Text

Change 1 to Rev 5 to ODCM
	ML20114C632
Person / Time
Site:	Davis Besse
Issue date:	05/19/1992
From:	Storz L; TOLEDO EDISON CO.
To:	;
Shared Package
ML20114C627	List: ML20114C625; ML20114C628; ML20114C630; ML20114C632;
References
	PROC-920519, NUDOCS 9209030022
	Download: ML20114C632 (231)
	v • d • e

e a

DAVIS-BESSE OFFSITE DOSE CA1.CUIATION HANUAL Revision 5 Change 1 Effective Date June 4 1992 Approval:

j l 't A (l

SRB Ghairman Date i l $ NN NO Plant Manager h Date phk DO b0 6 R

1

THE TOLED0 EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION OFFSITE DOSE CALCULATIONS KANUAL Reviewed by Revision No. station Review Board Date o y rPI '---sg 2./r.:/84-t b. u. E1D n % / 2=> / s r t A.u.E M sut .1issa.

Jul. 2 s ass a

j','.e, h-alsa l9 (

g C , D)JLO sl a l i'

i

,[~ 1 ODCM list of Effective pages Page No. Revision

i 5.1 11 5.1 111 5.1 iv 5.1 v 5.1 vi 5.1 vii 5.1 4 vill 5.1 ix 5.1 1 5.1 2 5 3 5.1 ~

4 5.1 5 5 6 5.1 7 5 8 5 9 5 10 5 11 5 12 5.1 13 5.1

, 14 5 15 5 16 5 17 5 18 5.1 19 5 20 5 21 5 22 5 23 5 _

24 5 25 5 26 5 ,

~

27 5 28 5 29 5 30 5 31 5 32 5 33 5 33 5 34 5.1 35 5.1 36 5.1 37 5.1 38 5 39 5 40 5.1

1 5 Davis-Besse ODCM i Revision 5.1

Revision 5.1 means Revision 5 Change 1

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

I I

C-1 l

/ )

ODCH List of Effective Pages (continued) ;

Page No. Revision

42 5 43 5 !

44 5 45 5 46 5 47 5.1 7

48 5 49 5 50 5

, 51 5 52- 5.1 53 5.1 54 5 55 5 56 5 57 5 58 5 59 5 60 5 61 5 62 5 63 5 '

64 5 65 5 66 5 67 5 68 5 69 5 70 5 71 5 72 5 73 5 74 5 ,

75 5 76 5 77 5 78 5 79 5 80 5 81 5' 82 5 83 -5 84 5 85 5

,86 5 87- 5 88- 5 89 5 90- 5 91 5 92 5 Davis-Besse ODCM 11 Revision 5.1

Revision 5.1 means Revision 5 Change 1 l

l l'

C-1 ODCM 1.ist of Effective Pages (continued)

'/

Page tJo. Revision

93 5 94 5 95 5 96 5 97 5.1 98 5 99 5 "

100 5 101 5 102 5 103 5 104 5 105 5.1 106 5 107 5.1 108 5.1 109 5.1 110 5.1 111 5 112 5 113 5 114 5 115 5 116 5 117 5 118 5 119 5 120 5 121 5 122 5 123 5 124 5 125 5 126 5 127 5 128 5 A- 1 5 A- 2 5 A- 3 5 B- 1 5 B- 2 5 B- 3 5 B4 5 B- 5 5 C- 1 5 C- 2 5 C- 3 5 C4 5 C- 5 5 C- 6 5 C- 7 5 C- 8 5 C- 9 5 j

l Davis-Besse.0DCM 111 Revision 5.1

Revision 5.1 means Revision 5 Chnage 1

l l

ODCH List of Effective Pages (continued) C-1 >

Page No. Revision

s

/

C 10 5 C- 11 5 C- 12 5 C. 13 5 C. 14 5 C- 15 5 C- 16 5 C- 17 5 C- 18 5 C- 19 5 C- 20 5 C. 21 5 C- 22 5 C- 23 5 C--24 5 C 5 C- 26 5 C- 27 5

C 28 5 C- 29 5 C J'O 5 C- 31 5 C 32 5 C- 33 5 C- 34 5 C- 35 5 C- 36 5.1 C- 37 5 J- 1 5 J- 2 5 J. 3 5' J- 4 5 J- 5 5 J- 6 5 J. 7 5 J- 8 5 J- 9 5 J- 10 5

'J. 11 5 J 12 5

. J . ' 13 5-J- 1/.- 5 J- 15 5 J. 16 5 J- 17 5 J 18 5-J- 19 5

! J- 20 5 J- 21 5 J 22 5 J- 23 5 J- 24 5 l

Davis-Besse ODCH iv Revision 5.1 l' ' Revision 5.1 means Revision 5 Change 1 l

l

!~

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

TABLE OF CONTENTS *

1.0 INTRODUCTION

. .. ........ .. . . . . . . . . . . . . . . 1 2.0 LIQUID EFFLUENTS . .. ...... . . . . . . . . . . . . . . . . 2 2.1 Radiation Monitoring Instrumentation and Controls . . . . . . 2 2.1.1 Required Monitors . .. . . . . . . . . . . . . . . 3 2.1.2 Non-Required Monitors . . . . . . . . . . . . . . . 4 2.2 Sampling and Analysis of Liquid Effluents . . . . . . . . . . 5 2.2.1 Batch Releases ........... . . . . . . . $

2.2.2 Continuous Releases . . . . . . . . . . . . . . . . $

2.2.3 Condensate Demineralizer Backvash . . . . . . . . . 7 2.2.4 Borated Vater Storage Tank and Primary Vater Storage Tank. . . . . . . . . . . . . 7 2.3 Liquid Effluent Monitor Setpoints . . . . . . . . . . . . . . 9 2.3.1 Concentration Limits. . . . . . . . . . . . . . . 9 2.3.2 Basic Setpoint Equation . . . . . . . . . . . . . . 9 2.3.3 Liquid Radvaste Effluent Line Monitor Setpoint Calculations. . . .......... . . . . . . . 10 2.3.4 Turbine Building Sump / Storm Sever Drain Monitor . . 12 2.3.5 Alarm Setpoints for the Non-Required Radiation Monitors .. . . . . . . . . . . . . . . 13 2;3.6 Alarm Response - Evaluating Actual Release Conditions. . . ............... . . . 14 2.4 Liquid Effluent Dose Calculations - 10 CFR 50 . . . . . . . . 16 16 2.4.1 Dose Limits to MEMBERS OF THE PUBLIC. . . . . . . .

2.4.2 MEMBER OF THE PUBLIC DOSE - Liquid Effluents. . . . 17 2.4.3 Simplified Liquid Effluent Dose Calculation . . . . 18 Contaminated TBS /SSO System - Dose Calculation. 19 l- 'z.4.4 . .

2.5 Liquid Ef fluent Dose Projections. . . . . . . . . . . . . . . 20 35 3.0 ' GASEOUS EFFLUENTS .................... . . . .

3.1 Radiation Monitoring Instrumentation and Controls . . . . . . 35 36 3.1.1 Alarm and Automatic Release Termination . . . . . .

Alarm only ... ............. . . . . 36 3.1.2 38 3.2 Sampling and Analysis of Gaseous Effluents . . . . , . . . . 38 i -3.2.1 Batch Releases. . .. . . . . . . . . . . . . . . .

38 3.2.2 Continuous Release. ... . . . . . . . . . . . .

3.2.3 Releases Resulting from Primary-to-Secondary 39 System Leakage. .... . . . . . . . . . . . . .

40 3.3 Gaseous Effluent Monitor Setpoint Determination . . . . . . .

40

'- 3.3.1 Release Rate Limits'. . . . . . . . . . . . . . . .

1 3.3.2 Individual Release Radiation Monitor Setpoints. . .

L 3.3.3 Conservative, Generic Radiation Monitor Setpoints . 42 42 3.3.4 Release Flov Rate Evaluation for Batch Releases . .

44 3.4 Site Boundary Dose Rate Calculation - Noble Gas . . . . . . .

v Revision 5.1 l C-1 Davis-Besse ODCM

(3.0 CASE 005 EFFLUENTS - continued) 3.5 Site Boundary Dose Rate Calculation - Radioiodine. Tritium, and Particulates. . ...... . . . . . . . . . . . . . .. 45 3.5.1 Dose Rate Calculation . . . . . . . . . . . . . . . 45 3.5.2 Simplified Dose Rate Evaluation for Radioiodine, Tritium a-/ 'er ticula t es. . . . . . . . . . . . . . 45 1

3.6 Goantifying Activity Released . . . . . . . . . . . . . . . . 46 j 3.6.1 Quantifying Noble Gas Activity Released Using !

Station Vent Monitor. . . . . . . . . . . . . . . . 46 3.6.2 Quantifying Noble Gas Activity Released Using ;

A Grab Sample . ..... . . . . . . . . . . . . . 47 f 3.6.3 Ouantifying Radiciodine Tritium, and Particulate Activity Released . ........... . . . . . 47 l

3.7 Noble Gas Dose Calculations - 10 CFR 50 . . . . . . . . . . . 49 j 49 3.7.1 UNRESTRICTED AREA Dose - Limits . . . . . . . . . .

Dose Calculations - Noble Cases . . . . . . . . 49 3.7.2 ..

3.7.3 Simplified Dose Calculation for Noble Gases . . .. 50 3.8 Radiciodine and Particulate Dose Calculations -

10 CFR 50 . . . . . . . . . . ....... . . . . . . . . . 51 51 3.8.1 UNRESTRICTED AREA Dose Limits . . . . . . . . . ..

3.8.2 Critical Pathvay. . . . . . . . . . . . . . . . . . 52 3.8.3 Dose Calculations - Radiciodine, Tritium and i

.... . . . . . . . . . . .. 52 j Particulates. . . .

3.8.4 Simplified Dose Calculation for P.adiolsl*.es and Particulates. . ................ 53 3.9 Gaseous Effluent Dose Projection . . . . . . . . . . . . .. 54

)

................. 97 4.0 SPECIAL DOSE ANALYSES .....

i 4.1 Doses To The Public Due To' Activities 97 inside the SITE BOUNDARY ..................

40 CFR 190 . . . . . . . . . 97 f 4.2 Doses to HEMBERS OF THC PUBLIC Effluent Dose Calculations. . . . . . . . . . . . . 99

! 4.2.1 4.2.2 Direct Exposure Dose Determination -

100 Onsite Sources. . . ............. ...

4.2.3 Dose Assessment Based on Radiological Environmental Monitoring Data . . . . . . . . . . . 101 4.2.4 Use of Environmental TLD for Assessing Doses 103 Due to Noble Gas Releases . . . . . . . . . . ..

. . . . . . . . . . . ... 105 5.0 ASSESSHENT OF LAND USE CENSUS DATA .

~

105 5.1 Land Use Census Requirements. . . . . . . . . . . . . . . ..

106 Data Compilation. . . . . . . . . . . . . . . . ..

5.1.1 106 5.1.2 Relative Dose Significance. . . . . . . . . . . . .

106 5.1.3 Data Evaluation . ..... . . . . . . . . . ...

i 5.2 Land Use Census to Support Realistic Dose Assessment . ... 107 Davis-Besse ODCH vi Revision 5.1 l C-1 l

l

__ m . .- m. _ _ _ . - . _ . - _ _ _ _

6.0 RADIOLOGICAL ENVIR0!!MEllTAL M0!i1 TORI!1G PROGRAM . . . . . . . . .. 108 I

6.1 Program Description . . . . . . . . . . . . . . . . . . . .. 108 l 6.1.1 General . . . . . . . . . . . . . . . . . . . . . . 108 i 6.1.2 Program Deviations. . .. . .. . .. . . . . . .. 108 i 6.1.3 Unavailability of Milk or Broad Leaf Vegetation Samples . . . . . .... . .. . . . . . . . .. 109 6.1.4 Seasonal Unavailability. Equipment Malfunctions.

Safety Concerns . . . .. . .. . . . . . .. 109 6.1.5 Sample Analysis . . . .. . .. . . . . . . . . .. 109 6.2 Reporting Levels. . . . . . . . . . . . . . . . . . . . . .. 109 109 6.2.1 General . . . . . . . . . . . . . . . . . . . . . .

Exceedance of deporting Levels. . 110 6.2.2 . . . . . . . ..

6.3 Interlaboratory Comparison Program . .. . . . . . . , , .. 110 1

7.0 ADMINISTRATIVE CONTROLS 7.1- Annual Radiological Environmental Operating Report . . . .. 123 7.2 Semiannual Effluent and Vaste Olsposal Report . . . . . . .. 123 125 7.3 Special Reports . . . . . . . .. . .. . . . . . . . . . ..

7.4 Major Changes to Radioactive Liquid and Gaseous 125 Vaste Treatment Systems . . . . .. .. . . . . . . . . ...

126 7.5 Definitions . .. . . . . . . .. .... .. . . . . . ...

126 7.5.1 Batch Release . . . . .... . . . . . . . . ... 126 7.5.2 Channel Calibration . . ... . . . . . . . . ... 126 Channel Check . . . .. . .., .. . . . . . ...

7.5.3 126 7.5.4 Channel Functional Test . .. .... . . . . ... 126 7.5.5 Ccmposite Sample. . ... ... .. . . . . . ...

Gaseous Radvaste Treatment System . . . . . . ... 126 7.5.6 127 Lover Limit of Detection (LLD). . . . . . . . ...

7.5.7 127 7.5.8 Member of the Pu'elic. . . . . . . . . . . . . ...

127 7.5.9 Operable - Operability. . .. . . . . . . . . ...

127 7.5.10 Purge-Purging . . . .. . . . - . . . . . . . . ... 128 7.5.11 Site Boundary . . . . . . . . . . . . . . . . ...

. . . . . .. . . . . . . . . . ... 128 7.5.12 Source Check 128 7.5.13 Unrestricted Area . . . ... . . . . . . . . ...

128 7.5.14 Ventilation Exhaust Treatment System. . . . . ...

128 7.5.15 Venting . . .. . .. . .... .. . . . . . ...

Davis-Besse ODCM vil Revision 5.1 l C-1

- _ - - _ - _ - - - _ _ . ~ . _ - - _ _ - . - _ - . . -. . . _ _ - - - . _ - . - . . - _ - _ - -

i APPENDICES APPENDIX A - Technical Basis for Simplifjed Dose Calculations, Liquid Effluent Releases. . . . . . . . . . . . . .. .. A-1 APPENDIX B - Technical Basis for Effective Dose Factors Gaseous Effluent Releases . . . . . . . . . . . . . . . . B-1 APPENDIX C - Radiological Environmental Monitoring Program, $ ample Location Haps . . . . .. . . . . ... C-1 .

I APPENDIX J - Justifications. . . . . . . . . . . . . . . . . . . .. . J-l LIST OF TABLES Table 2 Radioactive Liquid Effluent Monitoring Instrumentation . 22 .

Table 2 Radioactive Liquid Effluent Monitoring Instrementation Surveillance Requirements . . . . . . . . . . . . . . . . 24 Table 2 Radioactive Liquid Vaste Sampling and Analysis Program. . 26 Table 2 Limiting Radionuclide Concentrations in Secondary Side Clean-up Resins for Allevable Discharges to Onsite Settling Basin. . . . . . . .. . . . .. ... . . . ... 2.

Table 2-S - Radionuclide Activity Limits for the BVST and PVST. ... 30 Table 2 Liquid Ingestion Dose Committment Factors . . . . . . . . 31 Table 2 Bioaccumulation Factors . . .. . . . . ... .... .. 33 Table 3 Radioactive Gaseous Effluent Monitoring Instrumentation . 56 Table 3 Radioactive Gaseous Effluent Monitering Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . 59 Table 3 Radioactive Gaseous Vaste Sarplir.g and Analysis Program . 61 Table 3 Land !!se Census Summary . . . . . . . . . . . .. . ... 64 Table 3 Dose Fte : ors for Noble Cases . - . . .. .. . . . . ... 65 Table 3 Exposure Pathways, Controlling Parameters, and Atmospheric Dispersion for Dose Calculations. . . . ... 66 Inhalation Pathway Dose Factor. 6'/

Table _3 . . . . . . . . . . ...

Table 3 Grass - Cov - Hilk Pathvay Dose Facters . . . . . . . . 75 Table 3 Grass - Cov - Heat Pathvay Dose Facters . . . . . .... 83-Table 3-10-- Vegetation Pathway Dose Factors . . . . . . . .. .. 89 Ground Plane Pathvay Dose Factors . 95 Table 3 . . . . . . . ....

Table 4 Recommended Exposure Rates in Lieu of Site Specific Data. . ... . . . . . .. . . . . .... 104 Davis-Besse ODCM viii Revision 5.1 lC-1

l (List of Tables - Cont.)

Radiological Environtrental Monitoring Program . 111 Table 6 . ....

Required Senpling Locations . 116 Table 6 . . . . . .. . . . ....

Lover Limits of Detection . . .. . . .. .. . . .... 119 Table 6 Table 6 Reporting levels for Radioactivity Concentration: in Environmental Sartples. . . . . ..... 122 Table B Default Noble Gas Rad')nuclide Distribution B4 of Gaseous Effluents . . . . .. . . .... .. ....

B-5 Table B Effective Dose Factors - Noble Gas Effluents . . ....

J-8

~

Xe-133 Effective Concentration ... . . . . . . ....

Table J LIST OF FIGURES Figure 2-1 - Liquid Radioactive Effluent Honitoring and 34 Processing Diagram . . . . . .. , .. . . . . ... . .

Figure 3-1 - Gaseous Radioactive Effluent Monitoring and Ventilation Systems Diagram . . . . .. . . . .... . 96 1

ix Revision 5.1 lC-1 Davis-Besso 0DCM

- ~_-_m__ _ ___ __

- . ..- . . - . . .~ .. . --. .

. - . _ . . - .- ...-,- . . - - ~ . - - - . - - . . . . . . . . . - . - , - .

1 l

l l

I i

-i .

i r-i i

1 I

i l

i This page is intentionally blank.

~ ,

l

_ .[

r

[ ....

9 l

I

', h t

l; 1_

i

--' r m' e , e e, 4,,,,,W.,g ._

._..-.!..._. _,.L.,j,u....,_,_ ,_ ,_,, , _ - *- - . . - - , - - . _ . . . . , , , y.,

--- - - - - - - . . . - - _ - - - - - . - - . - ~ - . - . . .

7 1.0 INTRODUCTIO!!

The Davis-Besse Offsite Dose Calculation Manual (ODCM) describes the methojology and parameters used in: 1 I

- 1) determining the radioactive material release rates and cumulative releases:

2) calculating the raoloactive liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints: and

3) calculating the corresponding dose rates and cumulative quarterly and yearly doses.

The ODCH also describes and provides requirements for the Radiological Environmental Monitoring Program. Sampling locations, media and collection frequencies,and analytical requirements are specified. The methodology provided in this manual is acceptable for use in demonstrating compliance with concentration limits of 10 CFR 20.106: the cumulative Jose criteria of 10 CFR 50 Appendix II 40 CFR 1901 and the Davis-Besse Technical Specifications (TS) 6.8.4.d and 6.8.4.e. [l r

The exposure pathway and dose modeling presented provides estimates (e.g.,

calculational results) that are conservative (i.e., higher than actual exposures in the environment). This conservatism does not invalidate the modeling since the main purpose of these calculations is for demonstrating "As Lov As is Reasonably Achievable" (ALARA) for radioactive effluents. In using these models for evaluation and controlling actual effluents, further simplification and conservatism may be applied For purposes of demonstrating compliance with the EPA environmental dose standard for the Uranium Fuel Cycle (40 CFR 190), more realistic dose assessment modeling may be used.

The ODCH vill be maintained for use as a reference guide and training document of accepted methodologies and calculations. Changes to the ODCM calculational methodologies and parameters vill be made as necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR 50.

Appendix I,Section III and IV. Questions about the ODCM should be directed to the Manager - Radiological Control.

NOTE: Throughout this document, vords appearing all capitalized denote definitions specified in Section 7.5 of this manual, or comuon acronyms.

Section 2.0 describes equipment for monitoring and controlling liquid effluents, sampling requirements, and dose evaluation methods. Section 3.0 providus similar information on gaseous effluent controls, sampling. and dose evaluation. Section 4.0 describes special-dose analyses required for Regulatory Guide 1.21. Semiannual Effluent Reporting and EFA Environmental Dose Standard of 40 CFR 190. Section 5.0 describes the role of the annual land use censas in identifying the_ controlling pathways and locations of exposure for assessing the potential offsite deses. Section 6.0 describes I the Radiological Environmental Monitoring Program. Section 7.0 describes the environmental, efC aent and special reporting requirements, procedural

requirements for majur changes to liquid and gaseous radvaste systems, and l definitions.

Davis-Desse ODCM 1- Revision 5.1 l

l L --

.m _. _ . . _ _ _ . _ _ _ _ _ . _ _ _ _ . _ _ _ . _ _ . _ . _ . _ . _ . .

t l

I 2.0 LIQUID EFFLUENTS 2.1 RADIATION HONITORING INSTRUMENTATION AND CONTROLS i This section sunmarizes information on the liquid effluent radiation mcr.i'-ring instrumentation and controls. More detailed information is provided in the Davis-Besse USAR, Section 11.2. Liquid Vaste Systems and associattd design drawings from which this summary was derived. Location and control function of tbo monitors ate displayed in Figure 2-1.

The radioactive liquid effluent monitoring instrumentation channels listed in Table 2--I shall be OPERABLE vith their alarm / trip setpoints set to ensure that the limits of ODCH Section 2.3.1 are not ex reded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters of Section 2.3.

Vith a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

Vith less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the actions described in Table 2-1.

Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Effluent and Vaste Disposal Report (Section 7.2) 'hy the inoperability was not corrected in a timely _ manner.

Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated O!ERABLE by the performance of the CHANNEh r!!ECK, SOVRCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the l frequencies shown in Table 2-2. Each of these operations shall be l performed within 'he specified time interval with a maximum allovable L extension not to exceed 25 percent of the specified interval.

NOTE: The moaltors indicated in 2.1.1 a), b), and c) are inoperable if surveillances are not performed or setpoints are less conservative than required.

15e radioactive liquid effluent instrumentation is provided to monitor and co.* trol, as applicable, the releases of radioactive materials in liquid eff.'utnts during. actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with methods in-Sectic , 2.3~to ensure that the alarm / trip vill occur prior to exceciing the limits sf 10 CFR Part 20.

Davis-Besse ODCH 2 Revision 5

l This page is intentior, ally blank.

4

.r.

2.1.1 Required Monitors C-1 This section describes the monitoring required during liquid releases and the backup sampling tequired when monitors are inoperable, a) Alarm and Autoestic Release termination

i. Clee.n Radvaste Effluent Monitors-(RE-1770 A_) B)

Discharges from '.he Clean Ra(vaste Monito Tanks (2) are monitored by radundant radiation monitnring systems (RE-1770 A &

B). These monitors detect gross gamma activity in the effluent prior to mixing in the Collection Box. Heasurements from each detector read out on the Victoreen panel in the Control Room.

Each monitoring system is capable of initiating an alaim and an automstic termination of the release by closing valve VC-1771.

The method for determining setpoints for the alarms is discussed in Section 2.3.

11. Miscellanecus P.advnste Effluent Honitors (RE.1878 A & B)

DiscE'arges from the Miscellaneous Liquid Vaste Monitor Tank and the Detergent Vaste Drain Tank are monitored by redundant raolation monitoring systems (RE-1878 A & B). These monitors detect gross gamma activity in the effluent line prior to mixing in the Collectivn Box. Measurements from each detector read out on the Victoreen panel in the Control Room. Each monitor is separately capable of initiating an alarm and automatic termination of the release by clobina valve VH-1876. Setpoint determination for the alarms is discussad in Section 2.3.

b) Alarm (nnly)

1. Turbine Building Sump / Storm Sever Drain Line (RE 4686)

The monitor on the Turbine Building Sump / Storm Sever Drain effluent line detects abnormal radionuclide concentrationa in the sump effluent. This munitor is located near the end of the storm sever drain pipe, upstream of the final discharge point into the Training Center Pond. The most probable source of any radioactive material in the sump vou'.d be from 'he secondary system.

When radioactivity is present in the secondary system, the Turbine Building Sump effluent shall be directed to the onsite Settling Basins. In this configuration, the source of raditactivity in the Turbine Building Sump / Storm Sever Drain line is from Turbine Building drains that are not routed to the Turbine Building Sump or from Stotm Sever drains. Evaluation of the alarm setpoint for RE-4686 is discussed in Section 2.3.4.

Davis-Besse ODCH 3 Revision 5.1

c) Flow Rate Measuring Devices

1. C_ lean Radvaste Effluent Line Flow Indicator (FI) 1700 A & E Flov Totalizer (FOI) 1700 A & d !

11. Miscellaneous Radvaste Effluent Line j Flow Indicator (F1) 1387 A & B Flow Totalizer (F01) 1887 A & D iii. Dilution Flov to the Collection Box ,

Computer Polr.t F201 2.1.2 Non-Required Monitors lC-1 Additional monitors, although not required by the ODCH, have been installed to monitor radioactive material in liquid. The monitors ares lC-1 Collection Box outlet to the Lake (RE-8433) - monitors the final station effluent to the lake.

- Component Cooling Vater System (CCVS) (RE-1412 & 1413)-

monitors the CCVS return lines. High alarm closes the atmospheric vent valves on the CCVS surge tank.

- Service Vater System (SVS) (RE-8432) - off-line detector monitors the SVS outlet prior to discharge'to the Collection Box, and

- Intake Forebay (RE-0434) - monitors the st .lon-intake water from Lake Erie.

4 l-l-

l i

Davis-Besse ODCH 4 Revision 5.1

.. . - - . . . . - _ . . . . - . . . . - - - - . . ~ - . . . - _ . . - -

-y. .

l 4

l l

i i

i 1

P This-page is intentionally blank.

+

2 l

O 5

w w .e. .-,w., ..we,u y,,,,-e ,- r a r wt -m

V 2.2 SAMPLING AND ANALYSIS OF LIQUID EFFLUENTS As a minimum, radioactive liquid vastes Jhall be sampled and analyzed accordir:g to the sampling and analysis program of Table 2-3. Table 2-3 identifies three potential sourcer of liquid radioactive effluents.

The tesults of the radioactivity analyses shall be used in accordance with the methodology and parameters of this section to ensute that the concentrations at the point of release are maintained within the limits of 10 CFR 20.106.

2.2.1 Batch Release _s BATCH RELEASE is defined as the discharge of liquid vaste of a discrete volume. The releases from the Clean Vaste Monitor Tanks 1-1 and 1-2, the Miscellaneous Liquid Vaste Monita Tank, and the Detergent Vaste Drain Tank are classified as BATCH PELEASES. The following sampling and analysis requirements must be met for all releases from these tanks.

- Prior to each release, analysis of a representative grab sample for principal gamma emitters.

- Once per month, as a minimum, analysis of one sample from a BATCH RELEASE for dissolved and entrained gases (see note belov).

1 Once per month, analysis of a COMPOSITE SAMPLE of all releases that month for tritium and gross alpha activity. Samples contributed to i the composite are to be proportional to the quantity of liquid discharged.

- Once per quarter, analysis of a COMPOSITE SAMPLE of all releases that quarter for Strontium (Sr)-89, Sr-90, and Iron (Fe)-55.

NOTE: Identification of noble gases that are principal gamma-emitting

. radionuclides are included as a part of the gamma spectral analysis performed on all liquid radvaste effluents.

Therefore, the Table 2-3 requiretent for samplir.g and analysis of one batch per month for noble gases need not be performed as a separate program, f

2.2.2 Continuous Releases Releases from the Turbine Building Sump (TBS) and Storm Sever Drains (SSD) l

are classified as continuous releases.

l Turbine Building Sump discharges may contain minute concentrations of radionuclides due to primary-to-secondary system leakage. .In this situation, the Turbine Building Sump discharges are routed to the onsite Settling Basins instead of the TBS /SSD line. Overflov from the Settling Basins is pumped to the Collection Box vhere it is mixed with dilution flov and released to Lake Erie. Releases via this pathway are monitored by veekly analysis for principal gamma-emitting radionuclides and tritium, and by quatterly analysis of composite samplos for Fe-55, Sr-89 and St-90.

l Davis-Besse Ot<M 5 Revision 5 l

. , - - _ , - ~ _ _ - _ _

_ - _ - --..-.-.-.-.-_-..- ~.- -_- - . - - . - . - . -

Discharges to the Storm Sever Drains are from Turbine Building drains that are not routed to the TBS and from storm drains when the TBS effluent is routed to the Settling Basin;. The Storm Sever discharges to the Training Center Pond with the overflov discharging to the Toussaint River. For conservatism it is assumed that radioactive material released to the Training Center Fond is ultimately discharged to take Erie (unless actions are taken to prevent this occurrance).

Table 2-3 requires that a sample shall be collected trom the TBS or SSD if the on-line monitor is out-of-service and the activity level of the condensate (i.e., hot vell vater) exceeds 1.0 E-0$ uCl/ml gross beta / gamma. l This sample is to be collected once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyzed for i principal gamma emitters. i Grab samples are collected weekly fron the Settling Basins and analyzed by l gamma spectroscopy. If activity is identified, additional controls are l enacted to ensure that the release concentrations are maintained below MPC J and that the cumulative releases are a small fraction of the dose limits of i Section 2.4.1. The following actions vill De con:idered for controlling ,, l any radioactive materiel r61 eases via the TBS and SSD:

- Increase the sampling frequency of the TBS and SSD until the source of the contamination is identified. ,

- Perform gamma spectral analysis on each sample for principal gamma emitters,

- Compare the measured radionuclide concentrations in the sample with lC-1 HPC (equation 2-3) to ensure releases are within the limits. ;

- Based on the measured concentrations, a re-evaluation of the alarm setpoint for the SSD monitor (RE-4686) may be performed as specified in Section 2.3.4.

- Consider each sample representative of the releases thst have occurred since the previous sample. Determine the volume of liquid released from the Turbine Building Sump based'on the Turbine Building Sump pump runtimes and flow rates.

- Determine the total radioactive material released from the sample analysis and the calculated volume released. Determine cumulative d ses in accordance t " Section 2.4 9

Davis-Besse ODCM 6 Revision 5.1

I 2.2,3 condensate Deaintrallrer Backwash Discharges from the Condensate Demineralizer Backvash Receiving Tank (BRT) 1

-to the South Settling Basin are sampled in accordance with Table 2-3. I !

Samples are collected prior to each release of the resin / vater slurry and i separated into the liquid phase (transfer water) and solid phase (resin). j These samples are separately analyzed for principal gamma emitters. Toledo j Edison has imposed guidelines on concentrations of radionuclides that may I be discharged to the onsite Settling Basin. These guidelines are presented in Table 2-4.

The radioactive material contamination in the condensate deminerallrer backvash vill be contained on the powdered resin soluble or suspended radioactive material associated with the water phase is not expected.

The resin and the water are analyzed separately thus allowin7 for a determination of the amounts retained onsite in the Settling Basin (the resin) and the amounts released to Lake Erie as an effluent (the decant). l >

The BRT receives the spent resin from the Condensate Polishing System.

Lov-level radioactive material contamination of the spent resin is periodically expected due to minor veeps in the steam generators and the leaching of residual activity in the secondary system.

l During primary-to-secondary leakage, activity levels viA'. be elevated and typically above the limits imposed for ecceptable discharge to the basin.

Under these conditions, the powdered resins are retained within the plant and processed as solid radvaste for offsite transport and disposal at a licensed radioactive vaste disposal site. If within the criteria of rable 2-4, the DRT may be discharged to the onsite settling basin with the approval of the Manager - Radiological Control.

2.2.4 Borated Vater Storage Tank and Primary Vater Storage Tank The quantity of radioactive material stored in in the Borated Vater Storage Iank (BVST) and Primary Vater Storage Tank (PVST) shall be limited to ensure the following:

1) Protected Area boundary dose rates remain less than 0.25 mR/hr, and

2) Tank rupture vould result in isotopic concentrations below-the limits of 10 CFR 20.106 at the nearest offsite potable water intake.

The concentration of radionuclides in the DVS1 and PVST shall be dete'rmined-to be within the applicable limits by analyzing a representative sample of the tank contents at least once per 7 days when radioactive materials are

, being added to the tank. Although the PVST is not currently used to l support plant operation, the following limits still vould apply should it u be in use, l

i L

Davis-Besse ODCH 7 Revision 5 i l

l

The method for limiting the BVST and PVST radionuclide concentration to meet the criteria above is described below and represented in equation s[

(2-1).

1) Determine the limiting fraction of each radionuclide present in a liquid sample from the tank. This is the sample concentration times the volume of liquid in the tank divided by the limiting activity from Table 2-5.

2) Sum the limiting fractions of each rndinnuclide in the sample.

This sum should be less than one (1) to meet the limiting criteria for area dose rates and offsite dose rates via the liquid pathway.

n C I

VOL

3785 LP sum

- E (2-1) 1-1 A lim i Vhere

~~

s LF - sum of the limiting f raction of each radionuclide i in sum the sample, C - c ncentration of radionuclide i in the liquid sample ,

si (uC1/ml),

VOL - volume of liquid in the tank (gal),

3785 - ml per gal, A gg, g - limiting activity of radionuclide i f rom Table 2-5 (pci/ml), and n - number of radionuclides found in the liquid sample.

If the sum of the limiting fractions of radionuclides in the BVST or FVST axceeds one (1), then suspend all additions of radioactive material to the tank, reduce tank contents to vithin the limits, and describe the events leading to this condition in the next Semiannual Radiological Effluent and Vaste Disposal Report.

The values in Table 2-5 were celculated specifically for the BVST. Ther ;

are conservative for the PVST due to its smaller volume. .

Davis-Besse ODCM 8 Revision 5

2.3 LIQUID EFFLUENT MONITOR SETPolNTS 2.3.1 Concentration Limits The concentrations of radioactive material released in liquid effluents to UNRESTRICTED APEAS shall be limited to the concentrations specified in 10 CFR Part 20.106 for radionuclides othet than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 uCi/ml. If the concentration of radioactive material released in liquid ef fluents to UNRESTRICTED AREAS exceeds these limits, then vithout delay restore the concentrations to within these limits.

This limitation provides additional assurance that the levels of radioactive material in bodies of water outside the site should not result in exposures exceeding the Section II. A design objecti e of Appendix I, 10 CFR Part 50, to an individual, and the limits of 10 CFR Part 20.106(e) to the population. _

The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) vas converted to an equivalent concentration in vater using the methods described in International Commission on Radiological Protection (ICRP)

Publication 2.

2.3.2 Basic Setpoint Equation Radiation monitor setpoints shall be establiched to alarm and trip prior to exceeding the limits specified above. To meet this requirement. the alarm / trip setpoint for liquid effl".ot monitors measuring the radioactivi'y concentration prior to dilution is derived in Section 2.3.3 from the following basic relstionship:

CL (DF.RR)

SP$ (2-2)

. RR vheret .

SP = the setpoint of the monitor measuring the radioactivity concentration in the effluent line prior to dilution. The setpoint represents a value which, if exceeded, vould result in concentrations exceeding the MPC in the UNRESTRICTED AREA (UCi/ml),

CL - the UNRESTRICTED AREA effluent concentration limit defined in equation (2 4) vni.ch implements 10 CFR Part 20.106 (uci/ml),

RR = the liquid effluent release tate as measured at the radiation monitor location (gal / min), and I DF = the dilution water flow rate as measured prior to the release point (gal / min). I If no dilution is provided, then SP 3 CL. Also, when DF is large compared to RR. then (DF + RR) = DF.

Equations for calculating setpoints for specific radiation monitors are provided in the subsequent sections.

Davis-Besse ODCM 9 Revision 5

2.3.3 Liquid Radvaste Effluent Line Monitor Setpoint Calculations (RE-1770 ~~~

A & B, RE-1878 A & B)

The Liquid Radvaste Effluent Line Monito!1 provide alarm and automatic termination of releases prior to exceeding MPC at the UNRESTRICTED AREA. l As required by Table 2-3 and as discussed in Section 2.2.1, a sample of the liquid radvaste to be discharged is collected and analyzed by gamma spectroscopy to identify principal gamma-enL :;ing radionuclides. A maximum release rate from the tank is determined for the release based on the radionuclide concentrations and the available dilution flow rate.

The maximum release rate is inversely proportional to the ratio of the l radionuclide concentrations to their MPC values. This ratio of measured l concentration to MPC values is referred to as the MPC fraction (MPCF) and l I

ts calcula,ed by the equation:

Cg l HPCF - I (2-3) l 1 MPC j 3

vhere:

HPCF . sum of the fractions of the unrestricted area MPCa for a mixture l of radionuclides, Cg . concentration of each radionuellde i measured in tank prior to release (uci/,al), and HPC 3

unrestricted area HFC for tech radionuclide i f rom 10 CFR Part

20. Appendix B, Table II, Column 2. For dissolved and entrained noble gases an HPC value of 2.0E-04 uCi/ml shall be used (uC1/ml).

As expressed in equation (2-2), the concentration limit (CL), or effective UPC, tcpresents the equivalent MPC value for a mixture of radionuclides evaluated collectively. The equation for determining CL is:

I CL . (2-4)

HPCF Based on the HPCF, the minimum dilution factor (MDF) for the conduct of the release is established at 3.33 times larger than actually required. This safety factor (SF) provides conservatism, accounting for variations in monitor response and-flow rates and also for the presence of radionuclides that may not be detected by the monitors (i.e., non-ftmma emitters). The following equation is used for cal:ulating the required minimum dilution factor:

MDF . MPCF/SF (2-5) l vhere:

MDF. . minimum required dilution factor,,and l SF . 0.3 administrative safety factor.

Davis-Besse ODCM 10 Revision 5 e - e.r v --m-, . w. . , - - , w - .w+ .--,,-mmm,- . r% -,-.w- - - ..r...m.-,- , , - - , . ,---w-_-. e- - , . , , - - --,-ewy-- . - , - - e

The maximum release rate from the tank is then calculated by dividing the e.vailable dilutio.: flov rate (ADF) at the Collection Box by the MDF as calculated by equation (2-5).

HAX RR = 0.9 (ADF/MDF) (2-6) where HAX RR maximum allovable release rate (gal / min).

0.9 - administrative conservatism factor, and ADF - available dilution flow rate at the Collection Box as measured by Computer Point F201 (gal / min).

NOTE: Equations (2-5) and (2-6) are valid only for MPCF >1. For MPCF j $1, the vaste tank concentration is below the li-its of 10 CFR Part 20 vithout dilution, and MAX RR may take on any value within discharge pump capacity.

If MAX RR is greater than the maximum discharge pump capacity, then the pump capacity should be used in establishing the actual release rate (RR) for the radvaste discharge. For releases from the Miscellaneous Vaste Monitor Tank and Detergent Vaste Drain Tank, the discharge pump capacity is 100 gpm; for the Clean Vaste Monitor Tank, this value is 140 gpm.

Since the actual release rate from the tat i is derived such that 10 CFR 20.106 limits vill not be exceeded given the radionuclide concentration in the tank and the available dilution flow, setpoints must be established to ensure:

1) radionuclide concentration released from the tank does not increase above the concentration detected in the sample,

2) available dilution flow does not decrease, and

3) actual release rate from the tank does not increase above the calculated value.

The setpoints for the predilution radiation monitor (RE-1770 A & B, or RE-1878 A & B) are determined as follows:

Alert Alarm SP = [2

I (C g

SENg )) + Bkg (2-7)

High Alarm SP - [3

I (C g* SEN g)] + Bkg (2-8) vhere SP = setpoint of the radiation monitor (cpm).

Cg -- concentration of radionuclide i as measured by gamma spectroscopy (uCi/ml).

SEN g= monitor sensitivity for radionuclide i based on calibration curve (cpm per UC1/ml). and Bkg = background reading of the radiation monitor (cpm).

Davis-Besse ODCH 11 Revision 5

The Cs-137 sensitivity may be used in lieu ok the sensitivity values for individual radionuclides. The Cs-137 sensitivity provides a reasonably conservative monitor response correlation for radionuclides of interest in reactor effluents. Coupled with the safety factor SF in equation (2-5),

this assumption simplifies the evaluation without invalidating the overall

.:onservatism of the setpoint determination.

The high flov setpoint should be set equa'i to the MAX RR calculated in equation (2-6). The lov flov setpoint for dilution flov rate should be set at 0.9 times the available dilution f".ov rate.

2.3.4 Turbine Building Sump / Storm Sever Drain Monitor (RE 4686)

The setpoint for the TBS /SSD radiation nonitor, RE-4686, shall be established to ensure the radioactive raterial concentration in the effluent prior to discharge offsite do>ss not exceed MFC, UNRESTRICTED AREA (10 CFR 20, Appendix B. Table II, Colvian 2). The SSD is not normally radioactively contaminated by other than naturally-occurring radionuclides.

Therefore, the setpoint for this aionitor has been established at its lowest 1 ptactical level (i.e., three times the normal background) in order to provide an early indication of any abnormal conditions.

If radioactivity is found in this system, then a setpoint may be determined by using the measured radioactive naterial concentration from the grab sample and equation (2-10). For twe SSD line monitor, there is no dilution prior to discharge to the Training, Center Pond. Therefore, equation (2-2) is used in its simplified form for situations with no dilution flow:

SP $ CL (2-9)

Also, since discharge is to the Training Center Pond, exceeding the RE 4606 setpoint-does not necessarily mean Section 2.3.1 concentration limits have been exceeded at UNRESTRICTED AREAS. The verification of compliance with C-1 the limits on concentration should be based on actual samples of the effluent from the pond to the Toussaint River and Lake Erie. (Refer to Section 2.3.6).

Substituting eg'stion (2 4) for CL in equation (2-9), the alarm setpoint can be calcu.atad by the equation:

I (C g* SENg)

~

MPCF vheret Cg = concentration of each radionuclide r in the ef fluent (uCi/ml).

MPCF - MPC fraerion as determ.ined by equation (2-3), and SEN g. monitor sensitivity for radionuclide i based on calibration curve (cpm per uCi/ml).

Again, the Cs-137 sensitivity may be used in lieu of the individual radionuclide evaluation as discussed for equations (2 7) and (2-8).

Davis-Berse ODCM 12 Revision 5.1

2.3.5 Alarm Setpoints for the Non-Required Radiation M,nitors ,

a) Collection Box outlet to the Lake (RE-8433)

The radiation monitor on the Collection Box outlet utilizes a single off-line detector to continuously monitor all station liquid effluent discharges to the lake. Although this is the final effluent moniter, it does not serve any control function. Control functions have been placed on the upstream undiluted effluent line that vill terminate the release prior to exceeding the MPC for UNREETRICTED AREAS.

RE-8433 provides a final check of the total diluted effluent strt;m.

Since this monitor views the diluted radvaste discharges, its response during routine operations vill be minimal (i.e., typical of background 1evels). Therefore, the alarm setpoint for this monitor should be

[]} established as close to background as possible without incurring a spurious alarm due to background fluct'a' ions. The setpoint is controlled in accordance with the Radi tam onitor Setpoint Manual. _

The setpoint for the portdilution rad. .on monitor (RE 8433) on the liquid effluent st. ,aa be dete. mined as follows: ,

I (C,

SEN g )

RR SP = + Bkg (2-11)

MPCF

DF vhere:

SP = setpoint of the postdilution radiation monitor (epm),

Cg = concentration of radionuclide i in the tank as measured by gan.aa spectroscopy (uCi/ml),

SEN a mcnitor sensitivity for radionuclide i based on calibration i curve (cpm per pCi/ml),

DF = dilution flow rate (gal / min), {

RR = actual release rate of the liquid radvaste discharge (gal / min),

MrGF = MPC fraction as determined by equation (2-3), and Bkg - background reading of monitor (cpm).

The Cs-137 sensitivity may be used instead of the individual radionuclide sensitivities as discussed pteviously.

. Davis-Besse ODCM 13 Revision 5.1

b) Component Cooling Vater System (CCVS) (RE-1412 & 1413)

The monitors RE-1412 and 1413 provide indication of a breach in the CCVS integrity, allowing reactor coolant water to enter and I contaminate the system. Therefore, the alarm setpoint is established as close to background as possible without incurring a spurious alarm due to background fluctuations. The setpoint is controlled in I accordance with the Radiation Monitor Setpoint Manual.

c) Service Vater System (SVS) (RE-8437)

No radioactive material is expected to be contained within the SVS during normal operations. Therefore, the alarm setpoint is established as close to background as possible without incurring a spurious alarm due to background fluctuations. The setpoint is controlled in accordance with the Radiation Monitor Setpoint Manual. I d) Intake Forebay Monitor (RE-8434) =

The alarm setpoint for this monitor should be established as close to background as possible without in arring a spurious alarm due to background fluctuations. Although a very remote potential, a verified alarm from this system would indicate a possible contamination of the station intake water. The setpoint is controlled in accordance with l the Radiation Monitor Setpoint Manual.

2.3.6 Alarm Response - Evaluating Actual Release Conditions Liquid release rates are controlled and alarm setpoints are established to ensure that releases do not exceed the concentration limits of Section 2.3 (i.e., 10 CFR 20 HPCs at the discharge to Lake Erie). However, if any of the monitors (RF-1770 A & B, RE-1878 A & B, or RE-4686) alarm during a liquid release, it becomes necessary to re-evaluate the release conditions to determine compliance with the limits. After an alarm, the following actual release conditions should be determined:

c

- verify radiation monitor alarm setpoint to ensure consistency with the

setpoint evaluation for the telease;

- re-sample and re analyze the source of the release (e.g., release tank, TB sump, decant from Training Center rond to the Toussaint River); and re-determine the release rate and the dilution water flov. l Davis-Besse ODCM 14 Revision 5

. ~ __ _ _ _ . _.

Based on these data -the following equation may be used for evaluating the actual release conditions:

C RR 3

I *

$1 (2-12)

MPC g DF + RR C

3

. measured concentration of radionuclide in the effluent stream prior.to dilution (uci/ml),

MPC g= the MPC value for radionuclide I from 10 CFR 20, Appendix B, Table II, Column 2 or 2.0E-04'uci/ml for dissolved or entrained noble gases (pC1/ml),

RR . . actual release rate of the liquid effluent at the time of the alarm (gal / min), and DF = actual dilution water flov at the time or the release alarm (gal / min).

If the value calculated by equation 2-12 is less than or equal to 1, then the release did not exceed the limits of 10CFR 20.106.

Davis-Besse ODCM 15 Revision 5

.- l This page--is intentionally blank.

s k

1

t 2.4 L10VID EFFLUENT DOSE CALCULATION - 10 CFR 50 2.4.1 Dose Limits to MEMBERS OF THE PUBLIC Sf Technical Specification limits the dose or dose commitment to MEMBERS OF THE PUbLIC from radioactive materials in liquid effluents from Davis-Besse.

The limits are:

- during any calendar quarter:

< 1.5 mrem to total body

~$ 5.0 mrem to any organ

- during any calendar year:

$ 3.0 mrem to total body

$ 10.0 mrem to any organ e

Vith the calculated dose from the releasa of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of a Licensee -

Event Report, prepare and submit to tie Commission within 30 days, pursuant to Section 7.3, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the .orrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in complience vitt the above limits.

TS requires that cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

This requirement is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50.

This action provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I, 10 CFR Part 50 to assure that the releases of radioactive material in liquid effluents vill be kept "as lov as is reasonably achievable."

NOTE: For fresh water sites with drinkini vater supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility vill not result in ;)

radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR l'il. The dose calculations in the ODCM imolement the requirements of Section III.A of Appendix I of 10 CPR Part 50 that conformance with the guides of Appendix I is to be shown by calculational procedures based on modes and data such that the actual exposure of an individual thorough appropriate pathways is unlike'* to be substantially underestimated. The equations spec, ed in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Davis-Besse ODCM 16 Revision 3

_ - _ - ~ . - -- _ _ _ _ _ .. - ~ - - - _

Annual Doses to Man from Routine Releases of Reactor Effluents'for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 19/7.

2.4.2 MEMBER OF THE PUBLIC DOSE - Liquid Effluents The calculation of the potential doses to MEMBERS OF THE PUBLIC is a function of the radioactive material releases to the lake, the subsequent transport and dilution in the exposure pathvays, and the resultant individual uptake. At Davis-Besse, the combined fish consumption anl drinking vater pathvay has been modeled to provide a conservative dose assessment for exposures to MEMBERS OF THE PUBLIC, For the fish pathway, it has been conservatively assumed that the maximum exposed individual consumes 21 kg per year of fish taken in the immediate vicinity of the Davis-Besse discharge to the lake. For the drinking water pathway, the conservative modeling is based on an individual drinking 730 liters per year of water from'the beach wells located 966 m to the NV of the site discharge. (It is important to note that because of the high sulfur content, the water from these beach wells is not suitable for consumptiu,;

however, for conservatism this pathway has been included in the dose modeling for the maximum exposed individual.)

The equation for assessing the maximum potential dose to MEMBERS OF THE PUBLIC from liquid radvaste releases from Davis-Besse is:

1.67E-02

V0L D, -

I (C *Agg) g (2-13) where:

Dg - dose or dose commitment to organ o including total body (mrem),-

A,g

= site-specific ingestion dose commitment factor to the total body

. or any organ o for radionuclide i given in Table 2-6 (mrem /hr per pCi/ml),

C 1

- average conr.entration of radionuclide i in undiluted liquid ef fluent representative of the the volume VOL (pCi/ml),

VOL = total volume of undiluted liquid effluent released (gal),

DF = average dilution water-flow rate during release period (gal / min)

(typically 20,000 gpm),

Z = 10, near field dilution factor *, and 1.67E-02 -

I hr/60 min.

Near field dilution factor and dilution to beach vells are based on a study

, performed by Stone & Vebster for Toledo Edison entitied " Aquatic Dilution Factors within 50 Miles of the Davis-Besse Unit 1 Nuclear Power Plant", June 1980.

Davis-Besse ODCM 17 Revision S

I l

i i

The s'.te-specific ingestion dose / dose commitment factors (Ag) represent ,

J a composite-dose factor for the fish and drinking water pathway. The site-specific dose factor is based on the NRC's generic maximum individual consumption rates. Values of A g are presented in Table 2-6. These values were derived in accordance with ihe guidance of NUREG-0133 using the following equation:

4 Up

BF 3) DF 3 (2-14)

A g . 1.14E+05 (Up/Dy where:

Up . 21 kg/yr adult fisn consumption, Up . 730 liters /yr adult vater consumption, Dy - 5.7 additional dilution from the near field to the beach wells (net dilution of 57),

BF g . bioaccumulation f actor for radionuclide i in fish from Table 2 7 (pC1/kg per pC1/1),

DF g . dose conversica f actor for nuclide i for adults la organ o from Table E-11 of Regulatory Guide 1.109 (mrem /pCl), and 1.14E+05' . 106 (pcl/uci)

103 (ml/kg) / 8760 (hr/yr).

The radionuclides included in the periodic dose assessment required by Section 2.4.1 are those identified by gamma spectral analysis of the liquid {C-1 vaste samples collected and analyzed per the requirements of Table 2-3.

In keeping with the NUREG-0133 guidance, the adult age group represe.us the maximum exposed individual age group.- Evaluation of doses for other age groups is not required for demonstrating compliance with the dose criteria of Section 2.4.1. The dose analysis for radionuclides requiring l0-1 radiochemical' analysis vill be performed after receipt.of results of the analysis of the composite samples. In keeping with the required analytical least frequencies of Table-2-3 tritium dose analyses will be pe-formed atleast monthly; Sr-89, Sr-90 and Fe-55 dose analyses vill be performed at

. quarterly.

2.4.3 Simplified Liquid Effluent Dose Calculation-In lieu of the individual radionuclide dose assessment presented in Section 2.4.2, the following simplified dose calculation may be used for demonstrating compliance with the dose limits required by Section 2.4.1. lC-1 Radionuclides included in this dose calculation should be those measured in the grab sample of the release (principal gamma emitters measured by gamma spectroscopy). H-3 should not be included in this analysis. Refer to Appendix A for the deriva.t ion of this simplified method.

Total Body 9.70E+02

VOL

IC (2-15)

D g- g Maximum Organ 1.19E+03

VOL D . *I C (2-16) 3 18 Revision 5.1 Davis-Besse ODCh

where:

C. 3

. average concentration of radionuclide i excluding H-3 in ur.3ilu t ed liquid effluent representative of the release volume (uci/ml),

VOL - volume of liquid effluent released (gal),

DF = average dilution Vater flow rate during release period (gal / min),

D tb

= conservatively evaluated total body dose (mrem),

D,,x . conservatively evaluated maximum organ dose (mrem),

9.70E+02 0.0167 (hr/ min)

5.81E+C' (mrem /hr per UCi/ml, Cs-134 total body dose factor from Table 2-6) / 10 (near field dilution), and 1.19E+03 0.0167 (hr/ min)

7.11E+05 (mrem /hr per pC1/ml, Cs-134 liver dose factor from Table 2-6) / 10 (near field dilution).

2.4.4 Contaminated TBS /SSD System - Dose Calculation If the TBS /SSD system becomes contaminated, then any radioactive material released must be included in the evaluation of the cumulative dose to a -

HEMBER OF THE PUBLIC. Although the discharges are via the Training Center f

-Pond to Pool 3, and then to the Toussaint River (instead of directly to Lake Erle), the modeling of equation (2-11) remains reasonably conservative for determining a hypothetical maximum individual dose. The following assumptions should be applied for the dose assessment of any radioactive material releases from the TBS /SSD into the Training Center Pond and subsequently to the Toussaint River:

- If no additional controls are taken, then it chould be assumed that l any radioactive material released to the Training Center Pond vill

.. ultimately be discharged to the lake environment;

- If actions are taken to limit any release, then the assessment of dose should be made based on an evaluation of actual releases; and The dilution flow should consider additional dilution of the TBS /SSD discharge from other sources into the Training Center Pond prior to release to the river.

Davis-Besse ODCM 19 Revision 5

! 2.5 L10UID EFFLUENT DOSE PROJECTIONS 10 CFR 50.36a requires licensees to maintain and operate the radvaste system to ensure releases are maintained ALARA. This Section implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section II.D of Appendix I to 10 CFR Part 50. Based on a cost analysis of treating liquid radvaste, the specified limits governing the use of appropriate portions of the liquid radvaste treatment system were specified as the dose design objec .ives as set f orth in Section II. A of Appendix I,10 CFR Pr.rt 50, for liquid effluents. This requirement is implemented through this ODCH.

The liquid radioattive vaste processing system shall be used to reduce the radioactive material levels in the liquid vaste prior to release whers the projected doses in any 31-day period would exceed:

- 0.06 mrem to the total body, or

- 0.20 mrem to any organ. ,

This dose criteria for processing is established at one quarter of the design objective rate (i.e., 1/4 et 3 mrem /yr total body and 10 mrem /yr any organ over a 31-day projection).

Vith radioactive liquid vaste being discharged without treatment and in excess of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, a Special Report that includes the following information:

- explanation of why liquid radvaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability;

- action (s) taken to restore the inoperable equipment to OPERABLE

. statust and

- summary description of action (s) taken to prevent a recurrence.

TS requires that in any nonth in which radioactive liquid effluent is being discharged without treatment, doses due to liquid relesses to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCH.

Da"is-Besse ODCM 20 P.evision 5

. - - - . .. _ _ - . - - - .. ~ . -

di The following equations may be used for the dose projection calculation:

-D (2-17) tbp Dtb (31 / d)

D,,xp = D,,, (31 / d) (2-18) where D

tbp - the 31-day total body dose projection (mrem), l D

tb

- the cumulative total body dose for current calendar-quarter including release under consideration as determined by equation (2-13) or (2-15) (mrem),

-D maxp

= the 31-day maximum organ dose projection (mrem). -l D***

- the maximum organ dose for current calendar quarter including release under consideration as determined by equation (2-13) or (2-16) (mrem),

d . the number of days accounted for by the calendar quarter dose,

and 31 = the number of days in projection.

4 Davis-Besse ODCM 21 Revision 5

Table 2-1 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION .

MINIMUM CilANNELS OPERABLE APPLICABILIT7 ACTION INSTRUMENT

1. Gross Radioactivity Honitors Providing Alarms and Automatic ,

Termination of Relea :2 1 I

a. Liquid Radvaste Effluent Line 1 (1) A i I

(either Miscellaneous or Clean, but not both simultaneously)

2. Flow Rate Measurement Devices

a. Liquid Radvaste Effluent Line 1 (1) B

b. Dilution Flov to Collection Box 1 (1) B

3. Gross Dera or Gamma Radioactivity Monitors Eroviding Alarm But Not Providing Automatic Termination of Relesse (1) B,C

a. Turbine Building / Storm Sever Prain 1 l

i 22 Revision 5 Davis-Besse ODCM w.:

. ~ . . . - .- . .

Table 2-1 (continued)-

TABLE NOTATION (1) During radioactive releases via this pathway ACTION A Vith the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases may be resumed, provided that prior-to initiating a-release:

1. At least two independent samples are analyzed in accordance with Table 2-3 for analyses performed with each batch;

2. At least two independent verification of the release rate calculations are performed

3. At least.tvo independent verifications of the discharge valving are performed; Otherwise~, suspend release of radioactive effluents via.this pathway.-

ACTION B -Vith the number-of channels OPERABLE less than required by the minimum channels OPERA 3LE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be used

'to estimate flow.

' ACTION C- .Vith the number-of channels OPERABLE less than required by the-minimum channels OPERABLE requirement, effluent releases via this pathway may contiuue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are c711e ted and' analyzed for gross radioactivity

~

.(beta'or gamma) at a lover limit of dctection no greater than

-1.0E-07 uCi/ml.

Davis-Besse ODCM 23 Revision 5 l

l

Table 2-2

^

RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CllANNEL SOURCE CIIANNEL FUNCTIONAL CHAhNEL CHECK CALIBRATION TEST Ci!ECK INSTRUMENT

1. Gross Beta or Gamma Radioactivity Monitors Providing Alarm and l Automatic Isolation D II) P R I) O(

a. Liquid Radvaste Effluents Line

2. Flow Rate Manitors D('} N.A. R 0

a. Liquid Radvaste Effluent Line

b. Dilution Flow to Collection Box DI ') N.A. R 0 24 Revision 5 Davis-Besse CDCM o ..

- - - m ., _1 o

m . _ _. . . - _ _.__ _ _ .-~..- _ _ __._._ - , . - - - . _ _._ . ._.m_. _ . _ _ . _ _ - . . .

i

' Table _2-2 (continued)

TABLE MnTATION (1)_ During releases via this pathway.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of-this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the alarm / trip setpoint.

(3) The initial CHANNEL CALIBRATION for radioactivity measittement instrumentation shall be perforced using one or more of the_ reference standards certified by the Natienal Institute of Standards and Technnlogy or using standards that have been obtained from suppliers that participate in measurement assurance _ac*ivities vith NIST. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subaequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should he used, at intervals of it least once per eighteca months. For high range monitoring instrumentation, where calibration with a radioactive source is_ impractical, an electronic ,

calibration may be substituted for the radiation Jource calibration' .

(4)- CHANNEL CHECK.shall: consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be inade at least once daily on any day on which. continuous, periodic, or BATCH RELEASES are made.

(D) At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(P) Prior to each release.

(F) At least once per 18 month (550 days).

l(0);-At least'once per 92 days.

Davis-Besse ODCM 25 Revision 5 y -,+-- , ,% ,,,--.,,y- --,,,w ,e- --*- , - - - or,,-, ,r, -

3,--,- - , - -, ---,ys ,, ---r- e w -- T e 't + =e

- . . - . . ~ _

~\

l

.)

l

- Table 2-3 RADI0 ACTIVE LIQUID VASTE SAMPLING A14D ANALYSIS PPocPAM Minimum- Type of Lover Limit Liquid Release _ Type- -Sampling -/.nalysis . Activity of Detection Frequency Frequency- Analysis (LLD) (uCi/ml)" ,

P P Principal A. Batch Vaste d Each Batch Each Batch Gamma g 5.0E-07 b Releate Tanks Emitters I-131 I 1.;c-06 Discolved

~

P One Batch /M M and Entrained 1.0E-05

~

Gases P M Each-Batch Composite' H-3 1.0E-05 Gross Alpha 1.0E-07 P Q C

Each Batch Cosaposite Sr-89, Sr-?0 5.0E-08

~

Fe-55 1.0E-06 B. Turbine Building Principal b-Sump / Storm Continuous S ,' Gamma g 5.0E-07

-Sever-Drain Emitters I-131 I 1.0E-06 P- P Principal b

C. Condensate Each Satch Each Batch Gamma 5.0E-07

_Demineralizer Emitters BLckvash I

I-131 - 1.0E-06

(-

T I

Davis-Basse ODCH 26 Revision 5 t

U e -.< v - w - -

- - , --,m.- .- y ,

l Table 2-3 (continued)

TARI.E finTATinN

a. The LLD is the smallest concentration of radioactive material in a sample t!ct vill be detected with 95% probability with 5% probability of falsely concluding that a blank observation reprc~ents a "real" signal.

For a particular measurement system (vl nu may include radiochemical reparation):

1.LD = 4.66 s b E

V

2.22

Y

exp (-Aot) where

~

LLD is the lover limit of detection as defined above (as pCi per unit mass or volume); .

S is the standard deviation of the background counting rate or of the b

counting rate oi blank sample as appropriate (as counts per minute);

E is the counting efficiency (as counts per transformatit 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);

A is the radioactive decay constant for the particalar radionuclide; at for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

It should be recognized that the LLD is defined as an a griori (before the ,

fact) limit reprerenting the capability of a measuremr - system and not as an a posteriori (after the fact) limit f or a particular n.. .sure nent. ;

+

b Davis-Besse ODCM 27 Revision 5

Table 2-3 (continued)

TABLE NnTATInN

b. The prin'ipal gamma emitters for which the LLD specification vill apply are exclusively the folloving radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mc-99, Cs-134. Cs.137, and Ce-141. For Ce-144, the LLD is 2.0E-06 uC1/ml.

Other peaks which are measured r.nd identified shall also be reported.

Nuclides which ate below the LLD for the analysis should not be reported as being present at the LLD level. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Semiannual Effluent and Vaste Disposal Report.

c. A COMPOSITE SAMPLE is one in which the method of samplir.g employed results is

-nacimen which is representative of the liquids raleased,

d. A BATCH RELEASE is the discharge of liquid vastes of a discrete volume. #

e. When the mcnitor is out of service, a grab sample shall be taken and analyzed once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if the condensate pump discharge exceeds 1.0E-05 pC1/mi gross beta or gamma. ,

f. If an isotopic analysis is unavailable, gross beta or gamma measurement of BATCH RELEASE may be substituted provided the concentration released to the UNRESTRICTED AREA does not exceed 1.0E-07 uCi/ml and a COMPOSITE SAMPLE is analyzed for principal gamma emitters when instrumentation is available,

g. Frequency notation:

P - Prior to each release.

M - At least once per 31 days.

Q - At least once per 92 days.

S - At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (when the monitor is inoperable). [

c Davis-Eesse ODCM 28 Revision 5

l Table '-4 Limiting Radlonuclide Cnneentrations* In Secondary-Side Clean-Up Resins for DischatEes to Onsite Settling Basin Radionuclide LimitingConcen3 ration **

(uct/cm )

Cr-51 3.3E-02 Hn-54 6.2E-05 ,

Fe-59 5.1E-04 Co-58 3.0E-04 Co-60 5.4E-06 ,

Y-91 2.1E-03 Zr-95 4.1E-04 Nb-95 1.0E-03 Mo-99 3.5E-02 >

Ku-103 1.0E-03 Ru-106 1.6E-03 Ag-110m. 1.6E-05 Te-125m 5.4E-05 Te-127m 1.5E-05 Te-129m 6.2E-05 Te-131m- 1.1E-02 Te-132 7.4E-03 I-131 1.1E-04 I-133 3.8E-04 I-135 1.5E-03 Cs-134 1.1E-05 Cs-136 2.6E-03 Cs-137 1.0E-05 Ba-140 1.1E-02 La-140 7.4E-03 Ce-141 5.8E-03 Cs-144 4.1E-05 Pr-143 1.9E-02

_ Concentration limits based un the study, Disposal of Lov-Level Radioactively Contaminated Secondary-Side Clean-up Resins in-the on-site settling Basins at-the Davis-Besse Nuclear Power Station, J. Stewart-Bland, May 1983. The

'imits represent a hypothetical maximum individual' dose of lesa than 1 mrem per year due to an inadvertent release to the offsite environment. The allovable release limits as presented in Table 2 of the above reference

. report have been_ reduced by a factor of.10 for added conservatism representing a hypothetical dose of less tnaq 0.1 mres.

- Eith more'than one radionuclide identified in a resin .atch, the evaluatior for acceptable discharge to the onsite settling 'oasin shall be based on the

" sum of the fractions" rule as follows: Determine for each identified radionuclide the ratio between the measured concentration and tF limiting ~

concentration; the sum of these ratios for all radionuclides should be less than one (1) for4 discharge to the basin.

Davis-Besse ODCM 29 Revision 5 l-L 9 m -

Table 2 Radionuclide Activity Limits for the BVST and PVST V

Radionuclide Total Activity (C1)

H-3 2.12E+03 Cr-51 2.88E+02

-Hn-54 1.41E+01 Fe-59 1.07E+01 Co-57 1.26E+02 Co-58 1.18E401 Co-60 5.14E+00 Zn-65 2.16E+01 Rb-88 1.04E+02 Sr-89 2.12E+00 St-90 2.12E-01 Sr-91 1.73E+01 Sr-92 9.72E+00 Y-91 2.12E+01 Y-93 2.12E+01 Zr-95 4.23E+01 Zr-97 1.41E+01

, Nb-95 4.31E+00 Nb-97 1.63E+01 Ho-99 2.82E+01 Tc-99m 1.01E+02 Ru-103. 2.16E+01 Ru-105 7.06E+00 Ag-110m 4.31E+00 Sn-113 5.64E+01 Sb-125 2.47E+01 I-131 2.12E-01 I-132 5.00E+00 I-133 7.05E-01 I-134 4.53E+00 I-135 2.82E+00

-Cs-134 6.35E+00 Cs-136 5.44E+00' Cs-137 1.41S+01 Cs-138 2.73E+01 Ba-139 1.43E+03 Ba-140 1.41E+01 La-140 5.38E+00 Ce-141 6.37E+01 Ce-144 7.05E+00 Davis-Besse ODCH 30 Revision 5

Tabis 2-6:

Davis-Basse Site-speeic Liquid Ing2stion Dosa comitment factors, A g (mre Whr per vCi/al)-

Nuclide Bone . Liver ....

......., T.Bo #... Thyroid Eldney Lun ' Cl Lt!-

...... . ..,.... ....... ........ ... 8... ....... i m3 0.00E*0 1.7M+0 1.7M+0 1.7M+0 1.7M+0 1.7M +0 1.7M+0 bl4 - 3.15E+4 '6.7M *3 6.2M +3 6.2M *3 6.2M*3 6.2M+3 4.2M *3

-i

. We 64 4.32E*2. 4.32E+2 4.32E*2 4.3M+2 4.32E

2 4.32E+2 4.32E*2 l I

P 32 ' 1.39E*6 8.64E+4.5.37E+4 0.00E+0 0.00E+0 0.00E+0 1.5M+5 .

- Cr 51 0.00E+0 0.00E+0 1.31E+0 - 7.85E 1 2.09E 1 1. F '.E + 0 3.30E

2 i Mn 54 0.00E+0 4.44E+3 8.48E+2' O.00E+0 1.3N+3 0.00E+0 1.3M +4 -

Mn 56 0.00E+0 1.12E*2 1.98E+1 0.00E+0 1.42E+2 0.00E+0 3.57E*3 Fe 55 6.9?E*2 4.83E*2 1.1M

2 0.00E+0 : 0.00E+0 2.69E*2 2.77E

2 I

f e 59 -1.10E+3 2.5M*3. 9.9M*2 0.00E+0 0.00E+0 7.24E+2 8.ME

3 Co 57. -0.00E*0 2.35E+1-3.91E+1 0.00E+0 0.00E+0 0.00E*0 5.9M*2

~

Co 56 - 0.0X+0 1.00E+2 2.24E+2. 0.00E+0 0.00E*0 0.00E+0 2.03E+3

, Co-60 0.00E+0 2.87E*2. 6.34t+2 0.00E+0 0.00E+0 0.00E+0 5.40E+3 bl 63 3.30E+4 2.29E+3 1.11E+3 0.00E+0 0.00E+0 0.00E+0 4.78t+2 C kt 65- h34t*2-1.74E+1-7.95E+0 0.00E+0 0.00E+0 0.00E+0 4.42E*2 Cu-64' O 00E+0 1.12E+1 5.25E+0 0.00E+0 2.82E+1 0.00E+0 9.54E+2 2n 65 2.32E+4- 7.40E+4 3.34E+4 0.00E+0 4.95E+4 0.00E+0 4.6M +4

In-69 4.95E+1 9.46E+1 6.5M+0 0.00E*0 6.15E+1 0.00E+0 .1.42E+1 er 82- 0.00E+0. 0.00E+0 2.60E+2 ' O.00E+0 0.00E+0 -0.00E+0 2.98E*2 Br 83- 0.00E+0-0.00E+0 4.10E+1 0.00E;0 0.00E+0 0.00E*0 5.91E+1 Br 84 ~ 0.00E+0 0.00E+0 .5.31E+1 0.00E+0 0.00r+0 0.00E+0 4.1M 4 er 85 0.00E*0 0.00E+0 2.18E+0 0.00E+0 0.00E+0 0.00E+0 P.00E+0 Rb 86 0.00E+0 1.01E+5 4.72E+4 0.00E+0 0.00E+0 0.00E*0 2.00E+4 ab-88' O.00E+0 2.91E+2 1.54E+2 0.00E+0 0.00E+0 0.00E+0 4.01E 9

. th 89 0.00E+0 '1,9M+2 1.35E+2 0.00E+0 0.00E+0 0.00E+0 1.12E 11 sr 89' 2.66E*4 - 0.00E+0 7.64E+2 0.00E+0 0.00E+0 0.00E+0 4.27t+3 sr 90- 6.55E*5 0.00E+0-1.61E+5 0.00E+0 0.00E+0 0.00E*0 1.89E*4 tr-91 4.90E+2 0.00E+0'9.98E+1 0.00E+0 0.00E+0 0.00E+0 . 2.3M*3 n tr 92 1.8M+2 0.00E+0 8.04E+0 0.00E+0 0.00E+0 0.00E+0 3.68E+3

Y 90 7.1M i 0.00E+0 1.92E 2-- 0.00E+0 0.00E+0 0.00E*0 7.5M+3 Y.91m 6.77E 3 0.00E+0 2.62E 4 0.00E+0 0.00E+0 0.00E+0 1.99E 2 T 91 -1.05E+1--0.00E+0 2.81E 1 0.00E+0 0.00E+0-0.00E+0 5.78E+3 1.10E +3 t

' Y.92- 6.29E 2 0.00D0 1.64E 3 0.00E+0 0.00E+0 0.00E +0 Y 93 2.00E 1 l'.00E+0 5.51E 3 0.00E+0 0.00E+0 0.00E+0 6.3M +3 2r-95 6.84E 1 2.19E 1 1.49E 1 0.00E+0 3.44E 1 0.00E+0 6.95E+2

< tr 97 3.78E-2 7.6M 3 3.49E 3 0.00E+0 1.15E 2' O.00E+0 2.3M+3 bb 95 " 4.47E*2^2.49E*2 1.34E+2 0.00E+0 2.44E+2 0.00E+0 1.51E+4 ab-97 3.75E+0 9.48E 1 3.4M 1 :- 0.00E+0.1.11E+0 0.00E+0 3.50E+3 Mo 99 0.00E+0 1.6M+2 3.1M+1 0.00E+0 3.7R*2 0.00E+0 3.BM*2 te 99m- ~1 .25E 2 3.5M 2 4.49E 1 0.00E+0 5.35E 1 1.73E 2- 2.09E+1 Tc 101 1.28E 2 1.85t*2 1.81E-1 0.00E*0 3.33E 1 9.45E 3 5.5M 14 au-103 7.1M +0 0.00E+0 3.07E+0 0.00E+0 2.72E+1 0.00E+0 8.32E+2 Davis-Besse 00CM- 31 Revision 5 p

u A--p- r+ _ - w e * - *_r-

+-- _ _ - + e awi- T . *F

.. .- , . - - - - - .. .- . ~ - - . .. -~ ~ - - - -

[ -Table 2-6 (continued)

D2Vis-Bassa Site-Specific Liquid Ingestion Dose Comitmer.t- ractor 8, A,*

7

.(nreNhr per vCi/ml)'

Wucilde- Bane Liver T . ted/.: Thyrold E fibry Lwg El LLI .

. . . . . . + - ....... ....... -..... ....... ....... ....... .......

8u 105 5.94t 1 0.00t+0- 2.34t 1- 0.00t+0 7.67t+0 0.00t+0 3.63t*2 su 106 1.0M

2 0.00E+0 1.34t+1 0.00(+0 P.05t+2 0.00(+0 6.8M *3 Rh 103e 0.00t+0'0.00t+0 0.00t+0 0.00t+0 0.00t+0 0.00E+0 0.00t+0 th 106 -0.00(+0 0.00t*0- 0.00t+0 0.00t+0 0.0M+0 0.00t+0 0.00t+0

-As tion . .at + 0 2.98t*0 1.77t+0 0.0M + 0 5.85t d 0.00E+0 1.21t+3 sb 124 . 4.7M+ 1 8.99t 1 1.89E*1 1.15t 1 0.00t+0 3.70E+1 1.35t+3 sb 125 3.04t+1 3.40E 1 7.+4t+0 3.09E 2 0.00t+0 2.35E+1 3.35E+2 fe 125m 2.61t+3 9.44t+2 3.49t+2 7.84t+2 1.0M +4 0.00t+0 1.04t+4 fe 127e 6.58t+3 2.35t+3 8.02t*2:1.68t+3 2.67t+4 0.00E+0 2.21t+4 Te 127- 1.07t+2- 3.84t+1 2.31E+1 7.92t+1 4.36t+2 0.00t+0 8.44t+3 fe 129m 1.12t+4 4.17t+3 1.T7t+3 3.84t+3 4.67t+4 0.00t+0 5.6M+4 -

f e 129 - 3.05t+1 1.15t+1 7.44E+0 2.34t*1 1.28t*2 0.00t+0 2.3M *1 Te 131e 1.6M +3 8.22t+2 6.85E+2' 1.30t+3 8.33t+3 0.00t+0 8.17t+4 Te 131 1.92t+1 8.00t+0 6.05E+0. 1.57t*1 8.39E*1 0.00E+0 2.71t*0 fe 132 2.45t*3 1.58t+3 1.49t*3 1.75E+3 1.53t+4 0.00t+0 7.50E*4 11 130 3.82E+1- 1.13t+2 4.44E+1 9.55t+3 1.76t*2 0.00E+0 9.70t+1 1 131 2.1M +1 3.01t+2 1.72t+2 ~9.85t+4 5.15E+2 0.00E+0 7.93E+1 1 132 1.03t+1 2.74t+ 1 9.60t+0 9.60E*2 4.37t+1 0.00E*0 5.15t+0 1 133 7.17t+1 1.25t+2 3.80t+1 1.83E+4 2.18t+2 0.00E+0 1.12t+2

-1 134 5.35t*0 1.45E+1 5.2M+0 2.52t+2 2.31t*1 0.00E+0 1.27t 2 1 135. 2.24E+1 5.8M+1 ' 2.1M+1 3.8M+3 9.39t+1 0.00t+0 6.62t+1 Cs 134 '2.99t+5 7.11t+5 5.81t+5 0.00t+0 2.30t+5 7.64E+4 1.24t+4 ,

ts 136 - 3.1M*4 1.2M+5 8.8M +4 0.00t+0 6.87t+4 9.41E+3 1.40E+4 Cs 137 3.83E+5 5.2M+5 3.4M*5 0.00t+0 1.78'+5 5.91t+4-1.01t+4

- Cs 134 - 2.65t*2 5.23t*2 2.5 M*2 0.00E+0' 3.85t+2 3.80t+1. 2.23t 3 Sa 139 2.35t*0 1.67t 3 6,8M 2 0.00E+0 -.1.5M 3 9.48E 4 4.1M +0 8eE140 4.91E*2 6.1M 1 3.22t+1 - 0.00E+0 2.10E 1 3.53t 1 1.01E*3 ta 14' 1.14t+0 .8.61t 4 3.84t 2 0.00E+0 8.00E 4 4.88E 4 5.37E 10 Sa-142 5.15E 1 5.29E 4 3.24E 2 0.00t+0 4.47t 4 3.00E 4 7.25t 19 La 140 1.86t 1 9.38t 2 2.48t 2 0.00E+0 0.00t+0 0.00t+0 6.89t+3 La 142 9.53t 3- 4.33E 3 1.08t 3 0.00E+0 0.00t+0 : 0.00E+0 3.1M+1 Ce 141 1.59t*1 1.0M 1-1.22t 2 0.00t+0 5.00E 2 0.00E+0 4.11t+2 Ce 143 2.80E 2 2.07t+1 2.29t 3. 0.00t+0 9 *3t 3 0.00E+0 7.75t+2 Co 144 8.29t*0 3.67t+0 - 4.45E 1 0.00t+0 2.0M+0 0.00E+0 2.80E+3 Pr 143 6.85E 1- 2.75E 1 .3.39E 2 0.00E+0 1.59t 1 0.00t+0 3.0M*3 Pr 144 2.24t 3 9.318 4 1.14t 4 0.00(+0 5.25t 4 0.00t+0 3.221 10 I ud 147 '4.68t 1 5.41E 1 3.26t 2 0.00E+0 3.1 M 1 0.00t+0 2.60t+3 W-187 - ~ 2.97t*2 2.49t+2 8.69t+1 0.00t+0 0.00E+0 0.00t+0 8.14t+4 Np-239 4.59t 2 4.51E 3 2.49t 3 0.00t+0 1.41E 2 0.00t+0 9.25t*2 Davis-Besse ODCM 32 Revision 5 a . - - . -- .

c. . . . ~. . - . . - - .- - .-- -~~ . . . . - . -

,A 4 Table 2-7

Bioacenmulation. Factors'(BFi)

(pC1/kg per'pCl/ liter)*-

Element Freshvater Fish H 9.0E-01 C 4.6E+03

/ Na 1.0E+02

"-/D i P- 3.0E+03 ?

Cr 2.0E+02 Hn 4.0E+02 Fe 1.0E+02 Co 5.0E+01 Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E+03 Br- 4.2E+02 Rb 2.0E+03

-Sr 3.0E+01 ,

Y 2.5E+01 Zr 3.3E+00 Nb' 3.0E+04 Mo 1.0E+01 Tc 1.5E+01 Ru 1.0E+01 Rh 1.0E+01 Ag 2.3E+00 Sb 1.0E+00 Te 4.0E+02 I 1.5E+01 Cs 2.0E+03

-Ba 4.0E+00

.La -2.5E+01 Ce 1.0E+00-Pr 2.5E+01 Nd 2.5E+01 V '1.2E+03- -

ii" Np 1.0E+01

. *= Values in this Table are taken from Regulatory Guide 1.109 except for phosphorus 1which is_ adapted from NUREG/CR-1336 and silver and antimony which are taken from UCRL 50564 Rev. 1,.0ctober 1972.

t Davis-Besse ODCM 33 Revision 5

Figure 2-l' _[

Liquid Radioactive Effluent Monitoring and Processing Diagram LEGEND e ....

1... e ::ua:-

DAVIS-BESSE NPS 7 '"'

LIDUID RADI0 ACTIVE a . . ." *?.'." * . b-1 RELEASE PATHWAYS cowintumeur M itt'.*"

0434 BUILDIMO f %

'A' '

TURB1MC

, . [ - ^

SUILDING AUX. SUILOIHC NN! "'

RADWASTE AREA e432 g

-*G *

p CwMt DwCT wwuf SgR h

g r ti satte v 2"'

,g, ....

9..... 8,

.e...

2518,8 A&G8 '

' SOUTH

, TRAININS CENTER SASIN

.t it i TO

.PONO

......N. .....

9,,,,,,,,

COLLECTIOH ",

som i

i-i-

ossCwanat TO LAKE Davis-Besse ODCM 34 Revision 5.1

e This page is intentionally blank.

b-I

3.0 CASEOUS EFFLUENTS 3.1 RADI ATION MONITORING INSTRUME!TTATION AND CONTROLS This Secticn specifies the gaseous effluent monitoring instrumentation required at Davis-Besse for controlling and monitoring radioactive effluents. Locationandcontrolfunctionofthesemonitorsaredisplayedinh~_y Figure 3-1. More information is provided in the Davis-Besse USAR, Section 11.3, Gaseous Vaste System.

The radioactive gaseous effluent monitoring instrumentation channels shovn in Table 3-1 shall be OPEP.ABLE vith their alarm / trip setpoints set to ensure that the limits of Section 3.3 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordante with the methodology and parameters in Section 3.3.

Vith a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required, without delay suspend ~

the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conseivative.

Vith less than the minimum number of radioactive gaseous effluent monitoring i istrumentation channels OPERABLE, take the actions shown in Table 3-1.

n..e r t best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Effluent and Vaste Disposal Report (Section 7.2) why the inoperability was not corrected in a timely manner.

Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 3-2. Esch of these operations shall be performed within the specified time interval with a maximum allovable extension not to exceed 25 percent of the specified interval.

NOTE: The monitors specified in Table 3-2 are inoperable if surveillances are not performed or setpoints are less conservative than ~

required.

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. The alarm / trip setpoints for these instruments shall be calculated in accordance with methods in Section 3.3 to ensure that the alarm / trip vill occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFP Part 50.

Davis-Besse ODCM 35 Revision 5.1

3 3.1.1 Alarm end Automatic Ralcasa Termination a) Vaste Gas Decay System Honitor (RE-1622-A&B)

The radioactive vaste gas discharge line is continuously monitored by two off-line detectors, each measuring-gross activity. The monitors' control

-function vill terminate the vaste discharge prior to exceeding the release rate limits of Section 3.3.1. Table 3-1 requires that the Vaste Gas Decay System contain as a minimum the following instrumentatic1:

- i.oble gas activity monitor (RE-1822 A or B), and effleent system flov rate measuring device (PT-1821 or 1821 A).

If both noble gas monitors are declared inoperable, then the contents of the tank may be released provided that prior to the release: lC-1

- at least two independent gas samples are collected and analyzed by gamma spectroscopy for principal gamma emitters (noble gases).

- at least'tvo independent verifications of the release rate calculations are performed, and

- at least two independent verifications of the discharge valve line-up are performed.

If the flow rate device is inoperable, efiluent releases may continue provided that the flow rate is astimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Fle" ,

rates may be estimated based on fan curves or discharge valve header '

positicning, b) Containment Purge Exhaust Filter Monitor (RE-5052 A.B&C)

This detector monitors the containment atmosphere for radioactivity during Contairment VENT or PURGE. The noble gas activity monitor (Channel C) is required by Table 3-1. It provides an automatic termination of the release prior to exceeding the release rate limits of Section 3.3.1. Although not required in order to comply with Table 3.1, Channels A and B provide indications if increasing levels of particulate and radioiodine releases and terminate the release if their high alarm setpoint is exceeded. C-1 ,

3.1.2 Alarm Only i 1.

~

a) Station Vent Monitor (RE-4598 AA. BA)

The Station Vent is designed as the final release point for all gaseous radioactive effluents. Three separate channels (1, 2, and 3) are provided for each monitoring system. Channel 1 is a beta scintillation detector vieving a fixed air volume measuring for noble gases. Channel 2 is a beta scintillation detector viewing a fixed particulate filter sampler. Channel

-3 is a gamma scintillation-detector vieving a fixed cartridge sampler (e.g.,

charcoal or Ag zeolite). Only the Channel 1 radiation detector is required C-1 by Table 3.1.

l-Davis-Besse ODCH 36 Revision 5.1 i

l

The Chennal 2 cnd Ch nnal 3 datsetors provida infortation on potentici j

particulate and radioiodine releases. However, those monitors experience vide variations in response due, in part, to the much more abundant noble gases in the effluent stream relative to the particulate or radioiodines being sampled. Therefore, while Channels 2 and 3 provide useful information for identifying particulate and radioiodine releases, they are not required by Table 3.1 for quantifying the release rate. Refer to Section 3.5. C-1 cs The following sampling / monitoring instrumentation on the Station Vent is required by Table 3-1:

- noble gas activity monitor (Channel 1),

- particulate sampler filter (Channel 2),

- iodine sampler cartridge (Channel 3),

- sampler flow rate measuring device, and -

- unit vent flov rate measuring device (computer point; F883 or F885).

The hydrogen purge line serves as a Containment pressure relief route to the Station Vent. A separate radiation monitor on this lins is not required. Any release through the hydrogen purge line vill be monitored by the Station Vent monitor, RE-4598.

b) Vaste Gas System Oxygen Monitors (AE 5984 and 6570) ,

The Vaste Gas System is provided with two oxygen monitors (with an alarm function) as required by Table 3-1 to alert operators in the unlikely event of oxygen leakage into the vaste gas header. The concentration of oxygen is limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume. An oxygen concentration above the specified limit vill actuate a local and control room alarm.

Davis-Besse ODCM 37 Revision 5.1

l O

This page is intentionally blank.

_ ... _ _ _ _ _ _ _ _ _ _ _ _ .- _ ~ . . _ _ _ _ _ . _ . _ _ _

3.2 SAMPLING AND ANALYSIS OF GASEOUS EFFLUEttfS .

I Radioaetave gaseous vastes shall be sampled and analyzed in accordance vith Table 3-3. This sampling and anals is ensures that the dose rates and doses !

from gaseous effluents remain belov the release rate limits of Section ,

3.3.1, and the dose limits o' Sections 3.7.1 and 3.8.1.

l I

3.2.1 Batch Releases t

Table 3-3 requites that a grab gas sample be collected and analyzed prior to ear.h BATCH RELEASE from the Va$te Gas Decay Tanks (VGDT) or a Containment PUkGE. The analysis shall include the identification of all principal gamma [

esittets (nohis gas) and tritium. Although not required by Table 3-3, L Containment Pressure releases, Integrated Leak Rate Tests of Containment, !

and other tank venting operations are batch releast s .rd shall be sampled similarly.

The results of the sample analysis are used to establish the acceptable ,

release rate in accordance with Section 3.3.4. This evaluation is necessary to ensure compliance with the limits of Section 3.3.1. 1 3.2.2 continuous Release All releasc-s from the Station Vent are-required c.c be continuously sampled >

for radioactivity. As specified in Table 3-3. the following minimum samples l

and analyses are requc.eds once per week, analysis of an absorption media (e.g., charcoal i

, cartridge) for 1 131,

- once per veek, analysis of a filter sample for all principal gamma emitters (particulate radioactive material),

. once per month, analysis of a grab gas sample for all principal gamma emitters (noble gas) and tritium, '

- once per month, analysis of a composite of the particulate samples ?

of all releases for that month for gross alpha activity.

once per quarter, analysis of a composite of the particulate samples for all releases for that quarter for Sr-89 and 90, and

- continuous monitoring for noble gases (gross beta and gamma activity).

L i

l l

l_

I i

l

~

l l

Davis-Gesse ODCM 38 Revision 5

- . - - - . . . - . - _ . - - - _ . - . . - . - . . - . - . .- - - ..- _ . - - . . . . . . . -_.~

.___._._m______m_____

l l

3.2.3 Peleases Pesulting from Primary-to-Secondary System 1.cakage ,

Should the secondary coolant system become contaminated. then there are several additional gaseous release points to considers The Atmospheric Vent Valves (AVVs). l Main Steam System Relief Valves (HSSVs).

- Auxiliary Feed Pump Turbines (AFPTs), and

- Auxiliary Steam System Relief Valves.

Since these releases of radioactivity are not controlled on a batch basis, they should be considered continuous releases unless they are unplanned and uncontrolled in which case they are abnormal releases.

ateam may be released via any of these points due to improper -11ve seating.

Steam may be released via the MSSVs and AVVs if the plant trips, or via ti.e

,.VVs during a condenser outage. Steam is released through the AFPts during their operation. Steam may be released due to overpressurization of the Auxiliary Steam System via the relief val es on the various steam headers.

For secondary coolant system telease pathways, the following minimum samples and analyses are required:

- once per veek, analysis of a secondary system oit-gas sample for principal gamma emitters (noble gases) and tritium

- once per veek, analysis of a secondary system liquid sample for principal gamma emitters (lodines and particulates);

- once per quarter, analysis of a composite of secondary system liquid samples for strontium-89 and strontium-90.

Auxiliary Steam is obtained from Main Steam during normal opetations, and from the Auxiliary Boiler during Modes 5 and 6. For Auxiliary Steam System Relief lifts that occur when the Auxillery Boiler is the source of Auxiliary Steam, analyze liquid samples from the Auxiliary Boiler for gamma emitters and tritium.

If only one steam generator has a primary-to-secondary leak then radionuclides other than tritium are released through the valves on the leaking steam generator's main steam line. Demineralizing and gas stripping remove some radionuclides from the condensate prior to its return to the steam generator as feedvater. However, these processes do not remove tritium, i

1 l

! Davis-Besse ODCH 39 Rsvision 5 I

t

- -.. ..--.- -. . . . ~ . - - - - - - - - - . . _ - . - - . - - . .

, i 3.3 CASEOUS EFFLUENT MONITOR SrMPOINT DETERMINATION 1 3.1 Release Rate Limits All relesses of gaseous radioactive effluents are designed to occur via the Station Vent. Alarm setpoints shall be established for the Station Vent gaseous effluent monitoring instrumentation to ensure that the releast rato of effluents d;as not exceen the following limits.

The dose rate due to redicactive materials released in gaseous efficents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the followings

- for noble gast less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the skin, and

- iodine-131, tritium and all radionuclides in particulate form with '

half-lives greater than 8 dayst less than or egual to 1500 mrem / year to any organ. (Compliance with the 1500 mrem /yr dose rate limit is demonstrated by the method in Section 3.5.)

l C

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

This requirement is provided to ensure that th? dose at the SITE BOUNDARY from gaseous effluents from all units on the site vill 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 effluents vill not result in the exposure of a MEMBER OF THE PUBLIC outside the SITE BOUNDARY to annual average concentrations exceeding the limits specified in Appendix B. Table II of 10 CFR Part 20 (10 CFR Part 20.106(a)). For MEMBERS OF THE PUBLIC who may at times be within-the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC vill be suf ficiently lov to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDAPY. The specified release limits restrict the corresponding gamma and beta doses above backgrornd to an individual at-or beyond the UNRESTRICTED AREA boundcry to (L'O mrem / year to the total body or to <3000 mrem / year to the skin. These release limits also resttict, at all times, the corresponding

~

thyroid doses above background to a child via the inhalation pathway to

$1500 mrem / year.

Davis-Besse ODCM 40 Revision 5.1

. - - . - . . _ _ ._ . _ , . . _ . - - . . _ . - ._ _~._ __. __ . -_ _ _

3.3r2 individunt Palense Radiation Mnnitor satpoints

.Although. generic radiation monitor setpoints are normally used at Davis-Besse (seo Section 3.3.3), setpotnts may be established from a sample analysis of the applicable source (i.e., Station Vent, Vast _e Gas Decay Tanks, or Containment atmosphere), and the following equations: l EC 3* 500 )

SP TB

(3*I) l 472

x/Q gg *W* Eg*K) g IC 3

3000 -

SP S

- (3~2) -

t(c3 *(Lg

1.1 M )

412 + x/o *,,gvr

1 wheres (

)

SPTD . monitor setpoint corresponding to the release rate limit for the total body dose rate of 500 mrem per year (pCi/ml).

SP 3

= monitor setpoint corresponding to the release rate limit for the skin dose rate of 3000 mrem per year (ucl/ml).

500 -- total body dose rate limit (mrem /yr),

3000 .' skin dose rate limit (mrem /yr),

X/0gg.atmosphericX/0valuefordirectexposu$etonoblegasat the SITE BOUNDARY given in Table 3-6 (sec/m ),

VF- .ventilationsys3emflowrate-forthe.applicablereleasepoint and monitor (ft / minute),

Cg = concentratic,n of noble gas radionuclide / as determined by gamma -

spectral analysis of grab sample (uci/ml), t

-K g .-total-bod t ose d conversion f actor for radionuclide i-(mrem /vr per 4C1/m3 from Table 3-5, L k 3 = UC1/m beta' 3)in dose from conversion Table 3-5, f actor for radionuclide f (mrem /yr per

- gamma alt dose conversion f actor for radionuclide I (mrad /yr per Hg pCi/m 3 ) from Table 3-5

( .

-1,1 = mrem skin dose per mrad gamma air dose (mrem / mrad), and

'412 28,317 (ml/ft3)

1/60 (min /sec). ;

l. >

The lesser value of SP TB # SI is used t S

sta m sh the monh or setpoint. ]

i

.- Davis-Besse' ODLH - a1- -Revision 5 f

. i~. -~a . . . - - . . _ _ _ . = . . . - - . _ . -. . _ _ . . . . - . . - . . . - _ . _ - - - - -

The Station Vent monitor (RC 4598) elficiencies and read outs are in~pC1/mli hovever, the containment Purge Exhaust Monitor (RE. 5052) and the VGDT monitor (RE-1822) cf ficiencies and read outs are in counts per minute.

Therefore, for RE-5052 and RE-1822, the setpoints in UCi/ml must be corrected to an equivalent monitor counts per minute. The monitor calibtation curves are used for determining specific radionuclide l efficies.cles (com per pCi/ml).

Normally, the monitor efficiency fot Xe-133 is used in lieu of the l efficiency values for the individual radionuclides. Because its lover gamma l energy causes a higher monitor tesponse, tho Xe-133 elficiency provides a conservative value for alarm setpoint determination, t

3.3.3 Conseivative, Generic Radiation Monitor Setpoints Normally, generic alarm setpoints are established instead of those determined by individual radionuclide analysis. This approach eliminates the need to adjust the setpoint periodically to reflect minor changes in radionuclide distribution or telease flov rate. The alarm setpoint may be conservatively determined by assuming all activity released is Kr-89. The K:-89 total body dose conversion factor is the most limiting. Therefore, the mote restrictive setpoint is based on the total body dose rate limit and may be calculated using equation (3-1). Again, the Xe-133 monitor <

efficiency is used for conservatism. The alarm setpoints are controlled g for RC-4598, RE-5052, and RE-1822 in accordance with the Radiation Monitor Setpoint Manual.

3.3.4 Release Flov Rate Evaluation for Batch Releases To comply with the release rate limits of Section 3.3.1. each batch release r, hall be evaluated fo: maximum telease flov rate prior to being released.

Based on noble gas concentration, and the radiciodine, particulate, and tritium concentration in the sample as collected in accordance with Table 3-3, the allovable release rate is determined based on equations (3-3).

(3-4) and (3-5). The smallest value of RRtb, RR, or RRygg is used as the maximum allavable telease flow rate. ,

To determine RR organineverykggge group exactly, (28a values separate RRINH)must of RR . Thebesmallest calculatedof these for every 23 is the RR vhich is compared to RR ardNNR to determine maximum allovable$leaserate. AconservatNeshortEutistocalculateRR ygg once by using the largest inhalation dose factor (R from Table 3 7) for any organofanyagegroupforeachnuclidereleasb{l. The largest dose factors in the inhalation pathway are usually for the teen lung, ,

500 RR = (3-3) 472*xiOg !(1: g + CNG3) 3000 RR = (3-4)

D2

X/0 gg* E((h + 1.1 Mg)

CNGg) 1500 RR (3-5) 7933 = U2 , x,Q . g gg

\- .

9

c1NH{}

DF yp ,

Davis-Besse ODCM 42 Revision 5

+ . , , , - ,ww,-r.v, e-.-..,-.m - ,-.- v,,,-..r,r r---,

l l

vhere RR II ** as not to exceed a total body tb * " dose rate of-500 miem/yr (ft*I'aa'II""''30 / minute), l RR . . te so as not to exceed a skin dose s allovable release cate of 3000 mremflow rg/ minute),

/yr (ft RR as not to exceed an inhalation INH =allvablereleaseflowratesg/a.n),

dose rate of 1500 mrem /yr (ft 500 a total body dose rate limit at the SITE BOUNDARY (mrem /yr).

3000 . skin dose rate limit at the SITE BOUNDARY (mrem /yr), i 1

1500 . inhalation dose rate limit at the SITE BOUNDARY (mt em/yr), i

-472 28317 (ml/ft )* 1/60 (min /sec),

, X/0 gg = atmospheric X/Q givenvalueinfor direct a bl* 888 at th' )

SITE BOUNDARY Tablo 34 exposu5'),t (sec/m i

-X/0ggg = atmospheric X/0 valge for inhalation at the SITE BOUNDARY given in Table 3-6 (sec/m-),

Kg i

. total body) dose per uC1/m fromconversion Table 3-5, f actor for radionuclide I (mrem /yr ,

L 3

= beta skin dose conversion f actor for radionuclide i (mrem /yr- per uCi/m') from Table 3-5, H- g

= gamma 3 air dose conversion f actor for radionuclide I (mrad /yr per pCi/m )-from Table 3.5, l~ R, 3

- dose f actor for radionuclide i tf), organ o of age group a given in Table 3-7 (mrem /yr per uCi/m

-CNGg . concentration of-noble-gas radionuclide i analyzed in grab samples, CINilg = concentration of tritium, radiciodine, or particulate radionuclide i analyzed in grab samples, and ji y'

i DFyp . removal factor of 100 to be used for radiciodines and particulates when the effluent is processed through an absolute filter.(do ny use for tritium). .

h The actual release rate may be set lover than the maximum allovable release L rate:to provide an additional. assurance'that the release rate limits of Section 3.3.1 are not exceeded.

L p-l

, _ _ _ _ . - - . - . - _ , . . . _ . ~ _ _ . - _ - _ _ - - - - _ . _ . _ _ . . _ _ _ . - - _ . . _ . _ . , , _ . _ _ , ~ . _ . _ -._._;._ ,

0 3.4 SITE BOUNDARY DOSE RATE CALCULAT10tl - NOBLE GAS If an effluent noble gas monitor exceeds the alarm serpoint, t in evaluation of compliance with the release rate limits of Section . 3.1 must be performed using actual release conditions. This evaluatior requires collecting a sample.of the effluent to establish actual radionuclide concentrations and monitnr tesponse. .

The following equations may be used for evaluating compliance with the release rate limit of Section 3.3.1 for noble gases: ,

tb - 472

X/0 gg

VT

I(K g b *C) g (3 6) b, - 472

X/0 gg

VI' * -I((Lg + 1.1 Mg )

Cg ) (3-7) vheres ;

btb . total body dose rate (mrem /yr),

b, . skin dose rate (mrem /yr),

X/0g", - atmospheric X/0 for direct exposure to oble gases at the-SITE BOUNDARY given in Table 3-6 (sec/m ),

l 3

VT = ventilation system flow rate (ft / min), l ,

C 3

- concentration of radioneclide s as measured in the sample (uci/ml).

Kg - total body dose conversion f actor for nome gas ,

radionuclide-i (mrem /yr per uC1/m)) f rom l Table 3-5, Lg -

beta

((mremskin/yrdo.=e per pC1/m convef)sion from Tablefactor 3-5, for noble gas radionuclide Hg =

gamma radionuclideair -( dose' (mradconversion

/yr per uCi/m ' factor fromf)or Table noble 3-5,gas ,

1.1 = mrem skin dose per mrad gamma air doso (mrem / mrad), and 472 .-28,317 (ml/ft )

1/60 (min /sec).

l.

I l

l I

l .

Davis-Besse ODCM- 44 Revision 5

=*.r.+-.w,., - -.s',eeb w- e,e,-~-o.mm -m4=r-* m -e,e n- v y, r e w- :r ,-- m ir- e-%rw --ev.ww ,r

_ . - . _ .. _ _ _ . , _...____. ._ . . . ._.-- - . _ . . _ _ . . _ . . . . ~ . _ _ . . _ _ _ _ , _ _ _ . _ - - _ .._

t t

b This page is intentionally blank.

I l

l l .s-t-

l l -_

i

[',

6

-- --.,-..~.---a,e,.. u - . . . . - , . . . . -e.- .am...%___,, , , - . ...m, - ,.<n_m..--_.y ;, r - , rw - .,,ww,,,--- r.--r-wc.wr-- n.-,,,,.--m ,.- v.>,

- _ . - _ - - -- . _ _ . --. . - - - .-- - __.. - ~- - - - . , . - ~ , .

3.S SITE BOUNDARY DOSE RATE CALCULATION - RAD 10 IODINE, TitITIUM. AND PARTICULATES l 3.5.1 Dose Rate Calculation Section 3.3.1 limits the dose rate to $1500 mrem /yr to any ntgan for gneanus I releases of I-131 tritium and all particulates with half-lives greater than 8 days. To demonsteite compliance with this limit, an evaluation is performed in accordance with Table 3-3 (nominally once per 7 days). The !

following equation may be used for the dose rate evaluations j D, . X/0 INH

10 i) (3~0) l vheret Dg . dose rate to organ o over the sampling time period (mrem /yr)

X/0 7pg -

atmospheric X/0 valge for inhalation at the SITE BOUNDARY given l in Table 3-6 (sec/m ),

R .

dose f actor to organ o from radionuclide i fot thecontrylling l i 39 age group via the inhalation pathvay (mrem /yr per pC1/m ) from Table 3-7, and Og . average release rate over the appropriate sampling period and analysis f requency f or radionuclide i (uci/sec).

. 3.3 7 Simplified Dose Rate Evaluation for Radioiodine, Tritium and Particulates l It is conservative to evaluate dose rates by applying the I-131 dose factor to the collective releases for all measured radionuclides. By substituting 1500 mrem /yr for. the dose rate to organ o in Equation (3-8) and solving for ,

0 , an allovable release rate can be determined. Based on the annual 3

average reteorological dispersion (see Table 3-6) and the I-131 dose factor for the'most limiting potential pathway, age group)and organ (inhalation, child, thyroid -- R gg 1.62E407 mrem /yr per uCi/m ), the allovable release rate is 44.1 pCi/sec. An added conservatism factor of 0.8 has been included in this calculation to account for any potential dose contribution from other radioactive particulate material.

For a 7-day period, which is the nominal sampling and analysis frequency, the cumulative release vould be 26.7 Ct. Therefore, as long as the total radiolodine, tritium, and particulate releases in any 7-day period do not exceed 26.7 C1. no additional analyses are needed to verify compliance with the Section 3.3.1 limits on allovable release rate.

4 I

l l Davis-Besse ODCM_ 45 Revision 5 t'

3.6- QUANTIFYING ACTIVITY RELEASED NRC Regulatory Guide 1.21 requires reporting the quantities of individual i radionuclides released in gaseous etfluents. Therefore, these quantities shall be determined.

Quantifying Nable Gas Activity Released Using Station Vent Monitor

~

3.6.1 (RE-4598)

The quantification of continuous noble gas effluents is based on sampling and analysis of the Station Vent etfluent. The monitor provides a measurement of gross radioactive material concentration in the etfluent. .

As required by Table 3-3, a gas sample is collected at least monthly from the Station Vent. And, as discussed in Section 3.2.2, this sample is '

analyzed by gamma spectroscopy to identify principal gamma emitting t

radionuclides (noble gases). The results of the analysis are used to determine the quantities of racionuclides released. This simplified approach reasonably quantifies the continuous release provided that nc '

atypical levels have been observed (e.g., alert setpoint being exceeded).

Based on the average noble gas monitor reading and a gas analysis for j '

the release period, the individual noble gas radienuclides released are quantified by the equation A

Og 28,317 *

C

VF

T (3-9)

CA g wheret Og - total activity released of radionuclide I (pCi).

28,317. = milliliters per ft3, Ag = activity concentration of radionuclide i f rom the gamma spectral analysis of the grab sample from the release point (pC1/ml),

C - average gross activity concentration ove.r the release period as measured by the noble gas monitor excluding any BATCH RELEASES (UCi/ml),

VF = ventilation system flow rate (ft /3 min), and ,

T release duration (min). ,

i l

1^

l-Davis-Besse ODCM 46 Revision 5 l

~

l

. . , . . . _ _ . - . - . - - . - - . . _ , - ~ . -. ...-,

l l 2 l

. - .. , n

.- i

(

L This page is intentionally blank.

N f>

r

, -- , w-.--w,- - . , - . - - ,- , , _,. .a ---v--,v.me- - ..e.--,-,- , we s.-nn,+,--- ,_er ,. . v,w,,,--,,anen,.en,r,- +,, w r+,~m pre -g -.nn,...v,+,~,-e

3.6.2 Quantifying Noble Gas Activity Released Using A Grab Sarple Vith both Station Vent .adiation monitors inoperable (i.e., RE-4598 AA and BA, Channel 1), the once-per-8 hours grab samples provide for continued ,

quantification of releases in accordance with Table 3.1 requirements. lC-1 Analysis of grab san.ples provides the radionuclide con:entrations in the effluent. The flow measurement device (or flov rate estimate) and the release duration provide the total volume released. Vith these, the total amount of radioactive material released can be determined.

The following equation may be used for determinha the release quantities .

from any release point based on the grab sample analysis: l Og . 28,317

VF

T

Cg

1E-06 (3 10) where:

03 - total activity released of radionuclide f (Cl),

28,317 - milliliters per ft3, VF = ventilation system flov rate (ft / min),

T = release duration (min),

1E-06 . Ci per sci, and Cg = cone-ntration of radionuclide i as measured in the grab sam -l (pC1/el).

J.6.3 Quantifying Radiciodine Tritium, and Particulate Activity Released For radioiodine and particulates:

Og. Ag *A g

t

v

1h-06 (3-11)

, (1-e~ i E)

s

0.72 vhere:

Og . total activity released of radionuclide f (C1),

A g - activity of radionuclide i measured on filter media (uC1).

A g - decay constant of radionuellde ( (hr ~1),

t release duration (hr),

v total vent system flev for sampling period (cc),

lE-06 . Ci per uC1.

s - total flov through sampler (cc). and 0.?2 u isokinetic flow correction factor for normal range station J vent skid RE 4598 AA or BA filter media.

(-

Davis-Besse OD M .7 Revision 5.1

r-------------- ~' ' ' ' - ~ " ~ ' - ' '- ' ' ' ~ ' " ~ ' ' ' ' ' - ' ' ' ~ ' ' ~ ' ~ ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' - ' ' ' '

l '

l For Tritium s/

l -Q .'C

V

V

IE-06 l 0.9

S (3-12) vhere:

0 = total activity of tritium released (C1),

C - tritium concentration in gas vashing bottle (pci/ml),

V - volume of water added to gas vashing bottle (ml)-

V - total vent system-flov for release period (cc),

1E Ci per 901, 0.9 - efficiency for collection of tritium, and ,

S = total sample volume through gas vashing bottie (cc). l i

l l

l t

i i

v l

L

!l I

t i o :

l- :

1:

l

, I i

l l

!=

i I

Davis-Besse ODCH 48 Revision 5 l

I m__-- . - 1

3.7 NOBLE CA1. DOSE CALCtJLATIONS - 10 CFR 50 3.7.1 M AJSTRICTED AREA Dose - Limits ;

- CuNIP f lVe do$e tont ribut ions for the current calendar quarte

Bntl rurrent colendar year for noble gases shall be determined in accotdance with the methodology and parameters in this Section at least once per 31 days. This ,

periodic assessment of teleases of noble gases is to evaluate compliance '

with the quarterly dose limits and cslendar year limits.

The alt dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY shall be limited to the following:

- during any calendar quarters less than or equal to 5 mrad for garma radiation and less than or equal to 10 mrad for beta radiation, and

- during any calendat years less than or equal to 10 mrad for gamia radiation and less than or equal to 20 mrad for beta radiation.

Vith the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above 1; tits, in lieu of a Licensee Event Report, prepare and submit to the Commission vithin 30 days, pursuant to Section 7.3, a Special Report that identifies the cause(s) for exceeding the L.it(s) and defines the corrective actior.s that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that '

subsequent releases vill be in compliance vith the above limits.

This specification is provided to implemen; the requirements of Section II.B. III.A and IV.4 of Appendix I, 10 CFR part 50. The limits specified above ptovide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents vill be kept "as lov as is reasonably achievable." This section implements the requirements l of Section III.A of Apr.endix I that conformance with the guides of Appendix ,

l 1 to be shovn by calculational procedures based on mohls ar.d data such that the actual exposure of an individual through the appropriate pathways is unlikely to-be substantially underestimated. The dose calculations established for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses i to Man from Routine Releases of Reactor Effluents for the purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric

.. Transport and Dispersion of Gaseous Ef fluents in Routine Releases f rom L Light-Vater-Cooled Reactors," Revision 1,, July 1977.

3.7.2 Dose Calculations - Noble Gases u

The following equations may be used to calculate the gamma-air and beta-air doses:

Dy - 3.17E-08

y/0 gg **(M g *r ) (3-13) g

.DS . 3.17E-08

X/0gg *I@.*0') 1 O-W l

Davis-Besse ODCM 49 Revision 5

where Dy - air dose due to gamma emissions for noble gas radionuclides (mrad),

DS = air dose due to beta emissions for noble gas radionuclides (mrad),

i X/0 gg

- atmospheric the SITE B0lfNDARY X/0 value for direct given in Table exposure 3-6 (sec/m tg) noble gas at l Og - cumulative ' clease of noble gas radionuclide i over the period of intertst (9C1),

Mg j

= tir gas dose f actor due radionuclide to garma r (mrad /yr per emissiony)uCi/m f rom f romnoble Tame 3-5, I l

Ng j

= gas air dose factor due radionuclide f (mradto beta

/yr per emissiong)f UC1/m rom from noble Table_ 3-5, and 3.17E-08 - 1/3.15E+07 (yr/sec).

3./.3 Fimplified Dose Calculation for Noble. Gases In lieu of the individual noble gas radionuclide dose assessment presented i above, the following simplified equerlons may be used for verifying compliance with the dose limits of Section 2.7.1. (Refer to Appendix B for the derivation and justification of thir sim,dified method.)

Dy = 2.0

3.17E-08

X/0 gg

H,gg

IO f (3-15) and D6 - 2.0

3.17E-08

X/0 gg

N,gg * 'I 0 3

(3-16) l vhere:

H,gg = 5.7E+02, ef fective3gamma-ah dose factor hom Appen& B (mrad /yr per pCi/m ),

11,ff 1.1E+03, effective beta-air dose factor from Appendix B (mrad /yr per pCi/m3 ), anu L 2.0 - conservatism factor to account for potential variability in the radionuclide distribution.

Davis-Besse ODCM SO Revision 5

__ _ . ~ . . - _ - - , _ - _ . . _ _ _ . _ _ . . _ ~ . . _ - ~ . _ , _ , . _ _ . _ - - -

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

e 4

t: p 3

i o ,

1 I

i t

n

. +

i This page is intentionally blank. 1 i

y L

1 h

s t

b I

I I'

s N-a '

+4 e ewvd' en wer b g 1 dr .* 2 se a y. ar '4 ?M ie*P"o ' F ~F- D + MM P"'r4 74 "E I 9 9""#-M'W'-*tC'T-~

- 3.8 RAD 1010 DINE, TRITIUM AND PARTICULATE DOSE CALCULATIONS - 10 CFR 50 3.8.1 UNRESTRICTED AREA Dose Limits l A periodic assessment is required to evaluate compliance with the quarterly dose limit and the calendar year limit to any organ. Cuinulative dose contributions for the current calendar quarter and current calendar year for I-131,- tritium and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodelogy and parameters in this section at least once per 31 days.

i The dose to a MEMBER OF THE PUBLIC from I-131, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents '

released to arcat at and beyond the SITE 80VNDARY shall be limited to the following:

- During any calendar quarters less than or equal to 7.5 mrem to any organ, and

- During any calendar year: less than or equal to 15 mrem to any organ.

-Vith the calculated dose from the release of lodine-131, tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, s Special report that identifies the cause(s) for exceeding. '

the limit and defines the corrective actions that have been taken to reduce '

the releases and the proposed corrective actions to be taken to assure that subsequent releases vill be in compliance with the above limits.

This requirement is provided to 'splement the requirements of Section II.C.

III.A, and IV.A of Appendix I. 10 CFR part 50. The limits are the guides set forth 2.sSection II.C of Appendix 1. The actions specified provide the required operating flexibility and at the same time implement the guides set '

forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous e. duents vill be kept "as lov as is reasonably achievable." The ODCH calculational methods specified in this Section implement the requirements in Section III.A of Appendix I that 1 conformance with the guides of Appendix I be shovn by calculational procedure based on models and data such that the actual exposure of an individual through appropriato rathvays *.a unlikely to be suo "antially underestimated. _The ODCM methods for calculating the deses due to the j actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculating of Annual Doses to Man from Routine-Releases of Reactor Effluents for the Purpose of Evaluating Compliance vith 10 CTR 50. Appendix I", Revision 1, October 1977 l and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport ,

L and Disper3 ion of Gaseous Effluents in Routine Releases from

. Light-Vater-Cooled Resctors," Revision 1, July 1977. .

1 l'

l h Davis-Besse ODCM 51 Revision 5 l

Tha rolosse rato spacifications for rediolodinas and radioactive materia). in particulate form are dependent on the existing radionuclide phthways to man in the UNRECTRICTED AREA. The pathways which are examined in the development of these calculations stet

- individual inhalatinn of airborne radionuclides.

- deposition of radionuclides into green leafy vegetation with subsequent consumption by man,

- deposition onto grassy areas vhere milk animals and meat-producing animals graze with consumption of the milk and meat by man, and l

- deposition en the ground with subsequent exposure of man, j l

3.8.2 Critical Pathvay j i

The critical pathway is that exposure pathway, age group, organ, and I receptor location for which the maximum dose is calculated due to a given gaseous release of radionuclides. (setermination of the critical pathway is made as part of the Annual Land Use Census. As part of this process, the maximum exposure pathway is determined for each directional sector in the area surrounding Davis-Besse. The maxium exposure pathways for each sector are listed in Table 3-4. The critical. pathway is chosen from among the maximum pathways for each sector and is listed in Table 3-6.

Only the dose via the critical pathway identified in Table 3-6 need be

eveluated for complianet: vith the dose limits of Section 3.8.1. Dose shall be calculated to the organ with the highest dose factor for the controlling age group to determine the maximum organ dose. The dose factors for organs of the various age groups are listed by exposure pathway in Tables 3-7 through 3-11.

3.8.3 Dose Calculations - Radiolodine, Tritium and Particulates The following equation may be used to evaluate the maximum organ dose dae to [

releases of iodir.4-131, tritium and particulates with half-lives greater than 8 days:

D,,p - 3.17E-08

V

ICF

SF

I (Rg ,

03 ) (3-17) lC-1

-Vheret D,,p dose or dose commitment to crgan o via controlling pathway p and age group a as identified in Table 3-6 (mrem),

V - atmospheric dispersion factor to the controlling location as identified in Table 3-6 V- - X/0, dispersion f actor. f t.,r inhalation patgvay and H-3 dose co'ntribution via all pathways (sec/m )

V - D/0, deposition factor for vegetation., milk and grouna pla a exposure patnvays (m).

Davis-Besse ODCM 52 Revision 5.1

R, g . dose factor for radionuclide i to organ o of age group a via pathway p as identified in Table 3-7, 3-8, 3-9, 3 10,3or 3-11 2

depending on the pathway specified (mrem /yr per uC1/m ) or (m ,

mrem /yr per pCi/sec), ,

Og . cumulative release over the period of interest for radionuclide I(DCi).

ICF = elemental iodine correction factor which may be used in calculating doses from radiolodines via the vegetatio.s. milk, and ground plane exposure pathways . 0.5, SF = seasonal correction factor which may be used for milk and i vegetation pathways - 0.5, and C-1 3.17E-08 = 1/3.15E+07 (yr/sec).

The dose factors in Tables 3-7 through 3-11 are derived in accordance with NUREG-0133. The elemental iodine correction factor in equation (3-17) is referenced in Regulatory Guide 1.109.

3.8.4 Simplified-Dose Calculation for Radiolodines and Particulates In lieu of the individual radionuclide dose assessment presented in equation (3-17) the following simplified dose calculation may be used for verifying compliance with the dose limits of Section 3.8.1:

IQ g (3-18)

D,,x . 3.17E-08

V

ICF

SF

R 7,333 {C-1 where D . maximum rgan dose (mrem),

max Ry ,g31. I-131 dose factor for the thyroid for the controlling pathway identified in 'lable 3-6 and IQ . sum of the activities of all radiciodines, tritium and g

particulates'(uct).

The ground plano exposure and inhalation pathways need not be considered when the simplified method is used because of the negligible contribution of these pathways to the total thyroid dose. It is recognized that for some particulate radionuclides (e.g., Co-60 and Cs-137), the ground exposure pathvay may represent a higher dose contribution than either the vegetation or milk pathway. However, use of the I-131 thyroid dose factor for all radionuclides vill maximize the-organ dose calculation, especially considering that no other radionuclide has a higher dose factor for any organ via any pathway than I-131 for the thyroid via the vegetable or milk pathway.

L 9

?

Davis-Besse ODCM 53 Revision 5.1 r.., .- -y. - e. .,r -, _v . . . , . , ,. ., y , ., . %.,, -_ . , -,..,n, ,,. , , . , . ..,,.,,..,,c. .y._.,_.,_,,,,.-.,_..,m-,,. . . ,

. . . _ . ~ . . _ - . - . . . - - . - - - . - . - - . . . . - . - . . . . . . - . - ~ . - . ~ . . ~ . . . . - . . . - . - . . - - - - .

1 l

e

- t 9

t i

r s.

This page is intentionally blank.

f f

s 4

8 I f.

?

-. . . . - - - - - . ,~_.-_,..,;________--.,...;. -

, . . -. _ _ . - _ _ ~ _ - - - - - - ... - - - - . . . - _ _ _ . ~ - _ _ . . - - . . ~ . - . . -

3.9 GAS.'0US EFFLUENT DOSE PROJECTION As with liquid effluents, gaseous effluents require processing if the projected dose exceedt, specified limits. This requirement implements the requirements of 10 CFR 50.36a on maintaining and using the approptlate radvaste processing equipment to keep releases ALARA.

The CASE 0VS RADVASTE TREATMENT SYSTEM (i.e., Vaste Gas Decay Tank) shall be used to reduce noble gas levels prior to discharge when the projected air dose due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY vould exceed 0.2 mrad for gamma radiation and 0,4 mead for beta radiation in a 31 day period (i.e., one quarter of the design objective 1 rate). l I

The VENTILATION EXHAUST TREATHLNT SYSTEM shall be used to reduce radiolodine and particulate effluents, prior to their discharge, when the projected dose ,

due to gaceous effluents releases to areas at or beyond the SITE BOUNDARY ,

vould exceed 0.3 mrem to any organ in a 31-day period. Figure 3-1 presents the gaseous effluent selease points and the GASEOUS RADVASTE and VENTILATION '

EXHAUST TREATMENT SYSTEMS applicable ior reducing efIluents prfor to telease. ,

Vith the gaseous vaste being discharged without treatment and in excess of the limits, in lieu of a Licensee Event Report prepare and submit to the commission vithin 30 days, pursuant to Section 7.3 a Special Report that includes the following informations

- Explanation of why gaseous radvaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reasons for the inoperability.

- Actions taken to restore-the inoperable equipment to OPERABLE status, and v

- Summary description of action (s) taken to prever't a recurrence.

The requirements that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents vill be kept "as lov as is reasonably achievable."- This requirement implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, The specified limits governing the use of appropriate portions of the ,

systems were specified as a suitable fraction of the dose design' objectives '

sct forth in Sections.II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.- .

If-the CASE 00S RADVAsit and VENTILATION EXHAUST TRFATHENT SYSTEMS are not being used. dose projections shall l'e performed at icast once per 31 days using the following equations:

Di p - Dy- * (31/d) (3-19)

Do g

- DB- * ( 31/d) (3-20)

D maxp " max * (31/d) (3 21) 4-

t. avis-Besse 0DCM 54 Revision 5-w ,,#, , + m.-- ...U.- , e, . < -c ..,-% ,.%.-- , - . .imr;...ca -._i,.,.._--.,n--snr,

,,.m_. , - _ .- , .,..p% ee,-,-..,,e ,.--%,-eim+rr*

wheret Dy p

= projected.31-day gamma-air dose (mrad),

Dy = gamma-air dose for current calendar quarter (mrad),

t 00 p . projected 31-dny beta-air dose (mtad), ,

DS = beta-air dose for current calendar quarter (mrad),

D,,,p . projected 31-day maximum organ dose (mrem),

= maximum organ dose for current calendar quarter as D""* determined by equation (3-17) or (3-18) (mrem), .

d = number of days accounted for by current calendar quarter !

dose, and 31 . number of days in projection.

i I

4 t

r 1

t L- Davis-Besse'0DCH 55 Revision 5 i

I'

..m.m_.. . . _ _ _ _ . _ . . . _ _ . _ _ . . . , , . - , . - . . , , . _ . ,, . , , . . . , - , , . - . . . ~ . . . _ . . , _ , , . . - - . , - , _ . , . . . _ . . .

=

9

[ _

i

' Table 3-1 t.

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION .

i MINIMUM '

CHANNELS I' INSTRUMENT' 0/ERABLE APPLICABILITY FARAMETER ACTION i l

l 1. Vaste Gas Decay Systes

! (provides automatic. isolation) ';

I

, a. Noble Gas Activity Monitor 1 .(1) Radioactivity Measurement A

r. b, Effluent System Flow Rate 1 (1) System Flow Rate Ma.surement B l Measuring Device j

. 2. Vaste Gas System

1 (providts alarm function)' ;

i j a. . Oxygen Monitor 1 (2) % Oxygen D !

4 l 1 -3. Containcient Purge Moni toring System [

-(provides automatic isolation)- !

a. Noble Gas Activity Monitor 1 (1) Radioactivity measurement C 3 i

i l j

?' i

.; 1

)

! I i,

j -

1 I

Davis-Besse ODCM 56 Revision 5 ;

1 i

~

p.

l Table 3-1 (continued)

-I~ :

I i

! RADI0 ACTIVE GASEGUS' EFFLUENT MONITORING INSTRUMENTATION .,

. .i

i. !

4 i

l, MINIMUM

' 'CHANNF)3 l ' . INSTRUMENT ' OPERABLE .?PLICABILITY PARAMETER ACTION

'4. Station Vent Stack I 4

(provides alata function) i: !

2 a. Noble Gas' Activity Monitor 1 (1) Radioactivity Measurement C i I 'b.

. Iodine Sampler Cartridge 1 (1) Verify Presence of E fJ Cartridge

c. . Particulate Sampler Filter 1 (1) Verify Presence of Filter -E f i

i

d. i aluent System Flov. 1 (1) System Flov Rate B ;

Nte Measuring Device . Measurement i i

.e. S.impler Flov Rate Measuring i j Device 1 (1) Sampler Flow Rate B Measurement i

! I l

t t

i. i i- t i !

3 1 4 I i

, i

t. I j Davis-Besse ODCM 37 Revision 5 i

^

r

1 Table 3-1 (Continued) ;

TABLE NOTATION l (1) During radioactive vaste gas teleaces via this pathway.

(2) During additions to the vaste gas surge tank ACTION A Vith the number of channels OPERABLE less than requited by t!.e minimum channels OPERABLE requirement, the contents of the tank may be released to the environment provided that prior to initiating the rele,tvat

1. At least two independent samples are analyzed in accordance with table 3-3 for analyses performed with each batcht

2. At least two independent verifications of the release tate calculations are perfotmed

3. At least two independent verifications of the discharge valving are performed.

ACTION B Vith the number of channels OPERABLE less than required by the minimum channels OPERABLE tequirement, effluent releases via this pathway may continue provided the fluv rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION C Vith the number of channels OPERABLE less than required by the minimum channels GPERABLE requirement, effluent releases via this pathway mty' continue provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION D Vith the number of channels OPERAELE less than required by the minimum channels OPERABLE requirement, additions to the vaste gas surge tank may continue provided another method for ascertaining oxygen concentrations, such as grab sample s.ialysis, is implemented to provide measurements at least once per fou.t4) hours during degassing and daily during other operations.

ACTION E Vith the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement. effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment, as required in Table 3-3.

l-E i

Davis-Bessee ODCM 58 Revision 5

. - _ _ _ , . _ _ _ . _ _ _ . _ _ _ _ _ _ _ . . , . _ - . _ _ _ . _ _ . . . . . . . _ .__ . . _ . ~ . , . -

4 Table 3-2 i- RADI0 ACTIVE GASEOUS EFFLUENT MONITORING . INSTRUMENTATION SURVEILIANCE REQUIRE"EffrS CHANNEL .

CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CHECK CALIBFATION TEST INSTRUMENT I l '. Vaste Gas Decay' System I) P 'R O

'a. Noble Gas Activity Monitor P Effluent System Flow Rate P U) N/A. R Q b.

4 I. 2. Containsent Purge Vent System

a. Noble Gas Activity Monitor D I} P };MI0) R Q U}

3 Station Vent Stacit

)

a. Noble Gas Activity Monitor DI M R Q Iodine Sampler V II} N/A N/A N/A b.

i Particulate Sampler V II N/A N/A N/A c.

'd . System Effluent Flow Rate

{ D N/A R N/A Measurteent Device i

e. Sampler Flow Rate Measurement Device VI N/A R N/A l

5 Davis Besse ODCM 54 Revision 5 Y

i

- _ . . . - + , , , . - , - _ - - . . _ . - , _ . _ _ _ _ _ _ _ , _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - - . _

_ _ _ _ _ _ - _ .*

4 Table 3-2 (Continued) I TABLE NOTATION (1) During radioactive vaste gas releases via this pathvay.

(2) During additions to the vaste gas surge tank. -

(3) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic :

isolation of this patbvay and control room alarm annunciation

~

occurs if the instrument Indicates measured levels above the alarm / trip setpoint. l (4) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if the instrument indicates measured levels above the alarm / trip setpoint.

(5) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of they reference standards certified by the National Instatute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been releated to the initial calibration should be used, at intervals of at least once per eighteen months. For high range monitoring instrumentation, where calibration with a radioactive source is imprattical, an electronic calibration may be substituted for the radiation source calibration.

(6) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One' volume percent oxygen, balance nitrogen: and

2. Four volume percent oxygen, balance nitrogen.

(7) During containment purges.

(8) ~When used in a continuous mode.

4

-P Prior to each release.

R At least once per 18 months (550 days).

O At least once per 92 days.

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

t

H At least-once per 31 days.

V At least once per 7 days, f

Davis-Besse ODCH 60 Revision 5

m G3h

~ ~

'hp 1 &

^

Table 3-3 43EOUS VASTE SAMPLI'F Y RASI0ACT10 Minimum .Lo'ser Licit of Gaseous Release Type Sampling Analysis Pype of Detection {LLD Activity Analysis (pCi/al)

Frequency #requency P P ,

" Each Each Principal ' mma Emitters' l.0E-04 Waste Gas Decay Rele-se Release _

'l- 3 1 9E-06 Grab Sample P P C Each Parge Each Purge Principal Canna Emit ters 1.0: -04 2a Containment Purge (1, Grab Sample H-} 1.0E-(< =

H H C Principal Gamv Emitters ~~~ 1.0E-04 Station Vent Stack Crab Sampre H-3 --

1.0E-06 b

Charcoal I.1.I 1.0E-12 Centir/sous Sarple b 1.6E-Il Continuot.s Pa:ticulate Prineipa[Camma sample Emitters M

b Continuous composit

.' .4 r t icula iss Alpha 1.OE-11 h ele V

b Continuous C mr% site Particulat< , Sr-90 1.0E-11 Sample continuous' Noble Gas Noble Gases Monitor Gross Bet,- or Gamma 1.0E-06 61 Revision 5 Davis-Besse CDCM c- p ,

,-pv ,

- - . . . . . ~ . . . - . . - - . ~ . . . - - - - . . . . . . - - - . .-

Tabla 3-3 (Continued)

TABLE NOTATION

a. The 1.LD is the smallest concentration of radioactive material in a sample that vill be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radio-chemical separation):

LLD =

E

V

2.22

Y.* exp(-Aot) i where LLD is the lover limit of detection as defined above (es pCi per unit mass or volume);

s is the standard deviation of the-background counting rate or of the b

coanting 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 picocurie; Y le the fractional radiochemical yield (when applicable);

A is the radioactive decay constant for the particular c'dionuclide;

. 6t for plant effluents is the elapsed time between the midpoint of sc.nple collection and time of counting.

It should be recogr.ized that the LLD ls defined as an a priori (before ti.e fact) limit: representing the capability of a measurement system and not as a

-posteriori (after the fact) limit for a particular. measurement.

b. The ratio of the sample flow rate to the sampled stream flow care shall be knovn-for the time period covered by each dose or dose rate calculation made

-in accordance with Sections 3.3.'l and 3.8.

D 1

Davis-Besse ODCM 62 Revision 5

. -. _- . . . . . - - . _ . -.- - - . . - . . _ . - , . . - . , - . - . . _ _ . . ~ - . _ . . . ~ - .

Table 3-3 (Continued)

TABLE NOTATION

c. The principal gamma emitters for which the LLD snecification vill apply are exclusively the follJving radionuclides: Kr-87. Kr-88, Xe-133, Xe-133m, Xe 135, and Xe ';36 for gaseous emissions and Mn-54 Fe-59, co-58, Co.60, 2n-65, M9-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported. Other peaks which are-measured and identified, together.vith the above nuclides, shall also be identifed and reported. Nuclides vch are-below the LLD for the analyses should be teparted as "less than" ine ,

nuclide's LLD and should not be reported as being present at t h e. LLD level

~

for the nuclide. The 'iless than" values shall not be used in the required dose calculations. When unusual circumstance tsult in LLDs higher than required, the reasrns shall be ditumented in n Semiannual Effluent and Vaste Disposal Report.

Frequency notation:

P - Prior to each release.

N - At least once per 31 days, V - At least once per 7 days.

Q _ At least once per 92 days.

Davis-Besse ODCM 63 Revision 5 t

f Table-3-4 l i

Land-Use Census Summary l

' Exposure-Pathvay 1,ocations and Atmospheric Dispersion Paramatars Distance Exposure Controlling X/0 O ,

Sec t o r--- - (me t er s ) .. Pathway Age Group (sec/m ) (m'f0 ) .

N '880. inhalation child 9.15E-07 8.4E-09

- NNE '870- inhalation child 1 27E-06 1.47E-08 NE_ 900 inhalation child 1.26E-06 1.58E,08

. ENE*- -- -- . -. -- --

E* --' -~ -- -- --

ESE'* .-- -- -- --

_SE* -- -- -- -- --

SSE-- 2,900 vegetati.n child 6.80E-08 7.90E-10 S 1,450 vegetation child 1.21E-07 2.46E-09 SSV: 1,560** vegetatlon child 1.03E.07 2.28E SV '1,050** vegetation child 2.92E-07 5.33E-09:

VSV 4,270 cov/ milk infant 5.71E-08 5.31E-10 V- 1,720** vegetation child 2.47E-07 3.81E-09 VNV- 1,750** vegetation child 1.46E-07 1.72E-09 NV 2,630** vegetation- child 5.96E-08 4.50E-10 NNV 1,210 vegetation child 2.70E-07 1.92E-09

Since'these sectors are located over marsh areas and Lake Erie, no ingestion-or inhalation pathways are present.

- ** These values are a change to'this table as a result of the 1991 Land Use

-Census.

Note: The meteorological dispersion factors are taken from the Stone and Vebster report, Handbook for ODCM X/0 and D/0 calculations, o ctober 1983.

It f

~

- Davis-Besse ODCH- 64 Revision 5 a

g.--. - . _ ~ . . . . . ~ . .

II A: .' l

. Table 3 Dose Factors for Noble Gases

Total' Body Skin (.amma Air Beta Air Gamma Dose -Beta Dose Dose-Factor Dose Factor Fur.lide Factor K Factor 13 Hg N' (mrad /yr3 per (mrem pC1/m/yg)per . (mrem pC1/m /yg)per uCi/m )= .(mrad pCi/m /hg)per Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m l'.17E+03 1.46E+03 1.23E*03 1,97E+03 lf Kr-85 't.61E+01 -1.34E+03 1.72E+01 1.95E+03 Kr-87 ._5.92E+03 9.71E+03 6.17E+03_ 1.03E+04 Kr 1.47E+04 2.37E+03 1.52E+04 2.93E+03

'Kr-89 1.66E+04 1.01E*04 1.73E+04 1.06E+04 L Kr-90' 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m- 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E402 9.94E+02 3.27E+02 1.48E+03 j

- Xe-133 '2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m' 3.12EE03 7.11E+02 3.36E+03- 7 ~. 39E + 02 i y - Xe-135 : 1. 81E + 0 3. . 1.86E+03 1.92E+03 2.46E+03

- Ne-137. -1.42E+03 1.22E 04 1.51E+03 1.'27E+04 Xe '138 8.83E*03 4.13E+03 9.21E+03 -4.75E+03

-Ar L41 - 8.84E+03- 2.69E+03- 9.30E+03- 3.28E+03

?

.E

DoseLfactors_taken from NRC Regulatory Guide 1.109

t Davis-Besse.0DCM' 65 Revision 5 J

+ r- ,m ._ , ,,

Table 3 Exposure Pathways, Controlling Parameters.:and-Atmospheric Dispersion-for Dose s Oculations Atmospheric Dispersion

.. Exposure --!teceptor Controlling X/0 D/Q

Pathvay Location ; Age Group _ (sec/m3) (m-') 1 noble gases SITE BOUNDARY N/A 1.83E-06 N/A direct. NNE l exposure inhalation SITE BOUNDARY child 1.68E-06 N/A NNE (critical pathvay) grass - cov 4270 meters infant 5.71E-08 5.31E-10

- milk -VSV.

4 F

NOTES:

1. All meteorological dispersion values have been taken from the stone and-

Vebster report, Handbook for ODCM X/o and D/0 Caltitla tions, October -1983,

2. -The noble gas,-direct exposure x/Qs are based on the decayed, undepleted

,alues.

_3. _ Thi inhalation pathway X/Qs are based on the decayed. depleted values.

Davis-Besse ODCM- 66 Revistor 5

'su--e_-,e --em>vr a pr'wre- evw'<'- 'rv w w w wvw-wwe wt-qr--ewwwwy- -

,q-y>v w 199- 4m p 9 sM w m 9 t'**~'f' P7- eF]

Table 3 7-R gg, Inhalation Pathway Dose F3ctors - ADULT (mrem /yr per uC1/m )

Nuclide tone Liver thyroid Elchey LW Ot.tL1 f. Body H3 - 1.26E+3 1.2M+3 1.26E+3 1.26E+3 1.2M+3 1.26E*3 C 14 1.E2E+4 3.41E+3 3.41E*3 3.41E+3 3.41E+3 3.41E+3 3.41E*3 no 24 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E*4 1.02E+4 1.02f+4 P 32 .32E*6 7.71E+4 - - -

8.64E+4 5.01E+4 Cr 51 - -

5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.00E+2 Mn 54 - 3.9M+4 - 9.84E*3 1.40E+6 7.74E+4 6.30E+3 Mn 56 - 1.24E+0 - 1.30E+0 9.44E+3 2.02E+4 1.83E.1 fe 55 1.4M +4 - 1.70E+4 - -

7.21E+4 6.03E+3 3.94E+3 Fe 59 1.18E+4 2.78E+4 - -

1.02E+6 1.88E+5 1.06E+4 Co 57 - 6.92E+2 *

3.70E+5 3.14E+4 6.71E*2 Co 58 - 1.58E*3 - -

9.28E*5 1.06E+5 2.07E*3 Co 60 - 1.15E+4 - -

5.97E+6 2.85E+5 1.48E+4 ul 63 4.32E+5 3.14E+4 - - 1.7M+5 1.34E+4 1.45E+4.

Ni 65 1.54E+0 2.10E 1 - - 5.60E*3 1.23E+4 9.12E-2 Cu 64 - - 1.4M +0 -

4.62E+0 6.78E+3 4.90E+4 6.15E 1 2n 65' 3.24E+4 1.03E*5 - 6.90E+4 8.64E+5 5.34E+4 4.6M +4

- Zro49 3.38E 2 6.51E-2 -

4.22E 2 9.20E+2 1.6A +1 4.52E-3 tai - - - - -

1.04E+4 1.35E+4 tr 83 - * * - -

2.32E*2 2.41E+2 Br-84 - * * - -

1.64E 3 3.13E+2 tr 85 - - - - - -

1.28E+1 ab-86 - 1.35E+5 - - -

1.6M+4 5.90E+4 Rb 88 - 3.87E*2 - -

3.34E 9 1.93E+2

- - - 1.70E+2 Rb 89 -

2.56E+2 -

$r-89 3.04E+5 - . . 1.40E+6 3.50E+5 8.72E+3 sr 90 9.92E+7 . - - 9.60E+6 7.22E+5 6.10E+6

- Sr-91 6.19E+1 - - -

3.65E+4 1.91E+5 2.50E**

sr 92 6.74E+0 - - - 1.65E+4 4.30E+4 2.91E-1 Y 90 2.09E+3 - - 1.70E+5 5.06E+! 5.61E+1 Y 91a 2.61E 1 - - - 1.92E+3 1.33E+0 1.02E 2 Y 91 4.62E+5 - - - 1.70E+6 3.85E+5 1.24E+4 Y 92 1.03E+1 - - - 1.57E+4 7.35E+4 3.02E 1 Y 93 9.44E+1 - - - 4.85E+4 .4.22E*5 2.61E+0 tr M 1.07E*5 3.44E+4 -

5.42E +4 1.77E+6 1.50E+5 2.33E+4 l:

fr 97 9.68E+1 -1.96E+1 -

2.97E+1 7.87E+4 5.23E+5 9.04E+0 j-

~# Nb'95 1.41E+4 7.82E+3 - 7.74E+3 5.0$E+5 1.04E+5 4.21E+3

! Nb-97 2.22E 1 5.62E 2 - 6.54E 2 2.40E*3 2.42E+2 2.05E-2 Mo 99 - 1.21E+2 - 2.91E*2 9.12E+4 2.4.*E+5 2.30E+1 f c 9% '1.03E-3 2.91E 3 - 4.42E 2 7.64E+2 4.16E+3 3.7DE-2 l- Davis-Bes/e ODCM 67 Revicion 5 r

?

L

. + - - - , ,

Tablir 3-7 (continued)

R gg, InhEdation Pathvay Dose Factors3 - ADULT (cont.)

(mrem /yr per uCi/m )

suclide sono Liver Thyroid Eldhey twi St LLl f.Sody

....... ....... ....... ....... ....... ... 8... ....... .......

ic 101 4.1M 5 6.02E-5 =

1.08E 3 3.99E*2 -

5.90E-4 I tv-103 9.53E+3 . .

5.832+3 5.05E+5 1.10E+5 6.58t+2 tv 105 7.90E 1 . .

1.02E+0 1.10E+4 4.82E+4 - 3.11E-1 Eu 106 6.91E+4 - -

1.34t+5 9.3M4 9.12E+5 8.72E+3 th 103e - . . . . . .

j Eh 106 . *

a . *

A8 11';m 1.0EE+4 1.00E+4 -

1.97t+4 4.63E+4 3.02E*5

5+E*3 sb-124 3.12E+4 5.89E+2 7.55E*1 -

2.48E +6 4.0M +5 1.24E+4 Sb-125 5.34E+4 5.95E+2 5.40E+1 -

1.74E+6 1.01E+5 1.2M+4 fe 125s 3.42E*3 1.58E*3 1.0$E +3 1.24E +4 3.14E+5 7.0M+4 4.67E*2 fe 127m 1.26E 4 5.77E+3 3.29E+3 4.58E+' 9.60E +5 1.50E+5 1.57t+3 l to 127 1.40E+0 6.42E.1 1.06E+0 $.10E+0 6.51E+3 5.74E+= 3.1M 1 '

Te 129m 9.7M+3 4.67t*3 3.44E*3 3.66E+4 1.16E+4 3.83E+5 1.58E+3 fe 129 4.9M

2 2.39E 2 3.90E 2 1.871 1 1.94E+1 1.571+2 1.24E 2 Te 131m 6.99E+1 4.36t+1 5.50E+1 3.09E+2 1.46t+5 5.5M+5 2.90E+1 t e.1*.1 - 1.11E 2 5.95E 3 9.36E 3 4.371 2 1.39E*3 1.84E+1 3.59E 3 Te 132 2.60E+2 2.15E+2 1.90E+2 1.46E+3 2.88E+5 5.10E+5 1.62E+2 1 130 4.58t+3 1.34E+4 1.14E+6 2.09E+4 . 7.69E+3 5.28E+3 1 131 2.52E+4 3.58E+4 1.19E*7 6.13E+4 -

6.286+3 2.05E+4 1 132 1.16E+3 3.2M+3 1.14E+5 5.18E+1 . 4.0M+2 1.1M+3 1+133 8.64E+3 1.48t+4 2.15E+4 2.58t+4 - .

8.88E+3 4.52E+3 1 134 6.44E+2 1.73E+3 2.98E+4 2.75E+3 . 1.01E+0 6.15E*2 1 135 2.6M+3 6.95+3 4.48E+5 1.11E+4 -

5.25E+3 2.57t+3 Cs 134 3.73E+5 8.48E+5 -

2.87E+5 9.76t+4 1.04E*4 7.28E+5 Cs 136 - 3.90E+4 1.4M+5 .

8.5M+4 1.20E+4 1.17E+4 1.10E+5 Cs 137 4.78E+5 4.21E+5 . 2.22E+5 7.52E+4 8.40E *3 4.2M+5 Ca.138 3.31E+2 6.21E+2 . 4.80E+2 4.8M+ 1 1.86E 3 3.24E+2 Ea 139 9.36E 1 6.66E 4 .

6.221 4 3.76E+3 8.9Me 2 2.74E-2 Sa 140 3.90E+4 4.90E+1 . 1.67t+1 1.27t+4 2.he+5 2.57E+3 Sa 141 1.00E 1 7.53E 5 - 7.00E 5 1.94E+3 1.1M 7 3.36E 3 8t 142 2.634 2 2.7DE 5 . 2.29E 5 1.19E+3 - 1.66E 3 La-140 3.44E+2 1.74E+2 . . 1.3M+5 4.58E+5 4.5M *1

, La 142 6.83E 1 3.10E-1 . -

6.33E+3 2.11k+3 7.72E 2 f

co 141 1.97E+4 1.35E+4 . 6.2M *3 3.62E+5 1.20E+5 1.53E+3 Ce 143 1.8M+2 1.38E+2 . 6.08E+1 7.98E+4 2 26E*5 1.53E+1 C e-144 3.43E+4 1.43E+4 -

8.48E+5 T.78E+6 t 16E+5 1.84E+5 pr 143 9.3M +3 3.75E+3 . 2.16E+3 2.81E*5 2.00E+5 4.64E+2 Pr 144 3.01E 2 1.25E 2 - 7.05E-3 1.02E+3 2.15E-8 1.53E 3 ud 147 5.27E+3 6.10E+3 -

3.56E+3 2.21E+5 1.73E+5 3.65E+2 W 187 - 8.48E+0 7.08E*0 - - 2.90E+4 1.55E+5 2. W +0 hp 239 2.30E*2 2.2M+1 . 7.0C4+1 3.76t+4 1.19E+5 1.24E+1 Davis-Besse ODCM 68 Revision 5

Table 3-7 (continued) I Rg, Inhalation Pathway. Dose Fac4 ors - TEENAGER (mrem /yr per pCi/m')

MucLtde- Bone - Liver Thyroid Kichey Lme GI-LLI T.Sody N3 -

1.27t+3 1.27t+3 1.27E+3 1.27E*3.1.27t+3 - 1.27E*3 C 14 2.60E+4 4. 87E + 3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87t+3 Na 24 1.38E+4 1.38E+4 1.38t+4 1.3M +4 1.38t+4 1.38E+4 1.38E+4 P 32 1.Mt+4 1.iOE+5 - - -

9.2M+4 7.1M +4 Cr 51 - -

7.50E+1 3.07E+1 2.10E*4 3.00E+3 1.35E+2 Mn 54 - 5.11E+4 - 1.27t+4 1.98E*6 6.68E+4 8.40E+3 un 56 1.70E+0 - 1. 7W+0 1.52E+4 5.74E+4 2.52E 1-fe 55 3 ) E+4 2.38t+4 - -

1.24E+5 6.39E+3 5.54E+3 Fe 59 1.59E+4 3.70E+4 - -

1.53E+6 1.7BE+5 1.43E+4 '

Co 57 - 6.92E+2 - -

5.86t+5 3.14E++ 9.20E+2 Co 58 - 7 07t+3 - -

1.34E+6 9.52E+4 2.78E+3 Co-60 - 1.51E+4 - -

P.72E+6 2.59E+5 1.9BE*4 Wi 63 5.80E+5 4.34E*4 - -

3.07t+5 1.42E+4 1.9M*4 Wi 65 2.18E+0 2.93E 1 - -

9.3M+3 3.67E+4 1.27E 1 l l

Cu-64

2.03E+0 -

6.41E+0 1.11E+4 6.14E+4 8.4M 1 2n-65 3.84E+4 1.34E+5 - 8.64E+4 1.24E+6 4.6M+4 6.24E+4 2n-69 4.83E 2 9.20E-2 - 6.02E 2 1.58E+3 2.85E+2 6.4M 3 Br 82 - - - - - - 1.82E+4 tr-83 - - - - - - 3.44E+2 Br 84 - - - - - 4.33E+2 tr-85 - - - - - - 1.83E*1 ab 86 - 1.90E+5 - - -

9.TTE+4 8.40E+4 ab-88 - 5,46E+2 - - -

2.92E 5 2.72E+2 ab-89 - 3.52E+2 - - -

3.38E 7 2.33E+2 Sr 89 -4.34E+5 - - -

2.42E+6 3.71E*5 1.25E+4

$r 90 1.08E+8 - - -

1.65E+7 7.65E+5 6.68E*6 sr-91 8.80E+1 - - -

6.07E+4 2.59E+5 3.51E+0 sr-92 9.52E+0 - - - 2.74E+4 1.19E+5 4.06E 1 Y 90 2.98E+3 - - -

2.93E+5 5.59E+5 8.00E+1 Y 91e 3.70E 1 - - 3.20E+3 3.02E+1 1.42E 2 Y 91 6.61E+5 - - - 2.94E*6 4.09E+5 1.77E +4

, i Y 92 1.47t+1 - - - 2.68E+4 1.65E+5 4.29E 1 Y 93 1.33E+2 - - - 8.3N+4 5.79E+5 3.72E+0 4

Zr 95 1.4M+5 4.5M +4 - 6.74E+4 2.69E+6 1.49E*5 3.15E+4 2r 97 1.3M+2 2.72E+1 - 4.12t+1 1.30E+5 6.30E+5 1.2M+1 kb-95 1.86E+4 1.ctt+4 -

1.00E+4 7.51E+5 7.6M +4 5.6M+3 NO-97 .3.14E-1 7.78E 2 - 9.12E-2 3.93E+3 2.17t+3 2.84E 2 Mo 99 - 1.69E+2 - 4.11E+2 1.54E+5 2.69E+5 3.22E+1 Tc 99m 1.38E-3 3.86E 3 + 5. 7M-2 1.15E+3 6.13E+3 4.991 2 Davis-Besce ODCM 69 Revision 5

Table 3 7 (centinued)

Rgn, Inhalation Pathway Dose Factors -) TEENAGER (corit.)

(mrem /yr per UC1/m )

Wuclide 8ene Liver hr-old Elchey Lug gl.LL1 f.8ady

- f c 101 - 5.921 5 8.40E 5 .

1.521 3 6.67t*? 8.77t 7 8'.24t 4 au 103 2.1C(+ 3 *

7.43t+3 7.83t+5 1.09t+5 8.9M + 2 au 105 1.12t+0 - -

1.41t+0 1.825 4 9.04t+4 4.34 1 A9 106 9.84t+4 . - 1.90t+5 1.6't+7 9.60t+5 1.24 +4 th.103m . . . . . . .

th 106 . . - * * . -

A8 110e 1.3E +4 1.31t+4 -

2.50t+4 e.Mrie 2.73E+5 7.99t<

sb 124 4.30t+4 7.94t+2 9.7M+ 1

3.85t+6 3.98t+5 1.6M4 b 125 7.38E4 8.08t+2 7.04E+1 -

2.74 +6 9.92E+4 1.72t+4 fe 125e 4.88t+3 2.24E+) 1.40E+3 -

5.3M +5 7.50E+4 6.67t+2 fe 177a 1.80t+4 8.1M

3 4.3M +3 6.54+4 1.66t+4 1.59t+5 2.18t+3 fe 127 2.01t+0 7.121 1 1.42t+0 7.2M+C 1.12t+4 8.08t+4 4.42I 1 fe 129m 1.39t 4 6.58t+3 4.5M+3 5.19t+4 1.98t+4 4.05t+5 2.25t+3 fe 129 7.10E 2 3.3M 2 5.188 2 2.6M 1 3.30E+3 1.62E+3 1.7M 2 fe 131s 9.84t+1 6.01t+1 7.25t+1 4.39t+2 2.38E+5 6.21t+5 4.02t+1 te+131 - 1.5M 2 8.321 3 1.24E 2 6.18t 2 2.34 +3 1.51t*1 5.044-3 fe-132 3.60t+2 2.90t+2 2.46t+2 1.95t+3 %.49t+5 4 4t+5 2.19t+2 1+130 6.24t*3 1.79t+4 1.49t+6 2.MN - 9.12t+3 7.17t+3 1 131 3.54E+4 4.91t4 1.46t+T 8.40t+4 -

6.49t+3 2.64E+4 I. 32 1.59t+3 4.3M+3 1.51t+5 6.92t+3 - 1.2M+3 1.58t+3 Ia133 1 'M +4 2.05E+4 2.92t+6 3.59t+4 -

1.03t+4 4.22t+3 1 134 8.88t+2 2.32t+3 3.95E 4 3.64E+3 - 2.04E+1 8.40t*2 1 135 3.7W+3 9.44E+3 6.21t+5 1.19t+4 - 6.95E+3 3.49t+3

.4+134 5.02t+5 1.13E+6 - 3.Mt+5 1.4M +5 9.7M+3 5.49t+5 Cs 136 5.15E+4 1.94t+5 -

1.10t+5 1.78E4 1.09t+4 1.37t+5 Cs 137 6.7tlE+5 8.48t+5 -

3.04E+5 1.21t+5 8.48t+3 3.11t+5 Cs 138 4.6M+2 8.5M+2 - 6.e't+2 7.87t+1 2.N - 1 4.46t+2 se 139 1.34E+0 9.445 4 - 8.88t.4 6.4M+3 6.45E+3 3.908 2 te 140 5.47t+4 6.70E+1 - 2.2M*1 2.03E+6 2.29t+3 3.52t+1 84 141 1.425-1 1.0M 4 - 9.84t-5 3.29t+3 7.4M 4 4.744 -3 Sa 142 3.70E 2 3.7DE 5 - 3.14-5 1.91t+3 - 2.27t 3 La 140 4.79t+2 2.3M+2 * - 2.14E+5 4.87t*5 6.2M+1 La 142 9.60s.) +.25t 1 - -

021 4 1.102 4 1.0M 1 Ca 141 2.84t+4 1.90E+4 - 8.88t+3 6.14t+5 1.2 S $ 2.17t+1 Ce 143 2.66t+2 1.94E+2 - 8.64+1 1.30E*5 2.55E+5 2.1M+1 Co-144 4.89t+6 2.02t+6 - 1.21t+6 1.34 +7 8.64E+5 2.62t+5 Pr 143 1.34E+4 5.31t+3 - 3.09t+3 4.83t+5 2.14t+5 6.62t+2 Pr 144 4.30t.2 1.7M.2 - 1.01E 2 1.Mt+3 2.35E-4 2.182 3 ud 147 7.8M+3 8.5M+3 + 5.02t*3 3.72t+5 1.52t+5 5.13t+2 W-187 1. 2M + 1 9.76t +0 - - 4.74t4 1.77t+5 3.43t+0 ho 239 3.3M+2 3.19t+1 + 1.00t+2 6.49E4 1.32,1+5 1.77t+1 Davis-Besse ODCM 70 Revision 5

Table 3-7 (continued)

Rg , Inhalation Pathvay Dose Fj'etors - CHILD (mrem /yr per UC1/m )

Nucilde Bone Liver Thyroid Kleey Ltr GI LLI f.8My -

....... ....... ....... ....... ....... ....e... ....... .......

N3 -

1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C 14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73F+3 6.73E+2 6.71E+3 Na 24 1.61E+4 1.61E+4 1.61E+4 1.6M+4 1.61E+4 1.61E+4 1.61E+4 PG2 2.60E+6 1.14E+5 - - -

4.22E+4 9.68E+4 Cr 51 - -

8.55E+1 2.43E+1 1.70E+4 1 7 4+3 1.54E+2 nn 54 - 4.29E+4 -

1.00E+4 1.58t+6 2.29E+4 9.51E+3 Mn 56 - 1.66E+0 -

1.67E+0 1.31E+4 1.23E+5 3.12E 1 Fe 55 4.74E+4 2.52E+4 - -

1.11E+5 2.87E+3 7.77E*3 Fe-59 2.07E+4 3.34E*4 - -

1.27E+6 7.07t+4 1.67E+4 Co-57 -

9.03E+2 - -

5.07E+5 1.32E+4 1.07E*3 en 58 - 1. 77E +1 - -

1.11E+6 J.44E*4 3.1M +3 Co 60 - 1.31E+4 - -

7.07E+6 9.62E+4 2.2M+4 Ni 63 8.2iE+5 4.63E+4 - -

2.75E+5 6.33E*3 2.80E+4 Ni 65 2.99E+0 2.96E 1 - -

8.18E+3 8.40E+4 1.fi.E 1 Cu-64 -

1.99E+0 -

. 03E+0 9.58E+3 3.6TE*4 1.07E*0 2n-65 4.26E+4 1.13E+5 -

7.14E+4 9.95E+5 1.63E+4 7.03E+4

- 2n 69 6.70E 2 9.664 2 -

5.85E 2 1.42E+3 1.01E+4 8.92E 3 Br 82 - - - - - - 2.09E+4 Br-83 - - - - -

4.74E+2 Br 84 - - - - - -

5.4aE+2

-Br 85 - - - - - -

2.53E+1 tb-86 - 1.98E+5 - - -

7.99t+3 1.14E+5 ab-88 - 5.62E+2 - - - 1.72E+1 3.664+2 tb 89 . - 3.45E*2 - - -

1.89E+0 2.90E*2

$r 69 5.99E+5 - - -

2.16E+6 1.67E+5 1.72E+4 sr 00 1.01E+8 - - -

1.48E+7 3.43E+5 6.44E+6

$r 91 1.21E+2 - - -

5.33E+4 1.74E+5 4.59E+0 tr 92 1.31E+1 * - -

2.40E+4 2.42E+5 5.25E 1 Y 90 4- (E+3 - - -

2.62E+5 2.68E+5 1.11E+2 Y 91m 5.07E.1 - - ~- 2.81E+3 1.72 '.

3 1.84E 2 Y 91 9.14E+5 - - -

2.63E+6 1.84E+5 2.44E+4 4

Y-92 2.04E+1 - - -

2.39E+4 2.39E+5 5.81E-1 Y 93 1.86E+2 - - -

7.44E+4 3.89E+5 5.11E+0 2r 95 1.90E+5 4.18E+4 -

5.96E+4 2.23E+6 6.11E+4 - 3.70E+4 2r 97 1.88t+2 2.72E+1 - 3.89E+1 1.13E+5 3.51E+5 1.60E+1 Nb 95 2.35E+4 9.184+3 -

8.62E+3 6.14E+5 3.70E+4 6.55Ee3 hb-97 4.29E 1 7.70E 2 - 8.55E 2 3.42E+3 2.78E+4 3.6aE 2 No-99 - - 1.72E+2 - 3.92E+2 1 35E+5 1.27t+5 4.26E+1 fc-99m 1.78E 3 3.48E-3 -

5.07E 2 9.51E+2 4.81E+3 5.77E 2 Davis-Besse ODCM 71 Revision 5

1 Table 3-7 (continued)

Rg , Inhalation Pathway Dose Facto $s - CHILD (cont.)

(mrem /yr per uCi/m )

suct ide lane Liver fryeoid tmg Gt LLI f.8ccty

....... ....... ....... .......E......

f ewf. -...... ....... .......

14'101 8.10E 5 8.51t 5 .

1.45E 3 5.85E+2 1.63t+1 1.088 3 au 103 2.79t+3 - -

7.03t+1 6.62t+5 4.Aat+4 1.07t+3 tv 105 1.53E+0 . - 1.34 +0 1.59t+4 9.95t+4 5.551 1 89 106 1.3M + 5 . . 1.84t+5 1.433*7 4.29t+5 1.69t+4 th.103e - - - -

th 106 - - - -

44 114e 1.69t+4 1.144 4

1.12t+4 5.4Pa+6 1.00t+f 9.14t+3 sb 124 5.74t+4 7 40t+2 1.26t+2 - 3.241 4 1.44+5 2.00t+4 sb-125 9.84t+4 7.59t+2 9.10t+1 + 2.32t+6 4.03E+4 2.07t+4 fe 125m 6.T3t+3 2.S !"3 1.92t+3 - 4.77t+5 t *8t+4 9.14t+2 fe 127m 2.49t+4 8.55t+3 6.07t+3 6.34.+4 1.4st+6 7.14E4 3.02t+3 fe 127 2.77t+0 9.518 1 1.9M+0 7.07t+0 1.f4E+4 5.621 4 6.118 1 te 129m 1.92t+4 6.85t+3 6.33t+3 5.03f 4 1.76t+6 1.82e+5 3.04t+3 fe 129 9.T71 2 3.50t 2 7.148 2 2.57t 1 2.9'Jt+3 2.55t*4 2.38t 2 fe 131m 1.34t+2 5.92t*1 9.77t+1 4.00t+2 2.0M+5 3.08t+5 5.07t+1 fe 131 2.1 75-2 8.448 3 1.70t 2 5.68t 2 2.05t+3 1.33t+3 6.59t 3 fe 112 4.81t+2 2.72t+2 3.17t +2 1.77t+3 3.77t+5 1.3295 2.Mt+2 t tY 8.18t*3 1.64t+4 s.85F+6 2.45t+4 - 5.11t+3 8.44t+3 1 131 4. tit +4 4.81t+4 1.62t+7 7.8E+4 - 2.84E+3 2.73E+4 I 132 2.121*3 4.07t+3 1.94t+5 6.25t+3 -

3.20t+3 1.88t+3 1 133 1.66b4 2.03C+4 3.85t+4 3.3M+4

5.A8t+3 7.70t+3 I 134 1.17t+3 2 558+3 5.07t +4 3.3003 - 9.55t +2 9.95t+2 i

i t 135 4.92t+3 8.73t +3 7.92t+5 1.36t+4

- 4.444+3 4.1463 Ca 134 6.51t+5 1.01t+6 - F.30t+5 1.21k5 3.85t+3 2.25t+5 C4 134 6.51t+4 1.71t +4 - 9.55t+4 1.45t+4 4.18t+3 1.16t+5 Cs 137 9.071+5 t 23t+5 - 2.82t+5 1.04t*5 .3.?2t+3 1.28t+5 Cs 138 6.33t+2 8.40t+t - 6.22t+2 6.81t+1 2.70t+2 5.iSt+2 8*.-139 1.84t+0 9,84E 4 - 8.42E-4 5.77t+3 5.77t*4 5.37t 2 8e 140 7.40t+4 6.48t+1 - 2.11t+1 1.74t+6 1.02t+5 4.33F43 ,84-141 1.9M 1 1.096 4 - 9.47t 5 2.92E+3 2.75E 2 6.3M !

l Bs <.2 5.00E 2 3.60t 5 - 2.91t 5 1.6463 2.744+0 2.79t-3

(

.a 140 6.44t+2 2.25E+2 - - 1.8365 7.:2t+5 T.55t+1 f

ts 142 1.30E+0 4.11t 1 . . 8.70E*3 7.5M*4 1.29t 1 Co 141 3.92td 1.95t+4 - 8.55t+3 5.44t+5 5.6M4 2.90t+3 Ce-143 3.66t+2 1.999 2 8.3M+1 1.15t+a 1.27t+9 2.87t+1

'Co 144 6.77D6 2.12t+6 - 1.17t+6 1.20t+7 3.89t+5 3.6te+5 i

Pr*143 1.45t+4 5.55E+3 - 3.006 3 4.33t*5 9.73E+4 9. ' 4D 2 l

Pr 144 5.96E 2 1.85t 2 - 9.77t 3 1.57t+ 3 1.97t+2 3.001-3 44-147 1.082 4 8.73t+3 - 4.81t+3 3.28t+5 8.+1t4 6.81t*2 W 187 1.63t+1 9.64 +0 - - 4.ttt+4 9.10t< 4 4.33E+0 mp.239 4.66t+t 3.34t+1 - 9. 73E + 1 5.81t.4 S.40t+6 2.31D 1 Davis-Besse ODCM 72 Revision 5

1 Table 3-7 (continued)

Rg, Inhalation Pathvay_ Dose Fagtors - INFANT (mrem /yr per uCi/m )

Nuclide Bone Liver thyrou Ki&wy Lwg GI LLI f Body N3 -

6.47t + 2 6.47t+2 6.47E+2 6.47E +2 6.47t+2 6.47E+2 C 14 2.65E+4 5.31E*3 5.31E+3 5.311+3 5.31E+3 5.31E+3 5.31E+3 No 24 1. 0S.+4 1.06E+4 1.06E+4 l.06E+4 1.06t+4 1.0M+4 1.06E+4 P 32 2.03E+6 1.12t+5 * - -

1.61E+4 7.74E*4 cc-51 - -

5.75E . 1.32E+1 1.2SE+4 3.57E + 2 8.95E+1 mn 54 -

2.53E+4 -

4.98E+3 1.00E+6 7.06E+3 4.98r 3 Mn 56 -

1.54E+0 -

1.10E +0 1.23E+4 7.17E+4 2.211 1.

Fe 55 1.97t+4 1.17E+4 - -

8.69E+4 1.09E+3 3.33E+3 Fe 59 1.36t+4 2.35E+4 - -

1.02E+6 2.48E+4 9.4M +3 co 57 -

6.51E+2 - -

3.79E+5 4.86E+3 6.41E+2 Co 58 a 1.22E*3 - -

7.77E+5 1.11E+4 1.82E+3 co 60 -

8.02E+3 - -

4.51E+4 3.19E+4 1.18E+4 NI 63 3.39E+5 2.6.E+4 - -

2.09E+5 2.42E+3 1.16E+4 Ni 65 2.39t+0 2.ME 1 - -

8.12E+3 5.01F.+4 1.23E 1 Cu 64 -

1.28E+0 -

3.98E+0 9.30E+3 1.50E+4 7.74E.1 2n 65 1.93E+4 6.26E*4 -

3.25E+4 6.47E+5 5.14E+4 3.11t+4 2n-69 3.39E 2 9.67E 2 -

4.02E 2 1.47t+3 1.32E+4 7.18E 3 Br 82 - - - -' - -

1.33E+4 tr-83 - - - - - -

3.L1E+2 3r-64 - - - - -

4.00E+2 Br 85 - - - - - -

2.04E+1 ab-t6 - 1.90E+5 - - - 3.04E+3 8.82E+4 Rb E3 -

5.57t+2 - - -

3.39E+2 2.87t+2 Ab 89 -

3.212+2 - - - 6.82!+1 2.06E+2 tr-89 3.98t+5 - - -

2.03E+6 6.40E+4 1.14E+4 sr 90 '4.09E+7 - - -

1.12E+7 1.31E*5 2.59t+6

- sr 91 9.5M +1 - - - 5.26E+4 7.34E+4 3.46E+0 sr-92 1.05E+1 - - -

2.38E+4 1.40E+5 3.91E-1 Y 90 3.29E+3 - - - 2.69E+5 1.04E+5 8.82E

1

!-- Y 91m 4.07E 1 - - -

L.%3 2.35E+3 1.391 2 Y 91 5.82E+5 - - -

2.45E+6 7.03E+4 1.57E+4 l

Y 1.64E+1 - - - 2.45E+* 1.27E+5 4.61E-1 Y-93 1.50E*?, . - -

7.64E+4 1.67t+5 4.07t+0 Zr 95 1.15E+5 2.79E+4 -

3.11E+4 1. 75 E +6 2.17E+4 2.03E+4 2r 97 1.50E+2 2.56E+1 -

2.59E+1 1.10E+5 1.40E+3 1.17E+1 l .. Nb-95 1.57E+4 -6.43E+3 - 4.72E+3 4.79E+5 1.27E+4 3.78E+3 l hb-97 3.42E 1 7.29E 2 5.70E-2 3.32E+3 2.69E+4 2.63E-2 No.99 -

1.65E+2 -

2.65E+2 1.31E+5 4.87E+4 3.2M

1

! Tc-99, 1.40E 3 2.887 3 -

3.51E 2 8.11E+2 2.03E+3 J.T2E-2 l- Davis-Besse ODCM 73 Revision 5 h

l

e

']

. 1 i- , . .

Table 3 7 (continued).

. cont.) If Rg ,, Inhalation ~ Pathvay (mrem;Do::e/yr perFactorsuCi/m 3)INFAN*

j Wuctide Bene Liver fayroid Eldrwr. .L.es...

st tLt. .......

...... T.sedy l

Tc 101 6.51t 5 s.23t 5

9.79E 4 5.84t*2 8.44 + 2 8.121 4

~

89-103 2.C2t+3 - - 4.24E+3 5.52t+5 1.61t+4 6.79t+2

-ava05 1.21t+0 - - 8.991 1 1.57t+4 4.84t+4 4.10E 1 av 106 8.64t+4 - - 1.0M+5 1.1M+7 1.64t+5 1.09t+4 th 103e . . .+ - - -

Rh 106 * * * - * *

Ag 110m 9.90t+3 7.221*3 - 1. 00t +'. 3.6M +6 3.30E+4 5.0003 to-124 3.79e+4 5.5M+2 1.01t+2 -

2.65t+6 5.91t+4

40E+4

. i 56-125' 5.1M+4 4.77t+2 6.EE*1 -

1.64t+4 1.47t+4 1.09t+4 fe 125e 4.7M *3 1.99E+3 1.62t+3 -

4.47t+5 1.29t+4 6.5aE+2

-fe.127m 1.6M +4 6.902+3 4.8M+3 3.75t** 1.31t+6 2.7M+4 2.07t+3 Te 1P 2.23t+0 9.5M 1 - 1.85t+0 4.8M+0 1.0M+4 2.44 4 4.89t 1 te 129m 1.41t+4 6.09t+3 5.4M+3 3.18E+4 1.6.;E+4 6.90t4 2.23E+3 fe 129 7. set 2 - 3.4M 2 6.75t 2 1.75E 1 3.00t+3 2.6+.t+4 1.ast 2 fe Itte 1.07t+2 5.50E+1 8.93f+1 2.65E+2 1.99E+5 1.19f+5 3.63E+1 fe 131 _1.744-2 e.221 3 1.58E 2 3.99E 2 2.06E+3- 8.22E+3 .5.00E 3 Te 132 -3.778.+2 2.37t+2 2.79t+2 1,03E+3 3.40E+5 - 4.4184. 1.7M+2 1 130 6.36t+3' 1.39E 4 1.60t*4 1.5:E+4 - 1.99E+3 5.5M+3 1 131 3.79E+4 4.44E+4 1.44E+7 5.NE+4 - 1.0M+3 1.9M+4 t 132 1.69t+1 3.544*3 1.69t+5 3.95E+3 .

1.90E 1- 1.26t+3

-I 133 - ~ 1.3214 1.92t4 . 3.5M+4 2.24E+4 -

2.16E+3 5.60t+3 I' I 134 9.21t+2.1.8aE+3 4.45E+4 2.09E+3 - 1 29t+3 6.65t+2 1 135 - . 3.8M+3 7.ME +3 6.9M +5 8.47t+3 - 1.83t+3 2.7M+3

!- cs 134 3.9M*5 ~7.0M45 ~ - 1.90t+5 T.77E+4 1.3M+3 7.45t+4 -.

Ca 136 4.8M4 1.35t+5 - 5.64 4 1.18t+4 1.43E+3 5.29t+4 cs 137 5.4 m 5 6.12t+5 - 1.72t+5 7.1M4 - 1.33E+3 - 4.55t+4 Cv138 5.05E+2 7.81E+2 - 4.10t+2 6.5M +1 8.76t+2 3.9M+2 e

.se-139 * .4aE+0 9.648 4 -

5.92E 4 5 7M+3 5.10E+4 4.30E-2 to 140 3.60t4 5.60t+1 - -- 1.34E+1 1.60E+4 3.84E+4 2.90E)3 i -

+ .. .

se 141 - 1.575 1 1.Det 4 -

6.50E 5 2.97t+3 4.75t+3 4.975 se.142 3.9et 213.30E-5 - 1.90E 5 1.**AJ 6.93E+2 1.9M-3 La 140 4.05E.2 2.00E+2 +

1.60t+5 8.4aE+4 5.15t+t La-142 1.r!3t+0 3.77E 1 - - 8.22E+3 5.95E+4 9.04t 2 Oe 141 -2.77t+4 1.67t+4 5.25E+3 5.1M +5 2.1M+4 1.99E+3 to 143 2.93E+2 1.93d+2 -

5.64C+1 1.1M+5 . 4.97t4 2.21t+1 ce.144L ~3.19t+6- 1.21t+6 - 5.3M+5 9.84E+6 1.4at+5 1.7M+5 ,

is >

.pr-143. 1.40t4 5.2M+3 - 1.97t+3 4.33E+5 3.72E+4 6.99t+2 Pr.144 -4.795 2 _1.85t 2 . 6 T28 3 1.61t+3 4.25E+1 2.41E 3 ad 147 - 7.94t+3 8.13t+3 . 3.158+3 3.22t+5 3.12t+4 5.00E+2 -

i

-W-187 1.30t+1 9.02T+0 - - 3.96C+4 3.5M+4 3.121+0 r

up-239 3.71t +2 3.32t+1 - 6.62t+1 5.95t4 2.49t+4 1.8aE+1 i= Davis-Besse ODCM 74 Revfsion 5-t n

r P .5

/v ,4, , . , , , ,

Table 3-8 R gg. Grass - Cow - Milk Pgthway Dose Tactors . ADULT (mgem/yr per uCi/m ) for H-3 ar,d C-14 (m

mrem /yr per pCi/sec) for others Wuctide tore Liver Thyroid Eldwy Leg GI LLI T. Body H3 -

7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C 14 3.63E+5 7.;6E+4 7.2M +4 7.26E+4 7.26E+4 7.26E+4 7.26C+4 me.24 2.54E+6 2.54t+6 2.54E d 2.54E +6 L54E4 2.54E+6 2.54E+6 P ': 1.71E+t0 1.0M+9 - - -

1.92E+9 6.60E+8 Cr 51 - ---

1./1E+4 6.30E *3 3.80E+4 7.20E+6 2.86E+4 .

un-34 -

8.40E+6 -

2.50E+6 -

2.57E+ 7 1.60E+6 Mn-56' -

4.23E-3 -

5.38E 3 -

i.35E 1 7.51E 4 Fe 55 2.51E*7 1.73E*7 - -

9.67E+6 9.95E+6 4.04E+6 Fe 59 2.98E+7 7.00E+7- - -

i .95E+ 7 2.33E+8 2.68E+7 Co 57 -

1.28E+6 - - -

3.25E+7 2.13E+6 Co 58 -

4.72E+6 - - -

9.571+7 1. Ac+i co 60 -

1.64E+7 - - -

3.08E+8 3.62E+7 Ni-63 6.73E+9 4.6M + 8 - - -

9. ~3E + 7 2.2M +8 Wi 65 3.70E 1 4.81E 2 - - -

1.22E+0 2.19E 2 Cu-64 .

2.41E+4 -

6.08E+4 -

2.05E+6 1.13E+4 2n 65 1.37E+9 4.3M+9 -

2.92E+9 -

2.75E+9 1.97E+9 Zn-69 - - - - - - -

Br 02 - - - - - -

3.72E+7 3.25E+7 tr 83 - - * * -

1.49E-1 1.03E 1 4 gr.s4 . . . . . . .

Sr 85 ~ - - -

( Rb 86 - 2.59E+9 - -

l -.

5.11E+8 1.ZsE+9 ab-88 - - - - - - -

Ab f? - - * * - - -

Sr 89 1.45E+9 - - - -

2.33E+8 4.16E+ 7

$r 90 4.68E+10 - - - -

1.35E+9 1.15E+10 Sr 91- 3.13E+4 - - - -

1.49E+5 1.27E+3 tr 92 4.89E 1 * - * -

9.6aE+0 2.11E 2 Y 90 7.07t+1 * * *-

7.50E+5 1.90E+0 y.9te . . . . . . .

Y 91 8.60E+3 - - * -

4.73E+6 2.30E+2 i Y 92 5.42E 5 - - - -

9.49E 1 1.58E 6 Y 93 2.33E-1 - - - -

7.39E+3 6.43E 3 2r-95' 9.4M+2 3.03Z+2 -

4.7M+2 -

9.62E+5 2.05E+2 L- Zr-97 4.2M 1 8.59E-2 -

1.30E-1 -

2.66E+4 3.93E 2 L Nb-95 8.25E*4 4.59E+4 -

4.54E+4 -

2.79E+8 2.47t+4 Nb-97 - - - - -

5.47E-9 -

Mo-99 -

t.52E+7 -

5.72E+7 5.85E+7 4.80E+6 fc 99's 3.25E+0 9.19E+0 -

1.40E+2 4.iOE*0 5.44E+3 1.17E+2 Davis-Besse ODCM 75 Revision 5 f,

Table 3 R 39, Grass-Cov.-HilkPathvgyDoseFactors ADULT (cont.)

(mjem/yr per uCi/m ) f or 11-3 and C-14 (m

mrem /yr per uC1/ rec) for others mucude Sor Liv + thyr.ie riewr. . tm

....... ....... ....... ....... ...... ...e..

st.Lu f.soor.

fc 101 . - * * . -

Re103 1.02E+3 +

3.89E+3

1.19E+5 4.39E+2 au 105 8.57E 4 . - 1.11E*2 -

5.24E 1 3.38E 4 tv 106 2.04t * . - 3.94E+4 -

1.32E+6 2.58t+3 th.103a . . * * . . .

th 106 - - - - + a

a 1.06E+8 A9 110m 5.83E+7 5.39E+7 -

2.20E+10 3.20E+7 tb-124 2.57E+7 4.8M *5 6.24E4 -

2.00E*7 7.31E+8 1.02E+7 tb 125 Z.04E+7 2.28E+5 2.08E 4 1.58E+7 2.25E+8 4.8M4 Te 125e 1.632+7 5.90E+6 4.90E+6 6.63E*7 -

6.50E+7 2.18E+6 Te 127m 3M* 7 1.64E

7 1.17E+ 7 1.8M+8

1.54E+8 5.58E 4 fe 127 6.P ' 2.41E+2 4.90E+2 2.7'i+3 -

5.30E+4 1.45E*2 Te-129m o.04E+ * ?.25E+7 4. * =1 . 52E*8 -

3. kt+8 9.57E+6 Te 129 - - - -

te 131m 3.61E+5 1.77E +5 2.80E+5 1.79E*4 -

1.75E+7 1.47E+5 a - .

fe-131 . * * .

te'132 2.39E+4 1.55E4 1.71E4 1.49E+7

7.32E+7 1.45E4 1 130 4.2M+5 1. 2M +6 1.07t+8 1.96t+4 - 1.08E+4 4.9M+5 1 1*1 2.9M+8 4.24E+8 1.39E*11 7.27E+4 + 1.12E+8 2.43E+8 1 132 1.645 1 4.37E-1 1.53E+1 6.97E 1 - 6.22E 2 1.43E-1 1 133 3.97E+6 6.90E 4 1.01E+4 1.LCE+7 . 6.20E+4 2.10E+4 t-134 * - -

1 135 1.39E4 3.63E+4 2.40E+6 5.83E+4 -

4.1sE4 1.34E+4 Cs 19 5.65E+9 1.34E+10 . 4.35E+9 1.44E+9 2.35E-8 1.10E+10 ca*136 2.61E+8 1.c31+9 - 5.74E+6 7.87E*7 1.17E+8 7.42E+8 Ca 137 7.30E+9 1.01E+10 - 3.43E+9 1.14E+9 1.95E+8 6.61E+9 Ca*138 - .

Sa 139 4.7DE.8 - - - -

8.345 8 1.38E-9 is 140 2.69E+7 3.38E4 - 1.15E4 1.93E4 5.54E+7 1.7M4 Sa 141 - -

+

Re 14' . . . -

La 140 4.49E+0 2.26E+0 - - 1.6M+5 5.97E-1 La-142 - - * * - 3.03E 8 -

Ce 141 4.84E+3 3.27E+3 - 1.52E*3 -

1.25E+7 3.71E+2 C4 143 4.19E+1 3.09E+4 - 1.3M +1 -

1.1M+6 3.42E+0 Ce 144 3.58E*5 1.50E+5 - 8.87E4 -

1.21E+4 1.92E+4 i

' Pr 143 1.59E*2 6.37E+1 - 3.68t*1 - 6.964+5 7.88E+0 pc.144 . . .

m4 147 9.42E+t 1.0M*2 - 6.37E*1 -

5.23E+5 6.52E4 W 187 6.56E+3 5.4M+3 - - -

1.80E 4 1.92E*3 up-239 3.66t+0 3.ect 1 + 1.12E+0 -

7.30E+4 1J JE i E Davis-Besse ODCM 76 Pevicion 5 l-l -.

m Table 3-8 (continued)

~

R gg, Grass-Cov-MilkPatgvayDoseFactors-TEENAGER (ms,em/yr per uC1/m > ior !!-3 and C-14

-(m'

mrem /yr per uC1/r.ec)-for others Nuctide Bone tiver Thyroid ticbey L Cl tLI

....... ...-.. ....... ....... .. .... ..a..... ....... T.So#...

N3 -

9.a't+2 9.94E+2 9.94t+2 9.94t+2 -9.94t+2 9.HE*2 C 14 6.70t*5 1.34t+5 1.34t*5 1.34t*5 1.34E+5 1.34t+5 1.34t+5 Na i. 4.44t*6 4.44t+6 4.44t*6 4.44t+6 4.44t+6 4.44t+6 4.44E+6 P-32 3.15t+10 1.95t+9 - - - 2.65E+9 1.22t+9 Cr 51 - . 2.78t+4 1.10t+4 7.13E+4 8.40t+6 5.00t+4 m 54 - 1.40t+1

4.17t+6 - 2.87t+7 2.78t+6 m 56 -

7.51t 3 - 9.50E 3 - 4.94t 1 1.33t-3 Fe 55 4.45c+7 3.* M+ 7 - -

2.00t+7 1.37t+7 7.36t+6 Fe 59 5.20E*7 L .E+8 a - 3.82E+7 2.87t+8 4.68t+7 to 57 - 2.25t*6 - - - 4.19t+7 3.76t+6 Co 58 - 7.95t+6 - - -

1.10t*8 1.83t+7 to 60 - 2.722+7 - - - 3.621*8 6.26t+7 Ni 63 1.18t+10 8.35t+8 - - -

1.33t+8 4.01t+8 kl 65 6.78t 1 8.66t 2 - - - 4.70E+0

94E 2 Cu 64 < 4.29t+4 -

1.09E*5 - 3.33f+6 2.02t+4 2n 65 2.11t+9 7.31E+9 - 4.68t+9 - 3.10t+9 3.41t+9 2n 69 -

sr 82 - - - * - -

5.64t+7 er 83 * * - * * - 1.91t 1 er-84 -

gr.g3 ab-86 - 4.73E+9 - - - 7.00t+8 2.22t+9 Rb 88- -

Rb 89- -

$r 89 2.67t+9 - - - - 3.18t+8 7.66t+7 tr-90 6.61E+10 - -- -

1.86t+v 1.63E+10 sr 91 5.75t+4 - - - -

2.61t+5 2.29t+3 tr 92 8.95t 1 - - - - 2.28t+1 3.8tt 2 Ta90 1.30t+2 - - - - 1.07t+6 3.50t+0 y.91. . .

Y 91 1.58t+4 - - - - 3.48t+6 4.242+2 Y 92 1.00E 4 - - - -

2.75t+0 2.90E 6 T 93 4.30t 1 - - - - 1.31t+4 1.18t 2 2r 95 1.65t+3 5.22E+2 - 7.67t+2 - 1.20E+6 3.59t+2 2r+97 7.75E 1 1.531 1 - 2.32C 1 - 4.15t+4 7.06t-2 Mb 95 1.41t+5 7.80E*4 - 7.57t+4 - 3.34t+8 4.30t+4 kb-97 - - - - - 6.342 8 -

me 99 - 4.56t+7 -

1.04E+8 - 8.1M + 7 8.69t+6 e5-99m 5.64t+0 1.57t+1 -

2.34t*2 8.73t+0 1.03t+4 2.04E+2 Davis-Besse ODCM 77 Revision 5

t I

Table 3-8 (continuod)

R gg, Grass - Cov - Milk Pathway) Dose Factors - TEENAGER (cont.) ,

(mgem/ g per UC1/m ) for H 'l and C-14 (m

mrrm/yr per UCi/sec) for others buctide tone Livw Ybyroid IIemy LW Glatti 7.f sdy fc 101 * - - *

Ru-103 1.81t+3 * - 6.40t+3 a 1.52t+5 7.75t+2 29 105 1.571 3 - - 1.97t*2 - 1.26t4 6.08t 4 tw toe 3.73t+4 * - 7.23E 4 -

1.808 4 4. 7t + 3 th=103m - - - . .

th 106 - * - * - - -

4g 110m 9.63t*T 9.11t*? - 1.74E +8 -

2.56t+10 5.54t+ 7 sb-124 4.59t+7 8. 4M

5 1.04t+5 -

4.01t*T 9.25t+8 1.79t+7 tb 125 3.65t + 7 3.99t+1 3.49t+4

3.21t*7 2.84C+8 8.54t4 f e 125m 3.00t+T 1.08t*F 8.39t4 - - 8. 8M + T 4.02t+4 fe 127a 8,44t+7 2.99t+F 2.0i!+7 3.42t+8 .

2.10t+8 1.00t+7 fe 127 1.24t+3 4.41t+2 8.5M+2 5.04t+3 -

9.618 4 2.6M + 2 fv129m 1.11t+8 4.10t+7 3.571+T 4.62t+8 - 4.15t+8 1.75t + T Te.129 . . - 1.671 9 .

2.18t-9 .

fe 131m 6.5M+5 3.15t+5 4.74t+1 3.29t+6 -

2.53k.T 2.63e5 te 131 . - - . - -

fe 132 4.28t+6 2.71t+e 2.86t4 2.60t+T - 8.58t+7 2.55t+6 1 130 7.49t+5 2.17t+6 1.77t+8 3.34t+6 - 1.6M +6 8.668+5 l*131 5.38t+8 7.53t+8 2.20t+11 1.30t+9 -

1.49t+4 4.04t+8 1 132 2.90E 1 7.59t 1 2.mit+1 '.20t+0

3.314 1 2.721 1

. 133 7.2t.E+6 1.234+7 1.72t+9 2.15t+7 - 9.30t+6 3.75t4 g.134 - * - - - -

I 135 2.47t+4 . . Jt +4 4.088 4 1 00t+5

7.03t 4 2.35E+4 Cs 134 9.81E+9 2.31t+10 -

7.34t+9 2.80t+9 2.87t+8 1.0M+iG ts 136 4.45t+8 1.75t+9 -

9.53t+8 1.50t+8 1.41t+8 1.18t+9 Cs 137 1.34t+10 1.78t+10 - 6.06t+9 2.35t+9 2.53E+8 6.20t+9 Cs 138 -

Sa 139 8.69t-8 - * *

7.75E T 2.f1E 9 Sa 140 4.85t+7 5.95t+4 -

2.02t+4 4.00t+4 7.49t+F 3.13E+6

* - - - 4 8s 141 - .

8a 142 -

La 140 8.0M 4 3.9M +0 - - - 2.27t+5 1.05t+0 te 143 . - - - - 2.25t-7 -

Co 141 8.87t+3 5.92t+3 - 2.79t+3 -

1.69t+7 6.81t+2 Co 143 F.69t+1 5.60E+4 - 2.51E+1 - 1.68t+6 6.25t+0 te-144 6.58t+5 2.72t+5 - 1.63t+5 - 1.6M

8 3.54t+4 Pr.143 2.921*Z 1.17t+2 - 6.77t+1 -

9.61t+5 1.45t+1 pr.144 .

ud 147 1.81t+2 ).97t+2 + 1.16t+2 -

7.11t+5 1.18t+1 W 187 1.20td 9.78t+5 - - -

2.65'+6 3.43t+3 wo 239 6.99t+0 6.59t 1 - 2.07t+0 -

1.06t+5 3.6M 1 Davis-Besse ODCH 78 Revision 5

. .- ~ . ._- . . - - . - -

t Table 3 8 (continued) g R ,, Grass - Cov - Milk Pg)thway (mgem/yr per uCi/m for HDose 3 andFactors C CHILD (m

mrem /yr oer uC1/sec) for others Nuctide Bone Liver thyroid Eldwy Lmg Gl.LLI T . 8tay N3 -

1.57E 3 1.57t+3 1.5M+3 1.57E+3 1.57E*3 1.5 7E *3 C 14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 ma 24 t.23E+6 9.23E+6 9.23E+4 9.23E+6 9.23E+6 9.23E+6 9.23E+6 P 7,1 7.77E+10 3.64E+9 - - -

k.15E+9 3.00E*9 Cr 51 * -

5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 Mn 54 - 2.09E+7 -

5.87E+6 -

1.76t+7 5.58E+6 mn-56 -

1.31E 2 -

1.38E 2 -

1.90E+0 2.95E 3 Fe 55 1.12E+8 5.93E+7 - -

3.35E+7 1.10E*7 1.84E+1 f e 59 1.20E+8 1.95E+8 - -

5.65E+7 2.03E*8 9. 71E + 7 Co 57. - 3.84E+6 * - -

3.14E+7 ?.77E+6 to 58 -

i.21E+7 - - -

7.08E+7 3.72r -

co 60 - 4.32E*7 - - -

2.39E *8 1.27E*8 ul 63 2.96E+10 1.59E+9 * * -

1.0TE 8 1.01E+9 Ni 65 1.6eE+0 1.56E 1 - - -

1.91"+1 9.11E 2 Cu-64 -

7.55E+4 - 1.82E+5 -

3.54E+6 4.56E*4

' Zn 65 4.13E+9 1.10E+10 - 6.94E+9 -

1.93E+9 6.85E+9 2n-69' = * - - -

2.14E * .

Br 82 - - - - - - -

1.15E+8 Br 83 - + - * * -

4.69E*1 Br 84 - - - - - - .

gr 85 - - - - - - -

Rb 86 - 8.77E+9 - - - 5.64E+8 5.39E+9 Rb 88 - - - - - -

Rb-89 * ' * -

sr 89 6.62E+9 - - - -

2.56t+8 1.89E+8 sr 90 1.12E+11 - - - -

1.51E+9 2.83E+10 tr 91 1.41E+5 - - - - 3.12E+5 5.33E+3 Sr-92 2.19E+0 - - - -

+.14E+1 8.76E 2 Y-90 3.22f+2 - - - - 9.15E+5 8.61E+0 g.91. . . . . . . .

Y 91 3.91E++ - - - -

5.'.it e 1.04E+3 Y + 92 . 2.45E 4 - - - -

7.10E+0 7.03E 6 Y 93 -1.06E+0 - - - -

1.57E+4 2.90E 2 2r 95 .3.84E+3 8.45E+2 - 1.21E+3 -

8.81E+5 7.52E+2

=

2r 97 1 89E+0 2.72E 1 -

3.91E-1 - 4.13E*4 1.41E 1 kb-95 3.18E+5 1.24E+5 - 1.16E+5 - 2.29E+8 8.84E+4 kb 97 - - - -- - 1.45E-6 -

Mo 99 -

8.29E+7 - 1.77t+8 - 6.86E+7 2.05E+1 fc 99m 1.;b e 2.54E+1 - 3.68E+2 1.29E+1 1.44E+4 4.20E+2 Davis-Besse ODCM 79 Revision 5 o

s. Table 3-8 (continaed) r R yg, Grass - Cov - M11k.Pathv3y Dose ac;)rs - CHILD (cont.)

(mges/yr per uCi/m ) for H-3 and C-14 (m'

mrem /yr per pCi/sec) for-others Wctide tone Liver- Thyre 14 Eldru - tw GI LLI f .Seck fc 101 * * - - - - -

tv 103 4.29t+3 .

1.08E+4 a 1.16t+5 1.65t+3 29-105 3.82t 3 - -

3.3M V =

2.49t+0 1.39t 3 tu 106 5.24t+4 - -

1.25t+5 - 1.44t+4 1.15t+4 th 103e . . . . . . .

th 106 . . . . . . ,

At 110s 2.09t+L 1.41t+8 -

2.63t+8 -

1.6.9E+10 1.13t+8 tb 124 1.09t+8 1.41g+8 2.40t+5 -

6.03t+7 4.79t+8 3.81E+7 Sb 125 8.70t+7 1.41t+4 8. 04t+4 -

4.85t + / 2.0aE+8 1.82t+7

_g fe 125e 7.38E + 7 2,00E+7 2.07t+7 - -

7.12t*7 9.84t+6 fe 127m .2.08E+8 5.60E + 7 4 t't+7 5.93t+8 -

1.68E+8 2.41t+7 fe-127 3. 0t4 *

8.25t+2 2.12t+3 8.71t+3 .

+ 20E+5 6.56t+2 l

fe 129e 7.72t+8 7.61t+7 8.?tt+7 8.00E +8 -

3.321*8 4.23t+7 i

fe 129 - - -

2.87E-9 -

d.12E.8 .

fe 131e 1.60t+4 5.53t+5 1.14t+4 5.35t+6 -

2.24f+7 5.89t+$

fe.131 . . . . . . .

Te 172 1.02E+7 4.52t+6 6.58E+6 4.?0E+7 -

6.55L+7 5.4M+4 I 130 1.75t +6 3.54t+4 2 90t+8 5.a1E+6 -

1.6M +6 1.82t+4 I 131 1.30t+9 1.31t+9 4.34t+11 2.iSt+9 -

1.17t+8 7.4M+8 I 132 6.8M *1 1.2M+0 5.85f+1 1.934+0 -

1.48E+0 5.80E 1 1 133 1.74 +7 2.18t + 7 4.04t+f 3.63E+7 -

8.77t+6 8.23t+4 l _ -- 1 134 - . . - * - .

!*135 5.84t +4 1.05E+5 9.30E+4 1.61E+5 -

8.00E+4 4.97t+4 Cs 134 2.26t+10 3.71t+10 -

1.15t+10 4.13t+9 2.00E+r 7.83E+9 Cs 134 1.00E+9 2.7M +9

1.47t+9 2.19t+t 9.7DE+r 1.79E+9 Co 137 3.22t+10 3.09E*10 -

1.01t+10 3.62E+9 1.934+8 4.55E+9 Cs 138 . . - - . - -

l- 8a 139 2.144-7 - - * .

1.238 5 6.19t 9 l

84 140 1.17t+8 1.03t+5 + 3.34t+4 4.12t+4 5.94t+7 6.84t+4 Be 141 = . - * -

Ba 142 * * - * * * +

La 140 1.93t+1 6.74t+0 - . -

1.8aE+5 2.271+0 ts 142 - a a - - 2.51E-6

Co 141 2.19t+4 1.09t+4 - 4.78E+3 -

1.3M+7 1.621 1 Co 143 1.89t+2 1.02k+5 -

4.29t+1 -

1.50E:* + 'dE+1 Ce-144 1.62t+6 5.09t+5 . 2.82t+5 -

1.33t+8 8.66t+4 Pr 143 7.23t+2 2.17t+2 -

1.17t*2

7.80E+5 3.59E +1 pr.144 . . . - . . -

ud-147 4.45t+2 3.60t+2 - 1.uaE+2 -

5.71t+5 2.79t+1 W 187 2.91t+4 1.72t+4 - - -

2.42t+4 7.73t+3 up-239 1.721 1 1.23E+0 -

337t+0 - 9.14E*4 8.6M 1 Davis-Besse ODCH 80 Revision 5

Table 3-8 (continued)

Rg, Grass-Cov-MilkPaghvayDoseFactors-INFART

-(mgem/yrperUC1/m) fer H-3 and C-14 (m

mrem /yr per UCi/sec) for others Nuctide tone Liver thyroid Eldney (mg ct LLI 1.Sody M3 -

2.38t+3 2.38t+3 R.38E+3 2.38D 3 2.38D3 2.38E 3 C 14 3.23E*6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.8W+5 6.89E+5 us 24 1.61E+7 1.61E*7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 P 32 1.66E+11 9.42E+9 - - -

2.17E+9 6.21E*9 cc 51 - -

1.05E4 2.30E+4 2.0$E+5 4.71E+6 1.61E*5 W 54-

3.89E+7 - 8.63E+4 -

1.43E*7 8.83E+6 Mn 56 -

3.21E t - 2.7M 2 -

2.91E+0 5.53E 3 fe-55 1.35E+8 R.72E*7 - -

4.27E*7 1.11E+7 2.33E+7 f e 59 2.25E+8 3.93E+8 - -

1.1M* 8 1.88E+8 1.55E+8 co 57 - 8.95E+6 - - -

3.05E+7 1.46E*7 Co 58 - 2.43E+7 - - -

6.05E+7 6.0M+7 Co 60 -

8.81E+7 * - -

2.10E+8 2.08E*8 Wl-63 3.49E*10 2.1M +9 - - - 1.07E+8 1.21E*9 Ni 65 3.51E+0 3.97E 1 - - - 3.02E+1 1.31E 1 Cu-64 - 1.88E+5 -

3.17E*5 - 3.85E+6 8.69E+4 2n 65 5.55E+9 1.90E+10 - 9.23D 9 -

1.61E*10 8.78E+9 2n 69 - - - - - 7.36E-9 -

Ir 82 - - - - - - 1.94E+8 Ir-&3 - - - - - -

9.95E 1 Er.84 . . . . - . .

Ir 83 - - - - - - -

Itb 86 - 2.22E+10 - - -

5.69E+8 1.10E+10 Rb 88 - - - - - - -

RD 89 - - - - - - -

$r 89 1.2M+10 - - - -

2.59E+8 3.61E+8 5r 90 1.22E+11 - - - -

1.52E 4 3.10E+10 sr 91 2.94E+5 - - - - 3.48E+5 1.0M+4 tr 92 4.65E+0 - - - -

5.01E+1 1.73E 1 Y 90- 6.80E+2 - - - -

9.39E+5 1.82E+1 Y 91e - - - - - - -

!! Y 91 7.33E+4 - - - - 5.2M+6 1.95E+3

- Y 92 5.22E 4 - - - -

9.97E+0 1.47E-5 Y-93 2.25E+0 - - - -

1.78E+4 6.13E 2 p 2r 95 6.83E+3 1.6M +3 - 1.79E+3 - 8.2M+5 1.18E+3 l-

!~ 2r 97 3.99E+0 6.63E 1 - 6.91E 1 -

4.37E+4 3.13E-1 Nb-95 5.93E+5 2.44E+5 - 1. 75E+5 -

2.0M+8 1.43E+5 Nb 97 * * * * -

3.70E-6 -

Mo-99 -

2.12E+8 -

3.17E+8 -

6.98t+7 4.13E+7 l

Yc 99e 2.69E+1 5.55E+1 - 5.97E+2 2.90E+t 1.61E+4 7.15E+2 Davis-Besse ODCM- 81 Revision 5

x; ,

i,0 Table 3-8 (continued).

R io,. Grass-Cov.-HilkPathvey)DoseFactors-INFANT (mgem/yrperpC1/m .for H-3 and C (cont.)

-(m

mrem /yr per pCi/sec) for others- -

nuclide SJnB ~Llver Thyfeld .....

t i thwY.. Ll#1 Cl LLl I.8ady

....... ....... ....... ....... ... 8... ....... .......

Ic 101 * . - - - . .

sv 103 - 8.69t+3 - -

1.81E+4 -

1.0M* 5 2.91t+3 -

tw-105- 8.0H 3 * -

5.921-2 -

3.21t+0 2.714 3 tv 106 - 1.90t+5 - - 2.25t+5

1.44t+a 2.38t+4 th 103s * * * - - *

an.106 * = - - . . .

At 110m -3.8M*8 2.82t+8 - 4.03t*8

1.4M+10 1.8M +4 Sh 124 2.09t+8 3.0M +6 5.5H+5 - -

1.31t+8 6.4M *8 6.49t+7-tb-125 1.49t +8 1.45t+6 1.87t+5

9.343*7 1.99t+8 3.0 t+1

' s ~~

Te 125m 1.51168 5.04t + 7 5.07t+7 - -

7.18t+7 2.04t+7 Te 127m 4.21t+8 1.40t+8 1.222+8 1.04t+9 +

1.70E+8 5.10E*7 to-127 6.50D3 2.18t+3 5.29t+1- 1.59t+4 - 1.3M +5 1.40D3 fe 120m 5.59t+8 1.92t+4 2.15t+8 1.40f+9 -

3.3 t+8 8.62t+7 fe 129 2.093 9

1.75E 9 3.18E d + 1.6M 7 -

fe.131m 3.38t+6 1.361 4 2.7M+6 . 9.35t+6 -

2.29t+7-1.12t+6 te.131.- . . . . . .

Te 132 2.10pf 1.04t+7 1.54t+ 7 6.51t+7 -

3.85t*7 9.72t+6 l 130- 3.60t+6 7.92t+6 8.88h 8 8.70E+4 -

1.70E+4 3.1M*6 l 131 2.72E+9 3.21t+9 1.05t+12 3.75t+9 -

1.15t+4 1.41E+9

!=132 1.42E+0 2.49t+0 1.35t+2 3.22t+0 -

2.34t+0 1.03E+0 3 133 3.72t+7 5.41t+7 9.84t+9 6.3M+1 -

9.1M+6 1.58t+7-I.134 - -

1.018 9 + - - -

I-l I 135- 1.2tt+5 2.41t+5 2.144+1 2.69t+5 -

8.74t+4 8.80t+4 r .

--Cs=134 3.65t+10 6.80E+10

1.75t+10 ' 7.1M*9 - 1.85t+8 6.87t+9 Cs 136 - 1.9M+9 5.77t+0 -

2.30E+9 4.70E+8 4.7M+7 2.15t+9 Cs 137- .5.15E+10 6.02t+10 -

1.62t+10 6.55E +9 1.88t+8 4.27t+9 l- Ca 138 - +- * * * * *

84 139 4.55t 7 - - a

2.8st 5 1.322 8 44 140 2.41E+8 2.41t+$ -

. 5.73t+4 ' 1.48t+5 5.92t+7 1.24t+ 7 Se 141 . - - +- * * .

l-g Se 142 - - - - - - - .

b Le 140 -4.03t+1 1.59t+1 - *

1.37t+5 4.09t+0

, La 142 . - - -

5.215 6 -

l-F Co 141 4.33E+4 2.64t +4 - 8.15E+3 -

1.37t*7 3.11t+3 Ce 143 4.00t+2~2.65t+1 - 7.72t+1 -

1.55E+6 3.02E+1 Co 144 ' 2.33E+6- 9.52t+1 -

3.85E+5 -

1.33t+4 1.30E+5 Pe 143 1.49t+3 5.59t+2 - 2.08t+2 -

7.89t+5 7.41t+1 pr.144 . . . . . . . .

ud-147 8.82t+2 . 9.0M+2 - 3.49r+2 -

5.74t+5 5.55t+1 J 187 6.12t+4 4.2M + 4 - + -

2.5C4 +4 1.47t+4 40 239 3.64t+1 3.25t+0 - 6.49E*0 9.40E+4 1.84t+0 Davis-Desse ODCM- 82 Revision 5 i-li

Table 3-9 Rg ,, Grass - Cov - Meat Pgthway Dose Factors ADULT.

(mgem/yr per uCl/m ) for H-3 and C-14 (m'

mrem /yr per uCi/sec) for others tuc!!de gone . Liver thyroid Kichey Lmg GI-LLI t.8ody N3 -

3.25E+2 3.25E+2 3.25E+2 3.25E*2 3.25E*2 3.2*,E+2 C.14 3.33E+5 6.6M +4 6.66E+4 A.6M +4 6.66E+4 6.66E+4 6.66E+4 Na 24 1.84E-3 1.84E 3 1.84E 3 1.84E 3 1.84E 3 1.84E 3 1.84E 3 P.32 4.65E*9 2.89E+8 - - -

5.23E+8 1.80E+8 cr 51 - -

4.22E+3 1.56t+3 9.3M+3 1.78E+6 7.07E*3 Mn 54 -

9.15E+6 -

2.72E+6 -

2.80E+7 1.75E+6 Mn-56 -

Fe 55 2.93E+8 2.02E+8 - -

1.13E+8 1.16E+8 4.72E+7 Fe19 2.67E+6 6.27E*8 - -

1.75E+8 2.09E+9 2.40E+8 Co 5' -

5.64E+6 - - -

1.43E+8 9.37E+6 Co 58 - -1.83E+7 - - -

3.70E + 8 4.10E+7 Co 60 - 7.52E+7 - - -

1.41E+9 1.66E+8 Ni 63 1.89E+10 1.31E+9 - - -

2.73E+8 6.33E+8 gj.65 - - - - - - -

Cu-64 + 2.95E 7

7.45E 7 -

2.52E-5 1.39E-7 Zn 65 3.56E*8 1.13E+9 -

7.57t+8 -

7.13E+8 5.12E+8 Zn 69 - - -

Sr 82 - - - - -

1.44E+3 1.2M + 3 8r 83 - - - - - -

Sr 84 - - - - - - -

gr.g5 . . - . . - .

tb 86 - 4. 87E +8 - - - 9.60E+7 2.27E*8 tb-88 - - - - - - -

Ab 89 * - - -

sr 89 3.01E+8 - - - + 4.84E+7 8.65E+6 3r-90 1.24E+10 - - - - 3.59E+8 3.05E+9 tr 91 - - - -

1.38E-9 -

dr-92 - - - - - - - b Y 90 1.07E+2 - - - - 1.13E+6 2.86E y y.91. . .

Y 91 1.13E+6 - * - - 6.24E+8 3.03E+4 y.92 - -

y.93 . . . . . 2.08E 7 -

2r 95 1.8M +6 6.04E+5 -

9.48E+5 - 1.91E+9 4.09E+5 2r 97 1.83E 5 3.49E 6 - 5.58E-6 - 1.14E+0 1.69E 6 n-95 2.29E+6 1.28E*6 - 1.26E+6 -

7.75E+9 6.86E+5 ub-97 - -

Mo-99 - 1.09E*$ - 2.46t+5 -

2.52E+5 2.073+4 1c 993 - - -

Davis-Besse ODCM 83 Revision 5

?c

,I /

W&

a o"k IMAGd EVAL.U ATION QkN cs s, c'.

y'O . &a, ,. 'n a o' /,

j ' ,, & fg f TEST TARGET (MT-3) ,e z #

4N + / -

-c' 6-@3

\ %g, '

,y +

\x k;b 4 %[qv 4fl'/p

>a w x

4%^!c sq, 1.0 : F

~

m

~ z:

if lg w=2p j,l m l 1.8 llllWili l 1.25 I 1.4 'g I.6 i, i,___ w 4- -

150mm - >

4- 6" >

e&

%s. + A~' + ;

/A n:g"*.g;::

v j e

/[%

~ ~~~ ~

x 4 +p t , '# \

f i

oy'%

/

[

? ~Ci n .. ] __. , _ _ ,

Jd .p

/

g;.cb o . /O/

se %#, a6 e

, t ' 6, O % ' 4' v' IMAGE EVALU ATION

\//j/// ;, ' sh?

I/

- TEST TARGET (MT-3) e,8-:,'l? . #,,,

a 'h Q\

$?

~\ $+ gg ,, ;

$,/ .g, l.0 S ".

~

L m

,, .3 _-

u 5 l,l u m:-m till I.8 hlimv l.25 1.4 i j[en.6 u

150mm >

<- -6" -

l l

a- g ., ..

e g; g<yy , 4 /p4 o%,

/

ggO

\

/ .

y

n L-

~

,g --& ~s htl

0)

A '3 6 /-

$f ' k^

4 OW IMAGE EVALUATION / ' ,

s,,

9%

Y'g/f l : 43* TEST TARGET (MT-3)

/ f , N>, # # ,s 4 v

R(N'Ne -:::,',jsp

///' s qg), g

\ Q;k 'g[ g

'\fM 4g~

I.0 cP P i- u 2.2 u

L w

u:

L l,l m m' 2 .,

~

FUa 6 i 1.25 ! l.4 -

li I.6 l

l == ll ==

4 150mm >

< 6" >

4h.I" + M ANN

%~y, j/, 4>

& ,Cef 3>

~ ~ ' * "

.--- --~.

4) R$>

^

s ,x l .

t "s; g '

, Q S, -

,f p ,.g .a n Y ,,

4 l

jvg

l

?

(j/.*

j

?-

t

.< . . +

y

!- 4y *

{

y- ,

k_

D*-

Ja .. s , a %, ;w9 N.?b _ _

,/

Q>4 / g'0

w. .

vV,

@ s g%*

v9 i y, .

IMAGE EVALUATION #'# ,t %

O // ;,f[ ag

///// zX, i M " ' hf' 9,) TEST TARGET (MT-3) 7 NNk/.>ggh h/gg ,,,jh 9p g, l.0 i i

m; ;!!j =2 2 1:.. :

L !?!2.0 l,l LAsi a ts um i 1.25 l.4 1.6 l l' == m =s

150mm >

6" >

4.]

w b, b4 f+

Cf/ h ,> , ;,

g .

la$

. Y,// '[',/ ;h!* TEST TARGET (MT-3) h ,9g#'#;. 4, SIf' [ l.0 F" " O! 2o pses l,l Hi 1.8 1:\ =n ; l.25 l". l.4 L= li! 1.6b d 150mm > 6" > 4 [DI'D7P ($ p,s>\\\ .e %w; g Ajjj%y c -

T 2.62f+2 La 142 1.40E-6 6.35E 5 - - - 4.644 1 1.58E 5 Co 141 1.9M

5 1.33E+5 -

6.17t*4 - 5.0M +8 1.51E+4 Ce 143 1.00t+3 7.421*5 - 3.2W+2 - 2.77t +7 8.21E*1 Co 144 3.29t+7 1.38t+7 - 8.1M+6 - 1.11E+10 1.77t+6 Pr 143 6.34E+4 2.54E+4 - 1.47t+4 - 2.7BE+8 3.14E+3 Pr-144 - - - - - - - hd-147 3.34E+4 3. 8M +4 + 2.25t+4 - 1.85E+8 2.31E+3 w 157 3.82t+4 3.1&t+4 - - - 1.05E+7 1.12t+4 up 239 1.42f 3 1.40t+2 4. 37t + 2 1 67t + 7 7.72t+1 Davis-Besse ODCM 90 Revision 5 r l Table 3-10 (continued) Rg ', Vegetation Pathvay) Dose Factors - TEENAGER - (mgem/yr_perpC1/miforH-3andC-14 (m

mrem /yr per uC1/sec) for others Nuclide tone Liver thyroid Kl@ey - tmg cl.LL1 f.8ody M3

2.59E*3 2.59E+3 2.59E+3 2.59E*3 2.59E+3 2.59E+3 C 14 1.45E+6 2.91E+5 2.91E+5 2.91E*5 2.91E*5 2.91E+5 2.91E+5 Na 24 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E*5 2.45E+5 2.45E+5 P 32 1 61E+9 9.96E*7 - - -

1.33E+8 6.23E+7 Cr 51 - - 3.44E+4 1.3M +4 8.85E+4 1.04E+7 6.20E+4 Mn-54

4.52E+8 -

1.35E+8 - 9.i:E+8 8.97E+7 Mn 56 - 1.45E+1 - 1.83E+1 - 9.54E+2 2.58E+0 Fe 55 3.25E+8 2.31E+8 *

1.4M +8 9.98E+7 5.38E*7 f e 59 1.81E+8 4.22E+8 -

1.33E+8 9.98E+8 1.63E+8 -

Co 57 - 1.79E + 7 - - - 3.34E*8 3.00E*7 co 58 - 4.38D 7 - - ' 6.04E+8 1.01E+8 Co-60 - 2.49t+8 - *

3.24E+9 5.6006 Ni-63 1.61E+10 1.13E+9 - - -

1.81E+8 5.45E+8 Ni a 5.73D1 7.32E+0 - - - 3.97E*2 3.33D0 cu-tm - 8.40E+3 - 2.12E+4 - 4.51E+5 3.95E+3 2n 65 4.24E+8 1.47E*9 - 9.41E+8 - 6.23E*8 6.8M*8 Zn 69 8.19E-6 1.56E 5 - 1.02E 5 - 2.88E 5 1.09E 6 Be-82 - - - - - - 1.33E+6 Br 83 - * * - - - 3.01E+0 Br 84 - - - - - - - $r-85 - - - - - - ab-86 - 2.73E+8 - - - 4.05E+7 1.28E+8 ab-88 - - - - - - - ~ Ab-89 - - * - - - - tr 89 1.51E+18 - - - - 1.80E+9 4.33D 8 sr-90 -7.51E+11 - - - - 2.11E+10 1.85E+11 St-91 2.99E+5 - - - - 1.3M +6 1.1M +4 Sr-92 3.97E+2 - - - - 1.01E+4 1.6 0 1 Y 90 1.24E+4 - - - - 1.02E+8 3.34E*2 Y 91m 5.43E-9 - - - - 2.56E 7 - 1 91 7.87E+4 - - - - 3.2.3E+9 2.11E+5 Y 92 8.47E 1 - - - - 2.32E+4 2.45E-2 Y 93 1.63E+2 - - - - 4.98E+4 4.47E+0 Zr 95 1.74E+6 5.49E+5 - 8.07E+5 - 1.27E+9 3.78t+5 Zr 97 3.09D 2 6.11E+1

9.26E+1 -

1.65E+7 2.81E+1 Nb 95 1.92E+5 1.0M+5 - 1.03D5 - 4.55E+8 5.86E+4 Mb 97 2.69E 6 6.67E-7 - 7.80E-7 - 1.59E 2 2.44E-7 Mo 99 - 5.74E+6 - 1.31E+7 - 1.03D 7 1.09E+6 fc 99e 2. 70E +0 7.54E+0 ' - 1.12E+2 4.19E+0 4.95E+3 9. 77E+1 Davis-Besse ODCM 91 Revision 5 l i I Table 3-10 (conti ued) . R , Vegetation Pathway-Dosg)for (mgem/yrperuC1/m Factors H-3 and - TEENAGER C 14 (cont.) (m -* mrem /yr per uC1/sec) for others Nwilce Sane Liver Thyroid Kidney Lug s! LLI t.8 coy j Ic 101 - - - - - - - pu 103 6.87t+6 -

2.62t+7 .

5.74t+8 2.94t 6 tv-105 1.00t+1 - - 6.31t*2 - 4.04t+4 1.94t+1 tv 106 3.09t+8 . - 5.97t+8 + 1.48t+10 3 mt+7 th 103a * - - * . * . th.106 . * * * * .

As 110e 1.52t+7 1.44E+7 -

2.74f+7 - 4.0M +9 8.74t+6 $b 124 1.55t*8 2.85t+6 3.51t+5 - 1.35t+8 3.11E+9 6.03t+7 $b 125 - 2.14t+8 2.34t+6 2.04t+1

1.8M+ 8 1.6M +9 1.00t+7 fe 125e .1.48t+8 5.34E+7 4.14t+7 - -

4.37t+8 1.9m+7 to-127s 5.51t+8 1.96t+8 1.31t+8 2.24t+9 - 1.37t+9 6.544 + 7 te 127 5.43E+3 1.92t+3 3.74E+3 2.2ct+4 . 4.19t+5 1.17t+1 Te 129e 3.67t+8 1.364+8 1.18t+8 1.54t+9 . 1.38t+9 5.81t+7 fe-129 6.221 4 2.321 4 4.45t 4 2.61t 3 - 3.40E 3 1.51t 4 Te 131e 8.44E+5 4.05t+5 6.09t+5 4.22t+6 - 3.25t+7 3.38t*5 te.131 . . . . . . . Te 132 3.90t+6 2.47t+6 2.60t+6 2.37t+7 a 7.82t+7 2.321+6 t 130- 3.54t+5 1.02t+6 8.35t+7 1.58t+6 - 7.87t+5 4.09E*5 I 131 7.7DE+ 7 1.0M+8 3.14t+10 1.85t+8

2.13t+7 5.79t+7 t 132 5.18t+1 1.36t+2 4.57t+3 2.14t+2 . 5.91t+1 4.87t*1 1 133 1.97t+6 3.34t+6 4.6M+8 5.8M+6 - 2.534+6 1.02E+6 I 134 9.59t 5 2.544 4 4.24E 3 4.018-4 .

3.35t.6 9.134 5

l. 1-135 3.68t+4 9.48t+4 6.10t+6 1.50E+5 -

1.05E+5 3.52t+4 Cs 134 7.09t+9 1.67t+10 - 5.30t+9 2.02t+9 2.08t+8 7.74t+9 C4 136 4.29t+7 1.69t+8 - 9.19t+7 1.45E+7 1.3M+7 1.13E+8 Ca.137 1.01t+10 1.3*E+10 - 4.59t+9 1.?aE+9 1.92t+8 4.69t+9 , Cs 134 * * * * * *

Ba 139 2.771 2 1.95E 5 -

1.84E 5 1.34t 5 2.47t 1 8.08E 4 se-140 1.38t+8 1.69t+5 - 5.75t+4 1.14t+5 2.13t+8 8.91t+6 Sa 141 * * * * * . . 8 le.142 . . . . . . . Le 140 1.80L*3 8.84t+ 2 * * - 5.08t+ 7 2.35t+2 La 142 1.28t-4 5.69t 5 - - - 1.73t+0 1.421 5 Co 141 2.82t+5 1. 8M + 5

8.8M +4 .

5.38t+8 2.1M +4 [. Co 143 9.37t+2 6.82t+5 - 3.0M+2 - 2.05t+7 7.62t+1 Co 144 5.27t+7 2.18t+7 - 1.30E+7 - 1.33t+10 2.83t+6 Pr.143 7.12t+4 2.84t+4 - 1.65t+4 - 2.34E+8 3.55t+3 pr.144 . . . . . . . ud-147 3.63t+4 3.94t+4 - 2.32t+4 - 1.42E+8 2.36t+3 W-187 3.5?t+4 2.90t+4 - - . 7.84t+4 1.02t+4 No 239 1.3M+3 1.30t+2 - 4.09f*2 - 2.10t*7 7.24t+1 Davis-Besse ODCM 92 Revision 5 l l l Table 3-10 (continued) R "(mgem/yr per uC1/m for H-3 ) Vegetation and C-14 Pathvgy Doce Factors - CHIL (m

mrem /yr per uCi/sec) for others Nuclide Bone Liver thyroid Kidrw/. Lung c].LLI t.8ady N3 -

4.01E+3 4.01E . 4.01E+3 4 4t3+3 4.01E*3 4.01E+3 C 14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E'5 7.01E+5 7.01E*5 No 24 3.83E+5 3.83E*5 3.it3E+1 3.83E+5 3.83E+5 2.st3E+5 3.83E 5 P 32 3.37E+9 1.58E+8 - - - 9.30E+7 1.30to Cr 51 - - 6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.1 M +5 un 54 - 6.61E*8 - 1.85E+8 - 5.55E+8 1.76E+8 un 56 - 1.9't 1 - 2.29t+1 - ?.75E+3 4.2R+0 Fe 55 8.00E+8 4.24E+8 - - 2.40E+8 7.8M + 7 1.31E+8 f e 59 4.01E+8 6.49t+8 - - 1.88E*4 6.7M+e 3.23E+8 Co-57 2.99E*7 - - - 2.45E+8 6.04E+7 Co 58 - 6.47E+ 7 - - - 3.TTE+8 1. 9M+ 8 Co 60 -

3. 78E + 8 - - -

2.10E+9 1.12r-9 ul 63 1.421+8 1.34E+9 Ni 65 1.21E+3 5.77E+0 2.6M +4 - 5.20E+5 6.69E+3 Zn-65 3.80E+8 1.35E+9 Zn 69 1.3M 3 2.02E-6 Br 82 2.04E+6 Br.83 5.55E+0 Br 84 gr.33 . ab 86 - 4.5iE+8 - 2.91E+7 Rb-89 - sr 89 3.59E+10 1.39E+9 1.C3E+9 $r 90 1.24E+12 1.67t+10 3.15E+11 sr-91 1.21E+6 2.0M +4 sr 92 1.3M +4 6.5M + 7 6.17E+2 Y 91m Y 91 1.87E+7 2.49E+9 5.01E+5 Y 92 4.4SE+6 8.25E+0 Zr 95 1.23E+7 4.81E+1 Nb 95 3.95E+10 2.11E+9 - - - 1.05E+2 9.89E+0 - - - Cu-64 - 1.11E+4 - L.12E+8 2.16E+9 - 1.3M +9 - 1.51E 5 2.18E 5 - 1 32E 5 - - - - * * - - - - - - - - - - - - - - . . . . . . - - 2. 7M+ 8 Rb 88 - - - - - - - - - - - - - 5.50E+5 - - - - 7.28E+2 - - - - 2.92E+1 Y 90 2.30E+4 * - - - 9.94E 9 - - - - 1.95E 5 - - - * - 1.5&+0 - - - - 4.51E+4 4.46E 2 T 93 3.01E*2 - - - - 3.90E+6 8.58E+5 - 1.23E+6 - 8.95E+8 7.64E+5 Zr 97 5.64E+2 8.15E+1 - 1.17t+2 - 4.10E+5 1.59E*5 - 1.50E+5

2.95E+8 1.14E+5 ub 97 4.90E 6 8,85E-7 -

9.82E-7 - 2.73E 1 4.13E 7 mo 99 - 7.83E+6 - 1.67E+7 - 6.45E+6 1.94E+6 Tc 99m 4.65E+0 9.12E+0 - 1.33E+2 4.63E+0 5.19E+3 1.51E+2 - Davis-Besse ODCM 93 Revision 5 W . Table 3-10 (continued) R g' Vegetation Pathvay Ogsef or Factors - CllILD (cont.) j (mjem/yr per pC1/m ) 11-3 and C-14 (m

mrem /yr per uCi/sec) for others f.8edy uwclice Scr e Liver thyroid Eldrwr. .....

. t....me . Cl ......tLi. ....... Ic 101 * - - 3.89t+7 - 3.99t+8 5.94t+6 tv-tC3 1.55t+7 . - 8,0M + 2 - 5.98t+4 3.33t+1 4u 105 9.171+1 + 1. Cit +9 1.1M*10 9.30t+7 89-106 7.45t+8 - th*1C3m th 1D6 * - 4.05t*7 - 2.58t*9 1.74t+ 7 a8 110m 3.22t+7 2.17t+7 - 1.9M + 8 2.20E+9 1.23t+8 sb 124 3.52f*8 4.571 4 7.78t+5 - 2.7t t + 8 1.19t+9 1.05t+8 Sb 125 4.99t+8 3.85t4 4.62t+5 - - 3.388+8 4.67t+7 to 125m 3.51t+8 9.50t+7 9.84t+7 - 1.07t+9 1.57t +8 fe 127a 1.32t+9 1.561+8 3.16t+8 3.T7t+9 1.00t+4 2.7Dt+3 6,93t+3 2.85t*4 - 3.91t+5 2.15t+3 fe 127

2. 75 E + 8 2.511+9

- 1.044 9 1.33t< 8 fe 129m 8.54t4 2.39t+8 - 7.17t 2 2.74E 4 te 129 1.1%E 3 3.221 4 8.221-4 3.37E 3 - 2.168+7 5.688+5 to 131e 1.54t+6 5.33t+5 1.10t+4 5.16t+6 1,.13) - 3.11E+ 7 3.73t+4 te 132 6.98t4 3.09t+6 4.50t4 2.87t+7 - 5.81.*5 6.47t+5 1 130 6.21t+5 1.26t4 1.3M+ 8 1.8at+6 - 1.2M *7 8.18t+7 1 131 1.43t+8 1.44t+8 4.7M+10 2.3M+8 - 1.99t+1 7.77E*1 1 132 9.20t+1 1.69t+2 7.84t+3 2.59t+2 - 1.79t+4 1.6M +4 1 133 3.5M+4 4.ut+4 8.2St+8 7.40t+4 - 2.10E 4 1. 4M-4 1 134 1.70t 4 3.16t 4 7.'iSE 3 4.848 4 - 8.98t+4 5.57t4 t 135 6.54t+4 1.18t+5 1.04t+7 1.81E+5 - 8.14t +9 2.921+9 1.42t+8 5.54t+9- - Cs 134 1.6CE+10 2.63t+10 8.04t+7 2.22t+8 - 1.18t+2 1.764+7 7.79t+6 1.43t+8 Cs 136 - T.4M+9 2.68t+9 1,43t+8 3.38t+9 Cs 137 2.3M+10 2.29t+10 Cs 138 5.118-2 2.733 5 - 2.3M-5 1.615 5 2.95t+0 1.48t-3 Be 139 2.77t+8 2.43t+5 - 7.9Ct+4 1.45t+5 1.40E+8 1.62t+7 to-140 - 8e 141 8e*142 - - - 3.15E+7 3.81t+2 La 140 3.23E+3 1.13t+3 - *

1.47F+1 2.321 5 La-142 2.32t 4 7.40E 5

2.69t+4 - 7.6M*7 9.12t+3 Co 141 1.23t+1 6.14t+4

- 3.93E+2 - 1.37t+7 1.3M+2 Ca.143 1.73t+3 9.36t+5 - 2.21E+7 - 1.04t+10 6.78t+4 Co 144 1.27t+8 3.98t+7 2.41t+4 - 1.60t+8 7.37t+3 Pr=143 1.48t+5 4,46t+4 - pr.144 . - 9.18t+7 4.49t+3 l 7.16t +4 5.80t+4 - 3.18t+4 ' ind 147 - - - 5.38t+6 1.72t+4 w.187 6.47t+4 3.83t+4 . 5,30t+2 - 1.36t*7 1.2W +2 ap-239 2.53E+3 1.83t+2 94 Revision 5 Davis-Besse ODCM i ^ ~ ~ ' ~ - - _ Table 3-11 RI "' Ground Plane Pathvay Dose Factors [ (m'

mrem /yr per pCi/sec)

NutIide Ary Orgarg Nuctlde Any Organ 43 - tu 105 6.36E+5 C 14 . Ru-106 4.21E+8 Wa 24 1.21E+7 th*103a - p.32 . th 106 - l Cr 51 4.68E+6 Ag 110m 3.47E+9 Mn 54 1.342+9 fe 125m 't.55E+6 ! 1' Mn 56 9.05E+5 te 127a 9.17E+4 fe 55 - te 127 3.00E+3 Fe 59 2.75E+8 Te 129m 2.00E+7 l Co 58 3.82E+8 Te.129 2.60E+4 Co 60 2.16E+10 Te 131a 8.03E+6 ul 63 - Te 131 2.93E+4 NI 65 2.97E+5 te.132 4.22E+6 Cu-64 6.09E+5 130- 5.53E+6 2n-65 7.45E+8 1 131 1.72t+7 2n 69. - 3 132 .1.24E+6 i Br 83 4.89C+3 1 133 2.47E+6 tr 84 2.03E+5 1 134 4.49E+5 { Sr 85

I 135 2.56E+6

'ab-86 8.98E+6 Co 134 6.75E+9 Rb-88 3.20E+4 Cs 136 - 1.49E+8 Rb-89 1.21E+5 Cs.137 1.04E+10 sr 89 -2.16E+4 Cs 138 3.59E+5 sr*90

sa.139 1.06E+5

- Cr-91 2.19E+6 Ba*140 2.05E+7 sr 92 7.77E+5 (1 sa 141 4.18t+4 T Y 90 4.48E+3 ~ to 142 4.49E+4 T 91a - 1.01E+5 to 140 1.91E+7 Y 91 1.08E+6 La 147 7.34E+5 l t 'Y 92 1.80t+5 Co 141 1.36E+7 l J T-93 1.85E+5 Co 143 2.32E+6 Zr 95 2.48E+8 Ce 144 6.95E+7 Zr 97 . 2.94E+6 Pr.143 - Nb 95- 1.36E+8 Pr-144 1.83E+3 ! Mo-99 4.0$E+6 ud 147 8.40E+6 tc 99m 1.83E+5 W-187 2.36 +6 f .Tc 101 2.04E+4 up 239 1.71E+6 l .au-103 1.09E+8 l i Davis-Besse ODCM 95 Revision 5 l ' l l 1' g g . 1 W - ? 8 [ DAVIS-BESSE NUCLEAR POWER STATION LECENDL i.: :- .::: ;; :-~' g ATHOSPHERIC RADI0 ACTIVE-RELEASE PATHWAYS g 9., _g e . ." . ".. 3. .. .- i m .s. . = si m .= ,,,,,,. .. ~ s .. . ... ; 1 # ,,,..., n ...si ...s ,,,, g3 . ... .~. ,... . .,. ,......- , , g., e ..... ... _. . ; ...s g._ " I

- . i."

i 2 O.~.~ .. . . ... .f= 1 1. ... ~ _ a W

- ; 4.

,.....s. 2 2 O, ..... . . .. r cr r t ilg cr F ..... .. ..... o,. C r [r] c 0g8 . T. I

=

[r] Q. ,,, _ ..... g j .A. ... .. -@ . . . . . , _ . . . E 3.s.T[r][r] .. i.xg.......g. 4.r . .: .._4.,_ ........ . an . 2 . _ _ . I 2D %)< 3 -4

F

.A., ". . -7 ""Q'"* 3a l r g .... .. g 3 ., --, 6.. ** -4 7 16995 .a. ia. % 3

,. ,. ,, ,. ,. S = "" * ~" ,. , ,.

n a .. K y == u m . .u...,<........, @= . ~ - - co-..-... 3 LA. HOO.35 RADWASIL AREA .U.L M. M O . . .eG .6 C.f et ( . 4 8. ...si N .,, . u i .. . . ... ,,,, (i @ Y g .u ;.; .;,-.,, T- . 111 5 1 SEC.V f.. 1 r0R INFOR G T10N ONLY ._. . ._ _ ... _-,- ..-._- . . . -.-. . . _._._._ . . . .._ _ .. . _ ._ _ . ._~. _ .. .._ h i i i l-i, ,s l i 1 i l i !' j i l-_ 5 [ c- .) \. I l._ i i I 1 1 t L-This page is. intentionally blank. . -l l-i -n -i 1 i I l ., I : l i-i le t r r-l t l .- b l. i i__ . . ___ _ _ _ __ _ . y ,-y=,- . - . _ -. _ . . - . - . _ -. _- ~ _ _ _... . . _ _ _ . , . - _ . __ _ 1- -i 1 I i 4.0 S.P..ECIAL DOSE ANALYSES 4.1 DOSJS TO PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY I In accordance with Section 7.2. the Semiannual Effluent and Vaste Disposal l Report submitted within 60 days after January 1 and July 1 of each year shall include an assessment of radiation doses from radioactive liquid and I gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside l the SITE BOUNDARY. In special instances MEMBERS OF THE PUBLIC are permitted access to the radiological controlled area within the Davis-Besse station. Tours for the public are conducted with the assurance that no individual vill receive an &ppreciable dose (i.e., small' fraction of the 40 CFR 190 dose standards). The Visitor Center located inside the Davis-Besse Administration Building (DBAB) is also accessible to. MEMBERS OF THE PUBLIC. Considering the frequency and duration of the visits.-the resultant dose vould be a small , ~ fraction of the calculated maximum SITE BOUNDARY doses. The dose from gaseous effluents as modeled for the DBAB Visitor Center is considered the controlling f actor when . evaluating doses to MEMBERS OF THE PUBLIC f rom activities inside the SITE BOUNDARY. For purposes of assessing the dose to MEMBERS OF THE PUBLIC in accordance with Technical Specification 6.9.1.11 and ODCM Section 7.2, the following exposure assumptions may be used; - Exposure time for maximum exposed visitor of 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months (4 visits, 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months per visit).* ' - Annual average meteorological dispersion (conservative, default use of maximum SITE BOUNDARY dispersion) from Table 3-6. The equations in Section 4.2 may be used for calculating the potential dose to a MEMBER OF THE PUBLIC for activities inside the SITE BOUNDARY. Based on these assumptions, this dose would be at least a factor of-400 less than the maximum SITE BOUNDARY air dose as calculated in Section 3.7. There are no areas onsite accessible to the public where exposure to -liquid effluents could occur. - Therefore, the modeling of Section 2.4 conservatively estimates the maximum potential dose to MEMBERS OF THE -PUBLIC.

Based on a maximum conservative estimate.

4.2 -DOSES TO MEMBERS OF THE FUBLIC 40 CFR 190 'As required-by and ODCM Section 7.2 the Semiannual Effluent and Vaste C-1 Disposal Report shall also include an' assessment of the radiation dose to -the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle sources (including dose contributionsFor the likely most. from effluents and direct radiation from onsite sources). 97 Revision 5.1 Davis-Besse ODCM 8 I 4 (including dose contributions from effluents and direct radiation from j onsite sources). For the likely most exposed MEMBER OF THE PUBLIC in the ' vicinity of the Davis-Besse site, the sources of exposure need consider only the radioactive effluents and direct exposure contribution from Davis-Besse. No other fuel cycle facilities contribute'significantly to the cumulative dose to a MEMBER OF THE PUBLIC in the immediate vicinity of the site. Fermi-2 is the closest fuel cycle facility located about 20 miles to the NNV. Due to environmental dispersion, any routine releases from Fermi-2 vould contribute insignificantly to the potential doses in the vicinity l . of Davis-Besse. i l The correlation of measured. plant effluents with pathway modeling of this l ODCM provide the primary metSed for demonstrating / evaluating compliance with the limits specified below (40 CFR 190). However, as appropriate, the results of the environmental monitoring program may be used to provide additianal data on actual measured levels of radioactive material in the actual pathways of exposure. ODCM Section 4.2.3 discusses the methodology for' correlating measured levels of radioactive material in environmental pathway samples with potential doses. Also, results of the land use census may be used to determine actual exposure pathways and locations. The annual (calendar year)' dose or dose commitment to any MENBER OF THE TUBLIC due to releases of radioactivity and to radiation from utanium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyrold, which shall be limited to less than - or equal to 75 mrem. With the calculated doses from the releases of radioactive materials in - liquid or gaseous effluents exceeding twice the limits of Sections 2.4.1. 3.7.1, and 3.8.1, evaluations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of this Section have bet , exceeded. If such is the case, in lieu of a Licensee Event Report, p;epare and . .ibmi t to the Commission within 30 days, pursuant to Section 7.3, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Specirl Report, as defined-in 10-CFR Part 20.405c, shall include an analysis that estimatesLthe radiation exposure (dose) to a MEMBER OF'THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct-x radiation.-for the calendar year that includes the release (s) covered by this report. It shall also describe; levels of radiation and concentrations of radioactive material involved, and.the cause of the exposure levels or concentrations. If the estimated dese(s) exceeds the above limits, and -if t!:e release condition resulting in violation of.40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a "ariance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely tequest, and a variance is granted until staff action on the request-is complete. Davis-Besse ODCM 98 Revision 5 a 3- e w .m-- ._, - - - - , . This requirement is provided to meet the dose limitations of 40 CFR Part 190 that_have1been incorporated into 10 CFR Part 20 by 46 FR 18525. The ! requirement requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except' the thyroid, which shall be limited to less than or equal to 75 mrem. c It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC vill exceed the dose limits of 40 CFR Part 190 if the reactor remains within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor and outside storage tanks are kept small. The Special Report vill describe a course of action that should result in the , limitation of the annual dose to a MEMBER OF THE PUBLIC to vithin the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC f rom other uranium fuel i cycle sources is negligible, with the exception that the dose contributions from other nuclear fuel cycle facilities at the same site or vithin a radius of 8 km must be considered. If a dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), ir accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.405c, 4s considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only . elates to the limits of 40 CFR Part 190, and does not apply in any vay to the other dose requirements for dose limitation of 10 CFR Part 20, as add essed in Sections 2.2 and 3.3.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is a part of the nuclear fuel cycle. 4.2.1 Effluent Dose Calculations For purposes of implementing the above requirements of determining the cumulative dose contribution from liquid and gaseous effluents in accordance vith Sections 2 and 3 and the reporting requirements of Section 7, dose calculations for Davi"-Besse may be performed using the calculational methods contained within this ODCM; the conservative controlling pathways and' locations of Table 3-6 or the actual pathways and locations as o identified by the land use census may be used. Liquid pathway doses may be calculated using equations in ODCM Section 2.4. Doses due to releases of radiciodines, tritium and particulates are calculated based on equations in Section 3.8. i Tho following equations may be used for calculating the dose to MEMBERS OF THE PUBLIC from releases of noble gases: D tb = 3.17E-08

U

X/0

E (K 3 *Og) (4-1) 8760 and D

s = 3.17E-08

U

X/0

I ( ( L; + 1.1 Mg ) *O)t (4-2)

Davis-B+ se ODCM 99 Revision 5 l' f wheret D tb~.. total body dose due to gamma emissions for noble gas -radionuclides (mrem)- D,- --,. skin dose due to gamma and beta emissions for noble gas radionuclides (mrem) . U = duration of exposure (hr/yr, default values in Table 4-1) 3 X/0 = atmospheric dispersion to the offsite location (sec/m ) O- g . cumulative release of noble gas radionuclide i over the period of interest (uCl) Kg . total body dose factor due to gammt emissionsftfmnoblegas radionuclide i f rom Table 3-5 (mrem /yr' per UCt/m ) , L 3 = skin dose factor due to beta enissions from nobif gas radionuclide i f rom Table 3-5.(mrem /yr p UC1/m ) , -M g gamma air dose f ac3or for noble gas radic. iclide i f rom Table 3-5 (mrad /yr per uCi/m ) 8760

hours per year 1.1 - mrem skin dose per mrad gamma air dose (mrem / mrad)

--3.17E-08 - 1/3.15E+07 yr/sec Average annual meteorological dispersion i parameters or meteorological conditions-concurrent with the release period under evaluation may be used (e.g., quarterly averages or year-specific annual averages). . 4.2.2 _Jirect Exposure Dose Determination'- Onsite Sources Any potent-lally significant. direct exposure contribution from onsite - sources to offsite individual doses may be evaluated based on the results of dhe-environmental measurements (e.g., TLD, ion chamber measurements) or by the use of a radiation transport and shielding calculational method. Only:during atypical conditions vill there exist any potential for significant onsite sources at Davis-Besse that vould yield potentially significant.offsite doses to a HEMBER OF THE PUBLIC). However, should a situation exist whereby the direct exposure contribution is potentially , significant, onsite measurements, offsite measurements and calculational techniques vill be used .for determinat wn'of dose for assessin? CFR 190 compliance. The following simplified method may be used-for evaluating the ditect dose ' based on_onsite or site boundary measurements: D g ,0 -D'O B ' B ,0) I'~ ) (Xg,0)2 e 1 Davis-Besse ODCM 100- R(vision 5 . - . - . - . - - - .~ ~. . .- -. . . . - . _ ~ . . - _ . - - - . - . _ - . ~ . whete: DD'0 . . . direct radiation dose measured at location B (oneite or site boundary) in sector 0 D 0-- extrapolated dose at location L in same sector.0 X i e= distance to the location L from the radiation source-X 3,0 = distance to location B from the radiation source 4.2.3 Dose Assessment Based on Radiological Environmental Monitoring Data Hotinally,_ the assessment of potential doses to MEMBERS OF THE PUBLIC must l be ct.lculated based on the measured radioactive effluents at the plant. The resultant levels of radioactive material.in the offsite environment are so minute as to be undetectable. The calculational mathods as presented in this ODCM are used for-modeling the transport in t..., environment and the resultant exposure to offsite individuals. The results of the radiological environmental monitoring program can provide input into the overall assessment of impact of plant operations and radioactive effluents. Vith measured levels of plant related radioactive material in principal pathways of exposure, a quantitative assessment of potential _ exposures can.be performed. Vith the monitoring program not identifying any. measurable levels, the data provides a i qualitative assessment - a confirmatory demonstration of the negligible impact. Dose modeling can be simplified into three basic parameters that can be applied in using environmental monitoring data for dose assessment. D = C

U

DF (4-4) where:

0- - dose or dose commitment-C - -concentration in the exposure media, such as air concentration-for the ithalation pathway, or fish, vegetation or milk concentration for the ingestion pathway U = individual exposure to the pathway, such as br/yr for direct exposure, kg/yr for. ingestion pathway-DF - dose conversion factor to-_ convert from an exposurc ur uptake to an individual dose or dose commitmer.t The appicabil!ty of each of these basic modeling parameters to the use of' environmental monitoring data-for dose assessment is addressed below: -Davis-Besse ODCH 101 Revision 5 Concentration _C The main value of using environmental sampling data to assess pntential doses to individuals is that the data represents actual measured levels of radioattive material in the exposure pathways. This eliminates one main uncertainty in the modeling - the release from the plant and the transport to the environmental exposure medium. Environmental samples are collected on a routine frequency (e.g., veekly airborne particulate samples, monthly vegetable camples, annual fish sam-ples). To det rmine the annual average concentration in the environmental medium for use .n assessing cumulative dose for the year, an average con-centration should be determined based on the sampling frequency and measured levels. C - I(C 3

t)/365 (4-5) 3 wheret d

C4 - average concentration in the sampling medium for the year C 1 = concentration of each radionuclide i measured in the individual sampling medium t t - period of time that the measured concentration is considered I representative of the sampling medium (typically equal to i the sampling frequency; e.g., 7 days for veekly samples, 30 days for menthly samples). If the concentration in the sampling medium is below the detection capabilities (i.e., less than lower limits of detection -LLD), a value of zero should be used for Cg (Cg = 0). Exposure - U Default exposure values (U) as recommended in Regulatory Guide 1.109 are _ presented in Table 4-1. These values should be used only when specific - Cata applicable to the environmental pathway being evaluated is unavailable. Also, the routine radiological environmental monitoring program is designed to esmple/ monitor the environmental media that would provide .arly indications of any measurable levels in the environment but not necessarily levels to which any individual is exposed. For example, sediment samples are collected in the area of the liquid discharge: typically, no individuals are directly exposed. To apply the measured levels of radioactivity in samples that are not directly applicable to exposure to real individuals, the approach recommended is to correlate the location and measured levels to actual locations of exposure. Hydro-logical or atmospheric dilution factors can be used to provide reasonable correlations of concentrations (and doces) at other locations. The other alternative is to conservatively assume a hypothetical individual at the sampling location. Doses that are calculated in this manner should be presented as hypothetical and very conservatively determined - actual Davis-besse ODCM 102 Revision 5 exposure vould be much less. Samples collected from nearby vells or actual vater supply-intake (e.g.,-Port Clinton) sho'/ld be used for estimating.the -potential drinking vater doses. Other water samples collected, such as near field dilution area, are not applicable to this pathvay. Dose Factors - DF The dose factors are used to convert the intake of the radioactive material to an individual dose commitment. Values of the dose factors are . presented in NRC Regulatory Guide 1.109. The use.of the Regulatory Guide i 1.109 values applicable to the exposure pathvay and maximum exposed ; individual is' referenced ;n Table 4-1, 4.2.4 Use of Environmental TLD for Assessing Doses Due to Noble Gas Releases Thermoluminescent dosimeters (TLD) are routinely used to assess the direct exposure. component of radiation doses in the environment. However, because routine releases of radioactive material (noble gases; are so lov, the resultant direct exposure doses are also very lov. A study

performed-for the NRC concluded that it is possible to determine a plant _ contribution to the natural background radiation levels (direct exposure) of around 10 mrem per year (by optimum methods and high' precision data). Therefore, for routine releases from' nuclear _ power plants the uce of TLD is mainly confirmatory - ensuring actual exposurec are within the expected natural background variation.

For releases of noble gases, environmental modelli; using plant measured releases and atmospheric transport models as presented in this ODCM represents the best method of assessing potential environmental doses. ~ Hovever, any observed variations in TLD measurements outside the norm should be evaluated. e l

NUREG/CR-0711, Evaluation of Methods for the Determination of X- and Gamma-Ray. Exposure Attributable to a Nuclear Facility Using Environmental

TLD Measurements, Gail dePlanque, June 1979, USNRC.

Davis-Besse ODCM 103 Revision 5 p-Table 4 Recommended-Exposure Rates in Lieu of Site Specific Data * -Table Reference , Exposure _ Pathway Maximum Exposed Exposure Rates for Dose Factors ' Age Group from RG 1.109-Liquid Releases Fish Adult 21 kg/y E-11 Drinking Vater Adult 730 1/y E-11 30ttom Sediment Teen. 67 h/y- E-6 Atmospheric Releases-Inhalation Teen 8,000 m3 /y E-8 Direct Exposure All 6,100 h/y** N/A (ODCM Table 3-5)- ' Leafy Vegetables Child 26 kg/y E-13 Fruits, Vegetables & Grain Teen 630 kg/y E-12 u Milk Infant 330 1/y E-14 .*- Adapted-from Regulatory _ Guide 1.109. Table E-5

- Net exposure of 6,100 h/y is based on the total 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months per year adjusted by_a 0.7 shielding factor as recommended in Regulatory Guide

.1.109, > l 1- Davis-Besse ODCM 104 Revision 5 ll l r 5.0 ASSESSMENT OF LAND USE CENSUS DATA A land use census (LUC) is conducted annually in the vicinity of the Davis-Besse site. This tensus fulfills two main purposes: 1) meet requirements of TS 6.8.4.e (as required by 10 CFR 50, Appendix I, Section lC-1 IV.B.3) for identifying controlling location /pthway for dose assessrnent of ODCM Section 3.8.1; and (2) provide data on actual exposure pathways for assessing realistic doses to MEMBERS OF THE PUBLIC. f.1 LAND USE CENSUS REQUIREMEtifS A land use census shall be conducted during the growing season at least lC-1 once per twelve months using that information that vill provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agricultural authorities. The land use census shall identify within a distance of 4 km (5 miles) the location, in each of the 16 meteorological t garden of greater than 50 m* (500 producing ftsectors,broad of theleaf nearest milk animal.2)he neare vegetation. This requirement is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if required by the results of this census. This census satisfiestherequirementsutSectionIV.B.3ofAppendixIjo10CFRPart

50. Restricting the census to gardens of greater than 50 m (500 ft2) provides assurance that significant exposure pathways via leafy vegetables vill be identified and monitored. A garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regular.ory Guide 1.109 for consumption by a child. To determine this minimum garden size, the folluving assumptions were maden (1) 20% of the garden was used for growing broad leaf vegetation .e. , similar to let ttice and cabbage), and (2) a vegetation yield of 2 kg/m The data from the land t.Je census is used for updating the location / pathway for dose assessment and for updating the Radiological Environmental Monitoring Program. The results of the land une census shall be included in the Annual Radiological Environmental Operating Report pursuant to Sect. ion 7.1. -

Vith a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than tha values currently being calculated in Sections 3.8.1, in lieu of a Licensee Event Report, identify the nev locations (s) in the next Semiannual Effluent and Waste Disposal Report, pursuant to Section 7.2. Vitt a land use census identifying a locations (s) that yields a calculated dose or dose commitruent (via the same exposure pathvay) 20 percent greater than that at a location from which samples are currently being obtained in accordance with Section 6.1, add the nev locations (s) if practical (and readily obtainable) to the Radiological Environmental Monitoring Program within 30 days. The sampling locations (s), excluding the control station location, having a lover calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program. In lieu of a Licensee Event Report and pursuant ta Section 7.2. identify the new location (s) in the next Semiannual Effluent and Vaste Disposal Report and also include in the report a r9 vised figure (s) and table for the ODCM reflecting the new location (s). Davis-Besse ODCM 105 Revision 5.1 The following guidelines shall be used for assessing the results from the land use census to ensure compliance with this Section. 5.1.1 Data Compilation A. Locations and pathvsys of exposure as identified by the land use census will be compiled for comparison with the current locations as presented in Table 3-4. B. Changes from the previous year's census vill be identified. Also, any location /pathvay not currently included in the Radiological Environmental Monitoring Program (Table 6-2) vill be identified. C. Historical, annual average meteorological dispecslon parameters (X/0, D/0) for any new location (i.e., location not previousl-/ identified and/or evaluated) vill be determined. All locations should be evalutted i st the same historical meteorological data set. 5.1.2 Felative Dose Significance A. For all new locations, the relative dose significance vill be determined by applicable pathways of exposure. B. Relative dose calculations should be based on a generic radionuclide distribution (e.g., Davis-Besse USAR gaseous effluent source term or past year actual effluents). An I-131 source term dose may be used for assessment of the maximum organ ingestion pathway dose beesuse of its overwhelming contribution to the total dose relative to the other particulates. C. The pathvay dose equations of the ODCM should be used. 5.1.3 Data Evaluation A. The controlling location used in the ODCM Table 3-4 vill be verified. If any location / pathway (s) is identified with a higher relative dose, - this locat.on/ i pathway (s) should replace the previously identified controlling location /pathvay in Table 3-4. If the previously identified controlling pathway is no longer present, the current controlling location /pathvay should be determined. B. Any changes in either the controlling location / pathway (s) of the ODCM dose calculations (Section 3.7 and Table 3 4) or the Radiological Environmental Monitoring Program (ODCM Section 6.0 and Table 6-2) shall be reported to NRC in accordance with ODCM Section 5.1 and 7.2. Davis-Besse ODCM 106 Revision 5 __ . _ . . - _ _ - _ _ _ . . . - . _ _ _ _ _ - _ . _ _ . - ~ . _ . - _ _ _ . - . _ . 5.2: LAND USE CENSUS TO SUPPORT REALISTIC DOSE. ASSESSMENT Tae Land Use Census (LUC) provides_ data needed'to support the special dose analyses of Section 4.0.- Activities inside the SITE BOUNDARY should be periodically reviewed--for dose assessment as required by Section 4.1. c .1 ~ Assessment of realistic doses to MEMBERS OF THE PUBLIC is required by Section 4.0 for demonstrating compliance with the EPA Environmental Dose Standard, 40 CFR 190 (Section 4.2). g,y To support these dose assessments, the LUC shall include (a) areas within the SITE BOUNDARY _that are accessible to the public; and (b) use of Lake Erie water on and near the site. The scope of the LUC shall include the following: - Assessment of areas onsits that are accessible to MEMBERS OF THE PUBLIC, Particular attention should be give to assessing exposure times for_ visits to the Davis-Besse Administration- - Building. Data should be used for updating Table 4-1. , - Data on Lake Erie-use should be obtained from local and state officials. Reasonable efforts shall be made to identify individual' irrigation and potable water users, and industrial and commercial water users whose source is Lake Erie. This data is ' used to verify _the pathways of exposure used in Section 2.4 C-1 e > 4 107 Revision 5.1 Davis-Besse ODCM / - ^ - -- - * - y- ~ w --% - - .,, w 1r it , ~.- -. -- . - -. . - . . . . . . - - . _ . - . - . - . . 4 , g, i 1 i I -i 1 T This page is intentionally blank. 9 l i l.. l .: { l l t t 6.0. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program (REMP) provides , ~~1 measurements of-radiation and of radioactive materials in those exposure pathvays and for those radionuclides which lead to the higher potential radiation exposures of individuals resulting from the station operations. The sampling and analysis program described in this Section was developed to provide representative measurements of radiation and radioactive materials resulting from station operation in the principal pathvays of exposure of MEMBERS OF THE PUBLIC. This monitoring program implements Sections IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent controls by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling-of the environmental exposure pathvays. Guidance for the development of this monitoring program is provided by the Radiological Assessment Branch Technical Position on Fnvironmental Monitoring. 6.1 PROGRAM DESCRIPTION 6.1.1 General The REMP shall be conducted as specified in Table 6-1. This table describes the minimum environmental media to be sampled, the sample collection frequencies, the numbrr of representative samples r2 quired, the characteristics of the supling locations, and the type and fregrency of sample analysis. Table 6-2 provides a detailed listing of the sample locations-for Davis-Besse which satisfy the requirements of Table 6-1. Maps for each site listed in Table 6-2 are contained in Appendix C. The specific locations used to satisfy the requirements of Table 6-1 may be changed as deemed appropriate by the Radiological Environmental Supervisor. The changes shall be reported in the Annual Radiological Environmental as Operating Report and the Semiannual Effluent and Vaste Disposal Report required by Sections 7.1 and 7.2. respectively. If the changes are to be permanent, Table 6-2 and Appendix C sball be updated. Note: -For the purpose-of implementing Section 5.1, sampling locations vill be modified, to reflect the finding = of the land use census as-described in ODCM Section 5.1. 6.1.2 Program Deviations Vith the REMP_not being conducted as specified in Table 6-1, in lieu of a Licensee Event Report, prepare and submit to tne Commission, in the Annual Radiological Environmental Operating Report required by Sec tion 7.1.l c y l-a description of the reasons for not conducting the program as required and plans for preventing a recurrence. I 108 Revision 5.1 Davis-Besse ODCM 1 - . . - . - - ., ,. .- _- - . _ - .. _ .~. - -. _ _- - . . . -.-- -- 6.1.3 Unavailability of Milk or Brono Leaf Vegete; ion Samples Vith milk or fresh-leafy vegetable sampler snavailable from one or more of the sample locations required by Table 6-1,. identify locations for obtaining replacement samples and if practical add them to the REMP vithin 30 days. The locations from which samples vere unavailable may then be di.eted.from the monitoring program. In lieu of a Licensee Event Report and pursuant to Section 7.2, identify the cause of the unavailability of lC-1 samples and identify and_the nev locations (s) for obtaining replacement . samples in the next ~ ;siannual Effluent and Vaste Disposal Report and also = include in the report a revised figure (s) and table for the-0DCM reflecting the new locations (s). 6.' '. Seasonal Unavailability, Equipment Malfunctions, Safety Concerns Vith specimens unabtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons, every effort vill be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule vill be documented in the Annual Radiological -Environmental Operating report pursuant to Section 7.1. C-1 6.1.5 -Sample Analysis REMP samples shall be analyzed pursuant to the requirements of Table 6-1 and the detection capabilities required by Table 6-3. _ Cumulative potential dose ;nntributions-for the current calendar year from radionuclides detected in environmental samples shall be determined in accordance with the methodolog1* and parameters in this ODCH. j -6.2- REPORTIN9 LEVELS 6.2.1 General The reporting levels are based on the design objective doses of 10 CFR 50, Appendix I (i.e., levels of radioactive material in the sampling media corresponding to potential annual doses of 3 mrem, total' body or 10 mrem, >= maximum organ from liquid pathways; or 5 mrem, total body, or 15 mrem, maximum organ for gaseous effluent pathvays - the annual limits of Sections y 2.4.1, 3.7.1 and 3.8.1). These potential doses are modeled on the maximum exposure or consumption rates _of NRC Regulatory Guide 1.109. The evaluation of prient s' .1ses should be based solely on radioactive L material resultit.g from ps aperation. l l Dav'is-Besse ODCM 109 Revision 5.1 1 6.2.2 Exceedance of Reporting Levels. Vith the level of radioactivity as the result of plant effluents in an i environmental sampling medium at a specifiri location exceeding the l' reporting levels of Table 6 4 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, a Special Report that identifies l i the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to MEMBER OF THE PUBLIC is less than the calendar year limits of Sections 2.4.1, 3.7.1 and 3.8.1. Jhen more than one of the radionuclides in Table 6-3 are deter,ted in the sampling medium, this report shall be I submitted ils concentration _ (1) + concentration (2) + ...) 1.0. ) reporting level (1) reporting level (2) ) l Vhen radionuclides other than those in Table 6 4 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a KEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Sections 2.4.1, 3.7.1 and 3.8.1. The method described in Section 4.2.3 may be used for assessing the potential dose and required reporting for radionuclides other than those listed in Table 6-4.- ! A special report.is not required if the measured level of radioactivity was not the result of plant effluents: however, in such an event, the condition shall be reported and described in thi Annual Radiological Environmental Operating Report. 6.3 INTERLABORATORY COMPARISON PROGRAM of Analyses shall be performed on raouactive materials supplied as part an Interlaboratory Comparison Program that has been approved by the Commission. The cequiremen- 3r participating in an approved Interlaboratory Comparison Program is provided to ensure that independent , checks on the pre .ston and accuracy of the measurements of radicartive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the ersults are reasonably valid for the purposes of Section IV.B.2 of Appe dix I to 10 CTR Part 50. A summary of the results obtait.ed as part of the required Interlaboratory Nmparison Program shall be included in the Annual Radiological Vith analyses not C-1 ' Environmental Operating Report pursuant to Section 7.1 J.eing performed as required. report the corrective actions taken to prevent l a recurrence to the Commission in the Annual Radiological Environmental l C-T

Operating Repntt pursyant to Section 7 1 110 Revision 5.1 l

Davis-Besse ODCM . .~ i Table 6-1 ! RADIOLOGICAL E'NIRONMENTAL MONITORING PROGRAM . Exposure Pathway' Number of Representative Type and Frequency and/or Sample Samples and Sample Locations' Collection' Frequency of Analysi"

1. . DIRECT RADIATICtf 27. rwtine monitoring stations Quarterly Gama dose gaatterly .

either with two or more dosi-meters or with one instrument I for measuring and recording , dose rate continuously, placed ' as follows: an inner ring of stations, i generally one in each ; meteorological sector in the i general area of the SITE BOutOARY; an outer ring of stations, one in each meteorological -sector in the 6- to 8- km range from the site, excluding the j sectors over Lake Erie; ; the balance of the stations to l be placed in special interest areas such as population : centers, nearby residences, ! schools, and in 1 or 2 .sreas i to serve as control stations. DAVIS-BESSE ODCM 111 Revision 5 I m , ._, y .i. - , . - . , - . . -. - ,e - e -- -- -- -- . 1 . Table 6-1 (Continued) t i RADICIDGICAL UNIRCt2ELTAL POIITORIfG PROGRRt

Exposure Pathway Number of Representative Pype and Frequency and/or Sample Samples and Sa: nple Lcenicas' Collection Frequency of Analysis l 2.. AIRDOR!.T'

'Radiciodine and Sagles from $ locations, Continuous sagler Radiciodine Cannister:

j. Particulates placed as follows: operation with sample I-131 analysis weekly. ;

collection weekly, or ; 3 sagles from close to the more frequently if Particulate Sampler: s SITE BOUNDARY, in different required by dust Gross beta radioactivity ; sectors, generally from areas loading. analysis following filter i of higher calculated annual change;" Gamca isotopic

average groundlevel D/Q. analysis of composite t (by location) quarterly.

I samle from the vicinity ! ! of a nearby enn-mity, generally in the area of ; j ~ higher calculated annual i average groundlevel D/Q. , 1 sample from a control location,15- 30 km from the i site. i-3.

WATERDORt.T

a. Surface 2 samples weekly composite Tritium and gacuna t (untreated water) sample (Indicator isotopic

analysis of 3 location should be a comprsite sample monthly.

i cogosite) , i

b. Ground Sample from one source Quarterly n - Isotopic # and only if likely to be tritium analysis l affected' quarterly. !

Davis-Besse C001 112 Revision 5 ...,m.- 9 - - .-_3u .,.s y .,m y& , ym.w,, -,2p.i e~ ,- Table 6-1 (Continued) ImDICIff,ICAL CTJIROL".HTEAL P1CriITORI?C PFOGRAM m Ap2 and fr+,ency Exposure Pathway temier of Representsti ce Collection Frequency of Analysis arz!/or Sann le Samples and Sample Locations

Weekly composite Gross beta cn monthly Drinking 1 sample from the nearest c.

source. sample. coupesi te. Tritium (Treated water) and gamma iscropic 1 sample from a contro l analysis on quarterly location. composite. I-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year. semiannually Gam.a isotcpic analysis *

d. Sediment from 1 sample from area with semiannually.

Shoreline existing or potential recreational value.

4. IFEESTIOtl If available, sanples from Semimonthly -hen Gam.a isotopic' and I-131

a. Milk analysis semimonthly when animals up to 2 locations aniauls are on aniculs are on pasture; l

' within 8 km distance having pasture, conthly monthly at other tzmes. the highest dose potential. at other times l 1 sanple from milking anicals l at a control location 15-30 km distant and generally in a less prevalent wind direction. 113 Revision S Davis-Besse ODcn ~ . J Table 6-1 (continued) l i FADIOLOGICAL CTIIRCt7.CTTAL POiTTCRI!G FFOGFJJi i.'utrier of Representative Type and Frege?ncy l FJposure Pathway of Analysts and/or Sample Samples and Sample Locations

Collection Fre<percy l Gaarna isotopic analysis

Fish 1 sample each of 2 ccernercially 1 sample in season.

b. cn edible portions.

and/or recreationally important species in vicinity of site. i l 1 sample of sare species in areas not influenced by plant discharge. Samples of up to 3 different tionthly when available. Garra isotopic

and I-131 l

c. Food Products analysi kinds of broad leaf vegetation (Broad leaf l vegetation) growtr in two different offsite l locations of higher predicted l annual average grourxi-level DfD I if milk sarpling is not performed.

1 sample of each of the si:ailar rianthly when available. Caru isotopic

and I-131 broad leaf vegetations grown analysis.

15-30 km distant in a less prevalent wind direction if milk sampling is not performed. 114 Fevision 5 Davis-Besse ODCM e , f f

'4able 6-1 (Continued)

L TABLE tOfATICH Specific parameters of distance and direction sector from the centerline of the l reactor, and additional description (where pertinent) are provided for each and l every pmple location in Table 6-2. Refer to tATREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978, and to Radiological Astessment Branch Technical Position, Revision 1, November 1979. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most l desired location or time. In these instances suitable alternative media and I locations may be chosen for the particular pathway in question and appropriate ; substitutions made within 30 days in the Radiological Environmental Monitoring , Program. In lieu of a Licensee Event Report and pursuant to ' 7ecification l 6.9.1.11 and Section 7.2, identify the cause of the unaval] 'ty of samples for that pathway and identUy the new locations (s) for obtaining .. placement samples in the next Semiannual Lifluent and waste Disposal Report. Also, include in th. ' report a revised figure (s) and table for the ODCM reflecting the new location (s).

one or more instruments, such as a pressurized ion chamber, for measuring and l

--- recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (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 dosimeters for measuring direct radiation. The number of direct radiation i monitoring stations may be reduced according to geographical limitations; e.g., l at an ocean site, some sectors will be over water so that the number of l dosimeters may be reduced eccordingly. The frequency of analysis or readout for ' TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. ' Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hourn or more after sampling to allow for radon and thoron-daughter decay. If grosa beta activity in air particulate sarples .is greater than ten times the yearly mean of control samples, then gamma isotopic analysis shall be perform d on the individual samples. d Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that my be attributable to the effluents from the facility.

Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradiert or recharge properties are suitable for contamination.

Davis-Besse ODCM 115 Revision 5 = y i-y 3 s.- ymv.y, , ac.m- ..,--c,my-w,,,w:-,-,- en.,,,,- ..w,,,,__,,- Table 6-2 Required Sampling Locations Appendix C Type of Location Page Reference Location

Location Description T-1 C-3 I Site boundary, 0.6 mile DE of Station.

T-2 C-4 7 Site boundary, 0.9 mile E of Station. T-3 C-5 I Site boundary, 1.4 miles ESE of Station near mouth of Toussaint River. T-4 C-6 I Site bottndary, 0.8 mile 5 of Station. T-5 C-7 I tiain entrance to site, 0.5 mile W of Station. l T-6 C-8 I site boundary, 0.5 mile !NE of Station. T-7A & B C-9 I Sand Deach, 0.9 mile l iM of Station. T-8 C-10 I rarm, 2.7 miles WSW o^ Station. T-9 C-11 C Oak harbor substation, 6.8 miles SW of Station. ~ T-10 C-12 I site boundary, 0.5 mile SSW of Station. T-11 C-13 C Port Clinton Water Treatment plant, 9.5 miles SE of Station. T-12 C-14 C Toledo Water Treatment Plant, 23.5 miles WrM of Station. Water samples are col.1,ected 11.3 miles tM of site. T-25 C-15 I rarm, 3.7 miles S of Station.

I - Indicator locations; C = Control locations.

g f, Davis-Besse ODCM 116 Revision 5 Table 6-2 (continued) : Required Sampling Locationa Appendix C Ti'pe of 4 Location Page Reference Location

Location Description

- T-2 7 - C-16 C Crane Creek State Park, 5.3 miles W!M of Station. T-28 C-17 1 Davis-Besse Water Treatment Plant, onsite. T-33 C-18 I Lake Erie within a 5-mile radius from Station. 1 i T-35 C-19 C Lake Erie, greater than a l 10-mile radius from Station. j T C-20 C rarm, 13 miles SW of Station. .T-40 .C-21 I Site boundary, 0.7 mile , SE of Station. T-41 C-22 I Site Boundary, 0.6 mile SSE of Station. T-42 C-23 I site boundary, 0.8 mile SW of Station. T-44 C-24 -I Site boundary, 0.5 mile ! WSW of Station. T-46_ C-25 T Site boundary, 0.5 mile !M of Station. T-47 C-26 I Site boundary, 0.5 mile N of Station. T-48 .C-27 I site boundary, 0.5 mile NE of Station. F T-50 C-28 I Erie Industrial Park Water TreatJnent Plant, 4.5 mile c SE of Station.-

I = Indicator locations; C = Control locations..

Davis-Besse ODCM ~117 Revision 5. l v . t l-t _ . . _ . - _ _ . . . _ _ _ _ _ _ . . ~. _ _ , _ - - - - - , _ - - , - . . - - - - _ . _ , . . I b ble 6-2 (continued) ;j Required Sampling Locations Appendix C Type of Location _ _ Page Reference Location

Location Description .

T 52 C-29 I rata, 3.7 miles S of Station. T-54 C-30 1 ratm, 4.0 miles SW of Station. T-55 C-31 I rarm, 5.0 miles W. of Station. T-57 C-32 C rarm, 22 miles SSE of Station. T-67 C-33 I site boundary, 0.3 mile l ICM of Station. T-68 C-34 ! Site Boundary,-0.5 stiles -l MM of station T-91 C-35 1- Siren Post IJo. 1108, 2.5 , miles SSF of Station. l T-112 C-36 I State Route 2 and Thompson . Road, 1.5 miles SSW of ' Station. i T-151 C-51 1 State Route 2 and flumphrey Road,1.8 miles MM of Station.

I = Incidator locations; C = Control locati ns.' D

+ 4 s Davis-Basse ODCM 118 Revision 5 .- . . _ ~ _ - . . _ . - . - - _ - .- . - . . _ _ - . - _ . - . - . - . ! :')l '.LL [ { t ' ;}ii iiI ;It t f [fc !r{L![!}t[i f k 1 . ) y r t' d n - e,g m 0 ik 5 . _ d/ ei 1' e . b SC p _ l , ( l a E h . s n - , i o . s s e i . s) . d v tt di e - ce el R d uw t c r u o , rg on p Fk / 0 6 0 6 ee rv - di c oc op db na F( a e dh . et d t e

ch s

) et u D ) ti L L k/ 1 d ew b e - ( li 5 5 r . ic 1 1 1 ee y . N Mp bht a . C ( m i a oe t g I. o / 3 w ) et i - A t r C 6 t e . a , p D w e , e sl 0 l F h , eb 0 b T a O S T sg ik F / i 0 3 1 2 0 6 0 3 1 0 6 2 0 3 1 . lf da' ii ci 0 3 f 9 1 1 - I cp ut nn o M I ( e e L ed u si l e a R E~ E t' a h1 t n v . C l y a a _ L u _ c l e' , i ) 2 2 2 nl s t r sa'm 0 0 0 ' ob a t s aG/ E E E . t r i P - i rc 0 0 0 . hs au x e eop 1 7 6 t a - n ( e . y r nmd a o a e s r b eet i r mr r t i . aop a p A t ohe . ncr r . i e 8 shd e5 n t a r1 )

1, o a w e/ *

4 ) ds g

,ti 4 0 5 0 5 0 5 1 5 kd ac Wp 0 0 1 3 1 3 1 '01 1 tae sei i n 1 J ( 2 ( 5 i pf l i k n O C 1 rt i sen r e s a s ihe d s C td i s t B e C o ' .%Oi o n B e s ' * - y s ' a : f s l s n e n r I

a E r

I i v a o M F ' Z z *' "* " n u ca r ! A G ' t ' ' " * ' ' *

t *

< 7, b Tii }; 4i ll4 ! li ;i .f I:;i1

l!

i,I l Table 6-3 (Continued) l TABLE ICIATICt1

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 9% probability (with M probability of falsely concluding that a blank observation represents a "real" signal).

For a particular measurement system (which may include radiochemical j separation): ) 4.66 s * ! LLD = ! E

V
2.22
Y
exp(-Aot) l i

where ! LLD is the lower limit cf detection as defined above (pC1 per ur:it mass or volume), s is the standard deviat.on of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E is the counting efficiency (counts per transformation), V-is the sample size (in units of r;as oc volume), 2.21 is the number ef transformations per minute per picoeurie, Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, at is the elapsed time between end of the sample collection period and , time of counting, Typir:al values of E, V, Y and at should be used in the calculations. The I,LD is defined as an a priori (cofore the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit.for a particular measurement. Amlyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions, occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or uncontrollable _ circumstances may render these LLDs'unachievable. In such cases, the contributing factors will Le identified and described in the Annual Radiological Environmental ' Operating Report. -For more complete discussion of the LLD and other detection limits, see ~ l- the following: (1) HASL Procedures Manual, HASL-300 (revised annually). ! Davis-Besse ODCM 120 Revision 6 l l l- .- . - . - . - - ...- - ... ....- -_-. - ...~.~....-...,. _ .. - .. - - -- - . - _- - Table 6-3 (Contir,ued) TABLE fKYtATICri --(2) Currie, L. A. , " Limits for Qualitative Detection and Quantitative Determination - Application to B,adlochemistry" Anal. Chem._40, 586-93 (1960). (3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques", Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

b. LLD for drinking water.

-c. If no drinking water pathway exists, a value of 3000 pCi/ liter may be used.-

d. LLD only when specific'an& lysis for I-131 required.

i f I i i Davis-Be:se ODCM. 121 Revision-5 Table 6-4 REPORTING LEVELS FDR RADIGACTIVITY CCtG271TsATIOGS IN CNIBGECirAL SMiPLES Reporting Levels Fish M21k Vegetables Water Airborne Particulate (pCi'kg, wet! Analysis (pCi/L) or Gases (pCi/m') (pcifkg, wet) (pCi/L) H-3 2.0E+04* Mn-54 1.0E+03 3.0E+04 4.0E+02 1.0E+04 Fe-59 1.0E+03 3.0E+04 . Co-Sa ) i 3.0E+02 1.0E+04 Co-60 ! i 3.OE+02 2.0E+04 Zn-65 i 2 r-t.b-95 4.0E+02 I' 3.0E+00 1.0E+02 I-131 2.0E+00 9.0E-01 1.0E+03 6.CE+01 1.0E+03 Cs-134 3.0E+01 1.0E+01 f 2.0E+01 2.0E+03 7.0E+02 2.0E+03 l I Cs-13" 5.0E+01 3.0E+02 Ba-La-140 2.0E+02

For drinking water samples, this is the 40 CFR 141 value. If no drinking water pathway exists, a valt.e of 30,000 pCi/ liter ;,ey be used.

122 Revision S Davis-Besse COCM ._4 I (, This page is intentionally blank. w ..~-.-.--- -..._ ~ ~ __.._._ _ ._ ~__ _ -._._. 7.0 ADMINISTRATIVE CONTROLS 7.1 ANNUAL FADIOLOGICAL ENVIRONMENTAL OPERATING REPORT , Routine Radiological Environmental Operating reports covering the operation ! of the unit during the previous calendar year shall be submitted prior to l May 1 of each year. Tha initial toport shall be submitted prior to May 1 of the year following initial criticality. The Annual Radiological Environmental Operating Report shall include summaries. interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report petiod, including a comparison with the preoperational studies, with operational controls, as appropriate. and with ptevious environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The repotts shall also include the results of land use censuses as required in Section 5.1. j The Annual Radiological Environmental Operating Reports shall include the i results of analysis of all radiological environmental samples and of all i radiation measurements taken during the period pursuant to the locations specified in Sections 6.1 and Appendix C of this ODCM as well as summartred and tabulated results of these analyses and measurements. In the event that some individual'results are not available for inclusion vith the report. the report shall be submitted noting and explaining the reason-for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the followings a summary description of the radiological environmental monitoring program at least two legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results af licensee participation in the Interlaboratory Comparison Program, required by Section 6.31 and discussioni of all analyses in which the LLD required by Table 6-3 was not achievable. 7 ._2 SEMIANNUAL EFFLUENT AND VASTE DISPOSAL REPORT Routine Effluent and Vaste Disposal Reports covering the operation 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. The period of the first ,eport shall begin with the date of initial criticality. The Semiannual Effluent and Vaste Disposal Reports (Semiannual Reports) l shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid vaste released from the unit as outlined in Regulatoty L- Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid l ! Vastes and Releases of Radioactive Materials in Liquid and Gaseous l Effluents from Light-Vater-Cooled Nuclear Power Plants." Revision 1, June 1974. with data summarited on a quatterly basis following the format of Appendix B thereof, l Davis-Besse ODCM 123 Revision 5- The Samlannual Report to be submitted within 60 driys af ter January 1 of , each ar shall include an annual summary of hourly meteorological data ' collected over the previous year. This annual summary may be either in the i form of an hour-by-hour listing on magnetic tape of vind speed, vind 1 -direction, atmospheric stability, and precipitation (if measured). or in the form of joint frequency distributions of vind speed, vind direction, 3 and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include-an assessment of the radiation doses from . tadioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the reporting period. All assumptions used in makiry these assessments, i.e., specific activity, exposure time, and locatson, shall-be included in these reports. The - assessment of radiation doses shall be performed in accordance with the aethodology and parameters in this ODCH. The Semiannual report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF-THE PUBLIC f rom reactor releases and other nearby uranium fuel cycle sources, including dores from primaty effluent pathways and

direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environzental Radiation Protection Standards for Nuclear Pover Operation."

The Semiannual-report-shall include the following information for each class of solid vaste (as defined by 10 CFR Part 61) shipped offsite during the-report periods

a. container volume.

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

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

d. source of vaste and processing employed (e.g., devatored spent resin, compressed dry vaste, evaporator bottoms),

e.. type of container (e.g., Type A. Type 3, Large Quantity), and

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

The Semiannual Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the repo-ting period. l _ The Semiannual Reports shall include any changes made during the teporting. L period to the PROCESS CONTROL PROGP.AM (PCP) and to the ODCM, as.vell as a li listing of new locations for dose calculations ar.d pursuant to Section 5.1. 1 -Davis-Besse ODCM 124 Revision 5 l l E_ _ _ . . . . . . _ ._. _ _ _- _ _ _._ _ . _ _ ,_ _ . _ , . - , - - ,_ - _ . _ _ _ , - . _ _ _ _ . 1 7.3 SPECIAL REPORTS Special Reports shall be submitted to the U. S. Nuclear Regulatory Commission (NRC) in accordance vith 10 CFR 50.4 vithin the tire period specified f or each tepot t. These repot ts shall be submi'.ted covering the activities identified belov pursuant to the requirements of the applicable references

a. dose or dose commitment exceedences to a MEMBER OF Tile PUBLIC from radioactive materials in 11guld effluents released to UNRESTRICTED AREAS (Section 2.4.1),

b. the discharge of radioactive liquid vaste without treatment and in excess of the limits in Section 2,

c. the calculated air dose from radioactive gases exceeding the limits in r ection 3.7.1, -

d. t; e calculated dose f rom the release of lodine-131, tritium, and adionuclides in particulate form with half-lives greater than 8 Q days, in gaseous ef 1uents exceeding the limits of Section 3.8.1

e. the cise: trge of radioactive gaseous vaste without treatment and in excess os the limits in Section 3.9,

f. the calculated doses from the release of radioactive materials in 11guld or gaseous effluents exceeding the limits of Section 4.2.

and

g. the level of radioactivity as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 6-4 (Section 6.2.2).

7.4 MAJOR CHANGES TO BAD 10 ACTIVE LIQUID AND GASEOUS VASTE TREATHENT SYSTEMS Licensee initiated major changes to the radioactive vaste systems (liquid and gaseous):

1. Shall he reported to the Commission in the update to the Safety Analysis Report. The discussion of each change shall contain:

a. a summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59:

b. sufficient detailed information to totally support the reason fot the change without benefit of additional or supplemental information; 4 processes

c. a detailed description of the equipment, components a involved and the interfaces with other plant systemst

d. an evaluation of the change which shows the predicted releases of radioactive materials in liquid or gaseous effluents and/or quantity of solid vaste that differ from those previously predicted in the license application and amendments thereto1 Davis-Besse ODCM 125 Revision 5

e, an evaluation of the change which shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and the general population that differ from those previously estimated in the license applicatir and amendments thereto

f. a comparison of the predicted releases of tadioactive materials in liquid and gaseous effluents to the actual releases for the period prior to when the changes are to be mades

g. an estimate of the exposure to plant operating personnel as a result of the changes and

h. documentation of the fact that the change was revieved and found acceptable by the Statinn Reviev Board.

2. Shall beenme effective upon review and acc.ptance by the Station Review Board.

7.5 DErlNITIONS 7.5.1 BATCH RELEASE - The discharge of liquid vastes of a discrete volume. 7.5.2 CHANNEL CALIBRATION - A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip it'nctions, an' shall include the CHANNEL FUNCTIONAL TEST. CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel ic calibrated. 7.5.3 CHANNEL CHECK - A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination I _shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived frna independent instrument channels monitoring the same parameter. 7.5.4 CHANNEL FUNCTIONAL TEST - A CdANNEL FUNCTIONAL TEST shall bei

a. Analog Channels - The injection of r simulated signal into the channel as close to the primary sensuc as practicable to vetity OPERABILITY including alarm and/or trip functions.

b. Distable Channels - The injection nf a simulated signal into the channel sensor to verify OPERABIt.ITY including alarm and/or trip functions.

7.5.5 CuMPOSITE SAMPLE A sample in which the me: .od of sampling empicyed results in a specimen which as reptesentatave of the liquids releared. , 7.5.6 GASEOUS RADVASTE TREATMENT SYSTEM - The GASEOUS RADVACTE TREATMENT L SYSTEM is a system that is derigned snd fnstalled to reditee tadioactive , gaseous effluents by collecting primary coolant system off gases and l providing for decay for the purpose of reducing the total radioactivity i prior to release to the environment. I Davis-Besse ODCH 126 Revision 5 I 7.5.7 LOVER LIMIT OF LETECTIO'l (LLD) - The LLD is the smallest concentration of radluactive material in t. sample that vill be deter.ted with 95% probaollity, with 5% probability of falsely concluding that a blank ebservation represents a ' teal" signal. For a particular measurement system (which may include radiochemical separation): LLD a 4.66 Eb L

7
2.22
Y a exp(-Aot) vhett LLD is the lover limit of detection as defined above (as pCi per unit inass or volume):

Sb is the standard deviation of the background counting rate or of the _ counting rate of a blank sample as appropriate (as counts per minute): E is the counting efficiency (as counts per tiansformations); V is the sat.iple site ( in units of mass or volume): 2 22 is the number of transformations per minute per picocurie 1 is the fractional radiochenical yield (vhen applienble): A is the radioactive decay constant for the pattitular radionuclides and at tot plant effluents is the elapsed time betvaen the midpoint of stmple collection and time of counting. S It should be recognized that the LLD is defined as an a priori, (before the fact) limit representing the capability of a measurement system and not a an a posteriori (after the fact) limit for a particular meartremen t . 7.5.8 HEMBER OF Tile PUBLIC - Member (s) of the public r, hall include all persons sho are not occupationally associated vitn the plant. This catagory does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons vho enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site ir recreation, occupational, or other purposes not associated with the plant. 7.5.9 OPERABLE - OPERABILITY - A system, subsystem, train, component or device shall be operable et have operability when it is capable of perfocming its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources cooling nr seal vater, lubrication or other auxiliary devices to perform its function (s), are also capable of performing their related support functions (s). Davis-Besse ODCM 127 "tvicion 5 l i 7.5.10 PURGE ? URGING - PURGE OR PURGING is the controlled process of dischatging air or gas from a confinement to maintain tempetatute. prassure, humidity, concentiation or other operating condition, in such a ranner that teplacement air or gas is requited to purify the confineRent. 7.5,11 SITE BOUNDAM ~ The SITE BOUND /sRY shall be that line beyond which the land is r u ther ovned, nor leased, nor otherwise conttolled by the licenses. 7.1 12 SOUDt'E ChTCC. - A SOUPCE CH3CK shall be the observat ton of channel t; scale temponse vnen the channel sensor is exposed to a radioactive source. 7.5.13 UNRESTRICTED AREA - An unrestricted ar m shall be any arch at or beyond the SITE BOUNVAhY, access to which is not cot.ttolled by the licenses for purposes of protection of individuals from exposure to radiattor or radioactive materials, or any area vithin the SITE BOUNDARY used sor resinential quatters or for industrial, commercial, instituttoral, and/cr recreational putposes. The definition of untestricted area used in implementing the Radiological Effluent Technical Specifi<ations has 7 been expended over that in 10 CFR 100.3(a), but the unrest.icted area does not include areas over water bodies. The concept of untestricted areas, established at or beyond the S11E BOUNDARY, is utilized in the Tethnical Specifications and the ODCH to keep levels of radioactive matetfals in liquid and gaseous etfluents as lov as is reasonably achievable, pursuant to 10 CPR 50.36a. 7.5.14 VENTilA 10N EXHAUST TREATMENT SYSTEM - A VENTILATION EXHAUSl TPEATMENT SYSTE*d is a system that is designed and installed to reduce :adioactive u.terial in particulate form in effluents by passing ventilation or vent exhaust gases through HEPA filters for the purpose of temoving particule.tes from the gaseous exhaust stream prior to telease to the en.ronment. Engineered Saf ety Feature (ESP) atmosphet ic cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEH components. ~ 7.5.15 VENTING - VENTING is the controlled process of discharging air or gas trom a confinement to maintain temperatute, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not ptovided or required during VENTING. "ent, used in system names, does not imply a VENTING process. Davis-Besse ODCM 128 Revision 5 f 1 n i APTEllDIX A Technical Basis for Simplified Dose Calculations l Liquid Effluent Releases j I r .h i .i . t i I i f i i e t i. Davis-Besse ODCH' Revision 5 f ,,n.em.e# w s. ,m m.,%,,,h,h,,m.,wm.m.,-, d .- ,,w,_. .y',ee ...,m.he=,-,- ._y,.e,., +,_,ww. -, mg ,wm-cf e 3.. , v at -gv*f 4 wF'**-* =4 k -.g 6 e This page is intentionally blank. l APPENDIX A Technical Batis for Simplified Dose alculattens Liquid Effluent Peleases OVetViDV To simplify the dose calculation process. ;t is conservative to identify a controlling, dose-significant radionuclide and to use its dose cenversion factor in the dose calculations. Using the total release ti.e., the cumulat.ee activity of all radionuclides) and this single dose conversion i factor as inputs to a one-step dose assessment yields a dose calcu.ation method which is both rimple and conservative. Cs-134 it the controlling nuclide for the total body dose. It has the highest total body dose conversion factor for all the radionuclides listed in Table 2-6. Therefore. the use of its dose conversion factor in the simplified dose assessment method for evaluating the total body dose is demonsttably conservative. The selection of the maximum ergan dose conversion factor for use in the simplified calculation requires consideration of the prevalence of the tadionuclides in the effluents. An examination of the Table 2-6 factor vill show that the Nb-95 dose factor for the Gl-LLI represents the highest value (1.51E.06 mrem /hr per pC1/ml); and the P-32 bone factor (1.39E*06) is similarly high. Ilovuver, neither of these tvo radionuclides are of significance in the Davis-Besse effluents. Nh-95 is not typically measured in the liquid effluents and P-32 analyses are not even performed. (NRC has ca t egorically dete:rmined that P-32 is not a significant radionuclide in liquid effluents from nuclear power ptants and does not requite the special tadlochemical analyces needed for identification and quantification.) The next highest dose conversion factor is for Cs-134 liver, with a value of 7.11E405 mrem /ht per uCi/ml. Cs-134 is a prevalent radionuclide in the liquid effluents from Davis-Besse. Therefore, it is recommended that the Cs-134 livet dose conversion factor be used for the simplified maximum organ dose assessmer4t. Davis-Besse ODCM A-1 Revision 5 l Simplified Method For evaluating compliance with the dose limits of Section 2,4.1, tre folio ' simplllled equations may be used:- Total Body 1.67E-02

VOL I D

tb * ~ ' ' ^ (Cs-134,tb)

IU t (^'I) pp 3 g where D

tb = (i se to the total body (mrem) VOL . Volume of liquid effluents released (gal) l DF - average Collection Box release flov (gal / min) Z .- 10, near fleid dilution A(Cs-134,tb) . 5.81t+05 mrem /hr per pC1/m1, the total body ingestion dose factor-for Cs-134-t EC g . total concentration of all radlonuclides (pci/ml) 1.67E-02 . I hr/60 min Substituting the values for Z and the Cs-134 total body dose conversion ' factor, the equation simplifies tot 9,70 E+02'* VOL . , l- D tb . -

EC 3

(A-2) i-97 Haximum Organ - 1.67E-02

VOL-D max

( s-134,11ver)

C g M DF
Z.

where: - D,,g_ . ms imue organ dose'(arem) . 7.11E+05 'nrem/hr per pCi/ml, the liver ingestion dose ' A(Cs-134.11ver) factor for Cs-134 ' Davis-Besse.0DCH A-2 Revision 5 l-5 --~e-, - --,r,. , - . ,% y <-pq. --wa...'e++--+-+r iw-+ .we ,e .cw#,- -n,w 4,,v- v e .,.w.,, ~-,---w,,-- ,ge.,-,,-.., , -_.__.___.____...m.__.___.__-. . l 3 Substituting the values for Z and the Cs-134 liver dose conversion factor, the t equation simpilfles toi ; 1.19 E*03

VnL D,p =
IC t (A-4)

Tritium should not be included in the simplified analysis dose assessment fot , liquid releases, The potential dose resulting from normal reactor teleases of H-3 is relatively negligible. But, its relatively higher abundance vould yield resulting simplified doses that vould be overly conservative and untealistic. Excluding tritium has essentially no impact on the conservative use of this recommended simplified method. Furthermore, the release of i tritium is a function of operating history snd is essentially unrelated to radvaste system operations. i 1 r i Davis-Besse ODCH- A-3 Revision.5 g , v .,.m .....s m.,_._. . . . . . , - . ~ . ~ . . . . . . . ....-,..._,..-4,y...-.--,,4,_,- .----,.,-,~,.,,,-,r,- . . t,'._, _- . , ' _._. . _ ..-. _ _ . _ - . . . _ . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . . _ _ . _ _ _ . . _ _ .. v ti i h i t h t I t k .i b t This page is-intentionally blank. , , c c.. ' k .- b ? a ? s t e + 'F +

i w.-w..'w,.r.

.'yrwU.,-.., yswa. -H 6 wr,.m,y., .,rw.w - = =r,r- td-- e w. s , w w e---r-, r-4 e w+w a m e t- e n t v ew-v ry'- _....._____ _ _ _.. ..-____.m _. 4 i l 1 1 1 APPENDIX B Technical Basis for Effective Dose Factots i Gaseous Radvaste Effluents i i L ,I k r Davis-Besse ODCH Revision 5 T1 *t T T T F M 9d *++w"> -1 t r 32*f -w wtd--o-r+wr- ve e~'-e- - rM*ev= w e e *, w w e-v es --en e- mt^-r=+= u--- =r-v-* -**** r**r- w---mm , a~.- _. - _ - --_ . _ _ _ _ _ _ _ .1 e d I l l l I i f f 1 P _.m This page is intentionally blank. 4 = 5 ? g(g y y +y-w-vr,-e ey-my- 93 y 3 9 y -, yv,y, www g 9, s.r.g g _'*3g,,,.,g , y < m m.-c v f v m "d*M*8 -*--'e=** * -w o- TW-e *em+-4---* e- -4M== e re c- % e v or ~wwr-rn=---: writ-++w.+e v oe : e s -- - . . . .- . _. - _._. - .- . _..~---- - - _ _ . - _ . . . - 4 APPENDIX B Technical Basis for Effective Dose Factors Gaseous Radvaste Effluents Overview Dose evaluations for releases of gaseous rad'oactive effluents may be simplified by the use of an effective dose factor rather than radionuclide-specific dose factors. These effective dose factors are applied to the total radioactive release to approximate the various doses in the anvironment; i.e., the total body, gamma-air, and beta-air doses. The s ::tive dose factors are based.on the typical radionuclide distribution in the gaseous radioactive effluents.. The approach provides a reasonable estimate of the actual doses since under normal operating conditions, minor variations are expected'in the radionuclide distribution. Determination of Effective Dose Factors Effective dose factors are calculated by equations (B-1) through (B 4). K,gg - E( K3 *fg) (B-1) where: K,gg - theeffectivetotal.bodydosefactorduetogamm3 emissions from all noble gases released (mrem /yr per uCi/m ), Kg - the total body dose factor due to gamma emissions from each , noble gas radionuclide i released, from Table 3-5 (mrem /yr per I 3 pCi/m ), and fg - the fractional abundance of noble gas radionuclide i relative to the total noble gas activity. (L + 1.1 ft),gg - I((Lg + 1.lM )

f )

j 3 (B-2) where: (L+1.lM),gg - the effective skin dose factor due to beta and gamma emissjonsfromallnoblegasesreleased(mrem /yrper UCi/m ), and (L g+1.1Mg ) - the skin dose factor due to be.a and gamma emissions from each noble gas radgonuclide i released, from Table 3-5 l (mrem /yr per pCi/m ). Davis-Besse ODCM B-1 Revision 5 Mdf = I(Hg *f) 3 (B-3) where: H'- the effective' air dose factor due to gagma emissions from all noble gases released (mrad /yr per pC1/m ), and M .. 'he air dose factor due to gamma emissions from each noble gas 3 3 radionuclide i released, f rom Table 3-5 (mrad /yr per uC1/m . N df" TIN I *I) I (B-4) where , N "U = theeffectiveairdosefactorduetobejaemissicnsfromall noble gases released (mrad /yr per uCi/m ),-and Ng - the air dose factor due to beta emissions from each noble fas radionuclide i released, from Table 3-3 (mrad /yr per pC1/m ). Normally, past radioactive effluent data vould be used for the determination of the effective dose factors. However, the releases of noble gases from Davis-Besse have been exceedingly insignificant. Therefore, in order to ensure ove all conservatism in the modeling, the USAR estimate of radionuclide concentrations.at the site boundary-(summarized in Table B-1) has.been used as the' initial typical distribution.- The effective dose factors derived from - this distribution are presented in T4ble B-2. Ay lication To provide an additional degree of conservatism, a factor of 2,0 is introduced into the dose calculation when the effective dose factor is used. This -conservatism provides additional assurance that the evaluation of doses by the use of a single effective dose facter vill not significantly underestimate-any actua' doses in the environment. For evaloating compliance with the dose limits of Technical Specification 3.11.2.2 the following simplified equations may be used: , Dy = 2.0

3.17E-08
X/0
H ogg *' IQ 3 (B-5) and DS = 2.0
3.17E-08
X/0
N,gg
IQg (B-6)

Davis-Besse ODCM B-2 Revision 5 .. . . . .. .- . . . . . - - . ,. , . - ~ -.~_. . . . _ , . . - . . ,_- l V vhere - Dy . , air dose due to. gamma-emissions for the cumulative release of all noble gases (mrad), DS = air dose'due to beta emissions 'for the cumulative release of all noble gases (mtad), . .X/0 ;- - atmospheric dispersion _to the controlling site boundary (sec/m3 ), M,ff = 5.7E+02,-effective gamna-air dose factor (mrad /yr per uCi/m3 ), N,gg = .l.lE+03, effective beta-air dose factor (mrad /yr per uC1/m3 ), og = cumulative release for all noble gas radionuclides (uC1), 3.17E-08 =. conversion factor (yr/sec), and , 2.0 = conservatism factor to account for the variability in the effluent ! -data. l

Combining the constants, the dose calculation equations simplify tot i

Dy = 3.61E-05

x/0
IQ g (B-7) :

and DB = 7.20E-05

X/0
I0 g

. (B-8) - The effective dose factors are used-for the purpose of facilitating the timely. o assessment of radioactive effluent releases, particularly during periods when the' computer o'r ODCM software may be unavailable to perform a detailed dose assessment. p L l~ t. l l Davis-Besse ODCM B-3 Revision 5 = ,e ~- ,;. ... . _ _ _ _ . , . . . . . . _ __.m.- _ . _ . _ . . - . . _ . .. _ . . _ _ _ _ _ s 4 4 -s i Table B-1 " Default-Noble Gas Radionuclide Distribution

of Gaseous Effluents

-Fraction of Total = (A g / I A 3 ) Containment Station- Vaste Gas-Nuclide - Vessel Purge' Vent Decay-Tank Total Ar 41' O 0003- 0.004 0.004 ~0.003 Kr-85 0.12 0.012- 0.034 0.06 , Xe-131m 0,02 0.009 0.008 0.017 - Xe-133m 0.005 -0.011 .0.011 0.008 Xe-133 0.86 0.94 0.92 0.83' <^ Xe-135m -- 0.004 0.0034- 0.06 Xe~-.13 5 0.002 0.02 0.02 0.021 Total 1.0 1.0 1.0 1.0 + h ., -NOTE:- *- ' Data' adapted from Davis-Besse USAR Section 11.3, Table 11.3-13 and Table ~ 11.3-14 Kr-83m,=Kr-85m, Kr-87, Kr-88 and Xe-138 have-been excluded because of their negligible fractional abundance (i.e., C 1%), I 1

i

.g ? lL Davis-Besse ODCM B4 Revision 5 v .. . Table B-2 - Ef fective Dose Factors - tioble Gas Ef fluents Total Body Skin Dose Gamma Air Beta Air Dose Factor Factor. Dose Factor Dose Factor Isotope ~ Fractional. K (L+1.1H M N Abundance. (mfemfyrper (mremfyIhe)r($bkdfyrper(Ehkdfyrper UCi/m ) pCl/m ) uCi/m ) pCi/m ) Ar-41. 0.003 2.65E+01 3.87E+01 2.79E.01 9.84E+00 'Kr-85 . 0.06 9.96E-01 8.15E401 1.03E+00 1.17E+02 Xe-131m 0.017 1.55E+00 1.10E+01 2.65E+00 1.8BE+01 Xe-133m 0.008 2.00E+00 1.08E+01. 2.61E+00 1.18E+01 Xe-133- -0.83 2.44E+02 5.76E+02 2.93E+02 8.72E+02 Xe-135m 0.06 1.87E+02 2.64E+02 2.02E+02 4.43E+01 Xe_135 0.02 -3.62E+01 7.94E+02 4.03E+01 5.16E+01 TOTAL 1.0 4.98E+02 9.89E+02 5.69E+02 1.12E+03 f = Revision 5 ~ . Davis-Besse ODCM. B-5 . . . . ~ . . . . . .-- . . . . -. . . . . . ... - s: A 1 ? s + b This.page-is intentionally blank. 1 = ,.e--- w rv - --+,w - we- +r . --* - - - * -7 t 1 4 i ? - APPDOIX C Radiological Environmental Mo.11toring Program Sample Location Maps 1 E '. i s -( s l: l-lj, Davis N sse ODCM Revision 5 4 _. - m -. _. _ - . -- 5 t i l 1 -This page.is. intentionally blank. 1 .a 't T' k # $ I -- g __ _ _ _ _ _ _ _ _ _- . ._ _ __ , _ ,___, . l; ".

i. \*-

- _ ~ \ .\ - ~ * ".s

g

=.*.,.~.Y ~. ...a. ... 'g ~.*"* *** .... 1. .~ .." .. \, [ .g lp a m e T. 7 h _ S U. ' _ ir W W DL - ;a)i / A S e . S. T . h 1 qSW O ~ ~ t o 2-o N f ' , 4

y-.
T

[ yi t $ -. r n een. ,- , eU m. .\ . ,' - h g' " pn y... s - s G K i -

r. o s N ei t p'- - I

\' pa f R t

O eS 1 / 1,,

- T y - I t T. , N s re i m / .. O m s s pe ew M ho t P _ sgx' ,t ,Q. ,~ - / / f, \ m . L A T n r ~ ~ .c .\ 8 4 N o a ~ T

t. E

_ se *~ - . M N n c l [, . O ou :,4 ~'/< j\ ~- - . i n 6 - R N o - 8 _ . t T 2 , I a - < \ \- L. V . oc e T. N l ss e ]/ _. ( . \ y" . .. E g; i _ g _ _ g . nB- .k lI , \ . - c.f l - i . . i - l s . n ,c[ : pi 7 a_ _ 'a / J .\ mva x 4

T_

\ h 0;a 1 / I k Tq - SaD \ N - \g-7 . > i 6 - T g_ l . _ i N 4 ,M p. .. r ( ~ M r \ \x/L .,g ~ /, f. / f ' . [\ 6 ~g4- \ \ [T ,/ _ d4- . m_~ ,m,J / .T-4 . 1 1 9 * . I 4 T / mzt" - e. \' = ! 4' 1 T ,U ,,- -}1i 3 . ih((.i .. ,.f1 N 3' ;.5 /, '\ ' N .\ e-i m .7 . 4 G<r */ pee. oQM t 9 q- i u Sampling locations (excepting those on the site periphery). Davis-Besse Nuclear Power Station, Unit No.1. NW NHW N NNE ? 3 L*** .. O[s.,, wo) * '-as G . NE { WNW .- = o .= g 1-33 Put- a g 9 Orego ENE ' @ Lake - 12, N ,1 Erie e

1. 1

- g / '# Z g-" s )\.s. - n: / -E ; 4 1., oas 3,) "" ma , gyer P J lir - (9$) Sandusky j g [ - say 3g ,,.3, ENVIRONMENTAL MONITORING _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ . -_ J , , . : :l {

3. I No \

\ \yy . s N F O W E N E C . 3_ l ' E ; E L W i - I i M N - I 1 6 m - 2 7 ~ - T 0 ( . , H ; y T .. t R n W [ N O N i/ n U a N O I ,yT 7- . .. e i i s S A T T c* ' i m = ) ,g.-A 7N;~~ lj _ J' , E t . Vq. I j ,' R E \ \ 3.g-s 1,' Ea .p E t iY ,MP! X A L veeyr[.f e, s -s e es / y O t . E m O P S l oP' MU E nA / l A -g UO 'P H 3 l ~ w e T! oy mL ,g$s< .~. w ,

,,m x

r '[ .g' t Lake Erie - e j' T-2. SITE g)lJg)ARY, 0.9. Milf E OF. 3 a swim. f W STONE HOAD .I WOODS WOOOS n j~ ., [ 84Rmcaos v '% d N # #' ' ' '~' I h / p. / x o 'I . \ s j ~ p ~m hy /kNcw -" \s ] T ! l C# 5 c ][ P N a i '}, T s\ t . i,fa#-$ xx N.- y _, 1 m [e.5 \ h l t a I y . .. . - . . - . . - . . ? -4 f . / - i xc , I/ ~ -I o e G - l i kN 7 W n ,. 't. o o

l a

t s

i. O Lu o l t

- t . :

_ /rw I

_I ~1'l / n L ,/f/ ._ I j \ / ,/ , \ Y 5 / / i y H- ' / p ' J I m g b N I I x l , A e g .- i \.y 1 ) : 7 l ,j i j i ,. O sl1 W M :a >l wn v , >W /y ,.. , { - - Davis-Besse ODCM C-5 Pntsien 5 .3 l - - / / ,,/ -41 ? / !/ I' \ ;l .i' e \ ~ e I g = f' 1 <. \ ^ 3 l - 9-8 8 3 I Ut d7 n I I% o i $ p g' ? _ !J w n .- , ." / y i 'f l / 1 k [aB w Y cx: g 5 m !! w se se ! Ub T)$$ i j 3;- cs g - e z n =. o o d k $- $ i 9 ; -g g - l

3 waa E MW

{ -.

i. Q /

l J 1 Davis-Besse ODCM C-6 Revision 5 l l .- +~ . - - h4 _ A ~ I.O g T-5 i%Ill ENTRNEE TO SITE, 0.50 tilLE -g j 9 W 0F STATION. DBAB t t > v N ' ? i 6 DUFF W ASH A' RD. ~ D POND , \ . ;OOLINC , TWR N, \ N ' l

p. -V- ~ -

3 ; . 7 P ARKING LOT T-5 TLD * ~L " o a ON LIGHT POLE j ! DUFF W ASH A RD. ,s m J *- m. .p- - 'wem _ -p 4m-*e 33 a Mn 6 e n ,. , . _ . . ~ 4 4 z .L/- / 'e / *l "/ ..s / .- , k, . . (~ _-__ _ , / I g / / t ; y ;"- l-s # A \ j

e

. :c;:3 , . . . ., . .....;....... . & x / ;3 + a.o ... .... . . . . . a. . . g ,a .<. .. . ,, n ~,.. p g], .:: 4 . .n....e. a s/ n l; p(: . :;.~;:: 1.;,R' ';:: .* C V~t%'~$n

t. ';.' .l:,' .;; . ;.. :. ; %

. . . .. .. .. l .; ; , - , ,A..;; yr, jJ '; A '0l.':'h.0... . .. :j ,. .i . . , f . ... . . . .+ . , . .,.. . . . .. . . . . . . .+. . .. .. . . .. . .. . . . . . a.. .. . . g:: . . ..g, . . . <;a, , 4 s + ep3 . . ',;'s., - [- . , i . %. . . ' 1. , . .~ .. 4. .. - j' l-- ..e - ;,te* i, . >. ..- -e i. ,4 . , ,..'9.* 4- .- +- - ,I ,. , n. . . . mp ". . . ; ,5 'n .t**4 '4..., , 5 . & J +' ., 4 . +' '; j t + *(.' . ', ' . . Q up m .1 4 . 3 e., , * * , ,..* . 4 . 4i . , . - i E).v,..a. t 8 o ,. . g'.4 > > + i'5 i"' FA g ., [I 9 .; , +*' I k .,..44 g ,. . , . . . . +. - . ..4 w . i.. -I 4,...+. .4i 4,, * ,i. ' . *, .

i. . .. .

E' .. ). ,,g, g .. e a J-navic nacam onrM c-8 Revision 5 g a' 2J- A L & , _ 2- w JL 3 'A-M'< d 4 A- pm AI w 4 A- 4 ?==J=+ 3 b _b nW -t 2./ , ~ p ~ o g J # so *& +<n?; f f-e .I13SS0W u " 2;C p 2 . # 'q v" 9,fm w . O Vs, j W l

e. =0s

.= 4 g. m; -a , + c . 4 / .=w uw f -Qw_ s n we g y f No k 9 pN. Q. '%y f$ o 'O anovos s* 1 $s #E = ' ou 11assne < 1 i , Davis-Besse coat C-9 Revision 5 j - e' .~? '.[ ~ ; ~ 1 NO B. Dk W S W i e - e y S r _ E L E - I M e . k ._ g.W 8 7 a . - 2 L , T , ,_ M R 8 a A T T F . m . E N -

o " *t R O n _

J, _ O I o - N 0 T P A o T u L S s R A F E O g - o~- sot TT H C iD _ t 'o n - . & Rn r a 8 B 8 - D E e T w E H Ao ' SWT .T V ^ J .Q g 1,E 4 1 O O 2i D g>E R R H C el% O I a D O M 1 ' l Qi i? a Oy ; ?a {;wa u i ) a- , e C 1 E r l A e m l b fou ?oviuod.~~1Niv S 0001 /aei ^ 6 #Ih 4 = '08 30V1 hod-INIVSSnO1 ,, W o " 5 mz w m g mp Oo ' p $

c g

5<< g >- .i 0 to a m 5 , ; ei xm ~ H < .7 i m E oe 4a e G .s y 5._. h w b ) Davis-desse CDCM C-ll Revision 5 l 4 4 .aMa. -- A ,.A.!-3 Py,J 12A7 g- * . nf i- a c 4 a. scA. r a.-,dp'4 4 L A 2O._ 4 ' -- N. y l c=. > [.. '1 . K. ., __ / y: m . ~ " - ~ , [ p,, rij y F 4 -i. ; gg E n Ne , ' ^' \ f( ,g . 'l ] M p .j %gg, y d j p%gp --,- r v1f c - 1 ] ({_f:3K.4, , p . . t -r , }' y i .. 1- . >_ g - 4 e Fr ' i . ,, / g a ,, .

- i 8, ;

.m 8 w 4 ,, f 1 - s x , 1 , . w," 1 j ,. .c peoAp*A8d .yi- [- v . k, Z< S m - a . - Da 'is-Gesse ' ODCM C-12 Revision 5 i .evk 4 , , . ~ _ r r - - * - - .r. h Z(- C *y W %, ,Nose: 4.rg e . -E- t 9 5 _ w' . .Q~y A @G s2 . / g3 . a . i .

.3g b 5 E

9 ~ % / i ; o \ ) H w -W E . m -] c. c,=. g. e $ 4" $ -- l c < %.n ,e- > o o m . }. e 4 9. < m w. E o to -. e e i 9-

o

.c ' 1 g- g - .. p \g- - .t E85ss- -o oprr< ' E \. o$0i a g x N L .h o >= . E-1 DNIMWYd Add 3d A V 9 NI+10d Davis-Besse CDCM C-13 nevision 5 t a. . O j " c - o 9 A si . '! !<' h

o 5 #.

ww ,4*>I5 k c . y. p ( 15 OM133MM j7 4 < I{ za E d~g~ o 'e' x I 8 lg '+ 4 ' i E ci A $ g 8 ~ --t~ *+ E m 9w$a 5 e8 G o e a ; 8 5 55 C @5 g # #5 ! !I Zh 5 d 9g sn iS n-N e e 1! El x _ : a: O ., 3 ( : x m l (f . - = 0 l

s ..

m as a- - h g!e g:e ; x si s ! 8 T* O " 8sls9=d "*w e i ik 4 L _ ) Davis-Besse ODCM C-14 Revision 5 ..,. i . f. . l 7 a W $e '. wg1

9 5g5 k LL

. 3 g N o R nc

v.

b -- t.f> , .s g - - Q, - _f 3 a 'ou alu311 , et v3 6-- c ge - . ) ~ ! [ s? a b r i 8 e \ n r A =m EE I o ZD E $ -- E e d S z E . w j k = ~ ! h eg . 3NUO 3NOIS g $. > T 2 g . E .. ~ w & z 8 CL g' E < 3 o- E $OS

E 5*

s 8 5 : 3 $y $ m m 9 ^ J Davis-Besse CDCM C-15 Revision 5 ~ ( ~ r i .) s' p m yseJg j _ ,1." N. s , . s :8 g, - > e g - .a -, s - ."51 ' bl X '- . s . . N b5 3 ,: .

Ng \ .

s A k... ' y g,.. I it s ! ' ~~"" -f . h ,- , . s g 4 k . s , s pmyseJg .. -L _-. s , . s N- 'Nm N . .Iw . .. . o' > s a = - 4 5

j s

j. en g

'- ' = s . = ~ co. 9 % s s - s h .. as L .,

s MQ s

gm . .e w8 s . s +-

g. j Davis-BesLe ODCM C-16 Revision 5 U

y r v- , , -- - 3 , 4 f 3 E ' rgm mt . o -1 H.- / : a g l .V fg E@ /' .- [ ._jy_ y r- t 1- ./ t - i / a, / CP / - s /. \ b =e -- ! 1 ; ~ l m;- _--- . II O '1 - - . _ I - b 7 (~',J!(l[Wfy[Yhf

n r

s . t l rg!-hg.8.,%. . .W e ,, E **,w.. i - I ll l { 1 l t J i Davis-Besse ODCM C-ll Revision 5 l: r 3 b i ,,,....******...................**fS31iW ***....,, ,s ...,*... n MO j...***., s ex

r Hc *

/ t m. m < Toa '. / WQ '.

z l ....-. .

l \ \

t 0 t x .

-! -m "o i j Ny d / s i i W 5 i i -$. 3%. o e N cu zin31 f \. .< s 'G. .I . z m e < $ 0 o / . 3: , r e e - ' w 2 9 u. r < ./ . , 2 2 / ., o - $. . N / le 2 / ,. ., . s ii og ,k si w 2 y ./ -25 H. '. 9;, < <C *- e * **.,- P g .t e .M M. g - < o ty so. o /. '. h s,*, , r , * , * .' +. . , @,, 8 ...*** *' %'.4, ,49 7..g .m............. Mgtn i H-I Z t = I i:

3 1-y c:

! W WJ t > Davis-Besse 00CM C-18 Revision 5 v *- , .- ,r g 3 .... ,,,..... --*** ---. ... ro

g. .. ,, ..

T-31 - g ~~.. 4 ll m LM ERIE, GREATER TriAN 10 MILES O- /*. , FROM STATION. ~ . S : l . l ~ ^ LAKE ERIE \ l \. l oi ' dY T f6. ddW(. it + I - . . w~ .rtoun t..m a rp.oe, +-: - . _ : T-35 N l GRD - 7-I w-- x/rsp s g r n.~ . ~

x*.

1 / N" 8-OAK HAR8OR, Q . . / O ORNf . 5 tin y o n.f sn

o ** *.
n .*.

sP */.- ,s ,..*-a.............-*....*...**.... o j - * !i! ; ;;,i , !- [ . 1 e . - = w 1 _ A 5 h > B. No w D-A / r . - k-g v e-a E S U p O H ., '; ? s s e L l 3 s 0 2 M , I j . 9 7 6 6 3_ f 1 l O 7 .D' N 3- A'V T T S L. N. G TO - GU' I I S R F 'Y , 5 0 P 1 S I D E R 0 1 A E E T .R 5 A A T . 0 S N .G O N 1 7 , I .I 3- T T . K R A E T EA R S T P T A M F U O M O , R W A S F R S S E P I O N M E 3 B .1 I l 1 e ?y= ' gg O g<E8 o t - i < r 3 g{ ,. am m, *' . -m .;,. :; . : ' .. . . , .;; : , . ', '< tvQ v,/ ms . .... ,. . .+ .,. , - >- y . ., :.1 . M, 9 , ,4 . t t ,J / o . . ;. .,. ;,l p ,'s , p ;.,. ' / / i ,3 , , .,. ,'s, . .,,' .'. 6 '. ip 7 - .. , , , + , , . , , i / i l' { ,4.*.,.. *', s' i . ... ,t . . . . . ,, , l g ' . . , * ,. , ' .. . , ' . ,', , .: . . ~ e ..,s. ., . N. .q . , . ....,.,4.... p..,,.e., i, . , . ..i - xx i .4 . ... ys , > .~.... . . . y, .n .: i >p ,: , , .; . .:; . .n . ... . .. .... .. .. . ; c ; , .f.i.' (' .'. 'j ? ~. . . . . . . . .;'.Y,c. ,;'!j? . . .. . .., . v . , ,xs . d < ,' R w,d,r_ P yP- v -e ...,...:.. . . . . , s. ,v. wy . . . , . . .. , s . + ( . . . .. . . . . . . . . , . . .* .. c7 . . ,. . ,- , ,. 4 . . c. . . . . . ;. m . , , . . . . . . . ,..*....4 .;,. r u, .,.... .o . .e . .,',.+..,,.',g. . . :. ~ , , ~ . s : < . . . <. .. . , = . . . . + . . . , . . .,,. l-- 5....

., .,,,,..,,.....,6-

. ,.....,,.,. ..,+.. 4.t . . i i , og,,,, e 'l . 'ca e ..;. b ./;'. .. .?.,',-). .>, ng ii. y,V , , , 5 y ( , ;,'. . j ,,m, . +.,c+,.;,.'. ., s . , , ..' .4.. a . . . . . .. , . m

z. * .......

.,9...., . . c, ,' c +,;....., ,. . . +* .. L ,l., .. W p . . . . .. ... ,.. ,.. ,.,.,,.4 s m. i 1 . . . .. .. .. .. .,.. . . t. p.. .... .. .P , +,,,. .,,. e. ,N ,.,, c.. .. .. . , .,,

u. .

. ...c,,..:,,...,,.-, . .. ...."..'...'l .. v_,+,.... r , ,,4,,,.,.,,. . . .. . ... ,...l.,. i . ,* .. o, . . :. . -, ., ; .4 . . , ; + ,. + . . . i .,,.. y, , . ., '. . g ,. m e > Davis-Besse'ODCM C-21 Revision 5 l t r - t[ . - Z J q ' ww 4 * . ~ -- 5. . . . ... ,. , . . . , . , . . , 9 i. . . d ..',i,.>>,.,..*,,.j,. . , je a 1 .: ,i ..e,..3* ,- i a ')t , . . , . ' .. > ,s... . : ' I l , ..' '.).... i:'.; :.' (:. .',ll 0,, . V_ ., t .*';.. i . j, vt Y ,....'....y. . Ns ~3 y . ,) l,,q} ;) ,) .....,.*9 . . . . .. .. .s . . ,. , s, . I gq: . g 3g,Os .;.' ,.'.s.'".; , .:. ', . ;;;,; . :; .' . l ..6,....,,, ..s...,. ...t.,..,,. . 4 x ;l w ; g ~ 4: , y.+ ~ +, . ', vpW,/-c i.+., s u.--.9 * ',b t %q ~ .5 v . .. ....:.... . ,: s . t -m a x/ <r , , '. . : s....'. , ,,.4 , . . . ,..,,4 o, . . c, .' .; . ,.s'. . . .,: . y ,,. T, .l .l~

l'!: , .; '.'.' .' *: 9

..,.. .. .,.... m .. .. .. ., . . . . , . .. . . . . . . , . . - 3 . . , ;1 ,s a <... ..,*.,,..,. >..,,.4.......

e. , ; . < .

.. . . s...,., m, . . , . , . ; ,I ..,, . . : . o .. ;... 5, a., : . .. . , . , .s ', . . e . . . . . . . n. .,.. .= a.. a, ,,. .z..., s. . h , .4 , . ,4...,..,4. .. .. .,., c; l , . .. . ,. . , , . . . a a . . ......, > s . . , , . ,.4,+ , ... . . .... .. ,, ,. ,. ,. , ,. . .z. , i . . . ,l . 4. . ... . g. ' / .1 g ; .'. l,, r. .". +; ;. 4 . . . . .; ..;/. g ....l..'.,. s.

. 4 . . . < . . +. :'+.

-9 zo. *.. ,,,n .. . . , . . . . .. .... .. . ,. , . . ' . - ..i..,........,...,i,.. ., . 0 , , + , . ,*.... ... . . . ~ ., * ...i).. 4i 4 + '. j , 6 ., 4 l j .. .'.,*4. 4. ' g} . . ),'.>. .. '. ',. t ,. ei. c,',..,. . 4.,. 6 , . t. '$ . e . . .'. hai - ,,i . t , . . ..i.. f... . r*. .* . 4 .. .i.'e.. . . i. 4. . . . ....n.. '. e.,. .. w .y. 4 .,, , . 4 . , ...y, C; > , g , . ' ' ,' . ;' ' ' '[ ,'.' ,. 4 / 9 ', ', . ' ' ,' I ' *. ,l'. 4 ,' 4g I ' I l,. ...,, +.. . ,. . . . . . . . . ,,.,. 4. ...<...,. . - . . . . .. . .,. . , , . . . . .*i.. L. r, , i . , .3 .+ . . . {. l. . .. ' ' * '. ,43 . ' A. W < _. a cavis-sesse occn c-22 nevisien 5 l ~ a pe f ~ d I un DIR T & GR AVEL RO AD TO W AREHOUSE T-42 STONE or, ve SITE WEVWf, 0.8 MILE W & STATIM T-4 2 TLD 9 . BY K TEDROLOGICAL STATION. TRANSFORMER O o TAANSFORMER, O ' = = = / ^ ? .l ugt y , SHELTER , AAIN DUCKET ' O , 'i PRIM ARY 'j / ('\, MET , A, q OWER = f ' h ,i //[-- , AUX. MET. TOWER ' h, j/ ~~ ~ MET.~ g +'$' ~ i- _ . _ = . - .

H'i '* '

f~-- d{M,,b& E / - - =YaG+rl-} - 2 w- g "Dr^c=v \g u;'i.-d15 i, 3x .\ J. / ' i t,, , l . 3,T~(2/ ~ e s t- \* i u r .j ,s I i ei A a T-M g , . : - - - SITE B0lfRRY, 0.5 MILE WSW 0F STATICti BY C0h"iTRET10N GATE. z 2, E 3'" 5., $o y j""=r^, P == l/L - -- e a: . g //~ N 1 ---...r[ b ... . .. 1 T-44 _ :s o - )_ -j x ., y a -s v m ,)3l [r y;- wantnoust l 'd 1 I a O U 3 .. f. . . . sm ,. i -li m ,,,"* t H l m 5 6I l 6 %<Q , ,a(,'g' y ~, B . ,// ES '< k~ LO e E / ;. ~ {s / g. g NA ~9 ,/N, g . W r) , y%+ h, m iz x r3..., i f(w m,9 ,P c ,. n ,Jy, - <..4.. ; n' 3 l . O I 1 # 4

), < :

'.';y, ,L ((. vh L Qj s . J N :i R f 4.. . . .v; o u .- - , (. . o

f. 4 . a

,.i 4 3 ! E, jI Z( .$[t ..? , e ! {j. v ( cj g 4, + . ,,.o . . / .. 4 ., - . . , w . + . ." . , , . '. e .+,..*<..th*.a*4',*!.R. . ; j. y . . '+ :: . . ; . . . s , .,.:.. . s\ .: ;. V.. . ) ?.,.,*vg;;,$'s.T%<.'j? <,,;gy,=..m.,...:.ar., q o -

. . + :.w, w<.w. .

> t : ' * << .i ' n. , lll .,7*,yl.I ' +:p. . .,e if. t e,;. . . ,i:, .. ; . ., I ~ ' ; v . . < t ' <**,, < < l '+;,. ;.a .+**'..'r,'j.;+.,.{, ,(4 , ' . 4 , , . , .- ,, , 'J + ,';.,~ J C - - c-m] t c- - _ J -Davis-Besse o M ' C-25 Revision 5 . _ . . _ _ _ . _ _ _.u._ _ ___ _ . . _ _ _ _ . . . . _ . - . - _ L O r , De Private property i CHA!N LINK FENCE & GATE m I (Sand Beach) t cp " T-4 7 TLD m ~.: ' ':. . ...--? .-_. -. N- \ o . ;..... . . .' . p m.....:. ,.. . , . - . .c..- .. -;....+........... .... y ._.. . . w. . . .. T-47 ,_ ,c %i - ., . . .1 .;.. : ITE BulMMf, 0.5 MILE N T STATI(N * . ..:wverr. ~ . 5.. . . ..f_-. . < . unr.h .-2 , ..T_~ *,. * **. . . .. .J, .. .' .. .* + . * .............'] s .- , . , _. y 3 3, . a. * .,y,+ + .* .. , '+ ....g._, ? W... . j ., ~ ' " ^ %. .. ..RkQQnNyt};.' ~:....5 . - - ~. .. ..,, * * . .+ .. .. e . . _..' ].- ' T-47 - h, / /.\ , . , s 7 l WATER **[ , \ _ . f /- % x\ l r i .. , . .. z_ - ) J(0, r c' r ; .. _a s % \' x o + L. ,(. ' s * . > b s j s . . . . - r, +-. - < l i U . w -- \ '.{u [I m J *h y Q - i /h _ _- a) COOLING '_] '-" t - _ _7 f TOWER .. s ')__ / l j , O ---- - N_ h-- t (( MN J i i- ;g r / .. .. . . m r sa + . - . , e . m '/ 1 i s . g-e Private property (Sand Beach) ' CHAIN Lire - FENCE & GATE - . . ~ ,- .~ . sw

.-r- -

~.. . . . . + .

i

;+..+ .- . .*+.a . . - . . . . . ... . +. . ........,.g.-,, . .. * + .- ? * , . . . . . . w. .?.....s..;., ,.....,..~._.1....._#..,_..;.?.;...._ T-48 yto 9 n .. ... . ,. . ;.,.-.. . ,- ,s. ,. .. .* .. . . '* i _ ;.- a. . .. ,~.-.-_ ,x *; w . . : = .. . .. . l, , ;. + ,, ._,;,.. * * .+_.. *. .. '_. ,. ,. '_ : ~ ' " : Pool 1 Navarre Marsh * . * ,.2 . g 9 q ' / i T-48 t s\N -- ~. /' 4 T-48 ha/R - - - _* w_._IL.- g xs '\ s O ' N \ SITE BOLNEY, 0.5 MILE E OF STATION A ; ,k s$t [ g~- . <. N i M /7 I J y ,,r E

l. -

,G . k'4 N N $. ' \ l' . -s E_ F l J }, , b \\ O i y

l 8 'O '\,

* / l^_ _ _ _ l wmq, _ 1 ___7 . ~1 wI L .- l!I' g 4 -'\- t __ /' __ --mx ._ y J w 4 (.

t. , .

h, . F. ' 4 - BLDG +60s 9T-50 RIFLE R ANGE 3 pORANGE O TLD \ CONCRETE PAD 1 l' WTTER 4 TO4ER ' WATER WORKS UNDERGROUND W ATER BLDG. #606 S,LDG ggy- CONCRETE RESERVIOR s PAD \ GATE 6 . . . . t \k io.a. LAKE ERIE os T-50 ill ERIE It00STRIAL PARK WTER TEATENT E : J' 1 ~ Q-3 PLANT, 4.5 MILES TE OF STATICE. [ -J ltNDUSTR AL w . Paex l c A., , ERR, WEs1ERN RD. .:,_,, I .< g l 4 b i ~~ ~ . m , _ _._,,_._.,_.,m_., , , , _ _ . , , _ . - - , _ , , . . - -- 7 - y-o- .3 ; .s .. 2u / ia W 5, e E65 ov , , 1 M .gu - 88 a n el _ s no } kbh db &m g - ! \~ 4 g ou aiwa 11 we r] @E5 - = E n J-i - > m s o y o l r !!i s u. i 5 = e f ~~ c v I Zh E G - g l l I ? . 8 3" 1 E E . W > s ~ l F *68 4 y w wo aNois ( c N l T , a g i 3 " E W E z . E I < 8 u , ? o "' E f 8 E e 5 y C > 0 0 Bf Os h-l t > Davis-Besse ODCit . C-29 Fevision 5 l l . , . _ , , , , - . , . . e -- = ' * * * ' - * - - ' " ' - ' " ~ ' ~ .K..ha ss e , L 4M43 4'AL Ae - LSM- 4'h w a,~4 %_ .J y- ,,n.i--e km M A - L,Ga ,,.,,nss_m mm A= _._,s_K, a .A,_.n~-. r_ . 4 O / O \ fr C f a t C t b a: M u Z ! ( ', p 'Qu 2 ZAGD-_ i l b b d ; - o - s ; Qu NWnlH38 [ b $ o o.

i k

s . E aovwvt 3 .o ( - K N 4g% o Ei z~ N . o O -w E 28 2 ' ,,.. E' 4 : N ; Z W 8- !

O 3 e .

e O F - - DW E d$ s 00 b4 d O ; i = 4 : Ew @5 . -g 8 et % & =E < 5

Q E Y o

e .> .e, I ( > ; mgw,g C.W W8 > .= ', , - w - , .-4.- - , , , , - r- 'w- w v-e--- **-r-n*~, -a" -e- *---N.-*++-vv-c - - - - - ' r y > S ? : a' I STATE ROUTE 2 ! O i I 8402JSE #5967 T-5 KIPE FAWI, 5 MILES W T STATIGi , t , AT N & M M & M 2.. e 1 I* , - i.e , I "

Toos ,

a STONE DRtVE Shed , o i a: . 5 2 e T-55 4 8 TLD SAwtES 8800NTEo M i oN rENCE POST 11 Lake Erie > -.l O j A e , - \ [ .s. 3 >- d' en-ss W ASH A RD. i f~ b, " ' O 2 9 3 ass i W ~ - y e-r s so #' ; I e : R J - ) , -,,% ,,,74, , . , , - , , , ,, , , , - - , 8 d ROUTE.8 . d'

= _____m _ _ ..

, r COW P ASTURE o _. p # T-57 ~ ~ . ~/ - STATE ROUTE 2 TO INTE 6 EXIT, W ATEH T ANK

b HOUSE' \ #

MIES, TURN LEFT ONIO RT 510. TRAVEL l - 1.9 MILES ON RT 510. E EK'S FARM 4T T-s7 o o ==* O ; - is m Tit alatr,1518 N. sa 510. p d, # SIL j . DRIVEW AY 333 ___ , p Oo^a^a' = D. = = - = o . LAKE ERIE E 4 W ATER T ANK Q/ , 2 PnRT CLINTON i

; x ~

3- o .__ ~ 8 o , ee . 1_s, ! M 41 = OVERPASS gg ( _ . _ , .__.._.-__.! - - - - - - - ~ _ ~ - - - - - '-'s ~ _ ~ - - - _ _ T I r } l t. 7 V) O g Z ^W ? D_ 9ia y g //li l f I p y f. \ I l j, 3~ . ' s s v \ f6 O % ' ,' ['4*. I \ N., l lh ) h, j1., . ; ,,l' ' '),l* ,f e t, c' ?, ,"*l l j fn 4 Yj l, Wn,} ? &x /, ,1 y. w a k,;.. ,.l.$ ,~, :.y.,'.]. .}.?<,i,N.{ 4,f .,.I4*(..,i b ~ .. -( ')? . ,. 'c i *8 , . . ' ,4..<,,, L,- # e / ,.,# ..... M . . i. ....,,,. ' ,_ ir. . , r . . < g5.*. . ,e.'c*

4 .* * , < = 4 ,k',. l ,, * . ' d ' , t.,,,,.'(
4 j

}, ,,. . ,e 8a y ,4'. ,'e' ( 4,' 'e,4 g. ,,-4 ,. ..,,4. ' J. . f .y ;,y p+,;..:. .. 4 ..' . ,. .. .* ". f . ,. .8 k, , , ,' .-Q - 'h ,1 m.7, , ,

i, 4 ' ,

.t ,es ,. .,,j.8..**"4t a } i, ,* , , 2 I5 d , c 6'4"'9*** ,6 ' t,h! . 8' + O Jyi44',,4+fq.* , . ,y ' , . , , , . e** $ ?w - L4 l;a4','4 5g \ i h*<* . ; ?, . .,. f .' 'y'lA n' >l, o . . . I / \ .* , ,*,. 4 4,i .. ,*ii 3, o* s f'44 "*?4 . :: , . ..,e.' e f gh A*i,** a2:,f. .;,g, }.,N,';4',' ,gg ~

e.

e p gy ' ', W' e ' c z C-3Io +. C,i. ,, s /h.., N as - 3., 1 ( u ,, p ' h, * , ,, ' ' , , t,,g... 'E = 5 .',+.,t',Q,,i.p, 'c 2 , , * ' ' .,.,g*',; ,

3

[ ,, ,., .4 *

g

, . . . ?. . 't ,,1,,J.sgr ,*p. + ,. , t te$ ,. ..i...-. ..p. < J ( , Davis-Besse ODCM C'33 Revision 5 x_ -- -%----m -.__ ,1 ilil l l i rl l' ' I I m J N -\)\)e/j Y - B e - u b,;{t N N f O I R s s A T E W a _ - - T D T S I F G O N I = M L - O M OC , E L R ,( /, F / I M l J , 5 0 WS J - b ;j _ sp g - )k ,. c x ,9 nd ) jn kkg/yA[ - Y i l on oo f cp / r r ee g w / i rP. x~, L r at o 6 T Nf ;p[ m

i i l

] T S _ ( O P E C4 f E F a t O , I D L r T e 8 r w 6$ eod nt T a gon mnp f d S! a o o o R c e k iD l - ? ,,e r k 5L:T5y* ?g ,1~ "* ll lI i!llh\ljl( iff llllf(l iI llff ,\jl e e $m QU 5 .

2

- , O E d s Y . j ~ m @j f a ( s. 55 p -- h ZD w $iE sem - r :.; Ln .. N ed I f' 9 9 w O 1h e 0 ,// as.n f yi . tem-avaa> pu emuou . 0 4 et . s , , h c "g &. '%y h g i !

seg f

es l 1 l .- ... N&=g g Davis-Besse 000$ C-35 Revision 5 -i . ,. t l ,' , ; b :; l: . ! Il l r; 'l s o f l I NO e k E O P E L a o .h Y -o T WlT I L I T o. U . b , o 2 T r 0 I B,k D

l A '

l T S T-F O *o W , - S - S S M : p E L I M N 4 . 5 1 M A D l R N el s E O L u o O S P Hl Y P uM T mO t 4 N H O D T @ l L [ p T 2 1 ** 1 o e T \ \ s , i \ \ $OcAn NA T \ I / < a>1 I,* ,* 82 o . <:sE E s > _ L . O F e r _ Y c 1 f i o L _ I T s o _ U 1 T _ N - OT D L*< T w E G A R _ .@ >w@n.yaI A G dT pmEIn_73I _ m E T R . A C . H C A E 2 E [O T U R x N e a. E T i r o Y U eE T O I L R k I T E T a U A L T , S ' N . O F I O 1 T 5 A N h 1 T O D - S I . R T F r T D A A H 0 MRYO-1 S W j t 6 1 A W- ) l E h - S E l W P ~ T F F U T D A PR 'o L I M dE C$ 2i 8 f l & 0 1 P 2 - g % c _ < seh! O o 51E8u 1 . I l!;;

ji, i j; i ;f Il 4 !<ljj v

.=- j'p,e -' : 't 5 - This-page is intentionally blank. - C a I n .r - . a ,-e-.ms, ,n., ., ,,.r--,,---a,.-- nn , .. - - -n--- -- -n. - -. -.- ~ . -.-- ------ ,--- -.. - , - - r .-m,. a r 1 h Safety Evaluation for the Davis-Besse Padiological Effluent Technical Specifications Atoendment Overviev ! Revision to the Davis.Besse Appendix A and Appendix B Technical Specifications

are proposed which vill implement the regulatory requiremer.t of 10 CTR 50, Appendix I on ALARA for radioactive effluents and other NRC regulations and criterie on radioactive esterial monitoring instrumentation, radioactive '

material control, and radiological environmental monitoring. In keeping with f4RC guidelines, all radiological requitements are being deleted f rom Apper. dix B I .and placed in Appendix A. This proposed-amendment is a revision to a previously submitted amendment to the NRC dated. Hatch 16, 1979 (Seriet No. 488).

The major areas that are addressed in the revised submittal are as follows: :
Liquid and Easeous effluent monitoring .nstrumentation -- operation and periodic operability checks

- Liquid and gaseous radioactive material releases--maximum release rates, e quarterly dose limits and yearly dose limits: . Sampling and analysis requirements on batch and continuous radioactive material releases 4 .? Operation requirements on the liquid radvaste treatment systamt Curie inventory limit on outside temporary liquid storage tanks Maximum allovable oxygen concentration in the vaste gas systemt Davis-Besse ODCM J-1. Revision 5 ~ u. . . . - . , + . , .. _rm..._. _.~__.......w, _,,,,.e ,, ,,- , y r,.-. ,,v,,. ,_,.e- . , - . ., w., . 7...,, . m .- . - . m _ _ _ _ . _ _ _ . . ~ . - . _ . . _ , _ _ . , _ _ - _ . . _ _ - _ _ _ _ _ _ . . _ . . t 4 * -Requirements to assure all solid vaste meets applicable burial site requirements:

Radiological environmental monitoring program--minor revisions to reflect current program and current NRC guidelines.

l Changes have also been made to Section 6 of Appendix A to reflect the applicable administrative controls needed for the Section 3/4 revisions. A notable addition to the amendment is the inclusion of a requirement for an Offsite Dose Calculation Manual (ODCH) and a Process Control Program (PCP). The ODCH and PCP are not lleensed documents but are referenced in the Technical Specification as presenting acceptablo methods for evaluat- - ing compliance with applicable Technical Specification requirements. The ODCH-provides calculational methods for determining radioactive effluent instrumentation alarm setpoints, and for evaluatAng releases of radioac-tive effluents and corresponding doses. The ODCH also includes the sampling locations for the environmental monitoring program. The PCP presents the methods used to verify that vaste (devatered resins) as processed int disposal meets appropriate shipping and burial grot *d regulations. Changes m.ty be made to these documents without NRC approval; review by the SRB is required. Safety Evaluation-An evaluation of the revised amendment has been performed to assure that the revisions as proposed to do not involve an unreviewed safety question as defined in 10 CFR 50.59. The three criteria of 10 CTR 50.59 for the unreviewed safety question deternination are addressed belov.

1) Probability of occurrence or the censequences of an accident-or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased. l l

i Davis-Besse ODCH J-2 Revision 5 I w v sw * ., - u, m -~,-v - - . . , . , - . . , , , - - - - , . , - a n.n,- ---- - - , - . - , . . . - - . - , , <.~-r - .e, .. _ _ . . = _ _ _ _ .. ___ ._ _ __ __._ .__ _ _ 1 J Except far the addition of the-turbine building liquid effluent radiation monitor (for which an FCR has already been initiated), no plant equipment modifications are required by the proposed amenda.+nt. Certain procedural ! requirement vill need to be developed but these address routine radioac-tive material effluents and controls no accident procedures are involved. '

11) Probability for accident or malfunction of a different type than any evaluated previously in the $AR may be created.

L For reasons as stated in response to item (1).above, the proposed amend- ! ment does not directly or indirectly pose a probability for an accident or malfunction. The amendment vill implement the NRC regulations for routine releases and controls of radioactive material. The amendment does not address any engineered safety features of the plant design. ' 111) Margin of safety as' defined in the basis for any technical specifi- i . cation is teduced. The proposed amendment does not reduce the margin of safety. The proposed amendment addresses routine releases and control of radioactive materiali except as noted in item (i), no plant modifications are involved. Several operating procedure changes may be needed, but these changes vill be only for routine operations and vill have:no impact on accident probability or consequences. For_the reasons discussed above for eae.h of the criteria of 10 CFR 50.59, it is concluded that the amendment as proposed does not involve an unreviewed safety question. 3 Davis-Besse ODCH J-3 Revision 5 L l l Service Vater Systen--Radiological Effluent Mong oring Requirements - The service water is classified as a non-radioactive system, being removed from radioactive systems by two boundaries. Radioactive systems ; are serviced by the component cooling vater system interfaces and, the service water system provides cooling to the component cooling water ' system throgh closed-loop heat exchangers. Therefore, any leaks from l radioactive systems into the plant voter systems vould first be identified l by the monitoring of the component cooling water system prior to uy l additional unexpected leakage into the service vater system. As a prudent measure, the service vater system is monitored in accordance with the MtC guidance of Standard Reviev Plan. Section 11.5. However, because this system is a non-radioactive system and is separated from radioactive systems through two closed-loop boundaries, no Technical Specification requirements are needed for routine monitoring and analysis for radioac-tive effluents. , i-b 1 i Davis Besse ODCH J-4 Revision 5 u_ __ _ . - _ - --- - _ _ _ . _ _ __... , _ _ . _ . _ _ _ _ _ _ _ _ - _ _ . . _ _ _ - . . . _ . . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ = . _ _ - r Radioactive Effluent Instrumentation--Automatic Isolation Feature The radioactive effluent monitoring instrumentation at Davis-Besse does j not include provisions as called for in the NRC Standard Radiological j Effluent Technical specifications for automatic isolation should any of the following conditions existi circuit failure, dovnscale failure, or instrument not set in operate mode. Even though the automatic isolation features do not exist, administrative controls have been established such that should any of these conditions exist, the control of radioactive t effluents vould not be significantly impacted. Essentially all releases i of liquid radvaste are controlled as individual batch releases with predetermined allovable release conditions. Thereby the radiation monitor ; serves mainly as a back-ups primary control is established by the prerelease j - radiol'gical analyses and evaluations. To assure the availability of the - back-up monitoring, the status of the instruments is checked once per _ _ j shift by the control room operators. Indicator lights on the instrument panel are checked to verify operability. An indicator vould illuminate ~ should a failure occur such as the ones delineated above. Therefore, in addition to the administrative controls on allovable radioactive releases, the verification of instrument' operability prior to releases of radioactive effluents and the "once per shift" status check by the control room operators provides' adequate assurance of the proper control of the radioactive effluents. . 1 b I Davis-Besse ODCH J-5 Revisioa 5 I -,w44--- , .w _ ...m,,a n.,-- ,-...,c.~.o+--,--...m..a , , , - , . ,,-,, v-w_ - e-, ,-,-,.,,,-r.m.... r-,. p-.,,r-o -s.v....-.,.+-qys-.,-,..,.~.,- - < . . . - . - . - -.-..- ~ .- - - - - - - - ~ . - - - . - - . Techn! cal Bases for Eliminating Curie Inventory Limit for Gaseous Vaste Decay Tanks .The RRC Standard Technical Specifications include a limit for the amount i of radioactivity that can be stoted in a single vaste gas decay tank. , This curie inventory limit is established to assure that in the event of a tank failure releasing the radioactive content to the environment the resulting total body dose at the site boundary would not exceed 0.$ rem. For Davis-Besse the inventory limit in the vaste gas storage tank has been r determined to be approximately 45,000 curies (Xe-133, equivalent). An allovable primary coolant radioactivity concentration is established by , the Techniccl Specifications which limit the primary coolant radioactivity ; concentrations to 100/E vith E being the average energy of the radioactiv-ity in MeV. This equation yields an upper primary coolant gross activity limit of about ?OO UCi/ml. By applying this activity concentration limit to the total liquid volume of the primary system, a total activity limit can be determined. For Davis-Besse, the primary system volume is about $6,000 gallons, which yields a limiting total inventory of approximately 41,000 C1. By assuming a typical radionuclide distribution, an equivalent Xe-133

fnventory can be determined. Table J-l provides the typical radionuclide ,

(noble-gases) distribution and the Xe.133 equivalent concentration. The ' equivalent concentration is determined by multiplying the radionuclide concentration by the catto of the nuclide total body dose factor to the Xe-133 total body dose factor. Summing all the individual radionuclide equivalent concentrations provides the overall Xe-133 equivalent concen-tration. For determining concentration-in a vaste gas decay tank, a conservative assumption 01 40 hours decay in degassing the primary system has been used to correct the primary coolant concentrations. The data show that the equivalent concentration (decay corrected) is less than the gross concentration (i.e., 16 uCi/gm total.in primary coolant versus 12 uCt/gm equivalent). The resulting Xe-133 equivalent curie inventory for VGDT input is approximately 31,000 ci. l 1 Davis-Besse ODCh J-6 Revision $ .m- _ . . . _ _ u._. _._ -_ _ _ _ _ _ .. _ __.-.-_ _ . _ .~ _.__.x-. __ _. _ _ . . F: i , Therefore, even if the total primary system at the maximum T)ch Spec allovable concentration was degesaed to a single veste gas decay tank, the tank curie inventory would be vell below the 45,000 Ci limit. Based on this. evaluation, the curie inventory limit on a single vaste gas storage tank has not-been included as a Technical Specification requirement. -,i s I - Davis-Besse ODCM J-7 Revision 5 J ^ Table J-1 Xe-133 Effective Concentration Primary

Italf- Concentration Reg Guide 1.109 Ratio of Xe-133 Coolant 11 a @48 hr decay TB Dose Factor TB 0F Effective Conc.

(uCi/gm) (uC1/ml) (mrem /yr) Xe-133 DF 948 hr decay l (pCi/m') (vCi/ml) Kr-83m 2.0-02 1.9 hr - 7.6x10" - - Kr-85m 1.1-01 4.5 hr - 1.2x10~8 4.1 - Kr-85 7.4-02 10.7 yr 7.4x10 1.6x10" 0.06 .4.4x10 Kr-87 5.8-02 76.3 min - 5.2x10 20. - Kr-88 1.9-01 2.84 hr - 1.5x10 52. - Kr-89 4.0-03 3.16 min - 1.7x10 57. - Xe-131m 8.4-02 12 days 7.5x10 9.2x10 O.32 2.4x10'8 Xe-133m 2.0-01 2.2 days 1.1x10'* 2.5x10 O.86 9.5x10 Xe-133 1.5+01 5.3 days 1.2x10'* 2.9x10 1.0 1.2x10*' Xe-135m 1.3-02 16 min - 3.1x10 11. - Xe-135 3.3-01 9.1 hr 8.5x10 1.8x10~8 6.2 5.3x10'8 Xe-137 8.7-03 4 min - 1.4x10~8 4.8 - Xe-138 4.3-02 17 min - 8.8x10 30 - Total 1.6x10** 1.2x10** 1.2x10**

Adapted from Davis-Besse Evaluation of Compliance with Appendix I to 10 CrR 50, June 4, 1976.

Davis-Bebse ODCM J-8 Revision 5 Lower Limit of _ Detection-Decay Correction factor The equaMon and definition of the lower limit of detection in the tiRC Standard Radiological Effluent Technical Specification include the term e'" which is used to decay correct the analysis. The LLD is further uefined as an a priori (before the fact) limit representing the capabilities of a measurement system , and not an a posteriod (af ter the fact) limit for a particular measurement. Providing a decay correction for an evaluation of the capabilities of a system does not_ appear appropriate. It my be appropriate to decay correct certain analyses of specific samples to determine radionuelide concentrations at the time of release. Even in this case, such a correction is not appropriate for batch releases. Analyses are performed prior to any release; and, the sample will be decaying at the same rate as the batch from which the sample was taken. ror continuous teleases, decay correcting analyses of sampk s obtained over a specified sampling intervas est take into account the .' eslation of radioactivity in the sam .ing medium, the decay during s ,ampling interval e and, especially for short lived radionuclides, equiliLrium or quasi-equilibrium conditions that may be achieved. Short-lived radionuclides will tend to reach an equilibrium value in the sampling medium as a function of source input and half-life. A single decay correction to adjust for s mpli19 interval will provide an w1 acceptable overestimate. Equilibrium conce '. rations must be considered if analyses are to be indicative of actuti release quantities. Employing exp(-Mt) to adjust for radioactive decay tetween the end of sampling and time of analysis is straightfervard._ However, to attempt to use the same term to adjust the decay during the sampling peried is not proper. As a practical matter, when the half-life of a radionuclide is long relative to the t sampling time and the time between sampling and analysis (i.e , minimal decay) the correction term will be near unity. In that event, the correction term is relatively unimportant.-- b Davis-Besse ODCM J-9 Revision 5 l L - _ _ . . - . ~ _ _ - - - . _ . - _ . . _ _ _ . , . , . . . . , , _ , . _ . . , _ , , . , - , _ . . , _ _ . , . - - , _ , - - _ _ . _ _ At the other extreme, when the half-life of a radionuclide is mo:h shorter then the sampling time or the time tetween the end of sampling and the analysis, the term exp(-Ab.t) cculd be ut,d to adjust for dacay between the end of sampling and the analysis. However, it would not be apptcpriate in that case to use the same term to attempt to adjust for decay during sampling. The relationship between the radioactivity in a sample at the end of sampling and activity concentration in the medium being sampled is somewhat more involved. To explain this is the simplest condition, assume the radionuclide concentration is constant in the medium being sampled and that the medium is sampled at a constant rate. In the instance of water sampling, the relationship betwen the activity concentration in the water teing sampled and the activity concentration in he water sample at the end of sampling is: C, a C, At (1) 1 - e where C, - radionuclide concentratien in the water being sampled C, + radionuclide concentration in the water sample at the end of sampling t = duration of samplit.g A = radionuclide decay constant _ when t >> 1, C, a C,At. In the separate case of sampling a radionuclide in air by filtering the air and analyzing radioactive material collected on the filter, the radionuclide of interest is concentrated. Absent diluent air in the sample being analyzed, the relation between radioactivity on the sample media and radionuclide concentration in the air being sampled ist q - C,r (1-e " ) (2) I Davis-Besse ODCM J-10 Revision 5 . _. ._ . . - =. . _ _ where C, = radionuclide - concentration 1. the air being samplec' q = radioactivity on the sample media (assuming 100% conection ef ficiency) T = sampler flow rate (volume / time) A = radienuclide decay constant H t = duration of sampling when t > > 1, C, = q VT . 1 This merely recognizes that the rate of loss from the filter by radioactive decay equals the rate of collection onto the filter at equilibriem i l The NRC proposed equation appears to incorporate an adulterated wey of 1 encourt,ging analysis soon after the end of sampling and to encourage efficient ! sample concentration or radicchemical extraction. Although not rigorous, it combines both objectives in a simple and thus practical way, provided the decay i correction is not extrapolated to a time earlier than the end of sampling. A more nearly rigorous _wef of determining the activity concentration (or minimum-detectable activity) in the medium being sampled is to assess the LLD in the l. sample at the time of analysis. Then the activity concentration in the medium being sa pled can bn calculated with the product of exp(-Aot) for decay between the end of a: c'*m ; and the analysis and one of the equations derived herein for the relatie M n the medium being sampled and the_ activity in the sample at the end c. . sa.F ' g. ever, this method is not very pract.'. cal or necessary considering the types of sampling and aralyais at nuclear power plants, the significant radionuclidos, and the offsite potential doses. The bulk of radioactivity Te released as betch releases with all sampling and analysis performed prior to release. Therefore, decay corrections are applicable. It is in the sampling and analysis of . releases that the ectumulation and decay of the radioactive material -need to be considered. The use of NRC's guidance for decay correction to the mid-ool1t of the sampling period can grossly overestimate actual release oualities U. short-lives radionuclides, while providing little improvement for Davis-Besse ODCM J-ll Revision 5 I i I I the quantification of the longer half-life radionuclides that are the major dose contributors. Overall, it may be appropriate to decay correct a certsin analysis to account for radionuclide decay during the sampling period. However, simple decay correction to the mid-point of sampling will grossly overestimate any short-lives radionuclides that may be detected. In any case, the use of a decay correction f actor in defining a lower limit of detection is inappropriate. The LLD is a measurement of the capability of the measurement system and should not be used to try to establish a tegulatory position on sampling and decay correction for pnfification of releases. Davis-Besse OOCM J-12 Revision 5 1 ._ _ - _ . ..- . - . .. . ~ . - . . . . - . . - - - -. - Waste Gas Dechy System and Ventilation System--Operability Requirements At Davis-Besse, the operation of the waste gas decay system is essentially continuous, similar to the tc.utine operation of such a system at other PWRs. The system consists of a surge tank which receives the waste gases from the primary system, dual compressors (one in-service and the other in reserve), and three waste gas hold-up tanks (one in-service, one isolated for gas decay, and the third in reserve). Cnce the system is on-line with a vaste gas decay tank receiving primary system gases from the surge tank, operation is automatic; no operator actions ata required he operating philosophy at Davis-Besse is to essentially operate the waste gas system continuously. Not only is this philosophy prudent from an IJAPA standpoint, but it is also conservative and protective f rom an operational standpoint. Having to periodically evaluate primary system off-gas activity levels and anticipate unexpected increases in radioactivity would be an unnecessary burden in determining needed vaste gas system operation. For the ventilation systems, the operating philosophy is similar to that for the waste gas system; operation is continuous. But for the ventilation systems, the reasons for continuous operation are even more straightforward. Areas within the plant must be provided with outside air in order to provide an inside environment suitable for continued occupancy. Without continuous ventilation system operation, heat, humidity, and airborne radioactive material levels would increase and worker occupancy would be jeopardi::ed. As described in the Davis-Besse Appendix I-evaluation, the ventilation systems contain HEPA filters for removal cd airborne radioactive particulate material prior to release to the outside environment. (As evaluated for Appendix I compliance, only the waste gas vent includes charcoal filters for removal of radiciodines.) n e operation of the systems can est.entially be considered a passive operation. No active operational procedures are required for normal system operation for removal of airborne radioactive material. Davis-Besse ODCM J-13 Revision 5 - . _ . - - - _- . . . - - . . . . - . . _ - . - . - - . . . ~ , . - -. . . . - . ~ . - 4 4 Davis-Besse's operating philosophy (and operating procedures) for the vaste gas system and ventilation syrtems is a comitment in itself to the routine . continuous operation of the systems. Having to comit to such a requirement (in . lieu of a technical specification requirement on operation) without appropriate consideration of system down-time-and plant-shut-down (where operation may not be needed or feasible) is unacceptable and not in keeping with the principles of AIARA. Including special technical specifications that would impose additional procedures and periodic surveillance requirements in excess of those already established (which at present assure appropriate operation) is unnecessary and excessive, l t i t i l. l t I i t Davis-Besse 0D01 J-14 Revision 5 l-I Radiological Environmental Reporting Levels only the radionuclides listed in Table 3.12-2 of the proposed Radiological Effluent Technical Specifications !see note) for Davis-Besse are considered in the reporting requirements for elevated levels of radioactive material in environmental sampling media. The radionuclides listed are those that are dominant in the plant effluents and contribute essentially all of the environmental dose. Other radionuclides will be present in plant effluents, but their contribution to the calculateo total environmental dose will be minor compared to the contribution of the radionuclides listed in Table 3.12-2 (see note). Even the contents of the NRC's Standard RETS reflect this position; not all pathways include reporting levels foc all the radionuclides listed (e.g., no reporting levels are present for Co-58, co-60, or Fe-59 for the milk, airborne particulate, or vegetable pathway). This vary selective identification of pathway and important radionuclides reflects the very well defined concept of significant radionuclides for each particular pathway. Based on past experience in monitoring plant effluents and envi:enmental sampling media, it can be stated with confidence that_for the routine operation of Davis-Besse the radionuclides listed in Table 3.12-2 isee note) with applicable reporting levels by the identified pathways are the only radionuclides that need be considered when evaluating potential doses in the l offsite environment. Also, even if repo; ting levels were included for other radionuclidos, the values would be higher than those for the significant radionuclides and would have a very minor role in determining actual reporting requirements. The ;eporting levels for the significant radionuclides would be reached well before any identified levels of other radionuclides would even be controlling. Note: Table 3.12-2 has been incorporated into section 6 of the ODCM, Table 6-4. l Davis-Besse ODCM J-15 Revision 5 ~ . . --- ~ .. . . - _ _ - - ...-..- -..- . ~ - - . _ ~ .-_- - - . . . _ - Radiological Effluent Dose Analysis-Meteorology for Short Term Releases Except for the waste gas decay tank (WGDT) releases, containment purge releases .and containment pressure reductions, gaseous effluents from the Davis-Besse l Station are from ventilation systems and are considered continuous releases. Most of the radioactive material in gaseous effluents if released form the NGDT. Ilowever, because of the essentially random nature of NGDr releases (i.e., no prescribed diurnal time, frequency or duration), the dose analysis of these-releases is better modeled by the use of annual average meteorological conditions rather than short term meteorology. Containment purges are so infrequent-that special meteorological analyses are not warranted; reasonable evaluations of off-site deses can be provided by the use of annual average meteorlogical conditions. Davis-Besse ODCM J-16 Revision 5 .- -- . -- - --- .- . - - -. - - - .~ . Sampli.1g Frequency for I-131: Significance of Power Changes and Increases in Coolant Activity Levels The NRC guidance on ef fluent monitoring for I-131 (Standard PITS, tCPEG 0472, Table 4.11-2, rootnote 7) calls for increased sampling frequency for I-131 during increases (or decreases) in reactor power level and increases in primary coolant level or noble gas effluent activity level. By system design,. releases of radioactive material from plant operation are minor. Trying to identify small increases in I-131 releases that may (or may not) be associated with power changes is unnecessary. To evaluate the potential significance of increases in I-131 releases associated with power changes, the effect that may be associated with power changes and the effect that sampling time may have on actual quantification of releases, the following example situation is evaluated. Consider a power increase on the first day of a 7-day sampling period that leads to an increase in I-131 release rate by a factor of 10 for one day. After this one day increase, the release rate returns to the steady-state condition for the remaining 6 days of the sampling period. To evaluate the amount of I-131 on the sampling cartridge as a function of sampling time and concentration, the following equation is used: O, = C,_r (1-e" iI) m' A, where: Q, = quality of activity on collection medium C, - air concentration of radionuelide i F- = flow rate of sampler -l A, - decay constant for radionuclide i t = sample time m = correction factor for collection efficiency Assuming 100% collection efficiency at the end of the one day increase, the . total amount of activity (I-131) on the collection cartridge is determined to be 9.54 C,r. (For this example, the steady-state I-131 concentration is designated as C g and the one-day increase is 10 C,.) For the remainder of the sampling period with a concentration equal to C,, the I-131 activity on the collection cartridge is equal to 4.66 C,F. By decaying the' activity on the-collection cartridge for the one-day increase to the end of the sampling period and adding this quantity to 4.66 C,r, the total I-131 activity is determined to be 10.3 C,F. Davis-Besse ODCM J-17 Revision 5 m, If this value is decay correct to the mid-point of the sampling period in accordance with the guidance of Regulatory Guide 1.21, the I-131 activity which is used to determine the release quantity.is equal to 14.0 C,r. -If a _ similar analysis is perfomed for the case of analyzing the collection cartridge at the end of the one day increase and analyzing a new cartridge at the end of 6 days sampling (constituting a 7-day sampling period), the total activity (decay corrected to mid-point of sampling periods) is determined to be 16.0 C,F. By not analyzing the collection cartridge at the end of the one day increase, the total quantity of I-131 is underestimated by 14L This analysis represents a somewhat worse case situation. The later into the sampling period that the increase occurs, the less the error. If the increase in release rate occurs after the mid-point of the 7-day sampling period, the actual release will be overestimated. Over a period of time involving numerous ine eases and decreases in effluent level, the rules of probability dictate that the overestimations and underestimations will tend to cancel out, providing an overall closer approximation to actual releases. Both ,the NRC in-plant measurement. program and a study by EPRI* have indicted that minor increases in I-131 releases may be associated width reactor power changes and the iodine spiking phenomenon. However, these studies also indicate-that overall such increases are minor, not being a significant contributor.to -the total releases of I-131. As was concluded by the EPRI study for other PWRs, the main source of I-131 releases at Davis-Desse is associated with containment purges. Regardless of the source, the total I-131 releases are negligible. Since initial start-up of Davis-Besse, the annual releases of I-131 have been less than 0.06 Curies and calculated maximum individual doses less than 0.01 mrem. l *EPRI NP-939, " Sources of Radioiodine at Pressurized Water Reactors". !~ Science Application, Inc., November 1978 Davis-Besse ODCM J-18 Revision 5 J Even'considering a hypothetical 14% increase for sampling periods that may include iodine spiking in the primary coolant, the effect on total releases and calculated doses is still negligible. The actual increase will be even more ; insignificant considering the fact that the major source-of I-131 at Davis-Besse i 'is~ from containment purges.- Based on a review of plant operating data and the above analysis of the I-131. release quantification as a function of concentration and sampling time, it is concluded that for Davis-Besse, a sampling-frequency based on power changes and increases in primary coolant I-131 concentrations'is not- -justified. Determining the releases (and the significant environmental doses of these releases) on a weekly basis is sufficient verification of the negligible impact of plant operation. Trying to " fine tune" these releases is not justified considering the manpower and material costs associated with the additional sampling and analysis. 1 i l-1 I~ l Davis-besse ODCM J- 19 Revision 5 _ _ , . ~- ,- .._ _ __ _ , - _ ~..- __ _ . _ _ . __ _ . _ _ _ _ . . -_ . __ _. Condensate Demineralizer Backwash Receiving Tank - Radioactivity Control The discharge f rom the condensate deminerilizer backwash receiving tank is controlled on a batch-by-batch basis in lieu of continuous radioactive effluent monitoring. This method of operation has been determined to provide better control over the discharge of the backwash receiving tank, preventing any unanticipated, unevaluated releases of radioactively contaminated secondary-side clean-up resins to the on-site settling basin. Prior to discharge, the contents of the backwash receiving tank are sampled and analyzed for radioactivity. As required, radioactive)y contaminated resins are transferred to radwaste for processimg and disposal as radioactive material. The condensate demineralizer backwash receiving tank discharge line as originally designed included a radiation monitor. However, because of the nature of the resin-slurry mixture and the accumulation of resin beads in the monitor line, the radiation monitor has failed to provide the reliable indiction of radioactivity and control as originally intended. tot this reason, it has been determined that the sampling and analyses of each batch prior to discharge le needed to identify and evaluate radioactive contamination resulting from minor steam generator tube leaks (or residual radioactive material from previous leaks) that might otherwise go undetected and unevaluated by a gross radiation effluent monitor. The condensate demineralizer backwash receiving tank discharges to an on-site settling basin. No resin discharges are made directly to the off-site environment. Therefore, even in the event of personnel error resulting in the inadvertent discharge of unacceptably radioactive, contardnated resins to the settling basin, no off-site releases waald occur. All resins and radioactive material would be retained on-mite within the settling basin. Appropriate follow-up measures could then be initiated to control the radioactive material and prevent any potential for releases to the off-site environment in excess of the regulatory limits. Davis-besse ODCM J-20 Revir.lon 5 controlling the discharge of the condensate demineralizer backwash receiving tank on a batch-by-batch basis provides adequate control over the releases of any radioactive ruterial to the off-site environment f rom this pathway. Also, the discharge is to an.on-site settling basin, representing an additional passive barrier from release off-site. Even in the unlikely event of personnel error, by discharging to an on-site settling basin and its isolation from the i off-site environment, the probability of unwanted, unevaluated releases of -radioactive material to the off-site environment is exceedly remote. Any additional protectivo measures provided by a continuous radiation monitor (for . which operational performance and reliability are unlikely, based on past experience) are not considered needed, i I l l -. l l Davis-Besse ODCM J-21 Revision 5 . - , _ - . . - - - . . _ , , - . , . . . ~ _ . - . . c , . . - - , . ,, . . , - , , , Lower Limit of Detection Definition and Application To Detection Capabilities for Ce-144 i The lower limit detection (LLD), as defined in the Radiological Effluent Technical Specifications (RETS) is an "... a priori (before the fact) limit representing the capabilities of a measurement system and not an a posteriori (after the fact) limit for a particular measurement." As defined by this definition applicable to the detection capability for radioactive effluent analysis, the LLD is a statistical analysis of a background spectrum and repreterts the detection limits for a radionuclide if it is the only-radionuclide present above background. LLDs should be determined based on an analysis of a blank (or background) sample. However, even with this definition and application of LLD, it can be increasingly difficult to achieve a predesignated LLD value for particular radionuclides as the photon abundance (i.e., decay yield) decreases. To address this problem, specific radion2clides have been identified in the RETS as being the principal radionuclides for which the required LLD must be met. For the analysis of samples of liquid radioactive effluents, an LLD of 5 x 10 uCi/ml is required. For the principal gamma emitters listed, all have characteristic gammas with energy levels and abundances that provide for sufficient analytic.al' sensitivity yielding LLDs within the required value of 5 x 10 uC1/ml - except Ce-144. With a 10.8% abundance and an energy level of 133.5 kev, being able to meet the LLD of 5 x 10 vCi/ml requires optimum conditions-conditions which cannot be repeatedly achieved for an operational radiochemistry program at Davis-Besse. 'Ihe low gmna yield is a major factor; however, with an energy level which is located within the Compton continuum, the detection capability for Ce-144 even for a blank, background sample is significantly higher compared with other so-called principal gama emitters. The equation for LLD in the Davis-Besse RETS is: LLD - 4.66 S, E

V
2.22
Y l

l l Davis-Besse ODCM J-22 Revision 5 where S, = the standard deviation of the background counting rate = /B/T R = background count rate T = counting time E = counting efficiency V - sample size 2.22 = conversion factor (transformations per minute per picoeurie) Y = fractional chemical yield (when applicable) By substitution of typical values in this equation, the LLDs for different principal gamma emitters can be compared. For analysis of a typical background sample at Davis-Besse, the ratio of the LLDs for Ce-144 and Co-60 is about 5.35; for Ce-144 and Mn-54 the ratic is 8.34. These large ratics are demonstrative of some of the relative difficulties in achieving an LLD of 5 x 10-' vCi/ml for Ce-144 compared with other principal gama emitters. Examining the equation of LLD, two main factors can be altered in an attempt to improve the detection capability - counting time and detector efficiency. (Altering sample size is not considered realistic since larger samples would pose operational and standard calibration problems. It can also be shown that increasing sample volume does not strongly influence efficiency for counting on contact with the detector face due in part to sample self-shielding and deceased relative efficiency for the increased volume.) Davis-Besse ODCM J-23 Revision 5 ~ --_ 1 i LLD improves at best as the square root of the counting time. Therefore, increasing the counting time from 2000 seconds to 5000 seconds would enly provide a factor of 1.6 reduction in LLD. A 5000-second count is considered to l be a reasonable maximum for radioactive effluent analysis. Having to extend to longer cc'unting times would introduce a potential operational delay without commensurate improvement in detection capability. An improvement in efficiency is negated in oart by the corresponding increase in background count rate. A comparison of 5 GeLi detectors with relative ef ficiencies ranging frcm 7.2% to 22% ns performed at the University of Michigan". For a 500 m1 sample on contact with the detectors, the 151 relative efficiency detector demonstrated the highest photopeak efficiency in the 80 - 200 kev range. EN n the 10% relative efficiency detector had a higher photopeak efficiency in this energy range than did the 21% and 22% relative efficiency detectors. Some unexplainable differences may be due to inherent manufacturers specifications; however, a valid conclusion is that increasing the detector efficiency provides little if any improvement in detection capability, especially in the low energy range (<200 kev). Therefore, the analysis of effluent samples at Davis-Besse with a 10% relative efficiency GeLi and a 5000-second counting time provides a datection system that is not only practical for an operational radiochemistry program but cm also be considered as representative of state-of-the-art for toutine, general purpose radionuclide detection. Since the required LLD of 5 x 10" vCi/ml cannot be met on a routine basis for Ce-144, therefore the LLD for Ce-144 will be 2.0 x 10" uCif ul (Table 4.11-1 footnote b)**.

D. M. Minnema, C.G. Hudson, and J.D. Jones. "A Comparison of Ge(Li) Detectors with Different Efficiencies for Low-Level General Purpose Counting";

University of Michigan, 1978. ** Incorporated into ODCM Table 2-3 Davis-Besse ODCM J-24 Revision 5 { l _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _}}

ML20114C632

Text

1.0 INTRODUCTION

Navigation menu

Search