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* Public Service Electric and Gas Company
* Public Service Electric and Gas
* Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President  
* Company Stanley LaBruna                     Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations AUG 2 7 1992 NLR-N92123 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
-Nuclear Operations AUG 2 7 1992 NLR-N92123 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
RADIOACTIVE EFFLUENT RELEASE REPORT - 32 SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 In accordance with Section 6.9.1.11 of Appendix A to the Operating License for Salem Generating Station (SGS), Public Service Electric and Gas Company (PSE&G) hereby transmits one copy of the semi-annual Radioactive Effluent Release Report, RERR-32. This report summarizes liquid and gaseous releases and solid waste shipments from the Salem Generating Station for the period January 1 through June 30, 1992.
RADIOACTIVE EFFLUENT RELEASE REPORT -32 SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 In accordance with Section 6.9.1.11 of Appendix A to the Operating License for Salem Generating Station (SGS), Public Service Electric and Gas Company (PSE&G) hereby transmits one copy of the semi-annual Radioactive Effluent Release Report, RERR-32. This report summarizes liquid and gaseous releases and solid waste shipments from the Salem Generating Station for the period January 1 through June 30, 1992. Should you have any questions regarding this transmittal, please feel free to contact us. Sincerely, Attachment (1) 9209020034 920630 PDR ADOCK 05000272 R PDR IE'f8' I/ I Document Control Desk NLR-N92123 RERR REPORT only
Should you have any questions regarding this transmittal, please feel free to contact us.
* 2 c Mr. T. T. Martin, Administrator  
Sincerely, Attachment (1) 9209020034 920630 PDR ADOCK 05000272 R                           PDR IE'f8' I/ I
-Region I u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 AUG 2 7 1992 Mr. J. c. Stone, Licensing Project Manager -Salem u. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (S09) USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SGS RERR-32 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 AUGUST,1992
 
*
Document Control Desk           2
* SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -JUNE 1992 Table of Contents INTRODUCTION  
* AUG 2 7 1992 NLR-N92123 RERR REPORT only c   Mr. T. T. Martin, Administrator - Region I
* * * * * * *
: u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager - Salem
* 0 * * * * * * * *
: u. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (S09)
* 1 PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 3 1.0 REGULATORY LIMITS . . . . . .  
USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
* . * . . . * . . 3 2.0 3.0 4.0 5.0 6.0 7.0 8.0 PART B. PART c. PART D. PART E. PART F. PART G. PART H. PART I . 1.1 Fission and Activation Gas Release Limits 3 1.2 Iodine Particulates, and Tritium . . . *
 
* 3 1.3 Liquid Effluents Release Limits . . . . . . . 4 1.4 Total Dose Limit . . . . .  
SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SGS RERR-32 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 AUGUST,1992
* * * . * . . . . . 4 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) . . . 4 AVERAGE ENERGY . . . . . . . .  
 
* . . . 5 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY . . . . * . . . * * . . . .
SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1992 Table of Contents INTRODUCTION   * * * * *   * *
* 5 BATCH RELEASES . . . . * . . * . . * . 7 UNPLANNED RELEASES . . . . .  
* 0 * * * * * * * *
* . . . . . . 7 ELEVATED RADIATION MONITOR RESPONSES . . . * . 7 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS . . . . . . .
* 1 PART A. PRELIMINARY SUPPLEMENTAL INFORMATION                                 3 1.0 REGULATORY LIMITS . . . . . . * . * . . . * . .                     3 1.1 Fission and Activation Gas Release Limits                       3 1.2 Iodine Particulates, and Tritium . . . *
* 7 GASEOUS EFFLUENTS LIQUID EFFLUENTS SOLID WASTE . . . RADIOLOGICAL IMPACT ON MAN . . * * * . *
* 3 1.3 Liquid Effluents Release Limits . . . . .               . . 4 1.4 Total Dose Limit . . . . . * * * . * . . .               . . 4 2.0  MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)               .   . . 4 3.0  AVERAGE ENERGY . . . . . . . . * . . .                               5 4.0  MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY . . . . * . . . * * . . . .
* Liquid Pathways . . . . .
* 5 5.0  BATCH RELEASES . . . . * . . * . . * .                               7 6.0  UNPLANNED RELEASES . . . . . * .           . . . . .               7 7.0  ELEVATED RADIATION MONITOR RESPONSES           . . .       * . 7 8.0  MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS .                   . . .         . .     .
Air Pathways . * * . * . . Direct Radiation
* 7
* * . * . . . . . .
* PART B. GASEOUS EFFLUENTS                                                   7 PART c. LIQUID EFFLUENTS                                                     8 PART D. SOLID WASTE . . .                                                    8 PART E. RADIOLOGICAL IMPACT ON MAN . . * * * . *
* Total Dose . . . . . . . . .
* 8 Liquid Pathways . . . . .                                           8 Air Pathways . * * . * . .
* . . Dose to Members of the Public on Site 7 8 8 8 8
* 0
* 0
* Q 9 * *
* Q   9 Direct Radiation * * . * . . . . . . *            *  *
* e 9 * * * *
* e   9 Total Dose . . . .          . . . . . * . .      * * * *
* 10 0 * * *
* 10 Dose to Members of the Public on Site            0   *   *   *
* 10 Assessment . . . . . . . * * * . 11 METEOROLOGICAL DATA. .
* 10 Assessment . . . . .                           . . * * * . 11 PART F. METEOROLOGICAL DATA.                                         .
* 12 ODCM CHANGES . . . 12 INOPERABLE MONITORS * . . . . * . 12 ENVIRONMENTAL MONITORING LOCATION CHANGES . * . . . 12
* 12 PART G. ODCM CHANGES .                                               . . 12 PART H. INOPERABLE MONITORS * . . . . * .                                   12 PART I . ENVIRONMENTAL MONITORING LOCATION CHANGES       . * . . . 12
:INTRODUCTION SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -JUNE 1992 This report, SGS-RERR-32, summarizes information pertaining to the releases of radioactive materials in liquid, gaseous and solid form from the Salem Generating Station {SGS) Units 1 and 2 for the period January 1, 1992 to June 30 ,* 1992. This Semiannual RERR is submitted for both Salem Units and combines those sections which are common to each unit. Separate tables of releases and release totals are included whenever separate processing systems exist. Salem Unit 1 is a Westinghouse Pressurized Water Reactor which has a licensed core power of 3411 MWt and an approximate net electrical output of 1115 MWe. Salem Unit 1 achieved initial criticality on December 11, 1976. and went into commercial operations on June 30, 1977. Salem Unit 2 is a Westinghouse Pressurized Water Reactor which has a licensed core power of 3411 MWt and an approximate net electrical output of 1115 MWe. Salem Unit 2 achieved initial on August 2, 1980 and went into commercial operations on October 13, 1981. 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.
* SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1992
Preceding the tables summarizing the gaseous and liquid discharges and solid waste shipments are our responses to parts A-F of the "Supplemental Information" section of Regulatory Guide 1.21, Appendix B. As required by Regulatory Guide 1.21, our Technical Specification limits are described in detail within this report along with a summary description of how measurements and determinations of the total activity discharged were developed.
:INTRODUCTION This report, SGS-RERR-32, summarizes information pertaining to the releases of radioactive materials in liquid, gaseous and solid form from the Salem Generating Station {SGS) Units 1 and 2 for the period January 1, 1992 to June 30 ,* 1992.
This Semiannual RERR is submitted for both Salem Units and combines those sections which are common to each unit. Separate tables of releases and release totals are included whenever separate processing systems exist.
Salem Unit 1 is a Westinghouse Pressurized Water Reactor which has a licensed core power of 3411 MWt and an approximate net electrical output of 1115 MWe. Salem Unit 1 achieved initial criticality on December 11, 1976. and went into commercial operations on June 30, 1977.
Salem Unit 2 is a Westinghouse Pressurized Water Reactor which has a licensed core power of 3411 MWt and an approximate net electrical output of 1115 MWe. Salem Unit 2 achieved initial cri~icality on August 2, 1980 and went into commercial operations on October 13, 1981.
The report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Specification 6.9.1.11 of the Salem Technical Specifications. Preceding the tables summarizing the gaseous and liquid discharges and solid waste shipments are our responses to parts A-F of the "Supplemental Information" section of Regulatory Guide 1.21, Appendix B.
As required by Regulatory Guide 1.21, our Technical Specification limits are described in detail within this report along with a summary description of how measurements and determinations of the total activity discharged were developed.
1
1
* To facilitate determination.
 
of compliance with 40CFR190 requirements, the following information on electrical output is provided.
To facilitate determination. of compliance with 40CFR190 requirements, the following information on electrical output is provided.
Unit 1 generated 2 1 305 1 872 megawatt-hours of electrical energy (net) during the reporting period. Unit 2 generated 409,726 megawatt-hours of electrical energy (net) during the reporting period. Results of liquid and gaseous composites analyzed for sr-89, Sr-90 and Fe-55 for the second quarter of 1992 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 half of 1991 (refer to RERR-31) have been completed; amended pages to RERR-31 are included in this report . 2   
Unit 1 generated 2 1 305 1 872 megawatt-hours of electrical energy (net) during the reporting period.
Unit 2 generated 409,726       megawatt-hours of electrical energy (net) during the reporting period.
Results of liquid and gaseous composites analyzed for sr-89, Sr-90 and Fe-55 for the second quarter of 1992 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 half of 1991 (refer to RERR-31) have been completed; amended pages to RERR-31 are included in this report .
* 2
 
PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LXMXTS 1.1  Fission and Activation Gas 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 limit.ad 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 *
* 3
 
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 10 CFR, 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 milliliter.
In addition, the dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited:
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 apy calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
1.4  Total Dose Limit 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 MPCs 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. The MPC value used for dissolved or entrained noble gases is 2E-4 microcuries per milliliter .
* 4
 
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 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 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 require these tanks to be uniformly mixed for sampling and analysis before being released. Batch releases are defined as releases from the waste monitor hold-up tank and the chemical and volume control tanks. Continuous liquid releases are defined as condensate releases from intermittent blowdown of the steam generators. Specific activities 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 Effluents 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 multi-channel 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. Radionuclides measured at concentrations below the Technical Specification detection limits
*
*
* PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LXMXTS 1.1 Fission and Activation Gas 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:.
(LLDs) are treated as being present. Radionuclides for 5
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
which no activity was detected, while meeting the required LLDs, are treated as absent.
* 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 limit.ad to the following:
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 through the plant vent.
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:
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.
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
* 3
* 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 10 CFR, 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 milliliter.
In addition, the dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited: 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 apy calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ. 1.4 Total Dose Limit 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 MPCs used in determining allowable release rates for radioactive releases.
: a. b. c. MPC values were not used to determine the maximum release rates for fission gases, iodines, or particulates.
MPC values as stated in 10CFR20, Appendix B, Table II, Column 2 were used for liquids. The MPC value used for dissolved or entrained noble gases is 2E-4 microcuries per milliliter . 4
* 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 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 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 require these tanks to be uniformly mixed for sampling and analysis before being released.
Batch releases are defined as releases from the waste monitor hold-up tank and the chemical and volume control tanks. Continuous liquid releases are defined as condensate releases from intermittent blowdown of the steam generators.
Specific activities 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 Effluents 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 multi-channel 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.
Radionuclides measured at concentrations below the Technical Specification detection limits (LLDs) are treated as being present. Radionuclides for 5 which no activity was detected, while meeting the required LLDs, are treated as absent. 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 through 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 gaseous 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.
Batch Mode gaseous 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 radiation monitoring system readings while the channel is in an alarm state are treated as batch mode releases.
Elevated plant vent radiation monitoring system readings while the channel is in an alarm state are treated as batch mode releases. If specific activity data from grab samples taken is not available, then the abnormal release is quantified by the use of the plant vent radiation monitors. The monitor's response is converted to a "specific activity" using historical efficiency factors. The i*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.
If specific activity data from grab samples taken is not available, then the abnormal release is quantified by the use of the plant vent radiation monitors.
4.3 Estimated Total Error The estimated total error of reported liquid and solid releases is within 25%
The monitor's response is converted to a "specific activity" using historical efficiency factors. The i*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.
The estimated total error of the reported continuous gaseous releases is within 50% when concentrations exceed detectable levels. This error is due primarily to variability of waste stream flow rates and changes in isotopic distributions of waste streams between sampling periods. The estimated total error of the reported batch gaseous releases is within 10%.
4.3 Estimated Total Error The estimated total error of reported liquid and solid releases is within 25% The estimated total error of the reported continuous gaseous releases is within 50% when concentrations exceed detectable levels. This error is due primarily to variability of waste stream flow rates and changes in isotopic distributions of waste streams between sampling periods. The estimated total error 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. 6
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.
* S.O BATCH RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A-1 and 4B-1 for Unit 1 and 4A-2 and 4B-2 for Unit 2. 6.0 UNPLANNED RELEASES 7.0 8.0 PART PART During this reporting period there was no unplanned releases.
6
ELEVATED R-16/R41C CHANNEL RESPONSES During this reporting period, their were no elevated monitors readings on R16/R41C.
 
MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS our last report (RERR-31) did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the fourth quarter of 1991. Amended pages to RERR-31 are included at the end of this report. B. GASEOUS EFFLUENTS See Summary Tables lA-1 thru lC for Salem Unit 1 Operations.
S.O BATCH RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A-1 and 4B-1 for Unit 1 and 4A-2 and 4B-2 for Unit 2.
6.0 UNPLANNED RELEASES During this reporting period there was no unplanned releases.
7.0  ELEVATED R-16/R41C CHANNEL RESPONSES During this reporting period, their were no elevated
* 8.0 monitors readings on R16/R41C.
MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS our last report (RERR-31) did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the fourth quarter of 1991. Amended pages to RERR-31 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.
: c. LIQUID EFFLUENTS See Summary Tables 2A-1 thru 2C for Salem Unit 1 Operations.
PART c. LIQUID EFFLUENTS See Summary Tables 2A-1 thru 2C for Salem Unit 1 Operations.
See Summary Tables 2A-2 thru 2C for Salem Unit 2 Operations.
See Summary Tables 2A-2 thru 2C for Salem Unit 2 Operations.
7 l' PART D. SOLID WASTE See Summary in Table 3. PART E. RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on actual locations of nearby residents and farms. The population dose impact is based on historical site specific data i.e., food production, milk production, feed for milk animals and seafood production.
7
The doses were calculated using methods described in Regulatory Guide 1.109 and represent calculations for the six month reporting interval.
 
Individual doses from batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as described in the Offsite Dose Calculation Manual. Population doses were calculated using the meteorological dispersion coefficients for the six month reporting interval.
l' PART D. SOLID WASTE See Summary in Table 3.
Liquid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathway. Calculated doses to individuals are as shown below: Total body dose to an individual:
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 milk animals and seafood production.
4.06E-Ol mrem Highest organ dose: 2.82E+OO mrem to the GI-LLI. Dose to the 6 million individuals living within the 50 mile radius of the plant site: Total population dose: 8.SOE-02 person-rem Average population dose: l.47E-05 mrem/person 8
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.
L Air Pathways The calculated doses to individuals via the air pathway are shown below: Total body dose: 1.62E-02 mrem Skin dose: l.SOE-02 mrem Highest organ dose due to radioiodines and particulates with half lives greater than 8 days: 9.llE-03 mrem to the Thyroid. Dose to the 6 million individuals living within the 50 mile radius of the plant site: Total population dose: 2.44E-Ol person-rem Average population dose: 4.09E-05 mrem/person Direct Radiation Direct radiation may be estimated by thermoluminescent dosimetric (TLD) measurements.
Population doses were calculated using the meteorological dispersion coefficients for the six month reporting interval.
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, as well as natural background radiation.
Liquid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathway. Calculated doses to individuals are as shown below:
TLD data for the six month reporting period is given below: TLD 2S-2 5S-1 Location 0.3 mile 0.9 mile Measurement 5.7 mrad/month 4.9 mrad/month These values are intepreted to represent natural background, since they are within the statistical variation associated with the pre-operational program results, which are: 3.7 mrad/month for location 2s-2, and 4.2 mrad/month for location 5S-1. 9
Total body dose to an individual:     4.06E-Ol mrem Highest organ dose:   2.82E+OO mrem to the GI-LLI.
*
Dose to the 6 million individuals living within the 50 mile radius of the plant site:
* Total Dose 40CFR190 limits the total dose to members of the public due to radioactivity and radiation from uranium fuel cycle sources to: <25 mrem total body or any organ <75 mrem to the thyroid for a calendar year. For Artificial Island, the major sources of dose are from liquid and gaseous effluents from the Salem and.Hope Creek plants. The following doses to members of the public have been calculated for the six month reporting period: 0.778 2.930 0.179 mrem total body mrem organ (GI-LLI) mrem thyroid Dose to Members of the Public Due to Activities inside the Site Boundary.
Total population dose:     8.SOE-02 person-rem Average population dose:   l.47E-05 mrem/person 8
In accordance with the requirements of Technical Specification 6.9.1.7, the dose to members of the public inside the site boundary has been calculated based on the following assumptions:
 
Air Pathways The calculated doses to individuals via the air pathway are shown below:
Total body dose: 1.62E-02 mrem Skin dose:       l.SOE-02 mrem Highest organ dose due to radioiodines and particulates with half lives greater than 8 days:
9.llE-03 mrem to the Thyroid.
Dose to the 6 million individuals living within the 50 mile radius of the plant site:
Total population dose:     2.44E-Ol   person-rem Average population dose:   4.09E-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, as well as natural background radiation.
TLD data for the six month reporting period is given below:
TLD         Location            Measurement 2S-2       0.3 mile       5.7 mrad/month 5S-1        0.9 mile        4.9 mrad/month These values are intepreted to represent natural background, since they are within the statistical variation associated with the pre-operational program results, which are: 3.7 mrad/month for location 2s-2, and 4.2 mrad/month for location 5S-1.
9 L
* Total Dose 40CFR190 limits the total dose to members of the public due to radioactivity and radiation from uranium fuel cycle sources to:
              <25 mrem total body or any organ
              <75 mrem to the thyroid for a calendar year. For Artificial Island, the major sources of dose are from liquid and gaseous effluents from the Salem and.Hope Creek plants.
The following doses to members of the public have been calculated for the six month reporting period:
0.778 mrem  total body 2.930 mrem   organ (GI-LLI) 0.179  mrem   thyroid Dose to Members of the Public Due to Activities inside the Site Boundary.
In accordance with the   requirements of Technical Specification 6.9.1.7,   the dose to members of the public inside the site   boundary has been calculated based on the following   assumptions:
* Such persons are participating or spectators in local softball league
* Such persons are participating or spectators in local softball league
* 10 hours per week on site
* 10 hours per week on site
* Dose due to airborne pathway(inhalation and immersion)
* Dose due to airborne pathway(inhalation and immersion)
* persons are located about 3/4 mile east of plant discharge points {baseball fields)
* persons are located about 3/4 mile east of plant discharge points {baseball fields)
* occupancy coincides with batch gaseous discharges For the six month reporting period, the calculated doses are: 6.61E-05 6.96E-05 6.61E-05 mrem Total Body mrem Organ mrem Thyroid 10 Assessment Gaseous effluents continue to be low and are predominately xenon-133.
* occupancy coincides with batch gaseous discharges For the six month reporting period, the calculated doses are:
Calculated doses are low, due to the dose factor of xenon-133.
6.61E-05   mrem Total Body 6.96E-05   mrem Organ 6.61E-05   mrem Thyroid
Liquid effluents increased slightly from previous reporting periods. Calculated doses are due principally to isotopes of iron, cobalt and cesium. , The following two trend graphs show gaseous and liquid effluents and calculated doses from combined Salem 1 and 2 for the previous five years. 10 c u m
* 10
* r *
 
* m 0.1 0 0,01 1.00E+04 1.00&#xa3;+03 c 1.00E+02 u r 1.00&#xa3;+01 .m I r 1.00E+OO *
Assessment Gaseous effluents continue to be low and are predominately xenon-133. Calculated doses are low, due to the dose factor of xenon-133.
* 1.ooe-01 *m 1.ooe-02 0 1.00&#xa3;-03 r 1.00&#xa3;-04 1.00E-05 .... 00 Salem Unit.a 1 and 2 Liquid Effluenta Curles Released and Calculated Doses ;;; Reportinf Perioll Salem Unit 1 and 2 Gaseous Efftuenta Noble Gas Curles Released and Calculated Dose --............_
Liquid effluents increased slightly from previous reporting periods. Calculated doses are due principally to isotopes of iron, cobalt                         ,
_. x--! x-x-x--:a:....
and cesium.
_.,,. _.,,_ -"' a:: "" .... 113 c;; &deg;' 00 Reporting Period 11 --TB ---o--ORGAN ----CURIES -X-SKIN ----CURIES PART F. PART G. PART H. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for the first and second quarters of 1992 in Tables 5 and 6. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES During this period, there were was a revision to the SGS ODCM. Revision 7 was approved on 1/16/92, a summary of the revision along with the pages that were changed is included in an addendum to this report. INOPERABLE MONITORS During this period, the following effluent monitors were inoperable for more than 30 days
The following two trend graphs show gaseous and liquid effluents and calculated doses from combined Salem 1 and 2 for the previous five years.
Salem Unit.a 1 and 2 Liquid Effluenta Curles Released and Calculated Doses 10 c
u
                                                                                    --TB m
  ** r                                                                             ---o-- ORGAN
* m                                                                             ----CURIES 0.1 0
0,01
                  ....
00        ~        ~          ~                  ;;;
                  ~        ~        ~          ~                  ~
Reportinf Perioll Salem Unit 1 and 2 Gaseous Efftuenta Noble Gas Curles Released and Calculated Dose 1.00E+04             ~
1.00&#xa3;+03                             --............_                  _.
c 1.00E+02
                                        ~
u
                                                                                    ~TB
  .m 1.00&#xa3;+01 r
I r 1.00E+OO                                                                   -X-SKIN
  **
  *m 1.ooe-01 x--!    x-x-x--:a:....              _.,,. _.,,_
                                                                                -"' ----CURIES 1.ooe-02                                                             ~
0     1.00&#xa3;-03 r
1.00&#xa3;-04 1.00E-05
                        ....
00    ~        113          a::~              c;;     ""
                                                                                &deg;'
                        ~      ~        ~                              ~      ~
Reporting Period 11
 
PART F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for the first and second quarters of 1992 in Tables 5 and 6.
PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES During this period, there were was a revision to the SGS ODCM. Revision 7 was approved on 1/16/92, a summary of the revision along with the pages that were changed is included in an addendum to this report.
PART H. INOPERABLE MONITORS During this period, the following effluent monitors were inoperable for more than 30 days
* Unit 2 Plant Vent Noble Gas Monitor (2R41C)
* Unit 2 Plant Vent Noble Gas Monitor (2R41C)
* Unit 2 Chemical Waste Basin Process Monitor (2R37)
* Unit 2 Chemical Waste Basin Process Monitor (2R37)
* Unit 2 Steam Generator Blowdown Process Monitors ( 2 Rl 9 A, B , C , D) These monitors could not be returned to operating status within the 30 day time period due to a forced shutdown on Unit 2 and Design Change work being performed on the monitors.
* Unit 2 Steam Generator Blowdown Process Monitors
* Unit 2 Plant Vent Noble Gas Monitor (2R41C) -Monitor was inoperable for more than 30 days due to design change work being performed on the monitor (DCP 2EC-3086). Work included a primary calibration of the detector and the replacement of electronic components.
( 2 Rl 9 A, B , C , D)
Unit 2 Chemical Waste Basin Process Monitor (2R37) -Monitor could not be returned within the 30 day time period due to replacement  
These monitors could not be returned to operating status within the 30 day time period due to a forced shutdown on Unit 2 and Design Change work being performed on the monitors.
'of the detector following extensive troubleshooting and decontamination of the detector housing. The work on this monitor was further delayed due to a malfunctioning check valve in the sample line to the detector.
* Unit 2 Plant Vent Noble Gas Monitor (2R41C) - Monitor was inoperable for more than 30 days due to design change work being performed on the monitor (DCP 2EC-3086). Work included a primary calibration of the detector and the replacement of electronic components.
Unit 2 Steam Generator Blowdown Process Monitors (2R19 A,B,C,D).  
Unit 2 Chemical Waste Basin Process Monitor (2R37) -
-Monitors could not be returned within 30 days due to design work on the detector (2EC-3086) and a forced outage which limited flow to the detectors.
Monitor could not be returned within the 30 day time period due to replacement 'of the detector following extensive troubleshooting and decontamination of the detector housing. The work on this monitor was further delayed due to a malfunctioning check valve in the sample line to the detector.
Unit 2 Steam Generator Blowdown Process Monitors (2R19 A,B,C,D). - Monitors could not be returned within 30 days due to design work on the detector (2EC-3086) and a forced outage which limited flow to the detectors.
12
12
* PART I. PART J. *
* PART I. PROCESS CON'l'ROL PROGRAM (PCP) CHANGES During this reporting period, there were no changes to the Process Control Program.
* PROCESS CON'l'ROL PROGRAM (PCP) CHANGES During this reporting period, there were no changes to the Process Control Program. ENVIRONMEN'l'AL MONITORING LOCATION CHANGES During the reporting period, there was one change to the environmental monitoring sampling locations.
PART J. ENVIRONMEN'l'AL MONITORING LOCATION CHANGES During the reporting period, there was one change to the environmental monitoring sampling locations. Farm 14F4 was added to the Environmental Monitoring Program
Farm 14F4 was added to the Environmental Monitoring Program due to a neighboring Farm (14Fl) ceasing dairy operations
* due to a neighboring Farm (14Fl) ceasing dairy operations *
* 13
* 13
* SALEM GENERATING STATION TABLE lA-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992 UNIT 1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est. 1st Quarter 2nd Total Units Quarter Error % A. Fission and Activation Gases 1. Total release Ci 1.89E+02 2. Average release rate for period uCi/sec 2.41E+Ol 3. Percent of technical specification limit (T.S. 3.ll.2.2(a))  
 
% 1.40E-Ol B. Iodines 1.57E+02 25 1.99E+Ol 1.17E-Ol 1. Total Iodine-131 Ci 1.72E-05 2.29E-04 25 2. Average release rate for period uCi/sec 2.19E-06 2.92E-05 3. Percent of technical specification limit (2) (T.S. 3.11.2.3(a))  
SALEM GENERATING STATION TABLE lA-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 UNIT 1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est.
% 1.49E-03 1.13E-02 c. Particulates
1st     2nd     Total Units   Quarter  Quarter Error %
: 1. Particulates with half-lives  
A. Fission and Activation Gases
>8 days Ci 6.79E-06 25 2. Average release rate for period uCi/sec 4.33E-07 8.63E-07 3. Percent of technical specification limit (2) (T.S. 3.ll.2.3(a))  
: 1. Total release           Ci     1.89E+02 1.57E+02    25
% 1.49E-03 1.13E-02 4. Gross alpha Ci O.OOE+OO O.OOE+OO c. Tritium 1. Total Release Ci 2.52E+Ol 1.99E+Ol 25 2. Average release rate for period uCi/sec 3.20E+OO 2.54E+OO 3. Percent of technical specification limit (2) (T.S. 3.11.2.3(a))  
: 2. Average release rate for period       uCi/sec   2.41E+Ol 1.99E+Ol
% 1.49E-03 1.13E-02 (1) For batch releases the estimated overall error is within 10% (2) Iodine, tritium and particulates are treated as a group 14
: 3. Percent of technical specification limit (T.S. 3.ll.2.2(a))       %     1.40E-Ol 1.17E-Ol B. Iodines
* SALEM GENERATING STATION TABLE lA-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992 UNIT 2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est. 1st Quarter 2nd Total A. Fission and Activation Gases Units 1. Total release Ci 6.86E-Ol 2. Average release rate for period uCi/sec 8.73E-02 3. Percent of technical specification limit (T.S. 3.11.2.2(a))  
: 1. Total Iodine-131         Ci     1.72E-05 2.29E-04   25
% 5.lSE-04 B. Iodines 1. Total iodine-131 Ci O.OOE+OO 2. Average release rate for period uci/sec O.OOE+OO 3. Percent of technical specification limit (2) (T.S. 3.11.2.3(a))  
: 2. Average release rate for period       uCi/sec   2.19E-06 2.92E-05
% 7.lOE-04 c. Particulates
: 3. Percent of technical specification limit (2)
: 1. Particulates with half-lives  
(T.S. 3.11.2.3(a))       %     1.49E-03 1.13E-02
>8 days Ci 5.76E-06 2. Average release rate for period uCi/sec 7.33E-07 3. Percent of technical specification limit (2) (T.S. 3.11.2.3(a))  
: c. Particulates
% 7.lOE-04 4. Gross alpha Ci O.OOE+OO c. Tritium 1. Total Release Ci 2.57E+Ol 2. Average release rate for period uCi/sec 3.27E+OO 3. Percent of technical specification limit (2) (T.S. 3.11.2.J(a))  
: 1. Particulates with half-lives >8 days       Ci     3.40E~06 6.79E-06   25
% 7.lOE-04 Quarter Error % 1.78E+Ol 2.26E+OO 1.38E-02 1.llE-05 1.41E-06 1.21E-03 1.13E-05 1.43E-06 1.21E-03 O.OOE+OO 2.54E+Ol 3.22E+OO 1.21E-03 25 25 25 25 (1) For batch releases the estimated overall error is within 10% (2) Iodine, tritium and particulates are treated as a group 15
: 2. Average release rate for period       uCi/sec   4.33E-07 8.63E-07
* SALEM GENERATING STATION TABLE lB-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 1 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter ' 1. Fission Gases Krypton-85 Ci O.OOE+OO O.OOE+OO 5.38E-01 1.02E+OO Krypton-85m Ci O.OOE+OO O.OOE+OO 1.57E-02 1.65E-02 Xenon-131m Ci O.OOE+OO O.OOE+OO 1.82E-01 5.48E-01 Xenon-133 Ci 1. 76E+02 9.55E+01 1.10E+01 5.74E+01 Xenon-133m Ci O.OOE+OO O.OOE+OO 1.10E-01 7.13E-01 Xenon-135 Ci 9.14E-01 O.OOE+OO 1.42E-01 1.63E+OO Argon-41 Ci O.OOE+OO O.OOE+OO 2.41E-02 O.OOE+OO Krypton-87 Ci O.OOE+OO O.OOE+OO 3.57E-03 O.OOE+OO Krypton-88 Ci O.OOE+OO O.OOE+OO 1.88E-02 5.78E-03 TOTALS Ci 1.77E+02 9.55E+01 1.20E+01 6.13E+01 2. Iodines Iodine-131 Ci 1. 72E-05 2.29E-04 O.OOE+OO O.OOE+OO TOTALS Ci 1.72E-05 2.29E-04 O.OOE+OO O.OOE+OO 3. Particulates (half-live
: 3. Percent of technical specification limit (2)
>8 days Cobalt-58 Ci O.OOE+OO 4.88E-06 O.OOE+OO O.OOE+OO Cobalt-60 Ci 3.40E-06 1.45E-06 O.OOE+OO O.OOE+OO Cesium-137 Ci O.OOE+OO 4.55E-07 O.OOE+OO O.OOE+OO TOTALS Ci 3.40E-06 6.79E-06 O.OOE+OO O.OOE+OO 16 SALEM GENERATING STATION TABLE 1B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 2 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter
(T.S. 3.ll.2.3(a))       %     1.49E-03 1.13E-02
: 1. Fission Gases Krypton-85 Ci O.OOE+OO O.OOE+OO 2.45E-02 1.94E-Ol Krypton-85m Ci O.OOE+OO O.OOE+OO O.OOE+OO 8.19E-03 Krypton-88 Ci O.OOE+OO O.OOE+OO O.OOE+OO 2.27E-03 Xenon-131m Ci O.OOE+OO O.OOE+OO 8.07E-04 6.76E-02 Xenon-133 Ci O.OOE+OO l.05E+Ol 6.61E-Ol 6.35E+OO Xenon-133m Ci O.OOE+OO O.OOE+OO O.OOE+OO 9.36E-02 Xenon-135 Ci O.OOE+OO 4.0lE-02 O.OOE+OO 5.44E-Ol TOTALS Ci O.OOE+OO 1.0SE+Ol 6.86E-Ol 7.26E+OO 2. Iodines Iodine-131 Ci O.OOE+OO 1. llE-05 O.OOE+OO O.OOE+OO TOTALS Ci O.OOE+OO 1.11E-05 O.OOE+OO O.OOE+OO 3. Particulates (half-live
: 4. Gross alpha               Ci     O.OOE+OO O.OOE+OO
>8 days Cobalt-58 Ci O.OOE+OO 8.54E-06 O.OOE+OO O.OOE+OO Cobalt-60 Ci 5.76E-06 2.73E-06 O.OOE+OO O.OOE+OO TOTALS Ci 5.76E-06 l.13E-05 O.OOE+OO O.OOE+OO
: c. Tritium
* 17 
: 1. Total Release             Ci     2.52E+Ol 1.99E+Ol   25
: 2. Average release rate for period       uCi/sec   3.20E+OO 2.54E+OO
: 3. Percent of technical specification limit (2)
(T.S. 3.11.2.3(a))       %     1.49E-03 1.13E-02 (1) For batch releases the estimated overall error is within 10%
(2) Iodine, tritium and particulates are treated as a group
* 14
 
SALEM GENERATING STATION TABLE lA-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 UNIT 2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est.
1st     2nd     Total Units    Quarter  Quarter  Error %
A. Fission and Activation Gases
: 1. Total release           Ci     6.86E-Ol 1.78E+Ol    25
: 2. Average release rate for period       uCi/sec   8.73E-02 2.26E+OO
: 3. Percent of technical specification limit (T.S. 3.11.2.2(a))       %     5.lSE-04 1.38E-02 B. Iodines
: 1. Total iodine-131         Ci     O.OOE+OO 1.llE-05    25
: 2. Average release rate for period       uci/sec   O.OOE+OO 1.41E-06
: 3. Percent of technical specification limit (2)
(T.S. 3.11.2.3(a))       %     7.lOE-04 1.21E-03
: c. Particulates
: 1. Particulates with half-lives >8 days       Ci     5.76E-06 1.13E-05    25
: 2. Average release rate for period       uCi/sec   7.33E-07 1.43E-06
: 3. Percent of technical specification limit (2)
(T.S. 3.11.2.3(a))       %     7.lOE-04 1.21E-03
: 4. Gross alpha             Ci     O.OOE+OO O.OOE+OO
: c. Tritium
: 1. Total Release           Ci     2.57E+Ol 2.54E+Ol    25
: 2. Average release rate for period       uCi/sec   3.27E+OO 3.22E+OO
: 3. Percent of technical specification limit (2)
(T.S. 3.11.2.J(a))       %     7.lOE-04 1.21E-03 (1) For batch releases the estimated overall error is within 10%
*
*
* SALEM GENERATING STATION TABLE lC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY -JUNE 1992 UNITS 1 AND 2 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit 1st Quarter 2nd Quarter 1st Quarter There were no ground level gaseous releases during this reporting period . 18 2nd Quarter
(2) Iodine, tritium and particulates are treated as a group 15
* SALEM GENERATING STATION TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY -JUNE 1992 UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est. 1st 2nd Total Units Quarter Quarter Error % A. Fission and activation products 1. Total release (not including tritium, gases, alpha) Ci 1. 05E+O.O l.14E+OO 25 2. Average diluted concentration during period uCi/mL 2.02E-07 2.94E-07 3. Percent of technical specification limit (T.S. 3.11.1.2. (a)) % 1. 02E+Ol 1.70E+Ol B. Tritium 1. Total release Ci 7.44E+Ol 4.16E+Ol 25 2. Average diluted concentration during period uCi/mL 1.42E-05 1.07E-05 3. Percent of technical specification limit {T.S.
* SALEM GENERATING STATION TABLE lB-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 1 CONTINUOUS MODE     BATCH MODE 1st       2nd     1st       2nd Nuclides Released   Unit     Quarter   Quarter Quarter   Quarter
% 4.75E-Ol 3.56E-Ol c. Dissolved and entrained noble gases 1. Total release Ci 4.57E-Ol 1.61E-02 25 2. Average diluted concentration during period uCi/mL 8.75E-08 4.15E-09 3. Percent of technical specification limit (T. S. 3.11.1.1)
  ' 1. Fission Gases Krypton-85        Ci     O.OOE+OO   O.OOE+OO 5.38E-01  1.02E+OO Krypton-85m      Ci     O.OOE+OO   O.OOE+OO 1.57E-02  1.65E-02 Xenon-131m        Ci     O.OOE+OO   O.OOE+OO 1.82E-01  5.48E-01 Xenon-133        Ci     1. 76E+02 9.55E+01 1.10E+01  5.74E+01 Xenon-133m        Ci     O.OOE+OO   O.OOE+OO 1.10E-01  7.13E-01 Xenon-135        Ci     9.14E-01  O.OOE+OO 1.42E-01  1.63E+OO Argon-41          Ci     O.OOE+OO   O.OOE+OO 2.41E-02  O.OOE+OO Krypton-87        Ci     O.OOE+OO   O.OOE+OO 3.57E-03   O.OOE+OO Krypton-88        Ci     O.OOE+OO   O.OOE+OO 1.88E-02   5.78E-03 TOTALS            Ci     1.77E+02   9.55E+01 1.20E+01  6.13E+01
% 4.38E-02 2.07E-03 D. Gross alpha activity 1. Total release Ci O.OOE+OO O.OOE+OO E. Volume of waste release (prior to dilution -Batch Release) liters 2.26E+06 1.85E+06 F. Volume of dilution.water used during entire period liters 4.88E+ll 3.98E+10 19 SALEM GENERATING STATION TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est. 1st 2nd Total Units Quarter Quarter Error % A. Fission and activation products 1. Total release (not including tritium, gases, alpha) Ci 8.40E-Ol 1.46E+OO 25 2. Average diluted concentration during period uCi/mL 2.53E-07 2.96E-07 3. Percent of technical specification limit (T.S. 3.11.1.2. (a)) % 1.15E+Ol 1.77E+Ol B. Tritium 1. Total release Ci 5.89E+01 5.81E+01 25 2. Average diluted concentration during period uCi/mL 1.77E-05 1.18E-05 3. Percent of technical specification limit (T.S. 3.11.1.1)
: 2. Iodines Iodine-131        Ci      1. 72E-05  2.29E-04 O.OOE+OO   O.OOE+OO TOTALS            Ci     1.72E-05   2.29E-04 O.OOE+OO   O.OOE+OO
% 5.91E-Ol 3.94E-Ol c. Dissolved and entrained noble gases 1. Total release Ci 4.46E-Ol 4.70E-02 25 2. Average diluted concentration during period uCi/mL 1.34E-07 9.55E-09 3. Percent of technical specification limit (T.S. 3.11.1.1)
: 3. Particulates (half-live >8 days Cobalt-58        Ci     O.OOE+OO   4.88E-06 O.OOE+OO   O.OOE+OO Cobalt-60        Ci      3.40E-06  1.45E-06 O.OOE+OO   O.OOE+OO Cesium-137        Ci     O.OOE+OO   4.55E-07 O.OOE+OO   O.OOE+OO TOTALS            Ci      3.40E-06  6.79E-06 O.OOE+OO   O.OOE+OO 16
% 6.71E-02 4.78E-03 D. Gross alpha activity 1. Total release Ci O.OOE+OO O.OOE+OO E. Volume of waste release (prior to dilution -Batch Release) liters 1.77E+06 1.93E+06
 
* F. Volume of dilution water used during entire period liters 1.13E+10 2.91E+11 20 
SALEM GENERATING STATION TABLE 1B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 2 CONTINUOUS MODE       BATCH MODE 1st       2nd       1st       2nd Nuclides Released   Unit     Quarter   Quarter   Quarter   Quarter
... ---* _..._ ,;mu SALEM GENERATING STATION TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992 LIQUID EFFLUENTS UNIT 1 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter Sodium-24 Ci O.OOE+OO O.OOE+OO 2.58E-05 O.OOE+OO Chromium-51 Ci O.OOE+OO O.OOE+OO 1.20E-03 2.71E-03 Manganese-54 Ci O.OOE+OO O.OOE+OO 1.29E-02 4.15E-02 Iron-55 Ci O.OOE+OO O.OOE+OO 8.57E-03 O.OOE+OO Iron-59 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.20E-04 Cobalt-57 Ci O.OOE+OO O.OOE+OO 3.76E-03 4.19E-03 Cobalt-58 Ci O.OOE+OO 5.75E-05 8.32E-01 8.60E-01 Cobalt-60 Ci O.OOE+OO 2.27E-05 6.17E-02 8.54E-02 Zinc-65 Ci O.OOE+OO O.OOE+OO 8.04E-04 4.83E-05 strontium-89 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE-00 Strontium-90 Ci O.OOE+OO O.OOE+OO 7.44E-05 O.OOE-00 Niobium-95 Ci O.OOE+OO O.OOE+OO 2.83E-03 2.50E-03 Zirconium-95 Ci O.OOE+OO O.OOE+OO 1.36E-03 1.22E-03 Niobium-97 Ci O.OOE+OO O.OOE+OO 9.94E-05 1.17E-07 Technetium-99m Ci O.OOE+OO O.OOE+OO O.OOE+OO 3.18E-08 Silver-11om Ci O.OOE+OO O.OOE+OO 7.16E-05 6.73E-03 Antimony-122 Ci O.OOE+OO O.OOE+OO 4.60E-05 3.94E-05 Antimony-124 Ci O.OOE+OO O.OOE+OO 2.55E-03 6.99E-03 Antimony-125 Ci O.OOE+OO O.OOE+OO 1.25E-02 4.00E-02 Iodine-131 Ci O.OOE+OO O.OOE+OO 4.98E-03 1.33E-02 Iodine-133 Ci O.OOE+OO O.OOE+OO 5.47E-05 4.19E-04 Cesium-134 Ci O.OOE+OO O.OOE+OO 5.0SE-02 3.76E-02 Cesium-136 Ci O.OOE+OO O.OOE+OO 6.62E-04 Cesium-137 Ci O.OOE+OO O.OOE+OO 5.77E-02 3.96E-02 Lanthanum-140 Ci O.OOE+OO O.OOE+OO O.OOE+OO "2.21E-05 Cerium-141 Ci O.OOE+OO O.OOE+OO O.OOE+OO 3.69E-05 Tin-113 Ci O.OOE+OO O.OOE+OO 6.27E-05 3.28E-04 Ruthenium"."'105 Ci O.OOE+OO O.OOE+OO O.OOE+OO 3.22E-04 TOTALS O.OOE+OO 8.02E-05 1. 05E+OO 1.14E+OO
: 1. Fission Gases Krypton-85        Ci     O.OOE+OO O.OOE+OO 2.45E-02   1.94E-Ol Krypton-85m      Ci     O.OOE+OO O.OOE+OO O.OOE+OO   8.19E-03 Krypton-88        Ci     O.OOE+OO O.OOE+OO O.OOE+OO   2.27E-03 Xenon-131m        Ci     O.OOE+OO O.OOE+OO 8.07E-04  6.76E-02 Xenon-133        Ci     O.OOE+OO l.05E+Ol  6.61E-Ol  6.35E+OO Xenon-133m        Ci     O.OOE+OO O.OOE+OO O.OOE+OO   9.36E-02 Xenon-135        Ci      O.OOE+OO 4.0lE-02  O.OOE+OO   5.44E-Ol TOTALS            Ci     O.OOE+OO 1.0SE+Ol  6.86E-Ol  7.26E+OO
* 21 TABLE 2B-1 (CONT) Tritium Ci O.OOE+OO O.OOE+OO 7.44E+Ol 4.16E+Ol Xenon-133m Ci O.OOE+OO O.OOE+OO 3.00E-03 O.OOE+OO Xenon-133 Ci O.OOE+OO O.OOE+OO 4.44E-Ol 1.60E-02 Xenon-135 Ci O.OOE+OO O.OOE+OO 2.llE-03 1.02E-04 Xenon-131m Ci O.OOE+OO O.OOE+OO 7.67E-03 O.OOE+OO TOTALS O.OOE+OO O.OOE+OO 7.48E+Ol 4.16E+Ol 22 SALEM GENERATING STATION TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992 LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter Sodium-24 Ci O.OOE+OO O.OOE+OO 0 .* OOE+OO 4.43E-OS Chromium-S1 Ci O.OOE+OO O.OOE+OO 6.89E-04 2.SSE-03 Manganese-S4 Ci O.OOE+OO O.OOE+OO 1.19E-02 S.9SE-02 Iron-SS Ci O.OOE+OO O.OOE+OO 1.10E-02 O.OOE+OO Iron-S9 Ci O.OOE+OO O.OOE+OO 4.82E-OS 1.13E-04 Cobalt-S7 Ci O.OOE+OO O.OOE+OO 2.87E-03 S.1SE-03 Cobalt-SS Ci O.OOE+OO O.OOE+OO 6.S6E-01 1.lOE+OO Cobalt-60 Ci O.OOE+OO O.OOE+OO 4.20E-02 9.30E-02 Zinc-6S Ci O.OOE+OO O.OOE+OO 1.23E-03 9.3SE-OS Strontium-89 Ci O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE.+00 strontium-90 Ci O.OOE+OO O.OOE+OO 6.91E-OS O.OOE+OO Niobium-9S Ci O.OOE+OO O.OOE+OO 1.17E-03 1. 84E-03 Zirconium-9S Ci O.OOE+OO O.OOE+OO 4.SOE-04 S.23E-04 Niobium-97 Ci O.OOE+OO *o. OOE+OO 6.88E-OS 3.39E-04 Technetium-99m Ci O.OOE+OO O.OOE+OO 3.90E-OS O.OOE+OO Ruthenium-lOS Ci O.OOE+OO O.OOE+OO O.OOE+OO 9.07E-OS Silver-110m
: 2. Iodines Iodine-131        Ci     O.OOE+OO 1. llE-05 O.OOE+OO   O.OOE+OO TOTALS            Ci     O.OOE+OO 1.11E-05  O.OOE+OO   O.OOE+OO
*ci O.OOE+OO O.OOE+OO 3.87E-OS 4.32E-03 Antimony-122 Ci O.OOE+OO O.OOE+OO O.OOE+OO S.29E-OS Antimony-124 Ci O*.OOE+OO O.OOE+OO 3.0SE-03 6.SSE-03 Antimony-12S Ci O.OOE+OO O.OOE+OO 1.21E-02 4.86E-02 Iodine-131
: 3. Particulates (half-live >8 days Cobalt-58        Ci     O.OOE+OO 8.54E-06  O.OOE+OO   O.OOE+OO Cobalt-60        Ci     5.76E-06  2.73E-06  O.OOE+OO   O.OOE+OO TOTALS            Ci      5.76E-06  l.13E-05  O.OOE+OO   O.OOE+OO
*ci O.OOE+OO O.OOE+OO 7.48E-03 1.26E-02 Cesium-134 Ci O.OOE+OO O.OOE+OO 4.04E-02 7.2SE-02 Cesium-136 Ci O.OOE+OO O.OOE+OO 2.00E-04 1.12E-03 Cesium-137 Ci O.OOE+OO O.OOE+OO 4.84E-02 4.46E-02 Lanthanum-140 Ci O.OOE+OO O.OOE+OO 2.03E-OS 2.17E-OS Barium-140 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.14E-04 Tin-113 Ci O.OOE+OO O.OOE+OO O.OOE+OO 8.S1E-OS TOTALS O.OOE+OO O.OOE+OO 8.40E-01 1.46E+OO 23 TABLE 2B-2 (CONT) Tritium Ci O.OOE+OO O.OOE+OO 5.89E+Ol 5.81E+Ol Xenon-131m Ci O.OOE+OO O.OOE+OO 2.85E-03 0.00E+OO Xenon-133m Ci O.OOE+OO O.OOE+OO 8.90E-04 O.OOE+OO Xenon-133 Ci O.OOE+OO O.OOE+OO 4.41E-Ol 4.64E-02 Xenon-135 Ci O.OOE+OO O.OOE+OO 7.48E-04 5.75E-04 TOTALS O.OOE+OO O.OOE+OO 5.93E+Ol 5.82E+Ol
* 17
* 24 
 
SALEM GENERATING STATION TABLE lC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY - JUNE 1992 UNITS 1 AND 2 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE      BATCH MODE 1st        2nd      1st        2nd Nuclides Released  Unit    Quarter    Quarter  Quarter    Quarter There were no ground level gaseous releases during this reporting period .
*
*
* SALEM GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1. Type of waste a. Spent resins, filters, sludges, evaporator bottoms b. Dry compressible waste, contaminated equipment.
* 18
: c. Irradiated components, control rods d. Others (described) oil Units (1) m3 Ci m3 Ci m3 Ci m3 Ci 6-month period 1.70E+Ol 6.88E+02 3.44E+Ol 3.53E+OO O.OOE+OO a*. OOE+OO O.OOE+OO O.OOE+OO Est. Total Error, % 25 25 25 25 2. Estimate of major nuclide composition (for Type A and B waste) Iron-55 Manganese-54 Cobalt-58 Cobalt-GO Nickel-63 Cesium-134  
* SALEM GENERATING STATION TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY - JUNE 1992 UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.
1st        2nd      Total Units    Quarter    Quarter  Error %
A. Fission and activation products
: 1. Total release (not including tritium, gases, alpha)              Ci    1. 05E+O.O l.14E+OO    25
: 2. Average diluted concentration during period                  uCi/mL  2.02E-07  2.94E-07
: 3. Percent of technical specification limit (T.S. 3.11.1.2. (a))        %    1. 02E+Ol  1.70E+Ol B. Tritium
: 1. Total release              Ci    7.44E+Ol  4.16E+Ol    25
: 2. Average diluted concentration during period                  uCi/mL  1.42E-05  1.07E-05
: 3. Percent of technical specification limit
{T.S. 3.11.1~1)            %    4.75E-Ol  3.56E-Ol
: c. Dissolved and entrained noble gases
: 1. Total release              Ci    4.57E-Ol  1.61E-02    25
: 2. Average diluted concentration during period                  uCi/mL  8.75E-08  4.15E-09
: 3. Percent of technical specification limit (T. S. 3.11.1.1)          %    4.38E-02  2.07E-03 D. Gross alpha activity
: 1. Total release              Ci    O.OOE+OO  O.OOE+OO E. Volume of waste release (prior to dilution -
Batch Release)              liters  2.26E+06  1.85E+06 F. Volume of dilution.water used during entire period liters    4.88E+ll  3.98E+10 19
 
SALEM GENERATING STATION TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.
1st      2nd      Total Units    Quarter  Quarter  Error %
A. Fission and activation products
: 1. Total release (not including tritium, gases, alpha)             Ci    8.40E-Ol  1.46E+OO    25
: 2. Average diluted concentration during period                  uCi/mL  2.53E-07  2.96E-07
: 3. Percent of technical specification limit (T.S. 3.11.1.2. (a))      %    1.15E+Ol  1.77E+Ol B. Tritium
: 1. Total release            Ci    5.89E+01  5.81E+01    25
: 2. Average diluted concentration during period                  uCi/mL  1.77E-05  1.18E-05
: 3. Percent of technical specification limit (T.S. 3.11.1.1)          %    5.91E-Ol  3.94E-Ol
: c. Dissolved and entrained noble gases
: 1. Total release            Ci    4.46E-Ol  4.70E-02    25
: 2. Average diluted concentration during period                  uCi/mL  1.34E-07  9.55E-09
: 3. Percent of technical specification limit (T.S. 3.11.1.1)           %    6.71E-02  4.78E-03 D. Gross alpha activity
: 1. Total release            Ci    O.OOE+OO  O.OOE+OO E. Volume of waste release (prior to dilution -
Batch Release)              liters  1.77E+06  1.93E+06
* F. Volume of dilution water used during entire period liters    1.13E+10  2.91E+11 20
 
                                                                          ... ---* _..._ ,;mu SALEM GENERATING STATION TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 LIQUID EFFLUENTS UNIT 1 CONTINUOUS MODE        BATCH MODE 1st      2nd      1st        2nd Nuclides Released    Unit    Quarter  Quarter  Quarter    Quarter Sodium-24              Ci      O.OOE+OO  O.OOE+OO  2.58E-05  O.OOE+OO Chromium-51            Ci      O.OOE+OO  O.OOE+OO  1.20E-03  2.71E-03 Manganese-54          Ci      O.OOE+OO  O.OOE+OO  1.29E-02  4.15E-02 Iron-55                Ci      O.OOE+OO  O.OOE+OO  8.57E-03  O.OOE+OO Iron-59                Ci      O.OOE+OO  O.OOE+OO  O.OOE+OO  1.20E-04 Cobalt-57              Ci      O.OOE+OO  O.OOE+OO  3.76E-03  4.19E-03 Cobalt-58              Ci      O.OOE+OO  5.75E-05  8.32E-01  8.60E-01 Cobalt-60              Ci      O.OOE+OO  2.27E-05  6.17E-02  8.54E-02 Zinc-65                Ci      O.OOE+OO  O.OOE+OO  8.04E-04  4.83E-05 strontium-89          Ci      O.OOE+OO  O.OOE+OO  O.OOE+OO  O.OOE-00 Strontium-90          Ci      O.OOE+OO  O.OOE+OO  7.44E-05  O.OOE-00 Niobium-95            Ci      O.OOE+OO  O.OOE+OO  2.83E-03  2.50E-03 Zirconium-95          Ci     O.OOE+OO  O.OOE+OO  1.36E-03  1.22E-03 Niobium-97            Ci     O.OOE+OO  O.OOE+OO  9.94E-05  1.17E-07 Technetium-99m        Ci     O.OOE+OO  O.OOE+OO  O.OOE+OO  3.18E-08 Silver-11om            Ci     O.OOE+OO  O.OOE+OO  7.16E-05  6.73E-03 Antimony-122          Ci      O.OOE+OO  O.OOE+OO  4.60E-05  3.94E-05 Antimony-124          Ci      O.OOE+OO  O.OOE+OO  2.55E-03  6.99E-03 Antimony-125          Ci      O.OOE+OO  O.OOE+OO  1.25E-02  4.00E-02 Iodine-131            Ci      O.OOE+OO  O.OOE+OO  4.98E-03  1.33E-02 Iodine-133            Ci      O.OOE+OO  O.OOE+OO  5.47E-05  4.19E-04 Cesium-134            Ci      O.OOE+OO  O.OOE+OO  5.0SE-02  3.76E-02 Cesium-136            Ci      O.OOE+OO  O.OOE+OO  3.44E~04  6.62E-04 Cesium-137            Ci      O.OOE+OO  O.OOE+OO  5.77E-02  3.96E-02 Lanthanum-140          Ci      O.OOE+OO  O.OOE+OO  O.OOE+OO  "2.21E-05 Cerium-141            Ci      O.OOE+OO  O.OOE+OO  O.OOE+OO  3.69E-05 Tin-113                Ci      O.OOE+OO  O.OOE+OO  6.27E-05  3.28E-04 Ruthenium"."'105      Ci      O.OOE+OO  O.OOE+OO  O.OOE+OO  3.22E-04 TOTALS                        O.OOE+OO  8.02E-05  1. 05E+OO  1.14E+OO
* 21
 
TABLE 2B-1 (CONT)
Tritium    Ci O.OOE+OO  O.OOE+OO  7.44E+Ol 4.16E+Ol Xenon-133m Ci O.OOE+OO  O.OOE+OO  3.00E-03 O.OOE+OO Xenon-133  Ci O.OOE+OO  O.OOE+OO  4.44E-Ol 1.60E-02 Xenon-135  Ci O.OOE+OO  O.OOE+OO  2.llE-03 1.02E-04 Xenon-131m Ci O.OOE+OO  O.OOE+OO  7.67E-03 O.OOE+OO TOTALS        O.OOE+OO  O.OOE+OO  7.48E+Ol 4.16E+Ol 22
 
SALEM GENERATING STATION TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE            BATCH MODE 1st      2nd        1st          2nd Nuclides Released  Unit    Quarter  Quarter    Quarter      Quarter Sodium-24            Ci    O.OOE+OO   O.OOE+OO 0 .* OOE+OO  4.43E-OS Chromium-S1          Ci    O.OOE+OO  O.OOE+OO  6.89E-04    2.SSE-03 Manganese-S4          Ci    O.OOE+OO  O.OOE+OO 1.19E-02    S.9SE-02 Iron-SS              Ci    O.OOE+OO   O.OOE+OO 1.10E-02    O.OOE+OO Iron-S9              Ci    O.OOE+OO  O.OOE+OO  4.82E-OS    1.13E-04 Cobalt-S7            Ci    O.OOE+OO  O.OOE+OO  2.87E-03    S.1SE-03 Cobalt-SS            Ci    O.OOE+OO  O.OOE+OO  6.S6E-01    1.lOE+OO Cobalt-60            Ci    O.OOE+OO  O.OOE+OO  4.20E-02    9.30E-02 Zinc-6S              Ci    O.OOE+OO  O.OOE+OO  1.23E-03    9.3SE-OS Strontium-89          Ci    O.OOE+OO  O.OOE+OO  O.OOE+OO    0. OOE.+00 strontium-90          Ci    O.OOE+OO  O.OOE+OO  6.91E-OS    O.OOE+OO Niobium-9S            Ci    O.OOE+OO  O.OOE+OO  1.17E-03    1. 84E-03 Zirconium-9S          Ci    O.OOE+OO  O.OOE+OO  4.SOE-04    S.23E-04 Niobium-97            Ci    O.OOE+OO  *o. OOE+OO 6.88E-OS    3.39E-04 Technetium-99m        Ci    O.OOE+OO  O.OOE+OO  3.90E-OS    O.OOE+OO Ruthenium-lOS        Ci    O.OOE+OO  O.OOE+OO  O.OOE+OO    9.07E-OS Silver-110m          *ci    O.OOE+OO  O.OOE+OO  3.87E-OS    4.32E-03 Antimony-122          Ci    O.OOE+OO  O.OOE+OO  O.OOE+OO    S.29E-OS Antimony-124          Ci    O*.OOE+OO O.OOE+OO  3.0SE-03    6.SSE-03 Antimony-12S          Ci    O.OOE+OO  O.OOE+OO  1.21E-02    4.86E-02 Iodine-131          *ci      O.OOE+OO  O.OOE+OO  7.48E-03    1.26E-02 Cesium-134           Ci    O.OOE+OO  O.OOE+OO  4.04E-02    7.2SE-02 Cesium-136            Ci    O.OOE+OO  O.OOE+OO  2.00E-04    1.12E-03 Cesium-137            Ci    O.OOE+OO  O.OOE+OO  4.84E-02    4.46E-02 Lanthanum-140        Ci    O.OOE+OO  O.OOE+OO  2.03E-OS    2.17E-OS Barium-140            Ci    O.OOE+OO  O.OOE+OO  O.OOE+OO    1.14E-04 Tin-113              Ci    O.OOE+OO  O.OOE+OO  O.OOE+OO    8.S1E-OS TOTALS                      O.OOE+OO  O.OOE+OO  8.40E-01    1.46E+OO 23
 
TABLE 2B-2 (CONT)
Tritium    Ci O.OOE+OO  O.OOE+OO 5.89E+Ol 5.81E+Ol Xenon-131m Ci O.OOE+OO  O.OOE+OO 2.85E-03 0.00E+OO Xenon-133m Ci O.OOE+OO  O.OOE+OO 8.90E-04 O.OOE+OO Xenon-133  Ci O.OOE+OO  O.OOE+OO 4.41E-Ol 4.64E-02 Xenon-135  Ci O.OOE+OO  O.OOE+OO 7.48E-04 5.75E-04 TOTALS        O.OOE+OO  O.OOE+OO 5.93E+Ol 5.82E+Ol
* 24


Cesium-137
SALEM GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month    Est. Total
(%) 7.1 1.5 64.2 8.5 8.0 5.4 4.9 Resins (Ci) (%) 4.89E+Ol 52.2 1. 03E+Ol 1.7 4.42E+02 19.8 5.85E+Ol 12.0 5.51E+Ol 7.9 3.72E+Ol 1.4 3.37E+Ol 1.9 (1) Volumes are measured, activities are estimated 25 DAW (Ci) l.84E+OO 6.00E-02 7.00E-01 4.20E-Ol 2.80E-Ol 5.00E-02 7.00E-02
: 1. Type of waste                      Units (1) period      Error, %
: 3. SALEM GENERATING STATION TABLE 3 {CONT'D) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY -JUNE 1992 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Solid Waste Disposition Number of Mode of Type of Shipments Transportation Destination Containers 16 Truck Barnwell, SC Strong, tight containers 5 Truck Barnwell, SC HIC 4. IRRADIATED FUEL SHIPMENTS (Disposition)
: a. Spent resins, filters,          m3      1.70E+Ol sludges, evaporator bottoms      Ci      6.88E+02        25
Number of Shipments None Mode of Transportation N/A 26 Destination N/A SALEM GENERATING STATION TABLE 4A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY -JUNE 1992  
: b. Dry compressible waste,          m3      3.44E+Ol contaminated equipment.          Ci      3.53E+OO        25
: c. Irradiated components,          m3      O.OOE+OO control rods                    Ci      a*. OOE+OO      25
: d. Others (described)              m3      O.OOE+OO
* oil                              Ci      O.OOE+OO        25
: 2. Estimate of major nuclide composition (for Type A and B waste)
Resins                   DAW
(%)        (Ci)         (%)         (Ci)
Iron-55                  7.1      4.89E+Ol       52.2       l.84E+OO Manganese-54              1.5      1. 03E+Ol       1.7       6.00E-02 Cobalt-58                64.2      4.42E+02       19.8       7.00E-01 Cobalt-GO                8.5      5.85E+Ol       12.0       4.20E-Ol Nickel-63                8.0      5.51E+Ol         7.9       2.80E-Ol Cesium-134                5.4      3.72E+Ol         1.4       5.00E-02 Cesium-137                4.9      3.37E+Ol         1.9       7.00E-02 (1) Volumes are measured, activities are estimated
* 25
 
SALEM GENERATING STATION TABLE 3
{CONT'D)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY - JUNE 1992 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
: 3. Solid Waste Disposition Number of       Mode of                           Type of Shipments       Transportation     Destination   Containers 16             Truck             Barnwell, SC   Strong, tight containers 5             Truck             Barnwell, SC     HIC
: 4. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of       Mode of Shipments      Transportation       Destination None              N/A                 N/A 26
 
SALEM GENERATING STATION TABLE 4A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY - JUNE 1992


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY Dates: January 1 -March 30, 1992 2. Type of release: Gas 3. Number of releases during the 1st Quarter: 13 4. Total time duration for all releases of type listed above: 1.09E+03 minutes s. Maximum duration for release of type listed above: 1.96E+02 minutes 6. Average duration for release of type listed above: 8.38E+Ol minutes 7. Minimum duration for release of type listed above:* 5.90E+Ol minutes 8. Average stream flow (dilution flow) during the period of release: N/A 27 SALEM GENERATING STATION TABLE 4A-1 (CONT'D) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992  
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY Dates:     January 1 - March 30, 1992
: 2. Type of release:   Gas
: 3. Number of releases during the 1st Quarter:   13
: 4. Total time duration for all releases of type listed above:
1.09E+03 minutes
: s. Maximum duration for release of type listed above:
1.96E+02 minutes
: 6. Average duration for release of type listed above:
8.38E+Ol minutes
: 7. Minimum duration for release of type listed above:*
5.90E+Ol minutes
: 8. Average stream flow (dilution flow) during the period of release: N/A 27
 
SALEM GENERATING STATION TABLE 4A-1 (CONT'D)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1. Dates: April 1 -June 30, 1992 2. Type of release: Gas 3. Number of releases during the 2nd Quarter: 22 4. Total time duration for all releases of type listed above: 3.23E+04 minutes 5. Maximum duration for release of type listed above: l.05E+04 minutes 6. Average duration for release of type listed above: 1.47E+03 minutes 7. Minimum durati9n for release of type listed above: 4.40E+Ol minutes 8. Average stream flow (dilution flow) during the period of release: N/A 28
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY
*
: 1. Dates:     April 1 - June 30, 1992
* SALEM GENERATING STATION TABLE 4A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY -JUNE 1992  
: 2. Type of release:   Gas
: 3. Number of releases during the 2nd Quarter:   22
: 4. Total time duration for all releases of type listed above:
3.23E+04 minutes
: 5. Maximum duration for release of type listed above:
l.05E+04 minutes
: 6. Average duration for release of type listed above:
1.47E+03 minutes
: 7. Minimum durati9n for release of type listed above:
4.40E+Ol minutes
: 8. Average stream flow (dilution flow) during the period of release:   N/A 28
* SALEM GENERATING STATION TABLE 4A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY - JUNE 1992


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1. 2. 3. 4. 5. 6
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY
* 7. Dates: January 1 -March 30, 1992 Type of release: Gas Number of releases during the 1st Quarter: 13 Total time duration for all releases of type listed above: 1.38E+04 minutes Maximum duration for release of type listed above: 3.71E+03 minutes Average duration for release of type listed above: 1.06E+03 minutes Minimum duration for release of type listed above:. 1.00E+OO minutes 8. Average stream flow (dilution flow) during the period of release: N/A 29 SALEM GENERATING STATION TABLE 4A-2 (CONT'D) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992  
: 1. Dates:     January 1 - March 30, 1992
: 2. Type of release:   Gas
: 3. Number of releases during the 1st Quarter:   13
: 4. Total time duration for all releases of type listed above:
1.38E+04 minutes
: 5. Maximum duration for release of type listed above:
3.71E+03 minutes
* 6*  Average duration for release of type listed above:
1.06E+03 minutes
: 7. Minimum duration for release of type listed above:.
1.00E+OO minutes
: 8. Average stream flow (dilution flow) during the period of release: N/A 29
 
SALEM GENERATING STATION TABLE 4A-2 (CONT'D)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1. Dates: April 1 -June 30, 1992 2. Type of release: Gas 3. Number of releases during the 2nd Quarter: 30 4. Total time duration for all releases of type listed above: 5.44E+03 minutes 5. Maximum duration for release of type listed above: 1.35E+03 minutes 6. Average duration for release of type listed above: 1.81E+02 minutes 7. Minimum duration for release of type listed above: 3.00E+Ol minutes 8. Average stream flow (dilution flow) during the period of release: N/A 30 SALEM GENERATING STATION TABLE 4B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992  
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY
: 1. Dates:     April 1 - June 30, 1992
: 2. Type of release:   Gas
: 3. Number of releases during the 2nd Quarter:   30
: 4. Total time duration for all releases of type listed above:
5.44E+03 minutes
: 5. Maximum duration for release of type listed above:
1.35E+03 minutes
: 6. Average duration for release of type listed above:
1.81E+02 minutes
: 7. Minimum duration for release of type listed above:
3.00E+Ol minutes
: 8. Average stream flow (dilution flow) during the period of release: N/A 30
 
SALEM GENERATING STATION TABLE 4B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1. Dates: January 1 -March 30, 1992 2. Type of release: Liquid 3. Number of releases during the 3rd Quarter: 36 4. Total time duration for all releases of type listed above: 8.57E+03 minutes 5. Maximum duration for release of type listed above: 3.35E+02 minutes 6. Average duration for release of type listed above: 2.38E+02 minutes 7. Minimum duration for release of type listed above: 1.86E+02 minutes 8. Average stream flow (dilution flow) during the period of release: 1.61E+05 gpm 31 SALEM GENERATING STATION TABLE 4B-1 {CONT'D) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992  
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY
: 1. Dates:     January 1 - March 30, 1992
: 2. Type of release:   Liquid
: 3. Number of releases during the 3rd Quarter:   36
: 4. Total time duration for all releases of type listed above:
8.57E+03 minutes
: 5. Maximum duration for release of type listed above:
3.35E+02 minutes
: 6. Average duration for release of type listed above:
2.38E+02 minutes
: 7. Minimum duration for release of type listed above:
1.86E+02 minutes
: 8. Average stream flow (dilution flow) during the period of release: 1.61E+05 gpm 31
 
SALEM GENERATING STATION TABLE 4B-1
{CONT'D)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1. Dates: April 1 -June 30, 1992 2. Type of release: Liquid 3. Number of releases during the 2nd Quarter: 28 4. Total time duration for all releases of type listed above: 7.73E+03 minutes 5. Maximum duration for release of type listed above: 6.48E+02 minutes 6. Average duration for release of type listed above: 2.76E+02 minutes 7. Minimum duration for release of type listed above: 2.12E+02 minutes 8. Average stream flow {dilution flow) during the period of release: 1.33E+05 gpm 32 SALEM GENERATING STATION TABLE 4B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1992  
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY
: 1. Dates:   April 1 - June 30, 1992
: 2. Type of release:   Liquid
: 3. Number of releases during the 2nd Quarter: 28
: 4. Total time duration for all releases of type listed above:
7.73E+03 minutes
: 5. Maximum duration for release of type listed above:
6.48E+02 minutes
: 6. Average duration for release of type listed above:
2.76E+02 minutes
: 7. Minimum duration for release of type listed above:
2.12E+02 minutes
: 8. Average stream flow {dilution flow) during the period of release: 1.33E+05 gpm 32
 
SALEM GENERATING STATION TABLE 4B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1. Dates: January 1 -March 30, 1992 2. Type of release: Liquid 3. Number of releases during the 3rd Quarter: 28 4. Total time duration for all releases of type listed above: 6.42E+03 minutes 5. Maximum duration for release of type listed above: 3.29E+02 minutes 6. Average duration for release of type listed above: 2.29E+02 minutes 7. Minimum duration for release of type listed above: 1.74E+02 minutes 8. Average stream flow (dilution flow) during the period of release: l.37E+05 gpm 33 SALEM GENERATING STATION TABLE 4B-2 (CONT'D) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY -JUNE 1992  
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY
: 1. Dates:     January 1 - March 30, 1992
: 2. Type of release:   Liquid
: 3. Number of releases during the 3rd Quarter:   28
: 4. Total time duration for all releases of type listed above:
6.42E+03 minutes
: 5. Maximum duration for release of type listed above:
3.29E+02 minutes
: 6. Average duration for release of type listed above:
2.29E+02 minutes
: 7. Minimum duration for release of type listed above:
1.74E+02 minutes
: 8. Average stream flow (dilution flow) during the period of release: l.37E+05 gpm 33
 
SALEM GENERATING STATION TABLE 4B-2 (CONT'D)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY - JUNE 1992


==SUMMARY==
==SUMMARY==
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1. Dates: April 1 -June 30, 1992 2. Type of release: Liquid 3. Number
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY
: 1. Dates:    April 1 - June 30, 1992
: 2. Type of release:    Liquid
: 3. Number of releases during the 4th Quarter:  33
: 4. Total time duration for all releases of type listed above:
1.11E+04 minutes
: 5. Maximum duration for release of type listed above:
3.16E+
See summary Tables 2A-2 thru 2C for Salem Unit 2 Operations.
See summary Tables 2A-2 thru 2C for Salem Unit 2 Operations.
D. SOLID WASTE See Summary in Table 3. E. RADIOLOGICAL IMPACT OH MAH 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 milk animals and seafood production.
PART D. SOLID WASTE See Summary in Table 3.
The doses were calculated using methods described in Regulatory Guide 1.109 and represent calculations for the six month reporting interval.
PART E. RADIOLOGICAL IMPACT OH MAH 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 milk animals and seafood production.
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
The doses were calculated using methods described in Regulatory Guide 1.109 and represent calculations for the six month reporting interval. Individual doses from batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as
* described in the Offsite Dose Calculation Manual
* Population doses were calculated using the meteorological dispersion coefficients for the six month reporting interval.
* Population doses were calculated using the meteorological dispersion coefficients for the six month reporting interval.
Liauid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathway. Calculated doses to individuals are as shown below: Total body dose to an individual:
Liauid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathway. Calculated doses to individuals are as shown below:
3.83E-Ol mrem Highest organ dose: 1.79E+OO mrem to the GI-LLI. Dose to the 6 million individuals living within the so mile radius of the plant site: Total population dose: 7.lOE-02 person-rem Average population dose: 1.19E-05 mrem/person 8
Total body dose to an individual:     3.83E-Ol mrem Highest organ dose:   1.79E+OO mrem to the GI-LLI.
SALEM GENERATING STATION TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1991 UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est. 3rd 4th Total Units Quarter Quarter Error % A. Fission and activation products 1. Total release (not including tritium, I gases, alpha) Ci 6.65E-Ol 1.24E+OO 25 2. Average diluted concentration during period uCi/mL 8.79E-08 1.29E-07 3. Percent of technical specification limit (T.S. 3.11.1.2. (a)) % 5.62E+OO 1.68E+Ol B. Tritium 1. Total release Ci 1.46E+02 2.14E+02 25 2. Average diluted concentration during period uci/mL 1. 93E-05 2.23E-05 3. Percent of technical specification limit (T.S. 3_.11.1.1)  
Dose to the 6 million individuals living within the so mile radius of the plant site:
% 6.42E-Ol 7.42E-Ol c. Dissolved and entrained noble gases 1. Total release Ci 4.27E-02 3.16E-Ol 25 2. Average diluted concentration during period uCi/mL 5.64E-09 3.29E-08 3. Percent of technical specification limit . (T. S. 3.11.1.1)  
Total population dose:     7.lOE-02 person-rem Average population dose:   1.19E-05 mrem/person
% 2.82E-03 1.65E-02 D. Gross alpha activity 1. Total release Ci O.OOE+OO O.OOE+OO E. Volume of waste release (prior to dilution -Batch Release) liters 2.86E+06 3.29E+06 F. Volume of dilution water used during entire period liters 7.56E+09 9.60E+09 19 SALEM GENERATING STATION TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1991 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est. 3rd 4th Total Units Quarter Quarter Error % A. Fission and activation products 1. Total release (not including tritium, gases, alpha) Ci 3.62E-Ol 6.91E-Ol 25 2. Average diluted concentration during period uCi/mL 6.51E-08 1.35E-07 3. Percent of technical specification limit (T.S. 3.11.1.2. (a)) % 2.86E+OO 1. 05E+Ol B. Tritium 1. Total release Ci 1. OOE+02 1.39E+02 25 2. Average diluted concentration during period uCi/mL l.SOE-05 2.71E-05 3. Percent of technical specification limit (T.S. 3*.11.1.1)  
* 8
% 6.0lE-01 9.05E-Ol c. Dissolved and entrained noble gases 1. Total release Ci 5.91E-02 2.GOE-01 25 2. Average diluted *'* concentration during period uCi/mL 1.0GE-08 5.07E-08 3. Percent of technical specification limit (T.S. 3.11.1.1)  
 
% 5.JlE-03 2.54E-02 D. Gross alpha activity 1. Total release Ci O.OOE+OO O.OOE+OO E. Volume of waste release (prior to dilution -Batch Release) liters 1.72E+06 2.13E+06
SALEM GENERATING STATION TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.
* F. Volume of dilution water used during entire period liters 5.56E+09 5.13E+09 20 SALEM GENERATING STATION TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1991 LIQUID EFFLUENTS UNIT 1 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Beryllium-7 O.OOE+OO O.OOE+OO 2.47E-03 O.OOE+OO Sodium-24 O.OOE+OO O.OOE+OO 3.03E-04 8.31E-04 Chromium-51 O.OOE+OO O.OOE+OO 3.30E-04 3.61E-03 Manganese-54 O.OOE+OO O.OOE+OO 1.52E-02 1. 95E-02 Iron-55 O.OOE+OO O.OOE+OO 2.73E-02 3.95E-02 Iron-59 O.OOE+OO O.OOE+OO 2.31E-04 6.51E-05 Cobalt-57 O.OOE+OO O,OOE+OO 1.69E-03 3.03E-03 Cobalt-58 O.OOE+OO O.OOE+OO 4.89E-Ol 8.33E-01 Cobalt-60
3rd       4th     Total Units   Quarter   Quarter Error %
: 1. 97E-05 O.OOE+OO 5.87E-02 1.14E-Ol Zinc-65 O.OOE+OO O.OOE+OO 2.45E-04 1. 49E-05 strontium-89 O.OOE+OO O.OOE+OO 3.81E-04 9.87E-04 strontium-90 O.OOE+OO O.OOE+OO 8.63E-05 1. 25E-04 Niobium-95 O.OOE+OO O.OOE+OO 1.77E-03 2.19E-03 Zirconium-95 O.OOE+OO O.OOE+OO 7.44E-04 1.15E-03 Niobium-97 O.OOE+OO O.OOE+OO 3.74E-04 3.18E-04 Technetium-99m O.OOE+OO O.OOE+OO 2.30E-04 O.OOE+OO Silver-llOm O.OOE+OO O.OOE+OO 3.27E-04 1. 44E-04 Antimony-122 O.OOE+OO O.OOE+OO O.OOE+OO 2.49E-04 Antimony-124 O.OOE+OO O.OOE+OO 1.98E-04 1. 34E-02 Antimony-125 O.OOE+OO O.OOE+OO 1.07E-02 3.91E-02 Iodine-131 5.58E-05 O.OOE+OO 6.80E-03 3.36E-02 Iodine-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodirie-133 O.OOE+OO O.OOE+OO 1.79E-03 1. 26E-03 Strontium-92 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E-05 Cesium-134 1.18E-05 O.OOE+OO 1.85E-02 6.00E-02 Cesium-136 O.OOE+OO O.OOE+OO 3.50E-05 2.18E-03 Cesium-137 2.66E-05 O.OOE+OO 2.71E-02 6.73E-02 Lanthanum-140 O.OOE+OO O.OOE+OO 1.38E-04 8.50E-05 Cerium-144 O.OOE+OO O.OOE+OO 2.82E-04 O.OOE+OO Tin-113 O.OOE+OO O.OOE+OO 2.88E-05 3.85E-05 Fluorine-18 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E-04 Ruthenium-105 O.OOE+OO O.OOE+OO 4.83E-05 O.OOE+OO TOTALS 1.14E-04 O.OOE+OO 6.65E-Ol 1. 24E+OO 21 SALEM GENERATING STATION TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1991 LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Sodium-24 O.OOE+OO O.OOE+OO 1. 59E-04 1.36E-03 Chromium-51 O.OOE+OO O.OOE+OO 3.0lE-04 1.49E-03 Manganese-54 O.OOE+OO O.OOE+OO 7.14E-03 1.21E-02 Iron-55 O.OOE+OO O.OOE+OO 1.42E-02 1.38E-02 Iron-59 O.OOE+OO O.OOE+OO 3.17E-05 O.OOE+OO Cobalt-57 O.OOE+OO O.OOE+OO 8.82E-04 1.65E-03 Cobalt-58 O.OOE+OO O.OOE+OO 2.59E-Ol 5.08E-Ol Cobalt-60 O.OOE+OO O.OOE+OO 2.43E-02 3.62E-02 Zinc-65 O.OOE+OO O.OOE+OO 9.30E-05 O.OOE+OO Strontium-89 O.OOE+OO O.OOE+OO O.OOE+OO 7.02E-04 Strontium-90 O.OOE+OO O.OOE+OO 5.32E-05 1.15E-04
A. Fission and activation products
* Niobium-95 O.OOE+OO O.OOE+OO 1.08E-03 8.13E-04 Zirconium-95 O.OOE+OO O.OOE+OO 5.24E-04 2.83E-04 Niobium-97 O.OOE+OO O.OOE+OO 3.42E-05 1.19E-04 Technetium-99m O.OOE+OO O.OOE+OO 5.35E-05 1.0lE-05 Ruthenium-105 O.OOE+OO O.OOE+OO O.OOE+OO 3.21E-05 Silver-llOm O.OOE+OO O.OOE+OO 2.24E-04 3.86E-04 Antimony-122 O.OOE+OO O.OOE+OO 1.26E-05 5.82E-05 Antimony-124 O.OOE+OO O.OOE+OO 5.73E-04 9.26E-03 Antimony-125 O.OOE+OO O.OOE+OO 1.67E-02 2.18E-02 Iodine-131 O.OOE+OO O.OOE+OO 5.64E-03 2.06E-02 Iodine-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodine-133 O.OOE+OO O.OOE+OO 1.06E-03 9.0lE-04 Cesium-138 O.OOE+OO O.OOE+OO O.OOE+OO 6.51E-06 cesium-134 O.OOE+OO O.OOE+OO 1.23E-02 2.95E-02 Cesium-136 O.OOE+OO O.OOE+OO 1. 61E-04 8.68E-04 Cesium-137 O.OOE+OO O.OOE+OO 1.78E-02 3.04E-02 Lanthanum-140 O.OOE+OO O.OOE+OO 1.60E-05 3.42E-06 Barium-140 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Bromine-82 O.OOE+OO O.OOE+OO O.OOE+OO 6.04E-05 Fluorine-18 O.OOE+OO O.OOE+OO O.OOE+OO 9.18E-04 TOTALS O.OOE+OO O.OOE+OO 3.62E-Ol 6.91E-Ol 23 REVISION 7 TO SALEM ODCM
: 1. Total release (not including tritium, gases, alpha)
* REVISION 7 OF THE SALEM OFFSITE DOSE CALCULATION MANUAL Attached is a breakdown of the revisions made to the Salem Generating Stations Offsite Dose Calculation Manual (ODCM). The revisions were made to satisfy part B closure of some DCP's and to update information contained in the ODCM. Chanqe f 1 page 5 bottom Change From: Use of the effective MPC value as derived in Appendix A may be non-conservative for the R-19 Steam Generator Slowdown monitors and R37 Chemical Waste Basin monitors where I-131 transfer during primary to secondary leakage may potentially be more controlling blowdown monitors, lR13** Service Water monitor and R37 Chemical Waste Basin Change to: Based upon the potential for I-131 to be present in the secondary and service water systems, the use of the default effective MPC value as derived in Appendix A may be non-conservative for the 1Rl9 and 2Rl9 SGBD monitors, the R-37 Chemical Waste Basin Monitor and the lR-13 Service Water Monitors.
: 2. Average diluted Ci     6.65E-Ol 1.24E+OO   25 I
Reason: Clarified statement tor better understandinq of non-conservative conditions that will occur if the default effective MPC value is used
concentration during period                 uCi/mL   8.79E-08 1.29E-07
: 3. Percent of technical specification limit (T.S. 3.11.1.2. (a))       %   5.62E+OO 1.68E+Ol B. Tritium
: 1. Total release               Ci     1.46E+02 2.14E+02   25
: 2. Average diluted concentration during period                   uci/mL   1. 93E-05 2.23E-05
: 3. Percent of technical specification limit (T.S. 3_.11.1.1)           %   6.42E-Ol 7.42E-Ol
: c. Dissolved and entrained noble gases
: 1. Total release               Ci     4.27E-02 3.16E-Ol   25
: 2. Average diluted concentration during period                   uCi/mL   5.64E-09 3.29E-08
: 3. Percent of technical specification limit
      . (T. S. 3.11.1.1)           %   2.82E-03 1.65E-02 D. Gross alpha activity
: 1. Total release               Ci     O.OOE+OO O.OOE+OO E. Volume of waste release (prior to dilution -
Batch Release)               liters 2.86E+06 3.29E+06 F. Volume of dilution water used during entire period liters     7.56E+09 9.60E+09 19
 
SALEM GENERATING STATION TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.
3rd       4th       Total Units     Quarter   Quarter   Error %
A. Fission and activation products
: 1. Total release     (not including tritium, gases, alpha)             Ci     3.62E-Ol 6.91E-Ol     25
: 2. Average diluted concentration during period                 uCi/mL   6.51E-08 1.35E-07
: 3. Percent of technical specification limit (T.S. 3.11.1.2. (a))       %     2.86E+OO 1. 05E+Ol B. Tritium
: 1. Total release             Ci     1. OOE+02 1.39E+02     25
: 2. Average diluted concentration during period                   uCi/mL   l.SOE-05 2.71E-05
: 3. Percent of technical specification limit (T.S. 3*.11.1.1)           %     6.0lE-01 9.05E-Ol
: c. Dissolved and entrained noble gases
: 1. Total release             Ci     5.91E-02 2.GOE-01     25
: 2. Average diluted                                               *'*
concentration during period                   uCi/mL   1.0GE-08 5.07E-08
: 3. Percent of technical specification limit (T.S. 3.11.1.1)             %     5.JlE-03 2.54E-02 D. Gross alpha activity
: 1. Total release             Ci     O.OOE+OO O.OOE+OO E. Volume of waste release (prior to dilution -
Batch Release)               liters   1.72E+06 2.13E+06
* F. Volume of dilution water used during entire period liters     5.56E+09 5.13E+09 20
 
SALEM GENERATING STATION TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 LIQUID EFFLUENTS UNIT 1 CONTINUOUS MODE         BATCH MODE 3rd       4th       3rd       4th Nuclides Released   Unit     Quarter   Quarter   Quarter   Quarter Beryllium-7                   O.OOE+OO O.OOE+OO 2.47E-03   O.OOE+OO Sodium-24                     O.OOE+OO O.OOE+OO 3.03E-04   8.31E-04 Chromium-51                   O.OOE+OO O.OOE+OO 3.30E-04   3.61E-03 Manganese-54                 O.OOE+OO O.OOE+OO 1.52E-02   1. 95E-02 Iron-55                       O.OOE+OO O.OOE+OO 2.73E-02   3.95E-02 Iron-59                       O.OOE+OO O.OOE+OO 2.31E-04   6.51E-05 Cobalt-57                     O.OOE+OO O,OOE+OO 1.69E-03   3.03E-03 Cobalt-58                     O.OOE+OO O.OOE+OO 4.89E-Ol   8.33E-01 Cobalt-60                     1. 97E-05 O.OOE+OO 5.87E-02   1.14E-Ol Zinc-65                       O.OOE+OO O.OOE+OO 2.45E-04   1. 49E-05 strontium-89                 O.OOE+OO O.OOE+OO 3.81E-04   9.87E-04 strontium-90                 O.OOE+OO O.OOE+OO 8.63E-05   1. 25E-04 Niobium-95                   O.OOE+OO O.OOE+OO 1.77E-03   2.19E-03 Zirconium-95                 O.OOE+OO O.OOE+OO 7.44E-04   1.15E-03 Niobium-97                   O.OOE+OO O.OOE+OO 3.74E-04   3.18E-04 Technetium-99m               O.OOE+OO O.OOE+OO 2.30E-04   O.OOE+OO Silver-llOm                   O.OOE+OO O.OOE+OO 3.27E-04   1. 44E-04 Antimony-122                 O.OOE+OO O.OOE+OO O.OOE+OO   2.49E-04 Antimony-124                 O.OOE+OO O.OOE+OO 1.98E-04   1. 34E-02 Antimony-125                 O.OOE+OO O.OOE+OO 1.07E-02   3.91E-02 Iodine-131                   5.58E-05 O.OOE+OO 6.80E-03   3.36E-02 Iodine-132                   O.OOE+OO O.OOE+OO O.OOE+OO   O.OOE+OO Iodirie-133                   O.OOE+OO O.OOE+OO 1.79E-03   1. 26E-03 Strontium-92                 O.OOE+OO O.OOE+OO O.OOE+OO   2.17E-05 Cesium-134                   1.18E-05 O.OOE+OO 1.85E-02   6.00E-02 Cesium-136                   O.OOE+OO O.OOE+OO 3.50E-05   2.18E-03 Cesium-137                   2.66E-05 O.OOE+OO 2.71E-02   6.73E-02 Lanthanum-140                 O.OOE+OO O.OOE+OO 1.38E-04   8.50E-05 Cerium-144                   O.OOE+OO O.OOE+OO 2.82E-04   O.OOE+OO Tin-113                       O.OOE+OO O.OOE+OO 2.88E-05   3.85E-05 Fluorine-18                   O.OOE+OO O.OOE+OO O.OOE+OO   2.67E-04 Ruthenium-105                 O.OOE+OO O.OOE+OO 4.83E-05   O.OOE+OO TOTALS                       1.14E-04 O.OOE+OO 6.65E-Ol   1. 24E+OO 21
 
SALEM GENERATING STATION TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE         BATCH MODE 3rd       4th       3rd       4th Nuclides Released   Unit     Quarter   Quarter   Quarter   Quarter Sodium-24                   O.OOE+OO O.OOE+OO 1. 59E-04 1.36E-03 Chromium-51                 O.OOE+OO O.OOE+OO 3.0lE-04   1.49E-03 Manganese-54                 O.OOE+OO O.OOE+OO 7.14E-03   1.21E-02 Iron-55                     O.OOE+OO O.OOE+OO 1.42E-02   1.38E-02 Iron-59                     O.OOE+OO O.OOE+OO 3.17E-05   O.OOE+OO Cobalt-57                   O.OOE+OO O.OOE+OO 8.82E-04   1.65E-03 Cobalt-58                   O.OOE+OO O.OOE+OO 2.59E-Ol   5.08E-Ol Cobalt-60                   O.OOE+OO O.OOE+OO 2.43E-02   3.62E-02 Zinc-65                     O.OOE+OO O.OOE+OO 9.30E-05   O.OOE+OO Strontium-89                 O.OOE+OO O.OOE+OO O.OOE+OO   7.02E-04 Strontium-90                 O.OOE+OO O.OOE+OO 5.32E-05   1.15E-04 Niobium-95                   O.OOE+OO O.OOE+OO 1.08E-03   8.13E-04
* Zirconium-95 Niobium-97 Technetium-99m Ruthenium-105 Silver-llOm Antimony-122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.24E-04 3.42E-05 5.35E-05 O.OOE+OO 2.24E-04 1.26E-05 2.83E-04 1.19E-04 1.0lE-05 3.21E-05 3.86E-04 5.82E-05 Antimony-124                 O.OOE+OO O.OOE+OO 5.73E-04   9.26E-03 Antimony-125                 O.OOE+OO O.OOE+OO 1.67E-02   2.18E-02 Iodine-131                   O.OOE+OO O.OOE+OO 5.64E-03   2.06E-02 Iodine-132                   O.OOE+OO O.OOE+OO O.OOE+OO   O.OOE+OO Iodine-133                   O.OOE+OO O.OOE+OO 1.06E-03   9.0lE-04 Cesium-138                   O.OOE+OO O.OOE+OO O.OOE+OO   6.51E-06 cesium-134                   O.OOE+OO O.OOE+OO 1.23E-02   2.95E-02 Cesium-136                   O.OOE+OO O.OOE+OO 1. 61E-04 8.68E-04 Cesium-137                   O.OOE+OO O.OOE+OO 1.78E-02   3.04E-02 Lanthanum-140               O.OOE+OO O.OOE+OO 1.60E-05   3.42E-06 Barium-140                   O.OOE+OO O.OOE+OO O.OOE+OO   O.OOE+OO Bromine-82                   O.OOE+OO O.OOE+OO O.OOE+OO   6.04E-05 Fluorine-18                 O.OOE+OO O.OOE+OO O.OOE+OO   9.18E-04 TOTALS                       O.OOE+OO O.OOE+OO 3.62E-Ol   6.91E-Ol 23
 
REVISION 7 TO SALEM ODCM REVISION 7 OF THE SALEM OFFSITE DOSE CALCULATION MANUAL Attached is a breakdown of the revisions made to the Salem Generating Stations Offsite Dose Calculation Manual (ODCM). The revisions were made to satisfy part B closure of some DCP's and to update information contained in the ODCM.
Chanqe f 1 page 5 bottom Change From:
Use of the effective MPC value as derived in Appendix A may be non-conservative for the R-19 Steam Generator Slowdown monitors and R37 Chemical Waste Basin monitors where I-131 transfer during primary to secondary leakage may potentially be more controlling blowdown monitors, lR13** Service Water monitor and R37 Chemical Waste Basin monitor~
Change to:
Based upon the potential for I-131 to be present in the secondary and service water systems, the use of the default effective MPC value as derived in Appendix A may be non-conservative for the 1Rl9 and 2Rl9 SGBD monitors, the R-37 Chemical Waste Basin Monitor and the lR-13 Service Water Monitors.
Reason:
Clarified statement tor better understandinq of non-conservative conditions that will occur if the default effective MPC value is used *
* 1
* 1
* Chanqe f 2 Page 6, bottom Change From: MPCe of lE-05 uci/ml used for default _2Rl3 radiation monitor setpoint.
 
Change to: MPCe of 3.38E-06 uci/ml used for default 2Rl3 radiation monitor setpoint.
Chanqe f 2 Page 6, bottom Change From:
Reason: See Appendix A for justification of MPC* Chanqe f 3 page 24 section 2.4.l and page 25 section 2.4.2 Changed from: Qi = cumulative release of noble gas radionuclide i over the period of interest (uci) Change to: Q; = cumulative release of noble qas radionuclide i over the period of interest (uci) where uci * (uci/cc) (cc released) or (uci/sec) (sec released)
MPCe of lE-05 uci/ml used for default _2Rl3 radiation monitor setpoint.
Reason: Provided definition of how uci value is obtained
Change to:
MPCe of 3.38E-06 uci/ml used for default 2Rl3 radiation monitor setpoint.
Reason:
See Appendix A for justification of MPC*
Chanqe f 3 page 24 section 2.4.l and page 25 section 2.4.2 Changed from:
Qi = cumulative release of noble gas radionuclide i over the period of interest (uci)
Change to:
Q; = cumulative release of noble qas radionuclide i over the period of interest (uci) where uci * (uci/cc) (cc released) or (uci/sec) (sec released)
Reason:
Provided definition of how uci value is obtained *
* 2
* 2
* Cha.nqe 14 Page 41 table l-1 Changed from: Circulating Water Pump default value of l.85E5 gpm Changed to: Circulating water Pump default value of l.OOE5 gpm Reason: Tests conducted by Maplewood RTL indicated a flow of less than 185,000 gpm. Default value was adjusted downward to be conservative.
* Cha.nqe 14 Page 41 table l-1 Changed from:
Test results are found in test document #73752B Chanqe ts P1ge 41 tlble 1*1 Changed frC111: Parllll'lltter SEN 1*R18 1*R19 CA,B,C,D) 1*R13 CA,B,C,D,E)
Circulating Water Pump default value of l.85E5 gpm Changed to:
Change to: SEN 1 *R18 1*R19 (A,B,C,D) 1*R13CA,I) 1 *R13 CC,D,I) Reason: as dete1'111ined Actual VllUI .. detll'llined Def1Ult Units CClllllllntS Value Z.9E+07 per redwa1ta affluent (Cs*137> uc:i /Ill Z.9E+07 5.6Z&#xa3;+07 Def1Ult V1lU1 Z.91+07 Z.91+07 5.62E+07 1.01E+OI *unit*
Circulating water Pump default value of l.OOE5 gpm Reason:
uc:i/*l st ... Generator cca-137> Service Water
Tests conducted by Maplewood RTL indicated a flow of less than 185,000 gpm. Default value was adjusted downward to be conservative. Test results are found in test document #73752B Chanqe           ts P1ge 41 tlble 1*1 Changed frC111:
* Cont*i,_,t fan cooling (Cl*137) Comlnt* Rldwlste efflu.nt (Cl*137) St ... Gerwr1tor llowdown (Cs*137) Service W1ter &deg; Cont1i,_,t F1n Cooling <Cs-137) Monitor sensitivities changed due to a detector replacement in accordance with Design Change Package # lEC-3049,lEC-3061, and lEC-3056.
Parllll'lltter                 Def1Ult  Units              CClllllllntS Value SEN 1*R18             as        Z.9E+07  c~    per  redwa1ta affluent (Cs*137>
3
dete1'111ined          uc:i /Ill 1*R19                        Z.9E+07              st... Generator      ll~    cca-137>
*
CA,B,C,D) 1*R13                         5.6Z&#xa3;+07            Service Water
* Chanq* f 6 Page 41 table 1*1 Change from: Parameter SP 1*R18 1*R19** 1*R13 .. Change to: Parameter SP 1*R18 1*R19** Actual value calculated calculated calculated Actual Value calculated calculated 1*R13(A,B>..
* Cont*i,_,t fan cooling CA,B,C,D,E)                                        (Cl*137)
calculated CC,D,E)**
Change to:
Reason: Default Value Units 4.4E+05(+blcg) ci:m 1.3E+04(+blcg) 2.6E+03(+blcg)
Actual        Def1Ult    *unit*                    Comlnt*
Default Value Units 1.13E05(+blcg)
SEN 1*R18 1*R19
Cpnl 7.25E+03C+blcg) 6.7E+02(+blcg) 1.2E+03(+blcg)
                          ..
Cooments Default alarm setpoints; more conservative values may be used as deemed appropriate and desirable for ensuring regulatory compliance and for maintaining releases A LARA Conmen ts Default alarm setpoints; more conservative values mey be used as deemed appropriate and desirable for ensuring regulatory compliance and for .. intaining releases ALARA. Setpoints were changed following work from Design Change Package #lEC-3049,lEC-3061,lEC-3056 and updated Circulating Water Data. Chanqe f 7 page 42 table 1*2 Change fre11: Par-ter SEN 2*R18 2*R19 CA,B,C,D) 2*R13 (A,B,C) R37 Actual Value .. deten1fned Default Value 8.SE+07 8.SE+07 8.8E+07 8.8E+07 Unit* cpm per uci/cm1 4 Camientl radwast* effluent ccs-137) Stea1111 Generator Blowclown (Cs-137 Service Water* Contairment fan cooling cca-137> Ch .. ical Waste Basin (Ca*137)
VllUI detll'llined V1lU1 Z.91+07 Z.91+07
* Change to: Paranwter Actual V*lue SEN 2-R18 es determined 2-R19(A,C) 2*R19(8) 2*R19(D) 2-R13 CA,8,C) R37 Reason: Default Value 1.14E+08 1 .26E+08 1.14E+08 1.13E+08 9.05E+07 1.24E+08 Units cpn per uci/ml Conmentl Redwaste effluent CCs-137) S/G blowdown rate per generator Service Water* Contairment fan cooling (Cs-137) Cheiaical Waste Basin discharge Sensitivities were updated to reflect current design information and to include changes from Design Change Package #2EC-3049,2EC-3053, and 2EC-3054.
                                              ~per uc:i/*l Rldwlste efflu.nt (Cl*137)
Chanqe ta Page 42 table 1-2 Change from: Parameter cw Change to: Parameter cw Reason: Actual Value as detennined Actual Value as detel'llf ned Default Value 1.85E5 Default Value 1.00E5 Unit* Unit* ccnmenu *T Circulating Water System, a single cw no in service for 2R13 monitor see section 1.2.2 Caa.ntl Cfrculating W.ter Syst*, a single cw pulp (Note no CW pulp In service for 2R13 monitor '" section 1.2.2 Tests conducted by Maplewood RTL indicated a flow less than 185,000 gpa. Flow rate was adjusted downward to be conservative.
St... Gerwr1tor llowdown (Cs*137)
Test results can be found in test document #727538
(A,B,C,D) 1*R13CA,I)                  5.62E+07                 Service W1ter      &deg; Cont1i,_,t F1n Cooling <Cs-137) 1*R13 CC,D,I)               1.01E+OI Reason:
* 5 Chanqe f 9 Page 42 table 1-2 Change fr0111: Parameter AA A37 Change to: Parameter AA A37 Reason: Actual Value as detennined Actual Value as detenni ned Default Value 300 Default Value 1200 Units gpm Units gpni Conmen ts Chemical Waste Basin discharge Conmen ts Chemical Waste Basin discharge Clearwell Pumps were replaced in 1985 with higher capacity pumps. The maximum flowrate changed from 300 to 1200 gpm. Change was performed under Design Change Package #lEC-1025.
Monitor sensitivities changed due to a detector replacement in accordance with Design Change Package # lEC-3049,lEC-3061, and lEC-3056.
Chanq* f 10 page 42 table 1-2 Change fr0111: Par.,..ter ActUlll Value SP 2*A18-calculated 2-R19*-calculated 2*R13*-calculated R37"-calculated Change to: P11r111111ter Actual Valua SP 2*R18 calculated 2*R19(A,C>-
3
cah:ulated 2-R19CB>-2*A19(0)-2*A13-calculated R37'*'* calculated Deflult Units Value 8.0E+OS(+bkg)
* Chanq* f 6 Page 41 table 1*1 Change from:
Cpl 3.9E+04(+bkg) 8.8E+02(+bkg) 1.6E+04(+bkg)
Parameter       Actual    Default        Units                            Cooments value      Value SP   1*R18       calculated  4.4E+05(+blcg)  ci:m        Default alarm setpoints; more conservative values may be used as deemed appropriate 1*R19**     calculated   1.3E+04(+blcg)               and desirable for ensuring regulatory compliance and for maintaining releases ALARA 1*R13.. calculated  2.6E+03(+blcg)
Default Units Value 3.21E+05(+bkg)
Change to:
Cpill 3.15E+04(+bkg) 2.85E+04(+bkg) 2.825E+04(+bkg) 3.0SE+02(+bkg) 3.10E+03(+bkg) 6 Cannenta Default alal'lll setpoints; more conservative values may be used as deemed appropriate and desirable for ensuring regulatory ind for maintaining releesn Al.ARA . Cannents Def1ult alar111 1etpoints; more conservative v1lues.may be used as deemed appropriate and desir1ble for ensuring regulatory c&deg;""liance and for maintaining releasn Al.ARA.
Parameter        Actual    Default        Units                             Conmen ts Value      Value SP    1*R18          calculated 1.13E05(+blcg)     Cpnl     Default alarm setpoints; more conservative values mey be used as deemed appropriate and 1*R19**        calculated 7.25E+03C+blcg)             desirable for ensuring regulatory compliance and for .. intaining releases ALARA.
* Reason: Setpoints were updated to current design information and to include changes from Design Change Package #2EC-3049,2EC-3053, and 2EC-J054.
1*R13(A,B>.. calculated  6.7E+02(+blcg)
Corrected typographical error for number of asterisks after the RJ7 monitor and at the bottom of the page. Chanq* 111 Page 49 table 2*2 Change frcm: Par-ter SP 1*R41C 1*R16 1*R12A-Change to: Par-ter SP 1*R41C 1*R16 1*R12A-Reason: Act1.111l Default Value Value calculat9d 3.3E+04(+blcg) calculat9d 7.4E+04(+blcg) calculated 1.SE+04(+blcg)
CC,D,E)**            1.2E+03(+blcg)
Act1.111l Default Value Value calculat9d 3.2E+04(+blcg) .calculat9d 7.2E+04(+blcg) calculat9d 1.5E+04(+blcg)
Reason:
Unit* cs-Units cs-Defeult alal'll 1etpoint1; more conaervative values 11111y be used as cleemd appropriate and desirable for ensuring r-..ilatory and 111aintaining rel*** .. ALARA. Can11nt1 Defeult alal'll setpoint1; more conmervative values .. Y be used as de-.:1 9"M"opriata and desirable for ensuring regulatory coq>l iance and .. intafning relea1 .. ALARA. setpoints were revised slightly due to recalculation of current setpoints.
Setpoints were changed following work from Design Change Package
Values were rounded down to be conservative.
  #lEC-3049,lEC-3061,lEC-3056 and updated Circulating Water Data.
7 -
Chanqe f 7 page 42     table 1*2 Change fre11:
* Chanqe 112 Page 50 table 2-3 Change fran: Parameter SP 2*R41C 2-R16 2*R12A-Change to: Par!lllleter SP 2*R41C 2*R16 2-R12A-Reason: Actu.l V*lue c*lcul*tld c*lcul*Ud c*lcul*ted ActUlll Value calculated calculated calculated Default Value 3.3E+04(+b<<g) 7.2E+04(+b<<g) 2.4E+05(+bltg)
Par-ter             Actual      Default          Unit*                Camientl SEN     2*R18 2*R19
Default Value 3. 2E+04( +beg) 7.0E+04(+b<<g) 2.4E+05(+b<<g)
                            ..
Units unit* Cammi ts Default 1l1n1 setpoints; more conserv1tlve v1lues may be used H deemed approi:iriate Ind desirable for ensuring regulatory coq>lill'ICe and for 1111intaining releases Al.ARA. Default alar11 setpoints; more conserv11tfw values *Y be used u de..ct IRX"opriate and ctnfrable for ensuring regulatory ccaipli1nee and fOlt' nmintainf ng releHn ALARA. Setpoints were adjusted slightly following recalculation with current design information.
Value deten1fned Value 8.SE+07 8.SE+07 cpm per uci/cm1 radwast* effluent ccs-137)
Chanqe 113 Page 51 table 2-4 Change frca: Technical Specificatfon 6.9.1.10 Change to: Loctitfan second s.n (0.21 *flel*> Deleted Second 5'n frm table Reason: Pathw.y<s>
Stea1111 Generator Blowclown (Cs-137 CA,B,C,D) 2*R13                          8.8E+07                    Service Water* Contairment fan cooling (A,B,C)                                                    cca-137>
Controllfng Age Grcqa Dfrec:t upoeure n/a ..t fmalatfon Atmaplerfc Dfspersion X/Q (sec/113) a.ZZE-06 D/Q (l/182) n/* The second sun will no longer be used for visitors due to safety concerns
R37                          8.8E+07                    Ch..ical Waste Basin (Ca*137)
* 4
 
Change to:
Paranwter         Actual     Default  Units        Conmentl V*lue       Value SEN   2-R18               es   1.14E+08  cpn per Redwaste effluent CCs-137) determined           uci/ml 2-R19(A,C)               1.26E+08          S/G blowdown rate per generator 2*R19(8)                 1.14E+08 2*R19(D)                 1.13E+08 2-R13                     9.05E+07          Service Water* Contairment fan cooling CA,8,C)                                       (Cs- 137)
R37                     1.24E+08           Cheiaical Waste Basin discharge Reason:
Sensitivities were updated to reflect current design information and to include changes from Design Change Package #2EC-3049,2EC-3053, and 2EC-3054.
Chanqe       ta Page 42 table 1-2 Change from:
Parameter       Actual         Default  Unit*              ccnmenu Value         Value                                                 *T cw            as           1.85E5             Circulating Water System, a single cw detennined                          ~.(Note no CW~ in service for 2R13 monitor see section 1.2.2 Change to:
Parameter      Actual        Default  Unit*              Caa.ntl Value          Value cw            as          1.00E5            Cfrculating W.ter Syst*, a single cw detel'llf ned                      pulp (Note no CW pulp In service for 2R13 monitor ' " section 1.2.2 Reason:
Tests conducted by Maplewood RTL indicated a flow less than 185,000 gpa. Flow rate was adjusted downward to be conservative.
Test results can be found in test document #727538 *
* 5
 
Chanqe f 9 Page 42 table 1-2 Change fr0111:
Parameter         Actual  Default      Units                  Conmen ts Value    Value AA   A37             as      300            gpm        Chemical Waste Basin discharge detennined Change to:
Parameter       Actual     Default        Units                Conmen ts Value     Value AA  A37              as       1200          gpni        Chemical Waste Basin discharge detenni ned Reason:
Clearwell Pumps were replaced in 1985 with higher capacity pumps.
The maximum flowrate changed from 300 to 1200 gpm. Change was performed under Design Change Package #lEC-1025.
Chanq* f 10 page 42 table 1-2 Change fr0111:
Par.,..ter       ActUlll     Deflult        Units                  Cannenta Value      Value SP 2*A18-         calculated   8.0E+OS(+bkg)    Cpl    Default alal'lll setpoints; more conservative values may be used 2-R19*-         calculated   3.9E+04(+bkg)            as deemed appropriate and desirable for ensuring regulatory 2*R13*-        calculated   8.8E+02(+bkg)            c~lienc:e ind for maintaining releesn Al.ARA R37"-         calculated  1.6E+04(+bkg)
Change to:
P11r111111ter    Actual      Default          Units              . Cannents Valua      Value SP  2*R18          calculated    3.21E+05(+bkg)     Cpill Def1ult alar111 1etpoints; more conservative v1lues.may be used 2*R19(A,C>-    cah:ulated    3.15E+04(+bkg)           as deemed appropriate and 2-R19CB>-                    2.85E+04(+bkg)           desir1ble for ensuring regulatory 2*A19(0)-                    2.825E+04(+bkg)         c&deg;""liance and for maintaining releasn Al.ARA.
2*A13-          calculated    3.0SE+02(+bkg)
R37'*'*        calculated    3.10E+03(+bkg) 6
 
Reason:
Setpoints were updated to current design information and to include changes from Design Change Package #2EC-3049,2EC-3053, and 2EC-J054.
Corrected typographical error for number of asterisks after the RJ7 monitor and at the bottom of the page.
Chanq* 111 Page 49 table 2*2 Change frcm:
Par-ter      Act1.111l  Default      Unit*
Value      Value SP  1*R41C      calculat9d  3.3E+04(+blcg)  cs-   Defeult alal'll 1etpoint1; more conaervative values 11111y be used as 1*R16       calculat9d  7.4E+04(+blcg)          cleemd appropriate and desirable for ensuring r-..ilatory c~lianc:e and 1*R12A-     calculated  1.SE+04(+blcg)         111aintaining rel***.. ALARA.
Change to:
* Par-ter      Act1.111l    Default       Units                  Can11nt1 Value         Value SP    1*R41C    calculat9d 3.2E+04(+blcg)   cs-  Defeult alal'll setpoint1; more conmervative values ..Y be used as 1*R16    .calculat9d 7.2E+04(+blcg)         de-.:1 9"M"opriata and desirable for ensuring regulatory coq>l iance and 1*R12A-   calculat9d 1.5E+04(+blcg)        .. intafning relea1.. ALARA.
Reason:
setpoints were revised slightly due to recalculation of current setpoints. Values were rounded down to be conservative.
                                                                                              -
7
 
Chanqe 112 Page 50 table 2-3 Change fran:
Parameter        Actu.l           Default              Units                        Cammi ts V*lue            Value SP 2*R41C          c*lcul*tld        3.3E+04(+b<<g)                          Default 1l1n1 setpoints; more conserv1tlve v1lues 2-R16          c*lcul*Ud          7.2E+04(+b<<g)                          may be used H deemed approi:iriate Ind desirable for 2*R12A-       c*lcul*ted        2.4E+05(+bltg)                          ensuring regulatory coq>lill'ICe and for 1111intaining releases Al.ARA.
Change to:
Par!lllleter      ActUlll            Default            unit*
Value              Value SP 2*R41C          calculated         3. 2E+04( +beg)                       Default alar11 setpoints; more conserv11tfw values *Y be 2*R16          calculated          7.0E+04(+b<<g)                         used u de..ct IRX"opriate and ctnfrable for ensuring 2-R12A-        calculated          2.4E+05(+b<<g)                         regulatory ccaipli1nee and fOlt' nmintainf ng releHn ALARA.
Reason:
Setpoints were adjusted slightly following recalculation with current design information.
Chanqe 113 Page 51 table 2-4 Change frca:                                                       Atmaplerfc Dfspersion Technical        Loctitfan  Pathw.y<s>         Controllfng        X/Q          D/Q Specificatfon                                      Age Grcqa      (sec/113)      (l/182) 6.9.1.10        second s.n  Dfrec:t upoeure          n/a        a.ZZE-06        n/*
(0.21 *flel*> ..t fmalatfon Change to:
Deleted Second 5'n frm table Reason:
The second sun will no longer be used for visitors due to safety concerns *
* 8
* 8
* Chanqe f 14 Appendix A, Paqe A-3 Change From: :i: Ci where: Ci :i: ******* MPCi MPC 0 = an effective MPC v1lue for 1 mixture of rldionucl ide (uci/11l > Ci
 
Chanqe f 14 Appendix A, Paqe A-3 Change From:
:i:     Ci Ci
:i: *******
MPCi where:
MPC 0 = an effective MPC v1lue for 1 mixture of rldionucl ide (uci/11l >
Ci
* concentr1tion of rldionucl ide i in the 111lxture MPCi
* concentr1tion of rldionucl ide i in the 111lxture MPCi
* the 10 CFR 20, Appendix I, Table 11, Colum'I 2 MPC velue for the rldionucl Ide i (uci/111l)
* the 10 CFR 20, Appendix I, Table 11, Colum'I 2 MPC velue for the rldionucl Ide i (uci/111l)
B1sed on the 1bove Ind the rldionuclide di1tril:lutfon in the efflumnts for the past ye1rs from S1lem, 111 efflctlve MPC v1lue c., be deterafned.
B1sed on the 1bove ~tion Ind the rldionuclide di1tril:lutfon in the efflumnts for the past ye1rs from S1lem, 111 efflctlve MPC v1lue c., be deterafned. Results ire prnented In Tlbl* A*1 and A*2 for Unit 1 and Unit 2, respectively.
Results ire prnented In Tlbl* A*1 and A*2 for Unit 1 and Unit 2, respectively.
Considering the 1verqe efflctive MPC v1lue for the years 1911 through 1919, It Is reaaonlbla to select an MPC, value of 1E*05 uci/11l 11 typical of liquid rldwlste df1charg... Using this value to calculate the default R18 1l1nn setpoint v1lue, results in a setpoint that:
Considering the 1verqe efflctive MPC v1lue for the years 1911 through 1919, It Is reaaonlbla to select an MPC, value of 1E*05 uci/11l 11 typical of liquid rldwlste df1charg ... Using this value to calculate the default R18 1l1nn setpoint v1lue, results in a setpoint that: 1) Will not require re*edjuat.nt due to *inor variatiana In the ru:lide distribution which are typic*l of routine pl1nt oper1tfons, and 2> Will provide for 1 liquid rldw8ate disch1rge r1t1 ( 11 ..,.luated for each batch-rel****>
: 1) Will not require fr~t re*edjuat.nt                   due to *inor variatiana In the ru:lide distribution which are typic*l of routine pl1nt oper1tfons, and 2> Will provide for 1 liquid rldw8ate disch1rge r1t1 ( 11 ..,.luated for each batch-rel****> th*t ia CC11'4)1tible with pl1nt operations < refer to Tlbles 1*1 Ind 1*2).
th*t ia CC11'4)1tible with pl1nt operations  
Change To:
< refer to Tlbles 1*1 Ind 1*2). Change To: :i: c 1 <1 ...... itters only) J14PC. 8 *******o*ooo**********************
:i:   c <1......
c, <1--> c, (noi't*g .... ) :i: ************  
1        itters only)
+ :i: ***********o***
J14PC. 8   *******o*ooo**********************
MPC1 MPC1 Where: MPC*
c, <1-->       c, (noi't*g.... )
* an effective MPC value for a 11ixtur1 of radfonucl ide (uci /*l > C 1
:i: ************ + :i: ***********o***
* concentration.of redianuclide i in the 11ixtur1 MPC 1
MPC1                 MPC1 Where:
* the 10 CFI 20, I, Table II, Columt 2 MPC val .. for redionuclide f (uci/11l)
MPC*
The equation for det1M1fnfng the liquid affluwit S1tpolnta  
* an effective MPC value for a 11ixtur1 of radfonucl ide (uci /*l >
< Section 1.2.1, equation 1.2 > i 1 baaed on a rrultiplfc1tfon of the 1ffectlw MPC ti-th* 1111nltor  
C1
... ltlvlty. lbMvef', the redlation 1111nitors on the effluent l fnee wll l not detect  
* concentration.of redianuclide i in the 11ixtur1 MPC1
.. itting radlonucl ldn, such aa H*3, Fe*55, ltld Sr*90. The derivation of th* 1ffectiw Mlle ( section 1.2.1, aqumtlon 1.J > 11 valid for.,,,, distribution but .,.t bl modified to account for the feet that the effluent 1111nltor will not detect th* non*v-. The above modified equation for the effective MPC provldn for a default Sltpoint det1M1inatton that accounts for the non*g ...... lttlng redlcniclldaa.
* the 10 CFI 20, ~Ix I, Table II, Columt 2 MPC val .. for redionuclide f (uci/11l)
Considering the ._., ... effectlw MPC val .. for th* yurs 1918 through 1990, It Is r1uonabl1 to select an MPC, value of 4.711*06 ui;l/*l for Unit 1 ltld 3.38E*06 uci/*l for Unit 2 aa typical *of liquid rldw8ste dischargn.
The equation for det1M1fnfng the liquid affluwit S1tpolnta < Section 1.2.1, equation 1.2 > i 1 baaed on a rrultiplfc1tfon of the 1ffectlw MPC t i - th* 1111nltor . . . ltlvlty. lbMvef', the redlation 1111nitors on the effluent l fnee wll l not detect non-~ ..itting radlonucl ldn, such aa H*3, Fe*55, ltld Sr*90. The derivation of th* 1ffectiw Mlle ( section 1.2.1, aqumtlon 1.J > 11 valid for.,,,, distribution but .,.t bl modified to account for the feet that the effluent 1111nltor will not detect th* non*v-. The above modified equation for the effective MPC provldn for a default Sltpoint det1M1inatton that accounts for the non*g......lttlng redlcniclldaa.
Ualne these values to c.lculat*
Considering the ._.,... effectlw MPC val .. for th* yurs 1918 through 1990, It Is r1uonabl1 to select an MPC, value of 4.711*06 ui;l/*l for Unit 1 ltld 3.38E*06 uci/*l for Unit 2 aa typical *of liquid rldw8ste dischargn. Ualne these values to c.lculat* th* default R18 alaMI Sltpolnt val .. , results In a 1etpoint that:
th* default R18 alaMI Sltpolnt val .. , results In a 1etpoint that: 1) Will not require re*edjuat_,,t due to 11inor variations the nucl Ide distribution which 11r1 typical of routine plant operatlana, ltld 2> Will provide for a liquid radwaat* diacherge rate (II ..,.luated for each batch r1l .. H) that i1 with pl1nt operatiana  
: 1) Will not require f~t re*edjuat_,,t due to 11inor variations the nucl Ide distribution which 11r1 typical of routine plant operatlana, ltld 2> Will provide for a liquid radwaat* diacherge rate (II ..,.luated for each batch r1l ..H) that i1 c~tible        with pl1nt operatiana < refer to Tabl" 1*1 ltld 1*2).
< refer to Tabl" 1*1 ltld 1*2). Reason: To account for qamma and non-qamma emitters as required by Technical Specification 3.11.1.1 9 Cbanq* fl!F Tables A-1 and A-2 Change from: Tables of effective MPC values for the years 1984 -1989 for Unit l and Unit 2 Change to: Table of effective MPC values for the years 1988 -1990 Reason: To calculata a effective MPC value that includes the gamma and non-gamma required by Technical Specifications Chuqa t 11 Tabla E-1 Change From: STATION CODE 14Fl Chanqa To: STATION CODB 14Fl 14F4 Reason: STATION LOCATION 5.5 mi. WNW of vent1 local farm STATION LOCATION 5.!5 m.. WNW of vent; local fal'll 7.6 mi. WNW of vant1 local fal'll SAMPLE TYPE VGT,MLK SAMPLE TYPE VGT MLK Farm 14Fl cea*ed milk operation*
Reason: To account for qamma and non-qamma emitters as required by Technical Specification 3.11.1.1
on Juna 1,1991. Farm 14F4 was added to the Radiological Environmental Monitoring Program. 10
* 9
' SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCUIATION MANUAL Revision 7 1/06/92
 
* Approval SORC Chairun: tV" Date:
Cbanq* fl!F Tables A-1 and A-2 Change from:
Mtq. # 7 ""'-007 *
Tables of effective MPC values for the years 1984 - 1989 for Unit l and Unit 2 Change to:
* Salem ODCM Rev. 7 The radioactivity monitor setpoint equation (1.2) remains valid during outages when the circulating water dilution is potentially at its lowest value. Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria.
Table of effective MPC values for the years 1988 - 1990 Reason: To calculata a effective MPC value that includes the gamma and non-gamma e~itters required by Technical Specifications Chuqa t   11 Tabla E-1 Change From:
However, in order to maximize the available plant discharge dilution and thereby minimize the potential offsite doses, releases from either Unit-1 or Unit-2 may be routed to either the Unit-l or Unit-2 Circulating Water System discharge.
STATION CODE                 STATION LOCATION          SAMPLE TYPE 14Fl             5.5 mi. WNW of vent1 local farm       VGT,MLK Chanqa To:
This routing is possible via interconnections between the Service Water Systems (see Figures land 2). Procedural restrictions prevent simultaneous releases from either a single unit or both units into a single Circulating Water System discharge.
STATION CODB                STATION LOCATION         SAMPLE TYPE 14Fl              5.!5 m.. WNW of vent; local fal'll       VGT 14F4              7.6 mi. WNW of vant1 local fal'll       MLK Reason:
1.2.2-Conservative Default Valu*** Conservative alarm setpoints may be determined through the use of default parameters.
Farm 14Fl cea*ed milk operation* on Juna 1,1991. Farm 14F4 was added to the Radiological Environmental Monitoring Program.
Tables 1-1 and l-2 summarize all current default values in use for Salem Unit-l and Unit-2, respectively.
10
They are based upon the following:
 
a) substitution of the effective MPC value with a default value of 4.71E-06 uCi/ml (Unit 1) and 3.38E-.06 uci/ml (Unit 2). (refer to Appendix A for justification);
    '
b) for additional conservatism*, substitution of the I-131 MPC value of 3E-07 uci/ml for the Rl9 Steam Generator Slowdown Monitors, the R-37 Chemical Waste Basin monitor and the R-13 Service Water Monitors.
SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCUIATION MANUAL Revision 7 1/06/92
* Based upon the potential for I-131 to b* present in the secondary and service water systems, the use of the default effective MPC value as derived in Appendix A may be conservative for the 1, 2 R-19 SGBD monitors, the R-37 Chemical waste Basin Monitor and the R-13 Service Water Monitors.
* Approval SORC Chairun: tV"c?tZ'o-:L~    Date: @~6--      Mtq. # 7 ""'- 007
5
* Salem ODCM     Rev. 7 The radioactivity monitor setpoint equation (1.2) remains valid during outages when the circulating water dilution is potentially at its lowest value. Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria.
*
However, in order to maximize the available plant discharge dilution and thereby minimize the potential offsite doses, releases from either Unit-1 or Unit-2 may be routed to either the Unit-l or Unit-2 Circulating Water System discharge.     This routing is possible via interconnections between the Service Water Systems (see Figures land 2). Procedural restrictions prevent simultaneous releases from either a single unit or both units into a single Circulating Water System discharge.
* c) d) Salem ODCK Rev. 7 substitutions of the operational circulatinq water flow with the lowest flow, in qal/min: and, substitutions of the effluent release rate with the highest allowed rate, in gal/min. With pre-established alarm setpoints, it is possible to control the radwaste release rate (RR) to ensure the inequality of equation (1.2) is maintained under changing values for MPCe and* for differing Circulating Water System dilutions
1.2.2- Conservative Default Valu***   Conservative alarm setpoints may be determined through the use of default parameters.       Tables 1-1 and l-2 summarize all current default values in use for Salem Unit-l and Unit-2, respectively. They are based upon the following:
a) substitution of the effective MPC value with a default value of 4.71E-06 uCi/ml (Unit 1) and 3.38E-.06 uci/ml (Unit 2). (refer to Appendix A for justification);
b) for additional conservatism*, substitution of the I-131 MPC value of 3E-07 uci/ml for the Rl9 Steam Generator Slowdown Monitors, the R-37 Chemical Waste Basin monitor and the R-13 Service Water Monitors.
* Based upon the potential for I-131 to b* present in the secondary and service water systems, the use of the default effective MPC value as derived in Appendix A may be non-conservative for the 1, 2 R-19 SGBD monitors, the R-37
* Chemical waste Basin Monitor and the R-13 Service Water Monitors.
5
 
Salem ODCK   Rev. 7 c)  substitutions of the operational circulatinq water flow with the lowest flow, in qal/min: and, d)  substitutions of the effluent release rate with the highest allowed rate, in gal/min.
With pre-established alarm setpoints, it is possible to control the radwaste release rate (RR) to ensure the inequality of equation (1.2) is maintained under changing values for MPCe and*
for differing Circulating Water System dilutions *
* The Unit 2 seriice Water system utilizes the Unit l Circulating Water syat.. tor dilution prior to release to th* river. It is possible to have the Unit l Circulating Water system out of service when Unit l is in an outage. So, for conservatism no dilution is used for determining a 2Rl3 default alarm setpoint.
* The Unit 2 seriice Water system utilizes the Unit l Circulating Water syat.. tor dilution prior to release to th* river. It is possible to have the Unit l Circulating Water system out of service when Unit l is in an outage. So, for conservatism no dilution is used for determining a 2Rl3 default alarm setpoint.
Because no dilution is considered and the 2Rl3 monitor sensitivity is high, the of 3.38E-06 uCi/ml is used in calculating the alarm setpoint (otherwise using JE-07 uCi/ml would result in an alarm setpoint of l cpm) * '
Because no dilution is considered and the 2Rl3 monitor sensitivity is high, the ~* of 3.38E-06 uCi/ml is used in calculating the alarm setpoint (otherwise using JE-07 uCi/ml would result in an alarm setpoint of l cpm) *
* Salem ODCM Rev. 7 2.4 Noble Ga1 lttluent Po** Calculation*  
*                                  '
-10 CPR so ONRISTBXCTID AR.II pose Noble G&S!I. Technical Specification 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of mrad, gamma-air and mrad, beta-air and the calendar year limits mrad, gamma-air and mrad, beta-air.
 
The limits a.re applicable separately to each unit and are not combined site limits. The following equations shall be used to calculate the gamma-air and beta-air doses: where: = = X/Q * -= N. = I 3. l 7E-08 = = and = 3.17E-08
Salem ODCM       Rev. 7 2.4   Noble Ga1 lttluent     Po** Calculation* - 10 CPR so ONRISTBXCTID   AR.II pose       Noble   G&S!I. Technical Specification 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of     ~5  mrad,   gamma-air and     ~10  mrad,   beta-air and the calendar year limits       ~10  mrad, gamma-air and     ~20  mrad, beta-air.
The limits a.re applicable separately to each unit and are not combined site limits.         The following equations shall be used to calculate the gamma-air and beta-air doses:
                      =                                                 (2.7) and
                      =   3.17E-08
* X/Q
* X/Q
* I: (Nf
* I: (Nf
* Q 1) air dose due to gamma emissions for noble gas radionuclides (mrad) air dose due to beta emissions for noble gas radionuclides (mrad) (2.7) (2.8) atmospheric dispersion to the controlling SITE BOUNDARY location ( sac/m3) cumulative release of noble gas radionuclide i over the period of interest (uCi) where uci * (uci/cc) (cc releaaad) or (uCi/sec) (sec released) air dose factor due to gamma emissions from noble gas radionuclide i (mrad/yr per uCi/m3, from Table 2-1) air dos* factor due to beta emissions from noble gas radionuclide i (mrad/yr per uCi/m31 Table 2-1) conversion factor (yr/sec) 24 I
* Q1 )            (2.8) where:
* Per111111eter Ac:tu.l MP Ce c:alc:ullted MPC 1*131 3E*07 Ci measured MPCf ** clete,..i necl SEN 1-1'18 ..
            =    air dose due to gamma emissions for noble gas radionuclides (mrad)
1*R19 (A,11,C,D) 1*R13 CA,11) 1*R13 CC,D,E) cw ** clete,..i necl RR 1*R18 ** clete,..i necl 1*R19 1*R1l SP 1-lt18 c*lcul*tld Hl1.,_ c*lcul*tld 1*R13CA,I)
            =    air dose due to beta emissions for noble gas radionuclides (mrad)
.. calcul*tad 1*R13(C,D,E>
X/Q
.. Salem ODCM Rev. 7 Tlble 1*1 Par-tera for Ala,.. Setpofnt D*t*,..fNtiona unit 1 DefM.ll t units Value V1lue 4.71E*06*
* atmospheric dispersion to the controlling SITE
UC:i/*l c:alc:ulated for .. ch batch to be releued N/A UC:f/*l 1*131 MPC conael"V9tfvely used for SG blow clown Incl Service Water 111nitor satpoints N/A UC:i/*l taklf'I frm g-spectral aNlysis of  
            -    BOUNDARY location ( sac/m3) cumulative release of noble gas radionuclide i over the period of interest (uCi) where uci * (uci/cc) (cc releaaad) or (uCi/sec) (sec released)                         I
*ff lUlnt N/A UCl/*l taken frm 10 CFI 20, I, Tlble II, Col. 2. 2.9E+07 par R..,._t* effluent CC1*137> uci/*l 2.9E+07 Sta .. Generator ll&deg;""**" (Ca*137> 5.62E+07 Service Water
            =    air dose factor due to gamma emissions from noble gas radionuclide i (mrad/yr per uCi/m3, from Table 2-1)
* Contmi,_,t Fan Cooling CCa*137> 1.01E+OI 1.00&#xa3;+05 -circulating Water Syst*, single cw 120 p cletel'lllnecl pt-lor to rele ... ; release rate cen be edjUlted for Technical Specification CClllPl I ance 120 st ... Generator bl&deg;"'**" rate par Generator 2500 Service Water flo.i r*t* for Contai,_..t fan cool era 1 .13E+05C+bk;>
N.I =    air dos* factor due to beta emissions from noble gas radionuclide i (mrad/yr per uCi/m31 Table 2-1)
CPI Defa1lt *l*rm aatpointa;  
: 3. l 7E-08 =    conversion factor (yr/sec)
.,,.. consarv*tive val._ ..., be used n cla-.d apprapri*t*
* 24
and 7.251.aJ(+bq) cla9ir*l*
 
for ..urlftl retUl*tory cC111Plianc*
Salem ODCM                 Rev. 7 Tlble 1*1 Par-tera for     Li~icl  Ala,.. Setpofnt D*t*,..fNtiona unit 1 Per111111eter    Ac:tu.l        DefM.ll t       units                               C~ts Value         V1lue MP Ce            c:alc:ullted    4.71E*06*     UC:i/*l         c:alc:ulated for ..ch batch to     be releued MPC 1*131        3E*07          N/A           UC:f/*l         1*131 MPC conael"V9tfvely used for SG blow clown Incl Service Water 111nitor satpoints Ci              measured        N/A           UC:i/*l         taklf'I frm g - spectral aNlysis of         li~icl
end for *int*lnll'll rel._.. ALMA. 6.7!+02C+bkl>
                                                                    *ff lUlnt MPCf
1.Zt+G3C..atl>
                        **          N/A           UCl/*l             taken frm 10 CFI 20,       ~ht      I, Tlble II, SEN 1-1'18            ..
* Refer to A for mrlvatlon  
clete,..i necl cletena~
** The MPC of 1*131 C3E*07 UCl/*l> hu been used for derivation of the 119 St** Generator blC*clown end 113 service Water manltor satpoint1 as dl1CUIHd In Section 1.2.2
2.9E+07     c:~ par uci/*l Col. 2.
* 41 P11r11111eter Ac:tual Value ... ... .. .. -* ..............
R..,._t* effluent CC1*137>
MPCe c:alc:ulated MPC 1*131 3E*07 Cf measured MPCi IS deten1ined SEN 2*"18 IS 2*R19(A,C) det*r11ined 2*R19(8) Salem ODCM Rev. 7 Table 1*2 Par.meters for Liquid Alart11 Setpoint Deter111inationa Unit 2 Deflult Value 3.381!*06*
1*R19                      2.9E+07                           Sta.. Generator ll&deg;""**" (Ca*137>
N/A N/A N/A 1. 14E+Oa 1.26E+OS 1.14E+Oa units UCl/*l UCl/*l UCi/ml UCl/11l C:s-/UCf/*l Cammnta ---------*****---------------------------
(A,11,C,D) 1*R13 CA,11)                5.62E+07                         Service Water
calcul1ted for elCh bitch to be rele11ed 1*131 MPC conserv1tfvely used for SG blow* down, Service Water rd Che11ic1l W11te Basin 1110nitor 1etpoints tlken frm 11-apectrel 1n1lysis of Liquid effluent tlken fra1110 CFll 20, Appendfx B, Table II, Col. 2. R...._te effluent CC.*137> Ste .. Genlr1tor llowdown (Cs*137) R13 .19(0) 1.13E+OS 9.05E+07 Servfce W1ter
* Contmi,_,t Fan Cooling CCa*137>
* Cont1l,_,t fin cool Ing (Cl-137) * ** R37 cw .. deten1ined RR 2*R18 .. det*1"91ined 2*R19 2*R13 R37 SP 2*R18 c:1lc:ul1ted 2*R19CA,C>-
                                                  -
2*R19(8) .. 2*R19CD) .. 2*R13 .. R37'** 1 .24E+OS 1.00E+05 120 120 2500 1200 3.21E+05(+bq) 3.15E+04<+bkl>
1*R13 CC,D,E)              1.01E+OI cw                    **
clete,..i necl 1.00&#xa3;+05                         circulating Water Syst*, single       cw ~
RR    1*R18            **
clete,..i necl 120           p                 cletel'lllnecl pt-lor to rele...; release rate cen be edjUlted for Technical Specification CClllPl Iance 1*R19                        120                             st... Generator bl&deg;"'**" rate par Generator 1*R1l                      2500                             Service Water flo.i r*t* for Contai,_..t fan cool era SP 1-lt18        c*lcul*tld      1.13E+05C+bk;>   CPI             Defa1lt *l*rm aatpointa; .,,.. consarv*tive val._ ..., be used n cla-.d apprapri*t* and Hl1.,_      c*lcul*tld      7.251.aJ(+bq)                     cla9ir*l* for ..urlftl retUl*tory cC111Plianc*
end for *int*lnll'll rel._.. ALMA.
1*R13CA,I).. calcul*tad        6.7!+02C+bkl>
1*R13(C,D,E>..                    1.Zt+G3C..atl>
* Refer to ~Ix A for mrlvatlon
  ** The MPC val~ of 1*131 C3E*07 UCl/*l> hu been used for derivation of the 119 St** Generator blC*clown end 113 service Water manltor satpoint1 as dl1CUIHd In Section 1.2.2 *
* 41
 
Salem ODCM              Rev. 7 Table 1*2 Par.meters for Liquid Alart11 Setpoint Deter111inationa Unit 2 P11r11111eter     Ac:tual         Deflult        units                            Cammnta Value             Value
      ... ... . . -*   ..............
                                                                          ---------*****---------------------------
MPCe            c:alc:ulated      3.381!*06*    UCl/*l            calcul1ted   for elCh bitch to be rele11ed MPC 1*131        3E*07              N/A          UCl/*l            1*131 MPC conserv1tfvely used for SG blow*
down, Service Water rd Che11ic1l W11te Basin 1110nitor 1etpoints Cf              measured            N/A          UCi/ml            tlken frm 11- apectrel 1n1lysis of Liquid effluent MPCi                  IS            N/A          UCl/11l          tlken fra1110 CFll 20, Appendfx B, Table II, deten1ined                                        Col. 2.
SEN 2*"18            IS          1. 14E+Oa    C:s-/UCf/*l        R...._te effluent CC.*137>
2*R19(A,C)        det*r11ined      1.26E+OS                        Ste.. Genlr1tor llowdown (Cs*137) 2*R19(8)                          1.14E+Oa
.19(0)                                 1.13E+OS R13                            9.05E+07                         Servfce   W1ter
* Cont1l,_,t fin cool Ing (Cl-137) cw R37
                            ..
deten1ined 1.24E+OS 1.00E+05 Ch*ICll WUt* Blain dfsch1rge Clrcul1tfng W.ter Syst*, single cw ~
(Note no CW pulp fn servic:e for 2R13 111onf tor RR 2*R18             ..
det*1"91ined 120
                                                                          ' " aectlan 1.2.2>
deten1fnld prior to rel ....: rele111 rete c1n be adjusted for Technic:al Specffle1tion CallPlfera 2*R19                             120                        St** Genentor blowdawn rite per 11erwr1tor 2*R13                           2500                        hr'lfce *ter flOM l"llte for Cont1f ..-n: fan cool era R37                             1200                        Ch*fe1l Wute lain df ach1rge SP 2*R18 2*R19CA,C>-
2*R19(8) ..
2*R19CD)..
2*R13..
c:1lc:ul1ted      3.21E+05(+bq) 3.15E+04<+bkl>
2.85E+04(+bkg) 2.825!+04(+bQ) 3.05E+02<+bkl>
2.85E+04(+bkg) 2.825!+04(+bQ) 3.05E+02<+bkl>
: 3. 10E+03(+bkg)
Deflult 1l1r11 11tpofnts: mre conservative YllUM my be uud U       deemd li:ipr"OfX"ilte and desirable for ..urlng regul1tory campl lance rd for *fntalntng relelHS AL.ARA.
Ch*ICll WUt* Blain dfsch1rge Clrcul1tfng W.ter Syst*, single cw (Note no CW pulp fn servic:e for 2R13 111onf tor '" aectlan 1.2.2> deten1fnld prior to rel .... : rele111 rete c1n be adjusted for Technic:al Specffle1tion CallPlfera St** Genentor blowdawn rite per 11erwr1tor hr'lfce *ter flOM l"llte for Cont1f ..-n: fan cool era Ch*fe1l Wute lain df ach1rge Deflult 1l1r11 11tpofnts:
                                                                                                                                                -
mre conservative YllUM my be uud U deemd li:ipr"OfX"ilte and desirable for ..urlng regul1tory campl lance rd for *fntalntng relelHS AL.ARA. -Refer to Appendix A for deriv1tlon The MPC v1lue of 1*131 C3E*07 UCl/11l> his been UHd for clerfv1tion of the R19,R13,and R37 monitor setpoints  
R37'**                      3. 10E+03(+bkg)
** dfsc:uased In S9Ctfon 1.2.2
* Refer to Appendix A for deriv1tlon
* 42
**          The MPC v1lue of 1*131 C3E*07                 UCl/11l> his   been   UHd     for clerfv1tion   of   the   R19,R13,and R37 monitor setpoints ** dfsc:uased In S9Ctfon 1.2.2
*
* 42
* Salem ODCM Rev. 7 r.ol* 2-2 P1r-t1f'I for G.11ous Al11'11 Setpoint D*t*l'llinattona untt-1 P*r-ter Actl.Wl* Oefeul t Vlll.W V1lue -------* ----------------X/Q c1lcul1t1d 2.2E*06 VF 1s me1sured 1.25E+05 CPL1nt or Vent) f1n curves VF 1s ***ured 3.5E+04 (Cont. or Purge) f1n curves AF coordiMted 0.25 Ci me1sured N/A ICI nuclide 1p1eific N/A Li nuclide *P1Cific N/A Mi nuclide 1p1elflc N/A SEN 1*R41C-11 1.6E+07 1*R16 1*R12A detll'lli Md SP 1*R41c c1lcul1ted 1*R16 c1lcul1ted 1*R12A-c1lcul1ted 3.6E+07 2.1E+06 3. 2E+04< +btlU 7.2E+04<+titt>
 
1.51+04<+btt>
Salem ODCM           Rev. 7 r.ol* 2-2 P1r-t1f'I for G.11ous Al11'11 Setpoint D*t*l'llinattona untt-1 P*r-ter         Actl.Wl*       Oefeul t             units Vlll.W         V1lue
units ----------
    -------*       --------       --------         ----------
sec/m ft3/111in ftl/*ln unitl ..
X/Q           c1lcul1t1d       2.2E*06           sec/m              USNRC S1l111 S1fety Ev1luation, S~. 3 VF           1s me1sured     1.25E+05         ft3/111in          Pl 1nt Vint
* uCi/cllJ .,.91yr p1r uCi/113 mrwyr p1r uCf/113 wed/yr p1r uC I /113 ci:m p1r uCl/cllJ
* nonM l operet ion CPL1nt             or Vent)     f1n curves VF           1s ***ured       3.5E+04         ftl/*ln              conc.1..-,c purge (Cont.             or Purge)     f1n curves AF             coordiMted         0.25           unitl ..*          Adllnlltr1tlw 1l loe11tlon f1etor to with HCGS ensure cOIDinad r1l1u.. do not exclld rel1u1 r1t1 li*it for stt1.
* l*Hd on * .,. for c.l lbr1tlan with *txcure of redforu:lldes USNRC S1l111 S1fety Ev1luation, 3 Pl 1nt Vint
Ci             me1sured         N/A               uCi/cllJ ICI         nuclide 1p1eific   N/A         .,.91yr p1r uCi/113      V*lun frcm Tlbl* 2*1 Li         nuclide *P1Cific   N/A         mrwyr p1r uCf/113        V1lun fra11 Tlbl1 2-1 Mi           nuclide 1p1elflc   N/A         wed/yr p1r uC I /113      V1lun fra11 Tlbl1 2*1
* nonM l operet ion conc.1..-,c purge Adllnlltr1tlw 1l loe11tlon f1etor to with HCGS ensure cOIDinad r1l1u .. do not exclld rel1u1 r1t1 li*it for stt1. V*lun frcm Tlbl* 2*1 V1lun fra11 Tlbl1 2-1 V1lun fra11 Tlbl1 2*1 Plwit Vint Plwit Vint (rlCU!dlnU Cont1f ..-,t D1feult 1l1rm **tpolnt:
* SEN 1*R41C-1*R16 1*R12A SP 1*R41c 11 detll'lli Md c1lcul1ted 1.6E+07 3.6E+07 2.1E+06
mare conaarv1tiv1 v1lun my bl ua9d 11 de-.d 1i:ipropri1t1 Md deslrlbl*
: 3. 2E+04< +btlU ci:m p1r uCl/cllJ         Plwit Vint Plwit Vint (rlCU!dlnU Cont1f ..-,t D1feult 1l1rm **tpolnt: mare conaarv1tiv1 v1lun my bl ua9d 11 de-.d 1i:ipropri1t1 Md deslrlbl* for ..urtng rqul1tory c~ltmnce _..for .. 1nt1lntng r*l***..
for ..urtng rqul1tory
1*R16    c1lcul1ted    7.2E+04<+titt>                            ALMA.
_..for .. 1nt1lntng r*l*** .. ALMA. ** Appliclbl1 cU'lng MDDll 1 ttlr"'OUlll
1*R12A- c1lcul1ted      1.51+04<+btt>
: 5. During 111)1 6 (refUlltng), manltor ntpolnt shlill bl rlCM:ed to 2X in ICCOrdlnce with Tech Spec Tlbl* 3.3*6
* l*Hd on * .,. for c.l lbr1tlan with *txcure of redforu:lldes
  ** Appliclbl1 cU'lng MDDll 1 ttlr"'OUlll 5. During 111)1 6 (refUlltng), manltor ntpolnt shlill bl rlCM:ed to 2X bec:kgr~ in ICCOrdlnce with Tech Spec Tlbl* 3.3*6 *
* 41
* 41
* Salem ODCM Rev. 7 Table 2*3 Parameters for Gaseous Alarm Setpoint Detenainati(lnS Unit*2 Parameter ActUlll Default Units Conments Value Value ----------
 
*a*****************************************  
Salem ODCM               Rev. 7 Table 2*3 Parameters for Gaseous Alarm Setpoint Detenainati(lnS Unit*2 ActUlll         Default           Units                           Conments Parameter Value             Value
----------------X/Q calculated VF as measured (Plant or Vent) fan curves VF as measured (Cont. or Purge> fan curves AF coordinated Ci measured IC I nuclide specific Li nuclide specific Mi nuclide specific SEN 2*R41C* as detal'lli nect 2*R16 2*R12A SP 2*R41C calculatad 2*R16 calculated 2*R12A .. calculatad
  --------        --------          --------      ----------
--------2.2E*06 1.25E+OS 3.SE+04 0.25 N/A N/A N/A N/A 1.6E+07 3.SE+07 3.3E+07 3.2E+04(+bltg) 7.0E+04(+bkg) 2.4E+05(+bkg) sec/m3 ft3/min ft3/min 111i tless UCi/cm3 mrem/yr per UCl/1113 mrem/yr per UCl/m3 mrlld/yr per UCl/m3 C?ll per UCi/cm3 Licensing technical specification value Plant Vent
                                                                      *a*****************************************
* normal operation Containnent purge Acbinistrative allocation factor to with HCGS ensure conmined releases do not exceed release rnte limit for site. Values frOll Table 2-1 Values from Table 2*1 Values frOll Table 2*1 Plant Vent Plant Vent <redl.rdant>
calculated        2.2E*06        sec/m3                  Licensing technical specification value X/Q as measured       1.25E+OS      ft3/min                Plant Vent
Containnent Defeult alal'll 1etpoint1; 1110re conservative values *Y be used as deellled appropriate and desirable for ensuring regulatory arw:i for *intaining releases ALARA.
* normal operation VF (Plant               or Vent)           fan curves as measured       3.SE+04      ft3/min                  Containnent purge VF (Cont.               or Purge>         fan curves 0.25        111i tless              Acbinistrative allocation factor to with AF             coordinated                                               HCGS ensure conmined releases do not exceed release rnte limit for site.
* Bl!l!ed on man for c:alfbratfon  
Ci               measured           N/A          UCi/cm3 IC I         nuclide specific         N/A       mrem/yr per UCl/1113     Values frOll Table 2-1 Li          nuclide specific        N/A      mrem/yr per UCl/m3       Values from Table 2*1 N/A      mrlld/yr per UCl/m3       Values frOll Table 2*1
.,fth *fxture of radioru:lfdel  
* Mi          nuclide specific SEN 2*R41C*        as              1.6E+07      C?ll per UCi/cm3         Plant Vent detal'lli nect 2*R16                        3.SE+07                                Plant Vent <redl.rdant>
** Applicable during MODES 1 thraugh 5. During DE 6 (refueling), monitor setpoints shall be reduced to 2X backgr<Knl in ac:cot muca Jffth Tech Spec Tabla 3.3*6. 50
2*R12A                        3.3E+07                              Containnent calculatad        3.2E+04(+bltg)                        Defeult alal'll 1etpoint1; 1110re conservative SP 2*R41C                                                              values *Y be used as deellled appropriate and calculated        7.0E+04(+bkg)                        desirable for ensuring regulatory c~liance 2*R16                                                              arw:i for *intaining releases ALARA.
* Technic*l Specif i c*t ion *----*-------
2*R12A.. calculatad        2.4E+05(+bkg)
3.11.2.1*
* Bl!l!ed on man for c:alfbratfon .,fth *fxture of radioru:lfdel
3.11.2.1b 3.11.2.2 3.11.2.3 Salem ODCM Teble 2*4 Controlling LOClltiarw, Pethi.eys rd DISJ19rsion for Doe* CelC1Jlatiarw
  ** Applicable during MODES 1 thraugh 5. During DE 6 (refueling), monitor setpoints shall           be reduced to 2X backgr<Knl in ac:cot muca Jffth Tech Spec Tabla 3.3*6.
* Locetion Peth ... y(I) Controlling Age *********D***
50
a**************  
 
-----------
Salem ODCM         Rev. 7 Teble 2*4 Controlling LOClltiarw, Pethi.eys rd At~tc DISJ19rsion for Doe* CelC1Jlatiarw
lit* boundary noble pa .. N//A C0.83 *i le, II) direct exposure s i ,. boundary imalatlon child co.83 *i le, II) 1tte boundary 1-*alr II/A (0.83 *i le, II) beta*air rnidenee/datry  
* Atmspheric DISJ19rsion Technic*l Peth ...y(I)       Controlling
*ilk, grCU1d *infant (4.9 *il .. , W) plane and imalation Rev. 7 Atmspheric DISJ19rsion
                                                                            ----------------------
----------------------
X/Q            D/Q Specif i c*t ion      Locetion Age Gr~    (sec/"'1)      ( 1/m2)
X/Q D/Q (sec/"'1) ( 1/m2) ------*-2.2E-06 N//A 2.2&#xa3;-06 II/A 2.2&#xa3;-06 II/A 5.4E*OS 2. 1E*10
  *----*-------      *********D***         a**************
* The identified controll lacatt-, pathwys and dtapenlon are fl'Cll the safety Evaluation
                                                                ----------- ------*-
: Report, lo. 3 for the .. l* Muel*r Station, unit 2 (-EG-0517, Dec-.r 197!)
3.11.2.1*          lit* boundary         noble pa..               N//A  2.2E-06          N//A C0.83 *i le, II)       direct exposure 3.11.2.1b          s i ,. boundary         imalatlon             child   2.2&#xa3;-06          II/A co.83 *i le, II) 3.11.2.2          1tte boundary         1-*alr                   II/A  2.2&#xa3;-06          II/A (0.83 *i le, II)       beta*air 3.11.2.3          rnidenee/datry         *ilk, grCU1d           *infant 5.4E*OS        2. 1E*10 (4.9 *il .. , W)       plane and imalation
* The identified controll f~ lacatt-, pathwys and a~rtc dtapenlon are fl'Cll the safety Evaluation Report, S-l~ lo. 3 for the .. l
* Muel*r Gerwratl~ Station, unit 2 (-EG-0517, Dec-.r 197!) *
* 51
* 51
* where: MPC* c, MPC 1 Salem ODCM Rev. 7 E c 1 (qamaa emitter* only) (A. l) XPC =
 
* c 1 (qamaa) c, (non-qamma)
Salem ODCM     Rev. 7 E c 1 (qamaa emitter* only)
E -----------
XPC
+ ---------------
                  * = --------------~--------------
XPC 1 XPC 1 an effective MPC value for a mixture of radionuclide (uCi/ml)
c (qamaa)       c, (non-qamma)
* concentration of radionuclide i in the mixture -the 10 CFR 20, Appendix B, Table II, Column 2 MPC value for radionuclide i (uCi/ml) The equation for determininq the liquid effluent setpoints ( Section 1.2.l, equation 1.2 ) is based on a multiplication of the effective MPC times the monitor sensitivity.
(A. l) 1 E -----------
However, the radiation monitors on the effluent lines will not detect non-qamma emittinq radionuclides, such as H-3, Fe-55, and Sr-90. The derivation  
XPC    + ~ ---------------
*of the effective MPC ( Section 1.2.l, equation 1.3*) is valid for any distribution but must be modified to account for the fact that the effluent monitor will not detect the non-gammas.
XPC 1               1 where:
Th* above modified equation for the effective MPC provides for a default satpoint determination that accounts *for the non-gamma emitting radionuclide*
MPC*  ~  an effective MPC value for a mixture of radionuclide (uCi/ml) c,
* A-3 Salem ODCM Rev. 7 Table A*1 Calculation of Effective MPC Salem unit 1 Activity Released CCi) **-********a*******************************************
* concentration of radionuclide i in the mixture MPC 1  -   the 10 CFR 20, Appendix B, Table II, Column 2 MPC value for radionuclide i (uCi/ml)
Nuclide MPC
The equation for determininq the liquid effluent setpoints ( Section 1.2.l, equation 1.2 ) is based on a multiplication of the effective MPC times the monitor sensitivity. However, the radiation monitors on the effluent lines will not detect non-qamma emittinq radionuclides, such as H-3, Fe-55, and Sr-90. The derivation *of the effective MPC ( Section 1.2.l, equation 1.3*) is valid for any distribution but must be modified to account for the fact that the effluent monitor will not detect the non-gammas. Th* above modified equation for the effective MPC provides for a default satpoint determination that accounts *for the non-gamma emitting radionuclide* *
* 1988 1989 1990 TOTAL CuCi/ml> CURIES CURIES CURIES CURIES --------.............  
* A-3
----****-------------------Na*24 3E*05 1.38E*02 4.69E*04 1.69E*03 1.60E*02 Cr*51 2E*03 2.38E*02 5.25E*03 1.16E*02 4.06E*02 Mn*54 1E*04 1.01E*01 1.12E*01 1.52E*01 3.65E*01 Fe*59 5E*05 2.66E*04 1.32E*03 1.15E*03 2.73E*03 Co*57 4E*04 4.01E*03 6.11E*03 7.54E*03 1.m-02 Co*58 9E*05 1.27E+OO 1.82E+OO 1.98E+OO 5.07E+OO Co*60 3E*05 2.m-01 1.78E*01 2.39E*01 6.94E*01 Zr*95 6E*05 1.23E*02 1.53E*03 4.52E*03 1.84E*02 Nb*95 1E*04 1.53E*02 3.85E*03 9. 76E*03 2.89E*02 Nb*97 9E*04 2.44E*02 7.94E*05 6.30E*03 3.0SE*02 Tc*99m 3E*03 4.74E*03 4.62E*04 8.53E*04 6.05E*03 . Sr*89 3E*06 1.25E*02 1.54E*03 2.38E*03 1.64E*02 Sr*90 3E*07 2.40E*03 6.68E*04 4.66E*04 3.53E*03 Mo*99 4E*05 1.57E*03 N/D N/D 1.57E*03 Ag* 110m 3E*05 4.96E*D3 2.70E*03 8.40E*04 8.50E*03 Sn-113 SE*05 N/D N/D N/D N/D Sb*124 2E*05 6.32E*02 1.36E*02 1.94E*02 9.62E*02 Sb*125 1E*04 9.35E*02 6.53E*02 6.09E*02 2.20E*01 I* 131 3E*07 S.54E*02 3.04E*02 3.53E*02 1.21E*01
 
* I-133 1E*06 2.80E*02 6.88E*03 8.36E*03 4.32E*02 I *134 2E*5 1. 10E*02 N/D N/D 1.10E*02 I *135 4E*06 1.68E*02 1.94E*04 1.42E*04 1. 71E*02 Ce*144 1E*05 1.89E*02 1.19E*04 1.69E*04 1.92E*02 Cs*134 9E*06 1.31E*01 1.16E*01 1.91E*01 4.38E*01 Cs*136 6E*05 9.31E*05 9.79E*04 1.21E*03 2.28E*03 Cs*137 2E*05 1.34E*01 1.28E*01 2.02E*01 4.64E*01 Ba*140 2E*05 2.79E*04 N/D 1.10E*04 3.89E*04 La*140 2E*05 3.89E*04 2.66E*04 5.35E*04 1.19E*03 H*3 3E*03 6.34E+02 6.08E+02 3.53E+02 1.59E+03 Fe* SS 8E*04 5.40E*01 1. 75E*01 1.61E*01 8.76E*01 W*187 6E*05 1.25E*02 N/D N/D 1.25E*02 Zn*65 1E*04 5.49E*04 *3.62!*04 7.75E*03 8.66E-03 Zr*97 2E*OS 1.37E*02 N/D N/D 1.37E*02 Totel Ci G-2.33&#xa3;+00 2.49E+OO 2.94E+OO 7.77E+OO Total Cf Non*g-6.35E+02 6.0SE+OZ 3.53E+02 1.60E+03 MPCe (uCi/ml) 4.71E*06 6.88E*06 9.45E*06
Salem ODCM       Rev. 7 Table A*1 Calculation of Effective MPC Salem unit 1 Activity Released CCi)
* MPC value for er .. fre11 10 CFR 20, Appendix B, Table II, ColUll'I 2. ** N/D
                        **-********a*******************************************
Nuclide     MPC
* 1988         1989           1990       TOTAL CuCi/ml>         CURIES         CURIES         CURIES     CURIES
            --------     ............. ----****-       ---------     ---------
Na*24     3E*05         1.38E*02     4.69E*04       1.69E*03     1.60E*02 Cr*51     2E*03         2.38E*02     5.25E*03       1.16E*02     4.06E*02 Mn*54     1E*04       1.01E*01     1.12E*01       1.52E*01     3.65E*01 Fe*59     5E*05         2.66E*04     1.32E*03       1.15E*03     2.73E*03 Co*57     4E*04         4.01E*03     6.11E*03       7.54E*03     1.m-02 Co*58     9E*05         1.27E+OO     1.82E+OO       1.98E+OO     5.07E+OO Co*60     3E*05         2.m-01       1.78E*01       2.39E*01     6.94E*01 Zr*95     6E*05         1.23E*02     1.53E*03       4.52E*03     1.84E*02 Nb*95     1E*04         1.53E*02     3.85E*03       9. 76E*03   2.89E*02 Nb*97     9E*04         2.44E*02     7.94E*05       6.30E*03     3.0SE*02 Tc*99m   3E*03         4.74E*03     4.62E*04       8.53E*04     6.05E*03 .
Sr*89     3E*06         1.25E*02     1.54E*03       2.38E*03     1.64E*02 Sr*90     3E*07         2.40E*03     6.68E*04       4.66E*04     3.53E*03 Mo*99     4E*05         1.57E*03         N/D             N/D       1.57E*03 Ag* 110m   3E*05         4.96E*D3     2.70E*03       8.40E*04     8.50E*03 Sn-113   SE*05             N/D         N/D             N/D           N/D Sb*124   2E*05         6.32E*02     1.36E*02       1.94E*02     9.62E*02 Sb*125     1E*04         9.35E*02     6.53E*02       6.09E*02     2.20E*01 I* 131   3E*07         S.54E*02     3.04E*02       3.53E*02     1.21E*01
* I-133     1E*06         2.80E*02     6.88E*03       8.36E*03     4.32E*02 I *134   2E*5         1. 10E*02       N/D             N/D     1.10E*02 I *135   4E*06         1.68E*02     1.94E*04       1.42E*04     1. 71E*02 Ce*144     1E*05         1.89E*02     1.19E*04       1.69E*04     1.92E*02 Cs*134     9E*06         1.31E*01     1.16E*01       1.91E*01     4.38E*01 Cs*136     6E*05         9.31E*05     9.79E*04       1.21E*03     2.28E*03 Cs*137     2E*05         1.34E*01     1.28E*01       2.02E*01     4.64E*01 Ba*140     2E*05         2.79E*04         N/D         1.10E*04     3.89E*04 La*140     2E*05         3.89E*04     2.66E*04       5.35E*04     1.19E*03 H*3     3E*03         6.34E+02     6.08E+02       3.53E+02     1.59E+03 Fe* SS     8E*04         5.40E*01     1. 75E*01       1.61E*01     8.76E*01 W*187     6E*05         1.25E*02         N/D           N/D       1.25E*02 Zn*65     1E*04         5.49E*04     *3.62!*04       7.75E*03     8.66E-03 Zr*97     2E*OS         1.37E*02         N/D           N/D       1.37E*02 Totel Ci   G-           2.33&#xa3;+00     2.49E+OO       2.94E+OO     7.77E+OO Total Cf Non*g-         6.35E+02     6.0SE+OZ       3.53E+02     1.60E+03 MPCe (uCi/ml)           4.71E*06     6.88E*06       9.45E*06
* MPC value for ~trfcted er.. fre11 10 CFR 20, Appendix B, Table II, ColUll'I 2.
  ** N/D
* not detected
* not detected
* A-5
* A-5
*
 
* Salem ODCM Rev. Table A*2 Calculation of Effective MPC Salem Unit 2 Activity Released (Ci) --------------------------------------------------------
Salem ODCM           Rev. 7
* 1989 1990 Nuclide MPC 1988 TOTAL CUCi/ml) CURIES CURIES CURIES CURIES --------------------------------------------Na*24 3E-05 1.04E-02 8.0SE-04 2.28E-03 1.35E-02 Cr-51 2E-03 3. 17E-03 1 .57E-02 1 .48E-02 3.37E-02 Mn-54 1E-04 1. 74E-01 1. 19E-01 1 .52E-01 4.45E-01 Fe-59 SE-05 2.93E*05 3.00E-03 1 .09E-03 4. 12E-03 Co-57 4E-04 4.55E*03 6.70E*03 7.92E-03 1.92E*02 Co-58 9E-05 1.32E+OO 2.02E+OO 2.01E+OO 5.35E+OO Co-60 3E-05 2.97E-01 2.0SE-01 2.36E-01 7.41E-01 Zr-95 6E-05 3.15E*03 3.39E-03 5.22E-03 1.18E-02 Nb-95 1E*04 6.SSE-03 7.41E*03 1.03E*02 2.42E*02 Nb-97 9E-04 6.92E*03 2.54E*04 5.32E*04 7.71E-03 Tc-9911 3E*03 3.28E-03 6.64E*04 8.66C-04 4.81E-03 Sr-89 3E*06 . 1.69&#xa3;-02 1.52E-03 2.28E-03 2.07E-02 Sr-90 3E-07 4.11E-03 6.45E*04 4.73E-04 5.23E-03 Mo-99 4E-05 1.19E-04 N/D. N/D 1.19E-04 Ag-11(1111 3E-05 1.04E-02 6.41E-03 2.56E-03 1.94E*02 Sn-113 SE-05 N/D N/D N/D N/D Sb-124 2c-os 5.47E-02 1.89E-02 2.22e-02 9.58E-02 Sb-125 1E*04 9.22E*02 8.0SE-02 7.40E-02 2.47E-01 1-131 3E*07 1.35E*01 3.79E-02 3.83E*02 2.11E-01 1-133 1E-06 8.83E*02 8.64E-03 1.07E-02 1.0SE-01 1-134 2E-05 3.49&#xa3;-02 N/D N/D 3.49E-02 1-135 4E-06 1.90E*02 5.17E-04 7.09&#xa3;-04 2.02E*02 Ce-144 1E-05 2.24E-03 6.05E-04 7.67E-05 2.92E-03 Cs-134 9E-06 9.53E-02 1.43E*01 1.86E-01 . 4.24E*01 cs-136 6E-05 2.20E-03 1.39E-03 1.31E-03 4.90E-03 Cs-137 2E-05 1.09&#xa3;-01 1.55E*01 1.95E*01 4.59E-01 Ba-140 2E*05 1.57E-03 N/D N/D 1.57E-03 2E-05 1.03E*03 5.19E*04 6.23E*04 2.17E*03 H*3 3E*03 3.68E+02 5.02E+02 3.03E+02 1.17E+03 Fe* SS SE-04 4.69E*01 1.84E*01 2.09E*01 8.62E*01 W*187 6E*05 6.37E*04 N/D N/D 6.37E*04 Zn*65 1E*04 N/D 1.41E*04 1.06E*02 1.07E*02 Toul Ci G-2.48E+OO 2.84E+OO 2.98E+OO 8.30E+OO
* Table A*2 Calculation of Effective MPC Salem Unit 2 Activity Released (Ci)
* Total Cl Non*11-3.68E+02 5.02&#xa3;+02 3.03E+02 1.17E+03 MPCe (UCi /Ill) 3.381-06 7.85E*06 9.71E*06
MPC*
* MPC v*lue for WW"eStrtcted  
                            --------------------------------------------------------
*rn frm 10 CFR 20, Appendix a, Tele II, Coluiri 2. ** N/D
1988        1989             1990     TOTAL Nuclide CUCi/ml)     CURIES       CURIES         CURIES     CURIES Na*24
* not detected A-6 7 Salem ODCM Rev. 7 TABLB B-1 (Cont*d) STATION STATION LOCATION SAHPI.E TYPES 2F6 7.3 mi. NNE of vent; Southern 'i'raininq IOM Center 2F7 5.7 mi. NNE of vent; local farm MLK, VGT 3F2 5.1 mi. NE of vent; Hancocks Bridge IOM Municipal Building 3F3 8.6 mi. NE of vent; Quinton Township IOM School 5Fl 6.5 mi. E of vent F'PV,IOM 5F2 7.0 mi. E Of vent; local farm VGT 6Fl 6.4 mi. ESE of vent; Stow Neck Road IOM 7F2 9.1 mi. SE of vent; Bayside, NJ IOM 10F2 5.8 mi. SSW of vent IOM llFl 6.2 mi. SW of vent; Taylor's Bridge IOM Delaware 11F3 5.3 mi. SW of vent; Townsend, OE VGT 12Fl 9.4 mi. WSW of vent; Townsend Elem. IOM School 13F2 6.5 mi. W of vent; Od***a, DE IDM 13F3 9.3 mi. W of vent; Redding Middl* IDM School, Middletown, DE 13F4 9.8 :mi. W Of vent; Middletown, DE IDM 14Fl 5.5 mi. *WNW of vent; local farm VGT 14F2 6.6 ai. WNW Of vent; Boyd* Comar IDM 14F3 5.4 :mi. WNW of vent; local farm F'PV 14F4 7.6 mi. WNW of vent; local farm MLK 15F3 5.4 mi. NW of vent IDM
                    --------
3E-05
                                ---------
1.04E-02
                                              ---------
8.0SE-04
                                                              ---------
2.28E-03
                                                                          ---------
1.35E-02 Cr-51           2E-03         3. 17E-03     1.57E-02       1.48E-02   3.37E-02 Mn-54           1E-04         1. 74E-01     1. 19E-01       1.52E-01   4.45E-01 Fe-59           SE-05         2.93E*05     3.00E-03       1.09E-03   4. 12E-03 Co-57           4E-04         4.55E*03     6.70E*03       7.92E-03   1.92E*02 Co-58           9E-05         1.32E+OO     2.02E+OO       2.01E+OO   5.35E+OO Co-60           3E-05         2.97E-01     2.0SE-01       2.36E-01   7.41E-01 Zr-95           6E-05         3.15E*03     3.39E-03       5.22E-03   1.18E-02 Nb-95           1E*04         6.SSE-03     7.41E*03       1.03E*02   2.42E*02 Nb-97           9E-04         6.92E*03     2.54E*04       5.32E*04   7.71E-03 Tc-9911         3E*03         3.28E-03     6.64E*04       8.66C-04   4.81E-03 Sr-89           3E*06 .       1.69&#xa3;-02     1.52E-03       2.28E-03   2.07E-02 Sr-90           3E-07         4.11E-03     6.45E*04       4.73E-04   5.23E-03 Mo-99           4E-05         1.19E-04         N/D.           N/D     1.19E-04 Ag-11(1111     3E-05         1.04E-02     6.41E-03       2.56E-03   1.94E*02 Sn-113         SE-05           N/D         N/D               N/D         N/D Sb-124         2c-os         5.47E-02     1.89E-02       2.22e-02   9.58E-02 Sb-125         1E*04         9.22E*02     8.0SE-02       7.40E-02   2.47E-01 1-131           3E*07         1.35E*01     3.79E-02       3.83E*02   2.11E-01 1-133           1E-06         8.83E*02     8.64E-03       1.07E-02   1.0SE-01 1-134           2E-05         3.49&#xa3;-02         N/D             N/D     3.49E-02 1-135           4E-06         1.90E*02     5.17E-04       7.09&#xa3;-04   2.02E*02 Ce-144         1E-05         2.24E-03     6.05E-04       7.67E-05   2.92E-03 Cs-134         9E-06         9.53E-02     1.43E*01       1.86E-01 . 4.24E*01 cs-136         6E-05         2.20E-03     1.39E-03       1.31E-03   4.90E-03 Cs-137         2E-05         1.09&#xa3;-01     1.55E*01       1.95E*01   4.59E-01 Ba-140         2E*05         1.57E-03         N/D             N/D     1.57E-03 La~140          2E-05         1.03E*03     5.19E*04       6.23E*04   2.17E*03 H*3           3E*03         3.68E+02     5.02E+02       3.03E+02   1.17E+03 Fe* SS         SE-04         4.69E*01     1.84E*01       2.09E*01   8.62E*01 W*187           6E*05         6.37E*04         N/D             N/D     6.37E*04 Zn*65           1E*04             N/D       1.41E*04       1.06E*02   1.07E*02 Toul Ci         G-           2.48E+OO     2.84E+OO       2.98E+OO   8.30E+OO
* Total Cl     Non*11-         3.68E+02     5.02&#xa3;+02       3.03E+02   1.17E+03 MPCe (UCi /Ill)               3.381-06     7.85E*06       9.71E*06
* MPC v*lue for WW"eStrtcted *rn frm 10 CFR 20, Appendix a, Tele II, Coluiri 2.
    ** N/D
* not detected
* A-6
 
Salem ODCM   Rev. 7 TABLB B-1 (Cont*d)
STATION
    ~                    STATION LOCATION           SAHPI.E TYPES 2F6     7.3 mi. NNE of vent; Southern 'i'raininq       IOM Center 2F7     5.7 mi. NNE of vent; local farm               MLK, VGT 3F2     5.1 mi. NE of vent; Hancocks Bridge           IOM Municipal Building 3F3       8.6 mi. NE of vent; Quinton Township           IOM School 5Fl       6.5 mi. E of vent                             F'PV,IOM 5F2     7.0 mi. E Of vent; local farm                 VGT 6Fl     6.4 mi. ESE of vent; Stow Neck Road           IOM 7F2     9.1 mi. SE of vent; Bayside, NJ               IOM 10F2     5.8 mi. SSW of vent                           IOM llFl     6.2 mi. SW of vent; Taylor's Bridge           IOM Delaware 11F3     5.3 mi. SW of vent; Townsend, OE               MLK~  VGT 12Fl     9.4 mi. WSW of vent; Townsend Elem.           IOM School 13F2     6.5 mi. W of vent; Od***a, DE                 IDM 13F3     9.3 mi. W of vent; Redding Middl*             IDM School, Middletown, DE 13F4     9.8 :mi. W Of vent; Middletown, DE             IDM 14Fl     5.5 mi. *WNW of vent; local farm               VGT 14F2     6.6 ai. WNW Of vent; Boyd* Comar               IDM 14F3     5.4 :mi. WNW of vent; local farm               F'PV 14F4     7.6 mi. WNW of vent; local farm               MLK 15F3     5.4 mi. NW of vent                             IDM
* B-5}}
* B-5}}

Revision as of 10:10, 21 October 2019

Semiannual Radioactive Effluent Release Rept Jan-June 1992. W/920827 Ltr
ML18096A927
Person / Time
Site: Salem  PSEG icon.png
Issue date: 06/30/1992
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N92123, NUDOCS 9209020034
Download: ML18096A927 (86)


Text

l

  • Public Service Electric and Gas
  • Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations AUG 2 7 1992 NLR-N92123 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

RADIOACTIVE EFFLUENT RELEASE REPORT - 32 SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 In accordance with Section 6.9.1.11 of Appendix A to the Operating License for Salem Generating Station (SGS), Public Service Electric and Gas Company (PSE&G) hereby transmits one copy of the semi-annual Radioactive Effluent Release Report, RERR-32. This report summarizes liquid and gaseous releases and solid waste shipments from the Salem Generating Station for the period January 1 through June 30, 1992.

Should you have any questions regarding this transmittal, please feel free to contact us.

Sincerely, Attachment (1) 9209020034 920630 PDR ADOCK 05000272 R PDR IE'f8' I/ I

Document Control Desk 2

  • AUG 2 7 1992 NLR-N92123 RERR REPORT only c Mr. T. T. Martin, Administrator - Region I
u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager - Salem
u. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (S09)

USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SGS RERR-32 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 AUGUST,1992

SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1992 Table of Contents INTRODUCTION * * * * * * *

  • 0 * * * * * * * *
  • 1 PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 3 1.0 REGULATORY LIMITS . . . . . . * . * . . . * . . 3 1.1 Fission and Activation Gas Release Limits 3 1.2 Iodine Particulates, and Tritium . . . *
  • 3 1.3 Liquid Effluents Release Limits . . . . . . . 4 1.4 Total Dose Limit . . . . . * * * . * . . . . . 4 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) . . . 4 3.0 AVERAGE ENERGY . . . . . . . . * . . . 5 4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY . . . . * . . . * * . . . .
  • 5 5.0 BATCH RELEASES . . . . * . . * . . * . 7 6.0 UNPLANNED RELEASES . . . . . * . . . . . . 7 7.0 ELEVATED RADIATION MONITOR RESPONSES . . . * . 7 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS . . . . . . .
  • 7
  • PART B. GASEOUS EFFLUENTS 7 PART c. LIQUID EFFLUENTS 8 PART D. SOLID WASTE . . . 8 PART E. RADIOLOGICAL IMPACT ON MAN . . * * * . *
  • 8 Liquid Pathways . . . . . 8 Air Pathways . * * . * . .
  • 0
  • Q 9 Direct Radiation * * . * . . . . . . * * *
  • e 9 Total Dose . . . . . . . . . * . . * * * *
  • 10 Dose to Members of the Public on Site 0 * * *
  • 10 Assessment . . . . . . . * * * . 11 PART F. METEOROLOGICAL DATA. .
  • 12 PART G. ODCM CHANGES . . . 12 PART H. INOPERABLE MONITORS * . . . . * . 12 PART I . ENVIRONMENTAL MONITORING LOCATION CHANGES . * . . . 12
  • SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1992
INTRODUCTION This report, SGS-RERR-32, summarizes information pertaining to the releases of radioactive materials in liquid, gaseous and solid form from the Salem Generating Station {SGS) Units 1 and 2 for the period January 1, 1992 to June 30 ,* 1992.

This Semiannual RERR is submitted for both Salem Units and combines those sections which are common to each unit. Separate tables of releases and release totals are included whenever separate processing systems exist.

Salem Unit 1 is a Westinghouse Pressurized Water Reactor which has a licensed core power of 3411 MWt and an approximate net electrical output of 1115 MWe. Salem Unit 1 achieved initial criticality on December 11, 1976. and went into commercial operations on June 30, 1977.

Salem Unit 2 is a Westinghouse Pressurized Water Reactor which has a licensed core power of 3411 MWt and an approximate net electrical output of 1115 MWe. Salem Unit 2 achieved initial cri~icality on August 2, 1980 and went into commercial operations on October 13, 1981.

The report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Specification 6.9.1.11 of the Salem Technical Specifications. Preceding the tables summarizing the gaseous and liquid discharges and solid waste shipments are our responses to parts A-F of the "Supplemental Information" section of Regulatory Guide 1.21, Appendix B.

As required by Regulatory Guide 1.21, our Technical Specification limits are described in detail within this report along with a summary description of how measurements and determinations of the total activity discharged were developed.

1

To facilitate determination. of compliance with 40CFR190 requirements, the following information on electrical output is provided.

Unit 1 generated 2 1 305 1 872 megawatt-hours of electrical energy (net) during the reporting period.

Unit 2 generated 409,726 megawatt-hours of electrical energy (net) during the reporting period.

Results of liquid and gaseous composites analyzed for sr-89, Sr-90 and Fe-55 for the second quarter of 1992 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 half of 1991 (refer to RERR-31) have been completed; amended pages to RERR-31 are included in this report .

  • 2

PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LXMXTS 1.1 Fission and Activation Gas 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 limit.ad 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 *

  • 3

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 10 CFR, 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 milliliter.

In addition, the dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited:

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 apy calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

1.4 Total Dose Limit 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 MPCs 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. The MPC value used for dissolved or entrained noble gases is 2E-4 microcuries per milliliter .
  • 4

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 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 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 require these tanks to be uniformly mixed for sampling and analysis before being released. Batch releases are defined as releases from the waste monitor hold-up tank and the chemical and volume control tanks. Continuous liquid releases are defined as condensate releases from intermittent blowdown of the steam generators. Specific activities 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 Effluents 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 multi-channel 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. Radionuclides measured at concentrations below the Technical Specification detection limits

(LLDs) are treated as being present. Radionuclides for 5

which no activity was detected, while meeting the required LLDs, are treated as absent.

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 through 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 gaseous 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 radiation monitoring system readings while the channel is in an alarm state are treated as batch mode releases. If specific activity data from grab samples taken is not available, then the abnormal release is quantified by the use of the plant vent radiation monitors. The monitor's response is converted to a "specific activity" using historical efficiency factors. The i*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 Estimated Total Error The estimated total error of reported liquid and solid releases is within 25%

The estimated total error of the reported continuous gaseous releases is within 50% when concentrations exceed detectable levels. This error is due primarily to variability of waste stream flow rates and changes in isotopic distributions of waste streams between sampling periods. The estimated total error 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.

6

S.O BATCH RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A-1 and 4B-1 for Unit 1 and 4A-2 and 4B-2 for Unit 2.

6.0 UNPLANNED RELEASES During this reporting period there was no unplanned releases.

7.0 ELEVATED R-16/R41C CHANNEL RESPONSES During this reporting period, their were no elevated

  • 8.0 monitors readings on R16/R41C.

MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS our last report (RERR-31) did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the fourth quarter of 1991. Amended pages to RERR-31 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-1 thru 2C for Salem Unit 1 Operations.

See Summary Tables 2A-2 thru 2C for Salem Unit 2 Operations.

7

l' PART D. SOLID WASTE See Summary in Table 3.

PART E. RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on actual locations of nearby residents and farms. The population dose impact is based on historical site specific data i.e., food production, milk production, feed for milk animals and seafood production.

The doses were calculated using methods described in Regulatory Guide 1.109 and represent calculations for the six month reporting interval. Individual doses from batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as described in the Offsite Dose Calculation Manual.

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

Liquid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathway. Calculated doses to individuals are as shown below:

Total body dose to an individual: 4.06E-Ol mrem Highest organ dose: 2.82E+OO mrem to the GI-LLI.

Dose to the 6 million individuals living within the 50 mile radius of the plant site:

Total population dose: 8.SOE-02 person-rem Average population dose: l.47E-05 mrem/person 8

Air Pathways The calculated doses to individuals via the air pathway are shown below:

Total body dose: 1.62E-02 mrem Skin dose: l.SOE-02 mrem Highest organ dose due to radioiodines and particulates with half lives greater than 8 days:

9.llE-03 mrem to the Thyroid.

Dose to the 6 million individuals living within the 50 mile radius of the plant site:

Total population dose: 2.44E-Ol person-rem Average population dose: 4.09E-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, as well as natural background radiation.

TLD data for the six month reporting period is given below:

TLD Location Measurement 2S-2 0.3 mile 5.7 mrad/month 5S-1 0.9 mile 4.9 mrad/month These values are intepreted to represent natural background, since they are within the statistical variation associated with the pre-operational program results, which are: 3.7 mrad/month for location 2s-2, and 4.2 mrad/month for location 5S-1.

9 L

  • Total Dose 40CFR190 limits the total dose to members of the public due to radioactivity and radiation from uranium fuel cycle sources to:

<25 mrem total body or any organ

<75 mrem to the thyroid for a calendar year. For Artificial Island, the major sources of dose are from liquid and gaseous effluents from the Salem and.Hope Creek plants.

The following doses to members of the public have been calculated for the six month reporting period:

0.778 mrem total body 2.930 mrem organ (GI-LLI) 0.179 mrem thyroid Dose to Members of the Public Due to Activities inside the Site Boundary.

In accordance with the requirements of Technical Specification 6.9.1.7, the dose to members of the public inside the site boundary has been calculated based on the following assumptions:

  • Such persons are participating or spectators in local softball league
  • 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per week on site
  • Dose due to airborne pathway(inhalation and immersion)
  • persons are located about 3/4 mile east of plant discharge points {baseball fields)
  • occupancy coincides with batch gaseous discharges For the six month reporting period, the calculated doses are:

6.61E-05 mrem Total Body 6.96E-05 mrem Organ 6.61E-05 mrem Thyroid

  • 10

Assessment Gaseous effluents continue to be low and are predominately xenon-133. Calculated doses are low, due to the dose factor of xenon-133.

Liquid effluents increased slightly from previous reporting periods. Calculated doses are due principally to isotopes of iron, cobalt ,

and cesium.

The following two trend graphs show gaseous and liquid effluents and calculated doses from combined Salem 1 and 2 for the previous five years.

Salem Unit.a 1 and 2 Liquid Effluenta Curles Released and Calculated Doses 10 c

u

--TB m

    • r ---o-- ORGAN
  • m ----CURIES 0.1 0

0,01

....

00 ~ ~ ~  ;;;

~ ~ ~ ~ ~

Reportinf Perioll Salem Unit 1 and 2 Gaseous Efftuenta Noble Gas Curles Released and Calculated Dose 1.00E+04 ~

1.00£+03 --............_ _.

c 1.00E+02

~

u

~TB

.m 1.00£+01 r

I r 1.00E+OO -X-SKIN

  • m 1.ooe-01 x--! x-x-x--:a:.... _.,,. _.,,_

-"' ----CURIES 1.ooe-02 ~

0 1.00£-03 r

1.00£-04 1.00E-05

....

00 ~ 113 a::~ c;; ""

°'

~ ~ ~ ~ ~

Reporting Period 11

PART F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for the first and second quarters of 1992 in Tables 5 and 6.

PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES During this period, there were was a revision to the SGS ODCM. Revision 7 was approved on 1/16/92, a summary of the revision along with the pages that were changed is included in an addendum to this report.

PART H. INOPERABLE MONITORS During this period, the following effluent monitors were inoperable for more than 30 days

  • Unit 2 Plant Vent Noble Gas Monitor (2R41C)
  • Unit 2 Chemical Waste Basin Process Monitor (2R37)

( 2 Rl 9 A, B , C , D)

These monitors could not be returned to operating status within the 30 day time period due to a forced shutdown on Unit 2 and Design Change work being performed on the monitors.

  • Unit 2 Plant Vent Noble Gas Monitor (2R41C) - Monitor was inoperable for more than 30 days due to design change work being performed on the monitor (DCP 2EC-3086). Work included a primary calibration of the detector and the replacement of electronic components.

Unit 2 Chemical Waste Basin Process Monitor (2R37) -

Monitor could not be returned within the 30 day time period due to replacement 'of the detector following extensive troubleshooting and decontamination of the detector housing. The work on this monitor was further delayed due to a malfunctioning check valve in the sample line to the detector.

Unit 2 Steam Generator Blowdown Process Monitors (2R19 A,B,C,D). - Monitors could not be returned within 30 days due to design work on the detector (2EC-3086) and a forced outage which limited flow to the detectors.

12

PART J. ENVIRONMEN'l'AL MONITORING LOCATION CHANGES During the reporting period, there was one change to the environmental monitoring sampling locations. Farm 14F4 was added to the Environmental Monitoring Program

  • due to a neighboring Farm (14Fl) ceasing dairy operations *
  • 13

SALEM GENERATING STATION TABLE lA-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 UNIT 1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est.

1st 2nd Total Units Quarter Quarter Error %

A. Fission and Activation Gases

1. Total release Ci 1.89E+02 1.57E+02 25
2. Average release rate for period uCi/sec 2.41E+Ol 1.99E+Ol
3. Percent of technical specification limit (T.S. 3.ll.2.2(a))  % 1.40E-Ol 1.17E-Ol B. Iodines
1. Total Iodine-131 Ci 1.72E-05 2.29E-04 25
2. Average release rate for period uCi/sec 2.19E-06 2.92E-05
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))  % 1.49E-03 1.13E-02

c. Particulates
1. Particulates with half-lives >8 days Ci 3.40E~06 6.79E-06 25
2. Average release rate for period uCi/sec 4.33E-07 8.63E-07
3. Percent of technical specification limit (2)

(T.S. 3.ll.2.3(a))  % 1.49E-03 1.13E-02

4. Gross alpha Ci O.OOE+OO O.OOE+OO
c. Tritium
1. Total Release Ci 2.52E+Ol 1.99E+Ol 25
2. Average release rate for period uCi/sec 3.20E+OO 2.54E+OO
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))  % 1.49E-03 1.13E-02 (1) For batch releases the estimated overall error is within 10%

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

  • 14

SALEM GENERATING STATION TABLE lA-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 UNIT 2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est.

1st 2nd Total Units Quarter Quarter Error %

A. Fission and Activation Gases

1. Total release Ci 6.86E-Ol 1.78E+Ol 25
2. Average release rate for period uCi/sec 8.73E-02 2.26E+OO
3. Percent of technical specification limit (T.S. 3.11.2.2(a))  % 5.lSE-04 1.38E-02 B. Iodines
1. Total iodine-131 Ci O.OOE+OO 1.llE-05 25
2. Average release rate for period uci/sec O.OOE+OO 1.41E-06
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))  % 7.lOE-04 1.21E-03

c. Particulates
1. Particulates with half-lives >8 days Ci 5.76E-06 1.13E-05 25
2. Average release rate for period uCi/sec 7.33E-07 1.43E-06
3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))  % 7.lOE-04 1.21E-03

4. Gross alpha Ci O.OOE+OO O.OOE+OO
c. Tritium
1. Total Release Ci 2.57E+Ol 2.54E+Ol 25
2. Average release rate for period uCi/sec 3.27E+OO 3.22E+OO
3. Percent of technical specification limit (2)

(T.S. 3.11.2.J(a))  % 7.lOE-04 1.21E-03 (1) For batch releases the estimated overall error is within 10%

(2) Iodine, tritium and particulates are treated as a group 15

  • SALEM GENERATING STATION TABLE lB-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 1 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter

' 1. Fission Gases Krypton-85 Ci O.OOE+OO O.OOE+OO 5.38E-01 1.02E+OO Krypton-85m Ci O.OOE+OO O.OOE+OO 1.57E-02 1.65E-02 Xenon-131m Ci O.OOE+OO O.OOE+OO 1.82E-01 5.48E-01 Xenon-133 Ci 1. 76E+02 9.55E+01 1.10E+01 5.74E+01 Xenon-133m Ci O.OOE+OO O.OOE+OO 1.10E-01 7.13E-01 Xenon-135 Ci 9.14E-01 O.OOE+OO 1.42E-01 1.63E+OO Argon-41 Ci O.OOE+OO O.OOE+OO 2.41E-02 O.OOE+OO Krypton-87 Ci O.OOE+OO O.OOE+OO 3.57E-03 O.OOE+OO Krypton-88 Ci O.OOE+OO O.OOE+OO 1.88E-02 5.78E-03 TOTALS Ci 1.77E+02 9.55E+01 1.20E+01 6.13E+01

2. Iodines Iodine-131 Ci 1. 72E-05 2.29E-04 O.OOE+OO O.OOE+OO TOTALS Ci 1.72E-05 2.29E-04 O.OOE+OO O.OOE+OO
3. Particulates (half-live >8 days Cobalt-58 Ci O.OOE+OO 4.88E-06 O.OOE+OO O.OOE+OO Cobalt-60 Ci 3.40E-06 1.45E-06 O.OOE+OO O.OOE+OO Cesium-137 Ci O.OOE+OO 4.55E-07 O.OOE+OO O.OOE+OO TOTALS Ci 3.40E-06 6.79E-06 O.OOE+OO O.OOE+OO 16

SALEM GENERATING STATION TABLE 1B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 2 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission Gases Krypton-85 Ci O.OOE+OO O.OOE+OO 2.45E-02 1.94E-Ol Krypton-85m Ci O.OOE+OO O.OOE+OO O.OOE+OO 8.19E-03 Krypton-88 Ci O.OOE+OO O.OOE+OO O.OOE+OO 2.27E-03 Xenon-131m Ci O.OOE+OO O.OOE+OO 8.07E-04 6.76E-02 Xenon-133 Ci O.OOE+OO l.05E+Ol 6.61E-Ol 6.35E+OO Xenon-133m Ci O.OOE+OO O.OOE+OO O.OOE+OO 9.36E-02 Xenon-135 Ci O.OOE+OO 4.0lE-02 O.OOE+OO 5.44E-Ol TOTALS Ci O.OOE+OO 1.0SE+Ol 6.86E-Ol 7.26E+OO
2. Iodines Iodine-131 Ci O.OOE+OO 1. llE-05 O.OOE+OO O.OOE+OO TOTALS Ci O.OOE+OO 1.11E-05 O.OOE+OO O.OOE+OO
3. Particulates (half-live >8 days Cobalt-58 Ci O.OOE+OO 8.54E-06 O.OOE+OO O.OOE+OO Cobalt-60 Ci 5.76E-06 2.73E-06 O.OOE+OO O.OOE+OO TOTALS Ci 5.76E-06 l.13E-05 O.OOE+OO O.OOE+OO
  • 17

SALEM GENERATING STATION TABLE lC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY - JUNE 1992 UNITS 1 AND 2 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter There were no ground level gaseous releases during this reporting period .

  • 18
  • SALEM GENERATING STATION TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY - JUNE 1992 UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.

1st 2nd Total Units Quarter Quarter Error %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 1. 05E+O.O l.14E+OO 25
2. Average diluted concentration during period uCi/mL 2.02E-07 2.94E-07
3. Percent of technical specification limit (T.S. 3.11.1.2. (a))  % 1. 02E+Ol 1.70E+Ol B. Tritium
1. Total release Ci 7.44E+Ol 4.16E+Ol 25
2. Average diluted concentration during period uCi/mL 1.42E-05 1.07E-05
3. Percent of technical specification limit

{T.S. 3.11.1~1)  % 4.75E-Ol 3.56E-Ol

c. Dissolved and entrained noble gases
1. Total release Ci 4.57E-Ol 1.61E-02 25
2. Average diluted concentration during period uCi/mL 8.75E-08 4.15E-09
3. Percent of technical specification limit (T. S. 3.11.1.1)  % 4.38E-02 2.07E-03 D. Gross alpha activity
1. Total release Ci O.OOE+OO O.OOE+OO E. Volume of waste release (prior to dilution -

Batch Release) liters 2.26E+06 1.85E+06 F. Volume of dilution.water used during entire period liters 4.88E+ll 3.98E+10 19

SALEM GENERATING STATION TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.

1st 2nd Total Units Quarter Quarter Error %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 8.40E-Ol 1.46E+OO 25
2. Average diluted concentration during period uCi/mL 2.53E-07 2.96E-07
3. Percent of technical specification limit (T.S. 3.11.1.2. (a))  % 1.15E+Ol 1.77E+Ol B. Tritium
1. Total release Ci 5.89E+01 5.81E+01 25
2. Average diluted concentration during period uCi/mL 1.77E-05 1.18E-05
3. Percent of technical specification limit (T.S. 3.11.1.1)  % 5.91E-Ol 3.94E-Ol
c. Dissolved and entrained noble gases
1. Total release Ci 4.46E-Ol 4.70E-02 25
2. Average diluted concentration during period uCi/mL 1.34E-07 9.55E-09
3. Percent of technical specification limit (T.S. 3.11.1.1)  % 6.71E-02 4.78E-03 D. Gross alpha activity
1. Total release Ci O.OOE+OO O.OOE+OO E. Volume of waste release (prior to dilution -

Batch Release) liters 1.77E+06 1.93E+06

  • F. Volume of dilution water used during entire period liters 1.13E+10 2.91E+11 20

... ---* _..._ ,;mu SALEM GENERATING STATION TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 LIQUID EFFLUENTS UNIT 1 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter Sodium-24 Ci O.OOE+OO O.OOE+OO 2.58E-05 O.OOE+OO Chromium-51 Ci O.OOE+OO O.OOE+OO 1.20E-03 2.71E-03 Manganese-54 Ci O.OOE+OO O.OOE+OO 1.29E-02 4.15E-02 Iron-55 Ci O.OOE+OO O.OOE+OO 8.57E-03 O.OOE+OO Iron-59 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.20E-04 Cobalt-57 Ci O.OOE+OO O.OOE+OO 3.76E-03 4.19E-03 Cobalt-58 Ci O.OOE+OO 5.75E-05 8.32E-01 8.60E-01 Cobalt-60 Ci O.OOE+OO 2.27E-05 6.17E-02 8.54E-02 Zinc-65 Ci O.OOE+OO O.OOE+OO 8.04E-04 4.83E-05 strontium-89 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE-00 Strontium-90 Ci O.OOE+OO O.OOE+OO 7.44E-05 O.OOE-00 Niobium-95 Ci O.OOE+OO O.OOE+OO 2.83E-03 2.50E-03 Zirconium-95 Ci O.OOE+OO O.OOE+OO 1.36E-03 1.22E-03 Niobium-97 Ci O.OOE+OO O.OOE+OO 9.94E-05 1.17E-07 Technetium-99m Ci O.OOE+OO O.OOE+OO O.OOE+OO 3.18E-08 Silver-11om Ci O.OOE+OO O.OOE+OO 7.16E-05 6.73E-03 Antimony-122 Ci O.OOE+OO O.OOE+OO 4.60E-05 3.94E-05 Antimony-124 Ci O.OOE+OO O.OOE+OO 2.55E-03 6.99E-03 Antimony-125 Ci O.OOE+OO O.OOE+OO 1.25E-02 4.00E-02 Iodine-131 Ci O.OOE+OO O.OOE+OO 4.98E-03 1.33E-02 Iodine-133 Ci O.OOE+OO O.OOE+OO 5.47E-05 4.19E-04 Cesium-134 Ci O.OOE+OO O.OOE+OO 5.0SE-02 3.76E-02 Cesium-136 Ci O.OOE+OO O.OOE+OO 3.44E~04 6.62E-04 Cesium-137 Ci O.OOE+OO O.OOE+OO 5.77E-02 3.96E-02 Lanthanum-140 Ci O.OOE+OO O.OOE+OO O.OOE+OO "2.21E-05 Cerium-141 Ci O.OOE+OO O.OOE+OO O.OOE+OO 3.69E-05 Tin-113 Ci O.OOE+OO O.OOE+OO 6.27E-05 3.28E-04 Ruthenium"."'105 Ci O.OOE+OO O.OOE+OO O.OOE+OO 3.22E-04 TOTALS O.OOE+OO 8.02E-05 1. 05E+OO 1.14E+OO

  • 21

TABLE 2B-1 (CONT)

Tritium Ci O.OOE+OO O.OOE+OO 7.44E+Ol 4.16E+Ol Xenon-133m Ci O.OOE+OO O.OOE+OO 3.00E-03 O.OOE+OO Xenon-133 Ci O.OOE+OO O.OOE+OO 4.44E-Ol 1.60E-02 Xenon-135 Ci O.OOE+OO O.OOE+OO 2.llE-03 1.02E-04 Xenon-131m Ci O.OOE+OO O.OOE+OO 7.67E-03 O.OOE+OO TOTALS O.OOE+OO O.OOE+OO 7.48E+Ol 4.16E+Ol 22

SALEM GENERATING STATION TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter Sodium-24 Ci O.OOE+OO O.OOE+OO 0 .* OOE+OO 4.43E-OS Chromium-S1 Ci O.OOE+OO O.OOE+OO 6.89E-04 2.SSE-03 Manganese-S4 Ci O.OOE+OO O.OOE+OO 1.19E-02 S.9SE-02 Iron-SS Ci O.OOE+OO O.OOE+OO 1.10E-02 O.OOE+OO Iron-S9 Ci O.OOE+OO O.OOE+OO 4.82E-OS 1.13E-04 Cobalt-S7 Ci O.OOE+OO O.OOE+OO 2.87E-03 S.1SE-03 Cobalt-SS Ci O.OOE+OO O.OOE+OO 6.S6E-01 1.lOE+OO Cobalt-60 Ci O.OOE+OO O.OOE+OO 4.20E-02 9.30E-02 Zinc-6S Ci O.OOE+OO O.OOE+OO 1.23E-03 9.3SE-OS Strontium-89 Ci O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE.+00 strontium-90 Ci O.OOE+OO O.OOE+OO 6.91E-OS O.OOE+OO Niobium-9S Ci O.OOE+OO O.OOE+OO 1.17E-03 1. 84E-03 Zirconium-9S Ci O.OOE+OO O.OOE+OO 4.SOE-04 S.23E-04 Niobium-97 Ci O.OOE+OO *o. OOE+OO 6.88E-OS 3.39E-04 Technetium-99m Ci O.OOE+OO O.OOE+OO 3.90E-OS O.OOE+OO Ruthenium-lOS Ci O.OOE+OO O.OOE+OO O.OOE+OO 9.07E-OS Silver-110m *ci O.OOE+OO O.OOE+OO 3.87E-OS 4.32E-03 Antimony-122 Ci O.OOE+OO O.OOE+OO O.OOE+OO S.29E-OS Antimony-124 Ci O*.OOE+OO O.OOE+OO 3.0SE-03 6.SSE-03 Antimony-12S Ci O.OOE+OO O.OOE+OO 1.21E-02 4.86E-02 Iodine-131 *ci O.OOE+OO O.OOE+OO 7.48E-03 1.26E-02 Cesium-134 Ci O.OOE+OO O.OOE+OO 4.04E-02 7.2SE-02 Cesium-136 Ci O.OOE+OO O.OOE+OO 2.00E-04 1.12E-03 Cesium-137 Ci O.OOE+OO O.OOE+OO 4.84E-02 4.46E-02 Lanthanum-140 Ci O.OOE+OO O.OOE+OO 2.03E-OS 2.17E-OS Barium-140 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.14E-04 Tin-113 Ci O.OOE+OO O.OOE+OO O.OOE+OO 8.S1E-OS TOTALS O.OOE+OO O.OOE+OO 8.40E-01 1.46E+OO 23

TABLE 2B-2 (CONT)

Tritium Ci O.OOE+OO O.OOE+OO 5.89E+Ol 5.81E+Ol Xenon-131m Ci O.OOE+OO O.OOE+OO 2.85E-03 0.00E+OO Xenon-133m Ci O.OOE+OO O.OOE+OO 8.90E-04 O.OOE+OO Xenon-133 Ci O.OOE+OO O.OOE+OO 4.41E-Ol 4.64E-02 Xenon-135 Ci O.OOE+OO O.OOE+OO 7.48E-04 5.75E-04 TOTALS O.OOE+OO O.OOE+OO 5.93E+Ol 5.82E+Ol

  • 24

SALEM GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Est. Total

1. Type of waste Units (1) period Error, %
a. Spent resins, filters, m3 1.70E+Ol sludges, evaporator bottoms Ci 6.88E+02 25
b. Dry compressible waste, m3 3.44E+Ol contaminated equipment. Ci 3.53E+OO 25
c. Irradiated components, m3 O.OOE+OO control rods Ci a*. OOE+OO 25
d. Others (described) m3 O.OOE+OO
  • oil Ci O.OOE+OO 25
2. Estimate of major nuclide composition (for Type A and B waste)

Resins DAW

(%) (Ci) (%) (Ci)

Iron-55 7.1 4.89E+Ol 52.2 l.84E+OO Manganese-54 1.5 1. 03E+Ol 1.7 6.00E-02 Cobalt-58 64.2 4.42E+02 19.8 7.00E-01 Cobalt-GO 8.5 5.85E+Ol 12.0 4.20E-Ol Nickel-63 8.0 5.51E+Ol 7.9 2.80E-Ol Cesium-134 5.4 3.72E+Ol 1.4 5.00E-02 Cesium-137 4.9 3.37E+Ol 1.9 7.00E-02 (1) Volumes are measured, activities are estimated

  • 25

SALEM GENERATING STATION TABLE 3

{CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY - JUNE 1992 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition Number of Mode of Type of Shipments Transportation Destination Containers 16 Truck Barnwell, SC Strong, tight containers 5 Truck Barnwell, SC HIC
4. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Mode of Shipments Transportation Destination None N/A N/A 26

SALEM GENERATING STATION TABLE 4A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY - JUNE 1992

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY Dates: January 1 - March 30, 1992

2. Type of release: Gas
3. Number of releases during the 1st Quarter: 13
4. Total time duration for all releases of type listed above:

1.09E+03 minutes

s. Maximum duration for release of type listed above:

1.96E+02 minutes

6. Average duration for release of type listed above:

8.38E+Ol minutes

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

5.90E+Ol minutes

8. Average stream flow (dilution flow) during the period of release: N/A 27

SALEM GENERATING STATION TABLE 4A-1 (CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992

SUMMARY

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

1. Dates: April 1 - June 30, 1992
2. Type of release: Gas
3. Number of releases during the 2nd Quarter: 22
4. Total time duration for all releases of type listed above:

3.23E+04 minutes

5. Maximum duration for release of type listed above:

l.05E+04 minutes

6. Average duration for release of type listed above:

1.47E+03 minutes

7. Minimum durati9n for release of type listed above:

4.40E+Ol minutes

8. Average stream flow (dilution flow) during the period of release: N/A 28
  • SALEM GENERATING STATION TABLE 4A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY - JUNE 1992

SUMMARY

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

1. Dates: January 1 - March 30, 1992
2. Type of release: Gas
3. Number of releases during the 1st Quarter: 13
4. Total time duration for all releases of type listed above:

1.38E+04 minutes

5. Maximum duration for release of type listed above:

3.71E+03 minutes

  • 6* Average duration for release of type listed above:

1.06E+03 minutes

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

1.00E+OO minutes

8. Average stream flow (dilution flow) during the period of release: N/A 29

SALEM GENERATING STATION TABLE 4A-2 (CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992

SUMMARY

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

1. Dates: April 1 - June 30, 1992
2. Type of release: Gas
3. Number of releases during the 2nd Quarter: 30
4. Total time duration for all releases of type listed above:

5.44E+03 minutes

5. Maximum duration for release of type listed above:

1.35E+03 minutes

6. Average duration for release of type listed above:

1.81E+02 minutes

7. Minimum duration for release of type listed above:

3.00E+Ol minutes

8. Average stream flow (dilution flow) during the period of release: N/A 30

SALEM GENERATING STATION TABLE 4B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992

SUMMARY

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

1. Dates: January 1 - March 30, 1992
2. Type of release: Liquid
3. Number of releases during the 3rd Quarter: 36
4. Total time duration for all releases of type listed above:

8.57E+03 minutes

5. Maximum duration for release of type listed above:

3.35E+02 minutes

6. Average duration for release of type listed above:

2.38E+02 minutes

7. Minimum duration for release of type listed above:

1.86E+02 minutes

8. Average stream flow (dilution flow) during the period of release: 1.61E+05 gpm 31

SALEM GENERATING STATION TABLE 4B-1

{CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992

SUMMARY

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

1. Dates: April 1 - June 30, 1992
2. Type of release: Liquid
3. Number of releases during the 2nd Quarter: 28
4. Total time duration for all releases of type listed above:

7.73E+03 minutes

5. Maximum duration for release of type listed above:

6.48E+02 minutes

6. Average duration for release of type listed above:

2.76E+02 minutes

7. Minimum duration for release of type listed above:

2.12E+02 minutes

8. Average stream flow {dilution flow) during the period of release: 1.33E+05 gpm 32

SALEM GENERATING STATION TABLE 4B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1992

SUMMARY

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

1. Dates: January 1 - March 30, 1992
2. Type of release: Liquid
3. Number of releases during the 3rd Quarter: 28
4. Total time duration for all releases of type listed above:

6.42E+03 minutes

5. Maximum duration for release of type listed above:

3.29E+02 minutes

6. Average duration for release of type listed above:

2.29E+02 minutes

7. Minimum duration for release of type listed above:

1.74E+02 minutes

8. Average stream flow (dilution flow) during the period of release: l.37E+05 gpm 33

SALEM GENERATING STATION TABLE 4B-2 (CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANAURY - JUNE 1992

SUMMARY

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

1. Dates: April 1 - June 30, 1992
2. Type of release: Liquid
3. Number of releases during the 4th Quarter: 33
4. Total time duration for all releases of type listed above:

1.11E+04 minutes

5. Maximum duration for release of type listed above:

3.16E+03 minutes Average duration for release of type listed above:

3.36E+02 minutes

7. Minimum duration for release of type listed above:

l.81E+02 minutes

a. Average stream flow (dilution flow) during the period of release: 1.17E+05 gpm 34
  • ARTIFICIAL ISLAND 01/92-03/92 JOINT DISTRIBUTION OF lllND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS lllND: 300 FT LAPSE RATE: LE -1.9 DEG C/100M DELTA T: (300-33FT) CLASS A WIND SPEED GRWPS (MPH) o_o-oi5 0.6-3.5 3.6-7.5 7-6-12.5 12.6-18.5 18.6-24.5 GE 24.6 Slll PERCENT DIRECTION Slll PERCENT Slll PERCENT Slll PERCENT Slll PERCENT Slll PERCENT Slll PERCENT Slll PERCENT N 0 0.0 0 0.0 0 o.o 0 0.0 5 0.2 1 0.0 0 0.0 6 0.3 NNE 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 NE 0 0.0 0 0.0 0 0.0 0 o.o 0 0.0 0 0.0 0 o.o 0 0.0 ENE 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 E 0 0.0 0 0.0 0 0.0 2 0.1 .0 0.0 0 0.0 0 0.0 2 0. 1 ESE 0 o.o 0 0.0 0 o.o 0 0.0 2 0.1 0 0.0 0 0.0 2 0.1 SE 0 o.o 0 0.0 0 0.0 1 0.0 0 0.0 0 0.0 0 0.0 1 0.0 SSE 0 0.0 0 0.0 1 0.0 1 0.0 1 0.0 0 0.0 0 0.0 3 0.1 s 0 0.0 0 o.o 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 SSll 0 0.0 0 0.0 0 0.0 1 0.0 0 0.0 0 o.o 0 0.0 1 0.0 SW 0 0.0 0 0.0 0 o.o 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 WSW 0 0.0 0 o.o 0 0.0 0 0.0 0 o.o 3 0.1 3 0.1 6 0.3 0 0.0 0 o.o

"

111111 0 0.0 0 0.0 0.0 0

0 0.0 o.o 0

2 0.1 2

5 0.1 0.2 3

4 0.1 0.2 2

0 0.1 0.0 7

11 0.3 0.5 NW 0 o.o 0 0.0 0 0.0 1 0.0 5 0.2 11 0.5 14 0.7 31 1.5 NNW 0 0.0 0 0.0 0 0.0 0 0.0 2 0.1 5 0.2 4 0.2 11 0.5 0 0.0 0 0.0 1 o.o 8 0.4. 22 1.1 27 1.3 23 1. 1 81 4.0 HEAN lllND SPEED: 20.7 Table 5 MISSING: 8 Page 1 of 9

ARTIFICIAL ISLAND 01/92-03/92 JOINT DISTRIBUTION OF MIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS MIND: 300 FT LAPSE RATE: -1.8 TO *1.7 DEG C/100H DELTA T: (300-33FT) CLASS B MIND SPEED GROUPS (MPH) 0.0-.0.5 0.6-3.5 3.6-7.5 7.6-12.5 . 12.6-18.5 18.6-24.5 GE 24.6 SlJf PERCENT DIRECTION Slit PERCENT Slit PERCENT Slit PERCENT Slit PERCENT Slit PERCENT Slit PERCENT Slit PERCENT N 0 0.0 0 o.o 0 0.0 2 0.1 1 0.0 2 0.1 0 0.0 5 0.2 NNE 0 0.0 0 0.0 0 0.0 6 0.3 0 0.0 0 0.0 0 0.0 6 0.3 NE 0 0.0 0 0.0 0 0.0 1 0.0 0 0.0 0 0.0 0 0.0 1 0.0 ENE 0 0.0 0 0.0 0 0.0 1 0.0 0 0.0 0 0.0 0 0.0 1 0.0 E 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 ESE 0 0.0. 0 0.0 0 0.0 1 0.0 - 0 0.0 0

0 0.0 0.0 0

0 0.0 0.0 0

1 0.0 0.0 SE 0 0.0 0 0.0 0 0.0 1 0.0 2 0.1 1 0.0 0 0.0 4 0.2 SSE 0 0.0 0 0.0 2 0.1 0 0.0 0 0.0 0 0.0 0 0.0 2 0.1 s 0 0.0 0 0.0 2 0.1 0 o.o 1 0.0 0 0.0 0 0.0 3 0.1 SSM 0 0.0 0 0.0 0 0.0 0 o.o 0 0.0 0 0.0 0 0.0 0 0.0 SM 0 0.0 0 0.0 0 0.0 0 o.o 0 0.0 2 0.1 0 0.0 2 0.1 MSW 0 o.o 0 o.o 0 o.o 0 o.o 0 o.o 1 0.0 0 0.0 1 0.0 w 0 0.0 0 0.0 0 0.0 0. 0.0 1 0.0 6 0.3 2 0.1 9 0.4 MNW 0 o.o 0 0.0 0 0.0 0 0.0 3 0.1 5 0.2 0 0.0 8 0.4 NW 0 0.0 0 0.0 0 0.0 1 0.0 a 0.4 9 0.4 3 0.1 21 1.0 NNW 0 o.o 0 0.0 1 0.0 7 0.3 10 0.5 1 0.0 1 0.0 20 1.0 0 0.0 0 0.0 5 0.2 20 1.0 26 1.3 27 1.3 6 0.3 84 4.2 HEAN MIND SPEED: 16.5 Table 5 HISSING: 7 Page 2 of 9

  • ARTIFICIAL ISLAND Dl/92-03/92
  • JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT LAPSE RATE: 6 TO -1.5 DEG C/100H DELTA T: (300-33FT) CLASS C WIND SPEED GROUPS (MPH) o_o-o.5 0.6-3_5 3.6-7_5 7_6-12-5 12.6-18_5 18-6-24-5 GE 24.6 SUH PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N 0 o_o 0 o_o 1 0.0 1 0.0 0 0.0 0 0.0 0 0.0 2 O. 1 NNE 0 0.0 0 0.0 2 0.1 5 0.2 0 0.0 0 o_o 0 0.0 7 0.3 NE 0 0.0 0 0.0 0 0.0 4 0.2 1 0.0 0 0.0 0 0.0 5 0.2 ENE 0 0.0 0 0,0 1 0.0 0 0.0 0 0.0 0 0.0 0 0.0 1 0.0 E 0 0.0 0 0.0 1 0.0 0 0.0 ~ 0 0.0 0 0.0 0 0.0 1 0.0 ESE 0 0.0 0 0.0 0 0.0 1 0.0 0 0.0 0 0.0 0 o_o 1 0.0 SE 0 0.0 0 0.0 1 0.0 0 0.0 0 0.0 0 0.0 0 0.0 1 0.0 SSE 0 0.0 0 0.0 1 0.0 1 0.0 1 0.0 1 0.0 0 . 0.0 4 0.2 s 0 0.0 0 0.0 1 0.0 1 0.0 0 0.0 0 o.o 0 0.0 2 0.1 SSW 0 0.0 0 0.0 0 0.0 1 0.0 0 0.0 0 0.0 0 0.0 1 o_o SW 0 0.0 0 o.o 0 0.0 0 0.0 0 0.0 1 0.0 0 0.0 1 0.0 WSY 0 0.0 0 0.0 1 0.0 4 0.2 1 0.0 0 0.0 2 0.1 8 0.4 0 0.0 . 0.0 WNY" 0 0.0 0

0 0.0 0.0.

0 0 0.0 4

1 0.2 0.0 7

5 0.3 0.2 1

2 o.o 0.1 3 0.1 15 0_7 3 0.1 11 0.5 NY 0 0.0 0 0.0 1 0.0 2 0.1 11 0.5 5 0.2 2 0.1 21 1.0 NNY 0 0.0 0 0.0 4 0.2 1 0.0 5 0.2 3 0.1 0 0.0 13 0.6 0 0.0 0 0.0 14 0_7 26 . 1.3 31 1.5 13 0.6 10 0.5 94 4.7 MEAN WIND SPEED: 14.7 Table 5 HISSING: 9 Page 3 of 9

  • ARTIFICIAL ISLAND 01/92-03/92 JOINT DISTRIBUTION OF "IND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS "IND: 300 FT LAPSE RATE: -1.4 TO -0.5 DEG C/100M DELTA T: C300-33FT) CLASS D MIND SPEED GRClJPS (MPH) 0.0-0.5 0.6-3.5 3.6*7.~ 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N 0 0.0 1 0.0 5 0.2 7 0.3 10 0.5 13 0.6 0 0.0 36 1.8 NNE 0 0.0 . 0 0.0 3 0.1 5 0.2 16 0.8 4 0.2 2 0.1 30 1.5 NE 0 0.0 2 0.1 8 0.4 22 1.1 14 0.7 3 0. 1 8 0.4 57 2.8 ENE 0 0.0 1 0.0 9 0.4 13 0.6 23 1. 1 9 0.4 5 0.2 60 3.0 E 0 0.0 2 0. 1 4 0.2 10 0.5 7 0.3 0 0.0 0 0.0 23 1. 1 ESE 0 0.0 0 0.0 3 0.1 4 0.2- 0 0.0 0.0 0 0.0 8 0.4 SE 0 0.0 0 0.0 5 0.2 9 0.4 5 0.2 0.0 2 0. 1 22 1. 1 SSE 0 0.0 3 0.1 6 0.3 6 0.3 11 0.5 2 0.1 2 0.1 30 1.5 s 0 0.0 1 0.0 7 0.3 12 0.6 3 0.1 0 0.0 0 0.0 23 1.1 SS" 0 0.0 3 0.1 3 0.1 2 0.1 3 0.1 0 0.0 0 0.0 11 0.5 s" 0 0.0 0 0.0 1 0.0 5 0.2 7 0.3 3 0.1 1 0.0 17 0.8 MS" 0 0.0 0 0.0 5 0.2 8 0.4 5 0.2 4 0.2 0 0.0 22 1.1 M 0 0.0 0 0.0 5 0.2 10 0.5 13 0.6 17 0.8 23 1.1 68 3.4

\INM 0 0.0 2 0.1 5 0.2 7 0.3 27 1.3 28 1.4 20 1.0 89 4.4 N" 0 0.0 0 0.0 0.0 6 0.3 27 1.3 45 2.2 19 0.9 98 4.9 NNY 0 0.0 1 0.0 8 0.4 4 0.2 14 0.7 18 0.9 14 0.7 59 2.9 0 0.0 16 0.8 78 3.9 130 6.5 185 9.2 148 7.4 96 4.8 653 32.6 HEAN "IND SPEED: 16.2 Table 5 HISSING: 109 Page 4 of 9

ARTIFICIAL* ISLAND 01/92-03/92 JOINT DISTRIBUTION OF UIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS UIND: 300 FT LAPSE RATE: -0.4 TO 1.5 DEG C/100H DELTA T: (300-3lFT) CLASS E YIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 w.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUH PERCENT N 0 0.0 0 0.0 7 0.3 11 0.5 12 0.6 7 0.3 0 0.0 37 1.8 NNE 0 0.0 0 0.0 0 o.o 15 0.7 4 0.2 3 0.1 0 0.0 22 1.1 NE 0 0.0 0 0.0 4 0.2 9 0.4 12 o*.6 4 0.2 5 0.2 34 1. 7 ENE 0 0.0 2 0.1 6 O.l 22 1.1 21 1.0 3 0. 1 1 0.0 55 2.7 E 0 0.0 0 0.0 8 0.4 18 0.9 - 5 0.2 0 0.0 1 0.0 32 1.6 ESE 0 0.0 1 0.0 5 0.2 9 0.4 5 0.2 0 0.0 1 0.0 21 1.0 SE 0 0.0 2 0.1 4 0.2 6 0.3 14 0.7 12 0.6 13 0.6 51 2.5 SSE 0 0.0 3 0.1 7 0.3 6 0.3 11 0.5 10 0.5 6 0.3 43 2. 1 s 0 0.0 1 0.0 8 0.4 9 0.4 5 0.2 0 0.0 0 0.0 23 1.1 ssu 0 0.0 1 0.0 6 0.3 17 0.8 6 0.3 3 0.1 1 0.0 34 1. 7 SU 0 0.0 3 0.1 7 0.3 7 0.3 18 0.9 6 0.3 5 0.2 46 2.3 usu 0 0.0 1 0.0 4 0.2 10 0.5 17 0.8 9 0.4 3 0.1 44 2.2 y 0 0.0 2 0.1 .3 0.1 8 0.4 12 0.6 14 0.7 1 0.3 46 2.3 UNU 0 0.0 1 0.0 3 0.1 18 0.9 40 2.0 13 0.6 2 0.1 77 3.8 NU 0 0.0 1 0.0 5 0.2 10 0.5 83 4.1 40 2.0 15 0.7 154 7.7 NNU 0 0.0 0 0.0 2 0.1 17 0.8 23 1.1 21 1.0 3 0.1 66 3.3 0 0.0 18 0.9 79 3.9 192 9.6 288 14.4 145 7.2 63 3. 1 785 39.2 MEAN UIND SPEED: 15.0 Table 5 HISSING: 31 Page 5 of 9

_ARTIFICIAL ISLAND 01/92-03/92 JOINT DISTRIBUTION OF UINO DIRECTION ANO SPEED BY ATMOSPHERIC STABILITY CLASS WINO: 300 FT LAPSE RATE: 1.6 TO 4.0 DEG C/100M DELTA T: (300*33FT) CLASS F UIND SPEED GROUPS (MPH) 0.0*0.5 0.6*3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6*24.5 GE 24.6 SUH PERCENT DIRECTION SUM PER~ENT SUM PERCENT SUM PERCENT SuM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N 0 0.0 0 0.0 4 0.2 2 0.1 3 0.1 1 0.0 0 0.0 10 0.5 NNE 0 0.0 0 0.0 5 0.2 2 0.1 1 0.0 0 0.0 0 0.0 8 0.4 NE 0 0.0 0 0.0 2 0.1 7 0.3 9 0.4 1 0.0 0 0.0 19 0.9 ENE 0 0.0 0.0 3 0.1 6 0.3 12 0.6 0 0.0 0 0.0 22 1.1 E 0 0.0 0.0 3 0.1 3 0.1 3 0.1 0 0.0 0 0.0 10 0.5 ESE 0 0.0 0.0 3 0.1 3 0.1 0 0.0 0 0.0 0 0.0 7 0.3 SE 0 o.o 2 0.1 2 0.1 11 0.5 6 0.3 7 0.3 5 0.2 33 1.6 SSE 0 0.0 2 0.1 4 0.2 11 0.5 6 0.3 3 0.1 11 0.5 37 1.8 s 0 o.o 2 0.1 6 0.3 6 0.3 3 0.1 2 0.1 1 0.0 20 1.0 SSW 0 0.0 1 0.0 1 0.0 2 0.1 3 0.1 4 0.2 2 0.1 13 0.6 SW 0 0.0 1 o.o 4 0.2 4 0.2 8 0.4 5 0.2 0.0 23 1.1 WSW 0 0.0 0 0.0 1 o.o 4 0.2 3 0.1 2 0.1 0.0 11 0.5 0 0.0 1 0.0 1 0.0 o.o UNU" 0 0.0 0 0.0 4 0.2 6

1 0.3 0.0 0

5 0.2 1

0 0.0 0.0 0

0 0.0 0.0 9

10 0.4 0.5 NU 0 0.0 0 0.0 1 0.0 3 0.1 9 0.4 0 0.0 0 0.0 13 0.6 NNU 0 0.0 0 0.0 3 0.1 2 0.1 4 0.2 1 0.0 0 0.0 10 0.5 0 0.0 12 0.6 47 2.3 73 3.6 75 3.7 27 1.3 21 1.0 255 12.7 HEAN UINO SPEED: 13.4 Table 5 HISSING: 9 Page 6 of 9

ARTIFICIAL ISLAND 01/92-03/92 JOINT DISTRIBUTION OF MIND DIRECTION ANO SPEED BY ATMOSPHERIC STABILITY CLASS MIND: 300 FT LAPSE RATE: Gl 4.0 OEG C/100H DELTA T: (300-33FT) CLASS G MIND SPEED GROUPS (MPH) 0.0:0.5 0.6-3.5 3.6-7.5 7.6-12.5 . 12.6-18.5 18.6-24.5 GE 24.6 SlM PERCENT DIRECTION SlM PERCENT SIM PERCENT SIM PERCENT SIM PERCENT SIM PERCENT SIM PERCENT SIM PERCENT N 0 o.o 0 0.0 0 0.0 1 0.0 1 0.0 0 0.0 0 0.0 2 0.1 NNE 0 0.0 0 0.0 0 0.0 3 0.1 1 0.0 0 0.0 0 0.0 4 0.2 NE 0 0.0 0 0.0 1 0.0 1 0.0 0 0.0 1' 0.0 0 0.0 3 0. 1 ENE 0 0.0 0 0.0 0 o.o 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 E 0 0.0 0 0.0 0 0.0 0 0.0 - 0 0.0 0 0.0 0 0.0 0 0.0 ESE 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 SE 0 0.0 0 0.0 0 0.0 0 o.o 0 0.0 0 0.0 0 0.0 0 0.0 SSE 0 0.0 0 0.0 0 0.0 0 0.0 4 0.2 1 0.0 4 0.2 9 0.4 s 0 0.0 0 0.0 1 0.0 3 0.1 1 0.0 1 0.0 4 0.2 10 0.5 SSM 0 0.0 0 0.0 1 0.0 1 0.0 2 0.1 1 o.o 0 0.0 5 0.2 SM 0 0.0 0 0.0 0 0.0 1 0.0 2 0.1 2 0. 1 0 0.0 5 0.2 YSM 0 0.0 0 0.0 3 0.1 1 0.0 2 0.1 0 0.0 0 0.0 6 0.3 y 0 0.0 0 0.0 0 0.0 3 0.1 2 0.1 1 0.0 0 0.0 6 0.3 YNY 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 NY 0 0.0 0 o.o 1 0.0 0 o.o 0 0.0 0 0.0 0 0.0 1 0.0 NNY 0 0.0 0 0.0 0 0.0 0 o.o 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 o.o 7 0.3 14 03 15 0.7 7 0.3 8 0.4 51 2.5 HEAN MIND.SPEED: 16.4 Table 5 HISSING: 5 Page 7 of 9

ARTIFICIAL ISLAND 01/92-03/92 JOINT DISTRIBUTION OF MIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS MIND: 300 FT DELTA T: (300-33FT) ALL STABILITY CLASSES MIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N 0 0.0 1 0.0 17 0.8 24 1.2 32 1.6 24 1.2 0 0.0 98 4.9 NNE 0 0.0 0 0.0 10 0.5 36 1.8 22 1.1 1 0.3 2 0.1 n 3.8 NE 0.0 2 0.1 15 0.7 44 2.2 36 1.8 9 0.4 13 0.6 119 5.9 ENE 0.0 4 0.2 19 0.9 42 2.1 56 2.8 12 0.6 6 0.3 139 6.9 E 0.0 3 0.1 16 0.8 33 1.6 - 15 0.7 0 0.0 1 0.0 68 3.4 ESE 0.0 2 0.1 11 0.5 18 0.9 1 0.3 1 0.0 1 0.0 40 2.0 SE 0.0 4 0.*2 12 0.6 28 1.4 27 1.3 21 1.0 20 1.0 112 5.6 SSE 0.0 8 0.4 21 1.0 25 1.2 34 1.7 17 0.8 23 1.1 128 6.4 s 0.0 4 0.2 25 1.2 31 1.5 13 0.6 3 0.1 5 0.2 81 4.0 SSM 0.0 5 0.2 11 0.5 24 1.2 14 0.7 8 0.4 3 0.1 65 3.2 SM 0.0 4 0.2 12 0.6 17 0.11 35 1.7 19 0.9 1 0.3 94 4.7 MSM 0.0 1 0.0 14 0.7 27 1.3 28 1.4 19 0.9 9 0.4 98 4.9 0.0 3 0.1.

MHY" 0.0 3 0.1 9

12 0.4 0.6 31 29 1.5 1.4 37 85 1.8 4.2 43 52 2.1 2.6 37 25 1.8 1.2 160 206 8.0 10.3 NM 0 o.o 1 0.0 9 0.4 23 1.1 143 7.1 110 5.5 53 2.6 339 16.9 NNY 0 0.0 1 0.0 18 0.9 31 1.5 58 2.9 49 2.4 22 1.1 179 8.9 0 0.0 46 2.3 231 11.5 463 23.1 642 32.1 394 19.7 227 11.3 2003 100.0 HISSING HOURS: 181 HEAN MIND SPEED: 15.5 Table 5 Page 8 of 9

ARTIFICIAL ISLAND 01/92-03/92 JOINT DISTRIBUTION OF UIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS UIND: 300 FT DELTA T: (300-33FT) DIRECTION VS SPEED ONLY WIND SPEED GROUPS (MPH) 0.0-0.5 0.6*3.5 3.6-7.5 7.6*12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUH PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUH PERCENT SUM PERCENT N 0 0.0 1 0.0 17 0.8 24 1.2 32 1.6 24 1.2 0 0.0 98 4.9 NNE 0 0.0 0 0.0 10 0.5 36 1.8 22 1.1 7 0.3 2 0. 1 77 3.8 NE 0 0.0 2 0.1 15 0.7 44 2.2 36 1.8 9 0.4 13 0.6 119 5.9 ENE 0 0.0 4 0.2 19 0.9 42 2.1 - 56 2.8 12 0.6 6 0.3 139 6.9 E 0 0.0 3 0.1 16 0.8 33 1.6 15 0.7 0 0.0 1 0.0 68 3.4 ESE 0 0.0 2 0.1 11 0.5 18 0.9 7 0.3 1 0.0 1 0.0 40 2.0 SE 0 0.0 4 0.2 12 0.6 28 1.4 27 1.3 21 1.0 20 1.0 112 5.6 SSE 0 0.0 8 0.4 21 1.0 26 1.3 35 1. 7 17 0.8 23 1. 1 130 6.5 s 0 0.0 4 0.2 26 1.3 31 1.5 13 0.6 3 0.1 5 0.2 82 4. 1 ssu 0 0.0 5 0.2 11 0.5 24 1.2 14 0.7 8 0.4 3 0.1 65 3.2 SU 0 0.0 4 0.2 12 0.6 17 0.8 35 1.7 19 0.9 7 0.3 . 94 4.7 usu 0 0.0 1 0.0 14 0.7 27 1.3 28 1.4 19 0.9 9 0.4 98 4.9 0 0.0 3 0.1 9 0.4 31 1.5 37 1.8 43 2.1 37 1.8 160 8.0

"

UNU 0 0.0 3 0.1 12 0.6 29 1.4 85 4.2 52 2.6 25 1.2 206 10.3 NU 0 0.0 1 0.0 9 0.4 23 1.1 143 7.1 110 5.5 53 2.6 339 16.9 NNU 0 0.0 1 0.0 18 0.9 31 1.5 58 2.9 49 2.4 22 1.1 179 8.9 0 0.0 46 2.3 232 11.6 464 23.1 643 32.1 394 19.6 227 11.3 2006 100.0 HISSING HOURS: 178 MEAN UIND SPEED: 15.5 Table 5 Page 9 of 9

ARTIFICIAL ISLAND 4/92- 6/92 JOINT DISTRIBUTION OF UIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS UIND: 300 FT LAPSE RATE: LE -1.9 DEG C/lOOM DELTA T: (300-33FT) CLASS A UIND SPEED GRllJPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N 0 0.0 0 0.0 0 0.0 6 0.3 4 0.2 0 0.0 0 0.0 10 0.5 NNE 0 0.0 0 0.0 0 0.0 1 0.0 2 0.1 1 0.0 0 0.0 4 0.2 NE 0 0.0 0 0.0 0 0.0 4 0.2 6 0.3 0 0.0 0 0.0 10 0.5 ENE E

0 0

0.0 0.0 0

0 0.0 0.0 0

0 0.0 6 . 0.3 2 0.1 0 o.o 0 o.o 8 0.4 0.0 3 0.1 4 0.2 0 0.0 0 o.o 7 0.3 ESE 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 SE 0 0.0 0 0.0 0 0.0 5 0.2 3 0.1 2 0.1 3 0.1 13 0.6*

SSE 0 0.0 0 0.0 1. o.o 4 0.2 4 0.2 4 0.2 0 0.0 13 0.6 s 0 0.0 0 0.0 0 o.o 1 0.0 0 0.0 0 O.D 0 0.0 1 0.0 ssu 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 SU 0 0.0 0 0.0 6 0.3 2 0.1 0 0.0 0 0.0 0 0.0 8 0.4 usu 0 0.0 0 0.0 4 0.2 2 0.1 0 0.0 0 o.o 0 0.0 6 0.3 u 0 0.0 0 0.0 5 0.2 0 o.o 1 0.0 0 0.0 0 0.0 6 0.3 UNU 0 0.0 0 0.0 2 0.1 2 0.1 *4 0.2 1 0.0 0 0.0 9 0.4 NU 0 0.0 0 0.0 1 o.o 1 0.0 10 0.5 5 0.2 3 0.1 20 1.0 NNU 0 0.0 0 0.0 0 0.0 1 0.3 11 0.5 6 0.3 1 0.0 25 1.2 0 0.0 0 0.0 19 0.9 44 2.1 51 2.5 19 0.9 7 0.3 140 6.8 HEAN UIND SPEED: 13.9 Table 6 HISSING: 6 Page 1 of 9

  • ARTIFICIAL ISLAND 4/92- 6/92 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT LAPSE RATE: -1.8 TO -1.7 DEG C/100H DELTA T: (300-33FT) CLASS B WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SIM PERCENT DIRECTION SUH PERCENT Slit PERCENT Slit PERCENT Slit PERCENT Slit PERCENT Slit PERCENT Slit PERCENT N 0 0.0 0 0.0 1 0.0 10 0.5 2 0.1 0 0.0 0 0.0 13 0.6 NNE 0 0.0 0 0.0 1 0.0 4 0.2 0 0.0 o.o 0 0.0 6 0.3 NE 0 0.0 0 0.0 2 0.1 12 0.6 0 0.0 0.0 0 0.0 15 0.7 ENE 0 0.0 0 0.0 0 0.0 2 O.J 0.0 0 0.0 0 0.0 3 0.1 E 0 0.0 0 0.0 0 0.0 3 0.1 0 0.0 1 0.0 0 0.0 4 0.2 ESE 0 0.0 0 0.0 0 0.0 2 0.1 0 0.0 0 0.0 0 0.0 2 0.1 SE 0 0.0 0 0.0 0 0.0 0.0 2 0.1 6 0.3 0 0.0 9 0.4 SSE 0 0.0 0 0.0 2 0.*1 3 0.1 4 0.2 0.0 0 0.0 10 0.5 s 0 0.0 0 0.0 0 0.0 2 0.1 2 0.1 0 o.o 0 0.0 4 0.2 SSW 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 SW 0 0.0 1 0.0 2 0.1 0 0.0 0 0.0 0 0.0 0 0.0 3 0.1 WSW 0 0.0 1 0.0 8 0.4 1 0.0 0 o.o 0 o.o 0 o.o 10 0.5 w 0 0.0 0 0.0 4 0.2 3 0.1 0 0.0 0 0.0 0 0.0 1 0.3 WNW 0 0.0 0 0.0 4 0.2 1 0.0 2 0.1 0 o.o 0 0.0 7 0.3 NW 0 0.0 0 0.0 2 0.1 5 0.2 8 0.4 6 0.3 0 0.0 21 1.0 NNW 0 0.0 0 0.0 6 0.3 11 0.5 4 0.2 1 0.0 0.0 23 1.1 0 0.0 2 0.1 32 1.5 60 2.9 25 1.2 17 0.8 0.0 137 6.6 MEAN WIND SPEED: 11.5 Table 6 MISSING: 5 Page 2 of 9

ARTIFICIAL ISLAND 4/92- "6/92 JOINT DISTRIBUTION OF YIND DIRECTION AND SPEED BY ATMOSPHERIC* STABILITY CLASS YIND: 300 FT LAPSE RATE: -1.6 TO -1.5 DEG C/100M DELTA T: (300-33FT) CLASS C MIND SPEED GROOPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6*12.5 12.6-18.5 1a.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N 0 0.0 0 0.0 4 0.2 7 0.3 0.0 0 0.0 0 0.0 12 0.6 NNE 0 0.0 0 0.0 2 0.1 1 0.0 0 0.0 0 0.0 0 0.0 3 0.1 NE 0 0.0 0 0.0 3 0.1 4 0.2 2 0.1 2 0.1 0 0.0 11 0.5 ENE .0 0.0 0 0.0 0 0.0 0 0.0- 0.0 3 0.1 0.0 5 0.2 E 0 0.0 0 0.0 0 0.0 1 0.0 1 0.0 0 0.0 0 0.0 2 0.1 ESE 0 0.0 0 0.0 1 SE 0 0.0 3 0.1 0 0.0 -o 0.0 0 0.0 4 0.2 0.0 0 0.0 0.0 2 0.1 0 0.0 6 0.3 0 0.0 9 0.4 SSE 0 0.0 0 0.0 0.0 1 0.0 1 0.0 2 0.1 1 0.0 6 0.3 s 0 0.0 0 0.0 2 0.1 1 0.0 1 0.0 0 0.0 0 0.0 4 0.2 SSM 0 o.o 1 0.0 2 0.1 1 0.0 1 0.0 0 0.0 0 0.0 SM 0 5 0.2 0.0 1 0.0 2 0.1 3 0.1 1 0.0 0 0.0 0 0.0 7 0.3 MSM 0 o.o 0 0.0 3 0.1 4 0.2 0 0.0 0 0.0 0 o.o 0 0.0 7 0.3 YNY" 0 0.0 0

0 0.0 0.0 4

2 0.2 0.1 2

2 0.1 0.1 3

2 0.1 0.1 0

3 0.0 0.1 0 0.0 9 0.4 0 0.0 9 0.4 NY 0 0.0 0 0.0 2 0.1 6 0.3 8 0.4 2 0.1 0 0.0 18 0.9 NNY 0 0.0 0 0.0 2 0.1 8 0.4 6 0.3 2 0.1 0 o.o 18 0.9 0 0.0 2 O. 1 31 1.5 46 2.2 28 l .4 20 1.0 2 0. 1 129 6.2 HEAN UIND SPEED: 11.7 Table 6 HISSING: 8 Page 3 of 9

ARTIFICIAL ISLAND 4/92- 6/92 JOINT DISTRIBUTION OF YIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS YIND: 300 FT LAPSE RATE: -1.4 TO -0.5 Df.G C/100M DELTA T: (300-33FT) CLASS D YIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT PERCENT SUM SUM PERCENT SUM PERCENT N 0 0.0 0.0 5 0.2 6 0.3 6 0.3 3 0.1 0 0.0 21 1.0 NNE 0 0.0 1 0.0 11 0.5 10 0.5 5 0.2 5 0.2 0 0.0 32 1.5 NE 0 0.0 3 0.1 14 0.7 27 1.l 16 0.8 8 0.4 2 0.1 70 3.4 ENE 0 0.0 0 0.0 18 0.9 29 1.4 4 0.2 8 0.4 2 0. 1 61 3.0 E 0 o.o 1 0.0 28 1.4 27 1.3 11 0.5 0 0.0 0 0.0 67 3.2 ESE 0 0.0 0 0.0 2 0.1 18 0.9 17 0.8 0 0.0 0 0.0 37 1.8 SE 0 0.0 0 0.0 5 0.2 5 0.2 22 1.1 19 0.9 5 0.2 56 2.7 SSE 0 0.0 0 0.0 7 0.3 8 0.4 45 2.2 27 1.3 5 0.2 92 4.5 s 0 0.0 1 0.0 9 0.4 16 0.8 34 1.6 5 0.2 0 0.0 65 3.1 SSY 0 0.0 0 0.0 7 O.l 22 1.1 16 0.8 9 0.4 0 0.0 54 2.6 SY 0 0.0 6 0.3 10 0.5 4 0.2 7 0.3 2 0.1 0 0.0 29 1.4 MSY 0 0.0 0 0.0 6 0.3 6 O.l 0 0.0 0 0.0 0 y

0.0 12 0.6 0 0.0 0.0 9 0.4 8 0.4 3 0.1 0 0.0 0 0.0 21 1.0 YNY 0 0.0 0 0.0 10 0.5 0.0 12 0.6 11 0.5 0.0 35 1.7 NY 0 0.0 0 0.0 9 0.4 16 0.8 19 0.9 10 0.5 0.0 55 2.7 NNY 0 0.0 0 0.0 7 0.3 9 0.4 11 0.5 2 0.1 2 o. 1 31 1.5 0 0.0 14 0.7 157 7.6 212 10.3 228 11.0 109 5.3 18 0.9 738 35.7 HEAN YIND SPEED: 12.7 Table 6 HISSING: 25 Page 4 of 9

ARTIFICIAL ISLAND 4/92- 6/92 JOINT DISTRIBUTION OF MIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS MIND: 300 FT LAPSE RATE: -0.4 TO 1.5 DEG C/100M DELTA T: (300-33FT)

CLASS E MIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT Slll PERCENT Slll PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N 0 0.0 3 0.1 7 0.3 8 0.4 14 0.7 5 0.2 0 0.0 37 NNE 0 0.0 4 0.2 1.8 4 0.2 6 0.3 7 0.3 5 0.2 NE 0 0.0 0 0.0 26 1.3 0.0 8 0.4 18 0.9 20 1.0 8 ENE 0.4 0.0 56 2.7 0 0.0 0.0 10 0.5 11 0.5 11 0.5 3 0.1 0 0.0 36 1.7 E 0 0.0 0 0.0 3 0.1 18 0.9.. 11 0.5 0 0.0 0 0.0 32 ESE 0 0.0 1 0.0 1.5 2 0.1 11 0.5 6 0.3 8 0.4 SE 0 1 0.0 29 1.4 0.0 0 0.0 7 0.3 9 0.4 6 0.3 6 0.3 5 0.2 33 1.6 SSE 0 0.0 0 0.0 8 0.4 19 0.9 35 1.7 9 0.4 2 0.1 73 3.5 s 0 0.0 2 0.1 9 0.4 13 0.6 11. 0.5 3 0. 1 0 0.0 38 1.8 SSll 0 0.0 1 0.0 7 0.3 11 0.5 17 0.8 0.0 0 0.0 37 SM 0 0.0 3 0.1 1.8 9 0.4 9 0.4 17 0.8 16 0.8 1 llSll 0 0.0 0.0 55 2.7 0.0 5 0.2 15 0.7 2 0.1 1 0.0 II 0 0.0 0 0.0 24 1.2 1 0.0 6 0.3 15 0.7 7 0.3 0 0.0 0 0.0 29 1.4 MNY 0 o.o 0 0.0 6 0.3 14 0.7 8 0.4 3 0.1 0 NY 0 0.0 . 0.0 31 1.5 0.0 1 0.0 7 0.3 29 1.4 15 NNY 0.7 0 0.0 53 2.6 0 0.0 0.0 6 0.3 13 0.6 21 1.0 9 0.4 3 0.1 53 2.6 0 0.0 20 1.0 98 4.7 9.5 222 10.7 92 4.5 13 0.6 642 31. 1 HEAN lllND .SPEED: 13.0 Table 6 HISSING: 45 Page 5 of 9

ARTIF.ICIAL ISLAND 4/92- 6/92 JOINT DISTRIBUTION OF WIND DIRECTION ANO SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 300 FT LAPSE RATE: 1.6 TO 4.0 DEG C/100M DELTA T: (300-33FT)

CLASS F WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12~5 12.6* 18.5 18.6*24.5 GE 24.6 SUH PERCENT DIRECTION Slit PERCENT Slit PERCENT Slit PERCENT Slit PERCENT Slit PERCENT Slit PERCENT SLM PERCENT N 0 0.0 2 0.1 0 0.0 5 0.2 6 0.3 0 0.0 0 0.0 13 0.6 NNE 0 0.0 2 0.1 0 0.0 6 0.3 6 0.3 1 0.0 0 0.0 15 0.7 NE 0 0.0 0 0.0 1 0.0 4 0.2 2 0.1 1 0.0 0 0.0 8 0.4 ENE 0 0.0 1 0.0 0 0.0 2 1!-1 2 0.1 1 0.0 0 0.0 6 0.3 E 0 0.0 2 0.1 0 0.0 2 0.1 0 0.0 0 0.0 0 0.0 4 0.2 ESE 0 0.0 1 0.0 1 0.0 2 0.1 1 0.0 2 0.1 0 0.0 7 0.3 SE 0 0.0 0 0.0 2 o.*1 4 0.2 5 0.2 1 0.0 2 0. 1 14 0.7 SSE 0 o.o 1 0.0 3 0.1 7 0.3 9 0.4 6 0.3 6 0.3 32 1.5 s 0 0.0 0 0.0 3 0.1 3 0.1 3 0.1 2 0.1 0 0.0 11 0.5 SSll 0 0.0 1 0.0 3 0.1 6 0.3 5 0.2 4 0.2 0 0.0 19 0.9 Sii 0 0.0 0 0.0 0 0.0 6 0.3 5 0.2 3 0.1 0 0.0 14 0.7 WSW 0 0.0 0 o.o 0 0.0 10 0.5 1 0.0 2 0.1 0 0.0 13 0.6 w 0 0.0 0 0.0 0 0.0 5 0.2 6 0.3 0 0.0 0 0.0 11 0.5 WNll 0 0.0 0 0.0 4 0.2 5 0.2 6 0.3 1 0.0 0 0.0 16 0.8 NII 0 0.0 0 0.0 1 0.0 5 0.2 6 0.3 2 0.1 0 0.0 14 0.7 NNll 0 0.0 0 0.0 5 0.2 6 0.3 2 0.1 0 0.0 0 0.0 13 0.6 0 0.0 10 0.5 23 1. 1 78 3.8 65 3.1 26 1.3 8 0.4 210 10.2 HEAN WINO SPEED: 13.1 '!'able 6 HISSING: 18 Page 6 of 9

ARTIFICIAL ISLAND 4/92* 6/92 JOINT DISTRIBUTION OF MIND DIRECTION ANO SPEED BY ATMOSPHERIC STABILITY CLASS MIND: 300 FT LAPSE RATE: GT 4.0 DEG C/100M DELTA T: (300-33FT) CLASS G MIND SPEED GRCIJPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUH PERCENT N 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 NNE 0 0.0 0 0.0 0 0.0 1 0.0 1 0.0 1 0.0 0 0.0 3 0.1 NE 0 0.0 0 0.0 1 0.0 0 0.0 0 0.0 0 0.0 0 0.0 1 0.0 ENE .o 0.0 0 o.o 0 0.0 1 0.0

  • 0 o.o 0 0.0 0 o.o 1 0.0 E 0 0.0 0 0.0 1 0.0 3 0.1 0 0.0 0 o.o 0 0.0 4 0.2 ESE 0 0.0 0 0.0 1 0.0 1 0.0 1 0.0 0 0.0 0 0.0 3 0. 1 SE 0 0.0 0 0.0 0 0.0 0 0.0 1 0.0 0 o.o 1 0.0 2 0.1 SSE 0 o.o 0 0.0 0 0.0 1 0.0 3 0.1 2 0.1 4 0.2 10 0.5 s 0 0.0 0 o.o 0 0.0 3 0.1 1 0.0 1 0.0 1 0.0 6 0.3 SSM 0 0.0 0 0.0 1 0.0 3 0.1 6 0.3 0 0.0 0 0.0 10 0.5 SM 0 0.0 0 0.0 3 0.1 1 0.0 1 0.0 0 0.0 0 0.0 5 0.2 MSY 0 0.0 0 0.0 0 o.o 1 0.0 1 0.() 0 0.0 0 0.0 2 0.1 M 0 0.0 0 0.0 1 0.0 0 0.0 7 0.3 2 0.1 0 0.0 10 0.5 MNM 0 0.0 0 0.0 0 0.0 0 0.0 2 0.1 1 0.0 0 0.0 3 0.1 NM 0 0.0 0 0.0 0 0.0 3 0.1 5 0.2 0 0.0 0 0.0 8 0.4 NNM 0 0.0 0 0.0 0 0.0 0 0.0 2 0.1 0 0.0 0 0.0 2 0.1 0 0.0 0 0.0 8 0.4 18 0.9 31 1.5 7 0.3 6 0.3 70 3.4 HEAN MIND SPEED: 14.8 Table 6 HISSING: 4 Page 7 of 9
  • ARTIFICIAL ISLAND 4/92-.6/92 JOINT DISTRIBUTION OF UIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS UIND: 300 FT DELTA T: (300-33FT) All ST AB I LI TY CLASSES WIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 . 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N 0 0.0 6 0.3 17 0.8 42 2.0 33 1.6 8 0.4 D 0.0 106 5.1 NNE 0 0.0 7 0.3 18 0.9 29 1.4 21 1.0 14 0.7 0 0.0 89 4.3 NE 0 0.0 4 0.2 29 1.4 69 3.3 46 2.2 20 1.0 3 0.1 171 8.3 ENE 0 0.0 2 0.1 28 1.4 51 2.5 21 1.0 15 0.7 3 0.1 120 5.8 E 0 0.0 3 0.1 32 1.5 57 2.8 27 1.3 1 0.0 0 0.0 120 5.8 ESE 0 0.0 2 0.1 7 0.3 37 1.8 25 1.2 10 0.5 1 0.0 82 4.0 SE 0 0.0 0 0.0 15 0.7 26 1.3 39 1.9 40 1.9 16 0.8 136 6.6 SSE 0 0.0 1 0.0 22 1.1 43 2.1 101 4.9 51 2.5 18 0.9 236 11.4 s 0 0.0 3 0.1 23 1.1 39 1.9 52 2.5 11 0.5 1 0.0 129 6.2 ssu 0 o.o 3 0.1 20 1.0 43 2.1 45 2.2 14 0.7 0 o.o 125 6.1 SU 0 o.o 11 0.5 32 1.5 25 1.2 31 1.5 21 1.0 1 0.0 121 5.9 wsu 0 0.0 2 0.1 26 1.3 39 1.9 4 0.2 3 0.1 0 0.0 74 3.6 u 0 0.0 2 0.1 29 1.4 33 1.6 27 L3 2 0.1 0 0.0 93 4.5 WNU 0 0.0 0 0.0 28 1.4 25 1.2 36 L7 20 1.0 1 0.0 110 5.3 NU 0 0.0 1 0.0 16 0.8 43 2.1 85 4.1 40 1.9 4 0.2 189 9.1 NNll 0 0.0 1 0.0 26 1.3 54 2.6 57 2.8 20 1.0 7 0.3 165 8.0 0 0.0 48 2.3 368 17.8 655 31.7 650 31.5 290 14.0 55 2.7 2066 100.0 HISSING HOURS: 118 HEAN UIND SPEED: 12.8 Table 6 Page 8 of 9
  • *
  • ARTIFICIAL ISLAND 4/92- 6/92 JOINT DISTRIBUTION OF MIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS MIND: 300 FT DELTA T: (300-33FT) DIRECTION VS SPEED ONLY MIND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT OIRECTIOftl Slit PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT Slit PERCENT SUH PERCENT N 0 0.0 6 0.3 17 0.8 42 2.0 33 1.6 8 0.4 0 0.0 106 5. 1 NNE 0 0.0 7 0.3 18 0.9 29 1.4 21 1.0 14 0.7 0 0.0 89 4.3 NE 0 0.0 4 0.2 29 1.4 69 3.3 46 2.2 20 1.0 3 0.1 171 8.2 ENE 0 0.0 2 0.1 28 1.4 51 2.5 - 21 1.0 15 0.7 3 0.1 120 5.8 E 0 0.0 3 0.1 32 1.5 57 2.7 27 1.3 1 0.0 0 0.0 120 5.8 ESE 0 0.0 2 0.1 7 0.3 37 1.8 25 1.2 10 0.5 1 0.0 82 4.0 SE 0 0.0 0 0.0 15 0.7 26 1.3 40 1.9 40 1.9 16 0.8 137 6.6 SSE 0 o.o 1 0.0 22 1.1 43 2.1 101 4.9 51 2.5 18 0.9 236 11.4 s 0 0.0 3 0.1 23 1.1 39 1.9 52 2.5 11 0.5 1 0.0 129 6.2 SSM 0 o.o 3 0.1 20 1.0 46 2.2 45 2.2 14 0.7 0 0.0 128 6.2

.SU 0 0.0 11 0.5 32 1.5 28 1.4 31 1.5 21 1.0 1 0.0 124 6.0 MSM 0 0.0 2 0.1 26 1.3 39 1.9 4 0.2 3 0.1 0 0.0 74 3.6 0 0.0 2 IJNM" 0 0.0 0 0.1 0.0 29 28 1.4 1.4 33 25 1.6 1.2 27 36 1.3 1.7 20 2 0.1 1.0 0

1 0.0 0.0 93 110 4.5 5.3 NM 0 0.0 1 0.0 16 0.8 43 2.1 85 4.1 40 1.9 4 0.2 1B9 9. 1 NNM 0. 0.0 1 0.0 26 1.3 54 2.6 57 2.7 20 1.0 7 0.3 165 8.0 0 0.0 48 2.3 368 17.8 661 31.9 651 31.4 290 14.0 55 2.7 2073 100.0 HISSING HOURS: 111 HEAN MIND SPEED: 12.8 Table 6 Page 9 of 9

AMENDMENT TO RERR-31

  • PART c. LIQUID EFFLUENTS See summary Tables 2A-1 thru 2C for Salem Unit 1 Operations.

See summary Tables 2A-2 thru 2C for Salem Unit 2 Operations.

PART D. SOLID WASTE See Summary in Table 3.

PART E. RADIOLOGICAL IMPACT OH MAH 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 milk 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

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

Liauid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathway. Calculated doses to individuals are as shown below:

Total body dose to an individual: 3.83E-Ol mrem Highest organ dose: 1.79E+OO mrem to the GI-LLI.

Dose to the 6 million individuals living within the so mile radius of the plant site:

Total population dose: 7.lOE-02 person-rem Average population dose: 1.19E-05 mrem/person

  • 8

SALEM GENERATING STATION TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.

3rd 4th Total Units Quarter Quarter Error %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha)
2. Average diluted Ci 6.65E-Ol 1.24E+OO 25 I

concentration during period uCi/mL 8.79E-08 1.29E-07

3. Percent of technical specification limit (T.S. 3.11.1.2. (a))  % 5.62E+OO 1.68E+Ol B. Tritium
1. Total release Ci 1.46E+02 2.14E+02 25
2. Average diluted concentration during period uci/mL 1. 93E-05 2.23E-05
3. Percent of technical specification limit (T.S. 3_.11.1.1)  % 6.42E-Ol 7.42E-Ol
c. Dissolved and entrained noble gases
1. Total release Ci 4.27E-02 3.16E-Ol 25
2. Average diluted concentration during period uCi/mL 5.64E-09 3.29E-08
3. Percent of technical specification limit

. (T. S. 3.11.1.1)  % 2.82E-03 1.65E-02 D. Gross alpha activity

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

Batch Release) liters 2.86E+06 3.29E+06 F. Volume of dilution water used during entire period liters 7.56E+09 9.60E+09 19

SALEM GENERATING STATION TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.

3rd 4th Total Units Quarter Quarter Error %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 3.62E-Ol 6.91E-Ol 25
2. Average diluted concentration during period uCi/mL 6.51E-08 1.35E-07
3. Percent of technical specification limit (T.S. 3.11.1.2. (a))  % 2.86E+OO 1. 05E+Ol B. Tritium
1. Total release Ci 1. OOE+02 1.39E+02 25
2. Average diluted concentration during period uCi/mL l.SOE-05 2.71E-05
3. Percent of technical specification limit (T.S. 3*.11.1.1)  % 6.0lE-01 9.05E-Ol
c. Dissolved and entrained noble gases
1. Total release Ci 5.91E-02 2.GOE-01 25
2. Average diluted *'*

concentration during period uCi/mL 1.0GE-08 5.07E-08

3. Percent of technical specification limit (T.S. 3.11.1.1)  % 5.JlE-03 2.54E-02 D. Gross alpha activity
1. Total release Ci O.OOE+OO O.OOE+OO E. Volume of waste release (prior to dilution -

Batch Release) liters 1.72E+06 2.13E+06

  • F. Volume of dilution water used during entire period liters 5.56E+09 5.13E+09 20

SALEM GENERATING STATION TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 LIQUID EFFLUENTS UNIT 1 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Beryllium-7 O.OOE+OO O.OOE+OO 2.47E-03 O.OOE+OO Sodium-24 O.OOE+OO O.OOE+OO 3.03E-04 8.31E-04 Chromium-51 O.OOE+OO O.OOE+OO 3.30E-04 3.61E-03 Manganese-54 O.OOE+OO O.OOE+OO 1.52E-02 1. 95E-02 Iron-55 O.OOE+OO O.OOE+OO 2.73E-02 3.95E-02 Iron-59 O.OOE+OO O.OOE+OO 2.31E-04 6.51E-05 Cobalt-57 O.OOE+OO O,OOE+OO 1.69E-03 3.03E-03 Cobalt-58 O.OOE+OO O.OOE+OO 4.89E-Ol 8.33E-01 Cobalt-60 1. 97E-05 O.OOE+OO 5.87E-02 1.14E-Ol Zinc-65 O.OOE+OO O.OOE+OO 2.45E-04 1. 49E-05 strontium-89 O.OOE+OO O.OOE+OO 3.81E-04 9.87E-04 strontium-90 O.OOE+OO O.OOE+OO 8.63E-05 1. 25E-04 Niobium-95 O.OOE+OO O.OOE+OO 1.77E-03 2.19E-03 Zirconium-95 O.OOE+OO O.OOE+OO 7.44E-04 1.15E-03 Niobium-97 O.OOE+OO O.OOE+OO 3.74E-04 3.18E-04 Technetium-99m O.OOE+OO O.OOE+OO 2.30E-04 O.OOE+OO Silver-llOm O.OOE+OO O.OOE+OO 3.27E-04 1. 44E-04 Antimony-122 O.OOE+OO O.OOE+OO O.OOE+OO 2.49E-04 Antimony-124 O.OOE+OO O.OOE+OO 1.98E-04 1. 34E-02 Antimony-125 O.OOE+OO O.OOE+OO 1.07E-02 3.91E-02 Iodine-131 5.58E-05 O.OOE+OO 6.80E-03 3.36E-02 Iodine-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodirie-133 O.OOE+OO O.OOE+OO 1.79E-03 1. 26E-03 Strontium-92 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E-05 Cesium-134 1.18E-05 O.OOE+OO 1.85E-02 6.00E-02 Cesium-136 O.OOE+OO O.OOE+OO 3.50E-05 2.18E-03 Cesium-137 2.66E-05 O.OOE+OO 2.71E-02 6.73E-02 Lanthanum-140 O.OOE+OO O.OOE+OO 1.38E-04 8.50E-05 Cerium-144 O.OOE+OO O.OOE+OO 2.82E-04 O.OOE+OO Tin-113 O.OOE+OO O.OOE+OO 2.88E-05 3.85E-05 Fluorine-18 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E-04 Ruthenium-105 O.OOE+OO O.OOE+OO 4.83E-05 O.OOE+OO TOTALS 1.14E-04 O.OOE+OO 6.65E-Ol 1. 24E+OO 21

SALEM GENERATING STATION TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1991 LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Sodium-24 O.OOE+OO O.OOE+OO 1. 59E-04 1.36E-03 Chromium-51 O.OOE+OO O.OOE+OO 3.0lE-04 1.49E-03 Manganese-54 O.OOE+OO O.OOE+OO 7.14E-03 1.21E-02 Iron-55 O.OOE+OO O.OOE+OO 1.42E-02 1.38E-02 Iron-59 O.OOE+OO O.OOE+OO 3.17E-05 O.OOE+OO Cobalt-57 O.OOE+OO O.OOE+OO 8.82E-04 1.65E-03 Cobalt-58 O.OOE+OO O.OOE+OO 2.59E-Ol 5.08E-Ol Cobalt-60 O.OOE+OO O.OOE+OO 2.43E-02 3.62E-02 Zinc-65 O.OOE+OO O.OOE+OO 9.30E-05 O.OOE+OO Strontium-89 O.OOE+OO O.OOE+OO O.OOE+OO 7.02E-04 Strontium-90 O.OOE+OO O.OOE+OO 5.32E-05 1.15E-04 Niobium-95 O.OOE+OO O.OOE+OO 1.08E-03 8.13E-04

  • Zirconium-95 Niobium-97 Technetium-99m Ruthenium-105 Silver-llOm Antimony-122 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.24E-04 3.42E-05 5.35E-05 O.OOE+OO 2.24E-04 1.26E-05 2.83E-04 1.19E-04 1.0lE-05 3.21E-05 3.86E-04 5.82E-05 Antimony-124 O.OOE+OO O.OOE+OO 5.73E-04 9.26E-03 Antimony-125 O.OOE+OO O.OOE+OO 1.67E-02 2.18E-02 Iodine-131 O.OOE+OO O.OOE+OO 5.64E-03 2.06E-02 Iodine-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodine-133 O.OOE+OO O.OOE+OO 1.06E-03 9.0lE-04 Cesium-138 O.OOE+OO O.OOE+OO O.OOE+OO 6.51E-06 cesium-134 O.OOE+OO O.OOE+OO 1.23E-02 2.95E-02 Cesium-136 O.OOE+OO O.OOE+OO 1. 61E-04 8.68E-04 Cesium-137 O.OOE+OO O.OOE+OO 1.78E-02 3.04E-02 Lanthanum-140 O.OOE+OO O.OOE+OO 1.60E-05 3.42E-06 Barium-140 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Bromine-82 O.OOE+OO O.OOE+OO O.OOE+OO 6.04E-05 Fluorine-18 O.OOE+OO O.OOE+OO O.OOE+OO 9.18E-04 TOTALS O.OOE+OO O.OOE+OO 3.62E-Ol 6.91E-Ol 23

REVISION 7 TO SALEM ODCM REVISION 7 OF THE SALEM OFFSITE DOSE CALCULATION MANUAL Attached is a breakdown of the revisions made to the Salem Generating Stations Offsite Dose Calculation Manual (ODCM). The revisions were made to satisfy part B closure of some DCP's and to update information contained in the ODCM.

Chanqe f 1 page 5 bottom Change From:

Use of the effective MPC value as derived in Appendix A may be non-conservative for the R-19 Steam Generator Slowdown monitors and R37 Chemical Waste Basin monitors where I-131 transfer during primary to secondary leakage may potentially be more controlling blowdown monitors, lR13** Service Water monitor and R37 Chemical Waste Basin monitor~

Change to:

Based upon the potential for I-131 to be present in the secondary and service water systems, the use of the default effective MPC value as derived in Appendix A may be non-conservative for the 1Rl9 and 2Rl9 SGBD monitors, the R-37 Chemical Waste Basin Monitor and the lR-13 Service Water Monitors.

Reason:

Clarified statement tor better understandinq of non-conservative conditions that will occur if the default effective MPC value is used *

  • 1

Chanqe f 2 Page 6, bottom Change From:

MPCe of lE-05 uci/ml used for default _2Rl3 radiation monitor setpoint.

Change to:

MPCe of 3.38E-06 uci/ml used for default 2Rl3 radiation monitor setpoint.

Reason:

See Appendix A for justification of MPC*

Chanqe f 3 page 24 section 2.4.l and page 25 section 2.4.2 Changed from:

Qi = cumulative release of noble gas radionuclide i over the period of interest (uci)

Change to:

Q; = cumulative release of noble qas radionuclide i over the period of interest (uci) where uci * (uci/cc) (cc released) or (uci/sec) (sec released)

Reason:

Provided definition of how uci value is obtained *

  • 2
  • Cha.nqe 14 Page 41 table l-1 Changed from:

Circulating Water Pump default value of l.85E5 gpm Changed to:

Circulating water Pump default value of l.OOE5 gpm Reason:

Tests conducted by Maplewood RTL indicated a flow of less than 185,000 gpm. Default value was adjusted downward to be conservative. Test results are found in test document #73752B Chanqe ts P1ge 41 tlble 1*1 Changed frC111:

Parllll'lltter Def1Ult Units CClllllllntS Value SEN 1*R18 as Z.9E+07 c~ per redwa1ta affluent (Cs*137>

dete1'111ined uc:i /Ill 1*R19 Z.9E+07 st... Generator ll~ cca-137>

CA,B,C,D) 1*R13 5.6Z£+07 Service Water

  • Cont*i,_,t fan cooling CA,B,C,D,E) (Cl*137)

Change to:

Actual Def1Ult *unit* Comlnt*

SEN 1*R18 1*R19

..

VllUI detll'llined V1lU1 Z.91+07 Z.91+07

~per uc:i/*l Rldwlste efflu.nt (Cl*137)

St... Gerwr1tor llowdown (Cs*137)

(A,B,C,D) 1*R13CA,I) 5.62E+07 Service W1ter ° Cont1i,_,t F1n Cooling <Cs-137) 1*R13 CC,D,I) 1.01E+OI Reason:

Monitor sensitivities changed due to a detector replacement in accordance with Design Change Package # lEC-3049,lEC-3061, and lEC-3056.

3

  • Chanq* f 6 Page 41 table 1*1 Change from:

Parameter Actual Default Units Cooments value Value SP 1*R18 calculated 4.4E+05(+blcg) ci:m Default alarm setpoints; more conservative values may be used as deemed appropriate 1*R19** calculated 1.3E+04(+blcg) and desirable for ensuring regulatory compliance and for maintaining releases ALARA 1*R13.. calculated 2.6E+03(+blcg)

Change to:

Parameter Actual Default Units Conmen ts Value Value SP 1*R18 calculated 1.13E05(+blcg) Cpnl Default alarm setpoints; more conservative values mey be used as deemed appropriate and 1*R19** calculated 7.25E+03C+blcg) desirable for ensuring regulatory compliance and for .. intaining releases ALARA.

1*R13(A,B>.. calculated 6.7E+02(+blcg)

CC,D,E)** 1.2E+03(+blcg)

Reason:

Setpoints were changed following work from Design Change Package

  1. lEC-3049,lEC-3061,lEC-3056 and updated Circulating Water Data.

Chanqe f 7 page 42 table 1*2 Change fre11:

Par-ter Actual Default Unit* Camientl SEN 2*R18 2*R19

..

Value deten1fned Value 8.SE+07 8.SE+07 cpm per uci/cm1 radwast* effluent ccs-137)

Stea1111 Generator Blowclown (Cs-137 CA,B,C,D) 2*R13 8.8E+07 Service Water* Contairment fan cooling (A,B,C) cca-137>

R37 8.8E+07 Ch..ical Waste Basin (Ca*137)

  • 4

Change to:

Paranwter Actual Default Units Conmentl V*lue Value SEN 2-R18 es 1.14E+08 cpn per Redwaste effluent CCs-137) determined uci/ml 2-R19(A,C) 1.26E+08 S/G blowdown rate per generator 2*R19(8) 1.14E+08 2*R19(D) 1.13E+08 2-R13 9.05E+07 Service Water* Contairment fan cooling CA,8,C) (Cs- 137)

R37 1.24E+08 Cheiaical Waste Basin discharge Reason:

Sensitivities were updated to reflect current design information and to include changes from Design Change Package #2EC-3049,2EC-3053, and 2EC-3054.

Chanqe ta Page 42 table 1-2 Change from:

Parameter Actual Default Unit* ccnmenu Value Value *T cw as 1.85E5 Circulating Water System, a single cw detennined ~.(Note no CW~ in service for 2R13 monitor see section 1.2.2 Change to:

Parameter Actual Default Unit* Caa.ntl Value Value cw as 1.00E5 Cfrculating W.ter Syst*, a single cw detel'llf ned pulp (Note no CW pulp In service for 2R13 monitor ' " section 1.2.2 Reason:

Tests conducted by Maplewood RTL indicated a flow less than 185,000 gpa. Flow rate was adjusted downward to be conservative.

Test results can be found in test document #727538 *

  • 5

Chanqe f 9 Page 42 table 1-2 Change fr0111:

Parameter Actual Default Units Conmen ts Value Value AA A37 as 300 gpm Chemical Waste Basin discharge detennined Change to:

Parameter Actual Default Units Conmen ts Value Value AA A37 as 1200 gpni Chemical Waste Basin discharge detenni ned Reason:

Clearwell Pumps were replaced in 1985 with higher capacity pumps.

The maximum flowrate changed from 300 to 1200 gpm. Change was performed under Design Change Package #lEC-1025.

Chanq* f 10 page 42 table 1-2 Change fr0111:

Par.,..ter ActUlll Deflult Units Cannenta Value Value SP 2*A18- calculated 8.0E+OS(+bkg) Cpl Default alal'lll setpoints; more conservative values may be used 2-R19*- calculated 3.9E+04(+bkg) as deemed appropriate and desirable for ensuring regulatory 2*R13*- calculated 8.8E+02(+bkg) c~lienc:e ind for maintaining releesn Al.ARA R37"- calculated 1.6E+04(+bkg)

Change to:

P11r111111ter Actual Default Units . Cannents Valua Value SP 2*R18 calculated 3.21E+05(+bkg) Cpill Def1ult alar111 1etpoints; more conservative v1lues.may be used 2*R19(A,C>- cah:ulated 3.15E+04(+bkg) as deemed appropriate and 2-R19CB>- 2.85E+04(+bkg) desir1ble for ensuring regulatory 2*A19(0)- 2.825E+04(+bkg) c°""liance and for maintaining releasn Al.ARA.

2*A13- calculated 3.0SE+02(+bkg)

R37'*'* calculated 3.10E+03(+bkg) 6

Reason:

Setpoints were updated to current design information and to include changes from Design Change Package #2EC-3049,2EC-3053, and 2EC-J054.

Corrected typographical error for number of asterisks after the RJ7 monitor and at the bottom of the page.

Chanq* 111 Page 49 table 2*2 Change frcm:

Par-ter Act1.111l Default Unit*

Value Value SP 1*R41C calculat9d 3.3E+04(+blcg) cs- Defeult alal'll 1etpoint1; more conaervative values 11111y be used as 1*R16 calculat9d 7.4E+04(+blcg) cleemd appropriate and desirable for ensuring r-..ilatory c~lianc:e and 1*R12A- calculated 1.SE+04(+blcg) 111aintaining rel***.. ALARA.

Change to:

  • Par-ter Act1.111l Default Units Can11nt1 Value Value SP 1*R41C calculat9d 3.2E+04(+blcg) cs- Defeult alal'll setpoint1; more conmervative values ..Y be used as 1*R16 .calculat9d 7.2E+04(+blcg) de-.:1 9"M"opriata and desirable for ensuring regulatory coq>l iance and 1*R12A- calculat9d 1.5E+04(+blcg) .. intafning relea1.. ALARA.

Reason:

setpoints were revised slightly due to recalculation of current setpoints. Values were rounded down to be conservative.

-

7

Chanqe 112 Page 50 table 2-3 Change fran:

Parameter Actu.l Default Units Cammi ts V*lue Value SP 2*R41C c*lcul*tld 3.3E+04(+b<<g) Default 1l1n1 setpoints; more conserv1tlve v1lues 2-R16 c*lcul*Ud 7.2E+04(+b<<g) may be used H deemed approi:iriate Ind desirable for 2*R12A- c*lcul*ted 2.4E+05(+bltg) ensuring regulatory coq>lill'ICe and for 1111intaining releases Al.ARA.

Change to:

Par!lllleter ActUlll Default unit*

Value Value SP 2*R41C calculated 3. 2E+04( +beg) Default alar11 setpoints; more conserv11tfw values *Y be 2*R16 calculated 7.0E+04(+b<<g) used u de..ct IRX"opriate and ctnfrable for ensuring 2-R12A- calculated 2.4E+05(+b<<g) regulatory ccaipli1nee and fOlt' nmintainf ng releHn ALARA.

Reason:

Setpoints were adjusted slightly following recalculation with current design information.

Chanqe 113 Page 51 table 2-4 Change frca: Atmaplerfc Dfspersion Technical Loctitfan Pathw.y Controllfng X/Q D/Q Specificatfon Age Grcqa (sec/113) (l/182) 6.9.1.10 second s.n Dfrec:t upoeure n/a a.ZZE-06 n/*

(0.21 *flel*> ..t fmalatfon Change to:

Deleted Second 5'n frm table Reason:

The second sun will no longer be used for visitors due to safety concerns *

  • 8

Chanqe f 14 Appendix A, Paqe A-3 Change From:

i: Ci Ci
i: *******

MPCi where:

MPC 0 = an effective MPC v1lue for 1 mixture of rldionucl ide (uci/11l >

Ci

  • concentr1tion of rldionucl ide i in the 111lxture MPCi

B1sed on the 1bove ~tion Ind the rldionuclide di1tril:lutfon in the efflumnts for the past ye1rs from S1lem, 111 efflctlve MPC v1lue c., be deterafned. Results ire prnented In Tlbl* A*1 and A*2 for Unit 1 and Unit 2, respectively.

Considering the 1verqe efflctive MPC v1lue for the years 1911 through 1919, It Is reaaonlbla to select an MPC, value of 1E*05 uci/11l 11 typical of liquid rldwlste df1charg... Using this value to calculate the default R18 1l1nn setpoint v1lue, results in a setpoint that:

1) Will not require fr~t re*edjuat.nt due to *inor variatiana In the ru:lide distribution which are typic*l of routine pl1nt oper1tfons, and 2> Will provide for 1 liquid rldw8ate disch1rge r1t1 ( 11 ..,.luated for each batch-rel****> th*t ia CC11'4)1tible with pl1nt operations < refer to Tlbles 1*1 Ind 1*2).

Change To:

i: c <1......

1 itters only)

J14PC. 8 *******o*ooo**********************

c, <1--> c, (noi't*g.... )

i: ************ + :i: ***********o***

MPC1 MPC1 Where:

MPC*

  • an effective MPC value for a 11ixtur1 of radfonucl ide (uci /*l >

C1

  • concentration.of redianuclide i in the 11ixtur1 MPC1
  • the 10 CFI 20, ~Ix I, Table II, Columt 2 MPC val .. for redionuclide f (uci/11l)

The equation for det1M1fnfng the liquid affluwit S1tpolnta < Section 1.2.1, equation 1.2 > i 1 baaed on a rrultiplfc1tfon of the 1ffectlw MPC t i - th* 1111nltor . . . ltlvlty. lbMvef', the redlation 1111nitors on the effluent l fnee wll l not detect non-~ ..itting radlonucl ldn, such aa H*3, Fe*55, ltld Sr*90. The derivation of th* 1ffectiw Mlle ( section 1.2.1, aqumtlon 1.J > 11 valid for.,,,, distribution but .,.t bl modified to account for the feet that the effluent 1111nltor will not detect th* non*v-. The above modified equation for the effective MPC provldn for a default Sltpoint det1M1inatton that accounts for the non*g......lttlng redlcniclldaa.

Considering the ._.,... effectlw MPC val .. for th* yurs 1918 through 1990, It Is r1uonabl1 to select an MPC, value of 4.711*06 ui;l/*l for Unit 1 ltld 3.38E*06 uci/*l for Unit 2 aa typical *of liquid rldw8ste dischargn. Ualne these values to c.lculat* th* default R18 alaMI Sltpolnt val .. , results In a 1etpoint that:

1) Will not require f~t re*edjuat_,,t due to 11inor variations the nucl Ide distribution which 11r1 typical of routine plant operatlana, ltld 2> Will provide for a liquid radwaat* diacherge rate (II ..,.luated for each batch r1l ..H) that i1 c~tible with pl1nt operatiana < refer to Tabl" 1*1 ltld 1*2).

Reason: To account for qamma and non-qamma emitters as required by Technical Specification 3.11.1.1

  • 9

Cbanq* fl!F Tables A-1 and A-2 Change from:

Tables of effective MPC values for the years 1984 - 1989 for Unit l and Unit 2 Change to:

Table of effective MPC values for the years 1988 - 1990 Reason: To calculata a effective MPC value that includes the gamma and non-gamma e~itters required by Technical Specifications Chuqa t 11 Tabla E-1 Change From:

STATION CODE STATION LOCATION SAMPLE TYPE 14Fl 5.5 mi. WNW of vent1 local farm VGT,MLK Chanqa To:

STATION CODB STATION LOCATION SAMPLE TYPE 14Fl 5.!5 m.. WNW of vent; local fal'll VGT 14F4 7.6 mi. WNW of vant1 local fal'll MLK Reason:

Farm 14Fl cea*ed milk operation* on Juna 1,1991. Farm 14F4 was added to the Radiological Environmental Monitoring Program.

10

'

SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCUIATION MANUAL Revision 7 1/06/92

  • Approval SORC Chairun: tV"c?tZ'o-:L~ Date: @~6-- Mtq. # 7 ""'- 007
  • Salem ODCM Rev. 7 The radioactivity monitor setpoint equation (1.2) remains valid during outages when the circulating water dilution is potentially at its lowest value. Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria.

However, in order to maximize the available plant discharge dilution and thereby minimize the potential offsite doses, releases from either Unit-1 or Unit-2 may be routed to either the Unit-l or Unit-2 Circulating Water System discharge. This routing is possible via interconnections between the Service Water Systems (see Figures land 2). Procedural restrictions prevent simultaneous releases from either a single unit or both units into a single Circulating Water System discharge.

1.2.2- Conservative Default Valu*** Conservative alarm setpoints may be determined through the use of default parameters. Tables 1-1 and l-2 summarize all current default values in use for Salem Unit-l and Unit-2, respectively. They are based upon the following:

a) substitution of the effective MPC value with a default value of 4.71E-06 uCi/ml (Unit 1) and 3.38E-.06 uci/ml (Unit 2). (refer to Appendix A for justification);

b) for additional conservatism*, substitution of the I-131 MPC value of 3E-07 uci/ml for the Rl9 Steam Generator Slowdown Monitors, the R-37 Chemical Waste Basin monitor and the R-13 Service Water Monitors.

  • Based upon the potential for I-131 to b* present in the secondary and service water systems, the use of the default effective MPC value as derived in Appendix A may be non-conservative for the 1, 2 R-19 SGBD monitors, the R-37
  • Chemical waste Basin Monitor and the R-13 Service Water Monitors.

5

Salem ODCK Rev. 7 c) substitutions of the operational circulatinq water flow with the lowest flow, in qal/min: and, d) substitutions of the effluent release rate with the highest allowed rate, in gal/min.

With pre-established alarm setpoints, it is possible to control the radwaste release rate (RR) to ensure the inequality of equation (1.2) is maintained under changing values for MPCe and*

for differing Circulating Water System dilutions *

  • The Unit 2 seriice Water system utilizes the Unit l Circulating Water syat.. tor dilution prior to release to th* river. It is possible to have the Unit l Circulating Water system out of service when Unit l is in an outage. So, for conservatism no dilution is used for determining a 2Rl3 default alarm setpoint.

Because no dilution is considered and the 2Rl3 monitor sensitivity is high, the ~* of 3.38E-06 uCi/ml is used in calculating the alarm setpoint (otherwise using JE-07 uCi/ml would result in an alarm setpoint of l cpm) *

  • '

Salem ODCM Rev. 7 2.4 Noble Ga1 lttluent Po** Calculation* - 10 CPR so ONRISTBXCTID AR.II pose Noble G&S!I. Technical Specification 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of ~5 mrad, gamma-air and ~10 mrad, beta-air and the calendar year limits ~10 mrad, gamma-air and ~20 mrad, beta-air.

The limits a.re applicable separately to each unit and are not combined site limits. The following equations shall be used to calculate the gamma-air and beta-air doses:

= (2.7) and

= 3.17E-08

  • X/Q
  • I: (Nf
  • Q1 ) (2.8) where:

= air dose due to gamma emissions for noble gas radionuclides (mrad)

= air dose due to beta emissions for noble gas radionuclides (mrad)

X/Q

  • atmospheric dispersion to the controlling SITE

- BOUNDARY location ( sac/m3) cumulative release of noble gas radionuclide i over the period of interest (uCi) where uci * (uci/cc) (cc releaaad) or (uCi/sec) (sec released) I

= air dose factor due to gamma emissions from noble gas radionuclide i (mrad/yr per uCi/m3, from Table 2-1)

N.I = air dos* factor due to beta emissions from noble gas radionuclide i (mrad/yr per uCi/m31 Table 2-1)

3. l 7E-08 = conversion factor (yr/sec)
  • 24

Salem ODCM Rev. 7 Tlble 1*1 Par-tera for Li~icl Ala,.. Setpofnt D*t*,..fNtiona unit 1 Per111111eter Ac:tu.l DefM.ll t units C~ts Value V1lue MP Ce c:alc:ullted 4.71E*06* UC:i/*l c:alc:ulated for ..ch batch to be releued MPC 1*131 3E*07 N/A UC:f/*l 1*131 MPC conael"V9tfvely used for SG blow clown Incl Service Water 111nitor satpoints Ci measured N/A UC:i/*l taklf'I frm g - spectral aNlysis of li~icl

  • ff lUlnt MPCf
    • N/A UCl/*l taken frm 10 CFI 20, ~ht I, Tlble II, SEN 1-1'18 ..

clete,..i necl cletena~

2.9E+07 c:~ par uci/*l Col. 2.

R..,._t* effluent CC1*137>

1*R19 2.9E+07 Sta.. Generator ll°""**" (Ca*137>

(A,11,C,D) 1*R13 CA,11) 5.62E+07 Service Water

  • Contmi,_,t Fan Cooling CCa*137>

-

1*R13 CC,D,E) 1.01E+OI cw **

clete,..i necl 1.00£+05 circulating Water Syst*, single cw ~

RR 1*R18 **

clete,..i necl 120 p cletel'lllnecl pt-lor to rele...; release rate cen be edjUlted for Technical Specification CClllPl Iance 1*R19 120 st... Generator bl°"'**" rate par Generator 1*R1l 2500 Service Water flo.i r*t* for Contai,_..t fan cool era SP 1-lt18 c*lcul*tld 1.13E+05C+bk;> CPI Defa1lt *l*rm aatpointa; .,,.. consarv*tive val._ ..., be used n cla-.d apprapri*t* and Hl1.,_ c*lcul*tld 7.251.aJ(+bq) cla9ir*l* for ..urlftl retUl*tory cC111Plianc*

end for *int*lnll'll rel._.. ALMA.

1*R13CA,I).. calcul*tad 6.7!+02C+bkl>

1*R13(C,D,E>.. 1.Zt+G3C..atl>

  • Refer to ~Ix A for mrlvatlon
    • The MPC val~ of 1*131 C3E*07 UCl/*l> hu been used for derivation of the 119 St** Generator blC*clown end 113 service Water manltor satpoint1 as dl1CUIHd In Section 1.2.2 *
  • 41

Salem ODCM Rev. 7 Table 1*2 Par.meters for Liquid Alart11 Setpoint Deter111inationa Unit 2 P11r11111eter Ac:tual Deflult units Cammnta Value Value

... ... . . -* ..............


*****---------------------------

MPCe c:alc:ulated 3.381!*06* UCl/*l calcul1ted for elCh bitch to be rele11ed MPC 1*131 3E*07 N/A UCl/*l 1*131 MPC conserv1tfvely used for SG blow*

down, Service Water rd Che11ic1l W11te Basin 1110nitor 1etpoints Cf measured N/A UCi/ml tlken frm 11- apectrel 1n1lysis of Liquid effluent MPCi IS N/A UCl/11l tlken fra1110 CFll 20, Appendfx B, Table II, deten1ined Col. 2.

SEN 2*"18 IS 1. 14E+Oa C:s-/UCf/*l R...._te effluent CC.*137>

2*R19(A,C) det*r11ined 1.26E+OS Ste.. Genlr1tor llowdown (Cs*137) 2*R19(8) 1.14E+Oa

.19(0) 1.13E+OS R13 9.05E+07 Servfce W1ter

  • Cont1l,_,t fin cool Ing (Cl-137) cw R37

..

deten1ined 1.24E+OS 1.00E+05 Ch*ICll WUt* Blain dfsch1rge Clrcul1tfng W.ter Syst*, single cw ~

(Note no CW pulp fn servic:e for 2R13 111onf tor RR 2*R18 ..

det*1"91ined 120

' " aectlan 1.2.2>

deten1fnld prior to rel ....: rele111 rete c1n be adjusted for Technic:al Specffle1tion CallPlfera 2*R19 120 St** Genentor blowdawn rite per 11erwr1tor 2*R13 2500 hr'lfce *ter flOM l"llte for Cont1f ..-n: fan cool era R37 1200 Ch*fe1l Wute lain df ach1rge SP 2*R18 2*R19CA,C>-

2*R19(8) ..

2*R19CD)..

2*R13..

c:1lc:ul1ted 3.21E+05(+bq) 3.15E+04<+bkl>

2.85E+04(+bkg) 2.825!+04(+bQ) 3.05E+02<+bkl>

Deflult 1l1r11 11tpofnts: mre conservative YllUM my be uud U deemd li:ipr"OfX"ilte and desirable for ..urlng regul1tory campl lance rd for *fntalntng relelHS AL.ARA.

-

R37'** 3. 10E+03(+bkg)

  • Refer to Appendix A for deriv1tlon
    • The MPC v1lue of 1*131 C3E*07 UCl/11l> his been UHd for clerfv1tion of the R19,R13,and R37 monitor setpoints ** dfsc:uased In S9Ctfon 1.2.2
  • 42

Salem ODCM Rev. 7 r.ol* 2-2 P1r-t1f'I for G.11ous Al11'11 Setpoint D*t*l'llinattona untt-1 P*r-ter Actl.Wl* Oefeul t units Vlll.W V1lue


* -------- -------- ----------

X/Q c1lcul1t1d 2.2E*06 sec/m USNRC S1l111 S1fety Ev1luation, S~. 3 VF 1s me1sured 1.25E+05 ft3/111in Pl 1nt Vint

  • nonM l operet ion CPL1nt or Vent) f1n curves VF 1s ***ured 3.5E+04 ftl/*ln conc.1..-,c purge (Cont. or Purge) f1n curves AF coordiMted 0.25 unitl ..* Adllnlltr1tlw 1l loe11tlon f1etor to with HCGS ensure cOIDinad r1l1u.. do not exclld rel1u1 r1t1 li*it for stt1.

Ci me1sured N/A uCi/cllJ ICI nuclide 1p1eific N/A .,.91yr p1r uCi/113 V*lun frcm Tlbl* 2*1 Li nuclide *P1Cific N/A mrwyr p1r uCf/113 V1lun fra11 Tlbl1 2-1 Mi nuclide 1p1elflc N/A wed/yr p1r uC I /113 V1lun fra11 Tlbl1 2*1

  • SEN 1*R41C-1*R16 1*R12A SP 1*R41c 11 detll'lli Md c1lcul1ted 1.6E+07 3.6E+07 2.1E+06
3. 2E+04< +btlU ci:m p1r uCl/cllJ Plwit Vint Plwit Vint (rlCU!dlnU Cont1f ..-,t D1feult 1l1rm **tpolnt: mare conaarv1tiv1 v1lun my bl ua9d 11 de-.d 1i:ipropri1t1 Md deslrlbl* for ..urtng rqul1tory c~ltmnce _..for .. 1nt1lntng r*l***..

1*R16 c1lcul1ted 7.2E+04<+titt> ALMA.

1*R12A- c1lcul1ted 1.51+04<+btt>

  • l*Hd on * .,. for c.l lbr1tlan with *txcure of redforu:lldes
    • Appliclbl1 cU'lng MDDll 1 ttlr"'OUlll 5. During 111)1 6 (refUlltng), manltor ntpolnt shlill bl rlCM:ed to 2X bec:kgr~ in ICCOrdlnce with Tech Spec Tlbl* 3.3*6 *
  • 41

Salem ODCM Rev. 7 Table 2*3 Parameters for Gaseous Alarm Setpoint Detenainati(lnS Unit*2 ActUlll Default Units Conments Parameter Value Value


-------- -------- ----------

  • a*****************************************

calculated 2.2E*06 sec/m3 Licensing technical specification value X/Q as measured 1.25E+OS ft3/min Plant Vent

  • normal operation VF (Plant or Vent) fan curves as measured 3.SE+04 ft3/min Containnent purge VF (Cont. or Purge> fan curves 0.25 111i tless Acbinistrative allocation factor to with AF coordinated HCGS ensure conmined releases do not exceed release rnte limit for site.

Ci measured N/A UCi/cm3 IC I nuclide specific N/A mrem/yr per UCl/1113 Values frOll Table 2-1 Li nuclide specific N/A mrem/yr per UCl/m3 Values from Table 2*1 N/A mrlld/yr per UCl/m3 Values frOll Table 2*1

  • Mi nuclide specific SEN 2*R41C* as 1.6E+07 C?ll per UCi/cm3 Plant Vent detal'lli nect 2*R16 3.SE+07 Plant Vent <redl.rdant>

2*R12A 3.3E+07 Containnent calculatad 3.2E+04(+bltg) Defeult alal'll 1etpoint1; 1110re conservative SP 2*R41C values *Y be used as deellled appropriate and calculated 7.0E+04(+bkg) desirable for ensuring regulatory c~liance 2*R16 arw:i for *intaining releases ALARA.

2*R12A.. calculatad 2.4E+05(+bkg)

  • Bl!l!ed on man for c:alfbratfon .,fth *fxture of radioru:lfdel
    • Applicable during MODES 1 thraugh 5. During DE 6 (refueling), monitor setpoints shall be reduced to 2X backgr<Knl in ac:cot muca Jffth Tech Spec Tabla 3.3*6.

50

Salem ODCM Rev. 7 Teble 2*4 Controlling LOClltiarw, Pethi.eys rd At~tc DISJ19rsion for Doe* CelC1Jlatiarw

  • Atmspheric DISJ19rsion Technic*l Peth ...y(I) Controlling

X/Q D/Q Specif i c*t ion Locetion Age Gr~ (sec/"'1) ( 1/m2)

  • ----*------- *********D*** a**************

------*-

3.11.2.1* lit* boundary noble pa.. N//A 2.2E-06 N//A C0.83 *i le, II) direct exposure 3.11.2.1b s i ,. boundary imalatlon child 2.2£-06 II/A co.83 *i le, II) 3.11.2.2 1tte boundary 1-*alr II/A 2.2£-06 II/A (0.83 *i le, II) beta*air 3.11.2.3 rnidenee/datry *ilk, grCU1d *infant 5.4E*OS 2. 1E*10 (4.9 *il .. , W) plane and imalation

  • The identified controll f~ lacatt-, pathwys and a~rtc dtapenlon are fl'Cll the safety Evaluation Report, S-l~ lo. 3 for the .. l
  • Muel*r Gerwratl~ Station, unit 2 (-EG-0517, Dec-.r 197!) *
  • 51

Salem ODCM Rev. 7 E c 1 (qamaa emitter* only)

XPC

  • = --------------~--------------

c (qamaa) c, (non-qamma)

(A. l) 1 E -----------

XPC + ~ ---------------

XPC 1 1 where:

MPC* ~ an effective MPC value for a mixture of radionuclide (uCi/ml) c,

The equation for determininq the liquid effluent setpoints ( Section 1.2.l, equation 1.2 ) is based on a multiplication of the effective MPC times the monitor sensitivity. However, the radiation monitors on the effluent lines will not detect non-qamma emittinq radionuclides, such as H-3, Fe-55, and Sr-90. The derivation *of the effective MPC ( Section 1.2.l, equation 1.3*) is valid for any distribution but must be modified to account for the fact that the effluent monitor will not detect the non-gammas. Th* above modified equation for the effective MPC provides for a default satpoint determination that accounts *for the non-gamma emitting radionuclide* *

  • A-3

Salem ODCM Rev. 7 Table A*1 Calculation of Effective MPC Salem unit 1 Activity Released CCi)

    • -********a*******************************************

Nuclide MPC

  • 1988 1989 1990 TOTAL CuCi/ml> CURIES CURIES CURIES CURIES

............. ----****- --------- ---------

Na*24 3E*05 1.38E*02 4.69E*04 1.69E*03 1.60E*02 Cr*51 2E*03 2.38E*02 5.25E*03 1.16E*02 4.06E*02 Mn*54 1E*04 1.01E*01 1.12E*01 1.52E*01 3.65E*01 Fe*59 5E*05 2.66E*04 1.32E*03 1.15E*03 2.73E*03 Co*57 4E*04 4.01E*03 6.11E*03 7.54E*03 1.m-02 Co*58 9E*05 1.27E+OO 1.82E+OO 1.98E+OO 5.07E+OO Co*60 3E*05 2.m-01 1.78E*01 2.39E*01 6.94E*01 Zr*95 6E*05 1.23E*02 1.53E*03 4.52E*03 1.84E*02 Nb*95 1E*04 1.53E*02 3.85E*03 9. 76E*03 2.89E*02 Nb*97 9E*04 2.44E*02 7.94E*05 6.30E*03 3.0SE*02 Tc*99m 3E*03 4.74E*03 4.62E*04 8.53E*04 6.05E*03 .

Sr*89 3E*06 1.25E*02 1.54E*03 2.38E*03 1.64E*02 Sr*90 3E*07 2.40E*03 6.68E*04 4.66E*04 3.53E*03 Mo*99 4E*05 1.57E*03 N/D N/D 1.57E*03 Ag* 110m 3E*05 4.96E*D3 2.70E*03 8.40E*04 8.50E*03 Sn-113 SE*05 N/D N/D N/D N/D Sb*124 2E*05 6.32E*02 1.36E*02 1.94E*02 9.62E*02 Sb*125 1E*04 9.35E*02 6.53E*02 6.09E*02 2.20E*01 I* 131 3E*07 S.54E*02 3.04E*02 3.53E*02 1.21E*01

  • I-133 1E*06 2.80E*02 6.88E*03 8.36E*03 4.32E*02 I *134 2E*5 1. 10E*02 N/D N/D 1.10E*02 I *135 4E*06 1.68E*02 1.94E*04 1.42E*04 1. 71E*02 Ce*144 1E*05 1.89E*02 1.19E*04 1.69E*04 1.92E*02 Cs*134 9E*06 1.31E*01 1.16E*01 1.91E*01 4.38E*01 Cs*136 6E*05 9.31E*05 9.79E*04 1.21E*03 2.28E*03 Cs*137 2E*05 1.34E*01 1.28E*01 2.02E*01 4.64E*01 Ba*140 2E*05 2.79E*04 N/D 1.10E*04 3.89E*04 La*140 2E*05 3.89E*04 2.66E*04 5.35E*04 1.19E*03 H*3 3E*03 6.34E+02 6.08E+02 3.53E+02 1.59E+03 Fe* SS 8E*04 5.40E*01 1. 75E*01 1.61E*01 8.76E*01 W*187 6E*05 1.25E*02 N/D N/D 1.25E*02 Zn*65 1E*04 5.49E*04 *3.62!*04 7.75E*03 8.66E-03 Zr*97 2E*OS 1.37E*02 N/D N/D 1.37E*02 Totel Ci G- 2.33£+00 2.49E+OO 2.94E+OO 7.77E+OO Total Cf Non*g- 6.35E+02 6.0SE+OZ 3.53E+02 1.60E+03 MPCe (uCi/ml) 4.71E*06 6.88E*06 9.45E*06
    • N/D
  • not detected
  • A-5

Salem ODCM Rev. 7

  • Table A*2 Calculation of Effective MPC Salem Unit 2 Activity Released (Ci)

MPC*


1988 1989 1990 TOTAL Nuclide CUCi/ml) CURIES CURIES CURIES CURIES Na*24


3E-05


1.04E-02


8.0SE-04


2.28E-03


1.35E-02 Cr-51 2E-03 3. 17E-03 1.57E-02 1.48E-02 3.37E-02 Mn-54 1E-04 1. 74E-01 1. 19E-01 1.52E-01 4.45E-01 Fe-59 SE-05 2.93E*05 3.00E-03 1.09E-03 4. 12E-03 Co-57 4E-04 4.55E*03 6.70E*03 7.92E-03 1.92E*02 Co-58 9E-05 1.32E+OO 2.02E+OO 2.01E+OO 5.35E+OO Co-60 3E-05 2.97E-01 2.0SE-01 2.36E-01 7.41E-01 Zr-95 6E-05 3.15E*03 3.39E-03 5.22E-03 1.18E-02 Nb-95 1E*04 6.SSE-03 7.41E*03 1.03E*02 2.42E*02 Nb-97 9E-04 6.92E*03 2.54E*04 5.32E*04 7.71E-03 Tc-9911 3E*03 3.28E-03 6.64E*04 8.66C-04 4.81E-03 Sr-89 3E*06 . 1.69£-02 1.52E-03 2.28E-03 2.07E-02 Sr-90 3E-07 4.11E-03 6.45E*04 4.73E-04 5.23E-03 Mo-99 4E-05 1.19E-04 N/D. N/D 1.19E-04 Ag-11(1111 3E-05 1.04E-02 6.41E-03 2.56E-03 1.94E*02 Sn-113 SE-05 N/D N/D N/D N/D Sb-124 2c-os 5.47E-02 1.89E-02 2.22e-02 9.58E-02 Sb-125 1E*04 9.22E*02 8.0SE-02 7.40E-02 2.47E-01 1-131 3E*07 1.35E*01 3.79E-02 3.83E*02 2.11E-01 1-133 1E-06 8.83E*02 8.64E-03 1.07E-02 1.0SE-01 1-134 2E-05 3.49£-02 N/D N/D 3.49E-02 1-135 4E-06 1.90E*02 5.17E-04 7.09£-04 2.02E*02 Ce-144 1E-05 2.24E-03 6.05E-04 7.67E-05 2.92E-03 Cs-134 9E-06 9.53E-02 1.43E*01 1.86E-01 . 4.24E*01 cs-136 6E-05 2.20E-03 1.39E-03 1.31E-03 4.90E-03 Cs-137 2E-05 1.09£-01 1.55E*01 1.95E*01 4.59E-01 Ba-140 2E*05 1.57E-03 N/D N/D 1.57E-03 La~140 2E-05 1.03E*03 5.19E*04 6.23E*04 2.17E*03 H*3 3E*03 3.68E+02 5.02E+02 3.03E+02 1.17E+03 Fe* SS SE-04 4.69E*01 1.84E*01 2.09E*01 8.62E*01 W*187 6E*05 6.37E*04 N/D N/D 6.37E*04 Zn*65 1E*04 N/D 1.41E*04 1.06E*02 1.07E*02 Toul Ci G- 2.48E+OO 2.84E+OO 2.98E+OO 8.30E+OO

  • Total Cl Non*11- 3.68E+02 5.02£+02 3.03E+02 1.17E+03 MPCe (UCi /Ill) 3.381-06 7.85E*06 9.71E*06
  • MPC v*lue for WW"eStrtcted *rn frm 10 CFR 20, Appendix a, Tele II, Coluiri 2.
    • N/D
  • not detected
  • A-6

Salem ODCM Rev. 7 TABLB B-1 (Cont*d)

STATION

~ STATION LOCATION SAHPI.E TYPES 2F6 7.3 mi. NNE of vent; Southern 'i'raininq IOM Center 2F7 5.7 mi. NNE of vent; local farm MLK, VGT 3F2 5.1 mi. NE of vent; Hancocks Bridge IOM Municipal Building 3F3 8.6 mi. NE of vent; Quinton Township IOM School 5Fl 6.5 mi. E of vent F'PV,IOM 5F2 7.0 mi. E Of vent; local farm VGT 6Fl 6.4 mi. ESE of vent; Stow Neck Road IOM 7F2 9.1 mi. SE of vent; Bayside, NJ IOM 10F2 5.8 mi. SSW of vent IOM llFl 6.2 mi. SW of vent; Taylor's Bridge IOM Delaware 11F3 5.3 mi. SW of vent; Townsend, OE MLK~ VGT 12Fl 9.4 mi. WSW of vent; Townsend Elem. IOM School 13F2 6.5 mi. W of vent; Od***a, DE IDM 13F3 9.3 mi. W of vent; Redding Middl* IDM School, Middletown, DE 13F4 9.8 :mi. W Of vent; Middletown, DE IDM 14Fl 5.5 mi. *WNW of vent; local farm VGT 14F2 6.6 ai. WNW Of vent; Boyd* Comar IDM 14F3 5.4 :mi. WNW of vent; local farm F'PV 14F4 7.6 mi. WNW of vent; local farm MLK 15F3 5.4 mi. NW of vent IDM

  • B-5