ML20096G917

Proposed Changes to RETS

ML20096G917
Person / Time
Site:	Crane
Issue date:	05/19/1992
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20096G877	List: ML20096G872 ML20096G903 ML20096G917
References
NUDOCS 9205270039
Download: ML20096G917 (32)

Text

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IB LE OF CONTENTS Section P_ase IERLNICAl-SPECIFICATIONS 1-DEFINITIONS 1-1 1.1 RATED POWER l-1 1.2 REACTOR OPERATING CONDITIONS 1-1 1.2.1 Cold Shutdown 1-1 1.2.2 Hot Shutdown 1-1 1.2.3 Resctor Critical 1-1 1.2.4-Hot Standby.

1-1 1.2.5

. Power Operation 1-1 1.2.6 Refueling Shutdown 1-1 1.2.7 Refueling Operation 1-2 1.2.8 Refueling Interval 1-2 1.2.9 ptartup 1-2 1.2.10 Avg 1-2 1.2.11 Heatup-Cooldown Mode 1-2 1.2.12 Station, Unit, Plant, and Facility 1-2 1.3-OPERABLE l-2

.l.4 PROTECTIVE INSTRUMENTATION LOGIC 1-2 1.4.1 Instrument Channel 1-2

1. 4 '. 2 Reactor Protection System 1-2 1.4.3 Protection Channel 1-3 1.4.4 Reactor Protection System Logic 1-3 1.4.5 Engineered Safety. Features System 1-3 1.4.6 Degree of Redundancy 1-3 1.5 -

JNSTRUMENTATION SURVEILLANCE l-3 1.5.1 Trip Test 1-3

-1.5.2 Channel Test 1-3 1.5.3 Channel Check 1-4 1.5.4 Channel Calibration 1-4 1.5.5 Heat Balance Check 1-4

-1.5.6 Heat Balance Calibration 1-4 1.6:

POWER DISTRIBUTION 1-5 1.6.1 Quadrant Power Tilt 1-5 1.6.2 Axial Power Imbalance -

1-5 1.7 CONTAINMENT INTEGRITY l-5 1.8 FIRE SUPPRESSION WATER SYSTEM l-5 1.9 DELETED l-6 1.10-DELETED 1-6 1.11 DELETED 1-6 1.12 DOSE E0VIVALENT I-131 1-6 1.13 SOURCE CHECK 1-6 1.14 SOLIDIFICATION - DELETED l-6 l

1.15 0FFSITE DOSE CALCULATION MANUAL 1-6

.l.16 PROCESS CONTROL PROGRAM l-6 1.17-GASEOUS RADWASTE TREATMENT SYSTEM l-6 1.18 VENTILATION EXHAUST TREATMENT SYSTEM l-7 1.19 f_URGF-PURGING l-7 1.20 VENTING l-7 1.21 REPORTABLE EVENT l-7 1.22 M_ EMBER (S) 0F THE PUBLIC 1-7 1.23 SUBSTANTIVE CHANGES 1-7 1.24-

[0RE OPERATING LIMITS REPORT 1-8 l

l 1.25 FRE00ENCY NOTATION 1-8 i

Amendment No. 11, 72, 129, 137, 142, 150, 155 9205270039-920519 PDR ADOCK 05000209 i

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[IABLE OF CONTENTS-

- Sec t i on '-

5' DESIGN FEATURES 5-1 5.1:

Silf

_. 2 5-1

5.2

' CONTAINMENT

'5.2.1 REACTOR. BUILDING 5-2 5.2.2-

REACTOR BUILDING ISOLATION SYSTEM 5-3' 5.3:

REACTOR 5-4 5.3.1 REACTOR CORE 5-4 5.3.2 REACTOR COOLANT SYSTEM 5-4 5.4-NEW AND SPENT FUEL STORAGE-FACILITIES-5-6 5.4.1

- NEW: FUEL STORAGE-5-6 5.4.2 SPENT FUEL STORAGE 5-6' 5.5

-AIR INTAKE TUNNEL-FIRE PROTECTION SYSTEMS 5-8 6

ADMINISTRATIVE CONTROLS =

6-1 6.1-

' RESPONSIBILITY 6-1 6.2 ORGANIZATION--

61 6.2.1-

' CORPORATE 6-1

-6.2.2

-UNIT STAFF--

6-1 6.3 UNIT STAFF-0VALIFICATIONS 6-3

. 6. 4.

-IBAINING _

6 -

6.5

REVIEW AND-AUDITE 6-3 6.5.l' TECHNICAL REVIEW.AND CONTROL 6-4 6.5.2 INDEPENDENT. SAFETY REVIEW 6-5 6.5.3 AUDITS 6 -

6.5.4-

-INDEPENDENT:0NSITE SAFETY REVIEW GROUP 6 16.6 REPORTABLE EVENT ACTION

.6-10 6.7 SAFETY LIMIT VIOLATION 6-10 J6.8-PROCEDURES AND PROGRAMS.

6-11 l

6.9

' REPORTING RE0dIREM1HIS 6-12 6.9.11 ROUTINE REPORTS 6-12 6.9.2 DELETED 6-14 L6.9.31

. ANNUAL RADIOLOGICAL ENVIRONMENTAL-OPERATING REPORT 6-17 6.9.4-SEMIANNUAL RADI0 ACTIVE 1 EFFLUENT RELEASE REPORT 6-18 6.9.5 -

CORE OPERATING LIMITS REPORT-6-19 6.10-RECORD RETENTIDN. _

6-20 6.11 RADIATION PROTECTION PROGRAM 6-22 6.-12 HIGH RADIATION AREA 6-22 6.' 13 -

PROCESS CONTROL-PROGRAM 6-23' 16.~ 14 -

0FFSITE DOSE CALCULATION MANUAL (0DCM) 6-24 6.15 DELETED 6-24 6.16'

' POST ACCIDENT SAMPLING' PROGRAMS 6-24 NUREG 0737 (II.B.3. II.F.I.21

'6.17 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS 6.

t

-v-Amendment No.:ll, 47,.72, 77, 129, 150 m.

-. ~

LLST OF TABLFJ TE}11 TITLE JLAS1

-1.2 Frequency Notation 1-8 2.3-1 Reactor Protection System Trip Setting Limits 2-9 3.1.6.1-Pressure Isolation _ Check Valves Between the 3-15a Primary Coolant-System and LPIS 3.5-1 Instruments Operating Conditions 3-29 3.5-1A' DELETED 3.5-2 Accident Monitoring Instruments 3-40c 3.5 Post Accident Monitoring Instrumentation 3-40d 3.21-l Radioactive Liquid' Effluent Monitoring 3-97 Instrumentation 3.21-2 Radioactive Gaseous Process and Effluent 3-101 Monitoring Instrumentation 3.23-1 DELETED 3.23-2 DELETED 4.1-1 Instrument-Surveillance Requirements 4-3 4.1-2 Minimum Equipment Test Frequency 4-8 4.1-3 Minimum Sampling Frequency 4-9 4.1-4 Post Accident Monitoring Instrumentation 4-10a 4.19-1 Minimum Number of Steam Generators to be 4-84 Inspected During Inservice Inspection 4.19-2 Steam Generator Tube Inspection 4-85 4.21-1 Radioactive liquid Effluent Monitoring 4-88 Instrumentation Surveillance Requirements 4.21-2 Radioactive Gaseous Effluent Moeitoring 4-91 Instrumentation Sur eillance Requirements 4.22-1 Radioactive Li_ quid Waste Sampling &

4-96 Analysis Program 4.22-2 Radioactive Gaseous Waste Sampling &

4-102 Analysis Program

-4.23-1 DELETED vi Amendment No. 59, 72, 100, 106, 118, 137, 142, 147, 150

9 1.9 DELETED 1.10 DELETED 1.11 DELETED 1.12 DOSE EQUIVALENT-I-131 The DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present. The-thyroid dose conversion factors used for this calculation shall be ti.ose listed in Table III of TID 14844, " Calculation of Distence factors for Power and Test Reactor Sites".

[0r in-Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.]

1.13 SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

1.14 DELETED 1.15 0FFSITE DOSE CALCULATION MANUAL (0DCM)

The 0FFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and

- parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, 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 Section 6.8.4 and (2). descriptions of the information that should be included in the Annual Radiological-Environmental Operating and Semi-annual Radioactive Effluent Release Reports required by Specifications 6.9.3 and 6.9.4.

1.16 PROCESS CONTROL PROGRAM (PCP)

The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid

-ioactive wastes based on demonstrated processing of actual or simulated wet i d wastes will be accomplished in such a way as to assure compliance with ]~

.FR Parts 20, 61, and 71, State regulations, burial ground requirements,-and -her requirements governing the disposal of solid radioactive waste.

1.17 GASEOUS RADWASTE iREATMENT The GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluent by collecting primary coolant system off gases from the primary system and providing fer delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

1-6 Amendment No. 72, 137

=

1.18 VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTFM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluent by passing vantilation or vent exhaust gases through charcoal absorbers and/or UEPA filtars for the purpose of removing iodine or particulates from the gaseous exhaust system prior to the release to the environment.

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATHENi SYSTEMS.

1.19 PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that repincement air or gas is required to purify the confinement.

1.20 VENTING VENTING is the controlled process of discharging air as gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is not provided. Vent used in system name does not imply a VENTING process.

1.21 REPORTABLE EVENT A REDORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.

1.22 MEMBER (S) 0F THE PUBLIC MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally asociated with the plant. This category does not include employces of the GPU System, GPU contractors or vendors. Also excluded from this category are persord.

who enter the site to service equipment or to make deliveries.

-.23 SUBSTANTIVE CHANGES SUBSTANTIVE CHANGES are those which affect the activities associated with a document or the document's meaning or intent.

Examples of non-substantive changes are: (1) correcting spelling; (2) adding (but not deleting) sign-off spaces; (3) blocking in noter, cautions, etc.; (4) changes in corporate and personnel titles which do not reassign responsibilities and which are not referenced in the Appendix A Technical Specifications; and (5) changes in nomenclature or editorial changes which clearly do not change function, meaning or intent.

1-7 Amendment No. 72 137, 141, 150, 155, 157, 158 l

1.24 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT is a THI-l specific document that provides core operating limits for the current operatirg reload cycle.

These cycle-specific tore opert;ing-limits shall be determined for each reload cycle in accordance with Specification 6.9.5.

Plant operation within these operating limits is asidressed in individual specifications.

1.5 FRE0VENCY NOTATION The."NQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

TABLE 1.2 fEfiUENCY NOTATION

[J0TATION FRE0VENCY S

Shiftly (once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

D Daily (once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

W Weekly (once per 7 days)

M Monthly (once per 31 days)

Q Quarterly (once per 92 days)

S/A.

Semi-Annually (once per 184 days)

R.

Refueling Interval P S/U Prior to each reactor startup, if not done during the previous 7 days P

Completed prior to each release N/A (NA)

Not - applicable E

Once per 18 months l

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1-8 Amendment No. 72, 137, 155 l

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a-i 1.25 FREQUENCY NOTATION Bases Section 1.25 establishes the limit for which the specified time interval for Surveillance Requirements may be extended, it permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g.,

transient conditions or other ongoing surveillance or maintenance activities.

It also provides flexibility to accommodate the length of a fuel cycle for surveillance that are performed at each refueling outage and are specified with a fuel cycle length sure9111ance interval.

It is not intended that this provision be used repeate6ly as a i

convenience to extend surveillance intervals beyond that spectiied for surveillance that are not performed during refueling outages. The limitation of Section 1.25 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillanco Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified i

surveillance interval.

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19 Amendment No. 72,'137, 155 i

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3.22 RA010ACTIVL.EFFlVENT 3.22.1 L10010 EF.D1!Dil 3.22.1.1 CONCENTRAT10!i LIMITING CONDITION FOR OPERAILQti 3.22.1.1 The concentration of radictctive material released at anytime from the unit to unrestricted areas (see Figure 5-3) shall be limited to the concentrations specified in 10 CFR Part 20, Ap)endix B, Table 11 -Column 2 for radionuclides other than dissolved or entrainec ncble gases.

For diss entrained nobic gases, the concentration shall be limited to 3 x 10'p1ved or uti/cc total-activity.

APPLICABillTY: At all times ACTION:

With the concentration of radioactive material released from - the unit to unrestricted areas exceeding the above limits, immediately restore concentration within the above limits.

ME.1 This specification is provided to-ensure that the concentration of radioactive materials released in liquid waste effluent from the unit to unrestricted areas will be less than the concentration levels specified in 10 CFR -Part 20, Appendix B, Table II.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures with (1) the Section ll.A design objectives of Appendix 1, 10 CFR P&rt 50, to a MEMBER OF TliE PUBLIC and (2) the limits of 10 CFR Part 20.106(e)tothepopulation. The concentration limit for noble gases is based upon theiassumption the Xe-13b is the controlling radioisotope and its MPC in air (submersion) was converttd to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)

Publication-2.

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3 106 Amendment No. 72, 137, 149 ir

.iipris

l M010 ACTIVE EFFLUEtti 3.22.2 GASEOUS EFFLUENT 3.22.2.1 DOSE RA_1[

LIMITING CQ(iD11J0N FOR OPERAT10M 3.22.2.1 The dose rate due to radioactive materials released in gaseous effluent from the site (see Figure 5-3) 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 1-131, 1-133, tritium and all radionuclider in particulate form with half lives greater than 6 days:

less than or equal to 1500 mrem /yr to any organ.

APPLICABILITY: At all times.

EIJM:

With the release rate (s) exceeding the above limits, inrnediately decrease the release rate to comply with the above limit (s).

ILMfl iht specification is provided to ensure that the release rate at anytime at the site boundary from gaseous effluent from all units on the site will be

-within the annual dose limits of 10 CFR Part 20 for unrestricted areas.

The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II.

These limits provide reasonable assurance that radioactive material discharged in gaseous effluent will not result in the exposure of a MEMBER OF THE PUBLIC in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table 11 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 MEMBEF 0F THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary.

The specified release rate limits restrict, at all times, the corresponding gama and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the site boundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin.

These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to.a child via the cow-milk pathway to less than or equal to 1500 mrem / year for the nearest cow to the plant.

3-111 l

l Amendment No. 72, 137

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SOLID RAQ10 ACTIVE WASTE

. LIMITING CONDITION FOR OPERATION DELETED-l 8

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3-116 i

Amendment No. 72, 129 l

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7 3.23 BAD 10 LOGICAL ENVIRONMENTAL MONITORING 3.23.1 MONITORING PROGRAM LlHITING CONDITION FOR OPERAT10fl DELETED i

a 3-120 (3-121 deleted)

Amendment No. 72

__;.,s a

TABLE 3.23 1 RADIOLOGIC &L ENVIRONMENTAL MONITORING PROGRAM DELETED P

3-122 (3-123 thru 3-124 deleted)

Amendment No. 72 4

r_.

RADIOLOGICAL ENVIRONMENTAL MONITORING 3.23.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION DELETED l

1.

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i 3-125 Amendment No. 72 Ll'

TABLE 3.23-2 REPORTING LEVJLS FOR PADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES DELETED 3-126 Amendment No. 72

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.,..,m

RADIOLOGICAL ENVIRONMENTAL MONITORING

).23.3 INTERLABORA702Y COMPARIS0N PROGRAM

-- LIMITil t CONDITION FOR OPERATION DELETED 3-127 Amendment No. 72

4.22.3 SOLID RADI0ACTLVE WASTE

~10RVEILLANCE REQUIREMENTS i,22.3.1 SOLID RADWASTE SYSTEM DELETED 4.22.3 2 PROCES? CONTROL PROGRAM DELETED i

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l 4-107 Amendment No. 72, 137 l-

1 4.22.4 TOTAL DOSE SVRVElllANCE RE0VIREMENT 4.22.4.1 DOSE cal.CVLATION Cumulative annual dose contributions from liquid and gaseous effluer.ts shall be determined in accordance with TS 4.22.1.2, 4.22.2.2 and 4.22.2.3, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM.

4-108 (Pages 4-109 to 4-116 intentionally blank)

Amendment No. 72, 137

_ ~.-..

1 SURVEILLANCE REQUIREMENTS 4.23.1 DELETED l

i 4-117 Amendment No. 72

F TABLE 4.23-1 MAXIMUM VALVES FOR THE LOWER LIMITS OF DETECTION (LLD1 DELETED

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u 4-118 (4-119 thru 4-120 deleted)

Amendment No. 72 7

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SURVEILLANCE REQUIREMENTS 4.23.2 DELETED f

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l 4-121 Amendment No. 72

F

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SURVEILLANCE REQUIREMENTS 4.23.3 DELETED l

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l-4-122 l

-Amendment No. 72 p--

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6.8 PROCEDURES AND PROGRAMft 6.8.1 Written procedures shall be established, implemented and maintained covering the items referenced below:

a.

The. applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Surveillance and test activities of equipment that affects nuclear safety and radioactive waste management equipment.

c.

Refueling Operations.

d.

Security Plan Implementation, e.

Fire Protection Program Implementation, f.

Emergency Plan Implementation, g.

Process Control Program Implementation, h.

Offsite Dose Calculation Manual Implementation.

i.

Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 4.15, Revision 1.

J.

Plant Staff Overtime, to limit the amount worked by staff performing safety-related functions in accordance with NRC Policy Statement on working hours (Generic letter No. 82-12).

6.8.2 Further, each procedure required by 6.8.1 above, and substantive changes thereto, shall be reviewed and approved as described in 6.5.1 prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a.

The intent of the original procedure is not altered; b.

The change is approved by two members of GPUNC Hanagement Staff qualified in accordance with 6.5.1.14 and knowledgeable in the area affected by the procedure. For changes which may affect the operational status of unit systems or equipment, at least one of these individuals shall be a member of unit management or sup_rvision holding a Senior Reactor Op3rator's License on the unit.

c.

The change is documented, reviewed and approved as described in 6.5.1 within 14 days of implementation.

6-11 Amendment No. 11, 32, 72, 77, 84, 129, 141, 157 q

)

i 6.8.4 Radiological Environmental Monitorina Progs A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The prograni shall (1) be c.ntained in the ODCM, (2) conform to the guidance of Appendix 1 to 10 CFR Part 50, and (3) include the following:

(1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, (2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and (3)

Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

4 4

a 6-lla

m 6.9.3 ANNUAL RADIOLOGICAL ENVIR0f4 MENTAL OPERATING _REPORI i

6.9.3.1 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 Report shall include summaries, interpretations, and an a.:alysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in: (1) the ODCM; and, (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

Rgle: A single submittal may be made for the station.

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6-17 Amendment No. 59, 64, 72, 77, 108, 117, 179, 117

- - =....

6.9.4 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.4.1 The Semiannual Radioactive Effluent Release Report covering the operations of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year, i

The Report shall include a summary of the quantities of radioactive liquid and gaseous effluent and solid waste released from the unit.

The material provided shall be: (1) consistent with the objectives outlined in the ODCM and PCP; and, (2) in conformance with 10 CFR 50.36(a) and Section IV.B.1 of Appendix ! to 10 CFR Part 50.

L H21g:

A single submittal may be made for the station.

The submittal should combine those sections that are common to both units at the station.

i 6-18 Amendment No. 72, 77, 129, 137

r 6.9.5 CORE OPERATING _ LIMITS REPORT 6.9.5.1 The core operating limits addressed by the individual Technical Specifications shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reloaa cycle or prior to any remaining part of a reload cycle.

6.9,5.2 The analytical methods used to determine the core operating limits addressed by the individual Technical Specifications shall be those previously reviewed and approved by the NRC for use at THI-1, specifically:

(1) BAW-10122A Rev.1, " Normal Operating Controls." May 1984.

(2) BAWe10ll6-A, " Assembly Calculations and fitted Nuclear Data,"

May 1977.

i (3) BAW-10ll7P-A, " Babcock & Wilcox Version of P0Q User's Manue',"

January 1977.

(4) BAW-10ll8A, " Core Calculational Techniques and Procedures,"

December 1979.

(5) BAW-10124A, " FLAME 3 - A Three-Dimensional Nodal Code for Calculating Core Reactivity and Power Distributions,"

August 1976.

(6) BAW-10125A, " Verification of Three-Dimensional FLAME Code,"

August 1976.

(7) BAW-10152A, " NOODLE - A Multi-Dimensional Two Group Reactor Simulator," June 1985.

(8)'BAW-10119, " Power Peaking Nuclear Reliability Factors,"

June 1977..

6.9.5,3 The core operating limits shall be determined so that all applicable limits (e.g. fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS -limits, nuclear limits such as shutdown margin, and transient / accident analysis limits) of the safety analysis are met.

6.9.5.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions -

or: supplements theretn, shall be provided upon issuance for each reload cycle to the NRC Document-Control Desk with copies to the Regional Administrator and Resident Inspector.

6-19 Amendment No.-72, 77, 129, 137, 141, 149, 150

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6.10 EffaRD RETENTION 6.10.1 The following records shall be retained for at least five years:

a.

Records of normal station operation including power levels and periods of operation at each power level.

b.

Records of principal maintenance activities, including

-inspection, repairs, substitution, or replacement of principal items 6.' equipment related to nuclear safety, c.

All REPORTABLE EVENTS.

d.

Records of periodic checks, tests and calibrations.

e.

Records of reactor physics tests and other special tests related to nuclear safety.

f.

Changes to procedures required by Specification 6.8.1.

g.

Records of solid radioactive shipments.

6 20 Amendment No. 72,.77, 129, 137, 141, 149, 150

(___________

m.

Records of the service lives of all safety related hydraulic snubbers including the date at which the service life commences and associated installation and uaintenance records.

6.10.3 The following records shall be retained for the duration of the unit Operating License:-

o.

Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

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I-l 6-21 Amendment No. 72, 77, 129, 137, 141, 149, '50

r 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the-requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION _ARfA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203 (c)(2) of 10 CFR 20:

a. Each High Radiation Area as defined by paragraph 20.202 (b)(3) shall be barricaded and conspicuously posted as a High Radiation Area, and personnel desiring entrance shall obtain a Radiation Work Permit (RWP).

Any individual or group of individuals entering a High Radiation Area shall (a) use a continuously indicating dose rate monitoring device or (b) use a radiation dose rate integrating device which alarms at a pre set dose level (entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them), or (c) assure that a radiological control technician provides positive control over activities within the area and periodic radiation surveillance with a dose rate monitoring instrument.

b. Any area accessible to personnel where a major portion of the body could receive-in any one hour a dose in excess of one thousand mrem shall be locked or guarded to prevent unauthorized entry. The keys to these locked barricades shall be Laintained under the administrative control of the respective Radiological Controls Supervisor.

The Radiation Work Permit is not required by Radiological Controls personnel during the performance of their assigned radiation protection duties provided they are following radiological control procedures for entry into High Radiation Areas.

6-22 Amendment Nos.

11, 35, 72, 77, 106, 107, 129 l

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 GPU Nuclear Corporation initiated changes to the PCP:

1. Shall be submitted to the NRC in the Semiannual Radioactive Effluent Release Report for the period in which the changes were made.

This submittal shall contain:

a.

sufficiently detailed information to justify the changes without benefit of additional or i

supplemental information; 1

b.

a determination _that the changes did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.

documentation that the changes have been reviewed and approved pursuant to 6.8.2.

2. Shall become effective upon review and approval by GPUNC Management.

6-23

. Amendment Nos.

11, 35, 72, 77, 106, 107, 129

- ~ -. ~.

r' 6.14 0FFSITE DOSE CALCVLATION MANUAL (ODCM) 6.14.1 The ODCM sb il be approved by the Commission prior to implementation.

6.14.2 GPU Nuclear Corporation initiated changes to the ODCH:

1. Shall be submitted to the NRC in the Semiannual Radioactive Effluent

'i Release Report for the period in which the changes were made. This submittal shall contain:

a. sufficiently detailed information to justify the changes without benefit of additional or supplemental information;

b. a determination that the changes did not reduce the accuracy or reliability of dose calculations or setpoint determinations; and

c. documentation t'.at the changes have been reviewed and approved pursuant to 6.8.2.

2. Shall become effective upon review and approval by GPUNC Management.

6.15 DELETED 6.16 POST-ACCIDENT SAMPllNG PROGRAMS NVREG 0737 (II.B.3. II.F.1.2) s Program which will ensu re the capability to accurately sample and analyze vital areas under accident conditions have been implemented.

The following programs have been established:

1. Iodine and Particuiate Sampling

2. Reactor Coolant System

3. Containment Atmosphere Sampling Each program shall be maintained and shall include the following:

1. Training of personnel,

2. Procedures, and

3. Provisions for maintenance of sampling and analysis equipment.

6-24 Amendment No. 72, 77, 102 e

f'

4 O

6.17 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS 6.17.1 GPU Nuclea'r Corporation initiated safety related changes to the rcdioactive waste system (liquid, gaseous ano solid):

i 1.

Shall be reported to the Commission in the Annual Report (Specification f.9.18) for the period in which the evaluation was reviewed.

The discussion of each change shall contain:

a.

A summary of the evaluation that led to the determination that the change could be made in acco-dance with 10 CFR 50.59; b.

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

A detailed description of the equipment, components and processes involved and the Interfaces with other plant systems-d.

An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; e.

An evaluation of the change which shows the expected maximum exposures to individuals in the unrestricted area and tc the general population that differ from those previously estimated in the license application and anendments thereto; f.

A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g.

An estimate of the exposure to plant operating personnel as a result of the change; and h.

Documentation of the fact that the change was reviewed andapproved.

2.

Shall-become effective upon review and approval in accordance with Section 6.5.1.

l 6-25 Amendment No. 72, 77, 102

- _= -. - -

.-._. ~_

THI Radiological Controls Departmental Procedure 6610-PLN-4200.01 j

Revision No.

Title Offsite Dose Calculation Manual (ODCM) 1 Calculate offsite doses Responsible Office i

Applicability / Scope due to radioactive eff. uents for demsnetrating compliance with Site Technical Specifications 10 CFR 20 & 10 CFR 50 - Appendix I 6610 This doeurrnnt is within QA plan scope X

Yes No Ef F sctive Date Safety Reviews Required X

Yes No l

12/20/91

~

List of Effective Pages Page Revision Page Reviyion Page Revision Page Revision 1.0 1

27.0 1

53.0 1

79.0 1

2.0 1

28.0 1

54.0 1

80.0 1

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29.0 1

55.0 1

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104.0 1

4 ll SiqEr,ture l Concurring Organizational Element l Date iOriginator!\\

')

l^

N*

l Radioloolcal Enoineer, TMI l N*2MN/

l Env. Controls l72 b

= Concurred ll_ /.[ h *

- /

By ll Wh

! Rad. Eng. Manager, TMI l /2a @d /

ll

[1 I Rad. Con. Director, TMI l /2-b d /

ll%

l Chairman, TMI-2 Plant Reviaw Group l /2--Issd,/ _

/

//

V l TMI-2, Site Operations Director l/[

.ll yv-l l + <.v I

I, Approved llM7fbCor ble./.[l Rad con and Env Controls, Director l '8 h [f/

l-By ll l

l v

1.0 2171c i

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raz.aaotolosteat controis Departmentai Procedure 6610-PIJ-4200. 01 Title Revision No.

Offeite Dose Caiculation Manual (OON) 1 Page Revision Pye Revision Page Revision Page Revision 105.0 1'

E6-1 1

106.0 1

E7-1.

1

'107.0 1

E7-2 1

108.0 1

E7-3 1

109.0-1 E7-4 1

110.0 1

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-126.0 1

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-1

.130.0 1

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134.0

-- 1 135.0 1

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137.0-1

-138.0

-1 139.0 1~

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142.0-1 --

=143.0 1

'144.0.

1 El-1 1

E2-1

'1 4

E3-1:

1 E4-1.

1 E4 1-ES-1

-1

.E5-2 1

2.0 2171c

[ 2.jNuclear' TMI,adio1ogica1 Cont,ois 6610-PLN-4200.01 Departmental Procedure Revision i.o.

Title 1

Offsite Dose Calculation Manual (ODO4)

INTRODUCTION The OTFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the GPUNC Three The Mile Island Nuclear Station (THINS) Unit 1 and Unit 2 Technical Specifications.

ODCM describes the methodology and parameters to be used in the calculation of off-site This document also describes the doses due to radioactive liquid and gaseous effluents.

methodology used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. Liquid and Gaseous Radwaste Treatment System configurations are also included.

The ODCM also is used to define the requirem)nts for the TMINS radiological and contains a list and graphical description of environmental monitorinc 'cogram (REMP) the specific sample locamons used in the REMP.

site for use as a reference guide The ODCM is maintained at the Three Mile Island (TMI)

Changes in the and training document of accepted methodologies and calculations.

the ODCM calculation methoda or parameters will be incorporated into the ODCM to ensure GPUNC initiated changes to represents the present methodology in all applicable areas.

the ODCM will be implemented in accordance with the THI-l and TMI-2 Technical Specifications.

The ODCM follows the methodology and models suggetsted by NUREG-0133, and Regulatory affluent Guide 1.109, Revision 1 for calculation of offerite doses due to plant Simplifying assumptions have been applied in this manusl where applicable to releases.

provide a more workable document for implementat!.on of the Radiolog!. cal Effluent controle requirements.

CPUN implements the TMI Radiological Effluent Controla Program and Regulatory nuide 1.21, Revision 1 (Semiannual Radioactive Effluent Release Report) requirements by use of computorized system used to determine TMI effluent releases and to update cumulative effluent doses.

2171c 3.0

N THI Radiological Controls Departmental Procedure 6610-FLN-42OO.01 Revision No.

Tit 1s l

1

'.faite Dose Calculation Manual (CDCM)

TABLE OF CONTENTS PARTI EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Pg Section 13.0 1.0 LIQUID EFFLUENT HONITORS 13.0 1.1 THI-l and TMI-2 Liquid Radiation Monitor Set Points 14.0 1.2 TMI Liquid Release Points and Liquid Radiation Monitor Data If.0 1.3 Control of Liquid Releases 21.0 2.0 LIQUID EFFLUENT DOSE ASSESS!GDfT 21.0 2.1 Liquid Effluents - 10 CFR 50 Appendix I 23.0 2.2 TMI-1 Liquid Radwaste System Dose cales once per Month 24.0 2.3 Mternative Dose Calculational Methodology 29.0 3.0 LIQUID KFFLUENT WASTE TRIATMENT SYSTEM 29.0 3.1 ntI-l Liquid Ef fluent waste Treatment System 29.0 3.2 M rabi'ity of TMI-1 Liquid Effluent Waste Treatment System 30.0 3.3

'1F.I-2 Liquid Effluent Waste Treatment System 33.0 4.0 GASEOUS RFFLUENT MONITORS 33.0 4.1 TMI-1 Noble Gas Monitor Set Points 35.0 4.2 TMI-l Particulate and Radiolodine Monitor Set Pointo 36.0 4.3 THI-2 Gaseous Radiation Monitor Set Points 37.0 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 39.0 4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 41.0 4.6 Control of Gaseous Effluent Releases 53.0 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 53.0 5.1 Gabeous Effluents - 10 CFR 20 Limits 53.0 5.1.1 Noble Cases 4.0 2171c i

MUClear TMI Raeiological Controis Departmental Procedure 6610-PLN-4200.01 _

Revision No.

Title Of t' site Dose Calculation Manual (ODCM) 1 TABLE OF CONTENTS (Cont'd)

FARTI EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Page Section 53.0 5.1.1.1 Total Body 5.1.1. 2 Skin 54.0 5.1.2 Iodines and Particulates 54.0 5.2 Gaseous Effluents - 10 CTR 50 Appendix I 56.0 5.2.1 Noble Cases 56.0 5.2.2 Iodines and Particulates 57.0 5.3 Gaseous Radioactive System Dose Calculations Once per Month C9.0 5.4 Alternative Dose Calculational Methodologies 59.0 61.0 6.0 GASEOUS EFFIDENT WASTE TREATMENT SYSTEM 81.0 6.1 Description of the TMI-1 Gassous Radwaste Treatment System 81.0 6.2 Operability of the TMI-1 Gaseous Radwaste Treatment System 7.0 TMINS RADIO W ICAL ENVIROIOMNTAL MONITORING PROGRAM (REMP) 83.0 83.0 7.1 Monitoring Program Requirements 85.0 7.2 Land Use census 87.0 7.3 Interlaboratory Comparison Program 104.0 8.0 PART I REFERENCES 5.0 2171c l

l l

ENuclear THI Radiotootcat Controts Departmental Procedure 6610-PLN-42OO.01 Revision No.-

Title

_,1 Offsite Dose calculation Manu_al (ODOW)

TABLE OF CONTENTS (Cont'd)

PARTI EFFLUENT DATA AND CALCULATIGNAL METHODOLOGIES Page Section TABLES l'.. O TMI-l Liquid Release Point and Liquid Radiation Monitor Data Table l'.1 18.t' Table 1.2 TMI-2 Sump Capacities Table 2.1 Liquid Dose Coepersion Factors (DCF): DF 25.0 y

28.0 Table 2.2 Bioaccumulation Factors, BF3 42.0 Table 4.1 THI-l Gaseous Release Point & Gaseous Radiation Monitor Data 43.0 Table 4.2 THI-2 Gaseous Release Point & Gaseous Radiation Monitor Data 44.0 Table 4.3 Dose Factors for Noble Gases and Daughters 45.0 Table 4.4 Atmospheric Dispertion Factors for Three Mile Island.-

Station Vent 46.0 Table.4.5-Atmospheric Disperbion Factors for Three Mile Island -

Ground Release 47.0 Table 4.6 Dose Parameters for Radiolodines and Radioactive Particulate, Gaseous, Effluents Infant, Inhalation 60.0 Tab.e 5.2.1 Pathway Dose Factors, R3 s

- Child, Inhalation 61.0 Table 5.2.2 Pathway Dose Factors, R3 1

- Teen, Inhalation 62.0 Table 5.2.3 Pathway Dose Factors,.R3

- Adult, Inhalation 63.0 Table 5.2.4 Pathway Dose Factors, R3

- All Age Groups, Ground Plane 64.0 i-Table 5.3.1 Pathway. Dose Factors, R3 Table 5.4.1 Pathway Dose Factors, R. - Inf ant, Grass-cow-Milk 65.0 3

66.0 Table 5.4.2 Pathway Dose Factors, R _- Child, Grass-Cow-Hilk 3

- Teen, Grass-Cow-Hilk 67.0 Table 5.4.3 Pathway D9se Factors, R3

- s.wult, Grass-Cow-Milk 68.0 Table S.4.4 Pathway Dosa Factors, R3

- Infant, Grass-Goat-Hilk 69.0 Table 5.5.1 Pathway Dose Factors, R3

- Child, Grass-Goat-Milk 70.0 Table 5.5.2 Pathway Dose Factors, R3 r

6.0 2171c i

i

, -, - ~

l

- Nhthb TMI Radiological Controla Departmental Procedure 6610-PLN-4200.Ol

-Title Revision No.

Offsite Dose Calculation Manual (ODW) 1 TABLE OF CONTENTS (Cont'd)

PARTI EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLES

,_~

- Teen, Grass-Goet-Milk 71.0 Table'5.5.3 Pathway Dose Factors, R3

- Adult, Grass-Goat-Mi"t 72.0 Table'5.5.4 Pathway Dose Factors, R1

- Infant, Grass-Cow-Meat 73.0 Table 5.6.1 Pathway Dose Factors, R3

- Child, Grass-Cow-Meat 74.0 Table 5.6.2 Pathway Dose Factors, R3

- Teen, Grasa-Cow-Meat 75.0 Table 5.6.3 Pathway Dose Factors, R$

- Adult, Grass-Cow-Meat 76.0 Table 5.6.4 Pathway Dose Factors, R3

- Infant, Vegetation 77.0 Table 5.7.1 Pathway Dose Factors, Rg

- Child, Vegetation 78.0 Table 5.7.2 Pathway Dose Facters, R3

- Teen, Vegetation 79.0 Table 5.7.3 Pathway Dose Factors, R3

- Adult, Vegetation 80.0 Table 5.7.4 Pathway Dose Factors, Rg Table 7.1 Sample Collection and Analysis Requirements 88.0

-Table 7.2 Reporting Levels for Radioactivity Concentrations 93.0 in Environmental Samples Table 7.3 Detection Capabilities for Environmental Sample 94.0 Analysis 9 ~,

Table 7.4 TMINS REMP Station Locations - Air Particulate and Air Iedine Table 7.5 TMISS RIMP Station Locations - Direct Radiation 96.0 (TLD)

Table 7.6 TMINS REMP Station Locations - Surface Water 98.0 Table 7.7 TMINS REMP Station Locations - Aquatic Sediment 98.0 Table 7.8 TMINS REMP Station Locations - Milk 99.0 Table 7.9 TMINS REMP Station Locations - Fish 99.0 Table 7.10 TMINS REMP Station Locations - Food Products 100.0 7.0 2171c

~

l N

N TMI Radiological Controls Departmental Procedure (610 PLN-4200.01 Rsv>Jion No.

Title 1

Offsite Dose Calculation Manual (000()

TABLE OF CONTENTS (Cont'd)

PARTI EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Page Section TABLES 101.0 MAP 7.1 Three Mile leland Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 1 Hlle of the Site MAP 7.2 Three Mile Island Nuclear Station Locations of 102.0 Radiological Environmental Monitoring Program 6 cations within 5 miles of the Site MAP 7.3 Three Mile Island Nuclear Station Locations of 103.0 Radiological Environmental Monitoring Program Stations Creater than 5 miles from the Site TICURES 19.0 Figure 1.1 THI-1 Liquid Effluent Pathways 20.0 Figure 1.2 TMI-2 Liquid Effluent Pathways 31.0 Figure 3.1 TMI-1 Liquid Radwaste 32.0 Figure 3.2 TMI-l Liquid Waste Evaporators 48.0 Figure 4.1 THI-l Gaseous Effluent Pathways 49.0 Figure 4.2 THI-l Auxiliary & Fuel Handling Buildings Effluent Pathwayn 50.0 Figure 4.3 TMI-l Reactor Building Effluent Pathway 4

51.0 Figure 4.4 WI-l Condenser Of fgas Ef fluer : Pathway 52.0 Figure 4.5 THI-2 Gaseous Effluent Pathways 82.0 Figure 6.1 Waste Gas System 8.0 2171c

~.

~

.=-. _,-- --.

NU

_TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No.

~

offsite Doce calculation Manual (ODcM) 1

-TABLE OF CONTENTS (Cont'd)

PANT 11 TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section Page 1.0 DEFINITIoss 107.0 Table 1.1, Frequency Notation 109.0 2.0 RADIOIOGICAL EFFLUENT REQUIREMENTS 112.0 2.1 Radioactive Discharges 112.0 2.1.1 Liquid Effluents 112.0 2.1.2 Gaseous Effluents 114.0 2.2 Radioactive Gaseous Effluent Monitoring 119.0 Instrumentation 2.3 Rac81ation Monitoring Instrumentation 120.0 Table 2.2-1, Radioactive Gaseous Effluent Monitoring Instrumentation 121.0

. Table 2.3-1, Radiation Monitoring Instrumentation 122.0 3.0 MONITO"ING REQUIREMENTS 123.0 3.1 Radioactive Discharges 123.0 3.1.1 Liquid Effluents 123.0 3.1.2 Gaseous Effluents 124.0 3.2-Radioactive Gaseous Effluent Monitoring 128.0 Instrumentation 13. 3 Radiation Monitoring Instrumentation 129.0

' Tablo 3.1-1, Radioactive Liquid Waste Sampling and Analys;is 130.0' Table 3.1-2, Radioactive Gaseous Waste Sampling and Analysis 131.0

Table 3.1-3, Radioactive Gaseous Waste Sampling and 133.0 Analysis Program Table 3.2-1, Radioactive Gaseous Effluent Monitoring 136.0 Instrumentation Monitoring Requirements 9.0 2171c

• ~

(UClear zwI anatotoyieat Controis Departmental Procedure-6610-PLN-4200.01 Titre Revision No.

Offeite Dose calculation Manual (ODCM) 1 TABLE OF CONTENTS (Cont'd)

PART 11 -

TMI-2 RADIOLOGICAL EFFLt'ENT CONTROLS

- S_ect ion Page 4.O DESICN FEATURES 137.0 4.1 SITE 137.0 4.1.1 Exclusion Area 137.0 4.1.2 Low Population Zone 137.0 4.1.3 Site Boundary for Gaseous Effluents 137.0 4.1.4 Site Boundary for Liquid Effluents 137.0 5.0 PART II RRFERENCES-130.0 l

l 10.0 2171c i

MUClear.

TxI Radiotoyicat Contro1.

Departmentat Procedure 6610-PLN-42OO.01 Titie Revision No.

Offsite Dose Caicu1ation Manual (ODCM) 1 TABLE OF CONTENTS (Cont'd)

PART lil REPORTING REGUIREMENTS Section Page 1.0 TMI ANNUE RADIOIAGICAL ENVIRONMEETAL OPERATING REPORT 140.0 2.0 TMI SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 141.0 3.0 QUARTERLY RADIOI4GICAL RELEASES & ESTIMATED 143.0 DOSE REPORT-(TMI-2 only) 4.0 PART III REFERENCES-144.0 APPENDICES A.

Pathway Dose Rate Parameter (P )

El-1 3

B.

Inha1ation Pathway Dose Factor (R )

E2-1 g

C.

Ground Piane Pathway Dose Factor (R )

E3-1 g

D.

Grass-Cow-Milk Pathway Dose Factor (R )

E4-1 3

E.

Cow-P. eat Pathway Dose Factor (R )

E5-1 i

F.

Vegetation Pathway Dose Factor (R ).

E6-1 3

APPENDIX A'- F REFERENCES E7-1 11.0 2171c

4WCl88r ruz-naatoio,1 cat-controis-

-Departmental Procedure 6610-PIJt-4200. 01 Title.

Revision No.

Offsite Dose Calculation Manual (ODCN) 1 PART I EFFLUENT DATA-AND CALCULATIONAL METHODOLOGIES 12.0 2171c

~.

- 0 l OI TMI Radiological Controls Departmental Procedure 6619-PLN-4200.01 Revision No.

Title 1

Offsite Dose Calculation Manual (ODCM) 1.0 LIQUID EFFLUENT MONI'IDRS 1.1 TMI-l and THI-2 Liquid Radiation Monitor Set Points l

The liquid effluent off-line monitors are set such that the concentration (s) of radionuclides in t'ie liquid effluents will not exceed the concentration i

limits specified in 10 CFR 20, Appendix B Table II, Col 2.

Table 1.1 lists the Liquid Effluent Release Points and their parameters; Figure 1.1 provides a Liquid Release Pathway Disgram.

To meet the above limit, the alarm / trip set points for liquid effluent monitors and flow-measuring devices are set in accordance with the following equation e*f

<C (eq 1.1)

F+f where:

C=

the affluent concentration limit implementing 10 CFR 2) for the site, in pci/ml.

c=

the set point, in pci/ml, of the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to dilution and release. The set point is proportional-to the maximum volumetric flow of the effluent line and inversely proportional to the minimal volumetric flow of the dilution stream plus the effluent stream. The alert set point value is set to ensute that advance warning occurs prior to exceeding any limits. The high alarm set point value is such that if it were exceeded, it would result in concentrations exceeding the 10 CFR 20 limits for the unrestricted area.

f=

flow-set point as measured at the radiation monitor location., in volume per unit. time, but in the same units as F below. Discharge flow rangea and flow recorder designations are listed in Table 1.1.

F=

flow rate of dilution water measured prior to the release point, in volume per unit tims. On site dilution minimal fi~ m are listed in Table-1.1.

Tne set point concentration is reduced such that concentration contributions from multiple release points would not combine to axceed 10 CFR 20 limits.

Thi

'et point concentration is converted to set' point scale units using apt.opriate radiation monitor calibration factors.

This section of the ODCd is implemented by the Radiation Mon.itor System Set Points procedure and, for batch releases, the Releasing Radioactive Liquid Waste procedure.

13.0 2171c L -- -. -

TMI Radiological Controls Departmental Procedure 6610-PLN-42OO.Ol__

Revision No.

Title 1

C2faite Dose Calculation Kanual (ODCM) 1.2 TMI Liquid Ef fluent Release Points and Liquid Radiation Monitor Data TMI-l has three required liquid radiation monitors. These are RM-L6, RM-L10, and RM-L12.

These liquid release point radiation monitore and sample points are shown in Table 1.1.

The TMI outfall radiation monitor, RM-L7, is also lis*ad.

TMI-2 does not have any required liquid radiation monitors, but does utilize RM-L12, and RM-L7 for release of non-accident water.

TMI-2 'loes not release any processed water to the environment.

1.2.1 RM-L6 RM-L6 is an off-line system, acnitoring radioactive batch discharges from the TMI-1 liquid radwaste system (see Figure 1.1).

These batch rnleases are sampled and analyzed per site procedures prior to release. The release rate is based on releasing one of two Waste Evaporator Condensate Storage Tanks (WECST) at less than 10% MPC for each identified radionuclide, including conservative default values for Sr-89, Sr-90, and Fe-55.

This ensures this batch release will meet the following equations (C /MPC )

< 0.10, (eq 1.2) g g

where: ci

= diluted concentration of the 1" radionuclide, MPC

= The most limiting concentration for that 3

radionuclide in the unrestricted area (10 CFR 20, App.

B, Table :I, Col. 2).

A value of 3E-3 pCi/ml for dissolved and entrained noble gases shall be used.

The set points for RM-L6 are set for each release based on the monitor response to each radionuclide identified in the gamma scan sample results as follows:

(1.5)* [Il (pCL/cc)g*(CPM /pci/cc)1] + (CPMm ) = ALERT CPM (2.O)* [Il (pC1/cc)g (CPM /pC1/cc)3] + (CPMm) = HIGH ALARM CPM where:

(pCi/cc)g

= positively identified radionuclides (CPM /pCi/cc)g

= RM-L6 sensitivity to radionaclide 1.

(CPM 3g)

= RM-L6 background prior to batch release A high alarm on RM-L6 will close valve WDL-V-257 and terminate any WECST releases to the environment.

14.0 2171c

{

AUClear TMI Radtologica1 controis Departmental Procedure 6610-PLN-42OO.01 Revision No.

Title l

1 Offsite Dose-Calculation Manual {0DCM) 1.2.2-RM-L12 RM-L12 is an off-line system, monitoring combined releases from the Industrial Waste Treatment System / Industrial Waste Filtration System (IWTS/IWFS). The input to IWTS/IWFS originates in TMI-2 sumps, (see Figures 1.1 and 1.2) and the TMI-1 Turbine Building sump (see Figure 1.1).

The set points are based on the maxi. mum release rate from both IWTS and IWFS simultaneously, (see Figure 1.1) a minimum dilutir flow rate, and 50% MPC for I-131, which is the most limiting.

ionuclide at an MPc level of 3E-7 pci/ml. These inputs are used in equation 1.1 to determine the RM-L12 High Alarm set point. The alert set point is then 50% of

-the High Alarm set point. A high alarm on RM-L12 will close IWTS and IWFS release valves and trip release pumps to stop the release.

1.2.3 RM-L10 RM-L10 is a NaI detector submerged in the TMI-1 Turbine Building Sump (see Figure 1.1).

The'not points are based on the calculated RM-L12 set point concentration, since the '!BS discharges directly to the IWTS, which in turn discharges to the Susquehanna River.

Therefore,=the concentration from the Turbine Building Sump should not exceed the set point calculated for the IWTS/IWFS release point. This monitor's high alarm will isolate power to the TBS sump pumps to terminate releases to the IWTS.

1.2.4 RM-L7 RM-L7 is an off-line system, monitoring the THINS outfall to the Susquehanna River (see Figures 1.1 and 1.2).

RM-L7'has an associated proportional to fitsw compositor which is used to collect composite samples. This monitor is the final radiation monitor for l-TMI-1 and TMI-2 normal' liqui' effluent releases.

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TMI Radiological Controls

-Departmental Procedure 6610-PLN-42OO.01 Revision No.

Title 1

_ of fsite Dose Calculation Manual (ODCM) 1.3 control of Liquid Releases TMI liquid effluent releases are controlled to less than 1.0 MPC by limiting RM-L6, the percentage MPC allowabla from the two TMI liquid release poin+s. c 10%

and effluent sampling, limits batch releases to less than or equal MPC, and RM-L12, and effluent sampling, limits releases f rom TMI-1 and TMI-2

- to less than or equal to 50% MP( /sr I-131.

These radiation monitor set points also include built in meter error factors to further ensure that TMI liquid ef fluent releases are less than 1.0 MPC to the environment.

The' radioactivity content of each batch of radioactive liquid waste is determined prior to release by sampling and analysis in accordance with TMI-1 Tech. Spec. Table 4.22-1.

The results of pre-release analyses are used with the calculational methods in Section 1.1, to assure that the concentration at the point of release is maintained within the TMI-1 Tech. Spec. Section 3.22.1.1.

F Post-release analysis of samples compo11ted from batch releases are performed in accordance with TMI-1 Tech. Spec. Table 4.22-1.

The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentratiche ht the point of release were maintained within the TMe 1 Tech. Spec. Section 3.22.1.1.

The radioactivity. concentration of liquida discharged from continuous release points are determined by collection and analysis of samples in accordance

with T.9:-1 Tech. Spec. Table 4.22-1.

The results of the analysis are used with the,1alculational methods of the ODCM to assure that the concentration at the point of release is maintained within the TMI-1 Tech. Spec. Section 3.22.1.1.

16.0 2171c

l l

6610-P1Ji-4200.01 Sevision 1 TABLE 1.1 THI LIQUID RELEASE POIrf AND LIQUID RADIATION DONI1CR DATA (f)

(F)

(FR)

(DF)

LIQUID DISCEARGE RIVER REI. EASE LIQUID RELEASE FLOW FLOW PADIATION TEEMINATION PADIATION PO!rf GPM CN SITE RATE EEAR FIEID KMTOR INTERLOCK MC3fITUR (Marisum (FLOW DILUTION GPM CILtff!ON BENSITTVITY (TES/NO)

(DETEC70R) 14CATICH Values)

RECORDER)

GPM (Range)

FACIOR (CDL/pC1/cc)

VALVES RM-L5 281' Flevation WECST 0 30 gps ba5,000 227 AVE.

5 Co 137 YES (Nal)

DtI-1 Auxt-Batch (FT-84)

( PT-146)

(1.4E6+5.4EB) 7.16E7 WDL-V257 11ary Blog Releases (8000 gal.)

EM-L7 South and af Station

>=5,000 N.A.

227 AVE.

5 "I '/'

J&

(Nal)

TMI-1 MDCT Discharge (FT-146)

(1.4E6-5.438) i/3 hw Of

! +4' f.-1311 u

gg1 1 ant TMI..

[

Non-ACW f

b

~,

4 BM-L13 Suta.orge in Turbina 0-400 gre

" 15,000 237 AVE.

I

.-131 YES

{paI)

TMI-1 Turbine Butiding (FE-h t )

( PT-146 )

(1. 4 E6-5.4 Ee /

1.059 SD-P9A, SD-P93 B1dg. Sump Sump

( & 301)

Ce-137 (10,000 gal.)

1.0E9 DP-L12 IWFS Building IWTS/IW73 0-200 (nza

>=15,000 237 AVE.

5 I-131 YES (Nat)

NW Corner Continuous (FT-3421/

(FT 146)

(1 4E6-5.418) 1.5Et IV-V73, IW-P16,17,18 Releases 0-100 gpa Ca-137 (300,000/

(fr-373) 6.5E7 IW-V279, 80,000 gab)

IV-P29,30 l

• WDL-P-1311 has been flarged of f an a DtI-2 liqui 4 outfall.

"These monitors are utlas,ed for any nossal liquid reinased free THI-1 or TMI-2.

n h

t 17.0 2171c

l N

THI Radiological Controls l

Departmental Procedure 6610-PI.N-4 200. 01 Revision No.

~1tle T

1 Offsite Dose Calculation Manual (ODCM)

TABLE 1.2 TMI-2 SUMP CAPACITIES Total Capacity Gallone Gallons per Inch Sump

-2as 1346 22 As Turbine Building Sump 572

10. 59_,,_

y Circulating Water Pump House Sump 718 9A,

~

Control Building Area Sump 5

538 9.96 Tendon Access Galley Sump Control to Service Building Sump 1346 22.43 Emer. Diesel Generator Sump A/B Wet 837 9.96 Emer. Diesel Generator Sump A/B Dry 1200 14.29 Chlorinator House Sump 1615 22.43 f

Water Treatment Sump 700 Air Intake Tunnel Normal Sump Air Intake Tunnel Emergency Sump 100000 (36.00 Ccndensate Polisher Samp 2617 62.31 1106 26.33 Sludge Collection Sump Heater Drain Sump Solid Waste Staging Facility Sump 1476 24.00 Auxiliary Building Sump 10102 202.00 479 10.00 Decay Heat Vault Sump 479 10.00 Building Spray Vault Sump 61 18.0 2171c

E.;dNuclear Tx1.. 1 1,c.1 cent,o1s Departmental Procedure 6610-PLN-4200.01 Tit 1e Revision No.

offsite Dose calculation Manual (ODcM) 1 FIGURE 1.1 THI-1 LIQUID EFFLUENT PATHWAYS 3m o

a b

"I 3

h W< u d n 1

= i.

. :

a ac

!. g.

s = g S >o g IL G T-B.- 3 G 11! Il i s 'i 3 E ~ l h 1 y g 3 Li A A A p s s bb I G r-e - j 1 8 2 I, A

1. e.

t o = .f.- l 'T 3 3 h 5 5 sj r: 3 I. 1 $i 3 2 E.!! 'd d a i 38 4 is a: 3% * 'i 3I !! i l .m.: l 3 hj. [' B 1il 1il i I 1 3 G a#: 1- -~ - s li G{ 3.4,1 I a = .1 .jo s 2

i

tI i

i :

)

3< c j

*2 i

a t } i

1:

?;o .u1c 19.1

Ir L)] Nuclear' Tx1 s.e1 1,1c.1 come,o1. 6610-PLN-4200.01 Departmental Procedure Revision No. Title 1 offsite Dose calculation Manual (odd) FIGURE 1.2 THI-2 LIQUID EFFLUENT PATHWAYS Control Control + Building Service Sump Area Sump Turbine Diesel Building i 1 G en. 'A' Sump Sump Tendon Diesel Acces:

4 G e n. 'B' Gallery Sump Sume v

Sump v industrialWaste Treatmentsystem RML m RML 7 y O - > "'" *"' *""" TO RIVER 2171c 20.0 l l \\

(UClear TMI Radio 1ogical contro1s Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Dose Calculation Manual (DOCM) 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liquid Effluents - 10 CFR 50 Appendix I Ti a dose f rom liquid ef fluents results from the consumption of fi sh and drinking water. The location of the nearest potable water intake is PP&L Brunner Island S"vam Electric Station located downstream of TMI. The use of the flow of the Susquehanna River as the dilution flow is justified based on the complete mixing in the river prior to the first potable water supply, adequately demonstrated by fiume tracer die etudies and additional liquid effluent release studieo conducted using actual TMI-l tritium relaases. The dose Other pathways contribute negligibly at Three Mile Island. . contribution from all radionuclides in liquid effluente released to the unrestricted area is calculated using the following expression: f 1 FD I DF)}] (eq 2.1) ( f Dose j = E E (At) X (C ) X L ( AN I FR) + (AFy X g g i j where Dose j =.the cumulative dose commitment to the total body or any organ, j, from the liquid af fluents for the total time period, in mrem. and f are At = the length of the time period over which C1 averaged for all liquid releases, in hours. the average concentration of radionuclide, 1, in undiluted liquid Ci= ef fluent during time period At from any liquid release, in pCi/ml. NOTE: For Fe-55, Sr-89, Sr-90, prior to batch releases conserva-tive concentration values will be used in the initial dose calculation based on similar past plant conditions. LLD values are not used in dose calculations. undiluted liquid waste-flow, in gpm. f = plant dilution water flowrate, in gpm I FD = river flowrate, in gpm. FR = dilution factor as a result of mixing effects in the near field of .DF = the discharge structure of 0.2 (Reg. Guide 1.109, Rev. 1,- Table A-2) or taken to be 5 based on the inverse of 0.2. the site-related ingestion dose commitment factor to the total AW and Afy = body or any organ, j, for each identified principle gamma and g beta emitter, in mrum/hr per pCi/ml. AW is the factor for the l water pathway and AF is the factor for the fish pathway. l-l l 21.0 2171c l l

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01-Revision No. Title 1 -Offsite Dose Calculation Manual (ODO() values for AW are determined by the following equation: 33 y = (1.14r5) x _(U,) x (DFy) (eq 2.2) AW where 1.14E5 = (1.0E6 pCi/pci) x (1.0E3 al/kg) + (8760 hr/yr) Water consumption rato for adult is 730 kg/yr (Reg. Guide 1.109, U, = Rev. 1). ingestion dose conversion factor ft.r radionuclide, 1, for adults DF = y total body and for " worst case" organ, 3, in mrem /pci, from Table 2.1-(Reg. Guide 1.109) y *re determined by the following equation: Values'for AF AFy = (1.14ES) x (U ) x (DFy) x (BF ) (eq 2.2.2) t i where: 1.14E5 = defined above Ut= adult fish consumption, assumed to be 21 kg/yr (Reg. Guide 1.109, Rev. 1). DFy= ingestion dose conversion factor for radionuclide, i, for adult total body and for " worst case" organ, j, in mram/pci, from Table 2.1L(Reg. Guide 1.109, Rev. 1). Bioaccumulation factor for radionuclide, i, in fish, in pCi/kg BF = 3 per pel/L from Table 2.2 (Reg. Guide 1.109, Rev. 1). 22.0 2171c

~..- -...... MUClear Tal Radiological Controis Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Doeo calculation Manual (ODCM) 2.2-TMI-l Liquid Radwaste Syr. tem Dose Cales once/ Month .TMI-l Tech. Spec. Section 3.22.1.3 requires that appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the monthly projected doses due to the liquid effluent releases from each unit to unrestricted areas would exceed 0.06 mrom to the total body or 0.2 mrem to any organ in any calendar month. The following calculational method is provided for performing this dose projection. least once.a calendar month, the total dose from all liquid releases for At the month will be integrated. An estimated projected dose for the next month will be determined based on plant operation and the integrated dose-for the previous month ~. If this estimated projected dose exceeds 0.06 mrem total body or 0.2 mrom any organ, appropriate portions of the Liquid Radwaste Treatment System shall be used to teduce radioactivity levels prior to release. (This section does not apply to TMI-2.)- l l l 1. i I 23.0 2171c

N TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No. Title 3 Offeite Dose Calculation Manual (ODCM) 2.3 Alternative Dose Calculational Methodology As an alternative, models in, or based upon, those presented in Regulatory Guide 1.109 (Rev. 1) may be used to make a comprehensive dose assessment. Default parameter values from Reg. Guide 1.109 (Rev. 1) and/or actual site specific data would be used where applicable. l i l l l l l 24.0 2171c

ENuclear Tx1 Ra 1 1 9 ca1 contro1. 1 6610-PLN-4200.01 Departmental Procedure Revision No. Title 1 offsite Done calculation Manual (OccM) TABLE 2.1 LIQUID DOSE CONVERSION FACTORS (DCF): DFy Page 1 of 3 INGESTION DOSE FACTORS FOR ADULTS * (MREM PER PCI INGESTED) NUCLIDE RONE LIVER _ T. BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 c 14 2.84E-06 5.68E-07 5.6BE-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-C6 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 MN 56 NO DATA 1.15E-07 2.04E-08 No DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 =-.-~----. CO 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA No DATA 1.51E-05 CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-06 4.365-06 No DATA NO DATA NO DATA 1.88E-06 - - - - = _ NI 65 5.28E-07 6.86E-08 3.13m-08 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 =- s ZN 69 1.03E-08 1.97E-08 1.37E-09 No DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA HO DATA 5.79E-08 BR 84 SiO DATA NO DATA 5-21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR '35 NO DATA No DATA 2.14E-09 NO DATA No DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-J 9 RB 89 NO DATA 4.01L-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 No DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 N I f f 2171c 25.0 l I

l N TMI Radiological Controls Departmental Procedure 6610-PLN-4/OO.01 Revision No. Title I 1 offsite Dose calculation Manual (ODCM) TABLE 2.1 (Cont'd) LIQUID DOSE CONVERSION FACTORS (DCF): DFy Page 2 of 3 INGESTION DOSE FACTORS FOR ADULTS * (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T. BODY THYROID KIDNE'. LUNG GI-LLI Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA No DATA NO DATA 2.67E-10 Y 91 1.41E-07 No DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 _ =. - - _ _ - - - - _ - - - - _ - - -- -__---== Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 .3 DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-l' WJ DATA 5.12E-10 NO DATA 1 05E-04 = - - _ NB 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.30E-05 MO 99 NO DATA 4.31E-06 8.20E-07 No DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E.0 8.89E-09 RJ DATA 1.06E-08 3.42E-10 4.13E-07 --= TC 101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-22 RU 103 1.85E-07 NO DATA 7.97E-08 NO D ATA 7.06E-07 NO DATA 2.16E-05 RU 105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AG 130M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 SB 125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.0 1.3BE-06 1.97E-05 TE 125M 2.6BE-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 -=. TE 127M 6.77E-06 2.42E-06 8.25L-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE 127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 = = = _ TE 129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE 131 1.97E-08 8.232-09 6.22E-09 1.62E-08 8.63E-08 No DATA 2.79E-09 TE 132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7. '-05 1 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.6.1-06 I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No DATA 1 57E-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 26.0 2171c

-,------_-.----_.m_ - UClear TMz Radio 1ogica Controts Departmental Procedure 6610-PLN-4200.01 Revision No. Titie 1 Offsite Dose calculation Manual (ODcM) TABLE 2.1 (Cont'd) LIQUID DOSE CONVERSION FACTORS (DCF): DFy Page 3 of 3 INGESTION DOSE FACTORS FOR ADULTS * (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG CI-LLI I 135 4.43E-07 1.15E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS 134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 CS 136 6.51E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 = a CS 137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 BA 139 9. 1E-OS 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 B 140 2 3E 05 2.55E-08 1.33E-06 NO DATA 8.67E-0 1.46E-08 4.18E-05 BA 141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 BA 142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 LA 140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA 142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 =-- CE 143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR 143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 L PR 144 3.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND 147 c.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187

1. 03 E-O'I 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 NP 239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05 Dose factors of internal exposure are for continuous intake over a one-year period and include the dose cormnitment over a 50-year period; from Reg. Guide 1.109 (Rev. 1).

Additional dose factors for nuclides not inc1uded in this table may be obtained from NUREG-0172. 27.0 217'.c )

.n. ..7~.--- .+. -~.. Nuclear Tx1 adio1 gica1 Comer.1s Departmental Procedure -6610-PLN-4200.01 Revision No. 31 Tie. 1 Offeite Dose Calculation Manual (OD N) TABLE 2.2 BIOACCUMULATION FACTORS, BF g BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-S?ECIFIC DATA * (pci/kg per pCi/ liter) FRESHWATER ELEMENT FISH INVERTEBRATE H-9.OE-01 9.0E-01 C 4.6E+03 9.1E+03 NA1 1.0E+02 2.0E+02 CR. 2.0E+02 2.0E+03 HN 4.0E+02 9.0E+L1 FE 1.0E+02 3.2E+03 -CO 5.0E+01 2.0E+02 NI 1.0E+02 1.0E+02 CU 5.0E+01 4.0E+02 ZN 2.0F+03 -1.0E+04 BR 4.2E+02 3.3E+02 RB-2.0E+03 1.0E+03 SR-3.0E+01' 1.0E+02 Y 2.5E+01 1.0E+G3 ZR-3.3E+00 6.7E+00 NB 3.0E+04 1.0E*02 Mo' 1.0E+01 1.0E+01 TC 1.5E+01 5.0E+00 RU 1.OE+01 3.0L+02 RH-1.0E+01 3.0E+G2

• SB 1.0E+00 1.0E+00 TE 4.0E+02 6.1E+03-I 1.5E+01 5.0E+00 CS-2.0E+03 1.0E+03 EA 4.0E+00 2.0E+02 LA 2.5E+01 1.0E+03 CE 1.0E+00 1.0E+03 PR 2.5E+01 1.0E+03 ND 2.SE+01 1.CE+03 W

1.2E+03 1.0E+01 NP 1.0E+01 4.0E+02 Bloaccumulation factor va1ues'are taken from Reg. Guide 1.109 (Rev. 1), Tab 1e A-lj. Sb bicaccumulation factor value is taken from EPRI NP-3840. 28.0 2171c

MNuclear TM1 Radio 1ogica1 Controis 6610-PLN-42OO.01 Departmental Procedure Revision No. litle 1 _ Offalte Dose Calculation Manual _(ODCM) j, 3.0 TMI LIQUID kFFLUENT WASTE TREN1HENT SYSTEMS 3.1 TMI-l Liquid Effluent Waste Treatment System Description of the Liquid Radioactive Waste Treatment System (wee 3.1.1 Figure 3.1) Reactor Coolant Train \\ Water Sous?ces - (3) Reactor Coolant Bleed Tanks (RCDT) a. - (1) Reactor Coolant Drain Tank (RCDT) Liquid Processing - Reactor Coolant Waste Evaport,or (see b. Figure 3.2) - Domineralizers prior to release Liquid Effluent for Release - (2) Waste Evaporator Condensate c. Storage Tanks (WECST) d. Dilutier. Mec...si-al Draft Cooling Tower (0-60k gpm) - River Flow (2E7 gpt average) Miscellaneous Wante Train a. Wacer sources: - Auxiliary Building Surap - Reactor Building Sump - Miscellaneous Waste Storage Tank - Laundry Waste Storage Tank - Neutralizer Mixing Tank - Neutraliter Feed Tank - Used Precoat Tank - Dorated Water Tank Tunnel Sump - Heat Exchanger Vault Sump - Tendon Access Galley Sump - Spent Fuel Pool Room Sump _ Liquid Processing - Miscellaneous Waste Evaporator, MWE b. (see Figure 3.2) Dewineralizers prior t' release Liquid 9ffluent for Release - (2) Waste Evaporator Condensate c. Storagu Tanks (WECST) d. Dilution - Hochanictl Draft Cooling Towers, MDCT (0-60k gpm) - River Flow (2E7 g1xn average) 3.2 Operability of the TM1-1 Liquid Effluent Waste Treatment System The TrtI-l Liquid Waste Treatment System as described in Section 11 3.2.1 of the TMI-l Final Safety Analysis Report is considered to be operable when one of each of the following pieces of equipment is available to perforin its intended function: 29.0 2171c

i l P k4 Nuclear TMI xad1 1ogica1 controis Departmental Procedure 6610-P LN-42 OO. 01_, Revision No. T!tle 3 Offalte Dose Calculation Manual (ODCM) a) Miscellaneous waste Evaporator (VUL-Z'B) or Reactor Coolant Evaporator (WDL-Z1A) b) Wasts Evaporacor Condensate Deminera11:er (WDL-K3 A or B) c) Waste Evaporator Condensate Storage Tank (WDL-T 11 A or B) d) Evaporator Condensate Pamps (WDL-P 14 A or B) 3.2.W THI-1 Representative Sampling Prior to Discharge All liquid releases from the TMI-1 Liquid Waste Trmatment System are made through the Waste Etaporator Condensate Storage Tanks. To provide thorough nixing and a representative sample, the contents of the tank are recirculated using one of the Waste Evaporator condensate Transfer Pumps. 3.3 TMI-2 Liquid Effluent Wasts Treatment System 3.3.1 Description of the TMI-2 Liquid Radioactive Waste Treatment Syu *m The THI-2 Liquid Radioactive Waste Treatment System has been cut of service since the THI-2 A cident in 1979. TMI-2, hrwever, releases Usn-Accident Generated Water (AGW) from various sumps and tanks to c.e river (see Figures 1.1 and 1.2). This process is governed by plant procedures that encompass proper sampling, sample ana1ysis, and radiation monitoring techniques. I l l l 30.0 2171c 1

l TMI Radiological Controls Departmental Procedure 6610-PLN-42OO.01 Revision No. Title 1 offsite Dose calculation Manual (ODCH) FIGURE 3.1 THI-1 LIQUID RADWASTE aC -.--.g SW5T iuMP . pRaig I RE ACiOR l 1 F. SUMP N AKE %00 SUMP, itN00N M e0RIC ACIO N RC ORON LP GallIT gg, g Mix TANK tt } TANE _ Mt$C. OR AiN MU-v0 SAFTY AVK SLOG h AtLinF p q p V'LVII $ UMP 3 it U y l'1!l y

• %..v &U E RC OLitD RC Slit 0 RC 6.650

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k k4 Nuclear Tx1 sadio1ogica1 contro1s 6610-PLN-4200.01 Departmental Procedure Revision No. Title 1 1 Offsite Dose Calculation Manual (DDCH) 4.0 CASROUS G7 FLUENT MO851 TORS 4.1 THI-l Noble Gas Monitor Set Poin*s The gaseous effluent monitor set points are established for each gaseous effluent radiation monitor to assure concentrations of radionuclides in forth in 10 CFR 20. Tabic 4.1 gaseous effluer.ts do not exceed the limits set lists caseous Effluent Release Points and their associated parameters; Figure 4.1 provides a Ganeous Effluent helease Pathway Diagram. The set points are established to satisfy the more restrictive set point concentration in the following two equations: (eq 4.1.1) 500 > E (c3)(F)(K )(Dv) g L and (eq 4.1.2) 3000 > J (c )(Lg+ 1.1 H )(Dv)(F) 3 3 i wher6: set point concentration, in pCi/cc c3 = F = gaseoue affluent flowrate at the monicor, in ec/sec (reference Table 4.1) 3 from Table 4.2 total body dose factor, in mrem /yr per pC1/m K = 2 sector annual average atmospheric dispersion factor (X/0) Dv = highest at the unrestricted area boundary, in sec/m, from Table 4.4 for 3 station vent releases and Table 4.5 for all other releases, (Condenser off gar., ESF THB, and ground releases). Maximum values presently used are 4.19E-7 sec/m at sector SE for station vent, and 3 at sectors N and WNW 'or all other releases. 1.16E-5 sec/m3 skin dose factor due to bota emissions from radionuclide 1, in L = g 3 mram/yr per pC1/m from Table 4.3. H, = air dose f actor due to gamma emissions from radionuclide i, in 3 mead /yr per pCi/m from Table 4.3. 1.1 = mram skin dos. per mrad air dose. 500 = annual whole body dose limit for unrestricted areas, in mrem /yr. 3000 = annual skin dose limit for unrestricted areas, in mrem /yr. The set point concentration is further reduced such that the concentration contributions from meltiple release points would not combine to exceed 10 CFR 20 limits. 2171c 33.0 t

I'- ki lNuclear T,:1 Rad. 1o,1ca1 controis Departmental Procedure 6610-PLN-4200.01 Revision ho. Title I Offsite Dose Calculation !'.anual (ODCM) point concentration is converted to set point scale units on each The set radiation monitor using appropriate ca11bration factors. This section of *.he OCCM is implemented by the Radiation Monitor System Set Points procedure and the procedure for Releasing Radtoactive Gasecus Waste. l 1 i l l 2171c 34.0 t t

E.,2dNuclear 1M1,adio1 q1ca1 Cont o1s Departmental Procedure 6610-PLNy4200.01 Revision No. Title 1 Offsite Dose Calculation Manual (ODCH) Points 4.2 THI-l Particulate and Radiciodine Monitor Set radionuclides other than nuble gases are set points for monitors which detect also established to assure that concentrations of these radionuclides in gaseous effluents do not exceed the limits in 10 CTR 20. points are established so as to satisfy the following equationes set (eq 4.2) 1500 > E (c )(F)(P )(Dv) 3 g L where: c = set point concentration, in pCi/cc 3 F = gaseous effluent flow rate at the monitor, in ec/sec (Table 4.1) 3 for the inhalation = rathway dose parameter, in mrem /yr per pCi/m P pathway from Table 4.6. The dose factors are based on the actual 3 individual organ and most restrictive age groep (infant) (NUREG-0133). calculational method 71ogy. l l NOTE: Appendix A contains P3 1500 = annual dose limit to any organ from particulates and radiciodines and radionuclides (other than noble gases) with half lives greater than eight days. Dv = the annual average atmospheric dispersion f actor for the worst-case sector; maxLmum X/Q, in sec/m for the inhalation pathway at the 3 c unrestricted areas Dispersion factors may be read or interpolated from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. Maximum values of X/Q presently used are 4.19E-7 3 3 for station vent, at sector SE, and 1.16E-5 sec/m for all othe-sec/m releases, at sectors N and WNW. The set point concentration is further reduced such that concentration contributions from multiple release points would not combine to exceed 10 CFR 20 limits. scale untte on each The set point concentration is converted to se'. point radiation monitor using appropriate calibration factore. This section of the ODCH is Lmplemented by the Radiation Monitor Systems Est Points procedure and the procedure for Releasing Radioactive Gaseous Waste. 2171c 35.0

Ir k4 Nuclear TH1 Radio 1ogic.1 cent,ois Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Dose Calculation Manual (Ot G ) i 4.3 THI-2 Gaseous Radiation Manitor Set Points l THI-2 Gaseous Radiation Monitors have their set points described in THI-2 Plant Procedure 4210-OPS-3661.02. Figure 4.5 provides a gaseous effluent i release pathway diagram. Table 4.2 provides THI-2 Radiation Monitor Data. These set points are set in accordance with the Controle delineated in Part II of this ODCM. l t l l l I 36.0 2171c

k U1 Nuclear-TM1 R.dio1ogica1 Ceetrois Departmental Procedure L 6610-PLN-42OO.01 Revision No. Title 1 Offsite Dose Calculation Manual (ODCH) 4.4 TMI-1 Ganeous Effluent Release Points and Gaceous Radiation Monitor Data These are THI-1 has eight (8) required effluent gaseous radiation monitors. RM-A4, RM-AS, RM-AlS, RM-A6, PM-A7, RM-AB, RM-A9 and RM-A14. These gaseous release points, radiation monitors, and sample points are shown in Table 4.1. 1 4.4.1 RM-A4/RM-A6 Fuel Handling and Auxiilary Building Exhaust l RM-A4 is the particulate, radiolodine and gaseous radiation monitor for the THI-l Fuel HandAing Building Ventilation (see Figures 4.1 and 4.2). RM-A6 is the particulate, radioiodine, and gaseous radiation monitor for the TMI-l Auxiliary Building ventilation (see Figures 4.1 and 4.2). High alarms on RM-A4 or RM-AC noble gas channels will initiate shutdown of the related building ventilation air supply systen. These two radiation monitors concurre..tly will satisfy requirements for the Station Vent release point in place of RM-AB. 4.4.2 RM-AB Station Ventilation Exhaust _ RM-AB is the particulate, radiciodine and gaseous radiation monitor for the THI-l Station Ventilation (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters. High alarm on RM-AB noble gas low channel will initiate shutdown of the Station Ventilation air supply syttems. (The Fael Handling and Auxiliary Build!ng Ventilation). This radiation monitor satisfies requirements for the Station Vent release point in place of RM-A4 and RM-A6. 4.4.3 RM-A5/RM-A15 Condeneer Off Gas Exhaust RM-A5 is the gassous radiation monitor for the TMI-1 Condenser off Gas exhaust (see Figures 4.1 and 4.4). RM-A15 is the back up gaseous radiation monitor for the THI-l Condenser of f Gas exhaust (see Figures 4.1 and 4.4). High alarms on RM-A5 1cw channel or RM-A15 noble gas channels will initiate the MAP-5 Radioiodine Processor Station. These two radiation monitors together satisfy requirements for the Condenser off Gas release point. I I 4.4.4 AM-A7 Waste Gas Decay Tank Exhaust j RM-A7 is the gaseous radiation monitor for the THI-l Waste Gas Decay tankt (see Figures 4.1 and 4.2). This in plant effluent radiktion monitor also has an associated sampling panel. High alarm on RM-A7 noble gas channel will initiate shutdown of the waste Gas Decay Tank release in progress. This radiation monitor satisfies requirements for batch gaseous releases to the Station Vent release point. 1 l 37.0 2171c

le WINuclear I """** ' Ts1 maa1 1,1ca1 cont,ois Dupartmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manuel (ODCM) 1 4.4.5 RM-A9 Reactor Building Purge Exhaust RM-A9 is the particulate, radiciodine and gaseous radiation monitor for the TMI-l Reactor Building Purget system (see Figures 4.1 and 4.3). This in plant effluent radiation monitor also has an associated sa'r.pling panel with sampling lines located befare the sample filters. High alarm on RN-A9 noble gas low channel will initiate shutdown of the Reactor Building Purge System. Thir radiation monir.or satisfies requirements for the Reactor Building Purge System release point. 4.4.6 RM-A14 ESF FHB Ventilation System RN-A14 is the gaseous radiation monitor for the THI-1 Emergency Safeguards Featurec (EST) Fuel Handling Building Exhaust system (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel witt sampling lines located before the sampler filters. High alarm on RM-A14 noble gas channel will initiate shutdown of the ESF ruel Handling Building Exhaust System. This radiatiori monitor satisfios requirements for the ESF Fuel Handling Building Exhaust System release point. I i } 38.0 21710

k eM THI Radiological Controis Departmental Procedure 6610-PLN-42OO.01 Revision No. Title 1 Of f eitei Dose Calculation Manual 10DCH) THI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 4.5 THI-2 has neven (7) -egulatory required gaseous effluent radiation monitors. These are HP-R-219, HP-R-219A, ALC-RMI-18, WHP-RIT-1, HP-R-225, HP-R-226, and Also included in this discuselon is RLM-RM-1, which monitors PWD-RML-1. effluents from the Rispirator Cleaning and Laundry Maintenance (RLM) facility. These gaseous release points, radiation monitors, and sample points are shown in Table 4.2, and various gaseous effluent pathways are depicted in Figure 4.5. 4.5.1 HF-R-219 Station Ventilation Exhaust HP-R-219 is a Victoreen particulate, radioiodine, and gaseous radiation monitor for the TMI-2 ventilation exhaust. This in-plant effluent radiation monitor is located in the THI-2 Auxiliary Building 328 foot elevation and has an associated sample panel. A high alarm will initiate shutdown of the ventilation air exhaust system. 4.5.2 HP-R-219A Station Ventilation Exhaust HP-R-219A is an Eberline PING particulate, radiciodino, and gaseous radiation mcnitor for the THI-2 ventilt. tion exhaust. This in plant effluent radiation monitor is located on the TMI-2 Auxiliary Building roof and has an associated sample panel. 4.5.3 ALC-kMI-18 E0ICOR II Chemical Cleaning Facility (CCF) Ventilation Exhaust ALC-RMI-18 is an Eberline PING particulate, radiolodine, and gaseous radiation monitor for the TMI-2 EPICOR II radwaste processing building exhaust. Presently, the radiciodine channel is not in use. This monitor is located in the EPICOR II building on the ground floor, and has an associated sample panel. Sampling f or particulate activity is performed off of the monitor. 4.5.4 WHP-RIT-1 Waste Handling and Packaging Facility (WHPF) Exhaust WHP-RIT-1 is an Eberline PING particulate, radioiodine, and gaseous radiation monitor for the TMI WHPF. Presently, the radiciodine and gaseous channels are not in use. The monitor is located in the Mechanical Equipment Room in the WHPF. Sampling for particulate and radiciodine activity is performed off of the monitor. A high alarm will initiate shutdown of the ventilation air exhaust system. 4.5.5 PWD-RML-1 TMI-2 Accident Generated Water (AGW) Evapcrator Distillate Discharge PWD-RML-1 is a Nuclear Research Corporation liquid radiation monitor that evaluates evaporator distillate prior to the liquid The monitor in being vaporized and released to the environment. 39.0 2171c

- - ~.. -.. - ~ - AUClear TMI Radtological controls Departmental Procedure 6610=PLN-4200.01 Revision No. ~itle T I Offsite Dose calculation Manual (ODN) located in the TMI-2 Evaporator Building. This monitor has an associated sample system. A high alarm will initiate shutdown of the TMI-2 Processed Water Disposal System. 4.5.6 PLM-RM-1 Respirator Cleaning and Laundry Maintenance (RLM) Facility RLM-RM-1 is an Eberline PING particulate, radiciodine, and gaseous radiation monitor for the TMI RLM Facility. Presently, the radiniodine and gaseous channels are not in use. The monitor is s located in the Mechanical Equipment Room in the RLM. Sampling for particulate and radiciodine activity is perforred of f of the monitor. 4.5.7 HP-R-225 Reac*or Muilding Purge Air Exhaust Duct "A" HP-R-225 is a Victoreen particulate, radiciodine, and gaseoug radiation monitor for the TMI-2 Reactor Building Purge Air Exhaust. Systam. This in-plant ef fluent radiation monitor is located in the THI-2 Auxiliary Building 328' elevation area. A high alarm will initiate a shutdown of the TMI-2 Reactor Building Purge Exhaust Sy6 tem by tripping exhaust fans and dampers. "B" 4.5.8 _HP-R-226 Reactor Building Purge Air Exhaust Duct HP-R-226 is a Victoreen particulate, radiciodine, and gaseo>s radiation monitor for the THI-2 Reactor Building Purge Air Exhaust l System. This in-plant ef fluent radiation monitor is locate) in the TNT-2 Auxiliary Building 328' elevation are6. A high alarm will initiate a shutdown of the TMI-2 Reactor Bu.lding Purge Exhaust Lystem by tripping exhaust fans and dampers. l l l' L L P 40.0 2171c

k W1 Nuclear TMI xadio1ogica1 :ont,,1s Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 ___Offsite Dose Calculat8.on Manual (DDCM) 4.6 control of Gaseous Effluent Releases TMI gaseous effluent combined releases are controlled (per TMI.* Tech. Spec. Section 3.22.2.1 and ODCM Part II for THI-2) by effluent sampling and .adiation monitor set points. These measures assure that releases from the various vents do not combine to produca dose rates at the site boundary exceeding the most restrictive of 500 mrem per year to the total body orThis 3000 mrem per year to the skin, and 1500.nrem per year to the thyroid. is done by restricting simultaneous releases and by limiting the dose rates The various vent that may be contributed by the various vents at any time. radiation monitor set points are each based on fractions of the above limits and do not exceed the above limits when summed together. These effluent radiation monitor set points ar1 calculated using the methodology described in equations 4.1.1, or 4.1.2 and 4.2. The actual set points are then listed in TMI-1 Operations Procedure 1101-2.1. The radioactive content of each batch of gaseous waste is determined prior to release by sampling and analyses in accordance with THI-1 Tech. Spec. Table 4.22-2 and ODCM Part II for THI-2. The results of pre-release analyses are used with the calculational methods in Sections 4.1 and 4.2 to assure that the dose rates at the site boundary are mainta'.ned below the limits in THI-1 TesN. Spec. Section 3.22.2.1 ana ODCH Part II for TMI-2. Post-release analyses of samples composited from batch and continuous releases are performed in accordance with TMI-1 Tsch. Spec. Table 4.22-2 and ODCM Part II for TMI-2. The results of the analyses are used to assure that the dose rates at the site boundary are maintained within t's limits of THI-1 Tech. Spec. Section 3.22.2.1 and ODCM Part . fer TMI-2. 41.0 2171c

,.. - - - -. ~ _. - =- - - - - -.._==~ ~.-. ,- - ~- ~_-~ 6410 PLN 4200.01 Reviolon 1 7ASLE 4.1 t'M!*1 CASE 008 RELEASE POINT AND CASEOUS RA01 ATION OW170R CATA (F) EXEAUET PADIATI

• RA01ATION RADIATION RELEASE GAstIE'S FICW WNITUA K)NIMR PONITCR TERMIKATION RADIATICA GA&EOUS CFM SENSIT!YITT SENSITIVITY SEN3ITIVITY INTERLOCK MON!70R RE11A82 (FIDW (CPM / MIN /sC1/cc)

(CPM / MIN /yC1/cc) (CFM/pC1/cc) (YES/NO) (DETE0208) LOCATION PCIN1' RELOR.0ER) PAMICL' LATE 10 DINE GAS VALVES M-A4 306' Elevati*n Fuel Band. 0-$0,000 1.30E10 1.22E9

3. 9f,87 YES Auxiliary Sidg.

Building (FR*149) (8r-90) (!*131) (xe-133) AE E 10 Exhaust AM-D-120 AB D-121 AB-D-122 AM-A6 306' Elsystion Aurillary 0 100,000 1.3CE10 1.2219 3.96E1 YE8 Auxiliary 31dg. Su11 ding (FR-1$0) (st-901 (1-131) (Ko-133) AB E-11 { Exhaust l RM As RMA-8/9 31sg. Station 0-150,000 1.60E10 1.3089

3. 6 9E7 YEs

] Near BN8T Vant (FR-151) (ar-90) (1 131) (Ka-133) WDO-V47 AB-E-10 Exhauet AH-t-11 t Starts MO $ Radiciodine sampi er 4.00E7 YE3 RM-AS 322' Elevation Condenser 0-200 Second Ficor off Gas FM-1113 (xe-133) Starts MA*-$ Turbine Bldg. Exhaust 0.70E7 Radiciodine (Ex-45) Sampler 3.2$E7 YE8 RM-All 322' Elevation Condenser 0-200 second Flocr off Cas FR-1113 (Re-133) starts MAP-$ Turbine 81dg. Exhaust 9.11E7 Radiciodine (Kr-85) sampler i 4.00E5 YES M-A7 306' Elevation Waste Gaa 0-10 Auxiliary *1dg. Decay Tanka FR-123 (Ka-133) WDG-v47 (A,3,C) l RM*A9 RMA-8/9 Bldg. Rosetor 0-150,000 1.80510 1.4039 3.v637 YEs paar BW5? Building F3-909/ (St-90) (1 131) (Re '.33) AB-V-1A/8/C/D WDC-534/535 Purge FR-148 starte MAP-5 Exhaust Radiciodine Sampler 1.0127 No RM-114 331' Elevation-18F Fuel 0-7000 ESF THE sandling FR-1104A/S (xe 133) Manual outside Chem. Building 4.2137 Actione Addition sing. Exhauet (Ex-es) 42.0 2171c l l m

- ~ -.. - _ - ~ ----_.... 6610 PLN-4200.01 Paviolon 1 T/2!J 4.2

• N! 2 CASEOUS RE1J.AAF WINT AND GASEOUS RADIATION ON!1DR CATA RADIATICNI PADIAT!rst PADIATION ENITOR mMITOR MON 110R RELEASE GASEOUS SENSITIVITY SENSITIVITY SEN81TIY!TT TDM2"ATION RADIATION CASEOUS IXHAUST (CPM / MIN /mC1/cc)

(CPM / MIN /#C1/cc) (CPM /pci/cc) IsrrERLocR MNITOR 92 LEASE Flow FARTICULATE 200!NE BI"IA CAS ( YE8/f"7) (DETEC'!DP ) LOCATION PCIsrf CI'M BETA SCINTILLATCR 8CINT111ATOR Ns! CETEO!VR VALVES 3r RPR-219 320' Elevation Station 140,000 S.30311 3.89E12 1.0127 YES Auxiliary Vent ($r-90) (1 131) (KR 85) Tripe AR-t-23A/8, Building Exhaust 9A/E 12A/S, 7A/B Clones WDG V-30A/8, D 5129A/8/C/D HPR+219A Adjacent to Station 140,000 . 30ES 2.9054 2.06E7 NOME Station Stack vent (sR-90) (1-131) ( D-85) Exhaust ALC-BM1 19 Chemical EPICOR !! 8,000 1 40E5 2.86E4 2.06E7 NCNE Cleaning Ridg. Exhaust CPM / pct CPM / sci ( D 8$) 304' Elesation ayates (83 90) (1 131) WHP RIT 1 WHPF Mechanical WRPP 7,500 1 40El 2.86E4 2.06E7 YE8 Equipment Roaa Exhaust CPM /NC1 CPM /yC1 (D 85) WHPF Ventila-System (8R 90) (1 131) tion Tripe NOME RIM-MM 1 RIM Mechanical RLM 900 7.0484 ~~ Equipment Roca 4 xfiauet CPM /s.*1 S ystem (8R-90) RP-R-225 328' Elevation peactor $1dg 25,000 S.30311 3.89E12 7.8127 TES Auxiliary Purge Exhaust (8R-90). (1 131). ( D-85) Closea D-5129A, $uilding Duct "A" $1288. OPD8 D-51290, Tripe AB E-12A. KP R-226 328' Elevation Reactor B1dg 25,000 S.30E11 3.89E12 1.0127 YES

• uxi1* ~y Purge Exhaust (SR-90)

(1-131) (D-45) Closes D-51299, Building Duct "8 $128C. OPEN8 D-5129C, Tripe AH E*128. 3.20E0 TES FWD-RML-1 Maar tMI-2 TMI*2 S.0 ~~ Air Intate Accident GPM (Co-137) Closes Structure oenerated vaporizar Water Liquid Feed valves. Evaporator Stack 43.0 2171c

m.______ m. . _ _.. - _. _ = _. _m_-. __.________m.__.. _m. m_-.. 6610-F1.N 4200.01 Reviaton 1 TABLE 4.3 DOSE FA:!!M ICR NOBLE CAIES AND DAUNTER8" Gamma Beta Total Sody 6 tin Dose Gasse Air Dose Factor (s) Factor (b) Dose Factor Sota Air R1 Lg Mg Does rector N Radi0-( :am/yr per (atas/yr per (mra$/yg par 4 nuclide uC1/n 1 act/m 1 pC1/m- ) farad /yr per act/m3, 1.93E+01 2.88t+02 Kr 03e 7.66t+02** Kr-OSm 1.17E*03 1.46t+03 .23t+03 1.972+03 Kr-SS 1.61t+01 1.34t+03 1.72E+71 1.95E+03 Kr t? 5.*1E+03 9.93t+03 6.17t+03 1.0?r+04 Kr et 1.47t+04 2 37*.*! 1.522+04 2.93E+03 Kr-89 1.668+04 1.012+04 1.73t+04 1.06t+04 Kr-90 1.56t+04 7.293+03 1.631+04 7.83t+03 Xe-131s 9.15t+01 4.76E,02 1.56t*02 1.112 + 03 Xo-133e 2.11E+02 9.94t+02 3.273+02 1.482 03 Xe-133 2.94t+02 3.068*02 3.53t+02 1.05t+03 Xe-135m 3.12t+03 7.112+02 3.36t+03 7.39t+02 Xe-135 1.01t+03 1.862+03 1.92t+03 2.46t+03 Xe-137 1.42t+03 1.22t+04 1.$1t+03 1.27t+04 Xe 138 0.033+03 4.638*03 9.21t+03 4.75E+03 Ar-41 0.44t+03 2.693+03-9.3ct+03 3.28t+03

• Does factors are for immersion orposure in unifora wai infinite cloud of noble gas radionuclides that may be detected ta Dose factor values are taken frces Regulatory Guide 1.109 (Rev.1), Table 8 1.

gaseous effluente.

• *7.568-02
• 7. 56 x 10-- 2, (a) Total body dese factor for gamma penetration depth of 5 em into the body.

(b) Skin does factor at a tissue depta or tissue density taletness of 7 og/ce2, l l i I l l l l l 2171c 44.0 l l

.. _.. - _.. - ~ _ -. _ _. .__--___..-___m 6tl10 PLN-6200.01 JVeillon 1 T AE LE 4. 4 A19CEPRER10 O!8PERSION fat *!URS FOR IWEE tt!11 78'M

• 82A770N VtFT 013:AN05 EEC'IOR AVERAGE 1/Q (IN SE0/M )

(IN METERS) ELuiON - ANW.:AL f 24135 f 40225 56311 72405 SErroR 610 2413 4022 5631 7240 12067 i N 1.185 07 S.323-07 2.952-07 1.93E-07 1.393-07 5.i2E-08 1.912 c8 S.025 09 l1.88E-09 1.095 09 NFE 1.70E+07 7.17E-07 3.455-07 2.002-07 1.393-07 $.!42-08 1.7CE-04 4.77E-09 1.9 09 9.69E 10 FE 1.12E-07 1.75E-07 3.265-07 1.865-07 1.212-07 5.005-09 1.675 08 4.67E-09 1.855-09 9.93E 'O ENE 1.095-07 2.13E-07 2.671-07 1.93E-07 1.05R-07 4.31E-08 1.422-08 4.422-09 1.StE+09 8.64E 10 E 2.313-07 1.713-07 1.525 4) 1 4WE 07 1.065-07 4.633-08, 1.525 08 S.19E-09 2.445-09 1.50E-09 3.98E-08f1.SCE-08l5.925-09 2.92E-09 1.93E-09 RSE 3.50E-07 2.122-07 2.505 07 1.482-07 9.48t 08 RE 4.195-07 3.795-07 i 2.S35 07 1.$51-07 1.113-07 l4.825-os 1.812-04 6.848-09 3.30E-09 2.225-09 $st 2.90E 07 3.623-07 2.$$1-07 1.49E 07 1.115-07 $.021-08 1.98E-08 6.97E-09 2.945 09 1.70E-09 i 8 1 8?E-07 6.47E-08 2.165 07 1.30E-07 4.651-08 4.093-08 1.40E-08 4.96E-09 1.993 09 1.043 09 85W f.135-08 4.163-08 1.565-07 1.03E 07 6.812-04 2.745-08 9.745-09 3.0LE-09 1.50E-C9 4.232 10 rw $.765 04 1 143 07 1.7CE 07 1.053-07 6.93E.00 2.SLE-08 9.345-09 2.72E 09 1.333-09 8.332-10 Wsw 8.520-08 3.753-07 2.145-07 1.262 07 7.74E-08 3.08E-08 1.025-0$ 3.282 09 1.3EE 09 9.69E-10 W 1.15E-07 5.00E 07 2.84E-07 1.635-07 1.18E-07 5.23E-08 1.72E-08 $.065 09 1.983-09 1.192-09 WWW 1.415 07 6.283-07 3.303 07 2.193-01 1 485-07 l.643-08 1.951 08 6.323-09 2.164-09 1.34E-09 H-1.422-07 5.67E-07 3.173-07 1.932-07 1.303-07 5.67E-08 2.D6E 06 S.90E-09 2.105 09 1.4SE-09 NWh 1 00E-07 5.772 07 3.183-07 1.803-07 1.27E 07 $.203-08 1.773-08 4.82E-09 2.013-09 1.22E-09 DISTANCE

• 87ATION VENT

- 2) (IH METERS) EEASCW - ANr.'AL

• 850"IOR AVEPJu2E D/Q (IN M SECTOR 610 2413 4022

$631 7240 12067 24135 40225 $631$ 72405 N 2.$15-09 8.72E-10 4.848-10 2.98E-10 1.503-10 0.57E-11 2.515-11 4.98E-12 1.573-12 7.84E-13 WWE 3.893-09 1.985-09 9.$45 10 4.s95-10 3.385-10 1.102*10 2.893-11 6.063 12 2.10E-12 8.89E 13 FE 2.583-09 6.7D1-10 9.135-10 4.912 10 2.975-10 1.04E-10 2.073-11 6.0LE 12 1.995-12 9.235-13 ENE 2.153-09 $.855-10 5.545-10 3 365 10 2.08E-10 0.30E-11 2.322-11 5.4LE-12 1.632-12 7.64E-13 E 5,54E-09 1.231-09 6.17E-10 4.59E-10 3.638 10 1.34E-10 1.663-11 9.442-12 3.775-12 1.97E-12 ESE 9.173 09 2.058-09 1.515-D9 4 66E-10 5.1 E 10 1 823-10 5.775 11 1.72E-11 7.07E-12 4.07E-12 85 1.22E-08 2.885-09 1.842-09 1.022-09 6.85E-10 2.603-10 8.30E-11 2.34E-11 9.42E-12 5.5LE-12 SEE 7.$0E-09 1.625-09 1.083 09 S.0 F1 10 4.495-10 1.873-10 6.16E-11 1.613-11 5.67E 12 2.83E-12 8 3.86E-D9 6.53E-10 6.273-10 3.59E 10 2.32E-10 1.065 10 3.053-11 0.103 12 2.733 12 1.235-12 85W 1.135-09 2.945-10 4.195-10 2.533-10 1.56E*10 b.385-11 1.685-11 3.9LE-12 1.64E-12 7.843-13 8W 1 19E-09 3.845-10 4.968 10 2.80E 10 1.708-10 5.243 11 1.655-11 3.611 12 1 495-12 0.125-13 WSW 1.773-09 8.3 LE-10 6.493-10 3.50E-10 1.9ed-10 6.735-11 1.893 11 4.581-12 1.635 12 9.903-13 W 2.412 09 1.293-09

6. 8 LE - 10 3.65E 10 2.965-10 1.122-10 3.111 11 6.903-12 2.262-12 1.255-12 WWW 3.20E-09 1.393-09 7.73E-10 5.9tE-10 3.663 10 1.193 10 3.433-11 8.36E-12 2.392-12 1.295-12 NW 3.255*09 1.235-09 7.395 10 4.22E-10 2.775-10 1.14E-10 7.283-11 7.612-12 2.92E-12 1.36E-12 NWW 1 983-09 9.085-10 5.713-10 3.053-10 2.233-10 8.212-11 2.412-11 4.93E-12 1.723-12 9.033-13

%2A epam 1/1/78 TKama 12/31/86 USED IN CALCU1ATICsts 45.0 2171c w y r i m-. - y - -9 r, y. .- m..-.

- -. - - _ -. -. _ - - -. _ - _. - _ - - - ~ ~. - 6610 F1.N 4200.01 Pavlsion 1 TAELE 4.5 ADOSFEf3!C OISFEMtop FAmRS fth WPit MILE ISLAC

• GIO.fMD RELE.ASE CIATAN's 8st'iCR AVERACE 1/2 (IN SEC/M )

(1W MP3P.8) SEASCW ANN'.'AL ) l 12067 24135 40225 $6315 72405 8 tC":DR 0 2413 4022 $631 7240 3.45t-04f9.245-09 3.522-09 2.052-09 N 1.165 05 1.135-06 S.943 07 3.80E-07 2.J88 07 9.742-08 NWE 1.083-05 1.10E 06 $.668-07 3.412-07 2.388-07, 9.55t-08 3.11E-08 8.645-09 3.745 09 1.84t-09 rt 7.078-06 9.815-07 5.423-07 3.173-07 2.103 07 9.01E 08 3.105-08 8.875-09 3.54E-09 1.91t-09 ENE ?.14E-06 9.642-07 928-07 2.458-07 1.978-07 7.82E-06 2.641-Lt 8.388-09 3.045-09 1.665-09 E 8.491 06 1.095 06 S.485 0? 2.91E-07 1.87E-07 8.403-00 2.821-06 9.855-09 4.75t-09 2.872-09 Est 6.512 06 9.025-07 4.493-07 2.5 3-07 1.67307l7.20E05 2.778-08 1.123-08 S.S4E-09 . 68t-09 SE 6.702-06 9.068-07 4.537 07 2.815-07 2.031 01 0.943-08 3.332-08 1.281-08 6.193 09 4.183-09 EEE 7.268-06 9.255-07 4.91T 37

2. Bis 07 2.3LT 37 9.183-06 3.725-08 1.32E-08 S.623-09 3.262-09 s

8.70E-06 9.08E-07 3.99E-07 2.415-07 1.615 07 7.31E-08 2.573-04 9.23E-09 3.742-09 1.951-09 SW 6.053-06 7.01E-07 2.755-01 1.865-07 1.248-07 S.06E C8 1.828-06 S.718-09 2.87E-09 1.582-09 sw S.94E 06 S.718-C7 2.863 07 1.81E-07 1.225-07 1 4.502-08 1.72E-00 S.12E-09 2.53E-09 1.59E*09 W8W 6.0C5-06 7.025 07 3.603-07 2.158 07 1.345-07 5.$0E-04 1,87E-08 6.112-09 2.62E-09 1.838-09 W 1.025 05 1.07E-06 S.303-0V 3.025*07 2.055-01

9. 31W - 04 3.1511 06 9.482 09 3.141-09 2.38E-09 WW 1.163 05 1.135-06 S.985-01 3.673-07 2.53t-07 1.00E-07 3.563 08 1.185-08 4.073-09 2.54E-09 WW 1.112 0S 1.062-06 S.702-07 3.53E 07 2.408-07 1.025-07 3.82t-08 1.11b ee 5.14t-09 2.78E-09 KrW 1.08E-01 1.048-06 5.72E-07 3.27E 01 2.22E 07 9.063 08 3.20E-08 0.893-09 3.75E-09 2.295-09

• CIOUND RELEASE DISTANCE

~2 ) (15 METERS) SEASCE - ANNUAL SECIUR AVERACE 0/Q (tN M EECTOR 610 2413 4022 5631 7240 12067 24135 4022$ 56315 7240$ 3 2.305 08 1.085-09 8.933-10 4.82E+10 2.705-10 8.963-11 2.535-11 4.98E-12 1.57E-12 7.848-13 WNE 2.665-08 2.255-09 1.065-09 5.413 10 3.385-10 1.103-10 2.898-11 6.068-12 2.10E-12 8.893-13 NE 1.738-00 2.00E-09 1.013-09 5.043-10 2.948-10 1.047-10 2.885-11 6.012-12 1.99E-12 9.2iE-13 ENE 1.645-08 1.85E-09 8.655-10 4.285-10 2.653 10 0.57E-11 2.338-11 5.41E-12 1.63E-12 7.64E-13 3 2.883-06 2,995-09 1.393 09 6.345-10 3.675-10 1.353-10 3.682 11 5.423-12 3.77E-12 1.9?E. ESE 3.595 08 3.803-09 1.778 09 4.795 10 5.158-10 1.833-10 5.788-11 1.71E-11 7.062-12 4.06E-12 SE 4.125-08 4.$5E 09 2.133-09 1.153-09 7.508-10 2.723 10 9.313-11 2.34E-11 9.425-12 5.507.-12 SSE 3.12E-08 1.23E 09 1.595 09 8.005 10 5.205-10 1.482-10 6.18E-11 1.618-11 S.66E-12 2.83E-12 8 2.655-06 2.21E 09 9.073-10 4.755-10 2.868-10 1.07E*10 3.068 11 0.105-12 2.738 12 1.23E-12 85W 1 455-08 1.308 09 4.80E-10 2.82E-10 1.703-10 5.715 11 1.695-11 3.91E 12 1.64E 12 7.84E-13 sk 1.42E-08 1.10E-09 S.155 10 2.823 10 1.715-10 5.243-11 1.635-11 3.623-12 1.49E-12 8.123-13 vsW 2.015 08 1.41E 00 6.828-10 3.S4E-10 2.005-10 6.76E-11 1.891-11 4.585-12 1.63E 12 9.90E-13 W 2.555-00 2.163-09 1.005-09 4.913-10 3.015 10 1.12E-10 3.112-11 6.90E 12 2.27E-12 1.25E-12 WWW 2.883-00 2.3CE-09 1.135-09 5.933-10 3.673-10 1.195-10 3.433-11 8.36E-12 2.39E-12 1.29E 12 WW 2.783-00 2.158-09 1.063-09 5.583 10 3.415-10 1.193-10 3.578-11 7.613-12 2.923-12 1.36E-12 NW 2 173-08 1.758-09 8.755-10 4.245-10 2.573-10 8.553 11 2.423-11 4.93E-12 1.72E-12 9.033-13 DATA FIm 1/1/78 UDOUGH 12/31/06 UEED IN CALCULATI:58 2171c 46.0

Nuclear TxI Radio 1o,1ca1 Controis Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 O.folte Dose Calculation Manual (ODCM) TABLE 4.6 D_OSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVE PARTICULATE IN GASEOUS EFFLUENTS

• CRITICAL ORGAN CRITICAL ORGAN NUCLIDE ORGAN FACTOR P1'
• NUCLIDE ORGAN FACTOR Pi*'

H-3** TOTAL BODY 4.62E-07 6.5E+02 Ru-105 GI-LLI 3.46E-05 4.8E+04 C-14 BONE 1.89E-05 2.6E+04 Ru-106 LUNG 8.26E-03 1.2E+07 Na-24 TOTAL BODY 7.54E-06 1.1E+04 Ag-110M LUNG 2.62E-03 3.7E+06 Cr-51 LUNG 9.17E-06 1.3E+04 Sb-125 LUNG 1.17E-03 1.6E+06 Mn-54 LUNG 7.14E-04 1.0E+06 Te-125M LUNG 3.19E-04 4.5E+05 ?e-55 '.. NG 6.21E-05 8.7E+04 Te-132 LUNG 2.43E-04 3.4E+05 Fe-59 LUNG 7.25E-04 1.0E+06 I-131 THfROID 1.06E-02 1,5E+07 Co-58 LUNG 5.55E-04 7.8E+05 I-132 THYROID 1.21E-04 1.7E+05 Co-60 LUNG 3.22E-03 4.5E+06 I-133 THYROID 2.54E-03 3.6E+06 N1-63 BONE 2.42E-Ct 3.4E+05 1-134 THYROID 3.18E-05 4.5E+04 Zn-65 LUNG 4.62E-04 6.5E+05 I-135 THYROID 4.97E-04 7.0E+05 Sr-89 LUVG 1.453-03 2.0E+06 Cs-134 LIVER 5.02E-04 7.0E+05 Sr-90 BONE 2.92E-02 4.1E+07 Co-136 LIVER 9.61E-05 1.3E+05 Y-90 LUNG 1.92E-04 2.7E+05 Cs-137 LIVER 4.37E-04 6.1E+05 Er-95 LUNG 1.2SE-03 1.dE+06 Ba-140 LUNC 1.14E-03 1.6E+06 tr GI-LLI 1.00E-04 1.$E+05 La-140 LUNG 1.20E-04 1.7E+05 Nb-95 LUNG 3.42E-04 4.CE+05 Ce-141 LUNG 3.6?C-04 5.2E+C5 Mo-99 LUNG 9.63E-05 1.3E+05 Co-144 LUNG 7.03E-03 9.8E+06 Tc-99H GI-LLI 1.45E-06 2. 0 E + 0." Pr-144 GI-LLI 3.06E-06 4.3E+03 Ru-103 LUNG 3.94E-04 5.5E+05 l The listed dose parameters are fer radionuclides, other than noble gases that may be detected in gaseous effluents. Pi factore include all nonatmospheric pathway transport parameters, the receptor's usage of pathway media, and are based on the most restrictive age group (infant) critical organ, per THI-1 Tech. Spec. bection 3.22.2.1. Additional doce parameters for nuclides not included in this Table may be calculated using the mnthodology described in NUREG-0133. Tritium dose factors include an increase of 50% to account for the additional amount of this nuclide absorbed through the skin. 3 mram/ year per pC1/m. l 47.0 2171c I

- __ _ ~ _ - N NE THI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title T avision No. offsite Dose calculation Manual (ODCM) FIGURE 4.1 THI-1 GASEOUS EFFLUENT PATHWAYS C'"' t ta t t.aa ,tutw nr unna }' Y / ..o.,....

> = a 't

.. ~. . t,,,,,,, i nest's I k g; ;)_. g m.n m. t... =.n I[,ggggg,,, f re coe tre se too t's bh mm 7 ; -_ t__ EM

• c

? .m.s. m.. -. = c.. wentis riesp P c,r.u. e.en bfui 1 i "aiC: "id" ' a' , = =. 4 P r-

• 1 W EUS b.b0 Lt.

i 48.0 21 1# ~

i Nuclear exz.a,1 1,1 a1 cont, 1s Departrnental Procedure 6610-PLN-4200.01 Revision No. Title 1 Of f site Dose calculation Manual (ODCSI) TIGURE 4.2 TMI-1 AUXILIARY AND TUEL HANDLING BUILDINGS EFFLUENT PATHWAYS pg vtv lum u n 3-48HG m8 .,n a o a P A C ea rc.t g W5 nN'"ab RM-A4 W RM-Al4 K HD D wa a n ? ESTTUEL P A C 3 AUXILARY $ HARING ,3 BUILDING RM-A7 BuitDIE mamm /3 A n A FUEL HANDLING $ $t

• t 8'

BUILDING a i c g v v v AUXILIARY AND REL HANDLING C' aT* j BUILDINGS EXHAUST RADIATION G1 TORS AND SARING STAil0NS o oem 49.0 2171c

Nuclear ml R.eio1oyio.1 contr 1. Departmental Procedure 6610-PLN-4200.01 Revision No. Title Offeite Dose Calculation Manual (ODN) 1 FIGURE 4.3 TMI-1 REACTOR BUILDING EFFLUENT PATINAY PJG 170 W FEET l REACICR SUILDING PURGE EXHAUSI "G RADIAT10H MUNITCRS AND " '9 * " '8 SAMPLING STATICNS ws O rm m !TAIDI l Pdi/ REACTOR N BUILDING- ) A m 3 rpm g

1..

n v w:n sus i 01 ME flW gg U13 LUM LWtX MM FMIDLATUTRIllfs 9sPMIDLhli A 4350,(g[ C OWCW. l l 50.0 2171c

,_m-... 4 Nuclear TM1 4,1,1,1. 1 ceot.o1. Departmental Procedure 6610-PIR-4200. 01 Revision No. Title 1 offsite Dose Calcu1ation Manual (0D08) FIGURE 4.4 TMI-1 CONDENSER OFFGAS EFFLUENT PATHWAY CONDENSER OFF GAS STACK CONDENSER OFF GAS g 115 mm EXHAUST FEET RADIATION MONITORS AND SAMPLING STATIONS l#"Ji" ~} gp MAIN w g ~ ~ ' ' CONDENSER =,,. 51.0 2171C ~. -.

. ~ YUClear rni a.eioioste.1 contro1. Departmental Procedure 6610-PLN-4200.01 Revision No. Titie Of f site Dose calculation Manual (ODOI) 1 FIGURE 4.5 THI-2 GASEOUS EFFLUENT PATHWAYS E0>I va (w5

== 5 I e i N Q E g N< e 5 5 2 w d d IO 1 a1 M E $5 ke 3 ke a C0 IN SS 2 Um IN o w = = = r e z W Og e kO g E S2 a Q m$" $ N' d Wg Z zol e i a eo "sw Q tx 8 g g aG s z y k50 g g 3 8" Oa u. aa a T-eALA o.

== a. =! 9; Ag o LLL' La ZZZI 2 2 I l HO s a D E 5 g I X 1 l N i i t sa a~ y t l in i &a a* 2 2" Z l I 3 Ea o a <a ss: "e -83 Ad $$ d = =* <5 za 52.0 2171c I

ENuclear Tx1,adio1 gica1 Contro1s Departmental Procedure 6610-PLN-42OO.Ol Revision No. Title 1 Of fsite Dose Calculation Manual (ODOE) 5.0. CASSOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaoeous Effluents - 10 CY' 'O Limits (Instantaneous Release Limits) 5.1.1 Noble Gases For noble gases, the. following equations apply for total body and skin dose rate at the unrestricted area boundary 5.1.1.1 Total Body E (K ) x (Dv) x (Q ) (eq 5.1.1.1) Dose Rateg=I g 3 where: Dose Ratea= instantanaous total body dose rate limit, at the site boundary, in mrem /yr. Kj= total body dose factor due to gamma emissions for each 3 identified noble gas radionuclide, in mrem /yr per pC1/m from Table 4.3. Dv = average annual dispersion value X/Q at the site boundary for 3 worst case sector,-in sec/m. Values are obtained from Table 4.4 for releases-from station vent; and Tablo 4.5 for all others (Condenser Off Gas, EST THB, and ground releases). 3 at sector Maximum values presently in use are 4.19E-7 sec/m 8 for all other SE for station vent, and 1.16E-5 sec/m releases, at sectors N and WNW. Og =. Release rate of radionuclide, i, in pCi/sec. Calculated using the concentration of noble gas radionuclide, i, in pC1/cc, times the release pathway flow rate, in ec/second. l l l l l l 53.0 2171c L l'

m___.__ TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision a. Title 1 offsite Does calculation Manual (00CM) 5.1.1.2 Skin 1.1 M ) X (Dv) 1 (Q ) (eq 5.1.1.2) 'te,* E (L3+ 3 3 L where instantaneous mrom/ year skin dose rate limit, at the Dose Paton= site boundary, in mrom/yr. skin dose factor due to beta emissions for each Lg= 3 identified noble gas radionuclide, in mrom/yr per pci/m from Table 4.3. air dose factor due to gamma emissions for each H = 3 3 identified noble gas radionuclide, in mrad /yr per pci/m from Table 4.3. 1.1 = mrom skin dose per mrad air dose. Converts air dose to skin dese. Og = release rate of radionuclide, 1, in pci/sec, calculated using the concentration of noble gao radionuclide, 1, times the release pathway flow rate, in ec/second. Dv = average annual dispersion value X/Q at the site boundary for worst case sector, in sec/m. Values are obtained 3 from Table 4.4 for releases from station vent; and Table 4.5 for all others (Condenpar Off Gas, EST FHB, and ground releases). Maximum values presently in use are 4.19E-7 sec/m3 at sector SE for station vent, and 1.16E-5 sec/m3 for all other releases, at sectors N and WNW. 54.0 2171c

ENuclear xxx aadi 1,1ca1 Contro1. Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Dose Calculation Manual (ODCM) 5.1.2 Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form, with Half-Lives Greater than 8 Days For I-131, I-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, the following equation 1 applies: l Dose Rate, = I (P ) (Dv) (Q ) (eg 5.1.2) g g 1 i where mrem / year organ dose rate. Dose Rate a gy P - dose parameter for I-131, I-133, Tritium and g Radionuclides in Particulate Form, with half-lives greater than 8 days, for the inhalation pathway, in mrom/yr per pCL/m, from Table 4.6. The dose factors are 3 based on the critical individual organ and most restrictive age group (infant). Dv = the annual average atmospheric dispersion parameter, for the worst-case sector, for estimating the dose to the critical receptor; X/Q for the inhalation pathway, in sec/m. Dispersion factors may be read or interpolated 3 from Table 4.4 for releases frem the station vent and Table 4.5 for all other releases. saximum values of X/Q 3 presently used are 4.19E-7 sec/m for station vent, at 3 for all other releases, at sector SE, and 1.16E-5 sec/m sectors N and WNW. release rate of each radionuclide, i, in pC1/sec. Og = Calculated using the concentration of each radionuclide, 1, times the release pathway flow rate, in ec/second. i l 55.0 2171c l

F U1 Nuclear Tx: aadio1ogica1 contro1s De?artmental Procedure 6610-PLN-4200.01 Revision flo. Title 1 Offsite Dose Calculation Manual (ODCM) 5.2 caseous Effluents - 10 CTR 50 Appendix I j 5.2.1 Noble Gases The air dose in an unrestricted area due to noble gases released in gaseous effluents from the site is determined using the following expressions: Dose r = (3.17E-8) x E (M ) x (Dv) x (Qi) (eq 5.2.1) 3 i and Sose n = (3.17E-8) x E (N ) x (Dv) x (Qi) (eq 5.2.2) g I where: mrad gamma air dose due to gamma emissioni from noble Dose r = gas radionuclides. Dese D = mrad beta air dose due to beta emissions from noble gas radionuclides. air dose factor due to gamma emissions for each M = 3 identified noble gas radionuclido, in mrad /yr per 3 pCL/m, from Table 4.3. air dose factor due to beta emissions for each N = g identified noble gas radionuclide, in mrad /yr per 3 pci/m, from Table 4.3. Dv = the maximum annual average atmospheric dispersion factor, Q/X, for the worst-case sector, for any area at 3 or beyond the unrestricted area boundary, in sec/m. Values may be read or interpolated from Table 4.4 for releases from the stattor. vent and Table 4.5 for all other releases. saximum values of X/Q presently used are 4.19E-7 sec/m3 for station vent at sector SE, and 1.16E-5 sec/m3 for all other releases at sectors N or WNW. release of noble gas radionuclide, i, in pC1, over the Q = t specified time period, (pci/second a seconds). 3.17E-8 = inverse of the number of seconds in a year. _ _ _ _. = _ _ -- =_=__..__.._..._.. NOTE: If the methodc.sgy in this section is used in determining dose to an individual, rather than eir dose due to noble gases, substitute Ki, from Table 4.3, for Mi, and (Li + 1.1 M1) for Ni. 56.0 2171c

FGNuclear TxI Radio 1ogica1 contto1s Deoartment al Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Dose Calculation Manual (ODCM) Mp 5.2.2 Iodine-131, Iodine-133. Tritium and Madionuclides in Particulate e., Fotw, with Hnif-Lives Greater than 8 Days The dose to an individual from I-131, I-133, Tritium and ([d. Radionuclides in Particulate form with half-lives greater than r' - 5 8 days in gaseous effluer e released t.om the site to an k NI unrestricteu area is dettoutned by solving the following [ expression: Jose, = (3.17E-8) x E (R ) (Dv) (Q ) (eq 5.2.2) g i i s ~N where Dose, = dose to all real pathways, p, to organ, o, of an individual in age group, a, f rom I-131, I-133, Tritium and Radionuclides in Particulate Form, with half-lives 4 greater than 8 days, in mrtm, during any desired time period. the dose factor for each identified radionuclide, i, Rg= pathway, p, aga group, a, and organ, o, in mrem /yr per pci/m for the inhalation pathway and m2 - mrem /yr per 3 pCi/rx for m'.er pathways, from Tables 5.2 to 5.7. NOTE: Since there is minimal or no elemental iodine relear from the condenser off-gas air ejector (see NUREG-0017) alA dine values for all pathways, except the inhalation pathwa gare considered to be zero when performing dose calculatis,: for releases from the condenser off-gas air e$ector. Only calculate tre dose due to the inhalation pathway for condenser off-gas air ejecte-iodine *. =._-. - --.~---------. _ 3 NOTE: Tritiua, H-3, dcae farctor is mrem / year per pC1/m for all pathways.

---

....=___

Dv = the annual .erage atmospheric dispersien pirameter, for the worst,ese sesctor, for estimating the dose to an 3 indiv!. dual at the critical location; I/Q, in sec/m, for the inhalation pathway, and D/Q, in m-2, for other 3 for station pathways. Maximum values of X/Q in sec/m vent and all other releases are 4.19E-7 and 1.16E-5 for sectors FE and N, WNtr' respectively. Maximum values of D/Q in m-2 for station vent and all other releases are 1.225-8 and 4.12E-B for sector SE. 57.0 2171c

N NU TMI Radiological Controls Deptrtmental Procedure 6610-PLN-4200.01 Revisica No. Title 1 Cf fsite Dose calcula' 'n Manual (ODCN) In the case of H-3 only X/Q's are used for all pathways. Dv(H-3) = Dispersion factors may be read or interpolated from Table 4.4 for station vent releases and Table 4.5 for all other releases. release of I-131, I-133, Tritium and Radionuclides, 1, Q = t in Particulate Form with half-lives greater than 8 da s, s in pCL, cumulative over the specified time period (uCi/second

• seconds).

3.17E-8 = inverse of the number of seconds in a year. l I 58.0 2171c t

Number E U1 Nuclear TMI Radiotegica1 contro1s 6610-PLN-4200.01 I Departmental Procedure _ Revision No. ~ Title 1 Offsite f.cse Calculation Manual (ODOf) Gascous Radioactive System Dose Calculations Once per Month 5.3 Section 3.22.2.4 requires that appropriate subsystem of the System shall be used to reduce the radioactive TMI-l Tech. Spec. Gaseous Radwaste Treatment When the monthly materials in gaseous waste prior to their discha; .9. releasee from the site would projected doses due to the gaseous effluent exceed: tion; or 0.2 mrad to air from gamma ras 0.4 mrad to air trom beta radiation; or 0.3 mrem to any organ. The following calculational stethod is provided for perf orming this dose projection. least once a calancar month the gamma air dese, beta air dose and theAn estimated projec maximum organ dose for the month will be integrated. At h gamma Air dose, beta air dose, ar( the maximum organ dose for the next mont fcr the will be determined based on plant operation and the integrated doseIf th , previous month. appropriate portions of the Gaseous Waste Processing System listed above, shall be used to reduce radioactivity levels prior to release. p ternative Dose Calculational Methodologies for Gaseous Effluents 3.4 As an alternative to the methods described above, the models in/or based 1) may be u upon, thor a presented in Regulatory Guide 1.109 (Rev. Default parameter values from Regu a comprehensive dose assessment.and/or actual site specific data can be used where Dispersion parameter values for such analyses may be drawn from 1) Guide 1.109 (Rev. Table. 4.4 and 4.5 or may be computed from site meteorological data for the applicable. in specified time period using acceptable models such as those presented Regulatory Guice 1.111 (Rev. 1), i 2171c 59.0 i ~

,a. ~ - TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Dose Calculation Manual (OOCM) TABLE 5.2.1 PATHWAY DOSE FACTORS, Ri AGE GROUP. INFANT PATHWAY: INHALATION 3 OR'AN DOSE FACTORS; mrem / year per FCi/m - = - - NUCLIDZ BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI -. - =_ = ----== - - = - H-3 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 C-14 2.65E+04 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 CR-51 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 - =-.....--. .---------.---------...__==___ 'MN-54 0.00E+00 2.53E+04 4.98E+03 0.00E+00 4.98E+03 1.00E+06 7.06E+03 FE 1.97E+04 1.17E+04 3.33E+03 0.00E+00 0.00E+00 8.69E+04 1.09E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 =. C0-58 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 -7.77E+05 1.11E+04 CO-60 0.00E+00-8.02E+03 1.18E+04 0.00E400 0.00E+00 4.51E+06 3.19E+04 NI-63 3.39E+05 2.04E+04 1.16E+04 0.00E+00 0.00E+00 2.09E+05 2.42E+03 =.... -- ZN-65 1.93E+04-6.26E+04 3.11E+04 0.00E+00 3.25E+04 6.47E+05 5.14E+04 RB-86 0.00E+00 1.90E+05 8.82E+04 0.00E+00 0.00Z+00 0.00E+00 3.04E+03 SR 3.98E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 SR-90 4.09E+07 0.00E+00-2.53E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 Y-91 5.88E+05 0.00E+00 1.57E+04 0.00E+00 0.00E+00 2.45E+06 7.03E+04 ZR-95 1.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 NR-95 1.57E+04 6.43E+03 3.78E+03 0.00E+00 4.72E+03 4.79E+05 1.27E+04 RU-103 2.02E+03 0.00E+00 6.79E+02 0.00E+00 4.24E+03 5.52E+05 1.61E+04 RU-106-8.68E+04 0.00E+00 1.09E+04 0.00E+00 1.07E+05 1.16E+07 1.64E+05 AG-110M-9.98E+03 1.22E+03 5.00E+03 0.00E+00 1.09E+04 3.67E+06 3.30E+04 TE-125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 0.00E+00 4.47E+05 1.29E+04 TE-127M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 -2.73E404 TE-129M 2~41"+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 I-131 2 't a04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.00E+00 1.06E+03 I-133 +04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.00E+00 1.16E+03 CS-134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 -1.90E+05 7.97E+04 1.33E+03 CS-136 4.83E+04-1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18E+04 1.43E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+03 7.13E+04 1.33E+03 BA-140 5.60E+04 5.60E+01 2.90E+C3 0.00E+00 1.34E+01 1.60E+06 3.84E+04 CE-141 2.77E+04 1.67E+04 1.99E+03 0.00E+00 6.25E+03 5.17E+05 2.16E+04 CE-144 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.38E+05 9.04E+06 1.48E+05 ~PR-143 1.40E+04 ~ 5.24E+03 6.99E+02 0.00E+00 1.97E+03 4.33E+05 3.72E+04 ND-147 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E+03-3.22E+05 3.12E+04-d 60.0 2171c t

.-~, MUClear TMI Raatologt,.a1 contro1. Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offelte Dose Calculation Manual (ODCM) i TABLE 5.2.2 PATHWAY DOSE FATTORS, Ri AGE GROUP CHILD PATHWAY: INHALATION --_:_-, - - = - - - = 3 ORGAN DOSE FACTORS; mrem / year per pCi/m NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG OI-LLI' H-3 0.00E+00-1.12E+0 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 C-14 3.59E+04 6.73E+03 6.73E+03 '.73E+03 6.73E+03 6.73E+03 6.73E+03 CR-51 0.00E+00 0.00E+00 1.54E+02 .55E+01 2.43E+01 1.70E+04 1.08E+03 -MN-54 .0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 FE-55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 FE-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00-0.00E+00 1.27E+06 7.07E+04 Co-58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 .00-60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 NI-631 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 EN-65 4.26E+04. 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04~ =RB-86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 SR-89 5 99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 = -SR-90 '1.01E+08 0.00F+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 Y-91 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 IR-95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 NB-95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 3.62E+03 6.14E+03 3.70E+04 RU-103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 RU-106 '1.36E+05 0.00E+00 1.69E+04 .0.00E+00 1.84E+05 1.43E+07 4.29E+05 AG-110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1 00E+05 -TE-125M 6.73E+03-2.J3E+03 .9.14E+02 1.92E+03 0.00E+00 4.77E+05 3.38E+04 .TE-127tt 2.49E+04 8.55Ev03 3.02E+03 6.07E+03 6.36E+04 2.48E+06 7.14F+04 TE-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 I-133 1.66E+04 2.03E+04 7.70E+03 3.33E+06 2.3SE+04 0.00E+00 5.48E+03 CS-134 '6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 CS-136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04-1.45E+04 4.18E+03 .CS-137 9.07E+05 8.25E+05. '1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 BA-140 -7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01-1.74E+06 1.02E+05 .CE-141- -3.92F+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 l CZ-144. 6.77E*06 2.12E+06 3.61E+0$ 0.00E+00 1.17E+06 1.20E+07 3.89E+05 PR-143 1.85E+04' 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 ND-147 -1.08E+04 -8.73E+03 6.81E+02 0.00E+00 4.81E+03 3.28E+05 8.21E+04 _ =--- 1 61.0 2171c l e c ~^ ~ ~ ~ - - - -

. - ~ . -, ~. N TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No. Title Of fsite Dose Ca?culation Manual (ODCN) l 1 i e TABLE 5.2.3 PATHWAY DOSE FACTORS, Ri AGE GROUPS TEEN PATHWAY: INHALATION .....-------.......--..=-- _ =... ----..--------_=- 3 ORGAN DOSE FACTORS; mrom/ year pcr pC1/m VUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 C-14 2.60E+04 4.87E+03 4.87E+03 4.67E+03 4.87E+03-4.87E+03 4.87E+03 CR-51 0.00E+00 0.00E+00 1.35E+02 7.50E401 3.07E+01 2.10E+04 3.00E+03 KN-54 0.00E+00 5.11E+04 8.40E,03 0.00E+00 1.27E+04 1.98E+06 6.68E+04 FE-55. 3.34E+04 2.38E+04 5.54E+03 0.00E+00 0.OOE+00 1.24E+05 6.39E+03 FE-59 1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.78E+05

---

..... 58 0.00F+00 2.07E+03 2.78E+03-0.00E+00 0.00E+00 1.34E+06 9.52E+04 co-60 0.00E+00 1.51E+04 1.98E+04 0.00E+00 0.00E+00 8.72E+06 2.59E+05 NI-63 5.80E+05 4.34E+04 1.98E+04 0.00E+00 0.00E+00 3.07E+05 1.42E+04 ZN-65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 RB-86 0.00E+00

.1.90E+05 8.40E+04 0.00E+00 0.00E+00 0.00E+00 1.77E+04 Sn-89 4.34E+05 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E+05 SR-90 1.0aE+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 Y-91 6.61E+05 0.00E+00 1.77E+04 0.00E+"O 0.00E+00 2.94E+06 4.09E+35 ER-95 -1.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74E+04' 2,59E+06 1.49E+05 NB-95 1.86E+04 1.03E+04 5.66E+03 0.00E+00 1.00E+04 7.51E+05 9.68E+04 RU-103 2.10E+03 0.00E+00 8.95E+02 0.00E+00 7.43E+03 7.83E+05 1.09E+05 RU-106 9.84E+04 0.00E+00 1.24E+04 0.00E+00 1.90E+05 1.61E+07 9.60E+05 AG-110M 1.38E+04-1.31E+04 7.99E+03-0.00E+00 2.50E+04 6.75E+06 2.73E+05 - TE-125M_ 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.003+00 5.36E+05 7.50E+04 TE-127M 1.80E+04 8.16E+03 2.18E+03 4.3BE+03. 6.54E+04 1.66E+06 1.59E+05 TE-129N 1.39E+04 6.58E+03 2.2SE+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 I-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.4LE+04 0.00E+00 6.49E+03 I-133 1.22E+04 2.05E+04 6.22E+03 2.92F+06 3.S9E+04 0.00E+00 1.03E+04 CS-134 5.02E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 9.76E+03 CS-136-5.15E+04-1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 1.09E+04

CS-137 6.70E+05= ~8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 BA-140 5.47E+04

'6.70E+01 3.52E+03 0.00E+00 2.28E+01 '2.b3E+06 2.29E+05 CE-141 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 1.26E+05 CE-144 4.89E+06' 2.02E+06 2.62E+0h 0.00E+00 1.21E+06 1.34E+07 8.64E405 PR-143 1.34E+04 5.31E+03 6.62E+02 0.00E+00 3.09E+03 4.83E+05 2.14E+05 ND-147 7.86E+03 8.56E+03 5.13E+02 0.00E+00 5.02E+03 3.72E+05 1.82E+05 62.0 2171c

N TMI Radiological Controle Derartmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Dose Calculation Manual (ODCH) TABLE 5.2.4 PATHWAY DOSE FACTORS, Ri AGE GROUP: ADULT PATHWAY: INHALATION =--_

== _ 3 ORGAN DOSE TACTORS; mrom/ year per pC1/m

---

------------------ =

==------ NUCLIDE

---

==--

BONE LIVER T.DODY THYROID KIDNEY LUNG GI-LLI _ - - = =. H-3 0.00E+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 C-14 1.82E+04 3.41E+03 3. '. '. E + 0 3 3.41E+03 3.41E+03 3.41E+03 3.41E+03 CR-51 0.00E+00 0.00E+00 1.0c9+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03

==.------.---- =---=--_.:=-- MN-54 0.00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06 7.74E+04 FE-55 2.46E+04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.21E+04 6.03E+03 TE-59 1.18E+04 2.78E404 1.06E+04 0.00E+00 0.00E+00 1.02E+06 1.88Et05 $kbE03 2.b7E+03 b.bOE+00 0.0bE+00 92hE05 1 06E 05 CO 8 0.00E+00 Co-60 0.00E+00 1.15E+04 1.48E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 NI-63 4.32E+C3 3.14E+04 1.45E+04 0.00E+00 0.00E+00 1.78E+0b i.34E+04 = = _ _ ZN-65 3.24E+04 1.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.34E+04 RB-86 0.00E+00 1.35E+05 5.90E+04 0.00E+00 0.LOE+00 0.00E+0C 1.66E+04 SR-89 3.04E+05 0.00E+00 8.72E+03 0.00F+00 0.00E+00 1.40E+06 3.50E+05 =~-. - =---._ ...= -.==_. SR-90 9.92E+07 0.00E+00 6.10E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05 Y-91 4.62E+05 0.00E+00 1.24E+04 0.00E+00 0.00E+00 1.70E+06 3.85E+05 ZR-95 1,07E+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50E+05 ---.=- = NB-95 1.41E+04 7.82E+03 4.21E+03 0.OOE+00 7.74E+03 5.05E+05 1.04E+05 RU-103 1.53E+03 0.00E+00 6.58E+02 0.00E+00 5.83E+03 5.05E+05 1.10E+05 RU-106 6.91E+04 0.00E+00 8.72E+03 0.00E+00 1.34E+05 9.36E+06 9.12E+05 AG-110M 1.08E+04 1.00E+04 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 TE-125M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 TE-127M 1.26E+S4 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 TE-129M 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66Ev04 1.16E+06 3.83E+05 I-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.00E+00 6.28E+03 I-133 8.64E+03 1.A8E+04 4.52E+C3 2.15E+06 2.58E+04 0.00E+00 8.88E+03 CS-134 3.73E+05 8.48E+05 7.28E+05 0.00E+0C 2.87E+05 9.76E+04 1.04Ev04 CS-136 3.90E+04 1.46E+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04 CS-137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 1.bhE+06 2.18E+0b BA-140 3.90E+04 4.9bE+01 2.57E+b3 0.00E+00 1 67E 01 CE-141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.26E+03 3.62E+05 1.20E+05 CE-144 3.43E+06 1.43E+06 1.84E+05 0.00E+0C 8.48E+05 7.78E+06 8.16E+05 PR-143 9.36E+03 3.75E+03 4.64E+02 0.00E+0b 2 16E+03 2.81E+05 2.COE+05 ND-147 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05 =_ _=._ 63.0 2171c I

~.., _. ) i J I N TMI Radiological Controls-Departmental Procedure -6610-PLN-4TJ0.01 Revision No. Title 1 Offsite Dose Calculation Manual (OOCM) TABLE 5.3.1 PATHWAY DOSE FACTORS, Ri ' AGE GROUP: ALL PATHWAY: GROUND PLANE l ORGAN DOSE FACTORS

• l NUCLIDE l

T. BODY CEIN l lH-3 C.00E+00 0.00E+00l 0.00E+00l C-14 (.00E+00 lCR-51 4.65E+06 5.50E+06 . l MN. 4 1.39E+09 1.62E+09l 0.00E+00 0.00E+00 l7E-55 FE 2.73E+08 '3.21E+08l l CO-58 '3.79E+08 4.44E+08l Co-60~ 2.15E+10 2.53E+10 lNI-63 0.00E+00 0.00E+00l j'ZN-65 7.47E+08 '8.59EtOSl RB-86 8.97E+06 1.03E+07 lSR-89 2.16E+04 2.51E+04l l.SR-90 0.00E+00 0.00E+00l Y-91 1.07E+06 1.21E+06 lZR-95' 2.45E+08 2.84E+08l lNB-95 1.37E+08 1.61E+08l -1.26E+08l RU-103 1.08E+08 lRU-106 4.23E+08 5.06E+08 l~AG-110M 3.44'I+09 4.01E+09l -2.13E+06l 1.55E+06 lTE-125M. -1.08E+05 TE-127M 9.1*'E+04 lTE-129M 1.98E+07 2.31E+07 l 1.72E+07 2.09E+07., lI-131 I-133 2.45E+06 2.98E+06 g l_CS-134 6.86E+09 -8.00E+09l 1.51E+08 1.71E+08 1lCS-136 CS-137 1.03E+10 1.20E+10 l lEA-140 2.06E+0* 2.36E+07 l E 1.54E+07l CE-141 1.37E+07 lCE-144 6.96E+07 8.05E+07 4 l-PR-143 0.00E+00 0.00E+00l ND-147 8.39E+06 1.01E+07 1 a m - mram/ year per pCi/sec. 2 l t 64.0 2171c

N I k4 Nuclear TM1 Ra 1 1 91ca1 Cootro1e DJpartmental Procedure 6610-PLN-4200.01 i Revt.aien No. T'tle I Offeite Dose Calculation Marua1 (ODCM) l 1 TABLE 5.4.1 PATHWAY DOSE FACTORS, Ri AGE GROUP: INFANT PATHWAY: GRASE-COW-MILK ORGAN DOSE FACTORS; m2 - mrem / year per pCi/sec = =-----

---

=

= ---- -- = -- -----------===- NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.002+00 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.3bE+03 2.38E+03 C-14 2.34E+09 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 .00E+08 CR-51 0.00E+00 0.00E+00 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 =-=---------_---_----_-----__- =_---

---

=

MN-54 0.00E+00 3.91E+07 8.85E+06 0.00E+00 8.65E+06 0.00E+00 1.43E+07 FE-55 1.35E+08 8.74E+07 2.34E+07 0.00E+00 0.00E+00 4.27E+07 1.11E+07 FE-%9 2.25E+tJi 3.93E+08 1.55E+08 0.00E+00 0.00E+00 1.16E+08 1.88E+08 ._==_ -- .------.00E+00 2.43E+07 6.06E+07 0.00E+00 0.00E+00 0.00E+00 6.05E+07 0 Cr CL

1. 3 0.00E+00 8.d3E+07 2.08E+08 0.00E+00 0.00E+00 0.00E+00 2.10E+08 N1 13 3.50E+10 2.16E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 1.08E+08

=.-- -=__ n_ ZN-65 5.56E+09 1.91E+10 8.79E+09 0.00E+00 9.24E+09 0.00E+00 1.61E+10 RB-86 0.00E+00 2.23E+10 1.10E+10 0.00E+00 0.00E+00 0.00E+00 5.70E+08 SR-89 1 26E+10 0.00E+00 3.62E+08 0.00E+00 0.00E+00 0.00E+00 2.59E+08 SR-90 1.22E+11 000E+0b 3.10E+10 0.00E+00 0.00E+00 0.bbE+00 1.52E 09 Y-91 7.34E+04 0.00E+00 1.95E+03 0.00E+00 0.00E+00 0.00E+00 5.26E+06 ZR-95 6.81E+03 1.66E+03 1.18E+03 0.00E+00 1.79E+03 0.00E+00 8.27E+05 NB-95 5.94E+05 2.45E+05 1.41E+05 0.00E+00 1.75E+05 0.00E+00 2.07E+0B RU-103 S.68E+03 0.00E+00 2.90E+03 0.00E+00 1.81E+04 0.00E+00 1.06E+05 RU-106 1.91E+05 0.0CE+00 2.38E+04 0.00E+00 2.25E+05 0.00E+00 1.45E+06 AG-110M 3.86E+08 2.82E+08 1.87E+08 0.00E+00 4.03E+08 0.00E+00 1.46E+10 TE-125M 1.51E+08 5.05E+07 2.04E+07 5.08E+07 0.00E+00 0.00E+00 7.19E+07 TE-127M 4.22E+08 1.40E+08 5.10E+07 1.22E+C8 1.04E+09 0.00E+00 1.70E+08 TE-129M 5.58E+08 1.91E+08 8.59E+07 2.14E+08 1.39E+09 0.00E+00 3.33E+08 I-131 2.72E+09 3.21E+09 1.41E+09 1.05E+12 3.75E+09 0.0CE+00 1.15E+08 I-133 3.63E+07 5.29E+07 1.55E+07 9.62L+09 6.22E+07 0.00E+00 8.96E+06 CS-134 3.65E+10 6.81E+10 6.88E+09 0.00E+00 1.75E+10 7.19E+09 1.85E+08 CS-336 1.98E+09 5.83E+09 2.18E+09 0.00F+00 2.32E+09 4.75E+08 8.85E+07 CS-137 5.15E+10 6.03E+10 4.27E+09 0.00E+00 1.62E+10 6.55E+09 1.89E+08 BA-140 2.42E+0B 2.42E+05 1.25E+07 0.00E+00 5.75E+04 1.49E+05 5.94E+07 CE-141 4.343+04 2.65E+04 3.12E+03 0.00E+00 8.17E+03 0.00E+00 1.37E+07 CE-144 2.33E+06 9.53E+05 1.30E+05 0.00E+00 3.85E+05 0.00E+00 1.34E+08 PR-143 1.49E+03 5.56E+02 7.37E+01 0.00E+00 2.07E+02 0.00E+00 7.84E+05 ND-147 S.83E+02 9.07E+02 5.55E+01 0.00E+00 3.50E+02 0.00E+00 5.75E+05 = 65.0 2171c

ENuclear ruz 3.e1 1 9 c.1 C,,ntro1. 1 Departmental Procedure 6610-PLN-4200.01 i Revision No. Title 1 Offsite Dose calcu1ation Menua1 (ODCM) T ABLE _ _5. 4. 2 PATHWAY DOSE FACTORS, Ri AGE GROUP: CHILD PATH.AY: GEASS-COW-MILK -_=- - _ - - - _ _ - - = = - ~ =.- -------=- - mrem / year per pCi/sec 2 ORGAN DOSE FACTORS; m

---

== -

==----- NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI = __.--.-----==---=__ H-3 0.00E+00 1 57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 CR-51 0.00E+00 0.00E+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06

---

=

=-_------------------ --_ _ MN-54 0.00E+00 2.10E+07 5.59E+06 0.00E+00 5.89E+06 0.00E+00 1.76E+0! = - _ FE-55 1.12E+08 5.94E+07 1.84E+07 0.00E+00 0.00E+00 3.36E+07 1.10E+07 [ FE-59 1.20E+08 1.95E+08 9.70E+07 0.00E+0C 0.00E+00 5.65E+07 2.03E+08 --__-_n ..00E+0G 1.21E+07 3.72E+07 0.00E+00 0.00E+00 0.00E+00 7.08E+07 0 C0-58 Co-60 0.00E+00 4.32E+07 1.27E+08 0.00E+00 0.00E+00 0.00E+00 2.39E+08 NI-63 2.97E+10 1.59E+09 1.01E+09 0.00E+00 0.00E+00 0.00E+00 1.07E+08 . =. h ZN-65 4.14E+09 1.10E+10 6.86E+09 0.00E+00 6.95E+09 0.00E+00 1.94E+09 RB-86 0.00E+00 8.78E^?9 5.40E+09 0.00E+00 0.00E+00 0.00E+00 5.65E+08 SR-89 G.63E+09 0.00E+03 1.89E+08 0.00E+0) 0.00E+00 0.00E+00 2.57E+03 SR-90 1.12E+11 0.00E+00 2.84E+10 0.00E+00 0.00E+00 0.00E+00 1.51E+09 Y-91 3.91E+04 0.00E+00 1.05E+03 0.00E+( 0.00E+00 0.00E+00 5.21E+06 ZR-95 3.84E+03 8.43E+02 7.51E+02 0.00E+03 1.21E+ J 0.00E+00 8.80E+05 NB-95 3.18E+05 1.24E+05 8.86E+04 0.00E+00 1.15E+05 0.00E+00 2.29E+08 RU-103 4.29E+03 0.00E+00 1.65E+03 0.00E+0G 1.08E+04 0.00E+00 1.11E+05 RU-106 9.25E+04 0.00E400 1.15E+04 0.00E+00 1.25E+05 0.00E+00 1.44E+06 AG-110M 2.09E+08 1.41E+0B 1.13E+08 0.00E+00 2.63E+08 0.00E+00 1.68E+10 TE-125H 7.39E+07 2.00E+07 9.85E+06 2.07E+07 0.00E+00 0.00E+00 7.13E+07 TE-127M 2.08E+08 5.61E+07 2.47E+07 4.98E+07 5.94E+08 0.00E+00 1.69E+08 TE-129M 2.72E+08 7.59E+37 4.22E+07 8.76E+07 7.98E+08 0.00E+00 3.31E+08 I-131 1.31E+09 1.31E+09 7.46E+08 4.34E+11 2.16E+09 0.00E+00 1.17E+08 I-133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 0.00E+00 8.d8E+06 CS-134 2.27E+10 3.72E+10 7.85E+09 0.00E+00 1.15E+10 4.14E+09 2.01E+0e CS-136 1.01E+09 2.79E+09 1.80E+09 0.00E+00 1.49E+09 2.21E+08 9.80E+07 ~ CS-137 3.23E+10 3.09E+10 4.56E+09 0.00E+00 1.01E410 3.62E+09 1.93E+08 g -.=__ =. _. _ = - - - - = _ BA-140 2 18E+08 1.03E+V5 6.86E+06 0.00E+00 3.35E+04 6.14E+04 5.96E+07 CE-141 2.19E+04 1.09E+04 1.62E+03 0.00E+00 4.79E+03 0.00E+00 1.36E+07 CE-144 1.63E+06 5.09E+05 8.67E+04 0.00E+00 2.82E+05 0.00E+00 1.33E+08 --== PR-143 7.18E+02 2.16E+02 3.56E+01 0.00E+00 1.17E+02 0.00E+00 7.75E+05 ND-147 4.45E+02 3.61E+02 2.79E+01 0.0CE+00 1.98E+02 0.00E+00 5.71E+05 --= 66.0 2171c

0 NI TMI Radiological Contrais Departmental Procedure 6610-PLN-42OO.01__ Revision No. Title 1 Offsite Dose Caiculation Manual (OOCW) TABLE 5.4.3 PATIfWAY DOSE FACTORS, Ri i AGE GROUP: TEMN PAThMAY: GRASS-COW-MILK =. = ORGAN DOSE FACTORS; m2 - mram/ year per pCi/sec

--------~

== - NUCLIDE BONE LIVER T. BODY THYEDID KIDNEY LUNG GI-LLI = H-3 0.00E+00 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 C-34 4.86E+08 9.73E+07 9.73E+07 9.73E+07' 9.73E+07 9.73E+07 9.73E+07 CR-51 0.00E+00 0.00E+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 =_ MN-54 0.00E+00 1.40E+07 2.78E+06 0.00E+00 4.19E+06 0.00E+00 2.88E+07 FE-55 4.46E+07 3.1GE+07 7.37E+06 0.00E+00 0.00E+00 2.01E+07 1.37E+07 FE-59 5.19E+07 1.21E+08 4.60E+07 0.00E+00 0.00E+00 3.82E+07 2.86E+08 C0-58 0.00E+00 7.94E+06 1.83E+07 0.00E+00 0.00E+00 0.00E+00 1.10E+08 CO-66 0.00E+00 2.78E+07 6.27E+07 0.002+00 0.00E+00 0.00E+00 3.62E+08 NI-63 -1.18E+10 8.36E+08 4.01E+08 0.00E+00 0.00E+00 0.00E+00 1.33E408 ZN-65 2.11E+09 7.32E+09-0.42E+09 0.00E+00 4.69E+09 0.00E+00 3.10EtO9 RB-86 0.00E+00 4.73E+09 2.22E+09 0.00E+00 0.00E+00 0.00E+00 7.00E+0b SR-89 .2.6BE+09' O.00E+00 7.67E+07 0.00E+00 0.00E+00 0.00E+00 3.19E+08 SR-90 6.62E+10 0.00E+00 1.63E+10 0.00E+00 0.00E+00 0.00F+00 1.86E+09~ Y-91 1.58E+04 0.00E+00 4.24E+02 0.00E+00 0.00E+00 0.00E+00 6.48E+06 ER-95 1.65E+03. 5.21E+02 3.58E.02 0.00E+00 7.65E+02 0.00E+00 1.20E+06 NB-95 1.41E+05 7.82E+04 4.30E-04 0.00E+00 7.58E+04 0.00E+00 3.34E+08 Rt?-103 - 1.81E+03 0.00E+00 7.75E 07 0.00E+00 6.39E+03 0.00E+00 1.51E+05 RU-106 3.76E+04 -0.OOE+00 4.73E+03 0.00E+00 7.24E+04 0.00E+00 1.80E+06 =_. AG-110M' 9.64E+07 9.12E+07 E.SSE+07 0.002+00 1.74E+08 0.00E+00 2.56E+10 TE-125M 3.01E+07 1.08E+07 4.02E+06 8.40E+06 C.00E+00 _O.00E+00 8.87E+07 i TE-127M 8.45E+07 3.00Es07 1.00E+07 2.01E+07 3.42E+08 0.00E+00 2.11E+08 =_____ __. ~. l-l 'TE-129M 1.10E+08 4.09t+07 1.74E+07 3.562+07 4.61E+08 0.00E+00 4.14E+08 I-131 5.38E+08 7.53E+08 4.05E+08 2.20E+11 1.30E+09 0.OOE+00 1.49E+08 I-133 7.08E+06 1.20E+07 2.66E+06 1.68E+09 2.11E+07 0.00E+00 9.09E+06 CS-134 9.83E+09 2JN3'10 1.07E+10 0.00E+00 7.35E+09 2.81E+09 2.88E+08 CS-136 4.49E+08 1.'i7d+09 1.19E+09 0.00E+00 9.63E+08 1.52E+08 1.42E+08 CS-137 1.34E+10 1.7dE+10 6.21E+09 0.00E+00 6.06E+"9 2.36E+09 2.54E+08 BA-140 4.67E+07 5.97E+04 3.14E+06 0.00E+00 2.02E+04 4.01E+04 7.51E+07 .CE-141' 8.89E+03-5.94E+03 6.82E+02 0.00E+00 2.80E+03 0.COE+00 1.7C9+07 ). CE-144 6.59E+05 .2.73E+05 3.54E+04 0.00E+00 1.63E+05 0.00E+00 1.66E+08 l. .. = = _ _ PR-143 2.90E+02 1.16E+02 1.44E+01 0.00E+00 6.73E+01. O.00E+00 9.55E+05 ND-147 1.81E+02 1.J7E+02 1.18E+01 0.00E+00 1.16%+02 0.00E+00 7.12E+C 67.0 2171c 1 l 1: l

s l d Number TMI Radiological Controls Departmental Procedure 6610-FLN-42OO.01 Revision No. _ Title 1 Offsite Dose Calculation Manual (ODCM) TABLE 5.4.4 PATEWAY DOSE FACTORS, Ri AGE GAOUP: ADULT PATHWAY: GRASS-COW-MILK -===-.....----....----... 2-mrem / year per pCi/sec ORGAN DOSE FACTORS; m NUCLIDE BohE LIVER-T. BODY THYROID KIDNEY LUNG CI-LLI =- H 0.OOE+00 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 C-14 2.63E+08 5.26E+07. 5.26E+07 5.26E+07 5.26E+07 3.26E+07 5.26E+C7 CR-51 0,00Z+00 0.00E+00 2.85E+04 1.70E+04 6.28E+03 3.78E+04 7.17E+06 MN-54 0.00E+00 8.40u+06 1.60E+06 0.00E+00 2.50E+06 0.00E+00 2.57E+07 C FE-55 2.51E+07

1.73E+07 4.04E+06 0.06M+00 0.00E+00 9.66E+06 9 33E+06 TE-59 2.97E+07 6.97E+07 2.67E+07 0.OOE+00 0.OOE+00 1.95E+07 2.32E+08 00-58 0.OOE+00 4.71E+06 1.05E+07 0.00E+00 0.00C+00 0.OOE+00 9.54E+07 Co-60 0.OOE+00 1.64E+07 3.61E+07 0.00E+00 0.00E+00 0.OOE+00

3. OPE +08 NI-63 6.72E+09 4.65E+08 2.25E+08 0.00E+00 0.00E+00 0.00E+00 9.71E+07 ZN-65 1.37E+09 4.36E+09 1.97E+09 0.00E+00 2.91E+09 0.00E+00 2.74E+09 RB-86 0.OOE+00 2.59E+09 1.21E+09 0.OOE+00 0.00E+00 0.00E+00 5.10E+0S SR-89 1.45E:09 0.00E+00 4.16E+07 0.00E+00 0.00E+00 0.00E+00 2.32E+08 SR-90 4.67E+10.

0.00E+00-1.15E+10 0.COE+00 0.00E+00 0.00E+00 1.35E+09 Y-91 8.57E+03 0.OOE+00 2.29E+02 0.00E+00. O.OOE+00 0.00E+00 4.72E+06 l= ZR-95 9.41E+02 3.02E+02 2.04E+02 0.00E+00 4.74E+02-0.00E+00 9.57E+05 l NS 8.24E+04 4.58E+04 2.46E+04 C.OOE&OO 4.53E+04 0.00E+00 2.78E+0S RU-103 1.02E+03 0.00E+00 4.38E+02 0.00E+00 3.88E+03 0.OOE+00 1.19E405 RU-106 2.04E+04 - 0.00E+0V

2. 5 9E4 03 0.OOE+00 3.93E+04 0.OOE+00 1.32E+06 AG-110M 5.81E+07 5.38E+07 3.19E+07 0.OOE+00 1.06E+08 0.00E+00 2.19E+10 TE-125M.

1.63E+07 5.89E+06 2.18E+06 4.89E+06 6.61E+07 0.OOE+00 6.49E+07 l TE-127M 4.57E+07 -1.63E+07 5.57E+06 1.17E+07 1.86E+08 0.00C+00 1.53E+08 L L TE-129M 6.01E+07 2.24E+07 9.51E+06 2.06E+07 2.51E+08 0.00E+00 -3.02E+08 l I-131-2.96E+08 4.~23E+08 2. 42E +O-3 1.39E+11 7.25E+08 0.OOE+00 1.12E+08 I 33. 3.87E+06 6.73E+06 2.05E+06 9.88E+08 1.17E+07 0.OOE+00 6.04E+06 1 CS-134 5.64M+09 1.34E+10 1.10!+10 0.00E+00 4.34E+09 1.44E+09 2.35E+08 CS-136 2.63E+03 1.04E+O9 7.48E+08 0.00E+00 5.78E+08 7.92E+07 1.18E+08 CS-137 7.37E+09 .1.01E+10 6.60E+09 0.00E+00 3.42E+09 . 14E+0? 1.95E+0B BA-140-2.b9E+07 3.38E+04 1.76E+06 0.COE+00~ ~1.15E+04 1.94E+04 5.54E+07 CE-141 4.84E+03 3.27E+03 3.71E+02 0.OOE+00 1.52E+03 0.OOE+00 1.25E+07-CE-144 3.57E+05 1.49E+05 1.92E+04 0.00E+00 9.85E+04 0.OOE+00 1.21E+08 PR-143 1.57E+02 6.32E+01 7.81E+00 0.OOE+00 3.65E+01 0.00E+00 ' 6.90E+05 ND-147' 9.40E+01 1.09E+02 6.50E+00-0.00E+00 6.35E+01 0.00E+00 5.22E+05 =_ I-l i 68.0 2171c 1 +c -e r-- 1

Ubihh TMI Radiological Cc,'trols Departmental Procedure 6610-PLN-4200.01~ Revision No. Title 1-Offsite Dose Calculation Manual (ODCM) TABLE 5.5.1 PATHWAY _ DOSE FACTORS, Ri -AGE GRCUPt 'NFANT PATHWAY: GRASS-GOAT-MILK = ORGAN DOSE FACTORS; m - mrom/ year per pCi/sec 2

---

~*--------------- --

NUCLIDE BONE LIVER T.BCDY THYROID KIDNEY LFNG GI-LLI = - - - - - - - - - - - - - - - - - - - - - - - - - - - = = = = --

---

==-

- =------------ _ H-3 0.00E+00' 4.86E+C1 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 C-14 2.34E+09 5.00E+08 5.00E+08 5.00E+0S 5.00E+08 5.00E+08 5.00E+08 CR 0.00E+00 0.00E+00 1.94E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05

---

=

MN-54 0.00E+00 4.68E+06 1.06E+06 0.00E+00 1.04E+06 0.00E+00 1.72E+06 FE-55 1.76E+06-1.14E+06 3.03E+05 0.00E+0C 0.00E+00 C.55E+05 1.44E+05 FE-59: 2.92E+06 -5.10E+06 2.01E+06 0.00E+00 0.00E+00 1.51E+06 2.44E+06 __-.- _ =-- = ----------------------------------- CO-58 0.00E+00 2.91E+06 7.26E+06 0.00E+00 0.00E+00 0.00E+00 7.25E+06 CO 0.00E+00 1.06E+07 2.50E+07 0.00E+00 0.00E+00 0.00E+00 - 2.52E+07 NI-63 4.19E+09 2.59*.+08-1.46E+08 0.00E+00 0.00E+00 0.00E+00 1.29E+07 EN-65 6.67E+08 -2.29E+09 1.05E+09 0.00E+00 1.11E+09 'O.00E+00 1.93E+09 --RB-86 0.00E+00 2.67E+09-1.32E+09 0.00E+00 0.00E+00 0.00E+00 6.83E+07 SR-89 2.65E+10 0.00E+00 -7.59E+08 0.00E+00 . 0.00E+00 0.00E+00 5.44E*08 = -SR-90~ 2.55E+11 0.00E+00 6.50E+10 0.00E+00 0.00E+00 0.00E+00 3.19E+09 Y-91 8.80F+03 0.00E+00 2.34E+02 0.00E+00' O.00E+00 0.00E+00 6.31E+05 ZR-95 8.17E +02 --- -1.99E+02 1.41E+02 0.00E+00 ' 2.15E+02-0.00E+00 9.91E+04 =- NS-95 7.13E+04 2.93E+0' 1.70E+04 0.00E+00 2.10E+04 0.00E+00 2.48E+07 RU-103 1.04E+03 0.00E+0u 3.40E+02 0.00E+00 2.17E+03 C.00E+00 1.27E+04 RU-106-- 2.28E+04 -0.00E+00 2.85E+03 0.00E+00-2.70E404 0.00E+00 1.73E+05 hG-110M-4.63E+07 3.38E+07 2.24E+07 0.00E+00 4 84F+07 0.00E+00 1.75E+09 TE-125M 1.81E+07 6.05E+06 2.45E+06 6.09E+06 0.00E+00 0.00E+00 8.62E+06 TE-127M 5.060+07 1.68E+07 6.12E+06-1.46E+07-1.24E+08 0.00E+00 2.04E+07 .TE-129d 6.69E+07 3.29E+07 1.03E+07 2.57E+07 1.67E+0C 0.00E+00 3.99E+07 I-131 3.27E+09 3.CSE+09 1.69E+09 1.27E+12 4.50E+09 0.00E+00 1.37E+08 .I-133 4.36E+07 6.35E+07-1.86E+07 1.15E+10 7.46E+0/ 0.00E+00 1.07E+07 =_ CS-134 1.09E+11 2.04E+11 2.06E+10 0.03E+00 5.26E+10 2.15E+10 5.55E+08 CS-136- -5.94E+09 -- 1. 7 5E+10 - 6.52E+09 0.OOE+00 6.96E+09 1.42E+09 - 2.65E+08 [ C3-137 1.54E+11 1.81E+11 1.78E+10 0.00E+00 4.85E+10 1.96E+10 5.65E+08 BA-140 2. 9 0E+07 --- 2.90E+04 1.50E+06 0.00E+00 6.89E+03 1.78E+04-7.13E+06 CE-141 5.21E+03 3.18E+03 3.74E+02 0.00E+00 9.79E+02 0.00E+00 1.64Lvo6 CE-144: 2.79E+05 1.14E+05 14 56E+04 0.00E+00 4.62E+04 0.00E+00 1.60E+07 = =_ PR-143 1.78E+02 6.66E+01 S.83E+00-0.00E+00 2.48E+01 0.00E+00 9.40E+04 ND-147 1.06E+02 1.09E+02 6.66E+00 'O.00E+00 4.19E+01 0.00E+00 6.89E+04 69.0 2171c ,,-o, w ~r --v--- w

.~ _ ~-- l MUClear TM1 Rou otoc c.1 Controts Departmental Procedure 6610-PLN-42OO.01 Revision No. Title 1 Offsite Done Calculation Manual (ODCM) TABLE 5.5.2 PATH 4AY DOSE FACTORS, Ri AGE GROUP: CHIL. PATHWAY: GRASS-GOAT-MILK = - - - - - - - - - - - - - -. - - - -. - - - - .----.. -- _ _ = - - - -. _ORGAN DOSE FACTORS;-m2 - mrem / year per pCi/sec - = --------------------------

== = - = - - - - - NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.207.+03 C 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 CR-51 0.00E+00 0.00E+00 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.48E+05

---

=

MN-54 L 00E+6" 2.52E+06 6.71E+05 0.00C+00 7.06E+05 0.00E+00 2.11E+06 FE-55

1. ss+06 7.71E+05 2.39E+05 0.00E+00 0.00E+00 4.36E+05 1.430+05 FE-59 1.56E+05 2.534:06 1.26E+06 0.00E+00 0.00E+00 7.34E+05 2.64E+06

-=.==__= Co-58 0.00E+00 1.46E+06 4.46E+06 0.00E+00 0.00E+00 0.00E+00 8.49E+06 Co-60 J.00E+00 5.18E+06 1.53E+07 0.00E+00 0.00E+00 0.00E+00 2.87E+07 NI-63 3.56E+09 1.91E+08 1.21E+08 0.00E+00 0.00E+00 0.00E+00 1.28E+07 =- = - - - _. ZN-65 .4.96E+08 1.32E+09 8.22E+08 0.00E+00 8.33E+08 0.00E+00 2.32E*08 RB-86 .0.uCE+00 1.05E+09 6.47E+08 0.00E+00 0.00E+00 0.00E+00 6.77E+07 SR-89 -1.39E+10 0.00E+C0 3.97E+08 0.00E+00 0.00E+00 0.00E+00 5.39E+08 SI-90 2.35E+11 0.00E+00 5.95E+10 -0.00E+00 .00E+00 0.00E+00 3.16E+09 Y-51 4.69E+03 0.00E+00 1.25E'02 0.00E+00 SOE+00 0.00E+00 6.24E+05 ER-95 4.60E+02 1.01E+02 9.00E+01 0.00E+00 45E+02 0.00E+00 1.05E+05 NB-95 3.62E+04-1.49E+04' 1.06E+04 0.00E+00 1.40E+04 0.00E+00 2.75E+07 RU-103 5.14E+02 0.00E+00 1.98E+02 0.00E+00 1.29E+03 0.00E+00 1.33E+04 RU-106 1.11E+04 0.00E+00 1.38E+03 0.00E+00 1.50E+04 0.00E+00 1.73E+05 AG-110M 2.51E+07 1.69E+07 1.35E+07 0.00E+00 3.15E+07 0.00E+00 2.01E+09 TE-125M 8.86E+06 2.40E+06 1.18E+06 2.49E+06 0.00E+00 0.00E+00 8.55E'06 TE-127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 0.00E+00. 2.02E+07 -=---- _ TE-129M 3.26E+07 9.10E+06-5.06E+06 1.05E+07 9.56E+07 0.00E+00 3.97E+07 '1-131 1.57E+09 1.57E+09 8.95E608 5.21E+11 2.58E+09 0.00E+00-1.40E+08 I-133 -2.06Ev07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 0.00E+00 1.03E+07 CS-134 6.80E+10 1.12E+11 2.35E+10 0.00E+00 3.46E+30 1.24E+10 6.01E+08 CS-136 3.04E+09 8.36E+09. d.41E+09 0.00?'SO 4.45E+09 6.64E+08 2.94E+08 CS-137 9.68E+10 9.26E+10 1.37E+10 0.003-7 3.02E+10 1.09E+10 5.80E+08 BA-140' 1.41E+07 1.24E+04' 8.243+0s 0.00hd U 4.022+0J 7.37E+03 7.15E+06 -CE-141-2.63h+03 1.31E+03 1.9bs+02 0.00" JO 5.74E+02 0.00E+00 1.63E+06 CE-144 1.95E+05 6.11E+04 1.04E+C4

0. 0L+00 3.38E+04 0.00E+00 1.59E+07

.- _ _=.----- PR-143-- ~8.G3E+01 2.59E+01 4.27E+00 0.00E+00 1.40Et01 0.00E+00 9.29E+04 ND-147-5.34E+01 4.334+01 3.35E+00 0.00E+00 2.37E+01 0.00E+00 6.05E+04 70.0 2.'.71c

I'- U1 Nuclear TMz Rse,o1o9 c.1 contro1s 1 Departmental Precedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Done Calculation Manual (ODCM) TABLE 5.5.3 PATHWAY DOSE FACTORS, Ri AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK = =--------------. ORGAN DO3E FACTORS; m2 - mrem / year per pCi/sec

==------------ NUCLIDE - - - - - - - - - - - - - = - - - BONE LIVER T. BODY THYROID KIDMEY LUNG GI-LLI =---------- H-3 0.00E+00 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 C-14 4.86E+08 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 CR-51 0.00E+00 0.00E+00 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+06

== _ = - - __==----- MN-54 0.00E+00 1.68E+06 3.34E+05 0.00E+00 5.02E+05 0.00E+00 3.45E+06 FE-5F 5.79E+05 4.11E+05 9.58E+04 0.00E+00 0.0VE+00 2.61E+05 1.78E+05 FE-59 6.74E+05 1.57E+06 6.08E+05 0.00E+00 0.00E+00 4.96E+05 3.72E+06 000E+bo 9.h3E+05 2.20E+06 0.00E+00 0.00E+00 0.00E+00 1.31E+07 CO-58 00-60 0.00E+00 3.34E+06 7.52E+06 0.00E+00 0.00E+00 0.00Ev00 4.35E+07 NI-63 1.42E+09 1.00E+08 4.81E+07 0.00E+00 0.00E+00 0.00E+00 1.60E+07 ZN-65 12.53E+08 8.78E+08 4.10E+08 0.00E+00 5.62E+08 0.00E+00 3.72E+08 RS-86 0.00E+00 5.67E+0d 2.67E+08 0.uGE+00 0.00E+00 0.00E+00 8.40E+07 sR-89 5.62E+09 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0.OOE+00 6.69E+08 SR-90 1.39E+11 0.00E+00 3.43E+10 0.0 J+00 0.00E+00 0.00E+00 3.90E+09 Y-91 1.90E+03 0.00E+00 5.09E+01 0.00E+00 0.00E+00 0.00E+00 7.78E+05 l ZP-95 1.98E+02 6.25E+01 4.30E+01 0.00E+00 9.18E+01 0.00E+00 1.44E+05 -= l NB-95 1.69E+04 9.3SE+03 5.16Es43 0.00E+00 9.09E+03 0.00E+00 4.01E+07 RU-103 2.17E+02 0.00E+00 9. 2 0', e01 0.COEv00 7.66E+02 0.00E+00 1.82E+04 RU-106 4.50E+03 0.00E+00 5.o8E+02 0.OOE+00 8.69E+03 0.00E+00 2.16E+05 G-110M 1.16E+07 1.09E+07 6.65E+06 0.00E+00 2.09E+07 0.bOE+00 3.07Evo9 TE-125M 3.61E+06 1.30E+06 4.82E+05 1.01E+06 0.00E+00 0.00E+00 1.06E+07 TE-127M 1.01E+07 3.59E+0c 1.20E+06 2.41E+06 4.11E+07 0.0C0+00 2.51E+07 .32E+07 -=

---

_=

1 4.90E+06 2.09E+06 4.26E+06 5.53E+07 0.00E+00 4.96E+07 TE-129M I-131 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.56E+09 0.00E+01 1.79E+08 I-133 8.49E*06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 0.00E+00 1.09E+07 = -------- ^- CS-134 2.95E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+1D 8.41E+09 8.62E+08 CS-136 1.35E+09 5.30E+09 3.56E+09 0.00E+00 2.89E+09 4.55E+08 4.27E+08 CS-137 4.02E+10 5.34E+10 1.86E+10 0.00E+00 1.82L+10 7.07E+09 7.60E+08 .= BA-140 5.34E+06 7.16E+03 3.76E+05 0.00E+00 2.43E+03 4.81E+03 9.01E+06 CE-141 1.07E+03 7.12E+02 8.18E+01 0.00E+00 3.35E+02 0.00E+00 2.04E+06 CE-144 7.90E+04 3.27E+04 4.25E+03 0.00E+00 1.95E+04 0.00E+00 1.99E+07 PR-143 3.48E+01 1.39E+01 1.73E+00 0.00E+00 8.08E+00 0.00E+00 1.15E+05 ND-147 2.18E+01 2.37E+01 1.4kE+00 0.00E+00 1.39E+01 0.00E+00 8.54E+04 l _-=--- 71.0 2171c l l

A Nuclear TM1 R.61 1. c.1 Co tro1. Departmental Procedure 6610-PLN-4200.01 Revision No. Tit 1e 1 Offsite Dose'Calcu1ation Mancal (ODCM) TABLE 5.5.4 PATHWAY DOSE FACTORS, Ri ACE GROUFt ADULT PATHWAY: GRASS GOAT-MILK

---

------..-----.---- -----..=-_

ORGAN DOSE F*CTORS; m2 - mram/ year per pCi/sec =- = - - - - - - - - - - - - - - - - - - = - - NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI --..= _=- -_=.------------- H-3 0.00E+00 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 C-14 2.64E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 - CR-51 0.00E+00 0.00E+00 3.43E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+05 MN 54 O OOE+0~- 1.01E+06 1.93E 05 0.00E+00 3.01E+05 0.00E+00 3.10E+ 6 FE-55 3.27E+05 2.26E+05 5.26E+04 0.00E+00 0.00E+00 1.26E+05 1.30E+05 FE-59 3.87E+05 9.09E+05 3.48E+05 0.00E+00 0.00E+00 2.54E+05 3.03E+06 _- = .--.~___ co-58 0.00E+00 5.66E+05 1.27B>06 0.00E+00 0.00E+00 0.00E+00 1.15E+07 Co-60 0.00E+00 1.97E+06 4.35E+06 0.00E+00 0.00E+00 0.00E+00 3.70E+07 NI-63 8.08E+09-5.60E+07 2.71E+07 0.00E+00 0.00E+00 0.00E+00 1.47E+07 ZN-65 1.65E+08 5.24E+08 2.37E+08 0.00E+00 3.51E+08 .0.00E+00 3.30E+08 RB-86~ -0.00E+00 3.12E+08 1.45E+0S 0.00E400 0.00E+00 0.00E+00 6.14E+07 SR 3.05E+09 0.UUE+00 8.76E+07 0.00E+00 0.00E+00 0.00E+00 4.89E+08 = -------- SR-90 9.84E+10 0.00E+00 2.41E+10 0.00E+00' O.00E+00 0.00E+00 2.84Ev05 . Y-91 1.03E+03 0.00E+00 2.76E+01 0.00E+00 0.OCE+00 0.00E+00 5.68E+05 ZR-95 1.13E+02 3.63E+01 2.46E+01 0.OOE+00 5.70E+01 0.00E+00 -1.15E+05 =..----------..-- ------.. - NB -9.92E+03 5.52E+03 2.97E+03 0.00E+00 5.45E+03 0.00E+00' 3.35E+07 - RU-103 1.22E+02-O.00E+00 5.27E+01 -0.00E+00 4.67E+02 0.00E+00 1.43E+04 RU-106 2.45E+03 0.00E&OO 3.10E+02 0.00E+00 4.73E+03 0.00E+00 1.59E+05 AG-110M 6.99E+06 A.47E+06 3.84E+06 0.00E+00 1.27E+07 0.00E+00 2.64E+09 ' TE-125M 1.96E+06 7.09E+05 2.62E+05 5.89E+05 7.96E+06 0.00E+00 7.81E+06 TE-327M 5.50E+06 1.97E+06 6.70E+05

1. 41E +045 2.23E+07 0.00E+00 1.84E+07

-TE-129H 7.23E+06 2.70E+06 1.14E+06 2.4BE+06 3.02E+07 0.00E+00 3.64E+07 I-131 3.56E+08 5.09E+0C 2.92E+08 1.67E+11 8.73E+08 0.00E+00 2.34E+08 I-133 4 65E+06 8.10E+06 2.473+05 1.19E+09 1.41E+07 0.00E+00 7.28E+06 CS-134 1.70E+10 4.04E+10 3.30E+10 0.00E+00 1.31E+10-4.34E+09 7.07E+08-CS-136 7.92E+08 3.13E+09 2.25E+09 0.00E+00-1.74E+0* 2.38E+08 3.55E+08 - CS-137 2.22E+10 3.00E+10 1.99E+10 0.00E+00 1.03E+10 3.42E+09 5.87E+08 BA-140 3.24E+06 4.07E+03 2.12E+05 0.00E+00 1.28E+03 2.33E+03 6.67E+06 CE-141 5.82E+02 3.94E+02 4.47E+01 0.00E+00 1.83E+02 0.00E+00 1.51E+06 - CE-144 4.30E+04 1.80E+04 2.31E+03 0.00E+00 1.07E+04 0.00E+00 1.45E+07 PR-143 1.90E+01 7.60E+00 9.40e-01 0.OOE+00 4.39E+00 0.00E+00 8.30E+04 - ND-147 1.13E+01 1.31E+01 7.82e-01 0.00E+00 7.65E+00 0.00E+00 6.28E+04 72.0 2171c y---

ENuclear TMI R.e1 1,1ce1 cemtre1. Departmentat Procadure 6610-PLN-4200.01 Revisicn No. Title 1 Of f site Dose Calculation Manual (ODCM) TABLE 5.6.1 PATHWAY DOSE FACTORS, Ri AGE GROUP INFANT PATHWAY: GRASS-COW-MEAT

---

----_==------=_--

_n_ ORGAN DOSE FACTORS; m. mrem / year per pCi/sec 2 -=------ = --= ------------------=---- =-- -- NUCLIDE - - - - - - = - - - - - - - - BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI =------------ -- H-3 0.OCE+00 0.00E+00 0.00E+00 0.002 >00 0.00E+00 0.00E+00 0.OUE+00 C-14 0.OOE+00 0.00E+00 .22E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CR-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 --- =_ -- --- _=- --- =- _z.------_--_-_-- MN-54 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00Ets., 0.00E+00 0.00E+00 FE-53 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 = - - - - - -. - - - - - - CO-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 0.COE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.COE+00 NI-63 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.0bE+00 0.bbE00 0ObE+b0 0.bOE+00 0.00E+00 ZN-65 0.00E+00 0.00E+00 RB-86 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 =-- SR-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Y-91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+09 ZR-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+CO - - - = _ ---.COE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 NB-95 RU-103 0.00E+00 0.00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU-106 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 AG-110M O.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 TE-125M O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E&OO 0.00E+00 0.00E+00 TE -127M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+0C TE-129M O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 - - - - = _ - I-131 0.00E+00 0.00E+00 0.GCC+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 I-133 0.0CE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 CS-134 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 CS-136 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 CS-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE-141 0.OOE+00 0.00E+00 0.00E+00 0.COE+00 0.00E+00 0.00E+00 0.OOE+00 CE-144 0.00r<00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+0b 0.COE+00 0.00E+00 0.0bE+00 0.OOk+00 0.OOE+00 0 00E+00 PR-143 ND-147 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.002+00 0.00E+00 73.0 2171c

N N TMI Radiological Controli Departmental Procedure 6610-PLN-4200.01__ Revision No. Title 1 Offsite Dose Calculation Manual (ODCN) TABLE 5.6.2 PATHWAY DOSE FACTORS, Ri AGE GROUP: CHILD PATHWAY: GRASS-COW-MIAT p - =-- - OROAN DOSE FACTORS; m - mrwm/ year per pC1/sec 2 - - - - - - - - = - = - - - - = - - - - - - - - - - - - =--: NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI - - - - - - - - = - - - H-3 0.00E+00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 C-14 3.84E408 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.672+07 7.67E+07 CR-51 0.00E+00 0.00E+00 8.78E+03 4.88E+03 1.33R+03 8.9CE+03 4.66E+05 = - - -. - - -_ - - - = - - - -.. - - - - - - - - - - - - - - - MN-54 0.00Z+00 8.01E+06 2.13E+06 0.00E+00 2.25E+06 0.OOE+00 6.73E+06 FE-55 4.57E+08 2.43E+08 7.52E+07 0.00E+00 0.00E+00 1.37E+08 4.49E+07 FE-59 3.77E+08 6.10E+08 3.04E+08 0.00E+00 0.00E+00 1.77E+08 6.35E+08 - _ - - _ = -- - __= CO-58 0.00E+00 1.64E+07 5.03E+07 0.00E+00 0.00E+00 0.00R+00 9.58E+07 CO-60 0.00E+00 6.93E+07 2.04E+08 0.00E+00 0.00E+00 0.00E+00 3.84E+08 NI-63 2.93E+10 1.56E+09 9.91E+08 0.00E+70 0.00E+00 0.00E+00 1.05E+08 ZN-65 3.76E+08 1.00E+09 6.22E+08 0.00E+00 6.31E+08 0.00E+00 1.76E+08 RB-86 0.00E+00 5.76E+08 3.54E+08 0.00E+00 0.00E+00 0.00E+00 3.71E+07 SR-89 4.82E+08 0.00E+00 1.38E+07 0.00E+00 0.00E+00 0.00E+00 1.87E+07 SR9b 1.04E+10 0.00E+00 2.64E+09 0.00E+b0 b.00E+00 0.0bE+00 1.40E+08 Y-91 1.COE+06 0.00E+00 4.82E+04 0.00E+00 0.00E+00 0.00E+00 2.40E+08 ZR-95 2.66E+06 5.86E+05 5.21E+05 0.00E+00 8.38E+05 0.00E+00 6.11E+08 NB-95 3.10E+06 3.'1E+06 8.63E+05 0.00E+00 1.13E+06 0.00E+00 2.23E+09 RU-103 1.55E+08 c.0,E+00 5.96E+07 0.00E+00 3.90E+08 0.00E+00 4.02E+09 RU-106 4.44E+09 i 30E+00 5.54E+08 0.00E+00 6.00E+09 0.00E+00 6 01?'10 AG-110M 8.39E+06 5.67E+06 4.53E+06 0.00E+00 1.06E+07 0.OuE+00 6 3-08 TE-125M 5.69E+08 1.54E+08 7.59E+07 1.60E+08 0.00E+00 0.00E+00 5-401.08 TE-127M 1.78E+09 4.78E+08 2.11E+08 4.25E+08 5.06E+09 0.00E+00 1.44t+09 TE-129M 1.79E+09 5.00E+08 2.78E+08 5.77E+08 5.26E+09 0.00E+00 2.18E+09 I-131 1.66E+07 1.67E+07 9.48E+06 5.52E+09 2.74E+07 0.00E+00 1.48E+06 I-133 5.72e-01 7.08e-01 2.68e-01 1.31E+02 1.18E+00 0.00E+00 2.85e-01 CS-134 9.23E+08 1.51E+09 3.19E+08 0.00E+00 4.69E+08 1.68E+08 8.16E+06 CS-136 1.63E+07 4.48E+07 2.90E+07 0.00E+00 2.39E+07 3.55E+06 1.57E+06 CS-137 1.33E+09 1.28E+09 1.89E+08 0.00E+00 4.16E+08 1.50E+08 8.00E+06 . --= EA-140 4.'42E+07 3.87E+04 2.58E+06 0.00E+00 1.26E+04 2.31E+04 2.24E+07 CE-141 2.22E+04 1.11E+04 1.65E+03 0.00E+00 4.86E+03 0.00E+00 1.38E+07 CE-144 2.32E+06 7.23B+0C 1.24E+05 0.00E+00 4.02E+05 0.00E+~0 1.89E+08 PR-143 3.33r+04 1.00E+0k 1.65E+03 0.00E+0b 5.42E+03 0.00E+00 3.60E+07 ND-147 1.17L+04 9.48E+0 7.34E+02 0.00E+00 5.20E+03 0.00E+00 1.50E+07 74.0 2171c i

~n, TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Dose Calculation Manual /00CM) TABLE 5.6.3 PATHWAY DOSE FACTORS, Ri AGE GROUP TEEN PATHWAY: GRASS-COW-MEAT =.... _ = - - ORGAN DOSE FACTORS; m2 - mrem / year per pCi/sec

---

=

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI- .--........ -=== H-3 0.00E+00 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02-1.93Ev02 C-14 2.04E+06 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 CR-51 0.00E+00 0.00E+00 5.63E+03 3.13E+03 1.23E+03 8.03E+03 9.46E+05 KN-54 0.00E+00 7.00E+06 1.39E+06-0.00E+00 2.09E+06 0.00E+00 1.44E+07 ?E-55 2.38E+08 1,69E+08 3.94E+07 0.00E+00 0.00E+00 1.07E+08-7.31E+07 FE-59 2.12E+08 4.95E+08 1.91E+08 0.00E+00 0.00E+00 1.56E+08 1.17E+09

---

.==

==.--- 58 0.00E+00 1.40E+07 3.24E+07 0.00E+00 0.00E+00 0.00E+00 1.94E+0E CO-60 0.00E+00~ 5.83E+07 l'.31E+08 0.00E+00 0.00E+00 0.00E+00 7.60E+08 - NI-63 1.52E+10 1.07E+09 5.15E+08 0.00E+00 0.003+00 0.00E+00 1.71E+08 -ZN-65 2.50E+08 8.68E+0S 4.05E+08 0.00E+00 5.56E+08 0.00E+00 3.68E+08 RB-86 0.00E+00 4.06E+08 1.91E+08 0.00E+00 0.00E+00 0.00E+00 6.00E+07 SR-89 2.55E+08 0.00E+00 7.29E+06 0.00E+00 0.00E+00 0.00E+00 3.03E+07 SR-90 8.04E+09 0.00E+00 1.99E+09 0.00E+00 0.00E+00 0.00E+00 2.26E+08 Y-91 9.54E+05 0.00E+00' 2.56E+04 0.00E+00 0.0GE+00 0.00E+00 3.91E+08 ZR-95 .50E+06 4.73E+05 3.25E+05 0.00E+00 6.95E+05 0.00E+00 1.09E+09 4.2hE+0 NB-95 1.79E+06 9.95E+05 5.4SE+05 0.00E+00 9.64E+05 0.00E+00 RU-103-8.56E+07 0.00E+00 3.66E+07 0.00E+00 3.02E+08 0.00E+GO 7.15E+09 RU-106 2.36E+09 0.00E+00 2.97E+08 0.00E+00 4.54E+09-0.00E+00 1.1 E+11 AG-110M 5.06E+06 4.78E+06 ?.91E+06 0.00E+00 9.13E+06 0.00E+00 1.34E+09 TE-125M 3.03E+08-1.09E+08 4.05E+07 8.46E+07 0.00E+33 0.00E+00 8.94E+08 TE-127M-9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.81E+0V 0.00E+00 2.35E+09 TE-129M 9.49E+08 3.52E+08 1.50E+08 3.06E+08 3.97E+09 0.00E+00 3.56E+09 I-131-8.93E+06 1.25E+07 6.72E+06 3.65E+C9 2.15E+07 0.00E+00 2.47E+06 I-133

3. Ora-01 5.22e-01 1.59e-01 7.29E+01 9.16e-01 0.00E+00 3.95e-01 CS-134 5.23E+08 1.23E+09 5.71E+08 0.00E+00 3.91E+08 1.49E+08 1.53E+07 CS-136

-9.43E+06-3.71E+07 2.49E+07 0.00E+00 2.02E+07 3.18E+06 2.99E+06 CS-137 7.24E+08 9.63E+08 3.35E+08 0.00S+00 3.28E+08 1.27E+08 1.37E+07 BA-140 2.39E+07 2.93E40', 1.54E+06 0.00E+00 9.94E+03 1.97E+04 3.69E+07 CE-141 .1.18E+04 7.87E+03 -9.05E+02 0.00F400 3.71E+03 0.00E+00 2.25E+07 CE-144~ 1.23E+06 5.08E+05 6.60E+04

0. 00 R + 0')

3.03E+05-0.00E+00 3.09E+08 h.03E+03 8.76E+02 0.00E+00 4.08E+03 0.00E+00 5.79E+07 1R-143

1. 6E+04 i.

ND-147 6.23E+03-6.78t+03 4.06E+02 0.00E+00 3.98E+03 0.00E+00 2.44E+07 l L 75.0 2171c , ~..

. -...~. -. - LTMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No. Title. i 1 of f site Dose calculatic,a Manual (ODOO ' TABLE 5.6.4 PATHWAY DOSE FACTORS, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT ....= _----.....-------------==- ORGAN DOSE FACTORS; m2 - mram/ year per pCi/sec - - = = = - - - - - ~ ~ ~ ~ ~ - - - - - - - - - - -

---

~~~-~~~~~~-----~~~~~=

WUCLIDE ~~------ -- BONE ' LIVER

1. BODY THYROID KIDNEY LUNG GI-LLI

_-c.-.=- -...----....--.------..---........-----. -...------- --=---- H-3 - 0.00E+00 3.24E+02 3.24E+02 3.24E+02 . 24E+02 3.24E+02 3.24E+02 C-14 2.42E+08 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 CR-51 0.00E+00 0.00E+00 7.04C+03 -4.21E+03 1.55E+03 9.35E+03 1.77E+06 = = -MN-54 0.00E+00 9.18E+05 1.75E+06 0.00E+00 2.73E+06 0.00E+00 2.81E+07 FE-55 2.932v08 2.03E+08 4.73E+07 0.00E+00 0.00E*00 1.13E+08 1.16E+08 FE-59. 2.66E+03. 6.25E+08 2.39E+08 0.00E+00 0.00E+00 1.75E+08 2.08E+09 CO-58 0.00E+00. I.82E+07 4.09E+07 0.002+00 0.00E+00 0.00E+00 3.70E+08 -co-60 0.00E+00 7.52E+07: 1.66E+08. 0.00E+00 ~ 0.00E+00 0.00E+00 1.41E+09

NI 1.89E+10- -1.31E+09 6.33E+08 0.00E500 0.00E+00 0.00E+00 2.73E+08

_ = - - - .ZN-65 3.56E+08 1.13E+09 5.12E+08 0.00E+00 7.57E+08 0.00E+00 7.13E+08 RB-8o1 0.00E+00 -4.87E+08 2.27E+C8 0.00E+00 0.UOE+00 0.00E+00 9.59E+07 .SR-89= 3.02E+C6 0.00E+00 -8.66E+06 0.00E+00 0.00E+00 0.00E+00 4.84E+07 0.ObE+00 305E+b9 b00E+00 0 00E+00 0.00E+00 3 60E+08 SR-90 1.24E+10 Y-91 1.13E+06 0.00E+00 3.03E+04 0.00E+00 0.00E+00 0.00E+00 6.24E+08 ER-95 1.S7E+06 6.0.'+05 4.07E+05-0.00E+00

9. 4.' 7+0 5 0.00E+00 1.90E+09

[NB-95 2.30E+06. 1.28K+06 6.87E+05 0.00E+00-1.26E+06 0.00E+00 7.76E+09 4 -KU-103- -1.05E+08 0.00E+00 4.53E+07-0.00E+00 4.02E+08 0.00E+00 1.23E+10 RU-106 2480E+09 'O.00E+00 3.54E+08 0.00E+00 5.41E+09 0.00E+00 1.81E+11 AG-110M 6.68E+06 6.18E+06 3.67E+06 0.00E+00 1.22E+07 0.00E+00 2.52E+09 'TE-125M 3.59E+08 1.30E+08 4.81E+07 1.08E+08 -1.46E+09 0.00E+00 1.43E+09 TE-127M 1.12E+09 -3.99E+08 1.36E+08 2.85E+08' 4.53E+09 0.00E+00 3.74E+09 1.79E+08.~3.89E+08 4.73E+09 0.00E+00 5.71E+09- -TE-129M-1.13E+09 4.23E+08 ~ 8.82E+06 5.04E+09 2.64E+07 0.00E+00 '4.06E+06-I-131 1.08E+07 -1.54E+07. I-133' 3.68e-01 6.41e 1.95e-01 9.42E+01 1.12E+00 0.00E+00 5.76e-01 CS-124 6.58E+08 ~1.57E+09 1.28E+09 0.00E+00- -5.07E+08 1.68E+08 2.74E+07 CS-136 1.21E+07-4.78E+07-3.44E+07 0.00E+00 2.66E+07 3.65E+06 5.43E406-CS-137. 8.72E+08 1.19E+09 7.82E+08 O GOE+00 4.05E+08 1.35E+08 2.31E+07 EA-140 2.90E+07 3.64E+04-L1.90E+06 0.00E+00 1.24E+04 2.087+04 5.96E+07= CE-141 1.41E+04 9.51E+03 1.083+03-0.00E+00 4.42E+03 0.00E+00 3.64E+07 CE-144 1.46E+06 6.10E+05 7.83E+04: 0.00E+00-3.62E+05 0.00E+00 4.93E+08-PR-143 12.09E+04 8.40E+63

1.04E+03 0.00E+00-4.85E+03 0.00E+00 9.17E+07 ND-147 7.08E+03 8.18E+03 4.90E+02 0.00E+00-4.79E+03 0.00E+00 3.93E+07 l

76.0 2171c

n l MUClear TMI R atoto,1c.1 Controte Departmental Procedure 6610-PLN-4200.01 'I Revision No. Title Offsite Dose Calculation Manual (00CM) 1 _l -TABLE 5. 7,.1 9ATHWAY DO5E TACTOp0, Ri AGE GROUP - INFANT PATHWAY: VEGETATION

==.______._____... ORGAN DOSE FACTORS; m2 - mrem / year per pCi/sec =-- NUCLIDE BONE -LIVER T. BC SY THYROID KIDNEY LUNG GI-LLI

== -__ H-3 0.00E+00-0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00t+00 C-14 .0.00E+00-0.00E+00 0.00E+0C 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CR-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00-0.00E+00 hN54 -0.00E+00 0.00E~00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 000E+b0 .FE-55 0.00E+00 0.00E+00 0.00E+0G 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 co-58' O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 co-60' O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00-0.00E+00 NI-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00-0.00E+00-ZN 0.0GE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .0.00E+00 0.00E+00 0.00E+00 SR-89 0.00E+00' 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR-90 -0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 0.00E+00 0.00E+00

0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2R-55 0.00E+00-0.00E+00 0.00E+00 0.00E+00.

0.00E+00 0.00E+00 0.00E+00 NB-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .L 10E+00 0.00E+00 0.00E+00 'RU-103 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.-)E+00 0.00E+00 0.00E+00 RU-106 0.00E+00 0.00E+00 0.00E+00 0.00E+00-0.00E+00 0.00E+00 0.00E+00-AG-110M- -0.00E+00 0.00E+00 0.00E 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-125M 'O.00E+00 0.00E+00 0.00E+00 0.00E+00-0.00E+00 0.005+00 0.00F+00 TE-127M : 0.00E+00 0.00E+00-0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .TE-129M 0.00E+00 0.00E+00- -0.00Ev00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 0.00E+00 0.00E+00 ?.00E+00 0.00E+00 0.00E+00 0.00E+00' O.00E+00 I-133- .O.00E+00 .0.00E+00 C,00E+00 0.0C3+00 0.00E+00 0.00E+00 0.00E+00 CS-134 0.00E+00 0.00E+00: 0.00E+00 'O.00E+00 .0.00E+00 0.000:00 ^ ^^o^ CS-136 0.00E+00 0.00E+00' O.00E+00 0.00E+00 9.00E+00 0.00E+00 0.00E+00 .CE-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00~ 0.00E+00 0.00E+00 i CE-141 0.00E+00 0.00E+00 0.00E+00 C.00E+00 0.00E+00 0.00E+00 0.00E+00 L CE-144 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00-- 0.00E+00 0.00E+00 -PR-143. 0.00E+00 0.00E+00 0.00E+00 0.00E+CO 0.00E+00 0.00E400 0.00E+00 -ND-147 0.00E+00 .C.00E+00. 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 _1__ 77.0 2171c

Number k k4 Nuclear Tx1 Ra 1o1,1ca1 cener 1s 6610-PLN-4200.01 Departmental Procedure Revision No. Tit 1e 1 Offsite Dose Calculation Manual (ODCN) TABLE a.7.2 PATHWAY DOSE FACTORS, Ri AGE GROUP: CHILD PATHWAY: VEGETATION 2 - mrem / year per pCL/sec ORGAN DOSE FACTORS; m

---

-=- -

-=~~~~=-

-==-----~~~-

NUChIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI =------------------- ------ _ - - - = - - H-3 0.00E+00 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 _=. C-14 8.89E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78Ev08 CR-51 0.00E+00 0.00E+00 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+05 -=- -

---

- =

~ MN-54 0.00E+00 6.65E+08 1.77E+08 0.00E+00 1.86E+08 0.00E+00 5.58E+08 FE-55 8.01E+08 4.25E+08 1.32E+08 0.00E+00 0.00E+00 2.40E+08 7.87E+07 FE-59 3.98E+08 6.44E+08 3.21E+08 0.00E+00 0.00E+00 1.87E+08 6.71E+08 __ _,,_--. --E + 00 -_

== 0 00 6.44E+07 1.97E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+08 CO-58 Co-60 0.00E+00 3.78E+08 1.12E+09 0.00E+00 0.00E+00 0.00E+00 2.10E+09 NI-63 3.95E+10 2.11E+09 1.34E+09 0.00E+00 0.00E+00 0.00E+00 1.42E+08 ZN-65 8.12E+08 2.16E+C9 1.35E+09 0.00E+00 1.36E+09 0.00E+00 3.80E+08 RB-86 0.00E+00 4.51E+08 2.77E+08 0.00E+00 0.00E+00 0.00E+00 2.90E+07 SR-89 3.60E+10 0.00E+00 1.03E+09 0.00E+00 0.00E+00 0.00E+00 1.39E+09 -=-------------==_ _ SR-90 1.24E+12 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 Y-91 1.87E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 0.00E+00 2.49E+09 ZR-95 3.86E+06 8.48E+05 7.55E+05 0.00E+00 1.21E+06 C.00E+00 8.85E+08 _ =.---== =-- NB-95 4.11E+05 1.60E+05 1.14E+05 0.00E+00 1.50E+05 0.00E+00 2.96E+08 RU-103 1.53E+07 0.00E+00 5.90E+06 0.00E+00 3.86E+07 0.00E+00 3.97E+08 RU-106 7.45E+08 0.00E+00 9.30E+07 0.00E+00 1.01E+09 0.00E+00 1.16E+10 4.h4E+07 0.00E+00 2.58E+09 AG-110M 3.21E+07 2.17E+07 1.73E+07 0.00E+00 TE-125M 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.00E+00 0.00E+00 3.38E+08 TE-127M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.00E+00 1.07E+09 -- =----- TE-129M 8.40E+08 2.35E+0B 1.30E+08 2.71E+08 2.47E+09 0.00E+00 1.02E+09 I-131 1.43E+08 1.44E+08 8.18E+07 4.76E+10 2.36E+08 0.00E+00 1.28E+07 I-133 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 0.00E+00 1.76E+06 =- CS-134 1.60E+10 2.63E+10 5.55E+09 0.00E+00 8.15E+09 2.93E+09 1.42E+08 CS-136 8.28E+07 2.28E+08 1.47E+08 0.00E+00 1.21E+08 1.31E+07 8.00E+06 CS-137 2.39E+10 2.29E+10 3.38E+09 0.00E+00 7.46E+09 2.68E+09 1.43E+08 _=- -- BA-140 2.79E+08 2.44E+05 1.63E+07 0.00E+00 7.96E+04 1.46E+05 1.41E+08 CE-141 6.57E+05 3.28E+05 4.86E+04 0.00E+00 1.44E+05 0.00E+00 4.09E+08 CE-144 1.27E+08 3.99E+07 6.79E+06 0.00E+00 2.21E+07 0.00E+00 1.04E+10 __=---------- l PR-143 1.45E+05 4.36E+04 7.21E+03 0.00E+00 2.36E+04 0.00E+00 1.57E+08 ND-147 7.15E+04 5.79E+04 4.49E+03 0.00E+00 3.18E+04 0.00E+00 9.18E+07 _=------- l l l 78.0 2171c l l l

U N .TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Dose Calculation Manual (OOCM) TABLE 5.7.3 PATHWAY DOSE FACTORS, R1 AGE GROUP: TEEN PATHWAY: VEGETATION - = = - = - -... _ -..... - - - - - -...... _ - - - - - - -. =_ ORGAN DOSE FACTORS; m2 - mrem / year per pCi/sec

---

====

---~~---- --=- NUCLIDE

---

=

BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI. =. H-3 0.00E+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+C3 2.59E+03 C-14 3.69E+08 7,38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 CR-51 0.00E+00 0.00E+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 =_------...__...--___ MN-54 0.00E+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.00E+00 9.32E+08 FE-55 3.26E+08 2.31E+08 5.39E+07 0.00E+00 0.00E+00 1.47E+08 1.00E+08 FE-59 1.80E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+08 9.91E+0B 0bOE+00 0.00E+0b 6.01E+08 co-58 0.00E+00 4.36E+07 1.01E+08 0.00E+00 C0-60 0.00E+00 2.49E+08 5.60E'08 0.00E+00 0.00E+00 0.00E+00 3.24E+09 NI-63 1.61E+10 1.13E+09 5.45E+08 0.00E+00 0.00E+00 0.00E+00 1.81E+08 -_= ZN-65 4.24E+08 1.47E+09 6.86E+08 0.00E+00 9.42E+08 0.00E+00 6.23E+08 RB-86 0.00E+00 2.73E+08 1.28E+08 0.00E+00 0.00E+00 0.00E+00 4.04E+07 SR-89 .1.52E+10-0.00E+00 4.34E+08 0.00E+00 0.00E+00 0.00E+00 1.80E+09 ER-90 7.51E+11 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2.11E+10 Y-91 7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 0.00E+00 3.22E+09 ER-95 1.72E+06 5.43E+05 3.73E+05 0.00E+00 7.98E+05 0.00E+00 1.25E+09 NB-95 1.92E+05' 1.07E+05 '5.87E+04 0.00E+00 1.03E+05 0.00E+00 4.56E+08 RU-103 6.82E+06 0.00E+00 2.92E4r% 0.00E+00 2.41E+07 0.00E+00 5.70E+08 RU-106 3.09E+08 0.00E+00 3.90E+07 0.00E+00 5.97Ev00 0.00E+00 1.48E+10-AG-110M 1.52E+07-1.43E+07 8.72E+06 0.00E+00 2.74E+07 0.00E+00 4.03E+09 TE-125M 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0.00E+00 4.37E+08 L TE-127M 5.52E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 .0.00E+00 1.37E+09 l l

== TE-129H 3.61E+08 1.34E+0C 5.72E+07 1.17E+08 1.51E+09 C.00E+00 1.36E+0S 'I-131 7.69E+07 1.0BE+08 5.78E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 I-133 1.94E+06 3.29E+06 1.00E+06 4.59E+08 5.77E+06 0.00E+00 2.49E+06 CS-134-7.10E+09 1.57E+10 7.75E+09 0.00E+00 5.31E+09 2.03E+09 2.08E+08 L CS-136. 4.39E+07 -1.73E+08 1.16E+08 0.00E+00 9.41E+07 1.48E+07 1.39E+07 CS-137 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.59E+09 1.78E+09 1.92E+08 f L EA-140 1.39E+08 1.71E+05 8.97E+06 0.00E+00 5.78E+04 1.15E+05 2.15E+08 CE-141 2 83E+05 1.89E+05 2.17E+04 0.00E+00 8.90E+04 0.00E+00 5.41E+08 CE-144 5.28E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.00E+00 1.33E+10 PR-143 6.99E+04 .2.79E+04 3.48E+03 0.00E+00 1.62E+04 0.00E+00 2.30E+08 ND-147 3.62E+04 3.94E+04 2.36E+03 0.00E+00 2.31E+04 0.00E+00 1.42E+08 79.L 2173c

- __ ~ ~. TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No. ~ Title 1 Offsite Dose Calculation Manual (ODCM) TABLE 5.7.4 PATHWAY DOSE FACTORS, Ri AGE OROUP: ADULT PATHWAY: VEGETATION __..._-.___..._---...._ORGAN DOSE FACTORS; m2 - mrem / year per pCi/sec = NUCLIDE

---

=--

BONE LIVER T. BODY THYROID K2DNEY LUNG GI-LLI .... _... _ _ _ _... _ _ _. _ _ _ _ _ -. - - - - - _ _.. _. - - - _ -...... - -. _.. _ _ _.. - - - = - = - =. - _ _ _..... _ _ H 0.00E+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 C-14 2.28E+08 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 -CR-51 0.00E+00 0.00E+00 4.64E+04 2.77E+04 1.02E+04 6.35E+04 1.17E+07 'MN-54 0.00E+00 3.13E+08 5.97E+07 0.00E+00 9.31E?O7 0.00E+00 9.58E+08 FE-55 2.10E+08 1.45E+08 3.38E+07 0.00E+00 0.00E+00 8.08E+07 8.31E+07 7E-59 1.26E+08 2.97E+06 1.14E+08 0.00E+00 0.00E+00 8.29E+07 9.89E+08 '-58 0.00E+00 3.07E+07 6.89E+07 0.00E+00 0.00E+00 0.00E+00 6.23E+08 -60 0.00E+00 1.67E+08 3.69E+08 0.00E+00 0.00E+00 0.00E+00 3.14E+09 sI-63 .1.04E+10 7.21E+08 3.49E+08 0.00E+00 0.00E+00 0.00E+00 1.50E+08 ZN-65 3.17E+08 1.01E+09 4.56E*08 0.00E+00 6.75E+08 0bOE+00 6.36E+08 RB-86 0.00E+00 2.19E+08 1.02E+08 0.00E+00 0.00E+00 0.00E+00 4.32E+07 SR-89 9.98E+09. 0.00E+00 2.86E+08 0.00E+00 0.00E+00 0.00E+00 1.60E+09 -SR-90 6.05E+1? 0.00E+00 1.48E+11 0.00E+00 0.00E+00 0.00E+00 1.75E+10 Y 5.12E+0 0.00E+00, 1.37E+05 0.00E+00 0.00E+00 0.00E+00 2.82E+09-ZR-95 1.17E+06 3.77E+05 2.55E+05 0.00E+00 5.91E+05 0.00E+00 1.19E+09 NB 1.42E+05 7.92E+04 4.26E+04 0.00E+00 7.83E+04 0.00E+00 .4.81E+08 RU-103 4.77E+06 0.00E+00 2.06E+06 0.00E+00 1.82E+07 0.00E+00 5.57E+08 RU-106 1.93E+08 0.00E+00 2.44E+07 0.00E+00 3.72E+08 0.00E+00 1.25E+10 -AG-110M: 1.05E+07: 9.75E+06 5.79E+06 0.00E+00 1.92E+07 0.00E+00 3.98E+09 TE-125M -9.66E+07 3.50E+07 1.19E+07 2.90E+07 ' 3.93E+0B 0.00E+00 3.86E+08 TE-127M 3.49E+08 1.25E+08 4.26E+07-8.93E+07 1.42E+09 0.00E+00 1.17E+09 TE-129M -2.51E+08 9.37E+07 3.97E+07 8.63E+07 1.05E+09 0.00E+00 1.26E+09 I-131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E&O8 0.00E+00 3.05E+07 I-133 2.09E+06 3.63E+06 1.11E+06 5.34E+08 6.33E+06 0.00E+00 3.26E+06 CS-134 4.67E+09' 1.11E+10 9.08E+09 0.00E+00 3.59E409 1.19E+09 1.94E+08 CS-136 4.28E+07 1.69E+08 1.22E+08 0.00Z+00 's.41E+07 1.29E+07 1.92E+07 CS-137-6.36E+09 8.70E+09 5.70E+09 0.00E+00 2.95E+09 9.81E+08 1.68E+08 - - =....... RA-140 1.29E+08 1.62E+05 8.47E+06 0.00E+00 5.52E+04 9.29E+04 2.66E+08 .CE-141 1.97E+05 1.33E+05 1.51E+04 .0.00E+00 6.20E+04 0.00E+00 5.10E+08-CE-144 - 3.29E+07 1.38E+07 1.77E+06 0.00E+00 8.16E+06 0.00E+00 1.11E+10 PR-143 5.25E+04r 2.51E+04 3.10E+03 b.00Z+00 -1.45E+04 0.00E+00 2.74Evo8 ND-147 3.34E+04 -3.85E+04 2.31E+03 0.00E+00 2.25E+04 0.00E+00 1.85E+08 80.0 2171c

_ _ _ - ~-.. -... -.... =- O-Nuclear TM1 Rae1 1 gica1 controis Departmental Procedure 6610-PLN-42OO.Ol Revision No. Title i 1 -Offsite Dose calculation Manual (ODCM) 6.0 TKI-1 GASEOUS WASTE TREATMENT SYSTEM 6.1 Description of the TMI-l Gaseous Radwaste Treatment System.(see Figure 6.1) 6.1.1 Waste cas System -a. Reactor Building - Reactor Coolant Drain Tank (R.DT) header b. Auxiliary Building - Vent Header from 1.'Miscellaneoud Maste Storage Tank (MWST)

2. Three (3) Reactor Coolant Bleed Tanks (RCBT)

- Waste Gas Delay Tank - Two (2) Waste Gas Compressors - Three (3) Watte Gas Decay Tanks (WGDT) Filtration and dilution provided by the Station Ventilation c. -System. 6.2 ' operabilit;y operability of th.2 Caseoue Waste Treatment System is defined as the ability to r'emove gas from the vent header / tank gas spaces and store it under a higher pressure in the Waste Gas Decay Tanks for subsequent release. Except for initiating the make up tank sc.mple and waste gas venting and the recycle or disposal of compressed waste gasas stored in the waste gas decay tanks, the operation of the waste gas system is entirely automatic. One waste. gas compressor comes on automatically, removing gasee.from the vent header _ system as required, to maintain the pressure in the system at a maximum of about 16.4 psia. d 81.0 2171c

_m ...m-.,m _._.2 ... _ _ ~..- h 4>Q l 40 9 a@j'en s t IMAGE EVALUATION i / [g+ #. - p v[/* ' \\//q//7 4 \\ T TEST TARGET (MT-3) pe k? $r, 1.0 g m 812

M gn tu m

M kN l,l ll l.25 F !.4 1.6 .L. i 4 150mm d ow s N l 4 % p/p or s Af>.,,%&pf ;/ / gr/m h<4 ++fs,p r-g +3o;,/ p p v. -Cisul i -. A in,2wydj u-

. _ z

7;- 99 +o*$' %ib* l0 9c e IMAGE EVALUATION e@s o

• s W,.. Vp Q7

/g "t[ gk TEST TARGET (MT-3) / gy//,y> k%,,,,~jgc + s I.0 l2 M M i w m g=n " gu \\ l,l fC bb l I.8 l=== l.25 1.4 - l 1.6 4 4 150mm 4-6" i 4,NI,#4fx [ f4 > ~ = ,.,f, w >. uy w .g ggHu ~ 4 e,

• (h'<$t'

.Oy jj 46 s pg $EY:, s -suuudSU$Yh$ =j-w a. c

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 ~'tle Revision No. Ti Offsite Dose Calculation Manual (ODCM) 1 FIGURE 6.1 WASTE CAS SYSTEM P asses:na muses eenens utast aa seems l es ts ul ses.e l sea e4 o v n n as,eaans l l t u -.s.... s.a.,, vass a taas e ime sisaans ues I o ts .a b wes ess ta vanisaius -C4 easis sas sent taas sius wens sataas i, .6

Mp asageassa N

a_. ses vos to to 34 I Y I.asu waste nas esses saa oestt aas var, sam res v : s g usar sans usassees suas sans e a /; y ..f]..,,,jop,...p3 a_, l_ f I l B2.0 2171c I

_ = _ _ _ _ _ _ Nuclear TM1 sadio1 gica1 Cont ote Departmental Procedure 6610-PLN-4200.01 Revision No. 716tle I Offsite Does calculation Manual (ODCM) t 7.0 'rMIMS R*OIOLOGICAL ENVIROIOSETAL MONI'IORING PROGRAM (REMP) 7.1 Monitoring Program Requirements 7.1.1 controls In accordance with the TMI-l Tech. Specs. and THI-2 Tech. Specs., the radiological environmental monitoring program shall be conducted as specified in Table 7.1. 7.1.2 Applicability At all times. 7.1.3 Action With the radiological environmental monitoring program not being a. conducted as specified in Table 7.1, prepare and submit to the Commission in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. ith the level of radioactivity as the result of plant effluents in an W b. environmental sampling medium exceeding the reporting levels of Table 7.2 when averaged over any calendar quarter, prepare and submit to the Commicsion within 30 days from the er.d of the affected 4:indar quarter, a special report that identifias the cause(s) for exceeding the limit (s) and definsa the corrective actions to be taken to reduce radioactive effluents so.that the potential annual dose

• to a member of Q

the public is less than the ralandar year limits of TMI-l Tech. Spec. Section" 3.22.1.2, 3.22.2.2, 3.22.2.3 ar.d ODCM Part II, See. ions 2.1.1.3F, 2.1.2.3I, and 2.1.2.3J. When more than one of the radionuclidea in Table 7.2 are detected as the result of-plant effluents 3 in the sampling medium, this report shall be submitted if i. I concentration (1) +- concentration (2) +...> 1.0 -reporting level (1) reporting level (2) When radionuclides other than those in Table 7.2 are detected and are-the' result of plant effluents, this report shall be submitted if the l- . potential-annual dose

• to a member of the public is equal to or greater than-the calendar year limits of TMI-l Tech. Spec. Sections 3.22.1.2, 3.22.2.2, 3.22.2.3 and-ODCM Part II, Sections 2.1.1.3F, 2.1.2.3I, and 2.1.2.3J.

This report is not required if the measvred level of radioactivity was not the result of plant affluents however, in such an event, the condition shall be reported and describet in the Annual p Radiological Environmental Operating Report. The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report. 83.0 2171c

• wr-

1

• L)INuclear Tx1 Radt 1 gica1 Co,tro1s Departmental Procedure 6610-PLN-4200.01 Revision No.

Title 1 Offsite Dose Calculation Manual (ODCM) l With milk or fresh leafy vegetables samples unavailable from one or more c. of the sample locations required by Table 7.1, prepare and submit to the Commission, within 30 days, a special report which identifies the cause of the unavailability of samples and identifies the locations for obtaining replacement samples. Add the new locacions to the radiological environmental monitoring program within 30 days. The locations from which saxples were unavailable may then be deleted from the monitoring program. Idertify the cause of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Semi-annual Radicactive Effluent Release Report and also include in the report a revised figure (s) and table (s) from the ODCM reflecting the new locations. 7.1.4 Bases The radiological monitoring program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exrosures of members of the general public resulting from the station operation. This monitoring program implements Section IV B.2 of Appendix I to 10CTR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurtments and modeling of the environmental l exposure pathways. Guidance for this monitoring is provided by the l Radiological Assessment Branch Technical Position on Environmental Monitoring (Revision 1, November 1979). Program changes may be initiated based on operational ex trience. 7.1.5 Surveillance Requirements The radiological environmental monitoring samples shall be collected pursuant i to Table 7.1, from the specific locations given in Tables 7.4 through 7.10 and Maps 7.1 throrgh 7.3, and shall be analyzed pursuant to the requirements of Table 7.1 and the detection capabilities required by Table 7.3. l l l l 84.0 2171c

PUINuclear TMI Radiological Controls Departmental Procedure 6610-PLN-42OO.01 Revision No. Title Offeite Dose Calculation KAnual (ODCM) 1 7.2 Land Use Census 7.2.1 gentrole In accordance with the TMI-l Tech. Specs. and TMI-2 Tech. Specs., a land use census shall be conducted during the grazing season and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological 2 sectors the nearest milk animal, the nearest garden

• of greater than 50 m (500 f t ) producing broad leaf vegetation, and the nearest residence.

2 7.2.2 Agplicability At all times. 7.2.3 Action a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in THI-l Technical Specification 4.22.2.3 and ODCM Part II, Sections 2.1.1 and 2.1.2, prepare and submit a special report to the Commission within 30 days which identifies the new location (s). Identify the new location (s) in the next Semi-Annual Radioactive Effluent Release Report. b. With a land use census ? dentifying a location which yields a calculated dose or dose coemitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Table 7.1, add the new location (s) to the radiological environmental monitoring program within 30 days. Submit a special report to the Commission within 30 days which identifies the new locations (s). The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pathway) ay be deleted from the monitoring program after October 31 of the year v. which the 1&nd use census was conducted. Identify the new location (s) in the next Semi-Annual Radictctive Ef fluent Release Report and also include in the report a.. vised figure (s) and table (s) from the ODCN reflecting the new location (s). 7.2.4 Bases This Control is provided to ensure that changes in the use of unrestricted areas are identified and modifications to the monitoring program are made if required by the results of this census. The best information from the docr-to-door survey, aerial surveys, 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 50. Restricting the census to gardens Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two dif ferent sectors with the highest predicted D/Qs in lieu of the garden census. Requiremente for broad leaf sampling in Table 7.1 shall be followed, including analysis of control samples. 85.0 2171c

I'- L)] Nuclear

m Raeio1ogica1 ce=tro1s Departmental Procedure 6610-PLN-42OO.01 Revision No.

Title Offsite Dose Calculation Manual (ODCM) 1 of greater than 500 square feet (50 m ) provides assurance that significant 2 exposure pathways via leafy vegetables will be ide..tified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minLmum garden size, the following assumptions were used:

1) that 20% of the garden was used for growing broad leaf vegetation (i.e.,

similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter. 7.2.5 Surveillance Requirements The land use census shall be conducted at least once per 12 months, between the dates of June 1 and October 1, using the information that will prcvide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agricultural authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report. l l I l l l 86.0 2171c i l l

k L)1 Nuclear TMI Raeio1 gica1 contro1s Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Doon Calculation Manu.5.1 (ODCM) 1 7.3 Interlaboratory Comparison Program 7.3.1 Controle In accordance with the TMI-l Tech. Specs. and TMI-2 Tech. Specs., analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission (NRC). Only those samples and analyses which are required by Table 7.1 sha.ll be performed. 7.3. 2 Applicability At all times. 7.3.3 Action With analysis not being performed as required above, report the corrective action taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. 7.3.4 Bases The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on precision and l accuracy of the measurements of radioactive material in environmental sample matrices are performied as part of a quality assurance program for l l environmental monitoring in order to demonstrate that the results are l reasonably valid for the purpose of section IV, B.2 of Appendix I to 10 CFR 50. 7.3.5 Surveillance Requirements l A summary of the Interlaboratory Comparison Program results shall be included in the Annual Radiological Environmental Operating Report. i l l 87.0 2171c

. -...~. -..-~. v. - - - ~..,. -.~ ... _.... ~... - -.. =. NN TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 1 ~Offsite Dome Calculation Manual (ODCM) i ~ TABLE 7.1 -f 1 - SAMPLE COLLECTION AND ANALYSIS REQUIREMENTS Numbwr of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample-Sample Locations

• Collection Frequency of Analysis
• 8

1. Airborne Radioiodine and' Samples from 5 Continuous sampler Radiciodine Particulates locations from operation with sample Canister Table 7.4.

-collection weekly, or Analyze weekly for more frequently if 1-131. required by dust ~ Particulate Filters loading. Analyze for gross beta radioactivity following filter-d change. Perform gamma isotopic analysis

• on composite (by location)'eample i

quarterly. y' I. Direct . Samples from 40 Sample Quarterly Analyze for ganna l Radiation

• locations-from dose quarterly.

Table 7.5 (using either 2-dosimeters or at i l< 1 east 1 instrument for. continuously measuring and-recording dose rate at each location). 1 88.0 2171c

h TMI Radiological Controls 6610-PLN-42OO.01 l Departrental Procedure Revision No. Title 1 Offsite Dose calculation Manual (ODCM) TABLE ".1 (Cont'd) SAMPLE COLLECTION AND ANALYSIS REsJIREMENTS Number of Samples Samp ung mul Type and Frequency l d Collection Frequency

• of Analysin and Exposure Pathway Sample Locations" and/or Sample

3. Waterborne Samples from 2 Composite 8 sample Perform gamma isotopic analysis

• f over 1 monthly

a. Surface locations from monthly. Composite 1 Table 7.6.

period. L for tritium analysis quarterly. l 1 sample from I downstream (indicator) location 1 sample from upstream (control) location (or location not influenced by the station discharge) Perform gross beta

b. Drinking Samples from 2 Compositei sample and gamma isotopic over 1 monthly locations from analysis' monthly.

Table 7.6. period. Perform Sr-90 analysis if gross

• 1 sample at the beta of monthly location of the composite >10 times nearest water control. Composite supply that could for tritium be affected by the analysis quarterly.

station discharge.

• 1 sample from a control location.

Perform gamma

c. Sediment from Samples from 2 Sample twice per year isotopic analysis *

(Spring and Fall), on each sample. Shoreline locations (1 the interval not to Control and 1 exceed 184 days. Indicator) from Table 7.7. 2171c 89.0 1 - - _ _ ~ ~

humber L Nucleair m padioto,1ca1 cent,o1s Departmental Procedure 6610-PLN-42 00. 01 Revision No, Title Offsite Dose Calculation Manual (ODCM) 1 TABLE 7.1 (Cont'd) SAMPLE COLLECTION AND ANALYSIS REQUIREMENTS Number of Samples l Exposure Pathway and I Sampling and Type and Frequency and/or Sample Sample Locations

• Collection Frequency of Analysis' b

4. Ingestion

a. Milk Samples from 4 Sample semimonthly Perform gamma locations from when animals are on isotopic analysis' Table 7. 8.

pasture; monthly at and I-131 analysis other times. on each sample. Composite for Sr-90 analysis quarterly, b. Fish Samples from 2 Sample twice per year Perform gamma locations from (Spring and Fall), isotopic

• and Sr-90 Table 7.9.

the interval not to analysis on edible exceed 184 days. portions. = 1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators in the vicinity of the station discharge. 1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators from an area not influenced by the station discharge. i l l l l 1 90.0 2171c l l l l

' L)1 Nuclear TxI nadio1ogica1 contro1s Departmental Procedure 6610-PLN-42OO.01 Revision No. 1 Offsite Dose Calculation Manual (ODCM) TABLE 7.1 (Cont'd) ' SAMPLE COLLECTION AND ANALYSIS REQUIREMENTS l i i Number of Samples and Sampling and Type and Frequency Exposure Pathway and/or Sample Sample Locations

• Collection Frequency" of Analysis"

c. Food Samples from 2 Sample at t ime of Perform gamma Products locations from harvest.

isotopic", I-131, and Sr-90 analysis Table 7.10 (when on edible portions. available) 1 sample of green leafy vegetables or leafy vegetation at a location in the immediate vicinity of the station. (indicator) = 1 sample of same specica or group from a location not j influenced by the station discharge. Samples from 4 Sample fruits and Perform gamma locations (3 vegetabler at time isotopic analysis" indicator and 1 of harvest. on edible portions. control) from t Table 7.10 (when available). l 91.0 2171c

THI Radiological Controls f Departmental Procedure 6610-PLN-42OO.01 j Ravision No. Title. 1 of fsite Dose calculation Manual (CDCM) TABLE 7.1 (Cort'd) SAMPLE COLLECTION AND ANALYSIS REQUIREMENTS TABLE NOTATION Sampling locations are provided in Tables 7.4 through 7.10. They are depicted in a. Maps 7.1 through 7.3. Deviations are permitted f rom the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, All malfunction of automatic sampling equipment and other legitimate reasons. deviations from the sampling schedule shall be explained in the Annual Radiological Environmental Operating Report. b. Frequency notations weekly (7 days), sanimonthly (1S days), monthly (31 days), and quarterly (92 days).. All surveillance requirements shall be performed within the specified time interval with a maximum allowable extension.not to exceed 25% of the surveillance interval. A total maximum combined interval time for any 4 consecutive. tests shall not exceed 3.25 times the specified collection or analysis interval. c. One or more' instruments, such as a pressurized ion chamber for measuring and recording dose rate continuously, may be used in place of, or in-addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dostmeter (TLD).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 as dowimeters for measuring direct radiation. - Airborne particulate sample filters shall be analyzed f or gross beta radioactivity d. If 24 hours or more after sampling to allow for radon and thoron daughter decay. gross beta activity in an air particulate sample (s) is greater than ten times the calendar year mean of control samples, Sr-90 and gamma isotopic analysis shall be performed on the individual sample (s). Gamma isotopic enalysis mee_ns the identification, and quantification of gamma-e. emitting radionuclides that may be attributable to the ef fluents ufran the facility. The " upstream sample" shall be taken at a distance beyond significant influence of f. [ the discharge. _The " downstream sample" shall!be taken in an area beyond but near the mixing zone, Composite sample-aliquots shall be collected at time intervals that are short g. (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample. 92.0 2171c

I' L)] Nuclear TM1 maoio1ogica1 Centro 1s Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Dose Calculation Manual (ODCM) TABLE 7.2 REPORTING LEVELS FOR RADIOACTIVITY CONCFNTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Watar or gas Fish Milk Food Products Analysis (pci/L) (pCi/m ) (pci/kg, wet) (pCi/L) (PCi/kg, wet) 3 H-3 20,000(*) Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Sr-90 8 0.1 100 8 100 Zr-Nb-95 400 I-131 2 0.9 3 100 cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 300 (*I or drinking water samples. This is 40 CFR Part 141 value. F f i l 93.0 2171c i l

TMI Radiological Controls Departmental Procedure 6510-PLN-4200.01 Revision No. Title 1 Offeite Dose Calculation Manual (ODCM) TABLE 7.3 I DETECTION CAPABILITIES FOR EKVIROKMENTAL SAMPLE ANALYSIS

• _LORER LIMIT OF DETECTION (LLD)b

u, \\ Airborne Particulate Fish Food Sediment Water or Gas (pci/kg, Milk Products (pci/kg, Analysis (pci/L) (pci/m ) wet) (pci/L) (pci/kg, wet) dry) 3 Gross Beta 4 0.01 H-3 2000 Mn-54 15 130 Fe-59 30 260 co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Sr-90 2 0.01 10 2 10 Nb-95 15 I-131 1 0.07 1 60 8 Cs-134 15 0.05 130 15 60 150 Ca-137 18 0.06 150 14 80 180 Ba-140 60 60 La-140 15 15 l I l l l I 2171c 94.0 i i

Numbet NUCIMf TMI Radiological Controla Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Pose Calculation Manual (ODCM) TABLE 7.3 (Cont'd) \\ DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS' TABLE NOTATION This list does not mean that only these nuclides are to be considered. Other geaks a. that are identifiable, which may be related to plant operations, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report, Required detection capabilities for thermoluminescant dosimeters used for b. environmental measurements are given in Regulatory Guide 4.13 (Rev. 1). c. 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 radicchemical separation): LLD = 4.66 as E *V= 2.22 = Y

• erp (-lat)

Where: LLD is the "a priori" lower limit of detection as defined above, as picoeuries per unit mass or volume, s, is the standard deviation of the background counting rate or of the counting rste of a blank sample as appropriate, as counts por minute, E it the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintsgrations per minute per picoeurie, Y is the fractional radiochemical yield (when applicable), 1 is the radioactive decay constant for the particular radionuclide and At for environmental camples 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. It should be recognized that the LLD is defined as an "a priori" (befort the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDe will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small samples sizes, the presence of interfering nuclides, or other urcont rollable circumstances may render these LLDs unachievable. In such cases, thn contributing factors shall be identified and described in the Annual Radiological Invironmental Operating Report. I d. LLD for drinking water. 95.0 2171c 1

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Doce calculation Manual (ODCM) TABLE 7.4 TMINS RE"P STATION LOCATIONS-AIR PARTICULATE AND AIR IODINE Station Code Distanco (miles) Azimuth (*) Map No. B1-4 0.8 28 60 El-2 0.4 95 2 F1-3 0.6 105 70 G2-1 1.4 125 75 M2-1 1.3 253 3 A3-1 2.6 358 4 H3-1 2.3 159 5 J3-2 2.9 181 71 Q4-1 3.5 325 92 G10-1 9.8 127 6 J15-1 12.6 180 7 Q15-1 13.5 305 8 nmm. TABLE 7.5 TMINS REMP STATION LOCATIONS-DIRECT RADIATION (TLD) Station C(de Distance (miles) Azimuth (*) Map No. Al-1 0.4 0 1 Al-4 0.3 5 9 B1-1 0.6 25 10 B1-2 0.4 26 11 B1-3 0.5 15 12 Cl-2 0.3 54 13 D1-1 0.2 74 14 El-1 0.2 95 15 El-2 0.4 95 2 El-4 0.2 9a 16 F1-2 0.2 109 17 G1-3 0.3 129 18 H1-1 0.5 167 19 H1-9 0.3 167 20 J1-1 0.8 184 21 J1-3 0.3 189 22 J1-4 0.4 188 23 I Ki-4 0.2 208 24 K1-5 0.2 202 25 l L1-1 0.1 235 26 l. M1-1 0.1 249 27 N1-3 0.1 270 28 P1-1 0.4 293 29 P1-2 0.2 290 30 2171C 96.0

m,e, MNuclear 7;;g;1;;r;;;;;';;- ee10- - -42= ot Revision No. Title Of f site Dose calculation Manual (ODCM) 1 TABLE 7.5 (Cont'd) TMINS REMP STATION IX. CATIONS-DIRECT RADIATION (TLD) Station Code, Distance (miles) Azimuth (*) Map No. Q1-2 0.2 318 31 R1-1 0.2 335 32 C2-1 1.6 48 33 K2-1 1.1 200 34 M2-1 1.3 253 3 A3-1 2.6 358 4 H3-1 2.3 159 5 i R3-1 2.6 338 35 l B5-1 4.8 18 36 CS-1 4.5 42 37 ES-1 4.6 81 38 F5-1 4.7 107 39 G5-1 4.8 131 40 H5-1 4.1 157 41 J5-1 4.9 182 42 K5-1 5.0 200 43 L5-1 4.1 228 44 MS-1 4.3 249 45 NS-1 4.9 268 46 P5-1 4.9 285 47 QS-1 5.0 318 48 RS-1 4.9 339 49 D6-1 5.2 65 50 E7-1 6.8 86 51 Q9-1 8.5 308 52 B10-1 9.4 21 53 G10-1 9.8 127 6 G15-1 14.4 124 54 J15-1 12.6 180 7 Q15-1 13.5 305 8 R15-1 12.4 329 55 l t l l l 97.0 2171c

L JNuclear Ts1 madtete,1ca1 contro1, Departmental Procedure 6610-PLN-4200.01 Revision No. i Title 1 _ Offeito Dese calculation Manual (ODCH) i TABLE 7.6 TMINS BIMP STATION LOCATIONS-SURFACE WATER Qation Codo Distance (miles) AzLmuth (*) Map No. P1-3 (R) 0.1 284 56 J1-2 (R) 0.5 188 57 J2-1 (R) 1.5 182 58 A3-2 (R) 2.5 355 59 H5-2 (F) 4.2 157 61 Q9-1 (F) 8.5 308 52 G15-1 (F) 14.4 124 54 G15-2 (F) 13.6 128 62 G15-3 (F) 14.6 124 63 J15-2 (F) 14.7 178 64 F15-1 (R) 12.6 122 65 (R) = Raw Water (F) = Finished Water TABLE 7.7 TMINS REMP STATION LOCATIONS-AQUATIC SEDIMENT I Station Code Distance (miles) Azimuth ('i Map No. Al-2 0.8 6 66 Al-3 0.5 0 67 G1-1 0.3 137 68 K1-3 0.3 202 69 J2-1 1.5 182 58 l 98.0 2171c

q ENuclear TM1 maaio1,1ca1 controis Departroenta1 Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Dotia Calculation Manual (ODCM) TABLE 7.8 TMINS REMP STATION LOCATIONS-MILK Station Code Dintance (miles) Azimuth (*) M_ap No. A2-1 (MG) 1.2 5 72 A15-2 (MG) 14.2 9 73 D2-1 (M) 1.1 65 74 G2-1 (M) 1.4 125 75 P "/ - 1 (M) 6.7 293 76 K15-2 (M) 12.8 208 77 F3-1 (M) 2.3 104 78 EO-2 (H) 1.1 93 79 A4-1 (M) 3.3 10 93 (MG) = Goat Milk (M) = Cow Milk TABLE 7.9 TMINS REMP STATION LOCATIONS-FISH Station Code Station Lov tion TM-AQF-IND Downstream of Station Discharge TM-AQF-BKG Upstream of Station Discharge AQF = Fish l I l l l 1 l 99.0 2171c

N THI Radiological Controls Departrnental Procedure 6610-PLN-4200.01 Revicion No. Titla 1 Offelte Dose Calculation Manual (ODCM) ) TABLE 7.10 THINS REMP STATION LOCATIONS-FOOD PROCUCTS Station Code Dirtance (miles) Azimuth (*) Map No_. l D2-1 1.1 65 74 G2-1 1.4 125 75 A9-2 9.3 357 80 P3-1 2.6 293 81 A15-1 10.5 10 82 El-3 0.7 90 83 E2-1 1.1 80 84 H1-2 0.9 150 85 E6-1 5.9 100 86 M15-2 13.6 253 87 D1-3 0.5 65 88 A2-1 1.2 5 72 P7-1 6.7 293 76 K15-2 12.8 208 77 A15-2 14.2 9 73 F3-1 2.3 104 78 E2-2 1.1 93 79 B15-1 10.3 12 89 EA 2 0.4 95 2 R15-2 12.4 329 55 F1-1 0.5 117 91 J2-2 1.5 178 90 A4-1 3.3 10 93 M2-2 1.3 252 94 N2-2 1.3 265 95 U1-3 0.7 150 96 100.0 2171c

4 Nuclear TMI R.eto1 0tc.1 coot,o1. Departmental Procedure-6610-PLN-4200.01 Title Revi. ion No. Offsite Dose Calculation Manual (ODCM) 1 l N ,,. s . ses.7s i 3 \\ \\, i san.ts \\ ) A\\ MeLL R N',, * ' ss. n McMay i v. e (,%+,,.5p*\\ 4=-y coqMoem is. ) 4 0 7s.ts w s-I / "'3 0, 1 , s,.,, Od c 0 Y )p- ( ragn k) ?,V I j' O-j.,, 4" p,,,.,, i m f 250.1 }n u T E WLE AN CH A 3 fi3,7 5 r*

• H S 4

k sts.tv e \\ kS x a N PAP 1 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PkUGRAM 5fATICh5 WITHIN 1 MILE OF THF $1TE t MAP 7.1 THREE MILE ISLAND NUCLEAR STATION LCCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 1 MILE OF THE SITE i 101.0 2171c

r ~.... _ Nuclear mI R.diot o 1 Comt,,1. Departmental Procedure 6610-PLN-42OO.01 Revision No. Title 1 Of f site Dose calculation Manual (ODCM) l l N 8 g 0 0 a \\ ~ * * ,/ ~=~ \\ Ng N, x n, ,/ \\ "** U dp u% \\ d 6 5, wN -/ s i Loucometen?.\\\\ x d 'l /.g[M..., [,,. / m;.-

d c\\

) t ~ j 7 (?5 t = Q' /, f j3 'g'k'l5 )8 . / (3 i raborN /* i 65

• t i

/ u . *5 p I I .n NEWSERRY / \\ 4 l \\ ,/ /,, ./.. f \\'*.,-.. 5 .y 1 MAP 2 c THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIR0flMENTAL MONITORING FPCGPA61 STATIONS WITHIN 5 MILES OF THE SITE l 1 MAP 7.2 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITEIN 5 MILES OF THE SITE 102.0 2171c

Nuclear TMI maet 1,1ca1 cootrois Departmental Procedure 6610-PLN-42OO.01 Revision No. Title. 1 l offsite Dose calcu1ation Manua1 (ODCM) 1 4 F 1

== a i f \\o N

• r e

n 1 55 .oa 3.- ,3 l k* "T ~ ea S 12\\ o a- ,l' ,,,s.,,, / g mi.. e un am e...., \\ ) t {- d I k c., - .g = l" sa /r =m l. l b /

== /O f S . rp a e t 3 / \\ ~~ M l ~ .s. 4 r4AP 3 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RA010 LOGICAL ENVIRONMENTAL MONITORING PROGRAM r. STATIONS GREATER THAN 5 MILES FROM THE SITE -_l MAP 7.3 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGBAM ' STATIONS GREATER THAN 5 MILES FROM THE SITE I-103.0 2171c l l l

i TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No. j Title 1 Offsite Dose Calculation Manual (ODCM) 80 PART I REFERENCES 1. EPRI NP-3B40, RP 1560-3 Final Report, " Environmental Radiation Doses From Difficult-To-Measure Nuclides," January 1985 2. " Evaluation of the Three Mile Island Nuclear Station Unit 1 to Demonstrate Confccmance to the Design Objectivos of 10 CFR 50, Appendix 1," Nuclear Safety Associates, May 1976 3. TMI-1 Final Safety Analysis Report (FSAR) 4. TMI-2 Final Safety Analysis Report (PSAR) 5. Meteorological Information and Dose Assessment System (MIDAS) 6. NUREG-0017, " Calculation of Reloases of Radioactive Ma's-ials in Gaseous and Liquid Effluents from PWR," Revision 1, 1985 7. NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978 8. NUREG-0172, " Age-Specific Radiation Dose Commitment Factors For A One-Year Chronic Intaxe," November 1977 9. Regulatory Guids 1.21, " Measuring, Evaluating, and Reporting Radioactivity in i Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nucient Power Plants," Revision 1, i June 1974 10. Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releanes of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October 1977 f 11. Simplified Environmental Ef fluent Dosimetry System (SEEDS) l 12. TMI Recirculation Factor Memos, April 12, 1988 and March 17, 1988 13. rMI-1 Operations Procedure, 1101-2.1, " Radiation Monitor Set Points" 14. Title 10, Code of Federal Regulations, " Energy" 15. TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50 l 16. 7MI-2 Operating Procedure 4210-OPS-3661.02, " Radiation Monitor System Setpoints" and 17. Regulatory Guide 1.111, " Methods for EstOmating Atmospheric Transport Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977 104.0 2171c

~~ I' L)INuclear TM1 Radio 1o,1ca1 cent o1s Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Dose Calculation Manual (ODCM) 18. TMI-2 Recovery Technical Specifications, attached to Facility Operating License No. DPR-73 19. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 20. Title 40, code of Federal Regulacions, " Protection of Environment" 21. Regulatory Guide 4.13, " Performance, Testing, and Procedural Specifications for Thermoluminescence DonLmetry: Environmental Applications," Revision 1, July 1977 i l i i 2171c 105.0

Number Nb N TMI Radiological Controls Departmental Procedure 6610-PLM-4200.01 Revision No. Title Offsite Dose Calculation Manual (ODCM) 1 PART II TMI-2 RADIOLOGICAL EFFLUENT CONTROLS 1 l l l l l 1 106.0 2226c

m: 1 (UClear TNI Radiological Controis Departmental Procedure 6610-PLN-42OO.01 ~Eitle Revision No. Offsite Dose Calculation Manual (ODCM) 1 PART II DEFINITIONS 1.0 DEFINITIONS e DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part II of the ODCM. FACILITY MODE-3 1.2 FACILITY h0DE 3.is the current condition of TMI-2 and corresponds to the L following plant conditions: The Reactor Vessel and Reactor Coolant System have been defueled to the a. extent _ reasonably achievable. b. The po.sibility of criticality in the Reactor Building is precluded. There are no canisters centaining core material acored on the TMI-2 [.. -c. oite. ACTION 1.3 -ACTION shall be those additional requirements specified as corollary statements.o each control and'shall be part of the controls. OPERABLE - OPERABILITY 1.4 A system, subsystem, train, component or device shall be CPERABLE or have 3 OPERABILITY.when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all_necessary l-attendant instrumentation, controls, normal and emergency einctrical power j sources, cooling or seal water, lubrication or othesr-auxiliary equipment, L -that are required for the system, subsystem, train, component or device to K l perform its function (s), are also capable of perfonning their related support L function (s). l tz CHANNEL CALIBRATION l: 1.5 A CHANNEL CALIBRATION shall be the adjustment, as'necessary,.of-the channel l output'such that it responda.with necessary range and accuracy to known l-values of the parameter.which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions,- cnd shall -include the CHANNEL EONCTIONAL TEST. CHANNEL-CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that tbs entire chasinal' is. calibrated. l' [ l 107.0 2226c l

?-MNuclear Ts1 Radio 1o,1ca1 Cemtro1< Departmental Procedure 6610-PLN-4200.01 Revision No. Title offaite Done,calculat_ ion Manual (oOCH) 1 CP\\NNEL CHFCK 1.6 A CHANNEL CHECK shall be the qualitative asseusmer.t of channe) behavior during operation by observation. This determination shall include, where possible, camparison of the enannel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parimeter. = - = = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE: For radioactive effluent monitorp, except for those in Table 2.3-1, this shall include a verification which provides a qualitative assessment of channel response when tha channel sensor is exposed to a r.1dioactive source. l CHANNEL FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shall be Analog channels - the injoction of a simulated signal into the channel a. as c)ose to the prLmary sensor as practicable to verify OPERABILITY including alarm and/or trip functiots. b. Bistable channels - the injection of a e. ed signal into the channel senser to verify OPERABILITY including al.- nd/or trip functions. FREQUENCY NOTATION 1.8 The FRIQUENCY NOTATION specified for the performance of Surveillance Requirements anall correspond to the intervals defined in Table 1.1. COMPOSITE SAMPLE 1.9 A COMPOSITE SAMPLE is a combination of individual samples obtained at regular intervals over a time period. Either the volume of each individual sample is proportional to the low rate discharge at the time of sampling or the number of equal volume samples is proportional to the time period used to produce the composite. GRAB SAMPLE 1.10 A GRAS FAMPLE in an individual sample collected in less than fifteen minutes. BATCH RELEASE 1.11 A EATCH RELEASE is the discharge of fluid waste of a discrete volume. CONTINUOUS RELEASE l 1.12 A CONTINUOUS RELEASE is the discharge of fluid waste of a non-discrete volus-e.g., from a volume or system that has an input flow during the l CONTINUOUS RELEASE. i 108.0 2226c

\\ (UCle8V TM1 naatolostcat co. trois Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 Offsite Dose Calculation Manual (ODCM) TABLE 1.1 FREQUENCY NOTATION NOTATION FREQUENCY S (Shiftly) At least once per 12 hours. D (Daily) At least once per 24 hours. W (Weekly) At least once per 7 days. M (Monthly) At least once per 31 days. Q (Quarterly) At least once per 92 days. SA (Semi-Annually) At least once par 184 days. A (Annually) At least once per 12 months. At least once per 18 months. R N.A. Not applicable. l 1 I l l 109.0 2226c I

. = -. ~. - - _. _ - ~,... THI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No. Title 1 rf fj lte Doso Calculation Manual (Oth.st) SECTIONS 2.0, 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREME).TS 2/3.0 APPLICABILITY cowTacts 2/3.0.1 Controls and ACTION requirements shall be applicable during the conditions specified for each control. 2/3.0.2 Adherence to the requirements of the control and/or associated ACTION within the specified time interval shall constitute compliance with the control. In the event the control is restored prior to expiration to the specified time itierval, completion of the ACTION statement is not required. 2/3.0.3 In the event the control and/rar associated ACTION requirements cannot be satisfied becarse of circumstancas in excess of those addressed in the Control, initiate appropriate actions to rectify the problem to the extent possible under the circumstances, and submit a special report to the Commission pursuant to THI-2 Recovery Technical Spercification (Tech. Spec.) Section 6.9.2 within 30 days unless otherwise specified. sumysILIJusCE REQUIREBIENTS 4.0.1 Surveillance Requirements shall be applicable during the conditions specified {' for indiridual controls unless otherwise stated in an indivioual Surveillance Requirement. The Surveillance Requirements shall be performed to_ demonstrate compliance with the OPERABILITY requiremen"* of the control. 4.0.2 Rach Surveillance Requirement shall be performed within the specified time interval with: A maximum allowable h;. ension not to exceed 25% of the surveillance l a. interval, and b. A total maximum combined i* terval time for any 4 consecutive tests not to exceed 3.25 times the s pcified sur'elllance interval. 4.0.3 Performence'of a Surveillance Requirement within the specified time interval shall cN M;itute compliance with OPERAZILITY requirt nents for a Control and associa wd ACTION statements unless otherwise required by the Centrol. l-l 110.0 2226c l. L. ...u.. .-_._- - -. -. - -... ~,.. _,, _... _ _ -,,, -_ -. - -

THI Radiological Controls Departmental Procedure 6610-PLN-4200.01 -Title Revision No. Offsite Dose Calculation Manual (ODCM) 1 RASES The controls of this section provide the general requirements applicable to each of the Control and Surveillance Requirements. 2/3.0.1 This Control defines the applicability of each Control in terms of the i specified conditione and is provided to delineate specifically when each Control is applicable. 2/3.0.2 This Control defines those conditions necessary to constitute gompliance with the terms of an individual Control and associated ACTION requirement. p 2/3.0.3 This control delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements or when the provisions of the stated ACTION statement are not or cannot be complied with. The intent of this i Control is to require.that inoperable equipment be restored to an OPERABLE status in a prompt manner, that the unit be maintained in stable condittors, and that the Commission be promptly notified of such conditions. 4.0.1 This control provides that surveillanca activities necessary to ensure the Controls are met and will be perforned during the FACILITY MODE or other conditions for which the controls are applicable. 4.0.2 The provisions of this Control provide allowable tolerances for performing surveillance activities beyond those specified in the normal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations. le phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance value and permits the performance of more f requent surveillance activities. The tolerance valuss, taken either individually or consecutively over 3 test intervals, are sufficiently restrictive to ensure that the reliability associated with the surveillance activity is.not degraded beyond that obtained from the nominal specified interval. 4.0.3 The provisions of this control set forth the criteria for determination et -compliance with the OPERABILITY requirements of the control. Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within .the specified time interval. Nothing in this provision is to be construed as I defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance l " wquirement e. 111.0 2226c L,

ENuclear' Number g gi: g g ; :: : : aio - -42ao o2 Revision No. Title Offsite Dose calculation Manual (ODCM) 1 2.0 RADIOIAGICAL RFFLUENT l'SQUIREMENT.1 2.1 Radioactive Discharges 2.1.1 Liquid Effluents --2.1.1.1 OBJECTIVES-To define the limits and conditions for the controlled release of 11guld radioactive effluents to the environs to ensure that these releases are as low as practicable. These releases should not result in radiation exposures to offsite areas greater than a few percent of background exposures. The inntantaneous release rate for all effluent discharges i should be within the limits specified in 10 CTR Part 20. To assure that the releases of radioactive liquide to of fsite areas ineet the "as low as practicable" concept, the following objectives apply: A. The annual total quantity of radioactive materials in liquid waste, excluding tritium and dissolved gases, should not exceed 5 curies per. radioactive waste-producing reactor, and the annual dose to the-wnole body or any organ of an individual should not exceed 3 mrom to the total body and shall be less than or equal to 10 mrom to any organ. B. The annual average concentration of radioactive materials in the effluent from the Mechanical Draft cooling Towere prior to dilution L l' in the Susquehanna River, excluding tritium and dissolved gases, should not exceed 2E-8 pC1/ml. C. The annual average concentration of tritium in liquid waste prior to dilution in the environment should not exceed SE-6 pci/ml. 2.1.1.2 APPLICABILITY Applies to the controlled release of radioactive liquida from TMI-2. 2.1.1.3 CONTROLS A. The radioactivity release concentration in liquid effluents from THI-2 to the environment shall not exceed the values specified in 10 CFR 20, Appendix B, for unrestricted areas.- B. The total release of radioactive liquid effluent from THI-2, l . excluding tritium and noble gases, shall not exceed 10 curies -during any calendar quarter. C. The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process all radioactive liquid wastes prior to this discharge when the activity re3 ease rate will exceed 1.25 curies, excluding tritium and dissolved gases, during any calendar. quarter. 112.0 2226c 1-

l MUClear Tal Radiologteal controle i Departmental Procedure 6610-PLN-4200.01 i Revision No. Title l 1 Offsite Dose Calculation Manual (ODON) l l The maximum radioactivity to be contained in one liquid radwaste D. tank, excluding tritium and dissolved gases, that can be discharged directly, to the environs, shall not exceed 10 curies. hhen the average release rate of radioactive effluents, excluding E. tritium and dissolved games, exceeds 2.5 curies per radioactive waste-producing-reactor during any calendar (Jarter, the lica.tsee i shall notify the NRC within 30 days, identifying the causeo and describing the proposed program of action to reduce such release rates. For the purposes of this control, the HPC, (168 hour) for Xe-133 is l SE-3 pci/ml. The MPC, (168 hour) for Xe-135 is 1E-3 FCi/ml. l The osas or dose commitment from liquid effluents shall be less F. j than or equal to 3 mrom total body and less than or equal to 10 mrom to any organ for the calendar year. l 2.1.1.4 BASES i i L Liquid radioactive waste release levels to unrestricted areas should be l kept "as low as practicable" and are not to exceed the concentration j limits specified it. 10 CFR 20. The controls patvide reasonable assurance that the resulting annaal exposure to an individual in j off-site areas will not exceed the design objectives of Appendix I to 10 CFR Part 50, which were estab'd led as requirements for the cleanup of TMI-2 in the NRC's Statement. Policy of April 27, 1981. This ' assurance is based-on the~ fact that the Susquehanna River will dilute the liquid affluente upon their release from.the site. The affluents will be diluted by a factor of about 250 in the region where finfish can At the l exist (within a one-quarter mile radius.of the discharge point). same time these Controls permit the flexibility of operation,- compatible r with considerations of health and safety, to assure that the public is l provided a dependable source of power under unusual operating conditions, which may temporarily resuit-in higher-than normal releases, but still within the consentration limits specified in 10 CFR 20. It is expected that by using this operational flexibilit.y under unusual t operating conditions, and exerting uvery effort to keep levels of radioactive material in liquid wastes as low to practicable, the annual releases will not exceed a small fraction of the annual average concentration limite specified in 10 CFR 20. Control 2.1.1.3 A. above requires the licenses to limit the concentration of radioactive materials,in liquid effluents from TMI-2 to levels specified in 10 CFR 20, Appendix B, for unrestricted areas. This -Control provides-assurance that no member of the general public can ba exposed to liquids containing radioactive materials in excess of limite considered permissible under the Commission's rules and regulations. l above establishes an upper limit for the release of L Control 2.1.1.3 B. radioactive liquid effluents, excluding tritium and dissolved. gases, of 10 curies during any calendae quarter. The intent of this conteci is to i 2 113.0 2226c ,,._J_ ,_J...._.-._.. a. _ - _ --,_-_-_ -..- -,-.. _,.-... _. _ _ _ _, ~ _ -, -. _, -. - -. _ - - ~ _ - -,, -,-

I L)] Nuclear Ts, nad1 1ogica1 Cont,ois Departmental Procedure 6 610- P LN-42 00. 01 Revision No. Title 1 of f site Dose Calculat ion Manual (ODCM) permit the licensee the flexibility of operation to assure that the public is provided a dependable source of power under unusual operating conditions, whien may temporarily result in releases higher than the levels normally achievable when the unit and the liquid radwaste equipment are functioning as designed. Releases of up to 10 curies during any calendar quarter will result in concentrations of radioactive materials in liqutd ef fluents at small percentages of the limits specified in 10 CTR 20. Control 2.1.1.3 C. requires the licensee to maintain anc operate the evulpment installed in the liquid radioactive waste system to reduce the release of radioactive materials in liquid effluents to ar. Ivw as practicable, consistent with the requirements of 10 CFR 50.36a. Normal use and maintenance of installed equipment in the liquid radioactive system is expected to result in releases of not more than about five curies per year, excluding tritium and dissolved gases during normal operations. In order to keep releases of radioactive materials as low as practicable, the Control requires, as a minimum, operation of equipment whenever the rate of release exceeds 1.25 curies per quarter, excluding tritium and dissolved gases. In addition to Control 2.1.1.3 B., the reporting requirements of Control 2.1.1.3 E. and Appendix A, Section 6.6 c. the TMI-2 Tech. delineate that the licensee shall identify the cause whenever S pec s., the rate of radioactive effluents, excluding tritium and noble gases, exceeds 2.5 curies during any calendar quarter and describe the proposed program of action to reduce such releara rates. This report must be filed within 30 days following the calendar quarter in which the 2.5 curie release occurred. Control 2.1.1.3 F. requires that the dose to offsite personnel be limited to the declgn objectives of Appendix I of 10 CFR Part 50. This will assure the dose received by the public during the cleanup is Tt.e equivalent to or less than that from a normal operating reactor. limits also assure that the environmental impacts are consistent with those assessed in NUREG-0683, the TMI-2 Programmatic Environmental Impact Statement (PEIS). 2.1.2 Gasecun Effluents 2.1.2.1 OBJECTIVES To define the limits and conditions for the controlled release of radioactive gaseous effluents to the environs to ensure that these releases are as low as practicable. These releases should not result in of radiation exposures in of f site areas greater than a few percent l l background exposures. The instantaneous release rate for all effluent I discharge should be within the ILmits specified in 10 C;'R 20. To assure that the release of radioactive gases to offsite areas meet the as low as practicable concept, the release rate of gaseous effluents l result in doses to the public exceeding the design objectives l shall not of Appendix I to 10 CFR Part 50. 114.0 2226c \\

y yp] Nuclear La Tx1,adio1o,1ca1 Cont,o1s Departmental Procedure 6610-PLN-4200.01 Revision No. 'Titie Offeite Dose calculation Manual (DDcM) 1 l 2.1.2.2 APPLICABILITY i Applies to the controlled release of radioactive gases f rom TMI-2. 2.1.2.3 CONTROLS A. The instantaneous release rate of gross gaseous activity except for halogens and particulates with half-lives longer than eight dayc shall not exceed 3 3 jJu j $ 1.5 x 10 mj 23 I (MPC)g i sec where Q is the release rate in pCi/see for isotope 1, and MPC 3 t (pC1/m ) is the maximum permissible concentration of isotop) i as 3 defined in Appendix B, Table II, Column 1 of 10 CFR 20. B. The instantaneous release rate of particulates with half-lives greater than eight days, released to the environs as part of the airborne effluents, shall not exceed 0.3 pCi/sec. C. The release rate of gross gaseous activity shall not exceed: 3 Ju j $ 2.4 x 10' m j 23 (MPC)g 1 see when averaged over any calendar quarter. D. The release rate of particulates with half-lives greater than eight days, shall not exceed 0.024 pC1/ nee. when averaged over any calendar quarter. E. Radioactive gaseous wastes collected in the gas decay tanks shall be held up to a minimum of 45 days, except when the release rate does not exceed: 3 3 Jy g 3 3 x 10 m 1. 13 l\\ j (NPC)3 i sec (noble gases) or 2. 0.003 pCi/sec (particulates with half-lives greater than 8 days) Radioactive gases and particulates purged from the Reactor Building F. shall be filtered through the high efficiency particulate air filters. G. The maximum activity to be contained in one gas decay tank shall not exceed 8800 curies (equivalent to Xe-133). 115.0 2226c I n

i (UCl68r TMI Radiological Controls ~ Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 1 H. When the release rate of radioactive materiale in gaseous wastes, averaged over a calendar quarter exceeds: 1 1. E j,_f,y ) $ 6 x loi imj 1 (NPC)3 i sec (noble gases) or 2. 0.006 pci/sec (particulates with half-lives greater than 8 days) the licensee shall notify the NRC within 30 days, identifying the causes and describing the proposed program of action to reduce such release rates. I. The air dose due to noble gases in gaseous effluents shall be less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation for the calendar year. J. The doce for radioactive (other than noble gaseous effluents) shall be less than or equal to 15 mrom to any organ for the calendar year. L 2.1.2.4 BASES The specified levels provide reasonable assurance that the resulting annual exposure rate from noble gases at any location at the site boundary will not exceed 10 millireme per year. At the same time, these -Controls permit the flexibility of operation, compatible with consideration of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions, which may temporarily result _in higher than the design l-objectivs levels, but still within the concentration limits specified in l 10 CFR 20 and within the design objectives of Appendix I to 10 CFR 50. It is expected that using this operation'al flexibility under unusual operating conditions, and by exerting every ef fort to keep levet.s of radioactive material in gaseous wastes as low as practicable, the annual releases will not exceed a small fraction of the annual concentration l limits specified in 10 CTR 20 and will not result in doses which exceed I the design objectives of Appendix I to 10 CFR 50, which were endorsed as limits for the cleanup of THI-2 by the NRC's Statement of Policy of l April 27, 1981. These efforts c.hould include consideration of meteorological conditions during releases. - The annual objiactives have been developed taking into accoact a combination of system vr.riables including fuel failures, primary system leakage, primary to secondary system leakage, and the performance of radionuclide removal mechanisms. I-131 is not specifically monitored because it has decayed to less than detectable activity since the March 28, 1979 accident. 116.0 2226c I A

Number (t" hj y $N TMI Aadiological Controls Departmental Procedure 6610-PLN-4200.Ol Title Revision No. Offsite Does Calculation Manual (ODCM) 1 Control 2.1.2.3 A., requires the licensee to limit the concentration of noble gases f rom TMI-2 to levels specified in 10 CFR 20, Appendix B, for 3 unrestricted areas. Based on a X/Q of 6.7 x 10** sec/m, this Control provides assurance that no member of the general public would be exposed to radioactive materials in excess of limits specified in the Commission's rules and regulations. Control 2.1.2.3 B., requires the licensee to limit the concentration of particulates with half-lives greater than eight days, released from THI-2 to unrestricted areas to levels such that no individual will receive more than 500 mrem /yr to the total body or 3000 mrem /yr to the skin. The absence of iodine ensures that the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway is less than or equal to 1500 mrem /yr. A graring period of 6 months has been applied to all radionuclides in particulate form with half-lives greater than 8 days, to allow for the milk exposure pathway. The release rate la determined by using the methodology of Regulatory Guide 1.109 (Rev. 1) and a relative deposition factor (D/Q) of 2.1 x 10 m*2 The D/Q of 2.1 x 10 m 2 was calculated for the nearest cow located 1.2 miles SE of the station, using onsite meteorological data. Controls 2.1.2.3 C. and D., establish an upper limit for the release of gaseous activity at 16% of instantaneoua release limit of noble (4ses and at eight percent of the release rate of particulates with hal!-lives greater than 8 days, averaged over any calendar quarter, respectively. The intent of those Controle is to permit the licensee the flexibility of operation to assure that the public is provided a dependable source of power onder unusual operating conditions which may temporarily result in higher releases than the objectives. Control 2.1.2.3 E., requires a 45 day holdup time for radioactive gaseous wastes collected in the gas decay tanks to assure decay of most radioncclides. The whole body dose from noble gases at the site boundary is expected to be less than 10 mrem /yr (primarily from Kr-85). The whole body doso from particulates at the nearest farm is expected to be less than 5 mrem /yr. Control 2.1.2.3 F., limits the radioactivity that may be released to the environment to "as low as practicable." Control 2.1.2.3 G., limits the maximum of f site dose to well below tne limits of 10 CFR 100, postulating that the rupture of u Waste Gas Decay Tank holding the maximum activity releases all of the contents to the atmosphere. l In addition to the requirements of Controls 2.1.2.3 A., B. at3 C., the reporting requirements of Control 2.1.2.3 H. delineate that the licensee shall identify the causo whenever the radioactive gaucous release rate exceeds 4 percent of Control 2.1.2.3 A. or 2 percent of Control 117.0 2226c l -

1 Ir kl INuclear 1s1,adio1onc.1 centrois Departmental Procedure 6610-PLN-4200.01 Title Revision No. l offsite Dose calculation Manua1 (ODCH) 1 2.1.2.3 B., averaged over a calendar quarter, and describe the proposed program of action to reduce such re1 ease rates. The report must be flied within 30 days fo11owing the ca1endar quarter in which more than twice t'

• seign release rate occurred.

) 118.0 2226c

I k2 1Nuclesr Tx1,adio10,1ca1 cont,o1s Departmental Procedurc 6610-PLN-4200.01 Title Revision No. Offsite Dose calculation Manual (ODCM) 1 2.2 Radioactive Gaseous Effllent Monitoring Instrumentation 2.2.1 OFJECTIVE The radioactive gaseous ef fluent monitoring instrumentation channels shown in Table 2.2-1 shall be OPERABLE. 2.2.2 APPLICABILITY As shown in Tible 2.2-1. 2.2.3 CONTROL With less than the minimum number of radioactive gaseous ef fluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.2-1. 2.2.4 BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluet.ts. The OPERADILITY and use of this instrumentation is consistent with the requirements of General Design Criterion 64 of Appendix A to 10 CFR Part 50. 119.0 2226c I

Nuclear TM1 Badio10,1ca1 cont,ois Departmenta1 Procedure 6610-PLN-4200.01 T't1e Revision No. Offsite Dose Calculation Manua1 (ODCM) 1 2.J Radiation Monitoring Instrumentation 2.3.1 OBJECTIVE The radiation monitore 11sted in Tab 1e 2.3-1 sha11 be OPERABLE. 2.3.2 APPLICABILITY Ao reqJired in Tab 1e 2.3-1. 2.3.3 CONTROL As required in Tab 1e 2.3-1. 2.3.4 BAS P.S The OPERABILITY of the radiation moni'oring channe1s ensures that the radiation leve1s are measured in the areas served by the respective monitors. 120.0 2226c t

i t TMI Radiological Controls Departmental Procedure 6610-PLN-42OO.01 Revision No. Title Offsite Dose Calculation Manual (ODC3t) I TABLE 2.2-1 RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION MINIMUM CHANNF'.S INSTRUMENT OPERABLE APPLICABILITY ACTION EPICOR II VENTILATION SYSTEM a. - Noble Gas Activity Monitor 1 1 l b. ' Particulate Sampler 1 2 c. Flow Rate Monitor 1 3 d. Sampler Flow Rate Monitor 1 3 l TABLE NOTATION

• At all times.

l' I ACTICN 1 With the number of channels OPERABLE less than _ required by the Minimum Channels Operable requirement, affluent releases via the pathway may continue for up to 30 days provided GRAB SAMPLES are taken at least once per 8 hours and these samples are analyzed for gross activity within 24 hours. ACTION 2 - With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 3.1-3. ACTION With the number.of channels OPERABLE less than required _by the Minimum Channels OPERABLE requirement, offluent releases via this pathway may continue for up to 30 days provided the flow rate is estin sted at least once per 4 hours. I: 121.0 2226c ,-eyem= ,w--w w,,,3 y,y r w y -m-ry, , vu -w,or.-. e - -, y_. m.m--,----,wwrsn,- g-a r

THI Radiolos,1 cal Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODOI) 1 TABLE 2.3-1 RADIATION MONITORING INSTRUMENTATION i CEANNEL MINI &M CRANNEL CBAFNFL F A"Y1CEEAL CBANNELS Ft'Nc;10RAL LTIT CEECE CALIBRATION TEST OFLwABLE AFFLICABILITT ACTiCal

1. ccNTAINMEWY a.

Reactor Sullding Equipannt Doore ( AMS*3) D SA W 1 Note 1 Note 2

2. WACTE BANDLING AND PtCEAGING FACILITY a.

Enhaust Martitor .D R M 1 Note 3 Note 4 P . NOTES: 1. - With both Reactor Building equipment hatch airlock doors open s12nultaneously. 2. With the AMS-3 inoperable, close at least one of the Reactor Building Equipment -Doors and restore the inoperable equipment to OPERABLE status prior to the reopening of both Equipment Doors. 3. During operation of the snonitored system. 4. .With less than one char'tel operable, ef fluent releases via the affected pathway may continue for up to thirty (30) days provided that samples are contintously collweted with auxiliary sampling equipment.within the WHPF. These auxiliary -filter samples will be changed daily and a gamma scan performed within 24-hours. Af ter completion of the ganuna scan, an analysis for gross alpha, gross beta, and Sr/Y-90 activLties will be cCNnplated within 96 hours. 122.0 2226c ~,

_____.m THI Radiological Controls Departmental Procedurn 6610-PLN-4200.01 ~ Title Revision No. Offeite Dose Calculation Manual (ODON) 1 3.0 MONITORING REQUIRD0DITS 3.1 Radioactive Discharges 3.1.1 Liquid Effluents 3.1.1.1 OBJECTIVE To ensure that radioactiva liquid releases from the facility are within the limits of Controls 2.1.1.3 A. through F. 3.1.1.2 CONTROLS During release of liquid radioact.ve wastes from the Waste Evaporator Condensate Storage Tank and the Waste Evaporator Condensste Test Tar.k, the following conditions shall be met: A. The liquid gross activity monitor (WDL-R-1311 or similar device) and recorder on the radwaste ef fluent line shall be OPERABLE. B. The liquid gross activity monitor (WDL-R-1311 or similar device) shall be set to alarm and automatically close waste discharge valve (WDL-V-99) prior to exceeding the limits specified in 10 CFR 20, Appendix B for unrestricted areas. C. Liquid waste radioactivity and flow rate from the Waste Evaporator Condensate Test Tank shal'1 be continuously monitored and recorded during release. If this requirement cannot be met, continued release of liquid ef fluents shall be permitted only during the succeeding 48 hours provided that during this 48-hour period two independent samples of each tank shall be analyzed and two station -personnel shall independently check valve line-up prior to the discharge. D. Facility records shall be maintained of the radioactive concentrations knd volume before dilution of each batch of itquid ef fluent released, and the average dilution flow and longth of time over which each discharge occurred. Estimates of the error L associated with each reported value should be included in facility records. E. Radioactive liquid waste sampling and activity analysis shall be performed in accordance with Table 3.1-1. Prior to the release of each batch of liquid effluent, a sample shall be taken from that batch and analyzed for the concentration of each significant gamma emitter to demonstrate compliance with control 2.1.1.3 A. using the flow into which the affluent is discharged. F. The liquid effluent radiation monitor (WDL-R-1311) shall be calibrated at least quarterly by means of a known radioactive l source. - WDL-R-1311 shall also have a CHANNEL FUNCTIONAL TEST l 123.0 2226c

l Nuclear Tx1 madio1,1ca1 Cont,,1s i Deptrtmental Procedure 6616-PLP-42OO.01 Title Revision No. Offeite Dose Calculation Manual (ODCH) 1 5 monthly and r f31ANNEL CHECK prior to each discharge to verify that the read-out device is indicating as expected. G. The ability of. WDL-V-99 to close automatically or receipt of a high radiation alarm signa 1 from WDL-R-1311 shall be checked annually. { 3.1.1.3 BASES controls 3.1.1.2 A., B., and C. require that suitable equipment to r monitor-the release of radioactive materials in liquid ef fluent are e operating during any period these releases are taking place. l The monitoring requirements given in the remaining Controle provide assurance that liquid wastes are properly controlled and monitored during any planned release of radioactive materials in 11guld affluents. These monitoring requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive liquid wastes released to the environment. Reports on the quantition of radioactive materials released in liquid effluents shall be furnished to the commission on the basis of ODCH Part III Requirements. On the basis of such reports and any additional information obtained from the licensee or others, the Commission may require the licensee to take appropriate action.- 3.1.2 Gaseous Effluents 3.1.2.1 OBJECTIVE To ensure that radioactive gaseous releases from-the facility are within the limics of Controls 2.1.2.3 A. through J. 3.1.2.2 CONTROLS-During releatn of radioactive gaseous wastes, the following conditions shall be met: A. During release of gaseous waste from the waste gas decay tanke, the following conditions shall be' met 1. The waste gas discharge monitor (WDG-R-1480 or similar device) shall be OPERABLE. 2. The Auxiliary and Fuel Handling Buildings and Unit Exhaust j Vent exhauet gas, iodine and particulate monitor (HP-R-l 9 or I sLmilar device) shall be OPERABLE.

3..

The waste gas decay tank discharge valves (WDG-V-30A and 30B) shall be OPERABLE. 124.0-2226c i -i .w. , ~ -. _ .w.

TMI Radiological Controls Departmental _ Procedure 5610-PLN-4200.01 Title Revision No. Offsite Dose calculation Ma_nual (00CM) 1 4. The waste gas decay tank discharge valves (WDG-V-30A and 30B) shall be closed in receipt of any one of the following conditionse c a. A high radiation signal from the waste gas discharge monitor (WDG-R-1480). b. A high radiation signal from the Auxill.ary and Fust Building exhaunt monitor (HP-R-219). c. A high flow signal from the Waste Gas Decay Tank discharge flow transmitter (WDG-FT-3923). d. Observation of loss of flow through the Unit Vent. B. During purge of the Peactor Building, the following conditions shall be met 1. The Reactor Building Purge Exhaust Monitors (HP-R-225 or HP-R-226, and HP-R-219 or similar device) shall be OPERABLE. 2. The Purge Exhaust Valves (D5129 A/D and D5129 B/C) shall be CPFRABLE. l 3. The Purge Exhaust Valves (D5129 A/D and D5129 B/C) shall be interlocked to recirculate on receipt of a high radiation + signal from their respective Reactor Building Exhaust Monitors (HP-R-225 and HP-R-226). C. The flow rate for radioactive ef fluent streous and the Auxiliary and Fuel Handling Buildings and the Reactor Building, shall be monitored and recorded. Gaseous effluents from the Wasta Gas Decay Tanks and the Reactor Building Purge Exhaust shall be continuously monitored and recorded. D. Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with Table 3.1-2. E. The waste gas decay tank effluent monitor (WDG-R-1400) shall be tested using the installed check source or equivalent prior to any release of radioactive gas from a holdup tank and shall be calibrated quarterly using a referenced calibration source in a controlled reproducible geometry. F.. ~During power operation.-the condenser vacuum pump discharge shall -be continuously monitored for gross gaseous activity. The monitor shall not be inoperable for more than a week Whenever this - i monitor is inoperable, a GRAB SAMPLE Jhall be taken daily and analyzed for gross radioactivity (D,.yi G.. Facility records shall be maintained of radioactive concentration, release ratio and volume of each batch of gaseous effluents 125.0 2226c r. ~. v e-s._..w-..,------.,...-.,.-.. ....,._.-,..,..m.,..-, , w Jm,m ,._,a,.._4.-.-m.--J.--.._,----.-, ,..,_,4-~ . -+,

I MUClS8r TH! Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Does Calculation Manual (ODCM) 1 released and the length of time over which release occurred. Estimates of the error associated with each reported value should bo included in facility records. H. At least annually, automatic initiation and clesure of the Waste cas Decay Tank Discharge valve on alarm of WDG-R-1480 shall be 4 verified. 1 1. The Unit Vent monitors (HP-R-219, HP-A-219A, HP-R-225, and HP-R-226) shall ba CALIBRATED st least every eighteen months by means of a known radioactive source. These detectors shall have a i CRANNEL FUNCTIONAL TEST at least monthly, and a CHANNEL CHECK at least daily, to verify that the read-out device is indicated as expected. J. The release rate of radioactive materials, other than noble gases, in gaseous af fluents shall be determined to be within the limito calculated in accordance with this Control by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 3.1-3. 3.1.2.3 BASES Controis 3.1.2.2 A. through I. require that suitable esquipment to monitor the radioactive gaseous releases are operating during any period these releases are taking place. control 3.1.2.2 J. is provided to ensure that the dose at any time at the site boundary from gaseous effluents from THI-2 will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual. dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. ThJse limits provide resconable assurance that radioactive material discharged in gaseous affluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20.(10 GfR Part 20.106(b)). For individaals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. Tha specified release rate limits restrict, at all times, the corresponding gamr>3 and beta dose rates above background to an. individual at or beyond the 4.te boundary to less than or equal to 500 mrom/yr to the total body l or it ;*ss than or equal to.3000 mram/yr to the skin. These release rate 15mits also restrict, at all times, the corresponding thyroid _ dose rate above background to an infant via the cow-milk-infant pathway to less than or equal to 1500 mram/yr for the nearest cow to the plant. These monitoring requirements provide assurance that radioa-tive gaseous effluents from the station are properly controlled and monit. red over the life of the station. These monitoring requirements provide the data for the licensee and the Commission to evaluate the station's 126.0 2226c -u- -.. - -. i,

b N TMI Radiological Controls Departmental Procedurn 6610-PLN-4200.01 Revision No. Title Offolte Doon Calculation Manual (ODCH) I performance relative to radioactive gaseous wastes released to the environment. Reports on the quantities of radioactive materials released in 9aseous effluents shall be furnished to the Commission on the basis of ODCM Part III requirements. On the basis of such report and any additional information the Commission may obtain from the licensee or others, the Commission may f rom time to ttme require the licensee to take uuch action as the Commission deems appropriate. l l l l l l l l l 127.0 2226c

1 Fe L J1 Nuclear TMI Radiological Controls j Departmental vrocedure 6610-PI.N-4200.01 Revisien No. Title offolte Dose ca_1culation Manual __(ODCM) 1 l 3.2 Radioactive GaJeous Effluent Ponitoring Instrumentatior Each radioactive gaseous effluent monitoring instrumentation channel shall be i demonstrated OPERABLE by perf ormance of the CHANNF.L CHECK, CHANNEL CALIBRATION and CHANNEL TUN 0TIONAL TEST operations at the frequencies shown in Table 3.2-1 (per occupational exposure considerations and detector sensitivity in ambient radiation areae). l l l l l i l l l l 2226c l 120.0 l 1

7 \\ TMI Radiological Controle i Departmental Procedure 6610-PLN-4200.01 Title Revision No. ot'taitgbosa calculgtion Manua1 (o w ) 1 1 3.) Radiation Monicoting Instrumentation ) T.'ach radiation monitori!g instrumentation channel shall be demonstre,ted CSitABLE by the perf ormance of the ("4ANNEL CIIECK, CHANNEL CALIBRATION, and C11 ANNE', TUNCTIONAL TEST operations at the frequencliirs shown in Table i.3-1. i 1 i l 129.0 2226c

Ir kdNuclear Humber rM1 sadio1ogica1 Cont,ois Departmantal Procedure 6610-PLN-4200.01 Title Revtston No. Of feito Dose Calculation Manual (ODCM) 1 TABLE 3.1,-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS (4, 5) A. Moniter Tank Releases i 1 7 Type of Detectable Sampling Trsqucet/ hetivity Analysis, Concentration (3) w~.. _.~.. _._ e Each Batch ind1*idual Gamma SE-7 pct /ml (2) H-3 lE-5 pCi/mi Monthly Composite (1) Gross Alpha lE-7 pCi/ml Sr-89 SE-8 pCi/ml i Sr-90 SE-8 pC1/ml NOTES (1) A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant. (2) For certain mixtures of gamma Smitters, it may not be psasible to measure radionuclides in concentrations near this sensitivity.'imit when other nuclides are present in the sample in much groa*or concentrations. Under those circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using measured ration with those radionuclides which arc routinely identified and measured. (3) The detectability limits for radioactivity analysis are based on the technical feasibility and on the potential significance in the environment of the quantities released. For some nuclidos, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported. (4) The results of these analyses should be used as the basis for recording and reporting the quantities of radioactive material released in liquid ef fluents during the sampling period. In estinating releases for a period when analyses were not performed, the average of the two adjacent data points epanning this period should be used. Such estimates should be included in the ef fluent records and reports; however, they should be clearly identified as estimates, ard the method used to obtain these data should be described. (S) Deviations f rom the rampling/ analysis regime will be noted in the report specified in ODCM Part III. 130.0 2226c

. ~. - -. - -. - -. - =. .... -.. ~.. -. MUCl88r Tal Radioto,1 cat controis Departmental Procedu a 6610-PIJt-4 200. 01 Tit 1e Revision No. offaite Dose calculation Manual (0004) 1 TABLE 3.1-2 I PWIOACTIVE GASEOUS WASTE SAMPLING AND ANALYS!$ ($) SARPLING TYPE OF DETECTABLE SAMPLE POINT SAMPLE TYPE FPJOUYNCY-ACTIVITY ANALYSIS CONCENTRATION (1) J Waste Gaw Dee~ay Tank Release Gas Each Tank H-3 1E-6 pCi/ce Rs1 ease Individual Gamma Emitters 1E-4 pCL/cc (2) Reactor Building Purge Re1 eases Gas Each Purge g3 1E-6 pCi/cc Individual canna Emitters 1E-4 uCi/ec (2) Condenser Vacuum Pump Releases Gas Monthly H-3 1E-6 pCi/cc Individual Monthly (3) Ganna Emitters 1E-4 uCi/cc (2) Unit Exhau6t vent Release Points Cts-Monthly (4) H 1E-6 pC1/cc Individual Gamma Emitters 1E-4 pCL/cc (2) Charcoal Weekly (6) 1-131, 1-133, I-135 1E-12 9Ci/ec Individual Particulates Weekly Gamma Emitters 1E-10 pCi/cc (2)

4onthly Composits Sr-09 Sr-90 1E-11 pCL/cc Month 1y Gross Alpha Composite Emitters 1E-11 pCi/cc (1)

The above detectability limitw are based on technical feasibility and on the-potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable and when nuclides are sneasured belcw the stated limits, they should also be reported. I l 131.0 2226c ll' _,a,.

i l TMI Radiological Controls Departme,ntal Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 1 TABLE 3.1-2 (cont'd) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSy (5) (2) For certain mixtures of gamna emitters, it may be possible to measure radionuclides at levels near their sensitivity 1Lmits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios in the gaseous component in the reactor coolant for those radionuclides which are measurable. (3) Analysis shall also be performed following each refueling period, start-up or similar operational occurrence which could alter the mixture of radionuclides. (4) Sampled during periods when no waste gas decay tank release or reactor building purge is in progress. (5) Deviations from the sampling and analysis regime will be noted in the report specified in ODCM Part III. (6) Sampla not required for Unit Exhaust Vent. However, the charcoal in the charcoal sampler should be replaced on a weekly basis although a weekly analysis is not required. I l 132.0 2226c

l Ir L)] Nuclear TM1,a,1,1o,1 a1 cont,,1. Deparunental Procedure 6610-PLN-4200.01 Revisicn No. Title Offsite Dose Calculatlon Manual (ODCM) 1 TABLE 3.1-3 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimwn Lower Limit of Gaesous Release Sampling Analysis Type of Activity Detection (LLD) Type Frequency Trequency Analysis (pci/ml)* EPICOR-II M M Principal lE-4 b Ventilation Gamma Emitters' Grab Sample H-3 lE-6 l t l l l 1.13.0 22260

MUClear TMz Radio 1ogical Controle Departmental Procedure 6610-PLN-4200.Ol ~ Revision No. Title Offsite Dose Calculation Manual (ODCM) 1 TABLE 3.1-3 (Cont'd) RADIOACTIVE GASEOUS WASTE SAMPLI:4G AND ANALYSIS PROGRAM TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample that will a. be detected with 954 probability t6th 5% prnbability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): LLD = 4.66 s, E

• V
• 2.22
• Y
• orp (-lat)

Where LLD is the lower limit of detection as defined above (as picoeurie per unit mass or volume). S, is the standard deviation of *he 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 transformation), V is the sample size (in units of mass or volume), 2.22 is the number of transformations per minute per picoeurie, Y is the fractional radiochemical yield (when applicable), 1 is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant affluents, not environmental samples), The value of S used in the calculation of the LLD for a detection system e shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverifieo theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, arad At shall be ured in the calculation. The background count rate is calculated from the background counts that are determined to be with + one FWHH (rull-Width-at-Half-Maximum) energy band about the energy of the gamma-ray peak used for the quantitative analysis for that radionuclide, b. Tritium GRAB SAMPLES shall be taken at least once per 7 days from the ventilation exhaust from the Chemical Cleaning Building. 134.0 2226c 1 t

[r L 11 Nuclear TMI Radiological Controls Departmental Procedure 6610-l'g-4200.01 Title Revisk Offsite Dope Calculation Manual (ODCM) 1 TABLE 3.1-3 (Cont'd) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRUi TABLE NOTATION c. The principal ga ma emitters for which the LLD specification applies exclustvely are the following radionuclidass Mn-54, Fe-59, Co-58, Co-60, 2n-63, Mo-99, Cs-134, Co-137, Ce-141 and Ce-144 for particulato emissions. This list doec not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclice. The "less than" values shall not be used in the required dose calc alations. 4 l l l 135.0 2226c

l 1 ' " " ~ Le WINuclear THI Radiological controls l 9 0-PLN-42OO.01 Departmental Procedure Revision No. Title 1 Offsite Doce Calculation Manual (ODCM)__ TABLE 3.7-1 RADIOACTIVE GASEOUS EFFLUENT MONITOR 7.NG INSTRUMENTATION HONITORING REQUIREMENTS CHANNEL CEA'INEL CHANNEL FUNCTIONAL INSTRUMENT CHECK CALIBRATION TEST --w .u ~ ~ EPICOR II VENTILATION SYSTEM s. Noble Gas Activity donitor L R(i) Q(2) e. Particul4te Samplar W N/A N/A c. Flow Rate Monitor D SA SA d. Sampler Flow Rate Monitor D SA SA TABLE NOTATION (1) The initial CHANNZL CALIBRATION shall be performed using one or more of the reference standards certif Aed by the National Bureau of Standarda or using standards that have been obtainoa from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For wubsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (2) CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm outpoint. 2. Circuit failure (alarm function only). 3. Instrument indicatos a downside failure (alarm function only). 4. Instrument controls not s,et in cperate mode or the switch position administratively monitored and controlled. 136.0 2226c l

Nar. Der {f () f QQ M TMI RadiolDgical Controls Departmental Proctdure 6610-?LN-4200.01 Title Reision No. Offsite Oose calculation Kanual_(OccM) 1 SECTION 4.0 DESIGN TEATURIS i 4.0 DESIGN TEATURES 4.1 SITE EXCLUSION AREA 4.1.1 The exclusion area is shown in Figure 5-1, THI-l Tech. S poca. i Low POPULATION EONE 4.1.2 The low population zone is shown in Figura b-2, TMI-1 Tech. S pee s. S_ITE BOUNDARY TOR CASEOUS EFTLUENTS, 4.1.3 The site boundary for gaseous offluer.ts shall be as shown in Figuro 5-3, TMI-1 Tech. Specs. SITE BOUNDARY FOR LI2UID ETT'AJrN f 5 4.1.4 The alte boundary for liquid af fluents shall be as ahown in Figura 5-3, THI-1 Tech. Specs. i l l l l 137.0 2226c

I'- kJ 1 Nuclear TM1 padio1o,1ca1 contro1s Departmental Procedure 6610-PLN-4200.01 Pevision No. Title 1 Offeite Dose Calculation Manual (ODCM) 5.0 PART II REFERENCES NUREG-0683, " Final Programmatic Environmental Impact Statement related to 5,1 decontamination and disposal of radioactive wastes resulting from March 28, 1979, accident Three Mile Island Nuclear Station, Unit 2," March 1981 5.2 THI-2 Recovery Technical Spo'ifications, attached to Facility operating License Po. DPR-73 5.3 Title 10, code of Federal Regulations, " Energy" " Statement of Policy Relative to the NRC Programmatic Environmental Impact 5.4 Statement on the Cleanup of.'hree Mile Island Unit 2," dated April 27, 198?. Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine

4. 5 Releases of Reactor Effluents for the Purpose of Praluating Complian~e with 10 CFR Part 50, Appendix I," ?etision 1, October 1977 5.6 DCE/ TIC-27601, Atmospheric Scitace and Power Reduction 5.7 TMI-1 Technical Specifications, attached to Facility Operating License No.

UPR-50 2226c 138.0

TMI Radiological Controls Departmental Procedure 6610-PI.N-4200. Ol Revision No. Title Of f alta Dose Calculation hnual (ODCM) y PART III REPORTING REQUIREMENTS 1 i 139.0 2226c

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Kanual (9DCM) 1 PART III REPORTING REQUIREMENTS 1.0 'IMI ArtNUAL RADIOLOGICAL ENVIRONMENTAL 3PERATING REPORT

• 1.1 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted to the Commission prior to May 1 of each year.

1.2 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring activities for the report period, including a comparison with pre-operational studies, with operational controls as appropriate, end with previous environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environnent. The reports shall also include the results of land use censuses required by Part I, Section 7.2. 1.3 The Annual Radiological Environmental Operating Reports shall include the summarized tabulated results of analysis of all radiological environmental samples and environmental radiation measurements required by Part I Table 7.1 taken during the period pursuant to the locations specified in the tables and figures in this ODCM, as well as summarized and tabulated results of these analyses and measurements in a fermat similar to the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. 1.4 The reports shall also include the followings a summary description of the radiological environments monitoring program; a map (s) of all sampling locations keyed to a table giving distances and directions from a point that is midway between the Reactor Buildings of TMI-1 and TMI-2; the results of licensee participation in the Interlaboratory Comparison Program, required by Part I, Section 7.3; discussion of all deviations from the sampling schedule of Part I, Table 7.1; discussion of all the required analyses in which the LLD required by Part I, Table 7.3 was not achievable. I

• A single submittal may be made for the station.

140.0 2226c

... ~~,-- . - - - ~ ~ - - _ _. TMI Jadiological Controls Depprtmental Precedure 6610-FLN-4200.01 ' Title Revision No. Offsite Dose Calculation Manual (ODCM) 1 2.0 'IttI SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NOTE: A single submittal may be made for the station. The submittal should combine those sections that are common to both units at the station however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit. 2.1 Routine Radioactive Effluant Release Reports covering the operations of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. 2.2 The following information shall be included in both Radioactive Effluent Release Reports to be submitted each yea : The Radioactive Ef fluent Release Reports shall include a summary of the quantities of radioactive liquid anu gaseous effluents and solid waste released from the unit as outlined in Reg. Guide 1.21, Rev. 1, with data summariand ca a quarterly basis fcilowing the format of Appendix B thereof. 2.3 -The Radioactive Effluent Release Reports shall include the following information for each type of-solid waste shipped of f site during the report period: a. container volume, b. total curie quantity (specify whether determined by measurement or . catimate), i principal radionuclides (specify whether determined by measurement or c. estimate), d. type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),. e. type of shipment (e.g., LSA, Type A, Type B)-and f. solidification agent (e.g., cement). ~ -2.4 The Radioactive Effluent helease Reports shall include a summary of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid ef fluents made during the reporting period. 2.5 The Radioactive Ef fluent Release Reports shell include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents jl and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of L new locations for dose calculations and/or environmental monitoring I identified by the land use census pursuant to Part I Section 7.2. I l' L 141.0 2226c ~

TMI Radiological Controls Departmental Procedure 6610-PLN-4 2 OO. 01 Revision No. Title 1 Offsite Dose Calculation Manual (ODCM) 2.6 The Radioactive Effluent Release Reports shall include the instrumentation returned to OPERABLE status within 30 days per TMI-I Tech. Spec. not Sections 3.21.1.b and 3.21.2.b. The following information shall be included in the Radioactive Effluent 2.7 to be rubmitted 60 days after January 1 of each year Release Report 2.7.1 The Radioactive Effluent Release Report to be submittad 60 days after January 1 of each year shall include an annual summary of This hourly meteorological data collected over the previous year. annual summary may be either in the form of an hour-by-hour.isting of wind speed, wind direction, atmosphere stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability. 2.7.2 The Radioactive Effluent Release Report to be submJ t'ed C-days after January 1 of each year shall include an asses.went - the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The Radioactive Effluent Release Report to be submitted 60 days 2.7.3 of the after January 1 of each year shall include an assessment radiation doses from radioactive liquid and gaseous effluents to ( MEMBERS OF THE PUBLIC due to their activities inside the site boundary (Figure 5-3, TMI-1 Tech. Specs. ) during the report period. l All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included iri these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as shall be used for determined by sampling frequenef and measurement) determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with this ODCH. The Radioactive Effluent Release Report to be submitted 60 days 2.7.4 j after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed real individual from reactor releases and other nearby uranium fuel cycle sources radiation including doses from primary ef fluent pathways and direct for the previous 12 consecutive months to show conformance with 40 CFR 190 " Environmental Radiation Protec+ 1on Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contributtone f rom liquid and gaseous ef fluents are given in Regulatory Guide 1.109, Rev. 1. 142.0 2226c

Number b TMI Radiological Controlo Departmental Procedure 6610-PLN-4200.01 Revision No. Title Offsite Dose Calculation Manual (ODCM) 1 3.0 TMI-2 QUARTERLY RADICIOGICAL RELEASES AND ESTIMATED DOSE REICRT The following information shall be submitted in accordance with 10 CFR 50.4. Tnis information shall be submitted on a calendar quarter basis (January-March, April-June, July-September, and October-December) and shall be submitted no later than 60 days following the and of each calendar quarter. 1. Estimates of the amounts and types of radioactivity that were released to the environment during the quarter and during the calendar year. This shall include estimates of the total activity of each nuclide and time rate of release of each nuclide. 2. Estimates of populations and maximum individual doses which occurred during the calendar quarter and during the calendar year shall be provided. The estimates shall be based on actual hydrological and meteorological conditions which occurred during the releases. Calculational methods shall be those of U.S. NRC Regulatory Guides 1.109 (Revision 1), 1.111 (Revision 1), 1.132 (Revision 0-R) and 1.113 (Revision 1). These calculations shall be based on estimates of actual population distributions during the releases and shall take into consideration factors such as boating or fishing recreation. l l l i i i I i i l l l l l l 143.0 2226c

TMI Radiological Controls Departmental Procedure 6610-PLN-42OO.01 Revision No. Title 1 Offsite Dose Calculation Manual (ODCM) 4.0 PART III REFERENCES 4.1 Radiological Assessment Branch Technical Position, Revision 1, November 1979 4.2 Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous June Effluents from Light-Water-cooled Nuclear Power Plants," Revision 1, 1974 4.3 THI-1 Technical Specifications, attached to Facility Operating License No. DPR-50 4.4 Title 40, Code of Federal Regulations, " Protection of Environment" 4.5 Regulatory Guide 1.109, " Calculation of Annuel Doses to Man from Routine Releases of Reactor Ef fluent s for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,0 Revision 1, October 1977 4.6 Title 10. Code of Federal Regulations, " Energy" 4.7 Regulatory Guide 1.111, " Methods of Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-cooled Reactors," Revision 1, July 1977 4.8 Regulatory Guide 1.112, " Calculation of Releases of Radioactive Materialc in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors," Revision 0-R, April 1976 l l 4.9 Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Ef fluents f rom Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, ' Revision 1, April 1977 i i l l l 144.0 2226c

1 ENuclear TMI Radiological Controle ] Departmental Procedure 6610-PLN-4200.01 Revidion'No. l Title. 1 -Offsite Dose Calculation Manual (ODCN) APPENDIX A P - PATHWAY DOSE RATE PARAMETER (Eq A-1) P (inhalation) = k' (BR) DFA3 g Wheret the pathway dose rate parameter for radionuclide, 1, (other than noble ~ ~ P = gases)= for the inhalation pathway, in mrom/yr per microcurie /m). 3 The dose factors are based on the critical individual organ for the infant age group. k' = conversion factor, lE6 pCi/ microcurie BR

1400 m /yr, breathing rate for inf ant (Reg. Guide 1.lO9, Rev. 1, Table E-5) 3 the maximum organ inhalation dose factor for the infant age group for the DFAg

(m.sm/pci). Values are taken from Table E-lO, Reg. ith radionuclide r Guide 1.109 (Rev. 1). Resolution of the units yields: (CDCM Part I Table 4.6) (aren/yr per pC1/m ) (Eq A-2) 3 P - (inhalation) = 1.4E9 DFAg 3 NOTE: The latest NRC Guidance has deleted the requirement to t (food). In addition, determine P (ground plane).and Pg 3 the critical age group has been changed from infant to child. However, THI-1 Tech. Spec. Section 3.22.2.1 currently states infant as the critical age group. L 2226c El-1 I e- -,m- ,e ~ a ,w.-w 7"ww vi w r-w-' '-"m-' W

. ~. = 1 l TMI Radiological. Controls Departmental Procedure 6610-PIJf-4200. 01 j Revision No. Title ~ 1 Offsite Dose Calculation Manual (ODCM) APPENDIX B Ri - INHALATION PATHWAY DOSE FACTOR (DFA,,,,) (aren/yr per microcurie /m ) (Eq B-1) 3 R = k' (BR) 3 3 s - Wheres k' = converston-factor, IE6 pCi/ microcurie BR = breathing rate,.1400, 3700, 8000, 8000 m /yr for inf ant, child, 3 teer.ager, and adult age groups, respectively. (Reg, Guide 1.109, Rev. 1, Table E-5) 1 the inhalation dose factor for organ, o, of the receptor cf a given age DFA e,o = t group, a, -and for the ith radionuclide, in rares/pci. The total body is-considered.as an organ in the selection of DFA,,,,. Values are.teken 3 from Tables E-7 through E-10,-Reg. Guide.l.109 (Rev. 1). Resolutions.of the units yields: (DFA ',,,,) - inf ant (ODCM Part I Table 5.2.1) (1.4E9) Ri '= 3 (3.7E9)- (DFh,,,,) child (00CM Part I Table 5.2.2) Ri = g (0.0E9) (DFA,,,,) teen and adult (ODCH Part I Tables 542.3 and 5.2.4) R1 = g l i E2-1 2226c w m n e.. .-,.,.,m ,w

,~ -. - _. .... ~.. ~~ -,. -,. ~. ...-... ~.. . ~.. ~., _ d TMI Radiological Controls Departmental Procedure 6610-PLN-42OO.01 Revision No. .. Title. 1 offsite Dose Calculation Manual (ODC3() ' APPENDIX C Ri - GROUND PLANE PATHWAY DOSE FACTOR Rg = k' k" (SF) (DFC ) [(1-e "A t)/1 ) (Eq C-1) i g g Where conversion factor, lE6 pCi/ microcurie k' = ~ conversion factor,'8760 hr/yr k"- = 1- = - decay constant f or the it" radionuclide, see ~1 3 the exposure time (this calculation assumes that decay is the only operating. -t- = removal mechanism) 4.73 x 10 sec. (15 yrs), Reg. Guide 1.109 (Rev. 1), 8 Appendix C g = ~ the ground plane dose conversion f actor for the i radionuclide (mrem /hr per. th DFG 'pci/m )~.. Values'are taken from Table E-6, Reg. Guide 1.109 (Rev. 1). _These 2 values apply to all age groups. SF.= 0.7,-shielding factor, from Table E-15 Reg. Guide 1.109 (Rev. 1) Rafarence ODCM Part I Table 5.3.1 .l l l E3-1 2226c

} L 21 Nuclear TMI Radiological Controls 6610-PLN-4200.01 Departmental Procedure Revisaon No. Title 1 Offsite Dose Calculation Manual (ODCM) APPENDIX D Ri - GRASS COW-MILK P7THWAY DOSE FACTOR k' ( (Q, a Ugp) / (1 + 1,)] x (F,) x (r) x (DFL,,,,) x 3 R f,) e 'l 'h)/Y,) ei i*f (Eq D-1) 1 = l 3 l ( { { f, x f,)/Y ) + ((1-f x p p Wheres con *ersion factor, IE6 picoeurie/ microcurie (pci/pci) k' = cow consumption rate, 50 kg/ day, (Reo. Guide 1.109, Rev. 1) Q, = goat consumption rate, 6 kg/ day, (Reg. Guide 1.109, Rev. 1, Table E-2) Receptor's milk consumption rate; 330, 330, 400, 310 liters /yr for U = infant, child, teenager, and adult age groups, respectively (Reg. p Guide 1.109, Rev. 1) 2 0.7 kg/m agricultural productivity by unit araa of pasture feed grass, Y, = (NUREG-0133) 2 agricultural productivity by unit area of stored feed, 2.0 kg/m Y, = (NUREG-0133) stable element transfer coefficient (Table E-1, Reg. Guide 1.109, F, = Rev. 1) 0.2 for fraction of deposited activity retained in cow's feed grass, = r particulates, 1.0 for radiciodine (Table E-15, Reg. Guide 1.109, Rev. 1) the ingestion dose factor for organ, o, and the ith radionuclide for D rL,,,, = each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, 1 Rev. 1) -1 decay constant for the ith radionuclide, see 1 = 3 for weathering, 5.73 x 10-7 sec'l (NUREG-0133); based on a decay constant 1, = 14 day half life 1.73 x 10 sec, the transport time from pasture to cow to milk to 5 t receptor (Table T-15, Reg. Guide 1.109, Rev. 1), or 2 days r 7.78 x 10 sec, the transport time f rom pasture to harvest to cow to 8 t = milk to receptor (Table E-15, Reg. Guide 1.109, Rev. 1), or 90 days n 1.0, the *raction of the year that the cow is on pasture f, = 1.0, the fraction of the cow feed that is pasture grass while the cow is f, = on pasture 2226c E4-1

m. l -TMI. Radiological Controlc Departmental Procedure 6610-PLN-4200.01 Revision No. Title. 1 Of f site Dose Calculation Manual - (CDO() APPENDIX D (Cont'd) The concentration of tritium in tr. ilk is based on the airborne concentration rather than the deposition. Therefore, R is based on (X/Q): 3 (Ea D-2) .R g,,,,-= k' k' ' ' F, Q, UgFL,,,, (. 7 5 [. 5/B) } C g Wheret ~ lE3 grams /kg k = 8 grams /m, absolute humidity of the atmosphere 3 B- = fraction of the total _ feed grass mass that is water l. .75 = ratio of the. specific activity of the feed grass water to the .' 5 = atmospheric water (NUREG-0133) DFL,,,,=- the ingestion dose factor for tritium a'id organ, o, for each respective g age group, a (Talles E-11 to E-14, Reg. - Guide 1.109, Rev. 1) All other parameters and values are as given above.

---

=.

-_---.--=. NOTE: Goat-milk pathway f acto;, R, will be computed using the 3 cow-milk pathway factor equation. F, factor for goat-milk will be from Table E-2 Reg. Guide 1.109, Rev. 1. = - _ _

Reference:

CDCtd Part I' Tables 5.4.1 to S.4.4 I i l-l l. i l' i l-l E4-2 2226c ~

s N MI 'TMI Radiological Controls Departmental Procedure 6610-PIA-4200. 01 -Revision No. Title 1 ~offsite Dose Calculation Manual-(ooot)- APPENDIX E Ri - COW-MEAT PATHWAY DOSE FACTOR R[ =. k ' ((Q, x U,) / (1 + 1,) ) x (F ) x (r) x (DFI,1,,,,) x d "f (Eq E-1) i f.)/Y ) + ((1-f f.) e

• i h)/Y,] x e

[((f I p p p Where - conversion factor, 1E6 picoeurie/ microcurie (pci/pci) k' = cow consumption rate, 50 kg' day, (Reg. Guide 1.109, Rev. 1) Q,' = Receptor's meat consumption rate; 0, 41, 65, 110 kg/yr for infant, U = -child, teenager, and adult age groups, respectively (Reg. Guide 1.109, p Rev. 1) the stable element trannfer coefficients, days /kg (Table E-1, Reg. F = f Guide 1.109, Rev.21) = fraction.of deposited activity retained in cow's feed grass, 0.2 for r -particulates, 1.0 tor radiciodine-(Table E-15, Reg. Guide 1.109, Rev. 1) the ingestion dose factor for organ, o, and the ith radionuclide for DFL,,,, = each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, 3 Rev. 1) decay constant for the radionuclide 1, sec'1 1 = 3

1. -

1,. = decay constant for weathering, 5.73 x 10~7'sec-1 (NUREG-0133), based on a -14 day half life 1.73 x lo sec, the transport time from pasture to receptor (NUREG-0133)- l s t = g 1; 7.78 L x 10' sec, the transport time from crop to receptor.. (NUREG-0133) } _- tg -= 2 =. agricultural productivity by unit area of pasture feed grass,-0.7 kg/m T, (NUREG-0133) 2 = agricultural productivity by unit crea of stored feed, 2.0 kg/m Y, (NIREG-0133)- f, =.1.0, the f raction of the year that the row is on pasture = 1.0, the fraction of the cow f eed that is pasture grass while the cow is f,. t on pastura 2226c ES-1

TMI Radiological Controls Departmental Procedure 6610-ItN-42 00. 01 Revision No. Title 1 Offsite Dose Calculation Manual (ODCM) APPENDIX E (Cont'd) is based on the airborne concentration rather than The concentration of tritium in meat the deposition. Therefore, R is based on i././Q): 1 (DFL,,go) x 0.75 x (0.5/H]) (Eq E-2) R,,,,=k'k 7g Q, U, g g g Where All terms are as defined above and 1,e Appendix D. Reference ODCM Part I, Tables 5.6.1 to 5.6.4 2226c ES-2

1 l P r.VINuclear TMI Radiological Controls Departmental Procedure 6610-PIJi-4200. 01 Revision No. Title 1 Offsite Dose Calculation Manual (ODCM) APPENDIX F R1 - VEGETA'[_DN PATHWAY DOSE FACTOR 1,) ) ) x (DFL,,,,) x [(UL) f e'l ti L + Un g e'l th) (Eq F-1) k' a (r/ (Y, (l 3 a g g e + R = g 3 Wheres 1E6 picocurie / microcurie (pCL/pci) k' = the consumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for L U = infant, child, teenager, or adult age groups, respectively (Reg. 3 Guide 1.109, Rev. 1) the consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for Us, = infant, child, teenager, or adult age groups respectively (Reg. Guide 1.109 Rev. 1) the fraction of the annual intake of fresh leafy vegetation grown f = t locally, = 1.0 (NUREG-0133) the f raction of the stored vegetation grown locally = 0.76 (NURIG-0133) f, = the average time between harvest of leafy vegetation and its t w consumption, 8.6 x 10' seconds (Table E-15, Reg. Guide 1.109, Rev. 1 3 ( (24 hrs)) the average time between harvest of stored leafy vegetatian and its t = consumption, 5.18 x 10 seconds, (Table E-15. Reg. Guide 1.109 Rev. 1 n 5 (60 days)) the vegetation area density, 2.0 kg/m (Table E-15, Reg. Guide 1.109 2 = y, Rev. 1) All other parametern are as previously defined. The concentratton of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, R is based on (X/Q) g R,,,,=k'k [U f + Un f,] (DFL,,,,) (.75 [.5/H)) (Eq F-2) L g 3 t a s Where All terms are as defined above and in Appendix D.

Reference:

ODCM Part I, Tables 5.7.1 to 5.7.4 E6-1 2226c l ~ - _ - - _ - _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ - - - - - - - - - - - -

1 l -14uhihb TMI Radiological Controla Departmental Procedure 6610-PLN-4200.01 . Title Revision No. 1 offsite Dose calculation Manual (ODCN) APPENDIX A-F REFERENCES (Page 1 of 4) PARAMETERS USED IN DOSE FACTOR CALCULATIONS Origin of value Table in Section of Site-Parameter Value R.G. 1.109 NUREG-0133 Specific

• • • For P ***

1 DFA. Each radionuclide E-9 Note 1 i BR 1400 m /yr (inf ant) E-5 3

• • • For Ri (Vegetation)***

r Each element type E-3 2 E-15 Y,, 2.0 kg/m t 5.3.1.3 lw 5.73 E-7 sec DFL .Each age group and E-11 thru 2 radionuclide F-14 Note 1 Uf Each age group E-5 f, 1.0 5.3.1.5 t. 8.6 E + 4 seconds E-15 U.s : Each age group E-5 f, 0.76 5.3.1.5 ts 5.18 E + 6 seconds-E H 8.0 grams /kg 5.2.1.3 ~***For Ri (Inhalation)*** BR-Each age group E-5 DFA -Each age group and E-7 thru 3 nuclide E-10 Note 1 E7-1 2226c

~ - ~. -~. ~. . N N TMI Radiological Controls Departmental Procedure-6610-PLN-4200.01 Revision No. -Title _ 1 offsite Dose Calculation Manual (ODCSI) APPENDIX A-F REFERENCES (Page 2 of 4) 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS origin of Value Table in Section of Site-Parameter Value R.G. 1.109 NUREG-0133 Specific

• *
• For Rg ' (Ground Plane) ***

E-15 SF ,0. 7

DFG, Each radionuclide E-6 4,

t 4.73 E + 8 sec 5.3.1.2

• • • For Ri

-(crase/ Animal / neat) Q, (Cow)' 50 kg/ day E-3 .Q, (Goat) 6 kg/ day E-3 Ref. Onl/ [- U Each age group E-5 mm l i 5.3.1.3 -1w 5.73 E-7 soc F, (Both) Each element E-1 r Each-element type 'E-15 DFLj Each age group and E-11 thru nuclide E-14 Note I f, 1.0 5.3.1.3 Note 2 5.3.1.3 Note 2 -f. 1.0 3 E-15 Y, 0.7 kg/m t 7.78 E + 6 see E-15 w 2 (~ Y. 2.0 kg/m - E-15 t, 1.73 E + 6 sec E-15 H 8.0 grams /kg 5.2.1.3 t. E7-2 2226c L

4-MF !CI9ar rul Raat 1 gica1 Contro1s Departmenta1 Procedure 6610-PLN-4200.01 Revision No. Tit 1e 1 offsite Dose Calculation Manua1 (000() APPENDIX A-T REFERENCES (Page_3 of 4) PARAMETERS USED IN DOSE TACTOR CALCULATIONS \\ Origin of Value Tabte in Section of Site-Parameter. -Value R.G. 1.109 NUREG-0133 Specif ic

• • • For R3

'1 (Graes/ Cow / Milk) lp, Q, 50 kg/ day E-3 UJ Each age group E-5 t 5.3.1.3 kw 5.73 E-7 sec F. Each e1ement E-1 r Each e1ement type E-15 DFL - Each age group and E-11 thru nuclide E-14 Note 1 3 2 E-15 Y, 0.7 kg/m t, 7.78 E + 6 see E-15 2 E-15 Y. 2.C kg/m t, 1.73 E + 5 see E-15 5.3.1.3 f. 1.0 5.3.1.3 f. 1.0-5.2.1.3 H -8.0 grams /kg l E7-3 2226c l l

..~ Muclear TM1 Raeio1 gica1 contro1. Departmental Procedure 6610-PLN-4200.01 Revision No. -Title 1 Of f site Dose Calculation Manual (ODW) APPENDIX A-F REFERENCES (Paga J of 4) NOTES- ~ For Inhalation and ingestion dose factors were taken from the indicated source. 1. 1 each age group, for each nuclide,'the organ dose factor used was the highest dose f actor for that nuclide and age group in the referenced table. Annual land ourveys have Typically beef cattle are raised all year on pasture. 2.- indicated that the small number of gests raised within 5 miles typically are used for grasa control and not food or milk. Nevertneless, the goats can be treated as full maat sedeces where present, despite the fact that their numbers cannot sustain -the scat consumption rates of Table E-5, NF *.G-0133. REFERENCES Regulatory cuide 1.109, "Csiculation of Annual Doses to Man from Routine Releases il 1 ;' of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, 4-Appendix.I,": Revision 1, October 1977. 50. .THI-1 Technical Specifications, attached to Facility operating License No. DPR- '2. NUREG-0133, " Preparation of Radiological Effluent Technical Specificaticas for 3 Nuclear Power Plants," October 1978. L l u l [.. l 6c E7-4 1 .,. _}}