Text

Annual Radioactive Effluent Release Rept HCGS RERR-19 for Jan-Dec 1996
	ML20138E882
Person / Time
Site:	Hope Creek
Issue date:	12/31/1996
From:	Dawn Powell; Public Service Enterprise Group
To:	;
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ML20138E885	List: ML20138E882; ML20138F451;
References
	HCGS-RERR-19, NUDOCS 9705050186
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,l HOPE CREEK GENERATING STATION ANNUAL RADIOACTIVE I

EFFLUENT RELEASE REPORT HCGS RERR-19 I

DOCKET NO. 50-354

<g OPERATING LICENSE NO. NPF-57 lI

!I iiI I

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l April 1997 I

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IIOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 1996 I

TABLE OF CONTENTS INTRODUCTION.

.3 PART A PRELIMINARY SUPPLEMENTAL INFORMATION

... 4 1.0 REG ULATOR Y LIMITS..........

....... 4 I

1.1 Fission and Activation Gas Release Limits....

.4 1.2 lodine, Particulates and Tritium.

... 5 1.3 Liquid EfDuents Re. ease Limits..............

....... 5 1.4 Total Dose Limit.

.5 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC).

.5 3.0 AVERAGE ENERGY.

.6 4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY

.6 4.1 Liquid Effluents.

.6 I

4.2 Gaseous EfDuents.

..6 4.3 Estimated Total Error.

...... 8 5.0 BATCII RELEASES.

8 6.0 UNPLANNED RELEASES..............

.8 7.0 ELEVATED RADIATION MONITOR RESPONSES.

.S 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS.

8 I

PART B GASEOUS EFFLUENTS

.8 PART C LIQUID EFFLUENTS.

8 PART D SOLID WASTE.

8 PART E RADIOLOGICAL IMPACT ON MAN.

.9 Liquid Pathways.

.9 I

Air Pathways.

.9 Direct Radiation

.10 1

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PART E RADIOLOGICAL IMPACT ON MAN (Cont'd)

Total Dose..

. 10 Dose to Members of the Public on Site

.11 Assessment

.... 11 Gaseous..

........11 Liquid..

. 12 Trends.....

13 PART F METEOROLOGICAL DATA...

... 14 PART G OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES.14 PART H INOPERABLE MONITORS.

14 PARTI PROCESS CONTROL PROGRAM (PCP) CHANGES..

. 14 PARTJ ENVIRONMENTAL MONITORING LOCATION CHANGES.

. 14 PART K MAJOR CHANGES TO WATER PROCESSING SYSTEMS.

. 14 TABLES TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 15 I

TABLEIB GASEOUS EFFLUENTS - GROUND LEVEL RELEASES.

.17 TABLE 1C GASEOUS EFFLUENTS - ELEVATED RELEASES.

.... 19 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL REL. EASES.. 20 TABLE 2B LIQUID EFFLUENT.

.22 TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS.

.24 TABLE 4A

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE (GASEOUS).

.26 TABLE 4B

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE (LIQUID)..

.30 APPENDICES APPENDIX A 1996 METEOROLOGICAL DATA APPENDlX B OFFSITE DOSE CALCULATION MANUAL (Revision 15) 2 I

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I IiOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 1996 I

INTRODUCTION I

This report, liCGS-RERR-19, summarizes information pertaining to the j

releases of radioactive materials in liquid, gaseous and solid form from the liope Creek I

Generating Station (IICGS) for the period January 1,1996 to December 31,1996.

I The liope Creek Generating Station (IICGS) employs a General Electric (GE)

Boiling Water Reactor designed to operate at a rated core thermal power of 3293 MWt with a gross electrical output of approximately 1118 MWe and a net output of I

approximately 1067 MWe. The liCGS achieved initial criticality on June 28,1986 and went into commercial operation on December 20,1986.

This report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Specification 6.9.1.7 of the liope Creek Technical Specifications. Our responses to parts A-F of the "SupplementalInformation" section of Regulatory Guide 1.21, Appendix B, are included in the following pages.

As required by Regulatory Guide 1.21, the Ilope Creek Technical Specification I

limits are described in detail within this report along with a summary description of how total radioactivity measurements and their approximations were developed.

To facilitate determination of compliance with 40CFR190 requirements, the following information on electrical output is provided.

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llope Creek generated 7,068,591 megawatt-hours of electrical energy (net) during the reporting period.

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I PART A PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS I

1.1 Fission and Activation Gas Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following:

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

In addition, the air dose due to noble pues released in gaseous effluents from the site to areas at and aeyond the site bounday, shall be limited to the following:

During any calendar quarter: less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, I

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

I 1.2 Iodine, Particulates, and Tritium The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following:

For Iodine-131, lodine-133, Tritium, and for all radionuclides in Particulate form with half-lives greater than 8 days: Ixss than or equal to 1500 mrems/yr to any organ.

In addition, the dose to a member of the public from lodine-131, Iodine-133, I

Tritium, and all radionuclides in Particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the site boundary, shall be limited to the following:

I During any calendar quarter: Less than or equal tc 7.5 mrems to any organ and, I

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

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I 1.3 Liquid Effluents Release Limits The concentration of radioactive material released in liquid ef0uents to unrestricted areas shall be limited to the concentrations specified in 10CFR20, Appendix B Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 microcuries per milliliter.

In addition, the dose or dose commitment to a member of the public from radioactive materials in liquid ef0uents released to unrestricted areas shall be limited to:

During any calendar quarter: Less than or equal to 1.5 mrems to the total body, and less than or equal to 5 mrems to any organ, and During any calendar year: Irss than or equal to 3 mrems to the total body, and less than or equal to 10 mrems to any organ.

1.4 Total Dose Limit The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).

2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)

I Regulatory Guide 1.21 requires that the licensee provide the MPCs used in determining allowable release rates or concentrations for radioactive releases.

I a) MPC values were not used for gaseous releases in the gases, determination of maximum release rates for fission Iodines, or Pa@ulates.

b) MPC values as stated in 10CFR20, Appendix B, Table II, Column 2 are used for liquid effluents in accordance with current Technical Specifications.

l c) The MPC value used for dissolved or entrained noble gases is 2E-04 microcuries per milliliter.

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I 3.0 AVERAGE ENERGY Regulatory Guide 1.21 requires that the licensee provide the average energy of the radionuclide mixture in releases of fission and activation gases, if applicable.

Release limits for IICGS are not based upon average energy. Therefore this section is not applicable to HCGS.

I 4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4.1 Liquid Effluents Liquid effluents are monitored in accordance with Table 4.11.1.1.1-1 of the Technical Specifications. During the period of record, all batch liquid wastes were I

routed to the sampling tanks for monitoring prior to release. Technical Specifications require these tanks to be uniformly mixed for sampling and analysis before being released. Batch releases are defined as releases from the equipment drain sample tanks, I

floor drain sample tanks, detergent drain tanks, and the condensate storage tank dike.

Normally, there are no continuous liquid releases. Specific activities from analyses were multiplied by the volume of effluent discharged to the environment in order to determine the total liquid activity discharged.

The detection requirements of Table 4.11.1.1-1 of the Technical Specifications are achieved or exceeded. Radionuclides measured at concentrations below the Technical Specification detection limit (LLDs) are treated as being present.

Radionuclides for which no activity was detected while meeting the required LLDs are I

treated as absent.

4.2 Gaseous Effluents Gaseous effluent streams are monitored and sampled in accordance with Table I

4.11.2.1.2-1 of the Technical Specifications. The North Plant Vent (NPV) and South Plant Vent (SPV) are the final release points for most planned gaseous effluent releases. A small quantity of gaseous effluent will be released via the Filtration, Recirculation, and Ventilation System (FRVS) vent during testing periods. The NPV and SPV are continuously monitored for lodine, Particulates and noble gases; the FRVS is continuousiv monitored for noble cases. The NPV and SPV monitors have

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moving Particulate and fixed charcoal filters; the FRVS monitor has fixed Particulate and charcoal filters. The filters and charcoal are changed weekly for NPV and SPV, and monthly for the FRVS. These are analyzed on a multichannel analyzer. The NPV I

and SPV are sampled weekly for noble gases and Tritium.

The detection requirements of Tables 4.11.2.1.2-1 of the Technical I

Specifications are achieved or exceeded. Radionuclides detected at concentrations below the Technical Specification detection limit (LLDs) are treated as being present.

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I Radionuclides for which no activity was detected while meeting the required LLDs are treated as absent.

Continuous Mode gaseous releases are quantified by routine (weekly) sampling and isotopic analyses of the plant vents. If noble gases are detected during the routine sampling, the measured concentrations are adjusted using the radiation monitoring readings to obtain an average concentration for the period. This average concentration is then multiplied by the total vent flow value for tne entire sampling period in order to estimate the normal continuous release of radioactivity through the plant vent.

When monthly vent grab samples yield no cletectable activity, continuous mode releases are quantified by integrating Radiation Monitor System readings and a 95%

I Critical Level Test applied. Noble gas isotopic abundances for these integrations are based on the ANSI N237-1976/ANS-18.1 mix for BWRs. Doses calculated from this data employ the methods from Section 2.0 and Appendix C of the Hope Creek ODCM.

Batch Mode gaseous releases (primary containment purge) are quantified by pre-I release sampling and isotopic analysis. Specific activitiet for each isotope are multiplied by the total purge flow volume for that batch in order to estimate the batch release of radioactivity through the plant vent.

I Elevated plant vent radiation monitoring system readings while the channel is m an alarm state are treated as batch mode releases. If specific activity data from grab samples taken is not available, then the abnormal release is quantified by the use of the plant vent radiation monitors. The monitor's response is converted to a " specific activity" using historical efficiency factors. The " specific activity" is multiplied by the I

volume of effluent discharged while the channel was in an alarm state in order to estimate the total activity discharged.

4.3 Estimated Total Error The estimated total error of reported liquid and solid releases is within 25%.

The estimated total error of the reported continuous gaseous releases is within 50% when concentrations exceed detectable levels. This error is due primarily to variability of waste stream flow rates and changes in isotopic distributions of waste streams between sampling periods. The estimated total error of the reported batch gaseous releases is within 10%.

Error estimates for releases where sample activity is below the detectable I

concentration levels are not included since error estimates at the LLD are not defined.

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I 5.0 BATCII RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A and 4B.

6.0 UNPLANNED RELEASES During this reporting period there were no unplanned releases.

7.0 ELEVATED RADIATION MONITOR RESPONSES During this reporting period, there were no elevated radiation monitor readings.

8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS There were no modifications to previous Radioactive Effluent Release Reports during this reporting period.

I PARTH GASEOUS EFFLUENTS See Summary Tables I A through IC.

PART C LIQUID EFFLUENTS See Summary Tables 2A through 28.

PART D SOLID WASTE See Summary in Table 3.

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PART E RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on the controlling dose pathways and age groups as described below. The estimated dose represents the maximum radiation dose that could be received by a member of the general public. The population dose impact is based on historical site specific data i.e., food, food production, milk production, feed for milk animals and seafood production.

The doses were calculated using methods described in Regulatory Guide 1.109 and represent calculations for the 12 month reporting interval. Individual doses from I

batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as described in the Offsite Dose Calculation Manual. Population doses were calculated using the meteorological dispersion i

coefficients for the twelve month reporting interval.

I iquid Pathways I

Tyne Ace Group Location Pathway Total Body Adult Site Boundary Seafood Ingestion Organ Adult Site Boundary Seafood Ingestion T

Dose Limit m

I Total Body 0.119 mrem 3 mrem Organ Dose (Liver) 0.361 mrem 10 mrem Population (Total) 1.03 person-rem N/A I

Population (Average) 2.29E-04 mrem N/A I

Air Pathways I

T Ace Group location Pathway m

Total Body All Site Boundary Direct Exposure Skin All Site Boundary Direct Exposure Organ Infant 4.9 mi. W Milk, Ground Plane, Inhalation I

Tyg Dose Limit Total Body 1.59E-02 mrem 500 mrem /yr I

Skin Dose 3.47E-02 mrem 3000 mrem /yr Organ Dose (Thyroid) 5.52E-03 mrem 15 mrem Population (Total) 0 206 person-rern N/A I

Population (Average) 4.57E-05 mrem N/A I

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I Direct Radiation Direct radiation may be estimated by Thermoluminescent dosimetric (TLD) measurements. One method for comparing TLD measurements is by comparison with pre-operational data. It should be noted that the TLDs measure direct radiation from both the Salem and flope Creek Generating Stations at Artificial Island, and natural background radiation.

i TLD data for the twelve month reporting period is given below:

TLD Location Measurement I

2S-2 0.4 mi. NNE 4.1 mrad / month SS-1 1.0 mi. E 3.4 mrad / month I

These values are interpreted to represent natural background, since the values I

are within the statistical variation associated with the pre-operational program results, which are 3.7 mrad / month for location 2S-2, and 4.2 mrad / month for location SS-1.

Total Dose 40CFR190 limits the total dose to members of the public due to radioactivity and radiation from uranium fuel cycle sources to:

< 25 mrem total body or any organ, and

< 75 mrem thyroid for a calendar year.

For Artificial Island, the major sources of dose are from liquid and gaseous effluents from the llope Creek and Salem plants The following doses to a " hypothetical maximum exposed individual" have been I

calculated for the twelve month reporting period. They are the sum of gaseous and liquid pathway doses for the Salem 1 and 2 and flope Creek plants:

l 0.293 mrem total body 0.525 mrem organ (Liver) 0.026 mrem thyroid I

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I Dose to members of the public due to activities inside the site boundary.

g In accordance with the requirements of Technical Specification 6.9.1.7, the dose to members of the public inside the site boundary has been calculated based on the following assumptions:

2 a) The most limiting member of the general public are the commercial food vendors.

b) Food vendors spend 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months per week on site.

c) The highest total body dcse contributor is direct radiation received from Salem and IIope Creek operation, I

d) Occupancy coincides with gaseous effluent discharges.

e) The food vendors are located near the restricted area boundary.

I For the 12 month reporting period, January 1 1996 to December 31,1996 the calculated doses are:

I 3.60 mrem Total Body 5.42E-02 mrem Organ (Lung) 2.50E-02 mrem Thyroid Assessment I

1. Gaseous:

Gaseous efHuents released from llope Creek resulted in a minimal dose to the maximum hypothetical individual. The dose for the 12 month period was a small fraction of all applicable limits.

Gaseous effluents decreased significantly from the previous reporting period.

I This is due to the application of a 95% Critical level Test to the integrated noble gas readings. Gaseous efHuent releases continue to remain well within Federal limits and are comparable to other nuclear utilities. Fuel integrity and gaseous efnuent processing equipment continue to be maintained in order to ensure that all releases of gaseous radioactivity are As-Low-As-Reasonably-Achievable (ALARA).

In January 1997 it was self-identified that reactor building ventilation exhaust during periods when the Filtration, Recirculation and Ventilation System (FRVS) was in service had not been included in the permitting process since 1994. The FRVS I

system is placed in service for approximately 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months on a monthly basis for surveillance testing. During periods of operation the reactor building exhaust is diverted I

from the South Plant Vent (nominally 400,000 scfm) and discharged from a separate conduit at approximately 700 scfm. Samples were collected during the periods of I

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I operation but the results were not included into the effluent database. Permitting of this pathway during periods of system operation began in 1997.

It was determined that retrofitting of the permits for previous years was not necessary based on a conservative estimation of the additional dose increment via all pathways. This determination was based on the Reg. Guide 1.109 definition of a l

significant pathway as one in which "a conservative evaluation yields an additional dose increment equal to or more than 10 percent of the total from all pathways considered in this guide."

2. Liquids:

Liquid effluents released from Ilope Creek station resulted in a minimal dose to the maximum hypothetical individual and were well within all applicable limits.

The amount of radioactivity in liquid effluents decreased from previous reporting periods due to the repair of equipment associated with the liquid radwaste I

processing system. The equipment problems were identified and repaired during the 4th quarter of 1995.

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3. Trends:

The following two trend graphs show the total curies of gaseous and liquid I

effluents released for Hope Creek from 1990 through 1996. Calculated doses in the graphs are to the maximum hypothetical individual.

I Hope Creek Gascous Effluents Curies of Noble Gases Released and Calculated Doses Note : Calculated doses are to the maximum hypothetical mdividual I

1.00E+01 900 l

800 1.00E+00 700 I

600 1.00E-01 500.y 400 6

=

300 1

1.00E-02 200 100 #E I

1.00E-03 0

1990 1991 1992 1993 1994 1995 1996

+ Organ l l -+- Curies j L

Year I

Hope Creek Liquid Effluents Curies Released and Calculated Doses Note : Calculated doses are to the maximum hypothetical individual 1.60 1.5 1.40 d 3,3 1.20 3,3 1.00 I

g 2 0.80

'c f

0.60 i 0.70 0.5 0.40 0.3 0.20 5

-i. --

)

0.1 l-s-TB 0.00 l

1990 1991 1992 1993 1994 1995 1996 l -*- Organ Year l -+- Curies I

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PART F METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for 1996 in Appendix A at the end of this report.

PART G OFFSITE DOSE CALCULATION MANUAL (ODCM) CIIANGES l

During this period, there was a revision to the IICGS Offsite Dose Calculation Manual (ODCM). The revision included the incorporation of the MPC values formerly contained in 10CFR20 and updating of the default effluent monitor setpoints based on the most recent release data. The changes to the ODCM by this revision did not affect I

the dose calculation methodologies. The revised ODCM is provided in Appendix B at the end of this report I

PART II INOPERABLE MONITORS I

During this period the following effluent monitor was inoperable for greater than 30 days.

South Plant Vent Flow Rate Monitor - The South Plant Vent (SPV)IIigh Range Noble Gas Monitor was inoperable for a period of 38 days 9/16/96 to 10/23/96.

The cause of the monitor inoperability was repeated drifting in the flow instrumentation due to defective pneutuatic amplifiers in the square root extractors. The pneumatic instrumentation was replaced with electronic instrumentation to prevent recurrence of this problem.

PART I PROCESS CONTROL PROGRAM (PCP) CIIANGES During the reporting period, there were no changes to the process control program.

PART J ENVIRONMENTAL MONITORING LOCATION CIIANGES During the reporting period, there were minor changes made to the environmental monitoring sampling program. A complete list of the changes is contained in the ODCM revision that is included with this document. The changes made to the environmental monitoring program did not reduce the objectives of the Radiological Environmental Monitoring Program (REMP).

PART K MAJOR CIIANGES TO RADIOACTIVE WASTE SYSTEMS During the reporting period, there were no major changes to the Radioactive I

Waste Processing systems.

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IIOPE CREEK GENERATING STATION TABLE 1A I

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES I

Est.

Units 1" Quarter 2*' Quarter Total Error' A.

Fission and Ac*.ivation Products I

1.

Total Release Ci 2.87E +00 9.22E +00 25 %

2.

Average Release Rate I

For Period pCi/sec 3.65E-01 1.17E +00 3.

Percent of Technical l

Specification Limit (T.S. 3.I1.2.2(a))

3.92E-02 1.26E-01 i

B.

Iodines 1.

Total Iodine-131 Ci 0.00E +00 1.02E-04 25 %

2.

Average Release Rate For Period pCi/sec 0.00E+00 1.29E-05 3.

Percent of Technical Specification Limit:

(T.S. 3.I1.2.3(a))

6.02E-03 1.93E-02 I

l 1

C.

Particulates I

1.

Particulates With IIalf-lives >8 days Ci 3.44E-03 4.59E-05 25 %

2.

Average Release Rate I

For Period pCi/sec 4.38E-04 5.83E-06 3.

Percent of Technical 2

Specification Limit (T.S. 3.I1.2.3(a))

6.02E-03 1.93E-02 4.

Gross Alpha Ci 0.00E + 00 0.00E +00 D.

Tritiurn 1.

Total Release Ci 4.40E +00 1.77E +00 25 %

2.

Average Release Rate For Period pCi/sec 5.59E-01 2.25E-01 3.

Percent of Technical 2

Specification Limit (T.S. 3.11.2.3(a))

6.02E-03 1.93E-02

1. For batch releases, the estimated overall error is within 10%.

2. lodine, ?ritium, and Particulates are treated as a group.

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IIOPI ltEEK GENERATING STATION TABLElA I

EFFLUENTS AND WASTE DISPOSAI ANNUAL REPORT

.lANUARY - DECEMBER 1996 OASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Est.

Units 3'd Quarter 4* Quarter Total Error' A.

Fission and Activation Products I

1.

Total Release Ci 7.81 E +00 6.05E +00 25 %

2.

Average Release Rate For Period pCi/sec 9.83E-01 7.62E-01 3.

Percent of Technical Specification Limit (T.S. 3. ll.2.2(a))

8.51 E-02 8.26E-02 IL lodines 1.

Total lodine-131 Ci 2.19E-04 7.71 E-05 25 %

2.

Average Release Rate For Period pCi/sec 2.76E-05 9.70E-06 3.

Percent of Technical l

2 Specification Limit (T.S. 3.11.2.3(a))

2.73E-03 1.49E-02 C.

Particulates I

1.

Particulates With Half-lives >8 days Ci 1.61 E-04 9.83E-05 25 %

2.

Average Release Rate I

For Period pCi/sec 2.02E-05 1.24E-05 3.

Percent of Technical 2

Specification Limit (T.S. 3.I1.2.3(a))

2.73E-03 1.49E-02 4.

Gross Alpha Ci 0.00E + 00 0.00E+00 D.

Tritium 1.

Total Release Ci 6.50E+00 6.30E+00 25 %

2.

Average Release Rate For Period Ci/sec 8.17E-01 7.93E-01 3.

Percent of Technical 2

I Specification Limit (T.S. 3.I1.2.3(a))

2.73E-03 1.49E-02

1. For batch releases, the estimated overall error is within 10%.

2 lodine, Tritium, and Particulates are tieated as a group.

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ig IlOPE CREEK GENERATING STATION l5 TABLEIB EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT l

JANUARY - DECEMBER 1996 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode 3

M 8

1 Ouaner 2 Ouaner 1 Ouaner 2Equaner Nuclides Units Released 1.

Fission Gases I

Krypton-83m Ci 2.83E-02 9.22E-02 0.00E +00 0.00E + 00 Krypton-85m Ci 2.83E-02 9.22E-02 0.00E +00 0.00E+00 Krypton-87 Ci 1.13E-01 3.69E-01 0.00E +00 0.00E+00 Krypton-88 Ci 1.13E-01 3.69E-01 0.00E+00 0.00E +00 Krypton-89 Ci 7.63E-01 2.49E +00 0.00E +00 0.00E +00 Xenon-133 Ci 5.65E-02 1.84E-01 0.00E+00 0.00E+00 Xenon-135 Ci 1.41E-01 4.61E-01 0.00E +00 0.00E+00 Xenon-135m Ci 1.70E-01 5.53E-01 0.00E+00 0.00E+00 Xenon-137 Ci 8.76E-01 2.86E+00 0.00E +00 0.00E +00 Xenon-138 Ci 5.37E-01 1.75E +00 0.00E +00 0.00E+00 Argon-41 Ci 0.00E+00 0.00E+00 4.15E-02 0.00E +00 Totals Ci 2.83E + 00 9.22E+00 4.15E-02 0.00E+00 2.

lodines Iodine-131 Ci 0.00E +00 1.02E-04 0.00E+00 0.00E+00 Iodine-133 Ci 0.00E+00 5.18E-03 0.00E +00 0.00E+00 I

Totals Ci 0.00E+00 5.28E-03 0.00E+00 0.00E +00 I

3.

Particulates (llalf-life >8 days)

Manganese-54 Ci 1.16E-03 4.58E-05 6.73E-06 0.00E +00 Iron-59 Ci 9.73E-05 0.00E+00 0.00E + 00 0.00E+00 Cobalt-60 Ci 8.47E-04 0.00E +00 0.00E+00 0.00E +00 Zinc-65 Ci 1.33E-03 0.00E + 00 0.00E + 00 0.00E +00 Totals Ci 3.44E-03 4.58E-05 6.73E-06 0.00E+00 4.

Tritium Ci 4.40E + 00 1.77E +00 l 0.00E+00 0.00E +00 l

l lI 17 I

I I

IIOPE CREEK GENERATING STATION TABLEIB EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode I

i Nuclides Units ad ouarter 4S Ouaner ad ouarter 4* Ouarter Beleased 1.

Fission Gases I

Krypton-83m Ci 5.74E-02 6.05E-02 0.00E+00 0.00E+00 Krypton-85m Ci 5.74E-02 6.05E-02 0.00E +00 0.00E +00 Krypton-87 Ci 2.30E-01 2.42E-01 0.00E +00 0.00E +00 Krypton-88 Ci 2.30E-01 2.42E-01 0.00E +00 0.00E+00 Krypton-89 Ci 1.55E-00 1.63E +00 0.00E + 00 0.00E+00 I

Xenon-133 Ci 1.15E-01 1.21 E-01 0.00E +00 1.29E-04 Xenon-135 Ci 2.36E +00 3.03E-01 0.00E +00 0.00E+00 Xenon-135m Ci 3.44E-01 3.63E-01 0.00E +00 0.00E+00 Xenon-137 Ci 1.78E +00 1.88E +00 0.00E+00 0.00E+00 Xenon-138 Ci 1.09E +00 1.15E-00 0.00E+00 0.00E +00 Totals Ci 7.81 E +00 6.05E +00 0.00E+00 1.29E-04 2.

Iodines I

Iodine-131 Ci 2.19E-04 7.71 E-05 0.00E+00 0.00E+00 lodine-133 Ci 6.26E-03 3.76E-03 0.00E +00 0.00E +00 Totals Ci 6.48E-03 3.84E-03 0.00E +00 0.00E +00 3.

Particulates (Italf-life >8 days)

Chromium-51 Ci 1.05E-04 0.00E +00 0.00E + 00 7.92E-05 Manganese-54 Ci 5.55E-05 6.76E-07 0.00E+00 4.56E-07 Cobalt-58 Ci 0.00E+00 0.00E+00 0.00E + 00 1.13E-06 Cobalt-60 Ci 0.00E +00 0.00E+00 0.00E+00 9.59E-07 Zine-65 Ci 0.00E+00 0.00E+00 0.00E+00 1.53E-05 Silver-110m Ci 0.00E+00 0.00E+00 0.00E +00 5.98E-07 Totals Ci 1.60E-04 6.76E-07 0.00E+00 9.76E-05 4.

Tritium Ci 6.50E+ 00 6.30E +00 l 0.00E+00 1.50E-04 I

I 18

l I

IIOPE CREEK GENERATING STATION TABLEIC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996 GASEOUS EFFLUENTS - ELEVATED RELEASES l

There were no elevated gaseous releases during this reporting period, l

1 4

I lI

I I

I I

19 I

i I

I IIOPE CREEK GENERATING STATION TABLE 2A I

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES I

Est.

Units 1" Quarter 2*' Quarter Total Error A.

Fission and Activation Products I

1.

Total Release Ci 7.24E-01 6.93E-03 25 %

2.

Average Release Rate For Period pCi/sec 9.53E 07 6.llE-08 I

3.

Percent of Technical Specification Lirait (T.S. 3.I1.1.2(a))

7.55E +00 3.68E-02 B.

Tritium 1.

Total Release Ci 4.84E +00 6.93E-01 25 %

2.

Average Release Rate For Period pCi/sec 6.38E-06

6. ll E-06 3.

Percent of Technical Specification Limit (T.S. 3.11.1.1) 2.12E-01 2.04E-01 C.

Dissolved and Entrained Noble Gases I

1.

Total Release Ci 1.96E-05 9.61E-05 25 %

2.

Average Release Rate For Period Ci/sec 2.58E-11 8.47E-10 3.

Percent of Technical Specification Limit (T.S. 3. I 1.1.1) 1.29E-05 4.25E-04 D.

Gross Alpha 1.

Total Release Ci 0.00E +00 0.00E +00 25 %

E.

Volume of Waste Release I

(Prior to Dilution - Batch Release)

Liters 3.40E +06 3.28E+05 25 %

F.

Volume of Dilution Water I

Used During Entire Period Liters 1.23E + 10 1.76E + 10 25 %

I 20 I

1 I

i I

IlOPE CREEK GENERATING STATION j

TABLE 2A I

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT j

JANUARY - DECEMBER 1996 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES i

I Est.

Units 3'd Quarter 4* Quarter Total Error A.

Fission and Activation I

Products 1.

Total Release Ci 2.04 E-03 4.83E-02 25 %

2.

Average Release Rate I

For Period pCi/sec 2.28E-08 1.90E-07 3.

Percent of Technical Specification Limit (T.S. 3. l l. l.2(a))

1.02E-02 3.18E-01 l

II.

Tritium 1.

Total Release Ci 8.15 E-01 4.94E +00 25 %

2.

Average Release Rate i

For Period pCi/sec 9.10E-06 1.94E-05 3.

Percent of Technical Specification Limit (T.S. 3.11.1.1) 3.03E-01 6.47E-01 C.

Dissolved and I

Entrained Noble Gases i

1.

Total Release Ci 3.30E-05 2.04E-04 25 %

2.

Average Release Rate j

I For Period pCi/sec 3.68E-10 7.99E-10 3.

Percent of Technical Specification L.imit I

(T.S. 3.11.1.1) 1.84E-04 3.99E-04 D.

Gross Alpha 1.

Total Release Ci 0.00E +00 0.00E +00 25 %

E.

Volume of Waste Release I

(Prior to Dilution - Ilatch Release)

Liters 2.83E+05 1.29E+06 25 %

I F.

Volume of Dilution Water Used During Entire Period Liters 1.88E+ 10 1.41 E + 10 25 %

I 21 I

I I

IIOPE CREEK GENERATING STATION TABLE 2B I

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996 L.IQUID EFFI.UENTS Continuous Mode Batch Mode 3

d 3

Nuclides Released Units 1 Ouaner 2 Ouaner 1 Ouaner 2M auaner 1.

Fission and Activation I

Products Chromium-51 Ci 0.00E+00 0.00E+00 3.96E-04 1.45E-04 I

Manganese-54 Ci 0.00E+00 0.00E+00 1.10E-01 1.81E-03 fron-55 Ci 0.00E+00 0.00E+00 5.44E-01 4.27E-03 Cobalt-57 Ci 0.00E +00 0.00E+00 0.00E +00 3.01E-06 I

Cobalt-58 Ci 0.00E +00 0.00E +00 3.71E-03 6.45E-07 Iron-59 Ci 0.00E+00 0.00E+00 1.17E-02 2.84E-05 Cobalt-60 Ci 0.00E +00 0.00E +00 2.94E-02 4.89E-04 Zinc-65 Ci 0.00E +00 0.00E+00 2.41E-02 1.57E-04 Technetium-99m Ci 0.00E+00 0.00E + 00 0.00E +00 6.01 E-06 Silver.110m Ci 0.00E+00 0.00E+00 3.24E-(M 0.00E +00 Cesium-134 Ci 0.00E +00 0.00E +00 3.56E-05 1.23E-05 Cesium-137 Ci 0.00E + 00 0.00E + 00 4.43E-05 1.87E-05 Totals Ci 0.00E + 00 0.00E + 00 7.24E-01 6.93E-03 I

2.

Tritium Ci 0.00E +00 0.00E +00 l 4.84E+00 6.93E-01 3.

Dissolved and I

Entrained Noble Gases Xenon-135 Ci 0.00E +00 0.00E +00 1.96E-05 9.61E-05 Totals Ci 0.00E + 00 0.00E +00 1.96E-05 9.61 E-05 I

I I

I 22 I

I I

HOPE C3EEK GENERATING STATION TABLE 2B I

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units 3rd Ouarter 4e Ouarter 3rd Ouarter 4* Ouarter 1.

Fission and Activation I

Products Sodium-24 Ci 0.00E +00 0.00E+00 0.00E +00 1.74E-04 I

Chromium-51 Ci 0.00E +00 0.00E +00 2.26E-04 4.27E-03 Manganese-54 Ci 0.00E +00 0.00E +00 1.llE-03 6.87E-03 Iron-55 Ci 0.00E+00 0.00E +00 1.98E-04 3.21E-02 I

Cobalt-58 Ci 0.00E +00 0.00E +00 1.84E-06 3.51E-04 Iron-59 Ci 0.00E +00 0.00E+00 4.62E-06 8.06E-04 Cobalt-60 Ci 0.00E+00 0.00E+ 00 4.19E-04 2.78E-03 Zinc-65 Ci 0.00E + 00 0.00E +00 7.54E-05 9.05E-04 Technetium-99m Ci 0.00E +00 0.00E+00 0.00E+00 1.07E-05 Silver-110m Ci 0.00E+00 0.00E+00 7.32E-06 0.00E+00 Cesium-137 Ci 0.00E +00 0.00E+00 7.69E-06 9.91E-07 Totals Ci 0.00E +00 0.00E +00 2.04E-03 4.83E-02 I

2.

Tritium Ci 0.00E +00 0.00E +00 l 8.15E-01 4.94E +00 3.

Dissolved and Entrained Noble I

Gases Xenon-133 Ci 0.00E + 00 0.00E +00 0.00E + 00 3.66E-05 Xenon-135 Ci 0.00E +00 0.00E +00 3.30E-05 1.67E-04 Totals Ci 0.00E +00 0.00E +00 3.30E-05 2.04E-04 I

I I

I 23 I

I I

IIOPE CREEK GENERATING STATION TABLE 3 I

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996 SOLID WASTE AND IRRADIATED FUEL SIIIPMENTS SOLID RADWASTE SIIIPPED OFFSITE FOR BURIAL OF DISPOSAL (Not Irradiated Fuel) 12-Month Est. Total 1.

Type of Waste Units' Period Error 3

a.

Spent Resins, Filters, Studges, m

5.82E+01 25 %

Evaporator Bottoms Ci 1.91E +02 I

3 b.

Dry Compressible Waste, Contaminated m

4.04E +01 25 %

Equipment Ci 6.13E +00 l

I 3

c.

Irradiated Components, Control Rods m

0.00E +00 25 %

Ci 0.00E +00 3

d.

Others (described) m 0.00E +00 25 %

Ci 0.00E +00 l

2.

Estimate of Major Nuclide Composition RESINS DAW Nuclides Ci Ci Manganese-54 10.0 1.91E+01 5.3 3.25E-01 Iron-55 81.3 1.55E +02 91.0 5.58E +00 Cobalt-60 5.9 1.13E +01 3.2 1.96E-01 I

Zine-65 2.3 4.39E +00 0.0 0.00E +00

1. Volumes are measured, activities are estimated.

I I

I 24 I

lI l

IIOPE CREEK GENERATING STATION TABLE 3 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996 SOI,lD WASTE AND IRRADIATED FUEL SIIIPMENTS 4

3.

Solid Waste Disposal Number of Mode of Destination Type of Containers Shipments Transportation 9

Truck Barnwell, SC IIIC and 17E Drums I

11 Truck Oak Ridge, TN Strong, Tight Containers I

1 Truck Memphis, TN Strong, Tight i

Containers 4.

Irradiated Fuel Shipments (Disposition)

Number of Mode of Destination Shipments Transportation None N/A N/A I

I I

I

I l'I lI 25 I

I I

IlOFE CREEK GENERATING STATION TABLE 4A l

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996

SUMMARY

SIIEET FOR RADIOACTIVE EFFLUENTS RELEASED

,l IN A BATCil MODE BATCII RELEASES ONLY

1. Dates:

January 1 - March 31,1996 i

2. Type of release:

Gas

3. Number of releases during the 1st Qtr:

2

I

4. Total time duration for all releases of type listed above:

2030 min.

'l

5. Maximum duration for release of type listed above 1615 min.

6. Average duration for release of type listed above:

1015 min.

I

7. Minimum duration for release of type listed above:

415 min.

8. Average stream flow (dilution flow) durir.g the period of release:

N/A

!I

'I I

I I

26 I

E IIOPE CREEK GENERATING STATION TABLE 4A l

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996 l

SUMMARY

SilEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCII MODE

'I BATCII RELEASES ONLY

1. Dates:

April 1 - June 30,1996

2. Type of release:

Gas

3. Number of releases during the 2nd Qtr:

0 I

4. Total time duration for all releases of type listed above:

0 min.

5. Maximum duration for release of type listed above:

0 min.

6. Average duration for release of type listed above:

0 min.

I

7. Minimum duration for release of type listed above:

0 min.

8. Average stream flow (dilution flow) during the period of release:

N/A I

I I

I iI 2'

I

1 I

I IIOPE CREEK GENERATING STATION TABLE 4A I

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996

SUMMARY

SIIEET FOR RADIOACTIVE EFFL.UENTS RELEASED l

IN A BATCII MODE I

BATCil RELEASES ONLY

1. Dates:

July 1 - September 30,1996

2. Type of release:

Gas

3. Number of releases during the 3rd Qtr:

0

4. Total time duration for all releases of type listed above:

0 min.

5. Maximum duration for release of type listed above:

0 min.

I

6. Average duration for release of type listed above:

0 min.

I

7. Minimum duration for release of type listed above:

0 min.

8. Average stream flow (dilution flow) during the period of release:

N/A I

I I

I E

28 E

I

^I IlOPE CREEK GENERATING STATION TABLE 4A I

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996

SUMMARY

SIIEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCII MODE I

BATCII RELEASES ONLY

1. Dates:

October 1 - December 31,1996

2. Type of release:

Gas

3. Number of releases during the 4th Qtr:

2

4. Total time duration for all releases of type listed above:

1326 min.

5. Maximum duration for release of type listed above:

996 min.

6. Average duration for release of type listed above:

663 min.

I

7. Minimum duration for release of type listed above:

330 min.

8. Average stream flow (dilution flow) during the period of release:

N/A I

I I

29 I

.-a 4

I I

IIOPE CREEK GENERATING STATION TAPLE4B B

EFFLUENT AND WASTE LISpnSAL ANNUAL REPORT JANUARY - DECEMBER 1996

SUMMARY

SIIEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCil MODE I

BATCII RELEASES ONLY

1. Dates:

January 1 - March 31,1996

2. Type of release:

Liquid

3. Number of releases during the 1st Qtr:

109

4. Total time duration for all releases of type listed above:

7787.3 min.

5. Maximum duration for release of type listed above:

125.0 min.

6. Average duration for release of type listed above:

71.4 min.

I

7. Minimum duration for release of type listed above:

21.0 min.

8. Average stream flow (dilution flow) during the period of release:

25761 gpm I

I I

30 I

1 1

lI IIOPE CREEK GENERATING STATION TABLE 4B l

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l

l JANUARY - DECEMBER 1996

SUMMARY

SIIEET FOR RADIOACTIVE EFFLUENTS RELEASED

,l IN A BATCll MODE l

I BATCll RELEASES ONLY j

1. Dates:

April 1 - June 30,1996

2. Type of release:

Liquid

3. Number of releases during the 2nd Qtr:

16

4. Total time duration for all releases of type listed above:

909.9 min.

5. Maximum duration for release of type listed above:

98.2 min.

6. Average duration for release of type listed above:

56.9 min.

I

7. Minimum duration for release of type listed above:

1.0 min.

8. Average stream flow (dilution flow) during the period of release:

32929 gpm I

I I

I lI lI

,I 31 I

I I

IlOPE CREEK GENERATING STATION TABLE 4B I

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996

SUMMARY

SIIEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCII MODE I

BATCII RELEASES ONLY

1. Dates:

July 1 - September 30,1996

2. Type of release:

Liquid

3. Number of releases during the 3rd Qtr:

12

4. Total time duration for all releases of type listed above:

741.9 min.

5. Maximum duration for release of type listed above:

90.1 min.

6. Average duration for release of type listed above:

61.8 min.

I

7. Minimum duration for release of type listed above:

37.0 mm.

8. Average stream now (dilution flow) during the period of release:

31922 gpm I

I I

I 32 I

l i

g IIOPE CREEK GENERATING STATION m

TABLE 4B 1

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1996

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED

'l IN A BATCII MODE I

BATCII RELEASES ONLY

1. Dates:

October 1 - December 31,1996

2. Type of release:

Liquid

3. Number of releases during the 4th Qtr:

34

4. Total time duration for all releases of type listed above:

2544.0 min.

5. Maximum duration for release of type listed above:

99.2 min.

6. Average duration for release of type listed above:

74.8 min.

I

7. Minimum duration for release of type listed above:

26.0 min.

8. Average stream flow (dilution Dow) during the period of release:

26430 gpm I

I I

I lI lll I

33 l

I

!I i

I APPENDIX A i

I 1996 METEOROLOGICAL DATA lI

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i I

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i ARTIFICIAL ISLAND 1/96 - 3/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITT CLASS WIND: 300 FT LAPSE RATE: -0.4 To 1.5 DEG C/100M DELTA T: (300-33FT)

CLASS E ulND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6

$UM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT t

N O

0.0 5

0.2 12 0.6 7

0.3 15 0.7 22 1.0 3

0.1 64 3.0 l

HEE O

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0.4 7

0.3 1

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0.0 2

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0.0 2

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0.3 0

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0.1 0

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0.3 ESE O

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0.1 3

0.1 4

0.2 1

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0.1 12 0.6 9

0.4 30 1.4 l

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0.0 2

0.1 6

0.3 7

0.3 8

0.4 2

0.1 5

0.2 30 1.4 5

0 0.0 3

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0.0 2

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[

SW 0

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0.3 7

0.3 9

0.4 7

0.3 7

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0.3 42 2.0 wSu 0

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0.1 4

0.2 8

0.4 7

0.3 4

0.2 0

0.0 25 1.2 W

0 0.0 3

0.1 4

0.2 7

0.3 22 1.0 10 0.5 5

0.2 51 2.4 l

WNW 0

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0 0.0 2

0.1 5

0.2 22 1.0 48 2.3 19 0.9 5

0.2 101 4.8 kNW 0

0.0 3

0.1 9

0.4 15 0.7 17 0.8 8

0.4 11 0.5 63 3.0 0

0.0 39 1.8 82 3.9 166 7.8 248 11.7 124 5.9 62 2.9 721 34.0 MEAN WIND SPEED:

14.4 j

MISSING:

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M ARTIFICIAL ISLAND 1/96 - 3/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMCSPHERIC STABILITY CLASS u!ND: 300 FT DELTA T: (300-33FT)

ALL STABILITY CLASSES WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 CE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

0 0.0 5

0.2 18 0.8 28 1.3 48 2.3 49 2.3 17 0.8 165 7.8 NNE O

0.0 1

0.0 16 0.8 49 2.3 34 1.6 27 1.3 13 0.6 140 6.6 NE O

0.0 7

0.3 16 0.8 45 2.1 51 2.4 23 1.1 15 0.7 157 7.4 ENE O

0.0 3

0.1 8

0.4 23 1.1 14 0.7 4

0.2 7

0.3 59 2.8 E

O 0.0 6

0.3 12 0.6 12 0.6 0

0.0 0

0.0 2

0.1 32 1.5 ESE O

0.0 0

0.0 4

0.2 6

0.3 7

0.3 1

0.0 0

0.0 18 0.8 SE O

0.0 5

0.2 10 0.5 15 0.7 11 0.5 22 1.0 43 2.0 106 5.0 SSE O

0.0 4

0.2 17 0.8 33 1.6 33 1.6 28 1.3 44 2.1 159 7.5 S

0 0.0 7

0.3 12 0.6 35 1.7 59 2.8 18 0.8 13 0.6 144 6.8 SSW 0

0.0 3

0.1 25 1.2 35 1.7 41 1.9 19 0.9 12 0.6 135 6.4 Su 0

0.0 8

0.4 21 1.0 27 1.3 25 1.2 17 0.8 8

0.4 106 5.0 usu 0

0.0 3

0,1 16 0.8 23 1.1 30 1.4 12 0.6 0

0.0 84 4.0 W

0 0.0 7

0.3 15 0.7 22 1.0 51 2.4 20 0.9 6

0.3 121 5.7 WNW 0

0.0 2

0.1 10 0.5 25 1.2 89 4.2 53 2.5 40 1.9 219 10.3 NW 0

0.0 2

0.1 16 0.8 36 1.7 125 5.9 110 5.2 31 1.5 320 15.1 NNW 0

0.0 5

0.2 15 0.7 47 2.2 44 2.1 21 1.0 22 1.0 154 7.3 0

0.0 68 3.2 231 10.9 461 21.8 662 31.2 424 20.0 273 12.9 2119 100.0 MISSING HOURS:

65 FEAN WIND SPEED:

16.0

m M

M M

M ART!FICIAL ISLAND 1/96 - 3/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT DELTA T: (300-33FT)

DIRECTION VS SPEED ONLY WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 CE 24.6 SUM PERCENT i

DIRECTION SUM PERCENT SUM PEPCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

O 0.0 5

0.2 19 0.9 32 1.5 50 2.3 49 2.2 17 0.8 172 7.9 NNE O

0.0 1

0.0 17 0.8 50 2.3 34 1.6 27 1.2 13 0.6 142 6.5 NE O

0.0 7

0.3 17 0.8 46 2.1 51 2.3 23 1.1 15 0.7 159 7.3 ENE O

0.0 3

0.1 8

0.4 23 1.1 14 0.6 4

0.2 7

0.3 59 2.7 E

O 0.0 6

0.3 12 0.5 12 0.5 0

0.0 0

0.0 2

0.1 32 1.5 ESE O

0.0 0

0.0 4

0.2 6

0.3 7

0.3 1

0.0 0

0.0 18 0.8 SE O

0.0 5

0.2 10 0.5 15 0.7 12 0.5 22 1.0 43 2.0 107 4.9 SSE O

0.0 4

0.2 17 0.8 34 1.6 33 1.5 28 1.3 44 2.0 160 7.3 5

0 0.0 7

0.3 12 0.5 36 1.6 59 2.7 18 0.8 13 0.6 145 6.6 Ssw 0

0.0 3

0.1 26 1.2 35 1.6 41 1.9 19 0.9 13 0.6 137 6.3 SW D

0.0 8

0.4 22 1.0 27 1.2 25 1.1 17 0.8 8

0.4 107 4.9 WSW 0

0.0 3

0.1 17 0.8 26 1.2 30 1.4 12 0.5 0

0.0 88 4.0 i

W 0

0.0 9

0.4 17 0.8 25 1.1 52 2.4 21 1.0 6

0.3 130 6.0 WNW 0

0.0 2

0.1 12 0.5 31 1.4 96 4.4 55 2.5 40 1.8 236 10.8 NW 0

0.0 2

0.1 16 0.7 38 1.7 132 6.0 113 5.2 32 1.5 333 15.2 NNW 0

0.0 5

0.2 15 0.7 50 2.3 46 2.1 21 1.0 22 1.0 159 7.3 0

0.0 70 3.2 241 11.0 486 22.3 682 31.2 430 19.7 275 12.6 2184 100.0 1

MISSING HOURS:

0 NEAN WIND SPEED:

15.9

~ ~. -

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M M

M ARTIFICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION OF W!kD DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS I

WIND: 300 FT LAPSE RATE: -1.4 TO -0.5 DEG C/100M DELTA T: (300-33FT)

CLASS D WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT 1

N O

0.0 0

0.0 3

0.2 16 0.8 5

0.3 3

0.2 0

0.0 27 1.4 NNE O

0.0 1

0.1 5

0.3 19 1.0 17 0.9 2

0.1 0

0.0 44 2.3 NE O

0.0 1

0.1 8

0.4 14 0.7 12 0.6 2

0.1 1

0.1 38 2.0 ENE O

0.0 0

0.0 7

0.4 40 2.1 8

0.4 1

0.1 0

0.0 56 2.9 E

O 0.0 3

0.2 6

0.3 29 1.5 6

0.3 1

0.1 0

0.0 45 2.4 ESF 0

0.0 1

0.1 1

0.1 10 0.5 20 1.0 3

0.2 1

0.1 36 1.9 SE O

0.0 0

0.0 6

0.3 20 1.0 28 1.5 29 1.5 12 0.6 95 5.0 SSE O

0.0 1

0.1 16 0.8 29 1.5 40 2.1 22 1.2 2

0.1 110 5.8 5

0 0.0 0

0.0 9

0.5 17 0.9 7

0.4 5

0.3 0

0.0 38 2.0 SSW 0

0.0 0

0.0 5

0.3 12 0.6 13 0.7 17 0.9 11 0.6 58 3.0 SW 0

0.0 0

0.0 2

0.1 5

0.3 16 0.8 3

0.2 0

0.0 26 1.4 WSW 0

0.0 0

0.0 3

0.2 9

0.5 9

0.5 4

0.2 0

0.0 25 1.3 i

W 0

0.0 2

0.1 2

0.1 9

0.5 8

0.4 5

0.3 1

0.1 27 1.4 UNW 0

0.0 0

0.0 7

0.4 3

0.2 4

0.2 13 0.7 10 0.5 37 1.9 NW 0

0.0 0

0.0 2

0.1 4

0.2 12 0.6 4

0.2 15 0.8 37 1.9 NNW 0

0.0 0

0.0 1

0.1 5

0.3 7

0.4 8

0.4 1

0.1 22 1.2 0

0.0 9

0.5 83 4.3 241 12.6 212 11.1 122 6.4 54 2.8 721 37.7

+

MEAN WIND SPEED:

14.1 MISSING:

1

...... ~.. -...

-.. - ~_

m m

m i

ARTIFICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT LAPSE RATE: -0.4 TO 1.5 DEG C/100M DELTA T: (300-33FT)

CLASS E WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 CE 24.6 SUN PERCENT DIRECTION SUM FERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM FERCENT SUM PERCENT SUM PERCENT N

O 0.0 0

0.0 5

0.3 5

0.3 17 0.9 6

0.3 7

0.4 40 2.1 NNE O

0.0 1

0.1 2

0.1 3

0.2 26 1.4 6

0.3 1

0.1 39 2.0 NE O

0.0 0

0.0 5

0.3 4

0.2 8

0.4 1

0.1 4

0.2 22 1.2 ENE O

0.0 0

0.0 2

0.1 8

0.4 2

0.1 3

0.2 0

0.0 15 0.8 E

O 0.0 0

0.0 1

0.1 5

0.3 2

0.1 0

0.0 0

0.0 8

0.4 4

ESE O

0.0 1

0.1 3

0.2 4

0.2 6

0.3 2

0.1 1

0.1 17 0.9 SE O

0.0 0

0.0 3

0.2 11 0.6 16 0.8 5

0.3 12 0.6 47 2.5 SSE O

0.0 0

0.0 2

0.1 9

0.5 37 1.9 17 0.9 5

0.3 70 3.7 s

0 0.0 0

0.0 1

0.1 9

0.5 8

0.4 8

0.4 11 0.6 37 1.9 SSW 0

0.0 1

0.1 2

0.1 3

0.2 10 0.5 14 0.7 16 0.8 46 2.4 Sw D

0.0 2

0.1 4

0.2 4

0.2 29 1.5 9

0.5 3

0.2 51 2.7 wSW 0

0.0 0

0.0 1

0.1 7

0.4 23 1.2 6

0.3 1

0.1 38 2.0 W

0 0.0 2

0.1 0

0.0 16 0.8 8

0.4 3

0.2 1

0.1 30 1.6 wNu 0

0.0 1

0.1 1

0.1 10 0.5 21 1.1 13 0.7 1

0.1 47 2.5 Nw 0

0.0 0

0.0 6

0.3 18 0.9 14 0.7 12 0.6 4

0.2 54 2.8 NNw 0

0.0 2

0.1 1

0.1 6

0.3 10 0.5 9

0.5 4

0.2 32 1.7 0

0.0 10 0.5 39 2.0 122 6.4 237 12.4 114 6.0 71 3.7 593 31.0 l

MEAN WIND SPEED:

16.2 MISSING:

1 i

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M ARTIFICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT DELTA T: (300-33FT)

ALL STABILITY CLASSES WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5

3. 6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 CE 24.6 SUM PERCENT DIRECTt0N SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PE3 CENT N

0 0.0 0

0.0 12 0.6 36 1.9 32 1.7 21 1.1 8

0.4 109 5.7 WE O

0.0 2

0.1 11 0.6 31 1.6 55 2.9 8

0.4 1

0.1 108 5.7 NE O

0.0 1

0.1 15 0.8 25 1.3 24 1.3 5

0.3 5

0.3 75 3.9 ENE O

0.0 0

0.0 11 0.6 55 2.9 11 0.6 4

0.2 0

0.0 81 4.2 E

O 0.0 3

0.2 to 0.5 38 2.0 9

0.5 1

0.1 0

0.0 61 3.2 ESE O

0.0 2

0.1 9

0.5 15 0.8 26 1.4 6

0.3 2

0.1 60 3.1 SE O

0.0 1

0.1 17 0.9 43 2.3 52 2.7 41 2.1 34 1.8 188 9.8 SSE O

0.0 1

0.1 25 1.3 51 2.7 94 4.9 47 2.5 13 0.7 231 12.1 S

0 0.0 0

0.0 13 0.7 43 2.3 30 1.6 21 1.1 15 0.8 122 6.4 SSw 0

0.0 1

0.1 14 0.7 21 1.1 29 1.5 52 2.7 38 2.0 155 8.1 SW 0

0.0 2

0.1 11 0.6 13 0.7 62 3.2 25 1.3 8

0.4 121 6.3 WSu O

0.0 0

0.0 0.6 37 1.9 47 2.5 19 1.0 1

0.1 115 6.0 w

0 0.0 6

0.3 0.2 35 1.8 22 1.2 13 0.7 2

0.1 81 4.2 WNW 0

0.0 1

0.1 14 0.7 22 1.2 29 1.5 38 2.0 14 0.7 118 6.2 NW 0

0.0 0

0.0 12 0.6 35 1.8 55 2.9 31 1.6 28 1.5 161 8.4 NNw 0

0.0 2

0.1 12 0.6 33 1.7 40 2.1 28 1.5 to 0.5 125 6.5 0

0.0 22 1.2 200 10.5 533 27.9 617 32.3 360 18.8 179 9.4 1911 100.0 MISSING HOURS:

2 73 MEAN WIND SPEED:

15.0

m M

M M

ARi!FICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT DELTA T: (300-33FT)

DIRECTION VS SPEED ONLY WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

O 0.0 0

0.0 13 0.6 36 1.8 32 1.6 21 1.0 8

0.4 110 5.4 NNE O

0.0 2

0.1 13 0.6 31 1.5 55 2.7 8

0.4 1

0.0 110 5.4 kE O

0.0 1

0.0 15 0.7 26 1.3 24 1.2 5

0.2 5

0.2 76 3.7 ENE O

0.0 0

0.0 12 0.6 56 2.7 12 0.6 4

0.2 0

0.0 84 4.1 E

O 0.0 3

0.1 10 0.5 42 2.0 10 0.5 1

0.0 0

0.0 66 3.2 ESF 0

0.0 2

0.1 10 0.5 15 0.7 27 1.3 6

0.3 2

0.1 62 3.0 SE O

0.0 1

0.0 17 0.8 46 2.2 55 2.7 41 2.0 34 1.7 194 9.5 SSE O

0.0 1

0.0 26 1.3 56 2.7 102 5.0 52 2.5 17 0.8 254 12.4 S

0 0.0 0

0.0 14 0.7 47 2.3 30 1.5 21 1.0 15 0.7 127 6.2 SSW 0

0.0 1

0.0 15 0.7 21 1.0 31 1.5 53 2.6 38 1.9 159 7.8 SW 0

0.0 2

0.1 13 0.6 16 0.8 66 3.2 27 1.3 10 0.5 134 6.5 WSW 0

0.0 0

0.0 12 0.6 46 2.2 56 2.7 23 1.1 1

0.0 138 6.7 w

0 0.0 6

0.3 5

0.2 45 2.2 35 1.7 14 0.7 2

0.1 107 5.2 WNW 0

0.0 1

0.0 15 0.7 24 1.2 35 1.7 41 2.0 14 0.7 130 6.3 Nu 0

0.0 0

0.0 13 0.6 38 1.9 59 2.9 32 1.6 28 1.4 170 8.3 NNu O

0.0 2

0.1 13 0.6 35 1.7 40 2.0 28 1.4 10 0.5 128 6.2 O

0.0 22 1.1 216 10.5 580 28.3 669 32.7 377 18.4 185 9.0 2049 100.0 MISSING HOURS:

135 MEAN WIND SPEED:

14.9

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1 ARTIFICIAL ISLAND 7/96 - 9/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY A1MOSPHERIC STABILITY CLASS WIND: 300 FT LAPSE RATE: -1.4 TO -0.5 DEG C/100M DELTA T: (300-33FT)

CLASS 0 WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT j

DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT

{

N O

0.0 0

0.0 11 0.5 15 0.7 8

0.4 0

0.0 0

0.0 34 1.5 NNE O

0.0 0

0.0 11 0.5 8

0.4 11 0.5 4

0.2 2

0.1 36 1.6 NE O

0.0 1

0.0 2

0.1 9

0.4 3

0.1 4

0.2 1

0.0 20 0.9 ENE O

0.0 0

0.0 8

0.4 8

0.4 5

0.2 0

0.0 0

0.0 21 1.0 E

O 0.0 1

0.0 6

0.3 3

0.1 2

0.1 3

0.1 6

0.3 21 1.0 l

ESE O

0.0 2

0.1 6

0.3 1

0.0 9

0.4 1

0.0 13 0.6 32 1.5 SE O

0.0 1

0.0 6

0.3 17 0.8 43 2.0 21 1.0 6

0.3 94 4.3 l

SSE O

0.0 1

0.0 19 0.9 33 1.5 36 1.6 13 0.6 0

0.0 102 4.6

[

S 0

0.0 6

0.3 17 0.8 27 1.2 23 1.0 3

0.1 1

0.0 77 3.5 SSW 0

0.0 2

0.1 8

0.4 25 1.1 11 0.5 8

0.4 4

0.2 58 2.6 SW 0

0.0 1

0.0 8

0.4 26 1.2 18 0.8 1

0.0 2

0.1 56 2.5 1

WSW 0

0.0 0

0.0 5

0.2 19 0.9 8

0.4 0

0.0 2

0.1 34 1.5 f

W 0

0.0 2

0.1 1

0.0 10 0.5 18 0.8 3

0.1 1

0.0 35 1.6 l

WNW 0

0.0 3

0.1 6

0.3 8

0.4 11 0.5 2

0.1 3

0.1 33 1.5 NW 0

0.0 1

0.0 10 0.5 22 1.0 20 0.9 12 0.5 0

0.0 65 2.9 NNW 0

0.0 1

0.0 11 0.5 21 1.0 17 0.8 7

0.3 2

0.1 59 2.7 l

0 0.0 22 1.0 135 6.1 252 11.4 243 11.0 82 3.7 43 2.0 777 35.2 L

MEAN WIND SPEED: 13.0 MISSING:

0 t

l i

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f

g W

W W

M M

ARTIFICIAL ISLAND 7/96 - 9/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMCSPHERIC STABILITY CLASS WIND: 300 FT LAPSE RATE: -0.4 TO 1.5 DEG C/100M DELTA T: (300-33FT)

CLASS E WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT I

N O

0.0 2

0.1 5

0.2 14 0.6 12 0.5 1

0.0 0

0.0 34 1.5 NNE O

0.0 0

0.0 4

0.2 10 0.5 9

0.4 0

0.0 0

0.0 23 1.0 NE O

0.0 1

0.0 11 0.5 11 0.5 2

0.1 0

0.0 2

0.1 27 1.2 ENE O

0.0 0

0.0 2

0.1 9

0.4 11 0.5 0

0.0 0

0.0 22 1.0 E

O 0.0 1

0.0 8

0.4 15 0.7 8

0.4 0

0.0 0

0.0 32 1.5 ESE O

0.0 2

0.1 8

0.4 22 1.0 21 1.0 1

0.0 1

0.0 55 2.5 SE O

0.0 2

0.1 6

0.3 14 0.6 24 1.1 7

0.3 7

0.3 60 2.7 SSE O

n0 2

0.1 12 0.5 21 1.0 10 0.5 5

0.2 8

0.4 58 2.6 S

0 3

0.1 9

0.4 14 0.6 12 0.5 4

0.2 2

0.1 44 2.0 SSW 0

-.a 4

0.2 15 0.7 24 1.1 40 1.8 6

0.3 0

0.0 89 4.0 SW 0

0.0 2

0.1 10 0.5 36 1.6 32 1.5 1

0.0 1

0.0 82 3.7 WSW 0

0.0 2

0.1 16 0.7 27 1.2 14 0.6 0

0.0 0

0.0 59 2.7 W

0 0.0 3

0.1 8

0.4 28 1.3 23 1.0 1

0.0 0

0.0 63 2.9 WNW 0

0.0 5

0.2 17 0.8 22 1.0 14 0.6 6

0.3 0

0.0 64 2.9 NW 0

0.0 2

0.1 9

0.4 24 1.1 39 1.8 28 1.3 1

0.0 103 4.7 NNW 0

C.0 1

0.0 17 0.8 13 0.6 14 0.6 9

0.4 4

0.2 58 2.6 i

l 0

0.0 32 1.5 157 7.1 304 13.8 285 12.9 69 3.1 26 1.2 8 73 39.6 j

MEAN WIND SPEED: 12.1 MISSING:

0 I

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M ARTIFICIAL ISLAND 7/96 - 9/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WldD: 300 FT DELTA T: (300-33FT)

ALL STABILITY CLASSES r

WIND SPEED GROUPS (MPH) r 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

O 0.0 4

0.2 30 1.4 48 2.2 34 1.5 4

0.2 0

0.0 120 5.4 NNE O

0.0 0

0.0 25 1.1 30 1.4 39 1.8 4

0.2 2

0.1 100 4.5 NE O

0.0 2

0.1 24 1.1 27 1.2 9

0.4 4

0.2 3

0.1 69 3.1 ENE O

0.0 0

0.0 11 0.5 18 0.8 16 0.7 0

0.0 0

0.0 45 2.0 E

O 0.0 2

0.1 18 0.8 23 1.0 10 0.5 3

0.1 6

0.3 62 2.8 ESE O

0.0 6

0.3 14 0.6 30 1.4 33 1.5 2

0.1 14 0.6 99 4.5 SE O

0.0 7

0.3 15 0.7 43 2.0 81 3.7 33 1.5 19 0.9 198 9.0 SSE O

0.0 3

0.1 39 1.8 66 3.0 53 2.4 20 0.9 9

0.4 190 8.6 5

0 0.0 12 0.5 44 2.0 43 2.2 39 1.8 7

0.3 3

0.1 153 6.9 SSW 0

0.0 10 0.5 38 1.7 55 2.5 55 2.5 20 0.9 4

0.2 182 8.3 SW 0

0.0 9

0.4 28 1.3 72 3.3 63 2.9 4

0.2 5

0.2 181 8.2 usu 0

0.0 4

0.2 32 1.5 61 2.8 37 1.7 0

0.0 2

0.1 136 6.2 i

W 0

0.0 7

0.3 19 0.9 58 2.6 52 2.4 6

0.3 1

0.0 143 6.5 WNW 0

0.0 9

0.4 37 1.7 40 1.8 35 1.6 11 0.5 4

0.2 136 6.2 NW 0

0.0 4

0.2 26 1.2 65 2.9 81 3.7 46 2.1 4

0.2 226 10.2 NNW 0

0.0 2

0.1 43 2.0 50 2.3 4 t.

2.0 20 0.9 6

0.3 165 7.5 0

0.0 81 3.7 443 20.1 734 33.3 681 30.9 184 8.3 82 3.7 2205 100.0 MISSING HOURS:

3 MEAN WIND SPEED:

12.1 t

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M M

M ARTIFICIAL ISLAND 7/96 - 9/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT DELTA T: (300-33FT)

DIRECTION VS SPEED ONLY WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUN PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

O 0.0 4

0.2 30 1.4 48 2.2 34 1.5 4

0.2 0

0.0 120 5.4 NNE O

0.0 0

0.0 25 1.1 30 1.4 39 1.8 4

0.2 2

0.1 100 4.5 NE O

0.0 2

0.1 24 1.1 27 1.2 9

0.4 4

0.2 3

0.1 69 3.1 ENE O

0.0 0

0.0 11 0.5 18 0.8 16 0.7 0

0.0 0

0.0 45 2.0 E

O 0.0 2

0.1 18 0.8 23 1.0 10 0.5 3

0.1 6

0.3 62 2.8 ESE O

0.0 6

0.3 14 0.6 30 1.4 33 1.5 2

0.1 14 0.6 99 4.5 SE O

0.0 7

0.3 15 0.7 43 1.9 81 3.7 33 1.5 19 0.9 198 9.0 SSE O

0.0 3

0.1 39 1.8 67 3.0 53 2.4 20 0.9 9

0.4 191 8.7 S

0 0.0 12 0.5 44 2.0 48 2.2 39 1.8 7

0.3 3

0.1 153 6.9 SSW 0

0.0 11 0.5 38 1.7 56 2.5 55 2.5 20 0.9 4

0.2 184 8.3 SW 0

0.0 9

0.4 28 1.3 72 3.3 63 2.9 4

0.2 5

0.2 181 8.2 WSW 0

0.0 4

0.2 32 1.4 61 2.8 37 1.7 0

0.0 2

0.1 136 6.2 w

0 0.0 7

0.3 19 0.9 58 2.6 52 2.4 6

0.3 1

0.0 143 6.5 WNW 0

0.0 9

0.4 37 1.7 40 1.8 35 1.6 11 0.5 4

0.2 136 6.2 NW 0

0.0 4

0.2 26 1.2 65 2.9 81 3.7 46 2.1 4

0.2 226 10.2 NNW 0

0.0 2

0.1 43 1.9 50 2.3 44 2.0 20 0.9 6

0.3 165 7.5 0

0.0 82 3.7 443 20.1 736 33.3 681 30.8 184 8.3 82 3.7 2208 100.0 MISSING HOURS:

0 i

MEAN w!ND SPEED:

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M M-arf!FICIAL ISLAND 10/96-12/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT LAPSE RATE: -1.4 TO -0.5 DEG C/100M DELTA T: (300-33FT)

CLASS D WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

O 0.0 0

0.0 3

0.1 3

0.1 11 0.5 12 0.6 10 0.5 39 1.8 NNE O

0.0 1

0.0 5

0.2 10 0.5 16 0.7 2

0.1 1

0.0 35 1.6 NE O

0.0 1

0.0 10 0.5 7

0.3 3

0.1 0

0.0 0

0.0 21 1.0 ENE O

0.0 1

0.0 6

0.3 6

0.3 0

0.0 0

0.0 14 0.7 E

O 0.0 1

0.0 2

0.1 8

0.4 9

0.4 4

0.2 1

0.0 25 1.2 ESE O

0.0 2

0.1 4

0.2 4

0.2 3

0.1 4

0.2 21 1.0 SE O

0.0 1

0.0 2

0.1 7

0.3 to 0.5 0

0.0 0

0.0 20 0.9 SSE O

0.0 0

0.0 7

0.3 22 1.0 20 0.9 6

0.3 4

0.2 59 2.8 S

0 0.0 0

0.0 1

0.0 16 0.7 16 0.7 2

0.1 0

0.0 35 1.6 SSW 0

0.0 1

0.0 5

0.2 12 0.6 6

0.3 1

0.0 0

0.0 25 1.2 SW 0

0.0 1

0.0 6

0.3 13 0.6 8

0.4 0

0.0 0

0.0 28 1.3 VSW 0

0.0 3

0.1 7

0.3 25 1.2 13 0.6 12 0.6 1

0.0 61 2.8 W

0 0.0 1

0.0 9

0.4 18 0.8 17 0.8 12 0.6 5

0.2 62 2.9 WNW 0

0.0 3

0.1 8

0.4 16 0.7 17 0.8 12 0.6 12 0.6 68 3.2 NW 0

0.0 1

0.0 17 0.8 17 0.8 20 0.9 27 1.3 18 0.8 100 4.7 NNW 0

0.0 2

0.1 9

0.4 14 0.7 3

0.1 17 0.8 12 0.6 57 2.7 0

0.0 19 0.9 96 4.5 198 9.2 179 8.4 110 5.1 68 3.2 670 31.3 MEAN WIND SPEED: 14.4 MISSING:

14

m M

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M M

m m

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ARTIFICIAL ISLAND 10/96-12/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT LAPSE RATE: -0.4 TO 1.5 DEG C/100H DELTA T: (300-33FT)

CLASS E WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5' GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

O 0.0 1

0.0 5

0.2 7

0.3 23 1.1 7

0.3 7

0.3 50 2.3 NNE O

0.0 0

0.0 5

0.2 16 0.7 7

0.3 6

0.3 7

0.3 41 1.9 NE O

0.0 1

0.0 6

0.3 7

0.3 9

0.4 1

0.0 0

0.0 24 1.1 ENE O

0.0 1

0.0 6

0.3 18 0.8 9

0.4 3

0.1 0

0.0 37 1.7 E

O 0.0 5

0.2 1

0.0 5

0.2 9

0.4 1

0.0 2

0.1 23 1.1 ESE O

0.0 2

0.1 2

0.1 7

0.3 4

0.2 3

0.1 0

0.0 18 0.8 SE O

0.0 2

0.1 2

0.1 12 0.6 25 1.2 7

0.3 5

0.2 53 2.5 SSE O

0.0 1

0.0 8

0.4 16 0.7 35 1.6 2

0.1 1

0.0 63 2.9 S

0 0.0 3

0.1 11 0.5 14 0.7 16 0.7 4

0.2 2

0.1 50 2.3 SSW 0

0.0 4

0.2 9

0.4 21 1.0 25 1.2 11 0.5 2

0.1 72 3.4 Su o

0.0 2

0.1 7

0.3 26 1.2 16 0.7 5

0.2 0

0.0 56 2.6 WSu 0

0.0 4

0.2 9

0.4 25 1.2 19 0.9 3

0.1 1

0.0 61 2.8 W

0 0.0 2

0.1 5

0.2 23 1.1 23 1.1 7

0.3 0

0.0 60 2.8 WNW 0

0.0 0

0.0 15 0.7 22 1.0 47 2.2 20 0.9 0

0.0 104 4.9 NW 0

0.0 1

0.0 4

0.2 20 0.9 63 2.9 29 1.4 14 0.7 131 6.1 NNu 0

0.0 1

0.0 10 0.5 6

0.3 16 0.7 11 0.5 4

0.2 48 2.2 0

0.0 30 1.4 105 4.9 245 11.4 346 16.1 120 5.6 45 2.1 891 41.6 MEAN WIND $ PEED: 13.9 MISSING:

31

W W

M M

M W

M M

M ARTIFICIAL ISLAND 10/96-12/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT LAPSE RATE:

1.6 TO 4.0 DEG C/100M DELTA T: (300-33FT)

CLASS F WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

O 0.0 1

0.0 1

0.0 7

0.3 3

0.1 0

0.0 13 0.6 NNE O

0.0 0

0.0 1

0.0 0

0.0 1

0.0 0

0.0 3

0.1 NE O

0.0 0

0.0 1

0.0 0

0.0 4

0.2 ENE O

0.0 0

0.0 4

0.2 4

0.2 3

0.1 0

0.0 0

0.0 11 0.5 E

O 0.0 2

0.1 4

0.2 2

0.1 6

0.3 0

0.0 0

0.0 14 0.7 ESE O

0.0 2

0.1 3

0.1 8

0.4 4

0.2 0

0.0 0

0.0 17 0.8 SE O

0.0 1

0.0 0

0.0 7

0.3 19 0.9 3

0.1 10 0.5 40 1.9 SSE O

0.0 1

0.0 2

0.1 6

0.3 6

0.3 8

0.4 14 0.7 37 1.7 S

0 0.0 3

0.1 3

0.1 5

0.2 12 0.6 13 0.6 10 0.5 46 2.1 Ssw 0

0.0 2

0.1 0

0.0 2

0.1 to 0.5 6

0.3 1

0.0 21 1.0 SW 0

0.0 2

0.1 2

0.1 4

0.2 12 0.6 2

0.1 1

0.0 23 1.1 WSW 0

0.0 2

0.1 4

0.2 2

0.1 4

0.2 4

0.2 0

0.0 16 0.7 W

0 0.0 1

0.0 2

0.1 6

0.3 8

0.4 5

0.2 0

0.0 22 1.0 WNW 0

0.0 1

0.0 5

0.2 5

0.2 2

0.1 1

0.0 0

0.0 14 0.7 NW 0

0.0 1

0.0 0

0.0 4

0.2 8

0.4 3

0.1 0

0.0 16

0. 7 NNW 0

0.0 0

0.0 6

0.3 2

0.1 3

0.1 0

0.0 0

0.0 11 0.5 0

0.0 19 0.9 38 1.8 59 2.8 106 4.9 50 2.3 36 1.7 308 14.4 MEAN WIND SPEED:

15.4 MISSING:

14

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1

M M

M ARTIFICIAL ISLAND 10/96-12/96 JOINT DISTRIBUTION OF u!ND DIREC110N AND SPEED BY ATHOSPHERIC STARILITY CLASS WIND: 300 FT DELTA T: (300-33FT)

ALL STABILITY CLASSES WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SOM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

O 0.0 2

0.1 9

0.4 15 0.7 42 2.0 27 1.3 19 0.9 114 5.3 NNE O

0.0 1

0.0 14 0.7 31 1.4 29 1.4 to 0.5 8

0.4 93 4.3 NE O

0.0 2

0.1 20 0.9 18 0.8 17 0.8 4

0.2 0

0.0 61 2.8 ENE O

0.0 2

0.1 12 0.6 34 1.6 18 0.8 5

0.2 0

0.0 71 3.3 E

O 0.0 8

0.4 8

0.4 15 0.7 24 1.1 5

0.2 3

0.1 63 2.9 ESE O

0.0 6

0.3 12 0.6 19 0.9 12 0.6 6

0.3 4

0.2 59 2.8 SE O

0.0 4

0.2 4

0.2 31 1.4 55 2.6 10 0.5 15 0.7 119 5.6 SSE O

0.0 2

0.1 19 0.9 44 2.1 64 3.0 20 0.9 37 1.7 186 8.7 S

3 0.0 8

0.4 21 1.0 41 1.9 50 2.3 21 1.0 13 0.6 154 7.2 SSW 0

0.0 11 0.5 22 1.0 42 2.0 42 2.0 18 0.8 3

0.1 138 6.4 Su 0

0.0 6

0.3 22 1.0 48 2.2 38 1.8 7

0.3 1

0.0 122 5.7 usu 0

0.0 9

0.4 23 1.1 64 3.0 41 1.9 23 1.1 2

0.1 162 7.6 u

o 0.0 4

0.2 23 1.1 53 2.5 63 2.9 36 1.7 5

0.2 184 8.6 WNW 0

0.0 4

0.2 30 1.4 45 2.1 81 3.8 41 1.9 12 0.6 213 9.9 NW 0

0.0 3

0.1 24 1.1 49 2.3 98 4.6 62 2.9 37 1.7 2 73 12.7 NNW 0

0.0 3

0.1 28 1.3 28 1.3 25 1.2 30 1.4 17 0.8 131 6.1 I

O 0.0 75 3.5 291 13.6 577 26.9 699 32.6 325 15.2 176 8.2 2143 100.0 MISSING HOURS:

65 HEAN WIND SPEED:

14.3 I

l

M M

ARTIFICIAL ISLAND 10/96-12/96 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT DELTA T: (300-33FT)

OIRECTION VS SPEED ONLY WIND SPEED GROUPS (MPH) 0.0 0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 CE 24.6 SUM PERCENT DIRECTION SLH PERCEN1 SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

O 0.0 2

0.1 9

0.4 15 0.7 42 2.0 27 1.3 19 0.9 114 5.3 NNE O

0.0 1

0.0 14 0.7 31 1.4 29 1.4 10 0.5 8

0.4 93 4.3 NE O

0.0 2

0.1 20 0.9 18 0.8 17 0.8 4

0.2 0

0.0 61 2.8 ENE O

0.0 2

0.1 12 0.6 34 1.6 18 0.8 5

0.2 0

0.0 71 3.3 E

O 0.0 8

0.4 8

0.4 15 0.7 24 1.1 5

0.2 3

0.1 63 2.9 ESE O

0.0 6

0.3 12 0.6 19 0.9 12 0.6 6

0.3 4

0.2 59 2.8 SE O

0.0 4

0.2 4

0.2 31 1.4 55 2.6 10 0.5 15 0.7 119 5.6 SSE O

0.0 2

0.1 19 0.9 44 2.1 64 3.0 20 0.9 37 1.7 186 8.7 5

0 0.0 8

0.4 21 1.0 41 1.9 50 2.3 21 1.0 13 0.6 154 7.2 SSu 0

0.0 11 0.5 22 1.0 42 2.0 42 2.0 18 0.8 3

0.1 138 6.4 SW 0

0.0 6

0.3 22 1.0 48 2.2 38 1.8 7

0.3 1

0.0 122 5.7 WSW 0

0.0 9

0.4 23 1.1 64 3.0 41 1.9 23 1.1 2

0.1 162 7.6 u

0 0.0 0.2 23 1.1 53 2.5 64 3.0 36 1.7 5

0.2 185 8.6 WNu o

0.0 4

0.2 30 1.4 45 2.1 81 3.8 41 1.9 12 0.6 213 9.9 NW 0

0.0 3

0.1 24 1.1 49 2.3 98 4.6 62 2.9 37 1.7 2 73 12.7 NNW 0

0.0 3

0.1 28 1.3 28 1.3 25 1.2 30 1.4 17 0.8 131 6.1 0

0.0 75 3.5 291 13.6 577 26.9 700 32.6 325 15.2 176 8.2 2144 100.0 MIS $1NG HOURS:

64 MEAN WIND SPEED:

14.3

- -- --=___-

iiI lI

lI

,lI APPENDIX B

!,I HOPE CREEK ODCM d

i I i

REVISION 15

lI i

i I

I I

1I

, I 1

OFFSITE DOSE CALCULATION 31ANUAL FOR 1

i PUBLIC SERVICE ELECTRIC AND GAS COSIPANY l

)

IIOPE CREEK GENERATING STATION

]

Revision 15 December 1996 I

I I

Approval:

dh oate 1317 /' ( Mts.#

Th. -/ / 7 I

Oac casi< man:

. o ~<

I i

I

Hope Creek ODCM Rev 15

'I IIOPE CREEK GENERATING STATION OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS INTRODUCTION.

.1 1.0 LIQUID EFFLUENTS 4

l.1 Radiation Monitoring Instrumentation and Controls.

.2 I

1.2 Liquid Emuent Monitor Setpoint Determination.

.3

I 1.2.1 Liquid Emuent Monitors.

.2 1.2.2 Conservative Default Values.

.3 I

1.3 Liquid Emuent Concentration j

Limits -10 CFR 20.

.4 l.4 Liquid Emuent Dose Calculations - 10 CFR 50.

.5

,I 1.4.1 Member of the Public Dose -

I Liquid Emuents.

.5 1.4.2 Simplified Liquid Emuent Dose Calculation..

6 1.5 Liquid Emuent Dose Projections.

7 1.6 Representative Samples.

8 2.0 GASEOUS EFFLUENTS 2.1 Radiation Monitoring Instrumentation and Controls.

8 2.2 Gaseous Emuent Monitor Setpoint Determination.

9 2.2.1 Plant Vent and FRVS Monitors..

9 2.2.2 Conservative Default Values.

.10 1

2.3 Gaseous Emuent Instantaneous Dose Rate Calculatien - 10 CFR 20..

.I1 I

.g 1

Hope Creek ODCM Rev 15 f

2 3.1 Site Boundary Dose Rate -

Noble Gases..

.I1 2.3.2 Site Boundary Dose Rate -

Radiciodine and Particulates.

.12 2.4 Noble Gas Efiluent Dose Calculations - 10 CFR 50.

.13 2.4.1 UNRESTRICTED AREA Dose-Noble Gases.-

.13 2.4.2 Simplified Dose Calculation for Noble Gases.

.13 I

2.5 Radioiodine and Particulate Dose Calculations - 10 CFR 50.

.14 2.5.1 UNRESTRICTED AREA Dose-Radiciodine and Particulates.

.14 2.5.2 Simplified Dose Calculation for j

Radiciodines and Particulates.

.14 2.6 Gaseous Efiluent Dose Projection.

.15 3.0 SPECIAL DOSE ANALYSIS 3.1 Doses Due to Activities inside the SITE BOUNDARY.

.16 3.2 Total Dose to MEMBERS OF THE PUBLIC -

40 CFR 190.

.17 3.2.1 Effluent Dose Calculation..

.17 3.2.2 Direct Exposure Determination.

.17 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.

.18 4.1 Sampling Program..

.I8 4.2 Interlaboratory Comparison Program.

.18 I

g u

Hope Cieck ODCM Rev 15 TABLES 1-1 Parameters for Liquid Alarm Setpoint Determination.

.21 I

l-2 Site Related Ingestion Dose Commitment Factors, Aio.

.22 1-3 Bioaccumulation Factors (BFi).

.24 I

2-1 Dose Factors for Noble Gases.

.27 2-2 Parameters for Gaseous Alarm Setpoint Determination.

.28 2-3 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations.

.29 2-4 Pathway Dose Factors -

Atmospheric Releases.

.30 A-1 Calcu'ation of Effective MPC.

. A-5 B-1 Adult Dose Contributions Fish and Invertebrate Pathways.

.B-5 I

C-1 Effective Dose Factors.

.C-4 D-1 Infant Dose Contribution Fraction of Dose.

. D-3 I

Fraction of Dose Contributions by Pathway..

. D-3 D-2 E-1 Sample L ocations.

.E-3 F-1 Maximum Permissible Concentrations.

.F-2 APPENDICES Appendix A - Evaluation of Conservative, Default MPC Value for Liquid Efiluents.

. A-1 Appendix B - Technical Basis for Effective Dose Factors - Liquid Radioactive Effluents.

. B-1 Appendix C - Technical Basis for EfTective Dose Factors - Gaseous Radioactive Efiluents.

. C-1 Appendix D - Technical Basis for Effective Dose Parameters - Gaseous Radioactive Effluents.

. D-1 Appendix E - Radiological Environmental Monitoring Program - Sample Type, Location and Analysis.

. E-1 l

l Appendix F - Maximum Permissib?: +.,ncentration (MPC) values for liquid effluents.

..F-1 I

I g

m

Hope Crcck ODCM Rev 15 HOPE CREEK GENERATING STATION OFFSITE DOSE CALCULATION MANUAL INTRODUCTION The Hope Creek Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in:

1) the calculation of radioactive liquid and gaseous efUuent momtormg mstrumentation alarm / trip setpoints, and

2) the calculation of radioactive liquid and gaseous concentrations, dose rates and cumulative quarterly and yearly doses.

The methodology stated in this manual is acceptable for use in demonstrating compliance with 10 CFR 20.106,10 CFR 50, Appendix I and 40 CFR 190.

I More conservative calculation methods and/or conditions (e.g., location and/or exposure pathways) expected to yield higher computed doses for the maximally exposed person may be l

assumed in the dose evaluations.

The ODCM will be maintained at the station for use as a reference guide and training I

document of accepted methodologies and calculation.

'g Changes will be made to the ODCM calculation methodologies and parameters as is deemed ig necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR 50.36a and Appendix 1 for demonstrating radioactive efUuents are ALARA.

NOTE: As used throughout this document, excluding acronyms, words appearing all capitalized denote the application of definitions as used in the Hope Creek Technical Specifications.

!I l

l I

(I l

1 l

l

Hope Creek ODCM Rev 15 1.0 LIOUID EFFLUENTS 1.1 Radiation Monitorine Instrumentation and Controls I

The liquid emuent monitoring instrumentation and controls at Hope Creek for controlling and monitoring normal radioactive material releases in accordance with the Hope Creek Radiological Emuent Technical Specifications are summarized as follows:

1)

Alarm (and Automatic Termination)- Liquid I

Radwaste Discharge Line Monitor provides the alarm and automatic termination of liquid (RE4861) radioactive material releases from the liquid waste management system as required by Technical Specification 3.3.7.10.

I Alarm (Only)- The Cooling-Tower Blowdown Emuent Monitor (RE8817) provides an Alarm 2) function only for releases into the environment as required by Technical Specification 3.3.7.10.

I Liquid radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented in Figure 1-1.

1.2 Liouid Effluent Monitor Setpoint Determination Per the requirements of Technical Specification 3.3.7.10, alarm setpoints shall be established for the liquid monitoring instrumentation to ensure that the release concentration limits of 4

Specification 3.11.1.1 are met (i.e., the concentration of radioactive material released in liquid emuents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20 Appendix B. Table II, Column 2, (Appendix F) for radionuclides and 2.0E-04 uCi/ml f.,r dissolved or entrained noble gases). The following equation (adopted from NUREG-I 0133) must be satisfied to meet the liquid emuent restrictions:

I C (F + f) c$

(1.1) f I

where:

C=

the emuent concentration limit of Technical Specification (3.11.1.1) implementing the 10 CFR 20 MPC (Appendix F) for the site, in uCi/ml.

I the setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity c=

concentration in the emuent line prior to dilution and subsequent release; the setpoint, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the UNRESTRICTED AREA.

f=

the Cow rate at the radiation monitor location, in volume per unit time, but the same units as F, below.

l F=

the dilution water flow rate as measured prior to the release point, in volume per unit time.

[ Note that if no dilution is provided, c 5 C. Also, note that when (F) is large compared to (f),

I then (F + f) = F ]

2

Hope Creek ODCM Rev 15 1.2.1 Liquid Emuent Monitors The setpoints for the liquid emuent monitors at the Hope Creek Generating Station are l

determined by the following equation:

I MPC,

CTBD a CF SP$;

I

--- + b kg (l.2)

RR with:

E Ci(gamma emitters only)

MPC,=

(1.3)

C (gamma) 4 E

where:

SP alarm setpoint corresponding to the maximum allowable release rate (uCi/ml).

=

MPC,=

an effective MPC value for the mixture of radionuclides in the emuent stream, (uCi/ml).

C.

the concentration of radionuclide in the liquid emuent (uCi/ml).

=

i MPCi =

the MPC value corresponding to radionuclide i from (Appendix F) 10 CFR 20, Appendix B, Table II, Column 2 (uCi/ml).

I CTBD =

the Cooling-Tower Blowdown Discharge rate at the time of release (gal / min).

RR the liquid emuent release rate (gal / min) at the monitor location (i.e., at the

=

I liquid radwaste monitor or at the CTBD monitor).

bkg the background of the monitor (uCi/ml).

4

=

CF Correction factor to account for non-gamma emitting nuclides and radiation

=

monitor inaccuracies.

The radioactivity monitor setpoint equation (1.2) remains valid during outages when the Cooling-Tower Blowdown discharge is potentially as its lowest value. Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria.

Procedural restrictions prevent simultaneous liquid releases.

I I

I 3

I

Hope Creek ODCM Rev 15 1.2.2 Conservative Default Values Conservative alarm setpoints for liquid radwaste radiation monitors may be determined through the use of default parameters. Table 1-1 summarized all current default values in use for Hope Creek. They are based upon the following:

l a) substitution of the effective MPC value with a default value of 7.92E-05 uCi/ml for radwaste releases (Refer to Appendix A forjustification);

b) substitutions of the Cooling-Tower Blowdown discharge rate with the minimum average flow, in gal / min; and, c) substitutions of the emuent release rate with the highest allowed rate, in gal / min.

d) substitution of a 0.5 correction factor to account for monitor inaccuracies and non-I gamma emitting radionuclides.

With preestablished alarm setpoints, it is possible to control the radwaste release rate (RR) to ensure the inequality of equation (1.2) is maintained under changing values for MPCe and for ditTering Cooling-Tower Blowdown discharge.

1.3 I.iould Efiluent Concentration 1.imits - 10 CFR 20 Technical Specification 311.1.1 limits the concentration of radioactive material in liquid emuents (after dilution in the Cooling-Tower Blowdown Discharge System) to less than the concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F) for radionuclides other than noble gases. Noble gases are limited to a diluted concentration of 2.0E-04 uCi/ml. Release rates are controlled and radiation monitor alarm setpoints are established as addressed above to ensure that these concentration limits are not exceeded.

However, in the event any liquid release results in an alarm setpoint being exceeded, an evaluation of compliance with the concentration limits of Technical Specification 3.11.1.1 may be performed using the following equation:

I F

C RR i

I

<1 (1.4)

MPC; CTBD + RR where:

C actual concentration of radionuclide i as measured in the undiluted liquid

=

i emuent (uCi/ml).

MPCi =

the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F) (uCi/ml).

2E-04 uCi/mi for dissolved or entrained noble gases.

=

the actual liquid emuent release rate (gal / min)

RR

=

CTBD =

the actual Cooling-Tower Blowdown discharge at the time of release I

(gal / min) 4 I

Hope Creek ODCM Rev 15 1.4 I inuid Emnent Dose Calculation - 10 CFR 50 1.4.1 MEMBER OF TIIE PUBLIC Dose-Ilauid Emuents I

Technical Specification 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid emuents from Hope Creek Generating Station to:

I

- during any calendar quarter:

51.5 mrem to total body I

5 5.0 mrem to any organ I

- during any calendar year:

$ 3.0 mrem to total body 510.0 mrem to any organ Per the surveillance requirements to Technical Specification 4.11.1.2, the fol.

mg calculation methods shall be used for determining the dose or dose commitment due to the liquid radioactive emuents from Hope Creek.

8.35E-04

YOL Do

E (C

A,o)

(1.5)

=

i CTBD where:

Do dose or dose commitment to organ o, including total body (mrem).

=

I site-related ingestion dose commitment factor to the total body or any organ o A,o

=

for radionuclide i (mrem /hr per uCi/ml).

Ci average concentration of radionuclide i, in undiluted liquid emuent I

=

representative of volume VOL (uCi/ml).

4 VOL volume ofliquid emuent released (gal).

=

I Average Cooling-Tower Blowdown discharge rate during release period CTBD =

(gal / min).

8.35E-04 =

conversion factor (1.67E-2 hr/ min) and a near field dilution factor of 0.05 (refer to Appendix B, Page B-4 for definition).

The site-related ingestion dose / dose commitment factors (A o) are presented in Table 1-2 and i

have been derived in accordance with NUREG-0133 by the equation:

l Aw, = 1.14E5 l(UI a Bl) + (UF

BF)] Df (1.6) i i

i I

.I 5

I

Hope Creek ODCM Rev 15 where:

composite dose parameter for the total body or critical organ o of an adult for Am

=

radionuclide i, for the fish and invertebrate ingestion pathways (mrem /hr per uCi/ml).

1.14E5 conversion factor (pCi/uCi

ml/kg per hr/yr).

=

UI adult invertebrate consumption (5 kg/yr).

=

Bi, bioaccumulation factor for radionuclide i in invertebrates from Table 1-3

=

,g (pCi/kg per pCill).

E UF adult fish consumption (21 kg/yr).

=

Bf, bioaccumulation factor for nuclide i in fish from Table 1-4 (pCi/kg per pCi/l).

=

Df, I

dose conversion factor for nuclide i for adults in preselected organ, o, from

=

Table E-11 of Regulatory Guide 1.109 (mrem /pCi).

I The radionuclides included in the periodic dose assessment per the requirements of Technical Specification 3/4.11.1.2 are those as identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of Technical Specification 3/4.11.1.1, Table 4.11.1.1.1-1.

Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added to the dose analysis at a frequency consistent with the required minimum analysis frequency of Technical Specification Table 4.11.1.1.1-1.

1.4.2 Simplified Liquid Elliuent Dose Calculation In lieu of the individual radionuclide dose assessment as presented in Section 1.4.1, the I

following simplified dose calculation equation may be used for demonstrating compliance with the dose limits of Technical Specification 311.1.2. (Refer to Appendix B for the derivation and justification for this simplified method.)

Total Body Ds 1.,9,4 E+02

VOI, EC i

(1.7)

=

i CTBD Maximum Oruan I

D.,

=

4.28E+02

VOI,

EC (1.8) i CTBD I

I 6

Hope Creek ODCM Rev 15 I

where:

l Ds

= conservatively evaluated total body dose (mrem).

i Dn

= evaluated maximum organ dose (mrem).

C;

= average concentration of radionuclide i, in undiluted liquid efiluent representative of the volume VOL (uci/ml).

VOL = volume ofliquid effluent released (gal).

CTBD = average Cooling-Tower Blowdown discharge rate during release period (gal / min).

I 1.94E+02

= conversion factor (1.67E-2 hr/ min) the ingestion dose commitment factor (Zn-65, total body -- 2.32E5 mrem /hr per uCi/ml), and the near field dilution factor of 0.05 (See Appendix B).

I 4.28E+02

= conversion factor (1.67E-2 hr/ min) the conversion maximum organ dose conversion factor (Zn-65, Liver -- 5.13E5 mrem /hr per uCi/ml), and the nearfield dilution factor of 0.05 (See Appendix B).

1.5 Iiauid Effluent Dose Projections Technical Specification 3.11.1.3 requires hat the liquid radioactive waste processing system be used to reduce the radioactive material levels in the liquid waste prior to release when the 31-day projected doses exceed:

- 0.06 mrem to the total body, or I

- 0.2 mrem to any organ.

The applicable liquid waste processing system for maintaining radioactive material releases ALARA are the drain filters and demineralizers as delineated in Figure 1-1.

Dose projections are made at least once per 31-days by the following equations:

D s, (D s / d)

31d (1,9)

=

i i

D..,, = (D., / d) a 31d (1.10) where:

Do,p the total body dose projection for current 31-day period (mrem).

=

the total body dose to date for current calendar quarter as determined by Da,

=

equation (1.5) or (1.7).

D.op the maximum organ dose to date for current calendar quarter as determined by

=

equation (1.5 or (1.8)(mrem).

d the number of days in current calendar quarter at the end of the release

=

'l 31d the number of days of concern.

=

I 7

Hope Creek ODCM Rev 15 1.6 Representative Samples A sample should be representative of the bulk stream or volume of emuent from which it is l

taken. Prior to sampling, large volumes ofliquid waste should be mixed in as short a time interval as practicable to assure that any sediments or particulate solids are distributed uniformly in the waste mixture. Recirculation pumps for liquid waste tanks (collection or sample test tanks) should be capable of recirculating at a rate of not less than two tank volumes in eight hours. Minimum recirculation times and methods of recirculation are controlled by specific plant procedures.

GASEOUS EFFLUENTS I2.0 2.1 Radiation Monitorine Instrumentation and Controls I

The gaseous emuent monitoring instrumentation and controls at Hope Creek for controlling and monitoring normal radioactive material releases in accordance with the Radiological Emuent Technical Specifications are summarized as follows:

1)

Filtration. Recirculation. and Ventilation System -

The FRVS is maintained in a standby condition. Upon reactor building isolation, the FRVS recirculation system recirculates the reactor building air through HEPA and l

charcoal filters. Releases are made to the atmosphere via a reactor building vent or the South Plant Vent depending on mode c,f operation. Noble gas monitoring is provided by RE-4811 A.

2)

South Plant Vent -

The SPV receives discharge from the radwaste evaporator, reactor building purge, auxiliary building radwaste area, condensate demineralizer, pipe chase, feedwater heater, and untreated ventilation sources Emuents are monitored (for noble gas) by the RE-4875B monitor.

3)

North Plant Vent -

The NPV receives discharge from the gaseous radwaste treatment system (OfTgas system) and untreated ventilation air sources. Emuents are monitored (for noble gases) by the RE-4573B monitor Gaseous radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation controls are presented in Figures 2-1 and 2-2.

8

Hope Creek ODCM Rev 15 2.2 unseous Effluent Monitor Setnoint Determination 2.2.1 Plant Vent, FRVS Per the requirements of Technical Specification 3.3.7.11, alarm setpoints shall be established for the gaseous efiluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of Specification 3.11.21, which corresponds to a dose rate at the SITE BOUNDARY of 500 mrem / year to the total body or 3000 mrem / year to the skin.

Based on a grab sample analysis of the applicable release (i e., of FRVS, pipe chase, gaseous radwaste treatment system air, etc.), the radiation monitoring alarm setpoints may be established by the following calculation method. The measured radionuclide concentrations I

and release rate are used to calculate the fraction of the allowable release rate, as limited by i

Specification 3.11.2.1, by the equation:

FRAC = [4.72E+02

X/Q

VF * (C

K )] / 500 (2.1) i i

FRAC = [4.72E+02

X/Q

VF * (C * (L + 1.1M ))] / 3000 (2.2) i i

i FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate.

X/Q

= annual average meteorological dispersion to the controlling site boundary location (sec/m3).

VF

= ventilation system flow rate for the applicable release point and monitor (fl3/ min).

C

= concentration of noble gas radionuclide i as determined by radioanalysis of grab I

sample (uCi/cm3) i K

= total body dose conversion factor for noble gas radionuclide i (mrem /yr per i

uCi/m3), from Table 2-1 I

L

= beta skin dose conversion factor for noble gas radionuclide i (mrem /yr per i

uCi/m3), from Table 2-1 I

M;

= gamma air dose conversion factor for noble gas radionuclide i (mrad /yr per uCi/m3), from Table 2-1 1.1

= mrem skin dose per mrad gamma air dose (mrem / mrad)

I 4.72E+02 = conversion factor (cm3/ft3

min /sec) 500

= total body dose rate limit (mrem /yr) 3000

= skin dose rate limit (mrem /yr)

Based on the more limiting FRAC (i c., higher value) as determined above, the alarm setpoints for the applicable monitors may be calculated by the equation:

SP = [AF

E C / FRAC] + hkg (2.3) i 1

l 9

i

I Hope Creek ODCM Rev 15 I

where:

l SP

= alarm setpoint corresponding to the maximum allowable release rate (uCi/cc).

FRAC = highest fraction of the allowable release rate as determined in equation (2.2).

bkg

= background of the monitor (uCi/cc).

AF

= administrative allocation factor for the specific monitor (0.2 NPV,0.2 SPV,0.1 FRVS).

The allocation factor (AF) is an administrative control imposed to ensure that combined releases from Salem Units I and 2 and Hope Creek will not exceed the regulatory limits on I

release rate from the site (i.e., the release rate limits of Technical Specification 3.11.2.1).

Normally, the combined AF value for Salem Units 1 and 2 is 0.5 (0.25 per unit), with the remainder 0.5 allocated to Hope Creek. Any increase in AF above 0.5 for the Hope Creek I

Generating Station will be coordinated with the Salem Generating Station to ensure that the combined allocation factors for all units do not exceed 1.0.

2.2.2 Conservative Default Values A conservative alarm setpoint can be established, in lieu of the individual radionuclide evaluation based on the grab sample analysis, to eliminate the potential of periodically having to adjust the setpoint to reflect minor changes in radionuclide distribution and variations in l

rel. case flow rate. The alarm setpoint may be conservatively determined by the default values presented in Table 2-2.

l These values are based upon:

- the maximum ventilation (or purge) flow rate; I

- a radionuclide distribution adopted from ANSI N237-1976/ANS 18.1 " Source Term Specifications", Table 5 and,

- an administrative allocation factor of 0.5 to conservatively ensure that any releases from Hope Creek do not exceed the maximum allowable release rate.

I For the noble gas radionuclide distribution from ANSI N237-1976/ANS 18.1 (Note Table C-1), the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dore rate. The resulting conservative, default setpoints are presented in Table 2-2.

l l

l I

iI l

10

Hope Creek ODCM Rev 15 2.3 Gaseous Emuent Instantaneous Dose Rate Calculations - 10 CFR 20 2.3.1 Site Houndary Dose Rate - Noble Gases Technical Specification 3.11.2.la limits the dose rate at the SITE BOUNDARY due to noble gas releases to 5 500 mrem /yr, total body and 5 3000 mrem /yr, skin. Radiation monitor alarm l

setpoints are established to ensure that these release limits are not exceeded. In the event any gaseous releases from the station results in an alarm setpoint (as determined in Section 2.2.1) being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release shall be performed using the following equations:

D s = X/Q a E (K a Q,)

(2.4) i i

D = X/Q a E ((L, + 1.lM.) a Q, (2.5) where:

Ds

= Total body dose rate (mrem /yr).

i D,

= skin dose rate (mrem /yr).

X/Q

= atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3)

Q,

= average release rate of radionuclide i over the release period under evaluation (uCi/sec).

l Ki,

= total body dose conversion factor for noble gas radionuclide i(mrem /yr per uCi/m3), from Table 2-1 L

= beta skin dose conversion factor for noble gas radionuclide i (mrad /yr per uCi/m3),

i from Table 2-1 M,

= gamma air dose conversion factor for noble gas radionuclide i (mrad /yr per uCi/m3, from Table 2-1.

1.1

= mrem skin dose per mrad gamma air dose (mrem / mrad)

I As appropriate, simultaneous releases from Salem Units 1 and 2 and Hope Creek will be considered in evaluating compliance with the release rate limits of Specification 3.11.2.la, following any releases exceeding the above prescribed alarm setpoints. Monitor indications I

(readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity.

The 15-minute averaging is needed to allow for reasonable monitor response to potentially changing radioactive material concentrations and to exclude potential electronic spikes in monitor readings that may be unrelated to radioactive material releases. As identified, any l

electronic spiking monitor responses may be excluded from the analysis.

l l

NOTE:

For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed However, conditions exceeding these more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding the dose limits of Technical Specification 3.11.2 la. Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based on the above criteria, no further I

analyses are required for demonstrating compliance with the limits of Specification 3.11.2.1a.

I1

Hope Creek ODCM Rev 15 I

Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-4 may be used for evaluating the gaseous efiluent dose rate.

2.3.2 Site lloundary Dose Rate - Radioiodine and Particuintes I

Technical Specification 3.11.2.lb limits the dose rate to 51500 mrem /yr to any organ for I-

.g 131, 1-133, tritium and particulates with half-lives greater than 8 days. To demonstrate g

compliance with this limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period (e g., nominally once per 7 days). The following equation shall be used for the dose rate evaluation:

Do X/Q a E (R,,

Q,)

(2.6)

=

g u

where:

I Do

= average organ dose rate over the sampling time period (mrem /yr).

X/Q

= atmospheric dispersion to the controlling SITE BOUNDARY location for the inhalation pathway (sec/m3).

R;o

= dose parameter for radionuclide i (mrem /yr per uCifm3) and organ o for the child inhalation pathway from Table 2-4.

Q,

= average release rate over the appropriate sampling period and analysis frequency for 4

radionuclide i - - I-131, I-133, tritium or other radionuclide in particulate form with half-life greater than 8 days (uCi/sec).

By substituting 1500 mrem /yr for Do and solving for Q, an allowable release rate for I-131 can be determined. Based on the annual average meteorological dispersion (See Table 2-3) and the most limiting potential pathway, age group and organ (inhalation, child, thyroid -- Ri =

I 1.62E+07 mrem /yr per uCi/m3), the allowable release rate for I-131 is 34.7 uCi/sec. Reducing this release rate by a factor of 2 to account for potential dose contributions from other radioactive particulate material and other release points (e g., Salem), the corresponding release rate allocated to Hope Creek is 17.4 uCi/sec. For a 7-day period, which is the nominal sampling and analysis frequency for I-131, the cumulative release is 10.5 Ci.

Therefore, as long as the I-131 release in any 7-day period do not exceed 10.5 Ci, no additional analyses are needed for verifying compliance with the Technical Specification 3.11.2.1.b limits on allowable release rate.

12

Hope Creek ODCM Rev 15 2.4 Noble Gas Efiluent Dose Calculations - 10 CFR 50 2.4.1 UNRESTRICTED AREA Dose-Noble Gases Technical Specification 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of 5 5 mrad, gamma-air and s 10 mrad, beta-air and the calendar year limits s 10 mrad, gamma-air and 5 20 mrad, beta-air.

The limits are applicable separately to each generating station and are not combined site limits.

I The following equations shall be used to calculate the gamma-air and beta-air doses.

D, = 3.17E-08 X/Q a E (M

Q,)

(2.7) a i

Ds 3.17 E-08 X/Q

E (N a Q,)

(2.8)

=

i where:

I D,

= air dose due to gamma emissions for noble gas radionuclides (mrad).

D

= air dose due to beta emissions for noble gas radionuclides (mrad).

3 X/Q

= atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3).

Q,

= cumulative release of noble gas radionuclide i over the period ofinterest (uCi).

M,

= air dose factor due to gamma emission from noble gas radionuclide i (mrad /yr per uCi/m3, from Table 2-1.

N;

= air dose factor due to beta emissions from noble gas radionuclide i (mrad /yr per uCi/m3, Table 2-1).

3.17E-08

= conversion factor (yr/sec).

2.4.2 Simplified Dose Calculation for Noble Gases 4 I in lieu of the individual noble gas radionuclide dose assessment as presented

above, the following simplified dose calculation equations may be used for verifying compliance with the dose limits of Technical Specification 3.11.2.2 (Refer to Appendix C for the derivation and justification of this simplified method).

3.17E-08 D, =

X/Q

M,n

E Q, (2.9) 3.17E-08 D6=-

X/Q

N,n E Q, (2.10) a 0.50 I

13 I

i I

I Hope Creek ODCM Rev 15 where:

M,g

= 8.1E3, effective gamma-air dose factor (mrad /yr per uCi/m3).

N,g 8.5E3, efTective beta-air dose factor (mradlyr per uCi/m3).

=

Q,

= cumulative release for all noble gas radionuclides (uCi).

0.50

= conservatism factor to account for potential variability in the radionuclide distribution.

Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-3, may be used for the evaluation of the gamma-air and beta-air doses.

I 2.5 Radioiodine and Particulate Dose Calculations - 10 CFR 50 I

2.5.1 UNRESTRICTED AREA Dose - Radioiodine and Particulates I

In accordance with the requirements of Technical Specification 3.11.2.3, a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit 515 mrem to any organ. The following equation shall be used to evaluate the maximum organ dose due to release ofI-131,1-133, tritium and particulates with half-lives greater than 8 days:

D.op = 3.17E-08

W a SF E (R,op Q,)

(2.11) a I

p where.

D.op

= dose or dose commitment via all pathways p and age group a (as identified in Table 2-3) to organ o, including the total body (mrem).

W

= atmospheric dispersion parameter to the controlling location (s) as identified in I

Table 2-3.

X/Q

= atmospheric dispersion for inhalation pathway and H-3 dose contribution via other I

pathways (sec/m3).

D/Q

= atmospheric deposition for vegetation, milk and ground plane exposure pathways (1/m2).

I R,op

= dose factor for radionuclide i (mrem /yr per uCi/m3 or m2 - mrem /yr per uCi/sec) and organ o from Table 2-4 for each age group a and the applicable pathway p as identified in Table 2-3. Values for Rn,p were derived in accordance with the methods described in NUREG-0133.

Q,

= cumulative release over the period ofinterest for radionuclide i -- 1-131, I-133,11-3 or radioactive material in particulate form with half-life greater than 8 days (uCi).

Sf

= annual seasonal correction factor to account for fraction of the year that the p

applicable exposure pathway does not exist.

1)For milk and vegetation exposure pathways:

= A six month fresh vegetation and grazing season (May through October).

= 0.5 2)For inhalation and ground plane exposure pathways:

(I

= 1.0 l

14 l

Hope Creek ODCM Rev 15 I

For evaluating the maximum exposed individual, the infant age group is controlling for the milk pathway. Only the controlling age group as identified in Table 2-3 need be evaluated for compliance with Technical Specification 3.11.2.3.

2.5.2 Simplified Dose Calculation for Radioiodines and Particulates in lieu of the individual radionuclide (I-131,1-133 and partialates) dose assessment as

,g presented above, the following simplified dose calculation equation may be used for verifying 3

compliance with the dose limits of Technical Specification 3.11.2.3 (Refer to Appendix D for the derivation and justification of this simplified method).

I D.,

= 3.17E-08 a Wa SF,

RI-131 a E Q, (2.12) i where:

D.,

= maximum organ dose (mrem).

RI-131 = I-131 dose parameter for the thyroid for the identified controlling pathway.

= 1.05E12, infant thyroid dose parameter with the cow-milk pathway controlling (m2

- mrem /yr per uCi/sec).

W

= D/Q for radiciodine,2.87E-101/m2.

Q,

= cumulative release over the period ofinterest for radionuclide i -- I-131 or radioactive material in particulate form with half-life greater than 8 days (uCi).

I The location of exposure pathways and the maximum organ dose calculation may be based on the available pathways in the surrounding environment of Hope Creek as identified by the I

annual land-use census (Technical Specification 3.12.2).

Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-3.

2.6 Gaseous Elliuent Dose Proiection I

Technical Specification 3.11.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected doses in 31-days exceed:

- 0.2 mrad to air from gamma radiation, or 0.4 mrad to air from beta radiation, or

- 0.3 mrad to any organ of a MEMBER OF Tile PUBLIC The applicable gaseous processing systems for maintaining radioactive material releases ALARA are the Gaseous Radwaste Treatment System and Exhaust Treatment System as delineated in Figures 2-1 and 2-2.

I 15

Hope Creek ODCM Rev 15 Dose projection are performed at least once per 31-Jays by the following equations:

D,p

= (D, / d)

31d (2.13)

I Odp = (Dd / d)

31d (2.14)

D., = (Dm., / d)

31d (2.15) where:

D,p

= gamma air dose projection for current 31-day period (mrad).

D,

= gamma air dose to date for current calendar quarter as determined by equation (2.7)

I or (2.9) (mrad).

D,

= beta air dose projection for current 31-day period (mrad).

I D

= beta air dose to date for current calendar quarter as determined by equation (2.8) or 3

(2.10)(mrad).

D.,

= maximum organ dose p ojection for current 31-day period (mrem).

I D.,

= maximum organ dose to date for current calendar quarter as determined by equation (2.11) or (2.12)(mrem).

d

= number of days in current :alendar quarter at the end of the release.

31d

= the number ofdays of conc rn.

3 SPECIAL DOSE ANALYSIS I

.0 3.1 Doses Due to Activities Inside the SITE BOUNDARY In accordance with Technical Specification 6.9.1.7, the Radioactive Efiluent Release Report (RERR) submitted by May 1st of each year shall include an assessment of radiation doses from radioactive liquid and gaseous efiluents to MEMBERS OF THE PUBLIC due to their activities I

inside the SITE BOUNDARY.

The calculation methods as presented in Sections 2.4 and 2.5 may be used for determining the maximum potential dose to a MEMBER OF THE PUBLIC based on the parameters from Table 2-3 and 2-hours per visit per year. The default value for the meteorological dispersion data as I

presented in Table 2-3 may be used if current year meteorology is unavailable at the time of NRC reporting. However, a follow-up evaluation shall be performed when the data becomes available.

'I iI I

16 l

Hope Creek ODCM Rev 15 3.2 Total Dose to MEMBERS OF TIIE PUBLIC-40 CFR 190 The Radioactive Efiluent Release Report (RERR) submitted by May 1st of each year shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle courses (including dose contributions from efiluents and direct radiation from on-site sources) For the likely most exposed l

MEMBER OF T}IE PUBLIC in the vicinity of Artificial Island, the sources of exposure need only consider the Salem Generating station and the Hope Creek Generating Station: No other fuel cycle facilities contribute to the MEMBER OF TIIE PUBLIC dose for the Artificial Island vicinity.

The dose contribution from the operation of Salem Generating Stations will be estimated based on the methods as presented in the Salem Offsite Dose Calculation Manual (SGS ODCM).

As appropriate for demonstrating / evaluating compliance with the limits of Technical Specification 3.11.4 (40 CFR 190), the results of the ernironmental monitoring program may be used for providing data on actual measured levels of radioactive material in the actual pathways of exposure.

3.2.1 Efiluent Dose Calculations For purposes ofimplementing the surveillance requirements of Technical Specification 3/4.11.4 and the reporting requirements of 6.9.1.7 (RERR), dose calculations for the Hope Creek Generating Station may be performed using the calculation methods contained within the ODCM, j

the conservation controlling pathways and locations of Table 2-4 or the actual pathways and locations as identified by the land use census (Technical Specification 3/4.12.1) may be used.

Average annual meteorological dispersion parameters or meteorological conditions concurrent with the release period under evaluation may be used.

3.2.2 Direct Exposure Dose Determination Any potentially significant direct exposure contribution to off-site individual doses may be I

evaluated based on the results of the environmental measurements (e.g, TLD, ion chamber measurements) and/or by the use of a radiation transport and shielding calculation method. Only during a non-typical condition will there exist any potential for significant on-site sources at Hope I

Creek that would yield potentially significant oft-site doses (i.e.., in excess of 1 mrem per year to a MEMBER OF THE PUBLIC), that would require detailed evaluation for demonstrating compliance with 40 CFR 190. However, should a situation exist whereby the direct exposure contribution is potentially significant, on-site measurements, off-site measurements and/or calculational techniques will be used for determination ofdose for assessing 40 CFR 190 compliance.

I I

17 I

I Hope Creek ODCM Rev 15 I

4.0 RADIOLOGICAL, ENVIRONMENTAL MONITORING PROGRAM 4.1 Sampline Procram The operational phase of the Radiological Environmental Monitoring Program (REMP) is I

conducted in accordance with the requirements of Appendix A Technical Specification 312. The objectives of the program are:

- To determine whether any significant increases occur in the concentration of radionuclides in the critical pathways of exposure in the vicinity of Artificial Island;

- To determine if the operation of the Hope Creek Generating Station has resulted in any increase in the inventory oflong lived radionuclides in the environment;

- To detect any changes in the ambient gamma radiation levels; and I

- To verify that HCGS operations have no detrimental effects on the health and safety of the public or on the environment.

I The sampling requirements (type of samples *, collection frequency and analysis) and sample locations are presented in Appendix E.

NOTE: No public drinking water samples or irrigation water samples are taken as these pathways are not directly effected by liquid ellluents discharged from Hope Creek Generating Station.

I 4.2 Interlaboratory Comparison Program Technical Specification 312.3 requires analyses be performed on radioactive material supplied as part of an Interlaboratory Comparison. Participation in an approved Interlaboratory Comparison Program provides a check on the preciseness of measurements of radioactive materials I

in environmental samples. A summary of the Interlaboratory Comparison Program results will be provided in the Annual Radiological Environmental Operating Report pursuant to Technical Specifications 6 9.1.7.

I I

18 I

i Hope Creek ODCM Rev 15 I

FIGURE 1-1 LIQUID RADWASTE TREATMENT SYSTEM COOLING TOWER BASIN i

COLLECTOR I

TANKS (2)

EQUIPMENT EQUIPMENT EQUIPMENT I-DRAIN DRAIN DRAIN SAMPLE FILTER DEMIN TANKS (2) i SURGE I-TANK I

CONDENSATE I

STORAGE TANK FLOOR FLOOR I

DRAIN FLOOR FLOOR DRAIN CO'LLECTOR DRAIN DRAIN SAMPLE TANKS (2)

FILTER DEMIN TANKS (2)

CHEMICAL DECONTAMINATION VAPOR TO WASTE SOLUTION SOUTH PLANT I

TANK EVAPORATOR VENT BOTTOMS TO SOLID WASTE DETERGENT DETERGENT I

DRAIN DRAIN TANKS (2)

FILTER RE LOG: RE = EFFLUENT RADIATION MONITOR RE 4861 = LIQUID RADWASTE MONITOR 8817 8817 = COOLING TOWER BLOWDOWN MONITOR To Delaware River I

I 19 i

I t

i, d'

j Hope Creek ODCM Rev 15 i

!E FIGURE 1-2 l3 SOLID RADWASTE PROCESSING SYSTEM 1

I i

l a

I I

i I i

4lI l

d i

lI 4

i i

4 j

i I i

i i

l 4

4 A

i

! I I

I 20 I

I Hope Creek ODCM Rev 15 TABLE l-1 PARAMETERS FOR LIQUID ALARM SETPOINT DETERMINATION Actual Default Parameter Value Value Units Comments MPCe Calc 7.92E-5

uCi/ml Calculated for each batch to be released MPC 1-131 3.0E-07 N/A uCi/ml Taken from 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F)

Ci Measured N/A uCi/mi Taken from gamma spectral analysis ofliquid effluent

MPC, Measured N/A uci/ml Taken from 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F)

CTBD Measured 12000 gpm Cooling tower blowdown discharge RR Measured 176 gpm or Determined prior to release, release rate can be adjusted for Technical 1300 gpm(CST)

Specification compliance SP A)

RE4861 Calc 2.70E-03 uCi/ml Default alarm setpoints; more conservative values may be used as deemed appropriate and desirable RE3817 Calc 3.96E-05 uCi/ml for ensuring regulatory compliance and for maintaining releases ALARA B)

RE4861 Calc 3.66E-04 uCi/mi These setpoints are for condensate RE8817 Calc 3.96E-05 uCi/ml

See Appendix A for basis I

21 I

Hope Creek ODCM Rev 15 TABLE l-2 I

SITE IELATED INGESTION DOSE COMMITMENT FACTOR, Aw (FISH AND INVERTEBRATE CONSUMPTION)

(mrenVhr per uCi/ml)

I Nuclide 2.82E-l 182E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 C-14 1.45E+4 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4 57E-1 4.57E-1 I

P-32 4.69E+ 6 2.91 E+ 5 1.81 E+5 5.27E+5 Cr-51 5.58E+0 3.34E+0 1.23 E+0 7.40E+0 1.40E+3 Mn-54 7.06E+3 1.35E+3 2.10E+3 2.16E+4 Mn-56 1.78E+2 3.15E+ 1 2.26E+2 5.67E+3 Fe-55

5. l l E+4 3.53E+4 8.23 E+3 1.97E+4 2.03 E+4 Fe-59 8.06E+4 1.90E+5 7.27E+4 5.30E+4 6.32E+5 Co-57 1.42E+2 2.36E+2 3.59E+3 Co-58 I

Co-60 6.03 E+2 1.35E+3 1.22E+4 1.73 E+3 3.82E+3 3.25E+4 Ni-63 4.96E+4 3.44 E+3 1.67E+3 7.18E+2 Ni-65 2.02E+2 2.62E+ 1 1.20E+1 6.65E+2 Cu-64 2.14E+2 1.01E+2 5.40E+2 1.83 E+4 Zn-65 1.61 E+5 5 13E+5 2 32E+5 3.43 E+5 3 231D 5 I

Zn-69 4.07E+0 3.43 E+2 6.56E+2 4.56E+ 1 4.26E+2 9 85E+1 Br-82 4.67E+0 Br-83 7.25 E-2 1.04E-1 Br-84 I

9.39E-2 7.37E-7 Br-85 3.86E-3 Rb-86 6.24E+2 2.91 E+2 1.23 E+2 Rb-88 1.79E+0 9.49E-1 2.47E-11 Rb-89 1.19E+0 8.34E-l 6.89E-14 Sr-89 4.99E+3 1.43 E+2 8.00E+2 3

Sr-90 1.23E+5 3.01 E+4 3.55E+3 Sr-91 9.18E+ 1 3.71 E+0 4.37E+2 Sr-92 3.48E+1 1.51E+0 6.90E+2 Y-90 6 06E+0 1.63 E-1 6.42E+4 Y-91m 5.73 E-2 2.22E-3 1.68 E-1 Y-91 8 88E+1 2.37E+0 4.89E+4 Y-92 5.32E-1 1.56E-2 9.32E+3 Y-93 1.69E+0 4.66E-2 5.35E+4 Zr-95 1.59E+1 5.11 E+0 3.46E+0 8.02E+0 1.62E+4 Zr-97 8.81 E-1 1.78E-1 8.13E-2 2.68E-1 5.51 E+4 Nb-95 4.47E+2 2.49E+2 1.34E+2 2.46E+2 1.51 E+6 Nb-97 3.75E+0 9.49E-1 3.46E-1 1.llE+0 3.50E+3 Mo-99 1.28E+2 2.43 E+ 1 2.89E+2 2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+1 I

Tc-101 1.33E-2 1.92E-2 1.88E-1 3.46E-1 9.81 E-3 5.77E-14 As-76 4.38E+2 1.16E+3 5.14E+3 3.42E+2 1.39E+3 3.58E+2 4.30E+4 22

Hope Creek ODCM Rev 15 I

TABLE l-2 (cont'd)

SITE RELATED INGESTION DOSE COMMITMENT FACTOR, A;o l

(FISH AND INVERTEBRATE CONSUMPTION)

(mrem /hr per uCi/ml)

I Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Ru-103 1.07E+2 4.60E+1 4.07E+2 1.25E+4 Ru-105 8.89E+0 3.51 E+0 1.15 E+2 5.44E+3 I

Ru-106 1.59E+3 2.01 E+2 3.06E+3 1.03 E+5 Rh-103m Rh-106 Ag.110m 1.56E+3 1.45E+3 8.60E+2 2.85E+3 5.91 E+5 Sb-124 2.77E+2 5.23 E+0 1.10E+2 6.71 E-1 2.15 E+2 7.86E+3 Sb-125 1.77E+2 1.98E+0 4.21 E+ 1 1.80E-1 1.36E+2 1.95E+3 Te-125m 2.17E+2 7.86E+ 1 2.91 E+1 6.52E+1 8.82E+2 8.66E+2 Te-127m 5.48E+2 1.96E+2 6.68E+1 1.40E+2 2.23E+3 1.84E+3 I

Te-127 8.90E+0 3.20E+0 1.93 E+0 6.60E+0 3.63 E+1 7.03 E+2 Te-129m 9.31 E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 4.69E+3 Te-129 2.54E+0 9.55E-1 6.19E-l 1.95E+0 1.07E+1 1.92E+0 Te-131m 1.40E+2 6.85E+1 5.71 E+1 1.08E+2 6.94E+2 6.80E+3 Te-131 1.59E+0 6.66E-1 5.03 E-1 1.31 E+0 6.99E+0 2.26E-1 Te-132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 6.24E+3 I

I-130 3.96E+1 1.17E+2 4.61 E+1 9.91 E+3 1.82E+2 1.01E+2 I-131

' 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 8.23E+1 1-132 1.06E+1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 5.35E+0 I-133 7.45E+1 1.30E+2 3.95E+1 1.90E+4 2.26E+2 1.16E+2 I-134 5.56E+0 1.51 E+1 5.40E+0 2.62E+2 2.40E+ 1 1.32E-2 I-135 2.32E+1 6.08E+1 2.24E+ 1 4.01 E+3 9.75E+ 1 6.87E+ 1 I

Cs-134 6.84E+3 1.63E+4 1.33E+4 5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21 E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+0 1.20E+ 1 5.94E+0 8.81 E+0 8.70E-1 5.12E-5 Ba-139 7.85E+0 5.59E-3 2.30E-1 5.23 E-3 3.17E-3 1.39E+1 I

Ba-140 1.64E+3 2.06E+0 1.08E+2 7.02E-1 1.18E+0 3.38E+3 Ba-141 3.81 E+0 2.88E-3 1.29E-1 2.68E-3 1.63E-3 1.80E-9 I

'Ba-142 172E+0 1.77E-3 1.08E-1 1.50E-3 1.00E-3 2.43E-18 12-140 1.57E+0 7 94E-1 2.10E-1 5.83E+4 a-141 8.06E-2 3.67E-2 9.13E-3 2.68E+2 te-141 3.43 E+0 2.32E+0 2.63 E-1 1.08E+0 8.86E+3 Ce-143 6 04E-1 4.46E+2 4.94E-2 1.97E-1 1.67E+4 Ce-144 1.79E+2 7.47E+ 1 9.59E+0 4.43E+1 6.04E+4 Pr-143 5.79E+0 2.32E+0 2.87E-1 1.34 E+0 2.54E*4 I

Pr-144 1.90E-2 7.87E-3 9.64E-4 4.44E-3 2.73E 9 Nd-147 3.96E+0 4.58E+0 2.74E-1 2 68E+0 2.20E+4 W-187 9.16E+0 7.66E+0 2.68E+0 2.51 E+3 Np-239 3.53 E-2 3.47E-3 1.91 E-3 1.08E-2

7. I 1 E+2 23

I I

Hope Creek ODCM Rev 15 TABLE l-3 BIOACCUMULATION FACTORS (pCi/kg per pCi/ liter)*

ELEMENT SALTWATER F; JU SALTWATER INVERTEBRATES H

9.0E-01 9.3E-01 C

1.8E+03 1.4E+03 Na 6.7E-02 1.9E-01 I

P 3.0E+03 3.0E+04 Cr 4.0E402 2.0E+03 Mn 5.5E+02 4.0E+02 I

Fe 3.0E+03 2.0E+04 Co 1.0E+02 1.0E403 Ni 1.0E+02 2.5E+02 I

Cu 6.7E+02 1.7E+03 Zn 2.0E+03 5.0E404 Br 1.5E-02 3,1 E+00 Rb 8.3 E+00 1.7E+01 I

Sr 2.0E+00 2.0E+01 Y

2.5E+01 1.0E+03 Zr 2.0E+02 8.0E+01 Nb 3.0E+04 1.0E+02 Mo 1.0E+01 1.0E+01 Tc 1.0E+01 5.0E+01

'E Ru 3.0E+00 1.0E+03

,3 Rh 1.0E401 2.0E+03 l

Ag 3.3E+03 3.3E+03 Sb 4.0E401 5.4E+00 Te 1.0E+01 L0E402 1

1 1.0E+01 5.0E+01 Cs 4.0E401 2.5E+01

,l Ba 1.0E+01 1.0E402 m

La 2.5E+01 1.0E+03 Ce 1.0E+01 6.0E+02

'3 Pr 2.5E+01 1.0E+03 l3 Nd 2.5E+01 1.0E+03 i

W 3.0E+0) 3.0E+01 Np 1.0E+01 1.0E+01 As 3.3 E+02 3.3E+02 Values in this table are taken from Regulatory Guide 1.109 except for phosphorus (fish) which is o

I adapted from NUREG/CR-1336 and silver, arsenic and antimony which are taken from UCRL 50564, Rev.1. October 1972.

I 24

I I

Hope Creek ODCM Rev 15 FIGURE 2-1 GASEOUS RADWASTE TREATMENT SYSTEM Main or

]

Auxiliary Steam SJ12 r------------

I Offgas j

i Preheater Recombiner Recombiner I

ll Condenser l

l Condenser -

l l

Offgas Typical of 2 Recombiner Packages L_

_ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _J Holdup Pipes l

Cooler Reheater Guard l

Condenser Bed l

l I

i To North l

HEPA Filter Absorber Plant Vent Train l

{

(Figure 2-2) l Ambient Charcoal S t _ _ _ _ _ _ _ _ _ystem I

I I

I 25

I

.I Hope Creek ODCM Rev 15 I

FIGURE 2-2 VENTILATION EXHAUST TREATMENT SYSTEM RE Gaseous Radwaste Treatment System 48h3B (from Figure 2-1)

North Plant Vent I

Untreated Ventilation Air Sources

) I Radwaste Decon.

Evaporator l I Reactor Building R

H Purge Air (Typ. of 3)

RE Auxiliary Building 48h5B Radwaste Area R

H South Ventilation Plant I

(Typ. of 3)

Vent Condensate Demineralizer Room Air Pipe Chase Air R

H C

H Feedwater Heater Room Air Untreated Ventilation Air Sources RE (Recirculation) 4811A Reactor I

Building Air H

C H

FRVS System (Typ. of 6)

(Typ. of 2)

Vent Legend:

R=

Roughing Filter C = Charcoal Filter H-HEPA Filter RE = Effluent Radiation Monitor a

I 26 I

I I

Hope Creek ODCM Rev 15 DOSE FACTORS FOR NOBLE GASES Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Ki Li Mi Ni (mrem /yr per (mrem /yr per (mradlyr per (mrad /yr per Radionuclide uCi/m3) uCi/m3J uCi/m3) uCi/m3 Kr-83m 7.56E-02 I

1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03 E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93 E+03 Kr 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83 E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.1 IE+03 Xc-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 312E+03 7.1 lE+02 3.36E+03 7.39E+02 I

Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xc-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8 83E+03 4.13 E+03 9.21 E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 I

27 I

I

I Hope Creek O M Rev 15 I

TABLE 2-2 PARAMETERS FOR GASEOUS ALARM SETPOINT DETERMINATION HOPE CREEK Actual Default Parameter Value Value Units Comments X/Q Calculated 2.67E-6 sec/m3 From FSAR Table 2.3-31, 0.5 mile, N I

VF (NPV)

Measured 41900 fl'/ min Maximum Operation VF (SPV)

Measured 440,180 fl'/ min Maximum Operation VF (FRVS)

Measured 9000 ft'/ min Maximum Operation I

AF (NPV)

Coordinated 0.2 Unitiess Administrative with SGS allocation factor to ensure releases do not exceed AF (SPV) 0.2 Unitiess release rate limit AF (FRVS) 0.I Unitiess 3

C Measured N/A uCi/cm i

K Nuclide N/A mrem /yr Table 2-1 4

Specific per uCi/m' L Nuclide N/A mrem /yr Table 2-1 i

Specific per uCi/m')

M, Nuclide N/A mrad /yr Table 2-1 I

Specific per uCi/m 3

SP NPV Calculated 2.43E-4 uCi/cc Default alarm Setpoints, I:

SPV Calculated 2.31 E-5 uCi/cc more conservative values FRVS Calculated 5.65E-4 uCi/cc may be used as deemed appropriate for ensuring ALARA & regulatory i

compliance I

I 2

I

I Hope Creek ODChi Rev 15 TABLE 2-3 CONTROLLING LOCATIONS, PATHWAYS AND ATMOSPHERIC DISPERSION FOR DOSE CALCULATIONS

I Controlling X/Q D/Q Tech Sp_eg Location Pathway (s)

Age Group Lsec/m3)

(1/m2) 3 11.2. Ia Site Boundary Noble Gases N/A 2.67E-06 N/A 0.5 Mile, N direct exposure

3. I 1.2. Ib Site Boundary Inhalation Child 2.67E-06 N/A I

0.5 Mile, N 3.11.2.2 Site Boundary Gamma-Air N/A 2 67E-06 N/A I

0.5 Mile, N Beta-Air I

3.11.2.3 Residence /

Milk, ground Infant 7.2E-08 2.87E-10 Dairy - 4.9 plane and Miles, W inhalation I

I The identified controlling locations, pathways and atmospheric dispersion are from the Artificial Island Radiological Monitoring Program and the Hope Creek FSAR.

I I

I

I Ilope Creek ODCM Rev 15 I

Table 2-4 Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - ADULT (mrem /yr per uCi/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body I

H-3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 C-14 1.82E+4 3.41 E+3 3.41E+3 3.41 E+3 3.41 E+3 3.41 E+3 3.41 E+3 P-32 1.32E+6 7.71 E+4 8.64E+4 5.01E+4 l

Cr-51 5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.00E+2 Mn-54 3.96E+4 9.84E+3 1.40E+6 7.74E+4 6.30E+3 Fe-55 2.46E+4 1.70E+4 7.21 E+4 6.03 E+3 3.94E+3 Fe-59 1.I8E+4 2.78E+4 1.02E+6 1.88E+5 1.06E+4 Co-57 6.92E+2 3.70E+5 3.14E+4 6.71 E+2 Co-58 I

1.58E+3 9.28E+5 1.06E+5 2.07E+3 Co-60 1.15E+4 5.97E+6 2.85E+5 1.48E+4 Ni-63 4.32E+5 3.14 E+4 1.78E+5 1.34E+4 1.45E+4 Zn-65 3.24E+4 1.03 E+5 6.90E+4 8.64E+5 5.34E+4 4.66E+4 I

Rb-86 1.35E+5 1.66E+4 5.90E+4 Sr-89 3.04E+5 1.40E+6 3.50E+5 8.72E+3 I

Sr-90 9.92E+ 7 9 60E+6 7.22E+5 6.10E+6 Y-91' 4.62E+5 1.70E+6 3.85E+5 1.24E+4 Zr-95 1.07E*5 3.44E+4 5.42E+4 1.77E+6 1.50E+5 2.33 E+4 I

Nb-95 1.41 E+4 7.82E+3 7.74E+3 5.05E+5 1.04E+5 4 21E+3 Ru-103 1.53 E+3 5.83 E+3 5.05E+5 1.10E+5 6.58E+2 Ru-106 6.91 E+4 1.34E+5 9.36E+6 9.12E+5 8.72E+3 I

Ag-110m 1.08E+4 1.00E+4 1.97E+4 4.63 E+6 3.02E+5 5.94E+3 Sb-124 3 12E+4 5.89E+2 7.55E+1 2.48E+6 4.06E+5 1.24E+4 Sb-125 14E+4 5.95E+2 5.40E+1 1.74E+6 1.01 E+5 1.26E+4 Te-125m

-.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E+5 1.57E+3 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83 E+5 1.58E+3 I-131 2.52E+4 3.58E+4 1.19E+7 6.13 E+4 6.28E+3 2.05E+4 Cs-134 3.73E+5 8.48E+5 2.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-136 3.90E+4 1.46E+5 8.56E+4 1.20E+4 1.17E+4 1.10E+5 I

Cs-137 4.78E+5 6.21 E+5 2.22E+5 7.52E+4 8.40E+3 4.28E+5 Ba-140 3.90E+4 4.96E+ 1 1.67E+ 1 1.27E+6 2.18E+5 2.57E+3 I

Ce-141 1.99E+4 1.35E+4 6.26E+3 3.62E+5 1.20E+5 1.53 E+3 Ce-144 3.43 E+6 1.43E+6 8.48E+5 7.78E+6 8.16E+5 1.84E+5 Pr-143 9.36E+3 3 75F+3 2.16E+3 2.81 E+5 2.00E+5 4.64E+2 2

Nd-147 5.27E+3 6.10E+3 3.56E+3 2.21E+5 1.73 E+5 3.65E+2 30 I

I Hope Creek ODCM Rev 15 I

Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - TEENAGER (mrem /yr per uCi/m3)

Nuclide Bone Liver Ihyroid Kidney latng GI-LLI T Body I

'.63 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 L-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 P-32 1.89E+6 1.10E+5 9.28 E+4 7.16E+4 l

Cr-51 7.50E+1 3.07E+ 1 210E+4 3.00E+3 1.35E+2 Mn-54 5.1 l E+4 1.27E+4 1.98E+6 6.68E+4 8.40E+3 Fe-55 3.34E+4 2.38E+4 1.24E+5 6.39E+3 5.54E+3 Fe-59 1.59E+4 3.70E+4 1.53 E+6 1.78E+5 1.43E+4 Co-57 6.92E+2 5.86E+5 3.14E+4 9.20E+2 Co-58 2.07E+3 1.34E+6 9.52E+4 2.78E+3 Co-60 1.51 E+4 8.72E+6 2.59E+5 1.98E+4 Ni-63 5.80E+5 4.34E+4 3.07E+5 1.42E+4 1.98E+4 Zn-65 3.86E+4 1.34E+5 8.64E+4 1.24E+6 4.66E+4 6.24E+4 I

Rb-86 1.90E+5 1.77E+4 8.40E+4 Sr-89 4.34E+5 2.42E+6 3.71E+5 1.25E+4 I

Sr-90 1.08E+8 1.65E+7 7.65E+5 6.68E+6 Y-91' 6.61 E+5 2 94E+6 4.09E+5 1.77E+4 Zr-95 1.46E+5 4.58E+4 6.74E+4 2.69E+6 1.49E+5 3.15E+4 I

Nb-95 1.86E+4 1.03 E+4 1.00E+4 7.51 E+5 9.68E+4 5.66E+3 Ru-103 2.10E+3 7.43E+3 7.83E+5 1.09E+5 8.96E+2 Ru-106 9.84E+4 1.90E+5 1.61 E+7 9.60E+5 1.24E+4 I

Ag-110m 1.38E+4 1.31 E+4 2.50E+4 6.75E+6 2.73 E+5 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+ 1 3.85E+6 3.98E+5 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 2.74E+6 9.92E+4 1.72E+4 Te-125m 4.88E+3 2.24E+3 1.40E+3 5.36E+5 7.50E+4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2.25E+3 I-131 3.54E+4 4.91 E+4 1.46E+7 8.40E+4 6.49E+3 2.64E+4 Cs-134 5.02E+5 1.13 E+6 3.75E+5 1.46E+5 9.76E+3 5.49E+5 Cs-136 5.15E+4 1.94E+5 1.10E+5 1.78E+4 1.09E+4 1.37E+5 I

Cs-137 6.70E+5 8.48E+5 3.04E+5 1.21 E+5 8.48E+3 311E+5 Ba-140 5.47E+4 6.70E+1 2.2bE+1 2.03 E+6 2.29E+5 3.52E+3

,g Ce-141 2.84 E+4 1.90E+4 8.88E+3 6.14E+5 1.26E+5 2.17E+3 5

Ce-144 4.89E+6 2.02E+6 1.21E+6 1.34E+7 8.64E+5 2.62E+5 Pr-143 1.34E+4 5.31 E+3 3.09E+3 4.83E+5 2.14E+5 6.62E+2 Nd-147 7.86E+3 8.56E+3 5.02E+3 3.72E+5 1.82E+5 5.13E+2 i

I

I E

Hope Creek ODCM Rev 15 I

Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - CHILD (mrem /yr per uCi/m3)

Nuclide Bone Liver Thyroid Kidney Litng GI-LLI T, Body H-3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73 E+3 6.73 E+3 6.73 E+3 6.73 E+3 6.73E+3 6.73E+3 P-32 2.60E+6 1.14E+5 4.22E+4 9.88E+4 Cr-51 8.55 E+ 1 2.43 E+ 1 1.70E+4 1.08E+3 1.54E+2 Mn-54 4.29E+4 1.00E+4 1.58E+6 2.29E+4 9.51 E+3 Fe-55 4.74E+4 2.52E+4 1.llE+5 2.87E+3 7.77E+3 Fe-59 2.07E+4 3.34E+4 1.27E+6 7.07E+4 1.67E+4 Co-57 9.03 E+2 5.07E+5 1.32E+4 1.07E+3 Co-58 1.77E+3 1.llE+6 3.44E+4 3.16E+3 I

Co-60 1.31E+4 7.07E+6 9.62E+4 2.26E+4 Ni-63 8.21E+5 4.63 E+4 2.75E+5 6.33 E+3 2.80E+4 Zn-65 4.26E+4 1.13 E+5 7.14E+4 9.95 E+5 1.63E+4 7.03 E+4 I

Rb-86 1.98E+5 7.99E+3 1.14E+5 Sr-89 5.99E+5 2.16E+6 1.67E+5 1.72E+4 I

Sr-90 1.01 E+8 1.48E+7 3.43 E+5 6.44E+6 Y-9i' 9.14E+5 2.63E+6 1.84E+5 2.44E+4 Zr-95 1.90E+5 4.18E+4 5.96E+4 2.23 E+6

6. l l E+4 3.70E+4 I

Nb-95 2.35E+4 9.18E+3 8.62E+3 6.14E+5 3.70E+4 6.55E+3 Ru-103 2.79E+3 7.03 E+3 6.62E+5 4.48E+4 1.07E+3 Ru-106 1.36E+5 1.84E+5 1.43E+7 4.29E+5 1.69E+4 Ag-110m 1.69E+4 1.14E+4 2.12E+4 5.48E+6 1.00E+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 3.24E+6 1.64E+5 2.00E+4 Sb-125 9.8d E+4 7.59E+2 9.10E+1 2.32E+6 4.03 E+4 2.07E+4 Te-125m 6.73 E+3 2.33 E+3 1.92E+3 4.77E+5 3.38E+4 9.14E+2 Te-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1.48E+6 7.14E+4 3.02E+3 Te-129m 1.92E+4 6.85E+3 6.33 E+3 5.03 E+4 1,76E+6 1.82E+5 3.04 E+3 I-131 4.81 E+4 4.81E+4 1.62E+7 7.88E+4 2.84E+3 2.73 E+4 Cs-134 6.51E+5 1.01 E+6 3.30E+5 1.21 E+5 3.85E+3 2.25E+5 Cs-136 6.51 E+4 1.71E+5 9.55E+4 1.45E+4 418E+3 1.16E+5 I

Cs-137 9.07E+5 8.25E+5 2.82E+5 1.04E+5 3.62E+3 1.28E+5 Ba-140 7.40E+4 6.48 E+1

2. l l E+1 1.74E46 1.02E+5 4.33E+3 I

Ce-141 3.92E+4 1.95E+4 8.55E+3 5.44E+5 5.66E+4 2.90E+3 Ce-144 6.77E+6 2.12E+6 1.17E+6 1.20E+7 3.89E+5 3.61E+5 i

Pr-143 1.85E+4 5.55E+3 3.00E+3 4.33E+5 9.73 E+4 914E+2 Nd-147 1.08E+4 8.73E+3 4.81 E+3 3.28E+5 8.21 E+4 6.81 E+2 32

I Ilope Creek ODCM Rev 15 I

Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - INFANT (mrem /yr per uCi/m3)

Nucjide Bone Liver Thyroid Kidney Lung GI-LLI T Body 11-3 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 C-14 2 65E44 5.31 E+3 5.31 E+3 5.31 E+3 5.31 E+3 5.31E+3 5.31 E+3 P-32 2.03E+6 1.12E+5 1.61E+4 7.74 E+4

~

Cr-51 5.75 E+ 1 1.32E+1 1.28E+4 3.57E+2 8.95E+1 Mn-54 2.53E+4 4.98E+3 1,00E+6 7.06E+3 4.98E+3 Fe-55 1.97E+4 1.I7E+4 8.69E+4 1.09E+3 3.33E+3 '

Fe-59 1.36E+4 2.35E+4 1.02E+6 2.48E+4 9.48E+3 Co-57 6.51 E+2 3.79E+5 4.86E+3 6.41 E+2 Co-58 1.22E+3 7.77E+5 1.I1E+4 1.82E+3 I

Co-60 8.02E+3 4.51 E+6 3.19E+4 1.I8E+4 Ni-63 3.39E+5 2.04E+4 2.09E+5 2.42E+3 1.16E+4 Zn-65 1.93 E+4 6.26E+4 3.25E+4 6.47E+5 5.14E+4

3. l lE+4 I

Rb-86 1.90E+5 3.04E+3 8.82E+4 Sr-89 3.98E+5 2.03 E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 1.12E+7 1.31E+5 2.59E+6 Y-91 '

5.88E+5 2.45E+6 7.03 E+4 1.57E+4 Zr-95 1.15 E+5 2.79E+4

3. l l E+d 1.75 E+6 2.17E+4 2.03 E+4 I

Nb-95 1.57E+4 6.43E+3 4.72E+3 4.79E+5 1.27E+4 3.78E+3 Ru-103 2.02E+3 4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-106 8.68E+4 1.07E+5 1.16E+7 1.64 E+5 1.09E+4 Ag-l10m 9.98E+3 7.22E+3 1.09E+4 3.67E+6 3.30E+4 5.00E+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 2 65E+6 5.91E+4 1.20E+4 Sb-125 5.17E+4 4.77E+2 6.23 E+ 1 1.64E a 1.47E+4 1.09E+4 Te-125m 4.76E+3 1.99E+3 1.62E+3 4.47E+5 1.29E+4 6.58E+2 Te-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31 E+6 2.73E+4 2.07E+3 Te-129m 1.41E+4 6.09E+3 5.47E+3 3 18E+4 1.68E+6 6.90E+4 2 23E+3 1-131 3.79E+4 4.44E+4 1.48E+7 5.18E+4 1.06E+3 1.96E+4 Cs-134 3.96E+5 7.03 E+5 1.90E+5 7.97E+4 1.33E+3 7.45E+4 Cs-136 4.83 E+4 1.35E+5 5.64E+4 1.18E+4 1.43 E+3 5.29E+4 I

Cs-137 5.49E+5 6.12E+5 1.72E+5 7.13E+4 1.33 E+3 4.55E+4 Ba-140 5.60E+4 5.60E+1 1.34E+1 1.60E+6 3.84E+4 2.90E+3 Ce-141 2.77E+4 1.67E+4 5.25 E+3 5.17E+5 2.16E+4 1.99E+3 Ce 144 3.19E+6 1.21 E+6 5.38E+5 9.84E+6 1.48E+5 1.76E+5 Pr-143 1.40E+4 5.24E+3 1.97E+3 4.33E+5 3.72E+4 6.99E+2 Nd-147 7.94E+3 8 13E+3 3 15E+3 3.22E+5 3.12E+4 5.00E+2 I

3 I

llope Creek ODCM Rev 15 I

Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - ADULT I

(mrem /yr per uCi/m3) for H-3 and C-14 (m2

mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney

. Lung GI-LLI T. Body H-3 7.63 E+2 7.63 E+2 7.63 E+2 7.63 E+2 7.63 E+2 7.63E+2 C-14 3.63 E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 P-32 1.71E+10 1.06E+9 1.92E+9 6.60E+8 Cr-51 1.71E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Mn-54 8.40E+6 2.50E+6 2.57E+7 1.60E+6 Fe-55 2.51 E+7 1.73E+7 9.67E+6 9.95E+6 4.04E+6 Fe-59 2.98E+7 7.00E+7 1.95E+7 2.33E+8 2.68E+7 Co-57 1.28E+6 3.25E+7 2.13 E+6 I

Co-58 4.72E+6 9.57E+7 1.06E+7 Co-60 1.64E+7 3.08E+8 3.62E+7 Ni-63 6.73 E+9 4.66E+8 9.73E+7 2.26E+8 I

Zn-65 1.37E+9 4.36E+9 2.92E+9 2.75E+9 1.97E+9 Rb-86 2.59E+9

5. l lE+8 1.21 E+9 Sr-89 1.45E+9 2.33 E+8 4.16E+7 Sr-90' 4.68E+10 1.35E+9 1.15E+10 Y-91 8.60E+3 4.73E+6 2.30E+2 Zr-95 9.46E+2 3.03 E+2 4.76E+2 9.62E+5 2.05E+2 Nb-95 8.25E+4 4.59E+4 4.54E+4 2.79E+8 2.47E+4 Ru-103 1.02E+3 3.89E+3 1.19E+5 4.39E+2 Ru-106 2 04E+4 3.94E+4 1.32E+6 2.58E+3 Ag-110m 5.83 E+7 5.39E+7 1.06E+8 2.20E+10 3.20E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 2.00E+7 7 31E+8 1.02E+7 Sb-125 2.04E+7 2.28E+5 2.08E+4 1.58E+7

.25E+8 4.86E+6 Te-125m 1.63 E+7 5.90E+6 4.90E+6 6.63 E+7 6.50E+7 2.18E+6 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 1.54E+8 5.58E+6 Te-129m 6.04E+7 2 25E+7 2.086+7 2.52E+8 3.04E+8 9.57E+6 I-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 1.12E+8 2.43 E+8 Cs-134 5.65E+9 1.34E+10 4.35E+9 1.44E+9 2.35E+8 1.10E+10 Cs-136 2.6] E+8 1.03E+9 5.74 E+8 7.87E+7 1.17E+8 7.42E+8 Cs-137 7.38E+9 1.01E+10 3.43E6 1.14E+9 1.95E+8 6.61 E+9 Ba-140 2.69E+7 3.38E+4 1.15E+4 1.93E+4 5.54E+7 1.76E+6 I

Ce-141 4.84E+3 3.27E+3 1.52E+3 1.25E+7 3.71 E+2 Ce-144 3.58E+5 1.50E+5 8.87E+4 1.21E+8 1.92E+4 I

Pr-143 1.59E+2 6.37E+ 1 3.68E+1 6.96E+5 7.88E+0 Nd-147 9.42E+1 1.09E+2 6.37E+1 5.23E+5 6.52E+0 34

1 I

Hope Creek ODCM Rev 15 I

Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - TEENAGER I

(mrem /yr per uCi/m3) for H-3 and C-14 j

(m2

mrem /yr per uCi/sec) for others I

Nuclide Bone Liver Thyroid Kidn.ey Lu_ng GI-LLI T. Body H-3 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 i

C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 i

P-32 3.15E+10 1.95E+9 2.65E+9 1.22E+9

)

Cr-51 2.78E+4 1.10E+4 7.13 E+4 8.40E+6 5.00E+4 Mn-54 1.40E+7 4.17E+6 2.87E+7 2.78E+6 Fe-55 4.45E+7 3.16E+7 2 00E+7 1.37E+7 7.36E+6 Fe-59 5.20E+7 1.21E+8 3.82E+7 2.87E+8 4.68E+7 Co-57 2.25E+6 4.19E+7 3.76E+6 Co-58 7.95E+6 1.10E+8 1.83 E+7 I

Co-60 2.78E+7 3.62E+8 6.26E+7

{

Ni-63 1.18E+10 8.35 E+8 1.33E+8 4.01 E+8 Zn-65 2.1 I E+9 7.31 E+9 4.68E+9 3.10E+9 3.41 E+9 Rb-86 4.73E+9 7.00E+8 2.22E+9 Sr-89 2.67E+9 3.18E+8 7.66E+7 Sr-90' 9.92E+7 9.60E+6 7.22E+5 6.10E46 Y-91 1.58E+4 6.48E46 4.24E+2 Zr-95 1.65E+3 5.22E+2 7.67E+2 1.20E+6 3.59E+2 Nb-95 1.41 E+5 7.80E+4 7.57E+4 3.34Et8 4.30E+4 I

Ru-103 1.81E+3 6.40E+3 1.52E+5 7.75E+2 i

Ru-106 3.75E+4 7.23E+4 1.80E+6 4.73 E+3 j

Ag-llom 9.63 E+7

9. l l E+7 1.74E+8 2.56E+10 5.54E+7 I

Sb-124 4.59E+7 8.46E+5 1.04E+5 4.01 E+7 9.25E+8 1.79E+7 i

Sb-125 3.65E+7 3.99E+5 3.49E+4 3.21 E+7 2.84E+8 8.54E+6 Te-125m 3.00E+7 1.08E+7 8.39E+6 8.86E+7 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01 E+7 3.42E+8 2.10E+ 8 1.00E+7 Te-129m 1.llE+8 4.10E+7 3.57E+7 4.62E+8 4.15E+8 1.75E+7 I-131 5.38E+8 7.53 E+8 2.20E+11 1.30E+9 1.49E+8 4.04E+ 8 Cs-134 9.81 E+9 2.31E+10 7.34E+9 180E+9 2.87E+8 1.07E+10 Cs-136 4.45E+8 1.75E+9 9.53 E+8 1.50E+8 1.41E+8 1.18E+9 Cs-137 1.34E+ 10 1.78E+10 6.06E+9 2.35E+9 2.53E+8 6.20E+9 Ba-140 4.85E+7 5.95E+4 2.02E+4 4.00E+4 7.49E+7 3.13E+6 II Ce-141 8.87E+3 1.35E+4 2.79E+3 1.69E+7 6.81 E+2 Ce-144 6.58E+5 2.72E+5 1.63E+5 1.66E+8 3.54E+4 I

Pr-143 2.92E+2 1.17E+2 6 77E+1 9.61 E+5 1.45E+1 Nd-147 1.81E+2 1.97E+2 1.16E+2

7. l l E+5 1.18E+1 35

Hope Creek ODCM Rev 15 I

Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - CHILD (mrem /yr per uCi/m3) for H-3 and C-14 (m2

mrem /yr per uCi/sec) for others I

Nuclide Bone L.iver Thyroid Kidney Lung GI-LLI T Bod.y H-3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 P-32 7.77E+ 10 3.64E+9

2. I SE+9 3.00E+9 Cr-51 5.66E+4 1.55E*4 1.03 E+5 5.41E+6 1.02E+5 Mn-54 2.09E+7 5.87E+6 1.76E+7 5.58E+6 Fe-55 1.12E+8 5.93 E+7 3.35E+7 1.10E+7 1.84 E+7 Fe-59 1.20E+8 1.95E+8 5.65E+7 2.03E+8 9.71 E+7 Co-57 3.84E+6 3.14E+7 7.77E+ 6 Co-58 1.21E+7 7.08E+7 3.72E+7 Co-60 4.32E+7 2.39E+8 1.27E+8 Ni-63 2.96E+ 10 1.59E+9 i

1.07E+8 1.01 E+9 Zn-65 4.13 E+9 1.10E+ 10 6.94E+9 1.93E+9 6.85E+9 Rb-86 8.77E+9 5.64E+8 5.39E+9 Sr-89 6.62E+9 2.56E+8 1.89E+8 Sr-90' l.12E+11 1.51E+9 2.83E+10 Y-91 3.91 E+4 5.21 E+6 1.04E+3 Zr-95 3.84E+3 8.45E+2 1.21 E+3 8.81 E+5 7.52E+2 Nb-95 3.18E+5 1.24E+5 1.16E+5 2.29E+8 8.84E+4 Ru-103 4.29E+3 1.08E+4 1.llE+5 1.65E+3 Ru-106 9.24E+4 1.25E+5 1.44E+6 1.15E+4 Ag-110m 2.09E+8 1.41E+8 2.63E+ 8 1.68E+10 1.13E+8 Sb-124 1.09E+8 1.41E+8 2.40E+5 6.03 E+7 6.79E+8 3.81 E+7 Sb-125 8.70E+7 1.41E+6 8.06E+4 4.85E+7 2.08E+8 1.82E+7 Te-125m 7.38E+7 2 00E+7 2.07E+7 7.12E+7 9.84E+6 Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93 E+8 1.68E+8 2.47E+7 Te-129m 2.72E+8 7.61 E+7 8.78E+7 8.00E+8 3.32E+8 4.23E+7 I-131 1.30E+9 1.31E+9 4.34E+11 2.15 E+9 1.17E+8 7.46E+8 Cs-134 2.26E+ 10 3.71E+10 1.15E+10 4.13 E+9 2.00E+8 7.83E+9 I

Cs-136 1.00E+9 2.76E+9 1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs-137 3.22E+10 3.09E+10 1.01E+10 3.62E+9 1.93 E+8 4.55E+9 Ba-140 1.17E+8 1.03 E+5 3.34E+4 6.12E+4 5.94E+7 6.84E+6 I

Ce-141 2.19E+4 1.09E+4 4.78E+3 1.36E+7 1.62E+3 Ce-144 1.62E+ 6 5.09E+5 2.82E+5 1.33 E+ 8 8 66E+4 I

Pr-143 7.23 E+2 2.17E+2 1.17E+2 7.80E+5 3.59E+1 Nd-147 4.45E+2 3.60E+2 1.98E+2 5.71 E+5 2.79E+1 36

Hope Creek ODCM Rev 15 I

Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - INFANT (mrem /yr per uCi/m3) for H-3 and C-14 (m2

mrem /yr per uCi/sec) for others I

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 C-14 3.23 E+6 6.89E4 5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 P-32 1.60E+ 11 9.42E+9 2.17E+9 6.21 E+9 Cr-51 1.05E+5 2.30E+4 2.05 E+5 4.71E+6 1.61E+5 Mn-54 3.89E+7 8.63 E+6 1.43 E+7 8.83E+6 Fe-55 1.35E+8 8.72E+7 4.27E+7 1.I1E+7 2.33E+7 Fe-59 2.25E+8 3.93E+8 1.16E+8 1.88E+8 1.55E+8 Co-57 8.95E+6 3.05E+7 1.46E+7 Co-58 2.43 E+7 6.05E+7 6.06E+7 Co-60 8.81 E+7 2.10E+8 2.08E+8 Ni-63 3.49E+10 2.16E+9 1.07E+8 1.21 E+9 I

Zn-65 5.55E+9 1.90E+10 9.23E+9 1.61E+10 8.78E+9 Rb-86 2.22E+10 5.69E+8 1.10E+10 Sr-89 1.26E+10 2.59E+8 3.61 E+8 Sr-90' l.22E+11 1.52E+9 3.10E+10 Y-91 7.33 E+4 5.26E+6 1.95E+3 I

Zr-95 6.83 E+3 1.66E+3 1.79E+3 8.28E+5 1.18E+3 Nb-95 5.93 E+5 2.44E+5 1.75E+5 2.06E+8 1.41E+5 Ru-103 8.69E+3 1.81E+4 1.06E+5 2.91 E+3 Ru-106 1.90E+5 2.25E+5 1.44E+6 2.38E+4 Ag-llom 3.86E+8 2.82E+8 4.03E+8 1.46E+10 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E+5 1.31E+8 6.46E+8 6.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 9.38E+7 1.99E+8 3.07E+7 Te-125m 1.51E+8 5.04E+7 5.07E+7 7.18E+7 2.04E+7 Te-127m 4.21 E+8 1.40E+8 1.22E+8 1.04E+9 1.70E+8 5.10E+7 Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 3.34E+8 8.62E+7 I-131 2.72E+9 3.21 E+9 1.05E+12 3.75E+9 1.15E+8 1.41E+9 Cs-134

3. 55E+10 6.80E+10 1.75E+10 7.18E+9 1.85E+8 6.87E+9 Cs-136 1.96E+9 5.77E+9 2.30E+9 4.70E+ 8 8.76E+7 2.15E+9 Cs-137 5.15E+ 10 6 02E+10 1.62E+10 6.55E+9 1.88E+8 4.27E+9 Ba-140 2.41 E+8 2.41 E+5 5.73 E+4 1.48E+5 5.92E+7 1.24E+7 Ce-141 4.33E+4 2.64E+4 8.15E+3 1.37E+7

3. I 1E+3 Ce-144 2.33E+6 9.52E+5 3.85E+5 1.33E*8 1.30E+5 Pr-143 1.49E+3 5.59E+2 2.08E+2 7.89E+5 7.41 E+1 Nd-147 8.82E+2 9.06E+2 3.49E+2 5.74E+5 5.55E+1 e

37

I Hope Creek ODCM Rev 15 Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Vegetation Pathway Dose Factors - ADULT (mrem /yr per uCi/m3) for H 3 and C-14 (m2

mrem /yr per uCi/sec) for others Euclide Bone Liver Thyroid Kidn_ey Lang GI-LLI T. Body H-3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 P-32 1.40E+9 8.73 E+7 1.58E+8 5.42E+7 Cr-51 2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 Mn-54 3 11 E+8 9.27E+7 9.54E+8 5.94E+7 I

Fe-55 2.09E+8 1.45E+8 8.06E+7 8.29E+7 3.37E+7 Fe-59 1.27E+8 2.99E+8 8.35E+7 9.96E+8 1.14E+8 Co-57 1.17E+7 2.97E+8 1.95E+7 I

Co-58 3.09E+7 6.26E+8 6.92E+7 Co-60 1.67E+8 3.14E+9 3.69E+8 Ni-63 1.04E+10 7.21 E+8 1.50E+8 3.49E+8 Zn-65 3.17E+8 1.01E+9 6.75E+8 6.36E+8 4.56E+8 Rb-86 2.19E+8 4.32E+7 1.02E+8 Sr-89 9.96E+9 1.60E+9 2.86E+ 8 Sr-90 6.05E+11 1.75E+10 1.48E+10 Y-91 5.13 E+6 2.82E+9 1.37E+5 Zr-95 1.19E+6 3.81E+5 5.97E+5 1.21E+9 2.58E+5 Nb 95 1.42E+5 7.91 E+4 7.81 E+4 4.80E+8 4.25E+4 I

Ru-103 4.80E+6 1.83E+7 5.61 E+8 2.07E+6 Ru-106 1.93 E+8 3.72E+8 1.25E+10 2.44E+7 Ag-110m 1.06E+7 9.76E+6 1.92E+7 3.98E+9 5.80E46 Sb-124 1.04E+8 1.96E+6 2.52E+5 8.08E+7 2.95E+9

4. l l E+7 I

Sb-125 1.36E+8 1.52E+6 1.39E+5 1.05E+8 1.50E+9 3.25E+7 Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 3.86E+8 1.29E+7 Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 1.17E+9 4.26E+7 Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 1.28E+9 4.03 E+7 I-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 3.05E+7 6.63E+7 Cs-134 4.66E+9 1.llE+10 3.59E+9 1.19E+9 1.94E+8 9.07E+9 I

Cs-136 4.20E+7 1.66E+8 9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-137 6 36E+9 8.70E+9 2.95E49 9.81 E+8 1.68E+8 5.70E+9 Ba-140 1.29E+8 1.62E+5 5.49E+4 9.25E+4 2.65E48 8.43 E+6 Ce-141 1.96E+5 1.33 E+5 6.17E+4 5.08E+8 1.5164 Ce-144 3.29E+7 1.38E+7 8.16E+6 1.llE+10 1.~/E+6 Pr-143 6.34E+4 2.54E+4 1.47E+4 2.78E+8 3.1.tE+3 Nd-147 3.34E+4 3.86E+4 2.25E+4 1.85E+8 2.313+3 I

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liope Creek ODCM Rev 15 Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Vegetation Pathway Dose Factors - TEENAGER I

(mrem /yr per uCi/m3) for H-3 and C-14 (m2

mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney laing GI-LLI TJLqdy H-3 2.59E+3 2.59E+3 2.59E+3 159E+3 2.59E+3 2.59E+3 C-14 1.45E+6 2.91 E+5 2.91 E+5 2.91 E+5 2.91 E+5 2.91 E+5 2.91E+5 P-32 1.6]E+9 9.96E+7 1.35E+8 6.23 E+7 Cr-51 3.44 E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Mn-54 4.52E+8 1.35E+8 9.27E+8 8.97E+7 Fe-55 3.25 E+ 8 2.31 E+8 1.46E+8 9.98E+7 5.38E+7 Fe-59 1.81E+8 4.22E+8 1.33 E+8 9.98E+8 1.63 E+8 Co-57 1.79E+7 3.34E+8 3.00E+7

. I Co-58 4.38E+7 6.04E+8 1.01 E+8 Co-60 2.49E+8 3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13 E+9 1.81E+8 5.45E+8 Zn-65 4.24E+8 1.47E+9 9.41 E+8 6.23E+8 6.86E+8 Rb-86 2.73 E+8 4.05E+7 1.28E+8 I

Sr-89 1.51 E+10 1.80E+9 4.33E+8 Sr-90' 7.51 E+11

2. l lE+10 1.85E+11 Y-91 7.87E+6 3.23E+9

2. l l E+5 I

Zr-95 1.74E+6 5.49E+5 8.07E+5 1.27E49 3.78E+5 Nb-95 1.92E+5 1.06E+5 1.03E+5 4.55E+8 5.86E+4 Ru-103 6.87E+6 2.42E+7 5.74E+8 2.94E+6 Ru-106 3.09E+8 5.97E+8 1.48E+10 3.90E+7 Ag-110m 1.52E+7 1.44E+7 2.74E+7 4.04E+9 8.74E+6 Sb-124 1.55E+8 2.85E+6 3.51E+5 1.35E+8

3. llE49 6 03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+5 1.88 E+8 1.66E+9 5.00E+7 Te-125m 1.48E+8 J.34E+7 4.14E+7 4.37E+8 1.98E+7 Te-127m 5.51 E+8 1.96E+8 1.31E+8 2.24E+9 1.37E+9 6.56E+7 I

Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54 E+9 1.38E+9 5.81 E+7 I-131 7.70E+7 1.08E+ 8 3.14E+10 1.85E+8 2.13 E+7 5.79E+7 Cs-134 7.09E+9 1.67E+10 5.30E49 2.02E+9 2.08E+8 7.74E+9 I

Cs-136 4.29E+ 7 1.69E+8 919E+7 1.45E+7 1.36E+7 1.13 E+8 Cs-137 1.01 E+10 1.35E+ 10 4.59E+9 1.78E+9 1.92E+8 4.69E+9 Ba-140 1.38E+ 8 1.69E+5 5.75E+4 1.14E+5 2.13 E+8 8.91 E+6 Ce-141 2.82E+5 1.88E+5 8.86E+4 5.38E+8 2.16E+4 Ce-144 5.27E+7 218E+7 1.30E+7 1.33E+10 2.83 E+6 I

Pr-143 7.12E+4 2.84E+4 1.65E+4 2.34E+8 3.55E+3 Nd-147 3.63E+4 3.94E+4 2.32E+ 4

' 42E+8 2.36E+3 39

I Hope Creek ODCM Rev 15 Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases I

R(io), Vegetation Pathway Dose Factors - CHILD (mrem /yr per uCi/m3) for H-3 and C-14 (m2

mrem /yr per uCi/sec) for others l

l Nuclide Bone Liver Thyroid Kidney Lung Gl-LLI IBody l

H-3 l

4.01 E+3 4.01 E+3 4.01 E+3 4.01 E+3 4.01 E+3 4.01 E+3 C-14 3.50E+6 7.01 E+5 7.01 E+5 7.01 E+5 7.01 E+5 7.01 E+5 7.01E+5 P-32 3 37E+9 1.58E+8 9.30E+7 1.30E+8 Cr-51 6.54 E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 Mn-54 6.61 E+8 1.85E+8 5.55E+8 1.76E+8 Fe-55 8.00E+8 4.24E+8 2.40E+8 7.86E+7 1.31E+8 Fe-59 4.01 E+8 6.49E+8 1.88E+8 6.76E+8 3.23E+8 Co-57 2.99E+7 2.45E+8 6.04E+7 Co-58 6.47E+7 3.77E+8 1.98E+8 Co-60 3.78E+8 2.10E+9 1.12E+9 I

Ni-63 3.95E+10

2. l l E+9 1.42E+8 1.34E+9 Zn-65 8.12E+8 2.16E+9 1.36E+9 3.80E+8 1.35E+9 Rb-86 4.52E+8 2.91E+7 2.78E+8 I

Sr-89' 3.59E+10 1.39E+9 1.03 E+9 Sr-90 1.24E+12 1.67E+10 3.1SE+11 I

Y-91 1.87E+7 2.49E+9 5.01 E+5 Zr-95 3.90E+6 8.58E+5 1.23 E+6 8.95E+8 7.64E+5 ht-95 4.10E+5 1.59E+5 1.50E+5 2.95E+8 1.14E+5 Ru-103 1.55E+7 3.89E+7 3.99E+8 5.94E+6 Ru-106 7.45E+8 1.01E+9 1.16E+10 9.30E+7 Ag-110m 3.22E+7 2.17E+7 4.05E+7 2.58E+9 1.74E+7 ll Sb-124 3.52E+8 4.57E+6 7.78E+5 1.96E+8 2.20E+9 1.23E+8 Sb.125 4.99E+8 3.85 E+6 4.62E+5 2.78E+8 1.19E+9 1.05E+8 Te-125m 3.51 E+ 8 9.50E+7 9.84E+7 3.385+8 4.67E+7 Te-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 1.07E+9 1.57E+8 i

Te-129m 8.54E+8 2.39E+8

2. 75E+8 2.51 E+9 1.04E+9 1.33E+8 l

I-131 1.43E+8 144E+8 4.76E+10 2 36E+8 1.28E+7 8.18E+7 l

Cs-134 1.60E+10 2.63E+10 8.14E+9 2.92E+9 1>2E+8 5.54E+9 l

Cs-136 8.06E+7 2.22E+8 1.18E+8 1.76E+7 7.79E+6 1.43 E+8 Cs-137 2.39E+10 2.29E+10 7.46E+9 2.68E+9 1.43 E+8 3.38E+9 I

Ba-140 2.77E+8 2.43E+5 7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ce-141 6.35E+5 3.26E+5 1.43E+5 4.07E+8 4.84E+4 Ce-144 1.27E+ 8 3.98E+7 2.21 E+7 1.04E+10 6.78E+6 Pr-143 1.48 E+5 4.46E+4 2.41 E+4 1.60E+8 7.37E+3 Nd-147 7.16E+4 5.80E+4 3.18E+4 9.18E+7 4.49E+3 40 I

Hope Creek ODCM Rev 15 Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Ground Plane Pathway Dose Factors (m2

mrem /yr per uCi/sec)

Nuclide Any Organ

. E H-3 15 C-14 P-32 Cr-51 4.68E+6 I

Mn-54 1.34E+9 Fe-55 Fe-59 2.75E+8 i

Co-58 3.82E+8 I

Co-60 2.16E+10 Ni-63 Zn-65 7.45E+8 Rb-86 8.98E+6

':I Sr-89 2.16E+4 Sr-90 Y-91 1.08E+6

/

Zr-95 2.48E+8 1'g Nb-95 1.36E+8

3 Ru-103 1.09E+8 Ru-105 4.21 E+8 Ag-110m 3.47E+9 4

Te-125m 1.55E+6 Te-127m 9.17E+4

.E Te-129m 2.00E+7 5

I-131 1.72E+7 3

Cs-134 6.75E+9 3

Cs-136 1.49E+8 Cs-137 1.04E+ 10 Ba-140 2.05E+7 s

Ce-141 1.36E+7 Ce-144 6.95 E+7 Pr-143 l

i Nd-147 8.40E+6

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APPENDIX A EVALUATION OF DEFAULT MPC VALUES FOR LIQUID EFFLUENTS I

I A-1

I Ilope Creek ODCM Rev 15 APPENDlX A Evaluation of Default MPC Value for Liquid Radwaste Effluent Radiation Monitors In accordance with the requirements of Technical Specification 3. 3.7.10 the radioactive efiluent monitors shall be operable with alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed the MPC value of 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F) The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual monitor.

In order to limit the need for routinely having to reestablish the alarm setpoints as a function of changing radionuclide distributions, a default alarm setpoint can be established. This default setpoint can be based on an evaluation of the radionuclide distribution from the 1993 to 1995 release data of the liquid efiluents from Hope Creek and the effective MPC value for this distribution The effective MPC value for a radionuclide distribution is calculated by the equation:

I Ci (gamma emitters only)

(A.1)

MPC,

=

Ci(gamma)

I MPCi where:

I

MPC,

= an effective MPC value for a mixture of radionuclides (uCi/ml)

C

= concentration ofradionuclide iin the mixture i

MPCi

= the 10 CFR 20, Appendix B, Table II, Column 11 MPC value for radionuclide i (uCi/ml) Appendix F Considering the average effective MPC values from 1993 thm 1995 releases it is reasonable to select an MPC value of 7.92E-05 uCi/ml as typical ofliquid radwaste discharges. This value will be reviewed I

and adjusted as necessary based on the distribution history of efiluents from Hope Creek. Using the value of 7.92E-5 uCi/ml to calculate the default alarm setpoint, results in a setpoint that:

I

1) Will not require frequent re-adjustment due to minor variations in the nuclide distribution which are typical of routine plant operations, and,

1) Will provide for a liquid radwaste discharge rate (as evaluated for each batch release) that is compatible with plant operations (Refer to Table 1-1).

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Hope Creek ODCM Rev 15 1.0 Default Setpoint Determination:

Conservative alarm setpoints can be determined through the use of default parameters. Table 1-1 summarizes all current default values in use for Hope Creek.

A. Liquid Radwaste Monitor (RE4861)

MPC,a CTBD

CF SP <

+ bkg (1.2)

RR Default values from Table 1-1:

MPC,

= 7.92E-5 uci/ml CTBD

= 12000 gpm RR

= 176 gpm (1300 CST)

I Bkg

= 0 uci/ml CF

= 0.5

' 7 92E-5

12000

0.5 SP <

+0 176 SP < 2.70E-3 uci/mi 2.0 Correction Factor:

A conection factor must be applied to the default setpoint calculation in order to account for radiation monitor uncertainties and the contribution of non-gamma emitting radionuclides such as H-3, Sr, and Fe.

a. Radiation Monitor Inaccuracies:

Hope Creek PSBP 311649 lists a total loop accuracy of 30% for the liquid radwaste radiation monitors A factor of 0.30 is applied to the default setpoint to ensure the trip setpoint is reached before the analyticallimit is obtained.

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Hope Creek ODCM Rev 15 B. Non-Gamma Emitting Radionuclides:

Non-gamma emitting radionuclides are analyzed on a monthly and quanerly basis from composite samples ofliquid radwaste releases.

Nuclide MPC (uci.mD Activity (uci.ml)

Activity / MPC H-3 3 E-3 1.0E-2 3.33 Fe-55 8E-4 4.7E-4 0.59 Sr-89 3E-6 1.6E-6 0.53 Sr-90 3 E-7 2.0E-8 0.07 Total 4.52 The values in the table above represent the maximum reactor coolant values for non-gamma emitting nuclides in 1995. Reactor coolant values were chosen to represent the maximum concentration of non-I gamma emitting radionuclides that could be released from Hope Creek station. The activity values in the table will be further diluted by a minimum factor of 68 prior to release to the Delaware River. The minimum dilution factor is obtained by using the minimum cooling tower blowdown flowrate of 12,000 gpm and the maximum release rate of 176 gpm.

A conservative correction factor for non-gamma emitting radionulcides can he obtained by using the highest Activity / MPC fraction and the minimum dilution factor as follows:

Correction Factor (non-gamma) = 4.52 / 68 = 0.066 (Rounded up to 0.10)

I An overall correction factor can be obtained by adding the correction factor for radiation monitor inaccuracies and non-gamma emitting radionuclides aa follows:

Overall Correction factor = 0.30 + 0.10 = 0.40 (Rounded up to 0.50 for additional conservatism)

C. Cooling Tower Blowdown Radiation Monitor (RE8817)

The cooling tower blowdown radiation monitor provides an Alarm only function for releases into the environment. The cooling tower blowdown is the fmal release point for liquid efIluents from Hope Creek station to the Delaware River.

I SP < MPC,

0.5 SP < 7.92E-5 uci/ml

0.5 SP < 3.96E-5 uci/ml (RE8817)

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ilope Creek ODCM Rev 15 I

TABLE A-1 CALCULATION OF EFFECTIVE MPC 110PE CREEK 1993 ACTIVITY 1994 ACTIVITY 1995 ACTIVITY NUCLIDE MPC RELEASED (Ci)

RELEASED _(Ci) RELEASED (Cj)

,g Na-24 3.0E-05 1.20E-04 N/D 2.1SE-05 Cr-51 2.0E-03 1.57E-01 7.91E-02 1.29E-01 Mn-54 1.0E-04 6.30E-02 1.10E-01 4.12E-01 As-76 2.0E-05 1.03E-05 1.62E-04 8.42E-05 Co-58 9.0E-05 1.35E-03 3.04E-03 2.68E-02 Fe-59 5.0E-05 8.74E-03 1.14E-02 1.12E-01 Co-60 3.0E-05 1.15E-02 6.49E-02 8.48E-02 Zn-65 1.0E-04 7.01 E-02 7.79E-02 8.77E-02 Ag-110m 3.0E-05 2.16E-03 1.90E-03 7.42E-03 Zr-97 2.0E-05 1.45E-05 N/D 3.45E-05

}g Tc-99m 3.0E-03 1.79E-03 1.45E-03 8.68E-04 j5 Cs-134 9.0E-06 N/D 1.I1E-06 1.51E-04 Cs-137 2.0E-05 4.85E-05 1.33 E-05 2.97E-04 Zn-69m 6.0E-05 2.33E-05 7.22E-05 N/D Nb-97 9.0E-04 4.33E-04 2.32E-04 N/D In-115m 4.0E-04 N/D N/D 2.90E-05 H-3 3.0E-03 6.17E+01 3.33E+01 4.61 E+01 Fe-55 8.0E-04 4.51 E-02 1.86E-01 5.44E-01 i

Total Curies 3.16E-01 3.50E-01 1.40E+00 (Gamma) i SUM (Ci/MPCi) 2.06E+03 4.42E+03 1.07E+04 (Gamma) l SUM (Ci/MPCi) 2.06E+04 1.13 E+04 1.60E+04

!g

,E (Non-Gamma)

MPCe (uCi/ml) 1.53E-04 7.92E-05 1.31E-04 N/D=Not detected A-5

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APPENDIX B i

1 TECHNICAL B ASIS FOR EFFECTIVE DOSE FACTORS 4

LIQUID RADIOACTIVE EFFLUENT i

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I Hope Creek ODCM Rev 15 APPENDIX B Technical Basis for Effective Dose Factors -

Liquid Effluent Releases The radioactive liquid effluents from Hope Creek from 1993 through 1995 were evaluated to determine the dose contribution of the radionuclide distribution. This analysis was performed to evaluate the use of a limited dose analysis for determining environmental doses, providing a simplified method of determining compliance with the dose limits of Technical Specification 3.11.1.2. For the expected radionuclide distribution of efIluent from Hope Creek during 1993 to 1995, the controlling organ is the liver. The calculated liver dose is predominately a function of the Zn-65 and Fe-55 releases. The radionuclides, Zn-65 and Fe-55 also contribute the large majority of the calculated total body dose. The I

results of this evaluation are presented in Table B-1.

I For purposes of simplifying the details of tne dose calculation process, it is conservative to identify a controlling, dose significant radionuclide and limit the calculation process to the use of the dose conversion factor for this nuclide. Multiplication of the total release (i.e., cumulative actisity for all I

radionuclides) by this dose conversion factor provides for a dose calculation method that is simplified while'also being conservative.

For the evaluation of the maximum organ dose, it is conservative to use the Zn-65 dose conversion factor (5.13E5 mrem /hr per uci/ml). By this approach, the maximum organ dose will be overestimated since this nuclide has the highest organ dose fraction of all the radionuclides evaluated. For the total I

body calculation, the Zn-65 dose factor (2.32E5 mrem /hr per uCi/ml, total body) is the highest among the identified dominant nuclides.

l For evaluating compliance with the dose limits of technical Specification 3.11.1.2, the following simplified equations may be used:

Total Body 8.35E-04

Vol DS =

A.,S

Ci (B.1)

CTBD I

B-2

I I

Hope Creek ODCM Rev 15 where:

Da,

= dose to the total body (mrem)

I A,,a,

= 2.32ES, total body ingestion dose conversion factor for Zn-65 where A is dose conversion factor, i is isotope which is Zn-65, and TB is the total body (mrem /hr per uCi/ml)

I VOL

= volume ofliquid efiluent released (gal)

C,

= total concentration of all radionuclides (uCi/ml)

CTBD

= average cooling tower blowdown discharge rate during release period (gal / min) 8.35E-04

= conversion factor (l.67E-2 hr/ min) and the near field dilution factor 0.05 Substituting the value for the Zn-65 total body dose conversion factor, the equation simplified to:

1.94E+ 2

VOL Da, =

EC (B.2) i CTBD hiaximum Organ I

8.35E-4

VOL

Aio, Liver Dmax =

I Ci (B.3)

CTBD 4

Where:

l Dmax = maximum organ dose (mrem)

Aio, 5.13E5, liver ingestion dose conversion factor fbr Zn-65 where A is dose conversion

=

Liver factor, i is isotope which is Zn-65 and O is maximum organ which is the liver (mrem /hr per uCi/ml).

Substituting the value for Aio the equation simplifies to:

4.28E2

VOL Dmax = -

E Ci (B.4)

CTBD I

Tritium is not included in the limited analysis dose assessment for liquid releases, because the potential dose resulting from normal reactor releases is relatively negligible.

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liope Creek ODCM Rev 15 I

Near Field Dilution Factor 1

The near field dilution factor stems from NuReg-0133, Section 41. For plants with coolina towers, such as Hope Creek, a dilution factor is applicable so that the product of the average blowdown flow (in CFS) and the dilution factor is '000 cfs or less. The average minimum coo:ing tower blowdown far Ilope Creek is 190E4 GPM (from FSAR 11.2). This converts to 42 CFS, for conservatism a dilution j

factor of 20 will be used, giving a dilution flow of 880 CFS. This near field dilution factor of 20 is invened to a multiple of 0.05, muhiplied times the liquid efflueat case equations I

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Hope Creek ODCM Rev 15 TABLE B-1 I

Adult Dose Contributions Fish and Invertebrate Pathways liope Creek I

Nuclide Release TB Dose GI-LLI Dose Liver Dose Year (Ci)

Frac.

Fe-55 4.51 E-2 0.02 0.03 0.04 1993 Fe-55 1.86E-2 0.07 0.08 0.13 1994 Fe-55 5.44E-1 0.15 0.10 0.24 1995 Mn-54 6.30E-2 0.04 0.01 1993 Mn-54 1.10E-1 0.01 0.06 0.02 1994 Mn-54 4.12E-1 0.02 0.07 0.03 1995 Co-58 1.35E-3 1993 Co-58 3.04E-3 1994 Co-58 2.68E-2 1995 Fe-59 8.74E-3 0.04 0.18 0.04 1993 Fe-59 1.14E-2 0.04 0.17 0.04 1994 Fe-59 1.12E-1 0.22

' 53 0.22 1995 l

Co-60 1.15E-2 0.01 1993 Co-60 6.49E-1 0.01 0.05 1994 l

Co-60 8.48E-2 0.01 0.02 1995 l

Zn-65 7.01 E-2 0.93 0.69 0.90 1993 Zn-65 7.79E-2 0.87 0.61 0.81 1994 Zn65 8.77E-2 0.60 0.23 0.51 1995 0

Less than 0.01

=

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Hope Creek ODCM Rev 15 APPENDIX C I

Technical Basis for Effective Dose Factors -

Gaseous Radioactive EfIluents Overvinv The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific. These effective factors, which are based on typical radionuclide distributions of releases, can be applied to the I

total radioactivity releases to approximate the dose in the environment. Instead of having to perform individual radionuclide dose analysis only a single multiplication (i.e., Keff, Meff, or Neff times the total I

quantity of radioactive material releases) would be needed. The approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculation technique.

Determination of Effective Dose Factors Effective dose transfer factors are calculated by the following equations:

K,g = E (Ki

f,)

(C.1)

Where:

K,n

= the effective total body factor due to gamma emissions from all noble gases released.

K,

= the total body dose factor due to gamma emissions from each noble gas radionuclide i I

released.

f

= the fractional abundance of noble gas radionuclide i relative to the total noble gas activity.

i

( L + 1. l M,n) = I (( Li + 1. lM )

f )

(C.2) i i

where:

(L + 1.1Mog) = the effective skin dose factor due to beta and gamma emissions from all noble gases I

released.

(L + 1.1 M,) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i

i released.

C-1

Hope Creek ODCM Rev 15 Meg =E (M

f)

(C.3) i i

where:

M,g

= the effective air dose factor due to gamma emissions from all noble gases released.

l M,

= the air dose factor due to gamma emissions from each noble gas radionuclide i released.

Nog = I (Ni

f)

(C.4) i where:

N,g

= the effective air dose factor due to beta emissions from all noble gases released.

Ni

= the air dose factor due to beta emissions from each noble gas radionuclide i released.

Normally, it would be expected that past radioactive effluent data would be used for the determination of the efTective dose factors. However, the noble gas releases from Hope Creek have a short history and with continued excellent fuel performance, has hampered etTorts in collecting and detecting appreciable noble gas mixes of radionuclides. So, to provide a reasonable basis for the derivation of the effective noble gas dose factors, the source terms from ANSI N237-1976/ANS-18.1, " Source Term Specifications", Table 5 has been used as representing a typical distribution. The effective dose factors as derived are presented in Table C-1.

l Application To provide an additional degree of conservatism, a factor of 0.50 is introduced into the dese calculation process when the effective dose transfer factor is used. This conservatism provides addaonal assurance that the evaluation of doses by the use of a single effective factor will not significanSy underestimate any actual doses in the ensironment.

For evaluating compliance with the dose limits of Technical Specification 3.11.2.2, the following simplified equations may be used:

3.17E-08 I

D, =

X/Q

M,a

I Q, (C.5) 0.50 3.17E-08 De =

X/Q

N,g

I Q, (C.6) 0.50 C-2

Hope Creek ODCM Rev 15 Where:

D, air dose due to gamma emissions for the cu.nulative release of all noble

=

gases (mrad)

D3 air dose due to beta emissions for the cumulative release of all noble gases

=

(mrad)

X/Q 3

atmospheric dispersion to the controlling site boundary (sec/m )

=

8. l E3, effective gamma-air dose factor (mrad /yr per uCi/m')

M,a

=

8.5E3, effective beta-air dose factor (mrad /yr per uCi/m')

N,a

=

cumulative release for all noble gas radionuclides (uCi)

Q,

=

3.17E-08 = conversion factor (yr/sec) 0.50 conservatism factor to account for the variability in the efiluent data

=

Combining the constants, the dose calculation equations simplify to:

[

E D,

5.14E-4

X/Q

I Q, (C.7)

=

D 5.39E-4

X/Q

I Q, (C.8)

=

3 i

The effective dose factors are to be used on a limited basis for the purpose of facilitating the timely assessment of radioactive efiluent releases, particularly during periods of computer malfunction where a detail'ed dose assessment may be unavailable.

I 1

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I I

C-3 I

l Hope Creek ODCM Rev 15 I

TABLE C-1 EtTective Dose Factors Noble Gases - Total Body and Skin Total Body Effective Skin Effective l

K,g (L + 1.1 M,g) 3 Radionuclide j

(mrem /vr per uci/m )

(m_ rem /yr per uci/m')

Kr83m 0.01 I

Kr85m 0.01 1.0El 2.8El Kr87 0.04 2 4E2 6.6E2 Kr88 0.04 5.9E2 7.6E2 I

Kr89 0.27 4.5E3 7.9E3 Xel33 0.02 5.9E0 1.4El Xel35 0.05 90El 2.0E2 Xel35m 0.06 1.9E2 2.6E2 I

Xel37 0.31 4.4E2 4.3E3 Xel38 0.19 1.7E3 2.7E3 Total 7.8E3 1.7E4 Noble Gases - Air I

Total Body EfTective Skin Effective K,a (L.+ 1.1 Mog)

Radionuclide j

(mrem /vr ner uci/m')

(mrem /yr per uci/m')

Kr83m 0.01 3.0E0 Kr85m 0.01 1.2El 2.0El I

Kr87 0.04 2.5E2 4.1 E2 Kr88 0.04

6. lE2 1.2E2 Kr89 0.27 4.7E3 2.9E3 I

Xel33 0.02 7.0E0 2.lEl Xel35 0.05 9.6El 1.2E2 Xel35m 0.06 2.0E2 4.4El Xel37 0.31 4.7E2 3.9E3 Xel38 0.19 1.8E3 9,0E2 Total 8.1 E3 8.4E3 I

Based on noble gas distribution from ANSI N237-1976/ANS-18.1," Source Term Specification" I

I E

C-4

4 1

Hope Creek ODCM Rev 15 I

APPENDlX D I

TECHNICAL BASIS FOR EFFECTIVE DOSE PARAMETERS GASEOUS PADIOACTIVE EFFLUENTS I

I I

I

Hope Creek ODCM Rev 15 I

APPENDIX D Technical Basis for Effective Dose Parameters Gaseous Radioactive Efiluent Releases I

The pathway dose factors for the controlling infant age group were evaluated to determine the controlling pathway, organ and radionuclide. This analysis was performed to provide a simplified method for determining compliance with Technical Specification 3.11.2.3. For the infant age group, the controlling pathway is the grass - cow - milk (g/c/m) pathway. An infant receives a greater radiation dose from the I

g/c/m pathway than any other pathway. Of this g/c/m pathway, the maximum exposed organ including the total body, is the thyroid, and the highest dose contributor is radionuclide I-131. The results of this evaluation are presented in Table D-1.

For purposes of simplifying the details of the dose calculation process, it is conservative to identify a controlling, dose significant organ and radionuclide and limit the calculation process to the use of the dose conversion factor for the organ and radionuclide. Multiplication of the total release (i.e., cumulative activity for all radionuclides) by this dose conversion factor provides for a dose calculation method that is simplified while also being conservative.

For the evaluation of the dose commitment via a controlling pathway and age group, it is conservative to use the infant, g/c/m, thyroid,1-131 pathway dose factor (1.67E12m

mrem /yr per uCi/sec). By this 2

approach, the maximum dose commitment will be overestimated since I-131 has the highest pathway dose factor of all radionuclides evaluated.

For evaluating compliance with the dose limits of Technical Specification 3.11.2.3, the following simplified equation may be used:

Dmx

= 3.17E-8

W

RI-131

I Q, (D.1)

Where:

7 Dmx

= maximum organ dose (mrem)

I

= atmospheric dispersion parameter to the controlling location (s) as identified in W

Table 21 X/Q

= Atmospheric dispersion for inhalation pathway (sec/m')

I D/Q

= atmospheric disposition for vegetation, milk and ground plane exposure pathways (m)

Q,

= cumulative release over the period ofinterest for radiciodines and particulates (uCi).

3.17E-8

= conversion factor (yr/sec)

RI-131

= I-131 dose parameter for the thyroid for the identified controlling pathway.

= 1.05E12, infant thyroid dose parameter with the grass - cow - milk pathway controlling 2

(m mrem /yr per uCi/sec)

I D-1 I

Hope Creek ODCM Rev 15 The ground plane exposure and inhalation pathways need not be considered when the a*vove simplified calculational method is used because of the overall negligible contribution of these pathways to the total

)

I thyroid dose. It is recognized that for some particulate radionuclides (e.g., Co-60 and Cs-137), the ground exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway. However, use of the I-131 thyroid dose parameter for all radionuclides will maximize the organ dose calculation, especially considering that no other radionuclides has a higher dose parameter for any organ via any pathway than I-131 for the thyroid via the milk pathway.

The location of exposure pathways and the maximum organ dose calculation may be based on the available pathways in the surrounding environment of Hope Creek as identified by the annual land-use census (Technical Specification 3.12.2).

Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-3.

I I

D-2 I

i i

Hope Creek ODCM Rev 15 i

TABLE D-1 Infant Dose Contributions iI j

Fraction of Total Organ and Body Dose d

PATHWAYS Targ_1 Qrgans Grass - Cow - Milk Ground Plane e

l Total Body 0.02 0.15 Bone 0.23 0.14 l

l Liver 0.09 0.15 Thyroid 0.59 0.15 i

Kidney 0.02 0.15 Lung 0.01 0.14 i

GI-LLI 0.02 0.15 l

I s

TABLE D-2 Fraction of Dose Contribution by Pathway i

l f

Pathway Frac I

1 Grass-Cow-Milk 0.92 i

Ground Plane 0.08 Inhalation N/A l

I l

D-3 I

1 Hope Creek ODCM Rev 15

!I i

!I

!I APPENDIX E

}

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -

i j

SAMPLE TYPE, LOCATION AND ANALYSIS 1

d 1

1 i!I i

i d

i i

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I E-1 I

Hope Creek ODCM Rev 15 I

APPENDIX E SAMPLE DESIGNATION Samples are identified by a three part code. The first two letters are the power station identification code, in this case "SA" The next three letters are for the media sampled.

AIO = Air Iodine IDM = Immersion Dose (TLD)

APT = Air Particulates MLK = Milk ECH = Hard Shell Blue Crab PWR = Potable Water (Raw)

ESF = Edible Fish PWT = Potable Water (Treated)

ESS = Sediment SWA = Surface Water WWA= Well Water The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; i.e.,

2=NNE,3=NE,4=ENG, etc. The next digit is a letter which represents the radial distance from the plant:

S

= On-site location E

= 4-5 miles oft-site A

= 0-1 miles off-site F

= 5-10 miles off-site B

' = l-2 miles off-site G

= 10-20 miles off-site C

= 2-3 miles off-site H

= > 20 miles off-site D

= 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g.,1,2,3,.

Fcr example, the designation SA-WWA-5D1 would indicate a sample in the SGS program (SA), consisting of well water (WWA), which had been collected in sector number 5, centered at 90' (due east) with respect to the reactor site at a radical distance of 3 to 4 miles oft-site, (therefore, radial distance D). The number 1 indicated that this is sampling station #1 in that particular sector.

I The Radiological Environmental Monitoring Program is a common program for both Salem and Hope Creek Generating Stations I

I I

I

Hope Creek ODCM Rev 15 SAMPLING LOCATIONS All sampling locations and specific information about the individual locations are given in Table E-1.

Maps E-1 and E-2 show the locations of sampling stations with respect to the site.

TABLE E-1 A. Direct Radiation Monitoring Locations (IDM)

STATION CODE STATION LOCATION ISI O 55 mi. N of vent 2S2 0.4 mi. NNE of vent 2S4 0.59 mi. NNE of vent 3S1 0.58 mi. NE of vent 4SI 0.60 mi ENE of vent 5SI 1.0 mi. E of vent; site access road 6S2 0.21 mi. ESE of vent; observation building

7Si 0.12 mi. SE of vent; station personnel gate

10S1 0.14 mi SSW ofvent; circ water bldg.

llSI 0.09 mi. SW of vent; service water bldg.

ISSI 0.57 mi. NW of vent 16S1 0.54 mi. NNW of vent 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road SD1 3.5 mi. E of vent; local farm 10D1 3.9 mi. SSW of vent; Taylor's Bridge Spur 14D1 3.4 mi. WNW of vent; Bay View, Delaware 15D1 3.8 mi. NW of vent; Rt 9, Augustine Beach, DE.

2El 4.4 mi. NNE of vent; local farm 3El

4. I mi. NE of vent; local farm 1

9El 4.2 mi. S of vent 11E2 5.0 mi. SW of vent I

12El 4.4 mi. WSW of vent; Thomas Landing 13El 4.2 mi. W of vent; Diehl House Lab 16El 4.1 mi. NNW of vent; Port Penn IFl 5.8 mi. N of vent; Fort Elfsborg 2F2 8.7 mi. NNE of vent; Salem Substation 2F5 7.4 mi. NNE of v~it; Salem High School 2F6 7.3 mi. NNE of vent; PSE&G Training Center E-3

Hope Creek ODCM Rev 15 TABLE E-1 (Continued)

A. Direct Radiation Monitoring Lo;ations (IDM)

STATION CODE STATION LOCATION 3F2 I

5.1 mi. NE of vent; Hancocks Bridge Munc. Bldg 3F3 8.6 mi. NE of vent; Quinton Township School 4F2 6.0 mi. ENE of vent; Mays Lane, Harmersville 5F1 6.5 mi. E of vent; Canton 6F1 6.4 mi. ESE of vent; Stow Neck Road 7F2 9.1 mi. SE of vent; Bayside, NJ 10F2 5.8 mi. SSW of vent; Rt. 9 1IFl 6.2 mi. SW of vent; Taylors Bridge, DE.

12F1 9.4 mi. WSW of vent; Townsend Elementary School 13F2 6.5 mi. W of vent; Odessa, DE.

13F3 9.3 mi. W of vent; Redding Middle School 13F4 9.8 mi. W of vent; Middletown, DE.

14F2 6.6 mi. WNW of vent; Boyds Corner 15F3 5.4 mi. NW of vent 16F2 8.1 mi. NNW of vent; Delaware City Public School I

IG3 19 mi. N of vent; N. Church St. Wilmington, DE 3G1 17 mi. NE of vent; local farm 10G1 12 mi. SSW of vent; Smyrna, Delaware 16Gl 15 mi. NNW of vent; Wilmington Airport 3H1 32 mi. NE of vent; National Park, NJ 3H3 110 mi. NE of vent; Maplewood R&TL

TLD locations will be maintained by site area monitoring program f

B. Air Sampling L.ocations (AIO, APT)

STATION CODE STATION LOCATION 5S1 1.0 mi. E of vent; site access road 5D1 3.5 mi. E of vent; local farm 16El 4.1 mi. NNW of vent; Port Penn IFl 5.8 mi. N of vent; Fort Elfsborg 2F6 7.3 mi. NNE of vent; PSE&G Training Center 3H3 110 mi. NE of vent; Maplewood R&TL

.I I

4 g

E.4

'! ope Creek ODCM Rev 15 TABLE E-1 (Continued)

C. Surface Water Locations (SWA) - Delaware River STATION CODE STATION LOCATION 11 Al 0.2 mi. SW of vent; Salem Outfall Area 12Cl 2.5 mi. WSW of vent; West bank of Delaware River 7El 4.5 mi SE of vent; Delaware River 16F1 6.9 mi. NNW of vent; C&D Canal D. Ground Water Locations (WWA)

STATION CODE STATION LOCATION No public drinking water samples or irrigation water samples are taken as these pathways are not directly afTected by liquid emuents discharged from Hope Creek or Salem Generating Stations.

E. Drinking Watei Locations (PWR,PWT)

STATION CODE STATION LOCATION No public drinking water samples or irrigation water samples are taken as these pathways are not directly affected by liquid emuents discharged from Hope Creek or Salem Generating Stations.

F. Water Sediment Locations (ESS)

STATION CODE STATION LOCATION I

1lAl 0.2 mi. SW of vent; Salem outfall area 15Al 0.3 mi. NW of vent; Hope Creek outfall area I

16Al 0.7 mi. NNW of vent; South Storm Drain outfall 12Cl 2.5 mi. WSW of vent; West bank of Delaware river 7El 4.5 mi. SE of vent; I mi West of Mad Horse River I

16F1 6.9 mi. NNW of vent; C&D Canal I

G. Milk Sampling Locations (MLK)

STATION CODE STATION LOCATION 2F7 5.7 mi. NNE of vent; local farm 1IF3 5.3 mi. SW ofvent; Townsend DE.

14F4 7.6 mi. WNW of vent; local farm 3G1 17 mi. NE of vent; local farm E-5

Hope Creek ODCM Rev 15 TABLE E-1 (Continued)

II. Fish and Invertebrate Locations (ESF,ECH)

STATION CODE STATION LOCATION I

1lAl 0.2 mi. SW of vent; Salem outfall area 12Cl 2.5 mi. WSW of vent; West bank of Delaware River 7El 4.5 mi. SE of vent; I mi West of Mad Horse Creek

1. Food Product Locations I

STATION CODE STATION LOCATION The Delaware River at the location of Salem and Hope Creek Nuclear Power Plants is a brackish water source. No irrigation of food products is performed using water in the vicinity from which liquid plant wastes have been discharged.

I I

I E-6

Hope Creek ODCM Rev 15 SAMPLES COLLECTION AND ANALYSIS Sam _ple Collection Method Anaissis j

Air Particulate Continuous low volume Gross Beta analysis air sampler. Sample on each weekly collected every week sample. Gamma along with the filter spectrometry shall l

change.

be performed if gross beta exceeds 10 times the yearly I

mean of the control station value. Samples

'g shall be analyzed 3

24 hrs or more aller collection to allow for I

radon and thorium daughter decay. Gamma isotopic analysis I

on quarterly composites.

Air Iodine A TEDA impregnated Iodine 131 analysis charcoal cartridge is are performed on connected to air each weekly sample.

particulate air sampler and is collected weekly at filter chang I

Crab and Fish Two batch samples are Gamma isotopic sealed in a plastic analysis of edible bag or jar and frozen portion on collection.

semi-annually or when in season.

Sediment A sediment sample is Gamma isotopic taken semi-annually.

analysis semi-annually.

I Direct 2 TLD's will be Gamma dose quarterly.

collected from each location quarterly.

I I

4

IIope Creek ODCM Rev 15 SAMPLE COLLECTION AND ANALYSIS (Cont'd) 4 Sample Collection Method Angsis Milk Sample of fiesh milk Gamma isotopic 4

is collected for each analysis and 1-131 farm semi-monthly when analysis on each cows are in pasture, sample on collection.

ll.

monthly at other times.

Water Sample to be collected Gamma isotopic

Potable, monthly providing winter monthly H-3 on Surface) icing conditions allow.

quarterly surface sample, monthly on iI ground water sample.

I I

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I E-8

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Hope Creek ODCM Rev 15 i

lI

!I i

APPENDIX F MAXIMUM PERMISSIBLE CONCENTRATIONS 1

LIQUID EFFLUENTS I

1 i

lI l

b i

i a

t I

I I

I E-1 I

I Hopc Creek ODCM Rev 15 I

The following radionuclide concentrations were obtained from 10 CFR 20 Appendix B, Table II, Column 2 as revised January 1,1991.

Table F-1 I

Maximum Permissible Concentrations I

Element Isotope Soluble Conc Insoluble Conc.

(uci/ml)

Actinium (89)

Ac-227 2E-6 3 E-4 Ac-228 9E-5 9E-5 Americium (95)

Am-241 4E-6 3E-5 Am-242m 4E-6 9E-5 I

Am-242 1E-4 1E-4 Am-243 4E-6 3 E-5 I

Am-244 SE-3 5E-3 Antimony (51)

Sb-122 3E-5 3 E-5 i

Sb-124 2E-5 2E-5 Sb-125 IE-4 lE-4 Arsenic (33)

As-73 5E-4 5E-4 As-74 SE-5 SE-5 As-76 2E-5 2E-5 As-77 8E 5 8E-5 Astatine (85)

At-211 2E-6 7E-5 I

Barium (56)

Ba-131 2E-4 2E-4 Ba-140 3E-5 2E-5 I

Berkelium (97)

Bk-249 6E-4 6E-4 Bk-250 2E-4 2E-4 Beryllium (4)

Be-7 2E-3 2E-3 Bismuth (83)

Bi-206 4E-5 4E-5 Bi-207 6E-5 6E-5 Bi-210 4E-5 4E-5 I

Bi-212 4 E-4 4E-4 Bromine (35)

Br-82 3 E-4 4E-5 I

Cadmium (48)

Cd-109 2E-4 2E-4 Cd-115m 3E-5 3E-5 Cd-l 15 3 E-5 4E-5 Calcium (20)

Ca-45 9E-6 2E-4 Ca-47 SE-5 3E-5 I

I g

e.2

II Hope Creek ODCM Rev 15 Table F-1 (Continued) g Element Isotope Soluble Conc.

Insoluble Conc.

'3 (uci/ml)

(uci/ml)

Californium (98)

Cf-249 4E-6 2E-5 Cf-250 1E-5 3 E-5 Cf-251 4E-6 3E-5 Cf-252 7E-6 7E-6 Cf-253 1E-4 1E-4 Cf-254 1E-7 1E-7 Carbon (6)

C-14 8 E-4 Cerium (58)

Ce-141 9E-5 9E-5 Ce-143 4E-5 4E-5 I

Ce-144 lE-5 IE-5 Cesium (55)

Cs-131 2E-3 9E-4 Cs-134m 6E-3 IE-3 I

Cs-134 9E-6 4E-5 Cs-135 IE-4 2E-4 Cs-136 9E-5 6E-5 Cs-137 2E-5 4E-5 Chlorine (17)

Cl-36 8E-5 6E-5 Cl-38 4E-4 4E-4 I

Chromium (24)

Cr-51 2E-3 2E-3 Cobalt (27)

Co-57 SE-4 4 E-4 I

Co-58m 3E-3

?E-3 Co-58 1E-4 9E-5 Co-60 SE-5 3E-5 Copper (29)

Cu-64 3 E-4 2E-4 Curium (96)

Cm-242 2E-5 2E-5 Cm-243 5E-6 2E-5 Cm-244 7E-6 3 E-5 Cm-245 4E-6 3 E-5 I

Cm-246 4E-6 3E-5 Cm-247 4E-6 2E-5 Cm-248 4E-7 1E-6 Cm-249 2E-3 2E-3 Dysprosium (66)

Dy-165 4E-4 4 E-4 Dy-166 4E-5 4 E-5 I

I F-3

I Hope Creek ODCM Rev 15 l

Table F-1 (Continued)

Element Isotope Soluble Conc.

Insoluble Conc.

I (uci/ml)

(uci/ml)

Dysprosium (66) 1-135 4E-6 7E-5 Iridium (77)

Ir-190 2E-4

..E-4 I

Ir-192 4E-5 4E-5 Ir-194 3E-5 3 E-5 Iron (26)

Fe-55 8 E-4 2E-3 Fe-59 6E-5 5E-5 Lanthanum (57)

La-140 2E-5 2E-5 Einsteinium (99)

Es-253 2E-5 2E-5 Es-254m 2E-5 2E-5

,g Es-254 1E-5 1E-5 3

Es-255 3E-5 3E-5 Erbium (68)

Er-169 9E-5 9E-5 Er-171 1E-4 1E-4 Europium (63)

Eu-152 (9.2 hrs) 6E-5 6E-5 Eu-152 (13 yrd 8E-5 8E-5 Eu-154 2E-5 2E-5 Eu-155 2E-4 2E-4 Fermium (100)

Fm-254 1E-4 1E-4 I

Fm-255 3E-5 3 E-5 Fm-256 9E-7 9E-7 I

Fluorine (9)

F-18 8E-4 SE-4 Gadolinium (64)

Gd-l53 2E-4 2E-4 Gd-159 8E-5 8E-5 Gallium (31)

Ga-72 4E-5 4E-5 Gennanium (32)

Ge-71 2E-3 2E-3 Gold (79)

Au-196 2E-4 1E-4 Au-198 5E-5 SE-5 Au-199 2E-4 2E-4 Hafnium (72)

Hf-l81 7E-5 7E-5 I

Holmium (67)

Ho-166 3E-5 3 E-5 Hydrogen (3)

H-3 3E-3 3 E-3 Indium (49)

In-113m iE-3 1E-3

)

In-ll4m 2E-5 2E-5 I

In-115m 4E-4 4E-4 I

In-115 9E-5 9E-5 I

I F-4

i Hope Creek ODCM Rev 15 Table F-1 (Continued)

Element Isotope Soluble Conc.

Insoluble Conc.

(uci/ml)

Iodine (53)

I-125 2E-7 2E-4 I-126 3 E-7 9E-5 I-129 6E-8 2E-4 I-131 3 E-7 6E-5 I

I-132 8E-6 2E-4 I-133 1E-6 4E-5 I-134 2E-5 6E-4 Lead (82)

Pb-203 4E-4 4E-4 Pb-210 1E-7 2E-4 Pb-212 2E-5 2E-5 I

Lutetium (71)

Lu-177 IE-4 IE-4 Manganese (25)

Mn-52 3 E-5 3 E-5 I

Mn-54 1E-4 1E-4 Mn-56 lE-4 lE-4 Mercury (80)

Hg-197m 2E-4 2E-4 Hg-197 3 E-4 SE-4 Hg-203 2E-5 1E-4 Molybdenum (42)

Mo-99 2E-4 4E-5 Neodymium (60)

Nd-144 7E-5 8E-5 Nd-147 6E-5 6E-5 Nd-l49 3 E-4 3 E-4 Neptunium (93)

Np-237 3 E-6 3E-5 Np-239 1E-4 1E-4 I

Nickel (28)

Ni-59 2E-4 2E-3 Ni-63 3E-5 7E-4 Ni-65

'1E-4 1E-4 Niobium (41)

Nb-93 m 4 E-4 4E-4 Nb-95 1E-4 1E-4 ht-97 9E-4 9E-4 I

Osmium (76)

Os-185 7E-5 7E-5 Os-191m 3E-3 2E-3 I

Os-191 2E-4 2E-4 Os-193 6E-5 5E-5 Palladium (46)

Pd-103 3 E-4 3E-4 Pd-109 9E-5 7E-5 I

I F-5

I Hope Creek ODCM Rev 15 Table F-1 (Continued)

Element Isotope Soluble Conc.

Insoluble Conc.

I (uci/ml)

(ucilml)

Phosphorus (15)

P-32 2E-5 2E-5 I

Platinum (73)

Pt-191 1E-4 1E-4 Pt-193m iE-3 1E-3 Pt-19'l 9E-4 2E-3 Pt-19 /m lE-3 9E-4 Pt-197 1E-4 1E-4 Plutonium (94)

Pu-238 S E-6 3 E-5 Pu-239 5E-6 3E-5

~

Pu-240 SE-6 3E-5 I

.p-241 2E-4 lE-3 Lu-242 SE-6 3E-5 Pu-243 3 E-4 3E-4

_ Polonium (84)

Po-210 7E-7 3E-5

~

Potassium (19J K-42 3 E-4 2E-5 Praseodymium (59)

Pr-142 3 E-5 3E-5 Pr-143 SE-5 5E-5 Promethium (61)

Pm-147 2E-4 2E-4 Pm 149 4E-5 4E-5 I

Protactinium (91)

Pa-230 2E-4 2E-4 Pa-231 9E-7 2E-5 I

Pa-233 1E-4 1E-4 i

Radium (88)

Ra-223 7E-7 4E-6 Ra-224 2E-6 SE-6 Ra-226 3 E-8 3E-5 Ra-228 3E-8 3 E-5 Rhenium (75)

Re-183 6E-4 3 E-4 Re-186 9E-5 5E-5 Re-187 3 E-3 2E-3 I

Re-188 6E-5 3 E-5 Rhodium (45)

Rh-103m lE-2 lE-2 i

Rh-105 1E-4 1E-4 I

Rubidium (37)

Rb-86 7E-5 2E-5 Rb-87 IE-4 2E-4 Ruthenium (44)

Ru-97 4 E-4 3E-4 Ru-103 8E-5 8E-5

, I I

I

I Hope Creek ODCM Rev 15 Table F-1 (Continued)

Element Isotope Soluble Conc.

Insoluble Conc.

I (uci/ml)

(uci/ml)

Ru-105 lE-4 l E-4 I

Ru-106 1E-5 1E-5 Samarium (62)

Sm-147 6E-5 7E-5 Sm-151 4 E-4 4 E-4 Sm-153 8E-5 8E-5 Scandium (21)

Sc-46 4E-5 4E-5 Sc-47 9E-5 9E-5 Sc 48 3 E-5 3E-5 l

Selenium (34)

Se-75 3 E-4 3 E-4 I

Silicon (13 Si-31 9E-4 2E-4 Silver (47)

Ag-105 lE-4 lE-4 Ag-110m 3 E-5 3 E-5 Ag-111 4E-5 4E-5 Sodium (11)

Na-22 4E-5 3 E-5 Na-24 2E-4 3 E-5 Strontium (38)

Sr-85m 7E-3 7E-3 Sr-85 1E-4 2E-4 Sr-89 3 E-6 3E-5 I

St-90 3E-7 4E-5 Sr-91 7E-5 SE-5 Sr-92 7E-5 6E-5 Sulfur (16)

S-35 6E-5 3 E-4 Tantalum (73)

Ta-182 4E-5 4E-5 Technetium (43)

Tc-96m lE-2 lE-2 Tc-96 1E-4 5E-5 Tc-97m 4E-4 2E-4 I

Tc-97 2E-3 8 E-4 Tc-99m 6E-3 3 E-3 I

Tc-99 3 E-4 2 E-4 Tellurium (52)

Te-125m 2E-4 1 E-4 Te-l 27m 6E-5 5E-5 Te-127 3E-4 2E-4 Te-129m 3E-5 2E-5 Te-129 8 E-4 8 E-4 I

Te-131 m 6E-5 4E-5 I

I F-7

Hope Creek ODCM Rev 15 Table F-1 (Continued) ig Element Isotope Soluble Conc.

Insoluble Conc.

5 (uci/ml)

(uci/ml)

Te-132 3 E-5 2E-5 Terbium (65)

Tb-160 4E-5 4 E-5 Thallium (8I)

TI-200 4 E-4 2E-4 T1201 3 E-4 2E-4 TI-202 1E-4 7E-5 TI-204 IE-4 6E-5 Thorium (90)

Th-227 2E-5 2E-5 I

Th-228 7E-6 1E-5 Th-230 2E-6 3 E-5 I

Th-231 2E-4 2E-4 Th-232 2E-6 4E-5 Th-natural 2E-6 2E-5 Th-234 2E-5 2E-5 Thulium (69)

Tm-170 SE-5 5E-5 Tm-171 SE-4 SE-4 Tin (50)

Sn-113 9E-5 8E-5 Sn-124 2E-5 2E-5 Tungsten (74)

W-181 4E-4 3 E-4 W-185 1E-4 1E-4 i

W-187 7E-5 6E-5 Uranium (92)

U-230 SE-6 5E-6 U-232 3E-5 3E-5 U-233 3E-5 3 E-5 U-234 3E-5 3 E-5 U-235 3E-5 3E-5 I

U-236 3E-5 3 E-5 U-238 4E-5 4 E-5 I

U-240 3 E-5 3 E-5 O'-natural 3 E-5 3 E-5 Vanadium (23)

V-48 3 E-5 3E-5 Ytterbium (70)

Yb-175 1E-4 1E-4 I

F-8

1 4

Hope Creek ODCM Rev 15 I

Table F-1 (Continued)

Element Isotope Soluble Conc.

Insoluble Conc.

(uci/ml)

Yttrium Y-90 2E-5 2E-5 I.

Y-91 m 3E-3 3E-3 Y-91 3E-5 3 E-5 Y-92 6E-5 6E-f Y-93 3E-5 3E-5 Zine (30)

Zn-65 IE-4 2E-4 Zn-69m 7E-5 6E-5 Zn-69 2E-3 2E-3 g

Zirconium (40)

Zr-93 SE-4 8E-4 5

Zr-9 5 6E-5 6E-5 t

Zr-97 2E-5 2E-5 4

Any single radio-3 E-6 3E-6 nuclide not listed above with decay mode other than alpha emission or 4

spontaneous fission j

and with radio -

active half-life greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Any single radio-3E-8 3E-8 nuclide not listed above, which decays

=

l by alpha emission or spontaneous fission.

Notes:

4

1. If the identity of any radionuclide is not known, the limiting values for purposes of this table shall be: 3E-8 uci/ml.

2. If the identity and concentration of each radionuclide are known, the limiting values should be derived as follows: Determine, for each radionuclide in the mixture, the ratio between the quantity present in the mixture and the limit otherwise established in Appendix B for the specific radionuclide not in a mixture. The sum of such ratios for all the radionuclides in the mixture may not exceed "1" (i.e. " unity").

I I

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