ML061290347

Appendix C - Salem ODCM

ML061290347
Person / Time
Site:	Salem, Hope Creek
Issue date:	05/01/2006
From:	Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209
Download: ML061290347 (157)

Text

2005 SGS AND HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT APPENDIX C SALE DC U

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OFFSITE DOSE CALCULATION MANUAL FOR PSEG NUCLEAR LLC SALEM GENERATING STATION Revision 19 Prepared By:

Date Reviewed by:

Date Accepted by:

Accepted by: ?D0o Date Meeting#: 005- OZ I Approved by: -

cX,%-s--

Plant Man er bate Page 1 of 156

'ii Salem ODCM Rev. 19 L Revision, Summary L

1. Removed the wording" Providing Alarm and Automatic Termination of Release" and added the # symbol - Items 2

& 3 Table 3.3-13 (pg 25) i

2. Revised (**) footnote and added (#) footnote on Table 3.3-13 (pg 26) - modified wording:

• • During Containment otinet Purg ges OR CR ontainmen Prnessire-Vauu Relief L APPLICABILITY:

Modes 1-6, R41A/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).

U During Mode Undefined (Defueled) operation, containment purge is reclassified as a building ventilation process stream monitored by the PLANT VENT HEADER SYSTEM.

1. During movement of irradiated fuel within containment with the Containiiient Equipment Hatch OPEN, only U

R41A -can be credited for MINIMUM CHANNEL OPERBLE. ,

Durig movement of irradiated fuel within containment with Cntainent Euitch Hae CLOSED, R41AID L; or R12A may be credited MIMUM-C rif LO1ERA L LE X

• ma b i ,i2A !r * ,

3: ',Removed the wording" Providing Alarm and Automatic Ternmiinatiibof Release". - Item 2 Table 4.3-13 (pg 27)

4. Revised (**) footnote on Table 4.3-13 (pg 28) - modified wording:

. Containment Purges DuringOR Containment Pressure - acuim elief.

$reillance requirement -

Mdodes 1-6, R41A/D Monitors providing Alarm and Automatic Tekm'ination of Release Modes 1-5, R12A Monitors providing Alarm and Automatic TemainiUon ofPRlease I Modef6, R12A Monitors providing Alarnn only (Automatic Temnation of Releaseis not required).

During Mode Undefined (Defueled) operation, containment purge is recissified-as a building ventilation process stream monitored by the PLANT VENT HEADER SYSTEMS. .

During movement of irradiated fuel-within containhient withthe Containent Equipment Hatch OPEN, only R41A/D can be credited for MINIMUM CHANNEL OPERABLE. .

-Dufing movement of irradiated fuel within containment with the Containmnt Equipment Hatch CLOSED, R4 1A/D

..or R12A may be credited for MINIMUM CHANNEL OPERABLE.. '

Justification: L This ODCM further clarifies the 2 changes done by ODCM Revision 17 & 18 and further relaxes containment purging in refueling outages by redefining "purging" as "building ventilation" when the plant is in Mode Undefined (Defueled).

The design functions for the gaseous effluent radiation monitoring of releases from containment purge in Mode Undefined (Defueled) will be met by the use of the Plant Vent (PLANT VENT HEADER SYSTEM) radiation monitors.

When defueled, "Purging" can be reclassified as a building ventilation stream feeding into the Plant Vent. This change to the ODCM relaxes the requirements of the R12A - R4 IA/D monitors in a defueled containment, which was overly 1 restrictive. This ODCM change allows the Plant Vent radiation monitors with grab sample backup to support purging when defueled. l L

Page.2 of 1,56 L

Salem ODCM Rev. 19 TABLE OF CONTENTS INTRODUCTION .................................................................................................................................. 7 PART I - RADIOLOGICAL EFFLUENT CONTROLS .................................................................... 8 1.0 DEFINITIONS ........................................................................ 10 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS ........................................................ 16 3/4.0 APPLICABILITY .................................................................................................................. 16 3/4.3 INSTRUMENTATION ......................................................................... 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 LIQUID EFFLUENTS...................................................................... 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 GASEOUSEFFLUENTS...................................................................... 35 3/4.11.2.1 DOSE RATE ...................................................................... 35 3/4.11.2.2 DOSE - NOBLE GASES ...................................................................... 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 DOSE...................................... 41 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING .............................................. 42 3/4.12.1 MONITORING PROGRAM ............................................... 42 3/4.12.2 LAND USE CENSUS................................................ ;55 3/4.12.3 INTERL4BORATORY COMPARISON PROGRAM .............................................. 57 BASES.............. ,58 3/4.3 INSTRUMENTATION ........................... 59 3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION .... 59 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 60 3/4.11 RADIOACTIVEEFFLUENTS.......................... 62 3/4.11.1 LIQUID EFFLUENTS .......................... 62 3/4.11.2 GASEOUS EFFLUENTS .......................... 63 3/4.11.4 TOTAL DOSE ....................................................... 65 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING ........................................ ....... 66 3/4.12.1 MONITORING PROGRAM ........................ 6......................

66 3/4.12.2 LAND USE CENSUS ................................................. 66 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM .............................................. 66 5.0 DESIGN FEATURES ................................................. 68 5.1 SITE ................................................. 68 5.1.3 UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS .......................... 68 6.0 ADMINISTRATIVE CONTROLS .......................... 70 6.9.1.7 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT .............. 70 6.9.1.8 RADIOACTIVE EFFLUENT RELEASE REPORT ..................................................... 70 Page 3 of 156

Salemn ODCM Rev. 19U 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS .......................................... ... .. 72 PART II - CALCTJLATIONAL METHODOLOGIES ................................. 7`

1.0 LIQUID EFFLUENTS ........................... 74

• 1.1 RadiationMonitioringInstrumentationandCon-tr~ols..................................74 12Liquid-Effluent Monitor t.oint..Determ..nation ... 74

_1.2.1 Liquid Effluent Monitors (R~da'.V ste, StemGnrtrBodwi ChmcalW'aste'Ba'sin and Service Water.75.;-... .............. .............. ~..,;. ...

1.2.2 Conservative Default Values.................................... ....76 1,3LqiCfzSt~e~ieirto iit JCFR20",

- 177

1. iq~uid ~uentoe 14A. 1 MEMBER .OF THE PUBLIC Dose -Liquid Ef nfluiits.

1.5Secondary Side R-adioactiv Liqui ?Efflue and Dose. Ccwua~n During,Prmaj to-

• Secondary ... ... ..

.Leakage. 79 16Lq i Efle tD s Projections" -.. . . . .

. .' . . ................. .... ..... ... U 2

2.1 ConietaiE uitle~ n latk VentMhtor~~ ............ 82 2.2.2 Consrative Default Valus .l......... ............ 83 "2.3 Gaseous EffluentlInstantaneousDose'Rat~' Calculaions -10' CFR 20.~ 1~.,i..~.~...4..... 8 I ose-Nble Gaes.............."..8 2.4.1 NRESTICTEDAREA 2.4.2 Simlifed DoslCalclatio . . . . .ses.

. .8 2.5 RadobodinGas~ und Pariclae-D Calculations I -0 0 CFRSO ..

1F 8 251U ESRCTED' ARE os Radbioidnands Patcua .s ....... `87 2.45.2 Siiiplified Dose Calculationi foIr Radioiod e~ and' Pa cu.t..8 ..

'2.5 R'Sec~odndanySde PrtdioatDdseiaoics~fflueris; a0:d~oPe5ac0- in . .8 2.7 Gaseus:EffluenteDose,Projection ... .90

,3.1 Doses Due To Activities Insi1de theSITE BO0UADARY.W'4 p

"" ."4 ........ ..... 91 1~

32 Total-dose to MEMBERS, OF-TH-E PUBLIC,-4 CFR190 ... ........... ......... 91 3 .2.2 Drect Exposure Dose Determination.. ............ 4........ 9 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORINGPROGRAM...93 "44.1 Sampling Program...1.4.". -.. '" ..... ' ........ ....................... .......... 9

'4.2InterlaboratoryComparisonProgram-.93. .

Page 4 of 156 U

Salem ODCM Rev. 19 TABLES TABLE 1.1: OPERATIONAL MODES ..................................................................... 13 TABLE 1.2: FREQUENCY NOTATION ..................................................................... 14 TABLE 3.3-12: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

.19 TABLE 4.3-12: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ............. ....................................................... 22 TABLE 3.3-13: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION .................................................................... 25 TABLE 4.3-13: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS .............. ................................... 27 TABLE 4.11-1: RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

.30 TABLE 4.11-2: RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM.36....................................................................................................... ......................... 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 ANALYSIS~l), (2).52 ANALY SI (1),(2)............................................................................................................................5 Table 1-1.1: Parameters for Liquid Alarm Setpoint Determinations Unit 1................................. 97 Table 1-1.2: Parameters for Liquid Alarm Setpoint Determinations - Unit 2 .............................. 98 TABLE 1-2: Site Related Ingestion Dose Commitment Factor, Ai0 . ............................................ 99 Table 1-3: Bioaccumulation Factors ......................................................... 101 Table 2-1: Dose Factors For Noble Gases ......................................................... 104 Table 2-2.1: Parameters for Gaseous Alarm Setpoint Determinations - Unit 1.......................... 105 Table 2-2.2: Parameters for Gaseous Alarm Setpoint Determinations - Unit 2 ............ ............. 106 Table 2-3: Controlling Locations, Pathways .................. ....................................... 107 Table 2-4: Pathway Dose Factors - Atmospheric Releases ........................................................ 108 Table A-1: Calculation of Effective MPC - Unit 1......................................................... 123 Table A-2: Calculation of Effective MPC - Unit 2 ................................... 124 Table B-1: Adult Dose Contributions - Fish and Invertebrate Pathways - Unit 1...................... 128 Table B-2: Adult Dose Contributions - Fish and Invertebrate Pathways - Unit 2 ...................... 129 Table C-1: Effective Dose Factors .................................. . .. . 134 Table D-1: Infant Dose Contributions ............................. 138 TABLE E-1: REMP Sample Locations .................................... ,. 141 Table F-1: Maximum Permissible Concentrations .................................. 150 FIGURES Figure 5.1-3: Area Plot Plan Of Site ......................... !. , ,. .69 Figure 1-1: Liquid Release Flowpath Unit 1 .................................. ... ,,.....,.94 Figure 1-2: Liquid Release Flowpath Unit 2 ................................ 95 Figure 1-3: Liquid Radioactive Waste System ................................ 96 Figure 2-1: Salem Ventilation Exhaust Systems And Effluent Monitor Interfaces .................. 102 Figure 2-2: Gaseous Radioactive Waste Disposal System ....................................................... 102 Page 5 of 156

L Salem ODCM Rev. 19 L

Figure 2-2: Gaseous Radioactive Waste Disp-sal System .................................................... 103 Figure E-1: Onsite Sampling Locations ....................................................

Figure E-2: Offsite Sampling Locations ..................

147 148 1.4...........

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'APPNNDflA2 EVAW~ONOFDF~t LT PA TEtRS FOR IQIDEFEtBTS .... ' ,a $.'.'...121 PENDIX B: TECHNICAL BASIS FOR SLFDOSE C APPENDIX C: TECHNIcABAsEs FO E TI6 DOSE FACTORS -

ASEOUS EFFUENTS' I EFFLNTSVt. 126 131 G

APPENDIX D: TECHNICAL BASISTFR SIMPLIFIED DOSE CALCU GAS SEFFUeSNS.136 APPENDIX E: RADIOLOGICALIWENII AP>PENDIX !: AXMU .PEMSSIL ON ENTAL'Im ON.IOi.tNP ONETAIOSMCVLE M.

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Page 6 of 156

Salem ODCM Rev. 19 SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL INTRODUCTION The Salem Offsite Dose Calculation Manual (ODCM) is a supporting document to the Salem Units 1 and 2 Technical Specifications. The previous Limiting Conditions for Operations that were contained in the Radiological Effluent Technical Specifications (RETS) are now included in the ODCM as Radiological Effluent Controls (REC). The ODCM contains two parts: Part I - Radiological Effluent Controls, and Part II - Calculational Methodologies.

Part I includes the following:

• The Radiological Effluent Controls and the Radiological Environmental Monitoring Programs required by Technical Specifications 6.8.4

• Descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by Technical Specifications 6.9.1.7 and 6.9.1.8, respectively.

Part II describes methodologies and parameters used for:

• the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints; and

• the calculation of radioactive liquid and gaseous concentrations, dose rates, cumulative quarterly and yearly doses, and projected doses.

Part II also contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program (REMP), and the liquid and gaseous waste treatment systems.

Revisions to the ODCM shall be made in accordance with the Technical Specifications Section 6.14.

The current licensing basis applies Maximum Permissible Concentrations (MPCs) for radioactive liquid effluent concentration limits. Since the MPC values were removed from IOCFR20 effective 1/1/94, the MPC values are provided as Appendix F to the ODCM. As discussed in the Safety Evaluation by the Office of Nuclear Reactor Regulation related to Amendment Nos. 234 and 215, letters between the Nuclear Management and Resources Council (NUMARC) concerning the differences between the "old" 10CFR20 and the "new" IOCFR20 allowed continued use of the instantaneous release limits (MPCs).

The NUMARC letter of April 28, 1993, concluded that the RETS that reference the "old" Part 20 are generally more restrictive than the comparable requirements of the "new" Part 20, and therefore, in accordance with 10 CFR 20.1008, the existing RETS could remain in force after the licensee implements the "new" Part 20. The letter stated that the existing RETS which reference the "old" Part 20 would maintain the level of required protection of public health and safety, and would be consistent with the requirements of the "new" Part 20.

Page 7 of 156

1  ! . -Salem ODCM Rev. 19L Alied 14 Svi L J) "sit;'cil 1;sit9~ dlt:tt 'j l J.i i ! is;ij >Is'mg.,

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Salem ODCM Rev. 19 SECTION 1.0 DEFINITIONS Page 9 of 156

Salem ODCM Rev. 19 L 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 adjusien't, as necessary, of the channel output such that U

it responds with the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shAll renrdmpass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST.

LI Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. Whenever an RTD or thermocouple sensing element is L

replaced, the next required CHANNEL CALIBRATION shall include an inplace cross calibration that compares the other sensing elements with the recently installed sensing monitor. The CHANNEL L CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated. L CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by -

observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or' status derived from independent instrument channels measuring the same parameter. L' CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions. L CONTROL 1.10 The Limiting Conditions for Operation (LCOs) that were contained in the Radiological Effluent Technical Specifications were transferred to the OFFSITE DOSE CALCULATION MANUAL (ODCM) and were renamed CONTROLS. This is to distinguish between those LCOs that were retained L

in the Technical Specifications and those LCOs or CONTROLS that were transferred to the ODCM. L DOSE EOUIVALENT I-131 1.1 1 DOSE EQUIVALENT I-131 shall be that concentration of I- 131 (microcuries per gram), which alone would produce the same thyroid dose as the quantity, and isotopic mixture of I-13 1, I-132, I- A 133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844 "Calculation of Distance Factors for Power and Test Reactor Sites."

Page 10 of 156 i

Salem ODCM Rev. 19 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 1.16 MEMBER(S) OF THE PUBLIC shall be all those persons who are not occupationally associated with the plant. This category does not include employees of PSE&G, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.17 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the environmental radiological monitoring program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and the Radioactive Effluent Release Reports required by Technical Specification Sections 6.9.1.7 and 6.9.1.8, respectively.

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

function(s).

OPERATIONAL MODE - MODE 1.19 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.

PURGE - PURGING 1.23 PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

Page 11 of 156

Salem ODCM Rev. 19 RATED THERMAL POWER ='

1.25 RATED THERMALPOWER shall beia total reactor coie heat'transfer rate to the'reactor coolant of 3459 MWt.

REPORTABLE EVENT 1.27 A REPORTABLEEVENTs shahlbeanyiof th6s~onditibs4 speifiemd in-:Stion 50.7334to':

10CFRPat 50 -fi, f. 'H s .t(,1ws:dfl>

fS 4 iL 1.f. ;4. i 4iK~:

f,~ i7 ), Kmr.7 ;4  :. . :1 4i0 SITE BOUNDARY , ..

1.29 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3.

SOUR- CECHE HT?<:4HY; *f t H' P 'P '  ; ^P4. I m: 8 : .

1.31 SOUR(DCE CHECK h all b64he qualitative assessment of channel response .whenfithe channiel sensor is exposed toa ceo re dradi A4 '

t ; 4 r4; 4 .44i I i,'

4 4444 r , 4 4d i 444 44! 4 '..0jX -j THERMAL' POWER 1.33 THERMAL POWER shall be the total reactofrcoe h a ise Sti t t the re-c'to cooi t.i .~i 1.35 AtNRE ICTED'AR EIThalbn eto nd h TBUNDARY,,access to-'

which is notcntrolled ythe li'cen'seefiorpurpos'es' of protectionofo idii ls frmexposure to radiation and iadioactive materialsoray 'area ithlii-.the SITE BOUNDARY used for residential quarters, otpindusthia1; cobm 1'a linstitutina rand/o r ai .merdil 4 44 .purposes> 4 4:

44 ffl.x 4 l 4rEhw>4ii S!ft 4¢ 44 4' ., 44' 444 4 444444444 44 4 VENTILATION EXHAUSTTREATMENTSYSitM 4 'H 4; 44 I '

1.36 A VENTILATION bEXHAST TREATMENT SYSTEM shall be ansytem designeda 77

iI Salem ODCM Rev. 19 L

LI TABLE 1.1: OPERATIONAL MODES L

REACTIVITY AVERAGE COOLANT MODE CONDITION, Keff THERMAL POWER* TEMPERATURE

>0.99 >5% > 350 0F L 1. POWER OPERATION

2. STARTUP >0.99 < 5% > 350 0F L 3. HOT STANDBY <0.99 0 > 350 0F L

L 4. HOT SHUTDOWN < 0.99 0 350F > Tavg

> 200 0F L

L 5. COLD SHUTDOWN

6. REFUELING**

< 0.99

< 0.95 0

0

< 200 0F

< 140 0F

• 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 156

Salem ODCM Rev. 19 L TABLE 1.2: FREQUENCY NOTATION U NOTATION FREOUENCY L At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, II D 'At leiason'ce per `G24`hfr.

w At leastonce per 7 days.

M At kast once per 31 days.

Q At least once per 92 days. L SA At least once per 6 months. II :. U R At least once per 18 months.

sAU Prior to each reactor startup. ,,,,,

Ili I , 1 ji " , Li 7;"- , ( a, [ )

P Priqr to each release. i I I ,

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I 1, , P-,

i r,."k,,

- , I"

,I N.A. Not applicable. U Page 14 of 156

Salem ODCM Rev. 19 SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS Page 15 of 156

Salem ODCM Rev. 19 i 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITYU L 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. H 3.0.2 Noncompliance with a CONTROL shal exist w e requirents of the CONTROLS and associated ACTION requirements are not met within spied time intervals.

~he If the CONTROL is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a CONTROL is not met except as providein-theassotedACTION requirements, within one hour action shall be initiated to place the unit in a MODE' in-whfch the'CONTROL does not apply by placing it, as applicable, in:

1. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, L

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. L 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.

L This CONTROL is not applicable in MODE 5 or 6. L 3.0.4 Entry into an OPERATIONAL MODE or other specified condition: L (a) shall not be made when the conditions of the CONTROL are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. D (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. L This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual CONTROLS. L U

Page 16 of 156

Salem ODCM Rev. 19 APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual CONTROLS unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by CONTROL 4.0.2, shall constitute a failure to meet the OPERABILITY requirements for a CONTROL. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowed outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement(s) associated with the CONTROL has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

Page 17 of 156

- ir Salem ODCM Rev. 19 U 3/4.3 INSTRUMENTATION 3/ 4.3.3.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3.3,3.8jn accordance, with SalemUnits 1 and 2 Technical Specifications 6.8,4.g.1, the radioactive-,

liq iiiMt t montori nt entationt 'c anne s ' abk 3.3-1 shllbe PhoWnwin ER'LE with' their alaritipsetjiint' set't'estii-etihimits'fGNTROL i.1 aile j'a edl 't',' '

alarr/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CP~i.CULAION IANU ,(ODCV). f. *I APPLICABILIf Ding" lli re v t pathw

• 7>..

t'~I 4 4 i4

a. \ih~rcl~tvIqidefud otring in tuetto hinP1ritidpn't less conservative than required by theaboveCONTROL, without wd<l./!spen;d at N 1 release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable or c iange the setpoint so its acceably conservative.

b.^ 'W0iii 9 thantiinluii nbe fraqiacti4 ve 14 Uans mn~iit ing  ;,,4r~ : '

best efforts to retuing& l en to OPERALE s~tatus within 30 dys anid, if - L unsuccessful, explain in the next radioactive effluent release report why the inoperability late~~~manner.

was not corrected in a timely eektd

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

U SURVEILLANCE REQUIREMENTS U 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.

D Page180ofl$6 U

en r- f- ra; " n r77 r77 r7 Ir7_ c:- 7 c:- e7 cr7 Wc 1r7 lr--

Salem ODCM Rev. 19 TABLE 3.3-12: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INTSPT TMPNT OPERA BP ACTION

1. GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line 1 (1R18, 2R18) 26

b. Steam Generator Blowdown Line 4 (1R19A-D, 2R19A-D) 27

2. GROSS RADIOACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Containment Fan Coolers - Service Water Line 5 (Unit 1) (QR13A-E) 28 Discharge 3 (Unit 2) (2R13A-C)

b. Chemical Waste Basin 1 (R37) 31

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line 1 (lFR1064, 2FR1064) 29

b. Steam Generator Blowdown Line 4 (IFA-3178, -3180,-3182, -3184, 29 2FA-3178, -3180, -3182, -3184)

Page 19 of 156

I.

Salem ODCM Rev. 19 TABLE 3.3-12 (Continued) U 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 I

a release: I.:

a. At least two independent samples are analyzed in accordance with CONTROL U

4'-T1 1..l , and

b. Atdleast two technically qualified members :of the Facility Staff independeitly verify the release rate calculations and discharge line valving; U

Otherwise, suspend release of radioactive effluents- via this pathway. L ACTION 27 - With thntimberfof channels OPERABLE less than required by the Minimum Channels OPERABtE requirement, effluent releases via this pathway may contiuvided grab samples-ari. 'analyzed for p cip amma emitters, 13 and dissolvd n r4ained U

gases at the lower limits of detection required in ODCM CONTROL 4 1-1 2B, and the ODCM Surveillance Requirement 4.11.1.1.2 is performed: U

a. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENTj1-13 1, or

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of th6 secondary coolant is less than or equal to 0.01 microcuriesg DOSE EQUIVALENTI-131.

ACTION 28 - With the number of channels OPERABLE les than required bte Minimum Chan'nels L

OPERABLE requirement, effluent'rM1eases."via this pathway may,:oontinue provid2lthat:

a. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, lo6ll monitor readouts for the affected channels are L

b.

verified to be below their alarm setpoints, or r (Unit 2)

With a Service Water Systemnleak .onthe Containment Fanh Coil Unit associated with the inoperable monitor either.; .

U

1. At least onte per8 hours sample1gr e tb be CKcted and analyed' for U principal gamua 'emittersg, I-13fi,and dissolved and entiained gases at the jlower1imits.'of detection 'secifiedin ODCM`CONTRL Table 4.1l-1.Bl and

,,fth6e OD6CMC urVeillance Require,'ment 4;.11. 1.1.2 isper-formed, or U

2. Isolate the Mreleae pathway.

c. With no identified service water leakage on the Containment Fan Coil Unit L associated with the ihoperle, monito"r, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, collect grab samples and analyze for prncipal gamma emitters; I-13,1,and dissolved and entrained gases tat the lower limits of detection specified in'IODCM CONTROL L Table 4.11-I.B, and the ODCM Surveillance Requirement 4.11.1.1.2 is performed.

L Page 20 of 156 U

Salem ODCM Rev. 19 TABLE 3.3-12 (Continued)

TABLE NOTATION ACTION 29 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

Pump performance curves may be used to estimate flow.

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 that sampling is conducted in accordance with the following table:

Frequency Condition 1 per week During normal operation (all MODES) 1 per day During operation with an identified primary to secondary leak on either Salem Unit The samples shall be analyzed for principal gamma emitters, I-13 1, and dissolved and entrained gases at the lower limits of detection specified in ODCM CONTROL Table 4.1 1-1.B, and the ODCM Surveillance Requirement 4.11.1.1.2 shall be performed.

Page 21 of 156

Salem ODCM Rev. 19 TABLE 4.3-12: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION -SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL ~-SOURCE ' CHANNEL -- s" FUNCTIONAL TNSJqT TTRUMPNT  : CH1TCK,. -- C-AT T ATION TESRT:

. , g .

1. GROSS RADIOACTIVITY MONITORS PROVIDING 5 _i ....

ALARM AND AUTOMATIC TERMINATION OF RELESE- _. 'v.

• : ;. i 24

a. Liquid Radwaste Effluent Line D>< tt q.

Pk- Q(1)

... .7. /

b. Steam Generator Blowdown Line D-^; M- R(3) Q(1) n, ; T

2. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM -2

-. DS BUT NOT PROVIDING AUTOMATIC TERMINATION-,OF >

RELEASE

a. Containment Fan Coolers - Service Water Line D M R(3) Q(2)

Discharge I .-

b. Chemical Waste Basin Line D M - R(3)~. Q(2)

3. FLOW RATE MEASUREMENT DEVICES NA.

a. Liquid Radwaste Effluent Line NA.. iR N.A.

b. Steam Generator Blowdown Line D(4) -i, -R N.A.

Page 22 of 156 7- rm7- rz rr rr-: Ir-777, V7 rr U--- rcc U-71 u_-__

17-rr- U-__ r ---, I

Salem ODCM Rev. 19 TABLE 4.3-12 (Continued)

TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels at or above the alarm/trip setpoint.

2. Circuit failure. (Loss of Power)

3. Instrument indicates a downscale failure. (Indication on instrument drawer in Control Equipment Room only)

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels at or above the alarm/trip setpoint.

2. Circuit failure. (Loss of Power)

3. Instrument indicates a downscale failure. (Indication on instrument drawer in Control Equipment Room only {Unit 1})

4. Instrument controls not set in operate mode. (On instruments equipped with operate mode switches only {Unit 1})

(3) The initial CHANNEL CALIBRATION was performed using appropriate liquid or gaseous calibration sources obtained from reputable suppliers. The activity of the calibration sources were reconfirmed using a multi-channel analyzer which was calibrated using one or more NBS (now NIST) standards.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

1. The 1RI 8 channel is an in-line channel which requires periodic decontamination. Any count rate indication above 10,000 cpm constitutes a SOURCE CHECK for compliance purposes.

1. The 2R1 8 channel is an off-line channel which requires periodic decontamination. Any count rate indication above 10,000 cpm constitutes a SOURCE CHECK for compliance purposes.

Page 23 of 156

kw Salem ODCM Rev. 19 3/4.3 INSTRUMENTATION L 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLSw 3.3.3.9 In accordance with Salem Units 1 and 2 Technical Specifications 6i8.4.g.1, the&k§ LI radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with.theirialarfn/triplsetpdints set-to enrsurethat the limits of CONTROL 3.11.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance U w ith the ODJC M . ia'i"-g:..

t'>rli+

' ,'XS,/

APPLICABILIT-Y: As inPshon Table33-13f i - ,' ht j ACT1ION:)I~

a. With a radioactiVef gaseous luent mto n en tation chbilalm/trip setpoint less conservative than required by the above CONTROL, without delay

, t;suspend fthe releae Sergdioactive'ous effluentsitored f byithe5 affected L channel or declare the channel inoperable or change the 'setpoint so it'is acceptably conservative. [

b Wi ale nthe vtha 'mulnber of adiotive' gase usf nto ring instrumentation cdhannels OPERABLEtaCiNs howni Table 3.3-13.

Exe'rt best efforts to return the istrument to OPERABLE status within 30 days

, and if un cssflxla in the tadio e e t ease report why the inoperability was not corrected in at;tinIely er:

c ;The provisions of CONTROLS 3.0.3 and 3 0 re not applikable.F:

• SURVEILLANCE REQUI A U 4.3 3.9 'Each radioactie 'aseouus effluent monitorng ihtmnattion on ce shall bet ' n demonstrated OPERABLE by performanc ftheCHAN14ElkCHECKt'SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

.:;f

F)

,it

• tHR i fU 2, .;!,.;,,,.:;!' t..I,X.wj ;i lf f' nrfi ' .!,

Page 24 of 156 i

Id- rm =1 r ".- I:'" C: r7 r to_ er r. 77 W7 r: 7- ?[-

Salem ODCM Rev. 19 TABLE 3.3-13: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INTS'P AA I - L\~.

.1-T RUMPNT I . _ . _ - - _J_ . . _ G OPER us CT ABE v

P APPT.ICABITTLTTY ACTTON

- - -_ - - -- ^

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor - Providing 1 (lR41A&D,

• 31 Alarm and Automatic Termination of Release 2R41A&D)

2. CONTAINMENT PURGE

a. Noble Gas Activity Monitor 1 (1R12Aor1R41A&D, ** 34 2R12A or 2R41A&D) #

3. CONTAINMENT PRESSURE - VACUUM RELIEF

a. Noble Gas Activity Monitor 1 (1R12A or lR41A&D ** 37 2R12A or 2R41A & D) #

4. PLANT VENT HEADER SYSTEM##

a. Noble Gas Activity Monitor 1 (IR41A&D, 2R41A&D)

• 33

b. Iodine Sampler 1 (lRME4,5 or 1XT8911,

• 36 2RME4,5 or 2XT8911)

c. Particulate Sampler 1 (lRME4,5 or 1XT8911,

• 36 2RME4, 5 or 2XT8911)

d. Process Flow Rate Monitor (stack) 1 (1RM-1FA8603,

• 32 2R1M-2FA8603)

e. Sampler Flow Rate Monitor I (lRM-lFA17079 or SIPAS-IFA6863Z,

• 32 2RM-2FA17079 or S2PAS-2FA6863Z)

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 156

hi Salem ODCM Rev. 19 Lil ACTION 31 -

TABLE 3.3-13 (Continued)

TABLE NOTATION With the number of channels OPERABLE less than required by the Minimum Channels L

OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release: U a.: At least two independent samples of the tank's contents are analyzed, and' l

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valving lineup; L Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 32 - Wththe pumber of channels OPERABLE less than required by the Minimum Channels OP~iiBLE requirement, effluent releases via this pathway may continue provided the flow, L

rate is estimatedf at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 33 - Wjihi'the number of channels OPERABLE less than required by the MinimumiChannels OPER LE requirement, effluent releases via this pathway may continue provided grab L

samples are taken at le6stonceper!8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these sanIples are analyzed ifor aseous principal gamima' emitters atidjero* imifbof detectionirequired in ODCM CONTROL TBLE 4. i'-X 2.A, B','r.C Within hours,' Otherwise, s9up;end release dfradioactive effluents via this l

pathway.-r ACTION 34 - With the-mmberofcanneil's OPERABLE ls ihanreqid by thetMins OPERAB.LErequirement Aimmediately sus*end PURGPNG of radioative efflunts Via tisi' L

ACTION 36 -

pathway.-

With nm 'the ofhaels OPERABLE ses tdhan ad by E - ithfunm Cha s L

OPERABLE requireiient, e'iueiit-releasesyvidthis pathwaiy.'may continue provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2. +s L With the number of channels OPERABLE less than required by the Minimum Channels ACTION 37 -

O1tRABLE requirement, Containment Pressure Reliefs may be performed provided that pior' to:initiating the release:

U

a. At least two independent samples of containmientare analyzedsn

b. At least two technically qualified members of the Facility Staffinependently verify thed release rate calculations.

..Otherwise, suspend release of radioactive efflueretvia thispathway,.

• At all times, other than when thi'line is valved out 'and locked.

U During Containrimnt Purges OR Containment Pressure - Vacuum :Relief AI'PLICABILITY": -

Mode¢s 1-t6, R44fAD Monitors p-roviding Alirm and Automatic<nination ofCelase, ory U

Modes 1-'5, R1'2A Monitor providing:Alarm"and Automatic Teiation of kelease or Mode 6, Rl2A Monitor providing larm only (Automatic Tiination of R elease is not required).

During Mode Undefined Defleled) operation, containment purge is reclassified a 'a building ventilation L

processstream monitored by the PLANT VENT HEADER SYSTEM.

1. During movement of irradiated fuel within containment with the Containment Equipment Hatch OPEN, only R41A/D canbe credited 'for MINIMUM CHANNEL OPERABLE.

L During movement of irradiated fuel within containment with the Containment Equipment Hatch CLOSED, R4lA/D or RI2A 'may be credited for MINIMUM CHANNEL OPERABLE. U Page 26 of 156 UI

Salem ODCM Rev. 19 TABLE 4.3-13: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVIELLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor - Providing P P R(3) Q(1)

• Alarm and Automatic Termination of Release

2. CONTAINMENT PURGE AND PRESSURE - VACUUM RELIEF

a. Noble Gas Activity Monitor P P R(3) Q(1) **

3. PLANT VENT HEADER SYSTEM#

a. Noble Gas Activity Monitor D M R(3) Q(2) *

b. Iodine Sampler W N.A. N.A. N.A. *

c. Particulate Sampler W N.A. N.A. N.A. *

d. Process Flow Rate Monitor (stack) D N.A. R N.A. *

e. Sampler Flow Rate Monitor W N.A. R- N.A.

• The following process streams are routed to the plant vent where they are effectively monitored by the instruments described:

(a) Condenser Air Removal System (b) Auxiliary Building Ventilation System (c) Fuel Handling Building Ventilation System (d) Radwaste Area Ventilation System (e) Containment Purges & Pressure-Vacuum Relief Page 27 of 156

JM Salem ODCM Rev. 19 L

TABLE 4.3-13 (Continued) L TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolationtIf 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. (Lossof Power) '. ,. U

3. Instrument indicates aidownscale failure. (Alarm Only)

(2) The CHANNEL FUNCTIONAL TEST shall' adlsodembonstrateVlthat controlroom airm1 annunciation occurs if any of the follWing conditions exist:' I"

1. Instrument indicates measured levels at or above the alarm/trip setpoint. '

2. Circuit failure. (Lossof Power)

3. Instrument indicates a'downscale failure.

(3) The initial CHANNEL CALIBRATION'w'as ;perf6rmd using pproiate liquid or' g ous calibration sources obtained from reputable suppliers. The activity of the calibration'sources were reconfirmed using amnulti-'channel analyzer which was'calibrated using one o6i ore'NBS 2 U

(now NIST) standards. ,

• At all times

• • During Containment Purges Ok Containment Pressure - Vacuum Relief';

Surveillance requirment -, ,,

Modes 1-6, 'R41 Monitors providing Alarm and Automatic 1'eiminaion of Release Modes 1-5,' R12A-Monitors roviding Alarm and Automatic Tem at'ioniofRelease Mode 6, R12AMonitorsproviding Alarm only (Automatic ion of Release L

is not required).' is as aJbuildin During Mode Vi4idefnd (Defueled) operation, contaimnent purge is reciassified as a building; ventilation pioce ss'trieam monitored by the PLANT-VENT ADER STEM.

During movement of irradiated fuel within ontainment with, tContainment Equipment Hatch OPEN, onlyR4AIcan be credited for MN M CHIANNEL OPERABLE.

During movement of irradiated fueiwithin Qonimnithth~ Contalnment Equipment Hatch CLOSED, R41A/D or R12A ma~be credited:for MINIMUM CHANNEL OPERABLE. U 7U LI Page 28 of 156

Salem ODCM Rev. 19 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION CONTROLS 3.11.1.1 In accordance with the Salem Units 1 and 2 Technical Specifications 6.8.4.g. 2 and 3, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (See Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 104 microcuries/ml.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, without delay restore the concentration to within the above limits.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analyses program in Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the ODCM to assure that the concentrations at the point of release are maintained within the limits of CONTROL 3.11.1.1.

Page 29 of 156

l  ! i:: i: i Salem ODCM Rev. 19 Li TABLE 4.1 1-1: RADIOACTIVE .IOITTD WASTE SAMPLING AND ANALYSTS PROGRAM U Lower Limit Liquid Release Sampling Minimum Analysis Type of Actiywt - l of Detection lD) '

L A. BatchWaste Type Frequency P

- ' I Frequency P

I '

Analysis

- -: ' - '- -J (ptCi/ml)

) "' '~'

L U

I . jr ' tI  !

Release:.: . .Each Batch.: Each.Batch 'Pfrin'ipaltGamrha"v'l i ".,

,1

, .! 1.:i r

,f 1 ., %

i 4

.Mt1

I- -1 Tanks;  : t li 'fi~t'> f':",§"l4 j '

'," .

',,YEZ4"t4 ~ 4/i '

er 4 S x to j, ", lv0 t-,

I PtY' 44Ji":. i1 'kf I I t,tt P M Dissolve and ~,

One Batch/M Entrained Gases (Gamma Emitters) 4 P M ,H3 10

-- w*u 4:  ;"Eadh,`Bat`b h _ __ __ __ __ ___ _ __ __ __ __

L Gross Alpha lx107

- Q-1,1"'

L I .-,d

.--. , i , , .~-

.- i ,.

hB c - ,.Sr-89, -Sr-9 8.

pn "'

"U I I'"lt' t

Eac Batch;5

~

.-iti.l-; i'tS f-: i I~i :,,II' 3T 1 jI

! -i . .1 1 v 1 ll;-,1C1- - Obs I I'A I.

Fe-55 4.

t >flxij "I-' 4'>;

016,61." "' ifI, ,0~

`rl l5 rl fIr F;;'

I

,  ; . i., '

l ,, . ,',..;

,f..E.

r..S

- 1i. i, l ~

D ,'; i-0 Ij, 4,/ ; '

. \  ; Y. _ .' '.:

h' I I,j . > 44 4 ,

.4 r ._

.U ,

,f j S ,4. :J ll,?, I 11 e,' Ar T - i B. Continuous"i, 1 4F t '" " i,1 Principal Gammai r

,-,r,,,,, 5,_,

l I Ili, j I 1I j r Jj , , f r ,,..1 , , - , ., 7 .

Releasese X10, w w EmIttersc Grab Sample

1. Steam Generator L Blowdown 1-131 lx10-6 U Grab Sample M M Dissolved and Entrained Gases lx10 5 U

W M H-3 lxl(O5 Grab Sample Composited Gross Alpha lxl10 7 w Sr-89, Sr-90 5xl O8 U

Grab Sample Composited Fe-55 lxiO06 L

Page 30 of 156.

Salem ODCM Rev. 19 L 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)

L that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

L For a particular measurement system (which may include radiochemical separation):

L L LD= EeV 2.22E6.YSb exp(-2At)

L Where:

LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit L mass or volume),

4.66 is the statistical factor from NUREG 1301 L 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),

L V is the sample size (in units of mass or volume),

L 2.22E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

Xis the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.

Typical values of E, V, 4, and At should be used in the calculation.

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

Page 31 of 156

Salem ODCM Rev. 19 TABLE 4.11-1 (Continued)

TABLE NOTATION L

b. , ,Achrelease is te discharge of liq~id waites f a dis ue;P io to sampling for analyses, each batch shall be isblated, and then thoroughly mixed to assure representative sampling.

t~l ti .i v j.; ' i'

,,Z d,- jZUt

' t- l ' Z

c. The principal gamma emitters for which the LLD CONTROL applies exclusively are the following radionuclides:;Mn-54, Fe-59, Co-5$; Co-60,s Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144*. This list doi-s"n iit-hatonithise'nucdideis e` t6 be detected and reported. Other peaks that arleasurabfe and identifiable, together with the above nuclides, shall also be identified and reported. l

d. A composite sample is one in which the quantity of liquid sampled is proportional to the ani"htf of 1d a dd "'nw1hhth6id 6 swtnPo of sinil1ip results in a specimen that is representative of the liquids released.

e. A continuous release is the discharge of liqUid wastes6of a nondiscrete-volumee g from a volume of a system that has an input flow during the continuous release.

5 tr l i 4': SB

. %iv -I *; :I .3 t  ;.i i 3,

-i' ;t *1i t. I [ F ii/ '

LI The LLD for Ce-144A0 s i ef2xl 0-l' 9ia ,

/i ttftt-,*izi i

ii ri, , t4 r??'iIlg1-1t M\u8<

I 1'?

L Page 32 of 156

Salem ODCM Rev. 19 3/ 4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.2 DOSE CONTROLS 3.11.1.2 In accordance with Salem Units 1 and 2 Technical Specifications 6.8.4.g.4 and 5, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

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

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days.

Page 33 of 156

Salem ODCM Rev. 19 3/4.11 RADIOACTIVE EFFLUENTS , U 3/4.11.1.3 LIQUID RADWASTE TREATMENT CONTROLS

.i 3.11 .153, I-n, accordance withthe Salem Units 1 and 2Technicl ,SpeoficatiQns6I8Aiqg6 the L liquid radwastetreatment' system shall be use'd t$reduce teradioactive materials liquid wastes prior to theirdisadhargei whenithehprojected cumulative dosesdue to the liquid eflent from each&I reactor to UNRESTRICTED AREAS (see Figure 5.1-3j exceed 0.375 mrem to the total boy or 1.25 mrem to any organ during any calendar quarter.

U APPLICABILITY: At all times. 1UJ, ACTIOIY.4, r- j J / ta - r a ,i !a l'a'aP Vi

a. With the radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 304ay;,

Technical Specification 6.9.2, a Special Report that includes the following d rs uant tc , L information: >

1 ,t:xp1"nationofwhiiq uid radwaste, was bding dischirgedwi.ut treatment, Li

' - iidentificdtion of any inoper'able e;-quipment or. -subsystems, idhe reason for

, th opeabilit . ' f L aa' ' ^'r;L '; j

,-1,2 , a -Action(s)

taken to restor the inoprable equipment . toOPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

ifi:

a'>i  ;.  ! ait  : .livs a; ,, , 7 , , p ta ,,<at j ,, z af i

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

SURVEILLANCE REQUIREMENTS a ,,, ,j , tj i t { ,i- *-f3 i jJ JftrI ~ i ;s i.st-i 4 i ii a iiit jj ,wfl a

, ,;; s o a?,I 4.11.1.3 Doses due to liquid releases shall be projected at least once per,3,1,1daysin acordanfcel ,

with the ODCM. L L

U Page 34 of 156 jt

Salem ODCM Rev. 19 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE CONTROLS 3.11.2.1 In accordance with the Salem Units 1 and 2 Technical Specifications 6.8.4.g.3 and 7, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and

b. For iodine- 131, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate(s) exceeding the above limits, without delay restore the release rate to within the above limit(s).

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined continuously to be within the above limits in accordance with the ODCM.

4.11.2.1.2 The dose rate due to iodine-131, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

Page 35 of 156

Salem ODCM Rev. 19 L

F.

TABLE 4.11-2: RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum ofDetection D.

Gaseous Release Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis (PC,_ '___'

A. Waste Gas Storie '

P ach Tank 'T P

riicipal GiniaI i'I' L B. Containment 1tA ,

~PURE 1~ I'-

cPrincipal P

6Ec1~RGB "

P IMEachPURGE~~mtes~~ I a- .

Gamma lxlO I .II Lf0' e,,, ,;,,, ;0*l1" o' ts+

-;'-0t0, U

GrO--,17s

'ab Sanpl a GE a s (h L

C. Planu en Above Grab Sample MP Pricipal Emitters Gamma 1xlO 4 L

H-3 1a 0 L

f D. All Release Continuous ' I-13 1 G1xito Types as Charcoal.

B,and C L Above _______

ofo W Particulate Principal Gamma Emittersb lxi 0' 1 U

Sample (I-43 Others),

Continuousf M Gross Alpha' lxi011 L vCompositeo G B or at a Sample L a Ti1 6Confinuos VSr-89,"Sir-Qi Q

1,a, 1 f

'i 0110 U

omaposite L

,C fa '.1~a Particulate Sample _________

Continuousf Noble Gas Monitor Noble Gasses Gross Beta or lxlO61 L Gamma Page 36 of 156-L

Salem ODCM Rev. 19 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 I-131 concentration in the primary coolant has not increased more than a factor of three; and

2. The noble gas activity monitor shows that effluent activity has not increased by more than a factor of three.

d. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.

e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool.

f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with CONTROLS 3.11.2.1, 3.11.2.2 and 3.11.2.3.

g. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER change that, within one hour, exceeds 15 percent of RATED THERMAL POWER and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if (I) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased by more than a factor of three.

Page 37 of 156

Salem ODCM Rev. 19 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.2 DOSE - NOBLE GASES CONTROLS 3.11.2.2 In accordance with the Salem Units 1 and 2 Technical Specification 6.8.4.g.5 and 8, theL air dose!due tnoble gases tpel itfgseotsteffluents, fro creactor unit ro r h ite areas and beyond the SITE BOUNDA (ee Figi 5.-3) shall be lited to the following:

';t'a'Ji.i DurinUri' a ldar rr ess tr equalt r fraia in and l ,1,'es thiDay i1oi~q ~ t ldI arE410 mrO d fdr betarai atiox f7--i an,:

i -,`irit'i a0l-g$

'h5-di'  ?¢to-t7 2 riai, ^;W ?VPiarffitaxai'

.? i 1-* 'i6;iial; tnzin

b. During any calendar year Lessthan or equal to 10 mrad for gamma radiation and less thanm orqual to ,20 rad forb etaradiatii 2 ii j, APPLICABILITY: At all times. A9 I7;

a. With the calculated air dose from radioactive noble gases in gaseous effluents

• 'xceedingany of te above liiiitsprepare and submit to the Coiisionithin 30_

days, pursuant to Technical Speification 6.9.22, a Speciala wRert thatidenti fe s the cause(s) for exceeding the limit(s) and defines th corrective actions that have been taken to reduethe treleasie'and the prop osedrcoreiveadtionstbceakento- assure that subsequent releases will be in compliance with the abve imiits. i ? j b.e0L 3The pr6visions ofCdONTROLS 3. 03ad 13 0.4 d'rbn6tIapp I'cablef`

i i i 1ti1 4.11.2.2 Cumulative dose contributions for the bu'rirt clendar quarter anrd cur tcaendar year shall be determined in accordance with the ODCM at least once per 31 days.

L Y1 to I i ii , , v 1 'ti .,1 :I :. i  : I ;j  : I :;,; j; ,jf - ff if.. !f } 'L Page 38 'of 156

Salem ODCM Rev. 19 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.3 DOSE - IODINE-131, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS 3.11.2.3 In accordance with the Salem Units 1 and 2 Technical Specification 6.8.4.g.5 and 9, the dose to a MEMBER OF THE PUBLIC from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

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

b. During any calendar year: Less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from the release of iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

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

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine- 131, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the ODCM at least once per 31 days.

Page 39 of 156

Salem ODCM Rev. 19 3/4.11 RADIOACTIVE EFFLUENTS L 3/4.11. 2.4 GASEOUS RADDWASTE TREATMENT ' L CONTROLS 3.11.2.4 In accordance with the Salem Units 1 and 2 Technical Specifications 6.8.4.g.6, the GASEOUS SADWTESRATMENTSYSTEMand eVENTIL -NEXHAUST L

TREATMENT SYSTEh-S ahall beused to reduce rdioactivemaerals in gaseous waste prior to3 their discharge hehepoet seouseff irses due to g aseous effluent relens'.,

from;thesiteto a be ynd e 9STB A R seeFi 5.1-),'Jexc'ee 0.625 mrad for gamma radiationdand 1.25 ioradnfor beta radiation in any calendarquater Th e' VENILATION'EXHAUST TREATMEN' SYSTEMshall be used to reduce radioactive materials in gaseouswast eoprior to theft dischargeswhen the :proj 9cted doses due to gaeous effluent releases, from each reactortunit, from the site to'areas at aid beyond the SITE, BOUNDARY (see Fi:igure 5:-3 would  :) teed15emo e an orgta iyi calendar quarter.

APPLICABILITY: At all times. e ii. L ACTION: "O

a. With gaseousiwastew bn disoharged withouttreatmentain exces of he above,

. ,'e..S'1i4,:pX~~tethic lmits,. preppar~ n umtt e Cm isinwiti~ ~ 30" h aitaytu e ttoTchnical i Spec',;ifcahti o' , ' Specal

,a Repor tat includes the fwigi on:,

i9 r'ih' x n of khy A` b' .dhe Lt, t ygaseous radwaste was.being discharged withoutreatment, id ii j1 fi~cation ent. any inoperableequipenrsbsstemsa reason for the L

2. Actioh(s)' itaen to restorethe i'on' rble ipmenIt:to O1'ERA BBA E status, and L

3. Summary description of action(s) taken to prevent a recurrence. L

b. The provisions of CONTROLS 3.0.3 and 3.0.4 arent applicable. I'i Y r~'r SURVEILLANCE REQUIREMENTS' '..' s

" S., .rj L 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. L 4

Page 40 of156'b

Salem ODCM Rev. 19 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4. In accordance with Salem Units 1-and 2 Technical Specification s 6.8.4.g.11, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem).

APPLICABILITY: At all times ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of CONTROL 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b, calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the limits of this CONTROL have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

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

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with CONTROLS 4.11.1.2, 4.11.2.2, 4.11.2.3, and in accordance with the ODCM.

4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage shall be determined in accordance with the ODCM.

Page 41 of 156

Salem ODCM Rev. 19 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING, 3/4.12.1 MONITORING PROGRAM Y CONTROLS 3.12L.1 tIn iaccordane with Salem.Units 1 knd 2' Tedhnicial Specificidtons6.8.4.h1, l.the J

radiological envirnmehtalonitoringprgam sal es'conducted as specified in'Table 3.12-.

APPLJICABI'ijAt alltitmes; t-,,j r','

ACTION: U

a. With the radiological environmental monitoring program not being conducted as specifiediin Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological' Environmental' Operating Report required 1by Technical Specification 6o.9.,7,.a, descripti t s r not conducting the 'Proramasx ired and the plans frpreven ing a re ene.; 5- 1U,

,b.i W-ith thie level of radioactivity: as; the resuit of plat effluents inaeronmental ri i-samplingmedium atwaspecified locationhexceeding thereo gleveisofTable L S3'.12, when-averagedoer'ncalenarquater prepand s i-'f."'i~f~ to he

FCommission wPithin 30 dayspursuat to Te'chnica ecification'6.9.2, a Special R that identifiesthecause(s).for exceeding the limit(s)iandefinestheU

.. eport F orrectivea s to be tak to ucead e tss tential

- .~. a dose*t; to a MEMBER O MFTHE-PUBLI is less an ' calendr year limits

':/s-

,, vJ of CONT R OLS 3. 1.1.2,liit3.s1t2.2;nd3A 1.23; Whemorehan othe in Table ,3..12-2 are detected in the;sampling mediu thi report shall

'ftit.5.i1

*tradionuclides

<b~e~subinited-.if:, iir t¢ltilf 1 ' ~/i 'b'S' ', rf>ii ^ "xs L' cfonctre Y ntratii

,f'l.;ni;ski.j~ ~cn.1) enfaior(2 $;1 - ii t'Cir j

,t,  ; r. t90*'!i

, Li j ~ 40i' 'C i^{tf7;t;;tt'.t'

' P~L;:

Yn. . t<21.,

.ot .. epi gleel'(l)'rp  :  : - retingleve1(2y' rrvo Wvren aitnce otne~rihtnan noe im'Taul1e 3.l2-2.are letectdM anid a~re the result of plant effluernts, this report shall .be -submitted if the potential annual dose* to a U.

MEMBERI'OF AIHE PUBLIC fdA' tallrdioniiilldes is-equa1 to or greater than the i calendar year limits of CONTROLS 3.11.1.2, 341 .2.. an, U, j 3 Thisre,,o rts '

not inM :required the if the measuredEhlevelfitjue~all~ai' A buF",11td~ioLgical of radioactivity up'Atids-i ie~resul of plant noi th pu'rsuantd wasReporat1 to an' h effluents; l au~i

[,: -.! i  !' however,

,<,ii, ,lI .l , in such , - ,Ian) ifevent, l , ,,- r j - '$i ~,.t k;, j . I shall the1 *condition r,",-, j,, bet~j

,e,, , i,p (-: and reorted fiifi. described

, . ,,)" L'

• The metodology used to estimatsrthepential annual dose toi a MEMBER OF THE PUBLa ICn shall be indicated in this report. U Page42 of 156

Salem ODCM Rev. 19 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 envirom-nental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Technical Specification 6.9.1.8, identify the cause of the unavailability of samples and the new location(s) for obtaining replacement samples in the next Radioactive Effluent Release Report. Include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

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

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

Page 43 of 156

Salem ODCM Rev. 19 TABLE 3.12.1-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

• EXPOSURE PATHWAY NUMBEROF REPRESENTAIVE SAMPLING AND.'- TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTIONY OF ANALYSIS LOCATIONS ()

1. DIRECT RADIATION (2) Forty-nneronutine monitoring -- Qu ae --

Gamma dose quarterly stations with tWo or more dosimeters placed as flows: -

An inner 'ing.of stations one in. each land based meteorological sector (not bounded by water) in the general area of the SITE BOUNDARY; An outerring-of stations, one in each- k: ,,

land-ba s dinteorological sector m .

the 5 to 1 l4kii range from the site (not boundby or oydr water) _and .

The balance of the stations to b6' placed-in ial interest areas such aspopulation centers, nearby residencesldhoolsan,a in oneor or two areas-to-serve as colnsttions..

tr~ f =Er e , ';.,. e ._ese 0 <,~0a . ,s

• The number, media, frequency, and locationotsamples may vary from`site to site Tis table presents an acceptable minimum program for a site at which each entry is applicable.- Local site ctiacteristics must be examined to-determine-ifpathw'ays not covered by this table may significantly contribute to an indi.iual's dose and shoud be included in the sample program.

..... 6'u en shul be inlue In v7 r ric- r-, r= = = = 7nageV~1.f ' 5t-,r --r- c 7 r. ---- zr tic = rz: uI-

C Salem ODMRev, 19-Salem ODCM Rev. 19 TABLE 3.12.1-1 (Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTAIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION OF ANALYSIS LOCATIONS (1) FREQUENCY

2. AIRBORNE Radioiodine and Particulates Samples from 6 locations: Continuous sampler Radioiodine Canister I-13 1 operation with sample analysis weekly.

collection weekly or more frequently if required by dust loading.

4 Samples - One sample from close Particulate Sampler Gross beta to the SITE BOUNDARY location radioactivity analysis following and Three samples in different land filter change (3);

based sectors of a high calculated annual average ground level D/Q One sample from the vicinity of a Gamma isotopic analysis(4) of community having a high calculated composites (by location) annual average ground- level D/Q; quarterly.

and One sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction.

Page 45 of 156

Salem ODCM Rev. 19

'TABLE 3.-12.1-1 (Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF SAMPLING AND TYPE AND FREQUENCY OF ANALYSIS PATHWAY REPRESENTAIVELSAMPLES - COLLECTION AND/OR SAMPLE AND SAMPLE LOCATI (1) -FREQUENCY II s: .rS J "I

3. WATERBORNE

a. Surface() One sample upstream Gr-ab sample monthly Gamma isotopic analysis(4) monthly. Composite One sample downstream  :-', *4 q y- :

for tritium analysis qarterl-y One sample-ou: h One sample crossttea t . -

b. Ground Samples from one or two sources Monthly 5'Gamma isotopic analysis(4) monthly and tritium only if likely to be affected(7}. y'ansisqarterly.

c. Drinking~' 0 ) One sample of the nearest water Composite sa'mple- - -131 anaysis on each composite when the dose

supply affectdbyits dischar -- over two-week calculated for the consumption ofthe water.is period(6 ) whenI-1-31 greater than 1 mrem per year(8). Composite for analysis is performed; grosswbeta and gamma isotopic analysis( 4 )

monthly composite monthly Composite for tritium analysis quarterly otherwise. .6#4-f-C

d. 'ediment One sample from downs treamarea- emiannually Gamma isotopic analysisO4 )-semiannually

-Onesample pfoncos-team area, ~~~~~~~~~~j, ,-,,,-7,t, Y* ; t--.R=

One sample from outfall area,-'

One sample fromupstem are -

One sample from a control location One sample from shoreline aread-One sample from Cooling Tower Blowdown i-77 r_-7 r z- rz-, r_7 r_ r_-.l f= age ~f 15t= - - rir rim rim ri r_-_ u-.-

U7 r___" C-117 r-1 U177 r__711 U" r-"r" r= r_"' u"17, t"7 UIF7 r"_ r-"-- r_7 r'1177 U7 Salem ODCM Rev. 19 TABLE 3.12.1-1 (Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTAIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION OF ANALYSIS LOCATIONS (1) FREQUENCY

4. INGESTION

a. Milk Samples from milking animals in Semimonthly when animals Gamma isotopic (4) and I-131 three locations within 5 km distance are on pasture, monthly at analysis semi-monthly when having the highest dose potential. If other time animals are on pasture; monthly there are none, then, one sample at other times from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr(8).

One sample from milking animals at a control location 15 to 30 km distant.

b. Fish and Invertebrates One sample of each commercially Sample in season, or Gamma isotopic analysis(4) on and recreationally important species semiannually if they are not edible portions.

in vicinity of plant discharge area seasonal One sample of same species in area not influenced by plant discharge.

Page 47 of 156

Salem ODCM Rev. 19 tUi--! i

-- -AT- :;B LE. 3.

-312.1 -1 1 (Contd)

C RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF-: - TYPEAND FREQUENCY SAMPLING AND OF AAYSIS ANDIOR SAMPLE` REPRESE V SAMPLES AND SAMPLE FREQUENCY LOCATIONS (f)

c. Food Products One sample of each prncipal At time of harvest (9) Gamma isotopic analysis (4) on class of food products from a edible portion.

aethtis iriae a'i IrrIgat' TV yater wbh liquid plant w na bee rsc z+n,asT.tesha beenm argecN= rF

'5 s .' "' r S-> : ,,,5, ' i'

- I;. .  ; I r i~1 k I ,

11 11

, ]- I . %

1 4 11 ~ - - .,I K-7 r7-- r=1 r= r-I rrn rmrinrirrim U-7 I= rim U rim r_-,

r7-- ri U--- I

Salem ODCM Rev. 19 TABLE 3.12.1-1 (Continued)

TABLE NOTATION (1) Specific parameters of distance and direction sector from the centerline of one reactor, 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-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Reg. Guide 4.8 as amended by Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.

In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Pursuant to CONTROL 6.9.1.8, submit in the next Radioactive Effluent Release Report documentation for a change in the ODCM including revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for the pathway and justifying the selection of the new location(s) for obtaining samples.

(2) One or more instruments, such as pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.

For the purposes of this table, a Dosimeter of Legal Record (DLR) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used for measuring direct radiation. The frequency of analysis or readout will depend upon the characteristics of the specific dosimetry system used and should be selected to obtain optimum dose information with minimal fading. No direct radiation monitoring stations are located in the inner ring sectors 8, 9, 12, 13 and 14 and the outer ring sector 8 as originally determined during plant licensing and as permitted by Reg. Guide 4.8 as amended by The Branch Technical Position Revision 1, November 1979.

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

Page 49 of 156

Salem ODCM Rev. 19 U

TABLE 3.12. 1-1 (Continued)

TABLE NOTATION U (5) The '7up~streatm sample't shall-.be .taken,at a ditance .................. beyond -signiicantifl~~e.'ofthe ...........

.i': hrge. "The ."dciwistream"l >saleQ shaall;be a en inian !areabeyondbut nearthe' U mixing'zone.,Upstream'samplesin anestuary mnust be, akin& farnoughvpstream to be beyond the plant ihf luence.-Saltwta tersilbe sampled ly wen tefreceiving Wateris V utilized for- ecreational eaceivisties (6) A siomnpositespe.is`,ne which the qtanity ai'qut of liqud

-t the quanti of hfklwingl liquid inwch temet andI'd led is proportional ofysapiigtenploed results I U spe en that isrepresentative f quidflow. ths6progrmcomposte .sample

-dliquts hll ,be collected at tieintevals that are very short relai4 the siting period in ordei tssure.otainingd&a representatve sa ple.

(7f) roundwater sampslesshall be taken when thi~ssourctis ,tappedfor,drnki ngaogation L purposes in areas re hydraulic grdient oriechar prope e le for acontariination,.,. i a (8) The dose shaallbe calcuIlated for.the maximi oi~gan andage'group, using the a!methodologyand parameters in t ODCM Addiionally;2Sample ocations are .

monitored as management audit.,Broad leaf vegetation iay be obtained 'inleofmilk t ' t a tsi ncollections i U

26ti 1 ria in aa4fff ¶4Ia aa (9) If harvest occurs more than once a year, sampling shall be performed during each discrete U

, h:arvestx': Ifharvest ocstzrs contiuly,' sampinng shall be monAly. fAttention shall be, yat the

.n.,paid to,icluding samples of tuerou

,location ofSaieml and

and toot food roducts.The. D lawareiver, ope Creek NlclearPofwer PlaI is a brackish water source. No irrigation bof food pro4ucts 'is pefrmed using 'water in the vicinityifomwhc liquid L

,&,l plant Wastes have been dischared. .However,4 12 manaementaudit foodampes are ,

cl~tlec4ted: m a ,

a'slc ' a, a,^iN  ;', ................. t,,Ci >0,0~',jifj irQ;i:.........

i '- a 'ft j, 5t .

a1 ti, f , mjfa,.f4

/j44  ; fr au (10) No groudwater shamles b are required asHliquid s discharged omdal .nd alf' .aHopie Creek G(enerating S~tationsisdo noft directlya af~fect this pathway.,.'However for U managemecnt adit, o~ne raw tand one:.treated ground Swater sanile-from te nearestri unaffected wate supplyr is required,; ,, t.

a t L ath

't ' , ;

are;e~aigitt a C sp f t We a U Page, 50 of 1I561

o5 r7 F C F O Q F3 F3 r7 Salem ODCM Rev. 19 TABLE 3.12-2: REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS Water Airborne Particulate Fish Milk Food Products Analysis (pw1 or Gases (pCi/m3) (pCi/Kg, wet) (pCi/l) (pCi/Kg, wet)

H-3 3x10 Mn-54 lx103 3x104 Fe-59 4 x 102 1x 104 Co-58 Ix103 3 x 104 Co-60 3 x 102 1 x 104 Zn-65 3 x 102 2 x 104 Zr-Nb-95 4 x 102 I-131 20 0.9 3 1 x 10 2 i .. -. X 103 Cs-134 30 10 1x 103 60 1x103 Cs-137 50 20 2 x 10' 70 2 x10 Ba-La-140 2x-10 2 ------

-- -  ; 3 x 102 Page 51 of 156

Salem ODCM Rev. 19 TABLE-4.12-1: DETECTION CAPABILITIES FORENVIRONMENTAL SAMPLE-ANALY )-

LOWER LIMITS OF DETECTION (LLD) (3)

Water Airborne Particulate Fish Milk Food Products Sediment Analysis (pCi/l) or Gases (pCi/m3) (pCi/Kg, wet) (Ci/l) (p~i/Kg, wet) (pCi/Kg, dry) gross 4 1x10; 11-3 3000' Mn-54 15 130 Fe-59 30 260

-CO-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-131 10 7x 102 60a Cs-134 15 5 xO 1&.

.- = 30 -- 15 I50  :.

Cs-137 18 6 x1 2 150 18 80 180 Ba-La-140 _ 5 __ _.- 15i--_

ri rUr-_ = - - ~nC= iPag2of"Y6~n r--r--- = r:=m rim urnri rim vii

Salem ODCM Rev. 19 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 Sb E

• V

• 2.22E6

• Y e exp(-AAt)

Where:

LLD is the "a priori" lower limit of detection as defined above (as picocuries per unit mass or volume),

4.66 is the statistical factor from NUREG 1301 Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per disintegration),

V is the sample size (in units of mass or volume),

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide,i and At for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.

Typical values of E, V, Y, and At should be used in the calculation.

Page 53 of 156

Salem ODCM Rev. 19 TABLE 4.12-1 (Continued)

T B,E N T, T . N L

TABLE NOTATION L

It should beirecognized that the LLD Iisdefinedas .an g prigrn (before the fact) limit representing th"' ,

capability obf ai asureent systeni and aiti s an aostedpoti(after the fa)lImit for apartiular measurement. Aiaalyse shaill be perfor ein, d sucdi axanne th he stated: LLDswill be, achieved,.

under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes the presence, ofinrfeJrn niiclides,r oth ionftrllabtfeirc umSyetyredrth~sesefLLsiDsI unachievle stributing factors shall bde ientified aes ed i the Ahnua-l, Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7

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Salem ODCM Rev. 19 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2. In accordance with the Salem Units 1 and 2 Technical Specifications 6.8.4.h.2, a land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m (500 ft 2 ) producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in CONTROL 4.11.2.3, identify the new location(s) in the next Radioactive Effluent Release Report, pursuant to CONTROL 6.9.1.8.

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

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

• Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Q in lieu of the garden census. CONTROLS for broadleaf vegetation sampling in Table 3.12-1.4c shall be followed, including analysis of control samples.

Page 55 of 156

Salem ODCM Rev. 19 3/ 4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS (Cont'd)

U SURVEILLANCE REQUIREMENTS '

The land use census shall be conducted during the growing season 4at least' on'ce pper .12 Wmonths,' f 4.12.2 such as by a door-to-door survey, visual survey, using that information that will provide the best results, The results of the land use census shall be.

aerial survey, or by consulting local agriculture authorities. Reportp'ursuant'to'CONTROL 6.9.1.7.

includ'ed inthe Annual RadiologicalEnviroiiental'Operating 4

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Salem ODCM Rev. 19 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 In accordance with Salem Units 1 and 2 Technical Specifications 6.8.4.h.3, analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program. APPLICABILITY: At all times. ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7.

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

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7. Page 57 of 156

Salem ODCM Rev. 19

                                        ,. k. 4f A ^tN ,;

BASES SECTIONS 30AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS NOTE The BASES contained in the succeeding pages summarize the reasons for the CONTROLS of Sections 3.0 and 4.0, but are not considered a part of these CONTROLS. Page 58 of 156

Salem ODCM Rev. 19 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 IR18 Activity lb Steam Generator Blowdown Line lRl9A, B, C, and D(l) Gross Activity 2a Containment Fan Coolers Service 1R13 A, B, C, D and E(l) Water Line Discharge Gross Activity Unit 2: T/S Table Item No. Instrument Description Acceptable RMS Channels la Liquid Radwaste Effluent Line Gross 2R18 Activity __ lb Steam Generator Blowdown Line 2R19AB,C, Gross Activity and D(l) 2a Containment Fan Coolers - Service 2R13A, B and C(l) 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 156

Salem ODCM Rev. 19 3/ 4.3 INSTRUMENTATION L BASES L 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The rdioactive gaseous ve aaeffluentrenis e!ddtomor The ~ to iandtol i e fti, I 1monis,s~pplicable, I a',rol the, I I riad1sTingpseoiais efuuns dunn ptentieasepsigaS ogseus, o s effluents. The arm/rp m s ha1 ccIlated nd, dstedin accordce wihlthe proedures in t CM tosur the amtriplto e xpeedingelseotf 10 CR Pat The OP L adusefthis icnsntis niAith te eiiimn of General Design Criteria 60, 63,, aid 4f ,App~endi,~A tv0l CR Far 505.0t i ' , Rtf 13 'J CROSS REFERENCE - TABLES 3.3-13 and 4.3-13 L Unit 1: t: i $ :1 - 2 I T/S1Table item No. In's,'trume'ntDescrip3'tion Acceptaible RMS Channls,, la 9 1 Wate Ga odp ytm 1R41 A axd 1(2 52 Noble Gas Gas Activity _____________________ _ 2a  ; Co,,taiment Purg-eand 1R12&, 2A ,

                                              * ~?~essureVac um ~Re ie                                    o No b`e Go Activity,(I(2 3a ~'lat                              Vet Uade~~Syt~m                               .4A~ai 13(1)(2)
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              . . ,,                 , l Particuae'Sainpler(3 o,,,................... . ,..:-.

3c 'Plant Vent Header System ' 1RME 4,5 .(1R41)

                                                                                                       ', or Ji  2f,(

(1) The channels listed are re d to be opeable tomeet a singlejoer ehannel for the ODC}

     "Minimum Channels Operable" requir~eent, ,,s (2)    1R41D is the setpoint chann'el'L1R41A is the 'measurmentichanniel                                                       : .,,

(3) Laboratory 'analysis of the sampler flters ensures tha the limits of ODCM CO L 3 not exceeded.

               . ;.; Hi    Alarm/trip    t+t j .. setpoints
                                , 's's'iXji'!   ;

not apply, to these

                                                          +1,4iH do At.iR t . . thj         WFi passive corppnepts.

nili,1 otl,,nlp p - titiq,.'i ii'. ' U

                                                                      -Page 60 of 156                                                                                     L

Salem ODCM Rev. 19 3/ 4.3 INSTRUMENTATION BASES Unit 2: T/S Table Instrument Description Acceptable RMS Item No. Channels la Waste Gas Holdup System Noble Gas Activity 2R41A and D(1)(2) 2a Containment Purge and Pressure - Vacuum Relief 2R12A or 2R41A Noble Gas Activity and D(l)(2) 3a Plant Vent Header System Noble Gas Activity 2R41A and D(l)(2) 3b Plant Vent Header System Iodine Sampler (3) RME 4, 5 (2R41) or 2XT8911 (2R45) 3c Plant Vent Header System Particulate Sampler (3) 2RME 4, 5 (2R41) or 2XT8911 (2R45) (1) The channels listed are required to be operable to meet a single operable channel for the ODCM's "Minimum Channels Operable" requirement. (2) 2R41D is the setpoint channel. 2R41A is the measurement channel. (3) Laboratory analysis of the sampler filters ensures that the limits of ODCM CONTROL 3.11.2.1 are not exceeded. Alarm/trip setpoints do not apply to these passive components. Page 61 of 156

Salem ODCM Rev. 19 3/4.11 RADIOACTIVE EFFLUENTS BASES L 3/4.11.1 LIQUIDEFFLUENTS I . L 3/4.11.;1 .1 CONEN AION-The CON1ROL is provide to eiisu e that the concentration ofradioacive mat eials released in liquid effl uets will be lessithan the cohcecnration leve-lse in n o ppendix B Tsble II, Columnf2. Tis.limit atis provides:.additional assurancelthat the lee dte materials L bodies of inl .TRIED A R wil ulti posures e tion II.A dein objetv "pesdix ,1 CFORi'Par 5_0,t:a MEMBEROF TEPUBLIC'and ('1he imits of 10 CFR Part 20,.16() o the population.4 The concenttl imfrdiss ed or e bgases is based upontheassumptionthat e-35 is the controlling radioisotope and its MPC in air cnequivalentconcentratonfin water .using themethods described in International (submersion) was K. L Commissiog8;n R;adiological Protectioni -(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 4 F ' ~ 3 4 -20 I 9 ' , .f 5;?4

                                                                               't                          '  I

2. 4M*1 st;Eeri L

lols This CONTROL'i's pr'o"vid~ed to-i im impkment mpg: thezf'L P hilt~y Appendix I. 10 CFR Part 0.TheCONTROLiiplenigents .thel g ides setfbith in Sec ion IIAo AppendixI. The ATION,, statementsPrithseequied f ibliand ate same time implement the guides set forth ini etion IV.A of Appendix Ito a material injiquid efluents will be -kbp "as low' as is reasonably achievable." Als, for freshwater sites o tio iereis:retab L with driningwatst concentratio6s in the inshedt assurance that the operation of the fac Wll wiitynot resuwt drinking water that are in excess of the requirements of 40 CFR Part 141. The dose c in radionuclid iliiis4in te L 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 L underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor L Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purposes of Implementing Appendix I," April 1977. The CONTROL applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among L the units sharing that system. Page 62 of 156

Salem ODCM Rev. 19 RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID RADWASTE TREATMENT The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This CONTROL implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth the Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents. 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This CONTROL is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 [10 CFR Part 20.106(b)]. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the individual will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC with the appropriate occupancy factors shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 nirem/year to the whole body and 3000 mrem/yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year. This CONTROL applies to the release of gaseous effluents from all reactors at the site. 3/4.11.2.2 DOSE -NOBLE GASES This CONTROL is provided to implement the requirements of Section II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The CONTROL implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be Page 63 of 156

Salem ODCM Rev. 19 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 ingaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine U Releasesi bReactorEffluentsforithe Purpose of Evaluating Compliance with 10 ;CFR 50, fAppendix I,"- Reion I, Octobe 1977 dRegultryGuide11 M eods fr Estating.tmosperiTanort and Dispersionn-of ;Gaseous Efflue" tsin Routine Releases from gt- ooled.-Reactfrs," Revision' 1, July 1977. The ODM q ions provided fordminingthe air doses at and eyond tlhe SITTE ir AY'e based 6BOpon thehistoricalaverage' atosp ericV ditins.

      ':t{"1 ' .'j: ' ' 4' t'iJ 1   i: . '6      '

3/4.11.2.3 DOSE - IODINE-131. TRITIUM, AND RAIOND

                                                    ':        {   4   2       0t   t      -0',     77.6-UVQLIDES INKPARTICULATFORM                         l L This CONTROL is provided to implement the requirements of Section':IIC,, IH.A andfViA o Append ix I, 10 CFR Part 50. The CONTROL are the guides set forth in Section fII.C of Appendix I. The ACTION statements provide the required operating flexibility and at the:same time implementitht&ldes sf in SectionIVA of Appendix Ito assure that, the releases of radioactive materal in gaseous effluents will U

be6 k i'p'!as'l wias isreasoinably .chial TeD M cclatinlods specifiein Stillance v Requirements implement theq irmenin Section III.A ,of Apdix Ithat co n e i th e U guides of Ap.endix I beshown byraiculational pr'cedures on models ad dthat 'based th actul exposure of a MEMBER OF TEPUBLICtrghappropriate pathwaysis unlikely torbe substantially t underestimated. Jh;e ODCM calcula-ti'onalmeiods for calculatinge'doses due.to the actualreaserates L of thesubjectmaterialsareconsistentwiththemethoology provid' edoinR ory Guide. '109, "CalTculation of AnulSDses to Man frm'Routinie Releases ofReao ffluns frhe Pups ;of;e.-. n Evaluating:omplia'nce with 10 'CFR0,Appendix I," Revis'ion1; Octoberd 977 an&d Reulatory3Guide U 1.1;ll "Methods for .Estmating Atospheric Transportand Disps oeous fuents ;i in Releases'from Light-Water Cooled. Reacors;" R evision 1, July 177. Tsee i so .pr for rdtermining tthe actu al do se basedup the iverage h ditions, The eleasen ,a;t cofitrols -for iodine-I 31, tritium,. and radionuclides in pIarticulate iform with half-ifegrear than 8 days. . are dependent the existing radionudlide p ys to man in threas at nd beynd ith SiTE BOUNDARY. The pathways-,tat'were examined inhe developentofthese calculations were:' 1),,. individual iinhalation of airborne .ionuclides, 2) depositionofra udes onto green lea egetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing'animals graze with consumption of the milk and meatbymn; :andy 4). depositinon the'ground with subsequent exposure of man. 3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The requiremeit, that the ppropnrate portions of this systemnbe ,used, when specified, provides reasonable U

• assuran'e that the releases of radioactiveimaterials in gaiseous ieffluents will be kept "!aslow as is t.

reasonably'achiev6able 1 'This CONTROL implements hie requemens ofIOCE Part 50.$6a., .tGeneral Design Criterion ,60 of Appendix:A to 10 CFR :Part 50 and the design objectives given intSection 1i0 ,of

'Appendix I to .10 CR'Part 5O.The 'specified limits governing the use oof appropriate portions ofthe:

U systems were specifieddas a suitable fraction.of the dose design objectives set forth in Section IlB and.;- II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. Page 64 of 156 U

Salem ODCM Rev. 19 RADIOACTIVE EFFLUENTS BASES 3/4.11.4 TOTAL DOSE This CONTROL is provided to meet the dose limitations of 40 CFR Part 190 that have now been incorporated into 10 CFR Part 20 to 46 Fr 18525. The CONTROL requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. 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 the reporting requirement level. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190 and 10 CFR Part 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in CONTROLS 3.11.1 and 3.11.2. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. Page 65 of 156

Salem ODCM Rev. 19 RADIOACTIVE EFFLUENTS  :.. X BASES 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING Ii~ The radiological "en'Jr" daIs I monng program reqIre& "hi-CONTRO Vidmeasurements oqMiEnRhio al epoue ofEBESOF3{ PBIC 'r,&sutin' rnt~~ tto imp emenseon Q og Tmay 6F4,.ppig ths perod, ro am cbImpes brits ini edceo: Sectionatnal _ exp'I,', sliimi ptog e *i.11f1IOIJffnd, th i; 4 IL ,

             .;        ,*qii ,;>v Im,*.; ",. L        'A                          I -.,:+   s, . It.f'i    i;   A         sfflo i'l: P5taI  V ;s     is          :xs)':

Mti aett for monin!joji a  ;>.parwayfaii a:> ,t frawat: l~ast th fir0;a;tykst4>~ th~y1rs coinier , TV: ioeaion. This CONTR lrboideo OL o r th that the useofi areas aI a____ _nh BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the; door-to-door survey, aerial survey or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: 1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) yield of 2 kg/ 2 . 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM This requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix Idto 10 CIR Part 50. Page,66 oof 156

Salem ODCM Rev. 19 SECTION 5.0 DESIGN FEATURES Page 67 of 156

Salem ODCM Rev. 19 L 5.0 DESIGN FEATURES 5.1 SITE L 5.1.3 UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS II 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 L Specifications Section 5.0 is controlling.) I

qs. p!F,- j-:n U

U U L L L L Page 68 of 156

UI r u7 OOer C7 fpr- r3O I UNRESTRICTED AREA (PROPERTY OF U.S. GOVERNMENT)

                                                                                  --      N                i NUCLEAR ADMINISTRATION                                                         i BUILDING                                                       ,

COOLING TOWER .' SECURITY FENCE;

       ,   II ,        I        I on                             1                                      SITE                      BOUNDARY-0:

• HOPE CREEK -t SECURITY H CENTER 2 PROCESSING CENTER SALEM I o SWITCH YARD '

v  ::rMETEOROLOGICAL i

                       --FEED WATER. &TO
                     ,    CIRC. WATER INTAKE       /

v ,S~TRUCTRE,, 0

                             --           =

DELAWARE RIVER

Salem ODCM Rev. 19 6.0 ADMINISTRATIVE CONTROLS. . 6.9.1.7 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.7 In accordance with Salem Units 1 and 2 Technical Specifications 6.9.1.7, The Annual Radiological Environmental Operating Report* covering the operation of the unit during the previous calendar year shall be submitted prior to May ;1 of each year. The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends ote results of the radiological environmental surveillance activities for the 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 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 pursuat. to the Table and Figures in the environmental radiation section of the ODCM; as 'ell 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 P'osition, Revision'1, November 1979. In the event that some individual results are not available forfinclusion with the repot, 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 secondtcovering 'themore distant.locations, all keyed to a table giving"dances and directionsfrom the centerline of one reactor; the results of licensee participation in the Interla ry Comparison Program, required by CONTROL 3.12.1; and discussion ofa lyses in whichte LLD required by Table 4.12-1 was not achievable.. 6.9.1.8 RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 Inmaccordance with Salem Units I 'pd 2 Technical Specifications 6.9.1.8, The Annual Radiological Effluent Releas Report* cov g the operati'onof the uI dring the previous calendar year shall be submitted'prioretoMay 1 of ea year. and in accordancerith the requirements of 10CFR50.36a. The Radiact el Reeas Rert shallclude a summa of the quantities of radioactive liquid and gaseous' els and solid wastreleased pm the unit as outlined in Regulatory Guide 1.21. "Measuring, Evalting, and Reporting Radioactivity in Solid Wastes and Releases of

• A single submittal may be made for a-multiple unit station. The submittal should combine those sections that are common to all units atte station; however, for units with separate radwaste systems, the submittal shall specify the reieases'bf radioactive material from each unit.

                                              . Page 70 of 156

Salem ODCM Rev. 19 6.9.1.8 RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. The Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form ofjoint 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. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977. The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

The Radioactive Effluent Release Report shall include a list of descriptions of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period. Page 71 of 156

Salem ODCM Rev. 19 6.9.1.8 RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) L The RadioaciveEffluet ReleaseRpoi ~shall include ani chan'ges made dung the, repiorting periodtoI the PROCESS 'ONTROL PROG M (PCP), theOFFSITE DOSE ALAT ION MANIUAL' (ODCM), or radioactive waste systems. Also list new locations identified by the land use census pu4rsuantto ,CONTROL,3J,:12.2. for dose,, calculations orenironmental monitoring 6.15 :MAJORCHANGES:TO RADIOACTIVE iLQUID.' 3GASEOUS ANDS'OLIDWIASTE-.i - i 6.1.1 icenseeinititated La j Ie: ande u id I-, n,

  ,;,t';'aSha'3lib'h ws
                                         ,eporwoted,,tothe Opi t

CpmisioRIi-0onthe U$SR orthepeperiod in i~n

                                                                                                                                                       ,biohtevluto was review ed bythe$StationQ'eiati~~o~ns.Review .Committee,(,:ORC)' Te dis                                                                      sion'ofech :ea changeshaliconai
                                         -d;
                                                                  ,?.i,> '1     it       3I 0        riX j'r i:t'0    i*;     i:i' G i
                                                                                                                                            'f;;;     -*'<      i;'   'j'3Vi~aL a            Auh                                         evafutift ht                              ehderzinaion that!fHe cn'ge-coub:

made in accordance with 10CFR50.59;-,.. 1 bt Sufficienttdet,,' inf6pmaf ton totptallyysupport thereason, foh ge wthout benef of additionator suppleental infonnation; >,,> j c A detalld descriptiohof the equipm. components';and jroes's'inIVoled` te r

                                ..interfaces.with other plant systems;                                                                                                                    L An e                    a            of the 9hange, wich shows ,hepe6dictd y releases and/aruai ns 0 asesp           of doat Wast    i,,     :S~.4              ~ L

[i5Et,,<t,;;tjma tenifls~mliqu qu;"d sedu-,efutfIl6;,;io.Xts'f'f ,Nfei

                                  ,l,;,'i'        previously predicted-in
                                                        ,thofse                                     the     licetse&applicationn       a'nd-      dmenshrto                       f t ep                       ly-peice               ingi~

e. An evaluation' wf:,r of the chane whichsosthe ex6te046ium~pou ,'Ai 'I toU ' l _E

f. A co~mparison of the predicted releases, of radioactive materials, in Slud fand ,gaseous effluents and ini-solid waste;It o th atualfreleases for the periodl.prior to wheniethe changes are to be made; w

g. An estimate of the exposure to plant operating personnel as a result of the chanse; and

h. Documentation of the fact that the change was reviewed and; fouhd iaicc~eptle 'by the SORC.

I in: I ' r

2. Shall become effective upon review and acceptance by the SOR.

1-.,.. 1 . .

                                                                                           ' ePage 72 ofi156                                                                              U

Salem ODCM Rev. 19 PART II - CALCULATIONAL METHODOLOGIES Page 73 of 156

k 1 Salem ODCM Rev. 19 1.0 LIQUID EFFLUENTS 1.1 Radiation Monitoring Instrumentation and Controls The liquid effluent monitoring instrumentation and controls at Salem for controlling and monitoring normal radioactive material releasesin accordance with the Salem Tecnical Spfications 6.8.4.g and L ODCM CONTRL i~inh~zdas flos

1) Alarm (and Automatic Termination) - l-R18 (Unit 1) and 2-R18 (Unit 2) provide the alarm and automatic termination of liquid radioactive material releases as required by ODCM CONTROL 3.3.3.8. L 1-RI 9 A, B, C, and D provide the alarm and isolation function for the Unit 1 steam generator blowdown lines. 2-R19 A, B, C, and D provide this function for Unit 2.

L

2) Alarm (only) - The alarm functions for the Service Water System are provided by the radiation L monitors on the Containment Fan Cooler discharges (lR 13 A,B,C,D and E for Unit 1 and 2R 13 A, B, and C for Unit 2). L Releases from the secondary system are routed through the Chemical Waste Basin where the effluent is monitored (with an alarm function) by R37 prior to release to the environment.

Liquid radioactive release flow diagrams with the applicable, associated radiation monitoring: instrumentation and controls are presented as Figures 1-1 and 1-2 for Units 1 and 2, respectively. The Liquid Radioactive Waste System is presented in Figure 1-3. 1.2 Liquid Effluent Monitor Setpoint Determination Per the requirements of ODCM CONTROL 3.3.3.8, alarm setpoints shall be established for the liquid effluent monitoring instrumentation to ensure that the release concentration limits of ODCM CONTROL 3.11.1.1 are met (i.e., the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2, (Appendix F) for radionuclides and 2.OE-04 ,uCi/ml for dissolved or entrained noble U gases). The following equation* must be satisfied to meet the liquid effluent restrictions: U C(F +f) (1.1) U f Where: C = the effluent concentration limit of ODCM CONTROL 3.11.1.1 implementing the 10 CFR 20 MPC (Appendix F) for the site, in ,uCi/ml c = the setpoint, in gCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, U Page 74 of 156 Ii

Salem ODCM Rev. 19 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 1.2.1 Liquid Effluent Monitors (Radwaste, Steam Generator Blowdown, Chemical Waste Basin and Service Water.

The setpoints for the liquid effluent monitors at the Salem Nuclear Generating Station are determined by the following equations:

                                <MPCe*SEN*CW*CF*AF1 SPR[jRkg(1.2) with:

Z Ci (gamma only) MP~e=(1.3) MPCi (gamma only) Where: SP = alarm setpoint corresponding to the maximum allowable release rate (cpm) MPCe = an effective VPC value for the mixture of gamma emitting radionuclides in the effluent stream (pCi/ml) Ci = the concentration of radionuclide i in the undiluted liquid effluents (ptCi/ml) MPGC = the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F) (pCi/ml) SEN = the sensitivity value to which the monitor is calibrated (cpm per PCi/ml) CW = the circulating water flow rate (dilution water flow) at the time of release (gal/min) RR = the liquid effluent release rate (gal/min) bkg = the background of the monitor (cpm) CF = Correction factor to account for non-gamma emitting nuclides in setpoint calculations. AF = an allocation factor applicable for steam generator blowdown The radioactivity monitor setpoint equation (1.2) remains valid during outages when the circulating water dilution is potentially at its lowest value. Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria. However, in order to maximize the available plant discharge dilution and thereby minimize the potential offsite doses, batch releases from either Unit- 1 or

                                             - - Page 75 of 156

Salem ODCM Rev. 19 Unit-2 may be routed to either the Unit4Vl or Unit-2 Circulating Water System discharge. Procedural restrictions prevent simultaneous batch releases from either a single unit or both units into a single U Circulating Water System discharge. . 1.2.2 Conservative Default Values Conservative alarvm 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 U based upon the following: a) substitution of the effective MPC value with a default value of 6.05E-06 jCi/ml (Unit 1) and i:t?-- 4.81E06 pCi/Ii (Init 2)t (rere to it Appendi "Af justlfijictibt)l4r b) for additional conservatism*, substitution of the I-131 MPC value of 3E-07 [tCi/m orI the R19 Steam Generator Blowdown mionitors the R-37 Chemical Waste.Basin monitor and the R-13: Servicwater1o3tiitors;' , -l..., U c) for conservatism, use of an allocation factor of 0.5 for the Steam Generatorf8lowd6Wn-monito-rs to limit consequences of potential simultaneous prmary-to-secondary leaks in two steam generators.** The allocationfa'citortl .frallthfiuideffl"t stp ints d) 9ubstitutions of the operational circulating water flow withthe lowest in gal/min;*** IlOW, 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. L For batch liquid releases a fixed alarm setpoint is established for the 1, 2 RI 8 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 setpoinit latio(e.t., Tle -. 1 and Table 1-1.2) should be any set of reasonable values that provide asetpoint value repasonably ove anticipated monitor response, plus [1 background; so as not to yield spurious alarmss. The release rate is controlled too ensure compliance with the requirements of ODCM CONTR;OL 3.3'.8'  ;. Calculations, as performed by;'Engineering, to establish the actual fixed setpoints for use in the plant; " incorporate uncertainties and instrument drift. These factors will cause the actual installed instrument setpoint to be at ta'ower (c6 ae)t vWl f bat elas Whtiteis conlld, these iinrtie san'dishould noibd Iluded 'inteaieatioof accpble relea6 rate,'Hsne'this L could cause'a non-conservative correction, i.e., a higher allowable releaserate'.Tere'fo're,' for 1, 2 R18 monitors, the fetpoint vmluevused lfor calculitin'th'e ailow~abk rela'se rateshld betavalue priorfto corredtiionrUncerteainty and drift '; 'i.

• Based upon the 'potential f'or, 1-31 Atobe'presentin the'secondary anh servce water systems, the use.ofltheidefaulteffective MPC(MPC,)value as derived iniAppendix A may be-non-conservative for the 1, 2 R-19 SGBD monitors, the R-37 Chemical Waste Basin monitor and the R-13 Service Water monitors. tr U
  • Setpoints using the AllocationFaictor of 0.5 become inv'alid If primary-to-secondary leaks ire identified in more than two steam generators simultaneously. L

***ThContainment.Fan CoUl nit Discharge to Service Water Line is rou e to the opposite Coi                                                       outed        oppons litei Unit's ;( ulating Water System                    Ascharge. Therekore, durrg periods when circulatig water               L Page 76 of 156                                                        U

Salem ODCM Rev. 19 pumps are out of service, such as during refueling outages, the default setpoints of the other Unit's R13 radiation monitors are not valid. 1.3 Liquid Effluent Concentration Limits - 10 CFR 20 ODCM CONTROL 3.11.1.1 limits the concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) to less than the concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F) for radionuclides other than noble gases. Noble gases are limited to a diluted concentration of 2.OE-04 jLCi/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: LfCi

• RR <1 4 MPG* CW+RR (1.4)

'Where: Ci = actual concentration of radionuclide i as measured in the undiluted liquid effluent (LCi/ml) MPC = the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (p.Ci/ml) [ODCM Appendix F]

            = 2E-04 pCi/ml for dissolved or entrained noble gases RR      = the actual liquid effluent release rate (gal/min)

CW = the actual circulating water flow rate (dilution water flow) at the time of the release (gal/min) 1.4 Liquid Effluent Dose Calculation -10 CFR 50 1.4.1 MEMBER OF THE PUBLIC Dose , Liquid Effluents. ODCM CONTROL 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from each unit of the Salem Nuclear Generating Station to:

        - during any calendar quarter;
                < 1.5 mrem to total body per unit
                < 5.0 mrem to any organ per unit
        - during any calendar year;
                < 3.0 mrem to total body per unit
                < 10.0 mrem to any organ per unit.

Per the surveillance requirements of ODCM CONTROL 4.11.1.2, the following calculational methods shall be used for determining the dose or dose commitment due to the liquid radioactive effluents from Salem: Page 77 of 156

Salem ODCM Rev. 19 D1l67E-02 *,VOL - U Do =

• CcwAio3::

CW w, 1 i,:i r,j ,; i, ,I .1@ L Where:. U

                 =  dose or dose commitment to organ o (mrem).. Total body dose can alsonbe calculated.

using site-related total body dose commitment factor. U Aj5 '=': site-relatjed ing'estion-dose commitment factor to the Jtotal body or any organo for per Ci) U

,P radion cideim VI.

C1; t ' -'ra5ge cincenrtion 'ofradionuclide ti,t in ulndiluted lqidefluent rep~resetiat~ive, of the 4ae a6§aiaave,, volume VOL (GCi/n)i VOL = volume of liquid effluent released (gal) CW = average circulating water discharge rate during release period (gal/mm) 1.67E-02 = conversi factor r/mi) " ,

                                                                                         '       ' '   :    a E.F x               a a ,ys ?-, ,,+   ; f aa' a ,a n      fa, amtm
                                                                                 ,            q ,           '  ,        ,

• aII L The site-related ingestion dose/dose commitment factors (A1o) are presented in Table 1-2 and have been derived in accordance with the requirements of NUREG-0133 by the equation: I, 4t 0 1.14 ~ ~r(T~ ~DrVft~r~~l~rjo' - I0 (Ii;ollw jv -d "",

Where:  :'i .! . L Ai. = composite dose parameter for the total body cr ritiMcr organ of aon adiult for radionuclide iafor fthe fish and inertebrate ingti p th s rlbr per pCi) L UI = adult invertebrate consumption (5 kg/yr) BI; = bioaccumulation factor for radionuclideei in invertebrates from Table 1-3 (pCitkg per UF = adult fish consumption (21 kg/yr) q~i S a a BF1 DFi. =

                 =     bioaccumulation      factor  fotr~iilnuiude                  i   infish         fro dose conversion factor for nuclide i, for adults in pre-selected organ, o, from Table E-1 1 able 1`.3(pagW~i                   , P/

Per' U O Rguq I6e tory-ydu'eaa iv3:mrem)wp ti J t. 9: a U

                     ,   '  4 1.14E4-           -
                 =>    conv'ersi'on ct'or'        '(pLi/

1 mI/kgper p- hr/yr)"i; a a .g .a The radionuclides included in the periodic dose assessment per the re'qui'rem-ents of ODCM CONTROL 3/4.11.1.2 are those as identified by gamma spectral an'ysi ofteiqd waste aii1es collected and analyzed per the requirements of ODCM CONTROL 3/4.11.1.,; Table 4.11-1. C 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 I 4.11-1. . tj 'flla4a, ttS '- l,t a 1SL at".'

                                                                                                                                                                        '4 t11 Page' 78 of 156                                                                                            U

Salem ODCM Rev. 19 1.4.2 Simplified Liquid Effluent Dose Calculation. In lieu of the individual radionuclide dose assessment as presented in Section 1.4.1, the following simplified dose calculation equation may be used for demonstrating compliance with the dose limits of ODCM CONTROL 3.11.1.2. (Refer to Appendix B for the derivation and justification for this simplified method.) Total Body Dl l1. 2 1 E + 03 *VOL E ( Maximum Organ 2.52E +04*VOL D max =Yc Dmax= CWE Ci(1.8) Where: C, = average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (i+/-Ci/ml) VOL = volume of liquid effluent released (gal) CW = average circulating water discharge rate during release period (gal/min) Dtb = conservatively evaluated total body dose (mrem) Dmax = conservatively evaluated maximum organ dose (mrem) 1.21E+03 = conversion factor (r/min) and the total body dose conversion factor (Fe-59, total body -- 7.27E+04 mrem/hr per iLCi/ml) 2.52E+04 = conversion factor (hr/min) and the conservative maximum organ dose conversion factor (Nb-95, GI-LLI -- 1.5 lE+06 mremlbr per ptCi/ml) 1.5 Secondary Side Radioactive Liquid Effluents and Dose Calculations During Primary to Secondary Leakage During periods of primary to secondary leakage (i.e., steam generator tube leaks), radioactive material will be transmitted from the primary system to the secondary system. The potential exists for the release of radioactive material to the off-site environment (Delaware River) via secondary system discharges. Potential releases are controlled/monitored by the Steam Generator Blowdown monitors (RI9) and the Chemical Waste Basin monitor (R37). However to ensure compliance with the regulatory limits on radioactive material releases, it may be desirable to account for potential releases from the secondary system during periods of primary to secondary leakage. Any potentially significant releases will be via the Chemical Waste Basin with the major source of activity being the Steam Generator Blowdown. With identified radioactive material levels in the secondary system, appropriate samples should be collected and analyzed for the principal gamma emitting radionuclides. Based on the identified Page 79 of 156

Salem ODCM Rev. 19 radioactive material levels and the volume of water discharged, the resulting environmentaldoses may be calculated based on equation (1.5). U Becauseithe releasetrate from the secondary system.is indirect (e.g., ISG 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, -Tnhis 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 niieded to more accurately account for actual releases. In addition to the secondary releases described in this section, the Salem Ground Water Reme iation System also can potentially discharge radioactive materil to,theChemical Waste Basin. To ensure regulatory compliance, the releases are. onitotedby

Radiation Montr R-37.¢Samples are also collected,' and analy'zed for radionuclides'r 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 m;; i I ODCM CONTROL 3.1k1..3-requires ,that the liqui"d rad reduce the radioactive material levels waste processing iystem be used to Waste priortQ release twhen the quarterlyyin.'eliquid projecied U doses exceed: 0.375 mrem to ihe ftotal body orr. i 4.^

          -  1.2~5Iirexrntoanyb'rganI..,             ;,.,'~                  F   A         ;~!'

The applicable liquid waste processi ngsai radioactive mriaieleases ALARA is the ion exchange system as delineated in Figure 1-3. Alternately, the waste evaporator as presented in the S SeiFSA i s 1 i e :m"We efihnth&NRt-A1L apiem-FS'vha has ibc~si in`apabilitie `RA Vt f!+bdirei n ignrefqiirmnt 9L t n useM a eue in conjunction or in lieu of the ion exchange system for waste processing requirements'in-ac ordnhevi with ODCM CONTROL 3.11.1.3. These processing requirements are applicable to each unit ni~v'idally.t geedig th piojected dose requiring proce sing rto releasefobr one'unt does notin 0 itelf dictate cgce ssing -requirements for the 'other uit.; t6se projections are made at lea.t once per 34l daysby the followigeiu~t1ons: - U

                                  .1:3DD bp     -Dbi (91 d )(1.9)                                              *                    [

D maxp D .J. 9 .i) J >D'9U Where  :  : . ' ' .' Dtbp = the total body dose projection for current calendar quarter (rnrem) Page.80of156 U

Salem ODCM Rev. 19 Dtb = the total body dose to date for current calendar quarter as determined by Equation 1.5 or 1.7 (mrem) Dmaxp = the maximum organ dose projection for current calendar quarter (mrem) Dmax = the maximum organ dose to date for current calendar quarter as determined by Equation 1.5 or 1.7 (mrem) d = the number of days to date for current calendar quarter 91 = the number of days in a calendar quarter 2.0 GASEOUS EFFLUENTS 2.1 Radiation Monitoring Instrumentation and Controls The gaseous effluent monitoring instrumentation and controls at Salem for controlling and monitoring normal radioactive material releases in accordance with the Technical Specifications 6.8.4.g and ODCM CONTROLS are summarized as follows:

1) Waste Gas Holdup System - The vent header gases are collected by the waste gas holdup system.

Gases may be recycled to provide cover gas for the CVCS hold-up tank or held in the waste gas tanks for decay prior to release. Waste gas decay tanks are batch released after sampling and analysis. The tanks are discharged via the Plant Vent. 1-R41D provides noble gas monitoring and automatic isolation of waste gas decay tank releases for Unit-1. This function is provided by 2-R41D for Unit-2.

2) Containment Purge and Pressure/Vacuum Relief - containment purges and pressure/vacuum reliefs are released to the atmosphere via the respective unit Plant Vent. Noble gas monitoring and auto isolation function are provided by 1-R41D for Unit-I and 2-R41D for Unit-2. Additionally, in accordance with ODCM CONTROL 3.3.3.9, Table 3.3-13, 1-R12A and 2-R12A may be used to provide the containment monitoring and automatic isolation function during purge and pressure/vacuum reliefs (*).

3) Plant Vent - The Plant Vent for each respective unit receives discharges from the waste gas hold-up system, condenser evacuation system, containment purge and pressure/vacuum reliefs, and the Auxiliary Building ventilation. Effluents are monitored by R41D, a flow through gross activity monitor (for noble gas monitoring). Radioiodine and particulate sampling capabilities are provided by charcoal cartridge and filter medium samplers. Additionally, back-up sampling capability for radioiodine and particulates is provided at the 1-R45 and 2-R45 sampling skids. Plant Vent flow rate is measured and as a back-up may be determined empirically as a function of fan operation (fan curves). Sampler flow rates are determined by flow rate instrumentation (e.g., venturi rotameter).

Gaseous radioactive effluent flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented in Figures 2-1. A simplified diagram of the Gaseous radioactive waste disposal system is provided in Figure 2-2.

• The R12A in Mode 6 provides containment monitoring and alarm functions without automatic isolation Page 81 of 156

Salem ODCM Rev. 19 2.2 Gaseous Effluent' Monitor Setpint Determi'n'ation" 2.2.1 Containment and Plant Yent, Monitor L Per the requirements of ODCM CONTROL 3.3.3.9, atarm set6oints sh~allbeestablished 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, wh~ch corresponds'to a dose rate at the SITE 'OU )ARY of 500 L 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 ofthe Chin=t stits iay- be' L atmosphere, waste gas decay tank, or Plant V , e i nitorn established by the following calculation method. The measured radionuclide concentrations and release [1 ragt ar idae eatedbyp catio;3 .1,10.24 by i XeFP .4?l;- =+:i-/ '.S lF' ^*i¢ ' '

                                                                                                                  ~

(cm'MS)) (L>g

                                                                                                                             '30" (22                        L FRCsiiil6             fato of The allowale                                                                 tae'bged on th identifi'ted0 iadion i clide c ncentra;i;ns
                         .,. :eg, t!,.=.r               , I6A,F"i-. - i"i i ', sFWi i N             -q      A nsvaitS                     i             Ai                ,jr  i   jS; L  erg      t
                  ~t59ri     gnimair e~'<ltetii~jo^j~t           j.,lfgr,@lowati& facitor d'converion'                                      for ythj fora;,nolcbeXlaeXitidmoio  gas r ni     '                r      p&/ir Cr         from r^i"   C;bao  ,0 Table b~t~o~ioble        2-1)                     #          adoul ie Iaons                        defeifiindb                 "A aibaohilyis'of   grab       on              X~p
   '    300         i sksn dose
                       ,F ;da<:~f,2rYyS fB        1       &

r , rekrt 5 i5 lF 2 (e g iw f FE th ven iT lif it (e hi vle as determied 0 n~lingAg~fr ^t1 ';cd -omi

                                                                                                                                                                  ,      lmsoin                               Ll d;,fSi Mamteoto~oalbodydosersan                dc,                     atd,-      othefio~r letoundrym~r otlimig                              ---

henreegaplo(ain it"'ff'- Ode~ftprIil eo 500pnavrg I' 3000 skinjdos='-raeimt R2A mrm/r 4.2 apiabeontr(R 0=condersor

                      --                              ID, fatoan/o(conuci myb                             mite) cIbeatdbytheqatn i            s      riey               , a       sgo rb 6i
                                                                                    .-,  , 1.1. ..
                                                                                         ...        I..  )    ,   . .it,. 0 X ..  .<..w Hs I   .-   ^.. I'll, .

Bsito~h noelmtn FRA (iKe., hihe ualu asdteriedaoeteaZlIaNmstons o h

                                                '                '$pilabte'                                                                          ~~~~~~~~mior                                4D'r 1') yicaeb eu: -; :7 Page 82 of 156

Salem ODCM Rev. 19 F ZCi*SEN 1 SP= AF* iF C +bkg (2.3) Where: SP = alarm setpoint corresponding to the maximum allowable release rate (cpm) SEN = monitor sensitivity (cpm per iCi/cm3 ) bkg = background of the monitor (cpm) AF = administrative allocation factor for the specific monitor and type release, which corresponds to the fraction of the total allowable release rate that is administratively allocated to the release. The allocation factor (AF) is an administrative control imposed to ensure that combined releases from Salem Units 1 and 2 and Hope Creek will not exceed the regulatory limits on release rate from the site (i.e., the release rate limits of ODCM CONTROL 3.11.2.1). Normally, the combined AF value for Salem Units 1 and 2 is equal to 0.5 (0.25 per unit), with the remainder 0.5 allocated to Hope Creek. Any increase in AF above 0.5 for the Salem Nuclear Generating Station will be coordinated with the Hope Creek Generating Station to ensure that the combined allocation factors for all units do not exceed 1.0. 2.2.2 Conservative Default Values A conservative alarm setpoint can be established, in lieu of the individual radionuclide evaluation based on the grab sample analysis, to eliminate the potential of periodically having to adjust the setpoint to reflect minor changes in radionuclide distribution and variations in release flow rate. The alarm setpoint may be conservatively determined by the default values presented in Table 2-2.1 and 2-2.2 for Units 1 and 2, respectively. These values are based upon: - the maximum ventilation (or purge) flow rate; - a radionuclide distributions comprised of 95% Xe-133, 2% Xe-135, 1% Xe-133m, 1% Kr-88 and 1% Kr-85; and - an administrative allocation factor of 0.25 to conservatively ensure that any simultaneous releases from Salem Units 1 and 2 do not exceed the maximum allowable release rate. For this radionuclide distribution, the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dose rate. a) Adopted from ANSIN237-1976/ANS-18.1, Source Term Specifications, Table 6 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations -10 CFR 20 2.3.1 Site Boundary Dose Rate - Noble Gases ODCM CONTROL 3.11.2.1.a limits the dose rate at the SITE BOUNDARY due to noble gas releases to

<500 mrem/yr, total body and <3000 mrem/yr, skin. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event any gaseous releases from the station results in an alarm setpoint being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release shall be performed using the following equations:

Page 83 of 156

Salem ODCM Rev. 19 (2.4) UI and Li D, = ZQ

• Z((L +1. 1M) *QI) (2.5) I 4,-,

Where: 1, i I.i ;If  ! 4 "I , : AS_S , _ 1 -C ,i Dtb AA total body'dos'e rate (iATI) U x/ =atmospheric dispersion to the controlling SITE BOUNDAR'V46loca6d0`(s/m 1, AUnhde~r Aevauation (p.Cilsec),,N L

  ; l                  =~ve~

K;AAAt~averaygdre A conversaioniafq fei obv th~e~r'el'e'asetpdriod elas rt&of4dniedeior grddnifd trriiyipr~~ifo L A~fII A'A beta skn dosega-facto

                   =      oamadi dose-conversion, fcor for nolegsrdincdei(alypr                                              A..i/m, fr6l~

Ta1bl 2-1)ue 1.amrmaskin dose ponermrdgmm i ds memma) ti*~ U cisderdi L Asappropiae pm~aeisrlases

                                                ~on, Salem       Snt1              Pl2adHpel CieekWllb
                                                                  'DCMCOITROL 3.1 1;'2AaN 6-so evauain cmpia~ewfhth rleia~li                                                                    follgwigny~

C Monitor indications (readinigs) mybe averaged over'a"time period n~t to exekdd 15 nitites~whe determining noble gas release rate based oncorrelation :of theimn~iitor re~adin'g' and mo'ni~tor sensitivity. U The 15in~inueaeaigi De~4d a; Q o resnb~i~i6#iesponge, to ~oenial1y h~ging radjoactiiemaerial concn'aani~ atcexo u, poehtia kronicspikcis in mionito dnsta led may be unrelated to, radioactiy'p at ral rieleases. As identified, an ectqncsp iking oni'or responses U NOTE: Foroadministrativ set'6nt thnted~ea "A' U above may be imposed. 'However, conditjin'IsA.'ciedin"`these` oreiliim'itmgariii-,, setpoints do :not necessarily indicate radioactive material, release rates exceteding the limits o~fbOD`CM CONTRO 12.1La'. ~Pr~ovided A'aciu'al';rleat ese', iot result in"' U radiation monitor indications exceeding alarm setp oint values based on the above criteria, no furthe of ODCM CONTROL 3.11.2.1.a.

                                             "nIssae'eurdfrdeosrtn I' A         l            A compliance wiith the limits A ¶ U

Actual mteorological conditions ceoncurrentw~ith the ~release period or the rdefault,annual ayerage dlispefsion paramneters as presented inaTable Z-3~- may be used for evaluating the gasepus efflueifl dose A,

                                                                                                                                              'I rate.,

L Page ,;4Aof 156

Salem ODCM Rev. 19 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 I-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: D* (Rio* Q) (2.6)

                                            ~IQ     i Where:

Do = average organ dose rate over the sampling time period (mremiyr)

            = atmospheric dispersion to the controlling SITE BOUNDARY location for the inhalation pathway (sec/m 3)

Rio = dose parameter for radionuclide i (mrem/yr per pCi/m3) and organ o for the child inhalation pathway from Table 2-4 Qi = average release rate over the appropriate sampling period and analysis frequency for radionuclide i 131, tritium or other radionuclide in particulate form with half-life greater than 8 days (RCi/sec) By substituting 1500 mrem/yr forDo and solving for Q,an allowable release rate for 1-131 can be determined. Based on the annual average meteorological dispersion (see Table 2-3) and the most limiting potential pathway, age group and organ (inhalation, child, thyroid -- Rio = 1.62E+07 mrem/yr per RCi/m 3), the allowable release rate for I-131 is 42 pCi/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 pRCi/sec. For a 7 day period, which is the nominal sampling and analysis frequency for I-13 1,the cumulative release is 6.3 Ci. Therefore, as long as the I-13 1 releases in any 7 day period do not exceed 6.3 Ci, no additional analyses are needed for verifying compliance with the ODCM CONTROL 3.1 1.2.1 .b limits on allowable release rate. 2.4 Noble Gas Effluent Dose Calculations - 10 CFR 50 2.4.1 UNRESTRICTED AREA Dose - Noble Gases ODCM CONTROL 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of <5 mrad, gamma-air and <10 mrad, beta-air and the calendar year limits <10 mrad, gamma-air and <20 mrad, beta-air. The limits are applicable separately to each unit and are not combined site limits. The following equations shall be used to calculate the gamma-air and beta-air doses: Dy =3.17E -08* /*Z(Mi*Qi) (2.7) and Page 85 of 156

Salem ODCM Rev. 19 D = 3,17E -08 * *Z *Q,) (2.8) U Where: y- i'= air dose due to gamma emissions for noble gas mrad) :radionuclides Dro = air dose due to beta emissions for noble gas radionuclides (mrad) IQ = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/r 3 ) U Q; = cumulative release of noble gas radionuclide i over the period of interest (jtCi) Where

                           ,uCi -(lCi/cc)*(cc released) or (Ci/sec)*(sec released)

M = air dose Tacfor due to gammaEimssigni ~ioi94 e<as ra ionuc ld 3 (mrad/r'e pXCii , fr lT 2yr4)pr .e4 f O  ;  :,1t L N; = air dose factor due to beta emissions

               - 1t;?ie t                     ¢ 3    tipEw from   noble  gas
                                                                         ;tl!aite/-kt;i~   t0t;9 radionuclide
                                                                                                 - I-,~~~I IH i

2.4.2k m Table 2-1) -ti , - I Simiifedose Calculation fr~beGs iI' J 4 In lieu of the individual noble gas radionuclide dose assessment as presenteid b'e, the following simplified dose~calculation equations may; be: used 'for verifying compliance with the dose limits of ODCM CONi~tL.11:.2.2:. (Rfefto Appendix C derivain and-jistificatio for s pfiedde r method'and for Values of ifif,and Nff..'. AY ' ' ? 0.50 and 0.50 .:rdil ~,~ W/here: Meff

           ~~
           @~      ~      ~Z4 ~~~~~~~u
                                              ~~.
                                                            ,,;   ;i 4
                =5.3E+02, effective gamma-air dose fcor (nrd2,r pe j+/-i/z ief?+?,;ityL al        j      in>/it.he1.d    n 3pli       ,..li qd
                                                                                                                           ,      r bu¢ t
                                                                                                                                       ..     ,i, .

pC/ ) 3 Ncf~~per, QI~ cumulative release for, alnbegas adonuclides (4.Ci), were, +/-i(pic) c released) or 4Cilsec)* serleased)I yi! 0.50 conservatism factor-toacoot, fr p/te tial varikabt in th re dstib t Actual meteorological conditions concurrent with the release period or the default, annual averageU dispersion parameters as presented in Table 2-3,, may be used for the evaluation of the gamima-air and beta-airf oses. g Paged 156 .of

Salem ODCM Rev. 19 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 = 3.17E- 08

• W
• SFp* (Riop *Qi) (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 (mnrem) W = atmospheric dispersion parameter to the controlling location(s) as identified in Table 2-3 XQ 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 (m7 2) R1op = dose factor for radionuclide i (mrem/yr per PiCi/m 3 ) or (m2 - 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 Rjop were derived in accordance with the methods described in NUREG-0 133. Qi = cumulative release over the period of interest for radionuclide i -- I-131, tritium, or radioactive material in particulate form with half-life greater than 8 days (pCi). SFp = annual seasonal correction factor to account for the fraction of the year that the applicable exposure pathway does not exist. 1)For milk and vegetation exposure pathways: A six month fresh vegetation and grazing season (May through October) = 0.5

2) For inhalation and ground plane exposure pathways: = 1.0 For evaluating the maximum exposed individual, only the controlling pathways and age group as identified in Table 2-3 need be evaluated for compliance with ODCM CONTROL 3.11.2.3.

2.5.2 Simplified Dose Calculation for Radioiodines and Particulates. In lieu of the individual radionuclide (I-131, tritium, and particulates) dose assessment as presented above, the following simplified dose calculation equation may be used for verifying compliance with the dose limits of ODCM CONTROL 3.11.2.3 (refer to Appendix D for the derivation and justification of this simplified method). Dmax=3.17E- 08*W*SFp* RI I3-* Q: (2.12) Page 87 of 156

Salem ODCM Rev. 19 Where:  : ' l.-, ... .. ,^ ; , : '! ' ' , Dmax = maximum organ dose (mrem) R1.131 I- 131dos eparam eter,for the thyroid for the identified controlling pathway

                       ,     .05E+12,infant.thyroiid, dose~paramet                                          erwthpte grass-cow-milk pathway W

Qj

                      .controll
                  =D/Q for radioiodine,

( ing - 2remyr per gCi/sec),, 2JE-10 1/rn2. cumulative release over the period of interest for radionuclide i - I-131, tritium, or 131, or L

                  =

radioactive material in particulate m with half life greater than,.8 days (gCi) L 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 inODCM CONTROL 3.12.2. 0 0 *3  ! ' aw' '1 ": .S 0*, ' S g ! ' ', , - -a ,2,.6 Seconda Side RadioadctiVeGseouxs Efents 'and Dose- CacuPas ' Dugprod DurinS, fray; to seconidaryjleagemnolvlso riativematerial d'I may be releasedvi viaL [ theodr'systdfin:to lheaatmoshre'1i-6id§sbe (e4.g i,nbe~ .ga es)r*vll be predominatelyL released'via the condenser evacuation system and will be monited an. quantifiedby the routine plant vent moinioring and "aplingye$ (eegt,R on ndenser evacuation, R41D on plant vent, and the pla'nt vent"paiculate andc charcoal samplers). Howee, ifthe blowdon lg e t Steam Gentorbow dwtdirectly to teCemical Waste Basin (via the SG ed though direc ftlios ihe0-tr C . h)i1+ k 01i:iizi en.s:iayb4esirable to account for

                                                                                                                                                                          .t L

the potential atmospheric releases o fradiriodines and p tias o fsht vent (i e., releases duetomoisrecarry o e t th yis not sampled or monitored, it is necessary to calculate potenftl al a}!; d  ;. d' '9 If 4"Ibd

                                        > i' 'd'5     ;"      i
                                                                *r              teles   '.        7i
                                                                                                                                   '    j   0j t     '  ;                            r Based on the guidance in NRC NUREQ40133,the.releas                                                                of       adiodoies-and particulates shall be calculated by the equation:                                          -, . .                 ,* ,                     .

t Ctt0 R w4,.d.,;',i., \ . d  ;(2.13) Qi= CI*RP b*Fft*(1 nrato flashtakvn(C/s) Qj = the= release eesert h rate offtdionuclide1 , from tesanf~ ae 4m9V l~h t0,n0 nf<Jl,;,3, C1 = the concentration of rdio ulde, i, i the secondary coolant water average over not morethaineweel*Q.i(n4 il f

        .R5gb th                 ste'i         generar               b0dowr             ytethe                flash ta9k (K c)                      r
                  = th fra.tionfofblowd.nfashein thtank deteWrmine-d fom aheat l,alance taken around                                                                                   L the flash tank at the app'licable reactor pwer level SQftv= the measured steam quality in the flash tank vent; or an assumed value'of O18j, based on NUREG-0017.                                              -

Tritium releases via the steam flashing may also be quantified using the above equation with the assumption of a steam quality (SQiw) equal to 0. Since the H-3 will be associated with the water L

                                                                                       .Page88 of 156                                                                                  L

Salem ODCM Rev. 19 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 (Fe) is approximately 0.48. The equation simplifies to the following: Qi = 0.072* Ci*Rsgb (2.14) For H-3, the simplified equation is: Qi = 0.48

• C *Rsgb (2.15)

Also during reactor shutdown operations with a radioactively contaminated secondary system, radioactive material may be released to the atmosphere via the atmospheric reliefs (PORV) and the safety reliefs on the main steam lines and via the steam driven auxiliary feed pump exhaust. The evaluation of the radioactive material concentration in the steam relative to that in the steam generator water is based on the guidance of NUREG-00 17, Revision 1. The partitioning factors for the radioiodines is 0.01 and is 0.005 for all other particulate radioactive material. The resulting equation for quantifying releases via the atmospheric steam releases is: Q = 0.13 * (C#

• SFO)* PF1i (2.16)

Where: Qjj = release rate of radionuclide i via pathway j,(p.Ci/sec) CUj = concentration of radionuclide i, in pathway j,(p.Ci/ml) SFj = steam flow for release pathway j

              =    400,000 lb/hr per PORV
              =     850,000 lb/hr per safety relief valve
              =     62,500 lb/hr for auxiliary feed pump exhaust PFj   =    partitioning factor, ratio of concentration in steam to that in the water in the steam generator
               =    0.01 for radioiodines
              =     0.005 for all other particulates
               =    1.0 for H-3 0.13   =    conversion factor - [(hr*ml) / (sec*lb)]

Any significant releases of noble gases via the atmospheric steam releases can be quantified in accordance with the calculation methods of the Salem Emergency Plan Implementation Procedure. Alternately, the quantification of the release rate and cumulative releases may be based on actual samples of main steam collected at the R46 sample locations. The measured radionuclide concentration in the steam may be used for quantifying the noble gases, radioiodine and particulate releases. Page 89 of 156

Salem ODCM Rev. 19 Note: The expected mode of operation would-be: to isolate-the effected steam generator, thereby reducing the potential releases during the shutdown/cooldown process. Use of the above.- calculation methods should consider actual operating conditions and release mechanisms. The calculated quantities of radioactive materials may be used as inputs to the, equation (2. 11) or (2.I12) 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- RADWAST TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM be used toxreduce radioactive material levels prior  ;

     ,qhar    w      rojected doses.exceed one-half the annual design objective rate in any calendar
                            'l,-'        i                                        f                    7                  ! 11           ;

quer 7S~ J The applicable gaseous processing systems for maintaining radioactive meiia eas AAX~e Auxiliary Building normal ventilation system (filtration systems # -1 2 and 3) and the Waste Gas Decay Tanks a' dd6ineated in Figures 2-1 and 2-2. Pse projecti'onae i eifned a ileast once per 31 days by the following equations: Dr;p=Dr*91)(2.17 D=Dp* D DMP (91/ Z , ,, A - d )  ;; ., f, f-!-8~~S~ti0:+,f, Fj t.i ; siSfi

                                                                                                '>e2' j     t>EE.z;t Ad,,
                                                                                                   *.si.(Ta.hJleq:,i~ m.8

(  ? ) J sn ' t}XdAv

                                             ,{:9-iti o1/4m .
                                               ,';lI     tst         Im~9 .. pt           D(2.18)

Where: Dp = gamma air dose projection for current calendar quarter(md ' D = gamma air dose to date fof- curr-nt icandfiquaer-as detehiixed by Equation 2.7 or 2.9 (mrem) beta air dose projection for current calendar quarter (mrad)

                =

(ir' i= bncalendarequartas'detenined by Equation 2.8 or2.10 n Dmxap = maximum organ dose proiection for current calendar quaermreri

• ma maxii rm-organ dos 6to 'dat foicurrein calenar qUrte ast
• i determined 'y 'Equation 2.1& or 2.12 (nifni)t d = number of days to date in current calendar quarter 91 = number of days in a calendar quarter

Page,90 of.156

Salem ODCM Rev. 19 3.0 SPECIAL DOSE ANALYSES 3.1 Doses Due To Activities Inside the SITE BOUNDARY In accordance with ODCM CONTROL 6.9.1.8, the Radioactive Effluent Release Report (RERR) shall include an assessment of radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY. The calculation methods as presented in Sections 2.4 and 2.5 may be used for determining the maximum potential dose to a MEMBER OF THE PUBLIC based on the parameters from Table 2-3 and 2-hours per visit per year. The default value for the meteorological dispersion data as presented in Table 2-3 may be used if current year meteorology is unavailable at the time of NRC reporting. However, a follow-up evaluation shall be performed when the data becomes available. 3.2 Total dose to MEMBERS OF TIHE PUBLIC - 40 CFR 190 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: No other fuel cycle facilities contribute to the MEMBER OF THE PUBLIC dose for the Artificial Island vicinity. The dose contribution from the operation of Hope Creek Nuclear Generating Station will be estimated based on the methods as presented in the Hope Creek Offsite Dose Calculation Manual (HCGS ODCM). As appropriate for demonstrating/evaluating compliance with the limits of ODCM CONTROL 3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used for providing data on actual measured levels of radioactive material in the actual pathways of exposure. 3.2.1 Effluent Dose Calculations For purposes of implementing the surveillance requirements of ODCM CONTROL 3/4.11.4 and the reporting requirements of 6.9.1.8 (RERR), dose calculations for the Salem Nuclear Generating Station should be performed using the controlling pathways and locations of Table 2-3 and the calculation methods contained within this ODCM. If more limiting exposure pathways are determined to exist in the surrounding environment of Salem by the annual land-use census, Table 2-3 will be revised as specified in ODCM CONTROL 3.12.2. Average annual meteorological dispersion parameters or meteorological conditions concurrent with the release period under evaluation may be used. 3.2.2 Direct Exposure Dose Determination. Any potentially significant direct exposure contribution to off-site individual doses may be evaluated based on the results of the environmental measurements (e.g., DLR, ion chamber measurements) and/or by the use of a radiation transport and shielding calculation method. Page 91 of 156

L Salem ODCM Rev. 19 Only during a non-typical condition will there exist any potential for significant on-site sources atSalem U that would yield potentially significant off-site doses (i.e., in excess, of l mreSi -peryearto a MEMBER OF THE PUBLIC), that would require detailed evaluation for demonstraing' compliance with 40 CFR L 190. However, suid'a situation exist where .thedirect exp'osure 6otriibuut'1o'

                                                                                                                    ,                                                                                                             I1 otentia'ly sigica t, o-site U

measurements, off-site measurements and/or 'calculation techniques will be'used 'for' determi'ation oof dose for assessing 40 CFR 190.compliance. . . .. :K; , 4.... 4 LI ti  ?' "J!

                                                                -    ,      -itif isii):oi;:-..

j'f

                                                                                           ' J4   ~               ;'i:':i'i4
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4. i ,,i'3ii . gii~

1'4'! .' t {if; 'g '!4 'i ,4 ,

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                                                   " I!       '; .         I ",    ; - q, !               T I I. i     ; . I            1,    I I i ;i , \i ,!@y i.i4 i,.
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                                                                                                                                                                                                                                                                                   -:i.,

U 1444 4 2' ... ' ,'.".,. 4."-. t 444 "4' 4 . .r' 444 "44 4 4 4

                                                                                       '4f     '*..          1, 4 U'

• i' 4 4..*4444 24411, I b424t' ' A 4

4 '> Q4't1'411' 2 l' *- '**'*' .. ,,,,. 4' 14 44 '4 444'..4 *'. U 5'. . 4 . .4 4' 4 ~'2' 4.'.44 1

                               .~           '     4       ii'41.4 '4'4                                                                                         4             ~i                               ~U 4        4                      444*       ~               l~ll444~h..4                                                                      4                                4j4 4       4  4~,4A'     .              '               ~            4               ~          .                                                                                          .4                  4~4A44t4"4                                 '~q' 44        '.               7~.4,                                                                     -  '        4                    -        14          4o'o                 '14                        4.:'               2                             4    '
                                                                                                                                                                                                                .44.4  4                ~.. 3~ 42'U *-
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                                     '42'                   ,                                  4       414'             4,    4~

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                                                                                                                                                    ~.4 '>1(J.                            'j         '4              4'                          4;4                      ~ ~            4'4 4.41. 4~    .4     ~ "144           1            '444'4        '1       '14                            .4                                      '~4            '       4                                               *4.
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                                                                                                                                                             . I           :        I          :       i         F I           V        , :           , , , ,     i - ,          I    I         I    1; : ,     i Z L

L Page 92 of 156 L

Salem ODCM Rev. 19 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4.1 Sampling Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of ODCM CONTROL 3.12. The objectives of the program are: - To determine whether any significant increases occur in the concentration of radionuclides in the critical pathways of exposure in the vicinity of Artificial Island; - To determine if the operation of the Salem Nuclear Generating Stations has resulted in any increase in the inventory of long lived radionuclides in the environment; - To detect any changes in the ambient gamma radiation levels; and - To verify that SNGS operations have no detrimental effects on the health and safety of the public or on the environment. The sampling requirements (type of samples, collection frequency and analysis) and sample locations are presented in Appendix E. NOTE: No public drinking water samples or irrigation water samples are required as these pathways are not directly effected by liquid effluents discharged from Salem Generating Station. 4.2 Interlaboratory Comparison Program ODCM CONTROL 3.12.3 requires analyses be performed on radioactive material supplied as part of an Interlaboratory Comparison Program. Participation in an approved Interlaboratory Comparison Program provides a check on the precision and accuracy of measurements of radioactive materials in environmental samples. A summary of the Interlaboratory Comparison Program results will be provided in the Annual Radiological Environmental Operating Report pursuant to ODCM CONTROL 6.9.1.7. Page 93 of 156

Salem ODCM Rev. 19 FIGURE. 1-1: LI4iDRELEAS'E~-LOWPATH UNiTI. VOLUME CONTROL TANKS COMPONENfT #1 WATERTSTORAGE

                                  ~COOLING-1 SURGE TANK~

TO CVC!S HOLD-UP TANKI orH`61DUP TANS2

                                                         ~S-COSPETNTANKS-Pr DEA411qERAIZE
                                        -UNIT   2 RO
                           -*TO            NON-A (A)

(Figue12 GROUND. WATER T NNRA) C R1MONITORS REMEDIATION(Fgr12 SSTEM TO CRCATG

                           -*        TO NONJRAD (B)                   Z=ERSYSTEM (Fgue 2 Page 94 of 156 rz7 r= r-- rr.. r,t--, r-l r-77                t=            r--     r r77              r:     rx    U mrn-  u:7   Ur7 U-.

r-7 irn rn rn jrti in e--7, rn tri u---, r77--- r77 w-- ir--.-- Salem ODCM Rev. 19 FIGURE 1-2: LIQUID RELEASE FLOWPATH UNIT 2 Page 95 of 156

Salem ODCM Rev. 19 FIGURE 1-3: LiQuiD RADIOACTIVE WASTE SYSTEM

         ; ;, , ,5 A, ,    ;,-  , ! , , ,,

i '41 1 ,

                                           -1 .1, ":
                                                     . 4 - ,
                                                               - 0,,
                                                                     . -, ":" -,O
                                                                     ,,.          4 -- td, z..-% ,

Page 96 of 156 z r=- ri r-C r3 V- r- rz rS C r-7 rC= rC rr r---

Salem ODCM Rev. 19 Table 1-1.1: Parameters for Liquid Alarm Setpoint Determinations Unit 1 Parameter Actual Default Comments Value Value Units l MPC Calculated 6.05E-06

• iLCi/ml Calculated for each batch to be released.

MPC 1-131 3.OE-07 N/A ,uCi/ml 1-131 MPC conservatively used for SG blowdown and Service Water monitor setpoints. C_ Measured N/A pLCi/ml Taken from gamma spectral analysis of liquid effluent. MPGC as determined N/A .LCi/ml Taken from 10 CFR 20, Appendix B, Table II, Col 2 (Appendix F). Sensitivity as determined N/A cpm per Monitor sensitivities are controlled 1-RI8 giCi/ml under Public Service Blueprint l-R19 (A,B,C,D) Document (PSBP) 315733 l-R13 (AB,CD,E) CW as determined 1.OOE+05 gpm Circulating water system - single CW pump *** I RR as determined gpm Determined prior to release; release rate 1-RI8 120 can be adjusted for ODCM CONTROL compliance I-RI9 250 Steam Generator blowdown rate per Generator 1 R13 2500 Service Water flow rate for Containment fan coolers Setpoint Calculated N/A cpm Monitor setpoints are controlled under 1-R1I8 Public Service Blueprint Document 1-R19 (AB,C,D)** (PSBP) 315733 l-R13 (A,B,C,D,E)** Correction Factor as determined 0.75 Unitless Defauit parameter to account for non-(Non-Gamma) gamma emitting nuclides. Allocation Factor 0.5 0.5 Unitless Conservatism factor to preclude l-Rl9 exceeding MPGC limit in the case of simultaneous primary-to-secondary leaks'at both Salem Units

• Refer to Appendix A for derivation
  • The MPC value of 1-131 (3E-07 jiCi/ml) has been used for derivation of R19 Steam Generator Blowdown and R13 Service Water monitor setpoints as discussed in Section 1.2.2
    • During periods when Unit 2 Circulators are out of service, the CW flow for certain l-R13 monitors is zero. See Section 1.2.2.

Page 97 of 156

Salem ODCM Rev. 19 F Table 1- 1.2: Parameters for Liquid Alarm Selpoint Determinations - Unit 2 IU Paramer Actual Dfut UisCmet Valu Value MP~ Caclae 48lE0a*' ca1utlatedoreah atch to bereleased.

      ~4C1131                         .E0                               /            giCilmI         1-131 MPC conservatively used for SG blowdown, Service Water and Chemical sinnmonitor setvoints.

_______________Waste Fl MesrdN/A pc/i Taken frmgmaspectral analysis of 'I MIPCI Sensitivity K"a'eemie sdeemnd N/A ATbeCl2(Append NAcmpr jiml Tknfrom, 10 CER 20, Appendix B, Mntrssiviisaeotold i) U 2-Ri S pi/mi uner Puiblic Servie, BIuepint Dcmn 2R19,(ABI,C,D) 4 CW " sdetermined-LOE+05-, gpm" Circula~ting WatersSstem, single CW p pA'* 1 U RR 2-R1 as determined 120can gm Determined prior to elease; release fate be adjusted for ODCM CONTROL U A, Compiance 2-R19 A;'.'b i ~*o< 20Ste'am Generator Generator Blowdown rate per U 2-rRI3 A 20 'Srice; Water flow aefr Containmen 'U R37<" 100Chemical Waste Basin d-i rg U S CacltdN/A _i~e Setpoint cpm Mniorstpins cotold under' 2-RIl9(A B,C,,D)*-* AA' ' '(PB)35 44 ," . U Correction ac or (No-Q~in) 1 as'detM

                                                       ~              07 5          Unitless       Default prmtr to~accounit for non-amma emiting, nolides.,,:,                   U Allocation Factor                        0.5                           0.5           Unitless       Conservatism factor to preclude 2-R19exceeding
                                                                 'A',
                                                                           ~~'
                                                                                       ~     ~

MP,limit~n i~a~m~nt~ casof simuitane~ops ppimaryto-seconda I I le aks U Refer to Appendix A for derivation U

   **   The MPC value of I-131 (3.01E-7 gCi/ml) has been used for derivation of the R13, R19 and R37 monitor setpoints as discussed in Section 1.2.2 U
  ** During periods when Unit I Circulators are out of service, the CW flow for certain 2-RI3 monitors is zero. See Section 1.2.2.                                                                                                                            L Page 98 of 1,56

Salem ODCM Rev. 19 TABLE 1-2: Site Related Ingestion Dose Commitment Factor, AjQ (Fish And Invertebrate Consumption) (mrem/hr per ,LtCi/ml) H-3 - 2.82E-1 2.82E- 2.82E-1 2.82EE- 2.82E1 j C-14 1.45E+4 2.90E+3 2.9033 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-1i P-32 4.69E+6 2.91E+5 1.81E+5 - - - 5.27E+5 I Cr-51 - 1 24E2+ 5.584E 1.23E+ 7.40E+0 1.40E+3 Mn-54 - 7.06E+3 1.35E+3 - 2.10E+3 - 2.16E+4 Mo-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+41 Ni-63 4.96E+4 3.44E+3 1.67E+3 3.2+- 7.18E+2 Ni-65 2.02E+2 2.62E+1 1.20E+1 - - - 6.65E+2 Cu-64 - 2.14E+2 1.01E+2 - 5.40E+2 - 1.83E+4 Zn-65 1.61E+5 5.13E+5 2.32E+5 - 3.43E+5 - 3.23E+5 Zn-69 3.43E+2 6.56E+2 4.56E+1 - 4.26E+2 - 9-85E+1 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+0 - - - 4.67E+0 Br-83 - - 7.25E-2 - - - 1.04E-1 Br-84 - - 9.39E-2 - - - 7.37E-7 Br-85 - - 3.86E-3 - - - -5 7 Rb-86 - 6.24E+2 2.91E+2 --- 1.23E+2! Rb-88 - 1.79E+0 9.49E-1 - - - 2.47E- l2 Rb-89 - l.l9E+0 8.34E-1 - - - 6.89E-14 Sr-89 4.99E+3 - 1.43E+2 - - - 8.00E+2 Sr-90 1.23E+5 - 3.01E+4 - - - 3.55E+1 Sr-91 9.18E+1 - 3.71E+O - - 4.37E+2 Sr-92 3.48E+1 - 1.51E+0 - - - 6.90E+2 Y-90 6.06E+O - 1.63E-1 - - - 6.42E+4 Y-9lm 5.73E-2 -2.22E-3 --  ;  ; -1.68E-1 Y-91 8.88E+1 -2.37E+0 - 4.89E+4 Y-92 5.32E-1 -1.56E-2 - -- 9.32E+3 Y-93 1.69E+0 4.66E-2 - -- 5.35E+4 Zr-95 1.59E+1 5.11E+O 3.46E+O - 8.02E+O i - 1.62E+4 Zr-97 8.81E-1 1.78E-1 8.13E-2 - 2.68E-1, - 5.51E+4 Nb-95 4.47E+2 2.49E+2 1.34E+2 - 2.46E+2 - 1.51E+6 Nb-97 3.75E+O 9.49E-1 3.46E-1 - 1.l1E+O - 3.50E+3 Mo-99 - 1.28E+2 2.43E+1 - 2.89E+2 - 2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.66E-1 - 5.56E-1 1.79E-2 2.17E+1 Tc-101 1.33E-2 1.92E-2 1.88E-1 - 3.46E-1 I 9.81E-3 5.77E-14 Page 99 of 156

Salem ODCM Rev. 19 U Site Related Ingeston Dose Cmimn atr L (Fish And Invertebrt Consupin (mrem/hrper 1tCi/n1 F> -60 2DI Rib-1052' S.898+ 45E- 68E+635E"+O .9E1 `.6-~ 7514E+3 ku-'l156 1.771.59E8E+ 4201E+l .1- 3-0l.6E2 .9E+ L Te-2 U Se-'1241m~ 1.56+O Te1242.4+0 l.77E+ 320 955E-4 6,:.23E+:7' 8160E+O2 6.19E-l-1.5+

                                                                    .0+

310.107E+1 5.1E+10lE+2'66714B+I 36E1 11.92E+0i

                                                                                                    -~`~:
                                                                                                        -2 s       .91 E+2 6`,.86E+3, ~V' L

Te-13 Te-b1326 e-'1250 37E9+2 2.04E,2' i.96B+/-12.17E2 1.98E-l l.31E+2 78E+1 210E-P ,699+131+ 4.24E+2 4.261E+1; 1OR j136 6.46E+2 l.27E+3 6.52E1B+3', Pi.82+2-61E+2 2:~~.95&`11 24E+3!

                                                                                                                              ~

L I84E+1 1--1271 6-1327 2.48E+2: 1890E+1 74E+21-313 3-129E+27-23.85E+l0~ 13AE+2,,? l679E+2" L939E+O,- 1.40E+5£7,;:' 25.35E+2

                                                                  &.60E+2-?)',,' 43.54E+1 M2 3.95'l10E+24-            2.26E+23,
                                                                                                                  .3 16E+

L 1-,134, 545E+O 9.551El-1 2.6E+Q",2 Te-135n Cse-l3411,. 1.4E+2 6.84E+31-`63E+ 6.19E10 6.08E+1, :Y 52.71E+1 0.33E 14.08E+23~4, 31 E+ 1407E+l 9.754E+12. 56.99E+30 7E+

                                                                                                                   ,2-6.87E+1 2.26E+2I -
                                                                                                                                ' L Ce 132,'         2.04E+2            1.832E+        12.4E+23            -. 6+Z      1.27E+3,    2.14E+2           3.2lE+2 ;

Cs143: 8,.77E+3 I .2I E+4: 7.85E+3 -482E+3,; 1 1.5+.2E+2,~ Cs18 7E.020+ 59EE- 85.35E+2 8S72EE115.12E- , Ba-131 ~ .185E+20.:F 3.12E-2 2,.309E-2 - .3-3 31E3£ 9+ Ba-143 1.06E+1 2.85E+0, 919E+O96E2 - 7.02E,-l - 1.18E+0 5353E+3 Ba-141 .45E+~ 1.30E+2 3.295E-1 9E4

                                                                      -:,          2.268E-3     163- 2180 45l7E+,l7E-3       Ia                408E-l        26E-             l.50E-3      l0EE-3             ,2.4E1 La24          325E+1          6.08E-l         1241E-1             0E3,,~93+
                                                                      -                 --                      ~587E+4 La-14            7.16E-2           2-3.6E-2        2.04E-3                            57                           2168E+2 C9-141 Cs-1438 3.43E+0 6.07E-l I203E+4 1.20E+1 2..85E-3 4.94E-2 4 .07E+3 S19E-1 3858E+3(`J,,23EZ,
                                                                                                  -               126E+4 L

C-139 7.85E+2 5.7+ .59 E+O 40E. M, .04 E+4, L

                                                                     -           5.23E&3       3-Pra-140          1.64E+O          .2.32E+O        278EE11             -           1.34B+0          -32.8E+43 Ba-141u          1.97E-2O          1787E-3         1.08E-1                        4.54E-3 I             -              2.7EE-9, Nd-140x CW-187,,

1.57E+0 3.43E+0 7.94E-1 2.36E+0O2 2.74OE-1 2.631 -

                                                                                   .8+

08E+0

                                                                                        -        -8.86E+3~~:
                                                                                                                  .0+

U Ce-439 3.53E-2 34A6E-3 4.94E3 -lOE-2 1-7 I .7.E+2,,~ L, L Page 10,0 ~of 156 L

Salem ODCM Rev. 19 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-O1 P                              3.OE+03                                 3.OE+04 Cr                             4.OE+02                                 2.OE+03 Mn                             5.5E+02                                 4.OE+02 Fe                             3.OE+03                                 2.OE+04 Co                             1OE+02                                  l.OE+03 Ni                             1OE+02                                  2.5E+02 Cu                             6.7E+02                                 1.7E+03 Zn                             2.OE+03                                 5.OE+04 As                             3.3E+02                                 3.3E+02 Br                             1.5E-02                                 3.1E+OO Rb                             8.3E+00                                 1.7E+O1 Sr                             2.OE+00                                 2.OE+O1 Y                              2.5E+O1                                 l.OE+03 Zr                             2.OE+02                                 8.0E+Ol Nb                             3.OE+04                                 l.OE+02 Mo                             l.OE+O1                                 l.OE+O1 Tc                             l.OE+O1                                 5.OE+O1 Ru                             3.OE+OO                                 l.OE+03 Rh                             l.OE+O1                                 2.OE+03 Ag                             3.3E+03                                 3.3E+03 Sb                             4.OE+01                                 5.4E+OO Te                             l.OE+01                                 l.OE+02 I                              l.OE+O1                                 5.OE+O1 Cs                             4.OE+O1                                 2.5E+O1 Ba                             l.OE+O1                                 l.OE+02 La                             2.5E+o1                                 l.OE+03 Ce                             l.OE+O1                                 6.OE+02 Pr                             2.5E+O1                                 1.OE+03 Nd                             2.5E+O1                                 l.OE+03 W                              3.0E+01                                 3.OE+O1 Np                             l.OE+O1                                  l.OE+O1

• Values in this table are taken from Regulatory Guide 1.109 except for phosphorus (fish) which is adapted from NUREG/CR-1336 and silver, arsenic and antimony which are taken from UCRL 50564, Rev. 1, October 1972.

Page 101 of 156

Salem ODCM Rev. 19 FIGURE 2-1: SALEM VENTILATION EXHAUST SYSTEMS AND EFFLUENT MONITOR INTERFACES Simplified One Line, TO ATMOSPHERE R45 SKID L U

                                                                                      ...U AUX BLDG EXH   UNITS UGH'    HEPA  CHARCOAX, TER    FILTER     FILTER
                    ~i'
                                                    ~ -~ IOr iI ) /

Li

                                                                                      , U Page 102-of 156                                        I

Salem ODCM Rev. 19 FIGuRE 2-2: GASEOUS RADIOACTIVE WASTE DISPOSAL SYSTEM Simplified One Line Page 103 of 156

Salem ODCM Rev. 19 Table 2-1: Dose Factors For Noble Gases L Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Ki, Li Mi Ni Li _ Radioiuclide ,iCifm3)- -!Ci/m3) LCi/m3' uCi/m3) Kr-83m 7;5613-'02'. 1.93E+01 2.8 8E+02 "U 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

'i 87 5.9 5.92E+03             9.73E+03T           ,
                                                                             ;I-.

6.17E+03 Et0 1.03E+04 U Kr-88 1.47E+04 2.37E+03 1.52E+0 2.93E+03 "Kr-89 ' 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 i729E+03 ' .63E+04 7.83E+03 L Xel3.m 9.15E+01 4.76E+02-- , 1.56E+02 1.11E+03

 .      ,Xe-133m     -51E1                         9.94E+02        -       3.27E+02            1.48E+03
'Xe-133               ^       2.94E+02-,           3.06E+02     -O   -     3.53E+02            1.05E+03  L iXe-135m                      3 12E+03i            7.11E+02                3.36E+03           7.39E*02   L Xe-135                       1.81E+03             1.86E+03                1.92E+03           2.46E+03 Xe-137-                      1.42E+03             1.22E+04                1.511E+03'          1.27E+04' Xe-38             -          8.83E+03             4.13E+03                9.21E+03           4.75E+03   L Ar-41                        8.84E+03-:---        2.69E+03                9.30E+03           3.28E+03    1 Page 104 of 156

Salem ODCM Rev. 19 Table 2-2.1: Parameters for Gaseous Alarm Setpoint Determinations - Unit 1 Parameter Actual Default Units Comments Value Value X/Q calculated 2.2E-06 sec/r 3 USNRC Salem Safety Evaluation, Sup 3 VF as measured or (Plant Vent) fan curves 1.30E+05 ft3 /min Plant Vent - normal operation (Cont Purge) 3.50E+04 Containment Purge AF coordinated 0.25 N/A Administrative allocation factor with HCGS to ensure combined releases do not exceed release rate limit for site. Ci measured N/A p[Ci/cm 3 Taken from gamma spectral analysis of gaseous effluent Ks nuclide specific N/A -mrem/yr per Values from Table 2-1 _pCi /m3 nuclide specific N/A mrem/yr per Values from Table 2-1 3 _ _Ci/m Mi nuclide specific N/A mrem/yr per Values from Table 2-1 3 _LCi/m Sensitivities as determined N/A cpm per Monitor sensitivities are 1-R41 gCi/m3 or controlled under Public l-R12A cpm per Service Blueprint Document pCi/cc (PSBP) 315733 Setpoint calculated N/A cpm or Monitor setpoints are I-R41D . controlled under Public l-R12A ** PCi/sec Service Blueprint Document _(PSBP) 315733

      **Automatic Isolation function is applicable in all MODES except MODE 6 Page 105 of 156

i I L Salem ODCM Rev. 19 L Table 2-2.2: Parameters for Gaseous Alarm Setnoint Determinations`-Unit 2 Parameter Actual Default Units L X/Q Value. Calculated Value 2.2E-6 sec/mr3 Comments 1JSNRCSalem Safety LI _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 'Eva luation,.Sup3 VFasmeasured or Plant Vent fan ,curves -1 .30E+05 - f 3 /ln 'Plant Vent - normal operation-U Cont. Purge r' 3.,50E+0Q4+ CintainmentPure; 'i,'"- AF Coordinated 0.25 {N/A Administrative allocation factor L

                                      ,wit HCGS                                                                to ensure combi" no eced eease r4t
                                                                                                                                          -I o site. U 1    '"'                                 asured                      N/A                            ijectrT'A      from gamma l   i______________

_ i-_ v; r !* rs (t tt 01 analysis of gaseous effluen

                                         .nulide                          N/A            mrem/yr per           Values from Table 2-1

,__ _,__ specific pCci/rm3

                                        ,- ,Nu'clide,!                    N/A      ,,     memrper;                .ues from Table 2-14 specific                                             l.Ci/rn3

.:Nuchde N/A m imrm/rper Values from Table 2 "i G specific _______

1 C/ Sensitivities ias '

 , 41                              determined i'i',/m N/A                 cpm per. ,Monitor 3  or sensitivitiesare controlled under Public6Service L

2-R12A,, ^pm per p~i/c~ 3lI73 Blu` 4 ntomeo nu (PSBP) 1 D Setpdi'nt" 2-R41D

                   '                 'Calculated                         N/A                 cpm britl i Mitor setoints are o-oll g'Ci/sec          under Public Service BluePrint Documnent(PSBP) 3 157 3 4 "'`I L

L

   **A6mtic* '              Isolation           function,        is applicable in all MODES except MODE 6Ac-S -  ..: :         , .? :     '. .' : ft L

L L U Page 106 of 156 L

Salem ODCM Rev. 19 Table 2-3: Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations

• Atmospheric Dispersion ODCM Location Pathway(s) Controlling X/Q D/Q CONTROL Age Group (sec/m3) (1/m2) 3.11.2.1a site boundary noble gases N/A 2.2E-06 N/A (0.83 mile, N) direct exposure 3.11.2.1b site boundary inhalation child 2.2E-06 N/A (0.83 mile, N) 3.11.2.2 site boundary gamma-air N/A 2.2E-06 N/A (0.83 mile, N) beta-air 3.'l1.2.3 residence/dairy"* milk, ground infant 5.4E-08 2.1E-10 (4.9 miles, W) plane and inhalation
• The identified controlling locations, pathways and atmospheric dispersion are from the Safety Evaluation Report, Supplement No. 3 for the Salem Nuclear Generating Station, Unit 2 (NUREG-0517, December 1978).
  • Location and distance are determined from the performance of the annual land use census as required by ODCM CONTROL 3.12.2.

Page 107 of 156

Salem ODCM Rev. 19 U Table 2-4: kthway Dose Factors -wvAtmospheric Releases R(io), Inhalation Pathway Dose Factors - ADULT H (mre'ii/yrperCi/m3) L I I MS1 S M S H-3 1.26E+3 I 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3

 -:    f  t     .t82E+4      3.41E+3          3.41E+3             3.43341E+3                                           3.41E+3    I '

P-32 1.32E+6 7.71E+4 :t - - 8.64E+4 54O1EY4 6hN Cr51-i F95E+ 2 + I .44E+4 3.32E+3 1O Mn-54 3.96E+4 9.84E+33 1.40E+6 7.74E+4 6.30E+3 Fe- SS 2.46E+4 1.70E+4 ' _ t 7.21E+4' 6i.O3'tO

                                                                                            ,'__,                      3.94E+3-Fe-59         1.18E+4       2.78E+4                                         ,                  .02E+6 '       88E+     1.06E+4 1_

Co-57 ,, 6.92E+2 , ,, 370E+5 3.14Ef+4 6.71E.+2, Co-58 j 1.58E+3 ., ' 9.28E+5, ;l'O6E#$. 2.0E 3' Co-60 , L.15E+4' 5.97E+6 "2.'85E+54' 1.48E+4 Ni-63 f 4.32E+5> 3.14E+4 e- _ _ '.78E+5 l.734E+. 1.45E+4, Zn-65 3.24E+4 1.03E+5 - 6.90E*4 &64E+5 5.34E+4 4.66E+4 Rb-86 1.35E+5 - 1.66 5.90E+4 Sr-89 3.04E+5S., - . I ___j_ ,, -4OE+6 3.5OE*, 8.72E+3, Sr-90o 9.92E*7 - f F 7.22E,+5, 6.1OE+6, Y-91 4.62E+5 _ 1.70E+6 3.85E+5 1.24E+4 Zr-95 1.07E+5 Nb595 -iK, .41E-4i 3.44E+4

                            '7;.82E+3:      <

5.42E+4 1.77E+6

                                                           .a Jv.74E-3.- 5S.O5E+/-5t i O4E+m 42 XE+3 imF 1.50E+5 2.33E+4        U 03         .53                                                                                                   6,58E+2 -

Ru-106 6.91;E+4

                         .583+

Eu-1

                                       .5.83E+3 1.34E+5                   9.36E+6 l'.O45 5.O5,SE+S" ,,0t 9.12B+5     Sa2E+3'     U Ag-i lOmn      1.08E+4 '.OOE+4;                    -               1.97E+4                   4.63E+6       3,.02E-5    5.94E+3 Sb-4-24 Sb-125 I 312E4!4 5.34E+4 5.89E+2 5.95E+2 1F.'55E+1,.f 5.40E+1               -

F,,4,

                                                                                         ' 1.74E+'

6 kSL24E+4 46E05,

                                                                                                        -1:.O1      ' l26E+4' l

Te-125m 3.42E+3 1.58E+3 1.05E+3 I.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m Te-129m 1.26E+4 9.76E+3 5.77E+3 4.67E+3 3.29E+3 3.44E+3 4.58E+4 3.66E+4 9.60E+5 1.16E+6 1.50E+5 3.83E+5 1.57E+3 1.58E+3 U 1-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 6.28E+3 2.05E+4 I-132 1.16E+3 3.26E+3 1.14E+5 5.18E+3 4.06E+2 1.16E+3 I-133 8.64E+3 1.48E+4 2.15E+6 2.58E+4 8.88E+3 4.52E+3 1-134 6.44E+2 1.73E+3 2.98E+4 2.75E+3 1.OlE+O 6.15E+2 I-135 2.68E+3 6.98E+3 4.48E+5 1. 1E+4 - 5.25E+3 2.57E+3 Cs-134 3.73E+5 8.48E+5 - 2.87E+S 9.76E+4 1.04E+4 7.28E+5 Lo Cs-136 Cs-137 3.90E+4 4.78E+5 1.46E+5 6.21E+5

                                                  -8.56E+4 2.22E+5 1.20E+4 7.52E+4 1.17E+4 8.40E+3 1.1OE+5 4.28E+5    U Ba-140         3.90E+4       4.90E+l                               1.67E+1                   1.27E+6     2.18E+5       2.57E+3 Ce-141 Ce-144 1.99E+4 3.43E+6 1.35E+4 1.43E+6 6.26E+3 8.48E+5 3.62E+5 7.78E+6 1.20E+5 8.16E+5 1.53E+3 1.84E+5 U

Pr-143 9.36E+3 3.75E+3 l 2.16E+3 2.81 E+5 2.OOE+5 4.64E+2 f1 i i Nd-147 5.27E+3 6.1 OE+3 3.56E+3 2.21E+S 1.73E+S 3.65E+2 W Page 108 of 156 U

Salem ODCM Rev. 19 Table 2-4 (cont'd) Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - TEENAGER (mrem/yr per jgCi/m3) H-3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 C-14 2.60E+4 4.87E+/-3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 P-32 ' 1.89E+6 1.1OE+5 9.28E+4 7.16E+4 Cr-51 I - ' 7.50E+1 3.07E+1 2.1OE+4 3.OOE+3 1.35E+2 Mn-54 , 5.11E+4 1.27E+4 1.98E+6 6.68E+4 8.40E+3 Fe-55 3.34E+4 2.38E+4 1.24E+5 6.39E+3 5.54E+3 Fe-59 1.59E+4 3.70E+4 1.53E+6 1.78E+5 1.43E+4 Co-57 l 6.92E+2 5.86E+5 3.14E+4 9.20E+2 Co-58 - 2.07E+3 1.34E+6 9.52E+4 2.78E+3 Co-60 - I 1.51E+4 8.72E+6 2.59E+5 1.98E+4 Ni-63 f 5.80E+5 4.34E+4 3.07E+5 1.42E+4 1.98E+4 Zn-65 3.86E+4 1.34E+5 8.64E+4 1.24E+6 4.66E+4 6.24E+4 Rb-86 - ' 1.90E+5 1.77E+4 8.40E+4 Sr-89 4.34E+5 1_- 2.42E+6 3.71E+5 1.25E+4 Sr-90 1.08E+8 -

                                        -                    1.65E+7 7.65E+5   6.68E+6 Y-91    I  6.61E+5      l   -                                2.94E+6  4.09E+5   1.77E+4 Zr-95   l 1.46E+5         4.58E+4                 6.74E+4    2.69E+6   1.49E+5  3.15E+4 Nb-95 '     1.86E+4       1.03E+4                 l.OOE+4    7.51E+5  9.68E+4   5.66E+3 Ru-103     2.1OE+3          -                     7.43E+3    7.83E+5   1.09E+5  8.96E+2 Ru-106  i 9.84E+4       1-                        1.90E+5     1.61E+7 9.60E+5   1.24E+4 Ag-llOm    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      i 8.08E+2     7.04E+1        -       2.74E+6   9.92E+4   1.72E+4 Te-125m    4.88E+3      f 2.24E+3      1.40E+3       -       5.36E+5   7.50E+4  6.67E+2 Te-127m     1.80E+4       8.16E+3     4.38E+3     6.54E+4     1.66E+6  1.59E+5  2.18E+3 Te-129m     1.39E+4       6.58E+3     4.58E+3     5.19E+4     1.98E+6  4.05E+5  2.25E+3 I-131      3.54E+4        4.9 1E+4     1.46E+7    8.40E+4       -      6.49E+3  2.64E+4 I-132       1.59E+3     ' 4.38E+3      1.51E+5    6.92E+3       -      1.27E+3   1.58E+3 1-133    I 1.22E+4      . 2.05E+4     2.92E+6     3.59E+4              1.03E+4   6.22E+3 1-134       8.88E+2       2.32E+3     3.95E+4     3.66E+3       -      2.04E+1   8.40E+2 I-135    I-3.70E+3      I 9.44E+3     6.21E+5      1.49E+4      -      6.95E+3   3.49E+3 Cs-134     5.02E+5     l 1.13E+6          -       3.75E+5     1.46E+5  9.76E+3   5.49E+5 Cs-136      5.15E+4     I 1.94E+5         -        1.1OE+5    1.78E+4  14 09E+4  1.37E+5 Cs-137     6.70E+5        8.48E+5         -       3.04E+5     1.21E+5  8.48E+3   3.11E+5 Ba-140      5.47E+4     ' 6.70E+1         -       2.28E+1     2.03E+6  2.29E+5   3.52E+3 Ce-141     2.84E+4         1.90E+4                8.88E+3     6.14E+5  1.26E+5   2.17E+3 Ce-144      4.89E+6       2.02E+6                  1.21E+6    1.34E+7  8.64E+5  2.62E+5 Pr-143    i 1.34E+4     j 5.3 1E+3        -       3.09E+3    4.83E+5   2.14E+5   6.62E+2 Nd-147    I 7.86E+3        8.56E+3        -       5.02E+3     3.72E+5  1.82E+5   5.13E+2 Page 109 of 156

Salem ODCM Rev. 19 Table 2-4 (cont'd) L Pathway Dos'e FZt1rZZ- AtmosphericReleases R(io), Inhalation Paway Dose Factors - CHILD (-nere/yr per ,Ci/m3) 1.12E+3:, 1.12E+3 I.12E+13 1.12E+,31 II','1.12E+3 1.12=E+344 L? C:14 3.S9Ef4 6.73E+3 6.733E+/-3 6.&73E+3 6.73E+37 3E+3E+3 6.73E+3> P-321 2.60E46f` 1.14E+5 - .22E+~4 9.8E4 Cr-i; - e 8.55E+1 2.43zE+1. 1.70E+4i c 1.08E+3 1.54E+2 6F&55:

429E+41 474E+4,

_ 4Mn-4 2;524i LOOE+4 1.58E+/-6 1.1 1E+/-5 2.87E+3 2.29E+4 9,51E+3 7 7E3 U Fe-59 Co-5; 2.07 3344 9.03E+

5.07E+5 1 .2 64 7.:07E+4 1.32E+4 1 671E+

l. 107E+ L Co-58 ; - :177E+3 _ _.llE+f 3,44E+4 3.16E+3 C0-6:60`? 1.3 1E+  : -  : -.. . 7.07E+: 9.62E+/-4 '.26E+4 Ni63. r 8.21E+5 - 4.63E+4t: 25E+5 6.33E+I3 2.80E4 Zn-65  : 426E+04 1A.9+ .63E4 7.03E+4

                                 .l98E5- ;

L -Rb-g6. _______ - - ___ '799+3 1.14E+f5.

Sr-89.

599E  : S,

                                     -                                                      2.16E+6           1,67E+5              1.72E+4 Sr-90      r0     1.O1E+             - .;,.           -                     -                1.48E+7         3.43B+5               6.+

Y-91 9.14E+5 - . 2.63E+6  :.84E+5 2.44E+4 L Zr-95 1.90E-S'i .4ASE+. - 5.96E+4 2.23E+64 6.1I;E 37.0E+,4 Nb-95' 2.35E+4 9.188E+ - &62E+3 :6. 14E+5 ;3.7.0Q+ 6.5E3 L Ru-103 Ruj-1O064,i 2:79E+3 1.36E+5i '-

                                    -               -                    7.03E 3 :6.62E+5 : 4.408+4:
                                                                          .4E+5              1.43+7          4.29+

_.07E

                                                                                                                                     .9E+/-4~   L Ag-h1rn             1.69E44      1.14E+4               5;                 2.12E+4 :               48E+6        1.OIOE+5           i9;4E+

i:Sb-.124 .3 5t.74E4 cr 7.40E+2 1.26E+ 2 : :-

• 3.24+6; 1.64B5 2.OE- 4 L

Sb-125r Te-125m 9,.84E+4 6.73E3-`3 6 7:59E+2. 2,.33E+3.

                                                 .9.1OE+1::

1 .92E+3 f

                                                                                        2.32E+6 4.77E+5ff; 4.03E+4 3.38E+4 2.0 7E+4, 9.14E+/-:    L Te-127mt~~_ 2.49E+4-t Th-129m            1.92E+41' 8.55E+3t 6.85E+3 6O7+3 6.33E+_32 6.3'6E+4
                                                                           .0       `

J4AM

                                                                                           -1j
                                                                      ;'5.03B+4 L76B6 ',82E+/-5
                                                                                                                .4E4                 4 2+

3104E 3O4E L

 -131             4481E4       ;4 81E+4:           1.62E+                7.88E+4                             2'84E+3, 1                .2_73E+

I-132  : .12E+3 4.07E+3 1.94E+5 6.2E++3 3.38E+4 5322tE+ .;< -  :. 5A48+3 1.88E+3 7.70E+3' L 166E+4,~2.03E+4 r3.85E+6: L-33 -I 1-134 1.7B+03.f'; 2.16E+3 507E4 30+3 .& >95E2 9.E2 I-135 = 4.92E+3 8.73E+3 7.92E+5 1'.34E+4 - 4i44E+3 T 4.14E+3 Cs-134::~_ 6e.51E+5> L'OIE+6 - 3.30E+5 121E+5~ 3 85E+3 2.259+5 Cs-136 Cs-137 6., 1iSlE+4 9.07E+$5 1;.71+5E 8.25E+5 _ _ 9.55E+4 2.82E+5

                                                                                            ;145E+4 4. 18E+3 1.04E+%5        362E+3 1.16E+5 1.28E0+54  L

.Ba-140: Ce-141 7;."40E+4, 6.48E+1V 33;92E+4 195+49

                                                      -9                 2.11E+1 8.55E+3 1i 74E+6, 5.44E+5 1i,2E+5 5.66E+4.

4.33E+3' 2.90E+3 U Ce-'144 Pr-143 6.77E+65 ' 2.12E+6 1.85E+4'. 5.55E+3

1. 7E+6 3.OOE+3 1.20E+7 4.33E+5 3.89E+5 9.73E+4 3.61E+5 9.14E+2 L?

Nd-147 1.08E+4 873E+3 ' - 4.81 E+3 3.28E+5' 8 21 E+4 6181-E+2 Page 110 iof 1;56 L

Salem ODCM Rev. 19 Table 2-4 (cont'd) Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - INFANT (mrem/yr per ,uCi/m3)

                     -   -       -         -       n H               6.47E+2          6.47E+2       6.47E+2    6.47E+2   6.47E+2    6.47E+2 C-14      2.65E+4  5.31EE+3         5.31E+3       5.31E+3    5.31E+3   5.31E+3    5.31E+3 P-32      2.03E+6  1.12E+5            -             -           -      1.61E+4    7.74E+4 Cr-51                               5.75E+1       1.32E+l    1.28E+4   3.57E+2    8.95E+1 Mn-54              2.53E+4                        4.98E+3    I.OOE+6   7.06E+3    4.98E+3 Fe-55     1.97E+4  1.17E+4                             -     8.69E+4   l.09E+3    3.33E+3 Fe-59     1.36E+4  2.35E+4                                   1.02E+6   2.48E+4    9.48E+3 Co-57              6.51E+2                                   3.79E+5   4.86E+3    6.41E+2 Co-58              1.22E+3                                   7.77E+5   1.11E+4    1.82E+3 Co-60              8.02E+3                                   4.51E+6   3.19E+4    1.18E+4 Ni-63     3.39E+5  2.04E+4            -                      2.09E+5   2.42E+3    1.16E+4 Zn-65     1.93E+4  6.26E+4            -           3.25E+4    6.47E+5   5.14E+4    3.1 E+4 Rb-86              1.90E+5            -             -                  3.04E+3    8.82E+4 Sr-89     3.98E+5       -              -             -       2.03E+6   6.40E+4    1.14E+4 Sr-90     4.09E+7       -              -             -       1.12E+7   1.31 E+5   2.59E+6 Y-91      5.88E+5       -              -             -       2.45E+6   7.03E+4    1.57E+4 Zr-95     1.15E+5  2.79E+4             -          3.1 E+4    1.75E+6   2.17E+4    2.03E+4 Nb-95      1.57E+4 6.43E+3             -          4.72E+3    4.79E+5   1.27E+4    3.78E+3 Ru-103    2.02E+3       -              -          4.24E+3    5.52E+5   1.61E+4    6.79E+2 Ru-106    8.68E+4       -              -          1.07E+5     1.16E+7   1.64E+5   1.09E+4 Ag-i l On 9.98E+3  7.22E+3             -          1.09E+4    3.67E+6   3.30E+4    5.OOE+3 Sb-124    3.79E+4  5.56E+2          1.OlE+2          -       2.65E+6   5.91E+4    1.20E+4 Sb-125    5.17E+4  4.77E+2          6.23E+1          -        1.64E+6   1.47E+4    1.09E+4 Te-125m   4.76E+3   l.99E+3          1.62E+3         -       4.47E+5    1.29E+4   6.58E+2 Te-127m    1.67E+4 6.90E+3          4.87E+3       3.75E+4     1.31E+6  2.73E+4    2.07E+3 Te-129m    1.41E+4 6.09E+3          5.47E+3       3.18E+4     1.68E+6  6.90E+4    2.23Ef3 I-131      3.79E+4 4.44E+4           1.48E+7      5.18E+4         -     1.06E+3    1.96E+4 I-132      L.69E+3 3.54E+3           1.69E+5      3.95E+5        -      1.90E+3    1.26E+3 1-133      1.32E+4  1.92E+4         3.56E+6       2.24E+4         -     2.61E+3    5.60E+3 I-134      9.21E+2  1.88E+3         4.45E+4       2.09E+3         -     1.29E+3    6.65E+2 I-135      3.86E+3  7.60E+3         6.96E+5        8.47E+3        -     1.83E+3    2.77E+3 Cs-134     3.96E+5  7.03E+5             -          1.90E+5     7.97E+4  1.33E+3    7.45E+4 Cs-136     4.83E+4  1.35E+5             -         5.64E+4      1.18E+4  1.43E+3    5.29E+4 Cs-137     5.49E+5  6.12E+5             -          1.72E+5     7.13E+4  1.33E+3    4.55E+4 Ba-140    5.60E+4  5.60E+1             -          1.34E+1     1.60E+6  3.84E+4    2.90E+3 Ce- 141   2.77E+4  1.67E+4             -         5.25E+3      5.17E+5  2.16E+4    1.99E+3 Ce-144    3.19E+6  1.21E+6             -          5.38E+5     9.84E+6  1.48E+5    1.76E+5 Pr-143    1.40E+4  5.24E+3                        1.97E+3     4.33E+5  3.72E+4    6.99E+2 Nd-147     7.94E+3  8.13E+3                        3.15E+3    3.22E+5   3.12E+4    5.OOE+2 Page 111 of 156

Ii Salem ODCM Rev. 19

                                                          'Table 24 (cont'd)                                                                        L Pathway.Dose Factors - Aftosphenc Releases R(io), Grass-Cow-Millk Pathway Dose.Factr- ADULT                                                                      U (mrerm/yrper -gCi/m3) fbr H-3 and C-14                                                                   L
                                                *, mreniyr              per .i.Ci/sec),for others U

I H-3 C-14 ,i i ' 1- -

3.63E+t5'i' A-I 7.63E72~ 'I17.'63E+21 7.26E26E+4 7.63E:2 7.26E+4 7.63E+2:

7. 26E+4 7.6 3E+2 726Et4' 7.63E+2 7.26E+4 L

P-32 1.71E+10 1.06E+9 _ _ - 1.92E+9 6.6.E+8 Cr-51 - .- , 171;E+4 6.30E+3 3.80E+4 7.20E+6 2.86E4 Mn-5 F3D55 '2.5

                    -O.4E+6r        8A 1 73        -.

2.50E+~6 7E+6

                                                                                                                        .2.E7

_ 5E+ 6" 16E6 4.04E+6 L Fe-59 . .OOEk7 ' - .' S195E+T7 - 1z 2.33E+8 2.68E+7 7- 1.28+6 - - 213E+6 Co5 2+6 -____ ,* 957E+7' 1.~06E+7 Co-60 .64E+7 Ni-O; Zn-65 6.33rE+9 1.37E+9.

                                     .6+

4.36E+94

2.92E+9:

                                                                                            <308+

9735E+7i 2.:75E+9

                                                                                                                                         .62E+7 2.26,E+8; 7E L

Rb-86 - 2.59E9 1 - - 5.l'-I 4 .21t+O Sr-89: 1.45E+9', - .  : ... - 2.3+/-81 4 16E+ Sr-90 4.68E+0 - d,15E..iO L...I A-.1.3+9 Y-91;- Zr-95' 8.60E+3 9.46E+2 ,. 3.03E+2 4.76E+2 - 4.73E+ 6 0'9.62E+5

                                                                                                                                    , 2.30E+2 2.05E+/-2       L Nb-95          -8.25E+4'            4.59E+4                                       4.54E+4                 -              2.79E 8      2.47E 4'7 Ru-103 Ru-1066
               -:1.02E+3 2.04E+44 !.32E6i
                                       -.r  >

3.89E+3 3.94E,*4 -

                                                                                                          -          - 1.19E+5 2.20EO 3.20E7 39 2E+4+33
                                                                                                                                           '10.068 L

Ag-1 1O i 5.83E+7 5.39Ef7 "-; -, Sb-124 .2.57E+7 4.86E45 6.24E+4 ;_ _ . 2.OE+7,' 7g.3'1E8 B1.02E+7 Sb-125 2.04E+7 2.28E'+5- 2.08E+4 - ' '158:+7 "225E+8 '486E+6 Te-125m 1.63E+7 5.90E+6 4.90E+6' :6.63E+7 - 6.50E+7 ;2.'8E+6 Te-127m' 4.58E+7- . 1.64E47.;! 1.17Ei 1'.86E8 ' . 1.54E+'8 58E+6 2.52E+8 . 3.04E+ .9.57E+6 Te-129m I-131 6.04E+7 2.96E+8 2.25E 4.24E+8

                                                  '    2.08E+7 1.39E+11.                 727E+8               -                 1.12E+8      2.43E+8'      U 1-3               .4E1         4.37E-1              1.53E+1                   69E1                  -82E2                        15E1 L

I-133 I-134 , 3.97E6. -6.90E+6. 1.O13E+9 i 1.20E+7 ' rirjl :t 6,20E*6 I2.1OE+6 U 1-135-, ~139E+4 ~3.63E+4 2.40E+6 5,83E#-4~ _____ 4.E+4 1.34E+4" Cs-134 -- 5.65E+9, : 1.34E+ I -  : 4.35E+9 '144E+9 2.35E+8" .II E+1O Cs-136, 2.61E+8 1J.03E+9 " , 5.74E+8 7.87E+7 1.17E+8 7,42E+8 Cs-137 - 7.38E9- 1.O1E+O - 3.43E+9 1.14E+9 4.95E+8< 6.61E+9 Ba-140 2.69E+7 3.38E4 , 1.1SE+4 '--934

                                                                                                                        &654E+7       ;.76E6; Ce-I41 Ce-1444,o 4.84E+3 3.58E+5 1.59E+2 3.27E+3 '

1.50E+S 6.37E+1 1.52E+3-8.87E+4 3.68E+1 ,

                                                                                                                -        1.25E+7 1.21E+8 6.9.6E+5 3.71E+

1.S2E+4 7.88E+O L Pr-143 Nd-147, 9.42E+1 1.09E+2 - , 6.37E+1 - 5.23E+5 6.52E+O Page 112 of 156 U

Salem ODCM Rev. 19 Table 2-4 (cont'd) Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - TEENAGER (mrem/yr per jiCi/m3) for H-3 and C-14 (m2

• mnrern/yr per pCi/sec) for others H-3 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+5 1.34E+5 1.34E+5 I 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 1.1 OE+4 7.13E+4 8.40E+6 5.OOE+4 Mn-54 1.40E+7 - 4.17E+6 2.87E+7 2.78E+6 Fe-55 4.45E+7 3.16E+7 - . 2.OOE+7 1.37E+7 7.36E+6 Fe-59 5.20E+7 1.21E+8 - 3.82E+7 2.87E+8 4.68E+7 Co-57 . 2.25E+6 - - 4.19E+7 3.76E+6 Co-58 7.95E+6 ._ _ - 1.1OE+8 1.83E+7 Co-60 - 2.78E+7 - - 3.62E+8 6.26E+7 Ni-63 1.18E+10 8.35E+8 _ . - 1.33E+8 4.01E+8 Zn-65 2.11E+9 7.31E+9 - 4.68E+9 - 3.10E+9 3.41E+9 Rb-86 - 4.73E+9 _ - - 7.00E+8 2.22E+9 Sr-89 2.67E+9 . I . - 3.18E+8 7.66E+7 Sr-90 9.92E+7 .

                                       -             .           9.60E+6   7.22E+5  6.10E+6 Y-91     1.58E+4         -                             *            .       6.48E+6  4.24E+2 Zr-95    1.65E+3      5.22E+2          -          I7.67E+2                  1.20E+6  3.59E+2 Nb-95    1.41E+5      7.80E+4           .           7.57E+4         -       3.34E+8  4.30E+4 Ru-103   1.81E+3                                    6.40E+3         -       1.52E+5  7.75E+2 Ru-106   3.75E+4         -                          7.23E+4                 1.80E+6  4.73E+3 Ag-l lOm 9.63E+7      9.11E+7           -         I 1.74E+8         -       2.56E+l0 5.54E+7 Sb-124   4.59E+7       8.46E+5       1.04E+5      j   -           4.01E+7   9.25E+8  1.79E+7 Sb-125   3.65E+7       3.99E+5      3.49E+4       !    -          3.21E+7   2.84E+8  8.54E+6 Te-125m  3.OOE+7       1.08E+7      8.39E+6                         -       8.86E+7  4.02E+6 Te-127m  8.44E+7      2.99E+7       2.O1E+7         3.42E+8         -       2.10E+8  l.OOE+7 Te-129m  1.l1E+8      4.10E+7       3.57E+7         4.62E+8         -       4.15E+8  I.75E+7 I-131    5.38E+8      7.53E+8       2.20E+11        1.30E+9         -       1.49E+8  4.04E+8 1-132    2.90E-1      7.59E-1       2.56E+1         1.20E+0         -       3.3 lE-1 2.72E-1 I-133    7.24E+6       1.23E+7       1.72E+9        2.15E+7                 9.30E+6  3.75E+6 1-134 1-135    2.47E+4       6.35E+4      4.08E+6         l.OOE+5                 7.03E+4  2.35E+4 Cs-134   9.8 1E+9     2.3 1E+10                     7.34E+9       2.80E+9   2.87E+8   1.07E+10 Cs-136   4.45E+8       1.75E+9         -          J 9.53E+8       1.50E+8   1.41E+8   1.18E+9 Cs-137   1.34E+10      1.78E+10         -        J  6.06E+9       2.35E+9   2.53E+8  6.20E+9 Ba-140   4.85E+7       5.95E+4         -        _2.02E+4          4.00E+4   7.49E+7  3.13E+6 Ce-141   8.87E+3       1.35E+4         -            2.79E+3                 1.69E+7  6.81E+2 Ce-144   6.58E+5       2.72E+5         -            1.63E+5         -       1.66E+8  3.54E+4 Pr-143   2.92E+2       1.17E+2          -         I6.77E+1                  9.61E+5  1.45E+1 Nd-147   1.81E+2       1.97E+2          -           1.16E+2                 7.11E+5  1.18E+l Page 113 of 156

         .: I  u    : .e V="          ,

Salem ODCM Rev. 19 Table 24 (cont'd) L Pathw'ay Dose Faito - Releases &Anosphec I'I R(io), Grass-Cow-Milk.Pathway Dose Factors- CHILD I (mremn/yr per jiCi/m3) for H-3 and (C-1 7(m2A memyr per.u.tCi/s~ec) for others n II I:vL.57E+i3` 1.57E+3 41;57E+3 I157E+3 '1:.57E+3' 1.57E+3 C-14 i 65E+6 3.29E+5 3.29E+5 322.9+59 3.-29E+5 3.29E+5 . 3.29E+5d I11 P-32 ;:7.;77E+1 3.64E+9 - -  : -t (25E+9; 3.00E+9 Cr-5V8 ,

• 5.66E+4 1.55E+4 1.03E+5' 5.41E+6 1.02E+5I . I Mi54:

2:09E+7 - 5.87E+6 - 1.7,6E+7 5.58E+6

     'F-5                     1.12E+8                 593E+7:                           ~     -                                                   3E7                1IOE+7             1.4E+71i
.. Fe-59                                              l9E+8                                            1.20E+8;                              56 .                   2.071E+71 Co-s7                      __              _          3.84E+6                                 -;*                        -                                           3.14E+7           7.77E+6-Co-58            .           K>'             7 i                    .21E+7,                  -                        -                  ________                  7.08E+7           I 72E+7

,_:___-i_.__: 2.39E+:8- 127E+

N-3 2.96E+I0 1.59E+9

                                                  ;'Co-60:

4.32E+7

                                                                                              -l    ,_

i  :.07E+8101E+9 L 'Z-651C8,: 4A13E+9, t1.:1OE+1' i.-.'t ;74 '6.94E+9:S , 1.3E+9 .85E+9

R6: . 8.77E+9 - - - 5.64E+8 5.39E+9 Sr89 662E+9 2.56E+8 1.89E+8~

Sr-90 Y91 i 1 ..12E+11 3.91 E+4

                                                                                                                                                            ,        521E+6 1.51E+9  2.83E+10 1.04E+3 U

LI Zr-95 Nb-~'95 3.84.E+3 8.45E+2 ,t- ____ 1.21;E+3 8.841E+5. 2.2E+8 7.52E2, 884EI' 93 3.'18E+5 1.24E+5 ,.-

                                                                                                                            ,126E+5         _                 _     _

__ _2_.29_ .RU-1031 -4.29E+3 .

,RU406                . .24E+4                            -
                                                                                             -                       ,1.108E+,4 1.25E+SE,:;                                      l..
                                                                                                                                                                            +           1-5
                                                                                                                                                                                        .I5E+4:

c Ag-h-rn 2.09E+8. 1;.41E+8 .6 ;8 I.13E-+8 Sb-l24 Sb-125 1.09E+8 8'70E+7

                                                    . 141iE+8:
                                                ;i 14E+6..4 E 2;40E+5 '
                                                                            '8.06E+4                            ,

6.03E+7 4.85E+7 6.79E+ 2.08E8 3 S8E+T7 1.82E+7 I c ATe4125m 77.38E+7 2.OOE+7 2.07E+7 7,12E+7 9.84E+6 IU _t______ Te-127mrd 2.;08E+8 5.60E+7T J 4.97E+7 3.93E+8 - 1.68E+8 247E+7 - r

'e129mii                     2.72EX+8                17.61E+7 8.78E7                                             8.00E+8                            ,             3.32B8             4.23E+7
  -131'.                      1.30E+9                 1.31E+9                          4.34E1                      2.5E+9                         -       '_             17E+8             A     8 1-132                     -6.86E-1                    1.26E+O f ( .5.85E+ 1                                         1.-93E+O                            -            18E+              5.'80E1 I-133                         1;76E*7                 2.18E+7                      4.-04E+9                        3.63E+7                .                          8;77E+6           8.23E+6';

1I-134 .. ,4 - 55.84E+4 Cs-134,00 ':' 2'.26E+1 r3.i71E+1iO T. 1.05E+5

                                                                                 ~

i-.61E5 1.1'5E+1O 4.I3E+9 '.OOB+8 G9.30E+64.97E+4 8.OE+4 7.83E+9 LI U /Cs-136 1.OOE+9 3.22E+1O' 2.76E+9 3.09E+l:0

                                                    'Cs137

__..__ 1.47-E+9 IOlE+10 0 3.34E+4

                                                                                                                                          ,2.19E+8' 3.62E+9 6 12E+4 9.70E+7 i 1.93E+8 5.94E+7 1.79E+9 4.55E+91 6.84E+6 U

,Ba-140 1.17E+8 ' 1.03E+5 - ' ACe-141L' C61444 2.19E+4

                         ; 162E+6 1.09E+4 5.09E+5 4.78E+3 2.82E+5                     -
                                                                                                                                                 -                  1.36E+7-i 1i33E*8 1.62E+3 8.66E+4      U Pr-143'                      7.23E+2                  2.17E+2                                   "                  1.17E+2                    -                     7.80E+5            3.59E+1
!Nd.447                      4.45E+2                  3.60E+2                                                       i1.98E+2                     -                   5.71E+5           2.79E+;

Page,114 of 156 U

Salem ODCM Rev. 19 Table 2-4 (cont'd) Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - INFANT I(mrem/yr per ,uCi/m3) for H-3 and C-14 (m2

• mnrem/yr per giCi/sec) for others H-3 - 2.38E+3 2.38E+3 2.38E+3 !2.38E+3 2.38E+3 2.38E+3 C-14 P-32 3.23E+6 6.89E+5 6.89E+5 6.89E+5 T6.89E+5 6.89E+5 6.89E+5 1.60E+11 9.42E+9 - 2.17E+9 6.21E+9 Cr-51 - 1.05E+5 2.30E+4 I 2.05E+5 4.71E+6 1.61E+5 Mn-54 3.89E+7 - 8.63E+6 - 1.43E+7 8.83E+6 Fe-55 1.35E+8 8.72E+7 JI 4.27E+7 1. llE+7 2.33E+7 Fe-59 2.25E+8 3.93E+8 - - I 1.16E+8 1.88E+8 l.55E+8 Co-57 8.95E+6 - _ 3.05E+7 1.46E+7 Co-58 2.43E+7 - - 6.05E+7 6.06E+7 Co-60 8.81E+7 - _ 2.1OE+8 2.08E+8 Ni-63 3.49E+10 2.16E+9 - .2+1.07E+8 1.21E+9 Zn-65 5.5590E .0E+10 9.23E+9 - 1.61E+10 8.78E+9 Rb-86 2.22E+10 - 5.69E+8 l.1OE+10 Sr-89 1.26E+10 - - 2.59E+8 3.61E+8 Sr-90 1.22E+11 - - 1.52E+9 3.10E+10 Y-91 7.33E+4 - - - - 5.26E+6 1.95E+3 Zr-95 6.83E+3 1.66E+3 - I 1.79E+3 - 8.28E+5 1.18E+3 Nb-95 5.93E+5 2.44E+5 -1.75E+5 - 2.06E+8 1.41E+5 Ru- 103 8.69E+3 1.81 E+4 - 1.06E+5 2.91E+3 Ru-106 1.90E+5 - I 2.25E+5 - 1.44E+6 2.38E+4 Ag-11Om 3.86E+8 2.82E+8 - 4.03E+8 - 1.46E+10 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E+5 - 1.31E+8 6.46E+8 6.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 l - 9.38E+7 l.99E+8 3.07E+7 Te-125m 1.51EE+8 5.04E+7 5.07E+7 l - - 7.18E+7 2.04E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 11.04E+9 1.70E+8 5.1OE+7 Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 - 3.34E+8 8.62E+7 I-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 1.15E+8 1.41E+9 T-132 1.42E+O 2.89E+O 1.35E+2 3.22E+O _2.34E+O 1.03E+O I-133 3.72E+7 5.41E+7 9.84E+9 6.36E+7 9.16E+6 1.58E+7 I-134 1.O1E-9 I-135 1.21E+5 2.41E+5 2.16E+7 2.69E+5 8.74E+4 8.80E+4 Cs-134 3.65E+10 6.80E+10 1.75E+l0 7.18E+9 1.85E+8 6.87E+9 Cs-136 1.96E+9 5.77E+9 2.30E+9 4.70E+8 8.76E+7 2.15E+9 Cs-137 5.15E+10 6.02E+10_ 1.62E+10 6.55E+9 1.88E+8 4.27E+9 Ba-140 2.41E+8 2.41E+5 5.73E+4 1.48E+5 5.92E+7 1.24E+7 Ce-141 4.33E+4 2.64E+4 - I 8.15E+3 1.37E+7 3.11E+3 Ce-144 2.33E+6 9.52E+5 - 3.85E+5 1.33E+8 1.30E+5 Pr-143 1.49E+3 5.59E+2 - 2.08E+2 1- 7.89E+5 7.41E+l Nd-147 8.82E+2 9.06E+2 - 3.49E+2 I 5.74E+5 _5.55E+1 Page 115 of 156

Salem ODCM Rev. 19 Table 2-4 (corifd) L Pathway Dose Faors;- Aitopheri R-eleases R(io), Vegetation Pathway Dose:Ftactors - ADU;ILTi (nreni/yr per #Ci/m3) for H-3 ,aiidC-14 I (m2 t mrem/yr per ,uCi/sec) for others U

                                 -2.2                  E+3-2.26E+3                           2,J.26E+-3                2.26E+3               2.26+3        `2.26FE+3 C-14 ;:8.97E+5:                             t.79E+5                  1.79+15                   7E+5                  7 +                   1.795        ;79E+

p-32 ' .40Et9 8.73E+7 ._______ - - 1.58EtV8 5.42E+7 ______ - .. 79,E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 I5 ___ _ __ i9.27E+ 9,.54E+8 5.94E+i

     ';55          t2;O913+/-8              K' 1A5E+/-8                          -            .      -           ;        &0E+                   :              3. 7E+

S2;9E+fl7

      ,le-59              .27Et8            ,2.99E+                             .                       .         :           5+           -         +      l.14E+8);%
   -57                    -                  1.17.E+7                           ,                                                            2.9 7E+8.      1,95E       I1 Co-58.                      -      ,       3.09E+7                                    '                 -                     ;            6.26E+82 2-"     I 6.2E+7

,Co-6, 1 67E+8 ,, - 3.14E+9 3.E+8 Ni-63, a;,>, ,1.04E.+1'0, 7.21E+8 , = - .50E#8 i 4E Z65j :>3. 17E+/-8 1.OE+9 i 6.75E+8:6{) ,- 4.56Et L Rb-86. Sr-89 :9.96E,+9

                                .            2.19E+8 .__,___--

4.32E+-,7 116QE+; 1.02Et+8$ 2.86E+8 U Sr-90 - 6.05E+11 - . - . ,' ' ___'___ 1 1 i.48Ei+O t75E+1O Y-91'

.Zr-95,:
                         ,13E+6 1-,19E+6 3.81E+5 5.97+
                                                                                                                                     .       2,82E+9 1;21B+;Q 1.37E5:

2.58E+/-5 G

                      -  1.42E+          : 7.91E+4                          -,               7.8i,4         tNb-95 Sa-      k-,-        !480E8              4.25E+/-4 Ru-1Q3-              4.80E+6                 -;         . ' '.31                                                       -                  5.618          2.07E+6O R9-1Q6                 1.93E+8                 -..                   _____;__               3.72E+8                  ;.25E+1O                  2           2.44E A,, g-llOi       ¢f- 1.06-E+               9.76E+6                  _____,           __     l.92E+T,              ____                73,98E9i9           5,80Et6b Sb-124,                1,E+,8          -.r96E6 1                        2.52E+5                                   , 8.08E+7                   2       5         44
'Sb-125.-                1.36E+8              1.52E+6                   1.39E5                     -              tI1.05E+8            -1.5OE+9             3125E+7 Te-125,m               9.66E+7              3.50E+7                   2.90E,+7               3.93E+8,                                        386E+8        1.29E-7 u

Te127m 3A49E+8 '1.25E+8 ' 8,92E+7 1.42E+9 _-_,_t_. 1.17E+9 4.26E+7 Te-129m 0255Et8 9.50B+7 .875E+7 7.06E+9

                                                                                                                                -    ,         1.28E+9      4.031Ei7 1-131                   8,09E+7.              1.16E+8                 :3.7E+10                1.98E+8                                           .5+           .3+

1-132 I-133r . 5.74Etl 2.12E+6 1.54E+2 3.69E+6 5.38E+3 5,42E+8 2.45E+2 6.44E+6 __ 2,89E1, 3.3 1E*e6 : 5.38~tl 1.1Z6 u I-134

 '-135 Cs-34.;4.66E+9 1.06E;4 i.08E+4 2.88E-4,I 5.00E-3 1.07E+5 f.1lE+102
                                                                      -7.4E+6
                                                                                            .4.59E-4 ,::-,

1,71E+5 3.59E+9 .1i~ E+9 Al.94+8

                                                                                                                                 .21E+5 I2.51E-7       1.03E-4 3.94+4' 997E3+9
                                                                                                                                                                       £ Cs-136 TCs-i37i 4.20E+7 6336E+9
                                             -L66E+8 8.70E+9                 ;      -
                                                                               -              9.24E+7 2.95E+9 ,, 9.8HE8 1'27E+7                41 89E+7 16'8E+8 6

149E+8 5.70E+9 u Bna-140 1 .29,E8,62E+5 5.49E+4 9.2E+4 2.65+ 8.43E+5 Ce-141  ; 1.96E+5 1.33E+5 : ' 6.17E+4 . -tD, '.08E+.8 15lE+4 Ce-144 3.29E+7 1.38E+7 - 8.16E+6 . . .lE+iO ls,77E+6 Pr-143' 6.34E+4 2.54E+4 r  ;.+4 +4

• 2.78E+8 3.14E+3 Nd-147 3.34E+4 3.86E+4 ________ 2.25E+4 1.85B+8 r- 2.31E+/-3 U

Page .116 of 156 L

Salem ODCM Rev. 19 Table 2-4 (cont'd) Pathway Dose Factors - Atmospheric Releases R(io), Vegetation Pathway Dose Factors - TEENAGER (mrem/yr per iLCi/m3) for H-3 and C-14 (m2

• mrem/yr per jCi/sec) for others H-3 2.59E+3 2.59E+3 I 2.59E+3 2.59E+3 2.59E+3 2.59E+3 C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 P-32 1.61E+9 9.96E+7 1.35E+8 6.23E+7 Cr-51 3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Mn-54 4.52E+8 - 1.35E+8 - 9.27E+8 8.97E+7 Fe-55 3.25E+8 2.31E+8 - 1.46E+8 9.98E+7 5.38E+7 Fe-59 1.81E+8 4.22E+8 - 1.33E+8 9.98E+8 1.63E+8 Co-57 1.79E+7 - 3.34E+8 3.OOE+7 Co-58 4.38E+7 - 6.04E+8 1.O1E+8 Co-60 2.49E+8 - 3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13E+9 1.81E+8 5.45E+8 Zn-65 4.24E+8 1.47E+9 9.41E+8 6.23E+8 6.86E+8 Rb-86 2.73E+8 4.05E+7 1.28E+8 Sr-89 1.51E+10 - 1.80E+9 4.33E+8 Sr-90 7.51E+11 - 2.11E+10 1.85E+l1 Y-91 7.87E+6 - 3.23E+9 2.1 lE+5 Zr-95 1.74E+6 5.49E+5 - 8.07E+5 1.27E+9 3.78E+5 Nb-95 1.92E+5 1.06E+5 - 1.03E+5 4.55E+8 5.86E+4 Ru-103 6.87E+6 - 2.42E+7 5.74E+8 2.94E+6 Ru-106 3.09E+8 - 5.97E+8 1.48E+10 3.90E+7 Ag-i lOm 1.52E+7 1.44E+7 - 2.74E+7 4.04E+9 8.74E+6 Sb-124 1.55E+8 2.85E+6 3.51E+5 1.35E+8 3.1 lE+9 6.03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+5 1.88E+8 1.66E+9 5.OOE+7 Te-125m 1.48E+8 5.34E+7 4.14E+7 - 4.37E+8 1.98E+7 Te-127m 5.51E+8 1.96E+8 1.31 E+8 2.24E+9 - 1.37E+9 6.56E+7 Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 - 1.38E+9 5.81E+7 1-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 - 2.13E+7 5.79E+7 1-132 5.18E+1 1.36E+2 4.57E+3 2.14E+2 - 5.91E+1 4.87E+1 I-133 1.97E+6 3.34E+6 4.66E+8 5.86E+6 - 2.53E+6 1.02E+6 1-134 9.59E-5 2.54E-4 4.24E-3 4.01E-4 - 3.35E-6 9.13E-5 I-135 3.68E+4 9.48E+4 6.1OE+6 1.50E+5 - 1.05E+5 3.52E+4 Cs-134 7.09E+9 1.67E+10 5.30E+9 2.02E+9 2.08E+8 7.74E+9 Cs-136 4.29E+7 1.69E+8 -9.19E+7 1.45E+7 1.36E+7 1.13E+8 Cs-137 1.01E+10 1.35E+10 4.59E+9 1.78E+9 1.92E+8 4.69E+9 Ba-140 1.38E+8 1.69E+5 5.75E+4 1.14E+5 2.13E+8 8.91E+6 Ce-141 2.82E+5 1.88E+5 8.86E+4 - 5.38E+8 2.16E+4 Ce-144 5.27E+7 2.18E+7 - 1.30E+7 1.33E+10 2.83E+6 Pr-143 7.12E+4 2.84E+4 1.65E+4 _ 2.34E+8 3.55E+3 Nd-147 3.63E+4 3.94E+4 2.32E+4 1.42E+8 2.36E+3 Page 117 of 156

Salem ODCM Rev. 19 Table 2-4(contfd) U Pa,,thway Dose-Factors-. Atm eiceleases R(io), Vegetation Paway Dose Factors - CHILD (mreii/yr~per ft-i/m3) for H-3 and C-14 IU (m2' *' mrenmyr per ,9Ci/sdc) for others WMIMM j--3 - 4.0iE 1.4.O1E 3 4.O1E3 4.O1E+3 ;4.01E+.3 :4.01E+3 r-1

      -14               3.50E+6           O1E+: 7.01E+5: 7.01E*5                                      7.1E+:5            701-E5.       7.O1.B+5I:I*

P-32  : 3.37E+9 1.58E+8 -. - 9.3QE+7 1.30E+8. Cr-51 .' - :61.54E+4; i.79E+4 1.19E+5 6.25E+6 1.1 8E+5;. 5 6.61E+8 6Mn-4 - 185E+8  ; 5.55E+58 1.76E+8k FeS5 8.OE+ 4E+& - -- 240E+8 7861- 13 E+ 4.O1B+~8:

                     -e9               649,E+8              --                                        18E8               67 6E+8         .3+'
"o-57                  __'_____. _   2.99E+7                    _            -      .*'.                               2.45E+8       6.04E+7 :

Co-58 6 6.47A 7 - - __,____ 3.77E+8 1.98+8 Co-60. ,'Ni-63 't'!;: 3.95E+lO 3.78E+8

                                      '2.1 E+9
                                                           !-                  -  -*  4_
                                                                                                    .                   6 2.1OE+9
                                                                                                                    ;1.42E+8 J2E+

1.34E+.'~ U 2Zn-65.4--E 8.12BE+8 2.16E+9 -"-fl 1.36E+9 - 3.80E+8' 1.305E-I'- Rb*-86 Sr-89, i 4.59E+10 4.52E+8

                                                             -                       .                                   2.91E+                                                                                                                            i39E+9;,i 278E+&8 1I03E9,        L
  'Sr-01;~'             L24E+12'           -                                                                                 6E1       23.1E Y-91                  1.87E+7i              .             -                                                            2,49E+9','    5.01E+5I Zr-95,.'             3.90E*6'        8.58E+45            . r         '     1,23E+6                ___          .-      8.95E+88      7.64E+5':

N-5 4.O+ 1.59E+5~` -< 15 52.95E+8:! 1.14E+51

 ~Ru-4103,              1.55,E+7,          -                 -3.89E+7                                      -                .99E+8     5.94E+6,f
 .Ru-106                7.45E8                        ,          '       ,' 1.O1E+9                          '           1.16E+1; 9.3oE+/-7kR A1- Om-7'          3.22E+7         2.17-E+7                 :           4.05E+7'                       -             2.58E+9       I 74E+7:

SbL,124 Sb-125 3.52E+8 44.99E+8

                                      -. 57E+6-35E685E+6 7.78E+5 4.62E+5 I-        __              .'l' i.96E+8 2.78E+8 2.23E+89

i 1.19E+9 1.0E*8 '

L vTe-125in 3.51'E+8 9.50E+7 9.84E+7 ;- 3.38E8 4467E+7 Te-127n' 1.32E+9 3.56E+8 3.16E+8 1.77E+9'- -I iO7E-9 1.57E+8 `

'Te-129mi             8.54E+8        2.39E+8         , 2.75E+8              251E+9                ,                                 "1 33+8 9.04E9 1-131,                1A3E+8 ?       1.44E+8            4.76E+10 26E+8'                                                 1.28E+7       8.18E+74 1-132                9.20E+1        18.69E+2 -          .84E+3           '2.59E+2                                      1.99E+       7.77E+1.       U
  '1-133              3.59E+6          4.44E+6           *8.25E+8 7;.40E+6                                -

1.79E+6 1.68E+6. 2.10E-4e"- 1.46E-4: L 1317()-4 4I-135f-,; 6.,54E+4 Cs5134i 1.60E+'1i-

3.16E-4 1.18E+5' 2.63E+10 7128E-3 1.04E+7 ,

4.84E-4 1.81-E5 8.14E+9-2.-92E;9 8.98E+4 1' 2E+8 5.57E+4-5.54Ei+9 U

 ,Cs-136 '            :'8.06E+7        -2,22E+8 "                            1.18E+8               ,1     .76E+7         7.79E+6.      1.43E+:8 ';
 ':CsL137.: i2:39E+10 J2.'29E+10                                             7.46E+9, r12.68E+9                            .3+           .8+

Ba-140 2.77E+8 2.43E+5 ; 7.90E+4 1.4E+8 1.62E+7

'Ce-141l                6.35E+5        3.26E+5                               1.43E+5                       - .        r       7E+8     4.84E+4
   -Ce-144 ,1.27E+8                    3.98E+7              -                2.21E+7                  .                   1.04E+1 0    6.78E+6 Pr-143              :1.48E+5        4.46E+4                -              2.41E+4                           .          1.60E+8      7.37E+3 Nd-147               7-16E+4         5.80E+4              -               3.18E+4                _______              9.18E+7       4.49E+3, Page 118 of 156                                                                           L

Salem ODCM Rev. 19 Table 2-4 (cont'd) Pathway Dose Factors - Atmospheric Releases R(io), Ground Plane Pathway Dose Factors (m2

• mrem/yr per iiCi/sec)

Nuclide Any Organ H-3 C-14 P-32 Cr-Sl 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-llOm 3.47E+9 Te-125m 1.55E+6 Te-127m 9.17E+4 Te-129m 2.OOE+7 I-131 1.72E+7 1-132 1.24E+6 I-133 2.47E+6 1-134 4.49E+5 I-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 Page 119 of 156

Salem ODCM Rev. 19 EJ #aliza...t';-,j,:ion of Deful Prmters.dl ;;'..' U t '. j .l\ ('i,.'~~~ ~~

                                           -,, , C,, Ajii 4 : ;)i 'CiI                                  ,4w i
            '     q      !i*;s i ,,& ,. 1K j
                                         .J i

t w4 PageN 12 ofI -156,

Salem ODCM Rev. 19 APPENDIX A: Evaluation of Default Parameters for Liquid Effluents A. Effective Maximum Permissible Concentration (MPCe) In accordance with the requirements of ODCM CONTROL 3.3.3.8 the radioactive liquid effluent monitors shall be operable with alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed the MPC value of 10 CFR 20, Appendix B, Table II, Column 2 (Appendix F). The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual radionuclide distribution and corresponding vPC 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: EC gi ga MPG= ' MC (gamma) where: MPCe = an effective MPC value for a mixture of gamma emitting radionuclides (jiCi/ml) Ci = concentration of radionuclide i in the mixture MPCi = the 10 CFR 20, Appendix B, Table II, Column 2 MPC value for radionuclide i (Appendix F) (puCi/ml) The equation for determining the liquid effluent setpoints (Section 1.2.1, equation 1.2) is based on a multiplication of the effective MPC times the monitor sensitivity. Considering the average effective MPC value for the years 1993, 1994, and 1998, it is reasonable to select an MPCe value of 6.0E-06 p.Ci/ml for Unit 1 and 4.8 1E-06 giCi/ml for Unit 2 as typical of liquid radwaste discharges. Page 121 of 156

       '7 - -, ', ' , f ,    ,.                                                                                                             R a f>m on1     )T(VM R PV 1 (0 B. Correction Factor,                      R.                              .

The type of radiation detector used ,to'monitor radioactive releases is noticapable of detecting non-gamma emitting radionuclides such as H-3, Fe-55, and Sr-89, 90, as required by ODCM CONTROL 13.11.4l.'A conservative default, sa4fety factor can-be: determined to account for non-

 'gamma emitting radionuclides. NOn- gamma emitting radionuclides are analyzed;at Salem station L on a mohly basis.-froma compo'siteale of liqud relses.
                          *.                                             ,,.i 3,,, ...........................

t',)t;,-..i-,.i'41

                                                   ,,txl,,

o,,' a*.: Nuclide MPC (ACi/ml) Atvy( fim c0tiit AMPC IU lSr-89 ',31-6, ' 2 '.a 5 L T1Sr855 lTotal

                                         .3E-6                      r              .jrf
                                                                                      ?;ihp............
                                                                                                             .0 fC
                                                                                                                                                                           ;- ... >18 The values in the table above represent the m imum reiactr 'coolant values for non-gamma                                                                                     L emitting nuclides in 1994 for Unit 1 nd Reactor coolant Values were chosen to represent the maximum concentration of non-gamnma emitting n'clides that could be released from Salem Station. The activity values in the table will be diluted by a minimum factor of 800 prior to U

release. The minmum dilution factor is obtaintedby using the minimumcirculatingwaer

   ,flwrte of 100,,000 gprnafn'd t~he                       maimrelease rate of 120+ ,gp.,';.d,,,                                              ,               ,.

L Acoiqnserytiyte non-gam~mafctorf~ojrnov-a~mma, ,emitting ucie a~n be obtained usxntg the N n,io Fact o :~, fraction 1andfthe on- G Activity/MPG 8 .r minimum e0 dilution O.. ..3. i.fctor

                                                                                                                     ~.-. o nas.      po . 5 e f.oy:                    ~

U highest < . U

, Co,,rrjctinon Famctuor,.,,0.7,

'.f

0

                                      ,t e                :>>R0;,i U ,j'                iw             '         '.

asW o'-. dt:: f aal t ) t J U C. Def ault sr et po: n;ldet er- f?;h

                                          ;m 419>i na -t-lo n:                                                                             r  ii .               a Using the information and parameters described above a default setpoint can be calcula Unit 1 and 2 liquid radwaste disposal process radiation monitors (R78).

or U Using these values to calculate the default R8 alarm setpoinaltveprsut in a that: L

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 U compatible with plant operations (refer to Tables 1-1.1 and 1-1.2).

Page 122,of 156

Salem ODCM Rev. 19 Table A-1: Calculation of Effective MPC - Unit 1 Activity Released (Ci) Nuclide MPC* 1993 1994 1998 (iiCi/ml) CURIES CURIES CURIES BE-7 2.OOE-03 8.88E-04 ND ND NA-24 3.OOE-05 6.68E-04 1.62E-04 l.OOE-04 CR-51 2.00E-03 5.38E-03 2.02E-03 ND MN-54 l.OOE-04 3.52E-02 1.37E-02 7.16E-04 MN-56 l.OOE-04 ND ND O.OOE+OO FE-59 5.00E-05 4.76E-04 4.84E-03 ND CO-57 4.OOE-04 1.03E-02 3.1 OE-03 1.78E-05 CO-58 9.OOE-05 1.71E+00 6.47E-01 3.39E-02 CO-60 3.OOE-05 3.04E-O1 1.lOE-Ol 2.42E-02 ZR-95 6.00E-05 3.29E-03 7.13E-04 ND NB-95 l.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 SR-92 6.OOE-05 ND 7.32E-06 ND MO-99 - 4.OOE-05 1.76E-04 1.76E-04 ND AG-l lOm 3.OOE-05 1.19E-02 1.1OE-02 6.58E-05 SN-113 8.00E-05 7.88E-05 4.91E-05 ND SB-122 3.OOE-05 1.21E-03 5.35E-04 1.12E-03 SB-124 2.OOE-05 2.08E-02 1.75E-02 1.73E-02 SB-125 l.OOE-04 9.04E-02 8.23E-02 3.56E-02 SB-126 3.OOE-06 ND 6.18E-05 2.23E-04 I-131 3.OOE-07 1.27E-01 1.82E-02 2.32E-03 I-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 CE-143 4.OOE-05 5.42E-05 ND ND CS-134 9.OOE-06 3.54E-o1 6.46E-o1 2.49E-02 CS-136 6.OOE-05 3.61E-03 l.59E-03 ND CS-137 2.OOE-05 4.53E-01 8.54E-01 7.51E-02 CS-138 3.00E-06 4.15E-06 1.35E-04 ND BA-140 2.OOE-05 ND 8.62E-05 ND LA-140 2.OOE-05 2.12E-04 1.86E-04 ND RU-105 l.OOE-04 2.21E-04 1.35E-04 ND RU-106 1.OOE-05 ND 1.03E-03 ND ZN-65 l.OOE-04 6.72E-04 ND ND Total Ci Gamma 3.14E+00 2.42E+00 2.16E-O1 MPCe (4iCi/ml) 6.05E-06 1.28E-05 1.28E-05 MPC value for unrestricted area from 10 CFR 20, Appendix B, Table II, Column 2.

• • ND - not detected Page 123 of 156

1 Salem ODCM Rev. 19 T Iale; , Calcu.

                                                                ,    la;    .M Effec;ive        -    U it' 2 L

Table A-2: Calculation of Effective MPC - Unit 2 Activity Released (Ci) U Nuclide "' . , MPC* 1993 1994 1998 BE-7 i (RCi/ml) 2.OOE-03 CURIES

                                                        .59E-03 CURIES I-188E-,04 CURIES                       L NA-24                      3.OOE-05                      1.05E-03                 '5;77-05                   1<. l7839E-OS                      , 1 CR-51 i                    2.00E-03                       4.39E-03                                                   1'114E-04 MN-54'          .             .OOE-04               03 .73E-02                 1.37E-02                          7.54E-04                *0-L~

MN-56 l.OOE-04 4ND '466B-05 FE-59 ' 5.OOE-05 -4.83E-04 -;,3.25E-03 P),t;rz'kND CO-57 1-  !,4.00E-04 i'<1.7E-02 CO-58 9.OOE-05 ':'.S1 .Z7SE+OO 4.52E-02 CO-60 ZR-95 3.OOE-05 6.00E-05

                                                       '3.47E-O1
                                                    ;2:.34E-03
                                                                                 ~;1:03B-'01
                                                                                ,(3  .22-04,
                                                                                                                . 2.1'2E-02 ND U

NB-95 , YI:l.OOE-04 >1' ,3+9.7E-03 S NB-97 9.O0E-04 1.46E-03 r..,,4,2,2E-05 TC-99M ' ': ' '. '>3.OOE-03 i'3.77E-04 nsi rlri'.35E-06 b SR-89 TND 'ifs\ 2.d?>i71E-04 3.00E-06

                                                           <ND I,

SR-92 MO-99 "(f' -+' .'44.00E-05 AG-llOmrn 6.00E-05 3.OOE-05

                                                   ':A)3:'ND'
                                             ~'- 'i.3E-a2 1'f ND
                                                                                  `134E-02 O"
                                                                                                                  'ND

1ND 1/4 A LI SN-1 13 SB-122 SB-124 ",,,

                     '8.OOE-05
                   ;yw,,
                         '3.OOE-05 2'; 2.00E-05 7.45E-05
                                                       ~120E-03 KND 9o82E-03                          1
                                                                                                                 .44E
                                                                                                                      + 6,;-04
                                                                                                                          -02          -'.55 L

SB-125 SB-126 f<-f8'3.00E-06 I-13'1 -' >t 1.OOE-04

                      .'3.OOE-07 1.'2E-01 tv 3.517E-04 J.i$iiSIlE-4 1`rsT-i87E4;1 6.03E-02~

rrND

                                                                                                               ,    L 88E-02
                                                                                                         ',,1.'gS97E-04
                                                                                                                      !>3.14E-03 r>    4',-'
                                                                                                                                             -.1  L I-132 I-134 CE-141       t ux 8.OOE-06 l< 2.00E-05 9.0oE-05 i

qx ND 8 38.72E-05

'2.39E-04 V.85E-04 2:87E-05 1/41.68E-04 flW.

                                                                                                              , ND
                                                                                                            ' ; >%ND 1)
                                                                                                                                             -i L

CE-143 i,. :4.OOE-05 .-1.,- ND CS-134 9.OOE-06 4.57E-O1 l~,,'t2.64E-02 CS-136' i '1/46.OOE-05 fr-? 4.82E-03 1151E-03 N, D CS-137 2.OOE-05 5.706-O1 ,i27 97E-02 CS-138 3.OOE-06 'i -'LtND ~ND i4.'90E-05 BA-140 m 2.OOE-05 f  ;'fND 5 ND LA-140 1 2.OOE-05  !,2M03E-03 14 RU-105 RU-106 '

                  -        l.OOE-04 l.OOE-05

4.M7E-05

                                                ':V- ND
                                                                                '4.1 8E-04 iND I1,f;IND ND
                                                                                                                                 -'V k

L ZN-65 l.OOE-04 1.59E-04 ND W-187 rii ;6.OOE-05 ,1,, 4r ND: ,~!177.98E05 L Total Ci ' ts2?; Gamma -tlt 57E+00 A-2.38E+00 Iiii2.31E-01 fl MPCe - r f-i -'CH)I f ;; ;4.81E0 1' l.55ME-05-o 4, i, jf 'r tII E-05

• MPC value for unrestricted area from 10 CFR 20, Appendix B, Table II, Column 2.

I -1

• • ND = not detected Page L240of 156 U

Salem ODCM Rev. 19 APPENDIX B Technical Basis for Simplified Dose Calculations Liquid Radioactive Effluent Page 125 of 156

Salem ODCM Rev. 19 D 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 on ofthee-55;Co-58; Co-60, Fe-59 and Ag-i nOm releases. The radionuclides, Cs-134 and Cs-1377 contribute the large majority of the calculated total body dose. The results!ofth uationfi4 p93, 1994, and 1998 are presented in Li 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 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. L For the evaluation of the maximum organ dose, it is conservative to use the Nb-95 dose conversion factor (1.51 E+06 mrem/hr per jiCi/ml, GI-LLI). By this approach, the maximum organ dose will be overestimated since this nuclide has the highest organ dose factor of all the radionuclides evaluated. For the total body calculation, the Fe-59 dose factor (2.32 E+05 mrem/hr per gCi/ml, total body) is the l highest among the identified dominant nuclides. For evaluating compliance:with the dose limits of i ODCM CONTROL 3.11.1.2, the following simplified equations may be used: Total Body 1.6 7 E-0 2 *VOLi Dib = W*Ape - s9,TB

• EC, -1 Where: 1 Dhb = 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 juCi/ml) VOL C;

               = volume of liquid effluent released (gal)
               = total concentration of all radionuclides (PtCi/ml)

U CW = average circulating water discharge rate during release period(gallmin) 1.67E-02 = conversion factor hr/min) L U Page 126 of 156. L

Salem ODCM Rev. 19 Substituting the value for the Fe-59 total body dose conversion factor, the equation simplifies to: 1.21E+03*VOL Dtb=Zw *XA (B.2) Maximum Organ 1.67E-02* VOL Dmax = *ANb-95,GI.-LLIj*zCi (B.3) CW i Where: Dmax = maximum organ dose (mrem) ANb-95,GI.LLI = 1.5 1E+06, Gi-LLI ingestion dose conversion factor for Nb-95 (mrem/hr per 4iCi/ml) Substituting the value for ANb.95,GI-LLI the equation simplifies to: 2.52E+04*VOL Dmax= *Eoci CBA4) Tritium is not included in the limited analysis dose assessment for liquid releases, because the potential dose resulting from normal reactor releases is relatively negligible. The average annual tritium release from each Salem Unit is approximately 350 curies. The calculated total body dose from such a release is 2.4E-03 mrem/yr via the fish and invertebrate ingestion pathways. This amounts to 0.08% of the design limit dose of 3 mrem/yr. Furthermore, the release of tritium is a function of operating time and power level and is essentially unrelated to radwaste system operation. Page 127 of 156

Salem ODCM Rev. 19 Table B-1: Adult Dose Coi tbto Fish and Invertebrate Pathways - Unit 1 Nucide Release (Ci) T.Body Dose Fraionii- GI-LLI Dose Fraction Liver Dose Fraction 1994 1993 1998 1994 91993 1998 1994 1993 + 1998 1994 1993 1998 Mn-54 132E-2 3.51E-2 7.16E-4 * *

• 0.03 0.02 *
• 0.02
• Fe-55 1.49E-1 6AOE-2 8.39E-2 0.07 0.0 03'7 0.12 0.03 7 .: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 -.

7 -=0.1840.02 0.31 0.51 ,,0.13 0.01 0.07

• Co-60 1.1OE-I 3.04E-1 2.42E-2 0.02 = 0.0 >  :- 0.14 0.24 -0.24
• 0.03 0.01 Zn-65 NID 6.72E4 N/D *
• 50.01 .0.01 *
• 0.02
• Nb-95 1.28E-3 5.78E-3 N/D *
• 20.01 -i* ,* *
• Ag-llm l.lOE-2 1.19E-2 6.58E-5 * *
• 0-26 0.17 0O1 * *
• Sb-124 1.75E-2 2.58E-2 1.73E-2 * - *
• C4X4 * *
• Sb-125 8.23E-2 9.04E-2 3.56E-2
• 2 * <; 0.02 * -*
• Cs-134 646E-1 3.54E-1 2.49E-2 0.47 0,387 0.18 * ' 0.38 - 37 0.09 Cs-137 8.54E-1 4.53E-1 7.51E-2 0.37 0.28j 0.3 * - *
• 0.37 035 0.20 Total 2.53E+0 3.21E+0 3.31E-1 z,
• Less than 0.01 N/D = not detected I 11 Page 128 of 156 V-7 U--, r-77' r_-n rnl r= r-1 C7 riTriz~ rii:

r r7 r~r~ r- r17- - C-c- nc -ci-cr-,

Salem ODCM Rev. 19 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 1.1IE-3 3.97E-3 N/D * *
• 0.06 0.01 * * *
• Ag- lOrn 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 129 of 156

Salem ODCM Rev. 19 4 1 1 I I I i

                                          ;         i
                         ;-"I     ;   --1    i      i I

K. h APPENDIX C.; T ;4  : if,'So l ff r TechnGil Bseo e Pos Fac tors> Gdseous Radibactie Efluent I.

                                                                              ..                           .1 CJ-11;
                                                                               ,, I1. i I,

:,,  ; 111

                                                                                    ,       1. ,           1, I tA I   i 1,
                                                                             ;i""   f -,

i: I 1 1. ,

                                                                                   "I-   I,
                                                                                       ;!:i i

II I T It- t.

                                                                                          -]                     :    i V

1 i I I i i;: P 1 4; '

                                                                                                            , f 11
         ..... ....I-',I    .11-111-1     .

I I'll, I I:,-- f i 1. i, Ai'

                    ,I It t    :-

, I!, , 1.  ! , iI i ",; I Page 130 of 156

Salem ODCM Rev. 19 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 =X(Ki* fi) (C.1) i Where: Keff = the effective total body dose factor due to gamma emissions from all noble gases released Ki = the total body dose factor due to gamma emissions from each noble gas radionuclide i released fit = the fractional abundance of noble gas radionuclide i relative to the total noble gas activity (L+1 lM*f](C.2) lA eS=[(L+ Where: (L + 1.1 M)eff = the effective skin dose factor due to beta and gamma emissions from all noble gases released (Li t 1.1 Mi) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released Page 131 of 156

Salem ODCM Rev. 19 M~fi= (M~f)(C.3) M4= hefftif-#eir'asfact1or'a u'ega~~X ;ma'e"misons' e ft~a'rri a}il tobegdes.rla'ed&i ,!. Where: ,

.,;rL oriire 1 ti 2-- -; gas radionuclidei released-MNff = the effective air dose factor due to gamma emissions from all noble gases released M; = the air dose factor due to gabema emissions fom each noble gas radionuclide i released

 ;ormally,:itl wold be -exvct3fi&'11'Fl    -Pas tti
                                             .. !w  !i   ,.r! d~i  .id;,           idt,*            &      '          ;tOirr'            m4  i L';t Neff    = theffffective air dose factor due to beta emissions from: aiii noble gases rneleased                                          to Noraly ithwoul boeexpcterduetha                betradesio             nsieefl~i ddrteawoldtb usedfrtedeteriiaio                                     L of the effective dose factors. However, th'e 'noble gas releases from Salem have been maintained to such negligible quantities that thie inherent variability in the data malces any meaningfiul evaluations difficulit. ;E?' E'      d%t5 r 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. 1,' "Source Term L

Specifications," has bbeen used as represenpting a typicaldistributioni. The effective dose factors as derved arep'r~ekhe'nte in ablet' f;i ' T!'i To provide an additional d ogree 6 onserv a c trd 5Oi !Siitlieddoseo, in calculational process when the effective dose transfer factor is used. This conservatis m'provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment. U For evaluaating compliance with the dose limits of ODCM CONTROL 3.11.2.2, the following L simplified equations may be used:

                        '3.17E Me,'1 0.50~QfIX~                    .'
                                                                              '."'i 1!:.i ii u

U and ',ili z-,~l i Dp 3.17E&08*X oP50 / EQ (C.6) E 0.50 QNf*~ Where: Page 132 of 156 U

Salem ODCM Rev. 19 Dy = air dose due to gamma emissions for the cumulative release of all noble gases (mrad) Dp air dose due to beta emissions for the cumulative release of all noble gases (mrad) X/Q atmospheric dispersion to the controlling site boundary (sec/m3) Meff 5.3E+02, effective gamma-air dose factor (mrad/yr per ,uCi/m3) Neff 1.IE+03, effective beta-air dose factor (mrad/yr per p.Ci/m3) Qi cumulative release for all noble gas radionuclides (pCi) 3.17E-08 conversion factor (yr/sec) 0.50 conservatism factor to account for the variability in the effluent data Combining the constants, the dose calculational equations simplify to: Dr=3.5E-O5*%Q*Y (C.7) and Df6=7.OE-O5*% Q*ZQi (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. Page 133 of 156

Salem ODCM Rev. 19 Table C-1: Effective Dose Factors

                .- I 10I Noble Gases-. Total Body and $kin:                                                          U TotalBody Effectivee.                      Skin Effective

.J) 16.1i

                                           ;;:t'
                                                 . Dose Factor.

i '1 1:-. 77 F ,!:{

                                                            ~Keff(L1.Mef 5.

Dose Factor

                                                                                         ;;f w

L Radionuclid e fi* (mreyr per pCi/M (mrem/pepi/m3 )

           '---          :':f Kr-8 5                         0.0i                                 --                        1.4E+01 Kr-88                          0.01                          1.5E+02,       1!9Ei,02                        ;. tf , .i f f )ii' U

Xe-133m 0.01 2.5E+00 1.4E+01 Xe-133 0.95 2.8E+02 6.6E+02 Xe-135 0.02 3.6E+01 7.9E+ I Total 4.7E+02 9.6E+02 L NobleGases-Airi;'11..],,. L Gamma Ait.Effortive Beta Air Effective L Radionuclide f * (mrad/yr per iCi/m) (miSara/y per~4Ci/Iri3Y * ¢;t, Kr-85 Kr-88 Xe-133m 0.01 0.01 0.01 1.5E+02 3.3E+00 2.OE+01 2.9E+01 1.5E+01 U Xe-133 0.95 3.4E+02 1.OE+03 Xe-135 0.02 3.8E+01 4.9E+01 L Total 5.3E+02 1l lE+03 L

• Based on Noble gas distribution from ANSI N237-1976/ANSI-18.1, "Source Term Specifications."

L U

                                                                                                                                -1 Page 134-of 156-                                                           U

Salem ODCM Rev. 19 APPENDIX D Technical Basis for Simplified Dose Calculation Gaseous Radioactive Effluent Page 135 of 156

Salem ODCM Rev. 19 APPENDIX D: Technical Basis for Simplified Dose Calculation - Gaseous Effluents L 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 L 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 U receives a greater radiation dose from the g/c/m pathway than any other pathway. Of this g/c/m f-I pathway, the maximum exposed organ including the total body, is the thyroid, and the highest dose 'Si contributor is radionuclide I-131. The results for this evaluation are presented in Table D-1. U 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 bemig conserative. -: X, For the evaluation of the dose cmmitmient 'viaac6htoling pathway and ggroup, it is conservative to use the infant, g/inm, thyroid, 1-13:1 pathway dose factor (l.05E12 m2 mrem/yr per p.Ci/sec). By this approach, the maximum dose commitment willbe'ovejrestimatedsihce I-131 has the highest pathway dose factor of all radionuclides evaluated. L For evaluating compliance with the dose limits of ODCM CONTROL 3.11.2.3, the following simplified equation may be used: U Dmax=3.17E.08*W*RI-131* Qi L Where: Dmx W

                = maximum organ dose (mrem)
                = atmospheric dispersion parameters to the controlling location(s) as identified in L

Table 3.2-4. X/Q = atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (sec/n 3) U D/Q = atmospheric deposition for vegetation, milk and ground plane exposure pathways (mn2) Qi = cumulative release over the period of interest for radioiodines and particulates 3.17E-8 = conversion factor (yr/sec) U

                = I-131 dose parameter for the thyroid for the identified controlling pathway R 1,l 3 1
                = 1.05E+12 (m2 mrem/yr per p.Ci/sec), infant thyroid dose parameter with the grass-cow-milk pathway controlling U

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 L thyroid dose. U It is recognized that for some particulate radionuclides (e.g., Co-60 and Cs-137), the ground exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway. LI I-I Page 136 of 156 L

Salem ODCM Rev. 19 However, use of the I-13 1 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 137 of 156

Salem ODCM Rev. 19 u Table D,-1:InfantuDose Contitions Fraction of Total Organ and Body Dose PATHWAYS Target Organs Grass-Cow-Milk Ground Plane Total Body 0.02 0.15 Liver 0.23 0.14 Thyroid 0.59 0.15 Kidney 0.02 0.15 Lung 0.01 0.02 GI-LLI 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.138 of 156

Salem ODCM Rev. 19 APPENDIX E Radiological Environmental Monitoring Program Sample Type, Location and Analysis Page 139 of 156

Salem ODCM Rev. 19 APPENDIX E: Radiological Environmental Monitoring Program SAMPLE DESIGNATION L Samples are identified by a three part code. The first two letters are the power station identification i code, in this case "SA". The next three letters are for the media sampled. i AIO = Air Iodine IDM = Immersion Dose (DLR) Wl APT = Air Particulates MLK= Milk,,, ECH = Hard Shell Blue Crab ESF =Edible Fish Urfa [* PWR = Potable Water (Raw) 92PWT

                                               >;<,       PotaleWater(retd)        v$

U ESS = SedimentSWA Surfae Water WWA= Well Water The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors ,of22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; L i.e., 2=NNE, 3=NE, 4=ENG, etc. The next digit is a letter which represents the radial distance from the plant: L S = On-site location A = 0-1 miles off-site B '1-2 miles off-site E = 4-5 miles off-site F = 5-10 miles off-site G = 10-20 miles off-site U C = 2-3 miles off-site D = 3-4 miles off-site H = > 20 miles off-site L 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. LI SAMPLING LOCATIONS L All sampling locations and specific information about the individual locations are given in Table E- 1. Maps E-1 and E-2 show the locations of sampling stations with respect to the site. L L U Page 140 of 156;

Salem ODCM Rev. 19 TABLE E-1: REMP Sample Locations A. Direct Radiation Monitoring Locations (IDM) STATION CODE STATION LOCATION 151 0.55 mi. N of vent 2S2 0.4 mi. NNE of vent 2S4 0.59 mi. NNE of vent 3S1 0.58 mi. NE of vent 4S1 0.60 mi ENE of vent 5S1 1.0 mi. E of vent; site access road 6S2 0.21 mi. ESE of vent; observation building 7S1 0.12 mi. SE of vent; station personnel gate lOSi 0.14 mi. SSW of vent; circ water bldg. 11S1 0.09 mi. SW of vent; service water bldg. i5Si 0.57 mi. NW of vent 16S1 0.54 mi. NNW of vent 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road SD1 3.5 mi. E of vent; local farm 10D1 3.9 mi. SSW of vent; Taylor's Bridge Spur 14D1 3.4 mi. WNW of vent; Bay View, DE 15D1 3.8 mi. NW of vent; Rt 9, Augustine Beach, DE 2E1 4.4 mi. NNE of vent; local farm 3E1 4.1 mi. NE of vent; local farm llE2 5.0 mi. SW of vent 12E1 4.4 mi. WSW of vent; Thomas Landing 13E1 4.2 mi. W of vent; Diehl House Lab 16E1 4.1 mi. NNW of vent; Port Penn lF1 5.8 mi. N of vent; Fort Elfsborg 2F2 8.7 mi. NNE of vent; Salem Substation 2F5 7.4 mi. NNE of vent; Salem High School 2F6 7.3 mi. NNE of vent; PSE&G Training Center Salem NJ 3F2 5.1 mi. NE of vent; Hancocks Bridge, NJ Munc Bldg 3F3 8.6 mi. NE of vent; Quinton Township Elem. School NJ 4F2 6.0 mi. ENE of vent; Mays Lane, Harmersville, NJ SF1 6.5 mi. E of vent; Canton, NJ Page 141 of 156

TABLEiE-1 (Cont'd) Salem ODCM Rev. 19 L A. Direct Radiation Monitoring Locations (IDM) (Cont'd) , '; (r STATION CODE STATION LOCATION 6F1: 6.4 mi. ESE of vent; Stow Neck Road 7F2 9.1 mit.SE of vent; Bayside, NJ 0i' 9F1  : 5.3 ml. S of vent off Route #9, DE 1OF2  ;'.*:E: "i, 5.8 mi.': SSWof vent; Rt. 9 lFi ryK. .i7: .:' r 6. m. S fvent; Taylors Bridge, DE 12Fl r.W9i.WSW --- ,49 J of vent; Townsend Elementary School, DE 13F2 13F3 1

                                                              .W-of'vent; 6.50niWofyent;Odessa, DE 93--    mi                          Redding Middle School P      U 13F4                                                             r<:49.8,l 6                         . Wd             hvent; Middletown, DE                              ;':?:

14F2 ,60-6 nii N of vent; Boyds Corner 15F3 5.4 mi. NW of vent l16F2 162'-

                                                                                       ~i NW
                                                                                     ,.nf               sit 6f  f vet ven     eaware
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                                                                                                                       ,1qtj@:, l '!'8 City Public School 1G3            'in i," 4M    m;            . it     V                    lfm                 ofvent; N. Church St. Wilmington, DE 3G1I                                                               j'i 17 mi. NE ofQvent; local farm 10G1    ff8 '.l~l;d~       ili$l2.i;i';;il                          ~fm                     ;SSW-bfsvent. Smyrna, DE lti;12'1                                                        id'l'      'L 14G1                                                                         11.8 'mi. WNW of Vent; Rte 286, Bethel Church Rd., DE 16G1                                                     ,          .       (15 mi NNW of vent; Wilmington Airport                                           ; -

3H1 32, WmNE ofvent; National Park, NJ 'j1' l B. Air Sampling Locations (AIOAPT) L STATION CODE i ' ;4 t STAIONLOCATION

                                              ,4j, 't,7r'&.iOtmit,                            EE;vent; site access road                                           i 51D1                                                         d     .h 3                    ,^E4
                                                                                                 ,5d..i, mi,;;.yent; n local farm 1 6E1      '   ';   4 A K,       i? d,                                       4 4.1                        -,of  vent; Port Penn            .        ?             K    L 1F1 44'    MI :'.                                                     i    ;58'mi            Nofent;FortElfsborg 2F6                                                 Ai     4           ..-   7.3. ml,                E Qof vent; PSE&G Training Center Salem,rNJ L

4 14G1 11.8 mi. WNW of Vent; Rte 286, Bethel Church Rd., DE Page 142 of 156i L

Salem ODCM Rev. 19 Table E-1 (Cont'd) C. Surface Water Locations (SWA) - Delaware River STATION CODE STATION LOCATION I Al- 0.2 mi. SW of vent; Salem Outfall Area 12C1 2.5 mi. WSW of vent; West bank of Delaware River 7E1 4.5 mi. SE of vent; Delaware River 1.0 mi. W of Mad Horse Creek 16F1 6.9 mi. NNW of vent; C&D Canal D. Ground Water Locations (WWA) STATION CODE STATION LOCATION 3E1 4.1 mi NE of vent, local farm No groundwater samples are required as liquid effluents discharged from Hope Creek and Salem Generating Stations do not directly affect this pathway. However, this location (3E1) is being monitored as a management audit sample E. Drinking Water Locations (PWR, PWT) STATION CODE STATION LOCATION 2F3 8.0 mi NNE of vent, Salem Water Works No public drinking water samples or irrigation water samples are required as these pathways are not directly affected by liquid effluents discharged from Hope Creek and Salem Generating Stations. However, this location (2F3) is being monitored as a management audit sample F. Water Sediment Locations (ESS) STATION CODE STATION LOCATION 1lAl 0.2 mi. SW of vent; Salem outfall area 1SAl 0.3 mi. NW of vent; Hope Creek outfall area 16AI 0.7 mi. NNW of vent; South Storm Drain outfall 12C1 2.5 mi. WSW of vent; West bank of Delaware River 7E1 4.5 mi. SE of vent; 1 mni West of Mad Horse Creek 16F1 6.9 mi. NNW of vent; C&D Canal 6S2 0.2 mi. ESE of vent; observation building G. Milk Sampling Locations (MLK) STATION CODE STATION LOCATION 2G3 12.0 mi. NNE of vent, local farm 13E3 4.9 mi W of vent, local farm 14F4 7.6 mi. WNW of vent; local farm 3G1 17 mi. NE of vent; local farm Page 143 of 156

                     '   iSalem                                                                                                      ODCM Rev. 19 Table E- (Cont'd)                                                                                                       L H. Fish and Invertebrate Locations (ESF, ECH)                                                                                           ,

STATION CODE STATION LOCATION 1lAl -0.2mi. SW of vent; Salem outfall area J 12C1fJ if .25 mi WSW'0f vent; West bank ofDelaware River 7E1 45 mi SEof -vent; 1 mi West of Mad Horse Creek I I. Food Product Locationsf F ,i  ; P77J F ,t'j STATION CODE STATION LOCATION r /k A' s U The Delaware River at the locatiof Saliti and pe Ceek Nuclear Power Plants ija IdarcEishA water source. No irrigation of foo products is performed using water in the vicinity from which liquid plant wastes have been discharged. However, 12 management audit food samples are coliected ro vas loctions Contact CM c di fos iig loations. UAU

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Salem ODCM Rev. 19 SAMPLES COLLECTION AND ANALYSIS Sample Collection Method Analysis Air Particulate Continuous low volume Gross Beta analysis air sampler. Sample on each weekly collected every week sample. Gamma along with the filter spectrometry shall change. 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. Air Iodine A TEDA impregnated Iodine 131 analysis charcoal cartridge is are performed on connected to air each weekly sample. particulate air sampler and is collected weekly at filter change. Crab and Fish Two batch samples are Gamma isotopic sealed in a plastic analysis of edible bag or jar and frozen portion on collection. semi-annually or when in season. Sediment A sediment sample is Gamma isotopic taken semi-annually. analysis semi-annually. Direct 2 DLR's will be Gamma dose quarterly. collected from each location quarterly. Page 145 of 156

Salem ODCM Rev. 19 SAMPL;E 'COLLECTION AND ANALYSIS (Cont'd) Sample Collection Method. Analysis L Milk Sample ioffresh milk is collect.dfior eachkv,; Gamma isotopic an~alysis.,and(1-31' i L farm semi-monthly when analsis o~n eachv~ .r,;. cowo are inpasre, sarnple o~n ~llnectionl:, monthly. at otherimes. U-Water Sample .to ibeollected Gamma isotopic (Potable, m yproviding. winter monthly H-3 on Surface) i=ing cohditions :allow. quarterly surface sample, monthly on IU JkYU ? '.' , , ground water sample. L

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Salem ODCM Rev. 19 E-1: ONSITE SAMPLING LOCATIONS MAP B-1 ON-SITE SAMPLING LOCATIONS I 13 5 9 0108ftA IMAM4 AM FO.- Page 147 of 156

Salem ODCM Rev. 19 FIGUREE-2:- OFFSITE SAMPLING ILOCATIONSiS

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                         ,i ' ,. A Page 148 of 156

Salem ODCM Rev. 19 L L Li L APPENDIX F MAXIMUM PERMISSIBLE CONCENTRATIONS L LIQUID EFFLUENTS L L Page 149 of 156

Salem ODCM Rev. 19 APPENDIX F: Maximum Permissible Concentration (MPC) Values - Liquid Effluents L The following radionuclide concentrations were obtained from 10 CFR 20 Appendix B, Table II, Column 2 as revised January 1, 1991. Table F-1: Maximum Permissible Concentrations L Element Isotope Soluble Conc Insoluble Conc. (,uCi/ml) ([Ci/ml) Actinium (89) Ac-227 Ac-228 2E-6 9E-5 4E-6 3E-4 9E-5 3E-5 L Americium (95) Am-241 Am-242m 4E-6 9E-5 Am-242 E,. 1E-4 _ Am-243 4E-6  : 3E-5 Antimony (51) Sb-122

                                ,244..
                                       ,3E5 5E                    E 3E-.5 Y;

L Sb- 24 .'E-5i 2E-5 Sb-125 Sb-126 1E-4 3E-6. 1E-4 3E-6 L Arsenic (33) As-73 As-74 5E-4 5E-5 5E-4 5E-5 L As-76 2E-5 2E-'5 Astatine (8,5) As-77 At-21 1 8E-5 2E-6 8E-5 7E-5 U 'Barium (56) Ba-131 2E-4 2E-4 Berkelium (97) Ba-140 Bk-249 3E-5

                                                '6E-4 2E-5 6E-4 L
                      'Bk-250                   2E-4                2E-4 Beryllium (4)

Bismuth (83) Be-7 Bi-206 2E-3 4E-5 2E-3 4E-5 L Bi-207 Bi-210 6E-5 4E-5 6E-5 4E-5 L Bi-212 4E-4 4E-4 Bromine (35) Br-82 Br-83 3E-4 3E-6 4E-5 3E-6 D Cadmium (48) Cd-109 2E-4 2E-4 Cd-115m Cd-115 3E-5 3E-5 3E-5 4E-5 D Calcium (20) Ca-45 9E-6 2E-4 Ca-47 5E-5 3E-5 2E-5 U Californium (98) Cf-249 4E-6 Cf-250 1E-5 3E-5 Cf-251 4E-6 3E-5 U Cf-252 7E-6 7E-6 Cf-253 Cf-254 1E-4 1E-7 1E-4 1E-7 L Page 150 of 15.6

Salem ODCM Rev. 19 Table F-1 (Continued) Element Isotope Soluble Conc. Insoluble Conc. (,uCi/ml) (,uCi/ml) Carbon (6) C-14 8E-4 Cerium (58) Ce-141 9E-5 9E-5 Ce-143 4E-5 4E-5 Ce-144 1E-5 1E-5 Cesium (55) Cs-131 2E-3 9E-4 Cs-134m 6E-3 1E-3 Cs-134 9E-6 4E-5 Cs-135 1E-4 2E-4 Cs-136 9E-5 6E-5 Cs-137 2E-5 4E-5 Chlorine (17) Cl-36 8E-5 6E-5 Cl-38 4E-4 4E-4 Chromium (24) Cr-51 2E-3 2E-3 Cobalt (27) Co-57 5E-4 4E-4 Co-58m 3E-3 2E-3 Co-58 1E-4 9E-5 Co-60 5E-5 3E-5 Copper (29) Cu-64 3E-4 2E-4 Curium (96) Cm-242 2E-5 2E-5 Cm-243 5E-6 2E-5 Cm-244 7E-6 3E-5 Cm-245 4E-6 3E-5 Cm-246 4E-6 3E-5 Cm-247 4E-6 2E-5 Cm-248 4E-7 1E-6 Cm-249 2E-3 2E-3 Dysprosium (66) Dy-165 4E-4 4E-4 Dy-166 4E-5 4E-5 Einsteinium (99) Es-253 2E-5 2E-5 Es-254m 2E-5 2E-5 Es-254 lE-5 1E-5 Es-255 3E-5 3E-5 Erbium (68) Er-169 9E-5 9E-5 Er-171 1E-4 1E-4 Europium (63) Eu-152 (9.2 hrs) 6E-5 6E-5 Eu-152 (13 yrs) 8E-5 8E-5 Eu-154 2E-5 2E-5 Eu-155 2E-4 2E-4 Fermium (100) Fm-254 1E-4 IE-4 Fm-255 3E-5 3E-5 Fm-256 9E-7 9E-7 Page 151 of 156

i Salem ODCM Rev. 19 Table ,F-I (Continued); L Element 4sotoeSoulCnc Insoluble Conc. I Fluorine (9) F- 18 __ __ __ _ _ _ { i I/ml 8E-4 (gci/m i) : 5E-4: 2 L

                                                                                                                                                  ;-i   1  )

Gadolminiumrn (64) Gd-1I553 2-.2E-4 Gd-I 59 8E-5 8- i L Gallium (31) Germanium-f (32) a-24E54E5 Ge7~2E-3 Au-196 2E-4 2E-3; '-- P , " r,,,4 I ;j

                                                                                                                                   . r r1 11' Y-II Ij.

U Gold (79) Au-I7`5E5 E-Au ~2E-4 2E-4, Hafhuium i72). Hf-1-81 7E-5 7E-5 S ,Holmium~(67) H&663E5 E5 Hydrogent (3) H-41:, :3E-& E IU4. , Indium':(4)In1mlE3< lE.3 __ _ __ __ _ n U m2E4 In-115m 9E-4

                                                                                         ,-5       2 E5, E5 L

Iodine (5)I-125~ 2E-7 2E-4 1-2'E-8" 2E-4~ L 1-131-0-`7K 6E~ U 1~-133% U IU JE-~6,-_ _ __ _ _ _ _ _ _ _ _ _ _ 13-14 , P__ E-5 6E -4

                                                      -1 54E                           6-6~          7E 1,,U~

Iridium (77) ~ jr-1 90 " 2E-4 '2E-4 _ _ _ _ _ _ _ Ir 924E _ -5 4E -5 Iron (26)_, __ _ ___ _ _ _ _ r -r194 ,' e55" 3E 53 E42-E

• i i

                                                                                                                                              ,,,"~7
                                                    ~Fe-59`                       6E55E-                5       ~

Lanthanum (57) La102E-5 ~~ 2E5 Lead (82). Pb~-203` 4E44E-4~ Pb -21 IE-7~ E4 U Pb-'2l2z 2E-5 ;2E-5 Lutetium (71') LuI-I777, E4IE-4 Manganese (25) M523 E-5 13E-5 _ _ __ _ _ _ Mn-54' Mn;56,1" 1E-4' 1 E-4, E-4 U U Mercury. (80) Hg4'197in, 2E-4, 2E-4~ ___ _ __ _ _ _ _ Hg4197 3E4 , E _ _ _ _ _ _ _ _ Hg,203~ 2E-5 l - Molybdenum (42) Mo-99 2E-4 4-i i1 Paege;152.of 156. I'll

Salem ODCM Rev. 19 Table F-i (Continued) Element Isotope Soluble Conc. Insoluble Conc. A(CiO/ml) (0Ci/ml) Neodymium (60) Nd-144 7E-5 8E-5 Nd-147 6E-5 6E-5 Nd-149 3E-4 3E-4 Neptunium (93) Np-237 3E-63E-5 Np-239 1E-4 1E-4 Nickel (28) Ni-59 22E-4 E-3 Ni-63 3-E-S_ 7E-4 Ni-65 lE-4 lE-4 Niobium (41) Nb-93m 4E-4 4E-4 Nb-95 1E-4 1E-4 Nb-97 9E-4 9E-4 Osmium (76) Os-185 7E-5 7E-5 Os-191m 3E-3 2E-3 Os-191 2E-4 2E-4 Os-193 6E-5 5E-5 Palladium (46) Pd-103 3E-4 3E-4 Pd-109 9E-5 7E-5 Phosphorus (15) P-32 2E-5 2E-5 Platinum (78) Pt-191 1E-4 lE-4 Pt-193m IE-3 lE-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 1E-3 Pu-242 5E-6 3E-5 Pu-243 3E-4 3E-4 Polonium (84) Po-210 7E-7 3E-5 Potassium (19) K-42 3E4 2E-5 Praseodymium(59) Pr-142 3E-5 3E-5 Pr- 143 5E-5 SE-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                            Page 153 of 156

I ,f" W Salem ODCM Rev. 19 TableTF- (Continued) L Element Iotop -Solbeloc nsoluble Conc. riIi __________i.ci/ml) (gci/mI) Radium (88) Ra-223 7E74E-6, _________ ________ Ra-224 ; E-65 E- ___ _ _ _ _ _ _ _ Ra-226,. 3 E-8 3E-5, - _ _ __ _ _ _ _ _ Ra-228" 3E 8 3E-5' Rhenium ,(75):, Re- 1836E- 3-4. _ _ __ __ _ _ _ _ Re-186 .4 9E-5 ISE-S,5 ___ _ _ _ _ _ _ _ Re- 187,, 3E-3 2E-~Ij h _ _ _ ___ _ _ _ _ _ _ _ _ Re- l8~6 - E5 LI. Rhodium;(45); Rh-i103m~ 1E-2-'II-Z ~ < t: Rubidium (37) Rb-8 7E52E5 _ _ __ __ _ _ _ _ Rb-847 r 1EE4-1: 2E A Ruthe:ni'um '(44) Ru-97 4E4 3E-4

                                         'Ru-m10               8E5              E-Ru-103M-             -3E-6          3E- 6..                                             .I Ru-105 Ru-106' 141E4 JE5            AE-5                                                L Samarum (62)~,                           SM-147-              6E5fE5                                   4k,P, L
                                                                                                        -   i. 1; - I 11I ,

Sm-151, 4E-4 4E-4 1: i;:-, 10", s M-15 8E-5 E5 Scandiumi (21 S46- 4E-5 4-Sc-47 Sc4-48 9E5 3E-5S, 9E-3E515~ L Seeniumf(34 Silicon (14):S-Se-7,5 3E 9E4 3E-4j~ 2EP-4 gi "; lit 1"", II Li Silver (47). Agi0 E-4, IE-4~p Ag-4.lOm Agl

                                                  '4E-5 3E-5           3-4E5 ~                                               u Sodium (1:)                                Na-22,               4E5 S            E Strontium, (38)

Na-4 Sr-85mI 2E-41~ 7E-31 3E-5 7E3 u~

                                                                                                             ,I         i,

L Sr-!85 l:',,

E-4 2E-4 .I , Sr-89L Sr-90 3E 3E-7l~ 3E-5: 4E-5 r L Sr-9 1, 7E- 5E-5 U'1 _ _ _ _ _ _ _ _ _ Sr-92 7E-5 6E-Sulfur (1:6) S-35-' 6E Tantalum (7) Ta- 182 4E 4E5 I I fI Page 154 of 156' L

Salem ODCM Rev. 19 Table F-i (Continued) Element Isotope Soluble Conc. Insoluble Conc. _ (,uCi/ml) (jiCi/ml) Technetium (43) Tc-96m 1E-2 1E-2 Tc-96 l1E-4 5E-5 Tc-97m 4E-4 2E-4 Tc-97 21E-3 8E-4 Tc-99m_ 6E-3 3E-3 Tc-99 3E-4 2E-4 Telluriu (52) Te-125m 2E-4 1E-4 Te-127m 6E-5 5E-5 Te-127 3E-4 2E-4 Te-129m 3E-5 2E-5 Te-129 8E-4 8E-4 Te-13 lm 6E-5 4E-5 Te-132 3E-5 2E-5 Terbium (65) Th-160 4E-5 4E-5 Thallium (81) T1-200 4E-4 2E-4 T1-201 3E-4 2E-4 T1-202 1E-4 7E-5 T1-204 1E-4 6E-5 Thorium (90) Th-227 2E-5 2E-5 Th-228 7E-6 lIE-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 21E-5 2E-5 Thulium (69) Tm-170 5E-5 5E-5 Tm-171 5E-4 5E-4 Tin (50) Sn- 113 9E-5 8E-5 Sn-124 2E-5 2E-5 Tungsten (74) W-181 4E-4 3E-4 W-185 lE-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 Page 155 of 156

II i 61 Salem ODCM Rev. 19 Table, F-i1 (Cointinued), L Element Istp'Soluble6 Conc. Insoluble Conc. Vanadium (23) V-4-8

                                                               ~(gci/mi) 3E-5 (jtci/ml) 3E-5 L

Ytterbiumn (70) Yb-175- 1E-4 Il-YttriumY9 2E 2E-5 _ _ _ _ _ _ _ _ Y-91m- 3E-31-:- 3E-3 "'1 ___ __ _ _ _ _ _ - 13E-5 3E-5 1 Y~-921t-`! 6E-5!,~I'r 6E-5 ` _ _ _ _ _ _ _ _ Y-93 3 - 3E"-5; Zinc (30). Zn-65 1E-4,2- ___ __ _ _ _ _ _ Zn6 2E3! i2E-31 U Zirconium (.40) Zr-93, _8E- 8E4- ________Z-5 E56 E-E-5 Any snlrai-I .T Zr-977"'

                                      ~,,~;,!~~~~3E-6 2E-5I2 3E-                         11,,---1          I LI nucid rnot listed above w~ith decay mode oththn-alpha, emission"' or                                                                                                              I- 1i-.- 12 spontaneous fssion.

nd withrado6' .jj.< F, C 4 L ac'tive half-ife ..

                                                                                                                               -. I greater than .2 hour Aysngle rdo-t'7 3-E L

nucliidentlitd., above, which-decays., by alpha' emissionbor&. . I i U spontaneous "fSission. ~-~ Notes: L 1.I th~dniy of any riocleis be: 3E-8 JLCi/mL. not know~n,` tl6 limiting values, fcfi uuiposes of thst "1s1i U

2. If theldidetity, and concentration of each radionuolid'e a~re known, the 1iiiiiting~ values, should lb6-,.,"~~t~

derived-as follows: Determinep, for. each radionuclide Mixur, Wntet aIo betwenteqniy L present in the mixture and thelimit otherwise established in Appendix B for th specific radionuclide not in a mixture. The sum of such rdtids for all the radionudlides' in the mixture may not exce'ed "1I, (lie."niy) . - , LI Page l56 ~of 156 I}}