ML20067D574

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Semiannual Radioactive Effluent Release Rept, Jul-Dec 1993
ML20067D574
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 12/31/1993
From: Miltenberger S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N94030, NUDOCS 9403080302
Download: ML20067D574 (54)
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Public Service Electric and Gas Company Steven E. Miltenberger Pubuc Serwce Electric and Gas Company P O Bo< 236. Hancocks f3ndge, NJ 08038 609-339-4199 v,e p.cc, . , e ,, y c n , r ; , , , , ownr FEB 2 81994 NLR-N94030 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

RADIOACTIVE EFFLUENT RELEASE REPORT - 16 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In accordance with Section 6.9.1.7 of Appendix A to the Operating License for Hope Creek Generating Station (HCGS), Public Service Electric and Gas Company (PSE&G) hereby transmits one copy of the semi-annual Radioactive Effluent Release Report, RERR-16. This report summarizes liquid and gaseous releases and solid waste shipments from the Hope Creek Generating Station for the period of July 1 through December 31, 1993.

Should you have any questions regarding this transmittal, please feel free to contact us.

Sincerely, J

1 Attachment (1) 0.{ (I *7 ,

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94030B0302 931231 PDR ADOCK 05000354 R PDR

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s' . FEB 2 81994 Document Control Desk 2 NLR-N94030 l

RERR REPORT only l

.l C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. C. Stone, Licensing Project Manager U. S. Nuclear Regulatory Commission one White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. C. S. Marschall (SO9)

USNRC Senior Resident Inspector Mr. Kent Tosch, Manager IV NJ Department of Environmental Protection Division of Environmental Quality CN 415 Trenton, NJ 08625 t

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8 HOPE CREEK GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HCGS RERR-16 DOCKET NO. 50-354 OPERATING LICENSE NO. NFP-57 l

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HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1993 Table of Contents INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . 1 PART A. PRELIMINARY SUPPLEMENTAL INFORMATION . . . . . . . . . 2 1.0 REGULATORY LIMITS . . . . . . . . . .. . . . . . . . 2 1.1 Fission and Activation Gas Release Limits . . . . 2 1.2 Iodine, Particulates, and Tritium . . . . . .. . 2 1.3 Liquid Effluents Release Limits . . . . . . . . . 3 1.4 Total Dose Limit . . . . . . . . . . . . . . . . 3 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) . . . . . .. 3 3.0 AVERAGE ENERGY . . . . . . . . . . . . . . . . . .. . 4 4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4 5.0 BATCH RELEASES . . . . . . . . . . . . . . . . . . . . 6 6.0 UNPLANNED RELEASES . . . . . . . . . . . . . . . . . . 6.

7.0 ELEVATED RADIATION MONITOR RESPONSES . . . . . . . - . . 6 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE.

EFFLUENT RELEASE REPORTS . . .. . . . . . . . . . . . 6 PART B. GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . 7 PART C. LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . 7 PART D. SOLID WASTE . . . . . . . . . . . . . . . . . .. . . 7 PART E. RADIOLOGICAL IMPACT ON MAN . . . . . . . . . . . . . .7 Liquid Pathways . . . . . . . . . . . . . . . . . . . 7 Air Pathways . . . . . . . . . . . . . . . . . . . . . 8 Direct Radiation . . . . . . . . .- . . . . . . . . . . 8 Total Dose . . . . . . . . . . . . . . . . . . . . . . 9 Dose to Members of the Public on Site . . . . . . . . '

9 Assessment . . . . . . . . . . . . . . . . . . . . . 10 PART F. METEOROLOGICAL DATA . . . . . . . . . . . . . . . . 11 PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES . . . 11 PART H. INOPERABLE MONITORS

. . . . . . .. . .. . . . . . 11 PART I. PROCESS CONTROL PROGRAM (PCP) CHANGES. . . . . . . . 11 PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES. . . . . . 11

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4 HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1993 l

INTRODUCTION I This report, HCGS-RERR-16, summarizes information pertaining to the releases of radioactive materials in liquid, gaseous and solid form from the Hope Creek Generating Station (HCGS) for the period July 1, 1993 to December 31, 1993.

The Hope Creek Generating Station (;ICGS) 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 approximately 1067 MWe.

The HCGS 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 Hope Creek Technical Specifications. Our responses to parts A-F of the

" Supplemental Information" section of Regulatory Guide 1.21, Appendix B, are included in the following pages.

As required by Regulatory Guide 1.21, the Hope Creek Technical Specification 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.

Hope Creek generated 4,417,512 megawatt-hours of electrical energy (net) during the reporting period.

Results of liquid and gaseous composites analyzed for Sr-89, Sr-90 and Fe-55 for the fourth quarter of 1993 were not available for inclusion in this report. The results of these composites will be provided in the next Radioactive. Effluent Release Report.

The Sr-89, Sr-90 and Fe-55 analyses for the first half of 1993 (refer to RERR-15) have been completed; amenc'ed pages to RERR-15 are included in this report.

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PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS 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 gases released in gaseous effluents from the site to areas at and beyond the site boundary, 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, 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.

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,I-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

In addition, the dose to a member of the public from iodine-131, iodine-133, 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:

During any calendar quarter: Less than or equal to 7.5 mrems to any organ and, During any calendar year: Less than or equal to 15 mrems to any organ.

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1.3 Liquid Effluents Release Limits

) The concentration of radioactive material released in i

liquid effluents 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 l limited to 2E-4 microcuries per milliliter.

1 In addition, the dose or dose commitment to a member of the public from radioactive materials in liquid l effluents released to unrestricted areas shall be l 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 curing any calendar year: Less 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 menber 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 mremsj.

2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)

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

a. MPC values were not used to determine the maximum release rates for fission gases, iodines, or particulates.
b. MPC values as stated in 10CFR20, Appendix B, Table-II, Column 2 are used for liquid effluents.
c. The MPC value used for dissolved or entrained noble gases is 2E-4 microcuries per milliliter.

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4 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 HCGS are not based upon average energy.

Therefore this section is not applicable to HCGS.

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 routed to tho 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, floor drain sample tanks, detergent drain tanks, and the condensate storage tank dike. Normally, there are- no continuotes 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 treated as absent.

4.2 Gaseous Effluents Gaseous effluent streams are monitored and sampled in accordance with Table 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 iodine, particulates.and noble gases; the FRVS is continuously monitored for >

noble gases. The NPV and SPV monitors have moving 4

particulate and fixed charcoal filters; the FRVS monitor has fixed particulate and charcoal filters.

The filters and charcoal are changed weekly, and are analyzed on a multichannel analyzer. The NPV and SPV are sampled monthly for noble gases and tritium.

The detection requirements of Tables 4.11.2.1.2-1 of the Technical Specifications are achieved or exceeded.

Radionuclides detected 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 treated as absent.

Continuous Mode gaseous releases are quantified by routine (monthly) 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 the entire sampling period in order to estimate the normal continuous release of radioactivity through the plant vent.

When monthly vent grab samples yield no detectable activity, continuous mode releases are quantified by integrating Radiation Monitor System readings.

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-release sampling and isotopic analysis. Specific activities 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.

Elevated plant vent radiation monitoring system readings while the channel is in 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 volume of effluent discharged while the channel was in an alarm state in order to estimate the total activity discharged.

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4.3 Estimated Total Error The estimated total error of reported liquid 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 concentration levels are not included since error estimates at the LLD are not defined.

The estimated total error of reported solid releases is within 25%.

5.0 DATCH 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 3 unplanned releases. The contamination of the Auxiliary Boilers due to a small leak in the radwaste evaporators resulted in three unplanned liquid releases during this reporting period. The unplanned releases were liquid batch releases from the Auxiliary Boiler to the Cooling Tower Blowdown line which discharges to the Delaware River. Representative samples were taken before each release and each batch release was monitored by a Radiation Monitor equipped with an Alarm function to insure 10 CFR 20 Appendix B values were not exceeded. A total of 1.22E-3 curies of radioactivity was released due to the contamination of the Auxiliary Boilers. Air samples taken during steaming operations did not detect any_ gaseous radioactivity above its Lower Limit of Detection (LLD). Table 2 radionuclide summaries include the values from the unplanned releases.

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

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8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS Our last report (RERR-15) did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the first half of 1993. Amended pages to RERR-15 are included at the end of this report.

PART B. GASEOUS EFFLUENTS See Summary Tables 1A through IC.

PART C. LIQUID EFFLUENTS See Summary Tables 2A through 2B. )

PART D. SOLID WASTE See Summary in Table 3.

PART E. RADIOLOGICAL IMPACT ON MAN i The calculated individual doses in this section are based on actual locations of nearby residents and farms. The population '

dose impact is based on historical site specific data 1.e.,

food production, milk production, feed for milk animals and seafood production.

The doses ..are calculated using methods described in Regulatory Guide 1.109 and represent calculations for the six month reporting interval. Individual doses from batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as described in the Of fsite Dose Calculation Manual. Population doses were calculated using the meteorological dispersion coefficients for the six month reporting interval.

Liauid Pathways Doses to the " maximum hypothetical individual" in the population from liquid releases are primarily from the scafood ingestion pathway. Calculated doses are as shown below.

Total body dose : 4.73E-02 mrem Highest organ dose (LIVER): 1.08E-01 mrem Dose to the 6 million individuals living within the 50 mile radius of the plant site:

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i Total population dose: 5.33E-01 person-rem Average population dose: 8.93E-05 mrem / person Air Pathways l

The calculated doses to individuals via the air l pathway are shown below: J Total body dose: 1.57E-01 mrem Skin dose: 3.43E-01 mrem Highest organ dose due to radiciodines and particulates with half lives greater than 8 days:

1.54E-04 mrem to the LIVER Dose to the 6 million individuals living within the 50 mile radius of the plant site:

Total population dosa: 3.01E-01 person-rem Average population dose: 5.04E-05 mrem / person

. 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 Hope Creek Generating Stations at Artificial Island, and natural background radiation.

TLD data for the six month reporting period is given below:

TLD Location Measurement 2S-2 0.3 mile 5.8 mrad / month SS-1 0.9 mile 6.3 mrad / month These values are interpreted to represent natural background, since the values 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.

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

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<25 mrem total body or any organ

<75 mrem thyroid for a calendar year. For Artificial Island, the major sources of dose are from liquid and gaseous effluents from the Hope Creek and Salem plants.

The following doses to a " maximum hypothetical individual " have been calculated for the six ronth reporting period. They are the sum of gaseous and liquid pathway doses for the Salem 1 and 2 and Hope Creek plants:

0.723 mrom total body 2.030 mrem organ (GI-LLI) 0.587 mrem thyroid Dose to members of the oublic due to activities inside the site boundarv.

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:

a. Such persons are participating or spectators in company softball league
b. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per week on site
c. dose due to airborne pathway (inhalation and immersion)
d. persons are located about 3/4 mile east of plant discharge points (baseball fields)
e. occupancy coincides with batch gaseous discharges For the six month reporting period, the calculated doses are:

3.17E-04 mrem total body 3.22E-04. mrem organ (Lung) 3.17E-04 mren thyroid 9

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Assessment Gaseous and liquid effluents released from Hope Creek resulted in a minimal dose to the maximum hypothetical individual. The dose for the 6 month period was a small fraction of all applicable limits.

Individual noble gas radionuclide concentrations are too low to measure directly. Calculated doses from noble gases are based on a default isotopic mixture, which assumes little decay, and han principally short lived species with large dose factors. Because of this assumed isotopic mix, calculated doses are probably conservati.ve rey a factor of 25.

The following two trend graphs show the total curies of gaseous and liquid effluents released for Hope Creek since plant operation in 1986. Calculated doses in the graphs are to the maximum hypothetical individual.

Hope Creek Gaseous Emunnts Cunes of Notde Gases Roteneed

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Hope Creek LkpAd Emuents Curies Re4ensed and CakaAnted Doses i Note :Oscumso duees are in me mannum hyounma:m movouw

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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 the third and fourth quarters of 1993 in Tables 5 and 6.

PART G. OFFBITE DOSE CALCULATION MANUAL (ODCM). CHANGES During this period, there was a revision to the HCGS Off-site Dose Calculation Manual. The revision consisted of updating the ODCM to reflect current Environmental Sampling Locations. Copies of the revised ODCM pages are attached to the end of this report.

PART H. INOPERABLE MONITORS During this period, there were no effluent monitors inoperable for greater than 30 days.

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

PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES During the reporting period, 2 additional TLD's were added to the Environmental Monitoring program. The new TLD locations, 3.8 miles NW and 6.0 miles ENE of the plant ventilation discharge, were added for program enhancement purposes. The ODCM for Salem and Hope Creek '

stations were updated to reflect the added locations. A l complete list of the current sampling locations is included in the ODCM attached to the end of this report. j o l I

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i' HOPE CREEK GENERATING STATION TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1993 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES l

l Est. I 3rd 4th Total Units Quarter Quarter Error %

A. Fission and Activation Gases

1. Total release C1 4.22E+01 1.80E+01 25
2. Average release rate for period pCi/sec 5.37E+00 2.29E+00 l 3. Percent of technical t

, specification limit {

l (T.S. 3.11.2.2(a))  % 5.76E-01 2.46E-01  !

! I B. Iodines

1. Total iodine-131,133 Ci 0.00E+00 0.00E+00 25
2. Average release rate for period pCi/sec 0.00E+00 0.00E+00
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))  % 9.01E-04 1.14E-03 C. Particulates

1. Particulates with half-lives >8 days C1 1.28E-03 0.GOE+00 25
2. Average release rate for period pCi/sec 1.63E-04 0.00E+00 _
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))  % 9.01E-04 1.14E-03

4. Gross alpha Ci 5.99E-07 0.00E+00 D. Tritium
1. Total Release Ci 3.53E+01 2.76E+01 25
2. Average release rate for period pCi/sec 4.49E+00 3.51E+00
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))  % 9.01E-04 1.14E-03 (1) For batch releases the estimated overall error is within 10%

(2) Iodine, tritium and particulates are treated as a group 12 i

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HOPE CREEK GENERATING STATION TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1993 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission Gases Krypton-83m Ci 4.24E-01 1.80E-01 0.00E+00 0.00E+00 Krypton-85m C1 4.24E-01 1.80E-01 0.00E+00 0.00E+00 Krypton-87 Ci 1.69E+00 7.21E-01 0.00E+00 0.00E+00 Krypton-88 Ci 1.69E+00 7.21E-01 0.00E+00 0.00E+00 Krypton-89 Ci 1.14E+01 4.88E+00 0.00E+00 0.00E+00 Xenon-133 Ci 8.44E-01 3.61E-01 0.00E+00 0.00E+00 Xenon-135 Ci 2.12E+00 9.01E-01 0.00E+00 0.00E+00 Xenon-135m Ci 2.55E+00 1.08E&OO 0.00E+00 0.00E+00 Xenon-137 Ci 1.31E+01 5.57E+00 0.00E+00 0.00E+00 Xenon-138 Ci 8.01E+00 3.43E+00 0.00E+00 0.00E+00 TOTALS C1 4.22E+01 1.80E+01 0.00E+00 0.00E+00
2. Iodines Iodine-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS Ci 0.00E+00~ 0.00E+00 0.00E+00 0.00E+00
3. Particulates (half-life >8 days)

Manganese-54 Ci 9.09E-05 0.00E+00 0.00E+00 0.00E+00 Cobalt-60 Ci 5.05E-05 0.00E+00 0.00E+00 0.00E+00 Chromium-51 Ci 7.83E-04 0.00E+00 0.00E+00 0.00E+00 Zinc-65 Ci 3.53E-04 0.00E+00 0.00E+00 0.00E+00 TOTALS Ci 1.28E-03 0.00E+00 0.00E+00 0.00E+00 13

HOPE CREEK GENERATING STATION TABLE IC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1993 GASEOUS EFFLUENTS-ELEVATED RELEASES 1

1 There were no elevated gaseous releases during this reporting period.

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HOPE CREEK GENERATING STATION TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1993 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est. ,

3rd 4th Total Units Quarter Quarter Error %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha)
  • Ci 8.76E-02 8.11E-02 25
2. Average diluted concentration during release period. pCi/mL 5.58E-08 1.40E-07
3. Percent of technical specification limit (T.S. 3.11.1.2.(a))  % 1.44E+00 1.71E+00 B. Tritium
1. Total release Ci 2.22E+01 1.31E+01 25
2. Average diluted <

concentration during release period yCi/mL 1.42E-05 2.26E-05

3. Percent of technical specification limit (T.S. 3.11.1.1)  % 4.73E-01 7.53E-01 C. Dissolved and entrained noble gases
1. Total release Ci 2.42E-03 1.28E-03 25
2. Average diluted concentration during release period. 4Ci/mL 1.54E-09 2.21E-09
3. Percent of technical specifiestion limit (T.S. 3. 1.1.1)  % 7.70E-04 1.11E-03 D. Gross alpha activity
1. Total release Ci 0.00E+00 0.00E+00 25 E. Volume of waste release (prior to dilution - I Batch Release) liters 4.58E+06 2.98E+06 25 F. Volume of dilution water used during entire period liters 1.90E+10 1.22E+10 25 15

HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1993 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Niobium-97 Ci 0.00E+00 0.00E+00 4.33E-04 0.00E+00 Chromium-51 Ci 0.00E+00 0.00E+00 3.64E-02 4.44E-02 l Manganese-54 Ci 0.00E+00 0.00E+00 1.53E-02 1.68E-02 Iron-55 Ci 0.00E+00 0.00E+00 1.44E-02 0.00E+00 Iron-59 Ci 0.00E+00 0.00E+00 1.76E-03 4.94E-03 Cobalt-58 Ci 0.00E+00 0.00E+00 1.22E-04 9.69E-04 Cobalt-60 Ci 0.00E+00 0.00E+00 2.85E-03 2.61E-03 Zinc-65 Ci 0.00E+00 0.00E+00 1.50E-02 1.05E-02 Zinc-69m Ci 0.00E+00 0.00E+00 0.00E+00 2.33E-05 Silver-110m Ci 0.00E+00 0.00E+00 9.05E-04 4.13E-04 Sodium-24 Ci 0.00E+00 0.00E+00 4.40E-06 6.10E-07 Technetium-99m Ci 0.00E+00 0.00E+00 4.50E-04 4.10E-04 Arsenic-76 Ci 0.00E+00 0.00E+00 1.03E-05 0.00E+00 Cesium-137 Ci 0.00E+00 0.00E+00 3.34E-07 4.82E-05 Zirconium-97 Ci 0.00E+00 0.00E+00 1.45E-05 0.00E+00 TOTALS Ci 0.00E+00 0.00E+00 8.76E-02 8.11E-02 Tritium Ci O.00E+00 0.00E+00 2.22E+01 1.31E+01 Xenon-133 Ci 0.00E+00 0.00E+00 3.14E-04 9.26E-05 Xenon-135 Ci 0.00E+00 0.00E+00 2.10E-03 1.19E-03 TOTALS Ci 0.00E+00 0.00E+00 2.22E+01 1.31E+01 I

(

)

16

HOPE CREEK GENERATING STATIOil TABLE 3

( EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT.

JULY - DECEMBER 1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1 6-month Est. Total

( 1. Type of waste Units (1) period Error, %

a. Spent resins, filters, m3 7.18E+01 sludges, evaporator bottoms Ci 4.66E+03 25
b. Dry compressible waste, m3 4.00E+00 contaminated equipment. Ci 5.90E-01 25
c. Irradiated components, m3 0.00E+00 control rods Ci 0.00E+00 25
d. Others (described) m3 0.00E+00 Ci 0.00E+00 25 1
2. Estimate of major nuclide composition (for Type A and B waste)

RESINS DAW

(%) (C1) (%) (Ci)

Zinc-65 83.0 3.87E+03 2.2 1.00E-02 Iron-55 13.5 6.28E+02 71.2 4.20E-01

. Manganese-54 2.5 1.17E+02 8.3 5.00E-02 Cobalt-60 1.0 4.66E+01 1.6 1.00E-02 Chromium-51 0.0 0.00E+00 10.9 6.00E-02 Iron-59 0.0 0.00E+00 5.2 3.00E-02 (1) Volumes are measured, activities are est _nated 17

_a

i .

3 HOPE CREEK GENERATING STATION TABLE 3 (CONT'D) l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition I

Number of Mode of. Type of Shipments Transportation Destination Containers 24 Truck Barnwell, SC HIC and 17E Drums l

4 Truck Oak Ridge, TN Strong, Tight Containers I

t 1

IRRADIATED FUEL SHIPMENTS (Disposition)

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

1 18

.i i

HOPE CREEK GENERATING STATION TABLE 4A 1 i

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1993

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY

1. Dates: July 1 - September 30, 1993
2. Type of release: Gas
3. Number of releases during the 3rd Quarter: 0
4. Total time duration for all releases of type listed above:

0.00E+00 min

5. Maximum duration for release of type listed above:

0.00E+00 min

6. Average duration for release of type listed above:

0.00E+00 min

7. Minimum duration for release of type listed above:

0.00E+00 min

8. Average stream flow (dilution flow) during the period of release: N/A f

19

HOPE CREEK GENERATING STATION TABLE 4A (CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1993

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY

1. Dates: October 1 - December 31, 1993

!. 2. Type of release: Gas

3. Number of releases during the 4th Quarter: 1
4. Total time duration for all releases of type listed above:

4.79E+02 min

5. Maximum duration for release of type listed above

4.79E+02 min

6. Average duration for release of type listed above:

4.79E+02 min

7. Minimum duration for' release of type listed above:

4.79E+02 min

8. Average stream flow (dilution flow) during the period of release: N/A 20 l

HOPE CREEK GENERATING STATION TABLE 4B )

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l 1

JULY - DECEMBER 1993 i

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY

1. Dates: July 1 - September 30, 1993
2. Type of release: Liquid
3. Number of releases during the 3rd Quarter: 111
4. Total time duration for all releases of type listed above:

8.84E+03 min

5. Maximum duration for release of type listed above:

1.34E+02 min

6. Average duration for release of type listed above:

8.00E+01 min

7. Minimum duration for release of type listed above:

1.2E+01 min

8. Average stream flow (dilution flow) during the period of release: 38445 gpm I

21

HOPE CREEK GENERATING STATION TABLE 4B (CONT'D)

EFFLUENT.AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1993

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY

1. Dates: October 1 - December 31, 1993
2. Type of release: Liquid
3. Number of releases during the 4th Quarter: 76 j I
4. Total time duration for all releases of type listed above: '

6.16E+03 min

5. Maximum duration for release of type listed above:

1.19E+02 min

6. Average duration for release of type listed above: ,

8.11E+01 min

7. Minimum duration for release of type listed above:

2.9E+01 min

8. Average stream flow (dilution flow) during the period of release: 24371 gpm 22 l

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TABLE 5 PAGE 4 of 9

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ARTIFICIAL ISLAND 7/93 - 9/93 J0lNT DISTRIBUTION OF Wlho DIRECTION AND SPEED BY ATMOSPMERIC 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 PERCEdi SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N O 0.0 6 0.3 54 2.5 78 3.7 36 1.7 7 0.3 0 0.0 181 8.5 NME O 0.0 5 0.2 29 1.4 68 3.2 46 2.2 7 0.3 0 0.0 155 7.3 NE O 0.0 5 0.2 17 0.8 36 1.7 29 1.4 1 0.0 0 0.0 88 4.1 ENE O 0.0 9 0.4 19 0.9 26 1.2 16 0.8 0 0.0 0 0.0 70 3.3 E O 0.0 3 0.1- 12 0.6 22 1.0 6 0.3 0 0.0 0 0.0 43 2.0 ESE O 0.0 7 0.3 5 0.2 15 0.7 18 0.8 0 0.0 0 0.0 45 2.1 SE O 0.0 3 0.1 11 0.5 9 0.4 29 1.4 27 1.3 4 0.2 83 3.9 SSE O 0.0 5 0.2 37 1.7 44 2.1 93 4.4 49 2.3 5 0.2 233 10.9 5 0 0.0 12 0.6 41 1.9 56 2.6 73 3.4 24 1.1 5 0.2 211 9.9 SSW 0 0.0 9 0.4 39 1.8 53 2.5 56 2.6 17 0.8 2 0.1 176 8.3 SV 0 0.0 4 0.2 40 1.9 44 2.1 37 1.7 26 1.2 1 0.0 152 7.1 v$W 0 0.0 9 0.4 32 1.5 34 1.6 37 1.7 4 0.2 0 0.0 116 5.5 W 0 0.0 8 0.4 17 0.8 52 2.4 61 2.9 9 0.4 0 0.0 147 6.9 WNW 0 0.0 5 0.2 27 1.3 53 2.5 34 1.6 4 0.2 2 0.1 125 5.9 NW 0 0.0 2 0.1 24 1.1 49 2.3 36 1.7 5 0.2 1 0.0 117 5.5 NNW 0 0.0 6 0.3 33 1.6 66 3.1 72 3.4 8 0.4 1 0.0 186 8.7 0 0.0 98 4.6 437 20.5 705 33.1 679 31.9 188 8.8 21 1.0 2128 100.0 MIS $1NG HOURS: 80 MEAN WIND SPEED: 11.6 TABLE 5 PAGE 9 of 9

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i ARTIFICIAL ISLAND 10/93-12/93 J0!NT OISTRIBUTION OF WIND DIRECTION AtiO SPEED BY ATMOSPRERIC STABILITY CLASS WIND: 300 FT DELTA T: (300-33FT) ALL STABILITY CLASSES

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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 OIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N 0 0.c 2 0.1 17 0.8 36 1.7 50 2.4 25 1.2 5 0.2 135 6.5 kNE O 0.0 2 0.1 7 0.3 55 2.6 44 2.1 30 1.4 7 0.3 145 7.0 NE O 0.0 0 0.0 21 1.0 41 2.0 56 2.7 32 1.5 0 0.0 150 7.2 ENE O 0.0 1 0.0 15 0.7 33 1.6 45 2.2 10 0.5 0 0.0 10? 5.0 E O 0.0 6 0.3 16 0.8 31 1.5 13 0.6 1 0.0 0 0.0 67 3.2 ESE O' O.0 3 0.1 5 0.2 14 0.7 6 0.3 1 0.0 9 0.4 38 1.8 SE O 0.0 3 0.1 6 0.3 18 0.9 21 1.0 9 0.4 11 0.5 68 3.3 SSE O. 0.0 2 0.1 6 0.3 34 1.6 29 1.4 18 0.9 7 0.3  % 4.6 5 0 0.0 1 0.0 11 0.5 19 0.9 35 1.7 36 1.7 2 0.1 104 5.0 SSW 0 0.0 5 0.2 16 0.8 27 1.3 76 3.7 28 1.3 1 0.0 153 7.4 SW 0 0.0 to 0.5 18 0.9 62 3.0 57 2.7 6 0.3 7 0.3 160 7.7 WSW D 0.0 6 0.3 11 0.5 45 2.2 44 2.1 21 1.0 1 0.0 128 6.2 W- 0 0.0 7 0.3 19 0.9 34 1.6 65 3.1 41 2.0 26 1.3 192 9.2 WNW 0 0.0 5 - 0.2 12 0.6 24 1.2 28 1.3 17 0.8 18 0.9 104 5.0 NW ' O 0.0 6 0.3 34 1.6 31 1.5 92 4.4 48 2.3 12 0.6 223 10.7 MNW D 0.0 4 - 0.2 24 1.2 38 1.8 67 3.2 39 1.9 41 2.0 213 10.2 0 0.0 63 3.0 238 11.4 542 26.1 728 35.0 362 17.4 147 7.1 2080 100.0 MISSING HOURS: 128, MEAN WIND SPEE0: 14.5 1

TABLE 6 PAGE 8 of 9

ARTIFICIAL ISLAND 10/93-12/93 JOINT DISTRIBUTICai M WIND DIRECTION AND SPEED BY ATMCS*itERIC STABILITY CLASS WIND: 300 FT DELTA T: (300-33FT) DIRElflCN VS SPEED ONLY WIND SPEED GROLPS (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 StM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N O 0.0 2 0.1 17 0.8 37 1.8 50 2.4 25 1.2 5 0.2 136 6.5 kNE O D.0 2 0.1 7 0.3 55 2.6 44 2.1 30 1.4 7 0.3 145 7.0 WE O 0.0 0 0.0 21 1.0 41 2.0 56 2.7 32 1.5 0 0.0 150 7.2 ENE O 0.0 1 0.0 15 0.7 33 1.6 45 2.2 to 0.5 0 0.0 104 5.0 E O 0.0 6 0.3 16 0.8 31 1.5 13 0.6 1 0.0 0 0.0 67 3.2 ESE O 0.0 3 0.1 5 0.2 14 0.7 6 0.3 1 0.0 9 0.4 38 1.8 SE O 0.0 3 0.1 6 0.3 18 0.9 21 1.0 9 0.4 11 0.5 68 3.3 SSE O 0.0 2 0.1 6 0.3 34 1.6 29 1.4 18 0.9 7 0.3 96 4.6 5 0 0.0 1 0.0 11 0.5 19 0.9 35 1.7 36 1.7 2 0.1 1 04 5.0 SSW 0 0.0 5 0.2 16 0.8 27 1.3 76 3.7 28 1.3 1 0.0 153 7.4 SW 0 0.0 10 0.5 18 0.9 62 3.0 57 2.7 6 0.3 7 0.3 160 7.7 WSW 0 0.0 6 0.3 11 0.5 45 2.2 44 2.1 21 1.0 1 0.0 128 6.2 W D 0.0 7 0.3 19 0.9 34 1.6 65 3.1 41 2.0 26 1.2 192 9.2 WWW 0 0.0 5 0.2 12 0.6 24 1.2 28 1.3 17 0.8 18 0.9 404 5.0 NW D 0.0 6 0.3 34 1.6 31 1.5 92 4.4 48 2.3 12 0.6 -23 10.7 NW 0 0.0 4 0.2 24 1.2 38 1.8 67 3.2 39 1.9 41 2.0 213 10.2 0 0.0 63 3.0 238 11.4 '543 26.1 728 35.0 362 17.4 147 7.1 2081 100.0 MISSING tt0URS: 127 MEAN WIND SPEED: 14.5 l

t TABLE 6 PAGE 9 of 9 l

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i AMENDMENT TO RERR 15 l

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PART B. GABEOUS EFFLUENTS See Summary Tables 1A through IC.

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

PART D. SOLID WASTE See summary in Table 3.

PART E. RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on actual locations of nearby residents and farms. The population dose impact is based'on historical site specific data 1.e.,

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 six month reporting interval. Individual doses from 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 coefficients for the six month reporting interval.

Liauld Pathways Doses to the " maximum hypothetical individual" in the population from liquid releases are primarily from the seafood ingestion pathway. Calculated doses are as shown below.

Total body dose : 8.54E-02 mrom Highest organ dose (LIVER): 1.93E-01 mrem  ;

Dose to the 6 million individuals living within the l 50 mile radius of the plant site:

Total population dose: 9.80E-01 person-rem Average population dose: 1.64E-04 mrem / person 8

HOPE CREEK GENERATING STATION TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1993 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.

1st 2nd Total Units Quarter Quarter Error %

Fission and activation products

1. Total release (not ,

including tritium, I gases, alpha) Ci 6.31E-02 1.21E-01 25 l

2. Average diluted concentration during release period. pCi/mL 8.94E-08 1.41E-07 4
3. Percent of technical specification limit (T.S. 3.11.1.2.(a))  % 2.53E+00 3.23E+00 B. Tritium i
1. Total release- C1 1.37E+01 1.27E+01 25
2. Average diluted concentration during release period yCi/mL 1.95E-05 1.47E-05
3. Percent of technical specification limit (T.S. 3.11.1.1)  % 6.50E-01 4.90E-01 C. Dissolved and entrained noble gases
1. Total release Ci 2.32E-03 2.54E-03 25
2. Average diluted concentration during release period, pCi/mL 3.28E-09 2.94E-09 i
3. Percent of technical '

specification limit (T.S. 3.11.1.1)  % 1.64E-03 1.47E-03 D. Gross alpha activity

1. Total release Ci 0.00E+00 0.00E+00 25 E. Volume of waste release (prior to dilution -

Batch Release) liters 3.90E+06 3.65E+06 25 F. Volume of dilution water a used during entire period liters 1.17E+10 1.55E+10 25 l 16

HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1993 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE ist 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter Niobium-97 Ci 0.00E+00 '0.00E+00 0.00E+00 3.50E-07 Chromium-51 Ci 0.00E+00 0.00E+00 2.65E-02 4.92E-02 Manganese-54 Ci 0.00E+00 0.00E+00 1.19E-02 1.90E-02 Iron-55 Ci 0.00E+00 0.00E+00 4.02E-03 1.86E-02 l Iron-59 Ci 0.00E+00 0.00E+00 5.33E-04 1.51E-03 Cobalt-58 Ci 0.00E+00 0.00E+00 3.46E-05 2.22E-04 Cobalt-60 Ci 0.00E+00 0.00E+00 2.69E-03 3.32E-03 Zinc-65 Ci 0.00E+00 0.00E+00 1.65E-02 2.81E-02 Silver-110m Ci 0.00E+00 0.00E+00 4.90E-04 3.55E-04 Sodium-24 Ci 0.00E+00 0.00E+00 0.00E+00 1.15E-04 Technetium-99m Ci 0.00E+00 0.00E+00 4.37E-04 4.90E-04 TOTALS Ci 0.00E+00 0.00E+00 6.31E-02 1.21E-01 Tritium Ci i 0.00E+00 0.00E+00 1.37E+01 1.27E+01 Xenon-133 Ci 0.00E+00 0.00E+00 1.01E-04 {

2.20E-04 Xenon-135 Ci 0.00E+00 0.00E+00 2.21E-03 2.32E-03

__________________________________________________________________ j TOTALS Ci 0.00E+00 0.00E+00 1.37E+01 1.27E+01 l l

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HOPE CREEK ODCM -)I REVISION 13 i

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REVISION 13 OF TiiE HOPE CREEK OFFSITE DOSE CALCULATION MANUAL Attached is a breakdown of the revisions made to the Hope Creek Generating Station Offsite Dose Calculation Manual (ODCM). The revision was made to correct previous typographical errors and to update information contained in the ODCM.

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Change #1 ENVIRONMENTAL SAMPLING LOCATIONS Appendix E Page E-3,E-4,E-5 PAGE LOCATION CHANGE COMMENTS E-3 15D1 New Location Added new TLD (TLD) location (Delaware)

E-3 3E1 Added " Farm" Typographical Error E-3 2F4 Added " Farm" Typographical Error E-4 4F2 New Location Added new TLD (TLD) location (New Jersey)

  • E- 5 2G1 New Location Added location to (Vegetable) REMP for vegetable samples

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l OFFSITE DOSE CALCULATION MANUAL FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK GENERATING STATION Revision 13 December 1993 Approval:

SORC Chairman-w Date: / 2-f ff Mtg./ ff' b r i i

Hope Creek ODCM Rev 13 TABLE E-1 (Cont'd)

STATION

.CODI STATION LOCATION SAMPLE TYPES 11D1 3.5 mi. SW of vent GAM 14D1 3.4 mi. WNW of vent; Bay View, Delaware IDM 15D1 3.8 mi. NW of vent; Augustine Beach, Del. IDM l 2E1 4.4 mi. NNE of vent; local farm IDM 3E1 4.1 mi. NE of vent; local farm FPB, FPV, GAM, IDM, VGT, WWA l 3E3 5.6 mi. NE of vent; local farm FPV 7El 4.5 mi. SE of vent; 1 mi. W of Mad ESF, ESS, SWA Horse Creek 9El 5.0 mi. SW of vent IDM 11E2 5.0 mi. SW of vent IDM 12E1 4.4 mi. WSW of vent; Thomas Landing IDM 13E1 4.2 mi. W of vent; Diehl House Lab IDM 16El 4.1 mi. NNW of vent; Port Penn AIO, APT, IDM SOL 1F1 5.8 mi. N of vent; Fort Elfsborg AIO, APT, IDM SOL 1F2 7.1 mi. N of vent; midpoint of SWA Delaware 2F2 8.7mi. NNE of vent; Salem Substation AIO, APT, IDM, RWA 2F3 8.0 mi. NNE of vent; Salem Water Co. PWR,PWT ,

l 2F4 6.3 mi. NNE of vent; local farm FPV,FPL, SOL l l 2F5 7.5 mi. NNE of vent; Salem High School IDM l

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I Hope Creek ODCM Rev 13 TABLE E-1 (Cont'd)

STATION l CODE STATION LOCATION SAMPLE TYPES 2F6 7.3 mi. NNE of vent; Southern Training IDM Center 2F7 5.7 mi. NNE of vent; local farm MLK,VGT, SOL i

3F2 5.1 mi. NE of vent; Hancocks Bridge IDM  !

Municipal Building 3F3 8.6 mi. NE of vent; Quinton Township IDM School 4F2 6.0 mi. ENE of vent; LAC Township IDM l l 5F1 6.5 mi. E of vent SOL,IDM SF3 6.5 mi. E of vent; local farm FPL 6F1 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.1 mi. SE of vent; Bayside, NJ IDM 10F2 5.8 mi. SSW of vent IDM 11F1 6.2 mi. SW of vent; Taylor's Bridge IDM Delaware 11F3 5.3 mi. SW of vent; Townsend, DE MLK,VGT, SOL i

12F1 9.4 mi. WSW of vent; Townsend Elem. IDM School 13F2 6.5 mi. W of vent; Odessa, DE IDM 13F3 9.3 mi. W of vent; Redding Middle IDM School, Middletown, DE 13F4 9.8 mi. W of vent; Middletown, DE IDM 14F2 6.6 mi. WNW of vent; Boyds Corner IDM 14F3 5.4 mi. WNW of vent; 16:41 farm FPV 14F4 7.6 mi. WNW of vent; local farm MLK, SOL,VGT 15F3 5.4 mi. NW of vent IDM E-4

Hope Creek ODCM Rev 13 TABLE E-1 (Cont'd) l l STATION l CODJ STATION LOCATION SAMPLE TYPES 16F1 6.9 mi. NNW of vent; C&D Canal ESS, SWA 16F2 8.1 mi. NNW of vent; Delaware City IDM Public School 1G1 10.3 mi. N of vent; local farm FPV I 1G3 19 mi. N of vent; Wilmington, DE IDM 2G1 12 mi. NNE of vent; Wilmington, DE FPV l 2G2 13.5 mi. NNE of vent; local farm FPV 3G1 17 mi. NE of vent; local farm IDM, MLK, VGT SOL 10G1 12 mi. SSW of vent; Smyrna, DE IDM 16G1 15 mi. NNW of vent; Greater Wilmington IDM Airport 3H1 32 mi. NE of vent; National Park, NJ IDM 3H3 110 mi. NE of vent; Research and AIO, APT, IDM Testing Laboratory 3HS 25 mi. NE of vent; local farm FPL, FPV l

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