ML20205F322
| ML20205F322 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/30/1985 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| RERR-18, NUDOCS 8511050316 | |
| Download: ML20205F322 (50) | |
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1985 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT RERR-18 SALEM GENERATING STITION l
The Energy People UNIT 1 DOCKET NO. 50-272 l
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' UNIT 2 DOCKET NO. 50-311 OPERATING LICENSE NO. DPR-70 OPE RATING LICENSE NO. DPR-75 I
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UNIT NOS. 1& 2 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1985 I
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SALEM, GENERATING STATION Public Service Electric and Gas Company
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I SALEM GENERATING STATION UNIT NOS. 1 AND 2 I
RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 1985 TO JUNE 30, 1985 I
INTRODUCTION This report, RERR-18, summarizes the releases of radioactive I
materials in liquid, gaseous and solid form from the Salem Generating Station Units 1 and 2 for the period January 1, 1985 to June 30, 1985.
I The report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Specification 5.6.1.2 of the Salem Environmental Technical Specifications.
Preceding the I
tables summarizing the gaseous and liquid discharges and solid waste shipments is our response to parts A-F of the
" Supplemental Information" section of the Regulatory Guide I
1.21, Appendix B.
As required by Regulatory Guide 1.21, our Technical Spec-ification limits are described in detail within this report I-along with a summary description of how measurements and ap-proximations of the total activity discharged were developed.
To facilitate determination of compliance with 40CFR190 re-quirements, the following information on electrical output is provided.
Unit 1 generated 4,717,899 megawatt-hours of electrical energy (net) during the reporting period.
Unit 2 generated 1,364,471 megawatt-hours of electrical energy (net) during the reporting period.
Results of liquid and gaseous composites analyzed for Sr 89 and Sr 90 for the first half of 1985 were not available fo r inclusion in this report.
The results of these composites b
will be provided in the next Radioactive Effluent Release l
Report.
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.he Sr 89 and Sr 90 analyses for she last quarter of 1984 (refer to RERR-17) have been completed and the results were below our detection limit.
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M P79 43/33 3-gs I
I EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT RERR 18 Part A.
PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 Regulatory Limits We are required to summarize our regulatory limits in each report.
Symbols utilized in the equations listed below under Sections 1.1 and 1.2 are the same as those used in the Salem Environmental Technical Specifications (ETS).
The symbol 0 as explained in Section 2.3.3 of the ETS is the release rate of the gaseous activity in units of curies per second.
The K, L, M and N terms are actually site dependent dose conversion factors.
The equations listed below in Sec-tions 1.1 and 1.2 take into consideration the release point location, building wake eff ects and physical characteristics of the radionuclides released.
l In addition 40CFR190 regulations require that the annual dose equivalent does not exceed 25 mrem to the whole body or 9
any organ (except the thyroid which is limited to 75 mrem).
1.1 Fission and Activation Gases Release Limits a)
Gaseous releases frca the nuclear units are limited such that at no time will releases of gaseous radioactive materials cause a member of the general public to be exposed to an annual dose rate in excess of 500 mrem to the entire body or 3 rem to the skin in conformance with the requirements of 10CFR20.
b)
Gaseous releases f rom the units are further restricted such that when releases are averaged over a calendar quarter no member of the general public will be exposed to an annual dose rate in excess of 20 millirads of gamma radiation or 40 millirads of beta radiation.
c)
In addition, it is required that air doses averaged over a twelve month period be less than 40 and 80 millirads for gamma and beta radiation respectively.
We use the following equations to demonstrate compliance with these limits:
2.0 O v*K 1 1 t
v
+ 1.1 Ny) f1 0.33 O v*(L t
v 1
M P80 17 18/l I
t When averaged over a calendar quarter the release
- rate for radioactive gases must satisfy the following equation.
The I
basis for these equations is 10CFR50 Appendix I.
13 O v*Nv i1 t
6.3 O v*Evi1 t
I The limiting Unit I release limit 0 is calculated to be 5.95E+04 and 5.92E+04 microcuries/sec. for the 1st and 2nd quarters respectively.
The limiting Unit 2 release limit 0 is calculated to be 5.92E+04 and 5.92E+04 microcuries/sec for the 1st and 2nd quarters respectively.
When averaged over any twelve consecutive month period, the release rate for radioactive gases must satisfy the following I
equation.
The basis for this equation is 10CFR50 Appendix I.
25 O v*5vi1 t
13 O v*Evi1 t
The release limits of radioactive gases for the Salem Nuclear Generating Station are not fixed numbers, but depend upon the radioactive isotopes present in the effluent.
1.2 Iodine and Particulates, Half Life > 8 days The regulatory limits for iodines and particulates are listed below.
The release rates of iodine and particulates are restricted such that no member of the general public will receive a dose at a rate in excess of 1.5 rem /yr. to the thyroid.
Releases of iodines and particulates are further restricted to prevent any member of the general public from receiving a dose rate in excess of 30 mrem in a calendar quarter or 60 mrem in I
any twelve month period.
The equations which govern these conditions are listed below:
I At any instant of time the release rate for radioactive iodines and particulates material with a half life greater l
than 8 days is limited by the equation below.
The basis for this equation is 10CFR20.
I (1.5 x 105) Oy 11 M P80 20 06/1 lI
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During any calendar quarter the release limit is governed by the equations listed below.
The basis for these equations is 10CFR50 Appendix I.
2 curies of I-131 and Oy x 13 x (1.5 x 105) i 1 I
During any twelve month period radioactive releases should conform to the following constraints of 10CFR50 Appendix I.
25 x (1.5 x 105) x Oy 11 and 4 curies of I-131 1.3 Liquid Effluents Release Limits We are not permitted to discharge radioactive liquids such that we exceed the values in 10CFR20, Appendix B, Table II, Column 2.
In addition, the following limits apply:
The cumulative release of radioactive effluents, excluding tritium and dissolved gases, shall be less than 10 Ci in a calendar quarter for each unit.
The cumulative release of radioactive effluents, excluding tritium and dissolved gases, shall be less than 20 Ci in any twelve consecutive months for each unit.
2.0 Maximum Permissible Concentrations (MPC)
I Regulatory Guide 1.21 requires that the licensee provide the
[
MPC's used in determining allowable release rates for radio-active releases.
l a)
MPC values were not used to determine the maximum re-lease rates for fission gases, iodines, or g
particulates.
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MPC values as stated in 10CR20, Appendix B, Table 11, l
Column 2 were used for liquids.
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M P80 20 06/2 W
3.0 Average Energy Regulatory Guide 1.21 requires that the licensee provide the I
average energy of the radionuclide mixture in releases of fission and activation gases, if applicable.
Release limits for the SNGS are not based upon average energy, hence, this section does not apply.
4.0 Measurements and Approximation of Total Radioactivity 4.1 Liquid effluents are monitored in accordance with Table 2.3-3 of the Environmental Technical Specifications.
I During the period of record, all wastes from the chemical drain tank and the laundry and hot shower tanks were
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routed to the hold-up tanks for monitoring prior to re-I lease.
Technical Specifications require these tanks to be recirculated the equivalent of two tank volumes to produce uniform mixing before sampling and analyzsis be-3 fore any releases are made.
Batch releases are defined g
as releases from the waste monitor tanks, waste monitor hold-up tank, and the chemical and volume control tanks.
Continuous liquid releases are defined as condentate I
releases from intermittent blowdown of the steam gen-e ra to rs.
The predominate gamma emitting isotopes detected in sampling were CoS8, Co60, and Mn54.
Specific activity from analyses were mutiplied by the volume of I
effluent discharged to the environment in order to esti-mate the total liquid activity discharged.
I 4.2 Gaseous effluent streams are monitored and sampled in accordance with Table 2.3-4 of the Environmental Tech-nical Specifications.
The plant vent is the final re-lease point of all planned gaseous effluents and is I
continuous monitored by beta scintillators and high range GM tubes.
The vent is also continuously sampled for iodine and particulates with a charcoal cartridge and I
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.
I Sampling is also performed on all gas decay tanks and containment purges, prior to their release to the en-vironment.
The plant vent is sampled for noble gases monthly.
The detection requirements of Table 2.3-2 of the ETS are achieved or exceeded.
Isotopes existing at concentra-I tions below the achieved detection limit are not treated as being present.
I M P80 19 11 I L
Continuous Mode gaseous releases are quantif ied by rou-tine (monthly or weekly) sampling and isotopic analyses of the plant vent.
Specific activities for each isotope detected are raultiplied by the total vent flow vclume for 3
the entire sampling period in order to es timate the normal continuous release of radioactivity through the plant vent if any exis ts.
Batch Mode releases are quantified by the sample of each gas decay tank or containment purge prior to discharge.
l Specific activities for each isotope are multiplied by 5
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 mooa releases.
If specific activity data from grab samples taken while the release was in progress is not E
available, then the abnormal release will be quantified E
by the use of the plant vent radiation monitors.
The monitors response is converted in a " specific activity" g
using his torical ef ficiency f actors.
The " specific g
activity" is multiplied by the volume of ef fluent discharged while the channel was in an alarm state in order to estimate the total activity discharged.
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M P80 19 11 2 Sa I
I 4.3 The estimated total error of the reported continuous gaseous releases is within 50% when concentrations ex-ceed detectable levels.
This error is due primarily to I
variability of waste stream flow rates and changes in isotopic distributions of waste streams between sampling periods.
The estimated total error of the reported batch gaseous releases is within 10%.
Error estimates for continuous releases where sample activity is below the detectable concentration levels I
are not included since error estimates at the LLD are not defined.
I The estimated total error of reported liquid releases is within 25%.
5.0 Batch Releases Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A-1 and 4B-1 for Unit 1 and 4A-2 and 4B-2 for Unit 2.
6.0 Unplanned Releases During this reporting period there were no unplanned releases.
7.0 Elevated R-16 Channel Responses During tnis reporting period, some gas decay tank samples did not yield valid results.
As a result, some I
gas decay tank release estimates were based upon our radiation monitoring instrumentation.
We conserva-tively treated these releases as unidentified fission gases.
8.0 Modification to Previous Radioactive Effluent Release Reports Our last report RERR-17 did not include the quarterly Sr-89 and Sr-90 conposite data for the last quarter of I
1984.
Results were below the detection capability of our instruments.
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I M P80 18 05/1 I I
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Part B. Gaseous Effluents See Summary Tables lA-1 thru 1C-1 representative of Salem Unit 1 operations.
See summary Tables lA-2 thru 1C-2 representative of Salem Unit 2 operations.
Part C.
Liquid Effluents See Summary Tables 2A-1 and 2B-1 representative of Salem l
Unit 1 operations.
See Summary Tables 2A-2 and 2B-2 representative of Salem Unit 2 operations.
Part D.
Solid Waste See Summary Table 3 Units 1 and 2 I
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E M P82 3 07/3 I
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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 spe-cific data 1.e.,
food production, milk production, feed I
for milch animals and seafood production.
The doses were calculated using methods described in Reg-I ulatory Guide 1.109 and represent calculations for the six month reporting interval.
Doses from batch and continuous releases were calculated using the meteorological disper-sion coef ficient X/O for the six month reporting interval.
Liquid Pathways I
Doses to individuals in the population from liquid re-leases are primarily from the seafood ingestion pathway.
The total body dose to an individual was calculated to be g
1.34E-02 mrem.
The highest organ dose f rom liquid 3
releases was 9.33E-02 mrem to the gastrointestinal tract.
Th-calculated population total body dose was 3.26E-01 pe lon-rem.
I Air Pathways I
The resulting whole body and skin doses to an individual were calculated to be 2.67E-04 mrem and 4.55E-04 mrem respectively.
The calculated population total body dose was 1.09E-01 person-rem.
The average total body dose to I
the population within fifty miles of the site was 2.04E-05 rem / person.
Direct Radiation Direct radiation may be estimated by TLD measurements.
One method for comparing TLD measurements is by comparison I
with preoperational data.
TLD's at onsite locations 2S2 and SS1 which are 0.3 miles I
and 0.9 miles from the reactor containment, averaged 4.9 and 4.65 mrads/ month respectively.
The values for stations 2S1 and SS1 are within the statistical variation associated with the preoperation program results.
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I M P80 17 14 I
I All offsite monitoring locations remained within preopera-tional ranges.
It should be noted that the nearest resi-dent is 3.5 miles away.
It can thus be concluded that there was no measurable dose to any of f site locations from E
direct rad ia t io n.
E Part F.
Meteorological Data Cumulative joint wind frequency distribution by atmes-pheric stability class at the 300 foot elevation is pro-vided for the first and second quarters of 1985 as Tables 5 and 6.
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M M. W TABLE lA-1 EFFLUENT AND tJASTE DISPOSAL SEMIANNUAL REPORT (1985)
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT 1 1st 2nd Est. Total (l)
Units Quarter Quarter Error %
A.
Fission & Activation Gases 1.
Total release Ci 3.31E+01 1.09E+02 2.50E+01 2.
Average release rate for period uCi/sec.
4.26E+00 1.39E+01 3.
Percent of technical specification limit 7.15E-03 2.34E-U2 (See ETS Spec. 2.3.3.b)
B.
Iodines l.
Total iodine-131 Ci 6.46E-05 3.63E-05 2.50E+01 2.
Average release rate for period uCi/sec.
8.31E-06 4.62E-06 3.
Percent of technical specification (2Ci) limit 3.23E-03 1.82E-03 C.
Particulates 1.
Particulates with half-lives > 8 days Ci 2.50E+01 2.
Average release rate for period uCi/sec.
3.
Percent of technical specification limit S
4.
Gross alpha radioactivity (2)
Ci 0.00E+00 0.00E+00 5.00E+01 D.
Tritium 1.
Total release Ci 2.87E+00 1.06E+01 2.50E+01 2.
Average release rate for period uCi/sec.
3.69E-01 5.78E+00 3.
Percent of technical specification limit N/A N/A (1)
For batch releases the estimated overall error is within 10%.
(2)
Analyses indicate no me.asurable alpha emitting transuranics.
MP85 27/03 3-db 9-A
TABLE lA-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT 2 1st 2nd Est. Total (l)'
Unit Ouarter Quarter Error %
A.
Pission & Activation Gases 1.
Total release Ci 8.19E-03 2.34E+02 2.50E+01 2.
Average release rate for period uCi/sec.
1.05E-03 2.44E+01 3.
Percent of technical specification limit 1.78E-06 4.13E-02 (See ETS Spec. 2.3.3.b)
B.
Iodines 1.
Total iodine-131 Ci 4.14E-06 2.50E+01 2.
Average release rate for period uCi/sec.
5.27E-07 3.
Percent of technical specification limit 2.07E-04 C.
Particulates 1.
Particulates with half-lives > 8 days Ci 3.87E-04 4.43E-07 2.50E+01 2.
Average release rate for period uCi/sec.
4.98E-05 5.64E-08 3.
Percent of technical specification limit 9.70E-03 1.10E-05 4.
Gross alpha radioactivity (2)
Ci 0.00E+00 0.00E+00 D.
Tritium 1.
Total release Ci 2.34E+00 5.76E+00 2.
Average release rate for period uCi/sec.
3.01E-01 7.33E-01 3.
Percent of technical specification limit N/A N/A (1)
For batch releases the estimated overall error is within 10%.
(2)
Analyses indicate no measurable alpha emitting transuranics.
MP85 27/03 4-db 9-B
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TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985 UNITS 1 AND 2 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES I
I Nuclides Releases Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter I
All gaseous discharges fran the Salem Generating Station are sumnarized in Table 1B.
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I 1 I M P80 18 05/3 I l
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TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)
UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES lst 2nd Units Quarter Quarter Est.' Total Error, %
A. Fission and activation products
- 1. Total release (not including tritium, gases, alpha)
Ci 5.24E-01 4.40E-01 2.50E+01
- 2. Average diluted concentration g
during period uCi/ml 5.14E-09 2.40E-09 3
- 3. Percent of applicable limits of Technical Specifications
%5.24E+00 4.40E+00 B. Tritium
- 1. Total release Ci 3.64E+02 1.90E+02 2.50E+01
- 2. Average diluted concentration during period uCi/ml 3.57E-06 1.04E-06
- 3. Percent of applicable limit N/A N/A C. Dissolved and entrained gases
- 1. Total release Ci 2.91E-01 1.98E-01 2.50E+01
- 2. Average diluted concentration during period uCi/ml 2.85E-09 1.08E-09
- 3. Percent of applicable limit N/A N/A D. Gross alpha radioactivity
- 1. Total release Ci 0.00R+00 0.00E+00 2.50E+01 E. Volume of waste release (prior to dilution - Batch Release) liters 3.12E+06 2.88E+06 2.50E+01 F. Volume of dilution water used 3
during period - Batch Release liters 1.02E+11 1.83E+11 2.50E+01 5
N/A - Not Applicable I
I M P81 3 07/2 13-A I
I I
TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)
UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES lst 2nd Units Quarter Quarter Est. Total Error, %
l A. Fission and activation products
- 1. Total release (not including tritium, gases, alpha)
Ci 5.24E-01 4.40E-01 2.50E+01 I_
- 2. Average diluted concentration during period uCi/ml 5.14E-09 2.40E-09 3 Percent of applicable limits of Technical Specifications
%5.24E+00 4.40E+00 I. Tritium
_ S
- 1. Total release Ci 3.64E+02 1.90E+02 2.50E+01 8
- 2. Average diluted concentration during period uCi/ml 3.57E-06 1.04E-06
- 3. Percent of applicable limit N/A N/A B
. Dissolved and entrained gases C
- 1. Total release Ci 2.91E-01 1.98E-01 2.50E+01 1
- 2. Average diluted concentration during period uCi/ml 2.85E-09 1.08E-09
- 3. Percent of applicable limit N/A N/A D. Gross alpha radioactivity
- 1. Total release Ci 0.00E+00 0.00E+00 2.50E+01 IE.Volumeofwasterelease(prior to dilution - Batch Release) liters 3.12E+06 2.88E+06 2.50E+01 I F. Volume of dilution water used during period - Batch Release liters 1.02E+11 1.83E+11 2.50E+01
/A - Not Applicable I
I M P81 3 07/2 13-A I
\\
I TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)
UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES lst 2nd Units Quarter Quarter Est. Total Error, %
A.
Fission and activation products 1.
Total release (not including tritium, gases, alpha)
Ci 6.14E-01 3.40E-01 2.50E+01
- 2. Average diluted concentration E
during period uCi/ml 6.02E-09 1.85E-09 3
3.
Percent of applicable limits of Technical Specifications 6.14E+00 3.40E+00 B. Tritium
- 1. Total release Ci 6.40E+01 5.58E+01 2.50E+01
- 2. Average diluted concentration g
during period uCi/ml 6.27E-07 3.05E-07 5
3.
Percent of applicable limit N/A N/A C. Dissolved and entrained gases
- 1. Total release Ci 6.90E-03 1.90E-01 2.50E+01
- 2. Average diluted concentration during period uCi/ml 6.76E-ll 1.04E-09 3.
Percent of applicable limit N/A N/A D. Gross alpha radioactivity
- 1. Total release Ci 0.00E+00 0.00E+00 2.50E+01 E. Volume of waste release (prior to dilution - Batch Release) liters 2.31E+06 2.33E+06 F. Volume of dilution water used 3
during entire period liters 1.02E+11 1.83E+11 2.50E+01 g
N/A - Not Applicablo I
I M P81 3 07/1-srd 13-8 I
I TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)
LIQUID EFFLUENTS UNIT 1 I
CONTINUOUS MODE BATCH MODE INuclidesReleased lst 2nd 1st 2nd Unit Quarter Quarter Quarter Quarter Strontium-85 Ci Strontium-89 Ci Strontium-90 Ci I
Sodium-24 Fluorine-18 Ci Ci 2.08E-04 4.57E-03 Chromium-51 Ci 1.85E-02 Ci 1.75E-02 2.20E-02 I
Manganese-54 Iron-59 Ci Cobalt-57 Ci 1.17E-04 Cobalt-58 Ci 1.24E-01 4.86E-02 I
Cobalt-60 Ci 2.95E-01 2.57E-01 Zinc-65 Ci 7.40E-04 i
Zirconium-95 Ci 1.15E-03 9.91E-04 I
Niobium-95 Ci 6.llE-03 3.48E-03 NioDium-97 Ci 9.51E-04 6.25E-03 Molybdenum-99 Ci Technetium-99M Ci Iodine-131 Ci 1.19E-02 1.21E-02 Iodine-133 Ci 1.62E-03 1.11E-02 Iodine-135 Ci I
Cesium-134 Ci 1.61E-02 2.47E-02 Cesium -137 Ci 2.79E-02 4.76E-02 Barium-140 Ci Lanthanum-140 Ci I
Antimony-122 Ci 6.22E-04 9.72E-04 Antimony-124 Ci 1.50E-03 1.12E-03 Antimony-125 Ci I
Tin-ll3 Ci Total for period (above)
Ci 5.24E-01 4.40E-01 Ci 3.64E+01 1.90E+02 I
Tritium Xenon-133 Ci 2.91E-03 1.94E-01 Xenon-135 Ci 3.49E-03 Krypton-85m Ci Argon-41 Ci I
M P84 33/04 3-srd 14-A I
I TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)
LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE -
1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter S tront ium-89 Ci g
Strontium-90 Ci g
Sodium-22 Ci 3.96E-02 Sodium-24 Ci 2.54E-04 7.95E-04 l
Chromium-51 Ci 1.56E-02 1.22E-03 Manganese-54 Ci 2.09E-02 2.00E-02
- Iron-59 Ci Cobalt-57 Ci 5.70E-04 g
Cobalt-58 Ci 1.68E-01 3.70E-02 3 Cobalt-60 Ci 3.06E-01 1.78E-01 Zinc-65 Ci 6.62E-04 g
Zinc-69r.
Ci 3.69E-02 5 Zirconium-95 Ci 2.51E-03 9.69E-04 Niobium-95 Ci 8.15E-03 3.44E-03 Niobium-97 Ci 5.18E-04 5.18E-03 g Molybdenum-99 Ci 5
Technetium-99M Ci 5.53E-03 5.43E-03 E Iodine-131 Ci g
Iodine-132 Ci 2.73E-04 3.26E-03 o_
Iodine-133 Ci Iodine-134 Ci Iodine-135 Ci E
Cesium-134 Ci 1.64E-02 1.55E-02 W Cesium-137 Ci 2.77E-02 3.19E-02 Zirconium-97 Ci g
Barium-140 Ci g
Lanthanum-140 Ci Tungsten-187 Ci Antimony-122 Ci 9.10E-04 4.42E-04 Antimony-124 Ci 7.78E-04 3.91E-04 Antimony-125 Ci Tin-113 Ci Total for period (above)
Ci 6.14E-01 3.40E-01 Tritium Ci 6.40E+01 5.58E+01 Xenon-133m CL
~
Xenon-133 Ci 6.30E-03 1.89E-01 Xenon-135 Ci 7.44E-04 Krypton-85 Ci Argon-41 Ci M P84 33/08-cag 14-B I
l I
TABLE 3 I
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985 JANUARY 1, 1985 - JUNE 30, 1985 UNITS 1 AND 2
)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS I
A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
I 6-month Est. Total 1.
Type of waste Units Period Error, %
I a.
Spent resins, filters sludges, m3 2.42E+01 evaporator bottoms Ci 1.36E+03 1.50E+01 b.
Dry compressible waste, m3 2.98EF02 contaminated equip.
Ci 4.18E+00 1.50E+01 Irr.idiated components, m3 0.00E+00 v.
control rods, Ci 0.00E+00 d.
Others (describe) m3 0.00E+00 0.00E+01 Ci 0.00E+00 I
2.
Estimate of major nuclide composition (for type A and B waste)
Type A Type B (Ci)
(Ci)
I Manganese - 34 1.09%
1.48E+01 1.46E-02 Iron - 55 4.48%
6.08E+01 1.87E-01 Cobalt - 57
.23%
3.12E+00 1.00E-02 Cobalt - 58 64.00%
8.69E+02 2.68E+00 I
Cobalt - 60 13.30%
1.80E+02 5.56E-01 Nickel - 63 5.57%
7.56E+01 2.32E Tritium - 3
.86%
1.17E+01 3.60E-02 I
Carbon - 14
.02%
2.70E-01 1.00E-03 Strontium - 90
.02%
2.70E-01 1.00E-03 Technetium - 99
.02%
2.70E-01 1.00E-03 Cesium - 134 2.43%
3.30E+01 1.02E-01 I
Cesium - 137 2.51%
3.41E+01 1.05E-01 Cerium - 144
.07%
9.50E-01 3.00E-03_
Lanthanum - 140 2.78%
3.77E-01 1.16E-01 I
Barium - 140 2.44%
3.31E+01 1.02E-01 Plutonium - 241
.11%
1.49E+00 5,00E-03
~
0.07%
9.50E-01 3.00E-03 I-129, Pu-238, 239, Pu-240 I
Am-241, Cm-242, Cm-243, and Cm-244 P85 20/05 1-mw
-15A-I
. I TABLE 3 (Continued)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985 JANUARY 1, 1985 - JUNE 30, 1984 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 3.
Solid Waste Disposition Number of Shipments Mode of Transportation Destination 8
Truck
- Barnwell, South Carolina 8
Truck Hanford, Wash.
B.
IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination None N/A N/A I
I; 5.
I I
I I
I M P85 20/05 2-mw
-15B-
,I
r I
I TABLE 4A-1 S ALEM GENERATING STATION (1985)
I UNIT 1
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED I
IN A BATCH MODE BATCH RELEASES ONLY 1.
Dates January 1 - March 31, 1985 2.
Type of release (Gas) 3.
Number of releases during the 1st Quarter 4.00E+01 4.
Total time duration for all releases of type listed above 3.72E+02 minutes 5.
Maximum duration for releases of type listed above 1.02E+02 minutes 6.
Average duration for all releases of type listed above 9.30E+01 minutes 7.
Minimum duration for release of type listed above 8.80E+01 minutes 8.
For liquid batch releases only, provide the average stream flow (dilution flow) duri ng the period of release.
N/A I
I.
I I
I I-M P80 15 30/1-gs 16-A
.I, a
I I
TABLE -4A-2 I
SALEM GENERATING STATION (1985)
UNIT 2
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1.
Dates January 1 - March 31, 1985 2.
Type of release (Gas) 3.
Number of releases during the 1st Quarter 1.80E+01 4.
Total time duration for all releases of type listed above 2.70E+04 minutes 5.
Maximum duration for releases of type listed above 1.41E+04 g
minutes g
6.
Average duration for all releases of type listed above 1.50E+03 minutes 7.
Minimum duration for release of type listed above 5.30E+01 g
minutes 3
8.
For liquid batch releases only, provide the average stream g
flow (dilution flow) during the period of rele ase.
N/A g
I I
I I
I I
M P80 15 4 2/1-g s 16-B I
I TABLE 4A-1 (Cont'd)
SALEM GENERATING STATION (1985)
UNIT 1
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE I
BATCH RELEASES ONLY 1.
Dates April 1 - June 30, 1985 2.
Type of release (Gas) 3.
Number of releases during the 2nd Quarter 1.40E+01 4.
Total time duration for all releases of type listed above 1.30E+03 minutes 5.
Maximum duration for releases of type listed above 1.20E+02 minutes I
6.
Average duration for all releases of type listed above 9.30E+01 minutes 7.
Minimum duration for release of type listed above 7.80E+01 minutes 8.
For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release.
N/A I
I I
I I
I M P80 15 30 1/2-gs 17-A I
\\'
\\
. I TABLE 4A-2 (Cont'd)
S ALEM GENERATING STATION (1985)
UNIT 2
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1.
Dates April 1 - June 30, 1985 2.
Type of release (Gas) 3.
Number of releases during the 2nd Quarter 1.80E+01 4.
Total time duration for all releases of type listed above 5.31E+03 minutes 5.
Maximum duration for releases of type listed above 2.99E+03 minutes 6.
Average duration for all releases of type listed above 2.95E+02 minutes 7.
Minimum duration for release of type listed above 9.60E+01 minutes 8.
For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release.
N/A I
I l
I i
I I
I M P80 15 44/1 17-B I
I I
TABLt: 4B-1 SALEM GENERATING STATION (1985)
UNIT 1
SUMMARY
SHEET FOR RADIOACTIVE OFFLUENTS RELEASED IN A BATCH MCDE I
BATCH RELEASES ONLY 1.
Dates January 1 - March 31, 1985 2.
Type of release (Liquid) 3.
Number of releases during the 1st Quarter 5.00E+01 4.
Total time duration for all releases of type listed above I
1.15E+04 minutes 1
5.
Maximum duration for releases of type listed above 2.88E+02 minutes 6.
Average duration for all releases of type listeo above I
2.35E+02 minutes I
7.
Minimum duration for release of type listed above 2.04E+02 minutes 8.
For liquid batch releases only, provide the average stream I
flow (dilution flow) during the period of release.
1.85E+05 gpm I
I I
I I
I M P81 3 06/1-mw 18-A I
I I
TABLE 4B-2 SALEM GENERATING STATION (1985)
UNIT 2
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1.
Dates January 1 - March 31, 1985 2.
Type of release (Liquid) 3.
11 umber of releases during the 1st Quarter 3.80E+01 4.
Total time duration for all releases of type listed above 7.64E+03 minutes 5.
Maximum duration for releases of type listed above 3.59E+02 minutes 6.
Average duration for all releases of type listed above 2.07E+02 minutes 7.
Minimum duration for release of type listed above 7.60E+01 minutes 8.
For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release.
1.85E+05 g
gpm W
I I
I I
I M P81 3 06/2-mw 18-B
~
g'r
- #A
.I TABLE 4B-1 (Cont'd)
SALEM GENERATING STATION (1985)
UNIT 1
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY I
1.
Dates April 1 - June 30, 1985 2.
Type of release (Liquid) 3.
Number of releases during the 2nd Quarter 3.80E+01 4.
Total time duration for all releases of type listed above 9.42E+03 minutes 5.
Maximum duration for releases of type listed above 5.65E+02 minutes 6.
Average duration for all releases 2.sf type listed above 2.48E+02 minutes 7.
Minimum duration for release of type listed above 1.85E+02 minutes 8.
For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release 1.85E+05 gpm I
I I
I I
M P81 3 05/1-mw 19-A I
I
I TABLE 4B-1 (Cont'd)
SALEM GENERATING STATICN (1985)
UNIT 2 I
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE I
BATCH RELEASES ONLY 1.
Dates April 1 - June 30, 1985 2.
Type of release (Liquid) 3.
Number of releases during the 2nd Quarter 3.80E+01 4.
Total time duration for all releases of type listed above 3
7.75E+03 g
minutes 5.
Maximum duration for releases of type listed above 2.44E+0';
l minutes a
6.
Average duration for all releases of type listed above 5
2.09E+02 g
minutes 7.
Minimum duration for release of type listed above 1.33E+02 minutes 8.
For liquid batch releases only, provide the average stream g
flow (dilution flow) during the period of release 1.85E+05 g
gpm I
1 l
l I
l I
l M P81 3 05/2-mw 19-B I
I
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I t
ORTIFICIAL I$ LAND 4/85-(/8%
JOINT CISTatuuTION OF WIND DIRECTION AND SPEED LOCATION 300FT DEG C/100M LAPSE RATE (300-30FT)
-1.4/ -0.5 class D l
SPEEDS (MI/HR) 1-1 4-7 8-12 13-18 19-24 25 PLUS SUM PERCENT DIRECTION SUM PERCENT Sbi PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT I
N 0
0.0 3
0.2 8
0.4 9
0.5 8
3.4 5
0.1 33 1.7 NNE 1
0.1 5
0.1 7
0.4 0.4 0
0.0 3
- 0. 2 24 1.2 NE O
0.0 3
0.2 15 0.8 9
0.5 7
J.4 0
0.0 14 1.7 ENE O
0.0 4
0.2 15 0.3 13 0.7 1
0.1 0
0.0 33 1.7 E
O 0.0 7
0.4 12 0.6 6
0.3 2
0.1 0
0.0 27 1.4 l
ESE 1
0.1 2
0.1 7
0.4 1
0.1 1
0.1 0
0.0 12 0.6 SE 3
0.0 1
0.1 2
0.1 9
0.5 2
0.1 1
0.1 15 0.9 ssE 1
0.1 4
0.2 4
0.2 17 0.9 11 J.0 1
0.1 38 1.9 5
1 0.1 4
0.2 8
0.4 15 0.8 10 0.5 0
0.0 IS 1.9 SSW 2
0.1 5
0.1 12 0.6 9
0.5 8
0.4 1
0.1 37 1.9 SW 0
0.0 3
0.2 12 0.6 9
0.5 9
0.5 1
0.2 36 1.S l
Wsw 0
0.0 0
0.0 12 0.6 10 0.5 7
0.4 1
0.1 30 1.5 W
0 0.0 1
0.1 15 0.8 17 0.9 16 0.8 7
0.4 56 2.3 WNW 0
0.0 6
0.3 4
0.2 12 0.6 13 0.7 2
0.1 17 1.9 NW 2
0.1 0
0.0 1
0.4 9
0.5 3
0.2 1
0.2 25 1.3 NNW 0
0.0 1
0.1 3
0.2 1
0.1 0
0.0 1
0.1 6
0.3 6
0.4 47 2.5 144 7.3 154
- 7. 9 98 5.0 29 1.4 4 e1 24.4 CE AN WIND $ PEED 14.5 CALM HOURS 1
l PECCENT CALM 0.1 MISSING 44 TABLE 5 4 of 8
t
\\
ORTIFICIAL !$ LAND 4/85-6/95 J0!NT DISTRIeuTICN OF WIND DIRfCTION AND SPEED LOCATION 300FT OEG C/100P LAPSE R4TE 5
(300-30FT)
-0.4/
1.5 CLASS E SPEEDS (PI/HR) 1-3 4-7 8-12 13-13 19-24 25 PLUS SUM PERCENT 030ECT10N SUM PERCENT Sui PE4 CENT SUM PERffNT SUM PERCENT SUM P E R C E fe i SUM PERCENT N
O 0.0 3
0.2 7
0.4 9
0.5 17 J.9 5
0.4 44 2.2 NNE D
0.0 2
0.1 6
0.3 8
0.4 2
9.1 1
3.1 19 1.0 NE 2
0.1 10 0.5 10 0.5 18 1.9 8
J.4 0
0.0 48 2.4 ENE 1
0.1 1
0.4 12 0.6 17 3.9 4
0.2 0
0.3 41 2.1 E
2 0.1 6
0.3 25 1.3 4
0.2 1
0.1 0
0.0 38 1.9 ESE 2
0.1 6
0.3 3
0.2 1
0.1 2
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0.0 14 0.7 SE O
0.0 4
0.2 14 0.7 14 0.7 9
0.5 8
0.4 49 2.5 SSE D
0.0 7
0.4 13 0.7 13 0.9 12 0.6 3
0.2 53 2.7 5
3 0.2 7
0.4 21 1.1 16 0.9 25
- 1. 3 7
0.4 41 4.1 SSd 1
0.1 7
0.4 16 0.$
21 1.1 33 1.7 7
0.4 35 4.3 SW 3
0.2 5
0.3 21 1.1 36 1.8 23 1.2 3
0.2 91 4.s WSW 0
0.0 2
0.1 8
0.4 to 0.8 7
0.4 2
0.1 35 1,8 W
4 0.2 4
0.2 10 0.5 28 1.4 20 1.0 1
0.1 67 3.4 WNW 0
0.0 4
0.2 to 0.8 31 1.9 15 0.3 1
0.1 74 3.s NW 5
0.3 6
0.3 19 1.0 23 1.2 10 0.5 6
0.3 69 3.5 NNd 1
0.1 4
0.2 12 0.6 6
0.3 4
0.2 2
0.1 29 1.5 24 1.2 P4 4.3 213 10.8 274 13.9 193 9.3 44 2.5 137 42.5 MEAN WIND SPEED 14.6 CALM HOURS 0
DERCENT CALM 0.0 MISSING 65 i
l TABLE 6 5 of 8 e
I
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-_____-__..___.______.__________________.-_--_______--.--____-_._-____-__________-_____.________.__--___-__________O
M M
M M
M I
I ARTIFICIAL ISLAND 4/85*6/85 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED LOCATION 300FT DEG C/100M LAPSE RATE I
(300-30FT)
ALL STABILITIES SPEEDS (P!/HR) 1-3 4-7 6-12 13-18 19-24 25 PLUS SUM PERCENT DIRECTION SUM PERCENT SU9 PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SU9 PERCENT g
N O
0.0 17 0.9 26 1.3 46 2.5 39 1.9 15 0.8 142 7.2 NNE 2
0.1 10 0.5 19 1.0 23 1.2 4
0.2 4
0.2 61 3.1 NE 2
0.1 19 1.0 28 1.4 29 1.5 15 0.d 0
0.0 93 4.7 ENE 1
0.1 16 0.8 38 1.9 31 1.6 7
0.4 0
0.0 93 4.7 E
2 0.1 15 0.8 45 2.3 11 0.6 3
0.2 0
0.0 76 3.9 i
ESE 4
0.2 9
0.5 15 0.8 3
0.2 3
0.2 0
0.0 34 1.7 SE 1
0.1 9
0.5 26 1.3 31 1.6 16 0.8 12 0.6 95 4.8 SSE 2
0.1 14 0.7 26 1.3 48 2.4 40 2.0 6
0.3 136 6.9 i
5 6
0.3 18 0.9 42 2.1 35 1.8 39 2.0 13 0.7 153 7.8 S$d 3
0.2 25 1.5 39 2.0 38 1.9 49 2.5 14 0.7 168 8.5 SW 5
0.3 26 1.3 57 2.9 61 3.1 37 1.9 11 0.6 197 10.0 WSW D
0.0 9
0.5 45 2.3 41 2.1 19 1.0 7
0.4 1 01 6.1 W
5 0.3 15 0.8 45 2.5 63 3.2 48 2.4 9
0.5 185 9.4 WNd 2
0.1 16 0.$
43 2.2 61 3.1 37 1.9 3
0.2 162 8.2 NW 5
0.4 10 0.5 43 2.2 42 2.1 23 1.2 14 0.7 140 7.1 NNW 1
0.1 24 1.2 35 1.5 31 1.6 17 0.9 3
0.2
'111 5.6 e
44 2.2 252 12.3 572 29.0 594 30.2 395 20.1 til 5.6 1968 99.9 MISSING HOU45 214 MEAN WIND SPEED 14.2 TOTAL NUMBER OF CALM HCURS 2 PERCENT 0.1 TABLE 6 8 of 8
C%
Public Service Electric and Gas Company Ctrbin A. McNeill, Jr.
Public Service Electric and Gas Company P.O. Box 236. Hancocks Bndge, NJ 08038 609 339-4800 Vice President -
Nuclear August 30, 1985 Dr.' Thomas S.
Murley, Administrator Region 1 U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Murley:
RADIOACTIVE EFFLUENT RELEASE REPORT RERR-18 SALEM GENERATING STATION DOCKET NO. 50-272 AND 50-311 As required by Section 6.9.1.11 of Appendix A of the Operating Licenses for the Salem Generating Station, Units No. 1 and 2, we hereby transmit two copies of the semi-annual Radioactive Effluent Release Report, RERR-18.
This report summarizes liquid and gaseous releases and solid waste shipments from the Salem Generating Station for the period January - June 1985.
Should you have any questions on this report, please contact us.
Sincerely, Attachment C
Director, Office of Inspection and Enforcement n.S. Nuclear Regulatory Commission c/o Distribution Services Branch, DDC, ADM Washington, D.C.
20555 Mr.-Donald C.
Fischer Licensing Project Manager Mr. T. J. Kenny Senior Resident Inspector j/
6>h
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