05 CR 51 NO DATA NO DATA 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN 54 NO DATA 5.90E-06 l.17E-06 NO DATA 1. 76E-06 NO DATA 1. 21E-05 MN 56 NO DATA 1. 58E-07 2.81E-08 NO DATA 2.00E-07 NO DATA 1.04E-05 FE 55 3.78E-06 2.68E-06 6.25E-07 NO DATA NO DATA 1. 70E-06 l.16E-06 FE 59 5.87E-06 1. 37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 co 58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1. 34E-05 co 60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 NI 63 l.77E-04 1.25E-05 6.00E-06 NO DATA NO DATA NO DATA 1. 99E-06 NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5.19E-06 cu 64 NO DATA l.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA 8.92E-06 ZN 65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ZN 69 1..47E-08 2.80E-08 1. 96E-09 NO DATA 1.83E-08 NO DATA 5.16E-08 BR 83 NO DATA NO DATA 5.74E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 7.22E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 3.05E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.98E-05 l.40E-05 NO DATA NO DATA NO DATA 4. 41E-06 RB 88 NO DATA 8.52E-08 4.54E-08 NO DATA NO DATA NO DATA 7.30E-15 RB 89 NO DATA 5.50E-08 3.89E-08 NO DATA NO DATA NO DATA 8. 43E-17 SR 89 4.40E-04 NO DATA 1. 26E-05 NO DATA NO DATA NO DATA 5.24E-05 SR 90 8.30E-03 NO DATA 2.05E-03 NO DATA NO* DATA NO DATA 2.33E-04 SR 91 8.07E-06 NO DATA 3. 21E-07 NO DATA NO DATA NO DATA 3.66E-05 SR 92 3.05E-06 NO DATA 1. 30E-07 NO DATA NO DATA NO DATA 7.77E-05 y 90 1. 37E-08 NO DATA 3.69E-10 NO DATA NO DATA NO DATA l.13E-04 y 91M 1. 29E-10 NO DATA 4.93E-12 NO DATA NO DATA NO DATA 6.09E-09 y 91 2.0lE-07 NO DATA 5.39E-09 NO DATA NO DATA NO DATA 8.24E-05 y 92 1. 21E-09 NO DATA 3. 50E-11 NO DATA NO DATA NO DATA 3.32E-05 y 93 3. 83E-0*9 NO DATA 1. 05E-10 NO DATA NO DATA NO DATA 1 .. 17E:-04 ZR 95 4.12E-08 1. 30E-08 8.94E-09 NO DATA l.91E-08 NO DATA 3.00E-05 ZR 97 2.37E-09 4.69E-10 2.16E-10 NO DATA 7. llE-10 NO DATA 1.27E-04 NB 95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 MO 99 NO DATA 6.03E-06 l.15E-06 NO DATA 1. 38E...:05 NO DATA 1.08E-05 TC 99M 3.32E-10 9.26E-10 1. 20E-08 NO DATA l.38E-08 5.14E-10 6.08E-07

Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 96 of 160 ATTACHMENT A (Page 88 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A-3.2 (cont'd)

INGESTION DOSE FACTORS FOR TEENAGERS (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 3.60E-10 5.12E-10 5.03E-09 NO DATA 9.26E-09 3.12E-10 8.75E-17 RU 103 2.55E-07 NO DATA 1. 09E-07 NO DATA 8.99E-07 NO DATA 2.13E-05 RU 105 2.lBE-08 NO DATA 8.46E-09 NO DATA 2.75E-07 NO DATA 1. 76E-05 RU 106 3.92E-06 NO DATA 4.94E-07 NO DATA 7.56E-06 NO DATA 1. BBE-04 AG . 110M 2.05E-07 1.94E-07 1.lBE-07 NO DATA 3.70E-07 NO DATA 5.45E-05 TE 125M 3.83E-06 1. 38E-06 5.12E-07 l.07E-06 NO DATA NO DATA 1.13E-05 TE 127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 NO DATA 2.41E-05 TE 127 1. 58E:--07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 NO DATA 1. 22E-05 TE 129M l.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 NO DATA 6.12E-05 TE 129 4.48E-08 1.67E-08 1. 09E-08 3.20E-08 1. BBE-07 NO DATA 2.45E-07 TE 131M 2.44E-06 1.17E-06 9.76E-07 1. 76E-06 1. 22E-05 NO DATA 9.39E-05 TE 131 2.79E-08 1.15E-08 8. 72E-09 2.15E-08 1.22E-07 NO DATA 2.29E-09 TE 132 3.49E-06 2.21E-06 2.0BE-06 2.33E-06 2.12E-05 NO DATA 7.00E-05 I 130 1. 03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 NO DATA 2.29E-06 I 131 5.BSE-06 8.19E-06 4.40E-06 2.39E-03 1:41E-05 NO DATA 1.62E-06 I 132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 NO DATA 3.lBE-07 I 133 2.0lE-06 3.41E-06 1. 04E-06 4.76E-04 5.98E-06 NO DATA 2.58E-06 I 134 1.46E-07 3.87E-07 l.39E-07 6.45E-06 6.lOE-07 NO DATA 5.lOE-09 I 135 6.lOE-07 1.57E-06 5.82E-07 1.0lE-04 2.48E-06 NO DATA 1. 74E-06 cs 134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 cs 136 8.59E-06 3.38E-05 2.27E-05 NO DATA 1. 84E-05 2.90E-06 2. 72E-06 cs 137 l.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 l.97E-05 2.12E-06 cs 138 7.76E-08 1.49E-07 7.45E-08 NO DATA 1.lOE-07 1. 28E-08 6. 76E-11 BA 139 l.39E-07 9.78E-11 4.05E-09 NO DATA 9. 22E-11 6.74E-11 1. 24E-06 BA 140 2.84E-05 3.48E-08 1. 83E-06 NO DATA 1. lBE-08 2.34E-08 4.38E-05 BA 141 6. 71E-08 5. OlE-11 2.24E-09 NO DATA 4. 65E-11 3.43E-11 1. 43E-13 BA 142 2.99E-08 2.99E-11 1. 84E-09 NO DATA 2. 53E-11 1. 99E-11 9.lBE-20 LA 140 3.48E-09 1. 71E-09 4.55E-10 NO DATA NO DATA NO DATA 9.82E-05 LA 142 1. 79E-10 7. 95E-11 1. 98E-11 NO DATA NO DATA NO DATA 2.42E-06 CE 141 1.33E-08 8.BBE-09 l.02E-09 NO DATA 4.lBE-09 NO DATA 2.54E-05 CE 143 2.35E-09 1. 71E-06 1. 91E-10 NO DATA 7.67E-10 NO DATA 5.14E-05.

CE 144 6. 96E-07 2.BBE-07 3.74E-08 NO DATA 1. 72E-07 NO DATA 1.75E-04 PR 143 1. 31E-08 5.23E-09 6.52E-10 NO DATA 3.04E-09 NO DATA 4.31E-05 PR 144 4.30E-11 1.76E-11 2.lBE-12 NO DATA 1. OlE-11 NO DATA 4.74E-14 ND 147 9.38E-09 1.02E-08 6 .11E-10 NO DATA 5.99E-09 NO DATA 3.68E-05 w 187 1. 4 6E-07 1.19E-07 4.17E-08 NO DATA NO DATA NO DATA 3.22E-05

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use 0 age 97 of 160 ATTACHMENT A (Page 89 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A-3.2 (cont'd)

INGESTION DOSE FACTORS FOR TEENAGERS (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 1.76E-09 1. 66E-10 9. 22E-11 NO DATA 5.21E-10 NO DATA 2.67E-05 Sb 124** 3.87E-06 7.13E-08 1. 51E-06 8.78E-09 NO DATA 3.38E-06 7.BOE-05 Sb 125** 2.48E-06 2.71E-08 5.BOE-07 2.37E-09 NO DATA 2.lBE-06 1.93E-05 Sb 126** 1. 59E-06 3.25E-08 5. 71E-07 8.99E-09 NO DATA 1.14E-06 9.41E-05 Co 57** NO DATA 2.38E-07 3.99E-07 NO DATA NO DATA NO DATA 4.44E-06

- Taken from Regulatory Guide 1.109 (Rev. 0)

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information us*e Page 98 of 160 ATTACHMENT A (Page 90 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.3-3 INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED)

NUCLIDE, BONE LIVER' T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C 14 l.21E-05 2.42E-06 2.42E-06 2.42E-06. 2.42E-06 2.42E-06 2.42E-06 NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5. 80E-06' 5.80E-06 5.80E-06 p 32 8.25E-04 3.86E-05 3.18E-05 NO DATA NO DATA NO.DATA 2.28E-05 CR 51 NO DATA NO DATA 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4. 72E-07 MN 54 NO DATA l.07E-05 2.85E-06 NO DATA 3.. OOE-06 NO DATA 8.98E-06 MN 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.04E-07 NO DATA 4. 84E-.05 FE 55 l.15E-05 6.lOE-06 1. 89E-06 NO DATA NO DATA 3.45E-06 l.13E-06 FE 59 l.65E-05 2.67E-05 1. 33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 co 58 NO DATA 1. 80E-06 5.51E-06 NO DATA NO DATA NO DATA l.05E-05 co 60 NO DATA 5.29E-06 1. 56E-05 NO DATA NO DATA NO DATA 2.93E-05 NI 63 5.38E-04 2.88E-05 l.83E-05 NO DATA NO DATA NO DATA l.94E-06 NI 65 2.22E-06 2.09E-07 1. 22E-07 NO DATA NO DATA NO DATA 2.56E-05 cu 64. NO DATA 2.45E-07 1. 48E-07 NO DATA 5.92E-07 NO DATA l.15E-05 ZN 65 1. 37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ZN 69 4.38E-08 6.33E-08 5.85E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 BR 83 NO DATA NO DATA l.71E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA l.98E-07 NO DATA NO DATA NO DATA* LT E-24 BR 85 NO DATA NO DATA 9.12E-09 NO DATA NO DATA NO DATA . LT E-24 RB 86 NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4. 31E-06 RB 88 NO DATA l.90E-07 l.32E-07 NO DATA NO DATA NO DATA 9.32E-09 RB 89 NO DATA l.17E.:.07 l.04E-07 NO DATA NO DATA NO DATA 1. 02E-09 SR 89 l.32E-03 NO DATA 3.77E-05 NO DATA NO DATA NO DATA 5. l'lE-05 SR 90 l.70E-02 NO DATA 4.31E-03 NO DATA NO DATA NO DATA 2.29E-04 SR 91 2.40E-05 NO DATA 9.06E-07 NO DATA NO DATA NO DATA 5.30E-05 SR 92 9.03E-06 NO DATA 3.62E-07 NO DATA NO DATA NO DATA 1. 71E-04 y 90 4. llE-08 NO DATA l. lOE-09 NO DATA NO DATA NO DATA 1. 1 7E-04 y 91M 3.82E-10 NO DATA 1. 39E-ll NO DATA NO DATA NO DATA 7.48E-07 y 91 6.02E-07 NO DATA l.61E-0B NO DATA NO DATA NO DATA 8.02E-05 y 92 3.60E-09 NO DATA 1. 03E-10 NO DATA NO DATA NO DATA 1. 04E-04 y 93 l.14E-08 NO DATA 3.13E-10 NO DATA NO DATA NO DATA 1. 70E-04 ZR 95 l.16E-07 2.55E-08 2.27E-08 NO DATA 3. 65E-'o8 NO DATA 2.66E-05 ZR 97 6.99E-09 1. OlE-09 5.96E-10 NO DATA 1. 45E-09 NO DATA l.53E-04 NB 95 2.25E-08 8.76E-09 6.26E-:-09 NO DATA 8.23E-09 NO DATA l.62E-05 MO 99 NO DATA l.33E-05 3.29E-06 NO DATA 2.84E-05 NO DATA l.lOE-05 TC 99M 9.23E-10 l.81E-09 3.00E-08 NO DATA 2.63E-08 9.19E-10 l.03E-06

Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 99 of 160 ATTACHMENT A (Page '91 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.3-3 (cont'd)

INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 1.07E-09 1.12E-09 1. 42E-08 NO DATA 1.91E-08 5.92E-10 3.56E-09 RU 103 7.31E-07 NO DATA 2.81E-07 NO DATA 1. 84E-06 NO DATA 1.89E-05 RU 105 6.45E-08 NO DATA 2.34E-08 NO DATA 5.67E-07 NO DATA 4.21E-05 RU 106 1.17E-05 NO DATA 1. 46E-06 NO DATA 1. 58E-05 NO DATA 1.82E-04 AG .llOM 5.39E-07 3.64E-07 2.91E-07 NO DATA 6.78E-07 NO DATA 4.33E-05 TE 125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1. lOE-05 TE 127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 NO DATA 2.34E-05 TE 127 4. 71E-07 l.27E-07 1. OlE-07 3.26E-07 1. 34E-06 NO DATA 1. 84E-05 TE 129M 4.87E-05 1.36E-05 7.56E-06 l.57E-05 1. 43E-04 NO DATA 5.94E-05 TE 129 l.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 NO DATA 8.34E-06 TE* 131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 NO DATA 1. OlE-04 TE 131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 NO DATA 4.36E-07 TE 132 1.0lE-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 NO DATA 4.50E-05 I 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 NO DATA 2.76E-06 I 131 1. 72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 I 132 8.00E-07 l.47E-06 6. 76E-07 6. 8.2E-05 2.25E-06 NO DATA 1.73E-06 I 133 5.92E-06 7.32E-06 2.77E-06 1. 36E-03 l.22E-05 NO DATA 2. 95E-06

I 134 4 .. 19E-07 7.78E-07 3.58E-07 1. 79E-05 1.19E-06 NO DATA 5.. 16E-07 I 135 1. 75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 NO DATA 2.40E-06 cs '134 2.34E-04 3.84E-04 8.lOE-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 cs 136 2.35E-05 6.46E-05 4.18E-05 NO DATA 3.44E-05 5.13E-06 2.27E-06 cs 137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1. 96E-06 cs 138 2.28E-07 3.17E-07 2.0lE-07 NO DATA 2.23E-07 2.40E-08 1. 46E-07 BA 139 4.14E-07 2.21E-10 1. 20E-08 NO DATA 1. 93E-10 1. 30E-10 2.39E-05 BA 140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 BA 141 2.00E-07 1.12E'-10 6.51E-09 NO DATA 9. 69E-11 6.58E-10 1.14E-07 BA 142 8.74E-08 6.29E-11 4.88E-09 NO DATA 5.09E-11 3.70E-11 1.14E-09 LA 140 1.0lE-08 3.53E-09 1.19E-09 NO DATA NO DATA NO DATA 9.84E-05 LA 142 5.24E-10 1. 67E-10 5. 23E-11 NO DATA NO DATA NO DATA 3.31E-05 CE 141 3.97E-08 l.98E-08 2.94E-09 NO DATA 8.68E-09 NO DATA 2.47E-05 CE 143 6.99E-09 3.79E-06 5.49E-10 NO DATA 1. 59E-09 NO DATA 5.55E-05 CE 144 2.08E-06 6'. 52E-07 1. llE-07 NO DATA 3.61E-07 NO DATA 1. 70E-04 PR 143 3.93E-08 1.18E-08 1. 95E-09 NO DATA 6.39E-09 NO DATA 4.24E-05 PR 144 l.29E-10 3.99E-11 6.49E-12 NO DATA 2. llE-11 NO DATA 8.59E-08 ND 147 2.79E-08 2.26E-08 1. 75E-09 NO DATA 1.24E-08 NO DATA 3.58E-05 w 187 4.29E-07 2.54E-07 l.14E-07 NO DATA NO DATA NO DATA 3.57E-05

Revision: 9 - AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 100 of 160 ATTACHMENT A (Page 92 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.3-3 (cont'd)

INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 5.25E-09 3.77E-10 2.65E-10 NO DATA 1. 09E-09 NO DATA 2.79E-05 Sb 124** 1.11E-05 1. 44E-07 3.89E-06 2.45E-08 NO DATA 6.16E:....06 6.94E-05 Sb 125** 7.16E-06 5.52E-08 1. 50E-06 6.63E-09 NO DATA 3.99E-06 i.71E-05 Sb 126** 4.40E-06 6.73E-08 1. 58E-06 2.58E-08 NO DATA 2.lOE-06 8.87E-05 Co 57** NO DATA 4.93E-07 9.98E-07 NO DATA NO DATA NO DATA 4.04E-06

- Taken from Regulatory Guide 1.109 (Rev. 0)

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Dage 101 of 160 ATTACHMENT A (Page 93 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 3-4*

INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 3.0BE-07 3.0BE-07 3.0BE-07 3.0BE-07 3.0BE-07 3.0BE-07 C 14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA 24 l.OlE-05 l.OlE-05 1. OlE-05 l.OlE-05 l.OlE-05 1. OlE-05 l.OlE-05 p 32 1. 70E-03 l.OOE-04 6.59E-05 NO DATA NO DATA NO DATA 2.30E-05 CR 51 NO DATA NO DATA 1. 41E-08 9.20E-09 2.0lE-09 1. 79E-08 4. llE-07 MN 54 NO DATA l.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 MN 56 NO DATA 8.lBE-07 1. 41E-07 NO DATA 7.03E-07 NO DATA 7.43E-05 FE 55 l.39E-05 8.98E-06 2.40E-06 NO DATA NO DATA 4.39E-06 l.14E-06 FE 59 3.0BE-05 5.38E-05 2.12E-05 NO DATA NO DATA 1. 59E-05 2.57E-05 co 58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 co 60 NO DATA 1. 08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 NI 63 6.34E-04 3.92E-05 2.20E-05 NO DATA NO DATA NO DATA. 1. 95E-06 NI 65 4.70E-06 5.32E-07 2.42E-07 NO DATA NO DATA NO DATA 4.05E-05 cu 64 NO DATA 6.09E-07 2.82E-07 NO DATA 1. 03E-06 . NO DATA l.25E-05 ZN 65 l.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ZN 69 9.33E-08 l.68E-07 l.25E-08 NO DATA 6.98E-08 NO DATA l.37E-05 BR 83 NO DATA NO DATA 3.63E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 3.82E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA l.94E-08 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1. 70E-04 8.40E-05 NO DATA NO DATA NO DATA 4.35E-06 RB 88 NO DATA 4.98E-07 2.73E-07 NO DATA NO DATA NO DATA 4.85E-07 RB 89 NO DATA 2.86E-07 l.97E-07 NO DATA NO DATA NO DATA 9.74E-08 SR 89 2.51E-03 NO DATA 7.20E-05 NO DATA NO DATA NO DATA 5.16E-05 SR 90 l.85E-02 NO DATA 4. 71E-03 NO DATA NO DATA NO DATA 2.31E-04 SR 91 5.00E-05 NO DATA l.81E-06 NO DATA NO DATA NO DATA 5. 92E SR 92 l.92E-05 NO DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 y 90 8.69E-08 NO DATA 2.33E-09 NO DATA NO DATA NO DATA l.20E-04 y 91M 8.lOE-10 NO DATA 2. 76E-ll NO DATA NO DATA NO DATA 2.70E-06 y 91 l.13E-06 NO DATA 3.0lE-08 NO DATA NO DATA NO DATA 8.10E-c05 y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA l.46E-04 y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DATA NO DATA l.92E-04 ZR 95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50E-05 ZR 97 1. 48E-08 2.54E-09 l.16E-09 NO DATA 2.56E-09 NO DATA 1. 62E-04 NB 95 4.20E-08 1. 73E-08 l.OOE-08 NO DATA 1. 24E-08 NO DATA l.46E-05 MO 99 NO DATA 3.40E-05 6.63E-06 NO DATA 5.08E-05 NO DATA l.12E-05 TC 99M 1. 92E-09 3. 96E-09 5.lOE-08 NO DATA 4.26E-08 2.07E-09 .l.15E-06

Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 102 of 160 ATTACHMENT A (Page 94 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.3-4* (cont'd)

INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 2.27E-09 2.86E-09 2.83E-08 NO DATA 3.40E-08 1. 56E-09 4.86E-07 RU 103 1. 48E-06 NO DATA 4.95E-07 NO DATA 3.08E-06 NO DATA 1. 80E-05 RU 105 1.36E'-07 NO DATA 4.58E-08 NO DATA 1. OOE-06 NO DATA 5.41E-05 RU 106 2.41E-05 NO DATA 3.0lE-06 NO DATA 2.85E-05 NO DATA 1. 83E-04 AG 110M 9 96E-07 7.27E-07 4.SlE-07 NO DATA 1.04E-06 NO DATA 3.77E-05 TE 125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 NO DATA NO DATA 1. llE-05 TE 127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05 TE 127 1. OOE-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.lOE-05 TE 129M 1. OOE-04 3.43E-05 1. 54E-05 3.84E-05 2.50E-04 NO DATA 5.97E-05 TE 129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 NO DATA 2.27E-05 TE 131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DATA 1. 03E-04 TE 131 1. 7 6E-07 6.50E-08 4.94E-08 1. 57E-07 4.50E-07 NO DATA . 7. llE-06 TE 132 2.08E-05 1. 03E-05 9.61E-06 1.52E-05 6.44E-05 NO DATA 3.SlE-05 I 130 6.00E-06 1. 32E-05 5.30E-06 1.48E-03 1. 45E-05 NO DATA 2.83E-06 I 131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 I 132 1.66E-06 3.37E-06 1. 20E-'-06 1. 58E-04 3. 76E-06 NO DATA 2.73E-06 I 133 1. 25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 NO DATA 3.08E-06 I 134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1. 99E-06 NO DATA 1. 84E-06 I 135 .3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 NO DATA 2.62E-06 cs 134 3.77E-04 7.03E-04 7.lOE-05 NO DATA 1. 81E-04 7.42E-05 1. 91E-06 cs 136 4.59E-05 1. 35E-04 5.04E-05 NO DATA 5.38E-05 1.lOE-05 2.05E-06 cs 137 5.22E-04 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 cs 138 4.SlE-07 7.82E-07 3.79E-07 NO DATA 3.90E-07 6.09E-08 1.25E-06 BA 139 8.81E-07 5.84E-10 2.55E-08 NO DATA 3.51E-10 3.54E-10 5.58E-05 BA 140 1. 71E-04 1. 71E-07 8.81E-06 }JO DATA 4.06E-08 1.05E-07 4.20E-05 BA 141 4.25E-07 2.91E-10 1. 34E-08 NO DATA 1.75E-10 1. 77E-10 5.19E-06 BA 142 1. 84E-07 1. 53E-10 9.06E-09 NO DATA 8.81E-ll 9. 26E-11 7.59E-07 LA 140 2. llE-08 8.32E-09 2.14E-09 NO DATA NO DATA NO DATA 9.77E-05 LA 142 1. lOE-09 4.04E-10 9.67E-11 NO DATA NO DATA NO DATA 6.86E-05 CE 141 7.87E-08 4.80E-08 5.65E-09 NO DATA 1.48E-08 NO DATA 2.48E-05 CE 143 l.48E-08 9.82E-06 1.12E-09 NO DATA 2.86E-09 NO DATA 5.73E-05 CE 144 2.98E-06 1. 22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1. 71E-04 PR 143 8.13E-08 3.04E-08 4.03E-09 NO DATA 1.13E-08 NO DATA 4.29E-05 PR 144 2.74E-10 1. 06E-10 1. 38E-11 NO DATA 3. 84E-ll NO DATA 4.93E-06 ND 147 5.53E-08 5.68E-08 3.48E-09 NO DATA 2.19E-08 NO DATA 3.60E-05 w 187 9.03E-07 6.28E-07 2.17E-07 NO DATA NO DATA NO DATA 3.69E-05

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use age 103 of 160 ATTACHMENT A (Page 95 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.3-4* (cont'd)

INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 1. llE-08 9.93E-10 5.61E-10 NO DATA 1. 98E-09 NO DATA 2.87E-05 Sb 124** 2.14E-05 3.15E-07 6.63E-06 5.68E-08 NO DATA 1. 34E-05 6.60E-05 Sb 125** l.23E-05 1.19E-07 2.53E-06 1. 54E-08 NO DATA 7.72E-06 1.64E-05 Sb 126** 8.06E-06 1.58E-07 2.91E-06 6.19E-08 NO DATA 5.07E-06 8.35E-06 Co 57** NO DATA 1.15E-06 1. 87E-06 NO DATA NO DATA NO DATA 3.92E-06

- Taken from Regulatory Guide 1.109 (Rev. 0)

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use 0 age 104 of 160 ATTACHMENT A (Page 96 of 152)

OFFSITE D,OSE CALCULATION MANUAL TABLE A.3-5*

STABLE ELEMENT TRANSFER DATA Element Biv Fm (Cow) Ft Veg/soil Milk (d/1) Meat -"°(d/kg)

H 4.SE 00 1.0E-02 1.2E-02 I 3/18 C 5.SE 00 1. 2E-02 3.lE-02 Na 5.2E-02 4.0E-02 3.0E-02 p 1.lE 00 2.SE-02 4.6E-02 Cr 2.SE-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.SE-04 8.0E-04 Fe 6.6E-04 1. 2E-03 4.0E-02 Co 9.4E-03 1. OE-03 1. 3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1. 2E-01 1.4E-02 8.0E-03 Zn 4.0E-01 3.9E-02 3.0E-02 Rb 1. 3E-01 3.0E-02 3.lE-02 Sr 1.7E-02 8.0E-04 6.0E-04 y 2.6E-03 1. OE-05 4.6E-03 Zr 1. 7E-:-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.SE-03 2.BE-01 Mo 1. 2E-01 7.SE-03 8.0E-03 Tc 2.SE-01 2.SE-02 4.0E-01 Ru 5.0E-02 1. OE'-06 4.0E-01 Rh 1. 3E 01 1. OE-02 1. SE-03 Ag 1. SE-01 5.0E-02 1.7E-02 Te 1. 3E 00 1. OE-03 7.7E-02 I 2.0E-02 6.0E-03 2.9E-03 Cs l.OE-02 1.2E-02 4.0E-03 Ba 5.0E-03 4.0E-04 3.2E-03 La 2.SE-03 5.0E-06 2.0E-04 Ce 2.SE-03 1. OE-04 l.2E-03 Pr 2.SE-03 5.0E-06 4.7E-03 Nd 2.4E-03 5.0E-06 3.3E-03 w 1. SE-02 5.0E-04 1. 3E-03 Np 2.SE-03 5.0E-06 2.0E-04 Fm (Goat) 13/18 Milk (d/1)

H l.7E-01 C 1. OE-01 p 2.SE-01 Fe 1. 3E-04 Cu 1. 3E-02

$r 1. 4E-02 I 6.0E-02 Cs 3.0E-01

Taken from Regulatory Guide 1.109 (Rev. 1)

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 105 of 160 ATTACHMENT A (Page 97 of* 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.4-1 SITE RELATED DOSE COMMITMENT FACTOR AIT MREM/HR PER µCI/ML ADULT NUCLIDE BONE LIVER *. T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 8.96E 00 8.96E 00 8.96E 00 8.96E 00 8.96E 00 8. 96E 00 C 14 3.15E 04 6.30E 03 6.30E 03 6.30E 03 6.30E 03 6.30E 03 6.30E 03 NA 24 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 p 32 4.62E 07 2.87E 06 1. 7 9E' 06 O.OOE-01 O.OOE-01 O.OOE-01 5.20E 06 CR 51 O.OOE-01 O.OOE-01 l.49E 00 8.94E-01 3.29E-01 l.98E 00 3.76E 02 MN 54 0. OOE-Cll 4. 76E 03 9.08E 02 O.OOE-01 1. 42E 03 O.OOE-01 1. 46E 04 MN 56 O.OOE-01 1. 20E 02 2.12E 01 O.OOE-01 1.52E 02 O.OOE-01 3.82E 03 FE 55 8.87E 02 6.13E 02 1.43E 02 O.OOE-01 O.OOE-01 3.42E 02 3.52E 02 FE 59 1. 40E 03 3.29E 03 1.26E 03 O.OOE-01 O.OOE-01 9.19E 02 l. lOE 04 co 58 O.OOE-01 1. 51E 02 3.39E 02 0.00E-01 O.OOE-01 O.OOE-01 3.06E 03 co 60 O.OOE-01 4.34E 02 9.58E 02 O.OOE-01 O.OOE-01 O.OOE-01 8.16E 03 NI, 63 4.19E 04 2.94E 03 1.41E 03 O.OOE-01 O.OOE-01 O.OOE-01 6.07E 02 NI 65 1. 70E 02 2.21E 01 1.0lE 01 O.OOE-01 O.OOE-01 O.OOE-01 5. 61E 02 cu 64 O.OOE-01 1. 69E 01 7.93E 00 O.OOE-01 4.26E-01 O.OOE-01 1. 44E 03 ZN 65 2 .. 36E 04 7.50E 04 3.39E 04 O.OOE-01 5.02E 04 O.OOE-01 4.73E 04 ZN 69 5.02E 01 9.60E 01 6.67E 00 O.OOE-01 6.24E-01 O.OOE-01 1.44E 01 BR 83 O.OOE-01 O.OOE-01 4.38E 01 O.OOE-01 O.OOE-01 O.OOE-01 6.30E 01 BR 84 O.OOE-01 O.OOE-01 *5. 67E 01 O.OOE-01 O.OOE-01 O.OOE-01 4.45E-04 BR 85 O.OOE-01 O.OOE-01 2.33E 00 O.OOE-01 O.OOE-01* O.OOE-01 1. 09E-15 RB 86 O.OOE-01 1. 03E 05 4.79E 04 O.OOE-01 O.OOE-01 O.OOE-01 2.03E 04 RB 88 O.OOE-01 2.95E 02 1. 56E 02 O.OOE-01 O.OOE-01 O.OOE-01 4,07E-09 RB 89 O.OOE-01 1.95E 02 1.37E 02 O.OOE-01 O.OOE-01 O.OOE-01 l.13E-11 SR 89 4.78E 04 O.OOE-01 1. 37E 03 O.OOE-01 O.OOE-01 O.OOE-01 7.66E 03 SR 90 1.18E 06 O.OOE-01 2.88E 05 O.OOE-01 O.OOE-01 O.OOE-01 3.40E 04 SR 91 8. 79E 02 O.OOE-01 3.55E 01 O.OOE-01 O.OOE:-01 O.OOE-01 4.19E 03 SR 92 3.33E 02 O.OOE-01 1.44E 01 O.OOE-01 O.OOE-01 O.OOE-01 6.60E 03 y 90 1. 38E 00 O.OOE-01 3.69E-02 O.OOE-01 O.OOE-01 O.OOE-01 1. 46E 04 y 91M 1. 30E-02 O.OOE-01 5.04E-04 O.OOE-01 O.OOE-01 O.OOE-01 3.82E-02 y 91 2.02E 01 O.OOE-01 5.39E-01 O.OOE-01 O.OOE-01 O.OOE-01 1.llE 04 y 92 1. 21E-01 O.OOE-01 3.53E-03 O.OOE-01 O.OOE-01 ,0. OOE-01 2.12E 03 y 93 3.83E-01 O.OOE-01 1.06E-02 O.OOE-01 O.OOE-01 O.OOE-01 1. 22E 04 ZR 95 2.77E 00 8.88E-01 6. OlE-01 O.OOE-01 1. 39E 00 O.OOE-01 2.82E 03 ZR 97 1.53E-01 3.09E-02 1. 41E-02 O.OOE-01 4'.67E-02 O.OOE-01. 9.57E 03.

NB 95 4.47E 02 2.49E 02 1. 34E 02 O.OOE-01 2.46E 02 O.OOE-01 l.51E 06 MO 99 O.OOE-01 4.62E 02 8.79E 01 O.OOE-01 1.05E 03 O.OOE-01 1. 07E 03 TC 99M 2.94E-02 8.32E-02 1.06E 00 O.OOE-01 1.26E 00 4'.07E-02 4.92E 01

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use [)age 106 of 160 ATTACHMENT A (Page 98 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 4-1 (cont'd)

SITE RELATED DOSE COMMITMENT FACTOR AIT MREM/HR PER µCI/ML ADULT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 3.03E-02 4.36E-02 4.28E-01 O.OOE-01 7.85E-01 2.23E-02 1. 31E-13 RU 103 1.98E 01 O.OOE-01 8.54E 00 0. OOE.:...01 7.57E 01 O.OOE-01 2.31E 03 RU 105 1.65E 00 O.OOE-01 6.52E-01 O.OOE-01 2.13E 01 O.OOE-01 1. OlE 03 RU 106 2.95E 02 O.OOE-01 3. 73E 01 O.OOE-01 5.69E 02 O.OOE-01 1. 91E 04 AG 110M 1. 42E 01 1. 31E 01 7.BOE 00 O.OOE-01 2.58E 01 O.OOE-01 5. 36E 03 TE 125M 2.79E 03 l.OlE 03 3.74E 02 8.39E 02 1.13E 04 O.OOE-01 1.llE 04 TE 127M 7.05E 03 2.52E 03 8.59E 02 1. BOE 03 2. 86E 04 O.OOE-01 2.36E 04 TE 127 1.14E 02 4. llE 01 2.48E 01 8.48E 01 4.66E 02 O.OOE-01 9.03E 03 TE 129M 1. 20E 04 4.47E 03 l.89E 03 4. llE 03 5.00E 04 O.OOE-01 6.03E 04 TE 129 3.27E 01 1. 23E 01 7.96E 00 2.51E 01 1 .. 37E 02 O.OOE-01 2.47E 01 TE 131M l.BOE 03 8.BlE 02 7.34E 02 1.39E 03 8.92E 03 O.OOE-01 8.74E 04 TE 131 2.05E 01 8.57E 00 6.47E 00 1.69E 01 8.98E 01 O.OOE-01 2.90E 00 TE 132 2.62E .03 l.70E 03 1.59E 03 1. 87E 03 1.63E 04 O.OOE-01 8.02E 04 I 130 9.0lE 01 2. 66E 02 1. 05E 02 2.25E 04 4.15E 02 O.OOE-01 2.29E 02 I 131 4. 96E 02 7.09E 02 4.06E 02 2.32E 05 1. 22E 03 O.OOE-01 1. 87E 02 I 132 2.42E 01 6.47E 01 2.26E 01 2.26E 03 l.03E 02 O.OOE-01 1.22E 01 I 133 1. 69E 02 2.94E 02 8.97E 01 4.32E 04 5.13E 02 O.OOE-01 2.64E 02 I 134 1. 26E 01 3.43E 01 1. 23E 01 5.94E 02 5. 46E 01 O.OOE-01 2.99E-02 I 135 5.28E 01 1. 38E 02 5.lOE 01 9. llE 03 2.22E 02 O.OOE-01 1.56E 02 cs 134 3.03E 05 7. 21E 05 5.89E 05 O.OOE-01 2.33E 05 7.75E 04 1. 26E 04 cs 136 3.17E 04 1. 25E 05 9.0lE 04 O.OOE-01 6.97E 04 9.55E 03 1. 42E 04 cs 137 3.BBE 05 5. 31E 05 3.48E 05 O.OOE-01 1.BOE 05 5.99E 04 1. 03E 04 cs 138 2.69E 02 5.31E 02 2.63E 02 O.OOE-01 3.90E 02 3.85E 01 2.27E-03 BA 139 9.00E 00 6.41E-03 2.64E-01 0. OOE-01 . 5.99E-03 3.64E-03 1. 60E 01 BA 140 1. BBE 03 2.37E 00 1. 23E 02 O.OOE-01 8.05E-01 1. 35E 00 3.BBE 03 BA 141 4.37E 00 3.30E-03 1. 48E-01 O.OOE-01 3.07E-03 1.87E-03 2.06:E;-09 BA 142 1. 98E 00 2.03E-03 L 24E-01 O.OOE-01 1. 72E-03 1.15E-03 2.7BE~1B LA 140 3.58E-01 1. BOE-01 4.76E-02 O.OOE-01 O.OOE-01 O.OOE-01 1.32E 04 LA 142 1. 83E-02 8.33E-03 2.07E-03 O.OOE-01 O.OOE-01 O.OOE-01 6.0BE 01 CE 141 8.0lE-01 5.42E-01 6.15E-02 O.OOE-01 2.52E-01 O.OOE-01 2.07E 03 CE 143 1.41E-01 1.04E 02 1.16E-02 O.OOE-01 4.60E-02 O.OOE-01 3.90E 03 CE 144 4.lBE 01 1. 75E 01 2.24E 00 O.OOE-01 1. 04E 01 O.OOE-01 1. 41E 04 PR 143 1. 32E 00 5.28E-01 6.52E-02 O.OOE-01 3.05E-01 O.OOE-01 5.77E 03 PR 144 4. 31E-03 1. 7 9E-03 2.19E-04 O.OOE-01 1.0lE-03 O.OOE-01 6.19E-10 ND 147 9.00E-01 1.04E 00 6.22E-02 O.OOE-01 6.0BE-01 O.OOE-01 4.99E 03 w 187 3.04E 02 2.55E 02 8.90E 01 O.OOE-01 O.OOE-01 O.OOE-01 8.34E 04

Revision: . 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 107 of 160 ATTACHMENT A (Page 99 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.4-1 (cont'd)

SITE RELATED DOSE. COMMITMENT FACTOR AIT I

MREM/HR PER µCI/ML ADULT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LL!

NP 239 1.28E-01 1. 25E-02 6.91E-03 O.OOE-01 3.91E-02 O.OOE-01 2.57E 03 Sb 124 2.40E 02 4.53E 00 9.50E 01 5.BlE-01 O.OOE-01 1. 87E 02 6.BlE 03 Sb 125 1. 53E 02 1.71E 00 3.65E 01 1. 56E-01 O.OOE-01 1.lBE 02 1. 69E 03 Sb 126 9.85E 01 2.00E 00 3.55E 01 6.03E-01 O.OOE-01 6.04E 01 8.05E 03 Co 57 O.OOE-01 3.55E 01 5.90E 01 O.OOE-01 O.OOE-01 O.OOE-01 9.0lE 02

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 108 of 160 ATTACHMENT A (Page 100 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.4-2 SITE RELATED DOSE COMMITMENT FACTOR AIT MREM/HR PER µCI/ML TEEN NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 6.34E 00 6.34E 00 6.34E 00 6.34E 00 6.34E 00 6.34E 00 C 14 3.43E 04 6.86E 03 6. 86E 03 6.*86E 03 6. 86E 03 6. 86E 03 6.86E 03 NA 24 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 p 32 5.04E 07 3.12E 06 l.95E 06 O.OOE-01 O.OOE-01 O.OOE-01 4.23E 06 CR 51 O.OOE-01 O.OOE-01 l.52E 00 8.46E-00 3.34E-00 2.17E 00 2.56E 02 MN 54 O.OOE-01 4.65E 03 9.22E 02 O.OOE-01 1. 39E 03 O.OOE-01 9.53E 03 MN 56 O.OOE-01 1. 24E 02 2 .21E 01 O.OOE-01 1. 58E 02 O.OOE-01 8.19E 03 FE 55 9.09E 02 6.45E 02 l.50E 02 O.OOE-01 O.OOE-01 4.09E 02 2. 79E 02 FE 59 1. 41E 03 3.30E 03 l.27E 03 O.OOE-01 O.OOE-01 1. 04E 03 7.79E 03 co 58 O.OOE-01 1.45E 02 3.35E 02 O.OOE-01 O.OOE-01 O.OOE-01 2.00E 03 co 60 O.OOE-01 4.20E 02 9. 45E 02 O.OOE-01 O.OOE-01 O.OOE-01 5.47E 03 NI 63 4.26E 04 3.0lE 03 1. 44E 03 O.OOE-01 O.OOE-01 O.OOE-01 4.79E 02 NI 65 1. BOE 02 2.30E 01 1.05E 01 O.OOE-01 O.OOE-01 O.OOE-01 1.25E 03 cu 64 O.OOE-01 1. 72E 01 8.0BE 00 O.OOE-01 4.35E 01. O.OOE-01 1. 33E 03 ZN 65 2.13E 04 7.41E 04 3.46E 04 O.OOE-01 4.74E 04 O.OOE-01 3.14E 04 ZN 69 5.45E 01 1. 04E 02 7. 26E 00 O.OOE-01 6.78E 01 O.OOE-01 1. 91E 02 BR 83 O.OOE-01 O.OOE-01 4.73E 01 O.OOE-01 O.OOE-01 O.OOE-01 8.24E-16 BR .84 O.OOE-01 O.OOE-01 5.95E 01 O.OOE-01 O.OOE-01 O.OOE-01 8.24E-16 BR 85 O.OOE-01 O.OOE-01 2.51E 00 O.OOE-01 O.OOE-01 O.OOE-01 8.24E-16 RB 86 O.OOE-01 1.lOE 05 5.19E 04 O.OOE-01 O.OOE-01 O.OOE-01 1. 63E 04 RB 88 O.OOE-01 3.16E 02 1. 68E 02 O.OOE-01 O.OOE-01 O.OOE-01 2.71E-05 RB 89 O.OOE-01 2.04E 02 1. 44E 02 O.OOE-01 O.OOE-01 O.OOE-01 3.12E-07 SR 89 4.97E 04 O.OOE-01 1. 42E 03 O.OOE-01 O.OOE-01 O.OOE-01 5.91E 03 SR 90 9.37E 05 O.OOE-01 2.31E 05 O.OOE-01 O.OOE-01 O.OOE-01 2.63E 04 SR 91 9. llE 02 O.OOE-01 3.62E 01 O.OOE-01 O.OOE-01 O.OOE-01 4 .13E 03 SR 92 3.44E 02 O.OOE-01 1.47E 01 O.OOE-01 O.OOE-01 O.OOE-01 8.77E 03 y 90 1. 42E 00 O.OOE-01 3.83E-01 O.OOE-01 O.OOE-01 O.OOE-01 1.17E 04 y 91M 1. 34E-01 O.OOE-01 5.llE-03 O.OOE-01 O.OOE-01 O.OOE-01 6.32E-01 y 91 2.09E 01 O.OOE-01 5.59E-00 O.OOE-01 O.OOE-01 O.OOE-01 8.55E 03 y 92 l.26E-00 O.OOE-01 3.63E-02 O.OOE-01 O.OOE-01 O.OOE-01 3.44E 03 y 93 3.97E-00 O.OOE-01 1. 09E-01 O.OOE-01 O.OOE-01 O.OOE-01 1.21E 04

zR 95 2.64E 00 8.34E-01 5.74E-00 O.OOE-01 1. 23E 00 O.OOE-01 1.92E 03 ZR 97 1. 52E-00 3.0lE-02 1. 39E-01 O.OOE-01 4.56E-01 O.OOE-01 8.15E 03 NB 95 4.50E 02 2.50E 02 1. 37E 02 O.OOE-01 2.42E 02 O.OOE-01 1.07E 06 MO 99 O.OOE-01 4. 61E 02 8.78E 01 O.OOE-01 1.05E 03 O.OOE-01 8.25E 02 TC 99M 2.84E-01 7. 92E-02* 1.03E 00 O.OOE-01 1.18E 00 4.39E-01 5.20E 01

Revision*: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use 1Page 109 of 160 ATTACHMENT A (Page 101 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 4-2 (cont'd)

SITE RELATED DOSE COMMITMENT FACTOR AIT MREM/HR PER µCI/ML TEEN NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 3.0BE-01 4.38E-02 4.30E-00 O.OOE-01 7.92E-00 2.67E-01 7.48E-09 RU 103 1. 95E 01 O.OOE-01 8.33E 00 O.OOE-01 6.87E 01 O.OOE-01 l..63E 03 RU 105 l.67E 00 O.OOE-01 6.46E-00 O.OOE-01 2.lOE 01 O.OOE-01 1. 34E 03 RU 106 2.99E 02 O.OOE-01 3.77E 01 O.OOE-01 5.77E 02 O.OOE-01 l.44E 04 AG llOM 1. 28E 01 1. 21E 01 7.36E 00 O.OOE-01 2.31E 01 O.OOE-01 3.40E 03 TE 125M 3.02E 03 l.09E 03 4.03E 02 8.43E 02 O.OOE-01 O.OOE-01 8.90E 03 TE 127M 7.62E 03 2.70E 03 9. 06E 02 l.81E 03 3.09E 04 O.OOE-01 1. 90E 04 TE 127 1

1. 24E 02 4.41E 01 2.68E 01 8.59E 01 5.04E 02 O.OOE-01 9. 61E 03 TE 129M 1. 28E 04 4.77E 03 2.03E 03 4.14E 03 5.37E 04 O.OOE-01 4.82E 04 TE 129 3.53E 01 1. 32E 01 8.59E 00 2.52E 01 l.48E 02 O.OOE-01 1. 93E 02 TE 131M l.92E 03 9.22E 02 7.69E 02 l.39E 03 9.61E 03 O.OOE-01 7.40E 04 TE 131 2.20E 01 9. 06E 00 6.87E 00 1. 69E 01 9.61E 01 O.OOE-01 l.BOE 00 TE 132 2.75E 03 1. 74E 03 l.64E 03 1. 84E 03 l.67E 04 O.OOE-01 5.51E 04 I 130 8.81E 01 2.55E 02 l.02E 02 2.0BE 04 3.92E 02 O.OOE-01 l.96E 02 I 131 5.00E 02 7.00E 02 3. 76E 02 2.04E 05 1. 21E 03 O.OOE-01 l.39E 02 I 132 2.39E 01 6.24E 01 2.24E 01 2.lOE 03 9.83E 01 O.OOE-01 2. 72E 01 I 133 1. 72E 02 2.92E 02 8.89E 01 4.07E 04 5.llE 02 O.OOE-01 2.21E 02 I 134 1. 25E 01 3.31E 01 l.19E 01 5.51E 02 5.22E 01 O.OOE-01 4.36E-01 I 135 5.22E 01 1. 34E 02 4.98E 01 8.64E 03 2.12E 02 O.OOE-01 1. 49E 02 cs 134 3.lOE 05 7.30E 05 3.39E 05 O.OOE-01 2.32E 05 8.86E 04 9.0BE 03 cs 136 3.lBE 04 l.25E 05 8.41E 04 O.OOE-01 6.82E 04 1. 07E 04 1. OlE 04 cs 137 4.15E 05 5.52E 05 l.92E 05 O.OOE-01 1. SSE 05 7.30E 04 7. 86E 03 cs 138 2.88E 02 5.52E 02 2. 76E 02 O.OOE-01 4.0BE 02 4.74E 01 2.51E-01 BA 139 9.lOE 00

6.40E-03 2.65E-00 O.OOE-01 6.03E-02 4.41E-02 8.llE 01 BA 140 1. 86E 03 2.28E 00 1. 20E 02 O.OOE-01 7. 72E-00 1. 53E 00 2.87E 03 BA 141 4.39E 00 3.28E-03 1. 4 7E-00 O.OOE-01 3.04E-02 2.24E-02 9.36E-06 BA 142 l.96E 00 .l.96E-03 1. 20E-00 O.OOE-01 L 66E-02 1. 30E-02 6.0lE-12 LA 140 3.61E-00 l.77E-01 4. 72E-01 O.OOE-01 O.OOE-01 O.OOE-01 l.02E 04 LA 142 l.86E-01 8.25E-03 2.05E-02 O.OOE-01 O.OOE-01 O.OOE-01 2.51E 02 CE 141 7. 98E-'00 5.32E-01 6.12E-01 O.OOE-01 2.51E-00 O.OOE-01 l.52E 03 CE 143 1. 41E-00 1. 03E 02 l.15E-01 O.OOE-01 4.60E-01 O.OOE-01 3.0SE 03 CE 144 4.17E 01 1. 73E 01 2.24E 00 0. OOE:...01 1. 03E 01 O.OOE-01 1. 05E 04 PR 143 1. 36E 00 5.43E-01 6.76E-01 O.OOE-01 3.15E-00 . 0. OOE-01 4.47E 03 PR 144 4.46E-02 l.83E-03 2.26E-03 O.OOE-01 l.05E-02 O.OOE-01 4.92E-06 ND 147 9.73E-00 l.06E 00 6.34E-01 O.OOE-01 6.21E-00 O.OOE-01 3.82E 03 w 187 3.28E 02 2. 67E .02 9.37E 01 O.OOE-01 O.OOE-01 O.OOE-01 7.24E 04

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 110 of 160 ATTACHMENT A (Page 102 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 4-2 (cont'd)

SITE RELATED DOSE COMMITMENT FACTOR AIT MREM/HR PER µCI/ML TEEN NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 1. 34E-00 1.27E-02 7.04E-02 O.OOE-01 3.98E-01 O.OOE-01 2.04E 03 Sb 124 2.32E 02 4.28E 00 9.05E 01 5.26E-00 O.OOE-01 2.03E 02 4.68E 03 Sb 125. 1.49E 02 1.63E 00 3.48E 01 1. 42E-00 O.OOE-01 1.31E 02 1.16E *03 Sb 126 9.53E 01 1.95E 00 3.42E 01 5.39E-00 O.OOE-01 6.84E 01 5.64E 03 Co 57 O.OOE-01 3.55E 01 5.96E 01 O.OOE-01 O.OOE-01 O.OOE-01 6.63E 02

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 111 of 160 ATTACHMENT A (Page 103 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.4-3 SITE RELATED DOSE COMMITMENT FACTOR AIT MREM/HR PER µCi/ML CHILD NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

H 3 0. OOE-'01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 l.19E 01 C 14 4.45E 04 8.90E 03 8.90E 03 8.90E 03 8.90E 03 8.90E 03 8.90E 03 NA 24 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E .02 7.93E 02 p 32 . 6.49E 07 3.04E 06 2.50E 06 O.OOE-01 O.OOE-01 O.OOE-01 1. 79E 06 CR 51 O.OOE-01 O.OOE-01 1;92E 00 1. 06E 00 2.91E-OO 1. 94E 00 1.02E 02 MN 54 O.OOE-01 3.99E 03 1. 06E 03 O.OOE-01 1.12E 03 O.OOE-01 3.35E 03 MN 56 O.OOE-01 1.25E 02 2. 81E 01 O.OOE-01 1. 51E 02 O.OOE-01 1.80E 04 FE 55 1. 57E 03 8.34E 02 2.59E 02 O.OOE-01 O.OOE-01 4. 72E 02 1.55E 02 FE 59 2.26E 03 3.65E 03 l.82E 03 O.OOE-01 O.OOE-01 1. 06E 03 3.80E 03 co 58 O.OOE-01 l.75E 02 5.37E 02 O.OOE-01 O.OOE-01 O.OOE-01 1.02E 03 co 60 O.OOE-01 5.16E 02 1.52E 03 O.OOE-01 O.OOE-01 O.OOE-01 2.86E 03 NI 63 7. 36E 04 3.94E 03 2.50E 03 O.OOE-01 O.OOE-01 O.OOE-01 2.65E 02 NI 65 3.04E 02 2. 86E 01 1.67E 01 O.OOE-01 O.OOE-01 O.OOE-01 3.50E 03 cu 64 O.OOE-01 2.39E 01 1. 44E 01 O.OOE-01 5.77E 01 O.OOE-01 l.12E 03 ZN 65 2.23E 04 5.95E 04 3.70E 04 O.OOE-01 3.75E 04 O.OOE-01 1. 05E 04 ZN 69 7.15E 01 1. 03E 02 9.54E 00 O.OOE-01 6.26E 01 O.OOE-01 6.51E 03 BR 83 O.OOE-01 O.OOE-01 6.64E 01 O.OOE-01 O.OOE-01 O.OOE-01 3.89E-16 BR 84 O.OOE-01 O.OOE-01 7.69E 01 O.OOE-01 O.OOE-01 O.OOE-01 3.89E-16 BR 85 O.OOE-01 O.OOE-01 3.54E 00 O.OOE-01 O.OOE-01 O.OOE-01 3.89E-16 RB 86 O.OOE-01 1.09E 05 6. 72E 04 O.OOE-01 O.OOE-01 O.OOE-01 7.03E 03 RB 88 O.OOE-01 3.lOE 02 2.15E 02 O.OOE-01 O.OOE-01 O.OOE-01 l.52E 01 RB 89 O*. OOE-01 1. 91E 02 1.70E 02 O.OOE-01 O.OOE-01 O.OOE-01 1. 66E 00 SR 89 l.08E 05 O.OOE-01. 3.08E 03 O.OOE-01 O.OOE-01 O.OOE-01 4.18E 03 SR 90 1.39E 06 O.OOE-01 3.52E 05 O.OOE-01 0-. OOE-01 O.OOE-01 1. 87E 04 SR 91 1.96E 03 O.OOE-01 7.41E 01 O.OOE-01 O.OOE-01 O.OOE-01 4.33E 03 SR 92 7.38E 02 O.OOE-01 2.96E 01 O.OOE-01 O.OOE-01 O.OOE-01 1.40E 04 y 90 3.20E 00 O.OOE-01 8.56E-01 O.OOE-01 O.OOE-01 O.OOE-01 9.lOE 03 y 91M 2.97E-01 O.OOE-01 1.08E-02 O.OOE-01 O.OOE:-01 O.OOE-01 5.82E 01 y 91 4.68E 01 O.OOE-01 1. 25E-01 O.OOE-01 O.OOE-01 O.OOE-01 6.24E 03 y 92 2.80E-00 O.OOE-01 8. OlE-02 O.OOE-01 O.OOE-01 O.OOE-01 8.09E 03 y 93 8.87E-00 O.OOE-01 2.44E-01 O.OOE-01 O.OOE-01 O.OOE-01 l.32E 04 ZR 95 7.05E 00 1. 55E 00 1. 38E 00 O.OOE-01 2.22E 00 O.OOE-01 1.62E 03 ZR 97 4.25E-OO 6.13E-02 3.62E-01 O.OOE-01 8.81E-01 O.OOE-01 9.29E 03 NB 95 5.32E 02 2.07E 02 1.48E 02 O.OOE-01 1.95E 02 O.OOE-01 3.83E 05 MO 99 O.OOE-01 8.78E 02 2.17E 02 O.OOE-01 . 1. 87E 03 O.OOE-01 7.26E 02 TC 99M 6.46E-01 1.27E-01 2.lOE 00 O.OOE-01 1.84E 00 6.43E-01 7.20E 01

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use [)age 112 of 160 ATTACHMENT A (Page 104 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 4-3 (cont'd)

SITE RELATED DOSE COMMITMENT FACTOR AIT MREM/HR PER µCi/ML CHILD NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 7.48E-01 7.83E-02 9.93E-00 O.OOE-01 1. 34E 00 4.14E-01 2.49E-01 RU 103 4.83E 01 O.OOE-01 1. SSE 01 O.OOE-01 l.21E 02 O.OOE-01 1. 25E 03 RU 105 4. 26E 00 O.OOE-01 1. 54E 00 O.OOE-01 3.74E 01 O.OOE-01 2.78E 03 RU 106 7. 72E 02 O.OOE-01 9.64E 01 O.OOE-01 l.04E 03 O.OOE-01 1. 20E 04 AG llOM 3.23E 01 2.18E 01 l.74E 01 O.OOE-01 4.06E 01 O.OOE-01 2.60E 03 TE 125M 4.25E 03 l.15E 03 5.67E 02 l.19E 03 O.OOE-01 O.OOE-01 4.lOE 03 TE 127M 1. OSE 04 2.90E 03 l.28E 03 2.58E 03 3.07E 04 O.OOE-01 8.72E 03 TE 127 1. 76E 02 4.73E 01 3.77E 01 1. 22E 02 5.00E 02 O.OOE-01 6.86E 03 TE 129M 1. 82E 04 5.07E 03 l.70E 03 5.85E 03 5*. 33E 04 O.OOE-01 2.21E 04, TE 129 5.00E 01 1.39E 01 l.19E 01 3.56E 01 l.46E 02 O.OOE-01 3.llE 03 TE 131M 2.68E 03 9.28E 02 9.88E 02 1. 91E 03 8.98E 03 O.OOE-01 3.77E 04 TE 131 3.09E 01 9. 43E 00 9.21E 00 2.37E 01 9.36E 01 O.OOE-01 l.63E 02 TE 132 3.77E 03 l.67E 03 2. OlE 03 2.43E 03 l.55E 04 O.OOE-01 l.68E 04 I 130 2.04E 02 4.13E 02 2.13E 02 4.55E 04 6.17E 02 O.OOE-01 l.93E 02 I 131 l.20E 03 l.21E 03 6.88E 02 4. OOE 05 l.99E 03 O.OOE-01 1. 08E 02 I 132 5.60E 01 l.03E 02 4.73E 01 4.77E 03 l.57E 02 .0. OOE-01 l.21E 02 I 133 4.14E 02 5.12E 02 l.94E 02 9.51E 04 8.53E 02 O.OOE-01 2. 06E 02 I 134 2.93E 01 5.44E 01 2.50E 01 1. 25E 03 8.32E 01 O.OOE-01 3.61E 01 I 135 l.22E 02 2.20E 02 1. 04E 02 l.95E 04 3.38E 02 O.OOE-01 l.68E 02 cs 134 3.82E 05 6. 26E 05 l.32E 05 O.OOE-01 1. 94E 05 6.97E 04 3.38E 03 cs 136 3.83E 04 l.05E 05 6.82E 04 O.OOE-01 *5. 61E 04 8.37E 03 3.70E 03 cs 137 5.33E 05 5. llE 05 7.54E 04 O.OOE-01 l.66E 05 5.99E 04 3.20E 03 cs 138 3. 72E 02 5.17E 02 3.28E 02 O.OOE-01 3.64E 02 3.92E 01 2.38E 02 BA 139 2.54E 01 l.35E-02 7.35E-00 O.OOE-01 l. lSE-01 7.97E-02 l.47E 03 BA 140 5.09E 03 4.46E 00 2.97E 02 0.00E-01 1. 45E 00 2.66E 00 2.58E 03 BA 141 1. 23E 01 6.86E-03 3.99E-00 O.OOE-01 5.94E-02 4.03E-01 6.99E 00 BA 142 5.36E 00 3.85E-03 2.99E-00 O.OOE-01 3.12E-02 2.27E-02 6.99E-02 LA 140 7. 86E.-00 2.75E-01 9.26E-01 O.OOE-01 O.OOE-01 O.OOE-01 7.66E 03 LA 142 4.0SE-01 1. 30E-02 4.07E-02 O.OOE-01 O.OOE-01 O.OOE-01 2.58E 03 CE 141 2.34E 00 l.17E 00 1. 73E-00 O.OOE-01 5.llE-00 O.OOE-01 1. 46E 03 CE 143 4.12E-00 2.23E 02 3.24E-01 O.OOE-01 9.37E-01 O.OOE-01 3.27E 03 CE 144 1. 23E 02 3.84E 01 6.54E 00 O.OOE-01 2.13E 01 O.OOE-01 1. OOE 04 PR 143 3.06E 00 9.lSE-01 l.52E-00 O.OOE-01 4.97E-00 O.OOE-01 3.30E 03 PR 144 1. OOE-01 3.lOE-03 5.0SE-03 O.OOE-01 l.64E-02 O.OOE-01 6.68E 00 ND 147 2.17E 00 1. 76E 00 l.36E-00 O.OOE-01 9.65E-00 O.OOE-01 2.79E 03 w 187 4.30E 02 2.55E 02 l.14E 02 O.OOE-01 O.OOE-01 O.OOE-01 3.58E 04

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 113 of 160 ATTACHMENT A (Page 105 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.4-3 (cont'd)

SITE RELATED DOSE COMMITMENT FACTOR AIT MREM/HR PER µCi/ML CHILD NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 3.47E-00 2.49E-02 1. 7 5E-01 0.00E-01 7.19E-01 O.OOE-01 1.84E 03 Sb 124 6.54E 02 8.49E 00 2.29E 02 1.44E 00 O.OOE-01 3.63E 02 4.09E 03 Sb 125 4.22E 02 3.25E 00 8.84E 01 3.91E-00 O.OOE-01 2.35E 02 1. OlE 03 Sb 126 2.59E 02 3.97E 00 9.31E 01 1. 52E 00 O.OOE-01 1. 24E 02 5.23E 03 Co 57 O.OOE-01 4. 81E 01 9.73E 01 O.OOE-01 O.OOE-01 O.OOE-01 3.94E 02

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 114 of 160I ATTACHMENT A (Page 106 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 4-4 SITE RELATED DOSE COMMITMENT FACTOR AIT MREM/HR PER µCI/ML INFANT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 C 14 8.92E 02 1. 90E 02 1. 90E 02 1. 90E 02 1. 90E 02 1. 90E 02 1. 90E 02 NA 24 3.BOE 02 3.BOE 02 3.BOE 02 3.BOE 02 3.BOE 02 3.BOE 02 3.BOE 02 p 32 6.40E 04 3. 76E 03 2.48E.03 O.OOE-01 O.OOE-01 O.OOE-01 8.65E 02 CR 51 O.OOE-01 O.OOE-,01 5.30E-01 3.46E-01 7.56E-02 6.73E-01 1.55E 01 MN 54 O.OOE-01 7.49E 02 1. 70E 02 O.OOE-01 1. 66E 02 O.OOE-01 2.75E 02 MN 56 O.OOE-01 3.0BE 01 5.30E 00 O.OOE-01 2.64E 01 O.OOE-01 2.BOE 03 FE 55 5.23E 02 3.38E 02 9.03E 01 O.OOE-01 O.OOE-01 1.65E 02 4.29E 01 FE 59 1.16E 03 2.02E 03 7.98E 02 O.OOE-01 O.OOE-01 5.98E 02 9. 67E 02 co 58 O.OOE-01 1. 35E 02 3.38E 02 O.OOE-01 O.OOE-01 O.OOE-01 3.37E 02 co 60 O.OOE-01 4.06E 02 9.59E 02 O.OOE-01 O.OOE-01 O.OOE-01 9. 67E 02 NI 63 2.39E 04 l.47E 03 8.28E 02 O.OOE-01 O.OOE-01 O.OOE-01 7.34E 01 NI 65 1. 77E 02 2.00E 01 9.lOE 00 O.OOE-01 O.OOE-01 . O.OOE-01 1.52E 03 cu 64 O.OOE-01 2.29E 01 1. 06E 01 O.OOE-01 3.87E 01 O.OOE-01 4.70E 02 ZN 65 6.92E 02 2.37E 03 1.09E 03 O.OOE-01 1.15E 03 O.OOE-01 2. OlE 03 ZN 69 3.51E 00 6.32E 00 4.70E-01 O.OOE-01 2.63E 00 O.OOE-01 5.15E 02 BR 83 O.OOE-01 O.OOE-01 1. 37E 01 O.OOE-01 O.OOE-01 O.OOE-01 3.76E-17 BR 84 O.OOE-01 O.OOE-01 l.44E 01 O.OOE-01 O.OOE-01 O.OOE-01 3. 7 6E-17 BR 85 O.OOE-01 O.OOE-01 7.30E-01 O.OOE-01 O.OOE-01 O.OOE-01 3.76E-17 RB 86 O.OOE-01 6.40E 03 3.16E 03 O.OOE-01 O.OOE-01 O.OOE-01 1.64E 02 RB 88 O.OOE-01 1. 87E 01 1. 03E 01 O.OOE-01 O.OOE-01 O.OOE-01 1.82E 01 RB 89 O.OOE-01 1. DBE 01 7, 41E 00 O.OOE-01 O.OOE-01 O.OOE-01 3.66E 00 SR 89 9.44E 04 O.OOE-01 2. 71E 03 O.OOE-01 O.OOE-01 O.OOE-01 1. 94E 03 SR 90 6.96E 05 O.OOE-01 1.77E 05 O.OOE-01 O.OOE-01 O.OOE-01 8.69E 03 SR 91 1.88E 03 O.OOE-01 6.81E 00 O.OOE-01 O.OOE-01 O.OOE-01 2.23E 03 SR 92 7.22E 02 O.OOE-01 2.68E 01 O.OOE-01 O.OOE-01 O.OOE-01 7.79E 03 y 90 3.27E 00 O.OOE-01 .8.77E-02 O.OOE-01 O.OOE-01 O.OOE-01 4.51E 03 y 91M 3.05E-02 O.OOE-01 l.04E-03 O.OOE-01 O.OOE-01 O.OOE-01 1.02E 02 y 91 4.25E 01 O.OOE-01 1.13E 00 O.OOE-01 O.OOE-01 O.OOE-01. 3.QSE 03 y 92 2.BBE-01 O.OOE-01 .8.09E-03 O.OOE-01 O.OOE-01 O.OOE-01 5. 49E 03 y 93 9.14E-01 O.OOE-01. 2.49E-02 O.OOE-01 O.OOE-01 O.OOE-01 7.22E 03 ZR 95 7.75E 00 1.89E 00 1. 34E 00 O.OOE-01 2.04E 00 O.OOE-01 9.41E 02 ZR 97 5.57E-01 9.56E-02 4.36E-02 O.OOE-01 9.63E-02 O.OOE-01 6.09E 03 NB 95 1. SSE 00 6.SlE-01 3.76E-01 O.OOE-01 4.66E_:01 O.OOE-01 5.49E 02 MO .99 O.OOE-01 1. 28E 03 2.49E 02* O.OOE-01 1.91E 03 O.OOE-01 4.21E 02 TC 99M 7.22E-02 1. 49E-01 1. 92E 00 O.OOE-01 1. 60E 00 7.79E-02 4.33E 01

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 115 of 160 ATTACHMENT A (Page 107 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 4-4 (cont'd)

SITE RELATED DOSE COMMITMENT FACTOR AIT MREM/HR PER µCI/ML INFANT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LL!

TC 101 8.54E-02 l.OBE-01 1. 06E 00 O.OOE-01 l.28E 00 5.87E-02 l.83E 01 RU 103 5.57E 01 O.OOE-01 1. 86E 01 O.OOE-01 l.16E 02 O.OOE-01 6.77E 02 RU 105 5.12E 00 O.OOE-01 1. 72E 00 O.OOE-01 3.76E 01 O.OOE-01 2.04E 03 RU 106 9.07E 02 O.OOE-01 l.13E 02 O.OOE-01 1. 07E 03 O.OOE-01 6.88E 03 AG llOM 3.75E 01 2.73E 01 l.81E 01 O.OOE-01 3.91E 01 O.OOE-01 1. 42E 03 TE 125M 8.77E 02 2.93E 02 l.19E 02 2.95E 02 O.OOE-01 O.OOE-01 4.18E 02 TE 127M 2.20E 03 7.30E 02 2.66E 02 6.36E 02 5.42E 03 O.OOE-01 8.88E 02 TE 127 3. 76E 01 1. 26E 01 8.09E 00 3.06E 01 9.lBE 01 O.OOE-01 7.90E 02 TE 129M 3. 76E 03 l.29E 03 5.79E 02 1. 44E 03 9.41E 03 O.OOE-01 2.25E 03 TE 129 1. 07E 01 3.68E 00 2. 49E 00 8.95E 00 2.66E 01 O.OOE-01 8.54E 02 TE 131M 5,72E 02 2.30E 02 1. 90E 02 4.66E 02 1. SSE 03 O.OOE-01 3.87E 03 TE 131 6.62E 00 2.45E 00 l.86E 00 5.91E 00 l.69E 01 O.OOE-01 2.67E 02 TE 132 7.82E 02 3.87E 02 3.62E 02 5. 72E 02 2.42E 03 O.OOE-01 l.43E 03 I 130 2. 26E 02 4.97E 02 l.99E 02 5.57E 04 5.45E 02 O.OOE-01 1. 06E 02 I 131 l.35E 03 l.59E 03 7.00E 02 5.23E 05 1. 86E 03 O.OOE-01 5.68E 01 I 132 6.24E 01 1. 27E 02 4.SlE 01 5.94E 03 1. 41E 02 O.OOE-01 l.03E 02 I 133 4.70E 02 6.BSE 02 2.0lE 02 l.25E 05 8.0SE 02 O.OOE-01 l.16E 02 I 134 3.27E 01 6. 70E 01 2.38E 01 l.56E 03 7.49E .01 O.OOE-01 6.92E 01 I 135 1. 37E 02 2. 72E 02 9.93E 01 2.44E 04 3.04E 02 O.OOE-01 9. 86E 01 cs 134 1. 42E 04 2.64E 04 2.67E 03 O.OOE-01 6.81E 03 2.42E 03 7.19E 01 cs 136 1. 73E 03 5.0BE 03 1. 90E 03 O.OOE-01 2.02E 03 4.14E 02 7. 71E 01 cs 137 l.96E 04 2.30E 04 l.63E 03 O.OOE-01 6.17E 03 2.SOE 03 7.19E 01 cs 138 l.BlE 01 2.94E 01 l.43E 01 0 .. OOE-01 l.47E 01 2.29E 00 4.70E 01 BA 139 3.31E 1 01 2.20E-02 9.59E-01 O.OOE-01 l.32E-02 l.33E-02 2.lOE 03 BA 140 6.43E 03 6.43E 00 3'.31E 02 O.OOE-01 1. 53E 00 3.95E 00 l.SBE 03 BA 141 l.60E 01 1. 09E-02 5.04E-Ol O.OOE-01 6.SBE-03 6.66E-03 l.95E 02 BA 142 6.92E 00 5.76E-03 3.41E-01 O.OOE-01 3.31E-03 3.48E-03 2.86E 01 LA 140 7.94E-01 3.13E-01 8.0SE-02 O.OOE-01 O.OOE-01 O.OOE-01 3.68E 03 LA 142 4.14E-02* 1. 52E-02 3.64E-03 O.OOE-01 O.OOE-01 O.OOE-01 2.SBE 03 CE 141 2. 96E 00 1. BlE 00 2.13E-01 0. OOE-0:\. 5,57E-01 O.OOE-01 9.33E 02 CE 143 5.57E-01 3.69E 02 4'.21E-02 O.OOE::-01 1. OBE-01 O.OOE-01 2 .16E 03 CE 144 l.12E 02 4.59E 01 6.28E 00 O.OOE-01 1. SSE 01 O.OOE-01 6. 43E 03 PR 143 3.06E 00 l.14E 00 1. 52E-01 O.OOE-01 4.25E-Ol O.OOE-01 l.61E 03 PR 144 l.03E-02 3.99E-03 5.19E-04 O.OOE-01 1. 44E-03 O.OOE-01 1. SSE 02 ND 147 2.0BE 00 2.14E 00 l.31E-01 O.OOE-01 8.24E-01 O.OOE-01 1. 35E 03 w 187 3.40E 01 2.36E 01 8.16E 00 O.OOE-01 O.OOE-01 O.OOE-01 l.39E 03

Revision: 9 AP 07B~003 OFFSITE DOSE CALCULATION MANUAL Information Use IPage 116 of 160 ATTACHMENT A

(Page 108 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.4-4 (cont'd)

SITE RELATED DOSE COMMITMENT FACTOR AIT MREM/HR PER µCI/ML INFANT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 4.lSE-01 3.74E-02 2. llE-02 O.OOE-01 7.45E-02 O.OOE-01 1.0SE 03 Sb 124 8.05E 02 1.19E 01 2.49E 02 2.14E 00 O.OOE-01 5.04E 02 2.48E 03 Sb 125 4.63E 02 4.48E 00 9.52E 01 5.79E-00 O.OOE-01 2.90E 02 6.17E 02 Sb 126 3.03E 02 5.94E 00 1,09E 02 2.33E 00 O.OOE-01 1. 91E 02 3.14E 03 Co . 57 O.OOE-01 4.33E 01 7.03E 01 O.OOE-01 O.OOE-01 O.OOE-01 l.47E 02

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use age 117.of 160 ATTACHMENT A (Page 109 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-1 INHALATION DOSE PARAMETER FOR THE CHILD, PI MREM/YR per µCi/M 3

1. 12E 03 RU-103 6.62E 05 C-14 3.59E 04 RU-105 9.95E 04 NA-24 1. 61E 04 RU-106 l.43E 07 P-32 2.60E 06 AG-llOM 5.48E 06 CR-51 1. 70E 04 TE-125M 4.77E 05 MN-54 l.58E 06

TE-127M l.48E 06 MN-56 1. 23E 05 TE-127 5.62E 04*

FE-55 l. llE 05 TE-129M l.76E 06 FE-59 l.27E 06 TE-129 2.55E 04 C0-58 l.llE 06 TE-131M 3.0BE 05 C0-60 7.07E 06 TE-131 2.05E 03 NI-'-63 8.21E 05 TE-132 3.77E 05

NI-65 8.40E 04 I-130 1. 85E 06 CU-64 3.67E 04 I-131 1. 62E 07 ZN-65 9.95E 05 I-132 1. 94E 05 ZN-69 l.02E 04 I-133 3.85E 06 BR-83 4.74E 02 I-134 5.07E 04 BR-84 5.48E 02 I-135 7.92E 05 BR-85 2.53E 01 CS-134 l.OlE 06 RB-86 1. 98E 05 CS-136 1. 71E 05 RB-88 5.62E 02 CS-137 9.07E 05 RB-89 3.45E 02 CS-138 8.40E 02 SR-89 2.16E 06 BA-139 5.77E 04 SR-90 1. OlE .08 BA-140 \ 1. 74E 06 SR-91 1. 74E 05 BA-14.1 2.92E 03 SR-92 2 . .42E 05 BA-142 1. 64E 03 Y-90 2.68E 05 LA-140 2.26E 05 Y-91M 2.BlE 03 LA-142 7.59E 04 Y-92 2.39E 05 CE-141 5. 44.E 05 Y-93 3.89E 05 CE-143 1. 27E 05 ZR-95 2.23E 06 CE-144 l.20E 07 J 3/18 ZR-9'7 3.51E 05 PR-143 4.33E 05 NB-95 6.14E 05 PR-144 1. 57E 03 M0-99 1. 35E 05 ND-147 3.28E 05 TC-99M 4.BlE 03 W-187 9.lOE 04 TC-101 5.85E 02 NP-239 6.40E 04

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use rage 118 of 160 ATTACHMENT A (Page 110 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 5-2 INHALATION PATHWAY FACTOR MREM/YR PER µCI/M 3 ADULT (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE 01 1. 26E 03 1. 26E 03 l.26E 03 l.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 NA 24 1. 02E 04 l.02E 04 l.02E 04 l.02E 04 1. 02E 04 l.02E 04 . l.02E 04 p 32 l.32E 06 7.71E 04 5.0lE 04 O.OOE-01 O.OOE-01 O.OOE-01 8.64E 04 CR 51 O.OOE 01 O.OOE 01 1. OOE 02 5.95E 01 2.28E 01 1. 44E 04 3.32E 03 MN 54 O.OOE 01 3. 96E 04 6.30E 03 O.OOE-01 9.84E 03 l.40E 06 7.74E 04 MN 56 O.OOE 01 1. 24E 00 l.83E-00 O.OOE-01 1. 30E 00 9.44E 03 2.02E 04 FE 55 2. 46E 04 l.70E 04 3.94E 03 O.OOE-01 O.OOE-01 7.21E 04 6.03E 03 FE 59

l.18E 04 2.78E 04 l.06E 04 O.OOE-01 O.OOE-01 l.02E 06 l.88E 05 co 58 O.OOE 01 1. 58E 03 2.07E 03 O.OOE-01 O.OOE-01 9.28E 05 l.06E 05 co 60 O.OOE 01 l.15E 04 l.48E 04 O.OOE-01 O.OOE-01 5.97E 06 2.85E 05 NI 63 4.32E 05 3.14E 04 l.45E 04 O.OOE-01 O.OOE-01 l.78E 05 1. 34E 04 NI 65 1. 54E 00 2.lOE-01 9.12E-02 O.OOE-01 O.OOE-01 5.60E 03 1. 23E 04 cu 64 O.OOE 01 l.46E 00 6.15E-01 O.OOE-01 4.62E 00 6.78E 03 4.90E 04 ZN 65 3.24E"o4 1. 03E 05 4. 66E 04 O.OOE-01 6.90E 04 8.64E 05 5.34E 04 ZN 69 3.38E-02 6.51E-02 4.52E-03 O.OOE-01 4.22E-02 9.20E 02 l.63E 01 BR 83 O.OOE-01 o*. OOE-01 2.41E 02 O.OOE-01 O.OOE-01 O.OOE-01 2.32E 02 BR 84 O.OOE-01 O.OOE-01 3.13E 02 O.OOE-01 O.OOE-:-01 O.OOE-01 l.64E-03 BR 85 O.OOE-01 O.OOE-01 l.28E 01 O.OOE-01 O.OOE-01 O.OOE-01 8.00E-15 RB 86 O.OOE-01 1. 35E 05 5.90E 04 O.OOE-01 O.OOE-01 O.OOE-01 l.66E 04 RB 88 O.OOE-01 3 .*87E 02 1. 93E 02 O.OOE-01 O.OOE-01 O.OOE-01 3.34E-09 RB 89 O.OOE-01 2.56E 02 l.70E 02 O.OOE-01 O.OOE-01 O.OOE-01 9.28E-12 SR 89 3.04E 05 O.OOE-01 8.72E 03 O.OOE-01 O.OOE-01 1. 40E 06 3.50E 05 SR 90 9.92E 07 O.OOE-01 6.lOE 06 O.OOE-01 O.OOE-01 9.60E 06 7.22E 05 SR 91 6.19E 01 O.OOE-01 2.50E 00 O.OOE-01 O.OOE-01 3.65E 04 1. 91E 05 SR 92 6.74E 00 O.OOE-01 2.91E-01 O.OOE-01 O.OOE-01 l.65E 04 4.30E 04 y 90 2.09E 03 O.OOE-01 5.61E 01 O.OOE-01 O.OOE-01 1. 70E' 05 5.06E 05 y 91M 2.61E-01 O.OOE-01 l.02E-02 O.OOE-01 O.OOE-01 l.92E 03 1. 33E 00 y 91 4.62E 05 O.OOE-01 1. 24E 04 O.OOE-01 O.OOE-01 l.70E 06 3.85E 05 y 92 1. 03E 01 O.OOE-01 3.02E-01 O.OOE-01 O.OOE-01 . 1. 57E 04 7.35E 04 y 93 9.44E 01 O.OOE-01 2.61E 00 O.OOE-01 O.OOE-01 4.85E 04 4.22E 05 ZR 95 l.07E 05 3.44E 04 2.33E 04 O.OOE-01 5.42E 04 l.77E 06 1. 50E 05 ZR 97 9.68E 01 l.96E 01 9.04E 00 O.OOE-01 2.97E 01 7.87E 04 5.23E 05 NB 95 l.41E 04 7.82E 03 4.21E 03 O.OOE-01 7.74E 03 5.05E 05 1. 04E 05 MO 99 O.OOE-01 1. 21E 02 2.30E 01 O.OOE-01 2.91E 02 9.12E 04 2.48E 05 TC 99M l.03E-03 2.91E-03 3.70E-02 O.OOE-01 4.42E-02 7.64E 02 4.16E 03

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use IPage 119 of 160 ATTACHMENT A (Page 111 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-2 (cont'd)

INHALATION PATHWAY FACTOR MREM/YR PER µCI/M 3 ADULT (RI FACTORS)

NUCLIDE* BONE LIVER T BODY THYROID KIDNEY LUNG GT-LLI TC 101 4.lBE-05 6.02E-05 5.90E-04 O.OOE-01 1.0BE-03 3.99E 02 1.09E-ll RU 103 1. 53E 03 O.OOE-01 6.SBE 02 O.OOE-01 5.83E 03 5.0SE 05 1. lOE 05 RU 105 7.90E-01 O.OOE-01 3. llE-01 O.OOE-01 l.02E 00 1.lOE 04 4.82E 04 RU 106 6.91E 04 O.OOE-01 8.72E 03 O.OOE-01 1.34E 05 9.36E 06 9.12E 05 AG 110M 1. QBE 04 1. ODE 04 5.94E 03 O.OOE-01 1.97E 04 4.63E 06 3.02E 05 TE 125M 3.42E 03 1. SSE 03 4.67E 02 1. OSE 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.SBE 04 9.60E 05 1.SOE 05 TE 127 1.40E 00 6.42E-01 3.lOE-01 1.06E 00 5.lOE 00 6.51E 03 5.74E 04 TE 129M 9. 76E 03 4.67E 03 1. 58E 03 3.44E 03 3.66E 04 l.16E 06 3.83E 05 TE 129 4.98E-02 2.39E-02 1. 24E-02 3.90E-02 1. 87E-01 1. 94E 03 1. 57E 02 TE 131M 6.99E 01 4.36E 01 2.90E 01 5.50E 01 3.09E 02 1.46E 05 5. 56E 05 TE 131 1. llE-02 5.95E-03 3.59E-03 9.36E-02 4.37E-02 1.39E-03 1. 84E 01 TE 132 2. 60E 02 2.lSE 02 1.62E 02 1. 90E 02 l.46E 03 2.BBE 05 5.lOE 05 I 130 4.SBE 03 1. 34E 04 5.28E 03 1.14E 06 2.09E 04 O.OOE-01 7.69E 05 I 131 2.52E 04 3.SBE 04 2.0SE 04 l.19E 07 6.13E 04 O.OOE-01 6.28E 03 I 132 l.16E 03 3. 26E 03 1.16E 03 1.14E 05 5.lBE 03 O.OOE-01 4.06E 02 I 133 8.64E 03 1.48E 04 4.52E 03 2.lSE 06 2.SBE D4 O.OOE-01 8.BBE 03 I 134 6.44E 02 1.73E 03 6.lSE 02 2.98E 04 2.75E 03 O.OOE-01 1.0lE 00 I 135 2.68E 03 6.98E 03 2.57E 03 4.48E 05 1. llE 04 O.OOE-01 5.25E 03 cs 134 3.73E 05 8.48E 05 7.28E 05 O.OOE-01 2.87E 05 9.76E 04 1. 04E 04 cs 136 3.90E 04 1. 46E 05 1. lOE 05 O.OOE-01 8.56E 04 1. 20E 04 1.17E 04 cs 137 4.78E 05 6.21E 05 4.28E 05 O.OOE-01 2.22E 05 7.52E 04 8.40E 03 cs l3B 3.31E 02 6.21E 02 3.24E 02 O.OOE-01 4.BOE 02 4.86E 01 1.86E-03 BA 139 9.36E-01 6.66E-04 2.74E-02 O.OOE-01 6.22E-04 3. 76E 03 8.96E 02 BA 140 3.90E 04 4.90E 01 2.57E 03 O.OOE-01 1. 67E 01 1. 27E 06 2.18E 05 BA 141 1. OOE-01 7.53E-05 3.36E-03 O.OOE-01 7.00E-05 1.94E 03 1.16E-07 BA 142 2.'63E-02 2.70E-05 1. 66E-03 O.OOE-01 2.29E-05 1.19E 03 1. 57E-16 LA 140 3.44E 02 1. 74E 02 4.SBE 01 0. OOE-01

O.OOE-01 l.36E 05 4.SBE 05 LA 142 6.83E-01 3.lOE-01 7.72E-02 O.OOE-01 O.OOE-01 6.33E 03 2.llE 03 CE 141 1..99E 04 1. 35E 04 1. 53E 03 O.OOE-01 6.26E 03 3.62E 05 1.20E 05 CE 143 1. 86E 02 1. 38E 02 1.53E 01 O.OOE-01 6.0BE 01 7.98E 04 2. 26E 05 CE 144 3.43E 06 1.43E 06 1.84E 05 O.OOE-01 8.48E 05 7.78E 06 8.16E 05 PR 143 9.36E 03 3.75E 03 4.64E 02 O.OOE-01 2.16E 03 2.BlE 05 2.00E 05 PR 144 3.lOE-02 1.25E-02 1. 53E-03 O.OOE-01 7.0SE-03 1. 02E 03 2.lSE-08 ND 147 5.27E 03 6.lOE 03 3.65E 02 O.OOE-01 3.56E 03 2.21E 05 1. 73E 05 w 187 8.48E 00 7.0BE 00 2.48E 00 O.OOE-01 O.OOE-01 2.90E 04 1.SSE 05 NP 239 2.30E 02 2.26E 01 1. 24E 01 O.OOE-01 7.00E 01 . 3. 76E 04 1.19E 05

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use age 120 of 160 ATTACHMENT A (Page 112 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-3 INHALATION PATHWAY FACTOR MREM/YR PER µCI/M 3 TEEN ( RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 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 NA 24 1.38E 04 1. 38E 04 1. 38E 04 1. 38E 04 1. 38E 04 1.38E 04 1. 38E 04 p 32 1.89E 06 1.lOE 05 7 .16E 04 O.OOE-01 O.OOE-01 O.OOE-01 9.28E 04 CR 51 O.OOE-01 O.OOE-01 1. 35E 02 7.50E 01 3.07E 01 2.lOE 04 3.00E 03 MN 54 O.OOE-01 5.llE 04 8.40E 03 O.OOE-01 1. 27E 04 1. 98E 06 6.68E 04 MN 56 O.OOE-01 1.70E 00 2.52E-01 O.OOE-01 1. 79E 00 1.53E 04 5.74E 04 FE 55 3.34E 04 2.38E 04 5.54E 03 O.OOE-01 O.OOE-01 1.24E 05 6.39E 03 FE 59 1.59E 04 3.70E 04 1. 43E 04 O.OOE-01 O.OOE-01 1.53E 06 1. 78E* 05 co 58 O.OOE-01 2.07E 03 2.78E 03 O.OOE-01 O.OOE-01 1.\ 34E 06 9.52E 04 co 60 O.OOE-01 1. 51E 04 1. 98E 04 O.OOE-01 O.OOE-01 8. 72E 06 2.59E 05 NI 63 5.BOE 05 4.34E 04 1.98E 04 O.OOE-01 O.OOE-01 3.07E 05 1. 42E 04 NI 65 2.18E 00 2.93E-01 1. 27E-01 O.OOE-01 O.OOE-01 9.36E 03 3.67E 04 cu 64 O.OOE-01 2.03E 00 8.48E-01 O.OOE-01* 6.41E 00 1.llE 04 6.14E 04 ZN 65 3.86E 04 1. 34E 05 6.24E 04 O.OOE-01 8.64E 04 l.24E 06 4. 66E 04 ZN .69 4.83E-02 9.20E-02 6.46E-03 O.OOE-01 6.02E-02 1. SSE 03 2.85E 02 BR 83 O.OOE-01 O.OOE-01 3.44E 02 O.OOE-01 O.OOE-01 O.OOE-01 8.00E-15 BR 84 O.OOE-01 O.OOE-01 4.33E 02 O.OOE-01 O.OOE-01 O.OOE-01 8.00E-15 BR 85 O.OOE-01 O.OOE-01 1.83E 01 O.OOE-01 O.OOE-01 O.OOE-01 8.00E-15 RB 86 O.OOE-01 1.90E 05 8.40E 04 O.OOE-01 O.OOE-01 O.OOE-01 1.77E 04 RB 88 O.OOE-01 5.46E 02 2. 72E 02 O.OOE-01 0;00E-01 O.OOE-01 2.92E-05 RB 89 O.OOE-01 3.52E 02 2.33E 02 O.OOE-01 O.OOE-01 O.OOE-01 3.38E-07 SR 89 4.34E 05 O.OOE-01 1. 25E 04 O.OOE-01 O.OOE-01 2.42E 06 3. 71E 05 SR 90 1. 08E 08 O.OOE-01 6.68E 06 O.OOE-01 O.OOE-01 1.65E 07 7.65E 05 SR 91 8.80E 01 O.OOE-01 3. 51E 00 O.OOE-01 O.OOE-01 6.07E 04 2.59E 05 SR 92 9.52E 00 O.OOE-01 4.06E-01 O.OOE-01 O.OOE-01 2.74E 04 1.19E 05 y 90 2.98E 03 O.OOE-01 8.00E 01 O.OOE-01 O.OOE-01 2.93E 05 5.59E 05 y 91M 3.70E-01 O.OOE-01 1. 42E-02 O.OOE-01 O.OOE-01 3.20E 03 3.02E 01 y 91 6.61E 05 O.OOE-01 1'.77E 04 O.OOE-01 O.OOE-01 2.94E 06 4.09E 05 y 92 1.47E 01 O.OOE-01 4.29E:..01 O.OOE-01 O.OOE-01 2.68E 04 1.65E 05 y 93 1. 35E 02 O.OOE-01 3. 72E 00 O.OOE-01 O.OOE-01 8.32E 04 5.79E 05 ZR 95 1. 46E 05 4.58E 04 3.15E 04 O.OOE-01 6.74E 04 2.69E 06 1. 49E 05 ZR 97 1. 38E 02 2.72E 01 1. 26E 01

0. OOE-01 4.12E 01 1.30E 05 6.30E 05 NB 95 1. 86E 04 1. 03E 04 5.66E 03 O.OOE-01 1.00E 04 7.51E 05 9.68E 04 MO 99 O.OOE-01 1. 69E 02 3.22E 01 O.OOE-01 4. llE 02 1.54E 05 2.69E 05 TC 99M 1. 38E-03 3.86E-03 4.99E-02 O.OOE-01 5.76E-02 l.15E 03 6.13E 03

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use !Page 121 of 160 ATTACHMENT A (Page 113 of 152)

OFFSITE DOSE CALCULATION MANUAL

. TABLE A. 5-3 (cont'd)

INHALATION PATHWAY FACTOR MREM/YR PER µCI/M 3 TEEN ( RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 5.92E-05 8.40E-05 8.24E-04 O.OOE-01 1. 52E-03 6.67E 02 8.72E-07 RU 103 2.lOE 03 O.OOE-01 8.96E 02 O.OOE-01 7.43E 03 7.83E 05 1.09E 05 RU 105 1.12E 00 O.OOE-01 4.34E-01 O.OOE-01 1.41E 00 1.82E 04 9.04E 04 RU 106 9.84E 04 O.OOE-01 1. 24E 04 O.OOE-01 L90E 05 1.61E 07 9.60E 05 AG 110M 1.38E 04 1. 31E 04 7.99E 03 O.OOE-01 2.50E 04 6.75E 06 2. 7_3E 05 TE 125M 4.BBE 03 2.24E 03 6.74E 02 l.40E 03 O.OOE-01 5.36E 05 7.50E 04 TE 127M *1.BOE 04 8.16E 03 2.lBE 03 4.38E 03 6.54E 04 1. 66E 06 l.59E 05 TE 127 2.0lE 00 9.12E-01 4.42E-01 1. 42E 00 7.28E 00 l.12E 04 8.0BE 01 TE 129M 1. 39E 04 6.58E 03 2.25E 03 4.58E 03 5.19E 04 1.98E 06 4.05E 05 TE 129 7.lOE-02 3.38E-02 1. 76E-02 5.lBE-02 2.66E-01 3.30E 03 1.62E 03 TE 131M 9.84E 01 6.0lE 01 4.20E 01 7.25E 01 4.39E 02 2,38E 05 6. 21E 05 TE 131 1. SBE-02 8.32E-03 5.04E-03 1. 24E-02 6.lBE-02 2.34E 03 1. 51E 01 TE 132 3.60E 02 2.90E 02 2.19E 02 2. 46E 02 1.95E 03 4.49E 05 4.63E 05 I 130 6.24E 03 1.79E 04 7.17E 03 1.49E 06 2.75E 04 O.OOE-01 9.12E 03 I 131 3.54E 04 4. 91E 04 2.64E 04 1. 46E 07 8.40E 04 O.OOE-01 6.49E 03 I 132 1.59E 03 4.38E 03 1. SSE 03 l.51E 05 6.92E 03 O.OOE-01 1. 27E 03 I 133 1. 22E 04 2.05E 04 6.22E 03 2.92E 06 3.59E 04 O.OOE-01 1. 03E 04 I 134 8.BBE 02 2.32E 03 8.40E 02 3.95E 04 3.66E 03 O.OOE-01 2.04E 01 I 135 3.70E 03 9.44E 03 3.49E 03 6.21E 05 1.49E 04 O.OOE-01 6.95E 03 cs 134 5.02E 05 1.13E 06 5.49E 05 O.OOE-01 3.75E 05 1.46E 05 9. 76E 03 cs 136 5.15E 04 1.94E 05 1.37E 05 O.OOE-01 l. lOE 05 1.78E 04 l.09E 04 cs 137 6.70E 05 8.48E 05 3.11E 05 O.OOE-01 3.04E 05 1. 21E 05 8.48E 03 cs 138 4.66E 02 8.56E 02 4. 46E 02 O.OOE-01 6.62E 02 7.87E 01 2.70E-01 BA 139 1. 34E 00 9.44E-04 3.90E-02 O.OOE-01 8.BBE-04 6.46E 03 6.45E 03 BA 140 5.47E 04 6.70E 01 3.52E 03 O.OOE-01 2.28E 01 2.03E 06 2.29E 05 BA 141 1.42E-01 1. 06E-04 4.74E-03 O.OOE-01 9.84E-05 3.29E 03 7.46E-04 BA 142 3.70E-02 3.70E-05 2.27E-03 Q.OOE-01 3.14E-05 1. 91E 03 4.79E-10 l

LA 140 4.79E 02 2.36E 02 6.26E 01 O.OOE-01 O.OOE-01 ,2 .14E 05 4.87E 05 LA 142 9.60E-01 4.25E-01 1. 06E-01 O.OOE-01 O.OOE-01 l.02E 04 1.20E 04 CE 141 2.84E 04 1.90E 04 2.17E 03 O.OOE-01 8.BBE 03 6.14E 05 1.26E 05 CE 143 2. 66E 02 1.94E 02 2 .16E 01 O.OOE-01 8.64E 01 1.30E 05 2.55E 05 CE 144 4.89E 06 2.02E 06 2.62E 05 O.OOE-01 1.21E 06 1. 34E 07 8.64E 05 PR 143 1. 34E 04 5.31E 03 6.62E 02 O.OOE-01 3.09E 03 4.83E -05 2.14E 05 PR 144 4.30E-02 1. 76E-02 2.lBE-03 O.OOE-01 1.0lE-02 1.75E 03 2.35E-04 ND 147 7. 86E 03 8. 56E 03 5.13E 02 O.OOE-01 5.02E 03 3.72E 05 1. 82E 05 w 187 1. 20E 01 9. 76E 00 3.43E, 00 O.OOE-01 O.OOE-01 4.74E 04 l.77E 05 NP 239 3.38E 02 3.19E 01 '* 1. 77E 01 O.OOE-01 1. ODE 02 6.49E 04 1.32E 05

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use ~age 122 of 160 ATTACHMENT A (Page 114 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-4 INHALATION PATHWAY FACTOR MREM/YR PER µCI/M 3 CHILD (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

H 3 O.OOE-01 1.12E 03 1.12E 03 l.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 NA 24 1. 61E 04 1.61E 04 1.61E 04 1. 61E 04 1.61E 04 1. 61E 04

1.61E 04 p 32 2.60E 06 1.14E 05 9.88E 04 O.OOE-01 O.OOE-01 O.OOE-01 4.22E 04 CR 51 O.OOE-01 O.OOE-01 1. 54E 02 8.55E 01 2.43E 01 1.70E 04 1. 08E 03 .

MN 54 O.OOE-01 4.29E 04 9.51E 03 O.OOE-01 1.00E 04 1.58E 06 2.29E 04 MN 56 O.OOE-01 1.66E 00 3.12E-01 O.OOE-01 1.67E 00 1.31E 04 1.23E 05 FE 55 4.74E 04 2.52E 04 7.77E 03 O.OOE-01 O.OOE-01 1. llE 05 2.87E 03 FE 59 2.07E 04 3.34E 04 1.67E 04 O.OOE-01 O.OOE-01 1. 27E 06 7.07E 04 co 58 O.OOE-01 1. 77E 03 3.16E 03 O.OOE-01 O.OOE-01 1.llE 06 3.44E 04 co 60 O.OOE-01 1. 31E 04 2.26E 04 O.OOE-01 O.OOE-01 7.07E 06 9-. 62E 04 NI 63 8. 21E 05 4.63E 04 2.80E 04 O.OOE-01 O.OOE-01 2.75E 05 6.33E 03 NI 65 2.99E 00 2. 96E-01 1.64E-01 O.OOE-01 O.OOE-01 8.18E 03 8.40E 04 cu 64 O.OOE-01 1. 99E 00 1.07E 00 O.OOE-01 6.03E 00 9.58E 03 3.67E 04 ZN 65 4. 26E 04 1.13E 05 7.03E 04 O.OOE-01 7.14E 04 9.95E 05 1. 63E 04 ZN 69 6.70E-02 9.66E~02 8.92E-03 O.OOE-01 5.85E-02 1.42E 03 1.02E 04 BR 83 O.OOE-01 O.OOE-01 4.74E 02 O.OOE-01 O.OOE-01 O.OOE-01 3.70E-15 BR 84 O.OOE~o1 O.OOE-01 5. 48E 02 O.OOE-01 O.OOE-01 O.OOE-01 3.70E-15 BR 85 O.OOE-01 O.OOE-01 2.53E 01 O.OOE-01 O.OOE-01 O.OOE-01 3.70E-15 RB 86 O.OOE-01 1. 98E 05 l.14E 05 O.OOE-01 O.OOE-01 O.OOE-01 7.99E 03 RB 88 O.OOE-01 5.62E 02 3.66E 02 O.OOE-01 O.OOE-01 O.OOE-01 1. 72E 01 RB 89 O.OOE-01 3.45E 02 2.90E 02 O.OOE-01 O.OOE-01 O.OOE-01 l.89E 00 SR 89 5.99E 05 O.OOE-01 1. 7.2E 04 O.OOE-01 O.OOE-01 2.16E 06 l.67E 05 SR 90 l.OlE 08 O.OOE-01 6.44E 06 O.OOE-01 O.OOE-01 1.48E 07 3.43E 05 SR 91 1.21E 02 O.OOE-01 4.59E 00 O.OOE-01 O.OOE-01 5.33E 04 1. 74E 05 SR 92 1. 31E 01 O.OOE-01 5.25E-01 O.OOE-01 O.OOE-01 2.40E 04 2.42E 05 y 90 4.llE 03 O.OOE-01 l. llE 02 O.OOE-01 O.OOE-01 2.62E 05 2,68E 05 y 91M 5.07E-01 O.OOE-01 1. 84E-02 O.OOE-01 O.OOE-01 2.81E 03 1. 72E 03 y 91 9.14E 05 O.OOE-01 2.44E 04 O.OOE-01 O.OOE-01 2.63E 06 1. 84E 05 y 92 2.04E 01 O.OOE-01 5.81E-01 O.OOE-01 O.OOE-01 2.39E 04 2.39E 05 y 93 1. 86E 02 O.OOE-01 5.llE 00 O.OOE-01 O.OOE-01 7.44E 04 3.89E 05 ZR 95 1. 90E 05 4.18E 04 3.70E 04 O.OOE-01 5.96E 04 2.23E 06 6. llE 04 ZR 97 1.88E 02 2.72E 01 l.60E 01 O.OOE-01 3.88E 01 1.13E 05 3.51E 05 NB 95 2.35E 04 9.18E 03 6.55E 03 O.OOE-01 8.62E 03 6.14E 05 3.70E 04 MO 99 O.OOE-01 1. 72E 02 4.25E 01 O.OOE-01 3.92E 02 1. 35E 05 1. 27E 05 TC 99M 1. 78E-03 3.48E-03 5.77E-02 O.OOE-01 5.07E-02 9.51E 02 4.81E 03 I

i j

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use age 123 of 160 ATTACHMENT A (Page 115 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 5-4 (cont'd)

INHALATION PATHWAY FACTOR MREM/YR PER µCI/M 3 CHILD (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 8.lOE-05 B. SlE-05 1. OBE-03 O.OOE-01 1.45E-03 5.BSE 02 1.63E 01 RU 103 2.79E 03 O.OOE-01 1. 07E 03 O.OOE-01 7.03E 03 6.62E 05 4.48E 04 RU 105 1. 53E 00 O.OOE-01 5.SSE-01 O.OOE-01 1. 34E 00 1.59E 04 9.95E 04 RU 106 1. 36E 05 O.OOE-01 1. 69E 04 O.OOE-01 1.84E 05 1.43E 07 4.29E 05 AG 110M 1. 69E 04 1.14E 04 9.14E 03 -O.OOE-01 2.12E 04 5.4BE 06 l.OOE 05 TE 125M 6.73E 03 2.33E 03 9.14E 02 l.92E 03 O.OOE-01 4.77E 05 3.38E 04 TE 127M 2.49E 04 8.SSE 03 3.02E 03 6.07E 03 6.36E 04 1.4BE 06 7.14E 04 TE 127 2.77E 00 9. SlE-01 6.lOE-01 1.96E 00 7.07E oo. 1. OOE 04 5.62E 04 TE 129M 1.92E 04 6.SSE 03 3.04E 03 6.33E 03 5.03E 04 1. 76E 06 1. 82E 0_5 TE 129 9.77E-02 3.SOE-02 2.38E-02 7.14E-02 2.57E-01 2.93E 03 2.SSE 04 TE 131M 1. 34E 02 5.92E 01 5.07E 01 9.77E 01 4.00E 02 2.06E 05. 3.0SE 05 TE 131 2.17E-02 8.44E-03 6.59E-03 1. 70E-02 5.BSE-02 2.0SE 03 1. 33E 03 TE 132 4.81E 02 2. 72E 02 2.63E 02 3.17E 02 1.77E 03 3.77E 05 1. 38E 05 I 130 8.lBE 03 1.64E 04 8.44E 03 1. SSE 06 2. 45E 04 O.OOE-01 5.11E 03 I 131 4.81E 04 4;81E 04 *2;73E 04 1.62E 07 7.88E 04 O.OOE-01 2.84E 03 I

I 132* 2.12E 03 4.07E 03 1. SSE 03 1.94E 05 6.25E 03 O.OOE-01 3.20E 03 I 133 1. 66E 04 2.03E 04 7.70E 03 3.SSE 06 3.38E 04 O.OOE-01 5.48E 03 I 134 1.17E 03 2 .16E 03 9.95E 02 5.07E 04 3.30E 03 O.OOE-01 9.SSE 02 I 135 4.92E 03 8.73E 03 4.14E 03 7.92E 05 1. 34E 04 O.OOE-01 4.44E 03 cs 134 6.SlE 05 1. OlE 06 2.25E 05 O."OOE-01 3.30E 05 1. 21E 05 3.BSE 03 cs 136 6.SlE 04 1. 71E 05 l.16E 05 O.OOE-01 9.SSE 04 1. 45E 04 4.18E 03 cs 137 9.07E 05 8.25E 05 1.28E 05 O.OOE-01 2.82E 05 . 1. 04E 05 3.62E 03 cs 138 6.33E 02 8.40E 02 5.SSE 02 O.OOE-01 6.22E 02 6. BlE 01 2.70E 02 BA 139 1. 84E 00 9.84E-04 5.36E-02 O.OOE-01 .8.62E-04 5.77E 03 5.77E 04 BA 140 7.40E 04 6.48E 01 4.33E 03 O.OOE-01 2.11E 01 1. 74E 06 l.02E 05 BA 141 1. 96E-01 1. 09E-04 6.36E-03 O.OOE-01 9.47E-05 2.92E 03 2.75E 02 BA 142 4.99E-02 3.60E-05 2.79E-03 O.OOE-01 2.91E-05 1. 64E 03 2.74E 00 LA 140 6.44E 02 2.25E 02 7.SSE 01 O.OOE-01 O.OOE-01 1. 83E 05 2.26E 05 LA 142 1.29E 00 4 .11E-01 1.29E-01 O.OOE-01 O.OOE-01 8.70E 03 7.59E 04 CE 141 3.92E 04 1. 95E 04 2.90E 03 O.OOE-01 B.SSE 03 5.44E 05 5.66E 04 ,

CE 143 3.66E 02 1.99E 02 2.87E 01 O.OOE-01 8.36E 01 1. lSE 05 1.27E 05 CE 144 6.77E 06 2.12E 06 3. 61E 05 O.OOE-01 1.17E 06 1. 20E 07 3.89E 05 PR 143 1. SSE 04 5.SSE 03 9.14E 02 O.OOE-01 3.00E 03 4.33E 05 9.73E 04 PR 144 5.96E-02 1.BSE-02 3.00E-03 O.OOE-01 9.77E-03 1. 57E 03 1.97E 02 ND 147 1. OBE 04 8.73E 03 6.BlE 02 O.OOE-01 4.BlE 03 3.28E 05 8.21E 04 w 187 l.63E 01 9.66E 00 4.33E 00 O.OOE-01 O.OOE-01 4.11E 04 9.lOE 04 1

NP 239 4.66E 02 3.34E 01 2.35E 01 O.OOE-01 9.73E 01 5.81E 04 6.40E 04

Revision: 9 - AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use a?age 124 of 160 ATTACHMENT A (Page 116 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 5-5 INHALATION PATHWAY FACTOR MREM/YR PER µCI/M 3 INFANT ( RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 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 NA 24 1. 06E 04 1. 06E 04 l.06E 04 1. 06E 04 1.06E 04 1.06E 04 1.06E 04 p 32 2.03E 06 1.12E 05 7.74E 04 O.OOE-01 O.OOE-01 O.OOE-01 1.61E 04 CR 51 O.OOE-01 O.OOE-01 8.95E 01 5.75E 01 1. 32E 01 1.28E 04 3.57E 02 MN 54 O.OOE-01 2.53E 04 4.98E 03 O.OOE-01 4.98E 03 1. OOE 06 7.06E 03 MN 56 O.OOE-01 1. 54E 00 2.21E-01 O.OOE-01 1. lOE 00 1. 25E 04 7.17E 04 FE 55 l.97E 04 l.17E 04 3.33E 03 O.OOE-01 O.OOE-01 8.69E 04 l.09E 03 FE 59 1. 36E 04 2.35E 04 9.48E 03 O.OOE-01 O.OOE-01 1. 02E 06 2.48E 04 co 58 O.OOE-01 1.22E 03 1. 82E 03 O.OOE-01 O.OOE-01 7.77E 05 1. llE 04 co 60 O.OOE-01 8.02E 03 1.18E 04 O.OOE-01 O.OOE-01 4.51E 06 3.19E 04 NI 63 3.39E 05 2.04E 04 1.16E 04 O.OOE-01 O.OOE-01 2.09E 05 2.42E 03 NI 65 2.39E 00 2.84E-01 1.23E-01 O.OOE-01 O.OOE-01 8.12E 03 5.0lE 04 cu 64 O.OOE-01 1.88E 00 7.74E-01 O.OOE-01 3.98E 00 9.30E 03 1. SOE 04 ZN 65 1.93E 04 6.26E 04 3.llE 04 O.OOE-01 3.25E 04 6.47E 05 5.14E 04 ZN 69 5.39E-02 9.67E-02 7.18E-03 O.OOE-01 4.02E-02 1.47E 03 1. 32E 04 BR 83 O.OOE-01 O.OOE-01 3.81E 02 O.OOE-01 O.OOE-01 O.OOE-01 1. 40E~15 BR 84 O.OOE-01 O.OOE-01 4.00E 02 O.OOE-01 0. OOE-01 . O.OOE-01 1. 40E-15 BR 85 O.OOE-01 O.OOE-01 2.04E 01 O.OOE-01 O.OOE-01 O.OOE-01 1. 40E-15 RB 86 O.OOE-01 1.90E 05 8.82E 04 O.OOE-01 O.OOE-01 O.OOE-01 3.04E 03 RB 88

O.OOE-01 5.57E 02 2.87E 02 O.OOE-01 O.OOE-01 O.OOE-01 3.39E 02 RB 89 O.OOE-01 3.21E 02 2.06E 02 O.OOE-01 O.OOE-01 O.OOE-01 6.82E 01 '

SR 89 3.98E 05 O.OOE-01 1.14E 04 O.OOE-01 O.OOE-01 2.03E 06 6.40E 04 SR 90 4.09E 07 O.OOE-01 2.59E 06 O.OOE-01 O.OOE-01 1.12E 07 1. 31E 05 SR 91 9.56E 01 O.OOE-01 3. 46E 00 O.OOE-01 O.OOE-01 5.26E 04 7.34E 04 SR 92 1. 05E 01 O.OOE-01 3.91E-01 O.OOE-01 O.OOE-01 2.38E 04 l.40E 05 y 90 .,,3.29E 03 O.OOE-01 8.82E 01 O.OOE-01 O.OOE-01 2.69E 05 1. 04E 05 y 91M 4.07E-01 O.OOE-01 1.39E-02 O.OOE-01 O.OOE-01 2.79E 03 2.35E 03 y 91 5.88E 05 O.OOE-01 1.57E 04 O.OOE-01 O.OOE-01 2.45E 06 7.03E 04 y 92 1.64E 01 O.OOE-01 4.61E-01 O.OOE-01 O.OOE-01 2.45E 04 1.27E-05 y 93 1. SOE 02 O.OOE-01 4.07E 00 O.OOE-01 O.OOE-01 7.64E 04 l.67E 05 ZR 95 l.15E 05 2.79E 04 2.03E 04 O.OOE-01 3.llE 04 1.75E 06 2*. l 7E 04 ZR 97 1.50E 02 2.56E 01 1.17E 01 O.OOE-01 2.59E 01 1. lOE 05 1. 40E 05 NB 95 1.57E*04 6. 43E 03 3.78E 03 O.OOE-01 4.72E 03 4.79E 05 1. 27E 04 MO 99 O.OOE-01 1.65E 02 3.23E 01 O.OOE-01 2.65E 02 1. 35E 05 4.87E 04 TC 99M 1. 40E-04 2.88E-03 3.72E-02 O.OOE-01 3. llE-02 8.llE 02 2.03E 03

\

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL

Information Use 0 age 125 of 160 ATTACHMENT A (Page 117 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-5 (cont'd)

INHALATION PATHWAY FACTOR MREM/YR PER µCI/M 3 INFANT ( RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 6.SlE-05 8.23E-05 8.12E-04 O.OOE-01 9.79E-04 5. 84.E 02 8.44E 02 RU 103 2.02E 03 O.OOE-01 6.79E 02 O.OOE-01 4.24E 03 5.52E 05 1. 61E 04 RU 105 1. 22E 00 O.OOE-01 4.lOE-01 O.OOE-01 8.99E-01 1.57E 04 4.84E 04 RU 106 8.68E 04 O.OOE-01 1.09E 04 O.OOE-01 1. 07E 05 1.16E 07 1.64E 05 AG 110M 9.98E 03 7.22E 03 5.00E 03 O.OOE-01 1. 09E 04 3.67E 06 3.30E 04 TE 125M 4. 76E 03 1.99E 03 6.SBE 02 1.62E 03 O.OOE-01 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 127 2.23E 00 9.53E-01 4.89E-01 l.BSE 00 4.86E 00 1. 03E 04 2.44E 04 TE 129M 1. 41E 04 6.09E 03 2.23E 03 5.47E 03 3.18E 04 l.68E 06 6.90E 04 TE 129 7.BBE-02 3.47E-02 l;BBE-02 6.75E-02 1. 75E-01. 3.00E 03 2.63E 04 TE 131M 1.07E 02 5.SOE 01 3.63E 01 8.93E 01 2.65E 02 l.99E 05 1.19E 05 TE 131 l.74E-02 8.22E-03 5.00E-03 1.SBE-02 3.99E-02 2.06E 03 8.22E 03 TE 132 3.72E 02 2.37E 02. 1.76E 02 2.79E 02 1.03E 03 3.40E 05 4.41E 04 I 130 6.36E 03 1. 39E 04 5.57E 03 1.60E 06 l.53E 04 O.OOE-01 1. 99E 03 I 131 3.79E 04 4.44E 04 1.96E 04 1.48E 07 5.lBE 04 O.OOE-01 1.06E 03 I 132 1. 69E 03 3.54E 03 1.26E 03 1. 69E 05 3.95E 03 O.OOE-01 1.90E 03 I. 133 1.32E 04 1.92E 04 5.60E 03 3.56E 06 2.24E 04 O.OOE-01 2.16E 03 I 134 9.21E 02 1. SSE 03 6.65E 02 4. 45~ 04 2.09E 03 O.OOE-01 1.29E 03 I 135 3. 86E 03 7.60E 03 2.77E 03 6.96E 05 8.47E 03 O.OOE-01 1. 83E 03 cs 134 3. 96E 05 7.03E 05 7.45E 04 O.OOE-01 1. 90E 05 7.97E 04 1. 33E 03 cs 136 4.83E 04 1. 35E 05 5.29E 04 O.OOE-01 5.64E 04 l. lBE 04 1.43E 03 cs 137 5. 49E 05 6.12E 05 4.SSE 04 O.OOE-01 1.72E 05 7.13E 04 1.33E 03 cs 138 5.0SE 02 7.81E 02 3.98E 02 O.OOE-01 4.lOE 02 . 6. 54E 01 8.76E 02 BA 139 l.48E DO 9.84E-04 4.30E-02 O.OOE-01 5.92E-04 5.95E 03 5.lOE 04 BA 140 5.60E 04 5.60E 01 2.90E 03 O.OOE-01 1. 34E 01 1.60E 06 3.84E 04 BA 141 1. 57E-01 1.0BE-04 4.97E-03 O.OOE-01 6.SOE-05 2.97E 03 4.75E 03 BA 142 3.98E-02 3.30E-05 1. 96E-03 O.OOE-01 l.90E-05 1. SSE 03 6.93E 02 LA 140 5.0SE 02 2.00E 02 5.lSE 01 O.OOE-01 O.OOE-01 1.68E 05 8.48E 04 LA 142 1. 03E 00 3.77E-01 9.04E-02 O.OOE-01 O.OOE-01 8.22E 03 5.95E 04 CE 141 2.77E 04 1. 67E 04 l.99E 03 O.OOE-01 5.25E 03 5.17E 05 2.16E 04 CE 143 2.93E 02 1.93E 02 2.21E Ql O.OOE-01 5.64E 01 1.16E 05 4.97E 04 CE 144 3.19E 06 1. 21E 06 1. 76E 05 O.OOE-01 5.38E 05 9.84E 06 1.48E 05 PR 143 1.40E 04 5.24E 03 6.99E 02 O.OOE-01 1.97E 03 4.33E 05 3.72E 04 PR 144 4.79E-02 1.BSE-02 2. 41E-03 O.OOE-01 6.72E-03 1. 61E 03 4.28E 03 ND 147 7.94E 03 8.13E 03 5.00E 02 O.OOE-01 3.lSE 03 3.22E 05 3.12E 04 w 187 1.30E 01 9.02E 00 3.12E 00 O.OOE-01 O.OOE-01 3.96E 05 3. 56E 04 NP 239 3. 71E 02 3.32E 01 1.BBE 01 O.OOE-01 6.62E 01 5.95E 04 2.49E 04

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 126 of 160 ATTACHMENT A (Page 118 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-6 GRASS-COW-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC ADULT (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 7.63E 02 7.63E 02 7.63E 02 7.63E 02 7.63E 02 7.63E 02 C 14 2.63E 08 5.27E 07 5.27E 07 5.27E 07 5.27E 07 5 27E 07 5.27E 07 NA 24 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 p 32 1. 71E 10 1.06E 09 6.60E 08 O.OOE-01 O.OOE-01 O.OOE-01 l.92E 09 CR 51 O.OOE-01 O.OOE-01 2.86E 04 O.OOE-01 6.30E 03 3.79E 04 7.19E 06 MN 54 O.OOE-01 8.41E 06 1. 61E 06 O.OOE-01 O.OOE-01 O.OOE-01 2.58E 07 MN 56 O.OOE-01 4.16E-03 7.38E-04 O.OOE-01 5.28E-03 O.OOE-01 1.33E-01 FE 55 2.51E 07 1. 73E 07 4.04E 06 O.OOE-01 O.OOE-01 9.67E 06 9.95E 06 FE 59 2.97E 07 6.98E 07 2.68E 07 O.OOE-01 O.OOE-01 1. 95E 07 2.33E 08 co 58 O.OOE-01 4.71E 06 1.06E 07 O.OOE-01 O.OOE-01 O.OOE-01 9.56E 07 co 60 O.OOE-01 l.64E 07 3.62E 07 O.OOE-01 O.OOE-01 O.OOE-01 3.08E 08 NI 63 6.73E 09 4.71E 08 2.26E 08 O.OOE-01 O.OOE-01 O.OOE-01 9.73E 07 NI 65 4.63E-01 6.02E-02 2.75E-02 O.OOE-01 O.OOE-01 O.OOE-01 1.53E 00 cu 64 O.OOE-01 2.39E 04 1.12E 04 O.OOE-01 6.02E 04 O.OOE-01 2.03E 06 ZN 65 1. 37E 09 4.37E 09 1.97E 09 O.OOE-01 2.92E 09 O.OOE-01 2.75E 09 ZN 69 5.22E-12 9.99E-12 6.95E-13 O.OOE-01 6.49E-12 O.OOE-01 1.50E-12 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 2.59E 09 1. 21E 09 O.OOE-01 O.OOE-01 O.OOE-01 5.12E 08 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.45E 09 O.OOE-01 4.16E 07 O.OOE-01 O.OOE-01 O.OOE-01 2.33E 08 '

SR 90 4.68E 10 O.OOE-01 l.15E 10 O.OOE-01 O.OOE-01 O.OOE-01 l.35E 09 SR 91 2.87E 04 O.OOE-01 1.16E 03 O.OOE-01 O.OOE-01 O.OOE-01 1. 37E 05 SR 92 4.90E-01 O.OOE-01 2.12E-02 O.OOE-01 O.OOE-01 O.OOE-01 9.70E 00 y 90 7.07E 01 O.OOE-01 l.90E 00 O.OOE-01 O.OOE-01 O.OOE-01 7.50E 05 y 91M 6.03E-20 O.OOE-01 2.34E-21 O.OOE-01 O.OOE-01 O.OOE-01 1. 77E-19 y 91 8.59E 03 O.OOE-01 2.30E 02 O.OOE-01 O.OOE-01 O.OOE-01 4.73E 06 y 92 5.59E-05 O.OOE-01 1. 63E-0 6 O.OOE-01 O.OOE-01 O.OOE-01 9.79E-01 y 93 2.33E-01 O.OOE-01 6.44E-03 O.OOE-01 O.OOE-01 O.OOE-01 7.39E 03 ZR 95 9.44E 02 3.03E 02 2.05E 02 O.OOE-01 4.75E 02 O.OOE-01 9.59E 05 ZR 97 4.33E-01 8.75E-05 4.00E-02 O.OOE-01 1. 32E-00 O.OOE-01 2.71E 04 NB 95 8. 26E 04 4.59E 04 2.47E 04 O.OOE-01 4.54E 04 O.OOE-01 2.79E 08 MO 99 O.OOE-01 2.48E 07 4. 71E 06 O.OOE-01 5. 61E 07 O.OOE-01 5.74E 07 TC 99M 3.33E 00 9.40E 00 1. 20E 02 O.OOE-01 1. 43E 02 4.60E 00 5.56E 03

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 127 of 160 ATTACHMENT A (Page 119 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-6 (cont'd)

GRASS-COW-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC ADULT ( RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU 103 1. 02E 03 O.OOE-01 4.38E 02 O.OOE-01 3.88E 03 O.OOE-01 1.19E 05 RU 105 8.SBE-04 O.OOE-01 3.39E-04 O.OOE-01 l. llE-02 O.OOE-01 5.25E-01 RU 106 2.04E 04 O.OOE-01 2.58E 03 O.OOE-01 3.94E 04 O.OOE-01 1.32E 06 AG 110M 5.82E 07 5.39E 07 3.20E 07 O.OOE-01 1.06E 08 O.OOE-01 2.20E 10 TE 125M 1.63E 07 5.90E 06 2.lBE 06 4.90E 06 6.63E 07 O.OOE-01 6.SOE 07 TE 127M 4.58E 07 l.64E 07 5.58E 06 1.17E 07 1.86E 08 O.OOE-01 1.54E 08 TE 127 6.54E 02 2.35E 02 1.41E 02 4.84E 02 2.66E 03 O.OOE-01 5.16E 04 TE 129M 6.02E 07 2.25E 07 9.53E 06 2.07E 07 2.51E 08 O.OOE-01 3.03E 08 TE 129 2.84E-10 1. 07E-10 6. 29E-11 2.lBE-10 l.19E-09 O.OOE-01 2.14E-10 TE 131M 3.61E 05 1. 77E 05 1.47E 05 2.BOE 05 1. 79E 06 O.OOE-01 1. 73E 07 TE 131 3.67E-33 1.53E-33 1.16E-33 3.0lE-33 1.61E-32 O.OOE-01 O.OOE-01 TE 132 2.40E 06 1.55E 06 1. 46E 06 1. 72E 06 1. SOE 07 O.OOE-01 7.35E 07 I 130 4.20E 05 1. 24E 06 4.89E 05 1. OSE 08 1. 94E 06 0. OOE...:01 1.07E 06 I 131 2.96E 08 4.24E 08 2.43E 08 1.39E 11 7. 26E 08 O.OOE-01 1.12E 08 I 132 1. 65E-01 4.41E-01 1. 54E-01 1.54E 01 7.02E-01 O.OOE-01 8.28E-02

. I 133 3.87E 06 6.73E 06 2.0SE 06 9.90E 08 l.18E 07 O.OOE-01 6.0SE 06 I 134 2.03E-12 5.52E-12 1. 98E-12 9.57E-11 8.78E-12 O.OOE-01 4.BlE-15 I 135 1.29E 04 3.37E 04 l.24E 04 2.22E 06 5.40E 04 0 .. QQE-01 3.BOE 04 cs 134 5.65E 09 1. 35E 10 l. lOE 10 O.OOE-01 4.35E 09 l.45E 09 2.35E 08 cs 136 2.61E 08 1. 03E 09 7.42E 08 O.OOE-01 5.73E 08 7.86E 07 1.17E 08 cs 137 7.38E 09 1. OlE 10 6.61E 09 O.OOE-01 3.43E 09 l.14E 09 1.95E 08 cs 138 9.16E-24 1. BlE-23 8.97E-24 O.OOE-01 1.33E-23 . 1. 31E-24 7.72E-29 BA 139 4.56E-08 3. 25E-11 1. 34E-09 O.OOE-01 3. 04E-11 1. 84E-11 8.09E-08 BA 140 2.69E 07 3.38E 04 1. 76E 06 O.OOE-01 1.15E 04 1. 93E 04 5.54E 07 BA 141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 142 O.OOE-01 O.OOE-01 o*. OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA 140 4.52E 00 2.28E 00 6.02E-01 O.OOE-01 O.OOE-01 O.OOE-01 1. 67E 05 LA 142 9.39E-:-12 4.27E-12 1. 06E-12 O.OOE-01 O.OOE-01 O.OOE-01 3.12E-08 CE 141 4.84E 03 3.28E 03 3. 72E 02 O.OOE-01 1.52E 03 O.OOE-01 1. 25E 07 CE 143 4 .16E 01 3.07E 04 3.40E 00 O.OOE-01 1.35E 01 O.OOE-01 l.15E 06 CE 144 3.58E 05 1.SOE 05 1.92E 04 O.OOE-01 8.87E 04 O.OOE-01 l.21E 08 PR 143 1. SSE 02 6.33E 01 7.83E 00 O.OOE-01 3.66E 01 O.OOE-01 6:92E 05 PR 144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND 147 9. 46E 01 1. 09E 02 6.55E 00 O.OOE-01 6.40E 01 O.OOE-01 5.25E 05 w 187 6.56E 03 5.49E 03 1. 92E 03 O.OOE-01 O.OOE-01 O.OOE-01 1. BOE 06 NP 239 3.67E 00 3.61E-01 1. 99E-01 O.OOE-01 l.13E 00 O.OOE-01 7.41E 04

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 128 of 160 ATTACHMENT A (Page 120 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-7 GRASS-COW-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC TEEN (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYB,OID KIDNEY LUNG GI-LLI H 3 O.OOE-01 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 C 14 4. 86E 08 9. 72E 07 9. 72E 07 9.72E 07 9. 72E 07 9. 72E 07 9. 72E 07 NA 24 4. 26E 06 4.26E 06 4.26E 06 .4. 26E 06 4.26E 06 4. 26E 06 4.26E 06 p 32 3.15E 10 1.95E 09 1. 22E 09 O.OOE-01 O.OOE-01 O.OOE-01 2.65E 09 CR 51 O.OOE-01 O.OOE-01 4.99E 04 2.77E 04 1.09E 04 7.13E 04 8.39E 06 MN 54 O.OOE-01 1.40E 07 2.78E 06 O.OOE-01 4.lBE 06 O.OOE-01 2.87E 07 MN 56 O.OOE-01 7.37E-03 1. 31E-03 O.OOE-01 9.33E-03 O.OOE-01 4.BSE-01 FE 55 4.45E 07 3 .16E 07 7.36E 06 O.OOE-01 O.OOE-01 2.00E 07 1.37E 07 FE 59 5.lBE 07 1. 21E OB 4.67E 07 O.OOE-01 O.OOE-01 3.BlE 07 2.86E 08 co 58 O.OOE-01 7.94E 06 1. 83E 07 O.OOE-01 O.OOE-01 O.OOE-01 1.09E 08 co 60 O.OOE-01 2.78E 07 6. 26E 07 O.OOE-01 O.OOE-01 O.OOE-01 3.62E 08 NI 63 1.18E 10 8.35E 08 4.0lE 08 O.OOE-01 O.OOE-01 O.OOE-01 1.33E 08 NI 65 8.48E-01 1. OBE-01 4.94E-02 O.OOE-01 O.OOE-01 O.OOE-01 5.BBE 00 cu 64 O.OOE-01 4.25E 04 2.00E 04 O.OOE-01 1.0BE 05 O.OOE-01 3.30E 06 ZN 65 2. llE 09 7.31E 09 3.41E 09 O.OOE-01 4.68E 09 O.OOE-01 3.lOE 09 ZN 69 9.62E-12 1. 83E-11 1. 28E-12 O.OOE-01 1. 20E-11 O.OOE-01 3.38E-11 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 0. OOE-0.1 4.73E 09 2.22E 09 O.OOE-01 O.OOE-01 O.OOE-01 7.00E 08 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 . 0. OOE-01 O.OOE-01 RB 89 O.OOE-01 0 OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.67E 09 O.OOE-01 7.66E 07 O.OOE-01 O.OOE-01 O.OOE-01 3.19E 08 .

SR 90 6.61E 10 O.OOE-01 l.63E 10 O.OOE-01 O.OOE-01 O.OOE-01 1. 86E 09 SR 91 5.27E 04 O.OOE-01 2.lOE 03 O.OOE-01 O.OOE-01 O.OOE-01 2.39E 05 SR 92 8. 96E-01 O.OOE-01 3.82E-02 O.OOE-01 O.OOE~Ol O.OOE-01 2.28E 01 y 90 1. 30E 02 O.OOE-01 3.50E 00 O.OOE-01 O.OOE-01 O.OOE-01 1.07E 06 y 91M 1. llE-19 O.OOE-01 4.22E-21 O.OOE-01 O.OOE-01 O.OOE-01 5.22E-18 y 91 1. SSE 04 O.OOE-01 4.24E 02 O.OOE-01 O.OOE-01 O.OOE-01 6.48E 06 y 92 1.03E-04 O.OOE-01 2.99E-06 O.OOE-01 O.OOE-01 O.OOE-01 2.83E 00 y 93 4.30E-01 O.OOE-01* l. lBE-02 *o.OOE-01 O.OOE-01 O.OOE-01 l.31E 04 ZR 95 l.65E 03 5.21E 02 3.58E 02 iD.OOE-01 7.65E 02 O.OOE-01 1. 20E 06 1

ZR 97 7.89E-01 1. 56E-01 7.19E-02 0.00E-01 2.37E-01 o:ooE-01 4.23E 04 NB 95 1.41E 05 7. 81E 04 4.30E 04 'O.OOE-01 7.57E 04 O.OOE-01 3.34E 08 MO 99 O.OOE-01 4.47E 07 8.53E 06 O.OOE-01 1. 02E 08 O.OOE-01 8.0lE 07

- ). ... tG .. -~-~~ .....s.- 77E *oo .......1; 61E. 01.- ..... 2 ::osE 02 . /0.00E-01 2.40E 02 8.93E 00 1.06E 04

.. . ~

* .. *--* .*... ***** ....... .l

Revision: 9 AP 07B-003 I

OFFSITE DOSE CALCULATION MANUAL Information Use Page 129 -of 160

\

ATTACHMENT A (Page 121 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-7 (cont'd)

GRASS-COW-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC TEEN (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU 103 1. 81E 03 O.OOE-01 7.74E 02 O.OOE-01 6.38E 03 O.OOE-01 1. 51E 05 RU 105 *1. 57E-03 O.OOE-01 6. 08E-0_4 O.OOE-01 1.98E-02 O.OOE-01 1.27E 00 RU 106 3.75E 04 O.OOE-01 4.73E 03 O.OOE-01 7.23E 04 O.OOE-01 1.80E 06 AG 110M 9.63E 07 9.11E 07 5.54E 07 O.OOE-01 1.74E 08 O.OOE-01 2.56E 10 TE 125M 3.00E 07 1. 08E 07 4.02E 06 8.39E 06 O.OOE-01 O.OOE-01 8.86E 07 TE 127M 8.44E 07 2.99E 07 1. OOE 07 2. OlE 07 3.42E 08 O.OOE-01 2.lOE 08 TE 127 1. 21E 03 4.29E 02 2.61E 02 8. 36E 02 4.91E 03 O.OOE-01 9.35E 04 TE 129M 1. lOE 08 4.09E 07 1.74E 07 3.55E 07 4.61E 08 O.OOE-01 4.13E 08 TE 129 5.23E-10 1. 95E-10 1. 27E-10 3.74E-10 2.20E-09 O.OOE-01 2.86E-09 TE 131M 6.57E 05 3.15E 05 2.63E 05 4.74E 05 3.29E 06 O.OOE-01 2.53E 07 TE 131 6.70E-33 2.76E-33 2.09E-33 5.16E-33 2.93E-32 O.OOE-01 5.50E-34 TE 132 4.29E 06 2. 72E 06 2.56E 06 2.87E 06 2.61E 07 O.OOE-01 8. 61E 07 I 130 7.39E 05 2.14E 06 8.54E 05 1. 74E 08 3.26E 06 O.OOE-01 l.64E 06 I 131 5.37E 08 7.52E 08 4.04E 08 2. 2-0E 11 1.30E 09 O.OOE-01 l.49E 08 I 132 2.92E-01 7.65E-01 2.74E-01 2.58E 01 1. 20E 00 O.OOE-01 3.33E-01 I 133 7.07E 06 1. 20E 07 3.66E 06 l.67E 09 2.lOE 07 O.OOE-01 9.08E 06 I 134 3.61E-12 9.58E-12 3.44E-12 1. 60E-10 1.51E-11 O.OOE-01 1.26E-13 I 135 2.28E 04 5.88E 04 2.18E 04 3.78E 06 9.28E 04 O.OOE-01 6.51E 04 cs 134 9.82E 09 2.31E 10 l.07E 10 O.OOE-01 7.34E 09 2.80E 09 2.87E 08 cs 136 4.44E 08 1.75E 09 1.17E 09 O.OOE-01 9.52E 08 1. 50E 08 1.41E 08 cs 137 l.34E 10 1. 78E 10 6.20E 09 O.OOE-01 6. 06E 09 2.35E 09 2.53E 08

. cs 138 1. 66E-23 -3 .19E-23 l.60E-23 O.OOE-01 2.36E-23 2.74E-24 1. 45E-26 BA - 139 8.44E-08 5.94E-11 2.46E-09 O.OOE-01 5. 60E-11 4.09E-11 7.53E-07 BA 140 4.85E 07 5.95E 04 3. 13E O6 O.OOE-01 2.02E 04 4.00E 04 7.48E 07 BA 141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0. OOE-01 . O.OOE-01 LA 140 8.12E 00 3.99E 00 1. 06E 00 O.OOE-01 O.OOE-01 O~OOE-01 2.29E 05 LA 142 1. 69E-11 7.52E-12 1. 87E-12 O.OOE-01 O.OOE-01 O.OOE-01 2.29E-07 CE 141 8.88E 03 5.93E 03 6.81E 02 O.OOE-01 2.79E 03 O.OOE-01 1. 70E 07 CE 143 7. 64E 01 5.56E 04 6.21E 00 O.OOE-01 2.49E 01 O,OOE-01 1.67E 06 CE 144 6.58E 05 2. 72E 05 3.54E 04 O.OOE-01 1.63E 05 O.OOE-01 1.66E 08 PR 143 2.90E 02 l.16E 02 1. 44E 01 o:ooE-01 6.73E 01 O.OOE-01 9.55E 05 PR 144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND 147 1. 82E 02 1. 98E 02 1.19E 01 O.OOE-01 l.16E 02 O.OOE-01 7.15E 05 w 187 1. 20E 04 9.78E 03 3.43E 03 O.OOE-01 O.OOE-01 O.OOE-01 2.65E 06.

NP 239 7. OlE 00 6.61E-01 3.67E-01 O.OOE-01 2.07E 00 O.OOE-01 1.06E 05

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use age 130 of 160 ATTACHMENT A (Page 122 of 152).

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-8 GRASS-COW-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC CHILD (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1. 57E 03 1. 57E 03 C 14 1.19E 09 2.39E 08 2.39E 08 2.39E 08 2.39E 08 2.39E 08 2.39E 08 NA 24 8.86E 06 8.86E 06 8.86E 06 8.86E 06 8.86E 06 8. 8 6E 06 8.86E 06 p 32 7.77E 10 3.64E 09 3.00E 09 O.OOE-01 O.OOE-01 O.OOE-01 2.15E 09 CR 51 O.OOE-01 O.OOE-01 l.02E 05 5.65E 04 1.54E 04 1. 03E 05 5.40E 06 MN 54 O.OOE-01 2.lOE 07 5.59E 06 O.OOE-01 5.88E 06 O.OOE-01 1. 76E 07 MN 56 O.OOE-01 1.29E-02 2.90E-03 O.OOE-01 1. 56E-02 O.OOE-01 1. 86E 00 FE 55 1.12E 08 5.93E 07 l.84E 07 O.OOE-01 O.OOE-01 3.35E 07 1. lOE 07 FE 59 1.20E 08 l.94E 08 9.69E 07 O.OOE-01 Q.* OOE-01 5.64E 07 2.02E 08 co 58 O.OOE-01 l.21E 07 3.71E 07 O.OOE-01 O.OOE-01 O.OOE-01 7.07E 07 co 60 O.OOE-01 4.32E 07 1.27E 08 O.OOE-01 O.OOE-01 O.OOE-01 2.39E 08 NI 63 2.96E 10 1.59E 09 1.0lE 09 O.OOE-01 O.OOE-01 O.OOE-01 1. 07E 08 NI 65 2.07E 00 1.95E-01 1.14E-01 O.OOE-01 O.OOE-01 O.OOE-01 2.39E 01 cu 64 O.OOE-01 7.47E 04 4.51E 04 O.OOE-01 1. 81E 05 O.OOE-01 3.51E 06 ZN 65 4.13E 09 1.lOE 10 6.85E 09 O.OOE-01 6.94E 09 O.OOE-01 1. 93E 09 ZN 69 2.36E-11 3.42E-11 3.16E-12 O.OOE-01 2.07E-10 O.OOE-01 2.15E-09 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 8.77E 09 5.39E 09 O.OOE-01 O.OOE-01 O.OOE-01 5.64E 08 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 6.62E 09 O.OOE-01 l.89E 08 O.OOE-01 O.OOE-01 O.OOE-01 2.56E 08 SR 90 l.12E 11 O.OOE-01 2.83E 10 O.OOE-01 O.OOE-01 O.OOE-01 1. SOE 09 SR 91 l.29E 05 O.OOE-01 4.88E 03 O.OOE-01 O.OOE-01 O.OOE-01 2.85E 05 SR 92 2.19E 00 O.OOE-01 8.78E-02 O.-OOE-01 O.OOE-01 O.OOE-01 4.15E 01 y 90 3.22E 02 O.OOE-01 8.61E 00 O.OOE-01 O.OOE-01 O.OOE-01 9.15E 05 y 91M 2.70E-19 O.OOE-01 9.82E-21 O.OOE-01 O.OOE-01 O.OOE-01 5.29E-16 y 91 3.90E 04 O.OOE-01 1.04E 03 O.OOE-01 O.OOE-01 O.OOE-01 5.20E 06 y 92 2.54E-04 O.OOE-01 7.26E-06 O.OOE-01 O.OOE-01 O.OOE-01 7.33E 00 y 93 1.06E 00 O.OOE-01 2.90E-02 O.OOE-01 0. OOE'-01 O.OOE-01 1. 57E 04 ZR 95 3.83E 03 8.43E 02 7.50E 02 O.OOE-01 1. 21E 03 O.OOE-01 8.79E 05 ZR 97 1.92E 00 2.77E-01 1.64E-01 O.OOE-01 3.98E-01 O.OOE-01 4.20E 04 NB 95 3.18E 05 1.24E 05 8.85E 04 O.OOE-01 1.16E 05 O.OOE-01 2.29E 08 MO 99 O.OOE-01 8.14E 07 2.0lE 07 O.OOE-01 1.74E 08 O.OOE-01 6.73E 07

.:re ...... ':L9M. . .L:32E .Ol _;~. 2., ..5.9E .Ol ....A....30E 02 0. QOE-01 ;3.77E*02 1.32EOL 1.48E 04

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use !Page 131 of 160 ATTACHMENT A (Page 123 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 5-:8 (cont'd)

GRASS-COW-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC CHILD (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU 103 4.28E 03 0 .. OOE-01 l.65E 03 O.OOE-01 1. 08E 04 O.OOE-01 l. llE 05 RU 105 3.83E-03 O.OOE-01 1. 39E-03 O.OOE-01 3.36E-02 O.OOE-01 2.50E 00 RU 106 9.24E 04 o:ooE-01 l.15E 04 O.OOE-01 l .'25E 05 O.OOE-01 l.44E 06 AG llOM 2.09E 08 1. 41E 08 l.13E 08 O.OOE-01 2.63E 08 O.OOE-01 l.68E 10 TE 125M 7.38E 07 2.00E 07 9.84E 06 2.07E 07 O.OOE-01 O.OOE-01 7.12E 07 TE 127M 2.08E 08 5.60E 07 2.47E 07 4.97E 07 5.93E 08 O.OOE-01 l.68E 08 TE 127 2.98E 03 8.03E 02 6.39E 02 2. 06E 03 8.47E 03 O.OOE-01 l .16E 05 TE 129M 2. 71E 08 7.58E 07 4. 21E 07 8.75E 07 7.97E 08 O.OOE-01 3.31E 08 TE 129 1. 29E-09 3.60E-10 3.06E-10 9.21E-10 3.78E-09 O.OOE-01 8.03E-08 TE 131M 1. 60E 06 5.53E 05 5.89E 05 l.14E 06 5.36E 06 O.OOE-01 2.24E 0.7 TE 131 l.64E-32 5.0lE-33 4.89E-33 1. 26E-32 4.97E-32 O.OOE-01 8.64E-32 TE 132 l.02E 07 4.54E 06 5.48E 06 6.61E 06 4.21E 07 O.OOE-01 4.57E 07 I 130 l.73E 06 3. 49E 06 l.80E 06 3.85E 08 5.22E 06 O.OOE-01 l.63E 06 I 131 l.30E 09 l.31E 09 7.45E 08 4.33E ll 2.15E 09 O.OOE-01 l.17E 08 I 132 6.91E-01 1. 27E 00 5.84E-01 5.89E 01 l.94E 00 O.OOE-01 1. 49E 00 I 133 1. 72E 07 2.12E 07 8.04E 06 3.95E 09 3.54E 07 O.OOE-01 8.56E 06 I 134 8.55E-12 1. 59E-ll 7.31E-12 3.65E-10 2.43E-ll O.OOE-01 1. 05E-ll I 135 5. 41E 04 9.73E 04 4.60E 04 8 .-62E 06 l.49E 05 O.OOE-01 7.41E 04 cs 134 2.27E 10 3. 72E 10 7.84E 09 O.OOE-01 l.15E 10 4.13E 09 2.00E 08 cs 136 1. OOE 09 2.76E 09 l.78E 09 O.OOE-01 l.47E 09 2.19E 08

9.69E 07 I

cs 137 3.22E 10 3.09E 10 4.55E 09 O.OOE-01 1. om: 10 3.62E 09 l.93E 08 cs 138 4.03E-23 5.60E-23 3.55E-23 O.OOE-01 3.94E-23 4.24E-24 2.58E-23 BA 139 2.07E-07 l. llE-10 6.0lE-09 O.OOE-01 9. 67E-ll 6.51E-ll 1. 20E-05 BA 140 l.17E 08 1. 03E 05 6.84E 06 O.OOE-01 3.34E 04 6.12E 04 5.94E 07 BA 141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA 140 1. 94E 01 6.80E 00 2.29E 00 O.OOE-01 O.OOE-01 O.OOE-01 l.89E 05 LA 142 4.09E-ll 1. 30E-ll 4.08E-12 O.OOE-01 O.OOE-01 O.OOE-01 2.58E-06 CE 141 2.19E 04 1. 09E 04 l.62E 03 O.OOE-01 .4.78E 03 O.OOE-01 1. 36E 07 CE 143 l.88E 02 .1. 02E 05 l.47E 01 O.OOE-01 4.27E 01 O.OOE-01 l.49E 06 CE 144 l.62E 06 5.09E 05 8.66E 04 O.OOE-01 2.82E 05 O.OOE-01 1. 33E 08 PR 143 7.18E 02 2.16E 02 3.56E 01 O.OOE-01 l.17E 02 O.OOE-01 7.75E 05 PR 144 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND 147 4.47E 02 3.62E 02 2.80E 01 O.OOE-01 l.99E 02 O.OOE-01 5.73E 05 w 187 2.91E 04 l.72E 04 7.73E 03 O.OOE-01 O.OOE-01 O.OOE-01 2.42E 06 NP 239 l.72E 01 1. 24E 00 8.70E-01 0. OOE-01 . 3.58E 00 O.OOE-01 9.16E 04

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 132 of 160 ATTACHMENT A (Page 124 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-9 GRASS-COW-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC INFANT (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 2.38E 03 2.38E 03 2.38E 03 2.38E 03 2.38E 03 2.38E 03 C 14 2.34E 09 5.00E 08 5.00E 08 5.00E 08 5.00E 08 5.00E 08 5.00E 08 NA 24 1. 54E 07 1. 54E 07 1. 54E 07 1. 54E 07 1. 54E 07 1. 54E 07 1. 54E 07 p 32 1. 60E 11 9.42E 09 6.21E 09 O.OOE-01 O.OOE-01 O.OOE-01 2.17E 09 CR 51 O.OOE-01 O.OOE-01 1. 61E 05 1. 05E 05 2.30E 04 2.05E 05 4.70E 06 MN 54 O.OOE-01 3.90E 07 8.84E 06 O.OOE-01 8.64E 06 O.OOE-01 1. 43E 07 MN 56 O.OOE-01 3.15E-02 5.43E-03 O.OOE-01 2.71E-02 O.OOE-01 2. 86E 00 FE 55 1. 35E 08 8.72E 07 2.33E 07 O.OOE-01 O.OOE-01 4.26E 07 1. llE 07 FE 59 2.24E 08 3.92E 08 1. 54E 08 O.OOE-01 O.OOE-01 1.16E 08 1. 87E 08 co 58 O.OOE-01 2.43E 07 6.05E 07 O.OOE-01 O.OOE-01 O.OOE-01 6.04E 07 co 60 0. OOE-'01 8.82E 07 2.08E 08 O.OOE-01 O.OOE-01 O.OOE-01 2.lOE 08 NI 63 3. 4 9E 10 2.16E 09 1. 21E 09 O.OOE-01 O.OOE-01 O.OOE-01 1. 07E 08 NI 65 4.39E 00 4.97E-Oi' 2.26E-01 O.OOE-01 O.OOE-01 O.OOE-01 3.78E 01 cu 64 O.OOE-01 1. 86E 05 8.60E 04 O.OOE-01 3.14E 05 O.OOE-01 3.81E 06 ZN 65 5.55E 09 1. 90E 10 8.78E 09 O.OOE-01 9.23E 09 O.OOE-01 1. 61E 10 ZN 69 5.04E-ll 9.07E-ll 6.75E-12 O.OOE-01 3. 77E-ll 0. OOE-:-01 7.40E-09 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 2.23E 10 1.lOE 10 O.OOE-01 O.OOE-01 O.OOE-01 5.70E 08 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1. 26E 10 O.OOE-01 3.61E 08 O.OOE-01 O.OOE-01 O.OOE-01 2.59E 08 SR 90 1. 22E 11 O.OOE-01 3.lOE 10 O.OOE-01 O.OOE-01 O.OOE-01 1.52E 09 SR 91 2.69E 05 O.OOE-01 9.75E 02 O.OOE-01 O.OOE-01 O.OOE-01 3.19E 05 SR 92 4.66E 00 O.OOE-01 1. 73E-01 O.OOE-01 O.OOE-01 O.OOE-01 5.02E 01 y 90 6.80E 02 O.OOE-:01 1. 82E 01 O.OOE-01 O.OOE-01 O.OOE-01 9.39E 05 y 91M 5.72E-19 O.OOE-01 1.95E-20 O.OOE-01 O.OOE-01 O.OOE-01 1. 91E-15 y 91 7.33E 04 O.OOE-01 1. 95E 03 O.OOE-01 O.OOE-01 O.OOE-01 5.25E 06 y 92 5.39E-04 O.OOE-01 1.51E-05 O.OOE-01 O.OOE-01 O.OOE-01 1. 03E 01 y 93 2.25E 00 O.OOE-01 6.13E-02 O.OOE-01 O.OOE-01 O.OOE-01 1. 78E 04 ZR 95 6.81E 03 1. 66E 03 1.18E 03 O.OOE-01 1.79E 03 O.OOE-01 8. 26E 05 ZR 97 4.06E 00 6.98E-01 3.19E-01 O.OOE-01 7.03E-01 O.OOE-01 4.45E 04 NB 95 5.94E 05 2.45E 05 1.41E 05 O.OOE-01 1. 75E 05 O.OOE-01 2.06E 08 MO 99 O.OOE-01 2.08E 08 4.06E 07 O.OOE-01 3.llE 08 O.OOE-01 6.85E 07 TC 99M 2.75E*Ol 5.68E 01 7.31E 02 O.OOE-01 6.llE 02 2.97E 01 1. 65E 04

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 133 of 160 ATTACHMENT A (Page 125 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-9 (cont'd)

GRASS-COW-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC INFANT (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU 103 8. 67E 03 O.OOE-01 2.90E 03 O.OOE-01 l.BOE 04 O.OOE-01 1. OSE 05 RU 105 8.07E-03 O.OOE-01 2. 72E-02 O.OOE-01 5.93E-01 O.OOE-01 3.21E 00 RU 106 1. 90E 05 O.OOE-01 2.38E 04 O.OOE-01 2.25E 05 0. OOE-01' 1. 44E 06 AG llOM 3. 86E 08 2.82E 08 1. 86E 08 O.OOE-01 4.03E 08 O.OOE-01 L 46E 10 TE 125M 1. SlE 08 5.04E 07 2.04E 07 5.07E 07 O.OOE-01 O.OOE-01 7.18E 07 TE 127M 4.21E 08 1. 40E 08 5.lOE 07 1. 22E 08 L04E 09 O.OOE-01 1. 70E 08 TE 127 6.32E 03 2.12E 03 1. 36E 03 5.15E 03 1. 54E 04 O.OOE-01 1. 33E 05 TE 129M 5.57E 08 1. 91E 08 8.58E 07 2.14E 08 1. 39E 09 O.OOE-01 3.33E 08 TE 129 2.74E-09 9.43E-10 6.39E-09 2.29E-08 6.BlE-08 O.OOE-01 2.19E-07 TE 131M 3.38E 06 1. 36E 06 l.12E 06 2. 7 6E 06 9. 36E 06 O.OOE-01 2.29E 07 TE 131 3.49E-32 l.29E-32 9.78E-32 3. llE-31 8.91E-31 O.OOE-01 1. 41E-30 TE 132 2.llE 07 1. OSE 07 9.75E 06 1. 54-E 07 6.53E 07 O.OOE-01 3.87E 07 I 130 3.55E 06 7.81E 06 3.14E 06 8. 76E 08 8.58E 06 O.OOE-01 1. 68E 06 I .131 2. 72E 09 3.21E 09 1. 41E 09 1. OSE 12 3.74E 09 O.OOE-01 1. 14E 08 I 132 1. 43E 00 2.91E 00 l.04E 00 1. 37E 02 3.25E 00 O.OOE-01 2.36E 00 I 133 3.63E 07 5.28E 07 1. SSE 07 9.61E 09 6.21E 07 O.OOE-01 8.94E 06 I 134 1. 77E-ll 3. 63E-ll 1. 29E-10 8.47E-09 4.06E-10 O.OOE-01 3. 76E-ll I 135 l.12E 05 2.24E 05 8.lSE 04 2.00E 07 2.49E 05 O.OOE-01 8.09E 04 cs 134 3.65E 10 6.BOE 10 6.87E 09 O.OOE-01 1. 75E 10 6.21E 09 1. SSE 08 cs 136 1. 96E 09 5. 76E 09 2.lSE 09 O.OOE-01 2.30E 09 4.70E 08 8.75E 07 cs 137 5.lSE 10 6.02E 10 4.27E 09 O.OOE-01 1. 62E 10 6.SSE 09 l.88E 08 cs 138 8.SOE-23 l.38E-22 6.70E-22 O.OOE-01 6.89E-22 l.08E-23 2.21E-22 BA 139 4.41E-07 2.93E-10 l.28E-07 O.OOE-01 1. 7 6E-09 1. 77E-10 2.80E-05 BA 140 2.41E 08 2.41E 08 1. 24E 07 O.OOE-01 5.72E 04 1. 48E 05 5.92E 07 BA 141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA 140 4.06E 01 1. 60E 01 4.12E 00 O.OOE-01 O.OOE-01 O.OOE-01 1. SSE 05 LA 142 8.59E-ll 3.lSE-ll 7.SSE-11 O.OOE-01 O.OOE-01 O.OOE-01 5.36E-06 CE 141 4.34E 04 2.64E 04 3.llE 03 O.OOE-01 8.16E 03 O.OOE-01 1. 37E 07 CE 143 3.97E 02 2.63E 05 3.00E 01 O.OOE-01 7.67E 01 O.OOE-01 l.54E 06 CE 144 2.33E 06 9.52E 05 1. 30E 05 O.OOE-01 3.85E 05 O.OOE-01 1. 33E 08 PR 143 l.49E 03 5.56E 02 7.36E 01 O.OOE-01 2.07E 02 O.OOE-01 7.84E 05 PR 144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND 147 8. 86E 02 9.lOE 02 5.57E 01 O.OOE-01 3.SlE 02 o. oo'E-01 5.77E 05

w. 187 6.12E 04 4.26E 04 1. 47E 04 O.OOE-01 . 0. QOE-01 O.OQE-01. 2.SOE 06 NP 239 3.65E 01 3.26E 00 l.84E 00 O.OOE-01 1. SOE 00 O.OOE-01 9.43E 04

Revision: 9 AP 07B~003 OFFSITE DOSE CALCULATION MANUAL Information Use ~age 134 of 160 ATTACHMENT A (Page 126 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-10 GRASS-COW-MEAT PATHWAY FACTOR M? MREM/YR PER µCI/SEC ADULT (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LL!

H 3 O.OOE-01 3.25E 02 3.25E 02 3.25E 02 3.25E 02 3.25E 02 3.25E 02 C 14 2.41E 08 4.83E 07 4.83E07 4.83E 07 4.83E 07 4.83E 07 4.83E 07 NA 24 1. 36E-03 1. 36E-03 1. 36E-03 l.36E-03 1. 36E-03 l.36E-03 1. 36E-03 p 32 4.65E 09 2.89E 08 l.80E 08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 7.0SE 03 4.21E 03 1. SSE 03 9.35E 03 l.77E 06 MN 54 O.OOE-01 9.18E 06 l.75E 06 O.OOE-01 2.73E 06 O.OOE-01 2.81E 07 MN 56 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 2.93E 08 2.20E 08 4. 72E 07 O.OOE-01 O.OOE-01 l.13E 08 l.16E 08 FE 59 2.65E 08 6.24E 08 2.39E 08 O.OOE-01 O.OOE-01 1. 74E 08 2.08E 09 co 58 O.OOE-01 1. 82E 07 4.09E 07 O.OOE-01 O.OOE-01 O.OOE-01 3.70E 08 co 60 O.OOE-01 7.52E 07 1. 66E 08 O.OOE-01 O.OOE-01 O.OOE-01 1. 41E 09 NI 63 l.89E 10 1. 32E 09 6.33E 08 O.OOE-01 O.OOE-01 O.OOE-01 2.73E 08 NI 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 O.OOe-01 2.73E.:::07 1. 28E--'07 O.OOE-01 6.89E-07 O.OOE-01 2.33E-05 ZN 65 3.56E 08 l.13E 09 5.12E 08 O.OOE-01 7.57E 08 O.OOE-01 7.13E 08 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 4.87E 08 2.27E 08 O.OOE-01 O.OOE-01 O.OOE-01 9.61E 07 RB 88. O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 3.02E 08 O.OOE-01 8.66E 06 O.OOE-01 O.OOE-01 O.OOE-01 4.84E 07 SR 90 1. 24E 10 O.OOE-01 3.0SE 09 O.OOE-01 O.OOE-01 O.OOE-01 3.59E 08 SR 91 l.43E-10 O.OOE-01 5.73E-12 O.OOE-01 O.OOE-01 O.OOE-01 6. 76E-10 SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 1. 07E 02 O.OOE-01 2.86E 00 O.OOE-01 O.OOE-01 O.OOE-01 l.13E 06 y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 l.13E 06 O.OOE-01 3.03E 04 O.OOE-01 O.OOE-01 O.OOE-01 6.23E 08 y 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 6.59E-12 O.OOE-01 1. 82E-13 O.OOE-01 O.OOE-01 O.OOE-01 2.09E-07 ZR 95 1. 87E 06 6.0lE 05 4.07E 05 O.OOE-01 9.43E 05 O.OOE-01 l.90E 09 ZR 97 2.08E-05 4.19E-06 1. 92E-06 O.OOE-01 6.33E-06 O.OOE-01 1. 30E 00 NB 95 2.30E 06 1. 28E 06 6.88E 05 O.OOE-01 1. 26E 06 O.OOE-01 7. 76E 09 MO 99 O.OOE-01 9.99E 04 1. 90E 04 O.OOE-01 2. 26E 05 O.OOE-01 2.32E 05 TC 99M *4.50E-21 1. 27E-20 l.62E-10 O.OOE-01 l .. 93E-19 6.23E-21 7.53E-18 TC 101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use ['age 135 of 160 ATTACHMENT A (Page 127 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-10 (cont'd)

GRASS-COW-MEAT PATHWAY FACTOR M2 MREM/YR PER µCI/SEC ADULT (RI FACTORS)

NUCLIDE* BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI RU 103 1. 05E 08 O.OOE-01 4.53E 07 O.OOE-01 .4.0lE 08 O.OOE-01 l.23E 10 RU 105 5.87E-28 O.OOE-01 2.32E-28 O.OOE-01 7.58E-27 O.OOE-01 3.59E-25 RU 106 2.80E 09 O.OOE-01 3.54E 08 o*. OOE-01 5.40E 09 O.OOE-01 l.81E 11 AG 110M 6.68E 06 6.18E 06 3.67E 06 O.OOE-01 1. 22E 07 O.OOE-01 2.52E 09 TE 125M 3.59E 08 1. 30E 08 4.81E 07 1. 08E 08 1. 46E 09 O.OOE-01 1. 43E 09 TE 127M l.12E 09, 3.99E 08 l.36E 08 2.85E 08 4.53E 09 O.OOE-01 3.74E 09 TE 127 2.14E-10 7. 68E-ll 4. 63E-ll 1. 58E-10 8.71E-10 O.OOE-01 1. 69E-08 TE 129M l.13E 09 4.23E 08 l.80E 08 3.90E 08 4.73E 09 O.OOE~Ol 5. 71E 09 TE 129 O.OOE-01 O.OOE-01 O.OOE-01. O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE 131M 4.52E 02 2.21E 02 l.84E 02 3.50E 02 2.24E 03 O.OOE-01 2.20E 04 TE 131 . 0. OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE 132 1. 42E 06 9.19E 05 8.63E 05 l.OlE 06 8.85E 06 O.OOE-01 4.35E 07 I 130 2.12E-06 6.26E-06 2.47E-06 5.30E-04 9.76E-06 O.OOE-01 5.39E-06 I 131 1. 07E 07 1. 54E 07 8.81E 06 5.04E09 2.64E 07 O.OOE-01 4. 06E 06 I 132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 133 3.67E-01 6.38E-01 l.94E-01 9.37E 01 l. llE 00 O.OOE-01 5.73E-01 I 134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 lj I 1,35 4.47E-l,7 l.17E-16 4.32E-17 7.73E-15 l.88E-16 O.OOE-01 1. 32E-16 cs 134 6.58E 08 l.56E 09 l.28E 09 O.OOE-01 5.06E 08 l.68E 08 2.74E 07 cs 136 l.18E 07 4.66E 07 3.35E 07 O.OOE-01 2.59E 07 3.55E 06 5.24E 06 cs 137 8. 72E 08 l.19E 09 7.81E 08 O.OOE-01 4.05E 08 1. 35E 08 2.31E 07

cs 138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 139 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 140 2.87E 07 3. 61E 04 1. 88E 06 O.OOE-01 1. 23E 04 2.07E 04 5.92E 07 BA 141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 142 O.OOE-01 0. OOE-0.1 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA 140 3.76E-02 l.89E-02 5.00E-03 O.OOE-01 O.OOE-01 O.OOE-01 l.39E 03 LA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE 141 l.40E 04 9.50E 03 1. 08E 03 O.OOE-01 4.41E 03 O.OOE-01 3.63E 07 CE 143 2. OlE-02 l.49E 01 l.65E-03 O.OOE-01 6. 55E.-03 O.OOE-01 5.56E 02 CE 144 1. 46E 06 6.09E 05 9.83E 04 O.OOE-01 3.61E 05 O.OOE-01 4.93E 08 PR 143 2.lOE 04 8.41E 03 1. 04E 03 O.OOE-01 4.86E 03 0. O. OE-01 9.19E 07 PR 144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND 147 7.17E 03 8.29E 03 4. 96E 02 O.OOE-01 4.84E 03 O.OOE-01 3.98E 07 w 187 2.17E-02 1. 81E-02 6.33E-03 O.OOE-01 O.OOE-01 O.OOE-01 5.93E 00

~

.. ~-. --- ... ______ .. . ......

NP 239 2.59E-01 2.55E-02 1. 40E-02 O.OOE-01 7.94E-02 O.OOE-01 5:22E 03

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use !Page 136 of 160 ATTACHMENT A (Page 128 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 5-11 GRASS-COW-MEAT PATHWAY FACTOR M2 MREM/YR PER µCI/SEC TEEN (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 1. 94E 02 1. 94E 02 1. 94E 02 l.94E 02 1. 94E 02 1. 94E 02 C 14 2.04E 08 4.08E 07 4. 08E 07 4. 08E 07 4.08E 07 4. 08E 07 4.08E 07 NA 24 1. 09E-03 1. 09E-03 1. 09E-03 l.09E-03 1. 09E-03 1. 09E-03 1. 09E-03 p 32 3.93E 09 2.44E 08 l.52E 08 O.OOE-01 O.OOE-01 O.OOE-01 3.30E 08 CR 51 O.OOE-01 O.OOE-01 5.64E 03 3.13E 03 1. 24E 03 8.05E 03 9.47E 05 MN 54 O.OOE-01 7.00E 06 l.39E 06 O.OOE-01 2.09E 06 O.OOE-01 l.44E 07 MN 56 O~OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 2.38E 08 1. 69E 08 3.93E 07 O.OOE-01 O.OOE-01 1. 07E 08 7.30E 07 FE 59 2.12E 08 4.95E 08 1. OlE 08 O.OOE-01 O.OOE-01 1. 56E 08 l.17E 09 co 58 O.OOE-01 l.41E 07 3.24E 07 O.OOE-01 O.OOE-01 O.OOE-01 1. 94E 08 co 60 O.OOE-01 5.83E 07 1. 31E 08 O.OOE-01 0. 00.E-01 O.OOE-01 7.60E 08 NI 63 1. 52E 10 1. 07E 09 5.15E 08 O.OOE-01 O.OOE-01 O.OOE-01 l.71E 08 NI 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 O.OOE-01 2.23E-07 l.05E-07 O.OOE-01 5.64E-07 O.OOE-01 1. 73E-05 ZN 65 2.50E 08 8.69E 08 4.05E 08 O.OOE-01 5.56E 08 O.OOE-01 3.68E 08 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE~Ol O.OOE-01 O.OOE-01 RB 86 O.OOE-01 4.07E 08 1. 91E 08 O.OOE-01 O.OOE-01 O.OOE-01 6.02E 07 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.55E 08 O.OOE-01 7.29E 06 O.OOE-01 O.OOE-01 O.OOE-01 3.03E 07 SR 90 8.05E 09 O.OOE-01 l.99E 09 O.OOE-01 O.OOE-01 O.OOE-01 2.26E 08 SR 91 l.19E-10 O.OOE-01 4.75E-12 O.OOE-01 O.OOE-01 O.OOE-01 5.41E-10 SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 8.98E 01 O.OOE-01 2.42E 00 O.OOE-01 O.OOE-01 O.OOE-01 7.41E 05 y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 9.54E 05 O.OOE-01 2.56E 04 O.OOE-01 O.OOE-01 O.OOE-01 3.91E 08 y 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 5.56E-12 O.OOE-01 1. 53E-13 O.OOE-01 O.OOE-01 O.OOE-01 l.70E-07 ZR 95 l.50E 06 4.73E 05 3.26E 05 O.OOE-01 6.96E 05 O.OOE-01 1. 09E 09 ZR 97 1. 73E-05 3.42E-06 l.58E-06 O.OOE-01 5.19E-06 O.OOE-01 9.27E-01 NB 95 1. 80E 06 9. 96E 05 5.48E 05 O.OOE-01 9.66E.05 O.OOE-01 4.26E 09 MO 99 O.OOE-01 8.26E 04 l.58E 04 O.OOE-01 1. 89E 05 O.OOE-01 l.48E 05 TC 99M 3.58E-21 9.97E-21 1. 29E-19 O.OOE-01 l.49E-19 5.54E-21 6.55E-18

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use age 137 of 160 ATTACHMENT A (Page 129 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 5-11 (cont'd)

GRASS-COW-MEAT PATHWAY FACTOR M2 MREM/YR PER µCI/SEC TEEN ( RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU 103 8.56E 07 O.OOE-01 3. 66E 07 O.OOE-01 3.02E 08 O.OOE-01 7.15E 09 RU 105 4.91E-28 O.OOE-01 l.91E-28 O.OOE-01 6.91E-27 O.OOE-01 3.96E-25

- RU 106 2. 36E 09 O.OOE-01 2.97E 08 O.OOE-01 4.55E 09 O.OOE-01 l.13E 11 AG 110M 5.06E 06 4.79E 06 2.91E 06 O.OOE-01 9.13E 06 O.OOE-01 l.35E 09 TE 125M 3.03E 08 l.09E 08 4.05E 07 8.47E 07 O.OOE-01 O.OOE-01 8.94E 08 TE 127M 9.42E 08 3.34E 08 l.12E 08 2.24E 08 3.82E 09 O.OOE-01 2.35E 09 TE 127 1. BlE-10 6.43E-ll 3. 91E-ll 1. 25E-09 7.35E-10 O.OOE-01 l.40E-08 TE 129M 9.50E 08 3.53E 08 1. 50E 08 3.07E 08 3.97E 09 O.OOE-01 3.57E 09 TE 129 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE 131M 3.77E 02 1. BlE 02 1. 51E 02 2.72E 02 1. SSE 03 O.OOE-01 1. 45E 04 TE 131 O.OOE-01 O.OOE-01 O.OOE:...01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE 132 l.16E. 06 7.36E 05 6.93E 05 7.76E 05 7.06E 06 O.OOE-01 2.33E 07 I 130 1. 71E-06 4.94E-06 1. 97E-06 4.03E-04 7.61E-06 O.OOE-01 3.BOE-06 I 131 8.93E 06 1. 25E 07 6. 72E 06 3.65E 09 2.15E 07 O.OOE-01 2.47E 06 I 132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 *o.OOE-01 O.OOE-01 I 133 3.07E-01 5.20E-01 1. 59E-01 7.26E 01 9.12E-01 O.OOE-01 3.93E-01 I 134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 135 3.64E-17 9.37E-17 3.47E-17 6.03E-15 l.48E-16 O.OOE-01 l.04E-16 cs 134 5.23E 08 l.23E 09 5. 71E 08 O.OOE-01 3.91E 08 l.49E 08 1. 53E 07 cs 136 9.20E 06 3.62E 07 2.43E 07 O.OOE-01 l.97E 07 3.llE 06 2.91E 06 cs 137 7.24E 08 9.63E 08 3. 36E 08 O.OOE-01 3.28E 08 1. 27E 08 1. 37E 07 cs 138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 139 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 140 2.38E 07 2.91E 04 1. 53E 06 O.OOE-01 9.BBE 03 1. 96E 04 3. 67E 07 BA 141 O.OOE-01 0. OOE-01 . O.OOE-01 O.OOE-01 O.OOE-01 0,. OOE-01 O.OOE-01 BA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA 140 3.09E-02 l.52E-02 4.04E-03 O.OOE-01 O.OOE-01 O.OOE-01

8. 72E 02 LA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE 141 l.lBE 04 7.BBE 03 9.05E 02 O.OOE-01 3.71E 03 O.OOE-01 2.25E 07 CE 143 l.69E-02 l.23E 01 1. 38E-03 O.OOE-01 5.53E-03 O.OOE-01 3.70E 02 CE 144 l.23E 06 5.0BE 05 6.60E 04 O.OOE-01 3.04E 05 O.OOE-s-01 3.09E OB PR 143 l.77E 04 7.05E 03 8.78E 02 O.OOE-01 4.lOE 03 O.OOE-01 5. BlE 07 PR 144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND 147 6.32E 03 6.87E 03 4.llE 02 O.OOE-01 4.03E 03 O.OOE-01 2.48E 07 w 187 l.BlE-02 1.48E-02 5.lBE-03 O.OOE--,01 0.00E-01 O.OOE-01 4.00E 00 NP 239 2.26E-01 2.13E-02 1.19E-02 O.OOE-01 6.70E-07 O.OOE-01 3. 43E 03

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 138 of 160 ATTACHMENT A (Page 130 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 5-12 GRASS-COW-MEAT PATHWAY FACTOR M2 MREM/YR PER µCI/SEC CHILD (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 2.34E.02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 C 14 3.83E 08 7.67E 07 7.67E 07 7.67E 07 7.67E 07 7. 67E 07 7.67E 07 NA 24 1.73E-03 1.73E-03 1. 73E-03 1. 73E-03 1.73E-03 1.73E-03 1. 73E-03 p 32 7.41E 09 3.47E OB 2. 8 6E 08 O.OOE-01 O.OOE-01 O.OOE-01 2.05E 08 CR 51 O.OOE-01 O.OOE-01 8.79E 03 4.BBE 03 1. 33E 03 8.91E 03 4.66E 05 MN 54 O.OOE-01 8.0lE 06 2.13E 06 O.OOE-01 2.25E 06 O.OOE-01 6. 72E 06 MN 56 O.OOE-01 l.63E-53 3.67E-54 O.OOE-01 1.97E-53 O.OOE-01 2.36E-51 FE 55 4.57E 08 2.42E 08 7.50E 07 O.OOE-01 O.OOE-01 1.37E 08 4.49E 07 FE 59 3.76E 08 6.09E 08 3.03E 08 O.OOE-01 O.OOE-01 1. 76E 08 6.34E 08 co 58 O.OOE-01 1.64E 07 5.03E 07 O.OOE-01 O.OOE-01 O.OOE-01 9.58E 07 co 60 O.OOE-01 6.93E 07 2.04E 08 O.OOE-01 O.OOE-01 O.OOE-01 3.84E 08 NI 63 2.91E 10 l.56E 09 9.91E 08 O.OOE-01 O.OOE-01 O.OOE-01 1. 05E 08 NI 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 O.OOE-01 3.00E-07 1. BlE-07 O.OOE-01 7.24E-07 O.OOE-01 1. 41E-05 ZN 65 3.75E 08 l.OOE 09 6.22E 08 O.OOE-01 6.30E 08 O.OOE-01 1. 7 6E 08 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 5.77E 08 3.55E 08 O.OOE-01 O.OOE-01 O.OOE-01 3.71E 07 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 {.82E 08 O.OOE-01 1.38E 07 O.OOE-01 O.OOE-01 O.OOE-01 1. 87E 07 SR 90 1.04E 10 O.OOE-01 2.64E 09 O.OOE-01 O.OOE-01 O.OOE-01 1. 40E 08 SR 91 2.24E-10 O.OOE-01 8.45E-12 O.OOE-01 O.OOE-01 O.OOE-01 4. 94E-10

SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 1.70E 02 O.OOE-01 4.55E 00 O.OOE-01 O.OOE-01 O.OOE-01 4.84E 05 y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 1.BOE 06 O.OOE-01 4.82E 04 O.OOE-01 O.OOE-01 O.OOE-01 2.40E 08 y 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 1.04E-11 O.OOE-01 2.87E-13 O.OOE-01 O.OOE-01 O.OOE-01 1.56E-07 ZR 95 2.66E 06 5.86E 05 5.21E 05 O.OOE-01 8.38E 05 O.OOE-01 6.llE 08 ZR 97 3.22E-05 .4.65E-06 2.74E-06 O.OOE-01 6.68E-06 O.OOE-01 7.05E-01 NB 95 3.lOE 06 1.21E 06 8.63E 05 O.OOE-01 1.13E 06 O.OOE-01 2.23E 09 MO 99 O.OOE-01 1.15E 05 2.84E 04 O.OOE-01 2.45E 05 O.OOE-01 9.51E 04 TC 99M 6.27E-21 l.23E-20 2.04E-19 O.OOE-01 1. 7 9E-19 6.24E-21 7.00E-18

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 139 of 160 ATTACHMENT A (Page 131 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-12 (cont'd)

GRASS-COW-MEAT PATHWAY FACTOR M2 MREM/YR PER µCI/SEC CHILD ( RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU 103 1. SSE 08 O.OOE-01 5.95E 07 O.OOE-01 3.90E 08 O.OOE-01 4.00E 09 RU 105 9.16E-28 O.OOE-01 3.32E-28 O.OOE-01 8.0SE-27 O.OOE-01 5.98E-25 RU 106 4.44E 09 O.OOE-01 5.54E 08 O.OOE-01 5.99E 09 O.OOE-01 6.90E 10 AG llOM 8.34E 06 5.67E 06 4.53E 06 O.OOE-01 1. 06E 07 0.00E-01 6.74E 08 TE 125M 5.69E 08 l.54E 08 7.59E 07 l.60E 08 O.OOE-01 O.OOE-01 5.49E 08 TE 127M 1. 77E 09 4.78E 08 2.llE 08 4.24E 08 5.06E 09 O.OOE-01 l.44E 09 TE 127 3.41E-10 9.20E-ll 7.32E-ll 2.36E-10 9.71E-10 O.OOE-01 1. 33E-08 TE 129M l.79E 09 5.00E 08 2.78E 08 5.77E 08 5.26E 09 O.OOE-01 2.18E 09 TE 129 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE 131M 7.0lE 02 2.43E 02 2.58E 02 4.99E 02 2.35E 03 O.OOE-01 9.84E 03 TE 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE 132 2.12E 06 9.39E 05 l.13E 06 1. 37E 06 8.72E 06 O.OOE-01 9. 4 6E 06 I 130 3.0SE-06 6.17E-06 3.18E-06 6.80E-04 9.22E-06 O.OOE-01 2.89E-06 I 131 1. 66E 07 1. 67E 07 9.47E 06 5.51E 09 2.74E 07 O.OOE-01 1. 48E 06 I 132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 133 5.70E-01 7.04E-01 2.66E-01 1. 31E 02 l.17E 00 O.OOE-01 2.84E-01 I 134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 135 6.59E-17 l.19E-16 5.61E-17 l.OSE-14 1. 82E-16 O.OOE-01 9.04E-17 cs 134 9.22E 08 l.51E 09 3.19E 08 O.OOE-01 4.69E 08 l.68E 08 8.16E 06 cs 136 1. 59E 07 4. 36E 07 2.82E 07 O.OOE-01 2.32E 07 3.46E 06 l.53E 06 cs 137 l.33E 09 1. 28E 09 l.88E 08 0. OOE-0.1 4 .16E 08 1. SOE 08 7.99E 06 cs 138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 139 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01

BA 140 4.39E 07 3.84E 04 2.56E 06 O.OOE-01 1. 25E 04 2.29E 04 2.22E 07 BA 141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA 140 5.66E-02 l.98E-02 6.66E-03 O.OOE-01 O.OOE-01 O.OOE-01 5.51E 02 LA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE 141 2.22E 04 l.llE 04 1. 64E 03 O.OOE-01 4.86E 03 O.OOE-01 l.38E 07 CE 143 3.18E-02 1. 72E 01 2.SOE-03 O.OOE-01 7.23E-03 O.OOE-01 2.52E 02 CE 144 2.32E 06 7. 26E 05 1. 24E 05 O.OOE-01 4.02E 05 O.OOE-01 l.89E 08 PR 143 3.34E 04 1. OOE 04 1. 66E 03 O.OOE-01 5.43E 03 O.OOE-01 3.60E 07 PR 144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND 147 l.19E 04 9.60E 03 7.43E 02 O.OOE-01 5.27E 03 O.OOE-01 l.52E 07 w 187 3.36E-02 l.99E-02 8.94E-03 O.OOE-01 O.OOE-01 O.OOE-01 2.80E 00 NP 239 4.26E-01 3.06E-02 2.lSE-02 O.OOE-01 8.84E-02 O.OOE-01 2.26E 03

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use !Page 140 of 160 ATTACHMENT A (Page 132 of 1~2)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-13 VEGETATION PATHWAY FACTOR M2 MREM/YR PER µCI/SEC ADULT (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI .

H 3 O.OOE-01 2.26E 03 2.26E 03 2.26E 03 2.26E 03 2. 26E 03 2.26E 03 C 14 2.38E 08 4.55E 07 4.55E 07 4.55E 07 4.55E 07 4.55E 07 4.55E 07 NA 24 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 p 32 l.40E 09 8.73E 07 5.42E 07 O.OOE-01 O.OOE-01 O.OOE-01 1. 58E 08 CR 51 O.OOE-01 O.OOE-01 4.64E 04 2.78E 04 1.02E 04 6.16E 04 l.17E 07 MN 54 O.OOE-01 3.13E 08 5.97E 07 O.OOE-01 9.31E 07 O.OOE-01 9.58E 08 MN 56 O.OOE-01 l.59E 01 2.82E 00 O.OOE-01 2.02E 01 O.OOE-01 5.08E 02 FE 55 2.09E 08 l.45E 08 3.37E 07 O.OOE-01 O.OOE-01 8. 06E 07 8.29E 07 FE 59 1. 26E 08 2.96E 08 l.14E 08 O.OOE-01 O.OOE-01 8.28E 07 9.83E 08 co 58 O.OOE-01 3.07E 07 6.89E 07 O.OOE-01 O.OOE-01 O.OOE-01 6.23E 08 co 60 O.OOE-01 l.67E 08 3 .. 69E 08 O.OOE-01 O.OOE-01 O.OOE-01 3.14E 09 NI 63 l.04E 10 7.28E 08 3.49E 08 O.OOE-01 o:ooE-01 O.OOE-01 1. SOE 08 NI 65 6.93E 01 9.0lE 00 4. llE 00 O.OOE-01 O.OOE-01 O.OOE-01 2.28E 02 cu 64 O.OOE-01 9.21E 03 4.32E 03 O.OOE-01 2.32E 04 O.OOE-01 7.85E 05 ZN 65 3.17E 08 1. OlE 09 4.56E 08 O.OOE-01 6.75E 08 O.OOE-01 *6.36E 08 ZN 69 8.77E-06 l.68E-05 l.17E-06 O.OOE-01 1. 09E-05 O.OOE-01 2.52E-06 BR 83 O.OOE-01 O.OOE-01 3.llE 00 O.OOE-01 O.OOE-01 O.OOE-01 4.48E 00 BR 84 O.OOE-01 O.OOE-01 2. 49E-11 O.OOE-01 O.OOE-01 O.OOE-01 1. 96E-16 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 2.19E 08 1. 02E 08 O.OOE-01 O.OOE-01 O.OOE-01 4.33E 07 RB 88 O.OOE-01 3.47E-22 1. 84E-22 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 l.41E-26 9.88E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 9.97E 09 O.OOE-01 2.86E 08 O.OOE-01 O.OOE-01 O.OOE-01 l.60E 09 SR 90 6.0SE 11 O.OOE-01 l.48E 11 O.OOE-01 O.OOE-01 O.OOE-01 l.75E 10 SR 91 3.03E 05 O.OOE-01 1. 22E 04 O.OOE-01 O.OOE-01 O.OOE-01 l.44E 06 SR 92 4.27E 02 O.OOE-01 1. SSE 01 O.OOE-01 O.OOE-01 O.OOE-01 8. 46E 03 y 90 1. 33E 04 O.OOE-01 3.56E 02 O.OOE-01 0. OOE-0*1 O.OOE-01 l.41E 08 y 91M 5.24E-09 O.OOE-01 2.03E-10 O.OOE-01 O.OOE-01 O.OOE-01 l.54E-08 y 91 5. llE 06 O.OOE-01 1. 37E 05 O.OOE-01 O.OOE-01 O.OOE-01 2.81E 09 y 92 9.16E-01 O.OOE-01 2.68E-02 O.OOE-01 O.OOE-01 O.OOE-01 l.60E 04 y 93 1.74E 02 O.OOE-01 4.81E 00 O.OOE-01 O.OOE-01 O.OOE-01 5.52E 06 ZR. 95 l.18E 06 3.77E 05 2.55E 05 O.OOE-01 5.92E 05 O.OOE-01 l.20E 09 ZR 97 3.37E 02 6.81E 01 3.llE 01 O.OOE-01 l.03E 02 O.OOE-01 2. llE 07 NB 95 1. 43E 05 7.93E 04 4. 26E 04 O.OOE-01 7.84E 04 O.OOE-01 4. 81E 08 MO 99 O.OOE-01 6.15E 06 l.17E 06 O.OOE-01 l.39E 07 O.OOE-01 l.43E 07 TC 99M 3.lOE 00 8.77E 00 l.12E. 02 O.OOE-01 1. 33E 02 4.30E 00 5.19E 03

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use [Page 141 of 160 ATTACHMENT.A (Page 133 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-13 (cont'_d)

.. VEGETATION PATHWAY FACTOR M2 MREM/YR PER µCI/SEC ADULT ( RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LL!

TC 101 8.34E-31 1. 20E-30 1.18E-29 O.OOE-01 2 .16E-29 . 6.14E-31 O.OOE-01 RU* 103 4. 7 6E 06 O.OOE-01 2.05E 06 O.OOE-01 1. 82E 07 O.OOE-01 S-. 56E 08 RU 105 5.39E 01 O.OOE-01 2.13E 01 O.OOE-01 6.97E 02 O.OOE-01 3.30E 04 RU 106 1. 93E 08 O.OOE-01 2.44E 07 O.OOE-01 3. 72E 08 O.OOE-01 1. 25E 10 AG 110M

1. 05E 07 9.75E 06 5.79E 06 O.OOE-01 1.92E 07 O.OOE 3.98E 09 TE 125M 9.66E 07 3.50E 07 1.29E 07 2.90E 07 3.93E 08 O.OOE-01 3.86E 08

. TE 127M 3.49E 08 1.25E 08 4.26E 07 8.93E 07 1. 42E 09 O.OOE-01 l.17E 09 TE 127 5.66E 03 2.03E 03 1. 23E 03 4.20E 03 2.31E 04 O.OOE-01 4.47E 05 TE 129M 2.51E 08 9.38E 07 3.98E 07 8.63E 07 1. 05E 09 O.OOE-01 1. 27E 09 TE 129 7.65E-04 2.87E-04 1. 86E-04 5.87E-04 3.22E-03 O.OOE-01 5.77E-04 TE 131M 9.12E 05 4.46E 05 3. 72E 05 7.07E 05 4.52E 06 O.OOE-01 4.43E 07

.TE 131 1. 51E-15 6.32E-16 4.78E-16 1. 24E-15 6.63E-15 O.OOE-01 2.14E-16 TE 132 4.30E 06 2.78E 06 2.61E 06 3.07E 06 2.68E 07 O.OOE~Ol 1.32E 08 I 130 3.95E 05 1.16E 06 4.57E 05 9.81E 07 1. 81E 06 O.OOE-01 9.97E 05 I 131 8.08E 07 1.16E 08 6.62E 07 3.79E 10 1. 98E 08 O.OOE-01 3.05E 07 I 132 5.77E 01 1. 54E 02 5.40E 01 5. 40E 03 2. 46E 02 O.OOE-01 2.90E 01 I 133 2.09E 06 3.63E 06 l.llE 06 5.33E 08 6.33E 06 O.OOE-01 3.26E 06 I 134 9.69E-05 2.63E-04 9.42E-05 . 4.56E-03 4.19E-04 0. OOE-01

2.30E-07 I 135 3.90E 04 1.02E 05 3.77E 04 6.74E 06 1.64E 05 O.OOE-01 1.15E 05 cs 134 4. 67E 09 l.°ilE 10 9.08E 09 O.OOE-01 3.59E 09 1.19E 09 1. 94E 08 cs 136 4.20E 07 1. 66E 08 1.19E 08 O.OOE-01 9.22E 07 1. 26E 07 1.88E 07 cs 137 6.36E 09 8.70E 09 5.70E 09 O.OOE-01 2.95E 09 9. 81E 08 l.68E 08 cs 138 3. 94E-11 7.78E-11 3. 86E-ll O.OOE-01 5.72E-11 5.65E-12 3.32E-16 BA 139 2.90E-02 2.07E-05 8.50E-04 O.OOE-01 1.93E-05 1.17E-05 5 ..,15E-02 BA 140 1. 29E 08 1. 61E 05 8.42E 06 O.OOE-01 5.49E 04 9.25E 04 2.65E 08 BA 141 1.28E-21 9.64E-25 4.31E-23 O.OOE-:,01 8.96:E;-25 5.47E-25 6.0lE-31 BA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA 140 1. 98E 03 9.99E 02 2. 64E 02 O.OOE-01 O.OOE-01 O.OOE-01 7.33E.07 LA 142 1.42E-04 6.44E-05 1. 61E-05 O.OOE-01 O.OOE-01 O.OOE-01 4.70E-01 CE 141 1.97E 05 l.33E 05 l.51E 04 O.OOE-01 6.19E 04 O.OOE-01 5.lOE 08 CE 143 9.98E 02 7.38E 05 8.17E 01 O.OOE-01 3.25E 02 O.OOE-01 2. 76E 07 CE 144 3.29E 07 1.38E 07 1.77E 06 O.OOE-01 8.16E 06 O.OOE-01 l.llE 10 PR 143 6.26E 04 2.51E 04 3. llE 03 O.OOE-01 l.45E 04 O.OOE-01 2.74E 08 PR 144 3.13E-26 l.30E-26 1. 59E-27 O.OOE-01 7.32E-27 O.OOE-01 O.OOE-01 ND 147 3. 36E 04 3.89E 04 2.32E 03 O.OOE-01 2.27E 04 O.OOE-01 1. 87E 08 w 187 3.82E 04 3.20E 04 l.12E 04 O.OOE-01 O.OOE-01 O.OOE-01 1. 05E 07 NP 239 1.43E 03 1.40E 02 7.74E 01 O.OOE-01 4.38E 02 O.OOE-01 2.88E 07

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use [?age 142 of 160 ATTACHMENT A (Page 134 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-14 VEGETATION PATHWAY FACTOR M2 ,MREM/YR PER µCI/SEC TEEN (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 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 NA 24 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 p 32 1. 61E 09 9.96E 07 6.23E 07 O.OOE-01 O.OOE-01 O.OOE-01 1.35E 08 CR 51 O.OOE-01 O.OOE-01 6.17E 04 3.43E 04 1. 35E 04 8.BlE 04 1. 04E 07 MN 54 O.OOE-01 4.54E 08 9.0lE 07 O.OOE-01 1.36E 08 O.OOE-01 9.32E 08 MN 56 O.OOE-01 1.44E 01 2.55E 00 O.OOE-01 1. 82E 01 O.OOE-01 9.45E 02 FE 55 3.25E 08 2.31E 08 5.38E 07 0. OOE.:..01 O.OOE-01 1.46E 08 9.98E 07 FE 59 1. 79E 08 4.lBE 08 1.62E 08 O.OOE-01 O.OOE-01 1. 32E 08 9.90E 08 co 58 O.OOE-01 4.36E 07 1. OlE 08 O.OOE-01 O.OOE-01 O.OOE-01 6.0lE 08 co 60 O.OOE-01 2.49E 08 5.60E 08 O.OOE-01 O.OOE-01 O.OOE-01 3.24E 09 NI 63 1.61E 10 1.13E 09 5.44E 08 O.OOE-01 O.OOE-01 O.OOE-01 1. BlE 08 NI 65 6.45E 01 8.24E 00 3. 76E 00 O.OOE-01 0. OOE-01 , O.OOE-01 4.47E 02 cu 64 O.OOE-01 8.34E 03 3.92E 03 O.OOE-01 2.llE 04 O.OOE-01 6.47E 05 ZN 65 4.24E 08 1.47E 09 6. 86E 08 O.OOE-01 9.42E 08 O.OOE-01 6.23E 08 ZN 69 8.21E-06 1. 56E 05 1.lOE-06 O.OOE-0;1 1. 02E-05 O.OOE-01 2.BBE-05 BR 83 O.OOE-01 O.OOE-01 2.92E 00 O.OOE-01 O.OOE-01 O.OOE-01 5.0BE-16 BR 84 O.OOE-01 O.OOE-01 2. 27E-11 O.OOE-01 O.OOE-01 O.OOE-01 3.14E-28 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 2.74E 08 1.29E 08 O.OOE-01 O.OOE-01 O.OOE-01 4. OSE 07 RB 88 O.OOE-01 3.21E-22 1. 71E-22 O.OOE-01 O.OOE-01 O.OOE-01 2.75E-29 RB 89 O.OOE-01 1.26E-26 8.94E-27 O.OOE-01 O.OOE-01 O.OOE-01 1. 94E-35 SR 89

1. 51E 10 O.OOE-01 4.34E 08 O.OOE-01 O.OOE-01 O.OOE-01 1.BOE 09 SR 90 7.51E 11 O.OOE-01 1. SSE 11 O.OOE-01 O.OOE-01 O.OOE-01 2. llE 10 SR 91 2.83E 05 O.OOE-01 1.13E 04 O.OOE-01 O.OOE-01 O.OOE-01 1.28E 06 SR 92 3.98E 02 O.OOE-01 1. 70E 01 O.OOE-01 O.OOE-01 O.OOE-01 1. OlE 04 y 90 1. 24E 04 O.OOE-01 3.34E 02 O.OOE-01 O.OOE-01 O.OOE-01 1. 02E 08 y 91M 4.BBE-09 O.OOE-01 1. 87E-10 O.OOE-01 O.OOE-01 O.OOE-01 2.30E-07 y 91 7.84E 06 O.OOE-01 2.lOE 05 O.OOE-01 O.OOE-01 O.OOE-01 3.21E 09 y 92 8.61E-01 O.OOE-01 2.49E-02 O.OOE-01 O.OOE-01 O.OOE-01 2.36E 04 y 93 1.63E 02 O.OOE-01 4.47E 00 O.OOE-01 O.OOE-01 O.OOE-01 4.99E 06 ZR 95 1.72E 06 5.44E 05 3.74E 05 0. OOE,-01 7.99E 05 O.OOE-01 1. 25E 09 ZR 97 3.12E 02 6.lBE 01 2.85E 01 O.OOE-01 9.37E 01 O.OOE-01 1.67E 07 NB 95 1.93E 05 l.07E 05

. 5.BBE 04 .O.OOE-01 1. 04E 05 O.OOE-01 4.57E 08 MO 99 O.OOE-01 5.65E 06 1. OBE 06 O.OOE-01 1.29E 07 O.OOE-01 1. OlE 07 TC 99M 2.74E 00 7.64E 00 9.90E 01 O.OOE-01 1.14E 02 4.24E 00 5.02E 03

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use !Page 143 of 160 ATTACHMENT A (Page 135 of 152)

OFFSITE DOSE CALCULATION MANUAL T~LE A.5-14 (cont'd)

VEGETATION PATHWAY FACTOR M2 MREM/YR PER µCI/SEC TEEN (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 7.76E-31 l. lOE-30 l.OBE-29 O.OOE-01 2.00E-29 6.72E-31 O.OOE-01 RU 103 6.81E 06 O.OOE-01 2.91E 06 O.OOE-01 2.40E 07 O.OOE-01 5.69E 08 RU 105 5.0lE 01 O.OOE-01 1. 94E 01 O.OOE-01 6.32E 02 O.OOE-01 4.04E 04 RU 106 3.09E 08 O.OOE-01 3.90E 07 O.OOE-01 5.97E 08 O.OOE-01 1. 48E 10 AG llOM l.52E 07 l.43E 07 8. 72E 06 O.OOE-01 2.74E 07 O.OOE-01 4.03E 09 TE 125M l.48E 08 5.34E 07 1. 98E 07 4.14E 07 O.OOE-01 O.OOE-01 4.39E 08 TE 127M 5.52E 08 l.96E 08 6.56E 07 l.31E 08 2.24E 09 O.OOE-01 1. 37E 09 TE 127 5.34E 03 l.89E 03 l.15E 03 3.68E 03 2.16E 04 O.OOE-01 4.12E 05 .

TE 129M 3.62E 08 1. 34E 08 5.73E 07 l.17E 08 l.SlE 09 O.OOE-01 1. 36E 09 TE 129 7.16E-04 2.67E-04 1. 7 4E-04 5.12E-04 3.0lE-03 O.OOE-01 3.92E-03 TE* 131M 8.44E 05 4. OSE 05 3.38E 05 6.09E 05 4.22E 06 O.OOE-01 3.25E 07 TE 131 1. 41E-14 5.BOE-16 4.40E-16 l.OBE-15 6.lSE-15 O.OOE-01 l.lSE-16 TE 132 3.91E 06 , 2.48E 06 2.33E 06 2.61E 06 2.37E 07 O.OOE-01 7.84E 07 I 130 3.SlE 05 l.02E 06 4.0SE 05 8.28E 07 1. 56E 06 O.OOE-01 7.BOE 05 I 131 7.69E 07 1. OBE 08 5.78E 07 3.14E 10 1. SSE 08 O.OOE-01 . 2.13E 07 I 132 5.20E 01 l.36E 02 4.89E 01 4.59E 03 2.14E 02 O.OOE-01 5.93E 01 I 133 l.94E 06 3.29E 06 1. OOE 06 4.59E 08 5.77E 06 O.OOE-01 2.49E 06 I 134 8.76E-05 2.32E-04 8.34E-05 3.87E-03 3.66E-04 O.OOE-01 3.06E-06 I 135 3.52E 04 9.07E 04 3.36E 04 5.84E 06 l.43E 05 O.OOE-01 1. OlE 05 cs 134 7.lOE 09 l.67E 10 7.75E 09 O.OOE-01 5.31E 09 2.03E 09 2.0BE 08 cs 136 4.28E 07 1. 68E 08 l.13E 08 O.OOE-01 9 .16E 07 1. 44E 07 1. 35E 07 cs 137 1. OlE 10 1. 35E 10 4.69E 09 O.OOE-01 4.59E 09 l.78E 09 l.92E 08 cs 138 3. 64E-ll 6.98E-ll 3. 49E-ll O.OOE-01 5.15E-ll 6.00E-12 3.17E-14 BA 139 2.73E-02 l.92E-05 7.96E-04 O.OOE-01 1. BlE-05 1. *32E-05 2.44E-01 BA 140 1. 38E 08 1. 69E os 8.91E 06 O.OOE-01 5.74E 04 l.14E 05 2.13E 08 BA 141 l.19E-21 8.90E-25 3.98E-23 O.OOE-01 8.27E-25 6.lOE-25 2.54E-27 BA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 *O.OOE-01 O.OOE-01 O.OOE-01 LA 140 l.81E 03 8.89E 02 2.37E 02 O.OOE-01 O.OOE-01 O.OOE-01 5. llE 07 LA 142 1. 30E-04 5.78E-05 l.44E-05 O.OOE-01 O.OOE-01 O.OOE-01 l.76E 00 CE 141 2.83E 05 l.89E 05 2.17E 04 O.OOE-01 8.90E 04 O.OOE-01 5.41E 08 CE 143 9.33E 02 6.79E 05 7.58E 01 O.OOE-01 3.04E 02 O.OOE-01 2.04E 07 CE 144 5.27E 07 2.lBE 07 2;83E 06 O.OOE-01 1. 30E 07 O.OOE-01 l.33E 10 PR 143 7.0lE 04 2.BOE 04 3.49E 03 O.OOE-01 l.63E 04 O.OOE-01 2.31E 08 PR 144 2.93E-26 l.20E-26 1. 49E-27 O.OOE-01 6.BBE-27 O.OOE-01 3.23E-29 ND 147 3.66E 04 3*. 98E 04 2.38E 03 O.OOE-01 2.34E 04 O.OOE-01 1. 44E 08 w 187 3.56E 04 2.90E 04 1. 02E 04 O.OOE-01 O.OOE-01 O.OOE-01 7.84E 06 NP 239 1:39E 02 1. 31E 02 7. 26E 01 O.OOE-01 4.lOE 02 O.OOE-01 2.lOE 07

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 144 of 160 ATTACHMENT A (Page 136 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-15 VEGETATION PATHWAY FACTOR M2 MREM';YR PER µCI/SEC CHILD (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 4.0lE 03 4.0lE 03 4. OlE 03 4. OlE 03 4. OlE 03 4.0lE 03 C 14 8.89E 08 1. 78E 08 1. 78E 08 1. 78E 08 1. 78E 08 l.78E 08 1. 78E 08 NA 24 ' 3. 73E 05 3.73E 05 3.73E 05 3.73E 05 3. 73E 05 3.73E 05 3.73E 05 p 32 3.37E 09 1. SSE 08 l.30E 08 O.OOE-01 O.OOE-01 O.OOE-01 9.30E 07 CR 51 O.OOE-01 O.OOE-01 l.17E 05 6.50E 04 l.78E 04 l.19E 05 6.21E 06 MN 54 O.OOE-01 6.65E 08 l.77E 08 O.OOE-01 1. 86E 08 O.OOE-01 5.SBE 08 MN 56 O.OOE-01 l.BBE 01 4.24E 00 O.OOE-01 2.27E 01 O.OOE-01 2.72E 03 FE 55 8.00E 08 4.24E 08 1. 31E 08 O.OOE-01 O.OOE-01 2.40E 08 7. 86E 07 FE 59 3.97E 08 6. 43E OB 3.20E 08 O.OOE-01 O.OOE-01 1. 86E 08 6.69E 08 co 58 O.OOE-01 6.44E 07 1. 97E 08 O.OOE-01 O.OOE-01 O.OOE-01 3. 76E 08 co 60 O.OOE-01 3.78E 08 l.12E 09 O.OOE-01 O.OOE-01 O.OOE-01 2.lOE 09 NI 63 3.95E 10 2. llE 09 1. 34E 09 O.OOE-01 O.OOE-01 O.OOE-01 1. 42E 08 NI 65 l.lBE 02 l. llE 01 6.51E 00 O.OOE-01 O.OOE-01 O.OOE-01 1. 37E 03 cu 64 O.OOE-01 l.lOE 04 6.65E 03 O.OOE-01 2.66E 04 O.OOE-01 5.16E 05 ZN 65 8.12E 08 2.16E 09 l.35E 09 O.OOE-01 l;36E 09 O.OOE-01 3.BOE 08 ZN 69 l.SlE-05 2. i°9E-05 2.02E-06 O.OOE-01 l.33E-05 O.OOE-01 1. 38E-03 BR 83 O.OOE-01 O.OOE-01 5.38E 00 O.OOE-01 O.OOE-01 O.OOE-01 3.14E-17 BR 84 O.OOE-01 O.OOE-01 3.BSE-11 O.OOE_:_01 O.OOE-01 O.OOE-01 1. 94E-28 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 4.52E 08 2.78E 08 O.OOE-01 O.OOE-01 O.OOE-01 2.91E 07 RB 88 O.OOE-01 4.43E-22 3.0BE-22 O.OOE-01 O.OOE-01 O.OOE-01 2.17E-23 RB 89 O.OOE-01 1. 67E-26 1. 48E-26 O.OOE-01 O.OOE-01 O.OOE-01 l.45E-28 SR 89 3.60E 10 O.OOE-01 1. 03E 09 O.OOE-01 O.OOE-01 O.OOE-01 l.39E 09 SR 90 1. 24E 12 O.OOE-01 3.15E 11 O.OOE-01 O.OOE-01 O.OOE-01 l.67E 10 SR. 91 5.21E 05 . O.OOE:-01 1. 97E 04 O.OOE-01 O.OOE-01 O.OOE-01 l. lSE 06 SR 92 7.29E 02 O.OOE-01 2.92E *01 O.OOE-01 0. OOE-'01 O.OOE-01 l.38E 04 y 90 2.30E 04 O.OOE-01 6.17E 02 O.OOE-01 O.OOE-01 O.OOE-01 6.56E 07 y 91M 8.95E-09 O.OOE-01 3.26E-10 O.OOE-01 O.OOE-01 O.OOE-01 1. 75E-05 y 91 1. 86E 07 O.OOE-01 4.99E 03 O.OOE-01 O.OOE-01 O.OOE-01 2.48E 09 y 92 l.59E 00 O.OOE-01 4.54E-02 O.OOE-01 O.OOE-01 O.OOE-01 4.58E 04 y 93 3.0lE 02 O.OOE-01 8.26E 00 O.OOE-01 O.OOE-01 O.OOE-01 4.48E 06 ZR 95 3.86E 06 8.49E 05 7.56E 05 O.OOE-01 l.22E 06 O.OOE-01 8.85E 08 ZR 97 5.70E 02 8.24E 01 4.86E 01 O.OOE-01 1. lBE 02 O.OOE-01 1. 25E 07 NB 95 4.llE 05 l.60E 05 l.14E 05 O.OOE-01 l.50E 05 O.OOE-01 2. 96E 08 MO 99 O.OOE-01 7. 71E 06 l.91E 06 O.OOE-01 l.65E 07 O.OOE-01 6.38E 06 TC 99M 4.71E 00 9.24E 00 l.51E 02 O.OOE-01 l.34E 02 4.69E 00 5.26E 03

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 145 of 160 ATTACHMENT A (Page 137 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-15 (cont'd)

VEGETATION PATHWAY FACTOR M2 MREM/YR. PER µCI/SEC CHILD (RI FACTORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 1. 43E-30 l.49E-30 1. 89E-29 O.OOE-01 2.55E-29 7.90E-31 4.75E-30 RU 103 l.53E 07 O.OOE-01 5.88E 06 O.OOE-01 3.85E 07 O.OOE-01 3. 96E 08 RU 105 9.17E 01 O.OOE-01 3.33E 01 O.OOE-01 8.06E 02 O.OOE-01 5.99E 04 RU 106 7.45E 08 -O.OOE-01 9.30E 07 O.OOE-01 1. OlE 09 O.OOE-01 l .16E 10 AG 110M 3.21E 07 2 .1*7E 07 1. 73E 07 O.OOE-01 4.04E 07 O.OOE-01 2.58E 09 TE 125M 3.51E 08 9.50E 07 4.67E 07 9.84E 07 O.OOE-01 O.OOE-01 3.38E 08 TE 127M 1. 32E 09 3.56E 08 1. 57E 08 3.16E 08 3.77E 09 O.OOE-01 1.07E 09 TE 127 9.85E 03 2.66E 03 2. llE 03 6.82E 03 2.80E 04 O.OOE-01 3.85E 05 TE 129M 8.41E 08 2.35E 08 l.30E 08 2.71E 08 2.47E 09 O.OOE-01 1. 03E 09 TE 129 1.33E-03 3.70E-04 3.15E-04 9.46E-04 3.88E-03 O.OOE-01 8.25E-02 TE 131M 1. 54E 06 5.33E 05 5.68E 05 l. lOE 06 5.16E 06 O.OOE-01 2 .16E 07 TE 131 2.59E-15 7.90E-16 7.71E-16 1. 98E-15 7.84E-15 0. ,OOE-01 1. 36E-14 TE 132 7.00E 06 3.lOE 06 3.74E 06 4.51E 06 2.88E 07' O.OOE-01 3.12E 07 I 130 6.16E 05 1. 24E 06 6.41E 05 1. 37E 08 1. 8 6E. 06 O.OOE-01* 5.82E 05 I 131 1. 43E 08 l.44E 08 8.17E 07 4. 76E 10 2.36E 08 O.OOE-01 1. 28E 07 I 132 .9.23E 01 l.70E 02 ,7.80E 01 7.87E 03 2.60E 02 O.OOE-01 2.00E 02 I 133 3.53E 06 4.37E 06 1.65E 06 8.12E 08 7.28E 06 O.OOE-01 1. 76E 06 I 134 1. 56E-04 2:89E-04 1. 33E-04 6.65E-04 4.42E-04 O.OOE-01 1. 92E-04 I 135 6.26E 04 1.13E 05 5.33E 04 9.98E 06 l.73E 05 O.OOE-01 8.59E 04 cs 134 1.60E 10 2.63E 10 5.55E 09 O.OOE-01 8.15E 09 2.93E 09 1. 42E 08 cs 136 8.04E 07 2.21E 08 1.43E 08 O.OOE-01 1.18E 08 1. 76E 07 7.77E 0.6 cs 137 2.39E 10 2.29E 10 3.38E 09 O.OOE-01 7. 46E 09 2.68E 09 1.43E 08 cs 138 6. 61E-ll 9. 20E-ll 5.83E-ll O.OOE-01 6.47E-ll 6.96E-12 4. 24E-ll BA 139 5.04E-02 2.69E-05 1. 4 6E-03 O.OOE-01 2.35E-05 1.58E-05 2.91E 00 BA 140 2.77E 08 2.43E 05 1. 62E 07 O.OOE-01 7.90E 04 l.45E 05 1.40E 08 BA 141 2.20E-21 1. 23E-24 7.16E-23 O.OOE-01 1. 07E-24 : 7.24E-24 1. 25E-21 BA 142 O.OOE-01 O.OOE-01 O.OOE-01 0. OOE-0°1 O.OOE-01 O.OOE-01 O.OOE-01 LA 140 3.25E 03 l.14E 03 3.83E 02 O.OOE-01 O.OOE-01 O.OOE-01 3.17E 07 LA 142 2.36E-04 7.51E-05 2.35E-05 O.OOE-01 O.OOE-01 O.OOE-01 1.49E 01 CE 141 6.56E 05 3.27E 05 4.86E 04 O.OOE-01 1.43E 05 O.OOE-01 4.08E 08 CE 143 1.72E 03 9.31E 05 1. 35E 02 O.OOE-01 3.91E 02 O.OOE-01 1.36E 07 CE 144 1. 27E 08 3.98E 07 6.78E 06 O.OOE-01 2.21E 07 O.OOE-01 1.04E 10 PR 143 1. 46E 05 4.38E 04 7.23E 03 O.OOE-01 2.37E 04 O.OOE-01 1. 57E 08 PR 144 5.44E-26 1.68E-26 2.74E-27 O'.OOE-01 8.90E-27 O.OOE-01 3.62E-23 ND 147 7.24E 04 5. 86E 04 4.54E 03 O.OOE-01 3.22E 04 O.OOE-01 9.29E 07 w 187 6.47E 04 3.83E 04 1. 72E 04 O.OOE-01 O.OOE-01 O.OOE-01 5.38E 07 NP 239 2.56E 03 1. 84E 02 l.29E 02 O.OOE-01 5.31E 02 O.OOE-01 l.36E 07

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use IPage 146 of 160 ATTACHMENT A (Page 138 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-16 GROUND PLANE PATHWAY FACTOR M2 MREM/YR PER µCI/SEC (RI FACTOR)

H-3 O.OOE 00 Y-91M 1. OOE 05 CS-134 6.86E 09 C-'14 O.OOE 00 Y-91 1.07E 06 CS-136 1. 49E 08 NA-24 1.19E 07 Y-92 l.80E 05 CS-137 1. 03E 10 P-32 O.OOE 00 Y-93 1. 85E 05 CS-138 3.59E 05 CR-51 4.66E 06 ZR-95 2.45E 08 BA-139 1. 06E 05 MN-54 1. 39E 09 ZR-97 2.96E 06 BA-140 2.05E 07 MN-56 9.03E 05 NB-95 1. 37E 08 BA-141 4.18E 04 FE-55 O.OOE 00 M0-99 3.99E 06 BA-142 4.49E 04 FE-59 2.73E 08 TC-99M 1. 84E 05 LA-140 1.92E 07 TC-101 2.04E 04 C0-58 3.79E 08 RU-103 1. 08E 08 LA-142 7.37E 05 C0-60 2.15E 10 RU-105 6.36E 05 CE-141 1. 37E 07 NI-63 O.OOE 00 RU-106 4.21E 08 CE-143 ,2. 31E 06 NI-65 3.02E 05 AG-llOM 3.44E 09 CE-144 6.96E 07 CU-64 6.07E 05 TE-125M 1.55E 06 PR-143 O.OOE 00 ZN-65 7.46E 08 TE-127M 9.17E 04 PR-144 1. 83E 03 ZN-69 O.OOE 00 TE-127 2.98E 03 ND-147 8.46E 06 BR-83 4.87E 03 TE-129M 1. 98E 07 W-187 2.36E 06 BR-84 2.03E 05 TE-129 2.62E 04 NP-239 1.71E 06 BR-85 O.OOE 00 TE-131M 8.03E 06 RB-86 8.99E 06 TE-131 2.92E 04 RB-88 3.31E 04 TE-132 4.23E 06 RB-89 1. 21E 05 I-130 5.51E 06 SR-89 2.16E 04 I-131 1.72E 07 SR-90 O.OOE 00 I-132 1. 25E 06 SR-91 2.14E 06 I-133 2.45E 06 SR-92 7.77E 05 I-134 4.47E 05 Y-90 4. 49E 03 I-135 2.53E 06

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use ~age 147 of 160 ATTACHMENT A (Page 139 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-17 GRASS-GOAT-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC ADULT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 1. 56E 03 1.56E 03 1.56E'03 1.56E 03 1.56E 03 1. 56E 03 C 14 2.63E 08 5.27E 07 5.27E 07 5.27E 07 5.27E 07 5.27E 07 5.27E 07 NA 24 2.93E 05 2.93E 05 2.93E 05 2.93E 05 2.93E 05 2.93E 05 2.93E 05 p 32 2.05E 10 1.27E 09 7.93E 08 O.OOE-01 O.OOE-01 O.OOE-01 2.31E 09 CR 51 O.OOE-01 O.OOE-01 3.43E 03 2.05E 03 7.55E 02 4.55E 03 8.62E 05 MN 54 O.OOE-01 1. OlE 06 l.93E 05 O.OOE-01 3.00E 05 O.OOE-01 3.09E 06 MN 56 O.OOE-01 4.99E-03 8.85E-04 O.OOE-01 6.34E-03 O.OOE-01

1. 59E-01 FE 55 3.26E 05 2.25E 05 5.26E 04 O.OOE-01 O.OOE-01 1. 26E 05 l.29E 05 FE 59 3. 86E 05 9.07E 05 3.48E 05 O.OOE-01 O.OOE-01 2.54E 05 3.02E 06 co 58 0.00E-01 5.66E 05 1. 27E 06 O.OOE-01 O.OOE-01 O.OOE-01 l.15E 07 co 60 O.OOE-01 1. 97E 06. 4.34E 06 O.OOE-01 O.OOE-01 O.OOE-01 3.70E 07 NI 63 8.07E 08 5.65E 07 2. 71E 07 O.OOE-01 O.OOE-01 O.OOE-01 l.17E 07 NI 65 5.56E-02 7.22E-03 3.30E-03 O.OOE-01 O.OOE-01 O.OOE-01 l.83E-01 cu 64 O.OOE-01 2.66E 03 1. 25E 03 O.OOE-01 6.70E 03 O.OOE-01 2.27E 05 ZN 65 1. 65E 08 5.24E 08 2.37E 08 O.OOE-01 3.50E 08 O.OOE-01 3.30E 08 ZN 69 6.27E-13 l.20E-12 8.34E-14 O.OOE-01 7.79E-13 O.OOE-01 1. 80E-13 BR 83 O,OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0. OOE:...01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 . 0. OOE-01 RB 86 O.OOE-01 3.llE 08 1. 45E 08 O.OOE-01 O.OOE-01 O.OOE-01 6.14E 07 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 3.05E 09 O.OOE-01 8.75E 07 O.OOE-01 O.OOE-01 O.OOE-01 4.89E 08 SR 90 9.83E 10 O.OOE-01 2. 41E 10 O.OOE-01 O.OOE-01 O.OOE-01 2.84E 09 SR 91 6.02E 04 O.OOE-01 2.43E 03 O.OOE-01 O.OOE-01 O.OOE-01 2.87E 05 SR 92 l.03E 00

O.OOE-01 4.45E-01 O.OOE-01 O.OOE-01 O.OOE-01 2.04E 01 y 90 8.49E 00 O.OOE-01 2.28E-00 O.OOE-01 O.OOE-01 O.OOE-01 9.00E 04 y 91M 7.24E-21 O.OOE-01 2.80E-22 O.OOE-01 O.OOE-01 O.OOE-01 2.13E-20 y 91 1. 03E 03 O.OOE-01 2. 76E 01 0. O-OE-01 O.OOE-01 O.OOE-01 5.67E 05 y 92 6.71E-06 O.OOE-01 1. 96E-07 O.OOE-01 O.OOE-01 O.OOE-01 l.18E-Ol y 93 2.80E-02 O.OOE-01 7.73E-04 O.OOE-01 O.OOE-01 O.OOE-01 8.87E 02 ZR 95 l.13E 02 3.63E 01 2.46E 01 O.OOE-01 5.70E 01 O.OOE-01 l.15E 05 ZR 97 5.20E-02 l.05E-01 4.80E-03 O.OOE-01 1.58E-01 O.OOE-01 3.25E 03 NB 95 9.91E 03 5.51E 03 2.96E 03 O.OOE-01 5.45E 03 O.OOE-01 3.35E 07 MO 99 O.OOE-01 2.97E 06 5.65E 05 O.OOE-01 6.73E 06 O.OOE-01 6.89E 06 TC 99M 3.99E-01 l.13E 00 1. 44E 01 O.OOE-01 1. 71E 01 5.53E-01 6.67E 02

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 148 of 160 ATTACHMENT A (Page 140 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-17 (cont'd)

GRASS-GOAT-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC ADULT NUCLIDE* BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU. 103 1. 22E 02 O.OOE-01 5.26E 01 O.OOE-01 4.66E 02 O.OOE-01 1.43E 04 RU 105 1.03E-04 O.OOE-01 4.07E-05 O.OOE-01 1.33E-03 O.OOE-01 6.30E-02 RU 106 2.45E 03 O.OOE-01 3.lOE 02 O.OOE-01 4.73E 03 O.OOE-01 1. SSE 05 AG 110M 6.99E 06 6.46E 06 3.84E 06 O.OOE-01 1. 27E 07 O.OOE-01 2.64E 09 TE 125M 1. 95E 06 7.0BE 05 2.62E 05 5.BBE 05 7.95E 06 O.OOE-01 7.BlE 06 TE 127M 5.49E 06 1.96E 06 6. 70E 05 l.40E 06 2.23E 07 O.OOE-01 1.84E 07 TE 127 7.84E 01 2.82E 01 1.70E 01 5. 81E 01 3.19E 02 O.OOE-01 6.19E 03 TE 129M 7.22E 06 2.69E 06 1.14E 06 2.48E 06 3.02E 07 O.OOE-01 3.64E 07 TE 129 3.41E-11 l.28E-11 8.31E-12 2. 62E-11 1. 43E-10 O.OOE-01 2. 57E-11 TE 131M 4.33E 04 2.12E 04 1. 77E 04 3. 36E 04 2.15E 05 O.OOE-01 2.lOE 06 TE 131 4.40E-34 1.84E-34 1. 39E-34 3.62E-34 l.93E-33 O.OOE-01 6.23E-35 TE 132 2.88E 05 1. 86E 05 l.75E 05 2.06E 05 1.80E 06 O.OOE-01 8.82E 06 I 130 5.04E 05 1.49E 06 5.87E 05 1.26E 08 2.32E 06 O.OOE-01 1. 28E 06 I 131 3.55E 08 5.08E 08 2.91E 08 l.67E 11 8. 71E 08 O.OOE-01 1. 34E 08 I 132 1.98E-00 5.29E-00 1. 85E-00 1. SSE 01 8.43E-00 O.OOE-01 9.94E-01 I 133 4.65E 06 8.0BE 06 2.46E 06 1.19E 09 1.41E 07 O.OOE-01 7.26E 06 I 134 2.44E-12 6.63E-12 2.37E-12 1. lSE-10 1. OSE-11 O.OOE-01 5.78E-15 I 135. 1. 54E 04 4.04E 04 1.49E 04 2.66E 06 6.48E 04 O.OOE-01 4. 56E 04 cs 134 1.70E 10 4.04E 10 3.30E 10 O.OOE-01 1. 31E 10 4.34E 09 7. 06E 08 cs 136 7.83E 08 3.09E 09 2.23E 09 O.OOE-01 1. 72E 09 2.36E 08 3.51E 08 cs 137 2.21E 10 3.03E 10 1. 98E 10 O.OOE-01 1. 03E 10 3.42E 09 5.86E 08 cs 138 2.75E-23 5.43E-23 2.69E-23 O.OOE-01 3.99E-23 3.94E-24 2.32E-28 BA 139 5.48E-09 3.90E-12 1. 60E-10 O.OOE-01 3.65E-12 2.21E-12 9.71E-09 BA 140 3.23E 06 4.0SE 03 2. llE 05 O.OOE-01 1. 38E 03 2.32E 03 6.64E 06 BA 141, O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 142 O.OOE-01 O.OOE-01 *O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA 140 5.43E-01 2.73E-01 7.23E-02 O.OOE-01 O.OOE-01 O.OOE-01 2.0lE 04 LA 142 1.13E-12 5.12E-13 1. 28E-13 O.OOE-01 O.OOE-01 . 0. OOE-01 3.74E-09 CE 141 5. 81E 02 3.93E 02 4.46E 01 O.OOE-01 1. 83E 02 0. o*oE-01 1. SOE 06 CE 143 4.99E 00 3.69E 03 4.08E-00 O.OOE-01 1.62E 00 O.OOE-01 1. 38E 05 CE 144 4.29E 04 1.79E 04 2.30E 03 O.OOE-01 1.06E 04 O.OOE-01 1.45E 07 PR 143 1.90E 01 7.60E 00 9.39E-00 O.OOE-01 4.39E 00 O.OOE-01 8.30E 04 PR 144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND 147 1.14E 01 1. 31E 01 7.BSE-01 O.OOE-01 7.67E 00 O.OOE-01 6.30E 04 w 187 7.87E 02 6.58E 02 2.30E 02 O.OOE-01 O.OOE-01 O.OOE-01 2.16E 05 NP 239 4.41E-01 4.33E-02 2.39E-02 O.OOE-01 1. 35E-01 O.OOE-01 8.89E 03

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 149 of 160 ATTACHMENT A (Page 141 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 5-18 GRASS.-GOAT-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC TEEN NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 2.03E 03 2.03E 03 2.03E 03 2.03E 03 2.03E 03 2.03E 03 C 14 4.86E 08 9. 72E 07 9. 72E 07 9. 72E 07 9.72E 07 9.72E 07 9.72E 07 NA 24 5.llE 05 5.llE 05 5.llE 05 5.llE 05 5.llE 05 5.llE 05 5.llE 05 p 32 3.78E 10 2.34E 09 1.47E 09 O.OOE-01 O.OOE-01 O.OOE-01 3.18E 09 CR 51 O.OOE-01 O.OOE-01 5.99E 03 3.33E 03 1. 31E 03 8.55E 03 1. OlE 06 MN 54 O.OOE-01 1.68E 06 3.34E 05 O.OOE-01 5.02E 05 O.OOE-01 3.45E 06 MN 56 O.OOE-01 8.85E-04 1. 57E-04 O.OOE-01 l.12E-03 O.OOE-01 5.82E-02 FE 55 5.79E 05 4.lOE 05 9.57E 04 O.OOE-01 O.OOE-01 2.60E 05 l.78E 05 FE 59 6.74E 05 1. 57E 06 6.07E 05 O.OOE-01 O.OOE-01 4.96E 05 3.72E 06 co 58 O.OOE-01 9.52E 05 2.19E 06 O.OOE-01 O.OOE-01 O.OOE-01 1.31E 07 co 60 O.OOE-01 3.34E 06 7.52E 06 O.OOE-01 O.OOE-01 O.OOE-01 4.35E 07 NI 63 1. 42E 09 1. ODE 08 4.81E 07 O.OOE-01 O.OOE-01 O.OOE-01 l.59E 07 NI 65 1.02E-01 1.30E-02 5.92E-03 O.OOE-01 O.OOE-01 O.OOE-01 7.05E-01 cu 64 O.OOE-01 4.74E 03 2.23E 03 O.OOE-01 1. 20E 04 O.OOE-01 3.67E 05 ZN 65 2.53E 08 8.78E 08 4.09E 08 O.OOE-01 5. 62E 08 O.OOE-01 3.72E 08 ZN 69 1.15E-12 2.20E-12 1. 54E-13 O.OOE-01 1. 44E-12 O.OOE-01 4.05E-12 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85. O.dOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 5.67E 08 2.67E 08 O.OOE-01 O.OOE-01 O.OOE-01 8.40E 07 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 5.62E 09 O.OOE-01 1.61E 08 O.OOE-01 O.OOE-01 O.OOE-01 6.69E 08 SR 90 l.39E 11 O.OOE-01 3.43E 10 O.OOE-01 O.OOE-01 O.OOE-01 3.90E 09 SR 91 1. llE 05 O.OOE-01 4.40E 03 O.OOE-01 O.OOE-01 O.OOE-01 5.02E 05 SR 92 1. 88E 00 O.OOE-01 8.02E-02 O.OOE-01 O.OOE-01 O.OOE'-01 4.80E 01 y 90 1. 56E 01 O.OOE-01 4.20E-00 O.OOE-01 O.OOE-01 O.OOE-01 1.29E 05 y 91M 1.33E-20 O.OOE-01 5. 07E-22 . 0.00E-01 O.OOE-01 O.OOE-01 6.26E-19 y 91 1. 90E 03 O.OOE-01 5.08E 01 O.OOE-01 O.OOE-01 O.OOE-01 7.77E 05 y 92 1.24E-05 0.00E-01 3.59E-07 *O.OOE-01 O.OOE-01. O.OOE-01 3.40E-01 y 93 5.16E-02 0.00E-01 1. 41E-03 O.OOE-01 O.OOE-01 O.OOE-01 l.58E 03 ZR 95 1. 98E 02 6.25E 01 4.30E 01 O.OOE-01 9.18E 01 O.OOE-01 1. 44E 05 ZR 97 9. 47E-.02 1.87E-02 8.63E-03 O.OOE-01 2.84E-02 O.OOE-01 5.07E 03 NB 95 1. 69E 04 9.37E 03 5.16E 03 O.OOE-01 9.09E 03 O.OOE-01 4. OlE 07 MO 99 O.OOE-01 5.37E 06 1.02E 06 O.OOE-01 1. 23E 07 O.OOE-01 9.61E 06 TC 99M 6.92E-00 1.93E 00 2.50E 01 O.OOE-01 2.88E 01 1. 07E 00 1.27E 03 TC 101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION.MANUAL Information Use Page 150 of 160 ATTACHMENT A (Page 142 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 5-18 (cont'd)

GRASS-GOAT-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC TEEN NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI RU 103 2.17E 02 O.OOE-01 9.28E 01 O.OOE-01 7.66E 02 O.OOE-01 1. 81E 04 RU 105 1. 88E-04 0. OOE-:-01 7.30E-05 O.OOE-01 2.37E-03 O.OOE-01 1. 52E-01 RU 106 4.SOE 03 O.OOE-01 5.67E 02 O.OOE-01 8.68E 03 O.OOE-01 2 .16E 05 AG 110M 1.16E 07 1.09E 07 6.65E 06 O.OOE-01 2.08E 07 O.OOE-01 3.07E 09 TE 125M 3.60E 06 1. 30E 06 4.82E 05 1. OlE 06 O.OOE-01 O.OOE-01 l.06E 07 TE 127M 1. OlE 07 3.59E 06 1.20E 06 2.41E 06 4.lOE 07 O,OOE-01 2.52E 07 TE 127 1. 45E 02 5.15E 01 3.13E 01 1. OOE 02 5.89E 02 O.OOE-01 1.12E 04 TE 129M 1.32E 07 4.90E 06 2.09E 06 4.26E 06 5.53E 07 O.OOE-01 4.96E 07 TE 129 6.28E-11 2. 34E-11 1. 53E-11 4. 48E-11 2.63E-10 O.OOE-01 3.43E-10 TE 131M 7.89E 04 3.78E 04 3 .16E 04 5.69E 04 3.94E 05 O.OOE-01 3.04E 06 TE 131 8.04E-34 3.31E-34 ' 2. SlE-34 6.19E-34 3.SlE-33 O.OOE-01 6.60E-35 TE 132 5.15E 05 3.26E 05 3.07E 05 3.44E 05 3.13E 06 O.OOE-01 1. 03E 07 I 130 8.87E 05 2.57E 06 1. 02E 06 2.09E 08 3.95E 06 O.OOE-01 1.97E 06 I 131 6. 45E 08 9.03E 08 4.85E 08 2.63E 11 1. SSE 09 O.OOE-01 l.79E 08 I 132 3.SlE-01 9.18E-01 3.29E-01 3.09E 01 l.45E 00 O.OOE-01 4.00E-01 I 133 8.49E 06 1.44E 07 4.39E 06 2. OlE 09 2.52E 07 O.OOE-01 1.09E 07 I 134 4.34E-12 1. lSE-11 4.13E-12 1.92E-10 1.81E-11 O.OOE-01 1. SlE-13 I 135 2.74E 04 7.0SE 04 2.61E 04 4.54E 06 1.11E 05 O.OOE-01 7.82E 04 cs 134 2.94E 10 6.93E 10 3.22E 10 O.OOE-01 2.20E 10 8.41E 09 8.62E 08 cs 136 1. 33E 09 5.25E 09 3.52E 09 O.OOE-01 2. 86E 09 4.SOE 08 4.22E 08 cs 137 4.02E 10 5.34E 10 1. 86E 10 O.OOE-01 l.82E 10 7.06E 09 7.60E 08 cs 138 4.99E-23 9.58E-23. 4.79E-23 O.OOE-01 7.07E-23 8.23E-24 4.34E-26 BA 139 1. OlE-08 7.lJE-12 2.95E-10 O.OOE-01 6.72E-12 4.91E-12 9.04E-08 BA 140 5.82E 06 7.14E 03 3.75E 05 O.OOE-01 2.42E 03 4.08E 03 8.98E 06 BA 141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA 140 9.75E-01 4.79E-01 1.27E-01 O.OOE-01 O.OOE-01 O.OOE-01 2.75E 04 LA 142 2.03E-12 9.03E 13 2. 25E-13 O.OOE-01 O.OOE-01 O.OOE-01 2.75E-08 CE 141 1.07E 03 7.12E 02 8.18E 01 O.OOE-01 3.35E 02 O.OOE-01 2.04E 06 CE 143 9.17E 00 6.67E 03 7.45E-00 O.OOE-01 2.99E 00 O.OOE-01 2; OlE 05 CE 144 7.90E 04 3.27E 04 4.24E 03 O.OOE-01 1. 95E 04 O.OOE-01 1.99E 07 PR 143 3.48E 01 l.39E 00 1. 73E 00 O.OOE-01 8.08E 00 O.OOE-01 1.15E 05 PR 144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND 147 2.19E 01 2.38E 01 1.42E 00 O.OOE-01 1.40E 01 O.OOE-01 8.57E 04 w 187 1. 44E 03 1.1 7E 03 4 .11E 02 O.OOE-01 O.OOE-01 O.OOE-01 3.18E 05 NP 239 8.41E-01 7.93E-02 4.41E-02 O.OOE-01 2.49E-01 O.OOE-01 1.28E 04

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 151 of 160 ATTACHMENT A (Page 143 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 5-19 GRASS-GOAT-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC CHILD NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 O.OOE-01 3.20E 03 3.20E 03 3.20E 03 3.20E 03 3.20E 03 3.20E 03 C 14 1.19E 09 2.39E 08 2.39E 08 2.39E 08 2.39E 08 2.39E 08 2.39E 08 NA 24 1.06E 06 1. 06E 06 1.06E 06 l.06E 06 1.06E 06 1.06E 06 1.06E 06 p 32 9.33E 10 4.37E 09 3.60E 09 O.OOE-01 O.OOE-01 O.OOE-01 2.SBE 09 CR 51 O.OOE-01 O.OOE-01 l.22E 04 6.78E 03 1. SSE 03 1. 24E 04 6.48E 05 MN 54 O.OOE-01 2.52E 06 6.70E 05 O.OOE-01 7.06E 05 O.OOE-01 2. llE 06 MN 56 O.OOE-01 1. 54E-03 3.48E-04 O.OOE-01 1. 87E-03 O.OOE-01 2.24E-01 FE 55 1. 45E 06 7.70E 05 2.39E 05 O.OOE-01 O.OOE-01 4.36E 05 1.43E 05 FE 59 1. 56E 06 2.53E 06 l.26E 06 O.OOE-:01 O.OOE-01 7.33E 05 2.63E 06 co 58 O.OOE-01 1. 46E 06 4.45E 06 O.OOE-01 O.OOE-01 O.OOE-01 8.49E 06 co 60 O.OOE-01 5.lBE 06 1. 53E 07 0. OOE-01' O.OOE-01 O.OOE-01 2.87E 07 NI 63 3.56E 09 1. 90E 08 l.21E 08 O.OOE-01 O.OOE-01 O.OOE-01 1.28E 07 NI 65 2.49E-01 2.34E-02 1.37E-02 O.OOE-01 O.OOE-01 O.OOE-01 2.87E 00 cu 64 O.OOE-01 8.23E 03 5.03E 03 O.OOE-01 2.0lE 04 O.OOE-01 3.91E 05 ZN 65 4.96E 08 1. 32E 09 8.22E 08 O,OOE-01 8.33E 08 O.OOE-01 2.32E 08 ZN 69 2.84E-12 4.lOE-12 3.79E-13 O.OOE-01 2.49E-12 O.OOE-01 2.SBE-10 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 1. OSE 09 6.47E 08 O.OOE-01 O.OOE-01 O.OOE-01 6.77E 07 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01* O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.39E 10 O.OOE-01 3.97E OB O.OOE-01 O.OOE-01 O.OOE-01 5.38E 08 SR 90 2.35E 11 O.OOE-01 5.95E 10 O.OOE-01 O.OOE-01 O.OOE-01 3 .16E 09 SR 91 2.71E 05 O.OOE-01 l.02E 04 O.OOE-01 O.OOE-01 O.OOE-01 5.99E 05 SR 92 4.60E 00 O.OOE-01 1.84E-01 O.OOE-01 O.OOE-01 . 0. OOE-01 8. 71E 01 y _go 3. 86E 01 O.OOE-01 1.03E-00 O.OOE-01 O.OOE-01 O.OOE-01 1.lOE 05 y 91M 3.24E-20 O.OOE-01 l. lBE-21 O.OOE-01

0. OOE-01 O.OOE-01 6.34E-17 y 91 4. 68E 03 O.OOE-01 1. 25E 00 O.OOE-01 O.OOE-01 O.OOE-01 6.24E 05 y 92 3.04E-05 O.OOE-01 8. 71E-07 O.OOE-01 O.OOE-01 O.OOE-01 8.79E-01 y 93 1. 27E-01 O.OOE-01 3.48E-03 O.OOE-01 O.OOE-01 O.OOE-01 1.89E 03 ZR 95 4.60E 02 1. OlE 02 9.00E 01 O.OOE-01 1.45E 02 O.OOE-01 1. OSE 05 ZR 97 2.30E-01 3.33E-02 1. 96E-02 O.OOE-01 4.78E-02 O.OOE-01 5.04E 03 NB 95 3.82E 04 1.49E 04 1.06E 04 O.OOE-01 1.40E 04 O.OOE-01 2.75E 07 MO 99 0.00E-01 9.76E 06 2.42E 06 O.OOE-01 2.0BE* 07 O.OOE-01 8.07E 06 TC 99M 1. 59E oo 3.llE 00 5.16E 01 O.OOE-01 4.52E 01 1. SSE 00 1.77E 03 TC 101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 o.ooi;::-01 O.OOE-01 O.OOE-01

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use !Page 152 of 160 ATTACHMENT A (Page 144 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-19 (cont'd)

GRASS-GOAT~MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC CHILD NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI RU 103 5.14E02 O.OOE-01 1. 97E 02 O.OOE-01 l.29E 03 O.OOE-01 1. 33E 04 RU 105 4.59E-04 O.OOE-01 l.67E-04 O.OOE-01 4.04E-03 O.OOE-01 3.00E-01 RU 106 l. llE 04 O.OOE-01 l.38E 03 O.OOE-01 1. SOE 04 O.OOE-01 1. 72E 05 AG 110M 2.51E 07 1. 69E 07 l.35E 07 O.OOE-01 3.15E 07 O.OOE-01 2.0lE 09 TE 125M 8.85E 06 2.40E 06 l.18E 06 2.48E 06 O.OOE-01 O.OOE-01 8.54E 06 TE 127M 2.50E 07 6. 72E 06 2.96E 06 5.97E 06 7.12E 07 O.OOE-01 2.02E 07 TE 127 3.57E 02 9.64E 01 7.67E 01 2.47E 02 1. 02E 03 O.OOE-01 l.40E 04 TE 129M 3.26E 07 9.09E 06 5.05E 06 1. 05E 07 9.56E 07 O.OOE-01 3.97E 07 TE 129 1. 55E-10 4.32E-11 3. 68E-ll l.llE-10 4.53E-10 O.OOE-01 9.64E-09 TE 131M 1. 92E 05 6.64E 04 7.07E 04 l.37E 05 6.43E 05 O.OOE-01 2.69E 06 TE 131 l.97E-33 6.0lE-34 5.87E-34 l.51E-33 5.97E-33 O.OOE-01 l.04E-32 TE 132 l.23E 06 5.44E 05 6.58E 05 7.93E 05 5.05E 06 O.OOE-01 5.48E 06 I 130 2.07E 06 4.19E 06 2.16E 06 4.62E 08 6.27E 06 O.OOE-01 l.96E 06 I 131 1. 56E 09 l.57E 09 8.94E 08 5.20E 11 2.58E 09 O.OOE-01 l.40E 08 I 132 8.30E-01 l.52E 00 7.0lE-01 7.07E 01 2.33E 00 O.OOE-01 l.79E 00 I 133 2.06E 07 2.55E 07 9.65E 06 4.74E 09 4.25E 07 O.OOE-01 1. 03E 07 I 134 1. 03E-ll l.91E-ll 8.77E-12 4.39E-10 2.92E-ll O.OOE-01 1. 26E-ll I 135. 6.49E 04 l.17E 05 5.52E 04 1. 03E 07 l.79E 05 O.OOE-01 8.90E 04 cs 134 6.79E 10 l.llE 11 2.35E 10 O.OOE-01 3. 45E 10 1. 24E 10 6.0lE 08 cs 136 3.0lE 09 8.27E 09 5.35E 09 O.OOE-01 4.40E 09 6.57E 08 2.91E 08 cs 137 9.67E 10 9.26E 10 1. 37E 10 O.OOE-01 3.02E 10 1:09E 10 5.80E 08 cs 138 1. 21E-22 l.68E-22 l.07E-22 O.OOE-01 l.18E-22 1. 27E-23 7.74E-23 BA 139 2.49E-08 1. 33E-ll 7.21E-10 O.OOE-01 l.16E-ll 7.82E-12 1. 44E-06 BA 140 l.41E 07 l.23E 04 8.21E 05 O.OOE-01 4.0lE 03 7.34E 03 7.12E 06 BA 141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA 140 2.33E 00 8.16E-00 2.75E-01 O.OOE-01 O.OOE-01 O.OOE-01 2.27E 04 LA 142 4.91E-12 l.56E-12 4.90E-13 O.OOE-01 O.OOE-01 O.OOE-01 3.lOE-07 CE 141 2.63E 03 l.31E 03 l.94E 02 O.OOE-01 5.74E 02 O.OOE-01 l.63E 06 CE 143 2.25E 01 1. 22E 04 l.77E 00 O.OOE-01 5.12E 00 O.OOE-01 l.79E 05 CE 144 l.95E 05 6. llE 04 l.04E .04 O.OOE-01 3.38E 04 O.OOE-01 l.59E 07 PR 143 8.62E 01 2.59E 01 4.28E 00 O.OOE-01 1. 40E 01 O.OOE-01 9.30E 04 PR 144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND 147 5.36E 01 4.34E 01 3.36E 00 O.OOE-01 2.38E 01 O.OOE-01 6.88E 04 w 187 3.49E 03 2.07E 03 9.28E 02 O.OOE-01 O.OOE-01 O.OOE-01 2.90E 05 NP 239 2.07E 00 1. 4 9E-01 1. 04E-01 O.OOE-01 4.30E-01 O.OOE-01 l.lOE 04

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 153 of 160 ATTACHMENT A (Page 145 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A. 5-20 GRASS-GOAT-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC INFANT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG .GI-LLI H 3 O.OOE-01 4. 86E 03 4. 86E 03 4.86E 03 4.86E 03 4.86E 03 4.86E 03 C 14 2.34E 09 5.00E 08 5.00E 08 5.00E 08 5.00E 08

5.00E 08 5.00E 08 NA 24 1. SSE 06 1. SSE 06 l.BSE 06 1 .. SSE 06 l.BSE 06. 1. SSE 06 l.BSE 06 p 32 1. 92E 11 l.13E 10 7.45E 09 O.OOE-01 O.OOE-01 O.OOE-01 2.60E 09 CR 51 O.OOE-01 O.OOE-01 1. 94E 04 1. 26E 04 2. 76E 03 2. 46E 04 5.64E 05 MN 54 O.OOE-01 4.68E 06. 1. 06E 06 O.OOE-01 l.04E 06 O.OOE-01 l.72E 06 MN 56 O.OOE-01 3.78E-03 6.SlE-04 O.OOE-01 3.25E-03 O.OOE-01 3.43E-01 FE 55 1. 76E 06 l.13E 06 3.03E 06 O.OOE-01 O.OOE-01 5.54E 05 1. 44E 05 FE 59 2.92E 06 5.09E 06 2.0lE 06 O.OOE-01 O.OOE-01 l.SlE 06 2.43E 06 co 58 O.OOE-01 2.91E 06 7. 26E 06 O.OOE-01 O.OOE-01 O.OOE-Oi 7.25E 06 co 60 O.OOE-01 l.06E 07 2.SOE 07 O.OOE-01 O.OOE~Ol O.OOE-01 2.52E 07

.NI 63 4.i9E 09 2.59E 08 l.45E 08 O.OOE-01 O.OOE-01 O.OOE-01 l.29E 07

NI 65 5.27E-01 5.96E-02 2. 71E-02 O.OOE-01 O.OOE-01 O.OOE-01 4.54E 00 cu 64 O.OOE-01 2.07E 04 9.SBE 03 OiOOE-01 3.SOE 04 O.OOE-01 4.25E 05 ZN 65 6.66E 08 2.2BE 09 1. OSE 09 O.OOE-01 l. llE 09 O.OOE-01 l.93E 09 ZN 69 6,04E-12 1. 09E-ll 8.lOE-13 O.OOE-01 4.52E-12 O.OOE-Ot 8.87E-10 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 2.67E 09 1. 32E 09 O.OOE-01 0. OOE-.01 O.OOE-01 6.83E 07 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0 .. OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.64E 10 O.OOE-01 7.58E 08 O.OOE-01 O.OOE-01 O.OOE-01 5.43E 08 SR 90 2.55E 11 O.OOE-01 6.SOE 10 O.OOE-01 O.OOE-01 O.OOE-01 3.19E 09 SR 91 5.65E 05 O.OOE-01 2.05E 03 O.OOE-01 O.OOE-01 O.OOE-01 6.69E 05 SR 92 9.78E 00 O.OOE-01 3.63E-01 O.OOE-01 O.OOE-01 O.OOE-01 1. OSE 02 y 90 8.16E 01 O.OOE-01 2.19E 00 0. OOE-0.1 O.OOE-01 O.OOE-01 l.13E 05 y 91M 6.87E-20 O.OOE-01 2.34E-21 O.OOE-01 O.OOE-01 O.OOE-01 2.29E-16 y 91 8.79E 03 O.OOE-01 2.34E 02 O.OOE-01 O.OOE-01 O.OOE-01 6.30E 05 y 92 6.47E-05 O.OOE-01 l.82E-06 O.OOE-01 O.OOE-01 O.OOE-01 1. 23E 00 y 93 2.70E-01 O.OOE-01 7.36E-03 O.OOE-01 O.OOE-01 O.OOE-01 2.13E 03 ZR 95 8 .17E 02 . 1. 99E 02 1. 41E 02 O.OOE-01 2.14E 02 O.OOE-01 9.91E 04 ZR 97 4.BBE-01 8.37E-02 3.82E-02 O.OOE-01 8.44E-02 O.OOE-01 5.34E 03 NB 95 7.12E 04 2.93E 04 l.70E 04 O.OOE-01 2.lOE 04 O.OOE-01 2.48E 07 MO 99 O.OOE-01 2.50E 07 4.87E 06 O.OOE-01 3.73E 07 O.OOE-01 8.22E 06 TC 99M 3.30E 00 6.BlE 00 8.77E 01 O.OOE~Ol 7.33E 01 3.56E 00 l.98E 03

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 154 of 160 ATTACHMENT A (Page 146 of 152)

OFFSITE DOSE CALCULATION MANUAL TABLE A.5-20 (cont'd)

GRASS-GOAT-MILK PATHWAY FACTOR M2 MREM/YR PER µCI/SEC INFANT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU 103 1. 04E 03 O.OOE-01 3.48E 02 O.OOE-01 2.16E 03 O.OOE-01 1. 26E 04 RU 105 9.68E-04 O.OOE-01 3.26E-04 O.OOE-01 7.12E-03 O.OOE-01 3.85E-01 RU 106 2.28E 04 O.OOE-01 2.85E. 03 O.OOE-01 2.70E 04 O.OOE-01 1.73E 05 AG 110M 4.63E 07 3.38E 07 2.24E 07 O.OOE-01 4.83E 07 O.OOE-01 1.75E 09 TE 125M 1.81E 07 6.05E 06 2.45E 06 6.09E 06 O.OOE-01 O.OOE-01 8.62E 06, TE 127M 5.05E 07 1.68E 07 6.12E 06 1. 46E 07 1.24E 08 O.OOE-01 2.04E 07 TE 127 7.59E 02 2.54E 02 1.63E 02 6.18E 02 1. 85E 03 O.OOE-01 1.59E 04 TE 129M 6.69E 07 2.29E 07 1. 03E 07 2.57E 07 1.67E 08 O.OOE-01 3.99E 07 TE 129 3.28E-10 1.13E-10 7. 66E-11 2.75E-10 8.17E-10 O.OOE-01 2.62E-08 TE 131M 4. 05E 05 1. 63E 05 1. 35E 05 3.31E 05 l.12E 06 O.OOE-01 2.75E 06 TE 131 4.18E-33 1.54E-33 1.17E-33 3.73E-33 1.07E-32 O.OOE-01 1. 69E-31 TE 132 2.53E 06 1. 25E 06 1.17E 06 1. 85E 06 7.84E 06 O.OOE-01 4.64E 06 I 130 4.26E 06 9.38E 06 3.76E 06 1.05E 09 1. 03E 07 O.OOE-01 2.0lE 06 I 131 3.26E 09 3.85E 09 1. 69E 09 1.26E 12 4.49E 09 O.OOE-01 1. 37E 08 I 132 1. 72E 00 3.49E 00 1. 24E 00 1.64E 02 3.90E 00 O.OOE-01 2.83E 00 I 133 4.35E 07 6.34E 07 1. 86E 07 1.15E 10 7.45E 07 O.OOE-01 1. 07E 07 I 134 2.13E-11 4.36E-11 1. 55E-11 1.02E-09 4.88E-11 O.OOE-01 4. 51E-11 I 135 1.35E 05 2.68E 05 9.79E 04 2.41E 07 2.99E 05 O.OOE-01 9.71E 04 cs 134 1.09E 11 2.04E 11 2.06E 10 O.OOE-01 5.25E 10 1. 86E 10 5.54E 08 cs 136 5.88E 09 1. 73E 10 6. 45E 09 O,OOE-01 6.89E 09 1. 41E 09 2.63E 08 cs 137 1. 54E 11 1. 81E 11 1.28E 10 O.OOE-01 4.85E 10 1. 96E 10 5.65E 08 cs 138 2.55E-22 4.15E-22 2.0lE-22 O.OOE-01 2.07E-22 3.23E-23 6.63E-22 BA 139 5.30E-08 3. 51E-11 1. 53E-09 O.OOE-01 2 .11E-11 2 .13E-11 3.35E-06 BA 140 2.89E 07 2.89E 04 .1. 4 9E 06 O.OOE-01 6.87E 03 l.78E 04 7 .11E 06 BA 141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA 142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 p.OOE-01 LA 140 4.88E 00 1.92E 00 4.94E-00 O.OOE-01 O.OOE-01 O.OOE-01 2.26E 04 LA 142 1. 03E-11 3.78E-12 9.06E-13 O.OOE-01 O:OOE-01 O.OOE-01 6.43E-07 CE 141 5.20E 03 3.17E 03 3.74E 02 O.OOE-01 9.79E 02 O.OOE-01 1.64E 06 CE 143 4. 76E 01 3 .16E 04 3.61E 00 O.OOE-01 9. 21E 00 O.OOE-01 1.84E 05 CE 144 2. 79E 05 l.14E 05 1.56E 04 O.OOE-01 4.62E 04 O.OOE-01 1.60E 07 PR 143 1.78E 02 6.67E 01 8.84E 00 O.OOE-01 2.48E 01 O.OOE-01 9.41E 04 PR 144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND 147 1.06E 02 1.09E 02 6.69E 00 O.OOE-01 4.21E 01 O.OOE-01 6.92E 04 w 187 7.35E 03 5.11E 03 1. 77E 03 O.OOE-01 O.OOE-01 O.OOE-01 3.00E 05 NP 239 4.38E 00 . 3.91E-01 2.21E-01 O.OOE-01 7.80E-01 O.OOE-01 1.13E 04

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use 0 age 155 of 160 ATTACHMENT A (Page 147 of 152)

OFFSITE DOSE CALCULATION MANUAL APPENDIX B Meteorological Model

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use Page 156 of 160 ATTACHMENT A (Page 148 of 152)

OFFSITE DOSE CALCULATION MANUAL APPENDIX B The X/Qs and D/Qs are calculated using the computer code XOQDOQ which implements the guidance of Regulatory Guide 1.111.

The constant mean wind dire~tion model, as defined in equation 3 of Regulatory Guide 1.111, is used to calculate X/Q values.

2.032 Inij exp [-h;/2 o- 2zj(x)]

(X!Q )o = ij NxUi L (x )

zj Where:

he= effective release height (m) (All releases from Wolf Creek Generating Station are considered as ground releases therefore he 0) n 1 j = hours of valid d~ta for weather conditions in given direction, windspeed class I~ ~nd atmosbheric stability class j N = total hours of valid data Vi = midpoint of windspeed class (m/s) x = distance downwind (m)

Gzj(X) = vertical plume spread without volumetric correction at distance x and stability class j. See Figure B.1 Lzj(x) = vertical plume spread with*volumetric correction for release within buildings wake cavity, at distance x and stability class j For ground level releases Lzj(X) is the lesser of

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use !Page 157 of i60 ATTACHMENT A (Page 149 of 152)

OFFSITE DOSE CALCULATION MANUAL APPENDIX B *(cont'd.)

Where:

D~ = maximum adjacent building height either up- or down-wind from the release point 2.032 = (2/n)~ divided by width, in radians, of a 22.5 sector (X/Q) 0 = average effluent concentration, X, normalized to source strength, Q, at distance x in sector D For WCGS the above Meteorological Model will simplify to the following equation for X/Q:

2.032 rnij ij NUi xL(x) ij The calculation of the relative disposition per unit area, D/Q, is performed using the deposition rate graphs found in Regulatory Guide 1.111. For a 22.5 sector, since the effluent concentration is assumed uniform across the sector, the relative deposition per unit area is assumed uniform across the sector.

The calculation of D/Q is determined from relative deposition by the following relationship:

LDij (x)*DEPLii (x)

DIQ = .....,iJ~-- - - - - -

(2 Jr /16)x Where:

Dij(x) = Relative deposition rate for windspeed class i and stability class j at downwind distance x (1/m). See Figure B.3 (2n/16)x = length of arc across sector at downwind distance x (m)

D/Q = relative deposition per unit area (m)

DEPLij(X) = Reduction factor due to plume depletion at distance x for windspeed i and stability class j

Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use nage 158 of 160 ATTACHMENT A (Page 150 of 152)

OFFSITE DOSE CALCULATION MANUAL Figure .B.l 1000

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!3-evisi on: 9 AP 07B-003 OFFSITE DOSE CALCULATION. MANUAL Inform ation Use ['age 159 of 160 ATTACHMENT A (Page 151 of 152)

OFFSITE DOSE CALCULATION MANUAL Figure B.2 7

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Revision: 9 AP 07B-003 OFFSITE DOSE CALCULATION MANUAL Information Use rage 160 of 160 ATTACHMENT A (Page 152 of 152)

OFFSITE DOSE CALCULATION MANUAL Figure B.3

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R-6

-END-

Enclosure II to 2018 Annual Radioactive Effluent Release Report - Report 42 Wolf Creek Nuclear Operating Corporation Procedure, AP 078-004, Revision 22, "Offsite Dose _Calculation Manual (Radiological Environmental Monitoring Program)"

\~,: FCREEK

NUCLEAR OPERATING CORPORATION AP 07B-004 OFFSITE DOSE CALCULATION MANUAL (RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM)

Responsible Manager Manager Regulatory Affairs I Revision Number 22 I Use ~-;-te*~~~~- -* !Information I :~:::::::r:::-::::::0::0:::~:te_ ! YNe:- .

I Program Number 07B DC24 02/26/2018

Revision: 22 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 (RADIOLOGICAL ENVIRONMENTAL Information Use MONITORING PROGRAM) bage 1 of 36 TABLE OF CONTENTS SECTION TITLE 1.0 PURPOSE 2 2.0 SCOPE 2

3.0 REFERENCES

AND COMMITMENTS 2 4.0 DEFINITIONS 3 5.0 RESPONSIBILITIES 3 6.0 PROCEDURE 5 7.0 RECORDS 6 8.0 FORMS 6 ATTACHMENT A OFFSITE DOSE CALCULATION MANUAL (REMP) 7 ATTACHMENT B SPECIAL SCOPE QUALITY ASSURANCE FOR THE REMP 34

Revision: 22 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 (RADIOLOGICAL ENVIRONMENTAL Information Use MONITORING PROGRAM) Page 2 of 36 1.0 PURPOSE 1.1 This procedure contains the Offsite Dose Calculation Manual (ODCM) Radiological Environmental Monitoring Program (REMP) requirements.

1.2 This procedure also contains the Special Scope Quality Program for the REMP to assure the quality*of the results of measurements of radioactive materials ~n the environment.

2.0 SCOPE 2.1 Technical Specifications 5.5.1 and 5.6.2 shall be implemented PY this procedure.

2.2 Procedure AP 07B-003, OFFSITE DOSE CALCULATION MANUAL has been split into two procedures. Requirements for the REMP are now contained in this procedure.

2.3 ATTACHMENT B, SPECIAL SCOPE QUALITY ASSURANCE FOR THE REMP, ensures the environmental monitoring requirements of Technical Specification 5.4.1.c are met.

2.4 The requirements of the Special Scope Quality Program do not apply to hardware.

2.5 For NEI '07-07 [Final] Industry Ground Water Protection Initiative - Final Guidance Document "Communication Protocol" for offsite waters, see AI 07B-004, REPORTING REQUIREMENTS OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.

2.6 For NEI 07-07 [Final] Industry Ground Water-Protection Initiative - Final Guidance Document "Communication Protocol" for onsite waters, see AI 07-007, ONSITE GROUNDWATER PROTECTION PROGRAM MONITORING.

2.7 For NEI 07-07 [Final] Industry Ground Water Protection Initiative - Final Guidance Document "Communication Protocol" for leaks/spills, see AP 14B-003, SPILL AND RELEASE REPORTING.

3.0 REFERENCES

AND COMMITMENTS 3.1 References 3 .1.1 AP 07B-003, OFFSITE DOSE CALCULATION MANUAL 3 .1. 2 Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1,.November 1979 3 .1. 3 PIR 19g8-0112, Revising the ODCM with an OTSC 3 .1. 4 Technical Specification 5.5.1 3 .1. 5 Technical Specification 5.6.2

Revision: 22 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 (RADIOLOGICAL ENVIRONMENTAL Information Use MONITORING PROGRAM) Page. 3 of 36 3 .1. 6 Regulatory Guide 4.15 - Quality Assurance for RadiologiGal Monitoring Programs (Normal Operations) - Effluent Streams and the Environment, February 1979 3.1. 7 Technical Specification 5.4.1.c 3 .1. 8 07-00558, NEI. 07-07 [Final] Industry Ground Water Protection Initiative - Final Guidance Document 3 .1. 9 Technical Specification 5.6.3 3 .2 Commitments 3.2.1 None 4.0 DEFINITIONS 4.1 None 5.0 RESPONSIBILITIES 5.1 Manager Regulatory Affairs 5 .1.1 Ensures that a quality program has been developed f6r radiological environmental monitoring.

5 .1. 2 Ensures that the Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program) has been established, implemented and is maintained in accordance with Technical Specification 5.5.1.

5.2 Manager Quality 5.2.1 Ensures that internal and external audits are performed and documented.

5.3. Supervisor Regulatory Support 5.3.1 Implements and maintains the radiological environmental monitoring program.

5.3.2 Ensures procedures are developed and maintained which describe sample collection, sample preparation and sample shipping.

5.3.3 Ensures procedures are developed and maintained which describe equipment maintenance and calibration.

5.3.4 Ensures procedures are developed and maintained which describe data review and reporting requirements.

Revision: 22 OFFSITE DOSE CALCULATION MANUAL AP 07B~004 (RADIOLOGICAL ENVIRONMENTAL Information Use MONITORING PROGRAM) toage 4 of 36 5.3.5 Ensures personnel have received the required training prior to performing REMP-related activities. "

5. 3. 6 Ensures that problems are identified and are properly addressed for resolution in the corrective action program.*

5.4 Environmental Management Personnel 5.4.1 Ensure the REMP is established, implemented, and maintained.

5.4.2 Ensure that Condition Reports are generated for identified problems.

Revision: 22 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 (RADIOLOGICAL ENVIRONMENTAL

tnformation Use MONITORING PROGRAM) Page 5 of 36 6.0 PROCEDURE 6.1 Revisions to This Procedure NOTE To comply with.Technical Specification 5.5.1, revisions to this procedure are not permitted via APF 15C-004-04,. ON THE SPOT CHANGE form (3.1.3).

6 .1.1 Revisions to this procedure are to be submitted through'the Manager Regulatory Affairs via APF 15C-004-01, .DOCUMENT REVISION REQUEST (DRR).

6.1. 2 Changes to ATTACHMENT A shall include:

1. Sufficient information to support the change(s) together with .tpe appropriate analyses or evaluations justifying the change(s) and (3.1.4)

Changes to the REMP will have no impact upon the level of radioactive effluent control nor will impact the accuracy or reliability of effluent dose or setpoint calculations.

2. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or set point calculations. ( 3 .1. 4) 6.1. 3 The changes shall become effective after the approval of the Plant Manager. (3.1.4) 6 .1. 4 IF Figure 5.2 or Figure 5.3 are revised, THEN Emergency Planning should be notified so that the Radiological Emergency Response Plan may be revised accordingly.

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6.2.1 Changes to the ODCM shall be submitted to the NRC in the form of a complete, legible copy of the e.ntire ODCM as a part of or concurrent with the Radioactive Effluent Release Re~ort for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the. page that was .changed, and shall indicate the date (i.e., month and year) the change was implemented. (3.1.4) 6.2.2 The Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted to the NRC prior to May 1. (3.1.9) 7.0 RECORDS 7.1 The following is a lifetime QA Record:

7 .1.1 AP 07B-004, OFFSITE DOSE CALCULATION MANUAL (RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM) 8.0 FORMS 8.1 None

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OFFSITE DOSE CALCULATION MANUAL (REMP)

Wolf Creek Generating Station Offsite Dose Calculation Manual Radiological Environmental-Monitoring Program

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TABLE OF CONTENTS Title

1.0 INTRODUCTION

4 2.0 LIQUID EFFLUENTS (CONTAINED IN AP 07B-003) 3.0 GASEOUS EFFLUENTS (CONTAINED IN AP 07B-003) 4.0 TOTAL DOSE (CONTAINED IN AP 07B-003) 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5.1 Monitoring Program 4 5.2 Land Use Census 5 5.3 Interlaboratory Comparison Program 5 5.4 Reporting Requirements 6 6.0 BASES Sections 2.0 through 4.0 (Contained in AP 07B-003)

Section 5.0 Radiological Environmental Monitoring 24 Program Section 5.1 Monitoring Program 24 Section 5.2 Land Use Census 25 Section 5.3 Interlaboratory Comparison Program 25 7.0 REPORTS 7 .1 Annual Radiological Environmental Operating Report 26 7.2 Radioactive Effluent Release Report (Contained in AP 07B-003)

.APPENDIX A: Dose Conversion Factor Tables (Contained in AP 07B-003)

APPENDIX B: Meteorological Model (Contained in AP 07B-003)

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LIST OF TABLES Table Title 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 7 5-2 SAMPLING LOCATION IDENTIFIERS, DISTANCES (MILES) AND 13 DIRECTIONS 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE 15 ANALYSIS 5..,.4 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN 18 ENVIRONMENTAL SAMPLES LIST OF FIGURES Figure Title Page*

5.1 AIRBORNE PATHWAY SAMPLING LOCATIONS 19 5.2 DIRECT RADIATION PATHWAY SAMPLING LOCATIONS 20 5.3 WATERBORNE PATHWAY SAMPLING LOCATIONS 21 5.4 INGESTION PATHWAY SAMPLING LOCATIONS 22 5.5 DISTANT SAMPLING LOCATIONS 23

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OFFSITE DOSE CALCULATION MANUAL (REMP) 1.0 Introduction This attachment contains the ODCM for the Radiological Environmental Monitoring Program which was previously contained in AP 07B-003.

This program is provided to monitor the radiation and radionuclides in the environs of the plant. The program provides (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. This program conforms to the guidance of Appendix I to 10 CFR Part 50 and includes the following:

1. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment.

2. A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and the modifications to the monitoring program are made if required by the results of this census, and

.3. Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

This attachment also provides a description of the information that should be included in the Annual Radiological Envi.ronmental Operating Report.

2.0 Liquid Effluents (Contained in AP 07B-003) 3.0 Gaseous Effluents (Contained in AP 07B-003) 4.0 Total Dose (Contained in AP 07B-003) 5.0 Radiological Environmental Monitoring Program This section describes the Radiological Environmental Monitoring Program for Wolf Creek Generating Station.

5.1 Monitoring Program Table 5-1 provides a schedule which describes the pathways, specific locations, sample collection frequencies, and analyses to be performed to implement the Radiological Environmental Monitoring Program.

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Figures 5.1 through 5.5 contain maps depicting sampling locations in relation to the WCGS site. Table 5-2 lists distances and directions to these locations from the WCGS site.

Table 5-3 lists required detection capabilities for the analyses performed.

5.2 Land Use Census A Land Use Census shall be conducted annually during the growing season to identify the hearest ( 1) milk animal, (2) residence,

and (3) garden of greater than 500 square feet producing broadleaf* vegetation in each of the 16 meteorological section~

within five miles of the WCGS site. (Broadleaf vegetation sampling of available vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.

Specifications for broadleaf vegetation sampling in Table 5-1 shall be followed, including analysis of control samples.)

Methods shall be used in conducting the census that provide the best results, such as door-to-door surveys, telephone surv~ys, mailed surveys, drive-by surveys, consulting the U.S.D.A. office in Burlington, consulting with Coffey County Emergency Management, inspection of aerial photographs of the area, or reviewing leasing records for area farms and residences.

If a location(s) is identified which 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, and the cooperator agrees, the new location(s) shall be added to the Radiological Environmental Monitoring Program. The indicator sampling location(s) having the lowest calculated dose or dose commitment may then be deleted from the monitoring program.

The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report described in Section 7.1.

5.3 Interlaboratory Comparison Program The analysis laboratory contracted to analyze samples from the Radiological Environmental Monitoring Program participates in a Laboratory Intercomparison Program.

A summary of intercomparison results shall be included in the Annual Radiological Environmental Operating Report described in Section 7.1.

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OFFSITE DOSE CALCULATION MANUAL (REMP) 5.4 Reporting Requirements 5.4.1 Annual Radiological Environmental Operating Report To meet the requirements of Wolf Creek Technical Specification 5.6.2, the Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted to the NRC before May 1 of each year.

The content of this report is described in Section 7.1.

5.4.2 Special Reports A special report shall be prepared and submitted to the NRC within 30 days if levels of radioactivity as a result of plant effluents detected in an environmental medium at a specified location exceed the reporting levels of Table 5-4 when averaged over any calendar quarter. The special report shall identify the cause(s) for exceeding the limit(s) and define the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a member of the publi'c is less. than the calendar year limits of Wolf Creek Technical Specification 5.5~4. When one or more of the radionuclides in Table 5-4 is detected in the sampling medium, this report shall be submitted if:

Concentration (1) + Concentration (2) +.~~1.0 Reporting Level (1) Reporting Level (2)

When radionuclides other than those in Table 5-4 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a member of the public from all radionuclides is equal to or greater than the calendar year limits of Technical Specification 5.5.4. (*The methodology and parameters us~d to estimate the potential annual dose to a member of the public shall be indicated in this report.)

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TABLE 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Number of Samples and Sample Collection Type and Frequency Pathway/ Sample Locations (1) Frequency / of Analysis Sample Type

1. AIRBORNE FIGURES 5.1 & 5.5 Radioiodine arid Samples from six locations Continuous sampler Analyze radioiodine Particulates

operation with canister weekly for sample collection I-131 weekly, or mo.re frequently if required, by dust loading Samples from locations Analyze particulate near the site boundary in filter weekly for three sectors ~aving the gross beta activity highest calculated annual (2); perform average D/Q and one quarterly garruna supplemental location isotopic analy~is (Locations 2, 18, 37, or (3) composite (by 49 on Figure 5.1); location).

Sample from the vicinity of a corrununity having the highest calculated annual average D/Q (Location 32 on Figure 5.1, New Strawn);

Sample from a control location .9.5 to 18.5 miles distant i~ a low ranked D/Q sector (Location 53 on Figure 5. 5). (11)

2. DIRECT FIGURES 5.2 AND 5.5 RADIATION (4) 39 routine monitoring Quarterly Garruna dose stations with two or more quarterly dosimeters measuring dose continuously, placed as follows:

An inner ring of stations, one in each meteorological sector 0-3 mile range from the site (Locations 1, 7, 9, 11-13, 18, 26, 27, 29, 3 0, 3 7, 3 8, 4 6, & 4 9 on Figure*, 5. 2) .

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Information Use MONITORING PROGRAM) Page 14 of 36 ATTACHMENT A (Page 8 of 27)

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TABLE.5-1 (Co~tinued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway/ Number of Samples and Sample Collection Type and Frequency Sample Type Sample Locations (1) Frequency of Analysis DIRECT RADIATION An outer ring of (4) (CONTINUED)* stations, one in each meteorological sector in the 3 to 5 mile range from the site (Locations 4, 5, 15-17, 19, 22-25, 32, 34-36, 50 & 51 on Figure 5.2). Four sectors [A, B, G & J]

contain an additional station (Locations 2, 8, 14 & 20)

The balance of the stations to be placed in special interest areas such as population centers (Locations 23, 32

& 52), nearby residences (many loc_ations are near a residence), schools (Locations 23 & 52),

Wilson Cadman Wildlife Education Area (44), CCL Public Fishing Area (46) and in two areqs to serve as control stations 10-20 miles distant from the site (Locations 39 and 53 on Figure 5. 5) ( 11)

3. WATERBORNE FIGURE 5.3 Surface One sample upstream (5) Monthly grab sample Monthly gamma (Location JRR on Figure isotopic analysis 5.3) and one sample down- (3) and composite stream (Location SP on for tritium Figure 5.3) analysis quarterly.

Ground Samples from one or two Quarterly grab Quarterly gamma sources only if likely to sample isotopic analysis be affected (3) and tritium analysis.

Indicator samples at locations hydrologically down-gradient of the site (Locations C-10, C-49, F-l, G-2, J-1. and J-2 on Figure 5.3); control

-sample at a location hydrologically upgradient of the site (Location B-12 on Figure 5. 3) ( 6)

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TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway/ Number of Samples and Sample Collection Type and Frequency Sample Type Sample Locations (1) Frequency of Analysis 3 . WATERBORNE Sample of municipal water Monthly composite Monthly gamma (CONT.) supply at an indicator (7) isotopic analysis Drinking* location downstream of (3) and gross beta the Neosho River-Wolf analysis of Creek confluence composite sample.

(Location IO-DW on Figure Quarterly tritium 5.5); control sample from analysis of location upstream of* the composites (8).

Neosho River-Wolf Creek confiuence (Location BW-15 on Figure 5.3)

Shoreline Sediment One sample from the Semiannually Semiannual gamma vicinity of Coffey County isotopic analysis Lake discharge cove (3)

(Location DC 9n Figure

5. 3) ; control s*ample from John Redmond Reservoir (Location JRR on Figure

5. 3).

4. INGESTION FIGURES 5.4 AND 5.5 Milk Samples from milking Semimonthly April Gamma isotopic animals at three to November; analysis (3) and indicator locations monthly December- I-131 analysis of within 5 miles of the March (9) each sample.

site having the highest dose potential (cur~ently there are no locations producing milk for human consumption within 5 miles of the site); one sample from a control location greater than 10 miles from the site if indicator locations are

' sampled. (11)

Fish Indicator samples of 1 to Semiannually Gamma is_otopic 3 recreationally analysis (3) on important species from edible portions Coffey County Lake (Figure 5.4); control samples of similar species from John Redmond Reservoir Spillway (indicated on Figure

5. 4).

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TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway/ Number of Samples and Sample Collection Type and Frequency Sample Type Sample Locations (1) Frequency of Analysis

4. INGESTION Samples of available Monthly when Gamma isotopic (CONT.) broadleaf.vegetation from available (9) analysis (3) on Food Products two indicator locations edible portions.

(using the criteria from the "Land Use Census" section) with* highest calculated annual average D/Q (Locations A-3 and Q-6 and alternate Locations B-1, H-2, N-1 and R-2 on Figure 5.4); sample of similar broadleaf vegetation from a control location 9.5 to 18.5 miles distant in a low

ranked D/Q sector (Location D-2 on Figure

5. 5). (11)

Food Products Sample of crops irrigated At time of harvest Gamma isotopic with water from the (10) analysis (3) on Neosho River downstream edible portions of the Neosho River-Wolf Creek confluence (locations will vary from year to year, e.g.,

Location NR-Dl & NR-D2 on Figure 5. 5).

J

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TABLE 5-1 (Continued)

TABLE NOTATIONS (1) 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. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All.deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report described in Section 7.1.

It is*recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the* most desired location or time. In these instances, suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made.

(2) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more, preferably after 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , after sampling to allow for Rn-220 and Rn-222 daughter decay. If gross beta activity in air particulate samples is greater than 10 times the. yearly mean of control samples, gamma isotopic analysis shall be performed on t~e individual samples.

(3) .Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

( 4) 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.

Film badges shall not be used as dosimeters for measuring direct radiation. The 40 stationi are not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations, e.g.,

some sectors are over water so that the number of dosimeters may be reduced accordingly. Sector J is an example. The frequency or analysis or readout ~or the dosimeter system depends upon the characteristics of the specific system used and is selected to obtain optimum dose information with minimal fading.

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TABLE 5-1 (Continued)

TABLE NOTATIONS

( 5) The "upstream" sample is taken at a distance beyond significant influence of the discharge.

(6) Ground water samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(7) A composite sample is one in which the quantity (aliquot) of liquid sampled is consistent over the sampling period and in which the method of sampling employed results in a specimen that is representative of the liquid concentrate. In this program, composite sample aliquots shall be collected at time intervals that are very short (e.g., every two hours) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative'sample.

(8) If the dose calculated for consumption of water (using ODCM methodology and parameters) exceeds one millirem per year, composite sampling at the indicator location shall be performed every two weeks and I-131 anilysis shall be performed on the composite samples.

(9) Milk and broadleaf vegetation samples are often temporarily, but not permanently, unavailable at the scheduled sample collection times. Alternate sampling locations may therefore be listed in the Table and used at these times to provide continued monitoring of these pathways. If samples are considered permanently unavailable at a location, another location will be selected (if available) as described in Note (1).

(10) If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs

continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products.

(11) The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites'that provide valid background data may be substituted.

J

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TABLE 5-2 SAMPLING LOCATION IDENTIFIERS, DISTANCES (miles) AND DIRECTIONS Sample Type Location Distance Direction Sector Identifier from Reactor Air 2 2.7 N A Paiticula tes and Radioiodine 18 3.0 SSE H 32 3.1 WNW p 37 2.0 NNW R 49 0. 8 NNE B 53 10.8 ENE. D Dosimeters 1 1. 4 N A 2 2.7 N A 4 4.0 NNE B 5 4.1 NE C 7 2.1 NE C 8 1. 7 NNE B 9 2.0 ENE D 11 1. 7 E E 12 1. 9 ESE F 13 1. 6 SE G 14 2.5 SE G 15 4.6 ESE F 16 4.3 E E 17 3.7 SE G 18 3.0 SSE H 19 3.9 SSE H 20 3.3 s J 22 3.9 SSW K 23 4.3 SW L 24 4 .1 WSW M 25 3.4 w N 26 2.4 WSW M 27 2.2 SW L 29 2.7 SSW K 30 2.5 w N 32 3.1 WNW p 34 4.4 NW Q 35 4.6 NNW R 36 4.2 N A 37 2.0 NNW R 38 1.2 NW Q 39 13.1 N A 44 3.0 NNW R 46 1. 6 WNW p

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TABLE 5-2 (Cont.)

SAMPLING LOCATION IDENTIFIERS, DISTANCES (miles) AND DIRECTIONS Sample Type Location Distance Direction Sector Identifier from Reactor Dosimeters 49 0.8 NNE B 50 3.6 ENE D 51 4.3 s J 52 3.6 SW L 53 10.8 ENE D Surface Water JRR 3.7 w N SP 3.2 SSE H Ground Water - B-12 1. 9 NNE B C-10 2.7 w N C-49 2.8 SW L F-1 2.5 ESE F G-2 3.6 SE G J-1 3.8 s J J-2 4.3 s J Drinking Water BW-15 3.9 SW L IO-OW 26 .1 SSE H Shoreline DC 0.8 WNW p Sediment JRR 3.6 w N Fish CCL 0.6 E to NNW E to R JRR 3.7 w N Food/Garden A--3 2.6 N A B-1 0. 8 NNE B D-2 14.8 ENE D H-2 3.0 SSE H N-1 2.4 w N Q-6 2.4 NW Q R-2 2.0 NNW R Crops NR-01 8.9 s J NR-D2 11. 5 s J

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TABLE 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (l)

Lower Limit of Detection (LLD) (Z)

AIRBORNE FOOD PARTICULATE FISH PRODUCTS SEDIMENT ANALYSIS WATER OR GASES (pCi/kg, MILK (pCi/kg, (pCi/kg, (pCi/1) (pCi/m 3 ) wet) (pCi/1) wet) dry)

Gross 4* 0.01 Beta H-3 2,000**

Mn-54 15 130 Co-58 15 130 Fe-59 30 260 Co-60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-131 1*** 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15

LLD for drinking water samples.

- LLD for drinking water and ground water samples. For surface water samples, a value of 3,000 pCi/1 may be used.

- - LLD for drinking water and ground water samples. For surface water samples, a value of 15 pCi/1 may be used.

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TABLE 5-3 (Continued)

TABLE NOTATIONS (1) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report described in Section 7.1.

(2) The LLD is defined, 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 s~paration:

4.66 Sb LLD E

V

2.22

Y

exp (-,1, ~t)

Where:

LLD the "a priori" lower limit of detection (picoCuries per unit mass or volume),

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

E the counting efficiency (counts per disintegration),

V the sample size (units of mass or volume),

2.22 the number of disintegrations per minute per picoCurie, y the fractional radiochemical yield, when applicable, the radioactive decay constant for the particular radionuclide (sec-1), and Lit the elapsed time between sample collection, or end of the sample collection period, and time of counting (sec).

Typical values of E, V, Y, and Lit should be used in the calculation.

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TABLE 5-3 (Continued)

TABLE NOTATIONS 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~ 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 sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachieiable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report described in Section 7.1.

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TABLE 5-4 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AIRBORNE WATER PARTICULATE OR FISH MILK FOOD PRODUCTS ANALYSIS (pCi/1) GASES (pCi/m 3 ) (pCi/kg, wet) (pCi/1) (pCi/kg, wet)

H-3. 20,000*

Mn-54 1,000 30,000 Co-58 1,000 30,000 Fe-59 400 10,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 2** 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300

For drinking water and ground water samples. This is 40 CFR Part 141 value. For surface water samples, a value of 30,000 pCi/1 may be used.

- For drinking water and ground water samples. For surface water samples, a value of 20 pCi/1 may be used.

IF ground water or surface water results exceed the Reporting Levels, THEN proceed to AI 07B-004, REPORTING REQUIREMENTS OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM for specific details regarding NEI 07-07 [Final] Industry Ground Water Protection Initiative - Final Guidance Document "Communication Protocol" requirements.

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FIGURE 5.1 Q C D

N E AIRBORNE PATHWAY SAMPLING LOCATIONS

= AIRBORNE PARTICULATE AND RADIOIODINE .

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FIGURE 5.2

,1

\

C D

r N E DIRECT RADIATION PATHWAY SAMPLING LOCATIONS e = DOSIMETER LOCATIONS

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FIGURE 5.3 I

C D

WATERBORNE PATHWAY SAMPLING LOCATIONS e =.DRINKING WATER A = SURFACE WATER

= GROUND WATER e = SHORELINE SED1MENT

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OFFSITE DOSE CALCULATION MANUAL (REMP)

FIGURE 5.4 Q C D

N E INGESTION PATHWAY SAMPLING LOCATIONS

.A. = ASH (JRR) * = BROADLEAF VEGETATION

@ = ASH (CCL)

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OFFSITE DOSE CALCULATION MANUAL (REMP)

FIGURE 5.5 A

~~~~~=..---J1---~X----+-----'-,---,.c E

= Dosimeter

== AIRBORNE PARTIUIIATE & RADIOIODINE

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OFFSITE DOSE CALCULATION MANUAL (REMP) 6.0 Bases The bases contained on the succeeding pages summarize the general requirements of Section 5.0 of the ODCM (REMP).

Section 2.0 Liquid Effluents (Contained in AP 07B-003)

Section 3.0 Gaseous Effluents (Contained in AP 07B-003)

Section 4.0 Total Dose (Contained in AP 07B-003)

Section 5.0 Radiological Environmental Monitoring Program Section 5.1 Monitoring Program The Radiological Environmental Monitoring Program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for thos~ radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 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 the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Posit.ion on Environmental Mani taring, Revision 1, November 197 9.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an~ 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.

Detailed discussion of the LLD,,and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually),

Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination-Applic ation to Radiochemistry," Anal. Chern. 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975) ..

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OFFSITE DOSE CALCULATION MANUAL (REMP)

Section 5.2 Land Use Census This section is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. Information that will provide the best results, such as door-to-door survey, aerial survey, 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 Part 50.

Restricting the census to gardens of greater than 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/year) of leafy vegetables assume in Regulatory Guide 1.109 for consumption by a child.

To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broadleaf vegetation (i.e., similar to lettuce and cabbage)r and (2) a*

vegetation yield of 2 kg/m2.

Section 5.3 Interlaboratory Comparison Program The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part 0£ the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

Revision: 22 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 (RADIOLOGICAL ENVIRONMENTAL Information Use MONITORING PROGRAM) Page 32 of 36 ATTACHMENT A (Page 26 of 27)

OFFSITE DOSE CALCULATION MANUAL (REMP) 7.0 Reports 7.1 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and analysis of trends of the results.of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3 and IV.C of Appendix I to 10 CFR Part 50 (3.1.5), including a comparis~n with preoperational studies, with operational controls and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The report shall also include the results of the Land Use Census described in Section 5.2.

The Annual Radiological Environmental Operating Report shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in Table 5-1 as well as summarized and tabulated results of these analyses and measurements in the format of 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 noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The report shall. also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by Section 5.3; reasons for not conducting the Radiological Environmental Program as required by Section 5.1 with plans for preventing a recurrence and discussion of all deviations from the sampling schedule of Table 5-1; discussion of environmental sample measurements that exceed the reporting levels of Table 5-4 but are not the result of plant effluents, and discussions of all analyses in which the LLD required by Table 5-3 was not achieved.

7.2 Radioactive Effluent Release Report (Contained in AP 07B-003)

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OFFSITE DOSE CALCULATION MANUAL (REMP)

APPENDIX A Dose Conversion*Factor Tables (Contained in AP 07B-003)

APPENDIX B Meteorological Model (Contained in AP 07B-003)

.,-END-

Revision: 22 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 (RADIOLOGICAL ENVIRONMENTAL Information Use MONITORING PROGRAM) . [Page 34 of 36 ATTACHMENT B (Page 1 of 3)

SPECIAL SCOPE QUALITY ASSURANCE FOR THE REMP B.1 QUALITY REQUIREMENTS B.1.1 Review and Reporting of Data

1. Data from sample analysis are reviewed in accordance with approved procedures.

B.1. 2 Organization

1. Section 5 of this procedure identifies the organizational structure, management posit{ons and responsibilities.

B.1. 3 Personnel Qualifications

1. Personnel responsible for collection and preparation of radiological environmental monitoring samples shall be qualified in accordance with approved procedures.

2. Personnel responsible for digital flow meter calibration verifications shall be qualified in accordance with approved procedures.

B.1. 4 Procurement Document Control

1. Purchase orders for contracted radiological analysis services, contracted calibrator calibration services, or contracted dosimeter services shall:

a. Include quality requirements

b. Specify technical requirements

c. Identify documentation requirements

d. Detail records requirements

e. Extend applicable procurement document requirements to lower tier suppliers; and

f. Specifying special requirements such as reporting program deficiencies, documentation requirements and applicable acceptance criteria.

2. Purchase orders for contracted radiological analysis services shall require participation in an interlaboratory comparison program.

Revision: 22

OFFSITE DOSE CALCULATION MANUAL AP 07B-004 (RADIOLOGICAL ENVIRONMENTAL Information Use MONITORING PROGRAM) IPage 35 of 36 ATTACHMENT B (Page 2 of 3)

SPECIAL SCOPE QUALITY ASSURANCE FOR THE REMP B.1. 5 Instructions, Procedures and Drawings

1. This criterion applies to:

a. Surveillances, test and calibrations,

b. Environmental sampling, and

c. Data processing and evaluation

2. Activities shall be accomplished using procedures, instructions and drawings approved prior to use.

3. Instructions, procedures or drawings shall include appro~riate quantitative or qualitative.

acceptance criteria for determining that important activities have been satisfactorily accomplished.

. B.1. 6 Control of Purchased Radiological Analysis services, Calibrator Calibration services, or Dosimeter services

1. Controls shall*be established to ensure that purchased services conform to procurement document requirements.

2. Controls shall include evaluation and selection of su~pliers*and surveillance or audit of supplied services.

.B.1. 7 Control of Measuring and Test Equipment

1. Measures shall be established to assure that tools, gages, instruments, and other measuring and testing devices used in activities affecting quality are properly controlled, calibrated and adjusted at s~ecified periods to maintain accuracy within necessary limits.

B.1. 8 Ins~ection, Test and Operating Status for Purchased Calibrator Calibration Services

1. These inspections and tests shall be completed in accordance with approved procedures.

B.1. 9 Quality Assurance Records

1. All documentation shall be legible, reproducible and or microfilmable quality.

2. Documented records shall be maintained to show objective evidence of quality.

3~ Quality records shall not be destroyed or disposed of without written authorization.

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SPECIAL SCOPE QUALITY ASSURANCE FOR THE REMP

4. Eor the vendor laboratory that performs Radiological Analysis for the REMP, data sheets and finished records shall be ret~ined by the contactor for a period of five years.

B. 1. 10 Audits

1. Audits shall be performed in accordance with AP 20A-003, QA AUDIT REQUIREMENTS, FREQUENCIES, AND SCHEDULING, to verify compliance to requirements and to verify the effectiveness of th~ implemented activities affecting quality.

2. Triennial audits in accordance with AP 24C-008, SUPPLIER AUDITS AND COMMERCIAL GRADE SURVEYS, shall be performed.

-END-

Enclosure Ill to 2018 Annual Radioactive Effluent Release Report - Report 42 Wolf Creek Nuclear Operating Corporation Procedure, AP 31A-100, Revisions 8 and 9, "Solid Radwaste Process Control Program"

AP 31A-100 SOLID RADWASTE PROCESS CONTROL PROGRAM Responsible Manager Manager. Radi~tion Protection Revision Number 8 Use Category Information Administrativ e Controls Procedure Yes Management Oversight Evolution No Program Number 25A DC38 8/30/2011

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Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 1 of 34 TABLE OF.CONTENTS SECTION TITLE PAGE 1.0 PURPOSE 2 2.0 SCOPE 2

3.0 REFERENCES

AND COMMITMENTS 6 4.0 DEFINITIONS 8

5. 0. RESPONSIBILITIES 13 6.0 PROCEDURE 14 7.o* RECORDS 33 8.0 FORMS 33 ATTACHMENT A TECHNICAL REQUIREMENTS (SECTION 5.5.4) 34

('

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 2 of 34 1.0 PURPOSE 1.1 This procedure provides instructional guidance and a description of the solid waste Process Control Program (PCP). The PCP describes the methods, used for processing wet low-level radioactive waste into a waste form acceptable for disposal, in accordance with 10 CFR 61 requirements, at a licensed land disposal, facility.

2.0 SCOPE 2.1 This procedure describes current and planned practice for sampling, sample evaluation, classification, processing and packaging of radioactive material. This procedure does not address irradiated hardware which will be managed on a case-by-case basis under the direction of the Manager ~adiation Protection. System descriptions and operating practices are described in the following steps.

2.2 Waste Steam Identification - The station had initially identified eight different waste streams and treats each separately for classification purposes. The identification listing may be consolidated, expanded and streams deleted at the discretion of radwaste management without revising the PCP.

EXAMPLES For Information Only o Dry Active Waste (DAW) o Tubular Ultra Filtration/Reverse Osmosis Process Waste o Steam Generator Blowdown Bead Resin o Chemical and Volume Control System Bead Resin (1) (CVCS) o Reactor Coolant System Filters o Ultra Filtration Skid Waste o Spent Fuel Pool Filters o Radwaste Resins o Steam Generator Blowdown Filters (2)

(1) May contain combination of eves, Diversified, and Spent Fuel Pool Resins (2) May be disassembled and components handled as DAW

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 3 of 34 2.3 Non-Waste Stream Identification - The station has identified two different sources and treats each separately for classification purposes.

0 Non-irradiated material removed from the Spent Fuel Pool.

0 Any other radioactive material gen~rated by the station.

2.4 D~sposition of Radioactive Material Sent to -a Vendor for

.Intermediate Processing - Practices include sending radioactive material packages generated by the station to Energy Solutions, Studsvik or other vendors for volume reduction (VR)/processing instead 0£ directly to a burial site.

2.4.1 This procedure addresses the requirements for 10 CFR 61.55 (Waste Classification) for radioactive material sent to vendor facilities.

2.4.2 This procedure does NOT address the requirements for 10 CFR 61.56 (Waste Characteristics), since the final processing and packaging are performed at the vendor facilities.

2.4.3 Possible types of radioactive material include, but are NOT limited to the following:

0 DAW 0 Surface Contamiriated Objects 0 Bead Resins and Charcoal 0 Cartridge Filters 0 Contaminated Oil 0 Contaminated Soil 2.5 Disposition of Waste Sent Directly to a Burial Site - This procedure addresses both the 10 CFR 61.55 and 61.56 requirements for the waste streams listed in Step 2.2.

2.6 Waste Management Practices 2.6.1 DAW o This waste stream consists of plastic, wood, paper, metal, cloth, etc. generated at various locations within the station.

o The material may be sent to intermediate processors or directly to a burial site.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 4 of 34 o The station may preprocess DAW by compacting.

o Practices include shipping DAW classified as either SCO or LSA in numerous possible containers, such as:

30 to 85 gallon drums B-25 type boxes SeaLand containers Large liners o Prepacking inspection criteria includes the removal of liquid, protective clothing and equipment, paints, solvents, lead, instruments, gages and other valuable plant equipment.

2. 6. 2 Steam Generator Blowdown Bead Resin (S/G BD) o This waste stream consists of only S/G blowdown resin. The depleted resins are sluiced from the indi~idual processing vessels to the S/G Blowdown Resin Storage Tank and then to a CNSI 6-80 or 8-120 High Integrity Container (HIC), OR any other container approved by the Health Physic~ Radwaste Shipper (HPRS).

o Once a container is full or the transfer hai been terminated, the filter media (charcoal) and resins are then dewatered per RPP 07-131, BEAD RESIN/ACTIVATED CARBON DEWATERING PROCEDURW FOE CNSI 14-215 OR SMALLER LINERS. Compliance with freestanding water criteria is in accordance with the vendor waste acceptance criteria and/or 10CFR61.

o Practice may include shipping resins directly to a burial site or to a volume reduction processor for incineration or ~elease.

2. 6. 3 Chemical and Volume Control System Bead Resin (CVCS) o This waste stream consists of eves, various .

Diversified Technologies media and Spent Fuel Pool resins. The depleted charcoal filter media and resins are sluiced from -the individual processing vessels to a common Spent Resin Storage Tank. The media is then transferred in a batch mode to a CNSI 6-80 or 8-120 HIC, OR any other container approved by Health Physics Radwaste Shipper.

Revision: 8 'SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 5 of 34 o Once a container is full or the transfer has been termihated, th~ filter media (charcoal) and resins are then dewatered per RPP 07-131, BEAD RESIN/ACTIVATED CARBON DEWATERING PROCEDURE FOR CNSI 14-215 OR SMALLER LINERS. Compliance with freestanding water criteria is in accordance with the vendor waste acceptance criteria and/or 10CFR61.

o Practice may include shipping resins directly to a burial site or to a volume reduction processor.

2.6.4 Cartridge Filters o This category includes several waste streams which were defined in Step 2.2 and includes all filters generated by the station.

o Filters are removed from service based on operating parameters determined by the Operations Department.

o The filter housings are drained prior to filter removal. The filters.are then gravity drained prior to being placed into a-n intermediate storage container OR the final disposal container.

o With containers equipped with a dewatering internal, a final dewatering verification is performed on the disposal container after it has been loaded with filters. Compliance with freestanding water criteria is in accordance with the vendor waste acceptance criteria and/or 10CFR61.

o Absorbent material may be added to the disposal liner after final dewatering verification at the discretion of the HPSR.

o Practice may include shipping filters *to a volume reduction processor.

(

2. 6. 5 Tubulai Ultra Filtration/Reverse Osmosis Waste o This waste stream may consist of either dried solids in a standard 55-gallon drum or Drum Dryer Hold-Up Tank liquid waste.

o The material may be sent to intermediate processors or directly to a burial site. In the case of the liquid waste, additional processing is required.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 6 of 34

2. 6. 6 Solidification/Encapsulation Methods o Present and planned practice is NOT to solidify or encapsulate any waste streams.

o Wet wastes (filters and resips) are dewatered to less than O. 5 p*ercent or 1 perce'nt by volume depending on the container type. Wet waste sent to a vendor for additional processing will be dewatered in accordance with the vendor waste acceptance criteria

2. 6. 7 Operation and Maintenance of dewatering Systems and Equipment o Present and planned practice is to utilize station personnel to operate and maintain dewatering systems and equipment using station procedures.

o All disposal liners are manufactured by and purchased from QA approved vendors.

2. 6. 8 High Integrity Container Usage o High Integrity Containers (fabricated from high density cross-linked polyethylene) may be used* as the disposal package for any waste.

3.0 REFERENCES

AND COMMITMENTS 3.1 References 3 .1.1 WCGS Technical Requirements (TR 5.5.4) 3 .1. 2 RPP 07-101, CONTROL OF RADIOACTIVE MATERIAL MANAGEMENT SOFTWARE AND DATA BASES 3 .1. 3 RPP 07-123, PREPARATION AND SHIPMENT OF RADIOACTIVE WASTE AND MATERIAL 3.1.4 RPP 07-131, BEAD RESIN/ACTIVATED CARBON DEWATERING PROCEDURE FOR CNSI 14-215 OR SMALLER LINERS 3 .1. 5 10 CFR 20, "Standard For Protection Against Radiation" 3 .1. 6 10 CFR 61, "Licensing Requirements for Land Disposal of Radioactive Waste" 3 .1. 7 JO CFR 71, "Packaging and Transportation of Radioactive Materials" 3 .1. 8 40 CFR 302, "Reportable Quantity Adjustment -

Radionuclides"

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 7 of 34 3 .1. 9 49 CFR 171, "General Information, Regulations, and Definitions" 3 .1.10 49 CFR 172, "Shippers' General Requirements for Shipments and Packaging" 3 .1.11 49 CFR 177, "Carriage by Public Highway" 3 .1. 12 USNRC Branch Technical Position on Radioactive Waste Classification, May 1983

3. i. 13 USNRC Branch Technical Position on Waste Form, January 1991 3 .1.14 USNRC Branch Technical Position on Concentration Averaging and Encapsulation,* Revision in Part To Waste Classification Technical Position, January 1995 3 .1.15 NRC Bulletin No. 79-19, "Packaging of Low Level Radioactive Waste for Transport and Burial" 3.1.16 NRC Information Notice No. 80-24, "Low*Level Radioactive Waste Burial Criteria" 3.1.17 NRC Information Notice No. 83-33, "Non-Representative Sampling of Contaminated Oil"

3. 1. 18 NRC Information Notice No. 85-92, "Surveys of Wastes Before Disposal from Nuclear Reactor Facilities" 3 .1.19 NRC Information Notice No. 86-20, "Low Level

.Radioactive Waste Scaling Factors, .10 CFR 61" 3.1.20 NRC Information Notice No.88-101, "Shipment of Contaminated Equipment Between Nuclear Power Stations" 3.1.21 WMG-SW-006, *"computer Software Quality Assurance Program"

3. 1. 22 WMG-QA-001, "Quality Assurance Program" 3.1.23 WMG-P-065 "RADMAN Operating Manual" 3.1.24 RADMAN Computer Code, Main Topical Report to the USNRC 3.1.25 WMG-P-069, "FILTRK Operating Procedure" 3.1.26 WMG-P-070, "RAMSHP Operating Procedure"

3. 1. 27 WMG-P-075, "OSM Operating Procedure" 3.1.28 WMG Report #9006, "Computer Program Dose to Curie Methodology Verification and Validation"

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 8 of 34 3.1.29 U.S. Nuclear Regulatory Commission, "Radiological Effluent Technical Specifications for PWRs," NUREG-0472 3 .1. 30 NRC Guidelines for Preparation and Implementation of*

Solid Waste Process Control Program "DRAFT," Revision 4, October 1986

3. 1. 31 FO-AD-002, "Operating Guidelines for Use of Polyethylene High Integrity Containers" 3 .1. 32 FO-AD-023, "Bead Resin/Activated Carbon Dewatering Procedure for CNSI 14-215 or Smaller Liners" 3 .1. 33 NRC Generic Letter No. 91-02, "Reporting Mishaps Involving LLW Forms PTepared For Disposal" 3 .1. 34 WMG-9217, "10 CFR 61 Practice Assessment at Wolf Creek Generating Station, 1992" 3 .1. 35 AP 25-001, RADIATION PROTECTION QUALITY PROGRAM REQU+REMENTS 3.1.36 Letter from Rodney Wingard to Jimmy Still concerning the disposal of dried solids (HP 01-00601) 3.2 Commitments 3.2.1 None 4.0 DEFINITIONS 4.1 Abbreviations 4 .1.1 Activity/A2 /g - Package activity divided by (A 2 ) divided by gram 4 .1. 2 BTP - Branch Technical Position 4 .1. 3 CNSI - Chem Nuclear System, Inc.

4 .1. 4 HPRS - Health Physics Radwaste Shipper 4 .1. 5 LLD - Lower Limit of Detection 4 .1. 6 MCA - Multi-Channel Analyzer

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 9 of 34 4.2 Activity Correction Factor 4.2.1 The µCi/cc or µCi/g values may have to be corrected (plus or minus) if the waste stream specific 10 CFR 61 sample results (independent laboratory) and the replicate in-house specific activity values differ by more than 20 percent, and the differences cannot be resolved to the satisfaction of the HPSR.

Alternatively, the dose-to-curie characterization methodology can be used without applying correction factors.

4.3 As Generated Waste 4.3.1 Radioactive waste generated at a frequency contrary to the sampling requirements of waste classes A, B or C.

4'. 4 Batch 4.4.1 An isolated quantity of feed waste to be processed having essentially constant physical and chemical characteristics. (The addition or removal of water will not be considered to create a new batch).

4.5 Chelating Agents 4.5.1 EDTA, DTPA, hydroxyl-carboxylic acids, citric acid, carbolic acid and glucinic acid.

4.6 Confirmatory Analysis

4. 6 .1 - Verification of Gross radioactivity measurements using MCA and independent laboratory sample data.

4. 7 Density Correction

4. 7. 1 Density corrections may be required to convert sample data reported in µCi/g to µCi/cc or vice versa when comparing sample data with unlike units.

4.8 Dewatered Waste

4. 8 .1 Dewatered Waste refers to wet waste that has been processed by means other than solidification, encapsulation, or absorption to meet the free standing liquid requirements of 10 CFR 61.56 (a) (3) and (b) (2).

4.9 Encapsulation

4. 9 .1 Encapsulation is a means of providing stability for certain types of waste by surrounding the waste by an appropriate encapsulation media. -

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 10 of 34 4.10 Gamma-Spectral Analysis 4.10.1 Also known as IG, MCA, GE/Li and gamma spectroscopy.

4.11 Gross Radioactivity Measurements 4 .11. 1 More commonly known as Dose to Curies conversion for packaged waste characterization and classification.

4.12 Health Physics Radwaste Shipper or HPRS 4.12.1 The person designated to sign the shipment manifest and has been trained in the DOT and NRC regulatory requirements within the last three years.

4.13 Homogeneous 4 .13 .1 Of the same kind or nature; essentially alike. Most waste streams are considered to have the radioactivity distributed throughout for purposes of waste

classification.

4.14 Legacy Waste 4.14.1 Radioactive wast~ generated from past Plant processes.

4~15 Low-Level Radioactive Waste (LLW) 4.15.1 Those low-level radioactive wastes containing source, special nuclear, or by-product material that are acceptable for disposal in a land disposal facility.

For the purposes of this definition, low-level radioactive waste has the same meaning as in the Low-Level Waste Policy Act, that is, radioactive waste not classified as high-level radioactive waste, transuranic waste, spent nuclear fuel, or by-product material as defined in Section 113. (2) of the Atomic Energy Act (uranium or thorium tailings and waste).

4.16 Measurement of Specific Radionuclides 4.16.1 More commonly known as core sample or package sample using MCA data for packages waste characterization and classification.

J

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 11 of 34 4.17 Operable 4.17.1 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its 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).

4.18 Pre-qualification Program 4.18.1 The testing program implemented to demonstrate that the proposed method of _wet waste processing will result in a waste form acceptable to the land disposal facility.

4.19 QA Verification Sample 4.19.1 A representative sample of the waste that is tested to demonstrate control of the waste processing. The sample shall be obtained from at least every tenth batch of each type of wet radioactive waste processed for stabilization:

4.20 Quality Assurance/Quality Control 4.20.1 As used in this document, quality assurance" comprises all those planned and systematic actions necessary to provide adequate confidence that a structure, system, or component will perform satisfactorily in service.

Quality assurance includes quality control, which comprises those quality assurance actions related to control of the physical characteristics and quality of a material structure, component, or system to predetermined requiremerits.

4.21 Sampling Plan 4.21.l A sampling program implemented to ensure that representative samples from the feed waste and the final waste form are obtained and tested for conformance with parameters stated in the PCP and waste form acceptance criteria.

4.22 Scaling Factor 4.22.1 A dimensionless number which relates the concentration of an easy to measure*nuclide (gamma emitter) to one which is difficult to measure (beta/alpha emitters).

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100*

PROGRAM Information Use Page 12 of 34 4.23 Shipping Paper 4.23.1 At WCGS the shipping paper consists of an NRC form 540 and 541(or equivalent). Additional documentation may be provided (i.e., bill of lading) but is not consecutively numbered as part of the shipping papers.

4.24 Significant Quantity 4.24.1 For purposes of sample evaluation, waste classification and manifesting radionuclides on shipping papers, the following radionuclide limits shall be considered significant:

o Any LLD value for a 10 CFR Part 20, Appendix G required radionuclide.

o Any radionuclide representing greater than 5 percent of the relative A2 fraction hazard.

o Any real value for a radionuclide specifically listed in 10 CFR Part 61.55.

o Any radionuclide representing greater than 1 percent of the total activity.

o Any radionuclide greater than 0.5 RQ value .

.4.25 Special Nuclides 4.25.1 RADMAN Computer Code user term for 10 CFR Part 20, Appendix G required nuclides.

4.26 Stability

4. 26 .1 As used in this document, "stability" means structural stability. Stability requires that the waste form maintain its structural integrity under the expected disposal conditions .

. 4.27 Waste Container 4.27.1 A vessel of any shape, size, and composition used to contain the final or intermediate processed waste.

4.28 Waste Form 4.28.1 Waste in a stable waste form or container acceptable for disposal. at a licensed disposal facility.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 1-3 of 34 4.29 Waste Processing 4.29.1 Changing, modifying, packaging the commercial nuclear power plant generated wet radioactive waste into a form that is acceptable to a disposal facility.

4.30 Waste Stream 4.30.1 A station specific and constant source of waste with a distinct radionuclide content and distribution.

4.31 Waste Type

4. 31.1 A single packaging configuration tied to a specific waste stream, or multiple package types tied to the same waste stream.

5.0 RESPONSIBILITIES 5.1 Health Physics Radwaste Shipper is responsible for:

5 .1.1 Implementing this procedure.

5 .1. 2 Ensuring that radioactive waste is classified and characterized in accordance with 10 CFR 61.55 receiving facility criteria.

5.1. 3 Designating other approved procedures (if required) to be implemented in the packaging of any specific batch of waste.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 14 of 34 6.0 PROCEDURE 6.1 The precautions/limitations of this procedure are listed below.

6 .1.1 All plant personnel that have any involvement with the RADMAN, TRASHP, and FILTRK computer codes shall be familiar with its functions, operation, and maintenance.

6 .1. 2 Only authorized personnel will characterize or package radioactive waste or radioactive materials.

6.1. 3 Radioactive materials shall be handled in accordance with applicable Radiation Protection Procedures.

6 .1. 4 Pressure and heat may be encountered during the operation of liquid waste processing systems.

1. Caution must be exercised during disassembly and disconnection of lines or equipment and valve realignments.

6.1. 5 Each HIC is matched with specific closure components and seals at time of manufacture.

1. All components are identified using a common serial number.

2. Should components become mismatched, contact the HPSR for instructions prior to use.

6.1. 6 Waste must NOT be packaged for disposal in cardboard or fiberboard boxes.

6.1. 7 Liquid waste must be solidified or packaged in sufficient absorbent material to absorb twice the volume o"f the liquid.

6.1. 8 Solid waste containing liquid shall contain as little free standing and non-corrosive liquid as is reasonably achievable, but in no case shall the liquid exceed 1 percent of the volume in HIC's and 0.5% in a steel liner.

6 .1. 9 Waste must NOT be readily capable of detonation or of explosive decomposition or reaction at normal pressures and temperatures, or of explosive reaction with water.

Revision:. 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 15 of 34 6.1.10 Waste must NOT contain, or be capable of generating, quantities of toxic gases, vapors, or fumes harmful to persons transporting, handling, or disposing of the waste. This does NOT apply to radioactive gaseous waste packaged in accordance with Step 6.1.12 of this section.

6.1.11 Waste must NOT be pyrophoric. Pyrophoric materials contained in waste shall be treated, prepared, and packaged to be non-flammable.

6.1.12 Waste in a gaseous form must be packaged at a pressure that does not exceed 1.5 atmospheres at 20°C. Total activity must not exceed 100 curies per container.

6.1.13 Waste containing hazardous, biological, pathogenic, or infectious material must be treated to reduce to the maximum extent practicable the potential hazard from the non-radiological materials.

6.1.14 All data entries should use three significant figures only (i.e., X.XXE-x). IF more significant figures are provided, round off to generate three significant figures.

6.1.15 Use only those isotopes reported as real values, ignore all isotopes reported as LLD values, except those nuclides listed in Step 6.6.7.

6.1.16 Igndre all radioisotopes with half-lives less than eight (8) days based on I-131.

6.1.17 Revisions to this procedure shall be documented with form APF 15C-004-01, DOCUMENT REVISION REQUEST and shall contain: (Step 3.1.1)

1. Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change(s).

AND

2. A determination that the change will maintain the overall conformance of the waste product to existing requirements of F~deral, State, or other applicable regulations.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 16 of 34 6.2 Special equipment, material, and parts needed to perform tasks are shown below.

6.2.1 Required tools and equipment will vary depending on the specific process and waste container that is used.

6.2.2 The various tools and equipment, which may be required, are detailed in the vendor procedures listed in Section

3. 0.

6.3 Prerequisites before beginning work with this procedure.

6.3.1 Ensure that a current set of DOT, NRC and burial site regulations is maintained at the station and is available for reference.

6.3.2 Ensure that representative sample data is on file for each waste stream. Data is considered to be current if it meets the following:

1. The waste stream must be sampled at least every two years for NRC Class A waste.

2 The waste stream must be sampled at least every year for NRC Class B or C waste. Exceptions are:

a.legacy waste b.as generated waste

3. Non-waste radioactive material shall be sampled on a fuel cycle cir as generated basis with (non-irradiated) fuel pool material differentiated from balance of plant material.

6. 3. 3' A training program shall be developed and implemented for personnel having responsibilities related to waste processing operations to ensure the waste processi~g shall be performed within the requirements of the PCP.

1. Personnel will be trained to the extent equal to their responsibilities. WCGS credits training provided in accordance with standards or regulations of other federal agencies, such as the Occupational Safety and Health Administration or the Environmental Protection Agency.

2. The training program shall be repeated and the personnel requalified on a periodic schedule, not to exceed three years.

3. The individual's training records shall be maintained and available for audit and inqpection.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 17 of 34 6.3.4 Additional requirements for contracted vendors processing waste.

1. Management shall review vendor(s) topical reports.

NOTE The PCP does NOT have to include the vendors Topical Report if it has NRC approval, or has been previously submitted to the NRC.

a. This review will assure the vendors operations and requirements are compatible with the responsibilities and operation of the plant.

b. The training requirements and records listed in Step 6.3.3 also apply to contracted vendors.

c. The station shall maintain copies of records to verify training of vendor personnel.

6.4 Procedure For Performing Work 6.4.1 Methods and frequency for determining the radionuclide concentration for each waste stream.

1. Ensure samples are representative of the final waste form.

2. Determine the base line density for each waste stream (NOT applicable for DAW and filters).* The density is determined by waste weight ~nd volume.

NOTE For WCGS, waste stream radionuclide content is considered to be distributed throughout for purpose of waste classification.

6.4.2 Treat each waste stream separately for classification purposes.

6.4.3 Send all NRC Class A waste samples to an independent laboratory for gamma, beta and alpha analysis at least once every two years.

1. Perform an in-house analysis for gamma emitting radionuclides for each sample sent to an independent lab for future comparison.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 18 of 34

2. Periodically perform in-house analysis for gamma emitting nuclides for comparison to the current data base values for gamma emitters (the current data base is usuaily based on the most recent independent laboratory results).

6.4.4 Send all NRC Class B and C waste samp_les to an independent laboratory for gamma, beta.and alpha analysis at least once a year, except as defined in 6.3.2. The additional steps required are identical to substeps 1 and 2 of Step 6.4.3.

6. 4. 5 Determine the status (real value, LLD or not present) of the 10 CFR 20 Appendix G required nuclides for each waste stream from the recent independent laboratory data.

6. 4. 6 Document and track all samples per RPP 07-101, CONTROL OF RADIOACTIVE MATERIAL MANAGEMENT SOFTWARE AND .DATA BASES.

6.5 Current and planned practice for each waste stream is as follows:

6. 5 .1 DAW

1. Obtain composite smears from various contaminated areas of the plant periodically or at a minimum biennially and analyze (IG) them in-house for gamma emitters. Sample.periodicity should be based on the conditions outlined in Step 6.8.

2. Compare the results of the samples to the database to ensure adequacy of sample frequency.

3. Send the most recent group of composite smears to an independent laboratory for analysis biennially or more often IF determined necessary by HPRS.

4. Maintain records for all samples for nuclide identification, distribution and scaling factors.

NOTE The specific activity (µCi/cc or µCi/g) is NOT required since a11 characterization/c1assification calcu1atio~re performed using a dose/ curie methodology which only relies on frac.tional abundance.

5. Both in-house and independent laboratory results are normally reported in µCi/sample.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 19 of 34

6. Forward the results from the independent laboratory to the HP *Dosimetry/Calibration Lab for evaluation on RPF 01-405-05, "DETERMINATION OF DETECTABLE VS.

NON-DEtECTABLE ACTIVITY FOR RELEASE FROM THE RCA".

6.5.2 S/G Blowdown Resin

1. Obtain several (as determined by the HPRS) composite samples from the resin transfer line during liner loading operations on an "as generated".basis.

NOTE Each liner is considered a different batch for sampling and classification purposes.

2. Analyze the samples in-house ( IG) *and retain the results for future comparison to the replicate independent laboratory results.

3. Send the samples to an independent laboratory for analysis biennially or as generated .

4. Maintain records for all samples for nuclide identification, distribution and scaling factors.

5. Both in-house indepentjent laboratory ~esults are normally reported in the same units (µCi/g or

µCi/cc) .

6.5.3 CVCS Resin

1. The sampling procedure is exactly the same as listed above for S/G Blowdown Resin in Step 6.5.2 except the analysis frequency is annual or as generated.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 20 of 34 6.5.4 Filters

1. Obtain samples from each individual filter waste stream defined in Step 2.2 on an annual OR as generated basis.

NOTE Samples may be taken from the actual filter media, from a smear of the filter media, from a smear of the filter housing, or a crud sample, as determined by the HPSR. The preferred method is the crud sample.

2. Perform an in-house (IG) analysis of the sample ('or replicate sample) and retain the output record for future comparison to the independent laboratory results.

3. Send the sample to an independent laboratory for analysis once per year or more often if determine necessary by the HPRS.

4. Maintain records for all samples for nuclide identification, distributio~ and scaling factors.

NOTE CORRECTIVE ACTION FOR ADJUSTING Co-58 SCALING FACTORS FOR FILTERS DURING CRUD BURSTS ENCOUNTERED WITH CHEMICAL INJECTIONS AND 100%

LOAD REJECTIONS

5. The Co-58 scaling factors should be adjusted when the total radioactivity increases for filters during the above conditions, the activity increase is primarily Co-58 not Co-60, if the scaling factors are not adjusted the filters can be overestimated for NRC waste classification.

a. Step 1, Obtain a filter sample.

b. Step 2, Count the sample in-house, it is not necessary to perform an independent laboratory analysis.

c. Step 3, Divide the Co-58 value by the Co-60 value, this is the scaling factor.

d. Step 4, Obtain a hard copy of the Part 61 filter waste stream.

Revision: 8 SOLID RADWASTE PROCESS CONTROL .AP 31A-100 PROGRAM Information Use Page 21 of 34

e. Step 5, Apply the Step 3 scaling factor to the database Co-60 value.

f. Step 6, Create a new (crud burst) Part 61 waste stream with the new Co-58 value.

g. Step 7, Characterize filters.

NOTES o Document that there are two Part 61 waste streams for the same filters depending on operating conditions.

o The specific activity (µCi/cc or µCi/g) is not required since all characterization/classification calculations are performed using a dose/curie methodology which only relies on fractional abundance.

6. Both in-house and laboratory results are normally reported in µCi/sample.

6.5.5 Tubular Ultra Filtration/Reverse Osmosis Waste

1. Obtain a sample from the waste stream on an annual or as generated basis.

2. Perform an in-house (IG) analysis of the sample (or replicate sample) and retain the output record for future comparison to the independent laboratory results.

3. Send the sample to an independent laboratory for analysis once per year or more often if determine necessary by the HPRS.

4. Maintain records for all samples for nuclide identification, distribution and scaling factors.

6.6 Sample Evaluation

6. 6 .1 Infrequent or Abnormal Waste Types

1. Infrequent or abnormal waste types that may be generated must be evaluated on a case-by-case basis.

2. The HPRS will determine if the waste can be correlated to an existing waste stream.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 22 of 34

3. If the radioactive material cannot be correlated to an existing waste stream, the HPRS shall determine specific off-site sampling and analysis

requirements necessary to properly classify the material.

6. 6. 2 Examples of these radioactive materials 'include, but are not limited to:

o Contaminated Soil o Contaminated Oil o Special Filters or Resin o A mixture of radioactive material types in one container.

6. 6. 3 Requirements for analysis to be performed by an off-site vendor are as follows:

1. All sample results must reference the quantity received.

2. All sample results shall be decay corrected to a reference date provided by the station which is normally the sample date.

3. The sample results shall be reported in µCi/sample,

µCi/g or µCi/cc as determined the HPSR.

NOTE Outside analysis is NOT performed for any radionuclides with a half-life less than eight days.

6. 6. 4 The vendor shall perform analysis for the following radionuclides listed in Table 1 of 10 CFR 61.55.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 23 of 34

1. C-14, Tc-99, I-129, Pu-241, Cm-242 and the following alpha emitting transuranics (TRUs) with half-lives greater than five years, Np-237, Pu-238, Pu-239/240, Pu-242, Am-241, and Cm-243/244.

a. Additionally Ni-59 and Nb-94 are required for Rx cavity and fuel pool filters.

NOTE If evaluation of several sets (i.e., three or more) of waste stream specific historical sample data shows that some TRUs with half-life greater than five years are consistently reported as LLD values, sample analysis may be discontinued for those specific radionuclides.

2. Analysis for the "activated metal" radionuclides listed in Table 1 of 10 CFR Part 61 are only required for the fuel pool filters and reactor cavity filters waste streams identified at WCNOC.

3. It is NOT necessary to contract for an offsite vendor to perform analysis for enriched uranium or other naturally occurring radionuclides not delineated in this procedure.

4. Radionuclides listed in Table 1 of 10 CFR 61.55 shall be specifically identified and the quantities reported on shipping manifests if they are significant for purposes of classification.

6.6.5 The vendor shall perform analysis for the following radionuclides listed in Table 2 of 10 CF~ 61.55.

1. H-3, Co-60, Ni-63, Sr-90 and Cs-137

2. Radionuclides listed in Table 2 of 10 CFR 61.55 shall be specifically identified and the quantities reported on shipping manifests if they are sign~ficant for purposes of classification.

6. 6. 6 The vendor shall perform analysis for the following radionuclides NOT listed in Table 1 or Table 2 of 10 CFR 61.

1. Activation Products - Cr-51, Mn-54, Fe-55, Co-58, Fe-59, Sb-124, Sb-125, Zn-65, Ag-llOM and any other nuclides identif~ed in significant quantities by in-house IG equipment.

Revision: 8 SOLID RADWASTE PROCESS CONTROL 'AP 31A-100 PROGRAM Information Use Page 24 of 34

2. Fission Products - Zr-95, Nb-95, Ru-103, Ru-106, Cs-134, Ce-141, Sr-89, Ce-144 and any other nuclides identified in significant quantities by in-house IG equipment.

6.6.7 A waste stream specific database must include the foilowing radionuclides, even if they are report~d as LLD values:

1. H-3, C-14, Tc-99, I-129 required by 10 CFR 20 Appendix G. (H-3 is considered real or LLD for DAW because "not present" cannot be substanti~ted).

2. Co-60, Cs-137, and Ce-144 (only if TRUs are reported) required by the RADMAN computer code.

They are used as the primary scaling radionuclides.

3. The HPRS can change the base scaling radionuclides.

NOTE Samples sent to offsite laboratories for analysis should contain sufficient activity to determine the presence o~ transuranic nuclides. The minimum recommended sample activity level is 50,000 dpm. If that level cannot be attained, the highest activity should be used for offsite analysis.

6.7 Sample Analysis and Comparison 6.7.1 Whenever a sample is sent off-site for analysis, count the same sample (or replicate) in-house with the station IG system.

NOTE Isotopic results that are not considered statistically positive at the 99.9% confidence level are considered "suspect" values and shall be discarded as necessary.

6.7.2 Comparison of on-site versus off-site analysis shall be evaluated to identify and resolve any discrepancies.

As a minimum, the comparison shall include:

o Specific activity by gamma emitting radionuclides.

(NOT applicable for DAW or filter samples.)

o Co-60/Cs-137 Ratio o Presence or absence of radionuclides o Predominant radionuclides

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM I Information Use Page 25 of 34 o Individual radionuclide fractional abundance o Scaling factors 6.7.3 Records of on-site and off-site sample analysis and evaluations by waste stream are maintained by the HPRS.

6.7.4 IF a comparison between the in~house and independent laboratory results shows a variance. of 20 percent or greater for specific activity, the MCA results may be adjusted until the discrepancy is resolved. Reported MDC should be consistent with the measu~ement uncertainty. The relative uncertainty (lcr) of the measurement should be -30% at the MDC and should get smaller as the measured concentration increases above the MDC level.

1. Any discrepancies should be resolved (if p6ssible) in-house or with the independent laboratory as soon as possible.

2. The use of these activity correction factors is only valid if other conditions defined in Step 6.7.2 above compare favorably, otherwise the sample set should be considered suspect and the data should not be used.* This would require another sample as soon as possible.

6.7.5 Radionuclides with a half-life less than eight days are also ignored from internal MCA reports.

6. 7. 6 New sample qata shall be periodically obtained and evaluated.

6. 7. 7 New sample data may be either off-site analysis or in-house MCA analysis.

6.7.8 Once a database has been established, based on off-site analysis, the MCA results are primarily used as a "flag" to obtain and send additional samples off-site.

Exceptions to'this may occur during crud burst situations were it is necessary to adjust the scaling factor relationship of the activation products. An example would be the 58 Co/ 60 co ratio after hydrogen peroxide additions.

6.7.9 The RADMAN analyze utility program may be utilized to evaluate multiple sets of data.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 26 of 34 NOTE Isotopic resu1ts that are NOT considered statistica11y positive at the 99.9% confidence 1eve1 are considered "suspect" va1ues and sha11 be discarded as necessary.

6.7.10 Several comparisons to the existing database shall be considered when evaluating new sample data.

1. Radionuclide fractional abundance and scaling factor relationships

2. Specific activity by radionuclide

3. Swings in driving classifications radionuclides

4. Radionuclides present in database, but NOT present in new sample or vice versa

5. Total activity by sample set 6.8 Sample Frequency 6.8.1 The following may require increased sampling:

1. Increase in failed fuel fraction as determined by:

o D.E.I. 25% of Technical Specification limit o Increase of I-131/I-133 o Np-239 greater than 0.01 gCi/cc in reactor coolant o Significant increase in gross alpha sample results on any type of smear survey

2. Crud burst during 100% load rejection or chemical cleaning

3. Extended reactor sh~tdown (>90 days)

4. Changes to liquid waste processing, such as bypassing filters, utilizing filters or a change in ion exchange media

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 27 of 34 6.9 Scaling Factors 6.9.1 WCGS has established an inferential measurement program, whereby, concentrations of radioisotopes which cannot be readily measured are estimated through ratioing to concentrations of radioisotopes which can be readily measured.

6.9.2 Scaling factors have been developed on a facility and waste stream specific basis, and are periodically confirmed through direct measurements.

6.9.3 Correlations between measured and inferred radionuclides are currently as follows, but can be changed at HPRS discretion:

1. Ce-144 to transuranic nuclides

2. Co-60 to activation product nuclides and C-14

3. Cs-137 to fission product nuclides 6.10 Waste Classification NOTE The volume and mass of the waste form (not the waste container) is used for most waste classification calculations.

6.10.1 Determine the waste classification (Class A stable or unstable, Class B, Class C) by the concentration of certain radionuclides in the final waste form as listed in 10 CFR 61. 55.

6.10.2 Determine the radionuclide concentrations per RPP 07-123 PREPARATION AND SHIPMENT OF RADIOACTIVE WASTE AND MATERIAL, as follows:

1. DAW - "Gross Radioactivity Measurements" in conjunction with the RADMAN computer code or hand calculations

2. Filters - "Gross Radioactivity Measurements" in conjunction with the FILTRK computer code or hand calculations

3. All other waste streams - "Direct Measurement of Individual Radionuclides" in conjunction with the RADMAN computer code or hand calculations

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 28 of 34 6.11 Quality Control For Sampling And Classification 6 ._11. 1 The RADMAN computer code provides a mechanism to assist

,WCGS in conducting a quality control program to aid in compliance with the waste classification requirements listed in 10 CFR 61.55.

6. 11. 2 Management audits of the WCNOC Sampling and Classification Program shall be performed in accordance with the approved self assessment schedule.

6. 11. 3 The audits are performed and documented by any of the following:

Health Physics Department

Subject Matter Experts

Quality Assurance Department OR

Qualified Vendors 6.12 Non-Waste Classification 6.12.1 Determine the radioactive material classification (Excepted Package, LSA, SCO, Type A, >Type A or Type B) by the total activity or activity as listed in DOT regulations and the receiver's radioactive material licenses.

6.12.2 Determine the radionuclide concentrations per RPP 07-123 PREPARATION AND SHIPMENT OF RADIOACTIVE WASTE AND MATERIAL, as follows:

1. Non-irradiated material removed from the spent fuel pool - "Gross Radioactivity Measurements," "Direct Measurement of Individual Radionuclides", or "Measurement of Suiface Contamination Levels" for non-radioactive material contaminated with radioactive material in conjunction with the RAMSHP computer code or hand calculations.

2. Any other radioactive mateiial generated by the station - The same methods listed for fuel pool material may be used with a separate radionuclide database.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 2 9 ot' 34 6.13 Processing General Requirements NOTE The dewatering capabilities are verified by vendor Topical Reports or operating and testing procedures.

6.13.1 Verify the wastes contain only trace amounts of drainable liquid, and in NO case may the volume of free liquid exceed one percent of the waste volume when wastes are disposed of in containers designed to provide stability.

NOTE The following verification is performed on a case-by-case basis for each package using independent laboratory data and MCA data in conjunction with computer codes or hand calculations.

6.13.2 Verify that resins are NOT processed that have loadings which will produce greater than 1.0 E+8 rads (350

µCi/cc) total accumulated dose. This only applies to two radionuclides, Cs-137 and Sr-90.

6.13.3 The as generated waste must be compatible with the disposal container.

6.14 *Processing Requirements During Dewatering Operations 6.14.1 Perform all dewatering operations per RPP 07-131, BEAD RESIN/ACTIVATED CARBON DEWATERING PROCEDURE FOR CNSI 14-215- OR SMALLER LINERS.

NOTE This procedure may only be used to dewater CNSI's14-215 or smaller liners containing bead-type ion exchange resins and activated carbon with less than 1 percent oil.

6.14.2 Complete form RPF 07-131-01, HIC DEWATERING COMPLETION RECORD, for each liner prior to final closure.

6.14.3 Form RPF 07-131-01, HIC DEWATERING COMPLETION RECORD, must be included in the shipping paperwork package with the shipment.

6.14.4 The final transfer/dewatering cycle shall be counted as the first pumping cycle IF after the transfer is, completed, the liner is dewatering *per this procedure.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 30 of 34 6.14.5 Final dewatering verification is determined by the following:

1. 1% Free-Standing Water or Less

a. After a minimum of two (2) pumping cycles for bead resins or five (5) cycles for activated carbon, a measureq volume of less than five (5) gallons on the next eight (8) hours of pumping shall be the acceptance criteria.

b. IF five (5) gallons or more are collected, the waiting/pumping cycle shall be repeated until less than five (5) gallons are collected.

2. 0.5% Free-Standing Water or Less

a. After a minimum of five (5) pumping cycles for bead resins or eight (8) pumping cycles for activated carbon, a measured volume of less than two (2) gallons on the next eight (81 hours9.375e-4 days 0.0225 hours 1.339286e-4 weeks 3.08205e-5 months of pumping shall be the acceptance criteria.

b. IF two ( 2) gallons or more are collected, *the waiting/pumping cycle shall be repeated until less than two (2) gallons are collected.

6.15 Packaging General Requirements NOTE The L

following general requirements are normally verified by review of a HIC's Certificate of Compliance (C of C) and State/NRC approval.

6.15.1 Ensure that the waste is in a container or structure that provides stability after disposal.

6.15.2 Ensure that the container is resistant to degradation caused by radiation effects.

6.15.3 Ensure the container is resistant to bio-degradation.

6.15.4 Verify that the container will remain stable under the compressive loads inh_erent in the disposal environment.

6.15.5 Verify that the container will remain stable if exposed to moisture or water after disposal.

6.15.6 Ensure that the "as generated" waste is compatible with the container.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 31 of 34 6;16 Packaging Vendor Requirements 6.16.1 Perform all inspection, handling and loading operations per vendor procedure, FO-AD-002.

NOTE Prior to use, each user will have on file within Chem-Nuclear System, Inc. Regulatory Affairs Department a "Polyethylene High Integrity Container Certification Statement."

6.16.2 IF required, complete form FO-AD-002 HIC USER'S CHECKLIST, and transmit it to the vendor and maintain a copy on file.

6.16.3 Complete form FO-AD-002 HIC USER'S CHECKLIST, for each HIC liner as required.

6.16.4 Include Form FO-AD-002 HIC USER'S CHECKLIST, in the shipping paperwork package with the shipment as required.

6.16.5 Storage Conditions NOTES o Containers stored out-of-doors in direct sunlight must be used within one year of fabrication.

o The design of the storage facility must preclude the possibility of a wet or damp environment and any prolonged exposure of the container to ariy source of ultraviolet light.

1. Ensure that containers are stored out of direct sunlight (if possible) and away from any other sources of ultraviolet radiation.

2. Store all containers in such a way that the bottom is flat and that no weight is located over the manway/fill port area.

3. Each container shall be stored with its designated closure assemblies to prevent mismatching.

4. Following filling and closure of the container, it may be stored on-site prior to shipment for burial.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 32 of 34 6.16.6 Inspection Prior To Use

1. Visually inspect thread and seal areas to verify they are free of foreign matter that could impair the seal or thread engagement.

2. Visually inspect the exterior surfaces for damage that may have occurred during transport or storage that could lessen container integrity.

6.16.7 Handling.And Lift Requirements NOTE Due to the nature of the container material, some bowing and deformation may be evident during lifting.

l. Use only lift band(s), lift lugs and slings provided with the liner for lifting.

2. Inspect the underdrain assembly prior to use if the container was dropped or banged against another

object.

6.17 Additional Energy Solutions Containerized Waste Facility Requirements 6.17.1 Each package of waste must be clearly labeled to identify whether it is Class A, Class B, or Class C waste, in accordance with 10 CFR 61.55.

6.17.2 All waste received at the CWF facility must be disposed in approved disposal overpacks.

6.17.3 Void spaces within the waste and between the waste and its packaging shall ,be reduced to the extent pricticable, but in NO case shall the container less than 215 cubic foot be less than eighty-five percent (85%) full.

NOTE The acceptable void space depends upon the volume of the disposal container. This criteria is outlined in the Energy Solutions Waste Accep~ance Criteria.

6.17.4 HPRS must apply for a variance request prior to shipment.

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 33 of 34 7.0 RECORDS 7.1 The following QA Records are generated by this procedure.

7 .1.1 Com~leted HIC USER'S CHECKLIST (FO-AD-002) 7 .1. 2 Completed CERTIFICATION STATEMENT FOR DISPOSAL OF POLYETHYLENE HIGH INTEGRITY CONTAINERS (FO-AD-002) 7.2 The following Non-QA Record is generated by this procedure.

7.2.1 Completed POLYETHYLENE HIGH INTEGRITY CONTAINER CERTIFICATION STATEMENT (FO-AD-002) 8.0 FORMS 8.1 FO-AD-002, HIC USER'S CHECKLIST 8.2 FO-AD-002, CERTIFICATION STATEMENT FOR DISPOSAL OF POLYETHYLENE HIGH INTEGRITY CONTAINERS 8.3 FO-AD-002, POLYETHYLENE HIGH INTEGRITY CONTAINER CERTIFICATION STATEMENT

- END -

Revision: 8 SOLID RADWASTE PROCESS CONTROL AP 31A-100 PROGRAM Information Use Page 34 of 34 ATTACHMENT A (Page 1 of 1)

TECHNICAL REQUIREMENTS (SECTION 5.5.4)

Process Control Program (PCP)

The PCP shall contain the current formulas, sampling, analyses, test, and determinations made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requi~ements governing the disposal of solid radioactive waste~

Changes to the PCP:

1. Shall be documented and records of reviews performed shall be retained as required by the Quality Program Manual Section 17.9. This documentation shall contain:

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State; or other applicable regulations.

2. Shall b~come effective after review and acceptance by the Plant Safety Review Committee and the approval of the Plant Manager.

- END -

AP 31A-100 SOLID RADWASTE PROCESS CONTROL PROGRAM Responsible Manager MANAGER RADIATION PROTECTION.

LRevision __ Number _______ .. ___ .. __ . _____ J____ - *- ~ -. _____ _

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Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM !Page 1 of 33 TABLE OF CONTENTS SECTION TITLE 1.0 PURPOSE 2 2.0 SCOPE 2

3.0 REFERENCES

AND COMMITMENTS 5 4.0 DEFINITIONS 7 5.0 RESPONSIBILI TIES 12

6.0 PROCEDURE 13 7.0 RECORDS 32 8.0 FORMS 32 ATTACHMENT A TECHNICAL REQUIREMENTS (SECTION 5.5.4) 33

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM Page 2 of 33 1.0 PURPOSE 1.1 This procedure provides instructional guidance and a description of the solid waste Process Control Program (PCP).

The PCP describes the methods used for processing wet low-level radioactive waste into a waste form acceptable for disposal~ in accordance with 10 CFR 61 requirements, at a licensed land disposal facility.

2.0 SCOPE 2.1 This procedure describes current and planned practice for sampling, sample evaluation, classification, processing and packaging of radioactive material. This procedure does not address irradiated hardware which will be managed on a case by case basis under the direction of the Radiation Protection Manager (RPM). System descriptions and operating practices are described in the following steps.

2.2 Waste Stream Identification - The station identified six different waste streams and treats each separately for classification purposes. The identification listing may be consolidated, expanded and streams deleted at the discretion of radwaste management without revising the PCP.

EXAMPLES o Dry Active Waste (DAW) o Tubular Ultra Filtration/Reverse Osmosis* Process Waste o Chemical and Volume Control System(CVCS)Bead Resin (1) o Reactor Coolant System Filters o Spent Fuel Pool Filters o Radwaste Resins (l)May contain combination of eves, Diversified, and Spent Fuel Pool Resins 2.3 Non-Waste Stream Identification - The station has identified two different s6urces and treats each separately for classification purposes.

o Non-irradiated material removed from the Spent Fuel Pool.

o Any other radioactive material generated by the station.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM Page 3 of 33 2.4 Disposition of Radioactive Material Sent to a Vendor for Processing - Current practice includes sending all radioactive material types listed in step 2.2 to Energy Solutions, or other vendors for processing. Radioactive wastes shipped off-site for processing are not required to be solidified or dewatered to meet disposal requirements and are not subject to the solidification or dewatering requirements of the PCP.

2.4.1 This procedure addresses the requirements for 10 CFR 61.55 (Waste Classification) for radioactive material sent to vendor facilities.

2.4.2 This procedure does NOT address the requirements for 10 CFR 61.56 (Waste Characteristics), since the final processing and packaging are performed at the vendor facilities.

2.4.3 Vendors providing PCP services offsite will meet the requirements of their PCP process and applicable quality assurance requirements.

2.5 Disposition of Waste Sent Directly to a Burial Site - This procedure addresses both the 10 CFR 61.55 and 61.56 requirements for the waste streams listed in Step 2.2.

2.6 Waste Management Practices 2.6.1 DAW o This waste stream consists of plastic, wood, paper, metal, cloth, etc. generated at various locations within the station.

o The station may preprocess DAW by compacting.

o Practices include shipping DAW classified as either SCO or LSA in numerous possible containers, such as:

30 to 85 gallon drums

B-25 type boxes

SeaLand containers*

Large liners o Prepacking inspection criteria includes the removal of liquid, protective clothing and equipment, paints, solvents, lead, instruments, gages and other valuable plant equipment.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM !Page 4 of 33 2.6.2 Chemical and Volume Control System (CVCS) Bead Resin o This waste stream consists of eves, various Diversified Technologies media and Spent Fuel Pool resins. The depleted charcoal filter media and resins are sluiced from the individual processing vessels to a common Spent Resin Storage Tank or transferred directly to an* Energy Solutions 8-120 high integrity container (HIC),

OR any other container approved by Radiation Protection Radioactive Materials Shipper(RMS).

o Once a container is full or the transfer has been terminated, the filter media (charcoal) are processed and resins are then dewatered per RPP 07-131, Bead Resin/Activated Carbon Dewatering Procedure for Energy Solutions14-215 or Smaller Liners, Utilizing Energy Solutions Self-Engaging Dewatering System (S.E.D.S.) Compliance with freestanding water criteria is in accordance with the vendor waste acceptance criteria or 10CFR61.

2.6.3 Cartridge Filters o This category includes several waste streams which were defined in Step 2.2 and includes all filters generated by the station.

o Filters are removed from service based on operating parameters determined by the Operations Department.

o The filter housings are drained prior to filter removal. The filters are then gravity drained prior to being placed into an intermediate storage container OR the final disposal container.

o When sent for direct disposal, a final dewatering verification is performed on containers equipped with a dewatering internal after it has been loaded with filters. Compliance with freestanding water criteria is in accordance with the vendor waste acceptance criteria or 10CFR61.

o Absorbent material may be added to the disposal liner after final dewatering verification at the discretion of the RMS .

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM Page 5 of 33

2. 6. 4 Tubular Ultra Filtration/Reverse Osmosis Waste o This waste stream may consist of either filtration membranes or Drum Dryer Hold-Up Tank liquid waste.

o The membranes are processed as cartridge filters per step 2.6.3.

o Liquid wastes are transferred from the collection tank to an Energy Solutions 8-120 liner or other suitable container and sent directly to a vendor for additional processing.

2. 6. 5 Solidification/Encapsulation Methods o Present and planned practice is NOT to solidify or encapsulate any waste streams at the WCGS Facility.

2.6.6 Wet wastes o Filters and resins are dewatered to less than 0.5 percent or 1 percent by volume depending on the container type. Wet waste *sent to a vendor for additional processing will be processed in accordance with the approved vendor's processing program.

'\

2. 6. 7 Operation and Maintenance of Dewatering Systems and Equipment o Present and planned practice is to utilize station personnel to operate and maintain dewatering systems and equipment using station procedures.

o All disposal liners are manufactured by and purchased from approved vendors.

2. 6. 8 High Integrity Container Usage o High Integrity Containers(HIC) (fabricated from high density cross-linked polyethylene) may be used as the disposal package for any waste. Any vendor supplied HIC will have the appropriate regulatory approved report documenting compliance with waste form requirements when utilized for direct disposal.

3.0 REFERENCES

AND COMMITMENTS 3.1 References 3 .1.1 WCGS Technical Requirements (TR 5.5.4) 3 .1. 2 RPP 07-101, CONTROL OF RADIOACTIVE MATERIAL MANAGEMENT SOFTWARE AND DATA BASES

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM !Page 6 of 33 3.1. 3 RPP 07-123, PREPARATION AND SHIPMENT OF RADIOACTIVE WASTE AND MATERIAL 3 .1. 4 RPP 07-131, BEAD RESIN/ACTIVATED CARBON DEWATERING PROCEDURE FOR CNSI 14-215 OR SMALLER LINERS, Utilizing Energy Solutions Self-Engaging Dewatering System.

3.1. 5 1~ CFR 20, "Standard For Protection Agains~

Radiation" 3.1. 6 10 CFR 61, "Licensing Requirements for Land Disposal of Radioactive Waste" 3 .1. 7 10 CFR 71, "Packaging and Transportation of Radioactive Materials" 3 .1. 8 40 CFR 302, "Reportable Quantity Adjustment -

Radionuclides" 3 .1. 9 49 CFR 171, "General Information, Regulations, and Definitions" 3 .1.10 49 CFR 172, "Shippers' General Requirements for Shipments and Packaging" 3 .1.11 49 CFR 177, "Carriage by Public Highway"

3. 1. 12 USNRC Branch Technical Position on Radioactive Waste Classification, May 1983

3. 1. 13 USNRC Branch Technical Position on Waste Form, January 1991

3. 1. 14 USNRC Branch Technical Position on Concentration Averaging and Encapsulation, Revision in Part To Waste Classification Technical Position, January

1995 3 .1.15 NRC Bulletin No. 79-19, "P~ckaging of Low Level Radioactive Waste for Transport and Burial" 3 .1.16 NRC Information Notice No. 80~24, "Low Level Radioactive Waste Burial Criteria" 3.1.17 NRC Information Notice No. *83-33, "Non-Representative Sampling of Contaminated Oil"

3. 1. 18 NRC Information Notice No. 85-92, "Surveys of Wastes Before Disposal from Nuclear Reactor Facilities" 3 .1. 19 NRC Information Notice No. 86-20, "Low Level Radioactive Waste Scaling Factors, 10 CFR 61"

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM rage 7 of 33 3 .1. 20 NRC Informa~ion Notice No.88-101, "Shipment of Contaminated Equipment Between Nuclear Power Stations" 3.1.21 WMG-SW-006, "Computer Software Qua1ity Assurance Program" 3.1.22 WMG-QA-001, "Quality Assurance Program" 3.1.23 WMG-P-065 "RADMAN Operating Manual" 3.1.24 RADMAN Computer Code, Main Topical Report to the USNRC 3.1.25, WMG Report #9006, "Computer Program Dose to Curie Methodology Verification and Validation."

3.1.26 U.S. Nuclear Regulatory Commission, "Radiological Effluent Technical Specifications for PWRs,"

NUREG-0472 3 .1. 27 NRC Guidelines for Preparation .and Implementation of Solid Waste Process Control Program "DRAFT,"

Revision 4, October 1986 3.1.28 FO-AD-002, "Operating Guidelines for Use of Polyethylene High Integrity Containers" I 3.1.29 cs~oP-PR-010, "Bead Resin/Activated Carbon Dewateri,ng Procedure for Energy Solutions14-215 or Smaller Liners, Utilizing Energy Solutions Self-Engaging Dewatering System" 3 .1. 30 NRC Generic Letter No. 91-02, "Reporting Mishaps Involving LLW Forms Prepared For Disposal" 3 .1. 31 WMG-9217, "10 CFR 61 Practice Assessment at Wolf Creek Generating Station, 1992" 3 .1. 32 Letter from Rodney Wingard to Jimmy Still concerning the disposal of dried solids (HP 01-00601) 3.2 Commitments

3. 2 .1 None 4.0 DEFINITIONS 4.1 Abbreviations 4 .1.1 Activity/A 2 /g - Package activity divided by (A 2 )

divided by gram 4.;L.2 BTP - Branch Technical Position

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM* [)age 8 of 33 CNSI - Chem Nuclear System, Inc.

4 .1. 4 RMS - Radioactive Materials Shipper 4 .1. 5 LLD - Lower Limit of Detection 4 .1. 6 MCA - Multi-Channel Analyzer 4.2 Activity Correction Factor 4.2.1 The µCi/cc or µCi/g values may have to be corrected (plus or minus) if the waste stream specific 10 CFR 61 sample results (independent laboratory) and the replicate in-house specific activity values differ by more than 20 percent, and the differences cannot be resolved to the satisfaction of the RMS.

Alternatively, the dose-to-curie characterization methodology can be used without applying correction factors.

4.3 As Generated Waste 4.3.1 Radioactive waste generated at a frequency contrary to the sampling requirements of waste classes A, B or C.

4.4 Batch 4.4.1 An isolated quantity of feed waste to be processed having essentially constant physical and chemical chaiacteristics. (The addition or removal of water will not be considered to create a new batch).

4.5 Chelating Agents 4.5.1 EDTA, DTPA, hydroxyl-carboxylic acids, citric acid, carbolic acid and glucinic ac~d.

4.6 Confirmatory Analysis 4.6.1 Verification of Gross radioactivity measuremerits using MCA and independent laboratory sample data.

4.7 Density Correction 4.7.1 Density corrections may be required to convert sample data reported in µCi/g to µCi/cc or vice versa when comparing sample data with unlike units.

4. 8 Dewatered Waste 4.8.1 Dewatered Waste refers to wet waste that .has been processed by means other than solidification, encapsulatiort, or absorption to meet the free standing liquid requirements of 10 CFR 61. 56 (a) (3) and (b) ( 2) .

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM !Page 9 of 33

4. 9 Encapsulation 4.9.1 Encapsulation is a means of providing stability for certain types of waste by surrounding the waste by an appropriate encapsulation media.

4.10 Gamma-Spectral Analysis 4 .10 .1 Also known as IG, MCA, GE/Li and gamma spectroscopy 4.11 Gross Radioactivity Measurements 4.11.1 More commonly known as Dose to Curies conversion for packaged waste characterization and.classification.

4.12 Radiation Protection Radioactive Materials Shipper or RMS 4.12.1 The person designated to sign the shipment manifest and has been trained in the DOT and NRC regulatory requirements within the last three years.

4.13 Homogeneous 4.13.1 Of the same kind or nature; essentially alike. Most waste streams are considered to have the radioactivity distributed throughout for purposes of waste classification.

4.14 Legacy Waste 4 .14 .1 Radioactive waste generated from past Plant processes.

4.15 Low-Level Radioactive Waste (LLW) 4.15.1 Those low-level radioactive wastes containing source, special nuclear, or by-product material that are acceptable for disposal in a land disposal facility. For the purposes of this definition, low-level radioactive waste has the same meaning as in the Low Level Waste Policy Act, that is, radioactive waste not classified as high-level radioactive waste, transuranic waste, spent nuclear fuel, or by-product material as defined in Section 113. (2) of the Atdmic Energy Act (uranium or thorium tailings and wast~).

4.16 .. Measurement of Specific Ra4ionuclides '

1**;' ,., :.:* 1 ,_ 4;,~111.6!.,1 c:2: Mi:Y:te:: eofnmbn1iy ,knmJn as core sample or package sample

U~ih~-~CA a~ta fo~ packages waste characterization and classification .

. . ~- ..I

Revisiori: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM [Page 10 of 33 4.17 Operable 4.17.1 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its 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, tr'ain, component, or device to perform its *function(s) are also capable of performing their related support function(s).

4.18 Pre-qualification Program 4.18.1 The testing program implemented to demonstrate that the proposed method of wet waste processing will result in a waste form acceptable to the land disposal facility.

4.19 QA Verification Sample 4.19.1 A representative sample of the waste that is tested to demonstrate control of the waste processing. The sample shall be obtained from at least every tenth batch of each type of wet radioactive waste processed for stabilization.

4.20 Quality A~surance/Quality Control 4.20.1 As used in this document, "quality. assurance" comprises all those planned and systematic actions necessary to provide adequate confidence that a structure, system, or component will perform satisfactorily in service. Quality assurance includes quality control, which comprises those quality assurance actions related to control of the physical characteristics and quality of a material structure, component, or system to predetermined requirements.

4.21 Sampling Plan 4.21.1 A sampling program implemented to ensure that representative samples from the feed waste and the final waste form are obtained and tested for conformance with parameters stated in the PCP and waste form acceptance criteria.

4.22 Scaling Factor 4.22.1 A dimensionless number which relates the concentration of an easy to measure nuclide (gamma emitter) to one which is difficult.to measure (beta/alpha emitters).

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM Page 11 of 33 4.23 Shipping Paper 4.23.1 At WCGS the shipping paper consists of an NRC form 540 and 541(or equivalent). Additional documentation may be provided (i.e., bill of lading) but is not consecutively numbered as part of the shipping papers.

4.24 Significant Quantity 4.24.1 For purposes of sample evaluation, waste classification and manifesting radionuclides on shipping papers, the following radionuclide limits shall be considered significant:

o Any LLD value for a 10 CFR Part 20, Appendix G required.radionuclide.

o Any radionuclide representing greater than 5 percent of the relative A2 fraction hazard.

o Any real value for a radionuclide specifically listed in 10 CFR Part 61.55.

o Any radionuclide representing greater than 1 percent of the total activity.

o Any radionuclide greater than 0.5 RQ value.

4.25 Special Nuclides 4.25.1 RADMAN Computer Code user term for 10 CFR Part 20, Appendix G required nuclides.

4.26 Stability 4.26.1 As used in this document, "stability" means structural stability. Stability requires .that the waste form maintain its structural integrity under the expected disposal conditions.

4.27 Waste Container 4.27.1* A vessel of any shape, size, and composition used to contain the final *or interiediate processed waste.

4.28 Waste Form 4.28.1 Waste in a stable waste form or container acceptable

:for;:. d.J..*sposal . at, a [licensed t

rdisposal,.

( .

fac;:i}..:j,t:y*; *.. 1.,.,. ,.* .* ,, .,

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM !Page 12 of 33 4.29 Waste Processing 4.29.1 Changing, modifying, packaging the commercial nuclear power plant generated wet radioactive waste into a form that is acceptable to a.disposal facility.

4.30 Waste Stream 4.30.1 A station specific and constant source of waste with a distinct radionuclide content and distribution.

4.31 Waste Type

4. 31.1 A single packaging configuration tied *to a specific waste stream, or multiple package types tied to the same waste stream.

5.0 RESPONSIBILITIES 5.1 Radiation Protection Radioactive Material Shipper(RMS) is responsible for:

5.1.1 Implementing this procedure.

5.1. 2 Ensuring that radioactive waste is cl~ssified and characterized in accordance with 10 CFR 61.55 and reseiving facility criteria.

5 .1. 3 Designating other approved procedures (if required) to be implemented in _the packaging of any specific batch of waste.

Revision: 9 AP 3 lA'--1 0 0 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM !Page 13 of 33 6.0 PROCEDURE 6.1 The precautions/limita tions of this procedure are listed below.

6 .1.1 The RADMAN computer code is used for the characterization, classification and shipment of radioactive.materi als. All plant personnel that have any involvement with the RADMAN computer codes shall be familiar with its functions, operation, and maintenance.

6 .1. 2 Only authorized personnel will characterize or package radioactive waste or radioactive materials.

6 .1. 3 Radioactive materials shall be handled in accordance with applicable Radiation Protection Procedures.

6 .1. 4 Pressure and heat may be encountered during the operation of liquid waste processing systems.

1. Caution must be exercised during disassembly and disconnection of lines or equipment and valve realignments.

6 .1. 5 Each HIC is matched with specific closure components and seals at time of manufacture.

1. All components are identified using a common serial number.

2. Should components become mismatched, contact the RMS for instructions prior to use.

6 .1. 6 Waste must NOT be packaged for disposal in cardboard or fiberboard boxes.

6 .1. 7 Liquid waste must be solidified or packaged in sufficient absorbent material to absorb twice the volume of the liquid.

6 .1. 8 Solid waste containing liquid shall contain as little free standing and non-corrosive liquid as is reasonably achievable, but in no case shall the liquid exceed 1 percent of ~he volume in HIC's. and 0.5% in a steel liner.

6.1. 9 Waste must NOT be readily capable of detonation or of explosive decomposition or reaction at normal pressures and temperatures, or of explosive reaction with water.

Revision: 9 AP 31A:....100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM age 14 of 33 6 .1. 10 Waste must NOT contain, or be capable of generating, quantities of toxic gases, vapors, or fumes harmful to persons transporting, handling, or disposing of the waste. This does NOT apply to radioactive gaseous waste packaged in accordance with Step 6.1.12 of this section.

6 .1. 11 Waste must NOT be pyrophoric. Pyrophoric materials contained in waste shall be treated, prepared, and packaged to be non-flammable.

6 .1. 12 Waste in a gaseous form must be packaged at a pressure that does not exceed 1.5 atmospheres at 20oC. Total activity must not exceed 100 curies per container.

6. 1. 13 Waste containing hazardous, biological, pathogenic, or infectious* material must be treated to reduce to the maximum extent practicable the potential hazard from the non-radiological materials.

6 .1. 14 All data entries should use three significant figures only (i.e., X.XXE~x). IF more significant figures are provided, round off to generate three significant figures.

6 .1. 15 Use only those isotope~ reported as real values, ignore all isotopes reported as LLD values, except those nuclides listed in Step 6.6.7.

6.1.16 Ignore all radioisotopes with half-lives less than eight (8) days based on I-131.

6.1.17 Revisions to this prqcedure shall be documented with form APF 15C-004-01, DOCUMENT REVISION REQUEST and shall contain: (Step 3.1.1) o Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change(s).

o A dete.rmination that the change will maint*ain the overall conformance of the waste product to existing requirements of Federal, State, oir other applicable regulations.

6 .2 ,, Special equipment, material,* and 'parts rneededr,to. : :* .. i _.,.: : . ~, ,. j i .::;~; c>r;: ,;;'

perform tasks a.re shown below. . . * * :**. * * : * :: .. * ** , ' 1, * * '

6.2.1 Required tools and equipment will vary depending on the specific process and waste container that is used.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM Page 15 of 33 6.2.2 The various tools and equipment, which may be required, are detailed in the vendor procedures listed in Section 3.0.

6.3 Prerequisites before beginning work with this procedure.

6.3.1 Ensure that a current set of DOT, NRC and burial site regulations is maintained at the station and is available for reference.

6.3.2 Ensure that representative sample data is on file for each waste stream. Data is considered to be current if it meets the following:

1. The waste. stream must be sampled at least ev~ry two years *for NRC Class A waste.

2. The waste stream must be sampled at least every year for NRC Class B or C waste.

__ Exc_e_ptiQn_Q_ are: ________________ ____ _

a. legacy waste

b. as generated waste

3. Non-waste radioactive material shall be sampled on a fuel cycle or as generated basis with (non-irradiated) fuel pool material differentiated from balance of plant material.

6.3.3 The training program shall be developed and implemented for personnel having responsibilities related to waste processing operations to ensure the waste processing shall be performed within the requirements of the PCP.

1. Personnel will be trained to the extent equal to their responsibilities. WCGS credits training provided in accordance with standards or regulations of other federal agencies, such as the Occupational Safety and Health Administration or the Environmental Protection Agency.

2. The training program shall be repeated on a periodic schedule, not to exceed three years.

3. The individual's training records shall be maintained and available for audit and inspection.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM !Page 16 of 33 6.3.4 Additional requirements for contracted vendors processing waste.

1. Radiation Protection Management shall review vendor(s) topical reports.

The PCP does NOT have to inciude the vendor Topical Report if it has NRC approval, or has been previously submitted to the NRC.

a. This review will assure the vendors operations and requirements are compatible with the responsibilities and operation of the plant.

b. The training requirements and records listed in Step 6.3.3 also apply to contracted-vendors.

c. The station shall maintain copies of records to ¥erify training of vendor persorirrel.

6.4 Procedure For Performing Work

6. 4 .1 Methods and frequency for determining the radionuclide concentration for each waste stream.

1. Ensure samples are representative of the final waste form.

2. Determine the base line density for each waste stream (NOT applicable for DAW and filters). The density is determined by waste weight and volume.

For WCGS, waste stream radionuclide content is considered to be distributed throughout for.purpose of waste classification.

6.4.2 Treat each waste stream separately for classification purposes, , , , :* . .. t . ** .

Revision: 9 AP 31A-100

. SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM IDage 17 of 33 6.4.3 Send all NRC Class A waste samples to an independent laboratory for gamma, beta and alpha analysis at least once every two years.

1. Perform an in-house analysis for gamma emitting radionuclides for each sample sent to an independent lab for future comparison.

2. Periodically perform in-house analysis for gamma emitting .nuclides for comparison to the current data base values for gamma emitters (the current data base is usually based on the most recent independent laboratory results).

6.4.4 Send all NRC Class Band C waste samples to an independent laboratory for gamma, beta and alpha analysis at least once a year, except as defined in 6.3.2. The additional steps reqtiired are identical to substeps 1 and 2 of Step 6.4.3.

6.4.5 Determine the status (real value, LLD or not present) of the 10 CFR 20 Appendix G required nuclides for each waste stream from the recent independent laboratory data.

6. 4. 6 Document and track all samples per RPP 07-101, CONTROL OF RADIOACTIVE MATERIAL MANAG~MENT SOFTWARE AND DATA BASES 6.4.7 Sample *periodicity adjustment should be based on the conditiqns outlined in Step 6.8.

6.5 Current and planned practice for each waste stream is as follows:

6.5.1 DAW

1. Obtain composite smears from various contaminated areas of the plant periodically or at a minimum biennially and analyze (IG) them in-house for gamma emitters.

2. Compare the results of the samples to the database to ensure adequacy of sample frequency. \

3. Send the most recent group of composite smears to an independent laboratory for analysis biennially or more often-IF determined necessary by RMS.

4. Maintain records for all samples for nuclide identification, distribution and scaling factors.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM age 18 of 33 The specific activity (µCi/cc or µCi/g) is NOT required since all characterization/cl*assification calculations are performed using a dose/curie methodology which only relies on fractional abundance.

5. Both in-house and indepetident laboratory results are normally reported in µCi/sample.

6. Forward the results* from the independent laboratory to the HP'Dosimetry/Calibration Lab for evaluation on RPF 01~405-05, "DETERMINATION OF DETECTABLE VS.

NON-DETECTABLE ACTIVITY FOR RELEASE FROM THE RCA".

6.5.2 eves Resin .I

1. Obtain several composite samples from the resin transfer line during liner loading operations.

Each liner is considered a different batch for sampling and classification purposes.

2. Analyze the samples in-house (IG) and retain the results for future comparison to the replicate independent laboratory results.

3. Send the samples to*an independent laboratory for analysis annually or as generated.

4. Maintain records for all samples for nuclide identification, distribution and scaling "factors.

5. Both in-house independent laboratory results are normally reported in the same units

(µCi/g or µCi/cc).

6.5.3 Filters

1. Obtain samples from each individual filter waste stream defined in Step 2.2.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM !Page 19 of 33

Samples may be taken from the actual filter media, from a smear of the filter media, from a smear of the filter housing, or a crud sample, as determined by the RMS. The preferred method is the crud sample.

2. Perform an in-house (IG) analysis of the sample (or replicate sample) and retain the output record for future comparison to the independent laboratory results.

3. Send the sample to an independent laboratory for analysis annually or more often if determined to be necessary by the RMS.

4. Maintain records for all samples for nuclide identification, distribution and scaling factors.

CORRECTIVE ACTION FOR ADJUSTING Co-58 SCALING FACTORS FOR FILTERS DURING CRUD BURSTS ENCOUNTERED WITH.CHEMICAL INJECTIONS AND 100% LOAD REJECTIONS 5; The Co-58 scaling factors should be adjusted when the total radioactivity increases for filters during the above conditions, the activity increase is primarily Co-58 not Co-60, if the scaling factors are not adjusted the filters can be overestimated for NRC waste classification.

a. Step 1, Obtain a filter sample.

b. Step 2, Count the sample in-house, it is not necessary to perform an independent laboratory analysis.

c. Step 3, Divide the .Co-58 value by the Co-60 value, this is the scaling factor.

d. Step 4, Obtain a hard copy of the Part 61 filter waste stream.

e. Step 5, Apply the s*tep 3 scaling factor to the database Co-60 value.

Revision: 9 AP 31A-100 SOLID RA.DWASTE PROCESS CONTROL Information Use PROGRAM Page 20 of 33

f. Step 6, Create a new (crud burst) Part 61 waste stream with the new Co-58 value .

. g. Step 7, Characterize filters.

NOTES o Document that there are two Part 61 waste streams for the same filters depending on operating conditions.

o The specific activity ( Ci/cc or Ci/g) is not required since all characterization/classification calculations are performed using a dose/curie methodology which only relies on fractional abundance.

6. Both in-house a'nd laboratory results are normally reported in µCi/sample.

6.5.4 Tubular Ultra Filtration/Reverse Osmosis Waste

1. Obtain a sample from the waste stream on an annual or as generated basis.

2. Perform an in-house (IG) analysis of the sample (or replicate sample) and retain the output record for future comparison to the independent laboratory results.

3. Send the sample to an independent laboratory for analysis once per year or more often if determined to be necessary.

4. Maintain records for all samples for nuclide identification, distribution and scaling factors.

6.6 Sample Evaluation

6. 6 .1 Infrequent or Abnormal Waste Types

1. Infrequent or abnormal waste types that may be generated must be evaluated on a case-by-case basis.

2. The RMS will determine if the waste can be correlated to an.existing waste stream.

3. If the radioactive material cannot be correlated to an existing waste strea~, the RMs* shall determine specific off-site sampling and analysis requirements necessary to properly classify the material.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM Page 21 of 33 6.6.2 Examples of these radioactive materials include, but are not limited to:

o Contaminated Soil o Contaminated Oil o Special Filters or Resin o A mixture of radioactive material types in one container.

6.6.3 Requirements for analysis to be performed by an off site vendor'are as follows:

1. All sample results must reference the matrix received.

2. All sample results shall be decay corrected to a reference date provided by the station which is normally the sample date.

3. The sample results shall be reported in

µCi/sample, µCi/g or µCi/cc.

Outside analysis is NOT required for any radionuclides with a half life less than eight days.

6. 6. 4 The vendor shall perform analysis for the following radionuclides listed in Table 1 of 10 CFR 61. 55.

1. C-14, Tc-99, I-129, Pu-241, Cm-242 and the following alpha emitting transuranics (TRUs) with half-lives greater than five years, Np-237, Pu-238, Pu 239/240, Pu-242, Am-241, and Cm 243/2.44.

a. Additionally Ni-59 and Nb-94 are required for Rx cavity and fuel pool filters.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM age 22 of 33 If evaluation of several sets (i.e., three or more) of waste stream specific historical sample data shows that some TRUs with half-life greater than five years are consistently reported as LLD values, sample analysis may be discontinued for those specific radionuclides.

2. Analysis for the "activated metal" radionuclides listed in Table 1 of 10 CFR Part 61 are only required for the fuel pool filters and reactor cavity filters waste streams identified at WCNOC.

3. It is NOT necessary to contract for an offsite vendor to perform analysis for enriched uranium or other naturally occurring radionuclides not delineated in this procedure.

4. Radionuclides listed in Table 1 of 10 CFR 61.55 shall be specifically identified and the quantities reported on shipping manifests if they are significant for purposes of classification.

6.6.5 The vendor shall perform analysis for the following radionuclides listed in Table 2 of 10 CFR 61. 55.

1. H-3, Co-60, Ni~63, Sr-90 and Cs-137

2. Radionuclides listed in Table 2 of 10 CFR 61.55 shall be specificall~ identified and the quantities reported on shipping manifests if they are significant for purposes of classification.

6. 6. 6 The vendor shall perform analysis for the following radionuclides NOT listed in Table 1 or Table 2 of 10 CFR 61.

1. Activation Products - Cr-51, Mn-54, Fe-55, Co-58, Fe-59, Sb-124, Sb-125, Zn-65, Ag-llOM and any other nuclides identified in significant quantities by in-house IG equipment.

2. Fission Products - Zr-95, Nb-95, Ru-103, Ru-106, Cs-134, Ce-141, Sr-89, Ce-144 and any other nuclides identified in significant quantities by in-house IG equipment.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM !Page 23 of 33 6.6.7 A waste stream specific database must include the following radionuclides, even if they are reported as LLD values:

1. H-3, C-14, Tc-99, I-129 required by 10 CFR 20 Appendix G (H-3 is considered real or LLD for DAW because "not present" cannot be substantiated).

2. Co-60, Cs-137, and Ce-144 (only if TRUs are reported) required by the RADMAN computer code. They are used as the primary scaling radionuclides.

3. The RMS can change the base scaling radionuclides.

Samples sent to offsite laboratories for analysis should contain sufficient activity to determine the presence of transuranic nuclides. The minimum recommended sample activity level is 50,000 dpm. If that level cannot be attained, the highest activity should be used for offsite analysis.

6.7 Sample Analysis and Comparison 6.7.1 Whenever a sample is sent off-site for analysis, count the same sample (or replicate) in-house with the station IG system.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM Page 24 of 33 Isotopic results that are not considered statistically positive at the 99.9% confidence level are considered "suspect" values and shall be discarded as necessary.

6.7.2 Comparison of on-site versus off-site analysis shall be evaluated to identify and resolve any discrepancies. As a minimum, the comparison shall include:

o Specific activity by gamma emitting radionuclides. (NOT applicable for DAW or filter samples.)

o Co-60/Cs-137 Ratio o Presence or absence of radionuclides o Predominant radionuclides o Individual radionuclide fractional abundance o Scaling factors 6.7.3 Records of on-site and off-site sample analysis and evaluations by waste stream are maintained by the RMS.

6. 7. 4 IF a comparison between the in-house and independent laboratory results shows a variance of 20 percent or greater for specific activity, the MCA results may be adjusted until the discrepancy is resolved. Reported MDC should be consistent with the measurement uncertainty. The relative uncertainty (1) of the measurement should be -30% at the MDC and should get smaller as the measured concentration increases above the MDC level.

1. Any discrepancies should be resolved (if possible) in-house or with the independent laboratory as soon as possible.

2. The use of these activity correction factors is only valid if other conditions defined in Step 6.7.2 above compare favorably, otherwise the sample set should be considered suspect and the data should not be used. This would require another sample as soon as possible.

6.7.5 Radionuclides with a half-life less than eight days are also ignored from internal MCA reports.

Revision: 9 AP 3°1A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM Page 25 of 33

6. 7. 6 New sample .data shall be periodically obtained and evaluated.

6.7.7 New sample data may be either off~site analysis or in house MCA analysis.

6.7.8 Once a database has been established, based on off site analysis, the MCA results are primarily used as a "flag" to obtain and send additional samples off site. Exceptions to this may occur during crud burst situations were it is necessary to adjust the scaling factor relationship of the activation products. An example would be the ssco/60co ratio after hydrogen peroxide additions.

6. 7. 9 The RADMAN analyze utility program may be utilized to evaluate multiple sets of data.

Isotopic results that are NOT considered statistically positive at the 99.9% confidence level are considered "suspect" values and shall be discarded as necessary.

6.7.10 Several comparisons to the existing database shall be considered when evaluating new sample data.

1. Radionuclide fractional abundance and scaling factor relationships

2. Specific activity by radionuclide

3. Swings in driving classifications radionuclides

4. Radionuclides present in database, but NOT present in new sample or vice versa

5. Total activity by sample set

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM age 26 of 33 6.8 Sample Frequency

6. 8. 1 The following may require increased sampling:

1. Increase in failed fuel fraction as determined by:

o D.E.I. 25% of Technical Specification limit o Increase J .

of I-131/I-133 o Np-239 greater than 0.01 µCi/cc in reactor coolant o Significant increase in gross alpha sample results on any type of smear survey

2. Crud burst during 100% load rejection or chemical cleaning

3. Extended reactor shutdown (>90 days)

4. Changes to liquid waste processing, such as bypassing filters, utilizirig filters or a change in ion exchange media 6.9 Scaling Factors 6.9.1 WCGS has established an inferential measurement program, whereby, concentrations of radioisotopes which cannot be readily measured are estimated through ratioing to conceritrations of radibisotopes which can be readily measured.

6.9.2 Scaling factors have been developed on a facility and*waste stream specific basis, and are periodically confirmed through direct measurements.

6.9.3 Correlations between measured and inferred radionuclides are currently as follows, but can be changed at RMS discretion:

1. Ce-144 to transuranic nuclides

2. Co-60 to activation product nuclides and C-14

3. Cs-137 to fission product nuclides 6.10 Waste Classification 6.10.1 Determine the waste classification (Class A stable or unstable, Class B, Class C) by the concentration of certain radionuclides in the final waste form as listed in 10 CFR 61.55.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM ~age 27 of 33 6.10.2 Determine the radionuclide concentrations per RPP 07 123 PREPARATION AND SHIPMENT OF RADIOACTIVE WASTE AND MATERIAL, as follows:

1. DAW - "Gross Radioactivity Measur.ements" in conjunction with the RADMAN computer code or hand calculations

2. Filters - "Gross Radioactivity Measurements" in conjunction wjth the FILTRK computer code or hand calculations

3. All other waste streams - "Direct Measurement of Individual Radionuclides" in conjunction with the RADMAN computer code or hand calculations 6.11 Quality Control For Sampling And Classification 6.11.1 The RADMAN computer code provides a mechanism to assist WCGS in conducting a quality control program to aid in compliance with the waste classification requirements listed in 10 CFR

61. 55.

6. 11. 2 Management audits of the WCNOC Sampling and Classification Program shall be performed in accordance with the approved self assessment schedule.

6. 11. 3 The audits are performed and documented by any of the following:

Radiation Protection Department

Subject Matter Experts

Quality Assurance Department

Qualified Vendors 6.12 Non-Waste Classification 6.12.1 Determine the radioactive material classification (Excepted Package, LSA, SCO, Type A, >Type A'or Type B) by the total activity or activity as listed in DOT regulations and the receiver's radioactive material licenses.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM Dage 28 of 33 6.12.2 Determine the radionuclide concentrations per RPP 07-123, PREPARATION AND SHIPMENT OF RADIOACTIVE WASTE AND MATERIAL, as follows:

1. Non-irradiated material removed from the spent fuel pool - "Gross Radioactivity Measurements," "Direct Measurement of Individual Radionuclides", or "'Measurement of Surface Contamination Levels" for non-radioactive material contaminated with radioactive material in conjunction with the RADMAN computer code or.hand calculations.

2. Any other radioactive material generated by the station - The same methods listed for fuel pool *material may be used with a separate radionuclide database.

6.13 Processing General Requirements The dewatering capabilities are verified by vendor Topical Reports or operating and testing procedures.

6.13.1 Verify the wastes contain only trace amounts of drainable liquid, and in NO case may the volume of free liquid exceed one percent of the waste volume when wastes are disposed of in containers designed to provide stability.

The following verification is performed on a case-by-case basis for each package using independent laboratory data and MCA data in conjunction with computer codes or hand calcul~tions.

6.13.2 Verify that resins are NOT processed that have loadings which will produce greater than 1.0 E+8 rads (350 Ci/cc) total accumulated dose. This only applies to two radionuclides, Cs-137 and Sr-90.

6.13.3 The as generated waste must be compatible with the disposal container.

I Revision: 9 I AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM IT?age 29 of 33 6.14 Processing Requirements During Dewatering Operations 6.14.1 Perform all dewatering operations per RPP 07 131, Bead Resin/Activated Carbo~ Dewatering Procedure for Energy Solutions14-215 or Smaller Liners, Utilizing Energy Solutions Self-Engaging Dewatering System" NOTE This procedure may only be used to dewater Energy Solutions14-215 or smaller liners containing bead-type ion exchange resins and activated carbon with less than 1 percent oil.

6.14.2 Complete form RPF 07-131-01, HIC DEWATERING COMPLETION RECORD, for direct 'disposal liners prior to final closure.

6.14.3 Form RPF 07-131-01, HIC DEWATERING COMPLETION RECORD, must be included in the shipping paperwork package with the shipment.

6.14.4 The final transfer/dewatering cycle shall be counted as the first pumping cycle IF after the transfer is completed, the liner is dewatering per this procedure.

6.14.5 Final dewatering verification is determined by the following:

1. 1% Free-Standing Water or Less

a. After a minimum of three pumping cycles for bead resins or six cycles for activated carbon, a measured volume of less than five gallons on the next eight hours of pumping shall be the acceptance criteria.

b,.

IF five gallons or more are collected, the waiting/pumping cycle shall be repeated until less than five gallons are collected.

2. 0.5% Free-Standing Water or Less

a. After a minimum of six pumping cycles for bead resins or nine pumping cycles for activated carbon, a measured volume of less than two gallons on the next eight hours of pumping shall be the acceptance criteria.

Revision: 9 ' AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM Page 30 of 33

b. IF two gallons or more are collected, the waiting/pumping cycle shall be repeated until less than two gallons are collected.

6.15 Packaging General Requirements The following general requirements are normally verified by review of a HIC's Certificate of Compliance (C of C) and State/NRC approval.

6.15.1 Ensure that the waste is in a container or structure that provides stability after disposal ..

6.15.2 Ensure that the container is resistant to degradation caused by radiation effects.

6.15.3 Ensure the container is resistant to bio-degradation.

6.15.4 Verify that the container will remain stable under the compressive loads inherent in the disposal environment.

6.15.5 Verify that the container will remain stable if exposed to moisture or water after disposal.

6.15.6 Ensure that the "as generated" waste is compatible with the container.

6.16 Packaging Vendor Requirements 6.16.1 Perform all inspection, handling and loading operations per vendor procedure, FO-AD-002.

6.16.2 IF required, complete form FO-AD-002. HIC USER'S CHECKLIST, for each HIC liner and transmit it' to the vendor. Maintain a copy on file.

6.16.3 Include Form FO-AD-002 HIC USER'S CHECKLIST, in the shipping paperwork_ package with the shipment as required.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM Page 31 of 33 6.16.4 Storage Conditions NOTES o Containers stored out-of-doors in direct sunlight must be used within one year of fabrication.

o The design of the storage facility must preclude the possibility of a wet or damp environment and any prolonged exposure of the container to any source of ultraviolet light.

1. Ensure that containers are stored out of direct sunlight (if possible) and away from any other sources of ultraviolet radiation.

2. Store all containers in such a way that the bottom is flat and that no weight is located over the manway/fill port area.

3. Each container shall be stored with its designated closure assemblies to prevent mismatching.

4. Following fill~ng and closure of the container, it may be stored on-site prior to

'shipment for burial.

6.16.5 Inspection Prior To Use

1. Visually inspect thread and seal areas to verify they are free of foreign matter that could impair the seal or thread engagement.

2. Visually inspect the exterior surfaces for damage that may have occurred during transport or storage that could lessen containe~ integrity.

6.16.6 Handling and Lift Requirements Due to the nature of the container material, some bowing and deformation may be evident during lifting.

1. Use only lift band(s), lift lugs and slings provided with the liner for lifting.

Revision: 9 AP 31A-100 SOLID RADWASTE PROCESS CONTROL Information Use PROGRAM Page 32. of 33

2. Inspect the underdrain assembly prior to use if the container was dropped or banged against another object.

6.17 Additional Energy Solutions Containerized Waste Facility Requirements 6.17.1 Each package of waste must be clearly labeled to identify whether it is Class A, Class B, or Class C waste, in accordance with 10 CFR 61.55.

6.17.2 All waste received at the CWF facility must be disposed in approved disposal overpacks.

6.17.3 Void spaces within the waste and between the waste and its packaging shall be reduced to the extent practicable, but in NO case shall the container less than 215 cubic foot be less than eighty-five percent (85%) full.

The acceptable void space depends upon the volume of the disposal container. This criteria is outlined in the Energy Solutions Waste Acceptance Criteria~

6.17.4 RMS must apply for a variance request prior to shipment for any container not meeting the acceptance criteria.

7.0 RECORDS 7.1 The following QA Records are generated by this procedure.

7 .1.1 Completed HIC USER'S CHECKLIST (FO-AD-002) 7 .1. 2 Completed CERTIFICATION STATEMENT FOR DISPOSAL OF POLYETHYLENE HIGH INTEGRITY CONTAINERS (FO-AD-002) 7.2 The following Non-QA Record is generated by this procedure.

7.2.1 Completed POLYETHYLENE HIGH INTEGRITY CONTAINER CERTIFICATION.STATEMENT (FO-AD-002) 8.0 FORMS 8.1 FO-AD-002, ATTACHMENT 1, HIC USER'S CHECKLIST 8.2 FO-AD-002, ATTACHMENT 2, CERTIFICATION STATEMENT FOR DISPOSAL OF .POLYETHYLENE HIGH INTEGRITY CONTAINERS 8.3 FO-AD-002, ATTACHMENT 3, POLYETHYLENE HIGH INTEGRITY CONTAINER CERTIFICATION STATEMENT

Revision: 9 AP 31A-100

\

SOLID RADWASTE PROCESS CONTROL Information Use , PROGRAM Page 33 of 33 ATTACHMENT A (Page 1 of 1)

TECHNICAL REQUIREMENTS (SECTION 5.5.4)

Process Control Program (PCP)

The PCP shall contain the current formulas, sampling, analyses, test, and determinations made to ensure that processing and packaging of solid ra,dioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

Changes to the PCP:

1. Shall be document and records of reviews performed shall be retained as required by the Quality Program Manual Section 17.9. This documentation shall contain:

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and *

b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

2. Shall become effective after review and acceptance by the Plant Safety Review Committee and the approval of the Plant Manager.

-END-

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ML19126A086

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SUMMARY

3.0 REFERENCES

3.0 REFERENCES

4.1 ACTIONS

4.7 FUNCTIONAL-FUNCTIONALITY

1.0 INTRODUCTION

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ML19126A086

Text

Subject:

Enclosure:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

3.0 REFERENCES

3.0 REFERENCES

4.1 ACTIONS

4.7 FUNCTIONAL-FUNCTIONALITY

1.0 INTRODUCTION

3.0 REFERENCES

3.0 REFERENCES

1.0 INTRODUCTION

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

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