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r.t/ O'lifbae"/?.;Slt$ REGTfV:.A"'rrm*v 1987 SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SGS RERH.-23 SALEM UNIT NOS. 1 & 2 ,. . UNIT 1.
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NO. .. *_. UN.IT 2 DOC'K-*E1" NO. 50-272 50-311 DPR-70 DPR-75 LICENSE NO. OPERATING LICENSE NO. ::.'.-' FEBRUARY 1988 *:*  
REGTfV:.A"'rrm*v ~~mi 1987 SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE 1
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PS~G EFFLUENT RELEASE REPORT SGS RERH.-23 SALEM UNIT NOS. 1 & 2 The Energy People UNIT 1. ~d-c'.i<ET.
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                                                          ,. .                          NO.         50-272
* 'I .. SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SGS RERk-23 SALEM UNIT NOS. 1 & 2 UNIT 1 DOCKET NO. 50-272 UNIT 2 DOCKET NO. 50-311 OPERATING LICENSE NO. DPR-70 OPERATING LICENSE NO. DPR-75 FEBRUARY 1988
                                                          .. *_. UN.IT 2 DOC'K-*E1" NO.         50-311
* REPORT NO. SGS-RERR-23 UNIT NOS. 1 & 2 RADIOACTIVE EFFLUENT RELEASE REPORT JULY -DECEMBER 1987 SALEM GENERATING STATION Public Service Electric and Gas Company DPR 70 DPR 75 INTRODUCTION SALEM GENERATING STATION RADI.OACTIVE Er'FLUENT RELEASE REPORT JULY -DECEMBER 1987 This report, SGS-RERR-23, summarizes the releases of radioactive materials in liquid, gaseous and solid form from the Salem Generating Station (SGS) Units 1 and 2 for the period July 1, 1987 to December 31, 1987. 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.
                                                              *~*OPERATING LICENSE       NO.         DPR-70 OPERATING LICENSE       NO.         DPR-75 I t
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 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.
                                                                                                                              'iI FEBRUARY 1988
To facilitate determination of with 40CFR190 ments, the following information on electrical output is provided.
__ - -~* *~ .
Unit 1 generated 2,469,593 megawatt-hours of electrical energy (net) during the reporting period. Unit 2 generated 2,067,375 megawatt-hours of electrical (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 1987 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 second quarter of 1987 (refer to RERR-22) have been completed; amended pages to I RERR-22 are included in this report.
                                                                                          *:* ~-2*:*_*~-
Part A. PRELIMINARY SUPPLEMENTAL INFORMATION


===1.0 REGULATORY===
SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SGS RERk-23 SALEM UNIT NOS. 1 & 2 UNIT 1 DOCKET  NO. 50-272 UNIT 2 DOCKET  NO. 50-311 OPERATING LICENSE  NO. DPR-70 OPERATING LICENSE  NO. DPR-75 FEBRUARY 1988
'I


LIMITS 1.1 Noble 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:
DPR 70 DPR 75 REPORT NO. SGS-RERR-23 UNIT NOS. 1 & 2 RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 SALEM GENERATING STATION Public Service Electric and Gas Company
For 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.
1.2 Iodine, Particulates, 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:
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.


===1.3 Liquid===
SALEM GENERATING STATION RADI.OACTIVE Er'FLUENT RELEASE REPORT JULY - DECEMBER 1987 INTRODUCTION This report, SGS-RERR-23, summarizes the releases of radioactive materials in liquid, gaseous and solid form from the Salem Generating Station (SGS) Units 1 and 2 for the period July 1, 1987 to December 31, 1987.
Effluents Release Limits The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in lOCFR, Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 microcuries per mililiter.
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 R~gulatory Guide 1.21, Appendix B.
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 1 imi ted: During any calendar 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 to 10 mrems to any organ. 1.4 Total Dose Limit The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and 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). 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) Regulatory Guide 1.21 requires that the licensee provide the MPC's used in determining allowable release rates for radioactive releases.  
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.
: a. MPC values were not used to determine the maximum release rates for fission gases, iodines, or particulates.  
To facilitate determination of 6omplia~ce with 40CFR190 require-ments, the following information on electrical output is provided.
: 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.
Unit 1 generated 2,469,593 megawatt-hours of electrical energy (net) during the reporting period.
I I 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.
Unit 2 generated 2,067,375 megawatt-hours of electrical  en~r~y (net) during the reporting period.
Release limits for the SGS are not based upon average energy, hence, this section does not apply._ 4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY  
Results of liquid and gaseous composites analyzed for Sr-89, Sr-90, and Fe-55 for the fourth quarter of 1987 were not available for inclusion in this report. The results of these composites will be provided in the next Radioactive Effluent Release.Report.
The Sr-89, Sr-90, and Fe-55 analyses for the second quarter of 1987 (refer to RERR-22) have been completed; amended pages to
.~ RERR-22 are included in this report.
Part A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0  REGULATORY LIMITS 1.1  Noble 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:
For 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.
1.2  Iodine, Particulates, 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:
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.
1.3   Liquid Effluents Release Limits 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 gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 microcuries per 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 1 imi ted:
During any calendar 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
                ~qual to 10 mrems to any organ.
1.4 Total Dose Limit The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and 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).
2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)
Regulatory Guide 1.21 requires that the licensee provide the MPC's used in determining allowable release rates for radioactive releases.
: a. MPC values were not used to determine the maximum release rates for fission gases, iodines, or particulates.
: 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.
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 the SGS 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 4.11-1 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 requir~ 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 liqLid releases are defined as condensate I          releases from intermittent blowdown of the steam generators. The preponderant gamma emitting isotopes detected in sampling were Co-58, Co-60, and Mn-54.
Specif1c activity from analyses were multiplied by the 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 scintillators and high range GM tubes. The vent is also continuously sampled for iodine and particulates 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.
Continuous Mode gaseous releases are quantified by routine (monthly or weekly) sampling and isotopic analyses of the plant vent. Specific 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 radioactivity t.hrough the plant vent.
Slightly elevated plant vent radiation monitor 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 gaseou~ releases are quantified by sampling each gas decay tank or containment purge prior to
* discharge. Specific activities for each isotope are multiplied by the total volume of gas discharged.
Elevated plant vent ra~*ation 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 while the release was in progress 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" using historical efficiency factors. The "specific activity" is multiplied by the volume 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 varia.bility 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 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%.


===4.1 Liquid===
5.0   BATCH RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A-l and 4B-l for Unit 1 and 4A-2 and 4B~2 for Unit 2.
effluents are monitored in accordance with Table 4.11-1 of the Technical Specifications.
6.0   UNPLANNED RELEASES During this reporting period there were no unplanned releases.
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 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 liqLid releases are defined as condensate releases from intermittent blowdown of the steam generators.
7.0   ELEVATED R-16 CHANNEL RESPONSES During this reporting period, the plant vent radiation monitor indicated slightly elevated readings on several occasions. As indicated above, .~levated R-16 readings were quantified and treated as contiriuous relea~es. It was assumed that they were Xe-133 since it is the preponderant isotope released. They were. thus included in Tables lB-1 and lB-2.
The preponderant gamma emitting isotopes detected in sampling were Co-58, Co-60, and Mn-54. Specif1c activity from analyses were multiplied by the volume of effluent discharged to the environment in order to estimate the total liquid activity 4.2 discharged.
8.0   MODIFICATION TO PREVIOUS RADIOACTIVE *~FFLUENT RELEASE
* Gaseous effluent streams are monitored and sampled in accordance with Table 4.11-2 of the Technical Specifications.
    *REPORTS                                "'
The plant vent is the final release point of all planned gaseous effluents and is continuously monitored by beta scintillators and high range GM tubes. The vent is also continuously sampled for iodine and particulates 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.
Our last report (RERR-22) did not include the quarterly Sr-89, Sr-90, and Fe-55 composite* data for the second quarter of 1987. Amended pages to RERR-22 are included at the end of this report.
Sampling is also performed on all gas decay tanks and containment purges prior to their release to the environment.
Part B. GASEOUS EFFLUENTS See Summary Tables lA-1 thru lC for Salem Unit 1 Operations.
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.
1-. . Continuous Mode gaseous releases are quantified by routine (monthly or weekly) sampling and isotopic analyses of the plant vent. Specific 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 radioactivity t.hrough the plant vent. Slightly elevated plant vent radiation monitor 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 releases are quantified by sampling each gas decay tank or containment purge prior to
* discharge.
Specific activities for each isotope are multiplied by the total volume of gas discharged.
Elevated plant vent 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 while the release was in progress 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" using historical efficiency factors. The "specific activity" is multiplied by the volume 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 varia.bility 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 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%.
 
===5.0 BATCH===
RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A-l and 4B-l for Unit 1 and 4A-2 and for Unit 2. 6.0 UNPLANNED RELEASES During this reporting period there were no unplanned releases.  
 
===7.0 ELEVATED===
R-16 CHANNEL RESPONSES During this reporting period, the plant vent radiation monitor indicated slightly elevated readings on several occasions.
As indicated  
: above, R-16 readings were quantified and treated as contiriuous It was assumed that they were Xe-133 since it is the preponderant isotope released.
They were. thus included in Tables lB-1 and lB-2. 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE RELEASE "' *REPORTS Our last report (RERR-22) did not include the quarterly Sr-89, Sr-90, and Fe-55 composite*
data for the second quarter of 1987. Amended pages to RERR-22 are included at the end of this report. Part B. GASEOUS EFFLUENTS See Summary Tables lA-1 thru lC for Salem Unit 1 Operations.
See Summary Tables lA-2 thru lC for Salem Unit 2 Operations.
See Summary Tables lA-2 thru lC for Salem Unit 2 Operations.
Part C. LIQUID EFFLUENTS See Summary Tables 2A-l and 2B-l for Salem Unit 1 Operations.
Part C. LIQUID EFFLUENTS See Summary Tables 2A-l and 2B-l for Salem Unit 1 Operations.
See Summary Tables 2A-2 and 2B-2 for Salem Unit 2 Operations.
See Summary Tables 2A-2 and 2B-2 for Salem Unit 2 Operations.
Part D. SOLID WASTE See Summary Table 3 for Units 1 and 2.
Part D. SOLID WASTE See Summary Table 3 for Units 1 and 2.
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 based on historical site specific data i.e., food production, milk production, feed for milch animals and seafood production.
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 i~ 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.
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.
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 reporting interval.
Population doses were calculated using the meteorological dispersion coefficients for the six mont~ reporting interval.
Liquid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathw 'Y* The total body dose to an individual was calculated to be 2.26E-Ol mrem. The calculated highest organ dose from liquid releases was 8.31E-01 mrem to the gastrointestinal tract. The calculated population total body dose was l.20E-Ol person-rem.
Liquid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathw 'Y* The total body dose to an individual was calculated to be 2.26E-Ol mrem. The calculated highest organ dose from liquid releases was 8.31E-01 mrem to the gastrointestinal tract. The calculated population total body dose was l.20E-Ol person-rem. The calculated average total body dose to the population within fifty miles of the site was 2.25E-05 mrem/person.
The calculated average total body dose to the population within fifty miles of the site was 2.25E-05 mrem/person.
Air Pathways The resulting total body and skin doses to an individual were calculated to be 2.34E-02 mrem and 5.49E-02 mrem respectively. The calculated highest organ dose due to radioiodines and particulates with a greater than eight day half-life was 3.73E-02 mrem to the thyroid. The calculated population total body dose was 2.34E-Ol person-rem. The calculated average total body dose to the population within fifty miles of the site was 4.37E-05 mrem/person.
Air Pathways The resulting total body and skin doses to an individual were calculated to be 2.34E-02 mrem and 5.49E-02 mrem respectively.
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.
The calculated highest organ dose due to radioiodines and particulates with a greater than eight day half-life was 3.73E-02 mrem to the thyroid. The calculated population total body dose was 2.34E-Ol person-rem.
TLD's at onsite locations 2S-2 and 58-1, which are 0.3 miles and 0.9 miles from the point of origin, averaged 4.5 and 4.0 mrads/month respectively. The values for stations 2S-2 and SS-1 are within the statistical variation
The calculated average total body dose to the population within fifty miles of the site was 4.37E-05 mrem/person.
* associated with the preoperational program results.
Direct Radiation Direct radiation may be estimated by Thermoluminescent dosimetric (TLD) measurements.
It should be noted that the nearest resident is 3.5 miles away. It can thus be concluded that there was no measurable dose to any ottsite location tram direct radiation.
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.  
Part F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmo-spheric stability class at the 300 foot elevation are provided for the third and fourth quarters of 1987 in Tables 5 and 6.
* .. TLD's at onsite locations 2S-2 and 58-1, which are 0.3 miles and 0.9 miles from the point of origin, averaged 4.5 and 4.0 mrads/month respectively.
* Part G. ODCM CHANGES Part H. INOPERABLE MONITORS SALEM GENERATING STATION TABLE lA-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 UNIT 1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 3rd       4th Units   Quarter   Quarter   Est. Total ( J Error %
The values for stations 2S-2 and SS-1 are within the statistical variation associated with the preoperational program results. It should be noted that the nearest resident is 3.5 miles away. It can thus be concluded that there was no measurable dose to any ottsite location tram direct radiation.
A. Fission and Activation Gases
Part F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by spheric stability class at the 300 foot elevation are provided for the third and fourth quarters of 1987 in Tables 5 and 6.
: 1. Tota: release                         Ci     5.73E+02 2.70E+02       25
* Part G. ODCM CHANGES Part H. INOPERABLE MONITORS  
: 2. Average release rate for period                             uCi/sec. 7.29E+Ol   3.43_E+Ol
. SALEM GENERATING STATION TABLE lA-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987 UNIT 1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 3rd 4th Units Quarter Quarter Est. Error -A. Fission and Activation Gases 1. Tota: release Ci 5.73E+02 2.70E+02 2. Average release rate for period uCi/sec. 7.29E+Ol 3.43_E+Ol  
: 3. Percent of technical specification limit (T.S. 3.ll.2.2(a))                   %       4.21E-Ol 2.0lE-01 B. Iodines
: 3. Percent of technical specification limit (T.S. 3.ll.2.2(a))  
: 1. Total iodine-131                     Ci     2.97E-U4 3.78E-04       25
% 4.21E-Ol 2.0lE-01 B. Iodines 1. Total iodine-131 Ci 2.97E-U4 3.78E-04 2. Average release rate for ... period uCi/sec. 3.78E-05 4.81E-05 3. Percent of technical , specification limit ( 2) (T.S. 3.ll.2.3(a))  
: 2. Average release rate for period                             uCi/sec. 3.78E-05   4.81E-05     ,
% 1. 52E-02 l.88E-U2 c. Particulates  
: 3. Percent of technical specification limit ( 2)
: 1. Particulates with half-lives  
(T.S. 3.ll.2.3(a))                     %     1. 52E-02 l.88E-U2
> 8 days Ci O.OOE+OO O.OOE+OO 2. Average release rate for . period uCi/sec
: c. Particulates
* O.OOE+OO O.OOE+OO 3. Percent of technical specification limit ( 2 ) ( T. S. 3.ll.2.3(a))  
: 1. Particulates with half-lives
% O.OOE+OO O.OOE+OO 4. Gross alpha radioactivity Ci O.OUE+OO D. Tr1t1um 1. Total release 2. Average release rate for eriod 3. Percent of technical specification limit (2) (T.S. 3.ll.2.3(a))
          > 8 days                             Ci     O.OOE+OO O.OOE+OO       25
Ci 4.67E+Ol uCi/sec. 5.94E+OO % l.52E-02 4.30E+Ol 5.47E+OO l.88E-02 (1) For batch releases the estimated overall error is within 10%. (2) Iodine, tritium, and particulates are treated as a group. --. ' ' Total ( J % 25 25 25 
: 2. Average release rate for
... SALEM GENERATING STATION . TABLE lA-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL JULY -DECEMBER 1987 UNIT 2 GASEOUS EFFLUENTS-SUMMATION OF ALL REL A. Fission and Activation Gases . 1. Total release 2. Average relea3e rate for period 3. Percent of technical specification limit (T.S. 3.ll.2.2(a))
        . period                             uCi/sec
B. Iodines 1. Total iodine-131 Units Ci 3rd Quarter 5.62E+02 uCi/sec. 7.15E+Ol % 4.16E-01 Ci 6.07E.;.04
* O.OOE+OO O.OOE+OO
-. REPORT EASES 4th uu_arter Est. Error . 3.46E+02 4.40E+Ol 2.57E-01 2.90E:-:04
: 3. Percent of technical specification limit ( 2 )
: 2. Average release rate for period uCi/sec. 7.72t-05 * . 3* Percent of technical specification limit (2) (T.S. 3.ll.2.3(a))  
( T. S. 3.ll.2.3(a))                   %     O.OOE+OO O.OOE+OO
: c. Particulates
: 4. Gross alpha radioactivity             Ci     O.OUE+OO D. Tr1t1um
: 1. Particulates with half-lives  
: 1. Total release                         Ci      4.67E+Ol  4.30E+Ol
> 8 days 2. Average release rate for period 3. Percent of technical specification limit (2) (T.S. 3.ll.2.3(a))  
: 2. Average release rate for eriod                           uCi/sec. 5.94E+OO  5.47E+OO
: 4. Gross alpha radioactivity D. Tritium 1. Total release 2. Average release rate for period 3. Percent of technical specification limit (2) (T.S. 3.ll.2.3(a))  
: 3. Percent of technical specification limit (2)
% 3.56E-02 Ci O.OOE+OO uCi/sec. O.OOE+OO % O.OOE+OO Ci O.OOE+OO Ci 2.67E+02 uCi/sec. 3.40E+Ol % 3.56E-02 (1) batch releases the estimated overall error is (2) Iodine, tritium, and particulates are treated as a l.48E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.72E+Ol 6.00E+OO l.48E-02 within 10%. group. Total(!) % 25 25 25 SALEM GENERATING STATION TABLE lB-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 19B7 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 1 CONTINUOUS MODE BATCH MODE Nuclides Released Unit 1. Fission Gases Krypton-BS Ci Kryptori-BSm Ci Krypton-B7 Ci Krypton-BB Ci Xenon-13lm Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Argon-41 Ci Total for Period Ci 2. Iodines Iodine-131 Ci Total for Period Ci 3. Particulates (half life >8 Days) Ci Chromium-51 Ci Manganese-54 Ci Cobalt-SB Ci Cobalt-60 Ci Iron-55 Ci Yttrium-BB Ci Strontium-89 Ci Strontium-90 Ci Rubidium-88 Ci Cesium-137 Ci Total for Period Ci 4. Tritium Tritium Ci 3rd Quarter 3.05E+02 3.05E+02 2.97E-04 2.97E-04 O.OOE+OO 4th Quarter l.06E+02 l.06E+02 3.78E-04 3.78E-04 O.OOE+OO 3rd Quarter l.74E-Ol 6.44E-01 2.65E+02 l.91E+OO 2.68E+02 O.OOE+OO 4.67E+Ol 4th Quarter 3.25E-01 5.BlE-02 1.60E+02 7.53E-01 2.52E+OO l.64E+02 4.30E+Ul SALEM GENERATING STATION .. TABLE lB-2 En,LUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 2 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter 1. Fission Gases Kry2ton-85*
(T.S. 3.ll.2.3(a))                     %     l.52E-02 l.88E-02 (1) For batch releases the estimated overall error is within 10%.
Ci l.04E-Ol l.35E-01 Kry2ton-85m Ci 2.34E-02 2.48E-01 Kry12ton-87 Ci l.28E-03 Kry12ton-88 Ci 1. 63E-01 Xenon-13lm Ci 6.97E-Ol l.59E-02 Xenon-133 Ci l.87E+02 l.14E+02 3.74E+02 2.28E+02 Xenon-133m Ci l.18E+OO 7.56E-01 Xenon-135 Ci l.41E+OO 2.51E+OO 3.35E+OO Xenon-135m Ci Argon-41 Ci 6.23E-03 Total for Period Ci l.84E+02 l.14E+02 3.78E+02 2.32E+02 2. Iodines Iodine-131 Ci 6.07E-04 2.9UE-04 Iodine-133 Ci " Iodine-135 Ci Total for Period Ci 6.07E-U4 2.90E-04 3. Particulates (half life .>8 Dal'.:s) Ci Chromium-51 Ci Manganese-54 Ci Cobalt-58 Ci Cobalt-60 Ci Iron-55 Ci " Yttrium-88 . Ci Strontium-89 .Ci Strontium-90 Ci Cesium-137 Ci Cerium-144 Ci Gross AlEha Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4. Tritium Tritium Ci 2.67E+02 4.72E+Ol I. I ----
(2) Iodine, tritium, and particulates are treated as a group.
Nuclide Releases SALEM GENERATING STATION TABLE lC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987 lJNITS 1 AND 2 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter There were no ground level gaseous releases during this reporting period.
SALEM GENERATING STATION
                                        . TABLE lA-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 UNIT 2 GASEOUS EFFLUENTS-SUMMATION OF ALL REL EASES 3rd          4th Units  Quarter      uu_arter            Est. Total(!)
Error %
A. Fission and Activation Gases
      . 1. Total release                       Ci    5.62E+02 . 3.46E+02                  25
: 2. Average relea3e rate for                                                              -
period                            uCi/sec. 7.15E+Ol    4.40E+Ol
: 3. Percent of technical specification limit (T.S. 3.ll.2.2(a))                 %      4.16E-01    2.57E-01 B. Iodines
: 1. Total iodine-131                   Ci     6.07E.;.04  2.90E:-:04              25
: 2. Average release rate for period                            uCi/sec. 7.72t-05 * . 3* ~-6:-g*:E:*~'as*
3~ Percent of technical specification limit (2)
(T.S. 3.ll.2.3(a))                   %    3.56E-02    l.48E-02
: c. Particulates
: 1. Particulates with half-lives
            > 8 days                           Ci    O.OOE+OO    O.OOE+OO                25
: 2. Average release rate for period                           uCi/sec. O.OOE+OO    O.OOE+OO
: 3. Percent of technical specification limit (2)
(T.S. 3.ll.2.3(a))                   %    O.OOE+OO    O.OOE+OO
: 4. Gross alpha radioactivity           Ci    O.OOE+OO D. Tritium
: 1. Total release                       Ci    2.67E+02    4.72E+Ol                25
: 2. Average release rate for period                           uCi/sec. 3.40E+Ol    6.00E+OO
: 3. Percent of technical specification limit (2)
(T.S. 3.ll.2.3(a))                   %     3.56E-02     l.48E-02 (1) Fo~ batch releases the estimated overall error is within 10%.
(2) Iodine, tritium, and particulates are treated as a group.
SALEM GENERATING STATION TABLE lB-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 19B7 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 1 CONTINUOUS MODE        BATCH MODE 3rd        4th        3rd        4th Nuclides Released          Unit    Quarter    Quarter    Quarter    Quarter
: 1. Fission Gases Krypton-BS                Ci                          l.74E-Ol    3.25E-01 Kryptori-BSm              Ci                                      5.BlE-02 Krypton-B7                Ci Krypton-BB                Ci Xenon-13lm                Ci                          6.44E-01    2.~SE-01 Xenon-133                Ci    3.05E+02   l.06E+02  2.65E+02    1.60E+02 Xenon-133m                Ci                                      7.53E-01 Xenon-135                Ci                          l.91E+OO    2.52E+OO Xenon-135m                Ci Argon-41                  Ci Total for Period          Ci     3.05E+02  l.06E+02  2.68E+02    l.64E+02
: 2. Iodines Iodine-131                Ci     2.97E-04  3.78E-04 Total for Period         Ci     2.97E-04  3.78E-04
: 3. Particulates (half life >8 Days)       Ci Chromium-51               Ci Manganese-54             Ci Cobalt-SB                 Ci Cobalt-60                 Ci Iron-55                   Ci Yttrium-BB               Ci Strontium-89             Ci Strontium-90             Ci Rubidium-88               Ci Cesium-137               Ci Total for Period         Ci     O.OOE+OO  O.OOE+OO  O.OOE+OO
: 4. Tritium Tritium                  Ci                          4.67E+Ol    4.30E+Ul SALEM GENERATING STATION
  ..                                       TABLE lB-2 En,LUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 2 CONTINUOUS MODE      BATCH MODE 3rd        4th      3rd        4th Nuclides Released              Unit    Quarter    Quarter  Quarter    Quarter
: 1. Fission Gases Kry2ton-85*                  Ci                          l.04E-Ol    l.35E-01 Kry2ton-85m                  Ci                          2.34E-02    2.48E-01 Kry12ton-87                  Ci                                      l.28E-03 Kry12ton-88                  Ci                                      1. 63E-01 Xenon-13lm                    Ci                          6.97E-Ol    l.59E-02 Xenon-133                    Ci    l.87E+02    l.14E+02 3.74E+02    2.28E+02 Xenon-133m                    Ci                          l.18E+OO    7.56E-01 Xenon-135                    Ci    l.41E+OO            2.51E+OO    3.35E+OO Xenon-135m                    Ci Argon-41                      Ci                                      6.23E-03 Total for Period              Ci     l.84E+02    l.14E+02 3.78E+02    2.32E+02
: 2. Iodines Iodine-131                    Ci     6.07E-04    2.9UE-04 Iodine-133                    Ci Iodine-135                    Ci                                                "
Total for Period              Ci    6.07E-U4    2.90E-04
: 3. Particulates (half life .>8 Dal'.:s)      Ci Chromium-51                  Ci Manganese-54                  Ci Cobalt-58                    Ci Cobalt-60                    Ci Iron-55                      Ci Yttrium-88 .                 Ci
"        Strontium-89                .Ci Strontium-90                  Ci
~*
Cesium-137                    Ci Cerium-144                    Ci Gross AlEha                  Ci Total for Period             Ci     O.OOE+OO    O.OOE+OO O.OOE+OO    O.OOE+OO
: 4. Tritium Tritium                      Ci                           2.67E+02    4.72E+Ol SALEM GENERATING STATION TABLE lC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 lJNITS 1 AND 2 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES Nuclide Releases    3rd Quarter 4th Quarter   3rd Quarter 4th Quarter There were no ground level gaseous releases during this reporting period.
SALEM GENERATING STATION
SALEM GENERATING STATION
* TABLE 2A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987 UNIT 1 LIUUID EFFLUENTS-SUMMATION OF ALL RELEASES A. Fission and activation products 1. Total release (not including tritium, gases, alpha) 2. Average diluted concentration 3rd 4th Units Quarter Quarter Ci 7.75E-01 4.75E-Ol Est. Total Error, % 25 during p1riod uCi/ml 3.73E-08 8.32E-08 3. Percent (T.s. 3.11.1.2.(a))
* TABLE 2A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 UNIT 1 LIUUID EFFLUENTS-SUMMATION OF ALL RELEASES 3rd                4th Units        Quarter            Quarter            Est. Total Error, %
% 3.02E+OO B. Tritium 1. Total release 2. Average diluted concentration during period 3. Percent of applicable limit (T.S. 3.11.1.1)
A. Fission and activation products
Ci 9.86E+Ol uCi/ml 4.74E-06 % 1. 58E-:-01 c. Dissolved and entrained noble gases 2.35E+OO 2.50E+Ol 25 4.38E-06 l.46E-Ul 1. Total release Ci 8.60E-01 l.75E-Ol 25 2. Average diluted concentration .during period uCi/ml 4.14E-08 3.07E-08 3. Percent of applicable limit % (T.S. 3.11.1.1) 2.07E-02 D. Gross alpha radioactivity
: 1. Total release (not including tritium, gases, alpha)                                 Ci         7.75E-01 4.75E-Ol                                 25
: 1. Total release E. Volume of waste release {prior to diiution -Batch Release) F. Volume of dilution water used during entire period Ci O.OOE+OO liters 3.84E+06 l.61E+06 liters 2.08E+l0 5.71E+09 A. B. c. D. E. 1 F. SALEM GENERATING STATION TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 3rd 4th Units Quarter Quarter Fission and activation 12roducts
: 2. Average diluted concentration during p1riod                                         uCi/ml 3.73E-08 8.32E-08
: 1. Total release (not including tritium, g:ases, al12ha) *Ci l.14E+OO 7.64E-Ol 2. Average diluted concentration during: 12eriod uCi[ml 3.00E-08 2.15E-08 3. Percent of applic..lble limit (T.S. 3.11.1.2. (a)) % 6.30E+OO 4.52E+OO Tritium 1. Total release Ci 2.53E+02 5.77E+Ol 2. Average diluted concentration during 12eriod. uCi[ml 6.68E-06 l.62E-06 3. Percent of applicable limit % ( T .S. 3.11.1.1) 2.23E-01 5.41E-02 Dissolved and entrained noble. gases 1. Total release Ci 1.
: 3. Percent o~f,..:;;...;;a~p~p~l'1~*c-a~b'l-e---.l~i-m~i~t~~........;;;~..<.....;;..=-_;;_;..._~__;;_~__;;;~~;........;;;...;;...~~~~~~~~
7.79E-02 2. Average diluted concentration during: 12eriod uCil'.'.ml
(T.s. 3.11.1.2.(a))                                    %            3.02E+OO 2.35E+OO B. Tritium
: 5. 24E..;.08 2.19E-09 3. Percent of applicable limit % ( T .s. 3.11.1.1) 2.62E-02 l.lOE-03 Gross al12ha radioactivit:t:
: 1. Total release                                          Ci          9.86E+Ol            2.50E+Ol                    25
: 1. Total release Ci O.OOE+OO Volume of waste release (prior to dilution -Batch Release) liters l.04E+07 6.54E+06 Volume of dilution water used during entire 12er 1 iod liters 3.79E+l0 3.55E+l0 Est. Total Error, % 25 *,*: _,.
: 2. Average diluted concentration during period                                        uCi/ml 4.74E-06                  4.38E-06
SALEM GENERATING STATION TABLE 2B-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987 UNIT 1 LIQUID EFFLUENTS CONTINUOUS MOUE BATCH 3rd 4th 3rd Nuclides Released Unit Quarter Quarter Quarter Strontiurn-85 Ci Strontiurn-89' Ci l.46E-02 Strontiurn-90 Ci 6.91E-04 Fluorine-18 Ci Manganese-54 Ci 2.88E-02 Iron-55 Ci 6.91E-02 Iron-59 Ci Cobalt-58 Ci 3.46E-Ol Cobalt-60 Ci l.35E-Ol Zirconiurn-95 Ci Niobiurn-95 Ci l.35E-04 Niobiurn-97 Ci Iodine-131 Ci 7.20E-04 6.34E-02 Iodine-133 Ci B.75E-03 Cesium-134 Ci 9.28E-02 Cesium-137 Ci 2.02E-05 9.29E-02 Cesium-138 Ci Silver-llOm Ci Antimony-124 Ci 2.92E-03 Antirnony-125 Ci 4.57E-03 Total for period (above) Ci 7.40E-04 8.59E-Ol Tritium Ci Xenon-133 Ci 8.43E-Ol Xenon-135 Ci l.69E-02 MODE 4th <,Juarter 2.13E-03 3.32E-02 2.53E-01 5.09E-02 2.7!:1E-04 5.09E-04 2.83E-03 l.21E-02 3.88E-04 3.81E-02 l.lBE-02 4.5E-04 l.29E-02 1. 50E-0 2 4.74E-Ol l.74E-Ol 7. 79E-0.4 SALEM GENERATING STATION TABLE 2B-2 EFFLUENT AND WASTE DI8POSAL SEMIANNUAL REPORT JULY -DECEMBER 1987 LIUUID EFl''LUENTS UNIT 2 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Strontiurn-89 Ci l.OSE-03 l.66E-03 Strontiurn-90 Ci l.OSE-04 l.66E-04 *Fluorine-18 Ci l.2SE-03 Sodium-24 Ci l.64E-03 l.89E-03 Chromium-Sl Ci 7.26E-04 Manganese-S4 Ci 2.S7E-02 4.76E-02 Iron-SS Ci l.S7E-01 2.SOE-01 Iron-S9 Ci Cobalt-S8 Ci 2.82E-03 4.37E-Ol 4.21E-01 Cobalt-60 Ci l.90E-03 1. 29E-03 l.38E-Ol 6.SGE-02 **i_ .* Zirconium-9S Ci 3.60E-03
: 3. Percent of applicable limit                                  %
* 1. SSE-04 *:.:-: Niobium-9S Ci l.29E-03 7.14E-04 1. 93E-03 Niobium-97 Ci l.61E-03 '):;
(T.S. 3.11.1.1)                                                  1. 58E-:-01          l.46E-Ul
Ci Technetium-99M Ci 2.99E-04 Iodine-131 .Ci l.SlE-03 3.82E-03 S.78E-02 l.8SE-02 Iodine-132 Ci 2.49E-03 3.82E-03 Iodine-133 Ci 2.36E-03 3.32E-03 8.:.lSE-03 Iodine-134 Ci 2.88E-03 S.S3E-03 .;-.; Iodine-13S Ci 2.SSE-03 7.37E-03 -Cesium-134 Ci 8.72E-02 6.40E-02 Cesium-137 Ci 9.82E-04 9.67E-04 8.73E-02 6.lOE-02 .,., Cesium-138 Ci 3.86E-03 6.91E-03 Ci 7.06E-03 1. 48E-02 Antimony-12S Ci 7.42E-03 2.97E-02 Total for Eeriod (above) Ci l.8SE-01 3.78E-02 l.llE+OO 7.27E-01 Tritium Ci Xenon-13Sm Ci S.99E-03 Xenon-133 Ci 2.49E-02 l.20E-03 1. 93E+OO. 6.93E-02 Xenon-13S Ci l.24E-U3 9.67E-04 2.SOE-02 3*.61E-04 SALEM GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL A.' SOLID WASTE SHIPPED Or'FSITE FOR BURIAL OR DISPOSAL (Not irradiated tuel) 6-month 1. Type of waste Units(l) Period a. spent resins, filters, sludges, m3 31. 5 eva12orator bottoms Ci 8.81E+02 b. Dry compressible waste, m3 258.1 contaminated equi12. c. Irradiated components, control rods, d. Others (describe)
: c. Dissolved and entrained noble gases
: 2. Estimate of major Manganese
: 1. Total release                                           Ci          8.60E-01            l.75E-Ol                     25
-54' Iron -55 Cobalt -57 Cobalt -58 Cobalt -60 Nickel -63 Tritium -3 Carbon -14 Strontium
: 2. Average diluted concentration
-90 Antimony -125 Cesium -134 Cesium -137 Cerium -144 Lanthanum
    .during period                                        uCi/ml 4.14E-08                   3.07E-08
-140 Barium -140 Plutonium
: 3. Percent of applicable limit                                 %
-241 I-129,Pu-238, 239, 240 Sr-90, Tc-99, Arn-241 Cm-242, 243, and 244 C-14, Tc-99, I-129, Pu-238, 239, 240 Arn-241, Cm-242, 243, and 244 nuclide ( % ) 4.9 16.2 7.4 40.5 14.2 0.3 0.01 6.5 9.4 0.01 0.07 Ci l.lOE+Ol m3 Ci m3 Ci composition (for type A and Resin (Ci) ( % ) 4.27E+Ol 1.67 l.43E+02 1.01 6.48E+Ol 79.83 3.57E+02 8.57 1. 25E+02 5.74 2.22E+OO 3.97E-02 0.02 5.73E+u1*
(T.S. 3.11.1.1)                                                    2.07E-02            l.53E~02 D. Gross alpha radioactivity
1.59 8.32E+Ol 1.46 l.OlE-01 5.87E-Ol 0.02 (1) Volumes are measured, activities are estimated  Est. Total Error, % 25 25 B waste) DAW (Ci) l.83E-Ol l.llE-01 8.76E+OO 9.40E-Ol 5.29E-Ol 2.21E-03 l.75E-Ol l.61E-Ol l.69E-03 SALEM GENERATING STATION TABLE 3 (Continued)
: 1. Total release                                           Ci           O.OOE+OO E. Volume of waste release {prior to diiution - Batch Release)                              liters 3.84E+06                   l.61E+06 F. Volume of dilution water used during entire period                                      liters 2.08E+l0                  5.71E+09 SALEM GENERATING STATION TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 3rd          4th Units      Quarter    Quarter Est. Total Error, %
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL JULY -DECEMBER 1987 UNITS l AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS  
A. Fission and activation 12roducts
: 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 8 Truck Barnwell 9 Truck Richland B.
: 1. Total release (not including tritium, g:ases, al12ha)           *Ci        l.14E+OO    7.64E-Ol    25
FUEL SHIPMENTS (Disposition)
: 2. Average diluted concentration during: 12eriod                    uCi[ml 3.00E-08        2.15E-08
Number of Shipments Mode of Transportation Destination SALEM GENERATING STATION TABLE 4A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987  
: 3. Percent of applic..lble limit (T.S. 3.11.1.2. (a))                %          6.30E+OO    4.52E+OO B. Tritium
: 1. Total release                        Ci       2.53E+02     5.77E+Ol
: 2. Average diluted concentration during 12eriod.                    uCi[ml 6.68E-06        l.62E-06
: 3. Percent of applicable limit            %
( T .S. 3.11.1.1)                            2.23E-01    5.41E-02
: c. Dissolved and entrained noble. gases
: 1. Total release                        Ci       1. ~8E+OO    7.79E-02
: 2. Average diluted concentration                                                      _,.
during: 12eriod                    uCil'.'.ml 5. 24E..;.08 2.19E-09
: 3. Percent    of  applicable  limit        %
( T .s. 3.11.1.1)                              2.62E-02    l.lOE-03 D. Gross al12ha radioactivit:t:
: 1. Total release                        Ci        O.OOE+OO E. Volume of waste release (prior 1
to dilution    - Batch Release)      liters l.04E+07        6.54E+06 F. Volume of dilution water used during entire 12er1iod                  liters 3.79E+l0        3.55E+l0 SALEM GENERATING STATION TABLE 2B-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 UNIT 1 LIQUID EFFLUENTS CONTINUOUS MOUE        BATCH MODE 3rd       4th       3rd         4th Nuclides Released         Unit     Quarter   Quarter   Quarter     <,Juarter Strontiurn-85              Ci Strontiurn-89'            Ci                           l.46E-02 Strontiurn-90             Ci                           6.91E-04 Fluorine-18               Ci                                       2.13E-03 Manganese-54              Ci                           2.88E-02    3.32E-02 Iron-55                    Ci                           6.91E-02 Iron-59                    Ci Cobalt-58                  Ci                           3.46E-Ol    2.53E-01 Cobalt-60                  Ci                           l.35E-Ol    5.09E-02 Zirconiurn-95              Ci                                       2.7!:1E-04 Niobiurn-95                Ci                          l.35E-04    5.09E-04 Niobiurn-97                Ci                                       2.83E-03 Iodine-131                Ci                7.20E-04  6.34E-02   l.21E-02 Iodine-133                Ci                           B.75E-03   3.88E-04 Cesium-134                Ci                          9.28E-02    3.81E-02 Cesium-137                Ci                 2.02E-05  9.29E-02    4~03E-02 Cesium-138                Ci                                       l.lBE-02 Silver-llOm                Ci                                       4.5E-04 Antimony-124              Ci                           2.92E-03   l.29E-02 Antirnony-125              Ci                           4.57E-03   1. 50E-0 2 Total for period (above)  Ci                7.40E-04  8.59E-Ol    4.74E-Ol Tritium                    Ci Xenon-133                  Ci                          8.43E-Ol    l.74E-Ol Xenon-135                  Ci                           l.69E-02    7. 79E-0.4 SALEM GENERATING STATION TABLE 2B-2
~                EFFLUENT AND WASTE DI8POSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 LIUUID EFl''LUENTS UNIT 2 CONTINUOUS MODE        BATCH MODE 3rd        4th        3rd          4th Nuclides Released          Unit      Quarter    Quarter  Quarter      Quarter Strontiurn-89              Ci   l.OSE-03              l.66E-03 Strontiurn-90              Ci    l.OSE-04              l.66E-04
  *Fluorine-18                Ci                                         l.2SE-03 Sodium-24                  Ci   l.64E-03     l.89E-03 Chromium-Sl                Ci                                         7.26E-04 Manganese-S4                Ci                           2.S7E-02      4.76E-02 Iron-SS                    Ci    l.S7E-01               2.SOE-01 Iron-S9                    Ci Cobalt-S8                  Ci   2.82E-03               4.37E-Ol      4.21E-01  **i_ .*
Cobalt-60                  Ci    l.90E-03   1. 29E-03 l.38E-Ol      6.SGE-02     *:.:-:
Zirconium-9S                Ci    3.60E-03
* 1. SSE-04 Niobium-9S                  Ci                l.29E-03  7.14E-04      1. 93E-03
                                                                                        '):;
Niobium-97                  Ci                l.61E-03
                                                                                      '~/'
Mol~bdenum-99              Ci                                        2.ss~-04 Technetium-99M              Ci                                        2.99E-04 Iodine-131                .Ci   l.SlE-03    3.82E-03  S.78E-02      l.8SE-02 Iodine-132                  Ci    2.49E-03    3.82E-03 Iodine-133                  Ci    2.36E-03    3.32E-03  8.:.lSE-03                .;-.;
Iodine-134                  Ci    2.88E-03    S.S3E-03 Iodine-13S                  Ci    2.SSE-03    7.37E-03                                -
Cesium-134                 Ci                          8.72E-02      6.40E-02    .,.,
Cesium-137                  Ci    9.82E-04    9.67E-04  8.73E-02      6.lOE-02 Cesium-138                  Ci    3.86E-03    6.91E-03 Antimon~-124                Ci                          7.06E-03      1. 48E-02 Antimony-12S                Ci                          7.42E-03      2.97E-02 Total for Eeriod (above)   Ci    l.8SE-01    3.78E-02  l.llE+OO      7.27E-01 Tritium                    Ci Xenon-13Sm                  Ci                S.99E-03 Xenon-133                  Ci    2.49E-02    l.20E-03  1. 93E+OO. 6.93E-02 Xenon-13S                  Ci   l.24E-U3    9.67E-04  2.SOE-02     3*.61E-04 SALEM GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHI~MENTS A.' SOLID WASTE SHIPPED Or'FSITE FOR BURIAL OR DISPOSAL (Not irradiated tuel) 6-month    Est. Total
: 1. Type of waste                              Units(l) Period    Error, %
: a. spent resins, filters, sludges,          m3    31. 5 eva12orator bottoms                      Ci    8.81E+02      25
: b. Dry compressible waste,                 m3    258.1 contaminated equi12.                    Ci     l.lOE+Ol       25
: c. Irradiated components,                  m3 control rods,                            Ci
: d. Others (describe)                        m3 Ci
: 2. Estimate of major nuclide composition (for type A and B waste)
Resin                        DAW
( %)            (Ci)          ( %)        (Ci)
Manganese - 54'            4.9            4.27E+Ol        1.67      l.83E-Ol Iron - 55                  16.2            l.43E+02        1.01      l.llE-01 Cobalt - 57 Cobalt - 58                7.4            6.48E+Ol      79.83        8.76E+OO Cobalt - 60                40.5            3.57E+02        8.57      9.40E-Ol Nickel - 63                14.2            1. 25E+02      5.74      5.29E-Ol Tritium - 3                0.3            2.22E+OO Carbon - 14                0.01          3.97E-02        0.02      2.21E-03 Strontium - 90 Antimony -125 Cesium - 134                6.5            5.73E+u1*      1.59      l.75E-Ol Cesium - 137                9.4            8.32E+Ol        1.46      l.61E-Ol Cerium - 144 Lanthanum - 140 Barium - 140 Plutonium - 241            0.01          l.OlE-01 I-129,Pu-238, 239, 240 Sr-90, Tc-99, Arn-241 Cm-242, 243, and 244        0.07          5.87E-Ol        0.02      l.69E-03 C-14, Tc-99, I-129, Pu-238, 239, 240 Arn-241, Cm-242, 243, and 244 (1)  Volumes are measured, activities are estimated SALEM GENERATING STATION TABLE 3 (Continued)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPO~T JULY - DECEMBER 1987 UNITS l AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
: 3. Solid Waste Disposition Number of Shipments     Mode of Transportation     Destination 8               Truck                       Barnwell 9               Truck                       Richland B. !~RADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments     Mode of Transportation     Destination SALEM GENERATING STATION TABLE 4A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1. Dates: July 1 -September 30, 1987 2. Type of release: Gas 3. Number of releases during the 3rd Quarter: 11 4. Total time duration for all releases of type listed 8.25E+02 minutes 5. Maximum duration for releases of type listed above: l.03E+02 minutes 6. Average duration for all releases of type listed above: 7.SOE+Ol minutes 7. Minimum duration for release of type listed above: 2.90E+Ol  
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY
: 8. Average stream flow) during the period of release: N/A __ _J SALEM GENERATING STATION TABLE 4A-l (Cont'd) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987  
: 1. Dates:   July 1 - September 30, 1987
: 2. Type of release:   Gas
: 3. Number of releases during the 3rd Quarter:   11
: 4. Total time duration for all releases of type listed   abov~:
8.25E+02 minutes
: 5. Maximum duration for releases of type listed above:
l.03E+02 minutes
: 6. Average duration for all releases of type listed above:
7.SOE+Ol minutes
: 7. Minimum duration for release of type listed above:
2.90E+Ol m~~nutes
: 8. Average stream flow~(dilution  flow) during the period of release: N/A SALEM GENERATING STATION TABLE 4A-l (Cont'd)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1. Dates: October l -December 31, 1987 2. Type of release: Gas 3. Number of releases during the 4th Quarter: 17 4. Total time duration for all releases of type listed above: 3.48E+03 minutes 5. Maximum duration for releases of type listed above: 2.31E+03 minutes 6. Average duration for all releases of type listed above: 2.05E+02 minutes 7. Minimum duration for release of type listed above: 5.20E+Ol minutes 8. Average stream flow (dilution flow) during the period of release: N/A SALEM GENERATING STATION TABLE 4A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987  
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY
: 1. Dates: October l - December 31, 1987
: 2. Type of release: Gas
: 3. Number of releases during the 4th Quarter: 17
: 4. Total time duration for all releases of type listed above:
3.48E+03 minutes
: 5. Maximum duration for releases of type listed above:
2.31E+03 minutes
: 6. Average duration for all releases of type listed above:
2.05E+02 minutes
: 7. Minimum duration for release of type listed above:
5.20E+Ol minutes
: 8. Average stream flow (dilution flow) during the period of release: N/A SALEM GENERATING STATION TABLE 4A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1. Dates: July 1 -September 30, 1987 2. Type of release: Gas 3. Number of releases during the 3rd Quarter: 24 4. Total time duration for all releases of type listed above: l.96E+04 minutes 5. Maximum duration for releases of type listed above: l.72E+04 minutes 6. Average duration for all releases of type listed above: 8.18E+02 minutes 7. Minimum duration for release of type listed above: 8.00E+Ol minutes 8. Average stream flow (dilution flow) during the period of release: N/A SALEM GENERATING STATION TABLE 4A-2 (Cont'd) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987  
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY
: 1. Dates:   July 1 - September 30, 1987
: 2. Type of release:   Gas
: 3. Number of releases during the 3rd Quarter:     24
: 4. Total time duration for all releases of type listed above:
l.96E+04 minutes
: 5. Maximum duration for releases of type listed above:
l.72E+04 minutes
: 6. Average duration for all releases of type listed above:
8.18E+02 minutes
: 7. Minimum duration for release of type listed above:
8.00E+Ol minutes
: 8. Average stream flow (dilution flow) during the period of release:   N/A SALEM GENERATING STATION TABLE 4A-2 (Cont'd)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1. Dates: October 1 -December 31, 1987 2. Type of release: Gas 3. Number of releases during the 4th Quarter: 14 4. Total time duration for all releases of type listed above: 4.55E+04 minutes 5. Maximum duration for releases of type listed above: 2.53E+04 minutes 6. Average duration for all releasea pf type listed above: 3.25E+03 minutes 7. Minimum duration for release of type listed above: 9.60E+Ol minutes 8. Average stream flow (dilution flow) during the period of release: N/A '*
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY
SALEM GENERATING STATION TABLE 4B-l (Cont'd) EFFLUENT AND WASTE DI8POSAL SEMIANNUAL REPORT JULY -DECEMBER 1987  
: 1. Dates:   October 1 - December 31, 1987
: 2. Type of release:   Gas
: 3. Number of releases during the 4th Quarter:   14
: 4. Total time duration for all releases of type listed above:
4.55E+04 minutes
: 5. Maximum duration for releases of type listed above:
2.53E+04 minutes
: 6. Average duration for all releasea pf type listed above:
3.25E+03 minutes
: 7. Minimum duration for release of type listed above:
9.60E+Ol minutes
: 8. Average stream flow (dilution flow) during the period of release: N/A
 
SALEM GENERATING STATION TABLE 4B-l (Cont'd)
EFFLUENT AND WASTE DI8POSAL SEMIANNUAL REPORT JULY - DECEMBER 1987


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1. Dates: July l -September 30, 1987 2. Type of release: Liquid 3. Number of releases during the 3rd Quarter: 61 4. Total time duration for all releases of type listed above:. l.73E+04 minutes
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY
* 5. Maximum duration for releases of type listed above: 6.08E+02 minutes 6. Average duration for all releases of type listed above: 2.83E+02 minutes 7. Minimum duration for release of type listed above: 2.13E+02 minutes 8. Average stream flow (dilution flow) during the period of release: 3.18E+05 gpm SALEM GENERATING STATION TABLE 4B-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987  
: 1. Dates:   July l - September 30, 1987
: 2. Type of release:   Liquid
: 3. Number of releases during the 3rd Quarter: 61
: 4. Total time duration for all releases of type listed above:.
l.73E+04 minutes
* 5. Maximum duration for releases of type listed above:
6.08E+02 minutes
: 6. Average duration for all releases of type listed above:
2.83E+02 minutes
: 7. Minimum duration for release of type listed above:
2.13E+02 minutes
: 8. Average stream flow (dilution flow) during the period of release:   3.18E+05 gpm SALEM GENERATING STATION TABLE 4B-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1. Dates: October 1 -December 31, 1987 2. Type of release: Liquid 3. Number of releases during the 4th Quarter: 22 . 4. Total time duration for all releases of type listed above: 5.66E+03 minutes 5. MaximOm duration for releases of type listed above: 3.84E+02 minutes 6. Average duration for all releases of type listed above: 2.57E+02 minutes 7. Minimum duration for release of type listed above: 2.02E+02 minutes 8. Average stream flow (dilution flow) during the period of release: 2.66E+05 gpm SALEM GENERATING STATION TABLE 4B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY DECEMBER 1987  
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY
: 1. Dates:   October 1 - December 31, 1987
: 2. Type of release:     Liquid
: 3. Number of releases during the 4th Quarter:     22
. 4. Total time duration for all releases of type listed above:
5.66E+03 minutes
: 5. MaximOm duration for releases of type listed above:
3.84E+02 minutes
: 6. Average duration for all releases of type listed above:
2.57E+02 minutes
: 7. Minimum duration for release of type listed above:
2.02E+02 minutes
: 8. Average stream flow (dilution flow) during the period of release:   2.66E+05 gpm SALEM GENERATING STATION TABLE 4B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY ~ DECEMBER 1987


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1. Dates: July 1 -September 30, 1987 2. Type of release: Liquid 3. Number of releases during the 3rd Quarter: 62 4. Tot'l time duration for all releases of type listed above: l.56E+04 minutes s. Maximum duration for releases of type listed above: 6.14E+02 minutes 6. Average *duration for all releases of type listed above: 2.51E+02 minutes 7. Minimum duration for of type listed above: l.12E+02 minutes 8. Average stream flow (dilution flow) during the period of release: 6.42E+05 gpm SALEM GENERATING STATION TABLE 4B-2 (Cont'd) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1987  
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY
: 1. Dates:   July 1 - September 30, 1987
: 2. Type of release:   Liquid
: 3. Number of releases during the 3rd Quarter:   62
: 4. Tot'l time duration for all releases of type listed above:
l.56E+04 minutes
: s. Maximum duration for releases of type listed above:
6.14E+02 minutes
: 6. Average *duration for all releases of type listed above:
2.51E+02 minutes
: 7. Minimum duration for r~lease of type listed above:
l.12E+02 minutes
: 8. Average stream flow (dilution flow) during the period of release: 6.42E+05 gpm SALEM GENERATING STATION TABLE 4B-2 (Cont'd)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1. Dates: October l -December 31, 1987 2. Type of release: Liquid 3. Number of releases during the 4th Quarter: 30 4. Total time duration for all releases of type listed above: 7.93E+03 minutes 5. Maximum duration for releases of type listed above: 4.58E+02 minutes 6. Average duration for all releases of type listed above: 2.64E+02 minutes 7. Minimum duration for release of type listed. above: l.99E+02 minutes 8. Average stream flow (dilution flow) during the period of release: l.18E+06  
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY
,,,. TARLE 5 Page 1 of 9 ARTIFICIAL ISLAND 7/fH* 9/87 OF WIND OIPECTION AND 300FT DEG C/1001'1 LAP'iE RATE ( 300-3 HT> LE-1.9 CLISS A SP'.:EOS(l'll/HRJ 1-3 4-7 8-12 '13-111 19-24 25 PLUS SUll!
: 1. Dates:   October l - December 31, 1987
DIRECTION SUM PE RC ENT SU"! i>ERC'=.NT SUM SUI'! PERCENT :>UM PERCE.NT SU"I PERCENT N a o.o 0 a.a 0 o.o 0 o.o 0 o. cJ 0 Q.O 0 o.o NNE 0 a.a 0 0. I) 0 0. I) a o.o 0 J.O 0 a.a a o.o NE *a o.o a 0. 'l 0 o. *) a a.a (] 0. ) 0 o.o a 0.1) ENE a a.a a a.a 0 '). 0 '.) I). 0 0 o.o 0 a.o 0 o.o E 0 I). () 0 a.'1 Q o. 'l 0 Q.O a o.a 0 o.o 0 o.a ESE 0 a.o 0 0 .() I) o. (] 0 o.o 0 O.J 0 o.o 0 o.o SE 0 o.o 0 0.1) 0 a.a 0 o.o 0 o.o 0 o.o 0 o.o SSE 0 o.o 0 o.o 0 a.a 1 o.o I) o.o 0 o.o 1 o.o s 0 o.o 0 O.J 0 o.o 0 o.o Q o.o 0 o.o 0 o. \) SSW 0 o.o 0 o.o 0 o.o 0 o.o J o. ') 0 o.o 0 o.o SW 0 a. 'l 0 o.o 0 o.a 0 o.o 0 o.o 0 o.o 0 o.o WSW 0 o.o 0 o.o I) o.a 0 o. 0 a a.a 0 o.o 0 o.a II a o.o 0 o.J 0 a.o 0 o.a 0 o.o 0 o.a 0 o.o WNW 0 o.o 0 0. i) 0 a.a 0 o.a a O.J 0 0.') 0 0.1) NW a o.o I) o.o 0 o.o a o.a 0 O.J 0 a.a 0 o.o NNW 0 o.a 0 0 .*J a a.a a I). Q a o. ::J a o.a 0 o.o "' 0 o.o a a.o 0 o.a 1 1).0 a a.() 0 o.o 1 a.a l'IEAN WIND SPEED 14.0 CALPI HOURS 0 PEiUENT CAUi o.o l'IISSING 0
: 2. Type of release:     Liquid
TABLE 5 Page 2 of 9 ARTIFICIAL 7 IP.7-9 /6 7 Jf WINa DIRECTION LJCATION JCOFT or:;; C/100!" LAPSE RATE C300-35FTJ
: 3. Number of releases during the 4th Quarter:     30
-1.d/ -1.7 CLASS a SP<:EDS01l/HR) 1-3 4-7 8-12
: 4. Total time duration for all releases of type listed above:
* n-1 a-19-24 25 PLUS SUI'! PERCENT DIRECTION SUM Sli1 SUM
7.93E+03 minutes
'iUfll PERCC:NT 'SU1'1 PE RC C:N T :iUl'1 PERCENT N J o.u 1J J.J 0 o.o 0 a.a a a. u a a.a 0 o.o NNE a a.a J o. *) 0 Q.O 0 o.o () o.o a a.a 0 a.a Nf a a.J a o.a a J.O a a.a J a.ll a a.o a o.o ENt. a a.a 0 J.J a *). J a a.a a J. ll 0 0.i) 0 a. J E 0 o.o a a.a 0 a.a 0 a.a a a.a 0 a.a 0 a.a ESE 0 I u. :J J O.J 0 a.J 0 a.a J a.u 0 a.a 0 a.a :;i: a n.a J a.a 4 0.2 2 0.1 1 a.a a a.a 7 a. :s SSE a a.a a o.o 4 a.2 6 a.3 *l :J. u ( a a.a 1a a.5 :i u 0.1) 0 a.a a a.o 0 a.a 0 o.a a a.a a a. I) SSlll 0 a.a J a.a 0 a.J 1 a.a J Q.J a a.a 1 a.o SW 0 a.o 0 O.J 4 0.2 a a.a a O.J a a.a 4 a.2 llllSW a a.a 0 a.a a o.o 1 o.o l 0.1 0 a.a 4 o.z ... 0 o.o i) a.a 0 a.a a a.a a a.a 0 o.o a a.a WNW J a.a 0 o.J 0 o. () 0 a.a 1 a.a 0 a.a 1 a.a N,. a O.J J a.a a I.I. 0 0 o.o 2 0.1 a a.a 2 a.1 NNlll 0 o.J a o.J a a.a l) a.o a o.u Q a.a 0 a.a 0 a.a a J. i) 12 a.5 1a a. 5 7 0.3 a a.a 29 1.3 l'IEAN liiIND SPEED 14. 7 CALM HOURS a PEilCENT CALl1 a.a MISSING* 0 ... 
: 5. Maximum duration for releases of type listed above:
,
4.58E+02 minutes
* I ' . ... TABLE .S Page 3 of 9 ARTIFICIAL ISLAND 7/87-9187 JOINT DISTPteuTICN OF WIND AND SPEED L:JC Ill ION JO OFT DEG C/1001'1 LAP'iE RATE <JOO-BFT>
: 6. Average duration for all releases of type listed above:
-1.6/ -1.5 CLASS C 1-3 4-7 e-12 1:!-18 19-24 25 PLUS SUll! PERCFNT DIRECTION PERCENT SUM SU'l PEACF.NT SU., PEACf.NT 3U'l PERCENT PERCENT N 0 o.o 0 1).0 0 o.o 0 o.o a o. o 0 a.a* 0 0.1) NNE () o.o J o.o 0 o.o 0 o.o Q a.a I) o.o I) o.o NE a 0 .:J *J J.J 0 o.o 0 o.o a o.o 0 o.o I) o. o ENE 0 o.o 0 o.o 0 a.a I) o.o 0 I). Ll 0 o.o 0 O.J E J I). J 0 o *. ) 0 o.o 0 0. IJ I) 0. IJ I) o.o 0 O.l ESE J O.:J I) a.a I) o.o 0 o.o \) o.u 0 o.o 0 O.IJ SE a o.J 0 J.O 0 0.'1 4 I). 1 (). (} 1 o. o 6 o.3 SSE 0 o.o 1 'J.O z I). 1 R I). 4 1 *). J 0 a. o 1 2 o. '5 s 0 o.o a 1).0 0 o. J 0 o. I) 0 O.J 0 a. iJ a o.o SSW () O.'J 0 o.o 1 O.il 0 IJ. *) 0 .J. u a o.o 1 o.o SW 0 o. J J O.'l z U.1 I) 0. I) -* 0 o. o 0 O.IJ 2 0.1 WSW a o. CJ () Q.i) 0 0. ') 1 o.o 0 o. i) 0 o.o 1 o.o w 0 ci. ') 0 J.O 0 o.o 0 o. ,) i) o.u 0 o. a 0 o.o WNW 0 i).0 a J.J a o.o 0 o.o 1 O.J a a.a 1 o.o N .. 0 o.a 'J O.J 0 o.o 3 0.1 1 o.o a o.o 4 O.l NNll . () o.o 0 *J. 'J 0 o.o 1 o *. ) J o. :.I 0 O. IJ 1 o.o 0 a.a 1 o. a 5 f). 2 17 o. ii 4 J. l 1 o.o 28 1.3 MEAN WIND SPEED 15.6 CHI" HOURS 0 PERCEhT CAUi o.o MI SS ING 0 TABLE 5 Page 4 of 9 ARTIFICIAL ISLAND 7/'d7-9/r:.7 OF AND SPiEa LOCATION 300FT DE<i C/100M LAPSE RATE (Jl)0-35FU
2.64E+02 minutes
-1.4/ -0.5 CLASS D SPU DS(l'.l/HR) 1-3 4-7 8-1Z 13-1 !I 1'1-24 25 PLUS SUM PERCE'NT D 1111: CTlON Sl..11 PEilCtl\T SUM PERCENT :i\Jl1 PERCtlH SUM PERCENT 5Ur1 PERCENT .>Ul'I PERCENT Ill 2 0.1 21 1. ') 2!1 1 * .s 8 0.4 1 o. a 0 o.o oo 2.7 NlllE 0 o.o 19 0.9 H 1.d 10 0.5 1 0.1) 0 o.o 69 3.1 NE 1 a. J 11) u.s 23 1.0 6 o * .s *) O. l.l 0 o.o 40 1.d ENC. 0.1 5 0. 2 1a 0.5 1 a.o l.) a.J 0 a.a 1S 0.3 E a a.o b u. 3 13 a.6 2 0.1 a a.a a a.a 21 1.a ESE 0 o.o j a., 7 o * .s 4 o.z 2 0.1 0 a.a 16 0.7 :iif 4 0.2 0 0.3 <'3 1
: 7. Minimum duration for release of type listed. above:
* o 3o 1.0 21 ,
l.99E+02 minutes
* ll 10 I). 5 1ao 4.o SSE 1 o. :> 1 () 0.7 44 2. :> 71 3. 5 3? 1.5 6 0.3 172 7.8 :i 2 0.1 17 16 0.7 J8 ,
: 8. Average stream flow (dilution flow) during the period of release:   l.18E+06 TARLE 5 Page 1 of 9 7/fH* 9/87         JOI~T    OlSTRI~UTIO~      OF WIND OIPECTION AND   SP~EO ARTIFICIAL ISLAND                                                                                                DEG C/1001'1     LAP'iE RATE LOC~TIO'i  300FT
* 7 d J.4 I] o.o 3.7 SSllll 4 Q.2 !l 0 .4 1d 0.3 24 1.1 1 :l 0.5 0 ().0 64 2.9 Siii u o.o 14 o. C) 20 20 0.9 4 0.2 () o.o 58 2.6 w:. .. 0 O.J 0.4 21 1.0 15 0.7 0 J. j 0 o.o 51 2.3 Ii 1 o.o 7 o.3 21 1. () 14 0.6 0 O. ll a o.o 43 z.o WNlll 1 a.a 10 J.5 14 Q.6 12 0.5 3 0.1 0 *J.O 40 1.8 Niii 0 0. *) 9 0.4 30 1.4 19 o. \I 'd 0.4 J o.o 66 3.0 NNll 3 0.1 H o. 43 2.0 13 O.o 3 0.1 0 o.o 51 3.7 '-'1 1. 0 179 3.2 Ha 16. 9 295 n. s H 4.5 . 1o 0.7 44.7 MEAN llIND SPEED 12.0 CALM HOURS 0 PERCEhT CALM o.o fltISS lt.IG 8 
( 300-3 HT>           LE-1.9 CLISS A SP'.:EOS(l'll/HRJ
.. TABI.E 5 Page 5 of 9 ., ARTIFICIAL ISLAN1> 7/f'7-9/P7 DISTPieUTICN OF ANO L'lC AT IOf\I JC OFT iH(i C/1001"1 Ll'PSE UTE < jlJQ-3 3FT) -'l.4/ 1.5 ClAS'i !: 5pq :l5(f'II/HR) 1-.5 r.-r ll-1 2 1 !-1 ii 1Q-24 25 PLUS SUP!
                                                                                    '13-111           19-24             25 PLUS         SUll! PE~CENT 1-3              4-7                  8-12 SUM PE RC ENT   SU"! i>ERC'=.NT       SUM   PE~CENT        SUI'! PERCENT     :>UM PERCE.NT       SU"I PERCENT DIRECTION N       a     o.o     0       a.a         0         o.o         0       o.o       0     o. cJ       0     Q.O           0     o.o a.a     0       0. I)       0         0. I)       a       o.o       0     J.O         0     a.a           a     o.o NNE        0                                                                                                        o.o            a      0.1)
DIRECTION SU"l PBC F.11. T iU'1 PEHS:NT '5U"'I "ERCENT
NE      *a     o.o       a       0. 'l       0         o. *)       a       a.a       (]     0. )         0 a.a       a       a.a                   '). 0       '.)     I). 0     0     o.o         0     a.o           0     o.o ENE        a                                      0
;iU:-1 SU'1 PERCENT N 2 I). 1 .n :)
: o. 'l                          a      o.a                o.o            0      o.a E      0      I). ()    0       a.'1         Q                     0       Q.O                           0 o.o                   o.o ESE       0     a.o       0       0 .()       I)       o. (]       0       o.o       0     O.J         0                    0 0     o.o       0      0.1)         0       a.a         0       o.o       0     o.o         0     o.o           0     o.o SE                                                                                              o.o                o.o                    o.o SSE       0     o.o       0       o.o           0       a.a         1       o.o       I)                 0                     1 o.o               O.J           0       o.o           0     o.o       Q     o.o         0     o.o             0     o. \)
* 5 1 2 '). 5 25 1
s      0                0 o.o                 o.o              o. ')              o.o            0     o.o SSW        0     o.o       0       o.o           0                    0                J                   0 o.o                   o.o SW       0       a. 'l   0       o.o         0       o.a           0     o.o       0     o.o         0                     0 WSW         0     o.o     0       o.o         I)       o.a           0       o. 0     a     a.a         0     o.o             0     o.a II       a     o.o     0       o.J         0         a.o         0     o.a       0     o.o         0     o.a             0     o.o WNW               o.o     0       0. i)       0         a.a         0     o.a       a     O.J         0     0.')           0     0.1) 0 a     o.o     I)       o.o         0         o.o         a       o.a       0     O.J         0     a.a             0     o.o NW                                                                                            o. ::J      a     o.a                    o.o NNW        0     o.a      0        0 .*J       a         a.a         a       I). Q     a                                         0 0     o.o     a       a.o         0         o.a         1       1).0     a     a.()         0     o.o             1     a.a l'IEAN WIND SPEED     14.0 CALPI HOURS             0 PEiUENT CAUi           o.o l'IISSING               0
* 1 J ll.} 0 o.o 57 ?.6 NNE 5 1). 2 11 :). 5 h '). 7 1. 4 -)
* 1 I] o. o 65 J.O NE 4 J.2 3 I]. 4 11 0.5 ;:a 0.9 l l). 1 0 O.::J 46 2.1 ENE J o.o .5 !)
* 4 10 0.5 5 '). 2 *J !) * :) 0 O.:J 23 1
* I) E 3 0.1 7 )
* 3 21 1. iJ B o ... ) u. J 0 o.o 39 1. ESE 2 0 .1 1 J.J 15 0.1 311 1. 3 1 J. l) !) o.o SC ?.
* I) SE J 0.1 13 J.6 Z'3 1 i) 37 1.7 16 *l. 7 11 0.5 1 l'J '5 4.7 SSE :J o.o 12 0.5 26 1.2 1 1 I). 5 4 I). 2 1 o.o 54 2.c;* s 2 0.1 1.2 0.5 15 0.7: 20 . C! * ., i .). 4 0 O.'l 57 2.6 SSlll 1 c.o 0.4 ? 0.4 22 1.0 6 a. 5 0 o.o 47 ?.1 SW z o .1 p !)
* 24 1
* 1 19 o.o i 0.4 0 o.o 72 3.3 WSW 4 oJ. 2 H ).5 21 1
* J 19 I). \I 11 0.5 0 o. (J 67 S.1 w 0 O. J l4 1
* 1 1. 2 16 *J. 7 z !)
* 1 0 o.o 68 3.1 WNll 1 O.J 0.4 27 1
* 2 .15 !)
* 7 6 J.3 0 o.o 5'l 2.6 NW 3 I) .1 7 0.3 26 1. 2 l7 1.7 7 a. :s 2 0 .1 82 3.7 NNW 3 0.1 1J 0.5 23 1.0 1 'J. 0.9 1 J.J z J.1 58 2.6 "' 35 1.6 174 7.) 305 13. Q 15. 6 81 5. 7 16 0.7 954 4 3. 5 "IEAN WIND SPEE?> 1i!. 0 CAUi HOURS 0 PBCENT CALM c.o lllISSING 1 
* .. " ,, ,, -,, ARTIFICIAL ISLAND 7Je7-9/87 DIRECTION SUf'I N NNE lllt ENt f ESE lie s SSlll s .. WSW Ill Wiii,. Niii NNlll MEAN WilllD SPi;E D CAUi HOURS
* PEilCEt.T CALM MI INCi :l u () 0 1 1 () a 2 1 0 0 1 a 1 0 7 1-.s PERC 11.9 0 o.o 0 o.J O.tl o.o J.O a.a o.o o.o a.a :J. 1 J.J o.o O.J o.o o.o o.a o.o 0.1 Sl.i:'I (I z 0 1 l 0 z 6 2 1 1 1 1 0 1 2 29 TABLE 5 Page 6 of 9 DISTRitUTION Of AND L*)Cl.TION lOOFT SPEEDS CHI/HR) 4-7 l!-1l 13-1 d 19-24 PEH El'lT :a."1 PERCENT :iU!'I PERCENT SU:'!
J. 3 4 o.z 6 o * .s J o.o t) .1 d 0.4 11 o. 5 0 o.o o.J 2 0 *. 1 11 o.; 2 J.1 O.*l 2 u .1 3 0 .1 1 o.o 0.1 ll. 3 4 0.2 a o.u o.J l 0.1 7 0.3 0 o.o !)
* 1 2 0 .1 1 o.o l 0.1 O.l 4 o.z 3 0.1 0 a.a 0.1 l 0.1 1 O.J J J. ll I) .o 0 o). J 1 o.o z 0.1 O.*J 3 J .1 4 0.2 2 0.1 o.J 1 0. <J l 0.1 0 o. J ). ') 1 a * .J 3 0.1 1 a.a 0. LI 2 J .1 8 0.4 0 o.u i). tl 4 ;). l 5 0.2 !) -J.O a *. 1 7 O.l 8 0.4 tl o.o 1. l 64 z.9 79 3. 6 11 o.; Dl Ii C/100M LAP SE llAH ChlO-BFT>
: 1. 6 I 4.') CLASS f 25 PLUS SUM PERCENT PERCENT 0 o.o 16 0.7 0 a. o 21 1.a () o.o 15 0.7 0 !l.O 7 0.3 'l o.o 26 1.2 0 o.a 11 o.s 0 o.a 8 0.4 a o. 'l 1l 0.6 0 o.o fl 0.4 0 a. 'l 5 0.2 0 o.o 10 0.5 0 a.a 5 '0. 2 0 o.o 7 O.l 0 a.a 10 0.5 a o.o 11 0.5 0 o.o 17 0.8 *a o.o 190 8.7 '*
t *I TABLE 5 Page 7 of 9 ARTIFICIAL ISLAND 7187-9/67 JOINT OF DlP.ECTICN AND SPcED 3COFT Dl:G C/100[1'.
L'PH PAH UJ0-3 HT) liT. 4.IJ CLASS G 1-3 :.-1 8-1 !'. U-H 19-24 25 PLUS SUl"I PERCF.NT DIRECTION SUM PERCHT SU"I PERC:NT 'iU"I 5Ul'I PEF!CENT 5U'1 PEllC".NT
:iU"I ?ERCENT 1\1 0 o. o a a. a 0 O. IJ I) o.o !) !)
* 0 0 o. a 0 o. IJ NNE J ) . ') 1 o.a I) 0.1) I) IJ .1 a a. ll 0 o.o 0 o. o NE 0 J. IJ *J .J.O 1 u. *) 1 o.o 0 O. 'I 0 o.o z 0.1 ENE a O.IJ a J.J 0 O.J 4 I). z 0 o.J 0 o.o 4 I). 2 E a o. '.) l J.IJ z IJ. 1 2 0.1 J (). J 0 a. IJ 4 o.:? ESE 0 o.o J o.o 0 o.o 1 a.a 0 o.o !) o.o 1 o.o SE ') o.o IJ O.J 0 o.o 0 o.o I) J.J 0 o.o 0 0.1) SSE a o.o 0 '). J 0 o.o 0 o.o 0 O.J 0 o. o 0 o.o s 0 o. Cl il O.J 0 f). 0 0 o.o 0 O. ll 0 o.o 0 o. o SSlll 0 a.o J I). !J 0 o. a 0 o. ') 0 Q. l.) a a.a 0 o.a SW 0 a. iJ a IJ. ') I) O.J ') o.o 0 0. IJ 0 0 .IJ 0 . o.o WSW 0 o.a a a. '.l 0 o. 0 0 o.:) J o.a 0 a.o 0 o.o w 0 a o.o 0 a.a 0 0. ') 0 o. J 0 o. o 0 o.o WNil a O.oJ a o.o 0 o.o 0 a.a J a.J 0 a.a 0 a.a NW 0 a.'l Q a.o 0 o.o I) I).*) Q o. (J 0 a.a 0 o.o NNW 0 O.J a fJ. () 0 O.:J 0 o.o 0 O.J 0 a.a 0 0.1} .... 0 I). 'l 0 a. a 3 0.1 8 0.4 0 o.o 0 o.o *11 I). 5 MEAN WIND SP'EED 13.0 CALl'i HOURS 0 PERCENT CALlll o.o 11111 SS INS 0 


.. .. TABLE 5 Page 9 of 9 ARTIFICIAL I SL ANO 7187-9/87 JOPH DISTRI!'UTICN OF DIPECTION Al'.;D SP EEO
TABLE 5 Page 2 of 9 ARTIFICIAL        ISL~~D  7IP.7- 9/6 7          JOl~T  OlST~l~UTICN    Jf WINa DIRECTION        ~ND SP~ED LAPSE RATE LJCATION JCOFT                                      or:;; C/100!"
C300-35FTJ          -1.d/ -1.7  CLASS a SP<:EDS01l/HR) 1-3              4-7            8-12
* n-1 a-              19-24                25 PLUS        SUI'! PERCENT DIRECTION            SUM  Pf~Ci~T      Sli1  PE~CENT      SUM P~~C~NT          'iUfll PERCC:NT      'SU1'1 PE RC C:N T      :iUl'1 PERCENT N      J        o.u        1J    J.J        0      o
Air Pathways*
Air Pathways*
The resulting total body and skin doses to an individual were calculated to be 2.38E-02 mrem and 5.34E-02 mrem respectively.
The resulting total body and skin doses to an individual were calculated to be 2.38E-02 mrem and 5.34E-02 mrem respectively. The calculated highest organ dose due to
The calculated highest organ dose due to radioiodines and particulates with a greater than eight day half-life was 2.97E-02 mrem to the thyroid. The calculated population total body dose was 9.llE-01 person-rem.
"*        radioiodines and particulates with a greater than eight day half-life was 2.97E-02 mrem to the thyroid. The calculated population total body dose was 9.llE-01 person-rem. The
The calculated average. total body dose to the population within fifty miles of the site was l.70E-04 mrem/person.
* calculated average. total body dose to the population within fifty miles of the site was l.70E-04 mrem/person.
SALEM GENERATING 8TATION TABLE 2A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1987 UNIT l LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES A. Fission and activation products 1. Total release (not including tritium, gases, alpha) 2. Average diluted concentration during period 3. Percent of applicable (T.S. 3.11.1.2.(a))
SALEM GENERATING 8TATION TABLE 2A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1987 UNIT l LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1st      2nd Units  Quarter  Quarter Est. Total Error, %
B. Tritium 1. Total release 2. Average diluted concentration during period 3. Percent of applicable limit (T.S. 3.11.1.1) 1st 2nd Units Quarter Quarter Ci 5.66E-Ol l.36E+OO uCi/ml 7.36E-08 8.65E-08 % 3.97E+OO 5.03E+OO Ci l.lUE+0.2 l.45E+02 uCi/ml l.43E-05 9.20E-06 % 4.78E-Ol 3.07E-Ol c. Dissolved and entrained noble gases 1. Total release Ci 3.54E-01 8.87E-Ol 2. Average diluted concentration during period uCi/ml 4.60E-08 5.65E-08 3. Percent of applicable limit % (T.S. 3.11.1.1) 2.30E-02 2.82E-02 D. Gross alpha radioactivity
A. Fission and activation products
: 1. Total release E. Volume of waste release (prior to dilution -Batch Release) F. Volume of dilution water used during entire period Ci O.OOE+OO O.OOE+OO liters 2.02E+06 3.24E+06 liters 7.69E+09 l.57E+l0 Est. Total Error, % 25% .l ,. .,.. 
: 1. Total release (not including tritium, gases, alpha)           Ci    5.66E-Ol  l.36E+OO      25%
, .. SALEM GENERATING STATION TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1987 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1st 2nd Units Quarter Quarter A. Fission and activation products 1. Total release (not including tritium, gases, alpha) 2. Average diluted concentration during period 3. Percent of applicable limit (T.s. 3.11.1.2.(a))
: 2. Average diluted concentration during period                   uCi/ml 7.36E-08  8.65E-08
Ci 8.36E-01 l.18E+OO uCi/ml 7.40E-08 9.22E-08 % 5.86E+OO 4.99E+OO B. Tritium 1. Total release 2. Average diluted concentration during period 3. Percent of applicable limit (T.S. 3.11.1.1) . Ci l.51E+02 uCi/ml l.34E.;.05
: 3. Percent of applicable lim~t (T.S. 3.11.1.2.(a))               %  3.97E+OO  5.03E+OO B. Tritium
% 4.45E-Ol l.99E+02 1. 55E-05 5.17E-01.  
: 1. Total release                     Ci    l.lUE+0.2 l.45E+02
: c. Dissolved and entrained noble gases 1. Total release Ci 5.05E-01 8.00E-01 2. Average diluted concentration during period uCi/ml 4.47E-08 6.23E-08 3. Percent of applicable limit % (T.S. 3.11.1.1) 2.23E-02 3.12E-02 D. Gross alpha radioactivity  
: 2. Average diluted concentration during period                   uCi/ml l.43E-05  9.20E-06
: 1. Total release Ci O.OOE+OO O.OOE+OO :<, E
: 3. Percent of applicable limit        %
* Volume of waste release (prior Est. Total Error, % 25% 25% to dilution -Batch Release) liters 2.85E+06 2.91E+06  
(T.S. 3.11.1.1)                       4.78E-Ol 3.07E-Ol
,,. F*. Volume of dilution water used during entire period liters l.13E+l0 l.28E+l0 .; I 
: c. Dissolved and entrained noble gases
-*--. -. * -* .
: 1. Total release                    Ci   3.54E-01  8.87E-Ol
* SALEM GENERATING STATION TABLE 2B-l ;.., ... EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT .;... JANUARY -JUNE 1987 "' LIQUID EFFLUENTS UNIT 1 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter uuarter . Strontium-85 Ci Strontium-89 Ci l.09E-05 2.31E-04 7.46E-O* Strontium-90 Ci l.27E-06 2.70E-05 Fluorine.:;.18 Ci 5.58E-02 5.16E-0 *--sodium.:.
: 2. Average diluted concentration during period                    uCi/ml 4.60E-08  5.65E-08
24 Ci 6.92E-0 Chromium-51 Ci ... Manqanese-54 Ci l.02E-02 3.27E-O Iron-55 Ci l.64E-03 .. . 3.47E-02 4. 86E-.U Iron-59 Ci ,.:..,,.., Cobalt-57 Ci 2.llE-0 Cobalt-58 Ci 2.49E-Ul 6.91E-O Cobalt-60 Ci 8.88E-02 l.47E-0 Zinc-65 Ci Zirconium-95 Ci 5.85E-04 Niobium-95 Ci 1. 79E-03 Niopium-97 Ci **6. 93E-O Molybdenum-99 Ci l.OUE-0 Technetium-99M Ci l.llE-0 Iodine-131 Ci 5.33E-04 3.03E-02 7.B7E-O Iodine-132 Ci 2.91E-0 Iodine-133 Ci 2.64E.-U3 6.95E-U Iodine-134 Ci 3.l'OE-0 Iodine-135 Ci 1. 96E-0 Cesium-134 Ci 4.22E-02 l.38E-0 Cesium-136 Ci  
: 3. Percent of applicable limit        %
: 1. 55.t:;-0 Cesium""."137 Ci !*08E-04 4.40E-02 l.24E-C Cesium-138 Ci 6.81E-0 Lanthanum-140 Ci Antimonv-122 Ci Antimonv-124 Ci 2.70E-04 8.03E-C Antimon:i:-125 Ci 2.38E-U3 l.08E-U Tin-113 Ci ;I-Silver-llOm Ci . 2.3&sect;E-C Total for period (above) Ci 2.29E-03 5.64E-01 1. 3'6E+c Tritium Ci l.10E+02 l.45E+C Xenon-133 Ci 3.43E-01 8.53E-C Xenon-133m Ci l.OBE-03 Xenon-135 Ci 9.60E-03 3. 42E-( Argon-41 Ci Kr-87 Ci f -.. ' Nuclides Released Strontium-89 Strontium-90 Fluorine-18 Sodium-22 Sodium-24 Chromium-51 Man9anese-54 . Iron-55 Iron-59 Cobalt.-58 Cobalt-60 Zinc-65 Zinc-69m Zirconium-95 Niobium-95 Niobium-97 Molj:'.:bdenum-99 Techneti'um-99M Iodine-131 Iodine-132.
(T.S. 3.11.1.1)                        2.30E-02  2.82E-02 D. Gross alpha radioactivity
Iodine-133 Iodine-1J4 Iodine-135 Cesium-134 Cesium-136 Cesium-137 Antimony-124 Antimony-125 SALEM GENERATING STATION TABLE 28-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1987 LIUUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Unit uuarter Quarter Quarter Quarter Ci 4.27E-04 9.61E-04 Ci 6.26E-05 6.41E-05 Ci l.50E-Ol 4.58E-02 Ci Ci 7.27E-05 Ci 2.]0E-03 Ci l.47E-02 3.lGE-02 Ci 5.12E-02 6.99E-02 Ci Ci 3.14E...:O1 5.33E-Ol Ci l.25E-Ol*
: 1. Total release                    Ci    O.OOE+OO  O.OOE+OO E. Volume of waste release (prior to dilution - Batch Release)       liters 2.02E+06  3.24E+06          .l F. Volume of dilution water used during entire period               liters 7.69E+09  l.57E+l0 SALEM GENERATING STATION
9.08E-02 Ci Ci Ci 6.87E-04 Ci 3.99E-03 Ci Ci l.83E-04 Ci 2.73E-04 Ci 4.92E-02 9.83E-02 Ci Ci 5.20E-03 4.14t-03 Ci Ci Ci 5.GBE-02*
    ,..                                 TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1987 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1st        2nd Units  Quarter    Quarter  Est. Total Error, %
l.41E-01 Ci 8.05E-04 2.GBE-04 Ci 6.00E-U2 l.23E-Ol Ci 2.40E-02 Ci 1. BBE-03 2.02E-02 Total For Period (above) Ci 8.36E-Ol l. lBE+OO Tritium Ci 1. 51E+02 l.99E+U2 -Xenon-133m Ci l.84E-03 Xenon-133 Ci 4.95E-01 Xenon-135 Ci 7.53E-03 8.33E-Oa Kry)2t.__on-85 Ci Ar9on-41 Ci .. **-.. ........ **.
A. Fission and activation products
'"&#xa3;'}}
: 1. Total release (not including tritium, gases, alpha)            Ci    8.36E-01  l.18E+OO      25%
: 2. Average diluted concentration during period                    uCi/ml 7.40E-08  9.22E-08
: 3. Percent of applicable limit (T.s. 3.11.1.2.(a))                 %  5.86E+OO   4.99E+OO B. Tritium
: 1. Total release                     Ci    l.51E+02  l.99E+02      25%
: 2. Average diluted concentration during period                     uCi/ml l.34E.;.05 1. 55E-05
: 3. Percent of applicable limit          %
(T.S. 3.11.1.1)   .                   4.45E-Ol  5.17E-01.
: c. Dissolved and entrained noble gases
: 1. Total release                     Ci   5.05E-01   8.00E-01                 .;
: 2. Average diluted concentration during period                     uCi/ml 4.47E-08   6.23E-08
: 3. Percent of applicable limit           %
(T.S. 3.11.1.1)                         2.23E-02   3.12E-02 D. Gross alpha radioactivity
:<, E *
: 1. Total release Volume of waste release (prior Ci   O.OOE+OO   O.OOE+OO I
to dilution - Batch Release)         liters 2.85E+06   2.91E+06 1~___;;~..;;;..;~;..._~~~~~~~~~---''--~--~.;;...;;...;;...;;....;;_..;;_~~~~~~~~~~~~~~~
,,. F*. Volume of dilution water used during entire period                liters l.13E+l0  l.28E+l0 SALEM GENERATING STATION TABLE 2B-l                                          ;..,...
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT                          .;...
JANUARY - JUNE 1987 LIQUID EFFLUENTS UNIT 1                                    "'
CONTINUOUS MODE              BATCH MODE 1st                2nd      1st          2nd Nuclides Released              Unit    Quarter    .
Quarter          Quarter    uuarter Strontium-85                Ci Strontium-89                Ci     l.09E-05                    2.31E-04    7.46E-O*
Strontium-90                Ci     l.27E-06                    2.70E-05    5.19E-U~
Fluorine.:;.18              Ci                                  5.58E-02    5.16E-0
*--sodium.:. 24                Ci                                             6.92E-0 Chromium-51                  Ci Manqanese-54                Ci                                  l.02E-02    3.27E-O Iron-55                      Ci   l.64E-03         ~..      ~
3.47E-02    4. 86E-.U Iron-59                      Ci                   ,.:..,,..,
Cobalt-57                    Ci                                             2.llE-0 Cobalt-58                    Ci                                 2.49E-Ul    6.91E-O Cobalt-60                    Ci                                  8.88E-02    l.47E-0 Zinc-65                      Ci Zirconium-95                  Ci                                5.85E-04 Niobium-95                  Ci                                 1. 79E-03 Niopium-97                    Ci                                           **6. 93E-O Molybdenum-99                Ci                                             l.OUE-0 Technetium-99M                Ci                                            l.llE-0 Iodine-131                  Ci     5.33E-04                     3.03E-02   7.B7E-O Iodine-132                    Ci                                             2.91E-0 Iodine-133                  Ci                                 2.64E.-U3  6.95E-U Iodine-134                    Ci                                             3.l'OE-0 Iodine-135                  Ci                                             1. 96E-0 Cesium-134                    Ci                                 4.22E-02    l.38E-0 Cesium-136                  Ci                                 ~.73E-U4    1. 55.t:;-0 Cesium""."137                Ci   !*08E-04                    4.40E-02   l.24E-C Cesium-138                    Ci                                             6.81E-0 Lanthanum-140                Ci Antimonv-122                  Ci Antimonv-124                  Ci                                 2.70E-04    8.03E-C Antimon:i:-125                Ci                                 2.38E-U3    l.08E-U
                                                                                    ;I-Tin-113                      Ci Silver-llOm                  Ci        .                                   2.3&sect;E-C Total for period (above)      Ci    2.29E-03                    5.64E-01    1. 3'6E+c Tritium                      Ci                                l.10E+02    l.45E+C Xenon-133                    Ci                                3.43E-01    8.53E-C Xenon-133m                    Ci                                l.OBE-03 Xenon-135                    Ci                                9.60E-03    3. 42E-(
Argon-41                      Ci Kr-87                        Ci f
SALEM GENERATING STATION TABLE 28-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1987 LIUUID EFFLUENTS UNIT 2 CONTINUOUS MODE         BATCH MODE 1st       2nd         1st         2nd Nuclides Released                Unit   uuarter   Quarter   Quarter     Quarter Strontium-89                  Ci                         4.27E-04   9.61E-04 Strontium-90                  Ci                         6.26E-05   6.41E-05 Fluorine-18                    Ci                         l.50E-Ol   4.58E-02 Sodium-22                      Ci Sodium-24                      Ci                                     7.27E-05 Chromium-51                    Ci                         2.]0E-03 Man9anese-54                  Ci                         l.47E-02   3.lGE-02
      . Iron-55                        Ci                         5.12E-02   6.99E-02 Iron-59                        Ci Cobalt.-58                    Ci                         3.14E...:O1 5.33E-Ol Cobalt-60                      Ci                         l.25E-Ol*   9.08E-02 Zinc-65                        Ci Zinc-69m                      Ci Zirconium-95                  Ci                          6.87E-04                         ..
Niobium-95                    Ci                         3.99E-03 Niobium-97                    Ci                                               ..
Molj:'.:bdenum-99              Ci                                     l.83E-04 Techneti'um-99M                Ci                                     2.73E-04     ........:-~
Iodine-131                    Ci                         4.92E-02   9.83E-02 Iodine-132.                    Ci                                                       **.
Iodine-133                    Ci                          5.20E-03   4.14t-03         *~7:'
Iodine-1J4                    Ci                                                       '"&#xa3;'
Iodine-135                    Ci Cesium-134                    Ci                         5.GBE-02*   l.41E-01 Cesium-136                    Ci                         8.05E-04   2.GBE-04 Cesium-137                    Ci                         6.00E-U2   l.23E-Ol Antimony-124                  Ci                                     2.40E-02 Antimony-125                  Ci                         1. BBE-03   2.02E-02 Total For Period (above)       Ci                         8.36E-Ol   l. lBE+OO Tritium                       Ci                         1. 51E+02   l.99E+U2
      -Xenon-133m                     Ci                         l.84E-03 Xenon-133                     Ci                          4.95E-01    7~92E-01 Xenon-135                     Ci                         7.53E-03   8.33E-Oa Kry)2t.__on-85                 Ci Ar9on-41                       Ci
                                              }}

Latest revision as of 10:49, 23 February 2020

Semiannual Radioactive Effluent Release Rept for Jul-Dec 1987
ML18093A696
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Site: Salem  PSEG icon.png
Issue date: 12/31/1987
From:
Public Service Enterprise Group
To:
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ML18093A695 List:
References
SGS-RERR-23, NUDOCS 8803030216
Download: ML18093A696 (54)


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REGTfV:.A"'rrm*v ~~mi 1987 SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE 1

PS~G EFFLUENT RELEASE REPORT SGS RERH.-23 SALEM UNIT NOS. 1 & 2 The Energy People UNIT 1. ~d-c'.i<ET.

,. . NO. 50-272

.. *_. UN.IT 2 DOC'K-*E1" NO. 50-311

  • ~*OPERATING LICENSE NO. DPR-70 OPERATING LICENSE NO. DPR-75 I t

'iI FEBRUARY 1988

__ - -~* *~ .

. I

    • ~-2*:*_*~-

SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SGS RERk-23 SALEM UNIT NOS. 1 & 2 UNIT 1 DOCKET NO. 50-272 UNIT 2 DOCKET NO. 50-311 OPERATING LICENSE NO. DPR-70 OPERATING LICENSE NO. DPR-75 FEBRUARY 1988

'I

DPR 70 DPR 75 REPORT NO. SGS-RERR-23 UNIT NOS. 1 & 2 RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 SALEM GENERATING STATION Public Service Electric and Gas Company

SALEM GENERATING STATION RADI.OACTIVE Er'FLUENT RELEASE REPORT JULY - DECEMBER 1987 INTRODUCTION This report, SGS-RERR-23, summarizes the releases of radioactive materials in liquid, gaseous and solid form from the Salem Generating Station (SGS) Units 1 and 2 for the period July 1, 1987 to December 31, 1987.

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 R~gulatory 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 6omplia~ce with 40CFR190 require-ments, the following information on electrical output is provided.

Unit 1 generated 2,469,593 megawatt-hours of electrical energy (net) during the reporting period.

Unit 2 generated 2,067,375 megawatt-hours of electrical en~r~y (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 1987 were not available for inclusion in this report. The results of these composites will be provided in the next Radioactive Effluent Release.Report.

The Sr-89, Sr-90, and Fe-55 analyses for the second quarter of 1987 (refer to RERR-22) have been completed; amended pages to

.~ RERR-22 are included in this report.

Part A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS 1.1 Noble 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:

For 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.

1.2 Iodine, Particulates, 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:

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.

1.3 Liquid Effluents Release Limits 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 gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 microcuries per 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 1 imi ted:

During any calendar 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

~qual to 10 mrems to any organ.

1.4 Total Dose Limit The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and 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).

2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)

Regulatory Guide 1.21 requires that the licensee provide the MPC's used in determining allowable release rates for radioactive releases.

a. MPC values were not used to determine the maximum release rates for fission gases, iodines, or particulates.
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.

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 the SGS 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 4.11-1 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 requir~ 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 liqLid releases are defined as condensate I releases from intermittent blowdown of the steam generators. The preponderant gamma emitting isotopes detected in sampling were Co-58, Co-60, and Mn-54.

Specif1c activity from analyses were multiplied by the 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 scintillators and high range GM tubes. The vent is also continuously sampled for iodine and particulates 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.

Continuous Mode gaseous releases are quantified by routine (monthly or weekly) sampling and isotopic analyses of the plant vent. Specific 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 radioactivity t.hrough the plant vent.

Slightly elevated plant vent radiation monitor 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 gaseou~ releases are quantified by sampling each gas decay tank or containment purge prior to

  • discharge. Specific activities for each isotope are multiplied by the total volume of gas discharged.

Elevated plant vent ra~*ation 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 while the release was in progress 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" using historical efficiency factors. The "specific activity" is multiplied by the volume 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 varia.bility 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 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%.

5.0 BATCH RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A-l and 4B-l 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 this reporting period, the plant vent radiation monitor indicated slightly elevated readings on several occasions. As indicated above, .~levated R-16 readings were quantified and treated as contiriuous relea~es. It was assumed that they were Xe-133 since it is the preponderant isotope released. They were. thus included in Tables lB-1 and lB-2.

8.0 MODIFICATION TO PREVIOUS RADIOACTIVE *~FFLUENT RELEASE

  • REPORTS "'

Our last report (RERR-22) did not include the quarterly Sr-89, Sr-90, and Fe-55 composite* data for the second quarter of 1987. Amended pages to RERR-22 are included at the end of this report.

Part B. GASEOUS EFFLUENTS See Summary Tables lA-1 thru lC for Salem Unit 1 Operations.

See Summary Tables lA-2 thru lC for Salem Unit 2 Operations.

Part C. LIQUID EFFLUENTS See Summary Tables 2A-l and 2B-l for Salem Unit 1 Operations.

See Summary Tables 2A-2 and 2B-2 for Salem Unit 2 Operations.

Part D. SOLID WASTE See Summary Table 3 for Units 1 and 2.

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 i~ 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 mont~ reporting interval.

Liquid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathw 'Y* The total body dose to an individual was calculated to be 2.26E-Ol mrem. The calculated highest organ dose from liquid releases was 8.31E-01 mrem to the gastrointestinal tract. The calculated population total body dose was l.20E-Ol person-rem. The calculated average total body dose to the population within fifty miles of the site was 2.25E-05 mrem/person.

Air Pathways The resulting total body and skin doses to an individual were calculated to be 2.34E-02 mrem and 5.49E-02 mrem respectively. The calculated highest organ dose due to radioiodines and particulates with a greater than eight day half-life was 3.73E-02 mrem to the thyroid. The calculated population total body dose was 2.34E-Ol person-rem. The calculated average total body dose to the population within fifty miles of the site was 4.37E-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 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 58-1, which are 0.3 miles and 0.9 miles from the point of origin, averaged 4.5 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 that the nearest resident is 3.5 miles away. It can thus be concluded that there was no measurable dose to any ottsite location tram direct radiation.

Part F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmo-spheric stability class at the 300 foot elevation are provided for the third and fourth quarters of 1987 in Tables 5 and 6.

  • Part G. ODCM CHANGES Part H. INOPERABLE MONITORS SALEM GENERATING STATION TABLE lA-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 UNIT 1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 3rd 4th Units Quarter Quarter Est. Total ( J Error %

A. Fission and Activation Gases

1. Tota: release Ci 5.73E+02 2.70E+02 25
2. Average release rate for period uCi/sec. 7.29E+Ol 3.43_E+Ol
3. Percent of technical specification limit (T.S. 3.ll.2.2(a))  % 4.21E-Ol 2.0lE-01 B. Iodines
1. Total iodine-131 Ci 2.97E-U4 3.78E-04 25
2. Average release rate for period uCi/sec. 3.78E-05 4.81E-05 ,
3. Percent of technical specification limit ( 2)

(T.S. 3.ll.2.3(a))  % 1. 52E-02 l.88E-U2

c. Particulates
1. Particulates with half-lives

> 8 days Ci O.OOE+OO O.OOE+OO 25

2. Average release rate for

. period uCi/sec

  • O.OOE+OO O.OOE+OO
3. Percent of technical specification limit ( 2 )

( T. S. 3.ll.2.3(a))  % O.OOE+OO O.OOE+OO

4. Gross alpha radioactivity Ci O.OUE+OO D. Tr1t1um
1. Total release Ci 4.67E+Ol 4.30E+Ol
2. Average release rate for eriod uCi/sec. 5.94E+OO 5.47E+OO
3. Percent of technical specification limit (2)

(T.S. 3.ll.2.3(a))  % l.52E-02 l.88E-02 (1) For batch releases the estimated overall error is within 10%.

(2) Iodine, tritium, and particulates are treated as a group.

SALEM GENERATING STATION

. TABLE lA-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 UNIT 2 GASEOUS EFFLUENTS-SUMMATION OF ALL REL EASES 3rd 4th Units Quarter uu_arter Est. Total(!)

Error %

A. Fission and Activation Gases

. 1. Total release Ci 5.62E+02 . 3.46E+02 25

2. Average relea3e rate for -

period uCi/sec. 7.15E+Ol 4.40E+Ol

3. Percent of technical specification limit (T.S. 3.ll.2.2(a))  % 4.16E-01 2.57E-01 B. Iodines
1. Total iodine-131 Ci 6.07E.;.04 2.90E:-:04 25
2. Average release rate for period uCi/sec. 7.72t-05 * . 3* ~-6:-g*:E:*~'as*

3~ Percent of technical specification limit (2)

(T.S. 3.ll.2.3(a))  % 3.56E-02 l.48E-02

c. Particulates
1. Particulates with half-lives

> 8 days Ci O.OOE+OO O.OOE+OO 25

2. Average release rate for period uCi/sec. O.OOE+OO O.OOE+OO
3. Percent of technical specification limit (2)

(T.S. 3.ll.2.3(a))  % O.OOE+OO O.OOE+OO

4. Gross alpha radioactivity Ci O.OOE+OO D. Tritium
1. Total release Ci 2.67E+02 4.72E+Ol 25
2. Average release rate for period uCi/sec. 3.40E+Ol 6.00E+OO
3. Percent of technical specification limit (2)

(T.S. 3.ll.2.3(a))  % 3.56E-02 l.48E-02 (1) Fo~ batch releases the estimated overall error is within 10%.

(2) Iodine, tritium, and particulates are treated as a group.

SALEM GENERATING STATION TABLE lB-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 19B7 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 1 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission Gases Krypton-BS Ci l.74E-Ol 3.25E-01 Kryptori-BSm Ci 5.BlE-02 Krypton-B7 Ci Krypton-BB Ci Xenon-13lm Ci 6.44E-01 2.~SE-01 Xenon-133 Ci 3.05E+02 l.06E+02 2.65E+02 1.60E+02 Xenon-133m Ci 7.53E-01 Xenon-135 Ci l.91E+OO 2.52E+OO Xenon-135m Ci Argon-41 Ci Total for Period Ci 3.05E+02 l.06E+02 2.68E+02 l.64E+02
2. Iodines Iodine-131 Ci 2.97E-04 3.78E-04 Total for Period Ci 2.97E-04 3.78E-04
3. Particulates (half life >8 Days) Ci Chromium-51 Ci Manganese-54 Ci Cobalt-SB Ci Cobalt-60 Ci Iron-55 Ci Yttrium-BB Ci Strontium-89 Ci Strontium-90 Ci Rubidium-88 Ci Cesium-137 Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO
4. Tritium Tritium Ci 4.67E+Ol 4.30E+Ul SALEM GENERATING STATION

.. TABLE lB-2 En,LUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 2 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission Gases Kry2ton-85* Ci l.04E-Ol l.35E-01 Kry2ton-85m Ci 2.34E-02 2.48E-01 Kry12ton-87 Ci l.28E-03 Kry12ton-88 Ci 1. 63E-01 Xenon-13lm Ci 6.97E-Ol l.59E-02 Xenon-133 Ci l.87E+02 l.14E+02 3.74E+02 2.28E+02 Xenon-133m Ci l.18E+OO 7.56E-01 Xenon-135 Ci l.41E+OO 2.51E+OO 3.35E+OO Xenon-135m Ci Argon-41 Ci 6.23E-03 Total for Period Ci l.84E+02 l.14E+02 3.78E+02 2.32E+02
2. Iodines Iodine-131 Ci 6.07E-04 2.9UE-04 Iodine-133 Ci Iodine-135 Ci "

Total for Period Ci 6.07E-U4 2.90E-04

3. Particulates (half life .>8 Dal'.:s) Ci Chromium-51 Ci Manganese-54 Ci Cobalt-58 Ci Cobalt-60 Ci Iron-55 Ci Yttrium-88 . Ci

" Strontium-89 .Ci Strontium-90 Ci

~*

Cesium-137 Ci Cerium-144 Ci Gross AlEha Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

4. Tritium Tritium Ci 2.67E+02 4.72E+Ol SALEM GENERATING STATION TABLE lC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 lJNITS 1 AND 2 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES Nuclide Releases 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter There were no ground level gaseous releases during this reporting period.

SALEM GENERATING STATION

  • TABLE 2A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 UNIT 1 LIUUID EFFLUENTS-SUMMATION OF ALL RELEASES 3rd 4th Units Quarter Quarter Est. Total Error, %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 7.75E-01 4.75E-Ol 25
2. Average diluted concentration during p1riod uCi/ml 3.73E-08 8.32E-08
3. Percent o~f,..:;;...;;a~p~p~l'1~*c-a~b'l-e---.l~i-m~i~t~~........;;;~..<.....;;..=-_;;_;..._~__;;_~__;;;~~;........;;;...;;...~~~~~~~~

(T.s. 3.11.1.2.(a))  % 3.02E+OO 2.35E+OO B. Tritium

1. Total release Ci 9.86E+Ol 2.50E+Ol 25
2. Average diluted concentration during period uCi/ml 4.74E-06 4.38E-06
3. Percent of applicable limit  %

(T.S. 3.11.1.1) 1. 58E-:-01 l.46E-Ul

c. Dissolved and entrained noble gases
1. Total release Ci 8.60E-01 l.75E-Ol 25
2. Average diluted concentration

.during period uCi/ml 4.14E-08 3.07E-08

3. Percent of applicable limit  %

(T.S. 3.11.1.1) 2.07E-02 l.53E~02 D. Gross alpha radioactivity

1. Total release Ci O.OOE+OO E. Volume of waste release {prior to diiution - Batch Release) liters 3.84E+06 l.61E+06 F. Volume of dilution water used during entire period liters 2.08E+l0 5.71E+09 SALEM GENERATING STATION TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 3rd 4th Units Quarter Quarter Est. Total Error, %

A. Fission and activation 12roducts

1. Total release (not including tritium, g:ases, al12ha) *Ci l.14E+OO 7.64E-Ol 25
2. Average diluted concentration during: 12eriod uCi[ml 3.00E-08 2.15E-08
3. Percent of applic..lble limit (T.S. 3.11.1.2. (a))  % 6.30E+OO 4.52E+OO B. Tritium
1. Total release Ci 2.53E+02 5.77E+Ol
2. Average diluted concentration during 12eriod. uCi[ml 6.68E-06 l.62E-06
3. Percent of applicable limit  %

( T .S. 3.11.1.1) 2.23E-01 5.41E-02

c. Dissolved and entrained noble. gases
1. Total release Ci 1. ~8E+OO 7.79E-02
2. Average diluted concentration _,.

during: 12eriod uCil'.'.ml 5. 24E..;.08 2.19E-09

3. Percent of applicable limit  %

( T .s. 3.11.1.1) 2.62E-02 l.lOE-03 D. Gross al12ha radioactivit:t:

1. Total release Ci O.OOE+OO E. Volume of waste release (prior 1

to dilution - Batch Release) liters l.04E+07 6.54E+06 F. Volume of dilution water used during entire 12er1iod liters 3.79E+l0 3.55E+l0 SALEM GENERATING STATION TABLE 2B-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 UNIT 1 LIQUID EFFLUENTS CONTINUOUS MOUE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter <,Juarter Strontiurn-85 Ci Strontiurn-89' Ci l.46E-02 Strontiurn-90 Ci 6.91E-04 Fluorine-18 Ci 2.13E-03 Manganese-54 Ci 2.88E-02 3.32E-02 Iron-55 Ci 6.91E-02 Iron-59 Ci Cobalt-58 Ci 3.46E-Ol 2.53E-01 Cobalt-60 Ci l.35E-Ol 5.09E-02 Zirconiurn-95 Ci 2.7!:1E-04 Niobiurn-95 Ci l.35E-04 5.09E-04 Niobiurn-97 Ci 2.83E-03 Iodine-131 Ci 7.20E-04 6.34E-02 l.21E-02 Iodine-133 Ci B.75E-03 3.88E-04 Cesium-134 Ci 9.28E-02 3.81E-02 Cesium-137 Ci 2.02E-05 9.29E-02 4~03E-02 Cesium-138 Ci l.lBE-02 Silver-llOm Ci 4.5E-04 Antimony-124 Ci 2.92E-03 l.29E-02 Antirnony-125 Ci 4.57E-03 1. 50E-0 2 Total for period (above) Ci 7.40E-04 8.59E-Ol 4.74E-Ol Tritium Ci Xenon-133 Ci 8.43E-Ol l.74E-Ol Xenon-135 Ci l.69E-02 7. 79E-0.4 SALEM GENERATING STATION TABLE 2B-2

~ EFFLUENT AND WASTE DI8POSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 LIUUID EFlLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Strontiurn-89 Ci l.OSE-03 l.66E-03 Strontiurn-90 Ci l.OSE-04 l.66E-04

  • Fluorine-18 Ci l.2SE-03 Sodium-24 Ci l.64E-03 l.89E-03 Chromium-Sl Ci 7.26E-04 Manganese-S4 Ci 2.S7E-02 4.76E-02 Iron-SS Ci l.S7E-01 2.SOE-01 Iron-S9 Ci Cobalt-S8 Ci 2.82E-03 4.37E-Ol 4.21E-01 **i_ .*

Cobalt-60 Ci l.90E-03 1. 29E-03 l.38E-Ol 6.SGE-02 *:.:-:

Zirconium-9S Ci 3.60E-03

  • 1. SSE-04 Niobium-9S Ci l.29E-03 7.14E-04 1. 93E-03

'):;

Niobium-97 Ci l.61E-03

'~/'

Mol~bdenum-99 Ci 2.ss~-04 Technetium-99M Ci 2.99E-04 Iodine-131 .Ci l.SlE-03 3.82E-03 S.78E-02 l.8SE-02 Iodine-132 Ci 2.49E-03 3.82E-03 Iodine-133 Ci 2.36E-03 3.32E-03 8.:.lSE-03 .;-.;

Iodine-134 Ci 2.88E-03 S.S3E-03 Iodine-13S Ci 2.SSE-03 7.37E-03 -

Cesium-134 Ci 8.72E-02 6.40E-02 .,.,

Cesium-137 Ci 9.82E-04 9.67E-04 8.73E-02 6.lOE-02 Cesium-138 Ci 3.86E-03 6.91E-03 Antimon~-124 Ci 7.06E-03 1. 48E-02 Antimony-12S Ci 7.42E-03 2.97E-02 Total for Eeriod (above) Ci l.8SE-01 3.78E-02 l.llE+OO 7.27E-01 Tritium Ci Xenon-13Sm Ci S.99E-03 Xenon-133 Ci 2.49E-02 l.20E-03 1. 93E+OO. 6.93E-02 Xenon-13S Ci l.24E-U3 9.67E-04 2.SOE-02 3*.61E-04 SALEM GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHI~MENTS A.' SOLID WASTE SHIPPED Or'FSITE FOR BURIAL OR DISPOSAL (Not irradiated tuel) 6-month Est. Total

1. Type of waste Units(l) Period Error, %
a. spent resins, filters, sludges, m3 31. 5 eva12orator bottoms Ci 8.81E+02 25
b. Dry compressible waste, m3 258.1 contaminated equi12. Ci l.lOE+Ol 25
c. Irradiated components, m3 control rods, Ci
d. Others (describe) m3 Ci
2. Estimate of major nuclide composition (for type A and B waste)

Resin DAW

( %) (Ci) ( %) (Ci)

Manganese - 54' 4.9 4.27E+Ol 1.67 l.83E-Ol Iron - 55 16.2 l.43E+02 1.01 l.llE-01 Cobalt - 57 Cobalt - 58 7.4 6.48E+Ol 79.83 8.76E+OO Cobalt - 60 40.5 3.57E+02 8.57 9.40E-Ol Nickel - 63 14.2 1. 25E+02 5.74 5.29E-Ol Tritium - 3 0.3 2.22E+OO Carbon - 14 0.01 3.97E-02 0.02 2.21E-03 Strontium - 90 Antimony -125 Cesium - 134 6.5 5.73E+u1* 1.59 l.75E-Ol Cesium - 137 9.4 8.32E+Ol 1.46 l.61E-Ol Cerium - 144 Lanthanum - 140 Barium - 140 Plutonium - 241 0.01 l.OlE-01 I-129,Pu-238, 239, 240 Sr-90, Tc-99, Arn-241 Cm-242, 243, and 244 0.07 5.87E-Ol 0.02 l.69E-03 C-14, Tc-99, I-129, Pu-238, 239, 240 Arn-241, Cm-242, 243, and 244 (1) Volumes are measured, activities are estimated SALEM GENERATING STATION TABLE 3 (Continued)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPO~T JULY - DECEMBER 1987 UNITS l AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 8 Truck Barnwell 9 Truck Richland B. !~RADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination SALEM GENERATING STATION TABLE 4A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY

1. Dates: July 1 - September 30, 1987
2. Type of release: Gas
3. Number of releases during the 3rd Quarter: 11
4. Total time duration for all releases of type listed abov~:

8.25E+02 minutes

5. Maximum duration for releases of type listed above:

l.03E+02 minutes

6. Average duration for all releases of type listed above:

7.SOE+Ol minutes

7. Minimum duration for release of type listed above:

2.90E+Ol m~~nutes

8. Average stream flow~(dilution flow) during the period of release: N/A SALEM GENERATING STATION TABLE 4A-l (Cont'd)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY

1. Dates: October l - December 31, 1987
2. Type of release: Gas
3. Number of releases during the 4th Quarter: 17
4. Total time duration for all releases of type listed above:

3.48E+03 minutes

5. Maximum duration for releases of type listed above:

2.31E+03 minutes

6. Average duration for all releases of type listed above:

2.05E+02 minutes

7. Minimum duration for release of type listed above:

5.20E+Ol minutes

8. Average stream flow (dilution flow) during the period of release: N/A SALEM GENERATING STATION TABLE 4A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY

1. Dates: July 1 - September 30, 1987
2. Type of release: Gas
3. Number of releases during the 3rd Quarter: 24
4. Total time duration for all releases of type listed above:

l.96E+04 minutes

5. Maximum duration for releases of type listed above:

l.72E+04 minutes

6. Average duration for all releases of type listed above:

8.18E+02 minutes

7. Minimum duration for release of type listed above:

8.00E+Ol minutes

8. Average stream flow (dilution flow) during the period of release: N/A SALEM GENERATING STATION TABLE 4A-2 (Cont'd)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY

1. Dates: October 1 - December 31, 1987
2. Type of release: Gas
3. Number of releases during the 4th Quarter: 14
4. Total time duration for all releases of type listed above:

4.55E+04 minutes

5. Maximum duration for releases of type listed above:

2.53E+04 minutes

6. Average duration for all releasea pf type listed above:

3.25E+03 minutes

7. Minimum duration for release of type listed above:

9.60E+Ol minutes

8. Average stream flow (dilution flow) during the period of release: N/A

SALEM GENERATING STATION TABLE 4B-l (Cont'd)

EFFLUENT AND WASTE DI8POSAL SEMIANNUAL REPORT JULY - DECEMBER 1987

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY

1. Dates: July l - September 30, 1987
2. Type of release: Liquid
3. Number of releases during the 3rd Quarter: 61
4. Total time duration for all releases of type listed above:.

l.73E+04 minutes

  • 5. Maximum duration for releases of type listed above:

6.08E+02 minutes

6. Average duration for all releases of type listed above:

2.83E+02 minutes

7. Minimum duration for release of type listed above:

2.13E+02 minutes

8. Average stream flow (dilution flow) during the period of release: 3.18E+05 gpm SALEM GENERATING STATION TABLE 4B-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY

1. Dates: October 1 - December 31, 1987
2. Type of release: Liquid
3. Number of releases during the 4th Quarter: 22

. 4. Total time duration for all releases of type listed above:

5.66E+03 minutes

5. MaximOm duration for releases of type listed above:

3.84E+02 minutes

6. Average duration for all releases of type listed above:

2.57E+02 minutes

7. Minimum duration for release of type listed above:

2.02E+02 minutes

8. Average stream flow (dilution flow) during the period of release: 2.66E+05 gpm SALEM GENERATING STATION TABLE 4B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY ~ DECEMBER 1987

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY

1. Dates: July 1 - September 30, 1987
2. Type of release: Liquid
3. Number of releases during the 3rd Quarter: 62
4. Tot'l time duration for all releases of type listed above:

l.56E+04 minutes

s. Maximum duration for releases of type listed above:

6.14E+02 minutes

6. Average *duration for all releases of type listed above:

2.51E+02 minutes

7. Minimum duration for r~lease of type listed above:

l.12E+02 minutes

8. Average stream flow (dilution flow) during the period of release: 6.42E+05 gpm SALEM GENERATING STATION TABLE 4B-2 (Cont'd)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1987

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY

1. Dates: October l - December 31, 1987
2. Type of release: Liquid
3. Number of releases during the 4th Quarter: 30
4. Total time duration for all releases of type listed above:

7.93E+03 minutes

5. Maximum duration for releases of type listed above:

4.58E+02 minutes

6. Average duration for all releases of type listed above:

2.64E+02 minutes

7. Minimum duration for release of type listed. above:

l.99E+02 minutes

8. Average stream flow (dilution flow) during the period of release: l.18E+06 TARLE 5 Page 1 of 9 7/fH* 9/87 JOI~T OlSTRI~UTIO~ OF WIND OIPECTION AND SP~EO ARTIFICIAL ISLAND DEG C/1001'1 LAP'iE RATE LOC~TIO'i 300FT

( 300-3 HT> LE-1.9 CLISS A SP'.:EOS(l'll/HRJ

'13-111 19-24 25 PLUS SUll! PE~CENT 1-3 4-7 8-12 SUM PE RC ENT SU"! i>ERC'=.NT SUM PE~CENT SUI'! PERCENT  :>UM PERCE.NT SU"I PERCENT DIRECTION N a o.o 0 a.a 0 o.o 0 o.o 0 o. cJ 0 Q.O 0 o.o a.a 0 0. I) 0 0. I) a o.o 0 J.O 0 a.a a o.o NNE 0 o.o a 0.1)

NE *a o.o a 0. 'l 0 o. *) a a.a (] 0. ) 0 a.a a a.a '). 0 '.) I). 0 0 o.o 0 a.o 0 o.o ENE a 0

o. 'l a o.a o.o 0 o.a E 0 I). () 0 a.'1 Q 0 Q.O 0 o.o o.o ESE 0 a.o 0 0 .() I) o. (] 0 o.o 0 O.J 0 0 0 o.o 0 0.1) 0 a.a 0 o.o 0 o.o 0 o.o 0 o.o SE o.o o.o o.o SSE 0 o.o 0 o.o 0 a.a 1 o.o I) 0 1 o.o O.J 0 o.o 0 o.o Q o.o 0 o.o 0 o. \)

s 0 0 o.o o.o o. ') o.o 0 o.o SSW 0 o.o 0 o.o 0 0 J 0 o.o o.o SW 0 a. 'l 0 o.o 0 o.a 0 o.o 0 o.o 0 0 WSW 0 o.o 0 o.o I) o.a 0 o. 0 a a.a 0 o.o 0 o.a II a o.o 0 o.J 0 a.o 0 o.a 0 o.o 0 o.a 0 o.o WNW o.o 0 0. i) 0 a.a 0 o.a a O.J 0 0.') 0 0.1) 0 a o.o I) o.o 0 o.o a o.a 0 O.J 0 a.a 0 o.o NW o. ::J a o.a o.o NNW 0 o.a 0 0 .*J a a.a a I). Q a 0 0 o.o a a.o 0 o.a 1 1).0 a a.() 0 o.o 1 a.a l'IEAN WIND SPEED 14.0 CALPI HOURS 0 PEiUENT CAUi o.o l'IISSING 0

TABLE 5 Page 2 of 9 ARTIFICIAL ISL~~D 7IP.7- 9/6 7 JOl~T OlST~l~UTICN Jf WINa DIRECTION ~ND SP~ED LAPSE RATE LJCATION JCOFT or:;; C/100!"

C300-35FTJ -1.d/ -1.7 CLASS a SP<:EDS01l/HR) 1-3 4-7 8-12

  • n-1 a- 19-24 25 PLUS SUI'! PERCENT DIRECTION SUM Pf~Ci~T Sli1 PE~CENT SUM P~~C~NT 'iUfll PERCC:NT 'SU1'1 PE RC C:N T :iUl'1 PERCENT N J o.u 1J J.J 0 o.o 0 a.a a a. u a a.a 0 o.o NNE a a.a J o. *) 0 Q.O 0 o.o () o.o a a.a 0 a.a Nf a a.J a o.a a J.O a a.a J a.ll a a.o a o.o ENt. a a.a 0 J.J a *). J a a.a a J. ll 0 0.i) 0 a. J E 0 o.o a a.a 0 a.a 0 a.a a a.a 0 a.a 0 a.a ESE 0 I u. :J J O.J 0 a.J 0 a.a J a.u 0 a.a 0 a.a
i
a n.a J a.a 4 0.2 2 0.1 1 a.a a a.a 7 a. :s SSE a a.a a o.o 4 a.2 6 a.3 *l :J. u ( a a.a 1a a.5
i u 0.1) 0 a.a a a.o 0 a.a 0 o.a a a.a a a. I)

SSlll 0 a.a J a.a 0 a.J 1 a.a J Q.J a a.a 1 a.o SW 0 a.o 0 O.J 4 0.2 a a.a a O.J a a.a 4 a.2 llllSW a a.a 0 a.a a o.o 1 o.o l 0.1 0 a.a 4 o.z WNW

... 0 J

o.o a.a i) 0 a.a o.J 0

0 a.a

o. ()

a 0

a.a a.a a

1 a.a a.a 0

0 o.o a.a a

1 a.a a.a N,. a O.J J a.a a I.I. 0 0 o.o 2 0.1 a a.a 2 a.1 NNlll 0 o.J a o.J a a.a l) a.o a o.u Q a.a 0 a.a 0 a.a a J. i) 12 a.5 1a a. 5 7 0.3 a a.a 29 1.3 l'IEAN liiIND SPEED 14. 7 CALM HOURS a PEilCENT CALl1 a.a MISSING* 0

  • I TABLE .S Page 3 of 9 ARTIFICIAL ISLAND 7/87- 9187 JOINT DISTPteuTICN OF WIND DlRfCTI~N AND SPEED L:JC Ill ION JO OFT DEG C/1001'1 LAP'iE RATE

<JOO-BFT> -1.6/ -1.5 CLASS C SPFEDS(l'I/~A) 4-7 e-12 1:!-18 19-24 25 PLUS SUll! PERCFNT 1-3 SUM PE~CENT SU'l PEACF.NT SU., PEACf.NT 3U'l PERCENT SU~ PERCENT DIRECTION SU~ PERCENT 0 o.o 0 1).0 0 o.o 0 o.o a o. o 0 a.a* 0 0.1)

N o.o J o.o 0 o.o 0 o.o Q a.a I) o.o I) o.o NNE ()

o.o 0 o.o a o.o 0 o.o I) o. o NE a 0 .:J *J J.J 0 a.a o.o Ll 0 o.o 0 O.J ENE 0 o.o 0 o.o 0 I) 0 I).

o.o 0 O.l E J I). J 0 o*.) 0 o.o 0 0. IJ I) 0. IJ I) o.o O.:J I) a.a I) o.o 0 o.o \) o.u 0 0 O.IJ ESE J 4 I). ~ 1 (). (} 1 o. o 6 o.3 SE a o.J 0 J.O 0 0.'1

a. o 12 o. '5 SSE 0 o.o 1 'J.O z I). 1 R I). 4 1 *). J 0
a. iJ a o.o s o.o a 1).0 0 o. J 0 o. I) 0 O.J 0 o.o 0

O.'J 0 o.o 1 O.il 0 IJ. *) 0 .J. u a o.o 1 SSW ()

-* o. o 0 O.IJ 2 0.1 SW 0 o. J J O.'l z U.1 I) 0. I) 0

o. i) o.o o.o a o. CJ () Q.i) 0 0. ') 1 o.o 0 0 1 o.o WSW J.O 0 o.o 0 o. ,) i) o.u 0 o. a 0 w 0 ci. ') 0 a o.o 0 o.o 1 O.J a a.a 1 o.o WNW 0 i).0 a J.J o.o a o.o 4 O.l N.. 0 o.a 'J O.J 0 o.o 3 0.1 1 o.o NNll . () o.o 0 *J. 'J 0 o.o 1 o*.) J o. :.I 0 O. IJ 1 a.a 1 o. a 5 f). 2 17 o. ii 4 J. l 1 o.o 28 1.3 0

MEAN WIND SPEED 15.6 CHI" HOURS 0 PERCEhT CAUi o.o MI SS ING 0

TABLE 5 Page 4 of 9 7/'d7- 9/r:.7 JOI~T DISTRI~~TICN OF ~I~D ~IRECTION AND SPiEa ARTIFICIAL ISLAND DEUl'I PERCENT D1111: CTlON 21 1. ') 2!1 1 * .s 8 0.4 1 o. a 0 o.o oo 2.7 Ill 2 0.1 o.o 69 3.1 o.o 19 0.9 H 1.d 10 0.5 1 0.1) 0 NlllE 0 o.o 40 1.d NE 1 a. J 11) u.s 23 1.0 6 o* .s *) O. l.l 0

0. 2 1a 0.5 1 a.o l.) a.J 0 a.a 1S 0.3 ENC. ~ 0.1 5 E a a.o b u. 3 13 a.6 2 0.1 a a.a a a.a 21 1.a ESE 0 o.o j a., 7 o * .s 4 o.z 2 0.1 0 a.a 16 0.7 0.3 <'3 1*o 3o 1.0 21 ,
  • ll 10 I). 5 1ao 4.o
iif 4 0.2 0 0.3 172 7.8 1 o. :> 1 () 0.7 44 2. :> 71 3. 5 3? 1.5 6 SSE , *7 d J.4 I] o.o ~1 3.7
i 2 0.1 17 o.~ 16 0.7 J8 0 .4 1d 0.3 24 1.1 1 :l 0.5 0 ().0 64 2.9 SSllll 4 Q.2 !l o.o 58 2.6 u o.o 14 o. C) 20 o.~ 20 0.9 4 0.2 ()

Siii

~ 0.4 21 1.0 15 0.7 0 J. j 0 o.o 51 2.3 w:. ..

Ii 0

1 O.J o.o 7 o.3 21 1. () 14 0.6 0 O. ll a o.o 43 z.o 12 0.5 3 0.1 0 *J.O 40 1.8 WNlll 1 a.a 10 J.5 14 Q.6 19 o. \I 'd 0.4 J o.o 66 3.0 Niii 0 0. *) 9 0.4 30 1.4 NNll 3 0.1 H o. ~ 43 2.0 13 O.o 3 0.1 '-

0 o.o 51 3.7

16. 9 295 n. s H 4.5 . 1o 0.7 9~0 44.7

'1 1. 0 179 3.2 Ha MEAN llIND SPEED 12.0 CALM HOURS 0 PERCEhT CALM o.o fltISS lt.IG 8

TABI.E 5 Page 5 of 9 ARTIFICIAL ISLAN1> 7/f'7- 9/P7 JJl~T DISTPieUTICN OF WlN~ OJQ~CTIO~ ANO SP~E~

L'lC AT IOf\I JC OFT iH(i C/1001"1 Ll'PSE UTE

< jlJQ-3 3FT) -'l.4/ 1.5 ClAS'i  !:

5pq :l5(f'II/HR) 1-.5 r.-r ll-1 2 1 !-1 ii 1Q-24 25 PLUS SUP! oo;:qc~NT DIRECTION SU"l PBC F.11. T iU'1 PEHS:NT '5U"'I "ERCENT SU~ PEQC~NT ;iU:-1 PEQC~n SU'1 PERCENT N 2 I). 1 .n  :)

  • 5 12 '). 5 25 1* 1 J ll.} 0 o.o 57  ?.6 NNE 5 1). 2 11  :). 5 h '). 7 ~1 1. 4 ~ -)
  • 1 I] o. o 65 J.O NE 4 J.2 3 I]. 4 11 0.5  ;:a 0.9 l l). 1 0 O.::J 46 2.1 ENE J o.o .5  !)
  • 4 10 0.5 5 '). 2 *J  !) * :) 0 O.:J 23 1
  • I)

E 3 0.1 7 )* 3 21 1. iJ B o... ) u. J 0 o.o 39 1. ~

ESE 2 0 .1 1 J.J 15 0.1 311 1. 3 1 J. l)  !) o.o SC  ?.

  • I)

SE J 0.1 13 J.6 Z'3 1 ~ i) 37 1.7 16 *l. 7 11 0.5 1 l'J '5 4.7 SSE :J o.o 12 0.5 26 1.2 11 I). 5 4 I). 2 1 o.o 54 2.c;*

s 2 0.1 1.2 0.5 15 0.7: 20 . C! * ., i .). 4 0 O.'l 57 2.6 SSlll 1 c.o ~ 0.4  ? 0.4 22 1.0 6 a. 5 0 o.o 47  ?.1 SW z o.1 p  !) * ~ 24 1*1 19 o.o i 0.4 0 o.o 72 3.3 WSW 4 oJ. 2 H ).5 21 1*J 19 I). \I 11 0.5 0 o. (J 67 S.1 w 0 O. J l4 1* 1 2~ 1. 2 16 *J. 7 z  !)

  • 1 0 o.o 68 3.1 WNll 1 O.J ~ 0.4 27 1*2 .15  !)
  • 7 6 J.3 0 o.o 5'l 2.6 NW 3 I) .1 7 0.3 26 1. 2 l7 1.7 7 a. :s 2 0 .1 82 3.7 NNW 3 0.1 1J 0.5 23 1.0 1 'J. 0.9 1 J.J z J.1 58 2.6 35 1.6 174 7.) 305 13. Q 54~ 15. 6 81 5. 7 16 0.7 954 4 3. 5 "IEAN WIND SPEE?> 1i!. 0 CAUi HOURS 0 PBCENT CALM c.o lllISSING 1

TABLE 5 Page 6 of 9 ARTIFICIAL ISLAND 7Je7- 9/87 JOl~T DISTRitUTION Of ~I~D DI~ECilON AND SP~~O L*)Cl.TION lOOFT Dl Ii C/100M LAP SE llAH ChlO-BFT> 1. 6 I 4.') CLASS f SPEEDS CHI/HR) 1-.s 4-7 l!-1l 13-1 d 19-24 25 PLUS SUM PERCENT DIRECTION SUf'I PERC ~t.T Sl.i:'I PEH El'lT :a."1 PERCENT :iU!'I PERCENT SU:'! PERC~NT ~U:'I PERCENT N :l o.J (I J. 3 4 o.z 6 o* .s J o.o 0 o.o 16 0.7 NNE u O.tl z t) .1 d 0.4 11 o. 5 0 o.o 0 a. o 21 1.a lllt () o.o 0 o.J 2 0 *. 1 11 o.; 2 J.1 () o.o 15 0.7 ENt 0 J.O 1 O.*l 2 u.1 3 0 .1 1 o.o 0 !l.O 7 0.3 f 1 a.a l 0.1 1~ ll. 3 4 0.2 a o.u 'l o.o 26 1.2 ESE 1 o.o 0 o.J l 0.1 7 0.3 0 o.o 0 o.a 11 o.s lie () o.o z  !)

  • 1 2 0 .1 1 o.o l 0.1 0 o.a 8 0.4 S~f a a.a 6 O.l 4 o.z 3 0.1 0 a.a a o. 'l 1l 0.6 s 2 :J. 1 2 0.1 l 0.1 1 O.J J J. ll 0 o.o fl 0.4 SSlll 1 J.J 1 I) .o 0 o). J 1 o.o z 0.1 0 a. 'l 5 0.2 s .. 0 o.o 1 O.*J 3 J .1 4 0.2 2 0.1 0 o.o 10 0.5 WSW 0 O.J 1 o.J 1 0. <J l 0.1 0 o. J 0 a.a 5 '0. 2 Ill 1 o.o 1 ). ') 1 a* .J 3 0.1 1 a.a 0 o.o 7 O.l Wiii,. a o.o 0 0. LI 2 J .1 8 0.4 0 o.u 0 a.a 10 0.5 Niii 1 o.a 1 i). tl 4  ;). l 5 0.2  !) -J.O a o.o 11 0.5 NNlll 0 o.o 2 a*.1 7 O.l 8 0.4 tl o.o 0 o.o 17 0.8 0.1 29 1. l 64 z.9 79 3. 6 11 o.; *a o.o 190 8.7 7

MEAN WilllD SPi;E D 11.9 CAUi HOURS

  • 0
  • PEilCEt.T CALM o.o MI ~S INCi 0

t *I TABLE 5 Page 7 of 9 ARTIFICIAL ISLAND 7187- 9/67 JOINT DlSTRl~UTICN OF ~IN~ DlP.ECTICN AND SPcED LOCllTIC~ 3COFT Dl:G C/100[1'. L'PH PAH UJ0-3 HT) liT. 4.IJ CLASS G SP~EDS(l"I/HP) 1-3  :.-1 8-1 !'. U-H 19-24 25 PLUS SUl"I PERCF.NT DIRECTION SUM PERCHT SU"I PERC:NT 'iU"I PE~CENT 5Ul'I PEF!CENT 5U'1 PEllC".NT :iU"I ?ERCENT

o. o a a. a o.o o. a o. IJ NNE 1\1 0 J ) .') 1 o.a 0

I)

O. IJ 0.1)

I)

I) IJ .1

!)

a

!) *

a. ll 0 0 0 o.o 0

0 o. o NE 0 J. IJ *J .J.O 1 u. *) 1 o.o 0 O. 'I 0 o.o z 0.1 ENE a O.IJ a J.J 0 O.J 4 I). z 0 o.J 0 o.o 4 I). 2 E a o. '.) l J.IJ z IJ. 1 2 0.1 J (). J 0 a. IJ 4 o.:?

ESE 0 o.o J o.o 0 o.o 1 a.a 0 o.o  !) o.o 1 o.o SE ') o.o IJ O.J 0 o.o 0 o.o I) J.J 0 o.o 0 0.1)

SSE a o.o 0 '). J 0 o.o 0 o.o 0 O.J 0 o. o 0 o.o s 0 o. Cl il O.J 0 f). 0 0 o.o 0 O. ll 0 o.o 0 o. o SSlll 0 a.o J I). !J 0 o. a 0 o. ') 0 Q. l.) a a.a 0 o.a SW 0 a. iJ a IJ. ') I) O.J ') o.o 0 0. IJ 0 0 .IJ 0 . o.o WSW 0 o.a a a. '.l 0 o. 0 0 o.:) J o.a 0 a.o 0 o.o w 0 o~o a o.o 0 a.a 0 0. ') 0 o. J 0 o. o 0 o.o WNil a O.oJ a o.o 0 o.o 0 a.a J a.J 0 a.a 0 a.a NW 0 a.'l Q a.o 0 o.o I) I).*) Q o. (J 0 a.a 0 o.o NNW 0 O.J a fJ. ()

0 O.:J 0 o.o 0 O.J 0 a.a 0 0.1}

0 I). 'l 0 a. a 3 0.1 8 0.4 0 o.o 0 o.o *11 I). 5 MEAN WIND SP'EED 13.0 CALl'i HOURS 0 PERCENT CALlll o.o 11111 SS INS 0

~

.. (~ .

TABLE 5 Page 9 of 9 ARTIFICIAL I SL ANO 7187- 9/87 JOPH DISTRI!'UTICN OF ~IND DIPECTION Al'.;D SP EEO L0 CA:-' cl'l JCOFT DE *:i C/100~

(30U-BFT) DIRECTI'.lN vs SP'O E'>

'iPi:EDSCMI/W')

1-.S .-7 F.-1 ~ 1 ~-1 3 19-2 4 25 PLUS SUM PJ:RCENT DIRECTION SUM PE 'IC'::~ T SU"1 PS::~C'ONT SU"' PE RU NT su:~ Pfl!CC:NT SU"l PERCE~T SUM PERCENT N ,. IJ. 2 H 1* i 44 2.0 JQ 1 * 'I 7 1). J 0 o.o 133 6.0 NNE 5 'J. z 3~ 1* 5 6~ 7.. ~

s"  ?.4 l *). 1 0 o.o 1 55 7. ll NE 5 o.z n I). 3 H 1*7 3 '3 1.7 5 0.2 0 o.o 10'5 4.7 ENE ~ Q. 1 15 0.7 22 1. tJ 13 r). ei 1 o.o 0 o.o 5J 2.4 E 4 'J.2 1~ *). 7 54 <. 5 16 0.7 0 o.o 0 J.O 90 4.1 ESE s 0.1 4 I). z 25 1. 1 'i 1 2 * .s 3 0.1 a o.o 86 3.0 7 '). 3 21 1*J 52  ?.t. .30 3. 6 42 1 **, 22 1 * ::J 224 11). 2 SE SSE 1 o. i) J) 1. '> 81) "3. '> 1 02 4. 6 37 1.7 7 o. "3 2'>2 11.Q s ~ o.s 31 1.4 34 1. 5 5Q 2. 7 16 u. :- 0 o.o 146 6.6 SSW !I o.s B *). 8 "'3 1. ~ 4'1 2.2 13 o. ti 0 o.o 1P . 5. 4 s .. 2 0.1 34 1. 5 53 2.4 4J 2.0 14 O.b 0 o.o 146 6.6 WSW 4 o.z 23 1.a 4J 2.0 39 1. 'I 20 0.9 0 o.a 129 5.9 WNW

. 2 2

0.1 0.1 32 20 1* 5 Q.9 48 43 2.7 2.0 33 H

1. 5 1.6 11 s \). 1 o.s 0

0 o.o o.o 118 111 5.4 5.0 NW 4 0.2 17 0.8 63 2.~ 64 2.9 H 0. r:I z 0.1 16R 7.6 o.J 31 1.4 73 3.J 41 1* 9 4 0.2 2 I). 1 157 7.1 NNW 6 63 2.9 JO:i 1 7 .!> 762 34. 7 753 34. z 202 '1. 2 n 1.5 2199 100.0 li'lSSI~G HOURS 9 l'IEAN WIND SPEED 12 .1 TCTAL NUl'IBER CF CALI'! HOURS 0 PE'ICENT I). 0 FCRTP.Ar.I STOP XDtL~TE-W-SEARCHFAIL, EP'ICR HARCHIN:i FO~ 5YS,SYSR~OT:[SYSMGR.MES.PRODWRl~RLAPSE.LIS;*

-R"1S-E-FNF, FILE NOT F:JUNO XDELETE-I-FlLCEL, SYSSSY~AOOT:[SYS~GR.~E5.PRODWP]WqLAPSE.03Ji1 DIELEHD (42 3LCCKS)

XDEL~TE-I-FILC~L, SYStSYSROOT:[SYS~G~.MES.DROC~R]WP.LAPSE.lXEi1 o:LETED C4C 9LCCKS)

TABLE 6 Page l of 9 ARTIFICIAL ISLAND 10/87-12/87 JOINT DISTRieUTION OF WIND DIRECTlON.AND 3PEED LOCATlCN 300FT DlG C/100,., LAPSE RATE

<lOu-3HT> LE-1.9 CLASS A SPEEDS(llI/HR) 8-12 13-1 9 19-Zlt 25 PLUS SUM PERCENT 1-3 4-7 SUlll PERCENT SUI'! PERCENT SUM PE RCfNT SUl'l PERCENT SUM PERCF.NT DIRECTION SUlll PERCENT o.a 0 0.1) 0 a. o 0 o.o a o.o 0 o.o 0 o.o N 0 a o.o o.o 0.1) 0 o.a Q o.o 0 o.o 0 o-.o 0 0 o.o NNE a.a 0 a.a a a.a a o.o a a.u a o.a a NE 0 a a.a o.o 0 a.a a o.a 0 o.o 0 a.a ENE a o.a 0 a a.a a a.a a.a 0 o.o E a o.o a a.a 0 a.o 0 o.o. o.o a o.o a a.*l a a.a a a.a a a. u Q 0 ESE a.o a o.a 0 o.o 0 0.1.1 a o.o 0 o. !)

SE 0 a.a J o.o a.a 0 o.a 0 o. o SSE 0 o. () a o.a 0 o.o 0 0 o.o a o.a s a.o a.a a a.a 0 o.a 0 a.a 0 0 0 a ().a o.o 0 o.o 0 a.o 0 o.o 0 o.o SSW a o.o 0 o.o a a. I) 0 o.o a o.o SW 0 o.o a a.'.) 0 o.a 0 o.a o.o

a. o o.o *o a.a a o.o 0 a. ll 0 0 WSW 0 0 a.a a a.a a.o a a.a a o.a 1 a.a w 0 o.o a 1 a o.o a.a 0 o.o WNW 0 a.a 0 o.o 0 o.o 0 O.iJ 0 a o.a a.a o.o () a.a 0 o.o a a.a 0 a.a 0 a.')

NW 0 a a.a o.a a a.a a a.a () o.o a NNW a o.o 0 o.o a o.o 1 a.a 0 a.a 0 a.a 1 a.a a a.o a lllEAN WIND SPEED 18.0 CAL" HOURS 0 PERCENT CALM o.o

!'IISSINCi 0

'* ~ ~

  • TABI.E 6 if-

CALI'! HOURS a PERCENT CAL" o.o MISSING 0

TABLE 6 Page 3 of 9 ARTIFICIAL ISLAND 10/87-12/87 JOINT DISTRIBUTION OF ~IND DIRECTION AND SPEED DEG C/1001'1 LAPSE UTE LOCATION JOOFT

<300-BFT> -1.6/ -1.5 CLASS C SPEEDS(ll'I/HR>

1-3 4-7 8-12 13-18 19-24 Z5 PLUS SUl'I PERCENT DIRECTION SUl'I PERCENT SUfll PEltCENT SUI'! PEIH ENT SUM PERCENT SUt'I PERCENT SUfll PERCENT N 0 o. () 0 0.') 0 o.o 1 o.o z 0.1 0 o.o 3 0.1 NNE 0 o.o 0 a.a 0 o.o 0 o.a 0 o.o a a.a a a.a NE a o.o a O.iJ 0 o.o 0 o.o a o.o 0 a.a a a.a ENE a a.a 0 a. *J a o.o a o.a 0 O.J a a.a 0 a.IJ E a a.a a. a.a 0 0.1) 0 a.a a a. iJ 0 a.o a o.o ESE 0 a.a 0 o.o 0 o.o a a.a a o.o 0 a. o 0 a.a SE a o.o 0 o.o 0 . o.o 1 o.o a 0. tJ a a.o 1 a.a 0 a.a 0 o.a 0 o. '] 0 a.a 1 O.J 0 o.o 1 o.a SSE s

SSW 0

0 o.o o.o 0

0 o.a O.iJ 0

0 o.o o.o 0

1

o. 0 o.a a

0 o.o a.a 0

0 o.o o.o ,

0 o.o o.o 0.1 SW 0 o.o z 0.1 a o.o 0 o.:> 0 o. o 0 o.a 2 WSW 0 o.o 0 a.a a o.o 0 o.o - 0 o. 0 0 o.o 0 0.1) w 0 o.o 0 O.'l 0 a.o 0 o.o 0 o.o 0 a.a 0 o.o WNW 0 o.o 0 o.o* 0 o.o 0 o.o 3 0.1 z 0.1 5 o~z NW 0 o.o 0 O.*l a o.o 2 a.1 7 0.3 1 o.o 10 0.5 NNW 0 o.o 0 o.o 1 o.o 0 o. a. l) o.a 0 a.o 1 a.a 0 o.o z a.1 1 o. o 5 0.2 13 0.6 3 0.1 24 1.1 PUAN WIND SPEED 20.0 CALI'! HOURS 0 PERCENT CALM o.o PUSS ING 0

._ . )

~. {o  ;

  • t "'°!-
  • TABLE 6

"' 1 '

  • Page 4 of 9 ARTIFICIAL ISLANl 10/87-12/87 JJINT DISTRleUTlCN OF WIND DIRECTION AND SP~ED LOCATION JOaFT Dt.'.i C/100111 LAPSE RATE 000-JJFT) -1.4/ -a.5 CLASS D SPEEDSCfllI/ltR) 1-J 4-7 E!-1 z 1 J-18 19-24 25 PLUS SUM PERCENT DIRECTION SUl1 PERCENT SU" PERCENT SUl'I PERCENT SUl'I PEACfNT :iU" PERCENT SU"I PERCENT N 1 o.o ] (). 1 7 O.J 11 a.5 7 a.5 4 a.2 33 1.5 NNE 1 o. i) 7 o.:s 7 \). J 20 0.9 10 a. 5 ] a.1 48 2. z NE. 0 a.o 1 o*.J J 0.1 13 a.o z 0.1 a o.o 19 a.9 ENE a a.a 2 0.1 2 u.1 8 0.4 J J.1 a o.o 15 0.7 E 0 a.o 2 a.1 1 a.a a a.o () a. tJ a a.a J a.1 ESE 0 o.o J a.1 0 a.a 1 o.o a o.o a o.o 4 0.2 SE a 11.0 J 0.1 1a 0.5 5 a.2 5 0.2 z 0.1 25 1.z SSE 0 a.a 5 0.2 9 a.4 11 a.5 9 0.4 0 o.o 34 1.6 s a a.a 4 o. z 12 a.6 17 a. a 0 a. 5 5 0.2 44 z.o SSW 0 o.o 5 u.2 7 ll. 3 1J a.6 a o.o z 0.1 Z7 1.Z SW 4 o.z cl 0.4 9 a.4 8 0.4 1 o. o 1 a.a 31 1.4 WSW 0 a.a 6 0.5 1J 0.6 17 0.8 7 0.3 J 0.1 46 2.1 w 2 a.1 5 a.z 2a a.9 19 a. 9 H 1. s 18 o.s 97 4.5 WNlll 1 o.o ~ ().4 9 a.4 21 1.a 33 1.5 21 1 .1 95 4.4 Niii 0 o.o 6 a.s 13 a.6 21 1.0 44 2.a 55 2.5 139 o.4 tdOI 0 o.o 4 o.z 18 a.s 11 0.6 10 0.5 6 0.1 51 Z.4 9 0.4 7Z ]. J 140 6.5 198 9.1 17il 7. 8 122 5.6 711 12.s "EAN WIND SPEED 16.9 CALM HOURS 0 PERCENT CALM o.o MISSING 27

~

TABLE 6 Page 5 of 9 ARTIFICIAL ISLANO 10/87-12l87 JOINT DISTRI0UTIO~ OF WIND DIRECTION AND SPEED L()C ATION 30uFT DEG C/1001' LAPSE !UTE CJ00-3 5F T> -o. 4/ 1.5 CLASS e.

SPEEDSCMI/llq) 1-3 4-7 B-H 13-18 19-24 25 PLUS SUM PERC~NT SUflll PERCENT suiil PERCENT SU"! PE~CENT SU"' PERCENT SUM PERCENT SU"I PERCENT DIRECTION o.o 3 0.1 12 o.~ 30 1.4 11 o. s 7 O.l 64 3.0 1

NNE N

2 0.1 4 o.z 9 o.4 11 0.5 6 o. 3 4 o.z 36 1.7 NE 0 o.o 4 o.z 6 0.3 12 0.6 a O.J 0 o.o 22 1.1) 0.4 10  :). 5 0 o. IJ 25 1.2 ENE 2 0.1 z 0.1 ] 0.1 8.

z 13 0.6 z o.z 0 o.o 3 0.1 1 o * .J 0.1 ESE E

z 0.1 0.1 5

2 0., 5 r:i. 2 6 0.3 13 0.4 O.l 11 5 o. z 0.5 ZB 66 1.l

3. \)

SE 0 o.o 3 0.1 10 0.5 35 1.6 0.8 17 7

0~3 7 o.]. 68 3.1 SSE 3 0.1 6 0.3 18 0.8 17 s 4 o.z 12 0.6 11 O;, 5 25 . 1. 2 21 1.0 1 o.o 74 3. 4 8 Q.4 29 1.3 42 1.9 19 0.3 8 0.4 110 5.1 SSW 5 o.z o.o 83 l . l'.I o.z 6 o. :s 15 0.7 H 1.8 20 (). 9 0 SW 4 9 0.4 0 o.o 55 2.5 WSW l 0.1 6 0.5 16 0.7 21 1. 0 o* .? 19 0.9 48 2. *2 33 1.5 3 0.1 111 5.1 w' ] 0.1 5 104 4.a 1 o.o 9 0.4 18 0.8 44 2.0 21 1.0 11 0.5 WNW 16 0.7 130 6.0 NW z 0.1 14 0.6 16 0.7 31 1.4 51 2.4 o.o 6 O.l 16 0.1 11 0.5 10 0.5 3 0.1 46 2.1 NNW 0 95 4.4 203 9.4 382 17. 6 245 11.Z 7!J 3.6 1035 47.9 34 1.6 "UN WIND SPEED 15.l CALM HOURS 0 PEqCENT CALM o.o

!III SS ING 13

.. TABLE 6 tr ~ t.' *

~

Page 6 of 9 I

ARTIFICIAL ISLAND 10/87-12/d7 JOINT OISTRl&UTICN Of WINO DIRECTION ANO SPEED LOCATION :SOOFT OECi .C/100111 LAPSE UH OOU-HFT> 1.6 I 4.0 CLASS f SPEEDS Oii/HR) 1-:s 4-7 e-12 13-18 19-21t 25 PLUS SUM PERCENT DIAECTlON Sli" PERCENT SUl1 PERCENT SUllll PERCt:NT SUM PERCENT SUM PERCENT SUM PEitCENT N 0 a.a 2 a.1 6 o. 3 14 a.6 2 a.1 a a.a 24 1.1 NNE 0 a.a 2 0.1 s* 0.2 5 o. 2 6 o. :s D o.a 18 o. 8 NE 0 f).0 1 o.o 0 o.o s 0.2 1 o.u D o.a 7 o *.. J ENE 0 o.o 2 0.1 4 O.l a o.o il  !) * :) a o.o 6 o. 3 E 0 o.a 2 0.1 4 a.2 1 o.o i) o.o 0 o. i) 7 Q.3 ESE 0 o.o 4 o.z 2 0.1 3 0.1 . 1 o. i) 0 o.o 10 o.s SE 0 o.o 2 0.1 2 0.1 13 0.6 1 0. \) 0 0.3 24 1.1 SSt 1 o.o 0 o.:s 6 o. 3 7 a. :s 9 o ... 8 0.4 H 1.7 s 0 o.o 4 0.2 7 a. 3 12 0.6 s a. 2 1 o.o 29 1.3 SSW 1 o.o 2 0.1 4 0.2 27 1.2 15  :>. 7 d 0.4 57 2.6 SW 0 Q.a ] 0.1 7 0.3 19 0.9 9 0.4 0 o.o 38 1. !I WSW 0 o.o 2 0.1 ] 0.-1 6 o. 3 3 0.1 0 o.o 14 0.6 w 1 o. 0 4 a.2 1 o.o 2 0.1 1 o.o 0 o.o 9 a.4 WNW 1 o.o 3 0.1 .0 o.o 0 o.o 0 o.o 0 o.o 4 a.2 NW 1 o.o 1 o.o l 0.1 . :s 0.1 () o. () 0 o.o a 0.4 NNW a o.o 1 a.a 8 0.4 s a.2 0 o.a 0 o.o 14 a.o 5 o.z 41 1. ~ 62 2.9 122 5. 6 53 2.4 2l 1.1 306 14.1 MEAN WINO SPU.D 14.9 CALM HOURS 0 PERCEhT CALM o.o IUSSING* 1

TABLE 6 Page 7 of 9 ,.

ARTIFICIAL lSLAhO 1~/87-12/87 JOINT DISTRlbUTlON OF WIND DIREtTION AND SPEED LOCATION 150FT i>EG C/100M LAPSE RATE "

<300-HFTJ GT. 4.0 CLASS G ,

SPEEDSOll/HR>

1-3 4-7 e-12 13-18 19-.24 25 PLUS SUM PERCENT ,

DIRECTION SUM PERCENT SUfll PERCcNT SUM PERCENT SUM PERCENT SUi't PERCENT SUM PERCENT N a o.a 0 o.a 1 o.o 0 o.o a o.o 0 o.o 1 O.J hNE 0a .. o.o 0 o.o l 0.1 l 0.1 0 O.J 0 o.a 6 O.l NE o.o 1 a.a 2 a.1 a a.a 0 o.o a a.a J a.1 ENE 0 o.o 2 (j. 1 4 0.2 0 a.a 0 a.J a a.a 6 a.l E 0 a.a 2 a.1 2 a.1 0 a.a a a.o a o.o 4 o.z ESE 0 a.o 0 o.a l 0.1 2 a.1 0 ;J. J 0 o.o 5 0.2 Sc 0 a.o 2 0.1 1 o.o 1 o.o 1 O.J 0 a.a 5 0.2 SSE 2 0.1 0 a.a 4 o.z 5 o.z 2 a.1 0 o.a 13 o.o o.o 3 a.1 4 a.2 a J. I) 0 o.o 7 O.l s a o. i) a a.z 0. i) 0 o.o 7 a.l SSlll 0 o.u 2 0.1 0 a.o 5 J I) o. i) 0 o. f) 2 0.1 0 o.o () o. il 0 o.o 2 0.1 Siii o.o a a.a 2 0.1 a o.o a a. :J 0 a.a 2 a.1 WSW 0 0 a.a 0 a.o w 0 a.o 0 o.a 0 o.o a o.a 0 o.o WNW I) o.o 0 O.J 2 0.1 a o.o 0 a.J 0 a.a 2 0.1 tol 0 o.a J o.o 0 a.a a a.a J a.J 0 a.a 0 o.o NNlll 0 a.o () o.o 3 a.1 a o.o J a.a 0 a.a 3 0.1 2 0.1 9 0.4 J2 1.5 2a 1.0 l 0.1 0 o.o 66 J.2 MEAN WIND SPEED 11 .1 CAUt HOURS 0 PERCEU CALM o.o MISSING 16

\

    • 1 ,I) ...... Ii ~ ( [~. ~ ~l

.. . * <Ii TABLE 6 ' .. .. .. .'

Page 8 of 9 ARTIFICIAL ISLAN~ 10/87-12/67 JOINT DlSTRIBUTICN OF WIND DIRECTION AND SP~ED L'JC AT ION lOOFT DEG C/1001'1 LAPSE RATE ClOO-BFT> ALL STAislLITIES SPEE DS(MI/ tiR) 1-3 i.-7 e-12 13-18 19-21t 25 PLUS SUI'! PERCEtH DIRECTION SUit PERCENT SUit Pl:'H ENT SIJM PERUNT SUM HRCENT SUM PERCcNT SUM PERCENT N 2 0.1 8 0.4 27 1. 2 56 z. 6 zz 1. 0 11 0.5 126 5.d Nt.E 3 0.1 13 0.6 21 1. 0 40 1.8 24 1.1 7 0.3 108 5.0 NE 0 o.o 6 O.i 9 0.4 31 1.4 4 i). 2 0 o.o 50 2.3 ENE 2 0.1 6 0.3 10 0.5 16 0.1 13 O.o 0 o.o 47 2.2 E 2 0.1 9 0.4 10 0.5 5 0.2 1 o.o 2 0.1 29 1. l ESE 2 0.1 10 o.s 11 0.5 15 0.7 1J J.6 5 0.2 56 2.6 SE 0 o.o 8 0.4 24 1 .1 57 2.6 H 0.6 19 o. ~ 121 5.6 SSE 4 0.2 1d a.d 36 1.7 37 1.7 H 1. :s .!O 0.9 153 7.1 s 5 0.2 21 1.0 31 1.4 57 2. 6 37 1. 7 a 0.4 1 59 7. l SSw 6 0.3 1 ti O.d 42 1.9 84 3.9 37 1.7 18 0.3 205 9.5 Siii 8 0.4 20 0.9 32 1.5 65 3.0 31 1.4 1 o.o 157 7.2 WSil 3 a.1 14 0.6 33 1.5 47 2.2 21 1. 0 l 0.1 1 21 5.6 Iii 6 a.l 14 a.6 40 1.e 70 3. 2 69 l. 2 21 1. 0 22a 1c.2 lllNill 3 0.1 20 0.1 27 1. 2 67 3.1 57 2. :i 36 1.7 210 9.7 Nill l 0.1 21 1.1) 34 1.6 59 2.1 101 4.d 72 3.l 292 11.5 NNlll 0 a.a 11 0.5 41 2.a 29 1.1 20 o. ~ 9 0.4 112 5.2

-.. ~

49 2.3 217 1 a.a 430 19. 9 715 33.9 5al 2 3. 2 lH 1 o. 7 2166 1oa.o MISSING HOURS 42 MEAN WIND SPEED 15. 8 TOTAL NUl'ISER Of CALM HO~RS 0 PERCENT a.a

TABLE 6 Page 9 of 9 ARTIFICIAL ISLAND 10/87-12187 JOI'41 DISTRIF.!UTICN OF WIND DIRECTION AND SPEED LOCATION 30r)fT DEG C/1001'1 U00-3 HT) DIRHTION VS SPEED SPEEDS (I'! I/ HR) 1-3 4-7 e-H 13-18 19-21. 25 PLUS SUM PERCENT DIRECTION SU" PB CENT SU:'1 PERCENT SUM PERCENT SU!"! PEllCENT SU"'I PERCENT SUl1 PE RC ENT N 2 0.1 8 Q.4 27 1.2 57 2.6 22 1.0 11 0.5 1 Z7 s*. 9 NNE 3 0.1 13 a.o 21 1. 0 41) 1.3 24 1. 1. 7 0.3 108 5.0 NE 0 o.o 6 o. J 9 0.4 31 1.4 .~. .J. z 0 o.o 50 2. 3 ENE 2 0 .1 ~ 0.1 10 0.5 16 0.1 1l 0.6 0 o.o 47 2. z E 2 I). 1 9 0.4 10 0.5 5 0.2 1 o.u 2 0.1 29 1. 3 ESE 2 ') .1 10 o.s 11 I). s 1'i 0.7 13 0.6 5 0.2 56 2.6 SE a a.a 3 0.4 24 1.1 57 2. 6 1.S O.b 19 0.9 1 21 5.6 SSE 4 \J.2 1d O.SJ 36 1.7 H 1.7 3 !! 1* 3 20 0.9 153 7.1 s 5 0.2 21 1.*J 31 1.4 57 2.6 J7 1. 7 8 0.4 159 7.J SSW 6 0.3 113 o. /I 42 1. Q 84 3. 9 37 1.7 18 o. !! 205 9.5 SW 8 0.4 20 o.~ 32 1. 5 65 3. () 31 1. 4 1 o.o 157 7.2 WSW 3 0.1 14 0.6 33 1.5 47 2.2 21 1.0 J 0.1 121 5.6 w 6 0.3 14 0.6 40 1. SJ .10 3.2 69 3.l 21 1.0 2 20 .10.z WNW 3 0.1 20 Q.9 27 1.2 67 3.1 57 z.o *H 1. 7 210 9.7 NW 3 0.1 21 1.0 34 1.6 59 2.7 103 4.J 72 3. 3 292 13.5 NNirl 0 o. a 11 o.s 43 2.0 29 1. 3 20 0.9 9 0.4 112 5.2 49 2.3 217 1 o.o 430 19. ':l 736 :54. 0 503 2 3. ;! 232 10.7 2167 100.0 fHSSING HOURS 41

!'llEAN WIND SPEED 15.8 TOTAL NUMBER CF CALM HOURS 0 PERCENT o.o FORTRAN STOP

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AMENDMENT TO SALEM RERR-22

See Summary Tables 2A-2 and 2B-2 for Salem Unit 2 Operations.

Part D. SOLID WASTE See Summary Table 3 for Units 1 and 2.

Part E. RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on actual locations of nearby residents and farms. The population dose impact is based on historical site specific data 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 tor the six month reporting ~nterval. Individual doses from batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as described in the Offsite Dose Calculation Manual.

Population doses were calculated using the meteorological dispersion coefficients for the six month reporting interval.

Liquid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathway. The total body dose to an individual was calculated to be 2.36E-01 mrem. The calculated highest organ dose from liquid releases was l.36E+OO mrem to the gastrointestinal tract. The calculated population total body dose was l.39E-01 person-rem. The calculated average total body dose to the populatioh within fifty miles of the site was 2.60E-05 mrem/person.

Air Pathways*

The resulting total body and skin doses to an individual were calculated to be 2.38E-02 mrem and 5.34E-02 mrem respectively. The calculated highest organ dose due to

"* radioiodines and particulates with a greater than eight day half-life was 2.97E-02 mrem to the thyroid. The calculated population total body dose was 9.llE-01 person-rem. The

  • calculated average. total body dose to the population within fifty miles of the site was l.70E-04 mrem/person.

SALEM GENERATING 8TATION TABLE 2A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1987 UNIT l LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1st 2nd Units Quarter Quarter Est. Total Error, %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 5.66E-Ol l.36E+OO 25%
2. Average diluted concentration during period uCi/ml 7.36E-08 8.65E-08
3. Percent of applicable lim~t (T.S. 3.11.1.2.(a))  % 3.97E+OO 5.03E+OO B. Tritium
1. Total release Ci l.lUE+0.2 l.45E+02
2. Average diluted concentration during period uCi/ml l.43E-05 9.20E-06
3. Percent of applicable limit  %

(T.S. 3.11.1.1) 4.78E-Ol 3.07E-Ol

c. Dissolved and entrained noble gases
1. Total release Ci 3.54E-01 8.87E-Ol
2. Average diluted concentration during period uCi/ml 4.60E-08 5.65E-08
3. Percent of applicable limit  %

(T.S. 3.11.1.1) 2.30E-02 2.82E-02 D. Gross alpha radioactivity

1. Total release Ci O.OOE+OO O.OOE+OO E. Volume of waste release (prior to dilution - Batch Release) liters 2.02E+06 3.24E+06 .l F. Volume of dilution water used during entire period liters 7.69E+09 l.57E+l0 SALEM GENERATING STATION

,.. TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1987 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1st 2nd Units Quarter Quarter Est. Total Error, %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 8.36E-01 l.18E+OO 25%
2. Average diluted concentration during period uCi/ml 7.40E-08 9.22E-08
3. Percent of applicable limit (T.s. 3.11.1.2.(a))  % 5.86E+OO 4.99E+OO B. Tritium
1. Total release Ci l.51E+02 l.99E+02 25%
2. Average diluted concentration during period uCi/ml l.34E.;.05 1. 55E-05
3. Percent of applicable limit  %

(T.S. 3.11.1.1) . 4.45E-Ol 5.17E-01.

c. Dissolved and entrained noble gases
1. Total release Ci 5.05E-01 8.00E-01 .;
2. Average diluted concentration during period uCi/ml 4.47E-08 6.23E-08
3. Percent of applicable limit  %

(T.S. 3.11.1.1) 2.23E-02 3.12E-02 D. Gross alpha radioactivity

<, E *
1. Total release Volume of waste release (prior Ci O.OOE+OO O.OOE+OO I

to dilution - Batch Release) liters 2.85E+06 2.91E+06 1~___;;~..;;;..;~;..._~~~~~~~~~-----~--~.;;...;;...;;...;;....;;_..;;_~~~~~~~~~~~~~~~

,,. F*. Volume of dilution water used during entire period liters l.13E+l0 l.28E+l0 SALEM GENERATING STATION TABLE 2B-l  ;..,...

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT .;...

JANUARY - JUNE 1987 LIQUID EFFLUENTS UNIT 1 "'

CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter .

Quarter Quarter uuarter Strontium-85 Ci Strontium-89 Ci l.09E-05 2.31E-04 7.46E-O*

Strontium-90 Ci l.27E-06 2.70E-05 5.19E-U~

Fluorine.:;.18 Ci 5.58E-02 5.16E-0

  • --sodium.:. 24 Ci 6.92E-0 Chromium-51 Ci Manqanese-54 Ci l.02E-02 3.27E-O Iron-55 Ci l.64E-03 ~.. ~

3.47E-02 4. 86E-.U Iron-59 Ci ,.:..,,..,

Cobalt-57 Ci 2.llE-0 Cobalt-58 Ci 2.49E-Ul 6.91E-O Cobalt-60 Ci 8.88E-02 l.47E-0 Zinc-65 Ci Zirconium-95 Ci 5.85E-04 Niobium-95 Ci 1. 79E-03 Niopium-97 Ci **6. 93E-O Molybdenum-99 Ci l.OUE-0 Technetium-99M Ci l.llE-0 Iodine-131 Ci 5.33E-04 3.03E-02 7.B7E-O Iodine-132 Ci 2.91E-0 Iodine-133 Ci 2.64E.-U3 6.95E-U Iodine-134 Ci 3.l'OE-0 Iodine-135 Ci 1. 96E-0 Cesium-134 Ci 4.22E-02 l.38E-0 Cesium-136 Ci ~.73E-U4 1. 55.t:;-0 Cesium""."137 Ci  !*08E-04 4.40E-02 l.24E-C Cesium-138 Ci 6.81E-0 Lanthanum-140 Ci Antimonv-122 Ci Antimonv-124 Ci 2.70E-04 8.03E-C Antimon:i:-125 Ci 2.38E-U3 l.08E-U

I-Tin-113 Ci Silver-llOm Ci . 2.3§E-C Total for period (above) Ci 2.29E-03 5.64E-01 1. 3'6E+c Tritium Ci l.10E+02 l.45E+C Xenon-133 Ci 3.43E-01 8.53E-C Xenon-133m Ci l.OBE-03 Xenon-135 Ci 9.60E-03 3. 42E-(

Argon-41 Ci Kr-87 Ci f

SALEM GENERATING STATION TABLE 28-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1987 LIUUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit uuarter Quarter Quarter Quarter Strontium-89 Ci 4.27E-04 9.61E-04 Strontium-90 Ci 6.26E-05 6.41E-05 Fluorine-18 Ci l.50E-Ol 4.58E-02 Sodium-22 Ci Sodium-24 Ci 7.27E-05 Chromium-51 Ci 2.]0E-03 Man9anese-54 Ci l.47E-02 3.lGE-02

. Iron-55 Ci 5.12E-02 6.99E-02 Iron-59 Ci Cobalt.-58 Ci 3.14E...:O1 5.33E-Ol Cobalt-60 Ci l.25E-Ol* 9.08E-02 Zinc-65 Ci Zinc-69m Ci Zirconium-95 Ci 6.87E-04 ..

Niobium-95 Ci 3.99E-03 Niobium-97 Ci ..

Molj:'.:bdenum-99 Ci l.83E-04 Techneti'um-99M Ci 2.73E-04 ........:-~

Iodine-131 Ci 4.92E-02 9.83E-02 Iodine-132. Ci **.

Iodine-133 Ci 5.20E-03 4.14t-03 *~7:'

Iodine-1J4 Ci '"£'

Iodine-135 Ci Cesium-134 Ci 5.GBE-02* l.41E-01 Cesium-136 Ci 8.05E-04 2.GBE-04 Cesium-137 Ci 6.00E-U2 l.23E-Ol Antimony-124 Ci 2.40E-02 Antimony-125 Ci 1. BBE-03 2.02E-02 Total For Period (above) Ci 8.36E-Ol l. lBE+OO Tritium Ci 1. 51E+02 l.99E+U2

-Xenon-133m Ci l.84E-03 Xenon-133 Ci 4.95E-01 7~92E-01 Xenon-135 Ci 7.53E-03 8.33E-Oa Kry)2t.__on-85 Ci Ar9on-41 Ci