ML20247B320
| ML20247B320 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/30/1989 |
| From: | Miltenberger S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N89178, NUDOCS 8909120442 | |
| Download: ML20247B320 (58) | |
Text
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Puche Service
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Electric and Gas Company -
Cleven E. Miltenberger Public Service Electric and Gas Company P.O. box 236,14ancocks Bridge, NJ 08038 609-339-4199.
o vice Presdont and Chief Nuclear Othcor.
AUG 31 1989 NLR-N89178 '
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-United States Nuclear Regulatory Commission Document Control Desk Washington, DC '20555 P
Gentlemen:
RADIOACTIVE EFFLUENT RELEASE 1EPORT - 26 SALEM GENERATING STATION
= DOCKET NOS. 50-272 AND 50-311 In accordance with Section 6.9.1.11 of Appendix ~A to the Operating License for Salem Generating Station.(SGS), Public Servjae Electric and Gas' Company (PSE&G) hereby. transmits one
. cop! of the semi-annual Radioactive Effluent Release Report, RE!<R-2 6. - This-report summarizes liquid and gaseous releases and r,olid waste shipments from the Salem Generating Station for the
. period-January 1 through June 30, 1989.
Should you have any questions regarding this transmittal, please feel free to contact us.
Sincerely, Attachment (s)'
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' :'e RERR REPORT only y
. C Mr.
J.'C..Sto (1)
Licensing Proj Manager
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Ms. K. Halvey. Gi son- (1)'
. Senior.' Resident-Inspector i.
Mr. W. T. Russell, Administrator (2)
' Region I Mr. K. Tosch, ' Chief (1)
New Jersey' Department of Environmental Protection
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- Division of-Environmental Quality l
Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625-USNRC, Director (1)
Office of Nuclear Reactor Regulation Washington, DC 20555 i
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SALEM GENERATING STATION
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SEMIANNUAL RADIOACTIVE EETLUENT RELEASE REPOhT SGS RERR-26 SALEM UNIT NOS. 1'& 2 UNIT 1 UOCKET h0. 50-272 UNIT 2 DOCKET NO. 50-311 UPERATING LICENSE NO. LPR-70 OPERATING LICENSE NO. DPR-75 c.
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SEPTEMBER 1989 l
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UYu 70 (d
DPR 75 REPORT NO. SGS-RERR-26 UNIT NOS. 1& 2 l
KAD10 ACTIVE EFFLUENT RELEASE REPORT-l JANUARY - JUNE 1989 1
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l SALEM GENERATING STATION Public Service Electric and Gas Company i
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SALEM GENERATING STATION
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RADIOACTIVE EFFLUENT RELEAbE REPORT JANUARY - JUNE 1989 INTRODUCTION This report, SGS-RERR-26, summarizes the releases or radioactive materials in liquid, gaseous and solid form from the Salem Generating Station (SGS) Units 1 and 2 for the period January 1,
1969 to June 30, 1989.
The report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Specification 6.9.1.11 of the Salem 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 facilitate determination of compliance with 40CFR190 f-requirements, the following information on electrical output is provided.
Unit 1 generated 1,960,007 megawatt-hours of electrical energy (net) during the reporting period.
Unit 2 generated 3,715,566 megawatt-hours of electrical energy (net) during the reporting period, hesults of liquid and gaseous composites analyzed for Sr-89, Sr-90, and Fe-55 for the second quarter of 1989 were not available for inclusion in this report.
The results of these composites will be provided in the next Radioactive Etfluent Release Report.
l The Sr-89, Sr-90, and Fe-55 analyses tor the last half of 1988 (refer to RERK-25) have been completed, amended pages to RERR-25 are included in this report.
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Part.A.
PRELIMINARY SUPPLEMENTAL INFORMATION
D 1.0 REGULATORY LIMITS 1.1 hoble Gases Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following:
- ar noble gases:
Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin.
In addition, the air dose due to noble gases released in gaseous effluents, from 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 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, During any calendar year:
Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
l.2 Iodine, Particulate, and Tritium The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following:
For Iodine-131, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days:
Less than or equal to 1500 mrems/yr to any organ.
In addition, the dose to a member of the public from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the site boundary, shall be limited to the following:
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During any calendar quarter:
Less than or equal to 7.5 mrems to any organ and, During any calendar year:
Less than or equal to 15 mrems to any organ. u
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l.3.
Licuid Effluents Release Limits
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The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10CFR, Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble i
gases.
For dissolved or entrained noble gases, the l
concentration shall be limited to 2E-4 microcuries per i
mililiter.
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:
l During any calencar quarter to less than or equal to 1.5 mrems to the total body and to 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 than or equal to 10 mrems to any organ.
1.4 Total Dose Limit
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The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).
4 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)
Regulatory Guide'l.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 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.
c.
MPC value used for dissolved or entrained noble gases was 2E-4 microcuries per milliliter.
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b 96 3.0 ~ AVERAGE ENERGY Regulatory Guide l.21 requires that the' licensee provide the1 average energy of the radionucliae mixture in releases et fission and activation gases, if applicable.
Release limits.for.the SGS are not based upon average energy, hence, this section does not apply.
L 4.0 MEASUREMENTS AhD APPROXIMATION OF TOTAL RA BIOACTIVITY l
4.1..
Liquid etfluents are monitored in accordance with Table 4.11-l'of the Technical Specifications.
During-the period of record, all wastes from the chemical, drain tank and the laundry and hot shower tanks were routed to the hold-up tanks for monitoring prior to release.
Technical Specifications require these tanks to be uniformly mixed before sampling and analysis before any releases are made.
Batch releases are defined as releases from the waste monitor hold-up tank, and the chemical and volume control tanks.
Continuous liquid' releases are defined as condensate releaces from intermittent blowdown of the steam generators.
The preponderant gamma emitting isotopes detected in sampling were Co-58, Co-60, and Mn-54.
Specific activity from analyses were multiplied by the
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volume of effluent discharged to the environment in order to estimate the total liquid activity discharged.
4.2 Gaseous effluent streams are monitored and sampled in accordance with Table 4.11-2 of the Technical Specifications.
The plant vent is the final release point of all planned gaseous effluents and is continuously monitored by beta scintillator and high range GM tubes.
The vent is also continuously sampled for lodine and particulate with a charcoal cartridge and filter paper connected in series to a low volume air sampler.
The filter and charcoal are changed weekly, and analyzed on a multichannel analyzer in the laboratory.
Sampling is also performed on all gas decay tanks and containment purges prior to their release to the environment.
The plant vent is sampled for noble gases monthly.
The detection requirements of Tables 4.11-1 and 4.11-2 of the Technical Specifications are achieved or exceeded.
Isotopes existing at concentrations below the achieved detection limit are treated as not being present.
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l g'^g Continuous Mode gaseous releases are quantified by
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routine (monthly or weekly) sampling and isotopic analyses of the plant vent.
Specitic activities for each isotope detected are multiplied by the total vent flow volume for the entire sampling period in order to estimate the normal continuous release of l
radioactivity through the plant vent.
Slightly elevated plant vent radiation raonitor i
readings are treated as continuous releases.
The monitors response is converted to a " specific activity" using historical efficiency factors.
The
" specific activity" is multiplied by a default volume of effluent discharge to estimate the total activity discharged.
Batch Mode gaseous releases are quantified by sampling each gas decay tank or containment purge prior to discharge.
Specific activities for ecch isotope are multiplied by the total volume of gas discharged.
Elevated plant vent radiation monitoring system readings while the channel is in an alarm state are treated as batch mode releases.
If specitic activity data from grab samples taken while the release was in' progress is not available, then the abnormal release
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is quantified by the use of the plant vent radiation N -
monitors.
The monitor's response is converted to a
" specific activity" using historical efficiency tactors.
The " specific activity" is multiplied ny the volune of effluent discharged while the channel was in an alarm state in order to estimate the total activity discharged.
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 50% when concentrations exceed detectable levels.
This error is due primarily to variability of waste stream flow rates and changes in isotopic distributions of waste streams between sampling periods.
The estimated total error ot the reported batch gaseous releases is within 10%.
Error estimates for releases where sample activity is below the detectable concentration levels are not included since error estimates at the LLD are not defined.
The estimated total error of reported solid releases is within 25%.
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5.0.
BATCH ktLEASES 7,
k-Summaries ot batch releases of gaseous and liquid ettluents are provided in lables 4A-1 and 48-1 tor Unit 1 and 4A-2 i
and 4b-2 for Unit 2.
6.V UNFLAhNED nELEASES buring this reporting period tnere were no unplanneo releases.
1 7.0 ELLVATED R-16 CHANNtL xtSPONSES During this reporting period, the plant vent radiation monitor indicated slightly elevated readings on several i
occasions.
As indicated above, elevated K-16 readings were quantitied and treated as continuous releases.
It was assumed that they were Ae-133 since it is the preponderant isotope released.
They were thus included in Tables 16-1 and 18-2.
l 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE l
REPORTS Our last report (REkx-25) did not include the quarterly Sr-69, Sr-90, and Fe-55 composite data tor the last halt of fw 1969.
Amended pages to KbhR-25 are includea at the end ot l
this report.
y Part B.
GASEOUS EFFLUENTS See Summary Tables IA-1 thru iC for Salem Unit i uperations.
i See Summary Tables 1A-2 thru 1C tor Salem Unit 2 Operations.
Part C.
LIVUID EFFLUENT 6 i
See Summary tad 1es 2A-1 and 26-1 tor Salem Unit 1 Operations.
See dummary Tables 2A-2 and 2B-2 tor dalem Unit 2 Operations.
Part D.
SOLID WASTE See Summary in Table 3. t I
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Part E.
RADIOLOGICAL IMPACT'UN MAN N}
LThe calculated individual doses.in this section are based Hs/. :
on actual locations of nearby residents.and farms.
The population dose ~. impact is based on historical site specific datai1.e., food production, milk. production,-feed for milch animals and~ seafood production.
The' doses were calculated using metho's described in d
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 f rom liquid releases are primarily from the seafood ingestion pathway.- The
. total body dose to an individual was calculated.to be 1.52E-01 mrem.
The calculated highest organ dose from liquid releases-was 1.09E+00 mrem to the gastrointestinal tract.
The calculated population total body dose was 7.25E-02 person-rem.
The calculated average total' body dose to the population within fifty miles of the site was O-1.21E-05 mrem / person.
Air Pathways The resulting total body and skin doses to an individual were. calculated to be 2.15E-02 mrem and 4.85E-02 mrem respectively.
The calculated highest organ dose due to radiciodines and particulate with a greater than eight day half-live was 2.30E-02 mrem to the thyroid.
The calculated population total body dose was 4.97E-01 person-rem.
The calculated average total body dose to the population within fifty miles of the site was B.32E-05 mrem / person.
Direct Radiation Direct radiation may be estimated by Thermoluminescent dosimetric (TLD) measurements.
One method for comparing TLD measurements is by comparison with preoperational cata.
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 4.0 and 4.9 mrads/ month respectively.
The values for stations 2S-2 and SS-1 are within the statistical variation
_-O associated with the preoperational program results. _ - _ _ _ _ _ _ _ _ - -
lt should be noted that the nearest resident is 3.' an ies away.
It can thus be concluded that there was no I,,)
measurable dose to any offsite location,from direct
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radiation.
Part F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided tor tne tirst and second quarters or 1969 in Tables 5 and 6.
Part G.
INOPERABLE MUNITORS During the period of January 1, 1989 and June 30, 1989 there were three monitors inoperable that were not brought to operable status within 30 days.
Per Salem Technical Specification (T.S.) 3.3.3.8 an explanation of why the Inoperability was not corrected in a timely manner is given below:
Un December 10, 1988 the number 22 and 24 Steam Generator Blowdown Line flow indicators at Salem Unit 2 were declared inoperable.
On January 25, 1989 the monitors were declared operable arter being repaired.
The monitors were declared inoperable due to a condition of flow indication when tiow was not present.
The
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inoperability exceeded 30 days due to ditticulties in
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troubleshooting and repairs.
Although the inoperability occurred in 1966, the T.S.
3.3.3.8 requirement tor an explanation in the next semi-annual report atter 30 days of inoperability was not met until January 9, 1969.
Un March 13, 1989 the 24 Steam Generator Blowdown Line tiow meter was declared inoperable ~at Salem Unit 2.
The tiow nozzle for the tiow meter came loose and broke off.
As of June 30, 1989 the flow meter had not been repaired due to difficulties in obtaining a replacement tiow nozzle.
On April 24, 1989 the Salem Unit 2 R19 A through D Steam Generator Blowdown Monitors were declared inoperable.
The Unit 2 R19 A-D monitors were ceclared operable on June 1, 1989.
Unit 2 was in a scheduled retueling outage.
These monitors were declared inoperable because of work and tests being made on the Unit 2 Steam Generators which required periodic isolation of blowdown tiow to the R19 monitor.
When blowdown tiow is isolated to the K19 monitors they are inoperable.
Instead ot constantly declaring the R19 monitors operable and l
inoperable each time blowdown was isolated the monitors l
were declared inoperable during the entire cycle of the steam generator work.
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TABLE 1A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1989 UNIT 1 GASEOU6 EFFLUENTb-SUMMATION OF ALL PELEASES l
1st 2nd Units Quarter Vuarter Est. Total (.
Error %
A. Fission and Activation Gases
- 1. Total release Ci 4.97E+02 2.88E+02 25 2.
Average release rate for period uCi/sec. 6.33E+01 3.66E+01 3.
Percent or technical specification limit (T.E. 3.11.2.2(a))
3.67E-01 2.llE-01 B.
lodines
- 1. Total iodine-131 Ci 1.55E-03 1.62E-03
- 2. Average release rate tor period uCi/sec. 1.97E-04 2.06E-04 k/
g 3.
Percent or technical specification limit (2)
(T.S.
3.ll.2.3(a))
7.36E-02 7.77E-02 C.
Particulate 1.
Particulate with half-lives
> 8 cays Ci 9.75E-06 4.74E-05
- 2. Average release rate for period uCi/sec. 1.24E-06 6.03E-06
- 3. Percent of technical specification limit (2)
(T.S. 3.ll.2.3(a))
7.36E-02 7.77E-02 4.
Gross alpha radioactivity Ci 0.00E+00 D. Tritium
- 1. Total release Ci 2.55E+01 3.75E+01 2.
Average release rate for period uCi/sec. 3.24E+00 4.77E+00
- 3. Percent of technical specification limit (2)
(T.S. 3.11.2.3(a))
7.36E-02 7.77E-02 (1) For batch releases the estimated overall error is within 10%.
(2) Iodine, tritium, and particulate are treated as a group.
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TABLE lA-2 1
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1989 UNIT 2 j
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 1
l 1st 2nd Units Vuarter Quarter Est. Total (1 Error %
A.
Fission and Activation Gases
- 1. Total release Ci 5.52E+01 2.dSE+00 25
- 2. Average release rate tor period uCi/sec. 7.03E+00 3.62E-01 3.
Percent of technical l
specification limit l
(T.S.
3.11.2.2(a))
1.11E-01 2.30E-03 1
B.
- 1. Total iodine-131 Ci 3.71E-06 1.68E-05
- 2. Average release rate for period uCi/sec. 4.72E-07 2.14E-06 7s
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3.
Percent of technical
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specification limit (2)
(T.S. 3.11.2.3(a))
9.31E-04 3.02E-03 C. Particulate 1.
Particulate with halt-lives
>d days Ci 5.09E-05 1.32E-03
- 2. Average relcase rate for i
period uCi/sec. 6.47E-06 1.68E-04
- 3. Percent of-technical specification limit (2)
(T.S. 3.11.2.3(a))
9.31E-04 3.02E-03 4.
Gross alpha radioactivity Ci O.UOE+0V
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D. Tritium
- 1. Total release Ci 2.59E+01 7.82E+01 2.
Average release rate tor i
period uCi/sec. 3.29E+00 9.94E+00 3.
Percent of technical specification limit (2)
(T.S-3.ll.2.3(a))
9.31E-04 3.02E-03 (1) Fcr batch releases the estimated overall error is within 10%.
(2) Iodine, tritium, and particulate are treated as a group.
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(,y TABLE 1B-1 EFFLUENT AND WASTE DI;;'USAL SEMIANNUAL REPORT JANUARY - JUNE 1989 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 1 CONTINUUUS MODE BATCH MODE lst 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Vuarter 1.
bission Gases Krypton-65 Ci 8.99E-01 1.04E+00 Krypton-85m Ci 3.USE-02 1.64E-04 Krypton-68 Ci 1.36E-02 Xenon-131m Ci 3.92E-ul 4.30E-01 Xenon-133 Ci 4.59E+02 2.66E+02 3.51E+01 2.02E+01 Xenon-133m Ci 4.88E-01 9.36E-02 Xenon-135 Ci 9.3dE-01 9.33E-01 2.96E-02 Arcon-41 Ci 4.80E-03 Total for Perioc Ci 4.60E+02 2.66E+02 3.79E+ul 2.1dE+01
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2.
Iodines A
lodine-131 Ci 1.55E-03 1.62E-03 Total tor Period Ci 1.55E-03 1.62E-03
- 3. Particulate (half life >8 Days)
Ci Cobalt-58 Ci 3.18E-05 l
Cobalt-60 Ci 6.79E-06 1.23E-05 l
Cesium-134 Ci 4.64E-07 Cesium-137 Ci 2.96E-06 2.87E-06 Total tor Period Ci 9.75E-06 4.74E-05 1
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TABLE IB-2 g
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JAhUARY - JUNE 1989 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 2 l
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CONTINUOUS MODE BATCH MUDE lst 2nd 1st 2nd Nuclides Released Unit Vuarter Quarter Vuarter Quarter
- 1. Fission Gases Krypton-65 Ci 3.64E-02 9.99E-02 Krypton-85m Ci 5.42E-01 5.57E-03 8.88E-04 Krypton-60 Ci 1.06E+00 3.32L-03 Xenon-131m Ci 3.54E-02 2.08E-02 Xenon-133 Ci 2.78E+01 6.55E-01 1.85E+0U l.90E+00 Xenon-133m Ci 2.55E-02 3.36E-02 Xenon-135 C1 1.94E+01 1.36E-01 1.39E-U1 Xenon-135m Ci 4.31E+00 Argon-41 Ci 9.79E-04 (sv) Total for Period Ci 5.31E+01 6.55E-01 2.10E+00 2.19E+UO 2.
Iodines Iodine-131 Ci 3.71E-06 1.68E-05 Total for Period Ci 3.71E-06 1.68E-05 3.
Particulate (half life >8 Days)
Ci Chromium-51 Ci 2.76E-05 Manganese-54 Ci 1.13E-06 Cobalt-58 Ci 7.37E-06 3.82E-05 Cobalt-60 Ci 2.82E-05 2.84E-05 Niobium-95 Ci 7.38E-06 5.88E-04 Zirconium-95 Ci 6.19E-06 6.35E-04 CeLium-137 Ci 6.67E-07 4.63E-06 l
Gross Alpha Ci I
Total for Period Ci 5.09E-05 1.32E-06
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TABLE 1C
. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1989 UNITS 1 AND 2
~GASEQUS EFFLUENTS-GROUND-LEVEL RELEASES Nuclide Releases' 1st Vuarter 2nd Quarter 1st Quarter 2nd Quarter There were no ground level gaseous releases during this reporting period.
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TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JAhuARY - JUNE 1989 UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES lst 2nd Units Vuarter Quarter Est. Total Error, %
A.
Fissicn and activation products
- 1. Total release (not including tritium, gases, alpha)
Ci 5.53E-01 1.21E+00 25
- 2. Average diluted concentration during period uCi/ml 2.55E-08 1.23E-07 3.
Percent of applicable limit (T.S.'3.ll.l.2.(a))
2.42E+00 5.34E+00 B. Tritium
- 1. Total release Ci 2.27E2 5.03E+01 25
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- 2. Average diluted concentration
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during period uCi/ml 1.05E-5 5.llE-06 3.
Percent ot applicable limit (T.S. 3.11.1.1) 3.50E-1 1.70E-01 C.
Dissolved and entrained noble gases
- 1. Tota] release C1 3.85E-01 2.73E-02 25 2.
Average diluted concentration durina period uCi/ml 1.77E-08 2.77E-09 3.
Percent ot applicable limit j
(T.S. 3.11.1.1) 8.87E-03 1.39E-03
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D. Gross alpha radioactivity
- 1. Total release Ci O.00E+00 E.
Volume of waste release (prior to dilution - Batch Release) liters 4.94E6 2.56E6 l
F. Volume of oilution water used during entire period liters 2.17E10 9.85E9 O _ _ _ - _ _ _ _ _ _ _ _ - _ -
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TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1989 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1st 2nd Units Quarter Vuarter Est. Total Error, %
A.
Fission and activation products 1.
Total release (not including tritium, gases, alpha)
Ci 6.16E-01 1.53E+00 25
- 2. Average diluted concentration during period uCi/ml 7.09E-08 1.91E-07 3.
Percent of applicable limit (T.S. 3.ll.l.2.(a))
2.60E+00 1.14E+01 B. Tritium
- 1. Total release Ci 1.48E+02 5.98E+01 25
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- 2. Average dilutec concentration during period uCi/ml 1.71E-05 7.48E-06 3.
Pe rcent ot applicable limit (T.S. 3.11.1.1) 5.69E-01 2.49E-01 C.
Dissolved and entrained noble gases
- 1. Total release Ci 4.94E-01 1.93E-02 25 2.
Average diluted concentration durino period uCi/ml 5.69E-08 2.42E-09 3.
Percent of applicable limit (T.S. 3.11.1.1) 2.84E-02 1.21E-03 D. Gross alpha radioactivity
- 1. Total release Ci U. ode +00 0.00E+00 E. Volume of waste release (prior to dilution - Batch Release) liters 2.31E+06 2.62E+06 F.
Volume of dilution water used during entire period liters B.68E+09 8.00E+09 I
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TABLE 28-1 j
EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1989 I
l LIQUID EFFLUENTS UNIT 1
)
I i
CONTINUOUS MODE BATCH MODE j
I lst 2nd 1st 2nd
]
huclides heleased Unit Quarter Quarter Vuarter Quarter i
Strontium-89 Ci 7.32E-04 2.02E-04 Strontium-90 Ci 2.93E-04 0.10E-05 Fluorine-18 Ci 7.40E-02 1.99E-01 Sodium-24 Ci 4.BOE-05 Chromium-51 Ci 2.77E-03 Mancanese-54 Ci 1.11E-02 4.06L-02 Iron-55 C1 3.09E-02 8.77E-03 Iron-59 Ci
- 3. DOE-04 Cobalt-57 Ci 1.41E-03 2.43E-03 Cobalt-56 Ci 8.12E-U6 3.36E-01 6.00E-Ol CoDalt-60 Ci 5.33E-05 4.11E-02 6.25E-02 Zinc-65 Ci 5.21E-05 Zirconium-95 Ci 1.40E-04 hiobium-95 Ci 1.90E-04 5.60E-04 Niobium-95m Ci 7.15E-05 i
Technetium-99M Ci 9.58E-05 Silvet~'110m Ci 2.23E-04 1.05E-04 Iodine-131 Ci 2.72E-03 6.69E-03 4.22E-03 Iodine-133 Ci 9.13E-04 3.66E-04 3.38E-04 Cesium-134 Ci 1.36E-05 1.29E-02 2.76E-02 Cesium-136 Ci 1.60E-04 4.60E-05 Cesium-137 Ci 6.28E-05 1.37E-02 3.21E-02 Lanthanum-140 Ci 1.22E-04
~
Cerium-144 Ci 1.19E-04 Antimony-122 Ci 8.76E-04 2.58E-03 Antimony-124 Ci 2.7dE-03 6.13E-03 Antimony-125 Ci 1.57E-02 2.19E-02 Total for period (above)
Ci 3.77E-03 8.12E-06 5.50E-01 1.21E+00
~
Tritium Ci 8.90E+01 1.36E+02 5.03E+01 Xenon-131 Ci 3.09E-03 Xerson-13 3m C1 3.81E-03 Xenon-133 Ci 3.73E-ul 2.66E-u2 Xenon-135 Ci 4.846-03 5.15E-04 Kr-68 Ci 1.bzt-04 l
~
(
')
SALEM GENERATING STATION
\\,/
TABLE 2B-2 EttLUENT AND BASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1989 LlLUID ErFLUEhTS UNIT 2 CONTIhDOUS MODE BATCH MODE lst 2nd 1st 2nd Nuclices Released Unit Guarter vuarter vuarter vuarter Strontium-d9 Ci 7.40E-04 1.63E-04 Strontium-90 Ci 2.17E-04
/. 78E-05 riuorine-lb C1 1.93E-01 1.92E-U1 Sodium-24 Ci 1.02E-US Chromium-51 Ci 1.2dE-02 Manganese-54 Ci 1.17E-02 4.466-02 1ron-55 Ci 3.70E-U2 U.14E-03 1ron-59 Ci 1.60E-US 2.42E-03 Cobalt-57 Ci 1.03E-03 3.1dE-03 Cobalt-58 Ci 2.84E-01 9.79E-01 Cobalt-6U Ci 3.75E-02 9.02E-02 Zinc-65 Ci 4.33E-U5 S11ver-110m Ci 4.79E-05 5.08E-03
__ Niobium-95 Ci 4.68E-04 4.llE-03 Niobium-97 Ci 1.79E-05 3.74E-US Zirconium-95 Ci 1.74E-04 2.16E-03 Technetium-99M Ci 8.69E-05 lodine-131 Ci 1.17E-02 3.03E-03 lodine-133 Ci 3.51E-U4 6.7BE-04 Cerium-143 Ci 4.92E-US 3.14E-04 Ceriun-14%
Ci
~~
1.21E-02 5.96E-02 Cesium-134 C1 Eeslum-136 Ci 4.59E-04 Cesium-137 Ci 1.28E-02 6.45E-02 Lanthanum-140 Ci 3.38E-05 1.41E-04 Praseodymium-147 Ci 2.56E-04
_ Artimony-122 Ci 6.21E-04 2.90E-03 Antimony-124 Ci 1.5eE-U3 9.21L-U3 Antimony-125 Ci 9.73E-U3 4.13E-02 Total tor period (above)
C1 6.16E-01 1.53E+00 Tritium Ci 1.48E+02 5.96E+U1 Xenon-131m Ci 3.03E-03 Xenon-133m Ci 5.33E-03 Xenon-133 Ci 4.80E-Ul 1.65E-02 henon-135 Ci 5.40E-U3 7.901-U4 l
Krypton-88 Ci 6.97E-05
,. m
_ 1 u________._____
t
[..
I SALEM GENLKATING STATION
_,_s (v).
IAbLE J LrfLUENT AND hAb1E DISPUSAL dEM1 ANNUAL KtPORT JANUARY - JUNE 1989 UNIT 6 1 AND 2 SULiu WASTE AND 1RKADIATED FULL dn1PMENTS A.
dOLID HASTE SHIFPLD Uffb1TC YUR BURIAL UK DISPOSAL (Not arradiated tuel) b-month Est. Total 1.
Type of waste Units (l)
Period Error, 4 a.
bpent resins, r11ters, sivoges, m3 evaporator bottoms C1 b.
ury compressible waste, m3 contaminated equip.
Ci c.
Irradiated components, m3 1.05 control roos Ci 5.54E4 2$
c.
Uthers toescribe) m3 Ci 2.
Estimate ot major nuclide composition (tor type A and 8 waste)
Irradiated Components DAW
(^}
tt)
(C1)
(%)
(Ci)
's j Manganese - 54 3.b 1.96E+03 1ron - bb b4.1 J.b4E+04 Coba6t - bd 0.4 z.44t+02 Cobalt - bu 26.4 1.b7t+U4 64 2.3 1.27E+0J Nickel Tritium - 3 1.2 6.5btt02 Carbon - 14
~
Strontium - 90 Antimony -12b Cesium - 144 Ceslum - 147 Cerium - 194 Plutonium - 241 (1)
Volumes are measured, activities are estimated O _
SALEM GENERAT1hG bTAT10N
(^'
TABLE 3 x.j (CUhT'U) trTLUENT AND WAdTE UlSPOSAL -6LM1 ANNUAL KEPUhT JANUARY - JUNE 1989 UNIT 6 1 AND 2 bOLID WASTE AND 1RRADIATED t'UEL bHJ PMENTS 3.
Solic Waste Disposition humber of Mode of Typ2.or 6hipments Transportation destination Lontainers 5
Truck
- Barnwell, bouth Carolina All Type A B.
IRRADIATED FUEL Sh1PMENTE (Disposition)
Number of Shipments Mode or Transportation Destination im I,
None h/A N/A l
C ll Y) i !
Ql&
[
U.
b.
p.
SALEM GENERATING STATION (71 TABLE 4A-1
~.
?
EFFLUENT AND.WAbTE DISPOSAL SEMIANNUAL REPORT L
JAhUARY - JUNE 1989
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED j
IN A BATCH MODE I
UNIT 1 BATCH RELEASES ONLY l
1.
Dates:
January 1 - March 31, 1989 L
'2.
Type of release:
Gas 3.
Number of releases during the 1st Quarter:
14 4.
Total time duration for all releases of type listed ab7ver 1.28E+04 minutes 5.
Maximum duration for releases of type listed above:
6.42E+03 minutes 6.
Average duration for all releases of type listed above:
(
9.17E+02 minutes
\\
7.
Minimum duration for release of type listed above:
6.50E+01 minutes 8.
Average stream flow (dilution flow) during the period of release:
N/A _ _ _ _ _ _
1' l
l' l
/'%)
SALEM GEhERATING STATION L (_,/
TABLE 4A-1 (CONT'D)
EFFLUENT AND i<!ASTE DIbPOSAL SEMIAhNUAL hEPORT JI.NUARY - JUNE 1989
SUMMARY
SHEET iOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 l
l PATCH RELLASES Ot<LY 1.
Dates:
April 1 - June 30, 1989 2.
Type of release Gas 3.
Number of releases during the 2nd Quarter:
33 4.
Total time duration for all releases ot type listed above:
4.47E+04 minutes 3.
Maximum duration for releases of type listed above 1.41E+04 minutes
[
6.
Average duration for all releases of type listed above:
\\-
1.35E+03 minutes 7.
Minimu:a duration for release of type listed above:
5.00e+00 minutes 8.
Average stream flow (dilution flow) during the period of release :
N/A
!k J
i l _ - - - _ -
c&c _
y up E
- i. V-f'f/'N
. SALEM. GENERATING STATION
- .N
' TABLE '4A-2' L
EFFLUENT. AND WASTE' DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1989 n.
SUMMARY
' SHEET FOR-RADIOACTIVE EFFLUENTS RELEASED IN A BATCH-HUDE UNIT 2 s ;..
'e l
BATCH RELEASES ONLY
. 1.. Dates:. January Ic-LMarch 31, 1989' l
2.
Type of E-release :
Gas L
3.
. Number of releases.during'the 1st Quarter:
15'
. 4..: Total time duEation for.all. releases of type listed above:
1.40E+03. minutes 1
. 5.
-Maximum duration for releases of, type listed above:
1.22E+02. minutes' 6.
O-
, Average duration for.a11' releases of type listed above:
9.32E+01 minutes Minimum duration for release of type listed above:-
7..
1.20E+01 minutes 8.
' Average stream flow (dilution flow) during the period of release:
N/A.
W 4
L-1 L.
I mm,
.m_.._._____._m__-_-m.__.-m-______m____
w : 7",
a
'l U
_(C J. ;,
i
-w 3 <
..v
'[~'i SALEM GENERATING-STATION 1
(d_/
TABLE.'4A-2 l
(CONT'D)
{
/ EFFLUENT'AND WASTE DISPOSAL. SEMIANNUAL ~ REPORT JANUARY - JUNE 1989-
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED
'IN A: BATCH NODE UNIT 2 i
BATCH RELEASES'UNLY I
-1.
Dates:
April 1
-1 June 30, 1989 2.
-Type'of release:
Gas n
.3.
Number of releases during the 2nd Quarter:
18 4.
Total' time duration for'all. releases of type listed above:
1.94E+03 minutes 5.
' Maximum' duration for. releases of' type listed above:
1.27E+02 minutes.
^
r'N :
- (
-6.
LAverage duration for allfreleases of. type. listed above:
1~.08E+02 minutes.
-7.
Minimum duration for release of type. listed above:
6.50E+01 minutes 8..
Average stream' flow (dilution flow) during the period of release:
N/A 5
s t
3 SALEM GENERATING STATION
^
T j TABLE 4B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1989
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UhlT 1 BATCH RELEASES ONLY
'1.
Dates:
January 1 - March 31, 1989 2.
Type of release:
Liquid 3.
Number of releases during the 1st Quarter:
40 4.
Total time duration for ali re,tefases of type listed abeve:
9.36E+3 minutes 5.
Maximum duration'for releases of type. listed above:
3.96E+2 minutes 6.
Average duration for all releases of type listed above:
,(,}
2.34E+2 minutes
(-
7.
Minimum duration for release of type listed abover 1.44E*2 minutes 8.
Average stream flow (dilution flow) during the period of release:
6.12E5 gpm l
-n
.1, -
i
,i t-1
' /"N-SALEM GENERATING STATION
' \\,
TABLE 48-1
,f:
(CONT'D)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1989
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1.
Dates:
April 1 - June 30, 1989 2.-
Type of release:
Liquid 3.
Number of releases during the 2nd Vuarter:
41 1
4.
Total time duration for all releases of type listed above:
1.01E+4 rinutes 5.
Maximum duration for releases of' type listed above:
4.41E+2 minutes
,m
't 6.
Average duration tor all releases of type listed above:
\\l 2.46E+2 minutes 7.
Minimum duration for release of type listed above:
1.67E+2 minutes 8.
Average stream flow (dilution flow) during the period of relea se :
2.58E5 gpm l'
i
\\ - - - _ _ _ _ _ _ _ _ _ _ _ - - _ - _
l M
l:
1 T(~N._,)
SALEM GENERATING STATION TABLE 4B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT' JANUARY - JUNE 1989
SUMMARY
SHEET FOR RADIOACTIVE EFFLUE7TS RELEASED i
IN A BATCH MODE l
UNIT 2
~ BATCH RELEASES ONLY 1.
Dates January 1 - March 31, 1989 2.
Type of release :
Liquid 3.-
Number of releases during the 1st Quarter:
38 4.
Total time duration for all releases of type listed above:
9.20E+3 minutes 5.
Maximum duration for releases of type listed above:
3.56E+2 minutes 6.
Average duration for all. releases of type listed above:
-s
(
)
2.42E+2 minutes
\\./
7.
Minimum duration for release of type listed above:
2.03E+2 minutes 8.
Average stream flow (dilution flow) during the period of release:
2.49E5 gpm pG.
i l (~')
SALEM GENERATING STATION (y
TABLE 4B-2 (CONT'D)
EFFLUENT AND' HASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1989
SUMMARY
6HEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1.
Dates:
April 1 - June 30, 1989 l*
2.
Type of.releace:
Liquid 3.
Number of releases during the 2nd Quarter:
33 4.
Tctal time duration for all releases of type listed above:
8.07E+3 minutes 5.
Maximum duration for releases of type listed above:
3.21E+2 minutes
.,m
(
I 6.
Average duration for all releases of type listed above:
5#
2.45E+2 m.inutes 7.
Minimum duration for release of type listed above:
2.03E+2 minutes l
8.
Average stream flow (dilution flow) during the period of release :
2.62E+5 i
I b
'~'
j
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Amended pages to RERK-25 l ^
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1 l
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i
l Part E.
RADIOLOGICAL IMPACT ON MAN
.,r 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 i.e.,
food production, milk production, feed for milch 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.
Licuid 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 1.23E-01 mrem.
The calculated highest organ dose from liquid releases was 6.87E-01 mrem to the gastrointestinal tract.
The calculated population total body dose was 2.63E+00 person-rem.
The calculated average total body f-dose to the population within fifty miles of the site was
('
4.41E-04 mrem /verson.
Air Pathways The resulting total body and skin doses to an individual were calculated to be 1.27E-02 mrem and 3.00E-02 mrem respectively.
The calculated highest organ dose due to radiciodines and particulate with a greater than eight day half-life was 2.64E-02 mrem to the thyroid.
The calculated population total body dose was 7.82E-01 person-rem.
The calculated average total body dose to the population within fifty miles of the site was 1.31E-04 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 L.iles and 0.9 miles from the point of origin, averaged 4.8
(]
and 4.3 mrads/ month respectively.
The values for stations
\\s,/
2S-2 and SS-1 are within the statistical variation associated with the preoperational program results.. _ _ _
l
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(_/
SALEM GEhERATING STATION TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1988 UNIT 1 LIVUID EFFLUENTS-SUMMATION OF ALL RELEASLS 3rd 4th Units Vuarter Vuarter Est. Total Error, %
A.
Fission and activation products 1.
Total release (not including tritium, cases, alptya)
Ci 7.32E-01 7.32E-01 25
- 2. Average diluted concentration during period uCi/ml 3.60E-08 9.07E-08 3.
Percent ot applicable limit (T.S. 3.11.1.2.(a))
t 3.32E+00 3.39E+00 JL. Tritium
- 1. Total release Ci 9.49E+01 4.69E+01 25 2.
Average diluted concentration during period uCi/m3 4.66E-06 5.8]E-06 3.
Percent ot applicable limit (T.S. 3.11.1.1) 1.5SE-01 1.94E-01 C. Dissolved and entrained noble gases
- 1. Total release Ci 2.55E+00 4.290-02 25
- 2. Average diluted concentration during period
_uCi/ml 1.26E-07 5.31E-09 J.
Percent of applicable limit t
(T.S. 3.11.1.1) 6.28E-02 2.65E-03 D. Gross alpha radioactivity
- 1. Total release Ci U.000+0V u.00E+00 E.
Volume of waste release (prior to dilution - Batch Release) liters 3.37E+06 2.00E+06 F. Volume of dilution water used during entire period liters 2.04E+10 8.07E+09 7.-
v _ _ _ _ _
e,
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$ALLM GLhERATING STATloh TABLE 2A-2 EFFLUENT AND HASTE DISPOSAL SEMI AhhtlAL REPORT JULY - DECEMBEk 19de Uh1T 2 LIvulD EFFLf'LNTS-SUMMATlutJ UF ALL RELEASES 3rd 4th Units vuarter Quarter Est. Total Error, %
A.
Fission and activation products
~
1.
Total release (not including tritium, gases, alpha)
Ci 9.86E-01 8.85E-01 25
- 2. Average diluted concentration during period uCi/ml 4.65E-09 9.910-08 3.
Percent or applicable limit (T.S. 3.11.1.2.(a))
3.81E+00 3.24E+00
- u. Tritium C1 1.29E+U2 4.JbE+01 25 1.
Total telease
- 2. Average dilutec concentration during period uCi/ml 6.08E-07 4.90E-06 J.
Percent of applicable limit t
(T.S. 3.11.1.1)
,2.03E-02 1.63E-01 C. Dissolved and entrained noble gases
- 1. Total release Ci 3.13E+00 1.09E-02 25
- 2. Average diluted concentration during period uCi/ml 1.47E-08 1.22E-09 3.
Percent of applicable limit t
(T.S. 3.11.1.1) 7.36E-03 6.09E-04 D. Gross alpha radioactivity
- 1. Total release Ci O.UUE+0V O.uut+00 25 E. Volur.ie of waste release (prior to dilution - Batch Release) liters 4.41E+07 1.81E+06 F.
Volume of dilution water used during entire period liters 2.13E+11 8.94E+09 i
i N_l l L_
l SALEM GENERATING STATION TABLE 2b-1
.s
)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT
(
JULY - DECEMBER 1988 UNIT 1 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Beryllium-7 Ci 1.02E-03
__ Fl','orine-18 Ci 4.61E-02 9.04E-02 Sodium-24 Ci 1.37E-03 2.BJE-04 Chromium-51 Ci 1.72E-03 Manganese-54 Ci 2.87E-02 3.37E-02 1ron-55 Ci 1.03E-01 1.88E-02 Iron-59 C1 1.42E-04 Cobalt-57 Ci 4.70E-04 4.46E-04 Cobalt-58 C1 2.85L-01 3.48E-ul Cobalt-60 Ci 6.83E-02 2.26E-02 Rubidium-Eu Ci 1.05E-03 Yittrium-Bo Ci 4.98E-05 Strontium-89 Ci
~.40E-03 3.68E-03 Strontium-90 Ci 7.61E-04 1.34E-03 Yittrium-93 Ci l 4bE-04 Zirconium-95 Ci 4.14E-04 1.llE-03 Niobium-95 Ci 1.28E-03 1.51E-03 Molybdenum-99 Ci 1.52E-03 Technetium-99M Ci 2.62E-03 3.48E-05 Technetium-104 Ci 9.48E-44 4.59E-05 Ruthenium-lO3 Ci 1.61E-03 Silv?r-110m Ci 6.53E-04 TinlI13 Ci 4.41E-05 Antimony-122 Ci 3.67E-03 1.62E-03 Antimony-124 Ci 3.29E-02 2.87E-02 Antimony-125 Ci 2.48E-02 3.87E-02
~
l Antimony-126 Ci 9.93E-05 Iodine-131 Ci 3.36E-02 3.34E-03 Iodine-132 Ci 3.84E-05 Te 111 t-i um-13 2 C1 1.62E-05 lodine-133 Ci 8.20E-03 6.33E-04
~~" Cesium-134 Ci 1.95E-02 2.6bE-02 Cesium-137 Ci 2.31E-02 2.85E-02 Cesium-138 Ci 2.18E-04 6.92E-02 barium-133 Ci 3.77E-04 Barium-140 C1 1.89E-04 Lanthanum-140 Ci 2.60E-04 1.lat-04 Lathanum-141 Ci 1.96E-03 5.79E-03 Cerium-141 Ci 2.49E-04 1.U8E-03 Cerium-144 Ci 3.50E-04 1.79E-03 Praseodymium-144 Ci 3.12E-02 Total for period (above)
Ci 7.32E-01 7.32L-01
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TABLE 2B-1 (CONT'D)
EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1988 UNIT 1 LIVUID EFFLUENTS CONTIhUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter guarter vuarter guarter Tritium Ci 9.49E+01 4.69E+01 Xenon-131m Ci 1.71E-02 xenon-133 Ci 2.45E+UO 4.18E-02
~~
Xenon-133m C1 3.54E-02 2.46E-04 Xenon-135 Ci 5.32E-02 6.82E-04 Krypton-8Sm Ci 5.34E-04 Krypton-88 Ci 2.74E-04
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TABLE 28-2 EFFLUENT AND WA5TE DISPOSAL dEMIANNUAL REPORT JUI.Y - DECEMBER 1988 LIQU3D EFFLUENTS UNIT 2 l
1 CONTIhDOUS MUDE BATCH MODE l
i I
3rd 4th 3rd 4th j
Nuclides Released Unit Uuarter Quarter Quarter Quarter i
j Beryllium-7 Ci 2.69E-03 Fluorine-ld Ci 2.25E-03 4.330-02 1.JUE-01 Sodium-24 Ci 3.12E-03 4.52E-05 Chromium-51 Ci 1.02E-03 1.22E-03 Manganese-54 Ci 3.24E-02 3.77E-02 Manganese-56 Ci 1.93E-03 1ron-55 C1 2.58E-02 1.826-03 1.89E-01 3.63E-02 Iron-d9 Ci 2.93E-US Cobalt-57 Ci 7.89E-04 1.04E-03 Cobalt-56 Ci 3.v7E-04 2.55E-01 d.50E-OT Cobalt-60 Ci 5.08E-04 7.30E-02 2.72E-02 Rubidium-66 C1 2.64E-U3 Yttrium-88 Ci 8.42E-05 Strontium-89 C1 1.18E-03 3.UdE-04 8.54E-03 6.50E-03 Strontium-90 Ci 1.23E-04 1.34E-04 8.888-04 2.63E-03 Yttrium-93 Ci 1.45E-04 Zirconium-95 Ci 7.22E-04 2.98E-04 1.18E-U3 i
hiobium-95 Ci 7.UUE-U4 6.66E-U4 1.62E-03 Niobium-95a Ci 1.10E-04 Technetium-99M Ci 2.66E-03 Technetium-101 Ci 7.79E-05 Ruthenium-103 Ci 7.76E-05 1.29E-03 Ruthenium-lu5 Ci 6.47E-05 bilver-110m Ci 6.bbt-04 Tin-ll3 Ci 8.29E-US Antimony-122 Ci 2.10E-03 1.60E-03 Antimony-124 Ci 3.07E-02 2.11E-02 Antimony-125 Ci 2.600-02 2.94E-02 Tellurium-132 Ci 1.48E-04 Barium-133 Ci 2.60E-U4 Barium-140 Ci 8.33E-04 locine-131 Ci 2.12E-02 6.15E-02 5.35E-03 Iodine-132 Ci 2.98E-02 8.32E-US locine-131 Ci 3.82L-02 1.41E-02 3.UlE-US lodine-134 Ci 1.70E-02 Iodine-135 Ci 1.03E-02 8.02E-04 Cesium-134 Ci 2.31E-03 3.90E-05 2.91E-02 2.06E-02 Ceslum-136 Ci 2.3eE-04 6.93E-04 Cesium-137 C1 2.61E-03 4.99E-05 2.48E-02 2.23E-02 Cesium-138 C1 8.77E-U3 3.04E-03 4.98L-04
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' s' TABLE 28-2 (CONT'D)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1988 LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE BNICH MODE
)
3rd 4th 3rd 4th Nuclides Released Unit guarter Quarter Vuarter Quarter Lanthanum-140 Ci 7.70E-04 2.62E-04 Lanthanum-141 Ci
- 1. 54 E-0 3 5.06E-04 Cerium-141 Ci 2.49E-04 1.49E-03 Cerium-144 C1 3.71E-04 1.39E-03 Neptunium-239 Ci 3.OBE-03 Total for period (above)
Ci 1.64E-01 2.35E-03 8.22E-01 8.83E-01 Tritium Ci 1.86E+01 2.88E+00 1.11E+02 4.09E+01 Xenon-133m Ci 3.73E-02 Xenon-133 Ci 5.50E-03 2.07E+00 1.09E-02 xenon-135 Ci 1.10E-03 6.01E-02 Xenon-131m Ci 2.09E-02 Krypton-85m Ci 1.08E-03 Krypton-86 Ci 6.63E-04 Xenon-135m Ci 1.35E-01 1.10E-04 i
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