Text

Salem and Hope Creek - 2011 Annual Radioactive Effluent Release Report
	ML12122A919
Person / Time
Site:	Salem, Hope Creek
Issue date:	05/31/2012
From:	; Public Service Enterprise Group
To:	; Office of Nuclear Reactor Regulation
References
	LR-N12-0121
	Download: ML12122A919 (460)
	v • d • e

PSEG NUCLEAR LLC 2011 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SALEM AND HOPE CREEK GENERATING STATIONS SGS RERR-60 DOCKET NO. 50-272 DOCKET NO. 50-311 OPERATING LICENSE NO. DPR-070 OPERATING LICENSE NO. DPR-075 HCGS RERR-34 DOCKET NO. 50-354 OPERATING LICENSE NO. NPF-057 May 2012 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Table of Contents j INTRODUCTION 3 PART A. SUPPLEMENTAL INFORMATION 4 1.0 REGULATORY LIMITS 4 j 1.1 Fission and Activation Gas Release Limits 4 1.2 Iodines, Particulates, and Tritium 4 1 1.3 Liquid Effluents Release Limits 4 1.4 Total Dose Limit 5 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) 5 -3.0 AVERAGE ENERGY 5 4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 5 4.1 Liquid Effluents 5 4.2 Gaseous Effluents 6 1 4.3 Estimated Total Error 7 5.0 BATCH RELEASES 8 6.0 UNPLANNED RELEASES 8 7.0 ELEVATED RADIATION MONITOR RESPONSES 9 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT U RELEASE REPORTS 9 PART B. GASEOUS EFFLUENTS 10 PART C. LIQUID EFFLUENTS 10 PART D. SOLID WASTE 10 PART E. RADIOLOGICAL IMPACT ON MAN 11 i 1.0 LIQUID AND GASEOUS EFFLUENT DOSES 11 1 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 1.1 Total Dose Resulting from Radioactive Effluent Releases and Radiation from Uranium Fuel Cycle Sources 15 1.2 Dose to Members of the Public Due to Activities Inside the Site Boundary 16 1.3 Assessment of Carbon-14 in Gaseous Effluent 16 1.4 Effluent Assessment 18 1.5 Effluent Trends 20 PART F. METEOROLOGICAL DATA 22 PART G. OFFSITE DOSE CALCULATION MANUAL CHANGES 22 PART H. INOPERABLE MONITORS 22 PART I. PROCESS CONTROL PROGRAM (PCP) CHANGES 23 PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES 23 TABLE 1A GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES 24 TABLE IB GASEOUS EFFLUENTS

-ELEVATED RELEASES 30 TABLE 1C GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES 31 TABLE 2A LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES 37 TABLE 2B LIQUID EFFLUENTS 43 TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 49 TABLE 4

SUMMARY

FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE 56 APPENDIX A: METEOROLOGICAL DATA 68 APPENDIX B: MPC DATA 137 ATTACHMENT 1: SALEM OFFSITE DOSE CALCULATION MANUAL, Revision 26, and HOPE CREEK OFFSITE DOSE CALCULATION MANUAL, Revisions 26 (Separate Documents) 145 2 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT *SALEM AND HOPE CREEK GENERATING STATIONS, RADIOACTIVE EFFLUENT RELEASE REPORT: JANUARY -DECEMBER 2011 3 INTRODUCTION This report, SGS-RERR-60/HCGS-RERR-34, summarizes information pertaining to the releases I of radioactive materials in liquid, gaseous and solid form from the Salem Generating Stations (SGS) and the Hope Creek Generating Station (HCGS) for the period January 1, 2011, to December 31, 2011.Salem Unit 1 is a Westinghouse Pressurized Water Reactor that has a licensed core thermal power of 3459 MWt and an approximate net electrical output of 1180 MWe. Salem Unit 1 achieved initial criticality on December 11, 1976, and went into commercial operation on June 30, 1977.Salem Unit 2 is a Westinghouse Pressurized Water Reactor that has a licensed core thermal power of 3459 MWt and an approximate net electrical output of 1177 MWe. Salem Unit 2 achieved initial criticality on August 2, 1980, and went into commercial operation on October I 13, 1981.The Hope Creek Generating Station is a General Electric (GE) Boiling Water Reactor has an up rated core thermal power of 3840 MWt and an approximate net electrical output of 1213 MWe.The HCGS achieved initial criticality on June 28, 1986 and went into commercial operation on December 20, 1986.The electrical energy (net) output for 2011 was as follows: 8,835,758 megawatt-hours of electrical energy (net) were generated by Salem Unit 1, 9,078,855 megawatt-hours of electrical energy (net) were generated by Salem Unit 2, andi 10,505,927 megawatt-hours of electrical energy (net) were generated by Hope Creek Generating Station.This report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Control 6.9.1.8 of the Salem Units 1 and 2 Offsite Dose Calculation Manual (ODCM) and Control 6.9.1.7 of the Hope Creek ODCM. Our responses to parts A-F of the "Supplemental Information" section of Regulatory Guide 1.21, Appendix B, are included in the following pages.As required by Regulatory Guide 1.21, the ODCM limits are described in detail within this report. In addition, summaries describing methods for measuring and determining associated I approximations of total radioactivity are included in this report.I 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT PART A. SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS 1.1 Fission and Activation Gas Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site (i.e.Salem Units 1 and 2, and Hope Creek) to areas at and beyond the site boundary, shall be limited to the following:

For noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin.In addition, the air dose due to noble gases released in gaseous effluents from each reactor unit (i.e. Salem Units 1 and 2, or Hope Creek) to areas at and beyond the site boundary, shall be limited to the following:

During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

1.2 Iodine, Particulates, and Tritium The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

For iodine- 13 1, iodine- 133, tritium and all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.In addition, the dose to a member of the public from iodine- 131, iodine- 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, 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 mrem to any organ and, During any calendar year: Less than or equal to 15 mrem to any organ.1.3 Liquid Effluents Release Limits The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in lOCFR20, 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-04 microcurie 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 to: During any calendar quarter: Less than or equal to 1.5 mrem to the total body, and less than or equal to 5 mrem to any organ, and During any calendar year: Less than or equal to 3 mrem to the total body, and less than or equal to 10 mrem to any organ.4 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT I 1.4 Total Dose Limit I 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 I less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem).2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)Regulatory Guide 1.21 requires that the licensee provide the MPCs used in determining allowable release rates or concentrations for radioactive releases.a. MPC values are not used for gaseous releases.

Determination of maximum release rates for noble gases, Iodine- 131, Iodine- 133, tritium, and for all radionuclides in particulate form (with half-lives

>8 days), are based on dose rate calculations as specified in the ODCM.b. According to current Technical Specifications, MPC values as stated in I 1OCFR20, Appendix B, Table II, Column 2 are to be used for liquid effluents.

Since the MPC values were removed from 10CFR20 effective 1/1/94, the MPC values are now contained in the ODCM. These MPC values are added as Appendix B of this report.c. The MPC value used for dissolved or entrained noble gases in liquid effluents is 2E-04 microcurie per milliliter.

3.0 AVERAGE ENERGY Regulatory Guide 1.21 requires that the licensee provide the average energy of the radionuclide mixture in releases of fission and activation gases, if applicable.

Release limits for the Salem and Hope Creek Generating Stations are not based upon average energy. Therefore this section is not applicable to the Salem and Hope Creek Generating Stations.4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 4.1 Liquid Effluents Liquid effluents are monitored in accordance with Table 4.11-1 of the Salem ODCM and Table 4.11.1.1.1-1 of the Hope Creek ODCM.During the period of record, all batch liquid wastes were routed to the sampling tanks.for monitoring prior to release. The ODCM requires these tanks to be uniformly mixed for sampling and analysis before being released.Batch releases are defined as: 9 For Hope Creek, releases from the Equipment Sample Tanks, Floor Drain Sample tanks, Detergent Drain Tanks, and the Condensate Storage Tank. i 0 For Salem, FRAC Tank releases from the Groundwater Remediation Project, releases from the Service Water Drums, which are collected and disposed via the Chemical Waste Basin, and the Chemical Volume Control System (CVCS)Monitor Tanks. During the period of record, all batch liquid wastes from the I 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Chemical Drain Tank and Laundry and Hot Shower Tanks were routed to Waste Monitor Holdup Tanks for monitoring prior to release. For process flexibility of liquid effluents, the Salem Unit 1 and 2 Liquid Radwaste System is cross-connected.

Continuous releases are defined as: " For Hope Creek, a continuous liquid effluent release path exists through the Circulating Water Dewatering Sump Discharge.

For Salem, continuous liquid release pathways include condensate releases for blow-down of the Steam Generators, and through the Chemical Waste Basin.Representative samples were obtained in accordance with Table 4.11-1 of the Salem ODCM for the Salem Generating Stations and Table 4.11.1.1.1

-1 of the Hope Creek ODCM for Hope Creek Generating Station. The total liquid activity discharged is determined by multiplying specific activities from the analyses by the volume of effluent discharged to the environment.

The detection requirements of Table 4.11-1 (SGS) and Table 4.11.1.1.1-1 (HCGS) of the ODCM are achieved.

Radionuclides that are measured at concentrations below the ODCM-specified lower limit of detection (LLD) are considered present. A radionuclide for which no activity was detected while meeting the required LLD is considered absent.4.2 Gaseous Effluents Salem Units 1 and 2: Gaseous effluent streams at Salem Generating Stations are monitored and sampled in accordance with Table 4.11-2 of the ODCM. The plant vent is the final release point for planned gaseous effluent releases and is continuously monitored by installed radiation monitors.

The vent is also continuously sampled for iodine and particulates with a charcoal cartridge and filter paper. The filter and charcoal are normally changed weekly, and analyzed on a multi-channel analyzer.Sampling is also performed on all gas decay tanks and the containment atmosphere prior to release to the environment.

The plant vent is normally sampled weekly for noble gases, particulates, radioiodine, and tritium.The detection requirements of Table 4.11-2 of the ODCM are achieved or exceeded.

A radionuclide detected at a concentration below the ODCM LLD is considered present.A radionuclide for which no activity was detected while meeting the required LLD is considered absent.Continuous Mode gaseous releases are quantified by routine sampling and isotopic analyses of the plant vent, as required by the ODCM. Specific activities for detected isotopes are multiplied by the total vent flow volume for the entire sampling period in order to determine the normal continuous release of radioactivity through the plant vent.Batch Mode noble gas releases are quantified by sampling each decay tank or containment atmosphere prior to release. The total activity in a batch release was 6 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT U determined by multiplying the specific activities for detected isotopes by the total i volume of the discharged gas in that batch release.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 are not available, then the release is quantified by the use of the plant vent radiation monitors.

The monitor response is converted to "specific activity" using I historical efficiency factors. The total activity discharged is determined by multiplying the "specific activity" by the volume of effluent discharged while the channel was in an alarm state. l Hope Creek: Gaseous effluent streams at Hope Creek Generating Station are monitored and sampled in accordance with Table 4.11.2.1.2-1 of the ODCM. The North Plant Vent (NPV) and South Plant Vent (SPV) are the final release points for most planned gaseous effluent releases.

The NPV and SPV are continuously monitored for iodine, particulates and i noble gases. These monitors have fixed particulate and charcoal filters. The particulate filters and charcoal cartridges are normally replaced and analyzed weekly. These analyses are performed on a multi-channel analyzer.

The NPV and SPV are also i normally sampled weekly for noble gases and tritium.A small quantity of gaseous effluent is released via the Filtration, Recirculation, and Ventilation System (FRVS) vent during FRVS testing periods. The FRVS is continuously monitored for noble gases when in service, and has fixed particulate and charcoal filters. When the system is in vent mode for greater than two hours, samples 3 are collected at the end of the release period. During periods of extended runs, samples are normally taken weekly.The detection requirements of Tables 4.11.2.1.2-1 of the ODCM are achieved or i exceeded.

A radionuclide detected at a concentration below the ODCM detection limit (LLD) is considered present. A radionuclide for which no activity was detected while meeting the required LLD is considered absent.Batch Mode noble gas releases (i.e. primary containment purge) are quantified by pre-release sampling and isotopic analysis.

The total radioactivity released was estimated by multiplying the specific activities for detected isotopes by the containment volume.4.3 Estimated Total Error The estimated total error of reportedliquid and solid releases is within 25%.The estimated total error of the reported continuous gaseous releases is within 50% for the Salem Generating Stations and 25% for the Hope Creek Generating Station when I concentrations exceed detectable levels. These errors are primarily due 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 because error estimates at the LLD are not defined.7 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 5.0 BATCH RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A and 4B.6.0 UNPLANNED RELEASES Unplanned releases that occurred during 2011 at the Salem Generation Station are summarized below.Salem Unit 1 During the Salem Unit 1 Fall 2011 Refueling outage, the Salem Unit 1 Gland Steam Condenser, 11 and 12 Gland Steam Condenser Exhausters, and associated exhaust isolation valves were physically removed from the system with FME covers installed on their openings.

The Gland Seal exhausters tie into the Plant Vent upstream of the radiation monitors.

The removal of the exhaust isolation valves created an unmonitored flow path from the Plant Vent duct work into the Unit One Turbine Building.

The cause was determined to be backflow from the plant vent, which was not considered as an energy source or as a potential unmonitored release flow path. Because the exhauster discharge was not recognized as a potential energy source, the pipe openings were covered with FME covers instead of the blank flanges that would have provided appropriate boundary isolation.

Following the discovery, blank flanges were installed to isolate the flow path.The event and sequence of actions were also documented in the station operator logs. All local area air samples taken were below detection limits supporting the conclusion that no measureable amount of radioactivity was released from this event.Salem Unit 1 and Unit 2 The Salem Unit 1 and Unit 2 Turbine Driven Auxiliary Feed Pump Run Surveillance Testing and Preventative Maintenance (PM) work orders did not include actions for chemistry to sample Main Steam/Steam Generators for radioactivity and generate Effluent Release Permits. These turbine driven steam pumps use secondary side steam for pump function and some of this steam is released to the environment during pump runs. The Steam Generator Blow Down (water) contains on average 20,000-30,000 pCi/L of tritium, therefore the steam released during these pump runs contains the same levels of tritium. Following a review of the 2010 permits, eight (8) could not be aligned with Surveillance Testing or Preventative Maintenance driven pump runs, based on date conflicts.

In addition, there were gaps in 2007, 2008 and 2009. Chemistry has since generated permits for 2008, 2009, 2010, and 2011 and data are current. The estimated release is approximately 1E-4 Ci (total) per event. Salem chemistry is working on 2005, 2006, and 2007 and should be complete by mid-summer.

PSEG is in the process of changing the PM so that activities will be placed in the work orders and drive the permits via the work week process to preclude this from happening in the future.Salem Unit 1 The 11 CVCS Monitor Tank was sampled on 3/4/11 to prepare for a release of the tank.8 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT The proper analyses were completed, documented, and the pre-release paperwork was completed as required to support the release, which took place on 3/5/11. However, the tank sample could not be located to add to the monthly composite, which is analyzed for tritium, gross alpha, strontium-89, strontium-90, and iron-55. Activities detected in the monthly composite are attributed to all tanks released during that month. It was determined that the tank sample had been disposed prior to the tank release and was not available for compositing.

Furthermore, it was determine that the activity in the tank was at normal levels based on review of the other waste tanks released during the same time period. The tritium, gross alpha, strontium-89, strontium-90, and iron-55 were calculated based on the values analyzed from other Unit 1 releases during March and added to the database.

No ODCM dose limit was exceeded.7.0 ELEVATED RADIATION MONITOR RESPONSES During this reporting period, none of the effluent radiation monitors elicited an elevated response during the discharge of liquid and gaseous effluent from either of the SalemeI Units 1 and 2 or from the Hope Creek Generating Station.8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS The carbon-14 (C-14) doses reported in the 2010 Annual Radioactive Effluent Release Report were under-estimated due to the use of a draft version of the C-14 Airborne Dose Calculator obtained from EPRI. The C-14 doses were re-calculated after submittal of the 2010 report using the final version of the calculator spreadsheet.

The assumptions stated in the 2010 ARERR remained the same with the following exceptions:

95% of C-14 released from a BWR (i.e., Hope Creek) and 30% of C-14 released from a PWR (i.e., Salem Units 1 and 2) is in the form of CO 2 (based on information provided in EPRI Technical Report 1021106).Using scaling factors and 2010 power generation data, the estimated total C-14 released in 2010 was 9.86 Ci from Salem Unit 1, 11.17 Ci from Salem Unit 2, and 16.06 Ci from the Hope Creek Generating Station.The revised C-14 doses are: Site Boundarya 4.4 Miles WSWb Generating Total Body Organ Total Body Organ Station (mrem) (mrem) (mrem) (mrem)Salem Unit 1 3.55E-02 1.78E-01 4.47E-03 2.24E-02 Salem Unit 2 4.02E-02 2.01E-01 5.06E-03 2.54E-02 Hope Creek 1.1OE+00 5.50E+00 2.26E-02 1.13E-01 Site Total 1.78E+00 5.88E+00 3.2 1E-02 1.61E-01 4.64 Miles SWC 5.0 Miles NEd Generating Total Body Organ Total Body Organ Station (mrem) (mrem) (mrem) (mrem)Salem Unit 1 5.02E-03 2.5 1E-02 3.97E-03 1.99E-02 Salem Unit 2 5.69E-03 2.85E-02 4.50E-03 2.26E-02 Hope Creek 2.53E-02 1.27E-01 3.49E-02 1.75E-01 I I I I I I 9 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Site Total 3.60E-02 1.81E-01 4.34E-02 2.18E-01 a Hypothetical child receptor receiving a bounding dose from C-14 via ingestion pathways for garden produce, leafy vegetables, milk, and meat.b Real garden; child receptor receiving dose from C-14 via ingestion of garden produce and leafy vegetables.

'Real garden; child receptor receiving dose from C- 14 via ingestion of garden produce and leafy vegetables.

d Real garden; child receptor receiving dose from C- 14 via ingestion of garden produce and leafy vegetables.

The revised doses do not exceed the dose limits given in ODCM Control 3.11.2.3.

The C-14 dose to a hypothetical child receptor at the site boundary is less than 40% of the ODCM dose limit and the C-14 dose to the nearest real child receptor is less than 2% the ODCM dose limit.The C-14 dose component was also included in the determination of compliance with the 49CFRI 90 dose limit. Table 6 in Section 1.1 of Part E to the 2010 report is corrected to include the revised C-14 dose component to a child receptor at a real garden location (5 miles, NE) as follows: Table 6: Total Dose to a Member of the Public Parameter Annual Dose 40CFR190/10CFR72.104 Dose Limit: Total Body or Any Organ (mrem) 2.50E+01 Thyroid (mrem) 7.50E+01 Total Body(mrem) 2.OOE-01% Total Body 8.02E-0 1 Organ Dose (mrem) 8.23E-01% Organ Dose Limit 3.29E+00 Thyroid (mrem) 6.06E-01% Thyroid Limit 8.08E-01 PART B. GASEOUS EFFLUENTS See Summary Tables IA through IC.PART C. LIQUID EFFLUENTS See Summary Tables 2A through 2B.PART D. SOLID WASTE See Summary in Tables 3A and 3B.10 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT PART E. RADIOLOGICAL IMPACT ON MAN 1.0 LIQUID AND GASEOUS EFFLUENT DOSES: The calculated individual doses in this section are based on the controlling dose pathways and age groups as described in the Salem and Hope Creek ODCMs. The estimated doses from liquid and gaseous effluent represent the maximum potential radiation dose for a member of the general public. The total body and organ doses from liquid and gaseous effluent were calculated using methods described in Part 1I of the Salem and Hope Creek ODCMs, which are consistent with the methods described in Regulatory Guide 1.109. For gaseous effluent releases, quarterly doses were calculated using the average quarterly meteorological dispersion factors determined from site meteorological data recorded during 2011.The doses presented in the tables below represent calculations for the 12-month reporting interval.

The radiological impacts from liquid and gaseous effluent discharges from the Salem Unit 1 and 2 and the Hope Creek Generating Station are presented in Tables 5A and 5B, respectively, and demonstrate compliance with applicable regulatory limits. Dose limit values presented in bold font are regulatory limits. The quarterly doses must not exceed the quarterly limit in any quarter and the summation of two or more quarterly doses must not exceed the annual dose limit.Table 5A: Doses from Liquid Effluent Salem Unit 1 Liquid Effluent Parameter 1Q2011 2Q2011 3Q2011 4Q2011 Annual Total Body Dose Limit (mrem) 1.50E+00 1.50E+00 1.50E+00 1.50E+00 3.OOE+00 Maximum Total Body Dose (mrem) 1.29E-05 7.87E-06 1.59E-05 2.58E-05 6.25E-05% Dose Limit 8.59E-04 5.24E-04 1.06E-03 1.72E-03 2.08E-03 Organ Dose Limit (mrem) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01 Maximum Organ Dose (mrem) 2.09E-05 3.24E-05 2.52E-05 1.24E-04 2.03E-04% Dose Limit 4.18E-04 6.47E-04 5.04E-04 2.48E-03 2.03E-03 Salem Unit 2 Liquid Effluent Parameter 1Q2011 2Q2011 3Q2011 4Q2011 Annual Total Body Dose Limit (mrem) 1.50E+00 1.50E+00 1.50E+00 1.50E+00 3.OOE+00 Total Body Dose (mrem) 1.13E-05 1.46E-05 7.29E-06 7.67E-06 4.08E-05% Dose Limit 7.51E-04 9.71E-04 4.86E-04 5.11E-04 1.36E-03 Organ Dose Limit (mrem) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01 Maximum Organ Dose (mrem) 2.51E-05 6.54E-05 1.12E-05 2.69E-05 1.29E-04% Dose Limit 5.01E-04 1.31E-03 2.24E-04 5.37E-04 1.29E-03 Hope Creek Generating Station Liquid Effluent Parameter 1Q2011 2Q2011 3Q2011 4Q2011 Annual Total Body Dose Limit (mrem) 1.50E+00 1.50E+00 1.50E+00 1.50E+00 3.OOE+00 Maximum Total Body Dose (mrem) 2.39E-06 7.12E-06 7.58E-06 3.05E-05 4.76E-05% Dose Limit 1.60E-04 4.75E-04 5.06E-04 2.03E-03 1.59E-03 Organ Dose Limit (mrem) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01 Maximum Organ Dose (mrem) 7.06E-06 1.47E-05 1.85E-05 6.46E-05 1.05E-04% Dose Limit 1.41E-04 2.94E-04 3.70E-04 1.29E-03 1.05E-03 I I I I I I I I I I I I I I I I I I 11 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Salem-Hope Creek Site Total Liquid Effluent Parameter 1Q2011 2Q2011 3Q2011 4Q2011 Annual Total Body Dose Limit (mrem) 1.50E+00 1.50E+00 1.50E+00 1.50E+00 3.OOE+00 Maximum Total Body Dose (mrem) 2.66E-05 2.96E-05 3.08E-05 6.40E-05 1.51E-04% Dose Limit 1.77E-03 1.97E-03 2.05E-03 4.26E-03 5.03E-03 Organ Dose Limit (mrem) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01 Maximum Organ Dose (mrem) 5.31E-05 1.13E-04 5.49E-05 2.16E-04 4.36E-04% Dose Limit 1.06E-03 2.25E-03 1.10E-03 4.31E-03 4.36E-03 The population dose impact from liquid effluents is based on. a summation of the calculated maximum total body doses resulting from the discharge of liquid effluent from each unit, which was conservatively applied to the population within 50 miles of the Salem-Hope Creek site to obtain a maximum population dose from all liquid effluent discharged from the site. The maximum total body dose resulting from liquid effluent discharged from Salem Units 1 and 2 and Hope Creek Generating Station is 1.5 1E-04 mrem, which yields a maximum population dose equal 6.79E-01 person-rem.

Table 5B: Doses from Gaseous Effluent Salem Unit 1 Gaseous Effluent Parameter 1Q2011 2Q2011 3Q2011 4Q2011 Annual Gamma Air Dose (mrad) from Noble 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.00E+01 Gases -Limit Maximum Gamma Air Dose (mrad) 9.31E-06 1.08E-05 1.33E-05 6.1OE-06 3.95E-05% Dose Limit 1.86E-04 2.15E-04 2.66E-04 1.22E-04 3.95E-04 Beta Air Dose (mrad) for Noble Gases -1.00E+01 1.OOE+01 1.00E+01 1.00E+01 2.OOE+01 Limit Maximum Beta Air Dose (mrad) 3.51E-06 4.36E-06 5.33E-06 3.28E-06 1.65E-05% Dose Limit 3.51 E-05 4.36E-05 5.33E-05 3.28E-05 8.23E-05 Organ Dose (mrem) from 1-131, 1-133, Tritium, and particulate nuclides (>8 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 days half-life)

-Limit Organ Dose (mrem) from 1-131, 1-133, Tritium, and particulate nuclides (>8 days 3.02E-04 6.73E-04 2.89E-03 3.95E-04 4.26E-03 half-life)

-Site Boundary (0.8 mile N)% Dose Limit 4.02E-03 8.97E-03 3.85E-02 5.26E-03 2.84E-02 Organ Dose (mrem) from 1-131, 1-133, Tritium, and particulate nuclides (>8 days 8.15E-06 2.OOE-05 7.59E-05 1.1OE-05 1.15E-04 half-life)

-Resident/Dairy (4.9 mile W)% Dose Limit 1.09E-04 2.66E-04 1.01E-03 1.47E-04 7.67E-04 12 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Salem Unit 2 Gaseous Effluent Parameter 1Q2011 2Q2011 3Q2011 4Q2011 Annual Gamma Air Dose (mrad) from Noble 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01 Gases -Limit Maximum Gamma Air Dose (mrad) 1.72E-05 1.28E-05 1.32E-05 1.27E-05 5.59E-05% Dose Limit 3.44E-04 2.56E-04 2.64E-04 2.54E-04 5.59E-04 Beta Air Dose (mrad) for Noble Gases -1.OOE+01 1.OOE+O1 1.OOE+01 1.OOE+O1 2.OOE+O1 Limit Maximum Beta Air Dose (mrad) 6.56E-06 1.04E-05 5.48E-06 5.06E-06 2.75E-05% Dose Limit 6.56E-05 1.04E-04 5.48E-05 5.06E-05 1.38E-04 Organ Dose (mrem) from 1-131, 1-133, Tritium, and particulate nuclides (>8 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 days half-life)

-Limit Organ.Dose (mrem) from 1-131, 1-133, Tritium, and particulate nuclides (>8 days 4.59E-04 3.98E-04 2.51E-03 1.70E-04 3.54E-03 half-life)

-Site Boundary (0.8 mile N)% Dose Limit 6.12E-03 5.31E-03 3.35E-02 2.26E-03 2.36E-02 Organ Dose (mrem) from 1-131, 1-133, Tritium, and particulate nuclides (>8 days 1.24E-05 1.18E-05 6.61E-05 4.75E-06 9.51E-05 half-life)

-Resident/Dairy (4.9 mile W)% Dose Limit 1.65E-04 1.58E-04 8.81E-04 6.34E-05 6.34E-04 Hope Creek Generating Station Gaseous Effluent Parameter 1Q2011 2Q2011 3Q2011 4Q2011 Annual Gamma Air Dose (mrad) from Noble 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.00E+01 Gases -Limit Maximum Gamma Air Dose (mrad) 1.19E-05 0.OOE+00 O.OOE+00 3.60E-05 4.80E-05% Dose Limit 2.39E-04 0.OOE+00 0.OOE+00 7.20E-04 4.80E-04 Beta Air Dose (mrad) for Noble Gases -1.OOE+01 1.00E+01 1.OOE+01 1.OOE+01 2.OOE+01 Limit Maximum Beta Air Dose (mrad) 2.OOE-05 O.OOE+00 0.OOE+00 6.14E-05 8.14E-05% Dose Limit 2.OOE-04 O.OOE+00 0.OOE+00 6.14E-04 4.07E-04 Organ Dose (mrem) from 1-131, 1-133, 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 Tritium, and particulate nuclides (>8 days half-life)

-Limit Organ Dose (mrem) from 1- 131, 1-133, Tritium, and particulate nuclides (>8 days 1.79E-03 3.12E-03 4.24E-03 3.34E-03 1.25E-02 half-life)

-Site Boundary (0.5 mile N)% Dose Limit 2.39E-02 4.17E-02 5.66E-02 4.46E-02 8.33E-02 Organ Dose (mrem) from 1-131, 1-133, Tritium, and particulate nuclides (>8 days 3.67E-05 7.32E-05 8.41E-05 6.95E-05 2.64E-04 half-life)

-Resident/Dairy (4.9 mile W)% Dose Limit 4.89E-04 9.76E-04 1.12E-03 9.27E-04 1.76E-03 I I I I I I I I I I I I I I I I I I 13 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Salem-Hope Creek Site Total Gaseous Effluent Parameter 1Q2011 2Q2011 3Q2011 4Q2011 Annual Gamma Air Dose (mrad) from Noble 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01 Gases -Limit Maximum Gamma Air Dose (mrad) 3.84E-05 2.36E-05 2.65E-05 5.48E-05 1.43E-04% Dose Limit 7.69E-04 4.7 1E-04 5.30E-04 1. 1OE-03 1.43E-03 Beta Air Dose (mrad) for Noble Gases -Lmt1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01 Limit Maximum Beta Air Dose (mrad) 3.01E-05 1.48E-05 1.08E-05 6.97E-05 1.25E-04% Dose Limit 3.01E-04 1.48E-04 1.08E-04 6.97E-04 6.27E-04 Organ Dose (mrem) from 1-131, 1-133, Tritium, and particulate nuclides (>8 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 days half-life)

-Limit Organ Dose (mrem) from 1-131, 1-133, Tritium, and particulate nuclides (>8 days 2.55E-03 4.19E-03 9.64E-03 3.91E-03 2.03E-02 half-life)

-Site Boundary (N Sector)% Dose Limit 3.40E-02 5.60E-02 1.29E-01 5.2 1E-02 1.35E-01 Organ Dose (mrem) from 1-131, 1-133, Tritium, and particulate nuclides (>8 days 5.73E-05 1.05E-04 2.26E-04 8.53E-05 4.74E-04 half-life)

-Resident/Dairy (4.9 mile W)% Dose Limit 7.63E-04 1.40E-03 3.01E-03 1. 14E-03 3.16E-03 Total body and skin doses resulting from noble gases present in gaseous effluent discharged from the Salem -Hope Creek site were determined for the controlling site boundary location in the north sector. These doses (presented below) were calculated using methods described in the Salem and Hope Creek ODCMs, which are consistent with the methods described in Regulatory Guide 1.109.The population dose from gaseous effluent is based on (i) a summation of effluent discharges from the three units, (ii) the assumptions and site-specific data (i.e., food production, milk production, feed for milk animals and seafood production) as described in the Salem and Hope Creek ODCMs, (iii) age group fractions from Appendix D to Regulatory Guide 1.109, and (iv) the annual meteorological dispersion factors and wind frequencies determined from site meteorological data recorded during 2011. A total body dose for each sector was determined using methods described in the Salem and Hope Creek ODCMs, which are consistent with the methods described in Regulatory Guide 1.109. The sector total body doses were used to obtain an average dose to members of the population and a population dose, both of which are presented below.Dose Parameter Total Body Dose from Noble Gases -Site Boundary Skin Dose from Noble Gases -Site Boundary Average Dose from Gaseous Effluent to Population Population Dose from Gaseous Effluent Annual Dose 1.36E-04 mrem 2.46E-04 mrem 5.99E-06 mrem 2.69E-02 person-rem 14 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 1.1 Total Dose Resulting from Radioactive Effluent Releases and Radiation from I Uranium Fuel Cycle Sources An annual dose to a member of the public due to effluent releases and all other uranium fuel cycle sources presented on site was calculated as required by section 3.11.4 of the Salem and Hope Creek ODCMs. This calculation was performed to demonstrate compliance with radiation limits established in 40CFR190 and 10CFR72.104.

I Doses from radioactive effluent releases were calculated as described previously.

The direct radiation dose from sources present onsite, such as operation of the Independent Spent Fuel Storage Installation (ISFSI), was estimated using environmental dosimeter measurements.

The ISFSI is a closed system and the only exposure is direct radiation, which would be measured by the nearby site environmental dosimeters.

The spent fuel is stored in a sealed unit and no radioactive materials were released.

Therefore, there is no dose from effluents from the facility.In the fourth quarter of 2010, PSEG transitioned from dosimetry services provided by i Areva NP to dosimetry services provided by Landauer and conducted side by side monitoring for a full calendar quarter by co-locating Landauer dosimeters with the Areva dosimeters at all REMP direct radiation monitoring locations.

The Landauer I results showed a slightly higher reading at each station, which is attributed to the differences in the dosimetry technology.

Direct radiation measurements collected from six control REMP monitoring locations (all located between 11.8 miles and 32 miles from the site) between 2005 through 2009 demonstrated that the direct radiation levels at the control REMP stations have been historically less than or equal to pre-operational dose (55 mrem). Use of this information supported an assessment of the direct dose from the station. Although the Landauer dosimeter results for the control REMP monitoring locations are higher than past results for these REMP locations, they considered equivalent to the historical dose because of their distances from the site and because there have been no changes to the local environment that would have altered radiation levels. In 2011, the average dose for the six control REMP direct radiation monitoring locations, as recorded with the Landauer dosimeters, was 63 mrem.The approach for determining the direct dose component was based on a comparison of the offsite REMP dosimeters to dosimaters at the REMP control stations.

The average I dose for the two data sets is equal demonstrating that there is no offsite dose impact due to station operations.

40CFR190 and 1OCFR72.104 restrict the total dose to members of the public due to radioactivity and radiation from uranium fuel cycle sources (including the ISFSI facility).

Because the environmental dosimeter data indicated that there was no contribution at the site boundary via direct radiation from the ISFSI site in 2011, compliance with the regulatory requirements for total dose was demonstrated by summing the total body/organ dose contributions and the thyroid dose contributions from liquid effluent and gaseous effluent from the Salem Units 1 and 2 and the Hope Creek Generating Station (including the estimated carbon-14 dose contribution to a child receptor at a real garden location, 5 miles NE), and evaluating those sums against the respective regulatory dose limits. The total body/organ and thyroid doses to members of the public due to radioactivity and radiation from uranium fuel cycle sources are presented in Table 6.15 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Table 6: Total Dose to a Member of the Public Parameter Annual Dose 40CFR190/10CFR72.104 Dose Limit: Total Body or Any Organ (mrem) 2.50E+01 Thyroid (mrem) 7.50E+0 1 Total Body (mrem) 5.26E-02% Total Body/Any Organ Dose Limit 2.11E-01 Organ Dose (mrem) 2.38E-01% Organ Dose Limit 9.51E-01 Thyroid (mrem) 2.04E-02% Thyroid Limit 2.72E-02 1.2 Dose to Members of the Public Due to Activities Inside the Site Boundary Dose to members of the public is limited to 100 mrem total effective dose equivalent (TEDE) in a year in accordance with 1OCFR20.1301.

The dose to a member of the public performing activities inside the site boundary was calculated in accordance with the requirements of ODCM 6.9.1.8 (SGS) and 6.9.1.7 (HCGS). For the purpose of these dose calculations, a member of the public was assumed to be a full-time employee whose assigned duties do not involve exposure to radiation or to radioactive material (i.e., an unmonitored employee working 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months in a year).For the 12-month reporting period, January 1, 2011 to December 31, 2011 the calculated dose and percent of limit are: Parameter Total Body Dose to Member of the Public Inside Site Boundary 1.97E-02mrem

% Limit 1.97E-02 1.3 Assessment of Carbon-14 Releases The NRC has identified carbon-14 (C-14) as a potential principal radionuclide for gaseous effluent because analytical methods for determining C-14 have improved since the publication of Revision 1 to Regulatory Guide 1.21 and, over the same period of time, the radioactive effluents from commercial nuclear power plants have decreased to the point that C-14 is likely to be a principal radionuclide in gaseous effluents (refer to Regulatory Position 1.9 in Revision 2 of Regulatory Guide 1.21). Because gaseous effluent releases from a boiling water reactor (BWR), such as the Hope Creek Generating Station, and pressurized water reactor (PWR), such as the Salem Units, can contain significant quantities of C-14, the NRC has recommended that licensees evaluate C-14 as 16 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT a potential principal radionuclide for gaseous releases from their facility.

Carbon-14 in i gaseous effluent has been evaluated for the Salem and Hope Creek Generating Stations.Those evaluations have determined that C-14 is a "principal radionuclide" in gaseous effluent from each of the three stations.The assessment methodology used to estimate the quantity of C-14 discharged in gaseous effluent from the Salem and Hope Creek Stations involved the use of a I normalized C-14 source term and scaling factors based on power generation from EPRI Technical Report 1021106. This method was selected based on guidance offered in Regulatory Guide 1.21, and incorporates dose models described in I Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, and approach recommendations offered from industry peers and the NRC staff during the 20t Annual RETS-REMP Workshop San Jose, CA (June 2010).The following assumptions are incorporated into the method: o Only inorganic C-14 (i.e., C-14 in the form of C0 2) is incorporated into vegetation through the process of photosynthesis, thus presenting a potential dose via the ingestion exposure pathways.o Doses resulting from direct external exposure and inhalation are negligible (based on information provided at the 2010 RETS-REMP Workshop).

I o Dose from C-14 via the ingestion exposure paths is dominated by fruit and vegetable pathway, followed by the milk and meat pathways (based on information provided at the 2010 RETS-REMP Workshop).

o The concentration of C-14 in vegetation is proportional to the concentration of C-,14 in air (per equation C-8 in RG 1.109). I o 95% of C-14 released from a BWR (i.e., Hope Creek) and 30% of C-14 released from a PWR (i.e., Salem Units 1 and 2) is in the form of CO 2 (based on information provided in EPRI Technical Report 1021106).Using scaling factors and 2011 power generation data, the estimated total C-14 released in 2011 was 9.9 Ci from Salem Unit 1, 10.1 Ci from Salem Unit 2, and 17.8 Ci from the I Hope Creek Generating Station.The maximum total body and organ (bone) doses from C-14 occurred for a child receptor.

The doses from the estimated C-14 in gaseous effluents are less than 46% of the annual dose limit specified in the Salem and Hope Creek ODCMs (3.11.2.3) to a hypothetical child receptor at the site boundary and less than 1.5% for the nearest real child receptors.

The annual total body and organ doses due to the estimated C-14 releases in 2011 are: Site Boundarya 4.4 Miles WSWb Generating Total Body Organ Total Body Organ Station (mrem) (mrem) (mrem) (mrem)Salem Unit 1 9.68E-02 4.85E-01 5.30E-03 2.65E-02 Salem Unit 2 9.95E-02 4.98E-01 5.44E-03 2.73E-02 17 I I I 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT I Hope Creek 1 1.16E+00 5.82E+00 2.96E-02 1.48E-O1 Site Total 1.36E+00 6.80E+00 J 4.03E-02 2.02E-01 4.6 Miles SWC 5.0 Miles NEd Generating Total Body Organ Total Body Organ Station (mrem) (mrem) (mrem) (mrem)Salem Unit 1 5.23E-03 2.62E-02 5.70E-03 2.86E-02 Salem Unit 2 5.37E-03 2.69E-02 5.86E-03 2.94E-02 Hope Creek 2.92E-02 1.46E-01 3.19E-02 1.59E-01 Site Total 3.98E-02 1.99E-01 4.35E-02 2.17E-01 a Hypothetical child receptor receiving a bounding dose from C-14 via ingestion pathways for garden produce, leafy vegetables, milk, and meat.b Real garden; child receptor receiving dose from C-14 via ingestion of garden produce and leafy vegetables.

C Real garden; child receptor receiving dose from C-14 via ingestion of garden produce and leafy vegetables.

d Real garden; child receptor receiving dose from C-14 via ingestion of garden produce and leafy vegetables.

1.4 Effluent Assessment Liquids: Liquid effluents released from the Salem and Hope Creek Generating Stations resulted in doses to a hypothetical maximally exposed individual that were within all applicable regulatory limits (Salem Unit 1: 2.08E-03%

of the Total Body Limit, Salem Unit 2: 1.36E-03%

of the Total Body Limit, and Hope Creek: 1.59E-03%

of the Total Body Limit).When compared to releases in the previous reporting period, the fission & activation product activity in the liquid effluents decreased slightly from the Salem unit 1,"and dropped slightly for Salem unit 2. For the Hope Creek Generating Station, the liquid effluent and resulting dose dropped significantly from the previous reporting period.Effluent activities and doses were higher in the previous reporting period (2010) as a result of the decontamination of the RHR system during the fourth quarter 2010. The liquid effluent releases from the Salem Units and the Hope Creek Generating Station continue to remain well within Federal limits.Gaseous: Gaseous effluents released from the Salem and Hope Creek Generating Stations resulted in doses to a hypothetical maximally exposed individual that were within all applicable regulatory limits. The doses for the 12-month period were small fractions of all applicable limits (Salem Unit 1: 2.84E-02%

of the annual organ (including total body) dose limit, Salem Unit 2: 2.36E-02%

of the annual organ (including total body)dose limit, and Hope Creek: 8.33E-02%

of the annual organ (including total body)dose limit.18 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT When compared to releases in the previous reporting period, the Salem noble gas effluent activity increased slightly; whereas, the Hope Creek noble gas effluent activity decreased.

Gaseous effluent releases for the site continue to remain well within Federal limits and are comparable to other nuclear utilities.

Fuel integrity and gaseous effluent processing equipment continue to be maintained in order to ensure that all releases of gaseous radioactivity are As-Low-As-Reasonably-Achievable (ALARA).19 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 1.5 Effluent Trends The following two trend graphs show the total curies of liquid and gaseous effluents released for Salem from 2006 through 2011. Calculated doses in the graphs are to the hypothetical maximum exposed individual.

Liquid Releases (SGS) Fission & Activation Products Curies Released and Calculated Doses E 2!E 1.OOE+00 1.00E-01 1.00E-02 1.OOE-03 1.OOE-04 1.OOE-05 1.00E+00 1.O0E-01 1.00E-02 (A 1.00E-03 1. OOE-04 1.OOE-05 2006 2007 2008 2009 2010 2011 Year---Organ -- Total Body -A-Curies Gaseous Releases (SGS) Curies of Noble Gases Released and Calculated Doses E El E 1.OOE+05 1.OOE+04 1.OOE+03 1.OOE+02 1.OOE+01 1.OOE+00 1.OOE-01 1.OOE-02 1.OOE-03 1.OOE-04 1. OOE-05 2C 1.OOE+05 1.OOE+04 1.OOE+03 1.OOE+02 1.OOE+01 =U 1.OOE+00 1.OOE-01 1.OOE-02)06 2007 2008 2009 2010 2011 Year--- TotalBody -U--Skin -A-Curies 20 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT The following two trend graphs show the total curies of liquid and gaseous effluents released for Hope Creek from 2006 through 2011. Calculated doses in the graphs are to the hypothetical maximum exposed individual.

Liquid Releases (HCGS) Fission & Activation Products Curies Released and Calculated Doses 1.00E+00 -1.OOE-01 1.OOE-02ý1 .00E-03 1.OOE-04 1.00E-05 2006 1 .OOE+00 1.OOE-01 1.OOE-02 , 1.OOE-03 Z 1.OOE-04 1.OOE-05 2007 2008 2009 2010 Year 2011-- Total Body --*Organ -A-Curies I I I I I I I I I I I I I I I I I I I Gaseous Releases Curies of Noble Gases Released and Calcul Doses 1 .UUL+U3 1.OOE+02 1.OOE+01-i nnc rkn L be- 1.OOE-01 E 1~lated I .OOE+02 1.OOE+01 1.OOE+00 1.OOE-01 1.00E-021.OOE-04 1.OOE-05 1.OOE-06 1.OOE-07 1M00E-08 1.OOE-02 +1.OOE-03 +1.OOE-04 I 1.OOE-05 -2006 9 I' -I 9 2007 2008 Year 2009 2010 2011--*-Total Body -U-Skin -&-Curies 21 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT PART F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class for the reporting period are provided in Appendix A.PART G. OFFSITE DOSE CALCULATION MANUAL CHANGES Salem and Hope Creek The Salem and Hope Creek ODCMs were revised during the reporting period. Both ODCMs were revised for the reasons explained below. Copies of the Salem ODCM revision 26 and the Hope Creek ODCM revision 26 are provided as Attachment 1.Revision Summary 1. Table E-1 section B. Air Sampling Locations was revised to include one new air sampler location, 5S2. And table 3.12.1-1 was revised to describe the air sampling requirements for the program, increased from six locations to seven.Justification:

NOS audit finding from Maplewood Testing Services Laboratory vendor audit SNA 2009-091, refer to US NRC Reg Guide 4.15 revision 2, which calls for field duplicate sampling stations, reference DCP 80102652.

This was also recommended by REMP benchmarking 70084355-0110.

2. Updated Figure E-l On-site Sampling Locations to update the new sampling location for air sampler 5S2.And Figure E-2 Off-site Sampling Locations was updated with the location of a new management audit sample.Justification:

The map was updated to be consistent with the REMP station location listed in Table E- 1 section B. Figure E-2 was update to include location of offsite management audit sample for muskrat sampling (5C 1).3. Section 3.3 was added to assess dose due to C-14 for gaseous effluents, includes methodology for assessment based on guidance from Regulatory Guide 1.21 revision 2.Justification:

In accordance with guidance offered in Regulatory Guide 1.21 revision 2 the station conducted an evaluation which identified C- 14 as a principal radionuclide in gaseous effluent releases from the Salem Generating Station (SAP Order 70096339).

Revision to the ODCM documents the methodology used for estimating the doses from Carbon 14.PART H. INOPERABLE MONITORS Salem: Gross Activity Radiation Monitors 1R13 and 2 R13, which monitor Containment Fan Coolers Service Water Line Discharge, were inoperable for greater than 30 Days beginning in February and continuing throughout the year. These monitors have design deficiencies.

These monitors are on the schedule for replacement during the spring of 2012. Required compensatory actions were taken during the period these were inoperable.

22 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Hope Creek: There were no inoperable effluent radiation monitors at the Hope Creek I Generating Station during the reporting period.PART I. PROCESS CONTROL PROGRAM (PCP) CHANGES During the reporting period, there were no technical or programmatic changes to either the Salem or Hope Creek PCPs.PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES During the reporting period, a new air sampling location (5S2) was added to the 3 Environmental Monitoring Program within the site property boundary (see Figure E-1: Onsite Sampling locations in the Salem and Hope Creek ODCM's). This increases the number of program air samplers from six to seven.I I I I I I I I I I I I 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A-1 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Units 1 st Quarter 2 nd Quarter Error 1 A. Fission and Activation Gases 1. Total Release Ci 6.94E-02 6.87E-02 50%2. Average Release Rate For Period ýLCi/sec 8.93E-03 8.74E-03 3. Percent of Technical Specification Limit % 1.86E-04 2.15E-04 (ODCM 3.11.2.2(a))

B. Iodine 1. Total Iodine-131 Ci 3.07E-07 5.13E-07 50%2. Average Release Rate For Period jiCi/sec 3.95E-08 6.53E-08 3. Percent of Technical Specification Limit 2 % 4.02E-03 8.91E-03 (ODCM 3.11.2.3(a))

C. Particulates

1. Particulates With Half-lives >8 days Ci 0.OOE+00 O.OOE+00 50%2. Average Release Rate For Period gtCi/sec 0.OOE+00 0.OOE+00 3. Percent of Technical Specification Limit 2 % 0.OOE+00 0.OOE+00 (ODCM 3.11.2.3(a))

4. Gross Alpha Ci 0.OOE+00 0.OOE+00 D. Tritium 1. Total Release Ci 1.73E+01 2.67E+01 50%2. Average Release Rate For Period pCi/sec 2.23E+00 3.40E+00 3. Percent of Technical Specification Limit 2 % 4.02E-03 8.91E-03 (ODCM 3.11.2.3(a))

1. For batch releases, the estimated overall error is 10%.2. Iodine, Tritium, and Particulates are treated as a group. The percent TS Limit is based on most limiting nuclide and organ dose.24 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A-2 SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Error 1 Units I" Quarter 2nd Quarter A.I.2.Fission and Activation Gases Total Release Average Release Rate For Period Ci 1.33E-01 pCi/sec 1.71E-02 3. Percent of Technical Specification Limit (ODCM 3.11.2.2(a))

B. Iodine 1. Total Iodine- 131 2. Average Release Rate For Period 3. Percent of Technical Specification Limit2 (ODCM 3.11.2.3(a))

C. Particulates

1. Particulates With Half-Lives >8 days 2. Average Release Rate For Period 3. Percent of Technical Specification Limit 2 (ODCM 3.11.2.3(a))

4. Gross Alpha D. Tritium 1. Total Release 2. Average Release Rate For Period 3. Percent of Technical Specification Limit 2 (ODCM 3.11.2.3(a))

1: For batch releases, the estimated% 3.44E-04 Ci 0.OOE+00 2.67E-01 3.39E-02 2.56E-04 O.OOE+00 O.OOE+00 O.OOE+00 50%50%pCi/sec O.OOE+00 I I I I I I I I I I I I I I I I% O.OOE+/-0O 0.OOE+00 Ci p.C/sec O.OOE+00% O.OOE+00 Ci O.OOE+00 Ci 2.63E+01 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 1.58E+01 2.OOE+00 5.3 1E-03 50%50%oIci/sec 3.39E+00%6.12E-03 overall error is 10%.2. Iodine, Tritium, and Particulates are treated as a group. The percent TS Limit is based on most limiting nuclide and organ dose.25 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A-3 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Error'Units 1 st Quarter 2 nd Quarter A.B.C.Fission and Activation Gases 1. Total Release 2. Average Release Rate For Period 3. Percent of Technical Specification Limit (ODCM 3.11.2.2(a))

Iodine 1. Total Iodine- 131 2. Average Release Rate For Period 3. Percent of Technical Specification Limit 2 (ODCM 3.11.2.3(a))

Particulates

1. Particulates With Half-Lives >8 days 2. Average Release Rate For Period 3. Percent of Technical Specification Limit2 (ODCM 3.11.2.3(a))

Ci 5.11E-02 0.OOE+00 25%[tCi/sec 6.57E-03 0.OOE+00%2.39E-04 O.OOE+/-0O Ci 6.41E-04 7.60E-04 25%ptCi/sec 8.24E-05 9.66E-05% 2.39E-02 4.17E-02 Ci 2.96E-05 4.58E-05 25%ptCi/sec 3.80E-06 5.83E-06% 2.39E-02 4.17E-02 4. Gross Alpha Ci O.OOE+00 O.OOE+00 D. Tritium 1. Total Release Ci 9.69E-04 O.OOE+00 25%2. Average Release Rate For Period ýtCi/sec 1.25E-04 0.OOE+00 3. Percent of Technical Specification Limit2 % 2.39E-02 O.OOE+00 (ODCM 3.11.2.3(a))

1. For batch releases, the estimated overall error is 10%.2. Iodine, Tritium, and Particulates are treated as a group. The percent TS Limit is based on most limiting nuclide and organ dose.26 I 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A-4 SALEM GENERATING STATION -UNIT 1 3 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES '3 Est.d hTotal Units 3 rd Quarter 4 th Quarter Errort A. Fission and Activation Gases 3 1. Total Release Ci 5.9 1E-02 5.23E-02 50%2. Average Release Rate For Period ýiCi/sec 7.44E-03 6.57E-03 I 3. Percent of Technical Specification Limit % 2.66E-04 1.69E-04 (ODCM 3.11.2.2(a))

l B. Iodine 1. Total Iodine- 131 Ci 0.OOE+00 0.OOE+00 50% 5 2. Average Release Rate For Period gCi/sec O.OOE+00 O.OOE+00 3. Percent of Technical 3 Specification Limit2 % 0.OOE+00 0.OOE+00 (ODCM 3.11.2.3(a))

C. Particulates

1. Particulates With Half-Lives >8 days Ci 0.OOE+00 0.OOE+00 50%2. Average Release Rate For Period gCi/sec 0.OOE+00 0.OOE+00 3. Percent of Technical Specification Limit 2 % 0.OOE+00 0.OOE+00 (ODCM 3.11.2.3(a))

4. Gross Alpha Ci 0.OOE+00 0.OOE+00 D. Tritium 1. Total Release Ci 8.47E+01 1.14E+01 50%2. Average Release Rate For Period pCi/sec 1.07E+01 1.44E+00 3 3. Percent of Technical Specification Limit 2 % 3.85E-02 5.26E-03 (ODCM 3.11.2.3(a))

3 1. For batch releases, the estimated overall error is 10%.2. Iodine, Tritium, and Particulates are treated as a group. The percent TS Limit is based on most limiting nuclide and organ dose.27 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A-5 SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Units 3rd Quarter 4th Quarter Error'A. Fission and Activation Gases 1. Total Release Ci 6.51E-02 5.64E-02 50%2. Average Release Rate For Period pCi/sec 8.19E-03 7.1 OE-03 3. Percent of Technical Specification Limit % 2.64E-04 2.54E-04 (ODCM 3.11.2.2(a))

B. Iodine 1. Total Iodine-131 Ci 0.OOE+00 0.OOE+00 50%2. Average Release Rate For Period ptCi/sec 0.OOE+00 O.OOE+00 3. Percent of Technical Specification Limit 2 % 0.00E+00 0.OOE+00 (ODCM 3.11.2.3(a))

C. Particulates

1. Particulates With Half-Lives >8 days Ci 0.OOE+00 0.OOE+00 50%2. Average Release Rate For Period pCi/sec 0.OOE+00 0.OOE+00 3. Percent of Technical Specification Limit2 % 0.OOE+00 O.OOE+00 (ODCM 3.11.2.3(a))

4. Gross Alpha Ci 0.OOE+00 0.OOE+00 D. Tritium 1. Total Release Ci 7.38E+01 4.93E+00 50%2. Average Release Rate For Period pCi/sec 9.28E+00 6.20E-01 3. Percent of Technical Specification Limit2 % 3.35E-02 2.26E-03 (ODCM 3.11.2.3(a))

1. For batch releases, the estimated overall error is 10%.2. Iodine, Tritium, and Particulates are treated as a group. The percent TS Limit is based on most limiting nuclide and organ dose.28 i 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A-6 HOPE CREEK GENERATING STATION 3 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total 3 Units 3r Quarter 4t Quarter Error'A. Fission and Activation Gases 3 1. Total Release Ci O.OOE+00 3.64E-01 25%2. Average Release Rate For Period -pCi/sec O.OOE+00 4.58E-023 3. Percent of Technical Specification Limit % O.OOE+00 7.20E-04 (ODCM 3.11.2.2(a))

I B. Iodine 1. Total Iodine-131 Ci 7.09E-04 5.05E-04 25%2. Average Release Rate I For Period [tCi/sec 8.92E-05 6.35E-05 3. Percent of Technical 3 Specification Limit2 % 5.66E-02 4.46E-02 (ODCM 3.11.2.3(a))

C. Particulates

1. Particulates With Half-Lives >8 days Ci 1.04E-05 1.82E-05 25%2. Average Release Rate For Period pCi/sec 1.30E-06 2.29E-06 3. Percent of Technical Specification Limit 2 % 5.66E-02 4.46E-02 (ODCM 3.11.2.3(a))

4. Gross Alpha Ci O.OOE+00 0.OOE+00 D. Tritium 1. Total Release Ci O.OOE+00 0.OOE+00 25%2. Average Release Rate For Period ptCi/sec 0.OOE+00 0.OOE+00 i 3. Percent of Technical Specification Limit 2 % O.OOE+00 0.OOE+00 (ODCM 3.11.2.3(a))

3 1. For batch releases, the estimated overall error is 10%.2. Iodine, Tritium, and Particulates are treated as a group. The percent TS Limit is based i on most limiting nuclide and organ dose.29 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1B SALEM AND HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -DECEMBER 2011 GASEOUS EFFLUENTS

-ELEVATED RELEASES Salem and Hope Creek Generating Stations have no elevated release points.30 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE IC-1 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES I I i I Continuous Mode 1 st Quarter 2"d Quarter Nuclides Released 1. Fission Gases Argon-41 Xenon- 133 Xenon- 135 Total 2. Iodine Iodine-131 Total 3. Particulates Total 4. Tritium Batch Mode 1 st Quarter 2 d Quarter Units Ci Ci Ci Ci 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 3.07E-07 3.07E-07 0.OOE+00 0.0WE.+00 0.OOE+00 O.OOE+00 5.14E-07 5.14E-07 Ci Ci 5.59E-02 1.35E-02 0.OOE+00 6.94E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.39E-01 4.47E-02 2.39E-02 3.49E-05 6.87E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.71E-01 Ci O.OOE+00 Ci 1.72E+01 O.OOE+00 2.65E+01 I I I I I I U I I I I 31 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1C-2 SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES Continuous Mode 1 st Quarter 2 Quarter Batch Mode Nuclides Released Fission Gases Krypton-85 Xenon- 133M Xenon- 135 Argon-41 Xenon- 133 Total Units Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 1 st Quarter O.OOE+00 3.19E-04 O.OOE+00 1.03E-01 2.98E-02 1.33E-01 O.OOE+00 O.OOE+00 2 n Quarter 2.88E-04 3.27E-03 2.51E-02 4.15E-02 1.97E-01 2.67E-01 O.OOE+00 O.OOE+00 1.08E-01 2. Iodine Total 3. Particulates Total 4. Tritium Ci O.OOE+00 Ci O.OOE+00 Ci 2.63E+01 O.OOE+00 O.OOE+00 1.57E+/-01 I 6.98E-02 32 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1C-3 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES I I 3 I I I Nuclides Released Fission Gases Krypton 87 Xenon- 133 Xenon- 135 Total Continuous Mode Units I" Quarter 2nd Quarter Ci Batch Mode 1 st Quarter 2nd Quarter Ci 5.09E-02 2. Iodine Iodine-131 Iodine- 133 Total Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0.OOE+00 0.OOE+00 5.09E-02 6.41E-04 1.07E-02 1.13E-02 1.45E-05 0.OOE+00 1.89E-05 1.93E-05 0.OOE+00 O.OOE-00 0.OOE+00 O.OOE+oo 7.60E-04 1.32E-02 1.39E-02 4.58E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.58E-05 0.OOE-00 1.87E-04 3.53E-05 2.22E-04 0.OOE+00 O.OOE+00 O.OOE+00 1.11E-05 4.03E-06 O.OOE+00 0.OOE+00 1.51E-005 9.69E-04 o.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 3. Particulates Cobalt-60 Manganese-54 Molybdenum-99 Technicium-99 Total 0.OOE+/-0O 0.OOE+/-0O O.OOE+/-00 0.OOE+/-OO O.OOE+00 O.OOE+OO Ci 5.27E-05 Ci O.OOE+00 4. Tritium O.OOE+00 I U 3 U I I I I U I I I 33 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1C-4 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES Continuous Mode Units 3 rd Quarter 4 th Quarter Batch Mode 3 rd Quarter 4 th Quarter Nuclides Released Fission Gases Argon-41 Xenon- 133 Xenon-135 Total Ci Ci Ci Ci 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 4.02E-02 1.83E-02 6.86E-04 5.91E-02 1.75E-02 3.48E-02 0.OOE+00 5.23E-02 2. Iodine Total 3. Particulates Total 4. Tritium Ci O.OOE+00 Ci O.OOE+00 Ci 8.43E+01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.58E-01 1.10E+01 I 4.22E-01 34 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1C-5 SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES Continuous Mode 3 rd Quarter 4 th Quarter Batch Mode 3 rd Quarter 4 th Quarter Nuclides Released Fission Gases Xenon-133M Xenon- 133 Argon-41 Total Units Ci Ci Ci Ci 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.23E-04 2.5 1E-02 3.98E-02 6.51E-02 0.OOE+00 1.79E-02 3.85E-02 5.64E-02 2. Iodine Total 3. Particulates Total 4. Tritium Ci O.OOE+00 Ci O.OOE+00 Ci 7.36E+01 O.OOE+00 O.OOE+00 4.81E+00 O.OOE+00 O.OOE+00 1.44E-01 O.OOE+O0 O.OOE+O0 1.19E-01 I I I I I I I I I I 35 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1C-6 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 EFFLUENTS

-GROUND LEVEL RELEASES GASEOUS Continuous Mode 3 rd Quarter 4 th Quarter Batch Mode 3 Quarter 4 th Quarter Nuclides Released 1. Fission Gases Krypton-85 Xenon- 135 Total 2. Iodine Iodine-131 Iodine- 133 Total 3. Particulates Othera Cobalt-60 Cerium- 144 Telerium-132 Molybdenum-99 Technicium-99 Total Units Ci Ci O.OOE+0O O.OOE+00 Ci O.OOE+00 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 7.09E-04 1.39E-02 1.46E-02 O.OOE+00 9.04E-06 1.33E-06 1.OOE-05 3.74E-06 3.81E-06 2.80E-05 1.08E-01 2.56E-01 3.64E-01 5.05E-04 1.09E-02 1.14E-02 6.7 1E-07 1.43E-05 3.2 1E-06 O.OOE+00 0.OOE+00 0.OOE+00 1.82E-05 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 4. Tritium Ci O.OOE+00 O.OOE+00 I O.OOE+00 a "Other" was assigned to an unconfirmed peak appearing in the gamma analysis of a fourth quarter effluent sample. Doses associated with the activity were assessed using the most conservative dose conversion factors listed in the ODCM.36 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2A-1 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Error Units 1 st Quarter 2 d Quarter A. Fission and Activation Products 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification.

Limit (ODCM 3.11.1.2(a))

B. Tritium 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.1)C. Dissolved and Entrained Noble Gases 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.1)D. Gross Alpha Total Release E. Volume of Waste Release (Prior to Dilution)F. Volume of Dilution Water Used During Entire Period Ci 3.90E-03 gCi/ml 9.30E- 12% 8.59E-04 Ci 2.23E+02[ICi/ml 5.32E-07 6.90E-03 25%1.55E-11 6.47E-04 1.21E+02 25%2.72E-07 2.72E-02 2.80E-05 25%6.28E-14 3.14E-08 U I I I I I I I 3 I i I 3% 5.32E-02 Ci 1.77E-04 jtCi/ml 4.21E-13% 2.11E-07 Ci O.OOE+00 0.OOE+00 25%Liters 5.24E+07 Liters 4.19E+ 11 5.18E+07 4.46+11 37 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2A-2 SALEM GENERATING STATION- UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUALREPORT JANUARY -JUNE 2011 LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Error Units 1 st Quarter 2nd Quarter A. Fission and Activation Products 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.2(a))

B. Tritium 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.1)C. Dissolved and Entrained Noble Gases 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.1)D. Gross Alpha Total Release E. Volume of Waste Release (Prior to Dilution)F. Volume of Dilution Water Used During Entire Period Ci 2.48E-03 4.46E-03 25%LCi/ml 5.53E-12 1.37E-11% 7.51E-04 1.31E-03 Ci 1.70E+02 1.14E+02 25%gCi/ml 3.80E-07 3.50E-07% 3.80E-02 3.50E-02 Ci 2.17E-04 O.OOE+00 25%jtCi/ml 4.84E- 13 0.OOE+00% 2.42E-07 O.OOE+00 Ci O.OOE+00 0.OOE+00 25%Liters 4.99E+07 5.07E+07 Liters 4.48E+1 1 3.26E+1 1 38 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2A-3 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Error Units 1 st Quarter 2nd Quarter A. Fission and Activation Products 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.2(a))

B. Tritium 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.1.1.1)C. Dissolved and Entrained Noble Gases 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.1)D. Gross Alpha Total Release E. Volume of Waste Release (Prior to Dilution)F. Volume of Dilution Water Used During Entire Period Ci 4.27E-03 piCi/m1 3.49E-10% .60E-04 Ci 5.12E+/-00 jtCi/ml 4.18E-07% 4.18E-02 Ci 5.06E-06 pCi/ml 4.13E-13,% 2.06E-07 Ci 0.OOE+00 8.15E-03 25%5.54E-10 4.75E-04 4.49E+00 25%3.05E-07 3.05E-02 4.05E-06 25%2.75E-13 1.37E-07 O.OOE+00 25%I U I I I U I I I I I I I I I Liters 4.6iE+07, 5.07E+07 Liters 1.22E+10 1.47E+10 39 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2A-4 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Error Units 3 rd Quarter 4 th Quarter A. Fission and Activation Products 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.2(a))

B. Tritium 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.1)C. Dissolved and Entrained Noble Gases 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.1)D. Gross Alpha Total Release E. Volume of Waste Release (Prior to Dilution)F. Volume of Dilution Water Used During Entire Period Ci 3.13E-03 7.78E-03 ptCi/ml 7.02E- 12 2.62E-1 I% 1.06E-03 2.48E-03 Ci 2.66E+02 2.33E+02 25%25%p.Ci/ml 5.98E-07 7.83E-07% 5.98E-02 7.83E-02 Ci 1.41E-05 1.57E-05 25%p.Ci/ml 3.16E-14% 1.58E-08 5.29E-14 2.64E-08 Ci O.OOE+00 0.OOE+00 25%Liters 5.17E+07 4.46E+07 Liters 4.46E+11 2.97E+11 40 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2A-5 SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Error Units 3 rd Quarter 4th Quarter A. Fission and Activation Products 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.2(a))

B. Tritium 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.1)C. Dissolved and Entrained Noble Gases 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.1)D. Gross Alpha Total Release E. Volume of Waste Release (Prior to Dilution)F. Volume of Dilution Water Used During Entire Period Ci 1.87E-03 5.09E-03 25%ýiCi/ml 3.83E-12 1.1OE-11% 4.86E-04 5.37E-04 Ci 1.32E+02 1.43E+02 25%piCi/ml 2.69E-07 3.09E-07% 2.69E-02 3.09E-02 I 3 I U I I I I 3 I U I I Ci 1.14E-04 7.12E-06 25%ptCi/ml 2.33E-13 1.54E-14% 1.16E-07 7.70E-09 Ci O.OOE+00 O.OOE+00 25%Liters 5.1 OE+07 5.12E+07 Liters 4.89E+1 1 4.62E+1 1 41 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2A-6 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Error Units 3d Quarter th 4 Quarter A. Fission and Activation Products 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.2(a))

B. Tritium 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.1)C. Dissolved and Entrained Noble Gases 1. Total Release 2. Average Diluted Concentration

3. Percent of Technical Specification Limit (ODCM 3.11.1.1)D. Gross Alpha Total Release E. Volume of Waste Release (Prior to Dilution)F. Volume of Dilution Water Used During Entire Period Ci 6.OOE-03 1.26E-02ýCi/ml 3.04E-10 9.90E-10% 5.06E-04 2.03E-03 Ci 6.85E+00 1.21E+01 25%25%pCi/ml 3.47E-07 9.49E-07% 3.47E-02 9.49E-02 Ci 25%1.63E-05 2.40E-05ýtCi/ml 8.25E-13 1.88E-12% 4.12E-07 9.40E-07 Ci 0.OOE+00 0.OOE+00 25%Liters 5.18E+07 3.84E+07 Liters 1.97E+10 1.28E+10 42 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2B-1 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 LIQUID EFFLUENTS Continuous Mode Units 1 st Quarter 2 nd Quarter Batch Mode Ist Quarter 2 nd Quarter Nuclides Released 1. Fission and Activation Products Arsenic-76 Cobalt-57 Cobalt-58 Cobalt-60 Chromium-51 Cesium- 134 Cesium- 137 Iron-59 Manganese-54 Niobium-95 Niobium-97 Ruthenium

-105 Antimony-125 Tin-113 Tin- 117M Technicium-101 Tellurium-132 Yiyttrium-91M Total Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0.OOE+00 0.'OOEO00 0.OOE+00 0.OOEO00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 2.56E-06 7.45E-04 1.91E-03 0.OOE+00 1.12E-06 1.18E-03 0.OOE+00 2.01E-05 0.OOE+00 8.40E-06 8.92E-06 9.54E-06 0.OOE+00 0.OOE+00 3.18E-06 2.31E-06 5.60E-06 3.90E-03 9.33E-06 9.62E-06 5.29E-03 6.89E-04 2.88E-04 8.61E-07 3.82E-04 1.17E-04 3.66E-05 4.20E-05 4.04E-06 0.OOE+00 1.33E-06 1.11E-05 1.93E-05 0.OOE+00 0.OOE+00 0.OOE+00 6.90E-03 I I I I I I I 1 I I I I 2. Tritium Ci 6.31E-01 2.82E-01 2.22E+02 1.21E+02 3. Dissolved and Entrained Noble Gases Xenon- 133 Xenon- 135 Total 4. Gross Alpha Ci Ci Ci 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 1.70E-04 6.41E-06 1.77E-04 2.80E-05 0.OOE+00 2.80E-05 O.OOE+00 O.OOE+00 O.0OE+00 O.OOE+00 43 I 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2B-2 SALEM GENERATING STATION -UNIT 2 EFFLUENTS.

AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 LIQUID EFFLUENTS Continuous Mode Units 1 st Quarter 2 nd Quarter Batch Mode 1st Quarter 2nd Quarter Nuclides Released 1. Fission and Activation Products Silver-110M Barium-140 Cobalt-57 Cobalt-58 Cobalt-60 Chromium-51 Cesium- 134 Cesium-137 Iron-59 Manganese-54 Niobium-95 Niobium-97 Ruthenium-103 Antimony-125 Tin- 117M Total Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.0OE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 1.74E-05 9.85E-06 5.63E-06 6.12E-04 1.60E-03 0.OOE+00 4.34E-06 6.61E-05 0.OOE+00 1.02E-04 0.OOE+00 2.21E-05 2.69E-06 3.85E-05 0.OOE+00 2.48E-03 0.OOE+00 0.00-E00 1.48E-05 3.88E-03 1.79E-04 2.21E-04 0.OOE+00 8.67E-06 7.41E-05 1.86E-05 3.62E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.69E-05 4.45E-03 2. Tritium Ci 2.34E-01 1.57E-01 1.70E+02 1.14E+02 3. Dissolved and Entrained Noble Gases Xenon-133 Xenon-138 Total 4. Gross Alpha Ci Ci Ci 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 1.77E-04 3.99E-05 2.17E-04 0.OOE+00 0.OOE+00 O.OOE+00 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 44 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2B-3 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 LIQUID EFFLUENTS Continuous Mode Units 1 st Quarter 2 nd Quarter Batch Mode Ist Quarter 2 nd Quarter Nuclides Released 1. Fission and Activation Products Silver-110M Arsenic-76 Cerium-141 Cobalt-57 Cobalt-58 Cobalt-60 Chromium-51 Cesium- 137 Iron-59 Lanthanum-140 Lanthanum-142 Manganese-54 Niobium-95 Niobium-97 Ruthenium-103 Strontium-92 Zinc-65 Zinc-69M Total Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 1.OOE-05 6.16E-08 9.98E-06 O.OOE+00 2.07E-04 1.87E-03 2.87E-04 8.33E-08 8.28E-05 2.27E-05 2.51E-06 1.52E-03 2.47E-06 0.OOE+00 3.66E-06 8.53E-06 2.50E-04 0.OOE+00 4.27E-03 1.69E-05 0.OOE+00 5.12E-05 3.94E-07 2.71E-04 4.62E-03 6.13E-05 0.OOE+00 0.OOE+00 2.26E-05 0.OOE+00 1.83E-03 O.OOE+00 8.40E-06 0.OOE+00 3.16E-06 1.26E-03 7.65E-07 8.15E-03 I I I I I I I I 3 I I I I U I I I 2. Tritium Ci 9.77E-03 1.41E-01 5.11E+00 4.35E+00 3. Dissolved and Entrained Noble Gases Krypton-85M Krypton-88 Xenon- 135 Total 4. Gross Alpha Ci Ci Ci Ci O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.06E-06 5.06E-06 3.65E-07 1.25E-06 2.43E-06 4.05E-06 Ci O.OOE+00 O.OOE+00 45 O.OOE+00 O.OOE+00 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2B-4 SALEM GENERATING STATION -UNIT 1 EFFENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 LIQUID EFFLUENTS Continuous Mode Units 3 rd Quarter 4th Quarter Batch Mode 3 rd Quarter 4 th Quarter Nuclides Released Fission and Activation Products Silver-110m Cobalt:57 Cobalt-58 Cobalt-60 Chromium-51 Cesium-137 Iron-59 Lanthanam-142 Manganese-54 Niobium-85 Niobium-97 Antimony-125 Tin-I 17M Total Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.0OE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.0OE+00 0.OOE+00 8.61E-06 2.36E-03 6.78E-04 0.OOE+00 4.44E-05 0.OOE+00 6.40E-06 5.09E-06 0.OOE+00 6.08E-06 1.60E-05 0.OOE+00 3.13E-03 2.20E-04 1.45E-05 6.28E-03 9.17E-04 6.22E-05 0.OOE+00 4.74E-05 7.31E-05 4.09E-05 2.44E-05 5.21E-05 4.86E-05 3.26E-06 7.78E-03 2. Tritium Ci 9.86E-02 3.92E-02 2.66E+02 2.33E+02 3. Dissolved and Entrained Noble Gases Krypton-85M Xenon- 133 Total 4. Gross Alpha Ci Ci Ci 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 1.71E-06 1.24E-05 1.41E-05 0.OOE+00 1.57E-05 1.57E-05 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 46 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2B-5 SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 LIQUID EFFLUENTS Continuous Mode Units 3d Quarter 4 th Quarter Batch Mode 3 rd Quarter 4 th Quarter Nuclides Released Fission and Activation Products Silver-110m Barium- 139 Cobalt-57 Cobalt-58 Cobalt-60 Chromium-51 Cesium- 137 Iron-59 Manganese-54 Niobium-95 Niobium-97 Ruthenium-105 Tin- 117M Tungsten-187 Yittrium-91M Total 2. Tritium 3'. Dissolved and Entrained Noble Gases Xenon- 131M Xenon-133 Total 4. Gross Alpha Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.0OE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 6.87E-02 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 9.60E-06 1.67E-06 1.61E-03 1.68E-04 1.88E-05 2.98E-06 0.OOE+00 9.1OE-06 0.OOE+00 2.70E-05 6.1OE-06 0.OOE+00 1.37E-05 8.18E-06 1.87E-03 4.24E-05 0.OOE+00 1.19E-05 4.49E-03 3.04E-04 4.37E-05 0.OOE+00 1.46E-06 1.41E-04 9.2 1E-06 2.56E-05 0.OOE+00 1.04E-05 0.OOE+00 0.OOE+00 5.09E-03 I I I U I I I I I U I I I I I Ci 1.83E-02 1.32E+02 1.43E+02 Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+O0 9.42E-05 1.99E-05 1.14E-04 0.OOE+00 7.12E-06 7.12E-06 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 47 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2B-6 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units 3 rd Quarter 4 th Quarter 3 rd Quarter 4 th Quarter Fission and Activation Products Cerium-141 Ci O.OOE+00 O.OOE+00 4.03E-06 1.07E-04 Cerium-143 Ci O.OOE+00 O.OOE+00 1.30E-06 0.OOE+00 Cobalt-58 Ci O.OOE+00 O.OOE+00 8.26E-05 4.38E-04 Cobalt-60 Ci O.OOE+00 0.OOE+00 3.98E-03 7.78E-03 Chromium-51 Ci O.OOE+00 O.OOE+00 8.25E-05 O.OOE+00 Iron-59 Ci 0.OOE+00 0.OOE+00 8.11E-06 O.OOE+00 Lanthanum-140 Ci 0.OOE+00 O.OOE+00 O.OOE+00 3.87E-05 Manganese-54 Ci 0.OOE+00 O.OOE+00 1.17E-03 1.63E-03 Sodium-24 Ci O.OOE+00 O.OOE+00 O.OOE+00 7.53E-06 Niobium-97 Ci O.OOE+00 O.OOE+00 3.76E-06 9.50E-06 Ruthenium-105 Ci O.OOE+00 0.OOE+00 O.OOE+00 4.55E-06 Antimony-125 Ci 0.OOE+00 1.05E-04 0.OOE+00 0.OOE+00 Zinc-65 Ci 0.OOE+00 0.OOE+00 6.58E-04 2.51E-03 Zinc-69M Ci 0.OOE+00 O.OOE+00 4.08E-06 1.33E-06 Total Ci 0.OOE+00 1.05E-04 6.OOE-03 1.25E-02 2. Tritium Ci 2.99E-01 5.26E-02 I 6.55E÷00 1.21E+01 3. Dissolved and Entrained Noble Gases Krypton-85M Ci 0.OOE+00 0.OOE+00 1.98E-06 0.OOE+00 Krypton-87 Ci 0.OOE+00 O.OOE+00 3.38E-06 0.OOE+00 Xenon-133 Ci 0.OOE+00 O.OOE+00 5.20E-06 7.80E-06 Xenon-135 Ci 0.OOE+00 O.OOE+00 5.73E-06 1.62E-05 Total Ci O.OOE+00 O.OOE+00 1.63E-05 2.40E-05 4. Gross Alpha Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 48 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3A-1 SALEM GENERATING STATION -UNITS 1 AND 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)SGS 6-Month Est. Total 1A. Type of Waste (Class A) Units' Period Error a. Resins, Filters, & Evap Bottoms m 3 1.46E+01 25%Ci. 1.59E+00 b. Dry Active Waste -DAW m 3 3.14e+02 25%Ci 6.05E-01 c. Irradiated Components m 3 0.OOE+00 25%Ci O.OOE+00 d. Other Waste m 3 3.79E+01 25%NRW Resin/Resin Fines Ci 2.83E-01 SGS lB. Type of Waste (Class B)a. Resins, Filters, & Evap Bottoms m 3 5.24E+00 25%Ci 1.46E+02 25%b. Dry Active Waste -DAW m J 0.OOE+00 25%Ci O.OOE+00 25%c. Irradiated Components m 3 O.OOE+00 25%Ci O.OOE+00 25%d. Other Waste m 3 O.OOE+00 25%Ci O.OOE+00 25%'Volumes are measured, activities are estimated I I I I I I I I I 1 I I 49 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 2A. Estimate of Major Nuclide Composition

(>1%) (Class Resins, Filters, Evaporator Bottoms Nuclides % I Ci A) -SGS Dry Active Waste% Ci Tritium Iron-55 Cobalt-58 Cobalt-60 Nickel-63 Antimony-125 Cesium- 137 23.76 31.96 3.78 9.35 22.53 4.02 3.78E-01 5.08E-01 6.01E-02 1.49E-0 1 3.58E-01 6.39E-02 5,.05E-02 3.23 30.10 27.45 7.81 22.77 4.97 1.95E-02 1.82E-01 1.66E-01 4.73E-02 1.38E-01 3.01E-02 3.18 2A. Estimate of Major Nuclide Composition

(>1%) (Class Resins, Filters, Evaporator Bottoms B)-SGS Other Waste -NRW Resin/Resin Fines Nuclides Tritium Manganese 54 Iron-55 Cobalt-58 Cobalt-60 Nickel-63 Antimony-125 Cesium 134 Cesium-137 Cerium- 144 2.34 15.40 19.93 39.46 1.24 17.48 2.84 Ci 3.41E+00 2.24E+0 1 2.90E+01 5.74E+01 1.81E+00 2.54E+-1 4.13E+00 4.33 35.94 8.54 10.03 31.46 6.80 Ci 1.22E-02 1.02E-01 2.41E-01 2.83E-02 8.89E-02 1.92E-02 3A. Solid Waste Disposal-SGS Number of Mode of Shipments Transportation 5 Truck 6 Truck Destination Barnwell, SC Memphis, TN Type of Containers HIC Seavan 50 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3A-2 SALEM GENERATING STATION -UNITS 1 AND 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)SGS 1A. Type of Waste (Class A)a. Resins, Filters, Evaporator Bottoms Units 1 m3 Ci 6-Month Period O.OOE+00 0.OOE+00 Est. Total Error 25%b. Dry Active Waste- DAW-U-NA m 3 3.74E+02 25%Ci :1.23E+00 c. Irradiated Components m 3 O.OOE+00 25%Ci 0.OOE+00 d. Other Waste m 3 3.32E+01 25%Ci 1.21E+00 SGS lB. Type of Waste (Class B)a. Resins, Filters, Evaporator Bottoms m 3 O.OOE+00 25%Ci O.OOE+00 b. Dry Active Waste- DAW-U-NA mI 0.OOE+00 25%Ci 0.OOE+00 c. Irradiated Components m 3 0.OOE+00 25%Ci O.OOE+00 d. Other Waste m 3 0.OOE+00 25%Ci O.OOE+00 lVolumes are measured, activities are estimated I U I I I U I I I I I I I I I U I I U 51 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 2A. Estimate of Major Nuclide Composition

(>1%) (Class A) -SGS Dry Active Waste Other Wastes Nuclides H-3 Iron-55 Cobalt-57 Cobalt-58 Cobalt-60 Nickel-63 Cesium-137

%/Ci%/Ci 2.77 3.40E-02 2.40 2.89E-02 39.05 21.67 7.52 20.79 4.73 4.80E-01 2.66E-0 1 9.24E-02 2.56E-01 5.82E-02 49.41 13.32 7.48 19.61 4.68 5.96E-01 1.61E-01 9.02E-02 2.37E-01 5.65E-02 2B. Estimate of Major Nuclide Composition

(>1%) (Class B) -SGS Resins, Filters, Evaporator Bottoms Nuclides %Iron-55 Cobalt-60 Nickel-63--C {3A. Solid Waste Disposal-SGS Number of Shipments 6 Mode of Transportation Truck Destination Memphis, TN Type of Containers Seavan 52 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3B-1 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)HCGS 1A. Type of Waste (Class A)Units'6-Month Est. Total Period Error a. Resins, Filters, Evaporator Bottoms m 3 7.90E+O1 25%Ci 2.55E+02 b. Dry Active Waste -scrap metal m 3 1.25E+02 25%Ci 5.49E-02 c. Irradiated Components m 3 0.OOE+00 25%Ci 0.OOE+00 d. Other Waste m 3 8.33E+00 25%Ci 3.11E-04'Volumes are measured, activities are estimated 2A. Estimate of Major Nuclide Composition

(>1%)Resins, Filters and Evaporator Bottoms Nuclides % Ci (Class A) -HCGS Dry Active Waste I N I I I I I I I N I I I I I I I Ci Iron-55 Cobalt-60 Nickle-63 Manganese-54 80.05 13.95 1.58 2.74.04E+02 3.56E+01 4.05E+00 7.OOE+00 4917 43.46 5.55 2.70E02 2.38E-02 3.05E-03 Other Wastes I I Ci Nuclides Iron-55 Cobalt-60 86.59 11.51 2.70E-04 3.58E-05 Destination Barnwell, SC Memphis, TN Kingston, TN 3A. Solid Waste Disposal-HCGS Number of Mode of Shipments Transportation 16 Truck 4 Truck 2 Truck Type of Containers HIC Seavan Seavan 53 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 3B-2 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)HCGS 1A. Type of Waste (Class A)Units" 6-Month Period Est. Total Error a. Resins, Filters, Evaporator Bottoms m 3 O.OOE+00 25%Ci O.OOE+00 b. Dry Active Waste m 3 3.40E+02 25%Ci 1.91E-01 c. Irradiated Components m 3 O.OOE+00 25%Ci 0.OOE+00 d. Other Waste m 3 0.OOE+00 25%Ci O.OOE+00 Volumes are measured, activities are estimated HCGS 6-Month Est. Total lB.. Type of Waste (Class C) Units' Period Error a. Resins, Filters, Evaporator Bottoms m 3 O.OOE+00 25%Ci O.OOE+00 b. Dry Active Waste m 3 0.OOE+00 25%Ci 0.OOE+00 c. Irradiated Components m 3 5.85E-01 25%Ci 4.09E+04 d. Other Waste m 3 1.43E+00 25%Ci 1.98E+02 Volumes are measured, activities are estimated 2A. Estimate of Major Nuclide Composition

(>1%) (Class A) -HCGS Dry Active Waste% I Ci Nuclides Manganese-54 Iron-55 Cobalt-60 Nickel-63 7.74 36.06 54.02 1.00 1.4E-02 6.89E-02 1.03E-01 1.92E+03 2B. Estimate of Major Nuclide Composition

(>1%) (Class C) -HCGS 54 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Irradiated Components Other Waste Nuclides Manganese-54 Iron-55 Cobalt-60 Nickel-63 Ci Ci 4 4- 4 1.48 46.24 45.48 6.10 6.05E+02 1.89E+04 1.86E+04 2.49E+03 1.69 56.82 38.41 2.08 3.34E+00 1.12E+02 7.59E+01 4.12E+00 3A. Solid Waste Disposal-HCGS Number of Mode of Shipments Transportation 4 Truck Destination Bamwell, SC Memphis, TN Type of Containers Seavan Seavan 8 Truck I I I I I I I I I I I I I 1 I I I I I 55 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 4A-1 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE 1 2 3 4 5 6 7 8 BATCH RELEASES ONLY Dates: January 1, 2011-Type of release: Number of releases during quarter: Total time duration for all releases of type listed above: Maximum duration for release of type listed above: Average duration for release of type listed above: Minimum duration for release of type listed above: Average stream flow (dilution flow) during period of release: March 31, 2011 Gaseous 171 1.43E+04 1.98E+02 8.39E+01 4.50E+O 1 N/A Min.Min.Min.Min.BATCH RELEASES ONLY 1. Dates: April 1, 2011 -June 30, 2011 2. Type of release: Gaseous 3. Number of releases during quarter: 147 4. Total time duration for all releases of type listed above: 1.17E+04 Min.5. Maximum duration for release of type listed above: 1.93E+02 Min.6. Average duration for release of type listed above: 7.95E+O1 Min.7. Minimum duration for release of type listed above: 2.50E+01 Min.8. Average stream flow (dilution flow) during period of release: N/A 56 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 4A-1 (continued)

SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -SEPTEMBER 2011

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1. Dates: July 1, 2011- September 30, 2011 2. Type of release: Gaseous 3. Number of releases during quarter: 121 4. Total time duration for all releases of type listed above: 9.47E+03 Min.5. Maximum duration for release of type listed above: 1.80E+02 Min.6. Average duration for release of type listed above: 7.82E+01 Min.7. Minimum duration for release of type listed above: 2.80E-01 Min.8. Average stream flow (dilution flow) during period of release: N/A BATCH RELEASES ONLY 1. Dates: October 1, 2011 -December 31, 2011 2. Type of release: Gaseous 3. Number of releases during quarter: 122 4. Total time duration for all releases of type listed above: 3.12E04 Min.5. Maximum duration for release of type listed above: 3.28E+03 Min.6. Average duration for release of type listed above: 2.56E+02 Min.7. Minimum duration for release of type listed above: 1.40E+01 Min.8. Average stream flow (dilution flow) during period of release: N/A 57 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 4A-2 SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1. Dates: January 1, 2011 -March 31, 2011 2. Type of release: Gaseous 3. Number of releases during quarter: 159 4. Total time duration for all releases of type listed above: 1.13E+04 Min.5. Maximum duration for release of type listed above: 1.31E+02 Min.6. Average duration for release of type listed above: 7.09E++/-O Min.7. Minimum duration for release of type listed above: 3.50E+01 Min.8. Average stream flow (dilution flow) during period of release: N/A BATCH RELEASES ONLY 1. Dates: April 1, 2011 -June 30, 2011 2. Type of release: Gaseous 3. Number of releases during quarter: 107 4. Total time duration for all releases of type listed above: 8.69E+03 Min.5. Maximum duration for release of type listed above: 1.70E+02 Min.6. Average duration for release of type listed above: 8.12E+01 Min.7. Minimum duration for release of type listed above: 1.50E+01 Min.8. Average stream flow (dilution flow) during period of release: N/A 58 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 4A-2 (continued)

SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -DECEMBER 2011

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE 1 2 3.4 5 6 7.8.BATCH RELEASES ONLY Dates: July 1,2011 -Sept Type of release: Number of releases during quarter: Total time duration for all releases of type listed above: Maximum duration for release of type listed above: Average duration for release of type listed above: Minimum duration for release of type listed above:* Average stream flow (dilution flow) during period of release: tember 30, 2011 Gaseous 106 7.59E+03 1.22E+02 7.16E+01 7.OOE+00 N/A Min.Min.Min.Min.BATCH RELEASES ONLY 1. Dates: October 1, 2011 -December 31, 2011 2. Type of release: Gaseous 3. Number of releases during quarter: 94 4. Total time duration for all releases of type listed above: 6.28E+03 Min.5. Maximum duration for release of type listed above: 1.12E+02 Min.6. Average duration for release of type listed above: 6.68E+01 Min.7. Minimum duration for release of type listed above: 4.10E+01 Min.8. Average stream flow (dilution flow) during period of release: N/A 59 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 4A-3 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1. Dates: January 1, 2011 -March 31,2011 2. Type of release: Gaseous 3. Number of releases during, quarter: 2 4. Total time duration for all releases of type. listed above: 2.15E+03 Min.5. Maximum duration for release of type listed above: 1.39E+03 Min.6. Average duration for release of type listed above: 1.07E+03 Min.7. Minimum duration for release of type listed above: 7.62E+02 Min.8. Average stream flow (dilution flow) during period of release: N/A BATCH RELEASES ONLY 1. Dates: April 1, 2011 -June 30, 2011 2. Type of release: Gaseous 3. Number of releases during quarter: 0 4. Total time duration for all releases of type listed above: 0.OOE+00 Min.5. Maximum duration for release of type listed above: O.OOE+00 Min.6. Average duration for release of type listed above: 0.OOE+00 Min.7. Minimum duration for release of type listed above: 0.OOE+00 Min.8. Average stream flow (dilution flow) during period of release: N/A 60 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 4A-3 (continued)

HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1. Dates: July 1, 2011 -September 30,2011 2. Type of release: Gaseous 3. Number of releases during quarter: 0 4. Total time duration for all releases of type listed above: O.OOE+00 Min.5. Maximum duration for release of type listed above: 0.OOE+00 Min.6. Average duration for release of type listed above: 0.OOE+00 Min.7. Minimum duration for release of type listed above: 0.OOE+00 Min.8. Average stream flow (dilution flow) during period of release: N/A, 1 2 3 4 5 6 7 8 BATCH RELEASES ONLY Dates: October 1,2011 -Dec Type of release: Number of releases during quarter: Total time duration for all releases of type listed above: Maximum duration for release of type listed above:.Average duration for release of type listed above: Minimum duration for release of type listed above: Average stream flow (dilution flow) during period of release::ember 31, 2011 Gaseous 0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 N/A Min.Min.Min.Min.61 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 4B-1 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1. Dates: January 1, 2011 -March 31, 2011 2. Type of release: Liquid 3. Number of releases during quarter: 42 4. Total time duration for all releases of type listed above: 6.44E+03 Min.5. Maximum duration for release of type listed above: 4.37E+02 Min.6. Average duration for release of type listed above: 1.53E+02 Min.7. Minimum duration for release of type listed above: 1.00E+00 Min.8. Average stream flow (dilution flow) during period of release: 8.44E+05 GPM 1 2 3 4 5 6 7 8 BATCH RELEASES ONLY Dates: April 1, 2011 Type of release: Number of releases during quarter: Total time duration for all releases of type listed above: Maximum duration for release of type listed above: Average duration for release of type listed above: Minimum duration for release of type listed above: Average stream flow (dilution flow) during period of release:-June 30, 2011 Liquid 44 8.41E+03 4.19E+02 1.91E+02 1.00E+00E 8.97E+05 Min.Min.Min.Min.GPM 62 I 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT I TABLE 4B-1 (continued)

SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED 3 IN A BATCH MODE BATCH RELEASES ONLY 1. Dates: July 1,2011 -September 30, 2011 2. Type of release: Liquid 3 3. Number of releases during quarter: 28 4. Total time duration for all releases of type listed above: 7.98E+03 Min.5. Maximum duration for release of type listed above: 5.79E+02 Min.6. Average duration for release of type listed above: 2.85E+02 Min.7. Minimum duration for release of type listed above: 1.00E+00 Min.8. Average stream flow (dilution flow) during period of release: 8.97E+05 GPM I BATCH RELEASES ONLY I 1. Dates: Octoberl, 2011 -December 31, 2011 2. Type of release: Liquid I 3. Number of releases during quarter: 42 3 4. Total time duration for all releases of type listed above: 1.53E+04 Min.5. Maximum duration for release of type listed above: 1.26E+/-03 MinI 6. Average duration for release of type listed above: 3.65E+02 Min.7. Minimum duration for release of type listed above: 1.58E+01 Min.8. Average stream flow (dilution flow) during period of release: 5.97E+05 GPM I I 633 I 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 4B-2 SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1. Dates: January 1,2011 -March 31, 2011 1 2. Type of release: Liquid 3. Number of releases during quarter: 14 4. Total time duration for all releases of type listed above: 5.01E+03 Min.£ 5. Maximum duration for release of type listed above: 4.75E+/-02 Mi.6. Average duration for release of type listed above: 3.58E+02 Min.7. Minimum duration for release of type listed above: 2.7 1E+02 Min.3 8. Average stream flow (dilution flow) during period of release: 8.97E+05 GPM BATCH RELEASES ONLY 1. Dates: April 1, 2011 -June 30, 2011 2. Type of release: Liquid 3. Number of releases during quarter: 24 4. Total time duration for all releases of type listed above: 9.82E+03 Min.5. Maximum duration for release of type listed above: 9.90E+02 Min.6. Average duration for release of type listed above: 4.09E+02 Min.7. Minimum duration for release of type listed above: 1.50E+01 Min.8. Average stream flow (dilution flow) during period of release: 6.55E+05 GPM 64 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 4B-2 (continued)

SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1. Dates: July 1,2011 -September 30, 2011 2. Type of release: Liquid 3. Number of releases during quarter: 15 4. Total time duration for all releases of type listed above: 5.13E+03 Min.5. Maximum duration for release of type listed above: 5.06E+02 Min.6. Average duration for release of type listed above: 3.42E+02 Min.7. Minimum duration for release of type listed above: 1.00E+00 Min.8. Average stream flow (dilution flow) during period of release: 9.81E+05 GPM BATCH RELEASES ONLY 1. Dates: October 1,2011 -December 31, 2011 2. Type of release: Liquid 3. Number of releases during quarter: 18 4. Total time duration for all releases of type listed above: 5.93E+03 Min.5. Maximum duration for release of type listed above: 4.82E+02 Min.6. Average duration for release of type listed above: 3.29E+02 Min.7. Minimum duration for release of type listed above: 2.OOE+01 Min.8. Average stream flow (dilution flow) during period of release: 9.28E+05 GPM 65 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 4B-3 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2011

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1. Dates: January 1, 2011-March 31, 2011 2. Type of release: Liquids 3. Number of releases during quarter: 25 4. Total time duration for all releases of type listed above: 1.81E+03 Min.5. Maximum duration for release of type listed above: 8.70E+01 Min.6. Average duration for release of type listed above: 7.25E+01 Min.7. Minimum duration for release of type listed above: 3.60E+01 Min.8. Average stream flow (dilution flow) during period of release: 2.46E+04 GPM BATCH RELEASES ONLY 1. Dates: April 1,2011 -June 30, 2011 2. Type of release: Liquid 3. Number of releases during quarter: 26 4. Total time duration for all releases of type listed above: 1.91E+03 Min.5. Maximum duration for release of type listed above: 8.48E+01 Min.6. Average duration for release of type listed above: 7.34E+01 Min.7. Minimum duration for release of type listed above: 4.5 1E+01 Min.8. Average stream flow (dilution flow) during period of release: 2.96E+04 GPM 66 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 4B-3 (continued)

HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2011

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1. Dates: July 1,2011 -September 30, 2011 2. Type of release: Liquid 3. Number of releases during quarter: 41 4. Total time duration for all releases of type listed above: 2.83E+03 Min.5. Maximum duration for release of type listed above: 9.OOE+01 Min.6. Average duration for release of type listed above: 6.90E+01 Min.7. Minimum duration for release of type listed above: 3.OOE+00 Min.8. Average stream flow (dilution flow) during period of release: 3.97E+04 GPM BATCH RELEASES ONLY 1. Dates: October 1, 2011 -December 31, 2011 2. Type of release: Liquid 3. Number of releases during quarter: 23 4. Total time duration for all releases of type listed above: 1.67E+03 Min.5. Maximum duration for release of type listed above: 8.33E+01 Min.6. Average duration for release of type listed above: 7.24E+01 Min.7. Minimum duration for release of type listed above: 4.08E+01 Min.8. Average stream flow (dilution flow) during period of release: 2.56E+04 GPM 67 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT" APPENDIX A I* METEOROLOGICAL

DATA I U I I I I I I I I I 3 68 1 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT U U Lapse Rate Wind Distributions 300- 33 foot , 1/2011 -3/2011 u 69 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (01)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: LE -1.90 DEG C/100M, STABILITY CLASS A TOTAL HOURS WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 0 0 0 4 3 0 0 0 7 11.25 -33.75 NNE 0 0 0 0 0 1 0 0 0 0 0 1 33.75 -56.25 NE 0 0 0 0 0 0 0 0 0 0 0 0 56.25 -78.75 ENE -0 0 0 0 0 0 0 0 0 0 0 0 78.75 -101.25 E 0 0 0 0 0 0 0 0 0 0 0 0 101.25 -123.75 ESE 0 0 0 0 0 0 0 0 0 0 0 0 123.75 -146.25 SE 0 0 0 0 0 0 3 2 7 0 0 12 146.25 -168.75 SSE 0 0 0 0 0 0 0 0 0 0 -0 0 168.75- 191.25 S 0 0 0 0 1 0 0 0 0 0 0 1 191.25 -213.75 SSW 0 0 0 0 0 0 0 0 0 0 0 0.213.75 -236.25 SW 0 0 0 0 0 0 0 0 0 0 0 0 236.25 -258.75 WSW 0 0 0 0 0 0 2 1 0 0 0 3 258.75 -281.25 W 0 0 0 0 1 2 0 0 0 0 0 3 281.25 -303.75 WNW 0 0 0 0 0 0 0 3 2 0 0 5 303.75 -326.25 NW 0 0 0 0 0 0 9 10 8 0 0 27 326.25 -348.75 NNW 0 0 0 0 0 1 4 1 10 0 0 16 Total 75 70 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (Q1)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: LE -1.90 DEG C/100M, STABILITY CLASS A FREQUENCY

(%)WIND SPEED G~ROUJPS WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.000 0.000 0.186 0.139 0.000 0.000 0.000 0.32 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.05 33.75 -56.25 NE 0.000 0.000 0.000 0.000 0.000 -0.000 0.000 0.000 0.000 0.000 0.000 0.00 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.000 0.000 -0.000 0.000 0.000 0.000 0.000 0.00 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 101.25 -123.75 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 123.75 -146.25 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.139 0.093 0.325 0.000 0.000 0.56 146.25 -168.75 SSE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.05 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 213.75 -236.25 SW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.000 0.000 0.093 0.046 0.000 0.000 0.000 0.14 258.75- 281.25 W 0.000 0.000 0.000 0.000 0.046 0.093 0.000 0.000 0.000 0.000 0.000 0.14 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.139 0.093 0.000 0.000 0.23 303.75 -326.25 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.418 0.464 0.371 0.000 0.000 1.25 326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.000 0.046 0.186 0.046 0.464 0.000 0.000 0.74 Total 3.48 71-m no " m m U w-m m n m m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (Q1)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.89 TO -1.70 DEG C/1OOM, STABILITY CLASS B TOTAL HOURS WIND SPEED GROUPS WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 0 0 2 2 2 0 0 0 6 11.25 -33.75 NNE 0 0 0 0 1 1 1 1 0 0 0 4 33.75 -56.25 NE 0 0 0 0 0 0 0 0 0 0 0 0 56.25 -78.75 ENE 0 0 0 0 0 0 0 0 0 0 0 0 78.75 -101.25 E 0 0 0 0 0 0 0 1 0 0 0 1 101.25 -123.75 ESE 0 0 1 0 0 0 0 0 0 0 0 1 123.75 -146.25 SE 0 0 0 0 1 0 0 1 0 0 0 2 146.25 -168.75 SSE 0 0 0 0 0 0 0 0 0 0 0 0 168.75 -191.25 S 0 0 0 0 0 1 1 0 0 0 0 2 191.25 -213.75 SSW 0 0 0 0 2 0 1 0 0 0 0 3 213.75 -236.25 SW 0 0 0 0 1 1 1 0 0 0 0 3 236.25- 258.75 WSW 0 0 0 0 0 2 2 1 0 0 0 5 258.75 -281.25 W 0 1 0 0 0 3 0 0 0 3 0 7 281.25 -303.75 WNW 0 0 0 0 2 0 1 1 0 2 3 9 303.75 -326.25 NW 0 0 0 0 5 4 16 8 4 0 0 37 326.25 -348.75 NNW 0 0 0 0 1 4 5 5 1 0 0 16 Total 96 72 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY- MARCH 2011 (Q01 WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.89 TO -1.70 DEG C/100M, STABILITY CLASS B FREQUENCY

(%)WINfl gPFFrf} (RRflLP5 WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.000 0.093 0.093 0.093 0.000 0.000 0.000 0.28 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.046 0.046 0.046 0.046 0.000 0.000 0.000 0.19 33.75 -56.25 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.05 101.25 -123.75 ESE 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.05 123.75 -146.25 SE 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.046 0.000 0.000 0.000 0.09 146.25 -168.75 SSE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.000 0.046 0.046 0.000 0.000 0.000 0.000 0.09 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.093 0.000 0.046 0.000 0.000 0.000 0.000 0.14 213.75 -236.25 SW 0.000 0.000 0.000 0.000 0.046 0.046 0.046 0.000 0.000 0.000 0.000 0.14 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.000 0.093 0.093 0.046 0.000 0.000 0.000 0.23 258.75 -281.25 W 0.000 0.046 0.000 0.000 0.000 0.139 0.000 0.000 0.000 0.139 0.000 0.32 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.093 0.000 0.046 0.046 0.000 0.093 0.139 0.42 303.75 -326.25 NW 0.000 0.000 0.000 0.000 0.232 0.186 0.743 0.371 0.186 0.000 0.000 1.72 326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.046 0.186 0.232 0.232 0.046 0.000 0.000 0.74 Total 4.46 73 a -m ! m m m -I m ml W g m m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (01)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.69 TO -1.50 DEG C/100M, STABILITY CLASS C TOTAL HOURS WIND SPEED GROUPS (m/sec/WIND DIRECTION

< 0.5 0.5 -1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 0 .0 3 2 --1 0 0 0 6 11.25 -33.75 NNE 0 0 0 0 0 1 0 1 0 0 0 2 33.75 -56.25 NE 0 0 0 0 0 4 0 ,0 0 0 0 4 56.25 -78.75 ENE 0 0 0 0 0 0 0 0 0 0 0 0 78.75 -101.25 E 0 0 0 0 0 1 1 1 1 0 0 4 101.25 -123.75 ESE 0 0 0 0 0 0 1 0 0 0 0 1 123.75 -146.25 SE 0 0 0 0 2 2 0 2 5 0 0 11 146.25 -168.75 SSE 0 0 0 0 1 0 0 0 1 0 0 2 168.75-191.25 S 0 0 0 0 1 0 0 0 0 0 0 1 191.25 -213.75 SSW 0 0 0 0 3 0 0 1 0 0 0 4 213.75 -236.25 SW 0 0 0 0 2 2 1 1 0 0 0 6 236.25 -258.75 WSW 0 0 0 0 1 4 2 1 1 0 0 9 258.75 -281.25 W 0 0 0 0 0 2 1 0 0 1 0 4 281.25 -303.75 WNW 0 0 0 1 3 3 4 0 3 1 2 17 303.75 -326.25 NW 0 1 0 0 1 4 14 4 10 1 1 36 326.25 -348.75 NNW 0 0 0 0 2 7 5 0 1 0 0 15 Total 122 74 2011 SGS AND IICGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 201 1 (Q1)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.69 TO -1.50 DEG C/100M, STABILITY CLASS C FREQUENCY

(%)WIND SPEED GROUPS WIND DIRECTION

<0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1-4.0 4.1-5.0 5.1 -6.0 6.1 -8.0 8.1-10.0 >10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.000 0.139 0.093 0.046 0.000 0.000 0.000 0.28 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.046 0.000 0.000 0.000 0.09 33.75 -56.25 NE 0.000 0.000 0.000 0.000 0.000 0.186 0.000 0.000 0.000 0.000 0.000 0.19 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.000 0.046 0.046 0.046 0.046 0.000 0.000 0.19 101.25- 123.75 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.046 -0)000 0.000 0.000 0.000 0.05 123.75- 146.25 SE 0.000 0.000 0.000 0.000 0.093 0.093 0.000 0.093 0.232 0.000 0.000 0.51 146.25- 168.75 SSE 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.046 0.000 0.000 0.09 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.05 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.139 0.000 0.000 0.046 0.000 0.000 0.000 0.19 213.75 -236.25 SW 0.000 0.000 0.000 0.000 0.093 0.093 0.046 0.046 0.000 0.000 0.000 0.28 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.046 0.186 0.093 0.046 0.046 0.000 0.000 0.42 258.75 -281.25 W 0.000 0.000 0.000 0.000 0.000 0.093 0.046 0.000 0.000 0.046 0.000 0.19 281.25 -303.75 WNW 0.000 0.000 0.000 0.046 0.139 0.139 0.186 0.000 0.139 0.046 0.093 0.79 303.75 -326.25 NW 0.000 0.046 0.000 0.000 0.046 0.186 0.650 0.186 0.464 0.046 0.046 1.67 326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.093 0.325 0.232 0.000 0.046 0.000 0.000 0.70 Total 5.66 75 M MIm N M, nn m i M m MM m M m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (Q1)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.49 TO -0.50 DEG C/100M, STABILITY CLASS D TOTAL HOURS WIND SPEED GROUPS (mIsec)WIND DIRECTION

< 0.5 0.5- 1.0 1.1 -1.5 1.6- 2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 1 5 7 13 9 7 3 1 0 46 11.25-33.75 NNE 0 0 0 5 15 19. 15 2 3 0 0 59 33.75 -56.25 NE 0 1 1 12 22 19 7 5 2 0 0 69 56.25 -78.75 ENE 0 1 7 3 9 10 2 1 0 0 0 33 78.75- 101.25 E 0 0 2 3 5 6 5 4 4 0 0 29 101.25 -123.75 ESE 0 0 1 4 1 6 5 6 1 0 1 25 123.75 -146.25 SE 0 0 0 7 3 15 8 8 15 4 7 67 146.25 -168.75 SSE 0 0 1 0 7 9 9 6 4 4 0 40 168.75 -191.25 S 0 0 0 1 4 9 5 1 0 0 0 20 191.25 -213.75 SSW 0 0 0 4 5 6 3 2 3 0 0 23 213.75 -236.25 SW 0 0 2 1 5 10 8 2 0 0 0 28 236.25 -258.75 WSW 0 1 0 4 13 8 5 7 3 1 0 42 258.75 -281.25 W 0 1 2 2 6 17 10 8 7 3 2 58 281.25 -303.75 WNW 0 0 1 3 19 20 16 6 33 11 2 111 303.75 -326.25 NW .0 0 1 2 9 26 20 31 32 14 6 141 326.25 -348.75 NNW 0 0 0 3 7 12 16 8 8 2 0 56 Total 847 76 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (01)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.49 TO -0.50 DEG C/lOOM, STABILITY CLASS D FREQUENCY

(%)WIND SPEED GROUPS (mlsecI WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.046 0.232 0.325 0.604 0.418 0.325 0.139 0.046 0.000 2.14 11.25 -33.75 NNE 0.000 0.000 0.000 0.232 0.696 0.882 0.696 0.093 0.139 0.000 0.000 2.74 33.75 -56.25 NE 0.000 0.046 0.046 0.557 1.021 0.882 0.325 0.232 0.093 0.000 0.000 3.20 56.25 -78.75 ENE 0.000 0.046 0.325 0.139 0.418 0.464 0.093 0.046 0.000 0.000 0.000 1.53 78.75 -101.25 E 0.000 0.000 0.093 0.139 0.232 0.279 0.232 0.186 0.186 0.000 0.000 1.35 101.25- 123.75 ESE 0.000 0.000 0.046 0.186 0.046 0.279 0.232 0.279 0.046 0.000 0.046 1.16 123.75 -146.25 SE 0.000 0.000 0.000 0.325 0.139 0.696 0.371 0.371 0.696 0.186 0.325 3.11 146.25 -168.75 SSE 0.000 0.000 0.046 0.000 0.325 0.418 0.418 0.279 0.186 0.186 0.000 1.86 168.75 -191.25 S 0.000 0.000 0.000 0.046 0.186 0.418 0.232 0.046 0.000 0.000 0.000 0.93 191.25 -213.75 SSW 0.000 0.000 0.000 0.186 0.232 0.279 0.139 0.093 0.139 0.000 0.000 1.07 213.75 -236.25 SW 0.000 0.000 0.093 0.046 0.232 0.464 0.371 0.093 0.000 0.000 0.000 1.30 236.25 -258.75 WSW 0.000 0.046 0.000 0.186 0.604 0.371 0.232 0.325 0.139 0.046 0.000 1.95 258.75 -281.25 W 0.000 0.046 0.093 0.093 0.279 0.789 0.464 0.371 0.325 0.139 0.093 2.69 281.25 -303.75 WNW 0.000 0.000 0.046 0.139 0.882 0.929 0.743 0.279 1.532 0.511 0.093 5.15 303.75 -326.25 NW 0.000 0.000 0.046 0.093 0.418 1.207 0.929 1.439 1.486 0.650 0.279 6.55 326.25 -348.75 NNW 0.000 0.000 0.000 0.139 0.325 0.557 0.743 0.371 0.371 0.093 0.000 2.60 Total 39.32 77 marm mm m m m m m m n msom m 2011 S m -m I -mTIVE m m REP O 2011 SGS AND HCGS RADIOACTIVE .EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (Q1)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -0.49 TO 1.50 DEG C/100M, STABILITY CLASS E TOTAL HOURS WIND SPFFD (GRO'IJP5£ WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 2 5 15 15 4 2 0 0 0 43 11.25 -33.75 NNE 0 2 1 2 .23 7 4 4 0 0 0 :43 33.75 -56.25 NE 0 2 2 6 12 6 0 1 0 0 0 29 56.25 -78.75 ENE 0 3 6 4 4 1 0 0 0 0 0 18 78.75 -101.25 E 0 1 3 5 7 0 0 0 0 0 0 "16 101.25 -123.75 ESE 0 0 3 2 9 12 2 7 3 2 1 41 123.75 -146.25 SE 0 4 1 6 9 14 12 6 5 9 4 70 146.25 -168.75 SSE 0 1 2 3 7 9 0 1 0 0 0 23 168.75 -191.25 S 0 1 3 5 6 10 2 2 1 0 1 31 191.25 -213.75 SSW 0 1 2 .3 13 6 1 5 4 2 0 37 213.75 -236.25 SW 0 1 6 4 13 2 2 1 3 0 0 32 236.25 -258.75 WSW 1 1 4 8 14 7 7 2 3 0 1 48 258.75 -281.25 W 0 0 3 6 9 2 3 1 2 9 1 36 281.25 -303.75 WNW 0 3 8 13 19 15 9 2 1 3 0 73 303.75 -326.25 NW 0 1 7 13 42 27 18 7 9 1 0 125 326.25 -348.75 NNW 0 2 0 1 33 21 13 10 14 0 0 94 Total 759 78 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM /HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (Q1)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -0.49 TO 1.50 DEG C/lOOM, STABILITY CLASS E FREQUENCY

(%)WINfl ~PFFfl (~POLJP~ (mk~~c~WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1--10.0

> 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.093 0.232 0.696 0.696 0.186 0.093 0.000 0.000 0.000 2.00 11.25 -33.75 NNE 0.000 0.093 0.046 0.093 1.068 0.325 0.186 0.186 0.000 0.000 0.000 2.00 33.75 -56.25 NE 0.000 0.093 0.093 0.279 0.557 0.279 0.000 0.046 0.000 0.000 0.000 1.35 56.25 -78.75 ENE 0.000 0.139 0.279 0.186 0.186 0.046 0.000 0.000 0.000 0.000 0.000 0.84 78.75 -101.25 E 0.000 0.046 0.139 0.232 0.325 0.000 0.000 0.000 0.000 0.000 0.000 0.74 101.25 -123.75 ESE 0.000 0.000 0.139 0.093 0.418 0.557 0.093 0.325 0.139 0.093 0.046 1.90 123.75 -146.25 SE 0.000 0.186 0.046 0.279 0.418 0.650 0.557 0.279 0.232 0.418 0.186 3.25 146.25 -168.75 SSE 0.000 0.046 0.093 0.139 0.325 0.418 0.000 0.046 0.000 0.000 0.000 1.07 168.75 -191.25 5 0.000 0.046 0.139 0.232 0.279 0.464 0.093 0.093 0.046 0.000 0.046 1.44 191.25 -213.75 SSW 0.000 0.046 0.093 0.139 0.604 0.279 0.046 0.232 0.186 0.093 0.000 1.72 213.75 -236.25 SW 0.000 0.046 0.279 0.186 0.604 0.093 0.093 0.046 0.139 0.000 0.000 1.49 236.25 -258.75 WSW 0.046 0.046 0.186 0.371 0.650 0.325 0.325 0.093 0.139 0.000 0.046 2.23 258.75 -281.25 W 0.000 0.000 0.139 0.279 0.418 0.093 0.139 0.046 0.093 0.418 0.046 1.67 281.25 -303.75 WNW 0.000 0.139 0.371 0.604 0.882 0.696 0.418 0.093 0.046 0.139 0.000 3.39 303.75 -326.25 NW 0.000 0.046 0.325 0.604 .1.950 1.253 0.836 0.325 0.418 0.046 0.000 5.80 326.25 -348.75 NNW 0.000 0.093 0.000 046 152 095 0.604 044 0.650 0.000 0.000 4.36 Total 35.24 79 M- n m IM M M M M M M M M ME MMMM m m m mim m m mm mm m m m m m m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK ....JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (Q1)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: 1.51 TO 4.00 DEG C/1OOM, STABILITY CLASS F TOTAL HOURSWIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 >10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 2 2 0 1 2 0 0 0 0 0 7 11.25 -33.75 NNE 0 0 1 1 4 2 0 0 0 0 0 8 33.75 -56.25 NE 0 0 0 1 6 2 0 0 0 0 0 9 56.25 -78.75 ENE 0 1 2 1 0 0 0 0 0 0 0 4 78.75 -101.25 E 0 0 1 2 0 0 0 0 0 0 0 3 101.25 -123.75 ESE 0 1 2 6 4 5 0 0 0 0 0 18 123.75 -146.25 SE 0 2 1 3 7 7 8 3 13 2 0 46 146.25 -168.75 SSE 0 0 3 1 3 6 1 0 0 0 0 14 168.75 -191.25 S 0 1 4 2 3 3 4 0 0 0 1 18 191.25 -213.75 SSW 0 0 3 0 3 6 6 4 0 0 1 23 213.75 -236.25 SW 0 0 0 1 5 8 2 0 0 0 0 16 236.25 -258.75 WSW 0 0 0 0 3 0 1 0 0 0 0 4 258.75 -281.25 W 0 2 0 0 0 1 2 0 0 0 0 5 281.25 -303.75 WNW 0 1 0 0 2 0 0 0 0 0 0 3 303.75- 326.25 NW 0 1 0 0 0 5 0 0 0 0 0 6 326.25 -348.75 NNW 0 0 0 1 3 1 1 0 0 0 0 6 Total 190 80 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (Q1)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: 1.51 TO 4.00 DEG C/100M, STABILITY CLASS F FREQUENCY

(%)WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.093 0.093 0.000 0.046 0.093 0.000 0.000 0.000 0.000 0.000 0.32 11.25 -33.75 NNE 0.000 0.000 0.046 0.046 0.186 0.093 0.000 0.000 0.000 0.000 0.000 0.37 33.75 -56.25 NE 0.000 0.000 0.000 0.046 0.279 0.093 0.000 0.000 0.000 0.000 0.000 0.42 56.25 -78.75 ENE 0.000 0.046 0.093 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.19 78.75 -101.25 E 0.000 0.000 0.046 0.093 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.14 101.25 -123.75 ESE 0.000 0.046 0.093 0.279 0.186 0:232 0.000 0.000 0.000 0.000 0.000 0.84 123.75 -146.25 SE 0.000 0.093 0.046 0.139 0.325 0.325 0.371 0.139 0.604 0.093 0.000 2.14 146.25 -168.75 SSE 0.000 0.000 0.139 0.046 0.139 0.279 0.046 0.000 0.000 0.000 0.000 0.65 168.75 -191.25 S 0.000 0.046 0.186 0.093 0.139 0.139 0.186 0.000 0.000 0.000 0.046 0.84 191.25 -213.75 SSW 0.000 0.000 0.139 0.000 0.139 0.279 0.279 0.186 0.000 0.000 0.046 1.07 213.75 -236.25 SW 0.000 0.000 0.000 0.046 0.232 0.371 0.093 0.000 0.000 0.000 0.000 0.74 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 .. 0.139 0.000 0.046 0.000 0.000 0.000 0.000 0.19 258.75 -281.25 W 0.000 0.093 0.000 0.000 0.000 0.046 0.093 0.000 0.000 0.000 0.000 0.23 281.25 -303.75 WNW 0.000 0.046 0.000 0.000 0.093 0.000 0.000 0.000 0.000 0.000 0.000 0.14 303.75 -326.25 NW 0.000 0.046 0.000 0.000 0.000 0.232 0.000 0.000 0.000 0.000 0.000 0.28 326.25 -348.75 NNW 0.000 0.000 0.000 0.046 0.139 0.046 0.046 0.000 0.000 0.000 0.000 0.28 Total 8.82 81 m mm m m mm Im m m m mm m m m m 2011m m m m m m m m m m m m mRn 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (Q1)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: GT 4.00 DEG C/100M, STABILITY CLASS G TOTAL HOURS WIND ,£PFFD WIND DIRECTION

< 0.5 0.5- 1.0 1.1-1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1-5.0 5.1-6.0 6.1 -8.0 8.1-10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 0 0 0 0 0 0 0 0 0 11.25 -33.75 NNE 0 0 0 0 0 0 0 0 0 0 0 0 33.75 -56.25 NE 0 0 0 0 0 0 0 0 0 0 0 0 56.25 -78.75 ENE 0 0 1 1 0 0 0 0 0 0 0 2 78.75 -101.25 E 0 0 0 0 0 0 0 0 0 0 0 0 101.25 -123.75 ESE 0 0 1 1 2 1 2 2 1 0 0 10 123.75 -146.25 SE 0 0 1 0 4 3 9 13 15 3 0 48 146.25 -168.75 SSE 0 0 0 0 1 0 1 0 0 0 0 2 168.75 -191.25 S 0 0 0 0 0 0 0 0 0 0 0 0 191.25 -213.75 SSW 0 0 0 1 0 1 0 0 0 0 0 2 213.75 -236.25 SW 0 0 0 0 0 0 0 0 0 0 0 0 236.25 -258.75 WSW 0 0 0 0 0 0 0 ....0 0 0 0 0 258.75 -281.25 W 0 0 0 0 0 0 0 0 0 0 0 0 281.25 -303.75 WNW 0 0 0 0 0 0 0 ,0 0 0 0 0 303.75 -326.25 NW 0 0 0 0 1 0 0 0 0 0 0 1 326.25 -348.75 NNW 0 0 0 0 0 0 0 0 0 0 0 0 Total 65 82 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (Q1)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: GT 4.00 DEG C/1OOM, STABILITY CLASS G FREQUENCY

(%)WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 33.75 -56.25 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 56.25 -78.75 ENE 0.000 0.000 0.046 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.09 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 101.25 -123.75 ESE 0.000 0.000 0.046 0.046 0.093 0.046 0.093 0.093 0.046 0.000 0.000 0.46 123.75 -146.25 SE 0.000 0.000 0.046 0.000 0.186 0.139 0.418 0.604 0.696 0.139 0.000 2.23 146.25 -168.75 SSE 0.000 0.000 0.000 0.000 0.046 0.000 0.046 0.000 0.000 0.000 0.000 0.09 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 191.25 -213.75 SSW 0.000 0.000 0.000 0.046 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.09 213.75 -236.25 SW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 258.75 -281.25 W 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 303.75 -326.25 NW 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.05 326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 Total 3.02 83 m m m ~ ~ m m m m m m m m m mm m -ND m m m m mRT 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT.SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY- MARCH 2011 (Q1)WIND LEVEL: 33 FT DELTA T: (300-33 FT)ALL STABILITY CLASSES TOTAL HOURS WIND SPEED GROUPS (mlsec.WIND DIRECTION

< 0.5 0.5 -1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1-4.0 4.1-5.0 5.1-6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 2 5 10 23 35 21 15 3 1 0 115 11.25 -33.75 NNE 0 2 2 8 43 31 20 8 3 0 0 117 33.75 -56.25 NE 0 3 3 19 40 31 7 6 2 0 0 111 56.25 -78.75 ENE 0 5 16 9 13 11 2 1 0 0 0 57 78.75-101.25 E 0 1 6 10 12 7 6 6 5 0 0 53 101.25 -123.75 ESE 0 1 8 13 16 24 10 15 5 2 2 96 123.75 -146.25 SE 0 6 3 16 26 41 40 35 60 18 11 256 146.25 -168.75 SSE 0 1 6 4 19 24 11 7 5 4 0 81 168.75 -191.25 S 0 2 7 8 15 23 12 3 1 0 2 73 191.25 -213.75 SSW 0 1 5 8 26 19 11 12 7 2 1 92 213.75 -236.25 SW 0 1 8 6 26 23 14 4 3 0 0 85 236.25 -258.75 WSW 1 2 4 12 31 21 19 12 7 1 1 111 258.75 -281.25 W 0 4 5 8 16 27 16 9 9 16 3 113 281.25 -303.75 WNW 0 4 9 17 45 38 30 12 39 17 7 218 303.75 -326.25 NW 0 3 8 15 58 66 77 60 63 16 7 373 326.25 -348.75 NNW 0 2 0 5 46 46 44 24 34 2 0 203 Total 2,154 84 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY -MARCH 2011 (Q1)WIND LEVEL: 33 FT DELTA T: (300-33 FT)ALL STABILITY CLASSES FREQUENCY

(%)WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5- 1.0 1.1 -1.5 1.6- 2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 --6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.093 0.232 0.464 1.068 1.625 0.975 0.696 0.139 0.046 0.000 5.34 11.25 -33.75 NNE 0.000 0.093 0.093 0.371 1.996 1.439 0.929 0.371 0.139 0.000 0.000 5.43 33.75 -56.25 NE 0.000 0.139 0.139 0.882 1.857 1.439 0.325 0.279 0.093 0.000 0.000 5.15 56.25 -78.75 ENE 0.000 0.232 0.743 0.418 0.604 0.511 0.093 0.046 0.000 0.000 0.000 2.65 78.75 -101.25 E 0.000 0.046 0.279 0.464 0.557 0.325 0.279 0.279 0.232 0.000 0.000 2.46 101.25 -123.75 ESE 0.000 0.046 0.371 0.604 0.743 1.114 0.464 0.696 0.232 0.093 0.093 4.46 123.75 -146.25 SE 0.000 0.279 0.139 0.743 1.207 1.903 1.857 1.625 2.786 0.836 0.511 11.88 146.25 -168.75 SSE 0.000 0.046 0.279 0.186 0.882 1.114 0.511 0.325 0.232 0.186 0.000 3.76 168.75 -191.25 S 0.000 0.093 0.325 0.371 0.696 1.068 0.557 0.139 0.046 0.000 0.093 3.39 191.25 -213.75 SSW 0.000 0.046 0.232 0.371 1.207 0.882 0.511 0.557 0.325 0.093 0.046 4.27 213.75 -236.25 SW 0.000 0.046 0.371 0.279 1.207 1.068 0.650 0.186 0.139 0.000 0.000 3.95 236.25 -258.75 WSW 0.046 0.093 0.186 0.557 1.439 0.975 0.882 0.557 0.325 0.046 0.046 5.15 258.75 -281.25 W 0.000 0.186 0.232 0.371 0.743 1.253 0.743 0.418 0.418 0.743 0.139 5.25 281.25 -303.75 WNW 0.000 0.186 0.418 0.789 2.089 1.764 1.393 0.557 1.811 0.789 0.325 10.12 303.75 -326.25 NW 0.000 0.139 0.371 0.696 2.693 3.064 3.575 2.786 2.925 0.743 0.325 17.32 326.25 -348.75 NNW 0.000 0.093 0.000 0.232 2.136 2.136 2.043 1.114 1.578 0.093 0.000 9.42 Total 100.00 85 m m m m m m m m m m m m m m m m m -m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Lapse Rate Wind Distributions 300- 33 foot 4/2011 -6/2011 86 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (02)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LE -1.90 DEG C/lOOM, STABILITY CLASS A TOTAL HOURS LAPSE RATE: WIND SPEED GROUPS (rn/sec I WIND DIRECTION

<0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 0 1 3 0 4 0 0 0 8 11.25 -33.75 NNE 0 0 0 0 1 0 2 0 0 0 0 3 33.75 -56.25 NE 0 0 0 1 1 0 0 0 0 0 0 2 56.25 -78.75 ENE 0 0 0 0 0 0 0 3 0 0 0 3'78.75 -101.25 E 0 0 0 0 1 1 0 6 0 0 0 8 101.25 -123.75 ESE 0 0 0 0 0 0 0 0 0 0 0 0 123.75 -146.25 SE 0 0 0 0 0 0 1 2 5 0 0 8 146.25 -168.75 SSE 0 0 0 0 0 0 0 0 0 0 0 0 168.75 -191.25 S 0 0 0 0 0 0 0 0 0 0 0 0 191.25 -213.75 SSW 0 0 0 0 0 0 0 0 0 0 0 0 213.75 -236.25 SW 0 0 0 0 0 0 0 3 0 0 0 3 236.25 -258.75 WSW 0 0 0 0 0 2 1 2 4 0 0 9-258.75 -281.25 W 0 0 0 0 0 0 2 1 2 0 0 5 281.25 -303.75 WNW 0 0 0 0 0 0 0 1 1 0 0 2 303.75 -326.25 NW 0 0 0 0 0 0 1 3 6 0 0 10 326.25 -348.75 NNW 0 0 0 0 0 3 5 2 1 0 0 11 Total 72 87 m m m m m m m m m m m m m m 2011m m m m m m -ELAS m m m RE 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL-JUNE 2011 (Q2)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: LE -1.90 DEG C/IOOM, STABILITY CLASS A FREQUENCY

(%)WIND SPEED GROUPS WIND DIRECTION

< 0.5 0.5- 1.0 1.1-1.5 1.6-2.0 2.1 -3.0 3.1-4.0 4.1-5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.046 0.138 0.000 0.184 0.000 0.000 0.000 0.37 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.046 0.000 0.092 0.000 0.000 0.000 0.000 0.14 33.75 -56.25 NE 0.000 0.000 0.000 0.046 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.09 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.138 0.000 0.000 0.000 0.14 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.046 0.046 0.000 0.276 0.000 0.000 0.000 0.37 101.25 -123.75 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 123.75 -146.25 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.092 0.230 0.000 0.000 0.37 146.25 -168.75 SSE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 213.75 -236.25 SW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.138 0.000 0.000 0.000 0.14 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.000 0.092 0.046 0.092 0.184 0.000 0.000 0.41 258.75 -281.25 W 0.000 0.000 0.000 0.000 0.000 0.000 0.092 0.046 0.092 0.000 0.000 0.23 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.046 0.000 0.000 0.09 303.75 -326.25 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.138 0.276 0.000 0.000 0.46 326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.000 0.138 0.230 0.092 0.046 0.000 0.000 0.51 Total 3.31 88 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (Q2)WIND LEVEL: 33 FT DELTA T: (300-33 FT)-1.89 TO -1.70 DEG C/1 0OM, STABILITY CLASS B TOTAL HOURS LAPSE RATE: WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0. Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 0 1 4 3 0 0 0 0 8 11.25 -33.75 NNE 0 0 0 0 0 4 1 0 0 0 0 5 33.75 -56.25 NE 0 0 0 0 1 2 1 0 0 0 0 4 56.25 -78.75 ENE 0 0 0 0 0 0 0 0 0 0 0 0 78.75 -101.25 E 0 0 0 0 0 2 1 2 0 0 0 5 101.25 -123.75 ESE 0 0 0 0 0 1 1 -0 0 0 0 2 123.75- 146.25 SE 0 0 0 0 0 0 3 3 3 0 0 9 146.25 -168.75 SSE 0 0 0 0 3 1 2 1 0 0 0 7 168.75 -191.25 S 0 0 0 0 2 0 0 0 0 0 0 2 191.25 -213.75 SSW 0 0 0 0 1 0 0 2 0 0 0 3 213.75 -236.25 SW 0 0 0 0 3 0 1 0 0 0 0 4 236.25 -258.75 WSW 0 0 0 0 2 0 3 2 0 0 0 7 258.75 -281.25 W 0 0 0 1 0 0 1 0 1 0 0 3 281.25 -303.75 WNW 0 0 0 0 1 1 0 2 7 0 0 11 303.75 -326.25 NW 0 0 0 0 1 1 2 1 0 0 0 5 326.25 -348.75 NNW 0 0 0 0 2 4 6 1 0 0 0 13 Total 88 89 m m m m m m m m m m m m m m mn AND m m -Fm L mEm mnE RE 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (Q2)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.89 TO -1.70 DEG C/100M, STABILITY CLASS B FREQUENCY

(%)WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.046 0.184 0.138 0.000 0.000 0.000 0.000 0.37 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.000 0.184 0.046 0.000 0.000 0.000 0.000 0.23'33.75 -56.25 NE 0.000 0.000 0.000 0.000 0.046 0.092 0.046 0.000 0.000 0.000 0.000 0.18 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.000 0.092 0.046 0.092 0.000 0.000 0.000 0.23 101.25 -123.75 ESE 0.000 0.000 0.000 0.000 0.000 0.046 0.046 0.000 0.000 0.000 0.000 0.09 123.75 -146.25 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.138 0.138 0.138 0.000 0.000 0.41 146.25 -168.75 SSE 0.000 0.000 0.000 0.000 0.138 0.046 0.092 0.046 0.000 0.000 0.000 0.32 168.75 -191.25. S 0.000 0.000 0.000 0.000 0.092 0.000 0.000 0.000 0.000 0.000 0.000 0.09 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.092 0.000 0.000 0.000 0.14 213.75 -236.25 SW 0.000 0.000 0.000 0.000 0.138 0.000 0.046 0.000 0.000 0.000 0.000 0.18 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.092 0.000 0.138 0.092 0.000 0.000 0.000 0.32 258.75-281.25 W 0.000 0.000 0.000 0.046 0.000 0.000 0.046 0.000 0.046 0.000 0.000 0.14 281.25 -303.75 WNW 0.000 0.000 0.000' 0.000 0.046 0.046 0.000 0.092 0.322 0.000 0.000 0.51 303.75 -326.25 NW 0.000 0.000 0.000 0.000 0.046 0.046 0.092 0.046 0.000 0.000 0.000 0.23*326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.092 0.184 0.276 0.046 0.000 0.000 0.000 0.60 Total 4.04 90 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (Q2)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.69 TO -1.50 DEG C/100M, STABILITY CLASS C TOTAL HOURS WIND SPFFD (m/rspcr WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75- 11.25 N 0 0 0 0 7 4 3 0 0 0 0 14 11.25-33.75 NNE 0 0 0 0 0 2 2 0 0 0 0 4 33.75 -56.25 NE 0 0 0 0 2 1 1 0 0 0 0 4 56.25 -78.75 ENE 0 0 0 0 2 1 0 0 0 0 0 3 78.75 -101.25 E 0 0 0 0 5 2 1 0 0 0 0 8 101.25 -123.75 ESE 0 0 0 0 0 2 0 0 2 0 1 5 123.75 -146.25 SE 0 0 0 0 1 4 2 2 10 0 0 19 146.25- 168.75 SSE 0 0 0 0 6 2 1 1 0 0 0 10 168.75 -191.25 S 0 0 0 1 4 0 0 0 0 0 0 5 191.25 -213.75 SSW 0 0 0 0 3 0 1 1 0 0 0 5 213.75 -236.25 SW 0 0 0 0 2 0 2 0 0 0 0 4 236.25- 258.75 WSW 0 0 0 0 3 1 4 3 1 0 0 12 258.75 -281.25 W 0 0 0 2 1 2 2 3 1 0 0 11 281.25 -303.75 WNW 0 0 0 1 1 0 1 2 2 0 0 7 303.75 -326.25 NW 0 0 0 1 5 4 1 1 4 0 0 16 326.25 -348.75 NNW 0 0 0 0 10 5 5 0 0 0 0 20 Total 147 91 m m m1m m mm m m = Im -m m m m- m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (Q2)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.69 TO -1.50 DEG C/lOOM, STABILITY CLASS C FREQUENCY

(%)WIND SPEED (ROUP5~ (mI~cA WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total.(Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.322 0.184 0.138 0.000 0.000 0.000 0.000 0.64 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.000 0.092 0.092 0.000 0.000 0.000 0.000 0.18 33.75 -56.25 NE 0.000 0.000 0.000 0.000 0.092 0.046 0.046 0.000 0.000 0.000 0.000 0.18 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.092 0.046 0.000 0.000 0.000 0.000 0.000 0.14 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.230 0.092 0.046 0.000 0.000 0.000 0.000 0.37 101.25 -123.75 ESE 0.000 0.000 0.000 0.000 0.000 0.092 0.000 0.000 0.092 0.000 0.046 0.23 123.75 -146.25 SE 0.000 0.000 0.000 0.000 0.046 0.184 0.092 0.092 0.460 0.000 0.000 0.87 146.25 -168.75 SSE 0.000 0.000 0.000 0.000 0.276 0.092 0.046 0.046 0.000 0.000 0.000 0.46 168.75 -191.25 5 0.000 0.000 0.000 0.046 0.184 0.000 0.000 0.000 0.000 0.000 0.000 0.23 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.138 0.000 0.046 0.046 0.000 0.000 0.000 0.23 213.75 -236.25 SW 0.000 0.000 0.000 0.000 0.092 0.000 0.092 0.000 0.000 0.000 0.000 0.18 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.138 0.046 0.184 0.138 0.046 0.000 0.000 0.55 258.75 -281.25 W 0.000 0.000 0.000 0.092 0.046 0.092 0.092 0.138 0.046 0.000 0.000 0.51 281.25 -303.75 WNW 0.000 0.000 0.000 0.046 0.046 0.000 0.046 0.092 0.092 0.000 0.000 0.32 303.75 -326.25 NW 0.000 0.000 0.000 0.046 0.230 0.184 0.046 0.046 0.184 0.000 0.000 0.74 326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.460 0.230 0.230 0.000 0.000 0.000 0.0 0.92o-Total 6.76 92 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (Q2)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.49 TO -0.50 DEG C/100M, STABILITY CLASS D TOTAL HOURS WIND SPEED GROUJPS WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 2 7 3 3 1 0 0 0 16 11.25 -33.75 NNE 0 0 3 1 16 5 2 1 0 0 0 28 33.75 -56.25 NE 0 0 2 2 15 18 14 1 3 0 0 55 56.25 -78.75 ENE 0 2 1 4 13 9 5 1 4 0 0 39 78.75- 101.25 E 0 0 2 1 10 10 8 8 3 0 0 42 101.25 -123.75 ESE 0 1 0 1 5 22 14 9 6 1 2 61 123.75 -146.25 SE 0 0 1 1 7 14 29 32 62 14 4 164 146.25 -168.75 SSE 0 0 2 1 13 16 11 17 13 2 0 75 168.75 -191.25 S 0 0 3 5 15 21 15 -4 2 1 0 66 191.25 -213.75 SSW 0 1 1 5 12 6 2 0 2 0 0 29 213.75 -236.25 SW 0 0 2 5 19 11 11 5 2 0 0 55 236.25 -258.75 WSW 0 0 1 3 14 19 8 4 0 0 0 49 258.75 -281.25 W 0 1 0 4 10 10 11 8 4 1 0 49 281.25 -303.75 WNW 0 1 2 4 9 12 12 8 2 0 0 50 303.75 -326.25 NW 0 0 3 5 11 22 12 11 4 4 0 72 326.25 -348.75 NNW 0 0 2 5 15 9 11 8 0 0 0 50 Total 900 93 m m m m m m m m m m m m m m m m m -m m m m m AND m m m m m m -,,m m m m REn m2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK ...JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (Q2)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.49 TO -0.50 DEG C/100M, STABILITY CLASS D FREQUENCY

(%)WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.092 0.322 0.138 0.138 0.046 0.000 0.000 0.000 0.74 11.25 -33.75 NNE 0.000 0.000 0.138 0.046 0.735 0.230 0.092 0.046 0.000 0.000 0.000 1.29 33.75 -56.25 NE 0.000 0.000 0.092 0.092 0.689 0.827 0.643 0.046 0.138 0.000 0.000 2.53 56.25 -78.75 ENE 0.000 0.092 0.046 0.184 0.597 0.414 0.230 0.046 0.184 0.000 0.000 1.79 78.75 -101.25 E 0.000 0.000 0.092 0.046 0.460 0.460 0.368 0.368 0.138 0.000 0.000 1.93 101.25 -123.75 ESE 0.000 0.046 0.000 0.046 0.230 1.011 0.643 0.414 0.276 0.046 0.092 2.80 123.75 -146.25 SE 0.000 0.000 0.046 0.046 0.322 0.643 1.333 1.471 2.849 0.643 0.184 7.54 146.25 -168.75 SSE 0.000 0.000 0.092 0.046 0.597 0.735 0.506 0.781 0.597 0.092 0.000 3.45 168.75- 191.25 S 0.000 0.000 0.138 0.230 0.689 0.965 0.689 0.184 0.092 0.046 0.000 3.03 191.25 -213.75 SSW 0.000 0.046 0.046 0.230 0.551 0.276 0.092 0.000 0.092 0.000 0.000 1.33 213.75 -236.25 SW 0.000 0.000 0.092 0.230 0.873 0.506 0.506 0.230 0.092 0.000 0.000 2.53 236.25 -258.75 WSW 0.000 0.000 0.046 0.138 0.643 0.873 0.368 0.184 0.000 0.000 0.000 2.25 258.75 -281.25 W 0.000 0.046 0.000 0.184 0.460 0.460 0.506 0.368 0.184 0.046 0.000 2.25 281.25 -303.75 WNW 0.000 0.046 0.092 0.184 0.414 0.551 0.551 0.368 0.092 0.000 0.000 2.30 303.75 -326.25 NW 0.000 0.000 0.138 0.230 0.506 1.011 0.551 0.506 0.184 0.184 0.000 3.31 326.25 -348.75 NNW 0.000 0.000 0.092 0.230 0.689 0.414 0.506 0.368 0.000 0.000 0.000 2.30 Total 41.36 94 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (Q2)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -0.49 TO 1.50 DEG C/100M, STABILITY CLASS E .TOTAL HOURS WINfl (m/cPrI WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 2 0 6 13 5 3 2 0 0 0 31 11.25 -33.75 NNE 0 0 2 1 9 5 0 0 0 0 0 17 33.75 -56.25 NE 0 0 4 8 12 5 3 0 0 0 0 32 56.25 -78.75 ENE 0 1 5 13 9 3 4 0 0 0 0 35 78.75-101.25 E 0 3 5 6 8 7 1 0 0 0 0 30 101.25 -123.75 ESE 0 2 1 2 7 6 5 1 1 0 0 25 123.75- 146.25 SE 0 0 2 3 6 6 22 23 15 0 0 77 146.25 -168.75 SSE 0 0 3 2 6 6 5 7 1 0 1 31 168.75 -191.25 S 0 0 1 .4 9 5 6 7 11 2 4 49 191.25 -213.75 SSW 0 0 1 10 14 8 3 10 4 1 0 51 213.75 -236.25 SW 0 1 3 7 19 23 10 5 0 0 0 68 236.25 -258.75 WSW 0 1 5 6 19 16 8 2 0- 0 0 57 258.75- 281.25 W 0 0 4 8 10 17 10 0 1 0 0 50 281.25- 303.75 WNW 0 0 6 7 12 4 6 0 0 0 0 35 303.75- 326.25 NW 0 0 6 8 19 14 9 1 2 0 0 59 326.25 -348.75 NNW 0 0 4 2 14 7 2 2 1 0 0 32 Total 679 95 mm mmmmmmmmmmmmm mm mm m mm 2 0 1 m m m m m m m -m m R m mn m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (Q2)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -0.49 TO 1.50 DEG C/100M, STABILITY CLASS E FREQUENCY

(%)WIND SPEED GROUPS WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.092 0.000 0.276 0.597 0.230 0.138 0.092 0.000 0.000 0.000 1.42 11.25 -33.75 NNE 0.000 0.000 0.092 0.046 0.414 0.230 0.000 0.000 0.000 0.000 0.000 0.78 33.75 -56.25 NE 0.000 0.000 0.184 0.368 0.551 0.230 0.138 0.000 0.000 0.000 0.000 1.47 56.25 -78.75 *ENE 0.000 0.046 0.230 0.597 0.414 0.138 0.184 0.000 0.000 0.000 0.000 1.61 78.75 -101.25 .E 0.000 0.138 0.230 0.276 0.368 0.322 0.046 0.000 0.000 0.000 0.000 1.38 101.25 -123.75 ESE 0.000 0.092 0.046 0.092 0.322 0.276 0.230 0.046 0.046 0.000 0.000 1.15 123.75 -146.25 SE 0.000 0.000 0.092 0.138 0.276 0.276 1.011 1.057 0.689 0.000 0.000 3.54 146.25 -168.75 SSE 0.000 0.000 0.138 0.092 0.276 0.276 0.230 0.322 0.046 0.000 0.046 1.42 168.75 -191.25 S 0.000 0.000 0.046 0.184 0.414 0.230 0.276 0.322 0.506 0.092 0.184 2.25 191.25 -213.75 SSW 0.000 0.000 0.046 0.460 0.643 0.368 0.138 0.460 0.184 0.046 0.000 2.34 213.75 -236.25 SW 0.000 0.046 0.138 0.322 0.873 1.057 0.460 0.230 0.000 0.000 0.000 3.13 236.25 -258.75 WSW 0.000 0.046 0.230 0.276 0.873 0.735 0.368 --0.092 0.000 0.000 0.000 2.62 258.75 -281.25 W 0.000 0.000 0.184 0.368 0.460 0.781 0.460 0.000 0.046 0.000 0.000 2.30 281.25 -303.75 WNW 0.000 0.000 0.276 0.322 0.551 0.184 0.276 0.000 0.000 0.000 0.000 1.61 303.75 -326.25 NW 0.000 0.000 0.276 0.368 0.873 0.643 0.414 0.046 0.092 0.000 0.000 2.71 326.25 -348.75 NNW 0.000 0.000 0.184 0.092 0.643 0.322 0.092 0.092 0.046 0.000 0.000 1.47 Total 31.20 96 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (Q2)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: 1.51 TO 4.00 DEG C/lO00M, STABILITY CLASS F TOTAL HOURS WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 1 4 13 7 0 0 0 0 0 25 11.25 -33.75 NNE 0 0 1 1 13 7 0. 0 0 0 0 22 33.75 -56.25 NE 0 0 1 2 4 0 0 0 0 0 0 7 56.25 -78.75 ENE 0 0 3 2 5 3 0 0 0 0 0 13 78.75 -101.25 E .0 0 2 0 3 2 0 0 0 0 0 7 101.25 -123.75 ESE 0 0 0 0 2 4 0 0 0 0 0 6 123.75 -146.25 SE 0 0 1 1 2 0 10 17 5 0 0 36 146.25 -168.75 SSE 0 0 0 3 2 2 5 3 5 1 0 21 168.75 -191.25 S 0 0 2 3 1 1 5 8 6 2 1 29 191.25 -213.75 SSW 0 0 2 3 8 3 2 1 4 2 0 25 213.75 -236.25 SW 0 1 0 1 4 2 0 1 3 0 0 12 236.25- 258.75 WSW 0 0 1 2 4 5 1 1 0 0 0 14 258.75 -281.25 W 0 0 0 2 1 1 0 0 0 0 0 4 281.25 -303.75 WNW 0 0 0 0 0 0 0 0 0 0 0 0 303.75 -326.25 NW 0 1 1 1 4 2 0 0 0 0 0 9 326.25 -348.75 NNW 0 0 0 0 7 7 0 0 0 0 0 14 Total 244 97 m m m m m m m m m m m m m m m m m m m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (02)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: 1.51 TO 4.00 DEG C/1lOOM, STABILITY CLASS F FREQUENCY

(%)WINfl ~PFFfl (~PflhiP5~ (mI~~r~WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.046 0.184 0.597 0.322 0.000 0.000 0.000 0.000 0.000 1.15 11.25 -33.75 NNE 0.000 0.000 0.046 0.046 0.597 0.322 0.000 0.000 0.000 0.000 0.000 1.01 33.75 -56.25 NE 0.000 0.000 0.046 0.092 0.184 0.000 0.000 0.000 0.000 0.000 0.000 0.32 56.25 -78.75 ENE 0.000 0.000 0.138 0.092 0.230 0.138 0.000 0.000 0.000 0.000 0.000 0.60 78.75 -101.25 E 0.000 0.000 0.092 0.000 0.138 0.092 0.000 0.000 0.000 0.000 0.000 0.32 101.25 -123.75 ESE 0.000 0.000 0.000 0.000 0.092 0.184 0.000 0.000 0.000 0.000 0.000 0.28 123.75 -146.25 SE 0.000 0.000 0.046 0.046 0.092 0.000 0.460 0.781 0.230 0.000 0.000 1.65 146.25 -168.75 SSE 0.000 0.000 0.000 0.138 0.092 0.092 0.230 0.138 0.230 0.046 0.000 0.97 168.75 -191.25 5 0.000 0.000 0.092 0.138 0.046 0.046 0.230 0.368 0.276 0.092 0.046 1.33 191.25 -213.75 SSW 0.000 0.000 0.092 0.138 0.368 0.138 0.092 0.046 0.184 0.092 0.000 1.15 213.75 -236.25 SW 0.000 0.046 0.000 0.046 0.184 0.092 0.000 0.046 0.138 0.000 0.000 0.55 236.25 -258.75 WSW 0.000 0.000 0.046 0.092 0.184 0.230 0.046 0.046 0.000 0.000 0.000 0.64 258.75 -281.25 W 0.000 0.000 0.000 0.092 0.046 0.046 0.000 0.000 0.000 0.000 0.000 0.18 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 303.75 -326.25 NW 0.000 0.046 0.046 0.046 0.184 0.092 0.000 0.000 0.000 0.000 0.000 0.41 326.25 -348.75 FNNW 0.000 0.000 0.000 0.000 0.322 10.322 0.000 0.000 0.000 0.000 0.000 10.64 Total 11.21 98 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (Q2)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: GT 4.00 DEG C/1OOM, STABILITY CLASS G TOTAL HOURS WIND SPEED GROUPS WIND DIRECTION

<0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 .0 0 0 0 0 0 0 0 0 0 0 11.25 -33.75 NNE 0 0 0 2 2 1 0 0 0 0 0 5 33.75 -56.25 NE 0 0 0 0 0 0 0 0 0 0 0 0 56.25 -78.75 ENE 0 0 0 0 0 0 0 0 0 0 0 0 78.75 -101.25 E 0 0 0 0 0 0 0 0 0 0 0 0 101.25 -123.75 ESE 0 0 0 0 0 2 0 0 0 0 0 2 123.75 -146.25 SE 0 0 0 0 3 2 5 11 12 1 0 34 146.25 -168.75 SSE 0 0 0 0 0 0 0 1 2 0 0 3 168.75- 191.25 S 0 0 0 0 1 0 0 0 0 1 0 2 191.25 -213.75 SSW 0 0 0 0 0 0 0 0 0 0 0 0 213.75 -236.25 SW 0 0 0 0 0 0 0 0 0 0 0 0 236.25 -258.75 WSW 0 0 0 0 0 0 0 0 0 0 0 0 258.75 -281.25 W 0 0 0 0 0 0 0 0 0 0 0 0 281.25 -303.75 WNW 0 0 0 0 0 0 0 0 0 0 0 0 303.75 -326.25 NW 0 0 0 0 0 0 0 0 0 0 0 0 326.25 -348.75 NNW 0 0 0 0 0 0 0 0 0 0 0 0 Total 46 99 m m m m m -m m m m m m m -m --m

-m m m m m m m m m m m m m m m mEn m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (02)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: GT 4.00 DEG C/1OOM, STABILITY CLASS G FREQUENCY

(%)WIND SPEED GROUPS WIND DIRECTION

< 0.5 0.5- 1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1-10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 11.25 -33.75 NNE 0.000 0.000 0.000 0.092 0.092 0.046 0.000 0.000 0.000 0.000 0.000 0.23 33.75 -56.25 NE 0.000 0,000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 101.25 -123.75 ESE 0.000 0.000 0.000 0.000 0.000 0.092 0.000 0.000 0.000 0.000 0.000 0.09 123.75 -146.25 SE 0.000 0.000 0.000 0.000 0.138 0.092 0.230 0.506 0.551 0.046 0.000 1.56 146.25 -168.75 SSE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.092 0.000 0.000 0.14 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.046 0.000 0.09 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 213.75 -236.25 SW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 258.75 -281.25 W 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 303.75 -326.25 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.000 0n000 0,000 0.000 0.000 0.000 0.000 0.00 Total 2.11 100 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL- JUNE 2011 (Q2)WIND LEVEL: 33 FT DELTA T: (300-33 FT)ALL STABILITY CLASSES TOTAL HOURS WIND SPEED GROUPS (m/sec)WIND DIRECTION

<0.5 0.5-1.0 1.1 -1.5 1.6-2.0 .2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75-11.25 N 0 2 1 12 42 26 .12 7 0 0 0 102 11.25-33.75 NNE 0 0 6 5 41 24 7 1 0 0 0 84 33.75- 56.25 NE 0 0 7 13 35 26 19 1 3 0 0 104 56.25-78.75 ENE 0 3 9 19 29 16 9 4 4 0 0 93 78.75-101.25 E 0 3 9 7 27 24 11 16 3 0 0 100 101.25-123.75 ESE 0 3 1 3 14 37 20 10 9 1 3 101 123.75-146.25 SE 0 0 4 5 19 26 72 90 112 15 4 347 146.25-168.75 SSE 0 0 5 6 30 27 24 30 21 3 1 147 168.75-191.25 S 0 0 6 13 32 27 26 19 19 6 5 153 191.25-213.75 SSW 0 1 4 18 38 17 8 14 10 3 0 113 213.75 -236.25 SW 0 2 5 13 47 36 24 14 5 0 0 146 236.25 -258.75 WSW 0 1 7 11 42 43 25 14 5 0 0 148 258.75- 281.25 W 0 1 4 17 22 30 26 12 9 1 0 122 281.25 -303.75 WNW 0 1 8 12 23 17 19 13 12 0 0 105 303.75- 326.25 NW 0 1 10 15 40 43 25 17 16 4 0 171 326.25 -348.75 NNW 0 0 6 7 48 35 29 13 2 0 0 140 Total 2,176 MISSING HOURS: 8 101 m m m m m m m m -m m m m m -m m m m m =m m --=m-- m-- min -2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS APRIL -JUNE 2011 (02)WIND LEVEL: 33 FT DELTA T: (300-33 FT)ALL STABILITY CLASSES FREQUENCY

(%)WIND 5~P~FD (RDLJP5~ (m/~r'~WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.092 0.046 0.551 1.930 1.195 0.551 0.322 0.000 0.000 0.000 4.69 11.25 -33.75 NNE 0.000 0.000 0.276 0.230 1.884 1.103 0.322 0.046 0.000 0.000 0.000 3.86 33.75 -56.25 NE 0.000 0.000 0.322 0.597 1.608 1.195 0.873 0.046 0.138 0.000 0.000 4.78 56.25 -78.75 ENE 0.000 0.138 0.414 0.873 1.333 0,735 0.414 0.184 0.184 0.000 0.000 4.27 78.75 -101.25 E 0.000. 0.138 0.414 0.322 1.241 1.103 0.506 0.735 0.138 0.000 0.000 4.60 101.25 -123.75 ESE 0.000 0.138 0.046 0.138 0.643 1.700 0.919 0.460 0.414 0.046 0.138 4.64 123.75 -146.25 SE 0.000 0.000 0.184 0.230 0.873 1.195 3.309 4.136 5.147 0.689 0.184 15.95 146.25 -168.75 SSE 0.000 0.000 0.230 0.276 1.379 1.241 1.103 1.379 0.965 0.138 0.046 6.76 168.75 -191.25 5 0.000 0.000 0.276 0.597 1.471 1.241 1.195 0.873 0.873 0.276 0.230 7.03 191.25 -213.75 SSW 0.000 0.046 0.184 0.827 1.746 0.781 0.368 0.643 0.460 0.138 0.000 5.19 213.75 -236.25 SW 0.000 0.092 0.230 0.597 2.160 1.654 1.103 0.643 0.230 0.000 0.000 6.71 236.25 -258.75 WSW 0.000 0.046 0.322 0.506 1.930 1.976 1.149 0.643 0.230 0.000 0.000 6.80 258.75 -281.25 W 0.000 0.046 0.184 0.781 1.011 1.379 1.195 0.551 0.414 0.046 0.000 5.61 281.25 -303.75 WNW 0.000 10.046 0.368 0.551 1.057 0.781 0.873 0.597 0.551 0.000 0.000 4.83 303.75 -326.25 NW 0.000 0.046 0.460 0.689 1.838 1.976 1.149 0.781 0.735 0.184 0.000 7.86 326.25 -348.75 NNW 0.000 0.000 0.276 0.322 2.206 1.608 1.333 0.597 0.092 0.000 0.0001 6.43 Total 100.00 102 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT I I Lapse Rate I Wind Distributions 300- 33 foot I 7/2011 -9/2011 I I I I I I I I I I I I 103 I 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: LE -1.90 DEG C/100M, STABILITY CLASS A TOTAL HOURS WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1--6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 0 0 0 0 0 0 0 0 0 11.25 -33.75 NNE 0 0 0 0 0 0 0 0 0 0 0 0 33.75 -56.25 NE 0 0 0 0 0 0 0 0 0 0 0 0 56.25 -78.75 ENE 0 0 0 0 1 0 0 0 0 0 0 1 78.75 -101.25 E 0 0 0 0 0 0 0 0 0 0 0 0 101.25- 123.75 ESE 0 0 0 -0 0 0 0 0 0 0 0 0 123.75- 146.25 SE 0 0 0 0 0 0 0 1 2 1 0 4 146.25 -168.75 SSE 0 .0 0 0 0 0 4 2- 3 0 0 9 168.75- 191.25 S 0 0 0 0 0 0 0 0 0 0 0 0 191.25 -213.75 SSW 0 0 0 0 1 0 0 0 0 0 0 1 213.75 -236.25 SW 0 0 0 0 1 2 0 0 0 0 0 3 236.25 -258.75 WSW 0 0 0 0 0 0 0 0 0 0 0 0 258.75 -281.25 W 0 0 0 0 0 0 0 0 0 0 0 0 281.25 -303.75 WNW 0 0 0 0 0 0 0 0 0 0 0 0 303.75 -326.25 NW 0 0 0 0 0 0 0 0 0 0 0 0 326.25 -348.75 NNW 0 0 0 0 0 0 0 0 0 0 0 0 Total 18 104 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (03)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: LE -1.90 DEG C/100M, STABILITY CLASS A FREQUENCY

(%)WIND SPEED GRO1UPS (mIseci WIND DIRECTION

<0.5 0.5- 1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1-5.0 5.1-6.0. 6.1 -8.0 8.1-10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 33.75 -56.25 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.045 0.000 0.000 0.000 0.000 0.000 0.000 0.05 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 101.25 -123.75 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 123.75 -146.25 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.045 0.091 0.045 0.000 0.18 146.25 -168.75 SSE 0.000 0.000 0.000 0.000 0.000 0.000 0.182 0.091 0.136 0.000 0.000 0.41 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.045 0.000 0.000 0.000 0.000 0.000 0.000 0.05 213.75 -236.25 SW 0.000 0.000 0.000 0.000 0.045 0.091 0.000 0.000 0.000 0.000 0.000 0.14 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 258.75 -281.25 W 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 303.75 -326.25 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 Total 0.82 105-m -m m m -m m --------

2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.89 TO -1.70 DEG C/100M, STABILITY CLASS B TOTAL HOURS WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 0 0 0 0 0 0 0 0 0 11.25 -33.75 NNE 0 0 0 0 2 0 0 0 0 0 0 2.33.75 -56.25 NE 0 0 0 0 0 1 1 0 0 0 0 2 56.25 -78.75 ENE 0 0 0 0 0 0 0 ....0 0 0 0 0 78.75 -101.25 E 0 0 0 0 0 0 0 0 0 0 0 0 101.25 -123.75 ESE 0 0 0 0 0 1 0 0 0 0 0 1 123.75- 146.25 SE 0 0 0 0 0 2 0 0 0 0 0 2 146.25 -168.75 SSE 0 0 0 1 1 4 2 0 1 0 0 9 168.75 -191.25 S 0 0 0 0 3 0 0 0 0 0 0 3 191.25 -213.75 SSW 0 0 0 0 3 2 1 0 0 0 0 6 213.75 -236.25 SW 0 0 0 0 8 7 2 0 0 0 0 17 236.25 -258.75 WSW 0 0 0 0 0 0 1 0 0 0 0 1 258.75 -281.25 W 0 0 0 0 0 0 0 0 0 0 0 0 281.25 -303.75 WNW 0 0 0 0 0 0 0 1 0 0 0 1 303.75 -326.25 NW 0 0 0 0 0 0 0 0 0 0 0 0 326.25- 348.75 NNW 0 0 0 1 0 0 0 0 0 0 0 1 Total 45 106 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.89 TO -1.70 DEG C/100M, STABILITY CLASS B FREQUENCY

(%)WIND SPEED GROUPS (mIsee1 WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.091 0.000 0.000 0.000 0.000 0.000 0.000 0.09 33.75 -56.25 NE 0.000 0.000 0.000 0.000 0.000 0.045 0.045 0.000 0.000 0.000 0.000 0.09 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 101.25 -123.75 ESE 0.000 0.000 0.000 0.000 0.000 0.045 0.000 0.000 0.000 0.000 0.000 0.05 123.75 -146.25 SE 0.000 0.000 0.000 0.000 0.000 0.091 0.000 0.000 0.000 0.000 0.000 0.09 146.25 -168.75 SSE 0.000 0.000 0.000 0.045 0.045 0.182 0.091 0.000 0.045 0.000 0.000 0.41 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.136 0.000 0.000 0.0)00 0.000 0.000 0.000 0.14 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.136 0.091 0.045 0.000 0.000 0.000 0.000 0.27 213.75 -236.25 SW 0.000 0.000 0.000 0.000 0.363 0.318 0.091 0.000 0.000 0.000 0.000 0.77 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.000 0.000 0.045 0.000 0.000 0.000 0.000 0.05 258.75 -281.25 W 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.045 0.000 0.000 0.000 0.05 303.75 -326.25 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 326.25 -348.75 NNW 0.000 0.000 0.000 0.045 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.05 Total 2.04 107 mm -m m m m -m -u m m m -m m m 2 01 m -m RDA -E --m -EP OR 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE.REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.69 TO -1.50 DEG C/100M, -STABILITY CLASS C TOTAL HOURS WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 m 1.5 1.6-2.0 2.1 -3.0 3.1-4.0 4.1-5.0 5.1-6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 0 2 2 0 0 0 0 0 4 11.25 -33.75 NNE 0 0 0 0 0 1 1 0 0 0 0 2 33.75 -56.25 NE 0 0 1 0 0 1 1 0 0 0 0 3 56.25 -78.75 ENE 0 0 0 0 0 0 0 0 0 0 0 0 78.75 -101.25 E 0 0 0 0 2 0 0 0 0 0 0 2 101.25 -123.75 ESE 0 1 0 0 0 0 0 0 0 0 0 1 123.75 -146.25 SE 0 0 0 1 1 3 1 1 5 1 0 13 146.25 -168.75 SSE 0 0 0. 1 10 3 1 2 0 1 0 18 168.75 -191.25 S 0 0 0 0 5 1 1 1 2 0 0 10 191.25 -213.75 SSW 0 0 0 0 3 0 2 0 0 0 0 5 213.75 -236.25 SW 0 0 .0 2 4 1 2 0 0 0 0 9 236.25 -258.75 WSW 0 0 0 0 2 5 2 0 0 0 0 9 258.75 -281.25 W 0 0 0 0 1 1 1 2 0 0 0 5 281.25 -303.75 WNW 0 0 0 1 0 0 4 2 0 0 0 7 303.75- 326.25 NW- 0 0 0 0 1 0 3 3 0 0 0 7 326.25 -348.75 NNW 0 0 1 0 2 1 1 1 0 0 0 6 Total 101 108 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.69 TO -1.50 DEG C/100M, STABILITY CLASS C FREQUENCY

(%)WINfl RPF:I=l R('PliJP5 (m/Iqr~e WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.091 0.091 0.000 0.000 0.000 0.000 0.000 0.18 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.000 0.045 0.045 0.000 0.000 0.000 0.000 0.09 33.75 -56.25 NE 0.000 0.000 0.045 0.000 0.000 0.045 0.045 0.000 0.000 0.000 0.000 0.14 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.091 0.000 0.000 0.000 0.000 0.000 0.000 0.09 101.25 -123.75 ESE 0.000 0.045 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.05 123.75 -146.25 SE 0.000 0.000 0.000 0.045 0.045 0.136 0.045 0.045 0.227 0.045 0.000 0.59 146.25 -168.75 SSE 0.000 0.000 0.000 0.045 0.454 0.136 0.045 0.091 0.000 0.045 0.000 0.82 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.227 0.045 0.045 0.045 0.091 0.000 0.000 0.45 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.136 0.000 0.091 0.000 0.000 0.000 0.000 0.23 213.75 -236.25 SW 0.000 0.000 0.000 0.091 0.182 0.045 0.091 0.000 0.000 0.000 0.000 0.41 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.091 0.227 0.091 0.000 0.000 0.000 0.000 0.41 258.75 -281.25 W 0.000 0.000 0.000 0.000 0.045 0.045 0.045 0.091 0.000 0.000 0.000 0.23 281.25 -303.75 WNW 0.000 0.000 0.000 0.045 0.000 0.000 0.182 0.091 0.000 0.000 0.000 0.32 303.75 -326.25 NW 0.000 0.000 0.000 0.000 0.045 0.000 0.136 0.136 0.000 0.000 0.000 0.32 326.25 -348.75 NNW 0.000 0.000 0.045 0.000 0.091 0.045 0.045 0.045 0.000 0.000 0.000 0.27 Total 4.58 109=m m = m mu m m mm =- m = =

Sm m- -- I m m -m -m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.49 TO -0.50 DEG C/100M, STABILITY CLASS D TOTAL HOURS WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 1 4 13 15 18 6 5 0 2 0 64 11.25 -33.75 NNE 0 0 6 8 5 8 10 2 0 2 1 42 33.75 -56.25 NE 0 0 2 3 16 24 12 5 5 7 1 75 56.25 -78.75 ENE 0 0 3 3 10 8 1 1 0 0 0 26 78.75 -101.25 E 0 0 3 8 8 2 0 0 0 0 0 21 101.25 -123.75 ESE 0 2 6 2 6 10 4 1 0. 0 0 31 123.75 -146.25 SE 0 1 2 7 11 22 29 35 38 5 1 151 146.25 -168.75 SSE 0 1 3 11 24 27 26 29 12 6 0 139 168.75- 191.25 S 0 3 9 16 25 28 19 19 15 1 0 135 191.25-213.75 SSW 0 1 5 14 22 27 15 9 5 0 0 98 213.75 -236.25 SW 0 2 4 10 25 17 18 4 0 0 0 80 236.25 -258.75 WSW 0 0 3 4 17 6 4 --2 2 0 1 39 258.75 -281.25 W 0 0 6 2 16 11 2 2 0 2 3 44 281.25 -303.75 WNW 0 0 1 4 6 8 15 0 1 1 3 39 303.75 -326.25 NW 0 1 2 4 16 15 8 4 1 0 1 52 326.25 -348.75 NNW 0 1 2 10 17 21 6 2 2 2 0 63 Total 1,099 110 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.49 TO -0.50 DEG C/lOOM, STABILITY CLASS D FREQUENCY

(%)WIND SPEED GROUPS (mlsec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1-4.0 4.1-5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.045 0.182 0.590 0.681 0.817 0.272 0.227 0.000 0.091 0.000 2.91 11.25 -33.75 NNE 0.000 0.000 0.272 0.363 0.227 0.363 0.454 0.091 0.000 0.091 0.045 1.91 33.75 -56.25 NE 0.000 0.000 0.091 0.136 0.726 1.089 0.545 0.227 0.227 0.318 0.045 3.40 56.25 -78.75 ENE 0.000 0.000 0.136 0.136 0.454 0.363 0.045 0.045 0.000 0.000 0.000 1.18 78.75 -101.25 E 0.000 0.000 0.136 0.363 0.363 0.091 0.000. 0.000 0.000 0.000 0.000 0.95 101.25 -123.75 ESE 0.000 0.091 0.272 0.091 0.272 0.454 0.182 0.045 0.000 0.000 0.000 1.41 123.75 -146.25 SE 0.000 0.045 0.091 0.318 0.499 0.999 1.316 1.589 1.725 0.227 0.045 6.85 146.25 -168.75 SSE 0.000 0.045 0.136 0.499 1.089 1.226 1.180 1.316 0.545 0.272 0.000 6.31 168.75 -191.25 5 0.000 0.136 0.409 0.726 1.135 1.271 0.862 0.862 0.681 0.045 0.000 6.13 191.25 -213.75 SSW 0.000 0.045 0.227 0.635 0.999 1.226 0.681 0.409 0.227 0.000 0.000 4.45 213;75 -236.25 SW 0.000 0.091 0.182 -0.454 1.135 0.772 0.817 0.182 0.000 0.000 0.000 3.63 236.25 -258.75 WSW 0.000 0.000 0.136 0.182 0.772 0.272 0.182 0.091 0.091 0.000 0.045 1.77 258.75 -281.25 W 0.000 0.000 0.272 0.091 0.726 0.499 0.091 0.091 0.000 0.091 0.136 2.00 281.25 -303.75 WNW 0.000 0.000 0.045 0.182 0.272 0.363 0.681 0.000 0.045 0.045 0.136 1.77 303.75 -326.25 NW 0.000 0.045 0.091 0.182 0.726 0.681 0.363 0.182 0.045 0.000 0.045 2.36 326.25 -348.75 NNW 0.000 0.045 0.091 0.454 0.772 0.953 0.272 0.091 0.091 0.091 0.000 28 Total 49.89 ill m m m m m -m m m m mm m m m -o=,= mmm m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (03)WIND LEVEL: 33 FT .DELTA T: (300-33 FT)LAPSE RATE: -0.49 TO 1.50 DEG C/100M, STABILITY CLASS E TOTAL HOURS WIND SPEED GROUPS (mn/sect WIND DIRECTION

<0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1-4.0 4.1-5.0 5.1-6.0 6.1 -8.0 8.1 -10.0 >10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 5 6 4 10 6 4 2 2 2 0 41 11.25-33.75 NNE 0 1 4 7 9 5 0 2 0 0 0 28 33.75 -56.25 NE 0 5 2 10 11 5 0 1 0 0 0 34 56.25 -78.75 ENE 0 1 9 12 2 2 2 0 0 0 0 28 78.75 -101.25 E 0 5 11 8 4 4 0 0 0 0 0 32 101.25 -123.75 ESE 0 2 1 6 17 8 1 2 0 0 0 37 123.75 -146.25 SE 0 1 5 3 12 16 15 14 5 1 0 72 146.25 -168.75 SSE 0 2 2 6 17 15 9 8 0 0 0 59 168.75 -191.25 S 0 3 0 1 14 5 10 4 1 0 0 38 191.25 -213.75 SSW 0 0 3 7 23 23 11 4 0 1 0 72 213.75 -236.25 SW 0 0 4 12 32 18 14 0 0 0 0 80 236.25 -258.75 WSW 0 1 6 11 24 23 3 0 1 0 0 69 258.75 -281.25 W 0 0 5 6 19 11 0 0 1 0 0 42 281.25 -303.75 WNW 0 0 2 5 18 13 2 1 0 0 0 41 303.75 -326.25 NW 0 0 6 6 22 21 3 0 0 0 0 58 326.25 -348.75 NNW 0 4 6 6 14 4 1 1 1 0 0 37 Total 768 112 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -0.49 TO 1.50 DEG C/100M, STABILITY CLASS E FREQUENCY

(%)WIND SPEED GROUPS WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1-5.0 5.1-6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.227 0.272 0.182 0.454 0.272 0.182 0.091 0.091 0.091 0.000 1.86 11.25 -33.75 NNE 0.000 0.045 0.182 0.318 0.409 0.227 0.000 0.091 0.000 0.000 0.000 1.27 33.75 -56.25 NE 0.000 0.227 0.091 0.454 0.499 0.227 0.000 0.045 0.000 0.000 0.000 1.54 56.25 -78.75 ENE 0.000 0.045 0.409 0.545 0.091 0.091 0.091 0.000 0.000 0.000 0.000 1.27 78.75- 101.25 E 0.000 0.227 0.499 0.363 0.182 0.182 0.000 0.000 0.000 0.000 0.000 1.45 101.25 -123.75 ESE 0.000 0.091 0.045 0.272 0.772 0.363 0.045 0.091 0.000 0.000 0.000 1.68 123.75 -146.25 SE 0.000 0.045 0.227 0.136 0.545 0.726 0.681 0.635 0.227 0.045 0.000 3.27 146.25 -168.75 SSE 0.000 0.091 0.091 0.272 0.772 0.681 0.409 0.363 0.000 0.000 0.000 2.68 168.75 -191.25 S 0.000 0.136 0.000 0.045 0.635 0.227 0.454 0.182 0.045 0.000 0.000 1.72 191.25 -213.75 SSW 0.000 0.000 0.136 0.318 1.044 1.044 0.499 0.182 0.000 0.045 0.000 3.27-213:75- 236.25 SW 0.000 0.000 0.182 0.545 1.453 0.817 0.635 0.000 0.000 0.000 0.000 3.63 236.25 -258.75 WSW 0.000 0.045 0.272 0.499 1.089 1.044 0.136 0.000 0.045 0.000 0.000 3.13 258.75 -281.25 W 0.000 0.000 0.227 0.272 0.862 0.499 0.000 0.000 0.045 0.000 0.000 1.91 281.25 -303.75 WNW 0.000 0.000 0.091 0.227 0.817 0.590 0.091 0.045 0.000 0.000 0.000 1.86 303.75 -326.25 NW 0.000 0.000 0.272 0.272 0.999 0.953 0.136 0.000 0.000 0.000 0.000 2.63 326.25 -348.75 NNW 0.000 0.182 0.272 0.272 0.635 0.182 0.045 0.045 0.045 0.000 0.000 1.68 Total 34.86 113=mM 1mm m s m m m mm 1ýM m m ý1 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: 1.51 TO 4.00 DEG C/100M, STABILITY CLASS F TOTAL HOURS WIND RPEED GROtJPq WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 1 1 1 15 9 0 0 0 0 0 27 11.25-33.75 NNE 0 0 2- 6 16 2 0- 0 0 0 0 *26 33.75 -56.25 NE 0 0 1 7 4. 2 0 0 0 0 0 14 56.25- 78.75 ENE 0 0 5 5 1 0 0 0 0 0 0 11 78.75- 101.25 E 0- 1 2 2 1 0 0 0 0 0 0 6 101.25 -123.75 ESE 0 0 1 0 5 1 0 0 0 0 0 7 123.75- 146.25 SE 0 1 1 1 5 1 4 2 0 0 0 15 146.25- 168.75 SSE 0 0 0 0 3 0 0 0 0 0 0 3 168.75-191.25 S 0 0 0 1 3 1 0 0 0 0 0 5 191.25 -213.75 SSW 0 0 1 2 1 3 0 0 0 0 0 7 213.75 -236.25 SW 0 0 0 0 6 2 0 0 0 0 0 8 236.25 -258.75 WSW 0 0 1 2 5 0 0 0 0 0 0 8 258.75 -281.25 W 0 0 1 1 4 0 0 0 0 0 0 6 281.25 -303.75 WNW 0 0 0 0 1 0 0 0 0 0 0 1 303.75 -326.25 NW 0 0 0 2 6 0 0 -0 0 0 0 8 326.25 -348.75 NNW 0. 1 0 5 6 2 0 0- 0 0 0 14 Total 166 114 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: 1.5.1 TO 4.00 DEG C/100M, STABILITY CLASS F FREQUENCY

(%)WIND SPEED GROUPS WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.045 0.045 0.045 0.681 0.409 0.000 0.000 0.000 0.000 0.000 1.23 11.25 -33.75 NNE 0.000 0.000 0.091 0.272 0.726 0.091 0.000 0.000 0.000 0.000 0.000 1.18 33.75 -56.25 NE 0.000 0.000 0.045 0.318 0.182 0.091 0.000 0.000 0.000 0.000 0.000 0.64 56.25 -78.75 ENE 0.000 0.000 0.227 0.227 0.045 0.000 0.000 0.000 0.000 0.000 0.000 0.50 78.75 -101.25 E 0.000 0.045 0.091 0.091 0.045 0.000 0.000 0.000 0.000 0.000 0.000 0.27 101.25 -123.75 ESE 0.000 0.000 0.045 0.000 0.227 0.045 0.000 0.000 0.000 0.000 0.000 0.32 123.75 -146.25 SE 0.000 0.045 0.045 0.045 0.227 0.045 0.182 0.091 0.000 0.000 0.000 0.68 146.25 -168.75 SSE 0.000 0.000 0.000 0.000 0.136 0.000 0.000 0.000 0.000 0.000 0.000 0.14 168.75 -191.25 S 0.000 0.000 0.000 0.045 0.136 0.045 0.000 0.000 0.000 0.000 0.000 0.23 191.25 -213.75 SSW 0.000 0.000 0.045 0.091 0.045 0.136 0.000 0.000 0.000 0.000 0.000 0.32 213175- 236.25 SW- ..0.000 -0.000 0.000 0.000 -0.272 -0.091 0.000 0.000 0.000 0.000- 0.000 0.36 236.25 -258.75 WSW 0.000 0.000 0.045 0.091 0.227 0.000 0.000 0.000 0.000 0.000 0.000 .0.36 258.75 -281.25 W 0.000 0.000 0.045 0.045 0.182 0.000 0.000 0.000 0.000 0.000 0.000 0.27 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.045 0.000 0.000 0.000 0.000 0.000 0.000 0.05 303.75 -326.25 NW 0.000 0.000 0.000 0.091 0.272 0.000 0.000 0.000 0.000 0.000 0.000 0.36 326.25 -348.75 NNW 0.000 0.045 0.000 0.227 0.272 0.091 0.000 0.000 0.000 0.000 0.000 0.64 Total 7.54 115 mm m m m m J mm -mmmm -

2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: GT 4.00 DEG C/100M, STABILITY CLASS G TOTAL HOURS WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5- 1.0 1.1 -1.5 1.6- 2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 0 0 0 0 0 0 0 0 0 11.25 -33.75 NNE* 0 0 0 0 1 0 0 0 0 0 0 1 33.75 -56.25 NE 0 0 1 0 1 0 0 0 0 0 0 2 56.25 -78.75 ENE 0 0 0 3 0 0 0 0 0 0 0 3 78.75 -101.25 E 0 0 0 0 0 0 0 0 0 0 0 0 101.25 -123.75 ESE 0 0 0 0 0 0 0 0 0 0 0 0 123.75 -146.25 SE 0 0 0 0 0 0 0 0 0 0 0 0 146.25 -168.75 SSE 0 0 0 0 0 0 0 0 0 0 0 0 168.75 -191.25 S 0 0 0 0 0 0- 0 0 0 0 0 0 191.25 -213.75 SSW 0 0 0 0 0 0 0 0 0 0 0 0 213.75 -236.25 SW 0 0 0 0 0 0 0 0 0 0 0 0 236.25 -258.75 WSW 0 0 0 0 0 0 0 0 0 0 0 0 258.75 -281.25 W 0 0 0 0 0 0 0 0 0 0 0 0 281.25 -303.75 WNW 0 0 0 0 0 0 0 0 0 0 0 0 303.75 -326.25 NW 0 0 0 0 0 0 0 0 0 0 0 0 326.25 -348.75 NNW 0 0 0 0 0. 0 0 0 0 0 0 0 Total 6 116 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: GT 4.00 DEG C/100M, STABILITY CLASS G FREQUENCY

(%)WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1-4.0 4.1-5.0 5.1-6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.000 0.000 0.000 -0.000 0.000 0.000 0.000 0.00 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.045 0.000 0.000 0.000 0.000 0.000 0.000 0.05 33.75 -56.25 NE 0.000 0.000 0.045 0.000 0.045 0.000 0.000 0.000 0.000 0.000 0.000 0.09 56.25 -78.75 ENE 0.000 0.000 0.000 0.136 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.14 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 101.25 -123.75 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 123.75 -146.25 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 146.25 -168.75 SSE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 213.75- 236.25 SW 1 0.000 0.000 0.000 0.000 0.000 0.000ý -0.000- 0.000 0.000 0.000 0.000 0.00 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 258.75 -281.25 W 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 303.75 -326.25 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 Total 0.27 117 m m m mm mm m m m -mm m m mm m= m mm m mmm mm mm 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF.WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)ALL STABILITY CLASSES TOTAL HOURS WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1-4.0 4.1-5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 7 11 18 42 35 10 7 2 4 0. 136 11.25 -33.75 NNE 0 1 12 21 33 16 11 4 0 2 1 101 33.75 -56.25 NE 0 5 7 20 32 33 14 6 5 7 1 130 56.25 -78.75 ENE 0 1 17 23 14 10 3 1 0 0 0 69 78.75 -101.25 E 0 6 16 18 15 6 0 0 0 0 0 61 101.25 -123.75 ESE 0 5 8 8 28 20 5 3 0 0 0 77 123.75- 146.25 SE 0 3 8 12 29 44 49 53 50 8 1 257 146.25 -168.75 SSE 0 3 5 19 55 49 42 41 16 7 0 237 168.75 -191.25 S 0 6 9 18 50 35 30 24 18 1 0 191 191.25 -213.75 SSW 0 1 9 23 53 55 29 13 5 1 .0 189 213.75 -236.25 SW 0 2 8 24 76 47 36 4 0 0 0 197 236.25 -258.75 WSW 0 1 10 17 48 34 10 2 3 0 1 126 258.75 -281.25 W 0 0 12 9 40 23 3 4 1 2 3 97 281.25 -303.75 WNW 0 0 3 10 25 21 21 4 1 1 3 89 303.75 -326.25 NW 0 1 8 12 45 36 14 7 1 0 1 125 326.25 -348.75 NNW 0 6 9 22 39 28 8 4 3 2 -0 121 Total 2,203 118 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JULY -SEPTEMBER 2011 (Q3)WIND LEVEL: 33 FT DELTA T: (300-33 FT)ALL STABILITY CLASSES FREQUENCY

(%)WIND SPEED GROUPS WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.318 0.499 0.817 1.906 1.589 0.454 0.318 0.091 0.182 0.000 6.17 11.25 -33.75 NNE 0.000 0.045 0.545 0.953 1.498 0.726 0.499 0.182 0.000 0.091 0.045 4.58 33.75 -56.25 NE 0.000 0.227 0.318 0.908 1.453 1.498 0.635 0.272 0.227 0.318 0.045 5.90 56.25 -78.75 ENE 0.000 0.045 0.772 1.044 0.635 0.454 0.136 0.045 0.000 0.000 0.000 3.13 78.75 -101.25 E 0.000 0.272 0.726 0.817 0.681 0.272 0.000 0.000 0.000 0.000 0.000 2.77 101.25 -123.75 ESE 0.000 0.227 .0.363 0.363 1.271 0.908 0.227 0.136 0.000 0.000 0.000 3.50 123.75 -146.25 SE 0.000 0.136 0,363 0.545 1.316 1.997 2.224 2.406 2.270 0.363 0.045 11.67 146.25 -168.75 SSE 0.000 0.136 0.227 0.862 2.497 2.224 1.906 1.861 0.726 0.318 0.000 10.76 168.75 -191.25 S 0.000 0.272 0.409 0.817 2.270 1.589 1.362 1.089 '0.817 0.045 0.000 8.67 191.25 -213.75 SSW 0.000 0.045 0.409 1.044 2.406 2.497 1.316 0.590 0.227 0.045 0.000 8.58 213.75 -236.25 SW 0.000 0.091 0.363 1-.089 3.450 2.133 1.634 0.182 0.000 0.000 0.000 8.94 236.25 -258.75 WSW 0.000 0.045 0.454 0.772 2.179 1.543 0.454 0.091 0.136 0.000 0.045 5.72 258.75 -281.25 W 0.000 0.000 0.545 0.409 1.816 1.044 0.136 0.182 0.045 0.091 0.136 4.40 281.25 -303.75 WNW 0.000 0.000 0.136 0.454 1.135 0.953 0.953 0.182 0.045 0.045 0.136 4.04 303.75 -326.25 NW 0.000 0.045 0.363 0.545 2.043 1.634 0.635 0.318 0.045 0.000 0.045 5.67 326.25 -348.75 NNW 0.000 0.272 0.409 0.999 1.770 1.271 0.363 0.182 0.136 0.091 0.000 5.49 Total 100.00 119 m -m'ý m I m N m m m m- m m --m m m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Lapse Rate Wind Distributions 300- 33 foot 10/2011 -12/2011 120 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: LE -1.90 DEG C/1OOM, STABILITY CLASS A TOTAL HOURS WIND SPEED GROUPS (m/seci WIND DIRECTION

<015 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 0 0 0 0 0 0 0 0 0 11.25 -33.75 NNE 0 0 0 0 0 0 0 0 0 0 0 0 33.75 -56.25 NE 0 0 0 0 0 0 1 0 0 0 0 1 56.25 -78.75 ENE 0 0 0 0 0 0 0 0 0 0 0 0 78.75 -101.25 E 0 0 0 0 0 0 0 0 0 0 0 0 101.25 -123.75 ESE 0 0 0 0 0 0 0 0 0 0 0 0 123.75 -146.25 SE 0 0 0 0 0 0 3 0 0 0 0 3 146.25 -168.75 SSE 0 0 0 0 0 0 0 0 0 0 0 0 168.75 -191.25 S 0 0 0 0 0 0 0 .0 0 0 0 0 191.25 -213.75 SSW 0 0 0 0 0 0 0 0 0 0 0 0 213.75 -236.25-- SW 0 0 '-0 0 1 0 0 0 0 0 0 1 236.25 -258.75 WSW 0 0 0 0 0 0 0 0 0 0 0 0 258.75 -281.25 W 0 0 0 0 0 0 0 0 0 0 0 0 281.25 -303.75 WNW 0 0 0 0 0 0 0 1 0 0 0 1 303.75 -326.25 NW 0 0 0 0 0 0 0 0 0 0 0 0 326.25 -348.75 NNW 0 0 0 0 0 0 0 1 0 0 0 1 Total 7 121 m m mm -mm m m MmM mm mm m m

= m m m = m m nm m m m m m I m m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: LE -1.90 DEG C/1OOM, STABILITY CLASS A FREQUENCY

(%)WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 33.75 -56.25 NE 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.05 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 101.25 -123.75 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 123.75- 146.25 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.137 0.000 0.000 0.000 0.000 0.14 146.25- 168.75 SSE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 213.75 -236.25 SW 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.05 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 258.75 -281.25 W 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.05 303.75 -326.25 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.05 Total 0.32 122 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK ...JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.89 TO -1.70 DEG C/100M, STABILITY CLASS B TOTAL HOURS WIND SPEED GROUPS (m/seci WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect. _348.75 -11.25 N 0 0 0 0 0 0 0 0 0 0 0 0 11.25 -33.75 NNE 0 0 0 0 0 1 3 2 0 0 0 6 33.75 -56.25 NE 0 0 0 0 0 1 1 0 0 0 0 2 56.25 -78.75 ENE 0 0 0 0 0 0 0 0 0 0 0 0 78.75 -101.25 E 0 0 0 0 0 0 0 0 0 0 0 0 101.25 -123.75 ESE 0 0 0 0 0 0 0 0 0 0 0 0 123.75 -146.25 SE 0 0 0 0 0 2 3 0 0 0 0 5 146.25 -168.75 SSE 0 0 0 0 0 0 0 0 0 0 0 0 168.75 -191.25 S 0 0 0 0 0 0 0 0 0 0 0 0 191.25 -213.75 SSW 0 0 0 0 0 0 5 1 1 1 0 8 213.75 -236:25 SW 0 0 0 0 1 0 1 0 0 0 0 2 236.25 -258.75 WSW 0 0 0 0 0 3 1 2 2 0 0 8 258.75 -281.25 W 0 0 0 0 0 1 1 2 1 0 0 5 281.25 -303.75 WNW 0 0 0 0 0 1 .0 1 2 0 0 4 303.75 -326.25 NW 0 0 0 0 0 2 8 2 2 0 0 14 326.25 -348.75 NNW 0 0 0 0 0 0 3 0 1 0 0 4 Total 58 123 m m m m m mm m mm m m m mm al m m =

m 2 -m m m m mFERLSEO 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.89 TO -1.70 DEG C/1OOM, STABILITY CLASS B FREQUENCY

(%)WlNfl WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1-5.0 5.1-6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.000 0.046 0.137 0.091 0.000 0.000 0.000 0.27 33.75 -56.25 NE 0.000 0.000 0.000 0.000 0.000 0.046 0.046 0.000 0.000 0.000 0.000 0.09 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 101.25 -123.75 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 123.75 -146.25 SE 0.000 0.000 0.000 0.000 0.000 0.091 0.137 0.000 0.000 0.000 0.000 0.23 146.25 -168.75 SSE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.000 0.000 0.228 0.046 0.046 0.046 0.000 0.36 213.75 -236.25 SW 0.000 0.000 0.000 0.000 0.046 0.000 0.046 0.000 0.000 0.000 0.000 0.09 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.000 0.137 0.046 0.091 0.091 0.000 0.000 0.36 258.75 -281.25 W 0.000 0.000 0.000 0.000 0.000 0.046 0.046 0.091 0.046 0.000 0.000 0.23 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.046 0.091 0.000 0.000 0.18 303.75 -326.25 NW 0.000 0.000 0.000 0.000 0.000 0.091 0.365 -0.091 0.091 0.000 0.000 0.64 326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.000 0.000 0.137 0.000 0.046 0.000 0.000 0.18 Total 2.64 124 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.69 TO -1.50 DEG C/100M, STABILITY CLASS C TOTAL HOURS WINfl 5RPEfD CROUJP5 (m/se&I WIND DIRECTION

<0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 0 0 1 2 1 0 0 0 0 4 11.25 -33.75 NNE 0 0 0 0 2 3 2 2 2 0 0 11 33.75 -56.25 NE 0 0 0 0 1 0 0 0 0 0 0 1 56.25 -78.75 ENE 0 0 0 0 0 0 0 0 0 0 0 0 78.75 -101.25 E 0 0 0 0 1 0 0 0 0 0 0 1 101.25 -123.75 ESE 0 0 0 0 0 1 0 0 0 0 0 1 123.75 -146.25 SE 0 0 0 0 2 1 2 0 0 0 0 5 146.25 -168.75 SSE 0 0 0 0 2 0 1 0 0 0 0 3 168.75 -191.25 S 0 0 0 0 0 0 1 0 0 0 0 1 191.25 -213.75 SSW 0 0 0 0 0 1 0 6 0 0 0 7 213.75 -236.25 SW 0 0 0 1 1 2 1 1 0 1 0 7 236.25 -258.75 WSW 0 0 0 0 4 3 0 -0 2 1 0 10 258.75 -281.25 W 0 0 0 1 0 3 1 0 1 0 0 6 281.25 -303.75 WNW 0 0 0 0 2 5 1 0 2 1 0 11 303.75 -326.25 NW 0 0 0 1 3 4 10 3 4 2 0 27 326.25 -348.75 NNW 0 0 0 0 1 1 2 3 1 0 0 8 Total 103 125 m m m m m ý mm mm m mm mm m m m m m m m m ANDm m m -AmOmTV m m m -RmPmRm 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.69 TO -1.50 DEG C/100M, STABILITY CLASS C FREQUENCY

(%)WIND SPEED GROUPS WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.000 0.000 0.046 0.091 0.046 0.000 0.000 0.000 0.000 0.18 11.25 -33.75 NNE 0.000 0.000 0.000 0.000 0.091 0.137 0.091 0.091 0.091 0.000 0.000 0.50 33.75 -56.25 NE 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.05 56.25 -78.75 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 78.75 -101.25 E 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.05 101.25 -123.75 ESE 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.05 123.75 -146.25 SE 0.000 0.000 0.000 0.000 0.091 0.046 0.091 0.000 0.000 0.000 0.000 0.23 146.25 -168.75 SSE 0.000 0.000 0.000 0.000 0.091 0.000 0.046 0.000 0.000 0.000 0.000 0.14 168.75 -191.25 S 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.05 191.25 -213.75 SSW 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.273 0.000 0.000 0.000 0.32 213.75 -236.25 SW 0.000 0.000 0.000 0.046 0.046 0.091 0.046 0.046 0.000 0.046 0.000 0.32 236.25 -258.75 WSW 0.000 0.000 0.000 0.000 0.182 0.137 0.000 0.000 0.091 0.046 0.000 0.46 258.75 -281.25 W 0.000 0.000 0.000 0.046 0.000 0.137 0.046 0.000 0.046 0.000 0.000 0.27 281.25 -303.75 WNW 0.000 0.000 0.000 0.000 0.091 0.228 0.046 0.000 0.091 -0.046 0.000 0.50 303.75 -326.25 NW 0.000 0.000 0.000 0.046 0.137 0.182 0.456 0.137 0.182 0.091 0.000 1.23 326.25 -348.75 NNW 0.000 0.000 0.000 0.000 0.046 0.046 -0.091 0.137 0.046 0.000 0.000 0.36 Total 4.69 126 2011 SGS AND IICGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.49 TO -0.50 DEG C/1OOM, STABILITY CLASS D TOTAL HOURS WIND SPEED GROUPS WIND DIRECTION

<0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1-4.0 4.1-5.0 5.1-6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

-Sect.348.75 -11.25 N 0 0 3 0 5 3 0 1 3 6 0 21 11.25 -33.75 NNE 0 0 1 6 11 6 4 4 0 2 0 34 33.75 -56.25 NE 0 1 3 5 12 7 7 5 7 2 0 49 56.25 -78.75 ENE 0 0 3 2 7 7 2 3 2 0 0 26 78.75-101.25 E 0 1 3 2 7 5 0 0 0 0 0 18 101.25 -123.75 ESE 0 1 0 1 0 7 1 0 0 0 0 10 123.75 -146.25 SE 0 1 1 0 -0 7 15 4 4 0 0 32 146.25 -168.75 SSE 0 1 1 4 10 3 13 5 3 1 0 41 168.75 -191.25 S 0 0 2 8 6 12 17 13 4 1 0 63 191.25 -213.75 SSW 0 0 1 9 2 9 9 5 5 1 0 41 213.75 w 236.25 SW- 0 1 3 ' 1 3 16 16 3 6 8 0 57 236.25 -258.75 WSW 0 0 0 4 6 18 9 9 4 1 0 51 258.75 -281.25 W 0 0 3 0 11 10 8 17 3 1 0 53 281.25 -303.75 WNW 0 0 0 4 11 10 18 10 5 7 0 65 303.75-326.25 NW 0 0 2 1 11 21 40 25 15 4 0 119 326.25 -348.75 NNW 0 0 2 3 8 5 8 6 8 1 0 41 Total 721 127 m m m m m m m m m m m m m m m m m m m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (04)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -1.49 TO -0.50 DEG C/lOOM, STABILITY CLASS D FREQUENCY

(%)WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 -1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 .N 0.000 0.000 0.137 0.000 0.228 0.137 0.000 0.046 0.137 0.273 0.000 0.96 11.25 -33.75 NNE 0.000 0.000 0.046 0.273 0.501 0.273 0.182 0.182 0.000 0.091 0.000 1.55 33.75 -56.25 NE 0.000 0.046 0.137 0.228 0.547 0.319 0.319 0.228 0.319 0.091 0.000 2.23 56.25 -78.75 ENE 0.000 0.000 0.137 0.091 0.319 0.319 0.091 0.137 0.091 0.000 0.000 1.19 78.75 -101.25 E 0.000 0.046 0.137 0.091 0.319 0.228 0.000 0.000 0.000 0.000 0.000 0.82 101.25 -123.75 ESE 0.000 0.046 0.000 0.046 0.000 0.319 0.046 0.000 0.000 0.000 0.000 0.46 123.75 -146.25 SE 0.000 0.046 0.046 0.000 0.000 0.319 0.684 0.182 0.182 0.000 0.000 1.46 146.25 -168.75 SSE 0.000 0.046 0.046 0.182 0.456 0.137 0.593 0.228 0.137 0.046 0.000 1.87 168.75 -191.25 5 0.000 0.000 0.091 0.365 0.273 0.547 0.775 0.593 0.182 0.046 0.000 2.87 191 .25 -213.75 SSW 0.000 0.000 0.046 0.410 0.091 0.410 0.410 0.228 0.228 0.046 0.000 1.87 213.75 -236.25 SW 0.000 0.046 0.137 0.046 0.137 0.729 0.729 0.137 0.273 0.365 0.000 2.60 236.25 -258.75 WSW 0.000 0.000 0.000 0.182 0.273 0.820 0.410 0.410 0.182 0.046 0.000 2.32 258.75 -281.25 W 0.000 0.000 0.137 0.000 0.501 0.456 0.365 0.775 0.137 0.046 0.000 2.42 281.25 -303.75 WNW 0.000 0.000 0.000 -0.182 0.501 0.456 0.820 0.456 0.228 0.319 0.000 2.96 303.75 -326.25 NW 0.000 0.000 0.0911 0.046 0.501 0.957 1.823 -1.139 0.684 0.182 0.000 5.42 326.25 -348.75 NNW 0.000 0.000 0.091 0.137 0.365 0.228 0.365 0.273 0.365 0.046 0.000 1.87 Total 32.86 128 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -0.49 TO 1.50 DEG C/100M, STABILITY CLASS E TOTAL HOURS WIND SPEED GROUPS (m/sec)WIND DIRECTION

<0.5 0.5-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-4.0 4.1-5.0 5.1-6.0 6.1-8.0 8.1-10.0 >10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 2 6 14 5 7 1 2 0 0 37 11.25 -33.75 NNE 0 0 5 7 16 12 4 1 0 0 0 45 33.75 -56.25 NE 0 2 2 7 8 7 3 0 0 0 0 29 56.25- 78.75 ENE 0 0 6 6 6 2 0 0 0 0 0 20 78.75- 101.25 E 0 1 3 3 2 1 0 0 0 0 0 10 101.25 -123.75 ESE 0 2 3 3 8 5 1 2 0 0 0 24 123.75 -146.25 SE 0 1 3 4 10 20 11 2 8 5 2 66 146.25 -168.75 SSE 0 0 3 3 18 8 8 3 0 0 0 43 168.75 -191.25 S 0 2 6 3 13 20 19 10 7 1 0 81 191.25 -213.75 SSW 0 2 7 5 22 24 19 19 11 4 0 113 213.75 -236.25 SW 0 0 2 8 24 13 16 -15 6 1 0 85 236.25 -258.75 WSW 0 1 3 5 12 16 11 6 4 0 0 58 258.75 -281.25 W 0 3 3 6 9 10 6 2 1 0 0 40 281.25 -303.75 WNW 0 6 9 8 19 11 4 4 1 0 0 62 303.75 -326.25 NW 0 6 6 11 29 36 10 5 7 1 0 111 326.25 -348.75 NNW 0 0 1 3 21 24 9 5 3 0 0 66 Total 890 129 mm m m m m m m m m m m m m m m m m m m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: -0.49 TO 1.50 DEG C/lOOM, STABILITY CLASS E FREQUENCY(%

WIND SPEED GROUPS (misec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.091 0.273 0.638 0.228 0.319 0.046 0.091 0.000 0.000 1.69 11.25 -33.75 NNE 0.000 0.000 0.228 0.319 0.729 0.547 0.182 0.046 0.000 0.000 0.000 2.05 33.75 -56.25 NE 0.000 0.091 0.091 0.319 0.365 0.319 0.137 0.000 0.000 0.000 0.000 1.32 56.25 -78.75 ENE 0.000 0.000 0.273 0.273 0.273 0.091 0.000 0.000 0.000 0.000 0.000 0.91 78.75 -101.25 E 0.000 0.046 0.137 0.137 0.091 0.046 0.000 0.000 0.000 0.000 0.000 0.46 101.25 -123.75 ESE .0.000 0.091 0.137 0.137 0.365 0.228 0.046 0.091 0.000 0.000 0.000 1.09 123.75 -146.25 SE 0.000 0.046 0.137 0.182 0.456 0.912 0.501 0.091 0.365 0.228 0.091 3.01 146.25 -168.75 SSE 0.000 0.000 0.137 0.137 0.820 0.365 0.365 0.137 0.000 0.000 0.000 1.96 168.75 -191.25 5 0.000 0.091 0.273 0.137 0.593 0.912 0.866 0.456 0.319 0.046 0.000 3.69 191.25 -213.75 SSW 0.000 0.091 0.319 0.228 1.003 1.094 0.866 0.866 0.501 0.182 0.000 5.15 213.75 -236.25 SW 0.000 0.000 0.091 0.365 1.094 0.593 0.729 0.684 0.273 0.046 0.000 3.87 236.25 -258.75 WSW 0.000 0.046 0.137 0.228 0.547 0.729 0.501 0.273 0.182 0.000 0.000 2.64 258.75 -281.25 W 0.000 0.137 0.137 0.273 0.410 0.456 0.273 0.091 0.046 0.000 0.000 1.82 281.25 -303.75 WNW 0.000 0.273 0.410 0.365 0.866 0.501 0.182 0.182 0.046 0.000 0.000 2.83 303.75 -326.25 NW 0.000 0.273 0.273 0.501 1.322 1.641 0.456 0.228 0.319 0.046 0.000 5.06 326.25 -348.75 NNW 0.000 0.000 0.046 0.137 0.957 1.094 0.410 0.228 0.137 0.000 0.000 3.01 Total 40.57 130 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: 1.51 TO 4.00 DEG C/1OOM, STABILITY CLASS F TOTAL HOURS WIND SPEED GROUPS tm/sec)WIND DIRECTION

<0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 5 0 16 8 0 ...0 0 0 0 29 11.25 -33.75 NNE 0 4 5 9 4 1 0 0 0 0 0 23 33.75 -56.25 NE 0 0 4 8 9 0 0 0 0 0 0 21 56.25 -78.75 ENE 0 2 3 3 4 0 0 0 0 0 0 12 78.75 -101.25 E 0 2 4 6 2 0 0 0 0 0 0 14 101.25 -123.75 ESE. 0 1 5 3 9 7 0 0 0 0 0 25 123.75- 146.25 SE 0 4 3 7 13 17 20 7 3 1 0 75 146.25 -168.75 SSE 0 0 4 5 5 4 6 2 0 0 0 26 168.75 -191.25 S 0 0 4 5 2 3 6 0 0 1 0 21 191.25 -213.75 SSW 0 3 2 4 8 1 0 2 0 0 0 20 213.75 -236.25 SW 0 1 3 0 19 1 1 0 0 0 0 25 236.25 -258.75 WSW 0 2 3 1 3 2 0 0 0 0 0 11 258.75 -281.25 W 0 1 1 0 2 0 0 0 0 0 0 4 281.25 -303.75 WNW 0 1 1 4 1 0 0 0 0 0 0 7 303.75 -326.25 NW 0 0 6 8 6 1 0 0 0 0 0 21 326.25 -348.75 NNW 0 1 1 3 7 1 0 0 0 0 0 13 Total 347 131 m m m m m m m m m m m m m m m m m m m m m -m m m m m mmDmCm m m m m m m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: 1.51 TO 4.00 DEG C/1OOM, STABILITY CLASS F FREQUENCY

(%)WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.228 0.000 0.729 0.365 0.000 0.000 0.000 0.000 0.000 1.32 11.25-33.75 NNE 0.000 0.182 0.228 0.410 .0.182 0.046 0.000 0.000 0.000 0.000 0.000 1.05 33.75 -56.25 NE 0.000 0.000 0.182 0.365 0.410 0.000 0.000 0.000 0.000 0.000 0.000 0.96 56.25 -78.75 ENE 0.000 0.091 0.137 0.137 0.182 0.000 0.000 0.000 0.000 0.000 0.000 0.55 78.75 -101.25 E 0.000 0.091 0.182 0.273 0.091 0.000 0.000 0.000 0.000 0.000 0.000 0.64 101.25 -123.75 ESE 0.000 0.046 0.228 0.137 0.410 0.319 0.000 0.000 0.000 0.000 0.000 1.14 123.75 -146.25 SE 0.000 0.182 0.137 0.319 0.593 0.775 0.912 0.319 0.137 0.046 0.000 3.42 146.25 -168.75 SSE 0.000 0.000 0.182 0.228 0.228 0.182 0.273 0.091 0.000 0.000 0.000 1.19 168.75 -191.25 S 0.000 0.000 0.182 0.228 0.091 0.137 0.273 0.000 0.000 0.046 0.000 0.96 191.25 -213.75 SSW 0.000 0.137 0.091 0.182 0.365 0.046 0.000 0.091 0.000 0.000 0.000 0.91 213.75 -236.25 SW 0.000 0.046 0.137 0.000 0.866 0.046 0.046 0.000 0.000 0.000 0.000 1.14 236.25 -258.75 WSW 0.000 0.091 0.137 0.046 0.137 0.091 0.000 0.000 0.000 0.000 0.000 0.50 258.75 -281.25 W 0.000 0.046 0.046 0.000 0.091 0.000 0.000 0.000 0.000 0.000 0.000 0.18 281.25 -303.75 WNW 0.000 .0.046 0.046 0.182 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.32 303.75 -326.25 NW 0.000 0.000 0.273 0.365 0.273 0.046 0.000 0.000 0.000 0.000 0.000 0.96 326.25 -348.75 NNW 0.000 0.046 0.046 0.137 0.319 0.046 0.000 0.000 0.000 0.000 0.000 0.59 Total 15.82 132 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: GT 4.00 DEG C/100M, STABILITY CLASS G TOTAL HOURS WIND 5SPEED G~ROUPS (m/sec.WIND DIRECTION

< 0.5 0.5- 1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0 0 3 3 2 2 0 0 0 0 0 10 11.25 -33.75 NNE 0 0 1 0 3 1 0 0 0 0 0 5 33.75 -56.25 NE 0 1 1 3 1 0 0 0 0 0 0 6 56.25 -78.75 ENE 0 0 0 2 0 0 0 0 0 0 0 2 78.75 -101.25 E 0 1 5 0 0 0 0 0 0 0 0 6 101.25 -123.75 ESE 0 1 1 3 0 0 0 0 0 0 0 5 123.75 -146.25 SE 0 0 2 2 5 1 0 1 0 0 0 11 146.25 -168.75 SSE 0 0 0 2 1 0 1 0 0 0 0 4 168.75 -191.25 S 0 1 0 1 0 0 0 0 0 0 0 2 191.25 -213.75 SSW 0 0 1 0 0 1 0 0 0 0 0 2 213.75-236.25 -SW 0 0 -1 1 0 0 0 0 0 0 0 2 236.25 -258.75 WSW 0 1 0 0 1 0 0 0 0 0 0 2 258.75 -281.25 W 0 1 0 0 1 0 0 0 0 0 0 2 281.25 -303.75 WNW 0 0 1 0 0 0 0 0 0 0 0 1 303.75 -326.25 NW 0 0 1 2 2 0 0 0 0 0 0 5 326.25 -348.75 NNW 0 0 2 1 0 0 0 0 0 0 0 3 Total 68 133 mm m m m m m m m m m m m m m m m m =

m = = m m m m m m m mm m m m m m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)LAPSE RATE: GT 4.00 DEG C/100M, STABILITY CLASS G FREQUENCY

(%)WIND SPEED GROUPS (m/sec)WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.137 0.137 0.091 0.091 0.000 0.000 0.000 0.000 0.000 0.46 11.25 -33.75 NNE 0.000 0.000 0.046 0.000 0.137 0:046 0.000 0.000 0.000 0:000 0.000 0.23 33.75 -56.25 NE 0.000 0.046 0.046 0.137 0.046 0.000 0.000, 0.000 0.000 0.000 0.000 0.27 56.25 -78.75 ENE 0.000 0.000 0.000 0.091 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.09 78.75 -101.25 E 0.000 0.046 0.228 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.27 101.25 -123.75 ESE 0.000 0.046 0.046 0.137 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.23 123.75 -146.25 SE 0.000 0.000 0.091 0.091 0.228 0.046 0.000 0.046 0.000 0.000 0.000 0:50 146.25 -168.75 SSE 0.000 0.000 0.000 0.091 0.046 0.000 0.046 0.000 0.000 0.000 0.000 0.18 168.75 -191.25 S 0.000 0.046 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.09 191.25 -213.75 SSW 0.000 0.000 0.046 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.09 213.75 -236.25 SW 0.000 0.000 0.046 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.09 236.25 -258.75 WSW 0.000 0.046 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.09 258.75 -281.25 W 0.000 0.046 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.09 281.25 -303.75 WNW 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.05 303.75 -326.25 NW 0.000 0.000 0.046 0.091 0.091 0.000 0.000 0.000 0.000 0.000 0.000 0.23 326.25 -348.75 NNW 0.000 0.000 0.091 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.14 Total 3.10 134 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)ALL STABILITY CLASSES TOTAL HOURS WIND SPEED GROUPS WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1-5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75-11.25 N 0 0 13 9 38 20 8 2 5 6 0 101 11.25- 33.75 NNE 0 4 12 22 36 24 13 9 2 2 0 124 33.75- 56.25 NE 0 4 10 23 31 15 12 5 7 2 0 109 56.25 -78.75 ENE 0 2 12 13 17 9 2 3 2 0 0 60 78.75 -101.25 E 0 5 15 11 12 6 0 0 0 0 0 49 101.25 -123.75 ESE 0 5 9 10 17 20 2 2 0 0 0 65 123.75-146.25 SE 0 6 9 13 30 48 54 14 15 6 2 197 146.25-168.75 SSE 0 1 8 14 36 15 29 10 3 1 0 117 168.75-191.25 S 0 3 12 17 21 35 43 23 11 3 0 168 191.25-213.75 SSW 0 5 11 18 32 36 33 33 17 6 0 191 213.75-- 236.25 SW 0 -2 9- 11i 49 32 35 19, 12 10 0 179 236.25 -258.75 WSW 0 4 6 10 26 42 21 17 12 2 0 140 258.75- 281.25 W 0 5 7 7 23 24 16 21 6 1 0 110 281.25- 303.75 WNW 0 7 11 16 33 27 23 16 10 8 0 151 303.75- 326.25 NW 0 6 15 23 51 64 68 35 28 7 0 297 326.25 -348.75 NNW 0 1 6 10 37 31 22 15 13 1 0 136 Total 2,194 MISSING HOURS: 14 135 m m m m m m m m -m m m m m m m 2 0 m m m m m m m mEFmUm m m m m m m m 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS OCTOBER -DECEMBER 2011 (Q4)WIND LEVEL: 33 FT DELTA T: (300-33 FT)ALL STABILITY CLASSES FREQUENCY

(%)WINfl RPIFIfl (OhJ3IPR WIND DIRECTION

< 0.5 0.5-1.0 1.1 -1.5 1.6-2.0 2.1 -3.0 3.1 -4.0 4.1 -5.0 5.1 -6.0 6.1 -8.0 8.1 -10.0 > 10.0 Total (Degrees)

Sect.348.75 -11.25 N 0.000 0.000 0.593 0.410 1.732 0.912 0.365 0.091 0.228 0.273 0.000 4.60 11.25 -33.75 NNE 0.000 0.182 0.547 1.003 1.641 1.094 0.593 0.410 0.091 0.091 0.000 5.65 33.75 -56.25 NE 0.000 0.182 0.456 1.048 1.413 0.684 0.547 0.228 0.319 0.091 0.000 4.97 56.25 -78.75 ENE 0.000 0.091 0.547 0.593 0.775 0.410 0.091 0.137 0.091 0.000 0.000 2.73 78.75- 101.25 E 0.000 0.228 0.684 0.501 0.547 0.273 0.000 0.000 0.000 0.000 0.000 2.23 101.25 -123.75 ESE 0.000 0.228 0.410 0.456 0.775 0.912 0.091 0.091 0.000 0.000 0.000 2.96 123.75 -146.25 SE 0.000 0.273 0.410 0.593 1.367 2.188 2.461 0.638 0.684 0.273 0.091 8.98 146.25 -168.75 SSE 0.000 0.046 0.365 0.638 1.641 0.684 1.322 0.456 0.137 0.046 0.000 5.33 168.75 -191.25 S 0.000 0.137 0.547 0.775 0.957 1.595 1.960 1.048 0.501 0.137 0.000 7.66 191.25 -213.75 SSW 0.000 0.228 0.501 0.820 1.459 1.641 1.504 1,504 0.775 0.273 0.000 8.71 213.75 -236.25 SW 0.000 0.091 0.410 0.501 2.233 1.459 1.595 0,866 0.547 0.456 0.000 8.16 236.25 -258.75 WSW 0.000 0.182 0.273 0.456 1.185 1.914 0.957 0,775 0.547 0.091 0.000 6.38 258.75 -281.25 W 0.000 0.228 0.319 0.319 1.048 1.094 0.729 0.957 0.273 0.046 0.000 5.01 281.25 -303.75 WNW 0.000 0.319 0.501 0.729 1.504 1.231 1.048 0.729 0.456 0.365 0.000 6.88 303.75 -326.25 NW 0.000 0.273 0.684 1.048 2.325 2.917 3.099 1,595 1.276 0.319 0.000 13.54 326.25 -348.75 NNW 0.000 0.046 0.273 0.456 1.686 1.413 1.003 0.684 0.593 0.046 0.000 6.20 Total 100.00 136 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT APPENDIX B MPC Data 137 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT The following radionuclide concentrations were obtained from 10 CFR 20 Appendix B, Table II, Column 2 as revised January 1, 1991.Maximum Permissible Concentrations Element Isotope Soluble Conc Insoluble Conc.(gtCi/ml) (gCi/ml)Actinium (89) Ac-227 2E-6 3E-4 Ac-228 9E-5 9E-5 Americium (95) Am-241 4E-6 3E-5 Am-242m 4E-6 9E-5 Am-242 1E-4 1E-4 Am-243 4E-6 3E-5 Am-244 5E-3 5E-3 Antimony (51) Sb- 122 3E-5 3E-5 Sb-124 2E-5 2E-5 Sb-125 1E-4 1E-4 Sb-126 3E-6 3E-6 Arsenic (33) As-73 5E-4 5E-4 As-74 5E-5 5E-5 As-76 2E-5 2E-5 As-77 8E-5 8E-5 Astatine (85) At-211 2E-6 7E-5 Barium (56) Ba-131 2E-4 2E-4 Ba-140 3E-5 2E-5 Berkelium (97) Bk-249 6E-4 6E-4 Bk-250 2E-4 2E-4 Beryllium (4) Be-7 2E-3 2E-3 Bismuth (83) Bi-206 4E-5 4E-5 Bi-207 6E-5 6E-5 Bi-210 4E-5 4E-5 Bi-212 4E-4 4E-4 Bromine (35) Br-82 3E-4 4E-5 Br-83 3E-6 3E-6 Cadmium (48) Cd- 109 2E-4 2E-4 Cd-I 15m 3E-5 3E-5 Cd- 115 3E-5 4E-5 Calcium (20) Ca-45 9E-6 2E-4 Ca-47 5E-5 3E-5 Californium (98) Cf-249 4E-6 2E-5 Cf-250 1E-5 3E-5 Cf-251 4E-6 3E-5 Cf-252 7E-6 7E-6 Cf-253 lE-4 1E-4 Cf-254 lE-7 lE-7 138 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Element Isotope Soluble Conc. Insoluble Conc.(ýtCi/ml)

(ýtCi/ml)Carbon (6) C-14 8E-4 Cerium (58) Ce-141 9E-5 9E-5 Ce-143 4E-5 4E-5 Ce-144 1E-5 1E-5 Cesium (55) Cs- 131 2E-3 9E-4 Cs-134m 6E-3 1E-3 Cs-134 9E-6 4E-5 Cs-135 1E-4 2E-4 Cs-136 9E-5 6E-5 Cs-137 2E-5 4E-5 Chlorine (17) CI-36 8E-5 6E-5 C1-38 4E-4 4E-4 Chromium (24) Cr-51 2E-3 2E-3 Cobalt (27) Co-57 5E-4 4E-4 Co-58m 3E-3 2E-3 Co-58 1E-4 9E-5 Co-60 5E-5 3E-5 Copper (29) Cu-64 3E-4 2E-4 Curium (96) Cm-242 2E-5 2E-5 Cm-243 5E-6 2E-5 Cm-244 7E-6 3E-5 Cm-245 4E-6 3E-5 Cm-246 4E-6 3E-5 Cm-247 4E-6 2E-5 Cm-248 4E-7 1E-6 Cm-249 2E-3 2E-3 Dysprosium (66) Dy- 165 4E-4 4E-4 Dy-166 4E-5 4E-5 Einsteinium (99) Es-253 2E-5 2E-5 Es-254m 2E-5 2E-5 Es-254 1E-5 1E-5 Es-255 3E-5 3E-5 Erbium (68) Er-169 9E-5 9E-5 Er-171 1E-4 1E-4 Europium (63) Eu-152 (9.2 hrs) 6E-5 6E-5 Eu-152 (13 yrs) 8E-5 8E-5 Eu-154 2E-5 2E-5 Eu-155 2E-4 2E-4 Fermium (100) Fm-254 1E-4 1E-4 Fm-255 3E-5 3E-5 Fm-256 9E-7 9E-7 R I I I I I I I U I I I I I I 139 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Element Isotope Soluble Conc. Insoluble Conc.([tCi/ml) (PCi/ml)Fluorine (9) F-18 8E-4 5E-4 Gadolinium (64) Gd-153 2E-4 2E-4 Gd-159 8E-5 8E-5 Gallium (31) Ga-72 4E-5 4E-5 Germanium (32) Ge-71 2E-3 2E-3 Gold (79) Au-196 2E-4 1E-4 Au-198 5E-5 5E-5 Au- 199 2E-4 2E-4 Hafnium (72) Hf- 181 7E-5 7E-5 Holmium (67) Ho-166 3E-5 3E-5 Hydrogen (3) H-3 3E-3 3E-3 Indium (49) In-I 13m 1E-3 lE-3 In-i 14m 2E-5 2E-5 In- 115m 4E-4 4E-4 In- 115 9E-5 9E-5 Iodine (53) 1-125 2E-7 2E-4 1-126 3E-7 9E-5 1-129 6E-8 2E-4 1-130 3E-6 3E-6 1-131 3E-7 6E-5 1-132 8E-6 2E-4 1-133 1E-6 4E-5 1-134 2E-5 6E-4 1-135 4E-6 7E-5 Iridium (77) Ir- 190 2E-4 2E-4 Ir-192 4E-5 4E-5 Ir-194 3E-5 3E-5 Iron (26) Fe-55 8E-4 2E-3 Fe-59 6E-5 5E-5 Lanthanum (57) La-140 2E-5 2E-5 Lead (82) Pb-203 4E-4 4E-4 Pb-2 10 1E-7 2E-4 Pb-212 2E-5 2E-5 Lutetium (71) Lu- 177 1E-4 1E-4 Manganese (25) Mn-52 3E-5 3E-5 Mn-54 1E-4 1E-4 Mn-56 1E-4 1E-4 Mercury (80) Hg-197m 2E-4 2E-4 Hg-197 3E-4 5E-4 Hg-203 2E-5 1E-4 Molybdenum (42) Mo-99 2E-4 4E-5 140 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT I Element Isotope Soluble Conc. Insoluble Conc.(PCi/ml) ([LCi/ml)Neodymium (60) Nd-144 7E-5 8E-5 Nd-147 6E-5 6E-5 Nd-149 3E-4 3E-4 Neptunium (93) Np-237 3E-6 3E-5 Np-239 1E-4 1E-4 Nickel (28) Ni-59 2E-4 2E-3 Ni-63 3E-5 7E-4 Ni-65 1E-4 lE-4 Niobium (41) Nb-93m 4E-4 4E-4 Nb-95 lE-4 1E-4 Nb-97 9E-4 9E-4 Osmium (76) Os-185 7E-5 7E-5 Os-191m 3E-3 2E-3 Os-191 2E-4 2E-4 Os-193 6E-5 5E-5 Palladium (46) Pd- 103 3E-4 3E-4 Pd-109 9E-5 7E-5 Phosphorus (15) P-32 2E-5 2E-5 Platinum (78) Pt- 191 1E-4 1E-4 Pt-193m lE-3 1E-3 Pt-193 9E-4 2E-3 Pt-197m 1E-3 9E-4 Pt-197 lE-4 1E-4 Plutonium (94) Pu-238 5E-6 3E-5 Pu-239 5E-6 3E-5 Pu-240 5E-6 3E-5 Pu-241 2E-4 1E-3 Pu-242 5E-6 3E-5 Pu-243 3E-4 3E-4 Polonium (84) Po-210 7E-7 3E-5 Potassium (19) K-42 3E-4 2E-5 Praseodymium(59)

Pr- 142 3E-5 3E-5 Pr-143 5E-5 5E-5 Promethium (61) Pm-147 2E-4 2E-4 Pm-149 4E-5 4E-5 Protactinium(91)

Pa-230 2E-4 2E-4 Pa-231 9E-7 2E-5 Pa-233 lE-4 lE-4 I I I I I I I I I 1 I U I I I 141 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Element Isotope Soluble Conc. Insoluble Conc.(gtCi/ml) (iiCi/ml)Radium (88) Ra-223 7E-7 4E-6 Ra-224 2E-6 5E-6 Ra-226 3E-8 3E-5 Ra-228 3E-8 3E-5 Rhenium (75) Re- 183 6E-4 3E-4 Re-186 9E-5 5E-5 Re- 187 3E-3 2E-3 Re-188 6E-5 3E-5 Rhodium (45) Rh-103m lE-2 1E-2 Rh-l105 E-4 1E-4 Rubidium (37) Rb-86 7E-5 2E-5 Rb-87 1E-4 2E-4 Ruthenium (44) Ru-97 4E-4 3E-4 Ru- 103 8E-5 8E-5 Ru-103m 3E-6 3E-6 Ru-l105 E-4 1E-4 Ru-106 1E-5 1E-5 Samarium (62) Sm-147 6E-5 7E-5 Sm- 151 4E-4 4E-4 Sm-153 8E-5 8E-5 Scandium (21) Sc-46 4E-5 4E-5 Sc-47 9E-5 9E-5 Sc-48 3E-5 3E-5 Selenium (34) Se-75 3E-4 3E-4 Silicon (14) Si-31 9E-4 2E-4 Silver (47) Ag-l105 E-4 1E-4 Ag-110m 3E-5 3E-5 Ag-11 4E-5 4E-5 Sodium (11) Na-22 4E-5 3E-5 Na-24 2E-4 3E-5 Strontium (38) Sr-85m 7E-3 7E-3 Sr-85 1E-4 2E-4 Sr-89 3E-6 3E-5 Sr-90 3E-7 4E-5 Sr-91 7E-5 5E-5 Sr-92 7E-5 6E-5 Sulfur (16) S-35 6E-5 3E-4 Tantalum (73) Ta- 182 4E-5 4E-5 142 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Element Isotope Soluble Conc. Insoluble Conc.(gtCi/ml)

(ýtCi/mnl)

Technetium (43) Tc-96m 1E-2 1E-2 Tc-96 1E-4 5E-5 Tc-97m 4E-4 2E-4 Tc-97 2E-3 8E-4 Tc-99m 6E-3 3E-3 Tc-99 3E-4 2E-4 Tellurium (52) Te-125m 2E-4 1E-4 Te-127m 6E-5 5E-5 Te-127 3E-4 2E-4 Te-129m 3E-5 2E-5 Te- 129 8E-4 8E-4 Te-131m 6E-5 4E-5 Te-132 3E-5 2E-5 Terbium (65) Th-160 4E-5 4E-5 Thallium (81) TI-200 4E-4 2E-4 TI-201 3E-4 2E-4 TI-202 1E-4 7E-5 TI-204 1E-4 6E-5 Thorium (90) Th-227 2E-5 2E-5 Th-228 7E-6 lE-5 Th-230 2E-6 3E-5 Th-23 1 2E-4 2E-4 Th-232 2E-6 4E-5 Th-natural 2E-6 2E-5 Th-234 2E-5 2E-5 Thulium (69) Tm-170 5E-5 5E-5 Tm- 171 5E-4 5E-4 Tin (50) Sn- 113 9E-5 8E-5 Sn-124 2E-5 2E-5 Tungsten (74) W- 181 4E-4 3E-4 W-185 1E-4 lE-4 W-187 7E-5 6E-5 Uranium (92) U-230 5E-6 5E-6 U-232 3E-5 3E-5 U-233 3E-5 3E-5 U-234 3E-5 3E-5 U-235 3E-5 3E-5 U-236 3E-5 3E-5 U-238 4E-5 4E-5 U-240 3E-5 3E-5 U-natural 3E-5 3E-5 I I I I I I I I U I I I I I U I 143 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Element Isotope Soluble Cone. Insoluble Conc.([tCi/ml) (PCi/ml)Vanadium (23) V-48 3E-5 3E-5 Ytterbium (70) Yb-175 1E-4 1E-4 Yttrium Y-90 2E-5 2E-5 Y-91m 3E-3 3E-3 Y-91 3E-5 3E-5 Y-92 6E-5 6E-5 Y-93 3E-5 3E-5 Zinc (30) Zn-65 1E-4 2E-4 Zn-69m 7E-5 6E-5 Zn-69 2E-3 2E-3 Zirconium (40) Zr-93 8E-4 8E-4 Zr-95 6E-5 6E-5 Zr-97 2E-5 2E-5 Any single radio- 3E-6 3E-6 nuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radio -active half-life greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Any single radio- 3E-8 3E-8 nuclide not listed above, which decays by alpha emission or spontaneous fission.Notes: 1. If the identity of any radionuclide is not known, the limiting values for purposes of this table shall be: 3E-8 tCi/ml.2. If the identity and concentration of each radionuclide are known, the limiting values should be derived as follows: Determine, for each radionuclide in the mixture, the ratio between the quantity present in the mixture and the limit otherwise established in Appendix B for the specific radionuclide not in a mixture.The sum of such ratios for all the radionuclides in the mixture may not exceed "1" (i.e. "unity").144 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT ATTACHMENT 1 SALEM OFFSITE DOSE CALCULATION MANUAL Revision 26 And HOPE CREEK OFFSITE DOSE CALCULATION MANUAL Revisions 26 (Separate Documents) 145 2011 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT OFFSITE DOSE CALCULATION MANUAL FOR PSEG NUCLEAR LLC SALEM GENERATING STATION Revision 26 Prepared By: Reviewed by: SQR Accepted by: Approved by: ODCM Coordinator Jenny Shelton Salem Chemistry Manager Mark Pyle Reviewed by PORC Chairman John Garecht Meeting #: Date Date Date Date Date U U I Plant Manager Edwin Eilola, Jr.146 I SALEM ODCM REV. 26 Revision Summary 1. Table E-1 section B. Air Sampling Locations was revised to include one new air sampler location, 5S2. 3 And table 3.12.1-1 was revised to describe the air sampling requirements for the program, increased from six locations to seven.Justification:

NOS audit finding from Maplewood Testing Services Laboratory vendor audit SNA 2009-091, refer to US NRC Reg Guide 4.15 revision 2, which calls for field duplicate sampling stations, reference DCP 80102652.

This was also recommended by REMP benchmarking 70084355-0110.

2. Updated Figure E-1 On-site Sampling Locations to update the new sampling location for air 3 sampler 5S2.And Figure E-2 Off-site Sampling Locations was updated with the location of a new management audit sample.Justification:

The map was updated to be consistent with the REMP station location listed in Table E-1 section B. Figure E-2 was update to include location of offsite management audit sample for muskrat sampling.3. Section 3.3 was added to assess dose due to C-14 for gaseous effluents, includes methodology for 3 assessment based on guidance from Regulatory Guide 1.21 revision 2.Justification:

In accordance with guidance offered in Regulatory Guide 1.21 revision 2 the station conducted an evaluation which identified C-14 as a principal radionuclide in gaseous effluent releases from the Salem Generating Station (SAP Order 70096339, 70116850).

Revision to the ODCM documents the methodology used for estimating the doses from Carbon 14. 3 147 SALEM ODCM REV. 26 TABLE OF CONTENTS INTRODUCTION 152 PART I -RADIOLOGICAL EFFLUENT CONTROLS 153 1.0 DEFINITIONS 155 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 161 3/4.0 APPLICABILITY 161 3/4.3 INSTR UMENTA TION 163 3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 163 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 169 3/4.11.1 LIQUID EFFLUENTS 174 3/4.11.1.1 CONCENTRATION 174 3/4.11.1.2 DOSE 178 3/4.11.1.3 LIQUID RADWASTE TREATMENT 179 3/4.11.2 GASEOUS EFFLUENTS 180 3/4.11.2.1 DOSE RATE 180 3/4.11.2.2 DOSE -NOBLE GASES 183 3/4.11.2.3 DOSE -IODINE-131, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM 184 3/4.11.2.4 GASEOUS RADWASTE TREATMENT 185 3/4.11.4 TOTAL DOSE 186 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 187 3/4.12.1 MONITORING PROGRAM 187 3/4.12.2 LAND USE CENSUS 200 3/4.12.3 INTERLABORA TORY COMPARISON PROGRAM 202 BASES 203 3/4.3 INSTR UMENTA TION 204 3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 204 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION205 3/4.11 RADIOACTIVE EFFLUENTS 207 3/4.11.1 LIQUID EFFLUENTS 207 3/4.11.2 GASEOUS EFFLUENTS 208 3/4.11.4 TOTAL DOSE 210 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 211 3/4.12.1 MONITORING PROGRAM 211 3/4.12.2 LAND USE CENSUS 211 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 211 5.0 DESIGN FEATURES 213 5.1 SITE 213 5.1.3 UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 213 6.0 ADMINISTRATIVE CONTROLS 215 6.9.1.7 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 215 6.9.1.8 RADIOACTIVE EFFLUENT RELEASE REPORT 215 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 217 PART II -CALCULATIONAL METHODOLOGIES 218 148 I SALEM ODCM REV. 26 1.0 LIQUID EFFLUENTS 219 1.1 Radiation Monitoring Instrumentation and Controls 219 1.2 Liquid Effluent Monitor Setpoint Determination 219 1.2.1 Liquid Effluent Monitors (Radwaste, Steam Generator Blowdown.

Chemical Waste Basin and Service Water. 220 1.2.2 Conservative Default Values 221 1.3 Liquid Effluent Concentration Limits -10 CFR 20 222 1.4 Liquid Effluent Dose Calculation

-10 CFR 50 222 1.4.1 MEMBER OF THE PUBLIC Dose -Liquid Effluents.

222 1.4.2 Simplified Liquid Effluent Dose Calculation.

224 Total Body 224 1.5 Secondary Side Radioactive Liquid Effluents and Dose Calculations During Primall to Secondar Leakage 224 1.6 Liquid Effluent Dose Proiections 225 2.0 GASEOUS EFFLUENTS 226 2.1 Radiation Monitoring Instrumentation and Controls 226 2.2 Gaseous Effluent Monitor Setpoint Determination 227 2.2.1 Containment and Plant Vent Monitor 227 2.2.2 Conservative Default Values 228 2.33 Gaseous Effluent Instantaneous Dose Rate Calculations

-10 CFR 20 228 2.3.1 Site Boundary Dose Rate -Noble Gases 228 2.3.2 Site Boundary Dose Rate -Radioiodine and Particulates 230 2.4 Noble Gas Effluent Dose Calculations

-10 CFR 50 230 2.4.1 UNRESTRICTED AREA Dose -Noble Gases 230 2.4.2 Simplified Dose Calculation for Noble Gases 231 2.5 Radioiodine and Particulate Dose Calculations

-10 CFR 50 232 2.5.1 UNRESTRICTED AREA Dose -Radioiodine and Particulates 232 2.5.2 Simplified Dose Calculation for Radioiodines and Particulates.

232 2.6 Secondar Side Radioactive Gaseous Effluents and Dose Calculations 233 3 2.7 Gaseous Effluent Dose Projection 235 3.0 SPECIAL DOSE ANALYSES 236 3.1 Doses Due To Activities Inside the SITE BOUNDARY 236 3 3.2 Total dose to MEMBERS OF THE PUBLIC- 40 CFR 190 and 10 CFR 72.104 236 3.2.1 Effluent Dose Calculations 236 3.2.2 Direct Exposure Dose Determination.

237 3 3.3 Doses Due to Carbon 14 in Gaseous Effluents 237 3.3.1 Estimation of Carbon 14 in Annual Releases 237 3.3.2 Carbon 14 dose Determinations 238 n 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 238 4.1 Sampling Program 238 4.2 Interlaboratory Comparison Program 238 I 149 3 SALEM ODCM REV. 26 TABLES TABLE 1.1: OPERATIONAL M ODES .....................................................................................

158 TABLE 1.2: FREQUENCY NOTATION ..................................................................................

159 TABLE 3.3-12: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

.....................................................................................................................................................

16 4 TABLE 4.3-12: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREM ENTS ......................................................................................

167 TABLE 3.3-13: RADIOACTIVE GASEOUS EFFLUENT MONITORING IN STR U M EN TA TIO N ..............................................................................................................

170 TABLE 4.3-13: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

...............................................

172 TABLE 4.11-1: RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM.....................................................................................................................................................

17 5 TABLE 4.11-2: RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS P R O G RA M .................................................................................................................................

18 1 TABLE 3.12.1-1:

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *... 189 TABLE 3.12-2: REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENV IRONM ENTAL SAM PLES ...............................................................................................

196 TABLE 4.12-1: DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE A N A L Y S IS("' (2) .........................................................................................................................

197 Table 1-1.1: Parameters for Liquid Alarm Setpoint Determinations Unit 1 ...............................

242 Table 1-1.2: Parameters for Liquid Alarm Setpoint Determinations

-Unit 2 ............................

243 TABLE 1-2: Site Related Ingestion Dose Commitment Factor, AL ................... 244 Table 1-3: Bioaccum ulation Factors ...........................................................................................

246 Table 2-1: Dose Factors For N oble Gases ..................................................................................

249 Table 2-2.1: Parameters for Gaseous Alarm Setpoint Determinations

-Unit I ..........................

250 Table 2-2.2: Parameters for Gaseous Alarm Setpoint Determinations

-Unit 2 .........................

251 Table 2-3: Controlling Locations, Pathw ays ..............................................................................

252 Table 2-4: Pathway Dose Factors -Atmospheric Releases ........................................................

253 Table A- 1: Calculation of Effective M PC -Unit 1 .....................................................................

268 Table A-2: Calculation of Effective M PC -Unit 2 .....................................................................

269 Table B-l: Adult Dose Contributions

-Fish and Invertebrate Pathways -Unit 1 ......................

273 Table B-2: Adult Dose Contributions

-Fish and Invertebrate Pathways -Unit 2 ......................

274 Table C -1: Effective D ose Factors ..............................................................................................

279 Table D -1: Infant D ose Contributions

........................................................................................

283 TABLE E-1: REM P Sam ple Locations

......................................................................................

286 Table F-1: Maximum Permissible Concentrations

.....................................................................

295 150 I SALEM ODCM REV. 26 FIGURES 3 FIGURE 5.1-3: AREA PLOT PLAN OF SITE ......................................................................

214 Figure 1-1: Liquid Release Flowpath Unit 1 ..........................................................................

239 Figure 1-2: Liquid Release Flowpath Unit 2 ..........................................................................

240 Fi2ure 1-3: Liquid Radioactive W aste System .......................................................................

241 Figure 2-1: Salem Ventilation Exhaust Systems and Effluent Monitor Interfaces

...........

247 Figure 2-2: Gaseous Radioactive Waste Disposal System .....................................................

247 Fig-ure 2-2: Gaseous Radioactive Waste Disposal System .............................................

248 Fiigure E-1: ONSITE SAMPLING LOCATIONS

.................................................................

292 Figure E-2: OFFSITE SAMPLING LOCATIONS

...............................................................

293 APPENDICES 3 APPENDIX A: EVALUATION OF DEFAULT PARAMETERS FOR LIQUID EFFLUENTS

..............................

266 APPENDIX B: TECHNICAL BASIS FOR SIMPLIFIED DOSE CALCULATIONS

-LIQUID EFFLUENTS

.........

271 APPENDIX C: TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS -GASEOUS EFFLUENTS

................

276 APPENDIX D: TECHNICAL BASIS FOR SIMPLIFIED DOSE CALCULATION

-GASEOUS EFFLUENTS

....... 281 APPENDIX E: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .........................................

285 APPENDIX F: MAXIMUM PERMISSIBLE CONCENTRATION (MPC) VALUES -LIQUID EFFLUENTS

........ 295 1 I I I I U I I I 151 U SALEM ODCM REV. 26 SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL INTRODUCTION The Salem Offsite Dose Calculation Manual (ODCM) is a supporting document to the Salem Units 1 and 2 Technical Specifications.

The previous Limiting Conditions for Operations that were contained in the Radiological Effluent Technical Specifications (RETS) are now included in the ODCM as Radiological Effluent Controls (REC). The ODCM contains two parts: Part I -Radiological Effluent Controls, and Part II -Calculational Methodologies.

Part I includes the following:

The Radiological Effluent Controls and the Radiological Environmental Monitoring Programs required by Technical Specifications 6.8.4* Descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by Technical Specifications 6.9.1.7 and 6.9.1.8, respectively.

Part II describes methodologies and parameters used for: " the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints; and" the calculation of radioactive liquid and gaseous concentrations, dose rates, cumulative quarterly and yearly doses, and projected doses.Part II also contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program-(REMP), and the liquid and gaseous waste treatment systems.Revisions to the ODCM shall be made in accordance with the Technical Specifications Section 6.14.The current licensing basis applies Maximum Permissible Concentrations (MPCs) for radioactive liquid effluent concentration limits. Since the MPC values were removed from 10CFR20 effective 1/1/94, the MPC values are provided as Appendix F to the ODCM. As discussed in the Safety Evaluation by the Office of Nuclear Reactor Regulation related to Amendment Nos. 234 and 215, letters between the Nuclear Management and Resources Council (NUMARC) concerning the differences between the "old" 1 OCFR20 and the "new" 1 OCFR20 allowed continued use of the instantaneous release limits (MPCs).The NUMARC letter of April 28, 1993, concluded that the RETS that reference the "old" Part 20 are generally more restrictive than the comparable requirements of the "new" Part 20, and therefore, in accordance with 10 CFR 20.1008, the existing RETS could remain in force after the licensee implements the "new" Part 20. The letter stated that the existing RETS which reference the "old" Part 20 would maintain the level of required protection of public health and safety, and would be consistent with the requirements of the "new" Part 20.152 SALEM ODCM REV. 26 I I U U U I I PART I -RADIOLOGICAL EFFLUENT CONTROLS U I U l I U 3 I I U I 153 U SALEM ODCM REV. 26 SECTION 1.0 DEFINITIONS 154 II SALEM ODCM REV. 26 1.0 DEFINITIONS DEFINED TERMS I 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these CONTROLS.

3 ACTION 1.2 ACTION shall be that part of a CONTROL which prescribes remedial measures required under designated conditions.

CHANNEL CALIBRATION 1.4 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter that the channel monitors.

The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST.Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. Whenever an RTD or thermocouple sensing element is replaced, the next required CHANNEL CALIBRATION shall include an inplace cross calibration that compares the other sensing elements with the recently installed sensing monitor. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.

CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.

This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

CONTROL 1.10 The Limiting Conditions for Operation (LCOs) that were contained in the Radiological Effluent Technical Specifications were transferred to the OFFSITE DOSE CALCULATION MANUAL (ODCM) and were renamed CONTROLS.

This is to distinguish between those LCOs that were retained in the Technical Specifications and those LCOs or CONTROLS that were transferred to the ODCM.DOSE EQUIVALENT 1-131 I 1.11 DOSE EQUIVALENT 1- 131 shall be that concentration of 1- 131 (microcuries per gram), which alone would produce the same thyroid dose as the quantity, and isotopic mixture of 1-131, 1-132, I-133, 1-134, and 1- 135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Federal Guidance Report No. 11 (FGR 11), "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion".

155 SALEM ODCM REV. 26 FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.GASEOUS RADWASTE TREATMENT SYSTEM 1.14 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBER(S)

OF THE PUBLIC 1.15 MEMBER(S)

OF THE PUBLIC member of the public (10 CFR 20) -Means any individual except when that individual is receiving an occupational dose.1.16 MEMBER(S)

OF THE PUBLIC (40 CFR 190) -Means any individual that can receive a radiation dose in the general environment, whether he may or may not also be exposed to radiation in an occupation associated with a nuclear fuel cycle. However, an individual is not considered a member of the public during any period in which the individual is engaged in carrying out any operation which is part of a nuclear fuel cycle.OFFSITE DOSE CALCULATION MANUAL (ODCM)1.17 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the environmental radiological monitoring program. The ODCM shall also contain (1)the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and the Radioactive Effluent Release Reports required by Technical Specification Sections 6.9.1.7 and 6.9.1.8, respectively.

OPERABLE -OPERABILITY 1.18 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, normal or emergency electrical power source, cooling and seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its specified safety function(s) are also capable of performing their related support function(s).

OPERATIONAL MODE -MODE 1.19 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.PURGE -PURGING 1.23 PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER 156 U SALEM ODCM REV. 26 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3459 MWt. i REPORTABLE EVENT 1.37 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10CFR Part 50 or 10CFR 72.75.SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3.SOURCE CHECK i 1.31 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to either (a) an external source of increased radioactivity, or (b) an internal source of radioactivity (keep-alive source), or (c) an equivalent electronic source check.THERMAL POWER 1.33 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.UNRESTRICTED AREA 1.35 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential 3 quarters or industrial, commercial, institutional, and/or recreational purposes.VENTILATION EXHAUST TREATMENT SYSTEM 3 1.36 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine and radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the 3 purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be 3 VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING i 1.37 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.WASTE GAS HOLDUP SYSTEM 3 1.41 A WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity I prior to release to the environment.

I 157 3 SALEM ODCM REV. 26 TABLE 1.1: OPERATIONAL MODES MODE 1. POWER OPERATION 2. STARTUP 3. HOT STANDBY 4. HOT SHUTDOWN 5. COLD SHUTDOWN 6. REFUELING**

REACTIVITY CONDITION, Kf THERMAL POWER*> 0.99 >5%> 0.99 < 5%< 0.99 0 AVERAGE COOLANT TEMPERATURE

> 350°F> 350°F> 350°F 350°F > Tavg> 200°F< 200°F< 140°F< 0.99< 0.99< 0.95 0 0 0* Excluding decay heat.** Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.158 SALEM ODCM REV. 26 TABLE 1.2: FREQUENCY NOTATION NOTATION S D w M Q SA R S/U P FREQUENCY At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .At least once per 7 days.At least once per 31 days.At least once per 92 days.At least once per 6 months.At least once per 18 months.Prior to each reactor startup.Prior to each release.Not applicable.

N.A.159 SALEM ODCM REV. 26 SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS 160 SALEM ODCM REV. 26 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3 3/4.0 APPLICABILITY CONTROLS U 3.0.1 Compliance with the CONTROLS contained in the succeeding CONTROLS is required during 3 the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the CONTROL, the associated ACTION requirements shall be met.3.0.2 Noncompliance with a CONTROL shall exist when the requirements of the CONTROLS and associated ACTION requirements are not met within the specified time intervals.

If the CONTROL is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is I not required.3.0.3 When a CONTROL is not met except as provided in the associated ACTION requirements, within i one hour action shall be initiated to place the unit in a MODE in which the CONTROL does not apply by placing it, as applicable, in: 3 1. At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and i 3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the CONTROL. Exceptions to these requirements are stated in the individual CONTROLS.This CONTROL is not applicable in MODE 5 or 6.3.0.4 Entry into an OPERATIONAL MODE or other specified condition: (a) shall not be made when the conditions of the CONTROL are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval.(b) may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time.This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual CONTROLS.161 SALEM ODCM REV. 26 APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual CONTROLS unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by CONTROL 4.0.2, shall constitute a failure to meet the OPERABILITY requirements for a CONTROL. The time limits of the ACTION requirements are applicable at the time it is identified-that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowed outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement(s) associated with the CONTROL has been performed within the stated surveillance interval or as otherwise specified.

This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

162 SALEM ODCM REV. 26 3/4.3 INSTRUMENTATION 3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.8 In accordance with Salem Units 1 and 2 Technical Specifications 6.8.4.g.1, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of CONTROL 3.11.1.1 are not exceeded.

The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).APPLICABILITY:

During all liquid releases via these pathways.ACTION: a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above CONTROL, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Exert best efforts to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next radioactive effluent release report why the inoperability was not corrected in a timely manner.c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.163

=om M MM MM ODm MM RM M M SALEM ODCM REV. 26 TABLE 3.3-12: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE TNSTR I IMFENT ACTION INSTRUMENT

1. GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE a. Liquid Radwaste Effluent Line b. Steam Generator Blowdown Line 1 (1R18, 2R18)4 (1R19A-D, 2R19A-D)26 27 2. GROSS RADIOACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a. Containment Fan Coolers -Service Water Line Discharge b. Chemical Waste Basin 3. FLOW RATE MEASUREMENT DEVICES 2(Unit 1) (1R13A, B)2 (Unit 2) (2R13A, B)1 (R37)28 31 a. Liquid Radwaste Effluent Line b. Steam Generator Blowdown Line 1 (1FR1064, 2FR1064)4 (1FA-3178, -3180, -3182, -3184, 2FA-3178, -3180, -3182, -3184)29 29 164 SALEM ODCM REV. 26 TABLE 3.3-12 (Continued)

TABLE NOTATION ACTION 26 -ACTION 27 -ACTION 28 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release: a. At least two independent samples are analyzed in accordance with CONTROL 4.11.1.1.1, and b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving;Otherwise, suspend release of radioactive effluents via this pathway.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters, 1-131, and dissolved and entrained gases at the lower limits of detection required in ODCM CONTROL Table 4.11-1 .B, and the ODCM Surveillance Requirement 4.11.1.1.2 is performed:

a. At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT 1- 131, or b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/gram DOSE EQUIVALENT 1-131.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that: a. At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , local monitor readouts for the affected channels are verified to be below their alarm setpoints, or b. With a Service Water System leak (inside containment) on the Containment Fan Coil Unit associated with the inoperable monitor either: 1. At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , grab samples are to be collected and analyzed for principal gamma emitters, 1-131, and dissolved and entrained gases at the lower limits of detection specified in ODCM CONTROL Table 4.11-1 .B, and the ODCM Surveillance Requirement 4.11.1.1.2 is performed, or 2. Isolate the release pathway.c. With no identified service water leakage (inside containment) on the Containment Fan Coil Unit associated with the inoperable monitor, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , collect grab samples and analyze for principal gamma emitters, 1-131, and dissolved and entrained gases at the lower limits of detection specified in ODCM CONTROL Table 4.11-1..B, and the ODCM Surveillance Requirement 4.11.1.1.2 is performed.

165 I I I I I I I I I I I I I I U I!I I SALEM ODCM REV. 26 TABLE 3.3-12 (Continued)

TABLE NOTATION ACTION 29 -ACTION 31 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.Pump performance curves may be used to estimate flow.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that sampling is conducted in accordance with the following table: Frequency 1 per week 1 per day Condition During normal operation (all MODES)During operation with an identified primary to secondary leak on either Salem Unit The samples shall be analyzed for principal gamma emitters, 1-131, and dissolved and entrained gases at the lower limits of detection specified in ODCM CONTROL Table 4.11-1..B, and the ODCM Surveillance Requirement 4.11.1.1.2 shall be performed.

166 SALEM ODCM REV. 26 TABLE 4.3-12: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL INSTRUMENT CHECK SOURCE CHANNEL CHECK CALIBRATION CHANNEL FUNCTIONAL TEST 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a. Liquid Radwaste Effluent Line b. Steam Generator Blowdown Line D D R(3)R(3)Q(1)Q(l)M 2. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a. Containment Fan Coolers -Service Water Line Discharge b. Chemical Waste Basin Line 3. FLOW RATE MEASUREMENT DEVICES D D M M R(3)R(3)Q(2)Q(5)a. Liquid Radwaste Effluent Line b. Steam Generator Blowdown Line D(4)D(4)N.A.N.A.R R N.A.N.A.167 M m M M M M M M M m m M M m m M M m SALEM ODCM REV. 26 TABLE 4.3-12 (Continued)

TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels at or above the alarm/trip setpoint.2. Circuit failure. (Loss of Power)3. Control Room Instrument indicates a downscale failure.(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels at or above the alarm/trip setpoint.2. Circuit failure. (Loss of Power)3. Control Room Instrument indicates a downscale failure.4. Instrument controls not set in operate mode. (On instruments equipped with operate mode switches only {Unit 1})(3) The initial CHANNEL CALIBRATION was performed using appropriate liquid or gaseous, calibration sources obtained from reputable suppliers.

The activity of the calibration sources were reconfirmed using a multi-channel analyzer which was calibrated using one or more NBS (now NIST) standards.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels at or above the alarm/trip setpoint.2. Circuit failure. (Loss of Power)# The R1 8's channels off-line channels which requires periodic decontamination.

Any count rate indication above 10,000 cpm constitutes a SOURCE CHECK for compliance purposes.168 SALEM ODCM REV. 26 3/4.3 INSTRUMENTATION 3 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS i 3.3.3.9 In accordance with Salem Units 1 and 2 Technical Specifications 6.8.4.g. 1, the 3 radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of CONTROL 3.11.2.1 are not exceeded.

The alarm/trip setpoints of these channels shall be determined in accordance 3 with the ODCM.APPLICABILITY:

As shown in Table 3.3-13 3 ACTION:I a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above CONTROL, without delay suspend the release of radioactive gaseous effluents monitored by I the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Exert best efforts to return the instrument to OPERABLE status i within 30 days and, if unsuccessful, explain in the next radioactive effluent release report why the inoperability was not corrected in a timely manner.c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

I SURVEILLANCE REQUIREMENTS U 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.I 1691 SALEM ODCM REV. 26 TABLE 3.3-13: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1. WASTE GAS HOLDUP SYSTEM a. Noble Gas Activity Monitor -Providing Alarm and Automatic Termination of Release 2. CONTAINMENT PURGE a. Noble Gas Activity Monitor 3. CONTAINMENT PRESSURE -VACUUM RELIEF a. Noble Gas Activity Monitor 4. PLANT VENT HEADER SYSTEM##a. Noble Gas Activity Monitor 1 (1R41A&D, 2R41A&D)1 (1R12A or 1R41A&D, 2R12A or 2R41A&D) #1 (1R12A or 1R41A&D 2R12A or 2R41A & D) #1 (1R41A&D, 2R41A&D)*****31 34 37 33 36 36 32 32 b. Iodine Sampler 1 (1RME4, 5 or 1XT8911, 2RME4, 5 or 2XT8911)c. Particulate Sampler 1 (1RME4, 5 or 1XT8911, 2RME4, 5 or 2XT8911)d. Process Flow Rate Monitor (stack) 1 (1RM-1FA8603, *2RM-2FA8603)

e. Sampler Flow Rate Monitor 1 (1RM-1FA17079 or S1PAS-1FA6863Z, *2RM-2FA17079 or S2PAS-2FA6863Z)

1. The following process streams are routed to the plant vent where they are effectively monitored by the instruments described: (a) Condenser Air Removal System (b) Auxiliary Building Ventilation System (c) Fuel Handling Building Ventilation System (d) Radwaste Area Ventilation System (e) Containment Purges & Pressure-Vacuum Relief 170 SALEM ODCM REV. 26 ACTION 31 -ACTION 32 -ACTION 33 -ACTION 34 -ACTION 36 -ACTION 37 -TABLE 3.3-13 (Continued)

TABLE NOTATION With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release: a. At least two independent samples of the tank's contents are analyzed, and b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valving lineup;Otherwise, suspend release of radioactive effluents via this pathway.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gaseous principal gamma emitters at the lower limits of detection required' in ODCM CONTROL TABLE 4.11-2.A, B, or C within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, suspend release of radioactive effluents via this pathway.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.With the number of channels OPERABLE less than required by the Minimum Channels.OPERABLE requirement, effluent releases via this pathway may continue provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, Containment Pressure Reliefs may be performed provided that prior to initiating the release: I I U I U I I U I, 1 I I a. At least two independent samples of containment are analyzed, and b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations.

Otherwise, suspend release of radioactive effluents via this pathway.* At all times, other than when the line is valved out and locked.** During Containment Purges OR Containment Pressure -Vacuum Relief APPLICABILITY:

Modes 1-6, R41 A/D Monitors providing Alarm and Automatic Termination of Release, or Modes 1-5, R12A Monitor providing Alarm and Automatic Termination of Release, or Mode 6, R12A Monitor providing Alarm only (Automatic Termination of Release is not required).

During Mode Undefined (Defuieled) operation, containment-purge is reclassified as a building ventilation process stream monitored by the PLANT VENT HEADER SYSTEM.# During movement of irradiated fuel within containment with the Containment Equipment Hatch OPEN, only R41A/D can be credited for MINIMUM CHANNEL OPERABLE.During movement of irradiated fuel within containment with the Containment Equipment Hatch CLOSED, R41AiD or R12A may be credited for MINIMUM CHANNEL OPERABLE.171 m m m m m -m m -m m m m m m m m -SALEM ODCM REV. 26 TABLE 4.3-13: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVIELLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 1. WASTE GAS HOLDUP SYSTEM a. Noble Gas Activity Monitor -Providing P P R(3) Q(1)Alarm and Automatic Termination of Release 2. CONTAINMENT PURGE AND PRESSURE -VACUUM RELIEF a. Noble Gas Activity Monitor P P R(3) Q(1) **3. PLANT VENT HEADER SYSTEM#a. Noble Gas Activity Monitor D M R(3) Q(2) *b. Iodine Sampler W N.A. N.A. N.A. *c. Particulate Sampler W N.A. N.A. N.A. *d. Process Flow Rate Monitor (stack) D N.A. R N.A. *e. Sampler Flow Rate Monitor W N.A. R N.A. *# The following process streams are routed to the plant vent where they are effectively monitored by the instruments described: (a) Condenser Air Removal System (b) Auxiliary Building Ventilation System (c) Fuel Handling Building Ventilation System (d) Radwaste Area Ventilation System (e) Containment Purges & Pressure-Vacuum Relief 172 I SALEM ODCM REV. 26 1 TABLE 4.3-13 (Continued) 3 TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this i pathway and Control Room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm/trip setpoint.

3 2. Circuit failure. (Loss of Power)3. Control Room Instrument indicates a downscale failure. (Alarm Only)(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation I occurs if any of the following conditions exist: 1. Instrument indicates measured levels at or above the alarm/trip setpoint.

U 2. Circuit failure. (Loss of Power) 3 3. Control Room Instrument indicates a downscale failure.I (3) The initial CHANNEL CALIBRATION was performed using appropriate liquid or gaseous calibration sources obtained from reputable suppliers.

The activity of the calibration sources were reconfirmed using a multi-channel analyzer which was calibrated using one or more NBS (now NIST) standards.

At all times I** During Containment Purges OR Containment Pressure -Vacuum Relief Surveillance requirement

-3 Modes 1-6, R4 1A/D Monitors providing Alarm and Automatic Termination of Release Modes 1-5, R12A Monitors providing Alarm and Automatic Termination of Release Mode 6, R12A Monitors providing Alarm only (Automatic Termination of Release is not required).

U During Mode Undefined (Defueled) operation, containment purge is reclassified as a building ventilation process stream monitored by the PLANT VENT HEADER SYSTEM.During movement of irradiated fuel within containment with the Containment Equipment Hatch OPEN, only R41A/D can be credited for MINIMUM CHANNEL OPERABLE.During movement of irradiated fuel within containment with the Containment Equipment Hatch CLOSED, R41A/D or R12A may be credited for MINIMUM CHANNEL OPERABLE.173 SALEM ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION CONTROLS 3.11.1.1 In accordance with the Salem Units 1 and 2 Technical Specifications 6.8.4.g. 2 and 3, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (See Figure 5.1-3) 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 2 x 10-4 microcuries/ml.

APPLICABILITY:

At all times.ACTION: With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, without delay restore the concentration to within the above limits.SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analyses program in Table 4.11-1.4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the ODCM to assure that the concentrations at the point of release are maintained within the limits of CONTROL 3.11.1.1.174 SALEM ODCM REV. 26 TABLE 4.11-1: RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LoWer Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)a Type Frequency Frequency Analysis (RtCi/ml)A. Batch Waste P P Release Each Batch Each Batch Principal Gamma Tanksb Emitteisc 5x 10-1-131 1xl0 6 P M Dissolve and One Batch/M Entrained Gases lx1-(Gamma Emitters)P M H-3 1x10 5 Each Batch Composited

___x10_Gross Alpha lx10_7 P Q Sr-89, Sr-90 5x10 8 Each Batch Composite Fe-55 lxl0-6 B. Continuous Principal Gamma 7 Releasese W W Emittersc 5x10 Grab Sample 1. Steam Generator Blowdown 1-131 1xl0-6 M M Dissolved and 1x10-5 Grab Sample Entrained Gases W M H-3 lx10-5 Grab Sample Composite d Gross Alpha 1x10-7 W Q Sr-89, Sr-90 5x10 8 Grab Sample Composite 5x108 Fe-55 lx10-6 I I I I I I I I I I I I I I 175 SALEM ODCM REV. 26 TABLE 4.11-1 (Continued)

TABLE NOTATION a. The LLD is defined, for purposes of these CONTROLS as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system (which may include radiochemical separation):

LLD= 4.66eSb E V 9 2.22E6

Y e exp(-2At)Where: LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume), 4.66 is the statistical factor from NUREG 1301 Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2.22E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), X is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.Typical values of E, V, 4, and At should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact)limit for a particular measurement.

176 SALEM ODCM REV. 26 TABLE 4.11-1 (Continued)

TABLE NOTATION b. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.c. The principal gamma emitters for which the LLD CONTROL applies exclusively are the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144*. This list does not mean that only these nuclides are to be detected and reported.

Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.d. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.e. A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.* The LLD for Ce-144 shall be 2x10 6ýtCi/ml.I I I I I I I I I I I I I I I I I 177 SALEM ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.2 DOSE CONTROLS 3.11.1.2 In accordance with Salem Units 1 and 2 Technical Specifications 6.8.4.g.4 and 5, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1-3). shall be limited: a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.APPLICABILITY:

At all times.ACTION: a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.b. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days.178 SALEM ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3 3/4.11.1.3 LIQUID RADWASTE TREATMENT CONTROLS U 3.11.1.3 In accordance with the Salem Units 1 and 2 Technical Specifications 6.8.4.g.6, the liquid radwaste treatment system shall be used to reduce the radioactive materials liquid wastes prior to their discharge when the projected cumulative doses due to the liquid effluent from each reactor to UNRESTRICTED AREAS (see Figure 5.1-3) exceed 0.375 mrem to the total body or 1.25 mrem to any organ during any calendar quarter.APPLICABILITY-At all times. 3 ACTION: a. With the radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

I 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the I inoperability.

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and I 3. Summary description of action(s) taken to prevent a recurrence.

3 b. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.

I SURVEILLANCE REQUIREMENTS 4.11.1.3 Doses due to liquid releases shall be projected at least once per 31 days in accordance with the ODCM.I 179I SALEM ODCM REV. 26.3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE CONTROLS 3.11.2.1 In accordance with the Salem Units 1 and 2 Technical Specifications 6.8.4.g.3 and 7, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mremryr toi the total body and less than or equal to 3000 mrem/yr to the skin, and b. 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 mrem/yr to any organ.APPLICABILITY:

At all times.ACTION: With the dose rate(s) exceeding the above limits, without delay restore the release rate to within the above limit(s).SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined continuously to be within the above limits in accordance with the ODCM.4.11.2.1.2 The dose rate due to iodine- 131, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.180 SALEM ODCM REV. 26 TABLE 4.11-2: RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Gaseous Release Sampling Analysis Type of Activity (LLD)Type Frequency Frequency Analysis (gCi/ml)A. Waste Gas P P Storage Each Tank Each Tank Principal Gamma lx10-4 Tank Grab Sample Emittersb B. Containment P P Principal Gamma 1x10-4 PURGE Each PURGE Each PURGE Emitters" Grab Sample H-3 1x10-6 C. Plant Vent MCde Principal Gamma lx 10-4 Grab Sample Me Emittersb H-3 1xl0-6 D. All Release Continuous f Wg 1-131 x 10-12 Types as Charcoal Listed in A, Sample B, and C Above Continuousf Wg Principal Gamma 1x10-1 Particulate Emittersb Sample (1- 13 1, Others)Continuousf M Gross Alpha lxlO-1l Composite Particulate Sample Continuousf Q Sr-89, Sr-90 1x1l O 1 Composite Particulate Sample Continuousf Noble Gas Noble Gasses lx10-6 Monitor Gross Beta or Gamma I I I U I I I I I U I I I I I I I I I 181 SALEM ODCM REV. 26 TABLE 4.11-2 (Continued)

TABLE NOTATION a. The LLD is defined in Table 4.11.1 b. The principal gamma emitters for which the LLD CONTROL applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported.

Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.c. Sampling and analysis shall also be performed following shutdown, startup or a THERMAL POWER change that, within one hour, exceeds 15 percent of RATED THERMAL POWER unless: 1. Analysis shows that the DOSE EQUIVALENT 1- 131 concentration in the primary coolant has not increased more than a factor of three; and 2. The noble gas activity monitor shows that effluent activity has not increased by more than a factor of three.d. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool.f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with CONTROLS 3.11.2.1, 3.11.2.2 and 3.11.2.3.g. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler).

Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change that, within one hour, exceeds 15 percent of RATED THERMAL POWER and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased by more than a factor of three.182 SALEM ODCM REV. 26 1 3/4.11 RADIOACTIVE EFFLUENTS 3 3/4.11.2.2 DOSE -NOBLE GASES CONTROLS I 3.11.2.2 In accordance with the Salem Units 1 and 2 Technical Specification 6.8.4.g.5 and 8, the air 3 dose due to noble gases released in gaseous effluents, from each reactor unit, from the site areas and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 rmrad for gamma radiation and less than or equal to !10 mrad for beta radiation and, b. 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.

APPLICABILITY:

At all times.ACTION: 3 a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

I SURVEILLANCE REQUIREMENTS I 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.I 183I SALEM ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.3 DOSE -IODINE- 131, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS 3.11.2.3 In accordance with the Salem Units 1 and 2 Technical Specification 6.8.4.g.5 and 9, 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 (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, b. During any calendar year: Less than or equal to 15 mrem to any organ.APPLICABILITY:

At all times.ACTION: a. With the calculated air dose from the release of iodine- 131, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine- 131, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the ODCM at least once per 31 days.184 SALEM ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.4 GASEOUS RADWASTE TREATMENT CONTROLS 3.11.2.4 In accordance with the Salem Units 1 and 2 Technical Specifications 6.8.4.g.6, the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3), exceed 0.625 mrad for gamma radiation and 1.25 mrad for beta radiation in any calendar quarter. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) would exceed 1.875 mrem to any organ in any calendar quarter.APPLICABILITY:

At all times.ACTION: a. With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCM.185 SALEM ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4. In accordance with Salem Units 1 and 2 Technical Specification s 6.8.4.g.11, 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 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem).APPLICABILITY:

At all times ACTION: a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of CONTROL 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b, calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the limits of this CONTROL have been exceeded.

If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 or 10 CFR 72.104 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190 and 10 CFR 72.104. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with CONTROLS 4.11.1.2, 4.11.2.2, 4.11.2.3, and in accordance with the ODCM.4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage shall be determined in accordance with the ODCM.186 SALEM ODCM REV. 26 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1. In accordance with Salem Units land 2 Technical Specifications 6.8.4.h. 1, the radiological i environmental monitoring program shall be conducted as specified in Table 3.12-1.APPLICABILITY:

At all times. I ACTION: a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of CONTROLS 3.11.1.2, 3.11.2.2, and 3.11.2.3.

When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:-concentration (1) concentration (2) i 1.0i reportinglevel (1) reportinglevel (2)When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of CONTROLS 3.11.1.2, 3.11.2.2, and 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7.*The methodology used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.187 SALEM ODCM REV. 26 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS ACTION: (Cont'd)c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify specific locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.Pursuant to Technical Specification 6.9.1.8, identify the cause of the unavailability of samples and the new location(s) for obtaining replacement samples in the next Radioactive Effluent Release Report. Include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

d. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1, and the detection capabilities required by Table 4.12-1.188 SALEM ODCM REV. 26 TABLE 3.12.1-1:

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *EXPOSURE PATHWAY NUMBER OF REPRESENTAIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION OF ANALYSIS LOCATIONS (1) FREQUENCY 1. DIRECT RADIATION (2)Forty-nine routine monitoring stations with two or more dosimeters placed as follows: Quarterly Gamma dose quarterly An inner ring of stations one in each land based meteorological sector (not bounded by water) in the general area of the SITE BOUNDARY;An outer ring of stations, one in each land-based meteorological sector in the 5 to 1 1-km range from the site (not bounded by or over water); and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.*The number, media, frequency, and location of samples may vary from site to site. This table presents an acceptable minimum program for a site at which each entry is applicable.

Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an individual's dose and should be included in the sample program.189 mm m mn m m- -runm -mm -m -m m M = -=W= = M -" m = = m SALEM ODCM REV. 26 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTAIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION OF ANALYSIS LOCATIONS (1) FREQUENCY 2. ARBORNE Radioiodine and Particulates Samples from 7 locations:

Continuous sampler operation with sample collection weekly or more frequently if required by dust loading.-

-..Radioiodine Canister 1-131 analysis weekly.Five (5) Samples -Two samples from close to the SITE BOUNDARY location and three samples in different land based sectors of a high calculated annual average ground level D/Q One sample from the vicinity of a community having a high calculated annual average ground- level D/Q;and One sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction.

Particulate Sampler Gross beta radioactivity analysis following (3)filter change Gamma isotopic analysis(4) of composites (by location)quarterly.

190 SALEM ODCM REV. 26 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF SAMPLING AND TYPE AND FREQUENCY.OF ANALYSIS PATHWAY REPRESENTAIVE SAMPLES COLLECTION AND/OR SAMPLE AND SAMPLE LOCATIONS (1) FREQUENCY 3. WATERBORNE

a. Surface(5)b. Ground c. Drinking (10)d. Sediment One sample upstream One sample downstream One sample outfall One sample cross-stream Samples from one or two sources only if likely to be affected(7).One sample of the nearest water supply affected by its discharge One sample from downstream area One sample from cross-stream area One sample from outfall area One sample from upstream area One sample from a control location One sample from shoreline area One sample from Cooling Tower Blowdown Grab sample monthly Gamma isotopic analysis(4) monthly. Composite for tritium analysis quarterly.

Monthly Composite sample over two-week period(6) when 1- 131 analysis is performed; monthly composite otherwise.

Semiannually Gamma isotopic analysis(4) monthly and tritium analysis quarterly.

1-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year(8). Composite for gross beta and gamma isotopic analysis(4) monthly Composite for tritium analysis quarterly Gamma isotopic analysis(4) semiannually m m- mm m m m -m mm m m-m -mm m m -m m m m, m m --SALEM ODCM REV. 26 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTAIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION OF ANALYSIS LOCATIONS O) FREQUENCY 4. INGESTION a. Milk Samples from milking animals in three locations within 5 km distance having the highest dose potential.

If there are none, then, one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr(8).One sample from milking animals at a control location 15 to 30 km distant.One sample of each commercially and recreationally important species in vicinity of plant discharge area One sample of same species in area not influenced by plant discharge.

Semimonthly when animals are on pasture, monthly at other time Gamma isotopic (4) and 1-131 analysis semi-monthly when animals are on pasture; monthly at other times b. Fish and Invertebrates Sample in season, or Gamma isotopic analysis(4) on semiannually if they are not edible portions.seasonal 192 SALEM ODCM REV. 26 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE REPRESENTAIVE COLLECTION OF ANALYSIS SAMPLES AND SAMPLE FREQUENCY LOCATIONS (1)c. Food Products One sample of each principal class of food products from any area that is irrigated by water in which liquid plant wastes have been discharged At time of harvest (9)Gamma isotopic analysis (4) on edible portion.l -f m m -anlgI iii m -I ml SALEM ODCM REV. 26 TABLE 3.12.1-1 (Continued)

TABLE NOTATION (1) Specific parameters of distance and direction sector from the midpoint of a line between the center of the Salem units 1 & 2 containment domes, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12ý 1 in a table and figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Reg. Guide 4.8 as amended by Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Pursuant to CONTROL 6.9.1.8, submit in the next Radioactive Effluent Release Report documentation for a change in the ODCM including revised figure(s)and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for the pathway and justifying the selection of the new location(s) for obtaining samples.(2) One or more instruments, such as pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.

For the purposes of this table, a Dosimeter of Legal Record (DLR) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.

Film badges shall not be used for measuring direct radiation.

The frequency of analysis or readout will depend upon the characteristics of the specific dosimetry system used and should be selected to obtain optimum dose information with minimal fading. No direct radiation monitoring stations are located in the inner ring sectors 8, 9, 12, 13 and 14 and the outer ring sector 8 as originally determined during plant licensing and as permitted by Reg. Guide 4.8 as amended by The Branch Technical Position Revision 1, November 1979. Sector 7 does not have a direct radiation monitoring station in the outer ring due to inaccessibility.

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.194 SALEM ODCM REV. 26 TABLE 3.12.1-1 (Continued) i TABLE NOTATION (5) The "upstream sample" shall be taken at a distance beyond significant influence of the i discharge.

The "downstream" sample shall be taken in an area beyond but near the mixing zone. "Upstream" samples in an estuary must be taken far enough upstream to be 3 beyond the plant influence.

Saltwater shall be sampled only when the receiving water is utilized for recreational activities.

(6) A composite sample is one which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short relative to the compositing period in order to assure obtaining a representative sample.(7) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(8) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM. Additionally, 2 sample locations are i monitored as management audit. Broad leaf vegetation may be obtained in lieu of milk collections.

(9) If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products.

The Delaware River at the I location of Salem and Hope Creek Nuclear Power Plants is a brackish water source. No irrigation of food products is performed using water in the vicinity from which liquid plant wastes have been discharged.

However, 12 management audit food samples areI collected from various locations.

(10) No groundwater samples are required as liquid effluents discharged from Salem and I Hope Creek Generating Stations do not directly affect this pathway. However for management audit, one raw and one treated ground water sample from the nearest unaffected water supply is required.195

= mmmm m -m m mm mm mi m m m SALEM ODCM REV. 26 TABLE 3.12-2: REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS SALEM ODCM REV. 26 Water Airborne Particulate Fish Milk Food Products Analysis (pCi/1) or Gases (pCi/m3) (pCi/Kg, wet) (pCi/I) (pCi/Kg, wet)H-3 3 x 10 4 Mn-54 1 x 10 3 3 x 10 4 Fe-59 4x 10 2 1 x 104 Co-58 1 x 103 3 x 10 4 Co-60 3 x 102 1 X 104 Zn-65 3 x 102 2 x 10 4 Zr-Nb-95 4 x 102 1-131 20 0.9 3 1 x 10 2 Cs-134 30 10 1 x 10 3 60 1 x 10 3 Cs-137 50 20 2 x 10 3 70 2 x 10 3 Ba-La-140 2 x 102 3 x 10 2 196 SALEM. ODCM REV. 26 TABLE 4.12-1: DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS(1)'

(2)LOWER LIMITS OF DETECTION (LLD) (3)Water Airborne Particulate Fish Milk Food Products Sediment Analysis (pCi/1) or Gases (pCi/m3) (pCi/Kg, wet) (pCi/1) (pCi/Kg, wet) (pCi/Kg, dry)gross 4 1 x 10.2 beta H-3 3000 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 10 7 x 10-2 1 60 Cs-134 15 5 x 10-2 130 15 60 150 Cs-137 18 6 x 10-2 150 18 80 180 Ba-La-140 15 15 M @W m mM M M an -MW7ýMMý SALEM ODCM REV. 26 TABLE 4.12-1 (Continued)

TABLE NOTATION (1) This list does not mean that only these nuclides are to be considered. ,Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7.(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.(3) The LLD is defined, for purposes of these CONTROLS as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:

LLD= 4.66eSb E oV *2.22E6 o Y o exp (-2At)Where: LLD is the "a priori" lower limit of detection as defined above (as picocuries per unit mass or volume), 4.66 is the statistical factor from NUREG 1301 Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable), k is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.Typical values of E, V, Y, and At should be used in the calculation.

198 I SALEM ODCM REV. 26 1 TABLE 4.12-1 (Continued)

"1 TABLE NOTATION U It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.

Occasionally background fluctuations, unavoidable small sample sizes the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs 3 unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7.I I 3 I I I I I I 3 199 I SALEM ODCM REV. 26 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2. In accordance with the Salem Units 1 and 2 Technical Specifications 6.8.4.h.2, a land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden*of greater than 50 m 2 (500 ft 2) producing broad leaf vegetation.

APPLICABILITY:

At all times.ACTION: a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in CONTROL 4.11.2.3, identify the new location(s) in the next Radioactive Effluent Release Report, pursuant to CONTROL 6.9.1.8.b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with CONTROL 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days.The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

Pursuant to CONTROL 6.9.1.8, identify the new location(s) in the next Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Q in lieu of the garden census. CONTROLS for broadleaf vegetation sampling in Table 3.12-1.4c shall be followed, including analysis of control samples.200 SALEM ODCM REV. 26 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3 3/4.12.2 LAND USE CENSUS (Cont'd)SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months 3 using that information that will provide the best results, such as by a door-to-door survey, visual survey, aerial survey, or by consulting local agriculture authorities.

The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7.I I U U I I I I I I I U 201 3 SALEM ODCM REV. 26 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 In accordance with Salem Units 1 and 2 Technical Specifications 6.8.4.h.3, analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program.APPLICABILITY:

At all times.ACTION: a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7.b. The provisions of CONTROLS 3.0.3 and 3.0.4. are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7.202 SALEM ODCM REV. 26 BASES FOR SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS NOTE The BASES contained in the succeeding pages summarize the reasons for the CONTROLS of Sections 3.0 and 4.0, but are not considered a part of these CONTROLS.203 I I I I I I I I I I I I U!I I I I I SALEM ODCM REV. 26 3/4.3 INSTRUMENTATION BASES 3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.CROSS REFERENCE

-TABLES 3.3-12 and 4.3-12 Unit 1: T/S Table Item No. Instrument Description Acceptable RMS Channels la Liquid Radwaste Effluent Line Gross 1R18 Activity lb Steam Generator Blowdown Line 1R19A, B, C, and D(1)Gross Activity 2a Containment Fan Coolers Service 1R13A and B(')Water Line Discharge Gross Activity Unit 2: T/S Table Item No. Instrument Description Acceptable RMS Channels la Liquid Radwaste Effluent Line Gross 2R18 Activity lb Steam Generator Blowdown Line 2R19A,B,C, Gross Activity' and D(1)2a Containment Fan Coolers -Service 2R13A and B(')Water Line Discharge Gross Activity 2b Chemical Waste Basin Line Gross R37 Activity (1) The channels listed are required to be operable to meet a single operable channel for the ODCM's"Minimum Channels Operable" requirement.

204 SALEM ODCM REV. 26 3/4.3 INSTRUMENTATION BASES 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.CROSS REFERENCE

-TABLES 3.3-13 and 4.3-13 Unit 1: T/S Table Item No. Instrument Description Acceptable RMS Channels la Waste Gas Holdup System iR41A and D (1)(2)Noble Gas Activity 2a Containment Purge and 1R12A Pressure -Vacuum Relief Noble Gas Activity or 1R41A and D (1)(2)3a Plant Vent Header System 1R41A and D (1)(2)Noble Gas Activity 3b Plant Vent Header System 1RME 4, 5 (1R41)Iodine Sampler (3) or 1XT8911 (1R45)3c Plant Vent Header System 1RME 4, 5 (1R41)Particulate Sampler (3) or 1XT8911 (1R45)(1) The channels listed are required to be operable to meet a single operable channel for the ODCM's"Minimum Channels Operable" requirement.

(2) 1R41D is the setpoint channel. 1R41A is the measurement channel.(3) Laboratory analysis of the sampler filters ensures that the limits of ODCM CONTROL 3.11.2.1 are not exceeded.

Alarm/trip setpoints do not apply to these passive components.

205 I I I!I I I I I I!I U I I I I I SALEM ODCM REV. 26 3/4.3 INSTRUMENTATION BASES Unit 2: T/S Table Instrument Description Acceptable RMS Item No. Channels 1 a Waste Gas Holdup System Noble Gas Activity 2R41A and D(1)(2)2a Containment Purge and Pressure -Vacuum Relief 2R12A or 2R41A Noble Gas Activity and D(1)(2)3a Plant Vent Header System Noble Gas Activity 2R41A and D()(2)3b Plant Vent Header System Iodine Sampler (3) RME 4, 5 (2R41)or 2XT8911 (2R45)3c Plant Vent Header System Particulate Sampler (3) 2RME 4, 5 (2R41)or 2XT8911 (2R45)(1) The channels listed are required to be operable to meet a single operable channel for the ODCM's "Minimum Channels Operable" requirement.

(2) 2R41D is the setpoint channel. 2R41A is the measurement channel.(3) Laboratory analysis of the sampler filters ensures that the limits of ODCM CONTROL 3.11.2.1 are not exceeded.

Alarm/trip setpoints do not apply to these passive components.

206 SALEM ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3 3/4.11.1.1 CONCENTRATION The CONTROL is provided to ensure that the concentration of radioactive materials released in liquid 1 waste effluents will be less than the concentration levels specified in 10 CFR Part 20, Appendix B Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.106(a) to the population.

The concentration limit for dissolved or!U entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication

2. 3 The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). m 3/4.11.1.2 DOSE This CONTROL is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I. 10 CFR Part 50. The CONTROL implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time 3 implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for freshwater sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable I assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of I Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual I release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, l October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purposes of Implementing Appendix I," April 1977. 1 The CONTROL applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.207 SALEM ODCM REV. 26 RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID RADWASTE TREATMENT The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable".

This CONTROL implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth the Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This CONTROL is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 [10 CFR Part 20.106(b)].

For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the individual will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

Examples of calculations for such MEMBERS OF THE PUBLIC with the appropriate occupancy factors shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the whole body and 3000 mrem/yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year.

This CONTROL applies to the release of gaseous effluents from all reactors at the site.3/4.11.2.2 DOSE -NOBLE GASES This CONTROL is provided to implement the requirements of Section II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The CONTROL implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be 208 SALEM ODCM REV. 26 RADIOACTIVE EFFLUENTS 3 BASES 3 substantially underestimated.

The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine i Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

3 3/4.11.2.3 DOSE -IODINE-131, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM This CONTROL is provided to implement the requirements of Section II.C, III.A and IV.A of I Appendix I, 10 CFR Part 50. The CONTROL are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in I gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and U data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in U Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977.These equations also provide for determining the actual dose based upon the historical average atmospheric conditions.

The release rate controls for iodine- 131, tritium, and radionuclides in particulate form with half-life greater than 8 days are dependent on the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY.

The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2)deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3)deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM 3 The requirement that the appropriate portions of this system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This CONTROL implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate i portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

209 SALEM ODCM REV. 26 RADIOACTIVE EFFLUENTS BASES 3/4.11.4 TOTAL DOSE This CONTROL is provided to meet the dose limitations of 40 CFR Part 190 that have now been incorporated into 10 CFR Part 20 by 46 FR 18525 as well as the dose limitations specific to Independent Spent Fuel Storage Installation (ISFSI) operations in accordance with 10 CFR 72.104.Over the long term, as more storage casks are placed on the ISFSI pads, it is expected that ISFSI operations will become the prominent contributor to the dose limits in this section. ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. The PSEG 10 CFR 72.212 Report prepared in accordance with 10 CFR 72 requirements assumes a certain array of casks exists on the pads. The dose contribution from this array of casks in combination with historical uranium fuel cycle operations prior to ISFSI operations was analyzed to be within the 40 CFR 190 and 10 CFR 72.104 limits. The CONTROL requires the preparation and submittal of a Special Report whenever the calculated doses from plant including the ISFSI radioactive effluents exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units including outside storage tanks, etc. are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 or 10 CFR 72.104 limits. For purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.

If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190 or 10 CFR 72.104, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 or 10 CFR 72.104 have not already been corrected), in accordance with the provisions of 40 CFR Part 190 or 10 CFR 72.104 and 10 CFR Part 20.405c, is consideredto be a timely request and fulfills the requirements of 40 CFR Part 190 or 10 CFR 72.104 until NRC staff action is completed.

The variance only relates to the limits of 40 CFR Part 190 or 10 CFR 72.104, and does not applyin any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in CONTROLS 3.11.1 and 3.11.2. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.210 SALEM ODCM REV. 26 RADIOACTIVE EFFLUENTS 3 BASES 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM i The radiological environmental monitoring program required by this CONTROL provides measurements of radiation and of radioactive materials in those exposure pathways and for those 3 radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation.

This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure 3 pathways.

The initial specified monitoring program will be effective for at least the first three years of commercial operation.

Following this period, program changes may be initiated based on operational experience.

3 The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories.

It should be recognized that the LLD is defined as an a phori (before the fact)limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

3/4.12.2 LAND USE CENSUS This CONTROL is provided to ensure that changes in the use of areas at and beyond the SITE i BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, aerial survey or consulting with local agricultural authorities shall be used. This census satisfies i the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 I kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: 1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) yield of 2 kg/m 2.3/4.12.3 INTERLABORATORY COMPARISON PROGRAM This requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for I environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. 3 211 SALEM ODCM REV. 26 SECTION 5.0 DESIGN FEATURES 212 SALEM ODCM REV. 26 5.0 DESIGN FEATURES I 5.1 SITE 5 5.1.3 UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figure 5.1-3. (Provided FOR INFORMATION ONLY. Technical Specifications Section 5.0 is controlling.)

213 mm m m m mnmm m mm m m m m m UNRESTRICTED AREA-(PROPERTY OF U.S. GOVERNMNT)

.. ..... ....w' "- -,-t N I 6> NUCLEAR'AMINISTRATIONI"(BUILDING-n COOLING TOWER--I I}t~l rn- SWITCH YARD rm SITE BOUNDARY-30" SCI HOPE CREEK -SCRTPROCESSING

1i, -TECRIT .L_1ETE -CENTER C SALEM i SWITCH YARD i METEOROLOGICAL t* ' FEED WATER & o-i, CIRC. WATER m INTAKE 0 D ASTRUCTUREE I o DELAWARE RIVER SALEM ODCM REV. 26 6.0 ADMINISTRATIVE CONTROLS 3 6.9.1.7 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.7 In accordance with Salem Units 1 and 2 Technical Specifications 6.9.1.7, The Annual Radiological Environmental Operating Report* covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the I report period, including a comparison with preoperational studies with operational controls (as appropriate), and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use I censuses required by CONTROL 3.12.2. The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all measurements taken during the period pursuant to the Table and Figures in the environmental radiation section of the I ODCM; as well as summarized and tabulated results of locations specified in these analyses and measurements in the format of the table in Reg. Guide 4.8 as amended by Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.The reports shall also include the following:

a summary description of the radiological environmental monitoring program; at least two legible maps, one covering sampling locations near the SITE BOUNDARY and a second covering the more distant locations, all keyed to a table giving distances and directions from the midpoint of a line between the centers of Salem units 1 & 2 containment domes; the results of licensee participation in the Interlaboratory Comparison Program, required by CONTROL 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

3 6.9.1.8 RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 In accordance with Salem Units 1 and 2 Technical Specifications 6.9.1.8, The Annual i Radiological Effluent Release Report* covering the operation of the unit during the previous calendar year shall be submitted prior to May I of each year and in accordance with the requirements of 3 1OCFR50.36a.

The Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21."Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 3 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit. 3 215 SALEM ODCM REV. 26 6.9.1.8 RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.

The report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1-3) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The historical annual average meteorology or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL.The Radioactive Effluent Release Report shall identify those radiological environmental sample parameters and locations where it is not possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In addition, the cause of the unavailability of samples for the pathway and the new location(s) for obtaining replacement samples should be identified.

The report should also includea revised figure(s) and table(s) for the ODCM reflecting the new location(s).

The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation and 10 CFR 72.104, Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period: a. Container volume, b. Total curie quantity (specify whether determined by measurement or estimate), c. Principal radionuclides (specify whether determined by measurement or estimate), d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms), e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

The Radioactive Effluent Release Report shall include a list of descriptions of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.216 SALEM ODCM REV. 26 6.9.1.8 RADIOACTWE EFFLUENT RELEASE REPORT (Continued) 3 The Radioactive Effluent Release Report shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP), the OFFSITE DOSE CALCULATION MANUAL i (ODCM), or radioactive waste systems. Also list new locations identified by the land use census pursuant to CONTROL-3.12.2.

for dose calculations or environmental monitoring.

6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.15.1 Licensee initiated major changes to the radioactive waste system (liquid, gaseous and solid): 1. Shall be reported to the Commission in the UFSAR for the period in which the evaluation was reviewed by the Plant Operations Review Committee (PORC). The discussion of each change shall contain: a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR50.59;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid I waste that differ from those previously predicted in the license application and amendments thereto; I e. An evaluation of the change, which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;f. A comparison of the predicted releases of radioactive materials, in liquid and i gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; I g. An estimate of the exposure to plant operating personnel as a result of the change; and 3 h. Documentation of the fact that the change was reviewed and found acceptable by the PORC. 3 2. Shall become effective upon review and acceptance by the PORC.217 SALEM ODCM REV. 26 PART II -CALCULATIONAL METHODOLOGIES 218 SALEM ODCM REV. 26 1.0 LIQUID EFFLUENTS i 1.1 Radiation Monitoring Instrumentation and Controls i The liquid effluent monitoring instrumentation and controls at Salem for controlling and monitoring normal radioactive material releases in accordance with the Salem Technical Specifications 6.8.4.g I and ODCM CONTROLS are summarized as follows: 1) Alarm (and Automatic Termination) R1 8 (Unit 1) and 2-Ri 8 (Unit 2) provide the alarmI and automatic termination of liquid radioactive material releases as required by ODCM CONTROL 3.3.3.8. 3 1-R19 A, B, C, and D provide the alarm and isolation function for the Unit 1 steam generator blowdown lines. 2-R19 A, B, C, and D provide this function for Unit 2. 3 2) Alarm (only) -The alarm functions for the Service Water System are provided by the 3 radiation monitors on the Containment Fan Cooler discharges (1R 13 A and B for Unit 1 and 2R 13 A and B for Unit 2).Releases from the secondary system are routed through the Chemical Waste Basin where the effluent is monitored (with an alarm function) by R37 prior to release to the environment.

Liquid radioactive release flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented as Figures 1-1 and 1-2 for Units 1 and 2, respectively.

The Liquid Radioactive Waste System is presented in Figure 1-3. U 1.2 Liquid Effluent Monitor Setpoint Determination Per the requirements of ODCM CONTROL 3.3.3.8, alarm setpoints shall be established for the liquid effluent monitoring instrumentation to ensure that the release concentration limits of ODCM CONTROL 3.11.1.1 are met (i.e., the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2, (Appendix F) for radionuclides and 2.OE-04 jtCi/ml for dissolved or entrained noble gases).The following equation*

must be satisfied to meet the liquid effluent restrictions:

c < C(F + f) (1.1)fI Where: C = the effluent concentration limit of ODCM CONTROL 3.11.1.1 implementing the 10 CFR 20 MPC (Appendix F) for the site, in pCi/ml , c = the setpoint, in iCi/ml, of the radioactivity monitor measuring the radioactivity I concentration in the effluent line prior to dilution and subsequent release; the setpoint, 219 3 SALEM ODCM REV. 26 represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 (Appendix F) in the UNRESTRICTED AREA f = the flow rate at the radiation monitor location, in volume per unit time, but in the same units as F, below F = the dilution water flow rate as measured prior to the release point, in volume per unit time[Note that if no dilution is provided, c < C. Also, note that when (F) is large compared to (f), then (F+ f) = F.]* Adapted from NUREG-0 133 1.2.1 Liquid Effluent Monitors (Radwaste, Steam Generator Blowdown, Chemical Waste Basin and Service Water.The setpoints for the liquid effluent monitors at the Salem Nuclear Generating Station are determined by the following equations:

SP < [MPCe *SEN

CW* CF *AF] + bkg (1.2)with: Z Ci (gamma only)AMtPCe Ci (1.3)AIPCZ(gamma only)Where: SP = alarm setpoint corresponding to the maximum allowable release rate (cpm)MPCe = an effective MPC value for the mixture of gamma emitting radionuclides in the effluent stream (pCi/ml)Ci = the concentration of radionuclide i in the undiluted liquid effluents (gCi/ml)MPC, = the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F) (pCi/ml)SEN = the sensitivity value to which the monitor is calibrated (cpm per gCi/ml)CW = the circulating water flow rate (dilution water flow) at the time of release (gal/min)RR = the liquid effluent release rate (gal/min)bkg = the background of the monitor (cpm)CF = Correction factor to account for non-gamma emitting nuclides in setpoint calculations.

AF = an allocation factor applicable for steam generator blowdown 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 220 SALEM ODCM REV. 26 available plant discharge dilution and thereby minimize the potential offsite doses, batch releases from either Unit-1 or Unit-2 may be routed to either the Unit-1 or Unit-2 Circulating Water System discharge.

Procedural restrictions prevent simultaneous batch releases from either a single unit or both units into a single Circulating Water System discharge.

1.2.2 Conservative Default Values Conservative alarm setpoints may be determined through the use of default parameters.

Tables 1-1.1 and 1-1.2 summarize all current default values in use for Salem Unit-I and Unit-2, respectively.

They are based upon the following:

a) substitution of the effective MPC value with a default value of 6.05E-06 gtCi/ml (Unit 1) and 4.81E-06 jtCi/ml (Unit 2). (refer to Appendix A for justification);

b) for additional conservatism*, substitution of the 1-131 MPC value of 3E-07 gtCi/ml for the R19 Steam Generator Blowdown monitors, the R-37 Chemical Waste Basin monitor and the R- 13 Service Water monitors;c) for conservatism, use of an allocation factor of 0.5 for the Steam Generator Blowdown monitors to limit consequences of potential simultaneous

!primary-to-secondary leaks in two steam generators.**

The allocation factor equals 1.0 for all liquid effluent setpoints; d) substitutions of the operational circulating water flow with the lowest flow, in gal/min;***

e) substitutions of the effluent release rate with the highest allowed rate, in gal/min; and, f) substitution of a Correction factor of 0.75 to account for non-gamma emitting nuclides.For batch liquid releases a fixed alarm setpoint is established for the 1, 2 R18 monitors and the release rate is controlled to ensure the inequality of equation 1.1 is maintained.

With this approach, values selected for the parameters in the setpoint calculation (e.g., Table 1-1.1 and Table 1-1.2) should be any set of reasonable values that provide a setpoint value reasonably above anticipated monitor response, plus background, so as not to yield spurious alarms. The release rate is controlled to ensure compliance with the requirements of ODCM CONTROL 3.3.3.8.Calculations, as performed by Engineering, to establish the actual fixed setpoints for use in the plant, incorporate uncertainties and instrument drift. These factors will cause the actual installed instrument setpoint to be at a lower (conservative) value. However, for batch releases, when the rate is controlled, these uncertainties and drift should not be included in the evaluation of acceptable release rate, since this could cause a non-conservative correction, i.e., a higher allowable release rate. Therefore, for 1, 2 R18 monitors, the setpoint value used for calculating the allowable release rate should be that value prior to correction for uncertainty and drift.Based upon the potential for 1-131 to be present in the secondary and service water systems, the use of the default effective MPC (MPCe) 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.**Setpoints using the Allocation Factor of 0.5 become invalid if primary-to-secondary leaks are identified in more than two steam generators simultaneously.

- - The Containment Fan Coil Unit Discharge to Service Water Line is routed to the opposite Unit's Circulating Water System discharge.

Therefore, during periods when circulating 221 SALEM ODCM REV. 26 water pumps are out of service, such as during refueling outages, the default setpoints of the other Unit's R13 radiation monitors are not valid.1.3 Liquid Effluent Concentration Limits -10 CFR 20 ODCM CONTROL 3.11.1.1 limits the concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) to less than the concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F) for radionuclides other than noble gases. Noble gases are limited to a diluted concentration of 2.OE-04 [tCi/ml.Release rates are controlled and radiation monitor alarm setpoints are established as addressed above to ensure that these concentration limits are not exceeded.

However, in the event any liquid release results in an alarm setpoint being exceeded, an evaluation of compliance with the concentration limits of ODCM CONTROL 3.11.1.1 may be performed using the following equation: I 1

CW+RQ(1.4)(MPCi CW + RR Where: Ci = actual concentration of radionuclide i as measured in the undiluted liquid effluent (jiCi/ml)MPC = the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (pCi/ml) [ODCM Appendix F]= 2E-04 pCi/ml for dissolved or entrained noble gases RR = the actual liquid effluent release rate (gal/min)CW = the actual circulating water flow rate (dilution water flow) at the time of the release (gal/min)1.4 Liquid Effluent Dose Calculation

-10 CFR 50 1.4.1 MEMBER OF THE PUBLIC Dose -Liquid Effluents.

ODCM CONTROL 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from each unit of the Salem Nuclear Generating Station to:-during any calendar quarter;< 1.5 mrem to total body per unit< 5.0 mrem to any organ per unit-during any calendar year;< 3.0 mrem to total body per unit< 10.0 mrem to any organ per unit.222 SALEM ODCM REV. 26 Per the surveillance requirements of ODCM CONTROL 4.11.1.2, the following calculational methods shall be used for determining the dose or dose commitment due to the liquid radioactive effluents from Salem: I U I Do = 1.67E-O2 *VOL *j Ci* Aio)CW i (1.5)Where: D, Aio Ci VOL CW 1.67E-02= dose or dose commitment to organ o (mrem). Total body dose can also be calculated using site-related total body dose commitment factor.= site-related ingestion dose commitment factor to the total body or any organ o for radionuclide i (mrem/hr per ýtCi/ml)= average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (paCi/ml)= volume of liquid effluent released (gal)= average circulating water discharge rate during release period (gal/min)= conversion factor (hr/min)The site-related ingestion dose/dose commitment factors (Aio) are presented in Table 1-2 and have been derived in accordance with the requirements of NUREG-0 133 by the equation: Ai, = 1. 14E+05*[(UI*BIi)+(UF*BFi)]*DFio (1.6)Where: I I I I I U I I.I I I Aio = composite dose parameter for the total body or critical organ o of an adult for radionuclide i, for the fish and invertebrate ingestion pathways (mrem/hr per p.Ci/ml)UI = adult invertebrate consumption (5 kg/yr)Bli = bioaccumulation factor for radionuclide i in invertebrates from Table 1-3 (pCi/kg per pCi/1)UF = adult fish consumption (21 kg/yr)BFi = bioaccumulation factor for radionuclide i in fish from Table 1-3 (pCi/kg per pCi/1)DFio = dose conversion factor for nuclide i for adults in pre-selected organ, o, from Table E- 11 of Regulatory Guide 1.109 (mrem/pCi) 1.14E+05 = conversion factor (pCi/tCi

ml/kg per hr/yr)The radionuclides included in the periodic dose assessment per the requirements of ODCM CONTROL 3/4.11.1.2 are those as identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of ODCM CONTROL 3/4.11.1.1, Table 4.11-1.Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added to the dose analysis at a frequency consistent with the required minimum analysis frequency of ODCM CONTROL Table 4.11-1.223 SALEM ODCM REV. 26 1.4.2 Simplified Liquid Effluent Dose Calculation.

In lieu of the individual radionuclide dose assessment as presented in Section 1.4.1, the following simplified dose calculation equation may be used for demonstrating compliance with the dose limits of ODCM CONTROL 3.11.1.2. (Refer to Appendix B for the derivation and justification for this simplified method.)Total Body 1.21E + 03 *VOL Dtb= c *z Ci (1.7)CW i(17 Maximum Oran 2.52E + 04 *VOL ZC O rrmqx"" "S CW (1.8)Where: Ci = average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (iiCi/ml)VOL = volume of liquid effluent released (gal)CW -= average circulating water discharge rate during release period (gal/min)Dtb conservatively evaluated total body dose (mrem)Dmax conservatively evaluated maximum organ dose (mrem)1.21E+03 conversion factor (hr/min) and the total body dose conversion factor (Fe-59, total body-- 7.27E+04 mrem/hr per jiCi/ml)2.52E+04 conversion factor (hr/min) and the conservative maximum organ dose conversion factor (Nb-95, GI-LLI -- 1.5 1E+06 mrem/hr per ýtCi/ml)1.5 Secondary Side Radioactive Liquid Effluents and Dose Calculations During Primary to Secondary Leakage During periods of primary to secondary leakage (i.e., steam generator tube leaks), radioactive material will be transmitted from the primary system to the secondary system. The potential exists for the release of radioactive material to the off-site environment (Delaware River) via secondary system discharges.

Potential releases are controlled/monitored by the Steam Generator Blowdown monitors (R19) and the Chemical Waste Basin monitor (R37).However to ensure compliance with the regulatory limits on radioactive material releases, it may be desirable to account for potential releases from the secondary system during periods of primary to secondary leakage. Any potentially significant releases will be via the Chemical Waste Basin with the major source of activity being the Steam Generator Blowdown.With identified radioactive material levels in the secondary system, appropriate samples should be collected and analyzed for the principal gamma emitting radionuclides.

Based on the identified radioactive material levels and the volume of water discharged, the resulting environmental doses may be calculated based on equation (1.5).224 SALEM ODCM REV. 26 Because the release rate from the secondary system is indirect (e.g., SG blowdown is normally routed to condenser where the condensate clean-up system will remove much of the radioactive material), samples should be collected from the release point (i.e., Chemical Waste Basin) for quantifying the radioactive material releases.

However, for conservatism and ease of controlling and quantifying all potential release paths, it is prudent to sample the SG blowdown and to assume all radioactive material is released directly to the environment via the Chemical Waste Basin. This approach while not exact is 3 conservative and ensures timely analysis for regulatory compliance.

Accounting for radioactive material retention of the condensate clean-up system ion exchange resins may be needed to more I accurately account for actual releases.In addition to the secondary releases described in this section, the Salem Ground Water Remediation System also can potentially discharge radioactive material to the Chemical Waste Basin. To ensure i regulatory compliance, the releases are monitored by Radiation Monitor R-37. Samples are also collected, and analyzed for radionuclides.

Based on the identified radioactive material levels and the volume of water discharged, the resulting environmental doses may be calculated based on equation I (1.5).1.6 Liquid Effluent Dose Projections I ODCM CONTROL 3.11.1.3 requires that the liquid radioactive waste processing system be used to reduce the radioactive material levels in the liquid waste prior to release when the quarterly projected doses exceed:-0.375 mrem to the total body, or-1.25 mrem to any organ.The applicable liquid waste processing system for maintaining radioactive material releases ALARA is the ion exchange system as delineated in Figure 1-3. Alternately, the waste evaporator as presented in the Salem FSAR has processing capabilities meeting the NRC ALARA design requirements and may I be used in conjunction or in lieu of the ion exchange system for waste processing requirements in accordance with ODCM CONTROL 3.11.1.3.

These processing requirements are applicable to each unit individually.

Exceeding the projected dose requiring processing prior to release for one unit does I not in itself dictate processing requirements for the other unit.Dose projections are made at least once per 31 days by the following equations:

3]D:)tb-P = Zhbrld (1.9)3 D rnaxp = D maxl9 jJ (1.10) I Where: 3 Dtbp = the total body dose projection for current calendar quarter (mrem)Dtb = the total body dose to date for current calendar quarter as determined by Equation 1.5 or 1.7 (mrem)225 3 SALEM ODCM REV. 26 Dmaxp = the maximum organ dose projection for current calendar quarter (mrem)Dmax = the maximum organ dose to date for current calendar quarter as determined by Equation 1.5 or 1.7 (mrem)d = the number of days to date for current calendar quarter 91 = the number of days in a calendar quarter 2.0 GASEOUS EFFLUENTS 2.1 Radiation Monitoring Instrumentation and Controls The gaseous effluent monitoring instrumentation and controls at Salem for controlling and monitoring normal radioactive material releases in accordance with the Technical Specifications 6.8.4.g and ODCM CONTROLS are summarized as follows: 1) Waste Gas Holdup System -The vent header gases are collected by the waste gas holdup system.Gases may be recycled to provide cover gas for the CVCS hold-up tank or held in the waste gas tanks for decay prior to release. Waste gas decay tanks are batch released after sampling and analysis.

The tanks are discharged via the Plant Vent. 1-R41D provides noble gas monitoring and automatic isolation of waste gas decay tank releases for Unit-1. This function is provided by 2-R41D for Unit-2.2) Containment Purge and Pressure/Vacuum Relief -containment purges and pressure/vacuum reliefs are released to the atmosphere via the respective unit Plant Vent. Noble gas monitoring and auto isolation function are provided by l-R41D for Unit-I and 2-R41D for Unit-2. Additionally, in accordance with ODCM CONTROL 3.3.3.9, Table 3.3-13, 1-R12A and 2-R12A may be used to provide the containment monitoring and automatic isolation function during purge and pressure/vacuum reliefs (*)3) Plant Vent -The Plant Vent for each respective unit receives discharges from the waste gas hold-up system, condenser evacuation system, containment purge and pressure/vacuum reliefs, and the Auxiliary Building ventilation.

Effluents are monitored by R41D, a flow through gross activity monitor (for noble gas monitoring).

Radioiodine and particulate sampling capabilities are provided by charcoal cartridge and filter medium samplers.

Additionally, back-up sampling capability for radioiodine and particulates is provided at the 1-R45 and 2-R45 sampling skids. Plant Vent flow rate is measured and as a back-up may be determined empirically as a function of fan operation (fan curves). Sampler flow rates are determined by flow rate instrumentation (e.g., venturi rotameter).

Gaseous radioactive effluent flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented in Figures 2-1. A simplified diagram of the Gaseous radioactive waste disposal system is provided in Figure 2-2.* The R12A in Mode 6 provides containment monitoring and alarm functions without automatic isolation 226 SALEM ODCM REV. 26 2.2 Gaseous Effluent Monitor Setpoint Determination 2.2.1 Containment and Plant Vent Monitor Per the requirements of ODCM CONTROL 3.3.3.9, alarm setpoints shall be established for the gaseous I effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of ODCM CONTROL 3.11.2.1, which corresponds to a dose rate at the SITE BOUNDARY of 500 mrem/year to the total body or 3000 mrem/year to the skin.Based on a grab sample analysis of the applicable release (i.e., grab sample of the Containment atmosphere, waste gas decay tank, or Plant Vent), the radiation monitoring alarm setpoints may be established by the following calculation method. The measured radionuclide concentrations and release rate are used to calculate the fraction of the allowable release rate, as limited by Specification 3.11.2.1, by the equation: FRAC=L4.72E+02*'-

/Q*VF* r(Ci*Ki)]/500 (2.1) I FRAC=14.72E

+02* VF v* (Ci *(Li +1.IM))]/3000 (2.2)I I Where: FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate 7/Q = annual average meteorological dispersion to the controlling site boundary location (sec/m 3)VF = ventilation system flow rate for the applicable release point and monitor (ft 3/min)Ci = concentration of noble gas radionuclide i as determined by radioanalysis of grab sample (pCi/cm 3)Ki = total body dose conversion factor for noble gas radionuclide i (mrem/yr per pCi/m 3 from Table 2-1)Li = beta skin dose conversion factor for noble gas radionuclide i (mrem/yr per jCi/m 3 from Table 2-1)Mi = gamma air dose conversion factor for noble gas radionuclide i (mrem/yr per ptCi/m 3 from Table 2-1)1.1 = mrem skin dose per mrad gamma air dose (mrern/mrad) 500 = total body dose rate limit (mrem/yr)3000 = skin dose rate limit (mrem/yr)4.72 E+02 = conversion factor (cm 3/ft 3

min/sec) 3 Based on the more limiting FRAC (i.e., higher value) as determined above, the alarm setpoints for the applicable monitors (R41D, and/or R12A) may be calculated by the equation: 227 SALEM ODCM REV. 26[ Ci

SEN 1 SP= AF* j +bkg, (2.3)Where: SP = alarm setpoint corresponding to the maximum allowable release rate (cpm)SEN = monitor sensitivity (cpm per pCi/cm 3)bkg = background of the monitor (cpm)AF = administrative allocation factor for the specific monitor and type release, which corresponds to the fraction of the total allowable release rate that is administratively allocated to the release.The allocation factor (AF) is an administrative control imposed to ensure that combined releases from Salem Units 1 and 2 and Hope Creek will not exceed the regulatory limits on release rate from the site (i.e., the release rate limits of ODCM CONTROL 3.11.2.1).

Normally, the combined AF value for Salem Units 1 and 2 is equal to 0.5 (0.25 per unit), with the remainder 0.5 allocated to Hope Creek.Any increase in AF above 0.5 for the Salem Nuclear Generating Station will be coordinated with the Hope Creek Generating Station to ensure that the combined allocation factors for all units do not exceed 1.0.2.2.2 Conservative Default Values A conservative alarm setpoint can be established, in lieu of the individual radionuclide evaluation based on the grab sample analysis, to eliminate the potential of periodically having to adjust the setpoint to reflect minor changes in radionuclide distribution and variations in release flow rate. The alarm setpoint may be conservatively determined by the default values presented in Table 2-2.1 and 2-2.2 for Units 1 and 2, respectively.

These values are based upon:-the maximum ventilation (or purge) flow rate;-a radionuclide distributiona comprised of 95% Xe-133, 2% Xe-135, 1% Xe-133m, 1% Kr-88 and 1% Kr-85; and-an administrative allocation factor of 0.25 to conservatively ensure that any simultaneous releases from Salem Units 1 and 2 do not exceed the maximum allowable release rate. For this radionuclide distribution, the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dose rate.a) Adopted from ANSI N237-1976/ANS-18.1, Source Term Specifications, Table 6 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations

-10 CFR 20 2.3.1 Site Boundary Dose Rate -Noble Gases ODCM CONTROL 3.11.2.1 .a limits the dose rate at the SITE BOUNDARY due to noble gas releases to <500 mrem/yr, total body and <3000 mrem/yr, skin. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded.

In the event any gaseous releases from the station results in an alarm setpoint being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release shall be performed using the following equations:

228 SALEM ODCM REV. 26 I Dtb= Z(K QI) (2.4)and D,= XQ* :((Li +1. 1M)*Qi) (2.5)I Where: i Dtb = total body dose rate (mrem/yr)Ds = skin dose rate (mrem/yr)V = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m 3)Qi = average release rate of radionuclide i over the release period under evaluation (gCi/sec)Ki = total body dose conversion factor for noble gas radionuclide i (mrem/yr per gCi/m 3 , from Table 2-1) I Li = beta skin dose conversion factor for noble gas radionuclide i (mrem/yr per pCi/r 3 , from Table 2-1)Mi = gamma air dose conversion factor for noble gas radionuclide i (mrad/yr per gCi/m 3 , from I Table 2-1)1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad) i As appropriate, simultaneous releases from Salem Units 1 and 2 and Hope Creek will be considered in evaluating compliance with the release rate limits of ODCM CONTROL 3.11.2.1 a, following any release exceeding the above prescribed alarm setpoints.

Monitor indications (readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity.

I The 15-minute averaging is needed to allow for reasonable monitor response to potentially changing radioactive material concentrations and to exclude potential electronic spikes in monitor readings that may be unrelated to radioactive material releases.

As identified, any electronic spiking monitor responses may be excluded from the analysis.NOTE: For administrative purposes, more conservative alarm setpoints than those as I prescribed above may be imposed. However, conditions exceeding these more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding the limits of ODCM CONTROL 3.11.2.1.a.

Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based on the above criteria, no further analyses are required for demonstrating compliance with the limits of ODCM CONTROL 3.11.2.1.a.

Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-3 may be used for evaluating the gaseous effluent dose rate.I 229 SALEM ODCM REV. 26 2.3.2 Site Boundary Dose Rate -Radioiodine and Particulates ODCM CONTROL 3.11.2. .b limits the dose rate to <1500 mrem/yr to any organ for 1-13 1, tritium, and particulates with half-lives greater than 8 days. To demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period (e.g., nominally once per 7 days). The following equation shall be used for the dose rate evaluation:

Do(Ro * (2.6)i" Where: Do = average organ dose rate over the sampling time period (mrem/yr)iQ = atmospheric dispersion to the controlling SITE BOUNDARY location for the inhalation pathway (sec/m 3)Rio dose parameter for radionuclide i (mrem/yr per [tCi/m 3) and organ o for the child inhalation pathway from Table 2-4 Qi average release rate over the appropriate sampling period and analysis frequency for radionuclide i -- 1-131, tritium or other radionuclide in particulate form with half-life greater than 8 days ([tCi/sec)

By substituting 1500 mrem/yr for Do and solving for Q, an allowable release rate for 1-131 can be determined.

Based on the annual average meteorological dispersion (see Table 2-3) and the most limiting potential pathway, age group and organ (inhalation, child, thyroid -- Rio = 1.62E+07 mrem/yr per ptCi/m 3), the allowable release rate for 1-131 is 42 jiCi/sec.

Reducing this release rate by a factor of 4 to account for potential dose contributions from other radioactive particulate material and other release points (e.g., Hope Creek), the corresponding release rate allocated to each of the Salem units is 10.5 [tCi/sec.For a 7 day period, which is the nominal sampling and analysis frequency for 1-131, the cumulative release is 6.3 Ci. Therefore, as long as the 1-131 releases in any 7 day period do not exceed 6.3 Ci, no additional analyses are needed for verifying compliance with the ODCM CONTROL 3.11.2.1 .b limits on allowable release rate.2.4 Noble Gas Effluent Dose Calculations

-10 CFR 50 2.4.1 UNRESTRICTED AREA Dose -Noble Gases ODCM CONTROL 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 are 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: Dy =3.17E-(08*.

Z(M*Qi) (2.7)%2(27 230 SALEM ODCM REV. 26 and Dp= 3.17E-08*%Q

Z(N *Qi)(2.8)Where: Dr = air dose due to gamma emissions for noble gas radionuclides (mrad)D# = air dose due to beta emissions for noble gas radionuclides (mrad)V// = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/mr 3)7Q Qi= cumulative release of noble gas radionuclide i over the period of interest (tCi) where pCi = (pJCi/cc)*(cc released) or (pCi/sec)*(sec released)= air dose factor due to gamma emissions from noble gas radionuclide i (mrad/yr per gCi/m 3 , from Table 2-1)-air dose factor due to beta emissions from noble gas radionuclide i (mrad/yr per ýiCi/m 3 , Table 2-1)= conversion factor (yr/sec)3.17E-08 2.4.2 Simplified Dose Calculation for Noble Gases In lieu of the individual noble gas radionuclide dose assessment as presented above, the following simplified dose calculation equations may be used for verifying compliance with the dose limits of ODCM CONTROL 3.11.2.2. (Refer to Appendix C for the derivation and justification for this simplified method and for values of Meff, and Neff..)I I I I I I I i I I I I I i I I I I Dy=3.1 7 E-0 8* *Mff Qi 0. 0 0 Q _, (2.9)and Dfl = 3.17E5- 08 Q 0.50 YQi (2.10)Where: Seff Neff Qi 0.50= 5.3E+02, effective gamma-air dose factor (mradlyr per pCi/mn 3)= 1. 1E+03, effective beta-air dose factor (mrad/yr per pCi/rn 3)= cumulative release for all noble gas radionuclides

([tCi), where gCi = (pCi/cc) * (cc released) or (pCi/sec)

(sec released)= conservatism factor to account for potential variability in the radionuclide distribution Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-3, may be used for the evaluation of the gamma-air and beta-air doses.231 I SALEM ODCM REV. 26 2.5 Radioiodine and Particulate Dose Calculations

-10 CFR 50 2.5.1 UNRESTRICTED AREA Dose -Radioiodine and Particulates In accordance with requirements of ODCM CONTROL 3.11.2.3, a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit of <7.5 mrem and calendar year limit<15 mrem to any organ. The following equation shall be used to evaluate the maximum organ dose due to releases of 1- 131, tritium and particulates with half-lives greater than 8 days: Daop 3.17E- 08* W

SFp *Z (Riop*Q) (2.11)Where: Daop = dose or dose commitment via all pathways p and controlling age group a (as identified in Table 2-3) to organ o, including the total body (mrem)W = atmospheric dispersion parameter to the controlling location(s) as identified in Table 2-3 Q atmospheric dispersion for inhalation pathway and H-3 dose contribution via other 7Q pathways (sec/m 3)D/Q = atmospheric deposition for vegetation, milk and ground plane exposure pathways (m-2)Riop = dose factor for radionuclide i (mrem/yr per ýLCi/m 3) or (m 2 -mremnyr per jtCi/sec)and organ o from Table 2-4 for each age group and the applicable pathway p as identified in Table 2-3. Values for Riop were derived in accordance with the methods described in NUREG-0133.

Q = cumulative release over the period of interest for radionuclide i - 131, tritium, or radioactive material in particulate form with half-life greater than 8 days (pCi).SFp annual seasonal correction factor to account for the fraction of the year that the applicable exposure pathway does not exist.1) For milk and vegetation exposure pathways: A six month fresh vegetation and grazing season (May through October) = 0.5 2) For inhalation and ground plane exposure pathways:

= 1.0 For evaluating the maximum exposed individual, only the controlling pathways and age group as identified in Table 2-3 need be evaluated for compliance with ODCM CONTROL 3.11.2.3.2.5.2 Simplified Dose Calculation for Radioiodines and Particulates.

In lieu of the individual radionuclide (1-131, tritium, and particulates) dose assessment for the resident/dairy location as presented above, the following simplified dose calculation equation may be used for verifying compliance with the dose limits of ODCM CONTROL 3.11.2.3 (refer to Appendix D for the derivation and justification of this simplified method).D x =3.17E-08*W*SFp*RI-131*" Qi (2.12)Qi 232 SALEM ODCM REV. 26 Where: Dax = maximum organ dose (mrem)RI-131 = 1-131 dose parameter for the thyroid for the identified controlling pathway i= 1.05E+12, infant thyroid dose parameter with the grass-cow-milk pathway controlling (in 2 -mrem/yr per [tCi/sec)W = D/Q for radioiodine, 2.1E-10 1/i 2 i Qi = cumulative release over the period of interest for radionuclide i 131, tritium, or radioactive material in particulate from with half life greater than 8 days (PCi)The dose should be evaluated based-on the predetermined controlling pathways as identified in Table 2-3. If more limiting exposure pathways are determined to exist in the surrounding environment of Salem by the annual land-use census, Table 2-3 will be revised as specified in ODCM CONTROL 3.12.2.2.6 Secondary Side Radioactive Gaseous Effluents and Dose Calculations During periods of primary to secondary leakage, minor levels of radioactive material may be released via the secondary system to the atmosphere.

Non-condensables (e.g., noble gases) will be predominately released via the condenser evacuation system and will be monitored and quantified by the routine plant vent monitoring and sampling system and procedures (e.g., R15 on condenser evacuation, R4 1 D on plant vent, and the plant vent particulate and charcoal samplers).

However, if the Steam Generator blowdown is routed directly to the Chemical Waste Basin (via the SG blowdown flash tank) instead of being recycled through the condenser, it may be desirable to account for the potential atmospheric releases of radioiodines and particulates from the flash tank vent (i.e., releases due to moisture carry over). Since this pathway is not sampled or monitored, it is necessary to calculate potential releases.Based on the guidance in NRC NUREG-0 133, the releases of the radioiodines and particulates shall be calculated by the equation: Qi-Ci*Rsgb*Ffi* (I- SQftv) (2.13)Where: Qj = the release rate of radionuclide, i, from the steam generator flash tank vent (piCi/sec)

Ci = the concentration of radionuclide, i, in the secondary coolant water averaged over not more than one week (pCi/ml)Rsgb = the steam generator blowdown rate to the flash tank (ml/sec)Fft = the fraction of blowdown flashed in the tank determined from a heat balance taken around the flash tank at the applicable reactor power level SQftv= the measured steam quality in the flash tank vent; or an assumed value of 0.85, based on NUREG-0017.

Tritium releases via the steam flashing may also be quantified using the above equation With the assumption of a steam quality (SQf) equal to 0. Since the H-3 will be associated with the water 233 SALEM ODCM REV. 26 molecules, it is not necessary to account for the moisture carry-over which is the transport media for the radioiodines and particulates.

Based on the design and operating conditions at Salem, the fraction of blowdown converted to steam (Fft) is approximately 0.48. The equation simplifies to the following:

Qi = 0.072 Ci

Rgb (2.14)For H-3, the simplified equation is: Qi = 0.48 *Ci Rsgb (2.15)Also during reactor shutdown operations with a radioactively contaminated secondary system, radioactive material may be released to the atmosphere via the atmospheric reliefs (PORV) and the safety reliefs on the main steam lines and via the steam driven auxiliary feed pump exhaust. The evaluation of the radioactive material concentration in the steam relative to that in the steam generator water is based on the guidance of NUREG-00 17, Revision 1. The partitioning factors for the radioiodines is 0.01 and is 0.005 for all other particulate radioactive material.

The resulting equation for quantifying releases via the atmospheric steam releases is: QY= 0.13 (ci SFi) PFi (2.16)Where: Qj= release rate of radionuclide i via pathway j,(ýtCi/sec)

C0= concentration of radionuclide i, in pathway j,(pCi/ml)

SFj = steam flow for release pathway j-400,000 lb/hr per PORV= 850,000 lb/hr per safety relief valve= 62,500 lb/hr for auxiliary feed pump exhaust PFi = partitioning factor, ratio of concentration in steam to that in the water in the steam generator= 0.01 for radioiodines

= 0.005 for all other particulates

= 1.0 for H-3 0.13 = conversion factor -[(hr*ml) / (sec*lb)]Any significant releases of noble gases via the atmospheric steam releases can be quantified in accordance with the calculation methods of the Salem Emergency Plan Implementation Procedure.

Alternately, the quantification of the release rate and cumulative releases may be based on secondary samples. The measured radionuclide concentration in the secondary system may be used for quantifying the noble gases, radioiodine, and particulate releases.234 SALEM ODCM REV. 26 Note: The expected mode of operation would be to isolate the effected steam generator, thereby reducing the potential releases during the shutdown/cooldown process. Use of the above calculation methods should consider actual operating conditions and release mechanisms.

The calculated quantities of radioactive materials may be used as inputs to the equation (2.11) or (2.12)to calculate offsite doses for demonstrating compliance with the Technical Specifications 6.8.4.g and the ODCM CONTROLS.2.7 Gaseous Effluent Dose Projection ODCM CONTROL 3.11.2.4 requires that the GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected doses exceed one-half the annual design objective rate in any calendar quarter, i.e., exceeding:

-0.625 mrad/quarter, gamma air;-1.25 mrad/quarter, beta air; or-1.875 mrem/quarter, maximum organ.The applicable gaseous processing systems for maintaining radioactive material releases ALARA are the Auxiliary Building normal ventilation system (filtration systems # 1, 2 and 3) and the Waste Gas Decay Tanks as delineated in Figures 2- 1 and 2-2. Dose projections are performed at least once per 31 days by the following equations:

Dly ~D7 *(9Vd (2.17)DA,J= Do *(9Yd) (2.18)D maxp =Dmax*(9d (2.19)Where: Dyp = gamma air dose projection for current calendar quarter(mrad)

Dy = gamma air dose to date for current calendar quarter as determined by Equation 2.7 or 2.9 (mrem)OD3p = beta air dose projection for current calendar quarter (mrad)Dp = beta air dose to date for current calendar quarter as determined by Equation 2.8 or 2.10 (mrem)Dmaxp = maximum organ dose projection for current calendar quarter (mrem)Dmax = maximum organ dose to date for current calendar quarter as determined by Equation 2.11 or 2.12 (mrem)d number of days to date in current calendar quarter 91 = number of days in a calendar quarter 235 SALEM ODCM REV. 26 3.0 SPECIAL DOSE ANALYSES 3.1 Doses Due To Activities Inside the SITE BOUNDARY In accordance with ODCM CONTROL 6.9.1.8, the Radioactive Effluent Release Report (RERR) shall include an assessment of radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY.The calculation methods as presented in Sections 2.4 and 2.5 may be used for determining the maximum potential dose to a MEMBER OF THE PUBLIC located inside the site boundary.

For the purpose of this calculation, a MEMBER OF THE PUBLIC is an adult individual who is not subject to occupational exposure (i.e., an un-monitored site worker) performing duties within the site boundary, and who is exposed to radioactive material in gaseous effluent for 2,000 hours0 days 0 hours 0 weeks 0 months per year via the inhalation and ground plane exposure pathways.

The values for the atmospheric dispersion coefficients at the point of interest inside the site boundary (e.g., 0.25 mile) shall be developed from the current year meteorological data.3.2 Total dose to MEMBERS OF THE PUBLIC -40 CFR 190 and 10 CFR 72.104 The Radioactive Effluent Release Report (RERR) shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle sources (including dose contributions from effluents and direct radiation from on-site sources).

For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of Artificial Island, the sources of exposure need only consider the Salem Nuclear Generating Station and the Hope Creek Nuclear Generating Station which includes the Independent Spent Fuel Storage Installation (ISFSI): No other fuel cycle facilities contribute to the MEMBER OF THE PUBLIC dose for the Artificial Island vicinity.The dose contribution from the operation of Hope Creek Nuclear Generating Station will be estimated based on the methods as presented in the Hope Creek Offsite Dose Calculation Manual (HCGS ODCM).As appropriate for demonstrating/evaluating compliance with the limits of ODCM CONTROL 3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used for providing data on actual measured levels of radioactive material in the actual pathways of exposure.3.2.1 Effluent Dose Calculations For purposes of implementing the surveillance requirements of ODCM CONTROL 3/4.11.4 and the reporting requirements of 6.9.1.8 (RERR), dose calculations for the Salem Nuclear Generating Station should be performed using the controlling pathways and locations of Table 2-3 and the calculation methods contained within this ODCM. If more limiting exposure pathways are determined to exist in the surrounding environment of Salem by the annual land-use census, Table 2-3 will be revised as specified in ODCM CONTROL 3.12.2.Average annual meteorological dispersion parameters or meteorological conditions concurrent with the release period under evaluation may be used.236 SALEM ODCM REV. 26 3.2.2 Direct Exposure Dose Determination.

3 Any potentially significant direct exposure contribution to off-site individual doses may be evaluated based on the results of the environmental measurements (e.g., DLR, ion chamber measurements) and/or by the use of a radiation transport and shielding calculation method.Only during a non-typical condition will there exist any potential for significant on-site sources at Salem that would yield potentially significant off-site doses (i.e., in excess of 1 mrem per year to a MEMBER OF THE PUBLIC), that would require detailed evaluation for demonstrating compliance with 40 CFR 190 or 10 CFR 72.104.However, should a situation exist where the direct exposure contribution is potentially significant, on-site measurements, off-site measurements and/or calculation techniques will be used for determination I of dose for assessing 40 CFR 190 or 10 CFR 72.104 compliance.

3.3 Doses Due to Carbon 14 in Gaseous Effluents I Because gaseous effluent releases from a pressurized water reactor (PWR), such as the Salem Generating Station, can contain significant quantities of C-14 (i.e., approximately 5 to 7.3 curies annually -Regulatory Guide 1.21 rev 2), the NRC has recommended that licensees evaluate C-14 as a potential principal radionuclide for gaseous releases from their facility.

The results in an evaluation conducted in response to SAP Order 70096339 identified C-14 as a principal radionuclide in gaseous effluent releases from the Salem Generating Station.3.3.1 Estimation of Carbon 14 in Annual Releases The methodology for estimating the quantity C-14 released annually from the Salem Generating Station I incorporates the use of a normalized C-14 source term and a scaling factor based on power generation.

NCRP Report No. 81, Carbon-14 in the Environment, has been identified by the NRC as a source for scaling factors (refer to section 1.9 in Revision 2 of Regulatory Guide 1.21). This approach is one of I three NRC-recommended methods for estimating the quantity of C-14 'discharged in gaseous effluent (refer to Regulatory position 1.9 in Revision 2 of Regulatory Guide 1.21). Electrical energy output value for the reporting period should be used to estimate the quantity of C-14 released.I 237 SALEM ODCM REV. 26 3.3.2 Carbon 14 dose Determinations The methodology for determining doses from C-14 in gaseous releases incorporates dose models described in Regulatory Guide 1.109. Estimated C-i14 releases and average meteorological data for the reporting period should be used as input to the dose calculations.

The doses due to C-14 in gaseous releases are calculated for receptors located at and beyond the site boundary.

For doses at locations beyond the site boundaries, receptors shall be real individuals via active pathways as identified in the Annual Land Use Census. Doses due to C-14 in gaseous effluent and the assumptions used in the dose calculations shall be included in the annual Radioactive Effluent Release Report.4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4.1 Sampling Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of ODCM CONTROL 3.12. The objectives of the program are:-To determine whether any significant increases occur in the concentration of radionuclides in the critical pathways of exposure in the vicinity of Artificial Island;-To determine if the operation of the Salem Nuclear Generating Stations has resulted in any increase in the inventory of long lived radionuclides in the environment;

-To detect any changes in the ambient gamma radiation levels; and-To verify that SNGS operations have no detrimental effects on the health and safety of the public or on the environment.

The sampling requirements (type of samples*, collection frequency and analysis) and sample locations are presented in Appendix E.NOTE: No public drinking water samples or irrigation water samples are required as these pathways are not directly effected by liquid effluents discharged from Salem Generating Station.4.2 Interlaboratory Comparison Program ODCM CONTROL 3.12.3 requires analyses be performed on radioactive material supplied as part of an Interlaboratory Comparison Program. Participation in an approved Interlaboratory Comparison Program provides a check on the precision and accuracy of measurements of radioactive materials in environmental samples.A summary of the Interlaboratory Comparison Program results will be provided in the Annual Radiological Environmental Operating Report pursuant to ODCM CONTROL 6.9.1.7.238 SALEM ODCM REV. 26 FIGURE 1-1: LIQUID RELEASE FLOWPATH UNIT 1 FROM VOLUME CONTROL. TANKS TO VENTS TO CVCS I .#1 SPENT FUELPIT DEMINERALIZER SAMP I INr-STEAM GENERATOR SAMPLING LINES I R19 MONITORS.UNIT 2 R18 MONITOR I SERVICE WATER 5 CONTAINMENT FAN COIL UNITS rO NON-RAD (C)(Figure 1-2)TO NON-RAD (B)(Figure 1-2)TO CIRC ATING WATER SYSTEM R 13 MONITORS To River 239 m m mmmm m m mm m m m m m mm m

-m nE m m -m m m m m SALEM ODCM REV. 26 FIGURE 1-2: LIQUID RELEASE FLOWPATH UNIT 2 FROM VOLUME CONTROL TANKS CVCS#1 SPENT FUEL PIT DEMINERALIZER SAMP I INr, STEAM GENERATOR SAMPLING LINES UNIT 1 CROSS-CONNECT FROM UNIT 1 (B)NON-RAD LIQUID WASTE DISPOSAL TO CIRCULATING WATER SYSTEM FROM UNIT 1 1-1)MONITORS 240 SALEM ODCM REV. 26 FIGURE 1-3: LIQUID RADIOACTIVE WASTE SYSTEM LAUNDRY CHEMICAL WASTE AND HOT DRAIN[COMPRE SHOWER TANK WAST ANAL WASTE CANA HOLD-UP TANK TANK DRAINS WASTE HOLD-UP TANK FLOOR DRAINS SUMPSAND DRAINS DRAINS I WASTSTUM TANK 241 Sm m nm mmmmmm nm mm m m m mm SALEM ODCM REV. 26 Table 1-1.1: Parameters for Liauid Alarm Setwoint Determinations Unit 1 i

r Parameter Actual Default Comments Value Value Units MPCe Calculated 6.05E-06

pCi/ml Calculated for each batch to be released.MPC 1-131 3.OE-07 N/A p.Ci/ml 1- 131 MPC conservatively used for SG blowdown and Service Water monitor setpoints.

Ci Measured N/A ýiCi/ml Taken from gamma spectral analysis of liquid effluent.MPCi as determined N/A pCi/ml Taken from 10 CFR 20, Appendix B, Table II, Col 2 (Appendix F).Sensitivity as determined N/A cpm per Monitor sensitivities are controlled 1-R18 ICi/ml under Public Service Blueprint l-R19 (A,B,C,D)

Document (PSBP) 315733 1-R13 (A and B)CW as determined 1.OOE+05 gpm Circulating water system -single CW pump *RR as determined gpm Determined prior to release; release rate 1-R18 120 can be adjusted for ODCM CONTROL compliance 1-R19 250 Steam Generator blowdown rate per Generator Service Water flow rate for Containment fan coolers Setpoint Calculated N/A cpm Monitor setpoints are controlled under 1-R18 Public Service Blueprint Document l-R19 (A,B,C,D)** (PSBP) 315733 l-R13 (A and B)**Correction Factor as determined 0.75 Unitless Default parameter to account for non-(Non-Gamma) gamma emitting nuclides.Allocation Factor 0.5 0.5 Unitless Conservatism factor to preclude I-R19 exceeding MPC limit in the case of simultaneous primary-to-secondary leaks at both Salem Units* Refer to Appendix A for derivation

- The MPC value of 1-131 (3E-07 [tCi/ml) has been used for derivation of R19 Steam Generator Blowdown and R13 Service Water monitor setpoints as discussed in Section 1.2.2***During periods when Unit 2 Circulators are out of service, the CW flow for 1-R13 monitors is zero. See Section 1.2.2.242 SALEM ODCM REV. 26 Table 1-1.2: Parameters for Liquid Alarm Setpoint Determinations

-Unit 2 Parameter Actual Default Units Value Value Comments MPCe Calculated 4.81E-06

iiCi/ml Calculated for each batch to be released.MPC 1-131 3.0E-07 N/A ýtCi/ml 1-131 MPC conservatively used for SG blowdown, Service Water and Chemical Waste Basin monitor setpoints.

C 1 Measured N/A pCi/ml Taken from gamma spectral analysis of liquid effluent.MPCi as determined N/A ýLCi/ml Taken from 10 CFR 20, Appendix B, Table II, Col. 2 (Appendix F)Sensitivity as determined N/A cpm per Monitor sensitivities are controlled 2-R18 ItCi/ml under Public Service Blueprint Document 2R19(A,B,C,D) 315734 2-R13(A and B)R37 CW as determined 1.0E+05 gpm Circulating Water System, single CW pump ***RR as determined 120 gpm Determined prior to release; release rate 2-R18 can be adjusted for ODCM CONTROL Compliance 250 2-R19 Steam Generator Blowdown rate per Generator 1.0E+05 2-RI3 Circulating Water System, single CW 1200 Pump R37 Chemical Waste Basin discharge Setpoint Calculated N/A cpm Monitor setpoints are controlled under 2-R18 Public Service Blueprint Document 2-R19(A,B,C,D)** (PSBP) 315734 2-R13(A and B)**R37 **Correction Factor as determined 0.75 Unitless Default parameter to account for non-(Non-Gamma) gamma emitting nuclides.Allocation Factor 0.5 0.5 Unitless Conservatism factor to preclude 2-R19 exceeding MPC limit in the case of simultaneous primary-to-secondary leaks at both Salem Units* Refer to Appendix A for derivation

- The MPC value of 1-131 (3.OE-7 p.Ci/ml) has been used for derivation of the R13, R19 and R37 monitor setpoints as discussed in Section 1.2.2* During periods when Unit 1 Circulators are out of service, the CW flow for 2-R13 monitors is zero. See Section 1.2.2.243 I I I I I I I I I I I I.1 I I U I SALEM ODCM REV. 26 TABLE 1-2: Site Related Ingestion Dose Commitment Factor, Aio (Fish And Invertebrate Consumption)(mrem/hr per gCi/ml)iNucide Bio Iiiver T.Bod TrKney Long GlSI H-3 -2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 C-14 1.45E+4 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 P-32 4.69E+6 2.91E+5 1.81E+5 -5.27E+5 Cr-51 5.58E+O 3.34E+O 1.23E+O 7.40E+O 1.40E+3 Mn-54 7.06E+3 1.35E+3 -2.1OE+3 2.16E+4 Mn-56 -1.78E+2 3.15E+l -2.26E+2 5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 -1.97E+4 2.03E+4 Fe-59 8.06E+4 1.90E+5 7.27E+4 -5.30E+4 6.32E+5 Co-57 1.42E+2 2.36E+2 -3.59E+3 Co-58 6.03E+2 1.35E+3 -1.22E+4 Co-60 1.73E+3 3.82E+3 -3.25E+4 Ni-63 4.96E+4 3.44E+3 1.67E+3 --7.18E+2 Ni-65 2.02E+2 2.62E+l 1.20E+l -6.65E+2 Cu-64 2.14E+2 1.01E+2 -5.40E+2 1.83E+4 Zn-65 1.61E+5 5.13E+5 2.32E+5 -3.43E+5 3.23E+5 Zn-69 3.43E+2 6.56E+2 4.56E+l -4.26E+2 9.85E+l As-76 4.38E+2 1.16E+3 5.14E+3 3.42E+2 1.39E+3 3.58E+2 4.30E+4 Br-82 --4.07E+O --4.67E+O Br-83 --7.25E-2 --1.04E-1 Br-84 --9.39E-2 --7.37E-7 Br-85 --3.86E-3 ---Rb-86 -6.24E+2 2.91E+2 ---1.23E+2 Rb-88 -1.79E+O 9.49E-1 ---2.47E-11 Rb-89 1. 19E+O 8.34E-1 ---6.89E-14 Sr-89 4.99E+3 -1.43E+2 ---8.OOE+2 Sr-90 1.23E+5 -3.01E+4 ---3.55E+3 Sr-91 9.18E+l -3.71E+O ---4.37E+2 Sr-92 3.48E+l -1.51E+O ---6.90E+2 Y-90 6.06E+O -1.63E41 ---6.42E+4 Y-91m 5.73E-2 2.22E-3 ---1.68E-1 Y-91 8.88E+l 2.37E+O ---4.89E+4 Y-92 5.32E-1 -1.56E-2 --9.32E+3 Y-93 1.69E+O -4.66E-2 -- -5.35E+4 Zr-95 1.59E+1 5.11E+O 3.46E+O -8.02E+O -1.62E+4 Zr-97 8.81E-1 1.78E-1 8.13E-2 -2.68E-1 -5.51E+4 Nb-95 4.47E+2 2.49E+2 1.34E+2 -2.46E+2 -1.51E+6 Nb-97 3.75E+O 9.49E-1 3.46E-1 -1.11E+O -3.50E+3 Mo-99 -1.28E+2 2.43E+1 2.89E+2 -2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+1 Tc-101 1.33E-2 1.92E-2 1.88E-1 3.46E-1 9.81E-3 5.77E-14 244 SALEM ODCM REV. 26 i TABLE 1-2 (cont'd) i Site Related Ingestion Dose Commitment Factor, Aio (Fish And Invertebrate Consumption) 3 (mrem/hr per tCi/ml)Ru-103 1.07E+2 -4.60E+1 -4.07E+2 -1..25E+4 Ru-105 8.89E+O -3.51E+O -1.15E+2 -5.44E+3 Ru-106 1.59E+3 -2.01E+2 -3.06E+3 1.03E+5 Rh-103m .i Rh-106 --....Ag-1 10m 1.56E+3 1.45E+3 8.60E+2 -2.85E+3 -5.91E+5 Sb-122 1.98E+1 4.55E-1 6.82E+0 3.06E-1 -1.19E+1 7.51E+3 Sb-124 2.77E+2 5.23E+O 1.1OE+2 6.71E-1 -2.15E+2 7.86E+3 Sb-125 1.77E+2 1.98E+O 4.21E+1 1.80E-1 -1.36E+2 1.95E+3 Sb-126' 1.14E+2 2.31E+O 4.1OE+I 6.96E-1 -6.97E+1 9.29E+3 Te-125m 2.17E+2 7.86E+1 2.91E+1 6.52E+1 8.82E+2 -8.66E+2 Te-127m 5.48E+2 1.96E+2 6.68E+1 1.40E+2 2.23E+3 -1.84E+3 *Te-127 8.90E+O 3.20E+O 1.93E+O 6.60E+O 3.63E+1 -7.03E+2 l Te-129m 9.3 1E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 -4.69E+3 Te-129 2.54E+O 9.55E-1 6.19E-1 1.95E+O 1.07E+1 -1.92E+O *Te-131m 1.40E+2 6.85E+1 5.71E+1 1.08E+2 6.94E+2 -6.80E+3 lTe-131 1.59E+O 6.66E-1 5.03E-1 1.31E+O 6.99E+O -2.26E-1 Te-132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 -6.24E+3 1-130 3.96E+1 1.17E+2 4.61E+1 9.91E+3 1.82E+2 -1.01E+2 i 1-131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 -8.23E+1 1-132 1.06E+1 2.85E+1 9.96E+O 9.96E+2 4.54E+1 -5.35E+O 1-133 7.45E+1 1.30E+2 3.95E+1 1.90E+4 2.26E+2 -1.16E+2 1-134 5.56E+O 1.51E+1 5.40E+O 2.62E+2 2.40E+1 -1.32E-2 1-135 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 -6.87E+1 Cs-134 6.84E+3 1.63E+4 1.33E+4 -5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 -1.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 -4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+0 1.20E+1 5.94E+O -8.81E+O 8.70E-1 5.12E-5 Ba-139 7.85E+O 5.59E-3 2.30E-1 -5.23E-3 3.17E-3 1.39E+1 Ba-140 1.64E+3 2.06E+O 1.08E+2 -7.02E-1 1.18E+O 3.38E+3 Ba-141 3.81E+0 2.88E-3 1.29E-1 -2.68E-3 1.63E-3 1.80E-9 Ba-142 1.72E+O 1.77E-3 1.08E-1 -1.50E-3 1.OOE-3 2.43E-18 I La-140 1.57E+O 7.94E-1 2.10E-1 ---5.83E+4 La-142 8.06E-2 3.67E-2 9.13E-3 --2.68E+2 Ce-141 3.43E+O 2.32E+O 2.63E-1 1.08E+O -8.86E+3 Ce-143 6.04E-1 4.46E+2 4.94E-2 1.97E-1 -1.67E+4 Ce-144 1.79E+2 7.47E+1 9.59E+O 4.43E+1 -6.04E+4 Pr-143 5.79E+O 2.32E+O 2.87E-1 1.34E+O -2.54E+4 Pr-144 1.90E-2 7.87E-3 9.64E-4 4. 44E-3 -2.73E-9 Nd-147 3.96E+O 4.58E+0 2.74E-1 2.68E+O -2.20E+4 W-187 9.16E+O 7.66E+O 2.68E+O --2.51E+3 Np-239 3.53E-2 3.47E-3 1.91E-3 1.08E-2 -7.1IE+2 I 245 SALEM ODCM REV. 26 Table 1-3: Bioaccumulation Factors (pCi/kg per pCi/liter)*

H 9.OE-01 9.3E-01 C 1.8E+03 1.4E+03 Na 6.7E-02 1.9E-01 P 3.OE+03 3.OE+04 Cr 4.OE+02 2.OE+03 Mn 5.5E+02 4.OE+02 Fe 3.OE+03 2.OE+04 Co 1.OE+02 i.OE+03 Ni 1.OE+02 2.5E+02 Cu 6.7E+02 1.7E+03 Zn 2.OE+03 5.OE+04 As 3.3E+02 3.3E+02 Br 1.5E-02 3.1E+00 Rb 8.3E+00 1.7E+01 Sr 2.OE+00 2.OE+01 Y 2.5E+01 1,OE+03 Zr 2.OE+02 8.OE+01 Nb 3.OE+04 1.OE+02 Mo 1.OE+01 1.OE+01 Tc 1.OE+01 5.OE+01 Ru 3.OE+00 1.OE+03 Rh 1.OE+01 2.OE+03 Ag 3.3E+03 3.3E+03 Sb 4.OE+01 5.4E+00 Te 1.OE+01 1.OE+02 I 1.OE+0I 5.OE+01 Cs 4.OE+01 2.5E+01 Ba 1.OE+01 1.OE+02 La 2.5E+01 1.OE+03 Ce 1.OE+01 6.OE+02 Pr 2.5E+01 1.OE+03 Nd 2.5E+01 1.OE+03 W 3.OE+01 3.OE+01 Np 1.OE+01 1.OE+01* Values in this table are taken from Regulatory Guide 1.109 except for phosphorus (fish) which is adapted from NUREG/CR-1336 and silver, arsenic and antimony which are taken from UCRL 50564, Rev. 1, October 1972.246 SALEM ODCM REV. 26 FIGURE 2-1: SALEM VENTILATION EXHAUST SYSTEMS AND EFFLUENT MONITOR INTERFACES Simplified One Line TO ATMOSPHERE 247 SALEM ODCM REV. 26 FIGURE 2-2: GASEOUS RADIOACTIVE WASTE DISPOSAL SYSTEM Simplified One Line 248 SALEM ODCM REV. 26 Table 2-1: Dose Factors For Noble Gases Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Ki Li Mi Ni Radionuclide AtCi/m3) LtCi/m3) 1tCi/m3) LtCi/m3)Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.O1E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131 m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.5 1E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe- 137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 I I I I I I I I I I I I I I I 249 SALEM ODCM REV. 26 Table 2-2.1: Parameters for Gaseous Alarm Setpoint Determinations

-Unit 1 Parameter Actual Default Units Comments Value Value X/Q calculated 2.2E-06 sec/m 3 USNRC Salem Safety Evaluation, Sup 3 VF as measured or (Plant Vent) fan curves 1.30E+05 ft 3/min Plant Vent -normal operation (Cont Purge) 3.50E+04 Containment Purge AF coordinated 0.25 N/A Administrative allocation factor with HCGS to ensure combined releases do not exceed release rate limit for site.Ci measured N/A [tCi/cm 3 Taken from gamma spectral analysis of gaseous effluent Ki nuclide specific N/A mrem/yr per Values from Table 2-1 pCi /m 3 Li nuclide specific N/A mrem/yr per Values from Table 2-1_tCi/mi 3 Mi nuclide specific N/A mrem/yr per Values from Table 2-1 pCi/m 3 Sensitivities as determined N/A cpm per Monitor sensitivities are 1 -R41 pCi/m 3 or controlled under Public 1-R12A cpm per Service Blueprint Document ptCi/cc (PSBP) 315733 Setpoint calculated N/A cpm or Monitor setpoints are 1-R41D tCi/sec controlled under Public 1-R12A** Service Blueprint Document (PSBP) 315733**Automatic Isolation function is applicable in all MODES except MODE 6 250 SALEM ODCM REV. 26 1 Table 2-2.2: Parameters for Gaseous Alarm Setpoint Determinations

-Unit 2 Parameter Actual Default Units Value Value Comments X/Q Calculated 2.2E-6 sec/m 3 USNRC Salem Safety Evaluation, Sup 3 VF as measured or Plant Vent fan curves 1.30E+05 ft 3/min Plant Vent -normal operation Cont. Purge 3.50E+04 Containment Purge AF Coordinated 0.25 N/A Administrative allocation factor with HCGS to ensure combined releases do not exceed release rate for site.C, Measured N/A ýtCi/cm 3 Taken from gamma spectral analysis of gaseous effluent K, Nuclide N/A mrem/yr per Values from Table 2-1 specific __Ci/m 3 Li Nuclide N/A mrem/yr per Values from Table 2-1 specific __Ci/m 3 M, Nuclide N/A mrem/yr per Values from Table 2-1 specific _tCi/m 3 Sensitivities as N/A cpm per Monitor sensitivities are 2-R41 determined pCi/m 3 or: controlled under Public Service 2-R12A cpm per Blueprint Document (PSBP)pLCi/cc 315734 Setpoint Calculated N/A cpm or Monitor setpoints are controlled 2-R41D pCi/sec under Public Service Blueprint 2-R12A ** Document (PSBP) 315734**Automatic Isolation function is applicable in all MODES except MODE 6 251 I I I I I I I I I I I I I I SALEM ODCM REV. 26 Table 2-3: Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations

Atmospheric Dispersion ODCM Location Pathway(s)

Controlling X/Q D/Q CONTROL Age Group (sec/m3) (1/m2)3.11.2.1 a site boundary (0.83 mile, N)3.11.2.1 b site boundary (0.83 mile, N), noble gases direct exposure Inhalation and ground plane gamma-air beta-air milk, ground plane and inhalation N/A child N/A infant 2.2E-06 2.2E-06 2.2E-06 5.4E-08 N/A N/A N/A 2.1E-10 3.11.2.2 3.11.2.3 site boundary (0.83 mile, N)residence/dairy**

(4.9 miles, W)* The identified controlling locations, pathways and atmospheric dispersion are from Evaluation Report, Supplement No. 3 for the Salem Nuclear Generating Station, Unit 2 0517, December 1978).the Safety (NUREG-** Location and distance are determined from the performance of the annual land use census as required by ODCM CONTROL 3.12.2.252 SALEM ODCM REV. 26 Table 2-4: Pathway Dose Factors -Atmospheric Releases R(io), Inhalation Pathway Dose Factors -ADULT (mrem/yr per p.Ci/m3)H-3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 P-32 1.32E+6 7.71E+4 --8.64E+4 5.OlE+4 Cr-51 -5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.OOE+2 Mn-54 3.96E+4 -9.84E+3 1.40E+6 7.74E+4 6.30E+3 Fe-55 2.46E+4 1.70E+4 -7.21E+4 6.03E+3 3.94E+3 Fe-59 1.18E+4 2.78E+4 --1.02E+6 1.88E+5 1.06E+4 Co-57 6.92E+2 --3.70E+5 3.14E+4 6.71E+2 Co-58 1.58E+3 --9.28E+5 1.06E+5 2.07E+3 Co-60 1.15E+4 --5.97E+6 2.85E+5 1.48E+4 Ni-63 4.32E+5 3.14E+4 --1.78E+5 1.34E+4 1.45E+4 Zn-65 3.24E+4 1.03E+5 -6.90E+4 8.64E+5 5.34E+4 4.66E+4 Rb-86 1.35E+5 --1.66E+4 5.90E+4 Sr-89 3.04E+5 ---1.40E+6 3.50E+5 8.72E+3 Sr-90 9.92E+7 ---9.60E+6 7.22E+5 6.1OE+6 Y-91 4.62E+5 ---1.70E+6 3.85E+5 1.24E+4 Zr-95 1.07E+5 3.44E+4 -5.42E+4 1.77E+6 1.50E+5 2.33E+4 Nb-95 1.41E+4 7.82E+3 -7.74E+3 5.05E+5 1.04E+5 4.2 1E+3 Ru-103 1.53E+3 --5.83E+3 5.05E+5 1.1OE+5 6.58E+2 Ru-106 6.91E+4 --1.34E+5 9.36E+6 9.12E+5 8.72E+3 Ag-i10m 1.08E+4 1.OOE+4 -1.97E+4 4.63E+6 3.02E+5 5.94E+3 Sb-124 3.12E+4 5.89E+2 7.55E+1 -2.48E+6 4.06E+5 1.24E+4 Sb-125 5.34E+4 5.95E+2 5.40E+1 -1.74E+6 1.01E+5 1.26E+4 Te-125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E+5 1.57E+3 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 1.58E+3 1-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 -6.28E+3 2.05E+4 1-132 1.16E+3 3.26E+3 1.14E+5 5.18E+3 -4.06E+2 1.16E+3 1-133 8.64E+3 1.48E+4 2.15E+6 2.58E+4 -8.88E+3 4.52E+3 1-134 6.44E+2 1.73E+3 2.98E+4 2.75E+3 -1.O1E+O 6.15E+2 1-135 2.68E+3 6.98E+3 4.48E+5 1.11E+4 -5.25E+3 2.57E+3 Cs-134 3.73E+5 8.48E+5 -2.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-136 3.90E+4 1.46E+5 -8.56E+4 1.20E+4 1.17E+4 1.1OE+5 Cs-137 4.78E+5 6.21E+5 -2.22E+5 7.52E+4 8.40E+3 4.28E+5 Ba-140 3.90E+4 4.90E+1 -1.67E+1 1.27E+6 2.18E+5 2.57E+3 Ce-141 1.99E+4 1.35E+4 -6.26E+3 3.62E+5 1.20E+5 1.53E+3 Ce-144 3.43E+6 1.43E+6 -8.48E+5 7.78E+6 8.16E+5 1.84E+5 Pr- 143 9.36E+3 3.75E+3 -2.16E+3 2.81E+5 2.OOE+5 4.64E+2 Nd-147 5.27E+3 6.1OE+3 -3.56E+3 2.21E+5 1.73E+5 3.65E+2 I I I I I I I I I U I I I I I U I I 253 I SALEM ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Inhalation Pathway Dose Factors -TEENAGER (mrem/yr per piCi/m3)H-3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 P-32 1.89E+6 1.1OE+5 --9.28E+4 7.16E+4 Cr-51 -7.50E+1 3.07E+1 2.1OE+4 3.OOE+3 1.35E+2 Mn-54 -5.11E+4 -1.27E+4 1.98E+6 6.68E+4 8.40E+3 Fe-55 3.34E+4 2.38E+4 --1.24E+5 6.39E+3 5.54E+3 Fe-59 1.59E+4 3.70E+4 --1.53E+6 1.78E+5 1.43E+4 Co-57 -6.92E+2 --5.86E+5 3.14E+/-4 9.20E+2 Co-58 2.07E+3 --1.34E+6 9.52E+4 2.78E+3 Co-60 -1.51E+4 --8.72E+6 2.59E+/-5 1.98E+4 Ni-63 5.80E+5 4.34E+4 --3.07E+5 1.42E+4 1.98E+4 Zn-65 3.86E+4 1.34E+5 -8.64E+4 1.24E+6 4.66E+4 6.24E+4 Rb-86 -1.90E+5 --1.77E+4 8.40E+4 Sr-89 4.34E+5 -2.42E+6 3.71E+5 1.25E+4 Sr-90 1.08E+8 -1.65E+7 7.65E+5 6.68E+6 Y-91 6.61E+5 --2.94E+6 4.09E+5 1.77E+4 Zr-95 1.46E+5 4.58E+4 -6.74E+4 2.69E+6 1.49E+5 3.15E+4 Nb-95 1.86E+4 1.03E+4 -1.OOE+4 7.5 1E+5 9.68E+4 5.66E+3 Ru-103 2.1OE+3 --7.43E+3 7.83E+5 1.09E+5 8.96E+2 Ru-106 9.84E+4 --1.90E+5 1.61E+7 9.60E+5 1.24E+4 Ag-1Orn 1.38E+4 1.31E+4 -2.50E+4 6.75E+6 2.73E+5 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 -3.85E+6 3.98E+5 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 -2.74E+6 9.92E+4 1.72E+4 Te-125m 4.88E+3 2.24E+3 1.40E+3 -5.36E+5 7.50E+4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2.25E+3 1-131 3.54E+4 4.91E+4 1.46E+7 8.40E+4 -6.49E+3 2.64E+4 1-132 1.59E+3 4.38E+3 1.51E+5 6.92E+3 -1.27E+3 1.58E+3 1-133 1.22E+4 2.05E+4 2.92E+6 3.59E+4 -1.03E+4 6.22E+3 1-134 8.88E+2 2.32E+3 3.95E+4 3.66E+3 -2.04E+1 8.40E+2 1-135 3.70E+3 9.44E+3 6.21E+5 1.49E+4 -6.95E+3 3.49E+3 Cs-134 5.02E+5 1.13E+6 -3.75E+5 1.46E+5 9.76E+3 5.49E+5 Cs-136 5.15E+4 1.94E+5 -1.1OE+5 1.78E+4 1.09E+4 1.37E+5 Cs-137 6.70E+5 8.48E+5 -3.04E+5 1.21E+5 8.48E+3 3.11E+5 Ba-140 5.47E+4 6.70E+1 -2.28E+1 2.03E+6 2.29E+5 3.52E+3 Ce-141 2.84E+4 1.90E+4 -8.88E+3 6.14E+5 1.26E+5 2.17E+3 Ce-144 4.89E+6 2.02E+6 -1.21E+6 1.34E+7 8.64E+5 2.62E+5 Pr-143 1.34E+4 5.31E+3 -3.09E+3 4.83E+5 2.14E+5 6.62E+2 Nd-147 7.86E+3 8.56E+3 -5.02E+3 3.72E+5 1.82E+5 5.13E+2 254 SALEM ODCM REV. 26 1 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Inhalation Pathway Dose Factors -CHILD (mrem/yr per gtCi/m3)H-3 -1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 P-32 2.60E+6 1.14E+5 -4.22E+4 9.88E+4 Cr-51 8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Mn-54 4.29E+4 -1.OOE+4 1.58E+6 2.29E+4 9.51E+3 Fe-55 4.74E+4 2.52E+4 --1.11E+5 2.87E+3 7.77E+3 Fe-59 2.07E+4 3.34E+4 --1.27E+6 7.07E+4 1.67E+4 Co-57 9.03E+2 --5.07E+5 1.32E+4 1.07E+3 Co-58 1.77E+3 --1.11E+6 3.44E+4 3.16E+3 Co-60 1.31E+4 --7.07E+6 9.62E+4 2.26E+4 Ni-63 8.21E+5 4.63E+4 --2.75E+5 6.33E+3 2.80E+4 Zn-65 4.26E+4 1.13E+5 -7.14E+4 9.95E+5 1.63E+4 7.03E+4 Rb-86 1.98E+5 -7.99E+3 1.14E+5 Sr-89 5.99E+5 -2.16E+6 1.67E+5 1.72E+4 Sr-90 1.01E+8 -1.48E+7 3.43E+5 6.44E+6 Y-91 9.14E+5 --2.63E+6 1.84E+5 2.44E+4 Zr-95 1.90E+5 4.18E+4 -5.96E+4 2.23E+6 6.11E+4 3.70E+4 Nb-95 2.35E+4 9.18E+3 -8.62E+3 6.14E+5 3.70E+4 6.55E+3 Ru-103 2.79E+3 --7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-106 1.36E+5 --1.84E+5 1.43E+7 4.29E+5 1.69E+4 Ag-110m 1.69E+4 1.14E+4 -2.12E+4 5.48E+6 1.OOE+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 -3.24E+6 1.64E+5 2.OOE+4 Sb-125 9.84E+4 7.59E+2 9.1OE+l -2.32E+6 4.03E+4 2.07E+4 Te-125m 6.73E+3 2.33E+3 1.92E+3 -4.77E+5 3.38E+4 9.14E+2 Te-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1.48E+6 7.14E+4 3.02E+3 Te-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4 1.76E+6 1.82E+5 3.04E+3 1-131 4.81E+4 4.81E+4 1.62E+7 7.88E+4 -2.84E+3 2.73E+4 1-132 2.12E+3 4.07E+3 1.94E+5 6.25E+3 -3.22E+3 1.88E+3 1-133 1.66E+4 2.03E+4 3.85E+6 3.38E+4 -5.48E+3 7.70E+3 1-134 1.17E+3 2.16E+3 5.07E+4 3.30E+3 -9.55E+2 9.95E+2 1-135 4.92E+3 8.73E+3 7.92E+5 1.34E+4 -4.44E+3 4.14E+3 Cs-134 6.51E+5 1.01E+6 -3.30E+5 1.21E+5 3.85E+3 2.25E+5 Cs-136 6.51E+4 1.71E+5 -9.55E+4 1.45E+4 4.18E+3 1.16E+5 Cs-137 9.07E+5 8.25E+5 -2.82E+5 1.04E+5 3.62E+3 1.28E+5 Ba-140 7.40E+4 6.48E+1 -2.1 1E+1 1.74E+6 1.02E+5 4.33E+3 Ce-141 3.92E+4 1.95E+4 -8.55E+3 5.44E+5 5.66E+4 2.90E+3 Ce-144 6.77E+6 2.12E+6 -1.17E+6 1.20E+7 3.89E+5 3.61E+5 Pr-143 1.85E+4 5.55E+3 -3.OOE+3 4.33E+5 9.73E+4 9.14E+2 Nd-147 1.08E+4 8.73E+3 -4.81E+3 3.28E+5 8.21E+4 6.81E+2 I I I I I I I I I I I I I I I I I I 255 SALEM ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Inhalation Pathway Dose Factors -INFANT (mrem/yr per itCi/m3)1lIIIi. Bone Liver Tyi Kny uIII llBody H-3 -6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 P-32 2.03E+6 1.12E+5 ---1.61E+4 7.74E+4 Cr-51 -5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.95E+1 Mn-54 -2.53E+4 -4.98E+3 I.OOE+6 7.06E+3 4.98E+3 Fe-55 1.97E+4 1.17E+4 -8.69E+4 1.09E+3 3.33E+3 Fe-59 1.36E+4 2.35E+4 -1.02E+6 2.48E+4 9.48E+3 Co-57 -6.51E+2 -3.79E+5 4.86E+3 6.41E+2 Co-58 1.22E+3 -7.77E+5 1.11E+4 1.82E+3 Co-60 -8.02E+3 -4.51E+6 3.19E+4 1.18E+4 Ni-63 3.39E+5 2.04E+4 -2.09E+5 2.42E+3 1.16E+4 Zn-65 1.93E+4 6.26E+4 -3.25E+4 6.47E+5 5.14E+4 3.11E+4 Rb-86 -1.90E+5 -- -3.04E+3 8.82E+4 Sr-89 3.98E+5 --2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 --1.12E+7 1.31E+5 2.59E+6 Y-91 5.88E+5 ---2.45E+6 7.03E+4 1.57E+4 Zr-95 1.15E+5 2.79E+4 -3.11E+4 1.75E+6 2.17E+4 2.03E+4 Nb-95 1.57E+4 6.43E+3 -4.72E+3 4.79E+5 1.27E+4 3.78E+3 Ru-103 2.02E+3 -4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-106 8.68E+4 -1.07E+5 1.16E+7 1.64E+5 1.09E+4 Ag-110m 9.98E+3 7.22E+3 -1.09E+4 3.67E+6 3.30E+4 5.OOE+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 -2.65E+6 5.91E+4 1.20E+4 Sb- 125 5.17E+4 4.77E+2 6.23E+1 -1.64E+6 1.47E+4 1.09E+4 Te-125m 4.76E+3 1.99E+3 1.62E+3 -4.47E+5 1.29E+4 6.58E+2 Te-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 Te-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+3 1-131 3.79E+4 4.44E+4 1.48E+7 5.18E+4 -1.06E+3 1.96E+4 1-132 1.69E+3 3.54E+3 1.69E+5 3.95E+5 -1.90E+3 1.26E+3 1-133 1.32E+4 1.92E+4 3.56E+6 2.24E+4 2.61E+3 5.60E+3 1-134 9.21E+2 1.88E+3 4.45E+4 2.09E+3 -1.29E+3 6.65E+2 1-135 3.86E+3 7.60E+3 6.96E+5 8.47E+3 -1.83E+3 2.77E+3 Cs-134 3.96E+5 7.03E+5 -1.90E+5 7.97E+4 1.33E+3 7.45E+4 Cs-136 4.83E+4 1.35E+5 -5.64E+4 1.18E+4 1.43E+3 5.29E+4 Cs-137 5.49E+5 6.12E+5 -1.72E+5 7.13E+4 1.33E+3 4.55E+4 Ba-140 5.60E+4 5.60E+1 -1.34E+1 1.60E+6 3.84E+4 2.90E+3 Ce-141 2.77E+4 1.67E+4 -5.25E+3 5.17E+5 2.16E+4 1.99E+3 Ce-144 3.19E+6 1.21E+6 -5.38E+5 9.84E+6 1.48E+5 1.76E+5 Pr-143 1.40E+4 5.24E+3 -1.97E+3 4.33E+5 3.72E+4 6.99E+2 Nd-147 7.94E+3 8.13E+3 -3.15E+3 3.22E+5 3.12E+/-4 5.OOE+2 256 SALEM ODCM REV. 26 1 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors -ADULT (mrem/yr per pCi/m3) for H-3 and C-14 (m2

mrem/yr per pCi/sec) for others H-3 -7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 P-32 1.71E+10 1.06E+9 -1.92E+9 6.60E+8 Cr-51 --1.71E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Mn-54 -8.40E+6 2.50E+6 -2.57E+7 1.60E+6 Fe-55 2.51E+7 1.73E+7 9.67E+6 9.95E+6 4.04E+6 Fe-59 2.98E+7 7.OOE+7 1.95E+7 2.33E+8 2.68E+7 Co-57 -1.28E+6 -3.25E+7 2.13E+6 Co-58 -4.72E+6 -9.57E+7 1.06E+7 Co-60 -1.64E+7 -3.08E+8 3.62E+7 Ni-63 6.73E+9 4.66E+8 -9.73E+7 2.26E+8 Zn-65 1.37E+9 4.36E+9 2.92E+9 -2.75E+9 1.97E+9 Rb-86 -2.59E+9 -5.11E+8 1.21E+9 Sr-89 1.45E+9 -2.33E+8 4.16E+7 Sr-90 4.68E+10_

1.35E+9 1.15E+10 Y-91 8.60E+3 -4.73E+6 2.30E+2 Zr-95 9.46E+2 3.03E+2 -4.76E+2 -9.62E+5 2.05E+2 Nb-95 8.25E+4 4.59E+4 -4.54E+4 -2.79E+8 2.47E+4 Ru-103 1.02E+3 -3.89E+3 -1.19E+5 4.39E+2 Ru-106 2.04E+4 -3.94E+4 -1.32E+6 2.58E+3 Ag-i 10m 5.83E+7 5.39E+7 -1.06E+8 -2.20E+10 3.20E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 2.OOE+7 7.31E+8 1.02E+7 Sb-125 2.04E+7 2.28E+5 2.08E+4 1.58E+7 2.25E+8 4.86E+6 Te-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 -6.50E+7 2.18E+6 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 -1.54E+8 5.58E+6 Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 -3.04E+8 9.57E+6 1-131 2.96E+8 4.24E+/-8 1.39E+11 7.27E+8 -1.12E+8 2.43E+8 1-132 1.64E-1 4.37E-1 1.53E+1 6.97E-1 -8.22E-2 1.53E-1 1-133 3.97E+6 6.90E+6 1.O1E+9 1.20E+7 -6.20E+6 2.1OE+6 1-134 .- 135 1.39E+4 3.63E+4 2.40E+6 5.83E+4 -4.1OE+4 1.34E+4 Cs-134 5.65E+9 1.34E+10 -4.35E+9 1.44E+9 2.35E+8 1.10E+10 Cs-136 2.61E+8 1.03E+9 -5.74E+8 7.87E+7 1.17E+8 7.42E+8 Cs-137 7.38E+9 1.01E+10 -3.43E+9 1.14E+9 1.95E+8 6.61E+9 Ba-140 2.69E+7 3.38E+4 -1.15E+4 1.93E+4 5.54E+7 1.76E+6 Ce-141 4.84E+3 3.27E+3 -1.52E+3 1.25E+7 3.71E+2 Ce-144 3.58E+5 1.50E+5 -8.87E+4 1.21E+8 1.92E+4 Pr-143 1.59E{2 6.37E+1 -3.68E+1 6.96E+5 7.88E+O Nd-147 9.42E+1 1.09E+2 -6.37E+1 5.23E+5 6.52E+O I I I I I I I I I I I I I I I I I 257 I SALEM ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors -TEENAGER (mrem/yr per /Ci/m3) for H-3 and C-14 (m2

mrem/yr per [tCi/sec) for others H-3 -9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 P-32 3.15E+10 1.95E+9 2.65E+9 1.22E+9 Cr-51 --2.78E+4 1.1OE+4 7.13E+4 8.40E+6 5.OOE+4 Mn-54 -1.40E+7 4.17E+6 2.87E+7 2.78E+6 Fe-55 4.45E+7 3.16E+7 2.OOE+7 1.37E+7 7.36E+6 Fe-59 5.20E+7 1.21E+8 3.82E+7 2.87E+8 4.68E+7 Co-57 -2.25E+6 4.19E+7 3.76E+6 Co-58 7.95E+6 -1.1OE+8 1.83E+7 Co-60 -2.78E+7 -3.62E+8 6.26E+7 Ni-63 1.18E+10 8.35E+8 -1.33E+8 4.01E+8 Zn-65 2.11E+9 7.31E+9 -4.68E+9 3.1OE+9 3.41E+9 Rb-86 -4.73E+9 -7.OOE+8 2.22E+9 Sr-89 2.67E+9 3.18E+8 7.66E+7 Sr-90 9.92E+7 9.60E+6 7.22E+5 6.1OE+6 Y-91 1.58E+4 -6.48E+6 4.24E+2 Zr-95 1.65E+3 5.22E+2 7.67E+2 -1.20E+6 3.59E+2 Nb-95 1.41E+5 7.80E+4 7.57E+4 -3.34E+8 4.30E+4 Ru-103 1.81E+3 6.40E+3 -1.52E+5 7.75E+2 Ru-106 3.75E+4 -7.23E+4 -1.80E+6 4.73E+3 Ag-ll0m 9.63E+7 9.11E+7 1.74E+8 -2.56E+10 5.54E+7 Sb-124 4.59E+7 8.46E+5 1.04E+5 4.01E+7 9.25E+8 1.79E+7 Sb-125 3.65E+7 3.99E+5 3.49E+4 3.21E+7 2.84E+8 8.54E+6 Te-125m 3.OOE+7 1.08E+7 8.39E+6 -8.86E+7 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 -2.1OE+8 1.OOE+7 Te-129m 1.11E+8 4.1OE+7 3.57E+7 4.62E+8 -4.15E+8 1.75E+7 1-131 5.38E+8 7.53E+8 2.20E+ 11 1.30E+9 -1.49E+8 4.04E+8 1-132 2.90E-1 7.59E-1 2.56E+1 1.20E+O -3.31E-1 2.72E-1 1-133 7.24E+6 1.23E+7 1.72E+9 2.15E+7 -9.30E+6 3.75E+6 1-134 ....1-135 2.47E+4 6.35E+4 4.08E+6 1.OOE+5 7.03E+4 2.35E+4 Cs-' 134 9.81E+9 2.31E+10 -7.34E+9 2.80E+9 2.87E+8 1.07E+10 Cs-136 4.45E+8 1.75E+9 -9.53E+8 1.50E+8 1.41E+8 1.18E+9 Cs-137 1.34E+10 1.78E+10 -6.06E+9 2.35E+9 2.53E+8 6.20E+9 Ba-140 4.85E+7 5.95E+4 -2.02E+4 4.OOE+4 7.49E+7 3.13E+6 Ce-141 8.87E+3 1.35E+4 -2.79E+3 1.69E+7 6.81E+2 Ce-144 6.58E+5 2.72E+5 -1.63E+5 1.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 -6.77E+1 9.61E+5 1.45E+l Nd-147 1.81E+2 1.97E+2 -1.16E+2 7.11E+5 1.18E+l 258 SALEM ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors -CHILD (mrem/yr per ýtCi/m3) for H-3 and C-14 (m2

mrem/yr per [tCi/sec) for others Nucid Bon Lie muri iny ug GL1 J~H-3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 P-32 7.77E+10 3.64E+9 -2.15E+9 3.OOE+9 Cr-51 --5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 Mn-54 -2.09E+7 5.87E+6 -1.76E+7 5.58E+6 Fe-55 1.12E+8 5.93E+7 -3.35E+7 1.1OE+7 1.84E+7 Fe-59 1.20E+8 1.95E+8 -.5.65E+7 2.03E+8 9.71E+7 Co-57 3.84E+6 -3.14E+7 7.77E+6 Co-58 1.21E+7 --7.08E+7 3.72E+7 Co-60 4.32E+7 --2.39E+8 1.27E+8 Ni-63 2.96E+10 1.59E+9 --1.07E+8 1.OlE+9 Zn-65 4.13E+9 1.1OE+10 -6.94E+9 -1.93E+9 6.85E+9 Rb-86 8.77E+9 --5.64E+8 5.39E+9 Sr-89 6.62E+9 --2.56E+8 1.89E+8 Sr-90 1.12E+ 11 --1.51E+9 2.83E+/-10 Y-91 3.91E+4 ---5.21E+6 1.04E+3 Zr-95 3.84E+3 8.45E+2 -1.21E+3 -8.81E+5 7.52E+2 Nb-95 3.18E+5 1.24E+5 -1.16E+5 -2.29E+8 8.84E+4 Ru-103 4.29E+3 --1.08E+4 -1.11E+5 1.65E+3 Ru-106 9.24E+4 --1.25E+5 -1.44E+6 1.15E+4 Ag-110m 2.09E+8 1.41E+8 -2.63E+8 -1.68E+10 1.13E+8 Sb-124 1.09E+8 1.41E+8 2.40E+5 -6.03E+7 6.79E+8 3.81E+7 Sb-125 8.70E+7 1.41E+6 8.06E+4 -4.85E+7 2.08E+8 1.82E+7 Te-125m 7.38E+7 2.OOE+7 2.07E+7 --7.12E+7 9.84E+6 Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 -1.68E+8 2.47E+7 Te-129m 2.72E+8 7.61E+7 8.78E+7 8.OOE+8 -3.32E+8 4.23E+7 1-131 1.30E+9 1.31E+9 4.34E+1l 2.15E+9 -1.17E+8 7.46E+8 1-132 6.86E-1 1.26E+O 5.85E+1 1.93E+O -1.48E+O 5.80E-1 1-133 1.76E+7 2.18E+7 4.04E+9 3.63E+7 -8.77E+6 8.23E+6 1-134 --1-135 5.84E+4 1.05E+5 9.30E+6 1.61E+5 8.OOE+4 4.97E+4 Cs-134 2.26E+10 3.71E+10 -1.15E+10 4.13E+9 2.OOE+8 7.83E+9 Cs-136 l.OOE+9 2.76E+9 -1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs-137 3.22E+10 3.09E+10 -1.01E+10 3.62E+9 1.93E+8 4.55E+9 Ba-140 1.17E+8 1.03E+5 -3.34E+4 6.12E+4 5.94E+7 6.84E+6 Ce-141 2.19E+4 1.09E+4 -4.78E+3 -1.36E+7 1.62E+3 Ce-144 1.62E+6 5.09E+5 -2.82E+5 -1.33E+8 8.66E+4 Pr-143 7.23E+2 2.17E+2 -1.17E+2 -7.80E+5 3.59E+1 Nd-147 4.45E+2 3.60E+2 -1.98E+2 5.71E+5 2.79E+1 I I I I I I I I I I I I I I I I I 259 SALEM ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors -INFANT (mrem/yr per jtCi/m3) for H-3 and C-14 (m2

mrem/yr per pCi/sec) for others Nide nL.iv I r Kidne Lung G -I S .Bo'H-3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 P-32 1.60E+ll 9.42E+9 -2.17E+9 6.21E+9 Cr-51 1.05E+5 2.30E+4 2.05E+5 4.71E+6 1.61E+5 Mn-54 3.89E+7 -8.63E+6 -1.43E+7 8.83E+6 Fe-55 1.35E+8 8.72E+7 -4.27E+7 1.11E+7 2.33E+7 Fe-59 2.25E+8 3.93E+8 -- 1.16E+8 1.88E+8 1.55E+8 Co-57 8.95E+6 --3.05E+7 1.46E+7 Co-58 2.43E+7 ---6.05E+/-7 6.06E+7 Co-60 8.81E+7 ---2.1OE+8 2.08E+8 Ni-63 3.49E+10 2.16E+9 ---1.07E+8 1.21E+9 Zn-65 5.55E+9 1.90E+10 -9.23E+9 -1.61E+10 8.78E+9 Rb-86 2.22E+10 ---5.69E+8 1.1OE+10 Sr-89 1.26E+10 ---2.59E+8 3.61E+8 Sr-90 1.22E+11 --1.52E+9 3.10E+10 Y-91 7.33E+4 ---5.26E+6 1.95E+3 Zr-95 6.83E+3 1.66E+3 -1.79E+3 -8.28E+5 1.18E+3 Nb-95 5.93E+5 2.44E+5 -1.75E+5 -2.06E+8 1.41E+5 Ru-103 8.69E+3 -1.81E+4 -1.06E+5 2.91E+3 Ru-106 1.90E+5 -2.25E+5 -1.44E+6 2.38E+4 Ag-ll0m 3.86E+8 2.82E+8 -4.03E+8 -1.46E+10 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E+5 -1.31E+8 6.46E+8 6.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 9.38E+7 1.99E+8 3.07E+7 Te-125m 1.51E+8 5.04E+7 5.07E+7 --7.18E+7 2.04E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 -1.70E+8 5.1OE+7 Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 -3.34E+8 8.62E+7 1-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 -1.15E+8 1.41E+9 1-132 1.42E+O 2.89E+O 1.35E+2 3.22E+O -2.34E+O 1.03E+O 1-133 3.72E+7 5.41E+7 9.84E+9 6.36E+7 -9.16E+6 1.58E+7 1-134 1.O0E-9 --1-135 1.21E+5 2.41E+5 2.16E+7 2.69E+5 8.74E+4 8.80E+4 Cs-134 3.65E+10 6.80E+10 1.75E+10 7.18E+9 1.85E+8 6.87E+9 Cs-136 1.96E+9 5.77E+9 2.30E+9 4.70E+/-8 8.76E+7 2.15E+9 Cs-137 5.15E+10 6.02E+10 -1.62E+10 6.55E+9 1.88E+8 4.27E+9 Ba-140 2.41E+8 2.41E+5 -5.73E+4 1.48E+5 5.92E+7 1.24E+7 Ce-141 4.33E+4 2.64E+4 -8.15E+3 -1.37E+7 3.11E+3 Ce-144 2.33E+6 9.52E+5 -3.85E+5 -1.33E+8 1.30E+5 Pr-143 1.49E+3 5.59E+2 -2.08E+2 -7.89E+5 7.41E+1 Nd-147 8.82E+2 9.06E+2 3.49E+2 -5.74E+5 5.55E+1 260 SALEM ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Vegetation Pathway Dose Factors -ADULT (mrem/yr per jiCi/m3) for H-3 and C-14 (m2

mrem/yr per gaCi/sec) for others H-3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 P-32 1.40E+9 8.73E+7 -1.58E+8 5.42E+7 Cr-51 --2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 Mn-54 -3.11E+8 -9.27E+7 -9.54E+8 5.94E+7 Fe-55 2.09E+8 1.45E+8 --8.06E+7 8.29E+7 3.37E+7 Fe-59 1.27E+8 2.99E+8 --8.35E+7 9.96E+8 1.14E+8 Co-57 1.17E+7 --2.97E+8 1.95E+7 Co-58 3.09E+7 --6.26E+8 6.92E+7 Co-60 1- 1.67E+8 --3.14E+9 3.69E+8 Ni-63 1.04E+10 7.21E+8 --1.50E+8 3.49E+8 Zn-65 3.17E+8 l.O1E+9 -6.75E+8 6.36E+8 4.56E+8 Rb-86 -2.19E+8 -4.32E+7 1.02E+8 Sr-89 9.96E+9 --1.60E+9. 2.86E+8 Sr-90 6.05E+11 -1.75E+10 1.48E+10 Y-91 5.13E+6 --2.82E+9 1.37E+5 Zr-95 1.19E+6 3.81E+5 -5.97E+5 1.21E+9 2.58E+5 Nb-95 1.42E+5 7.91E+4 -7.81E+4 -4.80E+8 4.25E+4 Ru-103 4.80E+6 --1.83E+7 -5.61E+8 2.07E+6 Ru-106 1.93E+8 --3.72E+8 -1.25E+10 2.44E+7 Ag-110in 1-.06E+7 9.76E+6 -1.92E+7 -3.98E+9 5.80E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 8.08E+7 2.95E+9 4.11E+7 Sb-125 1.36E+8 1.52E+6 1.39E+5 1.05E+8 1.50E+9 3.25E+7 Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 -3.86E+8 1.29E+7 Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 -1.17E+9 4.26E+7 Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 -1.28E+9 4.03E+7 1-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 -3.05E+7 6.63E+7 1-132 5.74E+1 1.54E+2 5.38E+3 2.45E+2 -2.89E+1 5.38E+1 1-133 2.12E+6 3.69E+6 5.42E+8 6.44E+6 -3.31E+6 1.12E+6 1-134 1.06E-4 2.88E-4 5.OOE-3 4.59E-4 -2.51E-7 1.03E-4 1-135 4.08E+4 1.07E+5 7.04E+6 1.71E+5 -1.21E+5 3.94E+4 Cs-134 4.66E+9 1.11E+10 -3.59E+9 1.19E+9 1.94E+8 9.07E+9 Cs-136 4.20E+7 1.66E+8 -9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-137 6.36E+9 8.70E+9 -2.95E+9 9.81E+8 1.68E+8 5.70E+9 Ba-140 1.29E+8 1.62E+5 -5.49E+4 9.25E+4 2.65E+8 8.43E+6 Ce-141 1.96E+5 1.33E+5 -6.17E+4 -5.08E+8 1.51E+4 Ce-144 3.29E+7 1.38E+7 -8.16E+6 -1.11E+10 1.77E+6 Pr- 143 6.34E+4 2.54E+4 -1.47E+4 -2.78E+8 3.14E+3 Nd-147 3.34E+4 3.86E+4 -2.25E+4 -1.85E+8 2.3 1E+3 I I I I I I I I I I I I I I I I I 261 SALEM ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Vegetation Pathway Dose Factors -TEENAGER (mrem/yr per pCi/m3) for H-3 and C-14 (m2

mrem/yr per gtCi/sec) for others H-3 -2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 P-32 1.61E+9 9.96E+7 ---1.35E+8 6.23E+7 Cr-51 -3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Mn-54 -4.52E+8 -1.35E+8 -9.27E+8 8.97E+7 Fe-55 3.25E+8 2.31E+8 -1.46E+8 9.98E+7 5.38E+7 Fe-59 1.81E+8 4.22E+8 -1.33E+8 9.98E+8 1.63E+8 Co-57 -1.79E+7 --3.34E+8 3.OOE+7 Co-58 4.38E+7 --6.04E+8 1.01E+8 Co-60 -2.49E+8 --3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13E+9 --1.81E+8 5.45E+8 Zn-65 4.24E+8 1.47E+9 -9.41E+8 -6.23E+8 6.86E+8 Rb-86 -2.73E+8 --4.05E+7 1.28E+8 Sr-89 1.51E+10 --1.80E+9 4.33E+8 Sr-90 7.51E+11 --2.11E+10 1.85E+11 Y-91 7.87E+6 --3.23E+9 2.11E+5 Zr-95 1.74E+6 5.49E+5 -8.07E+5 -1.27E+9 3.78E+5 Nb-95 1.92E+5 1.06E+5 -1.03E+5 -4.55E+8 5.86E+4 Ru-103 6.87E+6 -2.42E+7 -5.74E+8 2.94E+6 Ru-106 3.09E+8 -5.97E+8 -1.48E+10 3.90E+7 Ag-110m 1.52E+7 1.44E+7 -2.74E+7 -4.04E+9 8.74E+6 Sb-124 1.55E+8 2.85E+6 3.51E+/-5 1.35E+8 3.11E+9 6.03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+5 1.88E+8 1.66E+9 5.OOE+7 Te-125m 1.48E+8 5.34E+7 4.14E+7 --4.37E+8 1.98E+7 Te-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 -1.37E+9 6.56E+7 Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 -1.38E+9 5;81E+7 1-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 -2.13E+7 5.79E+7 1-132 5.18E+1 1.36E+2 4.57E+3 2.14E+2 -5.91E+1 4.87E+1 1-133 1.97E+6 3.34E+6 4.66E+8 5.86E+6 -2.53E+6 1.02E+6 1-134 9.59E-5 2.54E-4 4.24E-3 4.01E-4 -3.35E-6 9.13E-5 1-135 3.68E+4 9.48E+4 6.1OE+6 1.50E+5 -1.05E+5 3.52E+4 Cs-134 7.09E+9 1.67E+10 -5.30E+9 2.02E+9 2.08E+8 7.74E+9 Cs-136 4.29E+7 1.69E+8 -9.19E+7 1.45E+7 1.36E+7 1.13E+8 Cs-137 1.01E+10 1.35E+10 -4.59E+9 1.78E+9 1.92E+8 4.69E+9 Ba-140 1.38E+8 1.69E+5 -5.75E+4 1.14E+5 2.13E+8 8.91E+6 Ce-141 2.82E+5 1.88E+5 -8.86E+4 -5.38E+8 2.16E+4 Ce-144 5.27E+7 2.18E+7 -1.30E+7 -1.33E+10 2.83E+6 Pr-143 7.12E+4 2.84E+4 -1.65E+4 -2.34E+8 3.55E+3 Nd-147 3.63E+4 3.94E+4 -2.32E+4 -1.42E+8 2.36E+3 262 SALEM ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Vegetation Pathway Dose Factors -CHILD (mrem/yr per ýtCi/m3) for H-3 and C-14 (m2

mrem/yr per gCi/sec) for others H-3 -4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.O1E+3 C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 P-32 3.37E+9 1.58E+8 --9.30E+7 1.30E+8 Cr-51 --6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 Mn-54 -6.61E+8 -1.85E+8 -5.55E+8 1.76E+8 Fe-55 8.OOE+8 4.24E+8 --2.40E+8 7.86E+7 1.31E+8 Fe-59 4.01E+8 6.49E+8 --1.88E+8 6.76E+8 3.23E+8 Co-57 -2.99E+7 --2.45E+8 6.04E+7 Co-58 -6.47E+7 --3.77E+8 1.98E+8 Co-60 -3.78E+8 --2.1OE+9 1.12E+9 Ni-63 3.95E+10 2.11E+9 1- -.42E+8 1.34E+9 Zn-65 8.12E+8 2.16E+9 1.36E+9 -3.80E+8 1.35E+9 Rb-86 -4.52E+8 --2.91E+7 2.78E+8 Sr-89 3.59E+10 ---1.39E+/-9 1.03E+9 Sr-90 1.24E+12 -- -1.67E+10 3.15E+11 Y-91 1.87E+7 ---2.49E+9 5.01E+5 Zr-95 3.90E+6 8.58E+5 -1.23E+6 -8.95E+8 7.64E+5 Nb-95 4.1OE+5 1.59E+5 -1.50E+5 -2.95E+8 1.14E+5 Ru-103 1.55E+7 -3.89E+7 -3.99E+8 5.94E+6 Ru-106 7.45E+8 -1.01E+9 -1.16E+10' 9.30E+7 Ag-110m 3.22E+7 2.17E+7 -4.05E+7 -2.58E+9 1.74E+7 Sb-124 3.52E+8 4.57E+6 7.78E+5 -1.96E+8 2.20E+9 1.23E+8 Sb-125 4.99E+8 3.85E+6 4.62E+5 -2.78E+8 1.19E+9 1.05E+8 Te-125m 3.5 1E+8 9.50E+7 9.84E+7 --3.38E+8 4.67E+7 Te-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 -1.07E+9 1.57E+8 Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 -1.04E+9 1.33E+8 1-131 1.43E+8 1.44E+8 4.76E+10 2.36E+8 -1.28E+7 8.18E+7 1-132 9.20E+1 1.69E+2 7.84E+3 2.59E+2 -1.99E+2 7.77E+1 1-133 3.59E+6 4.44E+6 8.25E+8 7.40E+6 -1.79E+6 1.68E+6 1-134 1.70E-4 3.16E-4 7.28E-3 4.84E-4 -2.1OE-4 1.46E-4 1-135 6.54E+4 1.18E+5 1.04E+7 1.81E+5 -8.98E+4 5.57E+4 Cs-134 1.60E+10 2.63E+10 -8.14E+9 2.92E+9 1.42E+8 5.54E+9 Cs-136 8.06E+7 2.22E+8 -1.18E+8 1.76E+7 7.79E+6 1.43E+8 Cs-137 2.39E+10 2.29E+10 -7.46E+9 2.68E+9 1.43E+8 3.38E+9 Ba-140 2.77E+8 2.43E+5 -7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ce-141 6.35E+5 3.26E+5 -1.43E+5 -4.07E+8 4.84E+4 Ce-144 1.27E+8 3.98E+7 -2.21E+7 -1.04E+10 6.78E+6 Pr-143 1.48E+5 4.46E+4 -2.41E+4 -1.60E+8 7.37E+3 Nd- 147 7.16E+4 5.80E+4 -3.18E+4 -9.18E+7 4.49E+3 I I I I I I I I I I I I I I I I I 263 SALEM ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Ground Plane Pathway Dose Factors (m2

mrem/yr per gCi/sec)Nuclide Any Organ H-3 C-14 P-32 Cr-51 4.68E+6 Mn-54 1.34E+9 Fe-55 Fe-59 2.75E+8 Co-58 3.82E+8 Co-60 2.16E+10 Ni-63 Zn-65 7.45E+8 Rb-86 8.98E+6 Sr-89 2.16E+4 Sr-90 Y-91 1.08E+6 Zr-95 2.48E+8 Nb-95 1.36E+8 Ru- 103 1.09E+8 Ru-106 4.21E+8 Ag-i 10m 3.47E+9 Te-125m 1.55E+6 Te-127m 9.17E+4 Te-129m 2.OOE+7 1-131 1.72E+7 1-132 1.24E+6 1-133 2.47E+6 1-134 4.49E+5 1-135 2.56E+6 Cs-134 6.75E+9 Cs-136 1.49E+8 Cs-137 1.04E+10 Ba-140 2.05E+7 Ce-141 1.36E+7 Ce-144 6.95E+7 Pr- 143 Nd-147 8.40E+6 264 Salem ODCM Rev. 26 APPENDIX A Evaluation of Default Parameters for Liquid Effluents I I U I I I U I I U I.I I I I I I I U 265 Salem ODCM Rev. 26 APPENDIX A: Evaluation of Default Parameters for Liquid Effluents A. Effective Maximum Permissible Concentration (MPCe)In accordance with the requirements of ODCM CONTROL 3.3.3.8 the radioactive liquid effluent monitors shall be operable with alarm setpoints established to *ensure that the concentration of radioactive material at the discharge point does not exceed the MPC value of 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F). The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual radionuclide distribution and corresponding MPC values.In order to limit the need for routinely having to reestablish the alarm setpoints as a function of changing radionuclide distributions, a default alarm setpoint can be established.

This default setpoint can be based on an evaluation of the radionuclide distribution of the liquid effluents from Salem and the effective MPC value for this distribution.

The effective MPC Value for a radionuclide distribution is calculated by the equation: YCi (gamma)MPCG i I -(gamma)where: MPCe = an effective MPC value for a mixture of gamma emitting radionuclides (gCi/ml)Ci = concentration of radionuclide i in the mixture MPCi = the 10 CFR 20, Appendix B, Table II, Column 2 MPC value for radionuclide i (Appendix F) (pCi/ml)The equation for determining the liquid effluent setpoints (Section 1.2.1, equation 1.2) is based on a multiplication of the effective MPC times the monitor sensitivity.

Considering the average effective MPC value for the years 1993, 1994, and 1998, it is reasonable to select an MPCe value of 6.05E-06 jtCi/ml for Unit 1 and 4.8 1E-06 p[Ci/ml for Unit 2 as typical of liquid radwaste discharges.

266 Salem ODCM Rev. 26 B. Correction Factor The type of radiation detector used to monitor radioactive releases is not capable of detecting non-gamma emitting radionuclides such as H-3, Fe-55, and Sr-89, 90, as required by ODCM CONTROL 3.11.1.1.

A conservative default safety factor can be determined to account for non-gamma emitting radionuclides.

Non-gamma emitting radionuclides are analyzed at Salem station on a monthly basis from a composite sample of liquid releases.Nuclide MPC (tiCi/ml)

Activity (pCi/ml) Activity / MPC H-3 3E-3 5.2E-1 173.3 Fe-55 8E-4. 2.5E-3 3.1 Sr-89 3E-61 2.OE-5 6.7 Sr-90 3E-7 7.2E-7 2.4 Total 185.5 The values in the table above represent the maximum reactor coolant values for non-gamma emitting nuclides in 1994 for Unit 1 and 2. Reactor coolant values were chosen to represent the maximum concentration of non-gamma emitting nuclides that could be released from Salem Station. The activity values in the table will be diluted by a minimum factor of 800 prior to release. The minimum dilution factor is obtained by using the minimum circulating water flowrate of 100,000 gpm and the maximum release rate of 120 gpm.A conservative non-gamma factor for non-gamma emitting nuclides can be obtained using the highest Activity/MPC fraction and the minimum dilution factor as follows: I I I I I I U I I I I I I I U I I U I Non-Gamma Factor -Correction Factor =185.5/800 0.25 =0.23 (Rounded up to 0.25)0.75 C. Default setpoint determination:

Using the information and parameters described above a default setpoint can be calculated for Unit 1 and 2 liquid radwaste disposal process radiation monitors (R18).Using these values to calculate the default R18 alarm setpoint value, results in a setpoint that: 1) Will not require frequent re-adjustment due to minor variations in the nuclide distribution which are typical of routine plant operations, and 2) Will provide for a liquid radwaste discharge rate (as evaluated for each batch release) that is compatible with plant operations (refer to Tables 1-1.1 and 1-1.2).267 Salem ODCM Rev. 26 Table A-i: Calculation of Effective MPC -Unit 1 Nuclide BE-7 NA-24 CR-51 MN-54 MN-56 FE-59 CO-57 CO-58 CO-60 ZR-95 NB-95 NB-97 TC-99M SR-89 SR-92 MO-99 AG-110m SN-113 SB-122 SB-124 SB-125 SB-126 1-131 1-133 1-134 CE-141 CE-143 CS-134 CS-136 CS-137 CS-138 BA-140 LA-140 RU-105 RU-106 ZN-65 Total Ci MPCe MPC*(RCi/ml)2.OOE-03 3.OOE-05 2.OOE-03 1.OOE-04 1.OOE-04 5.OOE-05 4.OOE-04 9.OOE-05 3.OOE-05 6.OOE-05 1.OOE-04 9.OOE-04 3.OOE-03 3.OOE-06 6.OOE-05 4.OOE-05 3.OOE-05 8.OOE-05 3.OOE-05 2.OOE-05 1.OOE-04 3.OOE-06 3.OOE-07 1.OOE-06 2.OOE-05 9.OOE-05 4.OOE-05 9.OOE-06 6.OOE-05 2.OOE-05 3.OOE-06 2.OOE-05 2.OOE-05 1.OOE-04 1.OOE-05 1.OOE-04 Gamma (.ICi/ml)Activity Released (Ci)1993 1994 CURIES CURIES 8.88E-04 ND 6.68E-04 1.62E-04 5.38E-03 2.02E-03 3.52E-02 1.37E-02 ND ND 4.76E-04 4.84E-03 1.03E-02 3.10E-03 1.71E+00 6.47E-01 3.04E-01 1.1OE-01 3.29E-03 7.13E-04 5.78E-03 1.28E&03 1.27E-03 1.07E-03 2.66E-04 ND ND ND ND 7.32E-06 1.76E-04 1.76E-04 1.19E-02 1.1OE-02 7.88E-05 4.91E-05 1.21E-03 5.35E-04 2.08E-02 1.75E-02 9.04E-02 8.23E-02 ND 6.18E-05 1.27E-01 1.82E-02 2.16E-03 1.88E-04 ND 3.63E-04 ND 4.24E-05 5.42E-05 ND 3.54E-01 6.46E-01 3.61E-03 1.59E-03 4.53E-01 8.54E-01 4.15E-06 1.35E-04 ND 8.62E-05 2.12E-04 1.86E-04 2.21E-04 1.35E-04 ND 1.03E-03 6.72E-04 ND 1998 CURIES ND 1.OOE-04 ND 7.16E-04 O.OOE+00 ND 1.78E-05 3.39E-02 2.42E-02 ND ND 4.90E-05 N ID 2.18E-04 ND ND 6.58E-05 ND 1.12E-03 1.73E-02 3.56E-02 2.23E-04 2.32E-03 8.32E-06 ND ND ND 2.49E-02 ND 7.51 E-02 ND ND ND ND ND ND 2.16E-01 1.28E-05 3.14E+00 6.05E-06 2.42E+00 1.28E-05 MPC value for unrestricted area from 10 CFR 20, Appendix B, Table II, Column 2.** ND -not detected 268 I Salem ODCM Rev. 26 I Table A-2: Calculation of Effective MPC -Unit 2 Activity Released (Ci) i Nuclide MPC* 1993 1994 1998 (jICi/ml)

CURIES CURIES CURIES BE-7 2.OOE-03 1.59E-03 2.88E-04 ND NA-24 3.OOE-05 1.05E-03 5.77E-05 7.39E-05 CR-51 2.OOE-03 4.39E-03 1.55E-03 1.14E-04 MN-54 1.OOE-04 3.73E-02 1.37E-02 7.54E-04 MN-56 L.OOE-04 ND ND 4.66E-05 FE-59 5.OOE-05 4.83E-04 3.25E-03 ND CO-57 4.OOE-04 1. 17E-02 3.24E-03 ND I CO-58 9.OOE-05 1.75E+00 6.60E-01 4.52E-02 CO-60 3.OOE-05 3.47E-01 1.03E-01 2.12E-02 ZR-95 6.OOE-05 2.34E-03 3.22E-04 ND i NB-95 L.OOE-04 3.97E-03 1.11E-03 ND NB-97 9.OOE-04 1.46E-03 1.1OE-03 4.22E-05'TC-99M 3.OOE-03 3.77E-04 ND 2.35E-06 I SR-89 3.OOE-06 ND ND 2.71E-04 SR-92 6.OOE-05 ND 1'.43E-05 ND MO-99 4.OOE-05 ND ND ND AG-110m 3.OOE-05 1.03E-02 1.34E-02 ND SN-l 13 8.OOE-05 7.45E-05 ND ND SB-122 3.OOE-05 1.20E-03 ND 6.37E-04 3 SB-124 2.OOE-05 3.77E-02 9.82E-03 1.44E-02 SB-125 1.OOE-04 1.35E-01 6.03E-02 1.88E-02 SB-126 3.OOE-06 3.51E-04 ND 1.97E-04 1-131 3.OOE-07 1.87E-01 7.98E-03 3.14E-03 1-132 8.OOE-06 8.72E-05 ND 1.68E-04 1-134 2.OOE-05 2.39E-04 1.85E-04 ND 3 CE-141 9.OOE-05 ND 2.87E-05 ND CE-143 4.OOE-05 ND ND ND CS-134 9.OOE-06 4.57E-01 6.44E-01 2.64E-02 CS-136 6.OOE-05 4.82E-03 1.51E-03 ND CS-137 2.OOE-05 5.70E-01 8.54E-01 7.97E-02 CS-138 3.OOE-06 ND ND 4.90E-05 BA-140 2.OOE-05 ND ND ND LA-140 2.OOE-05 2.03E-03 1.11E-04 ND RU-105 L.OOE-04 4.07E-05 ND ND RU-106 1.OOE-05 ND 4.38E-04 ND I ZN-65 L.OOE-04 1.59E-04 ND ND W-187 6.OOE-05 ND 7.98E-05 ND 3 Total Ci Gamma 3.57E+00 2.38E+00 2.31E-01 MPCe (tCi/ml) 4.81E-06 1.55E-05 1.12E-05 I* MPC value for unrestricted area from 10 CFR 20, Appendix B, Table II, Column 2.** ND = not detected I 269 Salem ODCM Rev. 26 APPENDIX B Technical Basis for Simplified Dose Calculations Liquid Radioactive Effluent 270 I Salem ODCM Rev. 26 I APPENDIX B: Technical Basis for Simplified Dose Calculations

-Liquid Effluents The radioactive liquid effluents for the years 1993, 1994, and 1998 were evaluated to determine the I dose contribution of the radionuclide distribution.

These were the most recent years of full power operation for both Units. This analysis was performed to evaluate the use of a limited dose analysis for determining environmental doses, providing a simplified method of determining compliance with the dose limits of ODCM CONTROL 3.11.1.2.For the radionuclide distribution of effluents from Salem, the controlling organ is typically the GI-LLI. I The calculated GI-LLI dose is predominately a function of the Fe-55, Co-58, Co-60, Fe-59 and Ag-I lOim releases.

The radionuclides, Cs- 134 and Cs- 137 contribute the large majority of the calculated total body dose. The results' of the evaluation for 1993, 1994, and 1998 are presented in Table B-I and Table B-2.For purposes of simplifying the details of the dose calculational process, it is conservative to identify a controlling, dose significant radionuclide and limit the calculation process to the use of the dose conversion factor for this nuclide. Multiplication of the total release (i.e., cumulative activity for all radionuclides) by this dose conversion factor provides for a dose calculation method that is simplified while also being conservative.

For the evaluation of the maximum organ dose, it is conservative to use the Nb-95 dose conversion factor (1.51 E+06 mrem/hr per jiCi/ml, GI-LLI). By this approach, the maximum organ dose will be overestimated since this nuclide has the highest organ dose factor.of all the radionuclides evaluated.

For the total body calculation, the Fe-59 dose factor (2.32 E+05 mrem/hr per p.Ci/ml, total body) is the highest among the identified dominant nuclides.

For evaluating compliance with the dose limits of I ODCM CONTROL .3.11.1.2, the following simplified equations may be used: Total Body I 1.67E- 02" VOL Dtb 167 OL* AFe -59,TB * (B.1) I CW Where: I Dtb = dose to the total body (mrem)A Fe-59,TB = 7.27E+04, total body ingestion dose conversion factor for Fe-59 (mremihr per iiCi/ml)VOL = volume of liquid effluent released (gal)Ci = total concentration of all radionuclides (pCi/ml)CW = average circulating water discharge rate during release period(gal/min) 1.67E-02 = conversion factor (hr/min)Substituting the value for the Fe-59 total body dose conversion factor, the equation simplifies to: 271 Salem ODCM Rev. 26 1.21E+/-+O3*

VOL Dtb = 12E 0 *V

Ci (B.2)CW *i Maximum Organ D= = 1.67E- *02*VOL ANb -95,GI -LLI

ZCi (B.3)CW i Where: Dmax = maximum organ dose (mrem)ANb-95,GI-LLI

= 1.5 1E+06, Gi-LLI ingestion dose conversion factor for Nb-95 (mrem/hr per PCi/ml)Substituting the value for ANb-95,GI-LLI the equation simplifies to: Arm=2.52E+O4

VOL cD i (B.4)Tritium is not included in the limited analysis dose assessment for liquid releases, because the potential dose resulting from normal reactor releases is relatively negligible.

The average annual tritium release from each Salem Unit is approximately 350 curies. The calculated total body dose from such a release is 2.4E-03 mrem/yr via the fish and invertebrate ingestion pathways.

This amounts to 0.08% of the design limit dose of 3 mrem/yr. Furthermore, the release of tritium is a function of operating time and power level and is essentially unrelated to radwaste system operation.

272 Salem ODCM Rev. 26 Table B- 1: Adult Dose Contributions

-Fish and Invertebrate Pathways -Unit 1 Nuclide Release (Ci) T.Body Dose Fraction GI-LLI Dose Fraction Liver Dose Fraction 1994 1993 1998 1994 1993 1998 1994 1993 1998 1994 1993 1998 Mn-54 1.32E-2 3.51E-2 7.16E-4 * *

0.03 0.02 *

0.02 *Fe-55 1.49E-1 6.40E-2 8.39E-2 0.07 0.04 0.37 0.12 0.03 0.52 0.19 0.14 0.67 Fe-59 4.84E-3 4.77E-4 N/D 0.02 *

0.12 0.01

0.03 0.01 *Co-58 6.47E-1 1.71E+O 3.39E-2 0.05 0.18 0.02 0.31 0.51 0.13 0.01 0.07 *Co-60 1.10E-1 3.04E-1 2.42E-2 0.02 0.09 0.05 0.14 0.24 0.24

0.03 0.01 Zn-65 N/D 6.72E-4 N/D

0.01 *

0.01 *

0.02 *Nb-95 1.28E-3 5.78E-3 N/D * * *

0.01 * * * *Ag-0mrn 1.1OE-2 1.19E-2 6.58E-5 * *

0.26 0.17 0.01 * * *Sb-124 1.75E-2 2.58E-2 1.73E-2 * * * *

0.04 * * *Sb-125 8.23E-2 9.04E-2 3.56E-2 * * * *

0.02 * * *Cs-134 6.46E-1 3.54E-1 2.49E-2 0.47 0.38 0.18 * *

0.38 0.37 0.09 Cs-137 8.54E-1 4.53E-1 7.51E-2 0.37 0.28 0.32 * *

0.37 0.35 0.20.Total 2.53E+0 3.21E+0 3.31E-1* Less than 0.01 N/D = not detected 273 M M M M M m m m m m M m M M M m m mSalemm m m -2mmm m Salem ODCM Rev. 26 Table B-2: Adult Dose Contributions

-Fish and Invertebrate Pathways -Unit 2 Nuclide Release (Ci) T.Body Dose Fraction GI-LLI Dose Fraction Liver Dose Fraction 1994 1993 1998 1994 1993 1998 1994 1993 1998 1994 1993 1998 Mn-54 1.37E-2 3.73E-2 7.54E-4 * *

0.01 0.02 *

0.01 *Fe-55 1.38E-1 6.61E-2 1.64E-2 0.06 0.04 0.10 0.10 0.03 0.18 0.18 0.12 0.27 Fe-59 3.25E-3 4.82E-4 N/D 0.01 *

0.08 0.01

0.02 * *Co-58 6.60E-1 1.75E+0 4.52E-2 0.05 0.16 0.04 0.29 0.51 0.29 0.01 0.06 0.01 Co-60 1.03E-1 3.47E-1 2.12E-2 0.02 0.09 0.06 0.12 0.27 0.37 0.01 0.03 0.02 Zn-65 N/D 1.59E-4 N/D * * * * * * * * *Nb-95 1.11E-3 3.97E-3 N/D * *

0.06 0.01 * * * *Ag-110m 1.34E-2 1.03E-2 N/D * *

0.31 0.14 * * * *Sb-124 9.82E-3 3.77E-2 1.44E-2 * * *

0.01 0.06 * * *Sb-125 6.03E-2 1.35E-1 1.88E-2 * * *

0.01 0.02 * * *Cs-134 6.44E-1 4.58E-1 2.64E-2 0.48 0.41 0.26 0.01 *

0.39 0.40 0.20 Cs-137 8.54E-i- 5.70E-1 7.97E-2 0.37 0.30 0.46 * *

0.38 0.36 0.45 Total 2.48E+0 3.65E+0 2.23E-1* Less than 0.01 N/D = not detected 274 Salem ODCM Rev. 26 APPENDIX C Technical Bases for Effective Dose Factors Gaseous Radioactive Effluent 275 Salem ODCM Rev. 26 APPENDIX C: Technical Bases for Effective Dose Factors -Gaseous Effluents Overview The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific.'These effective factors, which can be based on typical radionuclide distributions of releases, can be applied to the total radioactivity released to approximate the dose in the environment (i.e., instead of having to perform individual radionuclide dose analyses only a single multiplication (Keff, Muff or Neff)times the total quantity of radioactive material released would be needed).This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculational technique.

Determination of Effective Dose Factors Effective dose transfer factors are calculated by the following equations:

Keff=Y(K*f,)(C1 Where: Keff = the effective total body dose factor due to gamma emissions from all noble gases released Ki = the total body dose factor due to gamma emissions from each noble gas radionuclide i released fi = the fractional abundance of noble gas radionuclide i relative to the total noble gas activity (L/+A. 106e=1 [(Li+l.lMi)*f] (C.2)1i.Where: (L + 1.1 M)eff = the effective skin dose factor due to beta and gamma emissions from all noble gases released (Li + 1.1 Mi) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released 276 Salem ODCM Rev. 26 Meff= (M fi) (C.3)Where: Meff = the effective air dose factor due to gamma emissions from all noble gases released 3 Mi = the air dose factor due to gamma emissions from each noble gas radionuclide i released Neff =Z(Ni*f) (C.4)Where: Neff = the effective air dose factor due to beta emissions from all noble gases released 3 Ni = the air dose factor due to beta emissions from each noble gas radionuclide i released Normally, it would be expected that past radioactive effluent data would be used for the determination 3 of the effective dose factors. However, the noble gas releases from Salem have been maintained to such negligible quantities that the inherent variability in the data makes any meaningful evaluations difficult.

U Therefore, in order to provide a reasonable basis for the derivation

ýof the effective noble gas dose factors, the primary coolant source term from ANSI N237-1976/ANS-18.1, "Source Term I Specifications," has been used as representing a typical distribution.

The effective dose factors as derived are presented in Table C-i. 3 Application To provide an additional degree of conservatism, a factor of 0.50 is introduced into the dose 3 calculational process when the effective dose transfer factor is used. This conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment.

For evaluating compliance with the dose limits of ODCM CONTROL 3.11.2.2, the following simplified equations may be used: Dr=3.17E-08 Z Mff (C.5)0.50 and D,6 3.1 7 E-O 8 *Ne- *ZQi (C.6) I 0.50i Where: i 277 i Salem ODCM Rev. 26 Dy = air dose due to gamma emissions for the cumulative release of all noble gases (mrad)Dp = air dose due to beta emissions for the cumulative release of all noble gases (mrad)X/Q = atmospheric dispersion to the controlling site boundary (sec/m3)Meff = 5.3E+02, effective gamma-air dose factor (mrad/yr per [iCi/m3)Neff = 1.1 E+03, effective beta-air dose factor (mrad/yr per [iCi/m3)Qi= cumulative release for all noble gas radionuclides (pCi)3.17E-08 = conversion factor (yr/sec)0.50 = conservatism factor to account for the variability in the effluent data Combining the constants, the dose calculational equations simplify to: D 7=3.5E-05*

/Q*-Ql and Dfi=7.OE-05*%/Q*ZQI Q (C.7)(C.8)The effective dose factors are used on a very limited basis for the purpose of facilitating the timely assessment of radioactive effluent releases, particularly during periods of computer malfunction where a detailed dose assessment may be unavailable.

278 Salem ODCM Rev. 26 Table C-1: Effective Dose Factors Noble Gases -Total Body and Skin Total Body Effective Dose Factor Keff (mrem/yr per tCi/m 3)Radionuclide Kr-85 Kr-88 Xe-133m Xe-133 Xe-135 0.01 0.01 0.01 0.95 0.02 1.5E+02 2.5E+00 2.8E+02 3.6E+01 4.7E+02 Skin Effective Dose Factor (L+ 1.1 M)eff (mrem/yr per pCi/mr 3)1.4E+01 1.9E+02 1.4E+01 6.6E+02 7.9E+01 9.6E+02 Total Noble Gases -Air Gamma Air Effective Dose Factor Meff (mrad/yr per PCi/m 3)Radionuclide Kr-85 Kr-88 Xe-133m Xe-133 Xe-135 0.01 0.01 0.01 0.95 0.02 1.5E+02 3.3E+00 3.4E+02 3.8E+01 5.3E+02 Beta Air Effective Dose Factor Neff (mrad/yr per PCi/m 3)2.OE+0 1 2.9E+0 1 1.5E+01 1.OE+03 4.9E+0 1 1.1E+03!I I I I I I I I I I Total Based on Noble gas distribution from ANSI N237-1976/ANSI-18.1, "Source Term Specifications." 279 Salem ODCM Rev. 26 APPENDIX D Technical Basis for Simplified Dose Calculation Gaseous Radioactive Effluent 280 I Salem ODCM Rev. 26 APPENDIX D: Technical Basis for Simplified Dose Calculation

-Gaseous Effluents i The pathway dose factors for the controlling infant age group were evaluated to determine the controlling pathway, organ and radionuclide.

This analysis was performed to provide a simplified method for determining compliance with ODCM CONTROL 3.11.2.3 For the infant age group, the controlling pathway is the grass-cow-milk (g/c/m) pathway. An infant receives a greater radiation dose from the g/c/m pathway than any other pathway. Of this g/c/m pathway, the maximum exposed organ including the total body, is the thyroid, and the highest dose contributor is radionuclide 1-131. The results for this evaluation are presented in Table D- 1.For purposes of simplifying the details of the dose calculation process, it is conservative to identify a 3 controlling, dose significant organ and radionuclide and limit the calculation process to the use of the dose conversion factor for the organ and radionuclide.

Multiplication of the total release (i.e.cumulative activity for all radionuclides) by this dose conversion factor provides for a dose calculation method that is simplified while also being conservative.

For the evaluation of the dose commitment via a controlling pathway and age group, it is conservative 3 to use the infant, g/c/m, thyroid, 1-131 pathway dose factor (1.05E 12 m 2 mrem/yr per jiCi/sec).

By this approach, the maximum dose commitment will be overestimated since 1-131 has the highest pathway dose factor of all radionuclides evaluated.

For evaluating compliance with the dose limits of ODCM CONTROL 3.11.2.3, the following simplified equation may be used: D.mx =3.17E -08* W

R- 13 1*1Qi Where: Dmax = maximum organ dose (mrem)W = atmospheric dispersion parameters to the controlling location(s) as identified in I Table 3.2-4.X/Q = atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (see/in 3) I D/Q = atmospheric deposition for vegetation, milk and ground plane exposure pathways (M-2)Qi = cumulative release over the period of interest for radioiodines and particulates 3.17E-8 = conversion factor (yr/sec)Ri-131 = 1-13 1 dose parameter for the thyroid for the identified controlling pathway= 1.05E+12 (M 2 mremr/yr per jiCi/sec), infant thyroid dose parameter with the 3 grass-cow-milk pathway controlling The ground plane exposure and inhalation pathways need not be considered when the above simplified calculation method is used because of the overall negligible contribution of these pathways to the total thyroid dose.It is recognized that for some particulate radionuclides (e.g., Co-60 and Cs-137), the ground exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway.281 Salem ODCM Rev. 26 However, use of the 1-131 thyroid dose parameter for all radionuclides will maximize the organ dose calculation, especially considering that no other radionuclide has a higher dose parameter for any organ via any pathway than 1-131 for the thyroid via the milk pathway (see Table D-1).The dose should be evaluated based on the predetermined controlling pathways as identified in Table 2-3. If more limiting pathways in the surrounding environment of Salem are identified by the annual land use census, Table 2-3 will be revised as specified in ODCM CONTROL 3.12.2.282 Salem ODCM Rev. 26 Table D-1:* Infant Dose Contributions Fraction of Total Organ and Body Dose PATHWAYS Target Organs Total Body Liver Thyroid Kidney Grass-Cow-Milk 0.02 0.23 0.59 0.02 0.01 Ground Plane 0.15 0.14 0.15 0.15 0.02 0.15 Lung GI-LLI 0.02 Fraction of Dose Contribution by Pathway, Pathway f Grass-Cow-Milk 0.92 Ground Plane 0.08 Inhalation N/A 283 Salem ODCM Rev. 26 APPENDIX E Radiological Environmental Monitoring Program Sample Type, Location and Analysis 284 Salem ODCM Rev. 26 APPENDIX E: Radiological Environmental Monitoring Program SAMPLE DESIGNATION Samples are identified by a three part code. The first two letters are the power station identification code, in this case "SA". The next three letters are for the media sampled.AIO = Air Iodine APT = Air Particulates ECH = Hard Shell Blue Crab ESF = Edible Fish ESS = SedimentSWA

= Surface Water WWA = Well Water IDM = Immersion Dose (DLR)MLK = Milk PWR = Potable Water (Raw)PWT = Potable Water (Treated)The last four symbols are a location code based on direction and distance from the site center point.The midpoint of a line between the centers of Salem units 1 & 2 containment domes was used as the site center point. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; i.e., 2=NNE, 3=NE, 4=ENE, 5=E, 6=ESE, 7=SE, 8=SSE, 9=S, 10=SSW, 1 1=SW, 12=WSW, 13=W, 14=WNW, 15=NW and 16=NNW. The next digit is a letter which represents the radial distance from the plant: I I I I I I I I I 1 I I I I I I S = On-site location A = 0-1 miles off-site B 1-2 miles off-site C = 2-3 miles off-site D = 3-4 miles off-site E = 4-5 miles off-site F = 5-10 miles off-site G = 10-20 miles off-site H = > 20 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3. For example; the designation SA-WWA-5D1 would indicate a sample in the SGS and HCGS program (SA), consisting of well water (WWA), which had been collected in sector number 5, centered at 90'(due east) with respect to the reactor site at a radial distance of 3 to 4 miles off-site, (therefore, radial distance D). The number 1 indicated that this is sampling station #1 in that particular sector.SAMPLING LOCATIONS All sampling locations and specific information about the individual locations are given in Table E- 1.Maps E- I and E-2 show the locations of sampling stations with respect to the site center point.285 Salem ODCM Rev. 26 TABLE E-1: REMP Sample Locations A. Direct Radiation Monitoring Locations (IDM)STATION CODE STATION LOCATION*iSi 0.55 mi. N 2S2 0.4 mi. NNE 2S4 0.60 mi. NNE; in the equipment laydown area 3S1 0.58 mi. NE 4S1 0.60 mi ENE; site access road near intersection to TB-02 5S1 0.86 mi. E; site access road 6S2 0.23 mi. ESE; area around helicopter pad 7S1 0.12 mi. SE; station personnel gate lOSi 0.14 mi. SSW; circ water bldg.liSi 0.09 mi. SW; service water bldg.15SI 0.57 mi. NW; near river and barge slip 15S2 0.59 mi. NW, near river 16S1 0.57 mi. NNW; on road near fuel oil storage tank 16S2 0.60 mi. NNW; near security firing range 4D2 3.7 mi. ENE; Alloway Creek Neck Road 5D1 3.5 mi. E; local farm 1OD1 3.9 mi. SSW; Taylor's Bridge Spur 14D 1 3.4 mi. WNW; Bay View, DE 15D1 3.8 mi. NW; Rt 9, Augustine Beach, DE 2El 4.4 mi. NNE; local farm 3E1 4.2 mi. NE; local farm 1 1E2 5.0 mi. SW; Rt. 9 12E1 4.4 mi. WSW; Thomas Landing 13E1 4.2 mi. W; Diehl House Lab 16EI 4.1 mi. NNW; Port Penn IF1 5.8 mi. N; Fort Elfsborg 2F2 8.5 mi. NNE; Salem Substation 2F5 7.4 mi. NNE; Salem High School 2F6 7.3 mi. NNE; PSE&G Training Center Salem NJ 3F2 5.1 mi. NE; Hancocks Bridge, NJ Munc Bldg 3F3 8.6 mi. NE; Quinton Township Elem. School NJ 4F2 6.0 mi. ENE; Mays Lane, Harmersville, NJ 5F1 6.5 mi. E; Canton, NJ 286 Salem ODCM Rev. 26 TABLE E-1 (Cont'd)A. Direct Radiation Monitoring Locations (IDM) (Cont'd)STATION CODE STATION LOCATION*

3 6F 1 6.4 mi. ESE; Stow Neck Road 7F2 9.1 mi. SE; Bayside, NJ 9F1 5.3 mi. S; off Route #9, DE 10F2 5.8 mi. SSW; Rt. 9 11F1 6.2 mi. SW; Taylors Bridge, DE 12F1 9.4 mi. WSW; Townsend Elementary School, DE 13F2 6.5 mi. W; Odessa, DE 13F3 9.3 mi. W; Redding Middle School 13F4 9.8 mi. W; Middletown, DE 14F2 6.7 mi. WNW; Rt 13 and Boyds Comer Rd 3 15F3 5.4 mi. NW 16F2 8.1 mi. NNW; Delaware City Public School 1G3 19 mi. N; N. Church St. Wilmington, DE 3G1 17 mi. NE; local farm lOG1 12 mi. SSW; Smyrna, DE 3 14G1 11.8 mi. WNW; Rte 286, Bethel Church Rd., DE 16G1 15 mi. NNW; Wilmington Airport 3H1 32 mi. NE; National Park, NJ U B. Air Sampling Locations (AIO, APT)STATION CODE STATION LOCATION*5S1 0.86 mi. E; site access road 3 5S2 0.86 mi. E; site access road 5D1 3.5 mi. E; local farm 16E1 4.1 mi. NNW; Port Penn I IFI 5.8 mi. N; Fort Elfsborg 2F6 7.3 mi. NNE; PSE&G Training Center Salem, NJ 14G1 11.8 mi. WNW; Rte 286, Bethel Church Rd., DE 287 Salem ODCM Rev. 26 Table E-1 (Cont'd)C. Surface Water Locations (SWA) -Delaware River STATION CODE STATION LOCATION*11A1 0.2 mi. SW; Salem Outfall Area 1lAla Alternate 0.15 SE location in plant barge slip area 12C1 2.5 mi. WSW; West bank of Delaware River l12Cla Alternate 3.7 mi.WSW at the tip of Augustine Beach Boat Ramp 7El 4.5 mi. SE; River Bank 1.0 mi. W of Mad Horse Creek 7E1a Alternate 8.87 mi SE at the end of Bayside Road 1F2 7.1 mi. N; midpoint of Delaware R.16F1 6.9 mi. NNW; C&D Canal 16Fla Alternate 6.84 mi. NNW; Located at the C&D Canal Tip D. Ground Water Locations (WWA)STATION CODE STATION LOCATION*3E1 4.2 mi NE, local farm No groundwater samples are required as liquid effluents discharged from Hope Creek and Salem Generating Stations do not directly affect this pathway. However, this location (3E1) is being monitored as a management audit sample E. Drinking Water Locations (PWR, PWT)STATION CODE STATION LOCATION*2F3 8.0 mi NNE, City of Salem Water and Sewage Department No public drinking water samples or irrigation water samples are required as these pathways are not directly affected by liquid effluents discharged from Hope Creek and Salem Generating Stations.

However, this location (2F3) is being monitored as a management audit sample.F. Water Sediment Locations (ESS)STATION CODE STATION LOCATION*11A1 0.2 mi. SW; Salem outfall area 15AI 0.65 mi. NW; Hope Creek outfall area 16A1 0.24 mi. NNW; South Storm Drain outfall 12C 1 2.5 mi. WSW; West bank of Delaware River 7El 4.5 mi. SE; 1 mi West of Mad Horse Creek 16F1 6.9 mi. NNW; C&D Canal 6S2 0.23 mi. ESE; area around helicopter pad 288 I Salem ODCM Rev. 26 Table E-1 (Cont'd)G. Milk Sampling Locations (MLK)STATION CODE STATION LOCATION*2G3 11.8 mi. NNE, local farm 13E3 5.0 mi W, local farm 14F4 7.6 mi. WNW; local farm 3G1 17 mi. NE; local farm 3 H. Fish and Invertebrate Locations (ESF, ECH)STATION CODE STATION LOCATION*

3 11Al 0.2 mi. SW; Salem outfall area 12C1 2.5 mi. WSW; West baAk of Delaware River I 7El 4.5 mi. SE; 1 mi West of Mad Horse Creek I. Food Product Locations STATION CODE STATION LOCATION*The Delaware River at the location of Salem and Hope Creek Nuclear Power Plants is a brackish water source. No irrigation of food products is performed using water in the vicinity from which 3 liquid plant wastes have been discharged.

However, 12 management audit food samples are collected from various locations.

All distances and directions for the Station Locations are referenced to the midpoint between the two Salem units' containments.

The WGS 84 coordinates for this site center point location are: Latitude N 390 -27' -46.5" and Longitude W 750 -32' -10.6". 3 289 Salem ODCM Rev. 26 SAMPLES COLLECTION AND ANALYSIS Sample Air Particulate Collection Method Continuous low volume air sampler. Sample collected every week along with the filter change.Analysis, Gross Beta analysis on each weekly sample. Gamma spectrometry shall be performed if gross beta exceeds 10 times the yearly mean of the control station value. Samples shall be analyzed 24 hrs or more after collection to allow for radon and thorium daughter decay. Gamma isotopic analysis on quarterly composites.

Iodine 131 analysis are performed on each weekly sample.Air Iodine Crab and Fish A TEDA impregnated charcoal cartridge is connected to air particulate air sampler and is collected weekly at filter change.Two batch samples are sealed in a plastic bag or jar and frozen semi-annually or when in season.A sediment sample is taken semi-annually.

2 DLR's will be collected from each location quarterly.

Gamma isotopic analysis of edible portion on collection.

Sediment Gamma isotopic analysis semi-annually.

Gamma dose quarterly.

Direct 290 Salem ODCM Rev. 26 SAMPLE COLLECTION AND ANALYSIS (Cont'd)Sample Collection Method Analysis Milk Sample of fresh milk is collected for each farm semi-monthly when cows are in pasture, monthly at other times.Sample to be collected monthly providing winter icing conditions allow.Gamma isotopic analysis and 1-131 analysis on each sample on collection.

Gamma isotopic monthly H-3 on quarterly surface sample, monthly on ground water sample.Water (Potable, Surface)I I I I I I I I I I I I I I I I I I I 291 Salem ODCM Rev. 26 FIGURE E-1: ONSITE SAMPLING LOCATIONS 1 15'et16S2 2S 13 -6S- CREEK GENERATIN~STATION x'L "TOWER i.9 292 Salem ODCM Rev. 26 I FIGURE E-2: OFFSITE SAMPLING LOCATIONS I Salem ODCM Rev. 26 APPENDIX F MAXIMUM PERMISSIBLE CONCENTRATIONS LIQUID EFFLUENTS 294 APPENDIX F: Maximum Permissible Concentration (MPC) Values -Liquid Effluents The following radionuclide concentrations were obtained from 10 CFR 20 Appendix B, Table II, Column 2 as revised January 1, 1991.Table F-1: Maximum Permissible Concentrations Element Isotope Soluble Conc Insoluble Conc.(.tCi/ml) (PCi/ml)Actinium (89) Ac-227 2E-6 3E-4 Ac-228 9E-5 9E-5 Americium (95) Am-241 4E-6 3E-5 Am-242m 4E-6 9E-5 Am-242 1E-4 1E-4 Am-243 4E-6 3E-5 Am-244 5E-3 5E-3 Antimony (51) Sb-122 3E-5 3E-5 Sb-124 2E-5 2E-5 Sb-125 1E-4 lE-4 Sb-126 3E-6 3E-6 Arsenic (33) As-73 5E-4 5E-4 As-74 5E-5 5E-5 As-76 2E-5 2E-5 As-77 8E-5 8E-5 Astatine (85) At-211 2E-6 7E-5 Barium (56) Ba-131 2E-4 2E-4 Ba-140 3E-5 2E-5 Berkelium (97) Bk-249 6E-4 6E-4 Bk-250 2E-4 2E-4 Beryllium (4) Be-7 2E-3 2E-3 Bismuth (83) Bi-206 4E-5 4E-5 Bi-207 6E-5 6E-5 Bi-210 4E-5 4E-5 Bi-212 4E-4 4E-4 Bromine (35) Br-82 3E-4 4E-5 Br-83 3E-6 3E-6 Cadmium (48) Cd-109 2E-4 2E-4 Cd-115m 3E-5 3E-5 Cd- 115 3E-5 4E-5 Calcium (20) Ca-45 9E-6 2E-4 Ca-47 5E-5 3E-5 Californium (98) Cf-249 4E-6 2E-5 Cf-250 1E-5 3E-5 Cf-251 4E-6 3E-5 I I I I I I I I I I I I I I I I I 295 Cf-252 7E-6 7E-6 Cf-253 1E-4 1E-4 Cf-254 1E-7 1E-7 296 Table F-I (Continued)

Element Isotope Soluble Conc. Insoluble Conc.(ýICi/ml)

(ýLCi/ml)Carbon (6) C- 14 8E-4 Cerium (58) Ce- 141 9E-5 9E-5 Ce-143 4E-5 4E-5 Ce-144 1E-5 1E-5 Cesium (55) Cs-131 2E-3 9E-4 Cs-134m 6E-3 1E-3 Cs-134 9E-6 4E-5 Cs-135 1E-4 2E-4 Cs-136 9E-5 6E-5 Cs-137 2E-5 4E-5 Chlorine (17) C1-36 8E-5 6E-5 C1-38 4E-4 4E-4 Chromium (24) Cr-51 2E-3 2E-3 Cobalt (27) Co-57 5E-4 4E-4 Co-58m 3E-3 2E-3 Co-58 1E-4 9E-5 Co-60 5E-5 3E-5 Copper (29) Cu-64 3E-4 2E-4 Curium (96) Cm-242 2E-5 2E-5 Cm-243 5E-6 2E-5 Cm-244 7E-6 3E-5 Cm-245 4E-6 3E-5 Cm-246 4E-6 3E-5 Cm-247 4E-6 2E-5 Cm-248 4E-7 1E-6 Cm-249 2E-3 2E-3 Dysprosium (66) Dy- 165 4E-4 4E-4 Dy-166 4E-5 4E-5 Einsteinium (99) Es-253 2E-5 2E-5 Es-254m 2E-5 2E-5 Es-254 1E-5 1E-5 Es-255 3E-5 3E-5 Erbium (68) Er- 169 9E-5 9E-5 Er-171 1E-4 1E-4 Europium (63) Eu-152 (9.2 hrs) 6E-5 6E-5 Eu-152 (13 yrs) 8E-5 8E-5 Eu- 154 2E-5 2E-5 Eu-155 2E-4 2E-4 Fermium (100) Fm-254 1E-4 1E-4 I I I I i i I I I I I I I I I i I 297 IFm-255 I3E-5 I3E-5 Fm-256 9E-7 9E-7 298 Table F-I (Continued)

Element Isotope Soluble Conc. Insoluble Conc.(ptCi/ml) (pCi/ml)Fluorine (9) F- 18 8E-4 5E-4 Gadolinium (64) Gd-153 2E-4 2E-4 Gd-159 8E-5 8E-5 Gallium (31) Ga-72 4E-5 4E-5 Germanium (32) Ge-71 2E-3 2E-3 Gold (79) Au-196 2E-4 IE-4 Au-198 5E-5 5E-5 Au-199 2E-4 2E-4 Hafnium (72) Hf- 181 7E-5 7E-5 Holmium (67) Ho-166 3E-5 3E-5 Hydrogen (3) H-3 3E-3 3E-3 Indium (49) In-I 13m 1E-3 1E-3 In-I 14m 2E-5 2E-5 In- 15m 4E-4 4E-4 In- 115 9E-5 9E-5 Iodine (53) 1-125 2E-7 2E-4 1-126 3E-7 9E-5 1-129 6E-8 2E-4 1-130 3E-6 3E-6 1-131 3E-7 6E-5 1-132 8E-6 2E-4 1-133 IE-6 4E-5 1-134 2E-5 6E-4 1-135 4E-6 7E-5 Iridium (77) Ir-190 2E-4 2E-4 Ir-192 4E-5 4E-5 Ir-194 3E-5 3E-5 Iron (26) Fe-55 8E 2E-3 Fe-59 6E-5 5E-5 Lanthanum (57) La- 140 2E-5 2E-5 Lead (82) Pb-203 4E-4 4E-4 Pb-210 1E-7 2E-4 Pb-212 2E-5 2E-5 Lutetium (71) Lu- 177 1E-4 IE-4 Manganese (25) Mn-52 3E-5 3E-5 Mn-54 IE-4 1E-4 Mn-56 IE-4 1E-4 Mercury (80) Hg-197m 2E-4 2E-4 Hg-197 3E-4 5E-4 I I I I I I I I I I I I, I I I I I 299 Hg-203 2E-5 1IlE-4 Molybdenum (42) Mo-99 2E-4 4E-5 300 Table F-I (Continued)

Element Isotope Soluble Conc. Insoluble Conc.([LCi/ml)

(ýtCi/mnl)

Neodymium (60) Nd-144 7E-5 8E-5 Nd-147 6E-5 6E-5 Nd-149 3E-4 3E-4 Neptunium (93) Np-237 3E-6 3E-5 Np-239 1E-4 1E-4 Nickel (28) Ni-59 2E-4 2E-3 Ni-63 3E-5 7E-4 Ni-65 1E-4 1E-4 Niobium (41) Nb-93m 4E-4 4E-4 Nb-95 1E-4 1E-4 Nb-97 9E-4 9E-4 Osmium (76) Os-185 7E-5 7E-5.Os-191m 3E-3 2E-3 Os-191 2E-4 2E-4 Os-193 6E-5 5E-5 Palladium (46) Pd- 103 3E-4 3E-4 Pd-109 9E-5 7E-5 Phosphorus (15) P-32 2E-5 2E-5 Platinum (78) Pt- 191 1E-4 1E-4 Pt-193m 1E-3 1E-3 Pt-193 9E-4 2E-3 Pt-197m lE-3 9E-4 Pt-197 1E-4 1E-4 Plutonium (94) Pu-238 5E-6 3E-5 Pu-239 5E-6 3E-5 Pu-240 5E-6 3E-5 Pu-241 2E-4 1E-3 Pu-242 5E-6 3E-5 Pu-243 3E-4 3E-4 Polonium (84) Po-2 10 7E-7 3E-5 Potassium (19) K-42 3E-4 2E-5 Praseodymium(59)

Pr-142 3E-5 3E-5 Pr-143 5E-5 5E-5 Promethium (61) Pm-147 2E-4 2E-4 Pm-149 4E-5 4E-5 Protactinium(91)

Pa-230 2E-4 2E-4 Pa-231 9E-7 2E-5 Pa-233 1E-4 1E-4 I I I I I I I I I I I I I I I I I 301 Table F-1 (Continued)

Element Isotope Soluble Conc. Insoluble Conc.([1Ci/ml) (j4Ci/ml)Radium (88) Ra-223 7E-7 4E-6 Ra-224 2E-6 5E-6 Ra-226 3E-8 3E-5 Ra-228 3E-8 3E-5 Rhenium (75) Re- 183 6E-4 3E-4 Re- 186 9E-5 5E-5 Re- 187 3E-3 2E-3 Re-188 6E-5 3E-5 Rhodium (45) Rh-103m 1E-2 1E-2 Rh-105 1E-4 1E-4 Rubidium (37) Rb-86 7E-5 2E-5 Rb-87 1E-4 2E-4 Ruthenium (44) Ru-97 4E-4 3E-4 Ru-103 8E-5 8E-5 Ru-103m 3E-6 3E-6 Ru-105 1E-4 1E-4 Ru-106 1E-5 1E-5 Samarium (62) Sm-147 6E-5 7E-5 Sm- 151 4E-4 4E-4 Sm-153 8E-5 8E-5 Scandium (21) Sc-46 4E-5 4E-5 Sc-47 9E-5 9E-5 Sc-48 3E-5 3E-5 Selenium (34) Se-75 3E-4 3E-4 Silicon (14) Si-31 9E-4 2E-4 Silver (47) Ag- 105 1E-4 1E-4 Ag-110m 3E-5 3E-5 Ag-111 4E-5 4E-5 Sodium (11) Na-22 4E-5 3E-5 Na-24 2E-4 3E-5 Strontium (38) Sr-85m 7E-3 7E-3 Sr-85 1 E-4 2E-4 Sr-89 3E-6 3E-5 Sr-90 3E-7 4E-5 Sr-91 7E-5 5E-5 Sr-92 7E-5 6E-5 Sulfur (16) S-35 6E-5 3E-4 Tantalum (73) Ta-182 4E-5 4E-5 302 I I I Table F-I (Continued)

Element Isotope Soluble Conc. Insoluble Conc.(jICi/ml) (jiCi/ml)Technetium (43) Tc-96m 1E-2 1E-2 Tc-96 1E-4 5E-5 Tc-97m 4E-4 2E-4 Tc-97 2E-3 8E-4 Tc-99m 6E-3 3E-3 Tc-99 3E-4 2E-4 Tellurium (52) Te-125m 2E-4 1E-4 Te-127m 6E-5 5E-5 Te-127 3E-4 2E-4 Te-129m 3E-5 2E-5 Te-129 8E-4 8E-4 Te-131m 6E-5 4E-5 Te-132 3E-5 2E-5 Terbium (65) Th- 160 4E-5 4E-5 Thallium (81) TI-200 4E-4 2E-4 TI-201 3E-4 2E-4 TI-202 lE-4 7E-5 TI-204 1E-4 6E-5 Thorium (90) Th-227 2E-5 2E-5 Th-228 7E-6 1E-5 Th-230 2E-6 3E-5 Th-231 2E-4 2E-4 Th-232 2E-6 4E-5 Th-natural 2E-6 2E-5 Th-234 2E-5 2E-5 Thulium (69) Tm-170 5E-5 5E-5 Tm-171 5E-4 5E-4 Tin (50) Sn- 113 9E-5 8E-5 Sn-124 2E-5 2E-5 Tungsten (74) W- 181 4E-4 3E-4 W-185 1E-4 1E-4 W-187 7E-5 6E-5 Uranium (92) U-230 5E-6 5E-6 U-232 3E-5 3E-5 U-233 3E-5 3E-5 U-234 3E-5 3E-5 U-235 3E-5 3E-5 U-236 3E-5 3E-5 U-238 4E-5 4E-5 U-240 3E-5 3E-5 I I I I I I I I I I I I I I I 303 I I U-natural I 3E-5 I 3E-5 I I U-natural I 3E-5 I13E-5 i 304 Table F-I (Continued)

Element Isotope Soluble Conc. Insoluble Conc.(gtCi/ml)

(ýLCi/ml)Vanadium (23) V-48 3E-5 3E-5 Ytterbium (70) Yb-175 1E-4 1E-4 Yttrium Y-90 2E-5 2E-5 Y-91m 3E-3 3E-3 Y-91 3E-5 3E-5 Y-92 6E-5 6E-5 Y-93 3E-5 3E-5 Zinc (30) Zn-65 1E-4 2E-4 Zn-69m 7E-5 6E-5 Zn-69 2E-3 2E-3 Zirconium (40) Zr-93 8E-4 8E-4 Zr-95 6E-5 6E-5 Zr-97 2E-5 2E-5 Any single radio- 3E-6 3E-6 nuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radio -active half-life greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Any single radio- 3E-8 3E-8 nuclide not listed above, which decays by alpha emission or spontaneous fission.Notes: 1. If the identity of any radionuclide is not known, the limiting values for purposes of this table shall be: 3E-8 gCi/ml.2. If the identity and concentration of each radionuclide are known, the limiting values should be derived as follows: Determine, for each radionuclide in the mixture, the ratio between the quantity present in the mixture and the limit otherwise established in Appendix B for the specific radionuclide not in a mixture. The sum of such ratios for all the radionuclides in the mixture may not exceed "1" (i.e. "unity").305 I I U I I I I I I I I I I I I I OFFSITE DOSE CALCULATION MANUAL FOR PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION Revision 26 Prepared by: Accepted by: Accepted by: Hope Creek ODCM Coordinator

-Jenny Shelton Hope Creek Chemistry Manager -Frank. Leeser Date Date Hope Creek PORC Chairman-Eric Carr Date Meeting #: Approved by: Hope Creek Plant Manager- Lawrence Wagner Date 306 I HOPE CREEK ODCM REV. 26 Revision Summary 1. Table E-1 section B. Air Sampling Locations was revised to include one new air sampler location, 5S2. I And table 3.12.1-1 was revised to describe the air sampling requirements for the program, increased from six locations to seven.Justification:

NOS audit finding from Maplewood Testing Services Laboratory vendor audit SNA 2009-091, refer to US NRC Reg Guide 4.15 revision 2, which calls for field duplicate sampling stations, reference DCP 80102652.

This was also recommended by REMP benchmarking 70084355-0110.

2. Updated Figure E-I On-site Sampling Locations to update the new sampling location for air I sampler 5S2.And Figure E-2 Off-site Sampling Locations was updated with the location of a new management audit sample. 3 Justification:

The map was updated to be consistent with'the REMP station location listed in Table E-1 section B. Figure E-2 was update to include location of offsite management audit sample for muskrat sampling (5C 1).3. Section 3.3 was added to assess dose due to C-14 for gaseous effluents, includes methodology for assessment based on guidance from Regulatory Guide 1.21 revision 2.Justification:

In accordance with guidance offered in Regulatory Guide 1.21 revision 2 the station conducted an evaluation which identified C- 14 as a principal radionuclide in gaseous effluent releases from the Salem Generating Station (SAP Order 70096339).

Revision to the ODCM documents the methodology used for estimating the doses from Carbon 14.I I I I I U I 307 I HOPE CREEK ODCM REV. 26 TABLE OF CONTENTS INTRODUCTION 311 PART I -RADIOLOGICAL EFFLUENT CONTROLS 312 1.0 DEFINITIONS 314 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 320 3/4.0 APPLICABILITY 320 3/4.3 INSTRUMENTATION 322 3/4.3.7.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 322 3/4.3.7.11 RADIOACTIVE GASEOUS EFFLUENT MONITORJNG INSTRUMENTATION 327 3/4.11 RADIOACTIVE EFFLUENTS 334 3/4.11.1 LIQUID EFFLUENTS 334 3/4.11.1.1 CONCENTRATION 334 3/4.11.1.2 DOSE 338 3/4.11.1.3 LIQUID WASTE TREATMENT SYSTEM 339 3/4.11.2 GASEOUS EFFLUENTS 340 3/4.11.2.1 DOSE RATE 340 3/4.11.2.2 DOSE -NOBLE GASES 343 3/4.11.2.3 DOSE -IODINE- 131, IODINE- 133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM 344 3/4.11.2.4 GASEOUS RADWASTE TREATMENT 345 3/4.11.2.5 VENTILATION EXHAUST TREATMENT 346 3/4.11.2.8 VENTING OR PURGING 347 3/4.11.4 TOTAL DOSE 348 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 349 3/4.12.1 MONITORING PROGRAM 349 RADIOLOGICAL ENVIRONMENTAL MONITORING 362 3/4.12.2 LAND USE CENSUS 362 3/4.12.3 INTERLABORA TORY COMPARISON PROGRAM 363 BASES 364 3/4.3 INSTR UMENTA TION 365 3/4.3.7.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 365 3/4.3.7.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 365 3/4.11 RADIOACTIVE EFFLUENTS 366 3/4.11.1 LIQUID EFFLUENTS 366 3/4.11.2 GASEOUS EFFLUENTS 367 3/4.11.4 TOTAL DOSE 369 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 370 3/4.12.1 MONITORING PROGRAM 370 3/4.12.2 LAND USE CENSUS 370 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 371 5.0 DESIGN FEATURES 373 5.1 SITE 373 6.0 ADMINISTRATIVE CONTROLS 375 6.9.1.6 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 375 6.9.1.7 RADIOACTIVE EFFLUENT RELEASE REPORT 376 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 378 308 HOPE CREEK ODCM REV. 26 PART II -CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENTS 1.1 Radiation Monitoring Instrumentation and Controls 1.2 Liquid Effluent Monitor Setpoint Determination 1.2.1 Liquid Effluent Monitors 1.2.2 Conservative Default Values 1.3 Liquid Effluent Concentration Limits -10 CFR 20 1.4 Liquid Effluent Dose Calculation

-10 CFR 50 1.4.1 MEMBER OF THE PUBLIC Dose -Liquid Effluents 1.4. Simplified Liquid Effluent Dose Calculation 1.5 Liquid Effluent Dose Projections 1.6 Representative Samples 2.0 GASEOUS EFFLUENTS 2.1 Radiation Monitoring Instrumentation and Controls 2._2 Gaseous Effluent Monitor Setpoint Determination 2.2.1 Plant Vent, FRVS 2.2.2 Conservative Default Values 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations

-10 CFR 20 2.3.1 Site Boundary Dose Rate -Noble Gases 2.3.2 Site Boundary Dose Rate -Radioiodine and Particulates 2.4 Noble Gas Effluent Dose Calculations

-10 CFR 50 2.4.1 UNRESTRICTED AREA Dose -Noble Gases 2.4.2, Simplified Dose Calculation for Noble Gases 2.5 Radioiodine and Particulate Dose Calculations

-10 CFR 50 2.5.1 UNRESTRICTED AREA Dose -Radioiodine and Particulates 2.5.2 Simplified Dose Calculation for Radioiodines and Particulates 2.6 Gaseous Effluent Dose Projection 3.0 SPECIAL DOSE ANALYSIS 379 380 380 380 381 381 382 383 383 384 385 386 386 386 387 387 388 388 388 390 390 390 391 392 392 392 393 394 394 394 394 395 395 395 395 396 396 396 396 I I I I I I U I I I I I I I I I I U I 3.1 3.2 3.2.1 3.2.2 3.3 Dos D(ses Due to Activities Inside the SITE BOUNDARY Total Dose to MEMBERS OF THE PUBLIC -40 CFR 190 and 10 CFR 72.104 ses Effluent Dose Calculations Direct Exposure Dose Determination due to Carbon 14 in Gaseous Effluent 4.0 5.0 3.3.1 Estimation of Carbon 14 Annual Release 3.3.2 Carbon 14 dose Determinations RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4.1 Samplin! Proeram 4.2 Interlaboratory Comparison Program HCGS EXPLOSIVE GAS MONITORING PROGRAM 309 HOPE CREEK ODCM REV. 26 TABLES TABLE 1.1: SURVEILLANCE FREQUENCY NOTATION .................................................................................

317 TABLE 1.2: OPERATIONAL CONDITION S .........................................................................................................

318 TABLE 3.3.7.10-1:

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

..................

323 TABLE 4.3.7.10-1:

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SU RV EILLA N CE REQ U IREM EN TS .....................................................................................................................

325 TABLE 3.3.7.1 1-1: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

.............

328 TABLE 4.3.7.11-1:

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SU RV EILLAN CE REQ U IREM EN TS .....................................................................................................................

331 TABLE 4.11.1.1.1-1:

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM ...............

335 TABLE 4.11.2.1.2-1:

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM ..........

341 TABLE 3.12.1-1:

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM * ..................................

351 TABLE 3.12.1-2:

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN EN V IR O N M EN TA L SA M PLES .............................................................................................................................

358 TABLE 4.12.1-1:

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS)'.

2 ...........

359 TABLE 1-1: PARAMETERS FOR LIQUID ALARM SETPOINT DETERMINATION

.......................................

399 TABLE 1-2: SITE RELATED INGESTION DOSE COMMITMENT FACTOR, A. .........................

................... 400 TABLE 1-3: BIOACCUM ULATION FACTORS ....................................................................................................

402 TABLE 2-1: DOSE FACTORS FOR NOBLE GASES ............................................................................................

405 TABLE 2-2: PARAMETERS FOR GASEOUS ALARM SETPOINT DETERMINATION

...................................

406 TABLE 2-3: CONTROLLING LOCATIONS, PATHWAYS AND ATMOSPHERIC DISPERSION FOR DOSE C A L C U L A T IO N S * ..................................................................................................................................................

407 Table 2-4: Pathway Dose Factors -Atmospheric Releases, R(io) .............................................................................

408 TABLE A-1: CALCULATION OF EFFECTIVE MPC -HOPE CREEK ...............................................................

426 TABLE B-i: Adult Dose Contributions Fish and Invertebrate Pathways .................................................................

430 TA BLE C-i: Effective Dose Factors Noble Gases ...................................................................................................

435 TABLE D-l: Infant Dose Contributions

..........................................................................................................

439 TA B LE E-1: REM P Sam ple Locations

.....................................................................................................................

442 TABLE F-1: M axim um Perm issible Concentrations

................................................................................................

451 FIGURES Figure 5.1.1-1 A rea Plot Plan O f Site ....................................................................................................

374 Figure 1-1: Liquid Radwaste Treatment And Monitoring System .............................................................

396 Figure 1-2: Solid Radwaste Processing System .......................................................................................

93 Figure 2-1: Gaseous Radwaste Treatment System .....................................................................................

403 Figure 2-2: Ventilation Exhaust Treatment System ....................................................................................

404 Figure E- 1: O nsite Sam pling Locations

......................................................................................................

448 Figure E-2: O ff-Site Sam pling Locations

...................................................................................................

449 APPENDICES APPENDIX A: Evaluation of Default MPC Value for Liquid Effluent Monitors .....................................

421 APPENDIX B: Technical Basis for Effective Dose Factors -Liquid Effluent ..........................................

428 APPENDIX C: Technical Basis for Effective Dose Factors -Gaseous Effluents

......................................

432 APPENDIX D: Technical Basis for Effective Dose Parameters

-Gaseous Effluent .................................

437 APPENDIX E: Radiological Environmental Monitoring Program ............................................................

441 APPENDIX F: Maximum Permissible Concentration (MPC) Values For Liquid Effluents

.....................

451 310 I HOPE CREEK ODCM REV. 26 HOPE CREEK NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL INTRODUCTION The Hope Creek Offsite Dose Calculation Manual (ODCM) is a supporting document to the Hope Creek Technical Specifications.

The previous Limiting Conditions for Operations that were contained in the Radiological Effluent Technical Specifications (RETS) are now included in the ODCM as Radiological Effluent Controls (REC). The ODCM contains two parts: Part I -Radiological Effluent Controls, and l Part 1I -Calculational Methodologies.

Part I includes the following:

i* The Radiological Effluent Controls and the Radiological Environmental Monitoring Programs required by Technical Specifications 6.8.4* Descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by Technical Specifications 6.9.1.6 and 6.9.1.7, respectively.

Part II describes methodologies and parameters used for:* the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints; and 3" the calculation of radioactive liquid and gaseous concentrations, dose rates, cumulative quarterly and yearly doses, and projected doses.Part II also contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program (REMP), and the liquid and gaseous waste treatment systems.The current licensing basis applies Maximum Permissible Concentrations (MPCs) for radioactive liquid effluent concentration limits. Since the MPC values were removed from 10CFR20 effective 1/1/94, the MPC values are provided as Appendix F to the ODCM. As discussed in the Safety Evaluation By The I Office Of Nuclear Reactor Regulation Related to Amendment No. 121, letters between the Nuclear Management and Resources Council (NUMARC) concerning the differences between the "old" 1 OCFR20 and the "new" 10CFR20 allowed continued use of the instantaneous release limits (MPCs). The I NUMARC letter of April 28, 1993, concluded that the RETS that reference the "old" Part 20 are generally more restrictive than the comparable requirements of the "new" Part 20, and therefore, in accordance with 10 CFR 20.1008, the existing RETS could remain in force after the licensee implements the "new" Part I 20. The letter stated that the existing RETS which reference the "old" Part 20 would maintain the level of required protection of public health and safety, and would be consistent with the requirements of the"new" Part 20.311 HOPE CREEK ODCM REV. 26 PART I -RADIOLOGICAL EFFLUENT CONTROLS 312 HOPE CREEK ODCM REV. 26 SECTION 1.0 DEFINITIONS 313 HOPE CREEK ODCM REV. 26 1.0 DEFINITIONS The following terms are defined so that uniform interpretation of these CONTROLS may be achieved.The defined terms appear in capitalized type and are applicable throughout these CONTROLS.ACTION 1.1 ACTION shall be that part of a CONTROL which prescribes remedial measures required under designated conditions.

CHANNEL CALIBRATION 1.4 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter that the channel monitors.

The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST.Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an in place qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. Whenever an RTD or thermocouple sensing element is replaced, the next required CHANNEL CALIBRATION shall include an in place cross calibration that compares the other sensing elements with the recently installed sensing monitor. The CHANNEL CALIBRATION may be performed by means of.any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.

CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.

This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be: a. Analog channels -the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions and channel failure trips.b. Bistable channels -the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is tested.CONTROL 1. 10 The Limiting Conditions for Operation (LCOs) that were contained in the Radiological Effluent Technical Specifications were transferred to the OFFSITE DOSE CALCULATION MANUAL (ODCM)and were renamed CONTROLS.

This is to distinguish between those LCOs that were retained in the Technical Specifications and those LCOs or CONTROLS that were transferred to the ODCM.314 I HOPE CREEK ODCM REV. 26 DEFINITIONS (Continued)

DOSE EQUIVALENT 1-131 1 1.11 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram), which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844 "Calculation of Distance Factors for Power and Test Reactor Sites." FREQUENCY NOTATION 1.17 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.MEMBER(S)

OF THE PUBLIC 1.24 MEMBER(S)

OF THE PUBLIC (10 CFR 20) -Means any individual except when that individual is receiving an occupational dose.MEMBER(S)

OF THE PUBLIC (40 CFR 190) -Means any individual that can receive a radiation dose in the general environment, whether he may or may not also be exposed to radiation in an occupation associated with a nuclear fuel cycle. However, an individual is not considered a member of the public during any period in which the individual is engaged in carrying out any operation which is part of a nuclear fuel cycle.OFF-GAS RADWASTE TREATMENT SYSTEM (GASEOUS RADWASTE TREATMENT SYSTEM)1.26 An OFF-GAS RADWASTE TREATMENT SYSTEM (GASEOUS RADWASTE TREATMENT SYSTEM) is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the main condenser evacuation system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

OFFSITE DOSE CALCULATION MANUAL (ODCM) i 1.27 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the radiological environmental monitoring program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Reports required by Technical Specification Sections 6.9.1.6 and 6.9.1.7, respectively.

3 OPERABLE -OPERABILITY 1.28 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s).

315 HOPE CREEK ODCM REV. 26 DEFINITIONS (Continued)

OPERATIONAL CONDITION

-CONDITION 1.29 An OPERATIONAL CONDITION (i.e., CONDITION) shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specified in Table 1.2.PURGE -PURGING 1.34 PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER 1.35 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3339 MWT.REPORTABLE EVENT 1.37 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10CFR Part 50 or 10CFR 72.75.SITE BOUNDARY 1.41 The SITE BOUNDARY shall be that line beyond which the land or property is neither owned, nor leased, nor otherwise controlled by the licensee.SOURCE CHECK 1.43 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

THERMAL POWER 1.47 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.UNRESTRICTED AREA 1.50 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.VENTILATION EXHAUST TREATMENT SYSTEM 1.51 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine and radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment.

Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

316 HOPE CREEK ODCM REV. 26 DEFINITIONS (Continued)

VENTING 1.52 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.TABLE 1.1: SURVEILLANCE FREQUENCY NOTATION NOTATION S D W M Q SA A R S/U P z FREQUENCY At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .At least once per 7 days.At least once per 31 days.At least once per 92 days.At least once per 184 days.At least once per 366 days.At least once per 18 months (550 days).Prior to each reactor startup.Prior to each radioactive release.During startup, prior to exceeding 30% of RATED THERMAL POWER, if not performed within the previous 7 days.Not applicable.

N.A.317 HOPE CREEK ODCM REV. 26 DEFINITIONS (Continued)

TABLE 1.2: OPERATIONAL CONDITIONS MODE SWITCH POSITION AVERAGE REACTOR COOLANT TEMPERATURE CONDITION 1. POWER OPERATION Run Any temperature Any temperature

2. STARTUP 3. HOT SHUTDOWN 4. COLD SHUTDOWN 5. REFUELING*

Startup/Hot Standby Shutdown#, Shutdowns'

,*Shutdown or Refuel *> 200°F" 200 0 F+< 140°F# The reactor mode switch may be placed in the Run, Startup/Hot Standby, or Refuel position to test the switch interlock functions and related instrumentation provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff. If the reactor mode switch is placed in the Refuel position, the one-rod-out interlock shall be OPERABLE.## The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Technical Specification 3.9.10.1.* Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.** See Special Test Exceptions Technical Specification sections 3.10.1 and 3.10.3.*** The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided that the one-rod-out interlock is OPERABLE.+ See Special Test Exception Technical Specification 3.10.8.318 HOPE CREEK ODCM REV. 26 PART I RADIOLOGICAL EFFLUENT CONTROLS SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS I I 319 HOPE CREEK ODCM REV. 26 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY CONTROLS 3.0.1 Compliance with the CONTROLS contained in the succeeding CONTROLS is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the CONTROLS, the associated ACTION requirements shall be met.3.0.2 Noncompliance with a CONTROL shall exist when the requirements of the CONTROL and associated ACTION requirements are not met within the specified time intervals.

If the CONTROL is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.3.0.3 When a CONTROL is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the CONTROL does not apply by placing it, as applicable, in: 1. At least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and 3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the CONTROL. Exceptions to these requirements are stated in the individual CONTROLS.This CONTROL is not applicable in OPERATIONAL CONDITION 4 or 5.3.0.4 Entry into an OPERATIONAL CONDITIONS or other specified condition shall not be made when the conditions of the CONTROLS are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval.

Entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual CONTROLS.3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing to demonstrate its OPERABILITY or the OPERABILITY of other equipment.

This is an exception to CONTROL 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

320 I HOPE CREEK ODCM REV. 26 APPLICABILITY (Continued)

SURVEILLANCE REQUIREMENTS I 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual CONTROLS unless otherwise stated in an individual Surveillance I Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a I maximum allowable extension not to exceed 25 percent of the specified surveillance interval.4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by CONTROL 4.0.2, shall constitute a failure to meet the OPERABILITY requirements for a CONTROL.The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowed outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement(s) associated with the CONTROLS have been performed within the applicable surveillance interval or as otherwise specified.

This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

I 32I HOPE CREEK ODCM REV. 26 3/4.3 INSTRUMENTATION 3/4.3.7.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.10 In accordance with Hope Creek Technical Specifications 6.8.4.g. 1, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their Alarm/Trip setpoints set to ensure that the limits of CONTROL 3.11.1.1 are not exceeded.

The Alarm/Trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).APPLICABILITY:

During all liquid releases via these pathways.ACTION: a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip setpoint less conservative than required by the above CONTROL, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1.

Exert best efforts to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release report why the inoperability was not corrected in a timely manner.c. The provisions of CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3.7.10-1.

322 HOPE CREEK ODCM REV. 26 TABLE 3.3.7.10-1:

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE INSTRUMENT ACTION 1. RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a. Liquid Radwaste Discharge Line to the Cooling Tower Blowdown Line b. Turbine Building Circulating Water Dewatering Sump Discharge Line to the Cooling Tower*1 1 110 110 2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a. Cooling Tower Blowdown Effluent 3. FLOW RATE MEASUREMENT DEVICES a. Liquid Radwaste Discharge Line to the Cooling Tower Blowdown Line b. Cooling Tower Blowdown Weir c. Turbine Building Circulating Water Dewatering Sump Discharge Line**1 111 1 N/A 112 112 N/A 323 m m m -m um mm m -m mm m = m -m m HOPE CREEK ODCM REV. 26 TABLE 3.3.7. 10-1 (Continued)

TABLE NOTATION ACTION 110 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release: a. At least two independent samples are analyzed in accordance with CONTROL 4.11.1.1.2, and b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving;Otherwise, suspend release of radioactive effluents via this pathway.ACTION 111 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for principal gamma emitters, 1-131, and dissolved and entrained noble gases at the lower limits of detection required in ODCM CONTROL Table 4.11.1.1.1-1..B, and the Surveillance Requirement 4.11.1.1.2 is performed.

Otherwise, suspend the release of radioactive effluents via this pathway.ACTION 112 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Pump performance curves generated in place may be used to estimate flow.See Appendix A for setpoint determination for the Turbine Building Circulating Water Dewatering Sump (TBCWDWS).

Different setpoints are established for this monitor based on its use for batch release or continuous release. Automatic termination of releases from the TBCWDWS is by trip of the sump pump(s). ACTION 110 only applies to batch releases for the TBCWDWS. Continuous releases are not authorized with the TBCWDWS radiation monitor inoperable.

There are no discharge process flow rate measurement devices for this pathway. Conservative assumptions are made for release rates. The maximum release rate from the sump is 100 gpm.This value should be used for setpoint calculations to determine compliance with CONTROL 3.11.1.1.

More realistic values may be used to calculate total activity released and dose consequences.

Actual values should be used if process flow measurement devices are installed.

324 HOPE CREEK ODCM REV. 26 TABLE 4.3.7.10-1:

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL INSTRUMENT CHECK SOURCE CHANNEL CHECK CALIBRATION CHANNEL FUNCTIONAL TEST 1. RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a. Liquid Radwaste Discharge Line to the Cooling Tower Blowdown Line b. Turbine Building Circulating Water Dewatering Sump Discharge Line to the Cooling Tower D D(5)P R(3)R(3)Q(1)Q(1)(6)M 2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a. Cooling Tower Blowdown Effluent 3. FLOW RATE MEASUREMENT DEVICES a. Liquid Radwaste Discharge Line to Cooling Tower Blowdown Line D M R(3)Q(2)D(4)D(4)N.A.N.A.R R Q Q b. Cooling Tower Blowdown Weir 325 mm -n---- -m m m m mm m-mmm m m -

HOPE CREEK ODCM REV. 26 TABLE 4.3.7.10-1 (Continued)

TABLE NOTATIONS (1) The CHANNEL FUNCTIONAL TEST shall demonstrate that automatic isolation of release from this pathway and control room alarm annunciation occur if any of the following conditions exist: 1. Instrument indicates measured levels at or above the Alarm/Trip setpoint, or 2. Circuit failure, or 3. Instrument indicates a downscale failure.(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels at or above the Alarm/Trip setpoint, or 2. Circuit failure, or 3. Instrument indicates a downscale failure.(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS)/National Institute of Standards and Testing (NIST) or using standards that have been obtained from suppliers that participate in assurance activities with NBS/NIST.

These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration or are NBSiNIST traceable shall be used.(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.(5) In addition to performing channel check on rad monitor, PERFORM: CHANNEL CHECK -daily, including verification of sample flow through the radiation monitor during sump pump operation.

(6) Isolation is demonstrated by securing the discharge pump during the functional check 326 HOPE CREEK ODCM REV. 26 3/4.3 INSTRUMENTATION 3 3/4.3.7.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS-i 3.3.7.11 In accordance with Hope Creek Technical Specifications 6.8.4.g.1, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of CONTROLS 3.11.2.1 are not exceeded.

The alarm/trip setpoints of these channels meeting CONTROLS 3.11.2.1 shall 3 be determined and adjusted in accordance with the methodology and parameters in the ODCM.APPLICABILITY:

As shown in Table 3.3.7.11-1 3 ACTION: 3 a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above CONTROL, immediately suspend the release of radioactive gaseous effluents monitored by the I affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1.

Exert best efforts to return the instrument to OPERABLE status I within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to CONTROL 6.9.1.7 why this inoperability was not corrected in a timely manner.c. The provisions of CONTROLS 3.0.3 are not applicable.

3 SURVEILLANCE REQUIREMENTS 3 4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.11-1.

327 m m m m -mmm ummm mmm m mm m HOPE CREEK ODCM REV. 26 TABLE 3.3.7.11-1:

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT

1. DELETED 2. FILTRATION, RECIRCULATION AND VENTILATION MONITORING SYSTEM a. Noble Gas Activity Monitor b. Iodine Sampler c. Particulate Sampler d. Flow Rate Monitor e. Sampler Flow Rate Monitor 3. SOUTH PLANT VENT MONITORING SYSTEM a. Noble Gas Activity Monitor b. Iodine Sampler c. Particulate Sampler d. Flow Rate Monitor e. Sampler Flow Rate Monitor OPERABLE APPLICABILITY ACTION 1 1 1 1 1*****123 125 125 122 122 123 125 125 122 122 1 1 1 1 1*****328 HOPE CREEK ODCM REV. 26 TABLE 3.3.7.11-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT

4. NORTH PLANT VENT MONITORING SYSTEM a. Noble Gas Activity Monitor b. Iodine Sampler c. Particulate Sampler d. Flow Rate Monitor e. Sampler Flow Rate Monitor OPERABLE APPLICABILIT Y ACTION Y 1 1 1 1 1***123 125 125 122 122**329 M m M m m m m m m -M ý m M M M m m HOPE CREEK ODCM REV. 26 TABLE 3.3.7.11-1 (Continued)

TABLE NOTATION*At all times ACTION 122 -ACTION 123 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .Otherwise, suspend release of radioactive effluents via this pathway.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for principal gamma emitters (noble gases) at the lower limits of detection required in ODCM CONTROL Table 4.11.2.1.2-l.A or B within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, suspend release of radioactive effluents via this pathway.ACTION 124 -DELETED ACTION 125 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months samples are continuously collected with auxiliary sampling equipment as required in Table 4.11.2.1.2-1.

HOPE CREEK ODCM REV. 26 TABLE 4.3.7.11-1:

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL INSTRUMENT CHECK SOURCE CHANNEL CHECK CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVIELLANCE REOUIRED 1. DELETED 2. FILTRATION, RECIRCULATION AND VENTILATION MONITORING SYSTEM a. Noble Gas Activity Monitor b. Iodine Sampler c. Particulate Sampler d. Flow Rate Monitor e. Sampler Flow Rate Monitor 3. SOUTH PLANT VENT SYSTEM a. Noble Gas Activity Monitor b. Iodine Sampler c. Particulate Sampler d. Flow Rate Monitor e. Sampler Flow Rate Monitor D W W D D M N.A.N.A.N.A.N.A.R(2)N.A.N.A.Q(1)N.A.N.A.*****R R Q Q D W W D D M N.A.N.A.N.A.N.A.R(2)N.A.N.A.Q(1)N.A.N.A.*****R R Q Q 331 m =m- ý= m -m = M -M mm M m m HOPE CREEK ODCM REV. 26 TABLE 4.3.7.1 -1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL INSTRUMENT CHECK CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CALIBRATION TEST MODES IN WHICH SURVIELLANCE REOUIRED 4. NORTH PLANT VENT SYSTEM a. Noble Gas Activity Monitor b. Iodine Sampler c. Particulate Sampler d. Flow Rate Monitor e. Sampler Flow Rate Monitor D W W D NM N.A.N.A.N.A.N.A.R(2)N.A.N.A.Q(l)N.A.N.A.*****R R Q Q D 332 HOPE CREEK ODCM REV. 26 3 TABLE 4.3.7.11-1 (Continued)

TABLE NOTATION I* At all times 3 (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that the control room alarm annunciation occurs if any of the following conditions exist: 3 1. Instrument indicates measured levels above the alarm setpoint.2. Circuit failure.3. Instrument indicates a downscale failure. 3 (2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS)/National Institute 3 of Standards and Testing (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS/NIST.

These standards shall permit calibrating the system over its intended range of energy and measurement range. For I subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration or are NBS/NIST traceable shall be used.I I I I I I I I 333 I HOPE CREEK ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION CONTROLS 3.11.1.1 In accordance with the Hope Creek Technical Specifications 6.8.4.g.2 and 3, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (See Figure 5.1.1.1-1) 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 2 x 10-4 microcuries/ml.

APPLICABILITY:

At all times.ACTION: With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program in Table 4.11.1.1.1-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of CONTROL 3.11.1.1.334 HOPE CREEK ODCM REV. 26 TABLE 4.11.1.1.1-1:

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)(a)Type Frequency Frequency Analysis (itCi/ml)A. Batch Waste P P 1) Release(b)

Each Batch Each Batch Principal Gamma Sample Emitters(C) 5x 10-7 Tanks 1-131 lx10-6 2) Turbine Building P M Dissolved and Circulating Water One Entrained Gases Ix10-5 Dewatering Sump Batch/M (Gamma Emitters)when released in p M H-3 Batch Mode* Each Batch Composite(d) 105 Gross Alpha lO0 7 P Q Sr-89, Sr-90 Each Batch Composite(d) 5x10 8 Fe-55 B. Continuous M Principal Gamma Releases(e)

N/A Composite Emitters(c) 5x 10-7 1) Station Service Water System (SSWS) (If contaminated as indicated by SACS 1-131 or RACS system) lx10-6 2) Turbine Building W** M Dissolved and Circulating Water Grab Entrained Gases 1x 1-Dewatering Sump* Sample NA M )H-3 5 Composite (d)Gross Alpha 1x10-7 NA Q Sr-89, Sr-90 5x10 8 Composite (d)Fe-55 lxl0-6 I I U I I I I I I I I I I I I I I I 335 HOPE CREEK ODCM REV. 26 TABLE 4.11.1.1.1-1 (Continued)

TABLE NOTATION a. The LLD is defined, for purposes of these CONTROLS as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:

LLD= 4.66o Sb E e V 9 2.22E6

Y o exp (-AAt)Where: LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, 4.66 is the statistical factor from NUREG 1302 Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, X is the radioactive decay constant for the particular radionuclide (sec'), and At for plant effluents is the elapsed time between midpoint of sample collection and time of counting (sec).Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

336 HOPE CREEK ODCM REV. 26 TABLE 4.11.1.1.1-1 (Continued) i TABLE NOTATION I b. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.c. The principal gamma emitters for which the LLD CONTROL applies exclusively are: Mn- 3 54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an LLD of 5 x 10-6. This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, together with the above nuclides, shall i also be analyzed and reported in the Radioactive Effluent Release Report pursuant to CONTROL 6.9.1.7.d. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.e. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of a system that has an input flow during the continuous release.* The Turbine Building Circulating Water Dewatering Sump is a normal radwaste discharge i pathway and is monitored as such because of possible contamination from the Turbine Building Ventilation drains. Securing the sump pump provides discharge termination.

Siphoning does not occur do to the differential height between the sump and the discharge point. Releases from the I TBCWDS below the setpoint of 2X background are considered continuous releases.

Sampling of continuous releases is performed using a continuous composite sampler. Samples for analyses required in Table 4.11.1.1.1-1 for continuous releases are obtained from the composite sampler. I Releases from the sump at levels at or above 2x background may be performed as batch releases.Samples for analyses required in Table 4.11 .1.1.1-1 for batch releases are obtained from the sump. 3** The grab sample from the Turbine Building Circulating Water Dewatering Sump for dissolved and entrained noble gases is required Monthly from the composite sampler. 3 337 HOPE CREEK ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.2 DOSE CONTROLS 3.11.1.2 In accordance with Hope Creek Technical Specifications 6.8.4.g.4 and 5, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1.1-1) shall be limited: a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.APPLICABILITY:

At all times.ACTION: a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.b. The provisions of CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.338 HOPE CREEK ODCM REV. 26 1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.3 LIQUID WASTE TREATMENT SYSTEM I CONTROLS 3 3.11.1.3 In accordance with the Hope Creek Technical Specifications 6.8.4.g.6, the liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system shall be used to I reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1.1-1)would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any 31-day period. 3 APPLICABILITY:

At all times.ACTION: I a. With radioactive liquid waste being discharged and in excess of the above limits and any portion of the liquid Radwaste treatment system not in operation, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

3 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the I inoperability, 2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3 3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of CONTROL 3.0.3 are not applicable.

I SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall I be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM. 3 4.11.1.3.2 The installed liquid Radwaste treatment system shall be demonstrated OPERABLE by meeting CONTROLS 3.11.1.1 and 3.11.1.2.

3 339 HOPE CREEK ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE CONTROLS 3.11.2.1 In accordance with the Hope Creek Technical Specifications 6.8.4.g.3 and 7, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1.1-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and b. For iodine-13 1, iodine- 133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.APPLICABILITY:

At all times.ACTION: With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s).SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined continuously to be within the above limits in accordance with the methodology and parameters in the ODCM.4.11,2.1.2 The dose rate due to iodine- 131, iodine- 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11.2.1.2-1.

340 HOPE CREEK ODCM REV. 26 TABLE 4.11.2.1.2-1:

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Gaseous Release Sampling Analysis Type of Activity (LLD)(a)Type Frequency Frequency Analysis ([LCi/ml)A. Containment P P Principal Gamma lx104 PURGE Each PURGE(C) Each PURGE(c) Emitters(b) a Grab Sample P H-3 (oxide) 1x10.6 B. North Plant Vent M(c), (d) Principal Gamma lx104 South Plant Vent Grab Sample M(C) Emitters(b)

FRVS (g)H-3 (oxide) lx10.6 C. All Release Continuous(e)

W(f)Types as Charcoal 1-131 1x10'-2 listed in A Sample and B above Continuous(e)

Principal Gamma Particulate Emitters(b) lx10i Sample Continuous(e)

Q Gross Alpha 1x10-11 Composite Particulate Sample Continuous(e)

Q Sr-89, Sr-90 lx10-l" Composite Particulate Sample Continuous(e)

Noble Gas Noble Gasses lx10-6 Monitor Gross Beta or Gamma U I I I I I I I U I I I U I I I I I I 341 HOPE CREEK ODCM REV. 26 TABLE 4.11.2.1.2-1 (Continued)

TABLE NOTATION a. The LLD is defined in Table 4.11.1.1.1-1

b. The principal gamma emitters for which the LLD CONTROL applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate emissions, This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to CONTROL 6.9.1.7.c. Sampling and analysis shall also be performed following shutdown, startup or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period.This requirement does not apply if: 1. Analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of three; and 2. The noble gas monitor shows that effluent activity has not increased by more than a factor of three.d. Tritium grab samples shall be taken at least once per 7 days from the spent fuel pool area, whenever fuel is in the spent fuel pool.e. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with CONTROLS 3.11.2.1, 3.11.2.2 and 3.11.2.3.f. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased by more than a factor of three.g. Table 4.11.2.1.2-1, Notations "c", and "f' do not apply. Monthly samples for principle gamma emitters and tritium are required only if the FRVS Vent Fan(s) is in service greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . For noble gas and tritium, representative samples of Reactor Building may be obtained for compliance in lieu of skid samples. FRVS continuous samples required when FRVS Vent Fan(s) is in service for greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .342 HOPE CREEK ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.2 DOSE -NOBLE GASES CONTROLS 3.11.2.2 In accordance with the Hope Creek Technical Specification 6.8.4.g.5 and 8, the air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1.1-1) shall be limited to the following:

a. 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, b. 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.

APPLICABILITY:

At all times.ACTION: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.b. The provisions of CONTROLS 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.343 HOPE CREEK ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.3 DOSE -IODINE- 131, IODINE- 133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS 3.11.2.3 In accordance with Hope Creek Technical Specification 6.8.4.g.5 and 9, the dose to a MEMBER OF THE PUBLIC from iodine-13 1, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1.1-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, b. During any calendar year: Less than or equal to 15 mrem to any organ.APPLICABILITY:

At all times.ACTION: a. With the calculated dose from the release of iodine-13 1, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.b. The provisions of CONTROLS 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine- 131, iodine- 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.344 HOPE CREEK ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.4 GASEOUS RADWASTE TREATMENT CONTROLS 3.11.2.4 In accordance with Hope Creek Technical Specifications 6.8.4.g.6, the GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.

APPLICABILITY:

Whenever the main condenser steam jet air ejector is in operation.

ACTION: a. With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 7 days, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS I I I I I I I 1 I I I I I 4.11.2.4 The readings of the relevant instruments shall be checked every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the main condenser air ejector is in use to ensure that the gaseous radwaste treatment system is functioning.

345 HOPE CREEK ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.5 VENTILATION EXHAUST TREATMENT CONTROLS 3.11.2.5 In accordance with Hope Creek Technical Specifications 6.8.4.g.6, the VENTILATION EXHAUST TREATMENT SYSTEM for the Reactor Building and the Service and Radwaste Building shall be OPERABLE and the appropriate portions of the system shall be used to reduce release of radioactivity when the projected dose in 31 days due to gaseous effluent releases from each unit to areas at and beyond the SITE BOUNDARY (see Figure 5.1.1-1), would exceed: a. 0.2 mrad to air for gamma radiation, or b. 0.4 mrad to air for beta radiation, or c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC APPLICABILITY:

At all times.ACTION: a. With radioactive ventilation exhaust being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report.that includes the following information:

1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of CONTROLS 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM, when the VENTILATION EXHAUST TREATMENT SYSTEM is not being fully utilized.4.11.2.5.2 The installed VENTILATION EXAUST TREATMENT SYSTEM shall be considered OPERABLE by meeting CONTROLS 3.11.2.1, 3.11.2.2, and 3.11.2.3.346 HOPE CREEK ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.8 VENTING OR PURGING CONTROLS 3.11.2.8 VENTING or PURGING of the Mark I containment drywell shall be through either the reactor building ventilation system or the filtration, recirculation and ventilation system.*APPLICABILITY:

whenever the containment is vented or purged.ACTION: a. With the requirements of the above CONTROL not satisfied, suspend all VENTING and PURGING of the drywell.b. The provisions of CONTROL 3.0.3 are not applicable.

SURVEILLAINCE REQUIREMENTS 4.11.2.8 The containment shall be determined to be aligned for VENTING or PURGING through either the reactor building ventilation system, the filtration, recirculation and ventilation system, or the hardened torus vent within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to the start of and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING or PURGING of the drywell.* Following Type A Integrated Leakage Rate Testing, the Mark I containment drywell may be vented through the hardened torus vent.I I I I I I I I I I I I I I I I I I I 347 HOPE CREEK ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 In accordance with Hope Creek Technical Specification s 6.8.4.g. 11, 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 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.APPLICABILITY:

At all times ACTION: a. With the calculated doses from the release of radioactive materials in liquid- or gaseous effluents exceeding twice the limits of CONTROLS 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b, calculations should be made including direct radiation contributions from the units and including outside.storage tanks, etc.to determine whether the limits of CONTROL 3.11.4 have been exceeded.

If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 or 10 CFR 72.104 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190 and 10 CFR 72.104. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.b. The provisions of CONTROLS 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with CONTROLS 4.11.1.2, 4.11.2.2, 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units including outside storage tanks, etc. shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in CONTROL 3.11.4, ACTION a.348 HOPE CREEK ODCM REV. 26 3 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 1 3.12.1. In accordance with Hope Creek Technical Specifications 6.8.4.h.1, the radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.APPLICABILITY:

At all times.ACTION: a. With the radiological environmental monitoring program not being conducted as U specified in Table 3.12.1-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 6.9.1.6, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental i sampling medium at a specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of CONTROLS 3.11.1.2, 3.11.2.2, and 3.11.2.3.

When more than one of the-radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if: 3 concentration (1) + concentration (2) +... > 1.0I reportinglevel (1) reportinglevel (2)When radionuclides other than those in Table 3.12.1-2 are detected and are the result I of plant effluents, this report shall be submitted if the potential annual dose* to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of CONTROLS 3.11.1.2, 3.11.2.2, and 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.6.*The methodology used to estimate the potential annual dose to a MEMBER OF THE PUBLIC I shall be indicated in this report.349 HOPE CREEK ODCM REV. 26 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS (Continued)

ACTION: (Continued)

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12.1-1, identify specific locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to CONTROL 6.9.1.7, identify the cause of the unavailability of samples and the new location(s) for obtaining replacement samples in the next Radioactive Effluent Release Report pursuant to CONTROL 6.9.1.7 and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

d. The provisions of CONTROLS 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12. 1-1 from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12.1-1, and the detection capabilities required by Table 4.12.1-1.350 HOPE CREEK ODCM REV. 26 TABLE 3.12.1-1 : RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *EXPOSURE PATHWAY NUMBER OF REPRESENTAIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION OF ANALYSIS LOCATIONS (1) FREQUENCY 1. DIRECT RADIATION (2)Forty-nine routine monitoring stations with two or more dosimeters placed as follows: Quarterly Gamma dose quarterly An inner ring of stations one in each land based meteorological sector (not bounded by water) in the general area of the SITE BOUNDARY;An outer ring of stations, one in each land-based meteorological sector in the 5 to 11 -km range from the site (not bounded by or over water); and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.*The number, media, frequency, and location of samples may vary from site to site. This table presents an acceptable minimum program for a site at which each entry is applicable.

Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an individual's dose and should be included in the sample program.

= M M M M m = m m m = = m m m = = m -HOPE CREEK ODCM REV. 26 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTAIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION OF ANALYSIS LOCATIONS

() FREQUENCY 2. AIRBORNE Radioiodine and Particulates Samples from 7 locations:

Continuous sampler operation with sample collection weekly or more frequently if required by dust loading.Radioiodine Canister 1-131 analysis weekly.Five (5) Samples -Two samples from close to the SITE BOUNDARY location and Three (3) samples in land based sectors of a high calculated annual average ground D/Q One sample from the vicinity of a community having a high calculated annual average ground- level D/Q;and One sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction.

Particulate Sampler Gross beta radioactivity analysis following filter change (3);Gamma isotopic analysis(4) of composites (by location)quarterly.

352 HOPE CREEK ODCM REV. 26 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTAIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION OF ANALYSIS LOCATIONS (1) FREQUENCY 3. WATERBORNE

a. Surface(5)

b. Ground c. Drinking (10)d. Sediment One sample upstream.One sample downstream One sample outfall One sample cross-stream Samples from one or two sources only if likely to be affected(7).One sample of the nearest water supply affected by its discharge One sample from downstream area One sample from cross-stream area One sample from outfall area One sample from upstream area One sample from a control location One sample from shoreline area One sample from Cooling Tower Blowdown Monthly Grab sample monthly Composite sample over two-week period(6) when I-131 analysis is performed; monthly composite otherwise.

Semiannually Gamma isotopic analysis(4) monthly. Composite for tritium analysis quarterly.

Gamma isotopic analysis(a) monthly and tritium analysis quarterly.

1- 131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year .Composite for gross beta and gamma isotopic analysis(4) monthly Composite for tritium analysis quarterly Gamma isotopic analysis(4) semiannually

= = = m m ---M mm m m m m m -m m-m mm-m -m m m m -m m m m -m m HOPE CREEK ODCM REV. 26 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTAIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION OF ANALYSIS LOCATIONS (1) FREQUENCY 4. INGESTION a. Milk Samples from milking animals in three locations within 5 km distance having the highest dose potential.

If there are none, then, one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr8)One sample from milking animals at a control location 15 to 30 km distant.One sample of each commercially and recreationally important species in vicinity of plant discharge area One sample of same species in area not influenced by plant discharge.

Semimonthly when animals are on pasture, monthly at other time Gamma isotopic (4) and 1- 131 analysis semi-monthly when animals are on pasture; monthly at other times b. Fish and Invertebrates Sample in season, or semiannually if they are not seasonal Gamma isotopic analysis(4) on edible portions.354 HOPE CREEK ODCM REV. 26 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE REPRESENTAIVE COLLECTION OF ANALYSIS SAMPLES AND SAMPLE FREQUENCY LOCATIONS (1)c. Food Products One sample of each principal class of food products from any area that is irrigated by water in which liquid plant wastes have been discharged At time of harvest (9)Gamma isotopic analysis (4) on edible portion.= =m = M M M = M = M M = M HOPE CREEK ODCM REV. 26 TABLE 3.12.1-1 (Continued)

TABLE NOTATIONS (11) Specific parameters of distance and direction sector from the midpoint of a line between the center of the Salem units 1 & 2 containment domes and additional description where pertinent, shall be provided for each and every sample location in Table 3.12.1 -1 in a table and figure(s) in the ODCM. Refer to NUREG-0 133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Reg. Guide 4.8 as amended by Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.931.6. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Pursuant to CONTROL 6.9.1.7, submit in the next Radioactive Effluent Release Report documentation for a change in the ODCM including revised figure(s)and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for the pathway and justifying the selection of the new location(s) for obtaining samples.(12) One or more instruments, such as pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.

For the purposes of this table, a Dosimeter of Legal Record (DLR) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.

Film badges shall not be used for measuring direct radiation.

The frequency of analysis or readout for dosimetry systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. No direct radiation monitoring stations are located in the inner ring sectors 8, 9, 12, 13 and 14 and the outer ring sector 8 as originally determined during plant licensing and as permitted by Reg. Guide 4.8 as amended by The Branch Technical Position Revision 1, November 1979. Sector 7 does not have a direct radiation monitoring station in the outer ring due to inaccessibility.

(13) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.(14) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.356 HOPE CREEK ODCM REV. 26 TABLE 3.12.1-1 (Continued)

TABLE NOTATIONS (15) The "upstream sample" shall be taken at a distance beyond significant influence I of the discharge.

The "downstream" sample shall be taken in an area beyond but near the mixing zone. "Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence.

Saltwater shall be sampled only when the receiving water is utilized for recreational activities.

(16) A composite sample is one in which the quantity (aliquot) of liquid sampled is U proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program, 3 composite sample aliquots shall be collected at time intervals that are very short relative, to the compositing period in order to assure obtaining a representative sample.(17) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(18) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM. Additionally, 2 sample locations are monitored as management audit., Broad leaf vegetation may be obtained in lieu of milk collections.

(19) If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products.

The Delaware I River at the location of Salem and Hope Creek Nuclear Power Plants is a brackish water source. No irrigation of food products is performed using water in the vicinity from which liquid plant wastes have been discharged.

However, 12 management audit food I samples are collected from various locations.

(20) No groundwater samples are required as liquid effluents discharged from Salem and m Hope Creek Generating Stations do not directly affect this pathway. However for management audit, one raw and one treated ground water sample from the nearest unaffected water supply is required.357 m = M M m -M m m M M = M -M M -m HOPE CREEK ODCM REV. 26 TABLE 3.12.1-2:

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS Water Airborne Particulate Fish Milk Food Products Analysis (pCi/1) or Gases (pCi/m3) (pCi/Kg, wet) (pCi/1) (pCi/Kg, wet)H-3 3 x 10 4 Mn-54 1 x 103 3 x 104 Fe-59 4 x 10 2 1 x 10 4 Co-58 1 x 103 3 x 104 Co-60 3 x 102 1 X 104 Zn-65 3 x 10 2 2 x 10 4 Zr-Nb-95 4 x 102 1-131 2* 0.9 3 1 x 10 2 Cs-134 30 10 1 x 10 3 60 1 x 10 3 Cs-137 50 20 2 x 10 3 70 2 x 10 3 Ba-La-140 2 x 102 3 x 102*For drinking water samples. This is a 40 CFR Part 141 value. If no drinking water pathway exists, a value of 20 pCi/1 may be used.358 HOPE CREEK ODCM REV. 26 TABLE 4.12.1-1:

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIStu'

'2)LOWER LIMITS OF DETECTION (LLD) (3)Water Airborne Particulate Fish Milk Food Products Sediment Analysis (pCi/1) or Gases (pCi/m3) (pCi/Kg, wet) (pCi/1) (pCi/Kg, wet) (pCi/Kg, dry)gross 4 0.01 beta H-3 3000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1* 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15*LLD for drinking water samples. If no drinking water pathway exists, a value of 10 pCi/1 may be used.M m -MM --m -M -m m --m -

HOPE CREEK ODCM REV. 26 TABLE 4.12.1-1 (Continued)

TABLE NOTATIONS (4) This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.6.(5) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide: 4.13.(6) The LLD is defined, for purposes of these CONTROLS as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probabilitywith only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:

LLD~ -4.66o Sb E

V

2.22E6 o Y o exp (-'At)Where: LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume, 4.66 is the statistical factor from NUREG 13021 Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, X is the radioactive decay constant for the particular radionuclide (sec-1), and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting (sec).Typical values of E, V, Y, and At should be used in the calculation.

360 HOPE CREEK ODCM REV. 26 U TABLE 4.12.1- 1 (Continued)

TABLE NOTATIONS It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as :an a posteriori (after the fact)limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.

Occasionally background fluctuations, unavoidable small sample sizes the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.6. 3 3 I I I I I I I I I U 361 3 HOPE CREEK ODCM REV. 26 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2. In accordance with the Hope Creek Technical Specifications 6.8.4.h.2, a land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m 2 (500 ft 2) producing broad leaf vegetation.

APPLICABILITY:

At all times.ACTION: a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in CONTROL 4.11.2.3, identify the new location(s) in the next Radioactive Effluent Release Report, pursuant to CONTROL 6.9.1.7.b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with CONTROL 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

Pursuant to CONTROL 6.9.1.7, identify the new location(s) in the next Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

c. The provisions of CONTROLS 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing Season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, visual survey, aerial survey, or by consulting local agriculture authorities.

The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.6.*Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Q's in lieu of the garden census. CONTROLS for broadleaf vegetation sampling in Table 3.12.1-1, Part 4.c shall be followed, including analysis of control samples.362 HOPE CREEK ODCM REV. 26 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 In accordance with Hope Creek Technical Specifications 6.8.4.h.3, analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program.I U I I I I I I APPLICABILITY:

At all times.ACTION: a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.6.b. The provisions of CONTROLS 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS I 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.6.363 I I I I i I, I i I I HOPE CREEK ODCM REV. 26 BASES FOR SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS NOTE The BASES contained in the succeeding pages summarize the reasons for the CONTROLS of Sections 3.0 and 4.0, but are not considered a part of these CONTROLS.364 HOPE CREEK ODCM REV. 26 3/4.3 INSTRUMENTATION BASES 3/4.3.7.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.3/4.3.7.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM. This will ensure the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.365 HOPE CREEK ODCM REV. 26 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This CONTROL is provided to ensure that 'the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 11, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section Il-A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.106(a) to the population.

The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in Currie, L. A., "Lower Limit of Detection:

Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and the HASL Procedures Manual, HASL-300 (revised annually).

3/4.11.1.2 DOSE This CONTROL is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The CONTROL implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for freshwater sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirementsý of 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purposes of Implementing Appendix I," April 1977.366 HOPE CREEK ODCM REV. 26 RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID RADWASTE TREATMENT The OPERABILITY of the liquid Radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to their release to the environment.

The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable".

This CONTROL implements the requirements of General Design Criterion 60 of Appendix A to. 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth the Section ,II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This CONTROL is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, table II, Column I. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 [ 10 CFR Part 20.106(b)].

For MEMBERS OF THE PUBLIC who may at times be, within the SITE BOUNDARY, the occupancy of the individual will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

Examples of calculations for such MEMBERS OF THE PUBLIC with the appropriate occupancy factors shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year.

3 The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in Currie, L. A., "Lower Limit of Detection:

Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and the HASL Procedures Manual, HASL-300 (revised annually).

3 367 HOPE CREEK ODCM REV. 26 RADIOACTIVE EFFLUENTS BASES 3/4.11.2.2 DOSE -NOBLE GASES This CONTROL is provided to implement the requirements of Section II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The CONTROL implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October 1977 and Regulatory.

Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

3/4.11.2.3 DOSE -IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM This CONTROL is provided to implement the requirements of Section II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The CONTROLS are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRERSTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate controls for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-life greater than 8 days are dependent on the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY.

The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.368 HOPE CREEK ODCM REV. 26 RADIOACTIVE EFFLUENTS 3 BASES 3/4.11.2.4 AND 3/4.11.2.5 GASEOUS RADWASTE TREATMENT AND VENTILATION EXHAUST U TREATMENT The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION I EXHAUST TREAMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This CONTROL implements the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate U portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

3/4.11.2.8 VENTING OR PURGING This CONTROL provides reasonable assurance that releases from drywell venting or purging operations will not exceed the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. I 3/4.11.4 TOTAL DOSE 3 This CONTROL is provided to meet the dose limitations of 40 CFR Part 190 that have now been incorporated into 10 CFR Part 20 by 46 FR 18525 as well as the dose limitations, specific to Independent Spent Fuel Storage Installation (ISFSI) operations in accordance with 10 CFR 72.104. Over the long term, as more storage casks are placed on the ISFSI pads, it is expected that ISFSI operations will become the prominent contributor to the dose limits in this section. ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. The P SEG 10 CFR 72.212 Report prepared in accordance with 10 CFR 72 requirements I assumes a certain array of casks exists on the pads. The dose contribution from this array of casks in combination with historical uranium fuel cycle operations prior to ISFSI operations was analyzed to be within the 40 CFR 190 and 10 CFR 72.104 limits. The CONTROL requires the preparation and submittal of a Special 3 Report whenever the calculated doses from plant including the ISFSI radioactive effluents exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units including outside storage tanks, etc. are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 or 10 CFR 72.104 limits. For purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.

If the dose to any MEMBER OF THE PUBLIC is estimate~d to exceed the requirements of 40 CFR Part 190 or 10 CFR 72.104, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 or 10 CFR 72.104 have not already been corrected), in accordance with the provisions of I 40 CFR Part 190 or 10 CFR 72.104 and 10 CFR Part 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 or 10 CFR 72.104 until NRC staff action is completed.

The variance only relates to the limits of 40 CFR Part 190 or 10 CFR 72.104, and does not apply in any way to the other 3 requirements for dose limitation of 10 CFR Part 20, as addressed in CONTROLS 3.11.1.1 and 3.11.2.1.

An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 3 369 HOPE CREEK ODCM REV. 26 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological environmental monitoring program required by this CONTROL provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation.

This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.Guidance for this monitoring program is provided by the Reg. Guide 4.8 as amended by Radiological Assessment Branch Position on Environmental Monitoring, Revision 1, and November 1979. The initially specified monitoring program will be effective for at least the first three years of commercial operation.

Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4.12. 1-1 are considered optimum for routine environmental measurements in industrial laboratories.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits can be found in Currie, L. A., "Lower Limit of Detection:

Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and the HASL Procedures Manual, HASL-300 (revised annually).

3/4.12.2 LAND USE CENSUS This CONTROL is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey, from visual survey or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: 1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m 2.370 HOPE CREEK ODCM REV. 26 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.371 HOPE CREEK ODCM REV. 26 SECTION 5.0 DESIGN FEATURES 372 HOPE CREEK ODCM REV. 26 5.0 DESIGN FEATURES U (Provided FOR INFORMATION ONLY. Technical Specifications Section 5.0 is controlling.)

5.1 SITE MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 5.1.1 Information regarding radioactive gaseous and liquid effluents which will allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figure 5.1.1-1.3 1 I I I I I I I I I I I 373 I

=m mm m= =m m =m= m =m ==m=UNRESTRICTED AREA (PROPERTY OF U.S. GOVERNMENT)

.I." -,, p.N I I I* 1 0 COOLING TOWER NUCLEAR ADMINISTRATION BUILDING ii d N SECURITY FENCE i .---. --------/~ '.'SWITCH YARD I SITE BOUNDARY-3 Si' HOPE CREEK2 t1 HSECURITY PROCESSING H] CENTER TECENTER SALEM"I.1 N0.2 SWITCH YARD NC,1 METEOROLOGICAL

.,, NO. I1_ TOWER* FEED WATER &I, CIRC. WATER INTAKE "\*,',STRUCTURE,,...., ... .._ ....~Jm 0 z 0-r 0"0 0 rrl DELAWARE RIVER HOPE CREEK ODCM REV. 26 6.0 ADMINISTRATIVE CONTROLS 3 6.9.1.6 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 In accordance with Hope Creek Technical Specifications 6.9.1.6, The Annual Radiological Environmental Operating Report* covering the operation of the unit during the previous calendar year, shall be submitted prior to May 1 of each year.The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report I period, including a comparison with preoperational studies, with operational controls (as appropriate), and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by I CONTROL 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem. 3 The Annual Radiological Environmental Operating Reports shall include summarized and tabulated results in the format of Reg. Guide 4.8 as amended by Radiological Assessment Branch Technical Position, Revision 1, November 1979, for all of the radiological environmental samples taken during the report period pursuant to the table and figures in the environmental radiation section of the ODCM.Deviations from the sampling program identified in CONTROL 3.12.1 shall be reported.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. 3 The reports shall also include the following:

a summary description of the radiological environmental monitoring program; at least two legible maps, one covering sampling locations near the SITE BOUNDARY and a second covering the more distant locations, all keyed to a table giving distances and I directions from midpoint of a line between the center of the Salem units 1& 2 containment domes.; the results of licensee participation in the Interlaboratory Comparison Program, as required by CONTROL 3.12.3 and discussion of all analyses in which the LLD required by Table 4.12.1-1 was not achieved.The report shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of Technical Specification 3.4.5. The following information shall be included:

(1)Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2)Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the 3 limit was exceeded; (4) Graph of the 1- 131 per gram as a function of time for the duration of the specific activity of the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the limit. 3 A single submittal may be made for a multiple unit site. The submittal should combine those sections that are common to all units at the site.375 HOPE CREEK ODCM REV. 26 6.0 ADMINISTRATIVE CONTROLS 6.9.1.7 RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.7 In accordance with Hope Creek Technical Specifications 6.9.1.7, The Annual Radioactive Effluent Release Report* covering the operation of the unit, shall be submitted by May 1 of each year and in accordance with the requirements of 1 OCFR50.36a.

The Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21."Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.The Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.

The report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1.1-1) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. The historical annual average meteorology or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).The Radioactive Effluent Release Report shall identify those radiological environmental sample parameters and locations where it is not possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In addition, the cause of the unavailability of samples for the pathway and the new location(s) for obtaining replacement samples should be identified.

The report should also include a revised figure(s) and table(s) for the ODCM reflecting the new location(s).

The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation and 10 CFR 72.104 Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period: a. Container volume, b. Total curie quantity (specify whether determined by measurement or estimate), c. Principal radionuclides (specify whether determined by measurement or estimate), d. Type of waste (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms), e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

376 HOPE CREEK ODCM REV. 26 ADMINISTRATIVE CONTROLS 1 6.9.1.7 RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Radioactive Effluent Release Report

shall include a list of descriptions of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.The Radioactive Effluent Release Report shall include any changes made during the reporting period to 3 the PROCESS CONTROL PROGRAM (PCP), the OFFSITE DOSE CALCULATION MANUAL (ODCM), or radioactive waste systems. Also list new locations identified by the land use census pursuant to CONTROL 3.12.2. for dose calculations or environmental monitoring.

~I* A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.I N I I I I I I I I 377 1 HOPE CREEK ODCM REV. 26 ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.15.1 Licensee initiated major changes to the radioactive waste system (liquid, gaseous and solid): 1. Shall be reported to the Commission in the UFSAR for the period in which the evaluation was reviewed by the Plant Operations Review Committee (PORC). The discussion of each change shall contain: a. A summary of the evaluation that led to the determination that the change could be made in accordance with 1OCFR50.59;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;e. An evaluation of the change, which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;g. An estimate of the exposure to plant operating personnel as a result of the change; and h. Documentation of the fact that the change was reviewed and found acceptable by the PORC.2. Shall become effective upon review and acceptance by the PORC.378 HOPE CREEK ODCM REV. 26 PART II -CALCULATIONAL METHODOLOGIES I I I I I I I I U I I I I I 1 I I 379 HOPE CREEK ODCM REV. 26 1.0 LIQUID EFFLUENTS 1.1 Radiation Monitoring Instrumentation and Controls The liquid effluent monitoring instrumentation and controls at Hope Creek for controlling and monitoring normal radioactive material releases in accordance with the Hope Creek Radiological Effluent Technical Specifications are summarized as follows: (1) Alarm (and Automatic Termination)

-Liquid Radwaste Discharge Line Monitor provides the alarm and automatic termination of liquid (RE4861) radioactive material releases from the liquid waste management system as required by CONTROL 3.3.7.10.Circulating Water Dewatering Sump Discharge Monitor (RE4557) provides alarm and automatic termination of liquid radioactive releases from the circulating dewatering sump as required by CONTROL 3.3.7.10.

Condensation drains from certain supply ventilation units and liquids from the fill and venting of the circulating water side of the condenser waterboxes are directed to this sump. Automatic termination is performed by trip of the sump pumps on high gamma radiation signal.(2) Alarm (Only) -The Cooling-Tower Blowdown Effluent Monitor (RE8817) provides an Alarm function only for releases into the environment as required by CONTROL 3.3.7.10.Liquid radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented in Figure 1-1.1.2 Liquid Effluent Monitor Setpoint Determination Per the requirements of CONTROL 3.3.7.10, alarm setpoints shall be established for the liquid monitoring instrumentation to ensure that the, release concentration limits of CONTROL 3.11.1.1 are met (i.e., the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20 Appendix B. Table II, Column 2, (Appendix F) for radionuclides and 2.OE-04 pCi/ml for dissolved or entrained noble gases). The following equation (adopted from NUREG-0133) must be satisfied to meet the liquid effluent restrictions:

C (F+f)c_< -(1.1)f where: C = the effluent concentration limit of CONTROL 3.11.1.1 implementing the 10 CFR 20 MPC (Appendix F) for the site, in gCi/ml.c = the setpoint, in piCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the UNRESTRICTED AREA.f = the flow rate at the radiation monitor location, in volume per unit time, but the same units as F, below.380 HOPE CREEK ODCM REV. 26 F = the dilution water flow rate as measured prior to the release point, in volume per 3 unit time.[Note that if no dilution is provided, c < C. Also, note that when (F) is large compared to (f), 3 then (F + f) = F.]1.2.1 Liquid Effluent Monitors 3 The setpoints for the liquid effluent monitors at the Hope Creek Generating Station are determined by the following equation:

I SP < MPC,* CTBD *[1CF]+bkg (1.2)-I RR with: I Z C,(gamma) 3 MPCe= C (1.3)-(gamma)where: SP = alarm setpoint corresponding to the maximum allowable release rate (jtCi/ml).

MPCe an effective MPC value for the mixture of radionuclides in the effluent stream, ([iCi/ml).

Ci = the concentration of radionuclide in the liquid effluent (ptCi/ml).

MPCi = the MPC value corresponding to radionuclide.

i from (Appendix F) 10 CFR 20, Appendix B, Table II, Column 2 (ptCi/ml).

3 CTBD= the Cooling-Tower Blowdown Discharge rate at the time of release (gal/min).

RR = the liquid effluent release rate (gal/min) at the monitor location (i.e., at the liquid radwaste monitor, at the TBCW monitor, or at the CTBD monitor).bkg = the background of the monitor ([tCi/ml).

CF = Correction factor to account for non-gamma emitting nuclides and radiation monitor inaccuracies.

The radioactivity monitor setpoint equation (1.2) remains valid during outages when the Cooling-Tower Blowdown discharge is potentially at its lowest value. Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria.Procedural restrictions prevent simultaneous batch liquid releases.

The setpoints should be reduced to allow for potential or actual concurrent continuous releases such that the limits of ODCM CONTROL 3.11.1.1 are not exceeded.I 1.2.2 Conservative Default Values I 3813 HOPE CREEK ODCM REV. 26 Conservative alarm setpoints for liquid radwaste radiation monitors may be determined through the use of default parameters.

Table 1-1 summarizes all current default values in use for Hope Creek. They are based upon the following: (a) substitution of the effective MPC value with a default value of 4.09E-05 pCi/ml for radwaste releases (Refer to Appendix A for justification);(b) substitutions of the Cooling-Tower Blowdown discharge rate with the minimum average flow, in gal/min; and, (c) substitutions of the effluent release rate with the highest allowed rate, in gal/min.(d) substitution of a 0.8 correction factor (CF) to account for monitor inaccuracies and non-gamma emitting radionuclides.

The usei of the conservative alarm setpoint, or a setpoint below the conservative value, is acceptable provided that the value used is at least as conservative as the release specific setpoint calculated in accordance with Equation 1.2 above. Procedural controls exist to verify the setpoint utilized is at or below what is required.1.3 Liquid Effluent Concentration Limits -10 CFR 20 CONTROL 3.11.1.1 limits the concentration of radioactive material in liquid effluents (after dilution in the Cooling-Tower Blowdown Discharge System) to less than the concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F) for radionuclides other than noble gases. Noble gases are limited to a diluted concentration of 2.OE-04 uCi/ml.Release rates are controlled and radiation monitor alarm setpoints are established as addressed above to ensure that these concentration limits are not exceeded.

However, in the event any liquid release results in an alarm setpoint being exceeded, an evaluation of compliance with the concentration limits of CONTROL 3.11.1.1 may be performed using the following equation: Ci

RR 1 (1.4)MPC 1 CTBD + RR where: Ci = actual concentration of radionuclide i as measured in the undiluted liquid effluent (jiCi/ml).

MPCi = the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F) (pCi/ml).= 2E-04 jtCi/ml for dissolved or entrained noble gases.RR = the actual liquid effluent release rate (gal/min)CTBD = the actual Cooling-Tower Blowdown discharge at the time of release (gal/min).

382 HOPE CREEK ODCM REV. 26.1.4 Liquid Effluent Dose Calculation

-10 CFR 50 1.4.1 MEMBER OF THE PUBLIC Dose -Liquid Effluents CONTROL 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from Hope Creek Generating Station to:-during any calendar quarter:< 1.5 mrem to total body< 5.0 mrem to any organ-during any calendar year:< 3.0 mrem to total body< 10.0 mrem to any organ Per the surveillance requirements to CONTROL 4.11.1.2, the following calculation methods shall be used for determining the dose or dose commitment due to the liquid radioactive effluents from Hope Creek.Do= 8.35E-04*

VOL ,i

Aio CTBD (1.5)I I I I I I 1 I I I I where: DO Aio Ci VOL CTBD 8.35E-= dose or dose commitment to organ o, including total body (mrem).= site-related ingestion dose commitment factor to the total body or any organ o for radionuclide i (mrem/hr per ptCi/ml).= average concentration of radionuclide i, in undiluted liquid effluent representative of volume VOL (ptCi/ml).

= volume of liquid effluent released (gal).= Average Cooling-Tower Blowdown discharge rate during release period (gal/min).

04 = conversion factor (1.67E-2 hr/min) and a near field dilution factor of 0.05 (refer to Appendix B for definition).

383 HOPE CREEK ODCM REV. 26 The site-related ingestion dose/dose commitment factors (Aio) are presented in Table 1-2 and have been derived in accordance with NUREG-0133 by the equation: Ai. = 1.14E+05 [(UI

Bli) + (UF

BFi)] Dfio (1.6)where: 1.14E+05=z UI Bii UF Bfi Dfio composite dose parameter for the total body or critical organ o of an adult for radionuclide i, for the fish and invertebrate ingestion pathways (mrem/hr per pci/ml).conversion factor (pCi/ptCi

ml/kg per hr/yr).adult invertebrate consumption (5 kg/yr).bioaccumulation factor for radionuclide i in invertebrates from Table 1-3 (pCi/kg per pCi/1).adult fish consumption (21 kg/yr).bioaccumulation factor for nuclide i in fish from Table 1-3 (pCi/kg per pCi/1).dose conversion factor for nuclide i for adults in preselected organ, o, from Table E- 1I of Regulatory Guide 1.109 (mrem/pCi).

The radionuclides included in the periodic dose assessment per the requirements of CONTROL 3/4.11.1.2 are those as identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of CONTROL 3/4.11.1.1, Table 4.11.1.1.1-1.

Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added to the dose analysis at a frequency consistent with the required minimum analysis frequency of CONTROL Table 4.11.1.1.1-1.

1.4.2 Simplified Liquid Effluent Dose Calculation In lieu of the individual radionuclide dose assessment as presented in Section 1.4.1, the following simplified dose calculation equation may be used for demonstrating compliance with the dose limits of CONTROL 3.11.1.2. (Refer to Appendix B for the derivation and justification for this simplified method.)Total Body Dtb =1.94E+02*VOL, Ci CTBD i (1.7)Maximum Organ Dnx o -:- 5.28E + 02

VOL Ci CTBD (1.8)384 HOPE CREEK ODCM REV. 26 where: Dtb Dmax o Ci VOL CTBD 1.94E+02 5.28E+02 conservatively evaluated total body dose (mrem).evaluated maximum organ dose (mrem).average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (piCi/ml).

volume of liquid effluent released (gal).average Cooling-Tower Blowdown discharge rate during release period (gal/min).

conversion factor (1.67E-2 hr/min), the conservative total body ingestion dose commitment factor (Zn-65 = 2.32E+5 mrem/hr per [tCi/ml), and the near field dilution factor of 0.05. (See Appendix B)conversion factor (1.67E-2 hr/min), the conservative maximum organ ingestion dose commitment factor (Fe-59, GI-LLI -6.32E+5 mrem/hr per ptCi/ml), and the near field dilution factor of 0.05 (See Appendix B).1.5 Liquid Effluent Dose Projections CONTROL 3.11.1.3 requires that the liquid radioactive waste processing system be used to reduce the radioactive material levels in the liquid waste prior to release when the 31-day projected doses exceed:-0.06 mrem to the total body, or-0.2 mrem to any organ.The applicable liquid waste processing system for maintaining radioactive material releases ALARA are the drain filters and demineralizers as delineated in Figure 1-1.Dose projections are made at least once per 31-days by the following equations:

I I I I I I I I I I I I Dtbp = (Dtb / d)

31d Dmaxp = (Dmax I d)

31d (1.9)(1.10)where: Dtbp the total body dose projection for current 31-day period (mrem).Dtb the total body dose to date for current calendar quarter as determined by equation (1.5) or (1.7).Dmaxp the maximum organ dose to date for current calendar quarter as determined by equation (1.5 or (1.8) (mrem).d the number of days in current calendar quarter at the end of the release.31 d the number of days of concern.385 HOPE CREEK ODCM REV. 26 1.6 Representative Samples A sample should be representative of the bulk stream or volume of effluent from which it is taken. Prior to sampling, large volumes of liquid waste should be mixed in as short a time interval practicable to assure that any sediments or particulate solids are distributed uniformly in the waste mixture. Recirculation pumps for liquid waste tanks (collection or sample test tanks) should be capable of recirculating at a rate of not less than two tank volumes in eight hours. Minimum recirculation times and methods of recirculation are controlled by specific plant procedures.

2.0 GASEOUS EFFLUENTS 2.1 Radiation Monitoring Instrumentation and Controls The gaseous effluent monitoring instrumentation and controls at Hope Creek for controlling and monitoring normal radioactive material releases in accordance with the Radiological Effluent CONTROLS are summarized as follows: (1) Filtration, Recirculation, and Ventilation System -The FRVS is maintained in a standby condition.

Upon reactor building isolation, the FRVS recirculation system recirculates the reactor building air through HEPA and charcoal filters. Releases are made to the atmosphere via a reactor building vent or the South Plant Vent depending on mode of operation.

Noble gas monitoring is provided by RE-481 IA.(2) South Plant Vent -The SPV receives discharge from the radwaste evaporator, reactor building purge, auxiliary building radwaste area, condensate demineralizer, pipe chase, feedwater heater, and untreated ventilation sources. Effluents are monitored (for noble gas) by the RE-4875B monitor.(3) North Plant Vent -The NPV receives discharge from the gaseous radwaste treatment system (Offgas system) and untreated ventilation air sources. Effluents are monitored (for noble gases) by the RE-4573B monitor.Gaseous radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation controls are presented in Figures 2-1 and 2-2.386 HOPE CREEK ODCM REV. 26 2.2 Gaseous Effluent Monitor Setpoint Determination i 2.2.1 Plant Vent, FRVS Per the requirements of CONTROL 3.3.7.11, alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases i does not exceed the limits of CONTROL 3.11.2.1, which corresponds to a dose rate at the SITE BOUNDARY of 500 mrem/year to the total body or 3000 mrem/year to the skin.Based on a grab sample analysis of the applicable release (i.e., of FRVS, pipe chase, gaseous I radwaste treatment system air, etc.), the radiation monitoring alarm setpoints may be established by the following calculation method. The measured radionuclide concentrations and release rate are used to calculate the fraction of the allowable release rate, as limited by i CONTROL 3.11.2.1, by the equation: FRAC-F E *Z

1500 1/3 4.72 +*2 QVF (2.1)FRAC= 4.72E+02*Z

VF* (Ci*(Li +1.lM ))]3000 (2.2)where: FRAC = fraction of the allowable release rate based on the identified radionuclide U concentrations and the release flow rate.X/Q = annual average meteorological dispersion to the controlling site boundary location (sec/m3).VF = ventilation system flow rate for the applicable release point and monitor (ft3/min).

Ci = concentration of noble gas radionuclide i as determined by radioanalysis of grab sample (uCi/cm3)Ki -- total body dose conversion factor for noble gas radionuclide i (mrem/yr per p.Ci/m3), rom Table 2-1i pCi/m3), from Table 2-1 Mi = gamma air dose conversion factor for noble gas radionuclide i (mradlyr per 3[LCi/m3), from Table 2-1 1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad) 4.72E+02 = conversion factor (cm3/ft3

min/sec)500 = total body dose rate limit (mrem/yr)3000 = skin dose rate limit (mrem/yr)Based on the more limiting FRAC (i.e., higher value) as determined above, the alarm setpoints for the applicable monitors may be calculated by the equation: SP:5rAF* iFRAC]+3bkg (2.3)387 HOPE CREEK ODCM REV. 26 where: SP = alarm setpoint corresponding to the maximum allowable release rate (ýiCi/cc).

FRAC = highest fraction of the allowable release rate as determined in equation (2.2).bkg = background of the monitor (pCi/cc).AF = administrative allocation factor for the specific monitor (0.2 NPV, 0.2 SPV, 0.1 FRVS).The allocation factor (AF) is an administrative control imposed to ensure that combined releases from Salem Units 1 and 2 and Hope Creek will not exceed the regulatory limits on release rate from the site (i.e., the release rate limits of CONTROL 3.11.2.1).

Normally, the combined AF value for Salem Units 1 and 2 is .0.5 (0.25 per unit), with the remainder 0.5 allocated to Hope Creek. Any increase in AF above 0.5 for the Hope Creek Generating Station will be coordinated with the Salem Generating Station to ensure that the combined allocation factors for all units do not exceed 1.0.2.2.2 Conservative Default Values A conservative alarm setpoint can be established, in lieu of the individual radionuclide evaluation based on the grab sample analysis, to eliminate the potential of periodically having to adjust the setpoint to reflect minor changes in radionuclide distribution and variations in release flow rate. The alarm setpoint may be conservatively determined by the default values presented in Table 2-2.These values are based upon:-the maximum ventilation (or purge) flow rate;-a radionuclide distribution adopted from ANSI N237- 1976/ANS 18.1 "Source Term Specifications", Table 5 and;-an administrative allocation factor of 0.5 to conservatively ensure that any releases from Hope Creek do not exceed the maximum allowable release rate.For the noble gas radionuclide distribution from ANSI N237-1976/ANS 18.1 (Note Table C-I), the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dose rate. The resulting conservative, default setpoints are presented in Table 2-2.2.3 Gaseous Effluent Instantaneous Dose Rate Calculations

-10 CFR 20 2.3.1 Site Boundary Dose Rate -Noble Gases CONTROL 3.11.2.1a limits the dose rate at the SITE BOUNDARY due to noble gas releases to < 500 mrem/yr, total body and < 3000 mrem/yr, skin. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded.

In the event any gaseous releases from the station results in an alarm setpoint (as determined in Section 2.2.1) being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release shall be performed using the following equations:

388 HOPE CREEK ODCM REV. 26 Dtb= *Y (iQ (2.4)D, ~Z *Z((Lil+/-.1M)*Qi)

(2.5)I where: i Dtb total body dose rate (mrem/yr).

D, skin dose rate (mrem/yr).

X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3).Q = average release rate of radionuclide i over the release period under evaluation (pCi/sec).

= total body dose conversion factor for noble gas radionuclide i (mrem/yr perýtCi/m3), from Table 2-1 Li = beta skin dose conversion factor for noble gas radionuclide i (mrad/yr per jiCi/m3), from Table 2-1 3 Mi gamma air dose conversion factor for noble gas radionuclide i (mrad/yr per jiCi/m3, from Table 2-1.1.1 mrem skin dose per mrad gamma air dose (mrem/mrad)

As appropriate, simultaneous releases from Salem Units 1 and 2 and Hope Creek will be considered in evaluating compliance with the release rate limits of CONTROL 3.11.2.1 a, i following any releases exceeding the above prescribed alarm setpoints.

Monitor indications (readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity.

I The 15-minute averaging is needed to allow for reasonable monitor response to potentially changing radioactive material concentrations and to exclude potential electronic spikes in monitor readings that may be unrelated to radioactive material releases.

As identified, any I electronic spiking monitor responses may be excluded from the analysis.NOTE: For administrative purposes, more conservative alarm setpoints than those as i prescribed above may be imposed. However, conditions exceeding these more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding the dose limits of CONTROL 3.11.2.1a.

Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based on the above criteria, no further analyses are required for demonstrating compliance with the limits of CONTROL 3.11.2.1 a.Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-3 may be used for evaluating the gaseous effluent dose rate.389 HOPE CREEK ODCM REV. 26 2.3.2 Site Boundary Dose Rate -Radioiodine and Particulates CONTROL 3.11.2.1b limits the dose rate to < 1500 mrem/yr to any organ for 1-131, 1-133, tritium and particulates with half-lives greater than 8 days. To demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period (e.g., nominally once per 7 days). The following equation shall be used for the dose rate evaluation:

Do.= ZQ* (RIo*Qi) (2.6)where: Do average organ dose rate over the sampling time period (mrem/yr).

X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location for-the inhalation pathway (sec/m3).Rio = dose parameter for radionuclide i (mrem/yr per ýtCi/m3) and organ o for the child inhalation pathway from Table 2-4.Qi = average release rate over the appropriate sampling period and analysis frequency for radionuclide i --1-131, 1-133, tritium or other radionuclide in particulate form with half- life greater than 8 days (pCi/sec).

By substituting 1500 mrem/yr for Do and solving for Q, an allowable release rate for 1-131 can be determined.

Based on the annual average meteorological dispersion (See Table 2-3)and the most limiting potential pathway, age group and organ (inhalation, child, thyroid -- Ri= 1.62E+07 mrem/yr per ýtCi/m3), the allowable release rate for 1-131 is 34.7 pCi/sec.Reducing this release rate by a factor of 2 to account for potential dose contributions from other radioactive particulate material and other release points (e.g., Salem), the corresponding release rate allocated to Hope Creek is 17.4 pCi/sec. For a 7-day period, which is the nominal sampling and analysis frequency for 1-131, the cumulative release is 10.5 Ci.Therefore, as long as the 1-131 release in any 7-day period do not exceed 10.5 Ci, no additional analyses are needed for verifying compliance with the CONTROL 3.11.2.1.b limits on allowable release rate.2.4 Noble Gas Effluent Dose Calculations

-10 CFR 50 2.4.1 UNRESTRICTED AREA Dose -Noble Gases CONTROL 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 are applicable separately to each generating station and are not combined site limits. The following equations shall beused to calculate the' gamma-air and beta-air doses: 390 HOPE CREEK ODCM REV. 26 D 7=3.17EO8*y

J * (2.7)I=~ 3.17E -O8 Z*(Ni* ) (2.8)where: Dr air dose due to gamma emissions for noble gas radionuclides (mrad).Df = air dose due to beta emissions for noble gas radionuclides (mrad).X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3).

I Qi = cumulative release of noble gas radionuclide i over the period of interest (pCi).Mi= air dose factor due to gamma emission from noble gas radionuclide i (mrad/yr per ýtCi/m3, from Table 2-1.Ni= air dose factor due to beta emissions from noble gas radionuclide i (mrad/yr per [tCi/m3, Table 2-1).3.17E-08 = conversion factor (yr/sec).2.4.2 Simplified Dose Calculation for Noble Gases I In lieu of the individual noble gas radionuclide dose assessment as presented above, the following simplified dose calculation equations may be used for verifying compliance with I the dose limits of CONTROL 3.11.2.2 (Refer to Appendix C for the derivation and justification of this simplified method).Dr 3.17E1- 8 Mif Qi (2.9)0.50 IQ D -

(2.10) I Dl=.0.50 7 NefY i (.0 where: Meff = 8. 1E+03, effective gamma-air dose factor (mrad/yr per ýiCi/m3).Neff = 8.5E+03, effective beta-air dose factor (mrad/yr per gCi/m3).Qi = cumulative release for all noble gas radionuclides (iCi).0.50 = conservatism factor to account for potential variability in the radionuclide distribution.

Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-3, may be used for the evaluation of the gamma-air and beta-air doses.391 HOPE CREEK ODCM REV. 26 2.5 Radioiodine and Particulate Dose Calculations

-10 CFR 50 2.5.1 UNRESTRICTED AREA Dose -Radioiodine and Particulates In accordance with the requirements of CONTROL 3.11.2.3, a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit < 15 mrem to any organ. The following equation shall be used to evaluate the maximum organ dose due to release of 1- 131, 1-133, tritium and particulates with half-lives greater than 8 days: Daop= 3.17E -08 *W* SFp* (Riaop* Qi) (2.11)where: Daop = dose or dose commitment via all pathways p and age group a (as identified in Table 2-3) to organ o, including the total body (mrem).W = atmospheric dispersion parameter to the controlling location(s) as identified in Table 2-3.X/Q = atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (sec/m3).D/Q = atmospheric deposition for vegetation, milk and ground plane exposure pathways (1/m2).Riaop = dose factor for radionuclide i (mrem/yr per piCi/m3 or m2 -mrem/yr per [tCi/sec)and organ o from Table 2-4 for each age group a and the applicable pathway p as identified in Table 2-3. Values for Riaop were derived in accordance with the methods described in NUREG-0 133.Qi = cumulative release over the period of interest for radionuclide i -- 1-131, 1-133, H-3 or radioactive material in particulate form with half-life greater than 8 days ([iCi): Sfp = annual seasonal correction factor to account for fraction of the year that the applicable exposure pathway does not exist.(1) For milk and vegetation exposure pathways:= A six month fresh vegetation and grazing season (May through October)=

0.5 (2) For inhalation and ground plane exposure pathways.:

= 1.0 For evaluating the maximum exposed individual, the infant age group is controlling for the milk pathway. Only the controlling age group as identified in Table 2-3 need be evaluated for compliance with Control 3.11.2.3 2.5.2 Simplified Dose Calculation for Radioiodines and Particulates In lieu of the individual radionuclide (1-131, 1-133 and particulates) dose assessment for the resident/dairy location as presented above, the following simplified dose calculation equation may be used for verifying compliance with the dose limits of CONTROL 3.11.2.3 (Refer to Appendix D for the derivation and justification of this simplified method): 392 HOPE CREEK ODCM REV. 26 D.,x = 3.17E -08 *W* SPp

R -131" ZQi (.2 i where: Dmax o = maximum organ dose (mrem).R1_ 131 = 1-131 dose parameter for the thyroid for the identified controlling pathway.= 1.05E+12, infant thyroid dose parameter with the cow-milk pathway controlling (m2 -mrem/yr per jiCi/sec).

W = D/Q for radioiodine, 2.87E-10 l/m2.Qi = cumulative release over the period of interest for radionuclide i - 131 or radioactive material in particulate form with half-life greater than 8 days (.tCi).The location of exposure pathways and the maximum organ dose calculation may be based on the available pathways in the surrounding environment of Hope Creek as identified by the annual land-use census (CONTROL 3.12.2). Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-3.2.6 Gaseous Effluent Dose Projection U CONTROL 3.11.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected doses in 31-days exceed:-0.2 mrad to air from gamma radiation, or-0.4 mrad to air from beta radiation, or-0.3 mrad to any organ of a MEMBER OF THE PUBLIC The applicable gaseous processing systems for maintaining radioactive material releases ALARA are the Gaseous Radwaste Treatment System and Exhaust Treatment System as delineated in Figures 2-1 and 2-2.Dose projection are performed at least once per 31-days by the following equations:

DgP = (Dg/d)

31d (2.13)Ddp = (Dd / d)

31d (2.14)Dmaxp = (max / d)

31d (2.15)where: DgP = gamma air dose projection for current 31-day period (mrad).Dg = gamma air dose to date for current calendar quarter as determined by equation (2.7)or (2.9) (mrad).Dbp = beta air dose projection for current 31-day period (mrad). I Db = beta air dose to date for current calendar quarter as determined by equation (2.8) or (2.10) (mrad).Dmaxp = maximum organ dose projection for current 31-day period (mrem).393 HOPE CREEK ODCM REV. 26 Dmax = maximum organ dose to date for current calendar quarter as determined by equation (2.11) or (2.12) (mrem).d = number of days in current calendar quarter at the end of the release.31d = the number of days of concern.3.0 SPECIAL DOSE ANALYSIS 3.1 Doses Due to Activities Inside the SITE BOUNDARY In accordance with Technical Specification 6.9.1.7, the Radioactive Effluent Release Report (RERR) submitted by May 1st of each year shall include an assessment of radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY.The calculation methods as presented in Sections 2.4 and 2.5 may be used for determining the maximum potential dose to a MEMBER OF THE PUBLIC located inside the site boundary.

For the purpose of this calculation, a MEMBER OF THE PUBLIC is an adult individual who is not subject to occupational exposure (i.e., an un-monitored site worker) performing duties within the site boundary, and who is exposed to radioactive material in gaseous effluent for 2,000 hours0 days 0 hours 0 weeks 0 months per year via the inhalation and ground plane exposure pathways.

The values for the atmospheric dispersion coefficients at the point of interest inside the site boundary (e.g., 0.25 mile) shall be developed from the current year meteorological data.3.2 Total Dose to MEMBERS OF THE PUBLIC -40 CFR 190 and 10 CFR 72.104 The Radioactive Effluent Release Report (RERR) submitted by May 1st of each year shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle courses (including dose contributions from effluents and direct radiation from on-site sources).

For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of Artificial Island, the sources of exposure need only consider the Salem Generating station and the Hope Creek Generating Station which includes the Independent Spent Fuel Storage Installation (ISFSD): No other fuel cycle facilities contribute to the MEMBER OF THE PUBLIC dose for the Artificial Island vicinity.The dose contribution from the operation of Salem Generating Stations will be estimated based on the methods as presented in the Salem Offsite Dose Calculation Manual (SGS ODCM).As appropriate for demonstrating/evaluating compliance with the limits of CONTROL 3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used for providing data on actual measured levels of radioactive material in the actual pathways of exposure.3.2.1 Effluent Dose Calculations For purposes of implementing the surveillance requirements of CONTROL 3/4.11.4 and the reporting requirements of 6.9.1.7 (RERR), dose calculations for the Hope Creek Generating Station may be performed using the calculation methods contained within the ODCM; the conservation controlling pathways and locations of Table 2-4 or the actual pathways and locations as identified by the land use census (CONTROL 3/4.12.1) may be used. Average annual meteorological 394 HOPE CREEK ODCM REV. 26 dispersion parameters or meteorological conditions concurrent with the release period under evaluation may be used.3.2.2 Direct Exposure Dose Determination Any potentially significant direct exposure contribution to off-site individual doses may be evaluated based on the results of the environmental measurements (e.g., dosimetry, ion chamber measurements) and/or by the use of a radiation transport and shielding calculation method.Only during a non-typical condition will there exist any potential for significant on-site sources I at Hope Creek that would yield potentially significant off-site doses (i.e., in excess of 1 mrem per year to a MEMBER OF THE PUBLIC), that would require detailed evaluation for demonstrating compliance with 40 CFR 190 or 10 CFR 72.104. However, should a situation l exist whereby the direct exposure contribution is potentially significant, on-site measurements, off-site measurements and/or calculational techniques will be used for determination of dose for assessing 40 CFR 190 or 10 CFR 72.104 compliance.

I 3.3 Doses due to Carbon 14 in Gaseous Effluent Because gaseous effluent releases from a boiler water reactor (BWR), such as the Hope Creek Generating Station, can contain significant quantities of C-14 (i.e., approximately 8 to 9.5 curies annually -Regulatory Guide 1.21), the NRC has recommended that licensees evaluate C-14 as a I potential principal radionuclide for gaseous releases from their facility.

The results in an evaluation conducted in response to SAP Order 70096339 identified C-14 as a principal radionuclide in gaseous effluent releases from the Hope Creek Generating Station.3.3.1 Estimation of Carbon 14 Annual Release The methodology for estimating the quantity C-14 released annually from the Hope Creek Generating Station incorporates the use of a normalized C-14 source term and a scaling factor I based on power generation.

NCRP Report No. 81, Carbon-14 in the Environment, has been identified by the NRC as a source for scaling factors (refer to section 1.9 in Revision 2 of Regulatory Guide 1.21). This approach is one of three NRC-recommended methods for I estimating the quantity of C-14 discharged in gaseous effluent (refer to Regulatory position 1.9 in Revision 2 of Regulatory Guide 1.21). Electrical energy output value for the reporting period should be used to estimate the quantity of C-14 released.

I 3.3.2 Carbon 14 dose Determinations I The methodology for determining doses from C-14 in gaseous releases incorporates dose models described in Regulatory Guide 1.109. Estimated C-14 releases and average meteorological data for the reporting period should be used as input to the dose calculations.

The doses due to C-14 in gaseous releases are calculated for receptors located at and beyond the site boundary.

For doses at I locations beyond the site boundaries, receptors shall be real individuals via active pathways as identified in the Annual Land Use Census. Doses due to C-14 in gaseous effluent and the assumptions used in the dose calculations shall be included in the annual Radioactive Effluent I Release Report.395 I HOPE CREEK ODCM REV. 26 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4.1 Sampling!

Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of CONTROL 3.12. The objectives of the program are:-To determine whether any significant increases occur in the concentration of radionuclides in the critical pathways of exposure in the vicinity of Artificial Island;-To determine if the operation of the Hope Creek Generating Station has resulted in any increase in the inventory of long lived radionuclides in the environment;

-To detect any changes in the ambient gamma radiation levels; and-To verify that HCGS operations have no detrimental effects on the health and safety of the public or on the environment.

The sampling requirements (type of samples, collection frequency and analysis) and sample locations are presented in Appendix E.NOTE: No public drinking water samples or irrigation water samples are taken as these pathways are not directly effected by liquid effluents discharged from Hope Creek Generating Station.4.2 Interlaboratory Comparison Program CONTROL 3.12.3 requires analyses be performed on radioactive material supplied as part of an Interlaboratory Comparison.

Participation in an approved Interlaboratory Comparison Program provides a check on the preciseness of measurements of radioactive materials in environmental samples. A summary of the Interlaboratory Comparison Program results will be provided in the Annual Radiological Environmental Operating Report pursuant to CONTROLS 6.9.1.7.5.0 HCGS EXPLOSIVE GAS MONITORING PROGRAM The Hope Creek Explosive Gas Monitoring program was moved within the Hope Creek Technical Specifications to section 6.8.4.d. This was performed in Technical Specification Amendment 91.Details of the Hope Creek Explosive Gas Monitoring program are maintained in station implementing procedures and are controlled by the 50.59 safety evaluation and procedure processes.

FIGURE 1-1: LIQUID RADWASTE TREATMENT AND MONITORING SYSTEM HOPE CREEK ODCM REV. 26 FIGURE 1-2: SOLID RADWASTE PROCESSING SYSTEM 397 HOPE CREEK ODCM REV. 26 See Note 1 Note 1: Specified equipment is installed but not in use.Equipment is pending abandonment per DCP 4EC-3634.398 I I HOPE CREEK ODCM REV. 26 TABLE 1-1: PARAMETERS FOR LIQUID ALARM SETPOINT DETERMINATION Parameter Actual Default Value Value Units Comments MPCe Calc 4.09E-05"*

pCi/ml Calculated for each batch to be, released MPC 1-131 3.OE-07 N/A gCi/ml Taken from 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F)Ci Measured N/A ý.Ci/ml Taken from gamma spectral analysis of liquid effluent MPCi Measured N/A [iCi/ml Taken from 10CFR20, Appendix B, Table II, Column 2 (Appendix F)CTBD Measured 12000 gpm Cooling tower blowdown discharge RR Measured 176 gpm or Determined prior to release, release rate can be adjusted for CONTROL 1300 gpm(CST) compliance gpm Maximum flow rate with both pumps Estimated 100 (TBCW) running (50 gpm each)SP (Setpoints)

A) RE4861 Calc 5.58E-04 piCi/ml Default alarm setpoints; more conservative values may be used as appropriate and desirable for ensuring regulatory compliance and for maintaining releases ALARA RE8817 Calc 8.18E-06 pCi/ml Maximum alarm setpoint continuous RE4557 Calc 2.40E-06 J1Ci/ml release; more conservative value may be established by plant procedure B) RE4861 Calc 7.55E-05 ýtCi/ml These setpoints are for condensate storage tank releases RE8817 Calc 8.18E-06 [tCi/ml I I I I I I I I I I I I I I I* See Appendix A for basis 399 I HOPE CREEK ODCM REV. 26 TABLE 1-2: SITE RELATED INGESTION DOSE COMMITMENT FACTOR, Aio (FISH AND INVERTEBRATE CONSUMPTION)(mren/hr per pCi/mil)_ilSid Bnei Live 5s TrI iiev', lum II-LI H-3 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 C-14 1.45E+4 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 P-32 4.69E+6 2.91E+5 1.81E+5 --5.27E+5 Cr-51 --5.58E+O 3.34E+O 1.23E+O 7.40E+O 1.40E+3 Mn-54 -7.06E+3 1.35E+3 -2.1OE+3 -2.16E+4 MVn-56 -1.78E+2 3.15E+l -2.26E+2 -5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 --1.97E+4 2.03E+4 Fe-59 8.06E+4 1.90E+5 7.27E+4 --5.30E+4 6.32E+5 Co-57 -1.42E+2 2.36E+2 ---3.59E+3 Co-58 -6.03E+2 1.35E+3 ---1.22E+4 Co-60 -1.73E+3 3.82E+3 ---3.25E+4 Ni-63 4.96E+4 3.44E+3 1.67E+3 ---7.18E+2 Ni-65 2.02E+2 2.62E+1 1.20E+l ---6.65E+2 Cu-64 -2.14E+2 1.01E+2 -5.40E+2 -1.83E+4 Zn-65 1.61E+5 5.13E+5 2.32E+5 -3.43E+5 -3.23E+5 Zn-69m 5.66E+3 1.36E+4 1.24E+3 -8.22E+3 -8.29E+5 As-76 4.38E+2 1.16E+3 5.14E+3 3.42E+2 1.39E+3 3.58E+2 4.30E+4 Br-82 --4.07E+O ---4.67E+O Br-83 --7.25E-2 ---1.04E-1 Br-84 --9.39E-2 --7.37E-7 Br-85 --3.86E-3 ---Rb-86 -6.24E+2 2.91E+2 ---1.23E+2 Rb-88 -1.79E+O 9.49E-1 ---2.47E-11 Rb-89 -1.19E+O 8.34E-1 -- -6.89E-14 Sr-89 4.99E+3 -1.43E+2 --8.OOE+2 Sr-90 1.23E+5 -3.01E+4 -- -3.55E+3 Sr-91 9.18E+l -3.71E+O ---4.37E+2 Sr-92 3.48E+1 -1.51E+O ---6.90E+2 Y-90 6.06E+O -1.63E-1 ---6.42E+4 Y-91m 5.73E-2 -2.22E-3 ---1:68E-1 Y-91 8.88E+1 -2.37E+O ---4.89E+4 Y-92 5.32E-1 -1.56E-2 --9.32E+3 Y-93 1.69E+O -4.66E-2 -5.35E+4 Zr-95 1.59E+1 5.11E+0 3.46E+O -8.02E+O -1.62E+4 Zr-97 8.81E-1 1.78E-1 8.13E-2 -2.68E-1 -5.51E+4 Nb-95 4.47E+2 2.49E+2 1.34E+2 -2.46E+2 -1.51E+6 Nb-97 3.75E+O 9.49E-1 3.46E-1 -1.11E+0 -3.50E+3 Mo-99 1.28E+2 2.43E+1 -2.89E+2 -2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.66E-1 -5.56E-1 1.79E-2 2.17E+1 Tc-101 1.33E-2 1.92E-2 1.88E-1 -3.46E-1 9.81E-3 5.77E-14 400 HOPE CREEK ODCM REV. 26 TABLE 1-2 (cont'd)SITE RELATED INGESTION DOSE COMMITMENT FACTOR, Ai, (FISH AND INVERTEBRATE CONSUMPTION)(mrem/hr per [tCi/ml)iNul i ii ISI II5 Ru-103 1.07E+2 4.60E+1 -4.07E+2 -1.25E+4 Ru-105 8.89E+O 3.5 1E+O -1.15E+2 -5.44E+3 Ru-106 1.59E+3 2.01E+2 -3.06E+3 -1.03E+5 Ag-110m 1.56E+3 1.45E+3 8.60E+2 -2.85E+3 -5.91E+5 Sb-122 1.98E+1 4.55E-1 6.82E+O 3.06E-1 -1.19E+l 7.51E+3 Sb-124 2.77E+2 5.23E+O 1.1OE+2 6.71E-1 -2.15E+2 7.86E+3 Sb-125 1.77E+2 1.98E+O 4.21E+1 1.80E-1 -1.36E+2 1.95E+3 Sb-126 1.14E+2 2.31E+O 4.10E+l 6.96E-1 -6.97E+1 9.29E+3 Te-125m 2.17E+2 7.86E+1 2.91E+1 6.52E+1 8.82E+2 -8.66E+2 Te-127m 5.48E+2 1.96E+2 6.68E+/-1 1.40E+2 2.23E+3 -1.84E+3 Te-127 8.90E+O 3.20E+O 1.93E+O 6.60E+O 3.63E+1 -7.03E+2 Te-129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 -4.69E+3 Te-129 2.54E+0 9.55E-1 6.19E-1 1.95E+0 1.07E+l -1.92E+O Te-131m 1.40E+2 6.85E+1 5.71E+1 1.08E+2 6.94E+2 -6.80E+3 Te-131 1.59E+0 6.66E-1 5.03E-1 1.31E+0 6.99E+O -2.26E-1 Te-132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 -6.24E+3 1-130 3.96E+1 1.17E+2 4.61E+1 9.91E+3 1.82E+2 -1.01E+2 1-131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 -8.23E+1 1-132 1.06E+l 2.85E+1 9.96E+O 9.96E+2 4.54E+1 -5.35E+0 1-133 7.45E+1 1.30E+2 3.95E+1 1.90E+4 2.26E+2 -1.16E+2 1-134 5.56E+0 1.51E+l 5.40E+O 2.62E+2 2.40E+1 -1.32E-2 1-135 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 -6.87E+1 Cs-134 6.84E+3 1.63E+4 1.33E+4 5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+0 1.20E+l 5.94E+O -8.81E+O 8.70E-1 5.12E-5 Ba-139 7.85E+0 5.59E-3 2.30E-1 5.23E-3 3.17E-3 1.39E+1 Ba-140 1.64E+3 2.06E+O 1.08E+2 7.02E-1 1.18E+O 3.38E+3 Ba-141 3.81E+O 2.88E-3 1.29E-1 2.68E-3 1.63E-3 1.80E-9 Ba-142 1.72E+0 1.77E-3 1.08E-1 1.50E-3 1.OOE-3 2.43E-18 La-140 1.57E+0 7.94E-1 2.10E-4 -25.83E+4 La-142 8.06E-2 3.67E-2 9.13E-3 -2.68E+2 Ce-141 3.43E+0 2.32E+O 2.63E-1 1.08E+O -8.86E+3 Ce-143 6.04E-1 4.46E+2 4.94E-2 1.97E-1 -1.67E+4 Ce-144 1.79E+2 7.47E+1 9.59E+0 4.43E+1 6.04E+4 Pr-143 5.79E+0 2.32E+0 2.87E-1 1.34E+0 2.54E+4 Pr-144 1.90E-2 7.87E-3 9.64E-4 -4.44E-3 -2.73E-9 Nd-147 3.96E+0 4.58E+0 2.74E-1 -2.68E+0 2.20E+4 W-187 9.16E+0 7.66E+O 2.68E+O --2.51E+3 Np-239 3.53E-2 3.47E-3 1.91E-3 -1.08E-2 7.11E+2 I I U I I I I I I I I I I I I I I I I 401 HOPE CREEK ODCM REV. 26 TABLE 1-3: BIOACCUMULATION FACTORS (pCi/kg per pCi/liter)*

H 9.OE-01 9.3E-01 C 1.8E+03 1.4E+03 Na 6.7E-02 1.9E-01 P 3.OE+03 3.OE+04 Cr 4.OE+02 2.OE+03 Mn 5.5E+02 4.OE+02 Fe 3.OE+03 2.OE+04 Co 1.OE+02 1.OE+03 Ni 1.0E+02 2.5E+02 Cu 6.7E+02 1.7E+03 Zn 2.OE+03 5.OE+04 Br 1.5E-02 3.1E+00 Rb 8.3E+00 1.7E+01 Sr 2.OE+00 2.0E+01 Y 2.5E+01 1.0E+03 Zr 2.OE+02 8.OE+01 Nb 3.OE+04 1.OE+02 Mo 1.OE+01 1.OE+01 Tc 1.OE+01 5.OE+01 Ru 3.OE+00 1.OE+03 Rh 1.OE+01 2.OE+03 Ag 3.3E+03 3.3E+03 Sb 4.OE+01 5.4E+00 Te 10E+01 1.0E+02 I 1.1E+01 5.OE+01 Cs 4.OE+01 2.5E+01 Ba 1.OE+01 1.OE+02 La 2.5E+01 1.0E+03 Ce 1.0E+01 6.0E+02 Pr 2.5E+01 1.0E+03 Nd 2.5E+01 1.0E+03 W 3.0E+01 3.0E+01 Np 1.0E+01 1.0E+01 As 3.3E+02 3.3E+02* Values in this table are taken from Regulatory Guide 1.109 except for phosphorus (fish) which is adapted from NUREG/CR-1336 and silver, arsenic and antimony which are taken from UCRL 50564, Rev. 1, October 1972.402 HOPE CREEK ODCM REV. 26 FIGURE 2-1: GASEOUS RADWASTE TREATMENT SYSTEM SPV (Fig. 2-2)Main---------------------------------------------

Aux. Boiler Main System Steam Typical of 2 Recombiner Packages ondenserle Reheater Guard Bed IAmhianf Charh,'nal Q cfnm/-tllL~qlL ,J I To North Plant Vent (Fig. 2-2)bsorber Train 403 MM 1=1MMlM11Mm=

mMMMm=MM~M M

HOPE CREEK ODCM REV. 26 FIGURE 2-2: VENTILATION EXHAUST TREATMENT SYSTEM Gaseous Radwaste Treatment System (from Figure 2-1)Untreated Ventilation Air Sources NJorth Plant Ve nt 3outh Plant Vent FRVS System Vent (Typical of 6) : : R = Roughing Filter H = HEPA Filter C = Charcoal Filter RE = Radiation Effluent Monitor Note 1: Specified equipment is installed but not in use.Equipment pending abandonment per DCP 4EC-3634.404 HOPE CREEK ODCM REV. 26 TABLE 2-1: DOSE FACTORS FOR NOBLE GASES Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Ki Li Mi Ni Radionuclide ItCi/m3) AtCi/m3) A.Ci/m3) -tCi/m3 Kr-83m 7.56E-02 -1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131 m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 405 HOPE CREEK ODCM REV. 26 TABLE 2-2: PARAMETERS FOR GASEOUS ALARM SETPOINT DETERMINATION Parameter X/Q VF (NPV)VF (SPV)VF (FRVS)AF (NPV)AF (SPV)AF (FRVS)Actual Value Calculated Measured Measured Measured Coordinated with SGS Default Value 2.14E-6 41900 440,180 9000 Units sec/m3 ft 3/min ft 3/min ft 3/min Unitless Unitless Unitless ptCi/cm 3 Comments From FSAR Table 2.3-3 1, 0.5 mile, N Maximum Operation Maximum Operation Maximum Operation Administrative allocation factor to ensure releases do not exceed release rate limit Ci Li.Measured Nuclide Specific Nuclide Specific Nuclide Specific Calculated Calculated Calculated 0.2 0.2 0.1 N/A N/A N/A N/A mrem/yr per ýtCi/m 3 mrem/yr per [tCi/m 3)mrad/yr per gCi/m 3 Table 2-1 Table 2-1 Table 2-1 SP: NPV SPV FRVS 2.43E-4 2.3 1E-5 5.65E-4 gCi/cc gCi/cc jICi/cc Default alarm Setpoints; more conservative values may be used as deemed appropriate for ensuring ALARA & regulatory compliance 406 HOPE CREEK ODCM REV. 26 I I I TABLE 2-3: CONTROLLING LOCATIONS, PATHWAYS AND ATMOSPHERIC DISPERSION FOR DOSE CALCULATIONS*

ODCM CONTROL (seem3) (l/ 2)Location Pathway(s)

Age Group 3.11.2.1a Site Boundary 0.5 Mile, N 3.11.2. lb Site Boundary 0.5 Mile, N Noble Gases direct exposure Inhalation and ground plane Gamma-Air Beta-Air Milk, ground plane and inhalation N/A Child N/A Infant 2.14E-06 N/A 2.14E-06 N/A 2.14E-06 N/A 7.2E-08 2.87E-10 3.11.2.2 3.11.2.3 Site Boundary 0.5 Mile, N Residence/

Dairy -4.9 Miles, W*The identified controlling locations, pathways and atmospheric dispersion are from the Artificial Island Radiological Monitoring Program and the Hope Creek FSAR.407 I I I I I I I I I I I I I I I HOPE CREEK ODCM REV. 26 Table 2-4: Pathway Dose Factors -Atmospheric Releases, R(io)Inhalation Pathway Dose Factors -ADULT n(mrem/yr per gCi/m3)H-3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 P-32 1.32E+6 7.71E+4 --8.64E+4 5.01E+4 Cr-51 5.95E+1 2.28E+l 1.44E+4 3.32E+3 1.OOE+2 Mn-54 3.96E+4 -9.84E+3 1.40E+6 7.74E+4 6.30E+3 Fe-55 2.46E+4 1.70E+4 --7.21E+4 6.03E+3 3.94E+3 Fe-59 1.18E+4 2.78E+4 -1.02E+6 1.88E+5 1.06E+4 Co-57 6.92E+2 --3.70E+5 3.14E+4 6.71E+2 Co-58 1.58E+3 --9.28E+5 1.06E+5 2.07E+3 Co-60 -1.15E+4 --5.97E+6 2.85E+5 1.48E+4 Ni-63 4.32E+5 3.14E+4 --1.78E+5 1.34E+4 1.45E+4 Zn-65 3.24E+4 1.03E+5 -6.90E+4 8.64E+5 5.34E+4 4.66E+4 Rb-86 -1.35E+5 ---1.66E+4 5.90E+4 Sr-89 3.04E+5 -- -1.40E+6 3.50E+5 8.72E+3 Sr-90 9.92E+7 -- -9.60E+6 7.22E+5 6.1OE+6 Y-91 4.62E+5 -- -1.70E+6 3.85E+5 1.24E+4 Zr-95 1.07E+5 3.44E+4 -5.42E+4 1.77E+6 1.50E+5 2.33E+4 Nb-95 1.41E+4 7.82E+3 -7.74E+3 5.05E+5 1.04E+5 4.21E+3 Ru-103 1.53E+3 -5.83E+3 5.05E+5 1.1OE+5 6.58E+2 Ru-106 6.91E+4 -1.34E+5 9.36E+6 9.12E+5 8.72E+3 Ag-110m 1.08E+4 1.OOE+4 -1.97E+4 4.63E+6 3.02E+5 5.94E+3 Sb-124 3.12E+4 5.89E+2 7.55E+1 -2.48E+6 4.06E+5 1.24E+4 Sb-125 5.34E+4 5.95E+2 5.40E+l -1.74E+6 1.01E+5 1.26E+4 Te-125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E+5 1.57E+3 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 1.58E+3 1-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 -6.28E+3 2.05E+4 1-132 1.16E+3 3.26E+3 1.14E+5 5.18E+3 4.06E+2 1.16E+3 1-133 8.64E+3 1.48E+4 2.15E+6 2.58E+4 -8.88E+3 4.52E+3 1-134 6.44E+2 1.73E+3 2.98E+4 2.75E+3 1.01E+0 6.15E+2 1-135 2.68E+3 6.98E+3 4.48E+5 1.11E+4 -5.25E+3 2.57E+3 Cs-134 3.73E+5 8.48E+5 -2.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-136 3.90E+4 1.46E+5 -8.56E+4 1.20E+4 1.17E+4 1.1OE+5 Cs-137 4.78E+5 6.21E+5 -2.22E+5 7.52E+4 8.40E+3 4.28E+5 Ba-140 3.90E+4 4.90E+1 -1.67E+1 1.27E+6 2.18E+5 2.57E+3 Ce-141 1.99E+4 1.35E+4 -6.26E+3 3.62E+5 1.20E+5 1.53E+3 Ce-144 3.43E+6 1.43E+6 -8.48E+5 7.78E+6 8.16E+5 1.84E+5 Pr-143 9.36E+3 3.75E+3 2.16E+3 2.81E+5 2.OOE+5 4.64E+2 Nd-147 5.27E+3 6.1OE+3 -3.56E+3 2.21E+5 1.73E+5 3.65E+2 408 HOPE CREEK ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Inhalation Pathway Dose Factors -: TEENAGER (mrem/yr per gtCi/m3)H-3 1.27E+3 1.27E+3 1.27E+3 I 1.27E+3 1.27E+3 1.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 P-32 1.89E+6 1.1OE+5 -9.28E+4 7.16E+4 Cr-51 --7.50E+1 3.07E+1 2.1OE+4 3.OOE+3 1.35E+2 Mn-54 -5.11E+4 -1.27E+4 1.98E+6 6.68E+4 8.40E+3 Fe-55 3.34E+4 2.38E+4 --1.24E+5 6.39E+3 5.54E+3 Fe-59 1.59E+4 3.70E+4 --1.53E+6 1.78E+5 1.43E+4 Co-57 -6.92E+2 --5.86E+5 3.14E+4 9.20E+2 Co-58 2.07E+3 --1.34E+6 9.52E+4 2.78E+3 Co-60 -1.51E+4 -8.72E+6 2.59E+5 i.98E+4 Ni-63 5.80E+5 4.34E+4 -13.07E+5 1.42E+4 1.98E+4 Zn-65 3.86E+4 1.34E+5 7 8.64E+4 1.24E+6 4.66E+4 6.24E+4 Rb-86 -1.90E+5 -1.77E+4 8.40E+4 Sr-89 4.34E+5 -2.42E+6 3.71E+5 1.25E+4 Sr-90 1.08E+8 -1.65E+7 7.65E+5 6.68E+6 Y-91 6.61E+5 ---2.94E+6 4.09E+5 1.77E+4 Zr-95 1.46E+5 4.58E+4 -6.74E+4 2.69E+6 1.49E+5 3.15E+4 Nb-95 1.86E+4 1.03E+4 -1.OOE+4 7.51E+5 9.68E+4 5.66E+3 Ru-103 2.1OE+3 --7.43E+3 7.83E+5 1.09E+5 8.96E+2 Ru-106 9.84E+4 --1.90E+5 1.61E+7 9.60E+5 1.24E+4 Ag-il0m 1.38E+4 1.31E+4 -2.50E+4 6.75E+6 2.73E+5 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 -3.85E+6 3.98E+5 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 -2.74E+6 9.92E+4 1.72E+4 Te-125m 4.88E+3 2.24E+3 1.40E+3 -5.36E+5 7.50E+4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2.25E+3 1-131 3.54E+4 4.91E+4 1.46E+7 8.40E+4 6.49E+3 2.64E+4 1-132 1.59E+3 4.38E+3 1.51E+5 6.92E+3 1.27E+3 1.58E+3 1-133 1.22E+4 2.05E+4 2.92E+6 3.59E+4 1.03E+4 6.22E+3 1-134 8.88E+2 2.32E+3 3.95E+4 3.66E+3 2.04E+1 8.40E+2 1-135 3.70E+3 9.44E+3 6.21E+5 1.49E+4 -6.95E+3 3.49E+3 Cs-134 5.02E+5 1.13E+6 -3.75E+5 1.46E+5 9.76E+3 5.49E+5 Cs-136 5.15E+4 1.94E+5 -1.1OE+5 1.78E+4 1.09E+4 1.37E+5 Cs-137 6.70E+5 8.48E+5 -3.04E+5 1.21E+5 8.48E+3 3.11E+5 Ba-140 5.47E+4 6.70E+1 -2.28E+1 '2.03E+6 2.29E+5 3.52E+3 Ce-141 2.84E+4 1.90E+4 -8.88E+3 ;6.14E+5 1.26E+5 2.17E+3 Ce-144 4.89E+6 2.02E+6 -1.21E+6 !'1.34E+7 8.64E+5 2.62E+5 Pr-143 1.34E+4 5.31E+3 3.09E+3 4.83E+5 2.14E+5 6.62E+2 Nd-147 7.86E+3 8.56E+3 5.02E+3 3.72E+5 1.82E+5 5.13E+2 I I I I I I I I I I I I I I I I I 409 HOPE CREEK ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Inhalation Pathway Dose Factors -CHILD (mrem/yr per pCi/m3)H-3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 P-32 2.60E+6 1.14E+5 --4.22E+4 9.88E+4 Cr-51 --8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Mn-54 -4.29E+4 -1.00E+4 1.58E+6 2.29E+4 9.5 1E+3 Fe-55 4.74E+4 2.52E+4 -1.11E+5 2.87E+3 7.77E+3 Fe-59 2.07E+4 3.34E+4 -1.27E+6 7.07E+4 1.67E+4 Co-57 9.03E+2 -5.07E+5 1.32E+4 1.07E+3 Co-58 1.77E+3 -1.11E+6 3.44E+4 3.16E+3 Co-60 -1.31E+4 -7.07E+6 9.62E+4 2.26E+4 Ni-63 8.2 1E+5 4.63E+4 -2.75E+5 6.33E+3 2.80E+4 Zn-65 4.26E+4 1.13E+5 -7.14E+4 9.95E+5 1.63E+4 7.03E+4 Rb-86 -1.98E+5 --7.99E+3 1.14E+5 Sr-89 5.99E+5 -2.16E+6 1.67E+5 1.72E+4 Sr-90 1.O1E+8 -1.48E+7 3.43E+5 6.44E+6 Y-91 9.14E+5 --2.63E+6 1.84E+5 2.44E+4 Zr-95 1.90E+5 4.18E+4 5.96E+4 2.23E+6 6.1 1E+4 3.70E+4 Nb-95 2.35E+4 9.18E+3 8.62E+3 6.14E+5 3.70E+4 6.55E+3 Ru-103 2.79E+3 -7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-106 1.36E+5 -1.84E+5 1.43E+7 4.29E+5 1.69E+4 Ag-110m 1.69E+4 1.14E+4 2.12E+4 5.48E+6 1.00E+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 -3.24E+6 1.64E+5 2.OOE+4 Sb-125 9.84E+4 7.59E+2 9.10E+l -2.32E+6 4.03E+4 2.07E+4 Te-125m 6.73E+3 2.33E+3 1.92E+3 -4.77E+5 3.38E+4 9.14E+2 Te-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1.48E+6 7.14E+4 3.02E+3 Te-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4 1.76E+6 1.82E+5 3.04E+3 1-131 4.81E+4 4.81E+4 1.62E+7 7.88E+4 -2.84E+3 2.73E+4 1-132 2.12E+3 4.07E+3 1.94E+5 6.25E+3 -3.22E+3 1.88E+3 1-133 1.66E+4 2.03E+4 3.85E+6 3.38E+4 -5.48E+3 7.70E+3 1-134 1.17E+3 2.16E+3 5.07E+4 3.30E+3 -9.55E+2 9.95E+2 1-135 4.92E+3 8.73E+3 7.92E+5 1.34E+4 -4.44E+3 4.14E+3 Cs-134 6.51E+5 1.01E+6 -3.30E+5 1.21E+5 3.85E+3 2.25E+5 Cs-136 6.51E+4 1.71E+5 -9.55E+4 1.45E+4 4.18E+3 1.16E+5 Cs-137 9.07E+5 8.25E+5 -2.82E+5 1.04E+5 3.62E+3 1.28E+5 Ba-140 7.40E+4 6.48E+1 -2.1 1E+I 1.74E+6 1.02E+5 4.33E+3 Ce-141 3.92E+4 1.95E+4 -8.55E+3 5.44E+5 5.66E+4 2.90E+3 Ce-144 6.77E+6 2.12E+6 -1.17E+6 1.20E+7 3.89E+5 3.61E+5 Pr-143 1.85E+4 5.55E+3 -3.OOE+3 4.33E+5 9.73E+4 9.14E+2 Nd-147 1.08E+4 8.73E+3 4.81E+3 3.28E+5 8.21E+4 6.81E+2 410 HOPE CREEK ODCM REV. 261 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Inhalation Pathway Dose Factors -INFANT (mrem/yr per gCi/m3)H-3 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 P-32 2.03E+6 1.12E+5 ---1.61E+4 7.74E+4 Cr-51 -5.75E+l 1.32E+l 1.28E+4 3.57E+2 8.95E1+1 Mn-54 2.53E+4 4.98E+3 1.OOE+6 7.06E+3 4.98E+3 Fe-55 1.97E+4 1.17E+4 -8.69E+4 1.09E+3 3.33E+3 Fe-59 1.36E+4 2.35E+4 --1.02E+6 2.48E+4 9.48E+3 Co-57 6.51E+2 -3.79E+5 4.86E+3 6.41E+2 Co-58 -l.22E+3 -7.77E+5 1.11E+4 1.82E+3 Co-60 8.02E+3 -4.51E+6 3.19E+4 1.18E+4 Ni-63 3.39E+5 2.04E+4 -2.09E+5 2.42E+3 1.16E+4 Zn-65 1.93E+4 6.26E+4 -3.25E+4 6.47E+5 5.14E+4 3.11E+4 Rb-86 1.90E+5 -3.04E+3 8.82E+4 Sr-89 3.98E+5 --2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 --1.12E+7 1.31E+5 2.59E+6 Y-91 5.88E+5 ---2.45E+6 7.03E+4 1.57E+4 Zr-95 1.15E+5 2.79E+4 -3.11E+4 1.75E+6 2.17E+4 2.03E+4 Nb-95 1.57E+4 6.43E+3 -4.72E+3 4.79E+5 1.27E+4 3.78E+3 Ru-103 2.02E+3 --4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-106 8.68E+4 --1.07E+5 1.16E+7 1.64E+5 1.09E+4 Ag-110m 9.98E+3 7.22E+3 -1.09E+4 3.67E+6 3.30E+4 5.OOE+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 -2.65E+6 5.91E+4 1.20E+4 Sb-125 5.17E+4 4.77E+2 6.23E+1 -1.64E+6 1.47E+4 1.09E+4 Te-125m 4.76E+3 1.99E+3 1.62E+3 -4.47E+5 1.29E+4 6.58E+2 Te-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 Te-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+3 1-131 3.79E+4 4.44E+4 1.48E+7 5.18E+4 -1.06E+3 1.96E+4 1-132 1.69E+3 3.54E+3 1.69E+5 3.95E+5 -1.90E+3 1.26E+3 1-133 1.32E+4 1.92E+4 3.56E+6 2.24E+4 -2.61E+3 5.60E+3 1-134 9.21E+2 1.88E+3 4.45E+4 2.09E+3 -1.29E+3 6.65E+2 1-135 3.86E+3 7.60E+3 6.96E+5 8.47E+3 -1.83E+3 2.77E+3 Cs-134 3.96E+5 7.03E+5 -1.90E+5 7.97E+4 1.33E+3 7.45E+4 Cs-136 4.83E+4 1.35E+5 -5.64E+4 1.18E+4 1.43E+3 5.29E+4 Cs-137 5.49E+5 6.12E+5 -1.72E+5 7.13E+4 1.33E+3 4.55E+4 Ba-140 5.60E+4 5.60E+1 -1.34E+1 1.60E+6 3.84E+4 2.90E+3 Ce-141 2.77E+4 1.67E+4 -5.25E+3 5.17E+5 2.16E+4 1.99E+3 Ce-144 3.19E+6 1.21E+6 -5.38E+5 9.84E+6 1.48E+5 1.76E+5 Pr-143 1.40E+4 5.24E+3 1.97E+3 4.33E+5 3.72E+4 6.99E+2 Nd-147 7.94E+3 8.13E+3 3.15E+3 3.22E+5 3.12E+4 5.OOE+2 I I I I I I I I I I I I I I I I I I 411 HOPE CREEK ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors -ADULT (mrem/yr per gtCi/m3) for H-3 and C-14 (m2

mrem/yr per gCi/sec) for others IN Thyroid Kide Lo,," H-3 -7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 P-32 1.71E+10 1.06E+9 -- -1.92E+9 6.60E+8 Cr-51 -1.71E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Mn-54 -8.40E+6 -2.50E+6 -2.57E+7 1.60E+6 Fe-55 2.51E+7 1.73E+7 -9.67E+6 9.95E+6 4.04E+6 Fe-59 2.98E+7 7.OOE+7 1.95E+7 2.33E+8 2.68E+7 Co-57 -1.28E+6 -3.25E+7 2.13E+6 Co-58 -4.72E+6 -- i 9.57E+7 1.06E+7 Co-60 -1.64E+7 -3.08E+8 3.62E+7 Ni-63 6.73E+9 4.66E+8 -9.73E+7 2.26E+8 Zn-65 1.37E+9 4.36E+9 2.92E+9 -2.75E+9 1.97E+9 Rb-86 -2.59E+9 -5.11E+8 1.21E+9 Sr-89 1.45E+9 -2.33E+8 4.16E+7 Sr-90 4.68E+10 -1.35E+9 1.15E+10 Y-91 8.60E+3 -4.73E+6 2.30E+2 Zr-95 9.46E+2 3.03E+2 4.76E+2 -9.62E+5 2.05E+2 Nb-95 8.25E+4 4.59E+4 4.54E+4 -2.79E+8 2.47E+4 Ru-103 1.02E+3 -3.89E+3 -1.19E+5 4.39E+2 Ru-106 2.04E+4 3.94E+4 -1.32E+6 2.58E+3 Ag-ll0m 5.83E+7 5.39E+7 1.06E+8 -2.20E+10 3.20E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 2.OOE+7 7.31E+8 1.02E+7 Sb-125 2.04E+7 2.28E+5 2.08E+4 1.58E+7 2.25E+8 4.86E+6 Te-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 -6.50E+7 2.18E+6 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 -1.54E+8 5.58E+6 Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 -3.04E+8 9.57E+6 1-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 -1.12E+8 2.43E+8 1-132 1.64E-1 4.37E-1 1.53E+1 6.97E-1 -8.22E-2 1.53E-1 1-133 3.97E+6 6.90E+6 1.01E+9 1.20E+7 -6.20E+6 2.1OE+6 1-134 .- 135 1.39E+4 3.63E+4 2.40E+6 5.83E+4 4.1OE+4 1.34E+4 Cs-134 5.65E+9 1.34E+10 -4.35E+9 1.44E+9 2.35E+8 1.10E+10 Cs-136 2.61E+8 1.03E+9 -5.74E+8 7.87E+7 1.17E+8 7.42E+8 Cs-137 7.38E+9 1.01E+10 -3.43E+9 1.14E+9 1.95E+8 6.61E+9 Ba-140 2.69E+7 3.38E+4 -1.15E+4 1.93E+4 5.54E+7 1.76E+6 Ce-141 4.84E+3 3.27E+3 -1.52E+3 -1.25E+7 3.71E+2 Ce-144 3.58E+5 1.50E+5 -8.87E+4 -1.21E+8 1.92E+4 Pr-143 1.59E+2 6.37E+1 -3.68E+1 -6.96E+5 7.88E+O Nd-147 9.42E+1 1.09E+2 -6.37E+1 -5.23E+5 6.52E+O 412 HOPE CREEK ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors -TEENAGER (mrem/yr per ptCi/m3) for H-3 and C-i 4 (m2

mrem/yr per jCi/sec) for others H-3 -9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 P-32 3.15E+10 1.95E+9 -2.65E+9 1.22E+9 Cr-51 --2.78E+4 1.1OE+4 7.13E+4 8.40E+6 5.OOE+4 Mn-54 -1.40E+7 -4.17E+6 2.87E+7 2.78E+6 Fe-55 4.45E+7 3.16E+7 --2.OOE+7 1.37E+7 7.36E+6 Fe-59 5.20E+7 1.21E+8 --3.82E+7 2.87E+/-8 4.68E+7 Co-57 2.25E+6 --4.19E+7 3.76E+6 Co-58 7.95E+6 --.1OE+8 1.83E+7 Co-60 -2.78E+7 -3.62E+/-8 6.26E+7 Ni-63 1.18E+10 8.35E+8 -1.33E+8 4.01E+8 Zn-65 2.11E+9 7.31E+9 -4.68E+9 -3.1OE+9 3.41E+9 Rb-86 -4.73E+9 -7.OOE+8 2.22E+9 Sr-89 2.67E+9 --3.18E+8 7.66E+7 Sr-90 9.92E+7 -9.60E+6 7.22E+5 6.1OE+6 Y-91 1.58E+4 --6.48E+6 4.24E+2 Zr-95 1.65E+3 5.22E+2 -7.67E+2 1.20E+6 3.59E+2 Nb-95 1.41E+5 7.80E+4 -7.57E+4 3.34E+8 4.30E+4 Ru-103 1.81E+3 --6.40E+3 1.52E+5 7.75E+2 Ru-106 3.75E+4 --7.23E+4 1.80E+6 4.73E+3 Ag-ll0m 9.63E+7 9.11E+7 -1.74E+8 -2.56E+10 5.54E+7 Sb-124 4.59E+7 8.46E+5 1.04E+5 -4.01E+7 9.25E+8 1.79E+7 Sb-125 3.65E+7 3.99E+5 3.49E+4 3.21E+7 2.84E+8 8.54E+6 Te-125m 3.OOE+7 1.08E+7 8.39E+6 8.86E+7 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 2.1OE+8 1.00E+7 Te-129m 1.11E+8 4.1OE+7 3.57E+7 4.62E+8 4.15E+8 1.75E+7 1-131 5.38E+8 7.53E+8 2.20E+11 1.30E+9 1.49E+8 4.04E+8 1-132 2.90E-1 7.59E-1 2.56E+1 1.20E+O 3.31E-1 2.72E-1 1-133 7.24E+6 1.23E+7 1.72E+9 2.15E+7 9.30E+6 3.75E+6 1-134 ---1-135 2.47E+4 6.35E+4 4.08E+6 1.00E+5 7.03E+4 2.35E+4 Cs-134 9.81E+9 2.31E+10 -7.34E+9 2.80E+9 2.87E+8 1.07E+10 Cs-136 4.45E+8 1.75E+9 -9.53E+8 1.50E+8 1.41E+8 1.18E+9 Cs-137 1.34E+10 1.78E+10 -6.06E+9 2.35E+9 2.53E+8 6.20E+9 Ba-140 4.85E+7 5.95E+4 -2.02E+4 4.OOE+4 7.49E+7 3.13E+6 Ce-141 8.87E+3 1.35E+4 -2.79E+3 1.69E+7 6.81E+2 Ce-144 6.58E+5 2.72E+5 -1.63E+5 1.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 -6.77E+1 9.61E+5 1.45E+1 Nd-147 1.81E+2 1.97E+2 -1.16E+2 -7.11E+5 1.18E+1 I I I I I I I I I I I I I I I I I 413 HOPE CREEK ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors -CHILD (mrem/yr per gCi/m3) for H-3 and C-14 (m2

mrem/yr per gCi/sec) for others H-3 -1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 P-32 7.77E+10 3.64E+9 --2.15E+9 3.OOE+9 Cr-51 --5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 Mn-54 -2.09E+7 -5.87E+6 -1.76E+7 5.58E+6 Fe-55 1.12E+8 5.93E+7 -3.35E+7 1.1OE+7 1.84E+7 Fe-59 1.20E+8 1.95E+8 -5.65E+7 2.03E+8 9.71E+7 Co-57 -3.84E+6 -3.14E+7 7.77E+6 Co-58 -1.21E+7 -7.08E+7 3.72E+7 Co-60 -4.32E+7 -2.39E+8 1.27E+8 Ni-63 2.96E+10 1.59E+9 -1.07E+8 1.O1E+9 Zn-65 4.13E+9 1.10E+10 6.94E+9 -1.93E+9 6.85E+9 Rb-86 8.77E+9 --5.64E+8 5.39E+9 Sr-89 6.62E+9 --2.56E+8 1.89E+8 Sr-90 1.12E+11 --1 1.51E+9 2.83E+10 Y-91 3.91E+4 --5.21E+6 1.04E+3 Zr-95 3.84E+3 8.45E+2 1.21E+3 8.81E+5 7.52E+2 Nb-95 3.18E+5 1.24E+5 1.16E+5 -2.29E+8 8.84E+4 Ru-103 4.29E+3 -1.08E+4 1.11E+5 1.65E+3 Ru-106 9.24E+4 -1.25E+5 1.44E+6 1.15E+4 Ag-110m 2.09E+8 1.41E+8 2.63E+8 1.68E+10 1.13E+8 Sb-124 1.09E+8 1.41E+8 2.40E+5 -6.03E+7 6.79E+8 3.81E+7 Sb-125 8.70E+7 1.41E+6 8.06E+4 -4.85E+7 2.08E+8 1.82E+7 Te-125m 7.38E+7 2.OOE+7 2.07E+7 -7.12E+7 9.84E+6 Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 1.68E+8 2.47E+7 Te-129m 2.72E+8 7.61E+7 8.78E+7 8.OOE+8 3.32E+8 4.23E+7 1-131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 1.17E+8 7.46E+8 1-132 6.86E-1 1.26E+O 5.85E+1 1.93E+O 1.48E+O 5.80E-1 1-133 1.76E+7 2.18E+7 4.04E+9 3.63E+7 8.77E+6 8.23E+6 1-134 --1-135 5.84E+4 1.05E+5 9.30E+6 1.61E+5 8.OOE+4 4.97E+4 Cs-134 2.26E+10 3.71E+10 -1.15E+10 4.13E+9 2.OOE+8 7.83E+9 Cs- 136 1.00E+9 2.76E+9 -1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs-137 3.22E+10 3.09E+10 -1.01E+10 3.62E+9 1.93E+8 4.55E+9 Ba-140 1.17E+8 1.03E+5 -3.34E+4 6.12E+4 5.94E+7 6.84E+6 Ce-141 2.19E+4 1.09E+4 -4.78E+3 1.36E+7 1.62E+3 Ce-144 1.62E+6 5.09E+5 -2.82E+5 1.33E+8 8.66E+4 Pr-143 7.23E+2 2.17E+2 -1.17E+2 7.80E+5 3.59E+1 Nd-147 4.45E+2 3.60E+2 -1.98E+2 5.71E+5 2.79E+1 414 HOPE CREEK ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors -INFANT (mrem/yr per jtCi/m3) for H-3 and C-14 (m2

mrem/yr per ptCi/sec) for others H-3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 P-32 1.60E+1I 9.42E+9 --2.17E+9 6.21E+9 Cr-51 -1.05E+5 2.30E+4 2.05E+5 4.71E+6 1.61E+5 Mn-54 -3.89E+7 -8.63E+6 1.43E+7 8.83E+6 Fe-55 1.35E+8 8.72E+7 --4.27E+7 1.11E+7 2.33E+7 Fe-59 2.25E+8 3.93E+8 --1.16E+8 1.88E+8 1.55E+8 Co-57 -8.95E+6 ---3.05E+7 1.46E+7 Co-58 2.43E-7 ---6.05E+7 6.06E+7 Co-60 -8.81E-7 0 --2.1OE+8 2.08E+8 Ni-63 3.49E+10 2.16E+9 ---1.07E+8 1.21E+9 Zn-65 5.55E+9 1.90E+10 -9.23E+9 -1.61E+10 8.78E+9 Rb-86 -2.22E+10 --5.69E+8 1.10E+10 Sr-89 1.26E+10_

---2.59E+8 3.61E+8 Sr-90 1.22E+11 ---1.52E+9 3.10E+10 Y-91 7.33E+4 -- -5.26E+6 1.95E+3 Zr-95 6.83E+3 1.66E+3 -1.79E+3 -8.28E+5 1.18E+3 Nb-95 5.93E+5 2.44E+5 -1.75E+5 -2.06E+8 1.41E+5 Ru-103 8.69E+3 1- .81E+4 -1.06E+5 2.91E+3 Ru-106 1.90E+5 -2.25E+5 -1.44E+6 2.38E+4 Ag-ll0m 3.86E+8 2.82E+8 -4.03E+8 -1.46E+10 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E+5 -1.31E+8 6.46E+8 6.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 9.38E+7 1.99E+8 3.07E+7 Te-125m 1.51E+8 5.04E+7 5.07E+7 -7.18E+7 2.04E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 1.70E+8 5.10E+7 Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 -3.34E+8 8.62E+7 1-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 -1.15E+8 1.41E+9 1-132 1.42E+O 2.89E+O 1.35E+2 3.22E+O -2.34E+O 1.03E+O 1-133 3.72E+7 5.41E+7 9.84E+9 6.36E+7 -9.16E+6 1.58E+7 1-134 --1.01E-9 --1-135 1.21E+5 2.41E+5 2.16E+7 2.69E+5 8.74E+4 8.80E+4 Cs-134 3.65E+10 6.80E+10 -1.75E+10 7.18E+9 1.85E+8 6.87E+9 Cs-136 1.96E+9 5.77E+9 -2.30E+9 4.70E+8 8.76E+7 2.15E+9 Cs-137 5.15E+10 6.02E+10 -1.62E+10 6.55E+9 1.88E+8 4.27E+9 Ba-140 2.41E+8 2.41E+5 -5.73E+4 1.48E+5 5.92E+7 1.24E+7 Ce-141 4.33E+4 2.64E+4 -8.15E+3 1.37E+7 3.11E+3 Ce-144 2.33E+6 9.52E+5 -3.85E+5 1.33E+8 1.30E+5 Pr-143 1.49E+3 5.59E+2 2.08E+2 7.89E+5 7.41E+1 Nd-147 8.82E+2 9.06E+2 3.49E+2 5.74E+5 5.55E+1 I I I I I I I I I I I I I I I I I.415 HOPE CREEK ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Vegetation Pathway Dose Factors -ADULT (mrem/yr per gtCi/m3) for H-3 and C-14 (m2

mrem/yr per gCi/sec) for others H-3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 P-32 1.40E+9 8.73E+7 -1.58E+8 5.42E+7 Cr-51 --2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 Mn-54 -3.11E+8 -9.27E+7 -9.54E+8 5.94E+7 Fe-55 2.09E+8 1.45E+8 -8.06E+7 8.29E+7 3.37E+7 Fe-59 1.27E+8 2.99E+8 -8.35E+7 9.96E+8 1.14E+8 Co-57 -1.17E+7 -2.97E+8 1.95E+7 Co-58 -3.09E+7 --6.26E+8 6.92E+7 Co-60 -1.67E+8 --3.14E+9 3.69E+8 Ni-63 1.04E+10 7.21E+8 --1.50E+8 3.49E+8 Zn-65 3.17E+8 1.01E+9 -6.75E+8 -6.36E+8 4.56E+8 Rb-86 2.19E+8 ---4.32E+7 1.02E+8 Sr-89 9.96E+9 ----1.60E+9 2.86E+8 Sr-90 6.05E+11 ---1.75E+10 1.48E+10 Y-91 5.13E+6 ---2.82E+9 1.37E+5 Zr-95 1.19E+6 3.81E+5 -5.97E+5 -1.21E+9 2.58E+5 Nb-95 1.42E+5 7.91E+4 -7.81E+4 -4.80E+8 4.25E+4 Ru-103 4.80E+6 --1.83E+7 -5.61E+8 2.07E+6 Ru-106 1.93E+8 --3.72E+8 -1.25E+10 2.44E+7 Ag-110m 1.06E+7 9.76E+6 -1.92E+7 -3.98E+9 5.80E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 -8.08E+7 2.95E+9 4.11E+7 Sb-125 1.36E+8 1.52E+6 1.39E+5 -1.05E+8 1.50E+9 3.25E+7 Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 -3.86E+8 1.29E+7 Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 -1.17E+9 4.26E+7 Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 -1.28E+9 4.03E+7 1-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 -3.05E+7 6.63E+7 1-132 5.74E+1 1.54E+2 5.38E+3 2.45E+2 -2.89E+1 5.38E+1 1-133 2.12E+6 3.69E+6 5.42E+8 6.44E+6 -3.31E+6 1.12E+6 1-134 1.06E-4 2.88E-4 5.OOE-3 4.59E-4 -2.51E-7 1.03E-4 1-135 4.08E+4 1.07E+5 7.04E+6 1.71E+5 -1.21E+5 3.94E+4 Cs-134 4.66E+9 1.11E+10 -3.59E+9 1.19E+9 1.94E+8 9.07E+9 Cs-136 420E+7 1.66E+8 -9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-137 6.36E+9 8.70E+9 -2.95E+9 9.81E+8 1.68E+8 5.70E+9 Ba-140 1.29E+8 1.62E+5 -5.49E+4 9.25E+4 2.65E+8 8.43E+6 Ce-141 1.96E+5 1.33E+5 -6.17E+4 -5.08E+8 1.51E+4 Ce-144 3.29E+7 1.38E+7 -8.16E+6 -1.11E+10 1.77E+6 Pr-143 6.34E+4 2.54E+4 -1.47E+4 -2.78E+8 3.14E+3 Nd-147 3.34E+4 3.86E+4 -2.25E+4 -1.85E+8 2.31E+3 416 HOPE CREEK ODCM REV. 26 1 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Vegetation Pathway Dose Factors -TEENAGER (mrem/yr per gCi/m3) for H-3 and C-14 (m2

mrem/yr per jtCi/sec) for others H-3 -2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 P-32 1.61E+9 9.96E+7 -1.35E+8 6.23E+7 Cr-51 --3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Mn-54 -4.52E+8 1.35E+8 9.27E+8 8.97E+7 Fe-55 3.25E+8 2.3 1E+8 -1.46E+8 9.98E+7 5.38E+7 Fe-59 1.81E+8 4.22E+8 -1.33E+8 9.98E+8 1.63E+8 Co-57 -1.79E+7 --3.34E+8 3.OOE+7 Co-58 -4.38E+7 --6.04E+8 1.01E+8 Co-60 -2.49E+8 --3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13E+9 --1.81E+8 5.45E+8 Zn-65 4.24E+8 1.47E+9 -9.41E+8 -6.23E+8 6.86E+8 Rb-86 -2.73E+8 -4.05E+7 1.28E+8 Sr-89 1.51E+10 ---1.80E+9 4.33E+8 Sr-90 7.51E+11 ---2.11E+10 1.85E+11 Y-91 7.87E+6 ---3.23E+9 2.11E+5 Zr-95 1.74E+6 5.49E+5 -8.07E+5 -1.27E+9 3.78E+5 Nb-95 1.92E+5 1.06E+5 -1.03E+5 -4.55E+8 5.86E+4 Ru-103 6.87E+6 --2.42E+7 -5.74E+8 2.94E+6 Ru-106 3.09E+8 -5.97E+8 -1.48E+10 3.90E+7 Ag-110m 1.52E+7 1.44E+7 -2.74E+7 -4.04E+9L 8.74E+6 Sb-124 1.55E+8 2.85E+6 3.51E+5 -1.35E+8 3.11E+9 6.03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+5 -1.88E+8 1.66E+9 5.OOE+7 Te-125m 1.48E+8 5.34E+7 4.14E+7 --4.37E+8 1.98E+7 Te-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 -1.37E+9 6.56E+7 Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 -1.38E+9 5.81E+7 1-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 -2.13E+7 5.79E+7 1-132 5.18E+1 1.36E+2 4.57E+3 2.14E+2 -5.91E+1 4.87E+1 1-133 1.97E+6 3.34E+6 4.66E+8 5.86E+6 -2.53E+6 1.02E+6 1-134 9.59E-5 2.54E-4 4.24E-3 4.01E-4 -3.35E-6 9.13E-5 1-135 3.68E+4 9.48E+4 6.1OE+/-6 1.50E+5 -1.05E+5 3.52E+4 Cs-134 7.09E+9 1.67E+10 -5.30E+9 2.02E+9 2.08E+8 7.74E+9 Cs-136 4.29E+7 1.69E+8 -9.19E+7 1.45E+7 1.36E+7 1.13E+8 Cs-137 1.01E+10 1.35E+10 -4.59E+9 1.78E+9 1.92E+8 4.69E+9 Ba-140 1.38E+8 1.69E+5 -5.75E+4 1.14E+5 2.13E+8 8.91E+6 Ce-141 2.82E+5 1.88E+5 -8.86E+4 5.38E+8 2.16E+4 Ce-144 5.27E+7 2.18E+7 -1.30E+7 1.33E+10 2.83E+6 Pr-143 7.12E+4 2.84E+4 -1.65E+4 2.34E+8 3.55E+3 Nd-147 3.63E+4 3.94E+4 -2.32E+4 1.42E+8 2.36E+3 I I I I I I I I I I I I I I I I I 417 HOPE CREEK ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Vegetation Pathway Dose Factors -CHILD (mrem/yr per ptCi/m3) for H-3 and C-14 (m2

mrem/yr per [tCi/sec) for others H-3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 P-32 3.37E+9 1.58E+8 -9.30E+7 1.30E+8 Cr-51 6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 Mn-54 -6.61E+8 -1.85E+8 5.55E+8 1.76E+8 Fe-55 8.00E+8 4.24E+8 -2.40E+8 7.86E+7 1.31E+8 Fe-59 4.01E+8 6.49E+8 -1.88E+8 6.76E+8 3.23E+8 Co-57 2.99E+7 -2.45E+8 6.04E+7 Co-58 6.47E+7 .3.77E+8 1.98E+8 Co-60 3.78E+8 -2.1OE+9 1.12E+9 Ni-63 3.95E+10 2.11E+9 -1.42E+8 1.34E+9 Zn-65 8.12E+8 2.16E+9 -1.36E+9 -3.80E+8 1.35E+9 Rb-86 -4.52E+8 -2.91E+7 2.78E+8 Sr-89 3.59E+ 10 --1.39E+9 l.03E+9 Sr-90 1.24E+12 --1.67E+10 3.15E+11 Y-91 1.87E+7 --2.49E+9 5.01E+5 Zr-95 3.90E+6 8.58E+5 1.23E+6 -8.95E+8 7.64E+5 Nb-95 4.1OE+5 1.59E+5 1.50E+5 -2.95E+8 1.14E+5 Ru-103 1.55E+7 3.89E+7 -3.99E+8 5.94E+6 Ru-106 7.45E+8 1.01E+9 -1.16E+10 9.30E+7 Ag-110m 3.22E+7 2.17E+7 4.05E+7 -2.58E+9 1.74E+7 Sb-124 3.52E+8 4.57E+6 7.78E+5 1.96E+8 2.20E+9 1.23E+8 Sb-125 4.99E+8 3.85E+6 4.62E+5 2.78E+8 1.19E+9 1.05E+8 Te-125m 3.51E+8 9.50E+7 9.84E+7 -3.38E+8 4.67E+7 Te-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 -1.07E+9 1.57E+8 Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 -1.04E+9 1.33E+8 1-131 1.43E+8 1.44E+8 4.76E+10 2.36E+8 -1.28E+7 8.18E+7 1-132 9.20E+1 1.69E+2 7.84E+3 2.59E+2 -1.99E+2 7.77E+1 1-133 3.59E+6 4.44E+6 8.25E+8 7.40E+6 -1.79E+6 1.68E+6 1-134 1.70E-4 3.16E-4 7.28E-3 4.84E-4 -2.1OE-4 1.46E-4 1-135 6.54E+4 1.18E+5 1.04E+/-7 1.81E+5 -8.98E+4 5.57E+4 Cs-134 1.60E+10 2.63E+10 -8.14E+9 2.92E+9 1.42E+8 5.54E+9 Cs-136 8.06E+7 2.22E+8 -1.18E+8 1.76E+7 7.79E+6 1.43E+8 Cs-137 2.39E+10 2.29E+10 -7.46E+9 2.68E+9 1.43E+8 3.38E+9 Ba-140 2.77E+8 2.43E+5 -7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ce-141 6.35E+5 3.26E+5 -1.43E+5 -4.07E+8 4.84E+4 Ce-144 1.27E+8 3.98E+7 -2.21E+7 -1.04E+10 6.78E+6 Pr-143 1.48E+5 4.46E+4 -2.41E+4 -1.60E+8 7.37E+3 Nd-147 7.16E+4 5.80E+4 -3.18E+4 -9.18E+7 4.49E+3 418 HOPE CREEK ODCM REV. 26 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Ground Plane Pathway Dose Factors (m2

mrem/yr per [Ci/sec)Nuclide Any Organ H-3 I C-14 P-32 Cr-51 4.68E+6 Mn-54 1.34E+9 Fe-55 Fe-59 2.75E+8 Co-58 3.82E+8 Co-60 2.16E+10 Ni-63 Zn-65 7.45E+8 Rb-86 8.98E+6 Sr-89 2.16E+4 Sr-90 Y-91 1.08E+6 Zr-95 2.48E+8 Nb-95 1.36E+8 Ru-103 1.09E+8 Ru-106 4.21E+8 Ag-110m 3.47E+9 Te-125m 1.55E+6 Te-127m 9.17E+4 Te-129m 2.OOE+7 I 1-131 1.72E+7 1-132 1.24E+6 1-133 2.47E1+6 1-134 4.49E+5 1-135 2.56E+6 Cs-134 6.75E+9 Cs-136 1.49E+8 Cs-137 1.04E+10i Ba-140 2.05E+7 Ce-141 1.36E+7 Ce-144 6.95E+7 Pr- 143 Nd-147 8.40E+6 419 HOPE CREEK ODCM REV. 26 APPENDIX A EVALUATION OF DEFAULT MPC VALUES FOR LIQUID EFFLUENTS 420 HOPE CREEK ODCM REV. 26 APPENDIX A: Evaluation of Default MPC Value for Liquid Effluent Monitors I In accordance with the requirements of CONTROL 3.3.7.10 the radioactive effluent monitors shalln be operable with alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed the MPC value of 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F). The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual monitor.In order to limit the need for routinely having to re-establish the alarm setpoints as a function of changing radionuclide distributions, a default alarm setpoint can be established.

This default setpoint can be based on an evaluation of the radionuclide distribution from the 1997 to 1999 release data of the liquid effluents from Hope Creek' and the effective MPC value for this distribution.

The effective MPC value for a radionuclide distribution is calculated by the equation:Ci(gamma)MPCe i (A.1)Uc (gamma)where: MPCe = an effective MPC value for a mixture of radionuclides (ptCi/ml)Ci = concentration of radionuclide i in the mixture MIPCi = the 10 CFR 20, Appendix B, Table II, Column II MPC value for radionuclide i (gaCi/ml)

Appendix F Considering the average effective MPC values from 1997 thru 1999 releases it is reasonable to i select an MPC value of 4.09E-5 pCi/ml as typical of liquid radwaste discharges.

This value will be reviewed and adjusted as necessary based on the distribution history of effluents from Hope Creek.Using the value of 4.09E-5 gtCi/ml to calculate the default alarm setpoint, results in a setpoint that: (1) Will not require frequent re-adjustment due to minor variations in the nuclide distribution which are typical of routine plant operations, and; I (2) Will provide for a liquid radwaste discharge rate (as evaluated for each batch release) that is compatible with plant operations (Refer to Table 1-1).I 421I HOPE CREEK ODCM REV. 26 1.0 Default Setpoint Determination:

Conservative alarm setpoints can be determined through the use of default parameters.

Table 1-1 summarizes all current default values in use for Hope Creek.A. Liquid Radwaste Monitor (RE4861)SP CTBD*[1-CF]

+bkg (1.2)RR Default values from Table 1-1: MPCe 4.09E-5 gCi/ml CTBD = 12000 gpm RR = 176 gpm (LRW)Bkg = 0 ICi/ml CF = 0.8 4.09E-5

12000

0.2 SP< +----------------------------

0 176 SP < 5.58E-4 uCi/ml Correction Factor: A correction factor must be applied to the default setpoint calculation in order to account for radiation monitor uncertainties and the contribution of non-gamma emitting radionuclides.

such as H-3, Sr, and Fe.a. Radiation Monitor Inaccuracies:

Hope Creek PSBP 311649 lists a total loop accuracy of 30% for the liquid radwaste radiation monitors.

A factor of 0.30 is applied to the default setpoint to ensure the trip setpoint is reached before the analytical limit is obtained.422 HOPE CREEK ODCM REV. 26 b. Non-Gamma Emitting Radionuclides:

Non-gamma emitting radionuclides are analyzed on a monthly and quarterly basis from composite samples of liquid radwaste releases.Nuclide MPC (jLCi/ml)

Activity (gCi/ml) Activity / MPC H-3 3E-3 L.OE-1 33.3 Fe-55 8E-4 4.7E-4 0.59 Sr-89 3E-6 1.6E-6 0.53 Sr-90 3E-7 2.OE-8 0.07 Total 34.5 The values in the table above represent the historical maximum reactor coolant values for non-gamma emitting nuclides (H3 is an assumed maximum).

Reactor coolant values were chosen to represent the maximum concentration of non-gamma emitting radionuclides that could be released from Hope Creek station in liquid effluent.

The activity values in the table are further diluted by a minimum factor of 68 prior to release to the Delaware River. The minimum dilution factor is obtained by using the minimum cooling tower blowdown flowrate of 12,000 gpm and the maximum release rate of 176 gpm.A conservative correction factor for non-gamma emitting radionuclides can be obtained by using the highest Activity / MPC fraction and the minimum dilution factor as follows: Correction Factor (non-gamma)

= 34.5 / 68 = 0.5 An overall correction factor can be obtained by adding the correction factor for radiation monitor inaccuracies and non-gamma emitting radionuclides as follows: Overall Correction factor = 0.3 + 0.5 = 0.8 B. Cooling Tower Blowdown Radiation Monitor (RE8817)The cooling tower blowdown radiation monitor provides an Alarm only function for releases into the environment.

The cooling tower blowdown is the final release point for liquid effluents from Hope Creek station to the Delaware River.SP < MPCe *0.2 SP < 4.09E-5 ptCi/ml

0.2 SP < 8.18E-6 uCi/ml (RE8817)423 I I I I I I I I I I I I I

-HOPE CREEK ODCM REV. 26 C. Turbine Building Circulating Water Dewatering Sump Radiation Monitor (RE4557)The Turbine Building Circulating Water Dewatering Sump Radiation Monitor (RE4557) provides automatic termination of liquid radioactive releases from the Circulating Water Dewatering Sump.The sump pumps discharge to the circulating water system to the cooling tower. Plant design and procedures maintain the setpoint at <2 times background radiation levels. Releases from the sump at gamma activity concentrations less than the monitor setpoint are considered continuous releases since inputs to the sump would occur during discharge.

Releases of activity above the established continuous release setpoint may be performed on a batch basis following sampling and analysis of the sump contents.

Hope Creek calculation SP-0004 established a setpoint for the monitor at 1.4E-02 [tCi/ml based on a postulated release of reactor steam into the sump. Using the MPCe determined for Liquid Radwaste and Cooling Tower Blowdown monitors, a more conservative maximum default value for batch releases can be determined:

SP:< MPCe

CTBD * [1- CF] + bkg (1.2)RR Default values from Table 1-1: MPCe = 4.09E-5 ýtCi/ml CTBD = 12000 gpm RR = 100gpm Bkg = 0 iiCi/ml CF = 0.8 4.09E-5

12000

0.2 SP< +----------------------------

0 100 SP < 9.82E-4 uCi/ml (batch releases only)For continuous releases, the maximum setpoint should be less than 2.4E-6 pjCi/ml above background to limit dose consequences from this pathway. (4HE-0241, CVF-98-0002) 424 HOPE CREEK ODCM REV. 26 D. Releases from the Condensate Storage Tank If the Condensate Storage Tank (CST) requires release to the Delaware River', the discharge path would be through installed piping connected to the liquid Radwaste discharge path such that both the Liquid Radwaste Discharge Monitor and the Cooling Tower Blowdown monitor could detect and isolate/alarm on unexpected activity.

Default setpoints are determined for potential releases of the CST. 3 a. Liquid Radwaste Monitor (RE4861)MPCe

CTBD * [1- CF]SP +bkg (1.2)3 Default values from Table 1-1: m MPCe = 4.09E-5 ýtCi/ml CTBD = 12000 gpm RR = 1300 gpm Bkg = 0 ýiCi/ml CF = 0.8 4.09E-5

12000

0.2 SP_< ---------------------------

+ 0 1300 SP < 7.55E-5 uCi/ml (RE4861)b. Cooling Tower Blowdown Radiation Monitor (RE8817)The cooling tower blowdown radiation monitor provides an Alarm only function for releases into the environment.

The cooling tower blowdown is the final release point for liquid effluents from Hope Creek station to the Delaware River.SP < MPCe *0.2 SP < 4.09E-5 ptCi/ml

0.2 SP < 8.18E-6 uCi/ml (RE8817)425 HOPE CREEK ODCM REV. 26 TABLE A-i: CALCULATION OF EFFECTIVE MPC -HOPE CREEK 1997 ACTIVITY RELEASED (Ci)1998 ACTIVITY RELEASED (Ci)1999 ACTIVITY RELEASED (Ci)NUCLIDE Cr-51 Mn-54 Mn-56 CO-58 Co-60 Na-24 Cs-137 Zn-65 Zn-69m Fe-59 As-76 Nb-95 Mo-99 Zr-95 Tc-99m Ru-105 Ag-i 10m Sb-124 Cs-134 1-133 La-140 H-3 Fe-55 Sr-89 MPC 2.OOE-03 1.00E-04 1.OOE-04 9.OOE-05 3.OOE-05 3.OOE-05 2.OOE-05 1.OOE-04 6.OOE-05 5.OOE-05 2.OOE-05 1.OOE-04 4.OOE-05 6.OOE-05 3.OOE-03 1.OOE-04 3.OOE-05 2.OOE-05 9.OOE-06 1.OOE-06 2.OOE-05 3.OOE-03 8.OOE-04 3.OOE-06 7.44E-03 1.74E-02 N/D 5.68E-04 7.05E-03 N/D 2.84E-06 1.29E-03 1.58E-05 2.65E-03 7.70E-05 N/D 9.56E-05 N/D 1.29E-04 N/D 4.85E-05 N/D N/D N/D N/D 1.24E+01 2.28E-01 8.56E-03 3.68E-02 4.93E+02 7.27E+03 7.45E-05 2.37E-02 7.48E-03 N/D 7.67E-04 6.78E-03 7.02E-02 1.03E-06 1.39E-03 N/D 1.62E-04 N/D N/D N/D N/D 2.05E-04 N/D 1.36E-05 N/D N/D 3.11E-05 N/D 2.76E+01 6.40E-03 1.34E-05 1.11E-01 2.7 1E+03 9.2 1E+03 4.09E-05 1.66E-02 6.87E-02 9.36E-06 3.30E-03 2.05E-02 1.01E-03-2.23E-04 3.37E-03 2.64E-04 1.72E-02 9.94E-05 1.69E-04 N/D 4.08E-05 3.35E-04 4.45E-05 3.88E-04 4.63E-05 7.13E-05 N/D 4.82E-06 2.95E+01 2.83E-02 3.29E-05 1.32E-01 1.87E+03 9.88E+03 7.03E-05 Total Curies (Gamma)SUM (Ci/MPCi)(Gamma)SUM (Ci/MPCi)(Non-Gamma)

MPCe (gCi/ml)N/D=Not detected 426 HOPE CREEK ODCM REV 21 APPENDIX B TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS LIQUID RADIOACTIVE EFFLUENTS 427 Hope Creek ODCM Rev 26 APPENDIX B: Technical Basis for Effective Dose Factors -Liquid Effluent The radioactive liquid effluents from Hope Creek from 1997 through 1999 were evaluated to determine the dose contribution of the radionuclide distribution.

This analysis was performed to evaluate the use of a limited dose analysis for determining environmental doses, providing a simplified method of determining compliance with the dose limits of CONTROL 3.11.1.2.

For the expected radionuclide distribution of effluent from Hope Creek during 1997 to 1999, the controlling organ is the GI-LLJ (Bone dose was controlling in 1997 due to relatively high percentage of Fe-55).The calculated GJ-LLJ dose is predominately a function of the Zn-65, Fe-55, and Fe-59 releases.These radionuclides also contribute the large majority of the calculated total body dose. The results of this evaluation are presented in Table B-1.For purposes of simplifying the details of the dose calculation process, it is conservative to identify a controlling, dose significant radionuclide and limit the calculation process to the use of the dose conversion factor for this nuclide. Multiplication of the total release (i.e., cumulative activity for all radionuclides) by this dose conversion factor provides for a dose calculation method that is simplified while also being conservative.

For the evaluation of the maximum organ dose, it is conservative to use the Fe-59 dose conversion factor (6.32E5 mrem/hr per gCi/ml). By this approach, the maximum organ dose will be overestimated since this nuclide has the highest organ dose fraction of all the radionuclides evaluated.

For the total body calculation, the Zn-65 dose factor (2.32E5 mrem/hr per piCi/ml, total body) is the highest among the identified dominant nuclides.For evaluating compliance with the dose limits of CONTROL 3.11.1.2, the following simplified equations may be used: Total Body 8.35E -04

VOL

Ai.

C 1 Dtb =CTBD (B.1)where: Dtb = dose to the total body (mrem)Ai,tb = 2.32E5, total body ingestion dose conversion factor for Zn-65 where A is dose conversion factor, i is isotope which is Zn-65, and TB is the total body (mrem/hr per [tCi/ml)VOL = volume of liquid effluent released (gal)Ci = total concentration of all radionuclides (gCi/ml)CTBD = average cooling tower blowdown discharge rate during release period (gal/min)8.35E-04 = conversion factor (1.67E-2 hr/min) and the near field dilution factor 0.05 Substituting the value for the Zn-65 total body dose conversion factor, the equation simplified to: 428 Hope Creek ODCM Rev 26 1.94E + 02

VOL

Ci CTBD Maximum Organ 8.35E- 4* VOL

Ai, GI -LLI

C, CTBD (B.3)Where:~i Dmax = maximum organ dose (mrem)Ai, GI-LLI = 6.32E5, GI-LLI ingestion dose conversion factor for Fe-59 where A is dose conversion factor, i is isotope which is Fe-59 and o is maximum organ which is the GI-LLI (mrem/hr per jtCi/ml).Substituting the value for Ai, GI-LLI the equation simplifies to: 5.28E +2* VOL* Ci CTBD (B.4)Tritium is not included in the limited analysis dose assessment for liquid releases, because the potential dose resulting from normal reactor releases is relatively negligible.

Near Field Dilution Factor The near field dilution factor stems from NUREG-0133, Section 4.3. For plants with cooling towers, such as Hope Creek, a dilution factor is allowed so that the product of the average blowdown flow (in CFS) and the dilution factor is 1000 cfs or less. UFSAR Section 2.2.12 states that the dilution by river flow ranges from 14- to 40-fold in the mixing zone of effluent 3 discharges and that existing cross currents tend to improve this overall dilution.

The average minimum cooling tower blowdown for Hope Creek is 1.90E4 GPM (from FSAR 11.2). This converts to 42 CFS. Selecting a dilution factor of 20 (between 14 and 40 from the UFSAR)yields a product of 880 CFS, which is less than the 1000 cfs allowed by NUREG-0133.

This near field dilution factor of 20 is inverted to a multiple of 0.05, which is used in the liquid effluent dose calculations.

3 429 Hope Creek ODCM Rev 26 TABLE B-I: Adult Dose Contributions -Fish and Invertebrate Pathways Hope Creek Nuclide Release TB Gl-LLI Bone Liver Year Dose Dose Dose Dose Fraction Fraction Fraction Fraction (Ci)Fe-55 2.28E-01 0.77 0.63 0.96 0.86 1997 Fe-55 6.40E-03 0.12 0.12 0.58 0.22 1998 Fe-55 2.83E-02 0.1 0.04 0.43 0.15 1999 Mn-54 1.74E-02

0.05 0 0.01 1997 Mn-54 7.48E-03 0.02 0.14 0 0.05 1998 Mn-54 6.87E-02 0.04 0.1 0 0.07 1999 Co-58 5.68E-04 *

0

1997 Co-58 7.67E-04 *

0

1998 Co-58 3.30E-03 *

0

1999 Fe-59 2.65E-03 0.08 0.23 0.02 0.05 1997 Fe-59 1.62E-04 0.03 0.09 0.02 0.03 1998 Fe-59 1.72E-02 0.51 0.7 0.4 0.5 1999 Co-60 7.05E-03 0.01 0.03 0

1997 Co-60 6.78E-03 0.06 0.2 0 0.01 1998 Co-60 2.05E-02 0.03 0.04 0

1999 Zn-65 1.29E-03 0.12 0.06 0.02 0.07 1997 Zn-65 1.39E-03 0.75 0.4 0.4 0.68 1998 Zn-65 3.37E-03 0.32 0.07 0.16 0.27 1999* = Less than 0.0 1 430 HOPE CREEK ODCM REV 26 APPENDIX C.TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS GASEOUS RADIOACTIVE EFFLUENTS 431 Hope Creek ODCM Rev 26 APPENDIX C: Technical Basis for Effective Dose Factors -Gaseous Effluents Overview The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific.

These effective factors, which are based on typical radionuclide distributions of releases, can be applied to the total radioactivity releases to approximate the dose in the environment.

Instead of having to perform individual radionuclide dose analysis only a single multiplication (i.e., Keff, Meff, or Neff times the total quantity of radioactive material releases) would be needed. The approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculation technique.

Determination of Effective Dose Factors Effective dose transfer factors are calculated by the following equations:

Kef = Z(Ki* f) (C.1)Where: Keff = the effective total body factor due to gamma emissions from all noble gases released.Ki = the total body dose factor due to gamma emissions from each noble gas radionuclide i released.fi = the fractional abundance of noble gas radionuclide i relative to the total noble gas activity.(L+1.1M'ff)=

Z((Li+1.1M)*f) (C.2)i where: (L + 1.1 Meff) = the effective skin dose factor due to beta and gamma emissions from all noble gases released.(Li + 1.1 Mi) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released.Me f(Mif) (C.3)432 I Hope Creek ODCM Rev 26 where: 3 Meff = the effective air dose factor due to gamma emissions from all noble gases released.Mi = the air dose factor due to gamma emissions from each noble gas radionuclide i released.Neff (gi=* f) (C.A) I where: 3 Neff = the effective air dose factor due to beta emissions from all noble gases released.Ni = the air dose factor due to beta emissions from each noble gas radionuclide i released.Normally, it would be expected that past radioactive effluent data would be used for the determination of the effective dose factors. However, the noble gas releases from Hope Creek have a short history and with continued excellent fuel performance, has hampered efforts in collecting and detecting appreciable noble gas mixes of radionuclides.

So, to provide a reasonable basis for the derivation of the effective noble gas dose factors, the source terms from ANSI N237-1976/ANS-18.1, "Source Term Specifications", Table 5 has been used as representing a typical distribution.

The effective dose factors as derived are presented in Table C-i. I Application To provide an additional degree of conservatism, a factor of 0.50 is introduced into the dose calculation process when the effective dose transfer factor is used. This conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment.

For evaluating compliance with the dose limits of CONTROL 3.11.2.2, the following simplified equations may be used: Dy = 3.1 7 E- 0 8 Q Meff* Qi 0.50 i (C.5)Djl= 3.17E"- 08 **Nef*ZQi (C.6) 3 Where: Dr = air dose due to gamma emissions for the cumulative release of all noble gases (mrad) 4 433 Hope Creek ODCM Rev 26 Dp = air dose due to beta emissions for the cumulative release of all noble gases (mrad)X/Q = atmospheric dispersion to the controlling site boundary (sec/mi 3)Meff = 8.1 E3, effective gamma-air dose factor (mrad/yr per pCi/mi 3)Neff = 8.5E3, effective beta-air dose factor (mrad/yr per ptCi/m 3)Qi = cumulative release for all noble gas radionuclides (jtCi)3.17E-08 = conversion factor (yr/sec)0.50 = conservatism factor to account for the variability in the effluent data Combining the constants, the dose calculation equations simplify to: DY = 5.14E- 4 * (C.7)DO5.39E-4 Q i (C.8)i The effective dose factors are to be used on a limited basis for the purpose of facilitating the timely assessment of radioactive effluent releases, particularly during periods of computer malfunction where a detailed dose assessment may be unavailable.

434 Hope Creek ODCM Rev 26 TABLE C-i: Effective Dose Factors Noble Gases Total Body and Skin Dose Radionuclide Kr83m Kr85m Kr87 Kr88 Kr89 Xe 133 Xe135 Xe135m Xe137 Xe138-If 0.01 0.01 0.04 0.04 0.27 0.02 0.05 0.06 0.31 0.19 Total Body Effective KIff (mrem/yr per RCi/m 3)1.OEl 2.4E2 5.9E2 4.5E3 5.9E0 9.OEl 1.9E2 4.4E2 1.7E3 Skin Effective (L + 1.1 Meff)(mrem/vr per itCi/m 3)2.8E1 6.6E2 7.6E2 7.9E3 1.4El 2.0E2 2.6E2 4.3E3 2.7E3 1.7E4 Total 7.8E3 Noble Gases -Air I I I I I I I I I I I I I I Radionuclide Kr83m Kr85m Kr87 Kr88 Kr89 Xe133 Xe135 Xe135m Xe137 Xe138 0.01 0.01 0.04 0.04 0.27 0.02 0.05 0.06 0.31 0.19 Total Body Effective KIff (mrem/yr per UCi/m 3)1.2El 2.5E2 6.1E2 4.7E3 7.OEO 9.6E1 2.0E2 4.7E2 1.8E3 Skin Effective (L+ 1.1 Meff)(mrem/yr per LiCi/m 3)3.OEO 2.OE1 4.1E2 1.2E2 2.9E3 2.1El 1.2E2 4.4E1 3.9E3 9.0E2 8.4E3 Total 8.1E3* Based on noble gas distribution from ANSI N237-1976/ANS-18.1,"Source Term Specification".

435 Hope Creek ODCM Rev 26 APPENDIX D TECHNICAL BASIS FOR EFFECTIVE DOSE PARAMETERS GASEOUS RADIOACTIVE EFFLUENTS 436 1 Hope Creek ODCM Rev 26 1 APPENDIX D: Technical Basis for Effective Dose Parameters

-Gaseous Effluent The pathway dose factors for the controlling infant age group were evaluated to determine the controlling pathway, organ and radionuclide.

This analysis was performed to provide a simplified method for determining compliance with CONTROL 3.11.2.3.

For the infant age group, the controlling pathway is the grass -cow -milk (g/c/m) pathway. An infant receives a greater radiation dose from the g/c/m pathway than any other pathway. Of this g/c/m pathway, the maximum exposed organ including the total body, is the thyroid, and the highest dose contributor is radionuclide 1- 131. The results of this evaluation are presented in Table D- 1.For purposes of simplifying the details of the dose calculation process, it is conservative to identify a controlling, dose significant organ and radionuclide and limit the calculation process to the use of the dose conversion factor for the organ and radionuclide:

Multiplication of the total release (i.e., cumulative activity for all radionuclides) by this dose conversion factor provides for a dose calculation method that is simplified while also being conservative.

For the evaluation of the dose commitment via a controlling pathway and age group, it is conservative to use the infant, g/c/m, thyroid, 1-131 pathway dose factor (1.67E12 irn 2*mrem/yr per [tCi/sec).

By this approach, the maximum dose commitment will be overestimated since I-131 has the highest pathway dose factor of all radionuclides evaluated.

For evaluating compliance with the dose limits of CONTROL 3.11.2.3, the following simplified equation may be used: Dn= =3.17E-8*W*RI-131*jQi (D.1)Where: i Dmax = maximum organ dose (mrem)W = atmospheric dispersion parameter to the controlling location (s) as identified in Table 2-3.X/Q = Atmospheric dispersion for inhalation pathway (sec/m 3)D/Q = atmospheric disposition for vegetation, milk and ground plane exposure pathways (m-2)Qi = cumulative release over the period of interest for radioiodines and particulates (GCi).3.17E-8 = conversion factor (yr/sec)RI-131 = 1-131 dose parameter for the thyroid for the identified controlling pathway. 3= 1.05E12, infant thyroid dose parameter with the grass -cow -milk pathway controlling (m 2 mrem/yr per ýiCi/sec)The ground plane exposure and inhalation pathways need not be considered when the above simplified calculational method is used because of the overall negligible contribution of these 437 Hope Creek ODCM Rev 26 pathways to the total thyroid dose. It is recognized that for some particulate radionuclides (e.g., Co-60 and Cs-137), the ground exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway. However, use of the 1-131 thyroid dose parameter for all radionuclides will maximize the organ dose calculation, especially considering that no other radionuclides has a higher dose parameter for any organ via any pathway than 1-131 for the thyroid via the milk pathway.The location of exposure pathways and the maximum organ dose calculation may be based on the available pathways in the surrounding environment of Hope Creek as identified by the annual land-use census (CONTROL 3.12.2). Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-3.438 Hope Creek ODCM Rev 26 Target Organs Total Body Bone Liver Thyroid Kidney Lung GI-LLI TABLE D-1: Infant Dose Contributions Fraction of Total Organ and Body Dose PATHWAYS Grass -Cow -Milk Ground Plane 0.02 0.15 0.23 0.14 0.09 0.15 0.59 0.15 0.02 0.15 0.01 0.14 0.02 0.15 TABLE D-2 Fraction of Dose Contribution by Pathway Pathway Grass-Cow-Milk Ground Plane Inhalation Frac 0.92 0.08 N/A 439 Hope Creek ODCM Rev 26 APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -SAMPLE TYPE, LOCATION AND ANALYSIS 440 Hope Creek ODCM Rev 26 APPENDIX E: Radiological Environmental Monitoring Program SAMPLE DESIGNATION Samples are identified by a three part code. The first two letters are the power station identification code, in this case "SA". The next three letters are for the media sampled.AIO = Air Iodine APT = Air Particulates ECH = Hard Shell Blue Crab ESF = Edible Fish ESS = SedimentSWA

= Surface Water WWA = Well Water IDM = Immersion Dose (DLR)MLK = Milk PWR = Potable Water (Raw)PWT = Potable Water (Treated)The last four symbols are a location code based on direction and distance from the site center point. The midpoint of a line between Salem Units 1 & 2 containment domes was used as the site center point. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; i.e., 2=NNE, 3=NE, 4=ENE, 5=E, 6=ESE, 7=SE, 8=SSE, 9=S, 10=SSW, 11=SW, 12=WSW, 13=W, 14=WNW, 15=NW and 16=NNW. The next digit is a letter which represents the radial distance from the plant: I I I I I I I I I I I I.I I I I S = On-site location A = 0-1 miles off-site B = 1-2 miles off-site C = 2-3 miles off-site D = 3-4 miles off-site E = 4-5 miles off-site F = 5-10 miles off-site G = 10-20 miles off-site H = > 20 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3. For example; the designation SA-WWA-5D 1 would indicate a sample in the SGS and HCGS program (SA), consisting of well water (WWA), which had been collected in sector number 5, centered at 90' (due east)with respect to the reactor site at a radial distance of 3 to 4 miles off-site, (therefore, radial distance D).The number 1 indicated that this is sampling station #1 in that particular sector.SAMPLING LOCATIONS All sampling locations and specific information about the individual locations are given in Table E-1.Maps E- 1 and E-2 show the locations of sampling stations with respect to the site.441 I Hope Creek ODCM Rev 26 TABLE E-1: REMP Sample Locations A. Direct Radiation Monitoring Locations STATION CODE 151 2S2 2S4 3S1 4S1 5S1 6S2 7S1 lOSi l151 15SI 15S2 16S1 16S2 (IDM)STATION LOCATION*0.55 mi. N 0.4 mi. NNE 0.60 mi. NNE; in the equipment laydown area 0.58 mi. NE 0.60 mi ENE; site access road near intersection to TB-02 0.86 mi. E; site access road 0.23 mi. ESE; area around helicopter pad 0.12 mi. SE; station personnel gate 0.14 mi. SSW; circ water bldg.0.09 mi. SW; service water bldg.0.57 mi. NW; near river and barge slip 0.59 mi. NW, near river 0.57 mi. NNW; on road near fuel oil storage tank 0.60 mi. NNW; near security firing range 4D2 5D1 10D1 14D 1 15D 1 2E1 3El 11E2 12E1 13E1 16E1 3.7 mi. ENE; Alloway Creek Neck Road 3.5 mi. E; local farm 3.9 mi. SSW; Taylor's Bridge Spur 3.4 mi. WNW; Bay View, DE 3.8 mi. NW; Rt 9, Augustine Beach, DE.4.4 mi. NNE; local farm 4.2 mi. NE; local farm 5.0 mi. SW; Rt. 9 4.4 mi. WSW; Thomas Landing 4.2 mi. W; Diehl House Lab 4.1 mi. NNW; Port Penn IFI 2F2 2F5 2F6 3F2 3F3 4F2 5F1 5.8 mi. N; Fort Elfsborg 8.5 mi. NNE; Salem Substation 7.4 mi. NNE; Salem High School 7.3 mi. NNE; PSE&G Training Center Salem NJ 5.1 mi. NE; Hancocks Bridge, NJ Munc Bldg 8.6 mi. NE; Quinton Township Elem. School NJ 6.0 mi. ENE; Mays Lane, Harmersville, NJ 6.5 mi. E; Canton, NJ 442 Hope Creek ODCM Rev 26 TABLE E-1 (Cont'd) 3 A. Direct Radiation Monitoring Locations (IDM) (Cont'd)STATION CODE STATION LOCATION*6F11 6.4 mi. ESE; Stow Neck Road 7F2 9. 1 mi. SE; Bayside, NJ 9F1 5.3 mi. S;offRt. 9, DE 10F2 5.8 mi. SSW; Rt. 9 1IF1 6.2 mi. SW; Taylors Bridge, DE 12F1 9.4 mi. WSW; Townsend Elementary School, DE 13F2 6.5 mi. W; Odessa, DE l 13F3 9.3 mi. W; Redding Middle School 13F4 9.8 mi. W; Middletown, DE 14F2 6.7 mi. WNW; Rt 13 and Boyds Comer Rd 151F3 5.4 mi. NW 16F2 8.1 mi. NNW; Delaware City Public School 1G3 19 mi. N; N. Church St. Wilmington, DE 3G1 17 mi. NE; local farm 1OG1 12 mi. SSW; Smyrna, DE I 14G1 11.8 mi. WNW; Rte 286, Bethel Church Rd., DE 16G1 15 mi. NNW; Wilmington Airport 3H1I 32 mi. NE; National Park, NJ I B. Air Sampling Locations (AJO,APT)STATION CODE STATION LOCATION*5S1 0.86 mi. E; site access road I 5S2 0.86 mi. E; site access road 5D1 3.5 mi. E; local farm 16E1 4.1 mi. NNW; Port Penn IF1 5.8 mi. N; Fort Elfsborg 2F6 7.3 mi. NNE; PSE&G Training Center Salem, NJ 14G1 11.8 mi. WNW; Rte 286, Bethel Church Rd., DE I 443I Hope Creek ODCM Rev 26 Table E-1 (Cont'd)C. Surface Water Locations (SWA) -Delaware River STATION CODE STATION LOCATION*11Al 0.2 mi. SW; Salem Outfall Area 1lAla Alternate 0.15 SE location in plant barge slip area 12C1 2.5 mi. WSW; West bank of Delaware River 12C1a Alternate 3.7 mi.WSW at the tip of Augustine Beach Boat Ramp 7E1 4.5 mi. SE; 1.0 mi. West of Mad Horse Creek 7E1a Alternate 8.87 mi SE at the end of Bayside Road 1F2 7.1 mi. N; midpoint of Delaware R.16F1 6.9 mi. NNW; C&D Canal 16F1a Alternate 6.84 mi. NNW; Located at the C&D Canal Tip D. Ground Water Locations (WWA)STATION CODE STATION LOCATION*3El 4.2 mi NE of vent, local farm No groundwater samples are required as liquid effluents discharged from Hope Creek and Salem Generating Stations do not directly affect this pathway. However, this location (3E 1) is being monitored as a management audit sample E. Drinking Water Locations (PWR, PWT)STATION CODE STATION LOCATION*2F3 8.0 mi NNE, City of Salem Water and Sewage Department No public drinking water samples or irrigation water samples are required as these pathways are not directly affected by liquid effluents discharged from Hope Creek and Salem Generating Stations.

However, this location (2F3) is being monitored as a management audit sample F. Water Sediment Locations (ESS)STATION CODE STATION LOCATION*HAl 0.2 mi. SW; Salem outfall area 15A1 0.65 mi. NW; Hope Creek outfall area 16A1 0.24 mi. NNW; South Storm Drain outfall 12C1 2.5 mi. WSW; West bank of Delaware river 7E1 4.5 mi. SE; 1 mi West of Mad Horse Creek 16F11 6.9 mi. NNW; C&D Canal 6S2 0.23 mi. ESE; area around helicopter pad 444 Hope Creek ODCM Rev 26 Table E-1 (Cont'd)G. Milk Sampling Locations (MLK)STATION CODE STATION LOCATION*2G3 11.8 mi. NNE, local farm 13E3 5.0 mi W, local farm 14F4 7.6 mi. WNW; local farm 3G1 17 mi. NE; local farm H. Fish and Invertebrate Locations (ESF, ECH)STATION CODE STATION LOCATION*11Al 0.2 mi. SW; Salem outfall area 12C1 2.5 mi. WSW; West bank of Delaware River 7El 4.5 mi. SE; 1 mi West of Mad Horse Creek I. Food Product Locations STATION CODE STATION LOCATION*The Delaware River at the location of Salem and Hope Creek Nuclear Power Plants is a brackish water source. No irrigation of food products is performed using water in the vicinity from which liquid plant wastes have been discharged.

However, 12 management audit food samples are collected from various locations.

All distances and directions for the Station Locations are referenced to the midpoint between the two Salem units' containments.

The WGS 84 coordinates for this site center point location are: Latitude N 390 -27' -46.5" and Longitude W 75' -32' -10.6".I 445I Hope Creek ODCM Rev 26 SAMPLES COLLECTION AND ANALYSIS I Sample Collection Method Analysis Air Particulate Continuous low volume air sampler. Sample collected every week along with the filter change.Gross Beta analysis on each weekly sample. Gamma spectrometry shall be performed if gross beta exceeds 10 times the yearly mean of the control station value. Samples shall be analyzed 24 hrs or more after collection to allow for radon and thorium daughter decay. Gamma isotopic analysis on quarterly composites.

Iodine 131 analysis are performed on each weekly, sample.Gamma isotopic analysis of edible portion on collection.

Air Iodine Crab and Fish A TEDA impregnated charcoal cartridge is connected to air particulate air sampler and is collected weekly at filter change.Two batch samples are sealed in a plastic bag or jar and frozen semi-annually or when in season.A sediment sample is taken semi-annually.

2 DLR's will be collected from each location quarterly.

Sediment Direct Gamma isotopic analysis semi-annually.

Gamma dose quarterly.

446 Hope Creek ODCM Rev 26 SAMPLE COLLECTION AND ANALYSIS (Cont'd)Sample Collection Method Analysis Milk Sample of fresh milk is collected for each farm semi-monthly when cows are in pasture, monthly at other times.Sample to be collected monthly providing winter icing conditions allow.Gamma isotopic analysis and 1-131 analysis on each sample on collection.

Gamma isotopic monthly H-3 on quarterly surface sample, monthly on ground water sample.Water (Potable, Surface)I I I I II I I I I I I I I II I I I I 447 I I I I I I I I I I 17 I Hope Creek ODCM Rev 26 FIGURE E-1: ONSITE SAMPLING LOCATIONS 16 2 1ts 6S2 2S4 2S2 4 4f 11E CREEK .

TATION r MET TOWER.--__k ss1 5 9 448 Hope Creek ODCM Rev 26 FIGURE E-2: OFF-SITE SAMPLING LOCATIONS I I II Hope Creek ODCM Rev 26 APPENDIX F MAXIMUM PERMISSIBLE CONCENTRATIONS LIQUID EFFLUENTS 450 Hope Creek ODCM Rev 26 APPENDIX F: Maximum Permissible Concentration (MPC) Values For Liquid Effluents The following radionuclide concentrations were obtained from 10 CFR 20 Appendix B, Table 1I, Column 2 as revised January 1, 1991.TABLE F-i: Maximum Permissible Concentrations Element Isotope Soluble Conc Insoluble Conc.(ýtCi/ml) (PtCi/ml)Actinium (89) Ac-227 2E-6 3E-4 Ac-228 9E-5 9E-5 Americium (95) Am-241 4E-6 3E-5 Am-242m 4E-6 9E-5 Am-242 1E-4 1E-4 Am-243 4E-6 3E-5 Am-244 5E-3 5E-3 Antimony (51) Sb-122 3E-5 3E-5 Sb-124 2E-5 2E-5 Sb-125 1E-4 1E-4 Sb-126 3E-6 3E-6 Arsenic (33) As-73 5E-4 5E-4 As-74 5E-5 5E-5 As-76 2E-5 2E-5 As-77 8E-5 8E-5 Astatine (85) At-211 2E-6 7E-5 Barium (56) Ba- 131 2E-4 2E-4 Ba-140 3E-5 2E-5 Berkelium (97) Bk-249 6E-4 6E-4 Bk-250 2E-4 2E-4 Beryllium (4) Be-7 2E-3 2E-3 Bismuth (83) Bi-206 4E-5 4E-5 Bi-207 6E-5 6E-5 Bi-210 4E-5 4E-5 Bi-212 4E-4 4E-4 Bromine (35) Br-82 3E-4 4E-5 Cadmium (48) Cd- 109 2E-4 2E-4 Cd- 115m 3E-5 3E-5 Cd- 115 3E-5 4E-5 Calcium (20) Ca-45 9E-6 2E-4 Ca-47 5E-5 3E-5 Californium (98) Cf-249 4E-6 2E-5 Cf-250 1E-5 3E-5 Cf-251 4E-6 3E-5 Cf-252 7E-6 7E-6 Cf-253 1E-4 1E-4 451 I I I I I I I I I I I I I I I I I I I Hope Creek ODCM Rev 26 Cf-254 1E-7 1E-7 452 Hope Creek ODCM Rev 26 Table F-I (Continued)

Element Isotope Soluble Conc. Insoluble Conc.(jiCi/ml)

(ýtCi/ml)Carbon (6) C- 14 8E-4 Cerium (58) Ce- 141 9E-5 9E-5 Ce- 143 4E-5 4E-5 Ce-144 1E-5 lE-5 Cesium (55) Cs-131 2E-3 9E-4 Cs-134m 6E-3 1E-3 Cs-134 9E-6 4E-5 Cs-135 1E-4 2E-4 Cs-136 9E-5 6E-5 Cs-137 2E-5 4E-5 Chlorine (17) CI-36 8E-5 6E-5 CI-38 4E-4 4E-4 Chromium (24) Cr-51 2E-3 2E-3 Cobalt (27) Co-57 5E-4 4E-4 Co-58m 3E-3 2E-3 Co-58 1E-4 9E-5 Co-60 5E-5 3E-5 Copper (29) Cu-64 3E-4 2E-4 Curium (96) Cm-242 2E-5 2E-5 Cm-243 5E-6 2E-5 Cm-244 7E-6 3E-5 Cm-245 4E-6 3E-5 Cm-246 4E-6 3E-5 Cm-247 4E-6 2E-5 Cm-248 4E-7 1E-6 Cm-249 2E-3 2E-3 Dysprosium (66) Dy- 165 4E-4 4E-4 Dy-166 4E-5 4E-5 Einsteinium (99) Es-253 2E-5 2E-5 Es-254m 2E-5 2E-5 Es-254 1E-5 lE-5 Es-255 3E-5 3E-5 Erbium (68) Er- 169 9E-5 9E-5 Er-171 1E-4 lE-4 Europium (63) Eu-152 (9.2 hrs) 6E-5 6E-5 Eu-152 (13 yrs) 8E-5 8E-5 Eu-154 2E-5 2E-5 Eu-155 2E-4 2E-4 Fermium (100) Fm-254 1E-4 1E-4 Fm-255 3E-5 3E-5 Fm-256 9E-7 9E-7 I I I I I I I I I I I I I I I I I I I 453 Hope Creek ODCM Rev 26 Table F-i (Continued)

Element Isotope Soluble Conc. Insoluble Cone.(PtCi/ml) (gtCi/ml)Fluorine (9) F-18 8E-4 5E-4 Gadolinium (64) Gd-153 2E-4 2E-4 Gd-159 8E-5 8E-5 Gallium (31) Ga-72 4E-5 4E-5 Germanium (32) Ge-71 2E-3 2E-3 Gold (79) Au- 196 2E-4 1E-4 Au-198 5E-5 5E-5 Au-199 2E-4 2E-4 Hafnium (72) Hf- 181 7E-5 7E-5 Holmium (67) Ho- 166 3E-5 3E-5 Hydrogen (3) H-3 3E-3 3E-3 Indium (49) In-113m 1E-3 1E-3 In-I 14m 2E-5 2E-5 In- 115m 4E-4 4E-4 In- 115 9E-5 9E-5 Iodine (53) 1-125 2E-7 2E-4 1-126 3E-7 9E-5 1-129 6E-8 2E-4 1-131 3E-7 6E-5 1-132 8E-6 2E-4 1-133 IE-6 4E-5 1-134 2E-5 6E-4 I-135 4E-6 7E-5 Iridium (77) Ir- 190 2E-4 2E-4 Ir-192 4E-5 4E-5 Ir-194 3E-5 3E-5 Iron (26) Fe-55 8E-4 2E-3 Fe-59 6E-5 5E-5 Lanthanum (57) La- 140 2E-5 2E-5 La-141 3E-6 3E-6 Lead (82) Pb-203 4E-4 4E-4 Pb-210 IE-7 2E-4 Pb-212 2E-5 2E-5 Lutetium (71) Lu- 177 1E-4 IE-4 Manganese (25) Mn-52 3E-5 3E-5 Mn-54 IE-4 1E-4 Mn-56 IE-4 1E-4 Mercury (80) Hg- 197m 2E-4 2E-4 Hg-197 3E-4 5E-4 Hg-203 2E-5 iE-4 Molybdenum (42) Mo-99 2E-4 4E-5 454 Hope Creek ODCM Rev 26 Table F-I (Continued)

I Element Isotope Soluble Conc. Insoluble Conc.(ýLCi/mnl) i([LCi/ml)

Neodymium (60) Nd-144 7E-5 8E-5 Nd-147 6E-5 6E-5 Nd-149 3E-4 3E-4 Neptunium (93) Np-237 3E-6 3E-5 Np-239 1E-4 1E-4 Nickel (28) Ni-59 2E-4 2E-3 Ni-63 3E-5 7E-4 Ni-65 1E-4 1E-4 Niobium (41) Nb-93m 4E-4 4E-4 Nb-95 1E-4 1E-4 Nb-97 9E-4 9E-4 Osmium (76) Os-185 7E-5 7E-5 Os-191m 3E-3 2E-3 Os-191 2E-4 2E-4 Os-193 6E-5 5E-5 Palladium (46) Pd-103 3E-4 3E-4 Pd-109 9E-5 7E-5 Phosphorus (15) P-32 2E-5 2E-5 Platinum (78) Pt- 191 1E-4 1E-4 Pt-193m 1E-3 1E-3 Pt- 193 9E-4 2E-3 Pt-197m 1E-3 9E-4 Pt-197 1E-4 lE-4 Plutonium (94) Pu-238 5E-6 3E-5 Pu-239 5E-6 3E-5 Pu-240 5E-6 3E-5 Pu-241 2E-4 1E-3 Pu-242 5E-6 3E-5 Pu-243 3E-4 3E-4 Polonium (84) Po-210 7E-7 3E-5 Potassium (19) K-42 3E-4 2E-5 Praseodymium(59)

Pr- 142 3E-5 3E-5 Pr-143 5E-5 5E-5 Promethium (61) Pm-147 2E-4 2E-4 Pm-149 4E-5 4E-5 Protactinium(91)

Pa-230 2E-4 2E-4 Pa-231 9E-7 2E-5 Pa-233 1E-4 lE-4 I I I I I I I I I I I I I I I I I I I 455 Hope Creek ODCM Rev 26 Table F-I (Continued)

Element Isotope Soluble Conc. Insoluble Conc.(jiCi/ml) (VtCi/ml)Radium (88) Ra-223 7E-7 4E-6 Ra-224 2E-6 5E-6 Ra-226 3E-8 3E-5 Ra-228 3E-8 3E-5 Rhenium (75) Re-183 6E-4 3E-4 Re-186 9E-5 5E-5 Re- 187 3E-3 2E-3 Re- 188 6E-5 3E-5 Rhodium (45) Rh-103m 1E-2 1E-2 Rh-105 1E-4 1E-4 Rubidium (37) Rb-86 7E-5 2E-5 Rb-87 1E-4 2E-4 Ruthenium (44) Ru-97 4E-4 3E-4 Ru-103 8E-5 8E-5 Ru-105 1E-4 1E-4 Ru-106 1E-5 1E-5 Samarium (62) Sm-147 6E-5 7E-5 Sm- 151 4E-4 4E-4 Sm-153 8E-5 8E-5 Scandium (21) Sc-46 4E-5 4E-5 Sc-47 9E-5 9E-5 Sc-48 3E-5 3E-5 Selenium (34) Se-75 3E-4 3E-4 Silicon (14) Si-31 9E-4 2E-4 Silver (47) Ag- 105 1E-4 1E-4 Ag-110m 3E-5 3E-5 Ag-111 4E-5 4E-5 Sodium (11) Na-22 4E-5 3E-5 Na-24 2E-4 3E-5 Strontium (38) Sr-85m 7E-3 7E-3 Sr-85 1E-4 2E-4 Sr-89 3E-6 3E-5 Sr-90 3E-7 4E-5 Sr-91 7E-5 5E-5 Sr-92 7E-5 6E-5 Sulfur (16) S-35 6E-5 3E-4 Tantalum (73) Ta- 182 4E-5 4E-5 456 Hope Creek ODCM Rev 26 Table F-1 (Continued)

Element Isotope Soluble Conc. Insoluble Cone.(jtCi/ml) (itCi/ml)Technetium (43) Tc-96m 1E-2 1E-2 Tc-96 1E-4 5E-5 Tc-97m 4E-4 2E-4 Tc-97 2E-3 8E-4 Tc-99m 6E-3 3E-3 Tc-99 3E-4 2E-4 Tellurium (52) Te-125m 2E-4 1E-4 Tc-127m 6E-5 5E-5 Te-127 3E-4 2E-4 Te-129m 3E-5 2E-5 Te-129 8E-4 8E-4 Te-131m 6E-5 4E-5 Te-132 3E-5 2E-5 Terbium (65) Th-160 4E-5 4E-5 Thallium (81) TI-200 4E-4 2E-4 TI-201 3E-4 2E-4 TI-202 1E-4 7E-5 TI-204 1E-4 6E-5 Thorium (90) Th-227 2E-5 2E-5 Th-228 7E-6 1E-5 Th-230 2E-6 3E-5 Th-231 2E-4 2E-4 Th-232 2E-6 4E-5 Th-natural 2E-6 2E-5 Th-234 2E-5 2E-5 Thulium (69) Tm-170 5E-5 5E-5 Tm-171 5E-4 5E-4 Tin (50) Sn- 113 9E-5 8E-5 Sn-124 2E-5 2E-5 Tungsten (74) W-181 4E-4 3E-4 W-185 1E-4 1E-4 W-187 7E-5 6E-5 Uranium (92) U-230 5E-6 5E-6 U-232 3E-5 3E-5 U-233 3E-5 3E-5 U-234 3E-5 3E-5 U-235 3E-5 3E-5 U-236 3E-5 3E-5 U-238 4E-5 4E-5 U-240 3E-5 3E-5 U-natural 3E-5 3E-5 I I I I I I I I I I I I I I I I I I I 457 Hope Creek ODCM Rev 26 458 Hope Creek ODCM Rev 26 Table F-I (Continued)

Element Isotope Soluble Conc. Insoluble Conc.(ptCi/ml) (gtCi/ml)Vanadium (23) V-48 3E-5 3E-5 Ytterbium (70) Yb- 175 1E-4 1E-4 Yttrium Y-90 2E-5 2E-5 Y-91m 3E-3 3E-3 Y-91 3E-5 3E-5 Y-92 6E-5 6E-5 Y-93 3E-5 3E-5 Zinc (30) Zn-65 1E-4 2E-4 Zn-69m 7E-5 6E-5 Zn-69 2E-3 2E-3 Zirconium (40) Zr-93 8E-4 8E-4 Zr-95 6E-5 6E-5 Zr-97 2E-5 2E-5 Any single radio- 3E-6 3E-6 nuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radio -active half-life greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Any single radio- 3E-8 3E-8 nuclide not listed above, which decays by alpha emission or spontaneous fission.Notes: 1. If the identity of any radionuclide is not known, the limiting values for purposes of this table shall be: 3E-8 p.Ci/ml.2. If the identity and concentration of each radionuclide are known, the limiting values should be derived as follows: Determine, for each radionuclide in the mixture, the ratio between the quantity present in the mixture and the limit otherwise established in Appendix B for the specific radionuclide not in a mixture. The sum of such ratios for all the radionuclides in the mixture may not exceed "1" (i.e. "unity").459 I I I I I I I I I I I I I I I I I

LR-N12-0121, Salem and Hope Creek - 2011 Annual Radioactive Effluent Release Report

Contents

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

mMMMm=MM~M M

Navigation menu

LR-N12-0121, Salem and Hope Creek - 2011 Annual Radioactive Effluent Release Report

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

mMMMm=MM~M M

Navigation menu

Search