ML20236B003
| ML20236B003 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/31/1988 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20236B001 | List: |
| References | |
| HCGS-RERR-6, NUDOCS 8903200275 | |
| Download: ML20236B003 (60) | |
Text
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Ih HOPE CREEK GENERATING STATION 1988 PS G SEMIANNUAL RADIC' ACTIVE EFFLUENT RELEASE REPORT acGs RExa-6 The Energy People
^l- oocxET No. 50-354 OPEPATING LICENSE NO. NPF-57 I
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FEBRUARY 1989 I, ,m3 , - -
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SEMIANNUAL RADIOACTIVE-EFFLUENT RELEASE ^ REPORT HCGS RERR-b i
DOCKET NO. 50-354 OPERATING LICENSE NO. NFF-57> ~,~
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FEBRUARY 1989 L
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., REPORT NO. HCGS-RERR-6 RADIOACTIVE EFFLUENT RELEASE REPORT JULY l - DECEMBER 31, 1988 HOPE CREEK GENERATING STATION Public Service Electric and Gas Company
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HOPE CREEK GENERA 11NG STATION RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1988 INTRODUCTION This report, HCGS-RERR-6, summarizes the releases of radioactive materials in liquid, gaseous and solid form from the Hope' Creek Generating Station (HCGS) for the period July 1, 1988 to December 31, 1988.
The 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 Specification limits are described in detail within this report along with a summary description of how measurements and approximations of the total activity discharged were developed.
To facilitste determination of compliance with 40CFR190 requirements, the following information on electrical output is provided.
HCGS generated 4,145,337 megawatt-hours of electrical energy (net) during the reporting period.
Results of liquid and gaseous composites analyzed for gross alpha, Sr-89, Sr-90, and Fe-55 for the fourth quarter of 1988 were not available for inclusion in this report. The results of these composites will be provided in the next Radioactive Effluent Release Report.
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}g t' Part A. PRELIMINARY' SUPPLEMENTAL INFORMATION c ,
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l'. 0 REGULATORY LIMITS-
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D' l '.' 1 ; Noble dases Release' Limits a .,
?[ .The: dose rate due to radioactive' materials released:in
. gaseous eifluents from the'sitefto areas at and bey 6nd
.the' site boundary shall be. limited toithe.-follouing:
'For noble. gases: Less than.or equal.to.500
. mrems/yr to the. total body and less than orlequal' to 3000 mrems/yr to the skin.'-
In. addition, the: air' dose due to noble gases released <
,i 3- in gaseous effluents from the site to areas atLand' beyond the site boundary shall be limited to the following:
During any calendar quarters' Less than or equal ,
i to 5 mrad for gamma radiation and less than.or
. equal-to 10 mrad for beta radiation ~and,
'a During.any calendar year Less thanfor' equal.to )
10 mrad'for gamma radiation and less'than or equal to.20 mrad for t beta radiation.
1.2 Iodine, Particulate, and Tritium The dose rate due to radioactive materials. released'in
. gaseous effluents from the site,to areas at and.beyond ,
j the site boundary shall be. limited to.the following:
For Iodine-131, Iodine-133, for tritium, Land.for- .J
- all radionuclides in particulate form with half' lives greater than 8 days's Less than or equal to
.1500 mrems/yr to'any organ.
In addition, from iodine-133, the dose toLa member'of l- the public f rom iodine-131, ' f rom' tritiwa, and f rom all radionuclides'in particulate form with half-lives greater than 8 days in gaseous effluents released 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, l- During any calendar years Less than or equal to 15 mrems to any organ.
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l l.3 Liquid Effluents Release Limits-The concentration of radioactive r.aterial released in
. liquid effluents to unrestricted areas shel.1 be limited to the concentrations specified.in 10CFR, Part 20, Appendix B, Table II,: Column 2'for radionuclides
'- other thain edissolved or entrained noble gases. For
- dissolved or entrained noble gases, the concentration shall be limited to 2E-4 microcuries per millili'ter.
.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:
Du'tng r any calendar quarter to-less than or equal tc 1.5 mrems to - the total body and tc. less than or equal to 5 mrems to any organ, and During any calendar year to less than or equal to 3 mrems to the total body and to less titan on 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 radiaticn, from uranium duel 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 ,lititited to .less than or equal to 75 mrems).
2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)
Regulatory Guide 1.21 requires that the licensee provide the MPC's used in determining allowable release rates for radioactive releases.
- a. MPC values were not used to determine the maximum l
release rates for fission gases, iodines, or particulate,
- b. MPC values as stated in 10CFR20, Appendix B, Table II, Column 2 were used for liquids.
l c. MPC value-used for dissolved or entrained noble gases L
was 2E-4 microcuries per milliliter.
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3.0 AVERAGE ENERGY Rqquiatory Guide 1.21 raquires that the licensee provide the aver-age energy of the radionuclides mixture in releases of fission and activation gases, if applicable.
Release. limits for the HCGS are not based upon average en,rgy, hence, this section does not apply.
4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4.1 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 thoroughly mixed before sampling and analysis before any releases are made. Batch releases are defined as releases from equipment drain sample tanks, floor drain sample tanks, detergent drain tanks, and condensate storage tanks. There are no continuous liquid releases for this reporting period.
The preponderant gamma emitting isotopes detected in sampling were Cr-51, Na-24, and Zn-65. Specific activity from analyses were multiplied by the volume of effluent discharged to the environment in order to estimate the total liquid activity discharged.
The detection requirements of Table 4.11.1.1.1.-l of the Technicial Specifications are achievad or exceeded. Isotopes existing at concentrations below the achieved detection limit are treated as not being present.
4.2 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 prints for most planned gaseous effluent releases. A sma.1 quantity of gaseous effluent will be released via the Filtration, Recirculation, and Ventilation System (FRVS) vent during testir] periods. The NPV and SPV are continuously monitored for particulate, iodines, and noble gases; the FRVS is continuously monitored for noble gases. The NPV and SPV have moving particulate and fixed iodine filters; the FRVS has
, fixed particulate and iodine filters. The filters are l
changed and analyzed at least weekly when releases are in progress. The NPV and SPV are sempled monthly for noble gases and tritium.
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t o < the.TechnicalLSpecifications=are? achieved or. ,
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the achieved detection 41imit?are: treated'as not,beingl c l' '
present.. .
continuous Mode" gaseous 1 releases areiquantified'by. < 6 routine (monthly)' sampling andHisctopicnanalyses'of . ,,
the plant.' vents. LSpecificEactivities'forJeach isotope 4
' detected.duringjthe1 routine; sampling:are: adjusted; usingLthe; radiation monitoring readings;to;obtain'ans 4:
' averageLeoncentration,for the period. This'averagei' '
concentration isithen multiplied;by1.theftotal vent;
- flow = volume-for the
- entire sampling _periodiin' order to'-
TestimateEthe normal continuous.releaseoof'
' radioactivity through~the plant vent.
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.When monthly. noble, gas grab samples:yieldedino '. " ,
detectable: activity,,'continuoussmode releases:were' quantified-by integrating > Radiation. Monitoring System readings above. background. Noble Gas' Isotopic abundancesntor these' integrations were based'on the ANSI mix-for;BWR's. Doses: calculated.from this data-employed-the methods of the' Hope' Creek -0DCM Section
- 2. 0.4 y Batch Mode gaseous releases (primary containment
' purge) are quantified by pre-release sampling and q '
isotopic analyses. Specific activities for'each isotope are: multiplied by L the L total ~ purge' flow volume . .
in order'to estimate the batchirelease'of radioactivity through the, plant' vent.
4.3 .The estimated total error'of. reported liquid releases is within 25%.
The estimated total error of the reported continuous gaseous releases-is within 25% when concentrations exceed detectable levels. This' error is due primarily to variability of waste-stream flow rates and changes L in isotopic distributions of' waste streams between sampling periods. The estimated total error of the reported batch gaseous releases is within 25%.
i L 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.
.f 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 thic reporting period there. were no unplanned releases.
7.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS Recent internal Quality Assurance audits of the RERR
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program discovered erroneously reported data in past RERRs. Review of past RERR release rates discovered that gaseous release rates were being calculated, and thus reported, incorrectly. This was due to a computer program used to generate the RERR and inadequate review.- Further investigations also discovered that slightly contaminated (IE-14 uCi/cc) counting equipment was being used to count sample filters. This resulted in reporting false releases of radioparticulates to the environs. To prevent this from occurring again the computer program used to generate the RERR is being corrected and better administrative reviews being implemented. As well, better custodial practices for the counter equipment and improved technical reviews of counting results are being made when vent samples are analyzed.
Amended pages to RERR-2, RERR-3, RERR-4 and RERR-5 are included at the end of this report.
Part B. GASEOUS EFFLUENTS See Summary Tables lA thru 1C.
Part C. LIQUID EFFLUENTS See Summary Tables 2A and 2B.
Part D. SOLID WASTE See Summary 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 prodm: tion, feed for milch animals, and seafood production.
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The Joses were calculated using methods described ir.
Regulatory Guide 1.109. Individual doses from batch and continuous releases were calculated using the annual av9 rage. historic meteorological dispersion coefficients as describad in the Of f site Dose Calculation Manual.
.Popul.ation doses were calculated using the meteorological dispersion coefficients for tir six month interval trom January through June, 1988.
Liquid Pathways Doses to individuals ir the population from liquid releases are primarily from the seafood ingestion pathway. The total body dose to an individual was calculated to be 1.29E-01 mrem. The calculated highest organ dose from liquid releases was 2.75E-01 mrem to the liver. The calculated population total body dose was 1.44E+00 person-rem. The calculated average total body dose to the population within fifty miles of the site was 2.67E-04 mrem / person.
Air Pathways The resulting total body and ski'n doses to an individual were calcu'.ted to be 4.60E-02 mrem and 1.01E-01 mrem respectively. The highest organ dose due to radioiodines and particulate with half-lives greater than ? days was 8.66E-03 mrem to the thyroid. The calculated population total body dose was 1.00E+00 person-rem. The calculated average total body dose to the population within fifty miles of the site was 1.81E-04 mrem / person.
Direct Radiation Direct radiation may be estimated by thermoluminescent dosimetric (TLD) measurements. One metnod for comparing TLD measurements is by comparison with preoperational data. It should be noted that the TLDs measure direct radiation from both the Salem and Hope Creek Generating Stations at Artificial Island.
1 TLD's at onsite ' locations 2S-2 and SS-1, which are 0.3 miles and 0.9 miles from the point of origin, averaged 4.B l and 4.3 mrads/ month respectively. The values for stations i 2S-2 and SS-1 are within the statistical variation associated with the preoperational program results.
It should be noted that the nearest resident is 3.5 miles L
away. It can thus be concluded that there was no measurable dose to any offsite location from direct radiation.
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.Part F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for the third and fourth quarters of 1988 as Tables 5 and 6.
l Part G. PCP CHANGES During the reporting period of July 1 to December 31, 1988 the Process Control Program'(PCP) has been revised.
Revision 2 was approved by SORC during the 4th quarter of 1988. This revision consisted of rephrasing the first'two parzgraphs in Section 7.0. Revision 1 required all vendors temporarily processing and packaging rcdwaste on-site to have an approved topical report. Revision 2 was submitted to permit Class A waste to be processed by an off-site vendor, provided a satisfactory technical review of the processing and Quality Assurance programs has been completed. This revision permitted Hope Creek Station to send low-level waste to a vendor for. super-compacting and then to Btrnwell, South Carolina for burial. Per Hope Creek Technical Specification 6.13.2 PCP Revision 2 is attached.
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. TABLE'lA EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT :
JULY l - DECEMBER 31, 1988 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES I Units 3rd-Quarter 4th Quarter
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Est. Tot!
Error, %
A.' Fission & Activation Gases
- 1. Total release Ci 8.93E+01 8.71E+01
- 2. Average release ,
rate for period uCi/sec 1.14E+01 1.llE+01- 1
- 3. Percent of tech. specification limit (T.S. 3.11.2.2(a)) % 8.71E-01 8.49E-01 B. Iodines
- 1. Total iodine-131 Ci 0.00E+00 0.00E+00
- 2. Average release rate for period ~
uCi/sec 0.00E+00 0.00E+00 ~
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- 3. Percent of tech. specification limit (1) (T.S. 3.11.2.3(a)) % 0.00E+00 0.00E+00 C. Particulate
- 1. ParticulLtes with half-lives >8 days Ci 0.00E+00 0.00E+00
- 2. Average release ,
rate for period uC1/sec 0.00E+00 0.00E+00 1
- 3. Percent of tech, specification limit (1) (T.S. 3.ll.2.3(a)) % 0.00E+00 0.00E+00
- 4. Gross alpha radioactivity (2) Ci 0.00E+00 0.00E+00 D. Tritium
- 1. Total release (1) __ ,Ci 4.44E+0) 1.18E+02
- 2. Average release rate for' period uCi/sec 5.65E+00 1.50E+00
- 3. Percent of' tech. specification limit (1) _l T.S. 3.ll.2.3(a)) % 1.58E-02 4.19E-02 (1) Iodine, tritium, and particulate are treated as a group.
(2) Alpha analyses for the fourth quarter are not available for inclusion in this report.
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b HOPE CREEK GENERATING STATION TABLE IB-EFFLUENT AND WASTE DISPOSAL set 1IANNUAL REPORT JANUARY l - JUNE 30, 1988 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES.
CON _TINUOUS MODE 'DATCH' MODE 3rd 4th 3rd 4th Nuclides Released Units Quarter Quarter- Vuarter -Quarter
- 1. Fission cases Krypton-83m Ci 8.92E-01 8.71E-01 Krypton-85m Ci 8.92E-01 8.71E-01 Krypton-87 _C i 3.57E+00 3.48E+00 Krypton-88 C1 3.57E+00 3.48E+00 Krypton-89 Ci 2.41E+01 2.35Et_01 Xenon-133 Ci 1.783+00 1.74E+00 Xenon-135 C1 4.46E+00 4.3E+00 1.30E-01 1 Xenon-135m Ci 5.35E+00 5.23E+00 L Xenon-137 Ci 2 . 7 7 E +01 2.70E+01 Xenon-138 Ci 1.69E+01 1.65E+01 Total f or period Ci 8.92E+01 8.71E+01 1.20E-01
- 2. Iodines Iodine-131 Ci 0.00E+00 i Iodine-133 Ci Total foc period Ci 0.00E+00 0.00E+00 _
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- 3. Particulate (Half life >8 days)
Sodium-24 Ci l Chromiu.u-51 Ci Mancanese-54 .
Ci i-Cobalt-58 Ci i Cobalt-60 Ci Zinc-65 Ci Strontium-89 Ci l '
Strontium-90 Ci l- Gross Alpha Ci Total For Period Ci 0.00E+00 0.00E+00
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HOPE CREEK GENERATING STATION TABLE IC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY l - DECEMBER 31, 1988 GASEOUS EFFLUENTS-ELEVATED RELEASES There were no elevated releases during this reporting period.
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.HOPEICREEK, GENERATING STATION i
1 TABLE 2A' )
! EFFLUENT!AND WASTE DISPOSAL SEMIANNUAL:REPORTJ o JULY l -' DECEMBER 31, 1988: f
-LIQUID EFFLUENTS-SUMMATIONLOF ALL RELEASES c3rd' !4th' Units- ' Quarter ' Quarter. .Est.-Tota &
Error, % 'l
/A. Fission ' and activation ~ products
.1. Total 1 release-_(not including tritium,-cases,' alpha)i(1)- Ci 6.502-02' 7.52E-023 '25%.
- 2. Average diluted concentration durina period- '
uCi/ml 5.94E-08 ' l~ . 4 8E -3. Percent of. applicable limit (T.S.?3.ll.l.2.(a)) % 4.12E+00 14.04E+00 B.' Tritium
- 1. Total release Ci 1.92E+00 1.36E+00 25%
2.. Average diluted concentration- .
durino' period uCi/ml 1.74E-06 2.67E+06- l
- 3. . Percent.of;-applicable limit- % .
(T,.S. 3.11.1.1) 5.80E-02' 8.90E-02
'C.~ Dissolved and entrained noble cases 1.-Total release C1 3.45E-03 .4.30E-04 254
- 2. Average. diluted concentration durino period uCi/ml 3.15E-09 8.45E-10 3._ Percent of appl.icable limit 4- .
'(T.S.J3.ll.l.1) 2.32E-02 '4.33E-02 __
-D. Gross alpha radioactivity a _,,
- l. Total release (2) Ci 0.00E+00 0.00E+00 E. Volume of waste release (prior .
to dilution - Batch Release) liters 5.86E+06 3.17E+06' 25%'
F. Volume of dilution water used durino entire period liters 1.09E+09 5.06E+08 25%
HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY l - DECEMBER 31, 1988 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Cobalt-58 Ci 9.38E-04 4.76E-04 Cobalt-60 C1 3.11E-03 1.13E-0J Chromium-51 Ci 1.23E-02 3.(tE-02 Iron-55 Ci 8.32E-03 _
Iron-59 Ci 5.73E-04 1.09E-03 Manganese-54 Ci 5.3 IiE!03 3.21E-03 Marcury-203 Ci 5.10E-06 6.40E ~~
Molybdenum-99 Ci 0.0fiE+00
. 15ET O'4 Niobium-97 Ci 8.06E-05 1.46E~04 Neptunium-239 Ci 0.00E+00 4.40E-05 9.;3E-03 8.65E-03 Sodium-24 Ci ,.
Strontium-92 Ci 0.00E+00 2.63E-05 Technetium-99m Ci 1.01E-04 2.63E-04 Tellurium-132 Ci 0.00E+00 1.28E-05 Yttrium-91m Ci 6.00E-04 1.74E-04 Zine-65 C1 2.39E-02 2.33E-02 Zinc-69m Ci 6.68E-05 1.32E-05 Zirconium-97 Ci 3.97E-06 3.28E-05 Unidentified Ci 4.93E-04 0.00E+00 Total (Above) Ci 0.00E+00 0.00E+00 6.50E-02 7.52E-02 Tritium Ci 1.92E+00 1.36E+00 Xenon-131m Ci 1.11E-04 Xenon-133 Ci 1.76E-03 8.82E-05 Xenon-133m Ci 1.51E-06 9.39E-06 Xenon-135 Ci 3.57E-03 3.17E-04 Krypton-85m Ci 2.19E-06 8.07E-06 l
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cTABLE 3 ,
EFFLUENT AND WASTE DISPOSAL SEP.IANNUAL REPORT
' JULY l - DECEMBER 33,;19Bd SOLID WASTE AND IRRADIATED.FUELLSHIPMENTS ,
oi A. SOLID WASTE SHIPPED OFFSITE FOR BURIhL OR DISPOSAL- (Not iresdiated -f uel) ,
6-month- Este Total' Ll'.:. Type L of Waste Units Pe r iod . Error, 4-25
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- a. Spent resins, filters sludges, m3 80.5
. evaporator' bottoms- Ci 6.12E+02 9 'b. Dry compressible waste, m3 -
28 5 25 contaminated equipment Ci 4.09E-01 a c. Irr.adiated components, m3 0.00 a
control rods Ci 0.00E+00
- d. Others (Describe) m3 ,11. 9 ' . ,
25 4 1
Solidified 011' Ci ,
1.14E-05 1 2'. Estimate of msjor nuclide composi' tion (For ' Type A and B' waste):
Resin DAW Solidified Oil 3 (Ci) (Ci) -(C1) !
LChromium-31 '
7.97% 5.12E+01 8.86% 3.62E-02
""9.98%
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11anganese-54' 6.41E+01 3.52E-02 ~
T'ron-55 11.50% 7.38E+01 13.02% 5.32E-02 ;
Iron-59 0.81% 5.20E+00 Cobalt-58 1.14% 7.32E+00 2.96 1.21E-02 Cobalt-60 6.28% 4.03E+01' 9.49% 4.04E-02 ~
78.70% 7 . 8 '.' E - 0 6
' Nickel-63 0.46% 2.99E+00 _
Zinc-65 61.45%- 3.95E+02 56.64% 2.31E __
Tritium-3 0.01% 7.20E-02
' Carbon-14 0.00% 7.47E-03 _ _ , _'
Technetium-99 0.00% 6.80E-03
-Cesium-137 0.09% 5.61E-01 18.8i% 2.156706 Corium-144 0.27% 1.73E+00
' Plutonium-241 0.01% 6.36E-02 ,_
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, '1 EFFLUENT AND WASTE DISPOSAL , SEMIANNUAL ~ REPOP.f 9- -, '
JULY:1-' DECEMBER 31',: l'88. 3
.- SOLID .' WASTE > AND l IRRADIATED ' FUEL ' SHIPMENTS -
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- 4' Truck Richland, WA
- . B. TIRRADIATED FUEL SHIPMENTS-'(Dispos'ition) l i S, Number of Shipments Mode of Transportation _' Destination e
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, HOPE CREEK GENERATING STATION TABLE-4A EFFLUENT AND WASTE DISPOSAL 1 SEMIANNUAL REPORT JULY l'- DECEMBER l31, 1988 1
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SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE l l
NATCH RELEASES ONLY )
July 1,_1988 - September- 30, 1388-
- 1. Datss: -
. '2.- . Type'of releases Gas ]
- 3. Number of releases during the 3rd Quarter: ? ,
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- 4. Totaltimedurationforallreleasesoftypelishedabove 2849 minutes
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- 5. Maximum duration for releases of type listed above: 2849 minutes ]
- 6. Average ~ duration for all releases of type listed.above "
2849 minutes 7.- Minimum duration for release of type listed above: 2849 minutes:
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- 8. The average stream flow (dilution' flow) during the period of release: N/A a . - - - _ _ _ _ _ _ - _ _ _ - _ _ _ _ - _ - _ - _ - - - _ _ _
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HOPE CREEK GENERATING STATION TABLE 4A (Cont'd) g',
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY l - DECEMBER 31, 1988 e
SUMMARY
SHEET FOR RADIOACT1VE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: October 1, 1988 - December 31, 1988
- 2. Type of releases Gas
- 3. Number of releases during the 4th Quarter: 1
- 4. Total time duration for all releases of type listed above:
11,520 minutes
- 5. Maximum duration for releases of type listed above: -
11,520 minutes
- 6. Average duration for all r31 eases of type listed above: .
11,520 minutes o
- 7. Minimum duration for release of type listed above: .
11,520 minutes -
e .s
- 8. The average stream flow (dilution flow) during the period l-of release: N/A 1
l i,
.. 8
)
9-
' ^
O.
T HOPE CREEK GENERATING' STATION TABLE 4B-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT {
JULY l - DECEMBER 31~, 1988 j
SUMMARY
SHEET-FOR RADI0 ACTIVE EFFLUENTS RELEASED IN A BATCH MODE ~
.r-BATCH RELEASES ONLY
- 1. Dates: July 1, 1988 September 30,L1988 1
- 2. . Type of release: ' Liquid J
3.- Number of-releases during the 3rd Quarter: 130 -j
- 4. Total time duration for all. releases of type listed above 26,039 minutes- ,
- l 1
- 5. Maximum duration for releases of type listed above: 629 minutes
- 6. . Average duration' for all' releases of type listed above 200 minutes
- 7. Minimum duration for release of type listed above 67 minutes
- 8. The average stream flow.(dilution flow)'during the period of
-release:- 27,925 gpm
. . . . . . . . . -. m.. .. . . . .
h HOPE CREEK GENERATING STATION TABLE 4B ,
(Cont'd)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY l - DECEMBER 31, 1983
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED
} IN A BATCH MODE l BATCH RELEASES ONLY ,
- 1. Dates: . October 1, 1988 - December 31,'1988
- 2. Type of release: Liquid
- 3. Number df releases during the 4th Quarter 74
- 4. Total time duration for all releases of type. listed above:
17,884 minutes
- 5. Maximum duration for releases of type listed above :
1,654 minutes
- 6. Average' duration for all releases of type listed 5tbove:
'241.7 minutes
- 7. Minimum duration for release of type listed abover. 40 minutes
- 8. The average stream flow-(dilution flow) during the period of release: 24,046 gpm
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i 5.0 BATCH RELEASES Summaries'ofsbatch releases of gaseous and liquid effluents
-are providedJin Tables 4A and 4B.
6.0 UNPLANNED' RELEASES l l
During this reporting period'there were no unplanned releases.
I 7.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE
' REPORTS ,
Our last report (RERR-2) did not include the quarterly gross alpha, Sr-89, Sr-90, and Fe-55 composite data for:the fourth quarter of 1986. Also, the population total body- 1 dose reported was overly conservative and in error. !
Amended pages to RERR-2 are included at the end of this report.
1 Part B. GASEOUS EFFLUENTS See Summary Tables IA thru'lC.
L Part C.. LIQUID' EFFLUENTS See Summary Tables 2A and 28. (
s.
Part D. SOLID WASTE See Summary Table 3. (
Part E. RADIOLOGICAL IMPACT ON MAN 1
'i The calculated individual doses in this section are based on actual locations of nearby residents and farms. The population dose impact is based on historical site specific data 1.e., food production, milk production, feed tor milh l
animals, and seafood production.
}
i l The' doses were calculated using methods described in Regulatory Guide 1.109. 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 waspersion coefficients for the six month interval from J.auary through June, 1987, b
-3 Liquid Pathways Doses to individuals . in the population f rom liquid releases are primarily-from.the seafood ingestion pathwey. The total body. dose to an individual was calculated to be 1.98E-01 mrem. The calculated highest ~ organ dose from liquid' releases was-).70E-01 mrem to.the liver.- The calculated population total body dose was 6.30E-02 person-rem. . The calculated average total body doce to the population.within fifty. miles of the site was.l.188-05, mram/ person.
, Air Pathways-I The resulting total body and skin doses to an. individual' '
were calculated to be 4.38E-01 mrem and 4.61E-01 mrem .
respectively. The highest organ dose due t'o radiciodincs and particulate with half-lives greater than 8~ days was 1.21E+00 mrem to the thyroid. The calculated population total body dose was 1.00E+01 person-rem. The calculated average. total body dose to the population within fifty y miles of the site was 1.74E-03 mrem / person. !
I Direct Radiation Direct radiation may be estimated by thermoluminescent dosimetric (TLD) measurements.- One method for comparing !
LTLD measurements is by comparison with preoperational j data. It should be noted that the TLDs measure direct radiation f rom both the Salem and Hope Creek Generating Stations at Artificial Island.
TLD's at onsite locations 2S-2 and SS-1, which are 0.3 miles and 0.9 miles from the point of origin, averaged 4.5 and 4.2 mrads/ month respectively.- The values for stations 2S-2 and SS-1 are within the statistical' variation ;
associated with the preoperational program results. i It should be noted that the nearest. resident is 3.5 miles {
away. It can thus be concluded that'tl,ere was no measurable dose to any offsite location from direct radiation. a
-l 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 1987 as Tables 5 and 6.
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j E}f TABLE lAl i o,. , .
l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT,
' JULY 1.- DECEMBERu31,J1987 GASEOUS EFFLUENTS-SUMMATION OF 'ALL- RELEASES:
i
- 3rd' 4th. l l'
Unita -Quarter' . Quarter Est..To@
Error 0 ,
4"" A. Fission & Activation: Gases
- 1. Total release ci- 1.83E+02 1.04E+02 25%
n,e 4 .2. Average. release i j
' rate for period uCi/sec ~3.22E+00 '9.05E-01: R
- 3. Percent.of tech. specification limir (T.S. 3.11.2.2(a)) % 2.50E+00 2.41E+00:
4 B.' Iodines 1
- 1. Total iod'i ne-131 Ci 0.00E+00 0.00E+00 254 r 2.. Average release l rate for period f!Ci/sec 0.00E+00 0.00E+00 J
- 3. Percent.of tech. specification H '
limit ~(1)'(T.S.-3.ll.2.3(a)) % 0.00E+00 0.00E+00~
1 C. Particulate 1 1.cParticulates with
' half-lives >8 days 'Ci 0.00E+00 0.00E+00 254 H
- 2. Average release i rate for period. uCi/sec 0.00E+00 0.00E+00 3.sPercent otetach. specification limit (1) (T.S'. 3.ll.2.3(a)) 4 0.00E+00 0.00E+00 1
- 4. Gross alpha radioactivity (2)- Ci 0.00E+00 0.00E+00 -25%
l D. Tritium L 1. Total release (1) Ci 5.96E+02 4.45E+02 25%
l 2. Average release rate for period uCi/sec 7.58E+01 5.66E+01
(2) Alpha analyses for the fourth quarter are not available for inclusig in this report.
3
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TABLE 1B
- EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT: <
. JULY l - DECEMBER 31, 1987 d
GASEOUS EPTLUENTS-GROUND LEVEL RELEASES q CONTINUOUS; MODE BATCH MODE; L. .
m a .f 3rd 4th 3rd -4th i l
Nuclides Released Units Quarter Quarter Quarter , Quar te r'
']
l'. Fission Gases ,
Krypton-83m. C1 1.84E+00 9.61E-01 9 Krypton-85m C1 1.84E+00 9.61E j
__ Krypton-87 Ci 7.34E+00 , 3.84E+01 i l
- ~ Krypton-88 Ci 7.34E+00 3.84E+01 ;
l '. 2.0E+01 Krypton-89 Ci 4.96E+01 Xenon-133 Ci 3.67E+00 1.92E+00 1 Xenon-135 Ci- 9.18E+00 1.22E+01 1.75E-07 Xenon 135m C1 1.10E+01 5.77E+00 .
~~~
Xenon-137- Ci 5.69E+01 2.98E+01 Xenon-138 C1 3.49E+01 1.83E+01 :,
t Total For Period C1 1.83E+02 9.62E+01 1.75E-07 1 2. Iodines Iodines-131 Ci 0.00E+00 0.00E+00 Total'For Period Ci 0.00E+00 0.00E+00 .
- 3. Particulate' (Half-lives > 8 days)
Sodium-24 C1 L
Chromium-51 Ci Manaanese-54 C1 Cobalt-58 Ci Cobalt-60 Ci Iron-59 Ci Zinc-65 Ci Strontium-89 Ci Strontium-90 Ci Gross Alpha Ci l-l: Total For Period Ci 0.00E+00 0.00E+00
i: i e
AMENDED PAGES TO BOPE CREEK RERR-5 -
1 l
L k
-e .
.e 4
.,o, '
+
a<
1-5.0 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 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS Our last report (RERR-4) did not include the quarterly gross alpha, Sr-89, Sr-90, and Fe-55 composite data for the fourth quarter of 1987. Amended pages to RERR-4 are included at the end of this report.
Part B. GASEOUS EFFLUENTS See Summary Tables lA thru 1C.
Part C. LIQUID EFFLUENTS See Summary Tables 2A and 2B.
Part D. SOLID WASTE See Summary 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 milch animals, and seafood production.
The doses were calculated using methods described in Regulatory Guide 1.109. Individual doses from batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as described in the Of f site Dose Calculation Manual. Population doses were calculated using the meteorological dispersion coefficients for the six month interval from January through June, 1988.
a 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 4.1E-01 mrem. The. calculated. highest. organ dose from liquid j releases was 9.30E-01" mrem to the liver. The calculated- 1 population total. body' dose was 4.72E+00 person-rem.. The calculated average total body dose to the population within fifty. miles of the site waa 8.74E-04 mrem / person.
Air Pathways The.resulting; total body and skin doses to an individual l were calculated to be 0.00E+00 mrem and 0.00E+00 mrem. 1 respectively.. The highast organ dose due to radioiodines ;
and particulate with half-lives greater than 8 days was o
1.76E-05 mrem to the. thyroid. LThe calculated population total. body. dose was 4.09E-04 person-rem. The calculated. !
4 average total body dose to the population within fif ty miles of the site was 7.06E-08 mrem / person.
Direct Radiation Direct radiation may be estimated by thermoluminescent dosimetric (TLD) measurements. One method-for comparing TLD measurements is by comparison with preoperational data. It should be noted that the TLDs measure direct radiation from '
~
both .the -Salem and Hope Creek Generating Stations' at Artificial Island.
TLD's at.onsite locations 2S-2 and SS-1,'which:are 0.3 miles and 0.9 miles from the point of origin, averaged 4.95 and 4.35 inrads/ month respectively. The values for stations.2S-2 and SS-1 are within the statistical variation associated with the preoperational program results.
It should be noted that the nearest resident is 3.5 miles away. It can thus be concluded that there was no measurable dose to any offsite location from direct radiation.
Part F. METEOROLOGICAL DATA L
L Cumulative joint wind frequency distributions by atmospheric stability' class at the 300 foot elevation are provided for the first and second quarters of 1988 as Tables 5 and 6.
a jjp'-'if. ,--, a .- . , . ',,
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- 7. .
i -TABLE 1A-
,I n -
1-
$E '
EFFLUENT'AND WASTE' DISPOSAL' SEMIANNUAL REPORT JANUARY l~- JUNE 30, 1988 .
GASEOUS EFFLUENTS-SUMMATION 0F ALL RELEASES-1st 2nd Est. Tot (
' Units fQuarter' -Quarter ' Error 1(
l A. l'ission 4 Ac' tivation Gases-
- 1. Total release Ci 0.00E+00 0.00E+00
- 2. Average release rate for period uCi/sec. 'O.00E+00 :0.00E+00
- 3. Percent of;techn1 cal i specification limit (T.S. 3'.11.2.2(a)) 41 0.00E+00 0.00E+00' __
i i
3
-B. Iodines
> 1. Total iodine-131, iodine-133 0.00E+00 0.00E+00 '
- 2. Average release rate . :
for period uCi/sec. 0.00E+00 0.00E+00 1
- 3. Percent of. technical specification? limit (1) :
(T.S. 3.ll.2.3(a)) % 0.00E+00 0.00E+00 1 C. Particulate
- 1. Particulate with -j t half-lives >8 days Ci' O.00E+00 0.'00E+00 -l 2.-Average release rate for period uCi/sec. 0.00E+00 0.00E+00
- 3. Percent: of technical specification limit (1)
(T.S. 3.11.2.3(a))' 4 0.00E+00 0.00E+00-
- 4. Gross alpha radioactivity 'Ci 0.00E+00 0.00E+00 D. Tritium
- 1. Total release Ci 0.00E+00 1.65E-01
- 2. Average release rate for period uCi/bec. 0.00E+00 2.10E-02
- 3. Percent of technical specification limit (1)
(T.S. 3.ll.2.3(a)) % 0.00E+00 2.37E-04 (1) Iodine, tritium, and particulate are treated as a group.
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h- HOPE = CREEK GENERATING. STATION
' TABLE 18.
- EFFLUENT AND WASTE. DISPOSAL SEMIANNUAL REPORT 4 JANUARY 1 - JUNE'30, 1988
' GASEOUS ~ EFFLUENTS-GROUND LEVEL RELEASES =
q.
CONTINUOUS MODE BATCH MODE
'Ist' '2nd
. ls t' '2nd '
Nuclides; Released- Units: Quarter- Quarter. Quarter. ' Quarter l.' ' Fission cases Krypton-85 Ci Tota.1 for period- Ci 0.00E+00 0.00E+00 .
i 2.
~
Iodinem Iodine-131 Ci Iodine-133 Ci Total for period C i- 0.00E+00 0.00E+00 l 33' Particulate (Half life >8 days)
Sodium-24 Ci '
Chromium-51 Ci Manganese-54 Ci Cobalt-58 Ci jf Cobalt-60 Ci ,
l- Iron-59 Ci Ci Yttrium Strontium-89 Ci Stront:.um-90 Ci ,
2 i rcon :,um-9 5 - Ci Molybdenum-99 Ci Cesium-137 Ci l Cerium-139 Ci ,
Total For Period Ci 0.00E+00 0.00E+00
. _ _ - _ - _ _ _ _ _ _ _ _ _ _ - _ _ -