ML20138B464
| ML20138B464 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 05/06/1996 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20138B454 | List: |
| References | |
| 6610-PLN-4200.0, NUDOCS 9704290183 | |
| Download: ML20138B464 (273) | |
Text
{{#Wiki_filter:l 1 04-23-97 09:13:44 . Number TMI Radlological Controls
-Qgyy Departmental Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 14 Responsit>1e Otttee Effective Date Applicebulty/ Scope Calculate offsite doses due to radioactive s effluents for demonstrating compilance with Site Technical . . Specifications 10 CFR 20 & 10 CFR 50 - Appendix I 6610 05/09/96 This document is within OA plan scope X Yes No. Safety Reviews Required X Yes No Ust of Effective Pages l Revision Paae Revision Paae Revision Pagg Revision Paae 14 21.0 11 41.0 12 61.0 12 1.0 14 22.0 11 42.0 12 62.0 12 2.0 23.0 11 43.0 12 63.0 12 3.0 11 12 24.0 11 44.0 12 64.0 12 4.0 12 25.0 11 45.0 12 ' 65.0 12 5.0 ' 12 26.0 11 46.0 12 66.0 12 6.0 27.0 13 47.0 12 67.0 12 7.0 12. 12 28.0 12 48.0 14 68.0 12 8.0 29.0 12 49.0 12 69.0 12 9.0 12 10.0 12 30.0 12 ,50.0 14 70.0 '12 ; 12 31.0 12 51.0 14 71.0 12 i 11.0 12.0 ;12 32.0 12 52.0 12 72.0 '12 12 33.0 12 53.0 12 73.0 12 13.0 34.0 12 54.0 12 74.0 ~ 12 14.0 11 35.0 12 55.0 12 75.0, 12 15.0 11 36.0 12 56.0 12 76.0 12 16.0 11 37.0 12 57.0 12 77.0 12 17.0 11 38.0 12 58.0 12 78.0 12 18.0 11 11 39.0 12 59.0 12 79.0 12 19.0 40.0 12 60.0 13. 80.0 12 20.0 11 I
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Manager, TMI Reg. Affairs TY _g Rad Con / Safety Director, TM1 . 1.0 am. s 9704290183 970423 PDR ADOCK 05000289 R PDR
04-23-97 09:13:44 %, ) HmImr ' 7"' "ad'o'oa'ca' coatro Departritental' Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 14 ! l Ust of Effective Pages (Cont'd) l Paae Revision Pa2e Revision ~ ' Pace Revision 'Page Revision l
; C1.0 12 121.0 12 161.0 12 82.0 12 122.0 12 162.0 12 83.0 12 123.0 12 163.0 12 84.0 .12 124.0 12 164.0 12 85.0 12 125.0 . 12 165.0 -
12' 86.0 12 126.0 12 - 166.0 12 87.0 '12. 127.0 12 167.0 12 88.0 12 128.0 12 168.0 12
.89.0 12 129.0 12 169.0 12 90.0 12 ' 130.D 12 170.0 12 91.0 12' 131.0 '12 171.0 12' 92.0 ~12. 132.0 12. 172.0 12 l
93.0 12 133.0 12 173.0 12 94.0 12 134.0 12 174.0 12
- 95.0 12 135.0 12 .-175.0 12~
96.0 12 .136.0 12 176.0 12 , j 97.0 12 137.0 12 177.0 12 98.0 14 138.0 , 12 . 178.0 12 99.0 12 139.0 12 179.0 12 , 100.0 ' ' 12 140.0 12 180.0 12 101.0 12 141.0 12 181.0 12 102.0 12' .142.0 ' 12 182.0 12 103.0 12 143.0' ' 12 183.0 12 104.0 12 144.0 12 184.0 12 105.0 12 145.0 12 185.0 12 106.0 12 146.0 ' 12 186.0 12 107.0 12 147.0 12 .187.0 12 108.0 12 148.0. 12 188.0 12 109.0 12 149.0 12 E11 11 110.0 12 150.0 12 E2-1. 11
, 111.0 .12 - 151.0 12 E3-1 11 112.0 12 152.0' .12 E4-1 3 113.0 12 153.0 12 E4-2 11 114.0 12 154.0 12 ES-1 11
. 115.0 12 155.0 12 E6-1 11 116.0 12 156.0 12 E7-1 3 117.0 12 157.0 12 E7-2 3 118.0 12 158.0 12 ' E7-3 3
' 119.0 '12 159.0 12 E7-4 3 120.0 12 160.0 12
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, .. Namtwe Nuclear " "ad doad o "t'*
s Departmental Procedure 6610-PLN-4200.01 l Tale Hewis4on No. Offsite Dose Calculation' Manual (ODCM) - 11 l
^
- INTRODUCTION The OFFSITE DOSE CALCut.ATION MANUAL (ODCM) is a supporting document'of the GPUNC Three MDe Island Nuciear Station (TMINS) Unit 1 and Unit 2 PDMS Technical Specifications and implements TMI radiological effluent c6ntrols. The ODCNI contains the controls, bases, and surveillance requirements for liquid and gaseous I
radiological effluents. In addition, the ODCM describes the methodology and parameters to.be used in the calculation of off-stte doses due to radioactive liquid and, gaseous effluents. This document also describes the l I methodology used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm / trip set points. Uquid and Gaseous Radwaste Treatment System configurations are also included. The ODCM also is used to define the requirements for the TMINS radiological environrnental monitoring program (REMP) and contains a ilst and graphical description of the specific sample locations used in the REMP. The ODC'M is maintained at the Three Mile Island (TMI) site for use as a reference guide and training document of - accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated into the ODCM to ensure the ODCM represents the present methodology in all applicable areas. GPUNC initiated , chariges to the ODCM will be implemented in, accordance with the TMI-1 and TM1-2 PDMS Technical Specifications.
- Thel 0DCM follows the methodology and.models'suggetted by N'UREG4133, and Regulatory Guide 1.109, p
Revision 1 for calculation of off-site doses due to giant effluent releases. Simplifying assumptions have been I applied in this manual where applicable to provide a more workable document for implementa+Jon of the l Radiological Effluent Controls requirements. . GPUN implements the TM1 Badiological Effluent Controls. Program and Regulatory Guide 1.21, Revision 1 (Annual l Radioactive Effluent Release Report) requirements by use of a computerized system used to determine TMI effluent
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l releases and to update cumulative effluent doses. l
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04-23-97 09:13:44 Number n /j Nuclear. ' "ad'oiood co"d= Departmental Procedure- 6610 PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) , 12 TABLE OF, CONTENTS PARTI TMl 1 RADIOLOGICAL EFFLUE'NT CONTROLS , Section .
- Page 1.0 DEFINITIONS 15.0
. Table 1-1, Frequency Notations, 18.0 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES '20.0 2.1 Radioactive Effluent Instrumentation .i 20.0 .
2.1.1 Radioactive Uquid Effluent instrumentation '20.0 2.1 ~.2 Radicactive Gaseous PScess and Effluent Monitoring instrumentation ' 23.0 Table 2.1 1, Radioactive Uquid Effluent Instrumentation' 21.0 s.m 24.0
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Table 2.1-2, Radioactive' Gaseous Process and Effluent Monitoring Instrumentatior$ 2.2 Radiological Effluent Controls 30.0 . 2.2.1 Uquid Effluent Controls 30.0 2.2.2 Gaseous Effluent Controls 33.0 i 2.2.3 Total Radioactive Effluent Controls- 38.0 3.0 SURVEILLANCES , 39.0 3.1 Radioactive Effluent Instrumentation s 39.0 3.'1.1 ^ Radioactive Liquid Effluent instrumentation
- 39.0 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation ' 42.0 Table 3.1 1, Radioactive L'iquid Effluent Monitoring instrumentation Surveillance Requirements 40.0 i
Table 3.1-2, . Radioactive Gaseous Process and Effluent Monitoring instrumentation 43.0 Surveillance Requirements 3.2 Radiological Effluents 48.0' 3.2.1 Uquid Effluents 48.0 3.2.2 Gaseous Effluent's 54.0 4.0 wu
t l 04.23-97 09:13:44. , Number
# (UClear WI Radiological Control's
' Departmental Procedure 6610-PLN-4200.01 '
( TWe Rewsion No. Offsite Dose Calculation Manual (ODCM) 12 l
- ,, TABLE OF CONTENTS PARTI TMI-1 RADIOLOGICAL EFFLUENT CONTROLS 1
3 l Section Page Table 3.2-1, Radioactive Uquid Waste Sampling and Analysis Program 50.0 3 Table 3.2-2, Radioactive Gaseous Waste Samp!!ng and Analy' sis Program ' 56.0 313 Total Radioactive Effluents 61.0 4.0 - PART I REFERENCES , 62.0 d i 1 i ) i n E ? l 4 l 4 e Y l . i i
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l 04-23'-97.09:13:44
, l . Number
? ( m (ggy TMl Radiological Controls
. Departmental Procedure 6610-PLN-4200.01 Y Title %sion No.
l Offsite Dose Calculation Manual (ODCM) 12 ! l TABLE OF' CONTENTS (Cont'd) PART11 TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section s Page , 10' DEFINITIONS , '64.d Table 1.1, Frequency Notation 66.0 2.0 RADIOLOGICAL EFFLUENT CdNTROLS.AND BASES 67.0 2.1 Radioactive Effluent Instrumentation 67.0 2.1.1' Radioactive Uquid Effluent instrumentation 20.0 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 67.0 Table 2.1.2, Radioactive Gaseous Process and Effluent Monitoring instrumentation 69.0 b t 2.2- Radio' active Effluent Controls - 70.0 . 2.2.1 Uquid Effluent Controls 70.0 2.2.2 Gaseous Effluent Controls . 72.0 2.2.3 Total Radioactive Effluent Controls 76.0 4 3.0 SU'RVEILLANCES 78.0 3.1 Radioactive Effluent instrumentation . 78.0 3.'1.1 Radioactive'Uquid . Effluent Instrumentation 78.0 3.1.2 Radioactive Gaseous Process and Effluents Monitoring Instrumentation 78.0 Table 3.1-2, Radioactive Gaseou's Process and Effluent Monitoring instrumentation , 79.0 Surveillance Requirements 3.2 Radiological Effluents , 80.0 3.2.1., ' Uquid Effluents 8b.0 3.2.2 Gaseous Effluents 82.0 Table 3.2-1, Radioactive Uquid Waste Sarnp!ing and Analysis Program 81.0 Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 83.0 3.2.3 Total Radioactive Effluents ' 86.0 6.0 n n, e
04-23-97 09':13:44 Number Nuclear '"' "ad'o'oo'ca' contro'$ Departmental Procedure. 6610-PLN 4200.01 Tw. noen wo. Offsite Dose Calculation Manual (ODC'M) 12 TABLE OF CONTENTS. (Cont'd) l PART11 TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section ,Page 4_0 ' DESIGN FEATURES . 87.0 . t j 4.1 SITE 87.0
! '4.1.1 ' Exclusion Area 87.0 4.1.2 Low Population Zone 87.0 4.1.3 Site Boundary for Gaseous Effluents 87.0 4 .
l 4.1.4 Site Boundary for Oguid Effluents 87.0 , 5.0 PART 11 REFERENCES 88.0 I i a
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04-23-97 09:13:44 , Number '
'^s Nuclear ' "*dio'octo*' co"tro'*
Departmental Procedure 6610-PLN-4200.01 : ('v) Title Revision Ne, Offsite Dose Calculation Manual (ODCM) 12 TABLE OF CONTENTS PART lil EFFLUENT DATA 'AND CALCUl.ATIONAL METHODOLOGIES Section , Page.
~1 .0 UQUID EFFLUENT MONITORS -
89.0 1.1' . TMI-1 and TMI-2 Uquid Radiation Monitor Set Points -
,89.0 1.2 TMi Uquid R'elease Points'and Uquid Radiation Monit'or Data 90.0' 1.3 Control of Uquid Releases - 92.0 2.0 LIQUID EFFLUENT DOSE ASSESSMENT . 97.d -
2.1 Uquid Effluents - 10 CFR 50 Appendix 1, , 97.0 2.2 TMl Uquid Radwa'ste System Dose Cales Once per Month 99.0 A Alternative Dose Calculational Methodology - 100.0
)- 2.3 3.0 LtQUID EFFLUENT WASTE TREATMENT SYSTEM -
105.0 3.1 TMI-1 Uquid Effluent Waste Treatment System 105.0
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3.2 Operability of TMI-1'Uquid' Effluent Waste Treatment System 106.0 3.3' .TMI-2 Uquid Effluent Waste Treatment System 106.0-4.0 GASEOUS EFFLUENT MONITORS 109.0 4.1 'TMl-1 Noble Gas Monitor Set Points. 109.0 4.2 TMI-1 Particulate and Radiolodine Monitor Set Points 111.0 4.3 TM1-2 Gaseous Radiation Monitor Set Points 112.0 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 113.0 4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 115.0 4.6 Control of Gaseous Effluent Releases 116.0 9 8.0
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a J- 6 0 04-2'3 f97 09:13:44 '
' . ' N$mber c)
( Nuclear ' "ad'*o'ca' coa"* Departmental Procedura 6610-PLN-4200.01
%/ Title Revision No.
I l Offsite Dose Calculation Manual (ODCM) 12 TABLE OF CONTENTS PART111 EFFLUENT DATA AND-CALCULATIONAL METHODOLOGIES Section Page, 5.0 GASEOUS EFFLUENT DOSE' ASSESSMENT 128.0 5.1 Gaseous Effluents - Dose Rate Limits 128.0 5.1.1 Noble Gases 128.0 5.1.1.1 Total Body 128.0 5.1.1.2 Skin 129.0 5.1.2 lodines and Particulates 130.0 5.2 ' Gaseous Effluents - 10 CFR 50 Appen' dix ! 131.0 A 131.0 d l 5.2.1 Noble Gases [ 5.2.2 lodines and Particulates 132.0 i 5.3 Gaseous Radioactive System Dose Calculations Once per Month 134.0
- J j 5.4 Afternative Dose Calculational Methodologies 135.0 6.0 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM , 157.0 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System 157.0 6.2 - Operability of the TMI.1 Gaseous Radwaste Treatment System ,157.0 , I 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 159.0 8.0 ' TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 160.0
' l 8.1 Monitoring Program Requirements 160.0 .
8.2 Land Use Census - 162.0 6.3 Intertaboratory Comparison Program 164.0 9.0 PART 111 REFERENCES 181.0 O 9.0 , nn. l
O'4'-23-9,7 09:13:44 Number A GUCIO8r m Radi i s i Controis Departmental.Procedur6r 6610-PLN-4200.'01 ( ) V' Tr'Je , nevision No. Offsite Dose Calculation Manual (ODCM) 12
. TABLE OF CONTENTS (Cont'd)
PART111 EFFLUENT DATA AND CAL'CULATIONAL METHODOLOGIES Section Page TABLES Table 1.1 TMI-1 Liquid Release Point and Liquid Radiation Monitor Dat'a , 93.0 Table 1.2 TMI-2 Sump Capachles 94.0 ' Table 2'.1 Liquid Dose Conversion Factors (DCF): DFij . 101.0 1
. Table 2.2 Bioaccumulation Factors, BFi ~ 104.0 Table 4.1 TMI-1 Gaseous Release Point & Gaseous Radiati,on Monitor Data 117.0 Table 4.2 TMI-2 Gaseous Release Point & Gaseous Radiaticn Monitor Data 118.0
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, Table 4.3 Dose Factors for Noble Gases and Daughters 119.0 Table 4.4 ' Atmospheric Dispersion Factors for Three Mile Island - Station Vent 120.0 Table 4.5 , Atmospheric . Dispersion Factors for Three Mile Island Ground Release 121.0
, Table 4.6 Dose Parameters for Radiciodines and Radioactive Particulate, Gaseous, Effluents 122.0 Table 5.2.1 Pathway Dose Factors, R3 - Infant, inhalation ,
136.0-Table' 5.2.2 Pathway Dose Factors, R, - Child, Inhalation 137.0 Table 5.2.3 Pathway Dose Factors, Ri - Teen, inhalation 138.0 Table 5.2.4 Pathway Dose Factors, R3 - Adult, Inhalation 139.0
' 140.0 Table 5.3.1 Pathway Dose Factors, R';- All, Age' Groups, Ground Plane Table 5.4.1 Pathway Dose Factor's, Ri - Infant, G'rass-Cow-Mak 141.0 Table 5.4.2 Pathway Dose Factors,.R; , Child, Grass-Cow-Milk 142.0 Table 5.4.3 Pathway, Dose Factors, Ri - Teen, Grass-Cow-Milk 143.0 Table 5.4.4 Pathway Dose Factors, R, - Adult, Grass-Cow-Milk 144.0 p Table 5.5.1 Patf1way Dose Factors R; - Infant, Grass-Goat-Milk 145.0 l
- 10.0 nm.
l 4 04-23-97 09:13:44 l l Number G TM1 Radiological Controls (6) EUO!OOI ' Departmental Procedur5 6610-PLN-4200.01 Title s Revision No. Off'site Dose Calculation Manual (ODCM) 12 l TABLE OF CONTENTS (Cont'd) PART lli EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES l l Section Page. l
< l TABLES :
Table 5.5.2 Pathway Dose Factors, R; - Child, Grass-Goat-Milk - 446.0 Table 5.5.3 Pathway Dose Factors, Ri -Teen, Grass-Goat-Mak. 147.0 Table 5.5.4 Pathway Dose Factor.s, Ri - Adult, Grass-Goat-Milk 148.0 _ Table 5.6.1 Pathwa.y Dose Factors, Ri - Infant, Grass-Cow-Meat 149.0 Table 5.6.2 Pathway Dose Factors, R, - Child, Grass-Cow-Meat 150.0 Table 5.6.3 Pathway Dose Factors, R3 Teen, Grass-Cow-Meat 151.0 m
} Table 5.6.4 Pa'thway Dose Factors, Ri - Adult, Grass-Cow-Meat 152.0
[O Table 5.7.1 PathwayOose Factors, R3 -Infant, Vegetation 153.0-Table 5.7.2 Pathway Dose Factors, Ri - ChDd, Vegetation 1'54.0
-Table 5.7.3 Pathway Dose Factors, R; Teen, Vegetation 155.0 Table 5.7.4 Pathway Dose Factors, Ri - Adult, Vegetation 156.0 Table 8.1 Sarnple Collection and Analysis Requirements 165.0 Table 8.2 Reporting Levels'for Radioactivity Concentrations in Environmental Samples 170.0 Table 8.3 Detection Capabilities for Environmental Sample Analysis 171.0 Table 8.4 TMINS REMP Station Locations - Air Particulate and Air lodine 173.0 Tab'le 8.5 TMINS REMP Station Locations - Direct Radiation (TLD) 173.0 Ta'ble 8.6 TMINS REMP Station Locations - Surface Wate'r 175.0 Table 8.7 TMINS REMP Station Locations Aquatic Sediment ,
175.0 Table 8.8 TMINS REMP Station Locations - Milk 176.0 TMINS REMP Station Locations Fish 176.0 9 Table 8.9 Table 8.10 TMINS REMP Station Locations - Food Products - 177.0 11.0 rm.
04-23-97 09:13:44 Nurnber o Nuclear.
'"' aad'o'oa'ca' coatro
( Departmental Procedure- 6610-PLN-4200.01
. Title ,
Revision No. - Offsite Dose Calculation Manual (ODCM) 12 , TABLE OF CONTENTS (Cont'd)- PART111 EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLE'S . MAP 8.1 Three Mile Island Nuclear Station Locations of Radiological Environmental ' Monitoring Program Sta.tions within 1 Mile of the Site - 178.0
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MAP 8.2 Three Mile Island Nuclear Station Location's of Radiological Environmental 179.0 ^ l Monitoring Program Stations within 5 miles of the Site MAP 8.3 Three Mile Is!and Nuclear Station Locations of Radiological Environmental 180.0 l Monitoring Program Stations Greater than 5 miles from the Site FIGURES Figure 1.1 TMI-1 Uquid Effluent Pathways' 95.0 l A Figure 1.2 TMI-2 Uquid Effluent' Pathways 96.0 Figure 3.1 TMI-1 Uquid Radwaste 107.0 Figure 3.2 TMl-1 Uguid Waste Evaporators 108.0 Figure 4.1 TMI-1 Gaseous Effluent Pathways 123.0 Figura 4.2 TMI-1 Auxiliary & Fuel Handling Buildings Effluent Pathways '124.0 Figure 4.3 TMI-1 Reactor Building Effluent Pat'hway 125'.0 Figure 4.4 ' TMI.1 Condenser Offgas Effluent Pathway 126.0 Figure 4.5 TMI-2 Gaseous Effluent Filtration System / Pathways- 127.0 Figure 6.1 Waste Gas System 158.0 l l 12.0 nw
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04-23-97 0'9:13:44 j Number ( Neaclear '"' "ad'o'o9'ca' contro Departmental Procedure" 6610-PLN-4200.01 (, Tatle . f4evision No.
- Offsite Dose Calculation Manual (ODCM) 12 4
TABLE OF. CONTENTS (Cont'd) PART IV- REPORTING REQUIREMENTS _ i t i 1 5 Section~.
- Page 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 184.0.
2.0 TMl ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 185.0 3.0 - PART IV REFERENCES , 187.0 APPENDICES ' A. Pathway Dose Rate Parameter (P) 3 E1-1 B. Inhalation Pathway Dose Factor (R)i E21 C. Ground Plane Pathway Dose Factor (R) i E3-1 D. Grass-Cow-Milk Pathway Dose Factor (R)i E4-1 E. . Cow-Meat Pathway Dose Factor (R) i . E5-1 -' 4 F. Vegetation Pathway Dose Factor (R i ) , E6-1 APPENDIX A - F REFERENCES E7-1 g 4 4 d
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~, quCES8r m n di i ou contres Departmental Procedure Number 6610-PLN-4200.01..
i Title fension W. $ Offsite Dose Calculation Manual (ODCM) 11 ~ 1 1 ~- i
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j . , 4 . 4 i t i i i PARTI i, 1 TMI-1 RADIOLOGICAL EFFLUENT CONTROLS 1 J j . t
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Nurnb., ('~)' , luclear' M RaddogMmrds Departmemal' Procedure 6610-PLN-4200.01 T won No. Offsite Dose Calculation Manual (ODCM)- 11 1 1.0 , DEFINITIONS , l l
, The following terms are defined for uniforrn interpretation of these controls and surveillances. l 1.1 Reactor Operating'Condrtions .
1.1.1 Cold Shutdown , The reactor is in the cold shutdown condition when it is subcrtical by at least one percent. deita k/k and Tavg is no more than 200* F. Pressure.is defined by Technical Specification 3.1.2. 1.1.2 Hot Shutdown The reactor is in the hot shutdown condition when it is subcritical by at least one percent deha k/k and Tavg is at or greater than 525 F.
. 1.1.3 Fieactor Crtical -
The reactor is critical when the neutron chain reaction is self-sustaining and Keff 5 1.0. j 1.1.4 Hot Standby
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s The reactor is in' the hot standby condition when all of the' following conditions exist: ,
- a. Tavg is greater Utan 525* F
- b. The reactor is critical
- c. Indicated neutron power on'the power range channels is less than two
. percent of rated power. Rated power is defined in Technical Specification
, Definition 1.1.
1.1.5 _ Power Operation ' . The reactor is in a power operating condition when the indicated neutron power is above two percertt of rated power as indicated on the power range channels. Rated power is defined in Technical Specificaten Definition 1.1. . 1.1.6 Refueling Shutdown The reactor is in the refueling shutdown condition when, even vth all rods removed, the reactor would be suberftical by at least one percent delta kp and the coolant temperature at. the decay heat removal pump suction is no more than 140 F. Pressure _is defined by Technical Specification 3.1.2. A refueling shutdown refers to a shutdown to replace or rearrange a!! or a portion of the fuel assemblies and/or control rods. ['
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04-23-97 09:13:44 ,' n .
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, M Radiologic 61 Con'Jols Departmental Procedure 6610-PLN-4200.01 Tro. ,
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. 1.1.7 ' Refueling Operation An operatio'n involving a change'in core geometty by rnanipulation of fuel or control rods when the reactor vessel head is removed.
1.1.8 Refueling 1,nterval
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, 'Tirse between normal refuelings of the reactor. This is defined as once per 24 months. ,
1 1.1.9 Startup
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The reactor shall be considered in the startup mode when the shutdown margin is reduced with the irrtent of going critical. , 1.1.10 Tave Tave is defined as the arithmetic average of the coolarn temperatures in the hot and co!d legs of the loop wth the greater number of reactor coolant pumps operating, if such a distinction of loops can be made. (A} 1.1.11 Heatup .'Cooldown Mod,e , V ~
. The heatup-coMdown mode is the range of reactor coolant temperature treater than 200* F -
and less than 525* F. 1.2 Operable - A system, subsystbrn, train, component or device shall be OPERABLE or have OPERABILITY wheriit
'Is capable of performing its specified function (s) and when all necessary attendant instrumentation l controls, electrical power, cooling or seal water, lubrication or other atedliary equipmentthat are required for the system, subsystem, train, component, or device to' perform its function (s) are also '
capable of performing their related support function (s). 1.3 Instrument Channel An instrument channel is the combination of sensor, wires, amplifiers, and output devices which are connected for the purpose of measuring the value of a process variable for the purpose of ' observation, control land/or protection. An' instrument channel may be either analog or digital. 1.4 - Instrumentation Survellance 1.4.1 Channel Test , A CHANNEL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practical to venfy OPERABILITY,-including alarm and/or trip functions.
't .4.2 - ChannelCheck 9 A CHANNEL CHECK shall be the' qualitative assessment of channel behavior during operation by observatiort This determination shall include,.where possible, comparison of 16.0 ww
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i l 04-23-97.09:13:44 l l
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Number l l V , NucleaI '" "*dio'oa'o=' c " trot *' Depart' mental Procedure 6610-PLN-4200.01 1 Tree Ammon No. . Offsite Dose' Calculation Manual (ODCM) 11
.- the channel indication an'd /or status with other indications and/or s*atus derived from independent instrumentation channels measuring the same parameter.
1.4.3 Source Check A SOURCE CHECK,shall be the qualitative assessment of channel response when the , channd sensor is exposed to a radioactive source.~
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1.4.4 Channel Calibration - An instrument CHANNEL CAU'BRATION is a test, and adjustment (if necessary), to establish that the' channel output responds with acceptable range and accuracy to known values of
' the parameter which the channel measures or an accurate simulation of these values.
Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip. and shall be deemed to include the channel test. 1.5 Dose Equivalent 1-131 The. DOSE EQUIVALENT l-131 shall be that concentration of I-131 (microcurie / gram) which alone {g would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132,1-133,
- j I-134, and 1-135 actually present.lhe thyroid dose conversion factors used for this calculation shall D be those listed in Table 111 of TID 14844, " Calculation of Distance Factors for Power and Test Reactor Sites *..[Or in Table E-7 of NRC Regulatory Guide 1.,109, Revision 1, October 1977.] .
1.6 Offsite Dose CaIculation, Manual (ODCM), The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the methodology and parameters , used in the calculation of offsite doses resutting from radioactive-gaseous and liquid effluent, in the calculation of gaseous and liquid effluent monitoring Alann/ Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains (1) the Radiological Effluent Controls, (2) the fladiologica! Environmental Monttoring Program and (3) descriptions of the information that should be induded in the Annual Radiological Erwironmental Operating and Annual Radioactke Effluent Release Reports.
. 1.7 Gaseous Radwaste Treatment .
The GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluent by collecting prirrary coolant system off gases from the primary system and providing for delay or holdup for the purpose.of reducing the total radioactivity prior to release to the environment. 1.8 Ventilation Exhaust Treatment System A' VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to' reduce gaseous radioiodine or radioactNe material in particulate form in effluent by passing ventilation or vent exheust gases through charcoat absorbers and/or HEPA filters for the purpose of removing lodine or particulates from the gaseous exhaust system prior to the release to the environment. Engineered Safety Feature (ESP) atmospheric cleanup. systems are not considered to be 9 VENTILATION EXHAUST BEATMENT SYSTEMS., 17.0 sm. 1 l l
04-23-97 09:13:44 b Number [V Nuclear T"' "*dio'oo'6iit coat'o'$ Departmental Procedure . 6610-PLN-4200.01 Title , Asvisson No. i . . Offsite Dose Calculation Manual (ODCM) . 11 1.9 Purge , Purging PURGE o PURGING.is the controlled process of discharging air or Das from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a
, manner that replaceme'n t air or gas is required to purify the confinement.
I 1.10 Venting , VENTING is the c$ntrolled process of discharging air as gas from a confinement to maintain l temperature, pressure, humidity,' concentration or other o'perating condt:lons in such a manner that
. replacement air or gas is not provided. Vent used in system name does not imply a VENTING process. ,
1.11 Member (s) of the Public MEMBER (S) OF THE PUBUC shall include alf persons who are not occupationa!!y associated with the plant. This category does not include employees of the GPU System, GPU contractore or vendors. Also excluded from this category are persons who enter the site to service equiprneet or to m'ake deliveries. ' p Site Boundary 1 1.12
;b . . , , , , ,
The SITE BOUNDARY-is 'the boundary line forming the base for the limits on the release of gaseous
~
effluents as defined in Section 2.1.2 2 of the TMI.1 FSAR and shown on Figure 2.1-3 of the TMI-1
. FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Three Mile' island and between Three Mile island and Shelley,istand.
. 1.13 Frequency Notation The FREQUENCY NOTATION specified for the performance of SurveD!ance Requirements shall correspond to the intervals defined in Table 1-1.' All Survealance Requiremerra shall be performed within the specified time interval with a maximum allowable extension no,t to exceed 25% of the surveillance interval. The 25% extension applies to all frequency intervals with the exception of 'F.*
No extension is allowed for intervals designated 'F.' Table 11 Frequency Notation ,
. i Notation Frequency
,S .. .Shiftly (once per 12 hours)
D Daily (once per 24 hours) . W Weeldy (once per 7 days) M MontNy (once per 31 days) 4 18.0 ma
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- hCl@8p M RadiologicRontrols Departmental Procedure Nwnber 6610-PLN-4200.01 Tltie . Aswaion No.,
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'Offsite Dose Calculation Manual (ODCM) 11
- Notation ,
Frequency
.O ~. Quarterly (once per 92 days)
^ S/A Semi-Annually,(once per 184 days) R Refueling Interval (once per 24 morths)
- P S/U Prior to each reactor startup, if not done during trie previous 7 days P Completed prior to each retease 4
N/A QJA) Not applicable , E Once per 18 months F Not to exceed 24 months . Bases
/ . . . .
(%) Section 1.13 establishes the limit for which the specified time interval for SurveBlance Requirements may be , (f extended. it permits an allowable extension of the normal surveillance interval to fac8 tate surveU!ance scheduling and congideration of plant operating conditions that may not be suitable for conducting the , I surveDiance; e.g., transient conditions 'or other ongoing surveillance or maltnenance activities. It also provides flexiblity to accommodate the length of a fuel cycle for surveiHances that are specified to be , performed at least once each REFUEUNG IffTERVAL lt is not intended that this provision be used repeatedly as a convenience to extend survellance intervals beyond that specified for surveilances that are not performed once each REFUEUNG INTERVAL .ukewise, it is not the intent that REFUEUNG INTERVAL . surveElances be performed during power operation unless it is consistent with safe plant operation. The limitation of Section 1.13 is based on engineering judgernent and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance-Requ,irements. This provision is sufficient to ensure that the reliabulty ensured through surveillance activities Is not signiScantly degraded beyond that obtained from the specified surveillance interval. e # m. d (m . 19.0 rm. d
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gEgp ' TMI Radiological' Controls Departmental Procedure -6610-PLN-4200.01 tine fievmon No. OnsCe Dose C'alculation Manual (ODCM) . 11 2.0 CONTROLS AND BASES , 2.1 Radioactive Effluent instrumentation 2.1.1 Radioactive Uguld Effluent instrumentation l COtRROL: 4 The radioactrve liquid effluert monitoring instrumentation channels shown in Table 2.1-1 shall
. be OPERABLE whh their alarm / trip setpoints set to ensure that the limits of Control 2.2.1.1' are not exceeded. The alarm / trip serpoints of these channels'shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
1 AP."UCABluTY: At all times
- 1 1
ACTION: .
, a. Wrth a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative thali required by the above control, Itnmediately suspend
(~Y the release of radioactive ligtAd effluent monitored by the affected channel or ( ), , declare the charinclinoperable. v.
- b. . With less than the minimum' number of radioactive liquid effluent moriito'ingr instrumentation channels OPERABl.E. take the ACTION shown in Table 2.1 1. Exert best efforts to retum the instrurnentabn to OPERABLE stattis within'30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a tirr:ely manner.
- For FT-84, and RM-LS, operability is not required when discharges are postively controlled through the closure of WDL-V257. i
- For RM-L12 and associated IWTS/lWFS flow interlocks, operabElty is not required when discharges are positively controlled through the closure of IW-V72,75 ard IW-V280,281.
- For FT 146, operability is not required when discharges are posbively controlled through the closure of WDL V257, I,W-V72; 75 ard IW-V280,281.
BASES The radioactive liquid effluent instrumentation is provided to man'ftor and control,'as applicable, the releases of radioactive materials in liquid effluent during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding ten times the effluent concentrations of 1.0 CFR Part 20.
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04-23-97 09:13:44 n - ( Nx*er
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. Departmental Proceduro 6610-PLN-4200.01 Tale . hmsior. No.
Offsite Dose Calculation Manual (ODCM) 11' Table 2.1-1 Radioactive Uquid Effluent instrumentation l Minimum
- j Channels Instrument Operable ACTION
,
- 1. Gross RadioactMty Monitors ,
Providing Automatic Termination
'of Release
- a. Unit 1 Uguld Radwaste Effluent. 1 18' ,
Line (RM-L6)
- b. IWTS/lWFS Discharge une (RM-L12) 1 20 - l 1
l
- 2. Flow Rate Measurement Devices .i
[ a. Unit 1' LJguld Radwaste Efflu'ent __ 1 21 ,
^ /
- 9 Une (PT-84)
- b. Station Effluent Discharge 1 21 (FT-140) ,
Table Notation
. l ACTION 18 Wrth the number of channels OPERABE less than required by the Minimum Channels OPERABT i requirement, effluent releases may continue, provided that prior to int: fating a release; ;
l
- 1. At lea'st two independent samples are analyzed in accordance with Surveillances 3.2.1.1.1 and 3.2.1.1.2 aind; At least two techn'.cally qualified members of the Unt!. staff independent!y'vertfy the release 2.
rate calculations and verify'the discharge valve lineup.
- 3. Director Operations and Maintenance TMI shall approve each release.
Otherwise, suspend release of, radioactive' effluents via this pathway. ACTION 20 Wtth the number of channels OPERABliess than required by.the Minimum Channels OPERABE requirement, effluent releases via this pathway may commence or continue
.provided that grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 1x10# microcurie's/mt,' prior to initiating a release and at least once per 12 hours during release _
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- . - Number ggggggy W Radiologic & Controls Depailiv rdal Procedure-6610-PLN-4200.01
. j i
True Revapon No. l ! l
, Offsite Dose Cilculation Manual (ODCM) 11 l Table 2.1-1 (Cont'd) -
ACTION 21 With the number of channels OPERABLE less than required by the Minimum Channels I OPERABLE requirement, radioactive eff!uent releases via this pathway may continue, prcwided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate f!ow. i I
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04-23-97 0'9:13:44
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TMl RadiologicM Dontrols Departmental Procedure 6610-PLN-4200.01 TMe Feemsen No. , Offstte Dose Calculatiori Manual (ODCM) 11
' 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation -
COffrROL: The radioactrve~ gaseous process and effluent' monitoring instrumentation channels shown in . Table 2.1-2 shall be OPERABLE with their alarm / trip setpoims set to ensure that the limits of Control 2.2.2.1 are not exceeded. The slarm/ trip setpoints of these channels shall be l determined in accordance with the QFFSITE DOSE CALCULATION MANUAL (ODCM). s ,
' APPLICABILITY: As shown in Table 2.1-2.
ACTION: -
- a. With a radioactive gas'eous process or effluent monitoring instrumentation chanrel alarm / trip setpoint less conservative than required by the above control,.
Immediately suspend the release of radioactive effluent monitored by the affected ' channel or declare the channel inoperable.
- b. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACITION shown in Table 4
O f 2.1-2. Exert best efforts to return the' instrumentation to OPERABLE status within 30
~
( days and, if unsuccessful, explain in the next Annual Effluent Release Report why
' - the inoperability was not corrected in a timely manner.
BASES 1 The radioacthre gaseous efiluent instrumentation is provided to ' monitor and control, as
- i appucable, the releases of radioactive materials in gaseous effluent during actual.or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance' whh NRC approved methods in the ODCM to provide r9asonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301.-
1
- lne low range condenser offgas noble gas acthrity monitorslatso provide data for determination of steam generator primary to secondary leakage rate. Channel operability requirements are based on an ASLB Order No. LBP-84 47 dated October 31,1984, and as I l
cited in 20 NRC 1405 (1984). 1 4 i e 6 W.s F'd . 23.0 mm.
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. - O Table 2.1-2 6810-PLN-4200.01 '
w R,pvision 11 ' Radioactive G'asecus Process and Effluent Mon!toring instJumentation U
. . MINIMUM CHANNELS INSTRUMENT , OPERABLE APPUCABluTY ACTION
, 1. Waste Gas Holdup System .
1- *** 25
. a. Noble Gas Activity Monitor (RM.A7) ,
*** 26
- b. Effluent System Flow Rate Measurfng Device (FT-123) 1
~
^2. Waste' Gas Holdup System Explosive Gas Montoring System -
2 ** 30
. a. Hydrogen Monitor '
- b. Oxygen Mon! tor '2 ** 30 .
- 3. ' Containment Purge Monitoring System
- e. Noble Gas ActMty Monitor (RM-A9) 1 # ' 27.
~
- b. lodine Sampfer (RM.A9) 1 # '31 i
- c. Particutate Sampler (RMA9) 1 #. ~ 31
- d. Effluent S~y stem Flow Rate Measuring Dovice (FR.148) ~1~ # 26
- e. Sampler Flow Rate MonIt6r .,1 # 26 e
4 6
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- ~R,evision 11 ? .
Radioactive daseous Process and Effluent Monitoring Instrumentatlon ' w
-, y MIN 1 MUM CHANNELS INSTRUMENT . OPERABLE 'APPLICABluTY- ACTIQN
- 4. Condenser Vent System. .
- a. Low Range Noble' Gas IctMiy Monlior (RM-ASto and 2M ## .
32 . Sultable Equivalent) . . NOTE (1): For one of the channels, an operable channel may be defined for purposes of th!s cohtrol and 3.1.2.1 only as a suitable equivalent monitoring system capable of balng placed in service within one hour. A suitable equivalent, system shall include Instrumentat!on w!th. comparable sensitMty and responsa time to the RM-A5to rnonttoring channel. When the equivalent rnonitoring system is in service, - indication will be Continuously avaliablo to the operator, either through Indicatlon and alarm in the Control Room or through communication with a designated indMdual continuously observing local indication.
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' = Revision it ! e Radtbactive daseous Process and Effluent Mon!toring Instrumentation f b
b MINIMUM CHANNELS INSTRUMENT , OPERABLE APPLICABillTY ACTION - S. Auxiliary and Fuel Hand!1ng Butiding VentRation System -
- e. Nob!s Gas Activity Monitor (RM-A8) or (RM-A4 'and
. RM-AC) - . 1 . 27 ,
- b. lodine Samples (RM-A8) or (RM A4 and RM-AG) 1 *. 31
- c. Particulate Sampler (RM A8) or (RM-A4 and RM-A6) 1- 31'
- d. Effluent System Flow Rate M'essuring Devices (FR-149 i1 26 and FR-150) -
I Sam'pler Flow Rate Monitor
- 26
- e. 1
, 6. Fuel Handling BulidIng ESF Air Treatment System .
- a. Noble Gas ActMty Monitor (RM-A14 or Sultable ,
**** 27,33 Equfvalent) -1 l
' i
- b. ' 4tne Cartridge M **** 31,33 N/A -
*"* 31,33
- c. Particulate Filter ~ N/A9
**** 26,33
- d. Effluent System Ficw (UR-1104A/B) . 1~ -
- c. Sampler Fiow Rate Mon!!or 1
'*"*- 26,33 NOTE 2:' No Instrumentation cha nel is previded. However, for determining operability, the' equipment named must be installed and functional or the ACTION applies.
26.0 - mi.
. S'
.I ey, o Radioactive Gaseous Process and Effluent Monitoring instnamentation 4 S
MINIMUM y CHANNELS - w INSTRUMENT OPERABLE APPLICABILITY ACTION 'a b
- 7. Chemical Cleaning Building Ventilation System i a. Noble Gas Activity Monitor.(ALC RM-i-18) 1W ### - 27
- b. lodine Sampler (ALC RM-l-18) 1 W ### 31
- c. Particulate Sampler (ALC RM-t-18) 1 ### ~ 31
- 8. Waste H
' andling and Packaging Facility Ventilation System
- a. Particulate Sampler (WHP-RIT-1) 1 ### 31
- 9. -Respirator and Laundry Maintenance Facility Ventilation System
- a. Particulate Sampler (RLM-RM-1) 1 ### 31 t
NOTE 3: Channel only required when IIquid radwaste is moved or processed within the facility. 27.0 mm.
04-23-97 09:13:44 I Number (a\- 1 htte Nasclear T"' "ad'o'oo'cai contro's Departmental Procedure 6610-PLN-4200.01 Revison No. i 1 Offsite Dose Calculation Manual (ODCM) 12
, PART11 l
)
Definitions , ! 1.0 DEFINITIONS DEFINED TERMS . . 1.1 The DEFINED TERMS' of t?.is section appear in capitrJized type and are applicable throughout Part !! of the ODCM. PDMS 1.2 Post-Defueling Monitored Storage (PDMS) is that condition where TMI-2 defueling has been ! completed, the core debris removed from the reactor during the clean-up period has been shipped off-site and the facility has been placed .in a stable, safe and secu're condition. ACTION 1.3 ACTION shall be those additional requirements specified as corollary statements to each control and shall be part of the controls. [
\
OPERABLE - OPERABILITY 1.4 A system, subsystem, train, comporient or' device shall be OPERABLE or have OPERABluTY when it is capable of performing 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 or seal water, lubrication or other auxiliary equipment, that are required for the system, subsystem, train, component or device to perform its function (s), are also capable of performing their related support function (s). l CHANNEL CAUBRATION , 1.5 A CHANNEL CAUBRATION shall be the adjustment, as necessary, of the channel output such that it responds W1th necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAUBRATION shall encompass the entire channel including the sensor
. and alarm and/or trip functions, and shall include the CHANNEL FU.NCTIONAL TEST. CHANNEL CAUBRATION rnay be performed by any series of sequential, overiapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK ' 1.6 A Ch/NNEL CHECK shall be the qualitative assessment of channel behavior during operation by
, obseniation. .This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
) e V
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1 04-23-97 09:13:44 l
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(*) 4tECI9th,* l m R dia at al Contras Departmental Procedu?e 6610-PLN-4200.01 s
\
~ Jit' Revision No.
Offsite Dose Calculation Manual (ODCM) 12 CHANNEL FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shall be: at Analog channels - the injection of a' simulated signal intd the chahnel as close to the primary sensor as practicable to verify OPERABill1Y including alarm and/or trip functions. l
- b. Bistaole channels - the injectiori of a simulated signal into the channel sensor to verify OPERABILITY inclu' ding alarm and/or trip functions.
SOURCE CHECK 1.8 A SOURCE CHEdK shall'be the qualitative assessment of channel response when the channel ' sensor is exposed to a radioactive source. COMPOSITE SAMPLE 1.9 . A COMPOSITE SAMPLE is a combination of individual samples obtaliied at regular intervals over a l time period. Elther the volume of each indMdual sample is proportional to the flow rate discharge at j the time of sampling or the number of equal volume samples is proportional to the time period used l
/ s to produce the composite.
(' GRAB SAMPLE , 1.10 A GRAB SAMPLE is an individual sample collected in less than fifteen minutes. , BATCH RELEASE 1.11 A BATCH RELEASE is the discharge of fluid waste of a discrete volume. CONTINUOUS RELEASE 1.12 A CONTINUOUS RELEASE is the discharge of fluid waste of a nondiscrete volume, e.g., from a i volume or system that has an input flow during the CONTINUOUS RELEASE. I FREQUENCY NOTATION , 1.13 The FREQUENCY' NOTATION specified for the performance of Surveillance Requirements shall ' correspond to the intervals defined in Table 1.1. All Surveillance Requirements shall be performed within the specified time interval.wlth a maximum allowable extension not to exceed 25% of the . surveillance interval. 1 A (v) 65.0 n n, e
> e 04-23-97 ,09:13:44 .
Number e (UClear '
.W Radiolo@ cal Controls6610-PLN-4200.01 j ! (
U) m.. Departmental Procedure nevison no. Offsite Dose Calculation Manual (ODCM) 12 TABLE 1.1
)
Frequency Notation NOTATION FREQUENCY I S (Shiftly) At least once per 12 hours. D (Daily) At least'once per 24 hours. W (Weekly) ~ At least once per 7 days.
~
- M (Monthly) . ' At least once per 31 days.
J Q (Quarterly) At least once per 92 days. , SA (Semi-Annually) At least once per 184 days. ) 1
- A (Annually) At le'ast once per 12 months.
! Og E At least once per 18 months. i (j N A. Not applicable.
)
,1, < j P ' Completed prior to each release i 1 l I 4 d 8 e pm (' 6'6.0 nm. E 4
04-23-97 09:13:44 l Number ( A gggp TMl Radiological Controls 6610-PLN-4200.01
') inde Departmental Procedur~e Revision No.
Offsite Dose Calculation Manual (ODCM) 12 2.0 CONTROLS AND BASES 2.0.1 Controls and ACTION requirements shall be applicable during the conditions specified for each control. l
. l 2.0.2 Adherence to the' requirements of the Cont'ol r and/or associated ACTl,0N within the specified tima interval shall constitute compliance with the control. In the event the Control !
is restored prior to expiration to the'specified time interval, completion of the ACTION statement is not required. 2.0.3 In the event the Control and associated ACTION requirements cannot be satisfied because l
' of circumstances in excess of those addressed in the Control, initiata appropriate actions to rectify the problem to the extent possible under the' circumstances, and submit a special ]
report to the Commission pursuant to TMl-2 PDMS Technical Specification (Tech.' Spec.) Section 6.8.2 within 30 days unless otherwise specified. 2.1 Radioactive F; fluent instrumentation 2.1.1. Radioactive Liquid Effluent Instrumentation ' (b) Radioactive Liquid Effluent Instrumentation is common between T'MI-1 and TMI-2. Controls, I applicability, and actions are specified in ODCM Part I, Control 2.1.1 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CO'N TROL' The radioactive gaseous process and effluent m ' onitoring instrumentation channels shown in Table 2.1-2 shall be ' OPERABLE with their alarm / trip setpoints set to ensure that the limits of , Control 2.2.2.1 are not exceeded. The alarm / trip setpoints of these channels sha!! be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). APPUCABluTY; As shown in Table 2.1'2. - ACTION:
- a. - With a radioactive gaseous process or effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above control, Immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable.
i
- b. With less than the minimum number of radioactive gaseous process or effluent l
monitoring instrumentation channels OPERABLE, take the ACTION shown in Table ' 2.1-2. Exert best efforts to return the instrumentation to OPERABLE status within 30
. . days and, if unsuccessful, explain in the next . Annual Effluent Release Report why the inoperability was not corrected in a timely manner.
m 1 t 67.0 am, 9
04-23-97 09:13:44 Number gUCgGar TM1 Radiological Controls 3 y; w, Departmental Procedure 6610-PLN-4200.01 Revisson No. Offsite Dose Calculation Manual (ODCM) 12
' BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODQM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301.
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.a W
' Revision 12 g
~
. Radioactive Gaseous Process and Effluent Mon!toring Instrumentation MINIMUM U CHANNELS W INSTRUMENT OPERABLE APPLICABILITY ACTION -
- 1. . Containment Purge Monitoring System
- a. Noble Gas Activity Mon (tor (2HP-R-225) 1 NOTE i NOTE 2
- b. " 3rticulate Monitor (2HP-R-225) 1 NOTE 1 NOTE 2
- c. ' Effluent System Flow Rate Measuring Device 1 NOTE 1 NOTE 3 (2AH-FR-5064)
~
- 2. Station VentBation System 1 NOTE i NOTE 2 -
- a. Noble Gas ActMty Monitor (2HP-R-219) or .
(2HP-R-219A). , l' NOTE 1 NOTE 2
- b. Particulate Monitor (2HP-R-219) or (2HP-R-219A) 'I NOTE 1 NOTE 3 -
a
- c. Effluent System' Flow Rate Measuring Device
. (2HP-VPIR-219)
NOTES:
- 1. During operation of the monitored system.
~
~ 2; With the number of chandels OPERABLE less tisan required by the Minimum Channels OPERABLE requirement, secure Reactor Building Purge if in '
progress. 3: With now rate monitoring instrumentation out of service, flow rates from the AuxHlary, Fuel Handling, and Reactor Buildings may be estimated us!r,g - the maximum design flow for the exhaust fans in operation. . t 69.0 ma
04-23-97 09:13:44 Nurnber
/7 lUClear TMI Radiological Controls 6610-PLN-4200.01
(*) Title Departmental Procedurb Fievision No. Offsite Dose Calculation Manual (ODCM) , 12 2.'2 ' Radioactive Effluent Controls 2.2.1 Uquid Effluent Controls 2.2.1.1 . Liquid Effluent Concentration
' CONTROL:
The concentration of ' radioactive material released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part. 20.1001-20.2401, Appendix B, Table 2. Column 2. APPLICABluTY: At all times ACTION: With the concentration of radioactive material released from ;he unit to unrestricted areas ) exceeding the above limits, immediately restore concentrations within the above limits . O
! t l
y/ This control is provided to ensure that the concentration of radioactive materials released in (jquid waste effluent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2. These ! Controls permit flexibility under unusual conditions, which may temporarily result in higher than normal releases, but still within ten times the concentrations, specified in 10 CFR 20. It is expected that by using this flexibliity under unusual conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the annual average concentrations specified in 10 CFR 20. As a result, this Control provides reasonable assuranc'e triat the resulting annual exposure to an individual in off-site areas will not exceed the design objectives of Section ll.A of Appendix 1 to 10 CFR Part 50, which were established as requirements for the cleanup of TMI.2 in the NRC's Statement of Policy of April 27,1981. i 2.2.1.2 Liquid Effluent Dose CONTROL The dose or dose commitment to s MEMBER OF THE PUBUC from radioactive materials in liquid effluents released from the unit to the SITE BOUNDARY shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and
.to'less than or equal to 5 mrem to any organ.
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or. equal to 10 mrem to any organ.
APPLICABluTY: At all times [<m\ LY 70.0 nm,
04-23-97 09:13:44 Number A GUClear , M Radiological Controls Departmental Procedure 6610-PLN-4200.01 (% True Revision No. Offsite Dose Calculation Manual (ODCM) 12 l ACTION: r l 1
- a. With the calculated dose from th'erelease of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days,'a Special Report which identifies the cause(s) for i exceeding the limit (s) and defines the corrective actions to be taken to reduce the .
releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any indMdual from such releases during these four calendar quatters is within 3 mrem to the total body 7d 10 mrem to any l organ. This Special Report shall also include (1) the result of rr ological analyses of the drinking water source, and (2) the radiological impact or tished drinking water supplies with regard to the requirements of 40 CFR 141, kre Drinking Water Act.
. BASES This Control requires that the dose to off' site personnel be limited to the design objectives of -
Appendix l of 10 CFR Part 50. This will assure the dose received by the pubfic during PDMS is equivalent to or less than that from a normal operating reactor. The limits also assure that O the environmental impacts are consistent with those asse'ssed in NUREG-0683, the TMI-2 Programmatic Envirorimental Impact Statement (PElS). The ACTION statements provide the required flexibility under unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix'l to assure that the releases of radioactive material in liquid i
. effluents wl:1 be'kept "as low as is reasonably achievable". The dose calculatioris in the l ODCM implement the requirements in Section Ill.A. of Appendix ! that conformance with the guides of Appendix l'is to be shown by calcutational procedures based on models and data, such that the actual exposure of a MEMBER OF.THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified iri the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109,
' Calculation 'of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance witti 10 CFR Part 50, Appendix 1,' Revision 1, October, .
1977, and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April, 1977. NUREG-0133 provides methods for dose calculationg consistent with Regulatory Guides 1.1'09 and 1.113. 2.2.1.3 ' Liquid Radwaste Treatment System CONTROL: The apprppriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to eny organ in any calendar 4 month. , fs\
"Q APPLICABILITY: At all times 71.0 m
i
'b4-23-97 09: 13:44 i
'
- Number
!/') Nuclear TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 l
/ htte Rewaion No.
Offsite Dose Calculation Manual (ODCIVi) 12
/
ACTION:
- a. .With radioactive liquid waste being discharged without treatment and in
" excess of the above limits, prepare and submit to the NRC Region i Administrator within 30 days, a Special Report which includes the following
,. - information:
- 1. Explanation of Why liquid radwaste was being discharged without treatment, identifiestion of any inoperable equipment or subsystems.
- and the reason for inoperability,
- 2. Action'(s) taken to restore the inoperable equipment to OPERABLE status, and, 3.' A summary descriptiori of action (s) taken to prevent a recurrence.
BASES , The requirement that the appropriate portions of this system (shared with TMI-1) be used, when specified, provides assurance that the releases of radicactive materials O in liquid effluents will be kept as low as is reasonably achievable. This control k~ implements the requirements of 10 CFR Part 50.36a, General Design Criterton 60 of ' Appendix A to 10 CFR Part 50 and the design objective given in Section 11.D of Appendix l to 10 CFR Part 50. The intent of Section ll.D. Is to reduce effluents to as low as is reasonably achievable in a cost effective manner.' This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section ll.A of Appendix 1,10 CFR Part 50 dose requirements. This margin, a factor.of 4, constitutes a reasonable reduction. 2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL: , The dose rate due to radioactive materials released in gaseous effluent from the site shall be limited to the following: a.. For noble gases: less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and
- b. For tritium and all radionuclides in. particulate form with hali Irves greater than 8 days: less than or equal to 1500 mrem /yr to any organ.
APPLICADILITY: At all times. ACTION: With the release rate (s) exceeding the above limits, immediately decrease the release rate to comply with the above limit (s). 72.0 am.
l 1 04-23-97 09:13:44 . Number I Tui Radi 1 gi al Controts l
.( b) -(UClear Departmental Procedura 6610-PLN-4200 01 I
Title Revmon No. Offsite Dose Calculation Manual (ODCM) 12' t l BASES The control provides reasonable. assurance that the annual dose at the SITE BOUNDARY from gaseotJs effluent from all units on the site will be w!!hin the annual dose limits of 10 CFR Part 20 for unrestricted are&s. At the same time, these Controls permit flexibility under unusual conditions, which may temporarily result in higher than the design objective levels, but still within the dose limits specified in 10 CFR 20 and within the design objectives of Appendtk i to 10 CFR 50. It is expected that using this flexibility under unusual conditions, and by exerting every effort to keep levels of radioactive material in gaseous wastes as low l as practicable, the annual releases will not exceed a small fraction of the annual dose limits specified in 10 CFR 20 and will not result in doses which exceed the design objectives of Appendix 1 to 10 CFR 50, which were endorsed as limits for the cleanup of TMI-2 by the NRC's Statement of Policy of April 27,1981. These gaseous release rates provide reasonable assurance that radioactive material discharged in gaseous effluent will not result in the exposure of a MEMBER OF THE PUBUC in an unrestricted area, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the values specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY the occupancy of the MEMBER OF THE 4 PUBUC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The'specified release rate limits restrict, O at all times, the corresponding gamma and beta dose rates above background to a I MEMBER OF THE PUBUC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem / year to the total . body or to less than or equal to 3000 mrem / year to the skin. The absence of iodine ensures that the corresponding thyroid dose rate above background to an Infant via the inhalation pathway is less than or equal to 1500 mrem /yr (NUREG 0133), thus there is no need to specify dose rate limits for these nuclides. 2.2.2.2 Gaseous Effluents Dose-Noble Gases CONTROL: The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:
- a. During any calendar quarter: less than or edual to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,
- b. During any calendar year: less than or ' equal to 10 mrad for gtmma radiation and.
less than or equal to 20 mrad for beta radiation. APPUCABILITY: dt all times. ACTION:
- a. With the calculatedl air dose from radioactive noble gases in_ gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for 9 exceeding the limit (s) and defines the corrective actions that have been taken to
~
reduce the releases ar.d the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. 73.0 nm.
04-23-97 09:13:44 Number M Radiological Controls D 4MClear Departmental Procedure .6610-PLN-4200.01 (v) rnie nemion No.
, Offsite Dose Calculation Manual (ODCM)' 12 -
BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-2. 1 This control and associated action is provided to implement the requirements of Section ll.B, Ill.A and IV.A of Appendix 1,10 C,FR Part 50. The Control implements the guides set forth in Section Il B of Appendix 1. The ACTION statements provide flexibility'under unusual conditions and at the same time implement the guides set forth in Section IV.A of. Appendix l to assure that the releases of radioactive material in gaseous effluents will be kept 'as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with.the guides of Appendix 1 be shown by calculational procedures based on models and data such that the actual ex'posure of a i MEMBER OF THE PUBUC through the appropriate pathways is unlikely to be substantially j underestimated. The dose calculation methodology and parameters established in the l ODCM for cotculating the doses due to the actual release rates of radioactive noble gases in I gaseous effluents are consistent with the methodology provided in Regulatory Gulde 1.109,
" Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1,* Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"
,O. Revision 1 July 1977. The ODCM equations provided for 'deterrriining the air doses at and
( beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. NUREG.0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111, 2.2.2.3 Dose - lodine-131, lodine-133. Tritium, and Radionuclides in Particulate Form . CONTROL: The dose to a MEMBER OF THE PUBLIC from Tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released.from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:
.a. During any calendar quarter: less than or equal to 7.ti mrem to any organ, and
, b. During any calendar year: less than or equal to 15 mrem to any organ.
APPLICABILITY: At all times. . ACTION: , With the calculated dose from the release of Tritium and radionuclides in particulate" form with halllives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region 1 Administrator within 30 days, a Special Report which Hentifies 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 will be in compliance with the above limits.
/
- v ,
II7ls
04-23-97 09:13:44 Numtm C' -(UClear TMl Radiological Controls Departmental Procedur~e 6610-PLN-4200.01 4v Title Revision No Offsite Dose Calculation Manual (ODCM)- 12 BASES , This control applies to the release of radioactive materials in gaseous effluents from TMI-2. This control and associated action is provided to implement the requirements of Section ll.C. It!.A and IV.A of Appendix 1,10 CFR Part 50. The Controls are the guides set forth in Section 11.C of Appendix 1. The ACTION statement provides flexability during unusual . . conditions and at the same time implements the guides set forth in Section IV.A of Appendix i to assure that the releases of radioactive materials in gaseous offluents will De kept *as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section Ill.A,of Appendix i that' conformance with the guides of Appendix 1 be shown.by. calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBUC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational
~
methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the me'hodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,' P.evision 1 October, 1977 and Regulatory Guide 1.111," Methods for Estimating Atmospheric Transport and Oispersion of Gaseous Effluents in Routine Releases from Ught-Water. Cooled Reactors,"
(N Revision 1 July,1977. These equations also provide for determining the actual doses based (') .upon the historical average atmospheric conditions. The release rate controls for iodine-131, lodine-133, tritium and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing r'adionuclide pathways to man, in areas' at and beyond.the SITE BOUNDARY The pathways that were examined in the development of these calculations were: 1) indMdual inhalation of airborne radionuclides,2) deposition of radionuclides onto green leafy vegetation intth subsequent consumption by man,3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the m!!k and meat by man, and 4) deposition on the ground with subsequent exposure of man. The absence of iodines at the site eliminates the need to specify dose limits for these nuclides. 2.2.2.4 Ventilation Exhaust Treatment System - CONTROL The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the VENTILATION EXHAUST TREATMENT ' SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the montNy projected doses due to gaseous effluent releases from the site would exceed 0.3 mrem to any organ. APPUCABluTY: At all times. 75.0 m I l I l J
1 l 04-23-97 09:13:44 l ' Nurnber j NN l 4EIClear M Radiological Controls
' Departmental Procedure 6610-PLN-4200.01 (V T ue Revison No.
l
\
Offsite Dose Calculation Manual (ODCM) 12
)
ACTION. , 1
- a. With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste beitig discharged without treatment and in excess of the above limits, prepare'and submit to the NRC Region ! Administrator within 30 days, a Special Report which includes the fo!!owing information:
- 1. Identification of the inoperable equipment or subsystems and the. reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and .
- 3. A summary description of action (s) taken to prevent a recurrence.
. l BASES I The use of th'eVEfRILATION EXHAUST TREATMENT SYSTEM ensures that gaseous
, effluents are treated as appropriate prior to release to the environment. The appropriate l l '
portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be ke'pt *as low as is reasonably achievable.' This control s' implements th's requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 1'O CFR Part 50, and the design objectives given in Section ll.D of Appendix I 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 guide set forth in Sections ll.B and ll.C , of A'ppendix 1,10 CFR Part 50, for gaseous effluents.' ' 2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose ' CONTROL: The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem. APPLICABILITY: At all times. ACTION: With the ca!culated dose from the ' release of radioactive materials in liquid or gaseous
. effluents exceeding twice the limits of Controls 2.2.1.2.a 2.2.1.2.b, 2.2.2.2.a. 2.2.2.2.b, 2.2.2.3 a, or,2.2.2.3:b, calculations should be made including direct radiation contributions from the Unit and from outside storage tanks.to determine whether the above limits of Control 2.2.3.1 lieve been exceeded. If such is the cas'e, prepare and submit to the NRC
[T
\
- Region I Adrninistrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above i 76.0 i sm.
i l
04-23-97 09:13:44 i Number r TMI Radiological Controls 4tXClear , (NN Tiue , Departmental Procedure 6610-PLN-4200.01 Revision No. j { i Offsite Dose Calculation Mariual (ODCM) 12
, limits and includes the schedule for ' achieving conformance with the above limits. This
'Special Report, as defined in 10 CFR Part 20.2203(b), shall include an analysis which e'stimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel ,
cycle sources, including all effluent pathways and direct radiation, for the calendar yea'r that
- includes the release (s) covered by this report. It shall elso describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposuYe levels or concentrations. If the estimated dose (s) exceed the above limits, and if the release .
, condition resulting in violation of 40 CFR 100 has not already been correcteo, the Special Report shall include a' request for a variance in accordance with the provisions of 40 CFR
- 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
BASES. . { This control is provided to meet the dose limitations of 40 CFR Part 190 that have' been incorporated into 10 CFR Part 20.1301(d). This control 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 t'o less than or equal to 76 mrom. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF '. [] THE PUBLIC wil,1 exceed the dose lim!!s of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the *
\\j reactor units,and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBUC to within the 40 CFR Part 1JO limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member o,f the public from other uranium j fuel cycle sources is negligible, with the exception that dose contributions from other nuclear .
fuel cycle facilities at the same site or within a radius of 8 km must be considered.. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a ' timely request and fulfills the r.equirements of 40 CFR Part 190 until NRC staff action is ) completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in ; any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individual is not co.nsidered a MEMBER OF THE PUBUC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. l 1 1 l s l
. 1 77.0 nm.
I i
04-23-97 09:13:44 Number I Radiological Controls "T (UClear. Departmental Procedurn 6610-PLN-4200.01 d (
'j Title Revision No.
Offsite Dose Calculation Manual (ODCM) 12 t 3.0 SURVEILLANCES 3 3.0.1 Surveillance Requirements shall be applicable during'the conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement. The Surveillance Requirements shall be performed to demonstrate compflance with the OPERABluTY . . requirements of the Control. 3.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension nat to exceed 25% of the surveillance interval. 3.0.3 Failure to perform a Surveillance Requi.rement within the time interval specified in Section 3.0.2 shall constitute non-compliance with OPERABluTY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identtfied that a Surveillance Requirement has not been performed. .The ACTION requirements may be delayed for up to 24 hours to permit, completion of the surveUlance when the allowable outage time limits of the ACTION requirements are less than 24 hours. Surveillance Requirements do not have to be performed ' on inoperable equipment. l 3.1 Radioactive Effluent instrumentation
~
( 3.1.1 Radioactive Uquid Effluent Instrumentation Surveillance Requirements - , Ra'dioactive Uguid Effluent instrumentation is common between TMI-1 and TMI-2.
.Surveillances for this instrumentation are specified in ODCM Part I, Surveillance 3.1.1.
3.12 Radioactive Gaseous Process and Effluent M' onitoring Instrumentation i SURVEILLANCE RE.OUIREMENTS l l 3.1.2.1 Each radioactive' gaseous process or effluent monitoring instrumentation channel shall be ' demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, l CHANNEL CAUBRATION, and CHANNELTEST operations at the frequencies shown in Table 3.1-2. , 5 0 . 78.0 , mm.
S
., , n .
\ Table d.. .e 6610-PLN-4200.. . w 4
Revision 12 o Radloactive Gaseous Process and Emuent' Monitoring Instrumentation Surveitiance Requiremen's-U. a CHANNEL A CHANNEL- CHANNEL
' INSTRUMENT CHECK CAUBRATION FUNCTIONAL TEST APPUCABILITY
- 1. Containment Purge Monitoring System -
- a. Noble Gas ActMty Monitor (2HP-R-225) D E M NOTE 1
- b. Particutate Samp'er (2HP-R-225) -
W N/A N/A NOTE 1
- 2. Station Vent 2ation Monitoring System
- a. Noble Gas ActMty Monitor (2HP-R-219) and D E M NOTE 1 y
(2HP-R-219A) -
- b. Particulate Sampler (2HP-R-219) and (2HP-R-219A) W _
N/A N/A NOTE 1 NOTES: During operation of the monitored system. .i { 1. a e 4 0 I 79.0 m=
- um
04-23-97 09:13:44 Number 4 7% ggggggy M Radiological Contmls Departmental Procedure 6610-PLN-4200.01 ( ) . Revision No, (/' Trtte ; i Offstte Dose Calculation Manual (ODCM) 12 I 3.2 Radioactive Effluents
. 3.2.1 Liquid Effluents SURVEll1ANCE REQUIREMENTS 3.2.1.1 Concentration l 3 3.2.1.'t .1 The ra'dioactMty content of each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with ;
1 Table 3.2-1. The results of analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control .2.2.1.1. I 3.2.1.1.2 Analysis of samples composited from batch releases shall be performed in accordance with Table 3.21. The results of the analysis shall be used with the calculational methods in the ODCM to assure '
' that the conce'ntrations at the point of release were maintained within the limits of Control 2.2.1.1.
p 3.2.1.1.3- The radioactivity concentration of liquids discharged from continuous ( I release points shall be determined by collection and analysis of - I samples in accordance with Table 3.2-1. The results of the analysis shall be us'ed with the calculational methods of, the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.
. 3.2.1.2 Dose Calculations s
3.2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month. 3.2.1.3' Dose Projections 3.2.1.3.1 . Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM.. I O 80.0 sm. t
I 04-23-97 09:13:44 -
, s Number
" aadido*a' co""d*
p . Nuclear- Departmental Procedure 6610-PLN-4200.01 (V) Tale Revision No.
'Offsite Dose Calculation Manual (ODCM) 12 TABLE 3.2-1 Radioactive Liquid Waste Sampling and Analysis (4,5) .
A. Liould Releases
. Type of Detectable Sampling Frequency Activity Analysis, Concentration (3)
P, individual Gamma SE-7 Cl/ml (2) ', Each Batch H4 1E-5 pC1/mi Q Gross Alpha 1E-7 pCl/ml Quarterly Composite (1) - Sr-90 SE-8 pCi/mi NOTES: (1) A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional ' ~ to the quantity of liquid waste discharged'from the plant.
}
(2) For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in *:oncentrations near this sensitivity limit when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using ' measured ratios with those radionuclides which are routinely identified and measured. .
.(3) The detectability limits for radioactMty analysis are based on the technical feasibi!!!y and on tile potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported.
(4) The results of these analyses sho'uld be used as the basis for recording and reporting the quantities of radioactive material released in liquid effluents during the sampling period.1,rr estimating releases for a period when analyses were not performed, the average of the two adjac'ent data points spanning this period should be used. Such estimates should be included in ttle effluent records and reports; i.cwever, they should be clearly identified as estimates, and the method used to obtain these data should be described. (5) Deviations from the sampling / analysis regime will be noted in the rep' ort specified in ODCM Part IV. P $ o 9 f 81.0 a.n.
04-23-97 09:13:44 Number . TMl Radiological Controls
/~') MUClear Departmen*al Proceilura 6610-PLN-4200.01
( j Revision No.
\/ Trt6e Offsite Dose Calculation Manual (ODCM) 12 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates 3.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be
' determined to be within the limits of Control 2.2.2.1.a in accordance <
,wlth the methods and procedures of the ODCM.
3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be vkhin the limits of Control
. 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampiing and analysis program, specified in Table 3.2-2.
3.2.2.2 Dose, Noble Gas 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current O . calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.
' 3.2.2.3 Dose Tritium and Radionuclides in Particulate Form 3.2.2.3.1 Cumulative dose contributions from Tritium and radionuclides in particulate form with half lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CM) monthly.
3.2.2.4 Ventilation Exhaust Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM. O . 82.0 n n.
l
- l 04-23-97 09:13:44 l Nurnber O)
( IUClear M Radiolo@ cal Controls Departmental Procedure 6610-PLN-4200.01 l V Trtle Hewsion No. < l Offsite Dose Calculation Manual (ODCM) 12 l TABLE 3.2-2 Radioactive Gaseous Waste Sampling and Analysis (3) SAMPLE SAMPLING TYPE OF DETECTABLE
. SAMPLE POINT TYPE FREQUENCY ACTIVITY ANALYSIS CONCENTRATION (1)(a)
Reactor Building Purge Releases Gas P' H-3 1E-6 pCl/cc Each Purge IndMdual . 1 Gamma Emitters IE-4 pCi/cc (2) j q Unit Exhaust Vent Release Points Gas M H-3 , 1E-6 pCi/cc Monthly individual i l Gamma Em!tters 1E-4 pCi/cc (2) W Individual (b) Particutates Weekly Gamma Emitters 1E-10 pCl/cc (2) M , j Monthly Sr-90 1E-11 pCl/cc l Composite - ;
,n ,
I \ M Gross Alpha Q MontNy Emitters 1E-11 pCi/cc Composite Reactor Building Breather Particulates SA Indv.' Gamma 1E-10 Ci/cc (2) Semi-Annua!!y Emitters (b) j i Sr-90 1E-it pCi/cc Gross Alpha 1E-11 pCl/cc Emitters' t (1) The above detectability limits are based on technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable
, and when nuclides are measured below the stated limits, they should also be reported. .
l . .(2) For certain mixtures of gamma emitters, it may be possible 1,o measure radionuclides at levels near their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these l circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios
. in the gaseous component in the reactor coolant for those radionuclides which are measurable.
(3) . Deviations from the sampling and analysis regime ~will be noted in the report spccified in ODCM Part l'V. 4 83.0 mu, s
04-23-97 09: 13;44 , Number m aadid gi ai contres (
^ (UClear Departmental Procedure. 6610-PLN-4200.01 \ Revision No.
Title Offsite Dose Calculation Manual (ODCM) 12 1 TABLE 3.2-2 (Cont'd) Radioactive Gaseous Waste Sampilng and Analysis Program
, Table Notation
- a. The LLD is the smallest concentration of radioactive material in a sample that will 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 radiochemical separation): 4.66 S3 E V 2.22 Y
- exp (-Aat)
Where 1.1D is the lower limit of detection as defined above (as picocurie per unit mass or volume). O S is the standard deviatio'n of the background counting rate or'of the counting rate of a blank b sarnple 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 plcocurie, !
)
Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and At is,the elapsed time between midpoint of sample collection and time of counting (for plant , effluents, not environmental samples), . The value of Sbused in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of,the blank samples (as appropriate) rather than on an unverified theoreticar.y predicted variance. In calculating
' the LLD for a radionuclide determined by gamma-ray spectrom atry, the background shall include the typical contributions of other radionuclides normally present in .he samples'. Typical values of E V, Y, and at shall be used in the calculation. The background co Jnt rate is calculated from the background counts that are determined to be with e one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma-ray peak used for the quantitative analysis for that '
radionuclide. i 84.0 nm.
1 l 4 04-23-97 09:13:44 Number ! TMI Radiological Controls i
, .4MClear Departmentai Procedure 6610-PLN-4200.01
\ Reymon No.
- g, J
Offsite Dose Calculation Manual (ODCM). ' 12
. TABLE 3.2-2 (Cont'd)
- b. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn45, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate
' emissions. This list does not mean that only these nuclides are to.be detected and reported. Other peaks which are measurable and identifiabfe, together with the above nuclides, shall also be identffied and
- reported. Nuclides which are below the LLD for the analyses shall be , reported as "less than* the nuclide's .
- LLD and shall not be reported as being present at the LLD levet for that nuclide. The *less than". values shall not be used in the required dose calculations. i l 1 i i a I 5 O 1 t l, N 3 3 d D
/
04-23-97 09:1,3:44 Number (UClear ' TMI Radiological Controls
. Departmental Procedure 6610-PLN-4200.01 O . Title Revision No.
Offsite Dose Calculation Manual (ODCM) 12 3.2.3 Total Radioactive Eftluents 3.2.31 Dose Calculation
~
3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside stora'ge tanks. and in accordance with the methodology contained in the ODCM. 6
- I i
/
i 1 l h 1 O~ I
. 86.0 airw 4
04-23-97'09:13:44
. . Number t
n ggggggy W( Radidogd Contrds Departmental Procedurb 6610-PLN-4200.01 Title Revision No. j l Offsite Dose Calculation Manual (ODCM) 12 - I I ' SECTION 4.0 t
- Des,ign Features .
} 4.0 DESIGN FEATURES - , 4 i 4.1 SITE 4 EXCLUSION AREA The exclusion ared is shown in Figure 51, TMI 1 Tech. Specs. 4.1.1 1, LOW POPULATION ZONE
- 1 4.1.2 The low population zone is shown in Figure 5-2, TMI-1 Tech. Specs. j l SITE BOUNDARY FOR GASEOUS EFFLUENTS ,
4.1.3 The site boundary for gaseous effluents shall be as defined in Section i1.2.2 of the TMI-1 FSAR and i < as shown in Figure 2.1-3, TMi-1 FSAR. . (e ' i i SITE BOUNDARY FOR LIQUID EFFLUENTS i ' The site ' boundary for liquid effluents shall be as shown in Figure 54, TMI-1 Tech. Specs. l 4.1.4 0 1 t h i r l I 87.0 mm. t
0.4-23-97 09:13:44 , Number T -$UClear M Radiolodcal Contrds Departmental Procedur6
.6610-PLN-4200.01 Title hsion No.
Offsite Dose Calculation Manual (ODCM) 12. 5.0 PART 11 REFERENCES 5.1 NUREG4683, " Final Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28,1979, accident Three Mlle Island Nuclear Station, Unit 2," March 1981, and its supplements. 5.2 - TMI-2 PDMS Technical Specifications, attached to Facility License No. DPR-73' 5.3 ' Title 10, Code of Federal Regulations, " Energy" l ) . .. l 4 5.4 " Statement of Policy Relative to the NRC Programmatic Environmental Impact Statement on the Cleanup of Three Mile Island Unit 2," dated April 27,1981 5.5 Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routin'e Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 5.6 DOE /DC-27601, Atmospheric Science and Power Reduction 5.7 TMI-1 Technical Specifications, attached to Facility Operating Ucense No. DPR-50 5.8 PDMS - SAR t i l t 9 - 88.0 sou
04-23-97 09:13:44 Number
- /7 MUClear .
Tui Radioiogical Controis Departmental Procedure 6610-PLN-4200.01 Title Revision No. I Offsite Dose Calculation Manual (ODCM) 12 4 Table 2.1-2 (Cont'd)
~
Table Notation At all times. -
** s During waste gas holdup system operation. '
Operability is not required when discharges are positively controlled through the closure of ' , WDG-V47 and where RM-A8 (or RM-A4 and RM-A6), FT-149, and FT-150 are operable. During Fuel Handling Building ESF Air Tre,atment System Operation. l
.# At all times during containment purging.
## At all times when condenser vacuum is established.
### ' During operation of the ventilation system.
l ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank rnay be released to the environment ! provided that prior to initiating the release:
- 1. At least two independent samples of the tank's contents are analyzed in accordance . -
with Table 3.2-2. Item A, and
.[ j 2. At least two technically qualified members of the Unit staff independently verify the Q release rate calcu!ations and verify the discharge valve lineup.
- 3. The Director Operations & Maintenance TMl, shall approve each release.
Otherwise, suspend release of radioactive effluent via this pathway. ACTION 26 With the number of channels OPERABLE less thari required by the Minimum Channels OPERABE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. ' ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab . samples are taken at least once per 12 hours and the initial samples are analyzed for gross activity (gamma scan) within 24 hours after the channel has been declared inoperable. If RM-A9 is declared inoperable, see also Technical Specification 3.5.1, Table 3-5.1, item C;3.f. ACTION 30 1. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, a grab sample shall be collected and analyzed for the inoperable' gas channel (s) at least once per 24 hours. With ~both channels
, Inoperable, a grab sample shall be collected and analyzed for the inoperable gas
. channel (s):
(a) at least once per 4 hours during degassing operations. (b) at least once per 24 hours duririg other operations (e.g. Feed and Bleed).
~
\
v 28.0 nm. I
04-23-97 09:13: 44 Number w Radi I gi i Contmis (/7) $UCl68F Departmental Procedura 6610-PLN-4200.01 V' Titl* Revision No. ' Offsite Dose' Calculatiori Manual (ODCM) 12 Table it.12 (Cont'd) If the inoperable gas channel (s) is not restored to service within 14 days, a special
- 2. '
report shall be submitted to the Regional Administrator of the NRC Region 1 Office and a copy to the Director, Office of Inspection and Enforcement within 30 days of 4 declaririg the channel (s) . inoperable. The report shall describe (a) the cause.of the . monitor inoperabff tty, (b) action being taken to restore the instrument to service, and (c) action to be taken to prevent recurrence. . ACTION 31 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that within four hours after the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment. ACTION 32 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days, provided that one OPERABLE channel remains in service or is placed in service within 1 hour. After 28 days, or if one OPERABLE channel I does not remain in service or is not placed in service within 1 hour, the provisions of Technical Specification 3.0.1 apply, as if this Control were a. Tech C t
, Spec Limiting Condition for Operation.
ACTION 33 With the number of channels OPERABLE less than required by the Minimum
. Channels OPERABLE requirement, either restore the Inoperable channel to OPERABLE status within 7 days, or prepare and submit a special report within 30 )
days outlining the action (s) taken, the cause of the inoperability, and plans and schedule for restoring the system to OPERABLE status. . O V 29.0 n n.
04-23-97 09:13:44
,. i Number pI - gggp TMI Radiological Controls.
Departmental Procedurg i 6610-PLN-4200.01 V TNe Revision No. Offsite Dose Calculation Manual (ODCM) 12 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.1.1 Uquid Effluent Concentration CONTROL- i i The concentration of' radioactive material released at anytime fro' m the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part. 20.1001-20.2401,' Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble limited to 3 x 10~ gases.
. uCi/cc totalFor dissolved or entrained noble gases,'the concentration shall be activity.
APPLICABILITY: At all times ACTION: With the concentration of radi'oactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within the above limits. A (v) BASES This control is provided to ensure that the concentration of radioactive materials rAleased in. . liqu;d waste ef'luent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B. Table 2. This limitation provides additionaf assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures with (1) the Section ILA design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of,10 CFR Part 20.1301 to the population. The concentration limit for noble gases is based upon the a,ssumption the Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. 2.2.1.2 'Uquid Effluent Dose 4 CONTROL The dose or dose commitment to a MEMBER OF THE PUBUC from radioactive materials in liquid effluents released from the unit to the SITE BOUNDARY shall be limited:
- a. 'During any c la endar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
O)' k v APPLICABILITY: At all times 30.0 nm. ee<=
04-23-97 09:13:44 Number O. (ggClggr' TMI Radiological Controls (v) Title Departmental Procedure 6610-PLN-4200.01 navision No. Offsite Dose Calculation Manual (ODCM) 12 ACTI,0N: I
- a. With the calculated doce from the release of radioactive materials in !! quid effluents exceeding any of the above limits, prepare and. submit to the NRC Region 1 Administratot within 30 tiays, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the
, releases of radficactive materials iritiquid effluents during the t.emainder of the current calendar quarter and during the subsequent 3. calendar qua:ters so that the cumulative dose or dose commitment to any individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also inclyde (1) the result of radiological analyses of the drinking water source, and (2) the radiologierJ impact on finished drinking water supplies wi*h' regard to the requirements of 40 CFR 141, Safe Drinking Water Act. , , BASES , This control and associated action is provided to implement the requirements of Sections
!!.A, ll!.A. and IV.A of Appendix 1,10 CFR Part 50. The Control implements the guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating y flexibility and at the sa'me time implement the guides set forth in Section N.A of Appendix I (j
to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water s,upplies which can be potentially effected by plant operations.,there is reasonable assurance that the operation of the facility will not result in radionuc!ide concentrations in the finished drinking water that are
~
in excess'of the requirements of 10 CFR 20. The dose calculations in the ODCM implement The requirements in Section !!!.A. of Appendix ! that conformance with the guides of Appendbc I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBUC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the
~
doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Eva!'uatir.g Comp!iance with 10 CFR Part 50, Appendix 1," Revision 1, October,1977, and Regulatory - Guide 1:113,
- Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpo'se of Impfementing Appendix I," April,1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.
2.2.1.3 Uquid Radwaste Treatment System 4 cot #ROL:- . The appropriate portions of th's liquid' radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to thefr discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would. exceed 0.06 mrem to the total body or 0.2 mrem to any orgari in any calendar ! j'} , I () APPUCABILITY: At all times 31.0 n m,
04-23-97 09:13:44 Number
^
(UClear Tul Radiologicai Controis Departmental Procedur6 6610-PLN-4200.01 T$e Revision No. Offsite Dose Calculation Manual (ODCM) 12 ACTION:
- a. With radioactive' ilquid waste being discharged without treatmerb and in excess of the above limits, prepare and submit to the NRC Region i Administrator within 30 days, a Special Report which includes the following information:
- 1. Explanation of why liquid radwaste was being ^ discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperab!!ity,
- 2. Action (s) taken to restore the inopera'ble equipment to OPERABLE status, and,
- 3. A summary description of action (s) taken to prevent a recurrence.
. BASES The requirement that the appropriate portions of this system be u' sed, when specified, provides assurance that the relear.,s of radioactive materials in liquid
[O tj effluents will be kept as low as is reasonabl1 acnievable. This control implements the requirements of 10 CFR Part 50.36a, General Design'Cnterion 60 of Appendix A
, to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix i to 10 CFR Part 50. The intent of Section !!.D. is to reduce effluents to as low as is I reasonably achievable in a cost effective manner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section li.A of Appendix 1,10 CFR Part 50 dose requirements.' This margin, a factor of 4, constitutes a reasonable reduction.
I 2.2.1.4' Liquid Holdup Tanks CONTROL The quantity of radioactive material contained in each of the following tanks shall'be limited to less than or equal to 10 curies, excluding tritium and dissowed or. entralned noble gases. I
- a. Outside temporary tank ,
APPLICABILITY: At all times. , ACTION:
- a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce ... tank' contents to within the limit. '
b , 32.0 mi. e
l 04-23-97 09:13-:44 l Number Nuclear " "^d'doo'ca' co"t">'$ Departmental Procedure 6610-PLN-4200.01 ('N} b Title Revision No. Offsite Dose Calculation Manual (ODCM) 12 BASES Restricting the quantity of radioactive material contained in the specified tanks provides assurance that la the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less'than the limits of 10 CFR Part 20.1001-20-20.2401, Appendix B, Table 2, Column 2, at the nearest potable water i supply and the nearest surface water supply in an unrestricted area. ' 2.2.2 Gaseous Effluent C,ontrols - l 2.2.2.1 Gaseous Effluent D.ose Rate . CONTROL: The dose rate'due to radioactive materials' released in gaseous effluent from the site shall be limited to the following:
- a. For noble gases: less than or equal to 500 mrem /yr to the total body and less than )
. or equal to 3000 mrem /yr to the skin, and fg b. For I-131i1-133, tritium and all radionuclides in particulate form.with ha!f lives yV) greater than 8 days:. ,less than or equal to 1500 mrem /yr to any organ.
. dPPUCABILITY: At all times.
. ACTION:
With the release rate (s) exceeding the above limits, immediately decrease the release rate to comply with the above limit (s). , BASES , s , The control provides reasonable assurance that the annual dose at the SITE BOUNDARY from gaseous effluent frorn all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas while providing sufficient operational flexibility in ' establishing effluent monitor setpoints. These gaseous release rates provide reasonable assurance that radioactive material discharged in gaseous effluent will not result in the exposure of a MEMBER OF THE PUBUC in an unrestrictad area, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the values specified in Appendix B, Table 2 of 10 CFR Part 20. - For MEMBERS OF THE PUBUC who may at times be within the SITE BOUNDARY, the occupa'ncy of the MEMBER OF THE PUBUC will be . sufficiently low to compensate for any increase in the atmospheric diffusion factor above. that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBUC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year.to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child [, via the inhalation pathway to less than or equal to 1500 mrem / year (NUREG 0133). C 33.0 mu
04-23-97 09:13:44 Number (-] __gggy TMI Radiological Controls Departmental Procedura 6610-PLN-4200.01 (v) Title Revision No. Offsite Dose Calculation Manual (ODCM)' 12 l 2.2.2.2 Gaseous Effluents Dose-Noble Gdses , i CONTROL: The air dose due to noble gases released in gaseous effluents'from the unit to areas at and
- beyond the SITE BOUNDARY shall be limited to the following
- a. During any calendar quarter:. less than or equal to 5 mrdd for gamma radiation and less than or equal to 10 mrad for beta radiation and,
- b. During any calendar year. . less than or equal to 10 mrad for gamma radiation and -
less than or equal to 20 mrad.for beta radiation. APPLICABILITY: At a!! times. ACTION:
- a. With the calculated alt dose from radioactive noble gases in gaseous effluents' exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for -
[, exceeding the. limit (s) and' defines the corrective actions that have been taken to I,' j} reduc'e the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. BASES This control applies to the release of radioactive materials in gaseous effluents from TMI 1. This control and a'ssociated action is provided to implement the requirements of Sectio'n 11.B, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Control implements the guides set forth in Section ll.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix ! to assure that the releases of radioactive material in gaseous effluents wl!! be kept "as low as is reasonably achievable.' The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix l be shown by calculatior.al procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate patheys is unlikely to be substantially. underestimated.. The dose calculation , methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the 3 Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1,* Revision 1, October 1977 and Regulatory Guide 1.111,
- Methods for Estimating Atmospheric Transport and-Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,* !
I Revision 1, July 1977. The ODCM equations provided for determining the air dos'es at and j beyond the SITE BOUNDARY.are based upon the historical average atmospheric conditions. t n NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides j 1.109 and 1.111. v 1 l 34.0 sm.
04-23-97 09: 13:44 Number ggggggy N M Radiological Controls
)
g' Departmental Procedure 6610-PLN,4200.01 Title . Hovssion No. Offsite Dose Calculation Manual (ODCM) 12 2.2.2.3 Dose -lodine-131clodine-133, Tritium, and Radionucildes in Particulate Form CONTROL: The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-133, Tritium, and all r'adionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released frorrt the unit to areas at and beyond the SITE BOUNDARY shall be limited.to the following:
- a. During any calendar quarter: less than 'or equal to 7.5 mrem to any o.rgan, and
- b. During any calendar year: less than or equal to 15 mrem to any organ.
APPLICABILITY: At all times. ACTION: , With the calculated d'ose from the release of lodine-131, lodine-133, Tritium, and ' radionuclides in particulate form with half fives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator O within 30 days, a Special Report which identifies the cause(s) for exceeding the limit'and + define'sthe corrective actions that have been taken to reduce the releases and the proposed-corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. ' BASES ' This control applies to the release of radioactive materials in gaseous effluents from TMI-1. This control and associated actbn is provided to implem'ent the requirements of Section ll.C, I!!.A and IV.A of Appendix 1,10 CFR Part 50. The Controls are the guides set forth in Section 11.C of Appendix 1. The ACTION statement provide's the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix 1 to assure
.that the releases of radioactive materials in gaseous effluents will be kept *as low as ~is reasonably achievable." The ODCM calculational methods 'specified in the survel!!ance requirements implement the requirements in Section Ill.A of Appendix 1 that conformance with the. guides of Appendix ! be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational ~
methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide <1.109 T,alculation of 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,
'1977 and Regulatory Guide 1.111," Method for Estimating Atmospheric Transport and f
Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July,1977. These equations also provide for determining the actual doses based
-upon the historical average atmospheric conditions. The release rate controls for lodine-131,
[j
\g iodine-133, trttlum and radionuclides in particulate form with ha!f lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the Sr!E BOUNDARY. The pathways that were examined in the development of these 35.0 mu
1 04-23-97 09:13:44
, , , Number O'
y Nuclear. TM' aadio'oo'ca' contro'= Departmental Procedure 6610-PLN-4200.01 Thie hsion No. Offsite Dose Calculation Idanual (ODCM) .12 calculations were: 1) individual inhalation of airbome radionuclides,'2) deposition.of radionuclides onto green leafy vegetation with subsequent consumption by man,3) depositloo onto grassy areas where milk animals and meat producing animals graze wt'h consumption of the' milk and meat by roan, and 4) deposition on the ground with
~
subsequent exposure of man. , l 2.2.2.4 . Gaseous Radwaste Treatment System I l CONTROL ' l The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTil.ATION EXHAUST TREATMENT SYSTEM sha!! be OPERABLE. ,The appropriate portions of the GASEOUS RAD, WASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in the gaseous waste prior to their discharge when the monthly projected gaseous effluent air I doses due to untreated gaseous effluent releases from the unit would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate. portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected doses due l to gaseous effluent releases from the site would exceed 0.3 mrem to any organ. l
.O APPLICA'BluTY: At'all times.
ACTION:
- a. With the GASEOUS R ' ADWASTE TREATMENT SYSTEM 'and/o'r the VENTILATION l EXHAUST TREATMENT SYSTEM inoperable for 'more than a month or with gaseous ,
waste being discharged without treatment and in excess of the above limits, prepare l and submit to the NRC~ Region 1 Administrator within 30 days, a Special Report whicn includes the following information:
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE r'tatus,.
and.
- 3. 'A summary description of action (s) taken to prevent a recurrence.
BASES' The use of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate pilor to release to the environment. The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable " This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the m design objectives given in Section !!.D of Appendix I to 10 CFR Part 50. The specified limits j governing the use of appropriate portions of the systems were specified as a suitable [Q fraction of the guide set forth in Sections ll.B and ll.C of Appendix 1,10 CFR Part 50, for gaseous effluents. 36.0 v n.
04-23-97 09:13:44
- 1 Number - I A j $UClear Tui Radioiogical controis Departmental Procedure 6610-PLN-4200.01 b Title j Revision No.
Offsite Dose Calculation Manual (ODCM) 12 l 2.2.2.5 Explosive Gas Mixture CONTROL 1 The concentration of oxygen in the Waste Gas Hoidup System shall be limited to less than , 1 or equal to 2% by volume whenever the concen*sation of hydrogen in the Waste Gas Holdup - System is greater than or equal to 4% by volume. AVAILAB1UTY: At a!! times. ACTION: Whenever the concentration of hydrogen in the Wai;te Gas Holdup System is greater than or equal to 4% by volume, and: 1
- a. The concentration of' oxygen in the Waste Gas Holdup System is greater than 2%
s by volume, but less than 4% by volume, without delay begin to reduce the oxygen concentration to within its limit. '
. b. The concentration of oxygen in the Waste Gas Ho! dup System is greater than or
/ equal to 2% by volume, immediately suspend additions of waste gas to the Waste
\' Gas Holdup System and without delay begin to reduce the oxygen concentration to
. within its limit.
BASES:' Based on experimental data (Reference 1), lower limits of flammability for hydrogen is 5% and for oxyge'n is 5% by volume. Therefore, if the concentration of either gas is kept below it lower limit, the other gas may be present in higher amounts without the danger of an explosive mixture. Maintaining the concentrations of hydrogen and oxygen such that an explosive mixture does not occur in the waste gas holdup system provides assurance that the release of radioactive materials wi!I he control 19 d in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR 50. REFERENCES (1) Bulletin 503, Bureau of Mines; Limits of Flammability of Gasas and Vapors. 2.2.2.6 Waste Gas Decay Tanks CONTROL-The quantity of radioactMty contained in each waste gas decay tank shad be limited to less than or equal to 8800 curies noble gases (considered as Xe 133). i APPUCABlu'iY: At all times. fv . 37.0 nm.
04-23-97 09':13:44 Number o) Nuclear *'. Radiological Controls Departmental Procedur5 6610-PLN-4200.01 i l I** Hevision No. Offsite Dose Calculation Manual (ODCM) 12 ACTION: -
' a. 'With the quantity of radioactive material in any waste gas decay tank exceeding the ' l above limit, immediately suspend all additions of radioactive material.to the tank and within 48 hours reduce the tank contents to within the limit.
BASES - Restricting the quantity of radioactivty contained in each waste gas decay tank provides l assurance that in the event of an uncontrolled release of the tanks contents, the resulting l i
, total body exposure to a MEMBER OF THE PUBUC at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure." ,
2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose CONTROL: O The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBUC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be l limited to less than or equal 10 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem. APPUCABluTY: At all times. ACTION: With the calculated dose from the release of radioactive rnaterials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a. 2.2.1.2.b, 2.2.2.2.a, 2.2.2.2.b, 2.2.2.3.a. or,2.2.2.3.b, calculations should be made including direct radiation contnbutions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1,have been exceeded. If such is the case, prepare and submit to the NRC Region 1 Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releassa to prevent recurrence of exceeding the above limits and ' includes the schedJte for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b), shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBUC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year tnat
- includes the release (s) covered by this report. It shati also describe levels of radiation and .
concentrations of radioactive materialinvolved, and the cause of the exposure' levels or concentrations. If the estimated d.ose(s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a. request for a variahce in accordance with the provisions of 40 CFR ' 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. 38.0 m I
04-23-97 09:13:44 -
' Number (m
1
.j g g y' TMI Radiological Controls Departmental Procedure J 6610-PI N4200.01 Y Title newsion No.
Offsite Dose Calculation Manual (ODCM) 12 BASES
, This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d). This control 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 th'an or equal'to 75 rnrem. For sites containing up to 4 reactors, it is highly unilkely that the resulta'n t dose to a MEMBER OF THE PUBUC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice .the dose design objectives of Appendix 1, and if direct radiation doses from the teactor un!!s and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF y THE PUBUC to within 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 from other uranium fuel cycle so6rces is negligible, with the exception that dose contributions from other nuclear
' fuel cycle facilities at the same site or within a radius of 8 km must be considered. if the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release condttions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a
[\ y timely request and fulfills the requirements' of 40 CFR Part 190 until NRC staff action is , completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limttation of 10 CFR Part 2,0, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individual is not considered a MEMBER OF THE PUBUC during ariy period in which he/she is engaged in carrying out any operation that is part of
'the nuclear fuel cycle. '
3.0 SURVEILLANCES 3.1 Radioactive Effluent instrumentation 3.1.1 Radioactive Uquid Effluent Instrumentation Surveillance Requirements 3.1.1.1 Each radioactive liquid effluent monitoring instrumentation channel shall be ' demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAUBRATION, AND CHANNEL TEST operations during the MODES and at the frequer. cms shown in Table 3.1_.1. J G 39.0. am.
o 4
'9
~
Table . -/ 6610-PLN-420s.'. W Revision 12
- o RadNxtetive Uquid Effluent Monitoring Instrumentation Surveillance Requirements . $
H w INSTRUMENT CHANNEL SOURCE CHANNEL CHANNEL 1 CHECK CHECK CAUBRATION TEST A
- 1. RadioactMty Monitors Providing Alarm and Automatic -
Isolation ,
- a. Unit 1 Uguld Radwaste Effluents Une (RM-L-6) . D- _P R(2) O(1) b.- IWTS/lWFS Discharge une (RM-L-12) D 'P R(2) ~ O(1)
~
- 2. Flow Rate Monitors
- a. Unit 1 Uquid Radwaste Effluent une (FT-84) D(3) N/A ' R O
- b. Station Effluent Discharge (FT-146) D(3) N/A R O P
e M i . s g a 40.0 mw
1 04-23-97 09:13:44 > Number D) ( Trtle Nuclear-
" " di*ow co"tr*
Departmental Procedure 6610-PLN-4200.01 - nevnon No. Offsite Dose Calculation Manual (ODCM) 12
, Table 3.1-1 (Cont'd)
Table Notation (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the following condition exists: .
- 1. Instrument indicates measured levels above the high alarm / trip setpoint. *(Includes circuit failure)-
- 2. Instrument indicates a down scale failure. (Alarm function dnly.) (includes circuit failure)
- 3. Instrument controls moved from the operate mode (Alarm function only).
l (2) The inirla! CHANNEL CALIBRATION for radioactivity measurement instrumentation sha!! be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participated in measurement assurance activities with NES. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAUBRATION. sources that have been related to the initial calibration should be used. (Operating plants m'ay substitute previously established calibration procedures for this requirement) ( (3) CHANNEL CHECK shall consist of verifying indication of flow during periods of reicase. CHANNEL CHECK (j
, shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.
. ~
d 4 9 ' i l I i d 41.0 ame
- _ __. - = ._
' 04-23-97 09:i3:44 t i , , Number i
$UClear. TM1 Radiological Controls Departmental Procedurs 6610-PLN-4200.01 I Title Revision No.
Offsite Dose Calculation Manual (ODCM) 12 i , 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation ' j . . SURVEILLANCE REQUIREMENTS 3.1.2.1 Each radioactive gaseous process or effluent monitoring instru. mentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAUBRATI.ON,'and CHANNEL TEST operations at the frequencies shown in , Table 3.1-2. j 4 e 8 9 i f 9 0 9 e e f B 42.0 rm. J _
9 w E
\ ) \ W
) \ -
~ l a V Table d 6610 .PLN-420s.. . $
. Revision 12 Radioactive G ' aseous Process and E!!tuent Monitoring Instrumentation Surveillance. Requirements CHANNEL SOURCE CHANNEL CHANNEL A INSTRUMENT CHECK CHECK CAllBRATION TEST APPUCABILITY
~
- 1. Waste Gas Holdup System .
I .
- a. Noble Gas ActMty Monitor.(RM-A7) . P. P ***
, , E(3) Q(1)
- b. Effluent System Flow Rate Measuring Device (FT-123) P, N/A ,
;E Q ***
- 2. Waste Gas Holdup System Expicsive Gas Monitoring System
- a. Hydrogen Monitor D N/A Q(4) M **
~
- b. Oxygen Monitor D N/A Q(5) M **
- 3. Containment Purge Vent System -
- a. Noble 'Ga's Activity Monitor (RM-AD) D P E(3) M(1) ' #
- b. lodine Sampler (RM-A9). . W. N/A N/A N/A #
- c. Particulate Sampfer (RM-A9), W N/A N/A N/A # ,
- d. $ffluent System Flow Rate Measuring Device (FR-148) D~ N/A E O #
- e. Sampler Flow Rate klonitor -D .N/A E- N/A . #
- 4. Condenser Vent System L
- a. Noble Gas ActMty Monitor (RM-A5 and Sultable D M E(3) O(2) ##
Equivalent - See Table 2.1-2, item 4.a) J 43.0 - am. 4
eb. e '
-o)
Table 3.1-2 wont'd o4 6610-PLN-4206.2. Revision 12 o W Radioactive Gaseous Process and Effluent Monitoring Instrumentation Survei!!ance Requirements tu . CHANNEL SOURCE CHANNEL CHANNEL g INSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABlUTY
~
- 5. Auxiliary and Fuel Handling Budding VentDation S'ystem .
- a. Noble Gas ActMty Monitor (RM-A8) cr (RM-A4 and ~ ~D M E(3) .Q(1)
RM-A6)
- b. lodine Sampler (RM-A8) or (RM-A4 and RM-A6) . W N/A' N/A N/A
- c. PartictAate Sampler (RM-AB) or (RM-A4 and Rh8-?9) W' N/A 'N/A N/A
- d. System Effluent Flow Rate Measurement Devk M D N/A E Q (FR-149 and FR-150)
- e. Sampler Flow Rate Monitor D N/A_ E- N/A
- 6. ' Fuel Hand!!ng Buliding ESF Air Treatment System
- a. Noble Gas Activity Monitor (RM-A14) D. M' R(3) Q(2)
- b. System Effluent Flow Rate (UR-1104 A/B) 'D N/A R- Q i
c' Sampler Flow Rate Measurement Device D N/A R Q 44.0 ww
S . t fs u fm) y (.m s Table 3.1 beut'd) 6610-PLN-420d.tr' ( )
- Revision 12 '
~
Radioactive Gaseous Process and Emuent Monitoring Instrumentation Surveilance Requirements o F8 y CHANNEL SOURCE CHANNEL- , CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST APPUCABILIIY A s
- 7. Chemical Cleaning Building Ventilation System ,
- a. ~ Noble Gas-ActMty Monitor (ALC RM-l-18) D. M E(3) O(2) ###
- b. lodine Sampler (ALC RM-t-18) W. N/A N/A N/A ###
- c. Particulate Sampfer (ALC RM-I-18)' W N/A N/A N/A ###
- 8. Waste Handling and Packaging Facility Ventilation System _
- a. Particulate Sampler (WHP-RIT-1) D- W SA ,W. ###
~
- 9. Respirator and Laundry Maintenance Ventilation System
- a. Particulate Sampler'(RLM-RM-1) D W SA W ###
9 a
=
9 45.0 un,
04-23-97 09:13:44 Number l O) t (UClear g M Radiological Controls' Dopartmental Procedurs 6610-PLN-4200.01 O Title Revision No. Offsite Dose Calculation Manu'ai (ODCM) 12 Table 3.1-2 (Cont'd) Table Notation
* ~ At all times. .
During waste gas holdup system operation. , Operability is not required when discharges are positively controlled through the closure of WDG.V47., and where RM-A8 (or RM-A4 and RM-AS), FT-149, and FT-150 are operable. During Fuel Handling Building ESF Air Treatment System Operation.
# At all timos during containment purging. '
## At all times when condenser vacuum is established.
### During operation of the ventilatfori system.
I (1) The CHANNEL TEST shall also demon' strate that automatic isolation of this pathway for the Auxiliary and Fuel Handfing Building Ventilation. System, the supply ventilation is isolated and control room alarm annuncisition occurs if the following condition exists: s
- 1. Instrument indicates measured levels above the high alarm / trip setpoint (includes circuit failum).
ON j 2. Instrument indicates a down scale failure (Alarm function only) (Includes circuit failure).
~
- 3. lnstrument controls moved from the operate mode (Alarm function only).
(2) The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the fo!!oding conditions exist:
. 1. Instrument indicates measured levels a'bove the alarm setpoint. (includes circuit failure)
~
- 2. Instrument indicates a down scale failure (includes circuit failure).
- 3. Instrument controls moved from the operate mode.
- l (3) The initial CHANNEL CAUBRATION for radioactivity measurement instrumentation shall be i performed using one or more of the reference standards certified by the National Bureau of Standards or using star dards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards should permit calibrating the system over its ' intended range of energy and measurement range. For subsequent CHANNEL i
, CAUBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substitute previously established calibration procedures for this requirement.)
(4) The CHANNEL CAUBRATION shall include the use of standard gas samples containing a nominal: 1: One volume percent hydrogen, balance nitrogen, and
- 2. Four' volume percent hydrogen, balance nitrogen.
46.0 u n.
j 04-23-9'7 09:13:44-l . Number (RIClear : TMl Radiological Controls Departmental Proceduri 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 12 i - Table 3.1-2 (Cont'd) ! (5)- The CHANNEL CAUBRATION shallinclude the use of standard gas samples containing a nominal: i - l 1. One volume percent oxygen,. balance nitrogen, and 1 -
, 2. Four volume percent oxygen, balance nitrogen;. ,
1 4 6
+
M ) i 1 6 3 e i i 1 f 1 t i 1 r 1 s J j 8 e 2 l 47.0 ~ im.
- l U
04-33-97 09:13:44-Numbu
' "ad'o'**' co"tr* ~
Nuclear- Departmental Procedure 6610-PLN-4200.01 TitI* , Revision No. Offsite Dose Calculation Manual (ODCM) 14 ' 3.2 Radioactive Effluents 3.2.1 Uguld Effluents , SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration 3.2.1.1:1 The radioactivity content of each batch of radioactive liquid waste
' shall be determined prior to release by sampling and analysis in accordance,with Table 3.2-1; The results of pre-release analyses shall '
be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1. 3.2.1.1.2 Post-release analysis of samples composited from batch releases shall
. be performed in accordance with Table 3.2-1. The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2.1.1, 3.2.1.1.3 The radioactivity concentration of liquids discharge' d from continuous release points shall be determined by collection and analysis of samples in accordance with Table 3.2-1. The results of the analysis shall be used with the ceJculational methods o; the ODCM to assure that the concentration tat the point of release 11. maintained within the limits of Control 2.2.1.1.
3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month. 3.2.1.3 Liquid Waste Treatment 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month. ! In accordance with the ODCM. t 48.0 rm.
} ,
1 < l l
04-23-97 09:13:44 Number gggggy TMl Radiological Controls Depanmental Proceduft 6610-PLN-4200.01
, Te sem;on No.
}
~
O# site Dose Ca'lculation Manual (ODCM) 12 3.2.1.4 Liquid Holdup Tanks 3.2.1.4.1 The quantity of radioactive material contained in each of the tanks specified in Control 2.2.1.4 shall be determined to be wkhin the limit by analyzing a representative sample of the tank's content weekly when radioactive materials are being added to_the tank.
~
4 e E G
~'
t I ,
~
d t S e 49.0 ,,,,,
= ___.i.-.
o b
' Table 3.2-1 6610-PLN-4200.01 Revision 14 i
- W 4
Radioactive Liquid Waste Sampling and Analysis Program , l Lower Limit of 'h
!. Sampling Minimum Analysis' l Type of ActMty Detection (LLD)
Uquid Release Type Frequency Frequency l Analysis (pCi/ml) (Note a) $ A.1 Batch Waste Release Tanks (Note d) i P i . P l H-3 l. 1 x 104
.j Each Batch Each Batch ! Principal Gamma ! 5 x 10-7 l
l i Emitters (Note f) . I l-131 1 x 10-8 I 4
! Dissolved ad 1 x 10 l l Entrained g (Gamma G ses i.
g ' l e
; Emitters) t ll
.P Q -l Gross alpha. 1 x 10-7 Each Batch Composite (Note b) ! ,
l Sr-89, Sr 5 x 104
. -1 Fe-55 1 x 104-l -
l - I 1 W' b s em a 4 50.0 ' mu e _ . _ _ _ _ _____ _ _ . _ _ _ _ _ . . _ _ _ _ _ _ _ _ . m____________m.__ _ _ - _ _ . _ _ _ ._ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ --____-______m_ ___-_-_m - - - _ _ _ _ _ _ _- _-_.m_
o k I Table 3.2-1 (Cont'd) ~ 6610-PLN-4200.01 U Revision 14 4 4 Radioactive Uquid Waste Sampling and Analysis Program o m
! I .
. l '
Lower Umit of . U Sampling l Minimum Analysis i Type of ActMty . Detection (LLD) ; Liquid Release Type Frequency ; Frequency Analysis (pCl/ml) (Note a) A A.2 Continuous Releases (Note e) l Continuous. l W I Principal Gamma , 5 x 10-7 I (Note c) i Composite Emitters (Note f) l I l l (Note c) ', I l l-131 1 x-104
- 8 1 x 104 Dissolved and l i Entrained Gases -
l l (Gamma Emitters) Continuous M l. H-3 , 1 x 104
' ' (Note c) i Composite l l
(Note c) Gross alpha I 1 x 10 l
. i j , Continuous Q Sr-89, Sr-90 5 x 10-8 l (Note c) Composite (Note c) l Fe-55 1 x 104 l l
~! ! ! !
e e I s W 51.0 ma
04-23-97 09:13:44- ) Nurnber CT ggggggy M Raddogical Controls Departmental ProceduFe 6610-PLN-4200.01 l (") Title Hevision No. Offsite Dose Calculation Manual (ODbM) 12 I Table 3.2-1 (Cont'd) l Table Notation I l
- a. The LLD is defined, for purposes of this' surveillance, as the smallest concentration of radioactive l material in a sample that will yield a net ' count above system background that will be detected with 1 95% probability with 5% probability.cf falsely concluding that a blank observation represents a 'real*
signal. . . For a particular measurement system (which may include radiochemical separation): l l l LLD = 4.66 ss E x V x 2.22 x 106 x Y x exp (-A At)
]
Where: j LLD is the "a prior!" lower limit of detection as defined above (as microcurie per unit mass or
~
volume), g sb is the standard deviation of the ba'ckground counting rate or'of the counting rate of a blank
/ T sample as appropriate (as counts per minute),
\ )
E is the . counting efficiency (as counts per disintegration), ,
, V is the sample size (in enits of mass or volume),
2.22 x 108is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), A is the radioactWe decay constant for the particular radionuclide, and
. At is the elapsed time between midpoint of sample collection and time of counting.
. Typical values of E, V, Y and at shall be used in the calculation.
It should be recognizbd that the LLD is defined'as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.
- b. A composite sample is one in which the quantity of liquid ' sampled is proportional to the quantity of .
liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released,
- c. To be representative of the quantities and concentrations.of radioactive materials in liquid effluent, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order foi the composite sample to be representative of the effluent release.
52.0 ma
04'.-23-97.09:13:44 Nurnber j (UClear M Radiological Controls Departmenta! Procedure 6610-PLN-4200.01 True Revision No. Offsite Dose Calculation Manual (ODCM) . 12 Table 3.2-1 (Cont'd) ' d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, e&ch batch shall be isolated, and be thoroughly mtred, by a method described in the ODCM, to assure representative sampling. j e. i -' A continuous release is the discharge of liquid wastes of a non- discrete volu' m e; e.g., from a volume or system that has an input flow during the continuous release. f. The principal gamma 6mitters for which the Lb specification applies exclusively are the follow 4 radionuclides: Mn44, Fe-59, Co-58, Cof>0,'2n45, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not. mean that only these nuclides are to be considered. Other gamma peak's that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent. Release Report pursuant to TS 6.9.4. ) , n l I ( .
}
53.0 un.
04-23-97,.09:13:44 . Number [N
)
ggggggy. WI Radiological Controls . Departmental Procedurs 6610-PLN-4200.01 True Revirdon No. Offsite Dose Calculation Manual (ODCM) 12 3.2.2 Gaseous Effluents
, 1 SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates 1
\
3.2.2.1.1 The dose rato due to noble gases in gaseous effluents shall be d determined to be within the limits of Control 2.2.2.1.a in accordance j with the methods and procedures of the ODCM. . i 3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits of Control. 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in ] accordance with the sampling and analysis program, specified in Table 3.2-2. 3.2.2.2 Dose, Nobie Gas ' 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for th's current .
.(
- calendar quarter and current calendar year shall be determined in Q} accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.
3.2.2.3 Dose, lodine-131, lodine-133, Tritium, and Radionuclides in Particulate Form 3.2.2.3.1 Cumulative dose contributions from lodine-131, lodine-133 Tritium, and radionuclides in particulate form with half lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION
' MANUAL (ODCM) monthly.
3.2.2.4 Gaseous Waste Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM. 3.2.2.5 Explosive Gas Mixture 3,2.2.5.1 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the limits of Control 2.2.2.5 by monitoring the waste gases in the Waste Gas Holdup System with the hydrogen and oxygen monitors covered in Table 2.1-2 of Control 2.1.2. (" t U 54:0 , im,
04-23-97 09:13:44 Number
/
( Nuclear TM' aadio'oo'ca' contro's Departmental Procedura 6610-PLN-4200.01 D* fievision No. Offsite Dose Calculation Manual (ODCM) 12 3.2.2.6 Waste Gas DecapTank l 3.2.2.6.1 The concentration of radioactivity contained in the vent header shall be determined weekly, if the concentration of the vent header exceeds 10.7. C1/ce, daily samples shall be taken of each waste gas decay tank being added to, to determine if the tank (s) is less than or. 1 equal to 8800 Cl/ tank. , I l l t a l 4 e 9 4 55.0 ,,,,
o
~3 p ("N h Table 6610-PLN-420 Revision 12 ~ 4 I o Radioactive Gaseous Waste Sampling and Analysis Program l $
H i i W Minimum Lower Limit of
*a Sampilng Analysis Type of ActMty' Detection (LLD) ,
A Gaseous Release Type - Frequency ; Frequency
- Anatysts- pCl/ml) (Note a) l
~
P P l ~ A. Waste Gas Each Tank Principal Gamma d l Each Tank l 1 x 10 Decay Tank ; Grab Sample , Emitters (Note g) l 1 B. Containment - P (Note b) P (Note b) H-3 l 1 x 104 Purge
- Each Purge . Each Purge $ Principal Gamma i 1 x 104 Grab Sample ! Emitters (Note g)
C. Auxiiary and M (Notes c, e) M H-3 I 1 x 10 4 ' Fuel Handling Bulfding Grab Sample 4 Principal Gamma 1 x 10 Air Treatment System h Emitters (Note g) D. Fuel Hand!!ng Bu5 ding M (during M (during , H-3 - ESF Air Treatment System System . System i Principal Gamma 1 x 104 Operation) l Operation) ! Emitters (Note g) 4 1 x 10
-Grab Sample - '
t E. Condenser Vacuum M (Note h) l' M iH4 l Pumps Exhaust - Grab Sample ( ote h) ' Principal Gamma i 1 x 10+ (Note h) i Emitters (Note. g) ' 1 x 104 . e
- am 1 s 56.0 - mi, 9
l g-~'s E N' Table 3.2-ac gat %)'d) 6610-PLN-4200~ . NN
- Revision 12 O
W Radioactive Gaseous Waste Sampling and Analysis Program - e t.J Sampling l Minimum Analysis l Gaseous Release Type l Frequency l Lower Umit of Detection (LLD) g Frequency .(pCi/ml) (Note a) l q Type of ActMty Analysis j F. Chemical Cleaning Bu!! ding M (Note !) M - H.0 1 x 10-8 Air Treatment System ' Grab Sample Principal Gamma 1 x 104 - I Emitters (Note g) . G. Waste Handling and See Section I , See Section1 See Section i See Section i Packag!ng Facility of this table . l of this table of this table of this table
~
Air Treatment System
~j ,
H. ' Respirator and I.aundry l See Section i See Section I i See Sebion't See Section i Maintenance Facility.Alr j of this table ' of this table ' of this table , of th!s table Treatment System [ _ O e e f 4 1
=
h
~
57.0 nn, h m e _ ___- __m __ _ _ _ - _ _ _ - . . _ - _ _ _ _ _ _ _ . - - _
O ep.
~
Table 3.2-k ) Int'd) 6810-PLN-4200 . Revision 12
-o.
' W' Radioactive Gaseous Waste Sampling and Analysis Program -
H W Gaseous Release Type Sampling Frequency
-l Minimum Analysis . ! Lower Limit of Detection (LLD) - h
~l j . Frequency l Type of Activity Analysis l (pCl/mt) (Note a)
- l. A!! Release Types as Listed Above l Continuous l W (Note d) l l-131 1 x 1042 in A, B, C and D (During System j (Note f) ' Charcoal Sample l l Operation '
l-Continuous . W (Note d) ' ! rincipal P Gamma Emitters 1 x 104 ' - (Note f) Particulate (Note g) g
- (1-131, Others)
Continuous l O l ' 1 x 10-" (Note f) ! Composite ! Gross'Alpha - l Particulate Sample i Continuous -l Q
; (Note f) l Composite -
Sr-89, Sr-90 1 x 10"" ' l Particulate Sample J. Condenser Vent Stack Continuous ~ ,
. lodine -
l Continuous u W (Note d) 1-131 1 x 10 42 Sampler (Note j) I (Note k) ! Charcoal Sample ' t 9 4 1 e e S 58.0 mi,
04-23-97 09:13:44 ' Number CN - $UClG8F WI Radblogical Controls Departmental Pr'ocedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 12 Table'3.2 2 (Cont'd) ~ Table Notation
- a. The LLD is defined, for purposes of this surveillance, as the smallest concentration of radioactive matvial in a sample that will yleid a net count above system background that will 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 radiochemical separation): 4 , LLD = 4 66 s s
- E x V x 2.22 x 10' x Y x exp (-A At)
Where: LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume), sbis the standard deviation of the background counting rate or of the couriting rat'e of a blank sample as appropriate (as counts per minute). Q E is the pounting efficiency (as. counts per disintegration), V is the sample size (in un!!s of mass or volu'me),
~ 8 2.22 x 10 is the number of disintegrations per minute per microcurie, Y is the fra'ctional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular rad' ionuclide, and At is the elapsed time between midpoint of sample collection and time of counting. Typical values of E, V, Y and at shall be used in the calculation. - 11 should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.
, b. Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one. hour unless (1) analysis
. shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. -
c c. Tritium grab samples from the spent fuel pool area shall be taken at least once per 24 hours when ( the refueling canal is flooded. 9 l I 59.0 nm i
04 23-97 09:13t44 ' Number (UClear ~ WI Radiological Conirols Departmental Procedure 6610-PLN-4200.01 (7.~ w v'
- a. vision No.
Offsite Dose Calculation Manual (ODCM) 13 Table 3.2-2 (Cont'd) ,
- d. Charcoal cartridges and particulate filters shall be changed at Ieast once per 7 days and arialyses shall be completed within 48 hours after char)ging (or after removal from sampler).
. e. Tritium grab samples shal1 be taken weekly from the spent fuel pool area whenever spent fuel is in the spent fuel pool.
- f. The ratio of the sampl'e flow rate td,the sampled stream flow rate shall be known for the time period i
covered by each dose or dose rate calculation made in accordance with Controls 2.2.2.1,2.2.2.2, and 2.2.2.3.
- g. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54,
, Fe-59, Co-58, Co-60,2n-65, Mo-99, Cs-137, Co-141 and Ce-144 for particulate emissions. Thw list '
does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclidesishall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to TS 6.9.4. h.' Applicable only when condenser vacuum is estab!!ched. Sampling and analysis shall also be
/N performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of .
(V) RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUlVALENT l-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not. increased by more than a factor of 3.
- i. Gross Alpha, Sr-89,~and Sr-90 analyses do not apply to the Fuel Handling Building ESF Air Treatment System.
J. If the Condenser Vent Sta.ck Continuous lodine Sampler is unavailable, then alternate sampfincj equipment will be placed in service within 48 hours or a report will be prepared and submitted within i
' 30 days from the time the sampler is found or made inoperable which identifies (a) the cause of the '
inoperability, (b) the action taken to restore representative sampling capabliity, (c) the action thken { t'o prevent recurrence, and (d) quantification of the release via the pathway during the period and comparison to the limits prescribed by Control 2.2.2.1.b. kt Applicable only when condenser vacuum is established. 1. A'pplicable when liquid radwaste is moved or processed within the facility.
- m. lodine samples only required in the Chemical Cleaning Building when TMl-1 liquid radwaste is stored or processed in the facility.
U
- 60.0 nm.
. 1 04-23-97 09:13:44 -
Number
'jgggggy TMI Radiologigal Controls DepartmentalProceduie 6610-PLN-4200.01 Tme nevision No. ,
Offsite' Dose Calculation Manual-(ODCM) 12 1 3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous
' effluents shall be determined in accordance with Surveillances 3.2.1.2.1,3.2.2.2.1, and 3.2.2.3.1, including direct radiation
)
' ' l contributions from the Unit and f,rorn outside storage tanks, and in I accordance with the methodology contained in the ODCM. '
)
9 4 8 w ' e t 1 l l 4 l l o h
\s l 61.0 nm. l
0~4-23-97 09:13:44 Number Nuclear i M Radiological, Controls r Departmental Proceduro 6610-PLN-4200.01 TGe Revis4on No. Offsite Dose Calculation Manual (ODCM) 12 4.0 PART l REFERENCES 4.1 Title 10, Code of Federal Regulations, " Energy" 4.2 Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routing Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50. Appendix I, " Revision 1.- October 1977 4.3 TMI-1 Technical Specifications, attached to Facility Operating Ucense No. DPR-50 4.4 TMI-1 FSAR , l 1 e s O 62.0 n m.
~
i 04-23.-97 09:13:44 1 f , Nurnber i e Nuclear " "'dtdooic*' con"d* Departmental Procedure 6610-PLN-4200.01 l Tnte Hovisen No. i ] Offsite Dose Calculation Manual (ODCM) 12 i i i j . , 3 . i ? 1 (
- PART il TMI-2 RADIOLOGICAL EFFLUENT CONTROLS ' ,.
O e O 63.0 ,,,, i
1 04-23-97 09:13:44 Number l o I Nuclear '"' aadio'ooi: ' coatro'$
' Departrnental Procedurs 6610-PLN-4200.01 )
v Title . Flevision No. l Offsite Dose Calculation Manual (ODCM) 12 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFg Page 1 of 3 Ingestion Dose Factors for Adults * (MREM Per PCI Ingeste'd) NUCLtDE BONE LIVER T. BODY THYROID - KIDNEY LUNG GI-LLI H 3 NO DATA' '.1.055-07 1.05E-07. 1.05E-07 1.05E 07 1.05E-07 1.05E-07 C 14- 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E 07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1,70E 06 CR 51 NO DATA . NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 ' 6.69E-07 MN 54 NO DATA. 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 MN 56 NO DATA ' .15E-07 1 2.d4E48 NO DATA- 1.46E 07 NO DATA 3.67E-06
/ . FE 55' 2.75E-06 1.90E-06 '4.'43E-07 NO DATA NO DATA ' 1.06E-06 1.09E-06
\. FE. 59 4.34E-06 1.02E-05 3.91 E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58' NO DAT'A 7.45E-07 1.67E-06 NO DATA. NO DATA NO DATA 1.51 E-05 CO 60 NO DATA 2.14E-06 4.72E-06 ' NO DATA NO DATA NO DATA 4.02E-05 NI . 63 1.30E-04 9.01 E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E 08 3.13E 08 NO DATA NO DATA - NO DATA 1.74E-06 CU 64 NO DATA- 8.33E-08 3.91 E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 .NO DATA 9.70E-06 ZN 69 1.03E-08 1.97E-08 , 1.37E-09 NO DATA ~ 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA . 4.02E-08 NO DATA - NO DATA NO DATA 5.79E BR 84- NO DATA NO DATA 5.21 E-08 NO DATA NO DATA NO DATA 4.09E-13 BR .85 NO DATA .NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E45 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21 E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01 E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA fi.84E-06 NO DATA . NO DATA NO DATA 4.94E-05 SR 90 7.58E NO DATA - 1.86E-03 NO DATA NO DATA NO DATA 2.19E44 SR 91 5.67E-06 NG RATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05~
SR. 92 2.15E46 1;O CATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E NU DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E44 i - c) . 102.0 me. s .
04-23-97 09:13:44 Number
)
l m Nuclear TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 l
) ' V')- 1me -
Revision No. Offsite Dose Calculation Manual-{ODCM) 12 )
\
l TABLE 2.1 (Cont'd) l Liquid Dose Conversion Factors (DCF): DF g i Page 2 of 3 ingestion Dose Facto'rs for Adults
- I
. (MREM Pe'r PCI Ingested) '+
NUCUDE BONE' LIVER T. BODY . THYROID KIDNEY LUNG GI-LLI Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67El10 Y 91 1.41 E-07 NO DATA 3.77E-09 NO Co.TA NO DATA - NO DATA' 7.76E-05 Y. 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO D'ATA 8.50E-05 ZR ,95- 3.04E-08 9.75E49 6.60E-09 NO DATA 1.53E48 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 .NO DATA 5.12E-10 NO DATA 1.05E 04 NB 95 6.22E-09 3.46E-09 1.86E-09 ,- NO DATA 3.42E-09 NO DATA 2.10E-05 (% MO 99 NO DATA 4.31 E 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E 6.98E-10 ' 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC 101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU 103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU 105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E47 NO DATA 9.42E-06 RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AG 110M' 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91 E-07 NO DATA 6.04E-05 SB 125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.0 1.38E-06 1.97E-05 TE 125M 2.68E-06 , 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE 127M ~ 6.77E-06 2.42E-06 8.25E-07 1,73E-06 2.75E-05 NO DATA 2.27E-05 TE 127 1.10E-07 3.95E-08 2.38E-08 8.15E 4.48E-07 NO DATA 8.68E-06 TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E TE ~129 3.14E-08 1/18E OE) 7.65E-09 2.41E 08 1.32E-07 NO DATA 2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E 07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE 131 1.97E-08 8.23E-09 6.22E 09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE 132 2.52E-06 1.63E-06 1.53E-06 1.80E 06 1.57E-05 NO DATA 7.71E45 l 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 ' 3.48E-06 NO DATA 1.92E-06 1 131 4.16E-06 5.95E-06 3.41E46 1.95E-03 1.02E-05 NO DATA 1.57E-06 1 132 2.03E-07 5.43E 07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 I. 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 NO DATA 2.22E-06 1 134 1.06E-07 2.88E-07 1.03E-07 4.99E46 4.58E-07 NO DATA '2.51 E-10 f 103.0 me.
04-23-97 09:13:44 Number
^ Nuclear " "ad' 'oo'ca' oo"tr '$ , [V )
w. Departmental Procedure- 6610-PLN-4200.01 Feision No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 2.1 (Cont'd) Liquid Dose Conversion Factors (DCF): DFg - Page 3 of 3
, Ingestion Dose Factors for Adults *
(MREM Per PCI Ingested) NUCUDE _ BONE LIVER _T. BODY THYROID KIDNEY LUNG ___ . GI-LU l 135 4.43E 07 1.16E-06 4.28E-07 7.65E 05 1.86E-06 NO DATA 1.31 E-06 CS 134 - 6.22E-05 1.48E-04 ' 1.21 E-04 NO DATA 4.79E 05 1.59E-05 . 2.59E 06 CS 136 6.51E' 06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 . 2.92E-06 CS 137 7.97E-05' 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11 E-06 CS 138 5.52E-08 1.09E 07 5.40E-08 NO DATA 8.01E-08 7.91E49 4.65E-13 l BA 139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 BA 1'40 2.03E-05 2.55E-08 1.El3E-06 NO DATA 8.67E-09 1.46E48 4.18E-05 O BABA14t t 142 4.71E48 3.56E-11 .1.59E-09 NO DATA 3.31 E-11 2.02E-11 2.22E-17 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E 11 3 00E-26
)
LA 140 2.50E-09 1.26E 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA 142 1.28E.10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E 09 '6.33E-09 7.18E-10 NO DATA 2.94E 09 NO DATA 2.42E-05 CE 143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 . CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21 E-07 NO DATA 1.65E-04 PR 143 9.20E49 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO, DATA 4.03E-05 PR 144 3.01 E-11 1.25E-11 1.53E- NO DkTA 7.05E-12 NO DATA ' 4.33E-18 ND 147 6.29E-09 7.27E 4.35E 10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E47 ' 8.61 E-08 3.01 E.-08 NO DATA NO DATA NO DATA 2.82E-05 NP 239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05 Dose factors of intemal exposure are for continuous intake over a one year period and include the dose , commitment over a 50-year period; from Reg. Guide 1.109 (Rev.1). . Additional dose factors for nuclides not included in this table may be obtained from NUREG-0172.
'k_
104.0 me 4
04-23-97 09:13:44 , Number
.io Nuclear ' aad'o'oo'ca' contro's Departmental Procedure 6610-PLN-4200.01 C'j Tme nevmon uo. .
Offsite Dose Calculation Manual (ODCM) 12 TABLE 2.2 Bioaccumulation Factors, BF, , Bioaccurnulation Factors to be Used in the Absence of Site-Specific Data * (pCl/kg per pCi/ liter) FRESHWATER ELEMENT FISH INVERTEBRATE ~ H 9.0E 01 9.0E-01 C . 4.6E + 03 9.1 E + 03 NA 1.0E + 02 2.0E + 02 4 CR 2.0E + 02 2.0E + 03 MN 4.0E + 02 9.0E + 04 FE 1.0E + 02 3.2E + 03 CO . 5.0E + 01 2.0E 4 02 NI 1.0E + 02 1.0E + 02 CU 5.0E + 01 4.0E + 02, ZN 2.0E + 03 [mi BR 4.2E +'02
, 1.0E + 04 3.3E+ 02 C/ RB 2.0E +03 . 1.0E + 03 ,
SR 3.0E + 01 1.0E+ 02 Y 2.5E + 01 1.0E+03 ~ ZR 3.3E + 00 6.7E + 00 NB 3.0E + 04 1.0E + 02 MO 1.0E + 01 1.0E + 01 TC 1.5E + 01 ' 5.0E + 00 RU 1.0E + 01 3.0E + 02 RH 1.0E + 01 3.0E + 02
*SB 1.0E + 00 , 1.0E + 00 TE 4.0E+ 02 6.1E + 03 1 1.5E + 01 5.DE+ 00 CS > 2.0E + 03 1.0E + 03 BA - 4.0E + 00 2.0E+ 02 LA ' 2.5E + 01 1.0E + 03
~CE 1.0E4 00 1.0E + 03 PR 2.5E + 01 1.0E + 03 '
ND 2.5E + 01 1.0E + 03 W 1.2E + 03 1.0E + 01 , NP 1.0E + 01 4.0E + 02 Bioaccumulation factor values are taken from Reg. Guide 1.109 (Rev.1), Table A-1]. Sb bioaccumulation factor value is taken from EPRI NP-3840. m 105.0 ane
1 l l 4 04-23-97 09'i3:44 : l Number l M Radidogical Contrds
- (UClear Departmental Procedure 6610-PLN-4200.01 1
l'~NJ k/ Title Revtsion No. Offsite Dose Calculation Manual (ODCM) 12 3.0 TMI UQUID EFFLUENT WASTE TREATMENT S' YSTEMS 3.1 TMI-1 Llauid Effluent Waste Treatment System
~
3.1.1 Description of the Liquid Radioactive Waste Treatment System,(see Figure 3.1)
. Reactor Coolant Train
- a. Water Sources - (3) Reactor Coolant Bleed Tanks (RCBT)
- (1) Reactor Coolant Drain Tank (RCDT)
- b. Liquid Processing - Reactor. Coolant Wast'e Evaporator (see Figure 3.2) -
- Demineralizers prior to release
- c. Liquid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks (WECST)
- d. Daution - Mechanical Draft Cooling Tower (0-38k gpm)
River Flow (2E7 gpm average) l
,O Miscellaneous Waste Train l \V) -
- a. Water sources': - Auxiliary Budding Sump '
l l
- Reactor Building Sump
. .. Miscellaneous Waste Storage Tank
- Laundry Waste Storage Tank -
- Neutralizer Mixing Tank
- Neutralizer Feed Tank
- Used Precoat Tank
- Borated Water Tank Tunnel Sump
- Heat Exchanger Vault Sump ~
Tendon Access Galley Sump
- Spent Fuel Pool Room Sump
- TMI-2 Miscellaneous Waste Holdup Tank
- b. Liquid Processing Miscellaneous Waste Evaporator, MWE (see Figure 3.2)
' -Demineralizers prior to release
~
- c. bquid Effluent for Rele~ase - (2) Waste Evaporator Condensate Storage Tanks (WECST).
- d. . Dilution - Mechanical Draft Cooling Towar (0-38k gpm) ,
- River Flow (2E7 gpm average)
A i [%.
- 106.0 mm
04-23-97 09:13:44 ' Number A MUClGSF M Radiological Controls . l ( Departmental Procedure 6610-PLN-4200.01
\ Title Revision No.
Offsite Dose Calculation Manual (ODCM) 12 s . 3.2 Operability of the TMI-1 Liould Emuent Waste Treatment Svi; tem 3.2.1 The TMI-1 Uguid Waste Treatment System as described in Section 11 of the TMI-1 Final
. Safety Analysis Report is considered to be operable when one of each of the following
, pieces of equipment is eval!able to perform its intended function:
a) Miscellaneous Waste Evaporator (WDL-21B) or Reactor Coolant Evaporator (WDL-21A) b) Waste Evaporator Condensate Demineralizer (WDL-K3 A or B) c) Waste Evaporator Condensate Storage Tank (WDL-T 11 A or 8) d) Evaporator Condensate Pumps (WDL-P 14 A or B) 3.2.2 TMI-1 Representative Sampling Prior to Discharge . 4 All liquid releases from the TMI-1 Uquid Waste Treatment System are made through the Waste Evaporator Condensate Storage Tanks. To provide thorough mixing and a representative sample, the contents of the tank are recircu'ated using one of the Waste Evaporator Condensate Transfer Pumps. [ , 3.3 TMI-2 Llauld Effluent Waste Treatment System 3.3.1 Description of the TMI-2 Uquid Radioactive Waste Treatment System
'The TMI-2 Uquid Radioactive Waste Treatment System has been out of service since the TMI-2 Acciderft in 1979. TMI-2 Uquid Radioactive Waste is processed by the TMI-1 system described in Sectin 3.1 prior to release. In addition, TMI-2 releases water from various sumps'and tanks to the river (see Figures 1.1 and 1.2). These processes are governed by plant procedures that encompass proper sampling, sample analysis, and radiation -
. monitoring techniques.
j l , i e t 4 i . 7.- v 107.0 ms.
04-23-97 09:13:44 Number p\/ Nuclear * "**o'oo'camo"* Departmental Procedure 6610-PLN-4200.01 l Thte Revision No. Offsite Dose Calculation Manual (ODCM) 12 FIGURE 3.1 TMI t Liquid Radwaste
'RC B. A. M U-V8
, MIX - MAKE TANK UP RC DRAIN s
BWST' SUMP M TANK RB S.F. SUMP ' SUMP TEND. GAL. A l _ pony SAMPLE SUMP- I g I TANK 4-AW BWG -- MISC. DRAIN ALv SUMP - & REUEF 3r v9r
- _1r 3r1r + ^
4 4 4 TM12 'RCBT B RCBT C I M ST -RCBT A . MWHT i 1 I I u
'b b b b b
,, ,, .,, ,- ,r l I
( CATION 4PRECOAT4_ DEMIN FILTER PRECOAT CATION 4 FILTER - DEMIN & MAKE UP ( 1 OF 2) TO MU-V9 (1 O F 2) 3r
,r %Y
~
MISC. WASTE RC WASTE EVAP. ~otsTtLLATE EVAR Of STil LATf" Mr
,r 3r 4 +
CWST RBAT 4.__. AUX ---> (t op 2) (1 O F 2) STEAM HITTMAN D h MDCT , 1r v EUNA're 4 y h , 2 EFFLUENT BUILDtNG ' i
'^ ST J RECLAIM (1 O F 2) '
C OW. DEMtN WATER 4 . WATER p ' STOR TANK O 2) b\ O . RECLAIMED WATER SYSTEM 108.0 sui. W.
O b N
, -J 0 if. o
- t e
- n o C
.q _
c ..
^
Ng - CONC,
- 9: -
2r
"= +
T , 8 g rtusu -- , 6 E MATER $ h r E O
- 4 ,. SENIATOR . -
g m 4 o
,O
_r,_q y)i,, A _ stat u. F l' ag WATER l
~- M M 'N ... '
E ; Q 2.TNSCC. E
- n NSOC atir .- DIST.
;,y) C0iC8ENTRATOR = ;
50 d C OW ~ [
~C.) .
8'M E 8 y ?n -
.C r R W. c 5 g g",
E 'g" m DIST.
-L p
'i g- m y gy TANK 2. y.
h 0 k do me 0' i[O E U C A I i E as go
- o
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?I -_ _
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~ v v
. i i'"s.
}7 WASTE FALL m g
.? (V FEED TANK g g'.
j [. pg sen l$$ . O
~
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04-23-97 09:13:44 - Number f c Nuclear " "**'ootc=' co":'d=. Departmental Procedure 6610-PLN-4200.01 Tsue Revision No. Offsite Dose Calculation Manual (ODCM) 12 4.0 _ GASEOUS EFFLUENT MONITORS-4.1 TMI-1 Noble Gas Monitor Set Points , The gaseous effluent monitor set points are established for each gaseous effluent radiation monitor to assure concentrations of radionuclides in gaseous effluents do not exceed the limits set forth in ODCM Part I Control 2.2.2.1. Table 4.1 lists Gaseous Effluent Release Points and their associated parameters; Figure 4.1 provides a Gaseous Effluent Release Pathway Diagram. The set points are established to satisty the more restrictive set point concentration in the following two equations: 500 > I(c,)(F)(K)(Dv) (eg 4.1'.1) 1. and 3000 '> I(c)(L,3 + 1.1 M;)(Dv)(F) .(eq 4.1.2) I O where: - c, 3 set point concentration based on.Xe-1'3 3 equivalent, in pCl/cc F= ' gaseous effluent flowrate at the monitor, in ec/sec K, = total body dose factor, in mrem /yr per pCl/m3from Table 4.3 Dv = highest sector annual average gaseous atmospheric dispersion factor (X/Q) at or . beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for station vent releases and Table 4.5 for all other releases, (Condenser off gas, ESF FHB, and ground releases). Maximum values presently used are 7.17E-7 sec/m 8 at sector NNE for 3 station vent, and 1.16E-5 sec/m at sectors N and WNW for a!!,other releases, y- skin dose factor due to beta emissions from radionuclide I, in mrpm/yr per pCi/m 8 from Table 4.3. M=. i air dose factor due to gamma emissions from radionuclide 1, in mrad /yr per pCi/m8 from Table 4.3. 1.1 - mrem skin dose per mrad air dose. 500 = annual whole body dose rate limit for unrestricted areas, in mrem /yr. 3000 = annual skin dose rate limit for unrestricted areas, in mrern/yr. The set point concentration is further reduced such that the concentration contributions from (O V) multiple release points would'not combine to exceed ODCM Control limits. . The set point concentration is converted to set' point scale units on each radiation monitor using appropriate calibration factors. 110.0 ' un.
~
04-23-97 09:13:44 . Nurnber O ENuclear'
* "^d'= 'oo'd contro'$
Departmental Procedure 6610-PLN-4200.01 Title Revision No. Ottsite Dose Calculation Manual (ODCM) . 12 - 1 i This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure i and the procedure for Releasing Radioactive Gaseous Waste, I e i i ] . I ' 1
- 1 I t j
l l .
. I 1 l
! l
. . l l
l 111.0 , k . _'
04-23-97 09:13:44 Number (O MUClear i R did gi ai Contras Departmental Procedure 6610-PLN-4200.01 Title - Revision No. , Offsite Dose Calculation Manual (ODCM) . 12 4.2 ~ TMI-1 Particulate and Radiciodine Monitor Set Points Set points for monitors which detect radionuclides other than noble gases are also established to assure that concentrations of these radionuclides in gaseous effluents do not exceed the limits of OOCM Part I Control 2.2.2.1 , Set polnts are establist}ed so as to satisfy the following equations: 1500 > I(c;)(F)(P;)(Dv) (eq 4.2) I where: ci - set point concentration based on 1131 equivalent. In pCi/cc F= gaseous effluent flow rate at the monitor, in cc/see P,- g pathway dose parameter, in mrem /yr per pCl/m3 for the inhalation pathway from Table 4.6. The dose factors are based on the actual individual organ and most restrictive age group (chad) (NUREG-0133). r~'N NOTE Appendix A contains P; calculational methodology. 1500 - annual dose rate limit to any organ from particulates and radiolodine'. and i radionuclides (other than' noble gases) with half lives greater tha,n uight days in l mrem /yr.
- Dv = highest sector annual average gaseous dispersion factor (X/O (,r D/Q) at or beyond
_ the unrestricted area boundary from Table 4.4 for' releases from the station vent and
' Tabte 4.5 for all other releases. X/O is used for the inhalation pehway. Maximum 3
values of X/O gresentiy,used are 7.17E-7 sec/m for station vent, at sector SE, and 1.16E-5 sec/m for all other releases, at sectors N and WNW. The set point concentration is fu'rth'er reduced such that co'ncentration contributions from muttiple release points would not combine to exceed ODCM Control limits. The set point concentration'is converted to set point scale units on each radiation monitor using appropriate calibration factors. This section of the ODCM is implemented by the Radiation Monitor Systems Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste. v . 112.0 mm
I 04-23-97 09:13:44 , Number
- f. (UCIO8r M Radiological Controls Departrnental Procedura 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation . Manual (ODCM) 12 i 4.3 'TMI-2 Gaseous Radiation Monitor Set Points TMI-2 Gaseous Radiation Monitors have their set points described.in TMI Plant Procedure 1101-2.1. i Figure 4.5 provides a gaseous effluent release pathway diagrarn. Table 4.2 provides TMl-2 Radiation Monitor Data. 8
.These set points are set in accordance with the Controls delineated in Part'll'of this bDCM. ]
4 . e t W I y .
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113.0 , l 1
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04-23-97 09:13:44 Number M Rasological Contmls (O GUClear Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite' Dose Calculation Manual (ODCM) 12 4.4 TMI-1 Gaseous Effluent' Release Points and Gaseous' Radiation Monitor Data TMI-1 has eleven (11) required. effluent gaseous radiation monitors. These are RM-A4, RM-A5, RM-A15, RM-AS, RM-A7, RM-A8, RM-A9, RM-A14, ALC-RMI-18; WHP-RIT-1,.and RLM-RM-1. ' These gaseous release points, radiation monitors, and sample points are shown in Table 4.1. . 4.4.1 RM-A4/RM A6 Fuel Handlina and Auxiliary Buildina Exhaust RM-A4 is the particulate, radiolodine and gaseous radiation monitor for the.TMI 1 Fuel Handling Building Ventilation (see Figures 4.1 and 4.2). RM-A6 is the particulate, radioiodine, and gaseo'us radiation monitor for the TMI-1 AuxHiary Building Ventilation (see Figures 4.1 and 4.2). High alarms on RM-A'4 or RM-AS noble gas channels will initiate , shutdown of the related building ventuation air supply system. These two radiation monitors concurrently will satisfy requirements'for the Station Vent release point in place of RM-A8. 4.4.2 RM-A8 Station Ventilation Exhaust RM-A8 is the particulate, radioiodine and gaseous radiation monitor for the T,Mi-1 Station
- VentBation (see Figures 4.1 and 4.2)'. This in plant effluent radiation monitor also has an associated sampling panel with sampling tines located before the sample filters. High alarm on RM-A8 noble gas low channel wDI initiate shutdown of the Station VentBation air supply
's systems. (The Fuel Handling and Auxiliary Building Ventuation). This radiation monitor satisfies requirements for the Station Vent release point in place of RM-A4 and RM-A6.
4.4.3 RM-AS/RM-A15 Condenser Off Gas Exhaust RM-A5 is the gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). RM-A15 is the back up gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). High alarms on RM-A5 low channel or RM-A15 noble gas channels wal initiate the MAP-5 Radiolodine Processor Station. These two radiation monttors together satisfy requirements for the Condenser Off Gas release point. - 4.4.4 RM-A7 Waste Gas Decay Tank Exhaust RM-A7 is the gaseous radiation monitor,for the TMI-1 Waste Gas Decay tanks (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel. High alarm on RM-A7 noble gas channel will initiate shutdown of the Waste
. Gas Decay Tank release in progress. This radiation monitor satisfies requirements for batch gaseous releases to the Station Vent release point.
4.4.5 RM-A9 Reactor Bundina Purae Exhaust RM-A9 is the particulate, radioiodine and gaseous radiation monitor for the TMl-1 Reactor Building Purge system (see Figures 4.1 and 4.3). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters. High alarm on RM-A9 noble gas low channel WHI initiate shutdown of the Reactor Building 9' Purge System. This radiation monitor satisfies requirements for the Reactor Building Purge System release point. 114.0 mm
...h.-w . - - - - -
04-23-97 09:13:44 ' Number
,m "ggggggy M Radiological Controls
( ) Departmental Procedure .6610-PLN-4200.01 k/ Title Revision No. Offsite Dose Calculation Manual.(ODCM) 12 4.4.6 RM-A14 ESF FHB Ventilation System RM-A14 is the gaseous radiation monitor for the TMI-1 Emergency Safeguards Feat'ures (ESF) Fuel Hardling Building Exhaust system (see Figures 4.1 and 4.2). This in plant
' effluent radiation monitor also has an associated sampling panel with sampling lines located before the sampler filters. High alarm on RM-A14 noble gas channel will initiate shutdown of the ESF Fuel Handling Building Exhaust System. This radiation' monitor satisfies requirements for the ESF Fuel Handling Buildin'g Exhaust System telease point.
4.4.7 ALC-RMI-18 Chemical Cleanina Facility (CCF) Ventilation Exhaust s ALC-RMI-18 is an Victoreen, particulate, radioiodine, and gaseous radiation monitor for the Chemical Cleaning building exhaust. This monitor is located in the Chemical Cleaning building on the ground floor, and has an associated sample panel. Sampling for part!culate activity is performed off of the monitor.
~4.4.8 WHP-RIT-1 Waste Handlina and Packaoino Facility (WHPF) Exhaust .
WHP-RIT-1 is an Eberiine AMS-3 particutate radiation monitor for the TMI WHPF. The monitor is located in the Mechanical Equipment Room in the WHPF. Sampling for 3 particulate activity is performed off of the monitor. A high alarm will initiate shutdown of the
/ ventilation air exhaust system.
4.4.9 FILM-RM-1 Respirator Cieanina and Laundry Maintenance (RLM) Facility
- RLM-RM-1'is an Eberline AMS-3 particulate radiation monitor for the TMl RLM Facility. The monitor is located in the Mechanical Equipment Room in the RLM. Sampling for particulate activity is performed off of the monitor.-
s 4 I 1 l 115.0 - me, . 1 l l 1
04-23-97 09:13:44 1 Number
,O) (UClear TMl Radiological Controls-Departmental Procedure 6610-PLN-4200.01 )
X Trbo Revision No. Offsite Dose Calculation Manual (ODCM) 12 1 4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMI-2 has three (3) regulatory required gas'eods effluent radiation monitors. These are HP-R 219 HP-R-219A and HP-R-225. These gaseous release points, radiation monitors, and sample points are shown in Table 4.2, and various gaseous effluent' pathways are depicted in Figure 4.5. I 4.5.1 HP-R-219 Station Ventuation Exhaust HP-R-219 is a Victore'en particulate and gaseous radiation monitor for the TMI-2 ventilation exhaust. This in-plant effluent radiation monitor is located in the TMI-2 Auxuiary Building 328 foot elevation and has an associated sample panel. 4.5.2 HP-R-219A Station Ventaation Exhaust HP-R-219A is a Victoreen particulate and gaseous radiation monitor for the TMI-2 ventilation exhaust. This in-plant effluent radiation ' monitor is located in the TMI-2 Auxiliary Building'
, 328 foct elevation.
4.5.3 HP-R-225 Reactor Buildino Purae d!r Exhaust Duet "A" i HP-R-225 is a Victoreen particulate and gaseous radiation monitdr for the TMI-2 Reactor (j Building Purge Air Exhaust System. This in-plant effluent radiation monitor is located in the TMI-2 AuxDiary Building 328' elevation area. I i l 9 9 b - i 116.0 um
04-23-97 09:13:44
. Number /o Nasclear * " *d d oo'ca' o "tro'*
Departmental Procedure 6610-PLN-4200.01 Tstle Bevmon No. Offsite Dose Calculation Manual (ODCM) ^12 4.6 Control of Gaseous Effluent Releases ,c TMI gaseous effluent combined releases are controlled (per ODCM Part I for TMl-1 and ODCM Part li for TMI-2) by effluent sampling and radiation monitor set points. .These measures assure that releases from the'various vents do not combine to produce dose rates at the site boundary ' , exceeding the most restrictive of 500 mrem per. year to the total body or 3000 mrem per year to the skin, and 1500 mrem per year to the thyroid. This is done by restricting simultaneous releases and by limiting the dose rates that may be contributed by the various vents at any time. The various vent radiation monitor set points are each based on fractions of the above. limits and do not exceed the above limits when summed together. These effluent radiation monitor set points are calculated using the methodology described in equations 4.1.1, or 4.1.2 and 4.2. The actual set points are then listed in TMI-1 Operations' Procedure 1101-2.1. The radioactive content of each batch of gaseous waste is determined prior to release by sampling . , and analyses in accordance with ODCM Part I for TM1-1 and ODCM Part 11 for TMI-2. The results of pre-release analyses are used with the calculational methods in Sections 4.1 and 4.2 to assure that the dose rates at the site boundary are maintained below the limits in ODCM Part I for TMl-1 and ODCM Part 11 for TMI-2.
~
Postdelease analyses of samples composited from batch and continuous releases are performed in A accordance with ODCM Part I for TMI-1 and ODCM Part 11 for TMI-2. The results of the analyses are ( , used to assure that the dose ra'tes at the site boundary are maintained within the limits of ODCM Part I for,TMI-1 and ODCM Part 11 for TMI-2. e 0 g a 4 6 l x 4 117.0- me,
i l 04-23-97 09:13:d4 Number
"'\ ilACIO8r Tui nadiciogical controis Departmental Procedure 6610-PLN-4200.01 (L THle Fevisen No.
Offsite Dose Calculation Manual (ODCM) 12
~
TABi.E 4.1 l TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data ' RELEASE ~ GASEOUS TERMINATION RADIATION GASEOUS (F) (NTERLOC( MONITOR RELEASE FLOW. (YES/NO) (DETECTOR) LOCATION POINT RLOORDER VALVES
, YES AH-E 10 Fuel Hand. AH-D 120 300' Bevation Building AH-D-121
,
- RM A4 Auxiliary Bldg. Exhaust FR149 AH-D 122 Auxiliary .
306' Eevation Building YES 4 RM-A6 ' Auxiliary Bldg. Exhaust FR 150 AH-E-11 YES WDG-V47 NtE-10 (%
) RMA4/9 Btdg.
AH.E 11 Starts MAP-5 .
\." / Near BWST Station FR.149 Radioiodine RMA8 Exhaust Vent & FR 150- Sampler WS 322' Elevation Condenser Starts MAP-5 Second Floor Off Gas Radioiodine RM-A5 TuMne Bldg. Exhaust . FR-1113 Sarnpler i
YES 1 4 322' Oevation Condenser Starts MAP 5 Second Floor Off Gas Radiciodme
)
i 1 RM-A15 Turbine Bldg.- Exhaust FR 1113 Sarnpler Waste Gas 306' Devation' Decay Tanks YES RM-A7 Auxiliary Bidg. (A,B,C) . FR 123 WDG V47 YES AH-V 1A/B/C/D
, Reactor WDG434/535 Budding Starts MAP-5 RMA 8/9 Bldg. Purge FR 909/ Radiciodine RM-A9 Near BWST Exhaust ,FR 148 Sampler 331' Bevation ESF FHB ESF Fuel Outside Handling NO Chem. Building Manual '
RM.A14 Addition Bldg. Exhaust FR 1104A/B Actions f
- 118.0 -
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04-23-97 09:13:44 , Number - (UClear O M Radiological Con *Jols I (% l TWe Departmental Procedure 6610-PLN-4200.01 Revision No.
'Offsite Dose CalculatlOn Manual (ODCM) 12 TABLE 4.1' (Cont'd)
- 1 TM! 1 Gaseous Release Point and Gaseous Radiation Monitor Data l GASEOUS RELEASE RADIATION GASEOUS . TERMINATION l MONITOR . . RELEASE INTERLOCK (DETECTOR) LOCATION POINT (YES/NO) VALVES Chemical Osaning CCB Exnaust
- ALC-RM1 Bldg. 304' Elevation System NONE
'YES WHPF Mechanical WHPF Exhaust WHPF Ventitation ,
WHP4UT 1 Equipment Room System Trips RLM-Mechanical RLM Exhaust RLM-RM 1 Equipment Room System NONE TABLE 4.2 - TMI-2 Gaseous Release Point and Gaseous Radiation Mpnitor Data
/ %
~
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RELEASE I GASEOUS TERMINATION RADIATON GASEOUS INTERLOCK MONITOR RELEASE (YES/NO) (DETECTOR) LOCATION POINT VALVES 328' Elevation Station Auxiliary Vent HP-4219 Building Exhaust NONE 328' Elevation
- Auxiliary Station Vent HP-4219A Building Exhaust NONE 4
Reactor Bldg 328' Elevation Auxiilary Purge Exhaust HP R225 Building Duct "A*. NONE i J V[\ . r 119.0 ms. a
04-23-97 09:13:44 Number TMI Radiological Controls
$UClear Departmental Procedure - 6610-PLN-4200.01 me nevision No.
Offsite Doss Calculation Manual (ODCM) 12 TABLE 4.3 D, ose Factors for Noble Gases and Daughters * , l Gamma Beta ' l Total Body Skin Dose Gamma Air. Beta Air Dose Factor (a) Dose Factor , Dose Factor Factor (b)~ K, 4 M. g Ni Radio- (mrem /yr per (mrem /yr per (mrad /yr per (mrad /yr per nuclide pCl/m3) , pCl/m3) pCl/m3) pCi/m3)- Kr-83m 7.56E-02'* - 1.93E + 01 2.88E'+ 02 1.97E + 03 I Kr-85m . 1.17E + 03 1.46E + 03 1.23E + 03 Kr.85 1.61E + 01 1.34E + 03 1.72E+ 01 ' 1.95E + 03 Kr-87 5.92E + 03 9.73E + 03 6.17E + 03 1.03E + 04 ym Kr-88 1.47E + 04 ' 2.37E +03 1.52E + 04 2.93E + 03 l Kr 1.66E + 04 1.01E + 04 i.73E + 04 1.06E + 04 Kr-90 1.56E+ 04 7.29E + 03 1.63E + 04 7.83E + 03 Xe-41m 9.15E + 01 4.76E + 02 1.56E + 02 1.11 E + 03 Xe-13:h- 2.51 E + 02 ' 9.94E402 3.27E + 02 1.48E + 03 Xe-133 2.94E + 02 3.06E + 02 3.53E + 02 1.05E+ 03 Xe-135m 3.12E + 03 . 7.11 E + 02 3.36E + 03 7.39E + 02 - Xe-135 1".81 E + 03 1.86E + 03 1.92E + 03 2.46E + 03 Xe-137 1.42E + 03 .1.22E + 04 1.51 E + 03 ' 1.27E+04 Xe-138 8.83E + 03 4.13E + 03 9.21E + 03 4.75E + 03 , Ar-41 8.84E + 03 2.69E + 03 9.30E + 03 3.28E + 03
- Dose factors are for immersion exposure in uniform semi-infinite cloud of noble gas radionuclides that may be detected ingaseous effluents.- Dose factor values are taken from Regulatory Guide 1.109 (Rev.1), Table B-1.
**7.56E-02 = 7.56 x 10-2, (a).. Total body dose factor for osmma per.etration depth of 5 cm into the body.
2 (b) Skin dose factor at a tissue depth or tissue density thickness of 7 mg/cm , 9 , 120.0 mm e 1
04-23-97 09:13:44 Number '
/^)
(
-(UClear TMI Radiological Controls -
Departmental Procedure 6610-PLN-4200.01
%/ Tith Rusion No. 1 Offsite Dose Calculation Manual (ODCM),' 12 TABLE 4.4 Atmospheric Dispersion Factors for Three M'ile Island '
e STATION VENT DISTANCE .
- SECTOR AVERAGE X/O (IN SEC/M3) (IN METERS) s SEASON- ANNUAL i I
SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 . N 1.18E 07 5.32E-07 2.95E-07 1.93E-07 1.39E 07 5.52E 08 1.91E-08 5.02E49 1.88E49 1.09E49 NNE 1.70E-07 7.17E-07 3ASE-07 2.00E 07 1.39E 07 5.58E48 1.70E 08 4.77E49 1.98EC9 9.69E-10 ! NE 1.12E-07 1.75E-07 3.26E-07 1.86E47 1.21E 07 5.00E48 1.67E-00 4.67E-09 1.85E 09 9.93E-10 ENE 1.09E-07 2.13E47 2.67E-07 1.53E47 1.05E47 4.31E-08 1A2E-08 ~4.42E-09 1.59E49 8.64E 10 1 E 2.31E-07 1.7t E-07 1.52E 07 ' 1.49E47 1.0$E-07 4.63E-08 1.52E46 5.19E 09 2.48E49 1.50E 09 I ESE 3.50E 07 2.12E-07 2.50E-07 1.48E47 9.48E48 3.98E-08 1.50E-08 5.92E49 2.92E-09 1.93E 09 SE 4.19E-07 3.79E 07 2.53E 07 1.55E-07 1.11E 07 4.82E-08 1.81E48 6.84E49 3.30E49 2.22E49 SSE 2.90EW 3.62E-07 2.55E 07 1 A9E 07 1.11E 07 5.02E 08 1.98E-08 6.97E-09 2.94E49 .170E49 S 1.87E-07 6.47E-08 2.15E 07 1.30E 07 8.65E-08 4.09E48 1.40E-08 4 *' . 99E49 1.04E49 SSW 6.13E-08 4.16E48 1.56E-07 1.03E47 6 81E-08 2.72E 08 9.74E 07 .. 6 09 1.50E-09 8.23E-10 SW 5.76E-08 1.14E-07 1.70E-07 1.0$E47 6.93E48 2.518-08 9.34E 03 2.72E49 1.33E49 8.33E 10 i WSW 8.52E 06 3.75E 07 2.14E-07 . 1.26E 07 7.74E-08 3.08E-08 1.02E 08 3 28E 09 1.39E-09 9.69E-10 5 s W 1.15EW 5.80E-07 2.88E 07 1.63E 07 1.18E 07 5.23E48 1.72E48 5.06E-09 1.98E 09 1.25E-09 I WNW 1.41E-07 6.28E 07 3.30E 07 2.19E47 1.48E 07 5.68E 08. ' 1.95E-08 6.32E 09 2.16E-09 ' 1.34 E-09 NW 1A2EW 5.67E-07 3.17EW 1.93E47 1.30E 07 5.67E46 2.06E 08 5.90E-09 2.70E-09 1.45E49 NNW - 1.00E-07 5.77E-07 3.18E-07 l 120E47 1.77E& 5.20E 08 1.77E 08 4.82E49 2.0.1 E-09 1.22E-09
- STATON VENT DISTANCE !
e SECTOR AVERAGE D/O (IN M-2) (IN METERS) SEASON. ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 2.51E 09 8.72E-10 4.84E 10 2.98E 10 2.50E-10 8.57E 11 2.51E 11 4.98E-12 1.57E 12 7.84E 13 NNE 3.89E49 1.985C9 9.54E 10 4.99E 10 3.38E-10 1.10E-10 2.89E 11 6.00E 12 2.10E-12 8.89E-13 NE 2.58E-09 8.70E-10 9.13E.10 4.91E-10 2.97E-10 1.04E 10 2.87E-11 0.01E-12 1.99C 12 9.23E 13 ENE 2.15E49 5.85E 10 5.54E-10 3.06E 10 208E 10 8 30E 11 2.32E-11 5A1E-12 1.63E-12 7.64E 13 E 5.54E49 1.23E-09 6.17E-10 ' 4.59E-10 3.63E-10 1.34E-10 3 66E-11 9:44E 12 3.77E-12 1.97E 12 ESE 9.17E 09 2.0$E 09 1.51E-09 8.66E 10 5.11E 10 - 142E 10 5.77E-11 ' 1.72E-11 7.07E-12 4.07E-12 I
. SE 1.22E-06 2.88E49 1.84E 09 1.02E-09 625E 10 2.60E-10 8.30E 11 .2.34E-11 9A2E 12 5.51E-12 SSE- 7.50E.09 1.62E 09 1.08E-09 5.89E 10 4.49E 10 1.87E 10 6.16E-11 1.61E-11 5.67E-12 2.83E-12 S- 3.86E49 6.53E-10 6.27E-10 3.59E-10 2.32E-10 1.06E 10 3.05E 11 810E-12 2.73E 12 1.23E 12 SSW 1.13E49 2.94E 10 4.19E 10 2.53E-10 1.56E-10 5.38E 11 128E 11 3.91E-12 1.64E 12 7.84E 13 SW 1.19E49 3.84E 10 4.96E 10 2.80E-10 1.70E 10 5.24E-11 1.65E 11 '3.62E-12 1A9E 12 0.12E 13 WSW 1.77E-09 8.31 E-10 6.49E 10 3.50E 10 1.99E-10 6.73E-11 1.89E 11 4.58E-12 1.63E 12 ' 9.90E-13 W 2.41E 09 1.29E-09 6.81E 10 3.65E-10 2.96E 10 1.12E-10 3.11E 11 6.90E 12 2.26E 12 1.25E-12 WNW 3.20E49 1.39E 09 7.73E 10 5.91E-10 3.66E-10 1.19E 10 3.43E 11 8.36E-12 2.39E 12 1.29E 12
,q NW 3.2SE49 1.23E49 7.39E-10 4.22E 10 2.77E-10 1.14E 10 7.28E-11 7.61E-12 2.92E 12 1.36E-12 NNW 1.98E49 9.88E 10 . 5.71E 10 3.05E 10 2.23E-10 8.21E 11 2A1E-11 4.93E-12 1.72E-12 9.03E-13 fV) DATA FROM 1/1/78 THROUGH 12/31/86 U,$ED IN CALCULATIONS 121.0 mm 7
--.e.....=.
04-23-97 09.:13:44 Number A { AUClear TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01
-* Title - Revision No.
Offsite Dose Calculation Manual (ODCM) 12 TABLE 4.5 ! Atmospheric Dispersion Factors for Three Mile island e GROUND ret. EASE DISTANCE e SECTOR AVERAGE X/O (IN SEC/M3) (IN METERS) SEASON ANNUAL. I SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 1.16E45 1.13E46 5.94E-07 3 80E& 2.38E47 9.74E-08 3ASE-08 9.28E-09 3.52E 09 2.05E49 NE 1.08E45 1.10E4e 5.66E-07 3.41E-C7 2.38E 07 9.55E48 3.11 E-08 8.94E49 3.74E49 1.84E-09 NE 7.02E48 9.81 E-07 5.42E47 3.17E 07 ' 2.10E-07 9.01E 08 3.10E-08 8.87E49 3.54E-09 1.91E49 ~ ENE. 7.14E OS 9.64E47 4.92E-07 2.85E-07 1.97E47 7.82E-08 2.64E 08 8.38E-09 3.04E 09 1.6SE-09 E 8.49E-06 1.09E46 6.48E47 2.91E47 1.87E47 8A0E48 2,82E-08 9.85E49 4.75E 09 2.87E-09 ESE 6.91E-06 9.02E-07 4.49E-07 2.57E-07 1.67E-07 7.20E-08 2.77E-08 1.12E-08 5.54E-09 3.68E-09 SE 6.70E-06 0.06E-07 4.53E 07 2.81E 07 2.03E-07 8.94E 08 3.33E-08 1.28E-08 6.19E-09 4.18E-09 SSE 7.26E-06 '9.25E 07 4.9tE-07 2.87E 07 ' 2.08E-07 ' 9.18E-08 3.72E-08 1.32E48 5.62E-09 3.26E-09 S 8.70E-06 9.08E47 3.99E-07 2.41E-07 1.61 E47 7.31E 08 2.57E-08 ' 9.23E-09 3.74E-09 1.95E-09 SSW 6.05E-06 7.01E47 2.75E.07 1.86E-07 1.24E& 5.06E 08 1.82E-08 5.71 E-09 2.87E 09 1.58E49 SW 5.94E46 5.71E47 2.86E 1.81E-07 1.22E-07 4 50E48 1.72E48 5.12E49 2.53E-09 1.59E49 q WSW 8.00E-06 7.02E47 340E-07 2.15E47 1.34 E-07 530E 08 1.87E48 6.12E49 2.62E 09 1.83E-09 W 1.02E-05 1.07E46 5.30E 07 3.02E& 2.05E-07 9.31E-08 3.15E-08 9.48E 09 3.74E-09 2.38E-09 WNW 1.16E-05 1,13E46 5.98E-07 3.67E47 2.53E 07 1.00E 07 3.5GE-08 1.18E-08 4.07E 09 2.54E49 NW 1.13E 05 1.06E-06 5.70E 07 3.53E47 2.40E47 .1.02E 07 3.82E-08 1.11E-08 5.14E49 2.78E-09 NNW 1.08E.05 1.04E46 5.72E-07 3.27E-07 2.22E-07 9.06E-08 3.20E.08 8.89E-09 3.75E-09 2.29E-09 e' GROUND RELEASE , OlSTANCE e SECTOR AVERAGE D/O (IN M-2) (IN METERS) SEASON ANNUAL j SECTOR 610 .2413 4022 5631 7240 12067 24135 40225 .5S315 72405 N 2.30E-08 1.88E49 8.03E-10 4.82E-10 2.70E-10 8.96E 11 2.53E-11 4.98E-12 1.575-12 7.84E 13 NNE 2.66E 08 2.25E-09 1.06E-09 5.42E-10 3.38E-10 1.10E 10 ' 2.89E-11 6.06E-12 2.10E 12 8.89G13 NE 1.75E4s 2.00E49 1.01E-09 5.04E 10 2.98E-10 1.04E 10 2.8BE:11 6.01E 12 1.99E-12 9.23E.13 ENE 1.68E 08 1.85E-09 8.65E-10 4.28E 10 2.65E-10 '8.57E 11 2.33E-11 5.41E-12 1.63E 12 7.64 E.13 E 2.88E-08 2.99E.09 1.39E-09 6.34E-10 ' 3.67E 10 1.35E 10 ' 3.68E 11 9.42E-12 3.77E 12 1.97E.12 ESE 3.59E-08 3.80E-09 1.77E 09 8.79E 10 5.15E 10 1.83E 10 5.78E-11 1.71E 11 7.06E-12 4.06E 12 SE 4.12E-08 4.55E49 2.13E49 1.15E-09 7.50E 10 2.72E 10 8.31E-11 2.34 E-11 SA2E-12 5.50E.12 SSE 3.12E48 3.23E-09 1.59E-09 8.00E 10 5.20E-10 1.88E 10 6.18E-11 1.61E.11 5 66E 12 2.83E.12 S 2.65E 08 2.21E-09 9.07E-10 4.75E-10 2.86E-10 1.07E 10 3.06E-11 8.10E-12 2.73E-12 1.23E.12 SSW 1.45E-08 ~ 1.30E-09 4.80E.10 2.82E 10 1.70E-10 5.71 E-11 1.69E 11 3.9 t E-12 1.64E-12 7.84E.13 - SW 1.42E-08 1.10E49 5.15E 10 2.82E 10 1.71E 10 5.24E.11 1.65E 11 3.62E 12 1.49E-12 8.12E 13 WSW 2.01E-08 1.41E 09 6.82E-10 3.54 E-10 2.00E 10 6.76E 11 1.89E 11 4.58E 12 1.63E 12 9.90E-13 W 2.55E-08 2.16E-09 1.00E 09 4.91E-10 3.01E 10 1.12E 10 3.11E-11 6.90E-12 2.27E 12 1.25E.12 VNW 2.88E 08 220E49 1.13E 09 5.93E.10 3.67E.10 1.19E-10 3 43E-11 8.36E.12 2.39E-12 1.29E 12
.lW 2.78E48 2.15E49 1.06E.09 5.58E 10 3 41E-10 1.19E 10 3.57E 11 7.61E 12 2.92E-12 1.36E.12 O W/ 2.17E48 175E49 8.75E-10 4.24E 10 DATA FROM 1/1/78 THROUGH 12/31/88 USED IN CALCULATIONS 2.57E-10 8.55E 11 2.42611 4.93E 12 ' 1.72E-12 9.03E-13
.122.0 mk
04-23-97 09:13:44 Number lo') Nuclear ' "* dido **' contro'*- Departmental Procedure 6610-PLN-4200.01
'V Title .Remion No.
Offsite Dose Calculation Manual (ODCM) 12
/
TABLE 4.6 Dose Parameters for Radiolodines and Radioactive Particulate in Gaseous Efflu'e nts*
- CRITICAL- ORGAN -
CRITICAL ORGAN NUCLIDE ORGAN. FACTOR Pi**
- NUCUDE ORGAN FACTOR Pi* *
- H-3" TOTAL BODY 3.04E-07 4 1.12E + 03 RU-103 LUNG 1.79E 04 6.62E + 05 C 14 BONE 9.70E-06 3.59E + 04 RU-105 GI-LU 2.69E-05 9.95E + 04 NA-24 TOTAL BODY 4.SS.E 06 1.61E + 04 RU-106 LUNG 3.87E-03 1.43E4 07 P-32 BONE 7.04E-04 2.60E + 06 AG-110M LUNG 1.48E-03 5.46E + 06 CR-51 LUNG ^ 4.59E-06 1.70E + 04 TE-125M LUNG 1.29E-04 4.77E+ 05 '
MN-54 LUNG 4.26E-04 1.58E + 06 SB-125 LUNG 6.27E-04 2.32E + 06 MN-56 GI-LU 3.33 E-05 1.23E + 05 TE-127M LUNG 4.00E-04 ' 1.48E + 06 FE-55 LUNG 3.00E-05 1.11 E + 05 . TE-127 GI-LU 1.52E-05 5.62E + 04 FE-59 LUNG 3.43E-04 1.27E + 06 TE-129M LUNG 4.76E-04 1.76E+ 06 CO-58 LUNG 2.99E-04 1.11 E+ 06 TE-129 GI-LU 6.89E-06 2.55E + 04 CO-60 LUNG 1.91 E-03 7.07E + 06 - TE-131M GI-U 8.32E-05 3.08E + 05 NI-63 BONE 2.22E-04 8.21 E + 05 TE-131 LUNG 5.55E 07 2.05E+ 03 N1-65 GI-LLI 2.27E-05 8.40E + 04 - TE-132 LUNG 1.02E-04 3.77E + 05 CU-64 G!-LU ' 9.92E-06 3.67E +04 1-130 TYHROID 4.99E-04 1.85E + 06 ZN-65 LUNG 2.69E-04 ' 9 95E +05
. l-131 THYROID 4.39E-03 1.62E+ 07 (O)
U ZN-69 BR-83 GI-LLI 2.75E-06 1.28E-07 1.02E + 04 4.74E + 02 l132 1-133 THYROID THYROID 5.23E-05 1.04E-03 1.94E + 05 3.85E + 06 TOTAL B.ODY BR-84 TOTAL BODY ' 1.48E-07 - 5.48E + 02 1-134 THYRO!D 1.37E-05 5.07E + 04 j BR-85 TOTAL BODY 6.84E-09 2.53E + 01 ' l-135 THYROID 2.14E-04 7.92E + 05 ' RB46 LIVER 5.36E-05 1.98E + 05 CS-134 UVER 2.74E-04 1.01E + 06 i RB-88 UVER 1.52E 07 5.02E+02 CS-136- UVER 4.62E-05 1.71 E.+ 05 l RB-89 LIVER 9.33E-08 3.45E + 02 CS-137 BONE 2.45E-04 9.07E + 05 l SR-89 L'NG U 5.89E-04 2.16E + 06 ' CS-138 LIVER 2.27E-07 8.40E+ 02 SR-90 BONE . 2.73E-02 1.01 E + 08 BA-139 Gl-LU 1.56E-05 5.77E+04 ' SR-91 GI-LU 4.70E-05 ' 1.74E + 05 BA-140 LUNG 4.71 E-04 1.74E406 SR-92 ' GI-LLI 6.55E-05 2.42E + 05 BA-141 LUNG 7.89E-07 2.92E + 03 Y-90 GI-LU 7.24E-05 2.68E + 05 BA-142 - LUNG 4.44E-07 , 1.64 E + 03 . Y-91 M LUNG 7.60E-07 2.81 E + 03 LA-140 GI-LLI 6.10E-05 2.26E + 05 Y-91 LUNG 7.10E-04 2.63E + 06 LA-142 GI-LU 2.05E45 7.59E + 04 Y-92 GI-LLI 6.46E-05 2.39E + 05 CE-141 LUNG 1.47E-04 5.44E + 05 Y-93 GI-LU 1.05E44 3.89E + 05 CE-143 GI-LLI 3.44E45 , 1.27E + 05 ZR-95 LUNG 6.03E-04 2.23E + 06 CE-144 LUNG 3.23E-03 1.20E + 07 ZR-97 GI-LU 9.49E-05 3.51E+ 05 - PR-143 LUNG 1.17E44 4.33E + 05 NB-95 LUNG 1.66E-04 6.14E + 05 PR-144 LUNG 4.23E-07 1.57E + 03 MO-99 LUNG 3.66E-05 1.35E + 05 ND-147 LUNG 8.87E 05 3.28E + 05 TC-99M GI-LLI 1.30E-06 4.81 E + 03 W-187 GI-LLI 2.46E45 9.10E + 04 TC-101 LUNG 1.58E-07 5.85E + 02 NP-239 GI-LU 1.73E-05 6.40E + 04 The hsted dose parame ers are for radionuclides, other than noble gases that may be detected in gaseous effluents. .Pi factors include all nonatmospheric pathway transport' parameters, the receptor's usage of 8 pathway media, and are based on the most restrictive age group (child) critical organ. Additional dose .
!~ parameters for nuclides not included in this Table may be calculated using the methodology described in i NUREG 0133.
Tritium dose factors include an increase of 50% to account for the additional amount of this nucrde = absorbed through the skin. ~ l rnrem/ year per pCi/m3 , 123.0 m=
04-23r97.09:13:44 Number I O i (UClear . Ml Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revisaon No. 12 Offsite Dose Calculation Manual'(ODCM) q FIGURE 4.1 TMl-1 Gaseous Effluent Pathways .
~
FIGURE 4.1 0;^"?" ' Sgf0
#2% ~%
= man AUXILIARY BUILDING #** W w
[s
\v /g 410CFWI jgp -
P A C' C A P - REACTOR gg - l RM-A0 l BUILDWa wh MG22 I E 5G23 gg lRM-A14 ' A J L Uhec= 7 -M N d
~
FUEL eg ,T y ea % - HANDLING _ l waca BUILDING . . 4, o o cru M P-PRE FILTER Ia m - 54 A-ABSOLUTE HEPA E4N
- g. C-CHARCOAL FILTER COCEND 7 o .
i
=" !
i O . 124.0 rne
04-23-97 09:13:44 - 3 Number ('I Nuclear M Radiologdponus ' Departmental Procedure 6610-PLN-4200.01 bI TWe Revision No. Offsite Dose Calculation Manual (ODCM) 12 FIGURE 4.2 l TMI-1 Auxiliary and Fuel Handling Buildings Efflu,ent Pathways d a q ~~ m un . IIE 170 gg RN-A8 ' me sm a m ' gPAC g sa mi MP-$ RH-A6 o-in a . swtr RX-A14 l RH.A4 me an ('- I ESFFUEL I f- AUX LIARY I HAH 11NG
- P A C -
l ma== ' h
/
BUILDING Rs-A7 ? BulLDING . 3 at A at n A' FUEL HANDLING
$ V' Y A'
at V BUILDING AUXILIARY AND flEl HAN11NG BUILDINGS EXHAUST RADIAT10N $'i C = mm E KNITIlRS ANLSAMPLING STATIONS O - 125.d , ma, a
04-23-97 09:13:44 d Number (~Ni t Nuclear 7"' "*dio'oo'c*' co"2'o'* Departrnental Procedure 6610-PLN-4200.01 Title , Revision No. . Offsite Dose Calculation Manual (ODCM). 12 , FIGURE 4.3 1 i TMI-1 Reactor Building Effluent Pathway i ' s b 1 n k j 170 $
- TEET .
REACTOR BUILDING PURGE EXHAUST
*A9 55
- RADIATION HONITORS AND
**3 SAMPLING STATIONS C
W$ sw 0 . 7 A STAIR d PdT/ REACTOR ex mgg ,, BUILDING __ ) '
- tt, s umsus .
RUS swtz mros PdI10DIUTitITH P PMTEUTE A : ABS [LUIE C OWuK 5 126.0 mn I
J 04-23-97 09:13:44 Number o Nuclea. r TM Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No. , Offsite Dose Calc'ulation Manual (ODCM) 12 FIGURE 4.4 TMl-1 Condenser Offgas bffluent Pathway I i r j
, 1 i CONDENSER
- OFF GAS STACK
,3 CONDENSER OFF GAS 115 -m EXHAUST l FEET RADIATION HONITORS l AND SAMPLING STATIONS '
I
.s -
wYr "
.=> myan o<
~ O , . lj .,
~"
,w g MAIN m CONDENSER
, V 1 I
e 70 age au j Tff* wsm e i
~
127.0 mm 4
04-23-97 09:13:44 Number l l- p --ggggggy WI Radiological Controls - Departmental Procedure 6610-PLN-4200.01 ( Trtle Revison No. Offsite Dose Calculation Manual (ODCM) 12 FIGURE 4.5 TMi-2 Gaseous Effluent Filtration System / Pathways
. 5 aa -
.oz 1
g>t-- y- 95
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a: -= I W i I , 4 i
' I E
i I 6 W ! 'l E I . ~ i i c. ' 1 l I I i 2 l O i ' U E n i i g. . o
!- . 'E ; !- !! $$ Z 5 ? :95;; zy ' j ;
(E bo 4
/E oE
. 5 6 45 !. '
ES h 5 E [1:- 7
" 1 g g' 82 O J-i g g g. ,
Q i E R' 1 O E i ; ; l l . i < 1 l-l l @ l D ' i . . < , i 6 h. 'I n e y
. I E g, ,
I g N I 1 h_. I Z i .I D l > oo '
*Et a E t $5 g9
- -) Ed *5 I"
$E ,
\
128.0 mm
04-23-97 09:13:44 , s ., , Number i (N l- ggggggy' M Radiological Controls Departmental Procedure 6610-PLN-4200.01 V noe semien. so Offsite Dose Calculation Manual (ODCM) 12-5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents -Instantaneous Release Umns 1
.5.1.1 Noble Gases * '
For n'oble gases, the following eqpations apply for total body and skin dose rate at the unrestricted area boundary: , 5.1.1.1 Total Body - Dose Rate = E (K) x (Dv) x (Q) 3 3 (eq 5.1.1.1) I where: , Dose Ratetb= instantaneous total body dose rate limit, at the site boundary, in mrem /yr. K= i total body dose factor due to gamma emissions for'each identified noble gas radionuclide, in mrem /yr per pCi/m3 from Table 4.3. .
, Dv = highest. sector annual average gaseous dispersion factor (X/0) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for -
station vent releases; and Table 4.5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases). Maximum values pjesently in use are 7.17E-7 sec/m3at sector NNE for station vent, and 1.16E-5 sec/m 8 for all other releases lat sectors N and WNW. Q-3 Release rate of radionuclide' i, in pCf/sec as determined by sampling and analysis. Calculated using the cor] centration of noble gas radionuclide,1, in pCl/cc, times the release pathway flow rate, in cc/second. s e 5 b n 0 129.0 nm
1 04-23-9 19:13:44 i 1 Number
'n' (UClear M Radiological Controls ,
l i (%/ ) Departmental Procedure 6610-PLN-4200.01 1 me Remion No. Offsite Dose Calculation Manual (ODCM) 12 1 5.1.1.2 Skin l
, Dose Rateg .= I (1 3+ 1.1 M;) X (Dv) X (Q,) . (eq5.'1.1.2) l
.where:
Dose Rateg= , instantaneous mrem / year skin dose rate limit, at the site boundary, in mrem /yr. Q= skin dose factor due to-beta emissions for each identified noble gas radionuclide, in mrem /yr per Ci/m 3from Table 4.3. M;'= air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCl/m3from Table 4.3. 1.1 = mrem skin dose per mrad air dose. Converts air dose to skin dose. O, = release rate of radionuclide,1, in pCl/sec, as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, i, t
; in pCi/ce, times the release pathway flow rate, ii) cc/second.
l k Dv = highest sector annual average gaseous dispersion factor (X/Q) at or ' beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for ' station vent releases; and Table 4,5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases). Maximum values presently in use 3 are 7.17E-7 sec/m at sector NNE for station vent, and 1.16E-5 sec/m3 for
. all other releases, at sectors N and WNW.
I 1
. l s s O ,
130.0 me
1 04-23 1 97 09:13:44 . Number
/7 4HCIGar ' , W Radidogical Contrds .
' Departmental Procedure 6610-PLN-4200.01
( i b Title Revir.on No. Offsite Dose Calculation Manual (ODCM) 12 ) 5.1.2 - lodine-131. lolfine-133. Tritium and Radionuclides in Particulate Form with Half-Lives Greater
, than 8 Days -
For 1-131,1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than_8 ,
. days, the fouowing equation applies: ,
, Dose Rate, = I (P;) (Dv) (Q)
~
3 ,
. (eq 5.1.2) l
-where:
Dose Ratep = . mrem / year organ dose rate. - P'i dose parameter for 1-131,1133, Tritium and Radionuclides in Particulate
. Form, with half-lives greater than 8 days, for the inhalation pathway, in ,
mrem /yr per pCl/m 3, from Table 4.6. The dose factors are based on the
' critical individual organ and most restrictive age group (chud).
Dv = highest sector anndal average gaseous dispersion factor (X/O or.D/0) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for hg the station vent releases and Table 4.5 for all other releases. .X/O is used for the inhalation pathway. Maximum values of X/Q presently used are (/ 7.17E-7 sec/m3for station vent, at sector NNE, and 1.16E-5 sec/m8 for all i
' other releases, at sectors N and WifN.
0; = release rate of each radionuclide,1, in pCi/sec. Calculated using the concentration of each radionuclide. I, in pCi/ce, times the release pathway flow rata, in ec/second. S 131.0 ma
04-23-97 09:13:44 Number n ( Nuclear *' "*d'd**' contr$8 Departmental Procedure 6610-PLN-4200.01 Tide Revision No. f Offsite Dose Calculation Manual (ODCM) 12 5.2 Gaseous Effluents - 10 CFR 50 Apoendix I ' , 5.2.1 Noble Gases
\The air dose in an unrestricted area due to noble gases released in gaseous efflue,nts from
- the site is determined using the following expressions:
Dose r = (3.17E-8) x I(M;) x (Dv) x (Oi) (eg 5.2.1) i and Dose B = (3.17E-8) x E (N) x' (Dv) x (Qi) (eq 5.2.2) I where: Dose r = . mrad gamma a!r dose due to gamma emissions from noble gas radionuclides. Dose p = mrad beta air dose due to beta emissions frorn noble gas radionuc!! des.
, ,\
( . , ( / M- i air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCl/m 3, from Table. 4.3. N; - air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad /yr per Cl/m 3, from Table 4.3. Dv = highest sector annual average gaseous dispersion factor, X/O, at or-beyond the unrestricted area boundary, in sec/m3 . Values may be read or interpolated from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. Maximum values of X/O presendy used are 7.17E-7 sec/m 3for station vent at sector NNE, and 1.16E-5 sec/m8 for all other releases at sectors N or WNW. O=3 release of noble gas radionuclide, I, in pCI, over the specified time period, ( Ci/second
- seconds).
3.17E inverse of the number of second's in a year. NOTE , { If the methodology in this section is used in determining dose to an f individual, rather than air dose due to noble gases, substitute ~ Ki, from 1 Table 4.3, for Mi, and (LI + 1.1 Mi) for Ni. 1 l n 4 J 132.0 me
04-23,97 09:13:44 Number l (UClear TMl Radiological Controls Departmental Procedure 6610-PLN-4200,01 1
)
[Vl TW Mson No. l Offsite Dose Calculation Manual (ODCM) 12 l l i.2.2 lodine-131. lodine'133. Tritium and Radionuclides in Particulate Form. with Half-Lives Greater than 8 Days l The dose to an individual from I 131,1-133, Tritium and Radionuclides in Particulate Form l with half-lives greater than.8 days in gaseous effluents released from the site to ari
.* unrestricted area is detennined by soMng the following expression:
l Dose, = I(3.17E-8) x E (R,) (Dv) (Q,) (eq 5.2.2) ; i i l where: Dose, = dose to all real pathways, p, to organ,'o, of an' individual in age group, a, from I-131,1-133, Tritium and Radionuclides in Particulate Form, with half- 1 lives greater than 8 days; in mrem, during any desired time period. I R=i the dose factor for each Identified radionuclide, I, pathway, p, age groug, a, and organ, o, in mrem /yr per pCl/m8 for the inhalation pathway and m - mrem /yr per Cl/sec for other pathways, from Tables 5.2 to 5.7.
) NOTE %) .
l
.Since there is minimal or rio elemental iodine released from the condenser off-gas air eject,or (see NUREG-0017) all lodine Ri values for all pathways, except the inhalation pathway, are considered to be zero
. when piedorming dose ' calculations fo'r releases from the condenser off-gas air ejector. Only calculate the ilose due to the inhalation pathway for condenser off-gas air ejector lodines.
NOTE Tritium, H-3, dose factor is mrem / year per pCl/m3 for att pathways. Dv =' highest sector annual average gaseous dispersion factor (X/Q) at or
~
beyond the unrestricted area boundary, in sec/m 8, for the inhalation pathway, and D/0, in m-2, for other pathways. Table 4.4 is used for station vent releases and Table 4.5 for all other releases. Maximum values of X/O
- ' presently used are 7.17E-7 sec/m3 for station vent at sector NNE and 3
1.16E-5 sec/m .for all other releases at sectors N and WNW. Maximum values of D/O in m-2for station vent is 1.22E:8/m2 at sector SE, and for ground releases,4.12E-8/m2 for sector SE. Dv(H-3) = In the case of H-3 only the X/Q's are used for all pathways from Table 4.4 for station vent releases and Table 4.5 for all other releases. 133.0 nm
.. - - = . . - _ . .- -
04-23-97 09:13:44 Number O m a did gi ai controts ( (UClear Departmental Procedurer 6610-PLN-4200.01 Tme Revism No. 1 Offsite Dose Calculation Manual (ODCM) 12 1 . O, - release of I-131,1-133. Tritium and Radionuclides, i, in Particalate Form with : I half-lives greater than 8 days In Cl, cumulative over the specified time 3 period (pCi/second
- seconds).
3.17E-8 = inverse of the number of seconds in a year. i i j 1 l 1 s 4 4 134.0 22:=
04-23-97 09:13:44 Number ;,
'i
/ Jgggy TMI Radiological Controls
()) Departmental Procedure 6610-PLN-4200.01
' Title Revision No.
Offsite Dose Calculation Manual (ODCM) 12 5.3 Gaseous Radioactive System Dose Calculations Once per Month . ODCM Part i Control 2.2.2.4 and TMI-2 PDMS Tech Spec Section 6.7.4.a.6 requires that appropriate subsystem of the Gaseous Radwaste Treatment System shall be.used to reduce the radioactive materials in gaseous waste prior to their discharge. When the monthly projected doses due to the
. gaseous effluent release's from the site would exceed: .
0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ. The following calculational method is provide'd for performing this dose projection.
. At least once per month the gamma air dose, beta air dose and the maximum organ dose for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual release during the period for which the projection is made, if these projected doses exceed any of the values listed
, above, appropriate portions of the TMI-1 Gaseous Waste Treatment System, as defined in Section 6.0, or appropriate portions of the TMI-2 Gaseous Effluent Filtration System as shown on ,
Figure 4.5, shall be used to reduce radioactivity leva 4 pnor to release. k At the discretion of Ra'diological Engineering, time periods other than the current quarter-to-date may be used to project doses if the dose per day in the current. quarter-to-date is not believed to be representative of the dose per day projected for the next month.
~
z I
. )
1 e . l l 135.0 me,
4 04-23'97 09:13:44 ' Number Nuclear " "*d'docioa' coat'd$ (^/ L
)
Tiue Departmental Procedure 6610-PLN-4200.01 Revision No. Offsite Dose Calculation' Manual (ODCM) 12 5.4 Alternative Dose Calc $ational Methodolooies for Gaseous Effluents
, As an altemative to the methods described above, the models in/or based upon, those presented in Regulatory Guide 1.109 (Rev.1) may be used to make a comprehensive dose assessment. Default parameter values from Regulatory Guide 1.109 (Rev.1) and/or actual site specific data'can be used where applicable.
The onsite, on-line computerized system for tracning gaseous effluent dose uses annual average gaseous dispersion factors. As an attemative dose calculational methodology. GPU Nuclear
- calculates doses using an advanced class "A" dispersion model called SEEDS (simplified environmental effluent dosimetry system).
- 'This model incorporates the guidelines and methodology set forth in USNRC Regulatory Guide 1.109, and uses actual hourly meteorological information matched to the time of releases to more accurately assess the dispersion of effluents in the atmosphere. Combining this assessment of dispersion with TMINS effluent data *for each unit, postulated maximum hypothetical doses to the
~
pub!!c are calculated. ( ' b'_ 1 I A t O 136.0 me al
04-23-97 09:13:44 Number
,p)
(,/ Nuclear TMI Radiological Controls o ,,,1m mtol g,ocooo,0 es,o.ptu.42oo.o,' Tate Revision No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.2.1 Pathway Dose Factors, RI - AGE GROUP: INFANT PATHWAYi INHALATION ,
~ ~~
ORGAN DOSE FACTORS; mrem [ year per pCl/m3 NUCUDE - BONE LIVER T.B . KIDNEY LUNG GI-LLI
.. .__ . _ .. ODY THYROID . ..- ~.....
H-3 0.00E + 00 - 647E+ 02 6.47E+ 02 6.47E + 02 6.47E + 02 6.47E + 02 6.47E + 02 C-14 2.65E + 04 5.31 E+ 03 5.31E + 03 5.31 E + 03 5.31E + 03 5.31 E + 03 5.31 E + 03 CR-51 0.00E + 00 0.00E+ 00 8.95E + 0i 5.75E + 01 1.32E + 01 1.28E + 04 3.5 E + 02
. _ _ = _ _ _ .. ..--..--.
MN-54 0.00E + 00 2.53E+ 04 4.98E + 03 0.00E + 00 4.98E + 03 1.00E +0S . 7.06E+03 FE-55 1.97E + 04 ' 1.17E + 04 - 3.33E +03 0.00E + 00 0.00E + 00 8.695 + 04 1.09E + 03 FE-59 1.36E + 04 2.35E+ 04 9.48E +03 0.00E + 00 0.00E + 00 1.01E +06 2.48E + 04
'~
Id~58 0.00E + 00 1.22E+ 03 1.82E+b3 0.00E + 00 0.00E + 00 'f.77E + 05 1.11 E + 04 CO40 0.00E + 00 8.02E + 03 1.18E + 04 0.00E + 00 0.00E + 00 4.51E + 06 3.19E + 04 l NI-63 3.39E + 05 2.04E+ 04 1.16E +04 0.00E + 00 0.00E+ 00 2.09E + 05 2.42E + 03
~ ~ _ . .
O ZN 65 1.93E + 04 6.26E + 04 3.11 E + 04 0.00E + 00 3.25E + 04 6.47E + 05 5.14E +'04 h)
/ RB-86 SR-89 SR-90 0.00E + 00 1.90E + 05 8.82E + 04 0.00E + 00 0.00E + 00 0.00E + 00 3.04E + 03 3.98E + 05 0.00E+ 00 1.14E + 04 0.00E + 00 0.00E'+ 00 2.00E + 06 6.40E + 04 '
4'.09E + 07 0.00E+ 00 2.59E + 06 0.00E + 00 0.00E + 00 1.12E + 07 1.31 E+ 05
. - - . - =..._
Y-91 5.88E + 05 0.00E+ 00 1.57E + 04 . 0.00E + 00 0.00E + 00 2.45E+06, 7.03E+04 ZR-95 1.15E + 05 2.79E + 04 2.03E+ 04 0.00E + 00 3.11 E + 04 1.75E + 06 2.17E + 04 NB-95 1.57E + 04 6.43E+ 03 3.78E + 03 0.00E + 00 4.72E + 03 ~ 4.79E + 05 1.27E + 04
- RU-103 2.02E + 03 0.00E+ 00 6.79E + 02 0.00E + 00 4.24E + 03 5.52E + 05 1.61 E + 04 RU-106 8.68E + 04 0.00E + 00 1.09E + 04 0.00E + 00 1.07E + 05 1.16E + 07 1.64E + 05 AG-110M 9.98E + 03, 7.22E + 03 5.00E + 03 0.00E + 00 1.09E + 04 3.67E + 06 3.30E + 04
- . TE-125M 4.76E + 03 1.99E+ 03 6.58E + 02 1.62E + 03 0.00E + 00 4.47E+ 05 1.29E + 04 TE-127M 1.67E + 04 6.90E + 03 2.07E + 03 4.87E + 03 3.75E + 04 1.31E +~ 06 2.73E + 04
~
TE-129M 1.41 E + 04 6.09E + 03 2.23E + 03 5 47E +03 3.18E + 04 1.68E + 06 6.90E + 04 l-131 3.79E + 04 4.44E + 04 1.96E + 04 1.48E + 07 5.18E+ 04 0.00E + 00 1.06E + 03 1-133 ' 1.32E + 04 1.92E + 04 5.60E + 03 3.56E+06 ; 2.24E+ 04 0.00E + 00 2.16E + 03
~ ~
CS-134 3.96E +b5~f.53E + 05 7.45E + 04 d.00E+00 1.90E + 05 h.h7E + 04 1.33d+~b5 , CS-136 4.83E + 04 1.35E + 05 5.29E + 04 0.00E + 00 5.64E + 04 1.18E + 04 1.43E + 03 CS-137 5.49E +05 6.12E + 05 4.55E + 04 0.00E + 00 1.72E + 05 7.13E + 04 1.33E + 03
~ ~ ~ ~
bh~-140 5.60E + 04 5.00E + 01 2.90E + 03 0.00E + 00 1.34E + 01 1.60E + 06- 3.84E +b~4~ CE-141 2.77E + 04 1.67E + 04 1.99E + 03 0.00E + 00 5.25E + 03 5.17E+05 2.16E + 04 CE-144 3.19E + 06 1.21E + 06 1.76E + 05 0.00E + 00 5.38E + 05 9.84E + 06 1.48E + 05 ....... _ = _ . ____ __ - - _ PR.143 1.40E + 04 5.24E+03 6.99E + 02 0.00E + 00 1.97E + 03 - 4.33E + 05 3.72E + 04 i ND-147 7.94E + 0J 8.13E + 03 5.00E + 02 0.00E + 00 ,3.15E + 03 3.22E + 05 3.12E + 04 137.0 me
04-23-97.09:13:44 . . Number' '
^ -(UClear TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 (V] Utle Revision No.
Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.2.2 Pathway Dose Factors, Ri AGE GROUP: CHILD . PATHWAY: INHALATION
~ ~~ ' ~
ORGAN D6~SE FACTO'R5[ mrem / year per' Ci/m3 NUCUDE - - - -.- -- BONE LIVER T. BODY ' THYROID -- KIDNEY LUNG GI-LLI H-3 0.00E + 00 1.12E + 03 1.12E + 03 1.12E+ 0? 1.12E + 03 1.12E + 03 1.12E + 03 C-14 3.59E+ 04 6.73E + 03 6.73E+ 03 6.73E + 03 6.73E + 03 - 6.73E + 03 6.73 E,+ 03 CR-51 0.00E + 00 0.00E + 00 1.54E+ 02 8.55E + 01 2.43E + 01 1.70E + 04 1.08E + 03 MN-54 0.00E + 00 4.29E + 04 9.51 E + 03. 0.00E + 00 1.00E+ 04 1.58E + 06 2.29E + 04 FE-55 4.74E + 04 2.52E + 04 7.77E + 03 0.00E + 00 0.00E + 00 1.11E + 05 2.87E+ 03 FE-59 2.07E + 04 3.34E+ 04 1.67E+ 04 0.00E + 00 0.00E + 00 1.27E + 06 7.07E+ 04
~~
CO-58 0.00E + 00 1.77E + 03 3.16E + 03 0.00E + 00 0.00E+ 00 1.11E506 3.44E + D4 CO-60 0.00E + 00 1.31 E + 04 2.26E + 04 . 0.00E,+ 00 0. DOE + 00 7.07E + 06 9.62E + 04 NI-63 8.21 E + 05 4.63E + 04 2.80E+ 04 0.00E + 00 - 0.00E + 00 2.75E + 05 6.33E + 03
~ ~' , ~~i[5 Z 4.26E + 04 1.13E+b5 7.03E + 04 U.00 +00 7.145+04 9.95E + 05 1.63E + 04 \
RB-86 0.00E + 00' 1.98E + 05 1.14E+ 05 0.00E + 00 0.00E + 00 0.00E + 00 7.99E + 03 SR-89 5 99E+ 05 0.00E + 00 1.72E + 04 0.00E + 00 0.00E + 00 2.16E+06 ' 1.67E+05
^
SR-90 1.01E + 08 0.00E + 00 ~6.44
'~hdO6 d.00E+00 0.00E500 1.48E+ 07 3.43E + 05 Y-91 9.14E + 05 0.00E + 00 2.44E + 04 0.00E+00J 0.00E+00 2.63E+ 06 1.84E + 05 ZR-95 1.90E + 05 . 4.18E+ 04 3.70E + 04 0.00E + 00 5.96E + 04 2.23E + 06 6.11 E + 04
' NB-95 2.35E + 04 9.18E + 03 6.55E + 03 0.00E + 00 8.62E + 03 6.14E + 05 3.70E + 04 RU-103 2.79E + 03 0.00E + 00 1.07E + 03 0.00E + 00 7.03E + 03 6.62E + 05 4.48E + 04 RU-106 1.36E + 05 0.00E + 00 1.69E+04 . 0.00E + 00 1.84E + 05 1.43E + 07 4.29E + 05 AG-110M 1.69E + 04 1.14E + 04 9.14E + 03 0.00E + 00 2.12E + 04 5.48E+06 ' t .00E + 05 TE 125M 6.73E + 03 2.33E + 03 9.14E + 02 1.92E + 03 0.00E+ 00 4.77E + 05 3.38E + 04 TE-127M 2.49E + 04 8.55E + 03 3.02E + 03 . 6.07E + D3 6.36E+ 04 1.48E + 06 7.14E + 04 TE-129M 1.92E + 04 6.85E + 03 3.04E + 03 6.33E + 03 5.03E + 04 1.76E + 06 1.82E+ 05 l-131 4.81 E + 04 4.81 E + 04 2.73E + 04 1.62E + 07 7.88E + 04 0.00E + 00 2.84E+ 03 1-133 1.66E + 04 2.03E + 04 7.70E + 03-- 3.85E+06 ' 3.38E+04 0.60E + 00 ' 5.48E + 03 CS-134 6.51 E + 05 1.01 E + 06 2.25E + 05 0.00E + 00 '3.30E + 05 1.21E4 05 3.85E + 03 CS-136 6.51E + 04 1.71 E+ 05 1.16E+ 05 0.00E+00 ' 9.55E+04 1.46E + 04 4.18E + 03 CS-137 9.07E + 05 8.25E+ 05 1.28E+ 05 0.0GE + 00 2.82E + 05 - 1.01E + 05 3.62E + 03 BA-140 7.40E + 04 6.48E + 01 4.33E + 03 0.00E + 00 2.11E + 01 1.74E + 06 1.02E + 05 CE-141 3.92E + 04 1.95E+ 04 2.90E + 03 0.00E + 00 8.55E + 03 5.44E + 05 5.66E + 04 CE-144 6.77E + 06 2.12E + 06 3.61E + 05 0.00E + 00 1.17E + 06 1.20E + 07 3.89E + 05
~
7R343 1.85E b4 5.55E + 03 9.14E + 02 0.00E+00 3.00E + 03 4.33E +b5 9.73E + 04 ' ND-147 1.08E + 04 8.73E + 03 6.81 E + 02 0.00E + 00 4.81E + 03 3.28E + 05 8.21E + 04
- ... . -- .. ........- _=_ ..........
O 138.0 mk
1 04-23-97 09:13:44 l Number {o) Nuclear " "*$ d * *' contrd* Departmental Procedure 6610-PLN-4200.01i i
%) me# Revisaon No.
Offsite Dose Calculation Manual (ODCM) 12
' TABL'E 5.2.3 i l
Pathway Dose Factors, RI i l AGE GROUP: TEEN ' PATHWAY: INHALATION 1
~
I ORGAN DOSE FACTORS; mrem / year per Ci/m l NUCUDE _
. BONE UVER T. BODY THYROID . KIDNEY LUNG GI-LU H-3 0.00E + 00 1.27E + 03 i.27E+03 ~I.27E + 03 1.27E + 03 1.27E+ 03 1.27E + 03 l C-14 2.60E + 04 4.87E + 03 4.87E + 03 4.87E + 03 4.87E+03 - 4.87E+03 4.87E + 03 l CR-51 0.00E + 00 0.00E + 00 - 1.35E +02 7.50E + 01 3.07E + 01 2.10E + 04 3.00E + 03 MN-54 0.00E+00. 5.11E+04 6.40E+03 0.00E + 00 1.27E + 04 1.98E + 06 6.68E + 04 q FE-55 3.34E + 04 2.38E + 04 - 5.54E+03 0.00E + 00 0.00E + 00 1.24E + 05 6.39E + 03 FE-59 1.59E~
+ 04 3.70E + 04 1.43E + 04 0.00E + 00 0.00E + 00 1.53E + 06 1.78E+ 05 CO-58 0.00E + 00 2.07E+ 03 2.78E + 03 0.00E + 00 0.00E+ 00 1.34E+ 06 9.52E+ 04 l CO-60 0.00E + 00 1.51 E+ 04 1.98E + 04 0.00E + 00 0.00E + 00 8.72E + 06 2.59E+ 05 NI-63 5.80E + 05 4.34E + 04 1.98E + 04 0.00E+ 00 0.00E + 00 ' 3.07E + 05_ .42E 1
,, + 04 ZN-65 3.86E + 04 1.34E + 05 6.24 E + 04. . 0.00E + 00 8.64E + 04 1.24E + 06 4.66E + 04 ;
- RB-86 0.00E + 00 1.90E + 05 . 8.'40E + 04 0.00E + 00 0.00E + 00 0.00E+ 00 1.77E+ 04 I
* (vO) SR-89 4.34E +05 0.bOE+00 1.2SE + 04 0.00E + 00 0.00E + 00 2.42E+ 06 3.71E + 05
~
l SR-90 If0BE+08 0.00E + 00 6.68E + 06 . 0.00E + 00 0.00E + 00 1.65E + 07 7.65 +05 Y-91 6.61E + 05 0.00E + 00 1.77E + 04 0.00E + 00 0.00E + 00 2.94E + 06 4.09E + 05 ZR-95 1.46E+05 4.58E+04 3.15E + 04 0.00E + 00 ' 6.74E + 04 2.69E + 06 1.49E+ 05 NB-95 1.86E+04 .1.03E+04 5.66E + 03 'O.00E + 00 1.00E + 04 7.51E + 05 9.68E + 04 RU 103 2.10E + 03 0.00E + 00 8.96E + 02 0.00E + 00 7.43E + 03 7.83E +05 1.09E + 05 RU-106 9.84E + 04 0.00E +00 1.24E + 04 0.00E + 00 1.90E + 05 1.61 E + 07 9.60E + 05
~~ ~~
AG 110M . 1.38E + 04 1.31 E+04 7.99E + 03. 0.00E + 03 2.50E + 04 6.'75E + b6 2.73E +iS TE-125M 4.88E + 03 2.24E+ 03 6.67E + 02 1.40E + 03 ' O.00E + 00 ' 5.36E + 05 7.50E + 04 TE-127M 1.80E + 04 8.16'E + 03 2.18E + 03 4.38E+03 6.54E+04 1.66E + 06 1.59E + 05
~'~
TE 129M I.39E + 04 6.58E + 03 2.25E + 03 4.58E + 03 5.19E + 04 1.98E + 06 4.05E +bi 1131 3.54E + 04 4.91 E+ 04 2.64E + 04 1.46E + 07 8.40E + 04 - 0.00E + 00 6.49E + 03 1-133 1.22E + 04 ' 2.05E+ 04 6.22E + 03 2.92E + 06 3.59E + 04 0.00E + 00 1.03E + 04 CS-134 5.02E + 05 1.13E + 06 5.49E+05 OIO0E+ 00 3.75E'+h5 1.46E + 05 9.76E + 0E CS-136 5.15E + 04 1.94E + 05 1.37E505 0.00E+ 00 1.10E +05 1.78E + 04 1.09E + 04 CS-137 6.70E + 05 8.48E + 05 3.11 E + 05 0.00E + 00 3.04E +05 1.21 E+ 05 - 8.48E + 03 BA-140 5.47E + 04 6.70E + 01 3.52E + 03 0.00E + 00 2.28E + 01 2.03E + 06 2.29E + 05 CE-141 2.84E + 04 1.90E + 04 2.17E + 03 0.00E+00 8.88E+03 6.14E + 05 1.26E + 05 CE 144 4.89E + 06 2.02E + 06 2.62E + 05 0.00E + 00 1.21 E + 06' 1.34E + 07 8.64E + 05 PR-143 1.34E + 04 5.31E+03 6.625+ 02 0.00E500 3.09E + 03 ~ 4. 53Eli5 2.14E+ 05 i ND-147 7.86E + 03 8.56E + 03 5.13E + 02 0.00E + 00 5.02E + 03 3.72E + 05 1.82E + 05
< 139.0 mu 1
l l 04.-23-97 09:13:44. l Number n) ( Nuclear " "*didoo'ca' coa'ro'= Departmental Procedum 6610 PLN,4200.01
, v 'rrue ReviWon No.
Offsite Dose Calculation Manual (ODCM) 12 l TABLE 5.2.4 Pathway Dose Factors, R1
. AGE GROUP: ADULT PATHW'AY: INHALATION
~ ~
ORdb~DbSU FACTORS: mrem / year per pCl/m8 NUCUDE - - - - - - - - - - - - -- - - - - -- BONE UVER- T. BODY THYROID KIDNEY LUNG- GI-Lu
~
H-3 Oh0E+00 1.26E+ 03 1.26E + 03 1.26E + 03 1.26E + 03 1.26E + 03 126E + 03 C-141 1.82E + 04 . 3.41E+ 03 3.41 E + 03 3.41E + 03 ' 3.41 E + 03 3.41 E + 03 3.41E + 03 CR 0.00E + 00 0.00E + 00 1.00E + 02 5.95E + 01 ' 2.28E + 01 1.44E + 04 3.32E + 03 _ -51 __ MN-54 0.00E + 00 3.96E+04 6.30E + 03 0.00E + 00 9.84E + 03 1.40E + 06 7.74E + 04 FE-55 2.46E + 04 1.70E+ 04 3.94E + 03 0.00E + 00 ~ 0.00E + 00 7.21E + 04. 6.03E + 03 FE-59 1.18E +04 2.78E+ 04 1.06E + 04 0.00E + 00 0.00E + 00 1.02E+ 06 1.88E + 05_ CO-58 0.00E +00 1.58E+ 03 2.07E +03 0.00E + 00 0.00E +00 9.28E+05 1.06E + 05 CO-60 . 0.00E' + 00 1.15E+04 ' 1.48E+04 0.00E + 00 0.00E+ 00 5.97E + 06 2.85E + 05
' N1-63 4.32E + 05 3.14E+ 04 1.45E + 04 0.00E + 00 0.00E + 00 1.78E+ 05 1.34E + 04 1
ZN-65 3.24E + 04' 1.03E + 05 4.66E+ 04 0.00E+ 00 6.90E+ 04 8.64E+ 05 5.34E + 04 '
., RB-86 0.00E + 00 1.35E + 05 5.90E + 04 0.00E + 00 0.00E + 00 0.00E + 00 1.66E+ 04
/ SR-89 3.04E+ 05 0.00E + 00 8.72E+03 0.00E+00 0.00E + 00 1.40E. .+.06 3.50E + 05 SR-90 9.92E + 07 0.00E + 00 6.10E + 06 0.00E + 00 0.00E+ 00 9.60E + 06 7.22E + 05 Y-91 4:62E+05 0.00E+ 00 1.24E+04 0.00E+00 0.00E + 00 1.70E + 06 3.85E + 05 ZR 95 1.07E + 05 3.44E +04 2.33E + 04 0.00E +.-00 5.42E + 04 1.77E + 06 1.50E . . . . .
+ 05 __
l
\
NS-95 1,41 E + 04 7.82E *03 4.21 E + 03 0.00E + 00 7.74E + 03 5.05E + 05 1.04E + 05 RU-103 1.53E+ 03 0.00E + 00 ' 6.58E + 02 0.00E + 00 5.83E + 03 5.05E +05 1.10E + 05 RU-106 6.91E+ 04 0.00E + 00 8.72E + 03 0.00E + 00 1.34E+05 . 9.36E+06 9.12E.+ 05 AG-110M 1.08E + 04 1.00E + 04 5.94E + 03 0.00E + 00 1.97E +.04 4.63E + 06 3.02E + 05 TE-125M 3.42E + 03 1.58E + 03 4.67E + 02 1.05E + 03 1.24E + 04. 3.14E + 05 7.06E + 04 TE-127M _ _ _ _ 1.26E+04 5.77E + 03 1.57E + 03 3.29E + 03 4.58E + 04 9.60E L 1.50E + 05 _ _ TE 129M 9.76E + 03 4.67E + 03 ' 1.58E + 03 3.44E + 03 3.66E + 04. 1.16E + 06 3.83E + 05 l-131 2.52E + 04 3.58E + 04 2.05E + 04 1'.19E + 07 6.13E + 04 0.00E + 0'0 6.28E + 03 1133 8.64E+ 03 1.48E + 04 4.52E + 03 2.15E + 06 2.58E+ 04 0.00E + 00 8.88E + 03
~'
CS-134 3.73E+05 8.48E+05 7.28E + 05 0.00E + 00 2.87E + 05 9.76E + 04 1.04E + 04 CS 136 3.90E + 04 1.46E + 05 1.10E + 05 0.00E + 00 8.56E + 04 - 1.20E + 04 1.17E + 04 CS-137 4.78E + 05 - 6.21 E + 05 428E+05 0.00E +00 2.22E + 05 7.52E + 04 8.40E --= _---
+ 03 BA-140 3.90E + 04 4.90E + 01 2.57E + 03 0.00E + 00 1:67E + 01 1.27E + 06 2.18E + 05 CE-141 1.99E + 04 1.35E + 04 1.53E+ 03 0.00E + 00 6.26E + 03 3.62E + 05 1.20E4 05 CE-144 3.43E + 06 1.43E + 06 1.84E + 05 0.00E + 00 8.48E + 05 7.78E + 06 8.16E + 05 PR-143 9.36E + 03 - 3.75E + 03 4.64E + 02 0.00E + 00 2.16E + 03 2.81E + 05 2.00E + 05-ND-147 5 27E +03 6.10E + 03 3.65E +.02 0.00E + 00 3.56E + 03 2.21 E + 05 1.73E + 05
- - - - - - - - _ . _._ _ - - = = . . . . - .
f
~
140.0 _ m9
04-23-97 09:13:44
. ngg, . + .s >.-.r. . . . . . . . .
n
?
Nuclear TM Rad'o'oa'ca co""o's Departmental Procedure 6610-PLN-4200.01 .; Tme Revision No. 12 Offsite Dose Calculation Manual (ODCM)
, - l TABLE 5.3.1 -
1 Pathway Dose Factors,-R'i AGE GROUP: ALL PATHWAY: GROUND PLANE Y ORGAN DOSE FACTORSki INUCUDE --
---4 1 T. BODY- SKIN i h- -i .
H-3 0.00E + 00 0.00E + 00 ' l C-14 0.00E + 00 0.00E + 00 ' 2 - CR-51 4.65E + 06 5.50E + 06
'l MN-54 . 1.39E + 09 1.62E + 09
' 0.00E + 00 0.00E + 00 FE-55 i FE-59 2.73E + 08 ' 3.21E+ 08 I F---- 1 CO-58 3.79E + 08 4.44E + 08 l
, CO-60 2.15E + 10 2.53E +10 ;
NI-63 0.00E + 00 0.00E + 00 l , F-- - -l 4 ZN-65 7.47E + 08 8.59E + 08 RB-86 8.97E+ 06 1.03E + 07 b' p.SR-89 2.16E+ 04 2.51E + 04 ( ,
-[-
v SR-90 0.00E + 00 0.00E + 00 , Y-91 1.07E + 06 1.21 E + 06 ' ZR-95 2.45E + 08 2.84E 4 08 4 NB-95 1,37E + 08 1.61E+ 08 i ' RU-103 1.08E + 08 1.26E + 08 l RU 106 4.22E + 08 ,
- p. 5.06E + 08 {l
- _ = .
[ AG-110M 3.44E + 09 4.01E + 09 l TE-125M 1.55E + 06 2,13E + 06
. l TE-127M 9.17E + 04 1.08E+05 l F
TE-129M 1.98E + 07 2.31 E + 071, 1-131 1.72E + 07 2.09E+071 - l-133 2.45E +.06 2.98E+ 06 I ' F--- -l l CS-134 6.86E+09 880E+69 CS-136 1.51E + 08 1.71E + 08
. CS-137 '1.03E + 10 1.20E + 10 F- - - -I
, l: BA-140 2.06E + 07 2.36E+ 07 j - CE 141 1.37E + 07 1.54E+ 07 i 8.05E+ 07 I pCE-144 __ 6.96E + 07
. 4 PR-143 0.00E + 00 0.00E + 00 ND-147 8.39E +06 1.01E + 07
. L. -
. ......a i
- m 2mrem / year per pCi/sec.
9 . 141.0 , ms.
04-23'97 09:13:44 Number o Nuclear " ""di 'oa'o*' c "" Departmental Procedure 6610-PLN-4200.01
,4 wJ .. - . .
' Offsite Dose Calculation Manual (ODCM) 124
- TABLE 5.4.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MILK . . ....
NUCUDE BONE LIVER T. BODY THYROID K1DNEY LUNG GI-L1.1 H-3 0.00E+ 00 2.38E + 03 2.38E + 03 2.38E + 03 2.38E + 03 2.38E + 03 2.38E + 03 C-14 2.34Et09 5.00E'+08 5.00E + 08 . 5.00E + 08 5'.00E + 08 5.00E + 08 5.00E + 08 CR-51 0.00E + 00 0.00E + 00 1.61E + 05 1.05E + 05 2.30E + 04 ' 2.05E + 05 4.70E + 06 MN-54 0.00E+ 00 3.91 E + 07 8.85E + 06 0.00E + 00 8.65E + 06 0.00E + 00 1.43E + 07 FE-55 1.35E + 08 8.74E + 07 2.34E+ 07 0.00E+ 00 0.00E + 00 4.27E + 07 1.11E+ 07 FE-59 - 2.25E + 08 3.93E + 08 1.55E + 08 0.00E. +. .00 0.00E + 00 1.16E
+ 08 1.88E.
+ 0B CO-58 0 .00E + 00 2.43E+ 07 6.06E + 07 0.00E +00 0.00E + 00 0.00E + 00 6.05E + 07 CO-60 0.00E+00 8.83E+ 07 ' 2.08E+08 0.00E+ 00 0.00E + 00 0.00E + 00 2.10E+ 08
. NI-63 3.50E + 10 2.16E + 09 1.21E + 09 0.00E+ 00 0.00E + 00 0.00E + 00 1.08E + 08 ZN45 5.56E + 09 1.91 E + 10. 8.79E + 09 0.00E + 00 9.24E + 09 0.00E + 00 1.61 E + 10
'RB-86 0.00E + 00 2.23E + 10 - 1.10E + 10 0.00E+ 00 0.00E'+ 00 0.00E+00 5.70E+08 SR-89 1.26E + 10 0.00E + 00 .
3.62E + 08 0.00E+00 0.00E+00 0.00E+00 2.59E + 08
\
SR-90 1.22E + 11 0.00E + 00 3.10E+ 10 0.00E + 00 - 0.00E+ 00 0.00E+ 00 1.52E+ 09 Y-91 T34E+04 0.00E + 00 1.95E + 03 0.00E+ 00 0.00E + 00 . 0.00E + 00 5.26E + 06 ZR-95. 6.81 E + 03 1.6GE + 03 1.18E + 03 0.00E+ 00 1.79E + 03 0.00E + 00 8.27E + 05 . NS-95 5.94E + 05 2.45E + 05 1.41E + 05 0.00E + 00 1.75E + 05 0.00E+ 00 2.07E + 08
, RU-103 8.68E + 03 0.00E+00 ' 2.90E+03 0.00E + 00 1.81 E + 04 0.00E + 00 1.06E + 05 RU-106 1.91 E .+. 05 0.00E .. + 00 2.38E +. .04 .
0.00E + 00 2.25E +05 0.00E + 00 1.45E + 06 AG 110M 3.86E + 08 ' 2.82E + 08 1.87E+ 08 0.00E + 00 4.03E + 08 0.00E + 00 1.46E + 10 TE-125M 1.51 E + 08 5.05E + 07 2.04E + 07 . 5.08E + 07 0.00E + 00 0.00E + 00 7.19E + 07 TE-127M '4.22E + 08 1.40E + 08 5.10E+07 1.22E + 08 1.04E + 09 0.00E + 00 1.70E + 08 5129M 5.58E+08 1.91 E+ 08 8.'59E + 07 2.14E + 08 1.39E + 09 0.00E + 00 3.33E + 08 l-131 2.72E + 09 3.21 E + 09 1.41 E + 09 1.05E + 12 3.75E + 09 0.00E + 00 1.15E + 08 1133 3.63E + 07 5.29E + 07. 1.55E + 07 9.62E + 09 6.22E + 07 0.00E + 00 8.96E + 06 CS-134 3.65E + 10 6.81E + 10 6.88Eh 09 0.00E + 00 1.75E +l0 7.19E+ 09 1.85E+ 08 CS-136 1.98E + 09. 5.83E + 09 2.18E + 09' O.00E + 00 2.32E + 09 4.75E + 08 8.85E + 07 CS-137 5.15E + 10 6.03E + 10 4.27E + 09 0.00E + 00 ' 1.62E + 10 . 6.55E + 09 1.89E + 08 BA-140 2.42E + 08 ' 2.42E + 05 1.25E + 07 0.00E + 00 5.75E + 04 1.49E + 05 5.94E + 07 CE-141 4.34E + 04 2.65E + 04 3.12E + 03 0.00E + 00 8.17E + 03 0.00E + 00 1.37E + 07 CE-144 2.33E + 06 9.53E + 05 1.30E +05 0.00E + 00 3.85E + 05 0.00E + 00 1.34E + 08 PR-143 1.49E +03 5.56E + 02 7.37E + 01 0.00E +00 2.07E + 02 0.00E + 00 7.84E + 05 ND-147 8.83E + 02 9.07E + 02 5.55E + 01 'O.00E + 00 3.50E+ 02 0.00E + 00 5.75E ._
+ 05
= - - -. .. .
e . 142.0 me !
l l 04-23-97 09:13:44 , Number j , A ( 4 Nuclear W Rad!@gd Cmtr$ Departmental Procedure 6610-PLN-4200.01 True Revissori No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.4 2 Pathway Dose Factors, Ri - AGE GROUP: CHILD PATHWAY: GRASS-COW-MILK .- - - . ORGAN DOSE FACTORS; m2 - mrem / year per pCi/sec
= =----
NUCUDE - - - BONE UVER T. BODY THYROID KIDNEY LUNG GI-LLI . H3 0.00E + 00 1.57E + 03 1.57E + 03 1.57E + 03 1.57E + 03 1.57E + 03 1.57E+ 03 C-14 1.20E + 09 2.39E + 08 . 2.39E+ 08 2.39E + 08 2.39E+ 08 2.39E+ 08 2.39E + 08 CR-51 0.00E + 00 0.00E+ 00 1.02E + 05 5.66E + 04 1.54E + 04 1.03E + 05 5.40E+_ 06 . .. MN-54 0.00E + 00 2.10E + 07 5.59E+06 0.00E + D0 5.89E + 06' 0.00E + 00 1.76E + 07 FE-55 1.12E + 08 5.94E +07 1.84E+ 07 0.00E + 00 0.00E + 00 3.36E + 07. 1.10E + 07 FE-59 1.20E + 08 1.95E + 08 9.70E + 07 0.00E + 00 0.00E + 00 5.65E + 07 2.03E + 08 CO-58 0.00E + 00 1.21 E+ 07 3.72E + 07 0.00E + 00 0.00E + 00 0.00E + 00 7.08E+ 07 C040 0.00E+ 00 4.32E + 07 1.27E+ 08 0.00E + 00 0.00E + 00 0.00E + 00 2.39E + 08 Ni-63 . 2.97E + 10 1.59E + 09 1.01E + 09 0.00E + 00 0.00E + 00 0.00E + 00 1.07E + 08 ZN-65 4.14E + 09 1.10E+ 10 6.86E + 09 0.00E+ 00 6.95E + 09 0.00E + 00 1.94E + 09
- RB.86 0.00E + 00 8.78E + 09 . 5.40E + 09 ' O.00E + 00 0.00E + 00 0.00E 400 5.65E + 08
[ s SR-89 6.63E + 09 0.00E + 00 1.89E + 08 0.00E + 00 0.00E + 00 0.00E+ 00 2.57E =.... + 08 L SR-90 1.12E + 11 0.00E + 00 2.84E +10 0.00E + 00 0.00E + 00 0.00E + 00 1.51E + 09 Y-91 3.91E + 04 0.00E +00 1.05E +03 0.00E + 00 0.00E + 00 0.00E + 00 5.21E+ 06 ZR-95. 3.84E + 03 8.43E + 02 7.51E + 02 0.00E + 00 1.21 E + 03 0.00E + 00 8.80E4 05 , NB-95 3.18E + 05 1.24E + 05 8.86E + 04 0.00E + 00 1.16E + 05 0.00E + 00 2.29E + 08 RU-103 4.29E + 03 0.00E + 00 1.65E + 03 0.00E + 00 1.08E + 04 0.00E + 00 1.11E + 05 RU-106 9 25E + 04 0.00E + 00 1.15E + 04 0.00E + 00 1.25E + 05 0.00E + 00 1.44E......
+ 06 AG 110f4 2.09E + 08 1.41E + 08 1.13E + 08 0.00E + 00 2.63E + 08 0.00E + 00 1.68E +10 ,
TE-125M 7.39E + 07 2.00E+ 07 9.85E + 06 2.07E+07. 0.00E+00 0.00E + 00 7.13E + 07 TE-127M 2.08E + 08 . 5.61 E+ 07 2.47E + 07 4.98E + 07 5.94E + 08 0.00E + 00 1.69E + 08 TE-129M 2 72E + 08 7.59E+07 722E+07 8.76E + 07 .7.98E + 08 0.00E + 00 3.31E + 08 l-131 1.31E + 09 1.31 E + 09 7.46E + 08 4.34E + 11 ' 2.16E + 09 0.00E + 00 . 1.17E + 08 l1 _.,33 1.72E + 07 2.13E ......
+ 07 8.05E + 06 3.95E+..
09 3.55E + 07 0.00E + 00 8.58E
+ 06 CS-134 2.27E + 10 3.72E + 10 7.85E + 09 0.00E + 00 1.15E + 10 ,4.14E + 09 2 01E + 08 CS-136 1.01 E + 09 2.79E + 09. 1.80E + 09 0.00E + 00 1.49E+ 09 2.21E + 08 9.80E + 07 '
CS-137 3.23E + 10 3.09E + 10 4.56E + 09 0.00E + 00 1.01 E + 10 3.62E + 09 1.93E + 08
~ ~~~
BA-140 1.18E + 08 1.03E + 05 6.86E + 06 0.00E + 00 3.35E + 04 6.14E + 04 5.96E + 07 CE-141 2.19E + 04 1.09E + 04 1.62E + 03 0.00EiOO 4.79E+03. 0.00E+ 00 1.36E+ 07 , CE-144 1.63E+06 . 5.09E+05 0.00E + 00 2.82E + 05 0.00E + 00 1.33E + 08 8.67E + 04......__... - PR-143 7.18E + 02 2.16E + 02 3.56E + 01 . 0.00E+ 00 1.17E+ 02 0.00E + 00 .7.75E + 05 ND-147 4.45E + 02 3.61 E + 02 2.79E + 01 0.00E + 00 1.98E + 02 0.00E + 00 5.71 E + 05 i l V 143.0 mm I I l l
04-23-97 09:13:44 Number Nuclear' " "a* ' S ca' i Departmental Procedure
*o'$ -
. 6610 PLN-4200.01
}o}
b Tine , Revnion No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.4.3 l l Pathway Dose Factors, R1 l AGE GROUP: TEEN , PATHWAY:' GRASS-COW-MILK
~' ~~ ~ ~~ ~
ORGAN DOSE FACThlS; m ,"mIe~m~/ 2- yea 7p~er pCl/sec.
~
BONE LIV R T. BODY [ THYROID KIDNE LUNG,,~~ Gl
~[L H-3 0.00E + 00 9.93E + 02 9.93E + 02 9.93E + 02 9.93E + 02 9.93E + 02 9.93E + 02 C-14 4.86E + 08. 9.78E + 07 9.73E +07 9.73E+ 07 9.73E + 07 9.73E + 07 9.73E + 07 j CR-51 0.00E + 00 0.00E+00 ~
4.99E+04
~ ~~
2.77E+ 04 1.09E ~
+ ~04 7.13E + 04 8.39E + 06 '
MN5 0.00E + 00 1.40E + 0h~~2.78E + 06 0.00E + 00 4.19E + 06 0.00E + 00 2.88E+ 07 FE-55 4.46E + 07 3.16E + 07 7.37E +06 0.00E + 00 0.00E + 002.01 E + 07 1.37E + 07 FE-59 5.19E + 07 1.21E + 08 4.68E + 07 0.00E + 00 0.00E + 00 3.82E + 07 2.86E + 08 . CO-58 0.00E + 00 7.94E + 06 1.83E + 07 0.00E + 00 0.00E + 00 0.00E+ 00 1.10E + 08 CO-60 0.00E + 002.78E + 07 6.27E + 07 0.00E + 00 0.00E + 00 0.00E + 00 3.62E + 08
)
NI-63 1.18E + 10 8.36E + 08 4.01 E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.33E + 08 ZN-65 2.11 E + 09 7.32E + 09 3.42E + 09 0.00E + 00 4.69E + 09 0.00E + 00 3.10E + 09 l 0.00E + 00 4.73E + 09 2.22E + 09 0.00E + 00 0.00E + 00' ' O.00E + 00 7.00E + 08 9 . RB-86 SR
.-89 SR-90 Y-91 2.68E + 09 0.00E._ + 00 7.67E + 07 0.00E ..
+ 00 0.00E .+. 00 6.62E + 10 0.00E+00 1.63E+10 0.00E + 00 0.00E+00 ' O.00E+00 :1.86E + 09 0.00E + 00 1.58E + 04 0.00E + 00 4.24E + 02 0.00E+00 . 0.00E+00 0.00E + 00 6.48E + 06 3.19E + 08 1
ZR-95 1.65E + 03 5.21 E + 02 3.58E + 02 0.00E + 00 7.65E + 02 0.00E +00 .1.20E+06 NB-95 1.41 E + 05 7.82E + 04 4.30E + 04 0.00E +00 7.58E + 04 0.00E + 00 3.34E+ 08 . RU-103 1.81E + 03 0.00E + 00 7.75E + 02 0.00E + 00 6.39E + 03 0.00E + 00 1.51 E + 05
, RU-106 3.76E + 04 0.00E + 00 4.73E + 03 0.00E + 00 7.24E + 04 .0.00E + 00 1.80E + 06
~~ ~
' AG-110M 9.f 4E + 07 9.12E + 07 5.55E + 07 0.00E + 00 1.74E + 08 0.00E + 00 2.56E + 10 -
TE-125M 3.01 E + 07 1.08E+ 07 ' 4.02E+06 8.40E + 06 0.00E + 00 0.00E + 00 8.87E + 07 TE-127M 8.45E + 07 ' 3.00E + 07 1.00E + 07 2.01E + 07 3.42E+ 08 0.00E + 00 2.11E + 08 TE 129M 1.10E + 08 4.09E + 07 1.74E + 07 3.56E+07 4.61E+08 0.00E + 00 4.14E + 08
~
l-131 5.38E+08 7.53E + 08 4.05E + 08 2.20E+ 11 1.30E + 09 0.00E + 00 1.49E + 08 l-133 7.08E+ 06 1.20E + 07 3.66E + 06 1.68E+ 09 2.11E+ 07 0.00E + 00 9.09E + 06 CS-134 9.83E + 09 2.31 E +10 1.07E + 10 0.00E + 00 7.35E + 09 2.81E + 09 2.88E + 08 CS-136 - 4.49E + 08 1.77E + 09 1 19E + 09 0.00E + 00 9.63E + 08 1.52E + 08 1.42E + 08 CS-137 1.34E + 10 1.78E + 10 6.21E + 09 0.00E ~~
+ 00 6.06E
~ ~~~
+ 09 2.36E + 09 2.54E + 08 BA-140 4.87E + 07 5.97E + 04 3.14E + 06 h~00N +00 2.02E + 04 4.01E + 04 7.51E + 0h" CE-141 8.89E + 03 5.94E + 03 6.82E + 02 0.00E + 00 2.80E + 03 ' O.00E + 00 1.70E + 07 CE-144 6.59E + 05 2.73E + 05 3.54E + 04 0.00E + 00 1.63E + 05 0.00E + 00 1.66E + 08
~
. PR 143 2.90E + 02 1.16E + 02 1.44E + 01 0.00E + 00 6.73E + 01 0.00E + 00 9.55E + 05 ND 147 1.81 E + 02 .1.97E + 02 1.18E + 01 0.00E + 00 1.16E + 02' O.00E + 00 7.12E + 05 8
144.0 me.
04-23-97 09:13:44 . Number (o 4 Nuclear. '"' aadio'ooica' coatro'$ Departrnental Procedure 6610-PLN-4200.01 Tstle Revision No. Offsite Dose Calculation Manual (ODCM) 12-l
. l TABLE 5.4.4 Pathway Dose Factors, Ri AGE GRDUP: ADULT - PATHWAY: GRASS-COW-MILK
~~ ~~ ~ ~ ~
ORGAN DOSE FACTORS; m2 ( mrem / year per pCl/sec NUCLlDE - - - - BONE UVER T. BODY THYROID KIDNEY Gt
.-- LUNG... ... . ...-LU .
H-3 0.00E + 00' 7.62E + 02 7.62E + 02 7.62E + 02 7.62E + 02 7.62E+ 02 7.62E + 02 i C-14 2.63E 4 08 5.26E+07 5.26E+07 5.26E + 07 5.26E + 07 5.26E+07 5.26E + 07 l l CR-51 0.00E + 00 0.00E + 00 2.85E + 04 1.70E + 04 6.28E + 03 3.78E + 04 7.17E + 06 IdN-54 U.00E+ 00 8.40E + 06 1.60E+ 06 0.00E + 00 2.50E + 06 0.00E + 00 2.57E + 07 FE-55 2.51E + 07 1.73E + 07 4.04E + 06 0.00E +00 0.00E + 00 9.66E + 06 9.93E + 06 , FE;59 2.97E + 07
. - - 6.97E + 07- _ _ _ _ _ ' 2.67E + 07 0.00E + 00 0.00E + 00 1.95E +_. 07 2.31c+69 CO-58 0.00E + 00 ~ 4.71 E + 06 1.05E + 07 0.00E + 00 0.00E + 00 0.00E+ 00 9.54Et 07 CO-60 0.00E + 00 1.64E + 07 3.61 E + 07 0.00E + 00 0.00E + 00 0.00E + 00 3.08E + 08 N143 6.72E+ 09 4.65E + 08 2.25E + ~
08 0.00E + 00 0.00E + 00 0.00E + 00 9.71E ~~
+ 07
, ZN45 1.37E + 09 4.36E +[)9 1.97E+09 - 0.00h+00 2.91 E + 09 0.00E + 00 2.74E+ 09 m' . RB-86 0 00E +00 2.59E + 09 1.21E + 09 0.00E + 00 0.00E + 00 0.00E+00. 5.10E+08 SR-89 1.45E+09 ' O.00E400 4.16E+ 07 0.00E +~ 00 0.00E + 00 0.00E+ 00 2.32E + 08~
~
\ SR-90 E.67E + 10 b.00E+ 00 1.15E + 10 0.00E + 00 0.00E + 00 0.00E + 00 1.35E + 09 .
Y-91 8.57E+ 03 0.00E + 00 2.29E + 02 0.00E + 00 0.00E +00 0.00E + 00 4.72E + 06 I ZR-95 9.41 E + 02 3.02E + 02 2.04E + 02 0.00E + 00 4.74E
+02 0.00E+...00 9.57E._.+ .05 NB-95 8.24E + 04 4.58E + 04 2.46E + 04 0.00E + 00 4.53E+04 . 0.00E+00 2.78E + 08
' RU-103 1.02E + 03 0.00E+00 ~ 4.38E+02 0.00E + 00 3'.88E + 03 0.00E + 00 1.19E + 05 RU-106 2.04E + 04 0.00E + 00 2.58E + 03 0.00E + 00 3.93E + 04 0.00E + 00' 1.32E + 06~ .
~
~I AG.110M $.81E+ 07 ' 5.38E A 07 3.19E + 07 ' ' O.00E + 00 1.06E + 08 0.00E+0d 2.19E+IO TE-125M 1.63E + 07 5.89E + 06 2.18E + 06 4.89E + 06 6.61 E + 07 0.00E + 00 6.49E + 07 TE-127M . 4.57E + 07 1.63E + 07 5.57E + 06 1.17E + 07 1.86E + 08 0.00E + 00 1.53E + 08 TE-129M 6.01 E + 07 2.24E + 07 9.51E + 06 2.06E + 07 2.51E + 08 0.00E + 00 3.02E + 08 I l.131 2.96E + 08 4.23E + 08 2.42E + 08 1.39E + 11 7.25E + 08 0.00E + 00 1.12E + 08 l-133 3.87E + 06 6.73E + 06 2.05E + 06 9.88E + 08 1.17E + 07 0.00E + 00 6.04E + 06 i CS-134 5.64E + 09 1.34E A 10 1.10E A10 0.00E + 00 4.34E+ 09 1.44EE 09 2.35E + 08 CS-136 2.63E + 08 1.04E + 09 7.48E + 08 0.00E + 00 5.78E+08 7.92E+ 07 1.18E + 08 CS-137 7.37E + 09l 1.01 E + 10 6.60E + 09 0.00E + 00 3.42E + 09 1,14E + 09 1.95E + 08 BA-140 2.69E + 07 3.38E + 04 1.76E + 06 0.00E + 00 1.15E + 04 1.94E + 04 5.54E +07 CE-141 4.64E + 03 3.27E + 03 3.71 E + 02 0.00E + 00 1.52E + 03 0.00E + 00 1.25E + 07 CE 144 3.57E + 05 1.49E + 05 1.92E + 04 0.00E....+ 00 8.85E + 04 0.00E +..-00 1.21E + 08 PR-143 1.57E + 02 6.32E + 01 7.81E + 00 0.00E + 00 3.65E + 01 0.00E + 00 6.90E + 05 ND-147 9.40E + 01 1.09E+ 02 6.50E + 00 - 0.00E + 00 6.35E + 01 0.00E + 00 5.22E +0S 9
V 145.0 me
04-23-97 09:13:44 Number Raddogkal Controls
/ (UClear Departmental Procedura 6610-PLN-4200.01
(' Revision No. Titf4 Offsite Dose Calculation Manual (ODCM) 12 l TABLE 5.5.1 l l r Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK ~ ORGAN DOSE FACTORS; rn8 - mrem / year per pCl/sec NUCLIDE BONE LIVER ' T. BODY THYROID KIDNEY 1.UNG GI-LLI H-3 0.00E + 00 4.86E + 03 4.86E + 03 ' 4.86E + 03 4.86E + 03 4.86E503 4.86E + 03 C-14 2.34E + 09 5.00E +08 5.00E+08 5.00E+08 5.00E + 08 5.00E + 08 5.00E + 08 i CR 0.00E + 00, 0.00E + 00 1.94E + 04 1.26E + 04 2.76E + 03 2.46E+ 04 5.64E + 05 MN-54 0.00E + 00 4.68E + 06 1.06E + 06 0.00E+00 ' 1.04E+06 0.00E +00 1.72E + 06 FE-55 1.76E + 06 1.? 4E + 06 3.03E + 05 0.00E+00 ' O.00E+ 00 5.55E + 05 1.44E + 05 FE-59 2.92E + 06 5.10E+06 2.01 E + 06 0.00E + 00 0.00E + 00 1.51E + 06 2.44E + 06 CO-58 0.00E + 00 2.91 E + 06 7.26E + 06 0.00E + 00 0.00E + 00 0.00E + 00 7.25E + 06 CO-60 0.00E + 00 .1.06E +07 2.50E + 07 0.00E + 00 0.00E + 00 0.00E ^ 06 2.52E + 07 l NI-63 4.19E + 09 2.59E 408 1.46E + 08 0.00E + 00 0.00E + 0L 0.00E4~ 00
- 1.29E+07~
~
ZN 65 6.67E + 08 2.29E +b9~5.~055+~09 0.00E50b 1.11E+39 0.00E +bb~I.935+ b9 l RB-86 0.00E + 00 2.67E + 09 1.32E + 09 0.00E + 00 0.00E + 00 0'.00E + 00 6.83E + 07
\ 2.65E + 10'. 0.00E+ 00 7.59E + 08 0.00E + 00 0.00E + 00 0.00E + 00 5.44E + 08
(/.s
.V)
- SR-89 SR-90 2.55E + 11 0.00F + 00 6.50E + 10 0.00E + 00 0.00E + 00 0.00E + 00 3.19E + 09 Y-91 8.80E + 03 0.00E + 00 2.34E + 02 0.00E+ 00 0.00E + 00 0.00E + 00 6.31E + 05 ZR-95 8.17E + 02 1.99E _.
+ 02 1.41E + 02 0.00E .___
+ 00 2.15E+02 0.00E+00 9.91E + 04 n.- . ._
NB-95 7.13E + 04 2.93E + 04 1.70E + 04 0.00E + 00 2.10E + 04 0.00E + 00 2.48E + 07 RU 103 1.04E+03 . 0.00E+00 3.48E + 02 0.00E + 00~ 2.17E + 03 0.00E + 00 1.27E + 04 RU-106 2.28E+ 04 -. 0.00E + 00 2.85E . +
. .03
. . 0.00E + 00 ' .2.70E + ._04 0.00E + 00 1.73E + 05 AG-110M 4.63E + 07 3.38E + 07 2.24E + 07 0.00E + 00 - 4.84E + 07 0.00E + 00 1.75E +09 TE-125M 1.01E + 07 6.05E + 06 2.45E + 06 6.09E + 06 0.00E + 00 0.00E + 00 8.62E + 06 TE-127M 5.06E+ 07 1.68E + 07 6.12E+06 1.46E+ 07 1.24E
+ 08 0.00E
+a.00 2.04E + 07 TE-129M 6.69E + 07 2.29E + 07 1.03E + 07 2.57E+07 1.67E+08 0.00E + 00 3.99E + 07 l-131 3.27E+ 09 3.85E+09 1.69E + 09 1.27E + 12 4.50E + 09 0.00E + 00 1.37E + 08 l133 4.36E+ 07 6.35E+ 07 1.86E+ 07 1.15E + 10 7.46E + 07 0.00E -- _
+ 00 1.07E+ 07
. CS-134 1.09E +11 2.04E + 11 2.06E + 10 0.00E + 00 5.26E + 10 2.15E + 10 5.55E + 08 CS-136 5.94E + 09 1.75E + 10 6.52E + 09 0.00E+ 00 6.96E + 09 1.42E + 09 2.65E + 08
~
CS-137 1.54E + 11 1.81 E + 11 1.28E + 10 0.00E + 00 4.85E+ 10 1.96E + 10 . 5.65E + 05 BA-140 2.90E + n7 2.90E + 04 1.50E + 06 0.00E + 00 6.89E + 03 1.78E + 04 7.13E + 06 CE-141 5.21 E + 03' 3.18E + 03 3.74E + 02 0.00E + 00 9.79E + 02 0.00E + 00 1.64E + 06 CE-144 ' 2.79E + 05 1.14E + 05 1.56E ~+ 04 0.00E + 00 4.62E + 04 0.00E + 00 1.60E + 07 PR-143 ~I.78E + 02 6.66E +b1 8.83E + 00 0.00E + 00 2.48E + 01 0.00E + 00 9.40E+ 04 ND-147 1.06E + 02 1.09E + 02 6.66E + 00 0.00E + 00 4.19E + 01 0.00E + 00 6.89E + 04 t 146.0 me r o
04-23-97.09:13:44 Number Nuclear " Raeo'*^' co*of$ o) ( V me Departmental Procedure 6610-PLN-4200.01 Revson No. l l Offsite Dose Calculation Manual (ODCM) 12-TABLE 5.5.2
. Pathway Dose' Factors, Ri AGE GROUP: CHILD' 77.THWAY: GRASS-GOAT-Mli K 2
, ORGAN DOSE FACTOPS; m - mrem / year per pCl/sec NUCUDE - - - - - - - - --- - -
----r-BONE LIVER' T. BODY THYROID K!DNEY e LUNG Gl-LLI H-3 0.00E + 00 3.20E + 03 3.20E + 03 3.20E +03 ' 3.20E + 03 3.20E + 03 3.20E+ 03 C 1.20E + 09 2.39E+08 ' 2.39E+08 2.39E + 08 2.39E 408 2.39E + 08 2.39E + 08
'CR41 0.00E + 00 0.00E + 00 1.22E +~ 04 6.78E + 03 1.85E + 03 1.24E + 04 6.48E + 05 I l
MN-54 0.00E + 00 2.52E + 06 6.71 E + 05 b.00E+00 7.06E + 05 b~00E+00 2.11E+ 06 FE-55 1.45E +06 7.71E + 05 2.39E + 05 0.00E+ 00 0.00E + 00 4'.36E + 05 1.43E + 05 FE-59 1.56E + 06 2.53E + 06 1.26E+ 06 0.00E+00 0.00E +00 7.34E + 05 2.64E + 06 CO-58 b.00E +00 1.46E+06 _ 4.46E+ 06 0.00E + 00 0.00E+ 00 0.00E + 00 8.49E+06 ! CO-60 ' O.00E + 00 5.185+06 1.53E + 07 0.00E+ 00 0.00E + 00 0.00E + 00 2.87E+ 07 NI43 3.56E + 09 1.91E + 08 1.21E + 08 0.00E ~
+ 00 0.00E + 00 ~
0.00E + 00 ' 1.28E ~
+ 07
~
ZN-65 4.96E+ 08 1.32E + 09 8.22E+ b'8 UIO0E+00 8.33E + 08 0.00E + 00 2.32E + 08 g RB46 0.00.E + 00 1.05E+ 09 6.47E + 08 0.00E'+ 00 0.00E + 00 0.00E + 00 6.77E + 07 SR-89 1.39E + 10 0.00E+ 00 3.97E + 08 0.00E + 00 0.00E + 00 0.00E+ 00 5.39E + 08 D} i ~
. SR-90 Y-91
~
2.35E +11
~
0.00E+00 5[95E+10 b.~00E+ 00 0.00E + 00 0.00E + 00 3.16E+ 09 4.69E + 03 0.00E + 00 1.25E + 02 0.00E + 00 0.00E + 00 0.00E + 00 6.24E+ 05
~ ~
' ~
ZR-95 4.60E + 02 1.01E + 02 9.00E + 01 0.00E + 00 1.45E + 02 0.00E + 00 1.05E + 05 NB-95 3.82E + 04 1.49E + 04 1.06E+ 04 0.00E + 00 1.40E + 04 0.00E + 00 2.75E + 07 RU-103 5.14E + 02 0.00E + 00 1.98E + 02 0.00E + 00 1.29E + 03 0.00E + 00 1.33E + 04 RU-106 1.11E+ 04 0.00E+ 00 1.38E+ 03 0.00E + 00 1.50E + 04 0.00E+ 00 1.73E +05 i AG 110M 2.51 E + 07 1.69E + 07 1.35E+ 07 0.00E + 00 . 3.15E + J7 0.00E + 00 2.01 E + 09 TE-125M 8.86E + 06 2.40E+ 06 1.18E + 06 2.49E + 06 0.00E + 00 0.00E + 00 8.55E + 06 , . TE-127M 2.50E+ 07 6.72E + 06 2.96E+06 5.97E + 06 7.12E + 07 0.00E + 00 2.02E + 07 TE-129M 3.26E + 07 . 9.10E + 06 5.06E + 06 1.05E + 07 9.56E + 07 0.00E + 00 3.97E + 07 l-131 1.57E + 09 . 1.57E + 09 8.95E + 08 . 5.21 E + 11 . 2.58E + 09 . 0.00E + 00 1.40E + 08 l-133 2.06E + 07 2.55E+ 07 9.66E + 06 4.74E + 09 4.25E + 07 0.00E + 00 1.03.E .....+ 07 CS-134 6.80E + 10 1.12E + 11 2.35E + 10 0.00E + 00 3.46E + 10 1.24E + 10 6.01 E+ 08 CS-136 3.04E + 09 8.36E + 09 ' 5.41 E +09 0.00E + 00 ' 4.45E + 09 6.64E + 08 2.94E + 08 CS-137 9.68E + 10 9.26E + 10 1.37E+ 10 0.00E + 00 3.02E + 10 ' 1.09E + 10 5.80E+08
~~ ~ ~
BA-140 1.41 E + 07 1.24E + 04 8.23E+ 05 0.00E + 00 4.02E + 03 7.37E + 03 7.15E+ 06 CE-141 2.63E + 03 1.31 E + 03 1.95E + 02 0.00E + 00 5.74E + 02 0.00E+ 00 1.63E + 06 CE-144 1.95E + 05 6.11E + 04 ' 1.04E + 04 0.00E'+ 00 3.38E + 04 0.00E + 00 1.59E + 07 PR-143 8.61 E + 01 ' 2.59E + 01 4.27E + 00 0.00E + 00 1,40E + 01 0.00E +00 9.2IiE + 04~~~ ND-147 5.34E + 01 4.33E + 01 3.35E + 00 0.00E + 00 2.37E 401 0.00E + 00 6.85E + 04 1 147.0 ms. 1
04-23-97 09:13:44 Number (o Nuclear " "ad*ood co"o'* ' Departmental Procedure 6610-PLN 4200.01 ] bj Trtle , Revision No. Offsite Dose Calculation Manual (ODCM) 12
! TABLE 5.5.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK .
~ ~~
ORGAN DO5E FACTORS; 2m m$r$/ year per pCl/sec -
- NUCL'E -
, ' BONE LtVER T. BODY THYROtD KIDNEY LUNG Gt-LLI H-3 O.00E + 00 2.04E + 03 2.04E + 03 2.04E + 03 2.04E + 03~ 2.04E + 03 2.04E + 03 C-14 4.86E + 08 9.72E + 07 9.72E+07 - 9.72E+07 9.72E + 07 9.72E + 07 9.72E + 07 CR-51 0.00E + 00 0.00E+ 00 5.99E +03 3.33E+ 03 1.31 E + 03 8.55E + 03 1.01E + 06 1
MN-54 0.00E + 00 1.68E +06 3.34E + 05 0.00E + 00 5.02E+05 0.00E + 00 3.45E + 06 FE-55 5.79E + 05 4.11 E+ 05 9.58E + 04 0.00E + 00 0.00E + 00 2.61 E + 05 1.78E + 05 FE-59 6.74E + 05 1.57E+ 06 6.08E + 05 0.00E + 00 0.00E+00 ' 4.96E+05 3.72E + 06 CO-58 0.00E + 00 9.53E + 05 2.20E + 06 0.00E + 00 0.00E+ 00 0.00E + 00 1.31 E + 07 CO-60 0.00E + 00 3.34E + 06 7.52E + 06 0.00E,+ 00 0.00E + 00 0.00E + 00 4.35E + 07 N143 1.42E + 09 1.00E + 08 4.81 E + 07 0.00E+ 00 0.00E400 0.00E + 00 1.60E + 07 < ZN45 2.53E+ 08 8.78E + 08 4.10E + 08 0.00E + 00 5.62E+08 0.00E+ 00 3.72E + 0S
% RB-86 0.00E + 00 5.67E+08 ' 2.67E + 08 0.00E + 00 0.00E + 00 0.00E + 00 8.40E + 07 SR-89 5.62E+09 0.00E + 00' 1.61E + 08 0.00E + 00 0.00E + 00 0.00E+00 ' 6.69E+0S s
' SR-90 1.39E + 11 0.00E + 00 .3.43E + 10 0.00E + 00 0.00E + 00 0.00E+00 3.90E+09 Y-91 1.90E +03 0.00E + 00 5.09E + 01 0.00E+ 00 0.00E + 00 0.00E + 00 7.78E + 05 ZR-95 1.98E + 02 6.25E + 01 4.30E + 01 0.00E+ 00 9.18E + 01 0.00E + 00 1.44E + 05
~~~~ ~
~
NB-95 1.69 + 04 9.38E + 03 5.16E + 03 0.00E+ 00 9.09E + 03 5.00E+00 4.01E + 07 RU-103 2.17E + 02 0.00E + 00 9.29E +01 0.00E + 00 7.66E + 02 0.00E + 00 1.82E + 04 RU-106 4.50E + 03 0.00E --.
+ 00 5.68E + 02 0.00E +. 00 8.69E
+ 03 0.00E + 00 2.16E+
05 - AG-110M 1.16E+07 .1.09E+ 07 6.65E + 06 0.00E + 00 2.09E + 07 0.00E + 00 3.07E + 09 TE 125M 3.61E + 06 1.30E + 06 4.82E + 05 1.01E + 06 0.00E+00,. 0.00E+00 1.06E + 07 TE-127M 1.01E + 07 3.59E + 06 1.20E + 06 2.41E+ 06 4.11E+ 07 0.00E + 00 2.52E + 07 , TE-129M 1.32E + 07 4.90E'+ 06 2.09E + 06 4.26E + 06 5.53E + 07 0.00E + 00 4.96E + 0[ l l-131 6.45E + 08 9.03E+08 4.85E+08 2.64E + 11 1.56E + 09 0.00E + 00 1.79E + 08 l133 , S.49E + 06 1.44E + 07 4.40E + 06 2.01 E + 09].53E + 07 0.00E + 00 1.09E + 07
. . CS-134 2.95E + 10 , 6.93E + 10 3.22E + 10 0.00E + 00 2.20E + 10 . 8.41E + 09 8.62E + 08 CS-136 1.35E + 09 5.30E + 09 3.56E + 09 0.00E + 00 2.89E + 09 4.55E + 0B 4.27E + 08 CS-137 4.02E +10 5.34E + 10 1.86E + 10 0.00E + 00 1.82E+ 10 7.07E + 09 7.60E + 08 )
BA-140 5.84E + 06 7.16E + 03 3.76E + 05 0.00E + 00 2.43E + 03 4.01 E + 03 9.01E + 06 CE-141 1.07E + 03 7.12E + 02 8.18E + 01 0.00E + 00 3.35E + 02 0.00E + 00 2.04E + 06 CE-144 7.90E + 04 3.27E + 04 4.25E ~+ 03 0.00E + 00 1.95E +04 0.00E ~+ 00 1.09E + 07
~
PR-14[ 3.4BE + 01 1.39E + 01 1.73E + 00 0.00E + 00 8.08E + 00 b.00E+00 1.15E + 05 ND-147 2.18E + 01 2.37E + 01 1.42E + 00 0.00E + 00 1.39E + 01. 0.00E + 00 8.54E + 04 0 148.0 ms/
04-2'3-97.09:13:44
- Number A)
( Nuclear M Radiological Connols Departmental Procedure 6610-PLN-4200.01
\d Title Revision No Offsite Dose Calculation Manual (ODCM) 12 1
TABLE 5.5.4 Pathway Dose Factors, Ri AGE GROUP: . ADULT PATHWAY: GRASS GOAT-MILK ' . ORGAN. DOSE FACTORS; m2 - mrem / year per[ sci /sec l NUCL'lDE - - - - - - - -
. BONE UVER T. BODY THYROID KIDNEY LUNG GI-LU
~ ~~ ~
H-3 U80E+ 00. 1.56E +'03 1.56E + 03 1.56E+5 1.56E+03 1.56E+03 1.56E+bi C-14 2.64E+08 5.27E+07 5.27E + 07 5.27E + 07 5.27E + 07 5.27E+07 5.27E + 07 CR-51 0.00E+ 00 0.00E + 00 3.43E + 03 2.05E+ 03_ 7.56E + 02 4.55E + 03 8.63E + 05 MN-54 0.00E + 00 1.01 E + 06 ; 1.93E + 05 0.00E + 00 3.01E 4 05 0.00E + 00 . 3.10E + 06 FE-55 3.27E + 05 2.26E + 05 5.26E + 04 0.00E + 00 0.00E + 00 1.26E + 05 1.30E + 05 FE-59
~~ ~~~
3.87E + 05 ' 9.09E + 05 3.48E + 05 0.00E+ 00 0.00E ~+~ 00 2.54E + 05 3.03E+ 06 CO 58 0.00E +00
- 5.66E + 05 1.27E + 06 0.00E + 00 0.00E+iO 0.00E + 00 1.15E+i7~
CO 60 0.00E + 00 1.97E + 06 4.35E + 06 0.00E + 00 0.00E + 00 . 0.00E+ 00 3.70E + 07 N1-63 8.08E + 08 5.60E+07 2.71E + 07 0.00E + 00 0.00E + 00 0.00E + 00 1.17E ~
+ 07
. ZN 65 1.65E + 08 5.24E + 08 2.37E + b8 ' O.00E + 00 3.51 E + 08 0.00E + 00 3.30E+b8 m RB-86 0.00E+00 ' 3.12E+08 : 1.45E+08 0.00E + 00 0.00E + 00 0.00E + 00 6.14E + 07 l \ SR-89 3.05E + 09 0.00E + 00 8.76E + 07 0.00E +00 0.00E + 00 0.00E + 00 4.89E + 08 t'J SR 9.84E + 10 0.00E + 00 2.41 E + 10 0.00E + 00 0.00E + 00 0.00E + 00 2.84E + 09 Y-91 1.03E + 03 0.00E + 00 2.76E + 01 0.00E + 00 0.00E + 00 0.00E + 00 5.68E + 05 ZR-95 1.13 E + 02 . 3.63E + 0i 2.46E+ 01 0.00E+00 5.70E + 01 0.00E + 00 1.15E + 05
~
NB-95 9.92E + 03 5.5IEh03 2.97E + 03 0.00E + 00 5.45E + 03 - b.00E+ 00 3.35E + 07 l RU-103 1.22E + 02 0.00E + 00 5.27E + 01 .0.00E + 00 4.67E + 02 0.00E +'00 1.43E + 04 RU-106 2.45E + 03 0.00E + 00 - 3.10E + 02 ' O.00E + 00 4.73E + 03 ' O.00E + 00 1.59E + 05 A
' G-110M 6.99E + 06 6.47E + 06 3.84E + 06 . 0.00E + 00 1.27E + 07 0.00E + 00 2.64E + 09
.TE-125M 1.96E + 0S 7.09E + 05 2.62E + 05 ' 5.89E + 05 7.96E + 06 0.00E + 00 7.81 E + 0G TE-127M 5.50E + 06 1.97E + 06 6.70E + 05 1.41 E + 06 2.23E + 07 0.00E + 00 1.84E ~
+ 07 TE 129M 7.23E + 06 2.70E + 06 1.14E + 06 2.48E + 06 3.02E + 07 0.00E + 00 3.64E + 07 l-131 - 3.56E + 08 5.09E + 08 2.92E + 08 1.67E + 11 8.73E + 08 0.00E + 00 1.34E + 08 l133. 4.65E + 06 8.10E +_06 2.47E + 06 1.19E + 09 1.41 E + 07 0.00E + 00 7.28E + 06 CS-134 1.70E + 10 4.04E + 10 3.30E + 10 0.00E + 00 1.31 E + 10 4.34E + 09 7.07E + 08 CS-136 7.92E + 08 3.13E + 09 2.2SE+ 09 ~ 0.00E+00 1.74E + 09 2.38E + 08 3.55E + 08
< CS-137 2.22E + 10 3.03E + 10 1.99E + 10 0.00E +00 1.03E + 10 3.42E + ~09 5.87E+ 08
~
BA-140 3.24E + 06 4.075+~b3 2.12E + 05 0.00E + 00 1.38E + $ 2.33E + 03 6.67E +ES~ CE-141 5.82E + 02 3.94E + 02 4.47E + 01 0.00E + 00 1.83E + 02 0.00E + 00 1.51 E + 06 CE-144 4.30E + 04 1.80E + 04
~ ~
2.31 E + 03 0.00E + 00 1.07E ~
+ 04 0.00E+~ 00 1.45E + 07 PR 143 1.90E + 01 h.~605+~E0 9.40e-01 0.00N + 00 4.39E + 00 0.00E + 00 850[
ND-147 1.13E.+ 01 1.31E + 01 ' 7.82e-01 0.00E + 00 7.65E + 00 0.00E + 00 6.28E + 04 e 149.0 m O j
04-23-97 09:13:44 , 1 Number ( A Nuclear i Radol@al Comols Departmental Procedura 6610-PLN-4200.01 True Flevision te. l Offsite Dose Calculation Manual (ODCM) 12 l l TABLESI1 l , Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT 2 ORGAN DOSE FACTORS; m - mrem / year per pCl/sec NUCL!DE - - - - - - - -- - -- - --
' BONE UVER T. BODY THYROID KIDNEY . LUNG GI-LLI H-3 0.00E+00 0.00E+00 0 00E +00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 C-14 0.00E + 00 0.00E + 00 0.*)0E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 CR-51 'O.00E + 00 0.00E + 00 0.00E + 00 0.00E __ _
+ 00 0.00E +00 0.00E + 00 0.00E + 00 , ,
MN 54 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 FE-55 0.00E + 00. 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 FE-59 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 ' O.00E + 00 CO 58 0.00E'+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00' C040 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 ' O.00E+00 0.00E + 00 0.00E + 00 NI-63 . 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E+ 00 ,0.00E+ 00 0.00E + 0,0' O.00E + 00
,,, l ZN-65 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 f RB46 0.00E+00 0.00E+00 . 0.00E+00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 (S) SR-89 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 SR-90 0.00E + 00 0.00E +00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 Y-91 0.00E+ 00 0.00E + 00 'O.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E.+ 00 ZR-95 0.00E + 00 0.00E+ 00 0.00E + 00 . 0.00E+ 00 0.00E + 00 0.00E + 00 ' 0.00E + 00 NB-95 0.00E + 00 ' O.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 ' O.00E + 00 RU-103 - 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 . 0.00E + 00 0.00E + 00 0.00E + 00 '
RU-106 0.00E'+ 00 0.00E + 00. 0.00E + 00 ,0,00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 , AG-110M 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 TE-125M 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 TE-127M 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 TE-129M 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E+ 00. 0.00E+ 00 0.00E + 00 0.00E + 00 1-131 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 1-133 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 CS-134 0.00E + 00- 0.00E + 00 0.00E + 00 0.00E + 00' O.00E + 00 0.00E + 00 0.00E + 00 CS-136 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +* 00 0.00E + 00 0.00E + 00 CS-137 0.00E + 00 0.00E + 00 0.00E+00 ' O.00E + 00 0.00E ~00 0.00E + 00 0.00E.+ 00
~~~
BA 140 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 6.00E +00 0.00E + 00 0.00E+ 00 CE-141 0.00E + 00 . 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00
- CE-144 0.00E + 00 0.00E+00 . 0.00E + 00 0.00E
~ ~ ~
+ 00 0.00E + 00 0.00E + 00 0.00E ~~
+ 00 PR-143 0.00E +ib~b.~00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 ~5.00E + 00~b.~00E+00 ND-147 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 ' O.00E + 00 0.00E + 00 0.00E + 00 s
150.0 mm
l 04-23-97 09:13:44 , Number r^i g Nuclear '"' ">d' ' o'c"' contro'$ Departmental Procedure 6610-PLN-4200.01
\ Tree Revision No.
I
- Offsite Dose Calculation Manual (ODCM) ' 12 l
TABLE 5.6.2 Pathway Dose Factors, Ri AGE GROUP: CHILD . PATHWAY: GRASS-COW-MEAT ~ ~~
'~
ORGAN DOSE FACTORS;2 m mrem $ car perhl/sec. NUCLIDE BONE LIVER T. BODY THYROID KIDNEY GI
. . __ ___ . .. LUNG......-. ... .-LU ...
Ha 0.00E + 00 2.34E + 02 2.34E + 02 ~2.34E+ 02 ' 2.34E + 02 2.34E + 02 2.34E + 02 C-14 3.84E+08 7.67E + 07 7.67E + 07 7.67E + 07 7.67E + 07 7.67E + 07 7.67E + 07 ' CR-51 0.00E+ 00 0.00E + 00 8.78E + 03 4.88E+03 1.33E+03 8.90E + 03 4.66E + 05 MN-54 0.00E + 00 8.01 E + 06 2.13E + 06 0.00E + 00 2.25E + 06 0.00E + 00 6.73E+ 06 FE-55 4.57E + 08 2.43E + 08 7.52E + 07 0.00E + 00 0.00E + 00 1.37E + 08 4.49E + 07 FE-59 3.77E + 08 6.10E + 08 3.04E+ 08 0.00E+ 00 0.00E +00 1.77E+ 08 6.35E + 08 '~
~~~
CO-58 E00E+00 1.34E + 07 5.03E+07 0.00E + 00 0.00E + 00 0.00E + 00 9.58E + 07 CO-60 0.00E + 00 G9JE+07 2.04E + 08 0.00E + 00 0.00E + 00 0.00E + 00 3.84E + 08 ' NI 2.91E + 10 1.56 3 +09 9.91E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.05E + 08 ZN-65
- 3.76E+08 ' 1.00 i+09 6.22E + 08 0.00E+00 6.31E+08 0.00E+ 00 1.76E+ 08 RB-86 0.00E + 00 5.7EE+ 00 3.54E + 08 0.00E + 00 0.00E + 00 0.00E + 00 3.71E + 07
/ SR -89 4.82E + 08 0.00E + 00 158E + 07 0.00E + 00 0.00E + 00 0.00E + .00 1.87E + 07. _
. ~
\v) SR-90 1.04E +10 0.00E + 00 2.64E + 09 0.00E + 00 0.00E + 00 ' O.00E + 00 1.40E + 08 Y-91 1.80E+ 06 0.00E+ 00 4.82E + 04 0.00E + 00 0.00E + 00 0.00E + 00 2.40E + 08 ZR-95' 2.66E + 06 5.86E + 05' 5.21E+ 05 0.00E + 00 ~ 8.38E + 05 ' O.00E + 00 6.11 E+ 08 -
NB-95 3.10E + 06 1.21 E+ 06 8.63E + 05 0.00E + 00 1.13E + 06 . 0.00E + 00 2.23E + 09 RU-103 1.55E + 08 0.00E + 00 . 5.96E + 07 0.00E + 00 3.90E + 08 0.00E + 00 4.01E + 09 RU-106 4.44E + 09 0.00E+00 ' 5.54E+08 0.00E ~
+ 00 6.00E + 09 0.00E ~
+ 00 6.91E + 10 .
AG-110M . 8.39E + 06 5.67E+06 4.53E+ 06 0.00E+ 00 1.06E+ 07 ' O.00E + 00 6.74E + 08 , TE-125M 5.69E + 08 1.54E + 08 7.59E + 07 1.60E + 08 0.00E + 00 . 0.00E+ 00 5.49E + 08 - TE 127M 1.78E + 09' 4.78E + 08 2.11E+ 08 4.25E ._-_ ....
+ 08 5.06E
+ 09 .
0.00E + 00 1.44E + 09 -. TE-129M 1.79E + 09 S.00E + 08 2.78E + 08 5.77E + 08 5.26E+09 0.00E + 00 2.18E+ 09 l-131' 1.66E + 07 1.67E + 07 9.48E + 06 5.52E + 09 2.74E +07 0.00E + 00 ' 1.48E + 06
'l-133 5.72e41 7.08e-01 2.68e-01 1.31E ... +..02 1.18E + 00 0.00E+ ._. 00 . 2.85e-01
. CS-134 9.23E +08 1.51E + 09 3.19E + 08 0.00E + 00 4.69E +08 1.68E+ 08 8.16E+ 06 CS-136 1.63E + 07 4.48E + 07 2.90E + 07 0.00E + 00 2.39E +07 3.56E+ 06 1.57E + 06 CS-137 1.33E + 09 1.28E + 09 1.89E + 08 0.00E + 00 4.16E ~
+ 08 1.50E + 08 8.00E + 06 BA-140 4.42E + 07 3.87E + 04 2.5BE+06 0.00E + 00 126E + 04 2.31E + 04 2.24E + 07 CE-141 2.22E + 04 1.11E + 04 1.65E + 03 0.00E + 00 4.86E + 03 0.00E + 00 1.38E + 07 CE-144 2.32E+ 06 7.26E+ 05 1.24E + 05 0.00E + 00 4.02E
. _. = - - .
+.- 05 0.00E +...-.... 00 1.89E
+ 08 PR-143 3.33E +04 1.00E + 04 ' 1.65E + 03 0.00E +00 5.42E + 03 0.00E + 00 3.60E + 07 ND-147 1.17E + 04 9.48E + 03 7.34E + 02 0.00E + 00 5.20E + 03 0.00E
+ 00 1.50E + 07 l
l 151.0 ms.
04-23-97 09:13:44 Nurnber
. Nuclear M Radblogkal Contds
[q } Departmental Procedure- 6610-PLN-4200.01 (/ Tme Revision No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.6.3 Pathway Dose Factors, R1
~
AGE GROUP: TEEN PATHWAY: GRASS-COW-MEAT
~~ ~ ~~
ORGAN DOSE FACTORS; arn - mrem [eaIper pCi/sec $ NUCUDE - - - - - - - - - - --
=--
BONE UVER
, , ,, _ _ , T. BODY __' THYROID NDNEY LUNG GI-LU
{ H-3 0.00E+00 - 1.93E+02 1.93E + 02 1.93E + 02 1.93E + 02 ' 1.93E + 02 1.93E +02 C-14 2.04E + 08 4.08E+ 07 4.08E+ 07 4.08E+ 07 4.08E + 07 4.08E+ 07 - 4.08E + 07 CR-51 0.00E + 00 0.00E + 00 5.63E+ 03 3.13E + 03 1.23E + 03 8.03E + 03 9.46E + 05 MN-54 0.00E+ 00 7.00E + 06 1.39E+ 06 0.00E + 00 2.09E + 06 0.00E + 00 1.44E + 07 FE-55 2.38E + 08 1.69E + 08 . 3.94E + 07 0.00E + 00 0.00E + 00 1.07E + 0B 7.31E+ 07 FE-59 2.12E+08 4.95E+08 1.91E + 08 0.00E+ 00 0.00E + 00 ' 1.56E + 08 1.17E+ 09 CO-58 0.00E + 00 1.40E + 07 3.24E + 07 0.00E + 00 0.00E + 00 0.00E + 00 1.94E+ 08 C040 0.00E + 00 5.83E + 07 1.31 E+ 08 0.00E + 00 0.00E + 00 0.00E + 00 7.60E+08 NI-63 1.52E + 10 1.07E + 09 5.15
. ... . -....E+08 0.00E + 00 0.00E + 00 0.00E + 00 1.71E +08 ZN-65 2.50E + 08 8.68E + 08 4.05E + 08 0.00E +00 5.56E'+ 08 0.00E + 00 3.68E + 0B RB-86 0.00E + 00 4.06E + 08 1.91 E + 08 ' O.00E+ 00 0.00E + 00 0.00E+ 00 ' 6.00E+07
. SR-89 . 2.55E4 08 ' O.00E400 7.29E + 06 0.00E + 00 0.00E+ 00 6.00E + 00 3.03E + 07
~
~ ~'
% SR-90 8.04E + 09 0.00E + 00 1.99E+ 09 0.Eb00 0.00E + 00 h.00E +00 2.26E+~08 -
Y-01 9.54E + 05 0.00E +00 2.56E + 04 0.00E + 00 0.00E + 00 0.00E + 00 3.91E+ 08 - i ZR-95 1.50E + 06 4.73E + 05 3.2SE + 05 0.00E + 00 6.95E + 05 0.00E + 00 1.09E + 09 { NB-95 1.79E + 06 9.95E + 05 5.48E+05 0.00E + 00 9.04E + 05 ' O.00E+ 00 ' 4.25E + 09 - RU-103 8.56E+ 07 0.00E + 00 3.66E + 07 0.00E +'00 3.02E + 08 0.00E + 00 7.15E + 09 RU 106 2.36E + 09 0.00E + 00 2.97E + 08 0.00E + 00 4,54E + 09 0.00E+ 00 1.13E+ 11 l
~~ ~ ~ ~
~
AG 110M 5.06E + 06 4.78E + 06 2.91E +06 0.00E+b0 ' 9.13E+b6 U.00E+ 00 1.34E+ 09 TE 125M ' 3.03E+ 08 1.09E + 0e 4.05E+ 07 8.46E + 07 ' O.00E+ 00 0.00E+ 00 8.94E + 08 TE-127M 9.41E~~+ 08 - 3.34E + 08 1.12E+08 2.24E+08 3.81E + 09 0.00E+ 00 . 2.35E+09 I~ lE 129M 9[9E+08 3.52E + 08 1.50d+08 3.06E + 08 3.97E + 09 0.00E + 00 . 3.56E + 09 l.131 8.93E + 06 1.25E + 07 6.72E + 06 3.65E + 09 2.15E+ 07 0.00E+ 00 2.47E+06 -
, 1-133 3.08e41 5.22e41 1.59e-01 7.29E + 01 9.16e-01 0.00E+ 00 3.95e-01 CS-134 5.23E + 08 1.23E+ 09 5.71E+ 08 0.00E + 00 3.91 E+ 08 1.49E + 08 1.53E + 07 CS-136 9.43E + 06 3.71 E + 07 2.49E + 07 0.00E + 00 2.02E + 07 3.1 BE + 06 2.99E+ 06 CS.137 7.24E+ 08 9.63E + 08 3.35E+ 08 0.00E + 00 ' 3.28E + 08 1.27E+ 08 1.37E+ 07 BA.140 2.39E + 07 .2.93E + 04 1.54E + 06 0.00E + 00 9.94E + 03 1.97E + 04 3.69E + 07 CE-141 1.18E + 04. 7.87E + 03 9.05E+ 02 0.00E + 00 3.71 E + 03 0.00E + 00 2.25E + 07 CE-144 1.23E + 06 5.08E+05 6.60E + 04 0.00E + 00 3.03E + 05 0.00E+ 00 3.09E + 08 PR-143 1.76E + 04 7.03E + 03 8.76E + 02 0.00E + 00 4.08E + 03 0.00E + 00 5.79E + 07 ND 147
. 6.23E + 03 6.78E + 03 4.06E --
+ 02 0.00E + 00 3.98E + 03 0.00E + 00 2.44E + 07 J
152.0- mm
04-23-97 09:13:44 Number (^) Nuclear - M RadologM Controls Departmental Procedure 6610-PLN-4200.01 V .Tme seuon No. 1 Offsite Dose Caled6 tion Manual (ODCM) 12 TABI'E 5.6.4 Pathway Dose Factors, RI . AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT 2 ORGA.N DOSE FACTORS: m - mrem / year per pCi/sec BONE UVER . T.. BODY THYRO!D KIDNEY I
. . . '_ LUNG _ _ _.......
.. GI-LLI -
H-3 0.00E + 00 3.24E + 02 3.24E + 02 3.24E + 02 3.24E + 02 ' 3.24E + 02 3.24E + 02 C-14 2.42E + 08 4.83E + 07 4.83E + 07 4.83E + 07 4.83E + 07 4.83E + 07 4.83E + 07 CR-51 0.00E + 00 0.00E + 00 7.04E + 03 4.21E + 03 1.55E + 03 9.35F+ 03 1.77E + 06
~ ~
MN-54 0.00E + 00 9.18E+ 06 1.75E~+ 06 0.00E + 00 '2.73E + 06 0.00E + 00-~~~'E+If 2.81 FE-55 2.93E + 08 2.03E+ 08 4.73E + 07 0.00E+ 00 0.00E + 00 1.13E + 08 1.16E + 08 FE-59 2.66E~~'
+ 08 6.25E+ 08 2.39E + 08 0.00E+ 00 0.00E + 00 .1.75E + 08 2.08E + 09 CO-58 ~ .~CIOE+00 0 1.82E+ 07 4.09E + 07 0.00E+ 00 0.00E + 00 0.00E + 00 3.70E + 08 CO-60 0130E+00 7.52E + 07 1.66E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.41E + 09 NI-63 1.89E + 10- 1.31E + 09 6.33E + 08 0.00E +00 ' O.00E + 00 0.00E+ 00 2.73E + 08' ZN 65 3.56E+08 1.13E+09 5.12E + 08 0.00E + 00 7.57E +08 0.00E + 00 7.13E + 08
- RB-86 0.00E +00 4.87E + 08 2.27E+08 . 0.00E+ 00 0.00E + 00 0.00E + 00 9.59E + 07 SR-89 3.02E + 08 0.00E+ 00 8.66E + 06 0.00E + 00 0.00E + 00 0.00E+ 00 4.84E + 07
~
SR-90 1.24E + 10 0.00E + 00 -3.05E + 09 0.00E + 00 0.00E + 00 0.00E+00 3.60E+08 Y-91 1.13E + 06 0.00E + 00 3.03E + 04 0.00E + 00 0.00E + 00 0.00E+ 00 6.24E+ 08 ZR-95 1.87E+ 06 . 6.01E+ 05 4.07E + 05 - 0.00E + 00 9.43E + 05. 0.00E + 00 1.90E + 09 _ NB 2.30E + 06 ' 1.28E + 06 6.87E + 05 0.00E +00 .1.26E+06 ' O.00E+00 7.76E + 09, RU-103 1.05E + 08 0.00E+ 00 4.53E + 07 0.00E+00 ; 4.02E+08 0.00E + 00 1.23E + 10 RU-106 2.80E + 09 0.00E + 00 3.54E + 08 0.00E +00 5.41 E + 09 0.00E + 00 1.81E + 11 AG-110M 6.68E + 06 6.18E + 06 3.67E + 06 0.00E + 00 1.22E + 07 0.00E +00 2.52E+09 .
. TE 125M 3.59E + 08 1.30E+ 08 4.81 E + 07 1.08E + 08 1.46E +09 0.00E+ 00 1.43E + 09 TE-127M - 1.12E+ 09 3.99E+ 08 1.36E + 08 2.85E + 08 4.53E + 09 0.00E + 00 3.74E+ 09 TE 129M - 1.13E + 09 4.23E+ 08 1.79E + 08 3.89E + 08 4.73E +09 0.00E+ 00 5.71 E + 09 l-131 1.08E + 07 1.54E+ 07 8.82E + 06 5.04E + 09 2.64E + 07 0.00E + 0.0 4.06E + 06 l l-133 3.68e-01 6.41e 01 1.95e-01 9.42E +01 1.12E+ 00 0.00E+ 00 5.76e-01 l
~
'CS-134 6.58Es 08 1.57E + 09 1.28E+ Ci9 0.00E + 00 5.07E +08 168E+08 2.74E + 07 CS-136 1.21 E + 07 4.78E + 07 3.44E + 07 0.00E + 00 2.66E +07 3.65E+ 06 5.43E+ p6 CS-137 8.72E + 08 1.19E + 09 7.82E + 08 0.00E + 00 4.05E + 08 1.35E+08 2.31 E + 07 _ , , ,
BA-140 2.90E + 07 3.64E + 04 1.90E + 06 '0.00E + 00 1.24E + 04 2.08E + 04 5.96E+ 07 CE-141 1.41 E + 04 9.51 E + 03 1.08E + 03 0.00E + 00 4.42E + 03 0.00E + 00 3.64E + 07 CE 144 1.46E + 06 6.10E + 05 7.83E + 04 0.00E + 00 3.62E + 05 0.00E + 00 4.93E + 08 I
, i PR-143 2.09E + 04 8.40E +03 1.04E+03 - 0.00E +00 4.85E + 03 0.00E + 00 9.17E + 07 !
ND-147 7.08E + 03 8.18E + 03 4.90E + 02 0.00E + 00 ' 4.78E + 03 0.00E + 00 3.93E + 07 l m v . 153.0 me.
04-23-97 09:13:44 i Number l
't p-I Nuclear " "*d"oa'c^' coatro'=
Departmental Procedure 6610-PLN4200.01
\ Title
, Revision No. l Offsite Dose Calculation Manual (ODCM) 12-TABLE 5.7.1 Pathway Dose Factors, RI
~~~
AGE GROUP: INFANT . PATHWAY: VEGET TION
~
ORGAN DOSE FACTORS; nia m ' rem / year per yCi/sec , i
~ TOUE ; ~IVER l TIBODY THfROID KIDNEY . LUNG ~~lII'U~ L l t
H 0.00E+00 0.00E+00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 C 0.00E + 00 0.00E + 00 0.00E+ 00 'O.00E + 00 ' O.00E + 00 0.00E + 00 0.00E +00 CR-$1 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 MN 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +00 0.00E + 00
, FE-55 0.00E+00 'O.00E+00 0.00E+ 00 0.00E+ 00 0.00E + 00 ' O.00E + 00 0.00E+ 00 FE.69 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 -
l CO-58 . 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E +00 0.00E + 00 0.00E+ 00 0.00E + 00 CO-60 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E+ 00 N1-63 0.00E + 00 0.00E+00 0.00E+00 0.00E+ 00 0.00E + 00 0.00E + 00 0.06E+ 00 ZN-65 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E+ 00 RB-86 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00
/m i SR-89 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 SR-90 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 Y-91 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 ZR-95 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E + 00
~~
' NB-95 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E+ 00 0.5E+00 0.00E+ 00 RU-103 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E +00 RU-106 0.00E + 00 ' O.00E+ 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E+00 'O.00E+00 '
AG-110M 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 TE 125M 0.00Et00 0.00E + 00 0.00E + 00 0.00E+00 ' O.00E+ 00 0.00E + 00 0.00E + 00
~
TE-127M 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 ' 0.00E+00 0.00E + 00 0.00E + 00 TE'-129M 0.00E + 00 0.60E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 1-131 0.00E + 00 0.00E + 00 0.00E+ 00 0.00Et00 0.00E + 00 0.00E + 00 0.00E + 00 1-133 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E+ 00
~ ~ ' ~
CS-134 0.00E + 00 b.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.bOE+00 CS-136 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 CS-137 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +~ 00 0.00E + 00
~~ ~
BA-140 0.00E + 00 - . 0.00E + 00 ~ 0.00E + 00 0.00E + 00 0.00500 0.00E+00 - 0.00E+ 00 CE-141 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 ' O.00E + 00 0.00E + 0.0 0.00E + 00
. CE-144 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 PR-143 0.00E + 00 0.00E + 00 0.00E +00 0.00E +00 0.00E + 00 0.00E + 00 0.00E + 00 ND-147 0.00E + 00 0.00E + 00 . ' O.00E + 00 0.00E. + 00 0.00E + 00 0.00E + 00 0.00E+ 00
/ \
f 154.0 me 1
04-23-97 09:13:44 i Number ' o)' ( Nuclear "*"o* co** Departmental Procedufb 6610-PLN-4200.01 l V htle Revision No. i l l Offsite Dose Calculation Manual (ODCM) 12 l 1 TABLE 5.7.2 Pathway Dose FactorsiRi ' AGE GROUP: CHILD PATHWAY: VEGETATION
~ 1 2
ORGAN DOSE FACTORS; m - mrem / year per'pCl/sec NUCUDE = - - - - - - - = - - -- ---
~
BONE LIVER T. BODY THYROID. KIDNEY LUNG GI-LU
~
H-3 0.00E+ 00 4.02E + 03 4.02E+03 4.02E+03 4.02E + 03 4.02E + 03 4.02E + 03 C-14 8.89E + 08 1.78E + 08 1.78E + 08 1.78E+08 1.78E+08 1.78E+ 08 1.78E + 08 CR.51 0.00E + 00 0.00E + 00 1.17E + 05 6.49E+ 04 1.77E+ 04 1.18E + 05 6.20E + 06 MN-54 0.00E + 00 6.65E+ 08 1.77E + 08 0.00E + 00 1.86E + 08 0.00E + 00 5.58E + 08 FE-55 8.01 E + 08 4.25E + 08 1.32E + 08 0.00E+ 00 0.00E + 00 2.40E + 08 7.87E + 07 FE-59 3.98E + 08 6.44E + 08 3.21 E + 08 0.00E + 00 0.00E+ 00 1.87E+ 08 6.71 E+ 08 l CO-58 . 0.00E + 00 6.44E + 07 1.97E + 08 0.00E + 00 0.00E + 00 0.00E + 00 3.76E + 08 ' CO-60 0.00E + 00 3.78E + 08 1.12E + 09 0.00E + 00 0.00E+ 00 0.00E + 00 2.10E + 09 Ni-63 3.95E + 10 2.11E + 09 1.34E + 09 0.00E + 00 0.00E + 00 0.00E +00 1.42E + 08 ZN-65 8.12E + 08 . 2.16E + 09 1.35E + 09 U.00E+ 00 1.36E + 09 0.00E + 00 3.80E+6If RB-86 0.00E + 00 4.51E + 08 2.77E + 08 0.00E + 00 0.00E +00 0.00E + 00 . 2.90E + 07 ' SR-89 3.60E + 10 ' O.00E + 00 1.03E + 09 0.00E + 00 0.00E + 00 ~0.00E + 00 1.39E'+ 09 _ SR-90 1.24E + 12 0.00E+00. 3.15E+ 11 0.00E + 00 0.00E + 00 0.00E + 00 1.67E + 10 Y-91 1.87E + 07 0.00E + 00 4.99E + 05 0.00E+00 ' O.00E+00 0.00E + 00 2.49E + 09 l ZR-95 3.86E + 06 8.48E + 05 7.55E + 05 0.00E + 00 1.21E + 06 0.00E + 00 8.85E + 08 I
~ ~
NB-95 4.11E + 05 1.60E + 05 1.14E + 05 0.00E + 00 1.60E + 05 . 0.00E+00 2dE+08 RU-103 1.53E + 07 0.00E + 00 5.90E + 06 0.00E + 00 3.86E + 07 0.00E + 00 3.97E+ 08 RU-106 7.45E + 08 0.00E + 00 9.30E + 07 0.00E + 00 1.01 E + 09 0.00E + 00 1.16E + 10
~ ~ ~
AG-110M 3 15b~7 2.17E + 07 1.73EIO7 0.00E + 00 42I4EIO7"~6.~00E+ 00 2.58E + 09 TE-125M 3.51 E+ 08 9.50E + 07 4.67E + 07 9.84E + 07 0.00E+ 00 0.00E + 00 3.38E + 08 TE 127M 1.32E + 09 3.56E + ~~08 1.57E + 08 3.16E + 08 3.77E + 09 0.00E + 00 1.07E+ 09
' ~~~ ~
~fE-129M 8.40E + 08 E.~35EI~08 1.30E + 08 2.71 E + 08 . 5.~47E h 09 0.00E+00 1.02E+09 l-131 1.43E + 08 1.44E' + 08 8.18E+07 4.76E + 10 2.36E + 08 0.00E + 00 1.28E+ 07 l133 3.53E + 06 4.37E + 06 1.65E + 06 8.12E + 08 7.2SE + 06 0.00E + 00 1.76E+ 06
~~ ~ ~~
CS-134 ~iEY+10 2.63E + 10 5.S55 09 0.00E300 8.15E+ 09 2.93E + 09 5.42E + 08 CS-136 8.28E + 07 2.28E + 08 1.47E + 08 0.00E + 00 1.21 E + 08 1.81 E + 07 8.00E + 06 CS-137 2.39E + 10- 2.29E + 10 3.38E + 09 0.00E + 00 7.46E + 09 2.68E + 09 1.43E + 08 ! BA 140 2.79E + 08 2.44E + 05 1.63E + 07 0.00E+00 7.96E404 1.46E + 05 1.41E+ 08
.CE-141 6.57E + 05 3.28E + 05 4.86E + 04 0.00E + 00 1.44E + 05 0.00E + 00 4.09E + 08 CE-144 1.27E + 08 3.99E + 07 6.79E + 06 0.00E + 00 '2.21 E + 07 0.00E + 00 1.04E + 10
~ ~~
PR-143 1ASE+05 4.36E + 04 7.215 03 0.00EdOO 2.36E'+ 04 0.00E+00 1.57E + 08 ND-147 7.15E + 04 -5.79E + 04 4.49E + 03 0.00E + 00 3.18E + 04 0.00E + 00 9.18E + 07
. =....
f i ) v . 4 155.0 mm
04-23-97 09:i3:44
- Number o* Nuclear W RadidoM Cowds Departmental Procedure 6610-PLN-4200.01 -
(d im. n.vaion wo. l Offsite Dose, Calculation Manual (ODCM) 12 TABLE 5.7.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: VEGETATION
'ORGA . DOSE FACTORS: m8 - mrem / year per pCl/sec .
NUCUDE - - - - - - - - - - - - - - ---- - - -- - -- - BONE UVER T. BODY THYROID KIDNEY' LUNG GI-LU . , = - . . . .. - . - - HG 0.00E + 00 2.59E + 03 2.59E + 03 2.59E + 03 2.59E + 03 2.59E + 03 2.59E + 03 C-14 3.69E+08 7.38E+07 7.38E + 07 7.38E + 07 7.38E + 07 7.38E + 07 7.38E + 07 CR-51 ' 0.00E + 00 0.00E + 00 6.16E + 04 3.42E + 04 1.35E + 04 8.79E + 04 1.03E + 07
~~ ~
, MN-54 0.00E + 00 4.54E+~ 08 9.01E+07 0.00E + 00 1.36E + 08 0.00E+00 . 9.32E+08
- FE'55 3.26E + 08 2.31 E + 08 5.39E + 07 0.00E + 00 0.00E + 00 1.47E + 08 1.00E + 08 FE-59 1.80E + 08 4'19E . + 08 1.62E + 08 0.00E + 00 0.00E+ 00 1.32E + 08 ' 9.91E +....08 CO-58 0.00E +00 '4.36E + 07 - 1.01E + 08 0.00E+ 00 ' O.00E+ 00 0.00E + 00 6.01E + 08 CO-60 0.00E + 00 2.49E + 08 5.60E+08 0.00E+00 0.00E+ 00 0.00E+ 00 3.24E + 09 N1-63 1.61 E + 10 1.13E +09 5.45E + 08 0.00E+00 0.00E+00 0.00E+ 00 1.81 E + 08 ,
~ ~
1 ZN 65 4.24E + 0S 1.47E +09 6.86E + 08 0.00E + 00 9.42E + 08 b.00E+00 6.23E + 08 , 1 RB-86 0.00E+00 ~ 2.73E+08 1.28E + 08 0. 00E + 00 0.00E + 00 0.00E + 00 4.04E + 07 I
.O SR-89* 1.52E + 10 0.00E + 00 4.34E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.80E + 09 SR-90 7.51E + 11 0.00E + 00 1.85E + 11 0.00E+ 00 0.00E+ 00 0.00E + 00 2.11E+ 10 i Y-91 7.84E + 06 0.00E + 00 2.10E + 05 0.00E + 00 0.00E + 00 . 0.00E + 00 3.22E+ 09 ZR-95 1.72E + 06 5.43E+ 05 3.73E + 05 ' O.00E + 00 7.98E+ 05 0.00E + 00 1.25E + 09
~ ~
NB-95 1.92E + 05 1.07E + 05 5.87E + 04 0.00E+ 00 1.03E+ 05 0.00E + 00 4.56E + 08 l 4 RU-103 6.82E + 06 0.00E + 00 2.92E + 06 .0.00E + 00 2.41E+ 07 0.00E + 00 5.70E+08
, )
. , RU-106 3.09E + 08 0.00E + 00 3.90E + 07 0.00E + 00 5.97E+08 0.00E + 00 1.48E + 10' l AG-110M 1.52E + 07 1.43E + 07 8.72E + 06 0.00E + 00 2.74E+ 07 0.00E +00, 4.03E + 09 TE-125M 1.48E + 08 5.34E + 07 1.98E + 07 4.14E + 07 0.00E + 00 0.00E + 00 4.37E+ 08 TE-127M 5.52E + 08 1.96E + 08 6.56E + 07 1.31 E + 08 - 2.24E + 09 0.00E + 00 1.37E + 00 j TE-129M 3.61 E + 08 1.34E + 08 5.72E + 07 1.17E + 08 1.51E + 09 0.00E + 00 1.36E + 09 1131 7.69E + 07 1.08E + 08 5.78E + 07 3.14E + 10 1.85E+ 08 0.00E + 00 2.13E + 07 l-133 1.94E + 06 3.29E + 06 1.00E + 06 ; 4.59E + 08 5.77E + 06 0.00E + 00 2.49E + 06
. CS-134 7.10E + 09 1.67E+10' 7.75E+09 0.00E + 00 5.31 E+ 09 2.03E + 09 2.08E + 08 CS-136 , 4.39E + 07 1.73E + 08 1.16E + 08 0.,00E + 00 9.41 E+ 07 1.48E + 07 1.39E + 07
' CS 137 1.01 E + 10' 1.35E + 10 4.69E + 09 0.00E+ 00 4.59E+ 09 1.78E + 09 1.92E + 08
~
BA-140 1.39E + 08 1.71 E+ 05 8.97E + 06 0.00E + 00 5.78E + 04 1.15E + 05 2.15E + 08 CE-141 2.83E+05 1.89E+05 2.17E + 04 0.00E+ 00 8.90E + 04 0.00E + 00 5.41 E + 08 2 CE-144 5.28E + 07 2.18E + 07 2.83E + 06 0.00E+ 00 1.30E+ 07 0.00E + 00 1.33E + 10
...... - -_. _ _ _ _ _ __=---_= ..........
PR-143 6.99E + 04 2.79E + 04 3.48E +'03 0.00E + 00 1.62E + 04 0.00E + 00 2.30E + 08 ND-147 3.62E+ 04 3.94E+ 04 2.36E + 03 0.00E + 00. 2.31 E + 04 0.00E + 00 1.42E + 08 l m .
; 156.0 m e, ? -
04-23-97 09:13:44 Number i t O $UClear M RadidOcal Conads Departmental Procedure 6610-PLN-4200.01 j 1 Title Revision No. Ott's'ite Dose Calculation Manual (ODCM)' 12 TABLE 5.7.4 I Pathway Dose Factors, Ri
~
AGE GROUP: ADULT - PATHWAY: VEGETATION
~~
ORGAN DOSE FACTORS; m' - mrem / year per pCl/sec l NUCUDE - - - ----- - - - - - - - - - - - - - - l BONE UVER T. BODY THYROID: KIDNEY LUNG GI-LLI i H-3 0.00E + 00 2.26E + 03 2.26E + 03 2.26E + 03 2.2SE + 03 2.26E + 03 2.26E + 03 I' C-14 2.28E + 08 4.55E + 07 4.55E + 07 4.55E + 07 4.55E + 07 4.55E + 07 4.55E + 07 CR-51 0.00E + 00 0.00E+ 00 4.64E + 04 2.77E + 04 1.02E + 04 6.15E : 94 1.17E + 07
~
MN-54 0.00E + 00 3.13E+08 ' 5.97E+07 0.00E + 00 9.31 E + 07 0.00E + 00 9.58E+ 08 FE-55 2.10E+ 08 1.45E + 08 3.38E + 07 0.00E + 00 0.00E + 00 8.08E+ 07 8.31E + 07 l FE-69 1.26E + 08 .2.97E + 08 1.14E + 08 0.00E + 00 0.00E+ 00 8.29E + 07 9.89E + 08, i CO-58 0.00E + 00 3.07E + 07 6.89E + 07 0.00E + 00 0.00E + 00 0.00E + 00 6.23E + 08 I CO-60 0.00E + 00 1.67E+ 08 3.69E + 08 0.00E + 00 0.00E+ 00 0.00E + 00 3.14E+ 09 NI-63 1.04E + 10 7.21 E + 08 3.49E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.50E + 08 ZN-65 3.17E + 08 1.01 E + 09 ' 4.56E +08 . 0.00E + 00 6.75E + 08 0.00E + 00 6.36E + 08 ps RB-86' O.00E + 00 2.19E + 08 . 1.02E + 08 0.00E + 00 0.00E + 00 0.00E + 00 4.32E + 07 lU ) , SR-89 SR-90 9.98E+09 .0.00E+00 2.86E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.60E + 09 6.05E + 11 0.00E+00 1.48E+11 0.00E + 00 0.00E + 00 0.00E + 00 1.75E + 10 i Y-91 5.12E + 06 0.00E+00 ' 1.37E+05 0.00E + 00 0.00E + 00 0.00E + 00 2.82E + 09 ' ZR-95 1.17E + 06 3.77E + 05 2.55E + 05 0.00E .-
+ 00 5.91E + 05 0.00E + 00 1.19E + 09 NB-95 1.42E+05 ' 7.92E+04 4.26E + 04 0.00E + 00 7.83E + 04 0.00E + 00 4.81 E + 08 RU 103 4.77E + 06 0.00E + 00 2.06E + 06 0.00E + 00 1.82E + 07 0.00E + 00 5.57E + 08 RU-106 1.03E~~
+ 08 0.00E + 00 2.44E + 07 0.00E + 00 3.72E + 08 0.00E + 00. 1.25E + 10
~
' AG-110M 1.05E + 07 9.75E + 06 5.79E + 06 0.00E + 00 1.92E+ 07 0.00E + 00 3.98E + 09 TE-125M 9.66E + 07 ' 3.50E + 07 1.29E + 07 2.90E+ 07 3.93E + 08 0.00E + 00 3.86E + 08 TE-127M 3.49E + 08 1.25E + 08. 4.26E + 07 8.93E + 07 1.42E + 09 0.00E + 00 1.17E + 09 TE-129M 2.51 E + 08 9.372 + 07 3.97E + 07 8.63E+ 07 1.05E
- 09 0.00E + 00 1.26E + 09 l-131 8.08E + 07 1.16E + 08 6.62E + 07 3.79E + 10 1.98E+ 08 0.00E + 00 3.05E + 07 l-133 2.09E + 06 3.63E + 06 1.11E + 06 5.34E + 08 ' 6.33E+06 0.00E + 00 3.26E + 06 ..
~~~ ~ ~~~ ~~
CS-134 4 67d+~i9 1.11E + 10 9.08E + 09 - b.00d+~00 3.59E + 09 . 1.19E + 09 1.94E + 08 CS-136 4.28E + 07 1.69E + 08 1.22E + 08 0.00E + 00 9.41 E + 07 1.29E + 07 1.92E + 07 CS-137 6.36E + 09 8.70E + 09 5.70E ~~~
+ 09 0.00E + 00 2.95E+ 09 . 9.81E+08 ~~
1.68E + 08 BA-140 1.29E + 08 1.62E + 05 8.47d+~06 0.03E + 00 5.52E + 04 9.29E + 04 2.66E + 08 CE-141 1.97E + 05 1.33E + 05 1.51E + 04 0.00E + 00 6.20E + 04 0.00E + 00 5.10E+08 ' CE-144 3.29E + 07 1.38E ~~+ 07 1.77E + 06 0.00E + 00 8.16E + 06 0.00E + 00 1.11 E + 10 PR 143 6.25E + 04 2.51E + 04 3.10E + 03 0.00E + 00 1.45E + 04 0.00E + 00 2.74E +i8~ ND-147 3.34E + 04 3.85E + 04 2.31E + 03 - 0.00E + 00 2.25E + 04 0.00E + 00 1.85E + 08 ~ s 157.0 me
04-23-97'09:13:44 1 Number es l g'ggp TMI Radiological Controls . (d im Departmental Procedure 6610-PLN-4200.01 ~ Revision No. l Offsite Doso Calculation Manual (ODCM) 12 6.0 TMI-1 GASEOUS WASTE TREATMENT SYSTEM. , 6.1 Description of the TMI-1' Gaseous Radweste Treatment System (see Floure 6.1) , 6.1.1 Waste Gas System . .
- a.
- Reactor BuBd'ng:
i
- Reactor Coolant Drain Tank (RCDT) header 1 b. Auxiliary Building:
4
- Vent Header from
- 1. Miscellaneous Waste Storage Tank (MWST) .
' 2. Three (3) Reactor Coolant Bleed Tanks (RCBT) '
- Waste Gas Delay Tank
- Two (2) Waste Gas Compressors
- Three (3) Waste Gas Decay Tanks (WGDT)
- c. Filtration and dilution provided by the Station Ventilation System.
(j 6.2 Operabi!ity j Operability of the Gaseous Wabte T.reatment System is defined as the ability to remove gas from the vent header / tank gas spaces and store it under a higher pressure in the Waste Gas Decay Tanks for subsequent release. Except for initiating the make up tank sample and waste gas venting and the recycle or disposal of l compressed waste. gases stored in the waste gas decay tanks, the operation of the waste gas system is entirely automatic. One waste gas compressor comes on automatically, removirg gases d from the vent header system as required, to maintain the pressure in the system at a maximum of .
, about 16.4 psia.
9 - 158.0 me.
1 04 23-97 09:13t.44 l l -
) Number
$UClear TMI Raddpgical Controls Departmental Procedura 6610-PLN-4200.01
- l I
Title Raws,on No. i i Offsite Dose Calculation Manual (ODCM) 12 l 1 RGURE 6.1 I } . Waste Gas S'ystem l 1 i . l ees.seem. s s g.,ig am enasse l u 8rn ,- s 1
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l, h . I l 1 l l 159.0 ' aus. I l
04-23-97 09:13:44 ~ . l
. Number
. ggggggy MI Radiological Controls Departmental Procedure- 6610 PLN-4200.01 g
Title Revision No. l Offsite Dose CaIcu'lation Manual (ODCM) -12 l l l 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 7.1 Total Dose Calculation The annual (caIendar year) dose or dose commitment to any member of the pubile, due to releases l of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid,' which shall be limited to less than or equal to 75 mrem. This control is provided in order to meet the dose limifations of 40 CFR 190. The total dose from TM1-1 and TMl-2 (uranium fuel cycle facilities within 8 kilometers) is calculated by summing the calculated annual doses to critical organs of a real individual for liquid cffluent using l Section 2.1 methodology, for gaseous effluent using Section 5.2.1 and 5.2.2 methodology, and the direct radiation from the site from the envitonmental monitoring program's direct radiation (FLD) monitors.
. V t
t t t 9 O . 160.0 , m e, I i
4 04-23-97.09:13:44 1 Nu'mber I n
)
(UClear , W Radiological Controls Departmental Procedure 6610-PLN-4200.01 l 1 j Title , Revision No, Offs'ite Dose Calculation Manual (ODCM) 12 l
. \
8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) l 8.1 Monitorina Procram Reauirements 8.1.1 Control's -
- l In. accordance with the TMI-1, Tech. Specs. and TMI-2 PDMS Tech. Specs., the radiological. ;
' environmental monitoring pro. gram shall be conducted as specified in Table 8.1. I 8.1.2 . Applicabitity At all times.
8.1.3 Action
, a. With the radiological environmental monitoring program not being conducted as specified in Table 8.1, prepare and submit to the Commission in the Annual Radiological Environmental .
Operating Report, a description of the reasons for not conducting the program as required l and th.e plans for preventing a recurrence. i fG b. With the level of radioactivity as the result of plant effluents in an environmental sampling
\'- medium exceeding the reporting levels of Table 8.2 when averaged over any calendar '
quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a special report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose
- to a member of the public is less than the calendar year limus of ODCM Part I Controls 2.2.1.2, 2.2.2.2, 2.2.2.3 and ODCM Part II, Sections 2.1.1.3F,2.1.2.3D, and l 2.1.2.3E. When more than one of the radionuclides in Tabl'e 8.2 are detected as the result of I plant effluents in the sampling medium, this report shall be submitted !f:
concentration (1) + concentration (2) + ...' h 1.0 . reporting level (1) ' reporting level (2) When radionuc!! des other than those in Table 8.2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose
- to a member of the public is equal to or greater than the calendar year limits of ODCM Part i Controls 2.2.1.2, 2.2.2.2, 2.2.2.3 and ODCM Part 11 Sections 2.1.1.3F 2.1.2.3D, and 2.1.2.3E. This report is not required if the measured fevel of radioactivity was not the result of plant effluents; however, in such an event, the condttion shall be reported and described in the Annual Radiological Environmental Operating Report.
~
4 G* The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report. s 161.0 me,
asuur 04-23-97 09:13:44 Number (q)
, (ggp TMI Radiological Controis Departmental Procedura 6610-PLN-4200.01
/ Title Flavision No.
Offsite Dose Calculation Manual (ODCM) 12
- c. With mik or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 8.1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Envirotunenta! Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to TMi-1 Tech. Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12, submit in,the next Annual Radioactive Efiluent Release Report .
' documentation for a change in the ODCM including a revised figure (s) and table for the ODCM reflecting t.he new location (s) with ' support!ng information identifying the cause' of the
' unavailability of samples and justifying the selection of the new location (s) for obtaining samples.
8.1.4 Bases The radiological monitoring program required by this control provides representative measurements of radiation and of radioactive rnaterials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures'of members of the general public resulting from the station operation. This monitoring program implements Section IV B.2 of AppendirI to 10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials,and levels of radiation are not higher t,han expected on the basis of the eff!uent measurerpents and modeling of the environmental exposure
'f\ pathways. Guidance for this monitoring is provided by the Radiological Assessment Branch
. Technical Position on Environmental Monitoring (Revision 1, November 1979). Program changes may be initiated based on operational experience.
8.1.5 Survetilance Re'ouirements ' The radiological environmental monitoring samples shall be collected pursuant to Table,8.1, from the
, specific locations given in Tables 8.4 through 8.10 and Maps 8.1 through 6.3, and shall be analyzed pursuant to the requirements of Table 0.1 and the detection capabilities required by Table 8.3.
f)
\.
162.0 mm
l l 04-23-97 09:13:44 l
. Number l M Radiological Controls l
C. MUCIGar Departmental Procedure 6610-PLN-4200.01 ( Tme Revision No. Offsite Dose Calculation Manual (ODCM) . 12 8.2 Land Use Census 8.2.1 Controls . In accordance with the TMl-1-Tech. Specs. and TMI-2 PDMS Tech. Specs., a Land Use Census shat! ,
- be conducted and shall1deritify within s distance of 8 km (5 miles) the location in each of the 16 . I I
meteorological sectors of the' nearest milk animal, the nearest residence, and the nearest garden
- of greater than 50 m2 (500 ft 2) producing broad leaf vegetation.
8.2.2 Applicability - I At all times. j l 8.2.3 Action
. . 1
- a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated In'ODCM Part l' Surveillance 3.2.2.3.1, pursuant to ODCM, Part IV, Section 2.0, identify the new location (s) in the next
~
]
Annual Radioactive Effluent Release Report. With a Land Use Census identifying a location (s) that yields'a calculated dose or dose f]j ( b. commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Table 8.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location (s), excluding the control station locetion, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program efter October 31 of the' year in which this Land'Use Census was conducted. Pursuant to TMI-1 Tech. Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12 submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) ' , with information supporting the cha'nge in sampling locations. l i 8.2.4 Bases l This Control is provided to ensure that changes in the use of unrestricted areas are identified and
-modifications to the monitoring program are made if required by the results of this census. The best information from the door.to-door survey, aerial surveys, or consulting with local agriculfural authorities shall be used. This census sstisfies the requirements of Section IV.B.3 of Appendix I to -
10 CFR 50. Restricting the census to gardens of greater than 500 square feet (50'm2) provides assurance that significant exposure pathways via leafy vegetables will be identified and isonitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy
, vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.
i s Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different sectors with the highest predicted D/Os in lieu of the garden census. Requirements for broad leaf sampling in Table 8.1 shall be followed, including analysis of control samples. 163.0 mm
t 04-23-97 09:13:44
' Number M Radidogbl Contrds juClear Departmental Procedure 6610-PLN-4200.01 :
j' Revision No. Ltw 1 Offsite Dose Cciculation Manual (dDCM) . 12' . i i 8.2.5 Surveillance Reauirements l The Land Use Census shall be conducted during the growing season 'at least once per 12. months, , I j using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census shall be
' included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Part IV, Section 1.0.
.i e I l J i I i
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i 6 d 164.0 me 1 l i
04-23-97 09:13:44 Number p} Nuclear -
" andio'ootca' coatro'$
Departmental Procedure '6610-PLN-4200.01
. Me Flavision No.
Offsite Dose Calculation Manual '(ODCM) 12
' 8.3 Interlaboratory Comparison Proaram 8.3.1 Co'ntrols in accordance with the TMl 1 Tech. Specs. and TMI-2 PDMS Tech. Specs., analyses shall be performed on radioactive materials suppiled as part of an interlaboratory Comparison Program .
which has been approved by the Commission (NRC). Only those samples and analyses which are required by Table 8.1 shall be perf armed. 8.3.2 Applicability - At all times. , 8.3.3 Action With analysis not being performed as required above, report the corrective action taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Op'erating Report. 8.3.4 Bases , O The ' requirement for participation in an approved Interiaboratory Comparison Program is provided to (j ensure that independent checks on precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for
. environmentalm' onitoring in order to demonstrate that the results are reasonably valid for the purpose of Section IV, B.2 of Appendix 1 to'10 CFR 50. ,
8.3.5 . Surveillance Reauirements A summary of the Interlaboratory Comparison Program results shall be included in the Annual j Radiological Environmental Operating Report. , 1 l j h 165.0 mi.
1 A l - i ] 04-23-97 09:13:'44 . J l Number TMI Radiological Controls ( GMClear Departmental Procedure 6610-PLN-4200.01 Tsue Revision No. Offsite Dose Calculation Manual (ODCM) 12 , j ; TABLE 8.1 j Sample Collection and Analysis Requirements l l Number of Samples _ ) Exposure Pathway. and
- Sampling and .
' Type and Frequency i .
and/or Sample Sample' Locations
- Collection Frequencyb of Analysish i
. 1. Airbome .
l j Radiolodine and Samples from 5 locations. Continuous sampler Radiolodine Canister: j Particulates from Table 8.4. operation with sample Analyze weeldy for 1-131. I collection weeldy, or more Particulate Fliter: frequently if required by dust
~
Analyze for gross beta loading. radioactivity following filter changed . Perl'orm
~
i j gamma isotcpic analysis' 1 on composite (by
,: . location) sample,
- quarterly.
.I i 1 i
- 2. Direct Samples from 40 Sample Quarterty Analyze for gamma dose i Radiation
- locations from Table 8.5 quarteny.
(using either 2 7 dosimeters 'or at least 1 l . Instrument for i continuously measuring ,. and recording dose rate ! at each location). i 1 - i ' 4 s 4 , d 9 I j 168.0 me. e s- ,,
.w 04-23-97 09:13:44 Number gm ggggggy W Rabiological Controis Departmental Procedure ,6610-PLN-4200.01
( )
- \_/ Title Hewsion No.
Offsite Dose Calculation Manual (ODCM) 12 TABLE 8.1 (Cont'd) Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and . Type and Frequency . and/or Sample Sample. Locations
- Collection Frequencyb of Analysisb
- 3. Waterborne -
- a. Surface' Samples from 2 locations Composite 9 sample over 1 Perform gamma isotopic
. from Table 8.6. monthly period, analysis' monthly.
Composite for tritium - e i sample from analysis quarterly. downstream (indicator) location . ,
- 1 sample from upstream q (control) location (or ,
(V ! location not influenced by the station discharge)
- b. Drinking Samples from 2 locations Compostte9 sample over 1 Perform gross beta and ,
from Table 8.6. monthly period. gamma isotopic analysis I monthly. Perform Sr-90 e 1 sample at the location analysis if gross beta of ' of the nearest water monthly composite >10 , supply that could be times control. Composite l affected by the station for tritium analysis discharge. ' quarterty. -
+ 1 sample from a control -
location.
- c. Sediment from Samples from 2 locations ~ Sar'n ple twice per year Perform gamma isotopic
. Shoreline (1 Control and 1 Indicator) (S'pring and Fall), the Interval analysis' on each from Table 8.7 not to exceed 184 days. sample.
167.0 mm
l s 04-23-97 09:13:44 Number (UClear i Radiological Controls Departmental Procedure 6610-PLN-4200.01 i w ~ True flevision No. l Offsite Dose Calculation Manual (ODCM) 12
\
TABLE 8.1 (Cont'd)
. Sample Collection and Analysis Requirements I
. Number of Samples Exposure Pathway dnd Sampling and Type and Frequ'ency b
1 and/or Sample Sample Locations
- Collection Frequency.b of Analysis
- 4. Ingestion
- a. Milk Samples from 4 locations Sample semimonthly when Perform gamma isotopic from Tab!e 8.8. animals are on pasture; analysis
- and 1-135 analysis on each sample..
monthly at other times. (
< Composite for Sr analysis quarterly,
- b. Fish Samples from 2 locations Sample twice per year Perform gamma isotopic
- from Table 8.9, (Spring and Fall), the interval and Sr-90 analysis on f not to exceed 184 days. edible portions.
\
[d
- 1 sample of recreationallv important bottom f eders and 1-sample of recreationally important predators in ,
the vicinhy of the station, discharge. e 1 sample of . recreationally important bottom feeders and 1 sample of 'recreationally important predators frorb an area not influenced by the station discharoe.
, t 0
' s.
168.0 me
04-23-97 09:13:44
. Number M Radiological Contmis l^I k_ Tibe MUClear Departmental Procedure 6610-PLN-4200.01 Revis'en No.
Offsite Dose Calculation Manual (ODCM) 12 TABLE 8.1 (Cont'd) Sample. Collection and Analysis Requirements s Number of Samples Exposure Pathway 'and . Sampling and Type and Frequency and/or Sample Sample Locations
- Collection Frequency 4 of Analysis o
- c. Food Samples from 2 locations Sample at time of harvest. Perform gamma isotopic *,
Products from Table 8.10 (when 1-131, and St-90 analysis available) on edible portions.
- 1 sample of green leafy vegetables or leafy ,
vegetation at a location in the immediate vicin'rty-of the sbtlon. (indicator) e 1 sample of same
., d species or group from a
() , location not influenced by the station discharge. Samples from 4 locations Sample fruits and Perform gamma isotopic
- (3 indicator and 1 control) vegetables at time of analysis' on edible from Table 8.10 (when harvest. portions.
available). [T
)
('v . 169.0 me W
i
, l 04-23-97 09:13:44 I
Number r') % (V GUClear WI Radiological Contmis Departmental Procedurg 6610-PLN-4200.01
- s. on No.
offrite oose calculation Manuai (ODCM) 12 TABLE 6.1 (Cont'd) Sample Collection and Analysis Requirements Table Notation
- a. Sampling locations are provided in Tables 8.4 through 8.10. They are depicted in Maps 8.1 through 8.3.
Deslations are permitted from the required sampling schedule il specimens are unobtainable due to hazardous conditions, seasonal unavailabirity, malfunction of automatic sampling equipment and other legitimate reasons. All deviations from the* sampling schedule shall be e,xplained in the Annual Radiological Environmental Operating Report. b.' Frequency notation: weekly (7 days), semimonthly (15 days), monthly (31 days), and quarterly (92 days). j All surveillance requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. A total maximum combined interval time for any 4' consecutive tests shall not exceed 3.25 times the specified collection or analysis interval. i l
- c. One or more instruments, such as a pressurized ion chamber for measuring an'd recording dose rate.
, continuously, may be used in place of, or in addition to, integrating dosinieters. For th'e' purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in.a l' O
packet are considered as two or more dosimeters. Film badges shall not be used as dQsimeters for ( measuring direct radiation.
~
Airbome particulate sample filters shall be analyzed for. gross beta radioactivity 24 hours or more after l d. sarnpting to allow for radon and thoron daughter decay, if gross beta activity in an air particulate sample (s) )' is greater than ten times the calendar year mean of control samples, Sr-90 and gamma isotopic analysis shall be performed on the individual s'ample(s).
- e. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. j
- f. Th'e "upstredm sample" shall be taken at a distance beyond significant influence of the discharge. The
" downstream sample" shall be taken ir an area beyond but near the mixing zone.
- g. Composite sample aliqdots shall be collected at time intervals that are short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
9 17'0.0' mm 1
04'-23-97 09:13:44 Number M Radiological Controls (^) MUClear Departmental Procedure 6610-PLN-4200.01
\/ T614e f%wision No.
Offsite Dose Chiculation Manual (ODCM) 12 TABLE 8.2 , Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne Particulate Water or gas Fish Milk Food Products Analysis (pCl/L) (pCl/mk (pCl/kg. wet) (pCl/L) (pCl/kg, wet) -
~H4 20,000(*)
, Mn-54 1000 30,000 Fe-59 400 '10,000 ~
CM8 1000 30,000 CMO 300 10,000 i Zn45 300 - 20,000 (v) Sr-90 Zr-Nb-95 8
'400 0.1 100 8 100 l-131 2 0.9 3 100 Cs.134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 -
Ba-La 140 200 300 (*)For drinking water samples. This is 40~ CFR Part 141 value, t [ V 171.0 me. i
04-23-97 09:13:44 , Nurnber gggggp TMI Radiological Controls
~ 2(')
Departmental Procedure 6610-PLN-4200.01 Revision No. Offsite Dose Calculation Manual (ODCM) 12 l I
. TA'BLE 8.3 ,
Detection Capabilities for Erivironmental Sample Analysis' l Lower Limit of Detection (lld)bd I Airbome j
' Particulate Fish Food Sedim.ent Water or Gas (pCi/kg. Milk Products (pCl/kg, Analysis' (pCl/L) (pCl/m3) wet) (pCl/L) (pCi/k'g, wet) dry)
Gross Beta '4 0.01 l H-3 2000 Mn-54 15 130 Fe-59 30 260 . n Co-58, 60 15 130 . ( )s Zn45 -30 260 Zr 95 30 Sr-90 2 0.01 10 2 10 l Nb-95 15 l131 Id 0.07 '1 60 Cs-134 15 0.05 - 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 A ( 172.0 mu
04-23-97 09:13:44 . 1 1
, Number n Nuclear 7"' "adio' oto*' contro'*
( j)' N htte
- Departmental Procedure 6610-PLN-4200.01 Revision No.
Offsite Dose Calculation Manual (ODCM) 12 TABLE 8.3 (Cont'd)- Detection Capabilities for Environmentai Sample Analysis
- Table Notation ;
, a. This list does not mean that only these nuolides are to be considered. Other peaks that are identifiable, which may be related to plant operations, together with those of the above nuclides, shall also be analyzed , ,
and reported in the Annual Radiological Environmental Operating Report. . , j
- b. Required detection capabilttles for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13 (Rev.1). , ;
- c. The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material'in a sample that will yield a net count, above system background, that will .be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation): l LL.D = 4.66 S" ' E V 2 . 22, Y exp (- A A C) fN $ 'Where: , I LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume.
. sbis the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, .
E is the counting efficiency, as counts per disintegration,- V is the sample size in units of mass or volume,
' 2.22 is the number of disintegrations per minute per picoeurie, Y is the fractional radiochemical yield (when applicable),
4 A is the radioactive decay constant for the particular radionuclide and at for environmental samples is the elapsed time b'etween sample collection, or end of the sarr'ple collection period, and time of counting. 1 Typical values of E, V, Y and At should be used in the calculation. I it should be recognized that the LLD is defined as an "a priorl* (before the fact) limit representing the capabi!!!y of a measurement system and not as an "a posteriorf" (after the fact) limit for a particular measurement. Analyses'shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations,. unavoidable small' samples sizes, the presence of interfering nuclides, or other uncontro!!able circumstances may render these llDs unach!evable. In such cases, the contributing factors shall be identified and described in the Ahnual Radiological Environmental Operating Report. l d. LL'D for drinking water. I l- 173.0 me
j 04-23-97 09:13:44 Number j Nuclear a
- ,q '"'l,ag D, mj % %
- esso.ptn.42co.o1 l b Tsue Rev*n No.
Offsite Dose Calculation Manual (ODCM) 12' TABLE 8.4 TMINS REMP Station Locations-Air Particulate and Air lodine Station Code Distance (miles,J . Azimuth M MaoNo. B14 0.8 28 ' 60
! E1-2 0.4 95 2 F1-3 0.6 105 70 G2-1 1.4 125 74 M2-1 1.3 253 3 2.6 358 4
) A3-1 H3-1 2.3 159 5 ) J3-2 2.9 181' 71 04-1 3.5 325 61 G10-1 9.8 127 6 J15-1 12.6 180 7 Q15-1 13.5 305 8 l TABLE 8.5 TMINS REMP Station Locations-Direct Radiation (TLD) Station Code DistanceImites) Azimuth M Mao No. 1 A1-1 . 0.4 0 1 l A1-4 0.3 5 9 j B1-1 0.6 25 , 10 l B1-2 0.4 , 26- 11 j B14 05 15 12- i C1-2 0.3 54 13 D1-1 0.2 74 14 E1-1 02 95 15 , E1-2 04 95 2 I
. E14 02 98. '16 F1-2 0.2 109 17 G1-3 0.3 129 18 H1-1 0.5 167 '
19 . H1-9 0.3 167 20 l J11 0.8 184 21 l J1-3 0.3 189 22 J1-4 0.4 188 23 Ki-4 0.2 208 24 K1-5 0.2 202 25 L1 1 0.1 235 26 M11 0.1 249 27 N 9 N1-3 P1-1 P1-2 0.1 0.4 0.2 270 293 290 28 29 30 174.0 mm j
04-23-97 09:13:44 ' l ' Number Nuclear ' a^di*9'ca' co"tr*
^ 6610-PLN-4200.01
=, l Departmental Procedure k Title Revision No. Offsite Dose Calculation Manual (OD'CM) 12 I TABLE B.5 (Cont'd) TMINS REMP Station Locations-Direct Radiation (TLD) Station Code Distance (miles) Azimeh (*) Mao No.- 01-2 0.2 318 31 Rt 1 0.2 335 '32 < C2-1 1.6 48 33 K21 1.1 200. -Q4 M21 1.3 253 3 A31 . 2.6 358 4 H3-1 2.3 159 5 i R3-1 2.6 338 35 B5-1
' .8 4 18 36 C5-1 4.5 42 37 E5-1 4.6 '
81 38 j F5-1 . 4.7 107 39 G5-1 , 4.8 131 40 HS-1 4.T 157 41 l O J5-1 4.9 182 42 (-) K5-1 5.0 200 43 i LS-1 4.1 228 44 f MS-1 4.3 24'9 45 I NS-1 4.9 268 46 P5-1 4.9 285 47 05-1 5.0 318 48 R51 4.9 339 .49 D6-1 5.2 55 50 l E7-1 6.8 06
- 51 091 8.5 308 52 810-1 9.4 21 53 G10-1 9.8 127 6.
G15-1 14.4 124 54 J15-1 12.6 180 7 Q15-1 ' 13.5 305 8 R15-2 12.4 329 55 e d i 175.0 snu l l l
- 04-23-97 09
- 13:44 Number o
( Nuclear " "*d'o' a'ca' co"o'$
' Departmental Procedure 6610-PLN.-4200.01 Title Revision No. ,
Offsite Dose Calculation Manual (ODCM) 12 TABLE 8.6 TMINS REMP Station Locations-Surface Water Station Code ' Distance (miles) Azimuth M Map No.
- ) P1-3 (R) 0.1 284 56 j J12 (R) 0.5 188 57 J2-1 (R) 1.5 182 58 A3-2 (R) 2.5 355 59 09-1(F) 8.5 308 52 G15-1 (F), 14.4 124 54 G15-2 (F) 13.6 128 62 G15-3 (F) 14.8 124 63 4
J15-2 (F) 14.7 178 64
. F151 (R) 12.6 -
122 65' s (R) = Raw Water (F) = Finished Water i ( TABLE 8.7
.TMINS REMP Station Locations-Aquatic Sediment 1
Station Code Distance (miles) Azimuth M MapNo. l A1-2 0.8 6 66 l A1-3 0.5 0 67 G1-1 < 0.3 137 68 K1-3 0.3 202 69 J21 1.5 182 58 4 176.0 mm l
j , 04-23-97 09:13:44 1 I Number M Radidogical Conads
/
( MUClear Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose C'alcula' tion Man 6al (ODCM) 12 I TABLE 8.8 TMINS REMP Station Locations-Milk, Station Code Distance (miles) . Azimuth'M ~ MapNo. D2-1 1.1 65 72 . E2 1.1 93 73 G2-1 1.4 125 74 , A41 3.3 10 75-F41 3.2 104 76 P7-1 6.7 293 77 K15-2 12.8 208 , 78 i TABLE 8,9 TMINS REMP Station Locations-Fish Station Code Station Location IND Downstream of Station Discharge BKG Upstream of Station Discharge O e O . 177.0 me. W
04-23-97 09:13i44 Number Nuclear T"' a^dio'octo=' contro'$ Departmental Procedure 6610 PLN-4200.01 O Taue Revision No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 8.10 TMINS REMP Station Locations-Food Products
- jtation Code Distance (miles)* Azimuth (*) ._ Mao No.
D1-3 0.5 65 79 E1-2 0.4 95 2 F1-1 0.5 117 80 H1-2 0.9 '150- 81 D21 ' 1.1 65 72 4 E2-2 1.1
- 93 73 -
G2-1 1.4 125 74 J2-2 1.5 178 82 M22 1.3 252 83' N2-2 1.3 265 .84 A4-1 33 10 75 j F4-1 0.2. / 104 76
~
P7-1 6.7 293 77 A15-1 10.5 10 85 N K15-2 q 12.8 208 78 MIS-2 13.6 253 86 ! R15 2 12.4 329 55 l 4 f S t N) . 178.0 nu,
04-23-97 09:13:44 Number
,es MUClear Tui a di. i ai ai controis i i Departmental Procedure 6610-PLN-4200.01
\- Tm'
%sion No.
Offsite Dose Calculation Manual (ODCM) 12 , MAP 8.1 . l THREE MILE ISLAND NUCLEAR STATION ) LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 1 MILE OF THE SITE l t us-
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l l 04-23-97 09:13:44 ~ Nurnber O' g Nuclear TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01
'O Title Revision No.
Offsite Dose Calculation Manual (ODCM) 12 MAP 8.2 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL E.NVIRONMENTAL MONITORING PROGRAM STATIONS WITH.IN 5 MILES OF THE SITE l ( \ O 348.75* A ,# m
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04-23-97 0':13:44 9 , Number l r f Nuclear " "a*'a'd con"* Departrnental Procedure 6610-PLN-4200.01 me amnsion No. I Offsite Dose Calculation Manual (ODCM) 12
, . . MAP 8J THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STA'TIONS GREATER THAN 5 MILES FROM THE SITE l
O l mn - .A 11.25-R , B I a2s.25-
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04-23-97 09:13:44 1 Number . l
/5 - 1 (UClear MI Radidogical Contrds Departmental Procedure 6610-PLN-4200.01 bm Revision No.
Offsite Dose Calculation Manual (ODCM) i2 {
' .0 9 PART 111 REFERENCES -
- 1. EPRI NP-3840, RP 1560-3 Final Report,
- Environmental Radiation Doses From Difficult-To-Measure Nuclides," January 1985 - '
- 2. " Evaluation of the Th'ree Mile Island Nuclear Station Unit 1.to Demonstrate Conformance to the Design Objectives of 10 CFR 50, Append!x 1,* Nuclear Safety' Associates, May 1976 1
- 3. TMI-1 Fiital Safety Analysis Report (FSAR)
- 4.
- TMI-2 Final Safety Analysis Report (FSAR) .
l
- 5. 'Meteorologicalinformation and Dose Assessment System (MIDAS)
- 6. NUREG-0017,."CalcuIation of Releases of Radicar ve Materials in Gaseous and.Uquid Effluents from
,PWR," Revision 1,1985 .
- 7. NUREG 0133,
- Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,' October 1978 I
Ci 8. NUREG-0172, " Age-Specific Radiation Dose Commitment Factors For A One-Year Chronic Intake," November 1977
- 9. Regulatory Guide 1.21, " Measuring. Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Uquid and Gaseous . Effluents from Light-Water _ Cooled Nuclear Power Plants,." Revision 1, June 1974
- 10. Regulatory Guide 1,109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix 1,* Revision 1, .
October 1977 .
- 11. Simplified Environmental Effluent Dosimetry System (SEE'DS)
- 12. TMI Recirculation Factor Memos, April 12,1988 and March 17,1988 I
- 13. TMI-1' Operations Procedure, 1101-2.1, " Radiation Monitor Set Points" l
- 14. Title 10, Code of Federal Regulations, " Energy"
- 15. TMI-1 Technical Specifications, attached to Facility Operating Ucense No. DPR-50
- 16. Regulatory Guide 1.111,"Mefhods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Ught-Water-Cooled Reactors,' Revision 1, July 1977
- 17. TMI-2 PDMS Technical Specifications, attached to Facility License No. DPR-73
- 18. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1,
) November 1979
[
- 19. Title 40.. Code of Federal Regulations, " Protection of Environment" 182.0 nm
04-23-97 09:13:44 Number Nuclear TM' aad'o'oo'ca' cootro Departmental Procedure 6610-PLN-4200.01 ' , Title Rewston No. Offsite Dose Calculation Manual (ODCM) 12
- 20. Regulatory Guide 4.13, " Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications," Revision 1 July 1977 21e Post-Defueling Monitored Storage Safety Analysis Report (PDMS SAR) l a a
g e 4 4 e 4 o O 183.0 - ana l
1 04-23-97 09:13:44 Number 4I Nuclear 7"' ""dio'ooica' contro'$ Departmental Procedure 6610-PLN-4200.01 Title fevision No. b . Offsite Dose Calculation Manual (ODCM) 12 l 1 i i - - 1 I 4 i 1 1 1 4 J PART IV REPORTING REQUIREM'ENTS f e I
. 184.0 me,
)
04-23-97 09:13':44-Number ; G 4tEClear TMl Radiological Controls
,[d Tiu.
Departmental Procedure 6610-PLN-4200.01
- a. vision no.
)
l Offsite Dose Calculation Manual (ODCM)' 12 PART IV
, Rep'orting Requirements 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPEdATING REPORT" .
1.1 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted to the Commission prior to May 1 of each year. 1.2 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological envirorimental monitoring activities for the - report period, including a comparison with pre-operational studies. with operational controls as appropriate, and with previous enyironmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of Land Use Censuses required by Part 111, Section 8.2.' 1.3 The Anriual Radiological Environmental Operating Reports shall include the summarized tabulated ' l results pf analysis of all radiological environmental samples and environmental radiation l measurernents required by Part til Table 8.1 taken during the period pursuant to the locations ' specified in the tables and figures in this ODCM, as well as summarized and tabulated results of (9j
/
these analyses and measuremsnts in a format similar to the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a suppicmentary report. 1.4 The reports shall also include the following: a summary description of the radiological environments . monitoring program; a map (s) of all sampling locations keyed to a table giving distances and directions from a point that is midway between the Reactor Buildings of TMI-1 and TMI-2; the results of licensee participation in the Inter!aboratory Comparison Program, required by Part 111, Section 8.3; discussion of all deviations from the sampling schedule of Part lit, Table 8.1; discussion of a!I the required analyses in which the LLD required by Part lil, Table 8.3 was riot achievable. f v
"A single submitta! may be made for the station.
185.0 mm
1 04-23-97 09:13:44 Number m
) $UCIOSF M. Radiological Controls Departmental Procedure 6610-FLN-4200,01 sj Thie Revision No.
)
Offsite Dose Calculation Mar 1uai (ODCM) 12 l 2.0. TMl ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NOTE A single submittal may be made for the station. The submittal should . combine those sections that are common to both units at the station , however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit. 2.1 Routine Radioactive Effluent Release Reports covering the operations of the unit during the previous - 12 months of operation shall be submitted prior to May 1 for TMI-1 and TMI-2. 2.2 The following information shat! be included in both Radioactive Effluent Release. Reports to be - submitted each year: The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Reg. Guide 1.21, Rev.1, with data summarized on a quarterly basis following the format of. Appendix B thereof.
, 2.3 The Radioa'ctNe Effluent Release Reports shaft include the following information for each type of
[ solid waste shipped offsite during the report period: V .
- a. container volume,
~
, 1
- b. total curie quantity (specify whether determined by meast$rement or estimate),
- c. principal radionuclides (specify whettier' determined by measurement or estimate),
- d. type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
- e. type of silipment (e.g., LSA, Type A, Type B) and
- f. . solidification agent (e.g., cement).
l 2.4 The Radioactive Effluent Release Reports sha!! include a summary of unplanned releases from the , site.to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the l reporting period. , 2.5 The Radioactiv'e Effluent Release Reports shall include sny changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the OFFSITE DOSE
, CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or
. environmental monitoring identified by the land use census pursuant to Part lit Section 8.2.
2.6 The Radioactive Effluent Release Reports statl include the instrumentation not retumed to OPERABLE status within 30 days per ODCM Part I Controls 2.1.1b and 2.2.1b, and ODCM Part 11 Control 2.2.1.b. O\ 6 s 186.0 mu
04-23-97 09:13:44 , Number O t 1 MUClear WI Radiological Controls Departmental Procedure 6610-PLN-4200.01 N TiUe Revision No. Offsite Dose Calculation Manual (ODCM) 12 l 2.7 The Radioactive Effluent Release Report to be submitted shall include an annual summary of hourly l meteorological data collected over the previous year. This annual summary may be either in the I form of an hour-by-hour listing of wind speed, wind direction, atmosphere stability, and precipitation (if measured) on magnetic tape, or in the forrri of joint frequency distribution of wind speed, wind l direction, and atmospheric stability.' , l 2.8 The Radioactive Effluent Release' Report shall ir5clude an assessment of the radiation doses to
, l MEMBERS OF THE PUBUC due to the radioactive liquid and gaseous effluents released from the
~
. I Unit or station during the previous calendar year. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by samp!!ng frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with this ODCM. ~
2.9 The Radioactive Effluent Release Report shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBUC due to their actMties inside the SITE BOUNDARY during the report period, to verify compliance with the limits of 10CFR20.1301(a)(1). A!! assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. - 2.10 The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the [] ('y likely most expo' sed real individual from reactor releases and other nearby uranium fuel cycle sources including doses from primary effluent pathways and direct radiation for the previous 12 consecutive months to show conformance with 40 CFR 190 " Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contributions from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1. i
-g 187.0 ma,
l 04-23-97'09:13.:44 Nurbber (^
) Title (UClear M Radidogical Contrds
' Departmental Procedure 6610.-PLN-4200.01 FWvision No, l
Offsite Dose Calculation Manual (ODCM)' 12 l l 3.0 PART IV REFERENCES 3.1 Radiological Assessment Branch Technical Position, Revision 1, Novernber 1979 , 3.2 Regulatory Guide 1.21, "Measurin'g, kvaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Uquid and Gaseous Effluents from Ught-Water-Cooled Nuclear l Power Plants,* Revision 1, June 1974 3.3 TMI-1 Technical Specifications, attached to Facility Operating Ucense No. DPR-50 3.4 Title 40, Code of Federal Regulations,'" Protection of Environment" 3.5 Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine' Releases of, Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix If Revision 1, , October 1977 1 1, 3.6 Title 10, Code of Federal Regulations, " Energy" ' 3.7 Regulatory Guide 1.111, " Methods of Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine' Releases from Ught-Water-Cooled Reactors," Revision 1, July 1977 f
*y 3.8 Regutatory Guide 1.112, .* Calculation of Releases of Radioactive Materials in Gaseous and Uquid Effluents,from' Light-Water-Cooled Power Reactors,* Revision 0-R, April 1976 j 3.9 Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routirie Reactor Releases for the Purpose of implementing Appendix 1,'" Revision 1, April 1977 l
l 1 l l e. 188.0 m
\
l 04-23-97 09:13:44
~s .
- Number Nuclear " a d*oo * '*
Departmental Procedure . , 6610-PLN 4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 11 APPENDD('A' . Pi - Pathway Dose Rate Parameter Pi (inhalation) = k'(BR) DFA (Eq A-1) Where: P, = the pattiway dose rate parameter 3 for radionuclide, I, (other than noble gases) for the inhalation pathway, in mrem /yr per microcurie /m . The dose factors are based on the critical indMdual organ for the child age , group. - k' - conversion factor,1E6 pCl/rnicrocurie 3 BR , 3700 m /yr, breathing rate for chid (Reg. Guide 1.109/Rev.1, Table E-5)' DFA, = the maximum organ inhalation dose factor for the infant age group for the Ith radionudide (mrem /pCl). Values are taken from Table E-10, Reg. Guide 1.109 (Rev.1).
~~
A Resolution of the units yields: (ODCM Part 111 Table 4.6)
% Pi (inhalation) = 3.7E9 DFA, (mrem /yr per pCI~m / )
8 (Eq A 5) NOTE The latest NRC Guidance has deleted the requirement to determine P 6 (ground plane) and Pi (food). In addition, the crftical age group has ) been changed from infant to child. t g-0 ( en J. E1 1. 6
04-23-97 09:13:44 ( - , net-Nuclear ' ' "adid*= c ""ot* Departmental Procedure 6610-PLN-4200.01 no. a.ww>n no. Offsite Dose Calculation Manual (ODCM) 11 4 APPENDIX B Ri-Inhalation Pathway Dose Factor. - R3 = k'(BR) (DFAg),(mrom/yr per microcurie /m3)
. (Eq B-1)
Whore: k' = conversion factor,1E6 pCI/ microcurie BR = breathing rate, 1400,3700,.8000,'80'00 ms /yr for infant, child, teenager, and adult age groups, respectively. (Reg. Guide 1.109, Rev.1, Table E-5) -
- QFAg = the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the Ith .
radionucikfe, in mrem /pCl. The total body is considered as an organ in the selection of DFA go. Values are taken from Tables E-7 through E-10, Reg. Gukle 1.109 (Rev.1). Resolutions of the units yields: g Ri , (1.4ES) (DFA i ,,,,) infant (ODCM Part lit Table 5.2.1')' Ri = (3.7E9) (DFA i ,,) chad (OhCM Pdll! Table 5.2.2) R1 = (8.0E9) (DFA ,,,o) i teen and adult (ODCM Part til Tables 5.2.3 and 5.2.4)
~
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04-23-97 09:13:44 , Number V - Nuclear . - ' '"' pa"*0n'$,$"fu,e'* , 6610-Pl.N-4200.01 ite. , N&on No. Offsite Dose Calculation Manual (ODCM)" 11
- ~ '
APPENDIX C R1- Ground Plane Pathway Dose Factor ' R, '= k' k" (SF) (DFG) [(1-e T)/AJ s , (Eq C-1)
- Wnere:
k' = convers;on 1 actor,1E6 pCl/ microcurie k" = conversion factor,8700 hr/yr
- J, - decay constant for the if radionuclide, sec ,
t= the exposure time (this calculation assumes that decay is tN only operating removal rnechanism) 4.73 x s 10 sec. (15 yrs), Reg. Guide 1.109 (Rev.1), Appendbc C DFG,= the ground plane dose conversion factor for the i* radionuclide (mrem /hr per pCi/m2 ). Values are taken from Table E-6, Reg. Guide 1.109 (Rev.1). These values apply to all aoe aroups. l l' SF = 0.7, shielding factor, from. Table E-15. Beg. Guide 1,.109 (Rev.1) Reference CDCM Part ill Table 5.3.1 - ' E O 9
/
es. G E3-1 ms e 9
04-23-97 09:13:44 ( \ ' _ Nbmber .
- () , gggp TMI Radiological controls Departmental Procedure 6610-PLN-4200.01 rm. sem.on No.
Offsite Dose Calculation Manual (ODCM) ' 3 APPENDIX D RI- Grass Cow. Milk Pathway Dose Factor R= k' [(0, x U,) / (A, + A,,)] x (F ) x (r) x (DFV x [((f, x f,)/Y,) + ((I-f, x f,) ed fh)/Y,] e'Pf ' , (Eq D-1) i Where: k' = corwersion factor,1E6 picoeurie/ microcurie (pCl/pci) , Q, - cow consumption rate, 50 kg/ day, (Reg. Guide 1.109, Rev.1) l
- goat consumption rate, 6 kg/ day, (Reg. Guide 1.109, Rev.1. Table E-2) l U, = Receptor's mDk corisumption rate; 330, 330, 400,310 liters /yr for infant, chDd, teenager, and adult age groups, respectively (Reg, Guide 1.109. Rev.1)
Y, = agricultural productMty by unit area of past'ure feed grass,0.7 kg/m' (NUREG4133) ~ l Y, = agricultural productMty by unit area of stored feed,2.0 kg/rrf (NUREG-0133)
- p)
I ( F. = stable element transfer coefficient, { Table E-1, Reg. Guid'e 1.109, Rev.1) V l r- l fraction of deposited activity retained in cow's feed grass 0.2 for particulates,1.0 for radioiodine ' (table E-15, Reg. Guide 1.109, Rev.1).
~
DFh = . the ingestiori dose factor for organ, o, and the'Ith radionuclide for eitch respective age group, a (Tables E 11 to E 14, Reg. . Guide 1.109, Rev.1)
~
.J= decay constant for the ith radionuclide, seed 4
. A,, = decay constant for weathering,5.73 x 10* sec (NUREG4133): based on a 14 day half !!fe
. t, = 1.73 x 10'sec, the transport time from pasture to cow to milk to receptor (Table E-15, Reg.
Guide 1.109, Rev.1), or 2 days ' ll 8 t, = 7.78 x 10 sec, the transport time from pasture to harvest to cow to mHk to receptor (Table E-15 Reg. Guide 1.109, Rev.1), or 90 days , f, = 1.0, the fraction of the year that the cow is on pasture f, = 1.0, the trabtion of the cow feed that is pasture grass whHe the cow is on pasture [ b
'sx .,
E4-1 me.
04-23-97 09i13:44 - 4 (O - _ mmber (" ' LIClear TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01
%. eenson m.
- Offsite Dose Calculation Manual (ODCM)' 11 APPENDIX D (Cont'd)
The concentration of tritium in mDk is based on the airborne' concentration rather than the deposition. Therefo e, R, is based on (X/Q): - Rc w = k'k'" F,0, UgDFQ (.7515/H]) (Eq D 2' ) Where: k"' = 1E3 grams /kg ' ' H= 3 8 grams /m , absolute humidity of the atmosphere
.75 = fraction 6f the total feed grass mass that is water ,
.5 = ratio of the specific activity of the feed grass water to the atmospheric water (NUREG4133)
DFQ = the ingestion dose factor for tritfum and organ, o, for each' respective age group, a (Tables E 11 to E-14 Reg. Guide 1.109, Rev.1) ..
, All oth5r parameters and values are as given at1gv.p. -
NOTE Goat-mak pathway factor, Ri wEl be computed using the cow-milk , pathway factor equation. Fmfactor for goat-milk wDI be from Table E-2 Reg. Guide 1.109, Rev.1.
Reference:
ODCM Part til Tables 5.4.1 to.5.4.4 9 9 9 e. O O . L E4-2 mm
)
04-23-97 09:13t44 y) , Nuclear ' "*d'dd'"co*d* Nurnber Departrnenta! Procedure
- 74. , 6610-PLN-4200.01 n,vison No.
Offsite Dose Calculation Manual (ODCM)
-11 APPENDIX E '
, RI . Cow-Meat Pathway Dose Factor R} = x (F,) x (r) x k'.
[((1,[(Q,'x x f,)/Y,)U,) / (A e+ J,,)]Wh)/Yf ] x e4(DF() x. 3
+ ((I-f,f,) ,
(Eq E-1), Where:
< ~
k' =. conversion factor,1E6 picoeurle/ microcurie (pCl/pci)? Q, =
- cow consumption rate,50 kg/ day, (Reg. Guide 1l109, Rev.1)
U, =~ Receptor's meat consumption rate: 0, 41,65,110 kg/yr for infant, child, teenager, arKi adult age groups, respectively (Reg. Guide 1.109, Rev.1) F, = .the stable element transfer coefficients, days /kg [rable E-1, Reg. ' Guide 1.109, Rev.1) r= fraction of deposited actMty retained in cow's feed grass,0.2 for particulat'es,'1.0 for radioiodine g (Table E-15, Reg. Guide 1.109, Rev.1) f. DFQ = the inDestion dose factor for organ, o[and the ith radionuclide for each respective age group, a (Tables E 11 to E-14, Reg. Guide 1.109, Rev.1) . A=i decay constant for t'he radionuclide I, seed
- 4 = decay constant for weathering 5.73 x 10#seco (NUREG4133), based on a 14 day half life s
t, = ,1.73 x lo sec, the transport, time from pasture to receptor (NUREG4133) - 8 t, = 7.78 x 10 sec, the transport time from crop to receptor'(NUREG-0133) - Y, -- agriedtural productMty by unit area of pasture feed grass 0.7 kg/m2(NUREG4133) Y, = agriedtural productivity by unit area of stored feed 2.0 kg/m 2(NUREG4133)
~
~
1, = 1.0, the fraction of the year that the cow is on pasture 1, = 1.0, l'he traction of the cow feed that is pasture grass while the cow is on pasture The concentration of tritium in meat is based on the airbome concentration rather than the deposition. Therefore, Ri is based on (X/Q); R, = k'k'" F, Q, U, (DFlw) x 0.75 x (0.5/H]) (Eq E-2) Where: w All terms are as defined above'and in Appendix D. '
/ '
Reference:
ODCM Part lil, Tables 5.6.1 to 5.~6.4 E5-1 mi. t
04-23-97 09:13:44 O N j ', -(UCIOSr m Radi i gacontrois _ Num' ber Departmental Procedure 6610-PLN-4200.01 Title Fievision No. Offsite Dose Calculation Manual (ODCM) 11
~-
APPENDIX F ,
/ /
Ri- Vegetation Pathway Dose Factor . R, = t k' x [r/ (Y, (A, + y)] x (DF() x [(Ua) fg eTL + U 8, f, e#h] (Eq F-1) Where: k' = 1_E6 picoeurie/rnicrocurie (pCl/pc0 L U , = ' the consumption rate of fresh leafy vegetation, O, 26,42,64 kg/yr for irfant, child, teenager, or adult. age groups, respectively (Reg. Guide 1.109~ Rev.1) Usa ." . the consumption rate of stored vegetation,0,520,630,520 kg/yr for infant, chDd, teenager, or adult age groups respectivsly (Reg. Guide 1.109, Rev.1) , , f=g the fraction of the annual intake of fresh leafy vegetation grown locally, = 1.0 (NUREG 0133) ,
, f, = the fraction of the stored vegetation grown locally = 0,76 (NUREG-0133) ,
[m V} t-g the average time between harvest of leafy vegetation and its consumption,8.6 x 104 seconds [ Table E 15, Reg. Guide 1.109, Rev.1 (24 hrs)) t, - - the average timo between harvest of stored leafy vegetation and its consumption,5.18 x 106seconds, [ Table E 15, Reg. Guide 1.109, Rev.1 (60 days)], 2 y, = the vegetation area density,2.0 kg/m (Table E-15, Reg. Guide i.109, Rev.1) - All other parameters are as previously defirdd. The concentration of tritium in vegetation is based on the airbome concentration rather than the deposition. Therefore, Ri is based on (X/Q) ' L R = k'k'" [U , f + U n ,]f (DF )'(.75 [.5/H]) (Eq F-2) Where: i All terms are as defined above and in Appendix D.,
Reference:
ODCM Part 111, Tables 5.7.1 to S.7.4 4 ES1 mm
i 04-23-97 09i13:44 1 l l l 7m) . (J , Number N.uclear -
= aadidos ~ d' Departmental Procedure ' '
. tee 6610-PLN-4200.01 n==on te.
( Offsite Dose Calculation Manual (ODCM) 3 APPENDDC A-F REFERENCES I (Page 1'of 4) g i
< 1
. Parameters Used in Dose Factor Calculations Origin of Value
- Parameter TaNe in Section of Value Site-R.G.1.109 NUREG-0133 Specific
*** For P, m
- DFA Each radionudide _
E4 Note 1 BR 3700 rn'/yr (chad) E-5 rr ***For Ri (Vegetation)*" - s ( ) r Each element type . . E
- Y, 2.D kg/rrf ' .
E-15 Aw 5.73 E-7 sec' 5.3.1.3 DFL Each age group and radioriuclide E41 thru E-14 Note,1
'U,5 Each age group E-5 ft 1.0 5.3.1.5 t, &6 E + 4 seconds E-15 .
Uf Each age group E-5 f, 0.76 5.3.1.5
- t. 5.18 E + 6 seconds E-15 H RO grams /kg 5.2.1.3
***For Ri (Inhalation)"*
BR Each age group E-5 .
' DFA Each age group and -
nucrede E 7 thru E-10 . Note 1 4 , 1 f \. . E7-1 mm L 1
l 1 04-23-97 09:13:44 . n (v) s M , Nuclear " ""d* co*** Departmernal Procedure 6610-PLN-4200.01 I w. Revisson No. OffSite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES
, (Page 2 of 4)
- Parameters used in Dose Factor Calculations l
Origin of Value Table in Section of - Site-Pararneter. Value R.G.1.109 - NUREG4133 Specinc
*** For R, (Ground Plane) *** ,
4 SF . ' 0.7 E-15 DFG, Each radionuclide E-6 t 4.73 E + 8 sec 5.3.1.2 m [ \ '
\v./ 0,(cow)
'*** For R1 (Grass /Anunal/ Meet) ***
So kg/ day E-3 Q, (Goat) 6kg/ day E3-Ref. On!9 - U, Each age group E-5 Aw 5.73 E-7 sec' 5.3.1.3 F, (Both) Each element E-1 t Each element type .E-15 DF( Each age group and nudide E-11 thru E-14 Note 1 f, '1.0 5.3.1.3 . Note.2 f, 1.0 5.3.1.3 Note 2 Y, 0.7 kg/nf E 15 t, 7.78 E + 6 see . E 15 Y, 2.0 kg/m8 E-15 t, 1.73 E +' 6 see E 15 H- 8,0 grams /kg . 5.2.1.3 A E7 ~ zn= 4
i 04-2'3-97 09:13:44 ' e p ' i bClear WI RaddoM Contrds rm. DesL..iG Procedure 6610-PLN-4200.01
, n, an ha.
Offsite Dose Calculation Marual (ODCM) ' 3 APPENDIX A-F REFERENCES (Page 3'of 4) ~ Parameters used in Dose Factor Calculations Origin of Value . Table in Section of Site. Parameter Value R.G.1.109 NUREG4133 Sp=*c
*** For R, (Grass / Cow / Milk) =
0, 50 kg/ day E-3 U, Each age group E-5 Aw 5.73 E 7 sec' 5.3.1.3 F. Each element ** E-1
-rh
) r Each element type ..- , E-15 d Each age group arc ?melide DFL E-11 thru E-14 Note 1 Y, 0.7 kg/m' E-15 .
t, 7.78 E + 6 see E-15
- Y, . 2.0.kg/rtf ' E 15 t, 1.73 E + 5 see
. E-15 f, 1.0
. 5.3.1.3 f, ' 1.0
. S.3.1.3 H 6.0 grams /kg ,
5.2.1.3 l 1 v
- E7-3 m e
23-97 09:13:44 1
,m '
k e. . 1 14 r.N] Nuclear "Depermrental
"*d*ad Procedure co'*d' 6610-PLN 4200.01 a.m.on m.
- Offsite Dose Calculation Mandal (ODCM) 3 l
4 l APPENDIX A-F REFERENCES ~
\
'(Pade 4 of 4) '
NOTES 1. Inhalation and ingestion dose factors were taken from the . indicated roup, for each source F nuclide,table. referenced the organ dose factor used was the highest dose tatsor for that t'ucfide
- l
- 2. , l Typically beef catt:e are raised a!! year on pasture. Annual land surveys have i number of goats raised within 5 mies typica!!y are used for grass corard and not food 1 Nevertheless, the goats can be treated as full meat sources where er present, de) numbers cannot sustain the maat consumption rates of Table E-5, NUREG4133 . 3 SEFERENCES 1
i the Purpose of Evaluating Compliance with r 10 CFR Par{ uents for t
]
- 2. TM1-1 Technical Specifications, attac
' to FacBN Operating Ucense No. DPR-50. 3. NUhtEG4133,
- Preparation of Radiological Emuent Tecbnical Sp October 1978.'
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Encke,ure 2 1996 Annual Radi(xttive Effluents Releases Reprt fir TMI 6710-97-2161 Pmcedure Change Request (PCR) 1 RC-95-(MMI to the ODCM,6610-PLN-4200.01 1
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s 04-23-97 09:13:44 . ] Number Nuclear
. TMI Rabiological Controls 4
oegen,oomw e,oceoure es,o.ptN-4200.oi g, fWViteOn No, , b l Offsite Dose Calculation Manual (ODCM) 1.2 l l l r i , i 4 1 O l e 0 PART lli
. EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES l
l y. e e 9
~
4 89.0 822 6
1 04-23-97-09:13:44 Number M Radbogn! Controls MUClear Departmental Procedure 6610-PLN-4200.01 l {*)huo V .
.Revisen No, Offsite Dose Calculation Manual (ODCM) 12 1.0 UQUID EFFLUENT MONITORS 1.1 TMI-1 and TMI-2 Uould Radiation Monitor Set Points I
The liquid effluent off-line monitors are set such that the concentration (s) of radionuclides in the liquid offluents will not exceed ten times the concentrations specified in 10 CFR 20, Appendix B Table 2, Col 2. Table 1.1 lists the Uquid Effluent Release Points and their parameters; Figure 1.1 provides a Uquid Release Pathway Diagram. To meet the above limit, the alarm / trip set points for liquid effluent monitors and flow measuring devices are set in accordance with the following equation: c*f<C (eq 1.1) F+1' where:
~
C= ten times the effluent concentration of 50 CFR 20 for the site, in pCl/ml. l c- the set point in Ci/ml, of the liquid effluent monitor measuring the radioactivity
/ . concentration in the effluent line prior to dilution and release. The set point is inversely
(*' / proportional 10 the maxirnum volumetric flow of the effluent line and proportional to the rpini, mal volumetric flow of the dilution stream plus the effluent stream. The alert set point value is set to ensure that advance waming occurs prior to exceeding any limits. The high
~
otarm set point value is such tant if it were exceeded, it would result in concentrations exceedin'g ten times the 10 CFR 20 concentrations for the unrestricted area.
,f, flow set ' point as measured at the radiation monitor location, in volu'me per unit time, but in the same units as F below.
F= flow rate of dilution water measured prior to the release point, in volume per unit tirne. , The set point concentration is reduced such that concentration contributions from multiple release points would not combine to exceed ten times 10 CFR 20 concentrations. .The set point- , concentration is convered to set, point scale units using approprtate radiation monitor calibration l factors. This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and, for batch releases, the Releasing Radioactive Uquid Waste procedure. e O 4 90.0 mm l
04-23-97 09:13:44 Number l M Radiological Controls
<G
( )
- $UClear Departmental Procedure 6610-PLN-4200.01
%. J me -
nasmatp. l l Offsite Dose Calculation Manual (ODCM) 12 1.2 TMI Licuid Effluent Release Points and Ucuid Radiation Mon! tor Data TMI-1 has two required liquid radiation monitors. These are RM-LS and RM-L12. These liquid , release point radiation monitors and sample points are shown in Table 1.1. (The TMI outfall radiati.on monitor, RM-L7, is also listed for information only.) l TMI-2 does not have any requ,lred liquid radiation monitors, but does utilize RM-L12, and RM L7 for ; release of liquid waste. l
.1.2.1 RM-L6 l RM-L6 is an off-line system, monitoring radioactive batch discharges from the TMI-1 liquid l radwaste system (see Figure 1.1). These batch releases are sampled and analyzed per s!!e l procedures prior.to release. The release rate is based on releasing one of two Waste Evaporator Condensate Storage Tanks (WECST) at a flow which will add less than.10%, of ten times the 10 CFR 20 concentrations to radionuclide concentrations in the unrestricted area, including conservative default values for Sr-89, Sr-90, and Fe.-55.
The release flow rate used is the most restrictive of three flow rates calculated for each liquid batch release, per the approved plant procedure. A (v Three Dilution Factors (DF) are calculated to ultimately calculate the batch release' flow rate.' These three DF's are calculated to: 1) insure each radionuclide. released to the unrestricted area is less than 10 percent of ten times the 10CFR20 radionuclide concentrations,2) ensure each liquid batch release boron concentration to the river will not exceed 0.7 ppm, and 3), ensure ten times the 10CFR20 concentration for Ceslum-137 (IE-5 pCi/ml) will not be exceeded based on the calculated high alarm set point and the expected response of RM-L6 to this concentration of Cs-137. The ;naximum release figw rate is then calculated by dividing the most restrictive (largest) DF into 90 percent of the current dilution flow rate'of the Mechanical Draft Cooling Tower (MDCT). This conservative flow rate is then multiplied by O'.9 for the allowable flow rate.
- Calculation of 10' percent 10% of ten times the 10CFR20 concentration DF:
DF, '= y (SA;) + (10% of. ten times the 1dCFR20 concentration) SA = Specific Activity of each identified radionuclide .
- Calculation of Boron DF:
4 DF, m' Actual Tank Boron Concentration + 0.7.
- Calculation of Cs-137 Limit:
DF3 = High Alarm Set Point + (1E-5 pCl/mi
- 1 OSE8 cpm per pCl/ml)
- Maximum release flow rate calculation:
Max Flow = [(MDCT flow gpm
- 0.9) + (Most Restrictive DF)]
- 0.9 91.0 mm
04-23-97 09:13:44 , Number
^)
(V Tme (UClear TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Revision No. 1 Offsite Dose Calculation Manual (ODCM) 12 l l i The dilution flow rate used is the current flow rate at the site. The minimum dilution flow rate is 5000 gpm per the TMl-1 FSAR. This ensures this batch release wDI meet the following , equation. ! I I(C;/X;) .<_ 0.10, (eq 1.2) where: Ci - diluted concentration of the l* radionuclide, , X= i Ten times the concentration for that radionuclide in the unrestricted area (10 CFR 20, App. B. Table 2, Col. 2). A value of 3E-3 pCl/mi for dissolved and entrained noble gases shall be used. j The set points for RM-L6 are set for each release based on the monitor response to each radionuclide identified in the gamma scan sample results as follows: (1.5) [Il (pCi/cc),*(CPM /pCl/cc)J + (CPM,go) = MM N (2.0)* [2] (pCl/cc); (CPM /pCi/cc)J + (CPM,gn) = HIGH ALJLRM CPM
.where: (yCl/cc); = positively identified radionuclides
( (CPM /pCl/cc); = RM-L6 sensitivity to radionuclide 1. (CPMego) = , RM L6 background prior to batch release A E'rsh alarm on RM-L6 will close valve WDL-V-257 and terminate any WECST releases to the e.., ?onment. 1.2.2 RM-L12 l RM-L12 is an off-line system, monitoring periodic combined releases from the industrial Waste' Treatment. System / Industrial Waste Filtration System (IWTS/lWFS). The input to- l IWTS/lWFS originates in TMI-2 sumps, (see Figures 1.1.and 1.2) and the TMI-1 Turbine Building sump (see Figure 1.1). The set points are based on the maximum release rate from both IWTS and IWFS simultaneously (see Figure 1.1) a minimum dilution flow rate, and 50% of ten times the 10CFR20 concentration for Cs-137, which is the most limiting radionuclide at a coricentration of 1E-5 pCi/ml. These inputs'are used in equation 1.1 to determine the RM-L12 liigh Alarm set point for all radionuclides being released. A high alarm on RM-L12 will close IWTS and IWFS release valves and trip release pumps to stop the release.
- 5. 2.3 RM-L10
' i l
RM-L10 was a Nal detector submerged in the TM11 Turbine Building Sump. This detector l has been removed from service. 1.2.4 RM-L7 9 RM-L7 is not an ODCM required liquid radiation monitor. Rf3-L7 is an offline system, monitoring the,TMINS outfall to the Susquehanna River (see Figures 1.1 and 1.2). This monitor is the final radiation monitor for TMi-1 and TMI-2 normal liquid effluent releases. 92.0 m
04-23-97 09:13:44 Nurnber TMI Radiological Controls -
--jggp 6610-PLN-4200.01 A)
( Trtle Departmental Procedure Revison No.
- 12 Offsite Dose Calculation Manual (ODCM) 1.3 Control of Liould Re! eases TMl liquid effluent releases are controlled to less than ten times the 10CFR20 concentrations by -
limiting the percentaDe of this limit allowable from the two TML liquid release points'. RM-L6, and effluent sampling, limits batch releases to less than or equal to 10% for all radionuclides, and . RM-L12, and effluent sampling, limits releases from TMI-1 and TMI-2 to less than or equal to 50% for Cs-137.
^
These rad!ation monitor set points also include built in meter error factors to further ensure that TMl liquid effluent releases are less than ten times the 10CFR20 concentrations to the environment. . The radioactivity content of each batch of radioactive liquid waste is determined prior to reiease by sampling and analysis in accordance with ODCM Part i Table 3.2-1 or ODCM Part 11 Tahle 3.2-1. The results of analyses are used with the calculational methods in Section 1.1, to assure that the concentration at the point of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part il Control 2.2.1.1. Post-release analysis of samples composited from hatch releases are performed in accordance with ODCM Part l Table 3.2-1 or ODCM Part ll Tab'a 3.21. The results of the previous post-release , analysis shall be used with the calculational methods in the ODCM to assure that the concentrations O at the point of release were maintained within tiie ODCM Part I Control 2.2.1.1, and ODCM Part 11 Control 2.2.1.1. The radioactivity concentration of liquids discharged from continuous release points are determined by collection and analysis of sampics in accordance with ODCM Part i Table 3.2-1, or ODCM Part Table 3.2-1. The results of the analysis are used with the calculational methods of the .ODCM to assure that the, concentration at the point of release is maintained within the ODCM Part.l Control 2.2.1.1, and ODCM Part 11 Control 2.2.1.1. l
' j O \
nn 93.0
04-23-97 09:13:44 Number M Raddogical CovJols (
/' MUClear Departmental Procedure 6610-PLN-4200.01 Title Reviston No.
Offsite Dose Calculation Manual (ODCM) 12 TABLE 1.1 TMI Liquid Release Point and Liquid Radiation Monitor Data' UQUID RELEASE LlOU1D RELEASE TERMINATION RADIATION POINT DISCHARGE INTERLOCK MON! TOR (Maximum FLOW (YES/NO) (DETECTOR) LOCATION Volume) RECORDER' VALVES YES WDbV257 281' Elevation WECST Batch RM-L6 TMI-1 Auxiliary Releases (Nal) Bldg (8000 0al.) ' FT 84 Station YES RM-L7 Discharg'e ' WDL-V257 (Nal) South end of TMi-1 and *WDL.R-1311
** TMI1MDCT TMI.2. FT.146
' YES tWTS/IWFS .tW-VT3 Continuous . IW-P16,17.18 Releases O)
'g V
RM-L12 (Nat) fWFS Building NW Comer (300,000/ 80,000 gal.) FT-342/ FT-373 E V279. IW-P29.30
- WOL-R-1311 has been flanged off as a TMI-2 liquid outfall.
**RM-L7 is not an ODCM required liquid radiation' monitor.
I C i O 94.0 me
04-23-97 09:13:44 l i
, Number ,
l TMl Radiological Controls (q 400iOOI Departmental Procedure 6610-PLN-4200.01
)
( Tme Reymon No. Offsite Dose Calculation Manual (ODCM) 12 l TABLE 1.2 TMI-2 Sump Capacities l
' Total Capacity . Gallons .
Sump Gallons perInch Turbine Building Sump 1346 22.43 ; Circulating Water Pump House Sump. 572 10.59 Control Building Area Sump .718 .9.96 Tendon Access Galley Sump 538 9.96 Control to Service Building Sump 1346' 22.43 ) l Contaminated Drain Tank Room Sump . 135 3.80 ; Chlorinator House Sump (^N h/ Water Treatment Sump ** -1615 22.43' Air intake Tunnel Normal Sump 700 -- Air intake Tunnel Emergency Sump 100000 706.00 Condensate Polisher Sump
- 2617 62.31 ,
Studge Collection Sump" '1106 26.33 l I Heater Drain Sump - _ Solid Waste Staging Facility Sump 1476 24.00 l Auxiliary Building Sump '10102 202.00 Decay Heat Vautt Sump 479 10.00 Building Spray Vault Sump 479- 10.00
- Condensate Polisher Sump is deactivated and in PDMS condition.
" , The Water Treatment and Sludge Collection Sumps will be deactivated for PDMS.
O . 95.0 mi.
2 e O O ? w Figure 1'.1 g g,0mP,osite p, @ Radiation Monitor
?
TM1-1 Liquid Effluent Pathways ;. . Raawaste
' Disposat- 8' arad Sample [
Pre-Operation Auxiliary Powdex Solids, Graver Chemical Cleaning Boiler Vessels Systern Basins (2) Blow down 4 a- SB00iesel SSODiesel . TMI-2 Intermediate NS
---g g p Building j intermediate l S $,dy$*'
o Bu!Iding Sump - -@ Turbine " " conecdon < East Building ,i Sump Sump industrial Intermediate ' waste Building Sump v i , Treatm e.- t lhT Pretrea+JDent b I Y aste AV-1 g Tm System ., Condensatt 4 _ ,,' and TMI-2 Trh va~ f Tft 2't? g. " j Effluen ; Co Tta - MairiPumping v-ng _. conecuan sanons Secondary Sump Waste Waste f . 3. Plant ' > Evaporator
. Evaporator Neutralizer SeWa9e Tre'alment w"d "**"'"'
aste ;p a Condensati Condensati Storage Storage Tan)( Plant ;"tratgn,1 , g. Tank B 8g Tank A g ., , Solids ;; g 3 Filter M .! Component Mechanical Draft S; Cooling Cooling Tower ,,
, RIVER
,, y g -
Water TMI-1 TMl-1 3
04-23-97 09:13:44 6610-PLN-4200.01 , FIGURE 1.2 Revision 12
/ TMI-2 Liquid Effluent Pathways -
i CONTRO'L , CONTROL & i: BUILDING E4 SERVICE SUMP AREA SUMP O I TURBINE TENDON I BUILDING is ACCESS SUMP GALLERY SUMP 4 1F IWTSSUMP i l 4 i INDUSTRIAL WASTE
- TREATMENT ~ SYSTEM i
,i l
me r RML-12 C ' RML-7 C - COMPOSITE SAMPLER I 97.0 mm O
04-23-97 09:13:44 Number
* " d' ' 0' '
(UCIO8r "t' Departmental Procedure
'S 6610-PLN-4200.01 Title Revision No.-
.Offsite Dose Calculation Manual (ODCM) 14 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liou'Id Effluents - 10 CFR 50 Appendix !
The dose from liquid effluent's results from the consumption of fish and drinking water. The location of the nearest potable water intake is PP&L Brunner Island Steam Electric Station located downstream of TMI. The use of the flow of the Susquehanna River as the dilution flow is justified based on the complete mixing in the dver prior to the first potable water supply, adequately demonstrated by fiume tracer die studies and additional liquid effluent release studies conducted using actual TMl-1 tritlum releases. Other pathways contribute negligibly at Three Mile Island. The dose contribution from all radionuclides in liquid effluents released to 'the unrestricted area is calculated using the following expression: , Dose.] = (b t) X ( C,) X AW33X + AF,9 X-X (eq 2.1) where: Dose j = ' the cumulative dose commitment to the total body or any organ, J, from the liquid effluents for the total time period, in mrem. At = the length of the time period of actual releases, over which Ci and f are averaged for all liquid releases, in hours. C=i the average concentration of radionuclide,1, In undiluted liquid effluent during' tim 9 period at from any liquid release, in pCl/ml. NOTE For Fe-55, Sr-89, Sr-90, prior to batch releases conservative concentration values will be used in the initial dose calculation based
- on similar past plant conditions. LLD values are not used in dose calculations.
f= undiluted liquid wa's te flow, in gpm. FD = plant dilution water flowrate during the period of release, in gpm FR = actual river flowrato during the period of release or average river flowrate for the montb the release is occurring, in gpm. DF = diution factor as a result of mixing effects in the near field of the discharge structure of 0.2 (NUREG 0133) or taken to be 5 based on the inverse of 0.2. l AW;i and AFy = the site-related ingestion dose commitment factor to the total body or any organ, j, for l each identified principle gamma and beta emitter, in mrem /hr per pCl/ml. AW is the factor for the water pathway and AF is the factor for the fish pathway, 98.0 me, l
04-23-97 09:13:44 - Number
,o Nuclear 'l'e'#d%27;',o "fa' es,o-em-4200.01 .
u,. Rewmon No. Offsite Dose Calculation Manual (ODCM) 12
. Values for AWg are determined by the following equation:
AWg = (1.14ES) x (U) x (DF;;) (eq 2.2) where: 1.14E5 = '(1.0E6 pCi/pCl) x (1.0E3 ml/kg) 4- (8760 hr/yr) , U, = Water consumption rate for adult is 730 kg/yr (Reg. Guide 1.109 Rev.1). DFy - ingestion dose conversion factor for radionuclide,1, for adults total body and for
- worst case
- organ, J, in mrem /pCl, from Table 2.1 (Reg. Guide 1.109)
Values for AFg are determined by the following equation: AFig= (1.14ES) x (U,) x (DF;;) x (BF,) (eq 2.2.2) - where: 1.14E5 = defined above
- U, - adult fish consumption, assumod to be.21 kg/yr (Reg. Guide 1.109, Rev.1).
DF;j =' ingestion dose conversion factor for radionuclide,'i, for adu!t total body and for
- worst
. case
- organ, J, in mrem /pCI, from Table 2.1 (Reg. Guide 1.109, Rev.1).
BFi = Bioaccumulation factor for radionuclide, I, in fish, in pCi/kg per pCi/L from Table 2.2 i (Reg. Guide 1.109, Rev.1). I J r i . l . 9 99.0 , s e
04-23-97 09:13:44' , Number ggggggy M Radiolog' cal Controls (O) U Title Departmental Procedurb 6610-PLN-4200.01 Revisron No. 12 Offsite Dose Calculation Manual (ODCM) k.2 TMI Uauld Radwaste' System Dose Calcs Once/ Month ODCM Part i Control 2.2.1.3 and TMi-2 PDMS Tech Spec Section,6.7.4.a'6 requires that, appropriate portions of the liquid radwaste treatment system shall be used to reduce,the radioactive materials in liquid wastes prior to their discharge when the monthly projected doses due to the liquid effluent
- releases from each unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem .
to any organ in any calendar ' month. The following calculational method is provided for performing this dose projection. At least once per month, the total dose from all liquid releases for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include . the estimated dose due to any anticipated unusual releases during the period for which.the projection is made. If this projected dose exceeds 0.06 mrem total body or 0.2 mrem any organ, appropriate portions of the Liquid Radwaste Treatment System, as defined in Section 3.1, shall be - used to reduce radioactivity levels prior to release. At the discretion of Ra'diological Engineering, tirne periods other than the current quarter-to-date may be used to project doses if the dose per day in the current quarter-to4 ate is not believed to be representative of the dose per day projected for the next month. O \ 6
'wJ .
1 I d O \ 100.0 mm I
- j l
t
)
-s-04-23-97 09:13:44 nam w ol (V
E Nuclear Tni. i Raddogical Contrds bepartmental Procedure - 6610-PLN-4200.01 n on No. Offsite Dose Calculation Manual (ODCM) ' 12 2.3 Altemative Llauld Dose Calculational Methodoloav As an attemative, models in, or based upon, those presented in Regulatory Guide 1.109 '(Rev.1) may ' be used to make a comprehensive dose assessment. Default parameter values from Reg. Guide 1.109 (Rev.1) and/or actual' site' specific data are used where applicable. As an alternative dose calculational methodology GPU Nuclear calculates doses using SEEDS
~(simplified environmental effluent dosimetry system). , s The onsite and SEEDS calculational models use actual liquid release data with acttial monthly Susquehanna River flow data to assess the dispersion of effluents in the river.
l
, l A 'I l
IO> V 101.0 ,
o .,
)
03-11-97 10:35:21 1001A Revleiori 30 FIGURE 4 THREE MILE ISt.AND UNIT ONE SAFETY DETERMINATION Thee o t <mmenon is regured for as documents wnmn 1001A appiicemany/ scope, j New Procedure ,_- - _ TCH . . x eca / . f..C
. 9 40 Q._o 4 / srp . .
(,L,i o -vu- 42co.o i ii
- i. ie we a me., eene.? inaa. Yes ier - promedo,oe end sTre . Y. 2 No e a= i is no . sien and dois we vorm. Th. r.maind., of ih. iorm o d not in oom,i.ed.
- 2. oo. w. .ene. m any w .n nm.nw impea? (nover w osa,w.no s.eu.n or we p,.o.dur..) Yee No A
. n y . o.mp ee ne u,. e end .n.or. m eene. i emn.d = en*on nw cornr. and en*on nw u nein. orr w.
e compwee su remainder at we form.
- 3. Don we eense ham m poinnues to adveresey enoot nuoieer eefety or esse piant oileratione? Yes , _ No >c-(Refer to Paragraph 4.2.2)
- 4. oom we rnese ehenose in the teomiy a deeermed in uw eessay arWjois report? Yes No )c
- s. Does tNo mais eenges in uw procedures as deeormed in ther sessey enelysis report? YM No A
- e. Are wees or emperirrente conduceed wnich are not desarmed in the sessly ana#ysis report? Yes No X T. Does this cimes corest weh the requirements of me plant T.ohnical SpesNiosenne? / Yes No Y ffM of the enewere to 3. 4. 5. 8 OR F ere3 you must ful out Mgure 53 predes a weleen sessey evalueson. Sgn and done tNo form.
N trw enewere to 3. 4. S. 8 AND 7 nr.,g,,tjQ, ihl prestudes the emiseense of en U . -- T Bafety assagen or Tectrucal Speerncason change. Pnmde the bee 6e for why the change le sede here. Sign and date tNo term. l l
~
Prepared Dy: % N tt.FI i T- oute: dl D eis.1 ii"-
o , 03-11-97 10:35:21 SAFETY DETERMINATION. The change does not have the potential to adversely affect nuclear safety or safe plant operations. This change does not affect the type or quantity of radiological effluents released from the plant. The change will not adversely affect nuclear safety or safe plant i operations for the following reasons: The change rewrites ,the TMI-2 Effluent Controls and Surveillances in Part II of the ODCM so that they are in the same format as the TMI-1 equivalent contained in Part I. The change specifies' controls that are consistent with the content specified in NUREG 1301 "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors". Specifying the TMI-2 effluent controls in the same format as TMI-1 effluent controls will l enhance safe plant operations by making these controls easier j to use since plant personnel are familiar with the TMI-1 and i NUREG 1301 format. I The change also incorporates effluent sampling and monitoring ) requirements for the Chemical cleaning Building, the Waste ' Handling and Packaging Facility, and the Respirator and Laundry Maintenance Facility into Tables 2.1-2, 3.1-2, and 3.2-2 of Part I of the ODCM since these facilities are.now under the control of TMI-1 operations. . Safety is enhanced since all TMI-1 ef fluent sampling and monitoring requirements will be contained in one place in the ODCM. The change deletes the requirement for analysis of Sr-89 in, j TMI-2 liquid effluents. Due'to.its short half life days), this isotope is no longer present at TMI-2.
' (50.6 '
j The change requires the use of meteorological conditions
' concurrent with the time of release of radioactive gaseous effluents for calculating doses from such releases. This provides a more accurate. determination of these doses.
~
The change does not make changes to any facilities as described dit the safety analysis report. This PCR does not make any changes co facilities. The change does not make changes in the' procedures.as described in the safety analysis report. The changes not described. in the safety analysis report. No tests or experiments are conducted which are not described in the safety analysis report. The PCR does not conduct any tests or experiments.
03-11-97 10:35:21 l l l 1 The change does not conflict with the requirements of Technical Specifications. The changes are consistent with the required contents of an ODCM that are specified in TMI-2 PDMS Technical Specification 6.7.4. The change does not conflict with the current TMI-1 Technical Specifications ' or those proposed in Tech Spec Change Request 223. Based on the forgoing, the change is considered safe. B. A. Par itt S/1/95 j
~
l l O e e
] 03-11-97 10 :'3 6 : 3pho3cgg,74 l
~~ l Nuclear " " 'o' S " '
Departmental Procedure 6610-PLN-4200.01 l { Time mvmon No. Offsite Dose Calculation Manual (ODCM) 11
![
4 Applicatmy/seope Calculate o# site doses due to radioactrve mopon e omoe en cuve omne i effluents for demonstradn0 compilance with Site Technical ! 1 Specifications 10 CFR 20 & 10 CFR 50 Appendbc I 6610 03/24/95 ! l This document is within QA plan scope X Yes No , Safety Reviews Required X Yes No I List of ENective Pages
)
Eggg Revision _P_a.2 Revision Eggg Revision Eggg Revision l 1.0 11 21.0 11 41.0 11 61.0 11 2.0 11 22.0 11 42.0 11 62.0 11 3.0 11 23.0 11 43.0 11 63.0 11 4.0 11 24.0 11 44.0 11 64.0 .11 5.0 11 25.0 11 > 45.0 11 85.0 11 6.0 11 28.0 11 48.0 11 86.0 11 7.0 11' 27.0- 11 ~ 47.0 ' 11 67.0 11 8.0 11 28.0 11 48.0 11 St.0 11 9.0 11 29.0 11 49.0 '11 89.0 - 11 10.0 11 30.0 - ~ 11 50.0 11 70.0 11 11.0 11 . ~31.0 . 11 51.0 11 71.0 11 12.0 11 32.0 11 52.0 11 72.0 11 13.0 11 33.0 if~ 53.0 11 73.0 11 , 14.0 11. 34.0 11 54.0 11 74.0 11 15.0 11 35.0 11 55.0 11 75.0 11 16.0 11 36.0 11 56.0 11 76.0 11 17.0 11 37,0- 11 87.0 11 77.0 11 18.0 11 38.0 11 58.0 11- 78.0 11 19.0 11 39.0 11 50.0 11 78 & 11 20.0 11 40.0 11 80.0. 11 80.. 11 m M Env. Affairs . 77 {
~ . - ~ . -
laws %-l+k
- De,.ml - -O l c, 74 .1,_o-,c
~ ~ ~ .~.
l vj g M 4 ,L M
%,1 .o CCair. l
~ " \ "'"
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03-n-97 10:36':32 Number l' Q g- TMl Radiologioil Controis Departmental Procedure 6610 PLN-4200.01 ne, m so. Offsite Dose. Calculation Manuel (ODCM) 11 TABLE OF CONTENTS (Cont'd) PARTli 11Wil-2 RADIOLOGICAL EFFLUENT CONTROLS i ,
~
Section peg, i 1.0 DEFINITIONS 61.0
. Table 1.1, Frequency Notation ' 63.0 I i 2.0 RADIOLOGICAL EFFLUENT REQUIREMENT 5 . 66.0 '
I
. 2.1 Parenar*No Discharges 66.0 l
2.1.1 Uguld ENuents 66.0 2.1.2 Gaseous ENuents 68.0 2.2 RadioactNo Gaseous Monitoring instrumentation 70.0 Table 2.2-1, RadioactNo Gaseou Emuent-Monitoring instrumentation 71.0 3.0 - MONITORING REQUIREM 72.0
' 3.1 Radioacdve 72.0 3.1.1 Liquid Emuonts 72.0 3.1.2 neannn. 72.d 3.2 Rad Gaseous Emuont Monitoring instrumentation , 74.0 Table 3.1 1, R Uguld Weste Sampling and Analysis -
75.Q Table 3.1-2, adioadtve Gaseous Waste Sampling and Analysis 76.0 ( khb O em F e 8 e 6.0 nm.
-m 03-11-97 10:36:32 TABLE OF CONTENTE (Cont'd)
- PART11 TMI-2 RADIOLOGICAL EFFLUENT CONTROLS 3*81188 -
Page
- 1.0 DEFINITIONS 4t**
Table 1.1, Frequency Notation Gike-2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES g , 2.1 Radioactive Effluent Instrumentation 306-Radioactive Liquid Effluent Instrumentatier. 2.1.1 e 2.1.2 Radioactive Gaseous Process and Effluent idenitoring Instrumentation 23,0-Table 2.12, Radioactive Geseous Process and Effluent Monitoring Instrumentation M e- ! 1 2.2 Radiologica! Effluent Centrols aet-2.2.1 Liquid Effloont Controla -20 9-2.2.2 Gaseous Efflusst Controls -Si! 9- i l 2.2.3 ' Total Radicactive Effluent Centrols 97e* 3.0 SURVEILLANCES 98:t 3.1 Radioactive Effluent Instrunwntation e 3.1.1 Radioactive Uguid Effluent lastruinentation 40:9-3.1.2 Radioactive Gaseous Procou and Effluent Monitwing lastrumentation -4tt - Table 3.12, Radioactive Gaseous Process and Effluent Monitoring Instrunwntation 424 - Surveillance Requirunents
)
3.2 Redielogical Effluent: 46.0 3.2.1 Liquid Effluents WmG, 3.2.2 Gaseous Efftuents 33.lL Table 3.21, Radioactive Uquid Weste Sampling and Analysis Program -484-r Tehts 3.2-2, Radioactive Gaseous Wate Sasqding and Analysis Program 64 & 3.2.3 Total Radioactive Effluents ,51HF-9 4
4 03-11-97 10:36,:32 l Harreer
' TMI Radiologicaif Controls E Departmental Procedure 6610-PLN-4200.01 ns. . W No.
Offstte Dose Calculation Manual (ODCM) 11 TABt.E OF CONTENTS
- l j Secelon Page PARTlli EFFLUEPff' DATA AND CALCULATIONAL METHODOLOGIES
- 1.0 UQUID EFFLUENT MONITORS bio 1.; TMi-1 and TMI-2 Uquid Radiation Monitor Set Points '
82.0
- 1.2 TMI Uquid Release Points and Uquid Radiation Monitor Data 83.0 1.3 Control of Uquid Releasee '85 0
~
2.0 UQUID EFFLUENT DOSE ASSESSMENT 90.0 2.1 1.lquid Emuonts - 10 CFR 50 Appendix 1 90.0 1 , 2.2 TMI/ Uquid Radwaste System Dose Cak:s Once per Month . 92.0 , 2.3 Altemative Dose Calculational Methodology 93.0 l 3.0 'UOulD' EFFLUENT WASTE TREATMENT SYSTEM 98.0 3.1 TMi-1 Uquid Emuent Weste Treatment System 96.0
' 3.2 Operabelty of TMI-1 Uquid Emuent Waste Treatment System 90.0 1
^
l '3.3 TMI-2 Uguld ENuent Waste Treatment System 99.0 4.5 GASEOUS EFFLUENT MONITORS 102.0 4.1 TMI-1 Noble ($nsIMonitor Set Points 102.0 j 4.2 ' TM11 Particulate and RadiciodinskMonitor Sat Points 104.0 'l 4.3 TMI,2 nam = Radiation Monitor Set Points . 105.0 4.4 TMI-1 n=== Emuent Release Points and Gaseous Radiation Monitor Data 106.0 4.5 TMI-2 Caseous ENuent Release Points and Gaseous Radiation Montor Data 108.0 4.6 Control of Gaseous Emuent Releaset' 109.0 4 l I
- 4 8.0 mm' I 3
4 e i i
1 03-11-97 10:36':32 - ' l F 4 , n,mbw j , ggy TMl RadidogkW Contrds Departmental Procedure 6610-PLN-4200.01 re. %.on u . 2 Offatte Dose Calculation Manual (ODCM) 11 l 1 i s .
/
1 . 3 i e i I PARTI
~
. 1 TMI-1 RADIOLOGICAL EFFLUENT CONTROLS '
~
4 '* lPJ FciR 4 ATIO d' 4 i 14.0 tim i i
O w s ! e i
. m 4
Table 2.1-2 e61N-4200.01 Revision 11 i y
. Radioactive Gaseous Process and Elfluert Montoring Instrumentatkm .
w O MIN 3 MUM E CHANNELS INSTRUMENT OPERABLE APPUCABluTY ACTION
- 1. Waste Gao Holdup System
- a. Noble Gas ActMty Monkor (RMA7) '1- 25
*** 26
- b. EfBuert System Flow Rate Measuring Device (FT-123)
~ -
- 2. Waste Gas Hokfup System Exploche Gas Monitoring System
** 30
- a. Hydrogen Monitor 2
- b. Oxygen Montor ,2 ** 30
. 3. Containmut Purge,Montoring System
- a. Noble Gas Activty (RM-A9) 1 f 27
- b. lodine Sernpler (R AS) 1 # 31 Particulate # 31
- c. (RM49) 1
- d. Elliuent System Flow Rate Measuring Device (FR-148) 1 # 26
- e. Sampler Flow Rate Monitor 1 # 26 k
e 24.0 mw
03-11-97 10:36:32 h
- j. j k
1.]. l 5 fi a 1 1I i 1 5 8 : i1a ' 5
'k $
1 I i 5 !j ' ea [ ]- k] }Ejl .
~*
I s's N" Ijg ,
=
Il 1 g gjg* l 1 i li; -
!g ,
I io l!I f .
"14l- ]}l.
4 i i
" 33 al
- d. 1 e s v g
o w i V H I w w Tame 2.1-2 '(Cont'd) - 8610-PLN-4200.01,, g Rpwision 11 o Radioacdve Gaseous Process and EfEuent Monkoring i lon -
. m MINIMUM w CHANfELS INSTRUMENT OPERABLE APPUCABILITY ACT10N
- 5. AuxIlary and Fuel Haneng Building Venession System
- a. ' Noble Gas ActMty Monitor (RM48) m (RM-A4 and /
,.l1
- 27 RMAB)- .
~
- b. lodine Samples (RM-AB) or (RM.A4 and RM48) f/ 1 31
/ .
- c. Particulate Sampier (RM48) er (RM-A4 and RM46) 1 31
* '2B
- d. Emuent System Flow Rate Measuring Devices 49 l 1 .
. i and FR-1,50)
- 26
- e. SaU Flow Rate Monitor 1
- e. Fuel Handling Bunding'ESF Air Traetment S
- a. Noble Gas ActMty Monitor (RM 4 or Sukable '
Equivalent) 1
" *
- 27,33
~
- b. lodine Cartridge N/AM
"** ' 31,33
"** 31,33
- c. Particulate Fker N/A00
**** 26,33
- d. Efiluent System ow (UR-1104A/B) 1
- e. Sampler R Rate Monkor 1 26,33 NOTE 2:' strumentation channel is provided. However, for detemining operabilty, the' equipment named must be instafled and functional or the ON appRes.
26.0 un.
f o NEw Ta eix 2.i t_ Y TeMe 2.1-2 5818fLN4288.51 Y Revision 11 Re6eactrve Gasseus Process and Effluent Monitoring instrumentation 4 ; e o M811 Mull CHAF50ELS m INSTRUMENT DPERABit APPLICA81HTY ACTION y u
- 1. Weste Gas Heldup System l
- a. Nome Bos Activity Monitor 5tM47) '"
1 25 Efauent System Flow Rate Moseanne Device (FT.123) "*
- h. - 1 26 4
- 2. Weste Gas Heidup System Explosive Gas Mostweg System 1
- s. Hydrogen Monitor 2 30 Drygen Monitor "
- b. 2 30 i i
- 3. Centamment Perge Meurtenne System I i
- a. Nome Gas Activity Monitor (RM49) 1. .# 27 i b. lodine Sampler (RIl49) 1 # 31
- c. Particulate Sampler IRMAS) 1 # 31
! d^ Effluent System Row Rate Messunes Devics FR-148) 1 # 28 l i
- s. Sampler Flow Rete Moniter 1 F 26' !
l l l ( l i l i
. [
tt71: g
'o w
i H TeMe 2.12 (Cent'4 e61g-PLN-4200.01 P Revision 11 Rediesets Gessous Process and Effluent Monitoring hseementenon a e o ' MWIMUM CHANNELS -J MSTRUMENT OfERABLE APPLICABILITY ACTION w
- 4. Condenser Vent System
- e. Law Range NeWe Gas Activity Monitor (RM A5Le end Suitable - 2" # 32 Eqwveient)
N5TE(1h For one of to channels, en operuWe chamel may be defined for pwpeces of tis costrel and 3.1.2.1 only as a suiteWe egeivalent mesitoring system cepeWe of being pieced in service within one heer. A esitable egeneleet system ehet inclado instruusuteties wie conyerehle sensitivity end roepense time to the RM A5Le monitories chassel When , the equmlent mestering system is k senece, indcotion wE be continuessly eveilelle to to operator, either threegh indcotion end eierm h ths Centrol Reem or through commenication wie e deogneted indvidual cenanessely obsennas local indcation. l l l [ c i s i i Ilfk
O TeMe 2.12 (Cent'd) 8610-PLE4288.01 Revision 11 Radioactive Gaseous Process and Effluent Menneneg Instrementation 4 _ P o M98HlUM CHAIMELS 4 MSTRUMENT DPERA8tE APPLICABILITY ACTION s w
- 5. Amnliery and Fuel Handing Buildne Ventilation System .
- a. NeMe Gas Activity Monitor (RM-A8) er (RM-A4 and RM AG) 1 27
- b. lodne Samples (RM481 er IRM44 and RM46) 1 31 t
- c. Partadste Sacyler (RM48) er (RM44 and RM46i I 31 ,
- d. Efnuent System Row Rate Messunns Devices IFR-149 and FR-150) 1 26 -
- e. Sampler Flow Rete Monitor 1 26
- 6. Fuel Heading Buiding ESF Air Treatment System
- a. Noble Gas Activity Monitor (RM414 er SuiteMe Equwelent)
"" 27,33-1
- b. ledine Certndse '
NIA" 31,33
- c. Particulate Fiter 31,33 N/A"
- d. Ef9 ment System Flew (UR-1104AlB) 1 26,33
- e. Sampler Flew Rate Monitor 1 .. 2E 33 i
NOTE 2: No instrumentaties channelis provided. However, for _, _ ; opereluTdy, the eqmpment named must be instelled and functional er the ACTION applies. f sm.
O. H TeMe 2.12 (Cent'd) ESISPLE4200.31 P Revision 11 E Radioective Gessous Process and Effluent Monitoring lostnnentation 4 e o O MenMuM a CIWWlELS APPtfCABUTY ACTION W INSTRUMENT OPERABLE
- 7. Chenecal Cloening Building Ventiation System Atc.
- s. Noble Gas Activity MesterkM418) 1
### 27
- ALC.
- h. Iodine Sampler $M418) Im pg 33 ALC-
- e. Partemiste Sanvierh+18) 1 ### 31
- 8. Weste Heedes and Packaging FecEty Ventiation System
- s. Partculate Sampler (WHP-RIT-1) 1 ## 31 j .
y 9. Respirator and tendry Maintesence Feelity Ventistian System 0
- a. Paraculate Sampler (RLM4?M-1) I ### 31 i
l L NOTE 3: lodies channel only required when TMI1 Equid redweste is store @ precessed in the facilty I ! i l 1 IIIIS g
i 03-11-97 10:37.:53 l 4 Number
~
Nuclear *' "ad'd ad c '** Departrnental Procedure 6610-PLN-4200.01 h bWon No. Offsite Dose Calculation Manual (ODCM) , 11' l Table 2.12 (Cont'd) i ] Table Notation '
/
. f' d
At all times. D.tring was'.e gas hoidup system operation. '
,. /.-
Ope @T.;f is not required when discharges are pos controlled through the closure of WDG-V47 ad where RM A8 (or RM.A4 and RM-AS), 149, and FT 150 are operable. During Fuel Her. tiing BuNding ESF Air Treatment S Operatiort
#. At aN times during ch purgmg.. .
## At aN times when condenser vacuum is establ .
ACTION 25 ' With the number of channels OPERABW less n required by the Minimurn Channels OPERABW requirement, the contents of thef tank rney be reisesed to the erwironment .i provided that pdor to initionng the reisesef . 4
- 1. 'At least two independent samples of the tank's contents are analyzed in accordance 4 with Table 3.2-2, item A, and
! 2. . At least two 64sN' Uled rnembers of the Unit staff Independently verify the
- and verify the discharge valve lineup.
release rate cal _ _ ,
- 3. The Director O & Maintenance TMI, shaN approve each release.
! Otherwise, suspend rol of radioacdve affluent via this pathway ACTION 26 With .he number of OPERABW less then required by the Minimum Channels , O' EF. MM.E enluent releases via,this pathway rney continue provided the flow ] rai g astimated at once per 4 houra. . . i ACTION 27 With the number channels OPERABW less then required by the Minimum Cir.nnels ! OPERABLE neluent raiseses via this pathway may continue provided gr6 ! samples are takien at least once per 12 hours and the inittel semples are analyzed for gas
- actMiy (gamme scan) within 24 hours after the channel has been declared inoperable. 'f l . RMM is dedored inoperable, see also Technical Specifkstion 3.5.1, Table 34.1, item C 3.f.
! the number of channels OPERABW less than required by the Minimum ACTION 30 1.
' OPERABW requirement, a grab sample shen be conected and analyzed , / for the Inopse gas channel (s) at least once per 24 hours. With both channels
! Inoperable, a grab semple shes be coNected and analyzed for the Inoperable gas 1 channel (s): , (a) at least 'oncet.per 4 hours during degassing operations. i (b) at least once per 24 hours during of.her operations (e.g. Feed and Baeed). J j - 8cFLAc.E w)W ATTAc54 Gtd . i 27.0 nm i
03-11-97 10:37:53 - Number Nuoleer " "*d*' a'8
- Departmental Procedure.
6610-PLN4200.01 TMe A,vaan No, ; Offsite Dose Calculation Manual (ODCM) 11 Table 2.1-2 (Cort'd) +
- 2. . If the inoperable gas channel (s). is not restored to service in 14 days, a special report shall be submitted to the Regional Adminletrator of NRC Region 1 Omco and a copy to the Director, Omco of Inspection and Erd ment within 30 days of declaring the channel (s) inoperable. The report shall '(a) the cause of the monitor inoperablity, (b) acalon being taken to the instrument to service, and (c) action to be taken to provert recurrence, ACTION 31 With the rusnber of channels OPERABl.Eless n required by the Minimum
- Channels OPERABLE requirement, eNuent vk this pathway may continue provided that within four hours aber the nel has been declared inoperable,-
semples are continuously collected ausdliary sempling equipment. ACTION 32 With the number of channels less than required by the Minimum Channels OPERABLE emuent reiseees via this pathway may continue for up to 28 days, provided one OPERA 8LE channel remains in service or is placed in service within j . Amor 28 deys, or N one OPERAtt.E channel does not remain in or le not placed in servloe within 1 hour, the prevleions of T *paama= Hon 3.0.1 apply, as if this Control were a Tech Spec Limiting for Operation.
~
' ACTION 33 With the number channels OPERABLE less then required by the Minimum
- Channels requirement, either restore the inoperable channel to OPERABLE within 7 days, or. prepare and submit a special report within 30 days o the action (s) taken, the ceues of the inoperabity, and plans and sched for restoring the system to OPERABLE etetus.
9 6 e e hb, n
03-11-97 10:37:53 4 Table 2.12 (Cont'd) Table Notation At a0 ti nos. During waste gas holdup system operation. 7 OpwebDity is not required when discharges are positively centrolled through the closure of WDG%47 and whwe RM A8 (or RM-A4 and RM-A8), FT 149, and FT 150 are operable. During Fuel Handling Building ESF Air Treatment Systen Operation.
# At ou times during containment purging.
## At all times when condensw vacuum is established.
3 ### During operation of the ventiation system. ACTION 25 With the number of chanels OPERABLE less then required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment provided that prier to initiating the releasc
- 1. At least two independent samples of the tank's contents are analyzed in accordance with Table 3.2 2,
+ ltam A, and
- 2. At least two technically quaEfied members of the Unit staff independently verify the release rate calculations and verify the discharge valve Eneup.
- 3. The Director Operations & Maintenance TMI, sher approve each release.
i Otherwise, suspend release of radioactive effluent via this pathway.
- ACTION 26 With the number of channels OPERABLE less then required by the Minimum Channels OPERABLE requirement, effluent reisenes via this pathway may continue provided the flew rate is asumeted at least once pw 4 hours.
ACTION 27 With the number of channels OPERABLE less then required by the Minimum Channels OPERABLE requirement, effloset roleeses via this pathway may continue provided yab senyles are taken at leert once per 12 hours and the initial samples are analyzed for gross-activity (gamma scan) within 24 hours aftw the channel has been declwed inoperable. If RM49 is declwed inoperable, su also Technical Specification 3.5.1, Table 3-5.1, item C.3.f. ) ACTION 30 1. With the numbw of channels OPERABLE,less then required by the Minimum Channels OPERABLE
.squirement, a grab sample abau be colected and analyzed for the inopwable gas channel (s) et least once per 24 hours. With both channels inoperable a grab sample shell be ceRected and analyzed for the inoperable gas channei{s): '
i k (a) at least once per 4 hours during desassing operations, j , (b) - at least once per 24 hours during other operations (e.g. Feed and Bleed).
- 03-11-97 10
- 37:53 Tehle 2.12 (Cont'd) i 1
- 2. If the inopwable gas channel (s) is not restored to service within 14 days, a special report sh:5 he 3
' submitted to the Regional Adrninistrator of the NRC Region 1 Office and a copy to the Director, Office of Inspection and Enforcement sthin 30 days of declaring the channel (s) inoperable. The report shan describe (e) the cause of the nwnitor inoperability, (b) action being taken to restore the instrument to
- service, and (c) action to be taken to prevent recurrence.
ACTION 31 With the number of channels OPERABLE less then required by the Mininum Channels OPERABLE i requirement, effluent releases via this pathway may contines provided that within four hours after the i channel has been declared inopwable, sarnples are continuously cogected with audiary sampling equipment. 1 ACTION 32 With the number of channels OPERABLE less then required by the Minimum Channels OPERABLE j requirement, effluent rolesses via this pathway may continue for up to 28 days, provided that one OPERABLE channel remains in service er is placed is service within 1 how. After 28 days, er if ese OPERABLE obenmei dose met remain in servies er le est pleeed la servise within 1 hear, the . provielene of Teeknieel Speelfiestien 3.0.1 apply, as if this Centrol were a Tech Spec Limiting i Candities for Operaties. ACTION 33 - With the number of channels OPERABLE less than required by'the Mininums Channele OPERABLE . requirement, either resters the inoperable channel to OPERABLE status within 7 days, er propere and submit a special report within 30 days outlining the action (s) taken, the cause of the inopwabdity, and , plans and schedule for restering the system to OPERABLE status. - l 1 4 4 a I i 1 J 1 1 l , 4 1 e
.- _.__ m_ m ._ _ . _ _ _ . . . . . _ _ _ _ _ _ _ . . . _ _ . _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ ,_ _ _,_ ___ _ _ _ _ _ _ _ _ ,___ _
. o w
H H e V
-4 Tame 3.1-2 (Cont'd) 8610-PLN-4200.01 '
Rpvleion 11 e o Radioactive Gaseous Process and Emuert Monitoring instrumentation Survellance Requirements un CHANNEL SOURCE CHANNEL INSTRU$dENI CHECK CifCK CAUBRATON EHI APPUCA81UTY
- 1. Weste Gas Holdup System
- . .% Gas ActMiy Monitor (RM-A7) 2P P E(3) Q(1)
E D ***
- b. Efikwit System Flow Rate Measuring Device (FT 123) ' . P /A
- 2. Waste Gas Hokkp System W'c Qas Monitoring System -
M "
- a. Hydrogen Monitor . N/A O(4) .
i
- b. Oxygen Monitor D' 'N/A O(5) M "
- 3. Containment Purge Vent System
- n. Noble Gas Activity Monitor (RMA9) D P E(3) M(1) - #
W **
- b. lodne Sampler (RM-A9) N/A N/A N/A
~
- c. , Paretridmaa Seppler (RM-A9) W N/A N/A N/A #
- d. Emuent System Flow Rate Device (FR-148) D N/A E O' #
- e. . Sampler Row Rate Monitor D N/A E. N/A #
4.. Condenser Vent System
- a. Noble Gas ActMty Monitor (RMA8i and Sultable D M E(3) Q(2) ##
Eq0lvalent - See Table 2.12, item 4.a) M AE 3 I 2 **" 42.0 nn.
\.
o w v H w
.. 4
. Table 3.1-2 (Cont'd) 6610-PLN-4200.01, g
. Rpvlelon 11 o
' Radioacdve Gaseous Process and EMuent Monkodng Survellence Requirements tn CHANNEL OURCE CHANNEL INSTRURENT ,
CHECK - CECK CAU3 RATION TEST- CHANNEL APPUCA88UTY i
- 5. A*91ery and Fuel Handing Bulding Ventletion System ,
- a. Noble Gas Activ5y Monitor (RhMS) or (RhM4 and M E(3)' Q(1) !
. RhM8) -
- b. lodine Sampler (RhWS) or (RM-A4 and RhMS) W N/A. . N/A - N/A *
- c. Particulate Sampler (RhM8) or.(RAM 4 and RAMS) W -
N/A N/A N/A
' ~
- d. System Emuent Flow Rose Measurement -D, N/A E Q i
- (FR-149 px! FR-150)
- e. Sampler Flow Rate Monitor ' D - N/A E N/A i
- 6. Fuel Hanc51ng Bulding ESE AirTreatment S ,
- a. Noble Gas Activity Monitor (RM- 14)- D M R(3) Q(2) ' { ,
- y Q ""
- b. System Elguent Flow Rde -1104 A/B) .D N/A R.
R ~Q ****
- c. Sampler Riw Rate Device ,
D N/A i
- 8 e
m 4 e 6 I 43.0 un. i i
03-11-?7 10:37:53 4 1 Number Nuclear ' "*d'doa'o" cant'* Departmental Procedure 6610-PLN-4200.01 noe Revmon No.
- Offsite Dose Calculation Manual (ODCM) 11 i
- Table 3.1-2 (Cont'd)-
- Table Notadon At a8 times.
j During waste gas holdup system operation. i *" ' Operabity is not required when discharges are poeltively contrtilled through the closure of WDG-V47, and where RM-A8 (or RM-A4 and RM-A6), FT 140, and FT 150 are operable. During Fuel Handling Bulding ESF Air Treatment System Operatot
# At al times during containment purging.
## At ad times when condenser vacuum is estabilshed.
i 4 (1) The C TEST shau also demonstrate that automatic lealetion of this pathway for the AuxDiary and Fuel ung Bulding Ventention System, the supply ventuation is lenistawi and control room alarm annu ' occurs if the foRowing condition axists.
- 1. Instru indicates measured levels above the high alarm / trip seapoint (includes circuit i
isture). . ,
- 2. Instrument irmeme a dqwn scale falure (Alarm function only) (Indudes circut faDure).
- 3. Instrument a moved from the operate mode (Alarm function only).
(2) The CHANNEL TEST shall demonstrate that control room alarm annunciation occurs if any of the foRowing conditions
- 1. Instrument indicates ured lewis above the alarm setpoint. (indudes circut faBure)
- 2. Instrument Indicates a d scale fa8ure.(includes circolt falure). I
- 3. Instrument controls rnoved the operate mode. ,
(3) .' The initial CHANNEL CALIBRA110N radioactMty measurement instrumentation shall be p.6..ed using one or more of the ence standards certified by the National Bureau of Standards or using standards that have obtained from suppliers that participate in measurement assurance activtles with NB These standards should permit calibrating the system over its intended range of energy and .T-- i.e.. range. For stbeequent CHANNEL . CAUBRATION. eaurces that have been to,the initial calibration should be used. (Operating plants may substtute previously estabilshed procedures for this requirement.) (4), The CHANNEL CAUBRATION sheE Indude the standard gas samples containing's nominal:
- 1. One volume percent hydrogen, belance and
- 2. Four volume percent hydrogen, balance nitrogen.
s a 44.0 nm.
1 i' .
- 03-11-97 10
- 37:53 i
Nwnnw 4
~ggy Departmental Procedure TM! RadiologicnlControls .
661HLN-4200.01 ! re. am on No. 1 Offsite Dose Calculation Ma'nual (ODCM) 11 q Table 3.1-2 (Cont'd) , 1 - j (5) The CHANNEL CAUB TION shall include the use of standard gas samples containing a nominal: 1 i 1. One volume 1 oxygen, belance nitrogen, and ) i
- 2. Four vol'ume percent on, belance nitrogen. .
5 4 s J . l 1 s l I i . t I f
- 4 d
i p = a O i . i ~ i l ' a i 1 1 4
; 45.0 nm.
1 f e i 4 t
_ _ ~ . _ _ . . . _ . . _ _ _ _ _ . . . _ . O ye w Tism 3.t. t a Tame 3.12 49ent%I)- 881efLE4208.31 P Revielen 11' b i 4 Radienctive Gasseus Process and Effluent Monitwing Instrumentation Seveilence Requ'rements e U CHAfffEL SOURCE- CHAMIEL CHAIGIEL 4 INSTRUMQE CHECK CHECK CAllBRATION TEST APPLICABitITY w i
- 1. Weste Gas Heidup System
- a. ' NeWe Gas Activity Moniter (RM-A7) P P E(3) 0(1)
~
- b. EfRuent System Flew Rete Mosewing Devica RT.123) P WA E Q
- 2. Weste Gas Holdie System Explosive Gas Moutonne System
- a. flydrogen Mester D MA Q(4) M , ;
- b. Drygon Monitor . D NIA Q(5) M ;
- 3. Centamment Purge Vest System s
- s. Noble Gas Activity Monitw (RMA9) D P E(3) M(1) #
- b. ledine Sampler IRM-A9) W' MA N!A NA #
- c. Pwticulate Sempler (RM-A9) ,
W N.fA N!A N/A # l t
- d. Efhant System Flow Rete Messunns Device (FR-148) D MA E Q #
- e. Sampler Flow Rete Monitor 0 N/A E MA #
- 4. Condenser Vent System l
- a. Noble Gas Activity Mester (RM A5 and Suitable Equnralent - See - D M E(3) Q(2) ##
Table 2.12, item 4.e)
!b
w H TeMe 3.1-2 (Cent'd - 8818-PLN4200.31 P Revision 11 E 4 Reseects Gessous Process and Ef9eent Monitwing hstnessetetion Swveillence Regurements e O CHAledEL SOURCE CHANNEL CHAlgdEL 4 MSTRUMENT E!E_CK QiLCK CALERATION TEST APPLICABRJTY i
- 5. AuxiEery sed Fuel Heading Buildng Ventilation System
- a. Nehls Gas Activity Monitor (RM48) er (RM-A4 and & RM-AS) D M E(3) Ott)
- b. ledes Sempler plM-A81 er (RM-A4 and RM-A4 W WA MA N!A i
- c. Particulate Sempler (RM48) or (RM A4 and RM46)
W , NlA N/A N!A
- d. System Efflueet Flew Rete Mosewament Devices e(FR-149 and FR-150) D N!A E O
- e. Sonyler Flew Rate Monitor D N/A E NlA .
- 6. Fuel Handing Beilding ESF Air Treatment System
- e. Noble Gas Activity Monitor (RM-A14) D M RO) QQ)
- b. System Etnuent Flow Rate (UR 1104 A/B) D WA R Q
- c. Sempler How Rate Measurement D'evice D WA R Q e
' o w
e Table 3.12 (Cent'd) 9810PLN4208.81 P Revision 11 E 4 Radioactive Geessus Process and Ethent Monitoring Instrumentation Swvoilence Requirements ' e O w CHANNEL SOURCE CHAMEL CHAISIEL N NSTRUMENT CHECK CHECK CAllBRATION IISI APPLICABilTY f 7. Chenucal Cleemme Building Ventilation System AL4-
- s. Nolde Gas Activity Memterh+18) O M E(3) Qik ###
AW '
- b. ledine Semplerh+18)b W NfA ' WA . N/A F##
Ab
- c. Particulate Samplerhu+181 W NIA WA NA ###
- 8. Weste Handing and Packapas Fac5ity Ventiation System 3< a. Partculate Senyler (WHP4t!T-1) '
D W SA W ### j 1 > U g.9, Respirater and Laundry Maintenance Ventiation System
- a. Particulate Sampler (RLM-RM 11 D W SA W ###
I I t 6 21Fk b
03-11-97 10:37:53 Table 3.12 (Cont'd) Table Notation At all times.
. During waste gas holdup system operation.
Operability is not required when discharges are positively contre!!ad through the cleswa of WDG V47, and where RM-A8 (or RM A4 sad RM AG), FT 149, and FT.150 are operable. During fuel Handling Building ESF Air Treatment System Operation.
# At all times during containment purging.
## At all times when condenser vacuum is established.
6 C u AM E.~ {.### During operation of the ventilation system. (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway for the Auxilary and Fuel Handling Bunding Ventilation System, the supply vetilation is isolated and control room alarm annunciation occurs if the following , condition exists:
- 1. Instrument inficatu menswed levels above the high alarmItrip setpoint (indudes circuit failwe).
- 2. Instrument indicates a down scale failure (Alarm function only)(indudes circuit failure).
i .
- 3. Instrumsat controls moved from the operste mode (Alarm function only).
(2) The CHANNEL TEST shnu also demonstrate that control room siers annunciation occws if any of the fehwing conditions exist j 1. Instranent indicates muswed levels above the alum atpost. Ondudes circuit failure)
- 2. Instrument indicates a down scale failure (indudas circuit failure).
, 3. Instrument centrols noved from the operate mode. (3) The laitial CHANNEL CAllBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standwds certified by the National Breau of Standards er using standards that have been obtained from supplies that participate in meeswoment asserence activities with NBS. These standards should pwmit esiibrating the system over its 4 intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related , to the initial calibration sleuld be used. (Operating plants may substitute previously established calibration procedures for this l requirement.) (4) The CHAl#iEL CAllBRATION shalinclude tie use of standard gas samples containing a nominal:
- 1. One volume percent hydrogen, balance nitrogen, and i -
- 2. Few volume perient hydrogen, balance nitrogen.
4 l
\
s
- - - . -. ~ - . - -- - -- - - - - - ----- -
1 . 03-11-97 10:37:53 Table 3.12 (Cont'd) (5) The C}{ANNEL CAL!BRATION shallinclude the use of standard gas samples centaining a nominal: i j 1. One volume percent crygen, balance nitrogen, and } i 2. Four volume percent crygen, balance nitrogen. i ) l i O 4 9 9
__ . _ . __. _ _ . _ . . . ~ . . _ _ . . .. . _ . . . . _ _ _ _ . _ . _ . . _ _ . _ _ _ _ _ _ . _ _ _ _ _ . _ _ . . . _ , . __ _ _ ,,, __ , o W i H H w
- . -4 Table 3.2-2 6610-PLN-4200.01 '
Revision 11 i Radicadive Liquid Waste Sampling and Analysis Program
. - m Minimum ' Lnwer Umat of Sampling Analysis .
Type of l Detedion (LLD) . Gaseous Relenos Type Frequency Frequency l pCl/ml) (Note a} P P l l A. ' Weste Gas Each Tank - . Each Tank - Gamma ' 1 x 154 ' Decay Tank Grab Sample ! Ematers (Note g) , B. Containment -
.P (Note b) P b) H4 1 x 104 4
' Purge Each Piage . Purge ~
l Principal Gamma 1 x 10 Grab Sample Emtiers (Note g) 4 C. AuxBlery and . M c, of - M Ho' ,1 x 10 - 4 Fuel HandHng Bulding Sample Principal Gamma l 1 x 10 Air Tremtreent System Emhters (Note g)-
^
e.
,/ l D. Fuel Hondung Bueding M (during M (during H4 l 4 ESF Air Treatment System i ,Systern ~ l Syalam g PrincipalGamma .
l 1 x 104
. Operation) ' Operation) g Emhters (Note g) g 1 x 10 t Grab Sample i E. Condenser Vacuum ' M (Note h) . * .M' H4 1 x 104 I,
Pumps Exhaust Grab ' Sample g (Note h) e PrincipalGamma i 1 x 104 (Note h) 3 Emitters (Note g)
!- t E f% A C.E MGL.E. 3.2.- Z to n M Amme b 54.0 nrm
- . - - . < s. n. .w. u. . . , . . . , , ,u , ..a .. ,
O W le* H i e Table 3.2-2 (Cort"d) j e61@LNA200.01,,
. Rpvision 11 r y
./ ..
program W Radioactive Uquid Waste Sampung and
. . . , m .
l Sampling l Mirilmum Analysis I l ~ tower Limit of Detection (LLD)- Gaseous Release Type ' l Frequency l Frequency . Type of ActMty Analysis j Q,Cl/mi) (Note a) 42 F. AB ReleaseTypes as Usted Above l,Conthuous !W ' (Note d) ; l-131 l 1 x 10 h A, B, C and D (Dudng System j (Note f) l Charcoal l l Operadion Continuous lW d) Principal Gamme Emitters 'I 1 x 10'" (Nm Q (Note g) (l.131, Others) Continuous .l 0 l. - 1 x 10-" (Note Q l Compoelle i Gross Alpha '
~ l Partkxdete Sedple Q l l Composite.
f) Sr-89 St-90 l 1 x 10-" Particulate Sample G. Condenser Vent Stack ,. 42
! l-131 lodine Continuous l W (Note d) ."* 1 x 10 Sampier (Note ) . (Note k) l Charcoal 8 ample ,
I
~
O
/
9 S , D 55.0 mm
03-11-97 10:37:53 Nwnber g EE TMI Radiological Controis Departmental Procedure 6610-PLN 4200.01 m. Offsite Dose Calculation Manual (ODCM) 11 l Table 3.2-2 (Cont'd) , Table Notation l a. The LLD is defined, for purposes of this survellance, as the smallest concentration of radioactive
\, material in a sample that will yield a not count above system background that wll be detected with j r
g 95% probabtitywith 5% probabRty of falsely conduding that a blank observation represents a "reaf ' l N signal - For a particular measurement system (which may include radiochemical separation):
= 4.66 s ' ,
E x V x 2.22 r 10'ic Y x exp (-A At) Where: I l LLD is the " lower limit of detodion as defined above (as microcurie per unit mass or volume), seisthe standard of the background counting rate or d the counting rate of a b!ank earnple as app (as count:Lper minute), ] l E is the counting offic ' (as counts per disintegradon), Vis the sample size (in units mass or volume), 2.22 x 10s is the number of d ons per minute por rnicrocurie, Y is the fractional radiochemical applicible),' - i A is the radioactive decay constant for particular radionuclide, arx!.
'At is the alapaari time between midpoint of mple collection and time of counting.
Typkal values of E, V, Y and at shall be used i calcdation.
. It shodd te recognized that the LLD is delined as "a priori" (before the fact) timt represerting the -
capablity of a rnessurement system and rot as an 'a eriorf (after the fact) limit for a particular rnessurement. -
- b. Sampling and analysis shal also be performed foRowing own, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER one hour unless (1) atelysis' shows that the DOSE EQUlVALENT l.131 concentration in the cooler 1t has not increased more than a factor of 3; and (2) the noble gas actMty monitor sh that effluent actMty has not
~
] increased by more than a lador of 3. l c.' . Trttlum grab samples from the spent fuel pool area shal be taken at least per 24 hours when 4 the refueang canalis flooded i
, GB.0' smn' O
I a l J
1 03-11-97 10:37:53 j Numbw
- ggy
- TMI Radiologic 41 Controis Departmental Procedure 6610-PLN-4200.01 i
{ me, n m on No. Offstte Doise Calculation. Manual (ODCM) 11 Table 3.2-2 (Cont'd) i d. _ Che c.4,@ and particulate fIters shall be changed at least once per 7 days and analyses shaR completed wthin 48 hours after changing (or after removal from sampler).
- e. Tritium g samples shal be taken weeldy from the spent fual poci area whenever spent fusi is in
- . the spent poet. -
- f. The ratio of sample flow rate to the sampled stream flow rate shall be known for the time period ,
covered by does or dose rate ca'culation made in accordance wth Controls 2.2.2.1,2.2.2.2, . and 2.2.2.3. l g. The principal gamma mitters for which the LLD speJ.cMan appine excluelvely'are the following , radionuclides Kr-87 -88, Xo-133, Xe-133m, Xe 136 and Xe-138 for gaseous emissions and Mn 64, Fe49, Co 68,' Co410, MMie, Cs-137, Co-141 and Co-144 for partictAete emissions. This list does not mean.that only nuclides are to be considered. Other gamma peaks that are i identillable, together with of the above nuclides, shen eleo be analyzed and reported in the Annual Rarew%e E!Iluent Report pursuant to TS ELS.4. 1
- h. Appucable only when condenser is established. Samgiling and' analysis shaI also be 4
performed foBowing shutdown, 1 RATED THERMAL POWER within._ unless (1)_analysis
, or ashowsTHERMALthat the DOSE POWER EQUIVALENT change exceedin
, ,1131 concentration in the primary has not incrossed more than a factor of 3; and (2) the noble gas actMty monitor shows that ofR actMty has not increased by more than a factor of 3. L Gross Alpha, Sr.80, and Sr-90 analyses do apply to the Fuel Handung Belding ESF Air l Treatment System.
- j. If the Condenser Vent Stack' Continuous lodine is' unavalable, then attemate sampling
_ equiprnent wig be placed in service within 48 hours, a report wE be prepared and submitted wthin ' 30 days from the time the sampler is found or made which identNles (a) the cause of the inoperability, (b) the action taken to restore rCZ. sampilng refuhaty, (c) the action taken to prevent recurrence, and (d) quantincetion of the release the pathway during the period and comparison'to the !!mits prescrt)ed by Control 2.2.2.1.b.
- k. Applicable only when , condenser vacuum is estabilsind.
e. g 8 9
. 57.0 am,
.i
I
' o w
bjEsJ YAB&.E 1.7 -1 Table 3.2-2 4
- P Radoective Caseous Weste Sanying sad Amelysis Program o
w i i i
, l l Minuamn Analysis l Lower timit of L w
l Sam ,Eng l Frequency Detection (LLD)pCilmil l Type of Activity Analysis Gaseems Release Tvpe Frequency (Note a) l l O i l P l P A. Weste Gas !EachTank Each Tank Principal Gamme l1xla' Decey Tank l Grab Sample ,
' l Emitters Mete g) l 1
8 B. Containement l'Ppictsb) P mte b) Each l H4 l 1 x ID'
! Each Page Grab Procycl Gaman Esutters ! I x 104 Purge l Pree semple i l mte g) l
! ! I I i i C. Auxiliary and I, M pietes c. el Grab l M l H-3 l 1 x 10' Feel Heading Buibling l Sample l l Pnncipal Genuna Enstters l 1 x 1&*
Air Treatment System s piste g) l l i D. Fuel Handing Building I' M Iduring System. M (during System H4 l ESF Air Treatment System l Operanon) l Operation) Pnnceal Gamme Entters l 1 x 10' j Grab Sample e plate 31 l 1 x IC*
! -l !
E. Condenser Yacuum ! M Mete h) M H4 l Pumps Exhaust l Grab Semple mte hl Procyal Gamme Emitters l 1 x ID' Slots g) INete hl l l l 1 x 1D* i
o W e H H Tame 12-2 5810fLN420R.01 Itevision 11 a e Radioactive Gessous Weste Sampling and Analyss Program o W w
- Minimum Analysis Lower Limit of y Fregnes.7 w
Sangling l Type of Activity Analyas l Detection (LLD)pCilne Frequency (Note al Gaseems Release Type l 1-
! M plete il l M H4 1 x 10' Chenecal Cleemns I Grab Sample ! Principal Genune 1 x 104 F. BuRding Air Treatment System l , Emittars INete 31 G. Weste HandEng See Section I l See Section I See Section l l See Secten i
' of this table of this taide l ef this ta!de e and Packaging FaciEty l ei this table j Air Treatment Syesem j 1
4
% See Sectisn i 0 H. Respirator and laundry l See Section l l 'See Section !I See Secties i Mantemente Facility l of this table j ef this table l ei this table l of this taide a
( ; Air Treatnest System
! ! ! i h
i W mu l :
- - - - _. _ _ _ . - - . . _ . m. _ . ._ __ .__ . _ _ _ , _ _ . . , . _ , __, _ _ _ . . , _ _ _ __ _ , ,__ ,, , o w e e TeMe 3.2-2 (Cont'd) e a w
-J Redienctin Gessous Weste Samping and Analysis Program g o
i i i w l' Sampling Frequency - Meumum l Analysis j j Laww Limit of Detection (LLD)( CahnD w Geseems Release Type l l Frequency l Type of Activity Analysis j (Note el w AI Release Types as listed Above in A. B f Certtinues j W plote d) Charcoal 1 x 10'2 L ! l-131 l C, D F, G end H (Dwing System Operation) l Metes f.ml l Sample l l i i i l Contineous l W Mete d) Particulate l' Pnncipal Genene Emittas piste g)1 lx 1&" l G-131, Othws) l ! l Olete Q l . Centmeeus l Q 1 x 10" l (Note f) Composite Particulete Gross Alphe
, Sample l l continsees ! Q ';
l Mete f) l Composite Particulate Sr49. Sr-90 1 x 13" i Semple I ! i i J. Condenser Vent Stack Centmueus lodine
' l Sempler (Note l Centmueus ! W plate d) Cherceal I l-131 4 1 x 10'2 plate u l Sempi. l l s
I wu JA ; i
l l l < 03-11-97 10:39:13 l } Table 3.2 2 (Cont'd) l l , Table Notation i a. The LLD is defined, for purposes of this surveillance, as the smahcst concentration of radioactive matwinl in a sample that i ! will yield a not count above system background that will be detected with 95% probability with 5% probability of falsely l concluding that a blank obswvation represents a "real' signal For a particular measurement system (which may include radiochemical osparation): l i i LLD . 4.66 sm j E x V x 2.22 x 10' x Y x exp l-A At) Whws: l l LLD is the "a priori' lower limit of detection as defined above (as microcurie pw unit mass or volunw), s,is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minutel,
- E is the counting efficiency (as counts pw dieisteerstics),
i V is the sample size Dn units of mass or volumel, < l 2.22 x 10' is the numbw of disintegrations pn minute per miaocurie, Y is the fractional radiochenucal yield (when applicable),
- A is the radioactive decay constant fu the peticuler radienuclide, and At is the elapsed time between midpoint of sample conection and time of counting.
Typical values of E, V, Y and at shal be used in the calculation. I i it should be recognized that the LLD is defined as an "a priori"(before the fact) limit representing the capabilty of a measurement system and not as an 's postwicri" (after the fact) Emit for a particular measurement.
- b. Sampling and analysis shal also be pwformed fe8 ewing shutdown, startup, or a THERMAL POWEP. change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUlVALENT l131 concentration in the primary coalent has not increased more then a factor of 3; and (2) the noble gas activity monitor shows '
; that effluent activity has not increased by more than a factor of 3. l ! c. Tritium greb semples from the spent fuel pool ares shah be taken at least once per 24 hows 'when the refueling canal is j flooded.
4 03-11-97 10:39:13 Table 3.2 2 (Cont'd) d. Charecal cartridgw and particulate filters shed be changed at least once per 7 days and analyses shal be completed with 48 hours attw changing (nr afta removal from semplw). e. Tritium grab samples shall be taksn weeldy from the spent fuel pool area whenever spent fuel is in the spent fuel poo f. The ratio of the sample flow rate to the samped stroom flow rate shau be known for the time period covered by each dose or dose rate calculation made in acewdance with Controis 2.2.2.1, 2.2.2.2, and 2.2.2.3. g. The principal gamma emitters for which the LLD specification applies exclusively are the fonowing radionuclides: Kr 87, Kr48, Xe 133, Xs 133m, Xe.135 and Xe.138 for gaseous emissions and Mn-54, Fe 59, Co-68, Co 60,2n-65, Mo 99, Cs 137, Co-141 and Co-144 for particulat.: emissions. This list does not ansan that only these nucides we to be considwed. Othe gamme peaks that are identifiable, together with those of the above nuclides, shal also be analyzed and reported in the Annual Radioactive Erfluent Release Report pursuant to TS 6.9.4. h. Applicable only when condenser vecwan is established. Sampling and analysis shad also be performed fouowing shutdown, statup, or a THERMAL POWER change exceeding 15 pucent of RATED THERMAL POWER within one hour unlus (1) analysis shows that the D0$f EQUNALEl(T l.131 concentration in the primary calent has not incrossed more than a factw of 3; and (2) the nobis gas activity morutor shows that effluent activity has not increemd by mwe than a factor of 3. L Gross Alpha, Sr49, and St 90 analysm do not apply to the Feel Hamling Buildiris ESF Air Treatment System. j. If the Condenser Vent Stack Continues lodine Sampler is uneveilable, the altwnste sampling equipment will be placed in savice within 48 hours er a report wil be prepared and abmitted within 30 days from the time the sernpler is found or made inoperable which idatifies (a) the cause of the inoperability, N the action taken to restore representative sampling copainity, (c) the action taken to prevent recurrence, and (d) quantification of the refuse via the pathway during the period and compwinn to the ranite preeeribed by Centrol 2.2.2.1.b.
- k. AppEcable only when condenser vacuum is estaldished.
L Applicable when9fM+ liquid radwaste is stored or processed in the facility. CinApGE
- m. ladine samples only required in the Chemical Cleaning Building when TMI-1 Equid redweste is stored or processed in the factity. .
e
03-11-97 10:39:13 Numtw j Nuclear "! =*8 == ht Procedure 6610-PLN 4200.01
** moon ee.
J Offsite Doss Calculation Manual (ODCM) 11 4 j _ i i 4 i 1 l } j , l { . ) l 1 i
- . l 1 l 4
~PART ll .
O 9 TMS-2 RADIOLOGICAL EFFLUENT CONTROLS W t t
- al M E'oR.M Art o M -
a e i 8 4 60.0
- mu 9
03-11-97 10:39:13 i , gggp ' TMI Radiologicil Controls Departmental Procedure 6610 PLN-4200.01
- m. m m. 1 l
Offsite Dose Calculation Manual (00CM) . 11 PARTIl
'Definitione 1.0 DEFINITIONS , l DEFINED TERMS j 1.1 The DEFINED TERMS of this section appear in gr*an' type and are applicable throughout Part 11 of the.ODCM.
FA'CIUTY MODE 3 1.2 Post-Defueling Monitored Storage (PDMS) is condition where TMi-2 defueling has been ' completed, the core debris remcNed from the during the doen up period iss been shipped off-site and the faclilly has been placed in a ble, safe and secure condition. ACTION 1.3 ACTION shall be those addhional.r raments specified as corollary statements to each control and j shall be part of the controla.
~
OPERABLE - OPERASIUTY 1.4 A system, subsystem, train, or device shall be OPERABUE or have OPERABIUTY when it is capade cf performing ~ function (s). Implidt in this definition shed! be the assumption thst all nectosary instrumentahon, controls, normal and emergency electrical power sources, coolig or seal, , lubrication or other audiary equipment, that are required for the system, subsystem, tr% component or dwice to perform ts function (s), are also capable of Wumig their support function (s). , CHANNEL CAUBRATION , 1.5 A CHANNEL TION shall be the adjustment, als n-ry, of the channel output such that it responds with ry range and accuracy to,known values of the Esrder which the channel monitors. CHANNEL CALIBRATION shall encompees the entire channel induding the sensor , and alarm /or trip functions, and shell include the CHANNEL FUNCTIONALTEST. CHANNEL CAUBRATI may be performed by any series of sequential, overiapping or total channel steps such that entire channel is celibrated CHANNEL CHECK 1.6 A L CHECK shall be the qualitative assessment of channel behavior during operadon by 1 o on. This~ determination shallindude, where possible, mmperison of the channel Indication an /or status with other indications and/or status derived from independent instrument c,mnnels ring the same pararneter. , 3cPdCE ExisTl4r ?AET E ODCM h 61.0 81m e
03-11-97 10:39:13' meer i g gp TMI R,adiologicid Controls Departmmtad Procedure 6610-PLN-4200.01 me aw.on No. Offsite Dose Calculation Manual (ODCM) 11 NOTE For radioactive emuent rnonitors, except for those in Table 2.2-1, shall include a verification which provides a qualitative assesem of:
. channel response when the channel eensor is exposed to a rad etive source. .
r CHANNEL FUNCTIONAL TEST 1.7 'A CHANNEL FUNCTIONAL TEST shall be: ,
- a. ' Analog channels - the injection of a almtdated into the channel as close to the primary sensor as practionble to verify OPERABILITY uding alarm and/or trip functions.
- b. Bistable channels - the injection of a ed signal into the channel sensor to verify OPERABluTY includirfg alarm and/or functions. -
FREQUENCY NOTATION i 1.8 The FREQUENCY NOiATION specffled the performance of Survenance Requirements shall
. wii parmi to the Intervals denned-in 1.1. ,
COMPOSITE SAMPLE ,. 1.9 A COMPOSITE SAMPLE is a ' of indMdual samples obtained at regular Irtervals over a ' time period. Elther the vol of each indMdual sample is pivpoih-W to the, low rate discharge at the time of sampilng or number of equal voltsne samples is proportional to the time period used to produce the c.vi,- _- ' GRAB SAMPLE 1.10 A GRAB SAM an indMdual sample collected in less than fifteen minutes. BATCH RELEASE 1.11 , A BAT SE is the discharge of fluid waste of a dicende volume. CONTINUOUS PA * , 1.12 A NUOUS RELEASE is the discharge of fluid waste of a ncndiscrete volume, e.g., from a ume or system that has an input flow during the CONTINU,0US RELEASE. 1 62.0 ,, mm. e 6
j 03-11-97 10:39:13 - 1 j 5 Nurnte NuoleeI ' '"i "*dio'oaica' coao Departmental Procedure 6610-PLN-4200.01 rm. mn no. l Offsite Dose' Calculation Manual (ODCM) 11 i j TABLE 1.1 Frequency Notation - l NOTATION F ENCY S (Shittly) . At I once per 12 hours. ,
~
l . l j D (Daily) least once per 24 hours. l . . j W (Weeldy) , At least once per 7 days. j M (Monthly) At least once per 31 days. Q (Quarterly)- At least once per 92 days. l SA (Semi Annually) At least once per 184 days. A (Annualty) , At least once per 12 months. i E .. At least once per 18 months.
, N.A. Not applicable. ,
- 4 e
S 8 e e e 9 1 em 4 4 0 4
. INFORMAil0N ONLY
- - - -- - ~. - - .---.- -.. - . . - . --
03-11-97 10:39:13 J m l Nuclear ' "5S S'*8 coa'rd' Departmental Procedure 6610-PLN-4200.01 I Me
- f%wteson it.
4 Offsite Dose Calculation Manual (ODCM) 11 l
' SEC110NS 2.0,3.0 AND 4.0 Controls and Surveillance R I -
2/3.0- APPUCAllWTY 1 CONTROLS , l 2/3.0.1 Controls and ACTION requrements sher be a during the conditions specined for each .: contrd. 2/3.0.2 Adherence to the requirements of the and/or associated ACTION within thelspecified time interval shal constitute compliance with contrd. In the event the Control is restored prior to ] expiration to the spoolRed time Interval -$sd.,7 of the ACTION statement is not required. 1 ! ~ 2/3.0.3 in the event the Cortrol and/or ACTION requirements cannot be setiened because of , circumstances in soccess of addressed in the Control, initiate appropriate actions to rectify the i problem to the extort poselbie the circumstances, and submit a special report to the . l Commission pursuant to TMI PDMS Technical ' Specincetion (Tech. Spec.) Section 6 8 2 within l 30 days unless otherwtw - j SURVElu.ANCE REQUMEMENTS
- 4.0.1 Survemence Requirements lie appucable ciuring the conditions specmed for indMdual Controls unless , otherwise stated in an Surveillance Requirement. The Survellence Requirements shall be l
' compliance with the OPERABluTY requirements of the Control performed to de , '4.0.2. Each Survealence shall be performed within the speciMed time Interval with: ,, . a. A eBoweblo extenelon not to exceed 25% of the surveillance interval, and . l
- b. um comt,.ned interval time for any 4 consecudve tests not to exceed 3.25 times the
) At s surveBlance irterval.
- 4. .
- 4.0.3 P of a SurveHience Requirement within the specined time.irterval shal constitute compliance with j OP UTY requirements for a Control and amanelatari ACTION statements unless otherwise required by
.the 0 ,
gn. I e 4 E 64.0 , mw NFBRUlON ORY !
i
! 03-11-97 10:39:13 : ! Number l gy WI Radiologicid Contrds Departmental Procedure - 6610-PU4-4200.01 I Tree Andeson No.
Offstte Dose Calculation Manual (ODCM) 11-l
- BASES ; The Contrds of this section provide the general requirements applicable to each the Contrd and Survemance
' Requirements. 2/3.0.1 This Control deAnos the applicabilty of each Contrd in t of the speciRed conditions and is provided to delineate specificeBy when each Contrd is icable. 2/3.0.2' This Control dennes those conditions nernamary to c e compliance with the terms of an indMdual Control and associated ACTION i i 2/3.0.3 This Contrd delineates the ACTION-to be ta for circumstances not directly provided for in the ACTION statements or when the provisions the stated ACTION statement are not or cannot be i complied with. The intent of this Control to require that inoperable equipment be restored to an OPERABLE status in a prompt manner, the unit be maintained in stable conditions, and that the ', Commission be promp#y notilled of conditions. ' ' ~ 4.D.1 This Contrd prtwides that eurveHlance - noosesary to ensure the'Contrds are met and will be performed during the FACIUTY MODE other, conditions for whit:h the Controls are applicable.
! 4.0.2 The provisions of this Contrd allowable tolerances for performing survoulance actMties beyond
! those spedRed in the normal interval These tolerances are necessary to provide operational
. RedAty har=== of scheduling performance considerations. The phrase 'at least' associated ,with a ,
i surveBlance frequency does negate this alowabletolerance value and permits the p 10.Tr r.cs of more i frequent survellance a l l l
~ The tolerance' values, alther individualy or consect.afvely over 3 test intervals, are sufficiently restrictke to ensure that the rol ===aci=*M with the surveillance actMtyis not degraded beyond that obtained l l from the nominal interval 1 i
4.0.3 The provisions of Contrd set forth the criteria for determination of compliance with the OPERABILITY J requirements of Control.. Under this criteria, equipment, systems or components are assumed to be 1
- OPERABLEff associated survellence actMiles have been satisfactorty performed within the specified tiri e interval. In this provision is to be construed as defining equipment, systems or components
)
OP such items are found or known to be Inoperable although still meeting the Surveillance
- Requ ,
h j , i . s
. l I '
65.0 nm. NORIAATION DNLY i g
U l ! 03-11-97 10:39 13 . Number l ,
-(gglggy M Radidogica ha 4
Departmental Procedure ) 6610-PLN 4200.01 l m a.vemon m i Offsite Dose Calculation Manual (ODCM) 11 j 2.0 RADIOLOGICAL EFFLUENT REQUIREMENT 3 .
- 2.1 Radioactive Discharges 2.1.1 Uquid Effluents 2.1.1.1 OBJECTIVES
- i T'odefine the limits and conditions for the controlled release of radioactive emuents to the environs to ensure that these releaseg are aslow as practicable. releases should not result in
- radiation exposures to offsite areas greater than a few percent background exposures. The i instantaneous release rate for all'emuent disdurges should ten times the concentrations speelfied in 10 CFR Part 20.
, To assure that the telseees of radioactive liquids to' ' meet the 'as low as prac'ticable' j concept, the following objectives apply:
- f j A. The annual total quantity of radioactive in liquid waste, excluding tritium and
, dissolved gases, should not h S per radioactive waste-producing reactor, and l the annumi does to the whole tiody or organ of an indMdual should not exceed 3 mrem
, to the total body and shallte_ lese or equal to to rnrem to any organ.
; . s . .
l B. The annual average concentration radioactive meteriais in the eSuen: from the i Mechanical Draft Cooling Towers rior to dIution in the Susquehanna River, excluding - l tritium and disadved gasse. not amari 2E4 pCl/ml. ' i
~
j C. The annual average conce of tritium in liquid waste prior to dilutism in the i environment should not SE4 pCl/mL 4
- 2.1.1.2 APPUCABluTY j Applies to the controlled of radioactive liquids from TMI-2.
I 2.1.1.3 COfGROLS - A. The radioactMty concenirsoon in liquid emuents from B41-2 to the environment shan
- not ===r4 ten the values spectfled in 10 CFR 20, Appendix B, for unrestricted areas.
. t
] B. The total rol of radioactive Ilquid emuent from TMI-2, excluding tritium and noble gases, - shall not 10 curies during any calendar" quarter. C. The eq InstaBed in the liquid radioactive waste system shall be maintained and shall be o to process sit radioactive liquid westos prior to this discharge when the actMty release a ws exceed 1.25. curies, excludmg tritium and disadved gases, during any , omle quarter., , D. The aximum radioactMty to be contained in one liquid redweste tank, excluding tritium
~ dissolved gases, that con be. discharged drectly, to'the environs, shall not exceed ,
, 1 curies.
i
@g $171e NORMATION DNLY
, - - . . - . - . . - - - _ - - - -- . . - - ~ - -
1 03-11-97 10:39:13 ' Wmber jg I TMI Radiologicid Contrds Departmental Procedure- 6610-PLN 4200.01 nn. am n so. Offstte Dose Calculation Manual (ODCM) 11 E. When the average release rate of radioactive siMuents, excl tritium and disadved j gases, exceeds 2.5 curies per radioactive waste-producing during any calendar l l quarter, the liconese shal notify the NRC within 30 days, . the causes and - ! describing the proposed program of action to reduce release rates.
- F. The does or dose commitment from liquid ofRuonts be less than or equal to.3 mrom j total body and less than or equal to 10 mrom to organ for the calendar year.
2.1.1.4 BASES -
- Uquid radioactive waste release levels to unrestricted should be kept "as low as praedcable" and are not to exceed ten times the concentrations s in 10 CFR 20. The Controls provide l . reasonable assurance that the resulting annual to to an indMdual in off.elte areas will not exceed the design objedives of Appendix 1 to 10 Part 50, which were established as
, ., requirements for the cleanup of TM-2 in the NR s Statement of Policy of April 27,1981. This
- assurance is bened on the facithet the S River we dEute the liquid elHuents upon their 1 release from the site. The alguents wEl be di by a factor of about 250 in the region where finfish can exist (within a one quarter mie radius the discharge point). At the same time these Controls i permit flexibility under unusual conditkms, may temporarly result in higher than normal rolessee, but stil wthin ten times the specified in 10 CFR 20. It is expected that by using this lleutalty under unusuajiid , and exerting .every effort to keep levels of rad!ce ctive meterial in liquid wastes as low as pra , the annual releasse wil not exceed a smaR fraclon of the annual average concentrations in 10 CFR 20.-
Control 2.1.1.3 A. above requirse lloenoce to limit the concentration of radioec'Jve materials in liquid ofRuents from TMI-2 to ten the levels speciRed in 10 CFR 20, Appendix fl, for unrestricted areas. This Control assurance that no member.cf the general public can be exposed to liquids containing etive meterialp in excess of limits considered permissible under ; the Commission's rules and r ulations. Control 2.1.1.3 B. above ==4hn=hes an upper limt for the release of radioactive liquid ofnuorus, exduding tritium and gases, of 10 curles during any calendar quarter. The intent of this Control is to permit the flexibity under unusual conditions, which may temporarty result in releases higher than , normaRy a. chievable when the unit and the liquid radwaste equipment are fv C .sias . Releases of up to 10 curies during any omiendar quarter wRI result in concentrations of rad rnatorials in liquid ofOuents at oman percentages of the concentrations sped 5ed in 10 CFR . - Control 2.1.1.3 C. ulros the licensee to maintain and operets the equipment Installed in the liquid radhrWe wasta em to reduce the release of radioedive materials in liquid effluents to as low as practicable, 1eistent with the requirements of 10 CFR 50.36a. Normal use and maintenance of
,instaRed equ nt in the liquid radioactive system is expeded to result in releases of not more than
. about five per year, excluding _ tritium and dissolved gases during normal operations. In order
, to keep of radioactive materials as low as prar4hhle, the Control requires, as a minimum, operation equipment whenever the rate of release exc' aods 1.25 curies per quarter, exduding '
trtium and lesolved gases. - s 67.0 En
~
. NBRETION DNLY
03-11-97 10:39:13 i
, Nurnber
- gggy TMl Radiologicid Controls Departmental Procedure 6610-PLN-4200.01
] _ i noe nemen No. j . Offsite Dose Calculation Manual (ODCM) 11 4 1 In addition to Control 2.1.1.3 B., the reporting requirements of Contro! .1.3 E. and Section 6.6 of the TMl-2 PDMS Te9h. Specs., defineate that the licensee shall id the cause wheneverthe rate i of radioactive affluents, excluding trtium and noble gases. *wr==ds curies during any calendar j quarter and describe the proposed program of action to reduce s h release rates. This report must be fued within 30 days following the calendar quarter in wh' the 2.5 curie release occurred Control 2.1.1'.3'F. requires that the does to offsite personnel limited to the design objectives of Appendix 1 of 10 CFR Part 50. This wW assure the dose by the public during the cleanup is , equivalent to or less than that from a normal operating or The limits'also assure that the
, environmental impeds'are consistent with those = in NUREG4683, the TMI-2 Programrnatic j Environmental Impact Statement (PEIS).
~
2.1.2 Gaseous.Efluents -l 2.1.2.1 OBJECTIVES To defhe the limits and conditions for the release of radioactive gaseous effluents to the environs to ensure that these releases are low as practicable. These releases should not result in , radiation exposures in olleite areas , than a few percent of backgromd exposures. 5 . 1 To assure that the reisees of rad _ gases to offsite areas meet the as low as practicable l concept, the release rate of uents'shall not reedt in doses to the public exceeding the
- design objectives of Appendbc I to , CFR Part 50.
j 2.13.2 APPLICABILITY , Appiles to the controlled of . radioactive gases from TMI.2. 2.1.2.3 CONTROLS i' A.. The Instanta does rete from reienee of gross gaseous adivity except for hologens and par &daean heK4fves longer than eight. days shal not exceed 600 mrom/ year to the i total body mrom/ year to the sidn. B. 'The dose. rate from release of particulates with haff41ves greater than eight j days, to environs as part.of the airbome efnuents, shall not avraad 1500 mrem / year to
- ' any ,
C. , gases and particdotes purged from the Reactor Building shall be fItered the high efficiency particulate alt fIters. ] t . I J D. .The does due to noble gases in gaseous effluents shall be less than or equal to 10 mrad j for radiation and lees.than or equal to 20 mrad for beta radiation for the calendar
, and less than or equal to 5 mrad for gamma radiation and 10 mrad for beta radiation i
any calendar quarter. 1 . j E. he does for radioactive (other than noble gaseous afluents) shen be less than or equal to - l 5.mrom to any organ for the colondar year, and 7.5 mrom to any organ for any calendar j . quarter. ,
, 68.0 mm i
INFORMATION DNLY 4
l l 03-11-97 10:39:13 l l Number ggy TMi Radiological Controls ~ Departmental Procedure 6610-PLN-4200.01 I i I M* Revision No. l l Offstle Dose Calculation Mnual (ODCM) 11 l s F. When the releese of radioactive materials in gaseous exceeds the values in Controla A, B, D or E, the licensee shau notry the NRC hin 30 days. idera#ying the causes and describing the proposed prograrn of action to such releases.
~
-2.1.2.4 BASES The specified levels provide reason 6ble assurance thelraeulting annual exposure rate frorb noble l gases at any location at the she boundary.wll.not 10 mIlireme per year. At the same time, these Controis permit fledbORy under unusual ~ TJens, which may temporarty result in higher than the design objecthe levels,.but stR within dose limits specilled in to CFR 20 and within the design ob{sctives of Appendix I to 10 CFR 5 ..it is expected that using this flexibity under unusual conditions. and by exerting every effort to levels of radioactive material in gaseous wastes as low as practicable. the annual releases not exceed a sineD fraction of the annual dose limus specified in 10 CFR 20 and wl0 not res in doses which svraad the design objectives of Appendbc I
~ to 10 CFR 50, which woro endorsed limts for the cleanup of TMI-2 by the NRC's Statement of Policy of Apr5 27,1981.
These efforts should include eradon of meteorological conditions during releases Control 2.1.2.3 A., requires - licensee'to limit the concentradon of notto gases from TMI-2 to - unrestricted areas to such ty no indMdual wEl receh does at a rate greater than 500 mrom/yr to the t~.E -~ of 3GC0 mrom/yr to the sidn.
. Control 2.1.2.3 B., the licenses to limt the' concentration.of particulates with half.!Wes greater than eight ys. released from TMI-2 to unrestricted areas to levels such that no individual wlE receive does a rate greater than 1500 mrom/yr to any organ. The absence of iodine ensures that the un, -- ,Ging thyroid ' dose, rate above background to an infant via the cow-mak4nfant -
pathway is less or equal to,1500 mrom/yr.. A grazirgi period of 6 months has been applird so
. a5 in partictdate form with half-#ves greater than 8 days, to alow for the mIk exposure '
Control 2. C., litnits the radioactMty that may be released to the environment to "as low as in to the requirew of Controls 2.1.2.3 B., D. and E., the reporting requirements of
' Cont 2.1.2.3 F. deliner',e itwt the licensee shal Idertfy the cause whenever the radioactive releases ereed Control 2.1.2.3 D. or Control 2.1.2.3 E., and describe the proposed of action to reduce such releases. The. report must be fled wtthin 30 days following the quarter in which the relenes occurred.
O 4 g . 69.0 vm INFORETION ONLY
?, 03-11-97 10:39:13 ' Numtw J ggy - TMI Radiological' Controls Departmental Procedure 6610 PLN-4200.01 Tb l h No. i Offstte Dose Calculation Manual (ODCM) f 11' l 2.2 Radioactive Gaseous Efnuent Monitoring instrumentat !. 2.2.1 OBJECTIVE 1 The radioactive gaseous efAuent mor.!t instrumentation channels shown in Table 2.2-1 shall be OPERABLE. 2.2.2 APPUCABluTY } . l As shown in Table 2.2-1. l l l-2.2.3 CONTROL j ' With less than the number of radioactive gaseous olluent un.,..wy l j instrumentation c a OPERABLE, take the ACTION s%yn in Table 2.2-1. ! i 2.2.4 BASES ] , I The radioactiv Gaseous effluent instrumentation is provided to monitor and control, as
. applicable, rekases of radkiactive materials in gaseous ofRuents during actual or
. potential rol of gassops ofBuenta. The OPERABluTY and use of this instrumentation is' I i consistent the requirements of General Design Criterion 64 of Appendk A to 10 CFR
' l l Part 50. '
j . g b W 9
- b.
i i . i I 1 . 4 ) , i 70.0 in WOMTIDN ONLY 2 - 4
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1 l 4 l 03-11-97 10:39:13 -
%mber gggy TMl Radiological Dontrols Departmental Procedure 6610-PLN4200.01 Tw, .
novtwon No. 4 Offsite Dose Calculation Manual (OOCM) 11 i TABLE 2.2-1 Radioacthe Gaseous Effluent Monitoring n i CHANNEL MNMUM i CHANNEL CHANNEL CHANNELS-
- INSTRJMENT CHECK CAUBRATCN TE OPERABLE .APPUCAINUTY ACTON i
j HP&219 Gas D .E % 1 Note i Note'2 HPM10 Pareoulate D E [M 1 Note 1 Note 2 ] HP4210A Gas D E / M 1 Note 1
- Note 3 HPA21eA Parvoulete D E[ M 1 Note 1 Note 3 I HPeats Gas D [E M , 1 Note 1 Note 4 HPAct5 Particutsee D [ E M 1 Note 1 Note 4 NOTES:
- 1. During operation of the monit system._ . I
- 2. If the same channel on H -219A is. inoperable, s'enre Reactor Bunding Purge f in progress. '
- 3. If the same channel HP-R-219 is inoperable, eeours Reactor Sullding Purge N in progrsss.
- 4. If channelis e, securs Reactor Bulding Purge f in progrees.
f 8 4 s
. 8 6
9 9 e.
'9 4
e f ' 71.0 nm. INFORMATION ONI.Y
- 03-11-97 10
- 39:13 i i Number l
Nuclear "ade c a"a Departmental Procedure 6610-PLN-4200.01 nm ww.a e. Offsite Dose Calculation Manual (ODCM) 11 3.0 . MONITORING REQUIREMENTS , 3.1 Radioacdve Discharges *
- 3.1.1 Uguld EfRuonts 3.1.1.1 OBJECTIVE 1 To ensure that radioacthre liquid releases fr ne facity are within the limits of Controls 2.1.1.3 A.
through F. j 3.1.1.2 CONTROLS l During retensi of liquid radioactive es from Radinacthre Waste-Misceuaneous Uguids System, ! , the following rondtions sheH be l
, A Facetty records shef- maintained of the radioactive concentrations and volume before dButton of each of Ilquid effluert released, and the ransge dilution flow and length of time over which discharge occurred. Estimates of the error associsted with each reported value a be includ'ed in fac8ky records. '
B. Radioactive l' weste5Enpung and actMty analysis ehen be performed in accordance with Table 3. 1. Prior to the release of each batch of liquid elEuent, e semple shall be taken
.from that and analyzed for the concentration of each significant gamma emitter to
.d compliange with Control 2.1.1.3 A' using the flow int 6 which'the affluent is dische 3.1.1.3 BASES 6 These weaw' s requirements provide the data for the licensee and the Conwnission'to evaluate the station's relative to radioacth/e liquid wastes released to the environment. Reports on the of radioactive materials relemmed in liquid ofnuents' shad be fumished to the on the beels of ODCM Part IV Requirements. On the basis of such reports and any additional lon obtained from the Xcensee or othens, the Commission rney require the
' licensee take appropriate action.
3.1.2 Effluents. - 3.1.2.1 O' VE To neure that radioactive gaseous releases from' the facIlty are within the !!mits of Controls 2.1.2.3 A F. 3.1.2.2 ROLS , During release of radioactive gaseoQs wastes, ttdfoRowing conditions sheH be met: W.O **
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.INFDDIATION DNLY:
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- 03-11-97 10
- 39:13 l i
s i . Numtper . ggy TMI Radiological.Controis Departmental Procedure 6610-PLN 4200.01 I , no. %. ion No. i Offsite Dose Calculation Manual (ODCM) 11 1 A. During purge of the Reactor BuEding, the following conditions a be rnet: i i 1. The Reactor Bu8 ding Purge Exhaust Monitors (HP-R and HP-R-219 or simHar dwice) shan be OPERABLE. i B. The flow rate for radicadive ofRuent streams and the Hlary and Fuel Handling Bundings and the Reador Bulding, shall be monitored and ed. Geseous offluents from tho-Reactor Bu5 ding Purge Exhaust shan be con ' monitored and recorded. d
- note .
~
j With flow rate monitoring instrum out of service, low rates from j the Aindliary and Fuel Handling Buld may be estimated'using the -
- maximum design flow for the fans in operation.
C. ' adioactko gaseous wasta R and activity analysis sher be performed in accordance i with Table 3.1-2 D. FacHky records shal be intained'of radioactNe sFsa..AEi, release ratio ard volume of - ! each batd1 of ofBuents released and the length'of time.over which release ! occurred Estimates ,thronor nea,v ineart inith each reported value should be included in facity records
~
E. The release of ioactive meterials, other than noble gases, in gaseous einuents shall be
- determined to wthin the.limts calculated in accordance wth this Control by obtaining j representat samples and peds s.g analyses in accordance with the sampling and i analysis specified in Table 3.1.-2. ,
3.1.2.3 BASES .
~
l . Controis 3.1 A. through D. require that suhable equipment to monitor the radioactive gaseous , releases are during any period these releases are taldng place.
- Control .2.2 E. is provided to ensure that the does to a member of the public from daseous effluents
~ TMI-2 wel be wthin the limits of Control 2.1.2.3 d.and Control 2.1.2.3 E. These itoring requiremerts provide assurance that radioactive caseous ofRuants from the station , ans controBed and montored over the flie of the station. These monitoring requirements
. the data for the licensee and the Co.TT4 lon to waluate the station's performance relattve
! 'to loactive gaseous wastes rolessed to the environment. i
, eports on the quantities of radicadive materials released in gaseous eQluents shaR be fumished to Comnussion on the basis of ODCM Part IV requirements. On the basis of such report and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.
j . W 73.0 in NORETIONONI.Y
_ ._- - _. . . - - - . . .. - . - . - - . - _ . . . . . ~ - - . . _ . . . - - Y / 4 03-11-97 10:39:13
. Number "Departmental
""****o Nuclear Procedure "t'*
6610-PLN-4200.01 i i im. RevWon No. j Offsite Dose Calculation Manual (ODCM) 11 i 3.2 Radbacth Gaseous ENuort Monitoring i Te4 ;ci-i Each radioedive Oaseous eMuert ., =viiiw instrumentation channel shall be demonstrated i OPERABl.E by pedorir .ce of CHANNEL CHECK, CHANNEL CAUBRATION and CHANNEL FUNCTIONAL TEST o at the frequencies shcun in Table 2.21 (por occupational exposure I considerations and detect skMty in ambiert radiation areas). i 1 4 i . 1 l } t
- g. %
8 o d b 74.0 ,, .
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. INFORMATION DNLY, .
eq m
- . - . . - . - - -. - - - - . - - - - ~ _-
d 1 03-11-97 10:56:15 tenntw gy MI RadiolookiaYControls Departmental Procedure 6610-PLN-4200.01 me n=wn No. 4 Offsite Dose Calculation Manual (ODCM) 11 i TABLE 3.1-1
- Radioeotive Uquid W'este Sempting and Analysis , 5) i j A. Liauld Releases , ,
i l - Type at / Detectab6e
- Sampling Frequency ActMty Analysis / Concertration (3)
Each Batch indMdual Gamma SE-7 pCl/mi (2) e H4 ' 1E4 pCi/mi Quartetty Compoelte (1) Gross At 1E-7 pct /mi t ) -89 SE4pCl/ml ! Sr 90 SE4 pCl/mi ' NOTES: . ! (1) A COMPOSITE SAhPLE is which the quantity of liquid sampled is proportional to the quantity 5f liquid waste discharged fro plant. . i
,. " +
l' (2) For certain mktures of emitters, it may not be possible to measure radionuclides in concentrations near this sonstMty I other nuclides are present in the sample in much greater concentrations. Under these t wEl be more appropriate to calculate the concentrations of such radionuclides using measured with thoog radionuclides which are routinelyidentuledand measured. (3). The detectab81ty for radioactMty analysis r.re based on the technical feasibilky andlon the potential-sly,;Twse in errvironment of the quantitte rdeseed. For some nuclides, lower detection limRs rnay be . reedly a and when nuclides are rneesured below the stated limits, they should also be reported. i (4) The res' of these li should be used as the basis for recording and reporting the quant!tles of ! rad material reisesed in liquid emuents during the sampling period. In estimating releases for a period analyses were not performed, the average of the two adjacent data points spanning this period shotA be used. Such estimates should be included in the effluent recoals and reports; however, they j sho be clearly identified as. estimates, and the method used to.obtain these data should be described. f (5) D . tions from the sampling / analysis regirne wil be noted in the report spedlied IriODCM Part IV. i l g e d l . 4 75.0 an l . NORMATIDN ONI.Y
4
- 03-11-97 10
- 56:15
~
Neder ggp TM1 RadiologicWControis Departmental Procedure 6610 PLN 4200.01
- Tm. n vmon No.. -
l Offsite Dose CalculaUon Manual (ODCM) , '11 i j TABW 3.1-2 Radioactive Geseous Weste Samplin0 and Ana (3) t h SAMP2 SAMPUNG E OF DETECTABM SAMPE POINT TYPE. FREQUENCY ANALYSIS CONCENTRATION (1)(a) Reactor Bulding Purge Releases Gas Each Purge [3 1E4 pC1/cc . l Individual Gamma Emitters 1E 4 pCl/cc (2) i Unit Exhaust Vent Release Points Gas Mont H3 1E4 pCl/cc j
,. Individual
, Gamma Emitters IE-4'pCI/cc (2)
IndMdual (b) P atos Weeldy .. Gamma Emitters 1E-10 pCl/cc (2) l ._ _ umiMy
- Compoelte Sr-90 ' 1E-11 pCl/cc -
./ '
MontNy Composite Gross Alpha Emluers 1E-11 pCl/cc -
/
i Reactor Bulding Breather Particulates Semi-Annually Indv. Gamma 1E-10 pCI/cc (2) Emitters (b) I ' Sr-90 1t:i-11 pCl/cc I Groes Alpha , 1E-11 pCl/cc Emittgrs ) ' (1) The abov detectabilty limits s're beoed on technical feasibWty and on the potential sigrmcance in the. l ervoer 4 of the quantities rolessed For some nuclides, kwer detection.Ilmits rney be reedly achievable I and en nuclidee are rnesoured below the stated limita, they should also be reported. !
^
j (2) For rtain mbdures of gamma emitters, it may be possible to measure radionuclides at levels,near their sitivity limits when other nuclides are present in the sample at much higher levels. Under these s-nces, it ws! be more servpires to.calcuhte the levels of such radionuclides using observed ratios
~
j the gaseous component in the reactor coolart for those radionudidos which are measurable. ; l (3) Deviations fmm the sarnpling and analysis regime wEl be noted Iri the report specified in ODCM Part IV. j 4 en e
. 7tLO vm IN[BlWAll0N ONLY I
l 4 03-11-97 10:56:15 i l
' unno.,
9
-(dgy TMl RadiologicalControls Departmental Procedure 6610 PLN-4200.01
** RNum No.
j
~ Offsite Dose Calculation Manual (ODCM) 11 2
, TABLE 3.1-2 (Cont'd) 1 Radioective Gaseous Weste Sampling brul Analysis ram i Table Notation
- a. The LLD is the smallest concentration of radioactNo material in that wil be detected with 96%
, probabnity with 5% probabaty of falsely concluding that a observation represents a reer signal.
~
For a particular measurement system (which rney indude lochemical' separation): 1
- J Il.D =
4.66 Ss- 1 l E V 2 . 22
- Y
- exp AAC) wne,e i ,
j LLD is the lowerlirnit of as defined abovg (as picoeurie por unit mass or volume). l S3la the standard deviation the background counting rate or of the counting rate of a blank
- sample as appropriate (as per minuie) l E is the counting (as counts per' transformation),
j v is the sample stre unks of mass or volume), i . 2.22 is the number transformatione per minute per pcocurie, l i Y is the fract radiochemical yleid (when aprdimNo), ! : A is the ' decay constant for the particdar radionudido, and
- At is the time between midpoint of sample cclisction and time of counting (for plant ofnuents, erwironmental samples),.
I . The of Snused in the' calculation'of the LLD for a detection system shmil be based on the-a , observed variance of the background counting rate or of the counting rate of the blank I (as appropriata) rather than on an unverilled theoretically prodktad variance. In calculating for a radionuclide determined by gamme ray spectrometry, the background shad include the contributions of other radionudidas normally present in the semples. Typical values of E, V,
, and At shal be used in the calmdatinn. The background count rate is calcdated from the kground counts that are dWermined to be with 2 one FWHM (fur-Wkith.at-Half 4Aaximum)
! erergy band about the energy of the gamma-ray peak used for the quantitative anafysis for that
- mdionuclide.
l ) . . ! 77.0 nm. i l - WORMATION ONLY t
j 03-11-97 10 56:15 , l Nunibet 3 hlg wi andidogichicontrd. Departmental Procedure 6610-PLJ4-4200.01 1~2e . Arosion No. Offsite Dose Calculation Manual (ODCM) 11 j . . TABl.E 3.1-2 ( d) l Radioactive Gaeoops Weete Sa ng and Analysis Program Ta Notation a { b. The principal gamma emitters for the LLD speelAcadon' applies exdusively are the following ! radionuclidae: MrW54, Fo49, , Zn416, Mo 99, Cs-134. Co 137, Co-141 and Co-144 for particulate i emissions. This list does not that only these nudidos are to be detected and reported. Other peaks ! which are measurable and , together with the etwo nuclides, shal also be identlRed and i , reported. Nudides which h the llD for the analyses shaN be reported as "less than" the nuclide's
- ' L1D and shal not be as being present at the 1.LD level for that nudido The ' loss than' values shaR not be uped in the does calculatiorm 1 .
( l . _ . _ s 1 i l e.. J 1 i i . l .
~ 78.0 em.
t i 1
-lNFORMAT10N ONLY 4
s a t
03-11-97 10:56:15 NEtd bAR T. E ODCM PART11 Definitiene 1.0 DEFINITI0lls DEFINED TERMS 1 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part 11 of the 00CM. f.lL.S 1.2 Post-Defueling Monitored Storage (PDMS) is that con (stion whwe TMI2 defueling has been completed, the core debris removed from the reactor during the cluna, period has been shipped off-site and the facility has been placed in a stable, safe and ucure condition. ALIlQ!f 1.3 ACTION shat be then additional requirements specified as coronary staternents to sech control and that be part of the controls. OPERABLE . OPERABILITY 1.4 A system, subsystem, train, component or device shaR be OPERABLE or have OPERABILITY when it is capable of performing its specifed function (s). Implicit in this defmition abau be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical powet sources, cooling or seal water, lubrication or other sexiliary equipment, that are required for the system, subsystem, train, component or device to pwfem its function (s), are also capable of performing. their related support function (s). CHANNEL CAllBRATION l 1.5 A CHANNEL CAllBRATION shan be the adjustment, as necessary, of the channel output such that it responds with necessary rsngs and accuracy to known values of the paramster which the channel monitors. The CHANNEL CAllBRATION shall encompass the entire channel including the unsor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel stapa such that the entire channelis calibrated. CHANNEL CHECK 1.8 A CHANNEL CHECK slull be the quaitative assessment of channel behavier during operation by ohnervation. This determination sher include, where possible, conperinen of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. ROTE - For radioactive effluent monitors,A .7m , " this shallinclude a verification which native assessment of channel raponn chj - is exposed to a radioactive source. % CHANNEL FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog channels the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY laciuding alarm and/or trip functions.
- b. Bistable channels the injection of a simulated signallato the channel sensor to verify OPERABILITY locluding alarm and/or trip fumetions.
Sevec.E OHECX 1,e, A Sec8CE CHECK sk4}} be. 4kt.g4h4 , assessge c ka nne I response. nu w ek nm.) senu,c is upeaJ 4-a nJmaclue_sexua .
- 03-11-97 10
- 56:15 COMPOSITE SAMPLE 1.)9 A COMPOSITE SAMPLE is a ceneinstion of individual mples obtained at regular intavals ovw a time period. Eithw the volume of each indhsfuel sample is proportional to the rate discharge at the time of sampling or the number of equal volume samples is proportional to the time period used to produce the composite, i GRAB SAMPLE j 1.l A GRAB SAMPLE is an individual sansple eclieeted in less than fifteen minates.
BATCH RELEASE j U 1.}d A BATCH RELEASE is the discharge of fluid wasta of a discrete volume. 1 CONTINUOUS RELEASE l 2 ] 1.g#2 A CONTINUOUS RELEASE is the discharge of fluid waste of a nondiscrete volurre, e.g., from a volume or system } an input flow dwing the CONTINUOUS RELEASE.
- FREQUENCY NOTATION 83 l 1.R The FREQUENCY NOTATION specified for the puformance of Survoihnee Requirements shad correspond to the'intervsis defined in Table 1.1. AH SurveiRance Requirements shal be perfonned within the specified t'wns interval with a maximurn allowable extension not to ceed 25% of the surveillance intavat i
i TABLE 1.1 .
! 1 Frequenay Notatisa l
NOTATION FREQUENCY ! l S (Shiftly) At least once pw 12 hows. l s l 0 (Daily) At least once per 24 hows.
- W (Weeldy) At least once pw 7 days.
4 j M (Monthly) At least once pw 31 days. i 0 (Quarterly) At least'once pw 92 ders. i
- SA (Semi 4nnualy) At least once pw 184 days.
j A (Annually) At least once pw 12 months. E At least once per 18 months. i N.A. Not applicable. { P Completed prior to each release l 1 a 0 0
- - - -- - . = ._ . . - - - . . . _ .
I l 03-11-97 10:56:15 2.0 l CONTROLE AND RASES 1 2.0.1 Contrds and ACTION regsements shal be applicable during the conditions specified for each control 2.0.2 Adherence to the requirunents of the Control andler associated ACTION within the specified time intuval shall constitute compliance with the connel in the event the Controlis restored prior to expiration to the specified tirne interval, completion of the ACTION statement is not required. 2.0.3 in the event the Control and associated ACTION requirements cannot be satisfied because of circumstance in excess of those addressed in the Control, initiate appropriots actions to rectify the problem to the extent possible ' undu the circumstances, and submit a special report to the Commission pasuant to TMi-2 PDMS Technical i Specification (Tech. Spec.) Section 6.8.2 within 30 days unless otherwise specified. 1 2.1 Radioactive Effluent lastrumentation , 2.1.1 Radioactive liquid Effluent Instrumentation a Radioactive Liquid Effluent instrumentation is connon between TMl1 and TMI2. Centrds, applicability, and actions are specified in 00CM Part I, Control 2.1.1 4 2.1.2 Radioactive Gasmus Process and Effluent Moniterlag lastrumentation CONTROL: The radioactive gueous process and effluent monitoring instrumentation channels shown in Table 2.12 shal be OPERABLE with their alarmitnp setpoints set to ensure that the rnita of Centrol 2.2.2.1 are not exceeded. The alenettrip setpointe of these channels shall be deternened la accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCML APPLICABillTY: As shown in Table 2.12. ACTION:
- a. With a radioactive gasseus process or effluent monitoring instrumentation channel alarmitrip setpoint less conservative then required by the above control,immediately suspend the reisess of radioactive afiluent monitored by the affected channel or declare the channel inoperable.
- b. With less then the aanmun nunber of radleactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shows in Table 2.12. Exert best effwts to return the lastrumentation to OPERABLE status within 30 days and,if unsuccessful, explain in the next Annual Effluent Release Report why the inopwebility was not corrected in a timely mannw.
BASIS The radioactive gessous effluent . instrumentation is provided to monitor and control, as applicable, the releases of
, radioactive meterials in gaseous effluent during actual or potential releases. The alarmitn'p setpoints for these instruments shal be calculated in accordance with NRC approved methods in the 00CM to provide reasonable aneurence that the annesi releases are within the inits specified in 10 CFli 20.1301.
4
O e H TeMe 2.1-2 881BfLE42SO.01 P Revisies' 11 E Radeactwo Geseems Process and Effluent Monitoring histrumentation 4 H O sm MHNBUM CHAISfELS INSTRUMENT - OPERABLE APPUCABggy ACTION w
.1. Costasunent Purge Monitoring System g
' gl .
- a. NsMe Gas Activity Memter dip-R225) . 1- NOTE 1 NOTE 2 2.
- h. Particulate Monitor h-R-225) 1 NOTEI NOTE 2
- c. Effhrent System How Rete Messunes Device (2AHfR-5064) , 1 NOTE 1 NOTE 3
- 2. Station Ventilatice System i
- s. 2 -
- s. Noble Gas Activity Monitor kPS219) er kP4219Al 1 NOTE 1 NOTE 2 2.: 2- l
- b. Particulate Monitor kP-R-219) er P-R-219A) 'l NOTE 1 NOTE 2
- c. Eftuent System Fles Rate Messanng Device (2HPNPIR-219) 1 NOTE 1 NOTE 3 NOTES: ,
- 1. Dwing aparation of the monitored systent
- 2. With the number of channels GPERABLE less than required by the Mimmum Channels OPERABLE requirement, secure Reacter Bailding Purge if in progress.
- 3. With flew rate monitoring instnanentation out of service, flew rates from the Auxilary, Fuel Handing, and Reactor Buildings may be estirnsted using the maximum design flow for the exhaust fees in operation.
*%G. mm
i 03-11-97 10:56:15 2.2 Radioactive Effhant Controls 2.2.1 Liquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration i ! 1 i l CONTROL: j The concentration of radioactive meterial rolessed at anytime from the unit to unrestricted trees shou be limited to
+
{ ten times the concentrations specified in 10 CFR Part 20.100120.2401, Appendix B Table 2. Column 2. ! APPLICABILITY: At au times ACTION-With the concentration of radioactive meterial rolessed from the unit to unrestricted areas exending the above Trnits, irnmediately restore concentr'stions within the above limits.
, BASES i
This centrol is provided to ensure that the i:encontration of radioactive meterials released in liquid weste afflue'nt I { from the unit to unrestricted arms will be less then ten times the concentration levels specifwd in 10 CFR Part ; 20.1001 20.2401, Appendix B. Table 2. These Controle permit flextliity under usueuel conditions, which may i I temporarily result in higher then serieel reiness, but still within ten times the concentrations, specified in 10 CFR l 20. It is expected that by using this flextility unda uneeuel conditions, sed exerting every effort to keep levels of
' radiesetive meterialin liquid westes as low as practicable, the annual relemos wil not excmd e emeu fraction of 4 the annual everage concentrations specified in 10 CFR 20. As a reeutt, this Control provides reasonable escurence I that tiis resuhmg annual exposers to en individualin off-site areas wiR set exceed the daign objectives of Section l ILA of Appendix I to 10 CFR Part 50, which were established as requirements for the clanup of TMI-2 in the l 1 NRC's Statement of Policy of Apr0 27,1981, 4
2.2.1.2 Liquid Effluent Dose I j CONTROL i' I The dose or due commitment to e MEMBER OF THE PUBLIC from radioactive meterials in liquid affluents reisesed from the unit to the SITE BOUNDARY ahall be limited: t i s. During any calender quarter te less'then or aquel to 1.5 anrem to the total body and to las than or equel to 5 mrom to any orgen. 4 b. During any calender year to l' ass then or equal to 3 mrom to the total body and to iss: thin or aquel to
,10 mrom to any orgen.
i APPLICABILirY: At all timm ' 4 i i 1 i l M ' 4
03-11-97 10:56:15 ACTION: 4
- s. With the calculated dose from the release of ra(mactive materials in Equid effluents exceeding any of the I abow limits prepare and submit to the NRC Region 1 Administrator within 30 days, a Special Report which idntifies the cause(s) for excuding the Emit (s) and defina the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current
- calender quarter and during the subsequent 3 calender quarters so that the cumulative dose or dose commitment to any infrvidual from auch releases during these four calender quarters is within 3 mrem to the total body and 10 mrom to any orsen. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiologicalimpact on finished drinking watw supplies with regard to the requirements of 40 CFR 141, Safe Orinking Wetw Act.
BASES I This Control requires that the dose to offsite pusonnel be Ernited to the design objectives of Appendix 1 of 10 CFR Part 50. This wil usure the does recoind by the pubEc during POMS is equivalent to or luss than that from a a nonnel operating reactor. The limits else assure that the environmental impacts are consistent with those assessed
- in NUREG4683, the TML2 Programmatic Environmental Impact Statement (PElS). The ACTION statements provide 4
' the required flexibility undw unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix l to ensure that the rolesses of redisectiw meterial in liquid effluents wil be kept "as low as is j reasonably actuevable". The dose calculations in the ODCM implement the requirements in Section Ill.A. of Appendix 1 that conformance with the guides of Appendix lis to be shown by calculational procedures based on nodels and date auch that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is l unlikaly te be substantially underestimated. The equations specified in the 00CM for calculating the doses due to the actual releue rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1,109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpees of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October,1977, and Regulatory Guide 1.113, ? Estimating Aquatic Dispersion of Effluents from Accidatal and Routine Reactor Releens for the
, Purpose of implementing Appendix 1,* April,1977. NUREG 0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.
2.2.1.3 Liquid Redweste Treatment System , l CONTROL: l The appropriate portions of the liquid redweste treatment system shall be und to reduce the radioactive i materials is liquid westes prior to their discharge when the projected dous du to the liquid ofHunt from the unit to unrestricted areas would exceed 0.06 mrom to the total body or 0.2 mrom to any organ in any calendar month. LPPLICABILITY: At au times AC710N:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above
, runits, propero and submit to the NRC Region 1 Administrator within 30 days, a Special Report which includes the folowing information:
' ~
i 1. Explanation of why liquid redweste was being discharged without treatment,
, identification of any inoperable equipment or subsystems, and the reason for 2 inoperainlity,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and,
- 3. A summary description of action (s) taken to prevent a recurrence.
i BASES
03-11-97 10:56:15 ' Tbs requirement that the appropriate portions of this system (shared with TMI.11 be used, when specified, provides enurence that the rolesses of radioactive materials in liquid offlunts wil be kept as l low as is reasonably. schiwable. This controlimplanents the requirements of 10 CFR Part 50.36e, General Design Criterion 60 cf Appendix A to 10 CTR Part 50 and tie daign objective given in Section ILD of Appendix I to 10 CFR Part 50. The latent of Section R.D. is to reduce efflants to es low as is " reasonably achiweble in a cost effective manner. This contro! stisfies this ictent by estabishing a dose limit which is e small fraction (25%) of Section ILA of Appedix 1,10 CFR Port 50 dose requirements. This margin, e factor of 4, constitutes a reasonable reduction. 2.2.2 Gasmus Effluent Controls 2.2.2.1 Gasseus Effluent Dose Rate j CONTROL: t The dose rate du to radioactin meterials released in geseous effluent from the site sheG be Emited to the Iollowing: l e. For nok gesu: less then or equel to 500 aremlyr to the total body and las then or equal to 3000 aremlyr to the skin, and
- b. For ; T, ';Nritism and en radienucrules in particulate form with half Ens yester then 8 days:
- less than or equel to 1500 mromIyr to any orgen.
APPLICABillTY: At all times. ACTION: With the release rate (s) exceeding to aben limits, kumediately decreue the rolesse rate to comply with the above renit(sl. BASES The control provida reasonah esaurence that the annul does et the SITE BOUNOARY from gaseous effluent from en units on the site wil be' within the annual dose Enits of 10 CFR Part 20 for unrutricted areas. At the same time, these Cutrols permit flexibility under unusual conditions, which may temporarily result in higher than the design objective levels, but stir within the dose limits specified in 10 CFR 20 and within the design objectivu of Appendix i to 10 CFR 50. 'It is expected that using this flexibility under unusual conditions, and by exerting every effort to keep levels of radioactive meterial in genous westes es low as practicable, the annual rniasses wil not exceed e emot fraction of the annual does fenits specified in 10 CFR 20 and wil not result la doses which exceed the desip objectives of Appendix i to 10 CFR 50, which were endereed as limits for the doenup of TMI-2 by the NRC's Statement of Policy of Apri 27,1981. These gaseous rolenes rates provide ressenable esaurence that . radiesetive meterie! discharged in gessoas affluent wHl not result in the exposure of e. MEMBER OF THE PUBLIC in en unrestricted eres, either within or outside the SITE BOUNDARY, to ennual everoga concentrations exceeding the velas specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupeacy of the MEMBER OF TliE PUBLIC will be oeffsiently low to compensate for any incrosas in the atmospheric diffusion factor above that for the exclusion eres boundary. The specified release rate Emits restrict, et a0 tirms, the corresponding gemme and bete dose rates above background to a MEMBER OF THE PUBLIC et or beyond the SITE BOUNDARY to las then or equel to 500 nremlyear to the total body or te less then or aquel to 3000 mromlyear to the skin. The absence of iodine ensures that the corresponding thyroid does rate above background to en infant via the inholetion pathway is less then or e el to 1500 nremlyr INURE 0 0133),+ hiss &hese is w neeJ 4e upm4 Acme. 4%e. hh aw-
%ese. euc heles.
2.2.2.2 Desmus Effisents Dose Noble Geses CONTROL: W -
l 03-11-97 10:56:15 The air dose due to noble gasa released in gaseous effluents from Cs unit to areas si and beyond the SITE BOUNDARY ahal be faited to the fotowing-e. During any calendar quartsr: leu thu or aqest to 5 anii for genma redhtion and low then ei equal to 10 mrad for beta redstian and, b. During any calendar year: less than or equal to 10 mrad for gamme radiation and las then or equal to 20 mrad for beta radiation. . APPilCABillTY: At all times. 3 ACTION: ! a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the j thove Emits, prepare and submit to the NRC Region i Administrator within 30 days, a Special Report which identifies the causels) for exceeding the limitis) 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 relmses wit be in compliance with the above limits. BASES . This contrel' applies to the relsess of radiesetive materials in gasmus effluonk from TMI.2. 4 This centrol and associated action is provided to implement the requirements of Section N.8, llLA and IV.A of 4 Appendix 1,10 CFR Part 50. The Controlimplements the guides set fort in Section ILB of Appendix L The ACTION statements provide flexibihty under unueuel conditione and at the same time implanent the guida set forth in Section IV.A of Appendix 1 to asswa that the rolesses of radioactive materialin gaseous effluents wil be kept
; *as low as is ressenably achievable." The Swveillance Requrements implement the requirements in Section !!LA of j
Appendix 1 that conformance with the guides of Appendix I he shown by calculational precedures based on models and date such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantia 0y underestimated. The dose calculation methodelegy and parametws established in the 00CM for calculating the doses due to the actual release rates of radioective noble gases in gueous effluents are consistent with the methodology provided in Regulatory Guide 1.10g, *Celculation of Annual Duas to Man from Routine Release. of Reactor Effluents for the Pwpose of Evolusting CompEence with 10 CFR Part 50, Appendix 1,* Revision 1, October 1977 and Regulatory Guide 1.111,
- Methods for Estinating Atmospheric Transpwt and Dispersion of i
Geseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The 00CM equations provided for determining the air doses at and beyond the SITE BOUNDARY we based upon the historical average atmospheric conditions. NUREG41133 provides methods for does calculations ceneistent with Regulatory
- Guides 1.109 and 1.111.
1 .
- 2.2.2.3 Due - ledine.131, lodine.133, Tritium, and RadionucEdes in Particulate Form CONTROL
! The dose to a MEMBER OF THE PUBilC from ' " ::', ':f...; t'%Tritingand all radionuclida in particulate i form with half Eves greater then 8 days, in genous effluents reinsed from the unit to areas at and beyond the SITE BOUNDARY shal be ranited to the fdowing:
- a. During any calendar quarter:less then or equal to 7.5 mrom to any organ, and
- b. During any calender year:less than or equal to 15 mrom to any organ.
APPLICABILITY: At al t'unes. ACTION: With the calculated dose from the reinse of Li..10;. ' f ; '"_Tritiungand radionucEdes in particulate form with half livu greater then 8 days, in gemous effluents exceeding any of the above renits, prepare and submit to e
03-11-97 10:56:15 the NRC Regin i Administrator tithin 30 thys, a Spaial Report tehich identifies the cause(s) for exc'eeding the lirnit and defines the corrective actions that have bun taken to reduce the releases and the propossd corrective actions to be taken to asure that subsequent releases wil be in compEence with the above Innits. BASES l This control applies to the release of radioactive motorials in gaseous effluents from TMI6 i l
- This control and associated action is provided to implement the requirements of Section ILC. BLA and IV.A of
)
Appen6x 1,10 CFR Put 50.~ h Controls are the guides set forth in Sution ILC of Appendix L The ACTION statement provides fladility during unusual con 6tions and at the same tirne implements the guides set forth in l Section IV.A of Appendix 1 to assure that the taleeses of ra6eactive materials in gaseous effluents will be kept "as low as is reuenably achievable." N ODCM calculationst methods specified in the surveillancs requirements 4 implement the requirements in Section HLA of Appendix 1 that confwmence with the guides of Appendix I he shown by calculational procedures based en models and data such that the actual nposure of a MEMBER OF THE PUBLIC 4 through appropriate pathways is unlikely to be substantiaHy undwestimated. N ODCM calculational methodology j and parannters for calculating the deses due to the actuel release rates of the subject meterials are consistent i with the methodology provided in Regulatory Guide 1.109, ' Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents fer the Purpose of Evolusting Compfmece with 10 CFR Part 50, Appen6x 1,* Revision 1, Octobw,1977 and Regulatory Guide 1.111,
- Methods for Estimating Atmospheric Transport and Dispersion of j
Gaseous Effluents in Routine Releases from Light-Water.csoled Reectors," Revision 1, July,1977. These equations ! 1 also provide for detwmining the actual deses based upon the historical average etnisepheric conditions. The release ! rate controis for ledine-131, iodias 133, tritium and radienuclida in particulate form with half lives greater than 8 1 days are dependent upon Ilm existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY.
- & pathways that were examined in the development of these calculations were
- 1)in6vidualinhalation of airborne radionudides,21 depuition of radienudides ente green leafy vegetation with subsequent censumption by
? men,3) deposition ente grassy areas where mik animais and meet producing animais graze with consumption of I the milk and meet by men, and 4) ' n on the ground with uent exposure of mes.Tk.alescra of j iedess oAhs 5A,elwmem 14 ,wasA b specifg e imA bc-+hese ruddes,, j 2.2.2.4 Ventilation Exhmst Treatment System CONTROL The VENTILATION EXHAUST TREATMENT SYSTEM shou be OPERABLE. The appropriate portions of the . VENTILATION EXHAUST TREATMENT SYSTEM shal be used to reduce radioactive meterials in gaseous weste prior 4 to their discharge when the monthly projected doses due to gaseous affluent releases from the site would exceed ' 0.3 mrom to any organ. APPilCABillTY: At all times. ACTION:
- a. With the vel (TILAT10N EXHAUST TREATMENT SYSTEM inspeeble fu more then a month w with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region 1 Adamstrator within 30 days, a Spelal Repwt which includes the following i information:
- 1. Identificatien of the inoperable equipment er subsystems and the reason for inoperability,
)
- 2. Action (s) taken to rutore the inoperable equipment to OPERABLE status, and
- 3. A summary description of octionis) taken to prevent a recurrence.
4 BASES i The use of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gessoas effluents are treeted as j sppropriate prior to rolesse to the environment. N appropriate portions of this system provide reasonable sisurance that the rolesses of radioective meterials in geoeous effluents will be kept *as low as is reasonably ( .
M i 03-11-97 10:56:15 l' achievabb." This controlimplements the requirements of 10 CFR Part 50.36a, General Design Criterion to of Appendix A to 10 CFR Part 50, and the dnign objectives ginn in Section ILD of Appendix ! to 10 CFR Part 50. The specified limits govwning the use'of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections ILB and ILC of Appendr 1,10 CFR Part 50, for gaseous effluents. 2.2.3 Total Rediactin Effluent Centrols 2.2.3.1 TotalDose CONTR01 The annual (celender yur) due or dose commitment to any IEMBER OF THE PUBUC, due to releasu of radioactivity and to radiation from wanium fuel cycle sources shaR be Emited to less then er equal to 25 nrem to i the total body or any organ except the thyroid, which shall be limited to less then or equal to 75 rnrem. ) APPLICABILITY: At all times. 1 ACT10N: With the calculated dose from the release of radioactive meteriale in liquid er gaseous. effluents exceeding twice the Innits of Controls 2.2.1.2.a, 2.2.1.2.b. 2.2.2.2.a. 2.2.2.2.b, 2.2.2.3.a, or, 2.2.2.3.b, calculations should be made including direct radiation contributions from the unit and from outside storage tanks to determine whethw the above Emits of Control 2.2.3.1 have been exceeded. If such is the case, prepare and submit to the NRC Region i Administrator within 30 daysi e Special Report which defines the corrective action to be taken to reduce 5 subsequent reiseses to prevent recurrence of exceeding the above limits and *mcludes the schedule for schieving conformance with the ebeve limits. This Special Report, as defined in 10 CFR Port 20.2203(b), shallinclude an analysis which estimate the redletion expuure (due) to e MEMBER OF THE PUBUC from uranium fuel cycle sources, inriuding all effluent pathways and direct radiation, for the calender year that includes the release (s) covered by 21: report. It she0 else deserte levels of redwtion and concentretiens of reductin material innind, and the coese of the exposwo levels or concentrations. li the estimated due(s) exceed the above limits, and if the raisess condition resulting in vielstion of 40 CFR 190 Le not already been corrected, the Special Report shal . include a request for a variance in accordance with the previsions of 40 CFR 190. Submittel of the report is considwed a timely request, and a variance is greated W #eff action on the request is complete. ,i BASES i This centrol is pr'evided to meet the dose limitations of 40 CFR Part 190 that have been, incorporated into 10 CFR I Port 20.1301(dk This centrol4equ!res the properation and submittel of a Special Report wheenr the calculated doses from plant genereted radioactive affluents and direct radiation exceed 25 mrom to the total body or any I organ, except the thyroid, which shell be Emited to less then or equal to 75 arem. For sites containing up to 4 ructors, it is higidy unlikely that the rueltant dose to a MEMBER OF THE PUBlic wit exceed tlw dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appen6x 1, and il direct radiation doses from the reactor anits and outside storage tanks are kept small The Special Report will ducribe a course of setlen that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 Emits. For the purposu of the Special Reprt, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle faciEtim at the some site or within a radius of 8 km must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release condtions resulting in violation cf 40 CFR _ Part 190 han not already been corrected), in accordance with the previsions of 40 CFR Part 190.11 ard 10 CFR Port 20.2203(b), is considered to be a timely request and fulf5s the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relata to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individualis not cons!dered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nucles'r fuel cycle, Jetr .
03-11-97 10:56:15 3.0 SURVEILLAllCES
~
3.0.1 Surveillance Requiremsnts s5d be applicable during the esoditiene specified for individual Controla unless otherwise i stated is en individual Surveilence Requirement. The Surveillance Requirements shd be perforrned to demonstrate l compEence with the OPERABILITY requirements of the Control 1 3.0.2 Each S>rveillance Requirement sher be perfonned within the specified time interval with a maximum alowable extension not to exceed 25% of the surveillence interval. 3.0.3 Failure to perrform e Surveillance Requirement within the time interval specified in Section 3.0.2 sher constitute noncompliance with OPERABILITY requirements for a Control The time limits of the ACTION requirements ers j spplicable et the time it is identified that a Surveillance Requireamet has not been performed. The ACTION requirements may be delayed for op to 24 hours to permit cour)stion of the sunigence when the allowable outage time limits of the ACTION requirements are less ther 24 hours. Surve10ance Requirements do not have to be performed on looperable equipment. l 3.1 Radioactive Effluent lastrumentation 3.1.1 Rediesetive liquid Effluent Instrumentatin Surveigence Requirements
- Radiesetive Liquid Ofisent instrumentation is comnen betwun TMI-1 and TMI-2. Surveilences for this instrumentation are spdfied in DDCM Port I, Surveillence 3.1.1.
3.1.2 Radienctin Deesous Process and Effluent Monitoring instrumentet'ma SURVEILLANCE REQUIREMENTS 3.1.2.1 Each radienctive gaseous process er effisent monitoring instrumentation channel sheH be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION. and CHANNEL TEST operations at the frequencies shown in Table 3.12. 9
/
_ . . . . _ _ . _ , _ . . . _ . ~ . . _ _ _ _ _ . . . . _ . _ _ _._ _ _ _ _ . . . _ _ _ _ l i e i o l ta e l , e l Tame 3.1-2 6810PLN4208.51 P Revision 11 E a l Radiesetive Geseous Process and Effhmt Monitoring Instummatation Swweigence Requrements e O
, w I , m 3
P CHAWdEL CHAlelEL CHANNEL m i BISTRUMENT CHECK CALBRATIGN, FUNCTIONAL TEST APPLICABILITY
- 1. Centemenant Pwee Mestenne Systen 9-
- a. Noble Gas Activity Monitor tiP-R-225) D E M NOTE 1 Smpk '
- b. R225) gW g AIA / N/A NOTE 1 Paraculate-Monient {2.
- 2. Station Ventilation Monitoring System
- a. Nelle Gas Activity 18ests: P-R-219 g 2 9Al D E M NOTE 1 somyk ovwk M
- h. Paracelete Monieme R219)/ 4219Al .k'NM JrN/A NOTE 1 Z. A NOTES:
- 1. Dering operation of the memtered system I1714
l 03-11-97 10:56:15
; 3.2 Radioactive Effluents 3.2.1 Liquid Efflants SURVElllANCE REQUIREMENTS i
3.2.1.1 Concentration 311.1.1 The radionetivity content of each batch of radioactive liquid waste shall be determined
' by sampling and analysis in accordance with Table 3.21. The results of analyses shall be used with the calculational methods le the 00CM to assure that the concentration d
at the point of release is maintained within the limits of Control 2.2.1.1.
, 311.1.2 Analysis of semplu composited from batch rolesses sher be performed in accordance l 1
with Table 3.21. The results of the snelysis shall be used with the calculational methods in the DDCM to assure that the concentrations at the point of release were maintained within the limits of Control 211.1. 3.2.1.1.3 The radioactivity concentration of Equids discharged from continuous release points sha!! i he determined by ceRection and analysis of samples in accordance with Table 3.21. The results of the analysis shan be uss$ with the calculational methods of the ODCM 4 to esaurs that the concentretion at the point of release is amintained withis the limits of Controf 2.2.1.1. 1 3.2.1.2 Dose Calculations . 3.2.111 Cumulative dose contributions from Equid effluents shall be determined in accordance
, with the Offsite Dese Calemistion Manuel(0DCM) et least once a month. I l
l 311.3 Dose Projections l j 311.3.1 Deses due to liquid reiseses shal be projected at least once e month, in accordance l with the ODCM. l f 1 1 i J J I e i l 4 i tttf . l l
03-11-97 10:56:15 TABLE 3.21 Radienctive Liquid Weste Sampling and Analysis (4, El l A. Liould Releases Type of Detectable Sampling Frequency Activity Analysis Concentration ;3) l P Individual Gamms SE 7 Cilmi (21 Each Batch H4 1E4 pCilnd 0 Gross Alpha 1E 7 pCilml Quarterly Composite (1) St-90 SE.8 pCilmi NOTES: (1) A COMPOSITE SAMPLE is one in which the quantity of liquid sempled is proportional to the quantity of liquid waste dischstged from the plant. (2) For certain mixtwo: of genune emittus, it may not be possible to musure radionschdes in concentrations near this sensitivity lirnit when other nuc0 des are present la the sangle in much greater concentrations. Under these circumstances, it wit! be more appropriate to calculate the concentrations of such radienuclides using measured ratios with those radienudidas which are routinely identified and moseured. (3) The detectability limits for radioactMty analysis are based en the technical feasibility and on the potential significence in the environment of the quantities released. Fw some nucEdes,loww detection limits may be readily achievabis and when nuclides are j measured below the stated Emits, they should ales be reported. ' (4) The results of these snelyses should be used es the basis for recording and reporting the quantities of redometive material released in liquid effluents dwing the samping pwied in estimating releases for a period when analyses were not pwformed, the avwege of the two adjacent data points spannind this period should be used. Sad estimates should be indaded in the effluent records and reporte however, they should be clearly identified as estunstes, and the method used to obtain these data should be described. (5) Deviations from the semplinglenelysis regime wiR be noted in the report specified in ODCM Part IV. W e l
03-11-97 10:56:15 3 3.2.2 Oueous Effluents l SURVEILLANCE REQUlREMENTS 3.2.2.1 Dose Rates 3.2.2.1.1 The dose rate due to noble gases in gueous affluents shaR be determined to be within the Gmits of Control 2.2.2.1.s in accordance with the methods and procedures of the ODCM. J 3.2.2.1.2 The dose rate of radioactive materials, other than noble gesu, in gasuus effluents shall be determined to be within the Gmits of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative samples and i performing analyses in accordance with the sangling and analysis program. specified in ! Table 3.2 2. . l 3.2.2.2 Dose, Noble Gas i 3.2.2.2.1 Cunnletive due contributane from noble ses effluents for the current calendar gearter 4 and current calendar year shall be detenmined in cccordance with the OFFSITE DOSE i CALCUIATION MANUAL {0DCM) monthly. I 3.2.2.3 Due, ' . di, =_._ Nritigand Radienuchs la Particulate Form 3.2.2.3.1 Cumulative does contributions from ' " - ??!. E?i ATritigend radionuclidu in particulate form with half lives yester than 8 days for the current calender quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE j CALCULATION MANUAL (ODCM) monthly. 3.2.2.4 Ventiation Exhaust Treatment 1 i 3.2.2.4.1 Doses due to saaeous releases from the unit shall be projected monthly in accordance with the ODCM. i 1 t 4 , 4 e b
'T9:S. .
i k
03-11-97 10:56:15 TABLE 3.12 l Radioactive Caseeue Weste Sempting ned Analysis (3) SAMPilNG TYPEOF DETECTABLE SAMPLE POINT SAMPLE TYPE FREQUENCY ACTMTV ANALYSIS CONCENTRATION (1)W Reactor Building Purge Releases Gas P H3' 1E-6 pCUce Each Purge- Individual l Gemme Emitters IE4 utilce G) l 4 Unit Exhaust Vent Rduce Points Gas M H4 IE 6 Cilce Monthly individual l Gesuna Emitters IE4 Cilec (2) W ladividual (b) Particulates Weekly Gensna Emitters 1E 10 tilce (2) M l Monthly Sr90 1E 11 pCilec i Composite l M Gross Alpha Enders Monthly 1E 11 pCilec Composite Reactor Bulding Breather Particulates SA indv. Gamme Emitters (b) 1E 10 Cilce (2) Semi Annualy Sr 90 IE 11 pCilec Gross Alphs Emitters 1E 11 CiIce ill The above detectabiEty linits are based on tednical feasiblity and on the potential significance in the environment of the quantities rolessed. For some nuclides, lower detection runits may be readily achievable and when nuciales are measured bdow the stated limits, ' they should also be reported. (2) For certain mixtures of gamme emitters, it may be possible to maamre radienuclides at levels near their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be mers appropriate to calculate the levels of such radionucEdes using observed ratios in the gaseous component in the ructor coolant for those radionuclides which are measurable. (3) Deviations from the sempling and analysis regime wis be noted in the report specifed in ODCM Part IV.
.o
[ 21718
03-11-97 11:05:21 TABLE 3.2 2 (Cont'd) Radieestive Geessus Waste Samplies and Analysis Program Table listaties l
- a. The LLD is the smallest concentration of radioactive meterial in a sample that wil be detected with 95% probability with 5%
, probability of falsely concluding that a blank observation represents s "real* signal For a particular measurement system (which may indude radiochsmical separation): 4.66 S3
- E V
- 2 . 2 2
- Y exp (-A a t)
Whwe LLD is the loww limit of detection as defined above (as picoeurie per unit mass or volume). > . l S is the standard deviation of the background counting rate or ' of the counting rate of a blank samp!s as oppropriate (as counts per minute). E is the counting efficiency (as counts per transformation), V is the esmple size (in units of mass er volume), 2.22 is the number of transformations per minute per picecwie, , Y is the fractional radiochemical yield (when applicable), A is the radioactive decsv constant for the particular radionuclide, and ' , at is the s'apsed time between midpoint of sample colisction and time of counting (for plant affluents, not environmental
- samples),
The value of 3, used in the calculation of the LLD f'or a detection system shall be based on the actual observed variance of the background counting rate er of the counting rate of the blank semples (u appropriate) rather than on an unverified theoretically predicted variance. la calculating the LLD for a radienuclide determined by gamma <ay spectrometry, the , background shall include the typical contributions of othw radionucEdes normely present in the samples. Typical values of E, V, Y, and at shau be used in the calculation. The background count rate is calculated from the background counts that are detennised to be with 2 one FWHM (Ful-Width-st4faif-Maxunum) energy band about the energy of the gamme<sy peak used for the quantitative analysis for that radienuclide. s
- b. The principal samma emitters for which the LLD specification app 5es exclusively are the folowing radienuclidec Mn-54, Fe-59, Co-58, Co 60,2n 65, Mo-99, Cs 134, Cs437, Co 141 and Ce444 for particulate emissions. This list does not mean that ony these aucEdes i
are to be detected and reported. Othw peeks which are measurable and identifiable, together with the above nucEdes, shal aise be identified and reputed. NucEdse which are below the LLD for the analyses shaR be reported as "less than" the nucHde's LLO and shal not be reported as being present at the LLD level for that nuclide. The "less than* values shal not be used in the required dose calculations.
-94 sm.
- -__ _. . .. . . . .= . . . ..--. - - . .. . - --__. -- - - _
03-11-97 11:05:21
- 3.2.3 Total Radioactive Effluents i
l 3.2.3.1 Dose Calculation i 3.2.3.1.1 Cumulative annual dose contributions from liquid and Osseous effluents shau be .' determined in accordance with Surveilluces 32.1.2.1,3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained h the DDCM. 4 i e l ) 8 I, 1 1 I J i I a u a 9
% 1171s
1 I 03-11-97 11:05:21 SECTION 4.0 , Desige Festarse 4.0 DESIGN FEATURES 4.1 EM EXCLUSION AREA 4.1.1 The exclusion area is shown la Figure 51, TMI1 Tech. Specs. LOW POPULATION ZONE 4.1.2 The low populetlen zone is shown in Figure 5 2, TMI1 Ted Specs. ] SITE BOUNDARY FOR GASEOUS EFFLUENTS i ! 4.1.3 The site boundary for gaseous effluents shall be as defined in Section 2.1.2.2 of the TMl-1 FSAR and as shown in i Figure 2.13. TMII FSAR.
- SITE BOUNDARY FOR tt0U10 EFFLUENTS i
4.1.4 The site bouancry for liquid effluents abs 0 be as shown in Figure 53, TMII Tech. Specs. j i I l J i i i I i s a d
03-11-97 11:05:21 i 64 PART Il REFERENCES
, 5.1 NUREG 0683, " Final Programmatic Environmental impact Statement ralsted to decontamination and disposal of radioactive
- wastes resulting frem Much 28,1979, accident Three Mile Island Nuclew Station, Unit 2,* Much 1981, and its j supplements.
5.2 TMI2 PDMS Technical Specifications, attached to Facility License No. DPR-73 j 5.3 Title 10, Code of Fedwal Regulations, " Energy * , 5.4 " Statement of Policy Relative to the NRC Programmatic Environmental Impact Statement on the Cleanup of Three Mile Isla'nd . Unit 2,* dated April 27,1981 5.5 Regulatory Guide 1.109, "Celculation of Annual Doses to Man from Routine Releases of Em.' tor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1,* Revision 1, October 1977 5.6 00ETIIC 27801, Atmospheric Science and Poww Reduction [ ! 5.7 TkN Technical Specifications, attached to Facility Operating License No. OPR40 I i 5.8 PDMS SAF i l l a i J 4 s e 4 4 4
_ _ _ - - - . - . - . .. --..- .. . .- - _~ .- - -. l 03-1 17 11:05:21 -
! Number i
ggy TMt Radiologks! Controls Departmental Procedure 6610-PLN-4200.01 T15e . f%evision No. Offstte Dose Calculation Manual (ODCM) 11 l 1 1.3 Control of Llauld Relemees ! TMl liquid effluent rolesses are controlled to less than ten times the 10CFR20 concentrations by lirniting the percentage of this iltnit alowable frorn the twoTMI liquid . release points. RM-l.S. and ofRuent sempling, limits batch releases to less than or aquel to 10% for all radionuclides,'and l RM-l.12. and effluent sampling, limits roleeses frorn TMl-1 and TMI-2 to less then or equal to 50% for . Cs-137. I These radiation monitor est points also include built in meter error factors to further ensure that TMI , a liquid effluent releases are less then ten' times the 10CFR20 concentrations to the
- W 5.2 - 1 f^e oben The rartinar*Nity content of each batch of radioactiveInquid weste _ ...;..ed e-O ^;;'__z by l
j 3 sempting and analysis in accordance with ODCM Part i Table 3.2- The results of ;;: :Jz analyses are used with the cairsdananel methods in 3ection 1.1, to assure that the concentration at j l . the point of release is maintained.within the ODCM Part l Control 2.2.1.1, and oce.M PA JI Cdd z.z.it
- ,,, ocen (b & II T.bte s.t-l
- Post-release analysis of w..-_-
- '^ - j from batch rulesees are performed in accordance with
- , ODCM Part 1 Table 3.2-1 The results of the previous poet <elease analyels shal be used with the calculationsi mahods in the oDcu to assure that.the concentretly<+ E C 4atnel the2.1point of release were j maintained wthin the ODCM Part I Cortrol 2.2.1.1g occM .
gg l The radh concentration cIIIq~uids discharged'frorn coritinuous reisees poin are determined l by octoction and analysis of semples in accordance with ODCM Pat i Tabb 3.2-1.The results of l . the analysis are used with the calculational methods of the ODCM to assure that the concentration
- at the point of release is maintained within the ODCM Part I Control 2.2.1.1g ODc M Par 4 E l Mt 2.z.I. I -
i l h .. T 1 j . i . ! G8 i e i 1 85.0 ma s i
- -. - . . - . . - . -. . . . . - . . _ . _ ~ _ . . .-.
03-11-97 11:05:21 -
- wmbw l
ggy ml Radiologic &l cortrois Departmental Procedure 6610 PLN-4200.01 Two . m uo. Offsite Dose Calculation Manual (ODCM) 11 2.2 TMI/Uould Radwaste System Dose Celes Once/ Month l ODCM Part I Control 2.2.1.3 and TMI-2 PDMS Tech Spec Secdon 6.7.4.a.6 requires that appropriate
, portions of the liquid radweste treatmort system shall be used to reduce the radioactive materials in ,
j liquid westes prior to their discharge when the monthly projected doses due to the liquid effluent , releases from each unit ,to unrestricted areas would exceed 0.06 mrom to the total body or 0.2 mrem , to any organ in any calendar month. The following calmd=Hanal method is provided for performing this dose projection. l
~
At least once per month, the total doise from all liquid releases for the quarter.to<iate wil be divided i by the tvJmber of days into the quarter and multiplied by 31. Also, this does projection shah include the estimated does due to any anticipated unusual rolesses during the period for which the projection is made. If this projeded does exceeds 0.06 mrom total body or 0.2 mrom any organ, l appropriate portions of the Liquid Radweste Treatment System, as deGned in Section 3.1, shall be . , used to reduce radioactMty levels prior to release. , At the discretion of Radiologimi Enginooring, time periods other than the current quarter.to-date may 1 be used to project doses if the does per day.in the, cununt quarter.to<iate is not believed to, be
- repreeereadve of the does per day projected for the noxi montfL i
J B e . 1 l 4 6 e i e 6 9 % meg 4 92.0 mm e e
--~----a l j 03-11-97 11:05:21 i
i E Procedure 661pLN-4200.01 i ns . .
~
] Offsite Dose Calculation Manual (ODCM) 11 i 4.4 '
.TMI 1 Gaseous Emuent Release Points and Gaseous Rartinelan Monitor Data 4
. TMi-1 has eleven (11) required amuent geneous radletion rnonitors. These are RM-A4, RM A5, i
RM-A15, RM-AS, RM-A7, RIAA8, RM-A9, RM A14, Al.C4MI 18, WHP-RIT 1, and Rt.M-RM-1 These i gaseous release points, redletion monitors, and semple poirts are shown in Table 4.1. diurvellaneo-i Y ; L *= % ; J d n : . :.L . :. , , _ :^
- L. ~ ,., ^ L : ~ _- .,.n ', _- , ;=
' ' '- X : w,u,,L ,. ,-. ^^ ' ' . ;.,;^ ' s .h ^- CL'. . '
l 4.4.1 RM-A4/RM-A6 Fuel Handlina and Auxflary Buldina Exhaust I f RM-A4 le the peitticulate, radiolodine and gaseous radiadon rnonitor for the TMI-1 Fuel l l Harumng Sulding Verenstam (see Figures 4.1 and 4.2) RM-A8 is the partta d=*=, radiolodine, and nemmem radiation monitor for sie TMI-1 Aussiery Belding Ventilation (see 1
. Figures 4.1 and 4.2). High alarms on RM A4 or RM A8 noble gas channels we initiate !
shuidown of the related bulding vendadon air supply system. These two radiation monitors ' concurnesy we satisfy requirements for the Stadon Vent relopee ' point in place of RM-A8.
'4.4.2 RM-A8 Sladon VandadortExhaust RM.A8 is the partloulate,'r=,unamerie and faceous radiation monitor for the TMI-1 Station Venmedan (see rigures 4.1_and 4.2). This in plant emuont radiation monitor also has an -
===ani e=,+ sampano penes wth sampung lines located before the sample stars. High alarm on RM-A8 noble gas low channel wg intiate shutdown of the Station Ventletion air supply systems. (The Fusi Handling and Auxelary Bulding VentIndon). This radiation monitor setie5es requirements for the Station Vent release point in place of RM A4 and RLt-A6.
4.4.3' RM-A5/RM-A15 Condenser Olf Gas Exhaust RM-A5 is the gaseous radiation montor for the TMI 1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). RM-A15 la the back up gaseous redledon monitor for the TMI-1 Condenser Olt Gas exhaust (see Figures 4.1 and 4.4). High alarms on RM A5 low channel or RM A16 noble gas channels wIl intiste the MAP 6 Radiolodine Processor Station. These two radiation monitors together satisfy requirements forthe Condenser' Off Gas release Poir#- . 4.44 RM-A7 Waste Gas Decav Tanit Exhaust RM-A7 le'the gaseous radiation rnonitor for the TMI-1 Weste Gas Decay' tanks (see Figures 4.1 and 4.2). This in~plart emuent radation monitor aloo has an associated . sampIng panel. High alarm on RM-A7 noble gas channel wEl Initiate shutdown of the Waste Gas Decay Tanic release in progrees. This radiation monitor setiefles requirements for batch gaseous releases to the Station Vent release point. ' 4.4.5 RM AG Reactor Buldna Purbo Exhaust RM-As is the particulate, r=realarnrie and gaseous radiadon monitor for the TMI-1 Reactor Bulding Purge system. (see FigiJres 4.1 and 4.3). This in plant emuent radiation rnonitor also has an assoolsted sempung panel with sampung lines located before the sample filters. . High alarm on RM4 noble gas low channel wIl Initiate shutdown of the Reactor Buuding Purge System. This radiation monitor satisAss requirements for the Reactor Bunding Purge
- 106.0 mm 4
5
03-11-97 11:05:21 Number
-ggy .
TMt Radidogical Controls Departmental Procedure 6610-PLN-4200.01 Trtle Rowlsion No.
~ Offsite Dose Calculation Manual (ODCM) 11 J -
. System release point.
4.4.0 RM.A14 ESF FHB Vere'=*ws System RM.A14 le the gaseous radiation monitor for the TMI-1 Emergency Safeguardo Features (ESF) Fuel Handling Bulding Exhaust system (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sampier fBters. High alamt on RM.A14 noble gas channel wm initiate' shutdown of the ESF Fuel Handing Bulding Exhaust System. This radiation monitor. satisfies 4 requirernents for the ESF Fuel Handling Bulding Exhaust System release point. .
; 4.4.7 . ALC-RMI-18 Chemical Cleanino FacElly YCCF) Varesa*wi Eid= =*
4 ALC.RMI-18 is e a Victoreen partledate, radiolodine, and gaseous radiation monitor for the
, Chemical Oeeuung buuding endtaust. T _ . 2,,1. . - -- - _ .- _ _!- z ' ': 2d ' = This monitor le located in the Chemical cienning bunding on the ground noor, and has an associated sample panel. Sampling for particulate actMey is persormed on of the monitor.
j . . l 4.4.8 WHP.RTT-1 Waste Handlino and PsW FacAltV ONHPF) Exhaust
. WHP.RIT 1 is an EbeenefflS.3 particulate radiation monitor for the TMl WHPF. The
. monitor is larmhwi in the Mechanical %* nent Room in the WHPF. Sampling for .
particulate actMty is performed off of the monitor. A high elann wig initiate shutdown of the ' { vertHation air exhaust systent ! 4.4.9 RLM.RM-1 Reecirator deanino and I.aundry Maintenance (RLM) FacElty j RLM4tM 1 is an Ebertine AMS4 particulate rad!stion monitor for the TMi RLM Faclity. The
. monitor le located in the Mechanical EquW Room in the RLM. Sampling for particulate
' adMay is performed off of the monitor. i 4 h 1 107.0 me Y
03-11-97 11:09:21-a Number Nuclear ****a"* Departmental Procedure l- Trdo 6610 PL&4200.01 Asvleion No. t Offsite Dose Calculation Manual (OOCM) 11 i
-~
TABE 4.1 (Cont'd) l TMl 1 Geoo6ue Release Point and Geseous Radiation Monitor Data . i k QASEOUS NERASE a RADIATION GASEOU8 TERMINATdN MONITOR RELliASE INTEFLOCK (utievivry LOCATION PONT (YES/NO) VALVES cw % Cce e oet - ALC AMk18 Bido.30( Beve60n 8m NONE ' wm Meen.,e wm oet w w E on wHP-RT-1 tiquipment Room ' '9yesem Tripe RLM4Anchenical . MLM Beauet
- RLM-RM-1 Equipment Room System NONE
.;. x ,
n.m eav. Tu out or
~P%...'p- mpara ngo. nci.e7 l 4-E~T ///
% ,s v /
LOAN //V/ . / 4m% / urgaise
/ Of I i beurre / - -T~ w /- // s / A /0/ /
1 w+m-i # / o / // sA// / XV / Rin=V I o/ / ' , / / sV , / /"N / aQe 63.0 e 1.1 for , 1 l i i l b 4 i 4 111.0 2n* l 4 l . 4 2
03-11-97 11:05:21 I l Number ' ggggggy WI Radidogic@'Cormds Departmental Procedure 6610-PLN-4200.01 l
- Tm. a.vmon no.
l l Offsite Dose Calculation Manual (ODCM) 11 i i 2:0- TMI ANNUAL RADIOACTIVE EFFLUENT RFf FASE REPORT j 1 ' NOTE s l A single' submittal may be made for the station. The submittal should , j combine those sections that are common to both units at the station I however, for units with separate radweste systems, the submittal shall l specify the release of radioactive material from each unit. I ! 2.1 Routine Radioactive Effluent Release Reports covering the operations of the unit during the previous 12 months of operation shall be submitted prior to May 1 for TMI-1 and TMi-2. 2.2 The following 'i4vnv4;bn shall be included in both Radioacdve Effluent Release Reports to be submitted each year. The Radioactive Efluent Release Reports shallinclude a summary of the quantitles of radioactive liquid and gaseous affluents and solid waste relamead from the unit as outlined in Reg. Guide 1.21, i Rev.1. with data surnmartzed on a quarterly basis following the format of Appendix B thereof. ' 2.3 The Radioactria Effluent Release Reports shaN Indude the following information for each type of , solid waste shipped offsite during the report period:
- a. container volume, 1
- b. total curie quantly (specify whether determined by measurement or estimate),
- c. principai radionuclides (specify whether determined by measurement or estimate), ,
- d. type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
.e. ty'pe of shipment (e.g., LSA, Type A, Type B) and
- f. solidification agent (etg., cement).
2.4 The Radioactive Effluent Release Reports shall include a summary of unplanned releases from the site to unrestrictqd areas of radioactive materials in gaseous and liquid efiluents made during the reporting period. , 2.5 The Radioactive Effluent Raid Reports shall Indude any~ changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the 0,FFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locadons for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part 31 Section 8.2. 2.6 The Radioactive Effluent Release Reports shall Indude the instrumentation not retumed to OPERABLE status within 30 days per ODCM Part i Controis 2.1.1b and 2.2.1b 3 anJ, obCK R,. m C. 4 .t zz.i.b. 179.0 , mm
03-11-97 1 1 : 0 5 : 2"1 ! Number E Nuolear ' a'd'd oo'c8 co"" d* Dewm id.! Procedure 6610-PLN-4200.01 a.v.on m. ! ) Dose Calculation Manual (ODCM) 11 i The Radioactive Effluent Release Report to be submitted shall in'dude an annual summary of houriy
; meteorological data collected over the previous year. This annual summary may be either in the ;
a form of an hour by-hour listing of wind speed, wind direction, atmosphens stabilty, and pmcipitation 1 (if measured) on magnetto tape. or in the form cf joint frequency distribution of wind speed, wind . j direction, and atmospheric stabity. f u,E SE S 0[ . 2.8 T'he Radioactive EfBuont Release Report shallinclude an assessment of the radiation dosesi d ue to 1 the radioactive liquid and gaseous ofBuonts released from the unit or station during the previous l calendar year. A * ~ l e h wf8p9 mt A W t.m.4. .f ocrv.te,iset(e(e.,x . 2.9 The Radioactive Efiluent RedReport shall indude an assessment of the radiation. doses from radioactive liquid and gaseous affluents toMEMBERS ORTHE PUBUC due to their actMties inside , i the SITE BOUNDARY during the report Allassumptions used in making these m ents ' Itm.. =aaeme actMty, mwe time and I _ . ) shcI be included in these reports.}The j ' meteorological conditions concurrent with the tune of release of redloective metertels in gaseous efRuents (as determined by sampling frequency and measurement) shad be used for determining the ) gaseous pathney doses. The aseeeement of radiation doses shall be performed in accordance with J
'"a "I .
2.10 The Radioactive Efiluent Reisese Report shall eleolnclude an assessment of radiadon doses to the likely moet awpaaad real indMdugl_from reactor reisenes and other nearby uranium fuel cycle sources Induding doses from primary el5uent pathways and direct radiation for the previous 12 consecutMe months to show conformance with 40 CFR 100
- Environmental Radia*vi Protection Standards for Nuclear Power Operation." Accarmahla methods for coloulating the dose contributions from liquid and gaseous ofRuonts are given in Regulatory Guide 1.109, Rev.1.
l e een 4 4 e
\ '
180_D me. 4
l 03-11-97' 11:05:21
~
e m m a g. Og l' YOU r,r I l ' TMI1 PROCEDURE EVIEW AND APPROVAL j . WORD PRQCESSING/ PROOFREAD / SIGN OFF FORM ) PROCEDURE NO:.lo6/0 -P LN - VJdo. 0) To wp: // , p g - v PCR NO.: ['AM6-00// REMSION NO.: PROOFREAD /8IGN OFF: Relum to: /2/'d/M&/M
/ I j OmwCoonner Das ro: Auf,}l, .f;M. Y l
- r -
Corra:none j 1st Proof 2nd croof Please proofreed. Note correcdone in.BER -
@ YES O YES -
.11i15 on asected pages and CHECK THE YES pg 4o.o Typ..fr. p.. remim talock. If OK, sign and date procedure cover a n +s.o *s"st j peGe and return to Once Coonsnetor. ,F g ev.o .*meess or tw Posuc.
j O*6er Approver (s) ! WDRD PROCESSING / PROCEDURE CONTROL l .gc,.q.g coy / 4 W0-fuv- M M !l l:o 3-1FG 7
- Afqf-)
#7/7 h
l IM'9 S~ [(Al l} ~},2l lggge m w NY s i WORD PROCESSSIO: . . Date Received: //!8f/9.I Date Required: / I! Doc. iD J/'// C- Disk No.' db S Doc. D Disk No. . wiDWhb Disk No. ' Doo. D Disk No. Data Pages Date Mar;elved Operator WP Proof Printed Complete
- 1. />f '1 & )% ////$
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- m. ' ' ,
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.3 s-6>- '
_ /() s MO
I w i Table 3.1-1, 6610-PLN-4200.01 [ Revision 12 i e
~
.4
. Radioactive Liquid Effluent Montoring instrumentation Surveillance Requirements SOURCE CHANNEL CHANNEL o INSTRUMENT CHANNEL g CHECK CHECK CAUBRATION TEST ..
u F2
- 1. Radioactivty Monitors Providing Alarm and Automatic isolation L-(, '
- a. Unit 1 Liquid Radwaste Effluents Line (RM-44) D P R(2) O(1)
L-12,
- b. (WTS/lWFS Discharge LJne (R.M-+:te) -D P g R(2) O(1)
- 2. Row Rate Monitors
- a. Unt 1 Liquid Radwaste Effluent Line (FT-84) D(3) N/A R~ Q
- b. Station Effuent Discharge (FT-146) D(3) N/A R O e
e 40.0 nrw
o Table 3.1-2 (Cort'd) 6610-PLN-4200.01 Revision 12 hi Radioactive Gaseous Process and EfHuent Monitoring Instrumentation Surveillance Requirements , $ CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CAllBRATION TEST APPLICABILITY C l i>'
- 7. Chemical Oeaning Bulding Vent 8ation System e
- a. Noble Gas Activdy Monitor (ALC RM-l-18) D M E(3) O(2) ###
- b. lodine Sampler (ALC RM-1-18) W N/A N/A N/A ###
- c. Particulate Sampler (ALC.RM-i-18) W N/A N/A N/A ###
- 8. Waste Handling and Packaging FacIlty Ventiation System W
- a. Particulate Sampier (WHP-RIT-1) . D Jin SA W ###
- 9. , Respirator and bundry Maintenance VentBation System
- a. Partculate Sampler (RLM-RM-1). - D W SA W ###
m 4 45.0 mw
03-11-97 11:05:21 u,3, Nuclear " "ad'd a'o*' ooat'd* Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 12 , 2.7 The Radioactive Effluent Release Report to be submitted shall include an annual summary of houriy meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmosphere stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, wind direction and atmospheric stability. 2.8 'The Radioactke Effluent Release Report shall include an assessment of the radiation doses to y members of the public)lue to the radioactive. liquid and gaseous effluents released from the unit or h5n station ounng the previous calendar year. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and i Oo M measurement) shaR be used for determining the gaseous pathway doses. The assessment of CM radiation doses shall be performed in accordance with this ODCM. 2.9 The Radioactive Effluent Release Report shall include'an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBUC due to their activities inside l the SITE BOUNDARY during the report period, to verify compilance with the limits of f 10CFR20.1301(a)(1). All assumptions used in makir,g these assessments (i.e., specific actMty, exposure time and location) shall be included in these reports. 2.10 The Radioactive Effluent Release Report shaN also include an assessment of radiation doses to the likely most exposed real Individual from reactor releases and other nearby uranium fuel cycle sources including doses from primary effluent pathways and direct radiation for the previous 12 consecutive months to show conformance with 40 CFR 190 *ErMronmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contributions from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1. j l t l l l l 187.0 me
03-11-97 I 11 : 05 : hh03088174 i Nebw l Nuclear M Raddogentrds Departmental Procedure 6610-PLN-4200.01 l The hoo,No. i Offsite Dose Calculatiori Manual (ODCM) 11 l a 4puentsty/ scope CalctAate offstte doses due to radioactive AsaponWbio Office Eff covo case . effluents for demonstrating compliance with Site Technical Specifications 10 CFR 20 & 10 CFR 50 - Appendix i 6610 03/24/95 This document is within QA plan scope X Yes No l - Safety Reviews Required X ; Yes No l List of Effecove Pages i f3gg . Revision fagg Revision ,P_qgg . Revision Eggg Revision 1.0 11 21.0 11 41.0 11 61.0 11 2.0 11 22.0 11 42.0 11 62.0 11-4 3.0 11 23.0 11 43.0 11 63.0 11 i 4.0 11 24.0 11 44.0 11 64.0 11 5.0 11 ' 25.0 11 45.0 11 65.0 11 6.0 11 28.0 11 . 46.0 11 66.0 11 7.0 11 27.0 11 47.0- 11 67.0 11 s.O 11 2s.0 11 4s.0 11 68.0 11 9.0 11 29.0 11 49.0 '11 60.0 11 10.0 '11 30.0 11 50.0 11 70.0 ' 11
- 11.0 11 31.0 11 51.0 11 71.0 11
- 12.0 11 32.0 11 52.0 11 - ~72.0 11 3 53.0: 73.0 13.0 '11 33.0 .11~~ 11 11 i 14.0 11 34.0 11 54.0 11 74.0 11 i 15.0 11 35.0 11 55.0- 11 75.0 11 l 1s.0 ' 11 36.0 11 56.0 11 7s.0 11 17.0 11 '37 0
. 11 57.0 11 77.0 11 18.0 11 38.0 11 5s.0 11 78.0 11 i 19.0 11 39.0 11 59.0 11 79.0 11 20.0 11 40.0 11 60.0 11 80.0 11 s
l
- MO V5/.PiulfL/ lslukc
~ . - ~ ~ .
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-no . - -0 l c;pr4 l -,e
~ ~ .-
l v g y A .,, , GP U" Mge COMBS um 1.0 gg,o COP
03-11-97 11':05:21 4 l Nurnber I , gggp , TMI Radiologicil Controls Departmental Procedure 6610-PLN-4200.01 i rie. . am.on te. j Offsite Dose Calculation Manual (ODCM) 11 4 i I bat of Efective Pages (Cont'd) - fagg Redston fag's Revision Eggg Reveon Eggg Revisign 81.0 11 121.0 11 181.0 11 . 82.0 11 122.0 11 102.0 11 ! 83.0 11 123.0 11 103.0 11 84.0 11 124.0 11 164.0 11 l 85.0 11 125.0 11 , 165.0 11 j 86.0 11 126.0 11 106.0 11
- 87.0 11 127.0 11 187.0 11 l 88.0 11 128.0 11 168.0 11 89.0 . 11 120.0 11 100.0 11 90.0 11 130.0 11 170.0 11 91.0 11 131.0 11 171.0 11 92.0 . " 11 132.0 11 172.0 11 93.0 11 133.0 11 173.0 11 94.0 ' 11 134.0 11 174.0 11
' 96.0 11 135.0 11. 175.0 11 2
96.0 11 136.0 11 176.0 11 j 97.0 11' 137.0 11 ' 177.0 11 , j 98.0 11 138,0 11 178.0 11 l 1 99.0 11 139.0 11 179.0 11 { 100.0 , 11 140.0 11 180.0 11 l i 101.0 11 141.0 11 181.0 11 j 102.0 11 142.0 11 E11 11 . i 103.0 11 143.0 11 E2-1 11' ] 104.0 11' 144.0 11 E3-1 11 105.0 11 145.0 11 E41 3 106.0 11 146.0 11 E4-2 11 107.0 11 147.0 11 E5-1 11 108.0 11 148.0 11 E6-1 11 100.0 11 149.0 11 E71 3 110.0 11 150.0 11 E7 2 3 111.0 11 151.0 11 . ' E7 3 3-112.0 11 152.0 ' 11 E7 4 - 3 1110 11 1510 11 114.0 11 154.0 11 115.0 11 155.0 11 116.0 11 158.0 11 117.0 11 157.0 11 . 118.0 11 158.0 11 1190 - 11 159.0 11 .. - 120.0 11 160.0 11 GPUN DOCUuENT COMM CONTR00.E0 2.0 mw
03-11-97 11:08:41 TABLE 3.2 2 (Cont'd) Redieective Geseese Weste sempting med Analysis Program Table lletaties d
- e. The LLD is the smallest concentration of radioactive metwialin a sample that wil be detected with 95% probabiity with 5%
probability of falsely concluding that a blank observation represents a "real* signal. For a particular rnessurement system (which may include radiochemical separation): g, 4.66 S3 E
- V 2.22 Y exp (-Aac)
Whwe LLD is the lower limit of detection as defined above (as picocwie pw unit mass or volume). S6 is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per min 6te). l E is the counting efficiency (as counts pu transformation), V is the semple size Ga units of mass or volumel, 2.22 is the number of transformations pu minute pw picecurie, Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particulw radionuclide, and ' l At is the elapsed time between midpoint of sangle collection and time of counting (for plant effluents, not environmental samples), The value of S, used la the calculation of the LLD for a detectica system shall be based en the actual observed variance of l the background counting rate or of the counting rate of the blank samples (as appropriate) rathw than en an unverified theoreticaly predicted variance. la calculating the LLD for a radienuclide determined by gamma <ay spectrometry, the backyound shall include the typical contributions of othw radionuclides normeNy present in the sangles. Typical values of E, V, Y, anJ At shan be used in the calculation. The background count rate is calculated from the background counts that are determined to be with one FWHM (Full-Width-st Helf-Manmem) enwgy band about the anwgy of the gamma ray peak used for the quantitative analysis for that radionuclide,
- b. The principal samma emitters for which the LLD specification applies exclusively are the felowing radionuclides: Mn44, Fe-59, Co-58, Co-60, Zn 65, Mo-99, Cs 134, Cs 137, Co.141 and Ce 144 for particulate emissions. This list does not meen that only these nucEdes are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shal also be identified and reported. Nuclides which are below the LLD for the analyses shal be reported as *less than* the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The *iess_ than* values shal not be used in the required dose calculations.
& 11118
~ __ -_ . . __ . . . _ _ _ . . _ . _
03-11-97 11:08:41 3.2.3 Total Radioactive Effluent: 3.2.3.1 Dose Calculation 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shau be determined in accordance with Surveillances 3.2.1.2.1, 3.2.2.2.1 and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks. and in accordance with the methodology contained in the ODCM. l l l l 4 e 4 2171e seemem e em e
4
- 03-11-97 11
- 08:41
] SECTION 4.0 Desige Fosterse 4.0 DESIGN FEATURES { 4.1 SE
- EXCLUSION AREA 4.1.1 The exclusion area is shown in Figure 5-1, TMl1 Tech. Specs.
1 LOW POPULATION ZONE l 4.1.2 The low population zone is shown in Figure 5 2, TMI.1 Tech. Specs. SITE BOUNDARY FOR OASFOUS EFFLUENTS ! 4.1.3 The site boundary for gaseous effluents shan be es defined in Section 2.1.2.2 of the TMII FSAR and as shown in } Figure 2.13, TMF1 FSAR. I a l EE.300NDARY FOR tl0UID EFRUENTS { j 4.1.4 The ate bouedery for liquid effluents shau be es shown in Figure 53, TMl1 Tech. Specs. i i l 4 i n 1 ) - i 3
03-11-97 11:08:41 5.0 PART 11 REFEREllCES 1 4 5.1 NUREG4683, " final Programmatic Environanental lapact Statement related to decontarnination and disposal of radioactive wastes ruutting frcm March 28,1979, accident Three Mile Island Nuclear Station, Unit 2/ March 1981, and its supplements. 5.2 TMI2 POMS Technical Specifications, attached to Facility License No. DPR 73 5.3 Title 10, Code of Federal Regulations, " Energy
- 5.4
- Statement of Policy Relative to the NRC Programmatic Environmental Impact Statement on the Cleanup of Three Mile Isla'nd Unit 27 dated April 27,1981 5.5 Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routies Releans of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1,* Revision 1, October 1977 1
5.8 00EITIC27601, Atmospheric Science and Power Reduction 4 5.7 TMI1 Technical Specifications. attached to Facility Operating License No. DPR40 5.8 PDMS - SAR 4 i A i i e t b , 4 4 e-n
1 03-11-97 11:08:41 . Number ggy
- TMt Radiological Controls Departmental Procedure 6610-PLN-4200.01
' TMe. RevHion No. Offstte Dose Calculation Manual (ODCM) 11 l - 1.3 Control of 1.lauld Releases I TMI liquid effluent releases are controlled to less then ten times the 10CFR20 concertrations by limiting the percenta0e of this limit allowable from the twoTMi liquid release points. RM-LS, and efRuont sampling. limits batch releases to less than or equel to 10% for all radionuclides,'and l RM-l.12, and effluent sempling, limits releases from TMI-1 and TM1-2 to less than or equal to 50% for Co-137. ' These radiation monitor set points also inc8ude built in meter error factors to further ensure that TMt , j liquid effluent releases are less than ten' times the 10CFR20 concentrations t gnm The radioactMty content of each batch of radioactue' liquid weste is ed A ^; . J _ _:: by sampling and analysis in accordance with ODCM Part 1 Table 3.2- The results of ;;r:::': :: pnalyses are used with the calMmal methods in Section 1.1, to assure that the concentration at
. the point of raisese is maintained .within the OOCM Part I Control 2.2.1.1,,ane9 oce.M P.,4 JI Codd z.zM
,, occa P.,4 It T.W s.t.-l
. Post-release analysis of f,OJ-;-: ? 1 frorn batch releases are performed in accordance with
, ODCM Part i Table 3.21'. The results of the previous post <elease analysis shaI be used wth the calculational rnethods in the ODCM to assure that the concentrations at the of release were maintained within the ODCM Part i Control 2.2.1.1pJ coch R,4 E C, i 2.t .
P.,45 T.W. 3.H The radioactMty concentration of Ik;alds die.6gf.J fiorn cordinuous release kare determined 1 by co8ection and analysis of samples in accordance with.OOCM Part i Table 3.21t.The results of l the analysis are used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the ODCM Part 1 Control 2.2.1.1 4,J CDC M Pat
- E -
3 (,,Ar' \ 1.z.i. I . 1 l i T 1 e l 85.0 == 6
03-11-97 11:08:41 - 1 Number gggy TMI Radiologic &l Controls Departmental Procedure 6610 PLN-4200.01 - me. m no. i Offatte Dose Calculation Manual (ODCM) 11 2.2 TMI/t.iatdd Radwaste System Dose Calce Once/ Month i i ODCM Part i Control 2.2.1.3 and TML-2 PDMS Tech Spec tiection 6.7.4.a.6 requires that appropriate portions d the liquid radweste treatment system shall be used to reduce the radioactive materials in , liquid wastes prior to their discharge when the morithly projected doses due to the liquid effluent releases from each unit to unrestricted areas wotdd exceed 0.06 mrom to the total body or 0.2 rnrem to any organ in any calender month. The following calculational method is provided for performing this dose projedion. , 1 At least once per month, the total doise from as liquid'rulamana for the quarter.to< late wil be divided t by the number d days into the quarter and mtitlplied by 31. Also, this does projection shall include , the estimated does due to any ai% unusual releases dudng the period for which the i,i%. le rnede. If this projeded does exceeds 0.06 mrom total body or 0.2 mrom any organ. appropriate portions d the Uquid Radweste Treatment System, as defined in Section 3.1, shall be . used to reduce radioactMty levels prior to release. At the discretion at Radiological Engineering, time periods other than the current quarter.to.date may be used to project doses I the does per day in the, current quarter.to< fate is not bellwed to be r+ : _ ;.;;e d the does per day projected for the next month. 5 4 1
. l P .
e t t , e
, e% eq .
O me 92.0 s 4 5
=_m___ _ _ _ _ _ __
~
03-11-97'11:08:41 . Number UE TMI RadiologicalDontrols i r Departmental Procedure 6610-PLN-4200.01 m..
, m.
i Offsite Dose Calculation Manual (ODCM) 11 j 4.4 TMI 1 Gaseous Effluent Release Points and ha*anta Rarna*=1 Monitor Data !
. TMI-1 has eleven (11) required effluent gaseous radiation monitors. These are RM44, RM A5, j
RM-AIS, RM-AS, RM A7, RMA8, RM-A9, RM A14, ALC-RMi-18. WHP-RIT.1, and RLM-RM-te These j gaseous release points, radiation monitors, and sample points are shown in Table 4.1. Ow..L.c.a l , ' ; :-L '=T W ;d :.: i .=L.,.u. ; : 2 .T - ,..; Ca. " - t. 4 = '= j "
- 5 ;ir; na,b. a. --;+~ ' ."c / ' d.the-99GM-
- j
. . \
4.4.1 BMA4/RM-A8 Fuel Handlina and Auxiierv Buldina Exhaust ( ,
. RM44 la the particulate, radiolodine and gaseous 'adiation r monpor for the TMI-1 Fuel Handling .Buiding Ventiation (see Figures 4.1 and 4.2). RMA6 is the particulate. '
i radiciodine, and gaseous radiation monitor for the TMI 1 Auxiliary Building Ventilation (see Figures 4.1 and 4.2). High eintme on RM A4 or RM48 noble gas channels wil initiate l
' shutdown of the related bulding ventsation air supply system. These two radiation mo'nitors
- concurrently w91 satisfy requirements for the Station Vent release point in place of RM-A8.
l 4 4.4.2 'RM-A8 Station VentBation Exhaust f RM-A8 is the particulate, radiolodine and gapoous radiatiori monitor for the TMI-1 Station 4 Ventastion (see Figune 4.1_and 4.2). This in plant etRuont radiation monitor also has an . i aseodated sampling panel with sampling lines located before the sample fEters. High alarm on RM-A8 noble gas low channel wil initiate shutdown of the Stacon Ventiation air supply systems. TIhe Fuel Harding and AuxSlary Bulding Ventiation). This radiation monitor J
- satis 6es requirements for the Statiori Vent release poirit in place of RM-A4 and RMA6. l 45.3 'RM-A5/RM-A15 Condenser Off Gas Ezf=M l RM45 is the gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). RM-A15 la the back up gaseous tadiation monitor for the TMI-1 Condeneer Off Gas exhaust (see Figures 4.1 and 4.4). High alarms on RM A5 low channel -
- or RM-A15 noble gas channels wil initiate the MAP-6 Radiciodine Processor Station. These i
4 two radiation monitors together satisfy requirements for the C.ondenser Off Gas release 4 . l 4.4.4 RM-A7 Wants Gas Decav Tank Exharmt 1 l , RM A7 is the gaseous radiation rnonitor for the TMid Waste Gas Decay' tanks (sm l
, Figures 4.1 and 4.2). This In' plant emuent radiation monitor also has an associated l i sampling panel. High cJarm on RM-A7 noble gas channel will Intiate shutdown of the Waste *"
j
; Gas Decay Tank release in progress. This radiation monitor satisfies requireme~rns for batch 4
gaseous releases to the Station Vent release point. 1 i 4.45 RM-A9 Reactor Buldino Purae Exhaust j RM Ag is the particulate, radiolodine and gaseous radiation monitor for the TMI-1 ReacV.
- Bulding Purge system (see Figures 4.1 and 4.3). This r plant ofnuent radiation monitor .t.so has an associated sempling panel with samgding lines ici ararl before the sample filters.
l High alarm on RM-AG noble gas low channel wil Initiate shutdown of the Reactor Building j Purge System. This radiation monitor se'.lulles requirements for the Reactor Building Purge 100.0 mm i I
}
I I I
03-11-97 11:08:41 i
'l Numter '
i J e ggy TMl Radiological Cortrols Departmental Procedure 6610-PLN 4200.01 True Routslon No.
; ' Offsite Dose Calculation Manual (ODCM) 11 ! ) System release poirt l
4.4.6 RM414 ESF FHB Ver*a% System - RM.A14 is the gaseous radiation monitor for the TMI.1 Emergency Safeguards Features l (ESF) Fuel Handung Bulding Exhaust system (see Figures 4.1 and 4.2). This in plant j} effluent rMistion monitor also has an associated sampling panel with sampling !!nes located l before tw samoler fDtees. High alarm on RM-A14 noble gas channel wHl initiate shutdown of
. the ESF Fuel i ._diing BuBding Exhaust System. This radiation monitor, satisfies requirements for the ESF Fuel Handling Bulding Exhaust System release point. .
.]
! 4.4.7 . ALCAMI-18 Chemical demnina Facalty '(CCF) V r n* EW=*
E l ALC-RMI-18 is an Victoreen particulate, radiciodine, and gaseous radiation monitor for the , l l
' Chemical Osaning buiding exhaust.-Preewie r , G. .--- 14 2 -_i t r ' =. This i
j monitor is located in the Chemical Cleaning buttSng on the ground floor, and has an ! j associated sample panet Sampling for particulate actMty is performed off of the monitor.
! 4.4.8 WHP-RIT 1 Waste Handlino ard Pec'si,e FacaltV (WHPF) EW=* . l
- . WHP-RIT-1 is an EberlinefflS-3 partietdato radiation monitor for the TMI WHPF. The monitor is located in the Mechaniced Equipment Room in the WHPF. Sampling for .
i
- , particulate actMty is performed off of the monitor. A high alarm wiu initiate shutdown of the
- 1 j ventHatton air exhaust system.- 1 4.4.g Rt.M-RM-1 Resolrator Cleanino and I.aundry Maintenance (Rt.M) FacRv i
i RLM-MM-1 is an Eberline AMS-3 particulate redledion monitor for the TMI RLM FacEtty. The
. monitor is laretad in the Mechenkal Equ% Room in the Rt.M. Sampling for particulate . actMty is performed off of the monitor.
4 J a j - 4 4 4 i i 1 -
.A
) o 107.0 mm 4
03-11-97 11:08:41 l Number l Nuclear "Departmenta!
"*d Procedure t=**
6610-PLN-4200.01 rron Reviwan No. Offsite Dose Calculation Manual (ODCM) 11 l 1 TABLE 4.1 (Cont'd) 4 j TMI t Osse 6us Release Point and Geosous Radiatior. Monitor Data s b
'MSEOUS RELEASE IqADIATION GASEOUS - TERMINATIDN i MONITOR RELEASE INTEKOCK '
(DETECTOf0 LOCATION POINT DES /NO) VALVES Chemical Deaning CC8 Exhaust ALC RMi18 Mde.304'Bevaton 8m NONE l i YE8 . i WHPF Mechanical WHPF Exhaust WHP8 Vendeten ' i WHP4WT 1 Equipment Room '9ystem Tripe EM44echenloal . RLM Exhaust , RLM-RM1 Equipment Room Syneem NONE l
'*" L4 3 l TM Out of PI Radicehvo' Mo tntation 6--'-
knee L 6n~y b ~ wF uencleo[ l i bat ~~.Nr b/)UE b /M// dMdd I Atee+ ,eV / /// / V7. / Of . I \ betert . Wia R / - -/ w / // E / A /o/ / we=T-i # / o / // sA / / / N / R%*auV / / o/ / / sr // /"N / age 63.0 ble 1.1 for expl . l l 4 111.0 2nh O 6
03-11-9'7 11:08:41 Number i Radidogic@ hs (W (UClear Departmental Prowfure 6610-PLN-4200.01 RevieJon No. 4 Offsite Dose Calculation Manual (ODCM) 11 2t TMI ANNUAL RADIOACTIVE EFFLUENT RF1 FaSE R5 PORT NOTE A single' submittal may be made for the station. The submittal should combine those sections that are common to both units at the station j however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit.
)
2.1 Routine Radioactive Effluent Release Reports covering the operations of the unit during the previous 12 months of operation shall be submitted prior to May 1 for TMI-1 and TMi-2. 2.2 The following information shall be induded in both Radioactive Effluent Release Reports to be . submitted each year: . The Radioactive EfRuont Release Reports shall indude a summary of the quantitles of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Reg. Guide 1.21, Rev.1, with data summarized on a quarterly basis fo80 wing the format of Appendix B thereof. 2.3 The Radioactive Effluent Release Reports shan include the following information for each type of , solid waste shipped offsite during the report period i
- a. container volume, 1
- b. total curie quintty (specify whether determined by measurement or estimate),
f
- c. principai radionudidos (specify whether determined by, measurement or estimate), ,
1
- d. type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
- e. type of shipment (e.g., LSA, Type A, Type B) and
- f. solidification agent (e.g., cement).
2.4 The Radioactive Effluert Release Reports shad include a summary of unplanned releases from the site to unrestrictqd arene of radioactive materials in gaseous and lir.;uid effluents made during the reporting period. ,
~
i 2.5 The Radioactive Effluent Release Reports shah indude ar1y' changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the 0,FFSITE DOSE CALCULATION MANUAL (ODCM), as won as a listing of new locations for dose calculations and/or a enwonmental monitoring identified by the land use census pursuant to Part I!! Section 8.2. i 2.6 The Radioactive Effluert Release Reports shalf include the instrumentation not retumed to OPERABLE status within 30 days per ODCM Part i Controls 2.1.1b and 2.2.1b)ad oDCM 4 b.f[T' Cm4c.L 2.2.6.b. 179.0 , m= o
. _ . ~ . .-. -.. - . . .
\
\
03-11-97 l'1:08:41 Number l gggy TMI Radlologicid Controls Departmental Procedure 6610-PLN-4200.01 n.voon re. i j i Dose Calculation Manual (ODCM) 11 3 i The Radioeceve Effluent Release Report to be submitted shall include an annual summary of hourly i
; meteorological data collected over the pnmous year. This annual summary may be either in the i form of an hour-by-hour listing of wind speed, wind direction, atmosphere stability. ard precipitation 2 (if measured) on magnetic tape, or in the for:n of joint frequency distribution of wind speed, wind direchon, and stirWedc, stability. 4 um6C S O 2.8 The Radioactive Effluent Release Report shall include an assessment of the radiation dosesbue to the radioactive liquid and gaseous effluents released from the unit or station during the previous )
' calendar year. A e b w.r.C g e,9tEAN. mu ne 4. .f secrezo,isoi4 2.9 The Radioactive EfRuont ReleNReport shall include an assesement of the radiation. doses from radioactive liquid and gaseous elliuents to MEMBERS ORTHE PUBUC due to their actMties inside ; the SITE BOUNDARY during the report pe #1 assumptions used in rnaldng these ments ' l fl.a..=aa m actMty, ==pe time and l_ ) shall be included in these reports. e ! [ meteorological enh concurrent with the tune of release of radioactive meterials in gaseous ( effluents (as determined by sampling frequency and measuremert) shall be used for determining the j gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with,i this ODCM 2.10 The Radioecove Efiluent Release hloport shaR alao' include an assessment of radletion doses to the likely most awpammi real indMdua_i_from reactor releases and other nearby uranium fuel cycle sources including doses from primary ofRuont psthways and direct radiation for the previous 12 cowocutive months to show conformance with 40 CFR 190
- Environmental Padl=*vi Protection Standards for Nucieer Power Operation? Accar mahia methods for calculating the dose contributions ficm liquid and gaseous affluents are given in Regulator'y Guide 1.109, Rev.1.
t 1
. T l
l 180.0 mm I
l 4 ' j 03-11-97 11:08:41 Q[ fb l k,e}V i i TMM PROCEDURE EVIEW AND APPROVAL ' l . WORD PROCESSING / PROOFREAD / SIGN OFF FORM PROCEDURE NO:./o6/o - P LN - VJdo. 0) TO WP: //-#8"f5~ l PCR NO.: /-AC-fs-00p/ REVISION NO.: ! i 1 f i PROOFREAD / SIGN OFF: Relurn to: /2/'4/M&/// Omos' Coordinator
/
Date W l TO: Akibv>S$6 j r - Originator Corrections 1st Proof 2nd proof j j Please proofreed. Note corrections in BER -
]s YES. O YES -
l jtg on ellected pegue end CHECK THE YES PS40.o Typ..re,m p . remi.n ! block. If OK, sign and date procedure cover - g +s.o esst4 - ,, r ) { peDe end return to Osco Coonsnetor. g ev.o . %scas or ,w., eusuc. OMar Approver (s) ) ' l WORD PROCESS #tG/ PROCEDURE CONTROL i t . SpoolelInstrueSono: fK3 A c co'f/ Wo-Mk~ M0 'I i 1 I 0 T*ffe#
- y AS4f-l 1 41/1 1 l'#'M /k /.S >2/ lemus O Dess{f m -
1 l enesa. i WORD PROCESSSIO: . Date Received: // kI Date Required: / I[ i Doc. :D J/7/ L Disk No.M Doc.D Disk No. . Doc. iDM b Disk No. ' Doc.D Disk No. 1 i Rooseved Operator WP Proof Printed Complete 1. 2.
/N 'l Jih2 .
exulss.) dr%f sy) ~ 3 9//$
/b-du-f ys. '; _
d 4-gggy
0.
' H 6610-PW-4200.01 Table 3.1-1, Revision 12 i w
.a Radioactive Liquid Effluent Monitoring Instrumetaation Survealance Requirements e
H INSTRUMENT CHANNEL E RCE CHANNEL CHANNEL o CHECK CHECK CAUBRATION TEST .I a H
- 1. Radioactivity Monitors Providing Alarm and fehornatic isolation L-(,
- a. Unt 1 Liquid Radwaste Effluents Line (RM-4,6) D P R(2) O(1)
L-17
- b. IWTS/lWFS Discharge une (RM-+:te) D P g R(2) O(1)
- 2. Flow Rate Monitors
- a. Unt 1 Liquid Radwaste Emuent Line (FT-84) D(3) N/A R Q
- b. Station EfHuont Discharge (F-T-146) D(3) N/A R Q i
40.0 in
O , Tcbie 3.1-2 (Cont'd) 6610-PLN-4200.01 '[l Revision 12 i Radioactive Gaseous Process and Effluent Monitoring instrumentation Surveilance Requirements ,$ e CHANNEL SOURCE CHANNEL CHANNEL . INSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABILITY ll
- 7. Chemical Oeaning Bu8 ding VentBation System
- a. Noble Gas Activity Monitor (ALC RM-l-18) D M E(3) O(2) ###
- b. lodine Sampler (ALC RM4-18) W N/A N/A N/A ###
- c. Particulate Sampler (ALC RM418) W N/A N/A N/A ###
- 8. Waste Handling and Packagog FacRy Ventiation System W
- a. Particulate Sampler (WHP-RIT"1) , D Jin SA W ###
- 9. . Respirator and Laundry Maintenance Ventiation System
- a. Particulate Sampler (RLM-RM-1) D W SA W ###
l 45.0 mw
1 1 1 03-11-97 11:08:41 go,3,, Nuclear ' "*d'o'oa'ca' coatro'* Departmental Procedure 6610-PLN-4200.01 Title Rowsaon No. Offsite Dose Calculation Manual (ODCM) 12 2.7 The Radioactive Effluent Release Report to be submitted shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmosphere stability, and precipitation , (if measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability. 2.8 The Radioactive Effluent Release Report shall include an assessment of the radiation doses to y members of the publicJiua to the radioactive.IIquid and gaseous effluents released from the unit or station ouring the previous calendar year. The meteorological conditions concurrent with the time of 30 release of radioactive materials in gaseous effluents (as detem11ned by sampling frequency and
- O measurement) shall be used for determining the gaseous pathway doses. The assessment of CM radiation doses shall be pgfunnsd in accordance with this ODCM. ]
l 4 2.9 The Radioactive Effluent Release Report shall include an assessment of the radiation rioses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBUC due to their activities inside the SITE BOUNDARY during the report period, to verify compilance with the limits of 10CFR20.1301(a)(1). All assumptions used in making these assessments (i.e., specifle actMty, exposure time and location) shall be included in these reports. 2.10 The Radioactive Effluent Release Report shrJ also include an assessment of radiaton doses to the ; likely most exposed real indMdual from reactor releases and other nearby uraniam fuel cycle ' sources including doses from primary effluent pathways and direct radiation for the previous 12
)
consecutive months to show conformance with 40 CFR 100
- Environmental Radiation Protection Standards for Nuclear Power Operation.' Acceptable methods for calculating the dose contributions ;
from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1. ! I I
! l l
187.0 mm
03-11-97 ' 11:08:hh03088174
. Nwnbw Nuclear = a=ddoad*'*o'* .
Departmental Procedure 6610-PLN-4200.01 nse ReMon,No. ~ Offsite Dose Calculatior) Manual (ODCM) 11 :
. Applicaultty/ scope Calculate offsite doses due to radioactive A*sponWble Ortsoo Effectw Date effluents for demonstrating compliance with Ske Technical i 1pecifications 10 CFR 20 & 10 CFR 60 - Appendix I 6610 03/24/95 This document is wthin QA plan scope X Yes No Safety Reviews Required X Yes No List of Effective Pages
~
P,ggg Revision fa_gt Revision Eajgg. Resisjon Pggg Revision { 1.0 11 21.0 11 41.0 11 61.0 11 2.0 11 22.0 11 42.0 11 62.0 11-l 3.0 11 23.0 11 43.0 11 63.0 11 4.0 - 11 24.0 11 44.0 11 64.0 11 5.0 11 ' 25.0 11 45.0 11 65.0 11 6.0 11 28.0 11 46.0 ' 11 86.0 1' 7.0 11 27.0 11 47.0 11 67.0 11 8.0 11 28.0 11 48.0 11 68.0 11 9.0 11 29.0 11 40.0 ^11 68.0 1 '. 10.0 '11 30.0 11 50.0 11 70.0 '
#.1 11.0 11 31.0 11 51.0 . 11 71.0 11 12.0 11 32.0 11 52.0 11 - '72.0 11 -
13.0 '11 33.0 if~ 53.0 : 11 73.0 11 14.0 11 34.0 11 54.0 11 74.0 11 15.0 11 35.0 11 55.0 11 75.0 11 18.0 ' 11 36.0 11 54.0 11 76.0 11 17.0 11 '37.0 11 57.0 11 77.0 11 18.0 11 34.0 11 58.0 11 78.0 11 19.0 11 39.0 11 59.0 11 79.0 11 20.0 11 40.0 11 60.0 , 11 80 0 11 k
-0.,. ~m0.. -
l e g a . _ j ,f e
- 0.,. - - 0 l 9m I ,ae
~ ~i n .-
l y y M A ,,_ , , 1.0 [M GP U" \ ** cMD
~
... .T .....
, i 97 11:08:41 j 8 Nurnber a gggy . TMI Radiologicil Controls Departmental Procedure 6610-PLN 4200.01 Ts. . n.vi.on te. , 2 i i Offsite Dose Calculation Manual (ODCM) 11 [ . bet of Effective Pages (Cont'd) - j Egig Redslog fag't Revision fagt Revision fagg Revision I 81.0 11 121.0 11 161.0 11 ! 82.0 11 122.0 11 182.0 11 I 83.0 11 123.0 11 183.0 11 4 54.0 11 124.0 11, 1R0 11 RS.0 11 126.0 11 . 186.0 11 96.0 11 126.0 11 1M.0 11 87.0 11 127.0 - 11 187.0 11 I 88.0 11 128.0 11 168.0 11 i 89.0 11 120.0 '11 180.0 11 90.0 11 130.0 11 170.0 11
- 91.0 11 131.0 11 171.0 11
} 92.0. 11 132.0 11 172.0 11 93.0 11 133.0 11 173.0 11
- 94.0 ' 11 134.0 11 174.0 11
' 96.0 11 135.0 11 175.0 11
) 96.0 11 136.0 11 176.0 11
- 97.0 11 137.0 11_.' 177.0 11 ,
! 98.0 11 138.0 11 178.0 11 l l 90,0 11 130.0 11 179.0 11 ] 100.0 11 140.0 11 180.0 11 l 101.0 ' 11 .141.0 11 181.0 11 , 102.0 11 142.0 11 E1 1 11 103.0 11 143.0 11 E2-1 11' j 104.0 11- 144.0 11 E3-1 11 i j 106.0 11 145.0 11 E4-1 3 l .i 108.0 11 146.0 11 E4 2 11 l 1 07.0 11 147.0 11 E51 11 ! 108.0 11 148.0
- 11 E6-1 11 100.0 11 148.0 11 E71 3 1 110.0 11 150.0 11 E7 2 3
} 111.0 11 151.0 11 ' E7 3 .3 112.0 11 152.0 ' 11 E7 3 113.0 11 153.0 11 114.0 11 154.0 11 115.0 11 156.0 11 116.0 11 156.0 11 117.0 11 157.0 11 1 118.0 11 158.0 11 ' 119.0 - 11 159.0 11 -. 120.0 11 160.0 11 GPUN l DOCUMENT CONM j CONTROLLED . 2.0 m i 1 l
1 I i I l Enckwure 3 l l 1996 Annual Radimetive EfIluents Releases Reprt for TMI 6710-97-2161 l l Temporary Change Notice (TCN) 1 %0002 to the ODCM,6610-PLN-4200.01 l I l ( 1 l
_. __ __ ___ _ . _ _ . _ _ - . _ _ . _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ .____._____.m.__ . .. _ _ _ _ _ i .
' ijjI 03-11-97 10:24:35 I L d . o i .
tootA PIGURE 2 1-1%@ Revision 25
~
tanut auts loues tart est Tuireamst emaseE benet (fGB nefer to inservatene and guldennes in , AP 1001A Wien compioene tNe term. it.TCN No. f. b.Cd I' 'a-- (From TCN 12 4.-. - _ _ . oste I- g,gb Log inden) SS/SF Sgnature L= ~ -
- i. (elel0 "PLM - 4 240.01 l~2. O FFEiTE Presseurs No. Present now. No.
cu (.Au:.DLETW3 NANUAA. Time t ' 2. Oience ee ineeudo pees numbers, pareeraph numbers. and esset wensing et onense Afteen oddleenal sheete N noesseery M LS 2 '7. 0 AuD (.O.0 AS f aa ATTAcHs2> co pi/ l 3 noosen for Change: 1 C.s-Aett s' y Mosa:TotsW., AMD 5AMPuu(m VAQui2EucnJT5 4. ouremen et TCN . He lon0er then 90 emys from imptomenteses) date of TCN or as in a er b below. wnistlever escure first. i s. TCN wel be eenselled by a procedure rewteien tenued m' a result of a Pr dure Disnee j nequesi = be submined by B.A . L aerr-i hdMdual "i "J' , PCn (sue wi PCn u seen = poseeie) G' ! b. TCN is not valed aNet O (ren in emoumannene wmen we roei.n h TCN bebe ennessed)
- n. a preendure wann oa men esepe? . . . .. .
. ... . ... .. . . ... . .Yu V N.
- .. osee m ene,i.e a . *.e e. ori.mel-, -
. ... .... . . . .. . . v- No 1
- I an =re s es s arem. em onense may be appre=W try == sh,R Supendow fSesten to )
e f aneser to M le . Sto LWience must to rewtowed and approved in asserdenes weet Tobis 2 pner to implementation (Seet c 10 bl. e f answer to #6 le$,g triewer to es leg enange may beM (1) two member rewomed (Seeden 10.a)2 (2) rewtowed and appi ed bi assereense van reba : (soonen ion).
- 7. Cnense no emmended v b 1.== hr. Tr- oom Via[%
eman moinsee t ,ree u.eo.no,C - M %j1, ~ 9.w irr os,e i/uis.h M nin nos,enemie onme copa,mwn: No d/nemignee may son = w preendwo oener is une.emebu
*amey be by seneecas
- o. Teeh. Punseens nep. Noteed F reg *d.) k' b ii4Ir . ones
- 10. Asyssage b, esse (Per AP ,
. T - - --
(nTm Aew,,, ,j,g asnesum Q omeo (nfo aam N!Ar DJCddA.f , I-144
' one v j h h p. lg 1-14-%
'"'"'""*'"**"""""^*""""
asm .. .UAP8*9..
- c. es aspeous any: [nde approwel only used w ene. ore to quessene as tensowe osee one o e,o no-(Aso ,, sme Sleneham ones 89neh8e oess IAserewr)
[ alenseme ones
- 13. TCN is CanesNed -
3- b>h(O oom
\swn soorw.w/snni reamen E111 am
]
1 03-11-97 10:24:35 ' tootA Revlolon 30 FIGURE 4 THREE MILE ISt.AND UNIT ONE j SAFETY DETERMINATION l TNs determinaten is required for all documents wrtNo 1001 A apphcacihty/ scope. [ New Procedure *
- TCN . -
PCR l - * - C STP _ . ._ _
**""*"' " u-i o- 7.9 - u.co.e, i """
rz- { 1. le tNa a suneenneve change? hdiosto "Yt$' for new precedures and STP's Yes / No i
- N Som 1 ls *Ne'. sign and date thle form. The remainder of the form need not be compissed 1
- 2. Does tNo change invehe any non radiciogical envwenmenini imsmet? (noter to oennesens sessen of INe precedure.) Yes No V 1
i e r Neo . osmposes Figure g and ensure the change le submated to Erwanmental Conesis and Envwenmental j useneing ser enview. j e Compioes Ine remainder av mas seem.
- 3. Does 1No change have me poesnelal *
i
i . l } 03-11-97 10:24:35 g g Mfp ,, Ag., ytee.o I k l SAFETY DETERMINATION I The change does not have the potential to adversely affect nuclear
- l. safety or safe plant operations. This change does not affect the I
type or quantity of radiological effluents released from the plant. The change clarifies when the RMI-18 noble gas channel and iodine
- sampler are required to be in service. Monitoring and sampling of the ventilation system for noble gases and iodines are only required when liquid radwaste is being moved or processed within '
the facility. When liquid waste is being stored in the tanks I i within. the facility this type of monitoring will typically be i performed but is not required since there is no real motive force , exerted on the waste that would cause significant off gassing of these isotopes from the waste. The situation is analogous to water being stored in the BWST and other permanent outside tanks that are 1 i vented to atmosphere. Such tanks are not required to be monitored i because there is no process present which can cause significant off l gassing of these isotope. During the movement or processing of l liquid radwaste in the Chem Cleaning Facility, the ODCM will require that the iodine sampler 'and noble gas monitor be in i i service, or alternative monitoring methods will be used as' required ) by the specified action statements. 1 l . The change does not make changes to any facilities as described in ! 1 f the safety analysis report. This PCR does not make any changes to facilities. The change does not make changes in the procedures as described in the safety analysis report. The change does not conflict with
' Section 11.4.3.j of the FSAR.
No tests or experiments are conducted which are not described in the safety analysis report. The PCR does noti conduct any tests or experiments. The change does not conflict with the requirements of Technical Specifications. Radiological Effluent control are to be specified in the ODCM per TMI-1 Technical Specifications. Based on the forgoing, the change is considered safe. B. A. Par itt 1/18/96
i j 03-11-97 10:24:35 Nwnber i TMI Radiological Controls E Departmental Procedure 861pLN-4200.01 nos Rowman No. 1 OffsNe Dose Calculation Manual (ODCM) 12 Appmebaty/Soope Calculate oRalte doses oue to radioactive Respon*** Omes ENecove Date l effluents for demonstrating compliance with Site Technical Specsficatons to CFR 20 & 10 CFR 50 - Appendbc l. 6610 01/16/96 This document is within QA plan scope X Yes No 4 Safety Reviews Required X Yes No List of Effective Pages - Pggt Reviekm fagt fagg RO % Revision Pggg Revision + i 1.0" 12 21,0 11 41.0 12 01.0 12 3 2.0 12 22.0 11 42.0 12 82.0 12 3.0 11 23.0 11 43.0 12 82.0 12
- 4.0 12 24.0 11' 44.0 12 84.0 12 8.0 12 25.0 11 45.0 12 85.0 12 i S.0 12 28.0 11 48.0 12 08.0 12 j 7.0 12 27.0 12 47.0 12 87.0 12 j 8.0 12 23.0 12 48.0 12 88.0 12
] 9.0 12 29.0 12 48.0 12 00.0 12 .
- 10.0 12 30.0 12 80.0 12 70.0 12
) 11.0 12 31.0 12 51.0 12 71.0 12 j 12.0 12 32.0 12 52.0 12 72.0 12 1 i 13.0 12 33.0 12 53.0 12 73.0 12 l l 14.0 11 34.0 12 54.0 12 74.0 12 } 15.0 11 35.0 12 85.0' 12 75.0 12 1 16.0 11 38.0 12 56.0 12 74.0 12, 4 17.0 11 37.0 12 57.0 12 77.0 12 18.0 11 38.0 12
)
58.0 12 78.0 12 1 j 19.0 11 30.0 ' 12 59.0 12 79.0 j 20.0 11 40.0 12 80.0 12 80.0 12 12
)
l 1 l .
? 1
- ,. m, w#
,e,ter l N
Env. Aflairs g ! u n.oer. Red. Eno Tidi Qg ib.qr j ua . mi ucensio, p4 ,., ~ r j Rad C w S a y = eci . mi e n ,,)j-.u. yg f 00CUWENT CONTROt.)
,, cornao ,,,,. ; k. copy 1 i N j
4
o i w i s H Tame 2.1. .Anrd) es10-PLN-426. b' 4 Rawleton 12 Radioacthe Gaseous Process and EfBuont Montoring Instrumentation s o to M b N INSTRUMENT OPERABLE APPUCAINLITY ACTION m i
- 7. Chemical Cleaning BultNn0 Veregatlois System i i
- a. Noble Gas ActMty Monitor (ALC RM-1-18) 1(3) ### 27 '
i
- b. lodine Sarnpler (ALC RM-t-18) im ### 31
- c. Parkdmes Samplar (ALC RM4-18) 1 ### 31 -
- s. waste HandNng and Packaging Facety Ventsanan System .
- a. Particulate Sampier (Wlf-RIT-1) 1 ### 31
- 9. Respirator and I.aundry Maintenance Factity Venteadon System
- a. Puticulate Samplar (RLM4tM-1) 1 ### 31 a ., i W.,
NOTE 3: 4edine only required when 9dht ikluld redweste is A 4,,-M in the fechily . i i 27.0 anu
4 1 03-11-97 10:24:35 Numbw l ' gg TMI Radiological Contrais Departmental Procedure 6610-PLN-4200.01 ns. n ,,,.n so, i l Offsite Dose Calculation Manual (ODCM) 12 i Table 3.2-2 (Cont'd)
- d. Charcoal cartridges and partictdate fIters shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or aner removal from sempler).
- e. Tritium grab samples shes be taken weeldy from the spent fuel pool area whenever spent fuel is in i the spent fuel pool.
- f. The ratio of the sample Sow rate to the sampled stroem flow rate ad be known for the time period i
covered by each does or does rate calculatson made in accordance with Controls 2.2.2.1, 2.2.2.2,
- and 2.2.2.3.
1
- g. . The principal gamme emitters for which the LLD specification anpuas exclusively are the following l d
radionuclides: Kr-87. Kr418, Xe 133, Xe 133m, Xe-136 and Xe-138 for gaseous emissions and Mn-54, 4 Fe-69, Co-68, Co 80, ZrWl6, Mo 99, Co 137, Co 141 and Co 144 for particulate emissions. This list does not mean that only these nuclides are to be Considered. Other gamma peaks that are idenunable, together wth those of the abme nuclides, shes also be analyzed are reported in the Annual Radioactive Efiluent Release Report pursuant to TS 8.9.4.
- h. Applicable only when condenser vacuum is established. Sampling and analyses shed also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT I 131 concentration in the primary coolant has not increased more than a factor of 3; and (2) ;be noble gas actMty monitor shows that eAluent actMty has not increased by more than a factor of 3.
L Gross Alpha, St-89, and Sr-Go analyses do not apply to the Fuel HarxRing Bulding ESF Air Treatment System. J. If the Condenser Vent Stack Continuous lodine Sampler n :. navalable, then altamate sampling equipment w0t be placed in service wthin 48 hours or a report will be prepared and submitted wthin 30 days from the time the sempler is found or made inoperable which identlRes (a) the cause of the inoperabity, (b) the action taken to restore representative sampling capaNety, (c) the action taken to prevent recurrence, and (d) quantincetion of the release via the pathway during the period and comparison to the limits preecribed by Control 2.2.2.1.b.
- k. Applicable only when condenser vacuum is established l.
M 91. 4 6 Applicable when liquid radweste is stored or processed hthe facity. j
- m. lodine samples only required in the Chemical Cleaning Bulding when TMI-1 liquid radwaste is stored or processed in the facNity.
i 80.0 '" I
l l Encksure 4 1996 Annual Radioactive Efiluents Relises Reprt for TM1 6710-97-2161 1 1 I Procedure Change Request (PCR) 1-RC-%-0008 to the ODCM,6610-PLN-4200.01 l l 1 1
d * . 9 s.12.,, _1 . " ' PRIORITY + 1001A RGURE 1 3 -//- % Reviolo'n 25 ran j i No. .N O . k .,,,Q[J T W W la m W en i N ,ts W N8lWT FWG Refer 93 inoiruedone arWI guhlatnes in AP 1001A when completing this fe,m. ~ 4 1. GL,lo- PL.N- 4'dOO. O l 12.,
- procedw. w - preenne n N Ocasna.1.se. G -.o_reca nee KanuAt. (obcM)
- 2. - ceasee:
- o bueude pees nwnbe,s. pareeresh comae,s. end emnet wensne or ,eoemmended enenee.
1 M edmeonel eheste W necesse,y ' hAsets. 2.7.o Aute M.o As 39 ATTACME.D CoPV i
~
- 3. Bamses ter theses:
- e le this W,enge part of the tiennial P,eoedu e Review? . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Yes No include I&E Susanne. TSCR d. T. 8. Amendment d. ModNlossion d,. etc.
~
Yo CLAe.,1"Y Mona Tata Ner Aut, 3Af9PA-lMs hhus tE rne.d T4 Feg. , rgg Cwg%g ggggg
- ' 7483 NR. REP 6Acas TCM N 1 oco 2. .
9 l l
- 4. . le) Does Aeweien ,optene a TCN7 . . . . . . . . . - . . . . . . . . . . . . . . . . . .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .#. . Yee No
- p) N 'yes", indienne the TcN Number, N eweilahte l_ ch. coo 2.
- 5. le p,ocedwo within OA Plan Sempet . . . . . . . .
..............................................Yes a."" 'No
- 8. Che'nge Renommended Sy: N tt.C t~rT' Date L[36bb '
a ,
- r- l
- 7. ,,e.e e os,,e, con.w.e.es _NA _ osie i/u A4. .
.se,s.,0 e o,.co c se,,s e CJu'75tA44.ar os.o z -, . s
. e,.,,s.,,o To.,e,ien, ,,,s.e, c.,,.u,,e e hWMt- - -%Ac . -/s/w
,a . = e,s., -
A A . W 1hsfu -
/
== -
~ JZ .12 htf 2/ E' y
, , - ~
/y .,
, , . . c,,,,,,s .,,,e,em oI.- % z.t v #
- De e .
R s %g $$- , t-- w O h
%senWM
04-17-97 09:11:08 1001A Revision 30 MGURE 4 TNREE Mit.E ISLAND UNIT ONE SAFETY DETERMINATION. This determinadon le required for ou documents within 1001A spplicetety/ scope.' ,
] , New Procuture . - .
[ TCH .
,Ca > ._s_A.9_f.e.. e a o a ST, . .
Document No. Rev. No. M.lo -Pua - 42co .o i 12 ,
- 1. le this a autetentive ehenge? Indiosee "YE8' for new precedures.shd STP's Yes u No ,,_,_
If Box 1 le "No*, sign and dase this form. The temsdnder of sie form nosil not be completed.
- 2. Does this chen0s inwelve any nondedleiseleal environmentalimpeed (Redor to DeAnisone Seemen of thee pegedwa.) Yes No 7-e if "Yee*, compises Figure 9 and ensure the ehenge is submitted to Environmental Conseis and Environmental uoensine for review, e Composte the remainder of this form. ~ ..
~
- 3. Does file ehenge haws the potenesJ to adversely asset nuelser enfety or sede plant M Yes No -
(Refer to Pereyeph 4.2.2)
- 4. Does this make ehenges in the facelty as deer,tbed in the selsey onelyele repore Yee No #
- 5. Does this mehe ehenGes in the pacedures es deserted in tw reisty e.telysis report? ,
Yes No u
- 6. Are tests or orperimente condi, seed whleh eso net deseribed in the seM; onelysis report? . Yn No /
T. Does thee Menge eenfact with me -- T _ .Z of Wie plant Technical W . Yes No V form. if tie enowere to 3,4. 5,5 AND 7 are$3 Wile proeludes the seisennes et en C.---
~
' Safety Omeson er Toonnical %_- _ .cnenge.
Provide the beste for why Wie ehenge le seis hese. Egn and does file form. f o k pygpgtgg g AO $ e i
- b
- U ,, ,,
. ,t r
- 4 04-17-97 09.:11:08 ,
I
), kc4(a OI '
SAF'ETY DETERMINATION The change does not have the potential to adversely affect nuclear saf.ety or' safe plan't operations. This' change does not affect the type or quantity of radiological effluents released from the. plant. The change clarifies when the RMI-18 noble gas channel and iodine ; sampler are requ. ired'to be in service. Monitoring and sampling of the ventilation system for noble gases and iodines are only. required when liquid radwaste is'being moved or processed within'
~
- the facility. When liquid waste is being stored in the tanks within t;he facility this type .of monitoring will typically be performed but is.not required since there.is no.real motive. force' exerted on the waste that would cause signific' ant off gassing of these isotopes from the waste. The situation is analogous to water being stored 'in the BWCT and other permanent outside tanks that are s vented to atmosphere. .Such tanks are not required to be monitored because there is no process present;which can cause significant off gassing of these isotope. During the movement'or processing of
. liquid radwaste in the Chem Cleaning Facility,- the ODCM will require that the iodine ~ sampler .and noble gris monitor' be .in .
service, or alternative monitoring m'ethods will .be used as require'd , by the specified action. statements. The change.does'not make changes to any facilities as described in the safety analysis. report. This PCR does not make'any changes to ifacilities' . The change does not make changes in the' procedures as described in the safety analysis report. ~ The change'does not conflict with , Section ll.4.3.j of the FSAR. , - ~ No't'ests or experiments are conducted which are not. described in the safety analysis'. report. The PCR'does'not, conduct any tests or experiments. '
~
The change does not conflict with the requirements _of Technical Specifications. Radiological Effluent control are to be specified in the ODCM per TMI-l Technical Specifications. Based on the forgoing, the change is considered safe. B. A. Parfitt 1/30/96 ,
, e ,
a
. 4 4
- -. . . . ._- -. . - . . . . . - ._. . . - - - - . - . ~ . .
i 04-17-97 09:11i08 Number i Nuclear " "ad* **' Departmental Procedure 6610 PLN-4200.01 noe l m no. Offsite Dose Calculation Manual (ODCM) - 12 WJity/smpe Calculate onsite doses due to radioactive lheponede ONice h Date effluents for demonstrating cewv u,ce with See Technical .l Specifications 10 CFR 20 & 10 CFR 60 - Appendix 1 6610 01/16/96 i This document is within OA plan scope X Yes No Safety Reviews Required X Yes No l
, Ust of Effedive Pages - .
Eggt Revlalon Eggg' Rwision Eggg
. Revision , fagg RevisiQq
] 1.0" . 12 21.0 11 41.0 12 81.0 12
- 2.0 12 22.0 .11 42.0 12 82.0 12
- 3.0 11 23.0 11 43.0 -
' . 12 83.0 12 4.0 12 24.0 11 44.0' 12 ' 64.0 - 12 i 5.0 12 25.0 11 45.0 12 86.0 12 l S.0 12 26.0 11 48.0 12 88.0 12
- 7.0 12 27.0 12 47.0 11 '
' 67.0 12
, 8.0 12 28.0 12 48.0 12' 88.0 12 9.0 12 29.0 12 49.0. It ~ 00.0 12 .
10.0 12. 30.0 12 50.0. 12 70.0 12
.11.0 12 31.0 12 51.0 12 71.0 12 12.0 12 32.0 12 52.0 12 72.0 12 13.0 12 33.0 .,' 12 '12 -
53.0 .. 73.0 12 14.0 11 34.0 12 12
. 54.0.. 74.0 12 15.0 11. 35.0 12 55.0 12 75.0 12 16.0 11 38.0 12 58.0 12 ~ . 78.0 12 17.0 11 37.0 12 57.0 .12 77.0 12 18.0, 11
- 38.0 12 58.0' 12 78.0 12 19.0 ' 11 30.0
- 12 50.0 12 79.0 12 20.0 11 40.0 12 00.0 12 30.0 12 Radiological' Engineer, TMI
-l2.[2if97
~
- ^ - -
Manager, Rad. Eng., TMI l LLob4J as # l
,g Manager, TMIC.O. %',$h ' .
j.fprf[ . Rad, Con / Safety Director, TMt o j_,jg g f DOCUMENTCONTROL) 1.0 *"* COPY $ s , 4
~. . - _ _ ..-. . - _ _ .. . - . . _ . - - . . . . - - . . - - . . . - . - .-. . .. - .- - -.~.-... - . . .- .._ -_ ~ . - - ~.. -. . - o
. s .
s !
. e a, -
Tatte 2.1s , .,ont'd) se m e . Revleien 12 Redloodlive Ammarum Pmcess and Elguent Moreorks instrumentation o e
. p RAP 8 MUM P .
CHANNELS - E I INSTRUMENT . OPERABLE APPUCABAUTY ACTION * ; 7, Chemicd CleanhD th ^f!ng Vermandan System . , , ,
' ~
- a. Noble Gas Activsy Montor (ALC Rt4418) -
1(s) ### 27 - ;
- b. lodne Sampler (ALC RM4-18) 1# ### - - 31
~'
- c. Particdese Sernpler (ALC RM4-18) -
1 ##'s 31 i
- 8. . Weste Hensing and Packapng FacGy,Veneselon System -
- a. Particdste Sampler (WHP4tT.1) 1 ### 31
- 9. Respiratorand Laundry Mahlenance FacElly Verenasian System
- a. Pereiridass Sampler (RLM-It41) , 1
### 31 g as . .#. .n .
NOTE 3: sedne#hannel only required when TMI t liquid radweste is e-J/m-x _ _ _ f tr the facElty. ,
\
1 27.0 nm.
l 04-17-97 09.:11:08 s Numbw gggy . TMI Radidogical Controis Departmental Procedure 6610-PLN 4200.01 re. am n no. Offsite Dose Calculation Manual (ODCM) 12 1 Table 3.2-2 (Cont'd)
- d. Charcoal cartridges and particulate 19ters shal be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or after remmal.from sampler).
- e. Trtlurn grab samples shal be taken weeldy from th's spent fuel pod area whenever spent fuel is in the spent fuel pod. - '
- f. The ratio of the sample Sow rate to the sampled stream flow rate shall be'known for the time period covered by each dooo or dose rate calculation made in accordance with Controls 2.2.2.1, 2.2.2.2, and 9993 ,
- g. The principal gamma emitters for which the LLD g =hn applies exclusively are the following radionuclides: Kr.87, Kr-88, Xe-133, Xe-133m, Xs-135 and Xe-138 for gaseous emissions and Mn-54, Fe40, Co48, Co40, ZrW16, Mode, Cs-137, Co-141 and Co-144 for particdate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks t' ,I are identifiable, together with thnee of the above nuclides, sha!! also be analyzed and reputed in the Annual Radioactive EfRuert Release Report pursuant to TS 6.9.4..
- h. Applicable only when condenser vacuum is established. Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the
,. noble gas actMty monitor shows that erRuert actMty has not increased by more than a factor of 3.
~
L Gross Alphe, Sr49,*and Sr-00 analyses do not apply to the Fuel Handling Bunding ESF Air Treatment System. J. If the Condenser Vent Stack Continuous lodine Sampler is unavailable, then rJtemate sampling
- equipment will be placed in service wthin 48 hours or a report will be prepared and submitted wthin 30 days from the time the sampler is found or made inoperable which identifies (a) the cause of the, inoperability, (b) the action taken to restore representative sampling capabDty, (c) the action taken to prevent recurrence, and (d) qu.iCa.¬ the release via the pathway during the period anq
*y-si.on to the limits preecribed by Control 2.2.2.1.b.
- k. Applicable only when condenser vacuum is established.
w e) v.4k's
'l. Applicable when liquid radwaste is etered or processed in the facility.
- m. lodine samples only required in the Chemical Cleaning Bulding when TML1 liquid radwaste is stored or processed in the facilry.
60.0 m I
. .a
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llTY TMI-1 PROCEDURE REVIEW AND APPROVAL l . WORD PROCESSING / PROOFREAD / SIGN OFF FORM , PROCEDURE NO:. 6NO-M-9306, O/ . TO WP: ,2-23-R, l i l PCR NO.: /- AO- 94-00# REVISION NO.: /_1 l 0DCf/7 i . d'O'94 ! PROOPREAD/ SIGN OPF: Retum to: '?n.hlA#AAAl i . OElc4 Coonsnetor Date ! N#73-d l i
- TO:AM/ Correctione Originator l
1st Proof 2nd orpoi ! . Pleens prookesd. Nots correcelons inM1 '- - D YES: 0 YES' l M on spected peges and CHECKTHE YES . tsock. N OK, sign end date procedure cover l peos and return to OlBoo Coonsnetor. . Owner ' Approver (s) , WonD PROCEssetS/PROCEMNIE CONm0L . f ,,qe or or b.4Na7d
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spm instruemone: . 1 i ' issue Dets i i ! WonD PnoCassete: I l .. . Date w M M Date Regted: , ! D o o. iD 2 / '/ / d . Disk No.dd 9 Doo. ID Disk No. . Doo iDJAYaG Disk No. 9 Doc. ID Disk No.
- Date Pages Date 2
nooseved operator WP Prost ' Printed Complete -
! 1. .2].14 19(o & V- .t/ M A L
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- 2. -..s .
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l l ! Ench*;ure 5 1996 Annual Radimctive EfIluents Releases Reput for TMI 6710-97 2161 Procedure Change Request (PCR) 1 RC-%-0020 to the ODCM,6610-PLN-4200.01 I i
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! "~NiiifRITY '
' 1"Mut $ 4/ S/5-W/ MM PIGURE 1 PR1051If .
novlsients I .
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ble-Pt.M- 42co, o i " t. 49..this rrs nodese CAuua ned MAcow P,sessum No. P,eems now. No. Thh E asommendes enames: e heissie pese numbs,s. pares,aph numham, and einst .ensne of ,essmenended ehenee.
- Aemen enenenau emenen N neesenery
%* 48.03 Go.0,58.0, AAS) 98.o as #9escAraco ou ruec AtrAcaco MAtv.eb ue COPY. s 4
& besses for Genes: e Is this ehenge pe,t of the 'Monnial Preenshee Redewt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Yes No X i
e mesome as susanne.Taca e, T. S. A,noneneet p. RAmeReaden p. sea ' ', d) Ta EuHo3 ATE.' Ad Odd 8CE55A# V sueuarv3pi Recosactneay na, cmseAsn.i ry or. rus uguid ram 4Asre msATMeur sysrcew. l h 3 EuMMATE. RE.buabAu t ktquab 6FFu.3ENT GRA& SAMPudG,,. 1 t Reevia.sr6Euys . .
@ % caceae.T THE Ras Emsdca. Fea. WE.4CAErste n hurreod T Acreg *
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- 4. (a) Dame newtaien ,eptase a TCN7 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Yee '
- 5) N *We" Inesses the TCN hmte,. N euaushes No X
- 8. . to p eemeu,e withh Q4 Flen tempet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . a . . . . . . . . . . Yes X No a,es.e neuemme e. .r. GAQ L- h ire- I\
osie s/u/w. ,
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- 7. ,,eso e o.mo, eenes,,e,,se NA . '. no. 3/z rh 2 n,e,e,,s e o.e,; ca.se,,e,,ee ( X % W Cl # '
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R Received h1 P,ecedure toonfinster C.l !
04-17-97 09:15:26 i s 1005A' . l Revision 30 !
- FIGURE 4 l
l THREE MILE ISLAND UNIT ONE l l SAFETY DETERMINATION ) This determmason is required for es documems weeln ic01A appucebHNy/seope. I a New Presseure . .
, , , , , , , , _ TCN _ n -
i N PCR 1-[b 9 j?,,,, ,,,,,d A d O ' STP ,,,,,,, - _- _ _ I i I j Mov. No. l osoument No, ls(alD ~PL.N - 42.oo. c l l3 l 4 l j 1. le ins a em ehenge? hesen %v for row sweeeewee and STre ' Yes & Nr, j w ese : is "Ne*, siqp, and does tNa form. The remainder of to fann need not be sempioned. P
- 2. Does tNo shence inveeve any norwomeineinal enverenenemed impeerr gnmer to osannons asedan of tNo procedws.) Yes _ No 1
. . 4es. ee,np.see w . e.,e e se .,e e
. e is .m ed . , vere,,,,,.r.si ce,mois d .,,verer i i Usensine for 8eview. l j e compioes me remainder er tNo sonn.
i i
- s. Does'mie ehense hoe me poesness to adverseer enese nueleer esseev ier esse plant ei, ore 1ons? Yes ,,,,,,,'No X
- inder to paragraph 4221
- 4. Does tNs enehe eneness in the seemer as desenhed ir, the sessay enelysis report?
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.Yes No X l
\
- s. Does this enese emanges in the p,condures as h in'the endsey enelysis repert? Yes No X
- e. Are teses er espedmenes eenduend which am not deeermed in me esseer ansdyeis report? Yes No >
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- 7. Does mis ehense eeneet wah the requiremones of the piant Toshnemel Sposellendone?
Yes No X i .
- N AE of me enesses to a,4, s. e c / me,tB you must su out rieme sAtgt pavide a wemen endeer evalummen. Sion end den this..
! sonn.
I me ensuess to 3,4. 5. 6 Arm 7 ese ALL fEL mis pseeludes me esseenes of en < ' " gefear Queesen er Techniset ; _ - . change. Provide tie basis ter why 9,e ehenge.is seis he,s. Egn and dess 9,it tenn. . Sac ATwisco -
,,e,e,ed . WM L. h- = sMw -
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,_ ' E131
04-17-97 09:15:26-
/ ,,gc, 94-0047d
' SAFETY DETERMINATION The change does not have the po'tential to adversely affect nuclear safety or safe plant operations. This change does not affect the type or quantity of radiological effluents released from the plant.
The change will not adversely affect nuclear safety.or safe plant
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operations for the following reasons: The change eliminates surveillance 3.2.1.3.2 from Part I of the ODCM. This surveillance requires that the operability of the liquid radwaste treatment system be demonstrated by ' operating the equipment for 60 minutes each quarter. It is anticipated.that the future use of CC~T-1 to store liquid radwaste may permit processing of liquid radwaste at intervals longer than each quarter. Standard Radiological Effluent j Controls in NUREG 1301 and Standard Technical Specifications in NUREG 0472 Draft 7 do not have this type of operability surveillance requirement for this. system. In addition, ODCM ' Part I Control 2.2'.1.3.already provides requirements to, ensure that the liquid radwaste treatment system is operated to ensure effluent releases-are'ALARA. Since releases of processed liquid radwaste are sampled prior-to release this quarterly operability surveillance is not necessary.. The operation of the system solely to demonstrate operability would result.in unnecessary personnel radiation exposure and 1 would not be ALARA. For these reasons, this surveillance can safely be eliminated. ! The change'also eliminates monthly noble gas grab sampling for batch and continuous liquid releases in Part-I Table 3.2-1. Noble gases for batch releases are measured for each release
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during the. gamma scan of'the sample.' Noble gases for continuo.us releases are measured for each release during the gamma scan of the weekly composite sample. As a result', these monthly grab samples are redundant and provide less data than the practice of analyzing each sample. Table 3.2-1 is being - l amended to reflect.the measurement of noble gases in each I
. sample.
The change modifies the reference'used for near field dilution. The current referedce to Table A-2 of Reg Guide 1.109 is not the correct reference. NUREG 0133 provides the guidance for determination.of near field dilution factors The change does'not make changes to any facilities as described in the safety analysis report. This PCR does not make any changes _to facilities. The change does not make changes in the procedures as described in the safety analysis report. The changes are not described in' Section 11 of the TMI-1 FSAR. '
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