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)

Text

.CATEGORY 1 .

REGULATOROZNPOg+TION DISTRIBUTION ArSTEM (RIDE)

ACCESSION NBR:9604020111 DOCWDATE: 95/12/31 NOTARIZED: NO DOCKET N FACIL:50-387 Susquehanna Steam 'Electric Station, Unit 1, Pennsylva 05000387 50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva 05000388 AUTH. NAME AUTHOR AFFILIATION BYRAM,R.G. Pennsylvania Power G Light Co.

RECIP.NAME RECIPIENT AFFILIATION

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 COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-2 LA 2 2 ,=

'D1-2 PD 1 1 POSLUSNY,C 1 1 INTERNAL: ACRS 1 1 CENT-HR'1. 1 1 NRR/DRPM/PERB/B 1 1 RGN1 DRSS/RPB 2 2 RGN1 FILE ,1 1 EXTERNAL: LITCO AKERS,D 1 1 NRC PDR 1 1 NOTES: 1 1 D

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'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 ANNUALEFFLUENT 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

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@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 ANNUALEFFLUENT 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 13

3. Meteorological Data and Dispersion Estimates 37

4. Dose Measurements and Assessments 68

5. Changes to the Offsite Dose Calculation Manual 77 and the Solid Waste Process Control Program

6. Reports of Exception to the SSES Effluent 82 Monitoring Program

7. Correction to Doses Reported in Previous 84 Semiannual or Annual Effluent and Waste Disposal Report

8. Effluent from Additional Monitored Release Points 86 AppendixA Revisions to SSES ODCM Appendix B 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 6 Figure 3: Susquehanna River Monthly Average Flow Rates 22 Figure 4: SSES Monthly Liquid Radwaste Discharge Totals 23 Figure 5: SSES Wind Rose: 10-meter Sensors 40 Figure 6: SSES Wind Rose: 60-meter Sensors 41 Figure 7: SSES Pasquill Stability Class Prevalences 42 Figure 8: Areas Within the SSES Site Boundary Open to 73 Members of the Public

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.

3 of this report contains the meteorological data associated with the year

'ection 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

'ds, Susquehanna plant. Included are regulatory limits (Table 1) sam li anal y sis metho 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 Fi'g ure 3 'he Susquehanna River monthly average flow rates t h i ies o speci ic radionuclides in waterborne effluents over the report lists for epo perio .

1995 while Figure 4 presents the SSES monthly liquid radwaste discharge totals for 1995.

Tables 6 throu g h17 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.

Table 19 presents effluent data from previous report periods wh ich was no t avai'lable at preparation time for the associated annual report.

Section 3 of this report contains the meteorological data associated w'th i th e year

. 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 rima g'meter meteorolo ical 10-me 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 H hEACTOh hEACTDh WILOINO WILDIHO EXHAUST EXHAUST VKHT VENT 110'T ISLES CfM AT Ol+ F IlLKOCfM

,ATN F Il04f 220AXXICf M 1240 Cf M 2QSXO Cf M AT 100+I 120ff AT 120~f AT 100+K 12IWF OUTSIDE Alh INTAKE HEACTOh 4UILOIHQ UNIT I UNIT II EXHAUST STACKS TUXEIHE TUXSHIE DIESEL EXHAUST FLENUM 0UILOINC SUILOHIO EXHAUST EXHAUST DIESEL OE HE HATOh WILD HID VENT VENT

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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 2.0E-04 85K 5.0E-04 87K 4.0E-05 88K 9.0E-05

"'AI 7.0E-05 133mX 5.0E-04 133X 6.0E-04 135mx 2.0E-04

3. A~ ~

135X 2.0E-04 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. 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 C. Particulates: Particulates are continuously collected via an isokinetic sampling assembly in each vent. Filters are normally exchanged once per week and analyzed on a high resolution (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: 0 0

. 2. Total Time Period for Batch Release: NA NA

3. Maximum Time Period for a Batch Release: NA NA

4. Average Time Period for a Batch Release:

5. Minimum Time Period for a Batch Release: 'A NA NA NA Abnormal Releases

1. Number of Releases 0 0

2. Total Activity Released NA 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 4.6 E-08 Kr-88 5.3 E-08 Xe-1 33 5.4 E-08 Xe-1 33m 1.3 E-07 Xe-1 35 1.5 E-08 Xe-135m 5.0E-08 Xe-138 1.2 E-07 Mn-54 2.9 E-14 Fe-59 2.8 E-14 Co-58 1.8 E-14 Co-60 3.8 E-14

'n-65 4.4 E-14 Mo-99 3.3 E-13 Cs-134 2.4 E-14 14

Radionuclide LLD (uCi/cc)

Cs-137 2.1 E-14 Ce-141 1.5 E-14 Ce-144 7.0 E-14 l-1 31 4.4 E-14 Sr-89 2.0 E-15 Sr-90 3.0 E-16 H-3 2.6 E-08 Gross Alpha 5.0 E-16 15

TABLE 2 ANNUALEFFLUENT AND WASTE DISPOSAL REPORT (1995)

AIRBORNE EFFLUENT - SUMMATIONOF ALLRELEASES First Second Third Fourth A. Fission and Activation Gas Unit uarter uarter uarter uarter Total Release Ci'.32E-02 1.53E+01 0.00E+00 O.OOE+00 Average Release Rate for Period uCi/sec 8.13E-03 1.95E+00 O.OOE+00 0.00E+00 Percent of Technical Specification Limit 5.76E-05 1.38E-02 0.00E+00 O.OOE+00 B. Iodines Total I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Release Rate for Period uCi/scc 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 uCi/sec 2.80E-05 5.85E-05 9.22E-06 '.18E-04 Percent of Technical Specification Limit '2.17E-04 4.55E-04 7.18E-05 9.15E-04 Gross Alpha Radioactivity* Ci 1.06E-06 2.85E-07 0.00E+00 O.OOE+00 D. Tritium Total Release Ci 1.59E+01 1.24E+01 2.36E+01 1.02E+01 Average Release Rate for Period uCi/sec 2.04E+00 1.58E+00 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 ANNUALEFFLUENT AND WASTE DISPOSAL REPORT (1995)

AIRBORNE EFFLUENT Releases in Continuous Mode First Second Third Fourth Nuclides Released Unit Quarter Quarter Quarter Quarter A. Fission and Activation Gases Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m Ci 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00'.00E+00 Xe-133 Ci 0.00E+00 O.OOE+00 O.OOE+00 Xe-135 Ci 6.32E-.02 1.53E+01 O.OOE+00 O.OOE+00 Total for Period Ci 6.32E-02 1.53E+01 O.OOE+00 0.00E+00 B. Iodines I-131 Ci O.OOE+00 0.00E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 O.OOE+00 0.00E+00 1.71E-05 I-135 Ci 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 1.71E-05 C. Particulate Ci Cr-51 Ci 1.62E-05 2.46E-05 0.00E+00 0.00E+00 Mn-54 Ci, 1.10E-04 3.43E-04 4.95E-05 6.41E-04 Fe-59 Ci 0.00E+00 4.54E-05 0.00E+00 1.58E-04 Co-58 Ci 2.51E-05 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 2.99E-05 4.70E-05 2.38E-05 1.36E-04 Zn-65 Ci 3.65E-05 O.OOE+00 0.00E+00 0.00E+00 Sr-89~ Ci 0.00E+00 0.00E+00 0.00E+00'.OOE+00 Sr-90* Ci 1.26E-07 0.00E+00 O.OOE+00 O.OOE+00 Cs-134 Ci 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Cs-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for Period~ Ci 2.18E-04 4.60E-04 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" '.

Qtr. 1 gtr. 2 gtr. 3 gtr. 4 Number of Batch Releases 40 70 52 62

2. Total Time Period for a Batch Release 5.11E+03 1.30E+04 5.07E+03 1.10E+04

3. Maximum Time Period for a Batch 3.08E+02 5.64E+02 3.48E+02 5.20E+02 Release 4.. Average Time Period for a Batch Release 1.28E+02 1.86E+02 9.75E+01 1.78E+02

5. Minimum Time Period for a Batch 2.50E+01 .1.00E+00 2.00E+01 2.40E+Ol Release

6. Average Stream Flow During Period of 6.76E+03 6.86E+03 1.00E+04 7.60E+03 Release of Effluent into a Flowing Stream (Cooling Tower Blowdown Flow Rate) 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 0 0

2. Volume Released N/A N/A

3. Total ActivityReleased N/A N/A Ifa 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 4.5 E-08 Fe-59 5.0 E-08 Co-58 2.4 E-08 Co-60 5.4 E-08 Zn-65 4.9 E-08 Mo-99 1.7 E-07 I-131 2.0 E-08 Cs-134 2.2 E-08 18

Radionuclide LLD uCi/ml Cs-137 2.6 E-08 Ce-141 3.2 E-08 Ce-144 1.3 E-07 Sr-89 4.0 E-08 Sr-90 4.0 E-09 Fe-55 1.0 E-06 H-3 4.6 E-06 Gross Alpha 3.0 E-08 19

TABLE 4 ANNUALEFFLUENT AND WASTE DISPOSAL REPORT (1995)

WATERBORNE EFLUENT - SUMMATIONOF ALLRELEASES First Second Third Fourth A. Fission and Activation Products Unit Quarter Quarter Quarter Quarter

1. Total Release (not including Tritium, Gases, AI h'a ~ Ci 5.91E-02 4.44E-01 3.43E-02 4.21E-02

2. Average Diluted Concentration During uCi/ml 4.52E-07 1.27E-06 1.81E-07 1.37E-07 Period

3. PercentofA licableLimit O.OOE+00 '.OOE+00 O.OOE+00 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 uCi/ml 1.28E-04 7.86E-05 4.91E-05 8.37E-05 Period

3. Percent of A licable Limit 4.28E+00 2.62E+00 1.64E+00 2.79E+00 C. Dissolved and Entrained Gases Total Release Ci 1.51E-04 3.34E-03 3.19E-05 5.45E-04 Average Diluted Concentration During uCi/ml 1.15E-09 9.54E-09 1.68E-10 1.77E-09 Period

3. Percent of A licable Limit 2.88E-05 2.39E-04 4.20E-06 4.43E-.05 D. Gross Al ha Radioactivi

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Volume of Waste Released Gallons 3.95E+05 3.07E+06 3.08E+05 8.25E+05 (Prior to Dilution) Liters 1.50E+06 1.16E+07 1.17E+06 3.13E+06 F. Volume of Dilution Water Gallons 3.45E+07 9.22E+07 5.01E+07 8.10E+07 Used During Period of Release Liters 1.31E+08 3.50E+08 1.90E+08 3.07E+08 G. Volume of Dilution Water Gallons 8.76E+08 8.99E+08 1.32E+09 1.01E+09 Used Over Entire Period 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 ANNUALEFFLUENT AND WASTE DISPOSAL REPORT (1995)

WATERBORNE EFFLUENT Releases in Batch Mode First Second Third Fourth Nuclldes Unit Quarter Quarter Quarter Quarter Released A. Fission and Activation Products F-18 Ci 0.00E+00 3.94E-13 0.00E+M 0.00E~

Na-24 Ci 2.21E45 O.OOE+00 7.42E44 O.OOE+00 Cr-51 Ci 4.64E42 1.85E42 5.60E45 3.49E43 Mn-54 Ci 5.56E43 8.66E42 2.57E42 2.07E42 Mn-56 Ci O.OOE+00 0.00E+00 2.24E-IO O.OOE+00 Fe-55 Ci 2.69E43 2.72E41 5.47E43 5.47E43 Fe-59 Ci 2.05E43 3.63E42 1.94E44 6.13E43 Co-58 Ci 1.40E44 5.17E43 1.51E44 6.86E44 Ci 1.74E43 1.93E42 1.45E43 3.91E43 Ci 2.20E44 3.72E43 4.50E44 5.86E44 As-76 Ci 1.89E44 0.00E+00 0.00E+00 O.OOE40 Sr-89 Ci 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Sr-90 Ci O.OOE+00 O.OOE+M 0.00E+00 0.00E+00 Sr-92 Ci 4.24E48 6.53E46 5.48E47 5.71E46 Nb-95 Ci 0.00E~ 3.15E46 4.71E46 0.00E+00 Tc-99m Ci 3.05E46 6.89E47 3.58E47 0.00E40 A -110m Ci 3.49E45 1.94E43 9.43E45 1.10E43 Sb-124 Ci O.OOE+00 5.28E44 O.OOE+00 3.21E45 Te-131m Ci 0.00E+00 4.01E45 O.OOE+00 0:OOE+00 1-131 Ci 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 Ci 2.79E46 2.88E46 1.13E46 4.22E46 Cs-137 Ci 2.72E45 3.46E45 2.15E45 1.17E45 La-140 Ci O.OOE+00 O.OOE+00 O.OOE+00 8.23E46 Cc-144 Ci O.OOE+00 1.08E44 O.ME+00 O.OOE+00 Hi'-181 Ci 0.00E+00 5.03E45 0.00E+00 O.OOE+00 W-187 Ci 0.00E+00 O.OOE+00 0.00E+M O.OOE+00 Total for Period'.

Ci 5.91E42 4.44E41 3.43E42 4.21E42 Tritium H-3. Ci 1.68E+Ol 2.75E+01 9.32E+00 2.57E+01 Total for Period Ci 1.68E+Ol 2.75E+01 9.32E+00 2.57E+Ol C. Dissolved and Entrained Gasses Ci 0.00E+00 O.OOE+M O.OOE+00 O.OOE+00 Kr-86m Ci O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Kr-85 Ci O.OOE+00 3.07E43 0.00E+00 3.86E44 Kr-87 Ci 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Kr-88 Ci 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Xe-131m Ci O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Xc-133m Ci 0.00E+00 O.OOE+00 0.00E+00 O.OOEt00 Xc-133 Ci 3.66E-OS 1.75E44 1.65E45 9.05E45 Xe-135m Ci O.OOE+00 0.00E+00 O.OOOO O.OOE+00 Xc-135 Ci 1.14E44 9.15E45 1.54E45 6.83E45 Total for Period Ci 1.5 IE44 3.34E43 3.19E45 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 RADIOACTIVEWASTE REPORT ANNUALEFFLUENT AND WASTE DISPOSAL REPORT SOLID RADIOACTIVEWASTE DATAPERIOD: JANUARY 1 1995-DE EMBER31 1995 PREPARED BY:

. P. LEWI - AL YSICIST E

APPROVED BY:

3 S DOXSEY - LUENTS MANAGEMENTSUP 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 ANNUALEFFLUENT 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 ( 1.000EC4 0.00%

Am-241 Q 0.00%

3.076'.621E+00 C-14 0.14%

Cm-242 1.644EA3 0 00%

Co-58 2.596E+00 0.22%,

~0 2.556E+02 21 78%

Cr-51 1.501E42 0.00%

Cs-137 6.911E+00 0.59/o Fc-55 7.82&E+01 6.67%

Fe-59 5.373E+0 I 4 58%

H-3 nt&Ewl 4 +o

~

w 1-129 1.&OOE+3 0.00%

I-131 2.280E%2 0.00%

Mn-54 . 7.099E+02 60.48%

Ni<3 1.627E+00 0.14%

Pu-238 4 5.039E%4 0.00%

Pu-239 < 6.063E~ P 00%

Pu-241 3.386EA l 0 03%

Sr-90 '1.004E%2 0 nn/

Tc-99 4.951E%2 0 Zn<5 1.859E+01 l 58%

I3c47 2.000E<a 0.00 io Cm-244 < 3.985E%4 0.00%

Cc-144 ~ '.98&E+00 P 17%

KAO. 1.900E-03 P 00%

Nb-95 '.150E-O l P P2%

Pb-212 l.600E43 ppp Zr-95 2.079E+00 0. l8%

Xe-133 1.200 E<3 O.OO%

TOTAL ACTIVITY (Ci) I. 74 1 100.00%

CONTAINER VOLUME 295.GOO A 3 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 1.484EA3 P 00%

C-14 4.336&01 0.05%

Cm-242 5.992E+3 P 00%

Co-58 1.716' 0.21%

Co%0 2.031E+02 24.32%

Cr-51 4.728EO2 01%

Cs-137 5.687E+00 0.68'.56%

Fc-55 6.313E&1 Fc-59 3.394E+01 4.06%

H-3 1.321E+01 1.58%

I- 2.400E43 0.00%

l29'n-54

.4.894E&2 58.61%

Ni43 1.321E+00 0.16%

Pu-238 1237E<3 0.00%

Pu-239 , 1.271843 Q.00%

Pu-241 2.325EAI 0 03%

Sr-90 4.431E42 Q.Q1%

Tc-99 5.930E%2 0.01%

Zn<5 l.279E+0 l 1 53%

Cm-243 0.00%

6.832'.881E+00 Cc-l44 0.22%

Nb-95 L091E~ 0 13%

Zr-95 6.933 E+00 0 83%

TOTAL ACTIVITY (Ci) ~

0.835 100 Opoj CONTAINER VOLUME 1113.100 fQ 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 1.180E<3 0.45%

Am-241 7.340EA7 0.00%

C-14 2.700 E4 ~

0.08%

Cm-242 4.370EW6 0.00%

Co-58 1.550EA3 0.59/o Grip 1.290' 50 00%

Cr-51 5.250EA3 2.02'/0 Cs-137 3.500EA3 I 34%

Fe-55 ~ 4.060E+2 15 73%

Fe-59 2.780EA2 10 77%

H-3 7,62nE3 " 94oio 1-129 N/A LLD (4.27E48 uCi/cc)

Mn-54 . 3.290E<2 12 73%

Ni<3 8.090 E4 0.31/o Pu-238 5.660E7 0.00%

Pu-239 6.110EW7 0 00%

Pu-241 1.450E4 0.05o/o Sr-90 1.360E5 0.00%

Tc-99 1 440E<5 0 01/

Zn45 6.440EW3 2.48%

Ce-144 1.270E<3 0 50/o Cm-243 3.660EW7 0.00%

TOTAL ACTIVITY (Ci) 0.000 100 00%

CONTAINER VOLUME 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 "

7.810E42 P PP%

C-14 6.250E+00 9.00%

Cm-242 5.160E42 0.00%

GHM 5.210E+05 48.56%

,Cs-137 1.619E+03 Fe-55 20 78%

0.15%'.230E+05 H-3 2A60E41 0.00%

I-129 N/A LLD (1.45E46 uCi/cc)

Mn-54 2.870EW5 26 75%

Ni<3 8.170E&3 0.76%

Pu-238 1.942E42 . P PP%

Pu-239 1.956E42 0.00%

Pu-241 1.93&E+01 0.00'/o SR49 7.490E41 0.00%

Sr-90 2.240Et00 0 00/

Tc-99 9.370' 0 01%

Zn<5 3.030E~ 2.82%

Ce-144 9.750E+00 0.00%

Ni-59 1.640E+03 0 17%

Cm-243 7.660E<2 0.00%

TOTAL ACTIVITY (Ci) 1073.000 100.00%

CONTAINER VOLUME 264.800. ft 7.498 m3 30

TABL'E 15 CLASS A SOURCE OF WASTE CONDENSATE DEMINERALIZER RADWASTE DEMINERALIZER TYPE OF CONTAINER HIC METHOD OF PROCESS DEWATERED ISOTOPES ACTIVITY  % OF TOTAL Am-241 1.756E43 0.00%

C-14 5.263 E&0 3 24%

Cm-242 1.756E43 P PP%

Co-58 6.442E+01 39.61%

Grip 5.033' 30.94%

Cs-137 3.894E41 0.24%

Fe-55 2.234E+00 1 37%

Fe-59 3.150E41 0.19%

H-3 1.448E+01 8.90%

1-129 N/A LLD (2;85E45 uCi/cc)

Mn-54 2.132E+01 13.11%

Ni43 . 8.897E41 0 55%

Pu-238 2.335E43 P 00%

Pu-239 2.425E43 0.00%

Pu-241 5.571E41 0.35%

Sr-90 1.081E42 P P1%

Tc-99 N/A LLD (4.57E45 uCi/cc)

'n45 1.853E&0 1 15%

Ce-144 5.362E41 0 34%

Cm-243 1.572E43 0.00/o TOTAL ACTIVITY (Ci) 0.163 1PP PP%

CONTAINER VOLUME 87.600 fl 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 1.664 E+02 0.41%

Am-241 8.600E<3 Q 00'/

C-14 5.200E+01 13%

Cm-242 5.600E%3 P 00%

Co-58 2.863E&2 0 71%

~0 6.200E&3 15.24%

Cr-51 3.700E+02 0 91%

Cs-137 2.220E+01 0.06%

Fc-55 6.260E+03 15.38%

Fe-59 1.795E+03 4 42%

H-3 5.680E+01 0 14%

1-129 N/A LLD (6.53E45 uCi/cc)

Mn-54 2.490E+04 61.18%

Ni<3 1.078 E+02 0 27%

Pu-238 1.824E%2 P 00%

Pu-239 1.69IE42 , 0.00%

Pu-241 4.130E+00 0 01%

Sb-124 , 4.680E+01 0.12%

Sr-90 2.340EA I 0 00%

Tc-99 Zn45 Cc>>144 2.720E%1 4060E+02

1. 110E+0(}

'00/ Q.uu%

u (l(kvio Cm-243 5.610E%3 Q.oo%

Ni-59 6.7 IQE+00 0 02%

TOTAL ACTIVITY (Ct) 40.700 100 00'I CONTAINER VOLUME 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 3.223 E&2 0 18%

Am-241 2.560' 0.00%

C-14 2.377E+00 P PP%

Cm-242 2.509EI 0.00%

Co-58 2'.959E+03 64%

Co%0 2.783 E&4 IS 39%

Cr-Sl 8.496E+03 4 70%

Cs-137 7.416EWI 0.04%

Fe-55 2.406E+04 13.31%

Fe-59 1.173E+04 6 49%

H-3 1.213E+02 0 07%

1-129 N/A LLD (4.75E45 uC1/cc)

Mn-54 1.006E&5 55.64%

Ni<3 3.576E+02 0.20%

Pu-238 5.433' P PP%

Pu-239 5.032' P P0%

Pu-241 1.227E+02 0.07%

Sb-124 2.678E+02 0.15%

Sr-89 4.336E+00 0.00%

Sr-90 9.318E&1 U.UU"jo Tc-99* 1.080 E+00 0.00%

Zn45 3.520E+03 l.950jo Ce-144 1.248E+02 0.07%

Cm-243 .'.257EAI P PP%

Hf-181 2.631E+01 P P1%

Nb-95 7.619E+01 pp4 Ni-59 9.576E+0 I 0.05%

Sr-92 7.910E-16 P PP%

TOTAL ACTIVITY (Ci) 180.790 100 00 j' CONTAINER VOLUME 777.600 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 ANNUALEFFLUENT 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 15.9%

b. I-131 13 3%

c. Particulates 15.8%

d. Tritium 13.6%

2. Waterborne Effiuents

a. Fission and Activation Products 50 b, Tritium 33%

c. Dissolved and Entrained Gases 84%

d. Gross Alpha Activity 60%

e. Volume of Waste Released 5.0%

(Prior to Dilution)

f. Volume of Dilution Water Used During 15 0%

Period

3. Solid Wastes

a. Atmospheric Deminerlizer 15 1%

(Dewatered - HIC)

b. Condensate Demineralizer/ 15.1%

Radwaste Demineralizer (Dewatered - Carbon Steel Liner)

c. Condensate Demineralizer/ 15.1%

Radwaste Demineralizer (Dewatered - HIC)

d. Liquid Radwaste Filter Media 15 (Dewatered - HIC)

e. RWCU Filter Media 15.1%

(Dewatered - HIC) 34

Measurement Estimated TotaI Error

3. Solid Wastes (cont.)

f. Ultrasonic Resin Cleaning Waste 15.1%

(Dewatered - HIC)

g. Cartridge Filters 25 0%

(Dewatered - HIC)

h. Processe'd DAW 25 0%

(Strong Tight Container)

i. Non-Processed DAW 25 0%

(Strong Tight Container)

j. Incinerated DAW 25.0%

(Strong Tight Container) k, Cartridge Filters 25.0%

(HIC)

I. Irradiated Components 25.0%

(Dewatered-Steel Liner) 35

TABLE 19 ANNUALEFFLUENT AND WASTE DISPOSAL REPORT DATA NOT REPORTED IN PREVIOUS ANNUALREPORT NUCLIDE CATEGORY UNIT FOURTH QUARTER 1994 A. Airborne Effluents

1. Sr-89 Ci 0.00E+00

2. Sr-90 Ci 5.46E-09

3. Gross Alpha Ci 1.73E-06 B. Waterborne Effluents

1. Sr-89 Ci O.OOE+00

2. Sr-90 Ci 0.00E+00

3. Fe-55 Ci 6.18E-03

3. Gross Alpha Ci Q.QQEi00 36

SECTION 3 METEOROLOGICAL DA TA AND DISPERSION ES TIMATES 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 ANNUALEFFLUENT AND WASTE DISPOSAL REPORT METEOROLOGICAL DATA AVAILABILITY DATA PERIOD'995 PERCENT OF VALIDHOURS PARAMETER DURING PERIOD

1. Wind speed

a. 10-Meter Sensors g75

b. 60-Meter Sensor gg4

2. Wind direction

a. 10-Meter Sensors gg4

b. 60-Meter Sensor 99 5%

I

3. Indicator of Atmospheric Stability (Primary Tower)

a. Temperature Differential between 10 98 9%

and 60 meters (Delta-TA)

b. Temperature Differential between 10 g87 and 60 meters (Delta-TB)

c. Sigma Theta @ 10 Meters 50 1o/*

d. Sigma Theta @ 60 Meters 50.1%*

4. Percent of hours for which valid 10-meter g6g wind speed, 10-meter wind direction, and temperature differential were available.

5. Percent of hours for which valid 60-meter 988%

wind speed, 60-meter wind direction, and temperature differential were available.

of atmospheric stability by sigma theta is the secondary method

'Classification 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 0

0 0

CALM O.O.

ANNUAL 8838 08S.

mmH3 WIND DIRECTION FREQUENCY (PERCENT)

~~ MEAN WIND SPEED ( MI/HR )

].O-METER ANNUAL WIND ROSE - 1995

FIGURE 6 0

5 CALM O.O ANNUAL 8707 OBS.

EKE WIND DIRECTION FREQUENCY (PERCENT) tZi~ MEAN WEND SPEED ( MI/HR )

60-METER ANNUAL WIND ROSE - 1995

Figure 7 ES PASQUILL STABILITYCLASS PREVALENCES Data Period: 1995 Based on Joint-Frequency Distributions at 10 Meters (8487 Hourly Values)

Moderately Unstable Slightly Unstable 3.5%

4.6%

Very Unstable 5.3%

Neutral 41 1%

Very Stable 7.1%

Moderately Stable Slightly 11.3%

Stable 27.1%

42

Page 1 of 10 J

TABLE 21 JolNT WIND FREQUENCY DlSTRlBUTlON BY STABlLlTYCLASS PENNSTLVANIA POMER 8 LIGHT CO(PANT (PAL) - Susquehams Steie Electric Stetion 1/26/1996 PAGE 62 TINE OF DAT: 13:51:57 PROGRAHI JFD VERSION( PC-1.2 1995 Prietary Touer Data Foot Level SITE IDENTIFIER:

DATA PERIOD EXAHIKED: 1/ 1/95 - 12/31/95 STABILITY CLASS A STABILITY BASED ON: DELTA T SETMEEN 200.0 AND 33.0 FEET MIND NEASURED AT: 33.0 FEET MIND THRESHOLD AT: .50 NPH JOINT FREOUEKCT DISTRIBUTION OF MIND SPEED AND DIRECTION IN HOURS AT 33.00 FEET SPEED (NPH) . N NNE NE EKE E ESE SE SSE S SQl Ql MQI M MNM NM NNM TOTAL CALN 0

.51- 3.CO 0 0 1 0 7 1 2 0 0 0 0 0 0 0 11 3A1- 6.70 3 9 12 6 4 7 13 16 36 48 6 0 0 2 168 6.71-11.20 0 7 19 4 1 6 3 22 11 116 45 3 0 0 237 1.21-16.80 0 0 0 0 0 0 0 0 19 16 2 0 0 37 16.81-22.40 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>22.40 0 0 0 0 0 0 0 0 0 0 0 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 STAB I LITT BASED Nl: DELTA T SETMEEN 200.0 AND 33.0 FEET MIND NEASURED AT: 33.0 FEET MIND THRESHOLD AT: .50 NPH JOINT FREOUENCT DISTRIBUTIOH OF MIND SPEED AND DIRECTIOH IN HOURS AT 33.00 FEET SPEED (NPH) N NNE NE ENE E ESE SE SSE S SQI Ql MQI M MHM HM NNM TOTAL CALH 0

.51- 3.CO 0 0 1 0 2 2 4 1 1 1 0 0 0 0 13 3.41- 6.70 3 14 11 6 6 3 8 6 10 27 27 9 1 0 0 133 6.71-11.20 5 13 6 0 0 0 2 3 10 5 43 25 9 2

' 5 130 11.21.16.80 16.81-22.CO 0

0 0 0 0 0 0 0 0 0 0 10 1 0 0, 18 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1

>22.40 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 8 27 18 6 8 5 14 10 21 33 78 45 11 2 4 5 295 43

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

~ DATA PERIOD EXAHINEDI 1/ 1/95 12/31/95 STABILITY CLASS C STABILITT BASED OM: DELTA T BETMEEN 200.0 AND 33.0 FEET MIKD MEASURED AT: 33.0 FEET MIKD THRESHOLD AT:,50 HPH JOINT FREOUEHCY DISTRIBUTION OF MIKD SPEED AKD DIRECTION IN HCRIRS AT 33.00 FEET SPEED (HPH) N NNE KE ENE E ESE SE SSE S SSM SM MSM M MHM NM KIN TOTAL 0

.51- 3.40 0 0 5 3 1 6 2 2 0 2 1 0 0 0 24 3.41- 6.70 6.71.11.20 6 15 14 6 3 7 12'1 12 18 41 15 1

5 2 1

3 3 173 7 13 3 0 0 1 4 1 3 4 44 28 13 9 9 12 151 11.21-16.80 3 0 0 0 0 0 0 0 0 0 6 16 6 4 2 5 42 16.81-22.CO 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 2

>22.40 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 16 28 22 9 4 14 18 14 15 24 92 62 24 16 14 20 392 STAB I LITT CLASS D STABILITY BASED ON: DELTA T BETQEEN 200.0 AND 33.0 FEET MIND MEASURED AT: 33.0 FEET MIND THRESHOLD AT: .50 HPH JOINT FREOIEKCY DISTRIBUTION OF MIND SPEED AND DIRECTIOM IM HQIRS AT 33 ~ 00 FEET SPEED (HPH) H NKE NE ENE E ESE SE SSE S SSM Idyll SM M QKM NM KIN TOTAL CALM 0

.51- 3AO 31 51 88 69 107 62 82 67 51 66 40 26 12 9 4 9 774 "3.41- 6.70 123 157 172 66 45 32 76 113 79 115 1C5 99 78 66 66 66 1498

6. 71-11. 20 104 51 30 5 10 9 24 17 18 18 133 119 111 92 140 111 992 11.21-16.80 9 1 0 0 1 0 1 2 4 0 23 69 56 15 13 19 213 16.81-22AO 0 0 0 0 0 0 0 0 0 0 0 C 4 0 0 0 8

%22AO 0 0 0 0 ~

0 0 0 0 0 0 0 0 0 0 0 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 STABILITYCLASS

- Suaquehama Stean Electric Station 1/26/1996 PAGE 64 PENNSTLVANIA POMER 4, LIGHT C(BLPANY (PP1L)

TIME OF DAY) 13~51!57 PROGRAM: JFD VERSION: PC-1o2 1995 PrimarY Tour Data - 33.Foot Level SITE IDENTIFIER:

DATA PERIOD EXAMIKEDI 1/ 1/95 . 12/31/95 STABILITY CLASS E STABILITY BASED ON: DELTA T BETMEEN 200.0 AND 33.0 FEET MIND MEASURED AT: 33.0 FEET LIIND THRESHOLD AT: .50 HPH JOINT FREQUENCY DISTRIBUTIOH OF MIND SPEED AND DIRECTION IN INRIRS AT 33.00 FEET SPEED ESE SE SSE S SSM QI MQI M MNM NM NNM TOTAL (HPH) N NNE KE ENE E 0

CAN 228 114 115. 117 128 136 50 12 6 5 4 4 1388

.51- 3.40 27 77 180 185 76 54 2 2 28 - 35 67 160 140 54 25 11 12 26 752 3.41 6.70 39 21 8 2 4 20 23 18 27 16 ~ 3 1 0 144 6.71-11.20 12 3 1 2 ,

0 0 0 0 6 3 0 2 0 0 0 1 14 11.21-16.80 0 0 1 1 16.81-22.40 0 0 0 0 0 0 0 0 0 0 0 0 0 0 :0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>22.40 0 78 156 242 250 190 118 147 178 221 314 218 84 34 17 16 . 35 2298 TOTAL STABILITY CLASS F STABILITY BASED ON: DELTA T BETMEEN 200+0 AND 33.0 FEET LIIND MEASURED AT: 33.0 FEET MIND THRESHOLD AT: .50 MPH JOINT FREQUENCY DISTRIBUTIOH OF MIND SPEED AND DIRECTION IH H(AIRS AT 33.00 FEET SPEED (MPH) H NNE NE ENE E ESE SE SSE S SQI QI MSM LI MHM NM NNM TOTAL 1

CALM

.51- 3.40 2 18 104 360 190 63 31 28 30 22 9 0 2 1 0 0 860 3.41. 6.70 7 ' 5 47 3 1 1 1 2 12 8 0 1 0 0 2 95

6. 71-11. 20 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 11.21 16.80 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 16.81.22.40 0 0 0 0 0 0 0 ~ 0 0 0 0 0 0 0 0 0 0, i22.40 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 STABlLITYCLASS

'PENNSYLVANIA POMER 8 LIGHT CNIPANY (PAL) - Susquehama Stean Electric Station 1/26/1996 PAGE 65 TINE OF DAY: 13:51:57 PROGRAM: JFD VERSIDHI PC 1.2 1995 Prissry Teer Data Foot Level SITE IDENTIFIER:

DATA PERICO EXAHINEDI 1/ 1/95 - 12/31/95 STABILITY CLASS G STABILITY BASED OH: DELTA T BETMEEM 200.0 AND 33.0 FEET MIND MEASURED AT: 33.0 FEET MIND THRESHOLD AT: .50 KPH JOINT FREOUENCY DISTRIBUTION OF MIND SPEED AMD DIRECTION IN H(RIBS AT 33.00 FEET SPEED (HPH) N HHE NE EHE E ESE SE SSE S SSM SM MSM M MNM NM NNM TOTAL CALH 0

.51- 3.40 1 12 '5 358 82 21 5 2 4 2 0 1 0 0 0 1 564 3.41- 6.70 0 1 3 36 1 0 0 0 0 0 1 0 0 0

' (. 42 6.71.11.20 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 11.21-16.80 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 16.81 22.40 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>22.40 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 CLASS ALL STABILITY BASED OH: DELTA T BETMEEH 200.0 AND 33.0 FEET MIND MEASURED AT: 33.0 FEET MIND THRESHOLD AT: .50 NPH JOIN'I FREQUENCY DISTRIBUTION OF MIND SPEED AND DIRECTIOH IN HRIRS AT 33.00 FEET SPEED (NPH) K NHE KE ENE E ESE SE SSE S SSM SM MSM M MNM NM MKM TOTAL CALH 1

.51. 3.40 61 158 454 1018 574 268 240 219 214 101 40 20 16 8 14 3634 3.41- 6.70 181 277 271 188 64 50 132 179 186 410 183 110 79 84, 99 2861 6.71 11.20 130 87 66 10 13 12 40 44 76 56. 363 233 139 104 151 132 1656

11. 21-16. 80 12 1 0 0 2 0 1 8 7 0 56 113 65 19 15 25 324 16.81-22.40 0 0 0 0 0 0 0 0 0 0 0 7 4 0 0 0 11

>22.40 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 384 523 791 1216 653 330 413 450 483 653 930 576 338 218 258 270 8487 46

Page 5 of 10 TABLE 21 JOINT WlND FREQUENCY DlSTRlBUTlON BY STABlLITYCLASS PENNSYLVANIA POKER 8 LIGHT C?NIPANY (PPCL) - Susquehama Steea ELectric Station 1/26/1996 PAGE 66 TIHE OF DAY? 13?51?57 PROGRAM? JFD VERSION? PC-1.2 1995 Prie?ery To??er Data 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: 0 TOTAL M?RU?ER OF OBSERVATIONS KITH BACKUP DATA: 0 PERCENTAGE 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 3 8

16 32 10 6'

12 5 .14 18 38'7 183 67 5 0. 0 8 27 18 5 14 10 21 33 78 45 11 2 0 C 16 28 22 9 4 14 18 14 15 24 92 62 24 16 0 D 267 260 290 140 163 103 183 199 152 199 341 317 261 182 0 E 78 156 242 250 190 118 147 178 221 314 218 84 34 17 0 F 11 23 109 407 193 64 32 29 32 34 17 0 3 1 1 G 1 13 78 394 83 21 5 2 4 2 TOTAL 384 523 791 1216 '53 330 413 450 483 653 930 1

576 1 0 338 218 0 0 1

0 47

V Page 6 of 10 TABLE 2$

JOINT WlMD FREQVEMCY DfSTRlBVTlON BY STABlLITYCLASS PEKNSYLVANIA POMER C LIGHT C(N(PANT (PAL) - Suaquehsma Stean Electric Station 1/26/1996 PAGE 62 TIKE OF DAT: 13t54(54 PROGRAH: JFD VERSIONI PC 1.2 1995 Prieary Touer Data - 200.Foot Level SITE IDENTIFIER-DATA PERICO EKAHIKEDI 1/ I/95 - 12/31/95 STAB ILITY CLASS A STABILITY BASED Ok: DELTA T BETMEEN 200.0 AND 33.0 FEET MlKD HEASURED AT: 200.0 FEET MIND THRESHOLD AT: .50 HPH JOINT FREGUENCY DISTRIBUTION OF MlkD SPEED AND DIRECTION IN HOURS AT200.00 FEET SPEED (HPH) N NKE NE EKE ~ E ESE SE SSE S SQI Ql MQI M MKM NM KNM TOTAL

'ALH 0

.51- 3AO 0 0 0 4 2 1 0 1 0 0 0 0 0 0 0 8 3.41- 6.70 2 5 10 3 1 4 2 6 9 17 3 0 0 D 1 67 6.71-11.20 0 11 24 2 2 0 8 8 19 75 48 2 0 0 0 204

'1.21-16.80 0 3 5 0 0 0 4 12 17 57 47 6 0 0 0 153 16.81.22 AD 0 0 0 0 0 0 0 2 1 7 15 0 0 0 0 25

>>ZZAO 0 0 0 0 0 0 0 0 D 0 1 0 0 0 0 1 TOTAL 2 19 39 9 5 5 11 14 29 46 156 114 8 0 0 1 458 STABILITY CLASS 8 STABILITY BASED ON: DELTA T SETMEEK 200.0 AND 33.0 FEET MIND HEISURED AT- 200.0 FEET MIND THRESHOLD AT: .50 HPH JOINT FREQUENCY DISTRIBUTION OF MIND SPEED AND DIRECTIOH Ik HOURS AT200.00 FEET SPEED (HPH) N kNE kE ENE E ESE SE SSE S SQI Ql MSM M MKM NM NNM TOTAL CALN 0

.51- 3.40 0 2 2 2 1 1 1 2 0 0 0 ~ 0 0 13 3.41- 6.70 2 7 3 6 2 2 1 13 10 1 0 1 0 0 55 6.71-11.20 18 12 0 0 6 6 6

' 41 29 6 0 2 1 142

11. 21-16. 80 6 0 0 0 0 4 11 14 23 10 1 1 3 76 16.81-22.40 0 0 0 0 0 0 0 1 2 7 0 0 0 0 10

>>22.40 0 0 0 0 0 0 0 0 0 -0 1 0 0 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 STABlLlTYCLASS PENNSYLVANIA POMER 8 LICHT COMPANY (PPAL) - Suaquehamn Steie ELectric Station 1/26/1996 PACE 63 TIKE OF DAY: 13:54154 PROGRAM) JFD VERSION( PC 1+2 1995 PriaarY Taer Data - 200-Foot Level SITE IDENTIFIER:

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

.51. 3.40 0 0 5 2 4 2 1 2 1 1 0 1 0 0 0 0 19 3.41- 6.70 2 8 9 2 4 3 4 7 9 5 20 6 6 2 1 2 90 6.71-11.20 5 17 9 1 0 4 6 7 11 34 31 15 7 V 6 164 11.21-16.80 7 6 0 0 0 0 2 1 4 1 13 31 11 8 4 12 1)0

' 0 16.81-22.40 0 0 0 0 0 0 0 0 1 0 10 6 0 0 18

%22.40 0 0 0 0 0 0 0 0 0 0 0 4 0 0 0 0 4 TOTAL 14 31 23 5 8 9 13 14 22 18 68 83 38 17 12 20 395 STAB I L'ITY CLASS D STABILITY BASED Ol: DELTA T BETMEEN 200.0 AKD 33.0 FEET MIND MEASURED AT: 200.0 FEET MIND THRESHOLD AT: +50 KPH JOINT FREOUEHCY DISTRIBUTION OF MIND SPEED AMD DIRECTIOH IH HOURS AT200.00 FEET SPEED (KPH) M NNE KE ENE E ESE SE SSE S SSM QI MQI M MNM NM MKM TOTAL CALM 0

.51- 3.40 4 38 60 51 29 25 35 29 29 40 21 7 7 5 3 4 387 3.41 6.70 48 90 83 59 44 42 44 55 46 60 134 69 40 16 25 23 878 6.71.11.20 124 131 124 34 23 20 46 83 57 46 102, 151 123 134 138 121 1457

11. 21-16. 80 31 34 20 4 10 6 '12 13 18 35 59 174 102 51 49 62, 680 16.81 22.40 1 1 3 0 1 0 3 2 6 0 4 52 56 8 1 2 140

>22.40 0 0 0 0 0 0 0 0 0 1 4 5 . ~

0 0 0 11 TOTAL 208 294 290 148 107 93 140 182 157 181 321 457 333 214 216 212 3553 49

Page 8 of 10 TABLE 21 JOINT WlND FREQUENCY DlSTRlBUTlON BY STABlLlTYCLASS PENNSYLVANIA POMER 8 LIGHT C(NIPANY (PPCL) - SIFJeh~ St++0 Electric Stetim 1~/I PAGE 64 TINE OF DAY: 13:54:54 PROGRAH: JFD VERSION( PC-1.2 1995 Prienry Toeer Dote - 200-Foot level SITE IDENTIFIER:

DATA PERI(O EXAHINEDJ 1/ 'I/95 - 12/31/95 STABILITY CLASS E STABILITY BASED DKt DELTA T BETMEEN 200.0 AKD 33.0 FEET MIND HEASURED AT: 200.0 FEET MIND THRESHOLD AT: .50 HPH JOINT FREOUENCY DISTRIBUTION OF MIND SPEED AND DIRECTION IN H(RJRS AT200.00 FEET SPEED (NPH) N KNE KE ENE E ESE SE SSE S SSM QJ MSM M MKM NM NNM TOTAL CALH 0

.51- 3.40 23 72 114 69 46 37 42 43 52 42 31 12 4 2 5 3 597 3.41- 6.70 41 170 99 42 19 14 37 36 62 79 106 51 16 10 14 9 805 6.71-11.20 26 57 40 10 3 0 18 30 64 94 '128 132 31 15 16 18 682 11.21-16.80 4 9 13 2 2 1 3 12 27 34 42 91 6 0 0 2 248 16.81-22.40 0 2 1 0 1 1 1 8 9 5 3 4 '0 0 0 1 36

>>22.40 0 0 0 0 0 0 0 3 0 0 0 3 0 0 0 0 6 TOTAL 94 310 267 123 71 53 101 132 214 254 310 293 57 27 35 33 2374 STABILITY CLASS F STABILITY BASED ON: DELTA T BETMEEN 200.0 AKD 33+0 FEET Ml ND HEASURED AT: 200.0 FEET MIND THRESHOLD AT: 50 HPH JOINT FREOJENCY DISTRIBUTION OF MIND SPEED AND DIRECTIOK IN HOURS AT200.00 FEET SPEED (HPH) N NNE NE EKE E ESE SE SSE S SQI SM MSM ll MNM KM NNM TOTAL CALH 0

.51- 3.40 16 66 107 59 37 36 29 25 18 18 10 4 0 2 2 2 431 3.41- 6.70 33 203 63 18 8 7 6 8 21 35 35 10 2 1 3 5 458 6.71-'11.2D 5 9 4 1 D 1 3 3 3 1D 11 19 4 0 0 2 75 11.21-16.80 1 0 0 0 0 0 0 0 0 0 1 10 0 0 0 0 12 16.81-22.40 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>>22.40 0 0 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 STABILITYCLASS PENNSTLVANIA POMER t LIGHT CNIPANY (PPSL) - Susquelema Stean Electric Station 1/26/1996 PAGE TIKE OF DAY: 13:54t54 PROGRAM( JFD VERSION: PC 1.2 1995 Prieiry Tamr Date - 200-Foot Level SITE IDENTIFIER:

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

.51. 3.40 3.41. 6.70 3

29 36 159 62 65 32 8

24 8

28 5

17 8 '

'3 8 17 1C 17 6

14 1

2 0 1

' 0 1

4 1

~

6.71.11.20 2 3 0 0 0 1 0 2 0 2 3 ~ 0 0 1.21.16.80 0 0 0 0 0 0 0 0 0 0 0 0 0 0  : 0 0 16.81.22.40 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>>22.40 0 0 0 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 CLASS ALL STABILITY BASED ON: DELTA T BETMEEN 200.0 NN 33.0 FEET MIKD KEASURED AT: 200+0 FEET MIND THRESHOLD ATt ,50 KPH JOIN'I FREQUENCY DISTRIBUTION OF MIND SPEED AMD DIRECTION IM HQNS AT200.00 FEET SPEED (KPH) M KNE NE EKE E ESE SE SSE S SSM SM MSM M MN'M NM NKM TOTAL CALM 0

.51. 3.40 46 212 350 219 144 130 125 113 110 116 70 25 12 10 '11 9 1702 3.41- 6.70 158 637 336 135 90 79 105 118 162 218 336 1C2 64 30 47 41 2698 6.71.11.20 168 246 213 48 28 26 84 136 145 191 392 413 181 156 163 148 2738 11.21 16.80 45 58 38 6 12 7 19 31 65 98 186 376 135 60 54 79 1269 16.81 22.40 1 3 4 0 2 1 C 10 18 7 17 88 62 8 1 3 229

>>22.40 0 0 0 0 0 0 0 3 1 0 1 12 6 0 0 0 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 STABILITYCLASS PENNSYLVANIA PONER 8 LIGHT UNIPART (PPSL)

- Susquehanna Stean Electric Station 1/26/1996 'AGE 66 TINE OF DAY: 13:54:54 PROGRAH'FD VERSIONF PC 1.2 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: 0 TOTAL NOSER OF OBSERVATIONS IJITH BACKUP DATA: 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 DISTRIBUTION OF HIND DIRECTION VS STABILITY N NNE NE ENE E ESE SE SSE S SSM Ql llQI II NNN NN NNN 'CAUI A 2 19 39 9 5 5 11 14 29 46 156 114 8 0 0 0 B 11 26 21 5 8 5 9 10 12 35 69 60 17 2 3 4 0 C 14 31 23 5 8 9 13 14, 22 18 68 '83 38 17 12 20 ~ 0 D 20& 294 290 ~ 148 107 93 140 182 157 181 321 457 333 214 216 212 0 E 94 310 267 123 71 53 101 132 214 254,310 293 57 27 35 33 0 F 55 278 174 78 45 44 38 36 42 63 57 43 6 3 5 9 0 G 34 19& 127 40 32 34 25 23 25 33 21 6 1 1 5 1 0 TOTAL 418 1156 941 408 276 243 337 411 5D1 630 1002 1056 460 264 276 280 0 52

Page1 of 15 TABLE 22 AVERAGE ANNUALRELATIVE CONCENTRATIONS 8>avaaaa~ Ct~ tlaacala Ccaclva ~ NO&i'LEVEL &ELfdCE CZ&CECTED IN COCO Ttl&ll&&ECICCI&ATNNVCI&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

~

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~

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~

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~ ).0$ 'M I)

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~ I ZOM'Oa $ .9011 10 ).481% ~ ID l>296C 10 2.)LM'll ),)221 ~ 'It ).719C ~ I) ),76DC Ii

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~ I 2.5&II'08 &.ZOIC Oa ).Lidf'Oa I.bill'Oa I 'IT)I

~ ~ Oa i.&)TC'IO I OIIE'10 IAZM'll 2 $ 2&I 12 7 227%'I) cac I Ti)f'08

~ $ .60)c'oa Z.Bdc'oa I Sloe'Oa 8,410c 10 )A&lc 10 9.929C II 2.49il'll 4.1911 ~ 17 I.&LM'l2 9.479% Oa Z.IDCC'09 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 wliolac 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 ANNUALRELATIVE 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:

$ 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

$$V 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.

SV 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 lSV 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 V 4 )ASE'OF Lk)V t 2 8$ 5f'05 oeb))f'N 4.4$ CE 04 9>>K'Ob IAI?f 04 'I 0)5C~ Too)SE 07 5 04?E 07 ).741K 07 2.9OLK 07 ?.4?if 07 sv ?ASOE'05 8 901E Db S>>TE~ ),185K Ob I 744C& I,ODR& 7,400fi07 5,544E 07 4,21$ 07 l ) )'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 s 2.>>?f'05 4 4)at& ).576t Ob 2,?OR.DD I,tbff Ob 8,)tec 07 b,)OTE 07 4.SIDE 07 ).)$ ?f 07 2.714K 07 Z.?4?f 07 ssf 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 kf 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 Ctf 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

)

E 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 Klf 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 )

lf 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

$$K 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 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~

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 09 1.17af.ol T,T?iE.IO 4,?)of.10 ).559K ~ ID

)A)AE~ 10

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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 asl

).994K.OF 1,)?OI 07 4.46$ I CO )@DIE 08 7.785K 09

?.49R'DT 1,24TE 07 4,$ ?TE 08 I,CSCK N 7ATaf 09 2,4$ $ C 09

)~ 09 1,57?t 09 5.251K ~ 10 2.NZE ~ IO 1,$ 09f 10 I,NCE ID 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>>

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~ ) 7$9f'ID

~ 4~ Dilf'>>

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aav i,)FII De ~

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$1 9.0?SI OF  ?.9951 0) I.la)I Ot $ .?9)I 06 2.6>>1 08 9.'?Ill 09 ).Atef 09  ?.49?I ~ 10 ).85?I I I 4.$ ?ef I?

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~

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VIS) AKLIAIK ISOI VIV) SFKID IKII~ Illfe) Vfk) tILtAIC ICOK VIC) $ )CKD ISETltl/RC) VIIO CSEKD IICIftl/lte)

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Page 3 of 15 TABLE 22 AVERAGE ANNUALRELATlVE 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(ATIONul)40 SDECIAL n&KAIN AouSTIOIT TACTMS ANNVAL Av(CAct cNIFO (Stcncnf ()e(D) OI SIAN(t IN 1)LE$

SCCTN .$ 00 .750 1.000 - 1.500 2.000 2,500 ).000 ).$ 00 eAOC i.jO"

.2$ 0 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 5 I 104E 05 ) 9?bf ~

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 Z.ISOE'05 EvOI Lo(TE 07 4,244K 07 4.994( 0 4 4&M'0$ 1.44lE'05 Lbbft N 5 bbot M ) I)n~04 Z.Nn Oa 1,44LE 04 1.07$

~

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4.9)M'07 )A)tt 07

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$( 4AIef 04 I,Flit*04 1,009E Ob 4 jlDC'07 ) )jjt'07 2 079E 07 1,4(M~OF 'SANt'N 4 SLM'M 4'SMC'M )'579K'M 5 947K Ob 2,147C 04 I tbdt 04 7,4)n 07 ).Nil 07 2,)tbc 07 I,TSM'ol I,?bbf 07 9ottof'N 4.WE'M Slf A.oiiE'05 bawl( Avfticc callo ((cc)vert& cNED) 01$ )ANCE IN NILCS 5(it)ac - sAN r.joo Io.ooo ILooo to.ooo 25.000 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.>>

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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.>>

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( 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 10 ?0 to )0 )0 LO 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

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$ .4&D('Oe  ?.04$ ( 'Oe 9.)lr('OF $ .))bf '0) ).475( 07 I A9)t 07 ),t)$ ( 05 4.799( 09

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Page 4 of 15 TABLE 22 AVERAGE ANNUALRELATIVE CONCENTRATIONS Swrcrdwvre STO C IOOTVIA STATIC <<awr LEVCL CELCASK

<<DECAT, IEELETEDO CNEKCBTI lce Tete TlttAIO CfcltcNATIoa Idleo <<CEIAL Tfttila JUSTTCer TACTNS OISTAOCE Ie IIILCS Addle AVKCACC CAI/O CSEC/ICTCE ISCCDI

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)ALTK'07 ZASLE'07 I bat'07 Or I,otof 0.

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at 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 Eaf 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 K 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 Csf 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 cf 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 CIE S.OOIC 04 Z,TOOK@$ 1.249K 04 7A5LC 07 )AZ1C 07 t,scot 07 TASK 07 1,27Ã 07 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 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 >>

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~ e,otrt De 1,$ 1rl Oe F,WII 0r AAFFI Dr~

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I ll i

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Page 5 of 15 TABLE 22 AVERAGE ANNUALRELATIVE CONCENTRATIONS svvwevees sfew CL<<le f4 ffeffeeL Ncc) nc Do)sf la )cfcsfsf

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~ I VV ~ If <ef rf~ I > 0VIUIea Nloef Ief flog) 41 )

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Page 60f15 TABLE 22 AVERAGE ANNUALRELATIVE 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 7$ Q I QQQ

' $ 00 2>000 2>$ 00 3 000 3 500 4 000 4 '500 SECTOR 500 S 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 SQl 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 SM 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 MSM 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 Mxv 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 N 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 NNK 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 NE 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 Ekf 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 E 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 EBK 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 Sf 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 SSE 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) DISYANCE IN NILEB BKARINC 5.000 7 500 10.000 15,000 20.000 25 000 30>000 35>000 40>000 C5.000 50,000 5 8.40CE ~ 05 3>73ZE 08 1.899E 05 4.397E 09 1>963K 09 6.5HE ~ 10 3.6&YE 10 1.63TE.IO 1.084E ~ 10 &,NIE~ 11 S.HOE ~ 11 BSV 1.720E 07 7 845E 08 4,286K 05 1>3&YE.N 6.146E 09 2.2686-09 1 ~ 119K.09 3.767E 1D 2.HIE ~ 10 1.NIE.IO 9.386E 11 Ql C.31&E.OT 2.129E.DF 1.169K.07 3.500E.06 1,760E 08 7.9626.09 4.666K 09 2.C766.09 I 709E 09 9,805E ~ 10 5.579K 10 MSV ).398K 06 7 311E Ol 4 052K 07 I 1STE 07 5 409f N I 9536.08 1,069E N 4.088E 09 2>316E 09 l>DOCE 09 8,634K ~ 10 V C.899E.DT 2.325E 07 1.259E.OT 3.522K 08 1>CHS. 06 4 155E 09 2>30$ E 09 d,123E ~ 10 4>$ 73E ~ 10 1.97OE.IO 1..725K ~ 10 2.731E 07 I ~ 392K 07 'F.809K 08 2.691f >06 I ~ 249K.05 4.739E.09 2.060E.09 3.1S9E 10 1.7llf 10 d.080E>11 5>306E 11 NV 2.955E 07 I.S336.07 6.QTE 06 3>04CK 08 I ~ 291E.05 3.930f 09 1.676E 09 4,509E 10 2.dl5E ~ 10 I.IC1E 10 9,89CE 11 NXV R.NTE Dl I.S27E.07 5.468E ~ 08 2.626K 08 1>226E 05 4.07CE 09 2.498K 09 l>400E 09 8.425K 10 4.CITE 10 3>8276.10 N 2.699E 07 l>895E 07 1.011E 07 2 795K ~ 06 1 377K 06 6 263K 09 3.'lslf 09 1 101E.09 6.367K 10 3.015E.10 2>QOE '10 NNK 3.370K Dl 1.817E 07 9.860K 06 3.0ZZE.08 1.354K 05 4.980E 09 2>765E 09 I.ZTFE 09 5.166K 10 'C.NSE.IO 4>232K 10 Nf 2.COSE Dl 1,329E 07 7.623E 08 2.HPE 08 1,256K 05 3.891K 09 2.149E D9 9,660E 10 5.699K ~ 10 3. WE-10 2.769K.IO Exf 1.3dlE'Dl 7 $ 12E 06 C.TF5E 06 2 35CE 06 1.253E 05 6,699E 09 3,TRSE 09 1,711E 09 1.062E 09 5.600E 10 5 002E '10 E 5.500E N 2.843E 08 1.599K 05 6.00bf-09 3.0rsf.09 I.S93E 09 d.073E.IO 3.140E.IO 1.870E 10 9.706E.II b>339K 11 Elf 3.075E 06 1,280K 08 T,ZCCf 09 2.7966.09 1.47lE 09 6.110E ~ 10 3>639K 10 1,060E 10 5.609K ~ 11 2.CASE ~ 11 2.096E 11

'Sf 2.907K N 1.096E 06 6.246K 09 2.436K 09 1.0ZIE 09 3.274E ~ 10 '1.6156 10 5>640K 11 2.675E 11 6.051E.l'2 6 891K 12 SSK C.OC3E.Q5 1.6076.06 6.9696.09 3.3SZf 09 1.C$ 9f 09 S.lsbf ~ 10 2 &42K 10 1.056K ~ 10 6.241E 11 3.1&CE ll 2.72RE 11 Cxl/0 Isf C/NElfR CUBED) SOR EACH BECNENI SEQIKNI BIAXOARIES IN MILKS DIRE CY IIXI .5 ~ I 1.2 2.3 34 . Cs 5 ~ 10 lb.20 20.30 30 F 40 40.50 IRON SITE 5 2.269K -Db 7.886E Dl 3>33RE>DT 1.722E.DT I. 0)bf . 07 3.956E 05 6.5$ 6E 09 8.991E ~ 10 2>006K ~ 10 7.701K ~ 11 SCV C.DTBE>06 I.S03E ~ 06 6.829K 07 3.$ 5OE ~ Dl 2.117E 07 6.342E. N I 651K 05 2.643K ~ 09 5.424E ~ 10 I.CSBK ~ IO SV 8.695E.06 3.242K.06 1.49SE 06 5.33 1f .07 5.219E 07 2. INK.07 C.54&E 05 9 220E 09 2.dlDE 09 I 151E 09 MLV 2.155E 05 8.$ 31E.06 4.266E Db 2.C7SE Ob 1.6C9E.06 7 345K 07 1.52FE 07 '.521E 06 5.300E 09 1.346K>09 V 1.088K 05 3.6SOE.06 I.&35K.06 9. 041E ~ Ol $ .664K.07 2AZSE>OT 4.635K 08 6.2NK 09 '1.1DCE 09 2 651E ~ 10 VNV 5.323K Qb 1.9RRK 06 8.735E.OF 4.93lf Dl 3.253E Dl 1. 416E. 07 3.1676.05 5.734K.09 7.613E ~ 10 9.239K 11 S.TDCE.DC 2.NCE Db 9.C66E.OF 5. Cl I . 07 E 3.57CE.07 I S$ 5E 07 3.SDSE.06 5.$ 03E.09 7 968E 10 1.539E ~ 10 NXV 4.694K Ob 1.909K.Qb 6.62RE.OT 4.614 E ~ 07 3.284E.OT 1. $ 09E. Ol 3.369K 05 S.QYE.O9 1.SORE 09 5.3676 10 N C.DRTK.Ob 1. 517E ~ Qb 7.6CIE Ol C.C2FE Ol 3.050K.OT 1>NIE 07 3.791E 05 r.ORQK-09 I.SOCK 09 3.663K 10 NXI 5.472K.Ob R.066K Ob 1.003K 06 5.513E.Ol 3.9$ CE 07 I 7HE 07 3.800E.M 6.3856.09 1.534K 09 5>621E ID NK 3.766K.bb 'I.CDIE Ob 6.53FE Ol 4.056K Ol 2>dlRE OT I 316K OT 3.232E 06 S.SOSE.09 1 161E 09 3 5396 10 ENE 2.13DE Ob 7.836E ~ 07 3.719K Ol 2. 283 E ~ Dl 1.61$ E Dl 7 TOBE 06 2.C03E>05 7>131E 09 2.039K 09 &.HCE.ID K 1.25'IE 06 4.132E 07 1.510E 07 1. DOC E. Ol 6.S5$ E N 2.NIE M 6.922E.D9 1.673E.09 4.06&E 10 I ~ 166E 10 68

Page 7 of)5 TABLE 22 AVERAGE ANNUALRELATIVE CONCENTRATIONS ESE 9.8438.07 3.13SE 07 1.256K 07 6.605K 08 3.867E 08 Io432E 08 3,198K 09 8.177K 10 1 671K ~ 10 . 3.'513E ll 1.413E.07 6.781E 08 3.723E 08 1.289K 08 2.d54K 09 4.4$ 9E-TO 7.6$ 6E-11 1.575K-ll SE 1.009E 06 3.509K 07 4.137E 07 1.791E 07 9.3ME 08, 5.189E 08 1.8348~05 3.763E 09 6.665E.10 1.345E ~ 10 3.912K 11 SSE 1.250K 06 VENT AND BOILDING PARAHETERS:

(NETERS) 9 60 REP VINO HE IGNT (NKTERS) 10,0 RELEASE HEIGHT D IAHETER (HETERS) F 00 BUILDING HEIGHT (NETKRS) d1.3 EXIT VELOCITY (H/SEC ) .00 BLDG.IIIN.CRSoSEC.AREA (SOeHETERS) 2575+0 NfAT ENI SS I ON RATE (CAL/SEC) 0 AT THE RELEASE HEIGHT: AT THE EAASIXIED MIND NEIQlT ( 10+0 NKTERS):,

VENT RELEASE NCOE VINO SPEED (HETERS/SEC) VENT RELEASE Ikef IIIND SPEED (llETERS/SEC) VINO SPEED (HETERS/SEC)

STABLE COSITIONS ONSTABLE/NEIITRAL CONDITIONS I

ELEVATED LESS THAN +000 ELEVATED LESS 'INAN 000 LKSS THAN ,000 000 AND 000 I NIXED &KTNEEN,DOO AND,OOO BKTIJKEN .000 AND ,000 NI XED BETOKEN ~

CROWD LEVEL ABOVf +000 GRRIND LEVEL ABOVE,000 ABOVE .000 59

Page 8 of 15 TABLE 22 AVERAGE ANNUALRELATIVE 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 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?

SSV 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 SV VSU 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&

U &.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?

Wll. 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?

NV 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?

NNV 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 NNE 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?

NE 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 EN'f 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 E 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

~ ESE 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 SE 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 SSE $ .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 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 SSV 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 SV 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 VSV 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 V 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 IAIV 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 NV 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 N 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 NNK 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 Na 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 ERE 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 f 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 Esa 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 Sf 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 F. ~ 1 2 Slf 3. 954 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 cHI/0 (sa C/KEIER CUS(D) FOR EACH SKGKKNT SEGKKNI ROVNOARIKS IN KILES DIRKC'I ION .$ .1 1 2 2.3 3 4 4 5 5.10 10 20 20.30 30.40 40 50 Ft(tl Sill S 2.26RE 06 T.SCIE 0? 3.209K.Q? 1. 695K '0? 1.01?E D? 3.846E N 6<<231f 00 5.170E 10 1.745E 10 &A15E 11 SSV 4,06JE Qb I:C92a 0& 6.?44'E 0? 3.Cd?E 0? Z.060K-o? 5.046K 05 1 570K 05 2.515K 00 4.5$ 4E 'IO 1 15?a 10 SV 5.6$ ?E Od 3.21CE 06 I.C73f Ob d.lS?f 0? $ .0?SK.O? 2.006K 0? 4.106K 05 7.0?JK 00 2<<'RSOE 00 S.TS&E 10 VSV ZACSf 05 S.CSIE'06 4,200E 06 2.C2of 0& ,1.&02 E <<ob 7.015E 0? l.coca-or R.t?sf 05 4.201K 09 I OZQE 09 V I.OQE 05 JA15E.Q& 1.609f Ob 8.83?a 0? 5.60CE 0? 2.315(. O' C.264E 05 S,etta 00 8.901E '10 1.002K 10 5.209E Ob 1,904E 06 S.S9?a 0? 4.82?E 0? 3.1&DE 0? 1.355E.07 2.9Zbf 05 C.944f 09 6.20ZE 10 6,981K 11 S.bbof 0& 2.0&SE Ob 9.3C7K 0? S.JSSI 0? 3.4?5E ~ 0? 1.40JE OF 3<<ZJSK OS 4.799E 09 &.sd7K 10 I ldtf 10 NNV 4.5?C\.06 1,50JE 0& S.SORE'0? C.?10f 0? 3.200E 0? 1.449E OF 3.124E N 4.923E 00 I ~ 235K 09 4.1?3f.lo H C.QIIE 06 1,50CE. 06 7.534E.D? C.JCQE ~ 0? 2o073E 0? IA12E OT 3.$ 22E 05 6.14tf 00 1.24&E 00 3<<00?E ~ 10 NNK SAsta 0& 2 0?RE 06 0.001E 0? 5.?NE 0? 3.Seta 0? 1.725E 07 3.553E.N SAQE.09 1 290E 09 4.CTZE'IO NI 3. 75?E. 0& I 303E 06 6,??OE 0? 4.00ZE.OT Z.rezf.or 1.2?9$ .07 3.065K 05 5. 02?f -00 1.01?f 00 3.2285.10 ENE 2.12$ f.o6 7.709K ~ 0? 3.&SSE.O? 2.257'? 1 Solf 07 T.stsa 05 2<<203K 05 &.SNK-00 1.525E 09 5.09&E ~ 10 f 1>2C9E 06 C.114E 07 1.?9&E OF 9.9JIE 05 6.464E 08 2:817K.OS &.QJE <<00 'I.SStf-09 3.655E 10 1.031K 10 60

Page9 of 15 TABLE 22 AVERAGE ANNUALRELATIVE CONCENTRATIONS ESE 9 821E 07 3.121E 07 1.246E.07 6.533E 08 3@812K 08 IAOE 08 3 059K 09 7 565k 10 Io501E>10 2 867E 1'I SE 1.007E 06 3.496E.07 1.405K 0/ 6.722E 08 3abdOE.08 lo267f-08 2+564K 09 4+200K ~ TD 7.022E ~ 11 1.228K ~ 11

'SE 1.247E-06 4oT20E 07 'l.778K 07 9.263K 08 5 ~ 121E 08 1.796K 08 3od15E.09 6.215E.10 I o216E ~ 10 3.41df ~ 11 VKMT AXO SUILDIMC PARAMETERS:

RELEASE HEICHT (METERS) 9,60 REP. VINO MEICHT (METERS) 10.0 DIAMETER tkETfRS) +00 BUILD INC NE I CHT (NETERS) 61,3 EXIT VELOCITY tH/SEC ) .00 BLOC.IIIM.CRS.SEC,AREA (SO.METERS) 2575.0 NEAT ENI SS ION RATE (CAL/SEC) 0 AT TNE RELEASE ME!CRT:

I AT TNE NKASLNIED VIXD NEICHT ( 10.0 METERS):

VENT RELEASE IXOE VIIO SPEED tNETERS/SEC)

I VENT RELEASE IMNE VINO SPEED (ItETERS/SKC) VINO SPEED (METERS/SEC)

I STABLE CONDITIONS UNSTABLE/NEUTRAL CONDITIONS ELEVATED LESS THAN .000 LESS TNAM 000 LESS TNAM .000 I

MIXED SETVEKN 000 AMD 000 I SETVEKM ~000 AMD 000 SETVEEM +000 AXD F000 CR(AXO LEVEL ABOVE .000 ABOVE . 000 ABOVE ~ 000 61

Page 10 of 15 TABLE 22 AVERAGE ANNUALRELATIVE 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 ).OCIE.05 3.$ 90E 06 2 0028.06 1.270K.06 6.413E.OT 3.973E.OT 2.704E 07 I.BC7E 07 1.307E.07 9.911E 08 7.67)E 08 SSV Z,Q7$ E 05 d.C)PE 06 3.6$ )E 06 2.257K 06 ) ~ Zbdf 06 8.005E.07 5.592E 07 3~825K 07 2.686K.07 2.033K 07 1.5STE ~ 07 SV 4,437K.os ).339$ .05 7.749K-ob 4.976K 06 2.677E 06 1.714K.ob 1.215K 06 Bodrsf 07 6 37bf 07 4 OTIE 07 JobsJE 07 VSV 1,0878.04 3.259E 05 ).9)df-os I.zroE 05 Teoorf 06 c.720E 06 JesZSK 06 2.537K 06 1.875$ .06 I.S03E.06 1.230E'06 V 6.17OE 05 1.QbE 05 9 31$ E 06 5,74)E 06 2.974E 06 ).$ 9)f-ob 1.327E 06 9.JTSE 07 6.Q4$ .07 5.423K 07 4 365K'07 VMV 2.8$ SE 05 B.d)3E 06 4ASIE-06 2.911E.06 l.d12E 06 1.015$ .06 7.015$ .07 S.042E.OT 3.76)f-or 2.99CE.OT 2.C24E.07 MV 2,8$ 0E.05 8.90)E 06 5.))rf 06 3.115t.06 1.744E 06 1.095E 06 TAOOE 07 sisCCE~OT CiZ)sf+or 3.313K 07 RibSCE 07 NNll 2.182E.05 TeZTOE 06 4 281E ~ 06 2.9OOE 06 1.5STE ~ 06 9.962E-OT Tao)bf 07 4.9488 07 3.607E-OT 2.955E.OT 2.4688-07 N 2.112E.05 6.434K 06 3.S78K 06 2.203E 06 1.26$ E Ob B.SZOE.DT doJDTK 07 4 SIDE 07 3.352f 07 2,716E 07 2 242E 07 NNE 2,C79E.OS I.C73E 06 4.739K-ob 3,2)CK 06 ).690$ .06 ).)Zbf 06 Be245$ -07 5.90$ E.OT CAOSK-07 3.579E.OT 2.965K.07 NE ) Issf 05 5.936E 06 Jo359$ .06 2.095E 06 ).ldof 06 T.drBE 07 5+SIZE 07 4,067E 07 3,094$ .07 2;534E-07 2,1)IE.OT ENE ).OOCE.DS 3.31$ E 06 1.86)E 06 1 ~ 232E-06 6.30)E ~ 07 4.147E 07 J.DISK.07 2+252K F 07 1.752E 07 1.C46E OT ).ZZZE~OT E 6.046E 06 2.053E 06 1.114E 06 6.5888.07 3.364E.OT 2.113E 07 1.466K 07 ),0388 07 7.6SIE 08 6.05SE 08 4.908E 08 ESE 4.940$ -06 l.d)2$ .06 8,789$ -07 5.)TJE-OT 2.55ZE-07 ).SZOE-OT 9.9$ )K-M T.OOZE-M 5.)ZOE.OI 3.786K-M Z.BSDK.M SE C 562K 06 1 564K 06 9 002f Q7 5 TJbf 07 2 l57E 07 1 728K 07 I ~ )COE~DT TosTJE M 5+) JIE 08 J.rlbf 08 2.728E M Btf 5.669$ -06 1.99PE.06 I ~ '130E-06 b.d95E 07 3 326K 07 2.100E-OT 1.461E 07 1.012E 07 7.2$ SE 08 5.220E 08 3.774E M ANNUAL AVKRACE CHI/O TSKC/HETER CUBED) D')STANCE )N NILEB BfARIMC 5.000 7 SDO 10,000 15.000 20.000 25 000 30,000 35,000 40,000 Cs.ooo So.ooo B 6.229K 08 2.608K 08 1.261E 08 2.687K.09 I.)ZDE.OO 3.69OE 10 IA67$ .10 7.92$ E ~ 11 5.01)E ~ 11 3.046E.)1 2.$ )bf ~ 1 I SBV 1.273E.07 5.470E.OS 2.QTE.OS 8.3'11E 09 JoCQE'09 1.20OE 09 SA40E 10 I BISE.)0 1.1$ 5f 10 4 '13E F 11 3.920E 11 SV 3.)IOE.OT IAI)E 07 7.715K 08 2 120E 08 9 PZZE'09 4 ZZTE 09 2 334K DO 1 )Tdf 09 7 724E 10 C.ZJOE 10 J.S39E 10 V)V ).OJJE 06 S.DICE 07 2.67)E 07 7+DO)K)M J.OCbf 08 ).ORE M S.JJIE 09 ).PJbf OO T.OC4E.OO 4.3)bf 10 3.634K 10 J.d)bf ~ 07 ).6)df 07 8.302E 08 2.130E 08 I.JOIE 09 2.)OCE 09 )o)SOE.OO J.ICZE ~ 10 R.osbf 10 8.459K 1'I T,MZE 11 VNV 2.017E 07 9.679K 08 5.15DE 08 1.628E OS 7+DZSK 09 2.504K 09 )+028K OO 1.495E 10 7.975E ~ 11 Zeb)JE 11 2.)bof 11 NV 2.20bf.or 1.067E.07 S.d97E ~ 08 1.844E 08 T 2QE DO 2.0QE 09 9 405K 10 2,286E lo )oZ)lf 10 4.927K 11 4.089K F 11 NNV 2.075E 07 ).064K 07 5 S96E.OB I 71$ E 08 6,927K 09 2.163.09 I 254K 09 b,d72E ~ 10 J.IZ4f-lo 1.914E 10 I.SBTK ~ 10 N 1.996E or 1.320K 07 6AISE M 1.696E 08 7 785E OO J.JJIE QO 1,572K 09 5 2$ 1E 10 2.892K ~ 10 1.3OOE 10 I Mbf 10 NNL 2.493K-or 1.267K.OT 6.527K.ob ).Qbf Ob 7 674E OO 2ASSE 09 )oCObf 09 6.119E 10 '3.74)E 10 2 ~ 133E 10 1.771E.)0 Nf 1.783K 07 9,29ZE 08 5,063K 08 1.796E ~ 08 T.lbbf.09 2.09ZE.09 I ~ 095K.OO Cebbrf 10 2.734E.IO )oC)bf.)0 1.179$ .10 ENT 1.029E 07 5.25$ E F 08 3. )TIE Ob ).443E 08 7.179E OO 3.727E OO ).POPE'09 8.3$ 5E ~ 10 C.Obof Io 2.$ 9$ E ~ 10 2.150K ~ 10 f 4.MZE 08 l.991E.OI 1.065K 08 3.68$ f OO 1.76ZE 098.blsf 10 4.142E ~ 10 I.S35E lo $ .738K ll C.348E ~ 11 J.SME ~ 11

'Etf 2.28ZE F 08 8.96$ E 09 4.$ 22E OO 1.71$ E OO $ .462f 10 C.JQE 10 1.968E 10 5.17$ E ll 2.71lf ~ 11 ).DOCK ~ 11 9 004K.)2 Sf 2.1$ 9E 08 7.68$ $ IS 4.165K.OO 1.499E OO $ .$ 7ZE lo 1.778K 1D IoJZTK ll 2.871E 11 1.35ZE ~ ll 3AJJE.IZ 2.PIPE 12

$ )f 3.001E ~ 0$ 1.12$ f'OB $ .987K OO 2.0$ 7f OO 8.372E ~ 10 2.791E 10 1.357K 10 5.1$ 1E ~ 11 2.92ZE 11 1.42OE.11 1.17CE 11 CNI/O ISE C/HETER CUBED) fOR EACH BKCNENI SKCNENI BOUNOARIES IN IIILES DIR fCI I ON .5 ~ I 2.3 4.$ 5.10 10-20, 20 30 JO.CO Coiso fkOH Sllf B 2. 029f . 06 6.726E 07 2.70OE ~ Or I 34)E 07

~ T.bool.ob 2.$ 14E M 4.195E.09 4.963K 10 9.BISE-ll 3.C33E.II t)V JACTK ~ 06 l,zrof.ob $ .$ RBK or 2.762K'Dr 'I.SOSE Or $ .9)ZE 0$ ).062K 08 1.557K DO R.bsbf.)0 6.44$ E 11 BV 7.77)E.ob 2.76of . 06 1.209K Ob 6.C75f or 3.920E Or 1.545K ~ 07 2+862K ~ 08 4.988E DO ).JSJE OO 5.009K 10 V)V 1.92bf 0$ 7.257E.O6 3.449K Ob ).923K.ob 1.23$ E 06 5.)TIE~or 9.627E. 08 1.3TDE-M 2.568E 09 S.MQE 10 V 9.73rf -Ob J.lobf Ob I JZZf.ob 7. 023K ~ Of CADRE 07 1.7)ZE or 2.928E 08 3,431K DO 5.349K.lo ).)SCK.)0 lhlV 4.76)f Ob 1.QCE.Ob 7.063K or 3.Q5E.OT 2.C42E 07 O.OOBE 08 1. 999E. 08 3. 12OE. OO J.TJOE 10 4.04'IE F 11 NV 5 ~ OOOE Ob 1.776E Ob 7.6TZK.OT 4.2$ )f 07 2.684K Or 1.099E 07 2.20CE M 3. 012E. IS 3.9IOE 10 6.744E.)1 NNV 4.371E-ob 1.62bf Ob 6.975f.or J.rczf-or R.cbrt.or 1.064E 07 Zo)ZJE 08 3.070K OO 7 2QE 10 2.3S'Of F 10 N 3.602K.ob 1. 29OE 'Ob 6.178E or 3.cclf or 2.291E 07 1.'IIIE 07 2.397K 08 3.$ 17E 09 7 JCCE 10 )A96E 10 NNE 4.891E.Ob 1.778K 06 8.113E Or Co SZOE'07 2.972E 07 'l.266E-07 ZoCOCE 08 3,49CE 09 ToCQE ~ 10 2.C75E ~ 10 Nf 3.370K.ob 1.193E 06 5.53$ E Or 3.1SPE 07 2.117K.OT 9.310E 08 ZiOCJE 08 J.OCTK 09 seTJJE 10 1.'7'l9E-10 f'Nf ).Oosf 06 6. 681E. Or 3. 011E '07 1.778K ~ 07 1.217K 07 5 ASlE.OB 1,$ 06E.OI 3.92) E. 09 )oo)JE 09 3.)JIE ~ 10 f 1.)ZOE 06 3.524E 07 l.cb7E.OT '7.824E.08 4.942K M 2.0C4E 08 CoJTIE.OO OoZZIK 10 Zoofbf ~ 10 $ .367K-))

62

V Page 11 of 15 TABLE 22 AVERAGE ANNUALRELATlVE CONCENTRATIONS ESE 8.811E 07 2.87bE 07 1.018E.07 5.149K-08 2.917E 08 1,020E OS 2.019K 09 4 505K 10 8,380K 1'I 1.501E ~ 11 SE 9.0258-07 2.995K 07 1~ 147E 07 5.293K 08 2.81'IE.OS 9.211E 09 I.ddbf 09 2.492E 10 3.852K II 8.32df.12 SSE 1.118E Od 3.530E 07 1.452E 07 7.299K 08 3*9188.08 I 308K 08 MS'.09 3.70bf .10 8.718E 11 1.774E 11 VENT AND BUILD INC PAkAHKTERSI RELEASE HEI CRT (NETfRS) 9eb0 RfP UIND NEICHT (NETERS) . 10.0 DIANETER (HETEkS) .00 SUILO INC NE I CHT (HETERS) d1.3 EXIT VELOCITT 01/SEC ),00 SLDCoNIN ~ CRSoSEC.AREA (SOokfTERS) 2575.0 NEAT EN(SR ION NATE (CAL/SEC) o0 AT THE RELEASE NEICH11 AT THE NEASURED UIHD HEICNT ( 10+0 HETERS)I I

VEkT RELEASE HCOE UIIXI SPEED (NETERS/SEC) I Vfkl RELEASE IHXIE UIND SPEED (NETERS/SEC) VIND SPEED (NETERS/SEC)

STASLE C(HH)ITIQIS UNSTABLE/kEUTkAL CONDITIONS I

ELEVATED LESS THAN ~ 000 I ELEVATED LESS 1NAN 000 LESS TNAN .000 Nl XED HETMEEN .000 AIS,OOO / NIXED kfTUEEN 000 AIO 000 SETMEEN +000 ND .000 CR(XNO LEVEL ASOVE ~ 000 CR(XMD LEVEL AHOVE,OOO AHOVE .000 63

P Page 52 of 15 TABLE 22 AVERAGE ANNUALRELATIVE CONCENTRATIONS SvvPIehacw St~ E lect I Ic Stbtien ORIANA.LEVEL RELEASE ~ 1995 CORRECTED FOR OPEN TERRAI N RECIRCULAT ION USINC SPECIAL TERRAIN ADJUSTMENT FACTCRS RELATIVE D EPOSITIOI PER UNIT AREA.(Nee 2) AT FIXED POINTS 8T INAAOIIND SKCTORS D IRKCT I ON DISTANCES IN NILES FROI SITE .25 .50 .75 1.00 1.SO 2.00 2.50 3.00 3.SO C.OO 4.$ 0 6,1$ 6E 08 2.162E 08 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

~

S 6.207E 05 2.739E. 08 1,493K 05 $ .7856.09 4.5718.09 2e726E 09 Te61?fe09 1.189E 09 d.0$ 6E 10 S.OOSE 10 4.COOfe10

~

SQI 1.025K 07 J.SOCE.N 2.024EeN I.ZCJE-N 6.139Ee09 3.6$ 4E 09 2.4238-09 I ICTE-DO d.477Eelo 6.405Eelo SV VQI 1.436E. 07 5,107E 05 3 170E 0$ 2 035E 05 'I 028E 08 6 340E 09 4e341E 09 2e910E 09 2e023E 1edJTE-09 ~

I 1 539K 09 1 ROIS OO V 1.021E 07 3.496K.N 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 5.74?Eebb 1.9496.08 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 NV b. CSC E.08 2. 6596.0$ 1 566E 0$ 9 223E 09 4e6QE 09 2e743E 09 1 $ 12E 09 I R68E 09 9e30bf 10 7 092E 10 Se525E 10 2.596E 06 1.445E.05 9.S25E 09 4.$ 53849 2.7428.09 1.6408 09 1.246E 09 6.77SE 10 6.972E 10 $ .667Ee10

~

7.215E 05 N 7.151K 06 2.396E 05 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 NNK 9.489E.N 3.540E 08 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 NE 1 ~ 377E 07 4.742E 05 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 ENE 9e313E.06 3.1QE.08 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 E 5.327E.N 1.609E.N 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 ESE C,OJIE 06 1,295E 05 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 SE 4.312E 05 '1.446E 06 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 SSE C.716E 08 1.669E.08 d.9SSE 09 5.056E 09 2.3698.09 1.449Ee09 9.7Sbf 10 6.S7SE.ID 4ADIE 10 3eZC28.10 2.300E ~ 10 DIRECTION DISTANCES IN NILES FRCH SITE 5.00 7.$ 0 10e00 15 00 20 00 25 00 30e00 35 00 40e00 4500 SO 00 S 2.S$ 6E 10 1.009Ee10 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

'SV 3.5OCE-10 1.3556.10 7 090E 11 ZeOOJE 11 6 NIE 12 2 TDOE 12 le226E 12 3 836K 13 ZeJbdf 13 9 S3DE 1C 7 775E 14 5.129E 10 2.128E.10 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 VQI 9.675K 10 4 el?36.10 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 V 4.122K 10 1 QJE 10 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 2.7$ 2E '10 1,203K 10 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 NV 4A61E 10 I OOSE.IO IeDSCE ~ 10 3 3026.11 1.260K 11 3e491E.12 1.93' 12 3eQSE ~ 13 1.56CE ~ 13 7.$ 26E 14 6.143E ~ 14 NNV 4.649K. 10 2.202E 10 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 N 4.552E 10 2.7QE ~ 10 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 NNf 6.46CE 10 3. 029K ~ 10 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 Nf 9.648K 10 4.659E.10 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 ENE 7.1CCE.10 3A6SE 10 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 E 2.601K 10 1. 210E.10 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 ESK 1.3466 10 S.080E ~ 11 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 Sf I.CIGK.10 S.OQK ~ 11 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 SSK I.TOTE 10 b. 406E ~ 11 3.44SE ~ 11 I.ITOK 11 4.72lf.lt 1.546Ee12 '7.364Ee13 Z.TTZEe13 1.540K ~ 13 7.379K ~ 14 6.0236 ~ 14

~ eeeeeeeeeeeeeeeeeeeeeeo RELATIVE DEPOSITION PKR UNIT AREA {Ne ~

21 51 DOVNVIND SKC'IORS eeeeeeeeeeeeeeeeeeeeeeee SKCNKNT SOINDARIKS IN NILKS DIRECTION 5~1 1.2 2.3 J.C '

' 5 ~ 10 20.30 JO.CO Coe50 SROH SITE S 1.165 E ~ 08 3.C60E DO I.?63E.DO 5.699K.10 3.273E ~ 10 1. 122E ~ 10 l,dZOE. I I 1.648E 12 3.53SE.13 1.186E 13.

SQI 1.C97E N C.bbbf OO 1. 607E. OO 6.333K.IO 4.$ 1$ E 10 I.SSSE 10 2A02E 11 3.545E ~ 12 $ .690E IJ 1 eJDE. I3 sv 2.0066.06 6.QZE OO 2.Q7E 09 1.173K.OO b. SCTK ~ 10 2.3?bf ~ 10 3 546K ~ 11 5.964E ~ 12 1.46$ E.12 $ .1$ 5E ~ 13 VSv 3.0Obf ~ 06 1.077E 08 4.30?f DO 2.092K OO 1.215K.OO 4.437E 10 TeblbE 11 6.612K el? 1.4$ 1E 12 J,DSJE 13 v 1.84OE N S.JOOE OO 1.919E DO 9.NJK 10 5. 219K ~ 10 1.619K 10 2.7STE.11 2.6QE 12 4.0lbf.13 5.197E 14 vvv 1.054K 08 3. 216K ~ 09 I.ZOJK DO S.OOTK . I0 J.Cblf 10 1.296E 10 2.3CSE.11 3.3?tf.12 3. 719E.13 3,760E 1C Nv 1.567E ~ 06 4.616E.OO le643E OO OA?6E ~ 10 $ .603K 10 2.129E.IO 4.0036.11 5.136E ~ 12 6.3096.13 1.0376.13 NNv 1.Cbtf ~ Ob 4.8$ 3E OO 1.643K.OO 9.142K ~ 10 $ .677K ~ 10 2.278E 10 4.28CK.11 5.826E 12 1.303K ~ 12 4.062K.IJ

1. ZTTE ~ 06 3.979K DO 1.660K DO 6.609K 10 5.376K ~ 10 2.546E 10 C.6SbE ~ 11 7 176E ~ 12 1,JOSE,IZ 2.666E.13

, NNE 1.933Ee06 b.'ICSK 09 2.46?f OO 1. 279K ~ OO 7.919K 10 3 ~ 133E ~ 10 5eS92E 11 7.60CE 1? I.S376.12 4.6$ CE.13 NK 2.56?f N 8.201K DO 3.44bf . OO 1.64tf.OO 1.173K DO 4. 839K . I 0 1.011E ~ 10 I.CZSE ~ 11 2.S25E ~ 12 T.ttlf D EKK 1,7CSE'N $ .603K DO 2.336K 09 1 . 310K . OO 6.610f 10 3A626 e10 9.929E ~ 11 2.C94E ~ 11 6.191E.12 1.5QE 12 f 9.C7OK OO 2.7Nf OO 1.0Clf.OO S. 27TE ~ 10 3 ?06E ~ 10 1,273K ~ 10 2 A91E. I 1 S.S$ 6E 12 1, 166E ~ 12 3.0Slf.13 EST 6.606E 09 1.65CE 09 6.6CTK.10 J. 207E ~ 10 1.752E ~ 10 5.924E 11 1. 1dlf e 1 1 2.575 E-12 4. 691E.13 6.207E.14 SK 7e966E DO 2.C2SE DO 6.6STK 10 3.8ZCK ~ 10 1.9QE.10 6.2COE.11 I 1CJE 11 1 6836.12 2. $ $ 1E.13 C ~ 110K 14 SSK 6.95$ E DO 2.$ 71E OO 9.746K 10 4.6CTK.10 2 JOSE 10 7.660E ~ 11 1,366K 11 Ze0696.12 3.620E ~ 13 9etSJE 1C VENT AND RUILDINC PA RANKTERS:

Page 13 of 15 TABLE 22 AVERAGE ANNUALRELATIVE CONCENTRATIONS RELEASE NEI CRT (NETE Rs) 9 d0 lfP UIND Nf'ICNT (NKTEls) TO.O 0 IANETER (NETERS) ~ 00 SVILDINC NEI CRT (NKTEls) d1o3 EXIT VELOCITT (N/SEC ) 00 RLDC.NINeCkseSECoAREA (SOoNKTKRS) 2$ 73e0 NEAT KNISS ION kATE (CAL/SEC) e0 AT TkE RELEASE NEICNTI

) AT TNE NEAR%ED UIND NEICNT ( 10.0 NKTERS)I VENT RELEASf NCOK UIND SPEED (NETKRS/SEC) )

- VENT lELEASE N(OE UIND SPEED (NKTERS/SEC) UIND SPEED (NETERS/SEC)

) STASLE C(NOITIONS UNSTASLK/NEUTlAI, CONDITIONS ELEVATED LESS TRAN .000 I ELEVATED LESS TRAN .000 LESS TRAN .000 NIXED SETUEEN ,000 ANO,OOO NIXED f

~ TUE EN 000 AIO +000 Sf TUffN,OOO AND 000 CROUND LEVEL ASOVE .000 Ck(XNO LEVEL ASOVE e000 ASOVE . e 000

Page 14 of 15 TABLE 22 AVERAGE ANNUALRELATIVE CONCENTRATIONS 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 UNOEPLETED 'ROfPLETED DEPLETED S SITE RCRNOARY S ,3C S49. 6.691E.06 dA52E.06 6.240E 06 3.820E 06 S SITE 6IRNR)ARY SQI .42 d70. 9e441E.06 9AZIE 06 8.709E 06 3.722f 08 S SITE RIXNRIARY QI .62 1315. 7obHE 06 7ASSE.06 6 6IIE 06 1.7d7E 08 S SITE QSNDARY VSV 1.22 1965. lo096E 05 1.055E. 05 9,4C2E 06 1A52E 08 S SITE 8IRNOARY II 1.02 lbC9. d.349E 06 6.306E.06 5.$ 38E 06 1.016E 08 S SITE SXINDARY IANI .62 992. 7.137E.06 7.105E.06 6.4238.06 1.4C3E 05 S SITE 8CINNIARY NV ,64 1037. 6.813K 06 d.787E 06 6.115E 06 1.9)36~08 8 SITE 8IANOARY NNV .59 d.3SSE 06 6.334K 06 5.736E.06 2.002E ~ 08 S SITE DIAIKDARY N 59 951. 5.6646.06 Sodddf 06 5.131E 06 1.566E ~ 06 8 SITE RCANOARY NKE .79 1266. 4.6535.06 4 663K 06 4.334E 06 1.664K 05 S SITE IMRNKIARY NE ~ 70 1121. 4:191E 06 C-179E.06 3.7C7E 06 2.551K~M

$ SllK 60NOARY EKE .87 1398. 1.6968.06 la693E 06 1.499K 06 1.33SE 05 S SITE RCUNOAkY f ~ 64 135C. I,OC1E 06 1.038K. 06 9.204E.07 7.$ 808~09 S SITE 60UNDARY ESE C9 1.792E-06 1 +790K ~ 06 1ASTE 06 1.320K 05 S SITE 6IANOARY SE .42 2.19CE 06 2.192K 06 2.023E 06 1.911E 05 S SITE 6NJNOARY SSE 34 $ 49. 3.653E.06 3obSOE.Ob 3AOTK.06 2.926E. 05 S RESIDENCE S 1. 00 1609. 1.4SZE 06 1.4CTE.06 1.270E 06 67871E 09 S RESIDENCE SQI 90 1448. 3.'112E.06 3.0968 .06 2,739K ~ 06 loMDE 06 S RESIDENCE SV I 50 2415. 3.160E-06 3.131E.06 2.d77E 06 e. 7378.09 S RESIDENCE VSV 1.10 1770. 1.267K.OS 1.256K.OS 1. 100E.OS 1.729E.08 S RESIDEKCE V 1,20 1HI. 4.976E 06 4.937E 06 4,290E 06 7o5826.09 S RESIDENCE VKV .80 1287. 4,885E 06 4.560K 06 4.330K 06 9.6096.09 S RES INNCE NV .80 1287. 5.391E 06 5.365E 06 4.779K 06 1.448K 05 S RESIDENCE NNI .60 6.210E. 06 6.1ME 06 S.S99E 06 1 945K 08 S RESIDEKCE N 1.30 2092. 1.797E. 06 ).763K 06 1.S40E 06 4. 819E i 09 S RESIDENCE NNE 1.00 1609. 3.d77K.06 3.6SDE.06 3.214K 06 1.167E 05 S RESIDENCE NE 2.30 3702. 7.719K 07 7.649E.07 6,290E 07 3.954K 09 S RES INNCE ENE 2.10 3361. 4.6Hf 07 4.661E 07 3.661K 07 3.0$ 7E 09 S RESIDENCE E 1.40 2253. 4 ~ C'ZIE 07 4.CD3E.07 3.771E 07 2.MSE 09 S RESIDENCE ESE .50 605. 1.764E 06 1.7dlf 06 1.610E Ob I.296K N S RESIDEKCE SE .CO 2.377E 06 2.374E 06 Zst96E 06 2.056E'05 S RESIDENCE SSE AO 966. 1.702E 06 1.699E 06 1.$ 35E 06 1.252K M S GARDEN S 1.10 1770. 1,2C7E 06 1.242E 06 II083K 06 5. 767K. 09 S GARDEN SSV 1,20 1HI . 2.015E.06 2.003E 06 1.739K 06 6.544E 09 S GARDEN SV 1. 90 3059. 2.236K 06 2.211K 06 1.855E'06 4. 013K. 09.

S GARDEN VSV 1.10 1770. 1.2)3E.OS 1.26CE 05 1.105K 05 1.737E.M S GARDEN V 1.20 1H I. 4 976K.06 4.H7E ~ 06 4.290K'06 7.5626.09 S GARDEN VKV 1.30 2092. 2.319E 06 2.300E 06 1.966E ~ Oe ,3.9676.09 S GARDEN 90 14C8. 4,356K 06 C.362K 06 3.660E Ob 1.143E M S GARDEN NKV 4.00 6436. 3.873E.07 3.755E F 07 2.9SCE 07 6.970E 10 S GARDE K K 1.30 2092. 1.797$ .06 1.783E 06 1.$ COE 06 4.819E 09 S GARDEN 1.10 'I 770. 3.185f.06 NME . 3.167E 06 2.765K 06 '1.001E 08 S GARDEN Nf 2.30 3TOZ. 7.719K 07 7AC9E ~ 07 6.290K.07 3 954K 09 S GARDEN fNE 2.40 3663. 3.938E 07 3 907E F 07 3 '96E 07 .2ADCE 09 S GARDE K E 1.40 2253. 4.C21E 07 4.COSE 07 3.7/IE 07 2oMSE i09 S GARDEN ESE 2.50 CDZ4. 1.235E 07 IoZZSE 07 9.979E 08 6AOZE ~ 10 S GARDEN SE Io323E 06 I o321fiN I 19CE 06 I 0778 05

$ GARDEN SSE 60 1287. 1.'162E 06 I 1S9E 06 1.03IE 06 8. 090E. 09 S DAIRY f 4.50 7244. 6.516E 08 6.C2SE.M 4.907E 08 3.178E ~ 10 S DAIRY E 4.60 7405. bo266E 05 e.1796.08 4 706E 06 3.038E ~ 10 S DAIRY ESE 2.70 4346. 1.076E.07 07 6AZSE 08 S.S46E 10

'.067E 66

Page 15 of 15 TABLE 22 AVERAGE ANNUALRELATIVE CONCENTRATIONS 5 DAIRY ESE 4.10 6$ 99. 4.679K 08 4.618K 08 3.S67K.08 2.167K-10 5 DAIRY ESE 4.20 6760. 4.426K 08 4.367E 08 3.364K. 08 2.037E ~ 10 5 DAIRY SE 2.60 4185. 1.309K 07 1,3008.07 1.054E-07 7A74E 10 5 DAIRY 5 3.90 1.362K. 07 1,340E 07 1,044E 07 4.486E ~ 10 5 DAIRY SSV 3.00 4.835K 07 4.761E 07 3.824K 07 1,189E 09 5 DAIRY SSV 3.10 4990. 4.SOSE F 07 4.433K 07 3.S49E 07 lo095E 09 5 DAIRT SSV 3.50 3.4ME.07 3.3968-07 2AKSE 07 8.052E. 10 5 DAIRY SSV 3.80 6117. 2.946K 07 2.888K. 07 2.263K 07 b.dSTE ~ 10 5 DAIRY SSV 14.00 1.740E 08 1.dlbE.08 1.074E 08 2. 609E-11 5 DAIRY VSV 2,00 5.719K.06 5A4SE.06 4.71 8K. 06 6.33)K. 09 S DAIkY V 5.00 8049. 4,898K 07 4.739E 07 3.617K. 07 4 e121E-10 5 DAIRY NNV 4.20 6760. 3A13E 07 3.S268.07 2.737E. 07 6.386K-ID S RIVERLANDS/EIC Nf .70 1127. 4.158E.06 4.146E.06 3. 716E. 06 2.8SSE.08 VENT AHD SUILDINC PlkAHETERS:

kELEASE NEICHT (NETERS) 9 60 kfP VINO NEI CRT (IIETfRS) 10+0 DIAHETER (NKTERS) 00 RUILDINC NEI CRT (NETKRS) dl.3 EXIT VELOCITY tN/SEC ) e00 RLDC.NIN,CRS,SEC.AREA tSO.NETEkS) 2STS,O NEAT EN I 55 IOI RATE (CAL/SEC) .0 AT THE RELEASE HEICHI: I AT THE NEASURED VIND kEICNT ( TO+0 NETERS)I VENT RELEASE IHOE Vile SPEED (NETKkS/SEC) VKNl kELEASE Ntef VINO SPEED tNETERS/SKC) VINO SPEED (Nflfkk/SEC)

I STARLE CQS I 7 I OIS UHSTASLE/NEUTRAL C(WDITIONS ELEVlTED LESS THAN +000 I LKSS THAN, 000 LESS THlN .000 NI XED SETVEEN oO(m lND 000 f SETVEEN +000 AND +000 RE)VEEN .000 AHD .000 Ck(XHm LEVEL ASOVE e000 I ASOVE,OOO 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 (DANVILLERECEIVER)

FOR 1996 PARAMETER ENTIRE YEAR Cooling Tower Blowdown (CFS) 17.3 Average Net River Level (ft)(1) 5.3 Dilution Factor at Danville (2) 284.1 Transit time to Danville (hr)(2) 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 MAXIMUMINDIVIDUALOFFSITE DOSES AND DOSE COMMITMENTS TO MEMBERS OF THE PUBLIC DATA PERIOD'/1/95 TO 12/31/95 ESTIMATED

':A"GE APPLICABLE MAXIMUM PERCENT LIMIT

EFFLUENT GROUP 'ORGAN DOSE LOCATION OF LIMIT (MREM)~~

MREM DIST AFFECTED MILES SECTOR

~ Li uid uid

'EEN

'i TOTAL BODY ADULT GI-LLI 2.14E-02 1.00E-01 0.71 1.00 10 Noble Gas N/A AIR DOSE 7.10E-03 1.10 WSW 0.07 10 (GAMMA-MRAD Noble Gas N/A AIR DOSE 9.10E-03 1.10 WSW 0.05 20 (BETA-MRAD Noble Gas N/A TOTAL BODY 4.69E-03 1.10 WSW 0.09 Noble Gas N/A SKIN 1.24E-02 1.10 WSW 0.08 15 ue aud CHILD LUNG 6.27E-02 1.10 WSW 0.42 15 cula s

"'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,

\

~

~ K

$ ~

lr o &

I

~ ~

.-l I ~

No I

I

~

V at4.

0 ~ Q +IS 0 &Qa0 ~+~op 1.

I Vai ~

I own

> \ ~

~

'l I e~awl.

I I I I

~~

~ ~

I I I ga sas e ~ uP I '0 0 I

I I '

SW I I a ~

Pl'\

LC0%0 SUSQUEHANNA STEAM ELECTRIC STATION S SITE BOUNDARY DISTANCES v Pf IL hwnt,koe4pl (DISTANCES IN FEETl ~

aeaer %keel aors~

PENNSYLVANIA POWER 4 UGHT Locskn4tor cbee cakuhtiona HALUBURTON NUS

~L ace o ooo aooo oooo Navsmber 02,.1993 73

TABLE 25 CALCULATEDCOLLECTIVE DOSES TO MEMBERS OF THE PUBLIC WITHIN THE RIVERLANDS/INFORMATIONCENTER COMPLEX DATA PERIOD: 1/1/95 TO 12/31/95

'MAXIMUM COL'L'ECTIVE

. 'AGE -APPLICABLE DOSE RATE" DOSE EFFL'UENT GROUP ORGAN MREM/HR 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 TEEN LUNG 1.95E-06 1.95E-04 PARTICULATES 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 CALCULATEDDOSES FOR RESIDENCES WITHIN THE SSES SITE BOUNDARY 0.40 MILES SE SECTOR DATA PERIOD: 1/1/95 TO 12/31/95 ESTIMATED, PERCENT AGE APPLICABLE MAXIMUMDOSE 'OF

-."-EFFLUENT GROUP ORGAN (MREM) 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 TEEN LUNG 6.07E-03 0.04 15 PARTICULATES 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 ESTIMATED PERCENT AGE APPLICABLE MAXIMUMDOSE OF EFFLUENT GROUP ORGAN (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 CHILD LUNG 4.86E-02 0.32 15 PARTICULATES t

10 CFR 50, Appendix I limits are in terms of mrad or mrem/reactor-year.

PATHWAYS ANALYZED: PLUME, GROUND, VEGETATION, INHALATION 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 ESTIMATED PERCENT AGE 'PPLICABLE MAXIMUM OF

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

PATHWAYS ANALYZED: PLUME, GROUND, INHALATION,VEGETATION AND COW MILKINGESTION 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 CALCULATION MANUAL AND THE SOLID MfASTE PROCESS CONTROL PROGRAM 77

CHANGES TO THE OFFSITE DOSE CALCULATIONMANUAL 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 4

0

System classifications and references are added to Table 8 (NOT AN EFFLUENT PATHWAY) and Table 9 (INSIGNIFICANTEFFLUENT 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 SEMIANNUALOR ANNUALEFFLUENT AND WASTE DISPOSAL REPORT 84

CORRECTIONS TO DOSES REPORTED IN PREVIOUS SEMIANNUALOR ANNUALEFFLUENT 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 AGE LOCATION PATHWAYS GROUP ORGAN DOSE mrem 0.7 miles WSW Site Bounda 1,6 Teen Lun 8.75 E-04 1.7 miles WSW Dai Animal 1, 2, 3, 5, 6 Teen G.I. 6.04 E-04 1.2 miles WSW Garden 1, 5, 6 Teen G.l. 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 ADDITIONALMONITORED RELEASE POINTS 86

EFFLUENT FROM ADDITIONALMONITORED 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 LAUNDRYTRAILER Isoto e Mn-54 Effluent Released Ci 6.54E-08 TABLE 30 OFFSITE DOSE (RESIDENCE AT 1.1 MILES WSW)

RESULTING FROM LAUNDRYTRAILER EFFLUENT ESTIMATED

'EFFLUENT 'GE GROUP APPLICABLE ORGAN MAXIMUMDOSE MREM LIMIT MREM

'PERCENT L'IMIT

",OF 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 2 Prepared By Date Reviewed By Date / /

Supervisor-Environmen al Services Nuc ear Reviewed By Oate ing o.

Approved By 4. A Manager-Nuclear Technology 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 Maximally-Exposed Member of the. Public) is taken from Reg. Guide

'he 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 REVISION PAGE DATE DATE

1. 0 INTRODUCTION. 10/29/93 3/11/94 2 2/5/92 2/21/92 3 11/9/93'/5/92 3/ll/94 2.0 SETPOINTS............................... ~ . ~ t ~ ~ 2/21/92

2. 1 WATERBORNE EFFLUENT MONITORS.......... ~ ~ ~ ~ 4 2/5/92 2/21/92 5 12/11/89 '12/11/89 6 2/5/92 2/21/92 7 12/11/89 12/11/89 8 12/11/89 12/11/89 2.2 AIRBORNE EFFLUENT MONITORS............ ~ ~ ~ ~ 9 2/5/92 2/21/92 10 12/11/89 12/11/89 11 12/11/89 12/11/89 12 11/21/92 11/25/92 3.0 WATERBORNE EFFLUENT CONCENTRATION MEASUREMENTS 13 2/5/92 2/21/92 14 2/5/92 2/21/92 4.0 AIRBORNE EFFLUENT DOSE RATES ............. ~ ~ ~ ~ 15 2/5/92 2/21/92

4. 1 NOBLE GASES....... ~ ~ ~ ~ 15 1/16/95 1/20/95 4.2 RADIONUCLIDES OTHER THAN NOBLE GASES.. ~ ~ ~ ~ 16 1/16/95 1/20/95 17 2/11/92 2/21/92 18 2/5/92 ~

2/21/92 19 12/11/89 12/11/89 20 12/1/92 12/4/92 5.0 INDIVIDUAL DOSE DUE TO WATERBORNE EFFLUENT ~ ~ ~ ~ 21 10/29/93 3/11/94 5.1 FISH PATHWAY LIQUID EFFLUENT DOSE CALCULATION METHODOLOGY.... 22 2/18/94 3/11/94 5.2 POTABLE WATER PATHWAY EFFLUENT DOSE CALCULATION METHODOLOGY............... ~ ~ ~ ~ 23 ll/9/93 3/11/94 5.3 SHORELINE EXPOSURE PATHWAY. ~ ~ ~ 24 ll/9/93 3/11/94 5.4 PROJECTED DOSE FROM LIQUID EFFLUENT... ~ ~ ~ ~ 24 ll/9/93 3/ll/94 25 2/18/94 3/11/94 I

26 ll/9/93 3/ll/94 6.0 INDIVIDUAL DOSE DUE TO AIRBORNE EFFLUENT.. ~ ~ 1 ~ 27 10/29/93 3/ll/94

6. 1 NOBLE GASES........ ~ ~ ~ ~ 27 10/29/93 3/11/94 6.2 RADIONUCLIDES OTHER THAN NOBLE GASES.. ~ ~ ~ ~ 28 10/29/93 3/11/94 29 10/29/93 3/ll'/94 7.0 TOTAL DOSE ~ ~ ~ ~ 30 1/16/95 1/20/95 31 10/29/93 3/ll/94 8.0 OPERABILITY OF WASTE TREATMENT SYSTEMS.... ~ ~ ~ ~ 32 10/29/93 3/ll/94

8. 1 LIQUID WASTE TREATMENT................ ~ ~ ~ ~ 32 1/16/95 1/20/95 33 1/16/95 1/20/95 8.2 GASEOUS WASTE TREATMENT. '34 1/16/95 1/20/95 1/16/95 1/20/95 8.3 SOLID WASTE TREATMENT .......,......... 36 1/16/95 1/20/95 37 1/16/95 1/20/95 DAT Pev. 2

a E

APPROVAL REVISION PAGE DATE DATE 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. 42 1/16/95 1/20/95 9.1 DEFINITIONS............................... 42 1/16/95 1/20/95 9.2 MONITORING PROGRAM... 42 1/16/95 1/20/95 9.3 CENSUS PROGRAM...............'............. 43 1/16/95 1/20/95 9.4 INTERLABORATORY COMPARISON PROGRAM........ 44 1/16/95 1/20/95 45 1/16/95 1/20/95 10.0 DOSE ASSESSMENT POLICY STATEMENTS............ 53 1/16/95 1/20/95 10.1 SELECTION OF ANALYSIS RESULTS FOR 53 1/16/95 1/20/95 DOSE CALCULATIONS 10.2 ASSIGNMENT OF RELEASES TO THE REACTOR 53 1/16/95 1/20/95 UNITS 10.3 EVALUATION AND MONITORING CRITERIA FOR 53 1/16/95 1/20/95 EFFLUENT PATHWAYS 10.4 FLOW FROM THE SGTS VENT WHEN THE SYSTEM 54 1/16/95 1/20/95 IS NOT IN USE 10.5 ODCH SETPOINTS ARE UPPER LIHIT VALUES 55 1/16/95 1/20/95 10.6 DEFINITION OF "APPROPRIATE TREATMENT" 55 1/16/95 1/20/95 FOR LIQUID WASTES 10.7 HONITOR LINE-LOSS CORRECTIONS 57 1/16/95 1/20/95 10.8 SELECTION OF DATA FOR DETERMINATION OF 57 1/16/95 1/20/95 DOSE RATE COMPLIANCE 10.9 LOW-LEVEL RADIOACTIVITY IN THE SEWAGE 58 1/16/95 1/20/95 TREATMENT PLANT

11. 0 ODCH REVIEW AND REVISION CONTROL............. 60 1/16/95 1/20/95 APPENDIX A SAMPLE CALCULATIONS OF ODCM PARAMETERS........................... A-1 2/5/92 2/21/92 A-2 2/5/92 2/21/92 A-3 12/11/89 12/11/89 A-4 2/5/92 2/21/92 A-5 10/29/93 3/ll/94 A-6 10/29/93 3/ll/94 A-7 10/29/93 3/ll/94 A-8 10/29/93 3/ll/94 A-9 2/5/92 2/21/92 A-10 2/5/92 2/21/92 I A-1 1 10/29/93 3/ll/94 A-12 10/29/93 3/ll/94 A-13 10/29/93 3/ll/94 APPENDIX B REPORTING REQUIREMENTS............... B-l 12/11/89 12/11/89 B-2 10/29/93 3/ll/94 B-3 12/11/89 12/11/89 8-4 12/11/89 12/11/89 DAT Rev. 2

~ '

V'

APPROVAL REVISION PAGE DATE DATE 5-6c Composite Dose Factors: Haximum Hypothetical Child (2pp)....................................5-6c(1,2) 2/18/94 3/ll/94 5-6d Water Ingestion Dose Factors: Haximum Hypothetical Infant (2pp)......................5-6d(1,2) 2/18/94 3/ll/94 6 Operational Radiological Environmental Honitoring Program.. .. ... ................ 48 1/16/95 1/20/95 49 1/16/95 1/20/95 50 1/16/95 1/20/95 7 Detection Capabilities for Environmental Sample Analysis................ ............. 51 1/16/95 1/20/95 52 1/16/95 1/20/95 8 Systems Classified as Not an Effluent Pathway... 61 1/16/95 1/20/95 9 Systems Classified as Insigni'ficant Effluent p athwayo ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 62 1/16/95 1/20/95 B-l Radiological Environmental Honitoring Program Annual Summary. ... .......................... 8-3 12/11/89 12/11/89 B-2 Reporting Levels for Nonroutine Operating R eportso ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t B 4 12/11/89 3/ll/94 D-1 Dilution Factors and Transit Times for SSES Effluents to Oanville, PA........... . D-1 ll/9/93 3/ll/94

LIST OF FIGURES APPROVAL REVISION PAGE DATE DATE Figure 1 Liquid Radwaste System Flow Diagram.......................:.. 38 1/16/95 1/20/95 Figure 2 Offgas and Recombiner System F'tow Diagram........ ~ ~ ~ ~ ~ ~ o 39 1/16/95 1/20/95 Figure 3 Solid Waste Management System Flow Oiagram.......................... 40 1/16/95 1/20/95 Figure 4 SSES Dry Contaminated Waste Processing............................ 41 1/16/95 1/20/95 Figure 5 Environmental Monitoring Locations Within One Mile of SSES...'............ 46 1/16/95 1/20/95 Figure 6 Environmental Monitoring Locations Greater than One Mile from SSES....... 47 1/16/95 '/20/95 vi DAT Rev. 2

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) (Eq. 7) 1 and by the following equation for skin dose:

D g [L.1

~

+ ((1.11 (Mi)(S~))] (X/Q)(Q')) (Eq 8) 15 DAT ' Rev. 2

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~ 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 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 0 in the applicable plant procedures.

areas due to radioactive materials released may be determined by The dose the, following equation for rate in unrestricted in airborne effluents whole body dose:

Z ( )( /0)y (0'fy)( p) (Eq 7) 1 and by the following equation for skin dose:

D g [L1

~

+ ((1.11 (Mi) (Sr) ) j (X/9) v (9'iv) (Eq 8) 15

' Rev. 2 DAT

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 the annual whole-body dose (mrem/yr).

Li 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

) from Table 2 (conversion constant of 1. 1

'Ci/m converts air dose-mrad to skin dose-mrem).

D s

the annual skin dose (mrem/yr).

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 Rev. 2 16 OAT

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.1 with K.i from Table 2 for the whole-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:

D3 1

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 30 DAT Rev. 2 I

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 or replacement of components.

for'epair 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.

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 DAT 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.

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 OAT 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.

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.

\

I OAT 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.

35 At'rV Rev. 2 DAT

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.

36 DAT Rev. 2

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.

37 Rev. 2

REACTOR WELL SEAL LEAK DRAIN REACTOR BLDG. DRAINS FIGURE EVAP.

CONDS.

STEAM TANK

+- DRYWELL DRAINS LIQUID RADWASTE SYSTEM FLOW DIAGRAM TLSBINE BLDG. DRAINS PHASE SEPARATORS AADWASTE BLDG. DRAINS (DECANTATE) LIQUID RADWASTE RHR SYSTEM Rwcu SYSTEM LIQUID RADWASTE COLLECTION 8 SURGE LIGUID LIGUID LIauID RADWASTE RADWASTE RADWASTE TAHKS FILTERS DEN INERALIZEA SAMPLE TANKS OT.302 A THRU F OT.304 A THRU OF-302 A,B OF-301 OT-303 A THRU F D

CONDENSATE CONDENSATE DEVIH. TO WASTE MIXINQ TO SPENT STORAGE LRW COLLECTION RESIN AEGHERATIHQ TANK TANK PNLPS TANKS OT-307 A,B AESIH TANK TANKS OP-301 h>B,C OT-324 OT-522 A,B CHEVIGAL WASTE HEUTAALIZEA TANKS 1T-130 A,B 2T ~ 130 A,B RADWASTE DISTILLATE RE EVAPORATOR SAMPLE TANK CST BEAM WATEA CHEM. WASTE OE-302 A,B OT-321 SAMPLE STATIONS NEUTRALIZING AUX BOILER BLOWDOWNS TANK P NIPS TO CODLING RWCU CHEVICAL DECON. 1P 130 A>8 TOWER BLOW-LAB AHD DECOH. DRAINS 2P-130 A,B DOWN PIPE LRW SAMPLE TANK PLNPS OP-305 A>B,C CHEMICAL WASTE CHEMICAL WASTE PAOCESSINQ SUB-SYSTEM CHEM WAS'TE TANK (VENDOR SUPPLIED)

TANK PWPS OT-314 EVAPORATOR OP-328 A>8 COHCENTRATE STORAGE TANK LAUM)RY DRAINS REGLAATED SHOP DRAINS OT-322 PERSONAL DECONTAM-INATION {OETEAGEHTS)

CASK CLEAHIHG DRAINS TO WASTE MIXING TANKS OT-307 A>8 LAUNDRY DRAIN LAUNDRY DAAIN TANK TANK PUMPS LAUHDRY DRAIN LAUNDRY DRAIN OT-314 A,B OP.318 A>8 FILTERS SAMPLE TANK OF-318 A>8 OT-312 CONCENTRATE BTORAGE TANK DISCH. PQIP OP-328 LAUNORV DRAIN SAMPLE TANK PUMPS OP.319 A,B DAT t6 Rev. 2

AMBIENt TEMPF RATURE CI<aRCOAI Of F GAS RF COMBINE R SYSlf M I OFF GAS SYSTEM UNIT I Slf AM JET AIR EJECIOR UNII I IURBINE SLOG MaIN d AUX SIEAM E X I I AUS t IF 302OU LET HEPAFILTE IIAR QAL AOS RBEII BE 5 UNIT I ROM >NII I ai F E L HE I RACING I E 13h it 3ia it 305 IT.30B ii301 il 3aa Q OI F IIAS BYPASS I'R f Qr-------) l HE A IE II

'il DELAY PFPE IF IA ~ IE IA IE 3 A 5 IT 303a Nhlil I Stf AII DILUTIONSTEAM I COII I OTII STEA> I JET I I Tfh 15 125 I INLET PRE CIIILIER ~Z GUARO A'I 5 IE 13i 112 UIIII RECOMB NEPA COOl.f fi us B 0 5 I AGE EJEC VESSEL MOT I VE F ILTE R Z 1011 I STEAM COB JET DfII. 2na STAGA I 04- 'E 5 COND 2

SEII 131 RECOMB COND COMMON OFFGAS RECOMBINER SYS'EM SIEAM JET AIR fJECTOR CONDENSER IIAI1s UNI'T 2 DELAY PIPE STEA COII AMBIENT TEMPERATURE CIIAIICOAL DER. OFFGASSYSTfM SEII UNIT 2 Ohlt t OFFGAS RECOMBINER SYSTEM 2 OFFGAS BYPASS MAIte 5 AUX TURBINE BLOG EXHAUST Stf AU UNIT 2 PROD UNIT 2 FIGURE 2 OFFGAS AND RECOHBIHER SYSTEM FLOH DIAGRAM OAT Rev. 2

FIGURE 3 SOLID WASTE MANAGEMENT SYSTEM FLOW DIAGRAM CONDENSATE RADWASTE CONDENSATE FUEL POOL DEMIH RESIH DEMIHERAL IZER DEMIH RESIN RWCU BACKWASH RWCU BACKWASH F/0 BACKWASH RECEIVING TANK RECEIVINO TANK STORAGE VESSEL STORAGE VESSEL STORAGE VESSEL RECEIVINO TANK 1T-159 OF-301 2T-158 1T-225 2T-225 OT-203 .

REGEH WASTE REOEN WASTE SUADE TANKS SURGE TANKS SPENT RESIH 1T-108 A,B 2T-108 A,B TANK OT-324 1P-108 A,B REGEHERATIOH WASTE TRANSFER PUMPS SPENT RESIN I TRANSFER PUMP OP-320 TO VENDOR LIOUIO RAWASTE WASTE SLUDGE FILTERS PHASE SEPARATOR OF-302 A>8 WASTE SLUDGE OT-331 DISCHARGE IIIXIHG PUMP RWCU PHASE RWCU PHASE OP-332 SEPARATOR SEPARATOR TO RWSS PUMP OT-318 A OT-318 B TO RWSS PUMP WASTE MIXING TAHKS OT-307 A,B EVAPORATOR COHCENTRATE STORAGE TANK OT-322 RWCU SLUDGE DISCHARGE EVAPORATOR.

lllXIHG PUMP CONCENTRATE OP-3N TO VEHDOR STORAGE TANK DISCHARGE PUMP FROM OP-328 EVAPORATOR DAT Rev. 2

FIGURE 4 SSES ORY ACTIVE WASTE (OAW) PROCESSING Non- radiological Paper, Plastic, Rags, Trash from RCA Clothing from RCA Second-Sort DAW Dry Active Waste (DAW)

Monitoring System PPKL Drum Compactor Vendor Yes Ser vices Radioactive?

Supercompaction 55-gal. Drums or Boxes Incineration 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.

42 DAT Rev. 2

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 43 pAy / $ J Rev. 2

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.

44 A

DAT Rev. 2

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.

45 Rev. 2

'I FIGURE 5 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE SSES GOULD ISLAND a~

I g, Q p LAKE p ~ m ~ ~ m ~ ~ eel f5$ 1 ~TAW I,g I

I T ~

~

~ ~

52 ~/ 3$ l I

I 13 ma@

I b$ 7 r--~ I or Qa I ~ bN I T I I

/ f o~l

~

C

/Q~ QS3 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 SUSQUEHANNA NANTICOKE RIVER T

I GLEN LYON 15F1 SHICKSHINNY gn 14 MOCANAQUA

~ 4E2 POND HILL 1483 I

T SSES T

i gg WAPWALLOPEN

.T BERWICK gj ~1%2'~ iRI err. NESCOPECK gg TiRa T

MIFFLINVILLE 5 NILES T

I 12}{2 Etl

/

CON YNGHAM HAZLETON 1B NILES

~m DRSQNC INTER saagncr

~i THERMDLDMNESCENT DQSMERY OATF 47 Rev. 2

Page I o TABLE 6 OPERATIOHAL RADIOL06ICAL ENVIRDHHENTAL HONITORING PR06RAil Exposure Pathways Nraaber of Samples Sarrpl 1ng and Type and and or 5 le and Locat1 ons~

Airborne Continual sampler operation with Radioiodine Canister: analyze Radioiodine and 1251 0.4 ml MSM - E.O.F. Building sample collection weekly.'* ~

weekly for 1-131 Particulates* 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 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.

lrect Radiation 1S2 Perimeter Fence - 0.2 ml.N Quarterly Garrrna Dose: Quarterly.

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

'Mest of SSES APF - 0.2 mi ENE HE'S3 4E1 Ruckles HI)I Road Pole (t) 46422/H35197 - 4.8 ml ENE 4GI Crestwood Industrial Park-14 ml Perimeter Fence - 0.3 ml E ENE'S7 5E2 Bloss Farm - 4.5 mi E 6S4 Perimeter Fence - 0.2 ml ESE 6A4 Riverside Restaurant - 0.6 ml ESE DAT Rev. 2

Page 2 o Exposure Pathways Neer of San@les Sandal ing and Type and and or le and Locations~ Col lection F uenc o 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 Perimeter Fence - 0.2 mi SSE SE'52 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 Perimeter Fence - 0.4 mi M MSV'3S2 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 Vaterborne Surface 656 river water intake Monthly composite Ganma isotopic analysis.

tritltsn analysis at line'S7 cooling tower blowdown discharge line Honthly composite Composite least quarterly.

Drinking 12H2 Oanville Mater Co. Honthly composite Gross beta and gasma isotopic (Approximately 30 miles downstream) analyses monthly. Composite for tritium analysis at least quarterly.

Sediment from Shoreline 78 Bell Bend,- 1.2 mi SE Semi-annually Gasma isotopic analysis

'semi-annually.

OAT Rev.

Page 3 o Sandal Exposure Pathways Nuxber of Samples ing and Type and

~atat orat iona* Col lect i on F uenc of l HIIk~*~ 1283 Young Farm - 2.0 mi MSM Semi-monthly when animals are on Gamma Isotopic and 1-131 analysis 10GI Davis Farm - 14 mi. pasture, monthly otherwise of each sample.

Ray Ryman Farm - 3.5 mi.

SSN'OD2 SSM 10Dl R&C Ryman Farm - 3.0 mi. SSM Fish and Invertebrates Outfall area Semi-annually. One sample'rom Gasma Isotopic on edible portions.

2H Falls, each of two reacreationally PA'Approximately 30 mi HNE) Important species from any of the following families: bullhead catfish, sunfish, pikes, or perches.

Food Products IID1 Lehner Farm - 3.3. mi SV At time of harvest Gatnna I'sotopic on edible portions.

vegetable 12F7 Lupini Farm - 8.3 mi WSM vegetable

• 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)

Airborne Particulate A~nal sis Water Q)Ci ~1 C

or Gas Fish Ci k wet Milk Q)Ci ~1 Food Products C k wet C Sediment d

gross beta x 10 H-3 2000 Mn-54 130 Fe-59 30 260 Co-58 15 130 Zn-65 30 260 Zr-95 30 I-131 1b 7 x 10 60 Cs-134 15 5 x 10 130 15 60 150 Cs-137 18 6 x 10 150 18 80 180 ea-140 60 60 La-140 15 15 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 4.66 sb 2.22 EVY exp (-A 4 t) where:

LLD is the "a priori" lower limit of detection as defined above (as pCi 4

per unit mass or volume).

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.

52 DAT Rev. 2

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 53 DAT Rev. 2

'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.

55 Rev. 2

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.

'Reference Letter R. K. Barclay to R. A. Breslin: Atmospheric Demineralizer Effluent Results, PLI-70612, 3/4/92.

56 DAT Rev. 2

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:

COR C ON FACTO S N F THO T S ARE ~PART CII R Reactor Building Unit 1 1.5 3.2 Reactor Building Unit 2 1.5 3.2 Turbine Building Unit 1 1.6 3.6 Standby Gas Treatment 1.5 3.9 Turbine Building Unit 2 1.6 3.6

~CGRR CTIGA FACTIIRR POST ACCID T VENT MONITORS ~IODIII PARTICULATES Turbine Building Unit 1 1.7 4.2 Standby Gas Treatment 1.6 4.4 Turbine Building Unit 2 1,.7 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 57 DAT Rev. 2

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 purposes. In these cases, normal biological 'herapeutic 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 58 Rev. 2 DAT

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.

59 DAT Rev. 2

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.

60 Rev. 2 DAT

~ 8

'I

TABLE 8 SYSTENS CLASSIFIED AS NOT AN EFFLUENT PATHWAY (Page 1 of 2)

SYSTEN DESCRIPTION REFERENCE Domestic Water 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 61 DAT B Rev. 2

TABLE 8 SYSTENS CLASSIFIED AS NOT AN EFFLUENT PATHWAY (Page 2 of 2)

SYSTEN DESCRIPTION REFERENCE 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 (I) PP8L Calculation EC-ENVR-1008 r 62 DAT Rev. 2

TABLE 9 SYSTBlS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAY SYSTBl DESCRIPTION REFERENCE 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 (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 63 DAT Rev. 2

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:

Health Physicist-Operations Technology Date: 1/16/95

PENNSYLVANIA POMER 5 LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL Prepared By i4a -8 Zf cc Date 8>> 9S Reviewed By Date Supervisor-Environmental Services Nuclear Reviewed By Date 9 Z~ -PS

/ eetsng o.

Approved B Date

'Z ~a Hanager-Nuclear Technology

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

- Nuclear be. reviewed by PORC after approval by the Manager Technology.

Rev. 3

I '

APPROVAL REVISION

~AG ~DT ~

DATE 9.0 RADIOLOGICAL ENVIRONHENTAL MONITORING PROGRAM. 42 1/16/95 1/20/95 9o 1 DEFINITIONS@ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ e ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ 42

~ 1/16/95 1/20/95 9.2 MONITORING PROGRAM..............-......... 42 1/16/95 1/20/95 9.3 CENSUS PROGRAM............................ 43 1/16/95 1/20/95 9.4 INTERLABORATORY COMPARISON PROGRAM........ 44 1/16/95 1/20/95 45 1/16/95 1/20/95 10.0 DOSE ASSESSMENT POLICY STATEMENTS............ 53 1/16/95 1/20/95 10.1 SELECTION OF ANALYSIS RESULTS FOR 53 1/16/95 1/20/95 DOSE CALCULATIONS 10.2 ASSIGNMENT OF RELEASES TO THE REACTOR 53 1/16/95 1/20/95 UNITS 10.3 EVALUATION AND MONITORING CRITERIA FOR 53 3/23/95 3/30/95 EFFLUENT PATHWAYS 10.4 FLOW FROM THE SGTS VENT WHEN THE SYSTEM 55 3/23/95 3/30/95 IS NOT IN USE 10.5 ODCH SETPOINTS ARE UPPER LIMIT VALUES 55 3/23/95 3/30/95 10.6 DEFINITION OF "APPROPRIATE TREATHENT" 55 3/23/95 3/30/95 FOR LIQUID WASTES 10.7 MONITOR LINE-LOSS CORRECTIONS 57 3/23/95 3/30/95 10.8 SELECTION OF DATA FOR DETERMINATION OF 58 3/23/95 3/30/95 DOSE RATE COMPLIANCE 10.9 LOW-LEVEL RADIOACTIVITY IN THE SEWAGE 59 3/23/95 3/30/95 TREATMENT PLANT 11.0 ODCM REVIEW AND REVISION CONTROL............. 60 3/30/95 3/30/95 APPENDIX A SAMPLE CALCULATIONS OF ODCH PARAMETERS........................... A-1 2/5/92 2/21/92 A-2 2/5/92 2/21/92 A-3 12/11/89 12/11/89 A-4 2/5/92 2/21/92, A-5 10/29/93 3/ll/94 A-6 10/29/93 3/ll/94 A-7 10/29/93 3/ll/94 A-8 10/29/93 3/ll/94 A-9 2/5/92 2/21/92 A-10 2/5/92 2/21/92 A-ll 10/29/93 3/ll/94 A-12 10/29/93 3/ll/94 A-13 10/29/93 3/ll/94 APPENDIX B - REPORTING REQUIREMENTS............... B-1 12/11/89 12/11/89 B-2 10/29/93 3/ll/94 B-3 12/11/89 12/11/89 B-4 12/11/89 12/11/89 Rev. 3

APPROVAL REVISION PAG DATE DATE 5-6c Composite Dose Factors: Haximum Hypothetical Child (2pp)....................................5-6c(1,2) 2/18/94 3/11/94 5-6d Water Ingestion Dose Factors: "Haximum Hypothetical Infant (2pp)......................5-6d(1,2) 2/18/94 3/11/94 6 Operational Radiological Envi ronmental Honitoring Program........... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 48 3/23/95 3/30/95 49 3/23/95 3/30/95 50 3/23/95 3/30/95 7 Detection Capabilities for Environmental S ample Analysis................................. 51 1/16/95 1/20/95 52 1/16/95 1/20/95 8 Systems Classified as Not an Effluent Pathway... 61 3/29/95 3/30/95 9 Systems Classified as Insignificant Effluent p athway.......................................... 3/29/95 3/30/95 10 Systems Classified as Significant Effluent p athway......................................... 65 3/29/95 3/30/95 B-l Radiological Environmental Honitoring Program Annual Summary.................................. B-3 12/11/89 12/11/89 B-2 Reporting Levels for Nonroutine Operating R eports......................................... B-4 12/11/89 3/ll/94 D-l Dilution Factors and Transit Times for SSES Effluents to Danville, PA....................... D-l Il/9/93 3/ll/94

LIST OF FIGURES APPROVAL REVISION

~PG ~DA E ~DE Figure 1 Liquid Radwaste System F low Diagram.......................... 38 3/23/95 3/30/95 Figure 2 Offgas and Recombiner System F low Diagramo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 39 1/16/95 1/20'/95 Figure 3 Solid Waste Hanagement System Flow Diagram.......................... 40 1/16/95 1/20/95 Figure 4 SSES Dry Contaminated Waste Process 1 ng o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 41 1/16/95 1/20/95 Figure 5 Environmental Honitoring Locations

, Within One Hile of SSES............... 46 1/16/95 1/20/95 Figure 6 Environmental Honitoring Locations Greater than One Hile from SSES....... 47 1/16/95 1/20/95 Rev. 3 V1

l REACTOR WELL SEAL LEAK DRAIN REACTOR BLDG. DRAINS fIGURE EVAP. STEAM CONDS. AETUflN TANK DAVWELL DRAINS LIQUID RADWASTE SYSTEM FLOW DIAGRAM TLNBINE BLDG. DRAINS PHASE SEPARATORS RADWASTE BLDG. DRAINS (DECANTATE) LIQUID RADWASTE RHR SYSTEM RWCU SYSTEII LIQUID RADWASTE LIOUIO LIOUIO LIOUID COLLECTIOH 4 SURGE AADWASTE RADWASTE RADWASTE TAHKS FILTERS DENIHEAALIZER SAMPLE TAHKS OT-302 A THRU F OF-801 OT-303 A THRU F OF-302 A>B OT-301 A THAU D COHOENSATE TO WASTE IIIXIHG TO SPENT STORAGE COHOENSATE OEMIH.

LRW COLLECTION TANKS RESIN REGNEAATING TANK TANKS OT-307 A,B AESIH TANK TANK PLAB'S OT-522 A,B OP-301 A,B,C OT-324 LAW SAMPLE TANK PNIPS OP-305 A 8 C CHEMICAL WASTE HEUTRAL IZER TANKS 1T-130 A,B 2T-130 A,B AADWASTE DIST IL LATE AE EVAPORATOR SAMPLE TANK CST BEAII WATER CHEM.- WASTE OE-302 A,B OT-321 SAMPLE STATIONS NEUTAAL I ZING TO CODLING AUX BOILER BLOWDOWNS TAIN( PL%PS IP ~ I30 A,B TOWER SLOW-RWCU CHEIIICAL OECOH.

LAB AND DECOH. DflAIHS 2P ~ 130 A,B DOWN PIPE DISTILLATE SAMPLE TANK PCS OP.327 A,B CHEIIIGAL WASTE CHEIIICAL WASTE PROCESSING SUS-SYSTEII CHEM WASTE TANK (VENDOR SUPPLIED)

TANK PLBIPS OT-314 OP-325 A,B EVAPORATOR COHCENTflATE STORAGE TANK LAUMIRY DRAINS OT-322 REGLAATEO SHOP DRAINS PERSON@.L DECONTAII-INATION (DETEAGENTS) TO WASTE CASK CLEANING DRAINS IIIXIHO TANKS OT-307 A,B LAUNDRY DRAIN LAUNDRY DRAIN TANK TANK PUMPS LAUNDRY DRAIN LAUHOAY DRAIN OT-314 A,B OP ~ 318 AsB FILTERS SAMPLE TANK OF-318 A,B OT-312 COHCEHTAATE STORAGE TANK OISCH. PNIP OP ~ 32B LALINDAY DRAIN SJ4IPLE TANK PLIMPS OP.3I9 A,b DATE 9 ~ ~~ p

il Page of 3 TABLE 6 OPERATIONAL RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathways Number of Samples Sampling and Type and and Locations* Collection Fre uenc Fre u nc ofhnal sis hirborne Radioiodine and 12S I 0.4 mi WSW EOF Building sampler operation with sample Radioiodine Canister: analyze Particulates~ 9B I 1.3 mi S Transmission Line collection weekly.~~ weekly for I-131 SS4 0.8 mi E Environmental Laboratory 12E I 4.7 mi WSW Berwick Hospital 7G I 14 mi SE PAL Hazleton Particulate Sample:

Center'ontinual Complex'SES 3S2 0.5 mi NE Backup.Met. Tower Analyze for gross beta 7S7 0.4 nu SE End of Kline's Road radioactivity following filter IOS3 0.6 mi SSW East of Confer's Lane, South of change. Perform isotopic Towers Club analysis on composite sample 13S6 0.4 mi W Former Laydown Area, (by location) quarterly.

West of Confer's Lane'PN.

12G I 15 mi WSW Bloomsburg Service Direct Radiation IS2 Perimeter Fence -0.2 mi N Quarterly Gamnia Dose: Quarterly.

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

Page of 3 Exposure Pathways Number of Samples Sampling and Type and and Locations~ Collection 1re uenc Fre uene ofhnal sis 6S9 Perimeter Fence - 0.2 mi ESE 7S6 Perimeter Fence - 0.2 mi SE 7EI Harwood Transmission Line Pole N2 - 4.2 mi SE 7GI PPN. Hazleton Complex - 14 mi 8S2 Fence - 0.2 mi SSE SE'erimeter 8B2 LaWall Residence - 1.4 mi SSE 8D3 Mowty Residence - 4.0 mi SSE 9S2 Security Fence - 0.2 mi S 9D4 Country Folk Store - 3.6 mi S IOSI Post South of Switching Station -0.4 mi SSW IODI Ross Ryman Farm - 3.0 mi SSW IIS3 Security Fence - 0.3 mi SW IIEI Thomas Residence - 4.7 mi SW 12S3 Perimeter Fence -0.4 mi WSW 12EI Berwick Hospital - 4.7 mi WSW 12GI Pal, Bloomsburg Service Center - 15 mi 13S2 Fence -0.4 mi W WSW'erimeter 13E4 Kessler Farm -4.1 mi W 14S5 Beach Grove Rd. 4 Confer's Lane Intersection 0.5 mi WNW 14B3 Moskaluk Residence - 1.3 mi WNW ISFI Zawatski Farm - 5.4 mi NW 15S5 Perimeter Fence - 0.4 mi NW 16SI Perimeter Fence 0.3 mi NNW 16S2 Perimeter Fence -0.3 mi NNW 16FI Hidlay Residence - 7.8 NNW Waterborne 6S6 river water intake line'S7 Monthly composite Gatnma isotopic analysis.

cooling tower blowdown discharge line Monthly composite Composite tritium analysis at least quarterly.

Drinking l2H2 Danville Water Company Monthly composite Gross beta and gamma isotopic

{Approxintately 30 miles downstream) analyses monthly. Composite for tritium analysis at least quarterly.

Rev. 3

.I Page 3 Exposure Pathways Number of Samples Sampling and Type and and Locations~ Collection Fre uenc Fre uenc ofhual xis 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 Semi-montMy when animals are on pasture, Gamma isotopic and 1-131 montMy otherwisc analysis of each sample Fish and Invertebrates Outfall area Semi-annually. One sample'rom each of Gamma isotopic on edible 2H Falls, two reacreationally important species from portions.

Pa'Approximately 30 mi NNE) any of the following families: bullhead catfish, sunfish, pikes, or perches.

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.

"Ifa 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 willbc documented in the REMP annual report.

'Control sample location.

'Two-week composite ifcalculated doses due to consumption of water exceed onc millirem per year. In these cases, I-131 analyses willbe 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.

53 OAT Rev. 3

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).

54 DAT Rev. 3

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.

55 OAT Rev. 3

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.

and filtration are considered appropriate Demineralization modem 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 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.~'"

r 'ne

'0.7 Monit 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:

CORR TION FACTORS ROUTIN FFLUENT MONITORS MIO LNE ~PTIC I Reactor Building Unit 1 1.5 3.2 Reactor Building Unit 2 1.5 3.2 Turbine Building Unit 1 1.6 3.6 Standby Gas Treatment 1.5 3.9 Turbine Building Unit

'.6 2 1.6 CORR CT ON FACTORS POST ACC DENT VENT MONITORS ~IU IN ~PNN CULNIN Turbine Building Unit 1 1.7 4.2 Standby Gas Treatment 1.6 4.4 Turbine Building Unit 2 1.7 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: Atmospheric .

Demineralizer Effluent Results, PLI-70612, 3/4/92.

57

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.

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 A

DAT 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 REFERENCE 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 (1) PP5L Calculation EC-ENVR-1008 61 Rev. 3

TABLE 8 SYSTB5 CLASSIFIED AS NOT AN EFFLUENT PATHWAY (Page 2 of 3)

SYSTEN DESCRIPTION REFERENCE 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 (1) PP8L Calculation EC-ENVR-1008 62 DAT Rev. 3

f' TABLE 8 SYSTEMS CLASSIFIED AS NOT AN EFFLUENT PATHWAY (Page 3 of 3)

SYSTEM DESCRIPTION REFERENCE 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 63 Rev. 3

TABLE 9 SYSTENS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAY SYSTEM DESCRIPTION REFERENCE 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 Rev. 3

TABLE 10 SYSTENS CLASSIFIED AS SIGNIFICANT EFFLUENT PATHWAY SYSTEH DESCRIPTION REFERENCE Li uid Waste Mana ement S stems Gaseous Waste Mana ement Systems (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 Date Supervisor-Environmental Services Nuclear M~s o.z Date

/ eetsng Approved By Oate Hanager-Nuclear Technology

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

APPROVAL REVISION TABLE JPPGE ~0A E DATE 5-6c Composite Dose Factors: Haximum Hypothetical Child (2pp)....................................5-6c(1,2) 2/18/94 3/11/94 5-6d Water Ingestion Dose Factors: Haximum Hypothetical Infant (2pp)......................5-6d(1,2) 2/18/94 3/ll/94 Operational Radiological Environmental 6 .

Honitoring Program.............................. 48 4/17/95 . 4/20/95 49 3/23'/95 3/30/95 50 4/17/95 4/20/95 7 Detection Capabilities for Environmental Sample Analysis................................. 51 1/16/95 1/20/95 52 1/1'6/95 1/20/95 8 Systems Classified as Not an Effluent Pathway... 61 3/29/95 3/30/95 9 Systems Classified as Insignificant Effluent p athway......................................... 3/29/95 3/30/95 10 'Systems Classified ~

as Significant Effluent

~

p athway ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 65 3/29/95 3/30/95 B-1 Radiological Environmental Honitoring Program Annual Summary.................................; 8-3 12/11/89 12/11/89 B-2 Reporting Levels for Nonroutine Operating R eports....'..................................... B-4 12/11/89 3/11/94 D-l Dilution Factors and Transit Times for SSES Effluents to Danville, PA....................... D-l 11/9/93 3/ll/94

Page 1 o TABLE 6 OPERATIONAL RADIOLOGICALENVIRONMENTALMONITORING PROGRAM Exposure Pathways Number of Samples Sampling and Type and and Locations* Collection Fre uenc Fre uenc ofhnal sis hirborne Radioiodine and 12S I 0.4 mi WSW EOF Building sampler operation with sample Radioiodine Canister: analyze Particulates~ 9BI 1.3 mi S Transmission Line collection weekly." weekly for 1-131 5S4 0.8 mi E Environmental Laboratory 12EI 4.7 mi WSW Berwick Hospital 7G I 14 mi SE PP&L Hazleton Particulate Sample:

Center'ontinual Complex'SES 3S2 0.5 mi NE Backup Met. Tower Analyze for gross beta 7S7 0.4 mi SE End of Kline's Road radioactivity following filter IOS3 0.6 mi SSW . East of Confer's Lane, South of change. Perform isotopic Towers Club analysis on composite sample 13S6 0.4 mi W Former Laydown Area, (by location) quarterly.

West of Confer's Lane'P&L 12G I 15 mi WSW Bloomsburg Service Direct Radiation IS2 Perimeter Fence - 0.2 mi N Quarterly Gamma Dose: Quarterly.

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 nnfF. Rev. 4

Page 3 Exposure Pathways Number of Samples Sampling and Type and and Locations* Collection Fre uenc 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 Semi-monthly when animals are on pasture, Gamma isotopic and I-131 IOG I Davis Farm - 14.0 mi. monthly otherwise analysis of each sample Ray Ryman Farm - 3.5 mi. SSW SSW'OD2 10D I KLC Ryman Farm - 3.0 mi. SSW Fish and Invertebrates Outfall area Semi-annually. One sample'rom each of Gamma isotopic on edible 2H Falls, two reacreationally important species from portioils.

Pa'Approximately 30 mi NNE) any of the following families: bullhead catfish, sunfish, pikes, or perches.

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.

~~'Ifa 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 ifcalculated doses due to consumption of water exceed one millirem per year. In these cases, 1-131 analyses willbe performed.

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

DAT

I PENNSYLVANIAPOWER & LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION QFFSITE DOSE CALCULATIONMANUAL Revision 6 Prepared by: Date:

Reviewed by: Date:

Supervisor Environmental Services - Nuclear Reviewed by: Date:

PORC/Meeting No.

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 Approval Rev>sion

~pa e Date Date

1.0 INTRODUCTION

7/14/95 7/20/95 7/14/95 7/20/95 1119/93 3/11/94 2.0 SETPOINTS 2/5/92 2/21/92'/21/92 2.1 Waterborne Effluent Monitors 2/5/92 12/11/89 12/11/89 2/5/92 2/21/92 12/11/89 12/11/89 12/11/89 12/11/89 2.2 Airborne Effluent Monitors 9 2/5/92 2/21/92 10 12/11/89 12/11/89 11 12/11/89 12/11/89 12 '1/21/92 11/25/92 3.0 WATERBORNE EFFLUENT CONCENTRATION 2/5/92 2/21/92 MEASUREMENTS 14 2/5/92 2/21/92 4.0 AIRBORNE EFFLUENT DOSE RATES 15 2/5/92 2/21/92 4.1 Noble Gases 15 1/16/95 1/20/95 4.2 Radionuclides Other Than Noble Gases 16 1/16/95 1/20/95 17 2/11/92 2/21/92 18 2/5/92 2/21/92 19 12/11/89 12/11/89 20 12/1/92 12/4/92 5.0 INDIVIDUALDOSE DUE TO WATERBORNE EFFLUENT 10/29/93 3/11/94 5.1 Fish Pathway Liquid Effluent Dose Calculation Methodology 2/18/94 3/11/94 5.2 Potable Water Pathway Effluent Dose Calculation Methodology 23 11/9/93 3/11/94 5.3 Shoreline Exposure Pathway 24 11/9/93 3/11/94 5.4 Projected Dose From Liquid Effluent 24 11/9/93 .3/11/94 25 2/18/94 3/11/94 26 11/9/93 3/11/94 6.0 INDIVIDUALDOSE DUE TO AIRBORNE EFFLUENT 27 10/29/93 3/11/94 6.1 Noble Gases 27 10/29/93 3/11/94 6.2 Radionuclides Other Than Noble Gases 28 10/29/93 3/11/94 29 10/29/93 3/11/94 7.0 'OTAL DOSE 30 1/16/95 1/20/95 31 10/29/93 3/11/94 Rev. 5

Approval Revision

~Pa e Oats Date 8.0 OPERABIUTY OF WASTE TREATMENT SYSTEMS 32 10/29/93 3/11/94 8.1 Liquid Waste Treatment 32 1/16/95 1/20/95 33 1/16/95 1/20/95 8.2 Gaseous Waste Treatment 34 1/16/95 1/20/95 35 1/16/95 1/20/95 8.3 Solid Waste Treatment 36 1/16/95 1/20/95 37 1/16/95 1/20/95 9.0 RADIOLOGICALENVIRONMENTALMONITORING 42 1/16/95 1/20/95 PROGRAM 9.1 Definitions 42 1/16/95 1/20/95 9.2 Monitoring Program 42 1/16/95 1/20/95 9.3 Census Program 43 1/16/95 .1/20/95 9.4 Intertaboratory Comparison Program 44 1/16/95 . 1/20/95 45 1/16/95 1/20/95 10.0 DOSE ASSESSMENT POLICY STATEMENTS 53 7/14/95 7/20/95 10.1 Selection of Analysis Results for Dose Calculations 53 7/14/95 7/20/95

~ 10.2 Assignment of Releases to the Reactor Units 53 7/14/95 7/20/95 10.3 Evaluation and Monitoring Criteria for Effluent 53 7/14/95 7/20/95 Pathways 10.4 Flow From the Sgts Vent When the System is Not 54 7/14/95 7/20/95 In Use 10.5 ODCM Setpoints Are Upper Limit Values 56 7/14/95 7/20/95 10.6 Definition of "Appropriate Treatment" for 56 7/14/95 7/20/95 Liquid Wastes 10.7 Monitor Line-Loss Corrections 58 7/14/95 7/20/95 10.8 Selection of Data For Determination of Dose 59 7/14/95 7/20/95 Rate Compliance 10.9 Low-Level Radioactivity in the Sewage 60 7/14/95 7/20/95 Treatment Plant 11.0 ODCM REVIEW AND REVISION CONTROL 68 7/14/95 7/20/95 DAT Rev. 5

Approval Revision

~Pa e Date Date Appendix A - Sample Calculations of ODCM Parameters A-1 2/5/92 2/21/92 A-2 2/5/92 2/21/92 A-3 12/11/89 12/11/89 AQ 2/5/92 2/21/92 A-5 10/29/93 3/11/94 AW 10/29/93 3/11/94 A-7 10/29/93 3/11/94 A-8 10/29/93 3/11/94 A-9 2/5/92 2/21/92 A-10 2/5/92 2/21/92 A-11 10/29/93 3/11/94 A-12 10/29/93 3/11/94 A-13 10/29/93 3/11/94 Appendix B - Reporting Requirements B-1 12/11/89 12/11/89 B-2 10/29/93 3/11/94 B-3 12/11/89 12/11/89 BP 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

LIST OF TABLES Approval Revision Table ~pa e 1 Radiological Effluent Objectives and Standards 11/9/93 3/11/94 2 Dose Factors for Noble Gases 18 2/5/92 2/21/92 3 Sample Annual Average Relative Concentrations and Deposition Rates 19 11/9/93 3/11/94 4 Dose Factors for Inhalation, Ingestion and Ground Exposure Pathways: Radionuciides Other Than Noble Gases ~ 20 12/1/92 12/4/92 5-1 a Dose Factors for Fish Pathway, Maximum Hypothetical Adult (2pp) 5-1 a(1,2) 10/10/94 10/14/94 5-1b Dose Factors for Fish Pathway, Maximum Hypothetical Teen (2pp) 5-1b(1,2) 10/10/94 10/14/94 5-1c Dose Factors for Fish Pathway, Maximum Hypothetical Child (2pp) 5-1 c(1,2) 10/10/94 10/14/94 5-2a Dose Factors for Potable Water Pathway, Maximum Hypothetical Adult (2pp) 5-2a(1,2) 10/29/93 3/11/94 5-2b Dose Factors for Potable Water Pathway, Maximum Hypothetical Teen (2pp) 5-2b(1,2) 10/29/93 3/11/94 5-2c Dose Factors for Potable Water Pathway, Maximum Hypothetical Child (2pp) 5-2c(1,2) 10/29/93 3/11/94 5-2d Dose Factors for Potable Water Pathway, Maximum Hypothetical Infant (2pp) 5-2d(1,2) 10/29/93 3/11/94 5-3 Radioactive Decay Constants 5-3 10/29/93 3/11/94 5Q Dilution Factors and Transit Times for SSES Effluents to Danville, PA 5A(1,2) 10/29/93 3/11/94 5-5 Dose Factors for Shore Exposure Pathway, All Age Groups (2pp) '5-5(1,2) 10/29/93 3/11/94 5<a Composite Dose Factors: Maximum Hypothetical Adult (2pp) 5-6a(1,2) 10/10/94 10/14/94 5-6b Composite Dose Factors: Maximum Hypothetical Teen (2pp) 5-6b(1,2) 10/10/94 10/14/94 Rev. 5 IV DAT

Approval Revision Table ~Pa e Date Oate 5-6c Composite Dose Factor: Maximum Hypothetical Child (2pp) 5-6c(1,2) 2/18/94 3/11/94 1

5-6d Water Ingestion Dose Factors: Maximum Hypothetical Infant (2pp) 5-6d(1,2) 2/18/94 3/11/94 6 Operational Radiological Environmental Monitoring Program 48 4/17/95 ,4/20/95 49 3/23/95 3/30/95 50 4/17/95 4/20/95 7 Detection Capabilities for Environmental Sample Analysis 51 1/16/95 1/20/95 52 1/16/95 1/20/95 8 Systems Classified as Not an Effluent Pathway 62 7/14/95 7/20/95 9 Systems Classified as Insignificant Effluent Pathway 65 8/7/95'/20/95 10 Systems Classified as Significant Effluent Pathway 66 7/14/95 7/20/95 11 Systems with NRC I/E Bulletin 80-10 Applicability 67 8/7/95 7/20/95 B-1 Radiological Environmental Monitoring Program Annual Summary B-3 12/11/89'2/11/89 B-2 Reporting Levels for Nonroutine Operating Reports B-4 12/11/89 12/11/89 D-1 Dilution Factors and Transit Times for SSES Effluents to Danville, PA D-1 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 Approval Revision

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

0 1

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 53 Rev. 5

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.

54 Rev. 5

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, 55 Rev. 5

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.

56 Rev. 5

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.

57 Rev. 5

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 1.5 3.2 Reactor Building Unit 2 1.5 3.2 Turbine Building Unit 1 1.6 3.6 Standby Gas Treatment 1.5 3.9 Turbine Building Unit 2 1.6 3.6

. CORRECTION FACTORS Post-Accident Vent Monitors iodine Particulates Turbine Building Unit 1 Standby Gas Treatment 1.7 1.6 '4 4.2 Turbine Building Unit 2 1.7 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.

58 DAT Rev. 5

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.

59 OAT Rev. 5

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 above natural background levels. 'resent

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

1. Dispose of the sludge as low level radioactive waste.

60 Rev. 5

I'

"~v'i 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.

61 Rev. 5

TABLE 8 SYSTEMS CLASSIFIED AS NOT AN EFFLUENT PATHWAY(Page 1 of 3)

SYSTEM DESCRIPTION REFERENCE 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 PPRL Calculation EC-ENVR-1 008 62 Rev. 5

TABLE 8 SYSTEMS CLASSIFIED AS NOT AN EFFLUENT PATHWAY(Page 2 of 3)

SYSTEM DESCRIPTION REFERENCE Suppression Pool Primary Containment Vacuum Breakers Suppression Pool Cleanup Reactor Water Cleanup Pressure Vessel 'eactor 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 PP8L Calculation EC-ENVR-1008 63 Rev. 5

TABLE 8 SYSTEMS CLASSIFIED AS NOT AN EFFLUENT PATHWAY(Page 3 of 3)

SYSTEM DESCRIPTION REFERENCE 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 (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 64 Rev. 5

bl II

TABLE 9 SYSTEMS CLASSIFIED AS INSIGNIFICANTEFFLUENT PATHWAY SYSTEM DESCRIPTION REFERENCE H2 Seal Oil Condensate/Refuel Water Storage Tank and Berm Main Turbine/RFPT Lube Oil/H2 Seal Oil (1), (8)

Instrument Air (1) (8)

Service Air (1), (8)

Temporary Laundry Facility (2)

Second Sort (DAW Volume Reduction) Facility (3)

Low Level Radwaste Handling Facility (4)

Sewage Treatment Plant (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.

65 Rev. 5

TABLE 40 f

SYSTEMS CLASSIFIED AS SIGNIFICANT FFLUENT PATHWAY SYSTEM DESCRIPTION REFERENCE Liquid Waste Management Systems (5)

Gaseous Waste Management Systems (6)

(5) SSES FSAR Chapter 11.2 (6) SSES FSAR Chapter 11.3

, oa 66 Rev. 5

TABLE 11 SYSTEMS WITH NRC VE BULLETIN 80-10 APPLICABILITY SYSTEM NO. DESCRIPTION Service Water (F/P HTX Discharge) 16 RHR Service Water 18 Instrument Air 19 Service Air 27 Auxiliary Boilers 35 Shutdown Decay Heat Removal System 40 Batch Lube Oil Tank 48 Feedwater Pump Turbine Lube Oil 52 H2 Seal Oil Tank 54 Emergency Service Water 93 Main Turbine Lube Oil 99D Sewage Treatment Plant Rev. 5 67 OAT

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.

68 Rev. 5

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

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1 PROCEDURE COVER SHEET

'NUCLEAR DEPARTMENT PROCEDURE SOLID RADIOACTIVE WASTE NDAP-QA-064'6 PROCESS CONTROL PROGRAM Revision 4 Page 1 of 63

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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 Date 3 -~~. 9S Revi'ewed by Date Superv Recommended ctiona Un Manager PORC Committee Heeting No.

Date ERC Co tt Approved by Date FORM NDAP-QA-0002-1, Rev. 1, Page 1 of 1 IIIIHlslllllllIIIINlllIIIllIIIIlslflfllIIII lslllIIllliIlllllIlllSIl

NDAP-OA-0646 Revision 4 2 of 63'age 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), 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.

3) 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) Added Radlok (SEG) type containers to High Integrity Container approved for use list.

,6) 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.

NDAP-gA-0646 Revision 4 Page 3 of 63 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE

2. 0 POLICY/DISCUSSION ,6

3.0 REFERENCES

4. 0 RESPONSIBILITIES

4. 1 EFFLUENTS MANAGEMENT SUPERVISOR 4.2 SUPERVISOR - OPERATIONS TECHNOLOGY 4.3 . POMER PRODUCTION ENGINEER - EFFLUENTS MANAGEMENT 4.4 HEALTH PHYSICIST EFFLUENTS MANAGEMENT 10 4.5 RADMASTE SUPERVISOR 10 4.6 CHEMISTRY SUPERVISOR 4.7 HP FOREHAN EFFLUENTS MANAGEMENT 12 4.8 MANAGER-NUCLEAR ASSESSMENT SERVICES 13 4.9 AUXILIARY SYSTEHS OPERATOR 13

4. 10 SOLIDIFICATION/DEWATERING/SERVICES VENDOR 13

4. 11 HANAGER NUCLEAR PROCUREMENT 4.12 HANAGER - NUCLEAR SYSTEMS ENGINEERING 14 4.13 MANAGER NUCLEAR MAINTENANCE 14 4.14 LICENSING SUPERVISOR 14

4. 15 MANAGER NUCLEAR TRAINING 15

4. 16 HANAGER - NUCLEAR SECURITY 15

5. 0 DEFINITIONS 15

NDAP-gA-0646 Revision 4 Page 4 of 63 TABLE OF CONTENTS Continued SECTION PAGE 6.0 PROCEDURE 20 .

6. 1 CONTRACTED VENDOR SERVICES 20 6.2 WASTE TYPES 21

'7 6.3 RADIOACTIVE MASTE ANALYSIS AND CLASSIFICATION 6.4 TESTING/TREATMENT OF SOLIDIFIED RADMASTE FOR 30 COMBUSTIBLE GASES

6. 5 RADIOACTIVE WASTE SOLIDIFICATION 30 6.6 RADIOACTIVE WASTE DEWATERING 40 6.7 HIGH INTEGRITY CONTAINERS (HIC) 42 6.8 IRRADIATED HARDMARE PROCESSING AND DEWATERING 46

6. 9 CONTAINER INSPECTIONS 6.10 WASTE CONTAINER SPACE UTILIZATION 47 6.11 STORAGE OF PACKAGED RADIOACTIVE WASTE 47 6.12 TRANSPORTATION, SHIPPING AND DISPOSAL REGULATIONS 48 6.13 SHIPPING OF RADIOACTIVE .WASTE 6.14 SHIPMENT CONFIRMATION 51 6.15 CHANGES TO THE SOLID RADIOACTIVE MASTE PROCESS 51 CONTROL PROGRAM 6.16 EVALUATION OF PROCESS OR OPERATIONAL CHANGES 51 6.17 REPORTING OF HISHAPS INVOLVING LOW LEVEL 52 WASTE FORNS 6.18 PCP IHPLEHENTING PROCEDURES 53 7.0 RECORDS 54

NDAP-0A-0646 Revision 4 Page 5 of 63 ATTACHMENTS ATTACHMENT PAGE A Solidification Record Sheet 55 B Dewatering Record Sheet 56 C Susquehanna Guaranteed Solidified/Dewatered Waste Volume Record D PCP Implementing Procedure Matrix 60 E Materials not Compatible with Polyethylene Containers 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 SSES Technical Specifications Section 3/4. 11.3, Solid Radwaste System 3.7 SSES Technical Specifications Section 6.13, Process Control Program (PCP)

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NDAP-0A-0646 Revision 4 Page 7 of 63 3.8 NUREG 0800, Standard Review Plan 11.4 Solid Waste Management Systems 3.9 Technical Position on Waste Form Rev. 1, 1991 3.10 Technical Position on Radioactive Waste Classification, Rev. 0, 1983 3.11 Technical Position on Concentration Averaging and Encapsulation; Rev. 0, 1995 3.12 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 3.13 Regulatory Guide 1.143, Design Guidance of Solid Waste Management'ystems 3.14 Regulatory Guide 7. 1, Administrative Guide for Packaging and Transporting Radioactive Material 3.15 ANSI/ANS 40.35, Volume Reduction of Low Level Radioactive Waste 3.16 ANSI/ANS40.37, Mobile Radioactive Waste Processing Systems 3.17 ANSI/ANS 55.1, Solid Radioactive Wast'e Processing System for Light Water Cooled Reactor Pl.ant 3.18 Pacific Nuclear Dewatering System Topical Report No. TP-02-P-A, Rev. 3 3.19 Pacific Nuclear Solidification Process Control Procedure No.

PT-51-WS, Rev. 40 3.20 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 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 4.0 RESPONS I BI LITIES 4.1'ffluents Management Supervisor responsibilities:

4.1.1 Developing and implementing programs and procedures for radioactive waste processing, packaging, transportation and disposal.

4.1.2 Maintaining the overall radwaste program to ensure compliance with applicable radiological and shipping regulations.

4.1.3 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 Maintaining a current copy of local, state, federal and disposal facility regulations pertaining to disposal and transportation of low level radioactive waste.

4.2.3 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 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.

4.3.3 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.

4.3.4 Perform the duties of Radwaste Supervisor as specified in this procedure in his absence.

4.3.5 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 Maintain a sampling and arialysis program to ensure 10CFR61 compliance.

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

4.4.3 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.

4.4.4 Perform the duties of HP Foreman - Effluents Management as specified in this procedure in his absence.

4.4.5 Coordinate radioactive material evaluation of product acceptability for disposal at specific disposal facilities.

4.5 Radwaste Supervisor responsibilities:

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

4.5.2 Ensure appropriate waste solidification and.dewatering 4.5.4'nsure records'are generated.

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

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

NDAP-gA-0646 Revision Page ll of4 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 Ensure Solidification and Dewatering operations are carried out in an ALARA manner.

4.5.6 Interface with HP Foreman - Effluents management for liner and cask selection for solid waste shipping activities.

4.5.7 Ensure proper marking of containers prior to filling.

4.5.8 Ensure solidification/dewatering personnel are adequately trained per NTP-gA-42.6.

4.5.9 Estimate classification of waste for container selection and processing method.

4.5.10 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.

4.5.11 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.

4.5.12 Complete and process High Integrity Container User Certification Statement to ensure the container is used properly.

4.6 Chemistry Supervisor responsibilities:

4.6.1 Perform required sample preparation and analysis in accordance with approved chemistry procedures, 4.6.2 Perform test solidification if required. Store test solidification billet if required.

4.6.3 Provide density of initial and final waste form.

4.6.4 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 Complete Chemistry portion of the Solidification and Dewatering Records.

4.6.6 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- Effluents Management responsibilities:

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

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

4.7.3 Storage of packaged radioactive waste within the radwaste facilities.

4.7.4 Determine waste classification and description of solidified, dewatered, and other packaged waste.

4.7.5 Final disposition of solidified, dewatered and other packaged waste.

4.7.6 Ensures SSES is a registered user of applicable High Integrity Containers at specific disposal facilities.

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

4.7.8 Evaluate vendor services provided to ensure efficient and economical methods are used.

4.7.9 Complete and process Cert:" cation Statement for Disposal of High Integrity Containers as required by applicable regulatory agencies.

4.7.10 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 Perform periodic audit of implementation of this program and review of radwaste service vendor's gA Programs.

4.8.2 Inspection of Radwaste,Containers as required by applicable procedures.

4.8.3 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.

4.8.4 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 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.

4.10.3 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.

4.10.4 Provide procedures that are or can be placed into the SSES procedure format for the services being provided.

4.10.5 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 Complete applicable sections of Solidification and Dewatering Records required for each container processed.

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

'4.10.8 Provide a description of the equipment/process that; is used in processing waste.

4.10.9 Obtain waste samples from processing equipment in accordance with approved operating .procedures.

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

4.11 Hanager- Nuclear Procurement responsibilities:

H 4.11.1 Ensure High Integrity Containers are not exposed to ultra violet light (sunlight).

4.11.2 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 Calibration and maintenance of applicable plant equipment in Radwaste Processing Systems.

4.13.2 Provide maintenance personnel to support processing, packaging and transportation of low level radioactive waste.

4.14 Licensing Supervi sor responsibi1 i ties:

4.14.1 Submitting transportation cask user registration requests to, NRC per 10CFR71. 12.

NDAP-gA-0646 Revision 4 Page 15 of 63 4.14.2 'Submitting to the NRC the Annual Radioactive Effluent Release Report.

4.14.3 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 i i g tra'ni Prov'd'n i ng a n d 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 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.

5.3 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 CHEMICAL FORM: The chemical content of the Radioactive Material being shipped.

5.8 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])

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

5.13 DEWATERED: The removal of free liquid from solid material to a point where less than IX for HIC's and less than 0.5X for steel liners by waste volume remains as required by the disposal facility license.

5.14 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])

5.15 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

'5.16 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 101 and 172.102, and materials that meet F

the defining criteria for hazard classes and divisions in 49CFR173.

.NDAP-gA-0646 Revision 4 Page 17 of 63 5.17 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.

=

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

5.18.4 Is responsible for safety of transporting h'azardous material.

5.19 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.

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

5.21 ISOTOPIC ANALYSIS: The identification of the isotopic elements .

involved in a sample of Radioactive Material.

5.22 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) 5.23 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])

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

5.25 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 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.

5.27 MIXING RATIO: The ratio of waste to cement and additives required for satisfactory solidification.

5.28 MIXING RECIPE: The amount of waste, cement and additives mixed to solidi fy waste.

5.29 MIXED WASTE: A mixture of low level radioactive and hazardous waste.

5.30 NORMAL FORM RADIOACTIVE MATERIALS: Means radioactive materials which do not meet the requirements of Special Form Radioactive Materials (49 CFR 173.403[s]).

5.31 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) 5.32 PROCESS CONTROL PROGRAM (PCP): Program which contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is assured.

5.33 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])

5.34 RADWASTE WORKER: A Hazmat Employee involved with the. collection',

packaging, and transportation of radioactive waste.

5.35 SEALED SOURCES: Any by-product material that is encased in a capsule designed to prevent leakage o scape of by-product material.

5.36 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 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.

5.38 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).

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

5.40 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.

5.41 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).

5.42 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])

5.43 TYPE "A" QUANTITY RADIOACTIVE MATERIAL: That material which may be transported in Type "A" packaging. (49CFR 173.431[a])

5.44 TYPE "B" PACKAGING: Packaging which meets the standards for "A" Packaging, and in addition, meets the standards for the Type 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 WASTE STREAM: A by-product of a process system or component with unique characteristics and maintained separate from other waste streams.

5.47 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"..

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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 Solidified radwaste processing services are provided by Vectra, Inc. for waste types included in this Process Control Program.

6.1.2 NRC approved Topical Report TP-'02-P-A, describes, Vectra Inc. waste processing equipment, methods and verification of acceptable waste forms for dewatering.

6.1.3 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.

6.1.4 Volume reduction services are provided by Scientific Ecology Group (SEG) for waste types included in the Process Control Program.

F 1.5 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.

6.1.6 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 (2) Decon Shop drains (3) Chemistry Laboratory sink drains (4) Auxil'iary Boiler blowdown effluent

b. 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 C. Evaporator Concentrates in the range of 0-24 weight percent sodium sulfate (equivalent) shall be solidified for final disposal.

d. 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:

(1) LRW Filter Hedia. and drain liquid (2) Sump Sludge (3) Ultrasonic Resin Cleaner Waste'(URC Waste)

b. 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.

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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. 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.

C. Bead Resin may be used to demineralize Liquid Waste in either steel. liners or High Integrity Containers.

d. Condensate Demineralizer bead resin should be ultrasonically cleaned prior to collection in the Spent Resin Tank.

e. 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 or other evaluated method(s) on a case by case materials 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 filters, Rinse Tank filters and other pump metal components.

NDAP-gA-0646 Revision 4 Page 24 of 63 (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.

b. 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.

(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.

C. Cartridge Filters to be solidified for final disposal shall not be mixed with any other waste type.

d. 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.

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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, and components expended during hardware 'IP's processing and packag'ing acti.vities. Startup sources may also be processed as part of this stream. 'aste

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. The constituents of this waste stream may include turbine lubricating oil, EHC fluid and other petroleum based materials.

b. 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

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less than the waste activity.

.(2) Class B and C sources shall be stabilized within an approved solidification or encapsulation media.

Activated Carbon a0 Activated Carbon from vendor provided liquid waste demineralization is transferred directly to a liner/High Integrity Container. This waste stream is considered Activated- Carbon.

b. 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.

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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 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.

6.2.12 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.

6.2.13 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 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.

6.3.2 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 in plant operations (such as significant of'0) 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: *.

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.

b. Class B Physical form and characteristics .

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

C. Class C - Physical form and characteristics shall meet both the minimum and stability

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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. Complete radionuclide analysis of waste sample.

d. 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:

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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 ~ Wet Waste Collection tanks shall be recirculat'ed in accordance with approved operating to sampling or analysis.

procedures'rior

b. Waste processing in solidification liners/High Integrity Containers shall be mixed in accordance with approved procedures prior to sampling or analysis.

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.

6.3.8 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.

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'.3.9 Deviations from sampling and analysis requirements shall be approved by Chemistry Supervisor and Effluents Management Supervision.

( ) 6.4 TESTING/TREATMENT 'OF SOLIDIFIED RADWASTE FOR COMBUSTIBLE'GASES

(')

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

6.5 RADIOACTIVE WASTE SOLIDIFICATION 6.5.1 General Requirements a 0 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.

b. High Integrity Contasners shall be used to meet the stability crite.'. in accordance with federal and disposal facility regulations.

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

Services Vendor personnel.

d. 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. Preconditioning of waste shall be performed if required prior to determining mixing ratios.

C. 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. Waste preconditioning shall be performed in accordance with approved procedures to ensure waste is within the acceptable envelope for solidification.

e. 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 ~ Determination of mixing ratios .shall be performed for each waste batch to be processed.

b. Deviation from the recommended mixing ratios shall be reviewed by Plant Operations Review Committee (PORC).

c Chemistry Group determines:

(1) Density of the waste samples.

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

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

e. 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.

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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 device. Nominal surface 'nyielding 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.

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Oeviation from the container checking requirement, shall be approved by the Radwaste Supervisor.

Handling of Unacceptable Solidified Waste Containers.

a. If a solidified waste container does not meet acceptability requirements, a Condition Report (CR) shall be issued.

b. 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.

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

(5) 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.

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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.

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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 ~ 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.

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

Dewatering Services Vendor personnel.

c~ Dewatering of Radioactive Waste shall be

performed in accordance with approved procedures.

d. 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.

e. 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.

b. Once filled a High Integrity Container.may be stored for a period until a total of. one (1) year of ultraviolet radiation is received.

C. 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 6.7.2 Uses of High Integrity Containers a 0 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 <1 47'ms/cc (2) Loading temperature <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 <18500 lb (15) Enduropak 105 loaded weight <1700 lb (16) Enduropak 205 loaded weight ,<1900 lb (17) Enduropak 150 loaded weight 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. 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.

C. If the container exceeds the limits for Low Specific Activity or contains water and/or substances which could radiolytically

'rganic 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.

d. 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. Irradiated Hardware consisting of non-fuel Special Nuclear Haterial shall be inventoried during processing in accordance with NDAP-(A-0337.

d. 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 agenci es.

6.8.2 Dewatered Product'. Control

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.

6.8.3 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.

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.

6.10.2 *- ': 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.

6.10.3 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.

6.10.4 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.

6.11 STORAGE OF PACKAGED RADIOACTIVE WASTE 6.11.1 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.

6.11.2 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 Solidification and Dewaterino Records shall be part of the permanent shipping records and adhere to requirements of the Process Control Program.

6.11.4 For materials packaged in a high integrity container, documentation shall be maintained on HIC storage and pre-shipment checklist info'rmation.

6.11.5 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.

6.11.6 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. 49CFR100 - 199 Transportation.

C. Chem-Nuclear Systems Inc. Barnwell S.C. disposal site operating license number 097 State of South Carolina, as required.

d. Chem-Nuclear System Inc. NRC Material. License 12-13536-01, as required.

e. 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.

- c. Procedures shall contain guality Control notifications or hold points.

6.12.3 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 All radioactive'aste shall be shipped by Effluents Management.

6.13.2 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.

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

6.13.4 Waste containers shall be placed in a USNRC approved licensed shipping container if it:

'a ~ Exceeds Type A quantities

b. Exceeds 1000 mr/hr on contact C. 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 Changes in radioactive waste processing oe operational changes shall be evaluated to determine any impacts on waste characteristics and/or form.

6.16.2 Evaluation should include as a minimum:

a. Operational evaluation of processing impacts:

b. Chemistry evaluation of changes to sampling and analysis methodology.

C. Effluents Management evaluation of packaging and/or shipping impacts.

evaluation for

d. Effluents Management 10CFR61 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. 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).

b. 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.

C. 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.

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.

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

7.4 Radioactive waste shipping documentation shall consist of, but not limited to, the following records:

7.4.1 Radioactive Material Shipping Manifest 7.4.2 Evaluation of isotopic mix and concentration 7.4.3 Radiological surveys of:

a. Vehicle upon arrival

b. Package to be shipped

c. Loaded vehicle prior to shipment 7.4.4 Vehicle Safety inspection 7.4.5 Check-off sheet for loading procedure 7.4.6 Documentation of adherence to Process Control Program (i'f applicable) 7.4.7 Special instructions to driver

Attachment A NDAP-gA-0646 SOLIDIFICATION RECORD SHEET Revision 4 Page 55 of 63 PART I: Container Identification Information

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)

Estimated Liner Contact Dose Rates. mR/hr

2. Projected Curie Concentration pCi/gm

3. Expected Waste Classification/Stability

4. Container Type to be Used 5. Empty Weight of Container Tbs

6. Expected Cask Type to be Used PART 3: Documentation Checklist I. Form NDAP-gA-0646-1 (original)

2. 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 Health Physics Data p

.'ll Liner Radiological Survey (original)

Actual Filled Container Weight lb. (If available ALARA)

PART 4: REMARKS:

/ /

WA U O UKASE ~EVTEtt DATE FORM NDAP-OA-0646-1, Rev. 2, Page 1 of 1 (File R69-I)

Attachment 8 NDAP-gA-0646 Revision 4 Page 56 of 63 DEWATERING RECORD SHEET 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)

Estimated Liner Contact Dose Rates mR/hr

2. Projected Curie Concentration pCi/gm

3. Expected Waste Classification/Stability

4. Liner Type to be Used 5. Empty Weight of Container lbs.

6. Expected Cask Type to be Used a waste Superv>sor ate >me FORM NDAP-gA-0646-2, Rev. 3, (DUPLEX), Page 1 of 3 (File R69-I)

Attachment B NDAP-gA-0646 Revision 4 Page 57 of 63 DEWATERING RECORD SHEET PART 3: Sampling and Analysis Tank/Container sampled

2. Sample Number

3. Waste Stream 1sotopic Analysis attached 5.. Specific activity of Dewatered Sample pCi/gm

6. a. Dewatered Volume

b. Dewatered Weight gm

c. Sample density gm/cc x 62.43 lb/ft

7. Composite added/Log entry made on CH-TP-055-1 The 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)

Attachment B NDAP-gA-0646 Revision 4 58 of 63

'age DEWATERING RECORD SHEET PART 4: Container Shipment Information Summary PP8L Liner Number 2.. Waste Volume

3. Form NDAP-gA-0646-2 (original)

4. Waste Form Documentation NN-RP-..., Forms (original )

Calculated Waste Weight lb/ft x lb.

1 Ta Actual Filled Container Weight lb. (if available ALARA) 100 x (Dewatered Waste Volume) ft + ft X TvaiTTol ume

>85% Container Volume Utilized YES / NO (Circle one)

, Waste Waste Form:

Activity Documentation CN-RC-STABLE J

Forms (Copy)

UNSTABLE (Circle one)

Isotopic Analysis (Copy)

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 Date Liner number

2. Waste Type

3. Container Type

4. Burial Volume

5. Useable Container Volume

6. Guaranteed Hinimum Waste Volume

7. 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)

Attachment D NDAP-gA-0646 Revision 4 Page 60 of 63 PCP IMPLEMENTING PROCEDURE MATRIX WASTE PROCESSING 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 Nuclear OH-43-WS 'acific 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 SEG STD-P-22-002 SEG STD-P-03-051 (Resin Express)

WH-RP-106 'M-RP-104 WH-RP-108 Cartrid e Filters CNSI FO-OP-019 (Overpack)

WH-PS-230 Pacific Nuclear OH-16-NS WM-RP-105 II Page 1 of 3

Attachment D NDAP-gA-0646 Revision 4 Page 61 of 63 PCP IMPLEMENTING PROCEDURE MATRIX Irradiated Hardware - Dewatered'teel Liner None Dr Active Waste DAW - Packa in WM-PS-210 Li uid Oil Waste - Solidified Li uid Oil Waste Decontamination None None Solid Sealed Sources None WASTE ANALYSIS AND CLASSIFICATION - 10CFR61 Pacific Nuclear OM-45 NS WM-RP-008 CH-RC-075 WM-PS-155 CK-RC-076 WM-PS-160 CH-TP-OSS 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

Attachment D NDAP-gA-0646 Revision 4 Page 62 of 63 PCP IMPLEMENTING PROCEDURE MATRIX RADIOACTIVE WASTE DEWATERING GENERAL Pacific Nuclear OH-60-WS WH-RP-010 WM-RP-011 HIGH INTEGRITY CONTAINERS Pacific Nuclear OH-16-NS Pacific Nuclear H-18-NS WH-RP-012 DISPOSAL FACILITY RE UIREHENTS WM-PS-180 WM-PS-401 (LLRWHF)

PACKAGING WH-PS-310 (HN-142) WH-PS-354 (CNSI 14-215)

WM-PS-311 (LN-142) WH-PS-316 (SEG 14-215)

WH-PS-315 (SEG 3-82) WH-PS-318 (Westinghouse TCT)

WM-PS-345 (CNSI 14-'195)

WH-PS-351 (CNSI 21-300)

WH-PS-352 (CNSI 8-120A)

WH-PS-356 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

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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, Gasoline

,bexene, octane, etc.)

Acetone iodine Amyl Acetate Amyl Chloride Methyl Aniline Chloride bromide'ethyl Aqua Regia, Hethyl ethyl ketone (t1EK)

Nethylene Chloride Benzene Hoist Chlorine gas Bromine liquid Butane Nitric Acid (50K weight concentration)

Camphor Oil Organ Peroxides Carbon Disulphide Octyl cresol Carbon'Tetrachloride Oleic acid Chlorine liquid Oleum ~

Chlorobenzene Chloroform Pentane Chlorosulfonic acid Petroleum ether Chromic/sulfuric acid Phenol Cyclohexanone Propane Propylene dichloride Dibutylphtalate Dimethylamine Sulfric acid (60% weight concentration)

Di'esel fuel Tetrahydrofurance Ethyl acetate Titanium tetrachloride Ethyl butyrate Toulene Ethyl chloride Trichloroethylene Ethyl ether Turpentine Ethylene chloride Tetralin Ethylene chlorohydrin Ethylene dichloride Xylene Fluorine Furfural Furfuryl alcohol Fuel Oil Page 1 of 1

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I

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II.