ML20090A069

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Semiannual Radioactive Effluent Release Rept for 1991
ML20090A069
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 12/31/1991
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N92012, NUDOCS 9203020132
Download: ML20090A069 (52)
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F E B .: i 1992 NLR-N92012 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

RADIOACTIVE EFFLUENT RELEASE REPORT - 12 HOPE CREEK GENERATING STATION DOCKET NOS, 50-272-AND-50-311 7

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In accordance with SectioE 6.9.1.11 of Appendix A to the Operating License for Hope Creek Generating Station (HCGS),

Public Service Electric and Gas Company (PSE&G) hereby transmits one copy of tne semi-annual Radioactive Effluent Release Report, RERR-12. This report summarizes liquid and gaseous releases and solid Waste shipments from the Hope Creek Generating Station for the period July 1 through December 31, 1991.

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

Sincerely, _

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P Attachment 0 *I.0 t (3 J j!?28a!!3aa!8a54 rger PDR (g

Document Control Desk 2 f r g ,, g .m NLR-N92012 "'

RLtC PEPORT only C Mr. S. Dembek (1)

Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator (2)

Region I

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Mr. K. Tosch, Chief (1)

NJDEP USNRC, Director (1)

Office of Nuclear Reactor Reg lation Washington, DC 205SS

4 HOPE CREEK GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HCGS RERR-12

.70CKET NO. 50-354 OPERATING LICENSE NO. NFP-57

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l IlOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1991 Table of Contents INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . 1 PART'A. PRELIMINARY SUPPLEMENTAL INFORMATION . . . . . . . . . 2 1.0 REGULATORY LIMITS . .. . . . . . . . . . . . . . . . 2 1.1 Fission and Activation Gas Release Limits . . . . 2 1.2 . Iodine, Particulates, and Tritium . . . . . . . . 2 1.3 Liquid Effluents Release. Limits . . . . . . . . . 3 1.4 Total-Dose Limit . . . . . . .. . . . . . . . . 3 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) . . . . . . . 3 3.0 AVERAGE ENERGY . . . . . . . . . . . . . . . . . . . . 4 4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4 S . O. BATCH RELEASES . . . . . . . . . . . . . . . . . . . . 6 6.0 UNPLANNED RELEASES . . . . . . . . . . . . . . . . . . 6 7.0 ELEVATED RADIATION MONITOR RESPONSES . . . . . . . . . 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 pal';T E. RADIOLOGICAL IMPACT ON MAN . . . . . . . . . . . . . .7

-Liquid Pathways . . . . . . . . . . . . . . . . . . . . . 7 Air Pathways . . . . . . . . . . . . .. . . . . . . . 8 Direct Radiation 1 . ... . . . . . .. . . . . . . . 8 Total Dose . . . . . .. . . . . . . . . . . .. . . . 9 Dose to Members of the Public~on Site . . . . . . . . 9-Assessment . . . . . . . . . . . . . . . . . . . . . 10 PART F. METEOROLOGICAL DATA . .. . . . . . . . . .. . . . .. 11 PART G.- OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES . . . 11

'PART H. INOPERABLE MONITORS . . . . . . . . . . . . . . . . 11 PART I. ENVIRONMENTAL MONITORING LOCATION CHANGES . . . . . 11

HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1991 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 July 1 , 1991 to December 31, 1991.

The Hope Creek Generating Station (HCGS) employs a General Electric (GE) Boiling Water Reactor designed to operate at a rated core thermaj power of 3293 MWt with a gross electrical output of approximately 1118 MWe and a net output of approximately 1067.MWe. The HCGS achieved initial criticality on June 28, 1986 and went into commercial operation on December 20, 1986.

This report is prepared in the format of Regulatory Guide 1.21,

-Appendix B, as required by Specification 6.9.1.7 of the Hope Creek Technical Specifications . 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 1.21, Appendix B.

As required by Regulatory Guide 1.21, our Technical Spccification limits are described in detail within this report along with a summary description of how total activity 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 4,516,979 megawatt-hours of electrical energy (net) during the reporting period.

Results of liquid and gaseous composites analyzed for Sr-89, Sr-90 and Fe-55 for the fourth quarter of 1991 were not available

'for inclusion in this report. The results of these composites will be provided in the next Radioactive Effluent Release Report.

f The Sr-89, Sr-90 and Fe-55 analyses for the first half of 1991 (refer to RERR-11) have been completed; amended pages to RERR-11 are included in this report.

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t' PART~A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS 1.1 Fission and Activation Gas Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following:

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

In addition, the air dose due to noble gases released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following:

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

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

For Iodine-131,I-133, for tritium, and for a.ll 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-131,133, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents 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 calencar year: Less than or equal to 15 mrems to any organ.

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1.3 Liquid Effluents Release Limits The concentration of radioac2ive 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 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 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 mrems 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 3 mrems to the total body, and less than or equal to 10 mrems to any organ.

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

2.0 MAYIMUM PERMISSIBLE CONCENTRATIONS (MPC)

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

, a. MPC values-were not used to determine the maximum release rates for fission gases, lodines, 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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s 3.0 AVERAGE ENERGY Regulatory Guide 1.21 requires that the licensee provide the average energy of the radionuclide mixture in releases of fission and activation gases, if applicable.

Release limits for HCGS are not based upon average energy.

Therefore this section is not applicable to HCGS.

4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4.1 Liquid Effluents Liquid effluents are monitored in accordance with Table 4.11.1.1.1-1 of the Technical Specifications. During the period of record, all 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 analyses were multiplied by the volume of effluent discharged to the environment in order to determine the total liquid activity discharged.

The detection requirements of Table 4.1.1.1-1 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 with a one sigma gamma counting error > 30% are considered as not being present.

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

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

Radionuclides measured at concentrations below the Technical Specification detection limit (LLDs) are treated as being present. Radionuclides with a one sigma gamma counting error > 30% are considered as not being present.

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

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

Noble gas isotopic abundances for these integrations are based on the ANSI N237-1976/ANS-18.1 mix for BWEs.

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

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

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

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4.3 EJtimated Total Error The estimated total error of reported liqui's releases is within 25%.

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

Error estimates for releases where sample activity is below the detectable concentration levels are not included since ciror 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, the plant vent 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 1B.

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8.0 HODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS Our last report (RERR-11) did not include the quarteriy 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 of this report.

PART B. GA8EOUS EFFLUENTS See Fummary Tables 1A through IC.

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

PART D. SOLID WASTE See Summary in Table 3.

PART E. RADIOLOGICAL IMPACT ON HAN The calculated individual doses in this section are based on actual locations of nearby residents and farms. The population dose impact is based on historical site specific data 1.e., food production, milk production, feed for milk animals and seafood production.

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

Population doses were calculated using the meteorological dispersion coefficients for the six month reporting interval.

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

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Total. body dose to an individual: 4.34E-02 mrom Highest organ' dose: 1.00E-01 mrom to the Liver Dose to the 6 million individuals living within the 50 mile radius of the plant site:

Total population dose: 5. 08E-01 persor.~ rem Average population dose: 8.51E-05 mrem / person

?.ir Pathways The calculated doses to individuals via the air pat:way are shown below:

Total body-dose: 3.87E-01 mrem Skin dose: 8.42E-01 mrem Highest organ dose due to radiolodines 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: 5.42E+00 persor.-rem Average population dose: 9.08E-04 mrem /percon Direct Radiation Direct-radiation may be estimated by Thermoluminescent dosimetric (TLD) measurements. One method for

-comparing TLD measurements is by comparison-With pre-operational data. It should be noted that the TLDs measure direct radiation from both the Salem and Hope Creek Generating Stations at Artificial Island, and natural background radiation.

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

TLD- Location Measurement l 2S-2 0.3 mile .5.0 mrad / month SS-1 0.9 mile 4.7 mrad / month ,

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4 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, and4 4.2 mrad / month for location SS-1. ,

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

<25 mrem total body or any organ

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

The following doses to a 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 Salem 1 and 2 and Hope Creek plants:

0.752 mrem total body 1,74 mrem organ (GI-LLI) 0.336 mrem thyroid Dose to members of the nublic 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 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 airborne pathway (inhalation) and noble gases
  • persons are located about 3/4 mile west of plant discharge points,(baseball fields)
  • occupancy coincides with batch gaseous discharges For the six month reporting period, the calculated doses are:

5.4E-03 mrem total body 5.5E-03 mrem organ (Lung) 9 l

Assessment Hope Creek gaseous offluents continue to be one of the lowest of United States BWRs, with an average release rate of 9.3 microcuries per second, characteristic of a plant with no cladding defects.

Individual noble gas radionuclide concentrations are too low to measure directly. Calculated doses from noble gases are based on a default isotopic mixture, which assumes little decay, and 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, assuming that the actual discharge consisted of mostly xenon-137.

Hope Creek liquid effluents are about the same as the previous reporting period, and lower than the average discharges of the previous three years. Calculated doses are due principally to isotopes of iron and zinc.

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

Hope Creek Gaseous Effluents Curles of Noble Gases Released and Calculated Doses

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Hope Creek Uquid Effluents Curles Released and Calculated Doses 14

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5x Year PART F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for the third and fourth quarters of 1991 in Tables 5 and 6.

PART G. OFFBITE DOSE CALCULATION MANUAL (ODCM) CHANGES During this period, there were no changes to the HCGS Of f-sito Dosei Calculation Manual.

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

PART I. ENVIRONMENTAL MONITORING LOCATION CHANGES During the reporting period, there was no changes to the environmental monitoring sampling locations.

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HOPE CREEK GENERATING STATION TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT-JULY - DECEMBER 1991 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est.

3rd 4th Total  !

Units Quarter Quarter Error % ,

a 1 A. Fission and Activation Gases 1.-Total release Ci 6.24E+01 8.55E+01 25

2. Average release '

rate for period #Ci/sec 7.85E+00 1.08E+01

3. Percent of technical specification limit (T.S. 3 .11. 2. 2 ( a) ',  % 8.51E-01 1.17E+00 B. Iodines
1. Total iodine-131,133 Ci 0.00E+00 0.00E+00 25
2. Average release rate for period #Ci/sec 0.00E+00 0.00E+00
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))  % 3.01E-06 7.28E-04 C. Particulates

1. Particulates with half-lives >8 days Ci '2.44E-07 3.91E-04 25
2. Average release rate for period pCi/sec 3.07E-08 4.92E-05 3.-Percent of technical specification limit (2)

L (T.S. 3.11.2.3(a))  % 3.01E-06 7.28E-04 4.-Gross alpha Ci 0.00E+00' O.00E+00 i -- D. Tritium

1. Total Release ci 5.28E+00 5.11E+00 25
2. Average release rate for period pCi/sec 6.64E-01 6.43E-01

-3. Percent of technical specification limit (2)

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(T.S. 3.11.2.3(a))  % 3.01E-06 7.28E-04 i

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

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

HOPE CREEK GENERATING STATION TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission Gases Krypton-83m Ci 6.24E-01 8.55E-01 0.00E+00 0.00E+00 Krypton-85m Ci 6.24E-01 8.55E-01 0.00E+00 0.00E+00 Krypton-87 Ci 2.49E+00 3.42E+00 0.00E+00 0.00E+00 Krypton-88 Ci 2.49E+00 3.42E+00 0.00E+00 0.00E+00 Krypton-89 C1 1.68E+01 2.31E+01 0.00E+00 0.00E+00 Xenon-133 C1 1.25E+00 1.71E+00 0.00E+00 0.00E+00 Xenon-135 Ci 3.12E+00 4.28E+00 0.00E+00 0.00E+00 Xenon-135m Ci 3.74E+00 5.13E+00 0.00E+00 0.00E+00 Xenon-137 Ci 1.93E+01 2.65E+01 0.00E+00 0.00E+00 Xenon-138 Ci 1.19E+01 1.63E+01 0.00E+00 0.00E+00 TOTALS Ci 6.24E+01 8.55E+01 0.00E+00 0.00E+00
2. Iodines Iodine-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS Ci 0.00E+00 0.00E+00 0.00E400 0.00E+00
3. Particulates (half-live >8 days Manganese-54 Ci 1.09E-07 9.42E-05 0.00E+00 0.00E+00 Zinc-65 Ci 1.35E-07 2.97E-04 0.00E+00 0.00E+00 TOTALS C1 2.44E-07 3.91E-04 0.00E+00 0.00E+00 13

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TABLE 1C EFFLUEllT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 SASEOUS EFFLUENTS-ELEVATED RELEASES There were no elevated gaseous releases during this reporting period.

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HOPE CREEK GENERATING STATION TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ,

JULY - DECEMBER 1991 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.

3rd 4th Total Units Quarter Quarter Error % j l

A. Fission and activation i I

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1. Total release (not i including tritium, gases, alpha) Ci 6.25E-02 5.17E-02 25
2. Average diluted concentration during period pC1/mL 3.06E-08 2.81E-08
3. Percent of technical specification limit (T.S. 3.11.1.2.(a))  % 1.42E+00 1.48E+00 B. Tritium
1. Total release Ci 3.82E+00 6.62E+00 25
2. Average diluted concentration during period pCi/mL 1.87E-06 3.60E-06
3. Percent of technical specification limit (T.S. 3.11.1.1)  % 6.23E-02 1.20E-01 C.-Dissolved and entrained noble gases

-1. Total release Ci 3.48E 3.45E-03 25

2. Average diluted concentration during period pCi/mL 1.70E-09 1.88E-09
3. Percent of technical specification limit

-(T.S. 3.11.1.1)  % 8.50E-04 9.40E-04 D.-Gross alpha activity

1. Total 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 period liters 2.04E+09 1.84E+09 15

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HOPE CREEK GENERATING STATION j TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER-1991 LIQUID EFFLUENTS l l

CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Niobium-95 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 9.80Z-03 Iron-55 Ci 0.00E+00 0.00E+00 3.21E-02 0. 00 E+ 09 Iron-59 Ci 0.00E+00 0.00E+00 8.98E-04 1. 04 E-fs3 Cobalt-58 Ci 0.00E+00 0.00E+00 1.43E-04 2.06E-04 Cobalt-60 Ci 0.00E+00 0.00E+00 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 0.00E+00 0.00E+00 2.61E-05 1.36E-04 Mercury-203 Ci 0.00E+00 0.00E+00 2.72E-06 0.00E+00

-Cesium-137 Ci 0.00E+00 0.00E+00 0.00E+00 1.08E-05 TOTALS Ci 0.00E+00 0.00E+00 6.25E 5.17E-02

. Tritium- Ci 0.00E+00 0.00E+00 3.82E+00 6.62E+00 Xenon-133 Ci 0.00E+00 0.00E+00 7.36E-04 5.02E-04 Xenon-135 Ci 0.00E+00 0.00E+00 2.74E-03 2.95E-03 TOTALS Ci 0.00E+00 0.00E+00 3.82E+00 6.62E+00 Note: Composite sample results for Iron-55 in the 4th quarter were not.available in sufficient time to be included in this report.'Results will be transmitted in an amendment with the

.next report.

16

HOPE CREEK GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 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 6.58E+01 sludges, evaporator bottoms Ci 2.32E+03 25
b. Dry compressible waste, m3 2.31E+01 contaminated equipment. C1 2.82E+00 25
c. Irradiated components, m3 3.25E+00 control rods Ci 3.84E+04 25
d. Others (described) m3 1.51E+01 Oil Ci 2.95E-06 25
2. Estimate of major nuclide composition (for Type A and B waste)

RESINS DAW OIL '

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

Chromium-51 0.0 0.00E+00 1.4 3.90E-02 0.0 0.00E+00 Iron-55 73.3 1.73E+03 17.9 5.04E-01 79.7 2.35E-06 Tritium (H-3) 0.0 0.00E+00 0.0 0.00E+00 3.7 1.09E-07 ,

Manganese-54 3.6 8.36E+01 2.0 5.63E-02 1.4 3.98E-08 Carbon-14 0.0 0.00E+00 0.0 0.00Et00 3.7 1.09E-07 Cobalt-60 2.5 5.81E+01 1.3 3.70E-02 2.1 6.20E-08 Nickel-63 0.0 0.00E+00 0.0 0.00E+00 0.0 0.00E+00 Zinc-65 20.4 4.74E+02 76.8 2.16E+00 8.3 2.45E-07

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

Irradiated Hardware

(%) (Ci)

Iron-55 58.3 2.24E+04 Cobalt-60 36.8 1.41E+04 Manganese-54 3.3 1.27E+03 Nickel-63 1.7 6.52E+02 (1) Volumes are measured, activities are estimated 17

5 .

HOPE CREEK GENERATING STATION TABLE 3 (CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 SOLID-WASTE AND IRRADIA'2ED FUEL SHIPMENTS

3. Solid Waste Disposition Number of Mode of Type of

-shipments Transportation Destination Containers 29 Truck Barnwell, SC llIC and 17E drums 4 Truck Oak Ridge, TN Strong, tight containers 2 Truck Oak Ridge, TN 17E drums IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Mode of

' Shipments Transportation Destination None N/A N/A i

l l

l 18

--- , ,.m,, , - _ . - _ . , , _ , , _ , . . _ . , , _ , . , _ _ . . . . _ , .

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Ir

._ n

^

HOPE CREEK GENERATING STATION TABLE 4A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991

SUMMARY

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

1. Dates: July 1 - September 30, 1991 2.. Type of release: Gas
3. Number of releases during the 3rd Quarter: 0
4. Total time duration-for all releases of type listed above:

0.00E+00 min

5. Maximum duration for release of type listed above:

0.00E+00 min

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

0.00E+00 min-

7. Minimum duration for release of type listed above:

0.00E+00 min

- 8.- Average stream flow (dilution flow) during the period of release:_ N/A 1-l l.

19

-t HOPE CREEK GENERATING STATION-TABLE 4A (CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991

SUMMARY

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

- 1. - Dates: October 1 - December 31, 1991 2.- Type of release: Gas

3. Number of releases during the 4th Quarter: 0
4. Total time duration for all releases of type listed above:

0.00E+00 min

5. Maximum duration for release of type listed above:

0.00E+00 min

6. Average duration for release of type listed above:

0.00E+00 min

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

0.00E+00 min

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

l:

l t

{:

L:

20 f

, s- - ~,.4, . . W .~ , , w

llOPE CREEK GENERATING STATION TABLE 4B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991

SUMMARY

SilEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCli MODE BATCli RELEASES ONLY

1. Dates: July 1 - September 30, 1991
2. Type of release: Liquid _

3- Number of releases during the 3rd Quarter: 79

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

1.56E+04 min

5. Maximum duration for release of type listed above:

7.59E+02 min

6. Average duration for release of type listed above:

1.98E+02 min

7. Minimum duration for release of type listed above:

3.6E+01 min

8. Average stream flow (dilution flow) during the period of release: 34378 gpm 21

l

.. 1 i

l llOPE CREEK GENERATING STATION TABLE 4B (CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 l

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCll MODE l

BATCH RELEASES ONLY

1. Dates: October 1 - December 31, 1991
2. Type of release: Liquid 4
3. Number of releases during the 4th Quarter: 98
4. Total time duration for all releases of type listed above:

1.74E+04 min.

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

4.b9E+02 min

6. Average duration for release of type listed above:

1.78E+02 min

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

2.9E+01 min +

8. Average stream flow-(dilution flow) during the period of release:~27966 gpm 22

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AMMENDEllT TO RERR - 10

I! OPE CREEE GEllERATIllG STATIoll TABLE 1A ErrLUEllT AllD WASTE DISPOSAL SEMIA!111UAL REPORT JULY - DECEMBER 1990 GASEOUS EITLUEllTS-SUMMATIOli Or ALL RELEASES Est.

3rd 4th Total Unitu Quarter Quarter Error %

A. Fission and Activation Gases

1. Total release Cl 6.91E401 6.87E+02 25
2. Average release rate for period pCi/sec 8.69E+00 8. 6 4 E4 01
3. Percent of technical {

specification limit (T.S. 3.11.2.2(a))  % 9.43E-01 7.53E+00 B. Iodines

1. Total iodine- 131,133 Ci 0.00E+00 1.35E-03 25
2. Average release rate for period pCi/sec 0.00E+00 1.70E-04
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))  % 1.66E-05 1.60E-01 C. Particulates

1. Particulates with half-lives >8 days Ci 3.83E-07 8.74E-05 25
2. Average release rate for period pCi/sec 4.82E-08 1.10E-05
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))  % 1.66E-05 1.60E-01

4. Gross alpha Ci 0.00E+00 0.00E+00 D. Tritium
1. Total Eclease Ci 3.16E+01 4.20E+01 25
2. Average release rate for period pCi/sec 3.97E+00 5.28E+00
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))  % 1.66E-05 1.60E-01 (1) For batch releases the estimated overall error is within 10%

(2) Iodine, tritium and particulates are treated as a group 10

1 5

HOPE CREEK GE!1FRATI!1G STATIOli TABLE 2A EFFLUEllT A!10 WASTE DISPOSAL SFEIAlil10AL REPORT JULY - DECEMBER 1990 LIQUID EFFLUE!JTS-SUMMATIOli OF ALL RELEASES Est.

3rd 4th Total Units Quarter Quarter Error %

A. Fission and activation products -

1. Total release (not including tritium, gases, alpha) C1 2.75E-01 1.38E-02 25 ,
2. Average diluted concentration during period uci/mL 1.92E-06 3.91E-08 ,
3. Percent of technical specification limit (T.S. 3.11.1.2.(a))  % 5.16E+00 1.22E400 B. Tritium
1. Total release Ci 7.24E-01 3.39E+00 25
2. Average diluted concentration during period 4Ci/rL 5.06E-06 9.60E-06
3. Percent of technical repecification limit (T.S. 3.11.1.1)  % 1.69E-01 3.20E-01 C. Dissolved and entrained noble gases
1. Total release Ci 2.71E-04 2.44E-03 25
2. Average diluted concentration during period pCi/mL 1.90E-09 6.91E-09
3. Percent of technical specification limit (T.S. 3.11.1.1)  % 9.50E-04 3.46E-03 D. Gross alpha activity
1. Total release Ci 0.00E+00 0.00E+00 E. Volume of waste release (prior to dilution -

Batch Release) liters 6.05E+05 1.95E+06 P. Volume of dilution water used during entire period liters 1.43E+08 3.53E+08 13

e AMMEllDEliT TO RERR - 11

8.0 HODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEADE REPORTS Our last report (RERR-10) did not include Lne quarterly Sr-89, Sr-90 and re-55 composite data for the last half of 1990. Amended pages to RERR-10 are included at the end of this report.

Additionally, amended pages to RERR-9 are included. They were inadvertently omitted from RERR-10.

PART D. GADEOUD EFFLUENTH See Summary Tables IA through IC.

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

PART D. SOLID WABTE See Summary in Table 3.

PART E. RADIOLOGICAL IMPACT ON MAN The calcu'Tted individual doses in this section are based on actual ic :ations of nearby residents and f arms. The population dose impact is based on historical site specific data 1.e., food production, milk production, feed for milk animals and seafood production.

The doses were calculated using methods described in Regulatory Guide 1.109 and represent calculations for the six month reporting interval. Individual doses from batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as described in the Offsite Dose calculation Manus 1.

Population doses were calculated using the meteorological dispersion coefficients for the six month reporting interval.

Liquid Pathwav_a 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

l Total body dose to an individua?: 9.59E-02 mrem {

liighest organ dose: 2.62E-01 mrem to the Liver Doso to the 6 million individualu living within the 50 mile radius of the plant site:

Total population done: 1.38E400 person-rom Average population done: 2.31E-04 mrem / person bir PathEnya The calculated doses to individuals via the air pathway are shown below:

Total body dose: 1.15E-01 mrom Skin dose: 2.52E-01 mrom liighest organ dose due to radiciodines and particulates with half lives greater than 8 days:

4.01E-06 mrom to the Lung.

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

Total population dose: 1.97E-01 person-rom Average population dose: 3.30E-05 mrem / person Direct Radiation Direct radiation may be estimated by Thermoluminescent dosimetric (TLD) measurements. One method for comparing TLD measurements is by comparison with pre- g operational data. It should be noted that the TLDs measure direct radiation from both 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 3.6 mrad / month SS-1 0.9 mile 3.8 mrad / month 8

t IlOPE CREEE GEllERATI!4C STATIO!J TABLE 2A ErrLUE!1T AllD WASTE DISPOSAL SElil AliliUAL REPORT JAliUARY - JUllE 1991 LIQUID EFFLUE!JTS-SUMf4ATIOli or ALL RELEASES Est.

lot 2nd Total Units Quarter Quarter Error 1 A. Tission and activation producto

1. Total release (not including tritium, gases, a)pha) C1 2.80E-01 1.13E-01 25
2. Average diluted concentration during period pCi/mL 1.36E-07 5.30E-08
3. Percent of technical cpecification limit (T.S. 3.11.1.2.(a))  % 3.60E400 2.80E+00 B. Tritium
1. Total release C1 1.01E+01 3.97E400 25
2. Average diluted concentration during period pC1/mL 4.90E-06 1.89E-06
3. Percent of technical specification limit (T.S. 3.11.1.1)  % 1.63E-01 6.30E-02 C. Dissolved and entrained noble gases
1. Total release Ci 7.03E-04 2.60E-03 25
2. Average diluted concentration during period pCi/mL 3.410-10 1.24E-09
3. Percent of technical specification limit (T.S. 3.11.1.1)  % 1.71E-04 6.20E-04 D. Gross alpha activity
1. Total releano Ci 0.00E+00 0.00E+00 E. Volume of waste release (prior to dilution -

Batch Release) liters 4.60E+06 3.66E+06 F. Volume of dilution water used during entire period liters 2.06E+09 2.10E+09 15

l l

IlOPE CREEK GE!1 ERAT 1tiG STATIO!1 TABLE 2B EFFLUEliT AllD WASTE DISPOSAL SEMIAllt1UAL REPORT JAllUARY - JUllE 1991 LIQUID EFFLUEllTS CollTIllUOUS 140DE BATCil MODE ist 2nd 1st 2nd 11ucliden Released Unit Quarter Quarter Quarter Quarter Sodium-24 0.00E+00

~

C1 0.00E 00 2.05E-04 0.00E+00 Chromium-51 Ci 0.00E+00 0.00E+00 6.14E-04 1.95E-02 14anganese-54 C1 0.00E+00 0.00E+00 4.41E-03 1.50E-02 Iron-55 Ci 0.00E+00 0.00E+00 2.5BE-01 5.12E-02 Iron-59 Ci 0.00E+00 0.00E+00 8.42E-04 2.76E-03 Cobalt-58 Ci 0.00E+C0 0.00E+00 2.08E-05 5.16E-04 Cobalt-60 Ci 0.00E+00 0.00E+00 9.12E-04 3.09E-03 Zinc-65 Ci 0.00E+00 0.00E+00 1.47E-02 2.02E-02 Arconic-76 Ci 0.00E+00 0.00E+00 0.00E+00 8.39E-05 Yttrium-91m ci 0.00E+00 0.00E+00 0.00E+00 2.48E-05 Strontium-92 Ci 0.00E+00 0.00E+00 7.11E-06 1.57E-04 Technetium-99m Ci 0.00E+00 0.00E+00 0.00E+00 1.03E-05 Iodine-133 Ci 0.00E+00 0.00E+00 0.00E+00 7.91E-06 Cesium-137 Ci 0.00E+00 0.00E+00 0.00E+00 1.010-05 TOTALS Ci 0.00E+00 0.00E+00 2.80E-01 1.13E-01 Tritium Ci 0.00E+00 0.00E+00 1.01E+01 3.97E+00 _

Xenon-133 Ci 0.00E+00 0.00E+00 2.92E-04 4.92E-04 Xenon-135 Ci 0.00E+00 0.00E+00 4.11E-04 2.11E-04 TOTALS Ci 0.00E+00 0.00E+00 1.01E+01 3.97E+00 16

. . _ . . . . _ _ _

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