ML20082N316
| ML20082N316 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/30/1991 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N91138, NUDOCS 9109090107 | |
| Download: ML20082N316 (53) | |
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Pubhc Service Electne and Gas Company Stanley LaBruna Public Service Electnc and Gas Company P.O. Box 236 tiancocks Bodge, NJ 08038 609-339-4800 va rws aeno ha u aimen NLR-N91138 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 7
Gentlemen:
I RADIOACTIVE EFFLUENT RELEASE REPORT - 11 HOPE CREEK GENERATING STATION D 50 31=1 DOCKET NOS.
Og In accordance with Section 6.9.1.11 of Appendix A to the i
Operating License for Hope Creek Generating Station (HCGS),
Public Service Electric and Gas Company (PSE&G) hereby transmits one copy of the semi-annual Radioactive Effluent Release Report, RERR-11.
This report summarizes liquid and gaseous releases and solid waste shipments from the Hope Creek Generating Station for the period January 1 through June 30, 1991.
Should you have any questions regarding this transmittal, please feel free to contact us.
Sincerely,
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NLR-N91138 lugtR REPORT only C
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Dombek (1)
Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator (2)
Region 1 l
Hr. K. Tosch, Chief (1)
Office of Nuclear Reactor Regulation Washington, DC 20553 I
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!! OPE CREEK GEllERATIl1G STATIOli SEMIA!1!iUAL RADIOACTIVE EFFLUEllT RELEASE REPORT llCGS RERR-11 DOCKET 110. 50-354 OPERATIl1G LICEllSE 110. liFP-57 k
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e NOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1991 Table of contents INTRODUCTION.
1 PART A.
PRELIMINARY SUPPLEMENTAL INFORMATION.
2 1.0 REGULATORY LIMITS 2
1.1 Fission and Activation Gas Roloaco Limits.
2 1.2 Iodina, Particulates, and Tritium.
2 1.3 Liquid Effluents Rolosso Limits.
3 1.4 Total Dose Limit 3
2.0 MAXIMUM PERMISSIBLE CONCE!1TRATIONS (MPC) 3 3.0 AVERAGE ENERGY.
4 4.0 MEASUREMENTS *sND APPROXIMATION OF TOTAL RADIOACTIVITY 4
5.0 BATCil RELEASES 6
6.0 UNPLANNED RELEASES 6
7.0 ELEVATED RADIATION MONITOR RESPONSES 6
8.0 MODIFICATIO!1 TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS 7
PART D.
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 Doso.
9 Doso to Members of the Public on Sito 9
Assessment.
10 PART F.
METEOROLOGICAL DATA 11 PART G.
OFFSITE DOSE CALCULATION MANUAL (ODCM) JHANGES 11 PART H.
-INOPERABLE MONITORS 11 PART I.
ENVIRONMENTAL MONITORING LOCATION CHANGES 11
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s HOPE CREEK GEllERATI!1G STATIOli RADIOACTIVE EFFLUE!1T RELEASE REPORT JAHUARY - JUNE 1991 INTRODUCTION This report, HCGS-RERR-11, 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, 1991 to June 30, 1991.
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 MWo.
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 D.
As required by Regulatory Guide 1.21, our Technical Specification 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 Crook generated 2,877,886 megawatt-hours of electrical energy (not) during the reporting period.
Results of liquid and gaseous composites analyzed for Sr-09, Sr-90 and Fe-55 for the second 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.
The Sr-89, Sr-90 and Fe-55 analyses for the last half of 1990 (refer to RERR-10) have been completed; amended pages to RERR-10 are included in this report.
s PART A.
PRSLIMINARY SUPPLEMENTAL INFORMATION 1.0 RLGULATORY LIMITS 1.1 Fission and Activation Gas Holoase Limits The dose rato due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary, shall bo limited to the following:
For noble gasos:
Less than or equal to 500 mrems/yr to the total body and loss than or equal to 3000 mroms/yr to the skin.
In addition, the air dose duo to noble gases released in gaseous offluentn 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 years Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta rad.iation.
1.2 Iodine, Particulates, and Tritium The dose rato due to radioactive materials roloased in gaseous effluents from the sito to areas at and beyond the site boundary, shall be limited to the following:
For Iodino-131,I-133, for tritium, and for all" radionuclides in particulate form with half-lives greater than 8 days:
Ioss than or equal to 1500 mrems/yr to any organ.
In addition, the dose to a member of the public from iodino-131,133, from tritium, and from all radionuclides in particulate form with half-lives greator than 8 days in gaseous offluents released, from each reactor unit, from the site to areas at and beynnd the sito boundary, shall be limited to the following:
During any calendar quarter:
Less than or equal to 7.5 mroms to any organ and, During any calendar year:
Less than or equal to 15 mrems to any organ.
2
e 1.3 Liquid Effluents Holoauo Limits The concentration of radioactive material released in liquid offluents 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 por milliliter.
In addition, the done or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas chail be limited ** t 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 mroms to the total body, and less than or equal to 10 mroms to any organ.
1.4 Total Dose Limit The annual (calendar year) done or donc 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 mroms to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).
2.0 MAXIMUM PERMIDDIDLE CONCENTRATIONS (HPC)
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 l
noble gases is 2E-4 microcuries per milliliter.
3
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s 3.0 AVERAGE ENERGY Regulatory Guido 1.21 requires that the licensoo provido the average energy of the radionuclido mixturo in releanos of fission and activation gases, if applicablo.
Rolcaso limits for HCCS are not based upon average energy.
Thorofore this section is not applicable to HCGS.
4.0 MEASUREMENTS AND APPROXIRATION OF TOTAL RADIOACTIVITY 4.1 Liquid Effluents Liquid offluents are monitored in accordanco with Tablo 4.11.1.1.1-1 of the Technical Specifications.
During the period of record, all liquid wastes woro routed to the sampling tanks for monitoring prior to relonso.
Technical Specifications require those tanks to be uniformly mixed for sampling and analysis before being roloased.
Batch releases are defined as rolonsos from the equipment drain sample tanks, floor drain sample tanks, detergent drain tanks, and the condensato storage tank dike. Normally, there are no continuous liquid releases. Specific activities from analycos woro multiplied by the volume of offluent discharged to the environment in order to determine the total liquid activity discharged.
The detection requirements of Tabic 4.1.1.1-1 of the Technical Specifications are achieved or exceeded.
Radionuclidos measured at concentrations below the Technical Specification detection limit (LLDs) are treated as being present.
Radionuclidos for which no activity was detected while mooting the required LLDs are treated as absent.
4.2 Gaseous Effluents Gaseous offluent 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 vont (SPV) are the final releaso points for most planned gaseous effluent releases.
A small quantity of gaseous offluent will be released via the filtration, recirculation, and ventilation system (FRVS) vont during testing periods.
The NPV and SPV are continuously monitored for lodino, particulates and noble gasos; the FRVS is continuously monitored for noble gases. The NPV and SPV monitors havo moving particulato and fixed charcoal filters; the FRVS monitor has fixed particulato and charcoal filters.
4
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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 for which no activity was detected while mooting the required LLDs are treated as absent.
Continuous Mode gaseous releases are quantified by routine (monthly) sampling and isotopic analyses of the plant vents.
If noble gases are detected during the routino 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 noimal continuous release of radioactivity through the plant vent.
When monthly vent grab sao,nlos yield no detectable activity, continuous modo releases are quantified by integrating Radiation Monitor System readings.
Noble gas isotopic abundances for these integrations are based on the ANSI N237-1976/ANS-18.1 mix for BWRs.
Doses calculated from this data employ the methods from Section 2.0 and Appendix C of the Hope Creek ODCM.
Datch Mode gaseous releases (primary containment purgo) are quantified by pre-release samplina and isotopic analysis.
Specific activities for each isotope are multiplied by the total purgo 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, tnen 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 J
multiplied by the volume of effluent discharged while the channel was in an alarm state in order to estimate the total activity discharged.
5
e 4.3 Estimated Total Error The estimated total error of reported liquid releases is within 25%.
The estimated total error of the reported continuous gaseous releases is within 50% when concentrations exceed detectable icvels.
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 estinates for releases where sample activity is below the detectabic concentration levels are not included since error estimates at the LLD are not defined.
The f.stimated total error of reported solid releases is within 254.
5.0 BATCH RELEASED Summaries of batch releases of gaseous and liquid offluents are provided in Tables 4A and 48.
6.0 UNPLANNED RELEASES During this reporting period there were no unplanned releases.
7.0 ELEVATED RADIATION MONITOR RESPONDES 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, 6
8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTD Our last report (RERR-10) did not include the 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.
GASEOUS EFFLUENTS See Summary Tables lA 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 MAN The calculated indiviPaal 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 Ouide 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 inte rval.
l Liauid Pathways l
Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathway. Calculated doses to individuals are as shown i
below.
7
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Total body dose to an individual: 9.25E-02 mrom liighest organ dose: 2.47E-01 mrom to the Livor Dose to the 6 nillion individuals living within the 50 mile radius of the plant site:
Total population doso:
1.30E+00 person-rom Average populatior doso: 2.31E-04 mrom/ person Air Pathways The calcul.ated donos to individuals via the air pathway are shown below:
Total body doso: 1.15E-01 mrem Skin dose:
2.52E-01 mrom liighest organ dono due to radiciodines and particulates with half lives greator than 8 days:
1.01E-06 mrem to the Litng.
Doso 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 mrom/ person Direct Radiation Direct radiation may be estimated by Thc.rmoluminescent dosimetric (TLD) measurements.
One method for comparing TLD measurements is by comparison with pro-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 3.6 mrad / month SS-1 0.9 mile 3.8 mrad / month 8
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Those values aro inteproted 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.
Total Doso 40CFR190 limits the total dose to members of the public duo to radioactivity and radiation from uranium fuel cycle sources tot
<25 mrom total body or any organ
<75 mrom thyroid for a calendar year.
For Artificial Island, the major sources of dono aro-from liquid and gaseous affluents from the llopo Crook and Salem plants.
The following donos to a member of the public havo boon calculated for the six month reporting period. They are the sum of gaseous and liquid pathway donos for the Galom 1 and 2 and llopo Crook plants:
0.494 mrom total body 1.46 mrom organ (GI-LLI) 0.247 mrom thyroid D.pse to members of thc_public.due to activities inside__
the site boundaryx In accordance with the requirements of Technical Specification 6.9.1.7, the dose to members of the public insido the sito boundary has boon calculated based on the following assumptions:
- Such persons are lunch vendors, landscapers, deliverymen 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> por wook on site
- dono due to airborno pathway (inhalation) and noble gases
- persons aro located about 1/4 milo west of plant dischargo points (parking lots)
- occupancy coincidos with batch gaseous dischargeo For the six month reporting period, the calculated doses are:
3.0E-04 mrom total body 1.4E-07 mrom organ (Lung, particulato only) 9 l
= _..
Msessment During the report period, Hope Creek gaseous effluents returned to levels which are one of the lowest of United States BWRs, with an average release rate of 5.8 microcuries per second, characteristic of a plant with no fuel cladding defects. During the previous report period, (July-l: Sc 1990), gaseous effluentc were slightly elevated to an average release rate of 32 alcrocuries per second, due to a single fuel pin cladding defect. The defective fuel element was identified and replaced during the next refueling outage (Dec.1990 - Feb.1991).
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 repecies with large dose factors. Because of this assumed isotopic mix, caculated doses are probably conservative by a factor of 25, assuming that the actual discharge consisted of mostly xenon-133.
Ilope Creek liquid effluents are about the same as the i
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 gaseous and liquid of fluents and calculated doses from !! ope Crook since plant initial operation in 1986.
Hope Creek Gaseous Effluents Curies of Noble Gases Released and Calculated Doses 1.00E+03<
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Hope Creek Liquid Effluents curies Heleased and Calculated Doses 1.4
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./N,7 1986 1987 1987 1988 1988 1989 1989 1MO IND 1991 2rd 1st 2nd 1st 2rd 1st 2nd ist 2rd 1st fear 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 1991 in Tables 5 and 6.
FART G.
OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES During this perlod, there were no changes to the HCGS Off-site Dose Calculation Manual.
PART H.
INOPERABLE MONIIORS Durisig 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 one change to the environmental monitoring sampling locations.
Sampling station 14F1, a local farm 5.5 miles WNW has been replaced by station 14F4, a local farm 7.8 miles
'JNW. This farm provides milk and vegatable samples.
The HCGS ODCM will be changed during the next reporting period.
11
l HOPE CREEK GENERATING STATION TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1991 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est.
1st 2nd Total Units Quarter Quarter Error %
A.
Fission and Activation Gases
- 1. Total release C1 1.58E+01 2.84E+01 25
- 2. Average release rate for period pCi/sec 2.01E+00 3.61E+00 3.
Percent of technical specification limit (T.S. 3.11.2.2(a))
2.16E-01 3.88E-01 B.
- 1. Total lodine-133,133 Ci 0.00E+00 0.00E+00 25
- 2. Average release rate for period _ _
pC1/sec 0.00E400 0.00E+00 3.
Percent of technical specification limit (2)
(T.S. 3.11.2.3(a))
8.97E-06 9.46E-07 C.
Particulates 1.
Particulates with half-lives >8 days Ci 5.30E-05 0.00E+00 25 2.
Average release rate for period pCi/sec 6.81E-06 0.00E+00 3.
Percent of technical specification limit (2)
(T.S. 3.11.3.3(a))
8.97E-06 9.46E-07 l
4.
Gross alpha Ci 0.00E+00 0.00E+00 1
D. Tritium
- 1. Total Release Ci 1.03E+01 3.72E+00 25
- 2. Average release rate for period pCi/sec 1.31E+00 4.74E-01 3.
Percent of technical specification limit (2)
(T.S. 3.11.2.3(a))
8.97E-06 9.46E-07 (1) For batch releases the estimated overall error is within 10%
(2) Iodine, tritium and particulates are treated as a group 12
______ _.. _ _ _ _.-__.._ _ _. _ ___ _... _. -.. _ _.__ _.__-. __ _ _ _ m llOPE CREEK GENERATI/4G STATION TABI,E ID EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1991 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-C1 1.58E-01 3.84E-01 0.00E+00 0.00E+00 Krypton-85m Ci 1.58E-01 2.84E-01 0.00E+00 ' O.00E+00 Krypton-87.
Ci 6.32E-01 1.14E+00 0.00E+00 0.00E+00 Krypton-88 Ci 6.32E-01 1.14E+00 0.00E+00 0.00E+00 Krypton-89 Ci 4.27E+00 7.67E+00 0.00E+00 0.00E+00 Xenon-133 C1 3.16E-01 5.68E-01 0.00E+00 0.00E+00 Xenon-135 Ci 7.90E-01 1.42E+00 0.00E+00 0.00E400
'X non 135m Ci 9.48E-01 1.70E+00 0.00E+00 0.00E+00 e
Xenon-137 Ci 4.90E+00 8.80E+00 0.00E+00 0.00E+00 Xenon-138 Ci 3.00E+00 5.40E+00 0.00E+00 0.00E+00 TOTALS Ci 1.58E+01 2.84E+01 0.00E+00 0.00E+00 2.
Iodines Iodine-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.
Particulates (half-live >8 days Manganese-54 Ci 5.30E-05 0.00E+00 0.00E+00 0.00E+00 TOTALS Ci 5.30E-05 0.00E+00 0.00E+00 0.00E+00 l
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e llOPE CREEK GENERATI!1G STATION TABLE 2C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1991 GASEOUS EFFLUENTS-ELEVATED RELEASES 1
There voro no elevated gaseous relonnes during this reporting period.
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HOPE CREEK GENERATING STATION TABLE 2A 1
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1991 1
i LIQUID ErrLUENTS-SUMMATION OF ALL RELEASES Est.
1st 2nd Total Units Quarter Quarter Error %
A. Pission and activation products
- 1. Total release (not including tritium, gases, alpha)
C1 2.80E-01 6.14E-02 25
- 2. Average diluted concentration during period pCi/mL 1.36E-07 2.94E-08 3.
Percent of technical specification limit (T.S. 3.11.1.2.(a))
3.60E400 2.57E+00 D. Tritium
- 1. Total relonsa C1 1.01E+00 3.97E+00 25
- 2. Average diluted concentration during period
- Ci/mL 4.90E-06 1.89E-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 7.03E-04 2.60E-03 25
- 2. Average diluted concentration during period
- C1/mL 3.41E-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 rel(tase 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 1
IlOPE CREEK GENERATING STATION TABL2 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNP, 1991 LIQUID EFFLUENTS CONTINUOUS MODE BATCil MODE lot 2nd lut 2nd i
Nuclidos Released Unit Quarter Quarter Quarter Quarter Sodium-24 Ci 0.00E+00 0.00E+00 2.05E-04 0.00E400 Chromium-51 Ci 0.00E+00 0.00E+00 6.14E-04 1.95E-02 Mangancoo-54 Ci 0.00E+00 0.00E+00 4.41E-03 1.50E-02 1
-Iron-55 Ci 0.00E+00 0.00E+00 2.58E-01 0.00E+00 Iron-59 Ci 0.00E+00 0.00E+00 8.42E-04 2.76E-03 Cobalt-58 Ci 0.00E+00 0.00E+00 2.08E-05 5.16E-04 Cobalt-60 Ci 0.00E+00 0.00E+00 9.32E-04 3.09E-03 Zinc-65 Ci 0.00E+00 0.00E+00 1.47E-02 2.02E-02 Arsenic-76 C1 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 Cl 0.00E+00
- 0. 00E4 00 7.11E-06 1.57E-04 Technetium-99m Ci 0.00E+00 0.00E+00 0.00E+00 1.03E-05 Iodino-133 Ci 0.00E+00 0.00E+00 0.00E400 7.91E-06 Cosium-137 Ci 0.00E+00 0.00E+00 0.00E+00 1.01E-05 1
TOTALS Ci 0.00E+00 0.00E+00 2.80E-01 6.14E-02 Tritium Ci 0.00E+00 0.00E400 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 t
I
(
16 j
, -. - _ _ _ _,... _.. ~,,, _ _....,
.._..._._._.__m_
HOPE CREEK GENERATING STATION TABLE 3 4
i ETFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 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, %
l a.
Spent resino, filters, m3 7.91E+01 sludges, evaporator bottoms C1 2.34E+03
'25 i
j b.
Dry compressible waste, m3 2.67E+01 contaminated equipment.
Ci 5.13E+00 25 c.
Irradiated components, m3 0.00E+00 j
control rods Ci 0.00E+00 25 I
d.
Others (described) m3 3.26E+01 l
Oil C1 1.00E-03 25 t
i 2.
Estimate of major nucijde composition (for Type A and B waste)
RESINS DAW OIL i
(%)
(Ci)
(%)
(C1)
(%)
(Ci) i Chromium-51 1.4 3.27E+01 1.4 7.16E-02 0.0 0.00E+00
)
Iron-55 17.9 4.18E+02 17.9 9.19E-01 79.7 7.97E-04 Iron-59 0.1 3.27E+00 0.1 7.16E-03 1.4 1.35E-05 Manganese-54 2.0 4.67E+01 2.0 1.03E-01 0.0 0.00E+00 Cobalt-58 0.1 3.50E+00 0.1 5.13E-03 0.0 0.00E+00 Cobalt-60 1.3 3.04E+01 1.3 6.65E-02 2.1 2.10E-05 Nickel-63 0.1 2.34E+00 0.1 5.13E-02 0.3 2.60E-06 Zinc-65 76.8 1.79E+03 76.8 1.94E+00 8.3 8.30E-05 Technecium-99 0.0 0.00E+00 0.0 0.00E+00-0.3 3.00E-06 Silver-110m 0.1 2.34E+00 0.1 5.13E-03 0.0 0.00E+00 Iodine-329' O.0 0.00E+00 0.0 0.00E+00 0.3 3.00E-06 Cesium-137 0.0 0.00E+00 0.0 0.00E+00 0.1 1.00E-06 Cerium-144 0.0 0.00E+00 0.0 0.00E+00 0.2 2.00E-06 (1)
Volumes are measured, activities are estimated 17 y-eyt--
N-1p-r9-mm am grw e-weuiv+,-
-verm'-ww
-em v-*=:r y e-r m
-r+rTrme-
-nwN'
IlOPE c'.'. hen GENERATIl1G STATION TABLE 3 (CONT'D)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1991 SOLID WASTE AND IRRADIATED FUEL SilIPMENTS 3.
Solid Wasto Disposition Number of Modo of Type of Shipments Transportation Destination Containers 25 Truck Barnwell, SC 11IC and 17C drums 10 Truck Oak Ridge, TN Strong, ticht containers 2
Truck oak Ridge, TN 17C drums IRRADIATED FUEL SilIPMENTS (Disposition)
Number of Mode of Shipments Transportation Destination none N/A N/A h
6 lb l
f l
l llOPE CREEK GEllERATIliG STATIOli TABLE 4A EFPLUENT AllD WASTE DISPOSAL SEMI AllNUAL REPORT t
JANUARY - JUNE 1991 i
SUMMARY
SilEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCil MODE i
BATCil RELEASES ONLY 1.
Dates:
January 1 - March 31, 1991 I
2.
Typo of reloano:
Gas 3.
Number of roloncos during the lot Quarter: 1 4.
Total timo duration for all releason of typu listed abovo
{
168 hourn 5.
Maximum duration for rolonne of typo listed abovo:
168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> i
6.
Averago duration for releano of type listed abovo 368 hours0.00426 days <br />0.102 hours <br />6.084656e-4 weeks <br />1.40024e-4 months <br /> f
7.
Mir_imum duration for rolcase of typo listed above
.f 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> l
t 8.
Avorage stream flow (dilution flow) during the period of i
t relonno:
N/A
- i i
I P
I 19 i
i
_. _.. ~ _. _. _. _,. _.. _...
.. ~,. _. _..
I l
o llOPE CREEK GENERATING STATION TABLE 4A (CONT'D)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1991
SUMMARY
SilEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCil MODE
- r. Cil RELEASES ONLY 1.
Dates:
April 1 - June 30, 1991 2.
Type of release:
Gas 3.
Number of releases during the 2nd Quarter: 1 4.
Total time duration for all releases of type liFded above:
180.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> 5.
Maximum duration for release of type listed above:
180.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> 6.
Average durt '.on for release of type listed above:
180.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> 7.
Minimum duration for release of type listed above:
180.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> 8.
Average stream flow (dilution flow) during the period of release:
N/A 20 i
..~.. _. _ _ _. _ _ _.
i
'l HOPE CREEK GENERATING STATION TABLE 4D EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY ~ JUNE 1991
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS.RFLEASED IN A DATCH MODE l
l BATCH RELEASES ONLY 1.
Dates:
January 1 - March 31, 1991 2.
Type of release:
Liquid 3.
Number of releases during the 1st-Quarter: 100 4.
Total time duration for all releases of type listed above:
396 hour0.00458 days <br />0.11 hours <br />6.547619e-4 weeks <br />1.50678e-4 months <br />s-5.
Maximum duration for release of type-listed above:
12.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 6.
Average duration for release of type listed above:
3.96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 7.
Minimum duration for release of type listed above:
0.48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 8.
Average stream flow (dilution flow) during the period of release: 22913 gpm l
l 21 r
r y
.w
,-._,._-..,__-,,,..,m...m.,y my.
.,,., - - -, - - - ~ _ _.
llOPE CREEK GENERATING STATION TABLE 4B (CONT'D)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1991
SUMMARY
SIIEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCl! RELEASES ONLY 1.
Dates:
April 1 - June 30, 1991 2.
Type of release:-
Liquid 3.
Number of releases during the 2nd Quarter: 83 4.
Total timo duration for all releases of type listed above:
328 hours0.0038 days <br />0.0911 hours <br />5.42328e-4 weeks <br />1.24804e-4 months <br /> 5.
Maximum duration for release of type listed above:
14.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 6.
Average duration for release of type listed above:
3.95 hours0.0011 days <br />0.0264 hours <br />1.570767e-4 weeks <br />3.61475e-5 months <br /> 7.
Minimum duration for release of type listed above:
1.08 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 8.
Average stream flow (dilution flow) during the period of release: 28210 gpm 22
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l ARTIFICIAL ISLAND 1/91-3/91 J0!NT DISTRIBUTION OF WIND DIRECTION AND SPEED Bf ATMOSPHERIC STABILITY CLASS WIND: 300 FT LAPSE RATE: -1.4 TO -0.5 DEG C/1004 i
l CLASS 0 DELTA T: (300-33FT) l WIK3 SPEED GROJPS (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 GE 24.6 S m PERCERT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT StM PFRCENT itM PERCEh!
SUM PERCENT SIM PERCENT N
O 0.0 3
0.1 6
0.3 12 0.6 26 1.2 2
0.1 1
0.0 50 2.4 NNE O
0.0 2
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0.0 0
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0.0 0
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D 0.0 0
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0.4 44 2.1 WNV 0
0.0 0
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0.0 1
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16 0.8 14 0.7 81 3.9 NwW 0
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0.0 17 0.8 72 3.4 137 6.5 227 10.8 108 5.2 72 3.4 633 30.2 MEAN WIND SPEED: 15.1 MIS $1NG:
17 Table 5 Page 4 of 9
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~
ARilFICIAL ISLA C 1/91-3/91 Jolti DISTRIBUTION OF Wim DIRECT 104 AC SPEED BY ATMCSPkERIC STABILITT CLASS Wic: 300 ti DELTA T: (3CD-33FT)
Att ST ABILITY CLASSES l
ut e SPEED CR WPS (MpM) 0.0-0.5 0.6-3.5
'3.6-7.5
/.6 12.5 12.6-18.5 18.6-24.5
74.6 Suse FERami DIRECTION SUN PERCEh!
SLM PEECENT SLM PERCENT SUM PERCEnf SLM PERCENT SUN PERCEst SLM PER G47 m
0 0.0 6
0.3 19 0.9 35 1.7 63 3.0 5
0.2 1
0.0 129 6.2 kkE O
0.0 3
3.1 17 0.8 35 1.7 35 1.7 13 0.6 0
0.0 103 4.9 kE O
0.0 6
3.3 5
0.2 27 1.3 31 1.5 16 0.8 0
0.0 85 4.1 EWE O
0.0 4
0.2 13 0.6 17 0.8 16 0.8 5
0.2 0
s.0 55 2.6 E
O 0.0 7
0.3 14 0.7 24 1.1 28 1.3 3
0.1 0
0.0 76 3.6 ESE O
0.0 2
0.1 14 0.7 17 0.8 12 0.6 4
0.2 2
0.1 51 2.4 SE O
0.0 4
0.2 12 0.6 20 1.0 42 2.0 12 0.6 15 0.7 1 05 5.0 SSE O
0.0 4
0.2 11 0.5 25 1.2 41 2.0 29 1.4 24 1.1 134 6.4 5
0 0.0 5
0.2 14 0.7 26 1.2 48 2.3 17 0.5 2
0.1 112 5.3 S$V 0
0.0 5
0.2 17 0.8 40 1.9 51 2.4 33 1.6 5
0.2 151 7.2 SW 0
0.0 1
0.0 16 0.8 36 1.7 51 2.4 14 0.7 12 0.6 130 6.2 WSV 0
0.0 3
0.1 12 0.6 25 1.2 36 1.7 26 1.2 8
0.4 T13 5.3 u
o 0.0 5
0.2 16 0.8 16 0.8 45 2.1 39 1.9 13 0.6 134 6.4 ww 0
0.0 2
0.1 18 0.9 42 2.0 65 3.1 38 1.8 44 2.1 209 50.0 W
0 0.0 6
0.3 16 0.8 49 2.3 127 6.1 52 2.5 30 1.4 280 13.4 ww 0
0.0 2
0.1 20 1.0 51 2.4 90 4.3 46 2.2 22 1.1 231 11.0 0
0.0 65 3.1 234 11.2 485 23.2 781 37.3 352 16.8 178 8.5 2095 100.0 mlSSING fC AS:
65 MEAW WINO STEED:
14.7 Table 5 Pace P of 9
m ARTIFICIAL ISLANO 1/91-3/91 JOINT OISTRIBUTION CF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT DELTA T: (300-33FT)
DIRECTION VS SPEED ONLT l
WIND $9EED GROUPS (MPM) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 Supt PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SEM FERCFMT W
0 0.0 6
0.3 19 0.9 35 1.7 63 3.0 5
0.2 1
0.0 129 6.Z kNE O
0.0 3
0.1 17 0.8 35 1.7 35 1.7 13 0.6 0
0.0 103 4.7 kE O
0.0 6
0.3 5
0.2 27 1.3 31 1.5 16 0.8 0
0.0 85 4.1 ENE O
0.0 4
0.2 13 0.6 17 0.8 16 0.8 5
0.2 0
0.0 55 2.6 E
O 0.0 7
0.3 14 0.7 24 1.1 28 1.3 3
0.1 0
0.0 76 3.6 ESE O
0.0 2
0.1 14 0.7 17 0.8 12 0.6 4
0.2 2
0.1 51 2.4 SE O
0.0 4
0.2 12 0.6 20 1.0 42 2.0 12 0.6 15 0.7 105 5.0 SSE O
0.0 4
0.2 11 0.5 25 1.2 41 2.0 29 1.4 24 1.1 134 6.4 S
0 0.0 5
0.2 14 0.7 26 1.2 48 2.3 17 0.8 2
0.1 IT2 5.3 S$V O
0.0 5
0.2 17 0.8 40 1.9 51 2.4 33 1.6 5
3.2 151 7.2 SV O
0.0 1
0.0 16 0.8 36 1.7 51 2.4 14 0.7 12 0.6 130 6.2 WSu o
0.0 3
0.1 12 0.6 25 1.2 36 1.7 26 1.2 8
0.4 110 5.2 u
o 0.0 5
0.2 16 0.8 16 0.8 45 2.1 39 1.9 13 0.6 134 6.4 ww 0
0.0 0
0.1 18 0.9 42 2.0 65 3.1 38 1.8 44 2.1 209 10.0 wu o
0.0 6
0.3 16 0.8 49 2.3 127 6.1 52 2.5 30 1.4 280 13.4 mwu O
0.0 2
0.1 20 1.0 52 2.5 90 4.3 46 2.2 22 1.0 232 11.1 0
0.0 65 3.1 234 11.2 486 23.2 781 37.3 352 16.8 178 8.5 2006 100.0 MISSING HOURS:
64 MEAN Wind SPEED:
14.7 Table 5 Page 9 of 9
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>=
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w O O O O O O O OO O O O O O O O e
u M
m
+
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e w O O M N N N 4* N N mO N O O
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. O in.
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w O O N mm4 E0 *=
4 M. in N @
3 m
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e e
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a en W
- N O ** *= ** '= N *= N @ M 4 NN *=
Pm e=
M U
M J
4 m
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W 4
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mM 4 *= *= M g g en &
N e=
g-4 4 N
N M IA M @ M a
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a
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=
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to N. 4 4 O EO M @ M N.
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in.
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O to w
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O O= O U
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4
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O O O O O O O O O O O O O O O O O
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b W
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W O O O O O O O O O O O O O O O O
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40 0 O O *= 0 O O 4 *= m 41 N *= 0 4 O
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- =
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4 M.
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N N.
@ >=.
N. N.
r.
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m at 3
4 0
W 9
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W >= @ O O O *= N mm@ M 4 4 mN O
m <
- =
N *= *=
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M. N.
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N. e.==. N. @ *=. *=. *=. N.
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3
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C O O O O O O O O O O O O O O O M
O *= W m
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at W
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d6 3
u.*..
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(
N eO *= N *= *= mO N m ed N M M 4 m
h ".h "<-
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=
3 m
W O O O O O O O O O O O O O O O O N
2 p k.
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M N N *= M N'N M ** *= EO 4 M N O O 4 M
4
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as O.
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at m.
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W M
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4 o
E E I
l
ARTIFICIAL ISLAND 4/91-6/91 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT DELTA T: (300-33FT)
ALL S'ASILITY CLASSES WIND SPEED CROUPS (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 DIRECTION SUM PERCENT SLM PERCENT SLM PERENT SLM PERCENT Stm PERCENT SLM PERENT SUM FERCENT N
0 0.0 1
0.0 21 1.0 47 2.2 41 1.9 20 0.9 1
0.0 131 6.0 kNE O
0.0 3
0.1 24 1.1 35 1.6 26 1.2 16 C.7 0
0.0 104 4.8 NE O
0.0 1
0.0 14 0.6 27 1.2 45 2.1 11 0.5 0
0.0 98 4.5 ENE O
0.0 3
0.1 16 0.7 32 1.5 33 1.5 12 0.5 0
0.0 96 4.4 E
O 9.0 3
0.1 19 0.9 47 2.2 10 0.5 1
0.0 0
0.0 80 3.7 ESE O
0.0 6
0.3 11 0.5 39 1.8 17 0.8 0
0.0 0
0.0 73 3.4 SE O
0.0 3
0.1 20 0.9 22 1.0 26 1.2 5
0.2 8
0.4 84 3.9 SSE O
0.0 3
0.1 21 1.0 34 1.6 45 2.1 36 1.7 14 0.6 153 7.1 S
0 0.0 8
0.4 2G 0.9 45 2.1 36 1.7 5
0.2 '
O 0.0 114 5.3 SSW 0
0.0 3
0.1 33 1.5 37 1.7 48 2.2 19 0.9 0
0.0 140 6.5 SV 0
0.0 4
0.2 35 1.6 64
' 3.0 118 5.4 33 1.5 0
0.0 254 11.7 l
l WSU 0
0.0 3
0.1 32 1.5 57 2.6 69 3.2 19 0.9 0
0.0 180 8.3 l
W 0
0.0 7
0.3 46 2.1 71 3.3 108 5.0 22 1.0 4
0.2 258 11.9 WNW 0
0.0 2
0.1 27 1.2 41 1.9 34 1.6 12 0.6 10 0.5 127 5.9 W
D 0.0 3
0.1 26 1.2 33 1.5 63 2.9 22 1.0 3
0.1 150 6.9 NNW 0
0.0 2
0.1 24 1.1 42 1.9 32 1.5 21 1.0 3
0.1 124 5.7 C
0.0 55 2.5 389 16.0 674 31.1 751 34.7 254 11.7 43 2.0 2166 If,0.0 MISSINO MctRS:
18 MEAN WIND SPEED:
12.5 Table 6 Page H of 9 l
h
}'.
AtilflCIAL ISLAND 4/91-6/91
, JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMDSPMERIC STABILITY CLASS WIND: 300 FT DELTA T: (300-33FT)
DIRECTION VS SPEED ONLY-i WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5-12.6-18.5 18.6-24.5 GE 24.6
$UN PERCENT DIRECTION SUM PERCENT SIAt PERCENT SLM PERCENT SLAI PERCENT SIAI PERENT SLM PERCENT SUN PERCENT I
i H
0 0.0 1
0.0 21 1.0 47 2.2 41-1.9 20 0.9 -
1 0.0 131 6.0 l
NME O
0.0 3
0.1 24 1.1 35 1.6 26 1.2.
16 0.7 0'
O.0 104 4.8 NE O
0.0 1
0.0 14 0.6 27 1.2 45 2.1 11 0.5 0
0.0 98 4.5 ENE O
0.0 3
0.1 16 0.7 32 1.5 33 1.5 12 0.5 0
0.0 76 4.4 E
O 0.0 3
0.1 19 0.9 47 2.2 to 0.5 1
0.0 0
0.0 80 3.7-ESE O
0.0
-6 0.3 11 0.5 39 1.8
-17 0.8 0
0.0 0
0.0 73 3.3 SE D
0.0 3
0.1 20 0.9 22 1.0 26 1.2 5
0.2 8
0.4 84 3.8 SSE O
0.0 3
0.1 21 1.0 34 1.6 46 2.1
' 36 1.6 14 0.6
.154 7.1 5
0 0.0 8
0.4 20 0.9 45 2.1 36 1.6 5
0.2 0
0.0 114-
' 5.2 SSW 0
0.0 3
0.1 33 1.5 37 1.7 48 2.2 19 0.9 0
0.0
'140 6.4 -
SW 0
0.0 4
0.2 35 1.6 66 3.0 119 5.4 33 1.5 0
0.0 257 11.8 WSW 0
0.0 3
0.1 33 1.5 58
'2.7 70 3.2 19 0.9 0
0.0 183 8.4 V
0 0.0 7
0.3 50 2.3 74
' 3.4 110 5.0 22 1.0 4
0.2 267 12.2 WWW 0
0.0 2
0.1 27 1.2 43 2.0 34 1.e 12 0.5 10 0.5 128 5.9 WW 0
0.0 3
0.1 26 1.2 33 1.5 63 2.9 22 1.0 3
0.1 150 6.9 NNW 0
0.0 2
0.1 25 1.1 42 1.9 32 1.5 21 1.0 3
0.1 125' 5.7 l
s 0
0.0 55 2.5 395 18.1 681 31.2 756 34.6 254 11.6 43 2.0 2184 100.0.
MISSING NOURS:
0-MEAN WIND SPEED:
12.5 Table 6 Page 9 of 9
a
,4
.m.
8,,
3+5 9
AMENDMENT TO RERR 10 i
+
4 i
i 23 d
I b
e 6
e.
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.
Liquid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathway.
The total body dose to an individual was calculated to be 6.05E-02 mrem.
The calculated highest organ dose from liquid releases was 1.76E-01 mrem to the liver.
The calculated population total body dose was 9.70E-01 person-rem.
The calculated average total body dose to the population within fifty miles of the site was 1.62E-04 mrem / person.
Air Pathways The resulting total body and skin doses to an
-individual were calculated to be 1.63E+00 mrem and 3.03E+00 mrem respectively.
The calculated highest organ dose due to radiciodines and particulates with at greater than eight day half-life was 1.20E-02 mrem to the thyroid. The calculated population total body dose was 2.58E+00 person-rem.
The calculated average total body d-dose to the population within fifty miles of the f
site was 4.83E-04 mrem / person.
l Direct Radiation 4
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.
8
4 TLDs at onsite locations 2S-2 and SS-1,_which are 0.3 miles and 0.9 miles from the point of origin, averaged 4.9 and 4.2 mrad / month respectively.
The values for stations 2S-2 and SS-1 are within the statistical variation associated with the pre-operational-program results.
The pre-operational values for these locations are 3.7 mrad / month at 2S-2'and 4.2 mrad / month at SS-1.
Assessment Liquid effluents during the reporting period were substantially lower than previous periods ( 0.367 Curie versus 1.12 Curies for Jan.-June 1990)
Calculated doses from liquid effluents are principally due to isotopes of iron and zinc.
Gaseous effluents during the reporting period were higher than other. reporting periods due to the unplanned release described in Part A, Section 6 of this report, and a fuel cladding defect identified during the end-of-cycle refueling. The steady state release rate was 8.8 microcuries per second, for the third quarter of 1990, compared to 32 microcuries per second for the fourth quarter. These release rates are characteristic of a BWR with no fuel cladding defects, and-with a single fuel pin cladding defect, respectively. Including the unplanned release, about 70 percent of the 759 Curien of fission gases released during the reporting period are estimated to be due to the 3dentified fuel cladding defect.
9
I HOPE CREEK GENERATING STATION TABLE.2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1990 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 3rd 4th Est. Total Units Quarter Quarter Error % (1)
A.
Fission and-activation products
- 1. Total release (not including tritium, gases, alpha)
Ci 2.75E-01 9.18E-02 25 2.
Average diluted concentration during period pC1/ml 6.54E-07 6.20E-08 3.
Percent of technical specification limit (T.S. 3.11.1.2 (a))
5.16E+00 1.22E+00 B. Tritium
- 1. Total release Ci 7.24E-01 3.39E+00 25
- 2. Average diluted concentration during period pCi/ml 5.02E-06 9.54E-06 3.
Percent of technical specification limit (T.S. 3.11.1.1) 5.02E-04 9.54E-04 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 1.88E-07 6.85E-09 3.
Percent of technical specification limit (T.S. 3.11.1.1) 1.88E-07 6.85E-07 D. Gross alpha activity
- 1. Total release Ci 0.00E+00 0.00E+00 E.-Volume of waste release L
(prior to dilution -
Batch Release).
liters 6.05E+05 1.95E+06 l
F. Volume of dilution water used during entire period liters 4.20E+08 1.47E+09 14 I
l L
i..
HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1990 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released-Units Quarter Quarter Quarter Quarter Sodium-24 Ci 0.00E+00 0.00E+00 5.87E-06 0.00E+00 Chromium-51 Ci 0.00E+00 0.00E+00 2.47E-03 1.96E-03 Manganese-54 Ci 0.00E+00 0.00E+00 5.44E-03 3.18E-03 Iron-55 Ci
'O.00E+00 0.00E+00 2.50E-01 7.80E-02
)
Cobalt-58 Ci 0.00E+00 0.00E+00 5.22E-05 7.25E-05 Iron-59 Ci 0.00E+00 0.00E+00 1.50E-04 6.66E-04 1
Cobalt-60 Ci 0.00E+00 0.00E+00 1.62E-03 7.76E-04 Zinc-65 Ci 0.00E+00 0.00E+00 1.51E-02 7.01E-03 Silver-110m Ci 0~00E+00 0.00E+00 3.66E-05 7.48E-05 Iodine-131 Ci O.00E+00 0.00E+00 0.00E+00 6.73E-06 TOTALS Ci 0.00E+00 0.00E+00 2.75E-01 9.18E-02 Tritium Ci 0.00E+00 0.00E+00 7.24E-01 3.39E+00 Xenon-133 Ci 0.00E+00 'O.00E+00 9.44E-05 2.24E-03 Xenon-135 Ci 0.00E+00 0.00E+00
?. 77E-04 1.93E-04 TOTALS Ci 0.00E+00 0.00E+00 7.24E-01 3.39E+00 15
_ _ __ _,y AMENDMENT TO RERR-9 25
i 1
PART C.
LIQUID EFFLUENTS Sco Summary Tables 2A through 2C.
PART D.
SOLID WASTE See Summary in Table 3.
PART E.
RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on actual locations of nearby residents and farms.
The population dose impact is based on historical site specific data 1.e.,
food production, milk production, feed for milk animals and seafood production.
The doses were calculated using methods described in Regulatory Guide 1.109 and represent calculations for the six month reporting interval.
Individual doses from batch and nontinuous 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.
J iquid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathway.
The total body dose to an individual was calculated to be 6.32E-01 mrom.
The calculated highest organ dose from liquid releases was 1.50E+00 mrom to the liver.
The calculated population total body dose was 7.69E+00 person-rem.
The calculated average total body dosc to the population within fifty miles of the site was 1.29E-03 mrom/ person.
Air Pathways The resulting total body and skin doses to an individual were calculated to be 1.88E-01 mrem and 4.08E-01 mrem l
respectively.
The calculated highest organ dose due to I
radiciodines and particulates with at greater than eight day half-life was 6.82E-04 mrem to the liver.
The calculated population total body dose was 4.74E-01 person-rem.
The calculated average total & Tdv dose to the population within fifty miles of the site was,_94E-05 mrem / person.
7
t HOPE CREEK GENEPATING STATION TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT J ANUARY - JUNE 199 0 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1st 2nd Est. Total Units Quarter Quarter Error %
A.
Fission and activation products
- 1. Total release (not including tritium, gases, alpha)
Ci 7.66E-01 3.56E-01 25
- 2. Average diluted concentration during period 4C1/ml 1.22E-06 1.86E-06 3.
Percent of technical specification limit (T.S. 3.11.1.2.(a))
1.53E+01 3.06E+01 B. Tritium
- 1. Total release Ci 4.50E+00 3.17E+00 25 2.
Aversgo diluted concentration during period pC3/ml 7.12E-06 7.47E-06 3.
Percent of technical specification limit (T.S. 3.11.1.1) 2.30E-01 2.50E-01 C.
Dissolved and entrained noble gases
- 1. Total release Ci 6.34E-04 1.33E-04 25 2.
Average diluted concentration during period pCi/ml 1.01E-09 3.12E-10 3.
Percent of technical specification limit (T.S. 3.11.1.1) 5.06E-04 1.56E-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 3.45E+06 2.45E+06 F.
Volume of dilution water used during entire period liters 6.27E+08 4.21E+08 14 l
I
l HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter Sodium-24 Ci 0.00E+00 0.00E+00 0.00E+00 1.47E-05 Chromium-51 Ci 0.00E+00 0.00E+00 1.49E-02 5.55E-02 Manganese-54 Ci 0.00E+00 0.00E+00 7.13E-02 7.79E-02 Iron-55 Ci 0.00E+00 0.00E+00 5.87E-01 4.90E-03 Cobalt-58 Ci 0.00E+00 0.00E+00 3.09E-03 4.85E-03 Iron-59 Ci 0.00E+00 0.00E+00 1.15E-02 1.75E-02 Cobalt-60 Ci 0.00E+00 0.00E+00 1.54E-02 1.87E-02 Zinc-65 Ci 0.00E+00 0.00E+00 6.18E-02 1.80E-01 Strontium-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Strontium-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Strontium-92 Ci 0.00E+00 0.00E+00 5.62E-05 5.01E-04 Technetium-99m Ci 0.00E+00 0.00E+00 0.00E+00 3.36E-05 Silver-110m Ci 0.00E+00 0.00E+00 1.64E-04 1.24E-03 Antimony-124 Ci 0.00E+00 0.00E+00 0.00E+00 1.49E-05 TOTALS Ci 0.00E+00 0.00E+00 7.66E-01 3.56E-01 Tritium Ci 0.00E+00 0.00E+00 4.50E+00 3.17E+00 Xenon-133 Ci 0.00E+00 0.00E+00 8.43E-05 0.00E+00 Xenon-135 Ci 0.00E+00 0.00E+00 5.49E-04 1.33E-04 TOTALS Ci 0.00E+00 0.00E+00 4.50E+00 3.17E+00 15
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