CALCULATION - Nuclear Regulatory Commission · PENNSYLVANIA PlNER 5 LIGHT COMPANY SUSQUEHANNA STEAM...

OFFSITE DOSECALCULATION

UAL

s~~""-"'Aw~~ il44i4u'5~&4%4-" i"'"''

0Pennsylvania Power 5, Light CompanyTwo North Ninth StreetAllentown, Pennsylvania 18101-1179

cyppPP6043iPgR @DOCK O>GR

PENNSYLVANIA PlNER 5 LIGHT COMPANYSUSQUEHANNA STEAM ELECTRIC STATION

OFFSITE DOSE CALCULATION MANUAL

Prepared By Date

Reviewed Bynv. em. oup up .- uc ear

Date

Approved Byanager- r Services

Date

PORC REVIEW AFTER APPROVAL SHALL BE ARRANGED BY THE PREPARER.

~ ~ f

gJ

TABLE OF CONTENTS

1.0 INTRODUCTION........................,........,

2t0 SETPOINTSo ~ ~ ~ ~ ~ ~ ~ eo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

2. 1 WATERBORNE EFFLUENT MONITORS..............

2.2 AIRBORNE EFfLUENT MONITORS................

3.0 WATEPBORNE EFFLUENT CONCENTRATION MEASUREMENTS

4.0 AIRBORNE EFFLUENT DOSE RATES .................4. 1 NOBLE GASES...............................4.2 RADIONUCLIDES OTHER THAN NOBLE GASES......

5.0 INDIVIDUALDOSE DUE TO WATERBORNE EFFLUENT....

6.0 INDIVIDUAL DOSE DUE TO AIRBORNE EFFLUENT....6. 1 NOBLE GASES..........................,..6.2 RADIONUCLIDES OTHER THAN NOBLE GASES....

7 o 0 TOTAL DOSE o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~

8.0 OPERABILITY OF WASTE TREATMENT SYSTEMS......8.1 LIQUID WASTE TREATMENT..................8.2 GASEOUS WASTE TREATMENT.................

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

~Pa e

9101112131415151617181920212223

2525262?282930313131323334353637383940

RevisionDate

12/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/89

'2/11/89

12/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/89

9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.9.1 DEFINITIONS...............................9.2 MONITORING PROGRAM........................

9.3 CENSUS PROGRAM.......................9.4 INTERLABORATORY COMPARISON PROGRAM........

10.0 DOSE ASSESSMENT POLICY STATEMENTS............10. 1 SELECTION OF ANALYSIS RESULTS FOR

DOSE CALCULATIONS10.2 ASSIGNMENT OF RELEASES TO THE REACTOR

UNITS I

10.3 CRITERIA FOR POTENTIAL UNMONITOREDRELEASE PATHWAYS

10.4 FLOW FROM THE SGTS VENT WHEN THE SYSTEMIS NOT IN USE

10.5 OOCM SETPOINTS ARE UPPER LIMIT VALUES10.6 DEFINITION OF "APPROPRIATE TREATMENT"

FOR LIQUID WASTES10.7 MONITOR LINE-LOSS CORRECTIONS10.8 SELECTION OF DATA FOR DETERMINATION OF

'OSERATE COMPLIANCE10.9 LOW-LEVEL RADIOACTIVITY IN THE SEWAGE

TREATMENT PLANT

11.0 OOCM REVIEW ANO REVISION CONTROL....:.......

APPENDIX A - SAMPLE CALCULATIONS OF ODCMPARAMETERS...........................

APPENDIX 8 - REPORTING REQUIREMENTS...............

~Pa e

414141

4243444546474849505152

52

52

52

5353

5354,

55

5657

58

A-1A-2A-3A-4A-5A-6A-7A-8A-9A-10A-11A-12A-138-18-28-38-4

RevisionDate

12/11/8912/11/8912/11/89

12/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/89

12/11/89

12/11/89

12/11/89

12/11/8912/11/89

12/11/8912/11/89

12/11/89

12/11/8912/11/89

12/11/89

12/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/89

I

APPENDIX C - SITE SPECIFIC INFORMATIONUSED BY GASPAR CODE.................,

APPENDIX 0 - SITE SPECIFIC INFORMATIONUSED BY LADTAP CODE..................

APPENDIX E - METHODS USED TO GENERATEDOSE RATE CALCULATIONWORKSHEETS..........................

~Pa e

C-1

D-10-2D-30-4

E-1E-2E-3E-4E-5E-6E-7

RevisionDate

12/11/89

12/11/8912/11/8912/11/8912/11/89

12/11/8912/11/8912/11/8912/11/8912/11/8912/11/8912/11/89

LIST OF TABLES

~Pa eRevision

Date

Table 1 Radiological Effluent Objectives and Standards.. 3

Table 2

Table 3

Dose Factors for Noble Gases ................... 18

Annual Average Relative Concentrations andDeposition Rates................................ 19

Table 4 Dose Rate Parameters for Airborne RadionuclidesOther Than Noble Gases.......................... 20

Table 6 Maximum Pathway Dose Factors Due toRadionuclides Other Than Noble Gases............. 28

Table 5 Waterborne Effluent Dose Parameters for Adults.. 24

12/11/89

12/11/89

12/11/89

12/11/89

12/11/89

12/11/89

Table 7 Oper ational Radiological EnvironmentalMonitoring Program....................,.......... 47

4849

12/11/8912/11/8912/11/89

Table 8 Detection Capabilities for EnvironmentalSample Analysis................................. 50

Table B-1 Radiological Environmental Monitoring ProgramAnnual Summary.................................. B-3

Table B-2 Reporting Levels for Nonroutine OperatingReports......................................... B-4

12/11/89

12/11/89

12/11/89

LIST OF FIGURES

~Pa eRevision

Date

Figure 1

Figure 2

Liquid Radwaste System Flow Diagram......... 37

Offgas and Recombiner System Flow Diagram... 38

Figure 3 Solid Waste Management System Flow Diagram.. 39

Figure 4

Figure 5

Figure 6

SSES Dry Contaminated Waste Processing...... 40

Onsite Environmental Sampling Locations-Susquehanna SES............................. 45

Offsite Environmental Sampling Locations-Susquehanna SES............................. 46

Figure D-1 Dilution Factors and Transit TimesAs A Function Of River Level ............... 0-4

12/11/89

12/11/89

12/11/89

12/11/89

12/11/89

12/11/89

12/11/89

OEC 4 1 1989

I ~ ~

8

LIST OF WORKSHEETS

~Pa e Revision Date

Dose Rate Calculation Worksheet-Noble Gas Nuclides; Using Vent Monitor Data~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ o E 4

Dose Rate Calculation Worksheet-Noble Gas Nuclides; Using Laboratory Analysis Data~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o E 5

12/11/89

12/11/89

Dose Rate Calculation Worksheet-Nuclides other than Noble Gases;Using Vent Monitor Data~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e E 6 12/11/89

Dose Rate Calculation Worksheet-Nuclides Other than Noble Gases;Using Laboratory Analysis Data~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o E 7 12/11/89

OEC 11, $89

vi

1.0 INTRODUCTION

The purpose of this manual is to provide the parameters and methodology tobe used in calculating offsite doses and effluent monitor setpoints forthe Susquehanna Steam Electric Station, Units 1 and 2. Included aremethods for determining maximum individual, whole-body, and organ dosesdue to waterborne and airborne effluents to ensure compliance with thedose limitations in the Technical Specifications. Methods are includedfor~ performing dose calculations to ensure compliance with the waterborneand airborne treatment system operability sections of the TechnicalSpecifications. This manual includes the methods used for determiningquarterly individual doses for inclusion in Effluent and Waste DisposalSemiannual Reports.

The dose models consider two release modes: airborne and waterborne. Allairborne effluents are treated as ground-level'eleases. Dose to each ofthe seven organs listed in Regulatory Guide 1.109 (bone, liver, totalbody, thyroid, kidney, lung, and GI-LLI) are computed based on theindividual nuclide composition of the effluent. The largest of the dosesare compared to 10 CFR 50, Appendix I design objectives.

Liquid effluents discharged into a river undergo mixing prior toconsumption as either potable water or through the fish pathway. Forreleases to the Susquehanna River, river model dilution factors are used.Doses to the seven critical organs are determined from individual nuclidecontributions and are compared to the 10 CFR 50 Appendix I designobjectives. Compliance with the 10 CFR 20 maximum permissibleconcentrations is done on a batch-by-batch basis prior to discharge.

This manual discusses the methodology to be used in determining effluentmonitor alarm/trip setpoints to be used to ensure compliance with theinstantaneous release rate'limits in the Technical Specifications. Methodsare described for determining the annual cumulative dose to a realindividual from liquid effluents, gaseous effluents, and direct radiationfor critical organs to ensure compliance with 40 CFR 190 limits. The

~~~ 21198g

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 Section9.0 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 toensure that this manual is used in performance of the surveillancerequirements and for compliance with the limiting conditions of operationsstated in the Technical Specifications. It is the responsibility of theManager-Nuclear Services to ensure adequacy and correctness ofcalculational approaches.

OEC 0 1 889

LE 1

RADIOLOGICAL EFFLUENT OBJECTIVES & STANDARDS

10 CFR 50 40 CFR 190*APPENDIX I STANDARDSDESIGN OBJECTIVES (BOTH REACTOR(PER REACTOR UNIT) UNITS COMBINED)

10 CFR 20STANDARDS**(BOTH REACTORUNITS COMBINED)

WATERBORNE EFFLUENTS

Dose to Total Body From all Pathways 3 mrem/yearDose to any Organ From all Pathways - - - - - - - - - 10 mrem/year

AIRBORNE NOBLE GAS EFFLUENTS

Dose Rate to Total Body-Dose Rate to SkinGamma Dose in AirBeta Dose in AirDose to Total Body of an IndividualDose to Skin of an Individual

AIRBORNE RADIOIODINES AND PARTICULATES

Dose Rate to any OrganDose to any Organ From all Pathways

TOTAL URANIUM FUEL CYCLE

Dose to Whole Body From all Fuel Cycle OperationsDose to Thyroid From all Fuel Cycle OperationsDose to any Other Organ From all Fuel Cycle Operations

TOTAL IPUANTITIES RELEASED

Krypton-85 Released per Gigawatt-YearIodine-129 Released per Gigawatt-YearCombined Plutonium-239 and Other Alpha-

Emitting Radionuclides With Half LivesGreater Than One Year Released per Gigawatt-Year

10 mrad/year20 mrad/year

5 mrem/year15 mrem/year

15 mrem/year

500 mrem/year- - - - - - - - 3000 mrem/year

1500 mrem/year

25 mrem/year75 mrem/year

- - 25 mrem/year

50,000 curies5 millicuries

.5 mi llicuries* As currently reflected in Technical Specification 3. 11.4 ~

**Technical Specification limits set to ensure compliance with 10 CFR 20 limits

2.0 SETPOINTS

2.1 WATERBORNE EFFLUENT MONITORS

SPECIFICATION 3.3.7.10 - THE RADIOACTIVE LIQUID EFFLUENT MONITORINGI S RUM N TI N SH WN IN TABLE 3.3.7.10-1 SHALL BE OPERABLE WITHTHEIR ALARM/TRIP SETPOINTS SET TO ENSURE THAT THE LIMITS OFSPECIFICATION 3.11.1.1 ARE NOT EXCEEDED. THE ALARM/TRIP SETPOINTSOF THESE CHANNELS SHALL BE DETERMINED IN ACCORDANCE WITH THEMETHODOLOGY AND PARAMETERS DESCRIBED IN THE OFFSITE DOSE CALCULATIONMANUAL (ODCM).

A-gross radioactivity monitor providing automatic termination of

liquid effluent releases is present on the liquid radwaste effluent

line. Flow rate measurement devices are also present on the liquidradwaste effluent line and the discharge line (cooling tower

blowdown). Precautions, limitations, and setpoints applicable to

the operation of the Susquehanna Steam Electric Station liquideffluent monitors are provided in the applicable plant procedures.

Setpoint values are to be calculated to ensure that alarm and tripactions occur upon approaching the MPC limits of 10 CFR 20 at the

release point to the unrestricted area. The calculated alarm and

trip action setpoints for the liquid effluent monitor and each flow

measurement device must satisfy the following equation:

cf

where:

C = the liquid effluent concentration limit implementing 10 CFR20 for unrestricted areas (uCi/ml).

c = the setpoint (uCi/ml) of the radioactive liquid effluentmonitor measuring the radioactivity concentration in theeffluent line prior to dilution and subsequent release.

the radwaste discharge flow setpoint, in volume per unittime, in the same uni ts as F.

the dilution (cooling tower blowdown) water flow setpointas measured prior to injection of the radwaste, in volumeper unit time.

Radioactive liquid effluents from the SSES are orily discharged as

batch releases and are discharged through the liquid radwaste

effluent line. The radioactive liquid waste stream is diluted in

the plant discharge (cooling tower blowdown) line prior to entering

the Susquehanna River. The limiting batch release concentration (c)

corresponding to the liquid radwaste effluent line monitor setpoint

is calculated from the above expression. The MPC value used for the

liquid effluent concentration limit (C) 'in the above expression for'he

liquid radwaste effluent line monitor setpoint is 1 x 10

uCi/ml or the actual MPC for identified mixtures. Therefore, the

expression for determining the setpoint on the liquid radwaste

effluent line monitor becomes:

c ~ (1 x 10 ) —(uci/ml)'fIn order to prevent spurious isolations by the LRW effluent

radiation monitor, the setpoint concentration, (c) can be defined

as:

c = X(A)

where (A) is the actual tank concentration and X > 1

The setpoint dilution factor must then be some factor, Y (where Y >

X), times the minimum dilution factor.

~ e

1t, i

where F + f = the minimum dilution factorf M

F+f = Y((Af NPC

where F + f = the setpoint dilution factorf

The requirements of Equation (2) are then met as follows:

Y(A) = MPC F + ff

Since, by definition, Y > X and Y(A) P X(A), then:I

(c) = X(A) NPC F + f)f

The setpoint concentration (c) can be converted to a setpoint count

rate by use of the monitor calibration factor.

(Eq. 3)

Setpoint (cpm) = c uCi/ml + Background (cpm)Cal. Factor (uCi/ml per cpm)

The setpoint for the dilution water flow (cooling tower blowdown) is

5000 gpm from either cooling tower basin. The setpoint for the LRW

discharge flow can then be determined from:

(Eq. 4)

Sample calculations for determining the release concentration limits

and setpoints are given in Section A.l.1 of Appendix A.

The Service Water System provides screened water from the cooling

tower basin for cooling plant systems and equipment. The Residual

Heat Removal (RHR) Service Water System provides water" from the

QEC 4 1 1989

Engineered Safeguard Service Water (ESSW) spray pond to the RHR heat

exchangers. In post-accident conditions, RHR Service Water can

supply water for vessel and containment flooding. The Service Water

and RHR Service Water Systems are not normal pathways for liquid

effluents. Radiation monitors are in place on these systems to

provide indication of leaks across heat exchangers into the service

water. The high radiation setpoints for these monitors *are set at

2E-5 uCi/cc cesium-137 equivalent. Considering the radionuclides

predominant in SSES liquid effluents, e.g., Co-58, Co-60, Fe-59,

Mn-54 and Cr,-51, use of a setpoint based on the Cs-137 MPC is

conservative based on the following parameters:

1) photon abundance (85%)

2) magnitude of applicable MPC (2E-5 uCi/cc)

Because Service Water 5 RHR Service Water are not normal release

pathways for liquid effluents, no credit should be taken for

possible dilution scenarios. All service water should be maintained

below 2E-5 uCi/cc Cs-137 equivalent.

In order to minimize the chance of a change in the background of a

monitor masking a significant trend in monitored activity, the alarm

setpoints for the Service Water and RHR Service Water monitors are

determined as follows:

a .. When moni tor background < (2E-5)/Gal . Factor:

HI RAD Setpoint = 0.5 Background + (2E-5)/Cal. Factor

DOWNSCALE or.

LOW RAD Setpoint = 0.5 Background

b. When monitor background >(2E-5)/Cal. Factor:

HI RAD Setpoint = Background + 0.5 (2E-5)/Cal. Factor

DOWNSCALE or

LOW RAD Setpoint = Background - 0.5 (2E-5)/Cal. Factor

Where:

Setpoint = Alarm threshold value to be entered into monitor

(cps for Service Water, cpm for RHR Service

Water).

Background = Monitor background at most recent background

determination (cps for Service Water, cpm for,

RHR Service Water).

(2E-5) , = Cs-137 Maximum Permissible Concentration

(uCi/ml).

Cal. Factor = Monitor response factor per unit Cs-137

concentration determined during most recent

calibration (uCi/ml per cps for Service Water,

uCi/ml per cpm for RHR Service Water).

The ALERT RAD setpoints for the RHR Service Water monitors are

maintained at 80% of the applicable HI RAD setpoint (cpm).

2.2 AIRBORNE EFFLUENT MONITORS

SPECIFICATION 3.3.7.11 - THE RADIOACTIVE GASEOUS EFFLUENT MONITORINGNS R M N N CH N ELS SHOWN IN TABLE 3.3.7. 11-1 SHALL BE OPERABLE

WITH THEIR ALARM/TRIP SETPOINTS SET TO ENSURE THAT THE LIMITS OFSPECIFICATION 3.11.2.1 ARE NOT EXCEEDED. THE ALARM/TRIP SETPOINTSOF THESE CHANNELS SHALL BE DETERMINED IN ACCORDANCE WITH THEMETHODOLOGY AND PARAMETERS IN THE ODCM.

Noble gas activity monitors, iodine samplers, and practiculate

samplers are present on the reactor building ventilation system

(Units 1 and 2), the turbine building ventilation system (Units 1.

and 2), and the standby gas treatment system exhaust vents.

Effluent system flow rate and sampler flow rate are measured on allof the systems allowing the vent monitor microprocessor to calculate

release rates based on measured flow rates. Precautions,

limitations, and setpoints applicable to the operation of the SSES

airborne effluent monitors are provided in the applicable plant

procedures. Setpoints are conservatively established for each

effluent monitor so that the instantaneous dose rates corresponding

to 10 CFR 20 annual dose limits in unrestricted areas will not be

exceeded.

The general methodology for establishing plant ventilation airborne

effluent monitor setpoints is based upon vent release rates derived

from site-specific meteorological dispersion conditions, vent flow

OEc ~ ~ i9s9

rates, and measured or expected radionuclide mixtures in the gaseous

effluents. The vent release rate can then be converted to vent

concentrations for input as setpoints for the applicable detectors.

Since the vent monitors are programmed to calculate concentrations

of iodine-131 and particulate being released based on the rate of

accumulation of activity on the filters, setpoints can be

established for the iodine and particulate channels.

The following method is used for calculating vent monitor high radiation

alarm setpoints:

1. An isotopic mixture is selected for the detector in question, ifapplicable. Noble gas and particulate detector setpoints are based

on actual isotopic mixtures obtained from vent sample analysis or

the FSAR/FES expected release mixtures if actual samples do not

contain sufficient detectable activity to accurately estimate the

mixtures. The assumed isotopic mixtures are periodically reviewed

to'erify that they remain representative of plant effluents.

2. The selected noble gas or particulate mixture is used in the GASPAR

program run to calculate the associated doses. The total source

term (total curies used for the calculation) does not matter as long

as the proper nuclides are present in the relative proportions

indicated in sample analysis data or FSAR/FES tables.

For the iodine-131 setpoint, any release total for I-131 can be

entered. The highest calculated annual average relative

10

concentrations (X/qs) at the site boundary are used for these GASPAR

calculations.

3. The following ratio concept is used to calculate a release rate

limit for the assumed mixture (or I-131):

Calculated Dose mremTota GASPAR Source Term Ci

Dose Rate Limit mrem/ rLimiting Release Rate Ci/yr

The limiting release rate of the assumed mixture (or I-131) can

therefore be calculated:

Limiting Release (Ci/yr)

Total GASPAR Source Term, Ci Dose Rate Limit, mrem/ rCa cu ated Dose, mrem

(Eq. 5)

For the noble gas setpoint', the calculated whole body and skin dose

rates via the plume pathway are subject to the 10 CFR 20-derived

limits of 500 and 3000 mrem/yr, respectively. The whole-body dose

rate limit is usually most restrictive. For particulates and foriodine-131, the maximum calculated organ dose rate via the

inhalation pathway is subject to the limit of 1500 mrem/yr.

4. The limiting release rates are converted to limiting vent

concentrations using high limit vent flow rates.

11

Limiting Vent Concentration, uCi/cc =

Limitin Release Rate, Ci/ r) 1E6uCi/Ci

(5.26E5 min/yr) (Vent Flow Rate, cc/min)

(Eq. 6)

Sample calculations of waterborne and airborne effluent monitor

setpoints are presented in Section A. 1.2 of Appendix A.

Vent flow rates and sample flow rates are monitored and recorded for

each of the five SSES release points. The measured flow rates are

used to calculate vent concentrations and release rates. Flow

channel setpoints are set at approximately 10% and 90% of the

calibrated sensor ranges to provide indication of possibly abnormal

flow rates.

The main condenser offgas pre-treatment monitor provides indication

of offgas activity prior to input to the holdup system. Alarm

setpoints are based on two times and three times the steady state

full power offgas'activity readings.

SPECIFICATION 3.11.2.6 - THE CONCENTRATION OF HYDROGEN OR OXYGEN INGAS TREATMENT SYSTEM SHALL BE LIMITED TO LESS

THAN OR EQUAL TO 4'X BY VOLUME.

Hydrogen recombiners are used at SSES to maintain the relative

concentration of components of potentially explosive gas mixtures

outside the explosive envelope. The main condenser offgas treatment

system explosive gas monitoring system (offgas hydrogen analyzers)

have setpoints to alarm at 1% and 2X hydrogen.

12

0EG t ~ ~ass

~ ~ ~ 3.0 WATERBORNE EFFLUENT CONCENTRATION MEASUREMENTS

SPECIFICATION 3.11.1.1 - THE CONCENTRATION OF RADIOACTIVE MATERIALRELE 0 L 0 LUENTS TO UNRESTRICTED AREAS (SEEFIGURE 5.1.3-1) SHALL BE LIMITED TO THE CONCENTRATIONS SPECIFIED IN 10CFR PART 20, APPENDIX 8, TABLE II, COLUMN 2 FOR RADIONUCLIDES OTHERTHAN DISSOLVED OR ENTRAINED NOBLE GASES. FOR DISSOLVED OR ENTRAINEDNOBLE GASES, THE CONCENTRATION SHALL BE LIMITED TO THE CONCENTRATIONSSPECIFIED IN TABLE 3.11.1.1-1.

Liquid batch releases are controlled individually and each batch

release is authorized based upon sample analysis and the existing

dilution flow in the discharge line. The methods for sampling and

analysis of each batch prior to release are given in the applicable

plant procedures. A release rate limit is calculated for each batch

based upon analysis, dilution flow and all procedural conditions being

met before it is authorized for release.

Table 3. 11. 1-1 mentioned in Specification 3. 11. 1. 1 contains the

following "Maximum Permissible Concentrations of Dissolved or

Entrained Noble Gases Released From the Site to Unrestricted Areas in

Liquid Waste":

Nuclide

Kr-85mKr-85Kr -87Kr-88Ar-41

Xe-133mXe-133Xe-135mXe-135

MPC uCi ml)

2E-45E-44E-59E-57E-5

5E-46E-42E-42E-4

13

P

~ ~

These values were computed using Equation 20 of ICRP2 (1959), adjusted

fot infinite cloud submersion in water, with R equal to 0.01 rem/week,

the density of water equal to 1.0 gm/cm , and p pT equal to 1.0.3

w T

The liquid radwaste effluent stream entering the discharge line is

monitored and will automatically be terminated if the pre-selected

monitor setpoint is exceeded as described in Section 2. 1.

Additional monthly and quarterly analyses shall be performed in

accordance with Table 4. 11-1 of the SSES Technical Specifications.

14

'.0 AIRBORNE EFFLUENT DOSE RATES

I

SPECIFICATION 3.11.2.1. THE DOSE RATE DUE TO RADIOACTIVE MATERIALSEL SE S FLUENTS 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 TOTALBODY AND LESS THAN OR EQUAL TO 3000 MREM/YR TO THE SKIN, AND

b. FOR IODINE-131, FOR TRITIUM, AND FOR ALL RADIONUCLIDES INPARTICULATE FORM WITH HALF LIVES GREATER THAN 8 DAYS: LESS THAN OREQUAL TO 1500 MREM/YR TO ANY ORGAN (INHALATION PATHWAY ONLY).

4.1 NOBLE GASES

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 forsampling and analysis of continuous ventilation releases are given

in the applicable plant procedures. The dose rate in unrestricted8

areas due to radioactive materials released in airborne effluents

may be determined by the following equation for whole body dose:

D„b =g()(()(X/())„ (Q';„) (Eq. 7)

and by the following equation for skin dose:

0 =$(L( + 1.1 N.) (X/())„(()'.„)I

(Eq. B)

DEC T 1 $89

,15

where:

iv

(x/o)

'wb

L.

D

the whole-body dose factor due to gamma emissions foreach iden)ified noble gas radionuclide (i) (mrem/yrper uCi/m ) from Table 2.

the release rate of radionuclide (i) from vent (v)(uCi/sec).

the highest calculated annual average relativeconcentration for any area at or beyond the siteboundary in an u~restricted area from vent releasepoint (v) (sec/m ) such as from Table 3.

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

the skin dose factor due to the beta emissions foreach iden)ified noble gas radionuclide (i) (mrem/yrper uCi/m ) from Table 2.

the air dose factor due to gamma emissions for eachidentjfied noble gas radionuclide (i) (mrad/yr peruCi/m ) from Table 2 (conversion constant of 1. 1converts air dose-mrad to skin dose-mrem).

the annual skin dose (mrem/yr).

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 RAD IONUCLIDES OTHER THAN NOBLE 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 of the

SSES Technical Specifications. The dose r'ate in unrestricted areas

due to inhalation of radioactive materials released in airborne

0~~5 1 i989

16

effluents may be determined by the following equation for anyorgan:

(P ) (W ) (Q v)

where:

P,. = the dose rate parameter for radionuclides other thannoble3gases for the inhalation pathway (mrem/yr peruCi/m ) from Table 4'.

Wv

Q';„

Dc

the highest annual average dispersion parameter forestimating the dose to the3critical receptor; relativeconcentration (X/Q) (sec/m ) for the inhalationpathway, such as from Table 3.

the release rate of radionuclide (i) from vent(v)(uCi/sec).

the annual organ dose (mrem/yr).

Sample calculations for determining doses to cr itical organs from

. radionuclides other than noble gases released from the SSES are given

in Section A.2.2 of Appendix A.

OEC5 1 t989

17

TABLE 2

DOSE FACTORS FOR NOBLE GASES

Radionuclide

'r-83m

Kr-85mKr-85Kr-87Kr-88Kr-89Kr-90Xe-131m

~ Xe-133mXe-133Xe-135mXe-135Xe-137Xe-138Ar-41

Whole BodyDose Factor

K.mrem/ r er uCi/m~)

7.56E-021.17E+031.61E+Ol5.92E+031.47E+041.66E+041.56E+049.15E+012. 51E+022.94E+023. 12E+031.81E+031.42E+038.83E+038.84E+03-

Skin Dose FactorL.

(mrem/ r'r uCi/m~)

1.46E+031.34E+039.73E+032.37E+031.01E+047.29E+034.76E+029.94E+023.06E+027.11E+021.86E+031.22E+044.13E+032.69E+03

Gamma AirDose Factor

M.mrad/ r eb uCi/m~

1.93E+011.23E+031. 72E+016. 17E+031.52E+041.73E+041.63E+041.56E+023.27E+023.53E+023.36E+031.92E+031.51E+039.21E+039.30E+03

Beta AirDose Factor

N.mrad/ r hr

uCi/m'.88E+02

1.97E+031.95E+031.03E+042.93E+031.06E+047.83E+031.11E+031.48E+031.05E+037.39E+022.46E+031.27E+044.75E+033.28E+03

aThe listed dose factors are for radionuclides that may be detected in airborne effluents and derivedfrom Table 8-1 in Reg. Guide 1.109.

7.56E-02 = 7.56 x 10

TABLE 3

SAMPLE ANNUAL AVERAGE RELATIVE CONCENTRATIONS AND DEPOSITION RATES

DownwindSector

NNE

NE

ENEE

ESESESSES

SSW

SW

WSW

W

WNM

NW

NNW

N

SiteBoundar

Miles

.821.1.86.80.50.34.34.34.39.77

1.21.0

.64

.64

.61

.61

Relative Concentrations(x/q) ,sec/m )

8.5E-62.6E-64. 1E-63.6E-65.7E-66.7E-65.5E-61. OE-58,9E-61. 7E-51.8E»S2.6E-51.0E-57.0E-67.5E-67.9E-6

Relative DepositionRates

2D/Q m

2.2E-87.3E-91.4E-S1.7E-S2.9E-S3.7E-S3.5E-83.4E-S2.5E-83.4E-82.3E-82.9E-81. 2E-81. OE-81.7E-S2.1E-S

From 1980 Meteorology Summary for SSESData Period: 01/Ol/80 - 12/31/80

Site Boundary distances are approximate, and current as of 11/88.

19

TABLE 4

DOSE RATE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLE GASES

Radionuclide

H-3C-14Cr-51Mn-54Fe-59Co-58Co-60Zn-65Sr-89Sr-902r-95Sb-124I-131I-133Cs-134Cs-136Cs-137Ba-140Ce-141

Inhal ation Pathwayb

p.mrem/ r hr

uCi/m'.47E2

ALL2.65E4 BO

1.28E4 LU1.00E6 LU

'1.02E6 LU7.77E5 LU4.51E6 LU6.47E5 LU2.03E6 LU4.09E7 BO

1.75E6 LUNo Data-1.48E7 TH

3.56E6 TH7.03E5 LI1.35E5 LI6.12E5 LI1.60E6 LU5.17E5 LU

aThe listed dose parameters are for radionuclides that may be detected in

airborne effluents. Additional dose parameters for isotopes not included maybe calculated using the methodology described in NUREG-0133.

bBased on infant age group, RG 1.109 Tables E-10, 14 in accordance with

methodology of NUREG-0133, pp. 22, 27.c I = infant, C = child, T = teenager, A = adult, ALL = all organs, BO = bone,GI = gastrointestinal tract - lower large intestine, LI = liver, LU = lungs,TH = thyroid.

OEC f 1 1989

20

Co ~ .

5.0 INDIVIDUAL DOSE DUE TO WATERBORNE EFFLUENT

SPECIFICATION 3.11.1.2 - THE DOSE OR DOSE COMMITMENT TO A MEMBER OF THEU L D E MATERIALS IN LIQUID EFFLUENTS RELEASED FROM EACH

REACTOR UNIT TO UNRESTRICTED AREAS (SEE FIGURE 5.1.3-1) SHALL BE LIMITED:

a. DURING ANY CALENDAR QUARTER TO LESS THAN OR EQUAL TO 1.5 MREM TO THETOTAL BODY AND TO LESS THAN OR EQUAL TO 5 MREM TO ANY ORGAN, AND

b. DURING ANY CALENDAR YEAR TO LESS THAN OR EQUAL TO 3 NREM TO THE TOTALBODY AND TO LESS THAN OR EQUAL TO 10 MREM TO ANY ORGAN.

The calculations of dose received by the hypothetical maximally exposed

individual from the ingestion of fish and drinking water are based on the

nearest public drinking water intake location (Danville Water Authority).Dose contributions from recreation, boating, and swimming have been shown

to be negligible in the NRC 10 CFR 50 Appendix I dose analysis (June 1976)

and do not need to be routinely evaluated.

The following expression is used to calculate the ingestion pathway dose

contributions for the total release period for each batch release from allradionuclides identified in the liquid effluents released to unrestricted

areas:

D= A. (AtCi F)

where:

(Eq. IO)

D~= the cumulative dose commitment to the total body or any organ (w)from the liquid effluents for the time period, 4t, of each batchrelease (mrem).

4t = the length of the time period for a batch release over which C,.and F are averaged for all liquid releases (hr);

C,. = the average concentration of radionuclide (i) in undilutedliquid effluent during time period, ~t, for any liquid effluentbatch release (uCi/ml).

21

F = the discharge line dilution factor for C. during any liquideffluent batch release. Defined as the hatio of the maximumundiluted liquid radwaste effluent line flow during releaseto the average flow from the plant discharge line tounrestricted receiving waters.

A . = the composite dose parameter for the total body or any organz) for each identified principal gamma and beta emitter (i)mrem/hr per uCi/ml) (see Equation 11, Table 5).

A. = k ((U + Uf BF.)/D ) DF. (Eq. 11)

where:

k = conversion factor of 1. 1 x 10 = 10 Ci/uCi 10 ml/k5 6

r yr

U = a receptor person's water consumption by age group fromRegulatory Guide 1. 109, Table E-5.

Dw= the dilution factor from the near field area of the release

point to potable water intake. (The nearest potable waterintake is located at Danville; dilution factors based on riverlevel are given in Table D-l of Appendix D. These dilutionfactors are based on fluorescent dye tracer studies conductedat various river levels during 1985.)

Uf,= a receptor person's fish consumption by age group fromRegulatory Guide 1. 109, Table E-5.

BF,. = the bioaccumulation factor for nuclide (i) in fish (pCi/kg perpCi/1) from Regulatory Guide 1.109, Table A-1.

DF,. = the dose conversion factor for nuclide (i) in a receptorperson for pre-selected organ (w), (mrem/pCi) from RegulatoryGuide 1.109, Tables E-ll, E-12, E-13, and E-14.

The projected quarterly dose contribution from batch releases for which

radionuclide concentrations are determined by periodic composite sample

analysis, as stated in Table 4. 11-1 of the SSES Technical Specification

may be approximated by assuming an average concentration based on the

previous monthly or quarterly composite analysis.

OEC g i >9N

22

However, for reporting purposes, the calculated dose contributions from these

radionuclides shall be based on the actual composite analysis. The cumulative

dose commitment to the total body or, any organ for a quarterly or annual

analysis shall be based on the calculated dose contributions from each batch

release occurring during that time period.

In actual practice, the LADTAP computer code developed by the NRC to implement

the liquid dose methodology of Regulatory Guide 1.109 will be used to perform'he

individual liquid pathway dose calculations for the SSES. The methods

outlined above are consistent with those of the LADTAP code; site specific

dose factors have been computed and are available for implementing the method

described above, if required.

A discussion of the LADTAP code is given in Section A.3.1 of Appendix A.

OEC g 2 889

23

TABLE 5

WATERBORNE EFFLUENT DOSE PARAMETERS FOR ADULTS

Radionuclide

H-3Mn-54Fe-55Co-58Fe-59Co-60Zn-65Sr-89Sr-90Mo-99I-131

~ Cs-134Cs-137

'Ce-141Ce-144

Fresh Water FishBioaccumulation Factor

Ci/k er Ci/liter

.9400100

5010050-

200030301015

20002000

1

1

Ingestion Dose Factorfor Critical Organ

(mrem/ Ci)

1.05E-71.40E-5.2.75E-6l.51E-53.40E-54.02E-51.54E-53.08E-47.58E-39.99E-61.95E-31.48E-41.09E-4,2.42E-51.65E-4

Critical~0r an

Total IjodyGI-LLIBoneGI-LLIGI-LLIGI-LLILiverBoneBoneGI-LLIThyroidLiverLiverGI-LLIGI-LLI

Dose Parameter (A. )(mrem/hr er uCi/hl)

2.446E-11.294E46.360E21.748E37.863E34.653E37.115E42.142E45.272E52.333E26.806E46.838E55.036E56.196E14.224E2

Additional factors for isotopes not included in Table 5 may be calculated using the methodologydescribed in NUREG-0133.

b GI-LLI = gastro-intestinal tract, lower lar ge intestine.

6.0 INDIVIDUALDOSE DUE TO AIRBORNE EFFLUENT

6.1 NOBLE GASES

SPECIFICATION 3.11.2.2 - THE AIR DOSE DUE TO NOBLE GASES RELEASED INN , R M EACH REACTOR UNIT, TO AREAS AT AND BEYOND

THE SITE BOUNDARY (SEE FIGURE 5. 1.3-1) SHALL BE LIMITED TO THEFOLLOWING'.

a. DURING ANY CALENDAR QUARTER: LESS THAN OR EQUAL TO 5 MRAD FORGAMMA RADIATION AND LESS THAN OR EQUAL TO 10 MRAD FOR BETARADIATION, AND

b. DURING ANY CALENDAR YEAR: LESS THAN OR EQUAL TO 10 MRAD FORGAMMA RADIATION AND LESS THAN OR EQUAL TO 20 MRAD FOR BETARADIATION.

The air dose in unrestricted areas beyond the site boundary due to

noble gases released in airborne effluents from the site shall be

determined by the following equation for gamma radiation during any

specific time period:

D = 3.17 x 10 g N; (X/Q)„Q,.„t

(Eq. 12)

and by the following equation for beta radiation during any

specified time period:

DD= 3.17 x 10 g N1 (X/Q)„Q1„.

IWhere:

(Eq. 13)

(X/Q)v =

the air dose factor due to gamma emissions for eachidentified noble g~s radionuclide (i)(mrad/yr per uCi/m ) from Table 2.

the air dose factor due to beta emissions for eachidentified noble ga~ radionuclide (i)(mrad/yr per uCi/m ) from Table 2.

the highest calculated annual average relativeconcentration for any area at or beyond the siteboundary in an u~restricted area from vent releasepoint (v) (sec/m ) such as from Table 3.

25 OEC 1 1 1989

D9

3.17 x 10

the total gamma air dose from gaseous effluents forspecified time period (mrad).

the total beta air dose for gaseous effluents for aspecified time period (mrad).

the integrated release of each identified noble gasradionuclide (i) in gaseous effluents from all vents(v) for a specified time period (uCi).

the inverse of seconds in a year (yr/sec).

A discussion of the method used to calculate the individual dose from

gaseous effluents is given in Section A.3.2 of Appendix A. Also,

sample calculations for determining gamma and beta air doses from

noble gas radionuclides released from the SSES are given.

6. 2 RADIONUCLIDES OTHER THAN NOBLE GASES

SPECIFICATION 3.11.2.3 - THE DOSE TO A MEMBER OF THE PUBLIC FROMIODIN -131, RITIUM, AND ALL'RADIONUCLIDES IN PARTICULATE FORM WITHHALF-LIVES GREATER THAN 8 DAYS IN GASEOUS EFFLUENTS RELEASED, FROMEACH REACTOR UNIT, TO AREAS AT AND BEYOND THE SITE BOUNDARY (SEEFIGURE. 5.1.3-1) SHALL BE LIMITED TO THE FOLLOWING:

a. DURING ANY CALENDAR QUARTER: LESS THAN OR EQUAL TO 7.5 MREMS TOANY ORGAN, AND

b. DURING ANY CALENDAR YEAR: LESS THAN OR EQUAL TO 15 MREMS TO ANYORGAN.

The critical organ dose to an individual from I-131, tritium, and

radioactive materials in particulate form with half-lives greater

than 8 days released in airborne effluents from the site to

unrestricted areas can be determined by the following equation

during any specified time period:

0 = 3.17 x 10 g(R<) (W ) (0<„) (Eq. 14)

26OEC 5 1 1989

where:

'c =

R. =1

Wv

the total dose to a critical organ from radio-nuclides other than noble gases for a specified timeperiod (mrem).

the dose parameter for each identified radionocli)e(i) for the inhalation pathway (mrem/yr p~r uCi/m )and for food and ground plane pathways (m 'rem/yrper uCi/sec) from Table 6.

the highest annual average dispersion parameter forestimating the dose to the critical3individual;relative concentration (X/g) (sec/m ) for theinh~lation pathway and relative deposition rate (D/g)(m ) for the food and ground pathways such as fromTable 3.

~iv =

3.17 x 10

the integrated release of each identified radio-nuclide other than noble gases (i) in gaseouseffluents from all vents (v) for a specified timeperiod (uCi).

the inverse of seconds in a year (yr/sec).

In actual practice, the GASPAR computer code developed by the NRC to

implement the airborne dose methodology of Regulatory Guide 1.109

will be used to perform the individual airborne pathway dose

calculations for the SSES. The methods outlined above are

consistent with those of the GASPAR code; site specific dose factors

have been computed and are available for implementing the method

described above, if required.

A discussion of the GASPAR code is given in Section A.3.2 of

Appendix A.

OEI: 11 198g

*27

TABLE 6

HAXIHUH PATHMAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES

Radionuclide

InhalationPathway

R.(mrek/yrer uCi/m~

Neat PathwayR.

(m2 . modem/yrer uCi/sec)

Ground PlanePathway

R.(m .. modem/yrp" 'I ")

Cow MilkPathway

R.(m2 . modem/yr

er uCi/sec)

LeafyVegetables

PathwayR.

(m2 . modem/yrer uCi/sec)

H-3C-14

Cr-51Hn-54Fe-59Co-58Co-60Zn-65Sr-89

co Sr-90Zr-95I-131I-133Cs-134Cs-136Cs-137Ba-140Ce-141

1. 27E33.59E42.10E41. 98E41.53E61.34E68.72E61.24E62.42E61.08E82.69E61.62E73.85E61.13E61.94E59.07E52.03E66.14E5

T, ALLC, BO

T, LUT$ LUT, LU

T, LU

T, LU

T, LU

T, LU

T, BO

T, LUC, TH

C, THT, LIT, LIC, LIT, LUT, LU

1.47E61.20E74.53E54.11E61. 98E71.03E75.48E76.69E81.32E88.51E91.00E52.63E94.83E12.32E93.60E91.92E91. 98E68.75E5

A, ALLA, BO

A, GIA, GIA, GIA, GIA, GIA, LIA, BO

A, BO

A, GIA, TH

A, THA, LIA, LIA, LIA, GIA, GI

00

5.50E61.62E93.20E84.45E82. 53E108.57E82. 51E4

2.91E82.09E72.98E67.97E91.70E81.20E102.35E71.54E7

1. 29E71. 20E91.51E61.82E71.24E83.94E71.83E88.66E94.13E96.23E104.28E52.65Ell2.42E93.35E101.47E93.09E106.12E74.93E6

I, ALLI, BO

C, GII, LII, LIT, GIT, GII, LII, BO

I, BO

T, GII, TH

I, THI, LII, LII, LII, BO

T, GI

1.49E78.89E83.55E79..58E89.91E86.25E83.24E92. 16E93. 60E101.24E121.28E94.76E108.08E82.63E102.25E82.39E102.77E85.40E8

C, ALLC, BO

A, GIA, GIT, GIA, GIT, GIC. LIC. BO

C, BO

T, GIC, TH

C, TH

C, LIC, LIC, LIC, BO

T. GI

Values presented for each pathway are the maximum R.s for each radionuclide. Additional dose factors forisotopes not included in Table 6 may be calcualted hsing the methodology described in NUREG-0133.

b I = infant, C = child, T = teenager, A = adult. ALL = all organs, BO = bone, GI = gastrointestinal tract—lower large intestine, LI = liver, LU = lungs, TH = thyroid.

Pathway is skin. Not age-group dependent.

7.0 TOTAL DOSE

SPECIFICATION 3. 11.4 - THE ANNUAL (CALENDAR YEAR) DOSE OR DOSE COMMITMENTNY MEMBER F THE PUBLIC, DUE TO RELEASES OF RADIOACTIVITYAND

RADIATION, FROM URANIUM FUEL CYCLE SOURCES SHALL BE LIMITED TO LESS THANOR 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 radioactivereleases from the SSES site is determined by summing the calculated doses

to critical organs from the previously discussed effluent sources. The

annual dose to critical organs of a real individual for the liquideffluents 'is determined by using Equations 10 and 11 of Section 5. The

annual dose to critical organs of a real individual for the noble gasesreleased in the gaseous effluents is determined by using Equation 12

modified by replacing M. with K. from Table 2 for the whole-body dose andi 1

by Equation 13 modified by replacing N. by (L. + 1. 1 M.) from Table 2 for1 1 1

the skin dose of Section 6.0:

= 3.17 x 10 Ki X/Q vQiv

Db= 3. 17 x 10 (L,. + 1. 1M,.)(X/Q)vQ.

(Eq. 15)

(Eq. 16)

The annual dose to critical organs of a real individual for theradionuclides other than noble gases released in the gaseous effluents.isdetermined by using Equation 14 of Section 6.0. for all dose

calculations from airborne effluents, the deposition rate used in theanalysis should be at the receptor location of the individual beingevaluated, not the highest calculated annual average relativeconcentration or relative deposition rate for any area at or beyond thesite. boundary as given in Table 3. The direct radiation from the siteshould be determined from the environmental monitoring program's directradiation (TLD) monitors. Since all other uranium fuel cycle sources aregreater 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'RC to implement the liquid and gaseous dose methodology of Regulatory

29 ~F-0 < C ~98S

Guide 1.109 will be used to perform the total dose calculations'or theSSES. The methods outlined above are consistent with those of the LADTAP

and GASPAR codes; site specific dose factors have been computed and are

available for implementing the method described above, if required.

A discussion of the methods used to calculate the total dose to criticalorgans of a real individual is given in Section A.4 of Appendix A.

OEC t i 1S8S

30

~ ~

I

8.0 OPERABILITY OF WASTE TREATMENT SYSTEMS

8.1 LI UID WASTE TREATMENT

SPECIFICATION 3.11.1.3 - THE LIQUID RADWASTE TREATMENT SYSTEM, AS, SHALL BE OPERABLE. THE APPROPRIATE PORTIONS

OF THE SYSTEM SHALL BE USED TO REDUCE THE RADIOACTIVE MATERIALS INLIQUID WASTE PRIOR TO THEIR DISCHARGE WHEN THE PROJECTED DOSES DUETO 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 0.2MREM TO ANY ORGAN IN A 31-DAY PERIOD.

The SSES liquid waste treatment system utilizes two 300 fthorizontal centrifugal discharge. type filters with 200 gpm normal

flow. Liquid from the filters enter a mixed bed demineralizer with- a volume of 140 ft and normal flow rate of 200 gpm. High

3

conductivity waste is treated in two stainless steel "pot boiler"evaporators which are heated with auxiliary steam. There are two

chemical waste neutralization tanks with 28,000 gal capacity. Low

conductivity liquid wastes are collected in three pairs of LRW surgetanks. A flow diagram of the liquid radwaste treatment system isshown in Figure 1.

Appropriate treatment for liquid effluents from SSES is defined inODCM Policy Statement 10.6. In cases when a batch of liquid waste

must be released with treatment less than that specified in Secti,on10.6, a dose assessment using LADTAP or the methodology of Section5.0 shall be performed prior to release to ensure that the limits ofSpecification 3. 11. 1.3 are not exceeded.

8.2 GASEOUS WASTE TREATMENT

SPECIFICATION 3. 11.2.4 - THE GASEOUS RADWASTE TREATMENT SYSTEM SHALLB I PER TI N.

APPLICABILITY: WHENEVER THE MAIN CONDENSER AIR EJECTOR (EVACUATION)OPE A IM.

SPECIFICATION 3.11.2.5 - THE APPROPRIATE PORTIONS OF THE VENTILATIONEM SHALL BE OPERABLE AND SHALL BE USED TO

REDUCE RADIOACTIVE MATERIALS IN GASEOUS WASTE PRIOR TO THEIRDISCHARGE WHEN THE PROJECTED DOSES DUE TO GASEOUS EFFLUENT. RELEASESFROM EACH REACTOR UNIT TO AREAS AT AND BEYOND THE SITE BOUNDARY (SEE

31OEC g 1 )989

FIGURE 5.1.3-1) WHEN AVERAGED OVER 31 DAYS WOULD EXCEED 0.3 MREM TOANY ORGAN IN A 31-DAY PERIOD.

The SSES offgas treatment system operates with four steam jet airejectors maintaining condenser vacuum. Noncondensible gases arepassed through one of three combiners (one for each reactor unitplus a common recombiner), reducing the amount of gases to be

filtered and released. Gases pass through a two to nine minuteholdup pipe before entering the offgas treatment system, whichconsists of two 100 percent capacity systems per reactor unit. Each

system consists of inlet HEPA filters, precoolers, chillers,reheaters, guard beds, and five charcoal absorbers and an outletHEPA filter. Monitored, filtered air then exits to the turbinebuilding vent. A flow diagram of the offgas and recombiner systemis shown in Figure 3.

Filtered exhaust systems serve selected areas of Zone I, II, and IIIof the SSES reactor building. The Zone I and Zone II equipmentcompartment and Zone III filtered exhaust systems each consist oftwo 100K capacity redundant fans and two 55K capacity filter trains.Each filter train has, in the direction of air flow, roughingfilters, upstream HEPA filters, a charcoal filter bed, and

downstream HEPA filters. Exhaust fan discharge is then routed tothe atmosphere via the reactor building vents, where effluents arecontinuously sampled and monitored.

The turbine building filtered exhaust system draws air from thoseareas of the building that are most likely to become contaminated.Two 100K capacity fans serve each system, which contains two 50K

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 potentiallycontaminated air from selected areas of the radwaste building. The

32OEC < t ~s89

system contains two 100% capacity fans and two 50% capacity filterhousings, 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

'equired, evaluations are performed to determine if components can

be removed from service when the need arises for maintenance,testing, etc. In order to properly project the dose consequences ofremoval of a exhaust treatment component from service, there are two

options:

1. Take samples in the system in question, upstream of thefilter trains, in order to characterize what would be

released if the component was removed from service as

proposed.

2. Take samples from the affected vent after the component has

been removed from service, and evaluate whether it can

remain out of service based on the analysis results.

Because the current plant design does not provide for samplingexhaust systems upstream of treatment, the following procedure isused to determine appropriate treatment of ventilation exhaust airwhen components must be removed from service:

A. Within two hours of removal of the component from service, new

particulate and iodine filters are placed in the system whichcontinuously samples and monitors the vent which ultimatelyreceives the flow from the component in question.

O~~ 3 1 1989

B. After a period of sample collection long enough to provideacceptable analytical sensitivities, the filters are retrievedand analyzed via gamma spectroscopy. Release rates 'are

determined for particulate and iodine nuclides.

33

'

I \ ~

C. The following equation is used to estimate the projected dosesthat would result if those releases rates were to persist for 31

days:

PROJD = (PRR x 0.189) + (IRR x 0.135)

where: PROJD = the estimated maximum projected dose at orbeyond the site boundary over a 31-day periodattributable to release rates PRR and IRR

(mi llirem).

PRR = the total release rate of radionuclides inparticulate form (uCi/minute).

IRR = the total radioiodine .release rate (uCi/minute).

0. 189 = a factor to convert gross particulate releaserate to a dose over 31 days. Based on theexpected nuclide composition of SSES effluentsfrom NUREG-0564, meteorological data collectedover 1984-1988, and land-use census results from1988. Calculated using GASPAR.

0. 135 = a factor to convert gross radioiodine releaserate to a dose over 31 days. Based on the same

assumptions as above.

D. Based on the projected dose value (PROJD), appropriate treatmentis defined as follows:

l. IF PROJD is 0.03 millirem or less, the component inquestion can remain out of service. If the component

remains out of service for an extended time period, an

evaluation will be performed at least once each 31 days,based on recent vent sample analyses performed as part of theroutine surveillance program. The value of 0.03 millirem is

34OEC

5 1 f989

10$ of the 0.3 millirem action level for use of appropriateportions of the treatment systems. When projected doses arebelow this level, the exhaust stream in question is not a

significant contributor to offsite doses attributable to thesite.

2. If PROJD is 0.3 millirem or greater, the component inquestion must be returned to service as soon as it can be

returned to an operable state.

3. If PROJD is above 0.03 but less than 0.3 millirem, a more

detailed assessment is required. Particulate, iodine,and tritium release rates for the entire unit (reactorbuilding vent, turbine building vent, and 1/2 of the SGTS

vent) are determined based on the most recent vent sample

analyses available. These release rates are then convertedto release totals (curies) over 31 days for all positivelydetected radionuclides, and input to the GASPAR program tocalculate the projected dose totals over 31 days. If themaximum dose exceeds 0.3 millirem, the component must be

returned to service as soon as it 'can be returned to an

operable state. If the maximum dose is 0.3 millirem or less,the component can remain out of service in the same manner as

in case 1 above.

8. 3 SOLID WASTE TREATMENT

SPECIFICATION 3.11.3 - THE'SOLID RADWASTE SYSTEM SHALL BE USED INOCESS CONTROL PROGRAM, FOR THE PROCESSING AND

PACKAGING OF RADIOACTIVE WASTES TO ENSURE MEETING THE REQUIREMENTSOF 10 CFR PART 20010 CFR PART 71, AND FEDERAL REGULATIONS COVERINGTHE DISPOSAL OF THE WASTE.

The SSES sol.id radwaste system was designed to solidify all wetwastes for ultimate offsite disposal. There are two Backwash

Receiving Tanks, one per unit, which collect two filter-demineralizer backwashes per tank (2450 gal capacity). Air spargersfor resin mixing are driven by instrument air. Regeneration Waste

35 ~~~5 i 1989

Surge Tanks (4) and Phase Separators (3) have internal mixingeductors for sludge mixing driven by recirculation flow. The SpentResin Tank has a reversible progressing cavity pump and internalmixing eductors. Two solidification trains have waste mixing tankprogressing cavity feed and mixing pumps, and screw conveyors forfeeding of dry Portland cement. Mixing is facilitated by theaddition of sodium silicate. Common solidification equipmentincludes waste container fillport, transfer cart, capper washdown

station, and swipe tool; cement silo with rotary feed valve,aeration blower, baghouse, and exhaust fan; sodium silicate tank and

pump. Vendor, solidification services may be used in accordance withthe SSES Process Control Program to supplement the plantsolidification system or to take the place of the plant system when

the plant system is out of service.

A flow diagram of the SSES solid radwaste treatment system is shown

in Figure 3. Dry contaminated waste processing is depicted inFigure 4.

Dry contaminated solids may be compacted with a drum compactor into55-gallon drums or with a box compactor into steel boxes. The trashcompactors utilize hydraulic press pistons with exhaust fans and

HEPA filters. In addition, dry contaminated solids may be processedusing vendor supercompaction and incineration services. An

automated dry active waste (DAM) monitoring system is used tosegregate radioactive from non-radioactive solid waste.

36

0~~ 1 'i f989

fhMEYAPOMTONNEATINOmao COmaATENETH'am

SR M PNAW WPAMTORSIOECANTNTO

FMO~ SYSTEWFMS MCS CYSTS

REACTOR WELL SEAL I.EAKORNNREACTOR SUILDINC DRAINSOWWLLDRAWSTNRNNE SNILOINODRAINSMDWASTE SUILOINC DRAINS

LIOUIORADWASTE

LIOUNRADWASTECOLLECTIONa SNRCE

TANKS~T~ATINNfOT~ATORO O

01 LIOUID Ql LIOUIONADWASTE NADWA5TE

flLTENS OEWNEMLIT5 ROf 4OJIJ OF&1

LIOUIORADWASTE~fTANKS

OT455A THOU F

Qi

Rm

FROW CONDENSATE OEWN.RfNN NfCENE RATTOO TMKS

LIRVIDNADWASTECOLLECtlONTANKfUWS Ot4S IAPJ

01

CHEWCALWASTENfVTMLQERTANKSIT.ISCION ST.I SOAP

CHE WCALWASTENfUth TANKPUWSlt.1SAP TP.IRAQ

TO WASTE WXINCTANKS 0't4f7 A, O

TO StENTNEIN TANK

OT411LIOUIDNAOWASTE

SAWLE 'TANKtLW5OP4SEAPQ

CONDE N5ATESTONACE tANKSOT.ETTA'"-I

RC7

~ SRIWSAWLESTATIONSfROW AUX SOILS R ROON~FRIW~ SYSTM CHEWCALOECONTAWMTIDNFROW SHEL POOL CLfANWSY5CHEWCALOECONTAWMTIONLAS AND DfCON DRAINS

CHEWCALWASTE

OT4IC CHfWCALWASTETANK

TANK PUWSOP41SAR

QS

NADWASTEfYAtONATORSOf451ILS

OT

DISllLLATE5AWLE TANK

OT411

QS

t'tI

hf

TO COOLINCTOWER SLOW

DOWN Pltf

011

LAUNDRYDMINSRECULATED SHOP DMINSfER5ORNEL DECONTAW-

IMTIONIDETERCENTSICASKCL~DRAINS

LAUNDRYDRAINTANKS

OT4IIAJ

QS LAUNOhYDRAIN ISFILTERS

OF4ITAJ

LAUNOhYDRAIN~LE 'TANKSOT411

DISTILLATE~f0»

EYAPORATONCONCENTMTE5TORASE TM'K

OT411

CONCE«thATESTORACETANKDISCHANCfPUW OP4ZS

TO WASTEMIXINCTANKS

0145t A,O

LAUNDRYDMINTMKPUWS

OP4I SAPLAUNDRYDRAINSADDLE TANKPVIW OP4ISAP

I ~

t

OFFGAS RECOMBINER SYSTEM I

AMBIENTTEMPERATURE CHARCOALOFFGAS SYSTEM UNIT 1

MAIN8 AUXSTEAM

FROM UNIT I

MAINSTEANCON.DEN.SER

UNIT

'FFGAS BYPASS

EL HEAT TRACING

1st STAGE

STEAMJETAIREJEC.

TORCON.DEN.

SER

tl)I

II

DILUTIONSTEAMII

I I

I

2nd STAG a. 2I

III

I

STEAM JET AIR EJECTOR UNIT 1

1E-136PREHEATER

I3

IS 125 IRECOMB Zs+lVESSEL

IE-137RECOMBCOND

TURBINE BLDGEXHAUST

UNIT 1

1F.302 OU LET HEPA F ILTE HARCOALADSORBER BE S

DELAYPIPE

IE-133 MOTIVESTEAM JET

6 7

IE.134MOTIVESTEAM

JETCOND

2 IH2 INLET PRE- CHILLER ~~ GUARD

HEPA COOLER us 8 DFILTER

1T-3 IO IT-309 T.308 IT307 1T- Q0

IF 'IA 9 1E. IA 1E. A 9 1T.303A

COMMON OFFGAS RECOMBINER SYSTEM

II

MAINSTE~CON-

OENSER

UNIT 2

STEAM JET AIR EJECTOR CONDENSER

UNIT2

II

IIII DELAYPIPE

AMBIENTTEMPERATURE CHARCOALOF FGAS SYSTEM

UNIT2

MAIN 5( AUXSTEAQFROlh UNIT2

C7

n

OFFGAS BYPASS

OFFGAS RECOMBINER SYSTEM 2

TURBINE BLDG EXHAUSTUNIT2

FIGURE 2

OFFGAS AND RECOISINER SYSTEM FLOW DIAGRAM

CCtEXHSATEIXHIH I%SIN

STIRIVX VESSEL17-158

RPDOSTE CZMXHSAIEOOLIKRALIZER IXKIH RESIN

CF-301 SINUVX VESSEL27 ISB

RGXH, HASTESOKX TAIKS1T-106 hiB

RGXN, WLSTESJLLX ThHCS21- 10948

FLAIL POLX.F/0 BACILH

RECEI'VINO TANL01-203

IbCU BACKHRECE IVIHQ ThtK

17-225

RLEXI BACONRGXIVIHQ ThtK

2'1-225

RfLXtCRAIICN

IP-106A a 8LLASTE

POPS2P-106hiB

SPENT RESINThtK

01-326

SPENT RESIN TRANS-POPOP-320

IO RHSS POP

TO RHSS POP WLSTE IIPUTS

LIQUIDBASEST EFILTERS

%-302'HASTE SLLXXX

PHASE SEP.OT-331

PNLTAIX.ESOL IOIF ICATION

SISTEH

HASTE SLLNQEOISCHARQE HIXINQ POP

OP-332

HASTECONTAIIXR

RHCUPHASE SEP,

OT-318A

RHCUPHASE SEPi

OT-3188

CDmn

cB

HASTE HIXIHQTAMCS

OT 307hiS

lgLSTE CNIRIHDI

IO RHSSPOE'O

RHSS POP

EVAPORATORCONCENTRATE

STORAQE ThM(0 ISCHARQE FLAP

OP-328

EVAPCILATORCONCENTRATE

STORAOE TAN(OP-328

FROHEVIIPORATOR

RHCU SLLXXX Ol SCHAROEHIXINO POP

OP~+

+ ~

a

FIGURE 4 .

SSES DRY CONTNINTED NSTE PR4CESSING

Paper, Plastic, Rags,

Sheet,ing, Clothing

Second-Sort

Dry Solid PasteContaninated

Dry Solid IIaste

Dr}I Active ilaste (DAD}

Nonitoring SyshaPPRL

IPES

Radioactive't

Vendor

Services

Sq)ercompaction

InclABration

Shredder

Box

Conpactor

Drum

Compactor

Free Released 55-gal. Druns or Boxes

OEC g | 589

40

~ ~

J$

) i

9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

9. 1 DEFINITIONS

Once in each calendar week at intervals ofapproximately 7 days, plus or minus 2 days.

Semi-Monthly: Twice each calendar month at intervals ofapproximately 15 days, plus or minus 4 days.

Monthly: Once each calendar month at intervals ofapproximately 30 days, plus or minus 6 days.

quarterly: Once in each three month period of a calendar year atintervals of approximately 13 weeks, plus or minus 3weeks.

9. 2 MONITORING PROGRAM

SPECIFICATION 3.12.1 - THE RADIOLOGICAL ENVIRONMENTAL MONITORINGPROGRAM SHALL BE CONDUCTED AS SPECIFIED IN TABLE 3. 12.1-1.

Environmental samples shall be collected and analyzed (as a minimum)according to Table 7 at locations shown in Figures 5 and 6.Analytical techniques used shall ensure that the detectioncapabilities in Table 8 are achieved.

A dust loading study (RMC-TR-81-01) was conducted to assure that theproper transmission factor was used in calculating gross betaactivity of air particulate samples. This study concluded that thesample collection frequency of once per week was sufficient and thatthe use of 1 for the transmission correction factor for gross betaanalysis of air particulate samples is valid.

The charcoal sampler cartridges used in the airborne radioiodinesampling program (Science Applications, Inc., Model CP-100) aredesigned and tested by the manufacturer to assure a high quality ofradioiodine capture. A certificate from the manufacturer issupplied and retained with each batch of cartridges certifying thepercent retention of radioiodine versus air flow rate through thecartridge.

41'

~ ~

f

t g

The results of the radiological environmental monitoring program areintended to supplement the results of the radiological effluentmonitoring by verifying that the measurable concentrations ofradioactive materials and levels of radiation are not higher thanexpected on the basis of the effluent measurements and modeling ofthe environmental exposure pathways. Thus, the specifiedenvironmental monitoring program provides measurements of radiationand of radioactive materials in those exposure pathways and forthose radionuclides which lead to the highest potential radiationexposures of individuals resulting from station operation. Program

changes may be proposed based on operational experience. Deviationsare permitted from the required sampling schedule if specimens areunobtainable due to hazardous conditions, seasonal unavailability,malfunction of automatic sampling equipment, and other legitimatereasons. If specimens are unobtainable due to sampling equipmentmalfunction, an effort shall be made to complete corrective actionprior to the end of the next sampling period. All deviations fromthe sampling schedule shall be documented in the annual report.Reporting requirements for the radiological environmentalsurveillance program are given in Appendix B.

9.3 CENSUS PROGRAM

SPECIFICATION 3. 12.2 - A LAND-USE CENSUS SHALL BE CONDUCTED ANDN 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 ofvegetation may be performed at the site boundary in each of twodirection sectors with the highest predicted 0/g's in lieu of thegarden census. Specifications for broad leaf vegetation samplingin Table 3. 12.1-1, item 4C shall be followed, including analysis ofcontrol samples.

If a land use census identifies a location(s) with a higher averageannual deposition rate (D/Q) than a current indicator location, thefollowing shall apply:

1. 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. The

indicator location having the lowest D/Q may be dropped from theprogram after October 31st of the year in which the land use censuswas conducted.

2. If the D/Q is not 20 percent greater than the previously highest D/Q,direction, distance, and 0/Q will be .considered in deciding whetherto replace one of the existing sample locations. If applicable,replacement shall be within 30 days.

Any evaluations of possible location replacement should include the pasthistory 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 agriculturalauthorities, 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 whichperform analyses shall participate in the Environmental ProtectionAgency's (EPA's) Environmental Radioactivity Laboratory IntercomparisonsStudies (Crosscheck) Program or an equivalent program which has been

approved by the Commission. This participation shall include some ofthe determinations (sample medium-radionuclide combination) that areoffered by EPA and that are also included in the monitoring program.

43~~~ 1 i 1989

The results of the analyses of these crosscheck samples shall be

included in the annual report.

If the results of analyses performed by the licensee or licensee'scontractor in conjunction with the EPA crosscheck program (or equivalentprogram) are outside the specified control limits, the laboratory shallinvestigate the cause of the problem and take steps to correct it. The

results of this investigation and corrective action shall be included inthe RENP annual report.

44 DEC < S eS9

FIGURE 5

ONSITE ENVIRNNENTAL SAMPLING LOCATIONS - SUSQUEHANNA SES

16

IIIIIIIIIIIIIlIIII

~ ~ ~ ~ ,

~ ~

~ ~~ ~

III 282

~ ~

e

r ~

'~

~ O~ ~

~ ~

e'

' ~

r..3

15 IIIIIII

~~

~O'(f) ~

R

l4

l2

15S4

14S

13S2

12S3

~ ~1S2 11S3

10SL

4S3

SS4

$9

'O 7S6

SS2'

5S7

<6S1 'S2S2 ~ 2S3 3S4

e ~

6S7

IIIIIIII

IIIIII

~ ~

a1,'Ie,

~ ~

5S4~ r

~ ~

~ ~~ ~

r5SS e".

~ ~~ ~

~ ~ ~~ ~

~

~ ~~ ~

~ ~ ~r ~ ~ ~, ~

~ e ~'

6S5

~ yI

, DEC g g 58910

rpa

0

h

I//r

IIIIIII

II

~e~ ~ ~

~e ~ ~

r ~ ~

e

~ ~~ ~ ~, ~I ~ l

e ~

~ r ~ ~

~ ee ~ r

er're ~ r ~ ~

~ ~

~ ~ ~~ ~

~ e ~ ~ ~r ~

~

~ ~~ ~ g ~

~ ~

~ e ~~ e ~I ~ ~ ~

~ ~ ~ ~, ~ ~

~ ~ ~,e ~ e~ ~

~ e ~ ~ ~ ~~ ~

, ~~ e'

e ~

~ ~~ ~

e, ~ 5

FI6URE 6

OFFSITE ENVIRONENTAL SAMPLING LOCATIONS - SUSQUEHANNA SES

$ $ TWP H AI/IH

F1 A/OVHfTWP

A<CP$P

HVHCOTWP

fAIOP

gfH /IP

Tl 0 Hfw

~ 18F1NEW

COLV VS

VH/0 HWP

HfW

a COxf

; 3F1

,/!2F1

T P

LO Alw

P'ICW.F61.

FIC

Hl 0ffWP 1482

~ 283 ~

~ 78

~ 882

OiOPAHCf!TH P

lI

OP/ APCHfff

TwP!I

< +1%4 sE1<sE2

6E1 ~

j

I

IOP iHl(fHJIIf'

~ 12E18C<<w<Cx

R1181

~ 951'E1 um

%1

<<R<AR (RCCx~

lSOVI'f

~ n.w P

7E1

IaVrC f

H'RP/ //I/

r /

~ N3 g~ 'CC, r<<G&M

g/F1261 's~ I

w QO

<<< +A< f+VfP '.

A/AVHfw I/

~*XW Si «Page'jOI<,

'ayr

i S

«AttCIG/I

P ~

TPP

Cf HH I $ 'OHrwP ~

$c

CVH/OH Cg

fw1 //

+sgV HI H

TWPASS

~ ~"'i 761

46DE,t: i1/989

T E 7

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

Page 1 of 3

Exposure Pathwaysand/or Sam le

Airborne

Radioiodine andParticulates

Direct Radiation

Number of Samplesand Locations*

11S2 (0.4 mi SW - Former Golomb House)9Bl (1.3 mi S - Transmission Line)5S4, 0.8 mi E - W of Bio. Consult.)12E1 4.7 mi WSW - Berwick Hospital)7G1 14 mi SE - PP&L Hazleton Chemical

Lab)2S2 (0.9 mi NNE - Susq. Energy Info.

Center)15S4 (0.6 mi NW - Transmission Corrodor1D2 (3.9 mi N — Mocanaqua Substation)3D1 (3.4 mi NE - Pond Hill)12G1 (15 mi W)W

- Bloomsburg ServiceCenter)

1S2 Perimeter Fence - 0.2 mi N

1D2 Mocanaqua Substation - 4.0 mi N

2S3 Perimeter Fence - 0.2 mi NNE2B3 Former Luzerne Outerwear-

1.3 mi NNE

2F1 St. Adalberts Cemetery - 5.9 mi NNE3S4 Perimeter Fence - 0.3 mi NE3Dl Pond Hill - 3.4 mi NE

3F1 Valania Resident (Nanticoke)-9.1 mi NE

3G3 Wilkes-Barre-Horton St. Substation-16 mi NE

4S3 Perimeter Fence - 0.2 mi ENE4E1 Pole (¹) 46422 N35197 - 4.8 mi ENE4Gl Mountain Top - Industrial Park-

14 mi ENE5S7 Perimeter Fence - 0.3 mi E

5E2 Bloss Farm — 4.5 mi E

6S4 Perimeter Fence - 0.2 mi ESE6A4 Former State Police — 0.6 mi ESE

Sampling andCollection Fre uenc

Continual sampler operationwith sample collection weekly.**

Quarterly

Type and Frequencyof Anal sis

Radioiodine Canister:analyze weekly for I-131

Particulate Sample:Analyze for gross betaradioactivity 24 hoursfollowing filter change.Perform gamma isotopicanalysis on compositesample (by location)quarterly.

Gamma Dose: Quarterly.

TABLE 7 ( tinued) Page 2 of 3


C7f31n

Waterborne

Surface

Drinking


6E1 St. James Church - 4.7 mi ESE6S9 Perimeter Fence - 0.2 mi ESE7S6 Perimeter Fence - 0.2 mi SE7E1 Harwood Transmission Line Pole 82-

4.2 mi SE7G1-Hazleton Chemical Lab - 14 mi SEaBS2 Perimeter Fence - 0.2 mi SSEBB2 LaWall Residence - 1.4 mi SSE8D3 Mowry Residence - 4.0 mi SSE9S2 Security Fence - 0.2 mi S9D1 Smith Farm - 3.6 mi S

10S1 Perimeter Fence - 0.4 mi SSW

10D2 Ross Ryman Residence - 3.0 mi SSW

11S3 Security Fence - 0.3 mi SW

11E1 Jacobsen - 4.7 mi SW

12S3 Perimeter Fence - 0.4 mi WSW

12El Berwick Hospital - 4.7 mi WSW

12G1 Bloomsburg - 15 mi WSW-13S2 Perimeter Fence - 0.4 mi W

13E4 Kessler Farm - 4.1 mi W

14S5 Site Pole 43996/N34230 0.5 mi WNW

14E1 Canouse Farm - 4. 1 mi WNW

15F1 Zawatski Farm - 5.4 mi NW

15S5 Perimeter Fence - 0.4 mi NW

16Sl Perimeter Fence - 0.3 mi NNW

16S2 Perimeter Fence - 0.3 mi NNW

16Fl Hidlay Residence (Huntington Mills)-7.8 NNW

6S6 river water intake linea

6S7 cooling tower blowdown dischargeline

12H2 Danville Water Co.(Approximately 30 miles downstream)


Monthly compositeMonthly composite

Monthly composite b

Type and Frequency-of Anal sis

Gamma isotopic analysis.Composite tritiumanalysis at leastquarterly.

Gross beta and garmaisotopic analyses monthlyComposite for tritiumanalysis at leastquarterly.

TABLE 7 (Continued)Page 3 of 3


Sediment fromShoreline

Milk***


7B Bell Bend - 1.2 mi SE

12B2 Shultz Farm - 1.7 mi WSW

9D3 Broyan Farm - 3.9 mi. S

10G1 Davis Farm - 14 mi. SSW10D1 Ryman Farm - 3.0 mi. SSW

13E3 Dent Farm - 5.0 mi. W

14B2 Stola Farm - 1.8 mi WNW


Semiannually

Semi-monthly when animalsare on pasture, monthlyotherwise

Type and Frequencyof Anal sis

Gamma isotopic analysissemiannually.

Gamma isotopic and I-131analysis of each sample.

Fish andInvertebrates

Food Products

Outfall area2H Falls, PA(Approximately 30 mi NNE)

llD1 Zehner Farm - 3.3 mi SW

vegetable

Semiannually. One samplefrom each of two recrea-tionally important speciesfrom any of the followingfamilies: bullhead catfish,sunfish, pikes, or perches.

At time of harvest

Gamma isotopic onedible portions.

Gamma isotopic onedible portions.

*T e ocation o samp es and equipment were designed using the guidance in the Branch Technical Position to NRC Rev.Guide 4.8, Rev. 1, Nov. 1979, Reg. Guide 48. 1975 and ORP/SID 72-2 Environmental Radioactivity Surveillance Guide.Therefore, the airborne sampler locations were based upon X/Q and/or D/Q.**A dust loading study (RMC-TR-81-01) concluded that the assumption of 1 for the transmission correction factor forgross beta analysis of air particulate samples is valid. Air particulate samples need not be weighed to determinea transmission correction factor.***Ifa milk sample is unavailable for more than two .sampling periods from one or more of the locations, a vegetationsample shall be substituted until a suitable milk location is evaluated. Such an occurrence will be documentedin the REHP annual report.

bControl sample location.Two-week composite if calculated doses due to consumption of water exceed one millirem per year. In these cases,I-131 analyses will be performed.The sample collector will determine the species based upon availability, which may vary seasonally and yearly.

~~~ 4 'I 1989

TABLE 8

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS

Lower Limit of Detection (LLD)

~Anal sis

gross beta

H-3

Mn-54

Fe-59

Co-58

g Zn-65

Zr-95

Water~Ci /1)

2000

15

30

15

30

15

Airborne Particulateor Gas

Ci/m3)

1x10

FishCi/k , wet)

130

260

130

260

Milk~Ci /l)

Food Products Sediment~/k'/k . k / k /k .k

I-131

Cs-134

Cs-137

ea-140

La-140

1b

15

18

60

15

7x10

5 x 10

6 x 10

130

150

15.

18

60

15

60

60

80

150

180

TABLE 8 (Continued)

aThe LLD is the smallest concentration of radioactive material in a samplethat will be detected with 95 percent probability and with 5 percentprobability of falsely. concluding that a blank observation represents a"real" signal.

For a particular measurement system (which may include radiochemicalseparation):

LLD = 4.66 sb

2.22 EVY exp - dt)where:

LLD is the "a priori" lower limit of detection as defined above (as pCiper unit mass or volume).

s„ is the standard deviation of the background counting rate or of thec5unting 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)

g is the radioactive decay constant for the particular radionuclide, and

ht 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-rayspectrometry, 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 griori (before thefact) limit representing the capability of a measurement system and not as aposteriori (after the fact) limit for a particular measurement.b

LLD for drinking water.

51.

~I, ~ '

I

10.0 DOSE ASSESSMENT POLICY STATEMENTS

10.1 Selection of Anal sis Results for Dose Calculations

For determination of compliance with SSES Technical Specificationdose limits, effluent totals shall be based only on activitypositively detected at the 95'A 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 Criteria for Potential Unmonitored Release Pathwa s

Doses from effluent pathways other than the usual, monitoredpathways shall be included in determining compliance with site dose

limits if an assessment made in accordance with the parameters and

assumptions of the ODCM indicates'that the total calculated dose

contribution from unmonitored pathways exceeds 5X of the calculateddose from normal, monitored pathways.

OEC gt $89

52

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 isexhaust 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 sampleat 4-hour intervals are not required from the SGTS vent when theSGTS continuous vent monitor is out of service, provided that-

a. the Standby Gas Treatment System is not being used,

b. there are proper administrative controls in place to ensurethat the required sampling will begin within 4 hours if thetreatment system is operated.

10.5 ODCM Set pints are U er Limit Values

Effluent monitor alarm/trip setpoints calculated in accordancewith 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 maximizethe 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 appropriateportions of the liquid waste treatment system be operable and be

used to reduce radioactivity in liquid wastes prior to theirrelease when projected doses from each reactor unit tounrestricted areas would exceed 0.06 mrem to the total body or 0.2mrem to any organ in a 31 day period. Appropriate treatment isdefined as follows:

a. Filtration combined with demineralization is considered

appropriate treatment for batches which yield projected doses

greater than 6.54E-04 mrem to the total body or 2. 15E-03 mrem

to any organ.

53 UE('1889,

b. Filtration alone is considered appropriate treatment forbatches which yield projected doses less than or equal to6.54E-04 mrem to the total body and 2.15E-03 mrem to any

organ.

BASES

The projected dose threshold values used are derived by dividingthe site-total maximum projected doses without treatment (0. 12 and

0.4 mrem) by 31 days and by 6, the maximum possible number ofbatches released per day, to yield per-batch dose action levels.The two levels of "appropriate" treatment are in place so as notto require application of demineralization for treating lowactivity, high conductivity water (e.g., from Circulating orService Water leakage). This would increase the overallefficiency of the solid radwaste program while ensuring calculateddoses remain at a suitable fraction of 10 CFR 50 designobjectives.

10.7 Monitor Line Loss Corrections

In order to correct for airborne effluent monitor sample lineloss, the following correction factors shall be applied to monitordata and sample analysis results:

ROUTINE EFFLUENT MONITORS

CORRECTION FACTORS

IODINE PARTICULATES

Reactor Building Unit 1

Reactor Building Unit 2

Turbine Building Unit 1

Standby Gas Treatment'Turbine Building Unit 2

1.5 3.21.6 . 3.61.5

1.6

3.93.6

1.5 3.2

QEC Z Z ~989

54

I~

'!

I fl

sl

POST ACCIDENT VENT MONITORS

CORRECTION FACTORS

IODINE PARTICULATES


Standby Gas Treatment


1.7

1.6

1.7

4.24.44.3

Each indicated iodine and particulates concentration shall be

multiplied by the appropriate correction factor to estimate theactual 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 accordancewith Section 2.2 to alarm before the dose rate limits ofSpecification 3. 11.2. 1 are exceeded. Station alarm responseprocedures contain instructions for investigation and verificationof monitor alarms. Because setpoint. calculations must includeassumptions about the composition of the monitored effluent, a

monitor high alarm does not necessarily indicate that a dose ratelimit has been exceeded. Dose rate calculations can be performedusing the methodology contained in the worksheets contained inAppendix E, based on vent monitor data or vent sample analyses.

For determination of compliance with the airborne effluent dose

rate limits, vent monitor history data should be used with theshortest averaging period which covers the period, of interest.The dose rate limits shall be treated as instantaneous limits, and

an effort should be made to capture all available data in the'arly stages of response to an incident to prevent loss of thedata.

Valid ten-minute averaged data should be the primary informationused to determine the compliance status of an incident.One-minute averaged data should also be reviewed if available, butthey may or may not provide additional information depending on

the magnitude of the release due to the manner in which the

55 OEG g 1 >989

Ly

~

q'A

, ~

monitors update values to be stored and associated statisticalconsiderations. Averages over a longer period should be used onlywhen data with higher resolution is not available. Grab sample

analyses should be performed whenever possible to confirm ordisprove monitor data, and to provide indication of thenuclide-specific composition of the effluent. When grab sample

data are available which, based on vent monitor data, areindicative of the period of elevated release, dose ratecalculations should be performed using the methodology of AppendixE and the actual effluent mix. The determination of compliancestatus should not be based on monitor data alone when it ispossible to collect and analyze a vent sample which will be

representative of the period of elevated release.

10.9 Low-Level Radioactivit in the Sewa e Treatment Plant

Like all sewage processing facilities, the SSES sewage treatmentplant can under certain conditions receive low levels ofradioactive materials. The most notable scenario is when

individuals who work on-site have been subjected to the medicaladministration of radiopharmaceuticals for diagnostic ortherapeutic purposes. In 'these cases, normal biologicalelimination processes can easily result in levels of radioactivityin sewage treatment plant solutions and suspensions which arewithin the detection capabilities of the associated sampling and

analysis program.

Because disposal of sewage treatment plant sludge by controlleddispersal on specified tracts of land is a common practice, thefollowing 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 decay toless than detectable levels.

56Ogg g g )989

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 of10 CFR 20.302.

d. The sewage treatment plant effluent should be sampled monthlyfor radioactivity. This can be accomplished by drawing a

sample from the chlorine contact chamber.

QEC q Z ~989

57

~ ~

I

11.0 ODCM REVIEW AND REVISION CONTROL

The Environmental and Chemistry Group Supervisor-Nuclear shallensure that a total review of the ODCM is performed during each

even-numbered year. Comments shall be documented and revisionsinitiated as appropriate.

Each ODCM page shall be stamped with its revision date. The

ODCM Table of Contents shall present the current revision datefor 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 they have

been approved by the Manager-Nuclear Services and have become

effective. Any changes recommended by PORC can be reflected insubsequent ODCM revisions.

ODCM copies shall be issued in a controlled fashion by the staffof the Nuclear Department Library. The distribution list shallbe maintained by the Nuclear Department Library Staff.

Any comments on ODCM contents or proposed revisions should be

directed to the Environmental and Chemistry Group Supervisor.

OEG gt $89

58

APPENDIX A

SAMPLE CALCULATIONS OF ODCM PARAMETERS

A. 1 SETPOINTS

A.l.1 Waterborne Effluent Moni tors

A. 1. 1. 1 Li uid Radwaste Dischar e Line Monitor

For an unidentified mixture with an assumed MPC of 1E-7

uCi/ml, an actual activity concentration of 1E-5

uCi/ml, and a blowdown flow setpoint of 5000 gpm, thesetpoint concentration, c, can be determined from c =

X (A). If X = 3, then the actual setpointconcentration is:

c = X (A) = 3 ( lE-5)c = 3E-5 uCi/ml

The setpoint value for the liquid effluent monitors isthen determined by Equation 3 in the ODCM. For theabove release conditions, the setpoint value, assuming

a typical calibration factor of 1.3 x 10 uCi/ml percpm, would be:

Setpoint cpm =

Cal. Factor

+ Background (cpm)

31" 3= 33. 3 33 3

1.3 1

Setpoint cpm = 2.3E3 + Background

A-1

The LRW discharge flow setpoint is then determined as

follows:

F+ f = Y(A)

where Y is made equal to 10.

5000 + f = 10(1E-5)

f = 5 gpm

For an identified mixture with an actual NPC of 7.22E-7uCi/ml and the same activity concentration, blowdownflow and X and Y values as above, the LRW dischargemonitor setpoint value and LRW discharge flow setpointbecome:

Setpoint concentration (c) = 3E-5 uCi/mlSetpoint value = 2.3E3 cpm + BackgroundLRW discharge flow setpoint (f) = 36 gpm

A. 1. 1.2 Service Water Nonitor

~gk 0 0: kg d = 00 pCalibration Factor = 1.5E-8 uCi/ml percps

(2E-5)/Cal. Factor = 1333 cps

Because 300 cps is less than 1333 cps:

HI RAD Setpoint = 0.5 Background + (2E-5)/Cal. Factor= 0.5 (300 cps) + (2E-5)/(1.5E-8)= 150 cps + 1333 cps = 1483 cps

DOWNSCALE Setpoint = 0.5 Background~ = (0.5)(300 cps) = 150 cps

~dk 0 0: 0 kg d = 1000 pCalibration Factor = 1.5E-8 uCi/mlper cps

(2E-5)/Cal. Factor = 1333 cpsBecause 1400 cps is greater than 1333 cps:

HI RAD Setpoint = Background + (0.5)(2E-5)/Cal. Factor= 1400 cps + (1E-5)/(1.5E-8)= 2067 cps

A-2 QEG g 1 1989

DOWNSCALE Setpoipt = Background - 0.5 (2E-5)/Cal.Factor

= 1400 cps - 0.5 (2E-5)/1.5E-B)= 1400 cps - 667 cps = 733 cps

A. 1. 1.3 RHR Service Water Monitor

Il 0 B kg d = 160 cpmCalibration Factor = 3.9E-9 uCi/ml percpm

(2E-5)/Cal. Factor = 5128 cpm

Because 160 cpm is less than 5128 cpm:

HI RAO Setpoint = 0.5 Background + (2E-5)/Cal. Factor= 0.5 (160 cpm) + (2E-5)/(3.9E-9)= 80 cpm + 5128 cpm = 5208 cpm

LOW RAD Setpoint = 0.5 Background= 0.5 (160 cpm) = 80 cpm

ALERT Setpoint = 0.8 HI RAD Setpoint = 4166 cpm

B kg d = 0000 0Calibration Factor = 3.9E-9 uCi/mlper cpm

(2E-5)/Cal. Factor = 5128 cpmBecause 6000 cpm is greater than 5128 cpm:

HI RAO Setpoint = Background + (0.5)(2E-5)/Cal. Factor= 6000 cpm + ( 1E-5)/(3.9E-9)= 6000 cpm + 2564 cpm= 8564 cpm

LOW RAD Setpoint = Background - 0.5 (2E-5)/Cal. Factor= 6000 cpm - 0.5 (2E-5)/(3.9E-9)= 6000 cpm - 2564 cpm = 3436 cpm

ALERT Setpoint - 0.8 HI RAD Setpoint = 6851 cpm

Gaseous Effluent Monitors

A.1.2.1 Noble Gas Monitor

To determine the release rate limit for noble gases,an isotopic mixture representative of plant effluentsis selected. For example, the following mixture from

A-3DEC g 1 1989

Table 4.4 of the SSES Final Environmental Statement(FES) can be used:

Argon-41

Krypton-83m

Krypton-85m

Krypton-85

Krypton-87

Krypton-88Xenon-131m

Xenon-133m

Xenon-133

Xenon-135m

Xenon-135

Xenon-138

Total

25 Ci/yr per reactor4

1,700

270

32

660

71

14

12,500

220

590

290

16,376 Ci/yr per reactor

The above annual release quantities are entered intoGASPAR with the following annual average dispersionestimates (Reference: 1982 SSES Meteorology Report):

Relative ConcentrationDecayed Relative ConcentrationDecayed Depleted Relative ConcentrationDeposition Rate

4.1E-5 sec/m

4.1E-5 sec/m

3.8E-5 sec/m

4.2E-8 m

This set of annual average meteorological parametersis the most conservative over the period 1973-1982.

The total body dose via the plume pathway which

results is 18.3 mrem. Equation 5 of the ODCM is then

used to calculate the limiting release rate from each

of the five plant release points:

A-4 OF.C <~$ 89

Limiting Release Rate =

32,752 Ci) (500 mrem/ r) 8 95E4 C /= 8.95E4 Ci/yr per vent(36.6 mrem) (5 vents)

This limiting release rate is then converted tolimiting (setpoint) concentrations using Equation 6 ofthe ODCM and high limit vent flow rates.

Sample High Limit Vent Flow Rates:

Unit 1 Reactor Building Vent

Unit 2 Reactor Building Vent

Standby Gas Treatment System Vent

Unit 1 Turbine Building Vent

Unit 2 Turbine Building Vent

4.75E9 cc/min4.75E9 cc/min5.04E8 cc/min

8.63E9 cc/min

6.50E9 cc/min

Limiting Vent Concentration =

(8.95E4 Ci/ r/vent ( lE6 uCi/Ci3 58E 5 C /

(5.26E5 min/yr) (4.75E9 cc/min) for ReactorBuildings 1&2

Substituting the other vent flow rates into Equation 6

as above, the following noble gas high radiation set-point concentrations are calculated for the remainingvents:

Standby Gas Treatment System

Unit 1 Turbine BuildingUnit 2 Turbine Building

3.37E-4 uCi/cc1.97E-5 uCi/cc2".62E-5 uCi/cc

A-5QE.G g 4 1989

A.1.2.2 Iodine -131 Monitor

When the FES expected annual release quantity forI-131 (2.40E-1 curies) is entered into GASPAR with thedispersion estimates of A. 1.2. 1, the maximum

calculated organ dose via the inhalation pathway is4.88 mrem to the child thyroid. Using Equation 5 ofthe ODCM, the limiting I-131 release rate is calcu-lated as follows:


(.24 Ci ( 1500 mrem/ r) 1.48E1 Ci/yr/vent(4.88 mrem) (5 vents)

Using Equation 6 of the ODCM, the limiting (setpoint)I-131 concentrations can be calculated for each of thefive plant vents.


( 14.8 Ci/ r/vent) 1E6 uCi/Ci = 5.92E-9 uCi/cc,for(5.26E5 min/yr) (4.75E9 cc/min) Reactor Buildings

1&2

Substituting the other vent flow rates into Equation 6

of the ODCM above, the high radiation setpoints forthe remaining plant vents are calculated to be thefollowing:



5.58E-B uCi/cc3.26E-9 uCi/cc4.33E-9 uCi/cc

A-6 QE.G 11 1989

A.1.2.3 Particulate Monitor

Following are the SSES Final Environmental Statement

(FES) expected annual release quantities for particu-late radionuclides:

Cr-51

Mn-54

Fe-59

Co-58

Co-60

Zn-65

Sr-89

Sr-90

Zr-95

Sb-124

Cs-134

Cs-136

Cs-137

Ba-140

Ce-141

Total

1.2E-4 Ci/yr per reactor,. 3.6E-4

1.6E-4

5.8E-5

1. 1E-3

5.5E-5

1. SE-5

3. 1E-6

8. 7E-6

5.1E-6

1.3E-4

1.3E-3

2.1E-4

4.2E-5

2.9E-5

3.6E-3 Ci/yr per reactor

When the above annual release quantities are enteredinto GASPAR with the annual average dispersion esti-mates of A. 1.2.1, the maximum calculated organ dose

via the inhalation pathway is 1.33E-2 mrem to the teen

lung. Using Equation 5 of the ODCM, the limitingrelease rate of particulates can be calculated:


(7.2E-3 Ci) 1500 mrem/ r 8.12El Ci/yr/vent(2.66E-2 mrem) (5 vents)

A-7 gEG'g" 4 1989

Using Equation 6 of the ODCN, the limiting (setpoint)particulate concentrations can be calculated for each

of the five plant vents.


(81.2 Ci/ r/ventmsn yr

(1E6 uCi/Ci = 3.25E-8 uCi/cc forcc msn Reactor Buildings

152

When the vent flow rates for the remaining five plantvents are substituted into Equation 6 as above, thefollowing high radiation setpoint concentrationsresult.



3.06E-7 uCi/cc1.79E-8 uCi/cc

. 2.38E-8 uCi/cc

A.2 AIRBORNE EFFLUENT DOSE RATE CALCULATIONS

A.2. 1 Noble Gases

To evaluate the annual whole-body or skin dose from

noble gas release rates, the highest calculated annual

average relative concentration for any sector isselected from Table 3. For the SSES site, thecritical downwind sector is the West sector with an

annual dispersion factor of 2.6 x 10 sec/m . The-5 3

expected release rate of the principal noble gas

radionuclide, xenon-133, is 396 uCi/sec. To calculatethe annual whole-body dose due to the release of any

noble gas in the gaseous effluent, Equation 7 in theODCM should be used. The whole-body dose factor (K.)

21

from Table 2 for xenon-133 is 2.94 x 10 mrem/yr

A-8GEC g11%9

E

3per uCi/m . Substituting these values in Equation 7,the whole-body dose contribution from xenon-133

releases from the SSES would be 3.0 mrem/yr:

Dwb= (K,.)(X/Q)v (Q',-v) (Equation 7)

Dwb= (2.94 x 10 mrem/ r) (2.6 x 10 sec)

2 -5

uCi/m m

X (396 uCi/sec) = 3.0 mrem/year

To calculate the annual skin dose due to release ofany noble gas in the gaseous effluent, Equation 8 inthe ODCN should be used. The skin dose factor (L.)

1

from Table 2 for xenon-133 is 3.06 x 10 mrem/yr

per uCi/m . The air dose factor (N.). from Table 2 for3

21

xenon-133 is 3.53 x 10 mrad/yr per uCi/m .

Substituting these values and the previous values forrelease rate and annual dispersion factor inEquation 8, the skin dose contribution from xenon-133

from the SSES would be 7. 1 mrem/yr:

= (L; + 1 1 ~;) (X/Q)v (Q';„) (Equation 8)

0 = (3.06 x 10 ~ + 1 IsuCi/m

(3.53 x 102 ~mrad/ r)) (2 6 „10-5 sec)

uCi/m m

x (396 uCi/sec) = 7. 1 mrem/year

A-9

A.2.2 Radionuclides Other Than Noble Gases

To evaluate the annual critical organ dose from

radionuclides other than noble gases, the highestannual average dispersion parameter for estimating thedose to the critical receptor is selected from

Table 3. The highest annual dispersion factor is2.6 x 10 sec/m in the West sector . The expected

-5 3

release rate of iodine-131 is 3.8 x 10 uCi/sec. The-6

expected release rate of cesium-137 is 6.66 x 10

uCi/sec.

To calculate the annual critical organ dose due to therelease of radionuclides other than noble gases in thegaseous effluent, Equation 9 in the ODCN should be

used. The inhalation pathway parameter (P.) from1

Table 4 for iodine-131 is 1.48 x 10 mrem/yr peruCi/m . Substituting these values in Equation 9, the

3

maximum thyroid dose contribution from iodine-131would be 1.5 mrem/yr from the inhalation pathway.

(Equation 9)

0 = (1.68 x 10 ~mrem/ r ) (2.6 x 10 sec)

uCi/m m

X (3.8 x 10 uCi/sec)

= 1.5 mrem/year INHALATION PATHWAY, I-131

A-10 DEC g 4 f989

A. 3 INDIVIDUAL DOSE

A.3. 1 Waterborne Effluents

The liquid effluent dose calculations are performed using theLiquid Annual Dose,To All Persons (LADTAP) computer program.

This program may be used to calculate the quarterly (or anyother time period) doses to both the maximum individual and the50-mile population due to radionuclides released in liquideffluents from the SSES. The procedure involves the use of thecomputer code LADTAP which was developed by the NRC to performdose calculations in accordance with Regulatory Guide 1. 109.

The User's Manual for the LADTAP program contains details of thecalculational procedures. The total number of curies releasedfor each radionuclide during the time period being evaluatedmust be supplied from the SSES radiation monitoring program.

A.3.2 Airborne Effluents

The airborne effluent dose calculations are performed using theGASPAR computer program. This program may be used to calculatethe maximum individual and population doses due to radionuclidesreleased in gaseous effluents from the SSES. The code

implements the semi-infinite cloud model and the dose

calculational models of Regulatory Guide 1. 109 and is used tocalculate all maximum individual and population doses and

maximum individual organ doses from the SSES. A more detaileddescription of the GASPAR code can be found in the GASPAR dose

code manuals dated October 17, 1975, and February 20, 1976. The

total number of curies released for each radionuclide during thetime period being evaluated must be supplied from the SSES

radiation monitoring program. The meteorological parametersmust be provided from the SSES meteorology program.

A-ll OEG g i 1989

~ ~

V+

To evaluate the air dose from noble gas release rates, thehighest calculated annual average relative concentration for anysector is selected from Table 3. This critical downwind sectoris the West sector with an annual dispersion factor of 2.6 x

10 sec/m . The expected release rate of the principal noble-5 3

gas radionuclide, xenon-133, is 396 uCi/sec. The total releasein a calendar quarter would be 7.9 x 10 seconds times6

396 uCi/sec or 3. 13 x 10 uCi. To calculate the quarterly gamma9

air dose due to the Xenon-133 release in the gaseous effluent,Equation 12 in the ODCN should be used. The gamma air dose

factor (N.) from Table 2 for xenon-133 is 3.53 x 10 mrad/yr2

per uCi/m . Substituting these values in Equation 12, thequarterly gamma air dose contribution from xenon-133 releasesfrom the SSES would be 0.9 mrad:

D =3.17 x10 ~r Ni XQ)v Qisec

(Equation 12)

0 = (3.17 x 10 ~r)(3.53 x 10 mead/ r)(2.6 x 10 sec)sec uCi/m m

X (3.13 x 10 uCi/qtr)9

= .9 mrad/quarter

To calculate the quarterly beta air dose due to the xenon-133release in the gaseous effluent, Equation 13 in the ODCN shouldbe used. The beta air dose factor (Ni) from Table 2 forxenon-133 is 1.05 x 10 mrad/yr per uCi/m . Substituting these

3 '. 3

values in Equation 13, the quarterly beta air dose contributionfrom xenon-133 releases from the SSES would be 2.7 mrad:

Db = 3. 17 x 10 Zr Ni (X/Q) Q'Equation 13)sec

0> = (3.17 x 10 ~r)(1.05 x 10s mead/ r)(2.6 x 10 sec)sec

uCi/m m

A-12 DEC g l 1989

X (3. 13 x 10 uCi/qtr) = 2.7 mrad/quarter9

Since the beta air dose is greater than the gamma air dose by a

factor of 3 for xenon-133 and the dose limits are only a factorof 2 greater for beta than gamma radiation, the beta air dose

would be controlling for'enon-133 releases.

A.4 TOTAL DOSE

The total cumulative annual dose to any member of the public fromoperations at the SSES should be determined by summing the critical organdoses to real individuals from all three sources of radiation. Only themaximum dose or dose commitment to a real individual needs to be

evaluated.

A.4.1 ~Li id Eff1

The cumulative dose to any member of the public due to liquideffluents from the SSES should be determined from the LADTAP

program used for evaluating the individual doses as stated inSection A.3. 1 of this Appendix.

A.4.2 Gaseous Effluents

The cumulative dose to any member of the public due to gaseous

effluents from the SSES should be determined from the GASPAR

program used for evaluating the individual doses as stated inSection A.3.2 of this Appendix.

A.4.3 Direct Radiation

The direct radiation to any member of the public due tooperations at the SSES should be determined from th'

environmental monitoring program results.

BEG g1>989

APPENDIX 8

REPORTING RE UIREMENTS

8.1 ANNUAL ENVIRONMENTAL OPERATING REPORT, PART 8, RADIOLOGICAL

A report on the radiological environmental surveillance program for theprevious calendar year shall be submitted to the Director of the NRC

Regional Office (with a copy to the Director, .Office of Nuclear ReactorRegulation) as a separate document by May of each year. The period ofthe first report shall begin with the date of initial criticality. The

reports shall include a summary (format of Table 8-1), interpretations,and an analysis of trends from the results of the radiologicalenvironmental surveillance activities for the report period, including a

comparison with operational controls, preoperational studies (as

appropriate), and previous environmental surveillance reports and an

assessment of the observed impacts of the station operation on theenvironment.

In the event that some results are not available, the report shall be

submitted noting and explaining the reasons for the missing results. The

missing data shall be submitted as soon as possible in a supplementaryreport.

QEG g t 1989

8-1

8.2 NONROUTINE RADIOLOGICAL ENVIRONMENTAL OPERATING REPORTS

When the level of radioactivity in an environmental sampling medium

averaged over any quarterly sampling period exceeds the reporting levelgiven in Table 8-2, a written report shall be submitted to the Directorof the NRC Regional Office (with a copy to the Director, Office ofNuclear Reactor Regulation) within 30 days from the end of the quarter.If it can be demonstrated that the level is not a result of stationeffluents (i.e., by comparison with control station or preoperationaldata) a report need not be submitted, but an explanation shall be givenin the annual report.

When more than one of the radionuclides in Table 8-2 are detected in themedium, the reporting level will have been exceeded if:

concentration 1)reporting eve

+ concentration (2) + ... > 1

reporting eve

If radionuclides other than those in Table 8-2 are detected and are due

from station effluents, a reporting level is exceeded if the potentialannual dose to an individual is equal to or greater than the designobjective doses of 10 CFR Part 50, Appendix I. This report shall includean evaluation of any release conditions, environmental factor, or otheraspects necessary to explain the anomalous result.

8-2 OF-G g I 1989

TABLE B-1

SAMPLE ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL SUMMARYReporting Period: 1/1/79 - 12/31/79

Medium or Type andPathway Sampled Total Number

(Unit of of AnalysesMeasurement Performed

MeanRan e

All Indicator Location with HighestLower Limit Locations Annual Mean

of Name,Detection Mean Distance &

L ~ N

Control Locations Number ofNonroutineReported

Mean Ran e Measurements

CXII

Air Particulates(10 pCi/m ) Gross Beta 336 26.6(234/234) 1D2

(7.7-71) 3.7 mi N

29.9(52/52) 28.2(102/102)(11-71) (9.8-64)

Air Iodine

(10 pCi/m )

Gamma 28Be-7

Cs-137

1-131 160

0.6

1.5

81(20/20)(37-130)

1.6(4/20)(1.1-1.8)

- (0/109)

3D1 82(4/4)3.2 mi NE (54-130)

N/A N/A

1D2 5.7(2/4)3.7 mi NE (2.3-9.0)

85(8/8)(51-140)

2.7(1/8)(2.7)

-(0/51)

o e: e examp e a a are provided for illustrative purposes only.

TABLE B-2

REPORTING LEVELS FOR NONROUTINE OPERATING REPORTS

~Anal sis

H-3

Mn-54

Fe-59

Co-58

Co-60

Zn-65

Zr-Nb-95I I-131

Cs-134

Cs-137

Ba-La-140

Water~Ci/\

2 x 104(')

1x104x10 2

1 x 103

3 x 102

3x10 2

4 x 102(b)

2

30

50

2 10

Airborne Particulateof Gases Ci/m3)

0.9

10

20

Fish( Ci/k, wet)

3 x 10

1 x 10

3 x 10

1x102x10 4

1x102 x 10

Nilk~(Ci/1

3

60

70

3 10(

Broad LeafVegetationCi/k , wet

1x101x102x10

C3

a For drinking water samples. This is 40 CFR Part 141 value.

Total for parent and daughter.I b

I~

C'I

APPENDIX C

SITE SPECIFIC INFORMATION USED BY GASPAR CODE

1) The distance from the facility to the NE corner of the U.S. (Maine) inmiles 590 miles.

')

Fraction of year leafy vegetables are grown 0.33

3) Fraction of year cows are on pasture 0.60 (April-Nov.)

4) Fraction of crop from garden 0.76

5) Fraction of daily intake of cows derived from pasture while on 'pasture0.42

6) Absolute humidity over growing season ~9.0 /m-3

Relative humidity is 67.6% if T is supplied.

7) Average temperature over growing season 60.2'F

8) Fraction of year goats are on pasture 0.60

9) Fraction of daily intake of goat from pasture while on pasture 0.75

10) Fraction of year beef cattle are on pasture 0.60

11) Fraction of daily intake of beef cattle derived from pasture while onpasture 0.55

'EC1)$ 89

APPENDIX D

SITE SPECIFIC INFORMATION USED BY LADTAP CODE

1) Total discharge from all units: 22 cubic feet per second

2) 50-mile Population: 1,608,000

3) Blowdown Rate: 22 cubic feet per second

4) Total Annual Blowdown Volume: 6.94E8 cubic feet

5) Dose to Maximum Hypothetical Individual; Location = Danville, PA

a. Shorewidth factor: .2b. Dilution factors: See Figure D-1c. Transit time to drinking water intake: See Figure D-l

6) Sport Fish Harvest:

a. Zero to ten miles:

i. 7,000 kg/yr usageii. 219 dilutioniii. 2.9-hour transit time

b. Ten to twenty miles:


c. Twenty to thirty miles:


d. Thirty to forty miles:

i. 13,000 kg/yr usageii. 332 dilutioniii. 16.l-hour transit time

e. Forty to fiftymiles:


D-1

"'» ass

7) Population. Drinking WaterDanville, PA (Closest active drinking water supplier)

a. Population: 9,000 servedb. Dilution factor: See Figure D-1c. Transit time: See Figure D-1

8) Population Shoreline (Recreation)

a. Zero to ten miles:

i. " Usage: 354,000 manhours per yearii. 219 di 1 uti oniii. 2.9-hour transit timeiv. Shorewidth factor: .2

b. Ten to twenty miles:

i. Usage: 268,800 manhours per yearii. 263 dilutioniii. 6.8-hour transit timeiv. Shorewidth factor: .2

c. Twenty to thirty miles:

i. Usage: 259,200 manhours per yearii. 306 dilutioniii. , 11.6-hour transit timeiv. Shorewidth factor: .2

d. Thirty to forty miles':


e. Forty to fiftymiles:


9) Population Boating:

a. Location: 0-10 milesb. Usage: 96,000 manhours per yearc. Di 1ution: 210d. 2.9-hour transit time

D-2

10) Biota Dose

a. Location: Plant dischargeb. Dilution: 5

c.. 1-hour trans it time

QEC gS >989

D-3

FIGURE 0-1

DILUTIONFACTORS AND TRANSIT TIMESAS A FUNCTION OF RIVER LEVEL

H0URS

Tp

DANVI

LLE

80757065605550454035302520'f510

50

Tilt/ES

FT AXISLE

I

OILUT ONS

Rl HT AXIS

147 147.5 148 148.5 149 149.5 150 160.6 15

RIVER LEVEL AT BIO. LAB (m above MSL)Based on dye tracer study results

17001600150014OO1300 L

I

1200 U

11001000 p

I

900 N800700 A

F

6005004oo R3002001001

APPENDIX E

METHODS USED TO GENERATE DOSE RATE CALCULATION WORKSHEETS PAGES E4 - Ej

I. BASED ON VENT MONITOR NOBLE GAS DATA

A. WHOLE BODY DOSE RATE

Equation 7 of the ODCM states that the whole body dose rate tounrestricted area due to gaseous effluents is calculated as follows:

Dw,= + (K,.)(X/Q)v (Q',.v)

where:

0wb

K.

Q'iv

(X/Q)„

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

the whole-body rate conversion factor due togamma emissions for each identified noble gasradionuclide (i) (mrem/yr per uCi/m3) from Table 2of the ODCM.

the. release rate of radionuclide (i) from vent (v)(uci/sec).

the highest calculated annual average relativeconcentration for any area at or beyond the siteboundary in an unrestricted area from vent releasepoint (v) (sec/m3).

The whole-body dose rate conversion constant iscalculated as follows:

mrem/ r . D bWB DOSE RATE FACTOR u s msn = . = K(f.)(K.)(X/O),(1.676-2)

where:

= is the fraction of the total noble gas release whichnuclide (i) constitutes.

1.67E-2 = the number of minutes per second.

The whole-body dose rate conversion factor (5.88E-4}is based on the SSES Final Environmental Statement (FES) expected annualnoble gas releases and an annual average relative concentration of4. 1E-5 sec/m3 (ref. SSES 1982 Meteorological Summary).

B. SKIN DOSE RATE

Equation 8 of the ODCM states that the skin dose rate to unrestrictedareas due to gaseous effluents is calculated as follows:

E-1

'swhere:

Ds

Li

the annual skin dose rate (mrem/yr).

the skin dose rate conversion factor due to thebeta emissions for each identified noble gasradionuclide (i) (mrem/yr per uCi/m') from Table2 of the ODCM.

the air dose factor due to gamma emissions for eachidentified noble gas radionuclide (i) (mrad/yr peruCi/m~) from Table 2 of the ODCM (conversionconstant of 1. 1 converts air dose (mrad) to skindose (mrem).

The skin dose rate conversion constant (mrem/yr per uCi/min)is calculated as follows:

Skin Dose Rate Ds

Conv. ~acro~ = 6O < q',.„ =,. ( ,)( , ,)( /q)( . - )

(mrem/yr per uCi/min)

The skin dose rate conversation factor ( 1.16E-3) is basedon the SSES-FES expected annual noble gas releases and an annual averagerelative concentration of 4. 1E-5 sec/m~.

II. BASED ON VENT MONITOR DATA OTHER THAN NOBLE GAS

Equation 9 ofradionuclides

D

the ODCM states that the dose rate from inhalation ofother than noble gases is calculated as follows:

6 (P,.) (Wv) (~ ,.v)

where:

Dc

Pi

W„

the annual organ dose rate (mrem/yr).

the dose parameter for radionuclides other than noblegases for the inhalation pathway (mrem/yr per uCi/m').

=. the highest annual average dispersion parameter forestimating the dose. to the critical receptor (relativeconcentration (X/g, sec/m~) for the inhalation pathway).

the release rate of radionuclide (i) from vent (v)(uCi/sec).

E-2Utt' 1 198S

The organ dose rate conversion factor for particulates and I-131(mrem/yr per uCi/min) are calculated as follows:

Organ Dose Rate0

c

Conv. Facto = (6O ; 0'iv) =; ( ;)(P;)( v)( .67F--2)

(mrem/yr per uCi/min)

where:

the fraction of the total particulate release which nuclide(i) constitutes (equals 1 for I-131 dose rate conversionfactor).

The organ dose rate conversion factors (1.94 for particulates and 10.64 forI-131) are based on SSES-FES expected releases and an annual average relativeconcentration of 4. 1E-5 sec/m3.

III.BASED ON NOBLE GAS LABORATORY ANALYSIS

The whole-body dose rate conversion constants-(Column M) are calculated asfollows for each nuclide:

mrem/ r wbi0

WB DOSE RATE CONY. FACTOR. unusemsn = ED g . = (K.)(X/O)(1.672-2)1 iv 1

The skin dose rate conversion constants (Column P) of Form ODCM-2 arecalculated as follows for each nuclide:

mrem/ r siSKIN DOSE RATE CONY. FACTOR,. u s msn = ~g .„ = Li + 1. 1M,. X Q 1.67E-2

An annual average relative concentration value of 4. 1E-5 sec/m3 was used forcalculation of the constants.

IV. BASED ON LABORATORY ANALYSIS FOR NON-NOBLE GASES

The organ dose rate conversion constants (Column BB) of Form ODCM-4 arecalculated as follows for each nuclide:

mrem/ r ci0

ORGAN DOSE RATE CONY. FACTOR . unusemTn = BD 1( . = (P.)(W )(1.67E-2)1 iv 1 v

An annual average relative concentration value of 4.1E-5 sec/m3 was used forcalculation of the constants.

Because different radionuclides result in maximum dose comnitments todifferent organs, the methodology is conservative because dose ratecontributions from nuclides to differing organs are su@red and compared to thedose rate limit which is applicable to any one organ. If an apparentnoncompliance is calculated by this method, an organ dose from eachradionuclide should be calculated to determine if an actual noncomplianceexists.

Util 1 ~ l989

E-3

DOSE RATE CALCULATION MORKSHEET

Noble Gas Nuclides; Using Vent Monitor Data

NOTE: RELEASE RATE COMPLIANCE CAN BE DETERMINED BY DIRECT COMPARISON OFMEASURED RELEASE RATES WITH CALCULATED RELEASE RATE LIMITS. Themethodology of this form provides the actual dose rate valuesassociated with the measured release rates.

Noble Gas Release Rates:

Vent Release Rate (uCi/min)

RB1

RB2

TB1 .

TB2 .

SGTS

(A)

(B)

(c)

. (D)

(E)

A+B+C+D+E = (F)

Whole BodyDose Rate(mrem/yr)-

(F) x (8.41E-04)

) x (8.41E-04)

(Tech. Spec. limit is 500 mrem/year)

SkinDose Rate(mrem/yr)

(F) x ( l.45E-3)

x (1. 45E-3)

(Tech. Spec. limit is 3000 mrem/year)

Qt;C g1>989

E-4

DOSE RATE CALCULATIONWORKSHEET- Noble Gas Nuclides; Using Laboratory Analysis Data

RELEASE RATES FROM VENTS (uCi per minute)

..-e

e'.NUCUDE=--

-'RX'-'::BLDG--'--',

'.:=::,UNIT=,:.—.1"==.'=.";TRX-'LDG.'-';.=:";@NIT.=-2-'.„-'

TLURBlflEj,'STANDBYS ';TTURBLINE::-

;.'-'-'.UNIT"1.'-7-'.,;„'-'LGAS,'-„:='.;i =..'=;UNIT„.2=:::-',-L":-..==SITE"-,:

-"= tTOTAL=~-'';:. (L)x(ML)'„»„.- ,-".,=-(L}x(P)';::.

KR-83m 5.18EN 1.45E-5

KR-85

8;01'.10E-5

.1.93';:

9.30ER

::::::-;.;:-', ';:4;05EN 1'."13E-'2':-

KR-88 1.01E-2 1.31E-2

6;27E-'.5.': '4 43E-4,':.:,':.'.

XE-133m 1.72EX 9.27EA

»4;:705'.:

XE-13501 2.14EN 3.02EQ

2;72E-.3':::. ':::: .'::

XE-138

AR-:.41':::-;

'-:.-'.05E-3:::::: '::. 6.05E-;3:

9.76';85E-3'.

SUM OF UrM EQUALS THE WHOLE-BODYDOSE RATE (mrem/»rr) TECH SPEC LIMITIS 500

SUM OF LxP EQUALS THE SKIN DOSE RATE (mrem/yr) TECH SPEC UMIT1S 3000SUM LxM SUM Lxp

DOSE RATE CALCULATION WORKSHEET

Nuclides Other Than Noble Gases; Using Vent Monitor Data

VentRelease RatesParticulates

(uCi/minute)Iodine-131

(A)

(B)

(C)

(D)

(E)

RB1

RB2

TB1

TB2

SGTS

A+B+C+D+E

Maximum OrganDose Rate FromParticulates (S) x (1.19) mrem/year

( ) x (1.94) = mrem/yr

OrganDose Rate FromIodine-131 (T) x (10.1) mrem/yr

) x (1O.1) = mrem/yr

(CC) + (DD) mrem/yr; Tech. Spec. Limit = 1500 mrem/yr

E-6 Q~C ~ < ice

DOSE RATE CALCULATIONWORKSHEET- Nuclides other than Noble Gases; Using Laboratory Analysis Data

RELEASE RATES FROM VENTS (uCi per minute)

-.'„QUGLIDE'„:;;".«,'": PX"('BMLDG~4')

:j,';-'-,,, Noh„=~.-""."

:;.:.~"",RX),BL'DG',,-::- . ";,. TURBINE-',.:.<', =-',,UNIT-;1'".".'; -",

» .STANDBY;,,:;"''T'.j-,'GAS;; ..'-;:

-„;-„~TURBINE "=- '.-'(A}.='QE';.'-';--"'=TOTAL.":., ',;—:

:== '-'*";(B) -,,::-="; -".=-,;=,'(A)'x(B)..=;:;-:.:,:,

HC

CP-'51;::;;;:::;..::;;:,::::,';,:,::

MN-54

4.43EQ

":.,',:-::.:-,8,76E-3-'-.e-'::,:::::;:,::,'.85E-1

=;::: 6;98E-':.1::::: ':-,"::::,'.

CO-58 5.32E-1

-:::: '::'3.'09E+x".0,-',-''::;:

ZN-65 4A3E-1

-:::-;-';-::::'::::':::::-:-'::::1 39E+.0':::-:::-.

SR-90 2.80E+1

:::-'": 1:::;::::::::1:20E+0 ": -':—;

1-131 1.01E+1

CS'-..134::::::::::::.::::::::::-:::. '::: -'::;::4;81E-..1'-,':

'S-1369.24E-2

CS'-:.137;::::::::::::::,"::::::::: :-:.::::-:4.19E-1'-: '.:;-: '.

BA-140 1.10E+0

CE-141 -':.' ':",3,54E-1':-

SUM OF (A)x(S) IS THE ORGAN DOSE RATE FROM 1-131, H4, AND PARTICULATES (mrem(yr)- LIMITIS 1500SUM (A)X(B)

CALCULATION - Nuclear Regulatory Commission · PENNSYLVANIA PlNER 5 LIGHT COMPANY SUSQUEHANNA STEAM...

Documents

Transcript of CALCULATION - Nuclear Regulatory Commission · PENNSYLVANIA PlNER 5 LIGHT COMPANY SUSQUEHANNA STEAM...