ML20086N228

Rev 7 to ODCM

ML20086N228
Person / Time
Site:	Comanche Peak
Issue date:	12/06/1991
From:	Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
References
PROC-911206, TUS-91385, NUDOCS 9112190177
Download: ML20086N228 (62)

Text

.

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?11UELECTRIC OFFICE MEMORANDUM CPSES-9130795 TUS-91385 December 6, 1991 TO:

All Copy Holders COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

REVISION 7 TO THE CPSES OFFSITE DOSE CALCULATION MANUAL (00CM)

Enclosed is Revision 7 to the CPSES Offsite Dose Calculation Manual (00CM) an receipt acknowledgement sheet.

Return the acknowledgement sheet as specified.

- If you have any questions regarding the 00CM, contact Connie Wilkerson at (214)-812-8819.

O dcrcjr D. R. Woodlan Docket Licensing Manager CLW/grp Enclosure c-CCS E06 File f 953 0-o gt,

/

I I 9112190177 911206 gna noacx osooggp

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COMANCHE PEAK STEAM ELECTRIC STATION Et OFFS!TE-DOSE CALCULATION. MANUAL o

INSTRU; TION SHEET S

.The following instructional information is being furnished to help insert Revision 7 into thi Comanche Peak Steam Electric Station 00CM.

In.accordance with CPSES.Techni al Specification 6.14b, this revision of the 00CM became effective w5 m i'. was approved by the Vice President, Operations on December 4, 1991.

3 Discard the old sheets and insert the new sheets as indicated below.

itoldets orithe CPSES 00CM should keep these instruction sheets in the front of

, the Effective Page Listing as e roccrd of the changes, until. a new listing is 4

issued.

g Engorg Insert i'

i

' thr!,

thru

. xili-xiii

[I-3/4-2:

' 3/4-2 l'3/4-5 I 3/4-5 r-I 3/4-18:

I 3/4-18

' Th. -

I:3/4 I 3/4-20 M

'I 3/4-22a-I:3/4-22a I 3/4-22b I 3/4-22b-1 I-B 3/4a4-

-! B 3/4-4 I B 3/4-5:

I B 3/4-5 113-1!.-

II 1-1 thru.

1thru LII'I-25 II 1-27

-II'2-45 II 2-45 i

I1 2-46 1I 2.

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-thru EFu-8 EPL-9 O

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4 OFFSITE DOSE CALCULATION MANUAL

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FOR 10 ELECTRIC COMANCilE PfAr. STCAM ELECTRIC STATION s

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i Rev. 7 12/91

(

TABLE OF CONTENTS O

l'192 List of Tables vi List of Figures viii Cross Reference to Technical Specifications and REC ix References xii Introduction xiii PART I - RADIOLOGICAL EFFLUENT CONTROLS SECT 10N 1.0 - DEFINITIONS 1 1-0 SECTION 2.0 - NOT USED I 2-0 SECTIONS 3.0 AND 4.0 - CONTROLS AND SURVFILLANCE 1 3/4-0 REQUIREMENTS 3/4.0 -

Applicability I 3/4-1 3/4.3.3.4 - Radioactive Liquid Effluent 1 3/4-3 Monitoring Instrumentation Os 3/4.3.3.5 - Radioactive Gaseous Effluent 1 3/4-8 Monitoring Instrumentation 3/4.3.3.6 - Meteorological Monitoring

! 3/4-13 Instrumentation 3/4.7.15 -

Sealed Source Leakage 1 3/4-15 3/4.11.1.1 - Liquid Effluent Concentration I 3/4-17 3/4.11.1.2 - Liquid Effluent Dose 1 3/4-21 3/4.11.1.3 - Liquid Radwaste Treatment System I 3/4-22 3/4.11.1.4 - Evaporation Pond I 3/4-22a 3/4.11.2.1 - Gaseous Effluent Dose Rate 1 3/4-23 3/4.11.2.2 - Gaseous Effluent Cose - Noble Gas 1 3/4-27 3/4.11.2.3 - Gaseous Effluent Dose - lodine-131, I 3/4-28 lodine-133, Tritium, and Radioactive Material in Particulate Form 3/4.11.2.4 - Gaseous Radwaste Treatment System I 3/4-29 ij Rev, 7 12/91

~

4TABli 0F CONTENTS EAR

.l

=f]-

3/4'.11.4'-

\\

Ra'ioactive Effluents Total Dose 1 3/4-30 d

3/4.12,1 -

Radiological Environmental Monitoring I 3/4-32 i

Program 3/4.12.2 -

Land Use Census I 3/4-44

-3/4.12.3 --

Interlaboratory Comparison Program I 3/4-45 BASES.

I B 3/4-0 SECTION 5.0 - DESIGN FEATURES I 5 5.1.3 -

Maps Defining Unrestricted Areas and I 5-1 Site Boundary for Radioactive Gaseous and Liquid Effluents SECTION 6.0 - ADMINISTRATIVE CONTROLS I 6-0 p

6.9.1.3 -

Annual Radiological Environmental.

I 6-1 Operating Report 6.9.1.4 -

Semiannual Radioactive Effluent I 6-2 Release' Report 6.14 Offsite Dose Calculation Manual I 6-3 PART II -' CALCULATIONAL METHODOLOGIES

.1.0 -LIQUID EFFLUENTS II 1-1 11.1-'10CFR20 And Radiological Effluent Control -

II 1-2 Compliance

1.1.1-I).ctopic Concentration of the Waste Tank II 1-2 1.1.2 MaximumEffluentFlowRate(f)

II 1-3 1.1.3 Dilution of Liqui' Fffluents II 1-4 1.1'. 4 Actual Dilution f u or (ADF)

II 1-5 1.1.5 RequiredDilutionFactor(RDF)

II 1-6 1.1. 6 ~

10CFR20 Compliance II 1-7 Rev. 7 iii 12/91

u TABLE OF CONTENTS EA22 1.2RadiationIMonitor. Alarm Setpoints-

-II 1-8

-1.2.1-.

= Primary Liquid Effluent Monitor II 1-8 XRE-5253-

1. 2. 2 : -Turbine Building Sump Effluent II 1-9 '

Radiation Monitor 1RE-5100

1. 2. 3 ' -Service Water Effluent Radiation 11 1-10 Monitor 1RE-4269/4270 1.3 Dose Calculations for Liquid Effluents II 1-11 1.3.1

' Calculation of Dose Due to II 1-12 Liquid Releases li3.2? Calculation of Dose Due to II 1-13 Radionuclide Buildup in the Lake j

-:1.4s Dose Projections for Liquid

-II 1-14

-Effluents-L.5--Definitions of Common Liquid Effluent Parameters II 1-15 1

2.0. GASEOUS EFFLUENTS II 2-1 2.1' Gaseous' Effluent Monitor Setpoints II 2-1 L2.1.1.

Dose Rates Due to Noble Gases II 2-3 1

2.1.2

-Plant Vent' Stack Noble Gas II 2-5 Monitors XRE-5570A/B and XRE-5567A/B

.2.1.3 Plant Vent Flow Monitors II 2-7 2.1.4 Auxiliary Building Ventilation Exhaust II 2-8 Monitor XRE-5701-

-2.1.5 Containment Atmosphere Gaseous.

II 2-10 Monitor 1RE-5503 2.1.6 Dose Rates Due-to Radiciodines, II 2-12 Tritium, and'Particulates

2.1.7

- Plant-Vent Stack Iodine Monitors II 2-13

'XRE-5575A/B

'r --

2.1.8 Plant

Vent Stack Particulate II 2-14 Monitors XRE-556BA/B jy Rey, 7 12/91

t t

TABLE OF CONTENTS

[N U

2.2 Gaseous Effluent Oose Calculations II 2-17 2.2.1

-Dose Due to Noble Gases II 2-17

2. 2. 2.

Dose Due to Radioiodines, Tritium, II 2-18 and Particulates 2.2.3 Dose. Projections for Gaseous Effluents II 2-20 2.2.4--

Dose-Calculations to Support Other II 2-20 i

Requirements 2,3 - Meteorological Model 11 2-47 2.3.1 Dispersion Calculations 11 2-47

-2.3.2 Deposition Calculations 11 2-49 E.4 Definition of Gaseous Effluent Parameters II 2-50 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING II 3-1 3.1 Sampling Locations II 3-1

.3.2 Interlaboratory Comparison Program II 3-l'

[

APPENDIX-A.L-Pathway Dose' Rate-Parameter (Pj)

A-1 B. --. Inhalation Pathway Dose' Factor B-1

-C.-

Ground Flane Pathway Dose Factor C1 0.-

Grass-Cow-Hilk Pathway Dose Factor D-1 E.

Cow-Meat Pathway Dose Factor-E-1 F._

Vegetation. Pathway Dose Factor F-1

G.

Supplemental Guidance Statements G-1 I

v Rev. 7 12/91

List of Tables rR Table No.

litit EAgg EART I - RADIOLOGICAL EFFLUENT CONTROLS 1.1 Frequency Hotation I 1-5 1.2 Operational Modes I 1-6 3.3-7 Radioactive Liquid Effluent Monitoring I 3/4-4 Instrumentation 4.3-3 Radioactive Liquid Effluent Monitoring I 3/4-6 Instrumentation Surveillance Requirements 3.3-8 Radioactive Gaseous Effluent Monitoring I 3/4-9 Instrumentation Ac3-4 Radioactive Gaseous Effluent Monitoring I 3/4-11 Instrumentation Surveillance Requirements 3.3-9 Meteorological Monitoring Instrumentation I 3/4-14 4.11-1 Radioactive liquid Waste Sampling and I 3/4-18 Analysis Program 4.11-2 Radioactive Gaseous Waste Sampling and I 3/4-24

()

Analysis Program 3.12-1 Radiological Environmental Monitoring I 3/4-34 Prograni

-3.12-2 Reporting Levels for Radioactivity I 3/4-40 Concentrations in Environmental Samples 4.12 Detection Capabilities for Environmental I 3/4-41 Sample Analyses-(LLDs)

PART-II --CALCULATIONAL METHODOLOGIES 1.1-Summary of Liquid Release Pathways II 1-19 1.2 Site Related Ingestion Dose Commitment II 1-20 Factor (Ajr) 2.1 Dose Factors for Exposure to a Semi-

!! 2-12 Infinite Cloud of Noble Gases 2.2 Pathway Dose Rate Parameter (Pj)

II 2-23 2.3 Pathway Dose Factors II 2-24 Rev 7

12/91 vi

List of Tabiti Table No.

lille Egge

-~

'd 2.4 Controlling Receptor Pathways and

!! 2-45 Locations, and Atmospheric Dispersion Parameters (For Dose Calculations Required by Radiological Effluent Control 3/4.11.2.3) 2.5 Deleted 11 2-46 3.1 Environmental Sampling Locations

!! 3-3

( %).

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L

+

vii Rev. 7 12/91

List of Fioures-c Fioure Title Eagg l

PART l-RADIOLOGICAL EFFLUENT CONTRO.LS 5.1-3 Site Boundary and Unrestricted Areas I 5-2 PART II - CALCULATIONAL METHODOLOGIES 1.1 Liquid Effluent Discharge Pathways II 1-24 1.2 Circulating Water Pump Curves

!! 1-26 1.3 Energy Response to Gamma Radiations 11 1-27 for RD-33 Type Detector 2.1 Gaseous Waste Processing System 11 2-56 2.2 Plume Depletion Effect for Ground 11 2-57 Level Releases 2.3 Vertical Standard Deviation of 11 2-58 Material in a Plume

-2.4 Relative Deposition for Ground-II 2-59 Level Releases (a~'i 2.5 Open Terrain Correction Factor 11 2-60 3.1 Radiological Environmental Monitoring II 3-9 Locations V

viii Rev. 7 12/91

Cross Reference to Technical SDecifications and REC

(^).

Humber or Document Section Reauirement 00CM Section PART I-RADIOLOGICAL EFFLUENT CONTROLS (REC 1 Tech Specs 6.8.3.e.1 Effluent monitoring instrumentation 3/4.3.3.4 and operability, surveillance, and 3/4.3.3.5 setpoint requirements Tech Specs 6.8.3.e.2 Limit liquid effluent concentration 3/4.11.1.1 Tech Specs 6.8.3.e.3 Effluent monitoring, sampling, and 3/4.11.1.1 and analysis requirements 3/4.11.2.1 Tech Specs 6.8.3.e.4 Limit doses due to liquid effluents 3/4.11.1.2 Tech Specs 6.8.3.e.5 Determine cumulative and projected 3/4.11.1.2, doses due to radioactive effluents 3/4.11.2.2, 3/4.11.2.3, 3/4.11.1.3, and 3/4.11.2.4 Tech Specs 6.8.3.e.6 Effluent treatment systems 3/4.11.1.3 and operability requirements 3/4.11.2.4 Tech Specs 6.8.3.e.7 Limit gaseous effluent dose rate 3/4.11.2.1 Tech Specs 6.8.3.e.8-Limit noble gas air dose 3/4.11.2.2 Tech Specs 6.8.3.e.9 Ltmit gaseous effluent iodine and 3/4.11.2.3 particulate dose Tech-Specs 6.S.3.e.10 Limit total dose 3/4.11.4 Tech Specs 5.8.3,f.1 Monitoring, sampling, and analysis 3/4.12.1 of radiation in the environment Tech Specs 6.8.3.f.2 Land Use Census 3/4.12.2 Tech Specs 6.8.3.f.3 Interlaboratory Compm ison Program 3/4.12.3 PART II - CALCULATIONAL METHODOLOGIES REC 3/4.11.1.1 Liquid effluent concentration 1.1 REC 3/4.11.1.2 Dose due to liquid effluents 1.3 REC 3/4.11.1.3 Dose projections for liquid 1.4 releases (n) u,'

$x Rev. 7 12/91

C'ross Reference to Technical Soecifications and REC

f s ;

Number or f

Qgcument Section 8touirement 00CM Section

REC 3/4.11.2.1.a Dose rate due to nobie gases 2.1.1

~ REC

-3/4.11.2.1.b -Dose rate due to iodine, tritium, 2.1.6 and particulates with half lives greater than eight days REC 3/4.11.2.2

-Air dose due to noble gases 2.2.1 REC-3/4.11.2.3 Doses due to todines, tritium, 2.2.2 and particulates with half-lives greater than eight days REC 3/4.11.2.4 Dose projections'for gaseous 2.2.3 releases REC 3/4.11.4 Total dose due to releases of 2.2.4 radioactivity and direct

. radiation REC =

l3/4.12.1 Description of; radiological 3.1 environmental sampling locations REC

-- 3/4.12. 2 l['

Dose calculations-for identifying 2.2.4 changes to environmental sampling 1%

locations

-REC 3/4.12.3 Description of the Interlaboratory 3.2 Comparison Program s

REC

-3.3.3.4 Radioactive liquid effluent-monitoring channels alarm / trip a

setpoints o turbine building sump (monitorliquid waste monitor XRE-525 1.2.1 o

1.2.2 (1RE-5100)

\\.L x

0 service water. monitor 1.2.3 g

(1RE-4269/4270) f)

x x

Rev. 7 12/91 l

t Cross Reference to-Technical Specifications and REC Number or-Document itttion Reauirement ODCM Section

~ REC 3.3 3.5 Radioactive gaseous effluent >

mod toring channels alarm / trip utpoints o noble gas release rate monitors 2.1.3 XRE-5570AandXRE-5570B(WGRM releaseratechannels) o noble gas activity monitors 2.1.2 XRE-5570A and XRE-55708-(WRGM low range activity channel)

XRE-5567A and XRE-55678 (PIG noble gas channel)_

o waste gas holdup system monitor-2.1.4 (auxiliary building vent monitor)

XRE-5701 o sampler flow rate monitor.

2.1.3 XFT-5570A2/B2

= Tech Specs 3.3.3.1 Radiation monitoring channels alarm / trip setpoint Containment atmosphere gaseous 2.1.5 o

monitor

/~T monitor)(containmentvent 1RE-5503 y.-

Tech Specs 6.9.1.4 Assessment of radiation doses due 2.2.4 REC 6.9.1.4 to liquid and gaseous effluents released _during the previous year Tech Specs 6.9.1.4 Assessment-of doses to members of 2.2.4 REC 6.9.1.4 the public inside the site boundary

' Tech Specs 6.9.1.4 Assessment of doses to the most 2.2.4 REC 6.9.1.4 likely exposed member of the public from reactor releases and direct radiation b,

xi Rev. 7 12/91

REFERENCES 1.

Boegli, J.S., R. R. Bellamy, W. L._Britz, and R. L. Waterfield,

(

)

" Preparation of Radiological Effluent Technical Specifications for

's-Nuclear Power Plants," NUREG-0133 (October 1978),

2. -

Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix 1, U. S. NRC Regulatory Guide 1.109 Rev. 1 (October 1977).

3.

" Environmental Report," TU Electric, Comanche Peak Steam Electric Station.

4

" Final Safety Analysis Report," IU Electric, Comanche Peak Steam Electric Station.

5.

Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, U.S. NRC Regulatory Guide l.111 (March 1976).

6.

Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Release from Light - Water - Cooled Reactors, U.S.

NRC Regulatory Guide 1.111, Rev. 1 (July 1977).

7.

Meteorology and Atomic Energy; Edited by Slade, D. H.; U. S. Department of Commerce (July 1968).

B.

"Ur*t 1 Technical Specifications," TU Electric. Comanche Peak Steam

(")

El..tric Station.

G' 9.

Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program (Generic Letter 89-01),1.lSNRC, January 31, 1989.

10.

CPSES. Technical Evalu; tion No. RP-90-3077, " Calculation of Site Related Ingestion. Dose Commitment Factors For Sb-122."

11.

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," USNRC Regulatory Guide 1.109 (March 1976).

Iv)

• ii Rev. 7 12/91

INTRODUCTION TheOFFSITEDOSECALCULATIONMANUAL(00CH)isasupportingdocumentofthe p.

()

CPSES Technical Specification.

Part I of the ODCM contains (1) t,he Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 6.8.1. (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Technical Specifications 6.9.1.3 6nd 6.9.1.4, ant. (3) Controls for Meteorological Monitoring Instrumentation and 50aled Source Leakage.

Part 11 of the ODCH describes the methodology and par *. meters to be used in the cak.ulation of offsite doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints.

Part 11 of the ODCM also contains a list and graphical description of the specific sample locations for the radiologict.1 environmental monitoring program.

Liquid and Gaseous Radwaste Treatment System configurations are shown in Figures 1.1 and 2.1 The 00CM will be maintained at the plant for use as a reference guide and training docurnent on accepted methodologies and calculations.

Changes in the calculation methods or parameters will be incorporated %to the ODCM in order to assure that the ODCM represents the present meth.^ ' y in all applicable TO Electric initiated changes to the ODCH wil,,e implemented in areas.

accorda::ce with Section 6.14 of the Technical Spec 1(ications.

The OOCH follows the methodology and models suggested by NUREG-0133 (Ref. 1) and Regulatcry Guide 1.109, Revision 1 (Ref. 2).

Simplifying assumptions have

/G bee applied in this manual where applicable to provide a more workable documeni for implementing the Radiological Effluent Control requirements.

V This simplified approach will result in a more conservative dose evaluation, but requires the least amouit of time for establishing compliance with regulatory requirements.

This manual is designed to provide necessary information in order to simplify the dose calculations.

Tte dose calculations can be optionally expanded to severti levels of effort. The complexity of the dose calculations can be expanded by several levels of effort, aiming toward a full calculaticn in accordance with Regulatory Guide 1.109.

Future changes to the ODCM may be initiated to implement more complex calculations as systems become available and are validated that can reliably, economically and properly perform these more complex calculations.

A beneficial approach to implementing the Radiological Effluent Control '.ogram and Regulatory Guide 1.21 (Semiannual Radioactive Efflue9 Release Report) requirements is to use a computerized system to determine the effluent releases and update cumulative doses.

Where additional claiification or information is required to adequately implement certain ODCM requirements, supplemental guidance is provided in Appendix G of Part !!.

5 OV L,.

12/91 xiii

APPLICABILITY SURVEILLANCE REOUIREMENTS O

4.0.1 Surveillance Requirements shall be vt during the OPERATIONAL MODES or other conditions specified for individua* Controls unless otherwise stated in an individual Surveillance Requirement.

Each Sarveillance Requirement shall be performed within the specified 3. '. 2 t i interval with a maximum allowable extension not to exceed 25% of the 7

111ance interval. Exceptions to these requirements are stated in the s<

n.vidual controls.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Surveillance Requirement 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Control.

The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Surveillance Requirements do not have to be performed on inoperable equipment.

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

This provision shall not prevent p ssage through or to OPERATIONAL g

MODES as required to comply with ACTION requirements.

Exceptions to these g

requirements are stated in the individual controls, n

b COMANCHE PEAK - UNIT 1 1 Ua-2 REV. 7 12/91

- - - - - _ - - _ =

1 TABLE 3.3-7 (Continued 1 ACTION STATEMENTS

' ACTION 30- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:

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

Control 4.11.1.1.1, and b.

At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 31-With the number of channels OPERABLE less than required by the Minimum Channels-OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity at a lower limit of detection of no more than 10-7 microcurie /ml:

a. -At least once per-12 hours when the specific activity of the i

secondary coolant is greater than 0.01 microcurie / gram DOSE EQ'jlVALENT l-131, or i

b.

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

ACTION 32-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operations may continue s

provided that:-

a.

With the component cooling water monitors (IRC-4509, 1RE-4510, &

1RE-4 1X10'g11) OPERABLE and indicating an activity of less than microcurie /ml, a grab sample is collected and analyzed for radioactivity at a lower limit of detection of no more than 10-7 microcurie /mi at least every 31 days; or b.

At'least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab sampics are collected and analyzed for more than 10gadioactivity at a lower limit of detection of no microcurie /ml.

HOTE:

Collection of grab samples is not required when there is no 7

process flow at the monitor.

ACTION 33-With the number of channels OPERABLE less than required by the Minimum Chamels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />'during actual releases.

Pump performance curver generated in place may be used to est b. ate flow.

O COMANCHE PEAK'- UNil l' 1 3/4 5 REO 7 12/91 1 ^

4

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,_.--,,.-,,--,>q y--.-w---,

y3., -

7,,,

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--v-.-,.--,,

,,.,:-_--,..m.g,,,-+,, ~. -

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TABLE 4.11 1 RadlDaCtive Liquid Waste Sampling and Analysis Program LIQUID RELEASE SAMPLING MINIMlUM TYPE OF ACTIVITY LOWER LIMIT OF O

TYPE FREQUENCY ANALYSIS ANALYSIS DETECTION (1)

FREQU'!NCY

( CVmi) 1 A. Batch Waste Release (2)

P P

Principal Osmma 5.CE 07 Tanks to the C6teulating Each Batch Each Batch Emnters (3) 7 Water Discharge tt31 1.0E 06

a. Waste Mennor Tanks DissoNed & Entrained 1.0E.05 Gases (Gamma Emnters) b LaundryHoldup

& Monnor Tanks M

H3 1.0E 05 M

hW Gross Alpha 1.0E 07 C'

p Tan s (8) o St69,St90 5 0E 08 Fe 55 1.0E 06 l

18. Batch Waste Release (2)

P P

Principal Gamma 5.0E 07 Tanks to the LYW Pond Each Batch Each Batch Emitters (3)

a. Condensate Polisher Backwash Recovery Tanks (6.7)

MEG

b. Component Cooling n

Water Drain

()

Tank (7)

c. Waste Water H3 1.0E 05 Holdup Tanks (6.8) 2A. Continuous Release (5)

Dalty Orab Compoone Principal Oamma 5.CE 07 to the Circulating Sample (9) over pond Emnters (3)

Water Discharge discharge

a. Low Volume Waste Pond Effluents DissoNed & Entralned 1.0E 05 Gans:(Camma Emeters)

H3 1.0E 05 Gross Alpha 1.0E 07 Q

St89,St90 5.0E 08 Componne (4)

Fe 55 1,0E 06 9B. Continuous Releases (5)

W W

Principal Gamma 5 CE 07 to the LVW Pond Grab Sample Emitters (3)

a. Turbine Btdg. Sump

~

No. 2 Emuents (6.7) 1131 1.0E 06 f

a. Turbine Bidg. Sump No. 4 Effluents (6,7)

H3 1.CE.05 COMANCHE PEAK - UNIT 1 1 3/4-18 REY. 7 12/91

s TABLE 4.11-1 (Continued)

TABLE NOTATIONS (q

(3) The principal gamma emmiters for which the LLO specification applies include the following radionuclides: Mn-54, Fe-59, Co-58 Co-60, Zn-65, Mo-99, Cs-134. Cs-137, Ce-141.

Co-144 shall also be measured, but with an LLO of 5 x 10-6 This list does not mean that only these nuclides are to be considered. Other ganna peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 in the format outlined in Regulatory Guide 1.21, Appendix B.

Revision 1. June 1974.

(4) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6) These waste streams shall be sampled and analyzed, in accordance with this table, if radioactive material is detected in the LVW Pond composite 7

samples in cocentrations that exceed 10% of the limits of 10 CFR 20, Appendix B. Table II, Column 2.

%is sampling shall continue until 2 consecutive samples from the waste stream show thtt the concentration of radioactive materials in the waste stream is less than or equal to 10% of the limits of 10 CFR 20, Appendix B. Table II, Column 2.

(7) All flow from these taste streams shall be diverted to the Waste Water Holdup Tanks if activity is present in the waste stream in concentrations that exceed the limits of 10 CFR 20 Appendix B. Table !!, Column 2.

Sampling and analysis of the respective Tanks or sumps are not required when flow is diverted to the Waste Water Holdup Tanks.

(B) Waste Water Holdup Tanks (WWHT) shall be discharged directly to the Circulating Water Discharge Tunnel when results of sample analyses indicate activity in concentrations that exceed the limits of 10 CFR 20 Appendix B. Table !!, Column 2.

Otherwise, WWHTs may be dhcharged to the Low Volume Weste Pond. WWHT discharges to the Circulating Water Discharge Tunnel shall be sampled and analyzt.d per item 1A.c of this table.

WWHT discharges to the LVW Pond shall be sampled and analyzed per Item 18.c of this table.

(9) Samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while the release is occurring.

To be representative of the liquid effluent, the sample volume shall be proportioned to the effluent stream discharge volume.

The ratio of sample volume to effluent discharge volume shall be maintained constant for all samples taken for the composite sample.

(3 G)

COMAtlCHE PEAK - UNIT 1 1 3/4-20 REV. 7 12/91 v.

1em

--r y -

w-+

r

~w

RADIDACTIVE EFFLUENTS r

LVW POND RESIN INVENTORY l7-

.g CONTROLS 3.11.1.4 The quantity of radioactive material contained in resins trar.sferred 7

to the LVW Pond shall be limited by the following expression:

%'I

< i.0 excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8 day half life, where*kj=

pond inventory limit for singir

'lionuclide"j"(Curies),

Cj =

10 CFR 20, Appendix B. Table !!,,olumn 2, concentration for singleradionuclide"j"(microcuries/ml),

i l

V=

volume of resins in the pond (gallons), and 264 =-

unitconversionfactor(microturies/Curiepermilliliter/ gallon).

7 APPLICABILITY: At all times.

l2 ACTION:

a.

. With the quantity of radioactive material in the LVW Pond 7

-exceeding the above limit, immediately suspend all additions of radioactive material to the pond, b.

The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

]2 SURVElllMCE REQUIREMENTS 4.11.1'.4 The quantity of radioactive material contained in each batch of t

slurry (used powdex resin)_ to be transfr red to the LVW Pond shall be determined to be within the above limit by analyzing a representative sample of the slurry, and batches to be transferred to the LVW Pond shail be-limited by the_ expression:

I

< acos-R I C; HCVMI where:-

Qj =

concentration of radioactive materials (microCuries/gm) in wet, drainedslurry(usedpowdexresin)forradionuclide"j", excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8. day half-life.

The analysis shall include at least Ce-144, Cs-134. Cs-137. Co-58 and Co-60.

Estimates of the O

Sr-89 and Sr-90 batch concentration shall be included based on the

-O most recent quarterly composite analysis, PEV. 7

- COMANCHE PEAK - UNIT 1

! 3/4-22a 12/91 w

e.

,,.-,-,..,--,,,,ww-,-

.r,-,,,-,--*3-,,,,,w-,-

.,,--,------7---,,-.,,-,-m--c..,n

---*,,%---r.e.-t--

w-

- e

-en*'e' sea e'r--t---e'e+r

=-n--

RADIDACTIVE EFFLUENTS 7

LVW POND RESIN INVENTORY SURVEILLANCE REOUIREMENTS (Centinuedi Cj =

10 CFR 20, Appendix B Table 11 Column 2, concentration for singleradionuclide"j"(microcuries/ milliliter),and 7

R=

Slurry volume to resin weight ratio (ml/gm) 4 0

REV. 7 COMANCHE PEAK - UNIT 1 1 3/4-22b 12/91

r PAD 10 ACTIVE EFFLUENTS BASES g

t QME (Continued)

This control applies to the release of radioactive materials in liquid effluents from each unit at the site.

For units with shared Radwaste Systems, the liquid effluents from the shared system are to be proportional among the units sharing that system.

3/4.11.1.3 L10VID RADWASTE TREATMENT SYSTEM The OPERABILITY of the Liquid Radwaste Treatment 3ystem ensures that this system will be available for use whenever liquia effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievabla." This control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section !!.0 of Appendix 1 to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forv.h in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents.

This control applies to the reicase of radioactive materials in liquid effluents from each unit at the site.

For units with shared Radwaste Systems, f

the liquid effluents from the shared system are to be proportioned among the

(

units sharing that system.

3/4.11.1.4 LVW POND RESIN INVENTORY The inventory limits of the LVW Pond are based on limiting the 7

consequences of an uncontrolled release of the pond inventory.

The expression in Control 3.11,1.4 assumes the pond inventory is uniformly mixed, and that the pond is located in an unrestricted area as defined in 10 CFR Part 20, and that the concentration limit in Note 1 to Appendix B of 10 CFR Part 20 applies.

This expression limits the total quantity of radioactive materials

.in resins discharged to the LVW Pond to a value such that the average concentration in the resins, calculated over the total volume of resins in the pond, will not exceed the Maximum Permissible Concentrations (MPCs) specified-in-10 CFR 20 Appendix B. Tdble 11, Column 2.

Because Control 3.11.1.1 limits the concentration of liquid effluents from other pathways to the LVW Pond to the 10 CFR 20 HPC values, also limiting the average concentration in resins to the MPC values will assure that the average concentration in the pond from all sources, calculated over the total volume of the pond (liquid and resins),

will not exceed the 10 CFR 20 HPC values.

%/

COMANCHE PEAK - UNIT 1 I B 3/4-4 REV. 7 12/91

RADIDACYIVE EFFLUENTS

}

BASES LVW POND JJSIN INVENTORY (Continued)

The batch limits of slurry to the LVW Pond assure that radioactive 7

material in the slurry transferred to the Pond are "as low as is reasonably achievable" in accordance with 10 CFR 50.36a.

The expression in Control 4,11.1.4 assures no batch of slurry will be transferred to the Pond unless the sum of the ratios of the activity of the radionuclides to their respective concentration limitation is less than the ratio of the 10 CFR Part 50 Appendix I, Section II A. total body level to the 10 CFR 20.105(a), whole body dose limitation, or that:

i C,"

sesaseawp

= toss where:

cj =

radioactive slurry concentration for radionuclide "j" entering the UNRESTRICTED AREA POND, in microCuries/ milliliter, and Cj =

10 CFR 20, Appendix B. Table !!, Column 2, concentration for single radionuclide "j", in microCuries/ milliliter.

The average concentration of radioactive materials in a particular batch of resin slurry released to the LVW Pond is dependent upon the slurry volume 2

to resin weight ratio. Additionally, the wet drained slurry density is approximately 1 gm/ml and the absorption characteristics for gamma radiation tre essentially that of water. Therefore, 13.I

< acoe l C

. C M aeWe g

I

< anos

• R where the terms are dtfined in Control 4,11,1,4, The batch limits provide assurance that activity input to the LVW Pond 7

wiil be minimized, and a means of identifying that the radioactive material released is within the inventory limitation of Control 3.11,1.4.

O COMANCHE _ PEAK - UN]T 1

.] 8 3/4 5 REV. 7 12/91-

1 SECTION 1.0 t

LIQUID ETFLUENTS The Comanche Peak Steam Electric Station is located on Squaw Creek 7

Reservoir (SCR),whichservesasthepointofsupplyanddischargefor the plant circulating water. Radioactive liquid effluent releases i

from the primary radwaste p,'ocessing system are batch type releases, i

U fromtheLaundryHoldup&MonitorTanks(LHMT)andWasteMonitorTanks (WMT),dischargedtoSCRviatheCirculatingWaterDischargeTunnel.

Potentially radioactive liquid effluent releases from secondary systems include a continuous release from the Turbine Building Sumps

-(TBSump),andbatchreleasesfrom'theComponentCoolingWaterDrain i

Tank.(CCWDT),andtheCondensatePolisherBackwashRecoveryTanks (CPBRT).. These secondary pathways ars normally discharged to the Low Volume Waste (LVW) Pond for chemical treatment.

The LVW Pond normally discharges to SCR via the circulating Water Discharge Tunnel.

Alternatively, secondary waste streams may be routed to the Waste WaterHoldupTanks(WWHT).

The WWHis may be released on a batch basis to the LVW Fond or to SCR via the Circulating Water Discharge Tunnel, depending on the levels of radioactivity present.

Table 4.11-1 of Part I of this document' requires that secondary waste streams be diverted to the WWHT's if radioactivity is present in the waste stream in concentratiens that exceed the limits of 10 CFR 20 Appendix B.

Table 11. Column 2.

Also, releases from the Station Service Water (SSW)Systemaremonitoredforradioactivity,althoughnosignificant releases of radioactivity are expected from-this pathway.

A su m ry of all liquid effluent release sources, volumes, flow rates, 7

and associated radiation monitors is shown in Tatie 1.1.

A flow diagram of all liquid effluent discharge pathways is shown_in Figure 1.1.

l i O COMANCHE PLAK - UNIT 1-11 1-1 Rev. 7 12/91

The liquid effluent radiation monitors shown in Figure 1.1 are part of 7

the plant Digital Radiation Monitoring System (DRMS) supplied by SorrentoElectronics(FormerlyGeneralAtomics).

Since the DRMS monitors provide a digital output, they may be calibrated to read out intheappropriateengineeringunits(i.e.uC1/ml).

The conversion factor for detector output from counts per minute to pCi/ml is i

determined in the calibration process and input into the database for the monitor microprocessor.

1.1 10 CFR 20 AND RADIOLOGICAL EFFLUENT CONTROL COMPLIANCE To demonstrate compliance with 10 CFR 20.106, 00CM 7

Radiological Effluent Control 3/4.11.1.1 requires that the concentration of radioactive material released in liquid effluents to UWRESTRICTED AREAS be limited to the concentrations specified in 10 CFR 20, Appendix B. Table 11, Column 2, for radionuclides other than dissolved or ettrained noble gases, and to 2E-4 uti/mi for dissolved or e,1 trained noble gases.

10 CFR 20 compliance is checked for all

()

discharges to SCR via the Circulating Water Discharge Tunnel listed in Table 1.1.

Because the LVW Pond is located in an UNRESTRICTED AREA, discharges to the LVW Pond are also checked for 10 CFR 20 compliance.

If radioactive materials are present in the LVW Pond discharge in concentrations that, exceed 10% of the limits of 10 CFR 20. Appendix B. Table 11, Column 2, then all inputs to the LVW Pond are sampled and checked for compliance with 10 CFR 20.

The following methodology is used to determine compliance with these limits.

7 1.1.1 Isotopic Concentration of the Waste T ck A

Determine the isotopic concentration in waste stream to be released:

ICg=IC + (C, + C, + C +Cg)

[Eq. 1-1}

g g

i 8

(./

COMANCHE PEAK. UNIT 1 11 1 2 Rev. 7 12/91

fU Wriero:

1=

Sum of the concentrations of each radionuclide,intherelease(UCi/ml),

7

,s=

Sum of the concentrations of each measured gamma emitter, g, (uti/ml) as required by Radiological Effluent Control 3/4.11.1.1.

Table 4.11-1.

C, a

concentration of alpha emitters as mTosured in the most recent composite sample 7

(Ci/ml) required by Radiological Effluent Control 3/4.11.1.1.

Table 4.11-1.

(Sample analyzed for gross alphaonly)

Cs concentration or 89 r and 90 r as

=

5 S

measured in the most recent composite sample 7

(uti/ml) required by Rcdiological fffluent Control 3/4.11.1.1, Table 4.11-1.

Ct concentration of 3H as measured in the most

=

recent composite sample (uCi/ml) required by n

(

)

Radiological Effluent Control 0/4.11.1.1 Table 4.11-1.

Ce F

concentration of 55Fe as measured in

=

l the most recent composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1. Table 4.11-1, 1.1,2 Effluent Flow Rate (f1 The maximum effluent discharge flow rates for each release 7

source are shown in Tabl\\ 1.1.

For pre-release calculations, the maximum effluent flow rate is used.

For post-release calculations, the average effluent flow rate during tne release may be used.

Since the maximum effluent flow rate is used fer pre-release calculations, no setpoint is required for the flow measuring device for the effluent release line.

COMANCHE PEAK - UNIT 1

!! 1-3 Rev. 7 12/91

i I

i l

r 7

1.1.3 Dilution of Liouid Effluents Discharges to SCR via Circulating Wtter Discharge a.

Tunnel Since liquid effluents from the radwaste treatment 7

t system, Waste Water Holdup Tanks and the LVW Pond are j

mixed with circulating water prior to being discharged

(

to Squaw Creek Reservoir, compliance with 10 CFR 20 is a function of the circulating water flow rate.

The maximum circulating water flow rate per plent is 1.1 million gpm.

This is determined from the Ingersoll-

-Rand pump curves (Fig. 1.2) which indicate a flow rate 7

per pump of 275,000 gpm.

The actual circulating water dilution flow is given by:

F(diluting flow) = ( %)0 gpm/ pump) x (# of pumps) x 0.9 7

(Eq. 1-2]

Where: 0.9 = Safety Factor to compensate for flow 7

fluctuations from the rate predicted by the circulatingwaterpumpcurves(Fig.1.2).

As an additional consideration --the available_ dilution flow 7

for any release may be corrected'to allow for simultaneous releases from_the Radwaste Processing System, a Waste Water Holdup Tank,'and/or the LVW Pond (i.e., a radwaste system tank, a Waste Water Holdup Tank, and the LVW Pond may be dischargedsimultaneously.) For simultaneous releases, the available dilution flow for any release is reduced by the required dilution flow for any other concurrent releases.

O COMANCHE PEAK UNIT 1 II 14 Rev. 7 12/91-

_.__m,

... m.

6 s

Also, the ritevoir into which the diluted radweste flows may build up a concentration of radioactive isotopes.

It is therefore necessary to account for recirculation of previous 1.v discharged radionuclides.

This is accomplished as follows:

r' = r (1 - {

(cj/gyc p i

Where:

F'=

Adjusted Circulating Wter flow Rate C'$ =

Concentration of radionuclide i in the Reservoir ( C1/ml) as measured in the analysis of the monthly sample of the Reservoir required by Radiological Effluent Control a

3/4.12.1. Table 3.12,1, This sample is taken at the circulating water intake structure as indicated by location SW6 on Table 3.1 and Figure 3-1 of this manual.

NPCj*=

Maximum Permissible Concentration cf Radionuclide i V

F=

(275.000 gpm/ pump) x (f of pumps) x 0,9 h0TE:

If C'j is less than LLD then F' = F and no adjusted flow rate need be, considered in the calculation of ADF.

The LLD values used for this determination shall be the LLD valves for water given in Radiological Effluent Control 3/4.12,1. Teble 4.12-1, b,

Discharges to the LVW Pond Secondary release sources are discharged directly to the LVW Pond with no dilution (i.e., F=0) 1.1.4 Actual Oilution Factor (ADF)

ADF is the ratio of the effluent flow rate plus the circulating water flow rate divided by the effluent flow rate.

COMAf4CHE PEAK Ut41T 1 11 1-5 Rev. 7 12/91

ADF = (f + F)/f

[Eq. 1-4) 7 Where:

f = effluent flow rate (gtm)

F = dilutim *loi ' ate (gpm) 7 HOTE:

If radioactivity is detected in the Reservoir, an adjusted circulating water flow rate, F', shall be used in place of F in the calculation of ADF.

See ection 1.1.3 for the calculation of F' (Eq.1-3).

7 Also, if simultaneous releases are occurring, the available dilution flow shall be reduced by the required dilution flow for any 'it er ioncurrent I

release.

1.1.5 Reauired Dilution F ctor (RDF) 4 The required dilution factor ensures that the maximum permissible concentration. expressed in,0CFR20. Appendix B, Table II, Column 2*, and a total concentration of dissolved or entrained noble gases of 2 : 10-4 uti/ml are not exceeded during a discharge.

The renuired dilution factor includes a safety fdetor of 2 to pfovide a margin of assurance that the 1

instantantcus cencentration limits are not exceeded.

.MPCs listed in 10CFR20 give values for each isotope in both a soluble and insoluble form. The lowest value for each isotope should be used. A value of 2 x 10-4 uC1/ml for dissolved or entrained noble gases shall be used, n

COMANCHE PEAK - UNIT 1 II 1-6 Rev. 7 12/91

f

/

i t

I i

O i

RDF = ( r (C /MPc )) x sr g

g I

i

= (t (C,/MPC,) + (C,/MPC, + C,/MPC, + C s

t t

+ C,,/MPC,,)) x sr (Eg. 141 Where: _MPCj* = Maximum Permissible Concentration of Radionuclide i i

SF = Safety factor-of 2.,

All other variables and subsuipts are previously defined.

NOTE:

If RDF is less than 1. the release meets discharge 7

limits without dilution. For conservatism, set RDF equal to 1.0.

The maximum value for tho high alarm setpoint for detector XRE-5253 would then be calculated in accordance with the equation for C w 1

in Section 1.2.1.

1.1.6 10 CFR 20 Como11angg 7-Compliance with 10 CFR 20 is demonstrated if the Actual:

-Oilution Factor (ADF) 'is greater than or equal to the Required OilutionFactor'(RDF),or:

RDF W

~~<'3'e' (Eq. 1-6]

e See footnote on page II 1-6.

'I

' COMANCHE PEAK - lii1T 1 11 1-7 Rev 7 I

12/91

1.2 Radiation Monitor Alarm Setooints 7

k 1.2.1 Primary Liouid Effluent Monitor XRE-5253 7

To ensure that releases from the primary radwaste processing i

7 system do not exceed 10 CFR 20, Appendix B. Table !!, Column 2 limits at.5e point of release to the UNRESTRICTED AREA, a radiation detector (XRE-5253) monitors discharges to the Circtdating Water Discharage Tunnel.

XRV-5253 is the isolation valve controlled by XRE-5253.

The isolation valve shuts automatiacally if the detector alarms on high radiation or a detector operation failure occurs.

The methodology for determining the setpoint for detector XRE-5253 is given below.

It should be noted that the liquid effluent monitor setpoint values determined using the methodology from this section will be regarded as upper bounds for the actual setpoint adjustments.

That is, setpoints may be established at values lower than the calculated values, if desired.

4 Further, if the calculated value should exceed the maximum range of the monitor, the setpoint shall be adjusted to a value that falls within the normal operating range.of the monitor.

C, = (ADF/RDF) x C

(Eq. 1-7}

7 g

Where: Cjw =

The liquid waste effluent monitor alarm setpoint.

This corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in MPC-level releases (uCi/ml).

All other variables are as previously defined.

V COMANCHE PEAK - UNIT 1 11 1-8 Rev. ;

12/91

When considering the mixture of nuclides in the liquid effluent stream in terms of detector sensitivity, the most

(]

probable nuclides present would be those referenced in Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. Table Notation 2.

Figure 1.3 is a representative energy spectrum 7

response for the RD-33 type detector used in XRE-5253.

This curve illustrates that for any given mixture of the most probable gamma emitting nuclides present, the conversion factor between counts per minute and microcuries por milliliter remains relatively constant.

In fact between 137 s and 60 C

C0, tne total change in sensitivity is approximately 7%.

Because this is well within the accuracy of measurement, there is no need to change the software sensitivity for given varied effluent concentrations.

However, should the concentration of previously unexpected nuclides become significant, further evaluation would be required.

1.2.2 TURBINE BUILDING SUMP EFFLUENT RADIATION MONITOR 1RE-5100 The purpose of the turbine building sump monitor (1RE-5100) is to monitor turbine building sump discharges and divert this discharge from the Low Volume Waste Pond to the Waste Water Holdup Tanks if radioactivity is detected. Because the only sources of water to the turbine building sump are from the secondary steam system, activity is expected only if a significant primary-to-secondary leak is present.

Since detectable radioactivity is not normally present in the Turbine Building Sump, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should not inadvertent radioactive release occur.

To this end, the setpoint will be initially estab1hhed at three (3) times background until further data can be collected.

Then, if this setpoint is exceeded, 1RE-5100 will direct valves 1RV-5100A and B to divert the turbine building sumps discharges from the LVW Pond to the Waste Water Holdup Tanks where the effluent can thEn be COMANCHE PEAK - UNii 1 11 1-9 Rev. 7 12/91

sampled and released in a batch mode to Squaw Creek Reservoir, if required by Radiological Effluent Control 3/4.11.1.1. Table 7

4.11-1.

When radioactive materials are detected in the Turbine Building Sump, a setpoint then may be established for 1RE-5100 using the methodology in Section 1.2.1 to ensure that 10 CFR 20 MPC limits are not exceeded in discharges to the LVW Pond.

1.2.3

$ERVICE WATER EFFLUENT RADIATION MONITORS 1RE-4269/4270 The concentration of radioactive material in the service water effluent line normally is expected to be insignificant.

Therefore, the monitor alert alarm setpoint should be established as close to background as practival to prevent spurious alarms and yet alarm should an inadvertent release To this end, the alarm setpoint will be initially occur.

Mtablished at three (3) times background until further data can be collected.

If this effluent stream should become contaminated, radionuclide concentrations should be determined from grab samples and a radiation monitor alarm setpoint determined as follows:

C

=(IC ) + DF

%. 1-8) s Csq = the Servich Water effluent monitor alarm setpoint.

Where:

C

= the concentration of each measured gamma g

emitter g, observed in the effluent (uCi/ml)

DF = [ (C /MPCj) = the dilution factor required to t

ensure maximum permissible concentrations are not exceeded.

For this release pathway no additional dilutio: is available.

Therefore, if the calculated DF is greater athan 1.0, any releases occurring via this pathway will result in a violation of Radiological Effluent Control 3/4.11.1.1.

If radioactivity is detected in this release stream, doses due to releases from this %tream shall be calculated in accordance with the

,q methodology given in Section 1.3. with the near field average V

dilution factor, F, equal to 1.0.

k COMANCHE PEAK - UNIT 1 11 1-10 Rev. 7 I

12/91

1.3 DOSE CALCULATION FOR L10010 EFFLUENTS For implementation of Radiological Effluent Control 3/4.11.1.2, the dose comitment from the release of liquid effluents will be calculated at least once per 31 days and a cumulative sumation of the total body and organ dose comitments will be maintained for each calendar cuarter and each calendar year. Dose calculations will be performed for 7

reletses from the Waste Monitor Tanks, laundry Holdup &

Monitor Tanks.-Waste Water Holdup Tanks, and the LVW Pond via the Circulating Water Tunnel at the point of discharge to Squaw Creek Reservoir.

Although the LVW Pond is located in an UNRESTRICTED AREA, dose calculations for discharges to the LVW Pond will not be performed because there are no real pathways for exposure to members of the public.

Doses for these pathways will be caluciated when the LVW Pond is dischartid to Squaw Creek Reservoir.

The cumulative dose over the desired time period (e.g., the sum of all doses due to releases during a 31 day period, calendar quarter, or a O

ca,eeearsear>wil,decaice,ateeesie,18efe,lowie, equation:

07=tDk ID(lake),

[Eq. 1-9]

+

Where 07=-

the dose comitment to the total body or any organ due to all releases curing the desired time interval (mrem).

Dk=

the dose comitment received by the total body or any organduringthedurationofreleasek(mrem).

The equation for calculating Dk is given in Section 1.3.1(Eq.1-10)

D(lake)m=

the dose comitment received by the total body or any or any organ during the desired time period, m.

(normally m 31 days) due to the buildup in the lake

./

of.previously discharged radionuclides.

The equation

(

for calculating D(lake)m is given in Section 1.3.2 (Eq.1-12).

COMANCHE PEAK UNIT 1 11 1-11 Rev. 7 12/91

1.3.1 Calculation of Dose Due to'Liouid Releases The dose '.cmmitment to the total body or any organ due to a 7

V release will be calculated using the following equation:

Uk * { *it 'k U

tk k gq, t.go)

Where:

tk

• ne time duration of the release k (hrs)

=

Cik a theisotopicconcentration(Ci/ml)of radionuclide i found in the release sample for release k.

Concentrations are determined primarily from gamma isotopic analysis of the liquid effluent sample. For Sr-89 SR-90, H-3 Fe-55 and alpha emitters, the last measured value will be used in the dose calculation.

Fk the near field average dilution factor during

=

a liquid effluent release.

This is defined as the ratio of the average undiluted liquid effluent flow rate to the average circulating

'V water flow rate during the release.

The average liquid effluent flow rate is based on the actual averaga flow into the circulating water during the release.

Fk = averaae undiluted liauid effluent flow rate circulating water flow rate Aj the site related ingestion dose commitment

=

factor for the total body or any organ,

, for each identified gamma or beta emitter (mrem /hr per Ci/ml). Att is calculated as follows:

1.g, = 1.14x105 (U,/0, + U ar ) or g

i i

gg, ggy q

O COMANCHE PEAK - UNIT 1 11 1-12 Rev. 7 12/91

Where: 1.14x105 o unit conversion factor, 7

Uw adult water unsumption, 730 litets/yr Ur - adult fish consumption, 21 kg/yr BFj - bioaccumulati'n factor for radionuclide i, in fish from Table A 1, Ref. 2 (pC1/kg per pCi/1) 0Fj

.dult dose conversion factor for radionuclide i, from Table E 11 Ref. 2 (mrem /pci inCssted)

Ow Oilution factor from the near field area within one quarter mile of the release point to the potable water intake' for the adult water consumption; 1.0 for CPSES. (unitiess)

Calculated values for A t.are given in Table 1.2.

i 1.3.2 Calculation of Dose Due to Radionuclide BuilduD in the Lake The does contribution due to buildup of previously discharged radionuclides-in the lake must be considered in the committed-dose calculation only if they are detected in the water of Squaw Creek Reservoir-or in fish from $quaw Creek Reservoir.

The contribution to the total dose due to this' buildup is determined as follows:

D(13e ), = 1,14x 10*4( ! DF((C ' {wU, + C' t rU())t i

[Eq. 1-121-Where:

1.14 x 10-4 = units conversion factor C'jw - concentration of radionuclide i in the-reservoir as measured at the circulating water intake structure shown as location SW6 on Table 3.1 and Figure 3.1 of this manual (pCi/1)

. MANCHE DUK - UNIT 1 1

M3 Rev. 7 12/91

C'jr - concentration of radionuclide i in fish 7

(~'T sa'apled from Squaw Creek Reservoir from V

location F1 on Table 3.1 and Figure 3.1 of this manual (pCi/kg) t - 744 hrs (31 days) or other time period of interest (hr)

All other variables are previously defined.

NOTE:

This calculation is only required if activity is detected in water and/or fish in excess of the appropriate LLD values given in Radiological Effluent Control 3/4.12.1. Table 4.12-1.

If the measured activity in water or fish is less than the required LLO values, the concentration for that particular pathway is assumed to be zero.

1.4 DOSE PROJECTIONS FOR LIOUID EFFLUENTS 7

Radiological Effluent Control 3/4.11.1.3 requires that appropriate subsystems of the liquid radwaste treatment system by used to reduce releases of radioactivity when the projected doses due to the liquid effluent from each reactor unit to UNRESTRICTED AREAS would exceed 0.06 mrem total body or 0.2

-mrem to any organ in a 31-day period.

The following calculational nethod is provided for performing this dose projection.

At least once every 31 days, the total dose from all liquid releases for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated does due to any anticipated unusual releases during the period for which the projection is made.

If this projected dose exceeds 0.06 mrem total body or 0.2 -rem any organ, appropriate portions of the Liquia Radwaste Treatment System shall be used to reduce v

radioactivity levels Rrior to release.

COMANCHE PEAK - UNIT 1 II 1-14 Rev. 7 12/91

1.5 DEFINITIONS OF COMMON L10VID EFFLUENT PARAMETERS IG11 DEFINITION ADF Actual Dilution Factor (unitiess).

This is defined as the ratio of the effluent flow rate plus the circulating water flow rate divided by the effluent flow rate.

A The site related ingestion dose commitment factor h

to the total-body or any organ, t, for each identified gamma or beta emitter, i.

(mrem /hrperUCi/ml)

BFj Biaccumulation factor for radionuclide, i, in fish from Reg. Guide 1.109.

(pC1/kgperpCi/1)

Ca The concentration of alpha emitters in liquid waste as measured in the analysis of the most recent monthly composite sample required by Radioingical Effluent Control 3/4.11.1.1. Table 4.11 1.

(uti/ml)-

Ce The concentration of-55 e in liquid waste as F

F measured in the analysis of the most v. cent O

quarterly composite sample required Fy Radiological Effluent Control 3/4.11.1.1 Table 4.11-1.

(uct/ml) cg The-concentration of each measured gamma emitter, g in the waste tank as. measured in the analysis of the sample of each batch as required by Radiological Effluent Control 3/4.11.1.1.

Table 4.11 1 (uci/ml)

Ci The concentrations of radionuclide, i, in the waste tank.

(uti/ml)

C' j.

The concentration of radionuclide i in the-l Reservoir as measured in the-analysis of the-

-monthly sample of the Reservoir require 1 by Radiological Effluent Control 3/a.12.1 Table 3.12 1.

This sample is taken at the Circulatory Water Intake Structure as indicated by location-SW6-on Table 3.1 and Figure 31_of

-.this manual.

(uCi/ml)

C'if-The concentration of radionuclide i in fish sampled from the reservoir from location F1 on Table 3.1 and Figure 3-1 of this manual (pC1/kg).

O C0!' AGE-PEAK UNIT 1 11 1-15 rey, 7 12/91

~

l Cik The isotopic concentration of radionuclide i m

I found in the pre release sample for batch k

release k.

Concentrations are determined 7

primarily from gama isotopic anajysis of the ]jguid effluent sample.

For WSr. vuSr.

3H, W Fe and alpha emitters, the last measured value will be used.

(uCi/ml)

C'$w The concentration of radionuclide i in the reservoir as measured at the circulating water intake structure shown as location SW6 on Table 3.1 and Figure 3 1 of this manual (pti/1).

C1w The liquid waste effluent monitor alarm setpoint.

This corresponds to the gama concentration in the undiluted waste stream which after dilution would result in MPC level releases.

(uti/mi)

Cs The concentration of 89 r and 90 r in liquid 5

S waste as measured in the analysis of the most recent quarterly composite sample required by Radiological Effluent Control 3/4.11.1.1, TTble 4.11 1 (uti/ml) r Csw The Service Water effluent monitor alarm setpoint.

(

(uti/ml)

Ct The concentration of 3H in liquid waste as measured in the analysis of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1 (uti/ml)

DFj Adult dose conversion factor for radionuclide, i, from Reg. Guide 1.109 (mrem /pci ingested)

Ok The dose comitment received by the total body or any organ during the duration of batch release k of liquid effluents.

(mrem) 0(lake)mThe dose comitment received by the total body or any organ during a desired time period, m, due to the buildup in the lake of previously discharged radionuclides.

(mrem)

DT The total dose comitment to the total body or any organ due to all releases of li during a desired time interval. quid effluents (mrem) 00t1ANCHE PEAK - UNIT 1 11 1-16 REV. 7 12/91

Dw Dilution factor, from the near field area within p) 7 q

1/4 mile of the release point to the potable water intake for adult water consumption, 1.0 for CPSES (unitiess) f Effluent flow rate.

(9pm)

F Circulating water flow rate (or dilution flow rate).

(gpm)

F' Adjusted circulating water flow rate to account for buildup of radionuclides in the circulating water due to previous releases.

(gpm)

F(

The near field average dilution factor during a liquid effluent release (unitiess).

This is defined as the ratio of the average undileted liquid waste flow to the average circulating water flow during the release.

MPCa Maximum Permissible Concentration

• of a mixture of unidentified alpha emitters.

(uCi/ml)

MPCre Maximum Permissible Concentration

• of 55re, (uci/ml)

(7 MPC Maximum Permissible Concentration

• of each g

(.)

identified gamma emitter, g.

(uCi/ml)

MPCj Maximum Permissible Concentration

• nf radionuclide, i.

(uCi/ml)

MPCs Maxi um Permissible Concentration

• of a mixture of o Sr and WUSr.

(uci/ml)

MPCt Maximum Permissible Concentration

• of tritium (JH)

(uCi/ml)

SF Safety Factor of 2.

Used in the calculation of the Required Dilution hctor (RDF) for liquid releases to provide a margin of assurance that the instantaneous concentration limits are nnt e x e. ped ed.

• MPCs are given in 10CFR20 Appendix 8. Table 11, Column 2.

Values are given for each isotope in both a soluble and insoluble form.

The most conservative (lowest) value for e ch isotope should be used. A value of 2x10-uC1/ml for dissolved or entrained noble gas shall be used.

O) l l

COMANCHE PrAK - UNIT 1 11 1-17 REV. 7 12/91

l

(~')

RDF Required Dilution Factor (unitiess).

This is V

defined as the dilution factor that ensures the maximum permissible isotopic concentrations expressed in 10CFR20, Appendix B. Table !!,

Column 2, are not exceeded during a discharge.

tk The time duration of batch release k. (hours)

Ur Adult fish consumption.

(kg/yr) f Ow Adult water consumption.

(liters /yr) i nU C0ftANCHE PEAK - UNIT 1 11 1-18 REV. 7 12/91

i o

1 TABLE 1.1

SUMMARY

OF LIOUID RELEASE PATHWAYS f

7 1.

RELEASES TO SCR VIA THE CIRC WATER DISCHARGE Release Source Release Type _

Max Flow Max Vol Monitor Rate (aom)

(aali j

t WMT-1

' Batch 100 5340 XRE-5253 i

WMT-2 Batch 100 5340 XRE-5253 i

LHMT-1 Batch 100 5875 XRE-5253 LHMT-2 Batch 100 5875 XRE-5253 WWHT-1 Batch 200 25000 None WWHT ' Batch 200 25000 None LVW Pond Continuous 1600 None 2.-

RELEASES TO THE LVW POND i

Release Source Release Type Max Flow Max Vol Monitor Rate (anmi (cal)

CPBRT Batch 25 8500 None CCWDT-Batch 40 2300 None WWHT-1 Batch 200 25000 None WWHT-2 Batch 200 25000 None-

,TBSump2(Uniti) Continuous:

.300 IRE-5100 TBSump4(Unit 2) Continuous _

300 None t

3.-

DIRECT RELEASES TO SCR (SAFE SHUTDOWN IMPOUNDMENT) i Release Source 2

. Release Type Max Flow Max Vol Monitor Rate (com)

(aal)-

SSW Train A.

Continuous 17,000 IRE-4269 SSK 1 rain B Continuous 17.000 IRE-4270 1

O COMANCHE PEAK - UNIT 1-II 1-19 REV. 7 12/91

_u._._,

.x o.

.a..

.m..

TABl.E 1.2 l7 c

SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mRer Sr per uCi/ml)

BN'E LIVER T-BODY THYROID KIDNEY

• UNC GI-LLI

') 00..+00

8. m ^^ 51.96E+00 8.96E+00 8.96E+00 3.96E+00 8.96E+00 l

3.15E604

6. 3M -

6.30E+03 6.30E+03 6,30E+03 6.30E+03 6.30E+03 5.40E*v2 5.48E402 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 i"

't i 62E+0' 2.87E+06 1.79E+06 0.00E+00 0.00E+00 0.00E+00 5.20E+06

+

or 51 0.00E+00 0.00E+ve 1.49E+00 8.94E-01 3.29E-01 1.9BE+00 3.76E+02 hr. 54 0.00E+00 4.76E+0S 9.08E+02 0.00E+00 1.42E+03 0.00E+00 1.46E+04 Mn-56

' 00E+00 1.20E+02 2.12E+01 0.60E+00 1.52E+02 0.00E+00 3.82E+03 Fe-55 8.B?'+02 6.13E+02 1.43E+02 0.00E+00 0.00E+00 3.42E+02 3.52E+02 Fe-59 1.40E+03 3.29E+03

1. / *'+0 3 0.00E+00 0.00E+00 9.19E+02 1.10E+04 Co-58 0.00E+00

1. 51F302 3.39L.02 0.00E+00 0.00E+00 0.00E+00 3.06E+03 Co-60 0.00E+00 4.34E+02 9.58E+02 0.00E+00 0.00E+00 0.00E+00 8.?fE+03 Ni-63 4.19E+04 2.91E+03 1.41E+03 0.00E+00 0.00E+00 0.00E+00 6.07E+02 Ni-65 1.70E+02 2.21E+01 1.01E+0! 0.00E%

0.00E+00 0.00E+00 5.61E+02 Cu-64 0.00E+00 1.69E+01 7.93E+00 0.00E+00 4.26E+01 0.00E+00 1.44E+0$

Zn-65 2.365+04 7.50E+04 3.39E+04 ^ ^ E+00 5.02E+04 0.00E+00 4.73E+04 v

En-60 5.02E+01 5.60E+01 6.67E* u 0.00E+00 6.24E+01 0.00E+00 1.44E+0!

[

Br-83 0.00E+00 0.00E+00 4.38E+01 0.00E+00 0.00E+00 0.00E+00 6.30E+01 Br-84 0.00E+03 0.00E+00 5.67E+01 0.00E+00 0.00E+00 0.00E+00 4.45E-04 Br-85 0.00E+00 0.00E+00 2.33E+C0 0.00E+00 0.00E+00 0.00E+00 1.09E-15 Rb-86 0.00E+00 1.03E+05 4.79E+04 0.00E+00 0.00E+00 0.00E+00 2.01E+04 Rb-88 0.00E+00 2.99E+02 1.59E+02 0.00E+00 0.00 +00 0.00E+00 4.00E-09 Rb-81 0.00E+00 1.9aE+02 1.39E+02 0.00E+00 0.00E+00 0.00E+00 1.15E-ll Sr-89 4.78E+04 0.00E+00 1.37E+03 0.00E+00 0.00E+00 0.00E+00 7.66E+03 COMANCHE PEAK - UNIT 1 pgy, 7

L TABLE 1.2

=U l7 SITE RELATED INGESTION DOSE COMMITHENT FACTOR Ah (mrem /hr per uCi/ml)

ISOTOPE-RONE LIVER T-bvDY TRYROID KIDNEY LtTNG GI-LLI Sr-90 1.18E+06 0.00E+00 2.88E+05 0.00E+00- 0.00E+00 0.00E+00 3.40E+04 Sr-91 8.79E+02 0.00E+00 3.55t+01 0.00E+00 0.00E+00 0.00E+00 4.19E+03 Sr 3.33E+02 0.00E+00 1.44F+01 0.00t+00 0.00E+00 0.00E+00 6.60E+03 Y-90 1.38E+00 0.00E+00 3.69E-02 0.00E+00 0.00E+00 0.00E+00 1.46E+04 Y-91m 1.30E-02 0.00E+00.5.04E 04 0.00E+00 0.00E+00 0.00E+00 3.82E-02 Y-91 2.02E+01 0.00E+00 s.39E-01 0.00E+00 0.00E+00 0.00E+00 1.11E+04 e

Y-92 1.21E-01 0.00E+00 3.53E-03 0.00E+00 0.00E+00 0.00E+00 2.12E+03 Y-93 3.83E-01 0.00E+00 1.06E-02 0.00E+00 0.00E+00 0.00E+00 1.22E+04 Zr-95 2.77E+00 8.88E-01 6.01E 0.00E+00 1.39E+00 0.00E+00 2.82E+03 Zr-97 1.53E-01 3.09E-02 1.41E-02 0.00E+00 4.67E-02 0.00E+00 9.57E+03 Nb-95 4.47E+02 2.49E+02 1.34E+02 0.00E+00 2.46E+02 0.00E+00 1.51E+06 Mo-99 0.00E+00 4.62E+02 8.79E+01 0.00E+00 1.05E+03 0.00E+00 1.07E+03 Tc-99m 2.94E-02 8.32E-02 1.06E+00 0.00E+00 1.26E+00 4.07E-02 4.92E+01 Tc-101 3.03E-02_ 4.36E-02 4.28E-01 'O.00E+00 7.85E-01 2.23E-02 1.31E-13 t -

Ru-103 1.98E+01 0.00E+00 B.54E+00 0.00E+00 2.57E+01 0.u0E+00 2.31E+03 Ru-105 1.65E+00 0.00E+00 6.51E-01 0.00E+00 2.13E+01 0.00E+00 1.01E+03 Ru-106 2.95E+02.0.00E+00 3.73E+01 0.00E+00 5.69E+02 0.00E+00 1.91E+04 p

Ag-110m 1.42E+01 1.31E+01 7.80E+00 0.00E+00 2.58E+01 0.00E+00 5.36E+03

-Te-125m 2.79E+03 1.01E+03 3.74E+02 8.39E+02 1.13E+04 0.00E+00 1.11E+04 Te-127t.,.0: 603 2.52E+03 8.59E+02 1.80E+03 2.86E+04 0.00E+00 2.36E+04 e

Te-127 1.14E+02 4.11E+01 1.48E+01 E.48E+11 4.66E+02 0.00E+00 9.03E+03 p-'/j

.Te-129m 1.20E+04 4.47E+03 1.89E+03 4.11E+03 5.00E+04 0.00E+00 6.03E+04 Te-129 3.27L+01 1.23E+01 7.96E+00 2.51E+01 1.37E+02 0.00E+00 2.47E+01 l

i COMANCHE PEAK - UNIf 1 REV. 7 Il 1-21 I

12/91

TABLE 1.2 l7

-SITE RELATED INCESTION DOSE COMMITMENT FACTOR A A' (mrem /hr per uCi/ml)

ISOTOPE BONE LIVER T-BODY THYROID KIDNEY LUNC CI-LLI Te-131m-1.80E+03 8.81E+02 7.34E+02 1.39E+03 8.92E:92 0.00E+00 6.74E+0'.

Te-131 2.0$E+0' 8.57E+00 6 47E+00 1.69E+01 8.98E+01 0.00E+00 2.90E+00 Te-132 2.62E+03 1.70E+03 1.59E+03 1.87E+03 1.63E+04 0.00E+00 8.02E+04 I-130 9.01E+01 -2.66E+02 1.05E+02 2.25E+04 4.15E+02 0.00E+00 2.29E+02 1-131' 4.96E+02 7.09E+02 4.06E+02 2.32E+05 1.22E+03 0.00E+00 1.87E+02 1-132 2.4?E+01 6.47E+01 2.26E+01 2.25E+03 1.03E+02 0.00E+00 1.22E+01 1-133 1.69E+02 2.94E+02 8.97E+01 4.32E+04 5.13E+02 0.00E+00 2.64E+02 1-134 1.26E+01 -3.43E+01-1.23E+01 5.94E+02 5.46E+01 0.00E+00 2.99E-02 I-135-5.28E+01 1.38E+02 5.10E+01 9.llE+03 2.22E-J2 0.00E+00 1.56E+02

[

).

C s-114 -- 3.03E+05 7.21E+05 5.89E+05 0.00E+00 2.33E+05 7.75E+04.1.26E+04 Cs-136 3.17E+04 1.25E+05 9.01E+04 C 00E+00 6.97E+04 9.55E+03 1.42E+04 Cs-137-3.88E+05 5.31E+05 3.48E+05 0.00E+00 1.80E+05 5.99E+04 1.03E+04 Cs-138 2.69E+02 5.31E+02 2.63E+02 0.00E+00 3.90E+02 3.85E+01 2.27E-03 Ba-139 '9.00E+00 6.41E-C3 2.64E-01 0.00E+00 5.91E-03 3.64E-03 1.60E+01 Ba-140 1.88E+03 2.37E+00- 1.23E+02 0.00E+00 8.05E+01 1.35E+00 3.88E+03 Ba-141 4.37E+00 3.30E-03 1.48E-01 0.00E+00- 3.07E-03 1.87E-03 2.00E-09 Ba-142 1.98E+00 2.03E-03 1.24E-01 0.00E+00 1.72E-03 1.15E-03 2.78E-18 La-140 3.58E-01 1.80E-01 4.76E-02 0.00E+00= 0.00E+00 0.00E+00 1.32E+04

.La-142 1.83E-02 7.55E-03 2.07E-03 0.00E+00 0.00E+00 0.00E+00 6.08E+01 Ce-141 8.01E-01 5.41E-01 6.15E-02 0.00E+00 2.52E-01 0.00E+00 2.07E+03 Ce-143 1.41E-01 1.04E+02 1.16E 0.00E+00 4.60E-02 C 00E+00 3.90E+03 1

Cc-145 4.18E+01 1.75E+01 2.24E+00 0.00E+00 1.04E+01 0.00E+00 1.41E+04

-Pr-143 1.32E+00 5.28E-01 6.5TE-02 0.00E+00 3.05E-01 0.00E+00 5.77E+03 CGMANCHE PEAK - UNIT 1

!! l 22 REV 7 12/91

m TABLE-1.2 7

l

/

SITE RELATE 0 INGESTION 00SE COMMITMENT FACTOR Aj7 (mrem /hr per uCi/ml)

' ISOTOPE.. B.QE LIER T-BODY THYR 010 K10NEY LyNQ.

GI-LLI Pr-144 4.31E-03 1.79E-03 2.19E-04 0.00E+00 1.01E-03 0.00E+00 6.19E-10 Nd-147 9.00E-01 '1.04E+00 6.22E-02 0.00E+00 6.08E-01 0.00E+00 4.99E+03 W-187.

3.04E+02 2.55E+02 8.90E+01 0.00E+00 0.00E+00 0.00E+00 8.34E+04-Np-239 1.28E-01 1.25E-02 6.91C-03 0.00E+00 3.91E-02 0.00E+00 2.57E+03

• Sb-122 1.98E+01~ 3.90E-01 5.79E+00 2.69E-01 0.00E+00 1.03E+01 5.68E+03

• • Sb-124 2.41E+02: 4.54E+00 -9.50E+01 5.81E-01 0.00E+00 1.87E+02 6.81E+03 5

• • Br 0.00E+00=-0.00E+00 1.93E+02 0.00E+00 0.00E+00 0.00E+00- 2.22E+02' l6

• • Sb-125 1.91E+02 2.05E+00 3.84E+01 1.70E-01 0.00E+00 1.99E+04 1.69E+03 l7

'The adult doselconversion factors, OFj, for Sb-122 are not published 5

in Reference 2.- The calculation of dose conversion factors and site-lrelated ingestion dose comitment factors for Sb-122 is documented in Reference 10.

-The adult dose conversion-factors, DFj, for Sb-124, Sb-125 and Br-82 l7

are_not published in Reference 2.

The site-related dose commitment factors for Sb-124, Sb-125 and Br-82 were calculated using the " Adult.

Ingestion Oose Factors" given in Table A-3 of Reference 11, and Equation 1-11 of Part II, Section 1.3.1 of this Manual.

i i

I L

--COMANCHE PEAK - UNIT 1 11 1-23 Revision 7 12/91 W

1 O

O O

l Unit 1 SSW-Tran A M-n 1N42s f

's L@

- Liquid Waste.

-Unit 1 SSW-Train B h.%3

[ W 501 y

Processng g

sysiem 1*ano (see page 2)

. l Unit 2 SSW-Tran A IW:

~I m

2R6-4269

.N

'/

v Wer)

N'

/

m-() xa.525,

l Unit 2SSW-TranB H"g(E 2[0 N

25.000 pai ea 2xn c.

V

/

N

,e x

' ",j l

' ounta:201 b-waste Water P

s i

t*mpTaru.

%r squaw creek.

=

' l-j

/

h

.\\ Tunnet

\\

/

m,s2

~

1975 gal

~

gpm Rxovery p

300 gpm A

I Tanks-Unit 1

_ d>

l.

l Buiksing

~

[h p

Turtune

=

=

U h

n n

\\

l Sump No.2 1M-5100 tow v*me wome eono i

A-namess-Pac l

[

B*c****h 300 gpm Turtune sump BuGding 7242 gal

.i'-

ura 2 chemed 150gpm Buiksng O

Sim p Turtune V

Sump No. 4 2M-5100 (later)

FIGURE 1.1 n

a n

g l

(page 1 of 2)-

Unit i unit 2 I

UQUlOEFFLUENT g,

Desel h Desel Gea CCW Drain CCW Drain Buiktng DISCHARGE PATHWAYS

,m N*

Tank Tank Sump 35.

Nos.1 & 2 Nos. 3 & 4.

No; 11 KEY:

-w j

50 gpm ea.

50 gpm ea.'

40 gpm 40 pm.

50 opn-Flow path N >MPC -

9 (later)-

(Wer)

---

___ % w < g N

m i

m w

h

+

,Mk+

. y I

LIQUID WASTE PROCESSING SYSTEM 3

DRAlte CHANNEL A g

-DHAsiCHAteNELS I

DnAaN CHAML C '

a l'

4 Waste Hoedup 3

Floor Drain L#F I "I De teot m

-)

S*"8* A

'a 9 *** * *I*',,,

"~

' ~ ~ ' '

TM Santis Accarweator!

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y -

hwer TM 6--

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g m

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.g g.

g g---

e l

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s,

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I Pecatese

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Evaporator 1

Moverse Oesnoeis Q

t

' -{><

l M

4' 4

g Waste Evaporator I

g; La aery Hese.

X.

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{

1. M*'N X

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h a'ammer l

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~

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l

(= =-.3. )-

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Dioenere.

.t j

sterces To ais

.[

FIGURE 1.1 (page 2 of 2)

G5' LIOUlO EFFLUENT

-E 31 DISCHARGE PATHWN/S

~_

o NOTES:

3 W Spared b place m

m DecharDe vehe closes on anonsor Nrad, loss of Bow, or channel out of-servke alerrns.

s V

Y 3

I i

l I

i l

3 i

g g

l 7E MH OfftlE 12&d 88 Mbed a.

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er 9

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n 1

n g

3,5, 9s m

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g p-p--

n f

'~~~

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j a

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e K

W

f. h.

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?

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O

=--gi-- =-

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. GAMMA PHOTON ENERGY,MeV ENERGY RESPONSE TO CMStA RADIATIONS FOR RD-33 TYPE DETECTOP Figure-1.3 IThe D:0 wen por00n Of the Cutyt was genersted Worst early r$0lODrC Calibra00ns usang a charnDet of similar geometry 88300 On One gamme per Ot$rnlegrshon.

iV=

c COMANCHE' PEAK - UNIT 1 II 1-27 IO"

-, _, _ _ ~

~.

TABLE 2'.4'

'i

-(Sheetl'~of-2)l CONTROLLINGLRECEPTOR PATHWAYS AND LOCATIONS (NOTE 1),.AND~

il

ATMOSPHERIC DISPERSION PARAMETERS (FOR DOSE CALCULATIONS 5-REQUIRED BY

RADIOLOGICAL EFFLUENT CONTROL-3/4.11.2.3)

.~

Pathway Distance X/Q

.0/Q Sector (Note 2)-

(Miles):

(Notes 3. 4)

(Notes 5. 6) t Retident 2.20 9.28E-07 5.32E 09 N-Garden 3.3 2.10E y=

Milk Cow 4.4 1 06E-09 Resident

.2.30 5.12E-07 2.60E-09~

NNE Garden 2.40 5

.2.30E-09 Milk Cow None~

Resident 2.30 3.58E-07 1.28E-09 fHE~

Garden 2.70 5

B.92E-10

.Hilk Cow 4.9 2.3BE-10 lf i

-Resident 2.40 2.58E-07 7.08E-10

.I 5 ENEs

-Garden

2.5 6.10E-10

-17 Milk. Cow None

-l5

\\

Resident 2.40 3.02E 6.62E-10.

.l5 E-Garden 3.3 3.32E-10 l7 Milk-Cow None

{5 Resident-

-2.0 4.7E-07 l'.20E-09 l7 ESE

-Garden 2.30 9.00E --

Milk Cow None 5

Resident 2.00 7.10E-07 2.80E-09

'SE Garden-2.50 1.60E 5

-Milk l Cow-None Resident 1.60 9.96E-07 5.92E l5 LSSE.

Garden

.1.7 5.24E-09 17 Milk Cow:

2.20-1.80E-09 I5

. Resident 1.60 7.74E-07 4.66E-09 l5 S-Garden

.1.8

-5.38E-09 Milk Cow No:,e 7

Resident.

1.90 4.42E-07 2.06E-09 15 SSW' Garden 4.3 2.92E l 7 Milk Cow None l5 LCOMANCHE PEAK - UNIT 1 11 2-45 Revision 7 l12/91' m

5 TABLE 2.4-t (Sheet 2)-

o,

CONTROLLING RECEPTOR PATHWAYS-AND LOCATIONS (NOTE 1), AND-5 if ATMOSPHERIC DISPERSION PARAMETERS (FOR DOSE CALCULATIONS 6 E

_ REQUIRED-8Y RADIOLOGICAL EFFLUENT CONTROL 3/4_.11. 2. 3 ) =

_ Pathway-.

Distance X/Q D/Q Eqctor (Note'2)-

(Miles)

(Notes 3. 4)

(Notes 5 61_

Resident 1,00 1.60E-06 7.50E-09 l7 SW

~ Garden-1.7 1.98E-09~

Milk Cow None 5

Resident 1.00 1.80E-06 6.50E-09 1.5 WSW Garden 1.5.

-2.20E-09 I7 Milk Cow.

None l5

-Resident 1.50 8.40E-07 2.80E-09 W

Garden 1.50 5

2.80E-09 Milk Cow-None Resident-4.0 2.00E-07 5.00E-10 l7 WNW.

Garden 3.00

-1.04E-09 Milk ~ Cow

-None-5

'V Resident

_2.70 6.98E 2.24E-09 HW Garden:

None 5

Milk Cow Hone Resident

-2.70 7,62E-07 3.22E-09 i5 iHNW Garden 3.6 1.60E-09 Milk Cow ~

None

'7 LHOTES:

(1) Recepto' loct.tions are taken from the nearest receptor locations 5

identified'in the CPSES 1991 land use census =

(2)-In addition to the pathways shown, the inhalation and ground plane Lpathways are present at the nearest resident.

(3)TheunitslforX/QareSec/CubicMeter.

(4)_X/Q Values.at distances l'.0, 1.5,-2.0,'2.5,:3.5, 4.0, 4.5, and 6.0 miles

~

were tak.1 from T4bh 2.3-16. " Average Annual Relative Concentration at

. CPSES " of-the ~"iES Environment Report, Operating Licensir; Stage (Reference 3).

%r X/Ql values at other distances were determined by linear-interpolation.

(5) The units for D/Q are inverse square meters (6) D/Q values at distances - 1.0, 1.5, 2.0, 2.5, 3.5, 4.0, 4.5, and 6.0 uiles f_..Y were taken from; Table -2.3-17

" Average Annual Relative Deposition Rate,"

_ if

of _the CPSES Environmental Report, Operating License Stage (Reference 3)..

The.D/Q values-at other distances were determined by-lira r interpolation.

-COMANCHELPEAK - UNIT 1 11 2-45 Revision 7 12/91

m APPENDIX G i.)

7 SUPPLEMENTAL GUIDANCE STATEMENT #3 I'AS BEEN DELETED

(~s

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(3 V

COMANCHE PEAK - UNIT 1 G-3 nev, 7 12/91

% yli O

COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL List of Effective Pages

( -

{

d I,Q

%)

EPL-1 December 1991

CP5tS.--0DCM f-~

List of Effective Pages

's /

Preface The-Effective Page Listing (EPL) provides a tabulation of the current pages in the CPSES ODCH.

Each page in_the CPSES ODCM is identified with a page number, including pages that contain tables or figures.

A-revision number and date are included on each page.

The revision number and date are' changed when the change represents a substantive revision to the information-that.is provided-on the page.

If the page-is revised or= reprinted but the-revision'is not considered substantive (i.e., it is an editorial correction), the revision numoer will not be changed._but will have the reprint date.

Sirce the EPL may not be updated with-each revision, an Instruction Sheet (s) 1will.be provided for subsequent revisions of the CPSE5 ODCH: it should be retainediimrtdiately in front of the EPL.

To identify the effective revision level of a page in the CPSES CDCM, check these Instruction Sheets first and, if not found, the EPL secoau.

If'any effective page cannot be'found, notify TV Electric Nuclear Licensing and the required effective pages will be provided.

Contact may-be made by

(-'s phone (214/812 4358) or by mail.

A marked up copy of pages from the~

t Instruction Sheets or the EPL is a convenient way to identify the required pages.

4 4

k.

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EPL December 1991

CPSES 00CH Effective Page Listing

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Pace No.

Revision No.

TABLE OF CONTENTS i

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