ML20114C175

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Semiannual Radioactive Effluent Release Rept for Jan-June 1992
ML20114C175
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/30/1992
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N92122, NUDOCS 9209020029
Download: ML20114C175 (50)
v • d • e


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AUG P,71992 ilLR-N92122 United States liuclear Regulatory Commission Document Control Desk Washington,-DC 20555 Gentlemon [

RADIOACTIVE EFFLUENT RELEASE REPORT - 13 llOpE CREEK -GENERATING STATIOli DOCKET NO. 50-354 In accordance with Section 6.9.1.11 of Appendix A to the oporating Licenso for llope Creek Generating Station (llCGS),

public Service Electric and Gas Company (pSET.G) hereby transmits one copy of the semi-annual Radioactivo Effluent Release Report,

-RERR-13. This report summarizes liquid and gaseous releases and solid wasto shipments from the !!opo Crook Generating Station for the period January 1 through June 30, 1992.

Should you have any questions regarding this transmittal, please fool-froo to contact us.

Sincoroly, Attachment (1) / ( 4 .g, ,

n JcA 010080 9209020029 920630 DR- ADOCK0500g4 _[ [ [

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4 Document Control Denk 2 AUG 2 71992 111,1(~l19 212 2 EEEILIGPORT_only C Mr. T. T. Martin, Administrator - llegian I U. S. Iluclear llegulatory Comminsion 475 Allendale l<oad King of Prunnia, PA 19406 Mo. A. Kollor U. S. 11uclear Itegulatory Comminnion Ono White l'11nt llorth 11555 Itockville Piko Ilockvillo, MD 20052 Mr. T. P. Johnson (805)

USilllC Senior llenident Inapector )i 4

Mr, K. Touch, Chief 11J Department of Environroental Protection Divinion of Environmental Quality Bureau of 11uclonr Engineering C11 415 Trenton, 11J 08625 m

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Il0PE CREEK GEllERATil1G STATIO!1 SEliT All!!UAL RADIOACTIVE EFFLUEliT RELEASE REPORT IICGS RERR-13 DOC 1'ET 110. 50-354 OPERATI!1G LICE!JSE 110. liFP-57

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ilOPE CREEK GEllERATIliG STATIOli RADIOACTIVE EFFLUEllT RELEASE REPORT JANUARY - JUllE 1992 Table of Contents INTRODUCTIO!I . . . . . . . . . . . . . . . . . . . . . . . . . . 1 PART A. PRELIMINARY SUPPLEMEllTAL I!1 FORMATION . . . . . . . . . 2 1.0 REGULATORY LIMITS . . . . . . . . . . . . . . . . . . 2 1.1 Fission and Activation Gas Releaco Limits . . . . 2 1.2 Iodine, Particulatos, and Tritium . . . . . . . . 2 1.3 Liquid Effluents Release Limits . . . . . . . . . 3 _

1.4 Total Doso Limit . . . . . . . . . . . . . . . . 3 2.0 MAXIMUM PERMISSIBLE CONCEllTRATIO!1S (MPC) . . . . . . . 3 3.0 AVERAGE ENERGY . . . . . . . . . . . . . . . . . . . . 4 4.C MEASUREMEllTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4 50 BATC!! RELEASES . . . . . . . . . . . . . . . . . . . . 6 6.0 UllPLANNED RELEASES . . . . . . . . . . . . . . . . . 6 7.0 ELEVATED RADI ATION MONITOR RESPollSES . . . . . . . . . 6 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS . . . . . . . . . . . . . . . 7 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 Doso to Members of the Public on Site . . . . . . . . 9 Assessment . . . . . . . . . . . . . . . . . . . . 10 PART F. METEOROLOGICAL DATA . . . . . . . . . . . . . . . . 11 PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM) CilANGES . . . 11 PART H. INOPERABLE MONITORS . . . . . . . . . . . . . . . . 11 PART I. ENVIRONMENTAL MONITORING LOCATION CHANGES . . . . 11

. . . = - ~ --.-. - -- .-. - -_ - - - - _-- _ - _ _ - . .

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HOPE CREEK GENERATINC STATION I RADIOACTIVE EFFLUENT RELEASP "EPORT i JANUARY - JUNE 1992 INTRODUCTION This report, HCGS-RERR-12, summarizes information portaining to the releases of radioactive materials in liquid, gaseous and solid form from the Hope Creek Generating Station (HCGS) for the period January 1, 1992 to June 30, 1992.

The Hope Crook Generating Station (HCGS) 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 not output of approximately 1067 MWe. The HCGS achieved initial criticality on June 28, 1986 and went lato 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.. Preceding the tables summarizing the gaseous and liquid discharges and solid waste shipments are our responses to parts A-F.of the " Supplemental Information" section of Regulatory Guide 3.21, Appendix B.

As required by Regulatory Guide 1.21, our Technical Specification limits are. described in detail within this report along uith a summary description of how total activity measurements and their approximations were developed.

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

Hope Creek generated 4,070,028 megawatt-hours of electrical energy (not) during the reporting period.

Results of liquid and gaseous composites analyzed for Sr-89, Sr-90'and Fe-55 for-the second quarter of 1992 were not available for-inclusion in this report. The rerults of these composites will lx3 provided in the next Radioactive Effluent Release Repor2.

The Sr-89, Sr-90 and Fe-55 analyses for the second half of 1991 (refer to RERR-12) have been completed; amended pages to RERR-12 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 r.t 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 Iodino, Particulates, and Tritium The dose rate due to radioactive mat.crials 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 racionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mcoms/yr to any organ.

In addition, the dose to a member of the public from iodine-131,133, from tritium, and from all radionuclides in_ particulate form with half-lives greater than 8 days in gaseous affluents released, from each reactor unit, 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 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 Roleaso Limits The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited ,

to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclidos other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 microcuries per milliliter.

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

During any calendar quarter: Less than or equal to 1.5 mrema to the total body, and less than or equal to 5 mroms to any organ, and During any calendar years Less than or equal to 3 mroms 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 er equal to 75 mrems).

2.0 MAXIMUM PERhISSIBLE 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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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 .

t 4.1 Liquid Effluents a Liquid effluents are monitored in accordance with Table 4.11.1.1.1-1 of the Technical Specifications. During the period of record, all liquid wastes were 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, floor drain sample tanks, detergent drain tanks, and the condensate storage tank dike.;Normally,_there are no continuous liquid releases. Specific activities from analysen were nultiplied by the volume of effluent discharged to the environment in order to determine the total liquid ,

activity discharged.

The detection requirements of Table 4.1.1.1-1 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 j 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 continuously monitored for noble gases. The NPV and SPV monitorn have moving particulate and fixed _ charcoal filters; the FRVS monitor has fixed particulate e.d charcoal filters.

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

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

Radionuclides measured at concentrations below the Technical Specification detection limit (LLDs) are treated as being present. Radionuclidos for which no activity was detected while meeting the required LLDs are treated as absent.

Continuous Mode gaseous releases are quantified by routino (monthly) sampling and isotopic analyses of the plant vents. If noble gases are detected during the toutino-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 abundancos for those_ integrations are based on the ANSI N237-1976/ANS-18.1 mix for BWRs.

Doses calculated from this data employ the motheds from Section 2.0 and Appendix C of the Hope Creek ODCM.

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

Elevated. plant vent radiation monitoring system >

-readings while the chanrel-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 efficiengy 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 d!s harged.

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

The estimated total error of the reported continuous gaseous releaues 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 cf the reported batch gaseous releases is within 10%.

Error cotimaton 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 ire 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 thin reporting period, the plant vont radiation monitors indicated slightly elevated readings on several occasions. As indicated above monitor readings were quantified and treated as continuous releases. The elevated readings are included in Tables 1A and 18.

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8.0 HODIFICATION TO PREVIOUS RADI0 ACTIVE EFFLUENT RELEASE REPORTS our last report (RERR-12).did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the second half of 1991. Amended pages to RERR-32 are included at the end of this report.

Additionally calculational errors were found in previous I reports, amended pages are included at 'he end of this report.

PART D. GABEOUS EFFLUENTS See Summary Tables 1h through 10.

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 d4ta i.e., food production, milk production, feel for milk animals and seafood production.

The doses were calculated using methods derarlben 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 Done Calculation Manual,

, Population doses were calculated using the acteorological l dispersion coefficients for the six month reporting interval.

Liauld P.a.thways Doses to individuals in the population from liquid releases are primarily from the sonfood ingestion pathway. Calculated doses to individuals are as shown below. '

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Total body dose to an individual: 3.59E-02 mrom ilignent organ dose: 1.01E-01 mrom to the GI-LLI Dose to the 6 million individuals living within the 50 mile radius of the plant site:

Total population dono: 4.05E-01 person-rem Average population dose: 6.78E-05 mrem / person Air Pathways The calculated doses to individuals via the air pathway are shown below:

Total body dose: 3.20E-01 mrem Skin dose: 7.00E-01 mrem

}!ighest organ dose due to radiciodines and particulates with half lives greater than 8 days:

1.96E-04 mrem to the Liver.

Dose to the 6 million individuals living wi.hin the 50 mile radius of the plant site:

Total population dose: 3.48E-01 person-rem Average population dose: 5.83E-05 mrem / person _

Qirecc Radiation Direct radiation may be estimated by Thermoluminescent dosimetric (TLD) measurements. One method for comparing TLD measurements is by comparisen with pre-operational data. It should be noted that the TLDs measure direct radiation from Prath the Salem and llope 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 5.7 mrad / month SS-1 0.9 mile 4.9 mrad / month 8

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These values are intepreted 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 SE-1. l Total Done ,

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 i

<75 mrom 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 member-of the public have been calculated for the six month-reporting period. They are -

the sum of gaseous and liquid pathway doses for the Solem-1.and 2 and Hope Creek plants:

0.778 mrem total body 2.930.nrem organ (GI-LLI) 0.179 mrom thyroid Dase to members of the_mublic 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:

  • Such persons are participating or spectators l in local softball league
  • 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per week on site
  • dose due to a.irborne pathway (inhalation and immersion)_
  • persons are located about 3/4 mile east of plant discharge points (baseball fields)
  • occupancy coincides with batch gaseous discharges c For1the six month reporting period, the calcu.ated doses are:-

5.52E-04. mrem total body 5.61E-04 mrem - organ-(Lung)

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Assessment l Hope Creek gaseous effluents continue to bo one of the lowest of United States BWRs, with an avarage release l i

rate of 7.8 microcuries per second, characteristic of s plant with no cladding defects.

j individual noble gas radionuclide concentrations are too low to measure directly, calculated doses from nobio gases are based on a default isotopic mixture, which assumes little decay, and har principally short lived species with large dose factors. Because of this assumed isotopic mix, caculated doser are probably conservative by a factor of 25, assuming that the actual discharge consisted of moutly Xenon-133. ,

Hope Creek 11guld effluents decreased slightly from previous reporting period. Calculated doses are due principally to isotopes of iron and zinc.

The following two trend graphs show the gaseous and liquid effluents and calculated doses from Hope Creek since plant initial operation in 1986.

Hope C#eek Geseous Effluents Cunes of Nob 4 Geese Renseead and Ca6culated Donoe 10 . ,

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l Yoor PART F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for the first and second quarters of 1992 in Tables 5 and 6.

PART G. OFFBITE DOBE CALCULATION MANUAL (ODCM) CHANGES During this period, there were no changes to the HCGS Off-site Dose Calculation Manual.

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

PART I. ENVIRONMENTAL MONITORING LOCATION CHANGE 8 During the reporting period, there were one change to the environmental monitoring san.pling locations. Farm 14F4 was added to the Environmental Monitoring Program riue to a neighboring farm (14F1) ceasing dairy operations.

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IIOPE CREEK GENERATING STATION TABLE 1A EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT JANUARY - JUNE 1992 GASEOUS EFFLUENTS-SUMMATION Of ALL RELEASES Est.

1st 2nd Total Units QuarteA Quarter Error 1 A. Flasion and Activation Gases

1. Total release Ci 1.00E+02 1.43E+01 25
2. Average release rate for period pCi/coc 1.37E+01 1.82E+00
3. Percent of technical '

specification limit (T.S. 3.11.2.2(a))  % 1.48E400 1.96E-01 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))  % 1.46E-03 1.15E-03 C. Particulates

1. Particulates with half-lives >8 days Ci 9.05E-04 6.35E-04 25 ,
2. Average release rate for period pCi/sec 1.15E-04 8.0EP.~05
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a)) t . 46E-03 1.15E-03

4. Gross alpha Ci 9.72E-06 0.00L+00 D. Tritium
1. Total Release Ci 7.92E-02 5.87E+00 25
2. Average releast rate for period pCi/sec 1.01E-02 7.47E-01
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a)) 1 1.46E-03 1.1SE-03 (1) For batch releases the estimated overall error is within lot (2) Iodine, tritium and particulates are treated ts a group 12 l

i HOPE CREEK GEllERATIliG STATIO!1 TABLE IB EFFLUENT AllD WASTE DISPOSAL SEMI AllliUAL REPORT JAliUAkV - JUNE 1992 GASEOUS EFFLUENTS-GROUllD LEVEL RELEASES ColiTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nucliden Released Unit Quarter Quarter Quarter Quarter

1. Finnion Gases Krypton-83m C1 1.09E+00 1.41E-01 0.00E+00 0.00E+00 Kry pt on- 8 5 ta C1 1.09E+00 1.41E-01 0.00E+00 0.00E+00 Krypton-87 C1 4.36E+00 5.66E-01 0.00E400 0.00E+00 Krypton-88 C1 4.36E400 5.66E-01 0.00E+00 0.00E+00 Krypton-89 Ci 2.94E+01 3.02E+00 0.00E+00 0.00E+00 Xenon-133 C1 2.14E+00 2.83E-01 0.00E+00 C,.00E+00 Xenon-135 Ci 5.45E400 7.07E-01 7.89E-06 0.00E+00 Xenon l'J5m Ci 6.54E+00 8.47E-01 0.00E+00 0.00E+00 Xenon-137 Ci 3.38E+01 4.38E+00 0.00E+00 0.00E+00 Xenon-138 Ci 2.03E+01 2.66E+00 0.00E+00 0.00E+00 TOTALS C1 1.08E+02 1.43E+01 7.89E-06 0.00E+00
2. lodines ,

Iodine-131 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS Ci 0.00Ee00 0.00E+00 0.00E+00 0.00E+00

3. Particulates (half-live >8 days Manganese-54 Ci 2.75E-04 1.13E-04 2.61E-09 4.35E-06

'1nc-65 4 Ci 5.87E-04 4.39E-04 6.02E-09 2.34E-05 Cobalt-60 Ci 4 20E-05 5.15E-05 3.21E-09 3.75E-06 TOTALS Ci 9.05E-04 6,03E-04 1.18E-08 3.15E-05 a

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110PE CREEK GENERATING STATION -l TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL _ REPORT <

4 JANUARY - JUNE 1992 GASEOUS EFFLUENTS-ELEVATED RELFASES There were no'clovated gaseous releases during this reporting period..

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HOPE CREEK GENERATING STATION l

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT j JANUARY - JUNE 1992 i LIQUID FFFLUENTS-SUMMATION OF ALL RELEASES Eat. ,

1st 2nd Total Units Quarter Quarter Error %

A. Fiscion and activation '

, products 1.' Total release. (not including tritium, gases alpha) Ci 5.70E-02 5.51E-02 25

2. Average diluted-concentration during

- period- -gCi/mL 5.09E-08 -5.98E-08

3. Percent of technical specification limit-(T.S. 3.11.1.2.(a))  % 1.20E+00 1.19E+00 B.. Tritium-
2. Total release- C1 1.83E+01 2.23E+01 25 ,
2. Average diluted concentration during period pci/mL- 1.63E-05 2.42E-05
3. Percent of technical specification limit (T.S. 3 .' 11.1.1 )  % 5.43E-01 8.07E-01 l C. Dissolved and entrained  !

l noble gases i 1. Total release Ci ' 4.18E-03 3.41E-03 25 L 2. Average diluted L concentration during period pCi/mL 3.73E-0S. 3.70E-09 3.-Percent of technical specification limit (T.S. 3.11.1.1)  % 1.87E-03 1.85E-02 ,

D.-Gross alpha activit.

1. Total release Ci 0.00E+00 0.00E+00

-E. Volume of waste re.1oa se-(prior-to dilution -

L . Batch Release) liters 5.91E+06 4.33E+06 1

F. Volume of dilution water used during entire period liters- 1.27E+10 1.48E+10 15

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t HOPE CREEK GEllERATING STATIO!4 TABLE 2B EFFLUElrP Al3D WASTE DISPOSAL SFM1 ANNUAL PEPORT JANLARY - JUNE 1992 LIQUID EFFLUEhTS CONTINLOUS MODE BATCl! MODE 1st 2nd 1st 2nd Nuclides Releaned Unit Quarter Quarter Quarter Quarter Niobium-95 Ci 0.00E+00 0.00E+00 7.13E-05 1.73E-05 Curomium-51 Ci 0.00E+00 0.00E+00 2.73E-02 3.13E-02 Manganese-54 Ci 0.00E+00 0.00E+00 8.75E*03 6.60E-03 Iron-55 Ci 0.00E+00 0.00E+00 5.44r 03 0.00E+00 Iron-59 Ci O.002+00 0.00E+00 1.631-03 2 . 2 E- 0 3 Cobalt-58 Ci 0.00E+00 0.00E+00 2.46E-04 1.5hE-04 Cobalt-60 Ci 0.00E+00 0.00E+00 1.94E-03 1.24E-03 Zinc-65 Ci 0.00E+00 0.00E+00 0.22E-03 9.35E-03 Silver-110m Cl 0.00E400 0.00E+00 2.R9"-03 2.96E-03 Sodium-24 Ci 0.00Ev03 0.00E+00 2.534-05 1.08E-03 Strontium-92 Ci 0.00E+00 0.00E+30 2.57E-04 0.00E+00 Arsenic-76 Ci 0.00E+00 0.00E+v0 0.00E+00 2.30E-05 Cosium-137 Cl 0.00E+00 0.00E+00 0.00E+00 1.56E-05 Zirconium-97 Ci 0.00E+00 0.00E+00 1.02E-05 1.21E-05 TOTALS Ci 0.00E+00 0.00L+00 S.70E-02 5.53E-02 Tritium Ci 0.00E+00 0.00E+00 1.83E+01 2.23E+01 Xenon-133 Ci 0,00E*00 0.00EF00 7.75E-04 4.71E-04 Xenon-135 Ci 0.00E+00 0.00E+00 3.40E-03 2.94E-03 TOTALS Ci 0.00E+00 0,00E+00 1.83E+01 2.23E+01 16

a l

!! OPE CREEK GENERATIl1G STATIOli TABLE 3 EFFLUEllT AtlD W/ STE DISPOSAL SEMIiditiUAL REPORT JA110ARY - JULY 1992 SOLID WASTE A!1D 1RRADI ATED FUEL SilIPMENTS a i

SOLID WASTE SillPPED OFFSITE FOR BURI AL OR DISPOSAL ,

(tiot irradiated fuel) 6-month Est. Total

1. Type of waste Units (1) period Error, %
a. Spent resins, filters, m3 7.94E+01 _
sludges, evaporator bottoms Ci 9.49E+02 25 i
b. Dry compressible waste, m3 8.66E+00 contaminated equipment. Ci 6.72E-01 25
c. Irradiated components, m3 3.25E+00 control rods C1 1.98E+04 ?5

~

d. Others (described) m3 1./9E+01 Oil, Freon ci 2.68E-05 25
2. Estimate of major nuclide composition (for Type A and B waste) ,

RESINS DAW O1L

(%) (Ci) (%) (Ci) ( 1. ) (Ci)

Chromium-61 13.7 1.30d+02 13.6 9.14E-02 0.0 0.00E+00 1ron-55 35.3 3.35E+02 35.2 2.37E-01 10.5 4.96E-06 Tritium (ll-L) 0.0 0.00E+00 0.0 0.00E+00 0.0 0.00E+00 Manganese-54 4.0 3.00E+01 4.0 2. 69E- 02 10.4 2.79E-06 Carbon-14 0.0 0.00E400 0.0 0.00E+00 0.0 0.00E+00 Cobalt-60 2.4 2 . 2 3 Ed-01 2.4 1.61E-02 8.5 2.28E-06 111ckel- 63 0.0 0.00E+00 0.0 0.00E+00 0.0 0.00E+00 71nc-65 43.1 4.09E+02 43.0 2.89E-01 52.5 1.41E-05

2. Estimate of major nuclide composition (for Type C waste) ,

Irradiated Hardware

(%) (Ci)

Iron-Sb 56.2 1.11E+04 Cobalt-E0 39.3 7.77E+03 Manganese-54 2.2 4.35E+02 Nickel-63 1.9 3.76E+02 (1) Volumes are measured, activities are estimated 17 l

c;-

HOPE CREEK GENERATING STATION TABLE 3 (CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMEANNUAL REPORT JANUARY - JUNE 1992

, -SOLID WASTE AND IRRADIATED FUI!L SHIPMENTS

3. Solid. Waste Disposition Number of Mode of Type of Shipments ' Transportation D!:stination Containers 27 Truck Barnwell, SC HIC and 17E drums 2 Truck Barnwell, SC Steel liners 5 Truck Oak Ridge, TN Strong tight Containers IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Mode of Shipments- Transportation Destination None N/A N/A 1'

lt l

l ::

( ;_

I l-18

-*rw -

IlOPE CREEK GENERATING STATION TABLE 4A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 SUMMAhY SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCII MODE BATCH RELEASES ONLY

1. Dates: January 1 - March 31, 1992
2. Type of release: Gas _
3. Number of releases w' g the 3L. Quarter: 1 ,

4

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

1.12E+03 min

5. Maxinum duration for release of type list 3d above:
) 1.12E+03 min a '.I(

6.

Average duration for release of type listed above: ,

1.12E+03 min

i. Minimum duration for release of type listed above:

1.12E+03 min

8. Average stream flow (dilution flow) during the pericd of release: N/A 19

I! OPE CREEK GENERATING STATIOli TABLE 4A (CONT'D) ,

) EFFLUENT AND WASTE DIJPOSAL SE.*.IANNUAL REPORT JANUARY - JUNE 1992

SUMMARY

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

]

1. Dates: April 1 - June 30, 1992 a
2. Type of release: Gas
3. Number of releases during the 2nd Quarter: 1
4. Total time duration for all rd cases of type listed above:

5.12E+03 min

5. Maximum duration for release of type listed above:

5.12E+03 min

6. Average duration for release of type listed above:

5.12E+03 min

7. Minimum duration for release of type listed above:

5.12E+03 min

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

20

-HOPE CREEK-GENERATING STATION TABLE l4B EFFLUENT AND WASTE: DISPOSAL SEMIANNUAL REPORT-JANUARY - JUNE 1992

SUMMARY

SHEET FOR' RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE-

' BATCH RELEASES ONLY 1.- Dates: January'l - March 31, 1992

'2.- Type of release: Liquid

3. Number of releases _during the 1st Quarter: 144 4=. -Total-time duration for all releases of type listed above: J l'.15E+04 . min l

5.- Maximum duration for release of type listed above:

1.14E+02 min 6_ Average duration for. release of type listed above: ,

8.00E+01 min i

17. Minimum duration-for release of type listed above:

2.SE+01 min 8 '. - Average _ stream flow (dilution-flow) during the period of release: 258591gpm

.w i

21 i

t ilOPE CREEK GENERATING STATION TABLE 4B (CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992

SUMMARY

SilEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCil MODE BATLil RELEASES ONLY

1. Dates: April 1 - June 30, 1992
2. Type of release: Liquid
3. Number of releases during the 2nd Quarter: 108
4. Total time duration for all releases of type listed above:

8.35E+03 min

5. Maximum duration for release of type listed above; 1.03E+02 nin
6. Average duration for release of type listed above:

7.74E+01 min

7. Minimum duration for release of type listed above:

2.2E*01 min

8. P.verage stream flow (di.ution flow) during the period of release: 29173 gpm 22 l

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1 ARIlFICIAL ISLAND 01/92-03/92 JOINI DISTRIBullow Of WILD OIRECfl0N AND SPEED BY ATMOSPNERIC SIA8illif CLASS WikD: 300 Et LAPSE RAIE: -0.4 10 1.5 DEG C/t(Os CLASS E DELIA i: 1300-33FT)

" WIND SPEED GROUPS (MPM) 4 12.6-18.0 1(l.6-24.5 GE 24.6 StM rtaCtur 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 SLM PERLEmi SLM PERCENT SLM PERCEki SI"M PERCENT SLM PERCENT SLM PERCENT D arf CI!ON Sim PERCENT 7 0.3 0 0.0 37 1.8 O 0.0 0 0.0 7 0.3 11 0.5 12 0.6 N

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( 0.5 0.8 9 0.4 3 0.1 usu o 0.0 1 0.0 4 0.2 to 17 12 0.6 14 0.7 7 0.3 46 2.3 u 0 0.0 2 0.1 - 3 0.1 8 0.4 2.0 13 0.6 2 J.1 77 3.8 D 0.0 1 0.0 3 0.1 18 0.9 40 uwW 0.7 154 7. 7 0.2 0.5 83 4.1 40 2.0 15 wu o 0.0 1 0.0 5 to 66 3.3 0.8 23 1.1 21 1.0 3 0.1 umu 0 0.0 0 0.0 2 0.1 17 14.4 145 7.2 63 3.1 785 39.1 0.9 79 3.9 192 9.6 255 0 0.0 18 etAn u ND srtfD: 15.0 Table 5 MisssNG: 31 ,

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==

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4 w W

OO O* O O O O 4 as N w 4

w" b k O O O O O O O 4 4 O O O OO O O no

  • =

W b

es _

M C. 0 0 0 00 0 0 0 0 . 0 00 0 0 m.

.W O

. w 1,5 OOC O O O O O O OO OOOO O a ..e N u

  • w 4 4k O O O w O O C 4w w w N C e O O O k O

w == ** *

, e a 0 C. O. O. O. O. O. N. O. . *=. *a. . O. O. O. N.

g g g O C 0 00 0 0 0 O 0 0 0 0 0 0 O O

  • - a 9

<M 4 2 M N == " O O O O O 4 ** N N N N O O O e 2 at **

=a *

.O= v -E O ,

e= m 4 u>

no e=

ea w

X w

w

== m == ** O Ca. e w A. e e* a 0. *. O. O. O. O. O. O. . O. O. O. e. O. O. O. N. O Q *= to. = 0 O O O O O O O O OO OO O O O O &

se O N G O C O > m @

2 m. M g 4

. w A

MQ A &

3 "u.. *= = 0 N w mw O O O O O m*-e mO O O w C fe w == 0 m I

w w

e p p.,

O X E 3 as - 4 w

a=

a d

O .J

= w O

  • = Q R e= 0 O **

a - a -

O. O. O. O. O. O. O. O. O. . O. O. O. O. m.

= 3 m w O rh OO O O O O O O O OOO O O O -

E.D. e a y

.as ag

. > N. p

MU @

O m K O O == 0 C O O O e= *= 0mO O *= 0 N em 5

.a=

0

=e

==- 0 0. O. O. O. O. O. O. O. C. O. C. O. O. O. O. O.

s ee w O O O O O O O O O O OO O O O O O i u

M es h

d O O O O OO OO O OO OO O O O O N

C.>

a m

O

  • m. O* O. O* O. O. O. O. O* O* O-N a O. O+ O. O= O. O* O*

Ch O O O O O O OO OOO DC C O O O V. e s m. U

" es 4 0 O. w e

% a o O. -i 2 O O O O O O O O O O O O OO O O O O

% O" t a so M 4.d

==  %

M e

4 X

U X W bha W led W 4id W @ ) ) ) )

R 2 2 M M M M M g

)

3 3

) h 2 **

U == K end w V. @ .Js J 2 ** O

. 2

=.

ne y 3 ==

    • h.s 2@
    • et V sat s.u. . =

% .O 1 E

ARilflCIAL ISLAND 01/92 01/92 'JolNT DISTRIBUTION Of ulND DIRECTION ANO SPEED 87 AIMOSPMRIC $1ABILIIT CL ASS ,

Ulmo: 300 Fi 0(LIA i: (300-33FT) ALL SI ABILIIT CL ASSE5 WIND $ PEED GROUPS (MPN) 0.0-0.5 0.6 3.5 3.6 7.5 7.6-12.5 12.6-18.5 15.6-24.5 CE 2(.6 sum Ptatthi DIRECil0N $UM PERCENT StM PERCENT SLM PERCENT StM Pf RCENT SUM PERCINs SUM PEht*WT SLM PERCENT N O 0.0 .1 0.0 ' 17 0.8 24 1.2 32 1.6 24 1.2 0 0.0 98 4.9 kWE O 0.0 0 0.0 10 0.5 36 1.8 22 1.1 7 0.3 2 0.1 77 3.8 NE O 0.0 2 0.1 15 0.7 44 2.2 36 1.8 9 0.4 13 0.6 119 5.9 (NE O 0.0 4 0.2 19 0.9 42 2.1 56 2.8 12 0.6 6 0.3 139 6.9 E 0 0.0 3 0.1 16 0.8 ~ 33 t.6 15 0.7 0 0.0 1 0.0 68 3.4 ESE O 0.0 2 0.1 11 0.5 18 0.9 7 0.3 1 0.0 1 0.0 40 2.0 SE O 0.0 4 0.2 12 0.6 28 1.4 27 1.3 21 1.0 20 1.0 112 5.6 SSE O 0.0 8 0.4 21 1.0 25 1.2 34 1.7 17 0.5 23 1.2 128 6.4 S 0 0.0 4 0.2 25 1.2 31 1.5 13 0.6 3 0.1 5 0.2 81 4.0 ssu o 0.0 5 0.2 11 0.5 24 1.2 14 0.7 8 0.4 3 0.1 65 3.2 SW 0 0.0 4 0.2 12 0.6 17 0.8 35 1.7 19 0.9 7 0.3 94 4.7 usu O 0.0 1 0.0 14 0.7 27 1.3 28 1.4 19 0.9 9 0.4 98 4.9 u O 0.0 3 0.1 ". 9 0.4 31 1.5 37 1.8 43 2.1 37 1.8 160 8.0 UNu o 0.0 3 0.1 12 0.6 29 1.4 85 4.2 52 2.6 25 1.2 206 10.3 ru O 0.0 1 0.0 9 0.4 23 1.1 143 7.1 110 5.5 53 2.6 339 16.9 NNu O 0.0 1 0.0 18 0.9 31 1.5 58 2.9 49 2.4 22 1.1 179 8.9 0 0.0 46 2.3 231 11.5 463 23.1 642 32.1 394 19.7 227 11.3 2003 100.0 Miss Nc nours: 18 et AN ulND $FF[D: 15.5 Table 5 Page 8 of 9 i

ARilf! IAL ISLAND 01/92-03/92 JOINI DIsrRIBuilON OF WIND DIRECilOf AND SPEED Bf AIMOSPMERIC STABILI1f CLASS WIND: 300 fi DEETA i: (300-3?ti) olRECT10N VS SPEED tmtf Wito SPEED GROUPS (MPM) 0.0-0.5 0.6 3.5 3.6-7.5 T.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 StM PERCENT DIRECI!ON Sim PERCEWi SLM PERCENT SLM PERCENT StM PERCEp! SUM PERCENT SUM PERCENT SUM PERCENT N O 4.0 1 0.0 17 0.8 24 1.2 32 1.6 24 1.2 0 9.0 98 4.9 NME O 0.0 0 0.0 to 0.5 36 t.8 ZI 1.1 7 0.3 2 0.1 TF 3.8 hE O 0.0 2 0.1 15 0.7 44 2.2 36 1.8 9 0.4 13 0.6 119 5.9 ENE O 0.0 4 0.2 19 0.9 42 4.1 56 2.8 12 0.6 6 0.3 139 6.9 E o 0.0 3~ 0.1 16 0.8 33 1.6 15 c.T 0 0.0 1 0.0 (8 3.4 ESE O 0.0 2 0.1 11 0.5 18 0.9 7 0.3 1 0.0 1 0.0 40 2.c SE O C.0 4 0.2 12 0.6 23 1.4 27 1.3 21 1.0 20 1.0 112 5.6 GSE O 0.0 8 0.4 21 1.0 26 1.3 35 1.7 17 0.8 23 1.1 130 6.5 5 0 0.0 4 0.2 26 1.3 31 1.5 13 0.6 3 0.1 5 0.2 82 4.1 SSU 0 C.0 5 0.2 11 0.5 24 1.2 14 0.T 8 0.4 3 0.1 65 3.2 SU 0 0.0 4 0.2 12 0.6 17 0.8 35 1.7 19 0.9 7 0.3 94 4.7 ,

WSU 0 0.0 1 0.0 14 0.7 27 1.3 28 1.4 19 0.9 9 0.4 98 4.9 9 0 0.0 3 0.1 9 0.4 31 1.5 37 1.8 43 2.1 37 1.8 160 8.0 UNW D 0.0 3 0.1 12 0.6 29 1.4 SS 4.2 52 2.6 25 1.2 206 10.3 NU 0 0.0 1 0.0 9 0.4 23 1.1 143 T.1 110 5.5 53 2.6 339 16.9 NNU 0 0.0 1 0.0 18 0.9 31 1.5 58 2.9 49 2.4 22 1.1 179 8.9 0.fs 46 2.3 232 11.6 464 23.1 643 32.1 304 19.6 227 11.3 2006 100.0 0

MISSINc nouRS: 1/a MtAu Wluo srEto: 15.5 Table 5 Page 9 of 9

. *-m

q w g e. N. e. w. M. O. 4 4 O. O. 4 m.**. 4 O. N. eo, w w OL O O O O O O O OOO O O = *= @

r u W

% 4 N U =d W O

W &

O 4 Ow ON O M M ** *=* 0 O @ 4P O a^ O

$ *= NN a e

p.

.=

w >=

0 O. O. O. O. O.

  • O. O. O. O. O.
  • O. M.

, a O. OO.O O.

@ w O O O O O O O O O O O O O O w

4+ m N w h

w D Q O O O OQ M O O O OOOOM e P=

E nd N *=

O. O* O = N

  • O O* O OO* ON M O*

A e* a * * * *

=d W w

W OO O* DooO O* O*O O* O O O O O OO **O O N

N. w 4 6 4 1 O ** O OO ON 4 O O OOO *= e +9 &

g e Q

w >=

  • w e 33 N. e. M. . N. O. e. N. O. O. O. 3. O. N. e. to. e.

h 4 0 * * * * * * * * * * * *

  • e r.1
  • W 4 4 M

M N d N @ N d O M 4 O O OO *= d O ** *=

E et *= *= *= c

== ^

-O W X

>= m CL u D. >= X w >= te. w a.= ed == M M*O* N *M* **=* *O* *N* N * *O O *=

e .=> *= o=

M M e* E Oa *= O* *m e *=* m O = ta= '

OO O O O O O O O OOOO O O O N e N  %

4 M

0

  • =
  • m, e O

== H> M w Q 4 @

3 M U ** **

== a O w

N 4 *= 4 4M Oe4 w O e' N O N *= >== 4 nn.

O as E e=

w w

e=e O 5ga 35a k S U e m' U k *

, O. O. O. O. O. O. O. O. O. O. M. N. N. **

. O. O m.

    • 3- m. O O O OO OO O O OO OO O O O O e

W N a e- > > w M e

==

w O M E O O O O O O O a O O @ W eN

  • O &

e.=

3 5

O M

  • = 0 O. O. O* O O. O. O. O. O O= O* O. O. O* O at + - - O.
  • d * * ** * * * * *** * *
  • M as
  • w 4 6 O -

O O O OOOO OO O OOOO J O O N 6

==

N' 3 0. C. C. O. O. O. O. O. O. O. O. O. O. O. O. O. O. -

O m* w O O O OOOOO O O O O OOO C C @

N W @.

M Q+ m M w em O Q. '

N O O OOO OO O O OO OOO O O O O-w w O kne

=* 4 rn I E W W W W W W W M M 3 @ .-

=

U z a a eea E r

== 2 w w e e 3 =* A3

== "I 2

y =

  • = w 2 Y
  • cs 4 M M == w ==

M C L E i

l l

I l

l l

i

  • =
e. emM O+

e *= @ N *N

  • 4 M* * *
  • * * * * +

m 3

w OO O O O O*O'4 O-to N OO* O O O O O' w e c

  • = sn u

% e as Y 5

'.'. u o m.

e eem4

    • N oc<O w m o n r= -N Nm e m e=

N O

.O=

  • =

a 0 O O O O O O O O O O. O. OO O O

+ * * - * -

4 w OO O* O* O O- O* O* O- O= O O O O O+ O* O U

O* 4 as Y $

w

.. O O O coo 9 0 O O O O O O O O - -

.o e

66.

3 g e*

a C. O. n. O. O. O. m. O. O. O. O. O. O. O. m. o. a.

w O O O O O O O O O O O O O O O O O 4.,e se ,a N su h

ai O - - O e Q e-CO O OO O wn n

,=

e-w e-

  • g3 m ** O. O. O.

. O. O. **. N. . O. @. O. O. ==. 4 N. N.

5 4 o=

0 a

9

( 6e A. t en N N O O ** O O N 4 N O O OON O 4 @

X 4 *= N O .4 *

~

m

  • u> > k O

$E

. .a e pq

$ m e*

e=

z e. N. 4.**.==.**.O. e=. *=. 0 0 0. **. O. F J. to. O.

O = en. OO O OOO O OO O OOO O O O N w me N D O e, a @

9 =<= O O es w gM mw w @ E N u .. .* O >= K O 4 N*=NM N ** M N O O *= m *= e *= 0 @

    • 4 m th g == = g >

w g **

.c en

, g gE 3 m d

M C H"

, e 9 .

. O. . O. O. O. O. . O. O. . . N. N. . m. o.

  • =

w OO O O O O OO OO O OOO O O B<

as 3 '- nn. u at

.= > P.= w A

.e. a 4

m e *= N OO O ON OO N ED 4 4 N @ N O m m.

a O

  • e

> e.

O. O. O. O. O. D. O. O. O. O. O. O. O. O m,

a y C0 0 0000000 00 0 0- O. 0O. O O M w O * * * ** * ** * '~ ~ * * *

  • N 5

m O

4

- N 3 O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O.

O O

% en. w u

O OO O O C= 0 C O O OOOO OO c.

e e

4 O es "

5 5 9 & 0 0 0 0 0 0 0 0 00 0000 0 0 O ..

< O.e

= .U.

N

.a 4 W M uW  %.8 &tJ W W 64a a*

treM 3ers 3 3 3 33 O2

= Q 3 2 E w

H M w M 3 3 2M "

u == 3 A J u 2 -e

.= w e og

==

es ==

a. ~

d o E Z

6 m **

$ 3 @ *=. e. N. N.

4 M. N. N.

a M. =a. d. P. &. N o

- e a w U

O .OOO O. O O O O r. - 0 0 C O O o

% 4 SE C U w N M *.- eN 4 & 4 =0 eN N O O @

. -=ED- R e.

e.

.O., O. O. O. O. O. O. O. O. O. O. O. O= O.

a O. O. O. ==.

C.

w O O O O C= 0 0 O O O O O O OO O O 4 u o

4 m N w 4

w d OO O *= 0 O O e O O O OO O O C N

  • e=

E

'm _

~

    • N g
  • =
0. O. *=.
    • ** ** s= 0 c* 3 . O. O. M. *=. O. O. O. O. O. . .

et w OO O O O O O O O O O OO O O L *=

o 0 u N m U. $

eo 3 D 8"4 N M C O 4 N O O O OO M N N

} O N

O w *=

e. X O. 0 *=. O. O. O. O. O. O. O. O. O.**. *=. W . M.

4 j

w O O O O O f'3 O OO OO OO OOO -

e3 w

  • = es 4

4 .

e N *= ON *= ** 2 O ** *= ** *= OM N ED 4 e 2 at ==

N Q .g a

=e u m E

    • ^ @

u n= =

R, w e- 4

  • W

== M == ** **

es.w a m M e* a M. C. N. O. O. . *=. O. O. O. **

.N.*=. .. M. 4 N O O = hm O O O OO OO O DO O OO O O O N i

Wr e4 N U' M O at ** es I R *= ft a w Q ti# Q $ & M h

==3@ '

u .. ** O >=

K Pm

  • 4 O ** M N e e e M vN N 4 a3 4 4 & A g g O 'aI k t G4 hA 3

O m 3- m<

w me e

  • '= w O

== 0 o a e- ** ** **

"J K == 2 N. e=. O. O O. O. . *=. *=. *=.N. . ** c.

=*

et. et 2 m e w

u O O O OO+ O. O OG OO OOO O O. O*=. w er >= es e- > <

e as b.

. e.

O M wN M OO *= **

  • N N N M *e N N N =
e. M M

O 7

3 0 o. O. O. O. O. O. O. O. O. O. O. O. O. O. O. *=.

e e w

u O O OOO O OO OOOOoO O O O m

M. w 4 (h.

d 5

    • * * * * * *' '- " ~

N w t>

4

  • *= 0 0 N 3 C. O. O. O. O. O. O. O. O. O. O. O. O. O. O.

N m. w O O O OOO O OO O OO O OOO O N u < ao W D E .=

i w -

O e.

04 O K O O O O O O OO O OO OO O OO O .

s O' ad M w O

"" w A

.a e if X

= 2 w2 Xw 2w ww M w Mbel #A M23" *J

. M3 0 u Q M m a x 2

==

.

at w w M M 2

  • O**

e 3 3

.m. y e- . 2 =A g 4 e a um 4 u **

Q E 1

___,__ m_.___ ___ _ _ _ _-_- - - - - - -- - - - - - - - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ . _ _ - - - - _ - - - - _ - - - - - - - - - - - - - - - - - - ~

I l

i 1

L O ==

3 O. e. .e. O. N. 40 ha. en. a. e. .a. @. O. A. N. to. N.

m we *= *= m mM

  • N W M N ** O *= ** N *= en
e. m u m 4 e6 u'% =e w u 6
  • N O ** N N <* N == en e *=

O N mN 4 4 me& en

@ bkN e N mem

{

40

+

O.

O == s= e+ 0 0 e= n 0 C. . N. N. O. O. O. O. O. O. O. *. O.

4 e. w U

O O O O. O O O O O O OO O O O O O 4 er 3

w OON N O O .n e O O O OO - - N e e=

ar W

D, >

. ,o. . ,. *e. .* O. O. 4* . M. N. 4 *=. O. O. e. 46 *=. m.

4

=e 4 w

u O O O O. O O O *= O O O O O O O O to N

N. W

@ b M a et e e3 O C#- 4 A en @ NOO **- O N

.sh. N - 8=

Q w *= **

w

e. a M. N. 4. N. to. 4D. . N. 4. GG. M. O.**. 4 O. en. O.

g 51 y OOO OO O - N -O > OO O O O -

es W

H 4+ &

m N @ en 4*= 4 **e=>= N E at O d

  • e= *= N e.n =

g P .4. *4 >= OM N == &

+= *=

  • =

a)

N

.= Q R N

  • = #%

u> == I W MS a ==

W M

%d o

== =.a t- 44 t.

R M. en. M. *w. M.

@. N. q. g. *=. N. M. =a. O. E.l ed. M.

e w

O == en M. en. a.a O O ** *= == 0 C OO w O OO O O O e O N U O.= 0 M OO e= et @

M 4."a OH m e w

== ta M ** O 4 A wf 3 @

U .. .. O N 4 O N @ N 40 eO =0 N 4 @ O ** *= @ @ N

  • O w a <O >= w *= N N N w *= N =

O M 3 w N

,C &

w == at A C f4 2

O A E 3 *= =a M

f* C

= w .n O M N. in. N. @. ww e-

p.

mo '

. w . . N. M. 4 M. an. M. =#. nn. W. M. 4 3 u O O O O == O OOO O O OO O OO >

- ag e. O m as

.= > N. w M

~ IA 4* 4 Q M in *=

k

  • = ,4 = EDm N 90 N nn >= 0 m.*=O 4@ O *= @ P.

h.

m 9

M

=.-

k

  • a O. O. *=. O. O. O. O. O. O. O. M. O. O. O. O. O. N.

en. w OO O O OO O O O 8") O OO O O O O u

M 88 b U b ***M C *= O O O *= C 4 O *= O OO w N

O 4

. *= 0 N

O a O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O.

nn. w O O O OO OO OO O O OO OOO O in

% u N. N

=# O su N b $

9 ci OO 0 000 0u0 0 0 0 00 0 0 0 ..

=e M O.a

"= .s A

s e

at M a w w w w wa weew e Lt 3e 3m 3

  • 3 3 0 u O z a a z3 "he a ..

==

as w w e e 3 w - s.3 m- g 3 2

    • beg e

gg 2 4 g

M =e e.

  • 4 O 1 =I i

ARiff!CIAL ISLAND 4/92- 6/92 J0lRT 01s1R18UT104 OF Wim OlRECilCM AND SPEED BY AinOSPNEttC STA81Llit CLASS WIND: 300 Fi LAPSE RATE: -0.4 10 1.5 DEG C/100m DELTA 1: (300-33FT) CtAss E WluD $vEED CROUPS (MPM) ,

I 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 PIRCEuf

~

DIRECTION SLM PERGliT SLM PERCEMI SLM PERCENT SIM PERCENT $1M PERCENT stM PERCE41 sum ftRCEnt l

1

( w 0 0.0 3 0.1 7 0.3 8 0.4 14 0.7 5 0.2 0 c.0 37 s.8 kWE o 0.0 4 0.2 4 0.2 6 0.3 7 0.3 5 0.2 0 0.0 26 1.3 NE D 0.C 1 0.0 8 0.4 18 0.9 20 1.0 8 0.4 1 0.0 54 2.7 l l

ENE o 0.0 1 0.0 10 0.5 11 0.5 11 0.5 3 0.1 0 0.0 36 1.7  !

E 9 0.0 0 0.0 3 0.1 18 0.9 11 0.5 0 0.0 0 0.0 32 1.5 ESE O 0.0 1 0.0 2 0.1 11 0.5 6 0.3 8 0.4 1 0.0 29 1.4 l SE O 0.0 0 0.0 7 0.3 9 0.4 6 0.3 6 0.3 5 0.2 33 1.6 SSE O 0.0 0 0.0 8 0.4 19 0.9 35 1.7 9 0.4 2 0.1 13 3.5 5 0 0.0 2 0.1 9 0.4 13 0.6 11 0.5 3 0.1 0 0.0 38 1.5

$$W 0 0.0 1 0.J 7 0.3 11 0.5 17 0.8 1 0.0 0 0.0 37 1.8 f SU 0 0.0 3 0.1 9 0.4 9 0.4 17 0.8 16 0.8 1 0.0 55 2.7 l usu 0 0.0 1 0.0 5 0.2 15 0.7 2 0.1 1 0.0 0 0.0 24 1.7 W 0 0.0 1 0.0 6 0.3 15 0.7 7 0.3 0 0.0 0 0.0 29 1.4 uwv 0 0.0 0 0.5 6 0.3 14 0.7 e 0.4 3 0.1 0 0.0 31 1.5 Wu 0 0.* 1 0.0 1 0.0 7 0.3 29 1.4 15 0.7 0 0.0 53 2.6 kwW 0 0.0 1 0.0 6 0.3 13 0.6 21  ?.0 9 0.4 3 0.1 53 2.6 i 0 0.0 20 1.0 98 4.7 197 9.5 222 10.7 92 4.5 13 0.6 642 31.1 1

MrAu utuo sufED: 13.0 Table 6 Miss!wG: 45 Page 5 of 9 l

l -

l

_ _ _ _ i a { e 9

I I

v w .

@ P*. @. M. @

m g . N. M. N. e. e. (l>. >=, @. 00. N. @

N.

e sn w O O O Q O O O a= 0 O O OO O O O. O

s. s *

% 4 3 VW W W &

M. .ee@ 4 >= 4 N w Om o M @WM e= O O g - M - - ---- --

z O.

4

3 = 0 4 3 O. O. O. O. O. *=. M. C. O. O. O. O. O. O. O.
  • d * * * * * * * * * *

" N g w

.. 3 O O 0 0 0 O N 4 0 0 0 0 0 0 0 O O em 4

m N -

O. O. **

st e e. a w

O. O. O. *=. 0. M. . N. *. *=. O. O. **. O. M. _

.,,te a u O O O O O O O O O O O O O O O O a as N. W

@ 4 M O * **C Na @ N W M N O

  • N O @

N O

w -

w a M. M. e. ==. O. O. N. w. *=. N. N. O. M. M. M. e=. ==.

a. e. w O O O OO O O O O O OOO O O O M M O U e as S

<* en @ 5 x < N w @ @ N N Ow eO M eM *= @ 4@ N e

=a

.O W em n E

L u> e. R w e= w w M w

  • e.s.=.,o em

. m x N. M. N. e=. e. N. M. *a. M. M. e. N. N. N. M. C. O O = em M. e. w OO OOO O O O O OO O OOO O M

em N W W

.E.Me-<M 8w as u 4

. w 4

. ,, o 3 w u .e ..

O N r e@ g NN N eN M @ @ O eee@ p- g) a;9- -

8 -

M e a =- f

- w o a. a.w

  • = e g;

es Q =

a e 3

m O. O. O. O. O. O.

0 0 0 00 0 0 0 000 0 0 00 O

. = = . = =* . . O. f'; O. N. O. N. .

- > N. w e se 4 4

==O M O O

  • OO ** N M M MOO O 4 == e K

M

- G E.

O n

> p 3 . *=. O. O. *=. O. O. O. O. O. O. O. O. O. O. O. e.

e. w O O O O O OO O O O O OO OO O O u

es M. w O x NN O. N - O - O - COOOO O O

~

a w

~

, 0 0 ,=. O. ,s. 0 00 00000 000 O.

o e y C O OOO O 2O O OO OO OO O O m =

~

2 N M O. w e=

O 4 N O O O OO O O O O OO OO OO O O

.w 5

M O.e

. 0 M" w 4

a u X

- = w w w a $ 5 = -2 o, y

m"'= J et 2@

er = 4 49

==

% O Z

I 1

1 o ==

3 0 **

. O. O. N. *=.

. e. e. e. N. *=. c. *=. d. *=. 4 eA w O O O O O O O O O O O O O O O O e e e u

% at W 4e w W EL OM ** *= 4 M N O 4O- eN O- M eN O o 5 Vs

- ~

O, 4

e. ==

g a O. O. O. O. O. O. O. N. O. O. O. t.1 O. O. O. O. M.

4 w O O O OOO O O O O O O O O O O O u

4 as N w Q.

d K O O O O OO *= 4 ** O O OO O O O 4 G

e EE e.

  • =

n O. 0 00.O. O. O.**. O. O. O. O. *=. O. O. O. M.

  1. d * * * * ** "* * **"* *
  • N m 4 t'
  1. O ** O O OOON *= 0 OO N *= O O >=

O w *= 0 e=-

c.

. w e a O. O. O. O. O. O. *=. 0. M. O. O. M. . N. *=.

g  ; y O 0 0 0 0 0 0 0 0 0 0 000 0 0 -

    • es 9

<mM 4 t N O *= 0 0 0 *= *= M ** @ ** * =

  • N eN ==

m et *= m w a

.O= u a em n L u t- *= K p E E, A *= 0 O. O. O. *=. O. O. O. e.

O. O. O. O. *=. O. &. w M e a .

== g.s O e=.

4 0 * * * * * * * * * * * * * * * *

  • o g c; m g"Q w a o

2 5 4 r G u .. ** O N * '- * * - " * - * ** " " ' - - * * " * '" ~

  • k w 5

w Om w == < a em m a 3* w l . a.

O e

== w O 4

== 0 Q a -

O. O. c. O. O. u. O. O. O. O.

e.

. O. O. O. O. O.

2E - a

-so *= 3 e.

w Q OOOO O OO O O OOO OO O O

< U er N, es a= s= w e es @ (L Q M g O O *= O * * '

  • OO O ** M O o'= O O O G3

.= 0 m

C 7

, O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O. O.

O n y m

C 0 0 0 0 00 000 0 000 0 0 M, w e o.

& a; 0 0 0 00 00 0 0 0000 0 00 O N G Ch

~

0 0 000 000 0 0 000 000 C.

C e.

R q g C 0 0 0 00 00 0 0 0 00000 4 O.

m .=

w O 46 9'

d O 0 0 00000 00 0 00 0 00 O ..

Oa

=* W

"* G.

W J

M v - =

2 w w r .M E s = 3g u

w 2 -.e

  • as
  • M

.m =

DG -

4 Q 1 E

i u f

I ARIlflCIAL R$tAND 4/92- 6/92 JOlWI DISIRIsui10*1 Of Wluo OIRECTIOW AND $ PEED BY AIMOSPNiRIC $1ABillif CLASS 14t kO: 300 FT DELTA T: (300-3371) Att SYasttt17 CtAssEs WIW SPEED GROLPS (MPN) 0.6-3.5 3.6 T.5 T.6-12.5 12.6-18.5 13.6-24.5 GE 24.6 $UM PERCENT 0.0-0.5 SLM PERCEmi stM PERCENT SLM PERCENT StDe PERCEst SLM PERCENT DIRECil0N $LM PERCEmi StW PERCENT 0.8 42 2.0 33 1.6 8 0.4 0 C.0 106 5.1 N 0 0.0 6 0.3 17 29 1.4 21 1.0 14 0.7 0 0.0 89 4.3 kWE O 0.0 7 0.3 18 0.9 1.4 69 3.3 46 2.2 20 1.0 3 0.1 171 8.3 at 0 0.0 4 0.2 29 1.4 51 - 2.5 21 1.0 15 0.7 3 0.1 120 5.8 EXE O 0.0 2 0.1 28 1.5 2.8 2T 1.3 1 0.0 0 0.0 120 5.8 E O 0.0 3 0.1 32 ST 0.3 37 1.8 25 1.2 to 0.5 1 0.0 82 4.0 ESE O 0.0 2 0.1 7 0.7 26 1.3 39 1.9 40 1.9 16 0.8 136 6.6 SE O 0.0 0 0.0 15 43 2.1 101 4.9 51 2.5 18 0.9 236 11.4

$$E O 0.0 1 0.0 22 1.1 0.1 1.1 39 1.9 52 2.5 11 0.5 1 0.0 129 6.2 5 0 0.0 3 23 1.0 43 2.1 45 2.2 14 0.7 0 0.0 125 6.1 SSW D 0.0 3 0.1 20 1.5 1.2 31 1.5 21 1.0 1 0.0 121 5.9 SW 0 0.0 11 0.5 32 25 1.3 39 1.9 4 0.2 3 0.1 0 0.0 74 3.6 tw 0 0.0 2 0.1 26 1.4 33 1.6 27 1.3 2 0.1 0 0.0 93 4.5 v 0 0.0 2 0.1 29 0.0 28 1.4 25 1.2 36 1.T 20 1.0 1 0.0 110 5.3 WWW 0 0.0 0 0.8 2.1 85 4.1 40 1.9 4 0.2 189 9.1 W 0 0.0 1 0.0 16 43 0.0 1.3 54 2.6 ST 2.8 20 1.0 7 0.3 165 S.O muu O 0.0 1 26 31.7 650 31.5 290 14.0 55 2.7 ste6 100.0 O 0.0 48 2.3 368 17.8 655 MisstwG nouns: its MUN UlWD SPEED: 12.8

  • Table 6 Page 8 of 9

i 1 ,

l l

l ARilflCI AL ISL AND 4/92- 6/92 JoiMT DISTRiguTION OF WIND DIREC110N AND SPf(D 87 ATMOSPHERIC STA81LIIf CLASS WINO: 300 FT DELTA T: (300-33fi) D'REClioN v5 SPEED ONtv W?ND SPEED CROUPS (MPM) 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 PfRC(Ni Stat PERCINT SWt PERCEMI SUM PERCENT SLM PERCENT SLM PERCENT SUM PfRCENT OttiC110N SUN PERCENT 0 0.0 6 0.3 17 0.8 42 2.0 33 1.6 8 0.4 0 0.0 106 5.1 M

WWE O 0.0 T 0.3 18 0.9 29 1.4 21 1.0 14 0.T C 0.0 89 4.3 O 0.0 4 0.2 29 1.4 69 3.3 46 2.2 20 1.0 3 0.1 171 8.2 kE ENE O 0.0 2 0.1 28 1.4 51 2.5 21 1.0 15 0.7 3 0.1 120 5.8 E O 0.0 3 0.1 32 1.5 ST 2.7 2T 1.3 1 0.0 0 0.0 120 5.8 O 0.0 2 0.1 7 0.3 3T 1.8 25 1.2 to 0.5 1 0.0 52 4.0 ESE SE O 0.0 0 0.0 15 0.7 26 1.3 40 1.9 40 1.v to 0.8 137 6.6 l

l $$E O 0.0 1 0.0 22 1.1 43 2.1 101 4.9 51 2.5 18 0.9 236 11.4 5 0 0.0 3 0.1 23 1.1 39 1.9 52 2.5 11 0.5 1 0.0 129 6.2

$$W 0 0.0 3 0.1 20 1.0 46 2.2 45 2.2 14 0.7 0 0.0 ils 6.2 SW 0 0.0 11 0.5 32 1.5 28 1.4 31 1.5 21 1.0 1 0.0 124 6.0 WSW 0 0.0 2 0.1 26 1.3 39 1.9 4 0.2 3 0.1 0 0.0 T4 3.6 0.1 29 1.4 33 1.6 27 1.3 2 0.1 0 0.0 93 s.5 U 0 0.0 2 WW D 0.D 0 0.0 28 1.4 25 1.2 36 1.7 20 1.0 1 0.0 110 5.3 W 0 0.0 1 0.0 16 0.8 43 2.1 85 4.1 40 1.9 4 0.2 189 9.1 WNW D 0.0 1 0.0 26 1.3 54 2.6 57 2.7 20 1.0 7 0.3 165 8.0 0 0.0 48 2.3 368 17.8 661 31.9 651 31.4 290 14.0 55 2.7 2073 100.0 missing nouR$: 111 l

l MraN WIND SrttD: 12.8 Table 6 Page 9 of 9 e

, , y _

AMENDMENT TO RERR - 5 l

. . . - - .- . - . . . . -. ~ _. ._.. . . . - ~

l HOPE CREEK GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1988 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Est. Total

1. Type'of waste Units (1) period Error, %
a. Spent resins, filters, m3 7.92E+01 sludges, evaporator bottoms C1 2.58E+03 25

.b. Dry compressible waste, m3 9.14E+01 contaminated equipment. Ci 2.95E+00 25

c. Irradiated components, m3 0.00E+00 control rods Ci O.00E+00 25
d. Others (described) m3 0.00E+00 Oil Ci 0.00E+00 25
2. Estimate of major nuclide composition (for Type A and B waste)

! RESINS LAW

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

Chromium-51 3.2 8.26E+01 62.4 1.84E+00

- Iror.-5 5 S.1 2.09E+02 7.7 2.30E-01 Iron-59 2.0 5.16E+01 2.6 7.70E-02

! Manganese-54 4.0 1.03E+02- 9.0 2.60E-01 l- Cobalt-58 1.3 3.35E+01 14.6 4.31E-01 Cobalt-60 2.4 6.19E+01 2.1 6.20E-02 Nickel-63 0.0 0.00E+00 0.0 0.00E+00 Zinc-65 78.8 2.03E+03 1.6 4.70E-02 l

l (1) Volumes are measured, activities are estimated

w i.

k 1.:  !

AMENDAIENT TO RERR - 12 j

)

i l-l.

8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS Our last report (RERR-11) did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the first half of 1991. Amended pages to RERR-11 are included at the end of this report.

Additionally, calculational errors were found after RERR-10 was submitted. Corrected values are included at the end j of this report. .

PART D. GASEOUS EFFLUENTS See Summary Tables 1A throimh 1C.

PART C. LIQUID EFFLUENTS

+

See Summary Tables 2A through 2C.

PART D. SOLID WACTE See semmary in Table 3.

PART E. RADIOLOGICAL IMPACT ON MAN The calculated individual dosec in this section are based on actual locutions of nearby residents and farms. The population dose impact is based on historical site specific data i.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.

Licuid Pathways y

Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathway. Calculated doses to individuals are as shown below.

7

Total body dose to an individual: 6.04E-02 mrem Highest organ dose: 1.73E-01 mrem to the Liver

' Dose to the 6 nillion individuals living within the 50 mile radius of the plant site:

Total population dose: 4.96E-01 person-rom Average population dose: 8.31E-35 mrem / person Air Pathwqyfi gr The calculated doses to individuals via the air pathway are shown below:

Total body dose: 3.87E-01 mrem Skin dose: S.42E-01 mrem Highest organ dose due to radiciodines and particulates with half lives greater than 8 days:

5.37E-05 mrem to the Liver.

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

Total population dose: 1.97E-01 person-rem Average population dose: 3.68E-05 mrem / person Dire.ct Radiatiqn 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 5.0 nrad/ month SS-1 0.9 mile 4.7 mrad / month 8

1

llOPE CREEK GENERATING STATION TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 LIQUID EFFLUE14TS-SUMMATION OF ALL RELEASES Est.

3rd 4th Total Units Quarter Quarter Error %

A. Fission and activation products =

1. Totti release (not
2. Average diluted concentration during period pCi/mL 8,40E'c6 1.22E-07
3. Percent of technical specification limit (T.S. 3.11.1.2.(a))  % 1.42E+00 2.23E+00 B. Tritium
1. Total release Ci 3.82E+00 6.62E+00 25
2. Avorage diluted concentration during period pCi/mL 1.87E-06 3.60E-06
3. Percent of technical specification limit (T.S. 3.11.1.1)  % 1.63E-03 6.30E-04 C. Dissolved and entrained noble gases
1. Total release Ci 3.47E-03 3.45E-03 25
2. Average diluted concentration during period pCi/mL 1.70E-10 1.88E-10
3. Percent of technical specification limit (T.S. 3.11.1.1)  % 1.71E-04 6.20E-04 D. Gross alpha activity
1. TotM1 release Ci 0.00E+00 0.00E+00 E. Volume of waste release (prior to dilution -

Batch Release) liters 3.21E+06 3.94E+06 F. Volume of dilution water used during entire perio3 liters 1.7"E+10 1.44E+10 15

l l

HOPE CREEK GENEPi. RING STATION "ABLE 28 EFFLUENT AND WArTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE

)

f 3rd 4th ird 4th Nuclidos Rolefsed Unit Quarter Quarter -rter nuarter Hiobiume95 Ci 0.00E+00 0.00E+00 5.23E-06 1.49E-05 -

Chromium-51 Ci 0.00E+00 0.00E+00 1.00E-02 2.59E-02 Manganese 54 Ci 0.00E+00 0.00E+00 5.02E-03 9.80E-03 Iron Ci 0.00E+00 0.00E+00 1.41E-01 1.73E-01

. Iron-59 Ci 0.00E+00 0.00E+0n 8.98E-04 1.04E-03 Cobalt-58 Ci 0.00E+00 0.00E+00 1.43E-04 2.06E-04 Cobalt-60 Ci 0.00E+00 0.00E+C0 1.21E-03 2.30E-03 Zinc-65 Ci 0.00E+00 0.00E+00 1.28E-02 1.17E-02 Silver-110m Ci 0.00E+00 0.00E+00 2.73E-04 5.92E-04 Strontium-91 Ci 0.00E+00 0.00E+00 4.67E-06 0.00E+00 Strontium-92 Ci ^ 00E+00 0.00E+00 2.61E-05 1.36E-04 Mercury-203 Ci L.00E+00 0.00E+00 2.76E-06 0.00E+00 Cosium-137 Ci 0.00E+00 0.00E+00 0.00E+00 1.08E-05 TOTALS Ci 0.00E+00 0.00E+00 1.71E-01 2.75E-01 Tritium Ci 0.00E+00 0.00E+00 3.82E+00 6.62E400 "

Xenon-133 Ci 0.00E+00 0.00E+00 7.36E-04 5.02E-04 -

Xenon-135 Ci 0.00E+v0 0.00E+00 2.74E-03 2.95_E-03 TOTALS Ci 0.00E+00 0.00E+00 3.82E+00 6.62E+00 .

. 16

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