ML20056H172

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Semiannual Radioactive Effluent Release Rept HCGS RERR-15
ML20056H172
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/30/1993
From: Hagan J
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N93134, RERR-15, NUDOCS 9309080327
Download: ML20056H172 (48)
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Pubic Servee Eiecuc and Gas Company Joseph J. Hagari Public Service Dectnc and Gas Company P.O. Box 236. Hancocks Bndge. NJ 0B038 609-339-1200 Vice Presniern Nocmar Owatsons AUG 3 01993 NLR-N93134  ;

i United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 i

Gentlemen:

RADIOACTIVE EFFLUENT RELEASE REPORT - 15 HOPE CREEK GENERATING STATION '

DOCKET NO. 50-354 In accordance with Section 6.9.1.7 of Appendix A to the Operating l 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 ROlcase Report, RERR-15. This report summarizes 1iquid and gaseous releases and solid waste shipments from the Hope Creek Generating Station for the period '

of January 1 through June 33, 1993.

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

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i Attachment (1) i 9309080327 930630 PDR K y R ADOCK 05000354 IO ;I pyg Q

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AUG 3 01993

. i Document Control Desk 2  ?

NLR-N93134  !

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RERR REPORT only I C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 1 475 Allendale Road I King of Prussia, PA 19406 Mr. S. Dembek, Licensing Project Manager - Hope Creek )

U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike l Rockville, MD 20852 l i

Mr. S. T. Barr (SOS)

USNRC Senior Resident Inspector l Mr. K. Tosch, Manager IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering '

CN 415 Trenton, NJ 08625 i

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i HOPE CREEK GENERATING STATION I SEMIANNUAL RADIOACTIVE i EFFLUENT RELEASE REPORT HCGS RERR-15 l

DOCKET NO. 50-354 OPERATING LICENSE NO. NFP-57 i

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. i HOPE CREEK GENERATING STATION

  • RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993 f Table of Contents [

t INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . 1 ,

PART A. PRELIMINARY SUPPLEMENTAL INFORMATION . . . . . . . . . 2 i r

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 l 1.4 Total Dose Limit . . . . . . . . . . . . . . . . 3 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) . . . . . . . 3 3.0 AVERAGE ENERGY . . . . . . . . . . . . . . . . . . . . 4 1

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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 i, 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE ,

EFFLUENT RELEASE REPORTS . . . . . . . . . . . . . . . 6  :

i PART B. GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . 7 PART C. LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . 7 l PART D. SOLID WASTE . . . . . . . . . . . . . . . . . . . . . 7 PART E. RADIOLOGICAL IMPACT ON MAN . . . . . . . . . . . . . . 7 Liquid Pathways . . . . . . . . . . . . . . . . . . . 7 Air Pathways . . . . . . . . . . . . . . . . . . . . . 8 Direct Radiation . . . . . . . . . . . . . . . . . . . 8 l Total Dose . . . . . . . . . . . . . . . . . . . . . . 9 Dose to Members of the Public on Site . . . . . . . . 9 l Assessment . . . . . . . . . . . . . . . . . . . . . 10 PART F. METEOROLOGICAL DATA . . . . . . . . . . . . . . . . 11 l

PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES . . . 11 PART H. INOPERABLE MONITORS . . . . . . . . . . . . . . . . 11 l l

PART I. PROCESS CONTROL PROGRAM (PCP) CHANGES. . . . . . . . 11 PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES. . . . . . 11 5 , __

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HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1993  :

INTRODUCTION This report, HCGS-RERR-15, 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 January 1, 1993 to June 30, 1993.

The Hope Creek 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 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 .9, 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 4,407,788 megawatt-hours of electrical energy (net) during the reporting period. l Results of liquid and gaseous composites analyzed for Sr-89, ,

Sr-90 and Fe-55 for the second 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 second half of 1992 (refer to RERR-14) have been completed; amended pages to RERR-14 are included in this report.

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t PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS t

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 i to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, i During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.  :

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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i 1.3 Liquid Effluents Release 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 radionuclides other than  !

dissolved or entrained noble gases. For dissolved or i entrained noble gases, the concentration shall be limited to 2E-4 microcuries per milliliter.

  • In addition, the dose or dose commitment to a member of i the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to: l During any calendar quarter: Less than or equal l to 1.5 mrens to the total body, and less than or equal to 5 mrems to any organ, and  :

During any calendar year: Less than or equal to '

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3 mrems to the total body, and less than or equal to 10 mrems to any organ.

1 1.4 Total Dose Limit ,

The annual (calendar year) dose or dose commitment to j any member of the public, due to releases of i radioactivity and radiation, from uranium fuel cycle  !

I 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 I to 75 mrems).

2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) 1 Regulatory Guide 1.21 requires that the licensee provide the j 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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t 3.0 AVERAGE ENERGY  ;

1 Regulatory Guide 1.21 requires that the licensee provide the ,

I 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, _i batch liquid wastes were  !

routed to the sampling tanks for ucinitoring prior to i release. Technical Specifications require these tanks  :

to be uniformly mixed for sampling and analysis before  !

being released. Batch releases arc 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 -

J liquid releases. Specific activities from analyses were multiplied by the volume of effluent discharged to the  !'

i environment in order to determine the total liquid activity discharged. [

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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

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

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

The detection requirements of Tables 4.11.2.1.2-1 of j 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 j activity was detected while meeting the required i LLDs are treated as absent.

Continuous Mode gaseous releases are quantified by -

routine (monthly) sampling and isotopic analyses of the l 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.  !

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

i 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.

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

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

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

8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS Our last report (RERR-14) did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the second half of 1992. Amended pages to RERR-14 are included at the end of this report.

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PART B. GASEOUS EFFLUENTS i i

See Summary Tables 1A through IC. l 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 l population dose impact is based on historical site specific data i.e., food production, milk production, feed for milk i animals and seafood production.  !

The doses were calculated using methods described in l Regulatory Guide 1.109 and represent calculations for the  !

six month reporting interval. Individual doses from batch i 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 1 dispersion coefficients for the six month reporting i interval. i Liauid 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. i i

Total body dose : 8.43E-02 mrem Highest organ dose (LIVER): 1.88E-01 mrem Dose to the 5 million individuals living within the 50 mile radius of the plant site:

Total population dose: 9.46E-01 person-rem Average population dose: 1.58E-04 mrem / person 7

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Air Pathways l

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The calculated doses to individuals via the air j pathway are shown below: j Total body dose: 3.39E-02 mrem Skin dose: 7.38E-02 mrem i Highest organ dose due to radiciodines and l particulates with half lives greater than 8 days:  ;

I 5.19E-05 nrem to the LIVER  !

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

1 Total population dose: 2.44E-01 person-rem Average population dose: 4.09E-05 mrem / person Direct Radiation  ;

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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  ;

i natural background radiation.  ;

'1 TLD data for the six month reporting period is given ]'

below:

TLD Location Measurement 2S-2 0.3 mile 4.6 mrad / month SS-1 0.9 mile 4.4 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. i 8

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i Total Dose ,

r l 40CFR190 limits the total dose to members of the public ;

due to radioactivity and radiation from uranium fuel l i cycle sources to ,

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! <25 mrem total body or any organ i

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

i The following doses to a " maximum hypothatical I individual " have been calculated for t'..e six month 3 reporting period. They are the sum of gaseous and l

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liquid pathway doses for the Salem 1 and 2 and Hope  !

Creek plants:

0.458 mrem total body 1.490 mrem organ (GI-LLI) l 0.339 mrem thyroid j j

Dose to members of the public due to activities inside  ;

-the site boundarv.  ;

l l In accordance with the requirements of Technical l Specification 6.9.1.7, the dose to members of the ]

l public inside the site boundary has been calculated l based on the following assumptions:

a. Such persons are participating or spectators in company softball league i
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 i

! c. dose due to airborne pathway.(inhalation  !

and immersion) j d. persons are located about 3/4 mile east of plant j discharge points (baseball fields)
e. occupancy coincides with batch gaseous i discharges

.i i For the six month reporting period, the calculated

! doses are:

i 7.08E-05 mrem total body 7.20E-05 mrem organ (Lung) i l 9 4

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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.  ;

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

Hope Creek liquid effluents decreased slightly from previous reporting period.

Tritium in liquid effluents decreased significantly from previous reporting period. Control rods removed from the core during the previous refueling outage appear to be the cause of the elevated tritium values.

Tritium in gaseous effluents increased significantly from previous reporting period. The increase can be  ;

attributed to the detection capability of the tritium analysis and the high flow rate of the plant vent.

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.

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PART F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation i are provided for the first and second quarters of 1993 in Tables 5 and 6. .

PART G. OFFSITE DOSE CkLCULATION MANUAL (ODCM) CHANGES i

During this period, there were no changes to the HCGS )'

l Off-site Dose Calculation Manual.

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PART H. INOPERABLE MONITORS I

During this period, there were no effluent monitors l inoperable for greater than 30 days.

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

the process control program. l i  !

l PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES During the reporting period, there were no changes to the environmental monitoring sampling locations.

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HOPE CREEK GENERATING STATION l TABLE 1A -

i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT i JANUARY - JUNE 1993 i C?SEOUS EFFLUENTS-SUMMATION OF ALL RELEASES I i

Est. l 1st 2nd Total }

Units Quarter Quarter Error %

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A. Fission and Activation Gases l

1. Total release Ci 9.25E+00 3.70E+00 25 l
2. Average release _

rate for period pCi/sec 1.19E+00 4.71E-01 l

3. Percent of technical I specification limit (T.S. 3.11.2.2(a))  % 1.26E-01 5.05E-02 B. Iodines

, 1. Total iodine-131,133 Ci 0.00E+00 0.00E+00 25 1

2. Average release l rate for period yCi/sec 0.00E+00 0.00E+00  !
3. Percent of technical j specification limit (2) i (T.S. 3.11.2.3(a))  % 5.13E-04 2.34E-04 C. Particulates l
1. Particulates with I half-lives >8 days Ci 2.08E-04 4.52E-04 25  !
2. Average release i rate for period pCi/sec 2.68E-05 5.74E-05
3. Percent of technical  !

specification limit (2)

(T.S. 3.11.2.3(a))  % 5.13E-04 2.34E-04

4. Gross alpha Ci 0.00E+00 2.84E-07 ,

D. Tritium

1. Total Release Ci 1.14E+01 9.15E+01 25
2. Average release rate for period pCi/sec 1.47E+00 1.16E+01  :

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3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))  % 5.13E-04 2.34E-04 i

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

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

HOPE CREEK GENERATING STATION TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1993 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission Gases Krypton-83m Ci 9.25E-02 3.70E-02 0.00E+00 0.00E+00 Krypton-85m Ci 9.25E-02 3.70E-02 0.00E+00 0.00E+00 Krypton-87 Ci 3.70E-01 1.48E-01 0.00E+00 0.00E+00 Krypton-88 Ci 3.70E-01 1.48E-01 0.00E+00 0.00E+00 Krypton-89 Ci 2.50E+00 9.99E-01 0.00E+00 0.00E+00  ;

Xenon-133 Ci 1.85E-01 7.40E-02 0.00E+00 0.00E+00 l Xenon-135 Ci 4.62E-01 1.85E-01 0.00E+00 0.00E+00 Xenon-135m Ci 5.55E-01 2.22E-01 0.00E+00 0.00E+00 Xenon-137 Ci 2.87E+00 1.15E+00 0.00E+00 0.00E400 Xenon-138 Ci 1.76E+00 7.04E-01 0.00E+00 0.00E+00 l TOTALS Ci 9.25E+00 3.70E+00 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-live >8 days Manganese-54 Ci 0.00E+00 1.97E-05 0.00E+00 0.00E+00 Zinc-65 Ci 2.08E-04 5.63E-05 0.00E+00 0.00E+00 Chromium-51 Ci 0.00E+00 3.76E-04 0.00E+00 0.00E+00 TOTALS C1 2.08E-04 4.52E-04 0.00E+00 0.00E+00 13

HOPE CREEK GENERATING STATION TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1993 GASEOUS EFFLUENTS-ELEVATED RELEASES There were no elevated gaseous releases during this reporting period.

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f HOPE CREEK GENERATING STATION -[

i TABLE 2A l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT  ;

JANUARY - JUNE 1993 i i

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES l

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Est. i ist 2nd Total 'j Units Quarter Quarter Error % j j

A. Fission and activation  ;

products i

1. Total release (not  !

including tritium, gases, alpha) Ci 6.32E-02 1.02E-C1 25 i

2. Average diluted ,

concentration during l release period, pCi/mL 8.94E-08 1.18E-07 j

3. Percent of technical specification limit  ;

(T.S. 3.11.1.2.(a))  % 2.53E+00 3.29E+00 l B. Tritium i

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1. Total release C1 1.37E+01 1.27E+01 25
2. Average diluted concentration during release period pCi/mL 1.95E-05 1.47E-05
3. Percent of technical specification limit I (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 .
3. Percent of technical j 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 I (prior to dilution - l Batch Release) liters 3.90E+06 3.65E+06 25 l l

F. Volume of dilution water used during entire period liters 1.17E+10 1.55E+10 25 l

15 t' *- m --

HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1993 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter Niobium-97 Ci O.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-S4 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 0.00E+00 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 1.02E-01 Tritium Ci O.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 O.00E+00 0.00E+00 2.21E-03 2.32E-03 TOTALS Ci 0.00E+00 0.00E+00 1.37E+01 1.27E+01 16 d

1 I

HOPE CREEK GENERATING STATION l l

TABLE 3 .

l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS i

^

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) ,

6-month Est. Total l

1. Type of waste Units (1) period Error, %
a. Spent resins, filters, m3 6.84E+01
  • sludges, evaporator bottoms Ci 1.98E+03 25 j i b. Dry compressible waste, m3 1.45E+01 j contaminated equipment. Ci 1.50E+00 25 i i
c. Irradiated components, m3 0.00E+00 ,

control rods Ci 0.00E+00 25 l

d. Others (described) m3 2.68E+01 '

Oil Ci 9.03E-03 25 j s

2. Estimate of major nuclide composition (for Type A and B waste) i <

RESINS DAW OIL q

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

Chromium-51 0.0 0.00E+00 13.6 2.00E-01 0.0 0.00E+00 Iron-55 43.7 8.64E+02 35.2 5.30E-01 36.8 3.32E-03 Manganese-54 12.6 2.49E+02 4.0 6.00E-02 13.8 1.25E-03 ,

Cerium-144 2.1 4.15E+01 0.0 0.00E+00 0.0 0.00E+00  !

Cobalt-60 5.5 1.09E+02 2.4 3.60E-02 2.5 2.26E-04 Nickel-63 0.0 0.00E+00 0.0 0.00E+00 0.0 0.00E+00 i Zinc-65 33.7 6.66E+02 43.0 6.50E-01 45.3 4.09E-03 j Cesium-137 0.9 1.78E+01 '

.i l

L i

1

[

17 e

1 6

  • i 1

i HOPE CREEK GENERATING STATION  !

1 TABLE 3 (CONT'D) i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 4 JANUARY - JUNE 1993 l SOLID WASTE AND IRRADIATED FUEL SHIPMENTS -

3. Solid Waste Disposition i

Number of Mode of Type of ,

Shipments Transportation Destination Cr? :. siners l

24 Tru'ck Barnwell, SC HIC and  ;

17E Drums '

5 Truck Oak Ridge, Tn Strong, Tight ;

Containers l l

1 i

IRRADIATED FUEL SHIPMENTS (Disposition)  !

Number of Mode of '

Shipments Transportation Destination i

None N/A N/A l i

A l

i I

l 1

18 l 1

l l

HOPE CREEK GENERATING STATION TABLE 4A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1993

SUMMARY

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

1. Dates: January 1 - March 31, 1993
2. Type of release: Gas
3. Number of releases during the 1st Quarter: 0
4. Total time duration for all releases of type listed abovr.:

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 19

4

)

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

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1993

SUMMARY

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

1. Dates: April 1 - June 30, 1993 j
2. Type of release: Gas
3. Number of releases during the 2nd Quarter: 1
4. Total time duration for all releases of type listed above:

6.84E+03 min

5. Maximum duration for release of type listed above:

6.84E+"3 min j

6. Average duration for release of type listed above:

6.84E+03 min

7. Minimum duration for release of type listed above:

6.84E+03 min

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

20

l 1

HOPE CREEK GENERATING STATION TABLE 4B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1993

SUMMARY

SHEET FOR RADIOACTIVE ~ EFFLUENTS RELEASED IN A BATCH MODE I

[

BATCH RELEASES ONLY ,

i

1. Dates: January 1 - March 31, 1993
2. Type of release: Liquid
3. Number of releases during the 1st Quarter: 97
4. Total time duration for all releases of type listed above: [

7.80E+03 min

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

1.27E+02 min

6. Average duration for release of type listed above:

8.04E+01 min

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

9.0E+00 min T

8. Average stream flow (dilution flow) during the period of release: 23465 gpm  ;

P 1

f I

21 r

6 i

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

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1993

SUMMARY

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

1. Dates: April 1 - June 30, 1993
2. Type of release: Liquid
3. Number of releases during the 2nd Quarter: 97
4. Total time duration for all releases of type listed above:

7.28E+03 min

5. Maximum duration for release of type listed above:

1.09E+02 min

6. Average duration for release of type listed above:

7.51E+01 min

7. Minimum duration for release of type listed above:

1.12+01 min

8. Average stream flow (dilution flow) during the period of release: 31116 3pm 22

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4 ARilFICIAL ISLAND 1/93 - 3/93 JOINT DISTRIBuilON OF WIND DIRECilON AND SPEED RT ATMOSPHERIC STABILITY CLASS WIND: 300 Fi L APSE RATE: -1.4 TO 0.5 DEG C/100M

( DELTA T: (300 33FT) CtASS D i

WIND SPEED GROUPS (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 PERCENT DIRECil0N SUM PERCENT SUM PERCENT SUM PERCENT SLM PERCENT SUM PERCENT SLM PERCENT SUM PERCENT N O 0.0 0 0.0 7 0.3 9 0.4 9 0.4 1 0.0 7 0.3 33 1.6 kNE O 0.0 0 0.0 12 0.6 26 1.3 54 2.6 23 1.1 4 0.2 119 5.8 NE O 0.0 0 0.0 4 0.2 31 1.5 19 0.9 3 0.1 10 0.5 67 3.3 l ENE O 0.0 1 00 4 0.2 13 0.6 11 0.5 10 0.5 14 0.7 53 2.6 E O 0.0 0 0.0 4 0.2 8 0.4 5 0.2 1 0.0 1 0.0 19 0.9 ESE O 0.0 1 0.0 4 0.2 8 0.4 7 0.3 5 0.2 0 0.0 25 f.2 1 SE O 0.0 0 0.0 6 0.3 5 0.2 4 0.2 7 0.3 4 0.2 26 1.3 SSE O 0.0 0 0.0 7 0.3 15 0.7 21 1.0 11 0.5 0 0.0 54 2.6

$ 0 0.0 0 0.0 10 0.5 4 0.2 6 0.3 14 0.7 0 0.0 34 1.7

$$W 0 0.0 0 0.0 2 0.1 7 0.3 1 0.0 0 0.0 0 0.0 10 0.5 SW 0 0.0 0 0.0 2 0.1 1 0.0 6 0.3 3 0.1 1 0.0 13 0.6 WSW 0 0.0 0 0.0 7 0.3 12 0.6 18 0.9 9 0.4 1 0.0 47 2.3 W 0 0.0 0 0.0 11 0.5 16 0.8 22 1.1 12 0.6 15 0.7 76 3.7 WWW 0 0.0 3 0.1 5 0.2 21 1.0 34 1.7 24 1.2 14 0.7 101 5.0 NW 0 0.0 0 0.0 6 0.3 17 0.8 24 1.2 36 1.8 35 1.7 118 5.8 NNW 0 0.0 0 0.0 9 0.4 9 0.4 11 0.5 3 0.1 23 1.1 55 2.7 0 0.0 5 0.2 100 4.9 202 9.9 252 12.4 162 7.9 129 6.3 850 41.T MEAN WIND SPEED: 16.5 MISSINGt 28 Table 5 Page 4 of 9

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ARTIFICIAL lSLAND 1/93 - 3/93 JOINT DISTRIBuil0N OF WIND DIRECTION AND SPEED BT ATMOSPHERIC STABILITY CLASS WINO: 300 ?T DELTA T: (300-33FT) ALL STAdlLITY CLASSES WIND SPEED GRC'JPS (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 DIREC1104 $UM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM P2RCENT N O 0.0 0 0.0 17 0.8 30 1.5 46 2.3 14 0.7 9 0.4 116 5.7 NNE O 0.0 1 0.0 i, 0.6 50 2.5 78 3.8 26 1.3 4 0.2 1 72 8.4 NE O 0.0 0 0.0 14 0.7 41 2.0 31 1.5 9 0.4 11 0.5 106 5.2 ENE O 0.0 2 0.1 14 0.7 41 2.0 26 1.3 12 0.6 16 0.8 111 5.4 E O 0.0 0 0.0 16 0.8 26 1.3 9 0.4 2 0.1 1 0.0 54 2.6 ESE O 0.0 2 0.1 12 0.6 22 1.1 14 0.7 17 0.8 0 0.0 67 3.3 SE O 0.0 0 0.0 12 0.6 14 0.7 to 0.5 14 0.7 11 0.5 61 3.0 SSE O 0.0 1 0.0 12 0.6 31 1.5 38 1.9 22 1.1 5 0.2 109 5.3 5 0 0.0 1 0.0 14 0.7 13 0.6 23 1.1 37 1.8 7 0.3 95 4.7 SSW 0 0.0 0 0.0 6 0.3 14 0.7 19 0.9 15 0.7 2 0.1 56 2.7 SW 0 0.0 1 0.0 6 0.3 15 0.7 23 1.1 19 0.9 5 0.2 69 3.4 WSW D 0.0 2 0.1 10 0.5 38 1.9 52 2.6 32 1.6 7 0.3 141 6.9 W 0 0.0 0 0.0 18 0.9 41 2.0 68 3.3 56 2.7 25 1.2 208 10.2 WWW D 0.0 3 0.1 8 0.4 43 2.1 74 3.6 53 2.6 23 1.1 204 10.0 NW 0 0.0 0 0.0 14 0.7 54 2.6 98 4.8 94 4.6 56 2.7 316 15.5 NNW 0 0.0 1 0.0 15 0.7 43 2.1 42 2.1 18 0.9 34 1.7 153 7.5 0 0.0 14 0.7 201 9.9 516 25.3 651 31.9 440 21.6 216 10.6 2038 100.0 MISSING HOU4S: 122 MEAN WIND SPEED: 15.8 Table 5 Page 8 of 9 9

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ARilFICIAL ISLAND 1/93 - 3/93 JOINI OISTRIBUTION OF WlhD OIRECilON AND SPEED BT ATMOSPHERIC STABillfY CLASS WIND: 300 FT DELIA i: (300 33FT) OIRECilcN v5 SPEED ONLY WIND SPEED GROUPS (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 SIR PERCENT DIRECil0N SUM PERCENT SLM PERCENT SUM PERCENT SLM PERCENT SUM PERCfMT SLM PERCENT SUM PERCENT N O 0.0 0 0.0 17 0.8 33 1.6 47 2.3 14 0.7 9 0.4 NNE O 0.0 0.0 120 5.8 1 13 0.6 51 2.5 78 3.8 26 1.3 4 0.2 1 73 8.3 NC 0 0.0 0 0.0 14 0.7 41 2.0 38 1.8 9 0.4 11 0.5 115 5.5 LNE O 0.0 2 0.1 14 0.7 42 2.0 33 1.6 0.7 0

14 16 0.8 121 5.8 L U 0.0 0.0 16 0.8 26 1.3 9 0.4 2 0.1 1 0.0 54 2.6 Est 0 0.0 2 0.1 12 0.6 22 1.1 0.7 14 17 0.8 0 0.0 67 3.2 SE O 0.0 0 0.0 12 0.6 14 0.7 11 0.5 0.7 0.0 15 11 0.5 63 3.0 SSE O 1 0.0 12 0.6 31 1.5 38 1.8 22 1.1 5 0.2 109 5.3 S 0 0.0 1 0.0 14 0.7 13 0.6 23 1.1 37 1.8 7 0.3

$$w 0 0.0 0 0.0 95 4.6 6 0.3 14 0.7 17 0.9 15 0.7 2 0.1 0 0.0 56 2.7 SW 1 0.0 6 0.3 15 0.7 23 1.1 .19 0.9 5 0.2 69 3.3 WSW 0 0.0 2 0.1 10 0.5 38 1.8 52 2.5 32 1.5 0.3 0 0.0 7 141 6.8 W 0 0.0 18 0.9 43 2.1 69 3.3 56 2.7 25 1.2 211 10.2 Www 0 0.0 3 0.1 9 0.4 43 2.1 75 3.6 54 2.6 23 1.1 207 10.0 WW D 0.0 0 0.0 14 0.7 56 2.7 98 4.7 94 4.5 56 2.7 318 15.3 WNW D 0.0 1 0.0 16 0.8 44 2.1 43 2.1 18 0.9 34 1.6 156 7.5 0 0.0 14 0.7 203 9.8 526 25.4 670 32.3 444 21.4 216 10.4 2073 100.0 MISSING MOURS: 87 MEAN WIND SPEED: 15.8 Tabic 5 Page 9 of 9

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f AtilFICIAL ISLAND 4/93 - 6/93 J0lNT DISTRIBUTION OF WINO DIRECil0N AND SPEED BY ATMOSPMERIC STA81LITY CLASS WINO: 300 FT DELTA T: (300 33FT) ALL STA81LliY CLASSES

+

WIND SPEED GROUPS (MPN) 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 $UM PERCENT DIREC*104 SUM PERCENT SUM PERCENT SLM PERCENT SUM PERCENT SLM PERCENT SUM *ERCENT SOM PERCENT N 0 0.0 2 0.1 16 0.8 56 2.8 32 1.6 21 1.0 14 0.7 141 7.1 WNE O 0.0 1 0.1 12 0.6 33 1.6 33 1.6 10 0.5 1 0.1 90 4.5 NE O 0.0 2 0.1 24 1.2 23 1.1 27 1.4 8 0.4 1 0.1 85 4.3 ENE O 0.0 0 0.0 31 1.5 28 1.4 12 0.6 3 0.2 0 0.6 74 3.7 E O 0.0 5 0.3 21 1.0 16 0.8 T 0.4 0 0.0 0 0.0 49 2.5 ESE O 0.0 1 0.1 9 0.4 22 1.1 16 0.8 2 0.1 4 0.2 54 2.7 SE O 0.0 2 0.1 15 0.8 18 0.9 37 1.9 37 1.9 27 1.4 136 6.8 SSE O e.0 3 0.2 30 1.5 50 2.5 92 4.6 52 2.6 27 1.4 254 12.7 5 0 0.0 4 0.2 29 1.4 44 2.2 34 1.7 28 1.4 4 0.2 143 7.2 SSW 0 0.0 5 0.3 16 0.8 28 1.4 53 2.6 45 2.3 9 0.4 156 7.8 SW 0 0.0 2 0.1 15 0.8 38 1.9 47 2.3 32 1.6 4 0.2 138 6.9 WSW 0 0.0 3 0.2 21 1.0 37 1.9 52 2.6 26 1.3 0 0.0 139 6.9 W 0 0.0 0 0.0 20 1.0 27 1.4 26 1.3 17 0.9 4 0.2 94 4.7 WNW 0 0.0 1 0.1 to 0.5 20 1.0 48 2.4 20 1.0 3 0.2 102 5.1 NW 0 0.0 1 0.1 16 0.8 28 1.4 76 3.8 58 2.9 30 1.5 209 10.5 NMW 0 0.0 0 0.0 19 0.9 32 1.6 53 2.6 23 1.1 9 0.4 136 6.8 0 0.0 32 1.6 304 15.2 500 25.0 645 32.3 382 19.1 137 6.8 2000 100.0 MISSING MOURS: 184 MEAN WIND SPEED: 14.5 Tabic 6 j Page 8 of 9 l

l l

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l 3

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ARilFICIAL ISLANO 4/93 6/93 J0!NT DISTRIBuil0N OF WIND DIf t?'10N AND SPEED BY ATMOSPNERIC STASIL11V CLASS WINO: 300 FT DELTA is (300-33FT) DIRECTION VS SPEED ONLY j WINO 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 SUM PERCENT I DIREttlON SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N O 0.0 2 0.1 16 0.8 60 2.8 35 1.6 21 1.0 14 0.7 148 T.0 W4E O 0.0 1 0.0 13 0.6 41 1.9 36 1.7 12 0.6 1 0.0 104 4.9 ht 0 0.0 2 0.1 25 1.2 30 1.4 29 1.4 8 0.4 1 0.0 95 4.5 ENE O 0.0 0 0.0 32 1.5 28 1.3 12 0.6 9 0.4 0 0.0 81 3.8 E O 0.0 5 0.2 21 1.0 16 0.8 7 0.3 0 0.0 0 0.0 49 2.3 ESE O 0.0 1 0.0 9 0.4 22 1.0 16 0.8 2 0.1 4 0.2 54 2.5 SE o 0.0 2 0.1 15 0.7 18 0.8 37 1.7 37 1.7 27 1.3 116 6.4 SSE O 0.0 3 0.1 30 1.4 52  ?.4 95 4.5 53 2.5 27 1.3 260 14.2 S 0 0.0 4 0.2 29 1.4 44 2.1 34 1.6 28 1.3 4 0.2 143 6.7 SSW D 0.0 5 0.2 17 0.8 28 1.3 53 2.5 45 2.1 9 0.4 157 T.4 SW 0 0.0 2 0.1 17 0.8 41 1.9 50 2.4 32 1.5 4 0.2 146 6.9 WS*J 0 0.0 4 0.2 26 1.2 41 1.9 54 2.5 26 1.2 0 0.0 151 T.1 W 0 0.0 0 0.0 26 1.2 34 1.6 27 1.3 17 0.8 4 0.2 108 5.1 Wuw 0 0.0 1 0.0 13 0.6 24 1.1 52 2.4 20 0.9 3 0.1 113 5.3 NW 0 0.0 1 0.0 16 0.8 32 1.5 91 4.3 63 3.0 30 1.4 233 11.0 NNW 0 0.0 0 0.0 20 0.9 38 1.8 57 2.7 23 1.1 9 0.4 147 6.9 0 0.0 33 1.6 325 15.3 549 25.8 685 32.2 396 18.6 137 6.4 2125 100.0 MISSING NOL1ts: 59 MEAN WINO SPEED: 14.4 7'a bil e 6 Page 9 of ')

AMENDMENT TO IERR 14 i

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

l 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 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.

Liauid 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 : 9.50E-02 mrem Highest organ dose (GI-LLI): 2.19E-01 mrem Dose to the 6 million individuals living within the 50 mile radius of the plant site:

Total population dose: 1.09E+00 person-rem Average population dose: 1.83E-04 mrem / person 7

o HOPE CREEK GENERATING STATION TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1992 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.

3rd 4th Total Units Quarter Quarter Error %

A. Fission and activation l products j

1. Total release (not including tritium, gases, alpha) Ci 1.06E-01 8.11E-02 25
2. Average diluted concentration during ,

release period. pCi/mL 6.13E-08 9.17E-08 I

3. Percent of technical specification limit (T.S. 3.11.1.2.(a))  % 2.87E+00 3.47E+00 B. Tritium
1. Total release Ci 6.06E+01 2.38E+01 25
2. Average diluted concentration during release period pCi/mL 3.50E-05 2.69E-05
3. Percent of technical specification limit (T.S. 3.11.1.1)  % 1.16E+00 8.97E-01 C. Dissolved and entrained noble gases
1. Total release Ci 4.60E-03 1.63E-03 25
2. Average diluted concentration during release period. yCi/mL 2.66E-09 1.84E-09
3. Percent of technical specification limit (T.S. 3.11.1.1)  % 1.33E-03 9.20E-04 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 7.04E+06 4.89E+06 25 F. Volume of dilution water used during entire period liters 1.61E+10 1.20E+10 25 15

{ *

+

HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1992 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter i

Niobium-95 Ci O.00E+00 0.00E+00 2.92E-05 4.66E-05 Chromium-51 Ci 0.00E+00 0.00E+00 2.95E-02 1.17E-02 Manganese-54 Ci 0.00E+00 0.00E+00 2.99E-02 2.66E-02 l Iron-55 Ci 0.00E+00 0.00E+00 6.49E-03 5.87E-03 Iron-59 Ci 0.00E+00 0.00E+00 5.53E-03 7.91E-03 Cobalt-58 Ci 0.00E+00 0.00E+00 9.23E-04 9.12E-04 i Ci Cobalt-60 0.00E+00 0.00E+00 5.20E-03 3.71E-03 Zinc-65 Ci 0.00E+00 0.00E+00 2.64E-02 2.23E-02 Silver-110m Ci 0.00E+00 0.00E+00 1.98E-03 2.00E-03 Sodium-24 Ci 0.00E+00 0.00E+00 0.00E+00 7.25E-06 Lanthanum-140 Ci 0.00E+00 0.00E+00 8.28E-06 0.00E+00 Arsenic-76 Ci 0.00E+00 0.00E+00 3.35E-05 0.00E+00 Zinc-69m Ci 0.00E+00 0.00E+00 9.24E-06 0.00E+00 TOTALS Ci 0.00E+00 0.00E+00 1.06E-01 8.11E-02 Tritium Ci 0.00E+00 0.00E+00 6.06E+01 2.38E+01 Xenon-133 Ci 0.00E+00 0.00E+00 2.91E-04 0.00E+00 Xenon-135 Ci 0.00E+00 0.00E+00 4.31E-03 1.63E-03 TOTALS Ci 0.00E+00 0.00E+00 6.06E+01 2.38E+01 16

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