Text

Salem - Attachment 1, Offsite Dose Calculation Manual Revision, 24
	ML101300373
Person / Time
Site:	Salem
Issue date:	10/27/2009
From:	Shelton J; Public Service Enterprise Group
To:	; Office of Nuclear Reactor Regulation
References
	LR-N10-0140
	Download: ML101300373 (156)
	v • d • e

{{#Wiki_filter:Attachment 1 ODCM Revisions Salem ODCM Rev 24 I.OFFSITE DOSE CALCULATION MANUAL FOR PSEG NUCLEAR LLC SALEM GENERATING STATION Revision 24 Prepared By: Reviewed by: SQR Accepted by: 'DatýIo-AT701 Date I9 V)Z:I='p I.Revi Wed by " .pURC-Ch~ii~an'f Michael Gwirtz Meeting #: 3240 -01Ia Approved by: Plan I er Edwin Eilola, Jr.Date Page 1 of 155 Salem ODCM Rev. 24* *Revision Summary 1. Table E-1 section A. Direct Radiation Monitoring Locations was revised& due to the relocation of a TLD station. TLD station code 2S4 was changed from 0.60 mi. NNE; N of equipment.laydown area to 0.42mi. NNE; in the equipment laydown area.Justification: TLD station 2S4 was moved because the direct radiation emitted from the Hope Creek Turbine Building was being shielded by the Cooling Tower. It was moved about 1,232 feet south to be in direct line of sight with the Hope Creek Turbine Building. This will provide a more representative measurement of the direct radiation dose to-a member of the public at this location. 2009 REMP FASA Order 70100559.2. Table E-1 section A. Direct Radiation Monitoring Locations was revised- due to the relocation of a TLD station. TLD station code 14F2 was changed from 6.6 mi. WNW; Boyds Comer to 6.7 mi. WNW;Rt 13 and Boyds Comer Rd.Justification: TLD.station 14F2 was moved 2,041 feet WSW because a Town road widening project resulted in the telephone pole that the TLD was posted on being removed. Salem Order 70103092.3. Updated Figures E-1 On-site Sampling Locations and E-2 Off-site Sampling Locations to update the new sampling locations. Justification: The maps were updated to be consistent with the REMP statiohlocations listed in Table E-1.I.d z 4. Verified that the formulas for the dose calculations and radioactive: effluent monitor alarm set points listed in this revision are correct. Notification 20427924 reported that some of the dose calculation formulas printed from the copy in DCRMS were illegible. The Microsoft Word< version of the Salem ODCM Rev 24 was used to print the pages for all equations. These Dequations were compared to those in Revision 21. All equationsmwere found to be exactly the< same.Justification: The equations in this revision of the Salem ODCM were verified to be accurate. Salem Order o 70101376.ILI 0 z I w-,I o,- Page 2 of 155 '" w-J Salem ODCM Rev. 24 TABLE OF CONTENTS INTR O DU CTIO N .................................................................................................................................. 7 PART I -RADIOLOGICAL EFFLUENT CONTROLS ......... ........................ 8 1.0DEFNITONS......................................... .......1 1.0 D EFIN ITIO N S ................................. ....... ...... ......... [............ .... ........... ................................. ... ..... 10 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS ............... I .................................... 16 3/4.0 APPLICABILITY ................................................. 16 3/4.3 INSTR UMENTA TION ........................ .................................. 18 3/ 4.3.3.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ... 18 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 24 3/4.11 RADIOACTIVE EFFLUENTS ........................................ 29 3/4.11.1 LIQ UID EFFLUEN TS ..................................................................................................... 29 3/4.11.1.1 CONCENTRATION ........................................ 29.3/4.11.1.2 DOSE .............................................. .. .................. ......... 33 3/4.11.1.3 LIQUID RADWASTE TREATMENT ........................... ................................ 34 3/4.11.2 GASEO US EFFLUEN TS 5...................................................... ......................................... 35 3/4.11.2.1 DOSE RATE .............................................. 35 3/4.11.2.2 DOSE -NOBLE GASES .......................... ,......................

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38 3/4.11.2.3 DOSE -IODINE- 131, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM ....... ............................................................... 39 3/4.11.2.4 GASEOUS RADWASTE TREATMENT ............ ................................. 40 3/4.11.4 TOTAL D OSE ....... ................................................. ............... ........................... 41" 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING .............................................. 42 i < 3/4.12.1 M ONITORING PROGRAM ................................................... .......... I .............................. 42 3/4.12.2 LAND USE CENSUS .............................................................. ........................................ 55 3/4.12.3 INTERLABORATOR Y COMPARISON PROGRAM ......................................... 5.7 B A S E S ........................................................................................................ ......................................... 58 V) 3/4.3 INSTRUM ENTATION ........................................................ ............................................. 59 S3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION .... 59 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 60 3/4.11 RADIOACTIVE EFFL UENTS ....................................... 62 3/4.11.1 LIQUID EFFLUENTS .. ... ........................................ 62 3/4.11.2 GASEOUS EFFLUENTS ............................................................................................. 63 S3/4.11.4 TOTAL D OSE ............. .... .................. ........................................ 65 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING ......... ......................................... 66 3/4.12.1 M ONITORING PROGRAM ............................................................................ ...66 3/4.12.2 LANDUSECENSUSGAM6 ,.3/4.12.2 LA N D U SE CEN SU S ........... ................ a .......................... i.......................................... 66 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM..... ................................... 66 t 5.0 DESIGN FEATURES ................................................ 68 5.1 SITE .................................................................................... -...... ............................................. 68 5.1.3 UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID Lt6. AD M NIS RATEEFFLU ENTS ............................................................................................... 68 6.0C O N T R O L S ...................................................... .......................................... 70 6.9.1.7 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ..... 70 6.9.1.8 RADIOACTIVE EFFLUENT RELEASE REPORT ............................................... 70 Ix Page 3 of 155"a Salem ODCM Rev. 24 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATM EN T SY STEM S ................................................................................................ 72 PART II -CALCULATIONAL METHODOLOGIES ............... ............... 73 I 1..0 LIQUID EFFLUENTS............................. .................. 74 1.1 Radiation Monitoring Instrumentation and Controls.............................. ............ 74 1.2 Liquid Effluent Monitor Setpoint Deternfination................................ 74 1.2.1 Liquid Effluent Monitors (Radwaste, Steam Generator Blowdown, Chemical Waste Basin and Service W ater 7 ................................................................................................ ......... 75 1.2.2 Conservative Default Values ............. ........... ........ ... .76 1.3 Liquid Effluent Concentration Limits -10CFR 20 ......................... i ................................... 77 1.4 Liquid Effluent Dose Calculation -10 CFR 50 ............ .................. 77 1.4.1 MEMBER OF THE PUBLIC Dose'- Liquid Effluents ............. ........................... 77 1.4.2 Simplified Liquid Effluent Dose Calculation ............................ 79 1. 5 Secondary Side Radioactive Liquid Effluents and Dose Calculatiohls During Primary to Secondary Leakage .............. , ........................................................ 79 1.6 Liquid*Effluent Dose Projections ....................................... 80 I1/42.0 GASEOUS EFFLUENTS ............................... .. ........... 81 2.1 Radiation Monitoring Instrumentation and Controls ................................... .* ..... 81 2.2 Gaseous Effluent Monitor Setpoint Determination ............................................................... 82 2.2.1 Containm ent and Plant Vent M onitor ................. 82........................................................... 82 2.2.2 Conservative D efault V alues .......3.......................................................... ............. ....... 83 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations -10 CFR 20 ............................... 83 2.3.1 Site Boundary Dose Rate -Noble Gases......... .................. 83 co 2.3.2 Site Boundary Dose Rate -Radioiodine and Particulates ..... .. ................ 85..2.4 Noble Gas Effluent Dose Calculations -10 CFR 50 ..................... ..................................... 85< 2.4.1 UNRESTRICTED AREA Dose -Noble Gases ........ ..................................................... CU 2.4.2 Simplified Dose Calculation for Noble Gases ................................................................... 86 2.5 Radioiodine and Particulate Dose Calculations -10 CFR 50 ....... w .................... 87< 2.5.1 UNRESTRICTED AREA Dose -Radioiodifie and Particulates .................................. 87 V 2.5.2 Simplified Dose Calculation for Radioiodines and Particulates ...................................... 87-2.6 Secondary Side Radioactive Gaseous Effluents and Dose Calculdtions ............................ 88 2.7 Gaseous Effluent Dose Projection ......... ............................. 90 (/o 3.0 SPECIAL DOSE ANALYSES .......................................... 91 o 3.1 Doses Due To Activities Inside the SITE BOUNDARY .............................. 91 Cn 3.2 Total dose to MEMBERS OF THE PUBLIC -40 CFR 190 ...... ........................................ 91 3.2.1 Effluent D ose C alculations ........................................................ ............ ............................... 91 0 3.2.2 Direct Exposure Dose Determination ........................................... ......9........ ...................... 92 z 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM............................... 92 ,4.1 Samp ling P rogram .... 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4......m................... ............... 92 0rv",,4.2 Interlaboratory Comparison Program..:........ .... ........... ............................... 92 00 (/3 Page 4 of 155.DI Salem ODCM Rev. 24 TABLES I TABLE 1.1: OPERATIONAL M ODES ........................................ .......................................... 13 TABLE 1.2: FREQUENCY NOTATION .......................................... 14 TABLE 3.3-12: RADIOACTIVE LIQUID EFFLUENT MONITOt.ING INSTRUMENTATION .................................... .. ............................................................................................................. 19 TABLE 4.3-12: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ...... i ........ ....................... I ............... 22 TABLE 3.3-13: RADIOACTIVE GASEOUS EFFLUENT MONITORING IN STRU M EN TA TION ............................................................................................................ 25 TABLE 4.3-13: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...... ....... ....... 27 TABLE 4.1-1-1: RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM.. .......... .... .... ... ....................................................................... TABLE 4.11-2: RADIOACTIVE GASEOUS WASTE SAMPLING ANDT ANALYSIS PR O G R A M ......................................................................................... ........................................... 36 TABLE 3.12.1-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *... 44 TABLE 3. 12-2: REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES ............................................................ 51 TABLE 4.12-1: DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE A N A LY SIS("' (') ........................ ...... .................................... I .......... ........................................... 52 Table 14. 1: Parameters for Liquid Alarm Setpoint Determinations Unit 1 .............. 96 Table 1-1.2: Parameters for Liquid Alarm Setpoint Determinations -Unit 2 .......................... 97 TABLE 1-2: Site Related Ingestion Dose Commitment Factor, Ai. .................... ................. 9 8 Table 1-3: Bioaccumulation Factors ...................................... 100 t0d Table 2-i: Dose Factors For Noble Gases ......................................... ......................................... 103-Table 2-2.1: Parameters for Gaseous Alarm Setpoint Determinations -Unit 1. ........... 104 Table 2-2.2: Parameters for Gaseous Alarm Setpoint Determinations -Unit 2 .................... 105 Table 2-3: Controlling Locations, Pathways ...................................... 106 F Table 2-4: Pathway Dose Factors -Atmospheric Releases ........................................................ 107 V) Table A-1: Calculation of Effective M PC -Unit 1 ..................................................................... 122Table A-2: Calculation of Effective M PC -Unit 2 ..................................................................... 123 Table B-i: Adult Dose Contributions -Fish and Invertebrate Pathways -Unit I ...................... 127-2 Table B-2: Adult Dose Contributions -Fish and Invertebrate Pathvcays -Unit 2 ....................... 128 0 Table C- 1: Effective D ose Factors ............................................................................................. 133 V) _m>Table D-1: Infant Dose Contributions ............................................................. 137'"y: TABLE E-1: REM P Sample Locations ...................................................................................... 140 10 Table F-1: M aximum Permissible Concentrations .................................................................... 149 U->U-Page 5 of 155 0 Salem ODCM Rev. 24 FIGURES FIGURE 5.1-3: AREA PLOT PLAN OF SITE ...................................... ................................ 69 Figure 1-1: Liquid Release Flowpath Unit 1 ................................. .................................... 93 Figure 1-2: Liquid Release Flowpath Unit 2 ............................. .......94 Figure 1-3: Liquid Radioactive W aste System ........ ................. ............................ ....... 95 Figure 2-1: Salem Ventilation Exhaust Systems and Effluent Monitor Interfaces ........ 101 Figure 2-2: Gaseous Radioactive W aste Disposal System ............ ....... ............................. 101 Figure 2-2: Gaseous: Radioactive W aste Disposal System .............. ........... , ........................ 102 Figure E-1: ONSITE SAMPLING LOCATIONS.........................146 Figure E-2: OFFSITE SAMPLING LOCATIONS ............................. ......... 147 APPENDICES. APPENDIX A: EVALUATION OF'DEFAUL-T PARAMETERS FOR LIQUID EFFLUENTS ............ .... 120 APPENDIX B: TECHNICAL BASIS FOR SIMPLIFIED DOSE CALCULATIONS LIQUID EFFLUENTS ......... 125 APPENDIX C: TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS -GASEOUS EFFLUENTS................ 130 APPENDIX D: TECHNICAL BASIS FOR SIMPLIFIED DOSE CALCULATION -GASEOUS EFFLUENTS .135 APPENDIX E: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.... ........... ................... 139 APPENDIX F: MAXIMUM PERMISSIBLE CONCENTRATION (MPC)ý VALUES -LIQUID EFFLUENTS ........ 149 I I I I I I I I) 'I I)0 LJ z 0 0 z U)D z" 0 UL w z V-D 0,.-J m 03U)i wY Lwc j I I I I I I I I I Page 6 of 155 Salem ODCM Rev. 24 SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL I.S INTRODUCTION The Salem Offsite Dose Calculation Manual (ODCM) is a supporting docu'ment 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: Pai't I -Radiological Effluent Controls, and Part II -Calculational Methodologies. Part I includes the following: I The Radiological Effluent Controls and the Radiological Environm'ental Monitoring Programs required by Technical Specifications 6.8.4 0 Descriptions of the information that should be included in the Annidal 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: I the calculation of radioactive liquid and gaseous effluent monitorinlg instrumentation alarm/trip setpoints; and 0.

the calculation of radioactive liquid and gaseous concentrations, dose rates, cumulative quarterly z and yearly doses, and projected doses.Part II also contains a list and graphical description of the specific sample locations for the radiological Iz 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.Cn The current licensing basis' applies Maximum Permissible Concentrations (MPCs) for radioactive liquid 2z effluent concentration limits. Since the MPC values were removed from 1'OCFR20 effective 1/1194, the_ MPC values are provided as Appendix F to the ODCM. As discussed in tle -Safety Evaluation by the> Office of Nuclear Reactor Regulation related to Amendment Nos. 234 and 215, letters between the W ac Nuclear Management and Resources Council (NUMARC) concerning the'differences between the "old" I0 10CFR20 and the "new" 1OCFR20 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 ry implements the "new" Part 20. The letter stated that the existing RETS which reference the "old" Part 0 20 would maintain the level of required protection of public health and safety, and would be consistent Eus with the requirements of the "new" Part 20.a: Page 7 of 155 Salem ODCM Rev. 24 S PARTI -RADIOLOGICAL EFFLUENT CONTROLS S w-7 V)0 0 L5 0 0 cnp w<D z'U-U-y 0 U---I2 m 0 0O 0 o.-w-I I:, I I I I I I I I I I I I I I I I I Page 8 of.155 I Ie Salem ODCM Rev. 24 SECTION 1.0 DEFINITIONS no I.a.(.9 U')uaJ i, U-0 Rio Page 9 of 155 i"1 Salem ODCM Rev. 24 p 1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these CONTROLS.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 outpu( 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 chlannel, 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 ndrmal calibration of the .remaining adjustable devices in the channel. Whenever an.RTD or therm~couple sensing element is replaced, the next required CHANNEL CALIBRATION shall include an i1nplace 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. I CHANNEL CHECK Vn 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 ZI< and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. 0 CHANNEL FUNCTIONAL TEST I in 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 in functions. o CONTROL> 1.10 The Limiting Conditions for Operation (LCOs) that were contained in the Radiological Effluent"'a Technical Specifications were transferred to the OFFSITE DOSE CALCULATION MANUAL 0 (ODCM) and were renamed CONTROLS. This is to distinguish between those LCOs that were retained Z in the Technical Specifications and those LCOs or CONTROLS that were-transferred to the ODCM.U- ." DOSE EQUIVALENT 1- 131 at> 1.11 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram), which I 0 alone would produce the same thyroid dose as the quantity, and isotopic nrrixture of 1-131, 1-132, I-1333, 1-134, and 1-135 actually present. The thyroid dose conversion factor5 used for this calculation _ shall be those listed in Federal Guidance Report No. I I (FGR 11), "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and n Ingestion". P 0" in a: Page 10 of 155 r,, Salem ODCM Rev. 24* 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 radiatilon 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 alarn t i.trip setpoints, and in the conduct of the environmental radiological monitoring program. The ODCM shall also contain (1)V) the Radioactive Effluent Controls and Radiological Environmental Monito'ring Programs required by* D 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, Z" component or device to perform its specified safety function(s) are also capable of performing their>o related support function(s). OPERATIONAL MODE -MODE, I 1. 19 An OPERATIONAL MODE (i.e., MODE) shall correspond to anyone inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table I1.1 o 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. 0~0 RATED THERMAL POWER Page II of 155 V) Salem ODCM Rev. 24 P 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3459 MWt.REPORTABLE EVENT 1.37 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to IlOCFR Part 5O0or I OCFR 72.75.I SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land or pr'operty 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 rateto 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 quarters or industrial, commercial, institutional, and/or recreational purposes.L".d VENTILATION EXHAUST TREATMENT SYSTEM 1.36 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine and radioactive rmaterial 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 0 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 com'ponents. I o VENTING>-m 1.37 VENTING shall be the controlled process of discharging air or gas frbm a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a o manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.LW WASTE GAS HOLDUP SYSTEM> 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 L-. Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity _ I prior to release to the environment. 0 bi 0 ry Page 12 of 155 V)0"'LU I Ij Salem ODCM Rev. 24 TABLE 1.1 : OPERATIONAL MODES MODE 1. POWER OPERATION 2. STARTUP 3. HOT STANDBY 4. HOT SHUTDOWN 5. COLD SHUTDOWN 6. REFUELING** REACTIVITY CONDITION, Ken" THERMAL POWER*> 0.99 > 5%> 0.99 < 5%< 0.99 0 AVERAGE COOLANT TEMPERATURE > 350°F> 350°F> 350OF 350°F > Tavg> 200OF< 200°F< 140OF< 0.99< 0.99< 0.95 0 0 0 (I )0 1+/-Hd* Excluding decay heat.** Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.Page 13 of 155 Salem ODCM Rev. 24 p TABLE 1.2: FREQUENCY NOTATION NOTATION S D w M Q SA R S/U P N.A.FREQUENCY At least once per 12 hours.At least once per 24 hours.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. p 03 0 0 LL1 0 H--0 Lý0 03 z 0 n LIl CV":-w.t 0', t0d 0 w'v w 0, Page 14 of 155 I VI I I I I Il-)I-3z 0 LII>-C1 M U"-)17-1CL V°tLd V,-Salem ODCM Rev. 24 I SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS Page 15 of 155 Salem ODCM Rev. 24 O 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 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 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: 1. At least HOT STANDBY within the next 6 hours,* 2. At least HOT SHUTDOWN within the following 6 hours, and W" 3. At least COLD SHUTDOWN within the subsequent 24 hours.z C-)- 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.DI This CONTROL is not applicable in MODE 5 or 6.0-I-- 3.0.4 Entry into an OPERATIONAL MODE or other specified condition: z"_0 (a) shall not be made when the conditions of the CONTROL are not met and the associated W ACTION requires a shutdown if they are not met within a specified time interval._z (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 complywith ACTION requirements. Exceptions to these requirements are stated in the individual CONTROLS.i-0 ry Page 16 of 155 DI Salem ODCM Rev. 24 I p 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 hours to permit the completion of the surveillance when the allowed outage time limits of the ACTION-requirements are less than 24 hours. Surveillance Requirements'do not have to be performed on inoperable equipment. co w 7--0 ICn z I-Uj>laJ_1_U-10 OL i, (A 17-4.0.4 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. Page 17 of 155 I Salem ODCM Rev. 24 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 alarrn/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 alarmý/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.Page 18 of 155 I I I I I I I I I I I I I I I I I I U)w C-7--0 C/)z 0 UO n F--0 U-(-J Z ry-0 Cy U, LI..D I USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES Salem ODCM Rev. 24 TABLE 3.3-12: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE INSTRUMENT ACTION 1. GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE a. Liquid Radwaste Effluent Line b. Steam Generator Blowdown Line 2. GROSS RADIOACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE I (1R18, 2R18)4 (1R19A-D, 2R19A-D)26 27 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) (2RI 3A, B)I (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 Page 19 of 155 Salem ODCM Rev. 24 TABLE 3.3-12 (Continued) TABLE NOTATION ACTION 26 -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 I 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.ACTION 27 -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 fo'r principal gamma emitters, 1-131, and dissolved and entrained gases at the lower limits of detection required in ODCM CONTROL Table 4.11-L .B, and the ODCM Surveillance Requirement 4.11.1.1.2 is performed:

a. At least once per 8 hours when the specific activity of the secondary coolant is b. greater than 0.01 microcuries/gram DOSE EQUIVALENT 1-131, or le b. At least once per 24 hours when the specific activity of the secondary coolant is co less than or equal to 0.01 microcuries/gram DOSE EQUIVALENT 1-13 1.Lii< ACTION 28 -With the number of channels OPERABLE less than required by the Minimum Channels U OPERABLE requirement, effluent releases via this pathway may continue provided that:< a. At least once per 8 hours, local monitor readouts for the affected channels are DV verified to be below their alarm setpoints, or< b. With a Service Water System leak (inside containment) on the Containment Fan V) Coil Unit associated with the inoperable monitor either: z" 0 1. At least once per 8 hours, grab samples are to be collected and analyzed for--> principal gamma emitters, 1-13 1, and dissolved and entrained gases at the Ira lower limits of detection specified in ODCM CONTROL Table 4.11 -1 .B, and 0the ODCM Surveillance Requirement 4.11.1.1.2 is performed, or 2. Isolate the release pathway.i,> c. With no identified service water leakage (inside containment) on the Containment 0: Fan Coil Unit associated with the inoperable monitor, at least once per 24 hours, 0,- 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 SM is performed.

0 V)f-Y' Page 20 of 155 VI Salem ODCM Rev. 24 1 I 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 hours 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 I per week Condition During normal operation (all MODES)IO LU 0 r-<Ig: 0L 03 d-Y rv-D I per day 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. Page 21 of 155 USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES w of fe Salem ODCM Rev. 24 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 2. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE D D R(3)R(3)Q(1)Q(1)M a. Containment Fan Coolers -Service Water Line Discharge D D M M R(3)R(3)Q(2)Q(5)b. Chemical Waste Basin Line 3. FLOW RATE MEASUREMENT DEVICES a. Liquid Radwaste Effluent Line b. Steam Generator Blowdown Line D(4)D(4)N.A.N.A.R R N.A.N.A.Page 22 of 155 M m -- M- --M M m M M M M M M M m Salem ODCM Rev. 24 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: I .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 I annunciation occurs if any of the following conditions exist: I. 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. C)(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, (I 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: I. Instrument indicates measured levels at or above the alarmn/trip setpoint.>.2. Circuit failure. (Loss of Power)# The RI 8's channels off-line channels which requires periodic decontamination. Any count rate"K indication above 10,000 cpm constitutes a SOURCE CHECK for compliance purposes.0 r-LIJ Page 23 of 155 Salem ODCM Rev. 24 I 3/4.3 INSTRUMENTATION 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.9 In accordance with Salem Units 1 and 2 Technical Specifications 6.8.4.g.1, the 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 with the ODCM.APPLICABILITY: As shown in Table 3.3-13 ACTION: a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip I setpoint less conservative than required by the above CONTROL, without delay suspend the release of radioactive gaseous 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 gaseous effluent.

monitoring I (/. instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.z '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.II c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable. 0- SURVEILLANCE REQUIREMENTS z 0_o I>L 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be ry demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, (D z CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.cw 0 0 a-D I 24 of 155 USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES Salem ODCM Rev. 24 TABLE 3.3-13: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OplPtR A RT APPIIC2ARITI TY A CTIOb1'APPLICABILIT 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)I (1R12A or 1R41A&D, 2R12A or 2R41A&D) #1 (1R12A or IR41A&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 I (1RME4, 5 or 1XT8911, *2RME4, 5 or 2XT8911)d. Process Flow Rate Monitor (stack) 1 (1RM-1FA8603, *2RM-2FA8603)

e. Sampler Flow Rate Monitor I (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 Page 25 of 155 Salem ODCM Rev. 24 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 hours.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 hours 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, orC within 24 hours. 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 hours 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 I I I I I I I I I I I I I I 7-)0--0 LI_0 ry z o__Z-0 U-LU-J mD_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 (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.Page 26 of 155 I I I 11M M- -M- M-- M M M M 1M M M USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES Salem ODCM Rev. 24 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(0)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 Page 27 of 155 Salem ODCM Rev. 24 TABLE 4.3-13 (Continued) TABLE NOTATION (I) 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 above the alarm/trip setpoint.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.2. Circuit failure. (Loss of Power)3. Control Room Instrument indicates a downscale failure.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 Z Nreconfirmed using a multi-channel analyzer which was calibrated using one or more NBS (now NIST) standards. I Z

At all times** During Containment Purges OR Containment Pressure -Vacuum Relief ISurveillance requirement-l--< Modes 1-6, R41A/D Monitors providing Alarm and Automatic Termination of Release 0 Modes 1-5, R12A Monitors providing Alarm and Automatic Termination of Release z Mode 6, R12A Monitorsproviding Alarm only (Automatic Termination of Release) is not required).

>During Mode Undefined (Defueled) operation, containment purge is reclassified as a building ry ventilation process stream monitored by the PLANT VENT HEADER SYSTEM.Dio During movement of irradiated fuel within containment with the Containment Equipment Hatch OPEN, only R41A/D can be credited for MINIMUM CHANNEL OPERABLE.a:J During movement of irradiated fuel within containment with the Containment Equipment HatchCLOSED, R4IA/D or RI2A may be credited for MINIMUM CHANNEL OPERABLE, 0 Lt_mI I..I P 2o" 22W Page 28 of 155 -'Salem ODCM Rev. 24'.O 3/4.11 RADIOACTIVE EFFLUENTS 3/4. 1. i LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION

CONTROLS 3.11. 1.1 In accordance with the Salem Units, I 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 i0 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.I O SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analyses program in Table 4.1 1-1.0 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.I°I I:g 0 Pae2>o 5 I R Salem ODCM Rev. 24 TABLE 4.11-1: RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM (I)Zý0 0 C,)z Li (I---(I,>.-U-r, 0~to)rU-(I,)D" Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)a Type Frequency Frequency Analysis (ý.Ci/ml)A. Batch Waste P P Release Each Batch Each Batch Principal Gamma Tanksb Emittersc 5xi0 1-131 1x10 6 P M Dissolve and One Batch/M Entrained Gases lx10 (Gamma Emitters) .P M H-3 Each Batch Composited Gross Alpha lx10.7 P Q Sr-89, Sr-90 518 Each Batch Composited 5x 1 Fe-55 lxi106 B. Continuous Principal Gamma 5x10 7 Releasese W W Emittersc 1. Steam Grab Sample Generator Blowdown 1-131 1x10 6 M M Dissolved and 1xl0s Grab Sample Entrained Gases W M H-3 lxiO Grab Sample Composited Gross Alpha 1x 10 7 W Q Sr-89, Sr-90 Grab Sample Composited 5x100 Fe-55 1x10 6 S, I I I I I I I I I I I I I I I I Page 30 of 155 1 I I 03 i,i V.)LI<(Z 03 I I i,i C-)0 II I~V-Hi 0~.Salem ODCM Rev. 24 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 4.66 S E. V. 2.22E6

Y ° 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), I. 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, ý, and At should be used in the calculation.

It should be recognized that the LLD is defined as an a prori (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. Page 31 of 155 Salem ODCM Rev. 24 S TABLE 4.11-1 (Continued) 0 w)W U M (D"7 V)0"7 0 U]0 CL U--0 Q-1 U](/)7-)©2 07>--0, 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 6 jlCi/ml.Page 32 of 155 I I I I I I I I I I I I I I I I I I Salem ODCM Rev. 24 I .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 W8 cause(s) for exceeding the limit(s) and defines the corrective actions that have been z 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 0 z4.11.1.2 Cumulative dose contributions from liquid effluents shall be determined in accordance with 0 the ODCM at least once per 31 days.>U-0 Ii P o I..Pae3 o 5 Salem ODCM Rev. 24 I 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.3 LIQUID RADWASTE TREATMENT CONTROLS 3.11.1.3 In accordance with the Salem Units I 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.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: 1.V)W 0 z C-):z 0i-0 Cn zD Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability. I I I I I I I I I I I I I I I I I I 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 and 3.0.4 are not applicable.

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.Page 34 of 155 Salem ODCM Rev. 24 E .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 I 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 mre.m/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and b. For iodine-13 1, 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.I @ ACTION: VWith the dose rate(s) exceeding the above limits, without delay restore the release rate to within the I above limit(s).SURVEILLANCE REQUIREMENTS V) 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 4.11-2.0 f-I_13 Page 35 of 155.D)D Salem ODCM Rev. 24 p 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 (ý.Ci/ml)A. Waste Gas P P Storage Each Tank Each Tank Principal Gamma lx 10.4 Tank Grab Sample Emittersb B. Containment P P Principal Gamma lxi 04 PURGE Each PURGE Each PURGE Emitters" Grab Sample *H-3 1xl0" 6 C. Plant Vent Mc'A'e Principal Gamma, lxi0"4 Grab Sample Mc Emittersb H-3 1x10" 6 D. All Release Continuous W, 1-131 1x 101 2 Types as Charcoal Listed in A, Sample B, and C Above Continuoust W" Principal Gamma 1x 10 Particulate Emittersb Sample (1-131, Others)Continuousf M Gross Alpha lx I011 Composite Particulate Sample Continuous Q Sr-89, Sr-90 lxl0" Composite Particulate Sample Continuousf Noble Gas Noble Gasses 1xi 10.6 Monitor Gross Beta or Gamma I I I I I I i I I I I I I I I I I I 0 C-)Ld 0 Z<-0 0 zM 0 a--LJ rm 0 (Y od V):D Page 36 of 155 Salem ODCM Rev. 24 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 I.' than a factor of three.V)ld d. Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded.C)Z 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.V/)D< f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time I period covered by each dose or dose rate calculation made in accordance with CONTROLS z 3.11.2.1, 3.11.2.2 and 3.11.2.3.I0-> g. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 ix hours after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours 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 hours of changing. When samples collected for 24 hours> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement ai does not apply if (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the o0 primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows I that effluent activity has not increased by more than a factor of three...13 P-V)Uj Page 37 of 155 Salem ODCM Rev. 24 0 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.2 DOSE -NOBLE GASES S U)z C-)z 0 i-)w z r-W 0>-2W Li D CONTROLS 3.11.2.2 In accordance with the Salem Units 1 and 2 Technical Specification 6.8.4.g.5 and 8, the air 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 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 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 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.Page 38 of 155 I I I I I I I I I I I I I I I I I I I Salem ODCM Rev. 24 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.3 DOSE -IODINE-1 31, TRITTUM, 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.i ACTION: a. With the calculated air dose from the release of iodine- 131, tritium, and radionuclides in i

particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any W) of the above limits, prepare and submit to the Commission within 30 days, pursuant to (I) 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.

z SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-1 31, 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.U-0 a-P 3i1Page 39 of 155 Salem ODCM Rev. 24 I 3/4,11 RADIOACTIVE EFFLUENTS 3/4.11.2.4 GASEOUS RADWASTE TREATMENT CONTROLS U 3.11.2.4 In accordance with the Salem. Units I 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 dosesdue 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: U 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 L0 Specification 6.9.2, a Special Report that includes the following information: 0-I- 1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability. <)0 2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and I.---I 0 3. Summary description of action(s) taken to prevent a recurrence. z 0 b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable. 0>I SURVEILLANCE REQUIREMENTS d> 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.0~I ta-Page 40 of 155:DI Salem ODCM Rev. 24 3/4.11 RADIOACTIVE EFFLUENTS i 3/4.11.4 TOTAL DOSE CONTROLS i 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).I 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 I .case, prepare and submit to the Commission within 30 days, pursuant to Technical VSpecification 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 o-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 0 levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CER Part 190 or 10 CFR 72.104 has not 0 already been corrected, the Special Report shall include a request for a variance in-z 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.u.b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable. I > SURVEILLANCE REQUIREMENTS 0 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in Cn*b accordance with CONTROLS 4.11.1.2, 4.11.2.2, 4.11.2.3, and in accordance with the ODCM.0- 4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and from 1W radwaste storage shall be determined in accordance with the ODCM.Page 41 of 155 FD I Salem ODCM Rev. 24 I.3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1. In accordance with Salem Units 1 and 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 I 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. I 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 l30 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:- , D0 concentration (1) +concentration (2) 1.0 z reporting level (1) reporting level (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 annhua'l dose* to a z_ 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; d> however, in such an event, the condition shall be reported and described in the AnnualRadiological Environmental Operating Report pursuant to CONTROL 6.9.1.7.0 mI*The methodology used to estimate the potential annual dose to a MEMBER OF THE PUBLIC 0 shall be indicated in this report.w I Ld' Page 42 of 155 Salem ODCM Rev. 24 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.

I ./ 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 V) Table 4.12-1.z uI-0>-r-Y 0 1+/-Page 43 of 155 USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES 9 Salem ODCM Rev. 24 TABLE 3.12.1-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTAIVE SAMPLES AND SAMPLE LOCATIONS (')SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS 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.Page 44 of 155 I-I --I- I-I --I -I I-I- -/- I-I-I -M- m m m -M- --M M- M M M MM USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES Salem ODCM Rev. 24 TABLE 3.12.1 -1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTAIVE SAMPLES AND SAMPLE LOCATIONS (1)SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS 2. AIRBORNE Radioiodine and Particulates Samples from 6 locations: Continuous sampler operation with sample collection weekly or more frequently if required by dust loading.Radioiodine Canister 1- 131 analysis weekly.4 Samples -One sample 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. Page 45 of 155 USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES 0 Salem ODCM Rev. 24 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTAIVE SAMPLES AND SAMPLE LOCATIONS (1)SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY.OFANALYSIS

3. WATERBORNE

a. Surface(5)One sample upstream One sample downstream One sample outfall One sample cross-stream Grab sample monthly Gamma isotopic analysis(4) monthly. Composite for tritium analysis quarterly.

b. Ground c. Drinking (10)d. Sediment 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 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 Page 46 of 155 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 USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES Salem ODCM Rev. 24 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTAIVE SAMPLES AND SAMPLE LOCATIONS ()SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF-ANALYSIS

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(s).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.of 155 USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES Salem ODCM Rev. 24 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTAIVE -SAMPLES AND SAMPLE LOCATIONS ()SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF-ANALYSIS

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.Page,"48 of 155 i M -----M- M- M- M- M- M 1

-- Salem ODCM Rev. 24 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 3.12-1 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 6.9.1.7. 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 I .uthe cause of the unavailability of samples for the pathway and justifying the selection of the new location(s) for obtaining samples.Z (2) One or more instruments, such as pressurized ion chamber, for measuring and recording dose rate<T- 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<1 for measuring direct radiation.. The frequency of analysis or readout will depend upon the V) 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 0I 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 shallbe analyzed for gross beta radioactivity 24 hours 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 t', shall be performed on the individual samples.(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting 0 radionuclides that may be attributable to the effluents from the facility.U-ZID.0 61+/-Page 49 of 155 Salem ODCM Rev. 24 I TABLE 3.12.1-1 (Continued) 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 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 I 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 istapped for drinking or irrigation I purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. I (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 monitored as management audit. Broad leaf vegetation may be obtained in lieu of milk L,. collections. 0 (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 z paid to including samples of tuberous and root food products. The Delaware River at the location of Salem and Hope Creek Nuclear Power Plants is a brackish water source. No (A 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. _ (10) No groundwater samples are required as liquid effluents discharged from Salem and> 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 0 unaffected water supply is required.U~-c12I 0 U--j 0 a_..-I, Page 50 of 155:DI ---M M- M M M M M M MM USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES Salem ODCM Rev. 24 TABLE 3.12-2: REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS Water Airborne Particulate Fish Milk Food Products Analysis (pCi/l) or Gases (pCi/m3) (pCi/Kg, wet) (pCi/l) (pCi/Kg, wet)H-3 3 x 10 4 Mn-54 1 x 101 3 x 104 Fe-59 4x 10 2 1 x 101 Co-58 1 x 101 3 x 104 Co-60 3 x 102 1 X 104 Zn-65 3 x 10 2 2 x 104 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 2x 10 3 70 2 x 10 3 Ba-La-140 2 x 102 3 x 102 Page 51 of 155 USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES w 0 wp Salem ODCM Rev. 24 TABLE 4.12-1: DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS('), (2)LOWER LIMITS OF DETECTION (LLD) (3)Water Airborne Particulate Fish Milk Food Products Sediment Analysis (pCi/l) or Gases (pCi/m3) (pCi/Kg, wet) (pCi/l) (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 Page 52 of 155 Salem ODCM Rev. 24 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 4.66.*S E

V
2.22E6
Y , exp(-2At)(11 I z Where:-o 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 I D 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), Z" E is the counting efficiency (as counts per disintegration),_0 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, and> At for environmental samples is the elapsed time between sample collection (or end of the ry sample collection period) and time of counting.0 Typical values of E, V, Y, and At should be used in the calculation.

P 3yPage 53 of 1.55 a Salem ODCM Rev. 24 TABLE 4.12-1 (Continued) TABLE NOTATION 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 inithe Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7.I I I I I I I I I I I I I I I I I I (n LU 0 Cn Z z U-n-0 L.o (A)7 LU 0 z 0 LU 0_D>-LUd z 0 LU_LU (AJ D~Page 54 of 155 Salem ODCM Rev. 24 RADIOLOGICAL ENVIRONMENTAL MONITORING I 3/4.12.2 LAND USE CENSUS I 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. I APPLICABILITY: At all times.I 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. 1.8S.5 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 F ~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.

Z *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.c-1 0 Page 55 of 155 Salem ODCM Rev. 24 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING .3/4.12.2 LAND USE CENSUS (Cont'd)s V)V)C_9 D 0 V-z 0 Lýz (A D z-0 Cu w¢U-U-D>-ka-CrY t-U-C/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 6.9.1.7.Page 56 of 155 I I I I I I I I I I I I I I I I I i I Salem ODCM Rev. 24 i1 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLSlI C-)0 7-0 U-U->r'y 0v>-J V, 12 V')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.Page 57 of 155 Salem ODCM Rev. 24 BASES FOR SECTIONS 3.0 AND 4.0 CONTROLS AND Ii z C-z 0 H--00 V.0 z U-.0 0 0 LU LU 0 C12 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.Page 58 of 155 Salem ODCM Rev. 24 1 .I*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(')Gross Activity 2a Containment Fan Coolers Service IR13A and BC)Water Line Discharge Gross Activity Unit 2: T/S Table Item No. Instrument Description Acceptable RMS Channels I a Liquid Radwaste Effluent Line Gross 2R1 8 Activity l b Steam Generator Blowdown Line 2R19A,B,C, Gross Activity and D(')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. Page 59 of 155 V)Vi)0 V-I.J II Salem ODCM Rev. 24 3/4.3 INSTRUMENTATION S BASES I C/)z z 0 Ci-)H-H-0 0 cZ w CL (n.Li, bl U--z 0 0._cx)w~~w~r ci-)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 relea'ses 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 1R41A and D 2 Noble Gas Activity 2a Containment Purge and IR12A Pressure -Vacuum Relief ,-or Noble Gas Activity or 1 R41tA and D !)2 3a Plant Vent Header System 1R41A and D (1)(2)Noble Gas Activity 3b Plant Vent Header System IRME 4, 5 (1R41)Iodine Sampler (3) or 1XT8911 (1R45)3c Plant Vent Header System 1RME 4, 5 (1R41)Particulate Sampler (3) or S1XT8911, (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) IR41D is the setpoint channel. IR41A 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. Page 60 of 155 I I I I I I I I I I I I I I I I I I I Salem ODCM Rev. 24 3/4.3 INSTRUMENTATION I.BASES I*Cf)I;U-0Z n,i Itif I, Unit 2: T/S Table Instrument Description Acceptable RMS Item No. Channels I a Waste Gas Holdup System Noble Gas Activity 2R41A and D(I)(2 2a Containment Purge and Pressure -Vacuum Relief 2R12A or 2R41A Noble Gas Activity and Dl)(2)3a Plant Vent Header System Noble Gas Activity 2R41A and D(1)(')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. Page 61 of 155 I Salem ODCM Rev. 24 3/4.11 RADIOACTIVE EFFLUENTS I BASES I 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION The CONTROL is provided to ensure that the concentration of radioactive materials released in liquid 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 1, 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).3/4.11.1.2 DOSE This CONTROL is provided to implement the requirements of Sections IL.A, III.A, and IV.A of I 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 U material in liquid effluents will be*kept "as low as is reasonably achievable." Also, for freshwater sites z 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 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 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 0 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 I Iy Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor 0 Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, z October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from ry Accidental and Routine Reactor Releases for the Purposes of Implementing Appendix I," April 1977.ry The CONTROL applies to the release of liquid effluents from each reactor at the site. For units with 0 ,L° shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among w the units sharing that system.z 0 W I"Page 62 of 155 Cn" D I~ Salem ODCM Rev. 24 I O 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 I1.0 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* r 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 Cn specified in Appendix B, Table II of 10 CFR Part 20 [10 CFR Part 20.106(b)]. For MEMBERS OF I Q 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 V) MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500mrem/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 W Appendix I, 10 CFR Part 50. The CONTROL implements the guides set forth in Section Il.B of Ld> Appendix I. The ACTION statements provide the required operating flexibility and at the same time a0 implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive ..W 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 o actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be LQa Page 63 of 155 I Salem ODCM Rev. 24 RADIOACTIVE EFFLUENTS BASES 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 l Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October 1.977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision I 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, 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 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 m data suchthat the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is I 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 V) Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor 0" Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October< 1977 and Regulatory Guide 1 .l I 1,."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<z atmospheric conditions. The release rate controls for iodine-131, tritium, and radionuclides in C0 particulate form with half-life greater than 8 days are dependent.on the existing radionuclide pathways to man in the areas att and beyond the SITE BOUNDARY. The pathways that were examined in the V- development of these calculations were: 1) individual inhalation of airborne radionuclides, 2)2ý deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3)o deposition onto grassy areas where milk animals and meat producing animals graze with consumption o_ 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 0 U zU-The requirement that the appropriate portions of this system be, used, when specified, provides ,.,d 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 10CFR Part 50.36a, o General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in W Section II.0 of Appendix I to 10,CFR Part 50. The specified limits governing the use of appropriate M J portions of the systems were specified as a suitable fraction of the dose design objectives set forth in V)_ Section II.B and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents. L I IIa Page 64 of 155 DI zo Salem ODCM Rev. 24* RADIOACTIVE EFFLUENTS I. 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 40CFR 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 I .annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 or 10 CFPR 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 Iradius of 8 km must be considered. If the dose to any MEMBER OFTHE 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 w 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 requirements for dose limitation of 10 CFR Part 20, as addressed in CONTROLS3.11.1 and 3.11.2. An individual is not considered a MEMBER OF THE PUBLIC during any S period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.0 Ii Page 65 of 155 1 rK I Salem ODCM Rev. 24 RADIOACTIVE EFFLUENTS I'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 radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section 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. 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. 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 r (before the fact)p 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 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 z survey, aerial survey or consulting with local agricultural authorities shall be used.. This census satisfies the requirementsiof Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens (.gs 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 minimumngarden size, the following assumptionswere made: 1) 20% of the garden was 0 used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) yield of 2 kg/mn 2.3/4.12.3 INTERLABORATORY COMPARISON PROGRAM This requirement for participation in an Interlaboratory Comparison Program is provided to ensure that i. 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 r environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes 0 o,. of Section IV.B.2 of Appendix I to 10 CFR Part 50.t__ii° I 0~tLd rY Page 66 of 155 DC-I- I r", I I I.I I I I I I I.(f)C-)0 Vj)w 0 U--Salem ODCM Rev. 24 SECTION 5.0 DESIGN FEATURES Page 67 of 155 Salem ODCM Rev. 24 S 5.0 DESIGN FEATURES 5.1 SITE 5.1.3 UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIOUID EFFLUENTS S V)0 z L-)z"-y z>.-w 0 Uv-w z 0 0_w w (./3 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.) Page 68 of 155 I I I I I I I I I I I I I I I I I I I Salem ODCM Rev. 24 I N°FIGURE 5.1-3: AREA PLOT PLAN OF SITE I I I I I-.1 -*.i,-S --* --S --** .-A-S u-I u-I U, I I..0 7 0 0 U->U U-06-S ~*a Ii 1 1z.I I I I I-=-=== 0) --I I I i iZ i-C l_.J* , I-- .j ,' 1 E11------------- ,, "',-"------------ -~ ~ ~ ~ ~ ---. ----c-f w 08 OI SECUR-TY----- I I Myo E 'RIVER Page 69 of 155 I Salem ODCM Rev. 24 6.0 ADMINISTRATIVE CONTROLS I 6.9.1.7 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.7 In accordance with Salem Units I 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 I of each year. I The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the i'adiolbgical 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 I 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 I BOUNDARY and a second covering the more distant locations, all keyed to a table giving dista.nces 0" and directions from the midpoint of a line between the centers of Salem units I & 2 containment z domes; the results of licensee participation in the Interlaboratory Comparison Program, required by o CONTROL 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

z 6.9.1.8 RADIOACTIVE EFFLUENT RELEASE REPORT H--V- 6.9.1.8 In accordance with Salem Units 1 and 2 Technical Specifications 6.9.1.8, The Annual Radiological Effluent Release Report* covering the operation of the unit during the previous calendar o year shall be submitted prior to May I of each year and in accordance with the requirements of_ 10CFR50.36a. I Q-1 The Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid Z_ 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 r_W: 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. I Uv--"J

A single submittal may be made for a multiple unit station. The submittal should combine those'n sections that are common to all units at the station; however, for units with separate radwaste 0 systems, the submittal shall specify the releases of radioactive material from each unit.0 (/P I La~lczPage 70 of 155 wv,,

Salem ODCM Rev. 24 U 6.9.1.8 RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) I .O 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 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 V) 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 (asdefined 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), z- 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, ry evaporator bottoms),>- e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and U-> f. Solidification agent or absorbent (e.g., cement, urea formaldehyde). 0 E u- 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 Lo during the reporting period.W Page 7l of 155 0 I Salem ODCM Rev. 24 6.9.1.8 RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) I 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 1,0CFR50.59;

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;o d. An evaluation of the change, which shows the predicted releases of< radioactive materials in liquid and gaseous effluents and/or quantity of solid-o waste that differ from those previously predicted in the license application and amendments thereto;z Vo e. An evaluation of the change, which shows the expected maximum exposures D< to individual in the unrestricted area and to the general population that differ 0 from those previously estimated in the license application and amendments z" thereto;0_ f. A comparison of the predicted releases of radioactive materials, in liquid and ,w, gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;z_-g. An estimate of the exposure to plant operating personnel as a result of the Ui change; and" I 0 h. Documentation of the fact that the change was reviewed and found acceptable

"- by the PORC.e-JI2. Shall become effective upon review and acceptance by the PORC.0 w0 I Page 72 of 155 Lw 03 I 17>Fi I*I I I I IW C)r,.ILl C/)D U--0~.Salem ODCM Rev. 24 PART II -CALCULATIONAL METHODOLOGIES Page 73 of 155 I Salem ODCM Rev. 24 I.1.0 LIQUID EFFLUENTS 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 and ODCM CONTROLS are summarized as follows: 1) Alarm (and Automatic Termination) -I-RI 8 (Unit 1) and 2-R1 8 (Unit 2) provide the alarm U and automatic termination of liquid radioactive material releases as required by ODCM CONTROL 3.3.3.8.1-R19 A, B, C, and D provide the alarm and isolation function for the Unit I steam generator blowdown lines. 2-R19 A, B, C, and D provide this function for Unit 2. I 2) Alarm (only) -The alarm functions for the Service Water System are provided by the radiation monitors on the Containment Fan Cooler discharges (1RI 3 A and B for Unit I and 2R 13 A and B for Unit 2).Releases from the secondary system are routed through the Chemical Waste Basin where the I effluent is monitored (with an alarm function) by R37 prior to release to the environment. Liquidradioactive release flow diagrams with the applicable, associated radiation monitoring I ,.,U3 instrumentation and controls are presented as Figures 1-1 and 1-2 for Units I and 2, respectively. The Liquid Radioactive Waste System is presented in Figure 1-3.1.2 Liquid Effluent Monitor Setpoint Determination z 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 V 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 0_- nolB, Tablegaes.H, Column 2, (Appendix F) for radionuclides and 2.0E-04 [.Ci/ml for dissolved or entrained V) noble gases).>LU The following equation* must be satisfied to meet the liquid effluent restrictions: -~C (F + f)0y c ( f (1.1)I> IfWhere:__ C = the effluent concentration limit of ODCM CONTROL 3.11.1.1 implementing the 10 uD CFR 20 MPC (Appendix F) for the site, in p.Ci/ml 0. c the setpoint, in ý.Ci/ml, of the radioactivity monitor measuring the radioactivity V). concentration in the effluent line prior to dilution and subsequent release; the setpoint, Q- Page 74 of 155 D" I Salem ODCM Rev. 24* 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-0133 I 1.2.1 Liquid Effluent Monitors (Radwaste, Steam Generator Blowdown, Chemical Waste Basin and Service Water.I The setpoints for the liquid effluent monitors at the Salem Nuclear Generating Station are determined by the following equations: SP[MPCe

EN *c F *AF]+bkg (1.2)I V) Ci (gamma only)MPCe~ (1.3)F Ci MPCi (gamma only)i" MPC i< Where: SP = alarm setpoint corresponding to the maximum allowable release rate (cpm)SMPCe = an effective MPC value for the mixture of gamma emitting radionuclides in the effluent stream (pjCi/ml)i QC 1 = the concentration of radionuclide i in the undiluted liquid effluents

(ý.Ci/ml)ZV) MPCI = the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table 1I, WColumn 2 (Appendix F) (p.Ci/ml)SEN = the sensitivity value to which the monitor is calibrated (cpm per ý.Ci/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)Sbkg = the background of the monitor (cpm)> bk = Correction factor to account for non-gamma emitting nuclides in setpoint calculations. o AF = an allocation factor applicable for steam generator blowdown a The radioactivity monitor setpoint equation (1.2) remains valid during outages when the circulating 2: ' 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 Page 75 of 155 I Salem ODCM Rev. 24 available plant discharge dilution and thereby minimize the potential offsite doses, batch releases from I either Unit-I or Unit-2 may be routed to either the Unit-i 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-1 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 liCi/ml (Unit 1) and 4.81E-06 pCi/ml (Unit 2). (refer to Appendix A for justification); b) for additional conservatism*, substitution of the 1- 131 MNC value of 3E-07 pCi/ml for the R1 9 Steam Generator B lowdown monitors, the R-37 Chemical Waste Basin monitor and the R- 13 Service Water monitors;I 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.C 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 U 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, o incorporate uncertainties and instrument drift. These factors will cause the actual installed instrument setpoint to be at a lower (conservative) value. However, for batchreleases, when the rate is controlled, 0- 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 o RI 8 monitors, the setpoint value-used for calculating the allowable release rate should be that value V0 prior to correction for uncertainty and drift.>-* Based upon the potential for 1-131 to be present in the secondary and service water systems, Z 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 idn the R-13 Service Water monitors.o **Setpoints using the Allocation Factor of 0.5 become invalid if primary-to-secondary leaks are t-t-,,,identified in more than two steam generators simultaneously. ý5 ***The Containment Fan Coil Unit Discharge to Service Water Line is routed to the opposite 0 Unit's Circulating Water System discharge. Therefore, during periods when circulating W0 I.:9 Page 76 of 155I ry" LýJ Salem ODCM Rev. 24* 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 1I, Column 2 (Appendix F) for radionuclides other than noble gases. Noble gases are limited to a diluted concentration of 2.OE-04 p.Ci/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: MPG (1.4)Where: Ci actual concentration of radionuclide i as measured in the undiluted liquid effluent (PCi/ml)MPC = the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, I .Column 2 (pCi/ml) [ODCM Appendix F]= 2E-04 pLCi/ml for dissolved or entrained noble gases I 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. V) ODCM CONTROL 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC 0- -from radioactive materials in liquid effluents from each unit of the Salem Nuclear Generating Station_.) to: LU r?, -during any calendar quarter;0_ < 1.5 mrem to total body per unit< 5.0 mrem to any organ per unit-during any calendar year;S< 3.0, mrem to total body per unit< 10.0 mrem to any organ per unit..o Page 77 of 155 Salem ODCM Rev. 24 Per the surveillance requirements of ODCM CONTROL 4.11.12, the following calculational methods shall be used for determining the dose or dose commitment due to the liquid radioactive effluents from Salem: S 1.67E-02*VOL

Aio)CW i.(1.5)Where: Do = dose or dose commitment to organ o (mrem). Total body dose can also be calculated using site-related total body dose commitment factor.Ai, = site-related ingestion dose commitment factor to the total body or any organ o for radionuclide i (mrem/hr per ptCi/ml)Ci = average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (l.Ci/ml)VOL = volume of liquid effluent released (gal)CW = average circulating water discharge rate during release period (gal/min)1.67E-02 = conversion factor (hr/min)The site-related ingestion dose/dose commitment factors (Ai,) are presented in Table 1-2 and have been derived in accordance with the requirements of NUREG-0133 by the equation: I I I I I I I I I I I I I I I Ao 1.14E +05 * [(UI
B~i)+(UF*

BF)]* DF io (1.6)0 z I rD 0 n Z 0 wCL w-.J 0 z~>-w.u w~0 Where: Ai =UI =B 1 i =UF =BFj =DFi 0 =1. 14E+05 =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 [tCi/ml)adult invertebrate consumption (5 kg/yr)bioaccumulation factor for radionuclide, i in invertebrates from Table 1-3 (pCi/kg' per pCi/l)adult fish consumption (21 kg/yr)bioaccumulation factor for radionuclide i in fish from Table 1-3 (pCi/kg per pCi/1)dose conversion factor for nuclide i for adults in pre-selected organ, o, from Table E- 1I of Regulatory Guide 1.109 (mrem/pCi) conversion factor (pCi/pCi

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.Page 78 of 155 Salem ODCM Rev. 24 1.4.2 Simplified Liquid Effluent Dose Calculation.
O 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 Dt 1.21E + 03* VOL Dtb= :* Ci (1.7)Maximum Organ_max 2.52E + 04 *VOL *Zc(CW Where: Ci = average concentration of radionuclide i, in undiluted liquid effluent representative of I the volume VOL (ýxCi/ml)VOL = volume of liquid effluent released (gal)CW = average circulatingwater discharge rate during release period (gal/min)I .Dtb = conservatively evaluated total body dose (mrem)Dmax = conservatively evaluated maximum organ dose (mrem)CD 1.2 1E+03 = conversion factor (hr/min) and the total body dose conversion factor (Fe-59, total body Z -- 7.27E+04 mrem/hr per p.Ci/ml)-U- 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 itCi/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_0 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 Ix discharges.

Potential releases are controlled/monitored by the Steam Generator Blowdown monitors 0 (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 Q:: secondary leakage. Any potentially significant releases will be via the Chemical Waste Basin with the 0 major source of activity being the Steam Generator Blowdown.I With identified radioactive material levels in the secondary system, appropriate samples should be S* collected and analyzed for the principal gamma emitting radionuclides. Based on the identified 1U ix Page 79 of 155 py I Salem ODCM Rev. 24 radioactive material levels and the volume of water discharged, the resulting environmental doses may* be calculated based on equation (1.5).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 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 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 regulatory compliance, the releases are monitored by Radiation Monitor R-37. Samples are also I 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 (1.5).1.6 Liquid Effluent Dose Projections 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:I 0z- 0.375 mrem to the total body, or-- -1.25 mrem to any organ.az 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 q-D the Salem FSAR has processing capabilities meeting the NRC ALARA design requirements and may 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:Z unit individually. Exceeding the projected dose requiring processing prior to release for one unit does 0 not in itself dictate processing requirements for the other unit.Ia Dose projections are made at least once per 31 days by the following equations: z_ D tbp D tb 9 (1.9)0 D maxp D max (1.10)_J m Where: 0 Qn. Dtbp the total body dose projection for current calendar quarter (mrem)i~ia:Pace 80 of 155 D , Salem ODCM Rev. 24 Dtb = the total body dose to date for current calendar quarter as determined by Equation 1.5 or 1.7 (mrern)n

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. l-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 1-R41D for Unit-I and 2-R4ID 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 z reliefs (*)3) Plant Vent -The Plant Vent for each respective unit receives discharges from the waste gas hold-up Z 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 I ~ 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 Sz" 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 rotamneter)..l Gaseous radioactive effluent flow diagrams with the applicable, associated radiation monitoring 0 instrumentation and controls are presented in Figures 2-I. A simplified diagram of the Gaseous radioactive waste disposal system is provided in Figure 2-2.0.The R12A in Mode 6 provides containment monitoring and alarm functions without automatic O isolation I..Oa Page 81 of 155 ('e S Salem ODCM Rev. 24 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 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: FRA C=[ 4.72E + 02*

VF*Z(Ci *Ki)J 500 FRA C = [4.72 E +02
v Q*VF *ZCi *(Li + 1. Mi))j3000 (2.1)(2.2)Where: FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate I I I I I I I I I I I I I I I I I I I CT)0 0 67)z LI..Co r,, w 0-L-V-0.--.--m _0 U-(I..Di.Vz YQ= annual average meteorological dispersion to the controlling site boundary location (sec/in 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 (mtenrlyr per ptCi/m 3 from Table 2-1)Li = beta skin dose conversion factor for noble gas radionuclide i (mrem/yr per gCi/m 3 from Table 2-1)Mi = gamma air dose conversion factor for noble gas radionuclide i (mrem/yr per pCi/m 3 from Table 2-1)1.1 = mrem skin dose per nrad gamma air dose (mrem/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)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: Page 82 of 155 Salem ODCM Rev. 24 SP=[AF*-7"FRAC J+bkg (2.3)Where: SP = alarm setpoint corresponding to the maximum allowable release rate (cpm)SEN = monitor sensitivity (cpm per 4tCi/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 V on the grab sample analysis, to eliminate the potential of periodically having to adjust the setpoint to H 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;V) -a radionuclide distribution' comprisedof95%Xe-133,2%Xe-135, 1%Xe-133m, 1%Kr-88 and< meKr-85;mandsm

0) -an administrative allocation factor of 0.25 to conservatively ensure that any simultaneous releases z" from Salem Units I 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.W C a) Adopted from ANSI N237-1976/ANS-18.1, Source Term Specifications, Table 6 U-c, 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations -10 CFR 20> 2.3.1 Site Boundary Dose Rate -Noble Gases 0©- ODCM CONTROL 3 1.2.l.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-n

established to ensure that these release limits are not exceeded.

In the event any gaseous releases from 0 the station results in an alarm setpoint being exceeded, an evaluation of the SITE BOUNDARY dose o. rate resulting from the release shall be performed using the following equations: Irla Page 83 of 155 I Salem ODCM Rev. 24 I Dt-- (K

Q,) (2.4)and D., = Q Z((Li + 1.1Mi)*Qi)

(2.5)Where: I Dtb = total body dose rate (mrem/yr)D, = skin dose rate (mremn/yr) Z/ = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/r 3)Qi = average release rate of radionuclide i over the release period under evaluation (l.Ci/sec) Ki = total body dose conversion factor for noble gas radionuclide i (mrem/yr per RCi/m 3 , from Table 2-1)Li = beta skin dose conversion factor for noble gas radionuclide i (mrem/yr per LCi/m 3 , from Table 2-1)Mi = gamma air dose conversion factor for noble gas radionuclide i (mrad/yr per j, Ci/m 3 , from Table 2- I)1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad) -S As appropriate, simultaneous releases from Salem Units 1 and 2 and Hope Creek will be considered in U3"' evaluating compliance with the release rate limits of ODCM CONTROL 3.11.2.1 a, following any z release exceeding the above prescribed alarm setpoints. Monitor indications (readings) may be averaged over a time period not toexceed 15 minutes when<Z determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity. I V The 15-minute averaging is needed to allow for reasonable monitor response to potentially changing D

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 I-.-co responses may be excluded from the analysis.0 NOTE: For administrative purposes, more conservative alarm setpoints than those as 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-U- 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. 0 LO" 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 ca rate.0 n V)rK Page 84 of 155 D I Salem ODCM Rev. 24* 2.3.2 Site Boundary Dose Rate -Radioiodine and Particulates

ODCM CONTROL 3.11.2.1.b limits the dose rate to <1500 mrem/yr to any organ for 1-131, 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**i (2.6)Q Z(Ri Where: Do = average organ dose rate over the sampling time period (mren/yr)I % = atmospheric dispersion to the controlling SITE BOUNDARY location for the inhalation pathway (sec/M 3)Rio = dose parameter for radionuclide i (mrem/yr per p.Ci/m 3) and organ o for the child I 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 (ýtCi/sec) i By substituting 1500 mremryr 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 (I) limiting potential pathway, age group and organ (inhalation, child, thyroid -- Rio = 1.62E+07 mrem/yr W" per pCi/m 3), the allowable release rate for 1-131 is 42 tCi/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 JLCi/sec.0 For a 7 day period, which is the nominal sampling and analysis frequency for 1-13 1, 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. .b limits on allowable release rate.I- 2.4 Noble Gas Effluent Dose Calculations -10 CFR 50.:f 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 conipliance with the quarterly dose limits of<5 mrad, gamma-air and <10 mrad, beta-air and thecalendar year limits <10 mrad, gamma-air and <20 mrad, beta-air. The limits are applicable separately

V to each unit and are not combined site limits. The following equations shall be used to calculate the 0 gamma-air and beta-air doses: coDr=3.17E -O8*,ZQ (M Q) (2.7)I n I Salem ODCM Rev. 24 and Dfi = 3.17E. 08 Q *Z(N,*Qi)

(2.8)Q Where: Dy = air dose due to gamma emissions for noble gas radionuclides (mrad)Do = air dose due to beta emissions for noble gas radionuclides (mrad)' = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/mr 3)XQ Q = cumulative release of noble gas radionuclide i over the period of interest (ýiXi) where tCi = (4Ci/cc)*(cc released) or (ý.Ci/sec)*(sec released)Mi = air dose factor due to gamma emissions from noble gas radionuclide i (mrad/yr per ýiCi/m 3 , from Table 2-1)Ni = air dose factor due to beta emissions from noble gas radionuclide i (mrad/yr per PCi/m 3 , Table 2-1)3.17E-08 = conversion factor (yr/sec)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..)V)_rDY 3-E * * (2.9)C- 0.50 Q< and VI)ID = Q Nff * (2.10)V) 0.50 Q z" () Where:>Menf = 5.3E+02, effective gamma-air dose factor (mrad/yr per ptCi/m 3)Neff = 1. 1E+03, effective beta-air dose factor (mrad/yr per ýLCi/m 3) I Qi = cumulative release for all noble gas radionuclides (IACi), where J.LCi = (ýCi/cc) * (cc'"> released) or (gCi/sec)

(sec released)> 0.50 = conservatism factor to account for potential variability in the radionuclide distribution 0 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 c beta-air doses.0 kda: Page 86 of 155 U-D D I Salem ODCM Rev. 24 U 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 I-13 1, tritium and particulates with half-lives greater than 8 days: Daop =3.17EO- 08 *SW * -p*S(R *QQ)) (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 zQ atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (sec/m 3)D/Q = atmospheric deposition for vegetation, milk and ground plane exposure pathways I(m2)Riop = dose factor for radionuclide i (mrem/yr per .Ci/m 3) or (in 2 -mrem/yr per p.Ci/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. wQ = cumulative release over the period of interest for radionuclide i -- 1-131, tritium, or z radioactive material in particulate form with half-life greater than 8 days (pCi).-SF, = annual seasonal correction factor to account for the fraction of the year that the applicable exposure pathway does not exist.<1) For milk arid 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 LI) For evaluating the maximum exposed individual, only the controlling pathways and age group as Sidentified 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.ita 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).0 II,,," D ma..= 3.17E- 08 *I* SS* RI-131*ZEQi (2.12)C.da Page 87 of 155 I Salem ODCM Rev. 24 Where: Dmax = maximum organ dose (mrem)Ri-1 3 1 = 1-131 dose parameter for the thyroid.for the identified controlling pathway= 1.05E+12, infant thyroid dose parameter withlthe grass-cow-milk pathway controlling (M 2 -mrem/yr per p.Ci/sec)W = D/Q for radioiodine, 2. 1E-1 0 1/m 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 (J.tCi)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, R41D on plant vent, and the plant vent particulate and charcoal samplers). However, if the Steam Generator blowdownis 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 0D z calculate potential releases.0Qi = the release rate of radionuclide, i, from the steam generator flash tank vent (p.Ci/sec) Wy Ci = the concentration of radionuclide, i, in the secondary coolant water averaged over not 0D more than one week (pCi/ml), Z 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 rý' SQft,= the measured steam quality in the flash tank vent; or an assumed value of 0.85, based on NUREG-0017. --Jz_ Tritium releases via the steam flashing may also be quantified using the above equation with the c. assumption of a steam quality (SQf,,) equal to 0. Since the H-3 will be associated with the water 0 t..da Page 88 of 155 w2 t0 I Salem ODCM Rev. 24* 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: I= 0.072* Ci** gb (2.14)For H-3, the simplified equation is: Qi = 0.48 *Ci* Rgb (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-0017, Revision 1. The partitioning factors for the Sradioiodines 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: Qi = 0.13* (CU* SF.)* PFi (2.16)*

Where: "Qj = release rate of radionuclide i via pathway j,(jtCi/sec)
I z = concentration of radionuclide i, in pathway j,(p.Ci/ml) -SFj = steam flow for release pathwayj= 400,000 lb/hr per PORV-850,000 lb/hr per safety relief valve< 62,500 lb/hr for auxiliary feed pump exhaust D PF = partitioning factor, ratio of concentration in steam to that in the water in the steam F_ generator-0.01 for radioiodines z= 0.005 for all other particulates V> 1.0 forH-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. 0 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.ry Page 89 of 155 I..ryld:D/ I Salem ODCM Rev. 24 Note: The expected mode of operation would be to isolate the effected steam generator, thereby I* 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, iLe., 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: SDlp Dr*9 d (2.17)z Dp
1(2.18)II DD maxp =D max* (2.19)z co Where: 0_ 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)z_ Dp = beta air dose projection for current calendar quarter (mrad)-_a. Dp = beta air dose to date for current calendar quarter as deteifrnined by Equation 2.8 or2.10 (mrem)> Dmaxp = maximum organ dose projection for current calendar I oquarter (mrem)Dmax = maximum organ dose to date for current calendar quarter as I determined by Equation 2.11 or 2.12 (mrem)S d = number of days to date in current calendar quarter 0 91 = number of days in a calendar quarter 0~w I rY Page 90 of,155 0 D -I Salem ODCM Rev. 24 U 3.0 SPECIAL DOSE ANALYSES I Q 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 hours 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 I 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 I *Installation (ISFSI): No other fuel cycle facilities contribute to the MEMBER OF THE PUBLIC V dose for the Artificial Island vicinity.I ~ 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).0) 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-I > 3 will be revised as specified in ODCM CONTROL 3.12.2.0 Average annual meteorological dispersion parameters or meteorological conditions concurrent with I i O the release period under evaluation may be used.a: Page 91 of 155 I Salem ODCM Rey 24 3.2.2 Direct Exposure Dose Determination. I* 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 I 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 wouldrequire detailed evaluation for demonstrating compliance with 40 CER 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 of dose for assessing 40 CFR 190 or 10 CFR 72.104 compliance. 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I 4.1 Sampling Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in I 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 I 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 ,,,c in the inventory of long lived radionuclides in the environment; z 0 -To detect any changes in the ambient gamma radiation levels; and z 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 Cn are presented in Appendix E.z" O- 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.z 4.2 Interlaboratory Comparison Program U-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 o Program provides a check on the precision and accuracy of measurements of radioactive materials in"_ environmental samples.ccjI 7_ A summary of the Interlaboratory Comparison Program results will be provided in the Annual z o Radiological Environmental Operating Report pursuant to ODCM CONTROL 6.9.1.7.I ctý Page 92 of 155 D0I 11=1- ------m --M M n IM USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES 0 Salem ODC*ev. 24 FIGURE 1-1: LIQUID RELEASE FLOWPATH UNIT 1 GROUND WATER TO NON-RAD (C)REMEDIATION -(Figure 1-2)SYSTEM 4 SERVICE WATER N4ITOR__________F CONTAINMENT FAN COIL UNITS TO CIRCULATING WATER SYSTEM R 13 MONITORS To River TO NON-RAD (B)(Figure 1-2)Page 93 of 155 USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES 0 Salem oDC1Rev. 24 FtGuRE. 1-2-. LiQuI RE, LEASE FLOW PATHt UNIT 2 m m- -M---- M-------- M USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES 0 0 Salem ODC~ ev. 24 FIGURE 1-3: LIQUID RADIOACTIVE WASTE SYSTEM Page 95 of 155 S Salem ODCM Rev. 24 Table 1-1.1: Parameters for Liquid Alarm Setpoint Determinations Unit I Parameter Actual Default Comments Value Value Units M1PCe Calculated 6.05E-06
pCi/rrl Calculated for each batch to be released.MPC 1-13I 3.OE-07 N/A gtCi/rnl 1-131 MPC conservatively used for SG blowdown and Service Water monitor setpoints.
Ci Measured N/A JtCi/ml Taken from gamma spectral analysis of liquid effluent.MPCi as determined N/A ttCi/ml Taken from 10 CFR 20, Appendix B, Table 1I, Col 2 (Appendix F).Sensitivity as determined N/A cpm per Monitor sensitivities are controlled I-RI 8 }.tCi/ml under Public Service Blueprint I-RI9 (A,B,C,D) Document (PSBP) 315733 l-R13 (A and B)CW as determined 1.00E+05 gpm Circulating water system -single CW pump ***RR as determined gpm Determined prior to release; release rate 1-RI8 120 can be adjusted for ODCM CONTROL compliance I-R 19 250 Steam Generator blowdown rate per Generator 1-R13 1.00 E +05 Service Water flow rate for Containment fan coolers Setpoint Calculated N/A cppm Monitor setpoints are controlled under I-R18 Public Service Blueprint Document I-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-RI9 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 I-131. (3E-07 ptCi/ml) has been used for derivation ofR19 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 l-R13 monitors is zero. See Section 1.2.2.Page 96 of 155 I I I I I I I I I I I I I I I I I I I 0 Cn 0 Lnd D z 01 01-.J U-.D1 Salem ODCM Rev. 24 I*Io I~z ,I.CV)0 Il, 14 U)rý'v 0 I-Ii/17-0 Table 1-1.2: Parameters for Liquid Alarm Setpoint Determinations
-Unit 2 Parameter Actual Default Units Value Value Comments MPCe Calculated 4.81E-06* I4Ci/ml Calculated for each batch to be released.MPC 1-131 3.OE-07 N/A lICi/ml 1-131 MPC conservatively used for SG blowdown, Service Water and Chemical Waste Basin monitor setpoints. C, Measured N/A jtCi/rnl Taken from gamma spectral analysis of liquid effluent.MPCi as determined N/A uCi/mi 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 ýtCi/ml under Public Service Blueprint Document 2R19(A,B,C,D) 315734 2-R13(A and B)R37 CW as determined L.OE+05 gpm Circulating Water System, single CW pump ***RR as determined 120 gpm Determined prior to release; release rate 2-RI8 can be adjusted for ODCM CONTROL Compliance 250 2-R19 Steam Generator Blowdown rate per Generator 1.OE+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 gtCi/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 I Circulators are out of service, the CW flow for 2-R13 monitors is zero. See Section 1.2.2.Page 97 of 155 Salem ODCM Rev. 24 TABLE 1-2: Site Related Ingestion Dose Commitment Factor, A.o (Fish And Invertebrate Consumption)(mremn/lr per ýCi/ml).H-3 282E-l 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+1 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 INi-65 2.02E+2 2.62E+1 1.20E+1 -6.65E+2 Cu-64 -2.14E+2 1.01E+2 5.40E+2 -11.83+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+1 4.26E+2 -9.85E+1 I 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 I U I I I I I I I I I I I I I I I Z<U-)-z 0 z Cr)F--z" 0 Cr W LU 0 z>-L, 0 r-V)L-J 0 0, LJ D Br-83 Br-84 7.25E-2 1.04E-1 9.39E-2 7.37E-7 Br-85 3.86E-3 -FRb-86 6.24E+2 2.91E+2 --1.23E+2 Rb-88 1.79E÷O 9.49E-1 --2.47E-I 1 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+1 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 -i2.37E+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 I 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 -.lIE+O 3.50E+3 LMo-99 -1.28E+2 2.43E+1 -2.89E+2 2.96E+2 10Tc-99m 3.66E-2 4.66E-1 -5.56E-1 1.79E-2 2.17E+1 LTc-101 1.33E-2 1.92E-2 1.88E-1 -3.46E-1 9.81E-3 5.77E-14 Page 98 of 155 I I Salem ODCM Rev. 24 TABLE 1-2 (cont'd)Site Related Ingestion Dose Commitment Factor, Aio (Fish And Invertebrate Consumption)(mrem/hr per jtCi/ml)Ru-103 1.07E+2 4.60E+1 4.07E+2 1.25E+4 Ru-105 8.89E+O -3.51E+O l.15E+2 -5.44E+3 Ru-106 1.59E+3 2.01E+2 3.06E+3 -1.03E+5 Rh-103m --Rh-106 -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+0 3.06E-1 1.19E+l 7.51E+3 Sb-124 2.77E+2 5.23E+0 1.1OE+2 6.71E-1 2.15E+2 7.86E+3 II Sb-125 1.77E+2 1.98E+0 4.21E+1 1.80E-1 1.36E+2 1.95E+3 Sb-126 1.14E+2 2.31E+O 4.IOE+l 6.96E-1 6.97E+l 9.29E+3 Te-125m 2.17E+2 7.86E+1 2.91E+1 6.52E+l 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+l -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+O 9.55E-1 6.19E-1 1.95E+O 1.07E+1 -1.92E+0 Te-131m 1.40E+2 6.85E+1 5.71E+1 I1.08E+2 6;94E+2 -6.80E+3-" Te-131 1.59E+O 6.66E-1 5.03E-1 1.31E+0 6.99E+0 -2.26E-Te-132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 6.24E+3 I 1-130 3.96E+1 1.17E+2 4.61E+1 9.91E+3 L82E+2 -1.01E+2 i t-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 U 1-134 5.56E+O 1.51E+l 5.40E+O 2.62E+2 2;40E+1 -1.32E-2 1-135 2.32E+l 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 I Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 ID Cs-137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 i Cs-138 6.07E+0 '1.20E+1 5.94E+0 8.81E+0 8.70E-1 5.12E-5 Ba-139 7.85E+0 5.59E-3 2.30E-1 5.23E-3 3.17E-3 l.39E+1 Ba-140 1.64E+3 2.06E+0 1.08E+2 7.02E-1 1.18E+O 3.38E+3 II Ba-141 3.8 1EE+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 L.OOE-3 2.43E-18 La-140 57E+0 7.94E-1 2.10E-1 .... 5.83E+4 0 La-142 8.06E-2 3.67E-2 9.13E-3 -2.68E+2 Ce-141 3.43E+O 2.32E+0 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-I-4 Ce-144 1.79E+2 7.47E+1 9.59E+O -4.43E+t -6.04E+4 Pr-143 5.79E+0 2.32E+O 2.87E-1 -1.34E+O -2.54E+4 0 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+O -2.20E+4 W-187 9.16E+O 7.66E+0 2.68E+O 2.51E+3/ ~ N~-239 3.53E-2 3.47E-3 1.91E-3 1.08E-2 7.11E+2 1g 9 ry Page 99 of 155 I c Salem ODCM Rev. 24 0 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 3.0E+03 3.OE+04 I Cr 4.OE+02 2.OE+03[ Mn 5.5E+02 4.OE+02 Fe 3.0E+03 2.0E+04 Co 1.OE+02 L.OE+03* Ni 1.0E+02 2.5E+02 1 Cu 6.7E+02 1.7E+03 Zn 2.0E+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 2.0E+02 8.OE+01 Nb 3.OE+04 _.OE+02 Mo 1.0E+01 1.OE+01 Tc _1.0E+01 5.0E+01 Ru 3.0E+00 I.OE+03 Rh L.OE+01 -2.OE+03 Ag 3.3E+03 3.3E+03 Sb 4.0E+01 5.4E+00 Te 1.E+01 1.OE+02 I __1.OE+01 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 _ 1.0E+03 SW 3.OE+01 3.OE+01 Np 1.0E+01 1.0E+01
J I I I I I I I I I I I I I I I I I I I (/)0 Z (I--z" C)7-J 0 U-ci, LJ w ck-{0 D D2* Values in this table are taken from Regulatory Guide 1.1 09 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.Page 100 of 155 Salem ODCM Rev. 24 FIGURE 2-1: SALEM VENTILATION EXHAUST SYSTEMS AND EFFLUENT MONITOR INTERFACES Simplified One Line I*TO ATMOSPHERE I6 L.)1<(V)F 03 I!w>U-0>-.w:D Page 101 of 155 Salem ODCM Rev. 24 FIGURE 2-2: GASEOUS RADIOACTIVE WASTE DISPOSAL SYSTEM Simplified One Line S PLANT VENT WA COM]HOLD-UP TANKS RECYCLE EVAPORATORj SPENT RESIN O STORAGE w REACTOR 0D COOLANT 0-r-<1 ~NITROGEN DRITAK-~SUPPLY SGAS DECAY TANKS>0¢U-LGAS AN n¢-J U W Page 102 of 155 r, W 0~
Salem ODCM Rev. 24 Table 2-1: Dose Factors For Noble Gases'p 0 I.)ro I_°:>-(, 0 I.LJA MC/Total Body Dose Factor Ki Skin Dose Factor Li Gamma Air Dose Factor Mi Beta Air Dose Factor Ni MM~3*Radionuclide LtCi/m3) .tCi/m3) _UCi/m3) 4Ci/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-131m 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 Page 103 of 155 Salem ODCM Rev. 24 a Table 2-2.1: Parameters for Gaseous Alarm Setpoint Determinations -Unit I 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.CQ 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 PLCi/m 3 Mi nuclide specific N/A mrem/yr per Values from Table 2-1.Ci/m 3 Sensitivities as determined N/A cpm per Monitor sensitivities are I-R41 gCi/r 3 or controlled under Public l-RI2A cpm per Service Blueprint Document_.iCi/cc (PSBP) 315733 Setpoint calculated N/A cpm or Monitor setpoints are 1 -R41D controlled under Public I-R12A ** iCi/sec Service Blueprint Document (PSBP) 315733 0 0 LLJ z 0:D 0 z z"©)-tml 2..0 0,-0 w, w~_0 I I I I I I I I I I I I I I I I I I I**Automatic Isolation function is applicable in all MODES except MODE 6 Page 104 of 155 Salem ODCM Rev. 24 I.I I I I I Ie 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'/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 pCi/cm 3 Taken from gamma spectral analysis of gaseous effluent K, Nuclide N/A mrem/yr per Values from Table 2-1 specific LCi/m3 Nuclide N/A mrem/yr per Values from Table 2-1 specific ýICi/m 3 M, Nuclide N/A mrem/yr per Values from Table 2-1 specific pCi/m 3 Sensitivities as N/A cpm per Monitor sensitivities are 2-R41 determined P.Ci/m 3 or controlled under Public Service 2-RI2A cpm per Blueprint Document (PSBP)gtCi/cc 315734 Setpoint Calculated N/A cpm or Monitor setpoints are controlled 2-R41D gCi/sec under Public Service Blueprint 2-R12A ** Document (PSBP) 315734**Automatic Isolation function is applicable in all MODES except MODE 6 Page 105 of 155 0 Ey LLJ U-0 U)LUi D) Salem ODCM Rev. 24 Table 2-3: Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations
ODCM CONTROL Location Pathway(s)
Controlling Age Group Atmospheric Dispersion X/Q D/Q (sec/m3) (1/m2)** Location and distance are determined from the performance of the annual land use census as 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 3.11.2.2 3.11.2.3 site boundary (0.83 mile, N)residence/dairy**. (4.9 miles, W)2. IE-10 CD C-)z.0 0 z" U-w>--tml w_..D* 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-I I I I I I I I I I I I I I I I I I I** Location and distance are determnined from the performance of the annual land use census as required by ODCM CONTROL 3.12.2.Page 106 of 155 Salem ODCM Rev. 24 I.a Table 2-4: Pathway Dose Factors -Atmospheric Releases R(io), Inhalation Pathway Dose Factors -ADULT (mrem/yr per .tCi/m3)I H-3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 I.V-)I!I I 0 me I n 17I ID 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- -- I 864E+4 5.01E+4 Cr-51 I 5.95E+1 2.28E+1 1.44E+4 3.32E+3 I 1.OOE+2 Mn-54 -3.96E+4 I 9.84E+3 1.40E+6 7.74E+4i 6.30E+3 Fe-55 2.46E+4 1.70E+4 -_ -7.21E+4 6.03E+3 i3.94E+3 Fe-59 1.18E+4 i2.78E+4 _____ 1.02E+6 1.88E+5 1.06E+4 Co-57 6.92E+2.... " 3.70E+5 3.14E+4 16.71E+2 Co-58 I1.58E+3 ___ _ 9.28E+5 1.06E+5 2.07E+3 Co-60 1. 1_15E+4 -__- 5.97E+6 2.85E+5 1.48E+4 Ni-63 4.32E+5 I3.14E+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 _ _ --i 9.60E+6 7.22E+5 6.1OE+6 Y-91 4.62E+5 -1.70E+6 3.85E+5 1.24E+4 1 Zr-95 1.07E+5 3.44E+4 -5.42E+4 1.77E+6 1.50E+5 12.33E÷4 Nb-95 i 1.41E+4 7.82E+3 -__ 7.74E+3 i 5.05E+5 1.04E+5 4.21E+3 Ru-103 1.53E+3 -_5.83E+3 i5.05E+5 I 1.10E+5 6.58E+2 Ru-106 6.91E+4 _ -_ _ 1.34E+5 9.36E+6 9.12E+5 8.72E+3 Ag-1r0m 1.08E+4 1.OOE+4 I_- 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 j 1.24E+4 Sb-125 T5.34E+4 5.95E+2 5.40E+1 I 1.74E+6 1.01E+5 1.26E+4 Te-125m 2 1 3 .05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127r I 1.26E--4 5.77E+3 .29E+3 4.58E+4 i9.60E+5 1.50E+5 11.57E+3 TeI129mi 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 I 1.19E+7 6.13E+4 -6.28E+3 2.05E+4 1-132 1.16E+3 3.26E+3 i 1.14E+5 5.18E+3 4.06E+2 1.16E+3 1-133 i8.64E+3 1.48E+4 2.15E+6 2.58E+4 -_ 8.88E+3 4.52E+3 1-134 1.73E+3 2.98E+4 2.75E+3 1 1.01E+O 6.ISE+2 1-135 2.68E+3 r 6.98E+3 4 4.E+5 1.11E+4 5_. ,.25E+3 2.57E+3 Cs-134 i3.73E+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+E+42034 .17E+ .10E+5 Cs-137 4.78E+5 i 6.21E+5 __- 2.22E+5 7.52E+4 i8.40E+3 4.28E+5 Ba-140 3.90E+4 4.90E+1 __- 1.67E+1 i.27E+6 i2.18E+5 2.57E+3 Ce-141 i 1.99E+4 i1.35E+4 -I6.26E+3 3.62E+5 I 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 19.36E+3 3.75E+3 -2.16E+3 2.81E+5 2.OOE+5 4.64E+2 Nd-1471 5.27E+3 6.1OE+3 3.56E+3 2.2 1.73E+5 3.65+2 Page 107 of 155 Salem ODCM Rev. 24 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Inhalation Pathway Dose Factors -TEENAGER (mrem/yr per .tCi/m3)I-I --TT 0 (-5")0'r" ,D 0 0 n (---z" U)W 03 Uv-(Y w.-J 0~_0v" 0..w'v w 03 1-1-3 -j " 1.2I+3 1.27TE+3 1.27EJ+3 1.27E+3 I 1.27E+3 1.27E+3 IC-14 2.60E+4 4.87E+3 I 4.87E+3 4.87E+3 .4.87E+3 L4.87E+3 4.87E+3 I P-32 I.89E+6 1. 1 OE+-51_-____ __ 9.28E+4 '7.16E+4 Cr-51 --7.50E+1I 3.07E+1 2.1OE+4 3.00E+3 1.35E+2[Mn-54 -5.11E+4 -11.27E+4 1.98E+6 6.68E+4 I8.40E+3 Fe-55 3.34E+4 2.38E+4 --1.24E+5 6.39E+3 i 5.54E+3 F-59 1.59E+4 3.70E+4 -._ -1.53E+6 1.78E+5 I1.43E+4 Co-57 .6.92E+2 t 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 I -F 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 1.344E+5 -8.64E+4 1.24E+6 4.66E+4 1 6.24E+4*,Rb-86 1.90E+51 --1.77E+4 8.40E+4 Sr-89 4.34E+5 --_2.42E+6 3.71E+5 1.25E+4 Sr-90 1-.08E8 -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+41 r-9 6.74E- -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 -I -7.43E+3 7.83E+5 i1.09E+5 8.96E+2 Ru- 106 9.84E+4 -! -1.90E+5 1.61E+7 9.60E+5 1.24E+4 Ag-110m 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 -J 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 ITe-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 1I-131- 3.54E+4 4.91E+4 1.46E+7 8.40E+4 -6.49E+3 2.64E+4 A-1 3 2 1.59E+3 4.38E+3 1.51E+5 6.92E+3 -1.27E+3 1.58E+3 11-133 1.22E+4 2.05E+4 2.92E+6 3.59E+4 -1.03E+4 6.22E+3[I-134 8.88E+2 _ 2.32E+3 3.95E+4 3.66E+3 -.. 2.04E+1 8.40E+2-13 3.70E+3 9.44E+3 6.2 1E+5 1.49E+4 -6.95E+3 3.49E+3 Cs-134 T 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 6370E+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 j6.t4E+5 i 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___________ ____ ___ __1;34E__4 4.83E+ 2.4+ 66E+Pr-143 1 34E+4 5.31E+3 -3.09E+3 __4.83E+5 2.14E+5 6.62E+2 Nd-147 7:86E+3j 8.56E+3 I 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 I I Page 108 of 155 Salem ODCM Rev. 24 i1 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Inhalation Pathway Dose Factors -CHILD (mrem/yr per j.LCi/m3)H-3 -1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 1.12E+3 1.12E+3 I 1.12E+3 1.12E+3............. .."l f 6.73E+3 6.73E+3 I 6.73E+3 6.73E+3 U U D z V-)0 w-P-32 .2.60E+6 1.14E+5 --" 1 4.22E+4 9.88E+4 Cr_-51 __ -!_ _ _ _ _ _ _ 8+Cr-Si 8.55E+1 i2.43E+1 1 1.70E+4 1.08E+3 11.54E+2 Mn-54 -4.29E+4 I -__ 1.OOE+4 1.58E+6 2.29E+4 9.513+3 Fe-55 4.74E+4 2.52E+4 i- -I 1.11E+5 2.87E+3 7.77E+3 Fe-59 I 2.073+4 3.343+4 -I -I 1.27E+6 7.07E+4 I 1.67E+4 Co-57 5..9.3+2 -___- 5.07E+5 I.32E+4 I 1.07E+3 Co-58 i _ 1.77E+3 -_ _ I 111E+6 3.44E+4 3.16E+3 Co-60 1.3 1E+4 1 _ _ 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 1.13E+5 -I 7.14E+4 9,95E+5 i 1.63E+4 7.03E+4 Rb-86 __"__ 1.98E+5 -_____ 7.99E+3 1.14E+5 Sr-89 I 5.99E+5 i --2.16E+6 1.67E+5 1.723+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 I 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 1.433+7 4.29E+5 1.69E+4 Ag-ll0m r 1.69E+4 1.14E+4 -2.12E+4 1 5.48E+6 1.00E+5 9.14E+3 Sb-124 T5.74E+4 7.40E+2 I 1.26E+2 3.24E+6 1.64E+5 2.00E+4 Sb-125 9.84E+4 7.59E+2 9.10E+1 -2.32E+6 4.03E+4 2.07E+4 Te-125m i6.73E+3 2.33E+3 1.92E+3 4.77E+5 3.38E+4 9.1 4E+2 Te-127m 2.49E+4 8.55E+3 i6.07E+3 , 6.36E+4 1.48E+6 7.14E+4 3.02E+3 Te-129m 1.92E+4 6.85E+3 6.33E+3 15.03E+4 1 176E+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 1.94E+5 6.25E+3 _, _i 3.22E+3 1.88E+3 1-133 1.66E+4 2.03E+4 1 3.85E+6 1 3.38E+4 I 5.48E+3 7.70E+3 1-134 1.17E+3 2.16E+3 1 5.07E+4 I 3.30E+3 1 9.55E+2 9.95E+2 1-135 4.92E+3 8.73E+3 i7.92E+5 1 1.34E+4 _ _ 4.44E+3 4.14E+3 Cs-134 6.5 1E+5 1.01E+6 I 1 3.30E+5 -1.21E+5 3.85E+3 2.25E+5*Cs-136 6.51E+4 1.71E+5 -19.55E+4 1.45E+4 4.1 8 E+3 1. 1.6E+5 Cs-137 9.07E+5 8.25E+5 I 2.82E+5 1.04E+5 3.62E+3 1.28E+5 Ba-140 1 7.40E+4 6.48E+1 -2.11E+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 T 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 -1 3.00E+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 Page 109 of 155 Salem ODCM Rev. 24 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Inhalation Pathway Dose Factors -INFANT (mrem/yr per U)CD z-)-z 0 UD Z-U1-0 z>-j 0 0 n V, 02 z U-U-I 0 U--Ji 0: Ld 0./H-3 6.47E47E+2 .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 I_5.31E+3 I 5.31E+3 P-32 1 2.03E+6 1.12E+5 ---1i .61E+4 7.74E+4 Cr-51 --5.75E+1 1.32E+1 i1.28E+4 3.57E+2 8.95E+1J... ......Mn-54 ... -- ...... ---- Sg9E+3-<Lr.0E+6 j7.06E+3 I4.98E+3 Fe-55 1.97E+4 1.17E+4 --69E+4 1.09E+3 3.33E+3 Fe-59 I1.36E+4 2.35E+4 I 1 il.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 1.1 1E+4 1.82E+3 Co-60 8.02E+3 4.5 1El'6 1. 18E+4j Ni-63 3.39E+5 2.04E+4 2i 2.09E+5 2.42E+3. 1.16E+4 I 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 i 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 1.1SE+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 I2.02E+3 _. -_ 4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru--106 8.68E+4 1_-____ 1.07E+5 1.16E+7 1.64E+5 l.09E+4 Ag-llrn 9.98E+3 7.22E+3 _ _- _ i1.09E+4 13.67E+6 3.30E+4 5.OOE+Sb-124 3.79E+4 5.56E+2 I1.0E+2 -2.65E+6 5.91E+4 1.20E+4 Sb-125 5.17E+4 4.77E+2 6.23E+1 -1.64E+6 I 1.47E+4 1.09E+4 Te-125m 4.76E+3 1.99E+3 1.62E+3 -4.47E+5 I.29E+4 i 6.58E+2 Te-127m .1.67E+4 6.90E+3 i4.87E+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-E+6 6.90E+4 ]2.23E+3 1-131 3.79E+4 4.44E+4 i1.48E+7 1 5.18E+4 -.06E+3 i l.96E+4 1-132, 1.69E+3 3.54E+3 1.69E+5 3.95E+5 T -1190E+3 1.26E+3 1-133 1.32E+4 1.92E+4 3.56E+6 2.24E+4 I- _ 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 11-135 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 i43E+3 5.29E+4 Cs-137 5.49E+5 I6.12E+5 1.72E+5 7.13E+4 1.33E+3 4.55E+4 Ba-140 5.60E+4 560E+1 1.34E+1 1.60E+6 3.84E+4 2.90E+3 f Ce-141 2.77E+4 I167E+4 -5.25E+3 5.17E+5 2.16E+4 1.99E+3 I Ce-144 3.19E+6 1.21E+6 5.38E+5 9.84E+6 1.48E+5 1.76E+5 Pr-143 I1.40E+4 5.24E+3 i 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 1 5.OOE+2 I I I I I I I I i I I I I I I I I I I Page 110 of 155 Salem ODCM Rev. 24 I*Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors -ADULT (mrem/yr per 4Ci/m3) for H-3 and C-14 (m2
mrem/yr per ,Ci/sec) for others H-3 7.63E+2 7.63E+2 I 7.63E+2 7.63E+2 7.63E+2 I 7.63E+2l)U-V.)0 V-Mw>-ry, 0 I!w 0 nt.(J)L..C-14 I 3.63E+5 I 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 __ I 1.71E+4 6.30_,+3 3.80E+4 7.20E+6 2.86E+4 Mn-54 -8.40E+6 2.50E6 +6 2.57E+7 _.60E+Fe-55 I2.51E+7 I _.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 i -1.28E+6 -- -j3.25E+7 2.13E+6 Co-58 __- 4.72E+6 --9.57E+7 1.06E+7 Co-60 1.- _ 1-64E+7 " --3.08E+8 _ 3,62E+7 N-63 6 6.73_E+9 4.66E+8 --9.73E+7 2.26E+8[h6 6.3+_________
______ 2.75E+9_ __.97E+9 Zn-65 1.37E+9 4.36E+9 2.92E+9 -197E+9 Rb-86 --2.59E+9 51 --5._+_1.21E+9 Sr-89 I 1.45E+9 3 -2.33E+8 4.161E+7 Sro0_ 4.68E+10 _ _- -1.35E+9 1.15E+10 Y-91 8.60E+3 4.73E+6 j 2.30E+2 Zr-95 9.46E+2 3.03E+2 -4.76E+2 I- 9.62E+5 2.05E+2 Nb-95 [8.25E+4 I 4.59E+4 -4.54E+4 -2.79E+8 2.47E+4 Ru-103 1.02E+3 -3.89E+3 -i.19E+5 4.39E+2 Ru-106 2.04E+4 --3.94E+4 -1.32E+6 2.58E+3_Ag-10m _ 5.83E+7 5.39E+7 j -1.06E+8 -2.20E+10 3.20E+7 Sb-124 2.57E+7 [4.86E+5 6.24E+4 -2.O0E+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 1 Te-127m I 4.58E+7 1.64E+7 1.17E+7 1.86E+8 -1.54E+8 5.58E+6 Te-129m i6.04E+7 2.25E+7 2.08E+7 2.52E+8 -3.04E+8 9.57E+6 1-131 [ 2.96E+8 J 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 1-135 1.39E+4 3.63E+4 2.40E+6 5.83E+4 -4.10E+4 1.34E+4 Cs-134 5.65E+9 i 1.34E+10 -4.35E+9 1.44E+9 2.35E+8 1.10E+10 Cs-136 2.61E+8 j 1.03E+9 -5.74E+8 7.87E+7 1.17E+8 7.42E+8 Cs-137 7.38E+9 I1.O1IE+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 13.27E+3 -1.52E+3 -1.25E+7 3.71E+2 Ce-144 3.58E+5 1.50E+5 8.87E+4 -1.21E+8 i 1.92E+4 Pr-143 1.59E+2 i 6.37E+1 3.68E+1 6.96E+5
7.88E+O Nd-147 9.42E+1I 1.09E+2 6.37E+1 5.23E+5 J 6.52E+O Page II1 of t55 Salem ODCM Rev. 24 S Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors -TEENAGER (mrem/yr per p.Ci/m3) for H-3 and C-14 (m2

mrem/yr per .Ci/sec) for others I I I I H-3 i 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 I Ld 0 z-)z Cu W L<UD z"¢,,-02 0~l~(j>L-U LU Ui, 1..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 -I --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 j 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 I Co-58 -7.95E+6 --.1.E+8 1.83E+7 Co-60, -_ 2.78E+7 -" I 3.62E+8 16.26E+7 Ni-63 I 1.18E+10 I8.35E+8 I --,1.33E+8 "4.01E+8 Zn-65 2.11E+9 7.31E+9 -4.68E+9 3.1OE+9 3.4 E+9 Rb-86 I4.73 9 7.0E+8 2.22E+9 Sr-89 2.67E+9 ---3.18E+8 7.66E+7 1 Sr-90 -9.92E+7 I --9.60E+6 7.22E+5 6.1OE+6 Y-91 I 1.58E+4 -6.48E+6 4.24E+2 i Zr-95 I1.65E+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 i 1.81E+3 T -6.40E+3 -1.52E+5 7.75E+2 Ru-106 3.75E+4 -.- 7.23E+4 -1.80E+6 4.73E+3 l 99.11E+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 i 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-127mr 8.44E+7 2.99E+7 2.01E+7 3.42E+8 -2.1OE+8 1.OOE+7 Te-129m , 1.1IE+8 I 4. 10OE+7 3.57E+7 4.62E+8 -4.15E+8 1.75E+7 1-131 5.38E+8 I 7.53E+8 2.20E+11 I 1.30E+9 -1.49E+8 J4.04E+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 I-i34 --____ --, --1434 1-135 2.47E+4 6.35E+4 4.08E+6 1.OOE+5 -7.03E+4 12.35E+4 Cs-134 19.81E+9 2.31E+10 -7.34E+9 2.80E+9 2.87E+8 j1.07E+10 i 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 I1.78E+10 -6.06E+9 2.35E+9 2.53E+8 6.20E+9 i 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 6.8 1EE+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 I 1.97E+2 _27. E+5 j1.18E+1 Page 112 of 155 I I Salem ODCM Rev. 24 I1 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors -CHILD (mrem/yr per p.Ci/m3) for H-3 and C-14 (m2
mrem/yr per tCilsec) for others H-3 'i 1.57E+3 I 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 I*V)0 C-)I 0 M U-0 U-LI_V-C-14 L1.65E+6 i 3.29E+5 3.29E+5 3.29ET5- 3.29E+5 3.29E+5 3.29E+5 P-32 __7.77 _ 3. E_-: 2.15E+9 03.0E+9 Cr-51 -I 5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 n5- 2.9E 7- 57E+6 .1.76E+7 5.58E+6 Fe-55 1.12E+8 1 5.93E+7 -_ 3.35E+7 1.1OE+7 I 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 I --1.21E+7 -I 7.08E+7 j 3.72E+7 Co-60 I -4.32E+7 2.39E+8 I 1.27E+8 Ni-63 I2.96E+1 1.59E+ 1.07E+8 1 1.01E+9 9 Zn-65' 4.13E+9 i1.10E+10
-6.94E+9 I 1 l.93E+9 6.85E+9 Rb-86 .-8.77E+9 I -5.64E+8 5.39E+9 Sr-89 6.62E+9 -_ 2.56E+8 1.89E+8 Sr-90 1.12E+11 -1 I I 1.51E+9 2.83E+10 Y-91 3.9184 5.21E+6 1.04E+3 Zr-95 3.84E+3 8.45E+2 1.21_E+3, 8.81E+5 7.52E+2 Nb-95 1.18E+5 1.24E+5 1.16E+5 ' 2.29E+8 8.84E+4 RU-103 i4.29E+3 --1.08E+4 1 1.11E+5 1.65E+3 Ru-106 l9.24E+4 --I1.25E+5 _ 1.44E+6 1.15E+42.09E+8 1.41E+8 .-2.63E+8 -I.68E+0 I.13E+8 Sb-124 1.09E+8 l141E+8 2.40E+5 -03E+7 Sb-61201.4+7 6.79E+-8 3 381E+7 Sb-125 8.70E+7 J1.41E+6 8.06E+4 -4.85E+7 2.08E+8 1.82E+7 Te-125m 7.38E+7 2.OOE+7 I2.07E+7 --7.12E+7 9.84E+6 Te-127mn 2.08E+8 I 5.60E+7 4.97E+7 5.93E+8 -1.68E+8 j2.47E+7 Te-_129m_ 2.72E+8 [7.61E+7 8.78E+7 8.OOE+8 -3.32E+8 1 4.23E+7 1-131 1.30E+9 1.3 1E+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+0 -1.48E+0 5.80E-1-133 .1.76E+7 2.18E+7 4.04E+9 3.63E+7 -8.77E+6 8 1-134 1 ----2+1 1 3 5 I 5.84E+4 i 1.05E+5 I 9.30E+6 1.61E+5 -8.OOE+4 4.97E+4 Cs-134 12.26E+10 3.71E+10 1 -1.15E+10 4.13E+9 2.OOE+8 7.83E+9 Cs-136 1.OOE+9 2.76E+9 I -1.47E+9 2.19E+8 j9.70E+7 1.79E+9 Cs-137 3.22E+10 3.09E+10 -I 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 2.19+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 -7.80E+5 3.59E+1 Nd-147 4.45E+2 3.60E+2 L J 1.98E+2 -5.71E+5, 2.79E+1 Page 113 of 155 N Salem ODCM Rev. 24 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors -INFANT (mremlyr per jiCi/m3) for H-3 and C-14 (m.2
mrem/yr per ý.+/-Ci/sec) for others H-3 I -2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 ,)W"7 0 C)z" V)D V-H-iy, 0 0 Z: 0 r)U-1_.J m _0.0./tad U-v 0" U-I/n C-14 i 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+1I1 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 872E+7 427E+7] I.E+7 2.33E+7 Fe-,59 2.25E+8 3.93E+8 -1.16E+8 i.88E+8 1.55E+8 Co-57 I 8.95E+6 --3.05E+7 1.46E+7 I Co-8 2.43E+7 I -6.05E+7 6.06E+7 Co-60 1 8.8 --E+7 2.1OE+8 2.08E+8 Ni-63 3.49E+1 0 2.16E+9 ---1.07E+8 1.21E+9 I Zn-65 5.55E+9 I 1.90E+10 I 9.23E+9 1.61E+10 8.78E+9.Rb-86 -2.22E+ 10 -5.69E+8 1.1OE+10 i Sr-89 1.26E+10 --2.59E+8 3 61E+8 Sr-90 1.22E+1I -t --1 1.52E+9 3[.0E+30 Y-91 _7_.33E+4
1. --.E95E+3 Zr-95 _ 6.83E+3 1.66E+3 -1.79E+3 -8.28E+5 .18E+3 Nb-95 i 5.93E+5 2.44E+5 -1.75E+5 -2.06E+8 1.4tE+5 Ru-103 8.69E+3 --1.81E+4 -1.06E+5 22.91E+37 Ru-106 1 .90E+5 i --2.25E+5 -1.44E+6 2.38E+4 SAg-llnm i 3.86E+8 1 2.82E+8 t 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 T 3.07E- 7 Te-125m L-.51E+8 I 5.04E+7 5.07E+7 --7.18E+7 2.04E+7 Te-127m [4.21E+8 1.40E+8T 1.22E+8 1.04E+9 -1.70E+8 15.10E E+7 Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 -3.34E+8I 8.62E+7 1-131 2.72E+9 i 3.21E+9 1.05E+12 3.75E+9 -1.15E+8 1.41E+9 1-132 1 .42E+0 289E+0 1.35E+2 3.22E+O -2
2.34E+0 1.03E+0-133 3.72E+77 5.41E+7 9.84E+9 6.36E+7 -9.16E+6 1.58E+7 1-134 --! 1.O1E-9 -I 1-135 1.21E+5 i 2.41E+5 2.16E+7 2.69E+5 -F8.74E+4 j 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 1.96E+9 5.77E+9 1 2.30E+9 4.70E+8 )8.76E+7 I 2.15E+9 Cs-137 I5.1-5E+10 6.02E+10 1 -1.62E+10 6:55E+9 1.88E+8 14.27E+9 Ba-140 2.41E+8 12.41E+5 -5.73E+4 1.48E+5 5.92E+7I 1.24E+7 C e-141 ........ ......C4.33E+4 1 2.64E+4 8.15E+3 -1.37E+7 111E+3 Ce-144 T 2.33E+6 I 9.52E+5 3.85E+5 -1.33E+8 1.30E+5 Pr-143 i 1.49E+3 5.59E+2 2.08E+2 -[7.89E+5 I 7.41E+1 Nd-147 i 8.82E+2 I 9.06E+2 3.49E+2 -T[5.74E+5
[5.55E+1 j I I I I I I I I I I I I I I I I I I I Page 114 of 155 Salem ODCM Rev. 24 I*Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Vegetation Pathway Dose Factors -ADULT (mrem/yr per for H-3 and C-14 (m2
mrem/yr per jtCi/sec) for others I.C)(IV)z" I..>U-0 al I°L n,I cv" H-3 -_ _2.26E+3 2.26E+3 2.26E+3 i2.26E+3 2.26E+3 2.26E+3 C-14 8.97E+5 i 1.79E+5 .71.79.7+5 1.795 1 79E 1.79E+5 P-32 1.40E+9 8.73E+7 -1.58+8 5.42E+7 Cr-51 -2.79E+4 1.03E+4 16.19E+4 1.17E+7 I 4.66E+4 Mn-54 -3.11 E+8 9.27E+7 -9.54E+8 5.94E+7 Fe-55 j 2.09E+8 I 1.45E+8 -i-8.06E+7 8.29E+7 3.37E+7 Fe-59 1.27E+8 j 2.99E+8 --8.35E+7 1 9.96E+8 1.14E+8 1 Co-57 -1.17E+7 -" -2.97E+8 1.95E+7 Co-58 i 3.09E+7- 6.26E+8 6.92E+7__o-60 i -1.67E+8 -. --i 3.14E+9 3.69E÷8 Ni-63 1.04E+10 7.21E+8 T- ---- 1.50E+8 3.49E+8 Zn-65 3.17E+8 1.01E+9 -6.75E+8 -6.36E+8 1 4.56E+8 Rb-86 -2.19E+8 ---4.32E+7 1 1.02E+8 Sr-89 9.96E+9 I --1.60E+9 12.86E+8 Sr-90 I6.05E+11
.... 1.75E+10 J 1.48E+10 Y-91 5.13E+6 ---2.82E+9 1.37E+5 Zr-95 1.1.192E+6 3.81E+5 5.9--+5-- __-__ 1.21E+9 12.58E+5 Nb-95 1.42E+5 7.91E+4 7.8 81E+4 1_4.80,+8 _ 4.25E+4 Ru-103 4.80E+6 1.83E+7 _ 5.61E+8 2.07E+6 Ru-106 1.93E+8 -F3.72E+8 _ 1.25E+10 2.44E+7 Ag-110m 1.06E+7 -9.76E+6 1 1 1.92E+7 3.9+9 5.80E.+6 Sb-124 1.04E+8 i1.96E+6 1 2.52E+5 -1 8.08E+7 2.95E+9 4.111E+7 Sb-125 1.36E+8 !1.2E+6 -.3-+ _ I 1.05E+8 I 50E+9 3.25E+7 Te-125m 9.66E+7 &3,50E+7 2.90E+7 3.93E+8 F 3.86E+8 1.29E+7 Te-127m 3.49E+8 7 1.25E+8 8.92E+7 1.42E+9 _ _ 1.17E÷9 4.26E+7 Te-129m r 2.55E+8 19.50E+7 8.75E+7 1.06E1+9 -1.281+9 4.03E+7 1-131 8.09E+7 J1.16E+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 1_ 2.89E+1 5.38E+1 1-133 i2.12E+6 3.69E+6 542E+8 6.442+6 _ 3.31E+6 1.12E+6 1-134 1 1.06E-4 j2.88E-4 5.00E-3 4.59E-4 1 _ 2.51E-7 1.03E-4 1-135 T4.08E+4 1.07E+5 7.04E+6 i 1.71E+5 I 1.21E+5 3.94E+4 Cs-134 I4.66E+9 1T.11E+10 -3.59E+9 1 1919+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 C s-137 6.36E+9 i8.70E+9 I -2.95E+9 9.81E+8 1.68E+8 5.70E-+9 Ba-140 1.29E+8 1 1.62E+5 f -5.49E+4 9.25E+4 2.65E+8 8.43E+6 Ce-141 I 1.96E+5 1.33E+5 5.08E+8 1.51E+4 Ce-144 3.29E+7 1.38E+7 -" 8.16E+6 i 1.11E+10 1.77E+6 Pr-14 3 6.34E+4 1 2.54E+4 -j 1.47E+4 _ _ 2.78E+8 3.14E+3 Nd-147 i 3.34E+4 3.86E+4 -J2.25E+4 !1.8512+8 2.311E+3 Page 115 of 155 Salem ODCM Rev. 24 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Vegetation Pathway Dose Factors -TEENAGER (mrem/yr per p.Ci/m3) for H-3 and C- 14 (m2.
mrem/yr per itCi/sec) for others Mh~Irml H-3 2.59E+3 I 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 0 CD r3 0 cjo 7 0 n U--(A3 z 0 L/I 0y tad 0o w w.0, Dr C-14 l.45E+6 2.91E+5 '2.91 E+5 12.91E+5 i2.91E+5 2.91E+5 2.91E+5 P-32 1.61E+9 9.96E+7 I --1.35E+8 !6.23E+7 Cr-5 i " -3.44E+4 1.36E+4 i8.85E+4 1.04E+7 6.20E+4 Mn-54 -4.52E+8 1.35E+8 -9.27E+8 8.97E+7 Fe-55 i3.25E+8 2.3 1E+8 1 -[1.46E+8 9.98E+7 5.38E+7 Fe-59 i 1.81E+8 i 4.22E+8 1 -1.33E+8 I 9.98E+8 1.63E+8 Co-57 1_ _ 1.79E+7 ---3.34E+8 3.OOE+7 Co-58 4.38E+7-, 6.04E+8 1.01E+8 Co-60 i 2.49E+8 --3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13E+9 --1.81E+8 I 5.45E+8 Zn-65 4.24E+8 1.47E+9 -I 9.41E+8 -6.23E+8 6.86E+8 Rb-86 -2.73E+8 _ _ -4.O5E+7 1.28E+8 Sr-89 1.51E+10 71-4 1.80E+9 4.33E+8 Sr-90 j7.51E+11
__ 1_ .2.1IE+10 1.85E+11 Y-91 7.87E+6 .-3.23E+9 2.11E+5 Zr-95 1.74E+6 5.49E+5 i -8.07E+5 1.27E+9 3.78E+5 Nb-95 I1.92E+5 1 .06E+5 1 -.03E+5 -4.55E+8 5.86E+4..Ru-103 I 6.87E+6 --2.42E+7 5.74E+8 2.94E+6 Ru-106 i3.09E+8 --5.97E+8 1.48E+10 3.90E+71 AAg-1lOm 1.52E+7 1.44E+7 i " 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 12.04E+5.j -1.88E+8 1.66E+9 OO5.E+7 Te-125m 1.48E+8 1 5.34E+7 4.14E+7 j _ -4.37E+8 1.98E+7 Te-127m 5.51E+8 }1.96E+8 1.31E+8 2.24E+9 1 -1.37E+9 6.56E+7 Te-129m 3.67E+8 J1.36E+8 1..18E+8 1.54E+9 -1.38E+9 5.81E+7 1-131 J7.70E+7 _ 1.08E+8 f 3.t4E+10 I 1.85E+8 -2.13E+7 5.79E+7 1-132 I 5.18E+1 1.36E+2 4.57E+3 12.14E+2 -5.91E+1 4.87E+ I 1-133 1 1.97E+6 13.34E+6 4.66E+8 5.86E+6 --2.53E+6 1.02E+6 1-134 I 9.59E-5 2.54E-4 4.24E-3 4.01E-4 I -3.35E-6 t9.13E-5 1-135 i 3.68E+4 9.48E+4 6.1 E+6 .1.50E+5 -1.05E+5 3.52E+4 Cs-134 I 7.09E+9 1.67E+10 -5.30E+9 1 2.02E+9 2.08E+8 7.74E+9 Cs-136 i 4.29E+7 1.69E+8 I 9.19E+7 1.45E+7 1i.36E+7 1. 13E+8 Cs-137 I1.O1E+10 1.35E+10 4.59E+9 i 1.78E+9 1.92E+8 4.69E+9 Ba-140 1.38E+8 1.69E+5 I 5.75E+4 i 1.14E+5 2.13E+8 8.91E+6 Ce-141 2.82E+5 1.88E+5 -i 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 I Pr-143 7.12E+4 2.84E+4 --1.65E+4 2.34E_8_ 3.55EI 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 I I Page 116 of 155 Salem ODCM Rev. 24 i1 Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Vegetation Pathway Dose Factors -CHILD (mrem/yr per pCi/m3) for H-3 and C- 14 (m2
mrem/yr per GCi/sec) for others I.)rA Iz" LII C-)LII I,.w 14 0 d-i, H-3 1 i4.01E+3 4. 01 E+3 4.01E+3 14.01E+3 4.01E+3 4.01E+3 EC-:14: !3.50E+6 7.01E+5 7. 01 E+5 17.01E+5 7.01E+5 7.01E+5 7.01E+5 P-32 1 3.37E+9 1.58E+8, -9.30E+7 1.30E+8 Cr-51 I 6,54E+4 1.9+ 1. 19E+5 6.25E+6 1. 18E+5 Mn-54 i -_ 6.61E+8 I1.85E+81
-5.55E+8 1.76E+8 Fe-55 8.OOE+8 1 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 i 2.99E+7 -2.45E+8 6.04E+7 Co-58 f 6.47E+7 --3.77E+8 1.98E-+8_Co-60 i- I3.78E+8 r T. 2.1OE+9 1.12E+9 Ni-63 3.95E+10 2.11E+9 1 -1.42E+8 1.34E+9 Zn-65 8.12E+8 1 2.16E+9 -.1.36E+9 -3.80E+8 1.35E+9-4.52E+8 --- 2.91E+7 2.78E+8 Sr-89 3.59E+10 -.T --1.39E+9 1.03E+9 Sr-90 1.24E+12 --+ -1.67E+10 3.l5E+li Y-91 1 87E+7 --2.49E+9 5.01E+5 Zr-95 1 3.90E+6 8.58E+5 1.23E+6 .- 95E+8 7.64E+5 b-5 3 .90E+5 8 .59E+5 t-ý-95 !4. 1OE+5 1.59E+5 1.50E+5 j -2.95E+8 I.14E+5 Ru-103 1.55E+7 I -.3.89E+7 j -3.99E+8 5.94E+6 Ru-106 7.45E+8 -I -I1.O1E+9 -1.16E+10 9.30E+7 Ag-ll0m 3.22E+7 2.17E+7 -_4.05E+7 -2.58E+9 1.74E+7 Sb-124 3.52E+8 14.57E+6 7.78E+5 -1.96E+8 2.20E+9 1.23E+8 Sb-125 4.99E+8 j 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 I 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 1i.44E+8 4.76E+10 2.36E+8 L 1.28E+7 8.18E+7 1-132 9.20E+ I 1.69E+2 I 7.84E+3 2.59E+2 I 1.99E+2 7.77E+1 1-133 1 3.59E+6 4.44E+6 8.25E+8 7.40E+6 1.79E+6 1.68E+6 1-134 _ _1.70E-4 _ 3._6E-4' 7.28E-3 4.84E-4 -2.10E-4 1.46E-4 1-135 i6.54E+4 1 1.18E+5 1.04E+7 1.81E+5 -8.98E+4 5.57E+4 Cs-134 1.60E+10 2.63E+1O 8.14E+9 2.92E+9 1.42E+8 5.54E+9 Cs-136 8.06E+7 I 2.22E+8 1.18E+8 1.76E+7 7.79E+6 1.43E1+8 Cs-137 I2.39E+10 I 2.29E+1O0 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 I 1.27E+8 3.98E+7 -2.21E+7 1.04E+10 6.78E+6 Pr-143 I 1.48E+5 4.46E+4 -2.41E+4 -1.60E+8 7.37E+3 Nd-147 7.16E+4 I 5.80E+4 3.18E+4 -9.18E+7 4.49E+3 Page 117 of 155 Salem ODCM Rev. 24 I Table 2-4 (cont'd)Pathway Dose Factors -Atmospheric Releases R(io), Ground Plane Pathway Dose Factors (m2
nlreirnyr per iiCi/sec)Nuclide Any Organ H-3 C-14 P-32 Cr-5I 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 2.001E7 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 I U)W CD z r U)QD V)z 0 V)Of F--z 0.-J n Ld 0r U)U-U-)D I I I I I I I I I I I I I I I I I I I Page 118 of 155 I I I.I I I I I Io Vi)C.)ini U-0 V-0 t.J Salem ODCM Rev. 24 APPENDIX A Evaluation of Default Parameters for Liquid Effluents Page 119 of 155 I Salem ODCM Rev. 24 APPENDIX A: Evaluation of Default Parameters for Liquid Effluents U 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: ZC0 (gamma) I MPC,, I MPe= -~ (gamma)MPG* where: ,, MPCe = an effective MPC value for a mixture of gamma emitting radionuclides (.LCi/ml)ZD C = concentration of radionuclide i in the mixture zI< MPC, = the 10 CFR 20, Appendix B, Table II, Column 2 MPC value for radionuclide i o (Appendix F) (ltCi/ml)z< The equation for determining.the liquid effluent setpoints (Section 1.2.1, equation 1.2) is based D 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 MIPCe value of 6.05E-06 pCi/ml for Unit 1 and 4.81E-06 ý+/-Ci/ml for Unit 2 as typical of liquid radwaste z" discharges. 0_z I>~I L_U-0~I>-o:2 0 L"Page 120 of 155..i nI Salem ODCM Rev. 24 I*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 (ýICi/ml) Activity (ptCi/ml) Activity / MPC H-3 3E-3 5.2E-1 173.3 Fe-55 8E-4 2.5E-3 3.1 Sr-89 3E-6 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*Non-Gamma Factor =Correction Factor =185.5/800 =1 -0.25 =0.23 (Rounded up to 0.25)0.75>LJ>-L~_Ln C//0 n~a 0Z I°J el.r3 L..d C. Default setpoint determination: Using the information and parameters described above a default setpoint can be calculated for Unit I and 2 liquid radwaste disposal process radiation monitors (R18).Using these values to calculate the default RI 8 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).Page 121 of 155 I Salem ODCM Rev. 24 Table A-I: Calculation of Effective MPC -Unit 1 I Activity Released (Ci)Nuclide MPC* 1993 1994 1998 (MCI) CURIES CURIES CURIES BE-7 2.OOE-03 8.88E-04 ND ND.NA-24 3.OOE-05 6.68E-04 1.62E-04 1.OOE-04 CR-5I 2.OOE-03 5.38E-03 2.02E-03 ND MN-54 .OOE-04 3.52E-02 1.37E-02 7.16E-04 MN-56 1.OOE-04 ND ND O.OOE+00 I FE-59 5.OOE-05 4.76E-04 4.84E-03 ND CO-57 4.OOE-04 1.03E-02 3.1OE-03 1.78E-05 CO-58 9.OOE-05 1.71E+00 6.47E-01 3.39E-02 I CO-60 3.OOE-05 3.04E-01 1.1OE-0I 2.42E-02 ZR-95 6.OOE-05 3.29E-03 7.13E-04 ND NB-95 1.OOE-04 5.78E-03 1.28E-03 ND NB-97 9.OOE-04 1.27E-03 1.07E-03 4.90E-05 TC-99M 3.OOE-03 2.66E-04 ND ND SR-89 3.OOE-06 ND ND 2.18E-04 n SR-92 6.OOE-05 ND 7.3.2E-06 ND MO-99 4.OOE-05 1.76E-04 1.76E-04 ND AG-110m 3.OOE-05 1.19E-02 1.1 OE-02 6.58E-05 SN-113 8.OOE-05 7.88E-05 4.9 IE-05 ND SB-122 3.OOE-05 1.21 E-03 5.35E-04 :1. 12E-03 SB-124 2.OOE-05 2.08E-02 1.75E-02 1.73E-02 SB-125 1.OOE-04 9.04E-02 8.23E-02 3.56E-02 SB-126 3.OOE-06 ND 6.18E-05 2.23E-04 0 1-131 3.00E-07 1.27E-01 1.82E-02 2.32E-03 z 1-133 1.OOE-06 2.16E-03 1.88E-04 8.32E-06 1-134 2.OOE-05 ND 3.63E-04 ND CE-141 9.OOE-05 ND 4.24E-05 ND Z CE-143 4.OOE-05 5.42E-05 ND ND CS-134 9.OOE-06 3.54E-01 6.46E-01 2.49E-02 D CS-136 6.00E-05 3.61E-03 1.59E-03 ND CS-137 2.00E-05 4.53E-01 8.54E-01 7.51E-02 CS-138 3.OOE-06 4.15E-06 1.35E-04 ND z BA-140. 2.OOE-05 ND 8.62E-05 ND 0 LA-I 40 2.OOE-05 2.12E-04 1.86E-04 ND> RU-105 1.OOE-04 2.2 IE-04 1.35E-04 ND W-cx RU-106 1.OOE-05 ND 1.03E-03 ND 0 ZN-65 I.OOE-04 6.72E-04 ND ND Total Ci Gamma 3.14E+00 2.42E+00 2.16E-01 cv-I ry MPCe (gCi/ml) 6.05E-06 1.28E-05 1.28E-05 0 ,*MPC value for unrestricted area from 10 CFR 20, Appendix B, Table II, Column 2.wI_** ND -not detected 0~Page 122 of 155 cx LO:Du I Salem ODCM Rev. 24 Table A-2: Calculation of Effective MPC -Unit 2 Activity Released (Ci)Nuclide MPC* 1993 1994 1998 (gCi/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 1.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 CO-58 9.OOE-05 1.75E+00 6.60E-0 l 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 NB-95 L.OOE-04 3.97E-03 .11E-03 ND NB-97 9.OOE-04 1.46E-03 1.I0E-03 4.22E-05 TC-99M 3.OOE-03 3.77E-04 ND 2.35E-06 SR-89 3.OOE-06 ND ND 2.7 IE-04 SR-92 6.OOE-05 ND 1.43E-05 ND MO-99 4.OOE-05 ND ND ND AG-1 10m 3.OOE-05 1.03E-02 1.34E-02 ND SN-113 8.OOE-05 7.45E-05 ND ND SB-122 3.OOE-05 1.20E-03 ND 6.37E-04 SB-124 2.OOE-05 3.77E-02 9.82E-03 1.44E-02 Cn SB-125 1.OOE-04 1.35E-01 6.03E-02 1.88E-02 C 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 r 1-132 8.OOE-06 8.72E-05 ND t.68E-04 1-134 2.OOE-05 2.39E-04 1.85E-04 ND< CE-141 9.OOE-05 ND 2.87E-05 ND Co 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 (I CS-137 2.OOE-05 5.70E-01 8.54E-01 7.97E-02 CS-138 3.OOE-06 ND ND 4.90E-05 0 BA-140 2.OOE-05 ND ND ND> LA-140 2.OOE-05 2.03E-03 1. l1 E-04 ND a: RU-105 L.OOE-04 4.07E-05 ND ND CD RU-106 1.OOE-05 ND 4.38E-04 ND ZN-65 1.OOE-04 1.59E-04 ND ND W-187 6.OOE-05 ND 7.98E-05 ND Total Ci Gamma 3.57E+00 2.38E+00 2.31E-01 ry MPCe (ptCi/ml) 4.81E-06 1.55E-05 1.12E-05-V-) MPC value for unrestricted area from 10 CFR 20, Appendix B, Table 11, Column 2.0 **ND = not detected r.a Page 123 of 155 Salem ODCM Rev. 24 APPENDIX B Technical Basis for Simplified Dose Calculations Liquid Radioactive Effluent 0 C)0 Cu U-0 U-CI)D Page 124 of 155 Salem ODCM Rev. 24 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 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.The calculated GI-LLI dose is predominately a function of the Fe-55, Co-58, Co-60, Fe-59 and Ag-i1m 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-1 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 5 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 1.Ci/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. S For the total body calc'ulation, the Fe-59 dose factor (2.32 E+05 mrem/hr per ý.Ci/ml, total body) is the z highest among the identified dominant nuclides. For evaluating compliance with the dose limits' of ODCM CONTROL 3.11.1.2, the following simplified equations may be used: r-)3 Total Body D)--.67E-O2*VOL (B.1)< Dtb=- *AFe -59,TB*ECi(B1 .,' CW> Where: 2 Dtb = dose to the total body (mrem)>- A Fe-59,TB = 7.27E+04, total body ingestion dose conversion factor for Fe-59 (mrem/hr per pCi/ml)i , VOL = volume of liquid effluent released (gal)> Ci = total concentration of all radionuclides (1ACi/ml)ry CW = average circulating water discharge rate during release period(gal/min) 0 1.67E-02 = conversion factor (hr/min)w P 1o V/)r.da Page 125 of 155 Salem ODCM Rev. 24 Substituting the value for the Fe-59 total body dose conversion factor, the equation simplifies to: Di=1..21 E+ 03* CW iZ.(B.2)Maximum Organ I I I I I I I I Dx = 1. 167E-02* VOL
ANb- 95,G LU

Z-C i C Wi (B.3)Where: Dmax maximum organ dose (mrem)ANb-95,GI-LL
= 1.5 lE+06, Gi-LLI ingestion dose conversion factor for Nb-95 (mrem/hr perýLCi/ml)Substituting the value for ANb-95,GI-LLI the equation simplifies to: Dnia- =2.52E+04* VOL w(B.4)i .i I z Cr)V)Zýz D--H-C/')z 0 C/I z>.-it..c-0..0 U-..0U-D.t.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% ofthe 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. Page 126 of 155 I I I I I I I I I I m m M m m m M m m m m m m m m m m m M USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES S0 S .alem ODCI~ev. 24 Table B-1: Adult Dose Contributions -Fish and Invertebrate Pathways -Unit I 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+0 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-110m 1.10E-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 Page 127 of 155 USER RESPONSIBLE FOR VERIFYING REVISION, STATUS AND CHANGES lp 0 Salem ODCNv. 24 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-1IOr 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-1 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 Page 128 of 155 M M m M M---- M M---- M M MM Salem ODCM Rev. 24 I I.APPENDIX C (I)w<, Ir I<0 Z-Si Technical Bases for Effective Dose Factors Gaseous Radioactive Effluent Page 129 of 155 S Salem ODCM Rev. 24 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, Meff 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 -Z(Ki*fi)i (C.1)LU 0 0 C-)z n-Ci)00 z 0 LU n V)U.-LU.r-y m ti, C.)0 0Y LUl Where: Kerr = 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 I I I I I I I I I I I I I I I I I (L-+I. 1M)e--j: [(L-+I. LAII)*f ](C.2)Where: (L + 1.1 M)eff (Li + 1.1 M 1)= the effective skin dose factor due to beta and gamma emissions from all noble gases released= the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released Page 130 of 155 Salem ODCM Rev. 24*Meff =Z(MW *f) (C.3)Where: IMeff = 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 =ZY(Ni *f)CA Where: 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 Salem have been maintained to such negligible quantities that the inherent variability in the data makes any meaningful evaluations
difficult.
Therefore, in order to provide a reasonable basis for the derivation of the effective noble gas dose factors, the primary coolant source term from ANSI N237-1976/ANS-18.l, "Source Term Specifications," has been used as representing a typical distribution. The effective dose factors as V derived are presented in Table C- 1.-7: ApplicationTo provide an additional degree of conservatism, a factor of 0.50 is introduced into the dose<c calculational process when the effective dose transfer factor is used. This conservatism provides 0 additional assurance that the evaluation of doses by the use of a single effective factor will not 1< significantly underestimate any actual doses in the environment. z2 For evaluating compliance with the dose limits of ODCM CONTROL 3.11.2.2, the following 0 simplified equations may be used: Dr= 3.17E-08*
Me* (.0.50 (>-I> and 3.17E-08-.50 *Nff (C.6)0 Where: iric Page 131 of 155 Salem ODCM Rev. 24 DY = air dose due to gamma emissions for the cumulative release of all noble gases (mrad)Dp X/Q Meff Neff Qi 3.17E-08 0.50 air dose due to beta emissions for the cumulative release of all noble gases (mrad)atmospheric dispersion to the controlling site boundary (sec/m3)5.3E+02, effective gamma-air dose factor (mrad/yr per gCi/m3)1. lE+03, effective beta-air dose factor (mrad/yr per ýLCi/m3)cumulative release for all noble gas radionuclides (piCi)conversion factor (yr/sec)conservatism factor to account for the variability in the effluent data Combining the constants, the dose calculational equations simplify to: Dr=3.5E-O5*YQ*>jQ (C.7)and Dco=7.OE-05* Qi (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.
I I I I I I I I w Lii 0 z-)0 (1)w 0 O'I z" U-U-0 U-U--LJ a~_l 0 VI)rx 0-Ii, L....0 t:D.Page 132 of 155 Salem ODCM Rev. 24 Table C-I: Effective Dose Factors I i Noble Gases -Total Body and Skin Total Body Effective Dose Factor Keff (mrem/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 2.5E+00 2.8E+02 3.6E+01 4.7E+02 Skin Effective Dose Factor (L+ 1.1 M)eff (mrem/yr per iiCi/m 3)1.4E+01 1.9E+02 1.4E+01 6.6E+02 7.9E+01 9.6E+02 Total NobleGases -Airl.lie C)I.U U 0_z">-Li 0__j GoUj Gamma Air Effective Dose Factor Meff (mrad/yr per p.Ci/rn 3)Radionuclide Kr-85 Kr-88 Xe-133m Xe-133 Xe-135 fi0 0.01 0.01 0.01 0.95 0.02 Beta Air Effective Dose Factor Ne-(mrad/yr per ptCi/mr 3)2.OE+01 2.9E+01 1.5E+01 1.OE+03 4.9E+01 1.1E+03 1.5E+02 3.3E+00 3.4E+02 3.8E+01 5.3E+02 Total* Based on Noble gas distribution from ANSI N237-1976/ANSI-18.1, "Source Term Specifications." Page 133 of 155 Salem ODCM Rev. 24 APPENDIX D Technical Basis for Simplified Dose Calculation Gaseous Radioactive Effluent C-)LU z D H-0 H-LI)V/)w z 0 n L-L,_Page 134 of 155 Salem ODCM Rev. 24 APPENDIX D: Technical Basis for Simplified Dose Calculation -Gaseous Effluents*
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 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 (1.05E12 m 2 mrem/yr per /.Ci/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:Dma.a=3.l7E-08*W*R,-,31*

Q, Where: Dmax = maximum organ dose (mrem)W = atmospheric dispersion parameters to the controlling location(s) as identified in< Table 3.2-4.IV X/Q = atmospheric dispersion for inhalation pathway and H-3 dose contribution via other (/3)< pathways (sec/m 3)Ln D/Q = atmospheric deposition for vegetation, milk and ground plane exposure pathways (m-z)zQi = cumulative release over the period of interest for radioiodines and particulates 0 3.17E-8 = conversion factor (yr/sec)> RI-131 = 1-131 dose parameter for the thyroid for the identified controlling pathway W -1.05E+12 (M 2 mrem/yr per tCi/sec), infant thyroid dose parameter with thegrass-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 a: thyroid dose.0 V)Se It is recognized that for some particulate radionuclides (e.g., Co-60 and Cs-137), the ground exposure a. pathway may represent a higher dose contribution than either the vegetation or milk pathway.IIa Page 135 of 155 0 V/)0 LU V)ry 0 Z 0 LU z Of LUJ>-0, LU.0,_..Salem ODCM Rev. 24 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.Page 136 of 155 I I I I I I I I I I I I I I I I I I)I)>0 In w, 0 o Salem ODCM Rev. 24 Table D-1: Infant Dose Contributions Fraction of Total Organ and Body Dose PATHWAYS Target Organs Total Body Liver Thyroid Kidney Lung GI-LLI Grass-Cow-Milk 0.02 0.23 0.59, 0.02 0.01 0.02 Ground Plane 0.15 0.14 0.15 0.15 0.02 0.15 Fraction of Dose Contribution by Pathway Pathway f Grass-Cow-Milk 0.92 Ground Plane 0.08 Inhalation N/A Page 137 of 155 Salem ODCM Rev. 24 10 APPENDIX E Radiological Environmental Monitoring Program Sample Type, Location and Analysis p V)Li 0 0 z 0 z 0 Z--H--0 Z"s 0 0-0 (Y, (.-J L,:D 0_..U-0 D I. : Page 138 of 155 Salem ODCM Rev. 24 Ia 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, 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: Is 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 L10 IJ>0 L.-1 M.7)0.t.nv 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-l.Maps E-I and E-2 show the locations of sampling stations with respect to the site center point.Page 139 of 155 I Salem ODCM Rev. 24 TABLE E-1: REMP Sample Locations* A. Direct Radiation Monitoring Locations (IDM)STATION CODE STATION LOCATION*1S1 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 0.95 mi. E; site access road 6S2 0.21 mi. ESE;.observation building 7S1 0.12 mi. SE; station personnel gate lOSi 0.14 mi. SSW; circ water bldg.11S1 0.09 mi. SW; service water bldg.15S 1 0.57 mi. NW; near river and barge slip 16S1 0.54 mi. NNW; on road near fuel oil storage tank 4D2 3.7 mi. ENE; Alloway Creek Neck Road 5D1 3.5 mi. E; local farm 1ODI 3.9 mi. SSW; Taylor's Bridge Spur 14DI 3.4 mi. WNW; Bay View, DE, 15D1 3.8 mi. NW; Rt 9, Augustine Beach, DE.2E1 4.4 mi. NNE; local farm 3El 4.1 mi. NE; local farm 11E2 5.0 mi. SW; Rt. 9 12EI 4.4 mi. WSW; Thomas Landing 13EI 4.2 mi. W; Diehl House Lab 16EI 4.1 mi. NNW; Port Penn l-)1FI 5.8 mi. N; Fort Elfsborg S2F2 8.7 mi. NNE; Salem Substation D 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 2" 3F3 8.6 mi. NE; Quinton Township Elem. School NJ 0 4F2 6.0 mi. ENE; Mays Lane, Harmersville, NJ 5F1 6.5 mi. E; Canton, NJ re-" 0 z_ý5 I 7O 0 C-z 0 IJ) I tCa Page 140 of 155 D I Salem ODCM Rev. 24*1 TABLE E-1 (Cont'd)I .A. Direct Radiation Monitoring Locations (IDM) (Cont'd)STATION CODE STATION LOCATION*6F1 6.4 mi. ESE; Stow Neck Road 7F2 9.1 mi. SE; Bayside, NJ 9F1 5.3 mi. S; off Route #9, DE 1 0F2 5.8 mri. SSW; Rt. 9 111F1 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 mni. WNW; Rt 13 and Boyds Comer Rd 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 1OGI 12 mi. SSW; Smyrna, DE 14GI 11.8 mi. WNW; Rte 286, Bethel Church Rd., DE I .16G1 15 mi. NNW; Wilmington Airport 3H1 32 mi. NE; National Park, NJ U)B. Air Sampling Locations (AIO, APT)I< STATION CODE STATION LOCATION*< 5St 0.95 mi. E; site access road U 5D1 3.5 mi. E; local farm 7 16EI 4.1 mi. NNW; Port Penn IF[ 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.-Ii,~Page 141 of 155 (13 I Salem ODCM Rev. 24 Table E-1 (Cont'd) I* C. Surface Water Locations (SWA) -Delaware River STATION CODE STATION LOCATION*11Al 0.2 mi. SW; Salem Outfall Area IlAla Alternate 0.15 SW 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 7El 4.5 mi. SE; River Bank 1.0 mi. W of Mad Horse Creek 7E Ia Alternate 8.87 mi SE at the end of Bayside Road IF2 7.1 mi. N; midpoint of Delaware R.16FI 6.9 mi. NNW; C&D Canal D. Ground Water Locations (WWA) I STATION CODE STATION LOCATION*3E I 4.1 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 S E. Drinking Water Locations (PWR, PWT) I t 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 0 Stations. However, this location (2F3) is being monitored as a management audit sample.H-I C-- F. Water Sediment Locations (ESS)_ STATION CODE STATION LOCATION* I>Q:h 11Al 0.2 mi. SW; Salem outfall area o 15AI 0.3 mi. NW; Hope Creek outfall area Z_ 16A1 0.7 mi. NNW; South Storm Drain outfall_- 12CI 2.5 mi. WSW; West bank of Delaware River 7E1 4.5 mi. SE; 1 mi West of Mad Horse Creek ry 16F1 6.9 mi. NNW; C&D Canal o-O 6S2 0.2 mi. ESE; observation building MII 0 Page 142 of 155 D0I O'3 Salem ODCM Rev. 24 Table E-1 (Cont'd)I, G. Milk Sampling Locations (MLK)STATION CODE STATION LOCATION*2G3 12.0 mi. NNE, local farm 133E3 4.9 mi W, local farm 14F4 7.6 mi. WNW; local farm 3Gl 17 mi. NE; local farm H. Fish and Invertebrate Locations (ESF, ECH)STATION CODE STATION LOCATION*11AI 12C1 7E1 0.2 mi. SW; Salem outfall area 2.5 mi. WSW; West bank of Delaware River 4.5 mi. SE; 1 mi West of Mad Horse Creek I.U LU U 0 ID LU U-0 U+/-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 39' -27' -46.5" and Longitude W 75' -32' -10.6".Page 143 of 155 Salem ODCM Rev. 24 SAMPLES COLLECTION AND ANALYSIS S Sample Collection Method Analysis Air Particulate Air Iodine Crab and Fish Sediment Direct Continuous low volume air sampler. Sample collected every week along with the filter change.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. 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 areperformed on each weekly sample.Gamma isotopic analysis of edible portion on collection. Gamma isotopic analysis semi-annually. Gamma dose quarterly. I I I I I I I I I I I I I I I I I I I 0 (-n Z-r 0 D U-H--0 z 0 z C--Lw-J cL .-0d_.1 0 w.w3 0~D>Page 144 of 155 Salem ODCM Rev. 24 SAMPLE COLLECTION AND ANALYSIS (Cont'd)Sample Milk Water (Potable, Surface)Collection Method Analysis 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.c~o-r-0 0 0 I-V)I!U-0 U-LUJ:D Page 145 of 155 Salem ODCM Rev. 24 FIGURE E-l: ONSITE SAMPLING LOCATIONS 0 I 5 r U z CD (I)cn 0-ni (1)CD z U-9 0 a--i, U-.U-.nii D2 a I I I Page 146 of 155 Salem ODCM Rev. 24 FIGURE E-2: OFFSITE SAMPLING LOCATIONS 0 0 V)CD I 0 cn tad rý, U 0 I-0 U 00 0 n V)z U-wk 0j U-D-Page 147 of 155 Salem ODCM Rev. 24 0 APPENDIX F MAXIMUM PERMISSIBLE CONCENTRATIONS LIQUID EFFLUENTS CD z-)-ci r_)z 0 CI---n H--(A z" 0 c,'3 Lii (..w:D U-w~.0..U-2 w CI,)w2 w~CI3 Page 148 of 155 Salem ODCM Rev. 24 APPENDIX F: Maximum Permissible Concentration (MPC) Values -Liquid Effluents The following radionuclide concentrations were obtained from 10 CFR 20 Appendix B, Table .1, Column 2 as revised January 1, 1991.Table F-1: Maximum Permissible Concentrations Element Isotope Soluble Conc Insoluble Conc.(/.tCi/ml) (fiCi/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 IE-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 Cf-252 7E-6 7E-6_Cf-253 1E-4 IE-4 I Cf-254 1E-7 IE-7 V)V)0 ia:'0 nJ Page 149 of 155 Salem ODCM Rev. 24 Table F-1 (Continued) S Element Isotope Soluble Conc. Insoluble Conc..(ýCi/ml) (pCi/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 IE-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 3EH-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-1 65 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 LE-5 1E-5 Es-255 3E-5 3E-5 Erbium (68) Er-169 9E-5 9E-5 Er-171 IE-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 IE-4 IE-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 oo z U)0 0 z U-0 U--J 0 D Page 150 of 155 Salem ODCM Rev. 24 Table F-I (Continued) I°I Io lie.)I.0 U-Iz>-Ila_ryt 102 D Element Isotope Soluble Conc. Insoluble Conc.(ýtCi/ml) (4Ci/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-1 96 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 IE-3 1E-3 In-1 14m 2E-5 2E-5 In-115im 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-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-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 1E-4 IE-4 Mn-56 LE-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 Page 151 of 155 I Salem ODCM Rev. 24 Table F-1 (Continued) a Element Isotope Soluble Conc. Insoluble Conc.(4tCi/ml) (}.tCi/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 IE-4 IE-4 Nickel (28) Ni-59 2E-4 2E-3 Ni-63 3E-5 7E-4 Ni-65 IE-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-191 m 3E-3 2E-3 Os-191 2E-4 2E74 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 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 1IE-31 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 1E-4 I I I I I I I I I I I I I 1 I V)r 0 0 V)z" 0 0 U--J I me V/)n U-tD¢-y trd I I I Page 152 of 155 Salem ODCM Rev. 24 Table F-1 (Continued) I.IO I I I I 03 C-)0-0 Lii>-ka..0 w cn 03 n-c V)2 w3 Element Isotope Soluble Conc. Insoluble Conc.(ýLCi/mnl) (ýLci/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 IE-2 IE-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 lE-4 1E-4 Ru-106 1E-5 lE-5 Samarium (62) Sm-147 6E-5 7E-5 Sm- 151 4E-4 41E-4 Sm-153 SE-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-1 10m 3E-5 3E-5 Ag-1 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 Page 153 of 155 Salem ODCM Rev. 24 Table F-I (Continued) a Element Isotope Soluble Conc. Insoluble Conc.(PCi/ml) (pLCi/ml)Technetium (43) Tc-96m 1E-2 IE-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 lE-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) Tb-160 4E-5 4E-5 Thallium (81) TI-200 4E-4 2E-4 TI-201 3E-4 2E-4 T1-202 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 Tin-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 U I I I I I I I I I I I I I V)0 Ln w 0 z LC-0 z 0 L-0 z MD 0 z" 03 CL2 V-LI..LL.w 0 03 Page 154 of 155 Salem ODCM Rev. 24 Table F-I (Continued) I.I I I I I I V)(I)U-0 Li LLJ_j M1 Element Isotope Soluble Conc. Insoluble Conc._____________(j.tCi/ml) (ptCi/mI)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 hours 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 jiCi/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").Page 155 of 155}}

LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual Revision, 24

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