Text

Hope Creek, and Salem, Units 1 and 2, 2008 Annual Radioactive Effluent Release Report, Cover Through Page 180
	ML091280378
Person / Time
Site:	Salem, Hope Creek
Issue date:	05/31/2009
From:	; Public Service Enterprise Group
To:	; Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209, LR-N09-0099
	Download: ML091280378 (181)
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PSEG NUCLEAR LLC 2008 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SALEM AND HOPE CREEK GENERATING STATIONS SGS RERR-57 DOCKET NO. 50-272 DOCKET NO. 50-311 OPERATING LICENSE NO. DPR-070 OPERATING LICENSE NO. DPR-075 HCGS RERR-31 DOCKET NO. 50-354 OPERATING LICENSE NO. NPF-057 May 2009 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Table of Contents INTRODUCTION 3 PART A. SUPPLEMENTAL INFORMATION 4 1.0 REGULATORY LIMITS 4 1.1 Fission and Activation Gas Release Limits 4 1.2 Iodines, Particulates, and Tritium 4 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 4.3 Estimated Total Error 7 5.0 BATCH RELEASES 8 6.0 UNPLANNED RELEASES 8 7.0 ELEVATED RADIATION MONITOR RESPONSES 8 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS 8 PART B. GASEOUS EFFLUENTS 8 PART C. LIQUID EFFLUENTS 8 PART D. SOLID WASTE 8 PART E. RADIOLOGICAL IMPACT ON MAN 9 1.0 LIQUID AND GASEOUS EFFLUENT DOSES 9 1 I 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT I 1.1 Total Dose Resulting from Radioactive Effluent Releases and Radiation from Uranium Fuel Cycle Sources 13 1.2 Dose to Members of the Public Due to Activities Inside the Site Boundary 14 1.3 Assessment 15 1.4 Trends 16 PART F. METEOROLOGICAL DATA 18 PART G. OFFSITE DOSE CALCULATION MANUAL CHANGES 18 3 PART H. INOPERABLE MONITORS 19 PART I. PROCESS CONTROL PROGRAM (PCP) CHANGES 19 I PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES 19 3 TABLE 1A GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES 20 TABLE 1B GASEOUS EFFLUENTS

-ELEVATED RELEASES 26 TABLE IC GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES 27 1 TABLE 2A LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES 33 n TABLE 2B LIQUID EFFLUENTS 39 TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 45 1 TABLE 4

SUMMARY

FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE 50 APPENDIX A: METEOROLOGICAL DATA 60 APPENDIX B: MPC DATA 173 APPENDIX C: SALEM OFFSITE DOSE CALCULATION MANUAL, 3 REV. 21 181 2 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT SALEM AND HOPE CREEK GENERATING STATIONS RADIOACTIVE EFFLUENT RELEASE REPORT: JANUARY -DECEMBER 2008 INTRODUCTION This report, SGS-RERR-57/HCGS-RERR-3 1, summarizes information pertaining to the releases 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, 2008 to December 31, 2008.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 1169 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 1155 MWe.Salem Unit 2 achieved initial criticality on August 2, 1980 and went into commercial operation on October 13, 1981.The Hope Creek Generating Station (HCGS) 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 1268 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 2008 was as follows: 9,333,862 megawatt-hours of electrical energy (net) were generated by Salem Unit 1, 8,221,999 megawatt-hours of electrical energy (net) were generated by Salem Unit 2, and 10,006,265 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 approximations of total radioactivity are included in this report.3 I 2008 SGS AND H]CGS RADIOACTIVE EFFLUENT RELEASE REPORT PART A. SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS I 1.1 Fission and Activation Gas Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site (i.e. I 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 I 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 1 radiation and less than or equal to 20 mrad for beta radiation.

1.2 Iodine, Particulates, and Tritium 3 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

For iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mremlyr 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 U the following:

During any calendar quarter: Less than or equal to 7.5 imrem to any organ and, During any calendar year: Less than or equal to 15 mrem to any organ.1.3 Liquid Effluents Release Limits H The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in I0CFR20, 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 41 2008"SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 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.1.4 Total Dose Limit The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 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 1 OCFR20, Appendix B, Table II, Column 2 are to be used for liquid effluents.

Since the MPC values were removed from 1 OCFR20 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:* For Hope Creek, releases from the Equipment Sample Tanks, Floor Drain Sample tanks, Detergent Drain Tanks, and the Condensate Storage Tank.5 I 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 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, Waste Monitor Holdup Tanks and the Chemical Volume Control System (CVCS) Monitor Tanks. During the period of record, all batch liquid wastes from the 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.

3 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 intermittent blow-down of the Steam Generators, and through the Chemical I 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 i ODCM for Hope Creek Generating Station. The total liquid activity discharged is determined by multiplying specific activities from the analyses by the volume of 3 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 l 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: I 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 3 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 i weekly, and analyzed on a multi-channel analyzer..

Sampling is also perfonned on all gas decay tanks and the containment atmosphere prior to release to the enviromnent.

The plant vent is normally sampled weekly for noble 1 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.I 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 3 6 3 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 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 determined by multiplying the specific activities for detected isotopes by the total 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 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 alarn state.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 noble gases. These monitors have moving particulate and fixed 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 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 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 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 reported liquid 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 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 7 I 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 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.5.0 BATCH RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A and 4B.6.0 UNPLANNED RELEASES There were no unplanned releases from Salem Units 1 and 2 or from the Hope Creek Generating Station during this reporting period.7.0 ELEVATED RADIATION MONITOR RESPONSES i During this reporting period, there was no abnormal liquid or gaseous release from the Salem Units 1 and 2 or from the Hope Creek Generating Station. In addition, none of I the effluent radiation monitors elicited an elevated response during the discharge of liquid and gaseous effluent from either of the Salem Units 1 and 2 or from the Hope Creek Generating Station.8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS I No modifications were made to previous Radioactive Effluent Release Reports.PART B. GASEOUS EFFLUENTS I See Summary Tables 1A through IC.PART C. LIQUID EFFLUENTS See Summary Tables 2A through 2B.PART D. SOLID WASTE See Summary in Tables 3A and 3B.I I 2008 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 II 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 2008.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 1Q2008 2Q2008 3Q2008 4Q2008 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 (lnrem) 1.09E-05 7.13E-06 5.84E-06 1.64E-05 4.03E-05% Dose Limit 7.27E-04 4.75E-04 3.89E-04 1.09E-03 1.34E-03 Organ Dose Limit (mrem) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01 Maximum Organ Dose (mrem) 2.02E-05 1.57E-05 1.29E-05 2.88E-05 7.76E-05% Dose Limit 4.04E-04 3.14E-04 2.58E-04 5.76E-04 7.76E-04 Salem Unit 2 Liquid Effluent Parameter 1Q2008 2Q2008 3Q2008 4Q2008 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) 1.99E-06 1.65E-06 2.74E-06 5.1OE-06 1.15E-05% Dose Limit 1.33E-04 1.1OE-04 1.83E-04 3.40E-04 3.83E-04 Organ Dose Limit (mrem) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01 Maximum Organ Dose (mrem) 6.20E-06 4.52E-06 4.57E-06 9.62E-06 2.49E-05% Dose Limit 1.24E-04 9.04E-05 9.14E-05 1.92E-04 2.49E-04 Hope Creek Generating Station Liquid Effluent Parameter 1Q2008 2Q2008 3Q2008 4Q2008 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 (lnrem) 1.16E-06 1.62E-06 1.18E-05 4.73E-07 1.51E-05% Dose Limit 7.73E-05 1.08E-04 7.87E-04 3.15E-05 5.02E-04 Organ Dose Limit (mrem) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01 Maximum Organ Dose (mrem) 5.06E-06 6.02E-06 4.38E-05 8.14E-07 5.57E-05% Dose Limit 1.01E-04 1.20E-04 8.76E-04 1.63E-05 5.57E-04 9 2008 SGS.AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Liqud Eflunt PramterSalem-Hope Creek Site Total Liquid Effluent Parameter 1Q2008 2Q2008 1 3Q2008 4Q2008 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 (torem) 1.41E-05 1.04E-05 2.04E-05 2.20E-05 6.69E-05% Dose Limit 9.37E-04 6.93E-04 1.36E-03 1.46E-03 2.23E-03 Organ Dose Limit (mrem) 5.OOE+00 5.OOE+00 5.OOE+00 5.OOE+00 1.00E+01 Maximum Organ Dose (mrem) 3;15E-05 2.62E-05 6.13E-05 3.92E-05 1.58E-04% Dose Limit 6.29E-04 5.25E-04 1.23E-03 7.85E-04 1.58E-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 was 6.69E-05 mrem, which yields a maximum population dose equal to 3.01E-01 person-rem.

Table 5B: Doses from Gaseous Effluent Salem Unit 1 1 1 1 I I I I I 1 I I 1 1 I I 1 Gaseous Effluent Parameter 1Q2008 2Q2008 3Q2008 4Q2008 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) 1.68E-05 9.72E-06 8.63E-06 8.37E-06 4.35E-05% Dose Limit 3.36E-04 1.94E-04 1.73E-04 1.67E-04 4.35E-04 Beta Air Dose (mrad) for Noble Gases -1.OOE+01 1.00E+01 1.00E+01 1.00E+01 2.OOE+01 Limit Maximum Beta Air Dose (mrad) 6.85E-06 4.05E-06 3.5 1E-06 5.87E-06 2.03E-05% Dose Limit 6.85E-05 4.05E-05 3.51E-05 5.87E-05 1.01E-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, 1.41E-03 2.92E-04 7.23E-04 1.04E-03 3.46E-03 Tritium, and particulate nuclides (>8 days half-life)

-Site Boundary (0.8 mileN)% Dose Limit 1.88E-02 3.89E-03 9.64E-03 1.38E-02 2.31E-02 Organ Dose (mrem) from 1-131, 1-133, 3.18E-05 9.15E-06 4.15E-05 1.07E-05 9.32E-05 Tritium, and particulate nuclides (>8 days half-life)

-Resident/Dairy (4.9 mile W)% Dose Limit 4.24E-04 1.22E-04 5.53E-04 1.43E-04 6.21E-04 10 I 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Salem Unit 2 Gaseous Effluent Parameter 1Q2008 2Q2008 3Q2008 4Q2008 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) 3.12E-05 6.14E-07 5.25E-06 1.02E-05 4.73E-05% Dose Limit 6.24E-04 1.23E-05 1.05E-04 2.04E-04 4.73E-04 Beta Air Dose (mrad) for Noble Gases -1.OOE+01 1.OOE+01 1.OOE+01 1.00E+01 2.OOE+01 Limit Maximum Beta Air Dose (mrad) 2.34E-05 5.24E-07 2.45E-06 3.62E-06 3.OOE-05% Dose Limit 2.34E-04 5.24E-06 2.45E-05 3.62E-05 1.50E-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, 3.95E-04 9.20E-05 2.99E-04 1.08E-04 8.95E-04 Tritium, and particulate nuclides (>8 days half-life)

-Site Boundary (0.8 mile N)% Dose Limit 5.27E-03 1.23E-03 3.99E-03 1.44E-03 5.96E-03 Organ Dose (mrem) from 1-131, 1-133, 8.96E-6 3.06E-06 1.72E-05 1.12E-06 3.03E-05 Tritium, and particulate nuclides (>8 days half-life)

-Resident/Dairy (4.9 mile W)% Dose Limit 1.19E-04 4.08E-05 2.29E-04 1.49E-05 2.02E-04 Hope Creek Generating Station Gaseous Effluent Parameter 1Q2008 2Q2008 3Q2008 4Q2008 Annual Gamma Air Dose (mrad) from Noble 5.OOE+00 5.OOE+O 5.OOE+00 5.OOE+O 1.00E+01 Gases -Limit 0 0 Maximum Gamma Air Dose (mrad) 5.84E-05 4.43E-05 7.57E-06 0.OE+00 1.1OE-04% Dose Limit 1.17E-03 8.86E-04 1.51E-04 O.OE+00 1.1OE-03 Beta Air Dose (mrad) for Noble Gases -1.00E+01 1.OOE+0 1.00E+01 1.00E+0 2.OOE+01 Limit 1 1 Maximum Beta Air Dose (mrad) 7.49E-05 5.67E-05 1.23E-05 0.OE+00 1.44E-04% Dose Limit 7.49E-04 5.67E-04 1.23E-04 O.OE+00 7.19E-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, 2.08E-03 4.20E-03 4.48E-03 5.32E-03 1.61E-02 Tritium, and particulate nuclides (>8 days half-life)

-Site Boundary (0.5 mile N)% Dose Limit 2.77E-02 5.60E-02 5.97E-02 7.09E-02 1.07E-01 Organ Dose (mrem) from 1-13 1, 1-133, 6.86E-05 1.07E-04 1.75E-04 1.52E-04 5.03E-04 Tritium, and particulate nuclides (>8 days half-life)

-Resident/Dairy (4.9 mile W)% Dose Limit 9.15E-04 1.43E-03 2.33E-03 2.03E-03 3.35E-03 11 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Salem-Hope Creek Site Total Gaseous Effluent Parameter 1Q2008 2Q2008 3Q2008 4Q2008 Annual Gamma Air Dose (mrad) from Noble 5.OOE+00 5.00E+00 5.OOE+00 5.OOE+00 1.OOE+01 Gases -Limit Maximum Gamma Air Dose (mrad) 1.06E-04 5.46E-05 2.15E-05 1.86E-05 2.01E-04% Dose Limit 2.13E-03 1.09E-03 4.29E-04 3.72E-04 2.01E-03 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) 1.05E-04 6.13E-05 1.83E-05 9.49E-06 1.94E-04% Dose Limit 1.05E-03 6.13E-04 1.83E-04 9.49E-05 9.72E-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, 3.89E-03 4.58E-03 5.50E-03 6.47E-03 2.04E-02 Tritium, and particulate nuclides (>8 days half-life)

-Site Boundary (N Sector)% Dose Limit 5.18E-02 6.11E-02 7.34E-02 8.62E-02 1.36E-01 Organ Dose (mrem) from 1-131, 1-133, 1.09E-04 1.19E-04 2.34E-04 1.64E-04 6.26E-04 Tritium, and particulate nuclides (>8 days half-life)

-Resident/Dairy (4.9 mile W)% Dose Limit 1.46E-03 1.59E-03 3.12E-03 2.18E-03 4.17E-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 2008. 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.

I I I I I I I I I I I I I I 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 1.89E-04 mrem 3.63E-04 nmrem 3.18E-06 mrem 1.43E-02 person-rem I I I U 12 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 1.1 Total Dose Resulting from Radioactive Effluent Releases and Radiation from 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 1 OCFR72.104.

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 thermoluminescent dosimeter (TLD) measurements.

The ISFSI is a closed system and the only exposure is direct radiation, which would be measured by the site TLDs. 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.Three TLD locations close to unrestricted areas were used to determine the direct radiation dose. Each TLD location represents limited accessibility for a member of the public. However, use of the data collected from these three TLD locations provides a conservative approach for demonstrating compliance with 1 0CFR72.104 requirements for a dose assessment to any "real person." The average annual dose determined from the 2008 TLD measurements was compared with the annual dose based on 1972-1976 pre-operational TLD data (i.e., 55 mrem/year).

TLD data for the 2008 reporting period is given below: Average TLD Reading Annual Dose Location Basis for Selection (mrem/month) (mrem)iS1 Identified as the Site Boundary location in 4.77 57.2 N Sector 5S1 Close to Security Check Point in E Sector 3.56 42.7 11SI 'At Shore Line in SW Sector 3.43 41.2 Average: 47.0 The 2008 TLD data are interpreted as representing a dose from natural background radioactivity because the average annual dose determined from the data is less than the annual dose based on 1972-1976 pre-operational TLD data.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 TLD data indicated that there was no contribution via direct radiation from the site in 2008, compliance with the regulatory requirements for total dose was demonstrated by summing the total body 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, and evaluating those sums against the respective regulatory dose limits. The total body and thyroid doses to members of the public due to radioactivity and radiation from uranium fuel cycle sources are presented in Table 6.13 2008 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 (morem) 7.50E+01 Total Body or Any Organ Dose (mrem) 5.36E-03% Total Body or Any Organ Limit 2.14E-02 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 I OCFR20.1301.

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 umnonitored 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 1,2008 to December 31, 2008 the calculated dose and percent of limit are: I I I I I I I I I I I I I I Parameter Total Body Dose to Member of the Public Inside Site Boundary% Limit 1.01E-02 mrem 1.01E-02 14 I 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 1.3 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: 1.34E-03 % of the Total Body Limit, Salem Unit 2: 3.83E-04 % of the Total Body Limit, and Hope Creek: 5.02E-04 % of the Total Body Limit).When compared to releases in the previous reporting period, the Salem fission &activation product activity in the liquid effluents increased slightly, whereas, the Hope Creek fission & activation products activity decreased slightly.

Nonetheless, liquid effluent releases from the Salem Units 1 and 2 and the Hope Creek Generating Station continue to remain well within Federal limits and compare favorably to other nuclear utilities.

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: 2.31 E-02 % of the annual organ (including total body) dose limit, Salem Unit 2: 5.97E-03 % of the annual organ (including total body) dose limit, and Hope Creek: 1.07E-01 % of the annual organ (including total body) dose limit).When compared to releases in the previous reporting period, the Salem and Hope Creek Generating Stations 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).15 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT 1.4 Trends The following two trend graphs show the total curies of liquid and gaseous effluents released for Salem from 2003 thl-ough 2008. Calculated doses in the graphs are to the hypothetical maximum exposed individual.

Liquid Releases (SGS) Fission & Activation Products Curies Released and Calculated Doses E E 1.OOE+00 .1.OOE-01 1.00E-02 1.OOE-03 1.OOE-04 .1.OOE-05 -2003..1.00E+O00 S-1.OOE-01 1.OOE-02 .1.OOE-03 L)1.00E-04-1.00E-05 2008 -- Organ Total Body A Curies I I I I I I I I I 2004 2005 2006 2007 Year Gaseous Releases (SGS) Curies of Noble Gases Released and Calculated Doses E E 1.OOE+05 -1.OOE+04 1.OOE+03 .1.OOE+02 1.OOE+01 1.OOE+00 1.00E-01 1.OOE-02 1.OOE-03 1.OOE-04 1.OOE-05 2003 1.OOE+05 1.OOE+04 1.OOE+03 1.00E+02 CD 1.OOE+01 1.OOE+00 1.00E-01 2004 2005 2006 2007 Year-.--I 1.OOE-02 20D48 Total Body*USkin* Curies I I I I I I I 16 2008 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 2002 through 2008. Calculated doses in the graphs are to the hypothetical maximum exposed individual.

Liquid Releases (HCGS) Fission & Activation Products Curies Released and Calculated Doses 1.OOE+00 ----------------

1.OOE+00 1OOE-01 1.OOE-01 1.OOE-02 ........ 1.OOE-02 l ooe 04 100E 3 ....................

..... !!; ! !! !! !! !!....1.0E.4...0e....t E 1.OOE-03 1 .OOE-03 1.OOE-04 1.OOE-04 1 .OOE-51 .OOE-05-4--- Total Body 2003 2004 2005 2006 2007 2008- Organ Year -A- Curies Gaseous Releases Curies of Noble Gases Released and Calculated Doses 1.OOE+03 1.OOE+02 1.OOE+02_

1.OOE+01 1 O E 0.. ........ ...............................

1 .0 0 E -0 1 1.OOE-02 1.OOE+03 1.00E-02 1.OOE-01 4 .OOE-03 o E 1.OOE-02 1.OOE-04 1.OOE-05 1.O O E -03 .. .. .. ..... ....... ....... ...... ..... .O O E-06 1 .OOE -04 1.OOE-07 1.OOE-05 1.OOE-08 2003 2004 2005 2006 2007 2008-Total Body Year -- Skin A Curies 17 I 2008 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 The Salem ODCM was revised during the reporting period. A copy of the Salem ODCM revision 21 is provided in Appendix C.Revision 21 of the Salem ODCM became effective September 30, 2008 and accomplished the following:

o Section 1.0, Definitions:

Added "or 10 CFR 72.75" to the definition of Reportable Event." Controls Section 3/4.11.4, Action (a): Added "or 10 CFR 72.104", and subsequently added "and 10 CFR 72.104", in addition to 40 CFR 190 which requires, when estimated dose limits have been exceeded a Special Report to the NRC is required." Bases Section 3/4.11.4, Total Dose: Revised the section to include the 3 dose limitations specific to the ISFSI in accordance with 10 CFR 72.104 which parallel the limits of 40 CFR 90.i o Administrative Controls Section 6.9.1.8, Radioactive Effluent Release Report: Revised the scope of the requirement to generate the RERR annually is to show conformance with 40 CFR 90 and 10 CFR 72.104.o PART II, Section 3.2, Total Dose to Members of the Public: Added 10 CFR 72.104 to be included in the title of the section and added the ISFSI to the HCGS as a source of exposure.o Section 3.2.2, Direct Exposure Dose Determination:

Revised section for non-typical conditions that would require detailed evaluation for demonstrating compliance with 40 CFR 190 to include 10 CFR 72.104.However, should a situation exist whereby the direct exposure contribution is potentially significant, on-site measurements, off-site measurements and/or calculation techniques will be used for determination of dose for assessing 40 CFR 190 or 10 CFR 72.104 compliance.

o Administrative Controls Section 6.1: Revised "Station" to "Plant" and"SORC" to "PORC." o Table 4.3-12, Table Notation:

Revised Item (1)3., (2)3., and added Item (5) to clarify current configuration.

o Table 4.3-13, Table Notation:

Revised Item (1)3. and (2)3. to clarify current configuration.

I 18 2008 SGS AND I-CGS RADIOACTIVE EFFLUENT RELEASE REPORT o Section 1.0, Definitions 1.18 OPERABLE or OPERABILITY and 1.31 SOURCE CHECK were changed to corresponding definitions in the Salem Technical Specifications.

o Table 4.3-12, Table Notation:

foot note number for IRI 8 was changed from "...in-line..." to "...off-line..." based on DCP80019351.

o Revised the 2R1 3 Radiation Monitor configuration in the following:

Table 3.3-12, Item 2a., section 3.3 Instrumentation, Bases, Unit 2, item2a, Part II -Calculational Methodologies, Section 1.0 Liquid Effluents, 1. 1 Radiation Monitoring Instrumentation and Controls, item 2, Figure 1-2: Liquid Release Flowpath Unit 2, Table 1-1.2: Parameters for Liquid Alarm Setpoint Determinations

-Unit 2. This change was based on DCP 80059614.Hope Creek No changes were made to the Hope Creek ODCM during this reporting period.PART H. INOPERABLE MONITORS During this reporting period, the following effluent radiation monitors were inoperable for greater than 30 days: Salem Unit 1: Containment Fan Cooler -Service Water Line Discharge Radiation Monitors (1R 13A-E).Salem Unit 2: Containment Fan Cooler -Service Water Line Discharge Radiation Monitors (2R13A -C).These radiation monitors were inoperable because the Containment Fan Coil Units were removed from service and drained during a maintenance outage at Unit 2. Each radiation monitor was tested and returned to service following completion of required maintenance during the outage. All required compensatory sampling was performed during the period of monitor inoperability.

PART I. PROCESS CONTROL PROGRAM (PCP) CHANGES During the reporting period, there were no changes to either the Salem or Hope Creek PCPs.PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES During the reporting period, there were no changes to environmental monitoring locations as currently described in the Salem and Hope Creek ODCMs.19 2008 SGS AND IHCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A-1 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2008 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Error'Units st Quarter 2 nd Quarter A. Fission and Activation Gases 1. Total Release Ci 1.351 2. Average Release Rate For Period gCi/sec 1.721 3. Percent of Technical Specification Limit % 3.36](ODCM 3.11.2.2(a))

B. Iodine 1. Total Iodine-131 Ci 5.08]2. Average Release Rate For Period [tCi/sec 6.46]3. Percent of Technical Specification Limit2 % 1.88](ODCM 3.11.2.3(a))

C. Particulates

1. Particulates With Half-lives >8 days Ci 0.00t 2. Average Release Rate For Period gCi/sec 0.001 3. Percent of Technical Specification Limit2 % 0.001 (ODCM 3.11.2.3(a))

4. Gross Alpha Ci 0.001 D. Tritium 1. Total Release Ci 6.991 2. Average Release Rate For Period [Ci/sec 8.901 3. Percent of Technical Specification Limit2 % 1.88](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 20 E-0 1 E-02 1.31E-01 1.67E-02 50%I I I I I I I I I I I I I E-04 1.94E-04 E-06 4.59E-08 50%E-07 5.84E-09 E-02 3.89E-03 E+00 1.46E-05 50%E+00 1.86E-06 E+00 3.89E-03 E+00 0.OOE+00 i+01 2.29E+01 50%-+00 2.91E+00 H-02 3.89E-03 I I I I I 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A-2 SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2008 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Units 1" Quarter 2nd Quarter Error'A. Fission and Activation Gases 1. Total Release Ci 7.44E-01 3.OOE-02 50%2. Average Release Rate For Period ýtCi/sec 9.46E-02 3.81E-03 3. Percent of Technical Specification Limit % 6.25E-04 1.23E-05 (ODCM 3.11.2.2(a))

B. Iodine 1. Total Iodine-131 Ci 1.63E-05 2.06E-06 50%2. Average Release Rate For Period tCi/sec 2.07E-06 2.62E-07 3. Percent of Technical Specification Limit 2 % 5.27E-03 1.23E-03 (ODCM 3.11.2.3(a))

C. Particulates 1.. Particulates With Half-Lives >8 days Ci 1.36E-06 1.49E-04 50%2. Average Release Rate For Period tC/sec 1.73E-07 1.89E-05 3. Percent of Technical Specification Limit 2 % 5.27E-03 1.23E-03 (ODCM 3.11.2.3(a))

4. Gross Alpha Ci 0.OOE+00 0.00E+00 D. Tritium 1. Total Release Ci 1.94E+01 7.06E+00 50%2. Average Release Rate For Period gCi/sec 2.47E+00 8.98E-01 3. Percent of Technical Specification Limit. % 5.27E-03 1.23E-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 21 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A-3 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2008 GASEOUS EFFLUENTS

-SUMMATION OF I I I I ALL RELEASES Est.Total ErrorI Units 1 st Quarter 2 d Quarter A. Fission and Activation Gases 1. Total Release Ci 5.86 2. Average Release Rate For Period [tCi/sec 7.46 3. Percent of Technical Specification Limit % 1.17](ODCM 3.11.2.2(a))

B. Iodine 1. Total Iodine-131 Ci 6.47]2. Average Release Rate For Period jtCi/sec 8.23]3. Percent of Technical Specification Limit 2 % 2.77 (ODCM 3.11.2.3(a))

C. Particulates

1. Particulates With Half-Lives >8 days Ci 1.38]2. Average Release Rate For Period jiCi/sec 1.75 3. Percent of Technical Specification Limit2 % 2.77](ODCM 3.11.2.3(a))

4. Gross Alpha Ci 0.001 D. Tritium 1. Total Release Ci 0.001 2. Average Release Rate For Period ptCi/sec 0.001 3. Percent of Technical Specification Limit2 % 0.001 (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 E-01 4.18E-01 25%E-02 5.3 1E-02 E-03 8.85E-04 E-04 1.26E-03 25%E-05 1.61E-04 E-02 5.60E-02 E-04 5.83E-04 25%E-05 7.41E-05 E-02 5.60E-02 E+00 0.OOE+00 E+00 0.OOE+00 25%E+00 0.OOE+00+00 O.OOE+00 I I I I I I I I I I I 22 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A-4 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2008 GASEOUS EFFLUENTS

-SUMMATION OF Units 3rd Quarter ALL RELEASES Est.Total 4th Quarter Error'A. Fission and Activation Gases 1. Total Release Ci 1.331 2. Average Release Rate For Period .tCi/sec 1.671 3. Percent of Technical Specification Limit % 1.731 (ODCM 3.11.2.2(a))

B. Iodine 1. Total Iodine-131 Ci 0.001 2. Average Release Rate For Period jtCi/sec 0.001 3. Percent of Technical Specification Limit2 % 0.001 (ODCM 3.11.2.3(a))

C. Particulates

1. Particulates With Half-Lives >8 days Ci 0.001 2. Average Release Rate For Period [LCi/sec 0.001 3. Percent of Technical Specification Limit 2 % 0.001 (ODCM 3.11.2.3(a))

4. Gross Alpha Ci 0.001 D. Tritium 1. Total Release Ci 6.811 2. Average Release Rate For Period [tCi/sec 8.571 3. Percent of Technical Specification Limit 2 % 9.641 (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 23 E-01 1.90E-01 E-02 2.39E-02 H-04 9.76E-05 ,+00 1.03E-06 E+00 1.30E-07_+00 1.38E-02 ,+00 1.09E-05 3+00 1.38E-06 3+00 1.38E-020.OOE+00>+01 5.74E+01?+00 7.23E+00 E-03 1.38E-02 50%50%50%50%

2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A-5 SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2008 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Error 1 Units 3 rd Quarter 4 th Quarter A.Fission and Activation Gases 1. Total Release Ci 1.03 2. Average Release Rate For Period VCi/sec 1.291 3. Percent of Technical Specification Limit % 1.05 (ODCM 3.11.2.2(a))

B. Iodine 1. Total Iodine-131 Ci 0.001 2. Average Release Rate For Period p, Ci/sec 0.001 3. Percent of Technical Specification Limit 2 % 0.001 (ODCM 3.11.2.3(a))

C. Particulates

1. Particulates With Half-Lives >8 days Ci 0.001 2. Average Release Rate For Period [iCi/sec 0.001 3. Percent of Technical Specification Limit 2 % 0.001 (ODCM 3.11.2.3(a))

4. Gross Alpha Ci 0.001 D. Tritium 1. Total Release Ci 2.811 2. Average Release Rate For Period j, Ci/sec 3.541 3. Percent of Technical Specification Limit 2 % 3.991 (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 E-01 6.10E-02 50%I I I I I I i I I I I E-02 7.68E-03 E-04 1.19E-04 E+00 0.OOE+00 50%g+00 0.OOE+00 i+00 O.OOE+00 i+00 0.OOE+00 50%i+00 O.OOE+00 E+00 O.OOE+00 i+00 0.OOE+00+/-+01 6.01E+00 50%E+00 7.56E-01 H-03 1.44E-03 I I I I I I I 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A-6 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2008 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES Est.Total Error'Units 3'd Quarter 4 th Quarter A. Fission and Activation Gases 1. Total Release Ci 1.711 2. Average Release Rate For Period ýtCi/sec 2.151 3. Percent of Technical Specification Limit % 1.52](ODCM 3.11.2.2(a))

B. Iodine 1. Total Iodine-131 Ci 1.821 2. Average Release Rate For Period XtCi/sec 2.29]3. Percent of Technical Specification Limit' % 5.97](ODCM 3.11.2.3(a))

C. Particulates

1. Particulates With Half-lives > 8 days Ci 1.05]2. Average Release Rate For Period ýtCi/sec 1.32]3. Percent of Technical Specification Limit' % 5.97](ODCM 3.11.2.3(a))

4. Gross Alpha Ci 0.001 D. Tritium 1. Total Release Ci 5.50]2. Average Release Rate For Period ýtCi/sec 6.91 3. Percent of Technical Specification Limit 1 % 5.97](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 E-01 0.OOE+00 25%E-02 0.OOE+00 E-04 0.OOE+00 E-03 3.51E-03 E-04 4.41E-04 25%E-02 7.1OE-02 E-03 9.46E-04 25%E-04 E-02 1.19E-04 7.1OE-02 E+00 0.OOE+00 E-05 3.53E-03 E-06 4.44E-04 25%E-02 7.1OE-02 25 I 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT I TABLE 1B SALEM AND HOPE CREEK GENERATING STATION I EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -DECEMBER 2008 GASEOUS EFFLUENTS

-ELEVATED RELEASES I Salem and Hope Creek Generating Stations have no elevated release points.I I I I I I I I I I I I 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE IC-1 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2008 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES 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 (Half-life

>8 days)Cobalt-58 Total Units Ci Ci Ci Ci Ci Ci 0.OOE+00 3.58E-06 0.OOE+00 3.58E-06 5.08E-06 5.08E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Batch Mode 1 st Quarter 2nd Quarter 8.64E-02 7.93E-02 4.87E-02 5.20E-02 1.54E-04 0.OOE+00 1.35E-01 1.31E-01 4.59E-08 4.59E-08 1.46E-05 1.46E-05 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 1.03E+00 Ci Ci 0.OOE+00 O.OOE+00 4. Tritium Ci 6.89E+01 2.18E+01 I 1.OOE+00 27 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1C-2 SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2008 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released Units 1 st Quarter 2 nd Quarter 1 st Quarter 2 nd Quarter 1. Fission Gases Krypton-85m Ci 0.OOE+00 0.OOE+00 5.85E-04 0.OOE+00 Xenon- 133m Ci 0.00E+00 0.OOE+00 8.19E-03 0.OOE+00 Xenon- 133 Ci O.OOE+00 0.OOE+00 5.59E-01 2.58E-02 Xenon- 135 Ci 0.OOE+00 0.OOE+00 4.18E-02 0.OOE+00 Argon-41 Ci 0.OOE+00 O.OOE+00 1.34E-01 4.15E-03 Total Ci O.OOE+00 O.OOE+00 7.44E-01 3.OOE-02 2. Iodine i Iodine- 131 Ci 1.63E-05 2.06E-06 0.OOE+00 0.OOE+00 Total Ci 1.63E-05 2.06E-06 O.OOE+00 O.OOE+00 3. Particulates (Half-life

>8 3 days)Tellurium-13 1m Ci 1.86E-05 0.OOE+00 0.OOE+00 0.OOE+00 Cobalt-58 Ci 1.36E-06 1.49E-04 0.OOE+00 0.OOE+00 Total Ci 1.99E-05 1.49E-04 O.OOE+00 O.OOE+00 4. Tritium Ci 1.92E+01 7.01E+00 1.81E-01 4.75E-02 3 28 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1C-3 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2008 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES Continuous Mode Units 1 s' Quarter 2"' Quarter Batch Mode I" Quarter 2 d Quarter Nuclides Released 1. Fission Gases Xenon- 135 Total 2. Iodine Iodine- 131 Iodine-133 Total 3. Particulates (Half-life

>8 days)Cobalt-60 Strontium-91 Strontium-92 Lanthanum-140 Barium-140 Barium-139 Cerium-141 Total Ci Ci Ci Ci Ci 5.86E-01 5.86E-01 6.47E-04 8.73E-03 9.38E-03 4.18E-01 4.18E-01 1.26E-03 1.65E-02 1.78E-02 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Ci Ci Ci Ci Ci Ci Ci 2.3 7E-05 1.72E-02 4.1OE-02 4.57E-05 1.14E-04 1.20E-03 0.OOE+00 5.96E-02 2.48E-05 0.00E+00 0.OOE+00 2.79E-04 5.50E-04 7.49E-02 8.19E-06 7.57E-02 4. Tritium Ci O.OOE+00 O.OOE+00 I 29 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1C-4 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2008 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES Nuclides Released Fission Gases Krypton-85m Xenon-133m Xenon- 133 Xenon- 135 Argon-41 Total 2. Iodine Iodine-131 Total 3. Particulates (Half-life

>8 days)Bromide-82 Cobalt-58 Total Continuous Mode Units 3 rd Quarter* 4 th Quarter Batch Mode 3rd Quarter 4th Quarter Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+O0 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 0.OOE+00 O.OOE+O0 1.03E-06 1.03E-06 5.27E-06 1.09E-05 1.62E-05 0.00E+00 0.OOE+00 4.7 1E-02 0.OOE+00 8.54E-02 1.33E-01 0.OOE+00 O.OOE+00 4.15E-04 2.57E-03 1.23E-01 2.37E-02 3.96E-02 1.90E-01 0.OOE+00 O.OOE+00 I I I I I I I I I I I 0.OOE+00 0.OOE+00 O.OOE+00 1.49E+00 0.OOE+00 0.OOE+00 O.OOE+00 3.91E-01 4. Tritium Ci 6.66E+01 5.70E+01 I 30 I 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1C-5 SALEM GENERATING STATION -UNIT 2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2008 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES Continuous Mode 3rd Quarter 4th Quarter Batch Mode 3rd Quarter 4th Quarter Nuclides Released 1. Fission Gases Krypton-85m Xenon-133m Xenon- 133 Xenon-135 Argon-41 Total 2. Iodine-3. Particulates (Half-life

>8 days)4. Tritium Units Ci Ci Ci Ci Ci Ci 0.00E+00 0.OOE+00 O.00E+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 O.OOE+00 1.38E-04 1.13E-03 4.36E-02 8.01E-03 4.97E-02 1.03E-01 Ci O.OOE+00 Ci O.OOE+00 Ci 2.80E+01 O.OOE+00 I O.OOE+00 0.OOE+00 0.OOE+00 8.1OE-04 0.OOE+00 6.02E-02 6.10E-02 O.OOE+00 O.OOE+00 1.76E-01 O.OOE+00 O.OOE+00 5.83E+00 1.55E-01 31 I 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1C-6 HOPE CREEK GENERATING STATION EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JULY -DECEMBER 2008 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released Units 3 rd Quarter 4 th Quarter 3 rd Quarter 4 th Quarter 1. Fission Gases Xenon-13 1m Ci 2.68E-04 0.OOE+00 0.OOE+00 0.OOE+00 Xenon-133 Ci 9.91E-02 0.OOE+00 0.OOE+00 0.OOE+00 Xenon- 135 Ci 7.18E-02 O.OOE+00 0.OOE+00 O.OOE+00 Total Ci 1.71E-01 O.OOE+00 O.OOE+00 O.OOE+00 3 2. Iodine Iodine- 131 Ci 1.82E-03 3.5 1E-03 0.OOE+00 0.OOE+00 3 Iodine- 133 Ci 2.16E-02 2.85E-02 0.OOE+00 0.OOE+00 Total Ci 2.34E-02 3.20E-02 O.OOE+00 O.OOE+00 3. Particulates (Half-life

>8 days) I Cobalt-60 Ci 1.85E-05 1.60E-05 0.OOE+00 0.OOE+00 Yttrium-91lm Ci 2.40E+00 0.OOE+00 0.OOE+00 0.OOE+00 Molybdenum-99 Ci 0.OOE+00 1.08E-05 0.OOE+00 0.OOE+00 Technicium-99m Ci 0.OOE+00 1.09E-05 0.OOE+00 0.OOE+00 Barium-139 Ci 3.36E+00 0.OOE+00 0.OOE+00 0.OOE+00 Barium-140 Ci 9.78E-04 9.17E-04 O.OOE+00 0.OOE+00 U Lanthanum-140 Ci 4.78E-04 2.11E-04 O.OOE+00 0.OOE+00 Cerium- 141 Ci 4.97E-05 1.32E-05 0.OOE+00 0.OOE+00 Total Ci 5.76E+00 1.18E-03 0.00E+00 O.OOE+00 4. Tritium Ci 5.50E-05 3.53E-03 O.OOE+00 O.OOE+00 3 32 2008 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 2A-1 SALEM GENERATING STATION -UNIT 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 2008 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))