ML18017A285

Annual Effluent & Waste Disposal Rept for Jan-Dec 1995. W/ 960329 Ltr

ML18017A285
Person / Time
Site:	Susquehanna
Issue date:	12/31/1995
From:	Byram R PENNSYLVANIA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9604020111
Download: ML18017A285 (376)

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.CATEGORY 1.REGULATOROZNPOg+TION DISTRIBUTION ArSTEM (RIDE)ACCESSION NBR:9604020111 DOCWDATE: 95/12/31 NOTARIZED:

NO FACIL:50-387 Susquehanna Steam'Electric Station, Unit 1, Pennsylva 50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva AUTH.NAME AUTHOR AFFILIATION BYRAM,R.G.

Pennsylvania Power G Light Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET N 05000387 05000388

SUBJECT:

"Annual Effluent 6 Waste Disposal Rept for Jan-Dec 1995." W/960329 ltr.DISTRIBUTION CODE: IE4SD COPIES RECEIVED:LTR I ENCL I SIZE: TITLE: 50.36a(a)(2)

Semiannual Effluent Release Reports NOTES: 05000387 E RECIPIENT ID CODE/NAME PD1-2 LA POSLUSNY,C COPIES RECIPIENT LTTR ENCL ID CODE/NAME 2 2 ,='D1-2 PD 1 1 COPIES LTTR ENCL 1 1 INTERNAL: ACRS NRR/DRPM/PERB/B RGN1 FILE 1 1 1 1 ,1 1 CENT-HR'1.

1 1 RGN1 DRSS/RPB 2 2 EXTERNAL: LITCO AKERS,D NOTES: 1 1 1 1 NRC PDR 1 1 D U~'OTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE.YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl r TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 13 r

Pennsylvania Power 8 Light Company Two North Ninth Street~Allentown, PA 18101-1179

~810/774-5151 Robert G.Byram Senior Vice Presidenr-/Vnc/ear 610/774-7502 Fax: 610/774-5019 MAR p 9 t996 U.S.Nuclear Regulatory Commission Attn.: Document Control Desk Mail Station P 1-137 Washington, D.C.20555 SUSQUEHANNA STEAM ELECTRIC STATION ANNUAL EFFLUENT dh WASTE DISPOSAL REPORT Docket No.50-387 and 50-388 In accordance with 10CFR50.36a(a)(2) and the Susquehanna SES Unit 1 and 2 Technical Specifications, attached is the Annual Effluent&Waste Disposal Report for SSES Units 1 and 2 covering the period January 1 tl1rough December 31, 1995.Very truly yours, R..ym Attachment copy: NRC Region I Mr.C.Poslusny, Jr., NRC Sr.Project Manager-OWFN Ms.M.Banerjee, NRC Sr.Resident Inspector-SSES VSOe02OX<i 95aasa PDR ADQCK 05000387l R PDR

+1.~iP k PO I h

@0 ANNUAL EFFLUENT 8c WASTE DISPOSAL REPORT FOR JANUARY-DECEMBER 1995 Pennsylvania Power&Light Company Two North Ninth Street Allentown, Pennsylvania 18101-1179

\March 1996...9604020111 SUSQUEHANNA STEAM ELECTRIC STATION ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT REPORT PERIOD: 01/01/95-12/31/95 Prepared by: R.K.Barclay Health Physicist Reviewed by: B.H.Carson Health Physicist Approved by: K.E.Shank Supervisor

-Environmental Services-Nuclear Pennsylvania Power&Light Company Two North Ninth Street Allentown, Pennsylvania 18101 TABLE OF CONTENTS SECTION PAGE 1.Introduction and Supplemental Information 2.Effluent and Waste Disposal Data 3.Meteorological Data and Dispersion Estimates 4.Dose Measurements and Assessments 13 37 68 5.Changes to the Offsite Dose Calculation Manual and the Solid Waste Process Control Program 77 6.Reports of Exception to the SSES Effluent Monitoring Program 7.Correction to Doses Reported in Previous Semiannual or Annual Effluent and Waste Disposal Report 82 84 8.Effluent from Additional Monitored Release Points 86 AppendixA Appendix B Revisions to SSES ODCM Revisions to SSES Solid Waste Process Control Program (NDAP-QA-0646) 0 LIST OF FIGURES PAGE Figure 1: SSES Airborne Effluent Release Points~Figure 2: SSES Waterborne Effluent Release Pathway Figure 3: Susquehanna River Monthly Average Flow Rates Figure 4: SSES Monthly Liquid Radwaste Discharge Totals Figure 5: SSES Wind Rose: 10-meter Sensors Figure 6: SSES Wind Rose: 60-meter Sensors Figure 7: SSES Pasquill Stability Class Prevalences Figure 8: Areas Within the SSES Site Boundary Open to Members of the Public 6 22 23 40 41 42 73 SECTION 1 INTRODUCTION AND SUPPLEMENTAL INFORMATION INTRODUCTION The Susquehanna Steam Electric Station (SSES)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 1,050 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 opeiation 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 Susquehanna Station via five rooftop vents on the reactor building (see Figure 1).Each vent is continuously monitored, and a program of periodic sarripling and analysis is conducted as specified in the plant Technical Specifications.

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 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 Susquehanna Steam Electric Station during the period from January 1, 1995 to December 31, 1995.In addition, this report serves as a medium for notifying the US Nuclear Regulatory Commission staff of changes to PPRL's Offsite Dose Calculation Manual (ODCM)and Solid Waste Process Control Program (PCP)and documentation of any exceptions to the SSES effluent monitoring program which must be reported per Technical Specifications 3.3.7.10 and 3.3.7.11.A section containing corrections to a previously reported dose is also included.Airborne and waterborne radioactive effluent releases to the environment during the report period were sampled and analyzed in accordance with the requirements of the Technical Specifications.

All radioactive effluent releases were within the concentration and release limits specified in the Radiological Effluent Technical Specifications (RETS).Calculations and terms utilized in this report are those outlined in the SSES Offsite Dose Calculation Manual (ODCIVI).

Section 1 contains supplemental information pertaining to effluents from the Susquehanna plant.Included are regulatory limits (Table 1), sampling and analysis methods, and characterization of the number and duration of batch and abnormal releases, if any.Section 2 contains effluent and waste disposal data for the report period.Table 2 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 3 presents the activity totals of specific radionuclides in airborne effluents.

Waterborne effluents are summarized in Table 4.Average diluted concentrations are presented and compared to the applicable limits.Table 5 presents the release quantities of specific radionuclides in waterborne effluents over the report period.Figure 3 lists the Susquehanna River monthly average flow rates for 1995 while Figure 4 presents the SSES monthly liquid radwaste discharge totals for 1995.Tables 6 through 17 present a characterization of the solid radioactive waste shipped offsite during the report period.Included are the volumes and curie contents associated with each type of solid waste.An estimate of major nuclide composition is presented for each waste type, as well as the number of waste shipments from the site, how they were transported, and their final destination:

Table 18 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.Table 19 presents effluent data from previous report periods which was'not available at preparation time for the associated annual report.'ection 3 of this report contains the meteorological data associated with the year 1995.Availability data for the SSES meteorological data are shown in Table 20.Meteorological data for the calendar year is presented in the form of joint wind frequency distributions by atmospheric stability class.These distributions are presented in Table 21.Figures 5 and 6 are wind rose plots for the SSES primary meteorological 10-meter and 60-meter sensors, respectively.

Figure 7 presents the relative prevalences of the Pasquill stability classes.In addition, the meteorological data from the report year were used to generate annual average relative concentrations (X/Qs)and deposition rates (D/Qs).These values are presented in Table 22, and are required input for use of the GASPAR code for calculation of the doses resulting from airborne releases.

II 0 Section 1 contains supplemental information pertaining to effluents from the Susquehanna plant.Included are regulatory limits (Table 1)sam li anal sis metho y'ds, and characterization of the number and duration of batch and abnormal releases, if any.Section 2 contains eNuent and waste disposal data for the report period.Table 2 contains a summation of all airborne releases, grouped into the radionuclide categories o gases, particulates, iodines, and tritium.Average release rates are presented and compared to the applicable limits.Table 3 presents the activity totals of specific radionuclides in airborne effluents.

Waterborne eNuents are summarized in Table 4.Average diluted concentrations are presented and compared to the applicable limits.Table 5 t h Fi ure 3 lists i ies o speci ic radionuclides in waterborne effluents over the report'.'g'he Susquehanna River monthly average flow rates for 1995 while epo perio.Figure 4 presents the SSES monthly liquid radwaste discharge totals for 1995.Tables 6 throu h17 g.present a characterization of the solid radioactive waste shipped offsite during the report period.Included are the volumes and curie contents associated with each type of solid waste.An estimate of major nuclide composition is presented for each waste type, as well as the number of waste shipments from the site, how they were transported, and their final destination Table 18 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 eNuent'measurements.

Error estimates are presented for each category of radionuclide detected in airborne and waterborne effluents and solid wastes during the report period.avai Table 19 presents effluent data from previous report periods wh ch t'lable at preparation time for the associated annual report.i was no Section 3 of this report contains the meteorological data associated w'th th.Availability data for the SSES meteorological data are shown in Table 20.i e year Meteorological data for the calendar year is presented in the form of joint wind frequency distributions by atmospheric stability class.These distributions are presented in Table 21.Figures 5 and 6 are wind rose plots for the SSES rima meteorolo ical 10-me g'meter and 60-meter sensors, respectively.

Figure?presents the relative prevalences of the Pasquill stability classes.In addition, the meteorological data from the report year were used to generate annual average relative concentrations (XJQs)and deposition rates (D/Qs).These values are presented in Table 22, and are required input for use of the GASPAR code for calculation of the doses resulting from airborne releases.

Section 4 of this report contains an assessment of the calculated doses attributed to the reported radiological effluents for the calendar year.The LADTAP II code was used for calculation of doses from waterborne effluents.

Table 23 contains site-specific parameters used for LADTAP II calculations, for the Danville receiver.The GASPAR code was 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 24 summarizes maximum calculated doses and dose commitments to members of the public from airborne and waterborne effluents and direct radiation.

Table 25 presents calculated collective doses to members of the public within the Riverlands/Information Center Complex.Table 26 summarizes the calculated doses for residences and other occupied areas within the SSES site boundary.Table 27 reports doses calculated for the nearest dairy facility.Section 5 of this report is reserved for documentation of changes to the Offsite Dose Calculation Manual and the Solid Waste Process Control Program.A copy of changes to the ODCM during the report period is included in Appendix A.A copy of changes to the Solid Waste Process Control Program is included in Appendix B.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 the time period specified in Technical Specification Table 3.3.7.10-1 or 3.3.7.11-1 Action Statements.

Section 7 contains corrections to doses reported in previous Semi-annual or Annual Effluent and Waste Disposal reports.(Table 28)Section 8 contains information on effluent (Table 29)and offsite dose (Table 30)from additional monitored release points.

FIGURE 1 SSES AIRBORNE EFFLUENT RELEASE POINTS UNIT I hEACTOh WILOINO EXHAUST VKHT ISLES Cf M AT Ol+F 110'T H hEACTDh WILDIHO EXHAUST VENT IlLKO Cf M ,ATN F Il04f 220AXXI Cf M 1240 Cf M 2QSXO Cf M AT 100+I 120ff AT 120~f AT 100+K 12IWF OUTSIDE Alh INTAKE HEACTOh 4UILOIHQ EXHAUST STACKS DIESEL EXHAUST FLENUM DIESEL OE HE HATOh WILD HID~%~~%EL.4)a'I" UNIT I TUXEIHE 0UILO INC EXHAUST VENT UNIT II TUXSHIE SUILOHIO EXHAUST VENT lbhADW 4 WILDING L4 I rr I I So+24-+rr 21'~TUhEINE SUILOINO Jg UNIT I EL 414'4 UNIT I I It r Il FIGURE 2 SSES WATERBORNE EFFLUENT PATHWAY I I I l~~~I ,I a t guy Z~a~u Xg)i)a noae PQ II cC~Ig 4g I e ee~gP, Qn~egr e(4I~n<>o I I~I I v5c Xn n IeldOOOC I I I e J I

SUPPLEMENTAL.lNFORMATlON 1.Re ulato Limits Technical Specifications 3/4.11.1 and 3/4.11.2 outline requirements for release of radioactive liquid and gaseous effluents, respectively.

Concentration of radioactive materials released in liquid effluents and dose or dose commitment resultant thereof 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 Specification limits are listed in Table 1.2.Maximum Permissible Concentrations in Waterborne Effluents The concentrations of radioactive materials in waterborne effluents are limited to the concentrations specified in 10 CFR Part 20 Appendix B Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentrations are limited to the following values, as stated in the applicable Technical Specification:

Nuclide MPC uCi/ml 85mK 85K 87K 88K"'AI 133mX 133X 135mx 135X 2.0E-04 5.0E-04 4.0E-05 9.0E-05 7.0E-05 5.0E-04 6.0E-04 2.0E-04 2.0E-04 3.A~~Based on gaseous effluent releases for the report period average beta energy is , 0.319 MeV and average gamma energy is 0.249 MeV.4.Measurements and A roximations of Total Radioactivi Analyses of specific radionuclides in effluent samples are used to evaluate the radioactive composition and concentration of effluents.

5.Methods of uantif in Effluents'ission and Activation Gases: Gas samples are routinely collected monthly and analyzed with a high resolution (Ge[Li]or HPGE)detector system which incoroorates a data reduction program to determine radionuclide composition in terms of specific activity.Data tapes from the continuous vent monitors are used to determine the average concentration of noble gases: The high resolution (Ge[Li]or 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 samples are taken from each vent once each eight hours (once each four hours for the standby gas treatment vent).b.C.lodines: iodine is continuously collected via an isokinetic sampling assembly in each vent.Filters are normally exchanged once per week and analyzed on a high resolution (Ge[Li]or HPGE)system.The daily average flow rates for the vents and sample pumps are averaged for the duration of the sa'mpling 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 monitors are out of service, iodine is continuously collected on charcoal cartridges attached to air samplers which draw directly from the affected rooftop vent(s)or from alternate sampling ports available on the sample lines.'I 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 (Ge[Li]or HPGE)system.Flow rate corrections are performed as for iodines.When the continuous vent monitors are out of service, particulates are continuously sampled directly from the affected rooftop vent(s)or from alternate sampling ports available on the sample lines.Tritium: Airborne tritium is collected monthly via bubbler sampler.The sample is collected for one hour at a flow rate of approximately 1000 cclmin.Tritium activity in the bubbler sample is determined by liquid scintillation counting.The liquid sample tritium concentration is converted to air concentration by volume proportion, then compared to the Technical Specification Table 4.11.2.1.2-1 Lower Limit of Detection (1 E-6 uCi/cc).

j<

I 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 (Ge[Li]or 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.The quarterly composite is sent to a vendor laboratory for iron-55, strontium-89 and-90, and gross alpha analyses.The concentration of each radionuclide in each batch is decay corrected from the time of counting to the midpoint of the release period, and is then multiplied by the volume of the batch to determine the total quantity of each nuclide released in each batch..The isotopic totals for each are summed to determine the total source term for the report period.

TABLE 1 1.TECHNICAL SPECIFICATION LIMITS A.NOBLE GASES: 1.s500 mrem-TOTAL BODY<3000 mrem-SKIN"-annual site total"instantaneous" limits (Tech Spec.3.11.2.1)2.<5 mrad-AIR GAMMA s10 mrad-AIR BETA quarterly air dose limits per reactor unit (Tech Spec.3.11.2.2)3.c1 0 mrad-AIR GAMMA&<0 mrad-AIR BETA annual air dose limits per reactor unit (Tech Spec.3.11.2.2)B.AIRBORNE I-131, TRITIUM, PARTICULATES WITH HALF-LIVES

>8 DAYS: s1 500 mrem-ORGAN'inhalation pathways only)annual site total"instantaneous" limits (Tech Spec.3.11.2.1)'-2.s7.5 mrem-'ORGAN quarterly dose limits per reactor unit (Tech Spec.3.11.2.3)3.c15 mrem-ORGAN annual dose limits per reactor unit (Tech Spec.3.11.2.3)10 C.~LI UIOEFFLUEMTR 1.Concentration g 10CFR20 Appendix B, Table II, Column 2-site total"instantaneous" limits (Tech Spec.3.11~1.1)s5 mrem-ORGAN quarterly dose limits per reactor unit (Tech Spec.3.11.1.2)t 3.s3 mrem-TOTAL BODY s10 mrem-ORGAN annual dose limits per reactor unit (Tech.Spec.3.11.1.2)D.AIRBORNE EFFLUENT: BASES FOR PERCENT OF APPLICABLE TECHNICAL SPECIFICATION LIMIT Fission and Activation Gases A derived release rate limit based on the Technical Specification limit of 500 mrem/yr was calculated from the expected mix of noble gas radionuclides

'resented in Table 4.4 of the SSES Final Environmental Statement (NUREG-0564).

The limit is 8.51E+05 uCi/min (1.42E+04 uCi/sec).Iodine-1 31 A derived release rate limit based on the Technical Specification limit of 1500 mrem/yr from l-131, tritium and particulates with half-lives greater than 8 days was calculated from the annual release quantity of I-131 provided in Table 4 4 of the SSES Final Environmental Statement (NUREG-0564).

The limit is 1.41E+02 uCi/min (2.35E+00 uCi/sec).Particulates A derived release rate limit.based on the Technical Specification limit of 1500 mrem/yr from l-131, tritium and particulates with half-lives greater than 8 days was calculated based on the expected mix of particulate radionuclides presented in Table 4.4 of the SSES Final Environmental Statement (NUREG-0564).

The limit is 7.72E+02 uCi/min (1.29E+01 U C I/sec).11 Tritium A derived release rate was calculated based on the 10 CFR 20 Appendix B, Table II, Column 1, Maximum Permissible Concentration for tritium (2.0E-07 uCi/cc)to unrestricted areas.A relative concentration of 4.1E-05 sec/m'was assumed.The limit is 2.93E+05 uCi/min (4.88E+03 uCi/sec).F.WATERBORNE EFFLUENT: BASES FOR PERCENT OF APPLICABLE TECHNICAL SPECIFICATION LIMIT 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 10CFR20 Appendix B, Table II, Column 2 Maximum Permissible Concentration Limits such that, with dillution, the sum of isotope concentrations divided by Maximum Permissible Concentrations must be<1.0.No Technical Specification limit for the total concentration of fission and activation products in liquid effluents is applicable for this category.Tritium Liquid effluent quarterly tritium concentrations are compared to the 10 CFR 20 Appendix B, Table II, Column 2, Maximum Permissible Concentration limit of 3.0E-03 uCi/ml to unrestricted areas.Dissolved and Entrained Gases Liquid effluent quarterly concentration totals for dissolved and entrained gases are compared to the most restrictive Maximum Permissible Concentration for a noble gas 4.0E-05 uCi/ml (Kr-87)from the SSES Technical Specification Table 3.11.1.1-1.

12 SECTION 2 EFFLUENT AND WASTE DISPOSAL DA TA 13

Airborne Effluents Summaries of the radionuclide total curie activities and average release rates are included in Tables 2 and 3.Third Fourth Quarter Quarter~1.Number of Batch Releases:.2.Total Time Period for Batch Release: 3.Maximum Time Period for a Batch Release: 4.Average Time Period for a Batch Release: 5.Minimum Time Period for a Batch Release: 0 NA NA NA'A 0 NA NA NA NA Abnormal Releases 1.Number of Releases 2.Total Activity Released 0 NA 0 NA 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 SSES Technical Specification Table 4.11.2.1.2-1, Radioactive Gaseous Waste Sampling and Analysis Program.In all cases, these LLDs were less than the levels required by Technical Specifications.

The following are typical LLDs.Radionuclide LLD (uCI/cc)Kr-87 Kr-88 Xe-1 33 Xe-1 33m Xe-1 35 Xe-135m Xe-138 4.6 E-08 5.3 E-08 5.4 E-08 1.3 E-07 1.5 E-08 5.0E-08 1.2 E-07 Mn-54 Fe-59 Co-58 Co-60'n-65 Mo-99 Cs-134 2.9 E-14 2.8 E-14 1.8 E-14 3.8 E-14 4.4 E-14 3.3 E-13 2.4 E-14 14 Radionuclide Cs-137 Ce-141 Ce-144 l-1 31 Sr-89 Sr-90 H-3 Gross Alpha LLD (uCi/cc)2.1 E-14 1.5 E-14 7.0 E-14 4.4 E-14 2.0 E-15 3.0 E-16 2.6 E-08 5.0 E-16 15

TABLE 2 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (1995)AIRBORNE EFFLUENT-SUMMATION OF ALL RELEASES A.Fission and Activation Gas Unit First uarter Second uarter Third uarter Fourth uarter Total Release Ci'.32E-02 1.53E+01 0.00E+00 O.OOE+00 Average Release Rate for Period Percent of Technical Specification Limit 5.76E-05 1.38E-02 uCi/sec 8.13E-03 1.95E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 B.Iodines Total I-131 Average Release Rate for Period Ci 0.00E+00 0.00E+00 uCi/scc 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Percent of Technical Specification Limit Q.OOE+00 0.00E+00 0.00E+00 O.OOE+00 C.Particulate

~~Particulate with Half-Lives

>8 Days*Ci 2.18E-04 4.60E-04 7.33E-05 9.35E-04 Average Release Rate for Period Percent of Technical Specification Limit Gross Alpha Radioactivity*

uCi/sec Ci 2.80E-05'2.17E-04 1.06E-06 5.85E-05 4.55E-04 2.85E-07 9.22E-06 7.18E-05'.18E-04 9.15E-04 0.00E+00 O.OOE+00 D.Tritium Total Release Average Release Rate for Period Ci uCi/sec 1.59E+01 2.04E+00 1.24E+01 1.58E+00 2.36E+01 1.02E+01 2.97E+00 1.28E+00 Percent of Technical Specification Limit 4.17E-02 3.22E-02 6.06EA2 2.62E-02*Sr-89, Sr-90 and Gross Alpha values for the fourth quarter 1995 are estimated based on third quarter 1995 sample analyses and fourth quarter 1995 ventilation exhaust rates.16

TABLE 3 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (1995)AIRBORNE EFFLUENT Releases in Continuous Mode Nuclides Released A.Fission and Activation Gases Unit First Quarter Second Quarter Third Quarter Fourth Quarter Kr-85m Xe-133 Xe-135 Total for Period B.Iodines I-131 I-133 I-135 Total for Period C.Particulate Cr-51 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Sr-89~Sr-90*Cs-134 Cs-137 Ce-141 Ce-144 Total for Period~Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci, Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0.00E+00 0.00E+00 0.00E+00 6.32E-.02 6.32E-02 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 1.62E-05 1.10E-04 0.00E+00 2.51E-05 2.99E-05 3.65E-05 0.00E+00 1.26E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.18E-04 0.00E+00 0.00E+00'.00E+00 1.53E+01 1.53E+01 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 2.46E-05 3.43E-04 4.54E-05 0.00E+00 4.70E-05 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.60E-04 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.71E-05 O.OOE+00 O.OOE+00 0.00E+00 1.71E-05 0.00E+00 0.00E+00 4.95E-05 6.41E-04 0.00E+00 1.58E-04 0.00E+00 0.00E+00 2.38E-05 1.36E-04 0.00E+00 0.00E+00 0.00E+00'.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 7.33E-05 9.35E-04*Reported values for the fourth quarter 1995 are estimated based on third quarter 1994 sample analyses and fourth quarter 1995ventilation exhaust rates.

Waterborne ENuents Summaries of the radionuclide total curie activities, average diluted concentrations, and percent of applicable Technical Specification limits are included in Tables 4 and 5.Batch Releases"'.Number of Batch Releases 2.Total Time Period for a Batch Release 3.Maximum Time Period for a Batch Release 4..Average Time Period for a Batch Release 5.Minimum Time Period for a Batch Release 6.Average Stream Flow During Period of Release of Effluent into a Flowing Stream Qtr.1 gtr.2 gtr.3 40 70 52 5.11E+03 1.30E+04 5.07E+03 3.08E+02 5.64E+02 3.48E+02 gtr.4 62 1.10E+04 5.20E+02 1.28E+02 1.86E+02 9.75E+01 2.50E+01.1.00E+00 2.00E+01 1.78E+02 2.40E+Ol (Cooling Tower Blowdown Flow Rate)6.76E+03 6.86E+03 1.00E+04 7.60E+03 7.94E+06 3.95E+06 6.53E+05 5.94E+06 (Susquehanna River Flow Rate)<<Units of time and flow are expressed in minutes and gallons per minute (gpm), respectively.

Abnormal Releases 1.Number of Releases 2.Volume Released 3.Total Activity Released 0 N/A N/A 0 N/A N/A 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 SSES Technical Specification Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program.In all cases, these LLDs were less than the levels required by Technical Specifications.

The following are typical LLDs.Radionuclide LLD uCi/ml Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 I-131 Cs-134 4.5 E-08 5.0 E-08 2.4 E-08 5.4 E-08 4.9 E-08 1.7 E-07 2.0 E-08 2.2 E-08 18

Radionuclide LLD uCi/ml Cs-137 Ce-141 Ce-144 Sr-89 Sr-90 Fe-55 H-3 Gross Alpha 2.6 E-08 3.2 E-08 1.3 E-07 4.0 E-08 4.0 E-09 1.0 E-06 4.6 E-06 3.0 E-08 19 TABLE 4 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (1995)WATERBORNE EFLUENT-SUMMATION OF ALL RELEASES A.Fission and Activation Products Unit First Quarter Second Quarter Third Quarter Fourth Quarter'1.Total Release (not including Tritium, Gases, AI h'a~2.Average Diluted Concentration During Period 3.PercentofA licableLimit Ci uCi/ml 5.91E-02 4.44E-01 3.43E-02 4.52E-07 1.27E-06 1.81E-07 O.OOE+00'.OOE+00 O.OOE+00 4.21E-02 1.37E-07 0.00E+00 B.Tritium 1.Total Release Ci 1.68E+01 2.75E+01 9.32E+00 2.57E+01 2.Average Diluted Concentration During Period 3.Percent of A licable Limit uCi/ml 1.28E-04 4.28E+00 7.86E-05 2.62E+00 4.91E-05 1.64E+00 8.37E-05 2.79E+00 C.Dissolved and Entrained Gases Total Release Average Diluted Concentration During Period Ci uCi/ml 1.51E-04 1.15E-09 3.34E-03 3.19E-05 9.54E-09 1.68E-10 5.45E-04 1.77E-09 3.Percent of A licable Limit D.Gross Al ha Radioactivi 1.Total Release Ci 2.88E-05 2.39E-04 4.20E-06 4.43E-.05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E.Volume of Waste Released (Prior to Dilution)Gallons 3.95E+05 3.07E+06 3.08E+05 8.25E+05 Liters 1.50E+06 1.16E+07 1.17E+06 3.13E+06 F.Volume of Dilution Water Used During Period of Release Gallons 3.45E+07 9.22E+07 5.01E+07 8.10E+07 Liters 1.31E+08 3.50E+08 1.90E+08 3.07E+08 G.Volume of Dilution Water Used Over Entire Period Gallons 8.76E+08 8.99E+08 1.32E+09 1.01E+09 Liters 3.39E+09 3.48E+09 5.13E+09 3.90E+09~Reported values for the fourth quarter 1995 are estimated based on third quarter 1995 sample analyses and fourth quarter 1995 discharge volumes.20 TABLE 5 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT (1995)WATERBORNE EFFLUENT Nuclldes Released Unit Releases in Batch Mode First Quarter Second Quarter Third Quarter Fourth Quarter A.Fission and Activation Products F-18 Na-24 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 As-76 Sr-89 Sr-90 Sr-92 Nb-95 Tc-99m A-110m Sb-124 Te-131m 1-131 Cs-134 Cs-137 La-140 Cc-144 Hi'-181 W-187 Total for Period'.Tritium H-3.Total for Period Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0.00E+00 2.21E45 4.64E42 5.56E43 O.OOE+00 2.69E43 2.05E43 1.40E44 1.74E43 2.20E44 1.89E44 0.00E+00 O.OOE+00 4.24E48 0.00E~3.05E46 3.49E45 O.OOE+00 0.00E+00 0.00E+00 2.79E46 2.72E45 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 5.91E42 1.68E+Ol 1.68E+Ol 3.94E-13 O.OOE+00 1.85E42 8.66E42 0.00E+00 2.72E41 3.63E42 5.17E43 1.93E42 3.72E43 0.00E+00 O.OOE+00 O.OOE+M 6.53E46 3.15E46 6.89E47 1.94E43 5.28E44 4.01E45 O.OOE+00 2.88E46 3.46E45 O.OOE+00 1.08E44 5.03E45 O.OOE+00 4.44E41 2.75E+01 2.75E+01 0.00E+M 7.42E44 5.60E45 2.57E42 2.24E-IO 5.47E43 1.94E44 1.51E44 1.45E43 4.50E44 0.00E+00 0.00E+00 0.00E+00 5.48E47 4.71E46 3.58E47 9.43E45 O.OOE+00 O.OOE+00 O.OOE+00 1.13E46 2.15E45 O.OOE+00 O.ME+00 0.00E+00 0.00E+M 3.43E42 9.32E+00 9.32E+00 0.00E~O.OOE+00 3.49E43 2.07E42 O.OOE+00 5.47E43 6.13E43 6.86E44 3.91E43 5.86E44 O.OOE40 O.OOE+00 0.00E+00 5.71E46 0.00E+00 0.00E40 1.10E43 3.21E45 0:OOE+00 O.OOE+00 4.22E46 1.17E45 8.23E46 O.OOE+00 O.OOE+00 O.OOE+00 4.21E42 2.57E+01 2.57E+Ol C.Dissolved and Entrained Gasses Kr-86m Kr-85 Kr-87 Kr-88 Xe-131m Xc-133m Xc-133 Xe-135m Xc-135 Total for Period Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 3.66E-OS O.OOE+00 1.14E44 1.5 IE44 O.OOE+M 0.00E+00 3.07E43 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.75E44 0.00E+00 9.15E45 3.34E43 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 1.65E45 O.OOOO 1.54E45 3.19E45 O.OOE+00 O.OOE+00 3.86E44 0.00E+00 O.OOE+00 0.00E+00 O.OOEt00 9.05E45 O.OOE+00 6.83E45 5.45E44<<Reported values for the fourth quarter are estimated based on third quarter 1995 sample analyses and fourth quarter 1995 discharge volumes.

FIGURE 3 SUSQUEHANNA RIVER MONTHLY AVERAGE FLOW RATES DATA PERIOD: 1995 GALLONS PER MINUTE x 1E6 12-.:*8:--'=-".':::::::,:::

'-"...'::.":.*6 4 2-.0 J F M A M J J A S 0 N D 1995 22 FIGURE 4 SSES MONTHLY LIQUID RADWASTE DISCHARGE TOTALS DATA PERIOD: 1995 GALLONS X 1E3 500,:.:...

400::::::::

300 200'00'I'~,~i~,~0 J F M A M J J A S 0 N D 1995 23

SUSQUEHANNA STEAM ELECTRIC STATION RADIOACTIVE WASTE REPORT ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT SOLID RADIOACTIVE WASTE DATAPERIOD:

JANUARY 1 1995-DE EMBER31 1995 PREPARED BY:.P.LEWI-AL YSICIST APPROVED BY: E 3 S DOXSEY-LUENTS MANAGEMENT SUP V.24 REPORT NOTES 1.All activities reported in millicuries (mCi)unless otherwise noted.t 2.Reported activities, as indicated with the (<)sign, are comprised in whole or part of MDL Values.3.No Class C Waste was disposed during this report period.4.The number of shipments listed in Table 6 includes only the shipments from SSES to the disposal site.It does not include shipments made to or from volume reduction vendors.25 TABLE 6 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS DATA PERIOD: JANUARY 1, 1995-DECEMBER 31, 1995 A.*SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL Number of Shi ments Mode of Trans ortation Destination Truck Barnwell, SC B.IRRADIATED FUEL SHIPMENTS Number of Shi ments Mode of Trans ortation Destination None Not Applicable Not Applicable The number of shipments listed in A include only the shipments from SSES to a disposal site.It does not include shipments made to or from volume reduction vendors.26 TABLE 11 CLASS A SOURCE OF WASTE INCINERATED DAW TYPE OF CONTAINER STRONG TIGHT CONTAINER METHOD OF PROCESS N/A ISOTOPES%OF TOTAL Ag-I lorn Am-241 C-14 Cm-242 Co-58~0 Cr-51 Cs-137 Fc-55 Fe-59 H-3 1-129 I-131 Mn-54 Ni<3 Pu-238 Pu-239 Pu-241 Sr-90 Tc-99 Zn<5 I3c47 Cm-244 Cc-144 KAO.Nb-95 Pb-212 Zr-95 Xe-133 TOTAL ACTIVITY (Ci)CONTAINER VOLUME (1.000EC4 Q 3.076'.621E+00 1.644EA3 2.596E+00 2.556E+02 1.501E42 6.911E+00 7.82&E+01 5.373E+0 I w nt&Ewl 1.&OOE+3 2.280E%2.7.099E+02 1.627E+00 4 5.039E%4<6.063E~3.386EA l'1.004E%2 4.951E%2 1.859E+01 2.000E<a<3.985E%4~'.98&E+00 1.900E-03'.150E-O l l.600E43 2.079E+00 1.200 E<3 I.1 74 295.GOO A 3 0.00%0.00%0.14%0 00%0.22%, 21 78%0.00%0.59/o 6.67%4 58%4+o~0.00%0.00%60.48%0.14%0.00%P 00%0 03%0 nn/0 l 58%0.00 io 0.00%P 17%P 00%P P2%ppp 0.l8%O.OO%100.00%8.37 l m3 27 TABLE 12 CLASS A SOURCE OF WASTE PROCESSED DAW TYPE OF CONTAINER STRONG TIGHT CONTAINER METHOD OF PROCESS N/A ISOTOPES%OF TOTAL Am-241 C-14 Cm-242 Co-58 Co%0 Cr-51 Cs-137 Fc-55 Fc-59 H-3 I-l29'n-54 Ni43 Pu-238 Pu-239 Pu-241 Sr-90 Tc-99 Zn<5 Cm-243 Cc-l44 Nb-95 Zr-95 TOTAL ACTIVITY (Ci)CONTAINER VOLUME 1.484EA3 4.336&01 5.992E+3 1.716'2.031E+02 4.728EO2 5.687E+00 6.313E&1 3.394E+01 1.321E+01 2.400E43.4.894E&2 1.321E+00 1237E<3 , 1.271843 2.325EAI 4.431E42 5.930E%2 l.279E+0 l 6.832'.881E+00 L091E~6.933 E+00~0.835 1113.100 fQ P 00%0.05%P 00%0.21%24.32%'01%0.68'.56%4.06%1.58%0.00%58.61%0.16%0.00%Q.00%0 03%Q.Q1%0.01%1 53%0.00%0.22%0 13%0 83%100 Opoj 31.520 m3 1-129 VALUES FOR SOME CONTAINERS WERE LISTED WITH LLD VALUES OP 3.01M4 uCi/cc OR LESS AN D ARE NOT INCLUDED IN THE ABOVE I-129 ACTIVITY.28 F

TABLE 13 CLASS A SOURCE OF WASTE NON-PROCESSED DAW TYPE OF CONTAINER STRONG TIGHT CONTAINER METHOD OF PROCESS N/A ISOTOPES ACTIVITY%OF TOTAL Ag-I ipm Am-241 C-14 Cm-242 Co-58 Grip Cr-51 Cs-137 Fe-55 Fe-59 H-3 1-129 Mn-54.Ni<3 Pu-238 Pu-239 Pu-241 Sr-90 Tc-99 Zn45 Ce-144 Cm-243 TOTAL ACTIVITY (Ci)CONTAINER VOLUME 1.180E<3 0.45%7.340EA7 0.00%2.700 E4~0.08%4.370EW6 0.00%1.550EA3 0.59/o 1.290'50 00%5.250EA3 2.02'/0 3.500EA3 I 34%~4.060E+2 15 73%2.780EA2 10 77%7,62nE3" 94oio N/A LLD (4.27E48 uCi/cc)3.290E<2 12 73%8.090 E4 0.31/o 5.660E7 0.00%6.110EW7 0 00%1.450E4 0.05o/o 1.360E5 0.00%1 440E<5 0 01/6.440EW3 2.48%1.270E<3 0 50/o 3.660EW7 0.00%0.000 100 00%5.9 II 0.167 m3 29 TABLE 14 CLASS B SOURCE OF WASTE RWCU FILTER MEDIA TYPE OF CONTAINER HIC METHOD OF PROCESS DEWATERED ISOTOPES ACTIVI'IY%OF TOTAL Am-241 C-14 Cm-242 GHM ,Cs-137 Fe-55 H-3 I-129 Mn-54 Ni<3 Pu-238 Pu-239 Pu-241 SR49 Sr-90 Tc-99 Zn<5 Ce-144 Ni-59 Cm-243 TOTAL ACTIVITY (Ci)CONTAINER VOLUME 7.810E42" P PP%6.250E+00 9.00%5.160E42 0.00%5.210E+05 48.56%1.619E+03 0.15%'.230E+05 20 78%2A60E41 0.00%N/A LLD (1.45E46 uCi/cc)2.870EW5 26 75%8.170E&3 0.76%1.942E42.P PP%1.956E42 0.00%1.93&E+01 0.00'/o 7.490E41 0.00%2.240Et00 0 00/9.370'0 01%3.030E~2.82%9.750E+00 0.00%1.640E+03 0 17%7.660E<2 0.00%1073.000 100.00%264.800.ft 7.498 m3 30 TABL'E 15 CLASS A SOURCE OF WASTE CONDENSATE DEMINERALIZER RAD WASTE DEMINERALIZER TYPE OF CONTAINER HIC METHOD OF PROCESS DEWATERED ISOTOPES ACTIVITY%OF TOTAL Am-241 C-14 Cm-242 Co-58 Grip Cs-137 Fe-55 Fe-59 H-3 1-129 Mn-54 Ni43 Pu-238 Pu-239 Pu-241 Sr-90 Tc-99'n45 Ce-144 Cm-243 TOTAL ACTIVITY (Ci)CONTAINER VOLUME 1.756E43 5.263 E&0 1.756E43 6.442E+01 5.033'3.894E41 2.234E+00 3.150E41 1.448E+01 N/A LLD (2;85E45 2.132E+01.8.897E41 2.335E43 2.425E43 5.571E41 1.081E42 N/A LLD (4.57E45 1.853E&0 5.362E41 1.572E43 0.163 87.600 fl 0.00%3 24%P PP%39.61%30.94%0.24%1 37%0.19%8.90%uCi/cc)13.11%0 55%P 00%0.00%0.35%P P1%uCi/cc)1 15%0 34%0.00/o 1PP PP%2.481 m3

TABLE 16 CLASS A SOURCE OF WASTE ULTRASONIC RESIN CLEANING WASTE TYPE OF CONTAINER HIC METHOD OF PROCESS DEWATERED ISOTOPES ACTIVITY%OF TOTAL Ag-I lorn Am-241 C-14 Cm-242 Co-58~0 Cr-51 Cs-137 Fc-55 Fe-59 H-3 1-129 Mn-54 Ni<3 Pu-238 Pu-239 Pu-241 Sb-124 Sr-90 Tc-99 Zn45 Cc>>144 Cm-243 Ni-59 TOTAL ACTIVITY (Ct)CONTAINER VOLUME 1.664 E+02 0.41%8.600E<3 Q 00'/5.200E+01'13%5.600E%3 P 00%2.863E&2 0 71%6.200E&3 15.24%3.700E+02 0 91%2.220E+01 0.06%6.260E+03 15.38%1.795E+03 4 42%5.680E+01 0 14%N/A LLD (6.53E45 uCi/cc)2.490E+04 61.18%1.078 E+02 0 27%1.824E%2 P 00%1.69IE42 , 0.00%4.130E+00 0 01%, 4.680E+01 0.12%2.340EA I 0 00%2.720E%1 Q.uu%4060E+02'00/1.110E+0(}u (l(kvio 5.610E%3 Q.oo%6.7 IQE+00 0 02%40.700 100 00'I 362.700 ft 10.271 m3 32 TABLE 17 CLASS A SOURCE OF WASTE LIQUID RADWASTE FILTER MEDIA TYPE OF CONTAINER HIC METHOD OF PROCESS DEWATERED ISOTOPES ACTIVITY%OF TOTAL Ag-I lpm Am-241 C-14 Cm-242 Co-58 Co%0 Cr-Sl Cs-137 Fe-55 Fe-59 H-3 1-129 Mn-54 Ni<3 Pu-238 Pu-239 Pu-241 Sb-124 Sr-89 Sr-90 Tc-99*Zn45 Ce-144 Cm-243 Hf-181 Nb-95 Ni-59 Sr-92 TOTAL ACTIVITY (Ci)CONTAINER VOLUME 3.223 E&2 2.560'2.377E+00 2.509EI 2'.959E+03 2.783 E&4 8.496E+03 7.416EWI 2.406E+04 1.173E+04 1.213E+02 N/A LLD 1.006E&5 3.576E+02 5.433'5.032'1.227E+02 2.678E+02 4.336E+00 9.318E&1 1.080 E+00 3.520E+03 1.248E+02.'.257EAI 2.631E+01 7.619E+01 9.576E+0 I 7.910E-16 180.790 777.600 0 18%0.00%P PP%0.00%64%IS 39%4 70%0.04%13.31%6 49%0 07%(4.75E45 uC1/cc)55.64%0.20%P PP%P P0%0.07%0.15%0.00%U.UU"jo 0.00%l.950jo 0.07%P PP%P P1%pp4 0.05%P PP%100 00 j'22.020 n13 TC-99 VALUES FOR SOME CONTAINERS WERE LISTED WITH LLD VALUES OF 8.84c-pS uCi/cc OR LESS AND ARE NOT INCLUDED IN THE ABOVE TC-99 ACTIVITY.33 TABLE 18 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT ESTIMATED TOTAL ERRORS ASSOCIATED WITH EFFLUENT MEASURENIENTS DATA PERIOD: January 1, 1995-December 31, 1995 Measurement Estimated Total Error 1.Airborne Effluents a.Fission and Activation Gases b.I-131 c.Particulates d.Tritium 15.9%13 3%15.8%13.6%2.Waterborne Effiuents a.Fission and Activation Products b, Tritium c.Dissolved and Entrained Gases d.Gross Alpha Activity e.Volume of Waste Released (Prior to Dilution)f.Volume of Dilution Water Used During Period 50 33%84%60%5.0%15 0%3.Solid Wastes a.Atmospheric Deminerlizer (Dewatered

-HIC)b.Condensate Demineralizer/

Radwaste Demineralizer (Dewatered

-Carbon Steel Liner)c.Condensate Demineralizer/

Radwaste Demineralizer (Dewatered

-HIC)d.Liquid Radwaste Filter Media (Dewatered

-HIC)e.RWCU Filter Media (Dewatered

-HIC)15 1%15.1%15.1%15 15.1%34 Measurement Estimated TotaI Error 3.Solid Wastes (cont.)f.Ultrasonic Resin Cleaning Waste (Dewatered

-HIC)g.Cartridge Filters (Dewatered

-HIC)h.Processe'd DAW (Strong Tight Container) i.Non-Processed DAW (Strong Tight Container) j.Incinerated DAW (Strong Tight Container) k, Cartridge Filters (HIC)I.Irradiated Components (Dewatered-Steel Liner)15.1%25 0%25 0%25 0%25.0%25.0%25.0%35 TABLE 19 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT DATA NOT REPORTED IN PREVIOUS ANNUAL REPORT NUCLIDE CATEGORY UNIT FOURTH QUARTER 1994 A.Airborne Effluents 1.Sr-89 2.Sr-90 3.Gross Alpha Ci Ci Ci 0.00E+00 5.46E-09 1.73E-06 B.Waterborne Effluents 1.Sr-89 2.Sr-90 3.Fe-55 3.Gross Alpha Ci Ci Ci Ci O.OOE+00 0.00E+00 6.18E-03 Q.QQEi00 36 SECTION 3 METEOROLOGICAL DA TA AND DISPERSION ES TIMA TES 37

~'

METEOROLOGY AND DISPERSION DATA Meteorological data have been collected at the Susquehanna SES 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 10-meter and 60-meter elevations on this tower.Vertical temperature differential is measured with redundant sensor pairs between~the 10m 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 10-meter tower providing alternate measurements of wind speed, wind direction, and sigma theta.SSES meteorological data is transmitted to the plant control room, Technical Support Center, and Emergency Operations Facility for emergency response availability.

The data is also transmitted via telephone line data-link to the PPB L corporate computer in Allentown.

Dispersion modeling for effluents from normal operation of SSES is done using XOQDOQ, a straight-line air flow Gaussian plume model designed to estimate average relative concentrations.

Tge model was developed in accordance with Regulatory Guide 1.111.Calm periods are distributed as the first non-zero wind-speed class in the input joint frequency distribution file.XOQDOQ uses terrain correction factors to account for the temporal and spatial variations in the airflow in the region, since a straight-line trajectory model assumes that a constant mean wind transports and diffuses effluents in the direction of air flow at the release point within the entire region of interest.The SSES terrain correction factors were determined by the ratio of the results of the stiaight-line model to the puff-advection model, and are incorporated into Table 22.38 TABLE 20 ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT METEOROLOGICAL DATA AVAILABILITY DATA PERIOD'995 PARAMETER PERCENT OF VALID HOURS DURING PERIOD 1.Wind speed a.10-Meter Sensors b.60-Meter Sensor g75 gg4 2.Wind direction a.10-Meter Sensors b.60-Meter Sensor gg4 99 5%I 3.Indicator of Atmospheric Stability (Primary Tower)a.Temperature Differential between 10 and 60 meters (Delta-TA) b.Temperature Differential between 10 and 60 meters (Delta-TB) c.Sigma Theta@10 Meters d.Sigma Theta@60 Meters 98 9%g87 50 1o/*50.1%*4.Percent of hours for which valid 10-meter wind speed, 10-meter wind direction, and temperature differential were available.

g6g 5.Percent of hours for which valid 60-meter wind speed, 60-meter wind direction, and temperature differential were available.

988%'Classification of atmospheric stability by sigma theta is the secondary method used at SSES.The input resolution of the Climatronic computer is reduced significantly by digital-analog conversion.

Halliburton-NUS began using the sigma theta values from Campbell's dataloggers effective July 1, 1995.39 FlGURE 6 CALM O.O.0 0 0 ANNUAL 8838 08S.mmH3 WIND DIRECTION FREQUENCY (PERCENT)~~MEAN WIND SPEED (MI/HR)].O-METER ANNUAL WIND ROSE-1995 FIGURE 6 CALM O.O 0 5 ANNUAL 8707 OBS.EKE WIND DIRECTION FREQUENCY (PERCENT)tZi~MEAN WEND SPEED (MI/HR)60-METER ANNUAL WIND ROSE-1995 Figure 7 ES PASQUILL STABILITY CLASS PREVALENCES Data Period: 1995 Based on Joint-Frequency Distributions at 10 Meters (8487 Hourly Values)Neutral 41 1%Slightly Unstable 4.6%Moderately Unstable 3.5%Very Unstable 5.3%Very Stable 7.1%Slightly Stable 27.1%Moderately Stable 11.3%42 Page 1 of 10J TABLE 21 JolNT WIND FREQUENCY DlSTRlBUTlON BY STABlLlTY CLASS PENNSTLVANIA POMER 8 LIGHT CO(PANT (PAL)-Susquehams Steie Electric Stetion 1/26/1996 TINE OF DAT: 13:51:57 PROGRAHI JFD VERSION(PC-1.2 PAGE 62 1995 Prietary Touer Data-33-Foot Level SITE IDENTIFIER:

DATA PERIOD EXAHIKED: 1/1/95-12/31/95 STABILITY BASED MIND NEASURED MIND THRESHOLD JOINT FREOUEKCT SPEED (NPH).SETMEEN 200.0 ON: DELTA T AT: 33.0 FEET AT:.50 NPH DISTRIBUTION OF MIND SPEED AND STABILITY CLASS A AND 33.0 FEET DIRECTION IN HOURS AT 33.00 FEET N NNE NE EKE E ESE SE SSE S SQl Ql MQI M MNM NM NNM TOTAL CALN.51-3.CO 3A1-6.70 6.71-11.20 1.21-16.80 16.81-22.40

>22.40 0 0 1 0 7 3 9 12 6 4 0 7 19 4 1 0 0 0 0'0 0 0 0 0 0 0 0 0 0 1 2 0 7 13 16 6 3 22 0 0 0 0 0 0 0 0 0 0 36 11 0 0 0 0 0 0 0 48 6 0 0 116 45 3 0 19 16 2 0 0 0 0 0 0 0 0 0 0 0 11 2 168 0 237 0 37 0 0 0 0 TO'IAL 3 16 32 10 12 5 14 18 38 47 183 67 5 0 1 2 453 STABILITY CLASS 8 AND 33.0 FEET SETMEEN 200.0 STAB I LITT BASED MIND NEASURED MIND THRESHOLD JOINT FREOUENCT SPEED (NPH)Nl: DELTA T AT: 33.0 FEET AT:.50 NPH DISTRIBUTIOH OF MIND SPEED AND DIRECTIOH IN HOURS AT 33.00 FEET S SQI N NNE NE ENE E ESE SE SSE Ql MQI M MHM HM NNM TOTAL CALH.51-3.CO 3.41-6.70 6.71-11.20 11.21.16.80 16.81-22.CO

>22.40 0 0 1 0 2 3 14 11 6 6 5 13 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 4 1 1 3 8 6 10 0 2 3 10 0 0 0 0 0 0 0 0 0 0 0 0 1 27 5 0 0 0 0 0 0 27 9 1 0 43 25 9 2'10 1 0 0 1 0 0 0 0 0 0 0 0 13 0 133 5 130 0, 18 0 1 0 0 TOTAL 8 27 18 6 8 5 14 10 21 33 78 45 11 2 4 5 29543 1

Page 2 of 10 TABLE 25 JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS PENKSTLVANIA POMER 8 LIGHT COIPANY (PPtL)-Susquehama Stelen Electric Station 1/26/1996 TIKE OF DAY: 13:51:57 PROGRAH: JFD VERSION: PC 1.2 PAGE 63 1995 Prisary Tater Date-33.Foot level SITE IDENTIFIER:

~DATA PERIOD EXAHINEDI 1/1/95 12/31/95 STABILITT BASED OM: DELTA T BETMEEN 200.0 MIKD MEASURED AT: 33.0 FEET MIKD THRESHOLD AT:,50 HPH JOINT FREOUEHCY DISTRIBUTION OF MIKD SPEED AKD SPEED (HPH)N NNE KE ENE E STABILITY CLASS C AND 33.0 FEET DIRECTION IN HCRIRS AT 33.00 FEET ESE SE SSE S SSM SM MSM M MHM NM KIN TOTAL.51-3.40 3.41-6.70 6.71.11.20 11.21-16.80 16.81-22.CO

>22.40 0 6 7 3 0 0 0 5 3 1 15 14 6 3 13 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 2 2 0 7 12'1 12 1 4 1 3 0 0 0 0 0 0 0 0 0 0 0 0 2 18 4 0 0 0 1 1 0 1 41 15 5 2 44 28 13 9 6 16 6 4 0 2 0 0 0 0 0 0 0 0 0 24 3 3 173 9 12 151 2 5 42 0 0 2 0 0 0 TOTAL 16 28 22 9 4 14 18 14 15 24 92 62 24 16 14 20 392 STABILITY BASED ON: DELTA T BETQEEN 200.0 MIND MEASURED AT: 33.0 FEET MIND THRESHOLD AT:.50 HPH JOINT FREOIEKCY DISTRIBUTION OF MIND SPEED AND SPEED (HPH)H NKE NE ENE E STAB I LITT CLASS D AND 33.0 FEET DIRECTIOM IM HQIRS AT 33~00 FEET ESE SE SSE S SSM SM Idyll M QKM NM KIN TOTAL CALM.51-3AO"3.41-6.70 6.71-11.20 11.21-16.80 16.81-22AO

%22AO 31 51 88 69 107 123 157 172 66 45 104 51 30 5 10 9 1 0 0 1 0 0 0 0 0 0 0 0 0~0 62 32 9 0 0 0 82 67 51 76 113 79 24 17 18 1 2 4 0 0 0 0 0 0 66 115 18 0 0 0 40 26 12 9 1C5 99 78 66 133 119 111 92 23 69 56 15 0 C 4 0 0 0 0 0 4 66 140 13 0 0 0 9 774 66 1498 111 992 19 213 0 8 0 0 TOTAL 267 260 290 140 163 103 183 199 152 199 341 317 261.182 223 205 3C85

Page 30f10 TABLE 21 JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS PENNSTLVANIA POMER 4, LIGHT C(BLPANY (PP1L)-Suaquehama Stean Electric Station 1/26/1996 TIME OF DAY)13~51!57 PROGRAM: JFD VERSION: PC-1o2 PAGE 64 1995 PrimarY Tour Data-33.Foot Level SITE IDENTIFIER:

DATA PERIOD EXAMIKEDI 1/1/95.12/31/95 STABILITY BASED MIND MEASURED LIIND THRESHOLD JOINT FREQUENCY SPEED (HPH)BETMEEN 200.0 ON: DELTA T AT: 33.0 FEET AT:.50 HPH DISTRIBUTIOH OF MIND SPEED AND STABILITY CLASS E AND 33.0 FEET DIRECTION IN INRIRS AT 33.00 FEET N NNE KE ENE E ESE SE SSE S SSM QI MQI M MNM NM NNM TOTAL CAN.51-3.40 3.41 6.70 6.71-11.20 11.21-16.80 16.81-22.40

>22.40 27 77 180 39 76 54 12 3 8 0 0 0 0 0 0 0 0 0 228 185 21 2 1 2 0 1 0 0 0 0 114 2 2 0 0 0 115.117 28-35 4 20 0 6 0 0 0 0 128 67 23 3 0 0 136 160 18 0 0 0 50 140 , 27 1 0 0 12 6 54 25 16~3 2 0 0 0 0 0 5 11 1 0 0 0 0 4 4 1388 12 26 752 0'144 0 1 14:0 0 0 0 0 0 TOTAL 78 156 242 250 190 118 147 178 221 314 218 84 34 17 16.35 2298 STABILITY BASED ON: DELTA T BETMEEN 200+0 LIIND MEASURED AT: 33.0 FEET MIND THRESHOLD AT:.50 MPH JOINT FREQUENCY DISTRIBUTIOH OF MIND SPEED AND SPEED (MPH)H NNE NE ENE E STABILITY CLASS F AND 33.0 FEET DIRECTION IH H(AIRS AT 33.00 FEET ESE SE SSE S SQI QI MSM LI MHM NM NNM TOTAL CALM.51-3.40 3.41.6.70 6.71-11.20 11.21 16.80 16.81.22.40 i22.40 2 18 104 7'5 2 0 0 0 0 0 0 0 0 0 0 0 360 190 47 3 0 0 0 0 0 0 0 0 63 1 0 0 0 0 31 28 30 22 1 1 2 12 0 0 0 0 0 0 0 0 0~0 0 0 0 0 0 0 1 9 0 2 1 0 0 860 8 0 1 0 0 2 95 0 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0, 0 0 0.0 0 0 0 TOTAL 11 23 109.407 193 64~32 29 32 34 17 0 3 1 0 2 958 45

Page 4 of10 TABLE 21 JOINT WIND FREQUENCY DfSTRIBUTlON BY STABlLITY CLASS'PENNSYLVANIA POMER 8 LIGHT CNIPANY (PAL)-Susquehama Stean Electric Station 1/26/1996 TINE OF DAY: 13:51:57 PROGRAM: JFD VERSIDHI PC 1.2 PAGE 65 1995 Prissry Teer Data-33-Foot Level SITE IDENTIFIER:

DATA PERICO EXAHINEDI 1/1/95-12/31/95 STABILITY BASED MIND MEASURED MIND THRESHOLD JOINT FREOUENCY SPEED (HPH)STABILITY CLASS G AND 33.0 FEET OH: DELTA T BETMEEM 200.0 AT: 33.0 FEET AT:.50 KPH DISTRIBUTION OF MIND SPEED AMD DIRECTION IN H(RIBS AT 33.00 FEET N HHE NE EHE E ESE SE SSE S SSM SM MSM M MNM NM NNM TOTAL CALH.51-3.40 3.41-6.70 6.71.11.20 11.21-16.80 16.81 22.40>22.40 1 12'5 0 1 3 0 0 0 0 0 0 0 0 0 0 0'358 36 0 0 0 0 82 1 0 0 0 0 21 5 2 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 1 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 564 0'(.42 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1 13 78 394 83 21 5 2 4 2 1 1 0 0 0 1 606 STABILITY BASED OH: DELTA T BETMEEH 200.0 MIND MEASURED AT: 33.0 FEET MIND THRESHOLD AT:.50 NPH JOIN'I FREQUENCY DISTRIBUTION OF MIND SPEED AND SPEED (NPH)K NHE KE ENE E STABILITY CLASS ALL AND 33.0 FEET DIRECTIOH IN HRIRS AT 33.00 FEET ESE SE SSE S SSM SM MSM M MNM NM MKM TOTAL CALH.51.3.40 3.41-6.70 6.71 11.20 11.21-16.80 16.81-22.40

>22.40 61 181 130 12 0 0 158 454 277 271 87 66 1 0 0 0 0 0 1018 574 188 64 10 13 0 2 0 0 0 0 268 50 12 0 0 0 240" 219 132 179 40 44 1 8 0 0 0 0 214 186 76 7 0 0 56.0 0 0 101 40 410 183 363 233 56 113 0 7 0 0 20 110 139 65 4 0 16 8 79 84, 104 151 19 15 0 0 0 0 1 14 3634 99 2861 132 1656 25 324 0 11 0 0 TOTAL 384 523 791 1216 653 330 413 450 483 653 930 576 338 218 258 270 8487 46 Page 5 of 10TABLE 21 JOINT WlND FREQUENCY DlSTRlBUTlON BY STABlLITY CLASS PENNSYLVANIA POKER 8 LIGHT C?NIPANY (PPCL)-Susquehama Steea ELectric Station 1/26/1996 TIHE OF DAY?13?51?57 PROGRAM?JFD VERSION?PC-1.2 PAGE 66 1995 Prie?ery To??er Data-33-Foot.level S!TE IDENTIFIER?

DATA PERICO EXAHIKED?1/1/95-12/31/95 ANNUAL STABILITY BASED DM?DELTA T'ETlJEEN 200.0 AND 33.0 FEET MIKD MEASURED AT: 33.0 FEET HIND THRESHOLD AT:.50 MPH TOTAL MLNBER OF OBSERVATIONS?

8760 TOTAL MQOIER OF VALID OBSERVATIONS?

8487 TOTAL NIRGIER OF HISSING OBSERVATIONS:

273 PERCENT DATA RECOVERY FOR THIS PERIOD?96+9 X HEAH MIND SPEED FOR THIS PERIOD?"4.9 HPH NINSER OF OBSERVATIONS VITH BACKUP STABILITY:

TOTAL M?RU?ER OF OBSERVATIONS KITH BACKUP DATA: 0 0PERCENTAGE OCCURRENCE OF STAB ILITT CLASSES A 8 C D E F G 5.34 3.48 4.62 41.06 27.08 11 29 7.14~DISTRIBUTION OF lllKD DIRECTION VS STABILITT H NKE NE ENE E ESE SE SSE S SQI Ql USU U IJKM MU NMU CALH A 8 C D E F G TOTAL 3 16 8 27 16 28 267 260 78 156 11 23 1 13 384 523 32 10 12 18 6'22 9 4 290 140 163 242 250 190 109 407 193 78 394 83 791 1216'53 5.14 5 14 14 18 103 183 118 147 64 32 21 5 330 413 18 10 14 199 178 29 2 450 38'7 183 21 33 78 15 24 92 152 199 341 221 314 218 32 34 17 4 2 1 483 653 930 67 45 62 317 84 0 1 576 5 0.0 11 2 0 24 16 0 261 182 0 34 17 0 3 1 1 0 0 0 338 218 1 0 47 V

Page 6 of 10 TABLE 2$JOINT WlMD FREQVEMCY DfSTRlBVTlON BY STABlLITY CLASS PEKNSYLVANIA POMER C LIGHT C(N(PANT (PAL)-Suaquehsma Stean Electric Station 1/26/1996 TIKE OF DAT: 13t54(54 PROGRAH: JFD VERSIONI PC 1.2 PAGE 62 1995 Prieary Touer Data-200.Foot Level SITE IDENTIFIER-DATA PERICO EKAHIKEDI 1/I/95-12/31/95 STABILITY BASED Ml KD HEASURED MIND THRESHOLD JOINT FREGUENCY SPEED (HPH)Ok: DELTA T BETMEEN 200.0 AT: 200.0 FEET AT:.50 HPH DISTRIBUTION OF MlkD SPEED AND STAB ILI TY CLASS A AND 33.0 FEET DIRECTION IN HOURS AT200.00 FEET N NKE NE EKE~E ESE SE SSE S SQI Ql MQI M MKM NM KNM TOTAL'ALH.51-3AO 3.41-6.70 6.71-11.20

'1.21-16.80 16.81.22 AD>>ZZAO 0 0 0 4 2 2 5 10 3 1 0 11 24 2 2 0 3 5 0 0 0 0 0 0 0 0 0 0 0 0 1 4 0 0 0 0 0 1 0 2 6 9 8 8 19 4 12 17 0 2 1 0 0 D 0 0 0 0 0 0 17 3 0 0 D 1 75 48 2 0 0 0 57 47 6 0 0 0 7 15 0 0 0 0 0 1 0 0 0 0 0 8 67 204 153 25 1 TOTAL 2 19 39 9 5 5 11 14 29 46 156 114 8 0 0 1 458 STABILITY BASED MIND HEISURED MIND THRESHOLD JOINT FREQUENCY SPEED (HPH)ON: DELTA T AT-200.0 FEET AT:.50 HPH DISTRIBUTION OF MIND SPEED AND SETMEEK 200.0 STABILITY CLASS 8 AND 33.0 FEET DIRECTIOH Ik HOURS AT200.00 FEET N kNE kE ENE E ESE SE SSE S SQI Ql MSM M MKM NM NNM TOTAL CALN.51-3.40 3.41-6.70 6.71-11.20 11.21-16.80 16.81-22.40

>>22.40 0 2 2 7 18 12 6 0 0 0 0 0 2 2 3 6 0 0 0 0 0 0 0 0 1 2 2 6 6 0 0 0 0 0 1 1 1 13 6'4 11 0 1 0 0 2 0 10 1 41 29 14 23 2 7 0-0 0 0 6 10 0 1 0~0 1 0 0 2 1 1 0 0 0 0 0 0 13 0 55 1 142 3 76 0 10 0 1 TOTAL 11 26 21 5 8 5 9 10 12 35 69 60 17 2 3 4 297 48 Page 7 of 10 TABLE 2l JOINT WlND FREQUENCY DlSTRIBUTlON BY STABlLlTY CLASS PENNSYLVANIA POMER 8 LICHT COMPANY (PPAL)-Suaquehamn Steie ELectric Station 1/26/1996 TIKE OF DAY: 13:54154 PROGRAM)JFD VERSION(PC 1+2 PACE 63 1995 PriaarY Taer Data-200-Foot Level SITE IDENTIFIER:

DATA PERICO EXAKIKEDt'1/'I/95 12/31/95 STABILITY CLASS C AND 33.0 FEET STABILITY BASED MIND MEASURED MIND TKRESKOLD JOINT FRNUEKCY SPEED (MPH)BETMEEN 200,0 OM: DELTA T AT: 200.0 FEET AT:.50 KPH DISTRIBUTION OF MIND SPEED ANO DIRECTIOH IN IKXIRS AT200,00 FEET H KKE NE EME E ESE SE SSE S SQI SM MQI M~MKM MM NKM TOTAL CALM.51.3.40 3.41-6.70 6.71-11.20 11.21-16.80 16.81-22.40

%22.40 0 0 5 2 4 2 8 9 2 4 5 17 9 1 0 7 6 0 0 0 0 0 0 0 0 0 0 0 0 0 2 1 3 4 4 6 0 2 0 0 0 0 2 1 7 9 7 1 4 0 1 0 0 1 0 5 20 11 34 1 13 0'0 0 0 1 0 0 0 0 19 6 6 2 1 2 90 31 15 7 V 6 164 31 11 8 4 12 1)0 10 6 0 0 0 18 4 0 0 0 0 4 TOTAL 14 31 23 5 8 9 13 14 22 18 68 83 38 17 12 20 395 STABILITY BASED Ol: DELTA T BETMEEN 200.0 MIND MEASURED AT: 200.0 FEET MIND THRESHOLD AT:+50 KPH JOINT FREOUEHCY DISTRIBUTION OF MIND SPEED AMD SPEED (KPH)M NNE KE ENE E STAB I L'I TY CLASS D AKD 33.0 FEET DIRECTIOH IH HOURS AT200.00 FEET ESE SE SSE S SSM QI MQI M MNM NM MKM TOTAL CALM.51-3.40 3.41 6.70 6.71.11.20 11.21-16.80 16.81 22.40>22.40 4 38 48 90 124 131 31 34 1 1 0 0 60 51 29 83 59 44 124 34 23 20 4 10 3 0 1 0 0 0 25 42 20 6 0 0 35 29 29 44 55 46 46 83 57'12 13 18 3 2 6 0 0 40 60 46 35 0 0 21 7 134 69 102, 151 59 174 4 52 1 4 7 5 3 40 16 25 123 134 138 102 51 49 56 8 1 5.~0 0 0 4 387 23 878 121 1457 62, 680 2 140 0 11 TOTAL 208 294 290 148 107 93 140 182 157 181 321 457 333 214 216 212 355349 Page 8 of 10 TABLE 21 JOINT WlND FREQUENCY DlSTRlBUTlON BY STABlLlTY CLASS PENNSYLVANIA POMER 8 LIGHT C(NIPANY (PPCL)-SIFJeh~St++0 Electric Stetim 1~/I TINE OF DAY: 13:54:54 PROGRAH: JFD VERSION(PC-1.2 PAGE 64 1995 Prienry Toeer Dote-200-Foot level SITE IDENTIFIER:

DATA PERI(O EXAHINEDJ 1/'I/95-12/31/95 STABILITY BASED MIND HEASURED MIND THRESHOLD JOINT FREOUENCY SPEED (NPH)DKt DELTA T BETMEEN 200.0 AT: 200.0 FEET AT:.50 HPH DISTRIBUTION OF MIND SPEED AND N KNE KE ENE E STABILITY CLASS E AKD 33.0 FEET DIRECTION IN H(RJRS AT200.00 FEET ESE SE SSE S SSM QJ MSM M MKM NM NNM TOTAL CALH.51-3.40 3.41-6.70 6.71-11.20 11.21-16.80 16.81-22.40

>>22.40 23 72 114 69 46 41 170 99 42 19 26 57 40 10 3 4 9 13 2 2 0 2 1 0 1 0 0 0 0 0 37 42 14 37 0 18 1 3 1 1 0 0 43 52 36 62 30 64 12 27 8 9 3 0 42 79 94 34 5 0 31 12 4 2 5 106 51 16 10 14'128 132 31 15 16 42 91 6 0 0 3 4'0 0 0 0 3 0 0 0 0 3 597 9 805 18 682 2 248 1 36 0 6 TOTAL 94 310 267 123 71 53 101 132 214 254 310 293 57 27 35 33 2374 STABILITY CLASS F AKD 33+0 FEET STABILITY BASED Ml ND HEASURED MIND THRESHOLD JOINT FREOJENCY SPEED (HPH)ON: DELTA T BETMEEN 200.0 AT: 200.0 FEET AT: 50 HPH DISTRIBUTION OF MIND SPEED AND DIRECTIOK IN HOURS AT200.00 FEET N NNE NE EKE E ESE SE SSE S SQI SM MSM ll MNM KM NNM TOTAL CALH.51-3.40 3.41-6.70 6.71-'11.2D 11.21-16.80 16.81-22.40

>>22.40 16 66 107 59 37 33 203 63 18 8 5 9 4 1 D 1 0 0 0 0 0 0 0 0 0 0 0 0 0'36 7 1 0 0 0 29 25 18 6 8 21 3 3 3 0 0 0 0 0 0 0 0 0 18 35 1D 0 0 0 0 10 4 0 2 2 2 431 35 10 2 1 3 5 458 11 19 4 0 0 2 75 1 10 0 0 0 0 12 0 0 0 0 0 0 0 o 0 o o o o o TOTAI.55 278 174 7S 45 44 3S 36 42 63 57 43 6 3 5"9 976 50 t h Page 9 of 10 TABLE 21 JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS PENNSTLVANIA POMER t LIGHT CNIPANY (PPSL)-Susquelema Stean Electric Station 1/26/1996 TIKE OF DAY: 13:54t54 PROGRAM(JFD VERSION: PC 1.2 PAGE 1995 Prieiry Tamr Date-200-Foot Level SITE IDENTIFIER:

DATA PERIOD EXAMINED t 1/1/95-12/31/95 STABILITY BASED MIND MEASURED MIND THRESHOLD JOINT FREOUENCY SPEED (KPH)OK!DELTA T BETMEEN 200 0 AT: 200.0 FEET AT:.50 KPH DISTRIBUTION OF MIKD SPEED Ni STAB I L I TY CLASS 0 AND 33aO FEET DIRECTION IM NOURS AT200+00 FEET K NKE NE EKE E ESE SE SSE S SSM SM MSM M MKM NM CALM.51.3.40 3.41.6.70 6.71.11.20 1.21.16.80 16.81.22.40

>>22.40 3 36 62 32 24 29 159 65 8 8 2 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 28 5 1 0 0 0 17'3 8'0 2 0 0 0 0 0 0 8 17 0 0 0 0 1C 17 2 0 0 0 1 1 0 0 0'0 0 0 0 0 0 6 1 1 14 2 4~3~0 0 0: 0 0 0 0 0 0 0 0 0 0 TOTAL 34 198 127 40 32 34 25 23 25 33 21 6 1 1 5 1 STABILITY BASED ON: DELTA T BETMEEN 200.0 MIKD KEASURED AT: 200+0 FEET MIND THRESHOLD ATt ,50 KPH JOIN'I FREQUENCY DISTRIBUTION OF MIND SPEED AMD SPEED (KPH)M KNE NE EKE E STABILITY CLASS ALL NN 33.0 FEET DIRECTION IM HQNS AT200.00 FEET ESE SE SSE S SSM SM MSM M MN'M NM NKM TOTAL CALM.51.3.40 3.41-6.70 6.71.11.20 11.21 16.80 16.81 22.40>>22.40 46 212 350 219 144 158 637 336 135 90 168 246 213 48 28 45 58 38 6 12 1 3 4 0 2 0 0 0 0 0 130 79 26 7 1 0 125 113 110 116 105 118 162 218 84 136 145 191 19 31 65 98 C 10 18 7 0 3 1 0 70 25 336 1C2 392 413 186 376 17 88 1 12 12 10 64 30 181 156 135 60 62 8 6 0'11 9 47 41 163 148 54 79 1 3 0 0 0 1702 2698 2738 1269 229 23 TOTAL 418 1156 941.408 276 243" 337 411 501 630 1D02 1056 460 264 276 280 8659 51

Page 10 of 10 TABLE 21 JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS PENNSYLVANIA PONER 8 LIGHT UNIPART (PPSL)-Susquehanna Stean Electric Station 1/26/1996 TINE OF DAY: 13:54:54 PROGRAH'FD VERSIONF PC 1.2'AGE 66 1995 Priaery Touer Data.200.Foot level SITE IDENTIFIER:

DATA PERIOD EXAHINED: 1/1/95"12/31/95 ANNUAL STABILITY BASED ON: DELTA T BETNEEH 200+0 AND 33.0 FEET llIND HEASURED AT: 200.0 FEET IIIND THRESHOLD AT:,50 HPH TOTAL NQISER OF OBSERVATIOHS:

8760 TOTAL NNBER OF VALID OBSERVATIONS:

8659 TOTAL NINBEB OF HISSING OBSERVATIONS:

'101 PERCENT DATA RECOVERY FOR THIS PERIODt 98.8 X IIEAM MIND SPEED FOR THIS PERIODs 7.4 HPH Nat&ER OF OBSERVATIONS MITH BACKUP STABILITY:

TOTAL NOSER OF OBSERVATIONS IJITH BACKUP DATA: 0 0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A 8 C D E F G 5.29 3 43 4.56 41.03 27.42 11.27 7.00 N NNE NE ENE DISTRIBUTION OF HIND DIRECTION VS STABILITY E ESE SE SSE S SSM Ql llQI II NNN NN NNN'CAUI A B C D E F G TOTAL 2 19 39 11 26 21 14 31 23 20&294 290 94 310 267 55 278 174 34 19&127 418 1156 941 9 5 5~148 123 78 40 408 5 5 8 5 8 9 107 93 71 53 45 44 32 34 276 243 11 9 13 140 101 38 25 337 14 29 10 12 14, 22 182 157 132 214 36 42 23 25 411 5D1 46 156 35 69 18 68 181 321 254,310 63 57 33 21 630 1002 114 8 60 17'83 38 457 333 293 57 43 6 6 1 1056 460 0 0 2 3 17 12 214 216 27 35 3 5 1 5 264 276 0 4 0 20~0 212 0 33 0 9 0 1 0 280 0 52

'

Page1 of 15 TABLE 22 AVERAGE ANNUAL RELATIVE CONCENTRATIONS 8>avaaaa~Ct~tlaacala Ccaclva~NO&i'LEVEL

&ELfdCE CZ&CECTED IN COCO Ttl&ll&&ECICCI&ATNN VCI&0 CTCCI6L Tf~lo lOAAW 1 E6CTI&$&EL&TIVE OETNITIOI CE&NIT i&f4~.ZI AT El)to OOICTC CT Ca&lb/INI CECTC&$D I ClCT I Oa~OIST6&CES 1$&ILES TCCV Clif 1,00 1.50 g.oo 2.50 3AO 3.50 i,DC 4.154E 08 2.1Qf N 1,1)TE.N 4,$7IE 09 3 244E 09 I OITE 09 T,Z)6EM$>)17%10$.726E 10 4.2)CE 10).ZIIC IC&.WE 08'Z.hof>CO I.LOM 00$,7$$%49 4.57IE 09 2 Tgbf 09 1&IZE 09 I TOTE 09$,0$4E~10 5 908E 10 4.LODE~IC 1,02)E.07 3,50if.o&Z.DZLE N I,ZLM.N 4.139%09)A5if'09 2,42M 09 I Qh 09 I~147%>09$.477t 10 4AOCC~IC I.Qdf 07 5~107t'$0 3.17ot 0&Z,OBE N 1>OZCE>N 4.540f 09 4&LE>0$2>'llof 09 Z.N'09 1.5)9%09 I.ZDM 00 I DZIE>07 3>496E 0&I$0)f'N I,NOf 08 4.974EW 2.916E 09 I.OOLE N I 2672M$.777%10 4ACZE 10$.1)it IC 5.7QE N T.OLSE N 1 OLDE>N 4.170040 3,11M%1$22C+1'l)M 09$.07M 10 5>'740%10 4.410%10).4)OE~IC&A5if OS 2.$$9E 0$1,)dbf 00 O.ZZM 09 4AQE~Z.ZQC 09 1,&ill 09 1,268%09 9,)04E~10 7.092E 10$.$2$E IO 7,21M N 2.$96E'N lAL)t>08 9,$2)t'09 4.$)M49 2.7QE 09 1ALDE 09 I Zbdf'09 0.77M 10 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4>tME>12 IA4IE'IZ d.hlf I)Z,&ICE.T)I~752E I)1.05of.1)$.$66C Ii SCV)SOLE 10 I 38)f~10 7.0%DE~11 Z.OO)E I'I&.Nlt 12 Z.TOTE>IZ I.ZZCE 12)>$)6E.I)2.)bdf I)9.5)CC 14 7.77)E Ii S.IZTE 10 Z,IZCC 10 1.072%~10 2.76LE TI I,gggf Il 4 96N 12 ZAZTE'll 1,276E.IZ$.12OE~I)4.)gif~1$3.$)OE 0 VTv O.dhf 1D 4.IZM'ID 2,0)M 10 4.90)E.IT 1,97&t'll 4,)OIE 12).009E'l2 T>OTIC 12 5.SLOE I)2.214E I)'I$09E'I)L.IZZE 10 IABE~10$.076E~11 I,9)IE 11 7.17IE 12 1.7&ll 12$.952C.Q 2,Clif 0 I,690f I)$.9)IE Ii 4.$57%Ii 2>TQC 10 I,ZDM'ID 4.229E~11'IAQE 11 7,4$0C 12 2,4'IOE~12 I 0)gf 12'1,45gl I)7,529E Ii ZAobl 14 I,obif N aV iACIE 10 1,99M 10 I,DSLE Io)AOZE 11 1,260C 11 3,491C~12 1,5BE 12)ABt I)IA&LC Q 7,)gbf Ii 4.IQC~Ii iAL9C~10 2.202%'Io I.LL&c 10)A14E~11 I>Bdf'll 4.049E>12 2 2$4t'Ig I~TCCE 12&472l I)),ZCOE~I)2.477%I)4$)ZE lo Z.TQE~10 I)CDE'IO 3.)hf 11 I,49M I'I 4,109E~IZ g,QIE'12'9,211E Q 4,9)CE 0 Z,ZODE'I)I,796E I)aal 4.44LE 10 3.029%10 1.5LSE~ID 4.211E~11 1.699E 11 5.497%12 2.9)LC 12 I.ZLSE.IZ 7ALCE I)6.14LE~I)).)99E 0 VE 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I.OLII'Oa$.277E~IO).Zoii~IO'I.ZTM IO Z,balf~II$.$)bc~12 1,186E'T2).Ollf I)CII 6.8oic Oa 1.&die.oa 4ALTI Io).281%10 I T)lc~IO$.9lic IL 1.141%LI 2.5751 17 iAOIL I)$,207%Ii II 7.986C'Oa 2.42IC'Oa 8.6171'10)Alii'10 I,ab)I IO 4.liOE II'I,IL)C'll 1,48)I 12 Z,SSIC~I)i,IIOC~Ii TII 8.9$$C Oa Z.STII'Oa 9.7iic'Io aA671 IO 2.)VM'lb 7,64CE II 1,)4&C 11 2,049C 12).62OC 1)9,2)M Ii vcaI ue wILolar aaaaacrcaLI acLclII acliaI IacTC65I'9.40 aca.viva acliaf Iacccal)10.0 olaaccca (aclcas>,00 wlio lac aclbaI IICTECII 41,S CCII VCLOCIII Ia/ICC I~00~OLOi.via.c&5.8CC lail ICO.OETECII 257$0 aclI CalllIOI&ill Icli/llc)0 lI Iac ccifllc belial: lI Ial acdIL&co vlao aflcaI I 10.0 vclcasI: VIVI acillsc scot vlao Crcco Iaccl~I/Lcca I VI~I&cccdLC Iaec vlao Callo La&If&8/Ccc) vlao Cafco IIocc&8/CECI I Slllcl I&xlITIOVS va5168LE/acvI&6L cool TIOVL Eclvllco LETS Iaaa ooo T cclvlTCD Ltll Taaa Dco cell I ala,ooo a I llo~EII&ca.000 aaa 000]vlaco'EIL&la 000 do 000 Cccvlla,ooo Jc\,000 cacaao Llvci dbovc 000 (caolo LlvEL b&o/c 000 dbovc 53 T

Page 2 of 15 TABLE 22 AVERAGE ANNUAL RELATIVE CONCENTRATIONS Stats)kssste

$14N EIskt/lc Statist~Ctckto LEVEL aCLCASE 8,000 DAT DECAT, CICafeTED H%est s Tftakl8 afelaOAATIN VS)so SKCIAL Ttaalls DAN)ST%81 TACTNS A)st)AL AVfaACE ct)/0 Ifte/Kffa CNED)oil)itec I 8 DIKES CKCIN.2$0.500,750 1.000 1.$00 Z.NO 2,500).000).500 A.NN 4.50:$$$V SV lSV V Lk)V sv s ssf kf Ctf E Klf lf$$K I.DICE 0$).59CE~2.00?f~I.ZFCC~4.4I)E.OF).97)E.OF?.FOIE 07 I.SITE 07 IAOFE 07 9.9>>E.OS 7.4FR N 2 01$E'05 4A19E 04)4)if 04 2,25TE'04 I,?44K 04 8,00M'07 5,59?f 07),N)f'07?A64E 07 2,0)R'07 I$$7E'0 4.4)TE.OS USE 05 7,749E N 4,974K Ob?ATTE 04 I,TIAHS 1,21$f,ob O.bhf 07 4.)74E.OT 4.9>>t 07)A5)f 0.I,OCTE DL),2$9E 0$1.9)bf 0$I,ZTDC 05 7,001E Db Aa??ef Ob)5?SC'04 2.5)TE4d IAT)f Ob 1.50K vob 1.2)OC Da 4.ITDC 05 I>8)bf 0$9.)TSC 04 5.74)Hb 2.974E 04 Isot)HS IL)?TE 04 9.5TM'07 4+8)AE 07 5 Am'07 4)ASE'OF 2 8$5f'05 oeb))f'N 4.4$CE 04 t 9>>K'Ob IAI?f 04'I 0)5C~Too)SE 07 5 04?E 07).741K 07 2.9OLK 07?.4?if 07?ASOE'05 8 901E Db S>>TE~),185K Ob I 744C&I,ODR&7,400fi07 5,544E 07 4,21$l 07))'IR'07 ZASaf'07?,INE 0$F,?FOE 04 4?SIE 04 2.990C45 1,557C 04 9.N?C 07 7 DICE 07 4.948K 07)AOTE 07 2.9$$K'07?,446E'07 2.>>?f'05 4 4)at&).576t Ob 2,?OR.DD I,tbf f Ob 8,)tec 07 b,)OTE 07 4.SIDE 07).)$?f 07 2.714K 07 Z.?4?f 07 2.419K'05 8.47)f Ob 4.7)9E Ob).tlif Ob IAIOC'Ob I,I?bf~8.24)f 07$.908K 07 4.405K.DF).579K 07 2.945K'07 IA5'R.05$,9$4C 04 W50E Ob 2,095K Ob I~140K 04 7,4TDE 07 5,$6?E OT 4,NTK OT),Okaf 07 2$)LE 07 Z.>>tf 07 I 004K'05)DISC'04 1,641K'Db lot)?f Ob 4AOIC'07 AeICTE 07)015K 07 2,2$?f 07 1,75ZI'07 I 444C 07 l,?2?f 07 A.oabf'04 2.05R Ob l,>>il 04 4.566E 07),)blf 07 2 Il)f 07 IAAAC 07 I.o)CC 07 7)LICK OS 4 0$$E'N 4 906f'N A.OLDE.N IAI?l 04 O.TOIC'07 5~IT)f 07 2.5SZE 07 1,$?CC 07 9.N)HS 7.00?K CO)e)?OE N)Tabf N 2.850K'N 4.54?f Ob 1.544K N 9.00?f OF$.7)bf OF 2.8$TE 07 1.7?8t OF 1.149C 07 7,57M.OO S.I)CE N),716C N 2.7?SK>>N 5AAOK Ob 1.999K 04 I,I)CC Ob AA9$E.OT Mbf 07 2,100E 07 1A41C 07 1,0'1?f 07 7 2$R N 5 t?N'N).T)aE'N Astk)AL AVKAAAK et I/O Ilfe/ICTEA OCKD)DISIASCC IS SILfl SKAAISC 5.000 7.5N 10.000 1$.000 20.000 lb.CO)0,000)$.000 40.000 ili000 SO.OOO AI Ikf tIIKAIE sf)catt VIS)AKLIAIK ISOI VIV)SFKID IKII~Illfe)LESS 1sAs SCILCI a AAOVK 6'4.2?TC'CO 2.4NC'N Io?4)E'N?ACTE'09 I~)?OK~)ACDI 10 I.NTC'10 7.9?CE'>>5.0>>E>>).044K v>>2.516K>>$$V I ZTR'07 5,470K 08 2,8)FE'N 8,$>>l 09 SACR 09 Io?OIC 09 SAIOCvlo IAISE 10 1,1$5E 10 4.71)f 11),9?of>>).)DIE 07 TANK 07 F.TIR 08?,I?Of 08 9,9??f 09 4~.09 2~09 1.17af.ol T,T?iE.IO 4,?)of.10).559K~ID I 0))f 04 5,NAC 07 2 4TR'07 7 OOIK 08)Oaef*N'I 0)Rkg 5)SSE'09 1.9$4E 09 I,Dail 09 i,)ICC 10)A)AE~10)ALCC'07 I Nkf'OT WOi%08 2'I)DI 08 8,)IN 09?,IDLE&I ISIC 09),84?E 10 2,0$8f ID 8.4$9I>>7,06?f.>>2 OITE'07 9.4TTC'08 5 1$OE OI I.b?CE 08 7.0?tfi09 2,$DLE 09 I,DZSC 09 1.49$f 10 7.97)f>>2.4OE'>>2 INE>>2.?OCI'07 I.NFE 07$.497K 08 I,beef'N TiKC'09?IOQE 09 Debo)f 10 Za?OCE 10 Ie?>>f 10 AWE~11 baNTE'>>2.07$E O'F 1.044K 07 5.594K DC 1.FISC.OD 4.9?TE 09?,IAR.09 1,254C 09 ART?f~10)A?if.lo 1,9)iC~10 1.56)E.IO).994K.OF 1,)?OI 07 4.46$I CO)@DIE 08 7.785K 09)~09 1,57?t 09 5.251K~10 2.NZE~IO 1,$09f 10 I,NCE ID asl?.49R'DT 1,24TE 07 4,$?TE 08 I,CSCK N 7ATaf 09 2,4$$C 09 I,aobf 09 4.>>ll 10).Tell~10 Z,IS)f 10 I.TTIE~IO I,TCR 07 9,?9?f 08 S.OAR 08 1,794K 08 7,146K 09?,N?t 09 1,095K 09 4A87E 10 2,7)al 10').416E 10 1>>9E 10 Eaf I~0?kf'07 5.t$6E 08).ITSE N I.AASK'N 7 1)VK'09),T?TK 09 I,DIVC 09 8,$$5E 10 4 940K IO 2.$9$E 10 2 ISDI IO 4 N?I'N 1.99)f'08 I 04$1'08).46)f 09 1.74?I'09~.AISE'10 4.14?f 10 1.5$$f 10 0.7$6I'>>4.)ibf>>)$46E I'I CII 2.?8?I'N 8.945K'09 4.8??f 09 1,7'ISK~09 6.44?C 10 4,)CR 10 1,94IC IO 5.175K~>>?.7>>E~Il I.okaf>>'9,00LE~12$1?.1$9C'08 7.465K Dk 4 14'R 09 1.499C 09 SAT?I 10 1.776K.IO 6,)?TE~>>?ATIE I'I 1,)IFK I'I).4)R'1??.VOVE 1?$$1).DOLE'08 1,1?)I N$.96)f~09 2,0$)l De 8.)T?I IO?.)VII 10 1.$$7K~10 5,16)f~>>?,9??E~>>).4?CC>>I.llil>>Ca)/4 Ikle/K)fk eLCKD)Fok Cack IIOCSI tlc)CSI DOAOAk III IS SILKS DI IKCIIca.I~I I?)a 4$$19 Io?o"?0)O)040 4050<kN$>>I I?.0?9K'04 4.7?il'DF?.TDoc~DF I.SAII DF T.aoc 06 z.t)if N 4.19)f ov 4.94R 10 9.NSf>>).4))I>>$$v).44'Fl D4 1.?FII Oe$.$?DI DF 2.74?I DF 1.$9)I~DF$.91?f 08 1,04?1.06 1,$$FI~09 2A$4f ID 4A45K>>Iv 7.77)f Oa?.TeOK 04 1.20II Da 4.4711 DF$.9?DI~OF 1.$4$f OF 2.84?K.N 4.964K 09 1.$$)K 09 5.009E~10 VLv 1.9?6I 0$7.?$)f De).449K Da).9?)I~De I,Z)tf Da 5.176K OF 9.4?FK N 1,)FCC N Z.546K Oe$.SNK 10 9.7$)I De)~106K Oe 1.)??I Da 7.0?R DF 4.40)I 0)1.71?f OF?.9?SI~Db).4)II 09$.$49I~IO 1.1$if IO LSv 4.741K~De IA)ef Oa 7.04R~DF).8)SI'0)Z.ai?I'OF 9.996K N).999K'N)~I?OI'09)~7$9f'ID 4~Dilf'>>av$.099f'Oa I.FFAC~04 7.47?I OF 4.?$11~DF?.4441 DF 1.099K'OF 2,?OLK 08),01?I 09).OIOI'IO 4.'FAAE~>>aav i,)FII~De IA?af'Da 4.97)f'0)5~Fill'0)?Ae)1'OF).64LI'OF?.IFR 06).OFOI'$9 F?AR'10 2$$9I 10 a).40?l De l,?90f De 4.1)tf~OF)Aitf DF Z.?9)l'OF I~It)I'07 2.)97K 06).SITE 09 7.$iif 10 I.bsaf'IO aaI 4.89)I De I.T)tl De 6.'>>ll DF 4,$?DI DF?.9)?1 DF I.?eaf OF?,ioif 06).49ii 09 7.48R 10?.47$I 10 VI),$)CC'Oe 1.19)1'Oe$.$$'R~0)$,1)VK 0)?.11)l~OF 9.)IDI'N?,OLR 06).OITK 09$.7)R~10 1.719K 10 IVI I.VOII Oa 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Page 3 of 15 TABLE 22 AVERAGE ANNUAL RELATlVE GONCENTRATlONS Saao)aavvae 5(eaa c(tc(FIC$(t()va-55(&at)Lfvt(&EL!A(t-199$2.240 DAV 0(CAT, Ieo(9(Knot Coat(CIED Iot (DKN nt&AIN&f01&(V(ATION ul)40 SDECIAL n&KAIN AouSTIOIT TACTMS ANNVAL Av(CAct cNIFO (Stcncnf ()e(D)OI SIAN(t IN 1)LE$SCCTN.2$0.$00.750 1.000-1.500 2.000 2,500).000).$00 eAOC i.jO" 5 SV VSV V W a NK Caf E ll($(Slf I 104E 05)9?bf 04 2?4)HS I 4n 04 1$)TE 07 4 77)t 47))Ill 07 ZAObf 07 Irbjlt 07 I trbf 07 I OOIE 0~Z.ISOE'05 7,0)lc'04 a,oadf 04 t,549E Ob I,agl 04 9.$9n 07 4.4(OE 07 b,ran~or),)94K 07?,409(07 t.o?b(OF 4 4&M'0$1.44lE'05 Lbbft N 5 bbot M)I)n~04 Z.Nn Oa 1,44LE 04 1.07$EvOI Lo(TE 07 4,244K 07 4.994(~0 I~Ian Oi).$41l'05?.)QC 0$1A45E 0$LIOM~Ob 5.4(&f Ob 4AOIE 04).I)of'M Z.)4(E oa Iootn Ob 1.59)K'Oe 4.51?t 0$t.ONC'05).OQE 05 4,5?SE 04)Arne t,tb)t~Isa)jtm I~$4(f Ob SA)5C 07 4.9)M'07)A)tt 07).OIM.0$9AIoc.oa i.toft ob).))Of~S.Njtm I.ZIMm 4,$4N 07 a.nol-or 4.74n 07).Stat or).)cot or).Deaf N O.ltn oa s.nit.oa)A?M-oa 2.0(ofm K>I)K-M 9.24?f-or 4.490E or$.)tot.or 4.?e?t or).44M or 2)OM 0$7Al5tvM 4.79OE 04).40)EHS TAZnW I.(9)t 04 4.574K 07 4.)QE 07 4.557E 07).7&at.or).?Oef 07 2 229C 05 7,0)IC 04 4 OOZE 04 2,$0)EM T,AME N I,o?IE~'F,TOFC~07 j,boet 07 4,2)jl 07).eeoc 07?.9>>K 07 2.417E 05 O.?alt 04 5.)lnf 04),bjtc IS 1,979C 04 IA49E~I,DOSE~7,)jjf 07 5.57n.or 4.59)t 07).4$4E'07 I 9$4C 0$4 il)l 04).74)t 04?AS)Em$.)doc~9A?of 07 4.4LM.OF 5.0ln.or).9?$C.DF).?4M 07 Z.rb)E 07'1.04OE'05

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cNED)01$)ANCE IN NILCS 5(it)ac-sAN r.joo Io.ooo ILooo to.ooo 25.000)0 LO 10?0 AI'Ia(t(LCA(f atliaI: Ka)t(llA(t)CO(VINO taf(D Iat)l~$/$(C)L?SLE 0$).419E 05 I.etn N 4.I)M'09 IrNFE~09 4.19(t 10).2)ft 10 IA14E~10 9.147t'll$.7'IaE.>>4.$?7E.>>I.brdf 07 7,54MiM 4,0bdf 0$I,tb)CNS$,5?ttk8 I,Mat,ot 9,5(n 10);)eet 10 2,0(TE 10 4,$10E~>>7,19$C>>SV 4 14$C 07 too)M'0l I'099t'07),190(05 I SSSC'04 4A)ff 09),erefi09 1.99ef 09 IA)lf 09 7 e?OE 10 4.29?E~10 I)jiE 04 4.94M.OT).799E 07 I,ojlt 07 4,754C 0$1A4M 0$e.~Inioo),teat'09 I WC'09 7 52$('10 4 41$(10 4.7(OK 07 2 t)M Or I.I)9K Or).ITIC.N IAOTE.N).5?jt Ol 1.49M.09 bajn.)0).$15t.)O I Aan.)O I.?elf~IO IVV L4iif OF I,)?at 07 7)Ibt.N t,eeoc 0$1 Ofef'04 4.0?st 09')A95(09 2,$17t'10 I S44C.ID 4.5(ot~II).4)bf.>>2.499K or I.ea(t or 4.>>SK o&?.Tiff o&I.)LM oo)erat oo I.saM.ol).455K.)o?.095(Io 4.boot>>7.)obf.>>2.7?rf 07 Isbn 07 7.990(0$2,$9IC 05 IAOI(N).5?n 09?,MOC 09 I,)en 09 4ATVE 10).40)t 10 2 4&M 10 t.4?M 07 1.~1)c 07 9.$49(0$Z.jaet ol I tts(.N 5.4(n~ZA)4E 09 9.01oc~10 5.MM 10?.mf 10'I.949f Io ea().?&M Or I,rirl 07 9,)$7(OS?,79et 0$1.l)lf 05 4,)rlf 09?A&Sf 09 I,obit 09 bA)iC 10 Leblt 10).?49E 10 2.)$4C 07 1.?90(07 7,)t)f 0$t,rbrl.N 1.1$9(M).521E'Do I 90)t 09 4AME 10 S.O)rt 10 t.477t'10?.trjf 10 la(l,)4IE 07 7,)?bf N AA\5(08 2,?)lf 05 I.)rn N 4,)ebt 09),571(09 1,52)t 09 9,)OFE~10 5,00of 10 i,tllE~10 (5.41$(M 2.777E 05 I.jil(M$.7?rt 09 Z,NM 09 I,lr\t.ol 7,)SLE~10?ADS(,ID I.el$E~10 5AOTE~>>7.>>OK.>>t(I),0?4(N 1,250(M 7,011(09?A4tt 09 1,)4?f'09 7 eee(10).4)5('10 OA))t>>5.057K~11 2 IolE~11 I 774(>>$(2 4)DE 05 1,07M 05 4.08)t 00 2,)i)C DO 9.4&)C IO).Obit 10 I.litt 10 5AZ)E>>2.$44(~11 7.145E~12~.058(~I?$$().95it M I.jrlf OS 5.7??f 09).?On'09 1.57?E~09 A.Tref~IO t.lIOC.ID 9.$0i(11 5.$19f>>2.7)Sf~>>?.))Lf.>>Cal/0 ($(CFIC)tt (Le(D)Iot CA(a$(ONNI$(ONNI SOAN)et)tl Ia NI(tl DIII ()loa,j I 2))e i 5$10 to)0 40.50 I)os>>II 5 t,?4tt Oe T.biH 07).?90(~OF I.eto(~0)1.01)l 0)).bi4(~CO 4,?)IC DO$.179f~10 1.'FAS(~10 4.41$(~>>$$v A.ob)f~Ce I.ll?I Oe d.riif OF).44)K OF?.049(DF 5.0llf 05 1.570(~05 t,jib(Oe i.jjif~10 1.157(~10 4.4$7f oe).?Iif.oe I.(7M De 4.1$)t 0)$.07$(DF?.Dtef 07 i.lie(ob 7.97)I 00?.?SDE 09 4.754(lo?.Iia('O)a.i)I(oe 4.?00(oe?.4?o(oe I.eo?(oe 7.014(0)),eoec~07 2.175E 05 4.?9)f 09 1.0?oc 09 v I,N)I 0$).41$(De).409(De 4AS)K 0)S.eel(DF Z.)1$E~OF l,?llt 05 5At?f~00 4.901(10 1.99n 10 mv$.?VVI Oe I.tol(Oe SASTI 0)eA?71'0)').)40(07)AS)f 07 t.l?eE Da A.ole(09 4.?on 10 4.95lf>>$.4&D('Oe?.04$('Oe 9.)lr('OF$.))bf'0)).475(07 I A9)t 07),t)$(05 4.799(~09 4,547(Io I 18?E~ID aav i.~Fi(oe 1.49M Oe 4.$0?(~OF e.r)9('OF).?Co(OF I.ill(07).1?l(08 i.'llM 09 I,t)jf 09 i 175(Io a i.o)l(Oe I.jol(Oe T,jji(0')i.)io(0)?.VTM OT)Alt(07).$?n 05 4.1in DV I,tieC 00).007(10~a(S.l)?I'Oe?.072('De 9.901(OF$.705('OF).ben OT I.r?5('07),$$)E Oa$,445('09 I,ttOE 09 4.472t)0

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I JZFE&O.cttt.or T.olbt 07 5.Q)f.or 4.)ebf 07,).$)SE~Or Z.sobf-of 7.9475.04 A.esot.oi).btsf-ob T.QTKm T.torte e.best.or 4.240K-or A.WOC Or).elec.or).tecf.or Z,zstt Of 7,0$IE 44 A,OTTERS Z,SZIE4d I 49)C4h T,ostt&TA17l 07 5.70M.OF AAZIE 07 3.$41f 07 2,947K 07'.42IE'0$OoteM 04 SAtet 04),blrt~04 I,OOLC4$IAQE~04 1,022E 04 TAllt.or SA75C.OF AAODE 07).eeet Or 1,<<of'05 4,5QE ob 3 rltf~2AObc 04 IAbec~O,tsec'07 4 9>>t 07 5~I)et~or),oert~or)o)IAE'07 t501$C'07 I.<<Ifiof)A)IC ob 2.090K 04 I.ANC 04 TAOC 07 S.OITKN).hsl 07 heLM 07 Z.thl'OF I.clot'Ol I.bzsf'Or 4AOIE.<<Z.test~.s.tfst 04 7.5)tt.or 3.947E M 2.$$4E~TI/TATLE 07 1.)lot 07 O.OLLE 00 7.91st'Oe 4.5'Ict N 5.22cf Ob 1.7444'04 9.07OE 07 5 915C 07).NOC 07 TASTE 07 TA)stool OA)OE N 4.$QC 05 A,osochl).resf N A.a<<ob I.h)c ob T.o>>fw 4.557K or)AAN.OF Z.Notm I Attf.or 9.$$Mm 4.402K.N A.efec.N).btoc oe S.OOIC 04 Z,TOOK@$1.249K 04 7A5LC 07)AZ1C 07 t,scot 07 TASK 07 1,27Ã07 9)tft 00 AAZM'00$.0>>i N braille AVttAct CAIIO ISEC/ICTft CNCDI olsrbact Ia VILCS~citlac 5,000 7,500 10.000 1$.000 20.000 25,<<0)0.000$5.000 40.000 45.000 So.ooo 10 20 ir Iat tILtAIC ACICVII VIVI ifttist ICDI VICl crttc IlCIItslstcl 5 4,ioet N),htt'N TAOTC'N 4,)TFE40 I.OQC4l 4AAOE~TO)A47E 10 T,QFK 10 T,NAC 10 4.<<lf>>$,9)of>>CCV 1.720E 07 FALSE De A.tfbf Oe TAATK&b,sect 09 ZAAN 09 1~119K 09).Tert~10 t.Q1E'10 T.NIC 10 9.$44C~TI SV 4.)lit 07 2.129K'07 I~149t 07 5.$ODC N 1.740K~7.902tH%A.bbbf 09 ZAFN 09 1.709K 09'9.<<ef'10 O.frsc 10 1.)Oct~04 7)>>E~or 4 ostt'07 I 157t'07 5AOIC 04 loof)t48 TAAOEM AA<<C'09 2.)lbf'09 I ooef'09 0 Qit'10 v A.Dolt or 2Azsf or I.tfot 07 3.522K.oe TAO)cw A.issfm 2AOSC-09 O.I)st.so 4.5hf.so I.OFDC.Io I.FZM.ID wv t,hit 07 T,)OZE'07 TAOOEW t 49IE'N'I tilt 04 4 hOEW Z,NOC 09)1$9C'10 1.771f'10 4.NOE>>S)ebf'>>VV Zeotl 07 I.SXR 07 eobtTK~N).oeebN S.ZOIE N 3.9)otioo SAFN+09 4,009K 10 ZAhl'lD 1.1lll 10 O.eccl 11 Z.Dort.or T.ftrt'0l~.44%'N Z.QSC~IS Toztbt.N A.crit N Z.AOOEW I.ADOC 09 O.AZSC~10 AAlrt'10).art 10 a ZAOOE 07 I,OTM'07 1,0>>E'07 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Ad>iooo clue LtvtL wovt.ooo I ctoao LEKL wovE.ooo Welf~000 56 I ll i g4 s" Page 5 of 15 TABLE 22 AVERAGE ANNUAL RELATIVE CONCENTRATIONS svvwevees sfew CL<<le f4 ffeffeeL Ncc)nc Do)sf l a)cfcsfsf Tftc Of OlsfCTMV 10 LDCIT)oe~LCNL NUIII~I sf aal S/4 g/0 S/0 4/I go)ul)Iaftss)gac/Ca~I)lggc/cf>>Jfnl) gac/a>>AKns)

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~/IUIea osevo Iles M Kfaef VKMI)1 If~<ef rf~I>'NLOCII~Ie/MC>4NIIAI~Aa)I Aa'TACTIC>>I.Nother)4)INDI r.))ran~.WC Ks 4.$$)CKO SANC Ka I~No OeffICKI IANCKI I,NICK>>t.)OMNI SASN~I IS)fKI LIMC~l.agcy')Agnes 4.07NAI I~KI SAOIC Ko.IAMI Ks I rancho Larnyx T.nn 07 IA07I 47 IATII 07 I.TIIIKI 2.)rnKK).)lQIAI I,tanKI T.N)IKO I.f)K oa I.tnl 0$a.frsl os 7.$)fl es a,l<<l Os).er)I 07 I.rfn<<).Ia)l os T.nn.07 l.tla 47 IAIII 47).I)SI 41'u)I.<<I.M)1 Os 4.)MI N~.)IN~IK'I.a)K N IA)N 04 s,a)K~1.)osl~or I.la)l er a.c)sl 07 I,SOLI 41).asa~07).feal Or).Tool ga S.TIII aa I.NN 07$.417I 07 I.I)N~I.taocAI LTONAI IAIICAI t.sate Ao S.SSNAS I.af)C Ds 4,)ISI a S,TSN Oo 5 I)TIKI LranKI I,INCUBI.OAOLC 07)A)nK>>Log)f W LaollKI I,ZTNKI LTSNKI lATTC.M'I Iao 0$I.WCKK I J)CIAO I.rrftk>>S.ffft KI I.QN<<Ltl4IKI I.lfac ar lAIIC 07 S.rrfl 07 TAIN Cs t.ffN 44).$$$)Os I~OC)C<<I,riel Oo'1.0)$1 OS 1,1011 OS I,lfa Os 1.foals$.<<N.II T.fsll 07 I,ILN<<).roSI Os 4.7101 07 l.f<<I Or 5 7711 47~.0)N a).IOSI Co)A)II OS IAOII a I.70K 00 OAC)f Aa~.Il)t Al 7;45$INI l,~0$I Joag~T,INCKI I.rsnKK I.SSLCKK S.WNKK IAI)c&I.ITNKI).00)CKI I,cal oa I,TSNKI Lfftf~SASIKM 1 Airs KO lAONKI LISICKI 1.)SNM I.f)nKI SAINT~, MKI I.rg)f m lASNAI TAKIN IAafc.ar I.ao)I ar I.roll os S.STM 04)Affl<<I,la)i 04 t,an<<Ltf f1~I.lssl 0$IAln oa T.loa eo I.)on Os S.rt)I 07 I.TSM Ds l A41t~os TAasl Of l.farl~07 4AO)I ar I.g)sl.ar M)II OS 1.))M os~.Ltsg 04 4.1)fl 04 I.esn.ar~.41N~MOOt 07 I.laol 07 I.Tall lr a,a))I 07 S.SIK 07).NN 07 IAIK 04)ALII 44 a.)lN 07$.$)st 07 I,MK<<~Alsl oe$.$4)l ge l.Ssal.a I.OSat Or).<<LI ar lA)sl or LSLN er t.so)g 47 7~)IM Dr I oral a a.rul<<SAI)I~07 T.nn er$.7MI os~1 IK 4)LCIM egfae1 Nef NLLIM KaK Vile aelfo I'Knee/Mc) 5155 I see,404 NIIKI~,DOO IN AOO oooo Aeo ILI<<fgs VI MD<<Isa LCNL~tr, Oleo NIV/I Ifoftal)10.0 0VIUIea Nloef Ief flog)41)~LDOAI~cl4NCANI INWMDI)l)1$,0 Naf Iv)NIVL aaff IQL/MC>.0~I fK Naoao Vfso N)lef I 10.0 IKTltl)1'Nef NLIIN asK VIVI Ngfo ILK nag/IICI)lf NLC CMI I I INI)Iuvaf f0 uss Teae.eoo of)Co N IN)~a>>IV)Aoo NON)UN)IOOK.a>>sATN a l.rftf N>>I,rgnAc I,I)tf N I.oul a I.KSI Oe).f))l a l.oo)l ce IAIK.N lANI 00 IA)sl.a T.SNT af IA)OI 00 I.OIIIKO t,f)K 04~Arll af I.eag.a 4.1)n'Oo 7.$gn'N OAOII&I.ILN N I.faa a I.a)TIe I.un a$.0SII~Los n ae tAOSI Of I.l<<I 04 IANC CK I.t))t 00 S.ra)i Oe~.SIK of a.a)$1 af I.rift Oa 7.)an os$.<<rt os),IIM a I.t7N'10 IAIOL 4S I.oof I a Ltsag Oe)AILI as t NSI'Oe~Ae)t 10 I.am.a~.Ofa Of$.1701 10$.0)M 10$.)LK 10 l,f471 10 1 0571'10 7.I<<I~10 I slog'10 I~INf'01 I Of)C Of 0.0171 10 IAsn 10)ANf Il~ll rl'oo I.un~10~,)IK 10 lA)$I 04 v)a)<<ego INTta/ac)IVIIIDLC/NVIQL cfo>>II)oe5 UN I<<e Aal NINge,oa IN,OCO aavg 000 57

Page 60f15 TABLE 22 AVERAGE ANNUAL RELATIVE CONCENTRATIONS SvtqutIIxrxIB steax Electric station-ORIRNo-LKYEL RELEASE ND DECAY, INIEPLEYED CORRECTED SQR QPEK TERRAIN RECIRCULATION USIKC SPECIAL YKR ANNUAL AVERAGE CKI/O ISEC/NEYER CUBED)DISTANCE IN SIILES SECTOR 500 7$Q I QQQ'$00 2>000 2>$00 3 000 3 500 4 000 4'500 S SQl SM MSM Mxv N NNK NE Ekf E EBK Sf SSE 1.107K.05 3.933K 06 2.245E 06 1.452E 06 T.S&CE 07 4.809K>07 3.347K 07 MME 07 I NZE.DT 1.297E>07 I.OZOE.OF Z,IHf 05 7,035K 06 4>101K 06 2 552K 06 1 494E 06 9>69SE 07 6>925E 07 C 8366 07 3 460E 07 2 664E 07 2 074E 07 4,690E 05 1.466K~05 8.707K>06 5.694E.06 3.161E 06 2.077E 06 1>SOTE 06 1.0986 06 8.221E>07 6.4CZE.07$.1356 07 I 149K 04 3.572E 05 2.1$3E.DS 1.454K.OS d.273E 06$.721E 06 4.371K 06 3.212K 06 2>418K 06 I 973K 06 l,&COE.06 6,$226.0$2.013E 05 I.OC7E 0$d>571E 06 3>$12E 06 2>ZHE>06 1>646K 06 1.1876.06 8>blbf OT T.IIdf 07 5.622K 07 3.016K 05 9>440E 06 5.234E>06 3.33rd 06 1.903E Ob 1.23IE>06 d.TOOK 07 6 363K>07 4.8$1E 07 3.928K>07 3.233E 07 3.0LSE.OS 9.7Sbf>06 S.TSDE>06 3.6448-06 2.059K-N 1>3276.06 9.422K-OT T.otbf-dr Semf>07 4.346K.OT 3.$366 Or 2 306K 05 7 967E 06 4 810K 06 3>C21E 06 1 537E 06 I 207E 06 b>699K Ol 6 260E>07 4 649E>OT 3 674f 07 3 285E Dl 2,232'K-0$

7.0516.06 4.019E.06 2.521E.06 1.493E.06 1>0326.06 7>817E.OT$.70SE 07 4>321E.OF 3.5dlf.07 2.987K 07 2,621K.OS 9.255E 06 5>324E 06 3>&TYE-06 1.994K 06 1.3&5E.06 1.0ZZE 06" T,CTlE OT$.675E 07 4.690K 07 3.945K.07 1.960E 05 d>S03E 06 3 7726.06 2.39&E.06 1>366E 06 9.294E 07 d.911E.07 5.1386>07 3.951f>07 3.316E>07 Z.blsf~07 I,0&If 05 3>631K 06 2.090E.06 1.405E.06 7>4306.07$.017E.07 3.731K 07 2>843K 07 2.2$3E.OT I>890K 07 Y,Q3f Q7 6,389K>06 2,249K 06 1 251E 06 7 532K 07 3 9&YE 07 2.556K 07 1.514'E Dr 1>310E>07 9.644K~05 T.HSE.D5 6.516K N 5 ZZDK 06 I Tdbf 06 9>d7DE>07 5 91SE 07 3>009K 07 1 839K 07 1>235K 07 d>839E 05 6>563K M C 950K 05 3,75$E 08 4,621K 06 1.7136.06 1.011E 06 6.55YE.DT 3.368E.OT 2.090E.07 1>QZE 07 9.55$E 06 6.&DZE.05 C,bsbf Q5 3,QQE Q5 5>991E.06 2.190E.06 l>269K>06 7.6548.07 3.921K 07 2>$40E 07 1.Nbf 07 l>275E'07 9.325E.06 6>623K N 5.011E 05 ANNUAL AVERACE CNI/O ISKC/NEYER CUBED)BKAR INC 5.000 7 500 10.000 15,000 DISYANCE IN NILEB 20.000 25 000 30>000 35>000 40>000 C5.000 50,000 5 BSV Ql MSV V NV NXV N NNK Nf Exf E Elf'Sf SSK Cxl/0 Isf 8.40CE~05 3>73ZE 08 1.899E 05 1.720E 07 7 845E 08 4,286K 05 C.31&E.OT 2.129E.DF 1.169K.07).398K 06 7 311E Ol 4 052K 07 C.899E.DT 2.325E 07 1.259E.OT 2.731E 07 I~392K 07'F.809K 08 2.955E 07 I.S336.07 6.QTE 06 R.NTE Dl I.S27E.07 5.468E~08 2.699E 07 l>895E 07 1.011E 07 3.370K Dl 1.817E 07 9.860K 06 2.COSE Dl 1,329E 07 7.623E 08 1.3dlE'Dl 7$12E 06 C.TF5E 06 5.500E N 2.843E 08 1.599K 05 3.075E 06 1,280K 08 T,ZCCf 09 2.907K N 1.096E 06 6.246K 09 C.OC3E.Q5 1.6076.06 6.9696.09 C/NElfR CUBED)SOR EACH BECNENI 4.397E 09 1>963K 09 6.5HE~10 3.6&YE 10 1.63TE.IO 1>3&YE.N 6.146E 09 2.2686-09 1~119K.09 3.767E 1D 3.500E.06 1,760E 08 7.9626.09 4.666K 09 2.C766.09 I 1STE 07 5 409f N I 9536.08 1,069E N 4.088E 09 3.522K 08 1>CHS.06 4 155E 09 2>30$E 09 d,123E~10 2.691f>06 I~249K.05 4.739E.09 2.060E.09 3.1S9E 10 3>04CK 08 I~291E.05 3.930f 09 1.676E 09 4,509E 10 2.626K 08 1>226E 05 4.07CE 09 2.498K 09 l>400E 09 2 795K~06 1 377K 06 6 263K 09 3.'lslf 09 1 101E.09 3.0ZZE.08 1.354K 05 4.980E 09 2>765E 09 I.ZTFE 09 2.HPE 08 1,256K 05 3.891K 09 2.149E D9 9,660E 10 2 35CE 06 1.253E 05 6,699E 09 3,TRSE 09 1,711E 09 6.00bf-09 3.0rsf.09 I.S93E 09 d.073E.IO 3.140E.IO 2.7966.09 1.47lE 09 6.110E~10 3>639K 10 1,060E 10 2.436K 09 1.0ZIE 09 3.274E~10'1.6156 10 5>640K 11 3.3SZf 09 1.C$9f 09 S.lsbf~10 2&42K 10 1.056K~10 1.084E~10&,NIE~11 2.HIE~10 1.NIE.IO I 709E 09 9,805E~10 2>316E 09 l>DOCE 09 4>$73E~10 1.97OE.IO 1.7llf 10 d.080E>11 2.dl5E~10 I.IC1E 10 8.425K 10 4.CITE 10 6.367K 10 3.015E.10 5.166K 10'C.NSE.IO 5.699K~10 3.WE-10 1.062E 09 5.600E 10 1.870E 10 9.706E.II 5.609K~11 2.CASE~11 2.675E 11 6.051E.l'2 6.241E 11 3.1&CE ll S.HOE~11 9.386E 11 5.579K 10 8,634K~10 1..725K~10 5>306E 11 9,89CE 11 3>8276.10 2>QOE'10 4>232K 10 2.769K.IO 5 002E'10 b>339K 11 2.096E 11 6 891K 12 2.72RE 11.5~I 2.269K-Db C.DTBE>06 8.695E.06 2.155E 05 1.088K 05 5.323K Qb S.TDCE.DC 4.694K Ob C.DRTK.Ob 5.472K.Ob 3.766K.bb 2.13DE Ob 1.25'IE 06 DIRE CY IIXI IRON SITE 5 SCV SV MLV V VNV NXV N NXI NK ENE K 1.2 7.886E Dl I.S03E~06 3.242K.06 8.$31E.06 3.6SOE.06 1.9RRK 06 2.NCE Db 1.909K.Qb 1.517E~Qb R.066K Ob'I.CDIE Ob 7.836E~07 4.132E 07 2.3 3>33RE>DT 6.829K 07 1.49SE 06 4.266E Db I.&35K.06 8.735E.OF 9.C66E.OF 6.62RE.OT 7.6CIE Ol 1.003K 06 6.53FE Ol 3.719K Ol 1.510E 07 1.722E.DT 3.$5OE~Dl 5.33 1f.07 2.C7SE Ob 9.041E~Ol 4.93lf Dl 5.Cl I E.07 4.614 E~07 C.C2FE Ol 5.513E.Ol 4.056K Ol 2.283 E~Dl 1.DOC E.Ol I.0)bf.07 2.117E 07 5.219E 07 1.6C9E.06$.664K.07 3.253E Dl 3.57CE.07 3.284E.OT 3.050K.OT 3.9$CE 07 2>dlRE OT 1.61$E Dl 6.S5$E N 3.956E 05 6.342E.N 2.INK.07 7 345K 07 2AZSE>OT 1.416E.07 I S$5E 07 1.$09E.Ol 1>NIE 07 I 7HE 07 I 316K OT 7 TOBE 06 2.NIE M SEQIKNI BIAXOARIES IN MILKS 34.Cs 5~10 lb.20 6.5$6E 09 I 651K 05 C.54&E 05 1.52FE 07 4.635K 08 3.1676.05 3.SDSE.06 3.369K 05 3.791E 05 3.800E.M 3.232E 06 2.C03E>05 6.922E.D9 20.30 8.991E~10 2.643K~09 9 220E 09'.521E 06 6.2NK 09 5.734K.09 5.$03E.09 S.QYE.O9 r.ORQK-09 6.3856.09 S.SOSE.09 7>131E 09 1.673E.09 2>006K~10 5.424E~10 2.dlDE 09 5.300E 09'1.1DCE 09 7.613E~10 7 968E 10 1.SORE 09 I.SOCK 09 1.534K 09 1 161E 09 2.039K 09 4.06&E 10 7.701K~11 I.CSBK~IO I 151E 09 1.346K>09 2 651E~10 9.239K 11 1.539E~10 5.3676 10 3.663K 10 5>621E ID 3 5396 10&.HCE.ID I~166E 10 30 F 40 40.50 68 Page 7 of)5 TABLE 22 AVERAGE ANNUAL RELATIVE CONCENTRATIONS ESE 9.8438.07 3.13SE 07 SE 1.009E 06 3.509K 07 SSE 1.250K 06 4.137E 07 VENT AND BOILDING PARAHETERS:

RELEASE HEIGHT (NETERS)D IAHETER (HETERS)EXIT VELOCITY (H/SEC)1.256K 07 1.413E.07 1.791E 07 9 60 F 00.00 ELEVATED LESS THAN+000 NI XED BETOKEN 000 AND CROWD LEVEL ABOVf+000 AT THE RELEASE HEIGHT: VENT RELEASE NCOE VINO SPEED (HETERS/SEC) 6.605K 08 3.867E 08 6.781E 08 3.723E 08 9.3ME 08, 5.189E 08 REP VINO HE IGNT (NKTERS)10,0 BUILDING HEIGHT (NETKRS)d1.3 BLDG.IIIN.CRSoSEC.AREA (SOeHETERS) 2575+0 NfAT ENI SS I ON RATE (CAL/SEC)0 AT THE EAASIXIED MIND NEIQlT (10+0 NKTERS):, VENT RELEASE Ikef IIIND SPEED (llETERS/SEC)

I STABLE COSITIONS ELEVATED LESS'INAN 000~000 I NIXED&KTNEEN,DOO AND,OOO GRRIND LEVEL ABOVE,000 VINO SPEED (HETERS/SEC)

ONSTABLE/NEIITRAL CONDITIONS LKSS THAN ,000 BKTIJKEN.000 AND ,000 ABOVE.000 Io432E 08 3,198K 09 8.177K 10 1 671K~10.3.'513E ll 1.289K 08 2.d54K 09 4.4$9E-TO 7.6$6E-11 1.575K-ll 1.8348~05 3.763E 09 6.665E.10 1.345E~10 3.912K 11 59

Page 8 of 15 TABLE 22 AVERAGE ANNUAL RELATIVE CONCENTRATIONS SVtqvt(INIVIN Stma EINCtl'IC StNtlOn CRIRNO LEVEL RELEASE 1995 2<<tbb DAY DECAY, IROEPLETED CORRECTED FOR OPEN TERRAIN RECIRCULAYIOI USING SPECIAL TERRAIN ADWSTNKNT fACT$ANNUAL AVERAGE CNI/O (SEC/HETER Cteao)DISTANCE IN IIILES SECTOR.250.500.750 1.000 1.500<<2.000 2.500 3.000 3.500 C.DQQ 4.SQO S SSV SV VSU U Wll.NV NNV NNE NE EN'f E~ESE SE SSE 1.10&E:05 3.926E 06 2.241K 06 1A4TE 06 7.519E 07 4.7?la<<07 3.314E.07 2.30&E<<07 l.i5bE 07 I.tref<<07 I.QQIK.D?2.100K-OS T.otra-ob C.ob&E.O&2.560K 06 1.453K 06 9.597K.OT 6.840E.OT C.rbn 07 3.395E OT 2.600K 07 Z.pt(a-or 4.&85K 05 IA&CK-0$SA&SE 06 S.&boa.o&3.13ZE 0&2.052K 0&1.484E 06 1.075E 06 S.OCTK.QT 6.25&E.OT 4.90&a 07 1.1CTK.04 3.561E.OS 2.1QE.OS 1A45E.OS 8.103K 05 5.645K 06 C<<JOIE.O&3.150E 06 2.364K 06 1 92tE.06 1.593E.D&&.S12E 05 2.00&5 05 I.OC2E 05 6.S25K~06 3A77K 06 2.2QE 06 1.610E 06 1~164E 06 S.dlSE 07 6.033K OF 5.6Sn.o?3<<0'IJE 05 9<<410K*06 S<<209K 06 3<<310E 06 1<<NSE 06 1'1SE<<06 8<<560K 07 6 2&DE 07 4 742E 07 3<<828E 07 3 140K Q?3.005E-OS 9.727E-O&5.724K 06 JAZJK 06 2.0405.06 1.311K 06 9.25n.or d.890E 07 5.320K 07 4.242E 07 3.4QE.D?2.303f.os 7.945E<<ob co?005.06 3.CDIE.O&1.822K 06 1<<IQJE.O&S.ST&a.or 6.153K 07 4.SSTE.QT 3.78&E-07 J.204E-D?2 229E 05 7<<031E 06 4 002K 06 2 SDTE 06 1<<480E 06 1 021E 0&7 70?K 07 Soeobf 07 4 23SE 07 JASQE 07 2,911K 07 Z.dlra 05 9.261K<<06 5.303K 06 3.&SSE 06 1.970K 06 U40E 06 I.ONE.O&7<<JSSE 07 5.572E 07 4.593E 07 3.8$&E.Q?1.9$5E 05 6.491E.O&3.7615.06 2.38?E 06 1.3&DE 06 9.RZOE 07 6.8QE 07 5.07?E 07 3.925E 07 3.2QE.07 2.?d5E.07 1<<0&DE 05 3.626K<<06 2<<NSE 06 1A04E.06 7.304E 07 4,954K-07 J.roof 07 2.515E 07 2<<227E 07 l<<565K 07 1.S99f 07 6<<JSCE 06 2<<245E<<06 1 245E 06 7 510E<<07 3 949K 07 2 SCOE 07 1 SOOE 0'7 l<<205K 07 9<<?JSE*N 7 blba 05 6 427E 08 5.RI&E 06 1.?QE 06 9.846E.OT$.59?E.OT Z.995E-OT 1.82?E 07 1.55E OT d.?S5E 05 6.509K>>ob 4.586E 05 J.?30K.N 4 dldf 06 1 711E<<06 1 000K 06 6 540E 07 3<<JSSE 07 2 0?0E 07 1 413f 07 9 452E N b<<SQE 05<<AOSE 05 3<<S?9E 05$.087K.oe Z.(bra.o&.I.2&6K-oe T.QZE or 3.004K.or 2.$2&K*a?1.?0sa-or t.wf-or 0.220K.N&.TQE-N c.occa-od ANNUAL AVERAGE CHI/O (SEC/HETER CUSED)DISTANCE IN NI LES SEARING 5 000 7 500 10<<000 15<<000 20<<000 25<<DQQ 30 000 35<<000 40 000 45 000 SO 000 S SSV SV VSV V IAIV NV N NNK Na ERE f Esa Sf Slf cHI/0 (sa b<<ZJCE N 3.619E.N 1.522K'08 4.13JE.09 1.80?E<<09 6.104E~10 3.230K.IO I.C1&E~10 9.157E~11 5.71&E 1'I 4<<52?E~11 1.6?&E 0?T.543E 05 4.066E 08 1.2QF.05 S.S28E.00 1<<05&a~00 9.S4tf 10 J.tcca 10 2.0(?a~10 8.510E-'ll 7.198E.II c.lbsa-o?Z.OJJE-QT 1.000K-QT J.Wa-od l.sssa-ob 6.836K.00 3.8?CE-00 1.904K-00 1.334K.00 rAtoa-lo 6.20n-to 1.35CE 06 6.9&Sf.Q?3.799K 0?I.oslf.o?4.75&E 05 1.&QE 08 S.bl?E 09 3.26&E 09 1.?03E 09 7.525E.10 6.41SE 10 C.?40E.O?2.213E 07 1.170E.D?3.191K 05 1<<309E<<N J.SZSE.09 1.89JE 09 6.4S7E.10 3.515E-IQ'1.46?E-IO 1.244E-10 2.&CCE 0?1.326K.o?7 31&E 05 2.440E N 1,09&E 05 C.OZSE 00 1.605K 09 2.51?K 10 1,36&E 10 4 540E 11 3 Qbf 11 2.509K 07 1.4&CE 07 8.115K 05 2.7?9E N I,IQE 05 3.376K 09 1.5dsf 00 J.NSE 10 2.008K~10 8.&SQE 11 7.306K 11 2.72?f~0?IA62E 07?.000K 05 2.591E 05 1,001K 05 3,522E 09 2,008K 09 1.142E 09&.d?0E 10 J.CQIE 10 2.bQE 10 2.623f 0?1.51SE 0?9.549E'05 2.5&cf 05 1.225E 05 5.442K 09 Z,Q&f 09 9,010K 10 5<<OQK 10 2<<JJJK 10 1<<969K 10 3.25JE 07 1.747E DT 9.357K 05 2.704E N 1,219E.DS 4.3?lf 09 2.385f.09 1.0&Ca.00 d.&S4E 10 3.569E 10 3.2d9E 10 Z.ssba.o?1.200K.o??.JI.N z.?e?a-ob I.159K-N J.szlf.00 1.9ora-00 S.CNE-IO$.03?E-IO Z.e??K-IO Z.zrsa-lo 1.3&cf.o?7.326K N 4.615E Ob 2.230K 05'.172E 05 6 JC&a'00 J<<371K 09 I.SZJE.00 9<<30?E 10 5<<QQQE~10 4.244f 10 S.CISE 05 2.7??E.QS I SC0E'N S.?2?E 09 2.5Qf 00 I.C?1E 00?.3$4E 10 2.505E 10 1.6C'5a 10 5.407K 11 7.11DE 11 3.02&E 05 1,2$QE N 7.01lf 09 Z.dbtf 00 I Jdtf.00 TA&&E 10 J.C?5K 10 9,C3$E 11 5.05?E 11 2.10&E>>11 1.776E 11 3.954~..~2.8?DE 05'1.075K.od 6.NSE<<00 2.3QK.09 9.&Qf 10 J.0&4K~10'I,492K~10 S,JZJE ll 2.556K~11?AcdE~12 6 035~2~.~.F.~1 f N 1.5?IE 08 S.rztf'00 3.2otf 00 I.J7ZE 00 4.7?bf.lo 2.C10E~10 9.504E.11$.519K 11 2.?S5E~11 2.334E.11 C/KEIER CUS(D)FOR EACH SKGKKNT DIRKC'I ION Ft(tl Sill S SSV SV VSV V NNV H NNK NI ENE f.$.1 2.26RE 06 4,06JE Qb 5.6$?E Od ZACSf 05 I.OQE 05 5.209E Ob S.bbof 0&4.5?C\.06 C.QIIE 06 SAsta 0&3.75?E.0&2.12$f.o6 1>2C9E 06 1 2 T.SCIE 0?I:C92a 0&3.21CE 06 S.CSIE'06 JA15E.Q&1,904E 06 2.0&SE Ob 1,50JE 0&1,50CE.06 2 0?RE 06 I 303E 06 7.709K~0?C.114E 07 2.3 3.209K.Q?6.?44'E 0?I.C73f Ob 4,200E 06 1.609f Ob S.S9?a 0?9.3C7K 0?S.SORE'0?7.534E.D?0.001E 0?6,??OE 0?3.&SSE.O?1.?9&E OF 1.695K'0?3.Cd?E 0?d.lS?f 0?2.C2of 0&8.83?a 0?4.82?E 0?S.JSSI 0?C.?10f 0?C.JCQE~0?5.?NE 0?4.00ZE.OT 2.257'?9.9JIE 05 1.01?E D?Z.060K-o?$.0?SK.O?,1.&02 E<<ob 5.60CE 0?3.1&DE 0?3.4?5E~0?3.200E 0?2o073E 0?3.Seta 0?Z.rezf.or 1 Solf 07 6.464E 08 3.846E N 5.046K 05 2.006K 0?7.015E 0?2.315(.O'1.355E.07 1.40JE OF 1.449E OF IA12E OT 1.725E 07 1.2?9$.07 T.stsa 05 2:817K.OS 6<<231f 00 1 570K 05 4.106K 05 l.coca-or C.264E 05 2.9Zbf 05 3<<ZJSK OS 3.124E N 3.$22E 05 3.553E.N 3.065K 05 2<<203K 05&.QJE<<00 5.170E 10 2.515K 00 7.0?JK 00 R.t?sf 05 S,etta 00 C.944f 09 4.799E 09 4.923E 00 6.14tf 00 SAQE.09 5.02?f-00&.SNK-00'I.SStf-09 1.745E 10 4.5$4E'IO 2<<'RSOE 00 4.201K 09 8.901E'10 6.20ZE 10&.sd7K 10 I~235K 09 1.24&E 00 1 290E 09 1.01?f 00 1.525E 09 3.655E 10&A15E 11 1 15?a 10 S.TS&E 10 I OZQE 09 1.002K 10 6,981K 11 I ldtf 10 4.1?3f.lo 3<<00?E~10 4.CTZE'IO 3.2285.10 5.09&E~10 1.031K 10 SEGKKNI ROVNOARIKS IN KILES 3 4 4 5 5.10 10 20 20.30 30.40" 40 50 60 Page9 of 15 TABLE 22 AVERAGE ANNUAL RELATIVE CONCENTRATIONS ESE 9 821E 07 3.121E 07 1.246E.07 6.533E 08 SE 1.007E 06 3.496E.07 1.405K 0/6.722E 08'SE 1.247E-06 4oT20E 07'l.778K 07 9.263K 08 VKMT AXO SUILDIMC PARAMETERS:

RELEASE HEICHT (METERS)9,60 DIAMETER tkETf RS)+00 EXIT VELOCITY tH/SEC).00 REP.VINO MEICHT (METERS)10.0 BUILD INC NE I CHT (NETERS)61,3 BLOC.IIIM.CRS.SEC,AREA (SO.METERS) 2575.0 NEAT ENI SS ION RATE (CAL/SEC)0 AT TNE NKASLNIED VIXD NEICHT (10.0 METERS): VENT RELEASE IMNE VINO SPEED (ItETERS/SKC)

STABLE CONDITIONS LESS TNAM 000 SETVEK M~000 AMD 000 ABOVE.000 I I I LESS THAN.000 I SETVEKN 000 AMD 000 I ABOVE.000 AT TNE RELEASE ME!CRT: VENT RELEASE IXOE VIIO SPEED tNETERS/SEC)

VINO SPEED (METERS/SEC)

UNSTABLE/NEUTRAL CONDITIONS LESS TNAM.000 SETVEEM+000 AXD F000 ABOVE~000 ELEVATED MIXED CR(AXO LEVEL 3@812K 08 IAOE 08 3 059K 09 7 565k 10 Io501E>10 2 867E 1'I 3abdOE.08 lo267f-08 2+564K 09 4+200K~TD 7.022E~11 1.228K~11 5~121E 08 1.796K 08 3od15E.09 6.215E.10 I o216E~10 3.41df~11 61

Page 10 of 15 TABLE 22 AVERAGE ANNUAL RELATIVE CONCENTRATIONS Svtovtkgz~

STOLEN EIBCtr)c Stat)on.CRIRNO LEVEL RELEASE-)995 Looo DAY DECAY, DEPLETED CORRECTED fOR OPEN TKRRAIN RECIRCULATION US)ko SPECIAL TERRAIN ADJQ5ggNT ANNUAL AVERACE CIII/O (SEC/METER CLRIED)DISTANCE IN MILES Sf CTOR~2$0 5QQ 750 I 000 I Soo 2 000 Zosoo 3 000 3 SOO 4 000 4$00 8 SSV SV VSV V VMV MV NNll N NNE NE ENE E ESE SE Btf).OCIE.05 3.$90E 06 2 0028.06 1.270K.06 6.413E.OT 3.973E.OT 2.704E 07 Z,Q7$E 05 d.C)PE 06 3.6$)E 06 2.257K 06)~Zbdf 06 8.005E.07 5.592E 07 4,437K.os).339$.05 7.749K-ob 4.976K 06 2.677E 06 1.714K.ob 1.215K 06 1,0878.04 3.259E 05).9)df-os I.zroE 05 Teoorf 06 c.720E 06 JesZSK 06 6.17OE 05 1.QbE 05 9 31$E 06 5,74)E 06 2.974E 06).$9)f-ob 1.327E 06 2.8$SE 05 B.d)3E 06 4ASIE-06 2.911E.06 l.d12E 06 1.015$.06 7.015$.07 2,8$0E.05 8.90)E 06 5.))rf 06 3.115t.06 1.744E 06 1.095E 06 TAOOE 07 2.182E.05 TeZTOE 06 4 281E~06 2.9OOE 06 1.5STE~06 9.962E-OT Tao)bf 07 2.112E.05 6.434K 06 3.S78K 06 2.203E 06 1.26$E Ob B.SZOE.DT doJDTK 07 2,C79E.OS I.C73E 06 4.739K-ob 3,2)CK 06).690$.06).)Zbf 06 Be245$-07)Issf 05 5.936E 06 Jo359$.06 2.095E 06).ldof 06 T.drBE 07 5+SIZE 07).OOCE.DS 3.31$E 06 1.86)E 06 1~232E-06 6.30)E~07 4.147E 07 J.DISK.07 6.046E 06 2.053E 06 1.114E 06 6.5888.07 3.364E.OT 2.113E 07 1.466K 07 4.940$-06 l.d)2$.06 8,789$-07 5.)TJE-OT 2.55ZE-07).SZOE-OT 9.9$)K-M C 562K 06 1 564K 06 9 002f Q7 5 TJbf 07 2 l57E 07 1 728K 07 I~)COE~DT 5.669$-06 1.99PE.06 I~'130E-06 b.d95E 07 3 326K 07 2.100E-OT 1.461E 07 I.BC7E 07 1.307E.07 9.911E 08 7.67)E 08 3~825K 07 2.686K.07 2.033K 07 1.5STE~07 Bodrsf 07 6 37bf 07 4 OTIE 07 JobsJE 07 2.537K 06 1.875$.06 I.S03E.06 1.230E'06 9.JTSE 07 6.Q4$.07 5.423K 07 4 365K'07 S.042E.OT 3.76)f-or 2.99CE.OT 2.C24E.07 sisCCE~OT CiZ)sf+or 3.313K 07 RibSCE 07 4.9488 07 3.607E-OT 2.955E.OT 2.4688-07 4 SIDE 07 3.352f 07 2,716E 07 2 242E 07 5.90$E.OT CAOSK-07 3.579E.OT 2.965K.07 4,067E 07 3,094$.07 2;534E-07 2,1)IE.OT 2+252K F 07 1.752E 07 1.C46E OT).ZZZE~OT),0388 07 7.6SIE 08 6.05SE 08 4.908E 08 T.OOZE-M 5.)ZOE.OI 3.786K-M Z.BSDK.M TosTJE M 5+)JIE 08 J.rlbf 08 2.728E M 1.012E 07 7.2$SE 08 5.220E 08 3.774E M ANNUAL AVKRACE CHI/O TSKC/HETER CUBED)BfARIMC 5.000 7 SDO 10,000 D')STANCE)N NILEB 15.000 20.000 25 000 30,000 35,000 40,000 Cs.ooo So.ooo B SBV SV V)V VNV NV NNV N NNL Nf ENT f'Etf Sf$)f CNI/O ISE 6.229K 08 2.608K 08 1.261E 08 1.273E.07 5.470E.OS 2.QTE.OS 3.)IOE.OT IAI)E 07 7.715K 08).OJJE 06 S.DICE 07 2.67)E 07 J.d)bf~07).6)df 07 8.302E 08 2.017E 07 9.679K 08 5.15DE 08 2.20bf.or 1.067E.07 S.d97E~08 2.075E 07).064K 07 5 S96E.OB 1.996E or 1.320K 07 6AISE M 2.493K-or 1.267K.OT 6.527K.ob 1.783K 07 9,29ZE 08 5,063K 08 1.029E 07 5.25$E F 08 3.)TIE Ob 4.MZE 08 l.991E.OI 1.065K 08 2.28ZE F 08 8.96$E 09 4.$22E OO 2.1$9E 08 7.68$$IS 4.165K.OO 3.001E~0$1.12$f'OB$.987K OO C/HETER CUBED)fOR EACH BKCNENI 3.046E.)1 2.$)bf~1 I 4'13E F 11 3.920E 11 C.ZJOE 10 J.S39E 10 4.3)bf 10 3.634K 10 8.459K 1'I T,MZE 11 Zeb)JE 11 2.)bof 11 4.927K 11 4.089K F 11 1.914E 10 I.SBTK~10 1.3OOE 10 I Mbf 10 2~133E 10 1.771E.)0)oC)bf.)0 1.179$.10 2.$9$E~10 2.150K~10 C.348E~11 J.SME~11).DOCK~11 9 004K.)2 3AJJE.IZ 2.PIPE 12 1.42OE.11 1.17CE 11 2.687K.09 I.)ZDE.OO 3.69OE 10 IA67$.10 7.92$E~11 5.01)E~11 8.3'11E 09 JoCQE'09 1.20OE 09 SA40E 10 I BISE.)0 1.1$5f 10 2 120E 08 9 PZZE'09 4 ZZTE 09 2 334K DO 1)Tdf 09 7 724E 10 7+DO)K)M J.OCbf 08).ORE M S.JJIE 09).PJbf OO T.OC4E.OO 2.130E 08 I.JOIE 09 2.)OCE 09)o)SOE.OO J.ICZE~10 R.osbf 10 1.628E OS 7+DZSK 09 2.504K 09)+028K OO 1.495E 10 7.975E~11 1.844E 08 T 2QE DO 2.0QE 09 9 405K 10 2,286E lo)oZ)lf 10 I 71$E 08 6,927K 09 2.163.09 I 254K 09 b,d72E~10 J.IZ4f-lo 1.696E 08 7 785E OO J.JJIE QO 1,572K 09 5 2$1E 10 2.892K~10).Qbf Ob 7 674E OO 2ASSE 09)oCObf 09 6.119E 10'3.74)E 10 1.796E~08 T.lbbf.09 2.09ZE.09 I~095K.OO Cebbrf 10 2.734E.IO).443E 08 7.179E OO 3.727E OO).POPE'09 8.3$5E~10 C.Obof Io 3.68$f OO 1.76ZE 098.blsf 10 4.142E~10 I.S35E lo$.738K ll 1.71$E OO$.462f 10 C.JQE 10 1.968E 10 5.17$E ll 2.71lf~11 1.499E OO$.$7ZE lo 1.778K 1D IoJZTK ll 2.871E 11 1.35ZE~ll 2.0$7f OO 8.372E~10 2.791E 10 1.357K 10 5.1$1E~11 2.92ZE 11 D I R f CI I ON fkOH Sllf B t)V BV V)V V lhlV NV NNV N NNE Nf f'Nf f.5~I 2.029f.06 JACTK~06 7.77)E.ob 1.92bf 0$9.73rf-Ob 4.76)f Ob 5~OOOE Ob 4.371E-ob 3.602K.ob 4.891E.Ob 3.370K.ob).Oosf 06 1.)ZOE 06 2.3 6.726E 07 l,zrof.ob 2.76of.06 7.257E.O6 J.lobf Ob 1.QCE.Ob 1.776E Ob 1.62bf Ob 1.29OE'Ob 1.778K 06 1.193E 06 6.681E.Or 3.524E 07 2.70OE~Or$.$RBK or 1.209K Ob 3.449K Ob I JZZf.ob 7.063K or 7.6TZK.OT 6.975f.or 6.178E or 8.113E Or 5.53$E Or 3.011E'07 l.cb7E.OT I~34)E 07 2.762K'Dr 6.C75f or).923K.ob 7.023K~Of 3.Q5E.OT 4.2$)f 07 J.rczf-or 3.cclf or Co SZOE'07 3.1SPE 07 1.778K~07'7.824E.08 T.bool.ob'I.SOSE Or 3.920E Or 1.23$E 06 CADRE 07 2.C42E 07 2.684K Or R.cbrt.or 2.291E 07 2.972E 07 2.117K.OT 1.217K 07 4.942K M 2.$14E M$.9)ZE 0$1.545K~07 5.)TIE~or 1.7)ZE or O.OOBE 08 1.099E 07 1.064E 07 1.'IIIE 07'l.266E-07 9.310E 08 5 ASlE.OB 2.0C4E 08 SKCNENI BOUNOARIES IN IIILES 4.$5.10 10-20, 4.195E.09).062K 08 2+862K~08 9.627E.08 2.928E 08 1.999E.08 2.20CE M Zo)ZJE 08 2.397K 08 ZoCOCE 08 ZiOCJE 08 1,$06E.OI CoJTIE.OO 20 30 4.963K 10 1.557K DO 4.988E DO 1.3TDE-M 3,431K DO 3.12OE.OO 3.012E.IS 3.070K OO 3.$17E 09 3,49CE 09 J.OCTK 09 3.92)E.09 OoZZIK 10 JO.CO 9.BISE-ll R.bsbf.)0).JSJE OO 2.568E 09 5.349K.lo J.TJOE 10 3.9IOE 10 7 2QE 10 7 JCCE 10 ToCQE~10 seTJJE 10)oo)JE 09 Zoofbf~10 Coiso 3.C33E.II 6.44$E 11 5.009K 10 S.MQE 10).)SCK.)0 4.04'IE F 11 6.744E.)1 2.3S'Of F 10)A96E 10 2.C75E~10 1.'7'l9E-10 3.)JIE~10$.367K-))62 V

Page 11 of 15 TABLE 22 AVERAGE ANNUAL RELATlVE CONCENTRATIONS 1.501E~11 8.32df.12 1.774E 11 8,380K 1'I 3.852K II 8.718E 11 4 505K 10 2.492E 10 3.70bf.10 ESE 8.811E 07 2.87bE 07 1.018E.07 5.149K-08 SE 9.0258-07 2.995K 07 1~147E 07 5.293K 08 SSE 1.118E Od 3.530E 07 1.452E 07 7.299K 08 VENT AND BUILD INC PAkAHKTERSI RELEASE HEI CRT (NETfRS)9eb0 DIANETER (HETEkS).00 EXIT VELOCITT 01/SEC),00 2.917E 08 1,020E OS 2.019K 09 2.81'IE.OS 9.211E 09 I.ddbf 09 3*9188.08 I 308K 08 MS'.09 Rf P UIND NEICHT (NETERS).10.0 SUILO INC NE I CHT (HETERS)d1.3 SLDCoNIN~CRSoSEC.AREA (SOokfTERS) 2575.0 NEAT EN(SR ION NATE (CAL/SEC)o0 AT THE NEASURED UIHD HEICNT (10+0 HETERS)I Vf kl RELEASE IHXIE UIND SPEED (NETERS/SEC)

STASLE C(HH)ITIQIS LESS 1NAN 000 kf TUEEN 000 AIO 000 AHOVE,OOO AT THE RELEASE NEICH11 VEkT RELEASE HCOE UIIXI SPEED (NETERS/SEC)

I I I~000 I.000 AIS,OOO/~000 ELEVATED Nl XED CR(XNO LEVEL LESS THAN HETMEEN ASOVE ELEVATED NIXED CR(XMD LEVEL VIND SPEED (NETERS/SEC)

UNSTABLE/kEUTkAL CONDITIONS LESS TNAN.000 SETMEEN+000 ND.000 AHOVE.000 63 P

Page 52 of 15 TABLE 22 AVERAGE ANNUAL RELATIVE CONCENTRATIONS Stbtien N RECIRCULA RELATIVE D SvvPIehacw St~E lect I Ic CORRECTED FOR OPEN TERRAI D IRK CT I ON FROI SITE S SQI SV VQI V NV N NNK NE ENE E ESE SE SSE DIRECTION FRCH SITE S'SV VQI V NV NNV N NNf Nf ENE E ESK Sf SSK.50 2.162E 08 2.739E.08 J.SOCE.N 5,107E 05 3.496K.N 1.9496.08 2.6596.0$2.596E 06 2.396E 05 3.540E 08 4.742E 05 3.1QE.08 1.609E.N 1,295E 05'1.446E 06 1.669E.08.25 6,1$6E 08 6.207E 05 1.025K 07 1.436E.07 1.021E 07 5.74?Eebb b.CSC E.08 7.215E 05 7.151K 06 9.489E.N 1~377E 07 9e313E.06 5.327E.N C,OJIE 06 4.312E 05 C.716E 08 5.00 2.S$6E 10 3.5OCE-10 5.129E 10 9.675K 10 4.122K 10 2.7$2E'10 4A61E 10 4.649K.10 4.552E 10 6.46CE 10 9.648K 10 7.1CCE.10 2.601K 10 1.3466 10 I.CIGK.10 I.TOTE 10 7.$0 1.009Ee10 1.3556.10 2.128E.10 4 el?36.10 1 QJE 10 1,203K 10 I OOSE.IO 2.202E 10 2.7QE~10 3.029K~10 4.659E.10 3A6SE 10 1.210E.10 S.080E~11 S.OQK~11 b.406E~11 RELATI~eeeeeeeeeeeeeeeeeeeeeeo 1.2 DIRECTION 5~1 SROH SITE S 1.165 E~08 SQI 1.C97E N sv 2.0066.06 VSv 3.0Obf~06 v 1.84OE N vvv 1.054K 08 Nv 1.567E~06 NNv 1.Cbtf~Ob 1.ZTTE~06 , NNE 1.933Ee06 NK 2.56?f N EKK 1,7CSE'N f 9.C7OK OO EST 6.606E 09 SK 7e966E DO SSK 6.95$E DO VENT AND RUILDINC PA 20.30 JO.CO Coe50 3.53SE.13$.690E IJ 1.46$E.12 1.4$1E 12 4.0lbf.13 3.719E.13 6.3096.13 1.303K~12 1,JOSE,IZ I.S376.12 2.S25E~12 6.191E.12 1, 166E~12 4.691E.13 2.$$1E.13 3.620E~13 1.122E~10 I.SSSE 10 2.3?bf~10 4.437E 10 1.619K 10 1.296E 10 2.129E.IO 2.278E 10 2.546E 10 3~133E~10 4.839K.I 0 3A626 e10 1,273K~10 5.924E 11 6.2COE.11 7.660E~11 3.C60E DO C.bbbf OO 6.QZE OO 1.077E 08 S.JOOE OO 3.216K~09 4.616E.OO 4.8$3E OO 3.979K DO b.'ICSK 09 8.201K DO$.603K DO 2.7Nf OO 1.65CE 09 2.C2SE DO 2.$71E OO RANK TERS: 1.648E 12 3.545E~12 5.964E~12 6.612K el?2.6QE 12 3.3?tf.12 5.136E~12 5.826E 12 7 176E~12 7.60CE 1?I.CZSE~11 2.C94E~11 S.S$6E 12 2.575 E-12 1 6836.12 Ze0696.12 1.186E 13.1 eJDE.I 3$.1$5E~13 J,DSJE 13 5.197E 14 3,760E 1C 1.0376.13 4.062K.IJ 2.666E.13 4.6$CE.13 T.ttlf D 1.5QE 12 3.0Slf.13 6.207E.14 C~110K 14 9etSJE 1C 5.699K.10 6.333K.IO 1.173K.OO 2.092K OO 9.NJK 10 S.OOTK.I 0 OA?6E~10 9.142K~10 6.609K 10 1.279K~OO 1.64tf.OO 1.310K.OO S.27TE~10 J.207E~10 3.8ZCK~10 4.6CTK.10 3.273E~10 4.$1$E 10 b.SCTK~10 1.215K.OO 5.219K~10 J.Cblf 10$.603K 10$.677K~10 5.376K~10 7.919K 10 1.173K DO 6.610f 10 3?06E~10 1.752E~10 1.9QE.10 2 JOSE 10 I.?63E.DO 1.607E.OO 2.Q7E 09 4.30?f DO 1.919E DO I.ZOJK DO le643E OO 1.643K.OO 1.660K DO 2.46?f OO 3.44bf.OO 2.336K 09 1.0Clf.OO 6.6CTK.10 6.6STK 10 9.746K 10 l,dZOE.I I 2A02E 11 3 546K~11 TeblbE 11 2.7STE.11 2.3CSE.11 4.0036.11 4.28CK.11 C.6SbE~11 5eS92E 11 1.011E~10 9.929E~11 2 A91E.I 1 1.1dlf e 1 1 I 1CJE 11 1,366K 11 ORIANA.LEVEL RELEASE~1995 T ION USINC SPECIAL TERRAIN ADJUSTMENT FACTCRS EPOSITIOI PER UNIT AREA.(Nee 2)AT FIXED POINTS 8T INAAOIIND SKCTORS DISTANCES IN NILES.75 1.00 1.SO 2.00 2.50 3.00 3.SO C.OO 4.$0 1.137E.05 6.571E 09 3.2448.09 1.917E 09 1.256E 09 be317E.10 5.726E~10 4.t38E.10 3,211K e10 1,493K 05$.7856.09 4.5718.09 2e726E 09 Te61?fe09 1.189E 09 d.0$6E~10 S.OOSE 10 4.COOfe10 2.024EeN I.ZCJE-N 6.139Ee09 3.6$4E 09 2.4238-09 1edJTE-09 I~ICTE-DO d.477Eelo 6.405Eelo 3 170E 0$2 035E 05'I 028E 08 6 340E 09 4e341E 09 2e910E 09 2e023E I 1 539K 09 1 ROIS OO 1.5036.05 1.060E.05 4.97CE 09 2.916K 09 1.904K 09 1,267E 09 d.777E.10 6.662E~10 5.154E e10 1 OCOf 06 6 170E 09 3 112K 09 1$228 09 1~183K DO 5 073K 10 5 760E 10 4e410E'10 3 CSOE 10 1 566E 0$9 223E 09 4e6QE 09 2e743E 09 1$12E 09 I R68E 09 9e30bf 10 7 092E 10 Se525E 10 1.445E.05 9.S25E 09 4.$53849 2.7428.09 1.6408 09 1.246E 09 6.77SE 10 6.972E~10$.667Ee10 I.?59K.N 7.305E 09 3.836E 09 2.42?f 09 1.702E.09 1.1668.09$.3SOE 10 6.546K.IO S.?50K-IO 1,6$6E 05 I~167Eedd 5.730E 09 3.$908 09 2.505E.09 1.724E 09 1.2ClE.09 9.779K 10 T.NJE~10 2.S$6E.08 1.S22E 05 T.d$6E 09 4.950K 09 3AS7E 09 ZAJSE.DO 1.795K DO 1eCJSE.DO 1.171E DO 1,692E 05 1.077E 08 5,222E.DO 3,306E 09 2 330fe09 1.69CE 09 1,2NE 09 le041E 09 6.QdE 10 93?OE.DO 5.266E.09 2.5496.09 I.SJOE 09 T.OJSE-DO 7.138E~10 5.1SIE~10 J.OOJE.\0 3.179E-10 6.7146.09 3.790E.09 1.771E.09 1.016Ee09 be4$JE~10 4.439E~10 J.ITOE 10 Ze JNK~10 1.709E 10 7.855E.09 4.5236.09 2.253E 09 1.333E~09$.632E~10 5.560E~10 3.699K~10 2eQlE.'10 1.901E~10 d.9SSE 09 5.056E 09 2.3698.09 1.449Ee09 9.7Sbf 10 6.S7SE.ID 4ADIE 10 3eZC28.10 2.300E~10 DISTANCES IN NILES 10e00 15 00 20 00 25 00 30e00 35 00 40e00 4500 SO 00 4.900K 11 1.032K~11 4.216E.12 1.36IE 12 6.7$1E 13 2.616K 13 1.7$2E-13 I.OSOE 13 6.$66E 14 7 090E 11 ZeOOJE 11 6 NIE 12 2 TDOE 12 le226E 12 3 836K 13 ZeJbdf 13 9 S3DE 1C 7 775E 14 1.07ZE 10 2.76CE~11 I 222K 11 4.960E~'12 2ebZTE 12 I 276E 12 de120E 13 Ce 324K D J.SJOE 13 2.053E.IO C.903Eell 1.975E.ll 6.301E~12 3.089E~12 1.071E.12 5.$49E.13 2.?lbE.13 1.509K~13 de074E-11 1.931K~11 7.171E~12 1.7$1E 12 6.932K~13 2.d74E~13 1.490E 13 S.OSIE 14 Ce$$7E-'l4 6,229E 11 1.8QE 11 7 650f 12 2.dlOE 12 1 032E 12 1,CSZE D 7,529E~'l4 2.406E 1C I 964E 1C IeDSCE~10 3 3026.11 1.260K 11 3e491E.12 1.93'12 3eQSE~13 1.56CE~13 7.$26E 14 6.143E~14 1.1Cbf~10 3.416Ee1 1 1.336Ee1 1 4.04OE 12 2.2868.12 1.1868-12 b.dTIE.13 3.250K.I 3 2.677E.13 1,360E~10 3,375f ll 1,493K 11 6.169E~12 2.$3IE~12 9.2'llf 13 4.958K~13 2,200f D 1.796K 13 1.545E~10 C.2llf 11 1.699E 11 SA97E 12 2.934E~12 1.2CSE~12 7.446K D 4.16CE~13 3.399K 13 2.546E 10 d.509E~11 3.403K 11 9A3CE~12 4.90SE 1?2e046E~12'1.167E 12 5.93lf 13 C,641E.13 2.113E 10 9.$19E 11 4.637E~11 2.35SE 11 1.16lf 11 5.069K~12 2.956K~12 1.522E~12 1.2C2f 12 6.559K~ll R.Z71E 11 1.072E 11 5.160E 12 2.C43E 12 6.924E 13 5.011E 13 2.463E D 2.011K 13 2.75?f.ll 9 OSOE.IZ C.d75E~12 2.CObE~12 1 107E~1Z 2edlbF~13 1.49tE 13 5.956K 14 C.6QE.14 2.612f.ll 1,023E.ll 3.986E.12 1.196E~12 5.544E 13 1,592K~13 6.827E IC 2.350E 1C 1.918E.'lC 3.44SE~11 I.ITOK 11 4.72lf.lt 1.546Ee12'7.364Ee13 Z.TTZEe13 1.540K~13 7.379K~14 6.0236~14 VE DEPOSITION PKR UNIT AREA{Ne~21 51 DOVNVIND SKC'IORS eeeeeeeeeeeeeeeeeeeeeeee SKCNKNT SOINDARIKS IN NILKS 2.3 J.C5~10 Page 13 of 15 TABLE 22 AVERAGE ANNUAL RELATIVE CONCENTRATIONS RELEASE NEI CRT (NETE Rs)0 IANETER (NETERS)EXIT VELOCITT (N/SEC)9 d0~00 00 ELEVATED LESS TRAN NIXED SETUEEN CROUND LEVEL ASOVE.000 ,000 ANO,OOO.000 AT TkE RELEASE NEICNTI VENT RELEASf NCOK UIND SPEED (NETKRS/SEC) lfP UIND Nf'ICNT (NKTEls)TO.O SVILDINC NEI CRT (NKTEls)d1o3 RLDC.NINeCkseSECoAREA (SOoNKTKRS) 2$73e0 NEAT KNISS ION kATE (CAL/SEC)e0)AT TNE NEAR%ED UIND NEICNT (10.0 NKTERS)I)-VENT lELEASE N(OE UIND SPEED (NKTERS/SEC)

)STASLE C(NOITIONS I ELEVATED LESS TRAN.000 NIXED~f TUE EN 000 AIO+000 Ck(XNO LEVEL ASOVE e000 UIND SPEED (NETERS/SEC)

UNSTASLK/NEUTlAI, CONDITIONS LESS TRAN.000 Sf TUf f N,OOO AND 000 ASOVE.e 000 Page 14 of 15 TABLE 22 AVERAGE ANNUAL RELATIVE CONCENTRATIONS UNOEPLETED

'ROf PLETED SVINVtNgea Steve EICCtrIC Static-GRIXNe-LEVEL RELEASE-1995 SPECIFIC POINTS OF IMTEkfST ORELEASE TYPE Of DIRECTION DISTANCE X/0 X/0 x/0 0/0 ID LOCAT ION (MILES)(METERS)(SEC/CNI.METER)(SEC/CUD.METER)(SEC/CUK.METER)

IPER SO.IIKTER)

'O DECAY 2o260 DAY DECAY 8.000 DAY DECAY DEPLETED S S S S S S S 8 S 8 S$S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S$S S S SITE RCRNOARY SITE 6IRNR)ARY SITE RIXNRIARY SITE QSNDARY SITE 8IRNOARY SITE SXINDARY SITE 8CINNIARY SITE 8IANOARY SITE DIAIKDARY SITE RCANOARY SITE IMRNKIARY SllK 60NOARY SITE RCUNOAkY SITE 60UNDARY SITE 6IANOARY SITE 6NJNOARY RESIDENCE RESIDENCE RESIDENCE RESIDENCE RESIDEKCE RESIDENCE RES INNCE RESIDENCE RESIDEKCE RESIDENCE RESIDENCE RES INNCE RESIDENCE RESIDENCE RESIDEKCE RESIDENCE GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDEN GARDE K GARDEN GARDEN GARDEN GARDE K GARDEN GARDEN GARDEN DAIRY DAIRY DAIRY S SQI QI VSV II IANI NV NNV N NKE NE EKE f ESE SE SSE S SQI SV VSV V VKV NV NNI N NNE NE ENE E ESE SE SSE S SSV SV VSV V VKV NKV K NME Nf fNE E ESE SE SSE f E ESE ,3C.42.62 1.22 1.02.62 ,64.59 59.79~70.87~64 C9.42 34 1.00 90 I 50 1.10 1,20.80.80.60 1.30 1.00 2.30 2.10 1.40.50.CO AO 1.10 1,20 1.90 1.10 1.20 1.30 90 4.00 1.30 1.10 2.30 2.40 1.40 2.50 60 4.50 4.60 2.70 S49.d70.1315.1965.lbC9.992.1037.951.1266.1121.1398.135C.$49.1609.1448.2415.1770.1HI.1287.1287.2092.1609.3702.3361.2253.605.966.1770.1HI.3059.1770.1H I.2092.14C8.6436.2092.'I 770.3TOZ.3663.2253.CDZ4.1287.7244.7405.4346.6.691E.06 9e441E.06 7obHE 06 lo096E 05 d.349E 06 7.137E.06 6.813K 06 d.3SSE 06 5.6646.06 4.6535.06 4:191E 06 1.6968.06 I,OC1E 06 1.792E-06 2.19CE 06 3.653E.06 1.4SZE 06 3.'112E.06 3.160E-06 1.267K.OS 4.976E 06 4,885E 06 5.391E 06 6.210E.06 1.797E.06 3.d77K.06 7.719K 07 4.6Hf 07 4~C'ZIE 07 1.764E 06 2.377E 06 1.702E 06 1,2C7E 06 2.015E.06 2.236K 06 1.2)3E.OS 4 976K.06 2.319E 06 4,356K 06 3.873E.07 1.797$.06.3.185f.06 7.719K 07 3.938E 07 4.C21E 07 1.235E 07 Io323E 06 1.'162E 06 6.516E 08 bo266E 05 1.076E.07 dA52E.06 9AZIE 06 7ASSE.06 1.055E.05 6.306E.06 7.105E.06 d.787E 06 6.334K 06 Sodddf 06 4 663K 06 C-179E.06 la693E 06 1.038K.06 1+790K~06 2.192K 06 3obSOE.Ob 1.4CTE.06 3.0968.06 3.131E.06 1.256K.OS 4.937E 06 4.560K 06 5.365E 06 6.1ME 06).763K 063.6SDE.06 7.649E.07 4.661E 07 4.CD3E.07 1.7dlf 06 2.374E 06 1.699E 06 1.242E 06 2.003E 06 2.211K 06 1.26CE 05 4.H7E~06 2.300E 06 C.362K 06 3.755E F 07 1.783E 06 3.167E 06 7AC9E~07 3 907E F 07 4.COSE 07 IoZZSE 07 I o321fiN I 1S9E 06 6.C2SE.M e.1796.08'.067E 07 6.240E 06 8.709E 06 6 6IIE 06 9,4C2E 06 5.$38E 06 6.4238.06 6.115E 06 5.736E.06 5.131E 06 4.334E 06 3.7C7E 06 1.499K 06 9.204E.07 1ASTE 06 2.023E 06 3AOTK.06 1.270E 06 2,739K~06 2.d77E 06 1.100E.OS 4,290E 06 4.330K 06 4.779K 06 S.S99E 06 1.S40E 06 3.214K 06 6,290E 07 3.661K 07 3.771E 07 1.610E Ob Zst96E 06 1.$35E 06 II083K 06 1.739K 06 1.855E'06 1.105K 05 4.290K'06 1.966E~Oe 3.660E Ob 2.9SCE 07 1.$COE 06 2.765K 06 6.290K.07 3'96E 07 3.7/IE 07 9.979E 08 I 19CE 06 1.03IE 06 4.907E 08 4 706E 06 6AZSE 08 3.820E 06 3.722f 08 1.7d7E 08 1A52E 08 1.016E 08 1.4C3E 05 1.9)36~08 2.002E~08 1.566E~06 1.664K 05 2.551K~M 1.33SE 05 7.$808~09 1.320K 05 1.911E 05 2.926E.05 67871E 09 loMDE 06 e.7378.09 1.729E.08 7o5826.09 9.6096.09 1.448K 05 1 945K 08 4.819E i 09 1.167E 05 3.954K 09 3.0$7E 09 2.MSE 09 I.296K N 2.056E'05 1.252K M 5.767K.09 6.544E 09 4.013K.09.1.737E.M 7.5626.09 ,3.9676.09 1.143E M 6.970E 10 4.819E 09'1.001E 08 3 954K 09.2ADCE 09 2oMSE i09 6AOZE~10 I 0778 05 8.090E.09 3.178E~10 3.038E~10 S.S46E 10 66 Page 15 of 15 TABLE 22 AVERAGE ANNUAL RELATIVE CONCENTRATIONS 4.679K 08 4.426K 08 1.309K 07 1.362K.07 4.835K 07 4.SOSE F 07 3.4ME.07 2.946K 07 1.740E 08 5.719K.06 4,898K 07 3A13E 07 4.158E.06 6$99.6760.4185.4990.6117.8049.6760.1127.4.10 4.20 2.60 3.90 3.00 3.10 3.50 3.80 14.00 2,00 5.00 4.20.70 4.618K 08 4.367E 08 1,3008.07 1,340E 07 4.761E 07 4.433K 07 3.3968-07 2.888K.07 1.dlbE.08 5A4SE.06 4.739E 07 3.S268.07 4.146E.06 5 DAIRY ESE 5 DAIRY ESE 5 DAIRY SE 5 DAIRY 5 5 DAIRY SSV 5 DAIRY SSV 5 DAIRT SSV 5 DAIRY SSV 5 DAIRY SSV 5 DAIRY VSV S DAI kY V 5 DAIRY NNV S RIVERLANDS/EIC Nf VENT AHD SUILDINC PlkAHETERS:

kELEASE NEICHT (NETERS)9 60 DIAHETER (NKTERS)00 EXIT VELOCITY tN/SEC)e00 3.S67K.08 3.364K.08 1.054E-07 1,044E 07 3.824K 07 3.S49E 07 2AKSE 07 2.263K 07 1.074E 08 4.71 8K.06 3.617K.07 2.737E.07 3.716E.06 kf P VINO NEI CRT (IIETf RS)10+0 RUILD INC NEI CRT (NETKRS)dl.3 RLDC.NIN,CRS,SEC.AREA tSO.NETEkS) 2STS,O NEAT EN I 55 IOI RATE (CAL/SEC).0 AT THE NEASURED VIND kEICNT (TO+0 NETERS)I VKNl kELEASE Ntef VINO SPEED tNETERS/SKC)

STARLE CQS I 7 I OIS LKSS THAN, 000 SETVEEN+000 AND+000 ASOVE,OOO AT THE RELEASE HEICHI: I VENT RELEASE IHOE Vile SPEED (NETKkS/SEC)

I ELEVlTED LESS THAN+000 I NI XED SETVEEN oO(m lND 000 f Ck(XHm LEVEL ASOVE e000 I 2.167K-10 2.037E~10 7A74E 10 4.486E~10 1,189E 09 lo095E 09 8.052E.10 b.dSTE~10 2.609E-11 6.33)K.09 4 e121E-10 6.386K-ID 2.8SSE.08 VINO SPEED (Nflfkk/SEC)

UHSTASLE/NEUTRAL C(WDITIONS LESS THlN.000 RE)VEEN.000 AHD.000 ASOVE 000 67 SECTION 4 DOSE MEASUREMENTS AND ASSESSMENTS 68 Radiolo icaI Im act 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 (LLD)outlined in the SSES Technical Specifications.

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 quarterly averaged 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, as measured by environmental thermoluminescent dosimeters located around the plant contributed a maximum of 4.23E-03 mrem (measured at TLD Location 11S3)at the Protected Area Boundary southwest of the plant.The maximum organ/total body dose (child lung, 1.1 miles WSW: Table 26)from all airborne effluent is 1.27E-01 mrem.The maximum organ/total body dose from liquid effluent (adult Gl-LLI: Table 24)is 1.00E-01 mrem.If it is conservatively assumed that a member of the public receives the maximum total body/organ dose from liquid and gaseous combined with the maximum total body dose determined from direct radiation, the result (2.31E-01 mrem)is (1%of the 40CFR190 limit of 25 mrem to total body/organ (except thyroid).Doses to a maximally exposed member of the public from waterborne effluents are 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 in each quarter and the entire year, are shown in Table 23.TABLE 23 SITE-SPECIFIC PARAMETERS USED FOR LADTAP II CALCULATIONS (DANVILLE RECEIVER)FOR 1996 PARAMETER Cooling Tower Blowdown (CFS)Average Net River Level (ft)(1)Dilution Factor at Danville (2)Transit time to Danville (hr)(2)ENTIRE YEAR 17.3 5.3 284.1 32.3 (1)Net River Level=Depth (ft above MSL)-483'2)From ODCIVI Table 5-4 69 I

Summaries of maximum individual doses resulting from airborne and waterborne radioactive effluent releases are given in Table 24.Meteorological data from Section 3 were used to calculate the dose from airborne effluents.

Technical Specification 6.9.1.11 requires assessment of radiation doses from radioactive airborne and waterborne effluent to members of the public within the site boundary.There are no significant exposure pathways from waterborne effluents in these areas.Onsite doses are assessed relative to offsite dose values and are adjusted for appropriate dispersion and occupancy factors.Summaries of.the calculated maximum onsite doses resulting from airborne effluents are presented in Tables 25 through 26.70 TABLE 24

SUMMARY

OF MAXIMUM INDIVIDUAL OFFSITE DOSES AND DOSE COMMITMENTS TO MEMBERS OF THE PUBLIC DATA PERIOD'/1/95 TO 12/31/95EFFLUENT

':A"GE GROUP APPLICABLE

'ORGAN ESTIMATED MAXIMUM DOSE MREM LOCATION DIST AFFECTED MILES SECTOR PERCENT OF LIMIT LIMIT (M REM)~~~Li uid'i uid'EEN TOTAL BODY ADULT GI-LLI 2.14E-02 1.00E-01 0.71 1.00 10 Noble Gas Noble Gas Noble Gas N/A N/A N/A AIR DOSE (GAMMA-MRAD AIR DOSE (BETA-MRAD TOTAL BODY 7.10E-03 9.10E-03 4.69E-03 1.10 1.10 1.10 WSW WSW WSW 0.07 0.05 0.09 10 20 Noble Gas ue aud cula s N/A SKIN CHILD LUNG 1.24E-02 6.27E-02 1.10 1.10 WSW WSW 0.08 0.42 15 15"'Estimated dose is based on a site total activity release."'10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year.

"'Doses from liquid effluent are estimated from fish ingestion and shoreline exposure at the site outfall and from the drinking water pathway at Danville, PA.AIRBORNE PATHWAYS ANALYZED: 0.40 (SE): PLUME, GROUND, INHALATION; 1.10 (WSW)~PLUME, GROUND, VEGETATION, INHALATION; 2.00 (WSW)DAIRY: PLUME, GROUND, VEGETATION, COW MILK, INHALATION WATERBORNE PATHWAYS ANALYZED: FISH, DRINKING WATER, SHORELINE The maximum calculated dose from all 1995 SSES waterborne effluent (combined pathways)was 1.00E-01 mrem (ADULT, GI-LLI).The maximum calculated dose from all 1995 SSES airborne effluent (both units)at 0.40 miles (SE sector)was 1.22E-02 mrem (TEEN, LUNG).The maximum calculated dose from all 1995 SSES airborne effluent (both units)at 1.10 miles (WSW sector)was 1.27E-01 mrem (CHILD, LUNG).maximum calculated dose from all 1995 SSES airborne effluent (both units)at 2.00 miles SW)was 7.26E-02 mrem (CHILD, LUNG).71 DOSES TO MEMBERS OF THE PUBLIC WITHIN THE SITE BOUNDARY SSES Technical Specification 6.9.1.11 requires that the Annual Effluent Release Reports include an assessment of the radiation dose from radioactive effluents to members of the public within the site boundary.Within the SSES site boundary there are three areas which are open to members of the public (See Figure 8):~The Susquehanna Riverlands Recreation Area/Energy Information Center~Residences in the southeast and west southwest sectors 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 Riverlands/Information Center complex each year.For dose calculations, the visitor stays in the area for one hour.Use of the GASPAR 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.In order to compute doses to members of the public who stay for only short periods of time, these doses are converted to dose rates which are averages for the entire year.Taking into account the estimated 100,000 person-hours of occupancy, the collective (person-rem) doses shown in Table 25 are calculated.

Calculated doses for residences within the SSES site boundary for the following sectors are presented in Table 26.~southeast (0.40 miles)'west southwest (1.10 miles)72

'1

.FIGURE 8 AREAS.WITHIN THE SSES SITE BOUNDARY, OPEN TO MEMBERS OF THE PUBLlC IIW,~~at4.~Qa 0~Q+IS 0&0 1.\~K~$~I I~I I V~+~op lr o&.-l No I I own Vai~>\~~'l I I~~I I I I~ga~sas e~'0 0 SW I e~awl.I II I I I I'a uP~\Pl'SUSQUEHANNA STEAM ELECTRIC STATION SITE BOUNDARY DISTANCES (DISTANCES IN FEETl~PENNSYLVANIA POWER 4 UGHT HALUBURTON NUS Navsmber 02,.1993 LC0%0 S v Pf IL hwnt,koe4pl aeaer%keel aors~Locskn4tor cbee cakuhtiona

.~L ace o ooo aooo oooo 73 TABLE 25 CALCULATED COLLECTIVE DOSES TO MEMBERS OF THE PUBLIC WITHIN THE RIVERLANDS/INFORMATION CENTER COMPLEX DATA PERIOD: 1/1/95 TO 12/31/95 EFFL'UENT.'AGE GROUP-APPLICABLE ORGAN'MAXIMUM DOSE RATE" MREM/HR COL'L'ECTIVE DOSE PERSON-REM NOBLE GAS N/A TOTAL BODY 2.90E-07 2.90E-05 NOBLE GAS N/A SKIN 7.66E-07 7.66E-05 IODINE AND PARTICULATES TEEN LUNG 1.95E-06 1.95E-04 Estimated maximum dose rate is based on a site total activity release.PATHWAYS ANALYZED: PLUME, GROUND, INHALATION The maximum calculated dose from all 1995 SSES airborne effluent (both units)at this location was 1.97E-02 mrem (TEEN, LUNG).74 TABLE 26 CALCULATED DOSES FOR RESIDENCES WITHIN THE SSES SITE BOUNDARY 0.40 MILES SE SECTOR DATA PERIOD: 1/1/95 TO 12/31/95--."-EFFLUENT AGE GROUP APPLICABLE ORGAN ESTIMATED, PERCENT MAXIMUM DOSE'OF (M REM)LIMIT LIMIT MREM NOBLE GAS N/A TOTAL BODY 8.98E-04 0.02 NOBLE GAS N/A SKIN 2.37E-03 0.02 15 IODINE AND PARTICULATES TEEN LUNG 6.07E-03 0.04 15 10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year.

PATHWAYS ANALYZED: PLUME, GROUND, INHALATION The maximum calculated dose from all 1995 airborne effluent (both units)at this location was 1.22E-02 mrem (TEEN, LUNG).CALCULATED DOSES FOR RESIDENCES WITHIN THE SSES SITE BOUNDARY 1.10 MILES WSW SECTOR DATA PERIOD: 1/1/95 TO 12/31/95 EFFLUENT AGE GROUP APPLICABLE ORGAN ESTIMATED PERCENT MAXIMUM DOSE OF (MREM)LIMIT LIMIT MREM NOBLE GAS N/A TOTAL BODY 4.69E-03 0.09 NOBLE GAS N/A SKIN 1.24E-02 0.08 15 IODINE AND PARTICULATES CHILD LUNG 4.86E-02 0.32 15 10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year.

PATHWAYS ANALYZED: PLUME, GROUND, VEGETATION, INHALATION t The maximum calculated dose from all 1995 SSES airborne effluent (both units)at this location was 1.27E-01 mrem (CHILD, LUNG).75 TABLE 27 CALCULATED DOSES FOR NEAREST DAIRY FACILITY 2.00 MILES WSW SECTOR DATA PERIOD'/1/95 TO 12/31/95:";:;EFFLUENT AGE'PPLICABLE

'GROUP.ORGAN ESTIMATED MAXIMUM DOSE mrem PERCENT OF LIMIT LIMIT mrem Noble Gas N/A Total Bod 2.06E-03 0.04 Noble Gas Iodine and Particulates N/A Child Skin Lung 5.44E-03 3.64E-02 0.04 0.24 15'15 10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year.

PATHWAYS ANALYZED: PLUME, GROUND, INHALATION, VEGETATION AND COW MILK INGESTION The maximum calculated dose from all 1995 airborne effluent (both units)at this location was 7.26E-02 mrem (CHILD, LUNG).76 SECTION 5 CHANGES TO THE OFFSITE DOSE CALCULA TION MANUAL AND THE SOLID MfASTE PROCESS CONTROL PROGRAM 77 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL The SSES ODCM was revised four times in 1995.The changes in 1995 are designated Revisions 2 through 5 by SSES Document Control Center.In Revision 2, Section 10.3 (Evaluation and Monitoring Criteria for Effluent Pathways)was expanded to show specific plant systems evaluated in the categories NOT AN EFFLUENT PATHWAY (listed in new Table 8), and INSIGNIFICANT EFFLUENT~PATHWAY (listed in new Table 9).References for the bases for these evaluations are included for each system in the Table.Unless otherwise listed, most of the systems were evaluated in PPRL Calculation EC-ENVR-1 008, which was performed in response to NRC Open Item 91-10-01-07.

This revision to the ODCM was submitted in response to NRC Open,Item 91-1 0-01-08.ODCM Equations 7,8, 17 and 18 were revised to show the Gamma Shielding'Factor (Si:).This factor has always been used in GASPAR calculations (NRC code referenced in the ODCM)for whole body and skin dose from noble gas effluent.The equations were revised to be consistent with the application of the GASPAR code.The Gamma Shielding Factor (=0.7 for the Maximally-Exposed Member of the Public)is taken from Reg.Guide 1.109 Table E-15.Sections 8.1 and 8.3 were revised to reflect the current state of liquid and solid radwaste processing, respectively.

Figures 1, 3 and 4 have also been updated to show changes to liquid and solid radwaste processing systems, including vendor interfaces, based on information from Effluents Management.

Revision 2 was submitted to SSES PORC (1/1 9/95)and approved (1/20/95).

In Revision 3, Table 6 (Operational Environmental Monitoring Program)was corrected to show information originally in Revision 1 of the ODCM (approved 10/14/94).

Some information in this table was noted to be incorrectly carried into Revision 2.Table 6 was not intended to be changed in any way in Revision 2.This information was documented as a status control issue in SOOR 95-045;corrections were made in resolution to that SOOR.Slight changes were made to Figure 1, Liquid Radwaste System Flow Diagram.These changes made the pathway from the distillate sample tank to the cooling tower blowdown pipe clearer, and to correct labeling of distillate sample tank pumps OP-327 A, B and LRW Sample Tank pumps OP-305 A, B and C.In Section 10.9.c.2, reference 10CFR20.302 is changed to 10CFR20.2002 to be consistent with the revision in the numbering of this regulation.

78 1 40 System classifications and references are added to Table 8 (NOT AN EFFLUENT PATHWAY)and Table 9 (INSIGNIFICANT EFFLUENT PATHWAY).Table 10 (SIGNIFICANT EFFLUENT PATHWAY)is added with references.

Section 11 is revised to state that ODCM revisions shall be reviewed by PORC after approval by the Manager-Nuclear Technology..

Revision 3 was submitted to SSES PORC (3/30/95)and approved (3/30/95).

In Revision 4, three milk sampling stations (10G1, 10D1 and 10D2)were inadvertently deleted in Revision 3 Table 6.These deletions were not noted in Revision 3 Table 6, which was submitted in resolution to SOOR 95-045.The name of the restaurant at TLD station 6A4 was deleted to make the description more generic (to allow for ownership change)in response to a PORC comment from the meeting on March 30, 1995.Revision 4 was approved by the Manger-Nuclear Technology (4/17/95)and reviewed by SSES PORC (4/20/95).

In Revision 5, the introduction was changed to specify that reference to MPC limits in 10CFR20 Appendix B apply to those limits in effect prior to January 1, 1994, and continuing in effect until such time that revised 10CFR20 Appendix B limits are implemented at SSES.A description of systems with NRC I/E Bulletin 80-10 applicability was added to Section 10.3.Reference was made to Table 11, which lists the 80-10 systems by number and name.Table 9 was revised to include Refuel Water Storage Tank with Condensate Storage Tank and Berm, and H>Seal Oil with Main Turbine/RFPT Lube Oil.The Sewage Treatment Plant was added to Table 9.Reference notes for these changes were located in the appropriate tables.Table 11 (Systems with NRC I/E Bulletin Applicability) was added to the ODCM.The Sewage Treatment Plant was added to Table 11 in response to PORC Meeting 95-098 Action Item E05532.Section 11 (ODCM Review and Revision Control)was repaginated to follow Tables 8-11 of Section 10.Reference to revision in accordance with NEPM-QA-1011 was added, which was submitted as an Action to Prevent Recurrence in SOOR 95-045.The distribution of ODCM copies was revised to indicate SSES Document Control Services, which replaced the staff of the Nuclear Department Library.79 Revision 5 was approved by the Manger-Nuclear Technology (7/17/95)and reviewed by SSES PORC (7/20/95).

Consistent with the requirements of Technical Specification 6.14.2.2, the revised methodology and parameters do not reduce the accuracy or reliability of dose calculations or setpoint determinations.

Copies of Revisions 2, 3, 4, and 5 of the SSES ODCM are included under separate cover in Appendix A.80 CHANGES TO THE SOLID WASTE PROCESS CONTROL PROGRAM The SSES Solid Radioactive Waste Process Control Program, NDAP-QA-0646, was reviewed and found acceptable by the PORC (PORC Meeting 95-041)during the report pel'Iod.Revision 4 to NDAP-QA-0646 incorporated PCAF 1-94-1 330 revising the PCP implementing procedure matrix to reflect actual procedures in use, and changed the requirements for disposal of radioactive waste samples after packaged radioactive waste has been in its designated storage area.PCAF 1-94-1 330 was incorporated into NDAP-QA-0646.

This PCAF was implemented due to the unavailability of offsite disposal facilities.

A review of existing regulatory guidance and implementing procedures reveals no requirement to store radioactive waste samples after the packaged radioactive waste is placed into its designated storage area.Existing records provide reasonable assurance that the waste has been properly analyzed.The Procedure Matrix (Attachment D)has been revised to reflect changes in the procedures.

Pages 11, 31, 57 and 59 were affected by this PCAF.These changes did not reduce the overall conformance of the solidified waste'product to existing criteria.A copy of SSES Radioactive Waste Process Control Program, NDAP-QA-0646, Revision 4, is included under separate cover as Appendix B.Added SEG NRC-approved Topical Report STD-P-05-001-P-A to Contracted Vendor Services to reflect use of SEG for waste processing equipment, methods and verification of acceptable waste forms for dewatering and solidification.

Added-Activated Carbon as a new waste type which is generated from processing of liquid wastes using vendor-provided demineralization services.Added the Solidification/Dewatering/Services Vendor may perform test solidification and determination of mixing ratios for solidification performed offsite (vendor facility).

Added Radlok (SEG)-type containers to High Integrity Container approved for use list.Added SNM inventory requirements during processing per SOOR 94-581 resolution.

Added NRC Technical Position on Concentration Averaging and Encapsulation to Radioactive Waste Analysis and Classification to ensure that radionuclide/

concentrations are adequately distributed over the volume or weight of the waste.81

SECTION 6 REPORTS OF EXCEPTION TO THE SSES EFFLUENT MONITORING PROGRAM 82 I

REPORTS OF EXCEPTION TO THE SSES EFFLUENT MONITORING PROGRAM No occurrences were indicated in 1995 where an instrument was INOPERABLE for a duration subject to the reporting conditions of Technical Specifications 3.3.7.10b or 3.3.7.11.b.

83 SECTION 7 CORRECTION TO DOSES REPORTED IN PREVIOUS SEMIANNUAL OR ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 84 CORRECTIONS TO DOSES REPORTED IN PREVIOUS SEMIANNUAL OR ANNUAL EFFLUENT AND WASTE DISPOSAL REPORTS During the preparation of calculations to determine the nuclear fuel cycle (40CFR190) dose to the public contribution from a proposed independent spent fuel storage.installation (ISFSI)at SSES, it.was noted that the program GASPAR rejected Ag-110m in the airborne source term.Ag-110m was reported in airborne samples from SSES only in 1985, however, it does enter the database for effluent calculations for the ISFSI licensing basis.This discrepancy caused a Condition Report (CR-95-0743) to be issued.During the investigation of this Condition Report, it was noted that Ag-110m was reported in Table 3 of the SSES Semiannual Effluent and Waste Disposal Reports for 1985.The isotope was grieved, however, in the GASPAR calculation submitted for that period, and it was not included in the determination of dose to Members of the Public reported at that time (February 1986).A separate gaseous dose calculation has been performed for the Ag-110m released in 1985, using the dose calculation factors in the SSES ODCM, and the actual dispersion (XIQ, D/Q)estimates for the offsite receivers reported for the period.Table 28 shows the maximum doses for the release of 148 pCi Ag-110m in 1985, calculated by maximum age group and organ for each of four receiver locations:

TABLE 28 AIRBORNE EFFLUENT OFFSITE DOSE FROM Ag-110m: 1985 LOCATION PATHWAYS AGE GROUP ORGAN DOSE mrem 0.7 miles WSW Site Bounda 1.7 miles WSW Dai Animal 1.2 miles WSW Garden 1,6 1, 2, 3, 5, 6 1, 5, 6 Teen Teen Teen Lun G.I.G.l.8.75 E-04 6.04 E-04 3.98 E-04 1.2 miles WSW Resident 1,2,3,4,5,6 Teen G.l.1.17 E-03 where pathway 1=ground shine 2=goat milk ingestion 3=cow milk ingestion 4=meat ingestion 5=vegetable ingestion 6=inhalation The highest dose calculated (1.17 E-03 mrem)from Ag-110m is approximately 1%of that reported for Members of the Public due to all other airborne iodine and particulate

.effluent in 1985.85 SECTION S EFFLUENT FROM ADDITIONAL MONITORED RELEASE POINTS 86

EFFLUENT FROM ADDITIONAL MONITORED RELEASE POINTS The temporary laundry facility is a processing system located in a trailer at the north end of the plant, near the radwaste building.Since the facility processes contaminated laundry, the trailer atmosphere is sampled routinely for airborne activity.The effluent potential for this system was determined in Safety Evaluation NL-90-029.

It has been classified as an Insignificant Effluent Pathway in the ODCM.The facility has been in continuous use since 1991.Airborne effluent.samples have been taken since operations began, with results typically indicating below detection level.In 1995, several air samples taken from the trailer were noted to have Mn-54 above the minimum detectable activity.The following airborne particulate effluent and resulting offsite dose to members of the public at the residence 1.1 miles WSW is reported for the temporary laundry facility.This effluent and resulting offsite dose is reported supplementary to Tables 3, 4, 24 and 26 since it is minor relative to the quantities reported therein (i.e.not observable at three significant figures): TABLE 29 AIRBORNE PARTICULATE EFFLUENT FROM LAUNDRY TRAILER Isoto e Effluent Released Ci Mn-54 6.54E-08 TABLE 30 OFFSITE DOSE (RESIDENCE AT 1.1 MILES WSW)RESULTING FROM LAUNDRY TRAILER EFFLUENT'EFFLUENT'GE GROUP APPLICABLE ORGAN ESTIMATED MAXIMUM DOSE MREM LIMIT MREM'PERCENT",OF L'IMIT"-'.Particulate Teen Lun 9.51E-08 15 6.34E-07 87 APPENDIX A REVISIONS TO SSES ODCM

PENNSYLVANIA POWER 5 LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL Revision 2Prepared By Date Reviewed By Supervisor-Environmen al Services Nuc ear Reviewed By ing o.Approved By 4.A Manager-Nuclear Technology Date//Oate Date

SUMMARY

OF ODCN CHANGES Changes other than those of a minor, editorial nature are summarized below.1.Section 10.3 (Evaluation and Monitoring Criteria for Effluent Pathways)has been expanded to show specific plant systems evaluated in the categories NOT AN EFFLUENT PATHWAY (listed in new Table 8), and INSIGNIFICANT EFFLUENT PATHWAY (listed in new Table 9).References for the bases for these evaluations are included for each system in the Table.Unless otherwise listed, most of the systems were evaluated in PP8L Calculation EC-ENVR-1008, which was performed in response to NRC Open Item 91-10-01-07.

This revision to the ODCM is submitted in response to NRC Open Item 91-10-01-08.

2.Equations 7, 8, 17 and 18 are revised to show the Gamma Shielding Factor (Sq).This factor has always been used in GASPAR calculations (NRC code referenced in the ODCM)for whole body and skin dose from noble gas effluent: the equations are revised to be consistent with the application of the GASPAR code.The Gamma Shielding Factor (0.7 for'he Maximally-Exposed Member of the.Public)is taken from Reg.Guide 1.109 Table E-15.3.'ections 8.1 and 8.3 have been revised to reflect the current state of liquid and sol,id radwaste processing, respectively.

Figures 1, 3 and 4 have also been updated to show changes to liquid and solid radwaste processing systems, including vendor interfaces, based on information from Effluents Management.

Rev.2 TABLE OF CONTENTS APPROVAL PAGE DATE REVISION DATE

1.0 INTRODUCTION

.

2.0 SETPOINTS...............................

~.2.1 WATERBORNE EFFLUENT MONITORS..........

2.2 AIRBORNE EFFLUENT MONITORS............

3.0 WATERBORNE EFFLUENT CONCENTRATION MEASUREM 4.0 AIRBORNE EFFLUENT DOSE RATES.............

4.1 NOBLE GASES.......

4.2 RADIONUCLIDES OTHER THAN NOBLE GASES..5.0 INDIVIDUAL DOSE DUE TO WATERBORNE EFFLUENT 5.1 FISH PATHWAY LIQUID EFFLUENT DOSE CALCULATION METHODOLOGY....

5.2 POTABLE WATER PATHWAY EFFLUENT DOSE CALCULATION METHODOLOGY...............

5.3 SHORELINE EXPOSURE PATHWAY., 5.4 PROJECTED DOSE FROM LIQUID EFFLUENT...

I 6.0 INDIVIDUAL DOSE DUE TO AIRBORNE EFFLUENT..

6.1 NOBLE GASES........

6.2 RADIONUCLIDES OTHER THAN NOBLE GASES..7.0 TOTAL DOSE 8.0 OPERABILITY OF WASTE TREATMENT SYSTEMS....

8.1 LIQUID WASTE TREATMENT................

8.2 GASEOUS WASTE TREATMENT.

8.3 SOLID WASTE TREATMENT.......,.........

~t~~~~~~~~~~ENTS~~~~~~~~~~~~~~~~~~~~~~~~~~~~~1~~~~~~~~~~~~~~~~~~~~~2 3 4 5 6 7 8 9 10 11 12 13 14 15 15 16 17 18 19 20 21 22 23 24 24 25 26 27 27 28 29 30 31 32 32 33'34 36 37 10/29/93 2/5/92 11/9/93'/5/92 2/5/92 12/11/89 2/5/92 12/11/89 12/11/89 2/5/92 12/11/89 12/11/89 11/21/92 2/5/92 2/5/92 2/5/92 1/16/95 1/16/95 2/11/92 2/5/92 12/11/89 12/1/92 10/29/93 3/11/94 2/21/92 3/ll/94 2/21/92 2/21/92'12/11/89 2/21/92 12/11/89 12/11/89 2/21/92 12/11/89 12/11/89 11/25/92 2/21/92 2/21/92 2/21/92 1/20/95 1/20/95 2/21/92~2/21/92 12/11/89 12/4/92 3/11/94 ll/9/93 ll/9/93 ll/9/93 2/18/94 ll/9/93 10/29/93 10/29/93 10/29/93 10/29/93 1/16/95 10/29/93 10/29/93 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 3/11/94 3/11/94 3/ll/94 3/11/94 3/ll/94 3/ll/94 3/11/94 3/11/94 3/ll'/94 1/20/95 3/ll/94 3/ll/94 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 2/18/94 3/11/94 DAT Pev.2 a E APPROVAL REVISION PAGE DATE DATE 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.9.1 DEFINITIONS...............................

9.2 MONITORING PROGRAM...

9.3 CENSUS PROGRAM...............'.............

9.4 INTERLABORATORY COMPARISON PROGRAM........

42 42 42 43 44 45 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 10.0 DOSE 10.1 10.2 10.3 10.4 10.5 10.6 10.7 10.8 10.9 ASSESSMENT POLICY STATEMENTS............

SELECTION OF ANALYSIS RESULTS FOR DOSE CALCULATIONS ASSIGNMENT OF RELEASES TO THE REACTOR UNITS EVALUATION AND MONITORING CRITERIA FOR EFFLUENT PATHWAYS FLOW FROM THE SGTS VENT WHEN THE SYSTEM IS NOT IN USE ODCH SETPOINTS ARE UPPER LIHIT VALUES DEFINITION OF"APPROPRIATE TREATMENT" FOR LIQUID WASTES HONITOR LINE-LOSS CORRECTIONS SELECTION OF DATA FOR DETERMINATION OF DOSE RATE COMPLIANCE LOW-LEVEL RADIOACTIVITY IN THE SEWAGE TREATMENT PLANT 53 53 53 53 54 55 55 57 57 58 1/16/95 1/16/95 1/20/95 1/20/95 1/16/95 1/16/95 1/16/95 1/16/95 1/20/95 1/20/95 1/20/95 1/20/95 1/16/95 1/20/95 1/16/95 1/20/95 1/16/95 1/20/95 1/16/95 1/20/95 11.0 ODCH REVIEW AND REVISION CONTROL.............

APPENDIX A-SAMPLE CALCULATIONS OF ODCM PARAMETERS...........................

I APPENDIX B-REPORTING REQUIREMENTS...............

60 A-1 A-2 A-3 A-4 A-5 A-6 A-7 A-8 A-9 A-10 A-1 1 A-12 A-13 B-l B-2 B-3 8-4 1/16/95 2/5/92 2/5/92 12/11/89 2/5/92 10/29/93 10/29/93 10/29/93 10/29/93 2/5/92 2/5/92 10/29/93 10/29/93 10/29/93 12/11/89 10/29/93 12/11/89 12/11/89 1/20/95 2/21/92 2/21/92 12/11/89 2/21/92 3/ll/94 3/ll/94 3/ll/94 3/ll/94 2/21/92 2/21/92 3/ll/94 3/ll/94 3/ll/94 12/11/89 3/ll/94 12/11/89 12/11/89 DAT Rev.2

~'V' PAGE APPROVAL DATE REVISION DATE 5-6c Composite Dose Factors: Haximum Hypothetical Child (2pp)....................................5-6c(1,2) 2/18/94 5-6d Water Ingestion Dose Factors: Haximum Hypothetical Infant (2pp)......................5-6d(1,2) 2/18/94 3/ll/94 3/ll/94 6 Operational Radiological Environmental Honitoring Program.......................

48 49 50 1/16/95 1/16/95 1/16/95 1/20/95 1/20/95 1/20/95 7 Detection Capabilities for Environmental Sample Analysis................

.............

51 52 8 Systems Classified as Not an Effluent Pathway...

61 1/16/95 1/20/95 1/16/95 1/20/95 1/16/95 1/20/95 9 Systems Classified as Insigni'ficant Effluent p athwayo~~~~~~~~0~~~~~~~~~~~~~~~~~~~~~~62 1/16/95 1/20/95 D-1 Dilution Factors and Transit Times for SSES Effluents to Oanville, PA...........

.D-1 B-l Radiological Environmental Honitoring Program Annual Summary..............................

8-3 B-2 Reporting Levels for Nonroutine Operating eportso~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~t B 4 R 12/11/89 ll/9/93 3/ll/94 3/ll/94 12/11/89 12/11/89 LIST OF FIGURES APPROVAL REVISION PAGE DATE DATE Figure 2 Offgas and Recombiner System F'tow Diagram........

~~~~~~o 39 Figure 3 Solid Waste Management System Flow Oiagram..........................

40 Figure 4 SSES Dry Contaminated Waste Processing............................

41 Figure 5 Environmental Monitoring Locations Within One Mile of SSES...'............

46 Figure 6 Environmental Monitoring Locations Greater than One Mile from SSES.......

47 Figure 1 Liquid Radwaste System Flow Diagram.......................:..

38 1/16/95 1/20/95 1/16/95 1/20/95 1/16/95 1/20/95 1/16/95 1/20/95 1/16/95 1/20/95 1/16/95'/20/95DAT Rev.2 vi

4.0 AIRBORNE EFFLUENT DOSE RATES SPECIFICATION 3.11.2.1.THE DOSE RATE DUE TO RADIOACTIVE MATERIALS RELEASED IN GASEOUS EFFLUENTS FROM THE SITE (SEE FIGURE 5.1.3-1)SHALL BE LIMITED TO THE FOLLOWING:

a.FOR NOBLE GASES: LESS THAN OR EQUAL TO 500 MREM/YR TO THE TOTAL BODY AND LESS THAN OR EQUAL TO 3000 MREM/YR TO THE SKIN, AND b.FOR IODINE-131, FOR TRITIUM, AND FOR ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS: LESS THAN OR EQUAL TO 1500 MREM/YR TO ANY ORGAN (INHALATION PATHWAY ONLY).4.1~IIOB i AEEK Noble gas activity monitor setpoints are established at release rates which permit some margin for corrective action to be taken before exceeding offsite dose rates corresponding to the 10 CFR 20 annual dose limits as described in Section 2.2.The methods for sampling and analysis of continuous ventilation.releases are given in the applicable plant procedures.

The dose rate in unrestricted areas due to radioactive materials released in airborne effluents may be determined by the following equation for whole body dose: Z (Ki(X/Q)v (Q')v)(Sp) 1 and by the following equation for skin dose: D g[L.+((1.11 (Mi)(S~))](X/Q)(Q'))

~1 (Eq.7)(Eq 8)DAT'Rev.2 15 N J 4.0 AIRBORNE EFFLU NT DOSE RATES SP CIF CATION 3.1.2.1.THE DOSE RATE DUE TO RADIOACTIVE MATERIALS RELEASED IN GASEOUS EFFLUENTS FROM THE SITE (SEE FIGURE 5.1.3-1)SHALL BE LIMITED TO THE FOLLOWING:

a~b.FOR NOBLE GASES: LESS THAN OR EQUAL TO 500 MREM/YR TO THE TOTAL BODY AND LESS THAN OR EQUAL TO 3000 MREM/YR TO THE SKIN, AND FOR IODINE-131, FOR TRITIUM, AND FOR ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS: LESS THAN OR EQUAL TO 1500 MREM/YR TO ANY ORGAN (INHALATION PATHWAY ONLY).0'4.1 N~OB aAS Noble gas activity monitor setpoints are established at release rates which permit some margin for corrective action to be taken before exceeding offsite dose rates corresponding to the 10 CFR 20, annual dose limits as described in Section 2.2.The methods for sampling and analysis of continuous ventilation releases are gi'ven in the applicable plant procedures.

The dose rate in unrestricted areas due to radioactive materials released in airborne effluents may be determined by the, following equation for whole body dose: Z ()(/0)y (0'fy)(p)1 and by the following equation for skin dose: D g[L+((1.11 (Mi)(Sr))j (X/9)v (9'iv)~1 (Eq 7)(Eq 8)DAT'Rev.2 15" where: K.the whole-body dose factor due to gamma emissions for each iden)ified noble gas radionuclide (i)(mrem/yr per uCi/m)from Table 2.the release rate of radionuclide (i)from vent (v)(uCi/sec).(X/g)the highest calculated annual average relative concentration for any area at or beyond the site boundary in an u~restricted area from vent release point (v)(sec/m)such as from Table 3.wb Li the annual whole-body dose (mrem/yr).

the skin dose factor due to the beta emissions for each iden)ified noble gas radionuclide (i)(mrem/yr per uCi/m)from Table 2.the air dose factor due to gamma emissions for each identjfied noble gas radionuclide (i)(mrad/yr per'Ci/m)from Table 2 (conversion constant of 1.1 converts air dose-mrad to skin dose-mrem).

D the annual skin dose (mrem/yr).

s S, the gamma shielding factor (0.7 for maximally exposed individual)

Sample calculations for determining whole body and skin doses from noble gas radionuclides released from the SSES are given in Section A.2.1 of Appendix A.'4.2 RADIONUCLIDES OTHER THAN NOB E GASES The methods for sampling and analysis of continuous ventilation releases for radioiodines and radioactive particulates are given in the applicable plant procedures.

Additional monthly and quarterly analyses shall be performed in accordance with Table 4.11.2.1.2-1 of the SSES Technical Specifications.

The dose rate in unrestricted I areas due to inhalation of radioactive materials released in OAT Rev.2 16

7.0 OT 0 C 0 3.-THE ANNUAL'(CALENDAR YEAR)DOSE OR DOSE COMMITMENT TO ANY MEMBER OF THE PUBLIC, DUE TO RELEASES OF RADIOACTIVITY AND RADIATION, FROM URANIUM FUEL CYCLE SOURCES SHALL BE LIMITED TO LESS THAN OR EQUAL TO 25 MREMS TO THE TOTAL BODY OR ANY ORGAN EXCEPT THE THYROID, WHICH SHALL BE LIMITED TO LESS.THAN OR EQUAL TO 75 MREMS.The cumulative dose to any member of the public due to radioactive releases from the SSES site is determined by sumaing the calculated doses to critical organs from the previously discussed effluent sources.The annual dose to critical organs of a maximally exposed individual for the liquid effluents is determined by using Equations 10, ll, and 12 of Section 5..The annual dose to critical organs of a real individual for the noble gases released in the gaseous effluents is determined by.using Equation 14 modified by replacing M.with K.from Table 2 for the whole-1 i body dose and by Equation 15 modified by replacing Ni by[Li+((1.11 Mi)(S,))]from Table 2 for the skin dose of Section 6.0: 1 D3 1 7x 10Ki (X/g)v(g)y)(Sp)(Eq.17)Db 3.17 x 10 fL.+((l.llM.)(S,))](X/g)(g',.)(Eq.18)The annual dose to critical organs of a real individual for the radionuclides other than noble gases released in the gaseous effluents is determined by using Equation 16 of Section 6.0.For all dose calculations from airborne effluents, the deposition rate used in the analysis should be at the receptor location of the individual being evaluated, not the highest calculated annual aver age relative concentration or relative deposition rate for any area at or beyond the site boundary as given in Table 3.The direct radiation from the site should be determined from the environmental monitoring program's direct radiation (TLD)monitors.Since all other uranium fuel cycle sources are greater than 20 miles away, only the SSES site need be considered as a uranium fuel cycle source for meeting the EPA regulations.

In actual practice, the LADTAP and GASPAR computer code developed by the NRC to implement the liquid and gaseous dose methodology of Regulatory Guide 1.109 will be used to perform the total dose.calculations for the I DAT Rev.2 30 1

8.0 P TY F WA T AT T SYST M AS T SP CIF CATION 3.11..3-THE LIQUID RADWASTE TREATMENT SYSTEM, AS DESCRIBED IN THE ODCM, SHALL BE OPERABLE.THE APPROPRIATE PORTIONS OF THE SYSTEM SHALL BE USED TO REDUCE THE RADIOACTIVE MATERIALS IN LIQUID WASTE PRIOR TO THEIR DISCHARGE WHEN THE PROJECTED DOSES DUE TO THE LIQUID EFFLUENT, FROM EACH REACTOR UNIT, TO UNRESTRICTED AREA (SEE FIGURE 5.1.3-1)WOULD EXCEED 0.06 MREM TO THE TOTAL BODY OR 0.2 MREM TO ANY ORGAN IN A 31-DAY PERIOD.The SSES Liquid Rad Waste Management system consists of three processing sub-systems, liquid, chemical and laundry.Redundant and backup equipment, alternate process routes, interconnections and spare volumes are designed into the system to provide for operational and unanticipated surge waste volumes due to refueling, abnormal leakage rates, decontamination activities and equipment'owntime, maintenance and repair.The Liquid Rad Waste Management System processes equipment drain and floor drain liquids collected in a common plant drainage system.The system also processes filter backwash, resin transfer liquids and resin cleaning liquids.The system has piping connections to allow the installation of vendor-supplied equipment to provide specific treatment of off-normal wastes or to enhance the normal treatment capabilities as necessary.

Appropriate vendor-supplied equipment may also be used in place of installed equipm'ent to allow for'epair or replacement of components.

Low conductivity liquid wastes are processed in the Liquid Radwaste Treatment Sub-system.

Liquid is collected in three pairs of LRW Collection tanks.Each pair of tanks has an approximate capacity of 28,000 gallons.Surge capacity is maintained with two pairs LRW Surge Tanks also with a 28,000 gallon/pair capacity.DAT Liquids from these tanks are normally processed through two vertical centrifugal discharge precoat filters with 300 ft filter area at a 200 gpm normal flow rate.Liquid from the filters is then sent to a mixed bed demineralizer with a volume of 140 ft and normal.flow rate of 200 gpm.The demineralizer effluent is collected in three pairs of LRW Sample Tanks.Each 32 Rev.2 pair of tanks has an'pproximate capacity of 28, 100 gallons.The water is isolated in these tanks for analysis prior to recycle to Unit 1 or discharge to the Susquehanna river.Off-specification liquids can be recycled back to the Liquid Rad Waste Management System, for additional processing.

High conductivity wastes are collected in the Chemical Drain Tank and in specific sumps located in the Turbine and Radwaste Buildings.

Liquid from these sources is collected in a Chemical ,'Waste Tank of approximately 12,000 gallons capacity.This liquid can then be sent to any one of two pairs of Chemical Waste Neutralizing Tanks.Each pair has a capacity of 31,000 gallons.The liquid is then sent to a vendor-supplied Chemical Waste Processing Sub-system for radionuclide removal.The effluent from the Chemical Waste Processing Sub-system is routed to the Evaporator Distillate Sample Tank where it can be isolated for analysis prior to discharge.

The capability exists to return the liquid to the Liquid Rad Waste Management System for additional processing if necessary.

The Laundry Waste Sub-system collects water from washdown, laundry and decontamination facilities in one of two Laundry Drain Tanks.Each tank has a capacity of approximately 820 gallons and has an independent mechanical filter system.One tank is normally valved to receive waste while the other is valved for processing.

Effluent from these tanks is routed to the Laundry Drain Sample Tank where it can be isolated for analysis prior to discharge.

Non-specification liquid can be returned to the Chemical Waste Processing Sub-system.

A flow diagram of the Liquid Radwaste Management System is shown in Figure l.OAT Appropriate treatment for liquid effluents from SSES is defined in ODCN Policy Statement 10.6;In cases when a batch of liquid waste must be released with treatment less than that specified in Section 10.6, a dose assessment using LADTAP or the methodology 33 Rev.2" of Section 5.4 shall be performed prior to release to ensure that the limits of Specification 3.11.1.3 are not exceeded.8.2 GAS OUS S T ATMENT SPECIFICATION 3.11.2.4-THE GASEOUS RADWASTE TREATMENT SYSTEM SHALL BE IN OPERATION.

~PP CAE'IIIENEYER TIII MAIN CIINRENEER AIR ECECTIIR TETACYATIIINT SYSTEM IS IN OPERATION.

SPEC FIC ON 3.1.2.5-THE APPROPRIATE PORTIONS OF THE VENTILATION EXHAUST TREATMENT SYSTEM SHALL BE OPERABLE AND SHALL BE USED TO REDUCE RADIOACTIVE MATERIALS IN GASEOUS WASTE PRIOR TO THEIR DISCHARGE WHEN THE PROJECTED DOSES DUE TO GASEOUS EFFLUENT RELEASES FROM EACH REACTOR UNIT TO AREAS AT AND BEYOND THE SITE BOUNDARY (SEE, FIGURE 5.1.3-1)WHEN AVERAGED OVER 31 DAYS WOULD EXCEED 0.3 MREM TO ANY ORGAN IN A 31-DAY'ERIOD.

The SSES off gas treatment system operates with four steam jet ai'r ejectors maintaining cond'enser vacuum.Noncondensible gases are passed through one of three recombiners (one for each reactor unit plus a common recombiner), reducing the amount of gases to be filtered and released.Gases pass through a two to nine minute holdup pipe before entering the off gas treatment system, which consists of one 100 percent capacity system per reactor unit.Each system consists of precoolers, chillers, reheaters, guard beds, and five charcoal absorbers and an outlet HEPA filter.Monitored, filtered air then exits to the turbine building vent.A flow diagram of the off gas and recombiner system is shown in Figure 2.I OAT Filtered exhaust systems serve selected areas of Zone I, II, and III of the SSES reactor building.The Zone I and Zone II equipment compartment and Zone III filtered exhaust systems each consist of two 100'apacity redundant fans and two 55X capacity filter trains.Each filter train has, in the direction of air flow, roughing filters, upstream HEPA filters, a charcoal filter bed, and downstream HEPA filters.Exhaust fan discharge is then routed to the atmosphere via the reactor building vents, where effluents are continuously sampled and monitored.

\Rev.2

The turbine building filtered exhaust system draws air from those areas of the building that are most likely to become contaminated.

Two 100X capacity fans serve each system, which contains two 50X capacity filter housings made up of a particulate prefilter, an upstream HEPA filter, a charcoal filter, and a downstream HEPA filter.Discharged air is released via the turbine building vents, which are continuously sampled and monitored.

The radwaste building filtered exhaust system draws potentially contaminated air from selected areas of the radwaste building.The system contains two 100X capacity fans and two 50X capacity filter housings, each containing a particulate filter bank and a HEPA filter.Filtered air is discharged via the turbine building vent.In order to minimize the quantities of radioactivity in airborne effluents from the station, the ventilation exhaust treatment (filtered exhaust)systems are normally kept in service at SSES.As the need arises, these systems are periodically rendered inoperable for maintenance'or testing activities.

If the most recent 31-day dose projection indicates that dose may exceed 0.3 mRem to any organ when averaged over the projected 31-day period, treatment systems rendered inoperable will be restored to operable status as quickly as is practicable.

The dose projections are performed at least once per 31 days based on the most recently available effluent data.If it is known prior to performing the dose projection that a treatment system will be out of service, and.if data exists which indicates how the lack of treatment will impact effluents, these factors will be considered when performing the dose projection.

At'r V DAT Rev.2 35 8.3 SO I WAST T T NT P 0-THE SOLID RADWASTE SYSTEM SHALL BE USED IN ACCORDANCE WITH A PROCESS CONTROL PROGRAM, FOR THE PROCESSING AND PACKAGING OF RADIOACTIVE WASTES TO ENSURE MEETING THE REQUIREMENTS OF 10 CFR PART 20, 10 CFR PART 71, AND FEDERAL REGULATIONS COVERING THE DISPOSAL OF THE WASTE.The SSES solid r adwaste system collects all wet wastes produced from the operation of other plant systems.The wastes are then processed and packaged by a vendor-supplied system into a waste form'hat meets all applicable Federal, State and local requirements for transportation, storage and disposal.The processing methodology and acceptance criteria for the final waste forms are controlled by the Process Control Program.Filter material from the Reactor Water Clean-up Systems and the Fuel Pool Clean-up Systems are collected in Backwash Receiving Tanks.There is one RWCU tank per unit, each with a capacity pf approximately 2450 gallons and one similar tank for the FPCU System.Wastes from these tanks are directed to one of two 6300 gallon capacity Phase Separators.

Normally, one'hase'Separator is valved to collect waste while the other is isolated to provide time for radioactive decay.The solid content of the waste is concentrated in the Phase Separator and transferred and processed through a vendor-supplied system and packaged for storage or final disposal.The supernatant liquid is collected and processed by the Liquid Rad Waste Management System.The Waste Sludge Phase Separator is a 9500 gallon capacity phase separator tank that accepts input from the Regen Waste Surge Tanks.The concentrated waste is then transferred and processed through a vendor-supplied system and packaged for storage or final disposal;The supernatant liquid is collected and processed by the Liquid Rad Waste Management System.DAT Rev.2 36 Spent bead resin from the Condensate System and from the Liquid Radwaste Demineralizer

'are collected in the Spent Resin Tank.These are then processed through a vendor-supplied system and packaged for storage or final disposal.Spent filter material from the Liquid Radwaste Filters are collected in two Waste Hixing Tanks.The contents of these tanks are-processed through a vendor-supplied system and packaged for storage or final disposal.A flow diagram of the SSES solid radwaste treatment system is shown in Figure 3.Dry Active Waste (DAW)consists of contaminated plastic, paper, clothing, metal or other trash and is collected throughout the RCA of SSES.OAW is processed and packaged for storage or disposal using off-site vendor-supplied super compaction and incineration services.OAW may also be compacted with an on-site'drum compactor into 55-gallon drums.An automated DAW monitoring system is used to ensure non-radiological waste collected in the RCA is free from radiological contamination prior to release.A flow diagram of DAW processing at SSES is shown in Figure 4.Rev.2 37 EVAP.STEAM CONDS.TANK PHASE SEPARATORS (DECANTATE)

RHR SYSTEM Rwcu SYSTEM REACTOR WELL SEAL LEAK DRAIN REACTOR BLDG.DRAINS+-DRYWELL DRAINS TLSBINE BLDG.DRAINS AADWASTE BLDG.DRAINS LIQUID RADWASTE FIGURE LIQUID RADWASTE SYSTEM FLOW DIAGRAM LIQUID RADWASTE COLLECTION 8 SURGE TAHKS OT.302 A THRU F OT.304 A THRU D LIGUID RADWASTE FILTERS OF-302 A,B LIGUID RADWASTE DEN INERALIZEA OF-301 LIauID RADWASTE SAMPLE TANKS OT-303 A THRU F CONDENSATE DEVIH.RESIN AEGHERATIHQ TANK LRW COLLECTION TANK PNLPS OP-301 h>B,C TO WASTE MIXINQ TANKS OT-307 A,B TO SPENT AESIH TANK OT-324 CONDENSATE STORAGE TANKS OT-522 A,B CHEVI GAL WASTE HEUTAALIZEA TANKS 1T-130 A,B 2T~130 A,B CST BEAM WATEASAMPLE STATIONS AUX BOILER BLOWDOWNS RWCU CHEVICAL DECON.LAB AHD DECOH.DRAINS LAUM)RY DRAINS REGLAATED SHOP DRAINS PERSONAL DECONTAM-INATION{OETEAGEHTS)

CASK CLEAHIHG DRAINS CHEMICAL WASTE TANK OT-314 CHEM.WASTE NEUTRALIZING TANK P NIPS 1P 130 A>8 2P-130 A,B CHEM WAS'TE TANK PWPS OP-328 A>8 RADWASTE EVAPORATOR OE-302 A,B CHEMICAL WASTE PAOCESSINQ SUB-SYSTEM (VENDOR SUPPLIED)DISTILLATE SAMPLE TANK OT-321 EVAPORATOR COHCENTRATE STORAGE TANK OT-322 LRW SAMPLE TANK PLNPS OP-305 A>B,C RE TO CODLING TOWER BLOW-DOWN PIPE TO WASTE MIXING TANKS OT-307 A>8 DAT t6 LAUNDRY DRAIN TANK OT-314 A,B Rev.2 LAUNDRY DAAIN TANK PUMPS OP.318 A>8 LAUHDRY DRAIN FILTERS OF-318 A>8 LAUNDRY DRAIN SAMPLE TANK OT-312 CONCENTRATE BTORAGE TANK DISCH.PQIP OP-328 LAUNORV DRAIN SAMPLE TANK PUMPS OP.319 A,B Of F GAS RF COMBINE R SYSlf M I AMBIEN t TEMPF RATURE CI<aRCOAI OFF GAS SYSTEM UNIT I MaIN d AUX SIEAM Slf AM JET AIR EJECIOR UNII I IURBINE SLOG E X I I A US t UNIT I IF 302OU LET HEPAFILTE IIAR QAL AOS RBEII BE 5 F ROM>NII I Nhlil Stf AII COII OTII Tfh UIIII'il 5 I AGE STEA>JET A'I 5 EJEC 1011 COB Df II.SEII OI F IIAS BYPASS E L HE ai I RACING l-Qr-------)

I DILUTION STEAM I I I I I 2na STAGA 2 I I E 13h I'R f HE A IE II 15 125 RECOMB VESSEL I 04-'E 131 RECOMB COND IE 13i MOT I VE STEAM JET 5 COND DELAY PFPE I 112 IF IA~IE IA IE 3 A 5 IT 303a INLET PRE CIIILI ER~Z GUARO NEPA COOl.f fi us B 0 F ILTE R Z it 3ia it 305 IT.30B ii301 il 3aa Q COMMON OFFGAS RECOMBINER SYS'EM IIAI1s STEA COII DER.SEII Ohlt t SIEAM JET AIR f JECTOR CONDENSER UNI'T 2 DELAY PIPE AMBIENT TEMPERATURE CIIAIICOAL OFFGASSYSTfM UNIT 2 MAIte 5 AUX Stf AU PROD UNIT 2 OFFGAS BYPASS OFFGAS RECOMBINER SYSTEM 2 TURBINE BLOG EXHAUST UNIT 2 FIGURE 2 OFFGAS AND RECOHBIHER SYSTEM FLOH DIAGRAM OAT Rev.2 FIGURE 3 SOLID WASTE MANAGEMENT SYSTEM FLOW DIAGRAM CONDENSATE DEMIH RESIH STORAGE VESSEL 1T-159 RADWASTE DEMI HERAL IZER STORAGE VESSEL OF-301 CONDENSATE DEMIH RESIN STORAGE VESSEL 2T-158 FUEL POOL F/0 BACKWASH RECEIVINO TANK OT-203.RWCU BACKWASH RECEIVING TANK 1T-225 RWCU BACKWASH RECEIVINO TANK 2T-225 SPENT RESIH TANK OT-324 REGEH WASTE SUADE TANKS 1T-108 A,B REOEN WASTE SURGE TANKS 2T-108 A,B SPENT RESIN TRANSFER PUMP OP-320 1P-108 A,B REGEHERATIOH WASTE TRANSFER PUMPS I TO VENDOR LIOUIO RAWASTE FILTERS OF-302 A>8 WASTE SLUDGE DISCHARGE IIIXIHG PUMP OP-332 TO RWSS PUMP WASTE SLUDGE PHASE SEPARATOR OT-331 RWCU PHASE SEPARATOR OT-318 A RWCU PHASE SEPARATOR OT-318 B WASTE MIXING TAHKS OT-307 A,B TO VEHDOR TO RWSS PUMP EVAPORATOR.

CONCENTRATE STORAGE TANK DISCHARGE PUMP OP-328 EVAPORATOR COHCENTRATE STORAGE TANK OT-322 RWCU SLUDGE DISCHARGE lllXIHG PUMP OP-3N FROM EVAPORATOR DAT Rev.2 FIGURE 4 SSES ORY ACTIVE WASTE (OAW)PROCESSING Non-radiological Trash from RCA Paper, Plastic, Rags, Clothing from RCA Second-Sort DAW Dry Active Waste (DAW)Monitoring System PPKL Radioactive?

Yes Vendor Ser vices Supercompaction Incineration Drum Compactor 55-gal.Drums or Boxes No Free Released zr OAT Rev.2 9.0 RAD OG C NVI 0 NTA MON TORING PROGRAH~~N.l~NN TIIINN Weekly: Once in each calendar week at intervals of approximately 7 days, plus or minus 2 days.Semi-Monthly:

Twice each calendar month at intervals of approximately 15 days, plus or minus 4 days.Honthly.Once each calendar month at intervals of approximately 30 days, plus or minus 6 days.quarterly:

Once in each three month period of a calendar year at intervals of approximately 13 weeks, plus or minus 3 weeks.9.2 MONITOR NG PROGRAH SP C FIC TION 3.1-THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SHALL BE CONDUCTED AS SPECIFIED IN TABLE 3.12.1-1.Environmental samples shall be collected and analyzed (as a mini'mum)according to Table 6 at locations shown in Figures 5 and 6.Analytical techniques used shall ensure that the detection capabilities in Table 7 are achieved.A dust loading study (RHC-TR-81-01) was conducted to assure that the proper transmission factor was used in calculating gross beta activity of air particulate samples.This study concluded that the sample collection frequency of once per week was sufficient and that the use of 1 for the transmission correction factor for gross beta analysis of air particulate samples is valid.The charcoal sampler cartridges used in the airborne radioiodine sampling program (Science Applications, Inc., Model CP-100)are designed and tested by the manufacturer to assure a high quality of radioiodine capture.A certificate from the manufacturer is supplied and retained with each batch of cartridges certifying the percent retention of radioiodine versus air flow rate through the'cartridge.

DAT Rev.2 42 The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent monitoring by veri fying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways'hus, the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and fo those radionuclides which lead to the highest potential radiation exposures of individuals resulting from station operation.

Program changes may be proposed based on operational experience.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability malfunction of automatic sampling equipment, and other legitimate reasons.If specimens are unobtainable due to sampling equipment malfunction, an effort shall be made to complete corrective action prior to the end of the next sampling period.All deviations from the sampling schedule shall'be documented in the next Annual Radioactive Effluent and Waste Disposal report.Reporting requirements for the radiological environmental surveillance program are given in Appendix BE 9.3 CENSUS PROGRAM SPECIFICATION 3.12.2-A LAND-USE CENSUS SHALL BE CONDUCTED AND SHALL IDENTIFY WITHIN A DISTANCE OF 8 KM (5 MILES)THE LOCATION IN EACH OF THE 16 METEOROLOGICAL SECTORS OF THE NEAREST MILK ANIMAL THE NEAREST RESIDENCE AND THE NEAREST GARDEN*OF GREATER THAN 50 M (500 FT~)PRODUCING BROAD LEAF VEGETATION

• .Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two di r ecti on sector s wi th the highest predicted 0/9'in lieu of the garden census~Specifications for broad leaf vegetation sampling in Table 3.12.1-1, item 4C shall be foll owed, including analysis of control samples pAy/$J Rev.2 43

If a land use census identifies a location(s) with a higher average annual deposition rate (D/Q)than a current indicator location, the following shall apply: l.If the D/Q is at least 20 percent greater than a previously high D/Q, the new location shall be added to the program within 30 days of documented identification of sampling feasibility.

The indicator location having the lowest D/Q may be dropped from the program after October 31 of the year in which the land use census was'conducted.

2.If the D/Q is not 20 percent greater than the previously highest D/Q, direction,.distance, and D/Q will be considered in deciding whether to replace one of the existing sample locations.

If applicable, replacement shall be within 30 days.Any evaluations of possible location replacement should include the p'ast history of the location, availability of sample, milk production history, and other applicable environmental conditions.

A land use census will be conducted at least once per calendar year by a door-to-door or aerial survey, by consulting local agricultural authorities, or by any combination of these methods.9,4 INTERLABORATORY COMPARISON PROGRAM SPECIFICATION 3.12.3-ANALYSES SHALL BE PERFORMED ON RADIOACTIVE MATERIALS SUPPLIED AS PART OF AN INTERLABORATORY COMPARISON PROGRAM WHICH HAS BEEN APPROVED BY THE COMMISSION.

The laboratories of the licensee and licensee's contractors which perform analyses shall participate in the Environmental Protection Agency's (EPA's)Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck)

Program or an equivalent program which has been approved by the Commission.

This participation shall include some of the'determinations (sample medium-radionuclide combination) that are offered by EPA and that are also included in the monitoring program.The results of the analyses of these crosscheck samples shall be included in the annual report.A DAT Rev.2 44 If the results of an'alyses performed by the licensee or licensee's contractor in conjunction with the EPA crosscheck program (or equivalent program)are outside the specified control limits, the laboratory shall investigate the cause of the problem and take steps to correct it.The results of this i'nvestigation and corrective action shall be included in the Annual Radiological Environmental Operating Report.Rev.2 45

'I FIGURE 5 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE SSES GOULD ISLAND I I I I 13 I I r--~I I I ma@Qa or/~f o~l/Q~QS3 C a~I g, Q p p~m~~m~~eel f5$1~~I,g~52~/3$l T~b$7~bN T I LAKE~TAW SITE BOUNDARY 1 NILE SUSQUEHANNA RIVER 4 svaiux sam T DOSQtElRY DAT~Rev.2

FIGURE 6 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN ONE MILE FROM THE SSES 15F1 T 15F1 SUSQUEHANNA RIVER I NANTICOKE GLEN LYON 14 SHICKSHINNY gn MOCANAQUA 1483 T~4E2 POND HILL T 12}{2 Etl I BERWICK err.MIFFLINVILLE SSES I T i gg WAPWALLOPEN.T gj~iRI 1%2'~T NESCOPECK gg TiRa 5 NILES CON YNGHAM/1B NILES HAZLETON~m DRSQNC INTER~i saagncr THERMDLDMNESCENT DQSMERY OATF Rev.2 47 TABLE 6 OPERATIOHAL RADIOL06ICAL ENVIRDHHENTAL HONITORING PR06RAil Page I o Exposure Pathways and or 5 le Airborne Radioiodine and Particulates*

lrect Radiation Nraaber of Samples and Locat1 ons~1251 0.4 ml MSM-E.O.F.Building 12EI 4.7 ml MSM-Berwlck Hospital 7GI 14 ml SE-PPSL Hazleton Complex 1053 0.6 ml SSM-East of Confer's Lane, South of Towers Club 13S6 0.4 ml M-Former Laydown Area, Mest of Confer's Lane 1S2 Perimeter Fence-0.2 ml.N ID2 Hocanaqua-4.0 ml H 253 Perimeter Fence-0.2 ml NHE 283 Ourabond Corporation

-'1.3 ml HHE 2FI St.Adalberts Cemetery-5.9 ml NNE 3S4 Perimeter Fence-0.3 ml HE 301 Pond Iiill/Lily Lake Fire Co.-3.4 mi HE 3FI Valanla Residence-9.1 ml HE 3G5 Mllkes-Barre-Parrish St.Substatlon-16 ml HE'S3'Mest of SSES APF-0.2 mi ENE 4E1 Ruckles HI)I Road Pole (t)46422/H35197

-4.8 ml ENE 4GI Crestwood Industrial Park-14 ml ENE'S7 Perimeter Fence-0.3 ml E 5E2 Bloss Farm-4.5 mi E 6S4 Perimeter Fence-0.2 ml ESE 6A4 Riverside Restaurant

-0.6 ml ESE Sarrpl 1ng and Continual sampler operation with sample collection weekly.'*~Quarterly Type and Radioiodine Canister: analyze weekly for 1-131 Particulate Sample: Analyze for gross beta radioactivity less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.Perform isotopic analysis on composite sarrple (by location)quarterly.

Garrrna Dose: Quarterly.

DAT Rev.2

Page 2 o Exposure Pathways and or le Neer of San@les and Locations~

6E1 St.James Church-4.7 mi ESE 659 Perimeter Fence-0.2 mi ESE 756 Perimeter Fence-'0.2 mi SE 7EI Harwood Transmission Line Pole N2-4.2 mi SE 7G1 PPSL Hazleton Complex-14 mi SE'52 Perimeter Fence-0.2 mi SSE BB2 LaVall Residence-1.4 mi SSE 803 Howry Residence-4.0 mi SSE 9S2 Security Fence-0.2 mi 5 9D4 Country Folk Store-3.6 mi S 10S1 Post South of Switching Station-0.4 mi SSV 10D1 Ross Ryman Farm-3.0 mi SSM 1153 Security Fence-0.3 mi SM 11E1 Thomas Residence-4.7 mi SV 1253 Perimeter Fence-0.4 mi MSM 12E1 Berwick Hospital-4.7 mi MSV 12G1 PPSL Bloomsburg Service Center-15 mi MSV'3S2 Perimeter Fence-0.4 mi M 13E4 Kessler Farm-4.1 mi V 1455 Beach.Grove Rd.8 Confer's Lane intersection 0.5 mi VNV 14E1 Canouse Farm-4.1 mi VNM 15F1 Lawatski Farm-5.4 mi NM 1555 Perimeter Fence-0.4 mi NV 16S1 Perimeter Fence-0.3 mi NNV 1652 Perimeter Fence-0.3 mi NNV 16F1 Hidlay Residence-7.8 NNV Sandal ing and Col lection F uenc Type and o Vaterborne Surface Drinking Sediment from Shoreline 656 river water intake line'S7 cooling tower blowdown discharge line 12H2 Oanville Mater Co.(Approximately 30 miles downstream) 78 Bell Bend,-1.2 mi SE Monthly composite Honthly composite Honthly composite Semi-annually Ganma isotopic analysis.Composite tritltsn analysis at least quarterly.

Gross beta and gasma isotopic analyses monthly.Composite for tritium analysis at least quarterly.

Gasma isotopic analysis'semi-annually.

OAT Rev.

Page 3 o Exposure Pathways HIIk~*~Fish and Invertebrates Food Products Nuxber of Samples~atat orat iona*1283 Young Farm-2.0 mi MSM 10GI Davis Farm-14 mi.SSN'OD2 Ray Ryman Farm-3.5 mi.SSM 10Dl R&C Ryman Farm-3.0 mi.SSM Outfall area 2H Falls, PA'Approximately 30 mi HNE)IID1 Lehner Farm-3.3.mi SV vegetable 12F7 Lupini Farm-8.3 mi WSM vegetable Sandal ing and Col lect i on F uenc Semi-monthly when animals are on pasture, monthly otherwise Semi-annually.

One sample'rom each of two reacreationally Important species from any of the following families: bullhead catfish, sunfish, pikes, or perches.At time of harvest Type and of l Gamma Isotopic and 1-131 analysis of each sample.Gasma Isotopic on edible portions.Gatnna I'sotopic on edible portions.*The location of samples and equipment were designed using the guidance In the 8ranch Technical Position to NRC Rev.Guide 4.8, Rev.1, Nov.1979, Reg.Guide 48.1975 and ORP/SID 72-2 Environ>>ntal Radioactivity Surveillance Guide.Therefore, the airborne sampler locations were based upon X/O and/or D/O.!"A dust loading study (RHC-TR-81-01) concluded that the assumption of I for the transmission correction factor for gross beta analysis of air particulate samples Is valid.Air particulate samples need not be weighed to determine a transmission correction factor."If a milk sample Is unavailable for more than two sampling periods from one or more of the locations, a vegetation sample shall be substituted until a suitable milk location Is evaluated.

Such an occurrence will be documented In the REHP annual report.a Control sample location.b Two-week composite If calculated doses due to consumption of water exceed one millirem per year.In these cases, 1-131 analyses will be performed.

c The sample collector will determine the species based upon availability, which may vary seasonally and yearly.AI'AT Rev.2 TABLE 7 DETECTION CAPABILITIES FOR ENVIRONNENTAL SNPLE ANALYSIS Lower Limit of Detection (LLD)A~nal sis gross beta H-3 Mn-54 Fe-59 Co-58 Zn-65 Zr-95 I-131 Cs-134 Cs-137 ea-140 La-140 Water Q)Ci~1 2000 30 15 30 30 1b 15 18 60 15 Airborne Particulate or Gas Cx 10 7 x 10 5 x 10 6 x 10 Fish Ci k wet 130 260 130 260 130 150 Milk Q)Ci~1 15 18 60 15 Food Products C k wet 60 60 80 Sediment C d 150 180 DW Rev.2 TABLE 7 (Continued)

The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability and with 5 percent probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system (which may include radiochemical separation):

LLD where: 4.66 sb 2.22 EVY exp (-A 4 t)LLD is the"a priori" lower limit of detection as defined above (as pCi per unit mass or volume).4 sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)E is the counting efficiency (as counts per transformation)

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

A is the radioactive decay constant for the particular radionuclide, and~t is the elapsed time between sample collection (or end of the sample collection period)and time of counting.In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background should include the contributions of other radio-nuclides normally present in the samples (e.g., potassium-40 milk samples).Typical values for E, V, Y, and t should be used in the calculations.

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

LLD for drinking water.DAT Rev.2 52

S S T P CY S AT H T 10.1 elect'o of A al s s Results or ose C lc lations For determination of compliance with SSES Technical Specification dose limits, effluent totals shall be based only on activity positively detected at the 95X confidence level.10.2 Assi nment of Releases to the Reactor U its V For determination of compliance with SSES radioactive effluent dose limits which are on a"per reactor unit" basis: a.Effluents from the Unit 1 Reactor Building vent and the Unit 1 Turbine Building vent shall be included as Unit 1 releases.b.Effluents from the'nit 2 Reactor Building vent and the Unit 2 Turbine Building vent shall be included as.Unit 2 releases.'.

Effluents from the Standby Gas Treatment System vent shall be equally divided between Unit 1 and Unit 2 release totals.d.Waterborne effluents shall be equally divided between Unit 1 and Unit 2 release totals.10.3 Evaluation and Monitorin Criteria or Effluent Pathw'a s Potential unmonitored effluent pathways will be evaluated on a case-by-case basis.Periodic sampling and/or realistic evaluation wi.ll be performed in order to demonstrate the significance of a potential effluent pathway.Results of sampling and/or evaluation may be used to classify a potential unmonitored effluent pathway into one of the following categories:

a.Not an Effluent Pathwa: Realistic evaluation (e.g., engineering design, system operation, radionuclide inventory) demonstrates that the pathway has no potential for release of radioactive material (Table 8).Although not required, periodic DAT Rev.2 53

'I 1 0'P sampling may at times be performed to confirm the result of the evaluation.

b.i t ffluent Pathw: Evaluation and/or periodic sampling demonstrate that the pathway may contain radioactive effluents, however, these effluents may not be reasonably expected to exceed 10 percent of the appropriate unrestricted area HPC value (fractional HPCs summed when appropriate) listed in Table II of Appendix 8 to 10 CFR 20 (Table 9).A'release pathway which falls in this category will be sampled periodically.

c.Si nificant ffluent Pathwa: Evaluation and/or periodic sampling demonstrate that the pathway may contain radioactive effluents, and these effluents may be reasonably expected to exceed 10 percent of the appropriate unrestricted area HPC value (fractional NPCs summed when appropriate) listed in Table II of Appendix B to 10 CFR 20.A release pathway which falls in this category will be sampled continuously.

Analyses of samples will be performed consistent with techniques used for samples of the same types collected from normal effluent pathways.Any radioactive materials detected in samples collected from either the Insignificant or the Significant Release Pathways will be included in determining'compliance with site dose limits.Additionally, any such occurrences will be reported in the Annual Effluent and Waste Disposal Report.10.4 Flow from the SGTS Vent when the S stem is Not in Use When the Standby Gas Treatment is not being used, there remains a small amount of flow from the SGTS vent.This residual flow is exhaust from the battery rooms in the control structure.

Because there are no identifiable sources of radioactivity in these rooms, auxiliary particulate and iodine sample and noble gas grab sample at 4-hour intervals are not required from the SGTS vent when the SGTS continuous vent monitor is out of service,~r vided that-4 Rev.2 e k a.the Standby Gas Treatment System is not being used, b.there are proper administrative controls in place to ensure that the required sampling will begin within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if the treatment system is operated.10.5 0 CH Set oin s are U er imit Va ues Effluent monitor alarm/trip setpoints calculated in accordance with the ODCN shall be considered upper limit values.Higher (less conservative).

setpoints shall not be used, however lower (more conservative) setpoints may be used as required to maximize the utility of the monitor.10.6 Defi tion of"A ro riate Treatment" for Li uid Wastes Technical Specification 3.11.1.3 requires that the appropriate portions of the liquid was'te treatment system be operable and be used to reduce radioactivity in liquid wastes prior to their release when projected doses from each reactor unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.o The normal treatment, which is considered appropriate for each subsystem, is as follows: Filtration is considered appropriate treatment for the Liquid Radwaste Laundry Processing Subsystem, which consists of high conductivity liquid wastes, such as those from equipment washdown and personnel decontamination facilities, or laundry.The atmospheric demineralizer (a vendor-supplied system which is directed to the Distillate Sample Tank)is considered appropriate for the Liquid Radwaste Chemical Processing Subsystem.

Rev.2 55 Demineralization and filtration are considered appropriate treatment for low conductivity/low organic contaminant liquid wastes entering the Liquid Radwaste Processing Subsystem (LRM collection tanks), except for batches which yield projected doses prior to treatment of less than or equal to 6.45-04 mrem to the total body and 2.15E-03 mrem to any organ, where filtration alone is appropriate, or o For batches which have no identified gamma activity above the Technical Specification Liquid Effluent LLD level (Table 4.11.1.1.1-1), release without treatment is considered appropriate.

BASES The projected dose threshold values used are derived by dividing the site-total maximum projected doses without treatment (0.12 and 0.4 mrem)by 31 days and by 6, the maximum possible number of batches released per day, to yield per-batch dose action levels.The two levels of"appropriate" treatment are in place so as not to require application of demineralization for treating low activity, high conductivity water (e.g., from Circulating or Service Mater leakage).This would increase the overall efficiency of the solid radwaste program while ensuring calculated doses remain at a suitable fraction of 10 CFR 50 design objectives and Technical Specification 3.11.1.2 1~~t (1)(2)~"'Reference Calculation No.OT-RKB-92-001:

Calculation of Liquid Isotope Offsite Dose Consequences for Use of Atmospheric Demineralizer System, PLI-70360, 2/4/92.DAT'Reference Letter R.K.Barclay to R.A.Breslin: Demineralizer Effluent Results, PLI-70612, 3/4/92.56 Rev.2 Atmospheric

10.7 it o s'rrections In order to correct for airborne effluent monitor sample line loss, the following correction factors shall be applied to monitor data and sample analysis results: 'N F THO T S COR C ON FACTO S ARE~PART CII R Reactor Building Unit 1 Reactor Building Unit 2 Turbine Building Unit 1 Standby Gas Treatment Turbine Building Unit 2 1.5 1.5 1.6 1.5 1.6 3.2 3.2 3.6 3.9 3.6POST ACCID T VENT MONITORS~CGRR CTIGA FACTIIRR~IODIII PARTICULATES Turbine Building Unit 1 Standby Gas Treatment Turbine Building Unit 2 1.7 1.6 1,.7 4.2 4.4 4.3 Each indicated iodine and particulates concentration shall be multiplied by the appropriate correction factor to estimate the actual concentration at the inlet to the sample line.10.8 Selection of Data for Determination of Dose Rate Com liance Airborne effluent monitor setpoints are maintained in accordance with Section 2.2.to alarm before the dose rate limits of Specification 3.11.2.1 are exceeded.Station alarm response procedures contain instructions for investigation and verification of monitor alarms.Because setpoint calculations must include assumptions about the composition of the monitored effluent, a monitor high alarm does not necessarily indicate that a dose rate limit has been exceeded.v DAT Rev.2 57

Valid ten-minute averaged data should be the primary information used to determine the compliance status of an incident.One-minute averaged data should also be reviewed if available, but they may or may not provide additional information depending on the magnitude of the release due to the manner in which the monitors update, values to be stored and associated statistical considerations.

Averages over a longer period should be used only when data with higher resolution is not available.

Grab sample analyses should be performed whenever possible to confirm or disprove monitor data, and to provide indication of the nuclide-.specific composition of the effluent.When grab sample data are available which, based on vent monitor data, are indicative of the period of elevated release, dose rate calculations should be performed using the actual effluent mix.The determination of compliance status should not be based on monitor data alone when it is possible to collect and analyze'vent sample which will be representative of the period of elevated release.10.9 Low-evel Radioactivit in the Sewa e Treatme t Plant Like all sewage processing facilities, the SSES sewage treatment plant can under certain conditions receive low levels of radioactive materials.

The most notable scenario is when individuals who work on-site have been subjected to the medical administration of radiopharmaceuticals for diagnostic or'herapeutic purposes.In these cases, normal biological elimination processes can easily result in levels of radioactivity in sewage treatment plant solutions and suspensions which are within the detection capabilities of the associated sampling and analysis program.Because disposal of sewage treatment plant sludge by.controlled dispersal on specified tracts of land is a common practice, the following guidelines have been established:

a.All sludge collected in the sludge holding tank should be sampled and analyzed prior to land disposal to quantify any DAT Rev.2 58 radioactivity present above natural background levels.b.Sludge containing nuclides with short half-lives, for example iodine-131, should be contained on-site to permit decay to less than detectable levels.c.When sludge is contaminated with nuclides which have half-lives sufficiently long to make hold-up for decay impractical, the following options should be considered:

1.Dispose of the sludge as low level radioactive waste.2.Obtain a special permit pursuant to the requirements of 10 CFR 20.302.d.The sewage treatment plant effluent should be sampled monthly for radioactivity.

This can be accomplished by drawing a sample from the chlorine contact chamber.DAT Rev.2 59 11.0 0 ON CONTRO The Supervisor-Environmental Services-Nuclear shall ensure that a total review of the ODCM is performed during each even-numbered year.Comments shall be documented and revisions initiate'd as appropriate.

Each ODCM page shall be numbered and provided with an approval and date box.The ODCH Table of Contents shall present the current revision date for each page so that any manual holder can check manual completeness based on a current Table of Contents.All ODCM revisions shall be reviewed by PORC before approval by the Manager-Nuclear Technology.

PORC review shall be indicated by PORC chairperson or designee signature on ODCH cover.ODCH copies shall be issued in a controlled fashion by the staff of the Nuclear Department Library.The distribution list shall be maintained by the Nuclear Department Library Staff.r Any comments on ODCM contents or proposed revisions should be directed to the Supervisor-Environmental Services-Nuclear.

DAT Rev.2 60

~8'I TABLE 8 SYSTENS CLASSIFIED AS NOT AN EFFLUENT PATHWAY (Page 1 of 2)Domestic Water SYSTEN DESCRIPTION REFERENCE River Water Hakeu Intake Com ressed Air Screens and Screenwash Fire Protection Water Fire Protection CO Fire Protection Halon Turbine Buildin Closed Coolin Water Buildin Drains: NON RAD Water Pretreatment Condensate and Refuel Water Transfer Low Pressure Air.Condensate Demins Lube Oil Transfer Purification Coolin Tower Acid Chlorination Circulatin Water Condenser Tube Cleanin Feedwater Extraction Steam Feedwater Heaters Residual Heat Removal Reactor.Core Isolation Coolin Core S ray Hi h Pressure Coolant Injection Standb Li uid Control Control Rod Drives (I)PP8L Calculation EC-ENVR-1008 DAT B Rev.2 61 TABLE 8 SYSTENS CLASSIFIED AS NOT AN EFFLUENT PATHWAY (Page 2 of 2)SYSTEN DESCRIPTION Su ression Pool Primar Containment Vacuum Breakers Su ression Pool Cleanu Reactor Water Cleanu Reactor Pressure Vessel Reactor Recirculation S stem Radwaste Chilled Mater Solid Radwaste Cement Silo LRW Collection Tb and Cond.Outer Area Sum s LRW Processin Radwaste Eva orator Gaseous Radwaste Recombiner Closed Coolin Water Nitro en Stora e H dro en Stora e Sam lin Stations Post Accident Sam lin S stem B ass Steam Hain Steam Isolation Valves/Nucle'ar'Steam Su 1 S stem Shutoff Automatic De ressurization S stem HSIV Leaka e Control Moisture Se arators Turbine Steam Seals Electroh draulic Control Stator Coolin Hain Generator Storm Drains REFERENCE (I)PP8L Calculation EC-ENVR-1008 r DAT Rev.2 62

TABLE 9 SYSTBlS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAY SYSTBl DESCRIPTION H Seal Oil Condensate Stora e Tank Hain Turbine RFPT Lube Oil Instrument Air Service Air Tem orar Laundr Facilit Second Sort DAW Volume Reduction Facilit.Low Level Radwaste Handlin Facilit REFERENCE (1)PP8L Calculation EC-ENVR-1008 (2)Safety Evaluation NL-90-029:

Temporary Laundry Facility (3)Safety Evaluation NL-89.-002:

Dry Active Waste Volume Reduction System (4)Safety Evaluation NL-92-007:

Operation of LLRWHF at SSES DAT Rev.2 63 It 0 PORC

SUMMARY

ODCH CHANGE 1 20 95 Section 10.3 (Evaluation and Monitoring Criteria for Effluent Pathways)has been expanded to show specific plant systems evaluated in the cate'gories NOT AN EFFLUENT PATHWAY (listed in new Table 8), and INSIGNIFICANT EFFLUENT PATHWAY (listed in new Table 9).References for the bases for these evaluations are included for each system in the Table.Unless otherwise listed, most of the systems were evaluated in PPKL Calculation EC-ENVR-1008, which was performed in.response to NRC Open Item 91-10-01-.07.

This revision to the ODCH is submitted in response to NRC Open Item 91-10-01-08.

J Equations 7, 8, 17 and 18 are revised to show the Gamma Shielding Factor (S).This factor has always been used in GASPAR calculations (NRC code referenced in the ODCH)for whole body and skin dose from noble gas effluent: the equations are revised to be consistent with the application of the GASPAR code.The Gamma Shielding Factor (0.7 for the Maximally-Exposed Member of the Public)is taken from Reg.Guide 1.109 Table E-15.Sections 8.1 and 8.3 have been revised to reflect the current state uf liquid and solid radwaste processing, respectively.

Figures 1, 3 and 4 have also been updated to show changes to liquid and solid radwaste processing systems, including vendor interfaces, based on information from Effluents Management.

Submitted by: Date: 1/16/95 Health Physicist-Operations Technology PENNSYLVANIA POMER 5 LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL Prepared By i4a-8 Zf cc Reviewed By Supervisor-Environmental Services Nuclear Reviewed By/eetsng o.Approved B Hanager-Nuclear Technology Date 8>>9S Date Date 9 Z~-PS Date'Z~a SUMNRY OF ODCll CHANGES Table 6, Operational Environmental Monitoring Program, has been corrected to show information originally in Revision 1 of the ODCM (approved 10/14/94).

Some information in this table was noted to be incorrectly carried into Revision 2 (approved 1/20/95).Table 6 was not intended to be changed in any way in Revision 2.This inconsistency was documented as a status control issue in,SOOR 95-045;corrections are made in resolution to this SOOR.Slight changes are made to Figure 1, Liquid Radwaste System Flow Diagram, to make the pathway from the distillate sample tank to the cooling tower blowdown pipe clearer, and to correct labeling of distillate sample tank pumps OP-327 A, B and LRM sample Tank Pumps OP-305 A, B, and C.In Section 10.9.c.2, reference 10CFR20.302 is changed to 10CFR20.2002 to be consistent with the revision in the numbering of this regulation.

System classifications and'references are added to Table 8 (Not an Effluent Pathway)and Table 9 (Insignificant Effluent Pathway).Table 10 (Significant Effluent Pathway)is added with references Section ll is revised to state that ODCM revisions shall be.reviewed by PORC after approval by the Manager-Nuclear Technology.

Rev.3 I'

APPROVAL~AG~DT REVISION~DATE 9.0 RADIOLOGICAL ENVIRONHENTAL MONITORING PROGRAM.9o 1 DEFINITIONS@

~~~~~~~~~~~~~~o~~e~~~~~~o~~~~~9.2 MONITORING PROGRAM..............-.........

9.3 CENSUS PROGRAM............................

9.4 INTERLABORATORY COMPARISON PROGRAM........

10.0 DOSE ASSESSMENT POLICY STATEMENTS............

10.1 SELECTION OF ANALYSIS RESULTS FOR DOSE CALCULATIONS 10.2 ASSIGNMENT OF RELEASES TO THE REACTOR UNITS 10.3 EVALUATION AND MONITORING CRITERIA FOR EFFLUENT PATHWAYS 10.4 FLOW FROM THE SGTS VENT WHEN THE SYSTEM IS NOT IN USE 10.5 ODCH SETPOINTS ARE UPPER LIMIT VALUES 10.6 DEFINITION OF"APPROPRIATE TREATHENT" FOR LIQUID WASTES 10.7 MONITOR LINE-LOSS CORRECTIONS 10.8 SELECTION OF DATA FOR DETERMINATION OF DOSE RATE COMPLIANCE 10.9 LOW-LEVEL RADIOACTIVITY IN THE SEWAGE TREATMENT PLANT 42 42 42 43 44 45 53 53 53 53 55 55 55 57 58 59 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 3/23/95 3/23/95 3/23/95 3/23/95 3/23/95 3/23/95 3/23/95 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 3/30/95 3/30/95 3/30/95 3/30/95 3/30/95 3/30/95 3/30/95 11.0 ODCM REVIEW AND REVISION CONTROL.............

60 3/30/95 3/30/95 APPENDIX A-SAMPLE CALCULATIONS OF ODCH PARAMETERS...........................

APPENDIX B-REPORTING REQUIREMENTS...............

A-1 A-2 A-3 A-4 A-5 A-6 A-7 A-8 A-9 A-10 A-ll A-12 A-13 B-1 B-2 B-3 B-4 2/5/92 2/5/92 12/11/89 2/5/92 10/29/93 10/29/93 10/29/93 10/29/93 2/5/92 2/5/92 10/29/93 10/29/93 10/29/93 12/11/89 10/29/93 12/11/89 12/11/89 2/21/92 2/21/92 12/11/89 2/21/92, 3/ll/94 3/ll/94 3/ll/94 3/ll/94 2/21/92 2/21/92 3/ll/94 3/ll/94 3/ll/94 12/11/89 3/ll/94 12/11/89 12/11/89 Rev.3 PAG APPROVAL DATE REVISION DATE 5-6c Composite Dose Factors: Haximum Hypothetical Child (2pp)....................................5-6c(1,2) 2/18/94 5-6d Water Ingestion Dose Factors: "Haximum Hypothetical Infant (2pp)......................5-6d(1,2) 2/18/94 3/11/94 3/11/94 6 Operational Radiological Envi Honitoring Program...........

ronmental~~~~~~~~~~~~~~~~~~~48 49 50 3/23/95 3/23/95 3/23/95 3/30/95 3/30/95 3/30/95 8 Systems Classified as Not an Effluent Pathway...

61 9 Systems Classified as Insignificant Effluent p athway..........................................

10 Systems Classified as Significant Effluent p athway.........................................

B-l Radiological Environmental Honitoring Program Annual Summary..................................

65 B-3 7 Detection Capabilities for Environmental S ample Analysis.................................

51 52 1/16/95 1/16/95 3/29/95 3/29/95 3/29/95 1/20/95 1/20/95 3/30/95 3/30/95 3/30/95 12/11/89 12/11/89 B-2 Reporting Levels for Nonroutine Operating R eports.........................................

B-4 12/11/89 Il/9/93 D-l Dilution Factors and Transit Times for SSES Effluents to Danville, PA.......................

D-l 3/ll/94 3/ll/94

LIST OF FIGURES APPROVAL REVISION~PG~DA E~DE Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 Liquid Radwaste System F low Diagram..........................

Offgas and Recombiner System F low Diagramo~~~~~~~~~~~~~~~~~~~~~~~~~Solid Waste Hanagement System Flow Diagram..........................

SSES Dry Contaminated Waste Process 1 ng o~~~~~~~~~~~~~~~~~~~~~~~~~~~Environmental Honitoring Locations , Within One Hile of SSES...............

Environmental Honitoring Locations Greater than One Hile from SSES.......

38 3/23/95 3/30/95 39 1/16/95 1/20'/95 40 1/16/95 1/20/95 41 1/16/95 1/20/95 46 1/16/95 1/20/95 47 1/16/95 1/20/95 Rev.3 V1 l

EVAP.STEAM CONDS.AETUflN TANK PHASE SEPARATORS (DECANTATE)

RHR SYSTEM RWCU SYSTEII REACTOR WELL SEAL LEAK DRAIN REACTOR BLDG.DRAINS DAVWELL DRAINS TLNBINE BLDG.DRAINS RADWASTE BLDG.DRAINS LIQUID RADWASTE fIGURE LIQUID RADWASTE SYSTEM FLOW DIAGRAM LIQUID RADWASTE COLLECTIOH 4 SURGE TAHKS OT-302 A THRU F OT-301 A THAU D LIOUID AADWASTE FILTERS OF-302 A>B LIOUIO RADWASTE DENIHEAALIZER OF-801 LIOUIO RADWASTE SAMPLE TAHKS OT-303 A THRU F COHOENSATE OEMIH.!RESIN REGNEAATING TANK LRW COLLECTION TANK PLAB'S OP-301 A,B,C TO WASTE IIIXIHG TANKS OT-307 A,B TO SPENT AESIH TANK OT-324 LAW SAMPLE TANK PNIPS OP-305 A 8 C COHOENSATE STORAGE TANKS OT-522 A,B CHEMICAL WASTE HEUTRAL IZER TANKS 1T-130 A,B 2T-130 A,B CST BEAII WATER SAMPLE STATIONS AUX BOILER BLOWDOWNS RWCU CHEIIICAL OECOH.LAB AND DECOH.DflAIHS CHEM.-WASTE NEUTAAL I ZING TAIN(PL%PS IP~I30 A,B 2P~130 A,B AADWASTE EVAPORATOR OE-302 A,B DIST IL LATE SAMPLE TANK OT-321 DISTILLATE SAMPLE TANK PCS OP.327 A,B AE TO CODLING TOWER SLOW-DOWN PIPE LAUMIRY DRAINS REGLAATEO SHOP DRAINS PERSON@.L DECONTAII-INATION (DETEAGENTS)

CASK CLEANING DRAINS CHEIIICAL WASTE TANK OT-314 CHEM WASTE TANK PLBIPS OP-325 A,B CHEIII GAL WASTE PROCESSING SUS-SYSTEII (VENDOR SUPPLIED)EVAPORATOR COHCENTflATE STORAGE TANK OT-322 TO WASTE IIIXIHO TANKS OT-307 A,B LAUNDRY DRAIN TANK OT-314 A,B DATE 9~~~pLAUNDRY DRAIN TANK PUMPS OP~318 AsB LAUHOAY DRAIN FILTERS OF-318 A,B LAUNDRY DRAIN SAMPLE TANK OT-312 COHCEHTAATE STORAGE TANK OISCH.PNIP OP~32B LALINDAY DRAIN SJ4IPLE TANK PLIMPS OP.3I9 A,b il TABLE 6 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Page of 3 Exposure Pathways Number of Samples and Locations*

Sampling and Collection Fre uenc Type and Fre u nc ofhnal sis hirborne Radioiodine and Particulates~

12S I 0.4 mi WSW 9B I 1.3 mi S SS4 0.8 mi E 12E I 4.7 mi WSW 7G I 14 mi SE 3S2 0.5 mi NE 7S7 0.4 nu SE IOS3 0.6 mi SSW 13S6 0.4 mi W 12G I 15 mi WSW EOF Building Transmission Line Environmental Laboratory Berwick Hospital PAL Hazleton Complex'SES Backup.Met.

Tower End of Kline's Road East of Confer's Lane, South of Towers Club Former Laydown Area, West of Confer's Lane'PN.Bloomsburg Service Center'ontinual sampler operation with sample Radioiodine Canister: analyze collection weekly.~~weekly for I-131 Particulate Sample: Analyze for gross beta radioactivity following filter change.Perform isotopic analysis on composite sample (by location)quarterly.

Direct Radiation IS2 Perimeter Fence-0.2 mi N ID5 Mocanaqua Sewage Treatment Plant-4.0 mi N 2S3 Perimenter Fence-0.2 mi NNE 2B3 Durabond Corporation

-1.3 mi NNE 2F I St.Adalberts Cemetery-5.9 mi NNE 3S4 Perimeter Fence-0.3 mi NE 4S3 West of SSES APF-02 mi ENE 4E2 Ruckles Hill A;Pond Hill Roads Intersection:

4.7 mi ENE 4GI Crestwood Industrial Park-14 mi ENE'S7 Perimeter Fence-0.3 mi E 5E2 Bloss Farm-4.5mi E 6S4 Perimeter Fence-0.2 mi ESE 6A4 Riverside Restaurant

-0.6 mi ESE 6EI St.James Church-4.7 mi ESE Quarterly Gamnia Dose: Quarterly.

Page of 3 Exposure Pathways Number of Samples and Locations~

Sampling and Collection 1re uenc Type and Fre uene ofhnal sis 6S9 7S6 7EI 7GI 8S2 8B2 8D3 9S2 9D4 IOSI IODI IIS3 IIEI 12S3 12EI 12GI 13S2 13E4 14S5 14B3 ISFI 15S5 16SI 16S2 16FI Perimeter Fence-0.2 mi ESE Perimeter Fence-0.2 mi SE Harwood Transmission Line Pole N2-4.2 mi SE PPN.Hazleton Complex-14 mi SE'erimeter Fence-0.2 mi SSE LaWall Residence-1.4 mi SSE Mowty Residence-4.0 mi SSE Security Fence-0.2 mi S Country Folk Store-3.6 mi S Post South of Switching Station-0.4 mi SSW Ross Ryman Farm-3.0 mi SSW Security Fence-0.3 mi SW Thomas Residence-4.7 mi SW Perimeter Fence-0.4 mi WSW Berwick Hospital-4.7 mi WSW Pal, Bloomsburg Service Center-15 mi WSW'erimeter Fence-0.4 mi W Kessler Farm-4.1 mi W Beach Grove Rd.4 Confer's Lane Intersection 0.5 mi WNW Moskaluk Residence-1.3 mi WNW Zawatski Farm-5.4 mi NW Perimeter Fence-0.4 mi NW Perimeter Fence 0.3 mi NNW Perimeter Fence-0.3 mi NNW Hidlay Residence-7.8 NNW Waterborne 6S6 river water intake line'S7 cooling tower blowdown discharge line Monthly composite Monthly composite Gatnma isotopic analysis.Composite tritium analysis at least quarterly.

Drinking l2H2 Danville Water Company{Approxintately 30 miles downstream)

Monthly composite Gross beta and gamma isotopic analyses monthly.Composite for tritium analysis at least quarterly.

Rev.3

.I Page 3 Exposure Pathways Number of Samples and Locations~

Sampling and Collection Fre uenc Type and Fre uenc ofhual xis Sediment from Shoreline 7B Bell Bend-1.2 mi SE Semi-annually Gamma isotopic analysis semi-annually.Milk~~~Fish and Invertebrates 12B3 Young Farm-2.0 mi WSW Outfall area 2H Falls, Pa'Approximately 30 mi NNE)Semi-montMy when animals are on pasture, montMy otherwisc Semi-annually.

One sample'rom each of two reacreationally important species from any of the following families: bullhead catfish, sunfish, pikes, or perches.Gamma isotopic and 1-131 analysis of each sample Gamma isotopic on edible portions.Food Products I ID I Zehner Farm-3.3 mi SW vegetable At time of harvest Gatnma isotopic on edible portions.12F7 Lupini Farm-8.3 mi WSW vegetable~The location of samples and equipment were designed using the guidance in thc Branch Technical Position to NRC Rev.Guide 4.8, Rev.I, Nov.1979, Reg.Guide 48.1975 and ORP/SID 72-2 Environmental Radioactivity Surveillance Guide.Therefore, the airborne sampler locations werc based upon X/Q and/or D/Q.~~A dust loading study (RMC-TR411) concluded that the assumption of I for the transmission correction factor for gross beta analysis of air particulate samples is valid.Air particulate samples need not be weighed to determine a transmission correction factor."If a milk sample is unavailablc for more than two sampling periods from one or morc of thc locations, a vegetation sample shall be substituted until a suitable milk location is evaluated.

Such an occurrence will bc documented in the REMP annual report.'Control sample location.'Two-week composite if calculated doses due to consumption of water exceed onc millirem per year.In these cases, I-131 analyses will be performed.

'The sample collector will determine the species based upon availability, which may vary seasonally and yearly.OAT Rt v.3 10.0 DOS S SS NT PO ICY STATEHENTS 10.1 1 c io of An 1 sis Results for Dose Calculations For determination of compliance with SSES Technical Specification dose limits, effluent totals shall be based only on activity positively detected at the 95X confidence level.10.2 Assi nment of Releases to the Reactor Units For determination of compliance with SSES radioactive effluent dose limits which are on a"per reactor unit" basis: a.Effluents from the Unit 1 Reactor Building vent and the Unit 1 Turbine Building vent shall be included as Unit 1 releases..b.Effluents from the Unit 2 Reactor Building vent and the Unit 2 Turbine Building vent shall be included as Unit 2 releases.c.Effluents from the Standby Gas Treatment System vent shall be equally divided between Unit 1 and Unit 2 release totals.d.Waterborne effluents shall be equally divided between Unit 1 and Unit 2 release totals.10.3 Evaluation and Mo itorin Criteria for ffluent Pathwa s Potential effluent pathways will be evaluated on a case-by-case basis.The evaluation will include identification of systems which are normally non-radioactive (as described in the FSAR)but could possibly become radioactive through interfaces with radioactive systems (

Reference:

NRC IE Bulletin No.80-10).The evaluation will determine the significance of any potential effluents pathways and extent of sampling and/or monitoring required.The frequency of sampling or monitoring will be determined based on the potential for contamination, the potential for inadvertent releases, the potential levels of contamination and releases, and the potential impact on station offsite doses.OAT Rev.3 53

Results of sampling and/or evaluation will be used to classify potential effluent pathways into one of the following categories:

a.Not an Effluent Pathwa: Realistic evaluation (e.g., engineering design, system operation, radionuclide inventory) demonstrates that the pathway has no potential for release of radioactive material (Table 8).Although not required, periodic sampling may at times be performed.to confirm the result of the evaluation.

b.Insi nificant ffluent Pathwa: Evaluation and/or periodic sampling demonstrate that the pathway.may contain radioactive effluents, however, these effluents may not be reasonably expected to exceed 10 percent of the appropriate unrestricted area HPC value (fractional HPCs summed when appropriate) listed in Table II of Appendix B to 10 CFR 20 (Table 9).A release pathway which.falls in this category will be sampled periodically.

c.Si nificant Effluent Pathwa: Evaluation and/or periodic sampling demonstrate that the pathway may contain radioactive effluents, and these effluents may be reasonably expected to exceed 10 percent of the appropriate unrestricted area'HPC value (fractional HPCs summed when appropriate) listed in Table II of Appendix B to 10 CFR 20 (Table 10).A release pathway which falls in this category will be sampled continuously.

If sampling indicates a non-radioactive system has become contaminated, further use of the system shall be restricted until the cause.of the contamination has been corrected and the system is decontaminated.

If continued operation of the system as contaminated is necessary, a 10CFR50.59 safety evaluation of the operation of the system as a radioactive system shall be performed immediately by the system operator/engineer.

The safety evaluation will include any changes in the effluent pathways and the impacts to offsite doses.(Ref.NRC IE Bulletin 80-10).DAT Rev.3 54

Positively detected radioactive material in samples collected from all airborne and waterborne offsite release pathways will be reported in the Annual Effluent and Waste Disposal Report.10.,4 Flow from the SGTS Vent when the S stem is Not in Use When the Standby Gas Treatment is not being used, there remains a small amount of flow from the SGTS vent.This residual flow is exhaust from the battery rooms in the control structure.

Because there are no identifiable sources of radioactivity in these rooms, auxiliary particulate and iodine sample and noble gas grab sample at 4-hour intervals are not required'from the SGTS vent when the SGTS con'tinuous vent monitor is out of service,~y~ovi~d~a a.the Standby Gas Treatment System is not being used, b.there are proper administrative controls in place to ensure that the required sampling will begin within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if the treatment system is operated.10.5 OD Set pints are U er Limit Value Effluent monitor alarm/trip setpoints calculated in accordance.

with the ODCH shall be considered upper limit values.Higher (less conservative) setpoints shall not be used, ho'wever=lower (more conservative) setpoints may be used as required to maximize the utility of the monitor.10.6 D i ition of"A ro riate Treatment" for Li uid Wastes Technical Specification 3.11.1.3 requires that the appropriate portions of the liquid waste treatment system be operable and be used to reduce radioactivity in liquid wastes prior to their release when projected doses from each reactor unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.OAT Rev.3 55

o The normal treatment, which is considered appropriate for each subsystem, is as follows: Filtration is considered appropriate treatment for the Liquid Radwaste Laundry Processing Subsystem, which consists of high conductivity liquid wastes, such as those from equipment washdown and personnel decontamination facilities, or laundry.The atmospheric demineralizer (a vendor-supplied system which is directed to the Distilla'te Sample Tank)is considered appropriate for the Liquid Radwaste Chemical Processing Subsystem.

Demineralization and filtration are considered appropriate treatment for low conductivity/low organic contaminant liquid wastes entering the Liquid Radwaste Processing Subsystem (LRW collection tanks), except for batches which yield projected doses prior to treatment of less than or equal to 6.45-04 modem to the total body and 2.15E-03 mrem to any organ, where filtration alone is appropriate, or o For batches which have no identified gamma activity above the Technical Specification Liquid Effluent LLD level (Table 4.11.1.l.1-1),.release without treatment is considered appropriate.

BASES The projected dose threshold values used are derived by dividing the site-total maximum projected doses without treatment (0.12 and 0.4 mrem)by 31 days and by 6, the maximum possible number of batches released per day, to yield per-batch dose action levels.The two levels of"appropriate" treatment are in place so as not to require application of demineralization for 56 OAT Rev.3 treating low activity, high conductivity water (e.g., from Circulating or Service Water leakage).This would increase the overall efficiency of the solid radwaste program while ensuring calculated doses remain at a suitable fraction of 10 CFR 50 design objectives and Technical Specification 3.11.1.2 limit.~'"'0.7 Monit r'ne oss Corrections In order to correct for airborne effluent monitor sample line loss, the following correction factors shall be applied to monitor data and sample analysis results: ROUTIN FFLUENT MONITORS CORR TION FACTORS MIO LNE~PTIC I Reactor Building Unit 1 Reactor Building Unit 2 Turbine Building Unit 1 Standby Gas Treatment Turbine Building Unit 2 1.5 1.5 1.6 1.5 1.6 3.2 3.2 3.6 3.9'.6 POST ACC DENT VENT MONITORS CORR CT ON FACTORS~IU IN~PNN CULNIN Turbine Building Unit 1 Standby Gas Treatment Turbine Building Unit 2 1.7 1.6 1.7 4.2 4.4 4,3"'Reference Calculation No.OT-RKB-92-001:

Calculation of Liquid Isotope Offsite Dose Consequences for Use of Atmospheric Demineralizer System, PLI-70360, 2/4/92.'Reference Letter R.K.Barclay to R.A.Breslin: Demineralizer Effluent Results, PLI-70612, 3/4/92.57 Atmospheric

.

Each indicated iodine and particulates concentration shall be multiplied by the appropriate correction factor to estimate the actual concentration at the inlet to the sample line.10.8 Selection of Data for Determination of Dose Rate Com liance Airborne effluent monitor setpoints are maintained in accordance with Section 2.2 to alarm before the dose rate l.imits of Specification 3.11.2.1 are exceeded.Station alarm response procedures contain instructions for investigation and verification oF monitor alarms.Because setpoint calculations must include assumptions about the composition of the monitored effluent, a monitor high alarm does not necessarily indicate that a dose rate limit has been exceeded.'alid ten-minute averaged data should be the primary information used to determine the compliance status of an incident.One-minute averaged data should also be reviewed if available, but they may or may not provide additional information depending on the magnitude of the release due to the manner in which the monitors update values to be stored and associated statistical considerations.

Averages over a longer period should be used only when data with higher resolution is not available.

Grab sample analyses should be performed whenever possible to confirm or disprove monitor data, and to provide indication of the nuclide-specific composition of the effluent.When grab sample data are available which, based on vent monitor data, are indicative of the period of elevated release, dose rate calculations should be performed using the actual effluent mix.The determination of compliance status should not be based on monitor data alone when it is possible to collect and analyze a vent sample which will be representative of the period of elevated release.58 Rev.3 10.9 1 Radioac'vit in the Sew e Tr a m t P nt Like all sewage processing facilities, the SSES sewage treatment plant can under certain conditions receive low levels of radioactive materials.

The most notable scenario is when individuals who work on-site have been subjected to the medical administration of radiopharmaceuticals for diagnostic or therapeutic purposes.In these cases, normal biological elimination processes can easily result in levels of radioactivity in sewage treatment plant solutions and suspensions which are within the detection capabilities of the associated sampling and analysis program.Because disposal of sewage treatment plant sludge by controlled dispersal on specified tracts of land is a common practice, the following guidelines have been established:

a.All sludge collected in the sludge holding tank should be sampled and analyzed prior to land disposal to quantify any radioactivity present above natural background levels.b.Sludge containing nuclides with short half-lives, for example iodine-131, should be contained on-site to permit dec'ay to less than detectable levels.c.When sludge is contaminated with nuclides which have half-lives sufficiently long to make hold-up for decay impractical, the following options should be considered:

l.Dispose of the sludge as low level radioactive waste.2.Obtain a special permit pursuant to the requirements of 10 CFR 20.2002.A DAT d.The sewage treatment plant liquid effluent should be sampled monthly for radioactivity.

This can be accomplished by drawing a sample from the chlorine contact chamber.59 Rev.3

11.0 ODCM R V W AND REVISION CON RO The Supervisor-Environmental Services-Nuclear shall ensure that a total review of the ODCH is performed during each even-numbered year.Comments shall be documented and revisions initiated as appropriate.

Each ODCM page shall be numbered and provided with an approval and date box.The ODCM Table of Contents shall present the current revision date for each page so that any manual holder can check manual completeness based on a current Table of Contents.All ODCM revisions shall be reviewed by PORC after approval by the Manager-Nuclear Technology.

PORC review shall be indicated by PORC chairperson or designee signature on ODCH cover.ODCM copies shill be issued in a controlled fashion by the staff of the Nuclear Department Library.The distribution list shall be maintained by the Nuclear Department Library Staff.Any comments on ODCM contents or proposed revisions should be directed to the Supervisor-Environmental Services-Nuclear.

0>A~5~Rev.3 60

TABLE 8 SYSTEMS CLASSIFIED AS NOT AN EFFLUENT PATHMAY (Page 1 of 3)SYSTEM DESCRIPTION Domestic.Mater River Mater Makeu Intake Com ressed Air Screens and Screenwash Fire Protection Water Fire Protection CO Fire Protection Halon Turbine Buildin Closed Coolin Mater Buildin Drains: NON RAD Water Pretreatment Condensate and Refuel Water Transfer Low Pressure Air Condensate Demins Lube Oil Transfer Purification Coolin Tower Acid Chlorination Circulatin Mater Condenser Tube Cleanin Feedwater Extraction Steam Feedwater Heaters Residual Heat Removal Reactor Core Isolation Coolin Core S ra Hi h Pressure Coolant Injection Standb Li uid Control Control Rod Drives REFERENCE (1)PP5L Calculation EC-ENVR-1008 Rev.3 61 TABLE 8 SYSTB5 CLASSIFIED AS NOT AN EFFLUENT PATHWAY (Page 2 of 3)SYSTEN DESCRIPTION Su ression Pool Primar Containment Vacuum Breakers Su ression Pool Cleanu Reactor Water Cleanu Reactor Pressure Vessel Reactor Recirculation S stem Radwaste Chilled Water Solid Radwaste Cement Silo LRW Collection Tb and Cond.Outer Area Sum s LRW Processin Radwaste Eva orator Gaseous Radwaste Recombiner Closed Coolin Water Nitro en Stora e H dro en Stora e Sam lin Stations Post Accident Sam lin S stem B ass Steam Main Steam Isolation Valves/Nuclear Steam Su 1, S stem Shutoff Automatic De ressurization S stem MSIV Leaka e Control Moisture Se arators Turbine Steam Seals Electroh draulic Control Stator Coolin Main Generator Storm Drains REFERENCE (1)PP8L Calculation EC-ENVR-1008 DAT Rev.3 62 f'

TABLE 8 SYSTEMS CLASSIFIED AS NOT AN EFFLUENT PATHWAY (Page 3 of 3)SYSTEM DESCRIPTION Makeu Demineral i zers Fuel Oil Containment Instrument Gas Control Structure Chilled Water Turbine Bld.Chilled Water Reactor Bld.Chilled Mater Auxiliar Boilers fuel Pool Coolin Fuel Pool Demineralizers Fuel Pools Tem orary SDHR S stem REFERENCE Rev.3 63 TABLE 9 SYSTENS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAY SYSTEM DESCRIPTION H Seal Oil Condensate Stora e Tank and Berm Hain Turbine RFPT Lube Oil Instrument Air Service Air.Tem orar Laundr Facilit Second Sort DAW Volume Reduction Facilit Low Level Radwaste Handlin Facility REFERENCE Rev.3 TABLE 10 SYSTENS CLASSIFIED AS SIGNIFICANT EFFLUENT PATHWAY SYSTEH DESCRIPTION Li uid Waste Mana ement S stems Gaseous Waste Mana ement Systems REFERENCE (1)PPEL Calculation EC-ENVR-1008 (2)Safety Evaluation NL-90-029:

Temporary Laundry Facility (3)Safety Evaluation NL-89-002:

Dry Active Waste Volume Reduction System (4)Safety Evaluation NL-92-007:

Operation of LLRWHF at SSES (5)SSES FSAR Chapter 11.2 (6)SSES FSAR Chapter 11.3-(7)Safety Evaluation NL-95-001:

Refueling Outage Decay Heat Removal and Tie-In of the SDHR Temporary Cooling Equipment.

rv DAT Rev.3 P

PENNSYLVANIA POWER 8L LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL Revision 4 Prepared By Date Reviewed By Supervisor-Environmental ServicesNuclear M~s z/eetsng o.Approved By Hanager-Nuclear Technology Date Date Oate

SUMMARY

OF ODCM CHANGES Three milk sampling stations (IOGI, IOD2 and IODI)were inadvertently deleted in Table 6, Rev.3, and are restored herein.These deletions were not noted in review of Table 6, Rev.3, which was submitted in resolution to SOOR 95-045;The name of the restaurant at TLD station 6A4 has beea deleted to make the description more generic, in response to a PORC comment from the.meeting on March 30, 1995.Rev.4 TABLE APPROVAL REVISION JPPGE~0A E DATE 5-6c Composite Dose Factors: Haximum Hypothetical Child (2pp)....................................5-6c(1,2) 2/18/94 5-6d Water Ingestion Dose Factors: Haximum Hypothetical Infant (2pp)......................5-6d(1,2) 2/18/94 3/11/94 3/ll/94 6.Operational Radiological Environmental Honitoring Program..............................

48 49 50 4/17/95 3/23'/95 4/17/95'.4/20/95 3/30/95 4/20/95 1/20/95 1/20/95 3/30/95 3/30/95 3/30/95 1/16/95 1/1'6/95 3/29/95 3/29/95 3/29/95 8 Systems Classified as Not an Effluent Pathway...

61 9 Systems Classified as Insignificant Effluent athway.........................................

p 10'Systems Classified as Significant Effluent~~p athway~~~~~~~~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~B-1 Radiological Environmental Honitoring Program Annual Summary.................................;

65 8-3 12/11/89 12/11/89 7 Detection Capabilities for Environmental Sample Analysis.................................

51 52 B-2 Reporting Levels for Nonroutine Operating eports....'.....................................

R B-4 12/11/89 11/9/93 D-l Dilution Factors and Transit Times for SSES Effluents to Danville, PA.......................

D-l 3/11/94 3/ll/94 TABLE 6 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Page 1 o Exposure Pathways Number of Samples and Locations*

Sampling and Collection Fre uenc Type and Fre uenc ofhnal sis hirborne Radioiodine and Particulates~

12S I 0.4 mi WSW 9BI 1.3 mi S 5S4 0.8 mi E 12EI 4.7 mi WSW 7G I 14 mi SE 3S2 0.5 mi NE 7S7 0.4 mi SE IOS3 0.6 mi SSW.13S6 0.4 mi W 12G I 15 mi WSW EOF Building Transmission Line Environmental Laboratory Berwick Hospital PP&L Hazleton Complex'SES Backup Met.Tower End of Kline's Road East of Confer's Lane, South of Towers Club Former Laydown Area, West of Confer's Lane'P&L Bloomsburg Service Center'ontinual sampler operation with sample collection weekly." Radioiodine Canister: analyze weekly for 1-131 Particulate Sample: Analyze for gross beta radioactivity following filter change.Perform isotopic analysis on composite sample (by location)quarterly.

Direct Radiation IS2 Perimeter Fence-0.2 mi N ID5 Mocanaqua Sewage Treatment Plant-4.0 mi N 2S3 Perimenter Fence-0.2 mi NNE 2B3 Durabond Corporation

-1.3 mi NNE 2FI St.Adalberts Cemetery-5.9 mi NNE 3S4 Perimeter Fence-0.3 mi NE 4S3 West of SSES APF-0.2 mi ENE 4E2 Ruckles Hill&Pond Hill Roads Intersection:

4.7 mi ENE 4G I Crcstwood Industrial Park-14 mi ENE'S7 Perimeter Fence-0.3 mi E 5E2 Bloss Farm-4.5 mi E 6S4 Perimeter Fence-0.2 mi ESE 6A4 Restaurant

-0.6 mi ESE 6EI St.James Church-4.7 mi ESE Quarterly Gamma Dose: Quarterly.

nnfF.Rev.4

Page 3 Exposure Pathways Number of Samples and Locations*

Sampling and Collection Fre uenc Type and Fre uenc ofhnal sis Sediment from Shoreline 7B Bell Bend-1.2 mi SE Semi-annually Gamma isotopic analysis semi-annually.Milk~~~12B3 Young Farm-2.0 mi WSW IOG I Davis Farm-14.0 mi.SSW'OD2 Ray Ryman Farm-3.5 mi.SSW 10D I KLC Ryman Farm-3.0 mi.SSW Semi-monthly when animals are on pasture, monthly otherwise Gamma isotopic and I-131 analysis of each sample Fish and Invertebrates Outfall area 2H Falls, Pa'Approximately 30 mi NNE)Semi-annually.

One sample'rom each of two reacreationally important species from any of the following families: bullhead catfish, sunfish, pikes, or perches.Gamma isotopic on edible portioils.

Food Products 11D I Zehner Farm-3.3 mi SW vegetable At time of harvest Gamma isotopic on edible PoftioilS.

12F7 Lupini Farm-8.3 mi WSW vegetable~The location of samples and equipmcnt were designed using the guidance in the Branch Technical Position to NRC Rev.Guide 4.8, Rev.I, Nov.1979, Reg.Guide 48.1975 and ORP/SID 72-2 Environmental Radioactivity Surveillance Guide.Therefore, the airborne sampler locations were based upon X/g and/or D/Q.~'A dust loading study (RMC-TR-8141) concluded that the assumption of I for the transmission correction factor for gross beta analysis of air particulate samples is valid.Air particulate samples need not be weighed to determine a transmission correction factor.~~'If a milk sample is unavailable for more than two sampling periods from one or more of the locations, a vegetation sample shall be substituted until a suitable milk location is evaluated.

Such an occurrence will be documented in the REMP annual report.'Control sample location.rwo-week composite if calculated doses due to consumption of water exceed one millirem per year.In these cases, 1-131 analyses will be performed.

'The sample collector will de'termine the species based upon availability, which may vary seasonally and yearly.DAT I

PENNSYLVANIA POWER&LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION QFFSITE DOSE CALCULATION MANUAL Revision 6 Prepared by: Date: Reviewed by: Supervisor Environmental Services-Nuclear Date: Reviewed by: PORC/Meeting No.Date: Approved by:./Manager-Nuclear Technology Date: 7

SUMMARY

OF ODCM CHANGES 1.The Introduction has been revised to specify that reference to MPC limits of 10CFR20 Appendix B in the document applies to those limits in effect prior to January 1, 1994, and continuing in effect until such time that revised 10CFR20 Appendix B limits are implemented at SSES.\2.A description of systems with NRC I/E Bulletin 80-10 applicability has been added to Section 10.3.Reference is made to Table 11, which lists the 80-10 systems by number and name.3.Table 9 is revised to include Refuel Water Storage Tank with Condensate Storage Tank and Berm, and H2 Seal Oil with Main Turbine/RFPT Lube Oil.The Sewage Treatment Plant is added to Table 9.Reference notes for these changes are now located in the appropriate tables.4.Table 11 (Systems with NRC I/E Bulletin 80-10 Applicability) is added to the ODCM.The Sewage Treatment Plant is added to Table 11 in response to PORC Meeting 95-098 Action Item E05532.5.Section 11 (ODCM Review and Revision Control)is repaginated to follow Tables 8-11 of Section 10.Reference to revision in accordance with NEPM-QA-1011 is added, which is submitted as an Action to Prevent Recurrence in SOOR 95-045.The distribution of ODCM copies is revised to indicate SSES Document Control Services, which replaces the staff of the Nuclear Departme'nt Library.6.This revision does not reduce the accuracy or reliability of dose calculations or setpoint determinations.

Rev.5

TABLE OF CONTENTS

1.0 INTRODUCTION

~pa e Approval Date 7/14/95 7/14/95 1119/93 Rev>sion Date 7/20/95 7/20/95 3/11/94 2.0 SETPOINTS 2.1 Waterborne Effluent Monitors 2.2 Airborne Effluent Monitors 3.0 WATERBORNE EFFLUENT CONCENTRATION MEASUREMENTS 4.0 AIRBORNE EFFLUENT DOSE RATES 4.1 Noble Gases 4.2 Radionuclides Other Than Noble Gases 5.0 INDIVIDUAL DOSE DUE TO WATERBORNE EFFLUENT 5.1 Fish Pathway Liquid Effluent Dose Calculation Methodology 5.2 Potable Water Pathway Effluent Dose Calculation Methodology 5.3 Shoreline Exposure Pathway 5.4 Projected Dose From Liquid Effluent 6.0 INDIVIDUAL DOSE DUE TO AIRBORNE EFFLUENT 6.1 Noble Gases 6.2 Radionuclides Other Than Noble Gases 7.0'OTAL DOSE 9 10 11 12 14 15 15 16 17 18 19 20 23 24 24 25 26 27 27 28 29 30 31 2/5/92 2/5/92 12/11/89 2/5/92 12/11/89 12/11/89 2/5/92 12/11/89 12/11/89'1/21/92 2/5/92 2/5/92 2/5/92 1/16/95 1/16/95 2/11/92 2/5/92 12/11/89 12/1/92 10/29/93 2/18/94 11/9/93 11/9/93 11/9/93 2/18/94 11/9/93 10/29/93 10/29/93 10/29/93 10/29/93 1/16/95 10/29/93 2/21/92'/21/92 12/11/89 2/21/92 12/11/89 12/11/89 2/21/92 12/11/89 12/11/89 11/25/92 2/21/92 2/21/92 2/21/92 1/20/95 1/20/95 2/21/92 2/21/92 12/11/89 12/4/92 3/11/94 3/11/94 3/11/94 3/11/94.3/11/94 3/11/94 3/11/94 3/11/94 3/11/94 3/11/94 3/11/94 1/20/95 3/11/94 Rev.5 8.0 OPERABIUTY OF WASTE TREATMENT SYSTEMS 8.1 Liquid Waste Treatment 8.2 Gaseous Waste Treatment 8.3 Solid Waste Treatment 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 9.1 Definitions 9.2 Monitoring Program 9.3 Census Program 9.4 Intertaboratory Comparison Program~Pa e 32 32 33 34 35 36 37 42 42 42 43 44 45 Approval Oats 10/29/93 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95.1/16/95 Revision Date 3/11/94 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95 1/20/95.1/20/95 1/20/95 1/20/95 10.0 DOSE ASSESSMENT POLICY STATEMENTS 53 10.1 Selection of Analysis Results for Dose Calculations 53~10.2 Assignment of Releases to the Reactor Units 53 10.3 Evaluation and Monitoring Criteria for Effluent 53 Pathways 10.4 Flow From the Sgts Vent When the System is Not 54 In Use 7/14/95 7/14/95 7/14/95 7/14/95 7/14/95 7/20/95 7/20/95 7/20/95 7/20/95 7/20/95 10.5 ODCM Setpoints Are Upper Limit Values 10.6 Definition of"Appropriate Treatment" for Liquid Wastes 10.7 Monitor Line-Loss Corrections 10.8 Selection of Data For Determination of Dose Rate Compliance 10.9 Low-Level Radioactivity in the Sewage Treatment Plant 11.0 ODCM REVIEW AND REVISION CONTROL 56 56 58 59 60 68 7/14/95 7/14/95 7/14/95 7/14/95 7/14/95 7/14/95 7/20/95 7/20/95 7/20/95 7/20/95 7/20/95 7/20/95 DAT Rev.5 Appendix A-Sample Calculations of ODCM Parameters Appendix B-Reporting Requirements

~Pa e A-1 A-2 A-3 AQ A-5 AW A-7 A-8 A-9 A-10 A-11 A-12 A-13 B-1 B-2 B-3 BP Approval Date 2/5/92 2/5/92 12/11/89 2/5/92 10/29/93 10/29/93 10/29/93 10/29/93 2/5/92 2/5/92 10/29/93 10/29/93 10/29/93 12/11/89 10/29/93 12/11/89 12/11/89 Revision Date 2/21/92 2/21/92 12/11/89 2/21/92 3/11/94 3/11/94 3/11/94 3/11/94 2/21/92 2/21/92 3/11/94 3/11/94 3/11/94 12/11/89 3/11/94 12/11/89 12/11/89 Appendix C-Site Specific Information Used by Gaspar Code C-11 12/11/89 12/11/89 Appendix D-Site Specific Information Used by Ladtap Code 10/10/94 10/14/94 Rev.5 Table LIST OF TABLES Approval Revision~pa e 1 Radiological Effluent Objectives and Standards 2 Dose Factors for Noble Gases 3 Sample Annual Average Relative Concentrations and Deposition Rates 4 Dose Factors for Inhalation, Ingestion and Ground Exposure Pathways: Radionuciides Other Than Noble Gases 5-1 a Dose Factors for Fish Pathway, Maximum Hypothetical Adult (2pp)5-1b Dose Factors for Fish Pathway, Maximum Hypothetical Teen (2pp)5-1c Dose Factors for Fish Pathway, Maximum Hypothetical Child (2pp)5-2a Dose Factors for Potable Water Pathway, Maximum Hypothetical Adult (2pp)5-2b Dose Factors for Potable Water Pathway, Maximum Hypothetical Teen (2pp)5-2c Dose Factors for Potable Water Pathway, Maximum Hypothetical Child (2pp)5-2d Dose Factors for Potable Water Pathway, Maximum Hypothetical Infant (2pp)5-3 Radioactive Decay Constants 5Q Dilution Factors and Transit Times for SSES Effluents to Danville, PA 5-5 Dose Factors for Shore Exposure Pathway, All Age Groups (2pp)5<a Composite Dose Factors: Maximum Hypothetical Adult (2pp)5-6b Composite Dose Factors: Maximum Hypothetical Teen (2pp)18 19~20 5-1 a(1,2)5-1b(1,2)5-1 c(1,2)5-2a(1,2)5-2b(1,2)5-2c(1,2)5-2d(1,2)5-3 5A(1,2)'5-5(1,2)5-6a(1,2)5-6b(1,2)11/9/93 3/11/94 2/5/92 2/21/92 11/9/93 3/11/94 12/1/92 12/4/92 10/10/94 10/14/94 10/10/94 10/14/94 10/10/94 10/14/94 10/29/93 3/11/94 10/29/93 3/11/94 10/29/93 3/11/94 10/29/93 3/11/94 10/29/93 3/11/94 10/29/93 3/11/94 10/29/93 3/11/94 10/10/94 10/14/94 10/10/94 10/14/94 DAT Rev.5 IV Table 5-6c Composite Dose Factor: Maximum Hypothetical Child (2pp)1 5-6d Water Ingestion Dose Factors: Maximum Hypothetical Infant (2pp)~Pa e 5-6c(1,2)5-6d(1,2)Approval Revision Date Oate 2/18/94 3/11/94 2/18/94 3/11/94 6 Operational Radiological Environmental Monitoring Program 7 Detection Capabilities for Environmental Sample Analysis 48 49 50 51 52 4/17/95 3/23/95 4/17/95 1/16/95 1/16/95 ,4/20/95 3/30/95 4/20/95 1/20/95 1/20/95 8 Systems Classified as Not an Effluent Pathway 9 Systems Classified as Insignificant Effluent Pathway 10 Systems Classified as Significant Effluent Pathway 11 Systems with NRC I/E Bulletin 80-10 Applicability B-1 Radiological Environmental Monitoring Program Annual Summary B-2 Reporting Levels for Nonroutine Operating Reports D-1 Dilution Factors and Transit Times for SSES Effluents to Danville, PA 62 65 66 67 B-3 B-4 D-1 7/14/95 7/20/95 8/7/95'/20/95 7/14/95 7/20/95 8/7/95 7/20/95 12/11/89'2/11/89 12/11/89 12/11/89 11/9/93 3/11/94 Sewage Treatment Plant added in response to PORC Meeting 95-098 Action Item E05532.OAT Rev.5

LlST OF FIGVRES~Fi~u~Pa e Approval Date Revision Date 1 Liquid Radwaste System Flow Diagram 2 Offgas and Recombiner System Flow Diagram 3 Solid Waste Management System Flow Diagram 4 SSES Dry Contaminated Waste Processing 5 Environmental Monitoring Locations Within One Mile of SSES 6 Environmental Monitoring Locations Greater than One Mile from SSES 38 39 40 41 46 47 3/23/95 1/16/95 1/16/95 1/16/95 1/16/95 1/16/95 3/30/95 1/20/95 , 1/20/95 1/20/95 1/20/95 1/20/95

1.0 INTRODUCTION

The purpose of this manual is to provide the parameters and methodology to be used in calculating offsite doses and effluent monitor setpoints for the Susquehanna Steam Electric Station, Units 1 and 2.Included are methods for determining maximum individual, whole-body, and organ doses due to waterborne and airborne effluents to ensure compliance with the dose limitations in the Technical Specifications.

Methods are included for performing dose calculations to ensure compliance with the waterborne and airborne treatment system operability sections of the Technical Specifications.

This manual includes the methods used for determining quarterly individual doses for inclusion in Annual Effluent and Waste Disposal Reports.The dose models consider two release modes: airborne and waterborne.

All airborne effluents are treated as ground-level releases.Dose to each of the seven organs listed in Regulatory Guide 1.109 (bone, liver, total body, thyroid, kidney, lung, and GI-LLI)are computed based on the individual nuclide composition of the effluent.The largest of the doses are compared to 10CFR59, Appendix I design objectives.

Liquid effluents discharged into a river undergo mixing prior to consumption as either potable water or through the fish pathway.For releases to the Susquehanna River, river model dilution factors are used.Doses to the seven T critical organs are determined from individual nuclide contributions and are compared to the 10CFR50 Appendix I design objectives.

Compliance with the 10CFR20 maximum permissible concentrations is done on a batch-by-batch basis prior to discharge.

Henceforth in this document, reference to MPC limits of 10CFR20 Appendix B applies to those limits in effect prior to January 1, 1994, and continuing in effect until such time that revised 10CFR20 Appendix B limits are implemented at SSES.OAT Rev.5 This manual discusses the methodology to be used in determining eNuent monitor alarm/trip setpoints to be used to ensure compliance with the instantaneous release rate limits in the Technical Specifications.

Methods are described for determining the annual cumulative dose to a real individual from liquid eNuents, gaseous eNuents, and direct radiation for critical organs to ensure compliance with 40 CFR 190 limits.The calculational methodology for doses are based on models and data that make it unlikely to substantially underestimate the actual exposure of an individual through any of the appropriate pathways.The Radiological Environmental Monitoring, Program is described in Section 9.0 of the manual, which includes the annual land use census survey and interlaboratory comparison program., It is the responsibility of the Superintendent of Plant-Susquehanna to ensure that this manual is used in performance of the surveillance requirements and for compliance with the limiting conditions of operations stated in the Technical Specifications.

It is the responsibility of the Manager-Nuclear Technology to ensure adequacy and correctness of calculational approaches.

Rev.5 01 4 10.0 DOSE ASSESSMENT POLICY STATEMENTS 10.1 Selection of Anal sis Results for Dose Calculations For determination of compliance with SSES Technical Specificatio dose limits, effluent totals shall be based only on activity positively detected at the 95%confidence level.10.2 Assi nment of Releases to the Reactor Units'For determination of compliance with SSES radioactive effluent dose limits which are on a"per reactor unit" basis: a.Effluents from the Unit 1 Reactor Building vent and the Unit 1 Turbine Building ve'nt shall be included as Unit 1 releases.b.Effluents from the Unit 2 Reactor Building vent and the Unit 2 Turbine Building vent shall be included as Unit 2 releases.c.Effluents from the Standby Gas Treatment System vent shall be equally divided between Unit 1 and Unit 2 release totals.'d.Waterborne effluents shall be equally divided between Unit 1 and Unit 2 release totals.10.3 Evaluation and Monitorin Criteria for Effluent Pathwa s Potential:effluent pathways will be evaluated on a case-by-case basis.The evaluation will include identification of systems which are normally non-radioactive (as described in the FSAR)but could possibly become radioactive through interfaces with radioactive systems (

Reference:

NRC IE Bulletin No.80-10).The evaluation will determine the significance of Rev.5 53 I'P 4 any potential effluents pathways and extent of sampling and/or monitoring required.The frequency of sampling or monitoring will be determined based on the potential for contamination, the potential for inadvertent releases, the potential levels of contamination and releases, and the potential impact on station offsite doses.Results of sampling and/or evaluation will be used to classify potential effluent pathways into one of the following categories:

a.Not an Effluent Pathwa: Realistic evaluation (e.g., engineering design, system operation, radionuclide inventory) demonstrates that the pathway has no potential for release of radioactive material (Table 8).Although not required, periodic sampling may at times be performed to confirm the result of the evaluation.

b.Insi nificant Effluent Pathwa: Evaluation and/or periodic sampling demonstrate that the pathway may contain radioactive effluents, however, these effluents may not be reasonably expected to exceed 10 percent of the appropriate unrestricted area MPC value (fractional MPCs summed when appropriate) listed in Table II of Appendix B to 10 CFR 20 (Table 9).A release pathway which falls in this category will be sampled periodically.

c.Si nificant Effluent Pathwa: Evaluation and/or periodic sampling demonstrate that the pathway may contain radioactive effluents, and these effluents may be reasonably expected to exceed 10 percent of the appropriate unrestricted area MPC value (fractional MPCs summed when appropriate) listed in Table II of Appendix B to 10 CFR 20 (Table 10).A release pathway which falls in this category will be sampled continuously.

Rev.5 54 If sampling indicates a non-radioactive system has become contaminated, further use of the system shall be restricted until the cause of the contamination has been corrected and the system is decontaminated.

If continued operation of the system as contaminated is necessary, a 10CFR50.59 safety evaluation of the operation of the system as a radioactive system shall be performed immediately by the system operator/engineer.

The safety evaluation will include any changes in the effluent pathways and the impacts to offsite doses.(Ref.NRC IE Bulletin 80-10).Systems with NRC I/E Bulletin applicability are designed to be used as non-radioactive, but which could possibly become radioactive through interface(s) with radioactive systems, and which have a path for unmonitored and/or uncontrolled release to the environment.(Table 11)Positively detected radioactive material in samples collected from all airborne and waterborne offsite release pathways will be reported in the Annual Effluent and Waste Disposal Report.10.4 Flow from the SGTS Vent when the S stem is Not in Use When the Standby Gas Treatment is not being used, there remains a small amount of flow from the SGTS vent.This residual flow is exhaust from the battery rooms in the control structure.

'Because there are no identifiable sources of radioactivity in these rooms, auxiliary particulate and iodine sample and noble gas grab sample at 4-hour intervals are not required from the SGTS vent when the SGTS continuous vent monitor is out of service, trrovided that-a.the Standby Gas Treatment System is not being used, Rev.5 55 b.there are proper administrative controls in place to ensure that the required sampling will begin within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if the treatment system is operated.10.5 ODCM Set pints are U er Limit Values Effluent monitor alarm/trip setpoints calculated in accordance with the ODCM shall be considered upper limit values.Higher (less conservative) setpoints shall not be used, however lower (more conservative) setpoints may be used as required to maximize the utility of the monitor.10.6 Definition of"A ro riate Treatment" for Li uid Wastes Technical Specification 3.11.1.3 requires that the appropriate portions of the liquid waste treatment system be operable and be used to reduce radioactivity in liquid wastes prior to their release when projected doses from each reactor unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.~The normal treatment, which is considered appropriate for each subsystem, is as follows: Filtration is considered appropriate treatment for the Liquid Radwaste Laundry Processing Subsystem, which consists of high conductivity liquid wastes, such as those from equipment washdown and personnel decontamination facilities, or laundry.The atmospheric demineralizer (a vendor-supplied system which is directed to the Distillate Sample Tank)is considered appropriate for the Liquid Radwaste Chemical Processing Subsystem.

Rev.5 56 4 ,I 4 Demineralization and filtration are considered appropriate treatment for low conductivity/low organic contaminant liquid wastes entering the Liquid Radwaste Processing Subsystem (LRW collection tanks), except for batches which yield projected doses prior td treatment of less than or equal to 6.45-04 mrem to the total body and 2.15E-03 mrem to any organ, where filtration alone is appropriate, of~For batches which have no identified gamma activity above the Technical Specification Liquid Effluent LLD level (Table 4.11.1.1.1-1

), release without treatment is considered appropriate.

BASES The projected dose threshold values used are derived by dividing the site-total maximum projected doses without treatment (0.12 and 0.4 mrem)by 31 days and by 6, the maximum possible number of batches released per day, to yield per-batch dose action levels.The two levels of"appropriate" treatment are in place so as not'to require application of demineralization for treating low activity, high conductivity water (e.g., from Circulating or Service Water leakage).This would increase the overall efficiency of the solid radwaste program while ensuring calculated doses remain at a suitable fraction of 10 CFR 50 design objectives and Technical Specification 3.11.1.2 limit."'"'.

"'Reference Calculation No.OT-RKB-92-001:

Calculation of Liquid Isotope Offsite Dose Consequences for Use of Atmospheric Demineralizer System, PLI-70360, 2/4/92.Rev.5 57

10.7 Monitor Line Loss Corrections In order to correct for airborne eNuent monitor sample line loss, the following correction factors shall be applied to monitor data and sample analysis results: CORRECTION FACTORS Routine Effluent Monitors iodine Particulates Reactor Building Unit 1 Reactor Building Unit 2 Turbine Building Unit 1 Standby Gas Treatment Turbine Building Unit 2 1.5 1.5 1.6 1.5 1.6 3.2 3.2 3.6 3.9 3.6.CORRECTION FACTORS Post-Accident Vent Monitors iodine Particulates Turbine Building Unit 1 Standby Gas Treatment Turbine Building Unit 2 1.7 1.6 1.7 4.2'4 4.3 Each indicated iodine and particulates concentration shall be multiplied by the appropriate correction factor to estimate the actual concentration at the inlet to the sample line.+Reference Letter R.K.Barclay to R.A.Breslin: Atmospheric Demineralizer ENuent Results, PLI-70612, 3/4/92.DAT Rev.5 58

10.8 Selection of Data for Determination of Dose Rate Com liance Airborne effluent monitor setpoints are maintained in accordance with Section 2.2 to alarm before the dose rate limits of Specification 3.11.2.1 are exceeded.Station alarm response procedures contain instructions for investigation and verification of monitor alarms.Because setpoint calculations must include assumptions about the composition of the monitored effluent, a monitor high alarm does not necessarily indicate that a dose rate limit has been exceeded.Valid ten-minute averaged data should be the primary information used to determine the compliance status of an incident.One-minute averaged~data should also be reviewed if available, but they may or may not provide additional information depending on the magnitude of the release due to the manner in which the monitors update values to be stored and associated statistical considerations.

Averages over a longer period should be used only when data with higher resolution is not available.

Grab sample analyses should be performed whenever possible to confirm or disprove monitor'data, and to provide indication of the nuclide-specific composition of the effluent.When grab sample data are available which, based on vent monitor data, are indicative of the period of elevated release, dose rate calculations should be performed using the actual effluent mix.The determination of compliance status should not be based on monitor data alone when it is possible to collect and analyze a vent sample which will be representative of the period of elevated release.OAT Rev.5 59 10.9 Low-Level Radioactivit in the Sewa e Treatment Plant Like all sewage processing facilities, the SSES sewage treatment plant can under certain conditions receive low levels of radioactive materials.

The most notable scenario is when individuals who work on-site have been subjected to the medical administration of radiopharmaceuticals for diagnostic or therapeutic purposes.In these cases, normal biological elimination processes can easily result in levels of radioactivity in sewage treatment plant solutions and suspensions which are within the detection capabilities of the associated sampling and analysis program.Because disposal of sewage treatment plant sludge by controlled dispersal on specified tracts of land is a common practice, the following guidelines have been established:

a.At(sludge collected in the sludge holding tank should be sampled and analyzed prior to land disposal to quantify any radioactivity

'resent above natural background levels.b.Sludge containing nuclides with short half-lives, for example iodine-.131, should be contained on-site to permit decay to less than detectable levels.c.When sludge is contaminated with nuclides which have half-lives

'ufficiently long to make hold-up for decay impractical, the following options should be considered:

1.Dispose of the sludge as low level radioactive waste.Rev.5 60 I'I"~v'i 2.Obtain a special permit pursuant to the requirements of 10 CFR 20.2002.d.The sewage treatment plant liquid effluent should be sampled monthly for radioactivity.

This can be accomplished by drawing'a sample from the chlorine contact chamber.Rev.5 61 TABLE 8 SYSTEMS CLASSIFIED AS NOT AN EFFLUENT PATHWAY (Page 1 of 3)SYSTEM DESCRIPTION Domestic Water River Water Makeup Intake Compressed Air Screens and Screenwash Fire Protection Water Fire Protection CO2 Fire Protection Halon Turbine Building Closed Cooling Water'Building Drains: NON RAD Water Pretreatment Condensate and Refuel Water Transfer Low Pressure Air Condensate Demins Lube Oil Transfer/Purification Cooling Tower Acid/Chlorination Circulating Water Condenser Tube Cleaning Feedwater Extraction Steam Feedwater Heaters Residual Heat Removal Reactor Core Isolation Cooling Core Spray High Pressure Coolant Injection Standby Liquid Control Control Rod Drives REFERENCE PPRL Calculation EC-ENVR-1 008 Rev.5 62

TABLE 8 SYSTEMS CLASSIFIED AS NOT AN EFFLUENT PATHWAY (Page 2 of 3)SYSTEM DESCRIPTION Suppression Pool Primary Containment Vacuum Breakers Suppression Pool Cleanup Reactor Water Cleanup'eactor Pressure Vessel Reactor Recirculation System Radwaste Chilled Water Solid Radwaste/Cement Silo LRW Collection/Tb and Cond.Outer Area Sumps LRW Processing/Radwaste Evaporator Gaseous Radwaste Recombiner Closed Cooling Water Nitrogen Storage Hydrogen Storage Sampling Stations Post Accident Sampling System Bypass Steam Main Steam Isolation Valves/Nuclear Steam Supply System Shutoff Automatic Depressurization System MSlV Leakage Control Moisture Separators Turbine Steam Seals Electrohydraulic Control Stator Cooling Main Generator Storm Drains REFERENCE PP8L Calculation EC-ENVR-1008 Rev.5 63 TABLE 8 SYSTEMS CLASSIFIED AS NOT AN EFFLUENT PATHWAY (Page 3 of 3)SYSTEM DESCRIPTION Makeup Demineralizers Fuel Oil Containment Instrument Gas Control Structure Chilled Water Turbine Bldg.Chilled Water Reactor Bldg.Chilled Water Auxiliary Boileis Fuel Pool Cooling Fuel Pool Demineralizers Fuel Pools Temporary SDHR System REFERENCE (1)PP8 L Calculation EC-ENVR-1 008 (7)Safety Evaluation NL-95-001:

Refueling Outage Decay Heat Removal and Tie-ln of the SDHR Temporary Cooling Equipment Rev.5 64 bl II TABLE 9 SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAY SYSTEM DESCRIPTION H2 Seal Oil Condensate/Refuel Water Storage Tank and Berm Main Turbine/RFPT Lube Oil/H2 Seal Oil Instrument Air Service Air Temporary Laundry Facility Second Sort (DAW Volume Reduction)

Facility Low Level Radwaste Handling Facility Sewage Treatment Plant REFERENCE (1), (8)(1)(8)(1), (8)(2)(3)(4)(9)(1)PPB L Calculation EC-ENVR-1008 (2)Safety Evaluation NL-90-029:

Temporary I aundry Facility (3)Safety Evaluation NL-89-002:

Dry Active Waste Volume Reduction System (4)Safety Evaluation NL-92-007:.

Operation of LLRWHF at SSES (8)Main Tb/RFPT Lube Oil, Instrument Air and Service Air are designed to be operated as non-radioactive systems.They are classified as insignificant pathways based on source terms and offsite dose rate results for consideration of a contaminated source term.(9)Sewage treatment plant'is designed to be operated as a non-radioactive system.Classification as an insignificant effluent pathway is in accordance with Safety Evaluation NL-95-015.

Rev.5 65 TABLE 40 SYSTEMS CLASSIFIED AS SIGNIFICANT f FFLUENT PATHWAY SYSTEM DESCRIPTION Liquid Waste Management Systems Gaseous Waste Management Systems REFERENCE (5)(6)(5)SSES FSAR Chapter 11.2 (6)SSES FSAR Chapter 11.3 , oa Rev.5 66

TABLE 11 SYSTEMS WITH NRC VE BULLETIN 80-10 APPLICABILITY SYSTEM NO.16 18 19 27 35 40 48 52 54 93 99D DESCRIPTION Service Water (F/P HTX Discharge)

RHR Service Water Instrument Air Service Air Auxiliary Boilers Shutdown Decay Heat Removal System Batch Lube Oil Tank Feedwater Pump Turbine Lube Oil H2 Seal Oil Tank Emergency Service Water Main Turbine Lube Oil Sewage Treatment Plant OAT Rev.5 67 41.0 ODCM REVIEW AND REVISION CONTROL The Supervisor-Environmental Services-Nuclear shall ensure that a total review of the ODCM is performed during each evenwumbered year.Comments shall be documented and revisions initiated as appropriate.

Revisions to the ODCM shall be initiated in accordance with NEPM-QA-1011.

Each ODCM page shall be numbered and provided with an approval and date box.The ODCM Table of Contents shall present the current revision date for each page so that any manual holder can check manual completeness based on a current Table of Contents.All ODCM revisions shall be reviewed by PORC after approval by the Manager-Nuclear Technology.

PORC review shall be indicated by PORC chairperson or designee signature on ODCM cover.ODCM copies shall be issued in a controlled fashion by SSES Document Control Services.The distribution list shall be maintained by SSES Document Control Services.Any comments on ODCM contents or proposed revisions should be directed to the Supervisor-Environmental Services-Nuclear.

Rev.5 68

APPENDIX B REVISIONS TO SSES SOLID WASTE PROCESS CONTROL PROGRAIN (NDAP-QA-0646)

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1 PROCEDURE COVER SHEET'NUCLEAR DEPARTMENT PROCEDURE~~rc S>SOLID RADIOACTIVE WASTE PROCESS CONTROL PROGRAM NDAP-QA-064'6 Revision 4 Page 1 of 63 EFFECTIVE DATE: PERIODIC REVIEM FREQUENCY:

PERIODIC REVIEW DUE DATE: REVISED PERIODIC REVIEM DUE DATE'PROCEDURE TYPE: OA Program (g)YES ()NO Plant.Procedure (~}YES ()NO REVIEW METHOD: ()Alternate ()Expedited (Q)PORC ()ERC Prepared by Revi'ewed by Recommended Superv ctiona Un Manager Date 3-~~.9S Date Approved by PORC Committee Heeting No.ERC Co tt Date Date FORM NDAP-QA-0002-1, Rev.1, Page 1 of 1 IIIIHlslllllllIIIINlllIIIllIIIIlslflfllIIII lslllIIllliIlllllIlllSIl NDAP-OA-0646 Revision 4'age 2 of 63 PROCEDURE REVISION

SUMMARY

SOLID RADIOACTIVE WASTE PROCESS CONTROL PROGRAM'The following changes will not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.1)Incorporated PCAF 1-94-1330 revising the PCP implementing procedure matrix to reflect actual procedures in use and changed the requirements for disposal of radioactive waste'samples after packaged radioactive waste has been in its designated storage area.2), 3)Added SEG NRC approved Topical Report STD-P-05-Oll-P-A to Contracted Vendor Services to reflect use of SEG for waste processing equipment, methods and verification of acceptable waste forms for dewatering and solidification.

Added Activated Carbon as a new waste type which is generated from processing of liquid wastes using vendor provided demineralization services.4).Added the Solidification/Dewatering/Services Vendor may perform test solidification and determination of mixing ratios for solidification performed offsite (vendor facility)5),6)Added Radlok (SEG)type containers to High Integrity Container approved for use list.Added SNH inventory requirements during processing per SOOR 94-581 resolution.

7)Added NRC Technical Position on Concentration Averaging and Encapsul'ation to Radioactive Waste Analysis and Classification to ensure that radionuclide/concentrations are adequately distributed over the volume or weight of the waste.

SECTION 1.0 PURPOSE 2.0 POLICY/DISCUSSION

3.0 REFERENCES

4.0 RESPONSIBILITIES TABLE OF CONTENTS NDAP-gA-0646 Revision 4 Page 3 of 63 PAGE ,6 4.1 EFFLUENTS MANAGEMENT SUPERVISOR 4.2 SUPERVISOR

-OPERATIONS TECHNOLOGY 4.3.POMER PRODUCTION ENGINEER-EFFLUENTS MANAGEMENT 4.4 HEALTH PHYSICIST-EFFLUENTS MANAGEMENT 4.5 RADMASTE SUPERVISOR 4.6 CHEMISTRY SUPERVISOR 4.7 HP FOREHAN-EFFLUENTS MANAGEMENT 4.8 MANAGER-NUCLEAR ASSESSMENT SERVICES 4.9 AUXILIARY SYSTEHS OPERATOR 4.10 SOLIDIFICATION/DEWATERING/SERVICES VENDOR 4.11 HANAGER-NUCLEAR PROCUREMENT 4.12 HANAGER-NUCLEAR SYSTEMS ENGINEERING 4.13 MANAGER-NUCLEAR MAINTENANCE 4.14 LICENSING SUPERVISOR 4.15 MANAGER-NUCLEAR TRAINING 4.16 HANAGER-NUCLEAR SECURITY 5.0 DEFINITIONS 10 10 12 13 13 13 14 14 14 15 15 15 NDAP-gA-0646 Revision 4 Page 4 of 63 SECTION 6.0 PROCEDURE TABLE OF CONTENTS Continued PAGE 20.6.1 CONTRACTED VENDOR SERVICES 6.2 WASTE TYPES 6.3 RADIOACTIVE MASTE ANALYSIS AND CLASSIFICATION 6.4 TESTING/TREATMENT OF SOLIDIFIED RADMASTE FOR COMBUSTIBLE GASES 6.5 RADIOACTIVE WASTE SOLIDIFICATION 6.6 RADIOACTIVE WASTE DEWATERING 6.7 HIGH INTEGRITY CONTAINERS (HIC)6.8 IRRADIATED HARDMARE PROCESSING AND DEWATERING 6.9 CONTAINER INSPECTIONS 6.10 WASTE CONTAINER SPACE UTILIZATION 6.11 STORAGE OF PACKAGED RADIOACTIVE WASTE 6.12 TRANSPORTATION, SHIPPING AND DISPOSAL REGULATIONS 6.13 SHIPPING OF RADIOACTIVE.WASTE 6.14 SHIPMENT CONFIRMATION 6.15 CHANGES TO THE SOLID RADIOACTIVE MASTE PROCESS CONTROL PROGRAM 6.16 EVALUATION OF PROCESS OR OPERATIONAL CHANGES 6.17 REPORTING OF HISHAPS INVOLVING LOW LEVEL WASTE FORNS 6.18 PCP IHPLEHENTING PROCEDURES 7.0 RECORDS 20 21'7 30 30 40 42 46 47 47 48 51 51 51 52 53 54 NDAP-0A-0646 Revision 4 Page 5 of 63 ATTACHMENT ATTACHMENTS PAGE A Solidification Record Sheet B Dewatering Record Sheet C Susquehanna Guaranteed Solidified/Dewatered Waste Volume Record D PCP Implementing Procedure Matrix E Materials not Compatible with Polyethylene Containers 55 56 60 63 NDAP-QA-0646 Revision 4 Page 6 of 63 1.0 PURPOSE Provide administrative control, guidance and records for the processing, packaging, transportation, and disposal of radioactive waste.This procedure is the Process Control Program required by SSES Technical Specifications.

'2.0~LIC I UKM This procedure is applicable to Low Level Radwaste (LLRW)generated as a result of the operation of the Susquehanna Steam Electric Station (SSES).The waste streams include solid and liquid waste'as defined in the FSAR, but do not include spent fuel or greater than Class C waste.Efficient generation and processing of radioactive waste is very important to the overall operation of SSES.An important objective with respect to radioactive waste generation is to minimize the volume of waste generated.

The processing of large volumes of waste can result in the inability to dispose of or store'all waste packaged, the significant increased costs associated with increased waste generation, and the-potential to over-burden the processing system and degrade its long term reliability.

The Process Control Program describes the envelope within which processing and packaging of radioactive waste is accomplished to provide reasonable assurance of compliance.

with Low-Level Radwaste regulations and requirements.

Th'is procedure is applicable to SSES installed systems, temporary systems and equipment provided by vendors for processing, packaging, transportation, and disposal of applicable waste forms.

3.0 REFERENCES

3.1 49CFR100-l77, Transportation 3.2 10CFR20, Standards for Protection Against Radiation 3.3 10CFR61, Licensing Requirement for Lar" Disposal of Radioactive'aste A 3.4 10CFR71, Packaging and Transportation of Radioactive Material 3.5 40CFR261, Identification and Listing of Hazardous Waste 3.6 3.7 SSES Technical Specifications Section 3/4.11.3, Solid Radwaste System SSES Technical Specifications Section 6.13, Process Control Program (PCP) h e'i NDAP-0A-0646 Revision 4 Page 7 of 63 3.8 3.9 3.10 3.11 3.12 3.13 3.14 3.15 NUREG 0800, Standard Review Plan 11.4 Solid Waste Management Systems Technical Position on Waste Form Rev.1, 1991 Technical Position on Radioactive Waste Classification, Rev.0, 1983 Technical Position on Concentration Averaging and Encapsulation; Rev.0, 1995 Regulatory Guide 1.21, Measuring, Evaluating and Reporting Radioactive Material in Solid Wastes and Release of Radioactive Material in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plants Regulatory Guide 1.143, Design Guidance of Solid Waste Management'ystems Regulatory Guide 7.1, Administrative Guide for Packaging and Transporting Radioactive Material ANSI/ANS 40.35, Volume Reduction of Low Level Radioactive Waste 3.16 ANSI/ANS40.37, Mobile Radioactive Waste Processing Systems 3.17 3.18 3.19 3.20 ANSI/ANS 55.1, Solid Radioactive Wast'e Processing System for Light Water Cooled Reactor Pl.ant Pacific Nuclear Dewatering System Topical Report No.TP-02-P-A, Rev.3 Pacific Nuclear Solidification Process Control Procedure No.PT-51-WS, Rev.40 Scientific Ecology Group Mobile Incontainer Dewatering and Solidification System (MDSS)Topical Report No.STD-R-05-011-P-A; Rev.2 3.21 Disposal Site Criteria for Barnwell, S,C.3.22 DHEC-HIC-PL-001 South Carolina Certificate of Compliance for CNSI High Integrity Containers 3.23 DHEC-HIC-P0-006, South Carolina Certificate of Compliance for CNSI Overpack High Integrity Containers 3.24 DHEC-HIC-PL-012, South Carolina Certificate of Compliance for Vectra Technologies, Inc.High Integrity Container I

(")()()4.0 NDAP-gA-0646 Revision 4 Page 8 of 63 3.25 DHEC-HIC-PL-005, South Carolina Certificate of Compliance for Scientific Ecology Group, Inc.High Integrity Containers 3.26 DHEC-HIC-PL-017, South Carolina Certificate of Compliance for Scientific Ecology Group, Inc.High Integrity Containers 3.27 PLA-1237, Process Control Program, August 17, 1982 3.28 Review of Process Control Program for Susquehanna, Unit I, Youngblood to Curtis, September 30, 1982 3.29 Safety Evaluation NL-93-008, Solid Radwaste Waste Processing Services Utilizing Pacific Nuclear Processing System 3.30 IE Bulletin 79-19, Packaging of Low Level Radioactive Waste for Transportation and Burial 3.31 NRC Information.

Notice No.90-50, Minimization of Methane Gas Generation in Plant Systems and Radwaste Shipping Containers.

3.32 Generic Letter 91-02, Reporting Mishaps Involving LLW Forms Prepared for Disposal 3.33 SOOR-1-90-148, Barnwell Received Container Pressurized with Flammable Gas 3.34 SOOR 1-90-172, Incorrect Sampling Method Used on Resin Liner 3.35 SOOR 1-91-322, Dose Rates on Container Higher Than Expected 3.36 SOOR 94-581, Spent TIP Found Unexpectedly in TIP Room.t RESPONS I BI LITI ES 4.1'ffluents Management Supervisor responsibilities:

4.1.1 4.1.2 4.1.3 Developing and implementing programs and procedures for radioactive waste processing, packaging, transportation and disposal.Maintaining the overall radwaste program to ensure compliance with applicable radiological and shipping regulations.

Ensuring personnel who perform support activities such as processing, packaging, and transportation of low'evel radioactive waste are available and meet all qualifications and training required by SSES procedures..

NDAP-QA-0646 Revision 4 Page 9 of 63 Collecting, maintaining, reviewing and submitting accurate data/information related to waste stream quantity and nuclide composition for inclusion into Annual Radioactive Effluent Release Report and State DER-BRP'Quarterly Report.4.2 Supervisor

-Operations Technology responsibilities:

Providing technical assistance to Effluents Management personnel.

This includes interpretations of state, federal, and disposal facility regulations regarding new, imminent, or proposed regulatory changes governing processing, packaging, transportation, and disposal.4.2.2 4.2.3 Maintaining a current copy of local, state, federal and disposal facility regulations pertaining to disposal and transportation of low level radioactive waste.Coordinating the submittal of the Annual Radioactive Effluent Release Report as per the SSES Technical Specifications.

4.3 Power Production Engineer-Effluents Hanagement responsibilities:

Ensure procedures are adequate to provide for proper solidification and dewatering of waste.4.3.2 4.3.3 4.3.4 4.3.5 Ensure test data or rationale is available to justify applicable solidification and dewatering functions of each waste type, or any combinations, to address disposal and regulatory agencies'equirements.

Evaluate services provided by various vendors to ensure contracted solidification and dewatering operations are performed in the most efficient and economical method, as required by the applicable regulatory agencies.Perform the duties of Radwaste Supervisor as specified in this procedure in his absence.Define waste streams based on generator, filtration media and means of processing.

'P NDAP-gA-0646 Revision 4 Page 10 of 63 4.3.6 Collecting, reviewing and submitting data related to the reporting of mishaps and results of PCP surveillance specimen examinations to applicable regulatory agencies.4.4 Health Physicist-Effluents Management responsibilities:

4.4.1 4.4.2 4.4.3 4.4.4 4.4.5 Maintain a sampling and arialysis program to ensure lOCFR61 compliance.

Ensure procedures are adequate to provide for proper packaging and shipment of waste to ensure compliance with all applicable regulations.

Evaluate services provided by various vendors to ensure contracted waste packaging, processing, and transportation services are performed in the most efficient and economical method, as required by applicable regulatory agencies.Perform the duties of HP Foreman-Effluents Management as specified in this procedure in his absence.Coordinate radioactive material evaluation of product acceptability for disposal at specific disposal facilities.

4.5 Radwaste Supervisor responsibilities:

4.5.1 4.5.2 4.5.3 4.5.4'nsure Solidification/Dewatering Equipment is operated in accordance with approved operating procedure, incl.uding vendor supplied equipment.

Ensure appropriate waste solidification and.dewatering records'are generated.

Interface with station support groups to ensure proper implementation of process control programs.Provide direction to contractor personnel involved in solid waste processing activities including:

a~b.Ensuring test data is available to justify specific processing techniques.

Ensuring applicable vendor procedures and revisions are incorporated into applicable plant procedure and approved by PORC.

NDAP-gA-0646 Revision 4 Page ll of 63 c.Coordinating pre-processing and post-processing treatment activities.

d.Evaluating services provided to ensure efficient and economical methods are used.4.5.5 4.5.6 Ensure Solidification and Dewatering operations are carried out in an ALARA manner.Interface with HP Foreman-Effluents management for liner and cask selection for solid waste shipping activities.

4.5.7 4.5.8 4.5.9 4.5.10 4.5.11 4.5.12 Ensure proper marking of containers prior to filling.Ensure solidification/dewatering personnel are adequately trained per NTP-gA-42.6.

Estimate classification of waste for container selection and processing method.Ensure that'waste streams loaded into High Integrity Containers are sampled for radionuclide and evaluated for chemical compatibility applicable to the use of High Integrity Containers.

Ensure proper inspections and documentation are complete prior to use of a High Integrity Container and ensure that container is properly used up to the point of transfer to HP Foreman-Effluents Nanagement.

Complete and process High Integrity Container User Certification Statement to ensure the container is used properly.4.6 Chemistry Supervisor responsibilities:

4.6.1 4.6.2 4.6.3 4.6.4 Perform required sample preparation and analysis in accordance with approved chemistry procedures, Perform test solidification if required.Store test solidification billet if required.Provide density of initial and final waste form.Provide the isotopic mix and concentration of isotopes detected in the material sampled for solidification or dewatering.

NDAP-gA-0646 Revision 4 Page 12 of 63 4.6.5 4.6.6 Complete Chemistry portion of the Solidification and Dewatering Records.Ensure personnel are adequately trained per NTP-(A-41.2.

4.6.7-Provide chemical analysis and/or treatment support as necessary for use of High Integrity.Containers and liners.E 4.7 HP Foreman-Ef fl uents Management responsibilities:

4.7.1 4.7.2 Interface with Radwaste Supervisor for liner and cask selection and scheduling for solid waste shipping activities.

Complete, process, and,file radioactive waste shipping documentation.

4.7.3 Storage of packaged radioactive waste within the radwaste facilities.

4.7.4 4.7.5 4.7.6 4.7.7 4.7.8 Determine waste classification and description of solidified, dewatered, and other packaged waste.Final disposition of solidified, dewatered and other packaged waste.Ensures SSES is a registered user of applicable High Integrity Containers at specific disposal facilities.

Ensures HP personnel involved with radioactive waste handl.ing have received Radwaste Worker training per NTP-(A-42.6.

Evaluate vendor services provided to ensure efficient and economical methods are used.4.7.9 4.7.10 Complete and process Cert:" cation Statement for Disposal of High Integrity Containers as required by applicable regulatory agencies.Process and package Cartridge Filters, Dry Active Waste, solid sealed sources and other non process wastes.4.7.11 Collection of DAW and non-process waste (IOCFR61)samples.

NDAP-gA-0646 Revision 4 Page 13 of 63'.8 Hanager-Nuclear Assessment Services responsibilities:

4.8.1 4.8.2 4.8.3 4.8.4 Perform periodic audit of implementation of this program and review of radwaste service vendor's gA Programs.Inspection of Radwaste,Containers as required by applicable procedures.

Ensure process controls are adhered to by inspection of test solidification, waste volumes, solidification agent additions, product acceptability checks, dewatering process sequence/acceptance criteria and records review.Inspection of packaging, storage, and shipping activities, as required by applicabl.e procedures.

4.9 Auxiliary Systems Operator is responsible for operating the plant.solid and liquid radwaste equipment in accordance with approved operating procedures as directed by the Radwaste Supervisor and Assistant Unit Supervisor.

4.10 Solidification/Dewatering/Services Vendor responsibilities:

.Provide solidification, dewatering and/or volume reduction services in accordance with a valid contract for said services.4.10.2 4.10.3 4.10.4 4.10.5 Provide test data or make data available for PP8L review during vendor audits to demonstrate that their services and equipment meet the applicable regulatory and disposal facility limitations for the service they are providing.

Provide training documentation to demonstrate that the personnel being provided, to conduct the applicable

• service, are in fact trained and knowledgeable in the applicable services.Provide procedures that are or can be placed into the SSES procedure format for the services being provided.Ensure an approved guality Assurance Program exists that covers the services being provided.The vendor shall work within the SSES guality Assurance Program when applicable.

'C' NOAP-OA-0646 Revision 4 Page 14 of 63 4.10.6 4.10.7 Complete applicable sections of Solidification and Dewatering Records required for each container processed.

Ensure pre-qual'ification test data for each waste form shall be submitted to the Nuclear Regulatory Commission.

'4.10.8 4.10.9 4.10.10 4.11 Hanager-4.11.1 4.11.2 Provide a description of the equipment/process that;is used in processing waste.Obtain waste samples from processing equipment in accordance with approved operating.procedures.

Perform all pre and post treatment activities as determined by Radwaste Supervisor.

Nuclear Procurement responsibilities:

H Ensure High Integrity Containers are not exposed to ultra violet light (sunlight).

Ensure proper material certification is complete prior to issuance of High Integrity Containers to plant for use.4.11.3 Receipt inspection of High Integrity Containers and document review to ensure conformance.

4.11.4 Ensure Certificate of Compliance (C of C)is received with High Integrity Container.

4.12 Manager-Nuclear Systems Engineering is responsible for providing engineering support as required for operation of assigned radwaste systems and equipment.

4.13 Manager-Nuclear Maintenance responsibilities:

4.13.1 4.13.2 Calibration and maintenance of applicable plant equipment in Radwaste Processing Systems.Provide maintenance personnel to support processing, packaging and transportation of low level radioactive waste.4.14 Licensing 4.14.1 Supervi sor responsibi1 i ties: Submitting transportation cask user registration requests to, NRC per lOCFR71.12.

NDAP-gA-0646 Revision 4 Page 15 of 63 4.14.2 4.14.3'Submitting to the NRC the Annual Radioactive Effluent Release Report.Coordinating and submitting to the NRC'the reports required as a result.of Condition Report (CR)events, investigations, and resolutions.

4.15 Manager-Nuclear Training responsibilities:

4.15.1 Prov'd'n tra'ni a d i i g i ng n re training in applicable regulatory requirements to personnel directly involved in transfer, processing, packaging, storage, and transport of radioactive waste.4.15.2 Maintaining a record of training, attendees, and subject material for all Low Level Radioactive Maste training.4.16 Manager-Nuclear Security is responsible for notifying appropriate law enforcement a'gencies in the event of lost radioactive material shipments.

5.0 DEFINITIONS 5.1 APPROYED CONTAINERS:

Approved means approval issued or recognized by the NRC for use in shipment of radioactive material.5.2 5.3 BATCH: The total volume of waste contained in a liner, isolated-waste mixing tank-spent resin tank-concentrates tank or-phase separator that has been sampled for solidification/dewatering.

BILLS OF LADING: Shipping papers or manifests serving a similar purpose and containing the information required by 49 CFR 172.202, 203, and 204.5.4 CARRIER: Means a person engaged in the transportation of passengers or property.(10CFR71.4) 5.5 CERTIFICATE OF COMPLIANCE:

License requirements established by the Nuclear Regulatory Commission for.the use of approved Radioactive Material Shipping Containers.

5.6'CHELATING AGENT: A chemical which combines with a metal so as to form a ring structure held by coordination bonds.

NDAP-gA-0646 Revision 4 Page 16.of 63 5.7 5.8 5.9 CHEMICAL FORM: The chemical content of the Radioactive Material being shipped.CLOSED TRANSPORT VEHICLE: A vehicle equipped with a securely attached exterior enclosure, which during normal transport, restricts the access of unauthorized persons to the cargo space.(49 CFR 173-403[C])

COMPOSITE SAMPLE: A mixture of samples collected representing conditions at time of sampling, from the same sampling point, at different times.5.10 CONSIGNEE:

The individual or organization to whom the shipment is consigned or intended.5.11 CURING TIME: The time allowed for the solidified product to set prior to its evaluation for product acceptability.

5.12 5.13 5.14 5.15'5.16 DECAY'EAT:

The heat produced by radioactive decay, usually expressed in Watts or BTU/hr, but can be related to Curie Content.DEWATERED:

The removal of free liquid from solid material to a point where less than IX for HIC's and lessthan 0.5X for steel liners by waste volume remains as required by the disposal facility license.EXCLUSIVE USE VEHICLE (a/k/a: Sole Use or Full Load): Shipment from a single consignor having the exclusive use of a transport vehicle and for which all initial, intermediate.

and final loading and unloading is carried out by, or under the airection of the consignor, consignee, or his designated agent.(49 CFR 173.403[i])

FREE LIQUID: Liquid which is still visible after solidification or dewatering is complete, or is drainable from the low point of a punctured container.

1 HAZARDOUS MATERIAL-A substance or material, including a hazardous substance which has been determined by the Secretary of Transportation to be capable of posing a threat to health, safety, and property when transported in commerce, and which has been so designated.

The term includes hazardous substances, hazardous wastes, marine pollutants, and elevated temperature materials as defined in 49CFR171.8, materials designated as hazardous under the provisions of 49CFR172 F 101 and 172.102, and materials that meet the defining criteria for hazard classes and divisions in 49CFR173.

.NDAP-gA-0646 Revision 4 Page 17 of 63 5.17=5.18 HAZARDOUS WASTE: Waste which contains material listed in 40 CFR 261, Subpart D and/or exhibits one or more of the four characteristics cited in 40 CFR 261, Subpart C, and is not excluded from regulation under 40 CFR 261, Subpart A.Hazmat Employee means a person who is employed by a Hazmat Employer who during the course of employment:

5.18.1 Loads, unloads or handles hazardous materials.

5.18.2 Prepares hazardous materials for transportation.

5.18.3 5.18.4 Modifies, marks, or otherwise represents containers, drums, or packagings as qualified for use in transport of hazardous materials.

Is responsible for safety of transporting h'azardous material.5.19 5.20 5.21 5.22 5.23 5.24 5.25 HIGH INTEGRITY CONTAINER (HIC): A disposal site approved container that has an expected life of 300 years and provides the structural stability tb meet disposal requirements.

HIGHWAY ROUTE CONTROLLED QUANTITY: A quantity', the aggregate radioactivity of which exceeds that specified in (49 CFR 173.403[1]).

ISOTOPIC ANALYSIS: The identification of the isotopic elements.involved in a sample of Radioactive Material.LABELING: Labels applied to a container denoting the contents of the container and degree of hazard associated with the containers.

The labels are.identified as the White I label, the Yellow II, and Yellow III label.A label stating Radioactive

-LSA can also be applied to a container when appropriate.

(49 CFR 172,.Subpart E)LIMITED QUANTITY OF RADIOACTIVE MATERIAL: Means a quantity of radioactive material not exceeding the material package limits specified in 49 CFR 172.423, and which conforms with requirements specified in 49 CFR 173.421.(49 CFR 173.403[m])

LINER: Steel container in which dewatered or solidification product is deposited.

LOW SPECIFIC ACTIVITY: Material in which the acti vi ty is essentially uniformly distributed and in which the estimated average concentration per gram of contents does not exceed the specification as stated in 49 CFR 173.403 (n).

NDAP-gA-0646 Revision 4 Page'18 of 63 5.26 5.27 5.28 5.29 5.30 5.31 5.32 5.33 5.34 5.35 5.36 LOW LEVEL RADIOACTIVE WASTE (LLRW): Radioactive waste generated as a result of operation of SSES, excluding spent fuel or by product material, is classified by the NRC as low-level~radioactive waste.LLRW does not include"greater than class C" waste.MIXING RATIO: The ratio of waste to cement and additives required for satisfactory solidification.

MIXING RECIPE: The amount of waste, cement and additives mixed to solidi fy waste.MIXED WASTE: A mixture of low level radioactive and hazardous waste.NORMAL FORM RADIOACTIVE MATERIALS:

Means radioactive materials which do not meet the requirements of Special Form Radioactive Materials (49 CFR 173.403[s]).

PLACARDING:

A label affixed'to all four sides of the transport vehicle denoting'the presence and level of Radioactive material on the vehicle.(49 CFR 172, Subpart F)PROCESS CONTROL PROGRAM (PCP): Program which contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is assured.RADIOACTIVE MATERIAL: For purposes of transportation only, material in which the activity is essentially uniformly distributed and the estimated specific activity exceeds 0.002 microcuries per gram of material.(49 CFR 173.403[y]

and[aa])RADWASTE WORKER: A Hazmat Employee involved with the.collection', packaging, and transportation of radioactive waste.SEALED SOURCES: Any by-product material that is encased in a capsule designed to prevent leakage o scape of by-product material.SOLIDIFICATION:

A conversion of radioactive materials from liquid and solid systems to a homogeneous (uniformly distributed) monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free standing).

I NDAP-gA-0646 Revision 4 Page 19 of 63 5.37 5.38 5.39 5.40 5.41 5.42 5.43 5.44 SOLIDIFIED RADWASTE: Wet waste which is solidified (e.g.evaporator concentrates, sludge), meets the free liquid criteria, and satisfies applicable transportation and disposal site.requirements.

Dewatered resins or filter sludge satisfying the ,two latter criteria shall also be defined as solidified radwaste.SPECIAL FORM RADIOACTIVE MATERIALS:

Radioactive.

material that is either a single piece, or is contained in a sealed capsule,,that can be opened only be destroying the capsule and meets the additional requirements specified in 49 CFR Part 173.403(z).

STABLE AND UNSTABLE WASTE FORMS: Shall be defined as stated in 10CFRPart 61 and other supporting regulatory documents.

TEST SOLIDIFICATION:

The mixing of waste(s)and solidification agents in the laboratory to support selection of mixing ratios and, provide insurance for final product acceptability.

TRANSPORT INDEX (TI): The dimensionless number placed on the label of a package to designate the degree of control to be exercised by the carrier during transportation.

The transport index will be determined in accordance with 49 CFR 173.403(bb).

TYPE"A" PACKAGING:

Packaging which is designed in accordance with the general packaging, requirements of 49 CFR 173.24, ahd which is adequate to prevent the loss or dispersal of the radioactive contents, and to retain the efficiency of its radiation shielding properties if the package is subjected to the test described in 49 CFR 173.'465 or 173.466, as appropriate.

(49 CFR 173.403[gg])

TYPE"A" QUANTITY RADIOACTIVE MATERIAL: That material which may be transported in Type"A" packaging.

(49CFR 173.431[a])

TYPE"B" PACKAGING:

Packaging which meets the standards for Type"A" Packaging, and in addition, meets the standards for the hypothetical accident conditions set forth in 10CFR71.(49 CFR 173.403[hh])

5.45'YPE"B" QUANTITY RADIOACTIVE MATERIAL: That material which may be transported in Type"B" packaging.

(49CFR 173.431[b])

5.46 5.47 WASTE STREAM: A by-product of a process system or component with unique characteristics and maintained separate from other waste streams.WASTE TYPE: Specific contents of a liner or tank which may contain one or multiple waste streams, the category of waste suitable for a particular means of processing"..

'I I NDAP-QA-0646 Revision 4 Page 20 of 63 5.48 WASTE PRE-CONDITIONING:

The physical or chemical adjustment of the waste to bring it within an established envelope to assure solidification.

6.0 PROCEDURE 6.1 CONTRACTED VENDOR SERVICES 6.1.1 6.1.2 6.1.3 6.1.4 F 1.5 6.1.6 Solidified radwaste processing services are provided by Vectra, Inc.for waste types included in this Process Control Program.NRC approved Topical Report TP-'02-P-A, describes, Vectra Inc.waste processing equipment, methods and verification of acceptable waste forms for dewatering.

Vectra Inc.Solidification Process Control Procedure PT-51-WS, describes waste processing equipment, methods and verification of acceptable waste forms for solidification.

This procedure does not provide stability per the Branch Technical Position on Waste Form, Rev.l.Volume reduction services are provided by Scientific Ecology Group (SEG)for waste types included in the Process Control Program.NRC approved Topical Report STD-P-05-011-P-A, aescr>bes Scientific Ecoplogy Group (SEG)waste processing equipment, methods and verification of acceptable was'te forms for dewatering and solidification.

Selected solidified waste forms have been approved to provide stability per the Branch Technical Position on Waste Form, Rev..1.Other contracted vendor services which are required.for solidification, dewatering and volume reduction services shall be evaluated to the requirements stated in this Process Control Program on a case by case basis.

NDAP-gA-0646 Revision 4 Page 21 of 63 6.2 WASTE TYPES The following waste types shall be processed in accordance with this procedure or in combinations as defined.The waste should be dewatered whenever possible to minimize disposal volume.6.2.1 Evaporator Concentrates a~The following are concentrated with the Radw'aste Evaporators and are considered Evaporator Concentrates waste stream: (1)Condensate Demineralizer regeneration effluent b.C.d.(2)Decon Shop drains (3)Chemistry Laboratory sink drains (4)Auxil'iary Boiler blowdown effluent The constituents of this waste stream.may include the following:

(1)Tri-Sodium Phosphate (2)Sodium Sulfate (3)Phosphoric Acid (4)Sul furic Acid (5)Sodium Hydroxide (6)Decontamination solutions (?)Negligible amounts of reagent chemicals used for chemistry.analysis Evaporator Concentrates in the range of 0-24 weight percent sodium sulfate (equivalent) shall be solidified for final disposal.Evaporator Concentrates shall not be mixed with any other waste type in final processing.

NDAP-gA-0646 Revision 4 Page 22 of 63 Hixed Solids a.The following process waste streams are collected either in Waste Hix Tanks, Waste Sludge Phase Separator or transferred directly to a liner/High Integrity Container and are considered Hixed Solids: b.(1)LRW Filter Hedia.and drain liquid (2)Sump Sludge (3)Ultrasonic Resin Cleaner Waste'(URC Waste)The constituents of these waste streams may include the following:

(1)Diatomaceous Earth (2)Powdered Resins (3)Fibrous material (4)Carbon material.(5).Corrosion products (6)Various solids and dirt in small concentrations c~Hixed Solids may be solidified or dewatered for final.disposal.d.Each waste stream should be processed separately.

RWCU Filter Hedia a.The Reactor Water Cleanup System and Fuel Pool Cooling and Cleanup System filter/deminer alizer waste are collected in the RWCU Phase Separator and should be allowed to decay for 60 days.This waste stream is considered RWCU.Filter Media.'.Th constituents of this waste stream may include anion and cation powdered resin, corrosion and contaminants removed from the primary coolant.

4 0 1 ft NDAP-gA-0646 Revision 4 Page 23 of 63 C.RWCU Filter Media shall be dewatered in High Integrity Containers.

If this waste must be solidified, Technical Specification 3/4.11.3 action statement must be performed.

Condensate/Radwaste/Atmospheric Demineralizer Bead Resin a~Resins from the Condensate Demineralizers, Liquid Radwaste Oemineralizer and vendor provided demineralization are collected in the Spent Resin Tank or transferred directly to a liner/High Integrity Container.

Thi's is considered to be Condensate/Radwaste/Atmospheric Demineralizer Bead Resin.b.C.The constituents of this waste stream may include various types of anion, cation, mixed bead resin and corrosion and contaminates removed from liquid waste streams.Bead Resin may be used to demineralize Liquid Waste in either steel.liners or High Integrity Containers.

d.e.Condensate Demineralizer bead resin should be ultrasonically cleaned prior to collection in the Spent Resin Tank.Bead Resin may be solidified or dewatered for final disposal.Bead Resin may also be processed by volume reduction methods which include drying, incineration, compaction, use as fill materials or other evaluated method(s)on a case by case basis.Cartridge Filters Cartridge Filter waste type consists of the following waste streams and constituents: (I)CRD Filters-CRD or other filters and small un-irradiated primary system equipment such as valves, CRD lift pump filters, Rinse Tank filters and other metal components.

NDAP-gA-0646 Revision 4 Page 24 of 63 b.(2)RWCU Septa-Septa from RWCU Filter Demineralizer including septa from Fuel Pool Cleanup Filter Demineralizer.

(3)Radwaste Filters-including degasifier filters and other fiber or paper filter s other than primary system.(4)Underwater Vacuum Filters-non-process'ilters generated from wet cleaning activities.

Cartridge Filters may be processed by the following methods: 1 (I)Emplacement in a cement matrix in a steel.drum/liner or in a High Integrity Container.

C.d.(2)Dried to a point where no free liquid is visible.Absorbent material may be included to absorb unintentional and incidental amounts of liquids.(3)Dewatered if drying is impractical.

(4)Incineration or other volume reduction methods.Cartridge Filters to be solidified for final disposal shall not be mixed with any other waste type.Each cartridge filter waste stream should be packaged separately unless analyzed prior to packaging in accordance with the requirements of.this procedure.

Irradiated Hardware'a~Irradiated hardware is neutron activated metal removed from the internal area of the reactor pressure vessel.This waste stream is considered Irradiated Hardware.

'I NDAP-gA"0646 Revision 4 Page 25 of 63 b.The constituents of this waste stream may include control rod blades, LPRHS's, IRH's,'IP's and components expended during hardware processing and packag'ing acti.vities.

Startup sources may also be processed as part of this'aste stream.c.Irradiated hardware is packaged in steel liners for disposal.d.Liquid shall be drained to ensure free liquid Acceptance Criteria are met.e.Irradiated hardware shall not be mixed with any other waste type in final processing.

Dry Active Waste (DAM)a.Dry Active Waste is a waste stream.b.The constituents of this waste stream consist of contaminated paper, plastic, wood, metal and other discarded material.C.Dry Active Waste shall be processed by volume reduction methods which may include incineration, compaction, decontamination and metal melting.d.At a minimum, DAW shall be packaged in strong-tight containers for disposal.Liquid Oil Waste or Petroleum Based Haterials.a.b.The constituents of this waste stream may include turbine lubricating oil, EHC fluid and other petroleum based materials.

Contaminated Liquid Oil Waste generated at the facility should be processed by a decontamination system, solidified for final disposal, volume reduced by incineration, or other acceptable methods.

e NDAP-gA-0646 Revision 4 Page 26 of 63 C.Liquid Oil Waste at concentrations IX and greater may be solidified provided the following are adhered to: (I)An emulsification agerit is added at required concentrations.

(2)The Liner is NOT SHIPPED to a.disposal

.facility without prior disposal facility approval.Solid Sealed Sources a.Solid Sealed Sources requiring disposal shall be.packaged for disposal as requested by Health Physics Supervision.

b.Method of disposal is dependent on waste class of the Solid Sealed Source and disposal facility requirements.

c.Acceptable methods of disposal include:~(I)Placement within a container consisting of another waste type provided: (a)The source contains isotopics already in the waste.(b)The source activity is significantly

~less than the waste activity..(2)Class B and C sources shall be stabilized within an approved solidification or encapsulation media.Activated Carbon a 0 b.Activated Carbon from vendor provided liquid waste demineralization is transferred directly to a liner/High Integrity Container.

This waste stream is considered Activated-Carbon.The constituents of this waste stream may include various types of charcoal, ion specific carbon filter media and corrosion and contaminants from liquid waste streams.

4tV NDAP-gA-0646 Revision 4 Page 27 of 63 C.Activated Carbon may be solidified, dewatered or processed by volume reduction methods which include drying, incineration, compaction, use as fill-materials or other evaluated methods, on a case by case basis.6.2.11 6.2.12 6.2.13 A Waste Type that is combined with a known amount.of hazardous waste or"Hixed Waste" shall be processed for final disposal pending approval obtained from the processing and disposal facilities, Environmental Protection Agency, U.S.Nuclear Regulatory Commission and other regulatory agencies as required.Waste types containing chelating agents within the range of O.l to 8.0 percent by weight shall be processed to a stable waste form in accordance with and authorized by disposal facility requirements and appr oval s.Various other materials not specifically identified as waste types will be evaluated for solidification, dewatering volume reduction or other processing on a case by case basis.6.3 RADIOACTIVE WASTE ANALYSIS AND CLASSIFICATION 6.3.1 6.3.2 Radionuclide concentrations of radioactive waste are used to classify waste for shipping and disposal.Radionuclide concentrations should be determined based upon isotopic analysis, volume and weight of final waste form.The 10CFR61 Compliance Program establ.ishes a methodology for characterizing radioactive waste through the use of correlation factors.This program shall require as a minimum that: a.Samples representative of Susquehanna's waste streams are collected and analyzed such that results are obtained from a designated laboratory at least every two years (Class A)for development of specific correlation factors.Waste streams known or suspected to be classified Class 8 or Class C should be analyzed on an annual basis.

1'I NDAP-OA-0646 Revision 4 Page 28 of 63 Technical basis documentation and justification of correlation factors are developed for each waste stream and'are acceptable for use.Periodic evaluations and necessary adjustments to established ratios are performed in a timely manner.C.Co'rrelation factors are re-evaluated following significant changes (greater than a factor of'0)in plant operations (such as significant changes in fuel leakage, radwaste operations, or equipment).

Determination of waste classification shall be in accordance with 10CFR61.55, Waste Classification, and its supplementary Branch Technical Position on Radioactive Waste Classification as follows:*.b.C.Class A-Usually segregated from other waste classes at the disposal facility.Physical form and characteristics shall meet the minimum requirements specified in 10CFR61.56(a):

If.the stability requirements in 10CFR61.56(b) are met, the waste does.not have to be segregated for disposal.Class B-Physical form and characteristics

.shall meet both the minimum and stability requirements specified in 10CFR61.56.

Class C-Physical form and characteristics shall meet both the minimum and stability~requirements specified in 10CFR61.56.

In addition, measures shall be taken at the disposal facility to protect against inadvertent intrusion.

Isotopic analysis may be performed by: Gamma spectrometry of a sample and use of correlation factors.b.Direct gamma spectrometry of waste and use of correlation factors.C.d.Complete radionuclide analysis of waste sample.Dose to Curie calculations.

0 NDAP-gA-0646 Revision 4 Page 29 of 63 e.Activation analysis.Volume and weight of final waste may be determined by: t a.Calculation using analytically derived sample densities..

b.Calculation using standard waste densities.

c.Direct measurement of volume and weight.d.Acceptable methods described in the Technical Position on Concentration Averaging'and Encapsulation.

If samples.of waste are used for classification, sampling program shall include: a.Samples shall be obtained and analyzed for each batch of.wet waste if practical and ALARA.b.Preferentially, samples should be taken for analysis following processing into a final'aste form.c.Samples taken prior to final processing should enable results of sample analysis to be directly translated to final waste form.d.Head resin and Activated Carbon used for chemical demineralization shall be sampled after having'has been depleted in process.e.Solidification/Dewatering Services Vendor or another qualified individual shall obtain required.samples.Preparation of waste for sampling or analysis a~b.Wet Waste Collection tanks shall be recirculat'ed in accordance with approved operating procedures'rior to sampling or analysis.Waste processing in solidification liners/High Integrity Containers shall be mixed in accordance with approved procedures prior to sampling or analysis.

6.3.8'.3.9-NDAP-gA-0646 Revision 4 Page 30 of 63 c.Wet waste to be processed may also be mixed, recirculated and sampled or analyzed from mobile processing equipment.

Final waste form containing a mixture of waste types or streams shall be individually.

analyzed to determine radionuclide concentrations.

The summation of each individual radionuclide concentration shall be used to characterize the final waste form for shipping and: disposal.Waste types or streams of different waste classes (estimated by historical precedent or projected analysis)shall not be mixed.E Deviations from sampling and analysis requirements shall be approved by Chemistry Supervisor and Effluents Management Supervision.

Solidified waste shall be tested and/or treated to ensure it is not capable of generating quantities of'lammable or toxic gases, vapors or fumes which'ay be harmful to persons transporting, handling, storing or disposing of the waste.6.4.1 6.5 RADIOACTIVE WASTE SOLIDIFICATION

()6.4 TESTING/TREATMENT

'OF SOLIDIFIED RADWASTE FOR COMBUSTIBLE'GASES

(')6.5.1 General Requirements a 0 b.C.d.Wet Waste Types which may be solidified in High Integrity Containers are Evaporator Concentrates., Mixed Solids, Condensate/Radwaste.

Demineralizer Bead Resin, RWCU Filter Media and Liquid Oil Waste or Petroleum Based Material, Cartridge Filters, Solid Sealed Sources and Activated Carbon.High Integrity Contasners shall be used to meet the stability crite.'.in accordance with federal and disposal facility regulations.

Solidification processing shall be conducted by qualified SSES or Solidification/Dewatering/

Services Vendor personnel.

The solidification process shall be operated in accordance with approved procedures.

Procedures shall spec'ify waste stream, amounts of solidification agent and additives or method for determination.

NDAP-gA-0646 Revision 4 Page 31 of 63 Waste Preconditioning a.Waste preconditioning requirements shall be determined by chemistry analysis.b.C.Preconditioning of waste shall be performed if required prior to determining mixing ratios.Waste preconditioning is required when any of the following conditions exist: (1)A high or low pH condition, as determined by chemical analysis;(2)Liquid content of the batch is out of the acceptable envelope for solidification.

.(3)Solids content of the batch is out of the acceptable envelope for solidification.

(4)Known potential problem chemicals and constituents within waste that may adversely affect setting and stability of cement-solidified waste form.d.e.Waste preconditioning shall be performed in accordance with approved procedures to ensure waste is within the acceptable envelope for solidification.

Upon completion of waste preconditioning, additional samples, as required, shall be obtained in accordance with Radioactive Waste Analysis and Classification section of this procedure.

Determination of Hixing Ratios a~b.c Determination of mixing ratios.shall be performed for each waste batch to be processed.

Deviation from the recommended mixing ratios shall be reviewed by Plant Operations Review Committee (PORC).Chemistry Group determines:

(1)Density of the waste samples.

NDAP-gA-0646 Revision 4 Page 32 of 63 d.e.(2)Specific gravity of Sodium Sulfate Solution in Evaporator Concentrates.

Solidification/Oewatering/Services Vendor determines if the final mixing ratios are within the acceptable envelope for solidification.

For solidification performed on site: (1)Chemistry Group shall perform test solidification of waste as required by Test Solidification section of this procedure.

(2).Chemistry Group determines mixing ratios to ensure proper solidification.

For solidification performed offsite: (1)Solidification/Dewatering/Services Vendor , shall perform test solidification of waste as required by Test Solidification section of this procedure.

(2)Solidification/Oewatering/Services Vendor determines mixing ratios to ensure proper solidification.

Test Solidification

'a~Test solidification shall be performed to support.waste mixing ratios as follows: '(1)At least every tenth (10th)batch of the same waste stream.(2)When sample analysis fall outside the established range and criteria indicating a change in waste characteristics.

(3)When it is beli'eved that some unexpected or abnormal contaminant may be present.(4)When requested by Radwaste Supervisor.

NDAP-gA-0646 Revision 4 Page 33 of 63 (5)Hixing of materials shall be accomplished in a manner that duplicates, to the extent practical, mixing conditions that are obtained with full-scale mixing in container.

(6)Curing shall be performed under conditions similar to those used in laboratory qualification test program.Upon failure of a test solidification, an LCO is entered,'dditional samples shall be obtained, alternative solidification parameters are determined and a subsequent test verifies solidification.

Test solidification shall be performed on each subsequent batch of the same waste stream until at least three (3)consecutive initial test solidification

'emonstrate acceptability in accordance with Technical Specification 3/4.11.3.guality Control shall verify test solidification acceptability and indicate the acceptability on the surveillance documentation.

The acceptability requirements are defined in the PCP Surveillance Specimen section of this procedure.

Extra sample volume for backup testing shall be disposed of after acceptable container checks are completed.

.High Integrity Container test solidification billets should be disposed after acceptable container checks are completed.

Test solidification should be performed with samples from waste obtained as follows: (1)In accordance with Radioactive Maste Analysis and Classification section of this procedure.

(2)Sampling of the solids in the container and the liquids used for.hydration, then mixed to the ratios that exist in the container.

A'I I' NDAP-gA-0646 Revision 4 Page 34 of 63 f.g.Test Solidification Procedures shall be developed for each specific waste type as required.h.Cement, water'ype and additives to be used in actual solidification.

shall be used in , preparation of test solidification.

PCP Surveillance Specimens a.High Integrity Container test solidification billets shall be examined and tested for acceptability after the specified cure time'for: (1)Liquid on surface of solidified product less that 1.0X by waste volume.(2)Visible defects, such as cracking, spalling, or disintegration.

(3).Strength by physically poking the surface of solidified product with a rigid'nyielding device.Nominal surface denting is acceptable.

b.If cement sol'idification in steel liners is NRC approved to provide stability, PCP surveillance specimen examination testing and reporting is required in accordance with the Branch Technical Position on Waste Form, Rev.I.Curing Time.a.A minimum of 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> shall be allowed for curing prior to capping or transporting container.

b.The container may be moved during the first"hour after solidification but must remain undisturbed for the remaining 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br />.c., Deviations from minimum required curing time shall be approved by Radwaste Supervisor and justifications documented in remarks section of Solidification Record.

NOAP-gA-0646 Revision 4 Page 35 of 63 Solidification Product guality a~Solidification product quality is assured by use of predetermined mixing ratios of waste, cement and additive.Liquid to be used for solidification should be demineralized water.b.'re-qualification mixing ratios are based on laboratory testing using non-radioactive waste materials.

c.Hixing ratios are re-enforced by the following: (I)Test solidification performed periodically as stated in Test Solidification section of this procedure.

(2)Visually and physically checking at least every fifth (5th)container of the same waste type.d.Container checks shall consist of: (I)A visual check of solidified product for liquid on surface of product not to exceed.1.0X by waste volume.(2)Physically poking the surface of solidified product with a rigid unyielding device prior to capping (Nominal surface denting may occur and is acceptable).

e.guality Control shall verify acceptability of solidified product when containers are checked.I'.Oeviation from the container checking requirement, shall be approved by the Radwaste Supervisor.

Handling of Unacceptable Solidified Waste Containers.

a.b.If a solidified waste container does not meet acceptability requirements, a Condition Report (CR)shall be issued.If the reason for unacceptability is free liquid: (I}The free liquid wi11 be removed;or NDAP-gA-0646 Revision 4 Page 36 of 63 (2)Extra cement/additive will be added to solidify free liquid.If portions or all of the product did not solidify after three days: '(I)The waste container will be capped and placed in a storage location and periodically checked until such a time: product is acceptable; or (2)Additional solidification agents may be added to achieve satisfactory solidification, as determined by the Radwaste Supervisor.

If the product solidifies prematurely prior to completing the addition of required amount of cement-and additive, as calculated on the solidification calculation sheet for the specific procedure used, the following is required: (I)A test solidification shall be performed using the actual ratio of cement and waste in the container, provided sufficient

'sample volume remains to complete this item.(2)guality Control shall check the product for acceptability in accordance with Container Checks section of this procedure.

(3)" The container is considered to meet acceptable waste form criteria for shipping provided the subsequent test solidification and/or container checks are acceptable to-;ality Control and concurrence of the'Radwaste Supervisor is obtained.(4)The above apply only if the Effluents Management Supervisor determines that the product can be classified as"Class A Unstable" or is placed in a High Integrity Container or structure that provides stability in accordance with IOCFR61 and the disposal facility criteria.

t r NDAP-gA-0646 Revision 4 Page 37 of 63 e.If the product does not solidify properly in accordance with the specific solidification procedure, the following is required: (I)An evaluation of the liner shall be made by the following personnel: (a)Effluents Management Supervision (b)Solidification Vendor-Operations (c)Solidification Vendor-Engineering (2)Disposal facilities.shall be contacted and requirements for receipt of the liner in question shall be defined.(3)Alternative packaging/processing shall be evaluated.

(4)(5)Recommendations for final disposition shall be made to the Power Production Engineer-Effluents Management.

Final disposition shall be reviewed by Plant Operations Review Committee (PORC).(6)Records shall be kept and documentation supportive of final disposition attached to the solidification record package.(7)The liner may be shipped after g.C.review of documentation is complete and disposal facility concurrence is received in letter form.f.Specific instructions shall be established for handling unacceptable solidified waste container on a case by case basis.g.equality Control shall re-verify acceptability of solidified product by performance of Container Checks.Capping of Solidified Waste Containers a.The requirements of Solidification Product equality section of this procedure shall be met prior to capping the container.

4 l l I I 4*1 a NDAP-QA-0646 Revision 4 Page 38 of 63 b.If the container is not equipped with a passive vent and its contents are within the requirements of Low Specific Activity (LSA)ensure one of the following:

(1)lhe container should be snipped with>n (10)ten days after capping;or (2)If a container has been capped for longer than (10)days, it shall be opened, vented, and re-capped within (10)ten days of shipment.c.If the conta'incr exceeds the limits for Low Specific Activity and contains water and/or organic substances which could radiolytically generate combustible gases, determination must be made such that the following criteria are met over a period of time that is twice the expected shipment.time: (1)The hydrogen generated shall be l.imited to a molar quantity that would be no more than 5X by volume of the container gas void'1 (2)The container and shipping cask cavity shall be inerted with a diluent to assure that oxygen is limited to less.than 5X by volume in those portions of the package which could have hydrogen greater than 5X;Solidification Agent Control a.Portland Cement-ASTI C-150 Type I shall be used for the mobile solidification process.b.Other solidification agents may be used only after acceptable testing of the agent has been completed that demonstrates acceptable solidification and disposal facility approval has been obtained.

I t I NDAP-gA-0646 Revision 4 Page 39 of 63 C.Documented Certification is not required for materials received in bags provided material verification can be obtained as follows: (1)Cement is acceptable provided the bag conta>ning tne cement indicates that cement is Portland Type I.(2)Sodium Silicate is acceptable provided'the bag containing the additive indicates Anhydrous Sodium Netasilicate.

(3)Other additives are acceptable provided the container is clearly marked indicating the type of additive.de Other additives may be used for enhancement of solidification process as specified in the solidification procedure and documented in'he solidification records.Radioactive Waste Solidification Records A Solidification Record Sheet (Form NDAP-gA-0646-1) shall be completed for each container filled with solidification products.Completion of the Solidification Record Sheet and the.required accompanying documentation shall be as.follows: a.The Radwaste Supervisor is responsible for initiating this form and completing Parts 1 and 2.b.Effluents Management Supervision,.Chemistry and Solidification/Dewatering/Services Vendor personnel shall provide and check off the required documentation specified in Part 3.equality Control shall provide review as required for the Solidification Records.

NDAP-gA-0646 Revision 4 Page 40 of 63 6.6 RADIOACTIVE WASTE DEWATERING 6.6.1 General Requirements a~b.c~d.e.Waste Streams which may be dewatered in either.High Integrity Containers or steel liners are , LRW Filter Media, Ultrasonic Resin Cleaner Waste, Sump Sludge, RWCU Filter Media, Condensate/Radwaste Demineralizer Bead Resin,.Cartridge Filters and Activated Carbon.The type of container used shall be based on the waste classification and stability criteria in accordance with federal and disposal facility regulations.

Dewatering of Radioactive Waste shall be performed by qualified SSES or Solidification/

Dewatering Services Vendor personnel.

Dewatering of Radioactive Waste shall be: performed in accordance with approved procedures.

Dewatering procedures shall be based on documented test data that has demonstrated the ability to achieve free liquid limits as specified by disposal facilities and applicable regulatory agencies.Liquid volume and drainage calculations and actual drainage verification may also be used to meet free liquid limits.High Integrity Containers shall be used for disposal when the concentration of radionuclides with half-lives greater than 5 years exceeds 1 pCi/cc.Each waste stream which may be dewatered should be characterized by the Solidification/

Dewatering Services Vendor to ensure the, operating parameters and effectiveness of the dewatering system are in accordance with the parameters established in the Topical Report.

0 NDAP-gA-0646 Revision 4 Page 41 of 63 Dewatered Product Control a.The final dewatered product shall contain less than IX non-corrosive free liquid for High Inteoritv Containers and 0.5X for steel ljners.equality Control checks shall be performed on process steps.b.If a dewatered waste container does'ot meet: acceptability requirements, a Condition Report (CR)shall be issued.c.Specific instructions shall be established for handling unacceptable dewatered waste container on a case-by-case basis.d.Deviation from the container checking requirement shall be approved by the Power Production Engineer-Effluents Hanagement.

Radioactive Waste Dewatering Records A Dewatering Record Sheet (Form NDAP-gA-0646-2) shall be completed for each container filled with dewatered waste streams.Parts of the form shall be completed by the following responsible individuals or groups: a.The Radwaste Supervisor is responsible for initiating this form and completing Parts I and 2.b.Chemistry Group shall complete Part 3 Sampling and Analysis.c.Effluents Management Supervision, Chemistry and Solidification/Dewatering/Services Vendor personnel shall provide and check off the required documentation specified in Part 4..d.guality Control shall provide review as required for the Dewatering Records.

NDAP-gA-0646 Revision 4 Page 42 of 63 6.7 HIGH INTEGRITY CONTAINERS (HIC)6.7.1 Storage of High Integrity Containers a~Vectra, Radlok and CNSI High Integrity containers

~niC)stored ln u)rect sulli i/Ill.vl ln areas where there is a strong source of ultraviolet radiation shall be filled and disposed of within one year of manufacturing

date.6.7.2 b.C.Uses a 0 Once filled a High Integrity Container.may be stored for a period until a total of.one (1)year of ultraviolet radiation is received.Short exposures (i.e., several hours)to sunlight, such as occurring during shipment and on site transfer need not be counted when determining total ultraviolet exposure.t of High Integrity Containers High Integrity Containers may be used to package the following waste materials for disposal: (1)Dewatered bead resin, powdered resin and'diatomaceous earth.(2)Compressible and non-compressible solid wastes.(3)Filter elements and cartridges.

(4)Solidified resins, sludges, and liquid wastes.(5)Incinerator ash, residuals, or equivalent waste.which has been rendered non-dispensable i-'inding matrix..(6)Other dewatered and dry material provided concurrence is received by container vendor and disposal facility.

NDAP-gA-0646 Revision 4 Page 43 of 63 Prior to using a High Integrity Container for a specific waste material, procedures shall be established to define the specific requirement that shall be met during use of the container.

The procedures shall contain: Documentation requirements that specific conditions have been met such as inspection and exposure to degrading conditions.

Instructions as to how to handle and properly close the container.

Instructions for on-site storage of loaded containers for ultimate shipment for disposal.The procedures shall provide a method for documenting required information relevant to the container from initial receipt to shipping for disposal.Required information shall be based upon the container certificate of compliance and disposal facility requirements.

Retention and utilization of the documentation shall be defined in the procedures.

The procedures shall establish specific guality Control inspection requirements.

Prior to the first shipment of a specific type of High Integrity Container, authorization shall be requested from the applicable regulatory.

agency governing use of the container in question at the disposal facility of concer'n.

NDAP-(}A-0646 Revision 4 Page 44 of 63 High Integrity Container Limitations High Integrity Containers are approved for use provided the following physical limitations of the waste are met: (1)Vectra Payload density (2)Loading temperature

<1 47'ms/cc<170'F (3)Vectra EL-50 N.S..loaded weight:<4200 lb (4)Vectra EL-142 N.S.loaded weight: g8250 lb (5)Vectra EL-142 S.loaded weight: 611250 lb (6)Vectra EL-190 N.S.loaded weight:<11950 lb (7)Vectra EL-190 S..loaded weight:<14800 lb (8).Vectra EL-210 N.S.loaded weight:.<13000 lb (9)Vectra EL-210 S loaded weight:<17300 lb (10)CNSI Small loaded weight<2500 lb (11)CNSI Hedium loaded weight<2500.lb (12)CNSI Large loaded weight<2500 lb (13)Radlok 179 loaded weight<18500 lb (14)Radlok 195 loaded weight (15)Enduropak 105 loaded weight (16)Enduropak 205 loaded weight (17)Enduropak 150 loaded weight<18500 lb<1700 lb ,<1900 lb 52400 lb b.The maximum concentration of radionuclides with half lives greater than (5)fi.ve years that may be disposed of in a High Integrity Container is 350 pCi/cc.Other waste forms shall not exceed 1.0 X 10 rads maximum integrated dose to the container.

NDAP-gA-0646 Revision 4 Page 45 of 63 c.The polyethylene High Integrity Containers shall.not come into contact with materials listed in Attachment E.d.A passive vent design shall be incorporated into the container to relieve internal container-pressure.Closure of, High Integrity Containers Closure of High Integrity Containers shall be completed in accordance with approved procedures.

b.C.d.If the container is not equipped with a passive vent and its contents are within the limits of Low Specific Activity ensure one of the following:

(1)The container is shipped within (10)ten days after closing;or (2)If the container has been closed for longer than (10)ten days, it shall be opened, vented, and re-closed within ten (10)days of shipment.If the container exceeds the limits for Low Specific Activity or contains water and/or'rganic substances which could radiolytically generate combustible gases, determination must be ma'de such that the following criteria are met over a period of time that is twice the expected shipment time: (1)The hydrogen generated shall be limited to a molar quantity that would be no more than 5X by volume of the container gas void;ol (2)The container and shipping cask cavity shall be inerted with a diluent to assure that oxygen is limited to<5X by volume in those portions of the package which could have hydrogen greater than 5X.Step 6.7.4.b and 6.7.4.c shall also apply to dewatered waste in steel liners.

NDAP-gA-0646 Revision 4 Page 46 of 63 6.8 IRRADIATED HARDMARE PROCESSING AND DEMATERING 6.8.1 General Requirements a.Processing

'and dewatering of Irradiated

'Hardware~shall be.performed by.qualified SSES or vendor='ersonnel.

b.Processing and dewatering of Irradiated Hardware shall be performed in accordance with approved procedures..

C.d.agenci es.6.8.2.Dewatered Product'.Control Irradiated Hardware consisting of non-fuel Special Nuclear Haterial shall be inventoried during processing in accordance with NDAP-(A-0337.

Dewatering procedures shall be based on liquid volume and drainage calculations and actual drainage verificatiom to demonstrate the.ability.to achieve free liquid limits as specified by disposal facilities and'applicable reg'ulatory 6.8.3 a.The'final dewatered product sha11 contain less than 0.5X free liquid for steel liners.b.guality Control checks shall be performed on process steps.Irradiated Hardware Processing and Dewatering Records a.All records generated shall be completed and filed in accordance with approved implementing procedures.

6.9 CONTAINER INSPECTIONS 6.9..1 guality Control shall inspect containers to be used for solidification, dewatering, and other packaging for disposal.6.9.2'his inspection shall assure that prior to use, the containers to be used for solidification, dewatering, or other packaging are intact and their internals are free of any visual damage that would prevent them from performing their intended function.

NOAP-QA-0646 Revision 4 Page 47 of 63 6.9:3.Packages shall meet the general criteria for normal transport conditions in accordance with the requirements of 49'CFR.Type A packages shall meet the additional design requirements specified in 49 CFR.6.10 WASTE CONTAINER SPACE UTILIZATION 6.10.1 Waste volume shall be maximized within.the guidelines of specific procedures to minimize.'.potential void space at the top of waste container.

after solid)ication or dewatering,'is complete.P a.Additional radioactive material should be'dded only after the initial waste volume is in final form and sampled and the added waste volume is in final form and sampled.b.The additional material may be drawn into containers able to withstand higher external pressures without degredation by creating an area of low pressure inside the container, such-as with steel liners.6.10.2 6.10.3 6.10.4 6.11 STORAGE OF c.For all other containers, the additional

~material.'shall be added via mechani'cal processes.or'by other conveyance which does not exert higher external pressures.

• -': Waste volumes.shall meet or exceed disposal site criteria, If waste volume is less than"disposal

'acility criteria;requirement's for disposal of the cohtainer in question shall be defined by the disposal facility.Spec'ific waste volumes committed to by the, Solidification/Dewatering/Services Vendor shall be met or otherwise justified as to why waste volumes were not achieved.Susquehanna Guaranteed Solidified/Dewatered Waste Volume Record, Form NDAP-gA-0646-3, shall'e completed by the Solidification/Dewatering/

Services vendor personnel, approved by Radwaste Supervisor and shall be used to track.solidified/dewatered waste volumes achieved in each individual container.

PACKAGED RADIOACTIVE WASTE 6.11.1 6.11.2 Radwaste Supervisor shall provide Solidification and/or Dewatering Record sheets that have been reviewed by guality Control personnel stating that processed waste has been solidified or de-watered in accordance with the Process Control Program and meets~the applicable shipping and disposal criteria.Solidification and Dewatering Records shall include the isotopic mix,'isotopic concentration of the waste that was packaged, the total volume of the waste, and the amount of water, cement or other solidification agent used, as appropriate.

NDAP-gA-0646 Revision 4 Page 48 of 63 6.11.3 6.11.4 6.11.5 6.11.6 Solidification and Dewaterino Records shall be part of the permanent shipping records and adhere to requirements of the Process Control Program.For materials packaged in a high integrity container, documentation shall be maintained on HIC storage and pre-shipment checklist info'rmation.

Packaged radioactive waste shall be stored in areas".designated by HP Foreman Effluents Management.

Storage of packaged radioactive waste in the Low Level Radwaste Holding'acility (LLRWHF)shal,l be in accordance with approved procedures.

An inventory of stored, packaged waste shall.be maintained in accordance with approved procedures.

6.12 TRANSPORTATION, SHIPPING AND DISPOSAL REGULATIONS 6.12.1 Specific regulatory documents shall be maintained on site in a status that is current.Specific regulations that shall be maintained include but are not limited to the following:

a~10CFR71 Packaging of Radioactive Material for transport'nd transportation of radioactive material under certain conditions.

b.C.d.e.49CFR100-199 Transportation.

Chem-Nuclear Systems Inc.Barnwell S.C.disposal site operating license number 097 State of South Carolina, as required.Chem-Nuclear System Inc.NRC Material.License 12-13536-01, as required.Chem-Nuclear System Inc.Barnwell S.C.disposal site operating proc>".res and site criteria, as required.Scientific Ecology Group Licenses R-73008-E94, R-01052-A91.

g.Cask Manuals for casks of which PP&L is an authorized user.h.A copy of the license for each facility to which Radioactive Material is sent.

'(

NDAP-gA-0646 Revision 4 Page 49 of 63 i.10CFR61 Licensing requirements for land disposal of Radioactive Waste.6.12.2 Procedures applicable to transportation, shipping and disposal shall'be developed.

'a~Procedures shall be established and maintained to provide directions and assure regulatory compliance for manifesting, which include applicable federal, state, and disposal facility regulations, and NRC guidance.b.Procedures shall contain check off lists where and when applicable to assure specific attention is paid to the critical function being controlled.

6.12.3-c.Procedures shall contain guality Control notifications or hold points.Computer software used to implement applicable portions of the Process Control Program shall be in accordance with NDAP-(A-0801.

6.13 SHIPPING OF RADIOACTIVE WASTE 6.13.1 6.13.2 6.13.3 6.13.4 All radioactive'aste shall be shipped by Effluents Management.

All radioactive waste shipped from SSES shall only be to facilities licensed to receive the waste and in accordance with 10CFR20, 10CFR71 and 49CFR100-199.

Dry Active Waste (DAW)" should normally be shipped as Type A quantities and therefore do not require specific licensed containers.

Waste containers shall be placed in a USNRC approved licensed shipping container if it: 'a~b.C.Exceeds Type A quantities Exceeds 1000 mr/hr on contact Exceeds 1000 dpm/100 cm loose surface contamination on the exterior of the container.

NDAP-gA-0646 Revision 4 Page 50 of 63 The specific conditions of the Certificate of Compliance for each approved shipping cask shall be strictly adhered to.Packaged waste;may be shipped unshielded if: a.Contact dose rates are less than 200 mrem/hr and dose rates at 6 feet are less than 10mrem/hr.

b.Curie content of the package shall be a Type A quantity.c.Container shall be a minimum of a strong tight container.

Prior to the shipment of a package of radioactive waste, the HP Foreman Effluents Nanagement shall assure the container is surveyed for contact dose rates and surface contamination.

Decontamination, if required, shall be done under the direction of the HP Foreman Effluents Management.

Decontamination may be waived based upon radiological conditions.

All vehicles used to transport radioactive waste requiring the vehicle to be placarded shall be checked for adequate operation and safety conditions.

All Radwaste shipments from SSES shall normally be via"Exclusive Use" vehicles.Specific instructions given to the driver include: a.Expected route of travel to his final destination.

b.Maintaining"Exclusive Use" status.c.Specific actions to be taken in the event.of an accident.No vehicle carrying radioactive waste that is overweight shall leave SSES without a Pennsylvania overweight permit.a.A DAM shipment or other shipment capable of having its weight adjusted, shall not be allowed to leave SSES overloaded.

An overloaded condition for any vehicle is based on total weight and weight per axle.

NOAH'-QA-0646 Revision 4 Page 51 of 63 6.13.11 In the event access is denied to SSES at all operating disposal facilities, PP8L will provide carrier with a letter stating that SSES will meet all applicable federal, state, and compact requirements for receipt back of the radioactive waste/material in carrier's possession.

6.14 SHIPMENT CONFIRMATION If disposal site shipment acknowledgement is not received within 18 days from departure from SSES, Effluents Management Supervision shall conduct a trace investigation for shipment location.If the disposal facility shipment receipt can not be confirmed within 20 days, a Condition Report (CR)shall be generated.

6.15 CHANGES TO THE SOLID RADIOACTIVE WASTE PROCESS CONTROL PROGRAM 6.15.1 Any changes as descr ibed in the Technical Specifications, to the Solid Radioactive Waste Process Control Program shall be provided in the Annual Radioactive Effluent Release Report filed with the NRC.6.15.2 Any changes to the Solid Radioactive Waste Process Control Program shall be approved by Plant Operations Review Committee (PORC)prior to implementation.

()6.16 EVALUATION OF PROCESS OR OPERATIONAL CHANGES 6.16.1 6.16.2 Changes in radioactive waste processing oe operational changes shall be evaluated to determine any impacts on waste characteristics and/or form.Evaluation should include as a minimum: a.Operational evaluation of processing impacts: b.C.Chemistry evaluation of changes to sampling and analysis methodology.

Effluents Management evaluation of packaging and/or shipping impacts.d." Effluents Management evaluation for lOCFR61 compliance.

NDAP-gA-0646 Revision 4 Page 52 of 63 e.Solidification/Dewatering Services Vendor waste stream characteristic evaluation of the dewatering/solidification system operating parameters and effectiveness.

()6.17 REPORTING OF MISHAPS INVOLVING LOW LEVEL WASTE FORMS 6.17.1 IOCFR61 establishes the minimum and stability requirements for Low Level Waste (LLW)forms.10CFR20 requires certification that the processed waste satisfies the requirements of 10CFR61.Mishaps which may impact the final waste form shall be reported to'the NRC.6.17.2 Types of mishaps which should be reported include: a.b.C.Failure of high-integrity containers used to ensure a stable waste form.Container'failure can'e evidenced by changed container dimensions, cracking, or damage resulting from mishandling (e.g., dropping or impacting against another object).Mi s use of hi gh-integri ty containers, evi denced by a quantity of free liquid greater than 1 percent of container volume, or by an excessive (>l5X)void space within the container.

Production of a cement solidified Class B or C waste form that has any of the following characteristics:

(1)Contains free liquid in quantities exceeding 0.5 percent of the volume of the waste.(2)Contains waste with radionuclides in concentrations exceeding those considered during waste form qualification testing accepted by the regulatory agency, which could lead to errors in assessment of waste class.(3)Contains a significantly different waste loading than that used in qualification testing accepted by the regulatory agency.

.NDAP-gA-0646 Revision 4 Page 53 of 63 (4)Contains chemical ingredients not present in qualification testing accepted by the regulatory agency, and those quantities are sufficient to unacceptably degrade the waste product.(5)Shows instability evidenced by crumbling, cracking, spalling, voids, softening, disintegration, non-homogeneity, or dimensional changes.(6)Evidence of processing phenomena that exceed the limiting processing conditions identified in applicable topical reports or process control plans, e.g., foaming, temperature extremes, premature'or slow hardening, and production of volatile material.6.17.3 d.Failure to adhere to high integrity container limitations as required by container certificate of compliance.

e.Notification of violation by disposal facility regulatory authorities at time of container receipt for disposal.f.Failure of cement-solidified stable waste form long term PCP surveillance specimens due to evidence of significant cracking, spalling, or bulk disintegration, compression or penetrometer strength and.immersion test results.Requirements for reporting of mishaps shall.apply only to processing l.iners and high integrity containers containing radioactive waste in its final product form.6.17.4 A Condition Report (CR)shall be generated if.one of the mishaps mentioned occurs'.18 PCP IMPLEMENTING PROCEDURES Procedures required for implementation of the Process Control Program are shown in Attachment D.

NDAP-gA-0646 Revision 4 Page 54 of 63 7.0 RECORDS 7.1 The Solidification Records or Dewatering Records and the attached documents shall be forwarded to Effluents Management'Supervision for retention until such time as the container identified on Record is shipped for final disposition.

7.2 When the identified container is shipped the Solidification Records or Dewatering Records and other documents concerning the, Shipment shall be filed with the shipping'ocumentation and forwarded to DCS for retention.

7.3 7.4 Documentation of Radioactive Waste Shipments shall be retained as required by SSES Technical Specifications.

Radioactive waste shipping documentation shall consist of, but not limited to, the following records:7.4.1 7.4.2 7.4.3 7.4.4 7.4.5 7.4.6 7.4.7 Radioactive Material Shipping Manifest Evaluation of isotopic mix and concentration Radiological surveys of: a.Vehicle upon arrival b.Package to be shipped c.Loaded vehicle prior to shipment Vehicle Safety inspection Check-off sheet for loading procedure Documentation of adherence to Process Control Program (i'f applicable)

Special instructions to driver

SOLIDIFICATION RECORD SHEET PART I: Container Identification Information Attachment A NDAP-gA-0646 Revision 4 Page 55 of 63 1.PPEL Liner Number 2.Container Vendor Serial Number 3.Waste Stream (RWCU Filter Media cannot be entered)4.Test Solidification required?YES NO (circle one)PART 2: Container Selection (Refer to WM-PS-100) 2.3.Estimated Liner Contact Dose Rates.mR/hr Projected Curie Concentration pCi/gm Expected Waste Classification/Stability 4.6.Container Type to be Used Expected Cask Type to be Used 5.Empty Weight of Container Tbs PART 3: I.2.Documentation Checklist Form NDAP-gA-0646-1 (original)

Waste Form Documentation WM-RP-Forms (original)

SC-068-002 Forms (copy)Waste Form: STABLE UNSTABL'E (circle one)>85%Liner Volume Utilized: YES NO (circle one)Waste Activity Documentation CH-RC-Forms (copy)Isotopic Analysis (copy)Compost added/Log entry made on CH-TP-055-1 PART 4: Health Physics Data Liner Radiological Survey (original)

Actual Filled Container Weight REMARKS: p.'ll lb.(If available ALARA)WA U O UKASE~EVTEtt DATE//FORM NDAP-OA-0646-1, Rev.2, Page 1 of 1 (File R69-I)

DEWATERING RECORD SHEET Attachment 8 NDAP-gA-0646 Revision 4 Page 56 of 63 PART 1: Container Identification Information 1.PPLL Liner Number 2.Container Vendor Serial.Number 3.Waste Stream PART 2: Container Selection (Refer to WW-PS-100) 2.3.Estimated Liner Contact Dose Rates Projected Curie Concentration Expected Waste Classification/Stability mR/hr pCi/gm 4.6.Liner Type to be Used Expected Cask Type to be Used 5.Empty Weight of Container lbs.a waste Superv>sor ate>me FORM NDAP-gA-0646-2, Rev.3, (DUPLEX), Page 1 of 3 (File R69-I)

PART 3: Sampling and Analysis Tank/Container sampled DEWATERING RECORD SHEET Attachment B NDAP-gA-0646 Revision 4 Page 57 of 63 2.3.Sample Number Waste Stream 1sotopic Analysis attached 5..Specific activity of Dewatered Sample 6.a.Dewatered Volume pCi/gm b.Dewatered Weight c.Sample density gm gm/cc x 62.43 lb/f t on CH-TP-055-1 7.Composite added/Log entry madeThe above tank/container containing solids has been analyzed in accordance with CH-RC-0?5 and found to contain the isotopes and specific activities as indicated on the attached data sheets.emistry uperv>sion ate lme FORM NDAP-gA-0646-2, Rev.3, (DUPLEX)Page'2 of 3 (File R69-1)

DEWATERING RECORD SHEET PART 4: Container Shipment Information Summary Attachment B NDAP-gA-0646 Revision 4'age 58 of 63 3.4.PP8L Liner Number Form NDAP-gA-0646-2 (original)

Waste Form Documentation 2..Waste Volume NN-RP-..., Forms (original)Calculated Waste Weight lb/ft x 1 Ta lb.Actual Filled Container Weight 100 x (Dewatered Waste Volume)lb.(if available ALARA)ft+ft X Tvai TTol ume>85%Container Volume Utilized YES/NO (Circle one), Waste Form: STABLE UNSTABLE Waste Activity Documentation J CN-RC-Forms (Copy)Isotopic Analysis (Copy)(Circle one)PART 5: REMARKS: a waste upv ate eview ()ate oreman.Ngmt.()ate FORM NDAP-(A-0646-2, Rev.3, (DUPLEX), Page 3 of 3 (File R69-1)

Attachment C NDAP-gA-0646 Revision 4 Page 59 of 63 SUS UEHANNA GUARANTEED SOLIOIFIEO OEWATEREO WASTE VOLUME RECORD 2.3.4.5.Date Waste Type Container Type Burial Volume Useable Container Volume Liner number 6.7.Guaranteed Hinimum Waste Volume Waste Volume Attained inches x ft>/inch ftS 8.Waste Volume'ontainer Usage 100 x (Waste Vol.ft>~Guaranteed Hin.Waste Vol.ft>)-100 Dead band Assessment Volume Guaranteed Hin.Waste Vol.ft+(0.01 X Guaranteed Hin.Waste Vol.ft Hinimum(-)

ft to Maximum(+)

ft 10.Performance Assessment Volume Dead band Assessment Vol.ft-Waste Vol.ft=ft ll..Remarks: 12.Signature So s s scat>on en or epresentative 13.Signature a waste upervisor FORM NOAP-gA-0646-3, Rev.2, Page 1 of 1 (File R69-1)

WASTE PROCESSING PCP IMPLEMENTING PROCEDURE MATRIX Attachment D NDAP-gA-0646 Revision 4 Page 60 of 63 Eva orator Concentrates

-Solidified Pacific Nuclear PT-51-WS Pacific Nuclear OM-114-NS Pacific Nuclear OH-104 Mixed Solids-Solidified Pacific Nuclear PT-51-WS Pacific Nuclear OM-104 Pacific Nuclear OH-114-NS LRW Filter Media URC Waste RWCU Filter Med'ia Sum Slud e-Dewatered'acific Nuclear OH-43-WS WM-RP-107 Condensate Radwaste Demineralizer Bead Resin-Solidified Pacific Nuclear PT-51-WS Pacific Nuclear ON-114 Pacific Nuclear OM-104 Condensate Radwaste Demineralizer Bead Resin-Dewatered Pacific Nuclear OM-43-WS WH-RP-106 Cartrid e Filters CNSI FO-OP-019 (Overpack)

WH-PS-230 Pacific Nuclear OH-16-NS WM-RP-105 II SEG STD-P-22-002 (Resin Express)'M-RP-104 SEG STD-P-03-051 WH-RP-108 Page 1 of 3 PCP IMPLEMENTING PROCEDURE MATRIX Attachment D NDAP-gA-0646 Revision 4 Page 61 of 63 Irradiated Hardware-Dewatered'teel Liner None Dr Active Waste DAW-Packa in WM-PS-210 Li uid Oil Waste-Solidified None Li uid Oil Waste-Decontamination None Solid Sealed Sources None WASTE ANALYSIS AND CLASSIFICATION

-10CFR61 Pacific Nuclear OM-45 NS WM-RP-008 CH-RC-075 CK-RC-076 CH-TP-OSS WM-PS-155 WM-PS-160 WM-PS-170 TESTING TREATMENT COMBUSTIBLE GASES WM-RP-009 WM-RP-301 RADIOACTIVE WASTE SOLIDIFICATION

-GENERAL CEHENT Pacific Nuclear.OM-114-NS SC-068-002 (Test Solidification)

Page 2 of 3 PCP IMPLEMENTING PROCEDURE MATRIX Attachment D NDAP-gA-0646 Revision 4 Page 62 of 63 RADIOACTIVE WASTE DEWATERING

-GENERAL Pacific Nuclear OH-60-WS WH-RP-010 HIGH INTEGRITY CONTAINERS Pacific Nuclear OH-16-NS Pacific Nuclear H-18-NS WH-RP-012 DISPOSAL FACILITY RE UIREHENTS WM-PS-180 PACKAGING WM-RP-011 WM-PS-401 (LLRWHF)WH-PS-310 WM-PS-311 WH-PS-315 WM-PS-345 WH-PS-351 WH-PS-352 WH-PS-356 (HN-142)(LN-142)(SEG 3-82)(CNSI 14-'195)(CNSI 21-300)(CNSI 8-120A)WH-PS-354 (CNSI 14-215)WH-PS-316 (SEG 14-215)WH-PS-318 (Westinghouse TCT)TRANSPORTATION

-49CFR IOCFR7]WM-PS-100 WH-PS-120 WH-PS-140 WH-PS-180 WH-PS-240 WH-PS-250 Page 3 of 3

~I~Attachment E NDAP-gA-0646 Revision 4.Paqe 63 of 63 QATERTAPS NOT I OQDATJBLE'/(TED o>>vF~i>>~'!~"~.~>>~l~RS Aliphatic hydrocarbons (hexane, octane, ,bexene, octane, etc.)Acetone Amyl Acetate Amyl Chloride Aniline Aqua Regia, Benzene Bromine liquid Butane Camphor Oil Carbon Disulphide Carbon'Tetrachloride Chlorine liquid Chlorobenzene Chloroform Chlorosulfonic acid Chromic/sulfuric acid Cyclohexanone Dibutylphtalate Dimethylamine Di'esel fuel Ethyl acetate Ethyl butyrate Ethyl chloride Ethyl ether Ethylene chloride Ethylene chlorohydrin Ethylene dichloride Fluorine Furfural Furfuryl alcohol Fuel Oil Gasoline iodine Methyl bromide'ethyl Chloride Hethyl ethyl ketone (t1EK)Nethylene Chloride Hoist Chlorine gas Nitric Acid (50K weight concentration)

Organ Peroxides Octyl cresol Oleic acid Oleum~Pentane Petroleum ether Phenol Propane Propylene dichloride Sulfric acid (60%weight concentration)

Tetrahydrofurance Titanium tetrachloride Toulene Trichloroethylene Turpentine Tetralin Xylene Page 1 of 1

~~, I~v'Q P P'II.