ML061210159

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Susquehanna - Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-6041
ML061210159
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Issue date: 04/17/2006
From: McKinney B T
Susquehanna
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Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-6041
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-/Britt T. McKinney Vice President-Nuclear Site Operations APR 17 2006 PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3149 Fax 570.542.1504 btmckinney@pplweb.com TM U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OPI-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE EFFLUENT RELEASE REPORT AND OFFSITE DOSE CALCULATION MANUAL PLA-6041 Docket No. 50-387 and 50-388 In accordance with 10 CFR 50.36a(a)(2) and the Susquehanna Steam Electric Station (SSES) Units 1 and 2 Technical Specifications Section 5.6.3, attached is the annual Radioactive Effluent Release Report for SSES Units 1 and 2 covering the period January 1 through December 31, 2005. Additionally, pursuant to Technical Specification Section 5.5.1.C.3, attached is a copy of the Offsite Dose Calculation Manual as revised through December 31, 2005.If you have any questions, please contact Mr. Rocco R. Sgarro, Manager -Nuclear Regulatory Affairs, at (610) 774-7552.Sincerely, B. T. MzKinney Attachment copy: Mr. A. J. Blarney, NRC Sr. Resident Inspector Mr. S. J. Collins, NRC Region I, Regional Administrator Mr. J. T. Furia, NRC Region I, Senior Health Physicist Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP Mr. R. Maiers, DEP/BRP MIs. T. Lewis, DEP/BRP Mr. D. J. Allard, DEP/BRP Mr. W. Wendland, ANI Mr. S. Mainieri, INPO 4,v". t Susquehanna Steam.'l Electric Station ]Units1 &2 Radioactive

'Effluent Release Report 2005 Annual RADIOACTIVE EFFLUENT RELEASE REPORT REPORT PERIOD: 01/01/05 -12/31/05 Prepared by: Health Physicist Reviewed by: All /2-e Rayrfiond E. Doebler Chemistry Support Supervisor Approved by: ruce E. Rhoads Manager -Plant Chemistry L PPL Susquehanna, LLC 769 Salem Blvd.Berwick, Pennsylvania 18603 TABLE OF CONTENTS SECTION PAGE 1. Introduction, Summary and Supplemental Information 1-1 2. Effluent and Waste Disposal Data 2-1 3. Meteorological Data and Dispersion Estimates 3-1 4. Dose Measurements and Assessments 4-1 5. Changes to the Offsite Dose Calculation Manual (ODCM), 5-1 Technical Requirements Manual (TRM)and the Solid Radioactive Waste Process Control Program 6. Miscellaneous Technical Requirements Manual (TRM), FSAR and 6-1 40CFR190 Reporting 7. Corrections to Doses Reported in Previous Radioactive Effluent 7-1 Release Reports 8. Effluent from Systems Classified as Insignificant Effluent Pathways 8-1 Appendix A ODCM/TRM LIST OF TABLES i F IJI Table 1-1 Table 2-1 Table 2-2 Table 2-3 Table 2-4 Table 2-5 Table 2-6 Table 2-7 Table 2-8 Table 2-9 Table 2-10 Table 2-11 Table 2-12 Table 2-13 Table 2-14 Table 2-15 Table 2-16 Table 2-17 Table 2-18 PAGE Technical Requirement Limits 1-10 Airborne Effluent -Summation of All Releases 2-4 Airborne Effluent -Radionuclides Released 2-5 Waterborne Effluent -Summation of All Releases 2-8 Waterborne Effluent -Radionuclides Released 2-9 Estimated Total Errors Associated with 2-12 Effluents Measurements Waste Disposition 2-16 Liquid Radwaste Filter Media -Class A HIC (Dewatered) 2-17 Non-Processed DAW -Class A Steel Liner (Non-Processed) 2-18 RWCU Filter Media -Class A HIC (Dewatered) 2-19 CFS Backwash Media -Class A HIC (Pyrolysis) 2-20 Condensate Demineralizer/Radwaste Demineralizer 21 Class A HIC (Pyrolysis)

Contaminated Waste Oil -Class A 2-22 (Fuel Blending for Co-Generation)

Liquid Radwaste Filter Media -Class A HIC (Pyrolysis) 2-23 Mixed Waste -Class A Strong Tight Container (Compacted) 2-24 Processed DAW -Class A 2-25 Strong Tight Container (Compacted)

Sump Sludge -Class A 2-26 HIC (Pyrolysis)

Condensate Demineralizer/Radwaste Demineralizer 27 Class B HIC (Pyrolysis)

Sump Sludge -Class B 2-28 HIC (Pyrolysis)

LIST OF TABLES (cont.)PAG E Table :2-19 Condensate Demineralizer/Radwaste Demineralizer-Class C HIC (Pyrolysis) 2-29 Table :3-1 Meteorological Data Recovery for 2005 Table 3-2 Joint Frequency Distribution of Wind Speed and Direction 1 Om versus Delta Temperature 60-1 Om for the Period of January 1, 2005 through December 31, 2005 3-4 3-5 Table 3-3 Table 3-4 Table 3-5 Table 3-6 Table 3-7 Table .2-8 Joint Frequency Distribution of Wind Speed and Direction 60m versus Delta Temperature 60-1 Om for the Period of January 1, 2005 through December 31, 2005 2005 Annual Relative Concentrations No Decay, Undepleted X/Q (sec/mi 3)2005 Annual Relative Concentrations 2.26-Day Decay, Undepleted X/Q (sec/m 3)2005 Annual Relative Concentrations 8-Day Decay, Depleted X/Q (sec/M 3)2005 Annual Relative Deposition (D/Q meters 2)2005 Atmospheric Dispersion Estimates for RETDAS Input at Selected Locations 3-13 3-21 3-22 3-23 3-24 3-25 4-2 4-4 Table 4-1 Site-Specific Parameters Used for RETDAS Calculations (Danville Receiver) for 2005 Table 4-2 Summary of Maximum Individual Doses to Members of the Public Data Period: 1/1/05 to 12/31/05 Table 4-3 Table 4-4 Calculated Collective Doses to Members of the 4-5 Public Within the Riverlands/Energy Information Center Complex Data Period: 1/1/05 to 12/31/05 Summary of Maximum Individual Doses from Airborne Effluent 4-6 Table 8-1 Annual Release from Systems Classified as Insignificant Effluent Pathways 8-3 LIST OF FIGURES Figure Figure Figure 1-1 1-2 2-1 Figure 2-2 Figure .3-1 Figure :3-2 Figure :3-3 Airborne Effluent Release Points Waterborne Effluent Pathway Susquehanna River Monthly Average Flow Rates Data Period: 2005 Monthly Liquid Radwaste Discharge Totals 2005 Annual Wind Rose 1OM Level -Primary Tower 2005 Annual Wind Rose 60M Level -Primary Tower Pasquil Stability Class Prevalences Data Period: 2005 Airborne-Dose Calculation Locations PAGE 1-6 1-7 2-10 2-11 3-27 3-28 I i I p i I 3-29 Figure 4-1 4-7 SECTION 1 INTRODUCTION,

SUMMARY

AND SUPPLEMENTAL INFORMATION 1-1 INTRODUCTION The submittal of the 2005 Radioactive Effluent Release Report is in accordance with PPL Susquehanna, LLC Tech Spec. 5.6.3. The enclosed information is consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP). The 2005 Radioactive Effluent Release Report is in conformance with 10CFR50.36a and 10CFR50, Appendix I, Section IV.B.1.PPL Susquehanna, LLC is located in Salem Township, Luzerne County, Pennsylvania.

It is on the west bank of the Susquehanna River, 8 km northeast of Berwick. The Station consists of two boiling water reactor generating units, each with about 1,200 MW net electrical capacity.

The reactor and generating units were supplied by General Electric, while the Bechtel Corporation served as architect-engineer and constructor.

Construction of the Station began in the early 1970s. Fuel load began in Unit 1 in July of 1982. Initial criticality was achieved in the Unit 1 reactor on September 10, 1982.The reactor reached 100% power for the first time on February 4,1983. Commercial operation of Unit 1 was declared on June 8, 1983. Initial criticality of Unit 2 occurred on May 8,1984. Unit 2 was declared commercial on February 12, 1985.Airborne effluents are released from the Station via five rooftop vents on the reactor building (see Figure 1 -1). Continuous sampling for particulates and iodines is K performed at each vent as well as continuous monitoring for noble gases. A program of periodic sampling and analysis for tritium and noble gases along with periodic analysis of particulate and iodine samples is conducted as specified in the plant Technical Requirements.

All waterborne effluents are released in batch mode and are sampled and analyzed prior to release. Waterborne effluents from the site are released into the cooling tower blowdown line for dilution prior to release to the Susquehanna River (see Figure 1-2). Blowdown line flow rates are at least 5,000 gpm during periods of liquid radwaste release. The diluted effluent is introduced to the river by way of a perforated diffuser pipe placed on the river bed. The diffuser serves to rapidly and uniformly mix the station discharge with the main flow of the river.This report presents a summary of the quantities of radioactive materials which were released from the Station during the period from January 1, 2005 to December 31, 2005. In addition, this report serves as a medium for notifying the US Nuclear Regulatory Commiiission staff of changes to the ODCM, PCP and documentation of any exceptions to the effluent monitoring program which must be reported per Technical Requirements.

Airborne and waterborne radioactive effluent releases to the environment during the report period were sampled and analyzed in accordance with the Technical Requirements.

All radioactive effluent releases were within the concentration and release limits specified in the Technical Requirements.

Calculations and terms utilized in this report are those outlined in the ODCM.1-2 Section 1 contains supplemental information pertaining to effluents from the Susquehanna plant. Included are regulatory limits (Table 1-1), sampling and analysis methods, characterization of the number and duration of batch and abnormal releases and a brief summary of the applicable year's effluents.

Section 2 contains effluent and waste disposal data for the report period. Table 2-1 contains a summation of all airborne releases, grouped into the radionuclide categories of gases, particulates, iodines, and tritium. Average release rates are presented and compared to the applicable limits. Table 2-2 presents the activity totals of specific radionuclides in airborne effluents.

Waterborne effluents are summarized in Table 2-3. Average diluted concentrations are presented and compared to the applicable limits. Table 2-4 presents the release quantities of specific radionuclides in waterborne effluents over the report period.Figures 2-1 and 2-2 present the Susquehanna River Monthly Average Flow Rates for 2005 and the Monthly Liquid Radwaste Discharge Totals for 2005, respectively.

Table 2-5 contains estimates of the errors associated with the measurements involved in quantifying effluents.

Sampling errors, counting errors, and errors associated with determining effluent flow rates and volumes all contribute to the total error of effluent measurements.

Error estimates are presented for each category of radionuclide detected in airborne and waterborne effluents and solid wastes during the report period.Tables 2-7 through 2-19 present a characterization of the solid radioactive waste shipped offsite during the report period. An estimate of major nuclide composition is presented for each waste type. Also included are the volumes and curie contents associated with each type of solid waste. The number of waste shipments from the site transported directly for burial or disposal are listed in Table 2-6.Section 3 presents meteorological data for 2005, including data recovery, joint frequency distribution of wind speed and direction, stability class distribution, and atmospheric dispersion estimates for selected locations.

Section 4 of this report contains an assessment of the calculated doses attributed to the reported radiological effluents for the calendar year. The Radioactive Effluent Tracking and Dose Assessment Software (RETDAS) computer code was used for calculation of doses from waterborne effluents.

Site-specific parameters used in the calculations for the Danville receiver are shown in Table 4-1. The RETDAS code was also used for calculation of doses from airborne effluents.

The calculated doses and direct radiation estimates can be used to estimate the doses to maximally exposed members of the public. Table 4-2 summarizes maximum calculated doses to members of the public from airborne and waterborne effluents.

Table 4-3 presents calculated collective doses to members of the public within the Riverlands/Energy Information Center Complex.Table 4-4 summarizes the calculated doses for residences and other occupied areas within the site boundary and the nearest dairy.1-3 Section 5 of this report documents changes to the Offsite Dose Calculation Manual, Technical Requirements Manual and the Solid Radioactive Waste Process Control Program.Section 6 presents a listing of cases (if any) in which airborne or waterborne effluent monitoring instrumentation was declared inoperable and was not restored to operability within ihe time period specified in Technical Requirements 3.11.1.4, 3.11.1.5 and 3.11.2.6 Action Statements.

In addition, this section presents issues (if any) with the collection of milk or fresh leafy vegetables per Technical Requirement 3.11.4.1 and changes due to the land use census per Technical Requirement 3.11.4.2.Section 7 contains corrections (if any) to doses reported in previous Radioactive Effluent Release Reports.Section 8 contains information on effluent and offsite dose from the systems classified as insignificant effluent pathways.1-4

SUMMARY

Liquid and gaseous effluent releases for 2005 were similar to those of previous years.During 2005 there were ninety-six (96) liquid batch releases resulting in a total release volume of one million four hundred seventy thousand (1,470,000) gallons. The total number of liquid batch releases and total volume released in 2005 was higher than the corresponding values for 2004 (79 releases resulting in 917,500 gallons released in 2004). The predominant radionuclide released in liquid effluents during 2005 was tritium. Approximately seventy-four (74) curies of tritium were released in liquid effluents in 2005, compared to sixty-two (62) curies released in 2004. When compared with all radionuclides released in liquid effluents in 2005, tritium was the main contributor to the resultant offsite dose. Consistent with previous years, the offsite dose from liquid releases in 2005 was less than one percent (1 %) of the annual limits for both organ and whole body dose.Gaseous effluents for 2005 were also comparable to those of previous years. Similar to liquid effluents in 2005, the predominant radionuclide released in gaseous effluents was tritium. When compared with all radionuclides released in gaseous effluents in 2005, tritium was the main contributor to the resultant offsite dose. Approximately eighty-six (86) curies of tritium were released in gaseous effluents in 2005. The resultant maximum offsite organ dose due to gaseous effluents from Unit-1 for 2005 was 4.74E-01 mrem, which is 3.2 percent (3.2%) of the per unit annual limit of fifteen (15) mrem.The resultant maximum offsite organ dose due to gaseous effluents from Unit-2 for 2005 was 3.36E-01 mrem, which is 2.2 percent (2.2%) of the per unit annual limit of fifteen (15) mrem. The main source of the tritium in liquid and gaseous effluents is from control rod blades currently in each reactor's core.1-5 FIGURE 1-1 AIRBORNE EFFLUENT RELEASE POINTS--I- REACTOR REACTOR 4 aWLOfNG BUILDING EXHAusT EXHAUST.LA/160,770 CFM 157.350 CFM AT 60 F- I0 0 F AT 6O 0 F-110F 302.059 CFM 17.500 CFM :227.034 CFM AT 100 0 F-120 0 F AT 120 0 F Al IDOOF-120OF OUTSIDE AIR INTAKE \ I_REACTOR BUILDING UNIT It TURBINE TURBINE EXHAUST STACKS BUILDING BUILDING EXHAUSTPLENUM EXHAUST EXHAUST VENT VENT 9 RATOR BUILDING -kS#3-6-5--

L 7'- _ _ , _ _ __'_-1-6 FIGURE 1-2 WATERBORNE EFFLUENT PATHWAYl FROM EVAPOR STEAM CONDENSA1E RETURN TANK FROM PHA SEPARATOR I(DECAIT'_

FROM RHR SYSTEMl (SUPPRESSION PO TRANSFERS)

[ RADWASTE BUIL3G RAINS i4" REACTOR WELL SEAL LEAK DRAIN 1 44 REACTOR BUILDING DRAINS l< DRYWELL DRAINS [*F -TURBINE BUILDING DRAINS 4+ ~1RADWASTE BUILDING DRAINS LIQUID EFFLUENT RELEASE FLOWPATH I (M.1B1, M-182, M-163 AND M.164)ml. I.IQUID RADWASTE RECYCLE LIQUIDI DAT COLLECTION AND SURGW TANKS S R TANKS OT-302A THRU F r++ i OT-304A THRU DEE SLIQUID LIQUID X LQIl _ _ RDAS~TE ._ RADWASTE RADWASE rFILTERS ' _DEMINERALIZER SAPL OT-0ANTMUK LIQUID RADWASTE0 O I RA COLLECTION TANK PUMPS__ __OP-301A, B FvC 3= SAMPLE TANK PUMPS OP-522A, t Iul n e Il IS CODNATE STORAGE TANKS OT-SZ2A & Bl .RC U -CHEMIA EO. + <CEIA EO A tDCl SU.Bl~ LOWDOWNS ] CHEMICAL DRAIN TANK CH EMICAL WASTE TANK OT-314 _I CHEMICAL WASTE TANK PUMPS OP-326A, B i(Z2) CO N DiNEAilRESIN F_ EGN AK NEUTRALIZING TANKS IT-130A, B 2T-130A, B I CH EMICAL WASTE.FNUTRA LIZING TANK PUMPS'ON DRAINS I L 3r--------7 l RA~iASTE ll Ol~tLLAt E EVAPORATORS SAMPLE TANK OE32,B(I)

I I OT-321 l.,3 1 1 EVAPORATOR LlCONCENTRATE STORAGE TANK l @ DS ILT OT-32 l X SAMPLE TANK X l lPUMPSl @ lOP-327A, B CDNDENSATE STORAGE TANKE DISCHARGE PUMP OP-328lI EL DECONTAMINATION l(DETERGENTS) lDOO N SK CLEANING DRAINS REGULATED SHOP DRAINS LAUNDRY DRAINS (3)l ANLAUNDRY DRAIN LAUNR RI ANR DRAINlTANKS _ FITR I IrlSAMPLE TANKSllOT-3111LA, B LAUNDRY ORAINL0-13IA OT-312 l**TANK PUMPS I LAUNDRY DRAIN O-1BA, B SAMPLE TANK PUMPS J -~, (I) RADWASTE EVAPORATORS ARE NO" USED (2) COND DEMIN RESINS CURRENTLY NOT REGENERATED (3) CONTAMINATED CLOTHING CURRENTLY NOT LAUNDERED ONSITE 7 3 0 SUSQUEHANNA RIVER 1-7 SUPPLEMENTAL INFORMATION

1. Regulatory Limits Technical Requirements 3.11.1 and 3.11.2 outline requirements for release of radioactive liquid and gaseous effluents, respectively.

Concentration of radioactive materials released in liquid effluents and resulting dose are limited in unrestricted areas. Dose and dose rate due to radioactive materials released in gaseous effluents are limited in areas at or beyond the site boundary.

Technical Requirement limits are listed in Table 1-1.2. Maximum Permissible Concentrations in Waterborne Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas is limited to 10 times the concentrations specified in 10 CFR Part 20 Appendix B Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration is limited to 2.OE-04 pCi/ml total activity (TRO 3.11.1.1).

3. Average Energy of Fission and Activation Gas The Calculation of Noble Gas Effluent Average Energies E-Bar Beta and Gamma was not performed due to the fact that no noble gases were measured in station vent air samples above detection limits during 2005.4. Moasurements and Approximations of Total RadioactivitV Analyses of specific radionuclides in effluent samples are used to evaluate the radioactive composition and concentration of effluents.
5. Methods of Quantifying Effluents a. Fission and Activation Gases: Gas samples are routinely collected monthly and analyzed with a high resolution (HPGE) detector system which incorporates a data reduction program to determine radionuclide composition in terms of specific activity.

Data from the continuous vent monitors are used to determine the average concentration of noble gases. The high resolution (HPGE) isotopic scan is used to convert the continuous vent monitor activity to actual activity based on the determined nuclide mixture. The vent and sample flow rates are continuously monitored and the average flow rates for each vent are used to calculate the total activity released in a given time period. When the continuous monitors are out of service, manual grab 1-8 samples are taken from each vent once each eight hours (once each four hours for the standby gas treatment vent).b. lodines: Iodine is continuously collected on charcoal or silver zeolite cartridges via an isokinetic sampling assembly in each vent. Filters are normally exchanged once per week and analyzed on a high resolution (HPGE) system. The daily average flow rates for the vents and sample pumps are averaged for the duration of the sampling period and a ratio of vent flow rate to sample flow rate is determined.

The ratio is used to determine the total activity of each isotope released during the time period in question.

When the continuous samplers are out of service, iodine is continuously collected from alternate sampling ports available on the sample lines or directly from the affected rooftop vent(s).c. Particulates:

Particulates are continuously collected via an isokinetic sampling assembly in each vent. Filters are normally exchanged once per week and analyzed on a high resolution (HPGE) system. Flow rate corrections are performed as for iodines. When the continuous samplers are out of service, particulates are continuously collected from alternate sampling ports available on the sample lines or directly from the affected rooftop vent(s).d. Tritium: Airborne tritium is collected monthly via bubbler sampler. The sample is collected for one hour at a flow rate of approximately 1000 cc/min.Tritium activity in the bubbler sample is determined by liquid scintillation counting.

The liquid sample tritium concentration is then converted to air concentration by volume proportion.

e. Waterborne Effluents:

Each tank of liquid radwaste is sampled and analyzed for principal gamma emitters prior to release. Each sample tank is recirculated for a sufficient amount of time prior to sampling to ensure that a representative sample is obtained.

Samples are analyzed on a high resolution (HPGE) system and release permits are generated based on the values obtained from the isotopic analysis and the most recent values for tritium, gross alpha, iron-55, and strontium-89 and -90. An aliquot based on release volume is saved and added to monthly and quarterly composite containers.

The monthly tritium analysis is done in-house.

A monthly composite is s6nt to a vendor laboratory for gross alpha analysis.

A quarterly composite is sent to a vendor laboratory for iron-55, strontium-89 and-90 analyses.The concentration of each radionuclide in each batch is multiplied by the volume of the batch to determine the total quantity of each nuclide released in each batch. The isotopic totals for each batch are summed to determine the total source term for the report period.1-9 TABLE 1-1 TECHNICAL REQUIREMENT LIMITS A. NOBLE GASES: 1. 500 mrem/year

-TOTAL BODY3000 mrem/year

-SKIN-dose rate limit at and beyond the site boundary (TRO 3.11.2.1.1)

2. 5 mrad -AIR GAMMA10 mrad -AIR BETA-quarterly air dose limits per reactor unit at and beyond the site, boundary (TRO 3.11 .2.2a)3. 10 mrad -AIR GAMMA<20 mrad -AIR BETA-annual air dose limits per reactor unit at and beyond the site boundary (TRO 3.11.2.2.b)

B.. AIRBORNE I-131, 1-133, TRITIUM, PARTICULATES WITH HALF-LIVES

> 8 DAYS: 1. <1500 mrem/year-ORGAN (inhalation pathways only)-dose rate limit at and beyond the site boundary (TRO 3.11.2.1.Il.A)

2. 7.5 mrem -ORGAN-quarterly dose limit per reactor unit at and beyond the site boundary (TRO 3.11 .2.3.a)3. 15 mrem -ORGAN-annual dose limit per reactor unit at and beyond the site boundary (TRO 3.11.2.3.b) 1-10 C. LIQUID EFFLUENTS:
1. <1.5 mrem -TOTAL BODY<5.0 mrem -ORGAN-quarterly dose limits per unit (TRO 3.11.1.2.a)
2. <3.0 mrem -TOTAL BODY<10.0 mrem -ORGAN-annual dose limits per unit (TRO 3.11.1.2.b)

D. AIRBORNE EFFLUENT:

BASES FOR PERCENT OF APPLICABLE LIMIT VALUES IN TABLE 2-1 Fission and Activation Gases Derived release rate limits based on the Technical Requirement (TRO 3.11.2.11..A and B) limits of 500 mrem/yr to the total body and 3000 mrem/yr to the skin were calculated from the expected mix of noble gas radionuclides presented in Attachment A of ODCM-QA-003, Effluent Monilor Setpoints.

The lower limit of 1.00E+06 pCi/min (1.67E+04 pCi/sec) based on total body dose rate is used.Iodine-1 31 A derived release rate limit for 1-131 based on the Technical Requirement (TRO 3.11.2.1.1l.A) limit of 1500 mrem/yr from 1-131,1-133, tritium and particulates with half-lives greater than 8 days was calculated based on the ratio of the expected annual release quantities of 1-131 and 1-133 provided in Attachment E of ODCM-QA-004, Airborne Effluent Dose Calculations.

The limit is 1.04E+02 pCi/min 1-131 (1.73E+00 pCi/sec).Particulates A derived release rate limit for particulate activity other than iodines based on the Technical Requirement (TRO 3.11.2.1.1l.A) limit of 1500 mrem/yr from I-131,1-133, tritium and particulates with half-lives greater than 8 days was calculated (PPL calculation EC-ENVR-1 041) based on the expected annual release quanities of particulate radionuclides provided in Attachment E of ODCM-QA-004, Airborne Effluent Dose Calculations.

The limit is 3.02E+03 pCi/min (5.03E+01 pCi/sec).1-11 Tritium A derived release rate was calculated based on the 10 CFR 20, Appendix B, Table 2, Column 1, Effluent Concentration Limit for tritium (1.OE-07 pCi/cc) to unrestricted areas. A relative concentration of 4.1 E-05 sec/m 3 was assumed (PPL calculation EC-ENVR-1040).

The limit is 1.46E+05 pCi/min (2.44E+03 pCi/sec).Radionuclide Fractional Summation The sum of the percents of applicable limits for particulates, iodine and tritium must be less than 100%.E. WATERBORNE EFFLUENT:

BASES FOR PERCENT OF APPLICABLE LIMIT VALUES IN TABLE 2-3 Fission and Activation Products Concentrations of fission and activation products in liquid effluent from radwaste effluent are determined for each batch prior to release. Each isotope concentration is compared to ten times the 1 OCFR20 Appendix B, Table 2, Column 2 Effluent Concentration Values (TRO 3.11.1.1).

Tritium Liquid effluent quarterly tritium concentrations are compared to ten times the 10 CFR 20 Appendix B, Table 2, Column 2, Effluent Concentration value cf 1.OE-03 pCi/ml to unrestricted areas.Dissolved and Entrained Gases Liquid effluent concentrations for dissolved and entrained gases are compared to the limiting value for total noble gas activity of 2.OE-04 pCi/ml (TRO 3.11.1.1).

Radionuclide Fractional Summation The sum of the percents of applicable limits for fission and activation products, tritium and dissolved and entrained gases must be less than 100%.1-12 SECTION 2 EFFLUENT AND WASTE DISPOSAL DATA 2-1 Airborne Effluents Summaries of the radionuclide total curie activities and average release rates are included in Tables 2-1 and 2-2. If a radionuclide was not detected, zero activity was used for that isotope in dose calculations.

A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required Lower Limits of Detection (LLD) as specified in the Technical Requirement (TRO) Table 3.11.2.1-1, Radioactive Gaseous Effluent Sampling and Analysis Program. In all cases, the measurement laboratory LLDs were less than the levels required by Technical Requirements.

The following are typical measurement laboratory LLDs.Typical LLDs Radionuclide LLD (pCVcc)Kr-87 4.6 E-08 Kr-88 5.3 E-08 Xe-1 33 5.4 E-08 Xe-1 33m 1.3 E-07 Xe-135 1.5 E-08 Xe-1 35m 5.OE-08 Xe-138 1.2 E-07 Mn-54 2.9 E-13 Fe-59 2.8 E-13 Co-58 1.8 E-13 Co-60 3.8 E-13 Zn-65 4.4 E-13 Mo-99 3.3 E-12 Cs-134 2.4 E-13 Cs-137 2.1 E-14 Ce-141 1.5 E-14 Ce-144 7.0 E-14 1-131 4.4 E-14 Sr-89 2.0 E-15 Sr-90 3.0 E-16 H-3 1.2 E-08 Gross Alpha 5.0 E-16 Batch Releases 1. Number of Batch Releases:

0 2. Total Time Period for Batch Release: NA 3. Maximum Time Period for a Batch Release: NA 4. Average Time Period for a Batch Release: NA 5. Minimum Time Period for a Batch Release: NA 2-2 Abnormal Releases 1. Number of Releases 1*2. Total Activity Released NA*Historically, monitoring of NRC I/E Bulletin 80-10 applicable systems at the Station did not include analysis for tritium. Peer facilities were benchmarked in September 2004 regarding tritium analysis of 80-10 systems. The majority of benchmarked facilities analyze for tritium in 80-10 systems. Based on the benchmarking feedback and additional evaluation by the Chemistry group, tritium analysis was added to the auxiliary steam system 80-10 monitoring program. In October 2004 the auxiliary steam system was identified as contaminated with low levels of tritium (-1 E-5 uCi/cc). During 2005, approximately 20% of the samples from the auxiliary steam system identified tritium in excess of analysis detection limits. Conservative assumptions were used in support of the calculation of total radioactive effluent from operation of the auxiliary steam system during .2005. The radioactive effluent due to auxiliary steam system operation in 200)5 is a small fraction (<0.001 %) of the total releases due to station operation in 2005.Additional details on this release are outlined in Section 8.2-3 TABLE 2-1 AIRBORNE EFFLUENT -SUMMATION OF ALL RELEASES First Second Third Fourth Unit Quarter I Quarter Quarter Quarter A. Fission and Activation Gas Total Release Ci 0 0 0 0 Average Release Rate for Period pCi/sec 0 0 0 0 Percent of Applicable Limit (1.67E+04

% 0 0 0 0 ,uCi/sec)B. lodines Total 1-131 J Ci 0 9.71E-06 0 l 0 Average Release Rate for Period jpCi/sec 0 1.23E-06 0 0 Percent of Applicable Limit (1.73E+00

% 0 7.11 E-05 0 0 pCi/sec)C. Particulate Particulate wilh Half-Life

>8 Days Ci I 4.26E-04 I 9.95E-06 I 1.48E-05 I 3.32E-04 Average Release Rate for Period wCi/sec I 5.48E-05 I 1.27E-06 I 1.86E-06 I 4.18E-0!5 Percent of Applicable Limit (5.03E+01

% 1.10E-04 2.53E-06 3.73E-06 8.36E-0!,_Ci/sec) I Gross Alpha Radioactivity Ci 0 0 0 0 D. Tritium Total Release liCi 4.36E+01 1.63E+01 1.61 E+01 l 1.01E+01 Average Release Rate for Period _pCi/sec 5.61 E+00 2.07E+00 2.02E+00 1.27E+00lPercent of Applicable Limit (2.44E+03

% 2.30E-01 8.50E-02 8.29E-02 5.20E-02 pCisec)E. Radlonuclide Fractional Summation SumofPerceitofApplicableLimit'

-0.23 0.09 0.08 0.05 100% )_ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _2-4 TABLE 2-2 AIRBORNE EFFLUENT -RADIONUCLIDES RELEASED I Releases in Continuous Mode First Second _ Third Fourth Nuclides Released Unit Quarter Quarter Quarter Qu 3rter A. Fission and Activation Gases Ar-41 Ci 0 0 0 0 Kr-85 Ci 0 0 0 0 Kr-85m Ci 0 0 0 0 Kr-87 Ci 0 0 0 0 Kr-88 Ci 0 0 0 0 Kr-89 Ci 0 0 0 0 Xe-133 Ci 0 0 0 0 Xe-133m Ci 0 0 0 0 Xe-135 Ci 0 0 0 0 Xe-135rn Ci 0 0 0 0 Xe-137 Ci 0 0 0 0 Xe-138 Ci 0 0 0 0 Total for Period Ci 0 0 0 0 B. lodines 1-131 Ci 0 9.71 E-06 0 0 1-133 Ci 0 1.28E-05 0 0 1-135 Ci 0 0 0 _ 0 Total for Period Ci 0 2.25E-05 0 0 C. Particulate Cr-51 Ci 1.68E-04 0 0 5.41 E-05 Mn-54 Ci 1.44E-04 0 0 8.94E-05 Fe-59 Ci 1.69E-05 0 0 0 Co-57 Ci 0 0 0 3.11 E-06 Co-58 Ci 1.93E-05 0 0 5.02E-06 Co-60 Ci 6.30E-05 9.95E-06 0 1.81 E-04 Zn-65 Ci 0 0 0 0 Sr-89 Ci 0 0 0 0 Sr-90 Ci 0 0 0 0 Cs-134 Ci 0 0 0 0 Cs-137 Ci 0 0 0 0 Ce-141 Ci 0 0 0 0 Ce-144 Ci 0 0 1.48E-05 0 Nb-95 Ci 6.43E-06 0 0 0 Ba-La-140 Ci 8.73E-06 0 0 0 Total for Period Ci 4.26E-04 9.95E-06 1.48E-05 3.32E-04 2-5 Waterborne Effluents Summaries of the radionuclide total curie activities, average diluted concentrations, and percent of applicable Technical Requirement limits are included in Tables 2-3 and 2-4.Batch Releases*

Otr. I Qtr. 2 Qtr. 3 Qtr. 4 Annual 1. Number of Batch Releases 22 34 23 17 96 2. Total Time Period for a Batch Release 3.23E+03 6.90E+03 5.22E+03 2.75E+03 1.81 E+04 3. Maimum Time Period for a Batch Release 2.96E+02 3.01 E+02 3.03E+02 3.05E+02 3.05E+02 4. Average Time Period for a Batch Release 1.47E+02 2.03E+02 2.27E+02 1.62E+02 1.89E+02 5. Minimum Time Period for a Batch Release 2.50E+01 2.90E+01 3.OOE+00 2.70E+01 3.OOE+00 6. Average Cooling Tower Blowdown 7.37E+03 9.38E+03 8.31 E+03 7.62E+03 8.45E+03 Flow Rate During Periods of Release 7. Susquehanna River Flow Rate 1.21 E+07 9.51 E+06 8.61 E+05 9.52E+06 7.98E+06*Units of time and flow are expressed in minutes and gallons per minute (gpm), respectively.

If a radionuclide was not detected, zero activity was used for that isotope in dose calculations.

A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required Lower limits of Detection (LLD) as specified in the Technical Requirement 3.11.1.1 -1, Radioactive Liquid Waste Sampling and Analysis Program. In all cases, the measurement laboratory LLDs were less than the levels required by Technical Requirements.

The following are typical measurement laboratory LLDs.Radionuclide LLD (ui/ml)Mn-54 4.5 E-08 Fe-59 5.0 E-08 Co-58 2.4 E-08 Co-60 5.4 E-08 Zn-65 4.9 E-08 Mo-99 1.7 E-07 1-131

  • 2.0 E-08 Cs-1 34 2.2 E-08 Cs-1 37 2.6 E-08 Ce-1 41 3.2 E-08 Ce-144 1.3 E-07 Sr-89 4.0 E-08 Sr-90 4.0 E-09 Fe-55 1.0 E-06 H-3 3.6 E-06 Gross Alpha 3.0 E-08 2-6 Abnormal Releases 1. Number of releases 0 0 0 0 2. Volume Released N/A N/A N/A N/A 3. Total Activity Released N/A N/A N/A N/A 2-7 TABLE 2-3 WATERBORNE EFFLUENT -SUMMATION OF ALL RELEASES I _, .* ._ .First n. .!Mfsr Second r. .nrtar Third M IMrf'Mr Fourth tnl nrtfr A CE~Ic~,n~

~nnA A#.*i;%yo3,^n Dr^Asv^*,.I llnit L. Ig l -..- ". .u.. ..u .0 ....a 1. Total Release (excluding:

Tritium, Ent.Gases, Alpha) Ci 1.33E-03 7.66E-04 5.71 E-05 1.37E-04 2. Average Diluted Concentration During Period pCi/ml 1.47E-08 3.13E-09 3.48E-10 1.73E-09 3. Sum of Average Diluted CW/L, Ratio Durinq Feriod Unitless 2.35E-04 3.83E-05 9.16E-06 4.17E-05 4. Percent of Applicable Limit (Ratio < 1.0) I_%_ _ 0.02 0.004 0.001 0.004 B. Tritium 1. Total Release Ci 1.40E+01 l 2.97E+01 2.03E+01 9.96E+00 l2. Average Diluted Concentration I During Period pCi/mI 1.56E-04 1.21 E-04 1.24E-04 1.25E-04 3. Percent of Applicable Limit (1.OE-2 pCi/ml) % 1.56 1.21 1.24 1.25 C. Dissolved and Entrained Gases 1. Total Release Ci 4.99E-05 9.78E-05 8.73E-05 2.65E-05 2. Average Diluted Concentration pCi/ml 5.54E-10 4.OOE-10 5.32E-10 3.33E-10 During Period 3. Percent of Applicable Limit (2.OE-4 pCi/ml) _ 2.77E-04 2.OOE-04 2.66E-04 1.67E-04 D. Radionuclide Fractional Summationl1. Sum of Percent of Applicable Limit During Period for A, B and C (Limit = 100%) % 1.58 1.21 1.24 1.25 E. Gross Alpha Radioactivity 1 1. Total Re ease F. Volume of Water Released (Prior to Dilution)G. Volume of Dilution Water, Used During Period of Release H. Volume of Dilution Water Used Over Entire Period Ci 0 0 0 Ii ° Il Gallons I 2.55E+05 I 5.55E+05 I 4.39E+05 2 2.21 E+0:5 Liters 9.67E+05 2.1 OE+06 1.66E+06 l 8.38E+05lGallons l 2.35E+07 6.42E+07 4.31E+07 17 Liters 8.91 E+07 2.43E+08 1.63E+08T 7.86E+0L7E l Gallons l 9.54E+08 l 1.23E+09 l 1.17E+09 I81E+08lLiters 3.61 E+09 4.66E+09 4.43E+09 l.E+9 l2-8 TABLE 2-4 WATERBORNE EFFLUENT -RADIONUCLIDES RELEASED=___ _ lReleases In Batch Mode Nuclides Unit First Second Third l Fourth Released Quarter Quarter Quarter I Quarter A. Fission and Activation Products F-1 t3 Ci 0 0 0 _Na-24 Ci 0 0 0 )Cr-51 Ci 5.09E-04 3.23E-04 0 1.08E-05 Mn-54 Ci 1.42E-04 1.12E-04 1.25E-05 2.89E-05 Fe-!5 Ci 0 0 0 0 Co-58 Ci 3.44E-05 1.79E-05 0 1.02E-06 Fe-59 Ci 4.63E-06 0 0 0 Co-l60 Ci 5.68E-04 1.94E-04 4.27E-05 9.63E-05 Zn-65 Ci 7.03E-05 1.16E-04 1.89E-06 (I As-76 Ci 0 0 0 _Rb-136 Ci 0 0 0 C0 Sr-89 Ci 0 0 0 Sr-90 Ci 0 0 0 C Sr-92 Ci 0 0 0 1-13:3 Ci 0 2.45E-07 0 C0 Sb-- 24 Ci 0 3.32E-06 0 C0 Total for Period Ci 1.33E-03 7.66E-04 5.71 E-05 1.37E-04.B. Tritium Total for Period Ci 1.40E+01 2.97E+01 2.03E+01 9.96E+OC0 C. Dissolved and Entrained Gases Ar-41 Ci 0 0 0 C0 Kr-85 Ci0 0 0 C, Kr-85m Ci 0 0 0 C Kr-87 Ci 0 0 0 C Kr-88 Ci 0 0 0 C Xe-131 m Ci 0 0 0 C0 Xe-133m Ci 0 0 0 C0 Xe-1 33 Ci 3.03E-05 5.22E-05 2.05E-05 1.61 E-05 Xe-135m Ci 0 0 0 C)Xe-1 35 Ci_ 1 .95E-05 4.57E-05 6.68E-05 1.04E-05 Total for Period C, 4.99E-05 9.78E-05 8.73E-05 2.65E-0'5 2-9 Figure 2-1 Susquehanna River Monthly Average Flow Rates Data Period: 2005 25.0 E a)0)0 0 O-0)C: a.0 CD 20.0 15.0 10.0 5.0 0.0 A.& -6 'S e 0 -.- 2005 2-10 Figure 2-2 Monthly Liquid Radwaste Discharge Totals 19 El 0-0 0 0)I--.-2005 2-11 TABLE 2-5 ESTIMATED TOTAL ERRORS ASSOCIATED WITH EFFLUENTS MEASUREMENTS ESTIMATED MEASUREMENT TOTAL ERROR 1. Airborne Effluents a. Fission and Activation Gases 15.9%b. 1-131 13.3%c. Particulates (inc. Gross Alpha) 15.8%d. Tritium 13.6%2. Waterborne Effluents a. Fission and Activation Products 5.0%b Tritium 3.3%c. Dissolved and Entrained Gases 8.4%d. Gross Alpha Activity 6.0%e. Volume of Waste Released 5.0%(Prior to Dilution)f. Volume of Dilution Water Used During Period 15.0%ESTIMATED MAXIMUM MEASUREMENT ERROR 3. Solid Wastes a. Liquid Radwaste Filter Media -++/-5%Class A HIC (Dewatered)

b. Non-Processed DAW -+/-25%Class A Steel Liner (Non-Processed)
c. RWCU Filter Media -Class A HIC (Dewatered)

+/-25%d. CFS Backwash Media -Class A HIC (Pyrolysis)

+/-25%e. Condensate Demineralizer/Radwaste Demineralizer

-+/-25%Class A HIC (Pyrolysis)

f. Contaminated Waste Oil -Class A +/-25%(Fuel Blending for Co-Generation)
g. Liquid Radwaste Filter Media -Class A HIC (Pyrolysis)

+/-25%h. Mixed Waste -Class A Strong Tight Container

+/-25%(Compacted)

i. Processed DAW -Class A Strong Tight Container

+/-25%(Compacted) 2-12 ESTIMATED MAXIMUM MEASUREMENT ERROR MEASUREMENT

3. solid Wastes (cont.)j. Sump Sludge -Class A HIC (Pyrolysis))

+/-25%k. Condensate Demineralizer/Radwaste Demineralizer

-+/-25%Class B HIC (Pyrolysis)

I. Sump Sludge -Class B HIC (Pyrolysis)

+/-25%m. Condensate Demineralizer/Radwaste Demineralizer-

+/-25%Class C HIC (Pyrolysis) 2-13 SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE WASTE REPORT RADIOACTIVE EFFLUENT RELEASE REPORT SOLID RADIOACTIVE WASTE DATA PERIOD: JANUARY 1. 2005 -DECEM3ER 31. 2005 PREPARED BY: APPROVED BY: MICHAEL C. MICCA HEALTH PHYSICIST i FORAY T~HCK RADIOLOGICAL OPERATIONS SUPERVISOR 2-14 REPORT NOTES 1. All activities reported in Milli-Curies (mCi) unless otherwise noted.2. Reported activities, as indicated with the (<) sign, are comprised in whole or pair of MDL values.3. Estimated maximum measurement error is +/-25%.2-15 TABLE 2-6 WASTE DISPOSITION Data Period: January 1, 2005 -December 31, 2005 A. SOLID WASTE SHIPPED OFF-SITE FOR BURIAL OR DISPOSAL Number of Shipments Mode of Transportation Destination 4 Truck Barnwell, SC B. IRRADIATED FUEL SHIPMENTS Number of Shipments Mode of Transportation Destination NONE NOTE: The number of shipments listed in A include only the shipments from PPL Susquehanna, LLC to a disposal site. It does not include shipments made to or from volume reduction vendors.2-16 Table 2-7 Annual Waste Release Summary Report____________________________________

Year: 2005 Class: A Source: Liqu Container:

HIC Prozess: Dewa'Nuclides BA-131 C-14 CE-144 CO-57 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NB-95 NI -59 NI-63 PU-238 PU-239 PU-241 RE-182 SB-124 SB-125 SR-89 SR-90 TC-99 ZN-65 ZR-95 Volume Reduction id Radwaste Filter Media (High Integrity Container) tered Vendor: No Activity (mCi)______________

1.060E+01 1.807E+00 3.588E+02 4.580E+00 3.714E+03 3.185E+04 1.732E+04 3.262E+01 2.149E+05 5.958E+03 9.340E+01< 9.040E-06 4.810E+04 5.719E+02 1. 106E+00 2.300E+02 8.369E-01 7.573E-02 3.133E+00 2.650E+01 4.165E+02 2.460E+01 1.290E+00 3. 817E+00< 2.920E-05 3.110E+03 3.352E+02% of Total 0.00______

0.00 %0.00 %0.11 %0.00 %1.14 %9.74 %5.30 %0.01 %65.70 %1.82 %0.03 %0.00 %14.71 %0.17 %0.00 %0.07 %0.00 %0.00 %0.00 %0.01 %0.13 %0.01 %0.00 %0.00 %0.00 %0.95 %0.10 %Total hctivity (Ci)Container Volume 327.069 264.800 ft3 100.00 %7.498 m3 2-17 Table 2-8 Annual Waste Release Summary Report____________________________________

Year: Class: Soirce: Container:

Process: 2005 A Volume Reduction Vendor: No Non-Processed DAW Steel Liner Non-Processed Nuclides C-14 CE-144 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NB-95 NI-63 PU-238 SB-124 Q~' SB-125 TC-99 ZN-65 ZR-95 Activity (mCi)______________

< 4.300E-05 1.440E+00 9.390E+00 5.460E+02 8.430E+00 8.680E+00 1.35OE+04 8.660E+00 5.380E-01 3.260E-05 3.140E+02 6.900E+00 2.590E+01 6.520E-03 7.340E-01 2.620E+00< 6.350E-05 4.330E+00 3.540E+O0% of Total 0.00______

0.00 %0.01 %0.07 %3.78 %0.06 %0.06 %93.48 %0.06 %0.00 %0.00 %2.17 %0.05 %0.18 %0.00 %0.01 %0.02 %0.00 %0.03 %0.02 %Total Activity (Ci)ContairLer Volume 14.441 170.200 ft3 100.00 %4.820 m3 2-18 Table 2-9 Annual Waste Release Summary Report____________________________________

Year: CLass: Source: Container:

Process: 2005 A Volume Reduction Vendor: No RWCU Filter Media HIC (High Integrity Container)

Dewatered Nuclides C-14 CO-57 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NB-95 NI-59 NI-63 SB-124 SR-89 SR-90 TC-99 ZN-65 ZR-95______ .____________

Total Activity (Ci)Container Volume Activity (mCi)______________

< 6.710E-05 8.170E+01 2.050E+04 6.570E+04 4.620E+03 1.440E+02 4.220E+05 1.750E+03 2.980E+02< 1.580E-04 4.840E+04 3.420E+03 2.980E+01 1.300E+03 1.980E+02 7.170E+02 9.200E+O0< 2.800E-04 3.040E+04 1.970E+03_______________

601.538 132.400 ft3% of Total 0.00______

0.00 %0.01 %3.41 %10.92 %0.77 %0.02 %70.15 %0.29 %0.05 %0.00 %8.05 %0.57 %0.00 %0.22 %0.03 %0.12 %0.00 %0.00 %5.05 %0.33 %____________

100.00 %3.749 m3 2-19 Table 2-10 Annual Waste Release Summary Report____________________________________

Year: Class: Source: Container:

Prozess: 2005 A Volume Reduction Vendor: Yes CFS Backwash Media HIC (High Integrity Container)

Pyrolysis Nuclid-s C-14 CE-144 CM-244 C0-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 I-129 MN-54 NB-95 NI-59 NI-63 LV PU-241 SB-124 SR-90 TC-99 ZN-65 ZR-95 Total Activity (Ci)Container Volume Activity (mCi)______________

6.196E+00 5.843E+01 8.018E-03 1.155E+02 2.118E+04 2.227E+01 5.866E+01 9.207E+04 6.442E+01 1.280E+02 2.802E-02 1.192E+04 1.941E+01 9.850E-01 1.473E+02 4.360E-01 7.760E+00 5.318E-01 3.304E-01 2.166E+02 3.616E+01_______________

126.050 77.700 ft3% of Total 0.00______

0.00%0.05 %0.00 %0.09 %16.80 %0.02 %0.05 %73.04 %0.05 %0.10 %0.00 %9.46 %0.02 %0.00 %0.12 %0.00 %0.01 %0.00 %0.00 %0.17 %0.03 %____________

100.00 %2.200 m3 2-20 Table 2-11 Annual Waste Release Summary Report____________________________________

Year: 2005 Class: A Volume Reduction Vendor: Yes Source: Condensate Demineralizer

/ Radwaste Demineralizer Container:

HIC (High Integrity Container)

Process: Pyrolysis Nuclides C-14 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 H-3 I-129 I-131 MN-54 NB-95 NI-63 SB-124 SR-89 TC-99 ZN-65 ZR-95 Total Activity (Ci)Container Volume Activity (mCi)______________

5.689E+03 6.248E+01 1.076E+03 1.095E+02 3.578E+00 2.256E+03 3.507E+01 9.148E+02 3.011E-01 8.136E-01 5.942E+02 1.542E+01 1.336E+01 5.293E+00 6.060E-01 4.270E-01 7.805E+01 8.353E+00 10.863 292.930 ft3% of Total__________

52.36 %0.58 %9.91 %1.01 %0.03 %20.77 %0.32 %8.42 %0.00 %0.01 %5.47 %0.14 %0.12 %0.05 %0.01 %0.00 %0.72 %0.08 %100.00 %8.295 m3 2-21 Table 2-12 Annual Waste Release Summary Report____________________________________

Year: 2005 Class: A Volume Reduction Vendor: Yes Source: Contaminated Waste Oil Container:

None Process: Fuel Blending for Co-Generation Nuclides C-14 CE-144 CO-60 CS-137 FE-55 H-3 I-129 MN-54 NI-63 PU-238 TC-99 Total Activity (Ci)Container Volume Activity (mCi)< 1.200E-08 3.540E-04 1.340E-01 2.130E-03 3.310E+00 4.160E+00< 9.OOOE-09 2.310E-02 6.340E-03 1.600E-06< 1.800E-08 0.008 0.000 ft3% of Total 0.00 %0.00 %1.75 %0.03 %43.35 %54.48 %0.00 %0.30 %0.08 %0.00 %0.00 %____________

100.00 %0.000 m3 2-22 Table 2-13 Annual Waste Release Summary Report____________________________________

Year: 2005 CLass: A Source: Liquid Container:

HIC (Hi Process: Pyrolys Nuclides C-14 CE-144 CO-58 C0-60 CR-51 CS-137 FE-55 FE-59 H-3 1-129 MN-54 NB-95 NI-59 NI-63 PU-238 K.) PU-239 PU-241 SR-90 TC-99 ZN-65 Total }ctivity (Ci)Container Volume Volume Reduction Radwaste Filter Media gh Integrity Container) is Vendor: Yes Activity (mCi)______________

9.350E-01 3.180E+01 1.864E+01 1.536E+04 2.144E+00 1.674E+01 9.689E+04 2.782E+00 4.799E+01 2.430E-02 8.595E+03 4.442E-01 5.734E-01 1.187E+02 1.208E-01*1.102E-02 4.633E-01 1.950E+00 7.850E-02 1.357E+02_______________

121.224 14.910 ft3% of Total 0.00______

0.00 %0.03 %0.02 %12.67 %0.00 %0.01 %79.93 %0.00 %0.04 %0.00 %7.09 %0.00 %0.00 %0.10 %0.00 %0.00 %0.00 %0.00 %0.00 %0.11 %____________

100.00 %0.422 m3 2-23 Table 2-14 Annual Waste Release Summary Report Year: Class: Source: Container:

Pro:ess: 2005 A Volume Reduction Vendor: Yes Mixed Waste Strong Tight Container Compacted Nuclides CE-144 CO-58 CO-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-95 NI-63 PU-238 SB-124 SB-125 ZN-65 ZR-95 Total Activity (Ci)Container Volume Activity (mCi)______________

1.700E-04 1.420E-04 1.160E-01 1.800E-06 2.OOOE-03 2.600E+00 2.630E-05 3.950E-02 6.400E-06 6.030E-03 4.150E-07 6.850E-06 5.080E-04 4.580E-04 4.OOOE-05 0.003 11.700 ft3% of Total 0.01______

0.01 %0.01 %4.20 %0.00 %0.07 %94.04 %0.00 %1.43 %0.00 %0.22 %0.00 %0.00 %0.02 %0.02 %0.00 %____________

100.00 %0.331 m3 2-24 Table 2-15 Annual Waste Release Summary Report____________________________________

Year: Class: Source: Container:

Process: 2005 A Volume Reduction Vendor: Yes Processed DAW Strong Tight Container Compacted Nuclides Activity (mCi)% of Total AG- 110 AM-241 C-14 CD-109 CE-139 CE-141 CE-144 CM-242 CM-244 CO-57 C0-58 CO-60 CR-51 CS-134 CS-137 FE-55 FE-59 H-3 HG-203 I-129 I-131 MN-54 NB-95 NI-59 NI-63 PU-238 PU-239 PU-241 SB-124 SB-125 SN-113 SR-85 SR-89 SR-90 TC-99 Y-88 ZN-65 ZR-95 Total Activity (Ci)Container Volume 9.960E-02 1.750E-02 2.872E+01 5. 010E-03 8.790E-08 6. 000E-21 2.384E+00 1.290E-05 9.696E-04 1.030E-05 3.582E+00 1.254E+03 7.076E-01 8.810E-05 8.102E+00 1. 899E+04 1.520E+00 6.952E+00 5.240E-14 4.310E-03 4.950E-49 7. 118E+02 1.384E+00 4.018E-01 3. 742E+01 8.510E-03 2.840E-04 1.209E-02 1. 850E-01 1.790E+00 2.530E-08 1.650E-12 1.770E-43 4. 219E-01 3.123E-01 2. 050E-08 6. 610E+00 8.200E-01 21.059 9895.000 ft3 0.00 %0.00 %0.14 %0.00 %0.00 %0.00 %0.01 %0.00 %0.00 %0.00 %0.02 %5.96 %0.00 %0.00 %0.04 %90.18 %0.01 %0.03 %0.00 %0.00 %0.00 %3.38 %0.01 %0.00 %0.18 %0.00 %0.00 %0.00 %0.00 %0.01 %0.00 %0.00 %0.00 %0.00 %0.00 %0.00 %0.03 %0.00 %100.00 %280.200 m3 2-25 Table 2-16 Annual Waste Release Summary Report____________________________________

Year: Class: Source: Container:

Process: 2005 A Volume Reduction Vendor: Yes Sump Sludge HIC (High Integrity Container)

Pyrolysis Nuclid-s C-14 CO-60 CS-137 FE-55 H-3 I-129 MN-54 NI-63 TC-99 Total Activity (Ci)Container Volume Activity (mCi)3.110E+02 9.480E+02 6.500E+00 1.550E+04 2.320E+00 3.560E-03 1.280E+02 4.090E+01 2.610E-02 16.937 5.990 ft3% of Total 1.84 %5.60 %0.04 %91.52 %0.01 %0.00 %0.76 %0.24 %0.00 %100.00 %0.170 m3 2-26 Table 2-17 Annual Waste Release Summary Report____________________________________

Year: Class: Source: Container:

Process: 2005 B Volume Reduction Vendor: Yes Condensate Demineralizer

/ Radwaste Demineralizer HIC (High Integrity Container)

Pyrolysis Nuclides________C-14 CO-58 CO-60 CS-137 FE-55 H-3 I-129 LA-140 MN-54 NI-63 TC-99 ZN-65 Activity (mCi)______________

5.820E+02 6.890E+00 1.240E+02 3.650E-01 2.310E+02 4.070E+01 1.420E-02 1.100E-06 5.890E+01 1.360E+00 1.850E-02 1.470E+01% of Total 54.91 %0.65 %11.70 %0.03 %21.79 %3.84 %0.00 %0.00 %5.56 %0.13 %0.00 %1.39 %Total Akctivity (Ci)Container Volume 1.060 15.920 ft3 100.00 %0.451 m3 2-27 Table 2-18 Annual Waste Release Summary Report____________________________________

Year: 2005 Class: B Volume Reduction Vendor: Yes Source: Sump Sludge Container:

HIC (High Integrity Container)

Process: Pyrolysis Nuclides C-14 CO-60 CS-137 FE-55 H-3 I-129 MN-54 NI-63 TC-99 Total Activity (Ci)Container Volume Activity (mCi)______________

3.730E+02 1.140E+03 7.330E+00 l.900E+04 5.120E+00 7.800E-03 1.500E+02 4.920E+0l 5.740E-02_______________

20.725 18.490 ft3% of Total__________

1.80 %5.50 %0.04 %91.68 %0.02 %0.00 %0.72 %0.24 %0.00 %____________

100.00 %0.524 m3 2-28 Table 2-19 Annual Waste Release Summary Report____________________________________

Year: Class: Source: Container:

Pro=ess: 2005 C Volume Reduction Vendor: Yes Condensate Demineralizer

/ Radwaste Demineralizer HIC (High Integrity Container)

Pyrolysis Nuclides C-14 CO-58 CO-60 CS-137 FE-55 H-3 I-129 LA-140 MN-54 NI-63 TC-99 ZN-65______..____________

Total Activity (Ci)Container Volume Activity (mCi)5.380E+02 5.440E+00 1.130E+02 3.370E-01 2.110E+02 3.740E+01 1.310E-02 1.350E-09 5.250E+01 1.260E+00 1.710E-02 1.300E+01_______________

0.972 16.970 ft3% of Total 55.35 %0.56 %11.63 %0.03 %21.71 %3.85 %0.00 %0.00 %5.40 %0.13 %0.00 %1.34 %____________

100.00 %0.481 m3 2-29 SECTION 3 METEOROLOGICAL DATA AND DISPERSION ESTIMATES 3-1 METEOROLOGY AND DISPERSION DATA Meteorological data have been collected at the PPL Susquehanna, LLC site since the early 1970s. At the present time, the meteorological system is based on a 300-foot high tower located approximately 1,000 feet to the southeast of the plant.Wind sensors are mounted at the 1Oim and 60m elevations on this tower. Verlical temperature differential is measured with redundant sensor pairs between the 1lOm and 60m levels. Sigma theta (the standard deviation of horizontal wind direction) is calculated from wind direction at both levels. Dew point and ambient temperature sensors are present at the 10m level. Precipitation is measured at ground level.A back-up meteorological tower was erected in 1982. It is a 10m tower providing alternate measurements of wind speed, wind direction, and sigma theta. A 10m supplemental downriver meteorological tower is also available.

This tower measures wind speed, wind direction, sigma theta, temperature and dew point.Meteorological data are transmitted to the plant Control Room, Technical Support Center, Emergency Operations Facility for emergency response availability, and A13SG Consulting, Inc. ABSG Consulting, Inc., located in Rockville, Maryland, provides meteorological consulting services to PPL Susquehanna, LLC.Dispersion modeling for effluents from normal operation is done using the MIDAS system XDCALC program, a straight-line Gaussian plume model designed to estimate average relative concentration.

The model was developed in accordance with Regulatory Guide 1.1 11. For periods when the wind speed is calm, the actual wind direction that last occurred is used.XDCALC and the XQINTR program that interpolates X/Q values to exact locations both use terrain correction factors to account for the temporal and spatial variations in the airflow in the region. A straight-line trajectory model assumes that a constant mean wind transports and diffuses effluents in the direction of airflow at th9 release point within-the entire region of interest.

The terrain correction factors were taken from FSAR Table 2.3-128.Regulatory Guide 1.23 (Safety Guide 23) requires at least 90% data recovery for m teorological instrumentation.

The primary tower 60 meter wind direction instrument did not meet the 90% data recovery requirement for 2005. Outlined below is a summary of the problem experienced with the primary tower 60 meter wind direction instrument.

3-2 Cn July 22, 2005 the primary tower 60 meter wind rose diagram for June 2005 was reviewed and a deviation in the normal wind direction was identified.

The 60 rmeter wind direction instrument was found damaged and was promptly replaced and a calibration check was performed.

The PPL Susquehanna, LLC Emergency Plan offsite dose assessment model uses "ground level release" methodology as opposed to "elevated release" methodology.

The ground level release methodology uses the 10 meter elevation data. The primary tower 60 meter wind direction sensor is not used to support dose assessment for normal or emergency condition gaseous releases.

The use of possibly inaccurate wind direction data from the 60 meter elevation to support offsite dose assessment during June and most of July 2005 would not have occurred due to the ground level release methodology.

3-3 TABLE 3-1 METEOROLOGICAL DATA RECOVERY FOR 2005 PERCENT VALID PARAMETER DATA RECOVERY Wind Speed lOm -Primary i 99.1 Wind Speed 60m -Primary 99.1 Wind Speed lOm -Backup(2) 100.0 Wind Speed IOm -Downriver(3) 100.0 Wind Direction 1 Om -Primary 99.1 Wind Direction 60m -Primary 82.7 Wind Direction lOm -Backup 100.0 Wind Direction lOm -Downriver 100.0 Temperature lOm -Primary 99.0 Dew Point I Om -Primary 98.7 Delta Temperature 60m -Primary 99.0 Sigma Theta lOm -Primary 99.1 Sigma Theta 60m -Primary 82.7 Sigma Theta lOm- Backup 100.0 Sigma Theta IOm -Downriver 100.0 Precipitation

-Primary 95.9 Composite Parameters Wind Speed and Direction lOm, 99.0 Delta Temperature 60-lOm Wind Speed and Direction 60m, 82.6 Delta Temperature 60- 1 Om"Primary" meteorological tower"Backup" meteorological tower (3) "Downriver" meteorological tower 3-4 TABLE 3-2 Joint Frequency Distribution of Wind Speed and Direction 10m Versus Delta Temperature 60-lOm for the Period of January 1, 2005 through December 31, 2005 Period of Record =Elevation:

IOM Stability Class A_ind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Total Period Direction:

IOM Lapse: DT60-1O Delta Temperature Extremely Unstable Wind Speed (mph)1-4 0 4 14 14 18 27 20 13 19 11 14 9 3 I 1 2 170 4 -8 17 38 39 19 20 13 31 41 63 114 161 28 8 8 12 12 624 8 -13 34 27 6 0 0 0 1 5 7 25 92 50 16 4 3 5 275 13 -19 5 0 0 0 0 0 0 I 1 0 4 I 0 0 0 1 13 19 -25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 56 69 59 33 38 40 52 60 90 150 271 88 27 13 16 20 1082 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 2 0 88 1082 8759 3-5 TABLE 3-2 (continued)

Period of Record =Elevation:

IOM Stability Class B Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Total Period Direction:

IOM Lapse: DT60-10 Delta Temperature Moderately Unstable Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total 1-4 4-8 8-1 8 0 14 8 8 2 4 13 3 11 2 Wind Speed (mph).13 13 -19 1 4 3 9 1 1 0 o 0 o o o o 4 4 10 3 3 0 0 1 62 8 10 7 16 16 10 4 1 7 4 122 0 2 2 4 17 12 13 8 7 16 95 0 0 0 0 2 1 0 0 I 1 9 9 -25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 16 24 17 6 16 13 12 16 19 23 38 23 17 10 16 22 288 yjj11)Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 2 0 88 288 8759 3-6 TABLE 3-2 (continued)

Hours at Each Wind Speed and Direction Period of Record =01/01/05 1:00 12/31/05 23:00 Total Period Elevation:

IOM Stability Class C Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Direction:

IOM Lapse: DT60-10 Delta Temperature Slightly Unstable 1-4 1 4 5 3 13 13 4 4 5 6 3 0 I 0 0 1 63 4 -8 9 10 6 5 5 3 5 2 7 14 32 10 5 4 2 7 126 8 Wind Speed (mph)-13 13 -19 1 17 1 2 0 0 0 o o 1 0 0 0 3 1 2 4 18 22 15 4 13 18 120 0 0 0 0 2 3 0 0 3 I 10 9 -25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 28 16 11 8 19 16 12 7 14 24 55 35 21 8 18 27 319 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 2 0 88 319 8759 3-7 TABLE 3-2 (continued)

Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Period of Record =Total Period Elevation:

IOM Stability Class D Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Direction:

IOM Lapse: DT60-10 Delta Temperature Neutral 1-4 35 62 53 58 69 40 46 29 50 43 31 16 5 8 8 14 567 4 -8 142 114 79 24 16 22 61 61 81 144 123 66 56 53 37 74 1153 Wind Speed (mph)8 -13 13 -19 19. 25 84 5 0 30 0 0 1 0 0 2 0 0 2 0 0 l 0 0 18 3 0 17 8 0 11 4 0 22 1 0 121 17 0 95 29 3 68 12 0 74 7 0 143 25 0 104 14 1 793 125 4> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 266 206 133 84 87 63 128 115 146 210 292 209 141 142 213 207 2642 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 2 0 88 2642 8759 3-8 TABLE 3-2 (continued)

Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Period of Record =Total Period Elevation:

IOM Stability Class E Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Direction:

IOM Lapse: DT60-10 Delta Temperature Slightly Stable 1- 4 58 134 218 235 180 116 143 113 122 113 42 19 12 7 5 14 1531 4 -8 77 147 102 17 13 20 22 26 38 99 77 37 25 18 29 42 789 8 I Wind Speed (mph)-13 13-19 1 27 0 14 0 5 0 2 0 5 2 3 0 2 3 9 5 11 5 17 0 34 3 9 0 1 0 6 1 6 0 11 0 62 19 9 -25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 162 295 326 254 200 139 170 153 176 229 156 65 38 32 40 67 2502 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 2 0 88 2501 8759 3-9 TABLE 3-2 (continued)

Period of Record =Elevation:

IOM Stability Class F'%ind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Total Period Direction:

IOM Lapse: DT60-10 Delta Temperature Moderately Stable I -4 8 40 134 471 189 68 50 25 44 23 18 6 3 1 3 2 1085 Wind Speed (mph 4 -8 8.13 13 -19 2 0 0 3 3 9 0 0 0 I 0 5 3 2 0 0 1 2 31 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I)19 -25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 10 43 137 480 189 68 50 26 44 28 21 8 3 I 4 4 1116 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 2 0 88 1116 8759 3-10 TABLE 3-2 (continued)

Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Period of Record =Total Period Elevation:

1OM Stability Class G Wlind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Direction:

IOM Lapse: DT60-10 Delta Temperature Extremely Stable 1-4 3 4 126 452 66 19 11 13 9 2 1 0 0 0 0 0 706 1 3 6 0 I 0 0 0 2 1 0 0 0 0 0 15 8 Wind Speed (mph)-13 13 -19 1 0 0 0 0 o o 0 0 0 0 o o 0 0 o o 0 0 0 0 9 .25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 5 5 129 458 66 20 11 13 9 4 2 0 0 0 0 0 722 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 2 0 88 721 8759 3-11 TABLE 3-2 (continued)

Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Total Period Period of Record =Elevation:

IOM Direction:

IOM Lapse: DT60-10 Summary of All Stability Classcs Delta Temperature Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total 1-4 106 248 558 1235 548 294 278 201 259 201 112 50 24 18 18 34 4184 4 -8 256 327 240 84 57 61 127 141 196 394 413 153 98 84 88 141 2860 Wind Speed (mph)8-13 13 -19 19-25 166 14 0 82 1 0 13 0 0 4 0 0 8 2 0 4 0 0 24 6 0 34 14 0 33 10 0 72 1 0 282 28 0 188 34 3 113 12 0 96 8 0 172 29 0 154 17 1 1445 176 4> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 543 658 812 1323 615 359 435 390 498 668 835 428 247 206 307 347 8671 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 2 0 88 8669 8759 3-12 TABLE 3-3 Joint Frequency Distribution of Wind Speed and Direction 60m Versus Delta Temperature 60-lOm for the Period of January 1, 2005 through December 31, 2005 Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Period of Record =Total Period Elevation:

60M Stability Class A Direction:

60M Lapse: DT60-10 Delta Temperature Extremely Unstable W1ind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Win 1-4 4-8 8-13 1 3 16 4 18 41 12 33 17 9 17 14 6 9 2 12 9 0 9 20 16 3 19 11 4 20 14 7 43 33 7 42 65 2 10 36 0 0 12 1 0 7 0 6 5 0 4 4 77 253 293 id Speed (mph)13 -19 1 6 17 2 2 0 0 0 2 3 13 30 25 2 0 0 0 102 9 -25 2 0 0 0 0 0 0 0 2 0 1 0 0 0 0 0 5>25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 28 80 64 42 17 21 45 35 43 96 145 73 14 8 11 8 730 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 0 0 1528 730 8759 3-13 TABLE 3-3 (continued)

Period of Record =Elevation:

60M Slability Class B Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Total Period Direction:

60M Lapse: DT60-10 Delta Temperature Moderately Unstable 0 1 3 3 4 7 2 3 3 4 0 0 0 0 I 1 32 4 -8 4 5 15 5 3 2 I 6 I 6 12 2 4 I 3 1 71 Wind Speed (mph)8-13 13 -19 19 -25 3 5 1 9 7 0 4 1 0 1 1 0 2 0 0 1 0 0 5 0 0 3 2 0 2 0 1 7 1 1 8 3 2 8 12 1 6 7 0 9 0 0 9 1 0 7 5 0 84 45 6>25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 13 22 23 10 9 10 8 14 7 19 25 23 17 10 14 14 238 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 0 0 1528 238 8759 3-14 ijW TABLE 3-3 (continued)

Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Period of Record =Total Period Elevation:

60M Stability Class C Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Direction:

60M Lapse: DT60-10 Delta Temperature Slightly Unstable Wind Speed (mph)1 -4 0 4 3 6 3 5 I 3 1 4 2 0 0 0 0 0 32 4 -8 2 6 5 8 0 0 2 1 0 7 10 8 I 0 I 52 8 -13 7 9 3 4 2 3 3 4 1 4 12 12 9 7 11 9 97 13 -19 5 2 0 0 0 0 1 0 2 8 7 24 10 3 4 9 75 19 -25 0 0 0 0 0 0 0 0 0 0 1 2 0 0 0 0 3> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 14 21 11 18 5 8 7 5 4 23 32 46 20 10 16 19 259 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 0 0 1528 259 8759 3-15 TABLE 3-3 (continued)

Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Total Period Period of Record =Elevation:

60M Direction:

60M Lapse: DT60-10 Sftability Class D Delta Temperature Neutral Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total 1 -4 17 27 32 23 17 13 25 14 20 19 16 8 4 I 7 4 247 4 -8 46 84 46 26 22 21 33 27 12 36 68 33 30 20 9 26 539 8 c Wind Speed (mph)-13 13 -19 19 -25 105 31 3 94 36 0 39 1 0 17 1 0 5 2 0 10 2 0 37 7 2 35 16 10 39 7 1 49 33 7 72 38 6 106 164 31 82 69 11 61 54 2 120 67 4.00 42 5 971 570 82 0 for this Table 0 1528 2422 8759>25 0 0 0 0 0 0 0 2 3 2 0 6 0 0 0 0 13 Total 202 241 118 67 46 46 104 104 82 146 200 348 196 138 207 177 2422 Number of Calm Hours for this Table Number of Variable Direction Hours l Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 3-16 TABLE 3-3 (continued)

Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Period of Record =Elevation:

60M Stability Class E Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Total Period Direction:

60M Lapse: DT60-10 Delta Temperature Slightly Stable Wind Speed (mph)1.4 34 58 70 38 32 32 47 41 37 40 35 14 5 3 1 9 496 4-8 73 164 89 41 43 37 40 36 35 51 63 56 30 20 14 9 801 8 -13 36 95 68 12 12 17 15 23 26 51 62 71 29 13 34 30 594 13 -19 9 32 13 0 4 2 3 6 10 22 13 56 0 5 3 3 181 19-25 0 I 0 0 1 I 2 7 5 5 4 I 0 0 0 0 27> 25 0 0 0 0 0 I 0 2 3 3 0 0 0 0 0 0 9 Total 152 350 240 91 92 90 107 115 116 172 177 198 64 41 52 51 2108 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 0 0 1528 2108 8759 3-17 TABLE 3-3 (continued)

P eriod of Record =Elevation:

60M Stability Class F W ind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Total Period Direction:

60M Lapse: DT60-10 Delta Temperature Moderately Stable 1 -4 13 83 72 34 24 30 30 19 24 10 12 5 4 4 4 3 371 4 -8 55 197 39 7 14 11 5 6 10 23 27 5 7 2 7 2 417 Wind Speed (mph)8 -13 13 -19 19 -25 4 0 0 3 0 0 2 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1 0 0 3 0 0 5 1 0 5 0 0 19 1 0 1 0 0 0 0 0 2 0 0 1 0 0 47 2 0>25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 72 283 113 41 38 41 36 26 37 39 44 30 12 6 13 6 837 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 0 0 1528 837 8759 3-18 TABLE 3-3 (continued)

Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Period of Record =Total Period Elevation:

60M Stability Class G N'ind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Direction:

60M Lapse: DT60-10 Delta Temperature Extremely Stable 1 -4 10 46 63 34 21 19 15 12 12 6 3 1 1 1 0 4 248 4 -8 65 174 52 10 2 3 7 6 12 11 15 1 0 0 5 2 365 8 Wind Speed (mph)-13 13 -19 1 2 0 5 0 2 0 0 0 0 0 0 0 0 0 4 5 4 0 0 0 0 22 0 0 0 0 1 0 I 0 0 0 0 2 9 -25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 77 225 117 44 23 22 22 18'24 22 23 7 1 I 5 6 637 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 0 0 1528 637 8759 3-19 TABLE 3-3 (continued)

Hours at Each Wind Speed and Direction 01/01/05 1:00 12/31/05 23:00 Total Period Period of Record =Elevation:

60M Direction:

60M Lapse: DT60-10 Summary of All Stability Classes Delta Temperature Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total 1 -4 75 223 255 147 107 118 129 95 101 90 75 30 14 10 13 21 1503 Wind Speed (mph)4-8 8-13 13-19 19-25 248 173 56 6 648 256 94 1 279 135 17 0 114 48 4 0 93 23 6 1 83 31 4 1 108 77 11 4 101 74 26 17 90 85 22 9 177 153 79 13 237 229 91 14 115 256 283 35 72 139 88 11 43 97 62 2 45 181 75 4 45 151 59 5 2498 2108 977 123> 25 Total 0 558 0 1222 0 686 0 313 0 230 1 238 0 329 4 317 6 313 5 517 0 646 6 725 0 324 0 214 0 318 0 281 22 7231 Number of Calm Hours for this Table Number of Variable Direction Hours for this Table Number of Invalid Hours Number of Valid Hours for this Table Total Hours for the Period 0 0 1528 7231 8759 3-20 TABLE 3-4 2005 ANNUAL RELATIVE CONCENTRATIONS NO DECAY, UNDEPLETED X/Q (sec/m 3)DATFS OFI.ASTX/OACCrTTMTTT.ATTON ARE FROM S 1 1 0 TO 519124fn iC X/Q ACCUMULATION FOR GROUND AVERAGE FOR RELEASE POINT I SEC/M 3 MILES 0.5-1**DIRECTION 5.3213E-06

    • DIRECTION 8.4112E-06
    • DIRECTION 1.9139E-05
    • DIRECTION 5.2805E-05
    • DIRECTION 2.0383E-05
    • DIRECTION 1.0509E-05
    • DIRECTION 1.1462E-05
    • DIRECTION 8.1587E-06
    • DIRECTION 6.3426E-06
    • DIRECTION 7.1282E-06
    • DIRECTION 4.7967E-06
    • DIRECTION 2.7645E-06
    • DIRECTION 1.4631E-06
    • DIRECTION 1.3428E-06
    • DIRECTION 1.8899E-06
    • DIRECTION 2.5092E-06 1-2 FROM N 1.0232E-06 FROM NNE 1.7458E-06 FROM NE 3.5587E-06 FROM ENE 9.5828E-06 FROM E 3.7225E-06 FROM ESE 2.0382E-06 FROM SE 2.2942E-06 FROM SSE 1.5887E-06 FROM S 1.3321E-06 FROM SSW 1.4489E-06 FROM SW 9.7039E-07 FROM WSW 5.4421E-07 FROM W 2.8155E-07 FROM WNW 2.4855E-07 FROM NW 3.5185E-07 FROM NNW 4.7954E-07 2-3 4.2820E-07 7.8901E-07 1.6239E-06 4.6603E-06 1.6539E-06 9.3285E-07
1. 0612E-06 7.0840E-07 6.5714E-07 6.7296E-07 4.6990E-07 2.5851E-07 1.2321E-07 1.0015E-07 1.4168E-07 2.0395E-07 3-4 2.2734E-07 4.2449E-07 9.3222E-07 2.7883E-06 9.3963E-07 5.2607E-07 6.0285E-07
4. 0112E-07 3. 8611E-07 3.8359E-07 2.7342E-07 1.5408E-07 6.8119E-08 5.2571E-08 7.2738E-08 1.0881E-07 4-5 1.4714E-07 2.7543E-07 6.2271E-07 1.8730E-06 6.2915E-07 3.5064E-07 4.0169E-07 2.7159E-07 2.6633E-07 2.5539E-07 1.8493E-07 1.0649E-07 4.5013E-08 3.3633E-08 4.6395E-08 6.8962E-08 5-10 5.5391E-08 1.0324E-07 2.4986E-07 7.4806E-07 2.5632E-07 1.4250E-07
1. 6515E-07 1. 1866E-07 1.2480E-07 1.0685E-07 8.2454E-08 5.1359E-08 1.8748E-08 1.2486E-08 1.6932E-08 2.4353E-08 10-20 1.5479E-08 2.8677E-08 7.7053E-08 2.1999E-07 8.1483E-08 4.0009E-08 4.1821E-08 3.1666E-08 3.5164E-08 2.8142E-08 2.1886E-08 1.6607E-08 5.2061E-09 3.4241E-09 4.5439E-09
6. 1860E-09 20-30 7.5718E-09 1.4209E-08 3.9056E-08 1.0740E-07 4.1468E-08 1.7739E-08 1.5579E-08 1.1429E-08 1.2235E-08 1.0798E-08 7.5028E-09 6.3631E-09 2.1471E-09 1.6302E-09 2.1764E-09 2.9787E-09 30-40 4.7921E-09 9.0740E-09 2.5224E-08 6.9761E-08 2.6885E-08 1.1465E-08 1.0016E-08 7.3333E-09 7.8501E-09 6.8942E-09 4.7981E-09 3.3050E-09 1.3528E-09 1.0132E-09 1.3587E-09 1.8678E-09 40-50 3.4171E-09 6.5130E-09 1.8449E-08 5.1401E-08 1.9631E-08 8.3352E-09 7.2415E-09 5.3054E-09 5.6628E-09 4.9448E-09 3.4397E-09 1.8326E-09 9.5654E-10 7.0690E-10 9.5178E-10 1.3148E-09 3-21 VI TABLE 3-5 2005 ANNUAL RELATIVE CONCENTRATIONS 2.26-DAY DECAY, UNDEPLETED X/Q (sec/m 3)DATES OF LAST X/O ACCUMULATION ARE FROM 5 1 1 1 0 TO 5123124 0 X/Q ACCUMULATION FOR GROUND DECAYED S.AVG SEC/M 3 FOR RELEASE POINT I MILES Ce 0.5-1**DIRECTION 5.3101E-06
    • DIRECTION 8.3912E-06
    • DIRECTION 1.9081E-05
    • DIRECTION 5.2635E-05
    • DIRECTION 2.0304E-05
    • DIRECTION 1.0470E-05
    • DIRECTION 1.1423E-05
    • DIRECTION 8.1324E-06
    • DIRECTION 6.3253E-06
    • DIRECTION 7.1131E-06
    • DIRECTION 4.7885E-06
    • DIRECTION 2.7602E-06
    • DIRECTION 1.4608E-06
    • DIRECTION 1.3409E-06
    • DIRECTION 1.8875E-06
    • DIRECTION 2.5052E-06 1-2 FROM N 1.0169E-06 FROM NNE 1.7334E-06 FROM NE 3.5266E-06 FROM ENE 9.4899E-06 FROM E 3.6790E-06 FROM ESE 2.0153E-06 FROM SE 2.2707E-06 FROM SSE 1.5734E-06 FROM S 1.3212E-06 FROM SSW 1.4396E-06 FROM SW 9.6533E-07 FROM WSW 5.4157E-07 FROM W 2.8013E-07 FROM WNW 2.4746E-07 FROM NW 3.5050E-07 FROM NNW 4.7720E-07 2-3 4.2372E-07 7.7962E-07 1.5996E-06 4.5853E-06 1.6217E-06
9. 1539E-07 1.0430E-06 6.9700E-07 6.4818E-07 6.6571E-07 4.6578E-07 2.5640E-07 1.2216E-07 9.9412E-08 1.4076E-07 2.0227E-07 3-4 2.2397E-07 4.1737E-07
9. 1270E-07 2.7257E-06
9. 1408E-07 5. 1230E-07 5.8840E-07 3.9206E-07 3.7873E-07 3.7778E-07 2.7004E-07 1.5231E-07 6.7298E-08 5.2029E-08 7.2074E-08 1.0755E-07 4-5 1.4431E-07 2.6949E-07 6.0599E-07 1.8192E-06 6.0724E-07 3.3888E-07 3.8932E-07 2.6371E-07 2.5979E-07 2.5042E-07 1.8199E-07 1.0492E-07 4.4311E-08 3.3187E-08 4.5848E-08 6.7932E-08 5-10 5.3597E-08 9.9546E-08 2.3877E-07 7.1265E-07 2.4162E-07 1.3463E-07 1.5673E-07
1. 1295E-07 1.1972E-07 1.0339E-07 8.0263E-08 5.0084E-08 1.8255E-08 1.2209E-08 1.6596E-08 2.3744E-08 10-20 1.4472E-08 2.6652E-08 7.0366E-08 1.9971E-07 7.2409E-08 3.5706E-08 3.7643E-08 2.8675E-08 3.2347E-08 2.6341E-08 2.0730E-08 1.5783E-08 4.9295E-09 3.2726E-09 4.3622E-09 5.8764E-09 20-30 6.7654E-09 1.2576E-08 3.3584E-08
9. 1444E-08 3.4070E-08 1.4678E-08 1.3072E-08 9.6893E-09 1.0647E-08
9. 6714E-09 6.8543E-09 5.8443E-09 1.9590E-09 1.5116E-09 2.0323E-09 2.7342E-09 30-40 4.0939E-09 7.6508E-09 2.0429E-08 5.5721E-08 2.0428E-08 8.7989E-09 7.8365E-09 5.8232E-09 6.4652E-09 5.9106E-09 4.2292E-09 2.9342E-09 1.1895E-09 9.1166E-10 1.2341E-09 1.6573E-09 40-50 2.7899E-09 5.2325E-09 1.4078E-08 3.8531E-08 1.3801E-08 5.9356E-09 5.2843E-09 3.9464E-09 4.4145E-09 4.0585E-09 2.9258E-09 1.5727E-09 8.1037E-10 6.1720E-10 8.4062E-10
1. 1279E-09 3-22 TABLE 3-6 2005 ANNUAL RELATIVE CONCENTRATIONS 8-DAY DECAY, DEPLETED XIQ (se/rM 3)DATES OF LAST X/Q ACCUMULATION ARE FROM 5 1 1 1 0 TO 5123124 0 X/Q ACCUMULATION FOR DECAYED DEPLETION SEC/M 3 C FOR RELEASE POINT 1 MILES 5-10 0.5-1**DIRECTION 4.8614E-06
    • DIRECTION 7.6836E-06
    • DIRECTION 1.7480E-05
    • DIRECTION 4.8226E-05
    • DIRECTION 1.8612E-05
    • DIRECTION 9.5964E-06
    • DIRECTION 1.0467E-05
  • DIRECTION 7.4512E-06
    • DIRECTION 5.7934E-06
    • DIRECTION 6.5121E-06
    • DIRECTION 4.3826E-06
    • DIRECTION 2.5260E-06
    • DIRECTION 1.3369E-06
    • DIRECTION 1.2270E-06
    • DIRECTION 1.7270E-06
    • DIRECTION 2.2927E-06 1-2 FROM N 8.6653E-07 FROM NNE 1.4780E-06 FROM NE 3.0113E-06 FROM ENE 8.1073E-06 FROM E 3.1476E-06 FROM ESE 1.7236E-06 FROM SE 1.9406E-06 FROM SSE 1.3441E-06 FROM S 1.1275E-06 FROM SSW 1.2269E-06 FROM SW 8.2202E-07 FROM WSW 4.6105E-07 FROM W 2.3851E-07 FROM WNW 2.1060E-07 FROM NW 2.9817E-07 FROM NNW 4.0626E-07 2-3 3.4619E-07 6.3764E-07 1.3112E-06 3.7617E-06 1.3337E-06 7.5241E-07 8.5631E-07 5.7180E-07 5.3080E-07 5.4402E-07 3.8009E-07 2.0914E-07 9.9665E-08
8. 1039E-08 1. 1467E-07 1.6499E-07 3-4 1.7604E-07 3.2852E-07 7.2058E-07 2.1544E-06 7.2501E-07 4.0603E-07 4.6559E-07 3.0991E-07 2.9861E-07 2.9700E-07 2.1187E-07 1.1942E-07 5.2788E-08 4.0760E-08
5. 6415E-08 8.4336E-08 4-5 1.1014E-07 2.0603E-07 4.6509E-07 1.3981E-06 4.6881E-07 2.6138E-07 2.9967E-07 2.0272E-07 1.9905E-07 1.9115E-07 1.3856E-07 7.9815E-08 3.3729E-08 2.5218E-08 3.4802E-08 5.1683E-08 3.8479E-08 7.1648E-08 1.7297E-07 5.1740E-07 1.7676E-07 9.8332E-08 1.1410E-07 8.2051E-08 8.6489E-08 7.4227E-08 5.7377E-08 3.5757E-08 1.3047E-08 8.6999E-09 1.1806E-08 10-20 9.5117E-09 1.7594E-08 4.7040E-08 1.3408E-07 4.9365E-08 2.4267E-08 2.5427E-08 1.9285E-08 2.1511E-08 1.73OOE-08 1.3499E-08 1.0253E-08 3.2107E-09 2.1174E-09 2.8134E-09 20-30 4.0522E-09 7.5854E-09 2.0682E-08 5.6719E-08 2.1679E-08 9.2923E-09 8.1921E-09 6.0271E-09 6.5006E-09 5.7840E-09 4.0414E-09 3.4328E-09
1. 1560E-09 8.8178E-10 1.1796E-09 30-40 2.2936E-09 4.3284E-09 1.1898E-08 3.2782E-08 1.2456E-08 5.3264E-09 4.6777E-09 3.4388E-09 3.7200E-09 3.3045E-09 2.3178E-09 1.5999E-09 6.5293E-10 4.9229E-10 6.6201E-10 9.0364E-10 40-50 1.4807E-09
2. 8110E-09 7.8494E-09
2. 1765E-08 8. 1622E-09 3.4778E-09 3.0414E-09 2.2399E-09 2.4236E-09
2. 1474E-09 1.5089E-09 8.060OE-10
4. 1899E-10 3.1239E-10 4.2206E-10 5.7783E-10 1.6954E-08 3.8184E-09 1.6063E-09 3-23 TABLE 3-7 2005 ANNUAL RELATIVE DEPOSITION (D/Q meters 2)DATES OF LAST X/Q ACCUMULATION ARE FROM 5 1 1 1 0 TO 5123124 0 X/Q ACCUMULATION FOR DEPOSITION I/M 2 FOR RELEASE POINT I MILES 0.5-1**DIRECTION 3.1306E-08
    • DIRECTION 3.5731E-08
    • DIRECTION 4.1105E-08
    • DIRECTION 7.1316E-08
    • DIRECTION 3.2142E-08
    • DIRECTION 2.1623E-08
    • DIRECTION 3.1298E-08
    • DIRECTION 2.6666E-08
    • DIRECTION 2.4277E-08
    • DIRECTION 3.9139E-08
    • DIRECTION 4.4084E-08
    • DIRECTION 2.5779E-08
    • DIRECTION 1.2446E-08
    • DIRECTION 1.1539E-08
    • DIRECTION 1.8491E-08
    • DIRECTION 2.1063E-08 1-2 FROM N 4.6128E-09 FROM NNE 5.5364E-09 FROM NE 6.1998E-09 FROM ENE 1.1074E-08 FROM E 4.6952E-09 FROM ESE 3.2686E-09 FROM SE 4.7559E-09 FROM SSE 3.9804E-09 FROM S 3.8921E-09 FROM SSW 5.9865E-09 FROM SW 6.9982E-09 FROM WSW 3.9738E-09 FROM W 1.8681E-09 FROM WNW 1.6650E-09 FROM NW 2.7069E-09 FROM NNW 3.1282E-09 2-3 1. 8918E-09 2.4013E-09 2.6509E-09 4.9314E-09
1. 9129E-09 1.3936E-09 2.0772E-09 1.6956E-09 1.8279E-09 2.6851E-09 3.2925E-09 1.8559E-09 8.0836E-10 6.7086E-10 1.0846E-09 1.3216E-09 3-4 8.9669E-10 1.1421E-09 1.2831E-09 2.4126E-09 9.1339E-10 6.7281E-10 1.0257E-09 8.3726E-10 9.3937E-10 1.3593E-09 1.7036E-09
9. 9358E-10 4.0337E-10 3.2062E-10 5.0454E-10 6.3892E-10 4-5 5-10 5.2992E-10 6.7233E-10 7.6120E-10 1.4253E-09 5.4497E-10 4.0197E-10 6.1573E-10 5.1028E-10 5.8546E-10 8.2272E-10 1.0527E-09 6.3172E-10 2.4584E-10 1.9047E-10 2.9830E-10 3.7425E-10
1. 6794E-10 2. 0949E-10 2.4521E-10
4. 5107E-10 1.7972E-10 1.3329E-10 2.0805E-10 1.8268E-10 2.2660E-10
2. 8705E-10 3.9573E-10
2. 6053E-10 8. 8015E-11 6.1705E-11 9.4702E-11 1.1409E-10 10-20 4. 0177E-11 4.8834E-11 6.0081E-11 1.0279E-10 4.5505E-11 3.0284E-11 4.3297E-1l 4.0076E-11 5.2887E-11 6.3769E-11 8.9400E-11 7.3319E-11 2.1476E-11 1.5242E-11 2.2715E-11 2.5675E-11 20-30 1.4793E-11 1.7980E-11 2.2121E-11
3. 6042E-11 1.6754E-11 9.7800E-12 1.1850E-11 1.0652E-11 1.3567E-11
1. 8198E-11 2.2775E-11 2.1184E-11 6.7289E-12 5.6119E-12 8.3634E-12 9.4531E-12 30-40 7. 8953E-12 9.5965E-12
1. 1807E-11 1.9237E-11 8.9422E-12 5.2199E-12 6.3250E-12 5.6852E-12 7.2410E-12 9.7128E-12 1.2156E-11 9.2741E-12 3.5914E-12 2.9953E-12 4.4639E-12 5.0455E-12 40-50 4.9601E-12 6.0289E-12 7.4174E-12 1.2085E-11 5.6178E-12 3 .2794E-12 3.9736E-12 3.5717E-12 4.5491E-12 6.1020E-12 7 .6366E-12 4.5495E-12 2.2563E-12
1. 8817E-12 2.8043E-12
3. 1697E-12 3-24 TABLE 3-8 2005 ATMOSPHERIC DISPERSION ESTIMATES FOR RETDAS INPUT AT SELECTED LOCATIONS AFFECTED LOCATION MILES X/Q(l) X/Q DEC(2) X/Q DEC+DEP(3)

DEpO(4TION(4)-SECTOR _____ _ DEC__ X_________DEPOITIO I I/SW Maximum (X/Q) Site Boundary 0.61 1.36E-05 1.35E-05 1.22E-05 2.78E-08 9/S Closest (X/Q) Site Boundary 0.38 7.72E-06 7.71 E-06 7.18E-06 4.74E-08 12/ WSWV Maximum (X/Q) Residence 1.3 1.20E-05 1.19E-05 1.03E-05 1.41E-08 7/ SE Maximum (D/Q) Residence 0.5 1.82E-06 1.82E-06 1.66E-06 1.75E-08 12 / WS\V Maximum (D/Q) Garden 1.3 1.20E-05 1.19E-05 1.03E-05 I.41E-08 12 / WSWV Maximum (D/Q) Dairy 1.7 8.22E-06 8.12E-06 6.87E-06 9.17E-09 15 / NW Maximum (D/Q) Meat Producer 0.8 6.30E-06 6.26E-06 5.57E-06 1.5 1E-08 3/NE = Riverlands

/ EIC 0.7 3.03E-06 3.03E-06 2.71E-06 2.55E-08 12 /WSW Tower's Club 0.5 4.19E-05 4.18E-05 3.83E-05 5.63E-08 5/ E -East Gate 0.5 1.61E-06 1.61E-06 1.47E-06 1.34E-08 NEAREST RESIDENCE WITHIN A 5-MILE RADIUS BY SECTOR SECTOR AFFECTED NAME MILES X/Q Xl Q DEC DE+DEp DEPOSITION NUMBER: SECTOR DEC___ ______I N H.Burd 1.3 1.64E-06 1.63E-06 1.40E-06 4.90E-09 2 NNE E.Ashbridge III 1 2.65E-06 2.64E-06 2.3 1E-06 1.20E-08 3 NE W.Tuggle 0.9 2.10E-06 2.09E-06 1.84E-06 1.6'7E-08 It ENE D.Barberi 2.1 3.35E-07 3.32E-07 2.75E-07 2.40E-09:5 E LKozlowski/

W. Witts 1.4 3.13E-07 3.12E-07 2.67E-07 2.091E-09 6 ESE R.Panetta 0.5 1.48E-06 1.48E-06 1.35E-06 1.24E-08 7 SE J.Futoma 0.5 1.82E-06 1.82E-06 1.66E-06 1.75E-08 8 SSE J.Naunczek 0.6 2.04E-06 2.04E-06 1.84E-06 1.6'1E-08 9 S S.Slusser I 1.95E-06 1.94E-06 1.70E-06 9.5'1E-09 10 SSW S.Molnar 0.9 3.79E-06 3.77E-06 3.32E-06 I.3SE-08 I I SW F.Michael 1.5 3.62E-06 3.59E-06 3.06E-06 6.24E-09 12 WSW F.Michael 1.3 1.20E-05 1.19E-05 1.03E-05 1.4 IE-08 13 W F. Hummel 1.2 5.40E-06 5.35E-06 4.64E-06 7.03E-09 14 WNW R.Orlando 0.8 5.66E-06 5.62E-06 5.00E-06 1.O:IE-08 1.; NW H. Long 0.8 6.30E-06 6.26E-06 5.57E-06 1.5 E.E-S8_ NNW G. John 0.6 5.52E-06 5.49E-06 4.97E-06 1.70E-0S NEAREST GARDEN WITHIN A 5-MILE RADIUS BY SECTOR SECTOR AFFECTED NAME MILES X/Q X/Q DEC X/Q DEPOSITION NUMBER SECTOR DEC+DEP DPSTO_ N J.Wojcik 3.2 4.411E-07 4.33E-07 3.45E-07 1.1(OE-09 , NNE R.Chapin 2.3 7.91 E-07 7.83E-07 6.44E-07 3.1L'E-09 NE Yokum 2.7 4.27E-07 4.23E-07 3.42E-07 2.89'E-09.ENE G.Dennis 2.4 2.80E-07 2.78E-07 2.27E-07 2.0C'E-09 f. E W.Daily

  • 1.8 2.11 E-07 2.1 OE-07 1.76E-07 1.39E-09 6 ESE L.Travelpiece 2.5 1.OOE-07 9.96E-08 8.12E-08 6.6 E- 10_ SE F.Scholl 0.6 1.39E-06 1.39E-06 1.26E-06 1.2E.E-08 S SSE M.Zaletko 1.6 4.26E-07 4.24E-07 3.59E-07 2.7' E-09 ( S A. Kadir 1.1 1.68E-06 1.67E-06 1.45E-06 8.0';E-09 10 SSW S.Bodnar 1.2 2.46E-06 2.44E-06 2.1 IE-06 8.1 ';E-09 11_ SW R. Broody 1.9 2.55E-06 2.52E-06 2.11 E-06 4.211E-09 I 2 WSW F.Michael 1.3 1.20E-05 1.19E-05 1.03E-05 1.41 E-08 1 W F.Hummel 1.2 5.40E-06 5.35E-06 4.64E-06 7.03E-09 IL. WNW P.Moskaluk 1.3 2.61E-06 2.58E-06 2.23E-06 4.2(,E-09 If; NW D.Goff 1.8 1.79E-06 1.77E-06 1.49E-06 3.5S E-09 16 NNW P.Culver 4 3.2 1 E-07 3.13E-07 2.44E-07 6.2EE-10 3-25

-TABLE 3-8 (continued)

NEAREST ANIMAL RAISED FOR MEAT CONSUMPTION WITHIN A 5-MILE RAI)IUS BY SECTOR SECTOF' AFFECTED NAME MILES X/Q X/Q DEC X/Q DEPOSITION NUMBERt SECTOR _____ DEC+DEP ___2 NNE R.Chapin 2.3 7.91 E-07 7.83E-07 6.44E-07 3.14E-09 4 ENE G.Dennis 2.4 2.80E-07 2.78E-07 2.27E-07 2.00E-09 5 E W.Daily 1.8 2.11 E-07 2.1 OE-07 1.76E-07 1.39E-09 I_ SSW R. & C. Ryman 3 5.63E-07 5.55E-07 4.44E-07 1.59E-09 10 SSW C.K.Drasher 3.5 3.96E-07 3.89E-07 3.06E-07 1.06E-09 15 NW D. Goff 1.8 1.79E-06 1.77E-06 1.49E-06 3.59E-09 15 NW H. Long 0.8 6.30E-06 6.26E-06 5.57E-06 1.51 E-08 ALL DAIRY LOCATIONS SECTOR AFFECTED NAME MILES X/Q X/Q DEC XD Q DEPOSITION NUMBEE' SECTOR DEC+DEP 5 E W.Bloss 4.5 4.44E-08 4.37E-08 3.33E-08 2.42E-10 5 ESE D.Moyer 2.7 8.65E-08 8.58E-08 6.93E-08 5.64E-10 5 ESE F.Rinehimer 4.2 3.48E-08 3.44E-08 2.63E-08 2.01E-10 1_ SSW R. & C. Ryman 3 5.63E-07 5.55E-07 4.44E-07 1.59E-09 1') SSW R.Ryman 3.1 5.24E-07 5.16E-07 4.12E-07 1.45E-09 1) SSW C.K.Drasher 3.5 3.96E-07 3.89E-07 3.06E-07 1.05E-09 10) SSW K.Davis 14.0 3.26E-08 3.05E-08 2.03E-08 5.61E- I I 12 WSW T. & M. Berger 1.7 8.22E-06 8.12E-06 6.87E-06 9.17E-09 13 W J. Dent 5 4.96E-07 4.76E-07 3.63E-07 4.05E- 10_1 NNW H.Shoemaker 4.2 3.01 E-07 2.93E-07 2.27E-07 5.77E-10 1 X/Q RELATIVE CONCENTRATION (SEC/M 3)2 X/Q DEC DECAYED ANID UNDEPLETED, HALF-LIFE 2.26 DAYS X/Q DEC(SEC/H 3)3 CX/Q DEC+DEP DECAYED AflD DEPLETED, HALF-LIFE 8 DAYS (SEC/N 3)DEPOSITION RELATIVE DEPOSITION RATE (1/H) I 3-26 FIGURE 3-1 2005 ANNUAL WINI) ROSE 10M LEVEL -PRIMARY TOWER WIND ROSE (EI\NDS FROM)N 0.02% PERCENT CALMS (NOT INCLUDED IN PLOT)WIND SPEED LESS THAN 3.5 MPH* WIND SPEED LESS THAN 7.5 MPH 3 WIND SPEED LESS THAN 12.5 MPH WIND SPEED GREATERTHAN 12.5 MPH This wind rose displays the frequency of hourly average wind direction from a given sector. In 2005, the predominant wind direction occurred 15.3% of the time from the ENE sector. The average wind speed was 4.7 mph and the average wind speed for the predominant sector (ENE) was 2.4 mph. The sector with the highest average wind speed was NW (8.6 mph.).3-27 FIGURE 3-2 2005 ANNUAL WIND ROSE 60M LEVEL -PRIMARY TOWER It WIND ROSE (WINDS FROM)N F t 0.00% PERCENT CALMS (NOT INCLUDED IN PLOT)A WIND SPEED LESS THAN 3.5 MPH* WIND SPEED LESS THAN 7.5 MPH o WIND SPEED LESS THAN 12.5 MPH x WIND SPEED GREATERTHAN 12.5 MPH This wind rose displays the frequency of hourly average wind direction from a given sector. In 2OD5, the predominant wind direction occurred 16.9% of the time from the NNE sector. The average wind speed was 7.6 mph and the average wind speed for the predominant sector (NNE) was 6.4 mph. The sector with the highest average wind speed was WSW (11.6 mph.).3-28 FIGURE 3-3 PASQUIL STABILITY CLASS PREVALENCES DATA Period: 2005 Joint Frequency Distributions at 10 Meters Wind Speed and Direction lOM vs. Delta Temperature 60-IOM (Based on 8,671 Valid Hours)G 8.3%A 12.5%-IJ F 12.9%E2 _28.8%B 3.3%\- C 3.7%30.D 30.5%3-29 SECTION 4 DOSE MEASUREMENTS AND ASSESSMENTS 4-1 Radiological Impact on Man Sampling and analysis of airborne and waterborne effluents were performed in accordance with the frequencies, types of analysis, and Lower Limit of Detection (Ll D) outlined in the PPL Susquehanna, LLC Technical Requirements Manual.Radioactive material was detected in some of the airborne and waterborne effluent samples analyzed.

Dose calculations using measured effluent activity levels, meteorological data from the current reporting period and average river flow dilution factors resulted in estimated doses to individuals at levels below 10 CFR 20 and 10 CFR 50, Appendix I limits. Direct radiation resulting from plant operation (reported in the 2005 Annual Radiological Environmental Operating Report)contributed a maximum of 2.81 E-2 mrem (measured at TLD Location 9S2) at the Protected Area Boundary south of the plant. The maximum organ (including thyroid)/total body dose from all airborne effluent is 8.08E-1 mrem (CHILD, THYROID Table 4-4). The maximum organ/total body dose from all liquid effluent is 2.00E-3 mrem (ADULT, GI-LLI Table 4-2). Conservatively adding the maximum organ (including thyroid)/total body dose from liquid and gaseous effluent (even though different age groups) and the maximum total body dose determined from direct radiation bounds the dose that any member of the public receives from station operations.

The result (8.38E-1 mrem) is 3.4% of the 40CFR1 90 limit of 25 mrem to total body/organ (except thyroid) and 1.1% of the 40CFR190 limit of 75 mrem to the thyroid.Doses to a maximally exposed member of the public from waterborne effluents Eire calculated for fish ingestion and shoreline exposure at the plant outfall, and drinking water ingestion at Danville, PA. Site specific parameters used in the calculations for the Danville receiver, specific for actual average blowdown and river level for the entire year are shown in Table 4-1.TABLE 4-1 SITE-SPECIFIC PARAMETERS USED FOR RETDAS CALCULATIONS (DANVILLE RECEIVER)FOR 2005 PARAMETER ENTIRE YEAR Cooling Tower Blowdown (CFS) 18.4 Average Net River Level (ft.) 7.0 Dilution Factor at Danville(')

456.6 Transit time to Danville (hr.)(') 23.0 (')From ODCM-QA-005, Att. E 4-2 Summaries of maximum individual doses resulting from airborne and waterborne radioactive effluent releases from each unit are given in Table 4-2. Meteorological data from Section 3 were used to calculate the dose from airborne effluents.

The Radioactive Effluent Release Report includes an assessment of the radiation dose from radioactive effluents to members of the public within the site boundary.Within the Site Boundary there are several areas frequented by members of the public. There are no significant exposure pathways from waterborne effluents in these areas. Doses from airborne effluent are calculated for members of the public for the following locations:

Riverlands Energy Information Center, the Towers Club, the residence and garden with the maximum X/Q and D/Q value, the dairy and meat producing farm with the maximum D/Q value, and the site boundary with the maximum X/Q value. Summaries of the calculated maximum doses within the site boundary and selected locations resulting from airborne effluents are presented in Tables 4-3 and 4-4. The above referenced locations are shown on Figure 4-1.In the area comprising the Riverlands recreation area, which surrounds the Energy Information Center, three pathways of radiation exposure can be identified:

plume, ground, and inhalation.

There are no significant exposure pathways from waterborne effluents in this area. There are approximately 100,000 visitors to the Ri/erlands/Energy Information Center complex each year. For dose calculations, it is assumed the visitor stays in the area for one hour.Use of the RETDAS code yields calculated doses for the Riverlands area for the report period. These doses are the total doses at the location from gaseous effluents during the report period.4-3 TABLE 4-2

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES TO MEMBERS OF THE PUBLIC DATA PERIOD: 1/1/05 TO 12/31/05 ESTIMATED MAXIMUM LIMIT AGE APPLICABLE DOSE PERCENT (MREM/UNIT EFFLUENT GROUP ORGAN (MREM/IRAD)

LOCATION OF LIMIT MRAD)" 2)DIST AFFECTED (MILES) SECTOR .I Liquid") Child Total Body 8.50E-04 (3) 0.03 3 I Liquid"t)

Adult GI-LLI 1.00E-03 (3) 0.01 10 I Noble Gas N/A Air Dose 0.00E+00 0.5 WSW 0 10 (Gamma-._ _ _MRAD) .1 Noble Gas N/A Air Dose 0.00E+00 0.5 WSW 0 20_ _ (Beta-MRAD)

I Airborne Child Lung 4.74E-01 0.5 WSW 3.2 15 Iodine, Tritium and Particulates

.Liquid"i)

_ Child Total Body 8.50E-04 (3) 0.03 3 2 Liquid") Adult GI-LLI 1.00E-03 (3) 0.01 10 2 Noble Gas N/A Air Dose 0.00E-00 0.5 WSW 0 10 (Gamma-MRAD) ._i 2 Noble Gas N/A Air Dose 0.00E+00 0.5 WSW 0 20 (Beta-MRAD) 2 Airborne Child Thyroid 3.36E-01 0.5 WSW 2.2 15 Iodine, Tritium and Particulates

(')Estimated dose is based on a site total activity release equally divided between Unit 1 and' Unit 2.(2)10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year for airborne and waterborne effluent from each unit.3 bDoses from liquid effluent are estimated from fish ingestion and shoreline exposure at the site outfall and from the drinking water pathway at Danville, PA.4-4 TABLE 4-3 CALCULATED COLLECTIVE DOSES TO MEMBERS OF THE PUBLIC WITHIN THE RIVERLANDS/ENERGY INFORMATION CENTER COMPLEX DATA PERIOD: 1/11/05 TO 12/31/05 COLLECTIVE APPLICABLE DOSE RATE"') DOSE(2 EFFLUENT AGE GROUP ORGAN (MREM/HR) (PERSON-REM)

Noble Gas N/A Total Body O.OOE+00 O .OE+0O)Noble Gas N/A Skin O.OOE+00 O.OOE+00 Iodine, Tritium and Child Thyroid 7.31 E-06 7.31 E-04 ParticL ates I I I (')Estimated dose and dose rate is based on annual site total activity release.(2)Collective dose is based on 100,000 person-hours.

4-5 TABLE 4-4

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FROM AIRBORNE EFFLUENT MAXIMUM MAXIMUM MAXIMUM TOTAL BODY ORGAN THYROID DOSE DOSE DOSE LOCATION PATHWAY (MREM) (MREM) (MREM)1. Maximum site tioundary X/Q Total (All) 2.63E-01 (CHILD) 2.65E-01 (CHILD, THYROID) 2.65E-01 (CHILD)2. Maximum X/Q Residence

+Maximum D/Q Garden Total (All) 2.30E-01 (CHILD) 2.31 E-01 (CHILD, THYROID) 2.31 E-01 (CHILD)3. Maximum D/Q Dairy Total (All) 1.57E-01 (CHILD) 1.58E-01 (CHILD, THYROID) 1.58E-01 (CHILD)4. Maximum D/Q Meat Total (All) 1.22E-01 (CHILD) 1.23E-01 (CHILD, THYROID) 1.23E-01 (CHILD)5. Tower's Club Total (All) 8.04E-01 (CHILD) 8.08E-01 (CHILD, THYROID) 8.08E-01 (CHILD)6. Riverland/EIC Total (All) 6.24E-02 (CHILD) 6.40E-02 (CHILD, THYROID) 6.40E-02 (CHILD)Note: The doses shown above are based on 100% occupancy at the indicated locations.

Note: The doses shown above are based on a composite of all applicable pathways resulting in a total dose to the maximally exposed individual due to airborne effluents from both Unit-1 and Unit-2 operations.

4-6 FIGURE 4-1 AIRBORNE-DOSE CALCULATION LOCATIONS* Indicates airborne-dose calculation location 4-7 SECTION 5 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCMA), TECHNICAL REQUIREMENTS MANUAL (TRM)AND THE SOLID RADIOACTIVE WASTE PROCESS CONTROL PROGRAM 5-1 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL The PPL Susquehanna, LLC ODCM consists of nine (9) individual procedures.

ODCMI-QA-002, ODCM Review and Revision Control, was revised on October 17, 2005. The revision updated a reference from NDAP-QA-0728, SSES Technical Requi ements Program to NDAP-QA-0730, Licensing Document Changes. NDAP-QA-0728 has been deleted and replaced by NDAP-QA-0730.

ODCMI-QA-004, Airborne Effluent Dose Calculations, was revised on July 20, 2005.The revision:

1) clarified the requirements for gaseous effluent exposure pathway dose calculations;
2) clarified the process for performing dose projections for gaseous effluent;
3) added guidance for assignment of a noble gas isotopic mix to the applicable release period when a gaseous effluent noble gas monitor indicates a release has occurred.ODCMvl-QA-005, Waterborne Effluent Dose Calculations, was revised on September 9, 2005. The revision:
1) updated position titles; 2) revised the title of the Annual Effluent and Waste Disposal Report to Radioactive Effluent Release Report; 3) clarified the requirements for liquid effluent exposure pathway dose calculations;
4) clarified the process for performing dose projections from liquid effluent;
5) added applicable procedural Adherence Level classification.

ODCMVI-QA-006, Total Dose Calculations, was revised on August 17, 2005. The revision:

1) updated position titles; 2) added applicable procedural Adherence Level classif ication.ODCIMI-QA-007, Radioactive Waste Treatment Systems, was revised on August 17, 2005. The revision:
1) updated position titles; 2) added applicable procedural Adherence Level classification.

ODCIVI-QA-008, Radiological Environmental Monitoring Program, was revised on February 3 (revision

6) and July 20 (revision 7), 2005. The revisions:
1) updated position titles; 2) added frequency definitions;
3) added monitoring locations for sediment and food product sampling;
4) update Attachment C to: a) add Groundwamer Monitoring; b) add "Ingestion" as an exposure pathway for Milk, Fish and Invertebrates and Food Products; c) add Surface Water monitoring locations LTAW and 6S5; d)clarify TLD control locations; e) correct typographical errors; 5) added guidance for the use of the RETDAS computer program to support offsite dose calculations based on REMP sample results. .ODCIVM-QA-009, Dose Assessment Policy Statements, was revised on November 9, 2005. The revision:
1) updated position titles; 2) revised the title of the Annual Effluent and Waste Disposal Report to Radioactive Effluent Release Report.5-2 CHANGES TO THE TECHNICAL REQUIREMENTS MANUAL Section 3.11 and 3.6.1 of the Unit-1 and Unit-2 Technical Requirements Manual (TRMO)by reference are part of the ODCM. The following limits and requirements are contained in Section 3.11: liquid and gaseous effluent dose limits, liquid and gaseous effluent:

treatment system operability criteria (based on effluent dose), liquid and gaseous effluent radiation monitor operability criteria and the conduct of the Radiological Environmental Monitoring Program. Section 3.6.1 contains requirements for venting or purging of primary containment.

Unit-1 and Unit-2 TRM Table 3.11.2.1-1 note (c) was revised August 15, 2005 to clarify the process for gaseous effluent sampling following plant startup, shutdown or thermal power changes exceeding 150% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Unit-1 and Unit-2 TRM Section 3.11.2.5 was revised May 13, 2005 to provide additional detail regarding ventilation exhaust treatment system operability.

Specifically, the reference to ventilation exhaust treatment "subsystems" was added throughout section 3.11.2.5 to clarify system operability.

Unit-1 and Unit-2 TRM Section 3.11.4.1 was revised November 30, 2005 to incorporate the plant Corrective Action process to support Required Actions when the applicable Radiological Environmental Monitoring Program (REMP) Conditions are met. The revision enhances the tracking of items required to be reported in the Annual Radiological Environmental Operating Report.There were no changes to the Unit-1 or Unit-2 TRM Section 3.6.1 during 2005.5-3 PROCESS CONTROL PROGRAM CHANGES The following changes were made to the Process Control Program and implementing Q) procedures during 2005. None of the changes reduce the overall conformance of the solidified waste product to existing criteria for solid wastes. All changes were reviewed and approved by PORC (as necessary) as documented on the attached summary of procedure changes. The following procedures were changed: 1. NDAP-QA-0646, Process Control Program 2. CH-TP-055, Solid Radwaste 10CFR61 Correlation Factor Determination

-Sample Collection and Preparation

3. WM-PS-1120, Shipment of Radioactive Material by Air Carrier 4. WM-PS-1 80, Advanced Notification of Applicable States 5. WM-PS-310, Use of the 10-142B (USAN9208/B)

Shipping Cask 6. WM-PS-31 1, Use of the 10-142A Shipping Package 7. 'WIM-PS-316, Use of the SEG 14-215 Shipping Package 8. 'WM-PS-345, Use of the 14-190H Shipping Package 9. WIM-PS-351, Use of the CNS 21-200 (USAN9096/A)

Kk' 10. 'NIM-PS-356, Use of the CNSI 8-120 (USAN9168/B(u))

Shipping Package 11. 'NM-RP-009, Combustible Gas Check and Closure of Processing Liners and High Integrity Containers

12. WNM-RP-301, Biocide Injection to Deplete Waste Stream Biological Growth and Methane Generation
13. 'NM-RP-1 07, Transfer and Dewater A (B) RWCU Phase Separator 14. 'NM-RP-1 09, Transfer and Dewater of Waste Sludge Phase Separator 15. IMIE-ORF-1 65, Fuel Pool Cleanout -Duratek -Handling Procedure for 3-55 Cask C of C #5805 at PPL Susquehanna LLC NDAP-QA-0646 continues to fully implement the requirements and intent of the following:
1. Sections 11.4 and 13.5 of the FSAR 2. Section 3.7.4 of the Technical Requirements Manual 3. '10 CFR 20,10 CFR 61,10 CFR 71, 49 CFR 100-177, and 40 CFR 261 Compliance with all applicable regulatory requirements listed above continues to be met as the result of these changes to the program. These changes to the Process Control Program will not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.5-4 PROCEDURE REVISION

SUMMARY

NDAP-QA-0646, Revision 10 1. Added responsibilities and program description for Quality Control inspection of radioactive waste processing packaging and shipping to implement changes of FSAR LDCN#3905.

PROCEDURE REVISION

SUMMARY

CH-TP-055, Revision 5 1. Revise periodic review frequency.

2 year review is no longer required by NDAP-QA-0002.2. Update owner titles.3. These are administrative corrections.

PROCEDURE REVISION

SUMMARY

WM-PS-1 20, Revision 4 1. Made minor administrative changes.2. changed and clarified Limited Quantity requirements due to recent regulatory change.PROCEDURE REVISION

SUMMARY

WM-PS-180, Revision 7 1. [)ue to interpretation of a recent change to 49CFR Part 15, added steps to treat Form WM-PS-180-1 and WM-PS-180-3 as Sensitive Security Information (SSI)from the time of generation until the shipment arrives at the final destination (or is cancelled).

2. Added steps on how to control SSI.PROCEDURE REVISION

SUMMARY

WM-PS-310, Revision 3 1. Incorporate high intensity light inspection of cask upon receipt and prior to installing the primary lid per CR 613944 and updated the cask checklist (Form WVM-PS-31 0-1).5-5 PROCEDURE REVISION

SUMMARY

WM-PS-3110, Revision 4 1. Added requirement to obtain NRC approval prior to changing the cask per NRC IN 2005-10. (CRA #680009).2. Incorporated PCAF 2004-1013 and 2005-1031.

3. Updated the procedure adherence level.4. Added step 6.3.4 due to change in the vendor's procedure (OM-101-WS).
5. Incorporated various administrative enhancements.

PROCEDURE REVISION

SUMMARY

WM-PS-311, Revision 4 1. Incorporated PCAF 2004-1230.

2. Added cask internal inspection for residual waste using a high intensity light in accordance with CR 613944.3. Adjusted maximum payload and loaded cask limit weights to correspond to the vendor cask manual.4. Changed Effluents Management Supervision to Radioactive Material Shipper.5. Incorporated minor administrative changes.PROCEDURE REVISION

SUMMARY

WM-PS-316, Revision 4 1. This procedure is deleted.2. Incorporated this procedure into Revision 4 of WM-PS-354, Use of the CNS 14-215H, NUKEM 14-215, 14-210L and 14-21 OH Shipping Packages.PROCEDURE REVISION

SUMMARY

WM-PS-345, Revision 2 1. Deleted PCAF 2002-1140 (Incorporated into this PCAF 2005-1405).

2. Added requirements to inspect cask for residual waste per CR 613944.5-6
3. Changed "Effluents Management Supervision" to "Designated Radioactive Shipper" throughout the procedure and on Form WM-PS-345-1 to reflect current structure.
4. Added miscellaneous administrative changes.PROCEDURE REVISION

SUMMARY

WM-PS-351, Revision 1 1. Deleted PCAF 2004-1232 and PCAF 1-97-6043 (Incorporated into this PCAF:2005-1406).

2. Added requirements to inspect cask for residual waste per CR 613944.3. Changed "Effluents Management Supervision" to "Designated Radioactive Material Shipper" throughout the procedure and on Form WM-PS-351-1 to reflect current structure.
4. Added miscellaneous administrative changes.PROCEDURE REVISION

SUMMARY

WM-PS-356, Revision 1 1. Deleted PCAF 2004-1228.

2. Added requirements to inspect cask for residual waste per CR 613944.3. Updated cask expiration date.4. Changed "Effluents Management Supervision" on Form WM-PS-356-1 to"Designated Radioactive Material Shipper" to reflect current structure.

PROCEDURE REVISION

SUMMARY

WM-RP-009, Revision 4 1. Added requirements to check for gas pressurization of containers prior to shipment and a caution concerning the possibility of waste (bead resin) getting under the load collar of high integrity containers per AR 623224623224and AR 635358635358PROCEDURE REVISION

SUMMARY

WM-RP-009, Revision 5 1. Incorporated QC Hold Point from PCAF 2005-1137 that was inadvertently left out in Revision 5.2. Administrative correction to revision number on both forms.5-7

3. Incorporated PCAF 2005-1137, PCAF 2005-1137 added requirements to check for gas pressurization of containers prior to shipment and a caution concerning the possibility of waste (bead resin) getting under the load collar of high integrity containers per AR 623224623224and AR 635358635358PROCEDURE REVISION

SUMMARY

WM-RP-301, Revision 1 1. Reissued procedure after update due to gas generation in radwaste containers.

Issentially, the steps from WO 689808 replaced the body of the procedure.

PROCEDURE REVISION

SUMMARY

WM-RP-107, Revision 8 1. Procedure now specific to transfer and dewatering of RWCU.2. Instructions for sampling and drying have been moved to another procedure.

3. Instructions for container closure, combustible gas and waste on top of the container, have been moved to other procedures.

PROCEDURE REVISION

SUMMARY

WM-RP-1 09, Revision 1 1. Due to OP-068-001 division into three procedures, corrected reference to the proper procedure in steps 2.6(6.3.3.a)

(6.3.15) and (6.3.18).PROCEDURE REVISION

SUMMARY

ME-ORF-165, Revision 1 1. A copy of the current revision of Certificate of Compliance NO. 5805 shall be available on site prior to use of shipping package.2. F'PL shall be a registered user of the model CNS 3-55 shipping package with ttie Nuclear Regulatory Commission.

3. A copy of all documents referenced in the current revision of the certificate of compliance relating to the use and maintenance of the packaging and to the actions taken prior to shipment package, (i.e., applicable drawings and/or safety and design evaluations).

5-8 SECTION 6 MISCELLANEOUS TECHNICAL REQUIREMENTS MANUAL (TRM), FSAR AND 40CFR190 REPORTING 6-1

1. TRM Action 3.11.1.4.F.2 requires the reporting of Liquid Radwaste Effluent Monitoring Instrumentation inoperability not corrected in a timely manner.None to report for 2005.2. TRM Action 3.11.1.5.C.1 requires the reporting of Radioactive Liquid Process Effluent Monitoring Instrumentation inoperability not corrected in a timely manner.None to report for 2005.3. TRM Action 3.11.2.6.K requires an explanation for Radioactive Gaseous Effluent Monitoring Instrumentation required actions and completion times not met.None to report for 2005.4. TRM Action 3.11.4.1.F.2 requires reporting the cause of the unavailability of milk or fresh leafy vegetable samples and identify the new locations for obtaining replacements.

None to report for 2005.5. TRM Action 3.11.4.2.A requires reporting when land use census identifies a new location which yields a calculated dose or dose commitment greater than the values currently being calculated in Requirement 3.11.2.3 (Gaseous Effluent Dose due to Iodine, Tritium, and Radionuclides in Particulate Form).None to report for 2005.6. TRM Action 3.11.4.2.B requires reporting when land use census identifies locations that yield a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Requirement 3.11.4.1 (Radiological Environmental Monitoring Program).None to report for 2005.7. The 40CFR1 90.10 standard for normal operation for the uranium fuel cycle including annual dose equivalent and total quantities of radioactive material limits was not exceeded by Station operation.

Refer to Page 4-2 for specific values.8. FSAR Section 11.6.11 requires the reporting of airborne radioactivity detected in the Low Level Radwaste Holding Facility.None detected in 2005.6-2 SECTION 7 CORRECTIONS TO DOSES REPORTED IN PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS 7-1 CORRECTIONS TO DOSES REPORTED IN PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS No corrections to previous Radioactive Effluent Release Reports are submitted for this report period.7-2 SECTION 8 EFFLUENT FROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWA YS 8-1 EFFLUENT FROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAYS Insignilcant Effluent Pathways are: 1) evaporation from the Unit 1 and Unit 2 Condensate Storage Tanks (CST's); 2) evaporation from the common Refueling Water Storage Tank (RWST); 3) gaseous effluent from the Hydrogen Seal Oil, Main Turbine and RFPT lubrication oil mist eliminators which vent to the turbine building roofs.These pathways are not continuously monitored.

The CSTs and RWST are sampled monthly to determine the concentration of radionuclides present in these tanks. Tritium analysis on these samples is performed quarterly.

Airborne release to the environment from the tanks is estimated based on conservative estimates of the evaporation rates from each of the tanks using a modified method established within Chapter 7 of EPA A1P-42. A conservative carry-over fraction of radionuclides from the water to the evaporated liquid is then assumed. Airborne release to the environment from the demisters conservatively assumes the maximum moisture (condensate) concentration of the lubrication oil as measured via sampling during 2005. The calculation also assumes immediate removal of 100% of the water by the oil mist eliminators as it passes through the turbines.

Additionally, in October 2004 the auxiliary steam system was identified as contaminated with low levels of tritium (-1 E-5 pCi/cc). Airborne release to the environment from auxiliary steam system operation during 2005 is estimated JI based on conservative assumptions of system maximum vent flow rates and maximum identified tritium concentration levels. Offsite dose due to the release of 1.56E-5 Ci tritium from the auxiliary steam system operation during 2005 is included in the maximum dose to the public from insignificant effluents.

The annual release of tritium, iodines and particulates with half-lives greater than 8 days was calculated based on these Conservative assumptions.

The calculated releases are shown in Table 8-1. All nuclides, except for tritium, released from insignificant effluent pathways are negligible compared to the airborne release data shown in Tables 2-1 and 2-2. The maximum dose to the public from a release of 9.05 Ci of tritium is calculated to be 8.36E-2 mrem (child). This is a small fraction of the maximum dose from airborne effluent reported in Section 4.8-2 Kj)TABLE 8-1 ANNUAL RELEASE FROM SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAYS U1-CST and U2-CST and Main TurbineIRFPT Main Turbine/RFPT Nuclide RWST Lube Oil Systems Lube Oil Systems Aux. Steam System Total (Ci) (Ci) (Ci) (Ci) (Ci)H-3 6.3 1E-02 4.32E+00 4.66E+00 1.56E-05 9.05E+OO Mn-54 1.26E-08 4.06E-08 9.75E-07 1.03E-06 Co-60 8.77E-08 8.94E-08 1.47E-06 1.65E-06 Cs-137 I.26E-10 2.95E-09 O.OOE+OO 3.07E-09 Xe-135 O.OOE+OO 3.16E-06 1.22E-05 1 .53E-05 Co-58 _2.24E-09 2.98E-09 5.36E-08 5.88E-08 Zn-65 9.81E-10 3.77E-09 1.92E-08 2.40E-08 Sb-125 5.94E- I I O.OOE+OO O.OOE+OO 5.94E- l I Cr-51 1.45E-08 1.13E-08 4.18E-07 4.44E-07 Fe-59 4.87E-09 O.OOE+OO 2.04E-07 2.09E-07 Xe- 133 O.OOE+OO 1 .84E-06 O.OOE+OO 1 .84E-06 Sb- 124 O.OOE+OO O.OOE+OO 7.1 IE-09 7.1 1E-O9 Kr-88 O.OOE+OO 1.1 7E-09 O.OOE+OO 1.1 7E-(09 Nb-95 _.OOE+OO O.OOE+OO 1 .90E-08 I .90E-C8 Zr-95 O.OOE+OO 1.17E-09 1.55E-08 I .66E-C18 8-3

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