ML20012A258
| ML20012A258 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/31/1989 |
| From: | Miltenberger S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N90036, RERR-8, NUDOCS 9003090106 | |
| Download: ML20012A258 (46) | |
Text
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Public Service.
Electric and Gas -
J Company
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= Steven E. MHtenberger.
Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge..NJ 08038 609 339 4199
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Vce President a$d Chief Nuclear Officer
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,FEB _2 8 1990 '
'NLR-N90036 j
United States Nuclear Regulatory Commission-
. Document Control Desk-Washington,. DC 20555 I
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Gentlemen:.
l RADIOACTIVE EFFLUENT RELEASE REPORT - 8 y,
HOPE CREEK GENERATING STATION.
DOCKET NO.-50-354 4
InLaccordance with Section 6.9.1.7 of Appendix A to the Operating 1.
License for Hope Creek-Generating Station (HCGS), Public. Service Electric'and Gas' Company (PSE&G) hereby-transmits one copy of the o
-semi-annual Radioactive Effluent Release Report, RERR-8.-
This
. report summarizes liquid and gaseous releases ~and solid waste
. shi'pments: from the HCGS for the period July 1 through December 31',- 1989.
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Should you liave -any questions regarding this transmittal, please -
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. feel' free =to' contact us, f
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f Sincerely,.
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Document Control: Desk NLR-N90036 I E S 2 8 19 #)-
'RERR REPORT only C
Mr.'C. Y.-Shiraki (1)
Licensing Project Manager Ms.2 G.'W.
Meyer (1)
Senior Resident' Inspector
.Mr.' W. T. Pussell, Administrator (2)
Region I Mr. K. Tosch, (1)-
r New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 l
USNRC, Director (1).
-Office of Nuclear Reactor Regulation Washington, DC 20555 i
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HOPE CREEK GENERATING STATION SEMIANNUAL RADIOACTIVE s
EFFLUENT RELEASE REPORT HCGS RERR - 8 DOCKET No. 50-354 OPERATING LICENSE No. NFP-57
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HOPE CREEK GENERATING STATION i
RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1989 INTRODUCTION
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This report, HCGS-RERR-8, summarizes the releases of radioactive materials in liquid, gaseous and solid form from the HOPE CREEK Generating Station (HCGS) for the period July 1, 1989 to December 31, 1989.
The report is prepared in the format of Regulatory Guide 1.21, I
l-Appendix M, 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 wcste shipments are our responses to parts A-F of the " Supplemental Information" cection of Regulatory Guide 1.21, Appendix B.
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' As required by Regulatory Guide St.21, our Technical Specification j
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'limitu are described in detail within this report along with a k
summary description of how ma Annrements and approximations of the total activity discharged woro developed.
j 1-To facilitate dotormination of compliance with 400FR190
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.requiremente, the following information on electrical output is
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provided.
Hope Creek generated 4,109,036 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 1989 were not available for inclusion in this report.
The results of these composites will be provided in the next Radioactive Effluent Release Report.
i The Sr-89, Sr-90 and Fe-55 analyses for the first half of 1989 (refer to RERR-7) have been completed; amended pages to RERR-7 are included in this report.
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PART A. PRELIMINARY SUPPLEMENTAL INFORKATION 1.0 REGULATORY LIMITS i
1.1 Noble Gas Release Limits The dose rate due to radioactive materials released in i
gaseous affluents from the site to areas at and beyond
]
the site boundary, shall be limited to the following:
For noble gases:
Less than or equal to 500 arems/yr to the total body and less than or equal to 3000 arems/yr to the skin.
In addition, the air dose due to noble gases released in gaseous affluents from the site to areas at and beyond the sf,te boundary, shall be limited to the following l
During any calendar quarter Less than or equal to 5 mrad for gamma radiation and Icss than or equal to 30 nrad for beta radiation and, i
f During any calender yeart Lees than or equal to 10 L
mrad for gamma radiation.and ler.s than or aqual to
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'((-)3 20 mrad for bata radiation.
1.2 12dina Particulatas, and Tritium L
The dose rate due to radioactive matarials released in 2
gaseous affluents from the sits to areas at and beyond the site boundary, shall be limited to the fellowing:
For Iodine-131, for tritium, and for all radionuclides in particulate form with half lives i
greater than 8 days:
Less than or equal to 1500 arems/yr to any organ.
+
i In addition, the dose to a member of the public from I
iodine-131, from tritium, and from all radionuclides in i
particulate form with half-lives greater than 8 days in l
gaseous affluents released, from each reactor unit, from the site to areas at and beyond the site boundary, shall be limited to the following:
During'any calendar quarter:
Less than or equal to 7.5 areas to any organ and, During any calendar years Less than or equal to 15 areas to any organ.
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1.3 Licruid Effluents Relaana Limits i
The' concentration of radioactive material released in l
liquid effluents to unrestricted areas shall be limit to the concentrations specified in 10 CFR, Part 20, Appendix B, Table II, Column 2 for radionuclides other than i
dissolved or entrained noble gases.
For dissolved or i
entrained noble gases, the concentration shall be limited to 2E-4 microcuries per milliliter.
1 1
In addition, the dose or dose commitment to a member of I
the public from radioactive materials in liquid effluents released to unrestricted areas shall be limitedt t
.1m15 During any calendar quarter to less than or equal to 1.5 areas to the total body and to less than or equal to 5 mreus to any organ, and l
During any calendar year to less than or equal to 3 l
mreas to the total body and to less than or squal to 10 mrems to any organ.
t l A 1.4 Ig,p1 Dona Limit
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The annual (calendar year) dose or 6cse com:itnant to any
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l member of ths public, due to telonnes of radioactivity and l
radiation, from uranium fuel cycle sources-shall be limitcd to less than or equal to 25 areas to the total body or any organ (except the thyroid, which shall ba I hited to less than or equal to 75 mress).
2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)
Regulatory Guide 1.21 requires that the licensee provide the MPCs used in determining allowable release rates for radioactive releases.
a.
MPC values are not used to determine the maximum release
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i rates for fission gases, iodines, or particulates, i
b.
MPC values as stated in 10CFR20, Appendix B, Table II, Column 2 were used for liquids.
i c.
The MPC value used for dissolved or entrained noble gases i
is 2E-4 microcuries per milliliter.
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3.0 AVERAGE ENERGY Regulatory Guide 1.21 requires that the licensee provide the average energy of the radionuclide mixture in releases of fission and activation gases, if applicable.
Release limits for HCGS are not based upon average energy, hence, this section does not apply.
i 4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADI0 ACTIVITY 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 rerouted 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 4
the equipment drain sample tanks, floor drain sample i
tanks, detergent drain tanks and chemical waste tanks.
There are no continuous liquid releases for this 9
reporting period. The preponderant gamma emitting isotopes detected in sampling were 2n-C5, cr-51, and
,f N Mn-54.
Specific activity from analyses ware multiplied
( (,)
by the volume of effluent discharged to the environment in order to estinkte the total liquid activity discharged.
The detection requirements of Table 4.1.1.1-1 of the Technical Specifications are achieved or exceeded.
Isotopes that may be present at concentrations below che achieved detection limit are treated as not being present.
4.2 Gaseous effluent streams are monitored and sampled in i
accordance with Table 4.11.2.1.2-1 of the Technical p
Specifications.
The north plant vent (NPV) and south plant vent (SPV) are the final release points for most planned gaseous affluent 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 have. moving particulate and fixed charcoal filters; the FRVS has fixed particulate and charcoal filters. The filters and charcoal are changed weekly, and analyted on a multi-channel analyzer in the laboratory.
The NPV and SPV are sampled monthly for l
noble gases and tritium.
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The detection requirements of Tables 4.11.2.1.2-1 of the i
Technical specifications are achieved or exceeded.
Isotopes existing at concentrations below the achieved detection limit are treated as not being present.
continuous Mode gaseous releases are quantified by routine (monthly) sampling'and isotopic analyses of the plant vents.
Specific activities.for each isotope detected during the routine sampling are adjusted using i
the radiation monitoring readings to obtain an average concentration for the period.
This average concentration is then multiplied by the total vent flow i
value for the entire sampling period in ord0r to estimate the normal continuous release of r1dioactivity through the plant vent.
When monthly noble gas grab samples yielded no detectable activity, continuous mods releases were quantified by integrating Radiation Monitor System readinge above background.
Noble gas isotopic abundancen for these integrations were based on the ANSI N237-1976/ANS-18.1. mix for BWRs Doses calculated from L
this date employed the methode. of the Hope Creek ODCM i(.
Section 2,0.
EkMhji'2de 9aseous rele?.ses (primary containment purge) are quantiixed by pre-relenro sempling and isotopic
- analysia, specific activit3es 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" us4rc historical efficiency factors.
The " specific activity" is multiplied by the volume of effluent discharged while the channel was in an alarm state in ordir to estimate the total activity discharged.
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4.3 The estimated total error of reported liquid releases is i
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i within 254.
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The estimated total error of the reported continuous I
gaseous releases is within 50% when concentrations exceed detectable levels.
This error is due primarily to variability of vaste stream flow rates and changes in isotopic distributions of waste streams between sampling 1
periods.
The estimated total error of the reported batch gaseous releases is within 104.
Error estimates for releases where sample activity is below the detectable concentration levels are not included since error estimates at the LLD are not 1
defined.
l The estimated total error of reported solid releases is within 25%.
5.0 BATCH RELEASES Sunnaries of batch releases of gaseous and liquid affluents are provided in Tables 4A and 4E, j
d.0 UNPLANNED RELEAS'4S During this teporting period there were no onplanned releases.
7.0 ELZVATED R7sDIATION 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 were thus included in Tables 1A and 18.
8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE' REPORTS Our last report (RERR-7) did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the second quarter of 1989.
Amended pages to RERR-7 are included at the end of this report.
Part B.
GASEOUS EFFLUENTS See Summary Tables 1A thru 1C.
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Part C.
LIQUID EFFIDENTS l
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.See Summary Tables 2A thru 2C.
Part D..
SOLID NASTE see summary in Table 3.
Part E.
RADIDIDGICAL IMPACT ON MAN The calculated individual doses in this section are based on i
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 milch animals and seafood production.
I 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 menth reporting interval.
Liquid. Pathways Doses to individuals in the population frca liquid releases are primarily from the seafoed, inger. tion pathway.
The total body dose te an individual was calculated to te 4.t.32-01 area.
The calculated highett organ dose from liquid releases was 9.97E-01 area to the liver.
The calculated population total body dose was 5.41E+00 person-rem.
The calculated
+
average total body dose to the population within fifty miles of the site was 9.06E-04 aren/ person.
Air Pathways The resulting total body and skin doses to an individual were calculated to be 3.86E-02 aren and 6.38E-02 mram respectively.
The calculated population total body dose was 4.66E-01 person-rem.
The calculated average total body dose to the population within fifty miles of the site was 7.81E-05 aren/ person.
Direction Radiation Direct radiation may be estimated by Thermoluminescent dosimetric (TLD) measurements.
One method for comparing TLD
)
measurements is by comparison with preoperational data.
It 7
4 i
(-(7 should be noted that the TLDs measure direct radiation from both the Salem'and Hope creek Generating Stations at Artificial Island.
TLDs at onsite locations 28-2 and 58-1, which are 0.3 miles and 0.9 miles from the point of origin, averaged 4.9 and 4.6 arads/ month respectively.
The values for locations 2S-2 and 58-1 are within the statistical variation associated with the i
preoperational program results.
i It should be noted the nearest resident is 3.5 miles away.
It can thus be concluded that there is no measurable dose to any offsite location from direct radiation.
Part F.
METEOROIDGICAL DATA cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for the third and fourth quarters of 1989 in Tables 5 and 6.
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.(s HOPE CREEK GENERATING STATION TABLE 1A EFFIDENT AND WASTE DISPOSAL SENIANNUAL REPORT t
JULY - D7.,Ch.MBER 1989 t
GASEOUS EFFLUENTS-SUNNATION OF.ALL RELEASES 3rd 4th Units Quarter Quarter Est. Total Error % (1)
A. Finaion and Activation Gamma 1.
Total relaaaa ci 8.16E+01 6.64E+01 25
- 2. Average release rate for naried uci/sec 1.04E+01 8.45E+00
- 3. Percent of technical specification limit (T.S. 3.11.2.2fa))
4 7.96E-01 6.48E-01 B.
Indinem 1.
Total iodina-131. iodine-133 Ci O.00E+00 0.00E+00 25
- 2. Average release rate i
(
for nariod uci/mac 0.00E+00 0.00E+00
- 3. Percent of technical apacification limit (2) fT.S. 3.11.2. Ma))
0.00E-00 0.00E-00 C.
Particulatea
- 1. Particulaten with half-livan >8 davo ci 0.O_0E+00 0.00E+00 25
- 2. Average release rate for nariod uCi/mac 0.00E+00 0.00E+00
- 3. Percent of technical specification limit (2)
(T.S. 3.11.2.3fa))
0.00E-00 0.00E-00 4.
Grpas alnha Ci 0.00E+00 0.00E+00 l
D. Tritium 1.
Total Relaana ci 0.00E+00 0.00E+00 25
- 2. Average release rate for nariod uCi/mac 0.00E+0Q_,0.00E+00
- 3. Percent of technical specification limit (2)
(T.S. 3.11.2.3(a))
0.00E-00 0.00E-00 (1) For batch releases the estimated overall error is within 10%
(2) Iodine, tritium and particulates are treated as a group 9
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HOPE CREEK GENERATING STATION TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT i
i JULY - DECEMBER 1989 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS NODE BATCH MODE 3rd 4th 3rd 4th
+
Nuclides Released Unit Quarter Quarter Quarter Quarter
- 1. Fission Gases i
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Krvnton-83m Ci 8.16E-01 6.64E-01 l
Krvnton-85m Cd 8.16E-01 6.64E-01 l
Krvnton-87 Ca 3.27E+00 2.66E+00 Krvnton-88 Ci 3.27E+00 2.66E+00 Krvnton-89 Ci 2.20E+01 1.79E+01
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Yanon-133 Ci 1.63E+00 1.33E+01
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Xenon-135 __
Ci 4.08E+00 3.32E+00 Xalion-135m Ci 4.90E+00 3.99E+00 Xg7pn-137 Ci 2.53E+01 2.06E+01 Xeron-338 Ci 1.55E+01 1.26E+01
,,,__ Total for Petiod Ci 8.16E+01 6.64E+01
- 2. Iodines Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates (half-lives >8-days Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
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TABLE 1C EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT JULY - DECEMBER 1989 GASEOUS EFFLUENTS-ELEVATED RELEASES Nuclide Releases 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter There were no elevated gaseous releases during this reporting
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period.
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HOPE CREEK GENERATING STATION TABLE 2A EFFLUENT AND NASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1999 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 3rd 4th Units Quarter Quarter Est. Total Error %
i A.
Fission and activation nroducts
- 1. Total release (not including tritium, ammes, alnha) (1)
C1 1.26E-01 4.47E-01 25
- 2. Average diluted concentration durina nariod uC1/ml 1.13E-07 4.98E-07
- 3. Percent of applicable limit (T.S. 3.11.1.2.fa))
2.51E+00 2.71E+01 B. Tritium
- 1. Total release Ci 8.16E+00 6.34E+00 25 (s.s
- 2. Average diluted concentration durina nariod uCi/ml 7.22E-06 7.01E-06
- 3. Percent of applicable limit (T.S. 3.11.1.1) t 2.41E-01 2.34E-01 C.
Dissolved and entrained noble cases
- 1. Total relaana ci 1.48E-03 6.12E-05 25 l
- 2. Average diluted concentration release nyyiod uCi/ml 1.31E-09 6.78E-11 3.
Parcant of annlicable limit (T.S. 3.11.1.1) 6.55E-04 3.39E-05 D.
Gross alnha activity 1.
Total release (2)
Ci 0.00E+0C 0.00E+00 i
E. Volume of waste release - (prior i
to dilution - Batch Release) liters 5.06E+06 4.99E+06 F. Volume of dilution
- tater used durina antire narirwi liters 1.12E+09 8.96E+08 (1)
Fe-55, Sr-89 and Sr-90 analyses for the fourth quarter are not available for inclusion in this report.
(2)
Gross Alpha analyses for the second quarter are not available for O
inclusion in this report.
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HOPE CREEK GENERATING STATION
"'ABLE 2A l
EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT JULY - DECEMBER 1989-j LIQUID EFFLUENTS-SUNNATION OF ALL RELEASES 3rd 4th l
Units Quarter Quarter Est. Total Error %
ot 1 1
s inc d
I tritium, ammaa. alnha) (1)
C1 1.26E-01 4.47E-01 25
- 2. Average diluted concentration durina naried uci/nl 1.13E-07 4.98E-07
- 3. Percent of applicable limit fT.S. 3.11.1.2.fa))
t 2.51E+00 2.71E+01 i
B.
Tritium l
- 1. Total relmana ci 8.16E+00 6.34E+00 25
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- 2. Average diluted concentration
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durina naried uci/ml 7.22E-06 7.01E-06
- 3. Percent of applicable limit 1
(T.S.
3.11.1.1) t 2.41E-01 2.34E-01 i
C. Diamolved and entrained noble ammen
- 1. Total relaama ci 1.48E-03 6.12E-05
- 2. Average diluted concentration relaana naried uci/ml 1.31E-09 6.78E-11 3.
Parcant of annlicable limit (T.S.
3.11.1.1) 4 6.55E-04 3.39E-05 D.
Cross alnha activity 1.
Total relaana (2)'
Ci 0.00E+00 0.00E+00 E. Volume of waste release - (prior to dilution - Batch Relaama) liters 5.06E+06 4.99E+06 F. Volume of dilution water used durina antire nariod liters 1.12E+09 8.96E+08 (1)
Fe-55, Sr-89 and Sr-90 analyses for the fourth quarter are not I
available for inclusion in this report.
(2)
Gross Alpha analyses for the second quarter are not available for inclusion in this report.
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HOPE CREEK GENERATING STATION j
TABLE 28 EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT
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JULY - DECEMBER 1989 LIQUID EFFLUENTS CONTINUOUS NODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Bodium-24 C1 1.17E-03 2.82E-05 chranium-51 Ci 6.14E-02 4.85E-02 l
Mananname-54 Ci 9.83E-03 1.63E-01 Cobalt-58 Ca 1.01E-03 9.90E-03 Cobalt-60 CL 2.29E-03 3.34E-02 Iron-55 CL 3.24E-02 Iran-59 CL 3.42E-03 4.60E-02 Eine-65 CL 1.37E-02 1.45E-01 Armanic-76 Ca 2.44E-05 7
g'"
Strontium-92,,,,
ci 1.4OE-04 2.21E-04 Niobium-95 Ci Miobium-97 ci 4.33E-06 2.14E-05 E1Lver-110m,
C1 5.64Ea04 5.25E-04 Cesium-137 Ci 3.91E-06 Tft,tglg Ci 1.26E-01 4.47E-01 H-3 Ci 8.16E+00 6.34E+00 Xenon-133 Ci 3.15E-04 Xenon-135 Ci 1.16E-03 6.12E-05 4
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HOPE CREEK GENERATING STATION TABLE 3 9
EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT JULY - DECEMBER 1989 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 5.19E+01 sludges, evaporator bottoms ci 1.09E+02 25 b.
Dry compressible waste, m3 4.10E+01 contaminated equipment.
Ci 5.03E+00 25 c.
Irradiated components, m3 0.00E+00 control rods Ci 0.00E+00 25 d.
Others (described) 23 0.00E+00
^
Ci 0.00E+00 25 l
2.
Estimate of major riuclide composition (for Type A and B waste)
Rasina DAW ft)
(Ci)
(t)
(Cli chromaium - 51 3.2 3.47E+00 11.0 5.53E-01 Manaanama - 54 4.3 4. QE,+0 0 5.8 2.92E-01 Iron - 55 20.5 2.05E+01.
27.3 1.37E+00 Iron - 59 Cobalt - 58 0.3 3.63E-01 2.3 1.16E-01 l
1.4 7.04E-02 cobalt - 60 2.9 3.15E+00 2.2 1.11E-01 Nieka) - 59 0.6 W E-01 Nickel - 63 0.5 4.88E-01 Eine - 65 68.5 7.45E+01 49.8 2.50E+00 carbon - 14 0.1 1.08F-01 0.2 1.01E-02 Casium - 137 0.2 2.36E-01 Carium - 144 0.5 4.70E-01 (1)
Volumes are measured, activities are estimated O
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HOPE CREEK GENERATING STATION TABLE 3 (CONT'D)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1989 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 3.
Solid Waste Disposition
)
Number of Mode of Type of j
Shipments Transportation Destination containerq
]
17 Truck
- Barnwell, South Carolina All Type A i
4.
IRRADIATED FUEL SHIPMENT 8 (Disposition)
Number of Mode of shipments Trananortation Destination None N/A N/A i
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TABLE 4A EFFLUENT AND NASTE DISPOSAL SENIANNUAL REPORT
.7ULY - DECEMBER 1989 1
SUMMARY
SNEET FOR RADI0 ACTIVE EFFLUENTS RELEASED
.IN A BATCH NODE
.)
RhT 5 R5LEhEES ONLY 1.
Dates:-
July 1 - September 30, 1989 2
2.
Type of releaset Gas i
3.
Number:of. releases during the 3rd Quarter 2
4.
Total' time duration for all releases of type listed abovat 44217 minutes 5.
' Maximum duration for release'of type listed above 23997 minutes
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6.
Average duration for release of type listed above 22108 minutes L
7.
Minimun duration for release of type listed abovo:
L 20220 minutes f
f sv Average st:v.am flow (dilution flow) during the period of l
releasst H/A
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l i.
I b
o
- O 16
.~,<=*m.,-
-,.--v-.----
-~.--e,-
--w
.,,,,~-w-.-
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---m-
--m
+
~
g6*
w y.9 g; 3 y.
- y. g,s y e :; g n a
.e
<,.g.
.y,,.
(p 1;.,y
., p ;
y M;j
,:n 4
,/
,.;7-,
t.<
i
, t.
g&
6 --
p g.
m
.50PE CREEK GENERATING STATION 1
TABLE 4A (CONT'D) l i
. EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT l
JULY - DECEMBER 1989 i
SU3BEARY FREET FOR RADI0 ACTIVE EFFLUENTS RELEASED
- IN A RATCH NODE
~
-j i
4 RhTCH BELE&sES QMLY j
t, 1.
Dates: '
October 1 - December 31, 1989 i
2.-
Type of release:
Gas 3.
Number of releases during the 3rd Quarter: 1 l
4.
Total time duration for all releases of type listed above:
10110 minutes 5.
Maximum duration for release of type listed above 10110 minutes
(:.,)
l 6.
Average duration for release of type listed above:
i 10110 minutes i
7.
Minimum duration for release of type Aisted above:
10100 minutes 8.
Average atream flow (dilution flow) during the period of release:
N/A b
17
-~
b~
~
Tc 'I??'lY _
..]
' >(jflhff}{$j'Qf l;;:Y}yW$!
'Y f '.
. ~ m g. g y);, bf., y. "
L,.'
s q
- .y -
+
(u.. f
< :9 y
- ( u
((
'["
w.
1 e
d'
.,.gopg CREEK GENERATING STATION l
~
N ;
TABLE 43 l
d EFFLUENT AND FASTE DISPOSAL SENIANNUAL REPORT JULY - DECEMBER 1989' 4'"I "' SUISIARY SMEET FOR RADI0 ACTIVE EFFLUENTS RELEASED IN A_ BATCH NODE w...
+,
/
r 3,,
i akTCM RELEASES GRILY
)
1.
' Dates:
' July 1 - % cember 30, 1989 2.
Type of release:
Liquid I
3.
Number of releases during the 3rd Quarter 106 4.
Total time duration for all releases of type. listed above
.22119 minutes
]
5.
Maximum duration for release of type listed above 539 minutes (n.
V)..
6.
Average duration for release of type listed above:
209' minutes (L
7.
Minimum duration for release of type listed abovet 63 minutes 8.
Average stream flow (dilution flow) during the period ol' l
re! ease 35664 gpm i
i t
b b
18
y G
~ ~ ^ T ^^
~d.~+-l.
l p ' ::J. ;.;,
ny.ppmp: g% w wy, Jn,
.c v
m;, 7 y 4.
1-1
, r.
j
,s
,.c *~, y
.'5
,. O
- - l' -
ti
.p.
,,/y.y, a f e 1
+
s e
/. y -,.
-t f
.p
+
NOPE CREEK GENERATING STATION TABLE 4B (CONT'D)
J EFFIDENT AND WASTE DISPOSAL SEN: ANNUAL REPORT JULY - DECENBER 1989
" SUISEARY SHEET FOR RADI0 ACTIVE EFFIDENTS RELEASED
~
.s
[
. ic
.IN A RATCH NODE 1
~p, f
1 4
4 4
J EkTCK EELEARER_0RLY t
1. Dates:-
' October 1 - December 31, 1989 2.-
Type of release:
Liquid 1
-3.
Number of releases during the 3rd Quader:
105 4.
Total time duration for all releases of type listed above 18135 minutes 5.
Maximum duration for release of type listed above
( ')-
562 minutes
.~,
6.
' Average duration for release of type listed above t
173 minutes 7.
Mi.ttimum duration for release of type listed above l
36 minutes 3.
Average stream flow (dilution flow) during the period of f
release: 27900 gym i
b i
i t
4 t
19
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'~
~~ ^ ^~
.t 6;
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, <** J q +.*g ; g. -v
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"r-t i
7~
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Of Aftsm0RIC StatiLiff CL408 ex:
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\\
Of Aftelm ERIC STABILITY CLA08 Wie 300 FT LAPat tatti 1.6 TO 1.5 OtG C/10m 00LTATi(3003Ff)
CLAa8 C i
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- 9/09 J0!NT Distal 0 Wilms F Vie DIRECTIGI as 7000 i
If Afer4RIC Sf40!LifY CLA08 Vl8Eh 300 FT LAP 3E Raft
+1.4 70 -0.5 DEG C/1mPt CELf4 Ti (300 377)
CLA30 0 l
l Wie spest gePS (spel) 0.00.5
' O.6 3.5 3.6 7.5 T.6 12.5 18.4 10.5 10.'6 24.5 0( 24.6
$ W PERCBNT DIARCflei seePenCENT SWI PORCINT SW4 P9hCONf SUN PghCONT SWI PERCBNT SWI PGACINT SWI P(RCONT
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0.1 12 0.6 16 0.8
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0.1 23 1.1 60 2.4 16 0.0 It -
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TAaLE 5 PAGE (5 0F 9) l u
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CLASEt 1
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1.
0 1 ' /-.E
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+
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0.3 1
0.0 76 3.6 set -
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TABLE 5 PAGEl(6 OF 9) 1
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CLASS 7
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Liuuid 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 4.07E-01 arem.
The
' calculated highest organ dose from liquid' releases was 9.18E-01
' area to the liver.
The calculated population total body dose was 4.98E+00 person-rem.
The calculated average total body dose to.
the population within fifty miles of'the site was 8.34E-04 area / person..
Air Pathways The resulting total body and skin doses to an individual were calculated to be 4.35E-02 area and 9.48E-02 arem respectively.
The calculated highest organ dose due to radioiodines and particulates with a greater than eight day half-life was 2.35E-04 mram to the thyroid.
The calculated population total body dose was 6.64E-01 person-rem.
The calculated average total body dose to the population within fifty miles of the site was 1.11E-04
(
mram/ person.
\\
Direction Radiation
,s kL'3 Direct radiation may be estimated by Thermoluminescent dosimetric (TII) 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.
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 4.0 mrads/ 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 the nearest resident is 3.5 miles away.
It can thus be concluded that there is no measurable dose to any offsite location from direct radiation.
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 1989 in Tables 5 and 6.
O 7
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b HOPE CREEK GENERATING STATION TABLE 2A
- '; EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY JUNE 1989
. LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1st 2nd Units Quarter Quarter Est. Total ;
Error %
A.
Flaalon and activation nroducta
- l. Total release (not including tritium.'annes. alnha) (1)
Ci 1.39E-01 2.10E-01 25 L
.2. Average diluted concentration durina naried uci/ml 2.99E-07 2.78E-07
- 3. Percent of applicable limit (T.S. 3.11.1.2.fa))
1.38E+01 2.71E+01 B. Tritium
- 1. Total relaama ci 2.74E+00 6.30E+00 25 N
- 2. Average diluted concentration
. -b durina naried uci/ml 5.91E-06 8.37E-06
)' -M-
- 3. Percent of applicable limit I
(T.S. 3.11.1.1) 4 1.95E-01 2.76E r1
(;
l.
C.
Diamolved and entrained noble casas
- 1. Total relamma ci 3.44E-04 1.26E-03 25
- 2. Average diluted concentration I
relmana nariod uC1/mi 7.41E-10 1.67E-09 3.
Parcant of annlicable limit (T.S. 3.11.1.1) 3.71E-04 8.35E-04 i
D. Gro== alnha activity
- 1. Total relamme (2)
Ci 0.00E+00 0.00E+00 E. Volume of. waste release - (prior to dilution - Batch Relaama) liters 2.74E+06 4.69E+06 F. Volume of dilution water used durina antire nariod liters 4.64E+08 7.55E+08 (1)
Fe-55, Sr-89 and Sr-90 analyses for the fourth quarter are not available for inclusion in this report.
(2)
Gross Alpha analyses for the second quarter are not available for inclusion in this report.
20
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.i HOPE CREEK GENERATING STATION 1
l TABLE 2B EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT
. JANUARY - JUNE 1989 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE let 2nd 1st 2nd
)
l Nuclides Released Unit Quarter Quarter Quarter Quarter i
.Antimenv-125 Ci 5.82E-05 I
Cobalt-58 Ci 4.40E-03 1.57E-03 Cobalt-60 Ci -
4.61E-03 5.33E-03 chennium-51 Ci 1.87E-02 5.66E-02 Cesium-137 Ci 1.80E-07 3.17E-05 Iron-55 Ci 4.93E-03 4.41E-02 Iron-59 Ci 3.47E-03 4.77E-03 Iodine-131 Ci 1.33E-05 Manaaname-54 Ci 1.21E-02 1.66E-02 Silver-110m-Ci 2.41E-05 1.48E-05 Sodium-24 Ci 8.06E-03 1.76E-05 Strontaum-90 Ci 3.01E-05 StrontLum-92 Ci 8.22E-06 1.40E-05 Technetium-99m Ci 8.55E-05 1.44E-05 Zine-65 Ci 8.21E-02 8.08E-02 TOTATA Ci 1.39E-01 2.10E-01 H-3 Ci 2.74E+00 6.30E+00 Xenon-133 Ci 3.41E-05 1.09E-04 Xenon-135 Ci 3.10E-04 1.15E-03 O
21
.